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{{#Wiki_filter:ENERGY NORTHWEST Bradley J. Sawatzke Columbia Generating Station P.O. Box 968, PE08 Richland, WA 99352-0968 Ph. 509.377.4300 1 F. 509.377.4150 bjsawatzke  
{{#Wiki_filter:Bradley J. Sawatzke ENERGY                                                            Columbia Generating Station P.O. Box 968, PE08 NORTHWEST                                                            Richland, WA 99352-0968 Ph. 509.377.4300 1F. 509.377.4150 bjsawatzke @energy-northwest.com May 6, 2014 G02-14-073 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Energy Facility Site Evaluation Council ATTN: EFSEC Manager P.O. Box 43172 Olympia, WA 98504-3172
@ energy-northwest.com May 6, 2014 G02-14-073 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Energy Facility Site Evaluation Council ATTN: EFSEC Manager P.O. Box 43172 Olympia, WA 98504-3172


==Subject:==
==Subject:==
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 INDEPENDENT SPENT FUEL STORAGE INSTALLATION, DOCKET NO. 72-35 2013 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT  
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 INDEPENDENT SPENT FUEL STORAGE INSTALLATION, DOCKET NO. 72-35 2013 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT


==References:==
==References:==
: 1. Columbia Generating Station Technical Specification 5.6.1 2. Independent Spent Fuel Storage Installation Technical Specification 5.4.b 3. EFSEC Resolution No. 332, February 21, 2012  
: 1. Columbia Generating Station Technical Specification 5.6.1
: 2. Independent Spent Fuel Storage Installation Technical Specification 5.4.b
: 3. EFSEC Resolution No. 332, February 21, 2012


==Dear Sir or Madam:==
==Dear Sir or Madam:==
In accordance with the requirements of References 1-3, the subject report is submitted as an enclosure to this letter. If you have questions regarding this information, please contact TE Northstrom at (509) 377-8462.Respectfully, BJ Sawatzke Vice President, Nuclear Generation  
 
& Chief Nuclear Officer Enclosure cc: NRC Region IV Administrator NRC NRR Project Manager NRC Sr. Resident Inspector (988C)MA Jones -BPA/1 399 WA Horin (Winston & Strawn)Director, SFPO-NRC NMSS M. Priddy (WDOH)L. Albin (WDOH)L. Vigue (WDFW)JM Ayres (WDOE)
In accordance with the requirements of References 1-3, the subject report is submitted as an enclosure to this letter. If you have questions regarding this information, please contact TE Northstrom at (509) 377-8462.
I I I O ENERGY NORTHWEST* COLUMBIA GENERATING STATION I I OP RAT NG REPORT FOR THE COLUMBIA I EEAIN TTO I I I I I I I I ENERGY NORTHWEST People- Vision. Solutions COLUMBIA GENERATING STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2013 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT For Calendar Year 2013 Preparation Date: April 2014 Submitted Date: May 2014 Authored BM: EN:W Evi/i /LQ -Q David Mee, ENW Environmental Services Reviewed By: Elisa Nguyen, ENW Envir nentdlServices Approved By: Auevio Terry Northstrom, ENW'Enviromnental Services Supervisor TABLE OF CONTENTS SECTION PAGE 1.0 EXECUTIVE  
Respectfully, BJ Sawatzke Vice President, Nuclear Generation & Chief Nuclear Officer Enclosure cc:   NRC Region IV Administrator                       Director, SFPO-NRC NMSS NRC NRR Project Manager                           M. Priddy (WDOH)
NRC Sr. Resident Inspector (988C)                 L. Albin (WDOH)
MA Jones - BPA/1 399                               L. Vigue (WDFW)
WA Horin (Winston & Strawn)                       JM Ayres (WDOE)
 
I I
I         O   ENERGY NORTHWEST
* COLUMBIA GENERATING STATION I
I   OP RAT NG REPORT FOR THE COLUMBIA I           EEAIN     TTO I
I I
I I
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ENERGY NORTHWEST People- Vision. Solutions COLUMBIA GENERATING STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2013 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT For Calendar Year 2013 Preparation Date: April 2014 Submitted Date: May 2014 Authored BM: EN:W Evi/           i /LQ-Q David Mee, ENW Environmental Services Reviewed By:
Elisa Nguyen, ENW Envir     nentdlServices Approved By:           Auevio Terry Northstrom, ENW'Enviromnental Services Supervisor
 
TABLE OF CONTENTS SECTION                                                                                                       PAGE 1.0     EXECUTIVE  


==SUMMARY==
==SUMMARY==
1-1 2.0 DEFINITIONS 2-1  
1-1 2.0     DEFINITIONS                                                                                               2-1
 
==3.0      INTRODUCTION==
3-1 3.1      Site Description                                                                                3-1 3.2      Program Background                                                                              3-1 3.3      Program Objectives                                                                              3-2 4.0      PROGRAM DESCRIPTION                                                                                      4-1 4.1      Sample Locations                                                                                4-1 4.2      Independent Spent Fuel Storage Installation (ISFSI)                                            4-1 4.3      Land Use Census                                                                                4-2 4.4      Sampling Methods                                                                                4-2 4.4.1        Direct Radiation                                                                  4-2 4.4.2        Airborne - Particulate/Iodine                                                      4-2 4.4.3        Water                                                                              4-3 4.4.4        Soil                                                                              4-4 4.4.5        Sediment                                                                          4-4 4.4.6        Fish                                                                              4-4 4.4.7        Milk                                                                              4-5 4.4.8        Garden Produce                                                                    4-5 4.5      Sample Analyses                                                                                4-5 4.5.1        Analysis of TLDs                                                                  4-5 4.5.2        Gross Beta Activity on Air Particulate Filters                                    4-6 4.5.3        Measurement of Gamma Emitting Radionuclides                                        4-6 4.5.4        Gross Alpha and Gross Beta Activity in Water                                      4-6 4.5.5        Tritium in Water                                                                  4-7 4.5.6        Strontium-89/90, Iron-55, and Nickel-63                                            4-7 4.5.7        Low Level Radioiodine in Milk and Water                                            4-7 2013 Annual Radiological Environmental Operating Report i                  Energy Northwest/Columbia Generating Station
 
TABLE OF CONTENTS SECTION                                                                                                        PAGE 4.6    Data Analysis Methods                                                                            4-7 4.7      Changes to the Sampling Program in 2013                                                          4-8  3 5.0      RESULTS AND DISCUSSION                                                                                    5-1 5.1      Direct Radiation                                                                                5-1 5.2      Airborne Particulate/Iodine                                                                      5-3 5.3    Water                                                                                            5-5 5.3.1      Surface Water                                                                        5-5  U 5.3.2      Ground Water                                                                          5-6 5.4      Soil                                                                                            5-7 5.5      River Sediment                                                                                  5-7  3 5.6    Fish                                                                                              5-7 5.7    Milk                                                                                              5-8  1 5.8    Garden Produce                                                                                    5-8  3 5.9      Special Interest Stations                                                                        5-8 5.9.1        Storm Drain Pond (Station 101)                                                    5-8  3 5.9.2        Sanitary Waste Treatment Facility (Station 102)                                    5-9 5.9.3        Cooling System Sediment Disposal Area (Station 119)                              5-10  3 5.9.4          Spray Pond Drain Field (Station 120)                                            5-11 5.9.5        Independent Spent Fuel Storage Installation                                      5-11    3 5.9.6        Additional Air Sample and TLD Locations                                          5-12 5.10 2013 Sample Deviations                                                                            5-12    3 3
3 I
2013 Annual Radiological Environmental Operating Report ii                  Energy Northwest/Columbia Generating Station
 
TABLE OF CONTENTS SECTION                                                                                                  PAGE 6.0      QUALITY ASSURANCE AND QUALITY CONTROL                                                            6-1 6.1      Quality Control for the Energy Northwest Environmental TLD Program                        6-1 6.2      Quality Control for the Environmental Sample Program                                      6-1 6.2.1        Sample Collection Quality Control                                          6-2 6.2.2        Laboratory Instruments Quality Control                                      6-2 6.2.3        Sample Batch Quality Control                                                6-2 6.3      Laboratory Intercomparison Program Participation and Results                              6-3 6.4      Laboratory Quality Control Program Problems and Improvements                              6-3


==3.0 INTRODUCTION==
==7.0     REFERENCES==
7-1 8.0      ERRATA                                                                                            8-1 APPENDIX A. Data Tables A and B 2013 Annual Radiological Environmental Operating Report 111            Energy Northwest/Columbia Generating Station


3-1 3.1 Site Description 3-1 3.2 Program Background 3-1 3.3 Program Objectives 3-2 4.0 PROGRAM DESCRIPTION 4-1 4.1 Sample Locations 4-1 4.2 Independent Spent Fuel Storage Installation (ISFSI) 4-1 4.3 Land Use Census 4-2 4.4 Sampling Methods 4-2 4.4.1 Direct Radiation 4-2 4.4.2 Airborne -Particulate/Iodine 4-2 4.4.3 Water 4-3 4.4.4 Soil 4-4 4.4.5 Sediment 4-4 4.4.6 Fish 4-4 4.4.7 Milk 4-5 4.4.8 Garden Produce 4-5 4.5 Sample Analyses 4-5 4.5.1 Analysis of TLDs 4-5 4.5.2 Gross Beta Activity on Air Particulate Filters 4-6 4.5.3 Measurement of Gamma Emitting Radionuclides 4-6 4.5.4 Gross Alpha and Gross Beta Activity in Water 4-6 4.5.5 Tritium in Water 4-7 4.5.6 Strontium-89/90, Iron-55, and Nickel-63 4-7 4.5.7 Low Level Radioiodine in Milk and Water 4-7 2013 Annual Radiological Environmental Operating Report i Energy Northwest/Columbia Generating Station TABLE OF CONTENTS SECTION PAGE 4.6 Data Analysis Methods 4-7 4.7 Changes to the Sampling Program in 2013 4-8 3 5.0 RESULTS AND DISCUSSION 5-1 5.1 Direct Radiation 5-1 5.2 Airborne Particulate/Iodine 5-3 5.3 Water 5-5 5.3.1 Surface Water 5-5 U 5.3.2 Ground Water 5-6 5.4 Soil 5-7 5.5 River Sediment 5-7 3 5.6 Fish 5-7 5.7 Milk 5-8 1 5.8 Garden Produce 5-8 3 5.9 Special Interest Stations 5-8 5.9.1 Storm Drain Pond (Station 101) 5-8 3 5.9.2 Sanitary Waste Treatment Facility (Station 102) 5-9 5.9.3 Cooling System Sediment Disposal Area (Station 119) 5-10 3 5.9.4 Spray Pond Drain Field (Station 120) 5-11 5.9.5 Independent Spent Fuel Storage Installation 5-11 3 5.9.6 Additional Air Sample and TLD Locations 5-12 5.10 2013 Sample Deviations 5-12 3 3 3 I 2013 Annual Radiological Environmental Operating Report ii Energy Northwest/Columbia Generating Station TABLE OF CONTENTS SECTION PAGE 6.0 QUALITY ASSURANCE AND QUALITY CONTROL 6-1 6.1 Quality Control for the Energy Northwest Environmental TLD Program 6-1 6.2 Quality Control for the Environmental Sample Program 6-1 6.2.1 Sample Collection Quality Control 6-2 6.2.2 Laboratory Instruments Quality Control 6-2 6.2.3 Sample Batch Quality Control 6-2 6.3 Laboratory Intercomparison Program Participation and Results 6-3 6.4 Laboratory Quality Control Program Problems and Improvements 6-3
LIST OF TABLES TABLE                                                                                                PAGE      3 4-1           Radiological Environmental Monitoring Program Sampling Plan                                4-9 4-2           REMP Sample Stations and Requirements                                                    4-11    1 4-3           2013 Five Mile Land Use Census Results                                                  4-15    3 4-4           Comparison of Laboratory Nominal Lower Limits of Detection With Offsite Dose Calculation Manual Requirements                                            4-16    3 5-la          REMP Sample Deviations for 2013                                                          5-12 5-lb          CGS REMP Air Sample Percent in Service Time for 2013                                     5-14    1 5-2           Radiological Environmental Monitoring Program Summary                                    5-15 5-3           Quarterly TLD Data Summary with Comparison to Preoperational and                                I Operational Periods                                                                      5-25 6-1            2013 Environmental Spiked Dosimeter Results                                                6-1 6-2           ENW REMP Program Cross Check Performance Results                                          6-5   3 I
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Operating Report  iv        Energy Northwest/Columbia Generating Station 2013 Annual Radiological Environmental Annual Radiological Environmental Operating Report iv        Energy Northwest/Columbia Generating Station


==7.0 REFERENCES==
LIST OF FIGURES FIGURE                                                                                              PAGE 4-1          Select REMP Sampling Locations Within 0.8 Miles of CGS                                    4-17 4-2          Select REMP Sampling Locations Between 0.8 and 2.8 Miles                                  4-18 4-3          Select REMP Sampling Locations Beyond 2.8 Miles                                            4-19 4-4        ISFSI TLD Stations Layout                                                                  4-20 5-1        "S" Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean by Sector                                                                                      5-1 5-2        Near Plant Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean by Sector                                                                                5-2 5-3          Remote Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean by Sector                                                                                    5-2 5-4          1985-2012 Weekly Hi/Low/Mean and 2013 Weekly Mean Gross Beta in Air-Near Plant Stations                                                                          5-4 5-5          1985-2012 Weekly Hi/Low/Mean and 2013 Weekly Mean Gross Beta in Air-Remote Stations                                                                              5-4 5-6          Gross Beta in River/Drinking (Stations 26 & 29) and Plant Discharge Water (Station 27) for 2013                                                                        5-5 5-7        Tritium in River/Drinking (Stations 26 & 29) and Plant Discharge Water (Station 27) for 2013                                                                        5-6 5-8          Cooling System Sediment Activity Levels for Disposals Made in 2013                        5-10 5-9        ISFSI TLD Trend at CGS                                                                      5-11 2013 Annual Radiological Environmental Operating Report  V        Energy Northwest/Columbia Generating Station


7-1 8.0 ERRATA 8-1 APPENDIX A. Data Tables A and B 2013 Annual Radiological Environmental Operating Report 111 Energy Northwest/Columbia Generating Station LIST OF TABLES TABLE PAGE 3 4-1 Radiological Environmental Monitoring Program Sampling Plan 4-9 4-2 REMP Sample Stations and Requirements 4-11 1 4-3 2013 Five Mile Land Use Census Results 4-15 3 4-4 Comparison of Laboratory Nominal Lower Limits of Detection With Offsite Dose Calculation Manual Requirements 4-16 3 5-la REMP Sample Deviations for 2013 5-12 5-lb CGS REMP Air Sample Percent in Service Time for 2013 5-14 1 5-2 Radiological Environmental Monitoring Program Summary 5-15 5-3 Quarterly TLD Data Summary with Comparison to Preoperational and I Operational Periods 5-25 6-1 2013 Environmental Spiked Dosimeter Results 6-4 1 6-2 ENW REMP Program Cross Check Performance Results 6-5 3!I I I I I 2013 Annual Radiological Environmental Operating Report iv Energy Northwest/Columbia Generating Station 2013 Annual Radiological Environmental Operating Report iv Energy Northwest/Columbia Generating Station LIST OF FIGURES FIGURE PAGE 4-1 Select REMP Sampling Locations Within 0.8 Miles of CGS 4-17 4-2 Select REMP Sampling Locations Between 0.8 and 2.8 Miles 4-18 4-3 Select REMP Sampling Locations Beyond 2.8 Miles 4-19 4-4 ISFSI TLD Stations Layout 4-20 5-1 "S" Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean by Sector 5-1 5-2 Near Plant Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean by Sector 5-2 5-3 Remote Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean by Sector 5-2 5-4 1985-2012 Weekly Hi/Low/Mean and 2013 Weekly Mean Gross Beta in Air-Near Plant Stations 5-4 5-5 1985-2012 Weekly Hi/Low/Mean and 2013 Weekly Mean Gross Beta in Air-Remote Stations 5-4 5-6 Gross Beta in River/Drinking (Stations 26 & 29) and Plant Discharge Water (Station 27) for 2013 5-5 5-7 Tritium in River/Drinking (Stations 26 & 29) and Plant Discharge Water (Station 27) for 2013 5-6 5-8 Cooling System Sediment Activity Levels for Disposals Made in 2013 5-10 5-9 ISFSI TLD Trend at CGS 5-11 2013 Annual Radiological Environmental Operating Report V Energy Northwest/Columbia Generating Station 1.0 EXECUTIVE  
1.0 EXECUTIVE  


==SUMMARY==
==SUMMARY==


1.0 EXECUTIVE  
1.0       EXECUTIVE  


==SUMMARY==
==SUMMARY==
The primary purpose of the Energy Northwest Radiological Environmental Monitoring Program (REMP)is to evaluate the radiological impact that Columbia Generating Station (CGS) operation may have on the environment.
 
Sampling is performed as specified in the Offsite Dose Calculation Manual (ODCM) and agreements made with the State of Washington Energy Facility Site Evaluation Council (EFSEC).Additional sampling is also performed to meet Nuclear Energy Institute (NEI) guidelines or as an Energy Northwest initiative.
The primary purpose of the Energy Northwest Radiological Environmental Monitoring Program (REMP) is to evaluate the radiological impact that Columbia Generating Station (CGS) operation may have on the environment. Sampling is performed as specified in the Offsite Dose Calculation Manual (ODCM) and agreements made with the State of Washington Energy Facility Site Evaluation Council (EFSEC).
The program also serves to validate CGS effluent measurements and exposure pathway models and to provide a documented, historical record of CGS impact on the environment.
Additional sampling is also performed to meet Nuclear Energy Institute (NEI) guidelines or as an Energy Northwest initiative. The program also serves to validate CGS effluent measurements and exposure pathway models and to provide a documented, historical record of CGS impact on the environment. This report serves to document and communicate the program results and findings for calendar year 2013.
This report serves to document and communicate the program results and findings for calendar year 2013.A variety of environmental samples are routinely collected and analyzed by the REMP. The types of samples collected include air, water, soil, sediment, milk, fish, and garden produce. Additionally, the program continuously monitors direct radiation at numerous locations surrounding CGS. Analysis results are trended and compared to results from control locations, results obtained in previous operational and pre-operational periods, and regulatory limits.The results contained in this report indicate that CGS operation in 2013 had minimal radiological impact on the environment.
A variety of environmental samples are routinely collected and analyzed by the REMP. The types of samples collected include air, water, soil, sediment, milk, fish, and garden produce. Additionally, the program continuously monitors direct radiation at numerous locations surrounding CGS. Analysis results are trended and compared to results from control locations, results obtained in previous operational and pre-operational periods, and regulatory limits.
The only identified radiological impact to areas outside the CGS controlled area consisted of low level tritium in one plant discharge water sample that is attributed to recapture of CGS gaseous effluent tritium. All other identified radiological impact was limited to areas within the CGS controlled area. Sample results are consistent with the results obtained from control locations, results from the preoperational period, and historical results collected since CGS began commercial operation.
The results contained in this report indicate that CGS operation in 2013 had minimal radiological impact on the environment. The only identified radiological impact to areas outside the CGS controlled area consisted of low level tritium in one plant discharge water sample that is attributed to recapture of CGS gaseous effluent tritium. All other identified radiological impact was limited to areas within the CGS controlled area. Sample results are consistent with the results obtained from control locations, results from the preoperational period, and historical results collected since CGS began commercial operation.
With the exception of the one tritium sample result, all radioactive material identified outside the CGS controlled area was of natural origin or known to be present in the environment around CGS in the quantities identified.
With the exception of the one tritium sample result, all radioactive material identified outside the CGS controlled area was of natural origin or known to be present in the environment around CGS in the quantities identified. The results are consistent with and verify CGS effluent measurements and modeling of the exposure pathways.
The results are consistent with and verify CGS effluent measurements and modeling of the exposure pathways.Below is a summary of the 2013 results by exposure pathway: Direct Radiation  
Below is a summary of the 2013 results by exposure pathway:
-No impact was identified at locations beyond the CGS controlled area. Within the controlled area, the only impact identified was at locations known to be influenced by the Independent Spent Fuel Storage Installation (ISFSI) or radiation from the turbine building during operation.
Direct Radiation - No impact was identified at locations beyond the CGS controlled area. Within the controlled area, the only impact identified was at locations known to be influenced by the Independent Spent Fuel Storage Installation (ISFSI) or radiation from the turbine building during operation.
Airborne -No impact due to CGS operation was identified.
Airborne - No impact due to CGS operation was identified. The radionuclide activity identified in soil samples were consistent with activity levels known to exist in Hanford area soils.
The radionuclide activity identified in soil samples were consistent with activity levels known to exist in Hanford area soils.Waterborne  
Waterborne - No significant impact was identified. Low level tritium was identified in storm drain water and radionuclides related to CGS operation were identified in storm drain soil and cooling system sediment. Low level tritium was identified in one plant discharge water sample. All activity identified at these locations is attributed to recapture of CGS effluents. The 2013 data supports the longer term observation that storm drain tritium may be influencing groundwater tritium at locations near the storm drain pond. Tritium identified in sanitary waste water is attributed to discharges made from facilities operated by the Department of Energy. Tritium activity identified in groundwater was at levels consistent with levels known to exist in Hanford groundwater. Radionuclide activity identified in river sediment is consistent with activity levels known to exist in Hanford area sediment and soils.
-No significant impact was identified.
Ingestion - No impact was identified in any of the food sample results.
Low level tritium was identified in storm drain water and radionuclides related to CGS operation were identified in storm drain soil and cooling system sediment.
2013 Annual Radiological Environmental Operating Report 1-1             Energy Northwest/Columbia Generating Station
Low level tritium was identified in one plant discharge water sample. All activity identified at these locations is attributed to recapture of CGS effluents.
 
The 2013 data supports the longer term observation that storm drain tritium may be influencing groundwater tritium at locations near the storm drain pond. Tritium identified in sanitary waste water is attributed to discharges made from facilities operated by the Department of Energy. Tritium activity identified in groundwater was at levels consistent with levels known to exist in Hanford groundwater.
2.0 DEFINITIONS 2.0       DEFINITIONS a priori: refers to a "before the fact" limit that           Curie (Ci): A measure of radioactivity; equal to 3.7 x represent the capabilities of a measurement system and       1010 disintegrations per second, or 2.22 x 1012 not a limit for a particular measurement.                    disintegrations per minute.
Radionuclide activity identified in river sediment is consistent with activity levels known to exist in Hanford area sediment and soils.Ingestion  
a posteriori: refers to an "after the fact" limit             Direct Radiation Monitoring: The measurement of determined for a particular measurement and not a             radiation dose at various distances from the plant is limit for a measurement system.                               assessed using thermoluminescent dosimeters and Airborne Activity Sampling: Continuous sampling of           pressurized ionization chambers.
-No impact was identified in any of the food sample results.2013 Annual Radiological Environmental Operating Report 1-1 Energy Northwest/Columbia Generating Station 2.0 DEFINITIONS 2.0 DEFINITIONS a priori: refers to a "before the fact" limit that represent the capabilities of a measurement system and not a limit for a particular measurement.
air through the collection of particulates and radionuclides on filter media. Periodic soil samples are     DOE: U.S. Department of Energy.
a posteriori:
collected for gamma isotopic analysis to provide information on deposition to the soil from airborne           DOH: Washington State Department of Health.
refers to an "after the fact" limit determined for a particular measurement and not a limit for a measurement system.Airborne Activity Sampling:
releases.
Continuous sampling of air through the collection of particulates and radionuclides on filter media. Periodic soil samples are collected for gamma isotopic analysis to provide information on deposition to the soil from airborne releases.Alpha Particle (o): A charged particle emitted from the nucleus of an atom having a mass and charge equal in magnitude of a helium nucleus.Becquerel (Bq): One disintegration per second. One picocurie (pCi) equals 0.037 becquerel.
EFSEC: Energy Facility Site Evaluation Council.
Beta Particle (0): Charged particle emitted from the nucleus of an atom with a mass and charge equal in magnitude to that of an electron.Blank Sample: A sample of the same media as the field sample being analyzed but without any radionuclide(s) being measured.
Alpha Particle (o): A charged particle emitted from the nucleus of an atom having a mass and charge equal in         FFTF: Fast Flux Test Facility. This facility is referred magnitude of a helium nucleus.                               to as the DOE 400 area throughout this report.
It enables correction for the inherent sample background.
Becquerel (Bq): One disintegration per second. One           Flow Proportional Sampling: Sample collection picocurie (pCi) equals 0.037 becquerel.                      volume or frequency determined as a function of the flow rate of the water being sampled.
CGS: Columbia Generating Station, formerly referred to as WNP-2.CGS Controlled Area: The area within a 1.2 mile radius of the CGS reactor building and a narrow corridor extending from CGS east to the Columbia River.Composite Sample: A series of single collected portions (aliquots) analyzed as one sample. The aliquots making up the sample are collected at time intervals that are very short compared to the composite period.Control Station: A sampling station in a location not likely to be affected by plant effluents due to its distance and/or direction from the Columbia Generating Station.Counting Error: An estimate of the two-sigma uncertainty associated with the sample results based on respective count times.+ / -24F(SampleCPM/CountTine  
Beta Particle (0): Charged particle emitted from the nucleus of an atom with a mass and charge equal in           Grab Sample: A single discrete sample drawn at one magnitude to that of an electron.                             point in time.
+ BkgCPM/CouniTime)
Blank Sample: A sample of the same media as the               IDC: Energy Northwest Industrial Development field sample being analyzed but without any                   Complex, formerly referred to as the WNP- I and WNP-radionuclide(s) being measured. It enables correction         4 sites.
Curie (Ci): A measure of radioactivity; equal to 3.7 x 101 0 disintegrations per second, or 2.22 x 1012 disintegrations per minute.Direct Radiation Monitoring:
for the inherent sample background.
The measurement of radiation dose at various distances from the plant is assessed using thermoluminescent dosimeters and pressurized ionization chambers.DOE: U.S. Department of Energy.DOH: Washington State Department of Health.EFSEC: Energy Facility Site Evaluation Council.FFTF: Fast Flux Test Facility.
Indicator Station: A sampling location that is likely to CGS: Columbia Generating Station, formerly referred           be affected by plant effluents due to its proximity and/or to as WNP-2.                                                 direction from the Columbia Generating Station.
This facility is referred to as the DOE 400 area throughout this report.Flow Proportional Sampling:
CGS Controlled Area: The area within a 1.2 mile               Ingestion Pathway Monitoring: The ingestion radius of the CGS reactor building and a narrow               pathway includes milk, fish, and garden produce. Also corridor extending from CGS east to the Columbia             sampled (under special circumstances) are other media River.                                                       such as vegetation and animal products such as eggs and meat when additional information about particular Composite Sample: A series of single collected               radionuclides is needed.
Sample collection volume or frequency determined as a function of the flow rate of the water being sampled.Grab Sample: A single discrete sample drawn at one point in time.IDC: Energy Northwest Industrial Development Complex, formerly referred to as the WNP- I and WNP-4 sites.Indicator Station: A sampling location that is likely to be affected by plant effluents due to its proximity and/or direction from the Columbia Generating Station.Ingestion Pathway Monitoring:
portions (aliquots) analyzed as one sample. The aliquots making up the sample are collected at time           ISFSI: Independent Spent Fuel Storage Installation.
The ingestion pathway includes milk, fish, and garden produce. Also sampled (under special circumstances) are other media such as vegetation and animal products such as eggs and meat when additional information about particular radionuclides is needed.ISFSI: Independent Spent Fuel Storage Installation.
intervals that are very short compared to the composite period.                                                       Lower Limit of Detection (LLD): The smallest concentration of radioactive material in a sample that Control Station: A sampling station in a location not         will yield a net count (above system background) that likely to be affected by plant effluents due to its           will be detected with 95% probability with a 5%
Lower Limit of Detection (LLD): The smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with a 5%probability of a false conclusion that a blank observation represents "real" signal.Mean: The average, i.e., the sum of results divided by the number of results.Microcurie:
distance and/or direction from the Columbia                   probability of a false conclusion that a blank Generating Station.                                           observation represents "real" signal.
3.7 x 10a disintegrations per second, or 2.22 x 10 6 disintegrations per minute.2013 Annual Radiological Environmental Operating Report 2-1 Energy Northwest/Columbia Generating Station 2013 Annual Radiological Environmental Operat.ing Report 2-1 Energy Northwest/Columbia Generating Station Milliroentgen (mR): 1/1000 Roentgen; a unit of exposure to X or gamma radiation.
Counting Error: An estimate of the two-sigma                 Mean: The average, i.e., the sum of results divided by uncertainty associated with the sample results based on       the number of results.
MDA: Minimum Detectable Activity.MDC: Minimum Detectable Concentration.
respective count times.
NEI: Nuclear Energy Institute NIST: National Institute of Standards and Technology.
+ / - 24F(SampleCPM/CountTine+ BkgCPM/CouniTime)             Microcurie: 3.7 x 10a disintegrations per second, or 2.22 x 106 disintegrations per minute.
NPDES: National Pollutant Discharge Elimination System.NRC: U.S. Nuclear Regulatory Commission.
Report Operating Report  2-1                Energy Northwest/Columbia Generating Station 2013  Annual Radiological 2013 Annual              Environmental Operat.ing Radiological Environmental                  2-1                Energy Northwest/Columbia Generating Station
ODCM: Offsite Dose Calculation Manual. Licensing document that contains the offsite radiological requirements.
 
Picoeurie (pCi): 1 x 10-2 Curie or 2.22 disintegrations per minute, one millionth of a microcurie.
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Radioiodine:
Milliroentgen (mR): 1/1000 Roentgen; a unit of             Site Certification Agreement (SCA): The initial exposure to X or gamma radiation.
Radioisotopes of iodine. For commercial nuclear reactors, iodine-131 to iodine-135 are the principle radioiodines of concern. Due to its longer half-life, iodine- 131 is the most probable radioiodine identifiable in the environment.
MDA: Minimum Detectable Activity.
REMP: Radiological Environmental Monitoring Program.Range: The difference between the smallest and largest results.Restricted Area: Any area to which access is controlled for purposes of protection of individuals from exposure to radiation and radioactive materials.
Columbia Generating Station licensing agreement with the State of Washington. The REMP sampling commitments in the SCA have been modified by I
Roentgen:
MDC: Minimum Detectable Concentration.
Unit of exposure to ionizing radiation in air.Site Certification Agreement (SCA): The initial Columbia Generating Station licensing agreement with the State of Washington.
EFSEC agreements.
The REMP sampling commitments in the SCA have been modified by EFSEC agreements.
Spiked Sample: A sample that has had a known I
Spiked Sample: A sample that has had a known quantity of radionuclide(s) added for the purposes of assessing analytical performance.
NEI: Nuclear Energy Institute                              quantity of radionuclide(s) added for the purposes of NIST: National Institute of Standards and Technology.
Standard Deviation:
assessing analytical performance.
A measure of the scatter of a set of observations (or samples) around their mean value.Indicated by "a".Standard Error of the Mean: An estimate of the uncertainty associated with the mean of observation (or sample) averages.
Standard Deviation: A measure of the scatter of a set U
Also known as the standard deviation.
NPDES: National Pollutant Discharge Elimination System.
S-SE= n where S2, the variance is S2 =--n(Xi-X)2 ni (n-I)SWTF: Sanitary Waste Treatment Facility.
of observations (or samples) around their mean value.
The sanitary waste processing facility for the Columbia Generating Station, the IDC, and the Department of Energy's 400 Area.TEDA: triethylene diamine Thermoluminescent Dosimeter (TLD): A TLD is a phosphor that stores energy from exposure to radiation and emits that energy in the form of light when heated.I I I I U I I I I I U I I I I I U I I 2013 Annual Radiological Environmental Operating Report 2-2 Energy Northwest/Columbia Generating Station  
Indicated by "a".                                            I NRC: U.S. Nuclear Regulatory Commission.                   Standard Error of the Mean: An estimate of the ODCM: Offsite Dose Calculation Manual. Licensing document that contains the offsite radiological uncertainty associated with the mean of observation (or sample) averages. Also known as the standard I
deviation.
requirements.
Picoeurie (pCi): 1 x 10-2 Curie or 2.22 disintegrations SE=
S*
S-n I
per minute, one millionth of a microcurie.                 where S2, the variance is Radioiodine: Radioisotopes of iodine. For commercial nuclear reactors, iodine-131 to iodine-135 are the S2 =--n(Xi-X)2 ni  (n-I)
I principle radioiodines of concern. Due to its longer half-life, iodine- 131 is the most probable radioiodine identifiable in the environment.
SWTF: Sanitary Waste Treatment Facility. The sanitary waste processing facility for the Columbia I
Generating Station, the IDC, and the Department of REMP: Radiological Environmental Monitoring Program.
Energy's 400 Area.
TEDA: triethylene diamine U
Range: The difference between the smallest and largest results.                                                   Thermoluminescent Dosimeter (TLD): A TLD is a phosphor that stores energy from exposure to radiation I
Restricted Area: Any area to which access is                and emits that energy in the form of light when heated.
controlled for purposes of protection of individuals from exposure to radiation and radioactive materials.                                                                   I Roentgen: Unit of exposure to ionizing radiation in air.
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==3.0 INTRODUCTION==
==3.0 INTRODUCTION==


==3.0 INTRODUCTION==
==3.0     INTRODUCTION==
 
3.1      Site Description The Columbia Generating Station (CGS) is a 1230 MWe commercial nuclear power plant that achieved initial criticality on January 19, 1984. The plant is located in a sparsely populated shrub-steppe region within the Department of Energy (DOE) Hanford Site in southeastern Washington. The plant is approximately three miles west of the Columbia River and is surrounded on all sides by uninhabited desert land. The nearest large population centers are Richland, Pasco and Kennewick, which are 12 miles south, 18 miles southeast, and 21 miles southeast, respectively. The nearest privately owned lands are located approximately four miles east-northeast of the plant, across the Columbia River. The site has a bimodal wind pattern with winds primarily from the northwest and south. (1) The primary region of focus for REMP sampling is the farming region east of the plant.
Naturally occurring radionuclides exist in detectable quantities throughout the world and are seen in many of the samples collected for the REMP. Some examples of naturally occurring radionuclides that are frequently seen in samples are potassium-40, beryllium-7, actinium-228 (present as a decay product of radium-228), and radium-226. Additionally, some relatively long lived anthropogenic radioisotopes, such as strontium-90 and cesium-137, are also seen in some REMP samples; these radionuclides exist in measurable quantities    12 throughout the world as a result of fallout from atmospheric nuclear weapons testing. ' 3)
Due to the location of CGS on the Hanford Site, there are other sources of reactor produced radionuclides in close proximity to the plant. CGS is unique in the U.S. commercial nuclear power industry in this respect. Hanford related radionuclides, most notably tritium, are identified in some CGS REMP samples. Though the presence of these radionuclides in the vicinity of CGS are not necessarily reflective of CGS activity, changes in the levels of these radionuclides are monitored to assess any contribution that CGS may be making to the established background. The DOE has an active REMP program for the Hanford Site that overlaps the CGS REMP.
3.2      Program Background The CGS REMP is designed to conform to the Nuclear Regulatory Commission (NRC) Regulatory Guides 4.1,4) 4.8,(5) and the Radiological Assessment Branch Technical Position. 61 In addition, the REMP also meets the requirements of 10 CFR 72.44(d)(2) for coverage of the ISFSI.
The quality assurance aspects of the sampling program and the thermoluminescent dosimetry are conducted in accordance with Regulatory Guides 4.15(71 and 4.13.(8) The REMP also adheres to the requirements of the Washington Energy Facility Site Evaluation Council,(9 ) the Columbia Generating Station Technical Specifications,(10 .)and the Offsite Dose Calculation Manual"1 1 ) These requirements cover the environmental sampling and sample analysis aspects of the program, and also the reporting and quality assurance requirements.
2013 Annual Radiological Environmental Operating Report    3-1                Energy Northwest/Columbia Generating Station
 
1 I
The preoperational phase of the program, which lasted from March 1978 until initial criticality in January 1984, provided a baseline of background environmental data. Variability in the background levels of radioactivity over time is due to differences in geologic composition, meteorological I
conditions, decay of nuclear testing fallout material in the environment, and seasonal changes.
Variability in results may also have been introduced by changing analytical contractors and the use of different correction factors over the years.
I The Energy Northwest Environmental Services Laboratory performed all routine REMP sampling and analyses in 2013. Thermoluminescent dosimeters (TLDs) used in the REMP were processed by U
the Hanford External Dosimetry Program (HEDP) operated by Mission Support Alliance (MSA).
In addition to evaluating the environmental concentrations against regulatory limits, the REMP may I
also compare results to state standards.1 12. 13) The results may also be evaluated by comparing them to similar measurements made during the preoperational and previous operational periods and to the detection capabilities associated with the current methods of analysis.
I 3.3      Program Objectives I
The REMP provides an independent mechanism for determining the levels of radioactivity in the plant environs in order to empirically quantify and qualify any radiological effect plant operation may be making on the environment. The program serves to ensure that any accumulation of                              I radionuclides in the environment resulting from station operation will be identified promptly and before they become significant or exceed established limits.
While in-plant monitoring programs are used to ensure that 10 CFR 20(14) and 10 CFR 50(15) criteria I
for releases of radioactive effluents are met, the REMP further verifies that the measured concentrations of radioactive material and levels of radiation observed in the environment are not higher than expected based on CGS effluent measurements and modeling of the exposure pathways.
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2013 Annual Radiological Environmental Operating Report 3-2              Energy Northwest/Columbia Generating Station I
 
4.0 PROGRAM DESCRIPTION 4.0    PROGRAM DESCRIPTION The ODCM contains the CGS licensing based sampling requirements for the REMP. Additional sampling requirements are specified in resolutions with the Washington State Energy Facility Site Evaluation Council (EFSEC) or are self-initiated in response to site specific or industry wide concerns.
The sampling plan presented in Table 4-1 gives an overview of the REMP sampling routine, a summary of the sample locations, the specified collection frequency, and the types of analyses to be performed.
The methods of sampling and sampling frequencies utilized in the program are mostly dictated by regulatory requirements. Factors such as nuclide half-lives and the major exposure pathways for the radionuclides potentially released from the plant have been taken into account in determining the sampling methodology.
4.1      Sample Locations One hundred and ten sampling locations (referred to as 'stations') are included in the monitoring program. More than one sample type may be collected at a sample station. One hundred and one indicator and three control stations are located within a 10-mile radius of CGS. Six additional stations are located beyond the ten mile radius of the plant, two are indicator locations and four are control locations.
Sample stations are listed in Tables 4-1 and 4-2. Most station locations are shown in Figures 4-1 to 4-4.
The locations of most sample stations have been selected on the basis of an exposure pathway analysis. The exposure pathway analysis was based on factors such as weather patterns, anticipated emissions, likely receptors, and land use in the surrounding areas. Samples collected from stations located in areas that potentially could be influenced by CGS operation are used as indicators.
Samples collected from locations that are not likely to be influenced by CGS operation serve as controls. Results from indicator stations are compared to the results from control stations and results obtained during the previous operational and preoperational years of the program in order to assess the impact CGS operation may be having on the environment.
4.2      Independent Spent Fuel Storage Installation (ISFSI)
The Independent Spent Fuel Storage Installation (ISFSI) is a fenced, secured area constructed to provide a storage location for spent nuclear fuel. The spent fuel is stored in HI-STORM dry storage casks which are placed on concrete pads inside the facility. The pads are 30-feet wide by 135-feet long and each pad can hold up to 18 casks. The ISFSI is located approximately 500 meters north-northwest of the reactor building. Three security fences surround the ISFSI facility.
Direct radiation monitoring of the ISFSI is performed using TLDs placed at 10 different locations on the second of three security fences that surround the facility. The TLDs are exchanged quarterly. In addition, two other TLD stations, Station 121 located approximately 200 meters north of the turbine building and Station 122 located approximately 100 meters north of the ISFSI, were installed to monitor ISFSI direct radiation. Figure 4-1 shows the ISFSI location in relation to CGS and the position of the 2 additional TLD locations. Figure 4-4 shows the location of the 10 TLD stations located around the ISFSI. This arrangement of TLDs in conjunction with the radiological surveys conducted by the CGS Radiation Protection Department serve as the radiological monitoring program for the ISFSI.
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I 4.3:      Land Use Census                                                                                              I A land use census covering the areas within a five mile radius of CGS is performed annually. The objective of the land use census is to identify the locations of the nearest milk animal, residence, and garden greater than 500 ft2 producing broadleaf vegetation. This information is used to determine whether any site located during the census has a calculated dose or dose commitment greater than the sites currently monitored for the same exposure pathway. If a new location with a higher dose commitment was found, routine sampling of that dose pathway would be initiated at that new site. The I
results of the 2013 five miles land use census are presented in Table 4-3. No significant changes from the 2012 land use census were observed.
4.4      Sampling Methods                                                                                              3 Energy Northwest personnel collect environmental samples in accordance with the program plan outlined in Table 4-1. Methods of sample collection and TLD handling are specified in REMP specific procedures. All routine REMP samples collected in 2013 were prepared for analysis at the Energy Northwest Environmental Services Laboratory located in Richland, WA. The section 4.4 subsections I
below give a general overview of the sampling methods used in the REMP. Generic descriptions of the REMP sample analysis methods are given in section 4.5.                                                                  I 4.4.1    Direct Radiation Direct radiation dose levels are monitored with Harshaw Model 8807 thermoluminescent dosimeters (TLDs). The TLDs are placed in the field between three and five feet above the ground. TLDs are wrapped in aluminum foil and sealed in plastic bags to prevent damage. TLDs are exchanged on a quarterly basis.
The locations of the TLD stations are listed in Table 4-2 and are shown in Figures 4-1 through 4-4.
Station 9A near Sunnyside, WA serves as the environmental TLD control location. Station 11 9C serves as the control for Station 119B (the cooling system sediment disposal basin). The remaining TLDs deployed in the field serve as indicator TLDs.                                                                          U The TLDs are arranged in a series of rings that encircle CGS. The innermost ring of TLD stations, referred to as the "S" stations, are located inside the CGS site boundary at distances that range from 0.3-0.8 miles from the reactor building centerline. The second ring of TLDs, referred to as the "near plant"                I stations, are located at distances ranging from 0.9 to 2.1 miles from the reactor building. The outer ring of TLDs are located at distances that range from a little under three miles to around ten miles. A MicroRem dose rate meter is available as a backup device and to take real time readings as needed.
4.4.2    Airborne - Particulate/Iodine Weekly air particulate and radioiodine (Iodine -131) samples are obtained through the use of low volume (1.5 cfm), constant flow-rate sampling units located at 1.2 locations. The samples collected at Station 9A (Figure 4-3) serve as controls, the samples collected at all other locations (Figures 4-1, 4-2, and 4-3) are indicators. Air particulate samples are collected using 47mm diameter glass fiber filters, air iodine 3
samples are collected using Radeco CP- 100 TEDA impregnated charcoal cartridges. The air particulate filter and charcoal cartridge are placed in tandem, particulate filter first, in a holder that attaches to the air inlet of the sampler unit. The sampler units are placed in ventilated metal weatherproof housings mounted on elevated platforms at each air sample location. The filter media are changed weekly. Four 4-2 U
2013 Annual Radiological Environmental Operating Report                    Energy Northwest/Columbia Generating Station
 
additional air sample monitor locations are available to monitor work at the DOE 618-11 burial site if needed.
4.4.3    Water Water sampling is performed to meet ODCM and State of Washington EFSEC requirements, comply with NEI guidelines, or as a CGS initiative. REMP water sampling can be categorized as follows:
* Intake-River/Drinking Water; two locations (Stations 26 and 29)
* Deep Groundwater; three locations (Stations 52, 31 and 32)
* Shallow Groundwater; ten locations (MW-3, 5, 6 and MW-8 through MW-14)
* Plant Discharge Water; one location (Station 27)
* Storm Drain Water; one location (Station 101)
* Sanitary Wastewater; two locations (Stations 102A and 102B)
The sample at Station 26 is obtained using a composite sampler that draws water from the plant intake water system (TMU). The source of this water is the Columbia River. The station serves as a control location, as it is upstream of the plant discharge location, and also as a drinking water location as drinking water for CGS comes from this source. Station 29 is a composite sampler located at the City of Richland Water Treatment Plant located 11 miles downstream of the plant discharge. Station 29 is an indicator station for both river and drinking water.
The ODCM requirement for a downstream water sample "near but beyond the mixing zone" is conservatively met by Station 27, a composite sampler that collects water from the cooling tower discharge line just prior to final discharge into the Columbia River. This sample reflects the radioactivity present in the plant discharge prior to any river dilution, rather than the concentrations that would be found after dilution in the mixing zone. Composite samples from Stations 26, 27, and 29 are collected monthly and analyzed for gamma emitting radionuclides, gross beta, and tritium.
Three drinking water wells on Energy Northwest property are used to provide deep groundwater samples. These wells are greater than 400 feet deep and provide samples from the confined aquifer.
under CGS. Station 52 is a deep well located 0.1 mile north of the CGS reactor building. Station 31 and 32 are deep wells at the IDC (ENW Industrial Development Complex) located 1.2 miles down gradient from CGS. Water from Station 52 can be used as a backup source for drinking water and fire protection. The IDC wells supply water for drinking and. fire protection at the IDC site. All of these wells are considered indicator locations. Quarterly grab samples are collected from each well and analyzed for gamma emitting radionuclides and tritium.
Station 101 is a composite sampler that collects a representative sample of water flowing into the storm drain pond located east of CGS. The main sources of water to the pond are discharges from the potable water and plant makeup water demineralizer treatment systems. Storm water runoff from the CGS site is also directed to this location. Water discharges from CGS that have been verified to meet radiological environmental discharge limits are another potential source of water to the storm drain pond. Water is collected monthly using a flow-proportional composite sampler and analyzed for gross beta, gamma emitting radionuclides, and tritium.
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The Sanitary Waste Treatment Facility (SWTF) receives sanitary waste water from CGS, the IDC (ENW                      I Industrial Development Complex), the Kootenai Building, and the DOE 400 area. Discharge standards and monitoring requirements for the SWTF are established in EFSEC ResolutionNo. 300. (16) Station 102A is a flow meter and composite sampler located on the DOE 400 area sewer line before it ties into the sewer lines coming from Energy Northwest facilities. Water used at the DOE 400 area is drawn from aquifers that are known to be contaminated with tritium as a result of past DOE activities on the Hanford Site, consequently, the water sampled at Station 102A has tritium concentrations normally around 1500-3 2000 pCi/liter. Station 102B is a composite sampler that collects a representative sample of water flowing into the head works at the SWTF. The sample obtained here contains water from all the Energy Northwest facilities mentioned above and the DOE 400 area. Monthly samples are collected at both 3
Stations 102A and 102B and analyzed for gross alpha, gross beta, tritium, and gamma emitting radionuclides.
Routine quarterly grab samples are taken as part of the REMP from 10 shallow groundwater monitoring wells surrounding CGS. The monitoring well locations are shown in Figure 4-1. The shallow groundwater wells are all less than 100 feet deep and allow samples to be obtained from the unconfined I
aquifer under CGS. None of the wells are used for drinking water. Sampling from these locations is performed to meet NEI 07-07 guidelines (17) and requirements in the CGS NPDES permit.
4.4.4    Soil                                                                                                        I Annual soil samples are a requirement of EFSEC Resolution No. 332.(9) For 2013, two soil samples were collected from locations near CGS, two samples from farmland in Franklin County east of CGS, and one sample from a control location near Sunnyside, WA. Each sample was collected from an area of                          I approximately one square foot to a depth of approximately one inch. About two kilograms of soil was collected for each sample. Soil samples are analyzed for gamma activity on a dry weight basis.
4.4.5    Sediment River sediment samples are collected semiannually as required by the ODCM and EFSEC Resolution No. 332.(9) The upstream sediment sample location (Station .33) is approximately two miles upriver from the plant discharge. The downstream sample (Station.34) is collected approximately one mile downstream from the plant discharge. Each sample consists of approximately two kilograms of shallow surface sediment scooped from areas known to be underwater during high water periods and where the potential for sediment accumulation is likely. Sediment samples are dried in an oven and then analyzed for gamma emitting radionuclides on a dry weight basis.
Cooling system sediment samples are collected and analyzed whenever cooling system sediment is added to the disposal cells (Station 1 19B, Figure 4-1). Disposal of cooling system sediment is made in accordance with EFSEC Resolution No. 299.(18) Pre-disposal samples are collected and analyzed prior to                ,
transfer to ensure the material will be within the limits specified in the EFSEC resolution. Following transfer, the material is allowed to dry and a post-disposal sample is collected and analyzed.                        3 4.4.6    Fish Annual fish sampling is usually performed in the fall. Fish samples collected from the Columbia River (Station 30) serve as indicator samples, whereas fish collected on the Snake River (Station 38) serve as 3
control samples. Only edible portions of the fish are used to prepare the samples for analysis. Fish 2013 Annual Radiological Environmental Operating Report 4-4              Energy Northwest/Columbia Generating Station I
 
samples are analyzed for gamma emitting radionuclides on a wet weight basis. Three species of fish are collected; an anadromous species (salmon or steelhead), and two other species generally considered edible or potentially edible (typically carp, catfish, sucker, or whitefish). The same species are collected at each location. Electroshock techniques have historically been used for fish collection. Anadromous species are usually collected at fish hatcheries.
4.4.7    Milk Milk samples are collected monthly during the fall and winter months (October through March).
During the spring and summer months when cows are more likely to be grazing or on fresh feed, milk samples are collected twice per month. Raw milk samples are collected within a few hours of milking and the samples are normally prepared and analyzed within four days. Milk samples were collected in 2013 from two locations. Station 36 in Franklin County serves as the indicator location and is the only known dairy within a ten mile radius of CGS. Station 9B near Sunnyside, WA serves as the control location.
4.4.8    Garden Produce Samples of local garden produce are collected monthly during the growing season when the produce is readily available. Three types of garden produce are typically collected; root crops, fruits, and leafy vegetables. Control samples (Station 9C) are usually obtained from the lower Yakima Valley. Indicator samples (Station 37) are primarily collected from areas downstream of the CGS discharge where crops are irrigated with Columbia River water. The Riverview area of Pasco is the principle collection location for fruit and root crops. Collection of leafy vegetables is primarly made from locations that could potentially be influenced by CGS gaseous emissions. Vegetation samples may also be collected from locations closer to CGS; however none were collected in 2013. Garden and vegetable samples are typically purded in a food processor and then analyzed for gamma emitting radionuclides on a wet weight basis. Only edible portions are used for analysis.
4.5      Sample Analyses General descriptions of the procedures used to analyze REMP samples are provided in the following sections. All REMP TLDs in 2013 were processed by Mission Support Alliance (MSA) at the Hanford External Dosimetry Program (HEDP) facility located in Richland, WA. All routine REMP field samples were collected and analyzed by Energy Northwest Environmental Services personnel. Samples are normally collected and analyzed within a short time period to ensure required detection sensitivities are met and to provide timely results. Sample count times are conservatively calculated to ensure required a priori LLDs are achieved. Table 4-4 lists the ODCM required LLDs and the nominal target LLD used in the Energy Northwest REMP program.
4.5.1    Analysis of TLDs REMP TLDs are analyzed on a Harshaw Model 8800 hot gas reader. The reader is calibrated weekly and immediately prior to processing the environmental TLDs. The reader is calibrated with TLDs that have been given a known exposure from a cesium- 137 source. Each group of environmental TLDs is processed with blank (freshly annealed) TLDs and spiked TLDs that have been given a known exposure.
Exposure received by the field TLDs during transport is monitored with a set of 'trip' control dosimeters that accompany the field dosimeters to and from the field locations and while they are in storage.
2013 Annual Radiological Environmental Operating Report 4-5                Energy Northwest/Columbia Generating Station
 
I Another set of TLDs, the building controls, are used to determine~the exposure of the TLDs at the storage                I location. The TLD exposure during transport to and from the field was determined from the difference between the building control results and the trip control results.                                                      i 4.5.2    Gross Beta Activity on Air Particulate Filters Air particulate filters are counted directly in a gas flow proportional counter after a delay of several days to allow for the decay of radon and its progeny. Samples were counted using a Protean WPC-9550 instrument which allows automated sample counting and simultaneous alpha/beta determination. If gross beta activity is identified significantly above the mean of the control, gamma isotopic analysis is performed on the individual samples.
I 4.5.3    Measurement of Gamma Emitting Radionuclides                                                                    3 Gamma isotopic analysis allows identification and quantification of gamma-emitting radionuclides that may be attributable to CGS effluents. Shielded, high purity. germanium (HPGe) detectors are used to                      j assay environmental samples for gamma emitting radionuclides. All samples are counted in standardized, calibrated geometries.
    " Liquids - Measured aliquots of the liquid samples are poured into appropriately sized                              I Marinelli beakers or plastic canisters. Sample results are corrected for decay during the collection period if applicable. Results are reported in pCi/liter.                                            I
    "    Solids - Soil, sludge, and sediment samples are dried and if needed ground. Foodstuff, biota (fish), and vegetation, are chopped finely or pureed and then analyzed wet (no drying is done). For foodstuff (including fish), only the edible portion of the sample is used. Sample aliquots are placed in tared containers and weighed. Results are reported in pCi/kg.
* Charcoal Cartridges - Typically four charcoal cartridges are counted simultaneously using a cartridge holding jig that positions the cartridges in a standardized geometry to the side of the detector. Detector calibration files are maintained for both face count and side count positions. If radioiodines are identified in the assay of a group, each charcoal cartridge in the group is assayed separately. Results are corrected for decay during the sample collection period. Results are I
reported in pCi/m 3 .                                                                                          3
* Air Particulate Filters - At the end of each quarter, air particulate filters are composited on a station by station basis. The filters are stacked in a Petri dish and analyzed by gamma spectroscopy. Results are reported in pCi/m 3 and represent the total quarterly gamma activity collected at each station. Results are decay corrected to the midpoint of the sample collection I
period. If a radionuclide related to CGS operation is positively identified, the filters are separated and counted individually.                                                                            I 4.5.4    Gross Alpha and Gross Beta Activity in Water                                                                    g A measured aliquot of each sample is evaporated to a small volume then quantitatively transferred to a ribbed, stainless steel planchet. Final evaporation is normally done under a heat lamp. Residue mass is determined by weighing the planchet before and after mounting the sample. The planchet is counted for gross alpha and beta activity using a Protean WPC-9550 automatic gas flow proportional 3
counter which allows automated sample counting and simultaneous alpha/beta determination. Results 2013 Annual Radiological Environmental Operating Report 4-6                  Energy Northwest/Columbia Generating Station l
 
are corrected for sample self-absorption: using the sample residue mass values. Results are reported in pCi/liter.
4.5.5    Tritium in Water The sample is distilled, then 8.0mL of the distillate is mixed with 12.OmL of scintillation cocktail.
The sample mixture is analyzed on a Packard Tri-Carb 2900TR automatic liquid scintillation counter.
Results are reported in pCi/liter..
4.5.6    Strontium-89/90, Iron-55, and Nickel-63 These "hard to detect" analytes are not routinely analyzed as part of the CGS REMP. When needed, these analyses are performed under contract by Teledyne- Brown Environmental Services Laboratory located in Knoxville, TN using the vendor's standard analysis procedures.
4.5.7    Low Level Radioiodine in Milk and Water Four liters of sample are first equilibrated with stable iodide carrier. Anion exchange resin is then added and mixed for a period sufficient to allow any iodine present in the sample to be captured by the resin.
The resin is then isolated from the liquid sample and transferred to a small counting container. The radioiodine content is determined by gamma spectroscopy analysis. Results are reported in pCi/liter.
4.6      Data Analysis Methods Counting results for low level samples are often within the counting error of the background determination; consequently results. for these samples can be positive or negative values. Though most REMP analytical results are belowthe detection limit, an actual calculated value has been reported. In some cases the reported value is zero or a negative number. Reporting results in this manner is the preferred practice for low level environmental analyses as it gives an indication of positive or negative biases that may be present and prevents loss of individual results inherent in the use of "less than" (<)
values. Also reported in most cases are the aposterioriMDA values. Anuclide is flagged as positively identified if its calculated value is greater than the MDA. A listing of the Energy Northwest nominal target LLDs (apriori)for each sample type is provided in Table 4-4; the ODCM required LLDs are also included for a comparison.
Data is trended following analysis for many of the sample types analyzed. For analyses such as .gross beta on air particulate filters where results are normally above the detection limit, indicator results are plotted with the control results for better comparison. Analysis results that are normally below detection limits are plotted against historical data .to monitor if trends may be evident.
Thermoluminescent dosimeter (TLD) data is presented in both units of mR/day and mR/standard quarter.
TLD results in mR/day are calculated by taking the total exposure (in mR) determined for each TLD, correcting for storage background and any transit (or trip) exposure received during distribution and retrieval, then dividing by the number of days the TLD was in the field. The mR/standard quarter values are calculated by multiplying the mR/day value by 91.25 days (365/4). All TLD results are reported in units of exposure (Roentgen) and not in units of dose (Rem).
2013 Annual Radiological Environmental Operating Report 4-7              Energy Northwest/Columbia Generating Station
 
I 4.7      Changes to the Sampling Program in 2013 i
There were no major changes made to ODCM or EFSEC Resolution No. 332(9) mandated sampling in 2013. Sampling and analysis of shallow groundwater wells around CGS was continued as a routine I
part of the REMP. No samples were obtained from one of the shallow groundwater wells (MW-7) in 2013 due to lack of water. The last sample obtained from this location was in the third quarter 2012.
Sampling -from Station 102A was terminated at the end of December. This station consisted of a i
composite water sampler that sampled the sanitary effluent line coming from the DOE 400 area. The effluent line was plugged in mid-December and ENW is no longer accepting sanitary waste from this location. One TLD location, Station 73, was moved in October to a new location due to construction activities. The new location is in the same geographical sector and approximately 175 feet from the old location.                                                                                                    I i
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2013 Annual Radiological Environmental Operating Report              Energy Northwest/Columbia Generating Station
 
TABLE 4-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING PLAN SAMPLE METHOD AND SAMPLE STATION (b'                    COLLECTION                    TYPE AND FREQUENCY OF SAMPLE TYPE'a.                          NUMBER                        FREQUENCY* 1                              ANALYSIS AIRBORNE Particulates and              1, 4-8, 9A, 21, 23,40, 48,    Continuous sampling; weekly            Weekly air filters gross beta and Radioiodine (6/1 2 )1d)        and 57'                        collection.                            iodine cartridge gamma isotopic.
Quarterly air filter composite gamma isotopic.
DIRECT RADIATION TLD1 g)(34/79)                1-8, 9A, 10-25, 40-47, 49-    Continuous monitoring, quarterly      Radiation exposure monitoring 51, 53-56, 58, 65, 71-90,      collection.                            processed on a quarterly 119B, 119C, 120-129,                                                  frequency.
136A-138A, 150-151.
WATERBORNE River/Drinking Waterh)        26, 27 and 29                  Composite aliquots1'; monthly          Monthly gamma isotopic, gross (3/3)                                                        collection,                            beta, and tritium. lodine-1310) as required.
Storm Drain Water (0/1)        101                            Composite aliquots&deg;', monthly          Monthly gamma isotopic, tritium, collection.                            and gross beta.
Sanitary Waste                102A, 102B                    Composite aliquots"), monthly          Monthly gamma isotopic, gross Treatment Facility                                            collection.                            beta, gross alpha, and tritium.
Water (0/2)
Ground Water ( 2 / 3 )(k1      31, 32, and 52                Grab sample performed quarterly.      Quarterly gamma isotopic and tritium.
Ground Water                  MW-3, 5, 6, 8-14              Grab sample performed quarterly.      Quarterly gamma isotopic and Monitoring (0/I10)"                                                                                  tritium.
SOIL AND SEDIMENT Soi1l"(0/5)                    9A, 7, 8, 23, 48              Grab sample performed annually.        Annual gamma isotopic.
0 Strontium-90'    as required.
River Sediment (1/2)(1)        33 and 34                      Grab sample performed                  Semiannual gamma isotopic.
semiannually.
Cooling System                119B, 119C                    Grab sample of dried sediment          Gamma Isotopic. After disposal.
Sediment Disposal Area                                        within 30 days of disposal date.
(0/2)
INGESTION Milk'* (2/2)                  9B, 36                        Grab sample collected                  Gamma isotopic, Iodine-131 each semimonthly during grazing            sample. Strontium-90.'n) as season, monthly at other times.        required Fish'0 ' (2/2)                30, 38                        Grab samples collected annually.      Gamma isotopic each sample.
Garden Produce(')(l/2)        9C, 37                        Grab samples collected monthly or      Gamma isotopic each sample.
at time of harvest.
Report      4-9                          Energy Northwest/Columbia Generating Station 2013  Annual Radiological 2013 Annual                Environmental Operating Radiological Environmental  Operating Report      4-9                          Energy Northwest/Columbia Generating Station
 
I TABLE 4-1 FOOTNOTES:
(a)      -The fraction in parentheses for each sample type indicates the ratio of ODCM-required sample locations tothe total number of sample locations currently being monitored in the surveillance program. Additional sampling is perforimed to meet EFSEC Resolution 332 requirements or as an ENW initiative.
(b)      The underlined sample location designates a control station.
(c)      Sample collection is performed at a frequency specified in the ODCM and EFSEC resolutions. Some sampling referenced in Table 4-1 is performed at CGS initiative. Sample deviations are permitted if samples are unobtainable due to hazardous 5
conditions, seasonal availability, malfunction of automatic sampling equipment, or other legitimate reasons.
(d)      The ODCM specifies six air sample locations and EFSEC Resolution 332 specifies nine. Two of the air sample stations are maintained at CGS initiative and are not requirements of either the ODCM or EFSEC Resolution 332.                                      I (e)      Sampling is performed to meet NEI 07-07 guidelines and NPDES requirements.
(t)      Soil samples are collected from five locations to satisfy EFSEC Resolution 332 requirements. Two samples are collected from locations near CGS, two from locations in Franklin County, and one collected from a control location. Sample locations listed in 3
Table 4-1 are the location sampled in 2013. EFSEC 332 requires strontium-90 analysis be performed if gamma analysis results (g) are greater than a specified threshold.
TLD Stations 71-86 are not included among the 34 TLD stations required by the ODCM. Alternate designations for these
                                                                                                                                                  &#xa3; stations are I S-I 6S. EFSEC Resolution 332 requires 25 or more TLD stations to be located within a 10-mile radius of CGS.
Other instruments, such as a pressurized ion chamber (PlC), may be used in place of or in addition to TLDs as per ODCM table 6.3.1-1 (b). CGS REMP maintains a uRem meter for this purpose.
(h)      The term "river/drinking water" is used throughout this report because the drinking water is taken from the Columbia River.
Station 26, CGS makeup water intake from the Columbia River is both an upstream water sample and the drinking water sample location. Station 29 is a downstream drinking water sample location. The Station 27 sample, which is drawn from the plant discharge line, is taken in place of a "downstream" water sample near but beyond the mixing zone. It reflects the radioactivity present in the plant discharge prior to any river dilution. EFSEC Resolution 332 requires samples from at least one downstream I
drinking water location and samples from the plant intake and discharge water systems.
(i)      Composite samples are collected using automatic sampling equipment that collects samples based on a flow proportional or timed interval basis. If timed interval sampling is used, the interval period is short (e.g. hourly) relative to the compositing period 3
(e.g. monthly).
When the dose calculated via ODCM methodology for consumption of water exceeds I mrem per year, low level iodine-I 31 analyses are performed on the drinking water samples.
(k)      Sampling from these locations fulfills ODCM table 6.3.1-1 3b requirements. EFSEC Resolution 332 requires sampling from at least one deep well used for fire protection and/or as a backup drinking water sources.
(I)      Downstream sampling fulfills ODCM table 6.3.1-1 3d requirements. EFSEC Resolution 332 requires annual sediment samples upstream and downstream of the plant discharge.
(m)      ODCM table 6.3.1-1 4a milk collection requirements cannot strictly be met due to the lack of milking animals near CGS. Milk samples are collected from the nearest dairy potentially impacted by CGS operation and also from a control location at the I
frequency specified in the ODCM. EFSEC Resolution 332 specifies sampling from at least one milk location within the 10-mile radius of CGS and also from a control location. Broadleaf vegetation can be sampled in lieu of milk if a representative milk sample is not available.
(n)      ODCM table 6.3. 1-1 (k) requires that if cesium-134 or cesium-137 is measured in an individual milk sample in excess of 30 pCi/l iter, then a strontium-90 analysis will also be performed.
(o)      Station 30 is the Columbia River and station 38 is the Snake River. If an impact is indicated, sampling will be conducted semiannually per ODCM table 6.3.1-1 (i). There are no species fished commercially in the Hanford Reach of the Columbia I
River. The most recreationally important species in the area are anadromous, which ascend rivers from the ocean for breeding.
Anadromous fish species are normally obtained from hatcheries; Snake River samples are obtained from the Lyons Ferry Fish Hatchery, and Columbia River samples are obtained at the Ringold Fish Hatchery.
(p)      Garden produce is obtained from farms or gardens that use Columbia River water for irrigation. One sample of a root crop, leafy vegetable, and a fruit is typically collected each sample period, when available. EFSEC Resolution 332 further specifies fruit and vegetable sampling from locations potentially impacted by CGS gaseous emissions.
2013 Annual Radiological Environmental Operating Report          4-10                          Energy Northwest/Columbia Generating Station a
 
TABLE 4-2 REMP SAMPLE STATIONS AND REQUIREMENTS STATION            DISTANCE SECTORW            NUMBER"'            MILES"'          ODCM"d'  STATE"'                  OTHER")
N (1)                52                  0.07            DGW      DGW 71(1S)              0.28                                                TLD 47                  0.70                      TLD 57                  0.70            AP/AI 18                1.16              TLD      TLD 53                  7.54              TLD NNE (2)              72(2S)              0.32                                                TLD 2                  1.45              TLD      TLD 54                  6.08              TLD NE (3)                73(3S)              0.54                                                TLD 19                1.74              TLD      TLD 48                  4.59            AP/AI    AP/AI 46                  4.99              TLD MW-9                0.22                                                SGW ENE (4)              74(4S)              0.38                                                TLD 21                  1.45                    TLD, SO                  AP/AI 20                  1.93              TLD      TLD 11                3.16                      TLD 33                  3.44                        SE 45                  4.45              TLD 44                  5.90              TLD 101                0.22                                                SW MW-8                0.26                                                SGW MW-I1              0.10                                                SGW E (5)                75(5S)              0.37                                                .TLD 22                  2.08              TLD 10                3.16              TLD      TLD 26                  3.19            SW, DW      SW 27                  3.19              SW    DIS W 30")                3.5                FI      FI 43                  5.16              TLD 151 (Site 4)      0.83                                                TLD MW-12              0.12                                            .. SGW ESE (6)              76(6S)              0.42                                                TLD 31                  1.06            DGW 32                  1.27            DGW 51                  2.14              TLD 2013 Annual Radiological Environmental Operating Report  4-11    Energy Northwest/Columbia Generating Station
 
I TABLE 4-2 (cont.)
REMP SAMPLE STATIONS AND REQUIREMENTS a
SECTORa STATION NUMBERb' DISTANCE MILES"'          ODCM"'        STATE"'                OTHER"'
I ESE (6)(cont.)        34                3.32              SE              SE 23 8
3.03 4.39          TLD, AP/AI TLD, AP/AI. SO TLD, AP/AI I
42 36 5.85 7.33 TLD MI              MI                                        S 5                  7.72              TLD                                    AP/AI 38(g) 150 (Site 1) 26 0.90 Fl              FI TLD U
SE (7)                77(7S) 24 3
0.57 1.87 2.06 TLD            TLD TLD TLD I
41 40 5.79 6.51 TLD TLD, AP/AI        AP/AI I
MW-14              0.58                                                      SGW SSE (8)                119C 120 0.28 0.32 TLD TLD, SE I
102B 102G 0.50 0.56 SFW GP/VE                i 78(8S)            0.81                                                      TLD 25 55 1.50 6.05 TLD TLD TLD I
I 4                  9.57          TLD, AP/AI      TLD, AP/AI 29                11.57              DW              DW 37 h)                16              GP              GP MW-6 MW-13 0.33 0.52 SGW SGW                &#xa3; S(9)                  119B              0.31                            TLD, SE 102A 79(9S) 0.67 0.76 SFW TLD I
I 1                  1.25              TLD        TLD, AP/AI, SO 6                  7.72              TLD          TLD, AP/AI 65                8.87                                                      TLD SSW (10)              80(10S) 50 0.83 1.26              TLD            TLD TLD 1
56                6.65              TLD MW-3              0.31                                                    SGW I
I 2013 Annual Radiological Environmental Operating Report  4-12            Energy Northwest/Columbia Generating Station I
 
TABLE 4-2 (cont)
REMP SAMPLESTATIONS AND REQUIREMENTS STATION            DISTANCE SECTOR"a            NUMBER'b)            MILES")          ODCM")        STATE"'                OTHER"'
SW (11)              13                  1.26            TLD            TLD 81(11S)            0.74                                                    TLD 103A              0.63                                                    VE goo,                0.62                                                TLD, Al/AP MW-5                0.43                                                    SGW WSW (12)              82(12S)            0.57                                                    TLD 14                  1.26            TLD            TLD 9A                28.35          TLD, AP/AI  TLD, AP/AI, SO 9B                32.82              MI            MI 9C'i)                  32                            GP 890'                0.23                                                TLD, Al/AP 58                  0.44                                                    TLD W (13)                83(13S)            0.52                                                    TLD 15                  1.24            TLD            TLD WNW (14)              84(14S)            0.55                                                    TLD 16                -1.21            TLD            TLD 7                  2.83              TLD      TLD, AP/AI, SO 886,                0.17                                                TLD, AUAP MW-10              0.07                                                    SGW NW (15)              85(15S)            0.43                                                    TLD 49                  1.19            TLD            TLD 870'                0.20                                                TLD, AL/AP NNW (16)              121                0.12                                                    TLD 122                0.31                                                    TLD 123                0.29                                                    TLD 124                0.28                                                    TLD 125                0.28                                                    TLD 126                0.28                                                    TLD 127                0.26                                                    TLD 128                0.25                                                    TLD 129                0.17                                                    TLD 136A              0.29                                                    TLD 137A              0.24                                                    TLD 138A              0.17                                                    TLD 86(16S)            0.31                                                    TLD 17                  1.19            TLD            TLD 12                6.74                            TLD 2013 Annual Radiological Environmental Operating Report  4-13            Energy Northwest/Columbia Generating Station
 
I TABLE 4-2 (cont.)
REMP SAMPLE STATIONS AND REQUIREMENTS                                                              I TABLE 4-2 SAMPLE TYPE KEY I
p AP/AI - Air Particulate/Air Iodine                            DW - Drinking Water Dis W - Discharge Water                                      FI - Fish GP - Garden/Orchard Produce                                  DGW - Deep Ground Water MI - Milk                                                    SE - Sediment SFW - Sanitation Facility Water SW - Surface Water VE - Vegetation SO - Soil TLD - Thermoluminescent Dosimeter SGW - Shallow Ground Water I
I TABLE 4-2 FOOTNOTES:
I (a) The area in the vicinity of CGS is separated into 16 sectors for reporting purposes. The 16 sectors cover 360 degrees in equal 22.5 degree sections, beginning with sector I (N) at 348.75 to 11.25 degrees and continuing clockwise through sector 16 (NNW).                                                                                          I (b) Alternate designations for station are given in parentheses; i.e., TLD Stations 71-86 are also referred to as I S-16S.
(c) Distances are from GPS positions for each location as a radial distance from CGS reactor building.
I (d) ODCM - Offsite Dose Calculation Manual Table 6.3.1-1 requirement.
(e) STATE - State of Washington EFSEC Resolution requirement.                                                                  3 (f) OTHER -Special study stations. TLD Stations: 121 through 129 and 136A through 138A satisfy ISFSI monitoring requirements 10CFR72.44(d)(2). Sampling at MW locations performed to meet NEI 07-07 guidelines and NPDES requirements. Stations 102G and 103A are locations near CGS where vegetation samples have been collected in the past. No samples were collected from these locations in 2013.
I (g) Station 30 is the Columbia River at the vicinity of the plant discharge. Actual distance of fish collection locations from plant are variable, distance listed is approximation. Station 38 is the Snake River. Control resident fish are typically collected at variable locations in area below Ice Harbor Dam, distance listed is approximation. Control I
anadromous fish are typically collected at Lyons Ferry Fish Hatchery.
(h) Fruit and Vegetable indicator samples are typically collected from farms and gardens in the Riverview area of Pasco. Distance listed here is general distance of Riverview area to CGS. Station 37 designation is also used for I
any samples collected in Franklin County that could potentially be affected by CGS liquid or gaseous effluents.
(i)  Station 9C is the designation given for control fruits and vegetables. Distance listed is general distance to the Sunnyside-Grandview area where the majority of the control fruits and vegetables are obtained.
I 0.)  Stations 87-90 were installed at CGS initiative to monitor remediation work at the DOE 618-11 burial ground. No remediation work that affected CGS was performed in 2013 and no air samples were obtained from these locations in 2013. See Section 5.9.6 for further discussion.
I I
I 2013 Annual Radiological Environmental Operating Report    4-14                    Energy Northwest/Columbia Generating Station I
 
TABLE 4-3 2013 FIVE MILE LAND USE CENSUS RESULTS NEAREST                GARDEN~d)
SECTORta)              RESIDENT("                (>5 00 ft)      DAIRY ANIMALS                LIVESTOCK(b'c)
NE                      4.50                      none                    none                      none ENE                      3.88                      none                    none                      4.95 E                    4.64                      none                    none                      4.64 ESE                      4.26                      none                    none                      4.49 SE                    none                      none                    none                      none FOOTNOTES (a)      Within a five-mile radius of the plant, only the five sectors listed above contain activities related to land use census requirements. The other eleven sectors lay fully within the federally owned Hanford Site. Only those sectors containing potential land use census activities are presented here.
(b)      Estimated distances in miles from CGS Reactor Building based on GPS readings. Actual locations are same as identified in previous years, distance values may differ from those reported in past due to updated GPS data.
(c)      25 to 30 beef cattle were identified in a pasture in the ENE sector. The western edge of the pasture is just within the 5 mile radius. Additional feed appears to be provided at this location. 5 cows, 2 calves, 3 horses, and some chickens were observed in a small fenced area near a residence in the E sector. The animals were observed to be fed hay. A single horse was observed in the ESE sector. There is no pasture at this location and the horse appears to be fed hay.
(d)      Though no gardens > 500 fi2 were identified, commercial agriculture is extensively practiced in some parts of the sectors identified in Table 4-3. Agricultural activities observed were primarily apple and soft fruit orchards, corn, alfalfa, and grape vineyards.
2013 Annual Radiological Environmental Operating Report      4-15                  Energy Northwest/Columbia Generating Station
 
TABLE 4-4 I
COMPARISON OF LABORATORY NOMINAL LOWER LIMITS OF DETECTION WITH OFFSITE DOSE CALCULATION MANUAL REQUIREMENTS I
MEDIA (UNITS)                      ANALYSIS ENERGY NORTHWEST LLDs(a)
ODCM REQUIRED LLDs I
Air                          Gross Beta                        0.002                      0.01 (pCi/M3)                        Cs-134 Cs-137 1-131 0.001 0.001 0.03 0.05 0.06 0.07 I
Water:
(pCi/liter)
Gross Beta Tritium Sr-90 2.4 300 1
4 20001b,                I Ni-63 Fe-55 I-131(.c 200 5
1 I
Mn-54                                7                        15 Fe-59 Co-58 Co-60 10 7
7 30 15 15 I
Zn-65 Zr-Nb-95 Cs- 134 10 7
7 30 15 15 I
Cs-137                              7                        18 Soil/Sediment:
(pCi/kg dry)
Ba-La-140 Mn-54 Co-60 10 20 20 15 I
Zn-65 Cs-134 Cs-137 30 20 20 150 180 U
Sr-90                              10 Fish:
(pCi/kg wet)
Mn-54 Fe-59 Co-58 25 100 35 130 260 130 I
Co-60 Zn-65 Cs-134 25 50 30 130 260 130 I
Cs-137                            25                        150 Milk:
(pCi/liter) 1-31 (c)
Cs-134 Cs-137 0.5 7
7 1
15 18 I
Garden Produce:
Ba-La- 140 Sr-90 Cs- 134 10 1
10 15 60 I
(pCi/kg wet)                      Cs-137                              10                        80 1-131                              12                        60
() These are the nominal target LLDs (a priori) for analyses performed in the Energy Northwest Environmental Services Laboratory I
and are based on conservative assumptions. These calculations included corrections for decay during the collection period and delay prior to analysis using factors that are normally encountered for the different media types. Actual LLDs (a posteriori ) may be higher or lower for specific samples.
colIf no drinking water pathway exists, a value of 3,000 pCi/liter may be used.
I
(') This ENW Iodine- 131 LLD achieved by anion resin separation and does not represent a direct analysis of the sample media.
I 2013 Annual Radiological Environmental Operating Report          4-16                      Energy Northwest/Columbia Generating Station
 
0 0                                  05                          1 I
1 L
Miles A
A 72                73 3L-AVZ] "        9    vvA v-v A74 275 83 82 W2        A    119C    A  j W5                      119B          12016 W4                                        0 wf4 77 W-13 0b      ** ..
81 102a A                        A                        A 80                        79                      78 E    Water Sample            Sediment                  Facilities                      N A    TLD                    Security Barrier          DOE Burial Ground
* Air Sample
                          ,    Deep Well              Reactor Building        ISFSI Shallow Well            City Limits              Water FIGURE 4-1 SELECT REMP SAMPLING LOCATIONS WITHIN 0.8 MILES OF CGS 2013 Annual Radiological Environmental Operating Report    4-17                          Energy Northwest/Columbia Generating Station
 
I 0        05          1                          2                    3                    4 1                                                1                    1                    I I      EA Miles      L I  g  I  g  I I
E  ]        I gg  II  Ig                                                                                        COW"*~ law 2            19 A
A 18 17                                                  20 A
49 A                                                                                                A 16                                                                                              11 N-,                    A 15                                                          W&deg;31    L
        \,                                                                                                                    4W27 22 A
102a 5A A
13                                                                                  23 50            0 3
A 25            24
                                                  ~--~-
0      Water Sample                      Sediment                    Facilities                        N A      TLD Security Barrier            DOE Burial Ground Air Sample Deep Well                        Reactor Building
* ISFSI Shallow Well                      City Limits                Water FIGURE 4-2 SELECT REMP SAMPLING LOCATIONS BETWEEN 0.8 AND 2.8 MILES Operating Report            4-18                            Energy Northwest/Columbia Generating Station 2013                    Environmental Operating 2013 Annual Radiological Environmental                Report          4-18                            Energy Northwest/Columbia Generating Station
 
FIGURE 4-3 SELECT REMP SAMPLING LOCATIONS BEYOND 2.8 MILES 2013 Annual Radiological Environmental Operating Report 4-19 Energy Northwest/Columbia Generating Station
 
250 f r -- -    --        ---          --        --        -          .-      - - - - - - - - - -*7                      -r
                              - -0,-. -,_
                                        -------      ST.123 -----------                ST.124----------
                                                                                              ...                ST.125
                                                                                                                      +    -  i Isoltion Fence I                                                                                                  I Security Fence                                                                                            I I~  ~-------------------------------------------------------------------                                                        I Electrical Cntrl Bldg
: tT12 135tIt
        ,ST. 1261                                                                                                                                T.__71
                      +0                                                                          _    _        _
Dry Fuel Cask I                                      I ST.128'                                        0      0T.                                                                                  21 000000000 I              i -I                        I                                        - - - -I
                                                                                                                                      .. L... I,__
ST. 136A                          ST.137A                    ST. 1      .38A I---------------------+----------------------------
Cr
                          + REMP TLD                                                                                                0 FIGURE 4-4 ISFSI TLD STATION LAYOUT 2013 Annual Radiological Environmental Operating Report                                            4-20                      Energy Northwest/Columbia Generating Station
 
5.0 RESULTS AND DISCUSSION 5.0      RESULTS AND DISCUSSION The Columbia Generating Station environmental TLDs were collected by Energy Northwest Environmental Services personnel and analyzed by the Hanford External Dosimetry Program (HEDP) operated by Mission Support Alliance (MSA). All other CGS REMP samples were collected and analyzed by the Energy Northwest Environmental Services Laboratory located in Richland, WA. Table 5-2 provides a summary of the ODCM required REMP sample and CGS groundwater monitoring analysis results in the format specified in Regulatory Guide 4.8. Results for naturally occurring radionuclides that are not related to CGS operations have not been included in the summary table. The lower limits of detection (LLDs) listed in Table 5-2 are the ODCM required detection limits and are not the method detection limits listed in Table 4-4. Analytical results for all REMP samples are presented in Appendix A of this volume and summarize the results in greater detail.
5.1      Direct Radiation Direct radiation is monitored at 79 TLD locations surrounding CGS. TLDs are exchanged on a quarterly frequency at all locations. The 16 locations designated as "S"stations are located between 0.3 and 0.8 miles from the CGS reactor building and all are inside the property boundary, see Figure 4-1 for station locations. Figure 5-1 shows the 2013 "S"station mean quarterly TLD results separated into 16 geographical sectors around the plant. Figure 5-1 also shows the pre-operational mean and the high, low, and mean results in each sector for the 1984 - 2012 operational period for comparison. The 2013 "S" station TLD results were lower than the pre-operational mean in 11 of the 16 sectors and lower than the operational mean in 13 of the 16 sectors. TLD results from the N, NNE, and NNW sectors are slightly higher than the other "S" station locations as a result of being physically closer to the ISFSI and the CGS turbine building. Excluding the NNW sector, the average deviation relative to the pre-operational period was -1.40%; in 2012 the average deviation was -1.65%. The NNW sector is the closest "S" station to the ISFSI and the higher result here is attributed to the stations close proximity to this facility.
0.36                                                S-Stations 0.33 0.30
  >,  0.27 of  0.24 0.21 0.18 0.15 N NNE NE ENE                  E ESE SE SSE          S  SSW SWWSW W WNWNW NNW o  Pre-Operational Mean      -&  2013 Mean    -  1984-2012 High/Low/Mean Figure 5-1 "S" Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean by Sector Operating Report      5-1                      Energy Northwest/Columbia Generating Station 2013 2013 Annual Radiological Environmental Annual Radiological Environmental Operating Report      5-1                      Energy Northwest/Columbia Generating Station
 
U The 19 locations designated as near plant stations are located at distances between 0.9 and 2.1 miles from the CGS reactor building, see Figure 4-2 for station locations. Figure 5-2 shows the exposure rates for the near plant TLD locations separated into sixteen geographical sectors around the plant.
Figure 5-2 also shows the pre-operational mean and the high, low, and mean results in each sector for I
the 1984-2012 operational period for comparison. The 2013 near plant TLD results were lower than the pre-operational mean in 12 of the 16 sectors and less than or equal to the operational mean in 14 of the 16 sectors. The average deviation relative to the pre-operational period was -1.7%, in 2012 the average I
deviation was -3.2%.
I 0.36                                            Near Plant Stations 0.33 I
  >1 0.30 0.27 I
E 0.24                                                                                                                          I 0.21 0.18                                                                                                                          I 0.15 N    NNE NE ENE o
E Pre-Operational Mean ESE SE        SSE
                                                        ---- 2013 Mean S
SSW SWWSW W WNWNW NNW 1984-2012 HiglVLow/Mean I
Figure 5-2 Near Plant Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean by Sector I
0.36 Remote Stations Remote Stations I
0.33                                                                                                                          I 0.29 0.26 I
E 0.22                                                                                                                          I 0.19 0.15 I
N      NNE      NE      ENE        E    ,ESE    SE    SSE    S    SSW WSW WNW NNW 0 Pre Operational Mean              -  1984-2012 HighlLow/Mean          6 2013 Mean                      I Figure 5-3 Remote Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean By Sector I
2013 Annual Radiological Environmental Operating Report        5-2                      Energy Northwest/Columbia Generating Station I
 
The 22 TLD locations designated as remote locations are located between 2.83 and 28.35 miles from the CGS reactor building; see Figure 4-3 for station locations. Figure 5-3 shows the exposure rates for the remote TLD locations separated into geographical sectors around the plant. Figure 5-3 also shows the pre-operational mean and the high, low, and mean results by sector for the 1984-2012 operational period for comparison. The 2013 remote TLD results were lower than the pre-operational mean in 9 of the 13 sectors and lower than the operational mean in 11 of 13 sectors. Station 46 in the Wahluke Reserve (NE sector) remained the remote location with the highest exposure rate. This has been the case since the pre-operational measurement phase and is attributed to differences in the underlying rock and soil composition in this area. The 2013 average deviation relative to the pre-operational period was -3.7%; the average deviation in 2012 was -3.5%.
Offsite direct radiation monitoring results are consistent with previous years. The 2013 results indicate no observable dose contributions due to plant operations at locations outside the CGS controlled area. Dose contributions inside the CGS controlled area are limited to those locations known to be influenced by the Independent Spent Fuel Storage Installation (ISFSI) and/or radiation from the turbine building during operation. Environmental radiation exposure rates for 2013, the pre-operational period, and the long term operational period are summarized in Tables 5-3. See also Appendix A, Tables A-1.1 and B-1.1 for the 2013 quarterly TLD results. TLD results for special interest locations are discussed in further detail in Section 5.9.        "
5.2      Airborne Particulate/Iodine Air samples are collected weekly from 11 sample stations located around CGS. Additionally, an air sample station located 28 miles WSW of CGS is used as a control for comparison. Air particulate filters are analyzed for gross beta and iodine cartridges for radioiodines on a weekly basis. Air filters are also composited and analyzed for gamma emitting nuclides quarterly.
The 2013 mean weekly particulate filter gross beta results for the five stations located within three miles of CGS are plotted in Figure 5-4 (See also Appendix A, Tables A-2.1, A-2.2). Results for these near plant stations are similar to results from the remote locations and closely follow the trend of the control location.
Figure 5-5 is a plot of the 2013 mean weekly particulate filter gross beta results for the 6 sample stations located between 3 and 9.6 miles from CGS (See also Appendix A, Tables A-2. 1, A-2.2). Results for these remote stations are similar to results from the near plant stations and closely follow the trend of the control location. No correlation between air gross beta activity and proximity to CGS was observed.
For both near and remote air station locations, higher results and greater variability in air gross beta activity have historically been observed during fall and winter months due to weather induced background fluctuations. Gross beta levels typically increase during periods of inversion due to natural decay products being frapped near the earth surface. Gross beta results plotted over a period of several years typically show a cyclical pattern with higher results observed in the fall and winter compared to the spring and summer. Gross beta results above the normal trend range were observed in January, October, November, and December. The increases were observed at all sample locations including the control and are attributed to weather phenomena and not the result of CGS operation. The results for weeks 48-50 were among the highest gross beta air results observed by the CGS REMP. Weather conditions for this period were typical. of an inversion with below normal temperatures, overcast skies, and little to no winds. The smaller spike observed in week 43 occurred during a period when fog and blowing dust was noted.
2013 Annual Radiological Environmental Operating Report 5-3                Energy Northwest/Columbia Generating Station
 
I The quarterly particulate filter gamma isotopic results identified the presence of only naturally occurring I
radionuclides (See Appendix A, Tables A-3.1, A-3.2). Beryllium -7 was positively identified in all samples at both the indicator and control locations.
I Near Plant Stations 0.14                              Data from 1986 weeks 19-23 not included due to Chernobyl                                      I 0.12 I
0.10 E 0.08                                                                                                                            I
: a. 0.06 0.04                                                                                                                            I 0.02                011TTITTITTT~kd.
0.00  '--
1    3    5  7    9  11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 I
WEEK
                    -  HIGH/LOW/MEAN 1985-2012                    A-MEAN 2013            -<)-Control 2012 I
Figure 5-4 1985-2012 Weekly Hi/Low/Mean and 2013 Weekly Mean Gross Beta in Air - Near Plant Stations I
Remote Stations 0.14                                                                                                                            I 0.12 0.10                                                                                                                            I 0.08 0-0.06                                                                                                                            I 0.04 0.02 I
0.00                                            .....*..                          -.
WEEK      1 3
5  7  9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 HIGH/LOW/MEAN 1985-2012                  -A-  MEAN 2013            -Control 2012                        I Figure 5-5 1985-2012 Weekly Hi/Low/Mean and 2013 Weekly Mean Gross Beta in Air - Remote Stations I
The 2013 weekly iodine cartridge isotopic results showed no indication of radioiodines in any of the samples. Results for iodine- 131 were in all cases below the lower limit of detection. (See Appendix A, Tables A-4. 1,A-4.2).
I I
5-4 I
2013 Annual Radiological Environmental Operating Report                                  Energy Northwest/Columbia Generating Station
 
The 2013 air particulate and iodine sample results show no evidence of measurable environmental radiological air quality impact that can be attributed to CGS plant operation.
5.3        Water 5.3.1      Surface Water Composite water samples are collected from 6 surface water locations monthly and analyzed for tritium, gross beta, and gamma emitters. A plot of the 2013 gross beta results for the plant intake, plant discharge, and river/drinking water stations are shown in Figure 5-6.
Gross Beta in Water 2013 14.0 12.0t 10.0 8.0
      =6.0 CL 40
        -2.0 0.0
        -2.0 1        2          3        4          5    6        7        8        9        10      11        12 Month o    Station 26    ---o-  Staion 27              Stan 29 S
Figure 5-6 Gross Beta in River/Drinking ( Stations 26 & 29) and Plant Discharge Water (Station 27) for2013 All drinking and river water (Stations 26 and 29) gross beta results were below the analysis detection limits (See Appendix A, Tables A-5. 1, A-5.2). Gross beta levels in the plant discharge water (Station 27) were above the detection limits in ten of the twelve samples. Positive results for this location are expected due to the scrubbing action of the cooling towers which incorporates atmospheric particulate material into the discharge water and the concentration of natural radioactivity in the water by evaporative loss. Historically, higher gross beta results at Station 27 have been observed during periods when CGS circulating water was maintained at higher levels of concentration. The lower gross beta values for Station 27 during the summer months corresponds to a time period during and immediately after an outage. The Station 27 sample results are representative of the radioactivity present in plant discharge water before any mixing with river water occurs.
Monthly tritium results for all plant intake, plant discharge, and river/drinking water samples were below the analysis method a prioriLLD except for one plant discharge water sample. Tritium results for the three sample locations are plotted in Figure 5-7, quarterly averages for the locations are listed in Appendix A, Tables A-6. 1, A-6.2. The cause of the positive tritium activity in the March plant discharge water sample could not be identified; it is suspected that the activity was from recapture of CGS effluent tritium in the cooling water system.
2013 Annual Radiological Environmental Operating Report      5-5                          Energy Northwest/Columbia Generating Station
 
U Gamma spectroscopy results for all plant intake, plant discharge, and river/drinking samples showed no I
indication of gamma-emitting radionuclides of interest being present (See Appendix A, Tables A-7. 1, A-7.2).
I 600 500 Tritium in Water 2013 3
400 300 I
S200 I
0
      -100 I
1        2        3        4        5        6        7        8        9        10      11        12 Month
            --o-  Station 26        ---    Station 27          a  Station 29        -      Tritium LLD (300 pQiA)          I Figure 5-7 Tritium in River/Drinking ( Stations 26 & 29) and Plant Discharge Water (Station 27) for 2013 I
Analysis results for the plant intake, plant discharge, and river/drinking water samples showed only negligible impact to the environment due to CGS plant operations in 2013. Composite water samples are                            I also taken from two sanitary waste sample locations and one storm drain location. Analysis results for these samples are discussed in further detail in Section 5.9.
I 5.3.2    Ground Water Samples from 3 deep wells were collected quarterly to meet ODCM and EFSEC Resolution No. 332(9) requirements. Quarterly samples were also collected from ten shallow groundwater monitoring wells I
located near CGS as part of the CGS groundwater monitoring program. All well samples were analyzed for tritium and gamma emitting radionuclides. Well locations sampled are shown in Figures 4-1 and 4-2.                          U Analytical results for the three deep water wells were consistent with results seen in previous years.
Tritium results were below detection limits and no gamma emitting radionuclides related to CGS operation were identified in any of the samples (See Appendix A, Tables A-6.1, A-6.2, A-7.1, and A-I 7.2).
The CGS ground water monitoring program is conducted to meet the Nuclear Energy Institute (NEI)
I Groundwater Protection Initiative (NEI 07-07) (17)guidelines and to support NPDES requirements.
Ten shallow wells are routinely used to sample water from the unconfined aquifer around the CGS site. None of these monitoring wells are used as a source of drinking water. CGS is unique in the I
commercial nuclear power industry in that it is located in an area where the unconfined aquifer under the site is known to be contaminated with tritium as a result of past DOE activities on the Hanford Site.(19) The CGS groundwater program is intended to assess any contribution CGS may be making to I
the known groundwater contamination issue.
I 5-6                  Energy Northwest/Columbia Generating Station I
2013 Annual Radiological Environmental Operating Report
 
Gamma Spectroscopy results for the ten shallow monitoring wells did not identify any gamma emitting radionuclides of interest(See Appendix A, Tables B- 10.1, and B- 10.2). Tritium concentrations at these locations ranged from < LLD to 15,400 pCi/liter (See Appendix A, Table B-11.1). Tritium results from each well were consistent during the year and within the trend range observed in previous years. The highest tritium concentrations were consistently measured at MW-5 which is hydraulically up-gradient of CGS. No samples were obtained from MW-7 in 2013 due to lack of water in the well. In 2011, ENW identified a possible correlation between tritium levels at the CGS storm drain pond and tritium levels at two nearby well locations (MW-7 and MW-8). Tritium results for 2013 showed a similar trend. Tritium activity in the storm drain pond is attributed to recapture of CGS effluents, see section 5.9.1 for more discussion. No other correlations between groundwater tritium and CGS operation weire identified. With the exception of the MW-8 tritium.
results, there is no evidence that CGS operation made a measurable radiological impact on groundwater.
5.4      Soil Gamma spectroscopy analysis was performed on soil samples from 5 different locations in 2013 (See Appendix A, Tables A-8. 1, A-8.2). Two of the samples were from locations near CGS, two were from locations east of CGS in Franklin County, and one was from a control location. Naturally occurring radionuclides (potassium- 40 and bismuth- 214) were identified in all samples. Cesium-137 was identified in one of the samples near CGS. The level of cesium-137 identified was within the range historically observed in local soil samples and within the range considered normal background in Hanford area soils.(20' 21,22) The cesium-137 level was well below the level that would require strontium-90 analysis to be performedi 91 The soil sample results indicate no measurable impact from CGS plant operation.
5.5      River Sediment Gamma spectroscopy results of river sediment identified naturally occurring radionuclides (potassium-40, bismuth- 214) and cesium-137 (See Appendix A, Tables A-9.1, 9.2). Relative to the circulating water discharge point, cesium-137 was detected in one of the upstream samples (Station 33) and both of the downstream samples (Station 34). The downstream cesium- 137 activity levels were similar to the levels identified in previous years and within the range known to be present in Hanford area sediment and soil.(21) Cesium-137 was not identified in any samples of plant cooling water discharged to the Columbia River. CGS has not made a radioactive discharge to the Columbia River since 1998. The sediment sample results indicate no measurable impact from CGS plant operation.
5.6        Fish The gamma spectroscopy results of fish samples identified low level cesium -137 in the anadromous fish collected from the Columbia River. The level identified was just above the analysis detection limit and substantially below the ODCM specified lower level of detection. Cesium -137 is occasionally identified in this media and has been identified at low levels in Columbia River fish by the CGS REMP and in other studies (23) in past years. The cesium -137 is not believed to represent an impact from CGS operation. Results of the other fish samples collected in 2013 identified only the presence of naturally occurring radionuclides (See Appendix A, Tables A-10.1, 10.2). Only two of the three ODCM required fish species were collected from both the control and indicator locations in 2013, see section 5.10 for further discussion.
2013 Annual Radiological Environmental Operating Report 5-7                Energy Northwest/Columbia Generating Station
 
I 5.7      Milk                                                          .  -    .                            I No radioiodine activity was identified in any of the milk samples collected in 2013 (See Appendix A, Tables A- 11.1, A- 11.2). Gamma spectroscopy results of milk radionuclides other than radioiodine did not identify the presence of any radionuclides of interest. (See Appendix A, Tables A- 12.19 A- 12.2).
Naturally occurring potassium-40 was identified in all milk samples.
5.8      Garden Produce Garnma analysis was performed on ten different types of fruits and vegetables in 2013 (See Appendix A, Tables A-15.1, A-15.2, A-16.1, A-16.2, A-17.1, A-17.2). No radionuclides of interest were identified in any of the samples. Naturally occurring potassium-40 was identified in all samples.
5.9      Special Interest Stations                                                                          i Sampling and analysis is performed at the locations covered in this section to comply with EFSEC requirements or is performed at CGS initiative. The storm drain pond and the Sanitary Waste Treatment Facility (SWTF) were incorporated into the routine sampling schedule in 1992. In 1995, the cooling tower sediment disposal area was added. TLDs were placed around the spray pond drain field (Station 120) in June 1995. TLD monitoring in the vicinity of the planned Independent Spent Fuel Storage              I Installation (ISFSI) was first performed in 1998 to collect background data and TLD monitoring was established on the ISFSI fence line after construction was completed in 2002. Additional air monitoring and TLDs stations were established in 2008/2009 to monitor remediation work at the DOE 618-11 burial ground west of CGS. Discussions of the results from each of the locations are given in the following I
sections.                                                                                                    i 5.9.1    Storm Drain Pond (Station 101)
The storm drain pond (NPDES Outfall 002) is located approximately 1500 feet northeast of CGS.                i Water is sent to the pond through an 18-inch diameter pipe that discharges into a 300-foot long earthen channel that leads to a 100-foot diameter pond. The pond is a shallow, unlined percolation/evaporation basin. Water at the storm drain outfall is sampled using a flow proportional automatic sampler to collect monthly composite samples. The storm drain pond area is fenced and access is restricted.
Monthly water samples were analyzed for gamma emitting radionuclides, tritium, and gross beta.
Gamma spectroscopy results did not identify the presence of any gamma emitting radionuclides of interest (See Appendix A, Tables B-2.1, B-2.2). Gross beta was not positively identified in any of the monthly samples (See Appendix A, Tables B-3.1, B-3.2). Tritium was detected in eight of the twelve samples (See Appendix A, Tables B-4. 1, B-4.2). The samples with higher tritium levels were all from colder, wetter months which is consistentwith results seen in previous years. The source of the tritium in storm drain pond water is attributed to recapture of tritium from CGS gaseous effluents which is more likely to occur during cooler, rainier periods.
Four soil samples were collected from the CGS storm drain pond in 2013 and analyzed for gamma emitting radionuclides. The samples were collected from surface soil locations that were identified as having higher levels of activity in a 2011 storm drain pond soil characterization study. (24) Analysis of the 2013 samples identified many of the same radionuclides identified in the 2011 study but at levels generally lower than observed in 2011 (See Appendix A, Tables B- 12.1).
2013 Annual Radiological Environmental Operating Report 5-8      Energy NorthwestlColumbia Generating Station 3
I
 
5.9.2    Sanitary Waste Treatment Facility (Station 102)
The Sanitary Waste Treatment Facility (SWTF) is located approximately 0.5 miles south-southeast of the CGS. The facility processes sanitary: waste water from CGS, the ENW Industrial Development Complex (formerly referred to as WNP- I and WNP-4), the Kootenai Building, and the DOE 400 Area. Station 102B receives water from all these locations; Station 102A receives water only from the DOE 400 Area.
Discharge standards and monitoring requirements for the SWTF are established in EFSEC Resolution No. 300.(16)
Gross beta results for Station' 102B (SWTF head works) were consistent with results seen in previous years. Gross beta results for Station 102A (DOE 400 Area effluent ) showed an increase over the course of the year rising from a level of less than 10 pCi/l in'the first half of the year to greater than 20 pCi/l in November and December. The increase is attributed to changes in the waste stream composition coming from the DOE 400 area and corresponds to decreasing discharge volumes from that facility. The sanitary sewer line from the DOE 400 area was plugged in mid-December 2013 and ENW is no longer accepting sanitary waste from this location. Gross alpha was not positively identified in any of the 102A or 102B samples. (See Appendix A, Tables B-5.1, B-5.2, B-6.1, B-6.2).
Gamma spectroscopy results of the monthly SWTF water samples identified iodine- 131 in the January Station 102B composite sample. CR 278601 was written to document the finding. As no additional radioisotopes were identified in the sample, the source of the radioiodine was attributed to a medically administered treatment and not the result of CGS operation. No other gamma emitting radionuclides of interest were detected in any of the other SWTF samples analyzed in' 2013 (See Appendix A, Tables B-7.1, B-7.2).
Tritium activity was identified in all twelve 102A and five of the twelve 102B samples (See Appendix A, Tables B-8. 1, B-8.2). Tritium levels in the 102A samples were similar to the levels seen in previous years. The potable water used at the DOE 400 area is obtained from a groundwater well that is known to be contaminated with tritium as a result of past DOE activities on the Hanford site.(17)
Tritium concentrations in the 102B sampleswere no more than 2 times the LLD of the analysis.
Tritium activity in the station 102B samples is attributed to DOE 400 area discharges; 102B tritium values trending below the LLD during the second half of the year correspond to smaller discharge volumes from the DOE 400 area. Tritium levels in all sanitary waste samples remained well below the 20,000 pCi/liter action limits of EFSEC Resolution No. 300.16)
SWTF water from stabilization pond B was discharged to ground in March 2013. Grab samples were taken at CGS initiative during discharge and used to create a composite sample that was analyzed for gamma isotopic and tritium content. Gamma isotopic analyses of the composite sample did not identify any radioisotopes related to CGS operation. Tritium activity of the composite sample was determined to be 529 pCi/l. A total of 1.4 million gallons of SWTF water was discharged to ground in March 2013.
Report 5-9              Energy Northwest/Columbia Generating Station 2013 Annual 2013                    Environmental Operating Radiological Environmental Annual Radiological              Operating Report 5-9              Energy Northwest/Colunibia Generating Station
 
I 5.9.3    Cooling System Sediment Disposal Area (Station 119)
EFSEC Resolution No. 299(18) authorizes the onsite disposal of asdime nts from plant cooling systems I
containing low levels of radionuclides. The disposal area for these sediments is located just south of the CGS cooling towers. EFSEC Resolution No. 299( 8)requires direct radiation monitoring using quarterly TLDs in the vicinity of the disposal cells and the collection and analysis of a dry composite sediment I
sample from the disposal cell within thirty days following each cleaning to confirm that the disposal criteria outlined in the resolution have not been exceeded.                                                                          I Cleaning of the CGS cooling towers was performed in May and October 2013. Disposal of the material removed resulted in an estimated 51.5 cubic meters of dry sediment being placed in the disposal cell.
Figure 5-8 summarizes theestimated mass and radionuclide content of cooling tower sediment that was I
placed in the disposal area in 2013. For those isotopes listed in the table that were not positively identified, the MDA value obtained from the sample analysis was used in the table calculations. As such, the total activity reported is a conservative estimate.
I In addition to cooling tower sediment, ENW performed cleaning operations of the Standby Service Water (SSW) ponds in 2013. Material removed from the SSW ponds was temporarily Stored in bags in a lined basin south of the SSW ponds. Initial characterization of the material identified cobalt -60 in the I
400-3000 pCi /kg range. Transfer of the SSW sediment to the established cooling system disposal area was initiated in December 2013 and completed in January 2014. Final determination of the volume, density and radionuclide content of this material will be reported in the 2014 annual report.
I Figure 5-8 shows that the cooling tower sediment results were well below the disposal concentration limits specified in EFSEC Resolution No. 299."1" Cesium -137 levels identified in 2013 were similar to I
levels identified in previous years and within the range normally seen in Hanford area soils. Positive identification of cobalt -60 has been made in this media in past years and at level similar to those shown in Figure 5-8.                                                                                                                        I I
2013 Cooling System Sediment Disposal Data Disposal Date        May 2013          October 2013 I
Pit ID:          2007 Pit            2007 Pit Mass, kg Density, g/cc
                                                              ;39,720' 0.8.1 1,725 0.81 I
Analytical          Analytical Nuclide          Limit (pCi/kg)
Result (pCi/kg).
Result (p~i/g)            Total Curies I
Co-60              5.OOE+03          < 3.66E+01            2.79E+02              1.94E-06 Mn-54 Zn-65 3.OOE+04 5.00E+04
                                                            < 3.40E+01
                                                            <7.62E+01
                                                                                <5.07E+01
                                                                                < 9.14E+01
                                                                                                      < 1.4"4E7-06
                                                                                                      < 3.18E-06.
I Cs-134 Cs-137 1.00E+04 2.00E+04
                                                            <3.56E+01 1.91E+02
                                                                                < 5.99E+01 2.91E+02
                                                                                                      <1.52E-06 8.09E-06                      I 1.62E-05 Figure 5-8 Cooling System Sediment Activity Levels For Disposals Made In 2013                            I 2013 Annual Radiological Environmental Operating Report    5-10                          Energy Northwest/Columbia Generating Station K
 
Measurements of direct radiation at the disposal pit area was taken using TLDs. Two locations were used, an indicator location next to the collection area (Station 1199B) and a control location approximately 100 yards to the east (Station 119C). The mean quarterly TLD results agree well with results from previous operational years. The negligible difference between the indicator and the control TLDs indicate that there was no measureable dose contribution above background due to material in the disposal cells.
(See Tables 5.3 and Appendix A, Tables B-1.1).
5.9.4 Spray Pond Drain Field (Station 120)
There were no discharges to the Spray Pond Drain Field (NPDES Outfall 003) in 2013. The TLD results at Station 120 in 2013 are in agreement with those seen in previous operational years (See Table 5-3 and Appendix A, Tables B- 1.1).
5.9.5 Independent Spent Fuel Storage Installation The Independent Spent Fuel Storage Installation (ISFSI) is a fenced, secured area north northwest of CGS. Ten TLD stations, stations 123-129 and stations 136A-138A, are located on the second of three security fences that surround the ISFSI. TLD station 122 is just north of the ISFSI between the ISFSI and the plant access road. TLD station 121 is located approximately 0.1 mile north of the plant between the Transformer Yard and the ISFSI. Refer to Figure 4-4 for ISFSI TLD locations.
Radiological exposure rates inside the ISFSI security fence line are elevated and access to the area requires radiological dosimetry and security notification. In addition to the TLD monitoring program, quarterly radiological surveys of the ISFSI are conducted by the CGS Radiation Protection Department.
Trend of Exposure Rates at ISFSI Fence Line 2.6 2.2 E 1.4-1.0_
            '07 'QO '07&#xfd;    9? 'Q ?'QO 7 9O V7 'QO 'Q''QO V7~ '9? V'QO 'Q' '9? V'Q 'Q?'0                      '9? IQ'PO a-125 --- 126 --              127 ..      128 --  o-129 -+/-:136A -          137A -138A          -o-123      &124 Figure 5-9 ISFSI TLD Trend at CGS 2013 Annual Radiological Environmental Operating Report      5-11                      Energy Northwest/Columbia Generating Station
 
I No new spent fuel or additional storage casks. were added to::the ISFSI during 2013. As shown in                          I Figure 5-9, exposure rates at the ISFSI fence line have followed a downward trend since 2008.
Station 122 TLD results show a similar pattern with the long term trend for this location correlating to the overall ISFSI TLD trend but at a lower level. Station 12 1 TLD trend results show large                            I decreases during periods when CGS was shut down; this location has historically been influenced more by. turbine building radiation levels than by the ISFSI (See Table 5-3 and Appendix A, Tables B-
: 1. 1, 13-1.2).                                                                                                            I 5.9.6 Additional Air Sample and TLD Locations Four air sample locations (Stations 87-90) and 5 TLD stations (Stations 58, 87-90) were established in I
2008/2009 in order to monitor air quality and direct radiation during remediation work at the DOE 618-11 burial ground located just west of CGS (See Figure 4-1). No air samples were taken from these locations in 2013 as no work was performed at the 618-11 site that had the potential of impacting CGS.
I Quarterly TLDs were exchanged at all five locations in 2013. Three of the TLD stations (stations 87-89) had results higher than background due to the stations close proximity to the turbine building (See Appendix A, Table B- 1.1).
I 5.10      2013 Sample Deviations                                                                                          I A summary of REMP sample deviations encountered during 2013 is listed below in Table 5-1 a. All known deviations from the sampling schedule (i.e. sample was not obtained) or analyses where the ODCM specified lower limit of detection was not achieved are included. For locations where composite I
or continuous samples are collected, any known period greater than 24 hours during which samples were not collected have been included. Not all locations listed in Table 5-1a are required by the ODCM or EFSEC resolutions. Table 5-lb lists information regarding air sample station sampling requirements.
I TABLE 5-1a I
SAMPLE              DATE        LOCATION REMP Sample Deviations for 2013 CR ID                  PROBLEM / COMMENTS I
MEDIA Air Sampler 4/3/13 to 4/9/13        Station 1
[Pump found off with blown fuse, station OOS for- 6 282272 days. Station returned to service after pump replaced.
I INo sample collected, LLD requirements not met.
Air Sampler 5/29/13 to 5/30/13 Station 57 Station OOS for - 25 hours due to power outage.
286627 Station back in service when power restored. Sufficient sample volume obtained to meet LLD.
I Air Sampler 7/14/13 to 7/16/13 Station 48 Pump found off with blown fuse, Station OOS for - 41 290058 hours. Fuse replaced, pump restarted. Sufficient sample volume obtained to meet LLD.
I 8/19/13                                  Station OOS for -9.5 days due to power outage. No Air Sampler              to 8/28/13 Station 23      292376 sample collected or LLD meet week of 8/20 to 8/27.
Station back in service after power restored.
I I
5 2013 Annual Radiological Environmental Operating Report    5-12              Energy Northwest/Columbia Generating Station I
 
TABLE 5-1a (cont)
REMP Sample Deviations for 2013 SAMPLE              DATE        LOCATION            CR ID                    PROBLEM / COMMENTS MEDIA 1/14/.13                                    Composite sampler OOS for - 24 hours during planned Water                to        Station 29        277478 maintenance activities. Sampler returned to service and 1/15/13                                    1verified operable.
Circ water blow down samplers CBD-SR- 1 and 2 inoperable due to no signal from CW-LCV-1, blow 284853      down performed using temporary pumps. Daily grab 5/13/13                          285305      samples taken 5/20 to 5/25. CBD-SR-1 and 2 declared Water                to        Station 27        285021      operational 5/25 following logic circuit modification.
5/31/13                          286652      On 5/31, samplers determined not to be functional due to no valid flow indication signal and samplers -in proportional mode. Samplers placed in timed mode and verified operable on 5/31.
On 7/8, TMU-SR-1 determined to have been OOS since 6/30 when sample supply pump was taken out of.
288978      service. Daily grab samples taken 7/10 to 7/15. A 6/30/13                          289504      temporary sampler was installed on 7/12 and Water                to        Station 26        291368      continuous composite sampling initiated. Temporary 7/12/13                          294453      composite sampler in service until 1'2/9/13. TMU-SR-1 297177      returned to service on 12/7/13 following adjustments to samplesupply pump. Procedure revised to identify PWC-P-5 supplies water to TMU-SR- 1.
9/2/13                                      In service Circ. water blow down sampler CBD-SR-1 WaterWtrto 921            Statdeclared                            non-functional on 9/3. CBD-SR-2 placed in Station 27        293107 service and verified operational. Samplers estimated to 9/3/13                                      have been OOS for 30 hours..
9/29/13                            LCO        Circ water blow down samplers CBD-SR-1 and 2 Water            1Wtro9to        Station 227 St                  LCO      declared non-functional due to planned power outage.
10/3/13 Log 16673      Samplers returned to service and verified operable when power restored. Sample racks OOS for 74 hours.
TMU temporary composite water sampler found 11/20/13                                      without power on 11/25, sampler last confirmed Water                to        Station 26        298462 operational on 11/20. Investigation found GF1C circuit 11/26/13                                      was tripped. Power restored and sampler verified
                                                                    -operable.
Only 2 of the 3 required fish species were obtained Stations 30                  from the control and indicator locations. ENW was not Fish              Annual                          300634 permitted to use electroshock fishing techniques in and 38                      2013. Permission to electroshock or other means of fish collection is to be investigated. .
7/1/13            All                      Environmental TLDs were exchanged 2 weeks late due TLD                  to            ll            289107 to issue obtaining TLDs from vendor. Contract issues 7/17/13        Locations            .      causing delay resolved.
2013 Annual Radiological Environmental Operating Report        5-13                        Energy Northwest/Columbia Generating Station
 
I Table 5-lb below shows the percent time in service for the 12 air sample locations. The table shows I
that overall availability was greater than 99% for all ODCM required locations.
I TABLE 5-1b CGS REMP Air Sample Percent in Service Time for 2013                                    I Station ID          ODCM Required                    EFSEC Required  Percent Time in Service 1
4                        x x
x 98.2%
99.8%                          I 5                                                                          99.8%
6 7
x x
99.9%
99.8%
I 8                        x                            x                    99.9%
9 21 x                            x                    99.9%
99.7%
I 23                                                      x                    97.2%
40 48 x
x x
x 99.8%
99.2%
I 57                        x                                                  99.6%
I I
I I
U i
I i
I i
2013 Annual Radiological Environmental Operating Report    5-14 I
Energy Northwest/Columbia Generating Station


3.1 Site Description The Columbia Generating Station (CGS) is a 1230 MWe commercial nuclear power plant that achieved initial criticality on January 19, 1984. The plant is located in a sparsely populated shrub-steppe region within the Department of Energy (DOE) Hanford Site in southeastern Washington.
TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
The plant is approximately three miles west of the Columbia River and is surrounded on all sides by uninhabited desert land. The nearest large population centers are Richland, Pasco and Kennewick, which are 12 miles south, 18 miles southeast, and 21 miles southeast, respectively.
The nearest privately owned lands are located approximately four miles east-northeast of the plant, across the Columbia River. The site has a bimodal wind pattern with winds primarily from the northwest and south. (1) The primary region of focus for REMP sampling is the farming region east of the plant.Naturally occurring radionuclides exist in detectable quantities throughout the world and are seen in many of the samples collected for the REMP. Some examples of naturally occurring radionuclides that are frequently seen in samples are potassium-40, beryllium-7, actinium-228 (present as a decay product of radium-228), and radium-226.
Additionally, some relatively long lived anthropogenic radioisotopes, such as strontium-90 and cesium-137, are also seen in some REMP samples; these radionuclides exist in measurable quantities throughout the world as a result of fallout from atmospheric nuclear weapons testing.1 2' 3)Due to the location of CGS on the Hanford Site, there are other sources of reactor produced radionuclides in close proximity to the plant. CGS is unique in the U.S. commercial nuclear power industry in this respect. Hanford related radionuclides, most notably tritium, are identified in some CGS REMP samples. Though the presence of these radionuclides in the vicinity of CGS are not necessarily reflective of CGS activity, changes in the levels of these radionuclides are monitored to assess any contribution that CGS may be making to the established background.
The DOE has an active REMP program for the Hanford Site that overlaps the CGS REMP.3.2 Program Background The CGS REMP is designed to conform to the Nuclear Regulatory Commission (NRC) Regulatory Guides 4.1,4) 4.8,(5) and the Radiological Assessment Branch Technical Position.6 1 In addition, the REMP also meets the requirements of 10 CFR 72.44(d)(2) for coverage of the ISFSI.The quality assurance aspects of the sampling program and the thermoluminescent dosimetry are conducted in accordance with Regulatory Guides 4.15(71 and 4.13.(8) The REMP also adheres to the requirements of the Washington Energy Facility Site Evaluation Council,(9) the Columbia Generating Station Technical Specifications,(1 0.) and the Offsite Dose Calculation Manual" 1 1) These requirements cover the environmental sampling and sample analysis aspects of the program, and also the reporting and quality assurance requirements.
2013 Annual Radiological Environmental Operating Report 3-1 Energy Northwest/Columbia Generating Station The preoperational phase of the program, which lasted from March 1978 until initial criticality in January 1984, provided a baseline of background environmental data. Variability in the background levels of radioactivity over time is due to differences in geologic composition, meteorological conditions, decay of nuclear testing fallout material in the environment, and seasonal changes.Variability in results may also have been introduced by changing analytical contractors and the use of different correction factors over the years.The Energy Northwest Environmental Services Laboratory performed all routine REMP sampling and analyses in 2013. Thermoluminescent dosimeters (TLDs) used in the REMP were processed by the Hanford External Dosimetry Program (HEDP) operated by Mission Support Alliance (MSA).In addition to evaluating the environmental concentrations against regulatory limits, the REMP may also compare results to state standards.
1 12. 13) The results may also be evaluated by comparing them to similar measurements made during the preoperational and previous operational periods and to the detection capabilities associated with the current methods of analysis.3.3 Program Objectives The REMP provides an independent mechanism for determining the levels of radioactivity in the plant environs in order to empirically quantify and qualify any radiological effect plant operation may be making on the environment.
The program serves to ensure that any accumulation of radionuclides in the environment resulting from station operation will be identified promptly and before they become significant or exceed established limits.While in-plant monitoring programs are used to ensure that 10 CFR 20(14) and 10 CFR 50(15) criteria for releases of radioactive effluents are met, the REMP further verifies that the measured concentrations of radioactive material and levels of radiation observed in the environment are not higher than expected based on CGS effluent measurements and modeling of the exposure pathways.1 I I I U I I I I I I I I I I I I I I 2013 Annual Radiological Environmental Operating Report 3-2 Energy Northwest/Columbia Generating Station 4.0 PROGRAM DESCRIPTION 4.0 PROGRAM DESCRIPTION The ODCM contains the CGS licensing based sampling requirements for the REMP. Additional sampling requirements are specified in resolutions with the Washington State Energy Facility Site Evaluation Council (EFSEC) or are self-initiated in response to site specific or industry wide concerns.The sampling plan presented in Table 4-1 gives an overview of the REMP sampling routine, a summary of the sample locations, the specified collection frequency, and the types of analyses to be performed.
The methods of sampling and sampling frequencies utilized in the program are mostly dictated by regulatory requirements.
Factors such as nuclide half-lives and the major exposure pathways for the radionuclides potentially released from the plant have been taken into account in determining the sampling methodology.
4.1 Sample Locations One hundred and ten sampling locations (referred to as 'stations')
are included in the monitoring program. More than one sample type may be collected at a sample station. One hundred and one indicator and three control stations are located within a 10-mile radius of CGS. Six additional stations are located beyond the ten mile radius of the plant, two are indicator locations and four are control locations.
Sample stations are listed in Tables 4-1 and 4-2. Most station locations are shown in Figures 4-1 to 4-4.The locations of most sample stations have been selected on the basis of an exposure pathway analysis.
The exposure pathway analysis was based on factors such as weather patterns, anticipated emissions, likely receptors, and land use in the surrounding areas. Samples collected from stations located in areas that potentially could be influenced by CGS operation are used as indicators.
Samples collected from locations that are not likely to be influenced by CGS operation serve as controls.
Results from indicator stations are compared to the results from control stations and results obtained during the previous operational and preoperational years of the program in order to assess the impact CGS operation may be having on the environment.
4.2 Independent Spent Fuel Storage Installation (ISFSI)The Independent Spent Fuel Storage Installation (ISFSI) is a fenced, secured area constructed to provide a storage location for spent nuclear fuel. The spent fuel is stored in HI-STORM dry storage casks which are placed on concrete pads inside the facility.
The pads are 30-feet wide by 135-feet long and each pad can hold up to 18 casks. The ISFSI is located approximately 500 meters north-northwest of the reactor building.
Three security fences surround the ISFSI facility.Direct radiation monitoring of the ISFSI is performed using TLDs placed at 10 different locations on the second of three security fences that surround the facility.
The TLDs are exchanged quarterly.
In addition, two other TLD stations, Station 121 located approximately 200 meters north of the turbine building and Station 122 located approximately 100 meters north of the ISFSI, were installed to monitor ISFSI direct radiation.
Figure 4-1 shows the ISFSI location in relation to CGS and the position of the 2 additional TLD locations.
Figure 4-4 shows the location of the 10 TLD stations located around the ISFSI. This arrangement of TLDs in conjunction with the radiological surveys conducted by the CGS Radiation Protection Department serve as the radiological monitoring program for the ISFSI.2013 Annual Radiological Environmental Operating Report 4-1 Energy NorthwestlColumbia Generating Station 2013 Annual Radiological Environmental Operating Report 4-1 Energy Northwest/Columbia Generating Station I 4.3: Land Use Census I A land use census covering the areas within a five mile radius of CGS is performed annually.
The objective of the land use census is to identify the locations of the nearest milk animal, residence, and garden greater than 500 ft 2 producing broadleaf vegetation.
This information is used to determine whether any site located during the census has a calculated dose or dose commitment greater than the sites currently monitored for the same exposure pathway. If a new location with a higher dose I commitment was found, routine sampling of that dose pathway would be initiated at that new site. The results of the 2013 five miles land use census are presented in Table 4-3. No significant changes from the 2012 land use census were observed.4.4 Sampling Methods 3 Energy Northwest personnel collect environmental samples in accordance with the program plan outlined in Table 4-1. Methods of sample collection and TLD handling are specified in REMP specific procedures.
All routine REMP samples collected in 2013 were prepared for analysis at the Energy I Northwest Environmental Services Laboratory located in Richland, WA. The section 4.4 subsections below give a general overview of the sampling methods used in the REMP. Generic descriptions of the REMP sample analysis methods are given in section 4.5. I 4.4.1 Direct Radiation Direct radiation dose levels are monitored with Harshaw Model 8807 thermoluminescent dosimeters (TLDs). The TLDs are placed in the field between three and five feet above the ground. TLDs are wrapped in aluminum foil and sealed in plastic bags to prevent damage. TLDs are exchanged on a quarterly basis.The locations of the TLD stations are listed in Table 4-2 and are shown in Figures 4-1 through 4-4.Station 9A near Sunnyside, WA serves as the environmental TLD control location.
Station 11 9C serves as the control for Station 119B (the cooling system sediment disposal basin). The remaining TLDs deployed in the field serve as indicator TLDs. U The TLDs are arranged in a series of rings that encircle CGS. The innermost ring of TLD stations, referred to as the "S" stations, are located inside the CGS site boundary at distances that range from 0.3-0.8 miles from the reactor building centerline.
The second ring of TLDs, referred to as the "near plant" I stations, are located at distances ranging from 0.9 to 2.1 miles from the reactor building.
The outer ring of TLDs are located at distances that range from a little under three miles to around ten miles. A MicroRem dose rate meter is available as a backup device and to take real time readings as needed.4.4.2 Airborne -Particulate/Iodine Weekly air particulate and radioiodine (Iodine -131) samples are obtained through the use of low volume (1.5 cfm), constant flow-rate sampling units located at 1.2 locations.
The samples collected at Station 9A (Figure 4-3) serve as controls, the samples collected at all other locations (Figures 4-1, 4-2, and 4-3) are 3 indicators.
Air particulate samples are collected using 47mm diameter glass fiber filters, air iodine samples are collected using Radeco CP- 100 TEDA impregnated charcoal cartridges.
The air particulate filter and charcoal cartridge are placed in tandem, particulate filter first, in a holder that attaches to the air inlet of the sampler unit. The sampler units are placed in ventilated metal weatherproof housings mounted on elevated platforms at each air sample location.
The filter media are changed weekly. Four 2013 Annual Radiological Environmental Operating Report 4-2 Energy Northwest/Columbia Generating Station U additional air sample monitor locations are available to monitor work at the DOE 618-11 burial site if needed.4.4.3 Water Water sampling is performed to meet ODCM and State of Washington EFSEC requirements, comply with NEI guidelines, or as a CGS initiative.
REMP water sampling can be categorized as follows:* Intake-River/Drinking Water; two locations (Stations 26 and 29)* Deep Groundwater; three locations (Stations 52, 31 and 32)* Shallow Groundwater; ten locations (MW-3, 5, 6 and MW-8 through MW-14)* Plant Discharge Water; one location (Station 27)* Storm Drain Water; one location (Station 101)* Sanitary Wastewater; two locations (Stations 102A and 102B)The sample at Station 26 is obtained using a composite sampler that draws water from the plant intake water system (TMU). The source of this water is the Columbia River. The station serves as a control location, as it is upstream of the plant discharge location, and also as a drinking water location as drinking water for CGS comes from this source. Station 29 is a composite sampler located at the City of Richland Water Treatment Plant located 11 miles downstream of the plant discharge.
Station 29 is an indicator station for both river and drinking water.The ODCM requirement for a downstream water sample "near but beyond the mixing zone" is conservatively met by Station 27, a composite sampler that collects water from the cooling tower discharge line just prior to final discharge into the Columbia River. This sample reflects the radioactivity present in the plant discharge prior to any river dilution, rather than the concentrations that would be found after dilution in the mixing zone. Composite samples from Stations 26, 27, and 29 are collected monthly and analyzed for gamma emitting radionuclides, gross beta, and tritium.Three drinking water wells on Energy Northwest property are used to provide deep groundwater samples. These wells are greater than 400 feet deep and provide samples from the confined aquifer.under CGS. Station 52 is a deep well located 0.1 mile north of the CGS reactor building.
Station 31 and 32 are deep wells at the IDC (ENW Industrial Development Complex) located 1.2 miles down gradient from CGS. Water from Station 52 can be used as a backup source for drinking water and fire protection.
The IDC wells supply water for drinking and. fire protection at the IDC site. All of these wells are considered indicator locations.
Quarterly grab samples are collected from each well and analyzed for gamma emitting radionuclides and tritium.Station 101 is a composite sampler that collects a representative sample of water flowing into the storm drain pond located east of CGS. The main sources of water to the pond are discharges from the potable water and plant makeup water demineralizer treatment systems. Storm water runoff from the CGS site is also directed to this location.
Water discharges from CGS that have been verified to meet radiological environmental discharge limits are another potential source of water to the storm drain pond. Water is collected monthly using a flow-proportional composite sampler and analyzed for gross beta, gamma emitting radionuclides, and tritium.2013 Annual Radiological Environmental Operating Report 4-3 Energy Northwest/Columbia Generating Station 2013 Annual Radiological Environmental Operating Report 4-3 Energy Northwest/Columbia Generating Station The Sanitary Waste Treatment Facility (SWTF) receives sanitary waste water from CGS, the IDC (ENW I Industrial Development Complex), the Kootenai Building, and the DOE 400 area. Discharge standards and monitoring requirements for the SWTF are established in EFSEC ResolutionNo.
300. (16) Station 102A is a flow meter and composite sampler located on the DOE 400 area sewer line before it ties into the sewer lines coming from Energy Northwest facilities.
Water used at the DOE 400 area is drawn from aquifers that are known to be contaminated with tritium as a result of past DOE activities on the Hanford 3 Site, consequently, the water sampled at Station 102A has tritium concentrations normally around 1500-2000 pCi/liter.
Station 102B is a composite sampler that collects a representative sample of water flowing into the head works at the SWTF. The sample obtained here contains water from all the Energy 3 Northwest facilities mentioned above and the DOE 400 area. Monthly samples are collected at both Stations 102A and 102B and analyzed for gross alpha, gross beta, tritium, and gamma emitting radionuclides.
Routine quarterly grab samples are taken as part of the REMP from 10 shallow groundwater monitoring wells surrounding CGS. The monitoring well locations are shown in Figure 4-1. The shallow I groundwater wells are all less than 100 feet deep and allow samples to be obtained from the unconfined aquifer under CGS. None of the wells are used for drinking water. Sampling from these locations is performed to meet NEI 07-07 guidelines (17) and requirements in the CGS NPDES permit.4.4.4 Soil I Annual soil samples are a requirement of EFSEC Resolution No. 332.(9) For 2013, two soil samples were collected from locations near CGS, two samples from farmland in Franklin County east of CGS, and one sample from a control location near Sunnyside, WA. Each sample was collected from an area of I approximately one square foot to a depth of approximately one inch. About two kilograms of soil was collected for each sample. Soil samples are analyzed for gamma activity on a dry weight basis.4.4.5 Sediment River sediment samples are collected semiannually as required by the ODCM and EFSEC Resolution No. 332.(9) The upstream sediment sample location (Station .33) is approximately two miles upriver from the plant discharge.
The downstream sample (Station.34) is collected approximately one mile downstream from the plant discharge.
Each sample consists of approximately two kilograms of shallow surface sediment scooped from areas known to be underwater during high water periods and where the potential for sediment accumulation is likely. Sediment samples are dried in an oven and then analyzed for gamma emitting radionuclides on a dry weight basis.Cooling system sediment samples are collected and analyzed whenever cooling system sediment is added to the disposal cells (Station 1 19B, Figure 4-1). Disposal of cooling system sediment is made in accordance with EFSEC Resolution No. 299.(18) Pre-disposal samples are collected and analyzed prior to , transfer to ensure the material will be within the limits specified in the EFSEC resolution.
Following transfer, the material is allowed to dry and a post-disposal sample is collected and analyzed.
3 4.4.6 Fish Annual fish sampling is usually performed in the fall. Fish samples collected from the Columbia River 3 (Station 30) serve as indicator samples, whereas fish collected on the Snake River (Station 38) serve as control samples. Only edible portions of the fish are used to prepare the samples for analysis.
Fish 2013 Annual Radiological Environmental Operating Report 4-4 Energy Northwest/Columbia Generating Station I samples are analyzed for gamma emitting radionuclides on a wet weight basis. Three species of fish are collected; an anadromous species (salmon or steelhead), and two other species generally considered edible or potentially edible (typically carp, catfish, sucker, or whitefish).
The same species are collected at each location.
Electroshock techniques have historically been used for fish collection.
Anadromous species are usually collected at fish hatcheries.
4.4.7 Milk Milk samples are collected monthly during the fall and winter months (October through March).During the spring and summer months when cows are more likely to be grazing or on fresh feed, milk samples are collected twice per month. Raw milk samples are collected within a few hours of milking and the samples are normally prepared and analyzed within four days. Milk samples were collected in 2013 from two locations.
Station 36 in Franklin County serves as the indicator location and is the only known dairy within a ten mile radius of CGS. Station 9B near Sunnyside, WA serves as the control location.4.4.8 Garden Produce Samples of local garden produce are collected monthly during the growing season when the produce is readily available.
Three types of garden produce are typically collected; root crops, fruits, and leafy vegetables.
Control samples (Station 9C) are usually obtained from the lower Yakima Valley. Indicator samples (Station 37) are primarily collected from areas downstream of the CGS discharge where crops are irrigated with Columbia River water. The Riverview area of Pasco is the principle collection location for fruit and root crops. Collection of leafy vegetables is primarly made from locations that could potentially be influenced by CGS gaseous emissions.
Vegetation samples may also be collected from locations closer to CGS; however none were collected in 2013. Garden and vegetable samples are typically purded in a food processor and then analyzed for gamma emitting radionuclides on a wet weight basis. Only edible portions are used for analysis.4.5 Sample Analyses General descriptions of the procedures used to analyze REMP samples are provided in the following sections.
All REMP TLDs in 2013 were processed by Mission Support Alliance (MSA) at the Hanford External Dosimetry Program (HEDP) facility located in Richland, WA. All routine REMP field samples were collected and analyzed by Energy Northwest Environmental Services personnel.
Samples are normally collected and analyzed within a short time period to ensure required detection sensitivities are met and to provide timely results. Sample count times are conservatively calculated to ensure required a priori LLDs are achieved.
Table 4-4 lists the ODCM required LLDs and the nominal target LLD used in the Energy Northwest REMP program.4.5.1 Analysis of TLDs REMP TLDs are analyzed on a Harshaw Model 8800 hot gas reader. The reader is calibrated weekly and immediately prior to processing the environmental TLDs. The reader is calibrated with TLDs that have been given a known exposure from a cesium- 137 source. Each group of environmental TLDs is processed with blank (freshly annealed)
TLDs and spiked TLDs that have been given a known exposure.Exposure received by the field TLDs during transport is monitored with a set of 'trip' control dosimeters that accompany the field dosimeters to and from the field locations and while they are in storage.2013 Annual Radiological Environmental Operating Report 4-5 Energy Northwest/Columbia Generating Station I Another set of TLDs, the building controls, are used to determine~the exposure of the TLDs at the storage I location.
The TLD exposure during transport to and from the field was determined from the difference between the building control results and the trip control results. i 4.5.2 Gross Beta Activity on Air Particulate Filters Air particulate filters are counted directly in a gas flow proportional counter after a delay of several days to allow for the decay of radon and its progeny. Samples were counted using a Protean WPC-9550 instrument which allows automated sample counting and simultaneous alpha/beta determination.
If gross beta activity is identified significantly above the mean of the control, gamma isotopic analysis is I performed on the individual samples.4.5.3 Measurement of Gamma Emitting Radionuclides 3 Gamma isotopic analysis allows identification and quantification of gamma-emitting radionuclides that may be attributable to CGS effluents.
Shielded, high purity. germanium (HPGe) detectors are used to j assay environmental samples for gamma emitting radionuclides.
All samples are counted in standardized, calibrated geometries." Liquids -Measured aliquots of the liquid samples are poured into appropriately sized I Marinelli beakers or plastic canisters.
Sample results are corrected for decay during the collection period if applicable.
Results are reported in pCi/liter.
I" Solids -Soil, sludge, and sediment samples are dried and if needed ground. Foodstuff, biota (fish), and vegetation, are chopped finely or pureed and then analyzed wet (no drying is done). For foodstuff (including fish), only the edible portion of the sample is used. Sample aliquots are placed in tared containers and weighed. Results are reported in pCi/kg.* Charcoal Cartridges
-Typically four charcoal cartridges are counted simultaneously using a cartridge holding jig that positions the cartridges in a standardized geometry to the side of the detector.
Detector calibration files are maintained for both face count and side count positions.
If radioiodines are identified in the assay of a group, each charcoal cartridge in the group is assayed I separately.
Results are corrected for decay during the sample collection period. Results are reported in pCi/m 3.3* Air Particulate Filters -At the end of each quarter, air particulate filters are composited on a station by station basis. The filters are stacked in a Petri dish and analyzed by gamma spectroscopy.
Results are reported in pCi/m 3 and represent the total quarterly gamma activity I collected at each station. Results are decay corrected to the midpoint of the sample collection period. If a radionuclide related to CGS operation is positively identified, the filters are separated and counted individually.
I 4.5.4 Gross Alpha and Gross Beta Activity in Water g A measured aliquot of each sample is evaporated to a small volume then quantitatively transferred to a ribbed, stainless steel planchet.
Final evaporation is normally done under a heat lamp. Residue mass is determined by weighing the planchet before and after mounting the sample. The planchet is 3 counted for gross alpha and beta activity using a Protean WPC-9550 automatic gas flow proportional counter which allows automated sample counting and simultaneous alpha/beta determination.
Results 2013 Annual Radiological Environmental Operating Report 4-6 Energy Northwest/Columbia Generating Station l are corrected for sample self-absorption:
using the sample residue mass values. Results are reported in pCi/liter.
4.5.5 Tritium in Water The sample is distilled, then 8.0mL of the distillate is mixed with 12.OmL of scintillation cocktail.The sample mixture is analyzed on a Packard Tri-Carb 2900TR automatic liquid scintillation counter.Results are reported in pCi/liter..
4.5.6 Strontium-89/90, Iron-55, and Nickel-63 These "hard to detect" analytes are not routinely analyzed as part of the CGS REMP. When needed, these analyses are performed under contract by Teledyne-Brown Environmental Services Laboratory located in Knoxville, TN using the vendor's standard analysis procedures.
4.5.7 Low Level Radioiodine in Milk and Water Four liters of sample are first equilibrated with stable iodide carrier. Anion exchange resin is then added and mixed for a period sufficient to allow any iodine present in the sample to be captured by the resin.The resin is then isolated from the liquid sample and transferred to a small counting container.
The radioiodine content is determined by gamma spectroscopy analysis.
Results are reported in pCi/liter.
4.6 Data Analysis Methods Counting results for low level samples are often within the counting error of the background determination; consequently results. for these samples can be positive or negative values. Though most REMP analytical results are belowthe detection limit, an actual calculated value has been reported.
In some cases the reported value is zero or a negative number. Reporting results in this manner is the preferred practice for low level environmental analyses as it gives an indication of positive or negative biases that may be present and prevents loss of individual results inherent in the use of "less than" (<)values. Also reported in most cases are the aposteriori MDA values. Anuclide is flagged as positively identified if its calculated value is greater than the MDA. A listing of the Energy Northwest nominal target LLDs (apriori) for each sample type is provided in Table 4-4; the ODCM required LLDs are also included for a comparison.
Data is trended following analysis for many of the sample types analyzed.
For analyses such as .gross beta on air particulate filters where results are normally above the detection limit, indicator results are plotted with the control results for better comparison.
Analysis results that are normally below detection limits are plotted against historical data .to monitor if trends may be evident.Thermoluminescent dosimeter (TLD) data is presented in both units of mR/day and mR/standard quarter.TLD results in mR/day are calculated by taking the total exposure (in mR) determined for each TLD, correcting for storage background and any transit (or trip) exposure received during distribution and retrieval, then dividing by the number of days the TLD was in the field. The mR/standard quarter values are calculated by multiplying the mR/day value by 91.25 days (365/4). All TLD results are reported in units of exposure (Roentgen) and not in units of dose (Rem).2013 Annual Radiological Environmental Operating Report 4-7 Energy Northwest/Columbia Generating Station 4.7 Changes to the Sampling Program in 2013 There were no major changes made to ODCM or EFSEC Resolution No. 332(9) mandated sampling in 2013. Sampling and analysis of shallow groundwater wells around CGS was continued as a routine part of the REMP. No samples were obtained from one of the shallow groundwater wells (MW-7) in 2013 due to lack of water. The last sample obtained from this location was in the third quarter 2012.Sampling -from Station 102A was terminated at the end of December.
This station consisted of a composite water sampler that sampled the sanitary effluent line coming from the DOE 400 area. The effluent line was plugged in mid-December and ENW is no longer accepting sanitary waste from this location.
One TLD location, Station 73, was moved in October to a new location due to construction activities.
The new location is in the same geographical sector and approximately 175 feet from the old location.I i I i!I i I I I I U I!S i I I i 2013 Annual Radiological Environmental Operating Report 4-8 Energy Northwest/Columbia Generating Station TABLE 4-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING PLAN SAMPLE METHOD AND SAMPLE STATION (b' COLLECTION TYPE AND FREQUENCY OF SAMPLE TYPE'a. NUMBER 1  ANALYSIS AIRBORNE Particulates and 1, 4-8, 9A, 21, 23,40, 48, Continuous sampling; weekly Weekly air filters gross beta and Radioiodine (6/1 2)1d) and 57' collection.
iodine cartridge gamma isotopic.Quarterly air filter composite gamma isotopic.DIRECT RADIATION TLD 1 g)(34/79) 1-8, 9A, 10-25, 40-47, 49- Continuous monitoring, quarterly Radiation exposure monitoring 51, 53-56, 58, 65, 71-90, collection.
processed on a quarterly 119B, 119C, 120-129, frequency.
136A-138A, 150-151.WATERBORNE River/Drinking Waterh) 26, 27 and 29 Composite aliquots 1'; monthly Monthly gamma isotopic, gross (3/3) collection, beta, and tritium. lodine-1310) as required.Storm Drain Water (0/1) 101 Composite aliquots&deg;', monthly Monthly gamma isotopic, tritium, collection.
and gross beta.Sanitary Waste 102A, 102B Composite aliquots"), monthly Monthly gamma isotopic, gross Treatment Facility collection.
beta, gross alpha, and tritium.Water (0/2)Ground Water (2/3)(k1 31, 32, and 52 Grab sample performed quarterly.
Quarterly gamma isotopic and tritium.Ground Water MW-3, 5, 6, 8-14 Grab sample performed quarterly.
Quarterly gamma isotopic and Monitoring (0/I10)" tritium.SOIL AND SEDIMENT Soi1l"(0/5) 9A, 7, 8, 23, 48 Grab sample performed annually.
Annual gamma isotopic.Strontium-90' 0 as required.River Sediment (1/2)(1) 33 and 34 Grab sample performed Semiannual gamma isotopic.semiannually.
Cooling System 119B, 119C Grab sample of dried sediment Gamma Isotopic.
After disposal.Sediment Disposal Area within 30 days of disposal date.(0/2)INGESTION(2/2) 9B, 36 Grab sample collected Gamma isotopic, Iodine-131 each semimonthly during grazing sample. Strontium-90.'n) as season, monthly at other times. required Fish'0' (2/2) 30, 38 Grab samples collected annually.
Gamma isotopic each sample.Garden Produce(')(l/2) 9C, 37 Grab samples collected monthly or Gamma isotopic each sample.at time of harvest.2013 Annual Radiological Environmental Operating Report 4-9 Energy Northwest/Columbia Generating Station 2013 Annual Radiological Environmental Operating Report 4-9 Energy Northwest/Columbia Generating Station I TABLE 4-1 FOOTNOTES: (a) -The fraction in parentheses for each sample type indicates the ratio of ODCM-required sample locations tothe total number of sample locations currently being monitored in the surveillance program. Additional sampling is perforimed to meet EFSEC Resolution 332 requirements or as an ENW initiative.(b) The underlined sample location designates a control station.(c) Sample collection is performed at a frequency specified in the ODCM and EFSEC resolutions.
Some sampling referenced in 5 Table 4-1 is performed at CGS initiative.
Sample deviations are permitted if samples are unobtainable due to hazardous conditions, seasonal availability, malfunction of automatic sampling equipment, or other legitimate reasons.(d) The ODCM specifies six air sample locations and EFSEC Resolution 332 specifies nine. Two of the air sample stations are maintained at CGS initiative and are not requirements of either the ODCM or EFSEC Resolution 332. I (e) Sampling is performed to meet NEI 07-07 guidelines and NPDES requirements.(t) Soil samples are collected from five locations to satisfy EFSEC Resolution 332 requirements.
Two samples are collected from 3 locations near CGS, two from locations in Franklin County, and one collected from a control location.
Sample locations listed in Table 4-1 are the location sampled in 2013. EFSEC 332 requires strontium-90 analysis be performed if gamma analysis results are greater than a specified threshold.
&#xa3;(g) TLD Stations 71-86 are not included among the 34 TLD stations required by the ODCM. Alternate designations for these stations are I S-I 6S. EFSEC Resolution 332 requires 25 or more TLD stations to be located within a 10-mile radius of CGS.Other instruments, such as a pressurized ion chamber (PlC), may be used in place of or in addition to TLDs as per ODCM table 6.3.1-1 (b). CGS REMP maintains a uRem meter for this purpose.(h) The term "river/drinking water" is used throughout this report because the drinking water is taken from the Columbia River.Station 26, CGS makeup water intake from the Columbia River is both an upstream water sample and the drinking water sample location.
Station 29 is a downstream drinking water sample location.
The Station 27 sample, which is drawn from the plant discharge line, is taken in place of a "downstream" water sample near but beyond the mixing zone. It reflects the radioactivity I present in the plant discharge prior to any river dilution.
EFSEC Resolution 332 requires samples from at least one downstream drinking water location and samples from the plant intake and discharge water systems.(i) Composite samples are collected using automatic sampling equipment that collects samples based on a flow proportional or timed interval basis. If timed interval sampling is used, the interval period is short (e.g. hourly) relative to the compositing period (e.g. monthly).When the dose calculated via ODCM methodology for consumption of water exceeds I mrem per year, low level iodine-I 31 3 analyses are performed on the drinking water samples.(k) Sampling from these locations fulfills ODCM table 6.3.1-1 3b requirements.
EFSEC Resolution 332 requires sampling from at least one deep well used for fire protection and/or as a backup drinking water sources.(I) Downstream sampling fulfills ODCM table 6.3.1-1 3d requirements.
EFSEC Resolution 332 requires annual sediment samples upstream and downstream of the plant discharge.(m) ODCM table 6.3.1-1 4a milk collection requirements cannot strictly be met due to the lack of milking animals near CGS. Milk I samples are collected from the nearest dairy potentially impacted by CGS operation and also from a control location at the frequency specified in the ODCM. EFSEC Resolution 332 specifies sampling from at least one milk location within the 10-mile radius of CGS and also from a control location.
Broadleaf vegetation can be sampled in lieu of milk if a representative milk sample is not available.(n) ODCM table 6.3. 1-1 (k) requires that if cesium-134 or cesium-137 is measured in an individual milk sample in excess of 30 pCi/l iter, then a strontium-90 analysis will also be performed.(o) Station 30 is the Columbia River and station 38 is the Snake River. If an impact is indicated, sampling will be conducted I semiannually per ODCM table 6.3.1-1 (i). There are no species fished commercially in the Hanford Reach of the Columbia River. The most recreationally important species in the area are anadromous, which ascend rivers from the ocean for breeding.Anadromous fish species are normally obtained from hatcheries; Snake River samples are obtained from the Lyons Ferry Fish Hatchery, and Columbia River samples are obtained at the Ringold Fish Hatchery.(p) Garden produce is obtained from farms or gardens that use Columbia River water for irrigation.
One sample of a root crop, leafy vegetable, and a fruit is typically collected each sample period, when available.
EFSEC Resolution 332 further specifies fruit and vegetable sampling from locations potentially impacted by CGS gaseous emissions.
2013 Annual Radiological Environmental Operating Report 4-10 Energy Northwest/Columbia Generating Station a TABLE 4-2 REMP SAMPLE STATIONS AND REQUIREMENTS STATION DISTANCE SECTORW NUMBER"' MILES"' ODCM"d' STATE"' OTHER")N (1) 52 0.07 DGW DGW 71(1S) 0.28 TLD 47 0.70 TLD 57 0.70 AP/AI 18 1.16 TLD TLD 53 7.54 TLD NNE (2) 72(2S) 0.32 TLD 2 1.45 TLD TLD 54 6.08 TLD NE (3) 73(3S) 0.54 TLD 19 1.74 TLD TLD 48 4.59 AP/AI AP/AI 46 4.99 TLD MW-9 0.22 SGW ENE (4) 74(4S) 0.38 TLD 21 1.45 TLD, SO AP/AI 20 1.93 TLD TLD 11 3.16 TLD 33 3.44 SE 45 4.45 TLD 44 5.90 TLD 101 0.22 SW MW-8 0.26 SGW MW-I1 0.10 SGW E (5) 75(5S) 0.37 .TLD 22 2.08 TLD 10 3.16 TLD TLD 26 3.19 SW, DW SW 27 3.19 SW DIS W 30") 3.5 FI FI 43 5.16 TLD 151 (Site 4) 0.83 TLD MW-12 0.12 ..SGW ESE (6) 76(6S) 0.42 TLD 31 1.06 DGW 32 1.27 DGW 51 2.14 TLD 2013 Annual Radiological Environmental Operating Report 4-11 Energy Northwest/Columbia Generating Station TABLE 4-2 (cont.)REMP SAMPLE STATIONS AND REQUIREMENTS STATION DISTANCE SECTORa NUMBERb' MILES"' ODCM"' STATE"' OTHER"'ESE (6)(cont.)
34 3.32 SE SE 23 3.03 TLD, AP/AI. SO 8 4.39 TLD, AP/AI TLD, AP/AI 42 5.85 TLD 36 7.33 MI MI 5 7.72 TLD AP/AI 38(g) 26 Fl FI 150 (Site 1) 0.90 TLD SE (7) 77(7S) 0.57 TLD 24 1.87 TLD TLD 3 2.06 TLD 41 5.79 TLD 40 6.51 TLD, AP/AI AP/AI MW-14 0.58 SGW SSE (8) 119C 0.28 TLD 120 0.32 TLD, SE 102B 0.50 SFW 102G 0.56 GP/VE 78(8S) 0.81 TLD 25 1.50 TLD TLD 55 6.05 TLD 4 9.57 TLD, AP/AI TLD, AP/AI 29 11.57 DW DW 37 h) 16 GP GP MW-6 0.33 SGW MW-13 0.52 SGW S(9) 119B 0.31 TLD, SE 102A 0.67 SFW 79(9S) 0.76 TLD 1 1.25 TLD TLD, AP/AI, SO 6 7.72 TLD TLD, AP/AI 65 8.87 TLD SSW (10) 80(10S) 0.83 TLD 50 1.26 TLD TLD 56 6.65 TLD MW-3 0.31 SGW I a I I S U I I I i I I&#xa3;I I 1 I I I 2013 Annual Radiological Environmental Operating Report 4-12 Energy Northwest/Columbia Generating Station TABLE 4-2 (cont)REMP SAMPLESTATIONS AND REQUIREMENTS STATION DISTANCE SECTOR"a NUMBER'b)
MILES") ODCM") STATE"' OTHER"'SW (11) 13 1.26 TLD TLD 81(11S) 0.74 TLD 103A 0.63 VE goo, 0.62 TLD, Al/AP MW-5 0.43 SGW WSW (12) 82(12S) 0.57 TLD 14 1.26 TLD TLD 9A 28.35 TLD, AP/AI TLD, AP/AI, SO 9B 32.82 MI MI 9C'i) 32 GP 890' 0.23 TLD, Al/AP 58 0.44 TLD W (13) 83(13S) 0.52 TLD 15 1.24 TLD TLD WNW (14) 84(14S) 0.55 TLD 16 -1.21 TLD TLD 7 2.83 TLD TLD, AP/AI, SO 886, 0.17 TLD, AUAP MW-10 0.07 SGW NW (15) 85(15S) 0.43 TLD 49 1.19 TLD TLD 870' 0.20 TLD, AL/AP NNW (16) 121 0.12 TLD 122 0.31 TLD 123 0.29 TLD 124 0.28 TLD 125 0.28 TLD 126 0.28 TLD 127 0.26 TLD 128 0.25 TLD 129 0.17 TLD 136A 0.29 TLD 137A 0.24 TLD 138A 0.17 TLD 86(16S) 0.31 TLD 17 1.19 TLD TLD 12 6.74 TLD 2013 Annual Radiological Environmental Operating Report 4-13 Energy Northwest/Columbia Generating Station TABLE 4-2 (cont.)REMP SAMPLE STATIONS AND REQUIREMENTS TABLE 4-2 SAMPLE TYPE KEY AP/AI -Air Particulate/Air Iodine Dis W -Discharge Water GP -Garden/Orchard Produce MI -Milk SFW -Sanitation Facility Water SW -Surface Water VE -Vegetation DW -Drinking Water FI -Fish DGW -Deep Ground Water SE -Sediment SO -Soil TLD -Thermoluminescent Dosimeter SGW -Shallow Ground Water TABLE 4-2 FOOTNOTES: (a) The area in the vicinity of CGS is separated into 16 sectors for reporting purposes.
The 16 sectors cover 360 degrees in equal 22.5 degree sections, beginning with sector I (N) at 348.75 to 11.25 degrees and continuing clockwise through sector 16 (NNW).(b) Alternate designations for station are given in parentheses; i.e., TLD Stations 71-86 are also referred to as I S-16S.(c)(d)Distances are from GPS positions for each location as a radial distance from CGS reactor building.ODCM -Offsite Dose Calculation Manual Table 6.3.1-1 requirement.
I I I p I I I I I 3 I I I I I I I I (e) STATE -State of Washington EFSEC Resolution requirement.(f) OTHER -Special study stations.
TLD Stations:
121 through 129 and 136A through 138A satisfy ISFSI monitoring requirements 10CFR72.44(d)(2).
Sampling at MW locations performed to meet NEI 07-07 guidelines and NPDES requirements.
Stations 102G and 103A are locations near CGS where vegetation samples have been collected in the past. No samples were collected from these locations in 2013.(g) Station 30 is the Columbia River at the vicinity of the plant discharge.
Actual distance of fish collection locations from plant are variable, distance listed is approximation.
Station 38 is the Snake River. Control resident fish are typically collected at variable locations in area below Ice Harbor Dam, distance listed is approximation.
Control anadromous fish are typically collected at Lyons Ferry Fish Hatchery.(h) Fruit and Vegetable indicator samples are typically collected from farms and gardens in the Riverview area of Pasco. Distance listed here is general distance of Riverview area to CGS. Station 37 designation is also used for any samples collected in Franklin County that could potentially be affected by CGS liquid or gaseous effluents.(i) Station 9C is the designation given for control fruits and vegetables.
Distance listed is general distance to the Sunnyside-Grandview area where the majority of the control fruits and vegetables are obtained.0.) Stations 87-90 were installed at CGS initiative to monitor remediation work at the DOE 618-11 burial ground. No remediation work that affected CGS was performed in 2013 and no air samples were obtained from these locations in 2013. See Section 5.9.6 for further discussion.
2013 Annual Radiological Environmental Operating Report 4-14 Energy Northwest/Columbia Generating Station TABLE 4-3 2013 FIVE MILE LAND USE CENSUS RESULTS NEAREST GARDEN~d)SECTORta)
RESIDENT(" (>5 00 ft) DAIRY ANIMALS LIVESTOCK(b'c)
NE 4.50 none none none ENE 3.88 none none 4.95 E 4.64 none none 4.64 ESE 4.26 none none 4.49 SE none none none none FOOTNOTES (a) Within a five-mile radius of the plant, only the five sectors listed above contain activities related to land use census requirements.
The other eleven sectors lay fully within the federally owned Hanford Site. Only those sectors containing potential land use census activities are presented here.(b) Estimated distances in miles from CGS Reactor Building based on GPS readings.
Actual locations are same as identified in previous years, distance values may differ from those reported in past due to updated GPS data.(c) 25 to 30 beef cattle were identified in a pasture in the ENE sector. The western edge of the pasture is just within the 5 mile radius. Additional feed appears to be provided at this location.
5 cows, 2 calves, 3 horses, and some chickens were observed in a small fenced area near a residence in the E sector. The animals were observed to be fed hay. A single horse was observed in the ESE sector. There is no pasture at this location and the horse appears to be fed hay.(d) Though no gardens > 500 fi2 were identified, commercial agriculture is extensively practiced in some parts of the sectors identified in Table 4-3. Agricultural activities observed were primarily apple and soft fruit orchards, corn, alfalfa, and grape vineyards.
2013 Annual Radiological Environmental Operating Report 4-15 Energy Northwest/Columbia Generating Station TABLE 4-4 COMPARISON OF LABORATORY NOMINAL LOWER LIMITS OF DETECTION WITH OFFSITE DOSE CALCULATION MANUAL REQUIREMENTS I I I MEDIA (UNITS)Air (pCi/M 3)Water: (pCi/liter)
Soil/Sediment: (pCi/kg dry)ANALYSIS Gross Beta Cs-134 Cs-137 1-131 Gross Beta Tritium Sr-90 Ni-63 Fe-55 I-131(.c Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs- 134 Cs-137 Ba-La-140 Mn-54 Co-60 Zn-65 Cs-134 Cs-137 Sr-90 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 1-31 (c)Cs-134 Cs-137 Ba-La- 140 Sr-90 Cs- 134 Cs-137 1-131 ENERGY NORTHWEST LLDs(a)0.002 0.001 0.001 0.03 2.4 300 1 5 200 1 7 10 7 7 10 7 7 7 10 20 20 30 20 20 10 25 100 35 25 50 30 25 0.5 7 7 10 1 10 10 12 ODCM REQUIRED LLDs 0.01 0.05 0.06 0.07 4 20001b, 15 30 15 15 30 15 15 18 15 150 180 130 260 130 130 260 130 150 1 15 18 15 60 80 60 Fish: (pCi/kg wet)I I I I I I U I I I I I I I Milk: (pCi/liter)
Garden Produce: (pCi/kg wet)() These are the nominal target LLDs (a priori) for analyses performed in the Energy Northwest Environmental Services Laboratory and are based on conservative assumptions.
These calculations included corrections for decay during the collection period and delay prior to analysis using factors that are normally encountered for the different media types. Actual LLDs (a posteriori ) may be higher or lower for specific samples.col If no drinking water pathway exists, a value of 3,000 pCi/liter may be used.(') This ENW Iodine- 131 LLD achieved by anion resin separation and does not represent a direct analysis of the sample media.2013 Annual Radiological Environmental Operating Report 4-16 Energy Northwest/Columbia Generating Station 0 0 L 05 1 1 I Miles A 72 A 73 83 3 L-AVZ] " 9 v- v vvA A74 275 W2 A A 119C A j 119B 12016 W4 0 wf4 77 W-13 0b ..82 81 W5 A 80 102a A 79 A 78 E Water Sample Sediment Facilities N A TLD Security Barrier DOE Burial Ground* Air Sample , Deep Well Reactor Building ISFSI Shallow Well City Limits Water FIGURE 4-1 SELECT REMP SAMPLING LOCATIONS WITHIN 0.8 MILES OF CGS 2013 Annual Radiological Environmental Operating Report 4-17 Energy Northwest/Columbia Generating Station I 0 1 05 1 2 1 3 1 4 I g I I I g I g E ] I L I g I g I I EA Miles COW"*~ law 2 19 A 18 A 17 A 49 A 16 20 W&deg;31 L A 11 N-, A 15\, 22 4W27 A A 13 102a 0 A 25 5A 23 50 3 24~--~-0 Water Sample Sediment Facilities N A TLD Air Sample Security Barrier DOE Burial Ground Deep Well Reactor Building ISFSI Shallow Well City Limits Water FIGURE 4-2 SELECT REMP SAMPLING LOCATIONS BETWEEN 0.8 AND 2.8 MILES 2013 Annual Radiological Environmental Operating Report 4-18 Energy Northwest/Columbia Generating Station 2013 Annual Radiological Environmental Operating Report 4-18 Energy Northwest/Columbia Generating Station FIGURE 4-3 SELECT REMP SAMPLING LOCATIONS BEYOND 2.8 MILES 2013 Annual Radiological Environmental Operating Report 4-19 Energy Northwest/Columbia Generating Station 250 f r - -- -- --- -- -- -.----------7 -r ST.123 ST.124 ST.125 i-_ -. ---0, ... -,_ ------ -----------
----------
+ -Isoltion Fence I I Security Fence I I~ ~ -------------------------------------------------------------------
I Electrical Cntrl Bldg 135t It ,ST. 1261 T.__ _ _ _ : t T 1 2 71+ 0 Dry Fuel Cask I I ST.128' 0 0T. 21 000000000 I i I,__ ..L ...-I I ----I ST. 136A ST.137A ST. 1 .38A I---------------------+----------------------------
Cr+ REMP TLD 0 FIGURE 4-4 ISFSI TLD STATION LAYOUT 2013 Annual Radiological Environmental Operating Report 4-20 Energy Northwest/Columbia Generating Station 5.0 RESULTS AND DISCUSSION 5.0 RESULTS AND DISCUSSION The Columbia Generating Station environmental TLDs were collected by Energy Northwest Environmental Services personnel and analyzed by the Hanford External Dosimetry Program (HEDP)operated by Mission Support Alliance (MSA). All other CGS REMP samples were collected and analyzed by the Energy Northwest Environmental Services Laboratory located in Richland, WA. Table 5-2 provides a summary of the ODCM required REMP sample and CGS groundwater monitoring analysis results in the format specified in Regulatory Guide 4.8. Results for naturally occurring radionuclides that are not related to CGS operations have not been included in the summary table. The lower limits of detection (LLDs) listed in Table 5-2 are the ODCM required detection limits and are not the method detection limits listed in Table 4-4. Analytical results for all REMP samples are presented in Appendix A of this volume and summarize the results in greater detail.5.1 Direct Radiation Direct radiation is monitored at 79 TLD locations surrounding CGS. TLDs are exchanged on a quarterly frequency at all locations.
The 16 locations designated as "S" stations are located between 0.3 and 0.8 miles from the CGS reactor building and all are inside the property boundary, see Figure 4-1 for station locations.
Figure 5-1 shows the 2013 "S" station mean quarterly TLD results separated into 16 geographical sectors around the plant. Figure 5-1 also shows the pre-operational mean and the high, low, and mean results in each sector for the 1984 -2012 operational period for comparison.
The 2013 "S" station TLD results were lower than the pre-operational mean in 11 of the 16 sectors and lower than the operational mean in 13 of the 16 sectors. TLD results from the N, NNE, and NNW sectors are slightly higher than the other "S" station locations as a result of being physically closer to the ISFSI and the CGS turbine building.
Excluding the NNW sector, the average deviation relative to the pre-operational period was -1.40%; in 2012 the average deviation was -1.65%. The NNW sector is the closest "S" station to the ISFSI and the higher result here is attributed to the stations close proximity to this facility.0.36 S-Stations 0.33 0.30>, 0.27 of 0.24 0.21 0.18 0.15 N NNE NE ENE E ESE SE SSE S SSW SWWSW W WNWNW NNW o Pre-Operational Mean -& 2013 Mean -1984-2012 High/Low/Mean Figure 5-1 "S" Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean by Sector 2013 Annual Radiological Environmental Operating Report 5-1 Energy Northwest/Columbia Generating Station 2013 Annual Radiological Environmental Operating Report 5-1 Energy Northwest/Columbia Generating Station The 19 locations designated as near plant stations are located at distances between 0.9 and 2.1 miles from the CGS reactor building, see Figure 4-2 for station locations.
Figure 5-2 shows the exposure rates for the near plant TLD locations separated into sixteen geographical sectors around the plant.Figure 5-2 also shows the pre-operational mean and the high, low, and mean results in each sector for the 1984-2012 operational period for comparison.
The 2013 near plant TLD results were lower than the pre-operational mean in 12 of the 16 sectors and less than or equal to the operational mean in 14 of the 16 sectors. The average deviation relative to the pre-operational period was -1.7%, in 2012 the average deviation was -3.2%.Near Plant Stations>1 E 0.36 0.33 0.30 0.27 0.24 0.21 0.18 0.15 N NNE NE ENE E ESE SE SSE S SSW SWWSW W WNWNW NNW o Pre-Operational Mean ----2013 Mean -1984-2012 HiglVLow/Mean Figure 5-2 Near Plant Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean by Sector U I I I I I I I I I I I I I I I I I Remote Stations E 0.36 0.33 0.29 0.26 0.22 0.19 0.15 Remote Stations N NNE NE ENE E ,ESE SE SSE S SSW WSW WNW NNW 0 Pre Operational Mean-1984-2012 HighlLow/Mean 6 2013 Mean Figure 5-3 Remote Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean By Sector 2013 Annual Radiological Environmental Operating Report 5-2 Energy Northwest/Columbia Generating Station The 22 TLD locations designated as remote locations are located between 2.83 and 28.35 miles from the CGS reactor building; see Figure 4-3 for station locations.
Figure 5-3 shows the exposure rates for the remote TLD locations separated into geographical sectors around the plant. Figure 5-3 also shows the pre-operational mean and the high, low, and mean results by sector for the 1984-2012 operational period for comparison.
The 2013 remote TLD results were lower than the pre-operational mean in 9 of the 13 sectors and lower than the operational mean in 11 of 13 sectors. Station 46 in the Wahluke Reserve (NE sector) remained the remote location with the highest exposure rate. This has been the case since the pre-operational measurement phase and is attributed to differences in the underlying rock and soil composition in this area. The 2013 average deviation relative to the pre-operational period was -3.7%; the average deviation in 2012 was -3.5%.Offsite direct radiation monitoring results are consistent with previous years. The 2013 results indicate no observable dose contributions due to plant operations at locations outside the CGS controlled area. Dose contributions inside the CGS controlled area are limited to those locations known to be influenced by the Independent Spent Fuel Storage Installation (ISFSI) and/or radiation from the turbine building during operation.
Environmental radiation exposure rates for 2013, the pre-operational period, and the long term operational period are summarized in Tables 5-3. See also Appendix A, Tables A-1.1 and B-1.1 for the 2013 quarterly TLD results. TLD results for special interest locations are discussed in further detail in Section 5.9. " 5.2 Airborne Particulate/Iodine Air samples are collected weekly from 11 sample stations located around CGS. Additionally, an air sample station located 28 miles WSW of CGS is used as a control for comparison.
Air particulate filters are analyzed for gross beta and iodine cartridges for radioiodines on a weekly basis. Air filters are also composited and analyzed for gamma emitting nuclides quarterly.
The 2013 mean weekly particulate filter gross beta results for the five stations located within three miles of CGS are plotted in Figure 5-4 (See also Appendix A, Tables A-2.1, A-2.2). Results for these near plant stations are similar to results from the remote locations and closely follow the trend of the control location.Figure 5-5 is a plot of the 2013 mean weekly particulate filter gross beta results for the 6 sample stations located between 3 and 9.6 miles from CGS (See also Appendix A, Tables A-2. 1, A-2.2). Results for these remote stations are similar to results from the near plant stations and closely follow the trend of the control location.
No correlation between air gross beta activity and proximity to CGS was observed.For both near and remote air station locations, higher results and greater variability in air gross beta activity have historically been observed during fall and winter months due to weather induced background fluctuations.
Gross beta levels typically increase during periods of inversion due to natural decay products being frapped near the earth surface. Gross beta results plotted over a period of several years typically show a cyclical pattern with higher results observed in the fall and winter compared to the spring and summer. Gross beta results above the normal trend range were observed in January, October, November, and December.
The increases were observed at all sample locations including the control and are attributed to weather phenomena and not the result of CGS operation.
The results for weeks 48-50 were among the highest gross beta air results observed by the CGS REMP. Weather conditions for this period were typical. of an inversion with below normal temperatures, overcast skies, and little to no winds. The smaller spike observed in week 43 occurred during a period when fog and blowing dust was noted.2013 Annual Radiological Environmental Operating Report 5-3 Energy Northwest/Columbia Generating Station I I The quarterly particulate filter gamma isotopic results identified the presence of only naturally occurring radionuclides (See Appendix A, Tables A-3.1, A-3.2). Beryllium
-7 was positively identified in all samples at both the indicator and control locations.
Near Plant Stations 0.14 Data from 1986 weeks 19-23 not included due to Chernobyl 0.12 0.10 E 0.08 a. 0.06 0.04 0.02 011TTITTITTT~kd.
I 0.00 '--WEEK 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51-HIGH/LOW/MEAN 1985-2012 A-MEAN 2013-<)-Control 2012 I I I I I I I I I I I Figure 5-4 1985-2012 Weekly Hi/Low/Mean and 2013 Weekly Mean Gross Beta in Air -Near Plant Stations Remote Stations 0.14 0.12 0.10 0.08 0-0.06 0.04 0.02 0.00 ... ..-.WEEK 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51-HIGH/LOW/MEAN 1985-2012-A- MEAN 2013-0--Control 2012 I Figure 5-5 1985-2012 Weekly Hi/Low/Mean and 2013 Weekly Mean Gross Beta in Air -Remote Stations The 2013 weekly iodine cartridge isotopic results showed no indication of radioiodines in any of the samples. Results for iodine- 131 were in all cases below the lower limit of detection. (See Appendix A, Tables A-4. 1, A-4.2).I I I I 2013 Annual Radiological Environmental Operating Report 5-4 Energy Northwest/Columbia Generating Station The 2013 air particulate and iodine sample results show no evidence of measurable environmental radiological air quality impact that can be attributed to CGS plant operation.
5.3 Water 5.3.1 Surface Water Composite water samples are collected from 6 surface water locations monthly and analyzed for tritium, gross beta, and gamma emitters.
A plot of the 2013 gross beta results for the plant intake, plant discharge, and river/drinking water stations are shown in Figure 5-6.Gross Beta in Water 2013 14.0 12.0t 10.0 8.0=6.0 CL 40-2.0 0.0-2.0 1 2 3 4 5 6 7 8 9 10 11 12 Month o Station 26 ---o- Staion 27 S Stan 29 Figure 5-6 Gross Beta in River/Drinking ( Stations 26 & 29) and Plant Discharge Water (Station 27) for2013 All drinking and river water (Stations 26 and 29) gross beta results were below the analysis detection limits (See Appendix A, Tables A-5. 1, A-5.2). Gross beta levels in the plant discharge water (Station 27)were above the detection limits in ten of the twelve samples. Positive results for this location are expected due to the scrubbing action of the cooling towers which incorporates atmospheric particulate material into the discharge water and the concentration of natural radioactivity in the water by evaporative loss. Historically, higher gross beta results at Station 27 have been observed during periods when CGS circulating water was maintained at higher levels of concentration.
The lower gross beta values for Station 27 during the summer months corresponds to a time period during and immediately after an outage. The Station 27 sample results are representative of the radioactivity present in plant discharge water before any mixing with river water occurs.Monthly tritium results for all plant intake, plant discharge, and river/drinking water samples were below the analysis method a priori LLD except for one plant discharge water sample. Tritium results for the three sample locations are plotted in Figure 5-7, quarterly averages for the locations are listed in Appendix A, Tables A-6. 1, A-6.2. The cause of the positive tritium activity in the March plant discharge water sample could not be identified; it is suspected that the activity was from recapture of CGS effluent tritium in the cooling water system.2013 Annual Radiological Environmental Operating Report 5-5 Energy Northwest/Columbia Generating Station Gamma spectroscopy results for all plant intake, plant discharge, and river/drinking samples showed no indication of gamma-emitting radionuclides of interest being present (See Appendix A, Tables A-7. 1, A-7.2).Tritium in Water 2013 600 500 400 300 S200 0-100 U I I 3 I I I 1 2 3 4 5 6 7 8 9 10 11 12 Month-Tritium LLD (300 pQiA) I--o- Station 26---Station 27 a Station 29 Figure 5-7 Tritium in River/Drinking ( Stations 26 & 29) and Plant Discharge Water (Station 27) for 2013 Analysis results for the plant intake, plant discharge, and river/drinking water samples showed only negligible impact to the environment due to CGS plant operations in 2013. Composite water samples are also taken from two sanitary waste sample locations and one storm drain location.
Analysis results for these samples are discussed in further detail in Section 5.9.5.3.2 Ground Water Samples from 3 deep wells were collected quarterly to meet ODCM and EFSEC Resolution No. 332(9)requirements.
Quarterly samples were also collected from ten shallow groundwater monitoring wells located near CGS as part of the CGS groundwater monitoring program. All well samples were analyzed for tritium and gamma emitting radionuclides.
Well locations sampled are shown in Figures 4-1 and 4-2.Analytical results for the three deep water wells were consistent with results seen in previous years.Tritium results were below detection limits and no gamma emitting radionuclides related to CGS operation were identified in any of the samples (See Appendix A, Tables A-6.1, A-6.2, A-7.1, and A-7.2).The CGS ground water monitoring program is conducted to meet the Nuclear Energy Institute (NEI)Groundwater Protection Initiative (NEI 07-07) (1 7) guidelines and to support NPDES requirements.
Ten shallow wells are routinely used to sample water from the unconfined aquifer around the CGS site. None of these monitoring wells are used as a source of drinking water. CGS is unique in the commercial nuclear power industry in that it is located in an area where the unconfined aquifer under the site is known to be contaminated with tritium as a result of past DOE activities on the Hanford Site.(19)
The CGS groundwater program is intended to assess any contribution CGS may be making to the known groundwater contamination issue.I I I I U I I I I I I 2013 Annual Radiological Environmental Operating Report 5-6 Energy Northwest/Columbia Generating Station Gamma Spectroscopy results for the ten shallow monitoring wells did not identify any gamma emitting radionuclides of interest(See Appendix A, Tables B- 10.1, and B- 10.2). Tritium concentrations at these locations ranged from < LLD to 15,400 pCi/liter (See Appendix A, Table B-11.1). Tritium results from each well were consistent during the year and within the trend range observed in previous years. The highest tritium concentrations were consistently measured at MW-5 which is hydraulically up-gradient of CGS. No samples were obtained from MW-7 in 2013 due to lack of water in the well. In 2011, ENW identified a possible correlation between tritium levels at the CGS storm drain pond and tritium levels at two nearby well locations (MW-7 and MW-8). Tritium results for 2013 showed a similar trend. Tritium activity in the storm drain pond is attributed to recapture of CGS effluents, see section 5.9.1 for more discussion.
No other correlations between groundwater tritium and CGS operation weire identified.
With the exception of the MW-8 tritium.results, there is no evidence that CGS operation made a measurable radiological impact on groundwater.
5.4 Soil Gamma spectroscopy analysis was performed on soil samples from 5 different locations in 2013 (See Appendix A, Tables A-8. 1, A-8.2). Two of the samples were from locations near CGS, two were from locations east of CGS in Franklin County, and one was from a control location.
Naturally occurring radionuclides (potassium-40 and bismuth- 214) were identified in all samples. Cesium-137 was identified in one of the samples near CGS. The level of cesium-137 identified was within the range historically observed in local soil samples and within the range considered normal background in Hanford area soils.(2 0'2 1 , 2 2) The cesium-137 level was well below the level that would require strontium-90 analysis to be performedi 9 1 The soil sample results indicate no measurable impact from CGS plant operation.
5.5 River Sediment Gamma spectroscopy results of river sediment identified naturally occurring radionuclides (potassium-40, bismuth- 214) and cesium-137 (See Appendix A, Tables A-9.1, 9.2). Relative to the circulating water discharge point, cesium-137 was detected in one of the upstream samples (Station 33) and both of the downstream samples (Station 34). The downstream cesium- 137 activity levels were similar to the levels identified in previous years and within the range known to be present in Hanford area sediment and soil.(2 1) Cesium-137 was not identified in any samples of plant cooling water discharged to the Columbia River. CGS has not made a radioactive discharge to the Columbia River since 1998. The sediment sample results indicate no measurable impact from CGS plant operation.
5.6 Fish The gamma spectroscopy results of fish samples identified low level cesium -137 in the anadromous fish collected from the Columbia River. The level identified was just above the analysis detection limit and substantially below the ODCM specified lower level of detection.
Cesium -137 is occasionally identified in this media and has been identified at low levels in Columbia River fish by the CGS REMP and in other studies (23) in past years. The cesium -137 is not believed to represent an impact from CGS operation.
Results of the other fish samples collected in 2013 identified only the presence of naturally occurring radionuclides (See Appendix A, Tables A-10.1, 10.2). Only two of the three ODCM required fish species were collected from both the control and indicator locations in 2013, see section 5.10 for further discussion.
2013 Annual Radiological Environmental Operating Report 5-7 Energy Northwest/Columbia Generating Station I 5.7 Milk .-.I No radioiodine activity was identified in any of the milk samples collected in 2013 (See Appendix A, Tables A- 11.1, A- 11.2). Gamma spectroscopy results of milk radionuclides other than radioiodine did not identify the presence of any radionuclides of interest. (See Appendix A, Tables A- 12.19 A- 12.2).Naturally occurring potassium-40 was identified in all milk samples.5.8 Garden Produce Garnma analysis was performed on ten different types of fruits and vegetables in 2013 (See Appendix A, Tables A-15.1, A-15.2, A-16.1, A-16.2, A-17.1, A-17.2). No radionuclides of interest were identified in any of the samples. Naturally occurring potassium-40 was identified in all samples.5.9 Special Interest Stations i Sampling and analysis is performed at the locations covered in this section to comply with EFSEC requirements or is performed at CGS initiative.
The storm drain pond and the Sanitary Waste Treatment Facility (SWTF) were incorporated into the routine sampling schedule in 1992. In 1995, the cooling tower sediment disposal area was added. TLDs were placed around the spray pond drain field (Station 120) in June 1995. TLD monitoring in the vicinity of the planned Independent Spent Fuel Storage I Installation (ISFSI) was first performed in 1998 to collect background data and TLD monitoring was established on the ISFSI fence line after construction was completed in 2002. Additional air monitoring and TLDs stations were established in 2008/2009 to monitor remediation work at the DOE 618-11 burial I ground west of CGS. Discussions of the results from each of the locations are given in the following sections.
i 5.9.1 Storm Drain Pond (Station 101)The storm drain pond (NPDES Outfall 002) is located approximately 1500 feet northeast of CGS. i Water is sent to the pond through an 18-inch diameter pipe that discharges into a 300-foot long earthen channel that leads to a 100-foot diameter pond. The pond is a shallow, unlined percolation/evaporation basin. Water at the storm drain outfall is sampled using a flow proportional automatic sampler to collect monthly composite samples. The storm drain pond area is fenced and access is restricted.
Monthly water samples were analyzed for gamma emitting radionuclides, tritium, and gross beta.Gamma spectroscopy results did not identify the presence of any gamma emitting radionuclides of interest (See Appendix A, Tables B-2.1, B-2.2). Gross beta was not positively identified in any of the monthly samples (See Appendix A, Tables B-3.1, B-3.2). Tritium was detected in eight of the twelve samples (See Appendix A, Tables B-4. 1, B-4.2). The samples with higher tritium levels were all from colder, wetter months which is consistentwith results seen in previous years. The source of the tritium in storm drain pond water is attributed to recapture of tritium from CGS gaseous effluents which is more likely to occur during cooler, rainier periods.Four soil samples were collected from the CGS storm drain pond in 2013 and analyzed for gamma emitting radionuclides.
The samples were collected from surface soil locations that were identified as having higher levels of activity in a 2011 storm drain pond soil characterization study. (24) Analysis of the 2013 samples identified many of the same radionuclides identified in the 2011 study but at levels generally lower than observed in 2011 (See Appendix A, Tables B- 12.1).3 2013 Annual Radiological Environmental Operating Report 5-8 Energy NorthwestlColumbia Generating Station I 5.9.2 Sanitary Waste Treatment Facility (Station 102)The Sanitary Waste Treatment Facility (SWTF) is located approximately 0.5 miles south-southeast of the CGS. The facility processes sanitary:
waste water from CGS, the ENW Industrial Development Complex (formerly referred to as WNP- I and WNP-4), the Kootenai Building, and the DOE 400 Area. Station 102B receives water from all these locations; Station 102A receives water only from the DOE 400 Area.Discharge standards and monitoring requirements for the SWTF are established in EFSEC Resolution No. 300.(16)Gross beta results for Station' 102B (SWTF head works) were consistent with results seen in previous years. Gross beta results for Station 102A (DOE 400 Area effluent ) showed an increase over the course of the year rising from a level of less than 10 pCi/l in'the first half of the year to greater than 20 pCi/l in November and December.
The increase is attributed to changes in the waste stream composition coming from the DOE 400 area and corresponds to decreasing discharge volumes from that facility.
The sanitary sewer line from the DOE 400 area was plugged in mid-December 2013 and ENW is no longer accepting sanitary waste from this location.
Gross alpha was not positively identified in any of the 102A or 102B samples. (See Appendix A, Tables B-5.1, B-5.2, B-6.1, B-6.2).Gamma spectroscopy results of the monthly SWTF water samples identified iodine- 131 in the January Station 102B composite sample. CR 278601 was written to document the finding. As no additional radioisotopes were identified in the sample, the source of the radioiodine was attributed to a medically administered treatment and not the result of CGS operation.
No other gamma emitting radionuclides of interest were detected in any of the other SWTF samples analyzed in' 2013 (See Appendix A, Tables B-7.1, B-7.2).Tritium activity was identified in all twelve 102A and five of the twelve 102B samples (See Appendix A, Tables B-8. 1, B-8.2). Tritium levels in the 102A samples were similar to the levels seen in previous years. The potable water used at the DOE 400 area is obtained from a groundwater well that is known to be contaminated with tritium as a result of past DOE activities on the Hanford site.(17)Tritium concentrations in the 102B sampleswere no more than 2 times the LLD of the analysis.Tritium activity in the station 102B samples is attributed to DOE 400 area discharges; 102B tritium values trending below the LLD during the second half of the year correspond to smaller discharge volumes from the DOE 400 area. Tritium levels in all sanitary waste samples remained well below the 20,000 pCi/liter action limits of EFSEC Resolution No. 300.16)SWTF water from stabilization pond B was discharged to ground in March 2013. Grab samples were taken at CGS initiative during discharge and used to create a composite sample that was analyzed for gamma isotopic and tritium content. Gamma isotopic analyses of the composite sample did not identify any radioisotopes related to CGS operation.
Tritium activity of the composite sample was determined to be 529 pCi/l. A total of 1.4 million gallons of SWTF water was discharged to ground in March 2013.2013 Annual Radiological Environmental Operating Report 5-9 Energy Northwest/Columbia Generating Station 2013 Annual Radiological Environmental Operating Report 5-9 Energy Northwest/Colunibia Generating Station 5.9.3 Cooling System Sediment Disposal Area (Station 119)EFSEC Resolution No. 299( 18) authorizes the onsite disposal of asdime nts from plant cooling systems containing low levels of radionuclides.
The disposal area for these sediments is located just south of the CGS cooling towers. EFSEC Resolution No. 299( 8) requires direct radiation monitoring using quarterly TLDs in the vicinity of the disposal cells and the collection and analysis of a dry composite sediment sample from the disposal cell within thirty days following each cleaning to confirm that the disposal criteria outlined in the resolution have not been exceeded.Cleaning of the CGS cooling towers was performed in May and October 2013. Disposal of the material removed resulted in an estimated 51.5 cubic meters of dry sediment being placed in the disposal cell.Figure 5-8 summarizes theestimated mass and radionuclide content of cooling tower sediment that was placed in the disposal area in 2013. For those isotopes listed in the table that were not positively identified, the MDA value obtained from the sample analysis was used in the table calculations.
As such, the total activity reported is a conservative estimate.In addition to cooling tower sediment, ENW performed cleaning operations of the Standby Service Water (SSW) ponds in 2013. Material removed from the SSW ponds was temporarily Stored in bags in a lined basin south of the SSW ponds. Initial characterization of the material identified cobalt -60 in the 400-3000 pCi /kg range. Transfer of the SSW sediment to the established cooling system disposal area was initiated in December 2013 and completed in January 2014. Final determination of the volume, density and radionuclide content of this material will be reported in the 2014 annual report.Figure 5-8 shows that the cooling tower sediment results were well below the disposal concentration limits specified in EFSEC Resolution No. 299." 1" Cesium -137 levels identified in 2013 were similar to levels identified in previous years and within the range normally seen in Hanford area soils. Positive identification of cobalt -60 has been made in this media in past years and at level similar to those shown in Figure 5-8.I I I I I I I I I I I I I I I I I K 2013 Cooling System Sediment Disposal Data Disposal Date May 2013 October 2013 Pit ID: 2007 Pit 2007 Pit Mass, kg ;39,720' 1,725 Density, g/cc 0.8.1 0.81 Analytical Analytical Result Result Nuclide Limit (pCi/kg) (pCi/kg). (p~i/g) Total Curies Co-60 5.OOE+03 < 3.66E+01 2.79E+02 1.94E-06 Mn-54 3.OOE+04 < 3.40E+01 <5.07E+01
< 1.4"4E7-06 Zn-65 5.00E+04 <7.62E+01
< 9.14E+01 < 3.18E-06.Cs-134 1.00E+04 <3.56E+01
< 5.99E+01 <1.52E-06 Cs-137 2.00E+04 1.91E+02 2.91E+02 8.09E-06 1.62E-05 Figure 5-8 Cooling System Sediment Activity Levels For Disposals Made In 2013 2013 Annual Radiological Environmental Operating Report 5-10 Energy Northwest/Columbia Generating Station Measurements of direct radiation at the disposal pit area was taken using TLDs. Two locations were used, an indicator location next to the collection area (Station 1199B) and a control location approximately 100 yards to the east (Station 119C). The mean quarterly TLD results agree well with results from previous operational years. The negligible difference between the indicator and the control TLDs indicate that there was no measureable dose contribution above background due to material in the disposal cells.(See Tables 5.3 and Appendix A, Tables B-1.1).5.9.4 Spray Pond Drain Field (Station 120)There were no discharges to the Spray Pond Drain Field (NPDES Outfall 003) in 2013. The TLD results at Station 120 in 2013 are in agreement with those seen in previous operational years (See Table 5-3 and Appendix A, Tables B- 1.1).5.9.5 Independent Spent Fuel Storage Installation The Independent Spent Fuel Storage Installation (ISFSI) is a fenced, secured area north northwest of CGS. Ten TLD stations, stations 123-129 and stations 136A-138A, are located on the second of three security fences that surround the ISFSI. TLD station 122 is just north of the ISFSI between the ISFSI and the plant access road. TLD station 121 is located approximately 0.1 mile north of the plant between the Transformer Yard and the ISFSI. Refer to Figure 4-4 for ISFSI TLD locations.
Radiological exposure rates inside the ISFSI security fence line are elevated and access to the area requires radiological dosimetry and security notification.
In addition to the TLD monitoring program, quarterly radiological surveys of the ISFSI are conducted by the CGS Radiation Protection Department.
Trend of Exposure Rates at ISFSI Fence Line 2.6 2.2 E 1.4-1.0_'07 'QO '07&#xfd; 9? 'Q ? 'QO 7 9O V7 'QO 'Q' 'QO V7~ '9? V 'QO 'Q' '9? V 'Q 'Q?'0 '9? IQ 'PO---a-125 ---126 --127 128 --o-129 -+/-:136A .. -137A -138A -o-123 &124 Figure 5-9 ISFSI TLD Trend at CGS 2013 Annual Radiological Environmental Operating Report 5-11 Energy Northwest/Columbia Generating Station No new spent fuel or additional storage casks. were added to::the ISFSI during 2013. As shown in Figure 5-9, exposure rates at the ISFSI fence line have followed a downward trend since 2008.Station 122 TLD results show a similar pattern with the long term trend for this location correlating to the overall ISFSI TLD trend but at a lower level. Station 12 1 TLD trend results show large decreases during periods when CGS was shut down; this location has historically been influenced more by. turbine building radiation levels than by the ISFSI (See Table 5-3 and Appendix A, Tables B-1. 1, 13-1.2).5.9.6 Additional Air Sample and TLD Locations Four air sample locations (Stations 87-90) and 5 TLD stations (Stations 58, 87-90) were established in 2008/2009 in order to monitor air quality and direct radiation during remediation work at the DOE 618-11 burial ground located just west of CGS (See Figure 4-1). No air samples were taken from these locations in 2013 as no work was performed at the 618-11 site that had the potential of impacting CGS.Quarterly TLDs were exchanged at all five locations in 2013. Three of the TLD stations (stations 87-89)had results higher than background due to the stations close proximity to the turbine building (See Appendix A, Table B- 1.1).5.10 2013 Sample Deviations A summary of REMP sample deviations encountered during 2013 is listed below in Table 5-1 a. All known deviations from the sampling schedule (i.e. sample was not obtained) or analyses where the ODCM specified lower limit of detection was not achieved are included.
For locations where composite or continuous samples are collected, any known period greater than 24 hours during which samples were not collected have been included.
Not all locations listed in Table 5-1a are required by the ODCM or EFSEC resolutions.
Table 5-lb lists information regarding air sample station sampling requirements.
TABLE 5-1a REMP Sample Deviations for 2013 I I I I I I I I I I I I I I I I I 5 I SAMPLE DATE LOCATION CR ID PROBLEM / COMMENTS MEDIA 4/3/13 to [Pump found off with blown fuse, station OOS for- 6 Air Sampler 4/9/13 Station 1 282272 days. Station returned to service after pump replaced.INo sample collected, LLD requirements not met.5/29/13 Station OOS for -25 hours due to power outage.Air Sampler to Station 57 286627 Station back in service when power restored.
Sufficient 5/30/13 sample volume obtained to meet LLD.7/14/13 Pump found off with blown fuse, Station OOS for -41 Air Sampler to Station 48 290058 hours. Fuse replaced, pump restarted.
Sufficient 7/16/13 sample volume obtained to meet LLD.8/19/13 Station OOS for -9.5 days due to power outage. No Air Sampler to Station 23 292376 sample collected or LLD meet week of 8/20 to 8/27.8/28/13 Station back in service after power restored.2013 Annual Radiological Environmental Operating Report 5-12 Energy Northwest/Columbia Generating Station TABLE 5-1a (cont)REMP Sample Deviations for 2013 SAMPLE DATE LOCATION CR ID PROBLEM / COMMENTS MEDIA 1/14/.13 Composite sampler OOS for -24 hours during planned Water to Station 29 277478 maintenance activities.
Sampler returned to service and 1/15/13 1 verified operable.Circ water blow down samplers CBD-SR- 1 and 2 inoperable due to no signal from CW-LCV-1, blow 284853 down performed using temporary pumps. Daily grab 5/13/13 285305 samples taken 5/20 to 5/25. CBD-SR-1 and 2 declared Water to Station 27 285021 operational 5/25 following logic circuit modification.
5/31/13 286652 On 5/31, samplers determined not to be functional due to no valid flow indication signal and samplers -in proportional mode. Samplers placed in timed mode and verified operable on 5/31.On 7/8, TMU-SR-1 determined to have been OOS since 6/30 when sample supply pump was taken out of.288978 service. Daily grab samples taken 7/10 to 7/15. A 6/30/13 289504 temporary sampler was installed on 7/12 and Water to Station 26 291368 continuous composite sampling initiated.
Temporary 7/12/13 294453 composite sampler in service until 1'2/9/13.
TMU-SR-1 297177 returned to service on 12/7/13 following adjustments to samplesupply pump. Procedure revised to identify PWC-P-5 supplies water to TMU-SR- 1.9/2/13 In service Circ. water blow down sampler CBD-SR-1 Water 921 Statdeclared non-functional on 9/3. CBD-SR-2 placed in Wtrto Station 27 293107 service and verified operational.
Samplers estimated to 9/3/13 have been OOS for 30 hours..9/29/13 LCO Circ water blow down samplers CBD-SR-1 and 2 Wtro9 St 2 LCO declared non-functional due to planned power outage.Water to 1 Station 27 Log Samplers returned to service and verified operable 10/3/13 16673 when power restored.
Sample racks OOS for 74 hours.TMU temporary composite water sampler found 11/20/13 without power on 11/25, sampler last confirmed Water to Station 26 298462 operational on 11/20. Investigation found GF1C circuit 11/26/13 was tripped. Power restored and sampler verified-operable.
Only 2 of the 3 required fish species were obtained Stations 30 from the control and indicator locations.
ENW was not Fish Annual 300634 permitted to use electroshock fishing techniques in and 38 2013. Permission to electroshock or other means of fish collection is to be investigated.
.7/1/13 All Environmental TLDs were exchanged 2 weeks late due TLD to ll 289107 to issue obtaining TLDs from vendor. Contract issues 7/17/13 Locations
.causing delay resolved.2013 Annual Radiological Environmental Operating Report 5-13 Energy Northwest/Columbia Generating Station Table 5-lb below shows the percent time in service for the 12 air sample locations.
The table shows that overall availability was greater than 99% for all ODCM required locations.
TABLE 5-1b CGS REMP Air Sample Percent in Service Time for 2013 Station ID ODCM Required EFSEC Required Percent Time in Service 1 x 98.2%4 x x 99.8%5 99.8%6 x 99.9%7 x 99.8%8 x x 99.9%9 x x 99.9%21 99.7%23 x 97.2%40 x x 99.8%48 x x 99.2%57 x 99.6%I I I I I I I I I I I I U i I i I i I 2013 Annual Radiological Environmental Operating Report 5-14 Energy Northwest/Columbia Generating Station TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 mR/std.Medium: Environmental Direct Radiation TLD) Units: quarter Location With Highest Annual Total Lower Limit of Indicator Locations Mean Control Locations Number of Analysis Type Analyses Detection Mean (f)a Location Mean (f)a Mean (f)' Nonroutine Performed (LLD) Range Location Man Range Measurements Information .Range TLD Quarterly 228 21.5 (224 / 224) 86 27.9 (4/4) 20.5 (4/4) 0 (18.2-29.7)
 
NNW 0.3 miles (26.0-29.7)
COLUMBIA GENERATING STATION                                                         DOCKET NO. 50-397 Benton County, Washington                                                           Calendar Year 2013 mR/std.
(18.9-21.7)
Medium: Environmental Direct Radiation TLD)                                           Units: quarter Location With Highest Annual Total     Lower Limit of Indicator Locations               Mean                 Control Locations     Number of Analysis Type     Analyses     Detection         Mean (f)a           Location         Mean   (f)a       Mean (f)'       Nonroutine Performed       (LLD)             Range             Location Information        Man
: a. (f) is the number of positive measurements I total measurements at specified location.Reference Appendix A, Tables A-1.1, A-1.2 TABLE 5-2 (cont)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
                                                                                        .Range Range        Measurements TLD Quarterly         228                       21.5 (224 / 224)           86           27.9 (4/4)       20.5 (4/4)             0 (18.2-29.7)     NNW 0.3 miles       (26.0-29.7)       (18.9-21.7)
: a. (f) is the number of positive measurements I total measurements at specified location.
Reference Appendix A, Tables A-1.1, A-1.2 TABLE 5-2 (cont)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 mR/std.Medium: ISFSI Direct Radiation (TLD) Units: quarter Indicator Location With Highest Annual Total Lower Limit Mean Control Locations Number of Analysis Type Analyses of Detection Locations Mean (f)- Nonroutine Performed (LLD) Range Information Range Range Measurements 109.9 (40 / 40) 137A 146.4(4/4)  
 
--- (0/0)TLD Quarterly 401 (67.9-148.3)
COLUMBIA GENERATING STATION                                                         DOCKET NO. 50-397 Benton County, Washington                                                           Calendar Year 2013 mR/std.
NNW 0.24 miles (142.1-148.3)
Medium: ISFSI Direct Radiation (TLD)                                                 Units: quarter Indicator       Location With Highest Annual Total       Lower Limit                                   Mean                 Control Locations     Number of Analysis Type       Analyses     of Detection       Locations                                             Mean (f)-       Nonroutine Performed       (LLD)           Range           Information         Range             Range         Measurements 109.9 (40 / 40)         137A           146.4(4/4)         --- (0/0)
: a. (f) is the number of positive measurements  
TLD Quarterly         401                       (67.9-148.3)   NNW 0.24 miles     (142.1-148.3)
/ total measurements at specified location.Reference Appendix A, Tables B-1.1, B-1.2 ISFSI TLDs are Stations 123 to 129 and 136A to138A 2013 Annual Radiological Environmental Operating Report 5-15 Energy Northwest/Columbia Generating Station TABLE 5-2 (cont)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
: a. (f) is the number of positive measurements / total measurements at specified location.
Reference Appendix A, Tables B-1.1, B-1.2 ISFSI TLDs are Stations 123 to 129 and 136A to138A 2013 Annual Radiological Environmental Operating Report         5-15                     Energy Northwest/Columbia Generating Station
 
U I
TABLE 5-2 (cont)
I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: Air Particulate/Air Radioiodine Units: PCi/m 3 Indicator Location With Highest Annual Mean Total Lower Limit Control Locations Number of Analysis Analyses of Detection Locations (f)a Mean (f)' Nonroutine Type Performed (LLD)' Mean (f n Location Meange Range Measurements Range Information Range 4 0.0218 (570/570)
 
S 0.0239 (52/52) 0.0189(52/52)
COLUMBIA GENERATING STATION Benton County, Washington DOCKET NO. 50-397 Calendar Year 2013 I
Gross Beta 622 0.01 (0.00299-0.139)
Medium: Air Particulate/Air Radioiodine Total      Lower Limit Indicator Units: PCi/m Location With Highest Annual Mean 3
SSE 9.57 miles (0.00409 -0.125) (0.00322 -0.106)1-131 622 0.07 --- (0 / 570) --- --- (0 / 52) 0 Cs-134 48 0.05 --- (0/44) --- ---(0/4) 0 Cs-137 48 0.06 --- (0/44) --- (0/4) 0 a. (f) is the number of positive measurements  
Control Locations   Number of I
/ total measurements at specified location.b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.Reference Appendix A, Tables A-2.1, A-2.2, Tables A-3.1, A-3.2, and Tables A- 4.1, A-4.2.U I I I I I I I I I I 1 I I I I I I I 2013 Annual Radiological Environmental Operating Report 5-16 Energy Northwest/Columbia Generating Station TABLE 5-2 (cont)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
Analysis     Analyses   of Detection     Locations                                   (f)a           Mean (f)'       Nonroutine Type       Performed       (LLD)'         Mean (f         nLocation I
Meange                 Range       Measurements Range         Information         Range 4
0.0218 (570/570) S                   0.0239 (52/52)         0.0189(52/52)
Gross Beta       622           0.01     (0.00299-0.139) SSE 9.57 miles     (0.00409 - 0.125)
I (0.00322 - 0.106) 1-131         622           0.07       --- (0 / 570)         ---                                 --- (0 / 52)         0 Cs-134           48           0.05         --- (0/44)                             ---               --- (0/4)           0 I
Cs-137           48           0.06         --- (0/44)                                                 --- (0/4)           0
: a. (f) is the number of positive measurements / total measurements at specified location.
: b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.
I Reference Appendix A, Tables A-2.1, A-2.2, Tables A-3.1, A-3.2, and Tables A- 4.1, A-4.2.
I I
1 I
I I
I I
I 2013 Annual Radiological Environmental Operating Report       5-16                       Energy Northwest/Columbia Generating Station I
 
TABLE 5-2 (cont)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
COLUMBIA GENERATING.
 
STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: Water-River/Drinking Units: pCi/L Total Lower Limit Indicator Location With Highest Annual Mean Analysis Analyses of Detection Locations Control Locations Number of Type Performed (LLD)'c Mean (f)0 Location Mean (f)R Mea surem Range Information Range Range Measurements Gross Beta 24 4.0 --- (0 / 24) -b) --- --- (0/12) 0 H-3 8 2000 --- (0 8)(b) ---- --- (0/4) 0 Mn-54 24 15 --- (0/2 4)(b) --- (0/12) 0 Fe-59 24 30 --- (0/2 4)(b) --- --- (0/12) 0 Co-58 24. 15 --- (0/ 2 4)(b- --- ---(0 / 12) 0 Co-60 24 15 --- (0/2 4)(b) ---(0/12) 0 Zn-65 24 30 --- (0/2 4)(b) ---(0/12) 0 Zr/Nb-95 24 15 --- (0 / 2 4)(b) --- --- (0 / 12) 0 Cs-134 24 15 --- (0 / 2 4)(b) --- --- (0 / 12) 0 Cs-137 24 18 --- (0/2 4) b) --- --- (0 / 12) 0 Ba/La-140 24 15 --- (0 / 2 4) (b) --- --- (0 / 12) 0 a. (f) is the number of positive measurements  
COLUMBIA GENERATING. STATION                                                         DOCKET NO. 50-397 Benton County, Washington                                                           Calendar Year 2013 Medium: Water-River/Drinking                                                               Units: pCi/L Total     Lower Limit       Indicator       Location With Highest Annual Mean Analysis       Analyses   of Detection       Locations                                             Control Locations     Number of Type       Performed       (LLD)'c       Mean (f)0           Location         Mean (f)R                   Mea       surem Range           Information         Range               Range         Measurements Gross Beta         24           4.0       --- (0 / 24)               -b)             ---             --- (0/12)             0 H-3             8           2000         --- (0   8 )(b)         -               ---             --- (0/4)             0 Mn-54           24           15         --- (0/   24  )(b)                                         --- (0/12)             0 Fe-59           24           30         --- ( 0 / 2 4 )(b)                         ---             --- (0/12)             0 Co-58           24.           15         --- (0/   24  )(b-                         ---             --- (0 / 12)           0 Co-60           24           15         --- ( 0 / 2 4 )(b)                                         --- (0/12)             0 Zn-65           24           30         --- ( 0 / 2 4 )(b)                                         --- (0/12)             0 Zr/Nb-95         24           15         --- (0 / 2 4 )(b)                 ---                     --- (0 / 12)           0 Cs-134           24           15         --- (0 / 2 4 )(b)                           ---             --- (0 / 12)           0 Cs-137           24           18         --- (0/   24  ) b)                         ---             --- (0 / 12)           0 Ba/La-140         24           15         --- (0 / 2 4 ) (b)                         ---             --- (0 / 12)           0
/ total measurements at specified location.b. This includes the control sample for this group; the control (Station 26) is also a drinking water sample.c. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.Reference Appendix A, Tables A-5.1,A-5.2, Tables A-6.1, A-6.2, and Tables A-7.1, A-7.2 2013 Annual Radiological Environmental Operating Report 5-17 Energy Northwest/Coluinbia Generating Station TABLE 5-2 (cont)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
: a. (f) is the number of positive measurements / total measurements at specified location.
: b. This includes the control sample for this group; the control (Station 26) is also a drinking water sample.
: c. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.
Reference Appendix A, Tables A-5.1,A-5.2, Tables A-6.1, A-6.2, and Tables A-7.1, A-7.2 2013 Annual Radiological Environmental Operating Report             5-17                     Energy Northwest/Coluinbia Generating Station
 
TABLE 5-2 (cont)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: Water-Discharge Units: pCi/L Indicator Location With Highest Annual Mean Analysis Total Lower Limit Locations Control Locations Number of Type Analyses of Detection a Location Mean (0a Mean (f)0 Nonroutine RPerformed (LLD) b ange Information Range Range Measurements Gross Beta 12 4.0 5.83 (10 /12) 27 5.83 (10 /12) ---(0/0) 0 (1.2-11.8)
 
E 3.2 miles (1.2-11.8))
COLUMBIA GENERATING STATION                                                         DOCKET NO. 50-397 Benton County, Washington                                                           Calendar Year 2013 Medium: Water-Discharge                                                                   Units: pCi/L Indicator     Location With Highest Annual Mean Analysis         Total     Lower Limit       Locations                                             Control Locations   Number of Type         Analyses   of Detection               a         Location           Mean (0a             Mean (f)0       Nonroutine (LLD) b         RPerformed ange       Information         Range                 Range       Measurements Gross Beta           12           4.0       5.83   (10 /12)
H-3 4 2000 --- (0/4) --- ---(0/0) 0 Mn-54 12 15 --- (0/12) --- --- (0/0) 0 Fe-59 12 30 --- (0/12) ---- ---(0/0) 0 Co-58 12 15 --- (0/12) --. --- (0/0) 0 Co-60 12 15 --- (0/12) --- ---(0/0) 0 Zn-65 12 30 --- (0/12) --- --- ---(0/0) 0 Zr/Nb-95 12 15 --- (0 / 12) --- --- ---(0/0) 0 Cs-134 12 15 ---(0/12) --- --- (0/0) 0 Cs-137 12 18 --- (0/12) --- --- ---(0/0) 0 Ba/La-140 12 15 --- (0/12) 1- ...--- (0/0) 0 a. (f) is the number of positive measurements  
(1.2-11.8)     E 3.227miles      5.83  (10 /12)
/ total measurements at specified location.b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.Reference Appendix A, Tables A-5.1,A-5.2, Tables A-6.1, A-6.2, and Tables A-7.1, A-7.2 2013 Annual Radiological Environmeniat Operating Report 5-18 Energy Northwest/Columbia Generating Siation 2013 Annual Radiological Environmental Operating Report 5-18 Energy Northwest/Columbia Generating Station TABLE 5-2 (cont)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
(1.2-11.8))           ---(0/0)              0 H-3           4           2000           --- (0/4)                               ---             --- (0/0)             0 Mn-54           12           15         --- (0/12)                               ---             --- (0/0)             0 Fe-59           12           30         --- (0/12)               -   ---                         --- (0/0)             0 Co-58           12           15         --- (0/12)                               --.             --- (0/0)             0 Co-60           12           15         --- (0/12)                     ---                         --- (0/0)             0 Zn-65           12           30         --- (0/12)             ---               ---             --- (0/0)             0 Zr/Nb-95           12           15         --- (0 / 12)           ---               ---             --- (0/0)             0 Cs-134           12           15         --- (0/12)                               ---             --- (0/0)             0 Cs-137           12           18         --- (0/12)             ---               ---             --- (0/0)             0 Ba/La-140         12             15         --- (0/12)             ...---                       1-        (0/0)             0
: a. (f) is the number of positive measurements / total measurements at specified location.
: b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.
Reference Appendix A, Tables A-5.1,A-5.2, Tables A-6.1, A-6.2, and Tables A-7.1, A-7.2 Report       5-18                       Energy Northwest/Columbia Generating Siation 2013 2013 Annual                 Environmeniat Operating Radiological Environmental Annual Radiological                Operating Report         5-18                       Energy Northwest/Columbia Generating Station
 
TABLE 5-2 (cont)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: Water- Deep Ground Units: pCi/L Location With Highest Annual Mean Total Lower Limit Indicatorns Analysis Aaye ofettin Locations.CotoLoain Nubrf Type Analyses of Detection Mean (f Location Mean (f)0 Mean (f)' Nonroutine Performed (LLD)b Range Information Range Range Measurements H-3 12 2000 --- (0/12) --- -(0 /0) 0 Mn-54 12 15 --- (0/12) --- --- (0/0) 0 Fe-59 12 30 ---(0/12) --- (0/0) 0 Co-58 12 15 --- (0/12) --- (0/0) 0 Co-60 12 15 --- (0/12) ------ (0/0) 0 Zn-65 12 30 --- (0/12) --- --- (0/0) 0 Zr/Nb-95 12 15 ---(0/12) --- (0/0) 0 Cs-134 12 15 --- (0/12) --- --- --- (0/0) 0 Cs-137 12 18 --- (0/12) ---(0 / 0) 0 Ba/La-140 12 15 --- (0 / 12) ---(0 / 0) 0 a. (f) is the number of positive measurements  
 
/ total measurements at specified location.b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.Reference Appendix A, Tables A-6.1, A-6.2, and Tables A-7.1, A-7.2 2013 Annual Radiological Environmental Operating Report 5-19 Energy North~vest./Columbia Generating Station 2013 Annual Radiological Environmental Operating Report 5-19 Energy Northwest/Columbia Generating Station TABLE 5-2 (cont)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
COLUMBIA GENERATING STATION                                                           DOCKET NO. 50-397 Benton County, Washington                                                           Calendar Year 2013 Medium: Water- Deep Ground                                                                 Units: pCi/L Location With Highest Annual Mean Analysis      Aaye Total     ofettin Lower Limit     Locations.CotoLoain Indicatorns                                                                Nubrf Analyses     of Detection       Mean (f         Location         Mean (f)0             Mean (f)'         Nonroutine Type Performed       (LLD)b           Range         Information         Range                   Range         Measurements H-3           12           2000         --- (0/12)           ---                                   - (0 /0)             0 Mn-54           12             15         --- (0/12)           ---                                   ---(0/0)               0 Fe-59           12             30         --- (0/12)                                                 --- (0/0)               0 Co-58           12             15         --- (0/12)                                                 --- (0/0)               0 Co-60           12             15         --- (0/12)                             ------                 (0/0)               0 Zn-65           12             30         --- (0/12)           ---                                 --- (0/0)               0 Zr/Nb-95           12             15         --- (0/12)                                                 --- (0/0)               0 Cs-134           12             15         --- (0/12)           ---             ---                 --- (0/0)               0 Cs-137           12             18         --- (0/12)                                                 --- (0 / 0)             0 Ba/La-140           12             15         --- (0 / 12)                                               --- (0 / 0)             0
: a. (f) is the number of positive measurements / total measurements at specified location.
: b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.
Reference Appendix A, Tables A-6.1, A-6.2, and Tables A-7.1, A-7.2 Report     5-19                       Energy North~vest./Columbia Generating Station 2013 Annual 2013                        Environmental Operating Radiological Environmental Annual Radiological                Operating Report       5-19                       Energy Northwest/Columbia Generating Station
 
TABLE 5-2 (cont)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
COLUMBIA GENERATING STATION. DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: Water- Shallow Ground Units: pCi/L Location With Highest Annual Mean Total Lower Limit Indicator Control Locations Number of Analysis Analyses of Detection  
 
.. Locations Type Performed (LLD) b LoMean (f )ean (f)R Mean (f) M Nonroutine Range Information Range Range Measurements H-3 40 2000 3777.7 (35 / 40) MW-5 15,100 (4/4) --- (0/0) 0 (177-15,420)
COLUMBIA GENERATING STATION.                                                     DOCKET NO. 50-397 Benton County, Washington                                                         Calendar Year 2013 Medium: Water- Shallow Ground                                                           Units: pCi/L Location With Highest Annual Mean Total       Lower Limit     Indicator                                           Control Locations   Number of Analysis     Analyses   of Detection .. Locations Type       Performed       (LLD) b                         LoMean (f         )ean   (f)R         Mean Range        Information          Range              Range(f)     M Nonroutine Measurements H-3           40           2000     3777.7 (35 / 40)       MW-5           15,100 (4/4)           --- (0/0)             0 (177-15,420)     SW 0.43 miles     (14,900-15,400)
SW 0.43 miles (14,900-15,400)
Mn-54           40           15         --- (0/40)           ---               ---               --- (0/0)             0 Fe-59           40           30         --- (0 /40)         ---                                 --- (0/0)             0 Co-58           40           15         --- (0/40)           ---               ---               --- (0/0)             0 Co-60           40.           15         --- (0/40)           ---               ---               --- (0/0)             0 Zn-65           40           30         --- (0/40)           ---               ---               --- (0/0)             0 Zr/Nb-95         40           15         --- (0/40)           ------                                 (0/0)             0 Cs-134           40           15         --- (0/40)           ---               ---               --- (0/0)             0 Cs-137           40           18         --- (0/40)           ---               ---               --- (0/0)             0 Ba/La-140         40           15         --- (0/40)           ---               ---               --- (0/0)             0
Mn-54 40 15 --- (0/40) --- --- --- (0/0) 0 Fe-59 40 30 --- (0 /40) --- ---(0/0) 0 Co-58 40 15 --- (0/40) --- --- --- (0/0) 0 Co-60 40. 15 --- (0/40) --- --- --- (0/0) 0 Zn-65 40 30 --- (0/40) --- --- --- (0/0) 0 Zr/Nb-95 40 15 --- (0/40) ------ (0/0) 0 Cs-134 40 15 --- (0/40) --- --- --- (0/0) 0 Cs-137 40 18 --- (0/40) --- --- --- (0/0) 0 Ba/La-140 40 15 --- (0/40) --- --- --- (0/0) 0 a. (f) is the number of positive measurements  
: a. (f) is the number of positive measurements / total measurements at specified location.
/ total measurements at specified location.b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.Reference Appendix A, Tables B-10.1, B-10.2, and B-11.1.2013 Annual Radiological Environmental Operating Report 5-20 Energy Northwest/Columbia Generating Station TABLE 5-2 (cont)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
: b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.
Reference Appendix A, Tables B-10.1, B-10.2, and B-11.1.
2013 Annual Radiological Environmental Operating Report       5-20                       Energy Northwest/Columbia Generating Station
 
TABLE 5-2 (cont)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: River Sediment Units: pCi/kg Indicator Location With Highest Annual Mean Total Lower Limit Control Locations Number of AnalysisLocations Analysis Analyses of Detection Mean (f]I Nonroutine Type Performed (LLD) b Mean (f)M Location Mean (f)a Range Measurements Range Information Range Cs-134 4 150 --- (0/2) ---- (0/2) 0 Cs-137 4 180 121 (2/2) 34 121 (2/2) 42.2(1/2) 0 (121-122)
 
ESE 3.32 Miles (121-122)
COLUMBIA GENERATING STATION                                                       DOCKET NO. 50-397 Benton County, Washington                                                         Calendar Year 2013 Medium: River Sediment                                                                 Units: pCi/kg Indicator     Location With Highest Annual Mean AnalysisLocations Total       Lower Limit                                                         Control Locations   Number of Analysis     Analyses of Detection                                                                 Mean (f]I       Nonroutine Type       Performed       (LLD) b       Mean (f)M       Location           Mean (f)a             Range         Measurements Range         Information         Range Cs-134           4           150         --- (0/2)             -                                 --- (0/2)             0 Cs-137           4           180       121 (2/2)             34           121 (2/2)           42.2(1/2)             0 (121-122)     ESE 3.32 Miles       (121-122)           (34.6-49.8)
(34.6-49.8)
Co-60           4             ---       --- (0/2)           ---                                 --- (0/2)             0
Co-60 4 --- --- (0/2) --- ---(0/2) 0 a. (f) is the number of positive measurements  
: a. (f) is the number of positive measurements / total measurements at specified location.
/ total measurements at specified location.b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.Reference Appendix A, Tables A-9.1, A-9.2.2013 Annual Radiological Environmental Operating Report 5-21 Energy Northwest/Columbia Generating Station TABLE 5-2 (cont) .RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
: b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.
Reference Appendix A, Tables A-9.1, A-9.2.
2013 Annual Radiological Environmental Operating Report       5-21                       Energy Northwest/Columbia Generating Station
 
I I
TABLE 5-2 (cont) .
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calender Year 2013 Medium: Roots Units: pCi/kg Indicator Location With Highest Annual Mean Total Lower Limit Idcator Control Locations Number of Analysis Analyses of Detection L Mean (f)a Nonroutine Type Performed (LLD) b Mean (f)' Location Mean (f)I Range Measurements Range Information Range 1-131 6 60 --- (0/5) ---....---
 
(0/1) 0 Cs-134 6 60 ---(0/5) --- --- ---(0/1) 0 Cs-137 6 80 --- (0/5) --- (0/1) 0 a. (f) is the number of positive measurements  
I COLUMBIA GENERATING STATION                                                         DOCKET NO. 50-397 Benton County, Washington                                                           Calender Year 2013                 I Medium: Roots                                                                           Units: pCi/kg Analysis        Total Analyses    Lower Limit of Detection Indicator Idcator L
/ total measurements at specified location.b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.Reference Appendix A, Tables A-15.1, A-15.2.TABLE 5-2 (cont)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
Location With Highest Annual Mean Control Locations Mean (f)a         Number of Nonroutine I
Type       Performed     (LLD) b     Mean (f)'           Location         Mean (f)I               Range       Measurements 1-131           6           60 Range
                                              --- (0/5)
Information Range (0/1)             0 I
Cs-134           6           60         --- (0/5)             ---               ---               --- (0/1)             0       i Cs-137           6           80         --- (0/5)             ---                                     (0/1)             0
: a. (f) is the number of positive measurements / total measurements at specified location.                                               I
: b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.
Reference Appendix A, Tables A-15.1, A-15.2.
TABLE 5-2 (cont)
I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: Fruits Units: pCi/kg Location With Highest Annual Mean Total Lower Limit ndcator Control Locations Number of Analyses of Detection Locations Type Performed (LLD) b Mean (f)0 Location Mean (f)g Mean (f) M Nonroutine Range Information Range Range Measurements 1-131 9 60 --- (0/8) --- --- --- (0/1) 0 Cs-134 9 60 --- (0/8) --- --- ---(0/1) 0 Cs-137 9 80 --- (0/8) ..--- --- (0/1) 0 a. (f) is the number of positive measurements  
 
/ total measurements at specified location.b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.Reference Appendix A, Table A-16.1, A-16.2.I I I I I I i I I I i I I I I I I I I 2013 Annual Radiological Environmental Operating Report 5-22 Energy Northwest/Columbia Generating Station TABLE 5-2 (cont)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
COLUMBIA GENERATING STATION Benton County, Washington DOCKET NO. 50-397 Calendar Year 2013 I
Medium: Fruits                                                                           Units: pCi/kg Location With Highest Annual Mean i
Total     Lower Limit     ndcator                                               Control Locations     Number of Type        Analyses Performed    of Detection (LLD) b     Mean (f)0Locations Location Range          Information Mean (f)g Range Mean (f)
Range MNonroutine Measurements   I 1-131 Cs-134 9
9 60 60
                                              --- (0/8)
                                              --- (0/8)
                                                                                                          --- (0/1)
                                                                                                          --- (0/1) 0 0
I Cs-137           9           80         --- (0/8)                 ..---
: a. (f) is the number of positive measurements / total measurements at specified location.
                                                                                                          --- (0/1)              0 I
: b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.
Reference Appendix A, Table A-16.1, A-16.2.                                                                                             I I
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2013 Annual Radiological Environmental Operating Report         5-22                       Energy Northwest/Columbia Generating Station I
 
TABLE 5-2 (cont)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: Vegetables and Vegetation Units: pCi/kg Location With Highest Annual Mean Analysis Total Lower Limit Indicator Locations Control Locations Number of Type Analyses of Detection Mean (f)a Location Mean (f)' Mean (f)a Nonroutine Performed (LLD) b Range Information Range Range Measurements 1-131 12 60 --- (0/11) --- (0/1) 0 Cs-134 12 60 ---(0/11) --- --- ---(0/1) 0 Cs-137 12 80 ---(0/11) --- (0/1) 0 a. (f) is the number of positive measurements  
 
/ total measurements at specified location.b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.Reference Appendix A, Table A-17.1, A-17.2.TABLE 5-2 (cont)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
COLUMBIA GENERATING STATION                                                         DOCKET NO. 50-397 Benton County, Washington                                                           Calendar Year 2013 Medium: Vegetables and Vegetation                                                         Units: pCi/kg Location With Highest Annual Mean Analysis       Total       Lower Limit Indicator Locations                                         Control Locations   Number of Type       Analyses   of Detection       Mean (f)a         Location         Mean (f)'             Mean (f)a       Nonroutine Performed       (LLD) b           Range         Information         Range                   Range       Measurements 1-131         12             60         --- (0/11)                                                 --- (0/1)           0 Cs-134           12             60         --- (0/11)             ---             ---                 --- (0/1)           0 Cs-137           12             80         --- (0/11)                                                 --- (0/1)           0
: a. (f) is the number of positive measurements / total measurements at specified location.
: b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.
Reference Appendix A, Table A-17.1, A-17.2.
TABLE 5-2 (cont)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: Fish Units: pCilkg Location With Highest Annual Mean Analysis Total Lower Limit Indicator Locations Control Locations Number of Type Analyses of Detection Mean (f)' Location Mean (f)a Mean (f) Nonroutine Performed (LLD) b Range Range Measurements (LDbInformation Range Mn-54 4 130 --- (0/2) --- (0/2) 0 Fe-59 4 260 --- (0/2) --- --- --- (0/2) 0 Co-58 4 130 --- (0/2) --- --- --- (0/2) 0 Co-60 4 130 --- (0/2) --- --- --- (0/2) 0 Zn-65 4 260 --- (0/2) --- --- (0/2) 0 Cs-134 4 130 --- (0/2) --- --- ---(0/2) 0 Cs-137 4 150 10.6(1/2) 30 10.6(1/2)  
 
--- (0/2) 0 (2.19-19.1)
COLUMBIA GENERATING STATION                                                         DOCKET NO. 50-397 Benton County, Washington                                                           Calendar Year 2013 Medium: Fish                                                                               Units: pCilkg Location With Highest Annual Mean Analysis       Total       Lower Limit Indicator Locations                                       Control Locations     Number of Location         Mean (f)a             Mean (f)       Nonroutine Type        Analyses Performed   of (LLD)
E 3.5 miles (2.19-19.1)
Detection        Range(f)'
: a. (f) is the number of positive measurements  
Mean b (LDbInformation                              Range                 Range       Measurements Mn-54           4           130           --- (0/2)                                                 --- (0/2)             0 Fe-59           4           260           --- (0/2)             ---             ---                 --- (0/2)           0 Co-58           4           130           --- (0/2)             ---               ---               --- (0/2)           0 Co-60           4           130           --- (0/2)             ---             ---                 --- (0/2)           0 Zn-65           4           260           --- (0/2)             ---                                 --- (0/2)           0 Cs-134           4             130           --- (0/2)             ---             ---                 --- (0/2)           0 Cs-137           4             150         10.6(1/2)             30           10.6(1/2)             --- (0/2)           0 (2.19-19.1)       E 3.5 miles     (2.19-19.1)
/ total measurements at specified location.b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.Reference Appendix A, Table A-10.1, A-10.2.2013 Annual Radiological Environmental Operating Report 5-23 Energy Northwest/Columbia Generating Station TABLE 5-2 (cont)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
: a. (f) is the number of positive measurements / total measurements at specified location.
: b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.
Reference Appendix A, Table A-10.1, A-10.2.
2013 Annual Radiological Environmental Operating Report         5-23                       Energy Northwest/Columbia Generating Station
 
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TABLE 5-2 (cont)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: Milk Units: pCi/L Location With Highest Annual Mean Total Lower Limit Indicator Locationst Control Locations Number of Analysis Analyses of Detection Man ( Mean Nonroutine Type Aaye ofDtcin Ma(f Location Mean (f age Masrmet Performed (LLD) b Range oationRange Measurements Information Range 1-131 36 1.0 --- (0/18) --- (0/18) 0 Cs-134 36 15 --- (0/18) --- --- --- (0/18) 0 Cs-137 36 18 --- (0/ 18) --- --- --- (0/18) 0 Ba/La-140 36 15 --- (0/18) --- --- --- (0 / 18) 0 a. (f) is the number of positive measurements  
 
/ total measurements at specified location.b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.Reference Appendix A, Tables A-1 1.1, A-1 1.2, Tables A-12.1, A-12.2.I I I I I I I I I I I I I I I I I I I 2013 Annual Radiological Environmental Operating Report 5-24 Energy Northwest/Columbia Generating Station TABLE 5-3 QUARTERLY TLD DATA  
I COLUMBIA GENERATING STATION Benton County, Washington DOCKET NO. 50-397 Calendar Year 2013                 I Medium: Milk Analysis      Total Analyses    ofLower  Limit Indicator Locationst Detection        Man (
Units: pCi/L Location With Highest Annual Mean Control Mean Locations (f)*    Number of Nonroutine I
Type       Aaye Performed    ofDtcin             Ma(f             Location         Mean (f                   age       Masrmet (LLD) b           Range             oationRange Range 1-131         36             1.0           --- (0/18)
Information
                                                                                                          ---(0/18)
Measurements 0
I Cs-134         36             15           --- (0/18)           ---             ---               --- (0/18)             0       I Cs-137 Ba/La-140 36 36 18 15
                                                --- (0/ 18)
                                                --- (0/18)
                                                                                                          --- (0/18)
                                                                                                          --- (0 / 18) 0 0
I
: a. (f)is the number of positive measurements / total measurements at specified location.
: b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.                                                 I Reference Appendix A, Tables A-1 1.1, A-1 1.2, Tables A-12.1, A-12.2.
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I 2013 Annual Radiological Environmental Operating Report         5-24                       Energy Northwest/Columbia Generating Station I
 
TABLE 5-3 QUARTERLY TLD DATA  


==SUMMARY==
==SUMMARY==
WITH COMPARISON TO PREOPERATIONAL AND OPERATIONAL PERIODS Results in mR!Standard Quarter Pre-OPerational Operational to 2012 2013 Operational Station Mn Max StdDev MEAN Mn Max StdDev MEAN min max StdDev MEAN 1 19.16 23.73 2.07 21.90 18.25 27.38 1.66 22.13 21.32 22.75 0.61 22.10 2 17.34 22.81 2.09 21.10 16.43 25.55 1.56 21.64 19.88 22.16 1.04 21.40 3 18.25 21.90 1.46 20.42 16.43 24.64 1.69 20.86 19.12 21.36 1.03 20.36 4 15.51 23.73 2.65 19.96 14.60 22.81 1.67 *. 19.56 18.50 19.89 0.66 19.14 5 18.25 22.81 1.74 20.76 16.43 23.73 1.64 20.04 18.67 20.16 0.62 19.51 6 18.25 21.90 1.50 20.19 16.43 23.73 1.56 20.17 18.64 19.86 0.50 19.23 7 19.16 22.81 1.69 21.33 16.43 24.64 1.71 21.09 20.05 21.37 0.74 20.71 8 21.90 25.55 1.50 23.84 15.51 27.38 1.95 23.26 22.46 23.82 0.68 23.18 9 15.51 21.90 2.00 19.85 16.43 23.73 1.67 19.76 18.92 21.66 1.15 20.53 10 19.16 22:81 1.38 _ 20.99 16.43 24.64 1.65 20.96 19.50 21.37 0.96 20.38 11 19.16 22.81 1.38 21.44 16.43 24.64 1.47 21.55 20.24 21.74 0.65 21.01 12 20.99 24.64 1.60 23.04 18.25 26.46 1.70 23.14 21.61 23.80 1.04 22.63 13 19.16 22.81 1.54 , 21.44 17.34 27.38 1.78 21.32 19.89 21.43 0.87 20.67 14 19.16 24.64 2.07 21.90 17.34 25.55 1 1.50 21.47 20.24 21.72 0.78 20.96 15 20.99 25.55 1.37 23.15 17.34 27.38 1.69 23.05 21.29 23.82 1.05 22.44 16 20.08 23.73 1.52 22.13 16.43 26.46 1.79 21.95 19.92 22.71 1.24. 21.32 17 19,16 23.73 1.62 22.81 17.34 26.46 1.60 22.51 20.80 23.73 1.23 22.51 18 20.08 23.73 1.27 22.13 16.43 25.55 1.66 22.00 21.05 23.49 1.06 22.58 19 20.08 23.73 1.24 22.01 17.34 25.55 1.57 22.15 21.15 23.19 0.91 22.37 20 19.16 23.73 1.76 21.44 17.34 25.55 1.63 21.80 20.08 22.57 1.25 21.51 21 19.16 21.90 1.25 20.68 15.51 23.73 .1.43 20.32 18.93 20.61 0.81 19.76 22 19.16 23.73 1.58 22.01 16.43 25.55 1.49 21.73 19.97 21.76 0.93 20.88 23 20.08 23.73 1.49 21.60 17.34 25.55 1.62 21.15 19.68 22.23 1.11 21.08 24 20,99 23.73 1.09 .21.90 17.34 50.50 3.19 22.10 20.13 22.24 0.97 21.13 25 20,99 .24.64 1.46 23.15 17.34 27.38 1.91 22.76 21.44 24.88 1.46 22.80 40 17.34 21.90 1.70 19.94 , 15.51 24.64 1.74 20.05 18.18 19.42 0.55 18.88 41 20.08 25.55 2.00 23.73 17.34 27.38 2.03 22.44 20.46 22.72 0.97 21.35 42 20.08 23.73 1.61 .22.36 17.34 26.46 1.93 21.98 20.01 21.41 0.65 20.73 43 20,99 24.64 1.49 23.12 16.43 27.38 2.12 22.60 21.14 22.84 0.72 21.85 44 19.16 22.81 1.34 21.12 15.51 24.64 1.95 20.80 19.36 20.06 0.30 19.73 45 19.16 22.81 1.37 21.25 16.43 25.55 1.80 21.18 18.85 21.39 1.06 20.01 46 22,81 28.29 2.10 26.10 19.16 31.94 2.14 26.49 24.74 27.33 1.27 26.26 47 17.34 20.99 1.73 .19.85 15.51 26.28 1.71 20.23 18.59 20.38 0.91 19.47 49 21.90 21.90 -21.90 16.43 25.55 1.55 21.92 19.97 22.18 1.06 21.25 50 20.08 20.08 20.08 16.43 26.46 1.75 21.60 19.54 22.28 1.16 20.80 51 19.16 21.90 1.18 20.53 16.43 24.64 1.62 21.08 19.56 21.39 1.02 20.48 53 24.64 24.64 -24.64 18.25 29.57 2.04 23.36 20.17 21.59 0.58 20.88 54 23.73 23.73 23.73 18.18 26.46 1.98 22.07 20.30 22.80 1.19 21.40 55 20.99 20.99 20.99 16.43 25.55 1.49 21.45 20.01 22.24 0.93 21.28 56 21.90 21.90 21.90., 16.43 25.55 1.74 21.39 21.29 23.10 0.75 22.12 58 -18.07 20.53 0.61 19.17 18.59 21.73 1.41 20.53 65 " 17.73 22.72 1.20 19.90 18.50 20.33 0.87 19.53 2013 Annual Radiological Environmental Operating Report 5-25 Energy Northwest/Columbia Generating Station 2013 Annual Radiological Environmental Operating Report 5-25 Energy Northwest/Columbia Generating Station TABLE 5-3 (cont)QUARTERLY TLD DATA  
WITH COMPARISON TO PREOPERATIONAL AND OPERATIONAL PERIODS Results in mR!Standard Quarter Pre-OPerational                     Operational to 2012             2013 Operational Station     Mn       Max StdDev MEAN             Mn       Max StdDev MEAN       min     max StdDev MEAN 1       19.16     23.73   2.07   21.90       18.25   27.38   1.66     22.13 21.32   22.75     0.61   22.10 2       17.34     22.81   2.09   21.10       16.43   25.55   1.56     21.64 19.88   22.16     1.04   21.40 3       18.25     21.90   1.46   20.42       16.43   24.64   1.69     20.86 19.12   21.36     1.03   20.36 4       15.51     23.73   2.65   19.96       14.60   22.81   1.67 *. 19.56 18.50   19.89     0.66   19.14 5       18.25     22.81   1.74   20.76       16.43   23.73   1.64     20.04 18.67   20.16     0.62   19.51 6       18.25     21.90   1.50   20.19       16.43   23.73   1.56     20.17 18.64   19.86     0.50   19.23 7       19.16     22.81   1.69   21.33       16.43   24.64   1.71     21.09 20.05   21.37     0.74   20.71 8       21.90     25.55   1.50   23.84       15.51   27.38   1.95     23.26 22.46   23.82     0.68   23.18 9       15.51     21.90   2.00   19.85       16.43   23.73   1.67     19.76 18.92   21.66     1.15   20.53 10       19.16     22:81   1.38 _ 20.99       16.43   24.64   1.65     20.96 19.50   21.37     0.96   20.38 11       19.16     22.81   1.38   21.44       16.43   24.64   1.47     21.55 20.24   21.74     0.65   21.01 12       20.99     24.64   1.60   23.04       18.25   26.46   1.70     23.14 21.61   23.80     1.04   22.63 13       19.16     22.81   1.54 , 21.44       17.34   27.38   1.78     21.32 19.89   21.43     0.87   20.67 14       19.16     24.64   2.07   21.90       17.34   25.55 1 1.50     21.47 20.24   21.72     0.78   20.96 15       20.99     25.55   1.37   23.15       17.34   27.38   1.69     23.05 21.29   23.82     1.05   22.44 16       20.08     23.73   1.52   22.13       16.43   26.46   1.79     21.95 19.92   22.71     1.24. 21.32 17       19,16     23.73   1.62   22.81       17.34   26.46   1.60     22.51 20.80   23.73     1.23   22.51 18       20.08     23.73   1.27   22.13       16.43   25.55   1.66     22.00 21.05   23.49     1.06   22.58 19       20.08     23.73   1.24   22.01       17.34   25.55   1.57     22.15 21.15   23.19     0.91   22.37 20       19.16     23.73   1.76   21.44       17.34   25.55   1.63     21.80 20.08   22.57     1.25   21.51 21       19.16     21.90   1.25   20.68       15.51   23.73   .1.43   20.32 18.93   20.61     0.81   19.76 22       19.16     23.73   1.58   22.01       16.43   25.55   1.49     21.73 19.97   21.76     0.93   20.88 23       20.08     23.73   1.49   21.60       17.34   25.55   1.62     21.15 19.68   22.23     1.11   21.08 24       20,99     23.73   1.09 . 21.90       17.34   50.50   3.19     22.10 20.13   22.24     0.97   21.13 25       20,99 . 24.64   1.46   23.15       17.34   27.38   1.91     22.76 21.44   24.88     1.46   22.80 40       17.34     21.90   1.70   19.94     , 15.51   24.64   1.74     20.05 18.18   19.42     0.55   18.88 41       20.08     25.55   2.00   23.73       17.34   27.38   2.03     22.44 20.46   22.72     0.97   21.35 42       20.08     23.73   1.61 . 22.36       17.34   26.46   1.93     21.98 20.01   21.41     0.65   20.73 43       20,99     24.64   1.49   23.12       16.43   27.38   2.12     22.60 21.14   22.84     0.72   21.85 44       19.16     22.81   1.34   21.12       15.51   24.64   1.95     20.80 19.36   20.06     0.30   19.73 45       19.16     22.81   1.37   21.25       16.43   25.55   1.80     21.18 18.85   21.39     1.06   20.01 46       22,81     28.29   2.10   26.10       19.16   31.94   2.14     26.49 24.74   27.33     1.27   26.26 47       17.34     20.99   1.73 . 19.85       15.51   26.28   1.71     20.23 18.59   20.38     0.91   19.47 49       21.90     21.90     -     21.90       16.43   25.55   1.55     21.92 19.97   22.18     1.06   21.25 50       20.08     20.08           20.08       16.43   26.46   1.75     21.60 19.54   22.28     1.16   20.80 51       19.16     21.90   1.18   20.53       16.43   24.64   1.62     21.08 19.56   21.39     1.02   20.48 53       24.64     24.64     -     24.64       18.25   29.57   2.04     23.36 20.17   21.59     0.58   20.88 54       23.73     23.73           23.73       18.18   26.46   1.98     22.07 20.30   22.80     1.19   21.40 55       20.99     20.99           20.99       16.43   25.55   1.49     21.45 20.01   22.24     0.93   21.28 56       21.90     21.90           21.90., 16.43       25.55   1.74     21.39 21.29   23.10     0.75   22.12 58                   -                         18.07   20.53   0.61     19.17 18.59   21.73     1.41   20.53 65                                         "   17.73   22.72   1.20     19.90 18.50   20.33     0.87   19.53 Report         5-25                 Energy Northwest/Columbia Generating Station 2013 Annual 2013                    Environmental Operating Radiological Environmental Annual Radiological              Operating Report         5-25                 Energy Northwest/Columbia Generating Station
 
I TABLE 5-3 (cont)
QUARTERLY TLD DATA  


==SUMMARY==
==SUMMARY==
WITH COMPARISON TO PREOPERATIONAL AND OPERATIONAL PERIODS Results in mR/Standard Quarter Pre-Operational Station Min Max Std Dev MEAN Operational to 2012 Min Max Std Dev MEAN 71(1S) 20.08 22.81 1.58 21.90 18.25 30.39 2.45 72(2S) 21.90 23.73 0.91 22.81 18.25 29.65 1.96 73(3S) 20.08 21.90 0.91 20.99 16.43 24.64 1.54 74(4S) 23.73 24.64 0.53 24.03 18.25 28.29 1.87 75(5S) 19.16 21.90 1.39 20.38 15.51 26.46 1.85 76(6S) 20.99 22.81 0.91 21.90 17.34 26.46 1.69 77(7S) 21.90 23.73 0.91 22.81 17.34 25.55 1.59 78(8S) 21.90 23.73 1.05 22.51 17.34 25.55 1.56 79(9S) 22.81 23.73 0.53 23.12 17.34 25.55 1.63 80(10S) 20.99 22.81 0.91 21.90 16.43 25.55 1.74 81(11S) 20.08 23.73 1.90 22.20 17.34 25.55 1.52 82(12S) 21.90 24.64 1.39 23.42 17.34 26.46 1.55 83(13S) 21.90 23.73 0.91 22.81 17.34 26.46 1.84 84(14S) 20.99 22.81 1.05 22.20 16.43 27.17 1.76 85(15S) 21.90 24.64 1.58 23.73 17.34 27.83 1.87 86(16S) 21.90 23.73 0.91 22.81 18.25 31.28 2.61 87 -19.34 34.34 4.76 88 17.05 31.67 4.18 89 19.25 29.38 2.85 90 18.26 20.48 0.57 119B 19.24 25.64 1.46 119Ctrl 19.53 26.55 1.38 120East 19.78 31.12 1.81 121 (ISFSI) 19.52 130.27 23.63 122 (ISFSI) -19.62 42.49 7.28 123 (ISFSI) -24.99 160.33 38.26 124 (ISFSI) -26.89 201.05 48.67 125 (ISFSI) -26.46 135.52 29.35 126 (ISFSI) -26.00 145.68 32.15 127 (ISFSI) -28.97 102.08 19.71 128 (ISFSI) -25.64 187.25 48.29 129 (ISFSI) -30.16 138.08 33.14 136A (ISFSI -28.99 205.64 62.50 137A (ISFSI -29.47 238.74 71.26 138A (ISFSI -28.28 196.68 54.19 Site 1 -11.92 20.19 1.43 Site 4 -17.02 32.44 2.80 25.26 24.33 21.25 23.38 22.29 22.04 22.02 21.51 21.85 20.99 21.52 22.42 22.29 22.26 23.09 26.16 28.82 26.08 25.92 18.95 22.13 21.83 22.43 76.58 30.98 116.91 144.92 102.63 85.18 66.18 100.11 79.99 101.87 112.61 93.08 18.16 18.94 2013 Operational min max Std Dev MEAN 22.52 26.85 2.06 24.76 21.65 26.04 1.89 24.08 19.70 1 23.94 1.84 21.77 21.56 24.51 1.52 23.10 21.19 23.14 0.95 22.22 20.29 22.83 1.07 21.37 20.29 22.55 0.94 21.46 20.30 21.79 0.65 20.99 20.40 22.54 1.05 21.40 19.72 22.41 1.15 21.24 19.96 21.89 0.91 20.65 21.07 23.05 0.94 22.19 20.35 22.51 0.90 21.42 20.52 24.25 1.77 22.14 21.48 24.17 1.17 22.67 26.04 29.71 1.70 27.91 23.74 32.32 3.53 28.34 20.91 26.25 2.36 24.24 22.83 27.62 2.17 25.59 17.53 19.56 0.96 18.85 20.24 23.26 1.30 21.87 20.53 23.46 1.28 22.08 20.99 23.70 1.38 22.31 44.90 71.44 11.99 62.36 32.30 35.74 1.68 34.26 103.88 111.07 3.66 107.91 120.51 130.90 4.81 124.68 91.21 96.33 2.19 93.25 90.80 97.65 2.80 94.20 67.89 73.92 2.84 72.12 114.89 122.42 3.47 117.86 88.01 93.64 2.54 91.70 129.75 137.21 3.49 132.57 142.11 148.32 2.92 146.44 113.80 121.21 3.09 118.02 17.74 19.52 0.77 18.48 17.27 19.68 1.18 19.03 I I I I I I I I I I I U U I I I U I I Table 5-3 Notes: The preoperational mean is from 1982-1983 data. Station 65 was added in 1997.Stations 119B, 119Ctd, and 120 were added in 1995. Stations 121 and 122 were added in 1998 for the ISFSI.Stations 123-129 and 136A-138A were added in the 2nd quarter of 2002. Stations Site 1 and Site 4 were added in 2006.Stations 58 and 87 to 90 were added in 2008 to monitor remediation work at DOE 618-11 burial site.2013 Annual Radiological Environmental Operating Report 5-26 Energy Northwest/Columbia Generating Station 6.0 QUALITY ASSURANCE AND QUALITY CONTROL 6.0 QUALITY ASSURANCE AND QUALITY CONTROL The REMP is designed to meet the quality assurance (QA) and quality control (QC) criteria of the NRC Regulatory Guide 4.15 7) and 10 CFR 50 Appendix B 1 1 5). The contractors used for sample analysis, Energy Northwest Environmental Services, and Mission Support Alliance, maintain quality control programs to ensure that analytical results are accurate, precise, and defensible.
WITH COMPARISON TO                                                                     I PREOPERATIONAL AND OPERATIONAL PERIODS Pre-Operational Results in mR/Standard Quarter I
The following sections summarize the quality assurance and quality control aspects of the TLD, sample collection, and sample analysis components of the REMP.6.1 Quality Control for the Energy Northwest Environmental TLD Program The Quality Control program for the environmental TLD program covers the preparation, transportation, deployment, collection, storage, processing, and evaluation of the environmental TLDs and is designed to meet the requirements of NRC Regulatory Guides 4.13(8) and 4.15. (7 From the time the TLDs are annealed to the time they are placed in the field, they are stored and transported with control TLDs. Two sets of control TLDs are used, the building controls and the transportation (trip) controls.
Operational to 2012                 2013 Operational Station 71(1S) 72(2S)
The building controls monitor the exposure that the TLDs receive while being transported to and from the TLD vendor and while in storage awaiting deployment and analysis.The trip controls accompany the field TLDs when transported to and from the vendor and also during deployment and collection in the field. The building controls and trip controls are stored in a low background lead shield while the field TLDs are deployed.
Min 20.08 21.90 Max 22.81 23.73 Std Dev MEAN 1.58 0.91 21.90 22.81 Min 18.25 18.25 Max 30.39 29.65 Std Dev MEAN 2.45 1.96 25.26 24.33 min 22.52 21.65 max 26.85 26.04 Std Dev MEAN 2.06 1.89 24.76 24.08 I
If the trip control results are greater than the building control results, the difference between the two is subtracted from the field dosimeters to account for exposure during transit.Reader QC dosimeters serve as checks that the dosimeter reader calibration is satisfactory and that the TLDs were processed correctly.
73(3S) 74(4S) 75(5S) 20.08 23.73 19.16 21.90 24.64 21.90 0.91 0.53 1.39 20.99 24.03 20.38 16.43 18.25 15.51 24.64 28.29 26.46 1.54 1.87 1.85 21.25 23.38 22.29 19.70 1 23.94 21.56 21.19 24.51 23.14 1.84 1.52 0.95 21.77 23.10 22.22 I
These TLDs are annealed and then given a known exposure (typically 100 mR) to a cesium-137 source. The number of QC dosimeters used during each processing is generally 10% of the number of field dosimeters.
I 76(6S)     20.99    22.81    0.91   21.90      17.34   26.46    1.69  22.04    20.29    22.83    1.07    21.37 77(7S)     21.90   23.73     0.91  22.81      17.34   25.55     1.59  22.02    20.29    22.55    0.94    21.46 78(8S)    21.90    23.73    1.05  22.51      17.34   25.55     1.56  21.51    20.30    21.79    0.65    20.99 79(9S)     22.81    23.73     0.53  23.12      17.34   25.55     1.63  21.85    20.40    22.54    1.05    21.40 80(10S) 81(11S) 20.99 20.08 22.81 23.73 0.91 1.90 21.90 22.20 16.43 17.34 25.55 25.55 1.74 1.52 20.99 21.52 19.72 19.96 22.41 21.89 1.15 0.91 21.24 20.65 I
Evaluation of the 2013 reader QC dosimeter results indicated satisfactory agreement for all periods. The quarterly average reader QC results are presented in Table 6-1.TLDs designated as spikes are prepared by the Energy Northwest Radiation Protection Department by exposing the TLDs to a calibrated source to produce a known exposure.
82(12S)     21.90   24.64     1.39  23.42      17.34   26.46    1.55  22.42    21.07    23.05    0.94    22.19 83(13S) 84(14S) 21.90 20.99 23.73 22.81 0.91 1.05 22.81 22.20 17.34 16.43 26.46 27.17 1.84 1.76 22.29 22.26 20.35 20.52 22.51 24.25 0.90 1.77 21.42 22.14 I
The spiked dosimeters are submitted and processed with the field dosimeters to further verify the accuracy and precision of the environmental TLD results. Quarterly spikes receive a target exposure of 22 mR. Evaluation of the 2013 spiked dosimeter results indicated satisfactory agreement for all periods. Spiked TLD results are presented in Table 6-1.6.2 Quality Control for the Environmental Sample Program Quality control for the environmental sample program encompasses both the sample collection and sample analysis processes.
85(15S)    21.90    24.64    1.58  23.73      17.34    27.83    1.87  23.09    21.48    24.17    1.17    22.67 86(16S) 87 88 21.90    23.73    0.91 22.81      18.25 19.34 17.05 31.28 34.34 31.67 2.61 4.76 4.18 26.16 28.82 26.08 26.04 23.74 20.91 29.71 32.32 26.25 1.70 3.53 2.36 27.91 28.34              I 24.24 89 90 119B 19.25 18.26 19.24 29.38 20.48 25.64 2.85 0.57 1.46 25.92 18.95 22.13 22.83 17.53 20.24 27.62 19.56 23.26 2.17 0.96 1.30 25.59 18.85 21.87 I
Results are reviewed for correctness, reasonableness, and data entry errors.Sample results that are suspect are normally investigated.
119Ctrl 120East 121 (ISFSI) 19.53 19.78 19.52 26.55 31.12 130.27 1.38 1.81 23.63 21.83 22.43 76.58 20.53 20.99 44.90 23.46 23.70 71.44 1.28 1.38 11.99 22.08 22.31 62.36 I
A crosscheck program utilizing blind samples supplied by an outside vendor is maintained for all sample media routinely analyzed.2013 Annual Radiological Environmental Operating Report 6-1 Energy Northwest/Columbia Generating Station I 6.2.1 Sample Collection Quality Control I Duplicate samples are collected and submitted for analysis when practical.
122 (ISFSI)    -                                19.62    42.49    7.28 U
The duplicate samples are used to assess the repeatability of the sample collection process and the precision of the analytical I method.6.2.2 Laboratory Instruments Quality Control 3 Analytical Balances -Analytical balances used in the laboratory for sample preparations are calibrated every six months. Performance checks are performed prior to use and span the range of intended use. Performance check results are documented on the sample preparation forms and kept with the analytical results.Analytical Instruments
30.98    32.30    35.74    1.68    34.26 123 (ISFSI)    -                                24.99    160.33    38.26  116.91  103.88    111.07    3.66  107.91 124 (ISFSI)    -                                26.89    201.05    48.67  144.92  120.51    130.90    4.81  124.68 125 (ISFSI)    -                                26.46    135.52    29.35  102.63    91.21   96.33    2.19    93.25 126 (ISFSI) 127 (ISFSI) 26.00 28.97 145.68 102.08 32.15 19.71 85.18 66.18 90.80 67.89 97.65 73.92 2.80 2.84 94.20 72.12 U
-Analytical instruments used for determining radioactive emissions in I samples are calibrated for efficiency annually using standard reference material traceable to the National Institute of Standards and Technology (NIST). Below is a summary of the routine QC practices for the different analytical instruments.
128 (ISFSI)    -                                25.64    187.25    48.29  100.11  114.89    122.42   3.47  117.86 129 (ISFSI) 136A (ISFSI 137A (ISFSI 30.16 28.99 29.47 138.08 205.64 238.74 33.14 62.50 71.26 79.99 101.87 112.61 88.01 129.75 142.11 93.64 137.21 148.32 2.54 3.49 2.92 91.70 132.57 146.44 I
* Gas-flow Proportional Counter: Background and performance checks are performed daily when in use. Control charts are maintained with two and three-sigma limits specified; the checks must fall within the two-sigma warning limits prior to use. Mid-batch QC and end of batch performance checks are typically performed.
138A (ISFSI Site 1 Site 4 28.28 11.92 17.02 196.68 20.19 32.44 54.19 1.43 2.80 93.08 18.16 18.94 113.80 17.74 17.27 121.21 19.52 19.68 3.09 0.77 1.18 118.02 18.48 19.03 I
* Gamma Spectrometers:
Table 5-3 Notes:
Performance checked daily for efficiency, energy per channel relationship, peak resolution, and background when in use. The checks are performed and plotted for both a low and high energy peak.. Efficiency checks are held within two-sigma control limits. Long duration background checks are performed quarterly.
The preoperational mean is from 1982-1983 data. Station 65 was added in 1997.
A low level batch QC check is typically analyzed with each set of samples.* Liquid Scintillation Counter: Background and performance checks are performed daily when in use. A performance check standard of the same matrix as the samples is analyzed and results trended. A control chart with acceptance limits specified is maintained.
I Stations 119B, 119Ctd, and 120 were added in 1995. Stations 121 and 122 were added in 1998 for the ISFSI.
A low level batch QC check is typically analyzed with each set of samples.6.2.3 Sample Batch Quality Control Sample batch analysis is normally performed with sample blanks and known-addition samples (or i spiked samples) included.
Stations 123-129 and 136A-138A were added in the 2nd quarter of 2002. Stations Site 1 and Site 4 were added in 2006.
The type of known addition sample used is dictated by the sample media being analyzed, the primary analytes of interest, and the method being used. The following is a summary of sample batch QC activities.
Stations 58 and 87 to 90 were added in 2008 to monitor remediation work at DOE 618-11 burial site.
Iodine-131 Cartridges
U I
-At least one known-addition sample is analyzed with each batch. A charcoal cartridge of the same type used for sample collection but spiked with barium-133 is used.The 356 keV peak of barium-133 serves as a proxy for the 364 keV peak of iodine-131.
2013 Annual Radiological Environmental Operating Report        5-26                    Energy Northwest/Columbia Generating Station I
Samples from the control location serve as blanks. i Gross Beta Filters -At least one unused blank air particulate filter and at least one known-addition air particulate filter is analyzed with each batch. 3 Aqueous Samples -In most cases, samples collected from the control locations are analyzed as blanks. A known-addition sample is typically analyzed with each batch of samples. i 2013 Annual Radiological Environmental Operating Report 6-2 Energy Northwest/Columbia Generating Station I Gross Alpha/Beta in Water -Blank samples were prepared from reagent grade water and analyzed with each batch of samples. One known addition sample and one replicate sample is normally analyzed with each batch.Tritium in Water -A blank and a low level known addition sample is typically analyzed with each batch. A replicate sample is prepared and analyzed inside of each batch in most cases.6.3 Laboratory Intercomparison Program Participation and Results Participation in cross check intercomparison studies is mandatory for' laboratories performinig analyses of CGS REMP samples. Intercomparison studies provide a consistent and effective means to evaluate the accuracy and precision of analyses performed by a laboratory.
 
Study results should fall within specified control limits. Results that fall outside the control limits are investigated and corrective action taken.The Energy Northwest Environmental Services Laboratory participated in three proficiency testing studies involving radioactive measurements provided by Environmental Resource Associates (ERA)during 2013. The Laboratory's intercomparison program was further supplemented by additional cross check media provided by ERA. The Laboratory's intercomparison program results for 2013 are shown in Table 6-2. All 2013 Laboratory intercomparison program results were within acceptable limits. Participation in the ERA studies serves to meet the intercomparison program requirements specified in the ODCM.In addition to the studies noted above, the CGS REMP maintains a split sample program with the State of Washington Department of'Health.
6.0 QUALITY ASSURANCE AND QUALITY CONTROL 6.0    QUALITY ASSURANCE AND QUALITY CONTROL The REMP is designed to meet the quality assurance (QA) and quality control (QC) criteria of the NRC Regulatory Guide 4.15 7)and 10 CFR 50 Appendix B1 15). The contractors used for sample analysis, Energy Northwest Environmental Services, and Mission Support Alliance, maintain quality control programs to ensure that analytical results are accurate, precise, and defensible. The following sections summarize the quality assurance and quality control aspects of the TLD, sample collection, and sample analysis components of the REMP.
Split samples are sent to a State of Washington Lab on a scheduled frequency where they are independently analyzed.
6.1      Quality Control for the Energy Northwest Environmental TLD Program The Quality Control program for the environmental TLD program covers the preparation, transportation, deployment, collection, storage, processing, and evaluation of the environmental TLDs and is designed to meet the requirements of NRC Regulatory Guides 4.13(8) and 4.15. (7 From the time the TLDs are annealed to the time they are placed in the field, they are stored and transported with control TLDs. Two sets of control TLDs are used, the building controls and the transportation (trip) controls. The building controls monitor the exposure that the TLDs receive while being transported to and from the TLD vendor and while in storage awaiting deployment and analysis.
This program provides an additional check on the accuracy and precision of the results reported in this document.6.4 Laboratory Quality Control Program Problems and Improvements No issues with REMP sampling and analyses were identified by the QC and intercomparison programs in 2013.2013 Annual Radiological Environmental Operating Report 6-3 Energy Northwest/Columbia Generating Station 2013 Annual Radiological Environmental Operating Report 6-3 Energy Northwest/Columbia Generating Station TABLE 6-1 2013 ENVIRONMENTAL SPIKED DOSIMETER.RESULTS KNOWN REPORTED-EXPOSURE EXPOSURE PERIOD SPIKE ID (mR) (mR) BIAS (%)1st Quarter ENW Spike 22 21.6 -1.8%ENW Spike 22 21.2 -3.6%ENW Spike 22 21.2. -3.6%PNNL Avg. Reader 100 99.1 -0.9%2nd Quarter ENW Spike 22 21.5 -2.3%, ENW Spike 22 21.1 -4.1%ENW Spike 22 21.4 -2.7%PNNL Avg. Reader 100 99.3 -0.1%3rd Quarter ENW Spike 22 22.2 0.9%ENW Spike 22 22.2 0.9%ENW Spike 22 22.3 1.4%PNNL Avg. Reader 100 100.8 0.8%4th Quarter ENW Spike , 22 21.8 -0.9%ENW Spike 22, 21.5 -2.3%ENW Spike 22 21.9 -0.5%PNNL Avg. Reader 100 97.4 -2.6%I I I I I I I I U I I U I I I I I I I 2013 Annual Radiological Environmental Operating Report 6-4 Energy Northwest/Columbia Generating Station TABLE 6-2 ENW REMP PROGRAM: CROSS CHECK PERFORMANCE RESULTS ERA MRAD-18 Results Spring 2013 Reported Assigned Acceptance Performance StandardlAnalyte Units Value -Value Limits Evaluation Air Filter Radionuclides Americium-241 pCi/Filter 72 66.8 41.2-90.4 Acceptable  
The trip controls accompany the field TLDs when transported to and from the vendor and also during deployment and collection in the field. The building controls and trip controls are stored in a low background lead shield while the field TLDs are deployed. If the trip control results are greater than the building control results, the difference between the two is subtracted from the field dosimeters to account for exposure during transit.
-Cesium-134 pCi/Filter 1047 1110 706- 1380 Acceptable Cesium-137 pCi/Filter 1173 940 706 -1230 Acceptable Cobalt-60 pCi/Filter 246 214 166 -267 Acceptable Zinc-65 pCi/Filter, 275 199 142 -275 Acceptable Air Filter Gross Alpha/Beta Gross Alpha pCi/Filter 44 + 42.3 14.2 -65.7 Acceptable Gross Beta pCi/Filter 21 25.1 :15.9 -36.6 Acceptable Water Radionuclides Americium-241 pCi/L 117 118 79.5 -158 Acceptable Cesium-134 pCi/L 1255 1400 1030-1610 Acceptable Cesium-1 37 pCi/L 1923 1880 1600 -2250 Acceptable Cobalt-60 pCi/L 2229 2270 1970 -2660 Acceptable Zinc-65 pCi/L 418 384 320 -484 Acceptable Water Gross Alpha/Beta Gross Alpha IpCi/L 97 130 46.2 -201 =Acceptable Gross Beta pCi/L 56 78.9 45.2 -117 Acceptable Water Tritium Tritium pCi/L 11873 12300 8240 -17500 Acceptable Soil Radionuclides Actinium-228 pCi/kq 1152 1240 795- 1720 Acceptable Bismuth-212 pCi/kg 1133 1240 330-1820 Acceptable Bismuth-214 pCi/kq 3035 3660 2200 -5270 Acceptable Cesium-1 34 pCi/kg 6105 6370 4160- 7650 Acceptable Cesium-1 37 pCi/kg 6414 6120 4690- 7870 Acceptable Cobalt-60 pCi/kg 8089 7920 5360 -10900 Acceptable Lead-212 pCi/kg 1162 1240 812 -1730 Acceptable Lead-214 pCi/kq 3334 3660 2140 -5460 Acceptable Potassium-40 pCi/kg 10890 10300 7520 -13800 Acceptable Zinc-65 pCi/kg 1530 1400 1110 -1860 Acceptable 2013 Annual Radiological Environmental Operating Report 6-5 Energy Northwest/Columbia Generating Station TABLE 6-2 (cont)ENW REMP PROGRAM CROSS CHECK PERFORMANCE RESULTS ERA MRAD-19 Results Fall 2013 Reported Assigned Acceptance Performance StandardlAnalyte Units Value- Value' Limits Evaluation Air Filter Radionuclides Americium-241 pCi/Filter 72 66.4 40.9 -89:8 Acceptable Cesium-134 pCi/Filter 811 868 552-1080 Acceptable Cesium-137 pCi/Filter 734 602 452- 791 Acceptable Cobalt-60 pCi/Filter 556 494 382 -617 Acceptable Manganese-54 pCi/Filter
Reader QC dosimeters serve as checks that the dosimeter reader calibration is satisfactory and that the TLDs were processed correctly. These TLDs are annealed and then given a known exposure (typically 100 mR) to a cesium-137 source. The number of QC dosimeters used during each processing is generally 10% of the number of field dosimeters. Evaluation of the 2013 reader QC dosimeter results indicated satisfactory agreement for all periods. The quarterly average reader QC results are presented in Table 6-1.
< 10 < 50.0 0.00- 50.0 Acceptable Zinc-65 pCi/Filter 573 419- 300 -578 Acceptable Air Filter Gross Alpha/Beta Gross Alpha [pCi/Filter 84 [ 83 J 27.8-129 [ Acceptable Gross Beta pCi/Filter 1 47 56.3 35.6-82.2 Acceptable Water Radionuclides Americium-241 pCi/L 102 126 84.9- 169 Acceptable Cesium-1 34 pCi/L 1987 2180 1600-2510 Acceptable Cesium-137 pCi/L 2801 2760 2340-3310 Acceptable Cobalt-60 pCi/L 1869 1890 1640 -2210 Acceptable Manganese-54 pCi/L < 20 < 100 0.00 -100 Acceptable Zinc-65 pCi/L 1505 1370 1140-1730 Acceptable Water Gross AlphalBeta Gross Alpha pCi/L 88 96.6 34.3 -150 Acceptable Gross Beta pCi/L 56 84.5 I 48.4- 125 Acceptable Water Tritium Tritium pCi/L 1 19762 [ 19800 113300- 282001 Acceptable Soil Radionuclides ,ctinium-228 pCi/kg 1247 1240 795- 1720 Acceptable Bismuth-212 pCi/kg 983 1220 325 -1790 Acceptable Bismuth-214 pCi/kg 3593 3740 2250 -5380 Acceptable Cesium-1 34 pCi/kg 2858 2820 1840- 3390 Acceptable Cesium-137 pCi/kg 4422 4130 3160- 5310 Acceptable Cobalt-60 pCi/kg 5819 5680 3840 -7820 Acceptable Lead-212 pCi/kg 1146 1220 799- 1700 Acceptable Lead-214 pCi/kg 3835 3740 2180 -5580 Acceptable Manganese-54 pCi/kg < 100 < 1000 0.00 -1000 Acceptable Potassium-40 pCi/kg 10630 12400 9080 -16700 Acceptable Zinc-65 pCi/kg 3686 3160 2520-4200 Acceptable I I I I I I I I I I I I I I I I I I I 2013 Annual Radiological Environmental Operating Report 6-6 Energy Northwest/Columbia Generating Station TABLE 6-2 (cont)ENW REMP PROGRAM CROSS CHECK PERFORMANCE RESULTS.2013 ERA Crosscheck Result Iodine-131 Charcoal Cartridge Acceptance Performance Sample ID Analysis Units Result. Ref Value Limits Evaluation 03131390A Iodine-131 pCi/Filter 1174 1006 775-1328 Acceptable 09141205A Iodine-131 pCi/Filter 332 289 223 -382 Acceptable 2013 ERA RAD Results Iodine-131 in Milk___ _ Acceptance Performance Sample ID Analysis Units Result Ref Value Limits Evaluation RAD-94 Iodine-1 31 pCi/L 21.6 24.3 20.2-28.8 Acceptable 2013 Annual Radiological Environmental Operating Report 6-7 Energy Northwest/Columbia Generating Station  
TLDs designated as spikes are prepared by the Energy Northwest Radiation Protection Department by exposing the TLDs to a calibrated source to produce a known exposure. The spiked dosimeters are submitted and processed with the field dosimeters to further verify the accuracy and precision of the environmental TLD results. Quarterly spikes receive a target exposure of 22 mR. Evaluation of the 2013 spiked dosimeter results indicated satisfactory agreement for all periods. Spiked TLD results are presented in Table 6-1.
6.2    Quality Control for the Environmental Sample Program Quality control for the environmental sample program encompasses both the sample collection and sample analysis processes. Results are reviewed for correctness, reasonableness, and data entry errors.
Sample results that are suspect are normally investigated. A crosscheck program utilizing blind samples supplied by an outside vendor is maintained for all sample media routinely analyzed.
2013 Annual Radiological Environmental Operating Report 6-1              Energy Northwest/Columbia Generating Station
 
I 6.2.1 Sample Collection Quality Control                                                                            I Duplicate samples are collected and submitted for analysis when practical. The duplicate samples are used to assess the repeatability of the sample collection process and the precision of the analytical method.
I 6.2.2 Laboratory Instruments Quality Control                                                                        3 Analytical Balances - Analytical balances used in the laboratory for sample preparations are calibrated every six months. Performance checks are performed prior to use and span the range of intended use. Performance check results are documented on the sample preparation forms and kept with the analytical results.
Analytical Instruments - Analytical instruments used for determining radioactive emissions in samples are calibrated for efficiency annually using standard reference material traceable to the I
National Institute of Standards and Technology (NIST). Below is a summary of the routine QC practices for the different analytical instruments.
        *Gas-flow Proportional Counter: Background and performance checks are performed daily when in use. Control charts are maintained with two and three-sigma limits specified; the checks must fall within the two-sigma warning limits prior to use. Mid-batch QC and end of batch performance checks are typically performed.
* Gamma Spectrometers: Performance checked daily for efficiency, energy per channel relationship, peak resolution, and background when in use. The checks are performed and plotted for both a low and high energy peak.. Efficiency checks are held within two-sigma control limits. Long duration background checks are performed quarterly. A low level batch QC check is typically analyzed with each set of samples.
* Liquid Scintillation Counter: Background and performance checks are performed daily when in use. A performance check standard of the same matrix as the samples is analyzed and results trended. A control chart with acceptance limits specified is maintained. A low level batch QC check is typically analyzed with each set of samples.
6.2.3    Sample Batch Quality Control Sample batch analysis is normally performed with sample blanks and known-addition samples (or                      i spiked samples) included. The type of known addition sample used is dictated by the sample media being analyzed, the primary analytes of interest, and the method being used. The following is a summary of sample batch QC activities.
Iodine-131 Cartridges - At least one known-addition sample is analyzed with each batch. A charcoal cartridge of the same type used for sample collection but spiked with barium-133 is used.
The 356 keV peak of barium-133 serves as a proxy for the 364 keV peak of iodine-131. Samples from the control location serve as blanks.                                                                           i Gross Beta Filters - At least one unused blank air particulate filter and at least one known-addition air particulate filter is analyzed with each batch.                                                                 3 Aqueous Samples - In most cases, samples collected from the control locations are analyzed as blanks. A known-addition sample is typically analyzed with each batch of samples.                                   i 2013 Annual Radiological Environmental Operating Report 6-2            Energy Northwest/Columbia Generating Station I
 
Gross Alpha/Beta in Water - Blank samples were prepared from reagent grade water and analyzed with each batch of samples. One known addition sample and one replicate sample is normally analyzed with each batch.
Tritium in Water - A blank and a low level known addition sample is typically analyzed with each batch. A replicate sample is prepared and analyzed inside of each batch in most cases.
6.3    Laboratory Intercomparison Program Participation and Results Participation in cross check intercomparison studies is mandatory for' laboratories performinig analyses of CGS REMP samples. Intercomparison studies provide a consistent and effective means to evaluate the accuracy and precision of analyses performed by a laboratory. Study results should fall within specified control limits. Results that fall outside the control limits are investigated and corrective action taken.
The Energy Northwest Environmental Services Laboratory participated in three proficiency testing studies involving radioactive measurements provided by Environmental Resource Associates (ERA) during 2013. The Laboratory's intercomparison program was further supplemented by additional cross check media provided by ERA. The Laboratory's intercomparison program results for 2013 are shown in Table 6-2. All 2013 Laboratory intercomparison program results were within acceptable limits. Participation in the ERA studies serves to meet the intercomparison program requirements specified in the ODCM.
In addition to the studies noted above, the CGS REMP maintains a split sample program with the State of Washington Department of'Health. Split samples are sent to a State of Washington Lab on a scheduled frequency where they are independently analyzed. This program provides an additional check on the accuracy and precision of the results reported in this document.
6.4    Laboratory Quality Control Program Problems and Improvements No issues with REMP sampling and analyses were identified by the QC and intercomparison programs in 2013.
Operating Report 6-3            Energy Northwest/Columbia Generating Station 2013        Radiological Environmental Annual Radiological 2013 Annual              Environmental Operating Report 6-3            Energy Northwest/Columbia Generating Station
 
I TABLE 6-1 2013 ENVIRONMENTAL SPIKED DOSIMETER.RESULTS                                              I KNOWN
                                                        -EXPOSURE REPORTED EXPOSURE                                      I PERIOD                SPIKE ID                    (mR)    (mR)                  BIAS (%)
1st Quarter                ENW Spike                    22    21.6                -1.8%
I ENW Spike                    22    21.2                -3.6%
ENW Spike PNNL Avg. Reader 22 100 21.2.
99.1
                                                                                          -3.6%
                                                                                          -0.9%                  I 2nd Quarter                ENW Spike ENW Spike 22 22 21.5 21.1
                                                                                          -2.3%,
                                                                                          -4.1%
I ENW Spike                    22      21.4                -2.7%
PNNL Avg. Reader                  100    99.3                -0.1%                  I 3rd Quarter                ENW Spike ENW Spike 22 22 22.2 22.2 0.9%
0.9%
I ENW Spike                    22      22.3                  1.4%
PNNL Avg. Reader                  100    100.8                  0.8%
U 4th Quarter                ENW ENW Spike Spike ,
ENW Spike 22 22, 22 21.8 21.5 21.9
                                                                                          -0.9%
                                                                                          -2.3%
                                                                                          -0.5%
I PNNL Avg. Reader                  100    97.4                -2.6%
I U
I I
I I
I I
2013 Annual Radiological Environmental Operating Report  6-4        Energy Northwest/Columbia Generating Station I
 
TABLE 6-2 ENW REMP PROGRAM: CROSS CHECK PERFORMANCE RESULTS ERA MRAD-18 Results Spring 2013 Reported        Assigned      Acceptance          Performance StandardlAnalyte          Units          Value -        Value          Limits            Evaluation Air Filter Radionuclides Americium-241            pCi/Filter        72            66.8      41.2-90.4            Acceptable    -
Cesium-134                pCi/Filter      1047            1110        706- 1380            Acceptable Cesium-137                pCi/Filter      1173            940        706 - 1230          Acceptable Cobalt-60                pCi/Filter        246            214        166 - 267          Acceptable Zinc-65                  pCi/Filter,      275            199        142 - 275          Acceptable Air Filter Gross Alpha/Beta Gross Alpha              pCi/Filter        44 +          42.3       14.2 - 65.7        Acceptable Gross Beta                pCi/Filter        21             25.1       :15.9 - 36.6        Acceptable Water Radionuclides Americium-241              pCi/L          117            118        79.5 - 158          Acceptable Cesium-134                  pCi/L          1255            1400      1030-1610            Acceptable Cesium-1 37                pCi/L          1923            1880      1600 -2250          Acceptable Cobalt-60                  pCi/L          2229            2270        1970 - 2660          Acceptable Zinc-65                    pCi/L          418            384        320 -484            Acceptable Water Gross Alpha/Beta Gross Alpha              IpCi/L              97            130        46.2 - 201        =Acceptable Gross Beta                  pCi/L            56            78.9       45.2 - 117          Acceptable Water Tritium Tritium                    pCi/L        11873            12300      8240 - 17500          Acceptable Soil Radionuclides Actinium-228              pCi/kq          1152            1240      795- 1720            Acceptable Bismuth-212                pCi/kg          1133            1240      330-1820            Acceptable Bismuth-214                pCi/kq          3035            3660      2200 - 5270          Acceptable Cesium-1 34                pCi/kg          6105            6370      4160- 7650            Acceptable Cesium-1 37                pCi/kg          6414            6120      4690- 7870            Acceptable Cobalt-60                  pCi/kg          8089            7920      5360 - 10900          Acceptable Lead-212                  pCi/kg          1162            1240      812 - 1730          Acceptable Lead-214                  pCi/kq          3334            3660      2140 - 5460          Acceptable Potassium-40              pCi/kg        10890            10300      7520 - 13800          Acceptable Zinc-65                   pCi/kg          1530            1400      1110 - 1860          Acceptable 2013 Annual Radiological Environmental Operating Report    6-5                  Energy Northwest/Columbia Generating Station
 
I TABLE 6-2 (cont)
ENW REMP PROGRAM CROSS CHECK PERFORMANCE RESULTS                                                              I ERA MRAD-19 Results Fall 2013 Reported        Assigned      Acceptance          Performance I
StandardlAnalyte            Units          Value-          Value'        Limits            Evaluation Americium-241              pCi/Filter Air Filter Radionuclides 72            66.4        40.9 - 89:8          Acceptable               I Cesium-134                pCi/Filter        811            868        552-1080            Acceptable Cesium-137 Cobalt-60 Manganese-54 pCi/Filter pCi/Filter pCi/Filter 734 556
                                                    < 10 602 494
                                                                    < 50.0 452- 791 382 - 617 0.00- 50.0 Acceptable Acceptable Acceptable I
Zinc-65 Gross Alpha pCi/Filter
[pCi/Filter 573            419-Air Filter Gross Alpha/Beta 84      [    83 300 - 578 J 27.8-129 [ Acceptable Acceptable I
1 Gross Beta Americium-241 pCi/Filter pCi/L 47            56.3 Water Radionuclides 102            126 35.6-82.2 84.9- 169 Acceptable Acceptable I
Cesium-1 34 Cesium-137 Cobalt-60 pCi/L pCi/L pCi/L 1987 2801 1869 2180 2760 1890 1600-2510 2340-3310 1640 - 2210 Acceptable Acceptable Acceptable I
Manganese-54                  pCi/L          < 20          < 100        0.00 - 100          Acceptable Zinc-65                      pCi/L          1505            1370 Water Gross AlphalBeta 1140-1730             Acceptable               I Gross Alpha                  pCi/L            88            96.6        34.3 - 150          Acceptable Gross Beta                  pCi/L            56            84.5 Water Tritium 48.4- 125      I    Acceptable              I Tritium                      pCi/L      1  19762      [  19800    113300- 282001          Acceptable
        ,ctinium-228              pCi/kg Soil Radionuclides 1247            1240        795- 1720            Acceptable I
Bismuth-212                pCi/kg            983            1220        325 - 1790          Acceptable Bismuth-214 Cesium-1 34 pCi/kg pCi/kg 3593 2858 3740 2820 2250 - 5380 1840- 3390 Acceptable Acceptable I
Cesium-137                 pCi/kg          4422          4130        3160- 5310            Acceptable Cobalt-60 Lead-212 pCi/kg pCi/kg 5819 1146 5680 1220 3840 - 7820 799- 1700 Acceptable Acceptable I
Lead-214                    pCi/kg          3835          3740        2180 - 5580          Acceptable Manganese-54 Potassium-40 pCi/kg pCi/kg
                                                    < 100 10630
                                                                  < 1000 12400 0.00 - 1000 9080 - 16700 Acceptable Acceptable               I Zinc-65                    pCi/kg          3686          3160        2520-4200            Acceptable I
I I
I 2013 Annual Radiological Environmental Operating Report    6-6                  Energy Northwest/Columbia Generating Station I
 
TABLE 6-2 (cont)
ENW REMP PROGRAM CROSS CHECK PERFORMANCE RESULTS
                                              .2013 ERA Crosscheck Result Iodine-131 Charcoal Cartridge Acceptance          Performance Sample ID            Analysis            Units          Result. Ref Value            Limits          Evaluation 03131390A          Iodine-131         pCi/Filter         1174         1006           775-1328           Acceptable 09141205A           Iodine-131         pCi/Filter         332           289             223 - 382         Acceptable 2013 ERA RAD Results Iodine-131 in Milk
___    _   Acceptance         Performance Sample ID           Analysis             Units         Result     Ref Value           Limits           Evaluation RAD-94             Iodine-1 31           pCi/L           21.6         24.3           20.2-28.8           Acceptable 2013 Annual Radiological Environmental Operating Report   6-7                 Energy Northwest/Columbia Generating Station


==7.0 REFERENCES==
==7.0 REFERENCES==


==7.0 REFERENCES==
==7.0     REFERENCES==
: 1. Energy Northwest, "Columbia Generating Station Final Safety Analysis Report," Section 2.3.1.1.2. Nuclear Regulatory Commission Fact Sheet "Fact Sheet on Radiation Monitoring at Nuclear Power Plants and the "Tooth Fairy" Issue", NRC Library, www.nrc.gov/reading-rm/doc-collections/fact-sheets/.
: 1. Energy Northwest, "Columbia Generating Station Final Safety Analysis Report," Section 2.3.1.1.
: 3. The National Council on Radiation Protection and Measurements, 2006, "Cesium-137 in the Environment:
: 2. Nuclear Regulatory Commission Fact Sheet "Fact Sheet on Radiation Monitoring at Nuclear Power Plants and the "Tooth Fairy" Issue", NRC Library, www.nrc.gov/reading-rm/doc-collections/fact-sheets/.
Radioecology and Approaches to Assessment and Management", Report 154, NCRP, Bethesda, MD.4. U.S. Nuclear Regulatory Commission, "Programs For Monitoring Radioactivity in the Environs of Nuclear Power Plants," Regulatory Guide 4.1, Revision 1, April 1975.5. U.S. Nuclear Regulatory Commission, "Environmental Technical Specifications For Nuclear Power Plants," Regulatory Guide 4.8, December 1975.6. U.S. Nuclear Regulatory Commission, "An Acceptable Radiological Environmental Monitoring Program," Assessment Branch Technical Position Revision 1, November 1979.7. U.S. Nuclear Regulatory Commission, "Quality Assurance For Radiological Environmental Monitoring Program (Normal Operations), Effluent Streams and the Environment," Regulatory Guide 4.15, Revision 1, February 1979.8. U.S. Nuclear Regulatory Commission, "Performance, Testing and Procedural Specifications For Thermoluminescence Dosimetry-Environmental Applications," Regulatory Guide 4.13, Revision 1, July 1977.9. Energy Facility Site Evaluation Council, Resolution No. 332, approved February 21, 2012.10. Energy Northwest Nuclear Columbia Generating Station, Operating License NPF-21,"Technical Specifications" Sections 5.5.1 and 5.6.1 11. Columbia Generating Station Offsite Dose Calculation Manual (ODCM).12. Washington Administrative Code 173-200-040, "Water Quality Standards for Ground Water of the State of Washington  
: 3. The National Council on Radiation Protection and Measurements, 2006, "Cesium-137 in the Environment: Radioecology and Approaches to Assessment and Management", Report 154, NCRP, Bethesda, MD.
-Criteria." 13. Washington Administrative Code 173-201A, "Water Quality Standards for Surface Waters of the State of Washington." 14. Code of Federal Regulations, Title 10 Part 20, "Standards for Protection against Radiation." 15. Code of Federal Regulations, Title 10 Part 50, "Domestic Licensing of Production and Utilization Facilities." 2013 Annual Radiological Environmental Operating Report 7-1 Energy Northwest/Columbia Generating Station
: 4. U.S. Nuclear Regulatory Commission, "Programs For Monitoring Radioactivity in the Environs of Nuclear Power Plants," Regulatory Guide 4.1, Revision 1, April 1975.
: 16. Energy Facility Site Evaluation Council, Resolution No. 300, approved September 10, 2001.17. Nuclear Energy Institute, "Industry Ground Water Protection Initiative  
: 5. U.S. Nuclear Regulatory Commission, "Environmental Technical Specifications For Nuclear Power Plants," Regulatory Guide 4.8, December 1975.
-Final Guidance Document", NEI 07-07, Nuclear Energy Institute, 1776 I Street N. W., Suite 400, Washington D.C.18. Energy Facility Site Evaluation Council, Resolution No. 299, approved August 13, 2001.19. PNNL, 2007, "Summary of Hydrogeology and Evaluation of Existing Groundwater Monitoring Wells for Outfalls 002 and 003 at the Columbia generating Station", PNWD-3845, Pacific Northwest National Laboratory, Richland, WA.20. PNNL, 2009, "Hanford Site Environmental Monitoring Report for Calendar Year 2008", PNNL-18427, Pacific Northwest National Laboratory, Richland, WA 21. US DOE, 2013, "Hanford Site Environmental Report for Calendar Year 2012", DOE/RL-2013-18 Rev 0, US Dept. of Energy, Richland, WA 22. US DOE, 1995, "Hanford Site  
: 6. U.S. Nuclear Regulatory Commission, "An Acceptable Radiological Environmental Monitoring Program," Assessment Branch Technical Position Revision 1, November 1979.
: 7. U.S. Nuclear Regulatory Commission, "Quality Assurance For Radiological Environmental Monitoring Program (Normal Operations), Effluent Streams and the Environment,"
Regulatory Guide 4.15, Revision 1, February 1979.
: 8. U.S. Nuclear Regulatory Commission, "Performance, Testing and Procedural Specifications For Thermoluminescence Dosimetry-Environmental Applications," Regulatory Guide 4.13, Revision 1, July 1977.
: 9. Energy Facility Site Evaluation Council, Resolution No. 332, approved February 21, 2012.
: 10. Energy Northwest Nuclear Columbia Generating Station, Operating License NPF-21, "Technical Specifications" Sections 5.5.1 and 5.6.1
: 11. Columbia Generating Station Offsite Dose Calculation Manual (ODCM).
: 12. Washington Administrative Code 173-200-040, "Water Quality Standards for Ground Water of the State of Washington - Criteria."
: 13. Washington Administrative Code 173-201A, "Water Quality Standards for Surface Waters of the State of Washington."
: 14. Code of Federal Regulations, Title 10 Part 20, "Standards for Protection against Radiation."
: 15. Code of Federal Regulations, Title 10 Part 50, "Domestic Licensing of Production and Utilization Facilities."
2013 Annual Radiological Environmental Operating Report 7-1 Energy Northwest/Columbia Generating Station
 
I I
: 16. Energy Facility Site Evaluation Council, Resolution No. 300, approved September 10, 2001.
: 17. Nuclear Energy Institute, "Industry Ground Water Protection Initiative - Final Guidance I
Document", NEI 07-07, Nuclear Energy Institute, 1776 I Street N. W., Suite 400, Washington D.C.                                                                                         I
: 18. Energy Facility Site Evaluation Council, Resolution No. 299, approved August 13, 2001.
: 19. PNNL, 2007, "Summary of Hydrogeology and Evaluation of Existing Groundwater                             I Monitoring Wells for Outfalls 002 and 003 at the Columbia generating Station", PNWD-3845, Pacific Northwest National Laboratory, Richland, WA.
I
: 20. PNNL, 2009, "Hanford Site Environmental Monitoring Report for Calendar Year 2008",
PNNL-18427, Pacific Northwest National Laboratory, Richland, WA
: 21. US DOE, 2013, "Hanford Site Environmental Report for Calendar Year 2012", DOE/RL-I 2013-18 Rev 0, US Dept. of Energy, Richland, WA
: 22. US DOE, 1995, "Hanford Site  


==Background:==
==Background:==
Evaluation of Existing Soil Radionuclide Data",
I DOE/RL-95-55, US Dept. of Energy, Richland, WA.
: 23. PNNL, 2006, "Hanford Site Environmental Monitoring Report for Calendar Year 2005",
PNNL-15892, Pacific Northwest National Laboratory, Richland, WA i
: 24. Energy Northwest, 2012, "Soil and Vegetation Sampling Results of the Columbia I
Generating Station Storm Drain Pond For Samples Collected August 2011 ".
I I
I I
I I
I I
2013 Annual Radiological Environmental Operating Report 7-2  Energy Northwest/Columbia Generating Station I
8.0 ERRATA 8.0      ERRATA Revisions to the 2012 Annual Radiological Environmental Operating Report for the Columbia Generating Station are listed below.
In Section 4.2, second paragraph, annual TLDs are incorrectly identified as being used to monitor exposure rates at the Independent Spent Fuel Storage Installation (ISFSI). No annual TLDs were used to monitoi this facility in 2012, only quarterly TLDs were used.
2013 Annual Radiological Environmental Operating Report 8-1            Energy Northwest/Columbia Generating Station
ENERGY NORTHWEST People. Vision. Solutions APPENDIX A 2013 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT COLUMBIA GENERATING STATION DATA TABLES A and B Covers Sample Collection Period Starting January 2013 Through December 2013 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Prepared by:
Energy Northwest - Environmental Services Staff Richland, WA


Evaluation of Existing Soil Radionuclide Data", DOE/RL-95-55, US Dept. of Energy, Richland, WA.23. PNNL, 2006, "Hanford Site Environmental Monitoring Report for Calendar Year 2005", PNNL-15892, Pacific Northwest National Laboratory, Richland, WA 24. Energy Northwest, 2012, "Soil and Vegetation Sampling Results of the Columbia Generating Station Storm Drain Pond For Samples Collected August 2011 ".I I I I I I I I i I I I I I I I I I I 2013 Annual Radiological Environmental Operating Report 7-2 Energy Northwest/Columbia Generating Station 8.0 ERRATA 8.0 ERRATA Revisions to the 2012 Annual Radiological Environmental Operating Report for the Columbia Generating Station are listed below.In Section 4.2, second paragraph, annual TLDs are incorrectly identified as being used to monitor exposure rates at the Independent Spent Fuel Storage Installation (ISFSI). No annual TLDs were used to monitoi this facility in 2012, only quarterly TLDs were used.2013 Annual Radiological Environmental Operating Report 8-1 Energy Northwest/Columbia Generating Station ENERGY NORTHWEST People. Vision. Solutions APPENDIX A 2013 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT COLUMBIA GENERATING STATION DATA TABLES A and B Covers Sample Collection Period Starting January 2013 Through December 2013 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Prepared by: Energy Northwest
APPENDIX A - TABLE OF CONTENTS TABLE A: ROUTINE RESULTS A-1 .1  2013 Quarterly TLD Results A-1.2  2013 Quarterly TLD Results - Summary A-2.1  Gross Beta on Air Particulate Filters A-2.2  Gross Beta on Air Particulate Filters - Summary A-3.1  Gamma Spectrometry Results of Air Particulate Filters A-3.2   Gamma Spectrometry Results of Air Particulate Filters - Summary A-4.1  Gamma Spectrometry Results of Iodinel3l on Charcoal Filters A-4.2  Gamma Spectrometry Results of Iodinel3l on Charcoal Filters - Sunmary A-5.1  Gross Beta in Water A-5.2   Gross Beta in Water - Summary A-6.1   Tritium in Water A-6.2  Tritium in Water - Summary A-7.1  Gamma Spectrometry Results of Water A-7.2  Gamma Spectrometry Results of Water - Summary A-8.1   Gamma Spectrometry Results of Soil A-8.2   Gamma Spectrometry Results of Soil - Summary A-9.1   Gamma Spectrometry Results of Sediment A-9.2   Gamma Spectrometry Results of Sediment - Summary A-10.1 Gamma Spectrometry Results of Fish A-10.2 Gamma Spectrometry Results of Fish - Summary A-11.1 Iodine 131 in Milk A-11.2 Iodine 131 in Milk - Summary A-12.1 Gamma Spectrometry Results of Milk A-12.2 Gamma Spectrometry Results of Milk - Summary A- 15.1 Gamma Spectrometry Results of Root Crops A-15.2 Gamma Spectrometry Results of Root Crops - Summary A-16.1 Gamma Spectrometry Results of Fruits A-16.2 Gamma Spectrometry Results of Fruits - Summary A-17.1 Gamma Spectrometry Results of Vegetables A-17.2 Gamma Spectrometry Results of Vegetables - Summary i
-Environmental Services Staff Richland, WA APPENDIX A -TABLE OF CONTENTS TABLE A: ROUTINE RESULTS A-1 .1 2013 Quarterly TLD Results A-1.2 2013 Quarterly TLD Results -Summary A-2.1 Gross Beta on Air Particulate Filters A-2.2 Gross Beta on Air Particulate Filters -Summary A-3.1 Gamma Spectrometry Results of Air Particulate Filters A-3.2 Gamma Spectrometry Results of Air Particulate Filters -Summary A-4.1 Gamma Spectrometry Results of Iodinel3l on Charcoal Filters A-4.2 Gamma Spectrometry Results of Iodinel3l on Charcoal Filters -Sunmary A-5.1 Gross Beta in Water A-5.2 Gross Beta in Water -Summary A-6.1 Tritium in Water A-6.2 Tritium in Water -Summary A-7.1 Gamma Spectrometry Results of Water A-7.2 Gamma Spectrometry Results of Water -Summary A-8.1 Gamma Spectrometry Results of Soil A-8.2 Gamma Spectrometry Results of Soil -Summary A-9.1 Gamma Spectrometry Results of Sediment A-9.2 Gamma Spectrometry Results of Sediment -Summary A-10.1 Gamma Spectrometry Results of Fish A-10.2 Gamma Spectrometry Results of Fish -Summary A-11.1 Iodine 131 in Milk A-11.2 Iodine 131 in Milk -Summary A-12.1 Gamma Spectrometry Results of Milk A-12.2 Gamma Spectrometry Results of Milk -Summary A- 15.1 Gamma Spectrometry Results of Root Crops A-15.2 Gamma Spectrometry Results of Root Crops -Summary A-16.1 Gamma Spectrometry Results of Fruits A-16.2 Gamma Spectrometry Results of Fruits -Summary A-17.1 Gamma Spectrometry Results of Vegetables A-17.2 Gamma Spectrometry Results of Vegetables
 
-Summary i APPENDIX A -TABLE OF CONTENTS -TABLE B: SPECIAL INTEREST SAMPLE RESULTS 3 B-1.1 2013 Quarterly Special Interest TLD Results 5 B-1.2 2013 Quarterly Special Interest TLD Results -Summary B-2.1 Gamma Spectrometry Results of Storm Drain Water n B-2.2 Gamma Spectrometry Results of Storm Drain Water -Summary B-3.1 Gross Beta in Storm Drain Water 5 B-3.2 Gross Beta in Storm Drain Water -Summary B-4.1 Tritium in Storm Drain Water B-4.2 Tritium in Storm Drain Water -Summary B-5.1 Gross Alpha in Sanitary Waste Treatment Water &#xa3;B-5.2 Gross Alpha in Sanitary Waste Treatment Water -Summary B-6.1 Gross Beta in Sanitary Waste Treatment Water 3 B-6.2 Gross Beta in Sanitary Waste Treatment Water -Summary B-7.1 Gamma Spectrometry Results of Sanitary Waste Treatment Water 3 B-7.2 Gamma Spectrometry Results of Sanitary Waste Treatment Water -Summary B-8.1 Tritium in Sanitary Waste Treatment Water B-8.2 Tritium in Sanitary Waste Treatment Water -Summary B-10.1 Gamma Spectrometry Results of Groundwater Monitoring Well Samples 3 B-10.2 Gamma Spectrometry Results of Groundwater Monitoring Well Samples -Summary B-11.1 Tritium in Groundwater Monitoring Well Samples 3 B-12-1 Gamma Spectrometry Results of CGS Storm Drain Pond Soil I!I I I ii l FORWARD Since mid-1984, the results of the REMP analyses have been presented as net results calculated from total counts minus the observed background counts of the detection method. Counting results for low level samples are often within the counting error of the background determination; consequently results can range from negative to positive values, in these samples. Though most of the analytical results presented in this Appendix are below the detection limit, listing the actual calculated value, even when it is negative or below the detection limit, prevents positive biases and loss of individual results inherent in the use of "less than" (<) values. It is recommended practice to report radiological environmental data in this manner.Most results listed in this Appendix are accompanied by a plus or minus (+) error value. In most cases the error value represents the two sigma counting uncertainty determined for that particular analysis.
APPENDIX A - TABLE OF CONTENTS                              -
These error values are in the same units as the listed activity values. The two sigma error value represents the range that a recount of the same sample would be expected to fall within 95%.of the time, based on the statistics encountered in the original count.Also included in most cases are the analysis specific, minimum detectable activity (MDA) values.Though similar in concept to the LLD, these values are based on the statistics encountered in the specific sample count itself and not a blank determination.
TABLE B: SPECIAL INTEREST SAMPLE RESULTS                          3 B-1.1  2013 Quarterly Special Interest TLD Results                                 5 B-1.2 2013 Quarterly Special Interest TLD Results - Summary B-2.1 Gamma Spectrometry Results of Storm Drain Water                            n B-2.2 Gamma Spectrometry Results of Storm Drain Water - Summary B-3.1 Gross Beta in Storm Drain Water                                            5 B-3.2 Gross Beta in Storm Drain Water - Summary B-4.1 Tritium in Storm Drain Water B-4.2 Tritium in Storm Drain Water - Summary B-5.1 Gross Alpha in Sanitary Waste Treatment Water                              &#xa3; B-5.2 Gross Alpha in Sanitary Waste Treatment Water - Summary B-6.1 Gross Beta in Sanitary Waste Treatment Water                                3 B-6.2 Gross Beta in Sanitary Waste Treatment Water - Summary B-7.1 Gamma Spectrometry Results of Sanitary Waste Treatment Water                3 B-7.2 Gamma Spectrometry Results of Sanitary Waste Treatment Water - Summary B-8.1  Tritium in Sanitary Waste Treatment Water B-8.2  Tritium in Sanitary Waste Treatment Water - Summary B-10.1 Gamma Spectrometry Results of Groundwater Monitoring Well Samples          3 B-10.2 Gamma Spectrometry Results of Groundwater Monitoring Well Samples - Summary B-11.1 Tritium in Groundwater Monitoring Well Samples                              3 B-12-1 Gamma Spectrometry Results of CGS Storm Drain Pond Soil I
As such, they are a aposteriori (after the fact) determination where the LLD is a a priori (before the fact) determination.
I I
These values were included as they represent the level of activity that would have needed to be present in the sample for a positive identification to be made. .iii TABLE A-1.1 2013 QUARTERLY TLD RESULTS Results in milli-Roentgen (mR) per Standard Quarter Quarterly Station ID 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Sum 1 22.0 21.3 22.4 22.8 88.4 2 21.6 19.9 22.0 22.2 85.6 3 19.1 19.9 21.4 21.0 81.4 4 18.5 18.7 19.5 19.9 76.6 5 19.7 18.7 19.6 20.2 78.0 6 19.1 18.6 19.3 19.9 76.9 7 20.1 20.1 21.4 21.3 82.8 8 22.7 22.5 23.7 23.8 92.7 9 20.8 18.9 21.7 20.7 82.1 10 19.6 19.5 21.0 21.4 81.5 11 20.8 20.2 21.3 21.7 84.1 12 21.9 21.6 23.8 23.2 90.5 13 19.9 19.9 21.4 21.4 82.7 14 20.2 20.3 21.6 21.7 83.9 15 21.3 22.2 22.5 23.8 89.7 16 19.9 20.7 21.9 22.7 85.3 17 20.8 22.6 22.9 23.7 90.1 18 23.5 21.0 22.9 22.9 90.3 19 22.2 21.1 23.2 22.9 89.5 20 20.1 20.8 22.5 22.6 86.0 21 19.2 18.9 20.6 20.3 79.0 22 20.0 20.2 21.6 21.8 83.5 23 20.8 19.7 21.7 22.2 84.3 24 20.1 20.5 21.6 22.2 84.5 25 21.4 22.5 22.4 24.9 91.2 40 18.7 18.2 19.2 19.4 75.5 41 20.5 21.0 21.3 22.7 85.4 42 20.4 20.0 21.1 21.4 82.9 43 21.6 21.1 22.8 21.8 87.4 44 19.4 20.1 19.9 19.6 78.9 45 18.8 19.7 20.1 21.4 80.1 46 24.7 25.7 27.3 27.3 105.0 47 18.6 18.8 20.4 20.1 77.9 49 20.0 20.8 22.1 22.2 85.0 50 19.5 20.4 21.0 22.3 83.2 51 19.6 19.6 21.4 21.3 81.9 53 20.8 20.2 21.0 21.6 83.5 54 20.3 20.5 22.0 22.8 85.6 55 21.4 20.0 22.2 21.5 85.1 56 21.3 22.0 22.1 23.1 88.5 65 19.1 18.5 20.2 20.3 78.1 71 23.5 22.5 26.1 26.9 99.0 72 23.7 21.6 26.0 25.0 96.3 Page 1 of 2
I ii                        l
..i .I -: TABLE A-1.1, : 2013 QUARTERLY TLD RESULTS Results in milli-Roentgen (mR) per Standard Quarter Quarterly 3rd Quarter 4th Quarter Sum Station ID 1st Quarter 2nd Quarter 73 74 75 76 77 78 79 80 81 82 83 84 85 86 21.0 22.0 21.6 21.0 21.3 20.3 20.6 21.1 20.0 21.8 21.2 20.5 21.5.27.0 19.7 21.6 21;2 20.3 20.3-20.7 20.4 19.7 20.0 21.1 20.4 20.8 22.1 26.0 22.5 24.3,-23.1 22.8 22.5 21.2 22.0 22.4 20.8 22.9 21.6 24.2 23.0 29.7 23.9 24.5 22.9 21.4 21.7 21.8 22.5 21.8 21.9 23.0 22.5 23.0 24.2 28.9 87.1 92.4 88.9 85.5 85.8 84.0 85.6 85.0 82.6 88.8 85.7 88.6 90.7 111.6 I i I I i i I I i i I I I I t I I I I TABLE A-1.2 2013 QUARTERLY TLD RESULTS-  
 
FORWARD Since mid-1984, the results of the REMP analyses have been presented as net results calculated from total counts minus the observed background counts of the detection method. Counting results for low level samples are often within the counting error of the background determination; consequently results can range from negative to positive values, in these samples. Though most of the analytical results presented in this Appendix are below the detection limit, listing the actual calculated value, even when it is negative or below the detection limit, prevents positive biases and loss of individual results inherent in the use of "less than" (<) values. It is recommended practice to report radiological environmental data in this manner.
Most results listed in this Appendix are accompanied by a plus or minus (+) error value. In most cases the error value represents the two sigma counting uncertainty determined for that particular analysis. These error values are in the same units as the listed activity values. The two sigma error value represents the range that a recount of the same sample would be expected to fall within 95%.of the time, based on the statistics encountered in the original count.
Also included in most cases are the analysis specific, minimum detectable activity (MDA) values.
Though similar in concept to the LLD, these values are based on the statistics encountered in the specific sample count itself and not a blank determination. As such, they are a aposteriori(after the fact) determination where the LLD is a a priori(before the fact) determination. These values were included as they represent the level of activity that would have needed to be present in the sample for a positive identification to be made.          .
iii
 
TABLE A-1.1 2013 QUARTERLY TLD RESULTS Results in milli-Roentgen (mR) per Standard Quarter Quarterly Station ID 1st Quarter  2nd Quarter      3rd Quarter    4th Quarter      Sum 1        22.0          21.3            22.4            22.8          88.4 2        21.6          19.9            22.0            22.2          85.6 3        19.1          19.9            21.4            21.0          81.4 4        18.5          18.7            19.5            19.9          76.6 5        19.7          18.7            19.6            20.2         78.0 6         19.1          18.6             19.3            19.9         76.9 7        20.1          20.1            21.4           21.3          82.8 8        22.7           22.5             23.7            23.8          92.7 9        20.8          18.9            21.7           20.7          82.1 10        19.6           19.5            21.0            21.4          81.5 11        20.8          20.2            21.3            21.7          84.1 12        21.9          21.6            23.8            23.2          90.5 13        19.9           19.9            21.4            21.4          82.7 14        20.2          20.3            21.6           21.7          83.9 15        21.3          22.2            22.5           23.8         89.7 16        19.9          20.7            21.9            22.7         85.3 17        20.8          22.6             22.9            23.7          90.1 18        23.5           21.0            22.9            22.9         90.3 19         22.2          21.1            23.2            22.9          89.5 20        20.1          20.8            22.5            22.6         86.0 21         19.2          18.9             20.6            20.3         79.0 22         20.0          20.2             21.6            21.8         83.5 23        20.8          19.7             21.7            22.2          84.3 24        20.1          20.5            21.6           22.2          84.5 25        21.4          22.5            22.4            24.9         91.2 40        18.7          18.2              19.2           19.4          75.5 41        20.5          21.0            21.3            22.7          85.4 42        20.4          20.0            21.1            21.4          82.9 43        21.6           21.1            22.8            21.8          87.4 44        19.4          20.1              19.9          19.6          78.9 45        18.8           19.7             20.1            21.4          80.1 46        24.7          25.7            27.3           27.3          105.0 47        18.6           18.8            20.4           20.1          77.9 49        20.0          20.8            22.1            22.2         85.0 50        19.5           20.4            21.0           22.3         83.2 51        19.6          19.6            21.4            21.3          81.9 53        20.8          20.2            21.0            21.6          83.5 54        20.3          20.5            22.0            22.8         85.6 55        21.4           20.0            22.2            21.5          85.1 56        21.3           22.0             22.1            23.1         88.5 65        19.1          18.5            20.2            20.3          78.1 71        23.5          22.5            26.1            26.9          99.0 72        23.7          21.6             26.0            25.0          96.3 Page 1 of 2
 
I
                                              .   .*i . .I-:
TABLE A-1.1,        :
i 2013 QUARTERLY TLD RESULTS Results in milli-Roentgen (mR) per Standard Quarter Quarterly I
Station ID 73 1st Quarter 21.0 2nd Quarter 19.7 3rd Quarter 22.5 4th Quarter 23.9 Sum 87.1 I
74 75 76 22.0 21.6 21.0 21.6 21;2 20.3 24.3,-
23.1 22.8 24.5 22.9 21.4 92.4 88.9 85.5 i
77            21.3            20.3              22.5          21.7          85.8 78 79 20.3 20.6
                                -20.7 20.4 21.2 22.0 21.8 22.5 84.0 85.6 i
80            21.1            19.7             22.4           21.8          85.0 81 82 20.0 21.8 20.0 21.1 20.8 22.9 21.9 23.0 82.6 88.8 I
83            21.2            20.4              21.6          22.5          85.7 84 85 86 20.5 21.5
                .27.0 20.8 22.1 26.0 24.2 23.0 29.7 23.0 24.2 28.9 88.6 90.7 111.6 I
i i
TABLE A-1.2 2013 QUARTERLY TLD RESULTS-  


==SUMMARY==
==SUMMARY==
Results in milli-Roentgen (mR) per
 
Results in milli-Roentgen (mR) per Standard Quarter I
Average          Activity        Activity      Number of Location          Activity            Low          High          Samples I
Quarterly Indicator TLDs        21.5              18.2          29.7          224 Quarterly Control TLDs        20,5              18.9          21.7            4                I I
t I
I I
Page 2 of 2 I
 
TABLE A-2.1 GROSS BETA ON AIR PARTICULATE FILTERS
                                      .; - .. .., .Results in pCi per Cubic Meter Station 01                          Station 04              Station 05 Collection Period


==SUMMARY==
==SUMMARY==
Results in pCi per cubic meter Average Activity Activity Number of Number of Activity Low High Samples Positive IDs LOCATION Gross Beta Indicators Gross Beta Controls 2.18E-02 2.99E-03 1.39E-01 1.89E-02 3.22E-03 1.06E-01 570 52 570 52 Page 1 of 1 TABLE A-3.1 GAMMA SPECTROMETRY RESULTS OF AIR PARTICULATEFILTERS Results in pCi/cubic meter, results decay corrected to midpoint of the sample collection period Location and Quarter FN-uciide RQ' Activity Station 1 1stQ 2013 Error MDA Location and Quarter Station 1 Nuclide.
 
Error 2nd Q 2013 MDA BE-7 K-40 MN-54 FE-59 CO-60 ZN-65 ZRNB-95 CS-134 CS-1 37 BALA140 RU-106+ 7.16E-02 +4.58E-04 +3.61E-05 +4.31E-04 +7.77E-05 +0.OOE+00 +-1.75E-04
Results in pCi per cubic meter Average      Activity    Activity Number of  Number of LOCATION            Activity        Low        High    Samples  Positive IDs Gross Beta Indicators        2.18E-02    2.99E-03    1.39E-01    570        570 Gross Beta Controls        1.89E-02    3.22E-03    1.06E-01      52        52 Page 1 of 1
+0.OOE+00 +-4.16E-06
 
 
I TABLE A-3.1 GAMMA SPECTROMETRY RESULTS OF AIR PARTICULATEFILTERS Results in pCi/cubic meter, results decay corrected to midpoint of the sample collection period I
Location and Quarter FN-uciide RQ' Activity Station 1 Error 1stQ 2013 MDA Location and Quarter Nuclide.**Q**-Activity.
Station 1 Error 2nd Q 2013 MDA I
BE-7 K-40 MN-54 FE-59
                    + 7.16E-02 4.58E-04 3.61E-05 4.31E-04
                                      +
                                      +
                                      +
                                      +
1.49E-02 4.95E-03 5.73E-04 2.60E-03 1.11 E-02 9.02E-03 9.32E-04 4.10E-03 BE-7
                                                                                    .K-40 MN-54 FE-59
                                                                                                      +    1.O0E-0t +
3.14E-03 1.56E-04 1.73E-03
                                                                                                                      +
                                                                                                                      +
                                                                                                                      +
1.59E-02 6.73E-03 5.18E-04 2.71 E-03 9.41 E-03 1.09E-02 7.98E-04 3.68E-03 I
CO-60 ZN-65 ZRNB-95 7.77E-05 0.OOE+00
                        -1.75E-


==SUMMARY==
==SUMMARY==
Results in pCi/cubic meter, results decay corrected to midlpoint of the sample collection period Average Activity Activity .Average Activity Low High MDA Number of Samples I I Number of Positive IDs Nuclide BALA140 Ind BALA140 Cntl BE-7 Ind BE-7 CntI CO-60 -Ind CO-60 Cntl CS-134 Ind CS-134 CntI CS-137 Ind CS-1 37 CntI FE-59 Ind FE-59 Cntl K-40 Ind K-40 CntI MN-54 Ind MN-54 Cntl RU-1 06 Ind RU-106 .CntI ZN-65 Ind ZN-65 Cntl ZRNB-95 Ind ZRNB-95 CntI-5.13E-04 1.41 E-03 1.06E-01 9.96E-02 1.78E-05 5.38E-05-4.16E-05-3.06E-05-3.87E-06-6.04E-05-5.69E-05-2.07E-04 2.22E-04-1.22E-03 2.54E-05 4.65E-05 9.20E-05 4.18E-04-1.07E-04-4.99E-04-6.19E-03 ,-1 .45E-04 7.05E-02 6.87E-02-1.79E-04-1.01E-04-4.57E-04-1.51 E-04-1.93E-04-1.47E-04-1.61 E-03-6.31 E-04-4.15E-03-2.50E-03-3.15E-04-6.71 E-05-1.92E-03-7.41 E-05-1.26E-03-1.45E-03 5.17E-03 5.78E-03 1.63E-01 1.36E-01 3.21 E-04 3.35E-04 1.61 E-04 4.41 E-05 2.80E-04 2.60E-05 2.12E-03 2.09E-04 4.57E-03-5.77E-05 2.92E-04 2.53E-04 2.08E-03 1.17E-03 6.96E-04 1.30E-05 2.08E-02 3.03E-02 9.07E-03 8.99E-03 8.
 
Results in pCi/cubic meter, results decay corrected to midlpoint of the sample collection period I
Nuclide Average Activity Activity Low Activity . Average High          MDA Number of Number of Samples Positive IDs I
BALA140 Ind -5.13E-04 -6.19E-03                      5.17E-03      2.08E-02          44                0 BALA140 Cntl 1.41 E-03 ,-1 .45E-04                    5.78E-03      3.03E-02          .4                0 BE-7          Ind      1.06E-01      7.05E-02        1.63E-01      9.07E-03          44                44 BE-7        CntI      9.96E-02      6.87E-02        1.36E-01      8.99E-03            4                4 CO-60        -Ind      1.78E-05      -1.79E-04        3.21 E-04    8.40E-04          44                0 CO-60        Cntl      5.38E-05      -1.01E-04        3.35E-04      6.93E-04            4                0 CS-134        Ind -4.16E-05          -4.57E-04        1.61 E-04    7.88E-04          44                0 CS-134      CntI -3.06E-05          -1.51 E-04      4.41 E-05    7.69E-04            4                0 CS-137 CS-1 37 Ind -3.87E-06 CntI -6.04E-05
                                                    -1.93E-04
                                                    -1.47E-04 2.80E-04 2.60E-05 7.63E-04 7.51 E-04 44 4
0 0
I FE-59        Ind -5.69E-05          -1.61 E-03      2.12E-03      4.86E-03          44                0 FE-59        Cntl -2.07E-04          -6.31 E-04      2


==SUMMARY==
==SUMMARY==
Results in pCi per cubic meter, corrected for decay during collection period Average Activity Activity Average Number of Number of Nuclide Activity Low High MDA Samples Positive IDs 1-131 Ind 3.40E-04 -4.55E-03:
 
8.68E-03 1.33E-02 570 0 1-131 Cntl 4.51E-04 -4.39E-03 4.95E-03 1:29E-02 52 0 Ind = Indicator Stations Cntl = Control Station Page 1 of 1 TABLE A-5.1', GROSS BETA IN WATER Results in pCi per liter ST 26 River/Drinking Cnti ST 29 River/Drinking Ind Collection Period RQ Activity Error MDA RQ Activity Error MDA 01/02/13.-
Results in pCi per cubic meter, corrected for decay during collection period Average             Activity           Activity         Average           Number of Number of Nuclide             Activity             Low               High               MDA             Samples Positive IDs 1-131         Ind     3.40E-04         -4.55E-03:         8.68E-03           1.33E-02           570         0 1-131         Cntl     4.51E-04         -4.39E-03           4.95E-03           1:29E-02           52         0 Ind = Indicator Stations Cntl = Control Station                                                                       Page 1 of 1
01/31/13 5.76E-02 + 7.08E-01 2.56E+00 3.68E-01 + 7.42E-01 2.56E+00 01/31/13-02/28/13 2.81E-01 + 8.01E-01 2.77E+00 -4.66E-01  
 
+ 8.02E-01 2.77E+00 02/28/13 -04/01/13 -5.85E-01  
I TABLE A-5.1',
+ 7.25E-01 2.49E+00 -1.15E-01  
GROSS BETA IN WATER 1
+ 6.96E-01 2.50E+00 04/01/13 -04/30/13 -1.60E+00  
Results in pCi per liter I
+ 8.22E-01 2.64E+00 -4.64E-01  
ST 26 River/Drinking Cnti                             ST 29 River/Drinking Ind Collection 01/02/13.-
+- 7.60E-01 2.64E+00 04/30/13.-
01/31/13-Period 01/31/13 02/28/13 RQ Activity 5.76E-02 + 7.08E-01 2.81E-01 + 8.01E-01 Error          MDA 2.56E+00 2.77E+00 RQ Activity            Error 3.68E-01 + 7.42E-01
05/31/1.3 9.72E-01 + 7.75E-01 2.61E+00 1.33E-01 + 7.31E-01 2.61E+00 05/31/13 -07/01/13 6.33E-01 + 6.94E-01 2.38E+00 4.01E-01 + 6.85E-01 2.38E+00 07/01/13 -08/01/13 .2.87E-01  
                                                                                            -4.66E-01 + 8.02E-01 MDA 2.56E+00 2.77E+00 I
+ 6.91E-01 2.43E+00 -3.19E-01  
02/28/13 -
+ 6.86E-01 2.43E+00 08/01/13 -09/02/13 5.71E-01 + 7.69E-01 2.61E+00 1.01E+00 + 7.88E-01 2.61E+00 09/02/13 -09/30/13 1.99E+00 + 7.39E-01 2.23E+00 4.29E-01 + 6.41E-01 2.22E+00 09/30/13 -11/01/13 7.76E-01 + 7.03E-01 2.34E+00 1.08E+00 + 7.59E-01 2.34E+00 11/01/13 -12/02/13 9.24E-01 + 7.21E-01 2.31E+00 5.83E-01 + 6.64E-01 2.27E+00 12/02/13 -01/02/14 5.77E-01 + 6.54E-01 2.25E+00 -2.02E-01  
04/01/13 -
+ 6.32E-01 2.25E+00 ST 27 CW Discharge Collection Period IRQ Activity Error MDA 01/02/13 -. 01/31/13 + 6.02E+00 + 1.17E+00 3.06E+00 01/31/13.-
04/30/13.-
02/28/13 + 3.73E+00 + 1.09E+00 3.20E+00 02/28/13 -04/01/13 + 6.86E+00 + 1.20E+00 3.04E+00 04/01/13 -04/30/13 + 5.22E+00 + 1.16E+00 3.16E+00 04/30/13 -05/31/13 + 5.05E+00 + 1.1OE+00 3.03E+00 05/31/13 -. 07/01/13 1.20E+00 + 7.51E-01 2.42E+00 07/01/13 -08/01/13 + 3.77E+00 + 1.04E+00 2.94E+00 08/01/13 -09/02/13 2.90E+00 + 1.01E+00 3.04E+00 09/02/13 -09/30/13 + 7.05E+00 + 1.1OE+00 2.57E+00 09/30/13 -11/01/13 + 8.41E+00 + 1.27E+00 2.94E+00 11/01/13 -12/02/13 + 7.95E+00 + 1.20E+00 2.76E+00 12/02/13 -01/02/14 + 1.18E+01 + 1.33E+00 2.68E+00 I 1 I I i i i i I I I I I S.. " TABLE A-5.2 GROSS BETA IN WATER -
04/01/13 04/30/13 05/31/1.3
                                      -5.85E-01 + 7.25E-01
                                      -1.60E+00 + 8.22E-01 9.72E-01 + 7.75E-01 2.49E+00 2.64E+00 2.61E+00
                                                                                            -1.15E-01 + 6.96E-01
                                                                                            -4.64E-01 +- 7.60E-01 1.33E-01 + 7.31E-01 2.50E+00 2.64E+00 2.61E+00 i
05/31/13 -     07/01/13           6.33E-01 + 6.94E-01           2.38E+00               4.01E-01 + 6.85E-01       2.38E+00 07/01/13 -
08/01/13 -
08/01/13 09/02/13
                                      .2.87E-01 + 6.91E-01 5.71E-01 + 7.69E-01 2.43E+00 2.61E+00
                                                                                            -3.19E-01 + 6.86E-01 1.01E+00 + 7.88E-01 2.43E+00 2.61E+00 i
09/02/13 -     09/30/13           1.99E+00 + 7.39E-01           2.23E+00               4.29E-01 + 6.41E-01       2.22E+00 09/30/13 -
11/01/13 -
12/02/13 -
11/01/13 12/02/13 01/02/14 7.76E-01 + 7.03E-01 9.24E-01 + 7.21E-01 5.77E-01 + 6.54E-01 2.34E+00 2.31E+00 2.25E+00 1.08E+00 + 7.59E-01 5.83E-01 + 6.64E-01
                                                                                            -2.02E-01 + 6.32E-01 2.34E+00 2.27E+00 2.25E+00 i
Collection    Period      IRQ ST 27 CW Discharge Activity           Error         MDA i
01/02/13 -. 01/31/13       +   6.02E+00 + 1.17E+00             3.06E+00 01/31/13.-
02/28/13 -
02/28/13 04/01/13
                                  +
                                  +
3.73E+00 + 1.09E+00 6.86E+00 + 1.20E+00 3.20E+00 3.04E+00                                                       I 04/01/13 -     04/30/13       +   5.22E+00 + 1.16E+00             3.16E+00 04/30/13 -
05/31/13 -.
07/01/13 -
05/31/13 07/01/13 08/01/13
                                  +
                                  +
5.05E+00 + 1.1OE+00 1.20E+00 + 7.51E-01 3.77E+00 + 1.04E+00 3.03E+00 2.42E+00 2.94E+00 I
08/01/13 -     09/02/13           2.90E+00 + 1.01E+00             3.04E+00 09/02/13 -
09/30/13 -
09/30/13 11/01/13
                                  +
                                  +
7.05E+00 + 1.1OE+00 8.41E+00 + 1.27E+00 2.57E+00 2.94E+00 I
11/01/13 -     12/02/13       +   7.95E+00 + 1.20E+00             2.76E+00 12/02/13 -   01/02/14       +   1.18E+01 + 1.33E+00             2.68E+00 I
S..   " TABLE A-5.2 GROSS BETA IN WATER -  


==SUMMARY==
==SUMMARY==
Results in pCi per liter Average Activity Activity Location Activity Low High Number of Samples Number i of Positive IDs i ST 26 Control ST 29 Indicator ST 27 Discharge 4.07E-01 -1.60E+00 1.99E+00 2.03E-01 -4.66E-01 1.08E+00 5.83E+00 1.20E+00, 1.18E+01 12 12 12 0 0 10 n I I I I RQ = Results Qualifier.
 
If blank, result is less thandetection limit. If "+', result is above detection limit.Page 1 of 1 TABLE A-6.1 TRITIUM IN WATER Results in pCi peqrliter, MDA for all samnples is 300 pCi/I Location Description Collection Period RQ Activity Error 26 River/Drinking Control 29 River/Drinking Indicator 27 Plant Discharge 31 Ground Water Well 1 32 Ground Water Well 2 52 Ground Water Well 3 01/02/13'04/01/1.3 07/01/13 11/01/13 01/02/13 04/01/13 07/01/13 11/01/13 01/02/13 04/01/13 07/0.1/13 11/01/13 03/06/13 06/05/13 09/04/13 12/16/13 03/06/13 06/05/13 09/04/13 12/11/13 03/06/13 06/05/13 09/04/13 12/1.1/13 04/01/13 07/01/13.-' 11/01/13 01/02./14 04
I Results in pCi per liter Number Number of i
Average            Activity    Activity                  of            Positive Location            Activity            Low            High              Samples            IDs                  i n
ST 26 Control ST 29 Indicator 4.07E-01 2.03E-01
                                                        -1.60E+00
                                                        -4.66E-01 1.99E+00 1.08E+00 12 12 0
0 I
ST 27 Discharge            5.83E+00          1.20E+00,    1.18E+01                  12              10 I
I RQ = Results Qualifier. If blank, result is less thandetection limit. If "+', result is above detection limit.            Page 1 of 1 I
 
TABLE A-6.1 TRITIUM IN WATER Results in pCi peqrliter, MDA for all samnples is 300 pCi/I Location            Description                  Collection Period                  RQ          Activity        Error 26        River/Drinking Control          01/02/13            04/01/13                      1.48E+02      9.39E+01
                                                  '04/01/1.3          07/01/13.                      1.68E+02      .9.41 E+01 07/01/13      -'  11/01/13                      8.28E+01      9.44E+01 11/01/13            01/02./14                      7.77E+01      9.69E+01 29        River/Drinking Indicator        01/02/13            04/01/13                      1.35E+02    9.51 E+01 04/01/13            07/01/13                      1.67E


==SUMMARY==
==SUMMARY==
RIVER/DRINKING WATER Nuclide Average Activity Activity Low BALA140 BALA140 BI-214 BI-214 CO-58 CO-58 CO-60 CO-60 CR-51 CR-51 CS-134 CS-134 CS-137 CS-1 37 FE-59 FE-59 1-131 1-131 K-40 K-40 MN-54 MN-54 ZN-65 ZN-65 ZRNB-95 ZRNB-95 Ind Cntl Ind Cntl Ind CntU Ind Cntl Ind Cntl Ind Cntl Ind Cntl Ind Cntl Ind Cntl Ind Cntl Ind Cntl Ind Cntl Ind Cntl-5.19E-01-9.65E-01 1.85E+00 7.27E+00 1.59E-01 3.71 E01 2.97E-01-4.53E-01.
 
1.84E+00-3.87E+00-8.18E-01-2.65E-01-1.03E-01 8.31 E-02-1.48E-01 9.23E-02-3.93E-01 1.09E+00-3.31 E+01-3.52E+01 2.37E-01 4.07E-01-2.61 E-01-4.44E-01-2.52E-01-7.72E-01-2.09E+00-3.43E+00-4.83E+00-1.74E+00-6.56E-01-4.49E-01-5.92E-01-1.27E+00-1.83E+01-1.05E+01-1.79E+00-8.62E-01-1.48E+00-1.16E+00-1.97E+00-2.03E+00-5.95E+00-1.83E+00-5.21 E+01-5.01E+01-1.16E+00-1.01E+00.
RIVER/DRINKING WATER Average       Activity    Activity   Average  Number of  Number of Nuclide Activity       Low       High,      MDA      Samples  Positive IDs BALA140           Ind       -5.19E-01   -2.09E+00    1.37E+00   8.96E+00   12 BALA140          Cntl      -9.65E-01   -3.43E+00    1.OOE+00    8.27E+00    12 BI-214            Ind      1.85E+00     -4.83E+00    6.79E+00   9.19E+00    12 BI-214          Cntl      7.27E+00    -1.74E+00    4.22E+01   8.93E+00    12 CO-58            Ind        1.59E-01     -6.56E-01   1.62E+00   3.50E+00    12 CO-58            CntU        3.71 E01    -4.49E-01   1.06E+00    3.30E+00    12 CO-60            Ind        2.97E-01     -5.92E-01   1.78E+00   3.33E+00     12 CO-60            Cntl      -4.53E-01.  -1.27E+00     1.95E-01   3.54E+00    12 CR-51            Ind        1.84E+00   -1.83E+01     1.58E+01   3.95E+01     12 CR-51            Cntl      -3.87E+00     -1.05E+01    6.30E+00   4.10E+01    12 CS-134            Ind      -8.18E-01   -1.79E+00     1.03E-02  3.87E+00     12 CS-134          Cntl      -2.65E-01    -8.62E-01    6.59E-01    3.63E+00     12 CS-137            Ind      -1.03E-01    -1.48E+00     1.02E+00   3.49E+00     12 CS-1 37          Cntl        8.31 E-02  -1.16E+00     1.38E+00   3.30E+00     12 FE-59            Ind      -1.48E-01    -1.97E+00     2.09E+00   1.05E+01     12 FE-59            Cntl        9.23E-02   -2.03E+00     2.66E+00   9.96E+00     12 1-131            Ind      -3.93E-01    -5.95E+00     2.75E+00   1.31E+01     12 1-131            Cntl      1.09E+00     -1.83E+00     4.07E+00   1.13E+01     12 K-40              Ind      -3.31 E+01    -5.21 E+01   -1.45E+01.' 5.62E+01     12 K-40            Cntl      -3.52E+01    -5.01E+01    -1.72E+01   5.38E+01     12 MN-54            Ind        2.37E-01    -1.16E+00    1.61E+00   3.24E+00     12 MN-54            Cntl        4.07E-01    -1.01E+00. 2.05E+00   3.24E+00     12 ZN-65            Ind      -2.61 E-01  -2.39E+00    2.10E+00   7.23E+00     12 ZN-65            Cntl      -4.44E-01    -1.95E+00    9.68E-01   7.67E+00     12 ZRNB-95          Ind      -2.52E-01    -2.00E+00    2.19E+00   6.58E+00     12 ZRNB-95          Cntl      -7.72E-01    -2.13E+00    1.63E+00   6.58E+00     12 I
-2.39E+00-1.95E+00-2.00E+00-2.13E+00 Activity Average Number of High, MDA Samples 1.37E+00 8.96E+00 12 1.OOE+00 8.27E+00 12 6.79E+00 9.19E+00 12 4.22E+01 8.93E+00 12 1.62E+00 3.50E+00 12 1.06E+00 3.30E+00 12 1.78E+00 3.33E+00 12 1.95E-01 3.54E+00 12 1.58E+01 3.95E+01 12 6.30E+00 4.10E+01 12 1.03E-02 3.87E+00 12 6.59E-01 3.63E+00 12 1.02E+00 3.49E+00 12 1.38E+00 3.30E+00 12 2.09E+00 1.05E+01 12 2.66E+00 9.96E+00 12 2.75E+00 1.31E+01 12 4.07E+00 1.13E+01 12-1.45E+01.'
Ind = Indicator Stations Cntl = Control Stations                                                   Page 1 of 2
5.62E+01 12-1.72E+01 5.38E+01 12 1.61E+00 3.24E+00 12 2.05E+00 3.24E+00 12 2.10E+00 7.23E+00 12 9.68E-01 7.67E+00 12 2.19E+00 6.58E+00 12 1.63E+00 6.58E+00 12 Number of Positive IDs I Ind = Indicator Stations Cntl = Control Stations Page 1 of 2  
 
",1 &#xfd;."., -- !,TABLE A-7.2 GAMMA SPECTROMETRY RESULTS OF WATER -
                                                  ",1&#xfd;."., -- !,TABLE A-7.2 GAMMA SPECTROMETRY RESULTS OF WATER -  


==SUMMARY==
==SUMMARY==
"* --PLANT DISCHARGE WATER Nuclide Average , Activity: Artivitu:7 Lnw Activity : Average Number of Number of Hinh MDA qamnlAq Pnqitivp In-c K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140 BI-214 Ind Ind Ind Ind Ind Ind Ind Ind Ind Ind Ind Ind Ind-1.84E+01 2.23E+00 3.29E-01-1.38E-01-1.47E-01-5.84E-02-8.41 E-01-6.31 E-01-6.34E-01-2.43E-01 1.28E-01-3.12E-01 3.15E+00-3.28E+01-1.38E+01-9.21 E-01-1.40E+00-3.38E+00-5.86E-01-3.03E+00-3.03E+00-4.48E+00-1.44E+00-1.04E+00-3.29E+00-1.37E+00-9.95E-01 1.63E+01 2.05E+00 7.13E-01 2.81 E+00 7.69E-01 1.46E+00 1.34E+00 4.45E+00 1.45E+00 1.51 E+00 1.42E+00 8.35E+00 5.51 E+01 3.96E+01 3.34E+00 3.48E+00 9.92E+00 3.35E+00 8.30E+00 6.79E+00 1.21 E+01 3.77E+00 3.18E+00 8.42E+00 9.14E+00 12 12 12 12 12 12 12 12 12 12 12 12 12 GAMMA SPECTROMETRY RESULTS OF WATER -
 
                                          "*   -- PLANT DISCHARGE WATER Average , Activity:             Activity : Average     Number of Number of Nuclide Artivitu:7      Lnw              Hinh       MDA       qamnlAq Pnqitivp In-c K-40             Ind      -1.84E+01    -3.28E+01          -9.95E-01  5.51 E+01     12 CR-51            Ind      2.23E+00     -1.38E+01           1.63E+01   3.96E+01      12 MN-54            Ind        3.29E-01     -9.21 E-01         2.05E+00    3.34E+00      12 CO-58            Ind      -1.38E-01   -1.40E+00            7.13E-01   3.48E+00     12 FE-59            Ind      -1.47E-01   -3.38E+00          2.81 E+00  9.92E+00     12 CO-60            Ind      -5.84E-02    -5.86E-01           7.69E-01  3.35E+00     12 ZN-65            Ind      -8.41 E-01  -3.03E+00           1.46E+00   8.30E+00     12 ZRNB-95          Ind      -6.31 E-01  -3.03E+00           1.34E+00    6.79E+00     12 1-131            Ind      -6.34E-01   -4.48E+00          4.45E+00   1.21 E+01    12 CS-134            Ind      -2.43E-01   -1.44E+00           1.45E+00   3.77E+00     12 CS-137            Ind        1.28E-01  -1.04E+00           1.51 E+00   3.18E+00     12 BALA140          Ind      -3.12E-01   -3.29E+00           1.42E+00   8.42E+00     12 BI-214            Ind        3.15E+00   -1.37E+00           8.35E+00   9.14E+00     12 GAMMA SPECTROMETRY RESULTS OF WATER -  


==SUMMARY==
==SUMMARY==
DEEP GROUNDWATER Nuclide Average Activity Activity Average Number of Number of Hinh MflA, Sim PnitivA Hinh MDA Samples Positive 1Ds K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140 BI-214 Ind Ind Ind Ind Ind Ind Ind Ind Ind Ind Ind Ind Ind-19.38077-6.037893-0.206022-0.051158 0.3411166-0.305927-0.930563-1.099699 0.6442229 0.0350725 0.3926454-0.180296 188.91926-62.777645
 
-29.751329
DEEP GROUNDWATER Average       Activity           Activity   Average   Number of Number of Nuclide                                                    Hinh       MflA,     Sim nl*p PnitivA I1l*
-1.6769018
Hinh       MDA       Samples Positive 1Ds K-40             Ind      -19.38077  -62.777645        16.6067629  97.5524836      12          0 CR-51             Ind      -6.037893  -29.751329        20.5078375  61.4939589      12          0 MN-54            Ind      -0.206022  -1.6769018        2.47087422  6.13858406      12          0 CO-58            Ind      -0.051158    -2.782062        3.24538865  5.96320343      12          0 FE-59            Ind     0.3411166    -2.7710836        5.04771367  15.4107107      12          0 CO-60            Ind      -0.305927   -1.4593424        1.34175508  6.8394515      12          0 ZN-65              Ind      -0.930563    -11.24672            3.6068 26.1367431      12          0 ZRNB-95            Ind      -1.099699      -3.388893        3.51811696  11.3710584      12          0 1-131            Ind      0.6442229    -1.7730388         4.59444964  9.15610574      12          0 CS-134            Ind      0.0350725    -2.3448187         2.19801189  11.0457449      12          0 CS-137            Ind      0.3926454    -1.3682563         2.63397583  7.23204641      12          0 BALA140          Ind      -0.180296  -2.2908818        1.09289922  9.12374882      12          0 BI-214            Ind      188.91926    -2.2283558        828.447891 17.4645986      12          8 Ind = Indicator Stations Cntl = Control Stations                                                          Page 2 of 2
-2.782062-2.7710836
 
-1.4593424
TABILEA-8.1 GAMMA SPECTROMETRY RESULTS OF SOIL Results in pCi/kilogram I
-11.24672-3.388893-1.7730388
Location & Date                  Station 7      6/11/2013                  -    Location,& Date Station 8          6/11/2013 I
-2.3448187
Nuclide RQ Activity                          Error          MDA                  Nuclide RQ. Activity                Error      MDA      ,
-1.3682563
BE-7 K-40 2.07E+02 +
-2.2908818
                      + 1.53E+04 +
-2.2283558 16.6067629 20.5078375 2.47087422 3.24538865 5.04771367 1.34175508 3.6068 3.51811696 4.59444964 2.19801189 2.63397583 1.09289922 828.447891 97.5524836 61.4939589 6.13858406 5.96320343 15.4107107 6.8394515 26.1367431 11.3710584 9.15610574 11.0457449 7.23204641 9.12374882 17.4645986 12 12 12 12 12 12 12 12 12 12 12 12 12 0 0 0 0 0 0 0 0 0 0 0 0 8 Ind = Indicator Stations Cntl = Control Stations Page 2 of 2 TABILEA-8.1 GAMMA SPECTROMETRY RESULTS OF SOIL Results in pCi/kilogram Location & Date Nuclide RQ Activity Station 7 6/11/2013 Error MDA-Location,&
1.64E+02 8.90E+02 2.42E+02 2.84E+02 BE-7 K-40
Date Nuclide RQ. Activity Station 8 Error 6/11/2013 MDA , BE-7 K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 CS-134 CS-137 BALA140 BI-214 2.07E+02 ++ 1.53E+04 +2.69E+01 +-8.15E+00  
                                                                                                        + 2.73E+02 + 1.84E+02
+0.00E+00 +-1.97E+01  
                                                                                                      .+ 1.90E+04 + 1.13E+03 2.60E+02 2.91 E+02 I
+1.35E+01 +-2.53E+01
CR-51                   2.69E+01 +        1.65E+02          2.68E+02              CR-51              -7.62E+01 + 2.05E+02       3.29E+02 MN-54 CO-58 FE-59
+1.24E+01 +-4.61E-01
                          -8.15E+00 +
+3.00E+01 +3.47E-01 ++ 4.81E+02 +1.64E+02 8.90E+02 1.65E+02 2.23E+01 2.56E+01 5.82E+01.2.26E+01 5.68E+01 2.85E+01 2.24E+01 2.31 E+01 1.77E+01 6.90E+01 2.42E+02 2.84E+02 2.68E+02 3.56E+01 4.27E+01 9.25E+01 3.49E+01 9.02E+01 4.45E+01 3.67E+01 3.38E+01 2.90E+01 7.28E+01 6/11/2013 MDA BE-7 K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 CS-1 34 CS-1 37 BALA140 BI-214+ 2.73E+02 +.+ 1.90E+04 +-7.62E+01
0.00E+00 +
+1.33E+00 +3.47E-01 +3.00E+01 +-1.OOE+01  
                          -1.97E+01 +
+-3.02E+01
2.23E+01 2.56E+01 5.82E+01.
+1.17E+01 +1.12E+01 +2.12E+01 +-2.47E+00  
3.56E+01 4.27E+01 9.25E+01 MN-54 CO-58 FE-59 1.33E+00 + 1.86E+01 3.47E-01 + 2.26E+01 3.00E+01 + 5.91 E+01 3.03E+01 3.71 E+01 9.06E+01 I
++ 5.94E+02 +1.84E+02 1.13E+03 2.05E+02 1.86E+01 2.26E+01 5.91 E+01 5.52E+01 6.28E+01 3.52E+01 1.50E+01 2.55E+01 2.47E+01 8.51 E+01 2.60E+02 2.91 E+02 3.29E+02 3.03E+01 3.71 E+01 9.06E+01 4.57E+01 9.87E+01 5.56E+01 2.22E+01 3.85E+01 3.99E+01 7.73E+01 Location & Date Nuclide RQ Activity Station 9a Error Location & Date Nuclide RQ Activity Station 23 6/11/2013 Error MDA BE-7 -1.86E+01  
CO-60                  1.35E+01 +        2.26E+01         3.49E+01             CO-60              -1.OOE+01 + 5.52E+01       4.57E+01 ZN-65 ZRNB-95
+K-40 + 1.31E+04 +CR-51 0.00E+00 +MN-54 7.61 E+00 +CO-58 1.94E-02 +FE-59 7.30E-01 +CO-60 -4.16E+00
                          -2.53E+01 +
+ZN-65 -3.15E+01  
1.24E+01 +
+ZRNB-95 -2.11E+00
5.68E+01 2.85E+01 9.02E+01 4.45E+01 ZN-65 ZRNB-95
+CS-134 -1.99E+01  
                                                                                                            -3.02E+01 + 6.28E+01 1.17E+01 + 3.52E+01 9.87E+01 5.56E+01 I
+CS-1 37 2.89E+01 +BALA140 1.50E+00 +BI-214 + 4.42E+02 +Location & Date Nuclide RQ Activity 2.76E+02 1.12E+03 2.52E+02 2.85E+01 2.56E+01 7.87E+01 3.45E+01 8.20E+01 4.49E+01 3.24E+01-2.98E+01 2.67E+01 8.75E+01 Station 48 Error 4.51 E+02 4.55E+02 4.20E+02 4.55E+01 4.21E+01 1.29E+02 5.60E+01 1.30E+02 7.34E+01 5.04E+01 4.35E+01 4.34E+01 9.13E+01 6/11/2013 MDA BE-7 K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 CS-134 CS-1 37 BALA140 BI-214 1.11E+02 ++ 1.45E+04 +6.41E+01 +1.34E+01 +-3.92E+00
CS-134                -4.61E-01 +        2.24E+01          3.67E+01              CS-1 34               1.12E+01 + 1.50E+01      2.22E+01 CS-137 BALA140 BI-214 3.00E+01 +
+1.88E+01 +-3.50E+00
3.47E-01 +
+-3.69E+00
                      + 4.81E+02 +
+1.27E+01 +0.00E+00 ++ 5.30E+01 +-5.09E+00
2.31 E+01 1.77E+01 6.90E+01 3.38E+01 2.90E+01 7.28E+01 CS-1 37 BALA140 BI-214 2.12E+01 + 2.55E+01
++ 5.11E+02 +1.38E+02 9.03E+02 1.52E+02 1.77E+01 1.83E+01 5.08E+01 1.20E+02 3.94E+01 3.02E+01 2.11E+01 2.50E+01 2.01 E+01 8.89E+01 2.09E+02 2.41 E+02 2.43E+02 2.65E+01 2.95E+01 7.96E+01 2.48E+01 6.40E+01 4.73E+01 3.51E+01 3.35E+01 3.15E+01 7.19E+01 I I I I I I I I I I I I I I I I I BE-7 K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 CS-134 CS-137 BALA140 BI-214 2.31 E+02 ++ 1.47E+04 +1.30E+02 +-1.37E+00
                                                                                                            -2.47E+00 + 2.47E+01
+-4.02E-01  
                                                                                                        + 5.94E+02 + 8.51 E+01 3.85E+01 3.99E+01 7.73E+01 I
+-5.05E+00
Location & Date              Station 9a          6/11/2013                        Location & Date Station 23          6/11/2013 I
+6.05E+00 +-9.19E+00
Nuclide      RQ Activity                    Error          MDA                  Nuclide RQ Activity                Error      MDA BE-7 K-40            +
+2.46E+01 +0.OOE+00 +1.77E+01 +-9.06E+00
                          -1.86E+01 1.31E+04
++ 6.09E+02 +2.63E+02 1.17E+03 2.51 E+02 3.08E+01 3.06E+01 7.98E+01 3.69E+01 8.09E+01 5.23E+01 7.10E+01 3.48E+01 3.30E+01 1.OOE+02 3.98E+02 3.41 E+02 3.96E+02 5.03E+01 5.03E+01 1.30E+02 5.95E+01 1.32E+02 8.13E+01 1.18E+02 5.43E+01 5.16E+01 9.37E+01 RQ = Results Qualifier.
                                          + 2.76E+02
If blank, result is less than detection limit. If "+", result is above detection limit.Page 1 of 1 I &#xfd;&#xfd; ..TABLE A-8.2 GAMMASPECTROMETRY RESULTS OF SOIL -
                                          + 1.12E+03 4.51 E+02 4.55E+02 BE-7 K-40 1.11E+02 + 1.38E+02
                                                                                                        + 1.45E+04 + 9.03E+02 2.09E+02 2.41 E+02 I
CR-51                  0.00E+00      + 2.52E+02            4.20E+02              CR-51                6.41E+01 + 1.52E+02        2.43E+02 MN-54 CO-58 FE-59 7.61 E+00 1.94E-02 7.30E-01
                                          + 2.85E+01
                                          + 2.56E+01
                                          + 7.87E+01 4.55E+01 4.21E+01 1.29E+02 MN-54 CO-58 FE-59 1.34E+01 + 1.77E+01
                                                                                                            -3.92E+00 + 1.83E+01 1.88E+01 + 5.08E+01 2.65E+01 2.95E+01 7.96E+01 I
CO-60                -4.16E+00      + 3.45E+01             5.60E+01            CO-60                -3.50E+00 + 1.20E+02 ZN-65 ZRNB-95
                          -3.15E+01
                          -2.11E+00
                                          + 8.20E+01
                                          + 4.49E+01 1.30E+02 7.34E+01 ZN-65 ZRNB-95
                                                                                                            -3.69E+00 + 3.94E+01 1.27E+01 + 3.02E+01 2.48E+01 6.40E+01 4.73E+01 I
CS-134                -1.99E+01      + 3.24E+01-           5.04E+01            CS-134                0.00E+00 + 2.11E+01        3.51E+01 CS-1 37 BALA140 BI-214 2.89E+01 1.50E+00
                      + 4.42E+02
                                          + 2.98E+01
                                          + 2.67E+01
                                          + 8.75E+01 4.35E+01 4.34E+01 9.13E+01 CS-1 37 BALA140 BI-214
                                                                                                        + 5.30E+01 + 2.50E+01
                                                                                                            -5.09E+00 + 2.01 E+01
                                                                                                        + 5.11E+02 + 8.89E+01 3.35E+01 3.15E+01    I 7.19E+01 Location & Date                Station 48        6/11/2013 I
Nuclide      RQ Activity                    Error          MDA BE-7 K-40 2.31 E+02
                      + 1.47E+04
                                          +
                                          +
2.63E+02 1.17E+03 3.98E+02 3.41 E+02 I
CR-51                  1.30E+02      +   2.51 E+02        3.96E+02 MN-54 CO-58 FE-59
                          -1.37E+00
                            -4.02E-01
                          -5.05E+00
                                          +
                                          +
                                          +
3.08E+01 3.06E+01 7.98E+01 5.03E+01 5.03E+01 1.30E+02 I
CO-60                  6.05E+00      +   3.69E+01 ZN-65 ZRNB-95
                          -9.19E+00 2.46E+01
                                          +
                                          +
8.09E+01 5.23E+01 5.95E+01 1.32E+02 8.13E+01 I
CS-134                0.OOE+00      +    7.10E+01          1.18E+02 CS-137 BALA140 BI-214 1.77E+01
                          -9.06E+00
                      + 6.09E+02
                                          +
                                          +
                                          +
3.48E+01 3.30E+01 5.43E+01 5.16E+01                                                                          I 1.OOE+02          9.37E+01 I
RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit.                 Page 1 of 1
 
I &#xfd;&#xfd;..TABLE A-8.2 GAMMASPECTROMETRY RESULTS OF SOIL -  


==SUMMARY==
==SUMMARY==
..Results in pCi/kilogram Average Activity Activity Average Nuclide Activity CLw High MDA Number of Samples Number of Positive IDs BALA140 BALA140 BE-7 BE-7 BI-2 14 BI-214 CO-58 CO-58 CO-60 CO-60 CR-51 CR-51 CS-1 34 CS-1 34 CS-137 CS-137 FE-59 FE-59 K-40 K-40 MN-54 MN-54 ZN-65 ZN-65 ZRNB-95 ZRNB-95 Ind CntI Ind Cntl Ind Cntl Ind CntI Ind Cntl Ind CntI Ind Cntl Ind Cntl Ind CntI Ind CntI Ind CntI Ind CntI Ind CntI-4.07E+00 1.50E+00 2.05E+02-1 .86E+01 5.48E+02 4.42E+02-9.93E-01 1.94E-02 1.52E+00-4.16E+00 3.62E+01 0.OOE+00 2.68E+00-1.99E+01 3.05E+01 2.89E+01 6.00E+00 7.30E-01 1.59E+04 1.31 E+04 1.31 E+00 7.61 E+00-1.71 E+01-3.15E+01 1.54E+01-2.11E+00-9.06E+00 1.50E+00 1.11E+02-1.86E+01 4.81 E+02 4.42E+02-3.92E+00 1.94E-02-1.00E+01-4.16E+00-7.62E+01 0.00E+00-4.61 E-01-1.99E+01 1.77E+01 2.89E+01-1.97E+01 7.30E-01 1.45E+04 1.31E+04-8.15E+00 7.61 E+00-3.02E+01-3.15E+01 1.17E+01-2.11 E+00 3.47E-01 -4.07E+00 1.50E+00 4.34E+01 4 1 0 0 2.73E+02-1.86E+01 6.09E+02 4.42E+02 3.47E-01 1.94E-02 1.35E+01-4.16E+00 1.30E-+02 0.OOE+00 1.12E+01-1.99E+01 5.30E+01 2.89E+01 3.OOE+01 7.30E-01 1.90E+04 1.31E+04 1.34E+01 7.61 E+00-3.69E+00-3.15E+01 2.46E+01-2.11E+00 2.05E+02 4.51 E+02 5.48E+02 9.13E+01-9.93E-01 4.21 E+01 1.52E+00 5.60E+01 3.62E+01 4.20E+02 2.68E+00 5.04E+01 3.05E+01 4.35E+01 6.OOE+00 1.29E+02 1.59E+04 4.55E+02 1.31 E+00 4.55E+01-1.71E+01 1.30E+02 1.54E+01 7.34E+01 Ind =.Indicator Stations Cntl = Control StationsP Page 1 of 1 TABLE A=9.1."'GAMMA SPECTROMETRY RESULTS-OF SEDIMENT Results in pCi/kilogram dry material Station 33 Upstream Control Station 33 3/8/2013 Location & Date Error MDA Nuclide RQ t Activity Location & Date Nuclide: Rd- Activity Station 33 10/21/2013 Error MDA BE-7 K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 CS-134 CS-1 37 BALA140 BI-214 2.42E+02 ++ 1.67E+04 +-6.49E+01
 
+1.45E+01 +7.86E+00 +2.02E+00 +-6.03E+00
                                                    ..Results in pCi/kilogram Average         Activity       Activity       Average   Number of Number of Nuclide                       Activity         CLw           High           MDA     Samples Positive IDs BALA140       Ind          -4.07E+00 -9.06E+00              3.47E-01 -4.07E+00            4          0 BALA140        CntI          1.50E+00 1.50E+00            1.50E+00 4.34E+01              1           0 BE-7            Ind          2.05E+02 1.11E+02 2.73E+02                    2.05E+02 BE-7          Cntl        -1.86E+01 -1.86E+01 -1.86E+01                  4.51 E+02 BI-2 14        Ind           5.48E+02      4.81 E+02      6.09E+02        5.48E+02 BI-214        Cntl          4.42E+02      4.42E+02       4.42E+02       9.13E+01 CO-58          Ind          -9.93E-01 -3.92E+00           3.47E-01       -9.93E-01 CO-58          CntI            1.94E-02 1.94E-02            1.94E-02      4.21 E+01 CO-60          Ind            1.52E+00 -1.00E+01 1.35E+01                  1.52E+00 CO-60          Cntl          -4.16E+00 -4.16E+00 -4.16E+00                  5.60E+01 CR-51          Ind          3.62E+01 -7.62E+01            1.30E-+02        3.62E+01 CR-51          CntI          0.OOE+00 0.00E+00            0.OOE+00        4.20E+02 CS-1 34        Ind          2.68E+00 -4.61 E-01 1.12E+01                 2.68E+00 CS-1 34        Cntl          -1.99E+01 -1.99E+01 -1.99E+01                   5.04E+01 CS-137          Ind          3.05E+01       1.77E+01     5.30E+01         3.05E+01 CS-137        Cntl          2.89E+01      2.89E+01      2.89E+01        4.35E+01 FE-59          Ind          6.00E+00 -1.97E+01            3.OOE+01         6.OOE+00 FE-59          CntI          7.30E-01 7.30E-01            7.30E-01        1.29E+02 K-40            Ind            1.59E+04      1.45E+04      1.90E+04        1.59E+04 K-40            CntI          1.31 E+04      1.31E+04      1.31E+04        4.55E+02 MN-54          Ind            1.31 E+00 -8.15E+00         1.34E+01         1.31 E+00 MN-54          CntI          7.61 E+00 7.61 E+00          7.61 E+00      4.55E+01 ZN-65          Ind          -1.71 E+01 -3.02E+01 -3.69E+00 -1.71E+01 ZN-65          CntI        -3.15E+01 -3.15E+01 -3.15E+01 1.30E+02 ZRNB-95        Ind            1.54E+01 1.17E+01 2.46E+01                   1.54E+01 ZRNB-95        CntI          -2.11E+00 -2.11 E+00 -2.11E+00                 7.34E+01 Ind =.Indicator Stations Cntl = Control StationsP                                                        Page 1 of 1
+-1.37E+01  
 
+9.15E+00 +-1.16E+01  
I TABLE A=9.1."'
+3.46E+01 +-1.98E+01  
GAMMA SPECTROMETRY RESULTS-OF SEDIMENT Results in pCi/kilogram dry material I
++ 8.21E+02 +2.52E+02 9.81 E+02 1.98E+02 2.35E+01 2.12E+01 6.88E+01 2.97E+01 6.74E+01 5.04E+01 3.06E+01 3.07E+01 4.71E+01 9.11E+01 3.88E+02 2.93E+02 3.18E+02 3.64E+01 3.35E+01 1.13E+02 4.79E+01 1.09E+02 8.17E+01 4.92E+01 4.64E+01 7.34E+01 8.14E+01 BE-7 K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95.CS-134 CS-137 BALA140 BBI-214-1.02E+00
Station 33 Upstream Control                                                              I Location & Date            Station 33          3/8/2013                        Location & Date Station 33            10/21/2013 Nuclide: Rd- Activity BE-7              2.42E+02
++ 1.71E+04+2.23E+01 +1.62E+01 +9.05E+00 +-1.44E-01  
              + 1.67E+04
+-6.71E+00
                                +
+-3.66E+01
                                +
+1.03E+01 +-5.06E+00
Error 2.52E+02 MDA 3.88E+02 Nuclide RQ BE-7 t      Activity
++ 4.98E+01 +-2.78E+00  
                                                                                                    -1.02E+00 + 1.98E+02
++ 7.67E+02 +1.98E+02 9.81 E+02 1.94E+02 2.14E+01 1.87E+01 5.91E+01 2.63E+01 7.07E+01 3.42E+01 8.01 E+01 2.50E+01 2.15E+01 9.03E+01 3.26E+02 2.82E+02 3.17E+02 3.25E+01 2.90E+01 9.71 E+01 4.21 E+01 1.12E+02 5.45E+01 2.59E+01 3.36E+01 3.46E+01 8.24E+01 I I I U I I I I Station 34 Downstream Indicator I Location & Date Nuclide RQ BE-7 +K-40 +CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 CS-134 CS-137 +BALA140 BI-214 +Activity 4.62E+02 +1.57E+04 +0.OOE+00 +9.13E+00 +-6.26E+00
                                                                                                + 1.71E+04+
+-8.43E+00
Error     MDA 3.26E+02    U K-40                                   9.81 E+02        2.93E+02            K-40                                      9.81 E+02  2.82E+02 CR-51 MN-54 CO-58
+7.22E+00 +2.71E+01 +-2.91E+00
                -6.49E+01 1.45E+01 7.86E+00
+3.65E+00 +1.22E+02 +-4.40E+00
                                +
+7.39E+02 +Station 34 Error 2.58E+02 9.76E+02 2.59E+02 2.16E+01 2.34E+01 6.17E+01 2.69E+01 3.75E+01 4.19E+01 2.17E+01 3.72E+01 4.42E+01 9.21E+01 3/8/2013 MDA 3.71 E+02 3.27E+02 4.31 E+02 3.40E+01 3.75E+01 9.97E+01 4.3.1E+01 5.51E+01 6.84E+01 3.51 E+01 3.39E+01 7.16E+01 6.29E+01 Location & Date Nuclide RQ Activity BE-7 K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 CS-134 CS-137 BALA140 BI-214 0.OOE+00 ++ 1.51E+04 +5.94E+01 +3.85E+01 +-9.03E+00
                                +
+1.06E+01 +-1.14E+00
                                +
+2.80E+01 +0.OOE+00 +-2.99E+01
1.98E+02 2.35E+01 2.12E+01 3.18E+02 3.64E+01 3.35E+01 CR-51 MN-54 CO-58 2.23E+01 + 1.94E+02 1.62E+01 + 2.14E+01 9.05E+00 + 1.87E+01 3.17E+02 3.25E+01 2.90E+01 I
++ 1.21E+02 +-1.09E+01  
FE-59            2.02E+00      +     6.88E+01          1.13E+02           FE-59                  -1.44E-01 + 5.91E+01         9.71 E+01 CO-60 ZN-65
+.+ 1.13E+03 +Station 34 10/21/2013 Error ,MDA 2.54E+02 4.23E+02 9.38E+02 3.43E+02 2.53E+02 4.11E+02 2.89E+01 4.31 E+01 2.45E+01 3.90E+01 5.59E+01 8.99E+01 3.05E+01 5.OOE+01 4.14E+01 6.29E+01 4.81E+01 8.01 E+01 3.42E+01 5.37E+01 3.33E+01 3.18E+01 2.85E+01 4.46E+01 1.05E+02 9.75E+01 I I I I I I I I I I RQ = Results Qualifier.
                -6.03E+00
If blank, result is less than detection limit. If '+", result is above detection limit.Page 1 of 1 TABLE A-9.2 GAMMA SPECTROMETRY RESULTS OF SEDIMENT -
                -1.37E+01
                                +
                                +
2.97E+01 6.74E+01 4.79E+01 1.09E+02 CO-60 ZN-65
                                                                                                    -6.71E+00 + 2.63E+01
                                                                                                    -3.66E+01 + 7.07E+01 4.21 E+01 1.12E+02 I
ZRNB-95          9.15E+00      +     5.04E+01         8.17E+01             ZRNB-95                1.03E+01 + 3.42E+01          5.45E+01 CS-134 CS-1 37 BALA140
                -1.16E+01 3.46E+01
                -1.98E+01
                                +
                                +
                                +
3.06E+01 3.07E+01 4.71E+01 4.92E+01 4.64E+01 7.34E+01
                                                                            .CS-134 CS-137 BALA140
                                                                                                    -5.06E+00 + 8.01 E+01
                                                                                                + 4.98E+01 + 2.50E+01
                                                                                                    -2.78E+00 + 2.15E+01 2.59E+01 3.36E+01 3.46E+01 I
              + 8.21E+02 BI-214                          +    9.11E+01         8.14E+01             BBI-214            + 7.67E+02 + 9.03E+01             8.24E+01 I
Station 34 Downstream Indicator                                                          I Nuclide BE-7 Location & Date RQ Activity
              + 4.62E+02        +
Station 34 Error 2.58E+02 3/8/2013 MDA 3.71 E+02 Nuclide BE-7 Location & Date RQ Activity 0.OOE+00    +
Station 34 Error 2.54E+02 10/21/2013
                                                                                                                                    ,MDA 4.23E+02 I
K-40 CR-51
              + 1.57E+04 0.OOE+00
                                +
                                +
9.76E+02 2.59E+02 3.27E+02 4.31 E+02 K-40 CR-51
                                                                                                + 1.51E+04 5.94E+01    +
                                                                                                                  +   9.38E+02 2.53E+02 3.43E+02 4.11E+02 I
MN-54            9.13E+00       +     2.16E+01          3.40E+01            MN-54                  3.85E+01    +     2.89E+01  4.31 E+01 CO-58 FE-59 CO-60
                -6.26E+00
                -8.43E+00 7.22E+00
                                +
                                +
                                +
2.34E+01 6.17E+01 2.69E+01 3.75E+01 9.97E+01 4.3.1E+01 CO-58 FE-59 CO-60
                                                                                                    -9.03E+00 1.06E+01
                                                                                                    -1.14E+00
                                                                                                                  +
                                                                                                                  +
                                                                                                                  +
2.45E+01 5.59E+01 3.05E+01 3.90E+01 8.99E+01 5.OOE+01 I
ZN-65 ZRNB-95 CS-134 2.71E+01
                -2.91E+00 3.65E+00
                                +
                                +
                                +
3.75E+01 4.19E+01 2.17E+01 5.51E+01 6.84E+01 3.51 E+01 ZN-65 ZRNB-95 CS-134 2.80E+01 0.OOE+00
                                                                                                    -2.99E+01
                                                                                                                  +
                                                                                                                  +
                                                                                                                  +
4.14E+01 4.81E+01 3.42E+01 6.29E+01 8.01 E+01 5.37E+01 I
CS-137        + 1.22E+02        +     3.72E+01         3.39E+01            CS-137              + 1.21E+02       +     3.33E+01  3.18E+01 BALA140 BI-214
                -4.40E+00
              + 7.39E+02
                                +
                                +
4.42E+01 9.21E+01 7.16E+01 6.29E+01 BALA140 BI-214
                                                                                                    -1.09E+01
                                                                                                .+ 1.13E+03
                                                                                                                  +
                                                                                                                  +
2.85E+01 1.05E+02 4.46E+01 9.75E+01 I
I I
I I
RQ = Results Qualifier. If blank, result is less than detection limit. If '+", result is above detection limit.             Page 1 of 1 I
 
TABLE A-9.2 GAMMA SPECTROMETRY RESULTS OF SEDIMENT -  


==SUMMARY==
==SUMMARY==
Results in pCi/kilogram dry material Average Activity Activity Average Number of Number of Nuclide Activity Low High MDA Samples Positive IDs BALA140 Ind -7.64E+00  
 
-1.09E+01  
Results in pCi/kilogram dry material Average         Activity       Activity     Average   Number of Number of Nuclide                       Activity         Low           High         MDA     Samples Positive IDs BALA140 Ind                 -7.64E+00 -1.09E+01           -4.40E+00 5.81E+01           2           0 BALA140 CntI                 -1.13E+01 -1.98E+01           -2.78E+00 5.40E+01           2           0 BE-7           Ind           2.31 E+02 0.OOE+00             4.62E+02 3.97E+02           2           1 BE-7           CntI           1.21E+02 -1.02E+00             2.42E+02 3.57E+02           2           0 BI-214         Ind           9.36E+02       7.39E+02       1.13E+03 8.02E+01           2           2 BI-214         CntI           7.94E+02       7.67E+02       8.21E+02 8.19E+01           2           2 CO-58         Ind           -7.64E+00 -9.03E+00 -6.26E+00 3.82E+01                     2           0 CO-58         CntI           8.45E+00 7.86E+00 9.05E+00 3.13E+01                       2           0 CO-60         Ind           3.04E+00 -1.14E+00 7.22E+00 4.66E+01                       2           0 CO-60         CntI         -6.37E+00 -6.71 E+00 -6.03E+00 4.50E+01                     2           0 CR-51         Ind           2.97E+01 0.OOE+00             5.94E+01 4.21E+02           2           0 CR-51         CntI         -2.13E+01 -6.49E+01             2.23E+01 3.18E+02           2           0 CS-134         Ind           -1.31E+01 -2.99E+01             3.65E+00 4.44E+01           2           0 CS-134         CntI         -8.31E+00 -1.16E+01           -5.06E+00 3.76E+01           2           0 CS-137         Ind           1.21E+02       1.21E+02       1.22E+02 3.29E+01           2         .2 CS-1 37       CntI           4.22E+01       3.46E+01       4.98E+01 4.00E+01           2           1 FE-59         Ind           1.1OE+00 -8.43E+00             1.06E+01 9.48E+01           2           0 FE-59         Cnti           9.40E-01 -1.44E-01           2.02E+00 1.05E+02           2           0 K-40           Ind           1.54E+04       1.51E+04       1.57E+04 3.35E+02           2           2 K-40           CntI           1.69E+04       1.67E+04       1.71E+04 2.88E+02           2           2 MN-54         Ind           2.38E+01       9.13E+00       3.85E+01     3.85E+01     2           0 MN-54         Cntl           1.53E+01       1.45E+01       1.62E+01     3.45E+01     2           0 ZN-65           Ind           2.75E+01 2.71E+01             2.80E+01     5.90E+01     2           0 ZN-65           CntI         -2.52E+01 -3.66E+01           -1.37E+01     1.11E+02     2           0 ZRNB-95         Ind           -1.45E+00 -2.91E+00             0.00E+00 7.43E+01           2           0 ZRNB-95         CntI           9.72E+00 9.15E+00             1.03E+01 6.81E+01           2           0 Ind = Indicator Stations Cntl = Control Stations                                                     .Page 1 of 1
-4.40E+00 5.81E+01 2 0 BALA140 CntI -1.13E+01  
 
-1.98E+01  
I TABLE A-10.1 GAMMA SPECTROMETRY RESULTS OF FISH:
-2.78E+00 5.40E+01 2 0 BE-7 Ind 2.31 E+02 0.OOE+00 4.62E+02 3.97E+02 2 1 BE-7 CntI 1.21E+02 -1.02E+00 2.42E+02 3.57E+02 2 0 BI-214 Ind 9.36E+02 7.39E+02 1.13E+03 8.02E+01 2 2 BI-214 CntI 7.94E+02 7.67E+02 8.21E+02 8.19E+01 2 2 CO-58 Ind -7.64E+00  
Station 30 Columbia River - Station 38 Snake River I
-9.03E+00  
Results in pCi/kilogram (wet)
-6.26E+00 3.82E+01 2 0 CO-58 CntI 8.45E+00 7.86E+00 9.05E+00 3.13E+01 2 0 CO-60 Ind 3.04E+00 -1.14E+00 7.22E+00 4.66E+01 2 0 CO-60 CntI -6.37E+00  
I Location &         Collection Species                 Date             Nuclide         RQ       Activity               Error             MDA             I Steelhead Station 30 10/08/13                   K-40 MN-54 2.66E+03 5.38E-01 3.22E+02 8.52E+00 1.93E+02 1.39E+01 I
-6.71 E+00 -6.03E+00 4.50E+01 2 0 CR-51 Ind 2.97E+01 0.OOE+00 5.94E+01 4.21E+02 2 0 CR-51 CntI -2.13E+01  
Indicator                                        CO-58            -4.27E+00              1.38E+01        2.16E+01 FE-59 CO-60 ZN-65
-6.49E+01 2.23E+01 3.18E+02 2 0 CS-134 Ind -1.31E+01  
                                                                    -7.48E+00 5.94E+00
-2.99E+01 3.65E+00 4.44E+01 2 0 CS-134 CntI -8.31E+00  
                                                                    -5.63E+00 5.16E+01 1.32E+01 2.61E+01 8.29E+01 2.13E+01 4.17E+01 I
-1.16E+01  
ZRNB-95 CS-134 CS-137        +
-5.06E+00 3.76E+01 2 0 CS-137 Ind 1.21E+02 1.21E+02 1.22E+02 3.29E+01 2 .2 CS-1 37 CntI 4.22E+01 3.46E+01 4.98E+01 4.00E+01 2 1 FE-59 Ind 1.1OE+00 -8.43E+00 1.06E+01 9.48E+01 2 0 FE-59 Cnti 9.40E-01 -1.44E-01 2.02E+00 1.05E+02 2 0 K-40 Ind 1.54E+04 1.51E+04 1.57E+04 3.35E+02 2 2 K-40 CntI 1.69E+04 1.67E+04 1.71E+04 2.88E+02 2 2 MN-54 Ind 2.38E+01 9.13E+00 3.85E+01 3.85E+01 2 0 MN-54 Cntl 1.53E+01 1.45E+01 1.62E+01 3.45E+01 2 0 ZN-65 Ind 2.75E+01 2.71E+01 2.80E+01 5.90E+01 2 0 ZN-65 CntI -2.52E+01  
1.83E+00 5.51 E+00 1.91 E+01 2.44E+01 8.63E+00 1'14E+01 3.97E+01 1.30E+01 1.48E+01 I
-3.66E+01  
Bi-214            -3.20E+00              2.51 E+01      3.92E+01 White Fish Station 30 12/22/13                    K-40 MN-54
-1.37E+01 1.11E+02 2 0 ZRNB-95 Ind -1.45E+00  
                                                              +      2.89E+03
-2.91E+00 0.00E+00 7.43E+01 2 0 ZRNB-95 CntI 9.72E+00 9.15E+00 1.03E+01 6.81E+01 2 0 Ind = Indicator Stations Cntl = Control Stations.Page 1 of 1 TABLE A-10.1 GAMMA SPECTROMETRY RESULTS OF FISH: Station 30 Columbia River -Station 38 Snake River Results in pCi/kilogram (wet)Location & Collection Species Date Nuclide RQ Activity Error MDA Steelhead Station 30 Indicator White Fish Station 30 Indicator 10/08/13 12/22/13 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 CS-134 CS-137 Bi-214 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 CS-134 CS-137 Bi-214 2.66E+03 5.38E-01-4.27E+00-7.48E+00 5.94E+00-5.63E+00 1.83E+00 5.51 E+00 1.91 E+01-3.20E+00+Steelhead Station 38 Control White Fish Station 38 Control 10/08/13 12/21/13 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 CS-134 CS-137 Bi-214 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 CS-134 CS-137 Bi-214+ 2.89E+03-1.87E+00-2.32E+00-1.28E+01 2.19E+00 8.11 E+00-3.57E-01 1.53E+00 2.19E+00-1.20E+00+ 3.19E+03-5.08E-01-4.OOE+00-1.70E+01-3.82E-01-8.07E+00-5.13E+00 0.OOE+00 9.50E+00 2.14E+01+ 3.08E+03 7.05E+00-4.20E-01-2.86E+00-6.27E+00-2.54E+00 3.03E-01 9.82E+00 5.16E+00 9.03E+00 3.22E+02 8.52E+00 1.38E+01 5.16E+01 1.32E+01 2.61E+01 2.44E+01 8.63E+00 1'14E+01 2.51 E+01 4.14E+02 1.21 E+01 1.37E+01 4.93E+01 1.58E+01 3.03E+01 2.02E+01 1.30E+01 1.30E+01 3.26E+01 3.49E+02 9.76E+00 1.26E+01 4.85E+01 1.27E+01 2.73E+01 2.53E+01 1.47E+01 1.10E+01 2.33E+01 3.77E+02 8.98E+00 1.10E+01 3.30E+01 8.92E+01 3.02E+01 1.81E+01 8.94E+00 1.17E+01 2.85E+01 1.93E+02 1.39E+01 2.16E+01 8.29E+01 2.13E+01 4.17E+01 3.97E+01 1.30E+01 1.48E+01 3.92E+01 3.03E+02 1.94E+01 2.19E+01 7.83E+01 2.65E+01 4.79E+01 3.30E+01 2.10E+01 2.09E+01 5.71E+01 1.91E+02 1.59E+01 1.97E+01 7.50E+01 1.80E+01 4.31E+01 4.04E+01 2.41E+01 1.62E+01 3.98E+01 2.19E+02 1.25E+01 1.80E+01 5.34E+01 2.66E+01 4.91E+01 2.97E+01 1.22E+01 1.81E+01 5.13E+01 I I I I I I I I I I I!I I I I I I I RQ = Results Qualifier.
                                                                    -1.87E+00 4.14E+02 1.21 E+01 3.03E+02 1.94E+01 I
If blank, result is less than detection limit. If "+", result is above detection limit.Page 1 of 1 U U TABLE A-10.2 GAMMA SPECTROMETRY RESULTS OF FISH -
Indicator                                        CO-58 FE-59 CO-60
                                                                    -2.32E+00
                                                                    -1.28E+01 2.19E+00 1.37E+01 4.93E+01 1.58E+01 2.19E+01 7.83E+01 2.65E+01 I
ZN-65              8.11 E+00             3.03E+01        4.79E+01 ZRNB-95 CS-134
                                                                    -3.57E-01 1.53E+00 2.02E+01 1.30E+01 3.30E+01 2.10E+01 I
CS-137                2.19E+00             1.30E+01       2.09E+01 Steelhead              10/08/13 Bi-214 K-40      +
                                                                    -1.20E+00 3.19E+03 3.26E+01 3.49E+02 5.71E+01 1.91E+02 I
Station 38                                      MN-54              -5.08E-01              9.76E+00       1.59E+01 Control                                          CO-58 FE-59
                                                                    -4.OOE+00
                                                                    -1.70E+01 1.26E+01 4.85E+01 1.97E+01 7.50E+01 CO-60              -3.82E-01              1.27E+01       1.80E+01 ZN-65 ZRNB-95 CS-134
                                                                    -8.07E+00
                                                                    -5.13E+00 0.OOE+00 2.73E+01 2.53E+01 1.47E+01 4.31E+01 4.04E+01 2.41E+01 I
CS-137 Bi-214 9.50E+00 2.14E+01 1.10E+01 2.33E+01 1.62E+01 3.98E+01             I White Fish              12/21/13                    K-40      +      3.08E+03              3.77E+02       2.19E+02 Station 38 Control MN-54 CO-58 FE-59 7.05E+00
                                                                    -4.20E-01 8.98E+00 1.10E+01 1.25E+01 1.80E+01             I
                                                                    -2.86E+00              3.30E+01        5.34E+01 CO-60 ZN-65 ZRNB-95
                                                                    -6.27E+00
                                                                    -2.54E+00 3.03E-01 8.92E+01 3.02E+01 1.81E+01 2.66E+01 4.91E+01 2.97E+01 I
CS-134              9.82E+00              8.94E+00        1.22E+01 CS-137 Bi-214 5.16E+00 9.03E+00 1.17E+01 2.85E+01 1.81E+01 5.13E+01 I
I RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit.     Page 1 of 1 I
 
U U                                                             TABLE A-10.2 GAMMA SPECTROMETRY RESULTS OF FISH -  


==SUMMARY==
==SUMMARY==
Results in pCi/kilogram (wet)Nuclide Bi-214 Bi-214 CO-58 CO-58 CO-60 CO-60 CS-134 CS-134 CS-1 37 CS-137 FE-59 FE-59 K-40 K-40 MN-54 MN-54 ZN-65 ZN-65 Ind Cntl Ind Cntl Ind Cntl Ind CntI Ind Cntl Ind Cntl Ind Cntl Ind Cntl Ind Cnti Average Activity Activity Low-2.20E+00
 
-3.20E+00 1.52E+01 9.03E+00-3.30E+00
Results in pCi/kilogram (wet)
-4.27E+00-2.21 E+00 -4.OOE+00 4.06E+00 2.19E+00-3.33E+00
Average          Activity        Activity      Average    Number of . Number of Nuclide                        Activity            Low            .High        MDA        Samples  Positive IDs Bi-214              Ind        -2.20E+00        -3.20E+00      -1.20E+00      4.81E+01 Bi-214              Cntl        1.52E+01        9.03E+00        2.14E+01      4.56E+01 CO-58              Ind        -3.30E+00        -4.27E+00      -2.32E+00      2.18E+01 CO-58              Cntl        -2.21 E+00      -4.OOE+00        -4.20E-01;    1.89E+01 CO-60              Ind          4.06E+00        2.19E+00        5.94E+00      2.39E+01 CO-60              Cntl        -3.33E+00        -6.27E+00        -3.82E-01    2.23E+01 CS-134              Ind          3.52E+00          1.53E+00      5.
-6.27E+00 3.52E+00 1.53E+00 4.91E+00 Q.OOE-OO 1.06E+01 2.19E+00 7.33E+00 5.16E+OO-1.01E+01
-1.28E+01-9.95E+00
-1


==SUMMARY==
==SUMMARY==
Results in pCi per liter Nuclide BA- 133 BA-133 BALA140 BALA140 BE-7 BE-7 CO-60 CO-60 CS-1 34.CS-1 34 CS-1 37 CS-137 FE-59 FE-59 K-40 K-40 MN-54 MN-54 ZN-65 ZN-65 ZRNB-95 Average-Activity Ind -6.56E-01 Cntl -5.33E-02 Ind -3.44E-01 (Cntl 1.84E-02 Ind 2.37E+00 CntI 2.41E+00 Ind -1.43E-01 Cntl -9.68E-02 Ind. -6.87E-02 Cntl -2.98E-01 Ind 2.89E-01 Cntl .6.16E-02 Ind 2.19E-01 Cntl 1.76E-01 Ind .1.42E+03 Cntl 1.45E+03 Ind 5.58E-02 Cntl -7.71 E-02 Ind -5.35E-01 CntI 7.17E-02 Ind .-4.39E-02 Aictivity Low-2.53E+00-2.16E+00-1.84E+00-1.41 E+00-6.65E+00-1.15E+01-2.61 E+00-2.28E+00-1.71 E+00-2.15E+00-9.56E-01-1.40E+00-3.04E&#xf7;00-4.29E+00 1.29E+03 1.30E+03-8.37E-01-1.28E+00-3.94E+00-4.87E+00-3.06E+00 Activity Average High MDA 3.1OE+00 6.05E+O(3.90E+00 5.82E+Q(7.20E-01 5.79E+O(2.14E+00 5.59E+O(1.77E+01 3.73E+O 1.75E+01 3.81 E+O'2.58E+00 6.99E+O0 3.08E+00 7.15E+O0 3.17E+oO 4.85E+O0 1.90E+00 5.23E+O0 1.79E+00 5.50E+04 1.61E+00 5.42E+04 5.58E+00 1.38E+O 4.75E+00 1.44E+O 1.58E+03 7.34E+O 1.55E+03 7.23E+O 1.40E+00 5.31E+O0 2.27E+00 5.33E+O0 4.03E+'00 1.39E-0 4.95E+00.
 
1.26E+O 3.87E+00 9.03E+O0 Number Number of of Positive Samples IDs 0 0'0 0 1 1 0 0 0 0 0.01 1*]1 0 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18 18 0 0 0 0.0 ZRNB-95 Cntl -2.75E-01
Results in pCi per liter Number  Number of Average-    Aictivity    Activity      Average        of    Positive Nuclide               Activity      Low          High            MDA        Samples    IDs BA- 133     Ind      -6.56E-01 -2.53E+00 3.1OE+00              6.05E+O( 0    18        0 BA-133      Cntl      -5.33E-02 -2.16E+00 3.90E+00              5.82E+Q(      18        0 0'
-3.41E+00 3.09E+00 9.11E+00.Ind = Indicator Stations Cntl = Control Stations Page 1 of 1 TABLE A-45.1 GAMMA SPECTROMETRY RESULTS OF ROOTCROPS, Results in pCi/ kilogram (wet)Station 37 is Indicator
BALA140      Ind      -3.44E-01 -1.84E+00 7.20E-01             5.79E+O( 0    18        0 BALA140    (Cntl      1.84E-02 -1.41 E+00 2.14E+00            5.59E+O(      18        0 BE-7        Ind      2.37E+00 -6.65E+00 1.77E+01              3.73E+O0      18        0 BE-7        CntI      2.41E+00 -1.15E+01 1.75E+01              3.81 E+O' 1    18        0 CO-60        Ind      -1.43E-01 -2.61 E+00 2.58E+00            6.99E+O0      18        0 CO-60      Cntl       -9.68E-02 -2.28E+00 3.08E+00             7.15E+O0      18        0 0
-Station 9c is Control Station 37 Potato collected Nuclide RQ Activity Error 7/2/2013 Station 37 Potato collected MDA- Nuclide R-Q Activity Error 8/27/2013 MDA K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140+ 3.20E+03-1.57E-01 2.70E+00 3.76E-02 3.84E+00 1.29E+00-3.54E-01-2.49E+00 2.25E+00 3.92E+00-1.46E+00++++&#xf7;+3.29E+02 6.25E+00 4.78E+00 1.73E+01 9.03E+00 1.68E+01 9.43E+00 6.34E+00 4.54E+00 6.95E+00 8.21 E+00 1.48E+02 1.02E+01 6.79E+00 2.84E+01 1.38E+01 2.73E+01 1.54E+01 9.92E+00 6.73E+00 1.04E+01 1.29E+01 7/16/2013 MDA K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-1 34 CS-137 BALA140+ 3.40E+03 +0.OOE+00 +-8.67E-01
CS-1 34. Ind.     -6.87E-02 -1.71 E+00 3.17E+oO            4.85E+O010    18        0 CS-1 34    Cntl       -2.98E-01 -2.15E+00 1.90E+00              5.23E+O00      18        0 CS-1 37      Ind       2.89E-01 -9.56E-01 1.79E+00              5.50E+04      18        0 CS-137      Cntl      .6.16E-02 -1.40E+00 1.61E+00             5.42E+04        18        0 FE-59        Ind        2.19E-01 -3.04E&#xf7;00 5.58E+00             1.38E+O 0      18        0 FE-59      Cntl        1.76E-01 -4.29E+00 4.75E+00             1.44E+O        18        0 0.
+1.35E+00 +-2.17E+00
1*
+2.05E+00 +9.05E+00 +-1.38E+00  
K-40        Ind    . 1.42E+03   1.29E+03 1.58E+03            7.34E+O 01]    18        18 K-40        Cntl        1.45E+03    1.30E+03 1.55E+03            7.23E+O        18        18 MN-54        Ind        5.58E-02 -8.37E-01 1.40E+00             5.31E+O01      18        0 MN-54      Cntl      -7.71 E-02 -1.28E+00 2.27E+00             5.33E+O0       18        0 ZN-65      Ind        -5.35E-01 -3.94E+00 4.03E+'00            1.39E-0 0      18        0 ZN-65      CntI        7.17E-02 -4.87E+00 4.95E+00.             1.26E+O        18 ZRNB-95    Ind      .-4.39E-02 -3.06E+00 3.87E+00              9.03E+O0      18        0 ZRNB-95    Cntl      -2.75E-01  -3.41E+00 3.09E+00            9.11E+00.     18        .0 Ind = Indicator Stations Cntl = Control Stations                                                              Page 1 of 1
+2.82E+00 +4.42E+00 +-1.87E-01  
 
+2.92E+02 9.97E+00 7.13E+00 2.14E+01 2.53E+01 1.96E+01 1.54E+01 7.87E+00 6.88E+00 8.66E+00 8.84E+00 1.87E+02 1.64E+01 1.16E+01 3.50E+01 1.52E+01 3.19E+01 2.39E+01 1.28E+01 1.09E+01 1.36E+01 1.45E+01 8/27/2013 MDA Station 37 Onion collected Nuclide RQ Activity Error Station 37 Onion collected Nuclide RQ Activity Error K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140+ 7.65E+02-6.13E+00 2.45E+00 3.76E+00-9.91E-01 5.51 E+00 5.70E-02 0.OOE+00 5.27E+00 1.78E+00 2.01E-01+++++++++2.03E+02 1.01E+01 7.73E+00 2.25E+01 1.41E+01 1.99E+01 1.34E+01 1.02E+01 8.90E+00 9.33E+00 1.04E+01 2.29E+02 1.56E+01 1.22E+01 3.61 E+01 1.73E+01 3.17E+01 2.20E+01 1.68E+01 1.39E+(1 1.50E+01 1.71 E+01 K-40 + 1.64E+03 +MN-54 3.47E+00 +CO-58 -5.26E+00  
I TABLE A-45.1 GAMMA SPECTROMETRY RESULTS OF ROOTCROPS, Results in pCi/ kilogram (wet)
+FE-59 -9.18E+00
I Station 37 is Indicator        - Station 9c is Control                                      I Station 37 Potato collected                      7/2/2013                          Station 37 Potato collected      8/27/2013 Nuclide RQ Activity K-40      + 3.20E+03          +
+CO-60 -1.44E+00
Error 3.29E+02 MDA-1.48E+02 Nuclide R-Q Activity K-40    + 3.40E+03 +
+ZN-65 -8.32E+00
Error 2.92E+02 MDA 1.87E+02 i
+ZRNB-95 -2.30E+00
MN-54            -1.57E-01              6.25E+00          1.02E+01                  MN-54            0.OOE+00 +    9.97E+00    1.64E+01 CO-58 FE-59 CO-60 2.70E+00 +
+1-131 -3.72E+00  
3.76E-02 3.84E+00 +
+CS-134 -6.33E+00
4.78E+00 1.73E+01 9.03E+00 6.79E+00 2.84E+01 1.38E+01 CO-58 FE-59 CO-60
+CS-1 37 -2.55E+00  
                                                                                                        -8.67E-01 +
+BALA140 8.72E-02 +2.40E+02 8.34E+00 1.10E+01 2.84E+01 8.93E+00 2.46E+01 1.66E+01 1.13E+01 1.31 E+01 1.04E+01 9.30E+00 2.39E+02 1.31E+01 1.74E+01 4.51E+01 1.44E+01 3.92E+01 2.69E+01 1.82E+01 2.10E+01 1.67E+01 1.53E+01 I I I i I I I I I I I I I I I I I I I Station 37 Potato colle Nuclide RQ Activity K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-1 34 CS-137 BALA140+ 4.31E+03 +0.OOE+00 +2.34E+00 +0.OOE+00 +-1.72E+00
1.35E+00 +
+-1.39E+01  
                                                                                                        -2.17E+00 +
+-3.70E+00
7.13E+00 2.14E+01 2.53E+01 1.16E+01 3.50E+01 1.52E+01 I
+-5.81 E+00 +-6.37E+00
ZN-65            1.29E+00 +            1.68E+01        2.73E+01                  ZN-65          2.05E+00 +    1.96E+01 ZRNB-95 1-131
+-7.99E+00  
                    -3.54E-01 &#xf7;
+6.69E+00 +,cted 7/30/2013 Error MDA 4.20E+02 3.24E+02 1.47E+01 2.42E+01 1.20E+01 1.94E+01 3.39E+01 5.57E+01 1.15E+01 1.86E+01 3.48E+01 5.55E+01 2.43E+01 3.94E+01 1.29E+01 2.05E+01 1.62E+01 2.61E+01 1.56E+01 2.46E+01 1.26E+01 1.91E+01 Station 9c Potato collected Nuclide RQ Activity K-40 + 3.78E+0 MN-54 1.08E-0 CO-58 -1.51E+0 FE-59 7.26E-0 CO-60 -3.70E+0 ZN-65 -1.28E+0 ZRNB-95 -6.99E+0 1-131 -5.93E+0 CS-134 -3.69E+0 CS-137 -2.75E+0 BALA140 2.32E-0 Error 3+1+0+1+0+1+0+0+0+0+1+3.60E+02 9.07E+00 1.11E+01 2.89E+01 1.37E+01 2.74E+01 2.08E+01 1.43E+01 1.37E+01 1.30E+01 1.25E+01 8/9/2013 MDA 2.74E+02 1.49E+01 1.81E+01 4.74E+01 2.19E+01 4.32E+01 3.32E+01 2.29E+01 2.23E+01 2.11E+01 2.05E+01 RQ = Results Qualifier.
                    -2.49E+00 9.43E+00 6.34E+00 1.54E+01 9.92E+00 ZRNB-95 1-131 9.05E+00 +
If blank, result is less than detection limit. If "+", result is above detection limit.Page 1 of 1
                                                                                                        -1.38E+00 +
.; ;TABLE'A-15.2 GAMMA SPECTROMETRY RESULTS OF ROOT CROPS -
1.54E+01 7.87E+00 3.19E+01 2.39E+01 1.28E+01 I
CS-134            2.25E+00             4.54E+00         6.73E+00                 CS-1 34          2.82E+00 +   6.88E+00     1.09E+01 CS-137 BALA140 3.92E+00 +
                    -1.46E+00 6.95E+00 8.21 E+00 1.04E+01 1.29E+01 CS-137 BALA140 4.42E+00 +
                                                                                                        -1.87E-01 +
8.66E+00 8.84E+00 1.36E+01 1.45E+01 I Station 37 Onion collected                      7/16/2013                           Station 37 Onion collected        8/27/2013 I
Nuclide    RQ Activity                      Error            MDA                  Nuclide      RQ Activity            Error      MDA K-40 MN-54
              +      7.65E+02
                    -6.13E+00
                                    +
                                    +
2.03E+02 1.01E+01 2.29E+02 1.56E+01 K-40 MN-54
                                                                                                    + 1.64E+03 +
3.47E+00 +
2.40E+02 8.34E+00 2.39E+02 1.31E+01 I
                                    +
CO-58            2.45E+00               7.73E+00         1.22E+01                   CO-58          -5.26E+00 +     1.10E+01   1.74E+01 FE-59 CO-60 3.76E+00
                    -9.91E-01
                                    +
2.25E+01 1.41E+01 3.61 E+01 1.73E+01 FE-59 CO-60
                                                                                                        -9.18E+00 +
                                                                                                        -1.44E+00 +
2.84E+01 8.93E+00 4.51E+01 1.44E+01 I
ZN-65            5.51 E+00            1.99E+01         3.17E+01                  ZN-65          -8.32E+00 +    2.46E+01    3.92E+01 I
                                    +
ZRNB-95             5.70E-02              1.34E+01          2.20E+01              ZRNB-95            -2.30E+00 +     1.66E+01    2.69E+01
                                    +
1-131          0.OOE+00             1.02E+01          1.68E+01                    1-131        -3.72E+00 +     1.13E+01    1.82E+01
                                    +
CS-134            5.27E+00             8.90E+00          1.39E+(1                 CS-134          -6.33E+00 +     1.31 E+01   2.10E+01
                                    +
CS-137            1.78E+00             9.33E+00         1.50E+01                 CS-1 37          -2.55E+00 +     1.04E+01   1.67E+01 BALA140              2.01E-01      +
1.04E+01         1.71 E+01             BALA140              8.72E-02 +   9.30E+00    1.53E+01 I
Station 37 Potato colle,cted                    7/30/2013                          Station 9c Potato collected        8/9/2013 I
Nuclide    RQ Activity                      Error            MDA                  Nuclide RQ Activity                  Error K-40 MN-54
              + 4.31E+03 +
0.OOE+00 +
4.20E+02 1.47E+01 3.24E+02 2.42E+01 K-40 MN-54
                                                                                                    + 3.78E+0 3+
1.08E-0 1+
3.60E+02 9.07E+00 MDA 2.74E+02 1.49E+01 I
CO-58            2.34E+00 +             1.20E+01        1.94E+01                  CO-58          -1.51E+0 0+   1.11E+01     1.81E+01 FE-59 CO-60 0.OOE+00 +
                    -1.72E+00 +
3.39E+01 1.15E+01 5.57E+01 1.86E+01 FE-59 CO-60 7.26E-0 1+
                                                                                                        -3.70E+0 0+
2.89E+01 1.37E+01 4.74E+01 2.19E+01 I
ZN-65          -1.39E+01 +              3.48E+01         5.55E+01                   ZN-65          -1.28E+0 1+    2.74E+01   4.32E+01 ZRNB-95 1-131 CS-1 34
                    -3.70E+00 +
                    -5.81 E+00 +
                    -6.37E+00 +
2.43E+01 1.29E+01 1.62E+01 3.94E+01 2.05E+01 2.61E+01 ZRNB-95 1-131 CS-134
                                                                                                        -6.99E+0 0+
                                                                                                        -5.93E+0 0+
                                                                                                        -3.69E+0 0+
2.08E+01 1.43E+01 1.37E+01 3.32E+01 2.29E+01 2.23E+01 I
CS-137            -7.99E+00 +             1.56E+01        2.46E+01                CS-137          -2.75E+0 0+   1.30E+01   2.11E+01 BALA140            6.69E+00 +             1.26E+01         1.91E+01             BALA140                2.32E-0 1+   1.25E+01   2.05E+01   I I
RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit.                   Page 1 of 1 I
 
                                                    . ; ;TABLE'A- 15.2 GAMMA SPECTROMETRY RESULTS OF ROOT CROPS -  


==SUMMARY==
==SUMMARY==
Results in pCi/ kilogram (wet)Average Activity Activity Low Activity Average Number of Number of High MDA Samples Positive IDs Nuclide BALA140 Ind 1.07E+00 BALA140 cntl 2.32E-01 CO-58 Ind 2.72E-01 CO-58 cntl -1.51 E+00-1.46E+OO 6.69E+00 1.58E+01 2.32E-01 2.32E-01 2.05E+01-5.26E+00 2.70E+00 1.35E+01-1.51E+00
-1.51EOO 1.81E+01 CO-60 Ind CO-60 cntl-4.96E-01
-2.17E+00 3.84E+00 1.58E+01-3.70E+00
-3.70E+00
-3.70E+00 2.19E+01 5 1 5 1 , 5 1 5 1 5 1 0 0 0 0 0 0 0 0 0 0 CS-1 34 CS-134 Ind -4.74E-01 cntl -3.69E+00-6.37E+00-3.69E+00 5.27E+00 1.57E+01-3.69E+00 2.23E+01 CS-137 Ind -8.42E-02
-7.99E+00 4.42E+00 1.61E+01 CS-137 cntl -2.75E+00
-2.75E+00
-2.75E+00 2.11E+01 FE-59 Ind -8.08E-01 FE-59 entl 7.26E-0i 1-131 Ind -2.68E+00 1-131 cntl -5.93E+00 K-40 Ind 2.66E+03 K-40. cntl 3.78E+03 MN-54 Ind -5.64E-01 MN-54 cntl 1.08E-01-9.18E+00 3.76E+00 7.26E-01 7.26E-01-5.81 E+00 0.00E+00-5.93E+00
-5.93E+00 7.65E+02 3.78E+03 4.31 E+03 3.78E+03 4.01E+01 4.74E+01 1.56E+01 2.29E+01 2.26E+02 2.74E+02 1.59E+01 1.49E+01 3.71E+01 4.32E+01 5 1 5 1 5 1 5 1 ,0 0 0 0 5 1 0 0-6.13E+00 3.47E+00 1.08E-01 1.08E-01 ZN-65 Ind -2.68E+00
-1.39E+01 5.51 E+00 ZN-65 cntl -1.28E+01
-1.28E+01
-1.28E+01 5 1 5 1 0 0 0 0 ZRNB-95 Ind ZRNB-95 cntl 5.51 E-01 -3.70E+00 9.05E+00 2.55E+01-6.99E+00
-6.99E+00
-6.99E+00 3.32E+01 Ind = Indicator Stations Cntl = Control Stations Page 1 of 1


GAMMA SPECTROMETRY RESULTS- OFFRUITS Results in pCi/ kilogram. (wet)Station 37 is Indicator r Station 9c isControl-Nuclide K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140 Station,37, Peaches collected 7/12/2013 R- Activity Error -MDA Station 37 Apples+ 1..42E+03
Results in pCi/ kilogram (wet)
+-1.86E+00  
Average            Activity          Activity        Average      Number of Number of Nuclide                 Activity              Low              High              MDA      Samples  Positive IDs BALA140 Ind                1.07E+00          -1.46E+OO          6.69E+00          1.58E+01    5          0 BALA140 cntl              2.32E-01          2.32E-01          2.32E-01           2.05E+01    1          0 CO-58          Ind        2.72E-01        -5.26E+00          2.70E+00            1.35E+01    5          0 CO-58          cntl      -1.51 E+00        -1.51E+00         -1.51EOO            1.81E+01    1 ,        0 CO-60          Ind        -4.96E-01        -2.17E+00           3.84E+00           1.58E+01     5          0 CO-60          cntl      -3.70E+00         -3.70E+00         -3.70E+00           2.19E+01    1          0 CS-1 34        Ind        -4.74E-01        -6.37E+00           5.27E+00           1.57E+01     5          0 CS-134        cntl      -3.69E+00          -3.69E+00         -3.69E+00            2.23E+01     1          0 CS-137        Ind        -8.42E-02        -7.99E+00         4.42E+00           1.61E+01    5           0 CS-137        cntl      -2.75E+00         -2.75E+00        -2.75E+00            2.11E+01     1           0 FE-59          Ind        -8.08E-01         -9.18E+00           3.76E+00          4.01E+01     5              ,0 FE-59          entl        7.26E-0i          7.26E-01         7.26E-01          4.74E+01     1          0 1-131          Ind      -2.68E+00          -5.81 E+00         0.00E+00           1.56E+01     5          0 1-131          cntl      -5.93E+00          -5.93E+00        -5.93E+00           2.29E+01    1          0 K-40          Ind        2.66E+03            7.65E+02        4.31 E+03          2.26E+02    5          5 K-40.          cntl        3.78E+03          3.78E+03          3.78E+03          2.74E+02    1          1 MN-54          Ind        -5.64E-01        -6.13E+00          3.47E+00          1.59E+01     5          0 MN-54          cntl        1.08E-01           1.08E-01          1.08E-01          1.49E+01     1          0 ZN-65          Ind      -2.68E+00          -1.39E+01           5.51 E+00          3.71E+01    5          0 ZN-65          cntl      -1.28E+01         -1.28E+01         -1.28E+01           4.32E+01     1          0 ZRNB-95        Ind        5.51 E-01       -3.70E+00          9.05E+00            2.55E+01     5          0 ZRNB-95        cntl      -6.99E+00          -6.99E+00        -6.99E+00            3.32E+01     1          0 Ind = Indicator Stations  Cntl = Control Stations                                                              Page 1 of 1
+0.OOE+00 +-2.07E+00.
 
+3.06E+00 +-1.15E-01  
I TABLEA*-6.1 GAMMA SPECTROMETRY RESULTS- OFFRUITS Results in pCi/ kilogram. (wet)
+0.OOE+00 +-2.40E+00  
I Station 37 is Indicator r Station 9c isControl                                                    I Station,37, Peaches         collected         7/12/2013                              Station 37 Apples collected    8/14/2013
+-2.61 E+00 +-1.50E+00
-Nuclide R-K-40 Activity
+:0.00E+00  
                + 1..42E+03 +
+2.10E+02 6.48E+00 1'.05E+01.
Error-2.10E+02 MDA 1.34E+02 Nu cli1de Rd.-- Alctivity-K-40      -. 1.21E+03 +
1.89E+01 5.73E+00 1.43E+0V 1.14E+01, 7.21 E+00 6.73E+00 5.07E+00 1.17E+01 1.34E+02 1.02E+01 1 .73E+01 3.04E+01 8.25E+00 2.34E+01 1.58E+01 1.14E+01 1.05E+01 7.83E+00 1 .92E+01 Nu cli1d e Rd.-- Alctivity-K-40 -.1.21E+03 +MN-54 " 8.18E-01 +C.0-58 .0;00E+00  
                                                                                                                        .,Error'.
+FE-59 -1.62E+01  
2.68E+02 MDA 3.30E+02 i
+/-CO-60 -7.15E-01
MN-54            -1.86E+00 +           6.48E+00         1.02E+01                  MN-54        " 8.18E-01  +    1.25E+01      2.04E+01 CO-58 FE-59 CO-60 0.OOE+00 +-
+ZN-65., -4.40E+00  
2.07E+00. +
+ZRNB-95 2.75E+00 +1-131. -8.94E+00
3.06E+00 +
+CS-134 -1.04E+01
1'.05E+01.
+CS-137 -2.67E+00
1.89E+01 5.73E+00 1.73E+01 3.04E+01 8.25E+00 C.0-58 FE-59 CO-60
+BALA140 7.26E+00 +collected 8/14/2013.,Error'.
                                                                                                        .0;00E+00
MDA 2.68E+02 3.30E+02 1.25E+01 2.04E+01 1.27E+01 2.09E+01 4.12E+01 6.49E+01 1.39E+01.,., 2.28E+01 2.93E+01 , 4.74E+01 2.43E+01 3.96E+01 3.10E+01 5.OOE+01 1.86E+01 2.96E+01 1.42E+01*
                                                                                                        -1.62E+01
2.30E+01 2.20E+01 3.44E+01'Nuclide K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140 Station 37 Peaches collected Rd -Activity-
                                                                                                        -7.15E-01
-.. ...Error+ 1.92E+03 +6.46E+00 +0.OOE+00 +-5.65E+00
                                                                                                                  +
+8.88E-01 +1.44E+01 +7.49E-01 +4.68E+00 +0.OOE+00 +-3.43E+00
                                                                                                                  +/-
+0.OOE+00 +2.42E+02 7.45E+00 6.45E+00 2.30E+01 9.06E+00 1.72E+01 1.23E+01 8.88E+00 1.02E+01 9.20E+00 8.73E+00 7/30/2013 MDA 1.94E+02 1.10E+01 1.06E+01 3.67E+01 1.56E+01 2.53E+01 2.OOE+01 1.41 E+01 1.68E+01 1.46E+01 1.44E+01 Station 37 Peaches collected-Nuclide _ROQ- Acti-vity
                                                                                                                  +
-..- .:, Error.K-40 MN-54 CO-58 FE-59 CO-60: 'ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140+ 1.46E+03 +2.15E+00 +5.96E+00 +-7.52E-01
1.27E+01 4.12E+01 1.39E+01.,.,
+-2.15E-01
2.09E+01 6.49E+01 2.28E+01 I
+0.OOE+00 +4.32E-01 +--5.40E+00  
ZN-65            -1.15E-01 +           1.43E+0V          2.34E+01                 ZN-65.,        -4.40E+00  +    2.93E+01 ,   4.74E+01 ZRNB-95 1-131 0.OOE+00 +
+'6.29E-01 +-1.74E+00
                    -2.40E+00 +
+.4.17E-01  
1.14E+01, 7.21 E+00 1.58E+01 1.14E+01 ZRNB-95 1-131.
+.1.96E+02 7.40E+00 7.55E+00 1.90E+01 7.38E+00.2.77E+01 1.28E+01 9.01 E+00 8.86E+00 8.33E+00 5.91 E+00 8/27/2013 MDA 1.91 E+02 1.18E+01-1.15E+01 3.11E+01 1.21 E+01 4.56E+01.2.09E+01 1.43E+01 1.45E+01 11.35E+01 9.59E+00 I I I i I I I I I I I U I I I 1 I I I Station 37 Apples collected Nuclide Ro -Activity
2.75E+00
.. .Err-or 8/9/2013 MDA Station 37 Applescollected-Nuclide-Ro Actifvify Error 9/10/2013 MDA- -K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA1 40+ 1.19E+03 +1.86E+00 +-3.45E-02
                                                                                                        -8.94E+00
+-6.43E+00
                                                                                                                  +
+-5.24E-01
                                                                                                                  +
+-5.75E+00
2.43E+01 3.10E+01 3.96E+01 5.OOE+01 I
+-3.22E+00  
CS-134            -2.61 E+00 +           6.73E+00         1.05E+01               CS-134            -1.04E+01  +     1.86E+01    2.96E+01 CS-137 BALA140
+5.24E+00 +-3.49E+00
                    -1.50E+00 +
+3.37E+00 +5.88E+00 +2.46E+02 1.09E+01 1.23E+01 2.97E+01 1.47E+01 2.67E+01 1.69E+01 1.05E+01 1.42E+01 1.02E+01 1.37E+01 2.65E+02 1.76E+01 2.02E+01 4.74E+01 2.21 E +001 4.29E+01 2.71 E+01 1.64E+01 2.30E+01 1.60E+01 2.07E+01 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140+ 1.53E+03 +-2.99E+00  
:0.00E+00 +
+-3.05E+00  
5.07E+00 1.17E+01 7.83E+00 1.92E+01 CS-137 BALA140
+7.20E-01 +1.72E+00 +2.22E+00 +-2.04E-02
                                                                                                        -2.67E+00 7.26E+00 +
+6.69E-01 +-3.13E+00
                                                                                                                  +     1.42E+01*
+-4.95E+00  
2.20E+01 2.30E+01 3.44E+01   I Station 37 Peaches collected                  7/30/2013                            Station 37 Peaches collected      8/27/2013 I
+1.63E+00 +2.30E+02 9.79E+00 8.28E+00 2.03E+01 1.06E+01 2.11E+01 1.51 E+01 9.81 E+00 1.05E+01 1.09E+01 1.23E+01 2.11E+02 1.56E+01 1.30E+01 3.32E+01 1.80E+01 3.43E+01 2.48E+01 1.60E+01 1.70E+01 1.72E+01 1.99E+01 RQ = Results Qualifier.
'Nuclide    Rd -Activity- -... ..Error                        MDA                -Nuclide _ROQ- Acti-vity -..- . :, Error.            MDA K-40 MN-54
If blank, result is less than detection limit. If "+", result is above detection limit.Page 1 of 2  
                + 1.92E+03 + 2.42E+02 6.46E+00 +            7.45E+00 1.94E+02 1.10E+01 K-40 MN-54
,TABLE A-1 6.1 GAMMA- SPECTROMETRY RESULTS,,OFz FRUITS* 'Results in pCi/ kilogram (wet)Station 37 is Indicator
                                                                                                    + 1.46E+03 +
-Station 9c.is 'Cbntrol Station 37 wine grapes collected 9/10/2013 FNuclide--RQ -Activity
2.15E+00 +
-Er-r MDA K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95.1-131 0CS-134 CS-137 BALA140+ 2.36E+03 +-8.07E-03
                                                                                                                      .1.96E+02 7.40E+00 1.91 E+02 1.18E+01 I
+-1.25E-01  
CO-58            0.OOE+00 +           6.45E+00         1.06E+01                 CO-58            5.96E+00 +     7.55E+00      -1.15E+01 FE-59 CO-60 ZN-65
+-5.28E-01  
                    -5.65E+00 + 2.30E+01 8.88E-01 + 9.06E+00 1.44E+01 +           1.72E+01 3.67E+01 1.56E+01 2.53E+01 FE-59 CO-60:
+1.60E+00 +1.02E+01 +-9.69E-02
                                                                                      'ZN-65
+'2.54E+00
                                                                                                        -7.52E-01 +
+8.35E-02'+
                                                                                                        -2.15E-01 +
2.01E-01 +--1.38E+00  
1.90E+01 7.38E+00 0.OOE+00 + .2.77E+01 3.11E+01 1.21 E+01 4.56E+01 I
+2.46E+02 5.57E+00 5.64E+00 1.78E+01 5.76E+00, 1.41E+01 5.08E+00 4.78E+00 4.63E+00, 4.62E+00 5.95E+00 1.04E+02 9.15E+00 9.25E+00 2.91 E+01 8.93E+00 2.05E+01 8.31 E+00 7.23E+00 7.59E+00 7.54E+00 9.12E+00 Statior K-40&#xfd; +MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 -CS-137 BALA140 n 37 wine grapes collected.Activity
ZRNB-95 1-131 CS-134 7.49E-01 +
'; -Error'9/10/2013 MDA- -1 2.55E+03 +1.90E-01 +4.32E+00 +2.02E-01 +-3.38E+00
4.68E+00 + 8.88E+00 0.OOE+00 +
+-5.03E+00  
1.23E+01 1.02E+01 2.OOE+01 1.41 E+01 1.68E+01 ZRNB-95 1-131 CS-134 4.32E-01 +-   1.28E+01
+3.96E+00 +3.26E+00 +1.72E+00 +-2.05E+00  
                                                                                                        -5.40E+00 +' 9.01 E+00 6.29E-01 +   8.86E+00
+2.78E+00 +2.89E+02 9.78E+00 8.70E+00 1.94E+01 1.04E+01 2.05E+01 1.42E+01 9.97E+00 1.09E+01 1.04E+01 1.05E+01 2.44E+02 1.60E+01 1.36E+01 3.19E+01 1.66E+01 3.28E+01 2.26E+01 1.60E+01 1.77E+01 1.69E+01.1.66E+01 IStation 9c Apples collected r-Niide RQ Ac-tvity .V Error K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 0CS-134 CS-137!BALA140+ 1.01E+03 +-1.51 E+00 _+-2.18E+00  
                                                                                                                                      .2.09E+01 1.43E+01 1.45E+01 I
+,-1.10E+00
CS-137          -3.43E+00 + 9.20E+00                     1.46E+01               CS-137            -1.74E+00 + 8.33E+00          11.35E+01 BALA140              0.OOE+00 + 8.73E+00                    1.44E+01             BALA140              .4.17E-01 +   5.91 E+00    9.59E+00 U
_+6.61E-01 +-5.40E+00
Nuclide Station 37 Apples collected Ro -Activity ..                 .Err-or 8/9/2013 MDA                -Nuclide- Ro Station 37 Applescollected Actifvify        Error 9/10/2013 MDA- -
+.-5.05E-01 +6.72E-0.1
I K-40      + 1.19E+03 +               2.46E+02          2.65E+02                    K-40      +    1.53E+03  +    2.30E+02      2.11E+02 MN-54 CO-58 1.86E+00 +
+-3.63E+00  
                    -3.45E-02 +
+-2.50E.+00  
1.09E+01 1.23E+01 1.76E+01 2.02E+01 MN-54 CO-58
+-3.34E-01
                                                                                                        -2.99E+00
+1.94E+02 7.00E+00 7.84E+00 2.01 E+01 8.93E+00 2.15E+01 1.17E+01:1.13E+01 9.61 E+00 8.19E+00-1.08E+01 9/6/2013 MD-A...1.98E+02 1.,12E+01 1.25E+01 3.29E+01 1.54E+01 3.45E+01 1.91 E+01 1.85E+01 1:54E+01 1.31 E+01 1.77E+01 RO = Results Qualifier.
                                                                                                        -3.05E+00
If blank, result is less than detection limit. If "+", result is above detection limit.Page 2 of 2 I I TABLEA,- 16.2 GAMMA SPECTROMETRY RESULTS OF FRUITS-  
                                                                                                                  +
                                                                                                                  +
9.79E+00 8.28E+00 1.56E+01 1.30E+01 I
FE-59          -6.43E+00 +             2.97E+01         4.74E+01                  FE-59            7.20E-01 +   2.03E+01      3.32E+01 CO-60 ZN-65 ZRNB-95
                    -5.24E-01 +
                    -5.75E+00 +
                    -3.22E+00 +
1.47E+01 2.67E+01 1.69E+01 2.21 E+001 4.29E+01 2.71 E+01 CO-60 ZN-65 ZRNB-95 1.72E+00 2.22E+00
                                                                                                        -2.04E-02
                                                                                                                  +
                                                                                                                  +
                                                                                                                  +
1.06E+01 2.11E+01 1.51 E+01 1.80E+01 3.43E+01 2.48E+01 I
1-131 CS-134 CS-137 5.24E+00 +
                    -3.49E+00 +
3.37E+00 +
1.05E+01 1.42E+01 1.02E+01 1.64E+01 2.30E+01 1.60E+01 1-131 CS-134 CS-137 6.69E-01
                                                                                                        -3.13E+00
                                                                                                        -4.95E+00
                                                                                                                  +
                                                                                                                  +
                                                                                                                  +
9.81 E+00 1.05E+01 1.09E+01 1.60E+01 1.70E+01 1.72E+01 1
BALA1 40            5.88E+00 +           1.37E+01          2.07E+01            BALA140              1.63E+00 +   1.23E+01       1.99E+01 I
I RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit.                 Page 1 of 2     I
 
                                                                    ,TABLE A-1 6.1 GAMMA- SPECTROMETRY RESULTS,,OFz FRUITS
                                                            * 'Results in pCi/ kilogram (wet)
Station 37 is Indicator - Station 9c.is 'Cbntrol Station 37 wine grapes collected                  9/10/2013                        Statiorn 37 wine grapes collected    9/10/2013 FNuclide--RQ -Activity -                    Er-r        J* MDA                                        .Activity    '; -Error'        MDA- -1 K-40      + 2.36E+03 +               2.46E+02          1.04E+02                  K-40&#xfd; + 2.55E+03 + 2.89E+02                2.44E+02 MN-54            -8.07E-03 +            5.57E+00          9.15E+00                  MN-54             1.90E-01 +    9.78E+00      1.60E+01 CO-58           -1.25E-01 +           5.64E+00          9.25E+00                                   4.32E+00 +
CO-58                          8.70E+00     1.36E+01 FE-59          -5.28E-01 +           1.78E+01          2.91 E+01                FE-59            2.02E-01 +   1.94E+01      3.19E+01 CO-60            1.60E+00 +           5.76E+00,        8.93E+00                 CO-60          -3.38E+00 +     1.04E+01      1.66E+01 ZN-65            1.02E+01 +            1.41E+01          2.05E+01                 ZN-65          -5.03E+00 + 2.05E+01           3.28E+01 ZRNB-95            -9.69E-02 +           5.08E+00         8.31 E+00           ZRNB-95              3.96E+00 +    1.42E+01     2.26E+01
    .1-131
                    '2.54E+00 +             4.78E+00          7.23E+00                    1-131          3.26E+00 + 9.97E+00          1.60E+01 0CS-134            8.35E-02'+            4.63E+00, 7.59E+00                        CS-134 -          1.72E+00 +    1.09E+01      1.77E+01 CS-137            2.01E-01 +- 4.62E+00                    7.54E+00                CS-137          -2.05E+00 +      1.04E+01      1.69E+01 BALA140            -1.38E+00 +            5.95E+00          9.12E+00            BALA140              2.78E+00 +    1.05E+01    .1.66E+01 IStation 9c Apples collected                  9/6/2013 r-Niide      RQ Ac-tvity                . V Error MD-A...
K-40      + 1.01E+03 +                1.94E+02          1.98E+02 MN-54          -1.51 E+00 _+ 7.00E+00                    1.,12E+01 CO-58          -2.18E+00 +            7.84E+00          1.25E+01 FE-59        ,-1.10E+00 _+ 2.01 E+01                    3.29E+01 CO-60            6.61E-01 +            8.93E+00          1.54E+01 ZN-65          -5.40E+00 +            2.15E+01          3.45E+01 ZRNB-95            .-5.05E-01 +            1.17E+01          1.91 E+01 1-131 6.72E-0.1 + :1.13E+01                    1.85E+01 0CS-134          -3.63E+00 +            9.61 E+00          1:54E+01 CS-137          -2.50E.+00 +            8.19E+00          1.31 E+01
!BALA140            -3.34E-01 + - 1.08E+01                    1.77E+01 RO = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit.                 Page 2 of 2
 
I TABLEA,- 16.2 GAMMA SPECTROMETRY RESULTS OF FRUITS-  


==SUMMARY==
==SUMMARY==
Results in.pCi/ kilogram (wet)Average Activity Activity Low Nuclide BALA 40 BALA140 CO-58 CO-58 CO-60 CO-60 CS-134 CS-134 CS-137 CS-137 FE-59 FE-59 1-131 1-131 K-40 K-40 MN-54 MN-54 ZN-65 ZN-65 ZRNB-95 ZRNB-95 Ind CntI Ind CntI Ind CntI Ind CntI Ind Cnti Ind Cnti Ind CntI Ind CntI Ind CntI Ind CntI Ind CntI 2.07E+00-3.34E-01 8.84E-01-2.18E+00 3.04E-01 6.61 E-01-2.15E+00-3.63E+00-1.60E+00-2.50E+00-3.32E+00-1.10E+00-4.32E-02 6.72E-01 1.70E+03 1.01 E+03 8.28E-01-1.51 E+00 1.44E+00-5.40E+00 5.68E-01-5.05E-01-1.38E+00-3.34E-01-3.05E+00-2.18E+00-3.38E+00 6.61 E-01-1.04E+01-3.63E+00-4.95E+00-2.50E+00-1.62E+01-1.10E+00-8.94E+00 6.72E-01 1.19E+03 1.01E+03-2.99E+00-1.51 E+00-5.75E+00-5.40E+00-3.22E'+00
 
-5.05E-01 Activity Average High MDA 7.26E+00 1.80E+01-3.34E-01 1.77E+01 5.96E+00 1.45E+01-2.18E+00 1.25E+01 3.06E+00 1.56E+01 6.61E-01 1.54E+01 1.72E+00 1.71E+01-3.63E+00 1.54E+01 3.37E+00 1.46E+01-2.50E+00 1.31E+01 2.07E+00 3.81 E+01-1.10E+00 3.29E+01 5.24E+00 1.82E+01 6.72E-01 1.85E+01 2.55E+03 2.09E+02 1.01 E+03 1.98E+02 6.46E+00 1.40E+01-1.51 E+00 1.12E+01 1 ,44E+01 3.40E+01-5.40E+00 3.45E+01 3.96E+00 2.28E+01-5.05E-01 1.91 E+01 Number of Number of Samples Positive IDs 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 1 0 0 0 0 0 0 I I I I Ind = Indicator Stations Cntl = Control Stations Page 1 of1 TABLE A-17.1 GAMMA ,SPECTROM ETRY. RESUILTS OF VEGETABLES"Results in pCi/ kilogram (wet)Station 37 is Indicator  
Results in.pCi/ kilogram (wet)
-Station 9c is Control Station 37 Asparagus collected Nuclide RQ Activity Error 4/16/2013 Station 37 Green Bean collected MDA " Nucl"ide RQ Activity Error -7/16/2013 MDA--1 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140+ 2.57E+03 +-5.86E-01
I Average           Activity           Activity        Average      Number of Number of Nuclide                  Activity             Low               High              MDA        Samples  Positive IDs BALA 40 Ind              2.07E+00          -1.38E+00          7.26E+00          1.80E+01                  0 BALA140 CntI            -3.34E-01          -3.34E-01          -3.34E-01         1.77E+01                  0 CO-58 CO-58 Ind CntI 8.84E-01
+-7.03E-01  
                              -2.18E+00
+-7.71E+00  
                                                -3.05E+00
+1.68E+00 +-5.05E+00  
                                                -2.18E+00 5.96E+00
+-7.OOE-01  
                                                                    -2.18E+00 1.45E+01 1.25E+01 0
+-3.70E+00  
0            I CO-60          Ind        3.04E-01         -3.38E+00           3.06E+00           1.56E+01                  0 CO-60          CntI      6.61 E-01          6.61 E-01        6.61E-01         1.54E+01                 0 CS-134        Ind      -2.15E+00         -1.04E+01            1.72E+00         1.71E+01                 0 CS-134        CntI    -3.63E+00          -3.63E+00         -3.63E+00          1.54E+01                  0 CS-137        Ind      -1.60E+00         -4.95E+00           3.37E+00           1.46E+01                 0 CS-137        Cnti    -2.50E+00         -2.50E+00         -2.50E+00           1.31E+01                 0 FE-59          Ind      -3.32E+00         -1.62E+01            2.07E+00          3.81 E+01                0 FE-59          Cnti    -1.10E+00         -1.10E+00         -1.10E+00           3.29E+01                  0 1-131          Ind      -4.32E-02          -8.94E+00          5.24E+00         1.82E+01                  0 1-131          CntI      6.72E-01           6.72E-01         6.72E-01          1.85E+01                 0 K-40          Ind        1.70E+03          1.19E+03          2.55E+03          2.09E+02                  8 K-40          CntI      1.01 E+03          1.01E+03          1.01 E+03        1.98E+02                  1 MN-54          Ind        8.28E-01         -2.99E+00           6.46E+00         1.40E+01                 0 MN-54          CntI    -1.51 E+00         -1.51 E+00        -1.51 E+00         1.12E+01                 0 ZN-65          Ind        1.44E+00         -5.75E+00           1,44E+01          3.40E+01                 0 ZN-65          CntI    -5.40E+00          -5.40E+00        -5.40E+00          3.45E+01                 0 ZRNB-95        Ind        5.68E-01          -3.22E'+00         3.96E+00          2.28E+01                 0 ZRNB-95        CntI      -5.05E-01           -5.05E-01         -5.05E-01          1.91 E+01                 0 I
+1.84E+00 +-3.22E+00  
I I
+-2.22E+00
Ind = Indicator Stations Cntl = Control Stations                                                                   Page 1 of1
+2.93E+02: 9.96E+00 7.39E+00 2.57E+01 9.58E+00 2.48E+01 1.83E+01 1.11E+01 9.87E+00 1.02E+01 1.35E+01 2.24E+02 1.63E+01 1.20E+01 4.06E+01 1.66E+01 4.OOE+01 2.99E+01 1.78E+'01 1.60E+01 1.62E+01 2.17E+01 I K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95.1-131.CS-134 CS-137 BALA140+ 3.62E+03 +-8.64E+00  
 
+5.13E+00 +0.OOE+00 +-6.58E+00  
TABLE A-17.1 GAMMA,SPECTROM ETRY. RESUILTS OF VEGETABLES "Results in pCi/ kilogram (wet)
+0.OOE+00 +3.24E-01 +-7.31E+00  
Station 37 is Indicator - Station 9c is Control Station 37 Asparagus collected                   4/16/2013                         Station 37 Green Bean collected     7/16/2013 MDA--1 Nuclide RQ Activity                        Error            MDA "                Nucl"ide RQ Activity                Error -
+-1.25E+00  
K-40     + 2.57E+03 +                2.93E+02:        2.24E+02                    I K-40      + 3.62E+03 + 4.OOE+02            3.38E+02 MN-54            -5.86E-01 +           9.96E+00         1.63E+01                  MN-54          -8.64E+00 +     1.72E+01       2.71 E+01 CO-58            -7.03E-01 +            7.39E+00         1.20E+01                  CO-58            5.13E+00 +     1.31E+01      2.06E+01 FE-59          -7.71E+00 +             2.57E+01         4.06E+01                  FE-59          0.OOE+00 +    2.80E+01     4.60E+01 CO-60            1.68E+00 +             9.58E+00         1.66E+01                 CO-60          -6.58E+00 +     1.77E+01       2.81E+01 ZN-65          -5.05E+00 +             2.48E+01         4.OOE+01                   ZN-65          0.OOE+00 +    3.64E+01       5.98E+01 ZRNB-95            -7.OOE-01 +           1.83E+01         2.99E+01             ZRNB-95               3.24E-01 +    2.30E+01      3.78E+01 1-131        -3.70E+00 +             1.11E+01        1.78E+'01                  .1-131.       -7.31E+00 +     1.68E+01      2.69E+01 CS-134            1.84E+00 +             9.87E+00         1.60E+01                CS-134          -1.25E+00 +     1.44E+01      2.36E+01 CS-137          -3.22E+00 +             1.02E+01         1.62E+01                 CS-137          -4.68E+00 +     1.64E+01       2.63E+01 BALA140          -2.22E+00 +             1.35E+01         2.17E+01             BALA140              2.06E-01 +   1.63E+01       2.67E+01 Station 37 Asparagus            collected        5/14/2013                        Station  37 Bell Peppers collected    7/30/2013 Nuclide RQ Activity                        Error            MDA                Nuclide RQ          Activity        Error      ..,MDA K-40    + 2.25E+0:3 +               3.22E+02        3.18E+02                      K-40     +  1.46E+0 3+      2.64E+02      2.66E+02 MN-54         -2.50E+0' 0 ..I          1.06E+01          1.69E+01                 MN-54            4.51 E-0 1+    7.92E+00      1.29E+01 CO-58            5.77E+O00 ..I          1.13E+01          1.77E+01                 CO-58            1.46E-0 2+     1.06E+01      1.73E+01 FE-59            1.13E+0 1 +           2.99E+01.       4.69E+01                  FE-59            7.75E-0 1+     2.77E+01      4.53E+01
+-4.68E+00
                                    +
+2.06E-01 +4.OOE+02 1.72E+01 1.31E+01 2.80E+01 1.77E+01 3.64E+01 2.30E+01 1.68E+01 1.44E+01 1.64E+01 1.63E+01 3.38E+02 2.71 E+01 2.06E+01 4.60E+01 2.81E+01 5.98E+01 3.78E+01 2.69E+01 2.36E+01 2.63E+01 2.67E+01 Station 37 Asparagus Nuclide RQ Activity K-40 + 2.25E+0: MN-54 -2.50E+0'CO-58 5.77E+O0 FE-59 1.13E+0 CO-60 -1.06E+0I ZN-65 -3.38E+01 ZRNB-95 6.82E+0'1-131 -1.84E+O0 CS-1 34 -6.74E+0'CS-1 37 8.19E+0'BALA140 7.45E+0I 3 0 0 1 0 0 0 0 0 0 0+..I..I+++++..+++collected 5/14/2013 Error MDA 3.22E+02 3.18E+02 1.06E+01 1.69E+01 1.13E+01 1.77E+01 2.99E+01.
CO-60          -1.06E+0I0 +           1.35E+01         2.21E+01                 CO-60            2.16E+0 0+     1.07E+01     1.86E+01 ZN-65          -3.38E+010 +           2.70E+01         4.38E+01                   ZN-65          -2.75E+0 0+     2.68E+01     4.35E+01 ZRNB-95            6.82E+0' 0 +          2.09E+01         3.33E+01              ZRNB-95            -4.05E+0 0+      2.10E+01      3.39E+01 1-131        -1.84E+O00 ..+         1.34E+01         2.18E+01                     1-131        -8.94E+0 0+     1.39E+01      2.19E+01 CS-1 34          -6.74E+0'0 +            1.49E+0,1        2.38E+01..              CS-134            7.15E+0 0+      l.15E+01     1.79E+01 CS-1 37          8.19E+0' 0 +          1.1.7E+01        1.78E+01                CS-137           7.17E+0 0+      1.25E+01      1.94E+01 BALA140            7.45E+0I0              1.52E+01        2.32E+01             BALA140              1.92E+0 0+     1.56E+01      2.52E+01 Station 37 Broad Leaf Vegtable            collected        6/14/2013            Station 37 Broad Leaf Vegtable collected.       ,   8/9/2013 Nuclide RQ Activity                        Error            MDA                Nuclide RQ Activity                  Error        MDA K-40    + 5.39E+0.3 +               6.65E+02        3.52E+02                      K-40      + 4.81 E+03 + 5.69E+02          4.45E+02 MN-54            5.22E+0' 0 +           1.61E+01         2.50E+01                 MN-54            9.32E-01 +   1.82E+01       2.98E+01 CO-58            6.72E-0 1 +          1.22E+01         1.98E+01                 CO-58            1.64E-01 +   1.64E+01      2.70E+01 FE-59           -7.OOE+0' 0 +          4.75E+01        7.60E+01                    FE-59        -1.44E+01 +     5.22E+01      8.28E+01 CO-60          -2.86E+0'0 +            2.42E+01        3.91 E+01                 CO-60            1.20E+01 + 2.07E+01          3.39E+01 ZN-65            1.33E+0 1 +          2.60E+01         3.68E+01                   ZN-65            3.99E-01 + 4.64E+01         7.61E+01 ZRNB-95            -1.96E+0' 0 +           2.48E+01         4.02E+01             ZRNB-95            -4.34E+00 +    3.38E+01      5.48E+01 1-131          5.16E-0 1 +           1.39E+01         2.27E+01                     1-131        2.35E+01 + 2.26E+01           3.41E+01 CS-1 34          -3.06E+0'0 +           1.55E+01         2.47E+01                 CS-134            6.57E+00 + 2.06E+01          3.30E+01 CS-1 37          0.OOE+0' 0 +           1.62E+01         2.67E+01                 CS-137          -1.74E+00 + 2.02E+01           3.29E+01 BALA140            3.40E+0' 0 +           2.03E+01         3.18E+01             BALA140            -1.80E+00 + 2.66E+01           4.33E+01 RQ = Results Qualifier. If blank, result is less than detection limit. If '+", result is above detection limit.               Page 1 of 2
4.69E+01 1.35E+01 2.21E+01 2.70E+01 4.38E+01 2.09E+01 3.33E+01 1.34E+01 2.18E+01 1.49E+0,1 2.38E+01..
 
1.1.7E+01 1.78E+01 1.52E+01 2.32E+01 Station 37 Bell Peppers collected 7/30/2013 Nuclide RQ Activity K-40 + 1.46E+0 MN-54 4.51 E-0 CO-58 1.46E-0 FE-59 7.75E-0 CO-60 2.16E+0 ZN-65 -2.75E+0 ZRNB-95 -4.05E+0 1-131 -8.94E+0 CS-134 7.15E+0 CS-137 7.17E+0 BALA140 1.92E+0 3+1+2+1+0+0+0+0+0+0+0+Error ..,MDA 2.64E+02 2.66E+02 7.92E+00 1.29E+01 1.06E+01 1.73E+01 2.77E+01 4.53E+01 1.07E+01 1.86E+01 2.68E+01 4.35E+01 2.10E+01 3.39E+01 1.39E+01 2.19E+01 l.15E+01 1.79E+01 1.25E+01 1.94E+01 1.56E+01 2.52E+01 Station 37 Broad Leaf Vegtable collected Nuclide RQ Activity K-40 + 5.39E+0.MN-54 5.22E+0'CO-58 6.72E-0 FE-59 -7.OOE+0'CO-60 -2.86E+0'ZN-65 1.33E+0 ZRNB-95 -1.96E+0'1-131 5.16E-0 CS-1 34 -3.06E+0'CS-1 37 0.OOE+0'BALA140 3.40E+0'Error 3 0 1 0 0 1 0 1 0 0 0+++++++++++6.65E+02 1.61E+01 1.22E+01 4.75E+01 2.42E+01 2.60E+01 2.48E+01 1.39E+01 1.55E+01 1.62E+01 2.03E+01 6/14/2013 MDA 3.52E+02 2.50E+01 1.98E+01 7.60E+01 3.91 E+01 3.68E+01 4.02E+01 2.27E+01 2.47E+01 2.67E+01 3.18E+01 Station 37 Broad Leaf Vegtable collected. , 8/9/2013 Nuclide RQ Activity Error MDA K-40 + 4.81 E+03 + 5.69E+02 4.45E+02 MN-54 9.32E-01 + 1.82E+01 2.98E+01 CO-58 1.64E-01 + 1.64E+01 2.70E+01 FE-59 -1.44E+01
I TABLEA-,17.1 GAMMASPECTROMETRYRESULTS OF VEGETABLES
+ 5.22E+01 8.28E+01 CO-60 1.20E+01 + 2.07E+01 3.39E+01 ZN-65 3.99E-01 + 4.64E+01 7.61E+01 ZRNB-95 -4.34E+00
                                                              .Results in pCi/ kilogram (wet)
+ 3.38E+01 5.48E+01 1-131 2.35E+01 + 2.26E+01 3.41E+01 CS-134 6.57E+00 + 2.06E+01 3.30E+01 CS-137 -1.74E+00
I Station 37 is Indicator - Station 9c is Control                                                  I Station 37 Broad Leaf Vegtable collected                  6/28/2013            SNuclile* :RQ* Station 37        corn collected    8/27/2013
+ 2.02E+01 3.29E+01 BALA140 -1.80E+00
-Nuclide RQ --Activity .
+ 2.66E+01 4.33E+01 RQ = Results Qualifier.
K-40    + 4.75E+03 +
If blank, result is less than detection limit. If '+", result is above detection limit.Page 1 of 2 TABLEA-,17.1 GAMMASPECTROMETRYRESULTS OF VEGETABLES.Results in pCi/ kilogram (wet)Station 37 is Indicator
Error' 6.50E+02 MDA 3.90E+02                    K-40 MN-54
-Station 9c is Control Station 37 Broad Leaf Vegtable collected 6/28/2013-Nuclide RQ --Activity .Error' MDA K-40 + 4.75E+03 + 6.50E+02 3.90E+02 MN-54 -3.40E+00
                                                                                                      -   Activity.
+ 1.85E+01 2.95E+01 CO-58 1.99E+00 + 1.54E+01 2.47E+01 FE-59 0.00E+00 + 1.29E+01 2.12E+01 CO-60 1.33E+00 + 1.93E+O1 3.14E+01 ZN-65 0.OOE+00 + 9.27E+01 1.52E+"02 ZRNB-95 -3.78E+00  
                                                                                                    + 2.16E+03
+ 2.95E+01 4.75E+01 1-131 1.79E-01 + 1.58E+01 2.59E+01 CS-134 1.41 E+00 + 1.67E+01 2.71E+01 CS-137 7.36E+00 + 1.73E+01 2.62E+01 BALA140 -6.63E+00  
                                                                                                          -7.97E-01
+ 2.29E+01 3.53E+01K-40 +MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140 Station 37 corn collected-Activity.2.16E+03 +-7.97E-01  
                                                                                                                    +
+1.52E+00 +5.43E+00 +1.1OE+00 +1.85E+00 +-2.88E+00
                                                                                                                    +
+4.78E+00 +-1.30E+00
Error 2.55E+02 9.90E+00 MDA ---
+1.59E-01 +-1.22E+00
1.93E+02 1.62E+01 I
+Error 2.55E+02 9.90E+00 8.67E+00 2.12E+01 1.12E+01 1.98E+01 1.59E+01 8.79E+00 6.93E+00 8.83E+00 1.02E+01 8/27/2013 MDA ---1.93E+02 1.62E+01 1.40E+01 3.36E+01 1.91E+01 3.21 E+01 2.57E+01 1.38E+01 1.11E+01 S1.45E+01 1.64E+01 Station 37 Corn collected Activity Error 7/2/2013 Station 37 Broad Leaf Vegtable collected MDA Nuclide RQ Activity Error 9/17/2013 MDA Nuclide RQ K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-1 34 CS-1 37 BALA140+ 2.32E+03 +-2.83E+00
MN-54          -3.40E+00 +            1.85E+01         2.95E+01 CO-58 FE-59 CO-60 1.99E+00 +
+3.48E+00 +4.59E-01 +4.54E-01 +-6.18E+00  
0.00E+00 +
+2.57E+00 +3.98E-01 +-5.15E+00  
1.33E+00 +
+-1.35E+00
1.54E+01 1.29E+01 1.93E+O1 2.47E+01 2.12E+01 3.14E+01 CO-58 FE-59 CO-60 1.52E+00 5.43E+00 1.1OE+00
+-4.91 E+00 +2.93E+02 1.12E+01 8.81 E+00 2.51E+01 1.16E+01 2.39E+01 1.74E+01 9.87E+00 1.11 E+01 1.09E+-01 1.38E+01 2.47E+02 1.79E+01 1.38E+01 4.11E+01 2.00E+01 3.83E+01 2.81E+01 1.62E+01 1.76E+01 1.77E+01 2.16E+01 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-1 34 CS-137 BALA140 Nuclide K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140+ 2.65E+03 +-1 .65E+00 +4.73E+00 +-3.30E+00
                                                                                                                    +
+2.69E+00 +-1.52E+00
                                                                                                                    +
+5.04E-01 +0.00E+00 +-7.85E+00
                                                                                                                    +
+-2.38E-01
8.67E+00 2.12E+01 1.12E+01 1.40E+01 3.36E+01 1.91E+01 I
+-6.62E-02
ZN-65            0.OOE+00 + 9.27E+01                     1.52E+"02                ZN-65              1.85E+00 +   1.98E+01    3.21 E+01 ZRNB-95 1-131
+4.08E+02 1.36E+01 1.29E+01 3.10E+01 1.75E+01 2.57E+01 2.47E+01 1 .89E+01 1.78E+01 1.65E+01 1.88E+01 3.71 E+02 2.20E+01 2.02E+01 5.01 E+01 3.OOE+01 4.18E+01 4.06E+01 3.11E+01 2.83E+01 2.71 E+01 3.10E+01 8/9/2013 MDA 2.56E+02 1.55E+01 1.36E+01 4.03E+01 1.81 E+01 4.22E+01 2.58E+01 1.65E+01 1.64E+01 1.70E+01 2.OOE+01 I I I I I I I I I I I I I I I I U i I Station 37 Broad Leaf Vegtable collected 7/12/2013 Nuclide RQ Activity Error MDA -K-40 + 3.96E+03 + 4.92E+02 2.73E+02 MN-54 -2.32E+00
                    -3.78E+00 + 2.95E+01 1.79E-01 +           1.58E+01 4.75E+01 2.59E+01 ZRNB-95 1-131
+ 1.47E+01 2.37E+01 CO-58 3.93E+00 + 1.18E+01 1.83E+01 FE-59 1.16E+01 + 3.68E+01 5.69E+01 CO-60 -4.66E+00  
                                                                                                        -2.88E+00 4.78E+00
+ 1.74E+01 2.75E+01 ZN-65 -3.11E+00
                                                                                                                    +
+ 2.94E+01 4.74E+01 ZRNB-95 -3.OOE+00  
                                                                                                                    +
+ 1.88E+01 3.OOE+01 1-131 0.OOE+00 + 1.34E+01 2.20E+01 CS-134 3.17E+00 + 1.23E+01 1.95E+01 CS-137 5.86E+00 + 1.26E+01 1.91E+01 BALA140 9.68E-03 + 1.25E+01 2.05E+01 RQ+Station 9c Corn collected Activity Error 2.37E+03 + 2.90E+02 5.03E-02 + 9.43E+00 8.04E-01 + 8.34E+00 4.04E+00 + 2.50E+01-1.59E-01
1.59E+01 8.79E+00 2.57E+01 1.38E+01 I
+ 1.10E+01 3.28E-01 + 2.57E+01 4.52E+00 + 1.61E+01 7.70E+00 + 1.06E+01-4.90E+00
CS-134            1.41 E+00 +          1.67E+01        2.71E+01                 CS-134            -1.30E+00   +   6.93E+00    1.11E+01 CS-137 BALA140 7.36E+00 +
+ 1.03E+01-2.05E+00
                    -6.63E+00 + 2.29E+01 1.73E+01        2.62E+01 3.53E+01 CS-137 BALA140 1.59E-01
+ 1.05E+01 5.09E-01 + 1.23E+01 RQ = Results Qualifier.
                                                                                                        -1.22E+00
If blank, result is less than detection limit. If '+", result is above detection limit.Page 2 of 2 TABLE A -17.2 GAMMA SPECTROMETRYRESULTS OF VEGETABLES-  
                                                                                                                    +
                                                                                                                    +
8.83E+00 1.02E+01 S1.45E+01 1.64E+01 I Station 37 Corn collected                7/2/2013            Station 37 Broad Leaf Vegtable collected          9/17/2013 I
Nuclide RQ Activity                        Error           MDA                  Nuclide RQ Activity                    Error        MDA K-40 MN-54 CO-58
              + 2.32E+03 + 2.93E+02
                    -2.83E+00 +
3.48E+00 + 8.81 E+00 1.12E+01 2.47E+02 1.79E+01 1.38E+01 K-40 MN-54 CO-58
                                                                                                    +      2.65E+03
                                                                                                        -1.65E+00 4.73E+00
                                                                                                                    +
                                                                                                                    +
                                                                                                                    +
4.08E+02 1.36E+01 1.29E+01 3.71 E+02 2.20E+01 2.02E+01 I
FE-59 CO-60 ZN-65 4.59E-01 + 2.51E+01 4.54E-01 +
                    -6.18E+00 + 2.39E+01 1.16E+01 4.11E+01 2.00E+01 3.83E+01 FE-59 CO-60 ZN-65
                                                                                                        -3.30E+00 2.69E+00
                                                                                                        -1.52E+00
                                                                                                                    +
                                                                                                                    +
                                                                                                                    +
3.10E+01 1.75E+01 2.57E+01 5.01 E+01 3.OOE+01 4.18E+01 I
ZRNB-95            2.57E+00 +             1.74E+01         2.81E+01             ZRNB-95                5.04E-01 +   2.47E+01    4.06E+01 1-131 CS-1 34 3.98E-01 +
                    -5.15E+00 +
9.87E+00 1.11 E+01 1.62E+01 1.76E+01 1-131 CS-1 34 0.00E+00
                                                                                                        -7.85E+00
                                                                                                                    +
                                                                                                                    +
1.89E+01 1.78E+01 3.11E+01 2.83E+01  I CS-1 37        -1.35E+00 +            1.09E+-01        1.77E+01                CS-137             -2.38E-01  +    1.65E+01    2.71 E+01 BALA140            -4.91 E+00 +           1.38E+01        2.16E+01              BALA140                -6.62E-02  +   1.88E+01     3.10E+01 I
Station 37 Broad Leaf Vegtable collected Nuclide RQ Activity                        Error 7/12/2013 MDA -               Nuclide RQ Activity
                                                                                                  +
Station 9c Corn collected Error 8/9/2013 MDA      I K-40    + 3.96E+03 + 4.92E+02                        2.73E+02                    K-40            2.37E+03 + 2.90E+02        2.56E+02 MN-54 CO-58 FE-59
                    -2.32E+00 +
3.93E+00 +
1.16E+01 +
1.47E+01 1.18E+01 3.68E+01 2.37E+01 1.83E+01 5.69E+01 MN-54 CO-58 FE-59 5.03E-02 + 9.43E+00 8.04E-01 + 8.34E+00 4.04E+00 + 2.50E+01 1.55E+01 1.36E+01 4.03E+01 I
CO-60          -4.66E+00 +             1.74E+01         2.75E+01                   CO-60            -1.59E-01 +     1.10E+01     1.81 E+01 ZN-65 ZRNB-95
                    -3.11E+00 +
                    -3.OOE+00 +
2.94E+01 1.88E+01 4.74E+01 3.OOE+01 ZN-65 ZRNB-95 3.28E-01 +
4.52E+00 +
2.57E+01 1.61E+01 4.22E+01 2.58E+01 I
1-131        0.OOE+00 +             1.34E+01         2.20E+01                     1-131          7.70E+00 +     1.06E+01     1.65E+01 CS-134 CS-137 BALA140 3.17E+00 +
5.86E+00 +
9.68E-03 +
1.23E+01 1.26E+01 1.25E+01 1.95E+01 1.91E+01 2.05E+01 CS-134 CS-137 BALA140
                                                                                                        -4.90E+00 +
                                                                                                        -2.05E+00 +
5.09E-01 +
1.03E+01 1.05E+01 1.23E+01 1.64E+01 1.70E+01 2.OOE+01 I
U i
RQ = Results Qualifier. If blank, result is less than detection limit. If '+", result is above detection limit.                   Page 2 of 2 I
 
TABLE A - 17.2 GAMMA SPECTROMETRYRESULTS OF VEGETABLES-  


==SUMMARY==
==SUMMARY==
.Results in pCi/ kilogram (wet)Average Activity Nuclide BALA1 40 BALA140 CO-58 CO-58 CO-60 CO-60 CS-134 CS-134 CS- 137 CS-137 FE-59 FE-59 1-131 1-131 K-40 K-40 MN-54 MN-54 ZN-65 ZN-65 Ind Cntl Ind CntI Ind CntI Ind Cnti Ind CntI Ind CntI Ind CntI Ind Ontl Ind CntI Ind CntI-3.51 E-01 5.09E-01 2.43E+00 8.04E-01 5.72E-01-1.59E-01-4.74E-01-4.90E+00 1.59E+00-2.05E+00.-2.63E-01 4.04E+00 6.93E-01 7.70E+00 3.27E+03 2.37E+03-1.47E+00 5.03E-02-5.84E-01 3.28E-01 Activity Low-6.63E+00 5.09E-01-7.03E-01 8.04E-01-6.58E+00-1.59E-01-7.85E+00-4.90E+00-4.68E+00-2.05E+00-1.44E+01 4.04E+00-8.94E+00 7.70E+00 1.46E+03 2.37E+03-8.64E+00 5.03E-02-6.18E+00 3.28E-01 Activity Average Number of Number of High' MDA Samples Positive IDs 7.45E+00 5.09E-01 5.77E+00 8.64E-01 1.20E+01-1.59E-01 7.15E+00-4.90E+00 8.19E+00-2.05E+00 1.16E+01 4.04E+00 2.35E+01 7.70E+00 5.39E+03 2.37E+03 5.22E+00 5.03E-02 1.33E+01 3.28E-01 2.70E+01 2.OOE+01 1.87E+01 1.36E+01 2.60E+01 1.81E+01 2.20E+01 1.64E+01 2.22E+01 1.70E+01 4.91E+01 4.03E+01 2.31E+01 1.65E+01 3.11 E+02 2.56E+02 2.16E+01 1.55E+01 5.57E+01 4.22E+01 3.65E+01 2.58E+01 1.1 11 11 1 11 1 11 11 11 11 11 I1*11 11 1" 11 11 11 11 ZRNB-95 Ind ZRNB-95 Cntl-9.54E-01  
 
-4.34E+00 6.82E+00, 4.52E+00 4.52E+00 4.52E+00 0 0 Ind = Indicator Stations Cntl = Control Stations Page 1 of 1 TABLE B-1.11 2013 QUARTERLY SPECIAL INTEREST TLD-RESULTS Results in milli-Roentgen (mR) per Standard Quarter Station ID 1st Quarter 58 21.4 87 32.3 88 24.3 89 24.9 90 18.8 119B 21.5 119C 21.6 120 (East) 21.3 121 64.4 122 33.4 123 105.7 124 126.0 125 92.4 126 94.4 127 73.2 128 114.9 129 93.1 136A 137.2.137A 148.0 138A 118.7 150 (Site 1) 18.1 151 (Site 4) 19.6 2nd Quarter 18.6 23.7 20.9 22.8 17.5 20.2 20.5 21.0 44.9 32.3.103.9 121.3 91.2 90.8 67.9 115.4 88.0 130.0 142.1 113.8 17.7 17.3 3rd Quarter. 4th Quarter Quarterly Sum.21.7 28.9 26.3 27.6 19.6 22.5 23.5 23.3 71.4 35.7 110.9 130.9 96.3 97.6 73.9 118.7 92.1 133.3 147.3 121.2 18.6 19.7-.20.4 28.4 25.5 27.0 19.6 23.3 22.7 23.7 68.7 35.6 111.1 120.5 93.0 94.0 73.4 122.4 93.6 129.7 148.3 118.4 19.5 19.6 82.1 113.4 96.9 102.4 75.4 8725 88.3 89.3 249.5 137.1 431.6 498.7 373.0 376.8 288.5 471.4 366.8 530.3 585.7 472.1 73.9 76.1 I I I I I I I I I i I I I I I I!I I TABLE B-1.2 2013 QUARTERLY SPECIAL INTEREST TLD RESULTS-  
                                                        . Results in pCi/ kilogram (wet)
Average             Activity           Activity          Average      Number of Number of Nuclide                 Activity              Low                High'            MDA        Samples  Positive IDs BALA1 40 Ind             -3.51 E-01         -6.63E+00          7.45E+00          2.70E+01    1.1 BALA140 Cntl                5.09E-01           5.09E-01           5.09E-01         2.OOE+01 11 CO-58          Ind        2.43E+00          -7.03E-01         5.77E+00           1.87E+01 CO-58          CntI        8.04E-01          8.04E-01          8.64E-01         1.36E+01      11 1
CO-60          Ind        5.72E-01         -6.58E+00           1.20E+01          2.60E+01 CO-60          CntI      -1.59E-01          -1.59E-01          -1.59E-01         1.81E+01     11 1
CS-134          Ind        -4.74E-01         -7.85E+00           7.15E+00           2.20E+01 CS-134          Cnti      -4.90E+00         -4.90E+00         -4.90E+00           1.64E+01     11 CS- 137        Ind        1.59E+00         -4.68E+00           8.19E+00           2.22E+01      11 CS-137          CntI      -2.05E+00         -2.05E+00         -2.05E+00           1.70E+01 11 FE-59          Ind      . -2.63E-01         -1.44E+01           1.16E+01         4.91E+01      11 FE-59          CntI      4.04E+00           4.04E+00           4.04E+00           4.03E+01 11 1-131          Ind        6.93E-01         -8.94E+00           2.35E+01         2.31E+01      I1*
1-131          CntI      7.70E+00           7.70E+00            7.70E+00         1.65E+01 11 K-40            Ind        3.27E+03            1.46E+03          5.39E+03          3.11 E+02    11 K-40            Ontl      2.37E+03          2.37E+03            2.37E+03          2.56E+02 1"
MN-54          Ind      -1.47E+00          -8.64E+00            5.22E+00          2.16E+01     11 MN-54          CntI        5.03E-02          5.03E-02          5.03E-02          1.55E+01 11 ZN-65          Ind        -5.84E-01        -6.18E+00            1.33E+01         5.57E+01     11 ZN-65          CntI        3.28E-01          3.28E-01           3.28E-01         4.22E+01 11 ZRNB-95         Ind       -9.54E-01         -4.34E+00           6.82E+00,         3.65E+01                  0 ZRNB-95        Cntl      4.52E+00           4.52E+00           4.52E+00         2.58E+01                  0 Ind = Indicator Stations Cntl = Control Stations                                                                   Page 1 of 1
 
I TABLE B-1.11 I
2013 QUARTERLY SPECIAL INTEREST TLD-RESULTS Results in milli-Roentgen (mR) per Standard Quarter Quarterly I
Station ID 1st Quarter 2nd Quarter 58             21.4             18.6 3rd Quarter. 4th Quarter 21.7            20.4 Sum.
82.1 I
87              32.3             23.7               28.9            28.4             113.4 88 89 24.3 24.9 20.9 22.8 26.3 27.6 25.5 27.0 96.9 102.4 I
90              18.8              17.5              19.6             19.6               75.4 119B 119C 21.5 21.6 20.2 20.5 22.5 23.5 23.3 22.7 8725 88.3 I
120 (East)          21.3            21.0              23.3             23.7              89.3 121 122 64.4 33.4 44.9 32.3.
71.4 35.7 68.7 35.6 249.5 137.1                          I 123            105.7             103.9              110.9           111.1              431.6 124 125 126 126.0 92.4 94.4 121.3 91.2 90.8 130.9 96.3 97.6 120.5 93.0 94.0 498.7 373.0 376.8 I
127 128 129 73.2 114.9 93.1 67.9 115.4 88.0 73.9 118.7 92.1 73.4 122.4 93.6 288.5 471.4 366.8 I
136A            137.2            130.0              133.3          129.7             530.3
    .137A 138A 148.0 118.7 142.1 113.8 147.3 121.2 148.3 118.4 585.7 472.1 i
150 (Site 1)          18.1              17.7             18.6            19.5               73.9 151 (Site 4)          19.6              17.3             19.7-.           19.6              76.1 I
TABLE B-1.2 2013 QUARTERLY SPECIAL INTEREST TLD RESULTS-  


==SUMMARY==
==SUMMARY==
Results in milli-Roentgen (mR) per Standard Quarter Average Activity Activity Low Activity Number of High Samples.Location ISFSI Quarterly Ind SITE 1 & 4 Quarterly Ind Quarterly Control TLDs 109.9 18.8 20.5 67.9 17.3 18.9 148.3 19.7 21.7 40 8 4 Ind = Indicator Station Cntl = Control Station Stations 123 through 138A are locationed on the middle ISFSI fence.Stations 58 and 87 to 90 were established in 2009 to monitor exposure from remediation work at the DOE 618-11 burial site.Station 121 results high due to location being near transformer yard. Staion 122 results influenced by ISFSI.Quarterly Control TLD location is ST-9. See Table A-1.1 Page 1 of 1 Table B-2.1 GAMMA SPECTROMETRY RESULTS OF STORM DRAIN WATER STATION i01 Results in pCi/lite r, corrected for decay during collection period Location 101 collected i Nuclide- RQ -Actilty.
I Results in milli-Roentgen (mR) per Standard Quarter
Error.2/5/2013 MDA Location 101 collected rNu-cli 11e RQ Activity Error 2/28/2013 MDA -K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140 BI-214 Nuclide K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140 BI-214 Nuclide K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA 140 BI-214-1.35E+01
        . Location Average Activity Activity Low Activity High Number of Samples I
+-1.09E+00  
ISFSI Quarterly Ind           109.9              67.9            148.3                40                          I SITE 1 & 4 Quarterly Ind             18.8               17.3             19.7                 8 Quarterly Control TLDs              20.5              18.9            21.7               4 I
+3.13E-01 +-6.17E-01
Ind = Indicator Station Cntl = Control Station I
+7.84E-02 +-1.27E+00  
Stations 123 through 138A are locationed on the middle ISFSI fence.
+3.38E+00 +-7.11 E-02 +1.84E+00 +-1.75E-01  
Stations 58 and 87 to 90 were established in 2009 to monitor exposure from remediation work at the DOE 618-11 burial site.
+8.26E-01 +-6.32E-01
Station 121 results high due to location being near transformer yard. Staion 122 results influenced by ISFSI.               !
+2.92E+00 +3.35E+01 1.94E+01 1.75E+00 2.OOE+00 5.1OE+00 4.65E+01 4.41 E+00 3.17E+00 6.22E+00 1.60E+00 1.57E+00 5.28E+00 4.47E+00 4.58E+01 3.18E+01 2.83E+00 3.19E--00 8.37E+00 3.59E+00 6.71 E+00 5.20E+00 1.OOE+01 2.61 E+00 2.43E+00 8.55E+00 8.09E+00 4/2/2013 MDA 5.85E+01 4.10E+01 3.01 E+00 3.48E+00 1.02E+01 3.24E+00 7.18E+00 5.35E+00 9.58E+00 4.02E+00 2.1OE+00 7.51 E+00 8:86E+00 K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA1 40 BI-214 i Nuclide K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-1 34 CS-137 BALA140 BI-214-4.23E+01
Quarterly Control TLD location is ST-9. See Table A-1.1 I
+3.98E+00 +-1.33E-01  
Page 1 of 1 I
+O.OOE+00 +1.97E+00 +1.79E+00 +-3.71E-01
 
+-2.06E+00  
Table B-2.1 GAMMA SPECTROMETRY RESULTS OF STORM DRAIN WATER STATION i01 Results in pCi/lite r, corrected for decay during collection period Location 101 collected                 2/5/2013                                    Location 101 collected 2/28/2013 i Nuclide- RQ -Actilty.                       Error.           MDA                    rNu-cli RQ 11e Activity             Error   MDA -
+-2.22E+00  
K-40                 -1.35E+01 +          3.35E+01          4.58E+01              K-40                -4.23E+01  +  8.27E+01  5.74E+01 CR-51                -1.09E+00 +          1.94E+01          3.18E+01              CR-51                 3.98E+00  +  2.10E+01  3.41E+01 MN-54                   3.13E-01    +    1.75E+00          2.83E+00              MN-54                -1.33E-01  +  2.25E+00  3.68E+00 CO-58                -6.17E-01      +    2.OOE+00          3.19E--00            CO-58                 O.OOE+00  +   1.89E+00 3.11E+00 FE-59                  7.84E-02     +    5.1OE+00          8.37E+00              FE-59                1.97E+00   +   5.29E+00 8.22E+00 CO-60                -1.27E+00       +     4.65E+01         3.59E+00              CO-60                1.79E+00  +   2.22E+00 3.31 E+00 ZN-65                  3.38E+00      +     4.41 E+00         6.71 E+00             ZN-65                -3.71E-01  +   4.60E+00 7.50E+00 ZRNB-95              -7.11 E-02    +     3.17E+00         5.20E+00             ZRNB-95              -2.06E+00   +  4.44E+00 7.01 E+00 1-131                  1.84E+00     +     6.22E+00         1.OOE+01             1-131                -2.22E+00   +  6.30E+00 1.01E+01 CS-134                -1.75E-01     +     1.60E+00         2.61 E+00             CS-134                -1.52E-01  +   3.39E+00 5.57E+00 CS-137                  8.26E-01    +     1.57E+00         2.43E+00             CS-137                -5.32E-01  +  2.29E+00  3.70E+00 BALA140              -6.32E-01      +    5.28E+00         8.55E+00             BALA1 40               5.42E-01  +  4.64E+00  7.50E+00 BI-214               2.92E+00      +    4.47E+00          8.09E+00              BI-214                2.03E+00  +  4.67E+00  8.63E+00 Location 101 collected                4/2/2013                                    Location 101 col!ected 4/30/2013 Nuclide RQ Activity                        Error            MDA                i Nuclide    RQ      Activity        Error    MDA K-40                -3.01 E+01 + 6.OOE+01                  5.85E+01              K-40                -1.82E+01 + 4.12E+01      5.59E+01 CR-51                -1.50E+00 + 2.50E+01                    4.10E+01              CR-51                -9.22E+00   +   2.52E+01 4.06E+01 MN-54                  6.91 E-01 + 1.91E+00                3.01 E+00             MN-54                  5.22E-01  +   1.93E+00  3.09E+00 CO-58                  1.22E+00 + 2.24E+00                   3.48E+00             CO-58                -3.41E-02  +   1.70E+00 2.78E+00 FE-59                -9.63E-01 + 6.31 E+00                   1.02E+01            FE-59                -1.30E+00   +  5.93E+00  9.47E+00 CO-60                  2.05E-01 + 2.OOE+00                 3.24E+00             CO-60                -3.49E-01  +   1.51 E+00 2.39E+00 ZN-65                -6.64E-01 + 4.44E+00                   7.18E+00             ZN-65                  1.18E+00 4.22E+00  6.72E+00 ZRNB-95                1.14E+00 + 3.39E+00                  5.35E+00             ZRNB-95              2.80E+00  +   3.58E+00 5.38E+00 1-131                  4.05E+00 + 6.11E+00                  9.58E+00             1-131                  1.47E+00 +   5.07E+00  8.15E+00 CS-134                -8.36E-01 + 2.50E+00                   4.02E+00             CS-1 34              -8.91E-01  +   2.1IE+00 3.34E+00 CS-137                1.64E+00 + 1.50E+00                   2.1OE+00             CS-137                -6.05E-01  +  2.19E+00 3.51 E+00 BALA140              -1.12E+00 + 4.74E+00                   7.51 E+00            BALA140              -2.23E702  +   4.23E+00 6.95E+00 BI-214          + 1.34E+01 + 5.55E+00                       8:86E+00             BI-214          +   9.39E+00   +   5.13E+00  8.57E+00 Location 101 collected                6/3/2013                                    Location 101 collected  7/1/2013 Nuclide                                                      MDA                  Nuclide RQ Activity                  Error    MDA RQ        Activity              Error K-40                -9.32E+00       + 3.10E+01            5.32E+01              K-40                -9.87E+00 + 3.33E+01      5.52E+01 CR-51                  5.68E+00       + 2.02E+01            3.25E+01              CR-51                  1.32E+00 + 2.13E+01     3.48E+01 MN-54                  1.45E+00       + 2.04E+00             3.12E+00             MN-54                  7.25E-02 + 2.12E+00     3.47E+00 CO-58                  9.32E-02      + 1.63E+00             2.65E+00             CO-58                -2.21 E-02 + 2.33E+.00   3.83E+00 FE-59                -7.03E-01      + 7.03E+00             1.14E+01            FE-59                  1.34E+00 + 4.24E+00    6.57E+00 CO-60                -1.94E-01       + 2.05E.+00           3.33E+00              CO-60                0.OOE+00 + 2.33E+00      3.84E+00 ZN-65                  1.56E+00      + 4.15E+00             6.51 E+00             ZN-65                -1.76E+00 + 4.48E+00     7.05E+00 ZRNB-95                7.98E-02      + 3.93E+00             6.44E+00             ZRNB-95              -8.28E-01 + 3.22E+00     5.14E+00 1-131                  3.02E+00       + 6.51 E+00            1.04E+01             1-131                  1.04E-01 + 5.29E+00     8.67E+00 CS-134                -1.42E-01      + 2.50E+00             4.09E+00             CS-1 34                5.24E-02 + 2.15E+00     3.53E+00 CS-137                -4.84E-01       + 2.31 E+00           3.73E+00             CS-1 37                1.46E+00 + 2.28E+00     3.55E+00 BALA 140                1.64E-02      + 4.81 E+00            7.90E+00              BALA140              -2.99E-01 + 4.56E+00    7.43E+00 BI-214                3.91 E+00      + 5.26E+00            9.33E+00              BI-214               5.72E+00 + 5.OOE+00     8.75E+00 RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit.                     Page 1 of 2
+-1.52E-01  
 
+-5.32E-01  
I Table B-2.1 GAMMA SPECTROMETRY RESULTS OF STORM DRAIN WATER I
+5.42E-01 +2.03E+00 +8.27E+01 2.10E+01 2.25E+00 1.89E+00 5.29E+00 2.22E+00 4.60E+00 4.44E+00 6.30E+00 3.39E+00 2.29E+00 4.64E+00 4.67E+00 5.74E+01 3.41E+01 3.68E+00 3.11E+00 8.22E+00 3.31 E+00 7.50E+00 7.01 E+00 1.01E+01 5.57E+00 3.70E+00 7.50E+00 8.63E+00 4/30/2013 MDA Location 101 collected RQ Activity Error Location 101 col!ected RQ Activity Error-3.01 E+01 +-1.50E+00  
STATION 101 Results in pCilliter, corrected for decay during collection period I
+6.91 E-01 +1.22E+00 +-9.63E-01
Location 101 collected              7/31/2013                                    Location 101 collected  9/3/2013 SNuclide K-40 CR-51 RQ      Activity
+2.05E-01 +-6.64E-01
                        -1.96E+01 + 4.27E+01
+1.14E+00 +4.05E+00 +-8.36E-01
                        -7.14E+00 + 2.65E+01 Error            MDA 5.60E+01 4.29E+01 I Nuclide K-40 CR-51 RQ      Activity
+1.64E+00 +-1.12E+00  
                                                                                                          -7.61 E+00 1.71E+01
++ 1.34E+01 +6.OOE+01 2.50E+01 1.91E+00 2.24E+00 6.31 E+00 2.OOE+00 4.44E+00 3.39E+00 6.11E+00 2.50E+00 1.50E+00 4.74E+00 5.55E+00-1.82E+01
                                                                                                                      +
+-9.22E+00  
                                                                                                                      +
+5.22E-01 +-3.41E-02
Error 2.89E+01 2.44E+01 MDA 4.85E+01 3.84E+01 I
+-1.30E+00  
                        -1.09E-01 + 2.19E+00 MN-54 CO-58 FE-59
+-3.49E-01
                        -4.27E-02 + .1.62EE+00
+1.18E+00 +2.80E+00 +1.47E+00 +-8.91E-01
                        -3.70E-01 + 6.38E+00 3.59E+00 2.66E+06:'
+-6.05E-01
1.04E+01 MN-54 CO-58 FE-59
+-2.23E702
                                                                                                          -1.60E-03
+9.39E+00 +4.12E+01 2.52E+01 1.93E+00 1.70E+00 5.93E+00 1.51 E+00 4.22E+00 3.58E+00 5.07E+00 2.1IE+00 2.19E+00 4.23E+00 5.13E+00 5.59E+01 4.06E+01 3.09E+00 2.78E+00 9.47E+00 2.39E+00 6.72E+00 5.38E+00 8.15E+00 3.34E+00 3.51 E+00 6.95E+00 8.57E+00 7/1/2013 MDA+Location 101 collected RQ Activity Error-9.32E+00
                                                                                                          -6.89E-01 0.OOE+00
+5.68E+00 +1.45E+00 +9.32E-02 +-7.03E-01
                                                                                                                      +
+-1.94E-01  
                                                                                                                      +
+1.56E+00 +7.98E-02 +3.02E+00 +-1.42E-01
                                                                                                                      +
+-4.84E-01
2.12E+00 2.34E+00 2.98E+00 3.47E+00 3.74E+00 4.90E+00 I
+1.64E-02 +3.91 E+00 +3.10E+01 2.02E+01 2.04E+00 1.63E+00 7.03E+00 2.05E.+00 4.15E+00 3.93E+00 6.51 E+00 2.50E+00 2.31 E+00 4.81 E+00 5.26E+00 6/3/2013 MDA 5.32E+01 3.25E+01 3.12E+00 2.65E+00 1.14E+01 3.33E+00 6.51 E+00 6.44E+00 1.04E+01 4.09E+00 3.73E+00 7.90E+00 9.33E+00 Nuclide RQ K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-1 34 CS-1 37 BALA140 BI-214 Location 101 collected Activity Error-9.87E+00  
CO-60                  4.78E-02 + 1.95E+00                  3.20E+00            CO-60                  -2.82E-01  +  2.88E+00  3.34E+00 ZN-65 ZRNB-95 1-131 1.64E+00 + 3.95E+00
+1.32E+00 +7.25E-02 +-2.21 E-02 +1.34E+00 +0.OOE+00 +-1.76E+00
                        -7.56E-02 + 4.48E+00 8.80E-01 + 7.96E+00 6.15E+00 7.36E+00 1.30E+01 ZN-65 ZRNB-95 1-131 1.81 E-02
+-8.28E-01
                                                                                                          -1.87E+00
+1.04E-01 +5.24E-02 +1.46E+00 +-2.99E-01  
                                                                                                          -5.66E-01
+5.72E+00 +3.33E+01 2.13E+01 2.12E+00 2.33E+.00 4.24E+00 2.33E+00 4.48E+00 3.22E+00 5.29E+00 2.15E+00 2.28E+00 4.56E+00 5.OOE+00 5.52E+01 3.48E+01 3.47E+00 3.83E+00 6.57E+00 3.84E+00 7.05E+00 5.14E+00 8.67E+00 3.53E+00 3.55E+00 7.43E+00 8.75E+00 RQ = Results Qualifier.
                                                                                                                      +
If blank, result is less than detection limit. If "+", result is above detection limit.Page 1 of 2 Table B-2.1 GAMMA SPECTROMETRY RESULTS OF STORM DRAIN WATER STATION 101 Results in pCilliter, corrected for decay during collection period Location 101 collected SNuclide K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140 BI-214 RQ Activity-1.96E+01
                                                                                                                      +
+-7.14E+00  
                                                                                                                      +
+-1.09E-01
3.31 E+00 4.45E+00 4.58E+00 5.43E+00 7.03E+00 7.44E+00 I
+-4.27E-02
CS-134                -1.82E+00 + 2.57E+00                   4.04E+00             CS-134                -2.88E-02  +   2.02E+00   3.32E+00 CS-137 BALA140
+-3.70E-01  
                        -8.59E-01 + 2.53E+00
+4.78E-02 +1.64E+00 +-7.56E-02
                        -1.41E+00 + 6.69E+00 4.05E+00 1.07E+01 CS-1 37 BALA 40
+8.80E-01 +-1.82E+00  
                                                                                                          -3.47E-01
+-8.59E-01  
                                                                                                          -8.12E-01
+-1.41E+00  
                                                                                                                      +
+5.45E+00 +Error 4.27E+01 2.65E+01 2.19E+00.1.62EE+00 6.38E+00 1.95E+00 3.95E+00 4.48E+00 7.96E+00 2.57E+00 2.53E+00 6.69E+00 5.12E+00 Location 101 collected Nuclide RQ Activity Error 7/31/2013 MDA 5.60E+01 4.29E+01 3.59E+00 2.66E+06:'
                                                                                                                      +
1.04E+01 3.20E+00 6.15E+00 7.36E+00 1.30E+01 4.04E+00 4.05E+00 1.07E+01 8.97E+00 10/1/2013 MDA 5.31 E+01 3.79E+01 3.13E+00 2.98E+00 1.12E+01 3.50E+00 8.32E+00 7.80E+00 1.42E+01 3.64E+00 3.84E+00 1.01E+01 9.26E+00 12/1/2013 MDA Location 101 collected I Nuclide K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-1 37 BALA 40 BI-214 Nuclide K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-1 34 CS-1 37 BALA140 BI-214 RQ Activity-7.61 E+00 +1.71E+01 +-1.60E-03
2.OOE+00 4.98E+00 3.23E+00 7.97E+00 I
+-6.89E-01
BI-214                5.45E+00 + 5.12E+00                   8.97E+00             BI-214                5.88E-01  +  4.84E+00  9.04E+00 Location 101 collected              10/1/2013                                   Location 101 collected  11/1/2013 I
+0.OOE+00 +-2.82E-01
Nuclide      RQ      Activity              Error            MDA                   Nuclide RQ Activity                  Error    MDA K-40 CR-51
+1.81 E-02 +-1.87E+00  
                        -3.25E+01
+-5.66E-01
                        -1.12E-01
+-2.88E-02
                                        + 7.92E+01
+-3.47E-01
                                        + 2.31 E+01 5.31 E+01 3.79E+01 K-40 CR-51
+-8.12E-01
                                                                                                          -3.22E+01 +
+5.88E-01 +Error 2.89E+01 2.44E+01 2.12E+00 2.34E+00 2.98E+00 2.88E+00 3.31 E+00 4.45E+00 4.58E+00 2.02E+00 2.OOE+00 4.98E+00 4.84E+00 9/3/2013 MDA 4.85E+01 3.84E+01 3.47E+00 3.74E+00 4.90E+00 3.34E+00 5.43E+00 7.03E+00 7.44E+00 3.32E+00 3.23E+00 7.97E+00 9.04E+00 11/1/2013 MDA Location 101 collected RQ Activity Error K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140 BI-214-3.25E+01
                                                                                                          -3.63E+00 +
+-1.12E-01
6.33E+01 2.82E+01 5.84E+01 4.60E+01 I
+6.30E-01 +-3.31E-01
MN-54                   6.30E-01      + 1.97E+00              3.13E+00            MN-54                  2.65E-01 +    1.88E+00  3.04E+00 CO-58 FE-59 CO-60
+-4.19E-01
                        -3.31E-01
+-4.91E-01
                        -4.19E-01
+7.18E-02 +0.OOE+00 +-1.64E+00
                        -4.91E-01
+-7.66E-01
                                        + 1.85E+00
+-9.25E-01
                                        + 6.88E+00
+.-6.54E-01 +1.23E+00 +7.92E+01 2.31 E+01 1.97E+00 1.85E+00 6.88E+00 4.31 E+00 5.07E+00 4.74E+00 8.73E+00 2.27E+00 2.41 E+00 6.25E+00 5.04E+00-3.22E+01  
                                        + 4.31 E+00 2.98E+00 1.12E+01 3.50E+00 CO-58 FE-59 CO-60
+-3.63E+00  
                                                                                                          -2.62E-01 +
+2.65E-01 +-2.62E-01
3.64E+00 +
+3.64E+00 +-3.08E-01  
                                                                                                          -3.08E-01 +
+-1.98E+00  
2.15E+00 6.34E+00 2.13E+00 3.48E+00 9.62E+00 3.45E+00 I
+-1.13E-01
ZN-65                  7.18E-02      + 5.07E+00              8.32E+00            ZN-65                -1.98E+00 +     5.25E+00  8.32E+00 ZRNB-95 1-131 CS-134 0.OOE+00
+2.09E+00 +-1.27E-02
                      -1.64E+00
+-5.89E-01  
                        -7.66E-01
+4.21 E-02 +2.05E+00 +6.33E+01 2.82E+01 1.88E+00 2.15E+00 6.34E+00 2.13E+00 5.25E+00 4.12E+00 9.48E+00 2.53E+00 2.63E+00 6.39E+00 5.36E+00 5.84E+01 4.60E+01 3.04E+00 3.48E+00 9.62E+00 3.45E+00 8.32E+00 6.75E+00 1.54E+01 4.16E+00 4.25E+00 1.05E+01 9.66E+00 12/31/2013 I I I I I I I I I I I I I I I I I I I Location 101 collected Activity Error Location 101 collected Nuclide RQ Nuclide RQ Activity K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140 BI-214-4.19E+01
                                        + 4.74E+00
+1.18E+00 +-5.O0E-01
                                        + 8.73E+00
+2.64E-01 +-2.26E+00  
                                        + 2.27E+00 7.80E+00 1.42E+01 3.64E+00 ZRNB-95 1-131 CS-1 34
+-3.51E-01
                                                                                                          -1.13E-01 +
+-8.72E-01  
2.09E+00 +
+-1.40E+00  
                                                                                                          -1.27E-02 +
+-1.79E-01
4.12E+00 9.48E+00 2.53E+00 6.75E+00 1.54E+01 4.16E+00 I
+-1.46E+00  
CS-137 BALA140 BI-214
+8.14E-01 +-1.50E+00  
                        -9.25E-01
+7.62E+00 +8.92E+01 2.96E+01 1.86E+00 2.21 E+00 6.54E+00 2.21 E+00 4.39E+00 4.47E+00 6.66E+00 2.35E+00 2.05E+00 4.81 E+00 5.17E+00 6.OOE+01 4.86E+01 2.97E+00 3.59E+00 1.03E+01 3.57E+00 7.07E+00 7.14E+00 1.09E+01 3.70E+00 3.25E+00 7.53E+00 8.82E+00 K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140 BI-214-2.42E+01
                      .- 6.54E-01 1.23E+00
+1.58E-01 +-3.82E-01
                                        + 2.41 E+00
+3.54E-01 +9.11E-01 +-4.80E-01
                                        + 6.25E+00
+2.18E-02 +-1.39E+00
                                        + 5.04E+00 3.84E+00 1.01E+01 9.26E+00 CS-1 37 BALA140 BI-214
+-2.73E+00
                                                                                                          -5.89E-01 +
+-2.39E-02
4.21 E-02 +
+3.72E-01 +-6.59E-02
2.05E+00 +
+5.34E+00 +6 2 1 4i Error MDA 3.30E+01 5.61 E+01!.50E+01 4.12E+01.00E+00 3.22E+00'.03E+00 3.27E+00 k.41E+00 1.03E+01 ,.54E+00 3.71E+00 ,.08E+00 6.71E+00*.59E+00 7.33E+00 l.62E+00 1.55E+01.22E+00 3.65E+00.80E+00 2.89E+00*.97E+00 8.15E+00.15E+00 9.02E+00 RQ = Results Qualifier.
2.63E+00 6.39E+00 5.36E+00 4.25E+00 1.05E+01 9.66E+00 I
If blank, result is less than detection limit, If "+', result is above detection limit.Page 2 of 2 TABLE B-2.2 GAMMA SPECTROMETRY RESULTS OF STORM DRAIN WATER -
Nuclide    RQ Location 101 collected Activity              Error 12/1/2013 MDA                  Nuclide RQ Location 101 collected Activity          Error 12/31/2013 MDA I
K-40 CR-51 MN-54
                      -4.19E+01 1.18E+00
                        -5.O0E-01
                                        +
                                        +
                                        +
8.92E+01 2.96E+01 1.86E+00 6.OOE+01 4.86E+01 2.97E+00 K-40 CR-51 MN-54
                                                                                                          -2.42E+01 + 3.30E+01
                                                                                                          -3.82E-01 +
6 1.58E-01 + !.50E+01
                                                                                                                            .00E+00 5.61 E+01 4.12E+01 3.22E+00 I
CO-58                  2.64E-01     +     2.21 E+00        3.59E+00             CO-58                  3.54E-01 + '.03E+00     3.27E+00 FE-59 CO-60 ZN-65
                      -2.26E+00
                        -3.51E-01
                        -8.72E-01
                                        +
                                        +
                                        +
6.54E+00 2.21 E+00 4.39E+00 1.03E+01 3.57E+00 7.07E+00 FE-59 CO-60 ZN-65 9.11E-01 + k.41E+00
                                                                                                          -4.80E-01 + ,.54E+00 2.18E-02 + 2,.08E+00 1.03E+01 3.71E+00 6.71E+00 I
ZRNB-95              -1.40E+00       +    4.47E+00         7.14E+00           ZRNB-95              -1.39E+00 + 1*.59E+00     7.33E+00 1-131 CS-134 CS-137
                        -1.79E-01
                      -1.46E+00 8.14E-01
                                        +
                                        +
                                        +
6.66E+00 2.35E+00 1.09E+01 3.70E+00 1-131 CS-134
                                                                                                          -2.73E+00 + 4i
                                                                                                          -2.39E-02 +
l.62E+00
                                                                                                                            .22E+00 1.55E+01 3.65E+00 I
2.05E+00          3.25E+00           CS-137                  3.72E-01 +     .80E+00 2.89E+00 BALA140 BI-214
                      -1.50E+00 7.62E+00
                                        +
                                        +
4.81 E+00 5.17E+00 7.53E+00 8.82E+00 BALA140 BI-214
                                                                                                          -6.59E-02 + *.97E+00 5.34E+00 +      .15E+00 8.15E+00 9.02E+00   I I
RQ = Results Qualifier. If blank, result is less than detection limit, If "+', result is above detection limit.                     Page 2 of 2 I
 
TABLE B-2.2 GAMMA SPECTROMETRY RESULTS OF STORM DRAIN WATER -  


==SUMMARY==
==SUMMARY==
STATION 101 Results in pCi/liter, corrected for decay during collection period Number of Average Activity Activity Average Number of Positive Nuclide Activity Low High, MDA Samples IDs K-40 -2.35E+01  
 
-4.23E+01  
STATION 101 Results in pCi/liter, corrected for decay during collection period Number of Average         Activity         Activity       Average       Number of Positive Nuclide       Activity           Low             High,         MDA           Samples     IDs K-40         -2.35E+01       -4.23E+01 -7.61E+00               5.48E+01..         12       0 CR-51         5.65E-01     -9.22E+00         1.71E+01*,     3.92E+01           12       0 MN-54         2.35E-01       -5.00E-01       1.45E+00       3.22E+00           12       0 CO-58         -5.83E-03       -6.89E-01       1.22E+00       3.23E+00           12       0 FE-59         1.60E-01     -2.26E+00         3.64E+00       9.25E+00           12       0 CO-60         -1.40E-01     -1.27E+00         1.79E+00       3.37E+00             12       0 ZN-65         1.86E-01     -1.98E+00         3.38E+00       6.97E+00             12       0 ZRNB-95       -3.09E-01     -2.06E+00         2.80E+00       6.54E+00             12       0 1-131         5.11E-01     -2.73E+00         4.05E+00       1.11E+01           12       0 CS-134       -5.21E-01     -1.82E+00           5.24E-02     3.81E+00             12       0 CS-1 37       6.38E-02       -9.25E-01       1.64E+00       3.38E+00             12       0 BALA140       -4.92E-01     -1.50E+00           5.42E-01     8.40E+00             12       0 BI-214       4.97E+00         5.88E-01       1.34E+01       8.92E+00             12       2 Page 1 of 1
-7.61E+00 5.48E+01..
 
12 0 CR-51 5.65E-01 -9.22E+00 1.71E+01*, 3.92E+01 12 0 MN-54 2.35E-01 -5.00E-01 1.45E+00 3.22E+00 12 0 CO-58 -5.83E-03  
I TABLE B-3.1. -, I- -
-6.89E-01 1.22E+00 3.23E+00 12 0 FE-59 1.60E-01 -2.26E+00 3.64E+00 9.25E+00 12 0 CO-60 -1.40E-01  
GROSS BETA IN STORM D.RIN. WATER.:
-1.27E+00 1.79E+00 3.37E+00 12 0 ZN-65 1.86E-01 -1.98E+00 3.38E+00 6.97E+00 12 0 ZRNB-95 -3.09E-01  
Results in pCi per liter I
-2.06E+00 2.80E+00 6.54E+00 12 0 1-131 5.11E-01 -2.73E+00 4.05E+00 1.11E+01 12 0 CS-134 -5.21E-01  
Location ST-1i01 Collection Period 01/03/13:.       02/05/13 RQ          Activity ,.,
-1.82E+00 5.24E-02 3.81E+00 12 0 CS-1 37 6.38E-02 -9.25E-01 1.64E+00 3.38E+00 12 0 BALA140 -4.92E-01  
                                                                                      .6.70E-01 Error
-1.50E+00 5.42E-01 8.40E+00 12 0 BI-214 4.97E+00 5.88E-01 1.34E+01 8.92E+00 12 2 Page 1 of 1 TABLE B-3.1. -, I- -GROSS BETA IN STORM D.RIN. WATER.: Results in pCi per liter Location Collection Period RQ Activity ,., Error MDA ST-1i01 01/03/13:.
                                                                                                    . 7.92E-01 MDA 2.63E+00 I
02/05/13 02/28/13 04/02/13 04/30/13 06/03/1.3 07/01/13 07/31/13 09/03/13 10/01/13 11/01/13 12/01/13 02/05/13 02/28/13 04/02/13 04/30/13 06/03/13 07/01/13 01/31/13 09/03Mi3 10/01/13, 11/01/13 12/01/13 12/31/13.6.70E-01
02/05/13         02/28/13                     7.88E      *8.82E-01   2.95E+00 02/28/13 04/02/13 04/30/13 04/02/13 04/30/13 06/03/13
.7.88E-01 -.1.12S +0 +1.75E+00 +..7.20E-01 +1.99E+00 '+-3.07E-01  
                                                                                      .1.12S +0 +
-3.23E-01 +1.81E+00 +1.36E+00 +8.62E-01 +1.83E+00 +7.92E-01*8.82E-01 8.01 E-01 8.46E-01 7.88E-01 8.29E-01'7.29E-01 7.58E-01 7.43E-01 7.52E-01 7.10E-01 7.46E-01 2.63E+00 2.95E+00 2.55E+00 2.70E+00 2.65E+00 2.44E+00 2.49E+00 2.67E+00 2.29E+00 2240E+00 2.36E+00 2.30E+00 I I I I I I TABLE B-3.2 GROSS BETA IN STORM DRAIN WATER -
1.75E+00 +
                                                                                    ..7.20E-01 +
8.01 E-01 8.46E-01 7.88E-01 2.55E+00 2.70E+00 2.65E+00 I
06/03/1.3        07/01/13                    1.99E+00 '+       8.29E-01   2.44E+00 07/01/13 07/31/13 01/31/13 09/03Mi3
                                                                                    -3.07E '7.29E-01 3.23E-01 +      7.58E-01 2.49E+00 2.67E+00 I
09/03/13          10/01/13,                  1.81E+00 +        7.43E-01  2.29E+00 10/01/13 11/01/13 12/01/13 11/01/13 12/01/13 12/31/13 1.36E+00 +
8.62E-01 +
1.83E+00 +
7.52E-01 7.10E-01 7.46E-01 2240E+00 2.36E+00 2.30E+00 I
TABLE B-3.2 GROSS BETA IN STORM DRAIN WATER -  


==SUMMARY==
==SUMMARY==
Results in pCi: Per liter.Average, .Activity Activity Number of Number of Activity Low High Samp!es Positive IDs 1.09E+00 -3.07E-01 1,99E+00 12 .0-TABLE B-4.1 TRITIUM IN STORM DRAIN WATER Resutts in pC- per liter .Location Collection Period RQ Activity Error ST-101 01/03/13 -02/05/13 + 4.95E+03 + 1.89E+02 02/05/13.-
 
02/28/13 .+ T. i11E+03 + 1.24E+02 02/28/13.  
Results in pCi: Per liter.
-04?02/13 + 1.30E+03 + 1.26E+02 04/02/13 -04/30/13 + .3.42E+02  
Average, .
+ 1.04E+02 04/30/13.-
Activity Activity Low Activity High Number of Samp!es Number of Positive IDs I
06/03/13 1.78E+02 +. 9.57E+01 06/03/..13  
1.09E+00           -3.07E-01           1,99E+00                       12       .         0-                         I TABLE B-4.1 TRITIUM IN STORM DRAIN WATER I
-07101/13.  
Resutts in pC- per liter .
+ 3.44E+02 + 9.36E+01 07/01/13 -07/31113 -1.28E+02 + 9.97E+01 07/31/13 -09/03/13:-
Location ST-101 Collection Period 01/03/13 - 02/05/13 RQ
2.43E+02 + 9.62E+01 09/03/13 -10/01/13 + 4.31E+02 + 1.04E+02 10/01/13 -11/01/13 ..63E+02 + 9.85E+01 11/01/13 -12/01/13 + 9.53E+02 + 1.21 E+02 12/01/13 -12/31/13 + 1.69E+03 + 1.39E+02 TABLE B-4.2 TRITIUM IN STORM DRAIN WATER -
                                                                        +
Activity 4.95E+03     +
Error 1.89E+02 I
02/05/13.-     02/28/13 02/28/13. - 04?02/13 04/02/13 - 04/30/13
                                                                        .+
                                                                        +
                                                                        +
i11E+03 T.
1.30E+03
                                                                                    .3.42E+02
                                                                                                  +
                                                                                                  +
                                                                                                  +
1.24E+02 1.26E+02 1.04E+02 I
04/30/13.-     06/03/13                     1.78E+02   +. 9.57E+01 06/03/..13 - 07101/13.
07/01/13 - 07/31113 -
07/31/13 - 09/03/13:-
                                                                        +          3.44E+02 1.28E+02 2.43E+02
                                                                                                  +
                                                                                                  +
                                                                                                  +
9.36E+01 9.97E+01 9.62E+01 I
09/03/13 - 10/01/13                         4.31E+02     +     1.04E+02 I
                                                                        +
10/01/13 - 11/01/13                       . .63E+02     +   9.85E+01 11/01/13 - 12/01/13             +           9.53E+02     +     1.21 E+02 12/01/13 - 12/31/13             +           1.69E+03     +     1.39E+02 TABLE B-4.2 I
TRITIUM IN STORM DRAIN WATER -  


==SUMMARY==
==SUMMARY==
Results in pCi per liter Average Activity Activity Number of Number of Activity Low.' High Samples Positive IDs I I I I I I I I I I I 9.87E+02 1.28E+02 "- 4.95E+03' .12 8 RQ = Results Qualifier.
 
If blank, result is less than detection limit. If "+", result is above detection limit.Page 1 of 1 1 TABLE B-5.1 GROSS ALPHA IN-SANITARY:WASTE TREATMENT WATER Results in pCi pe& liter ST 102B Collection Period RO ' Activity Error MDA IRO Activity Error MDA__________________
Average              Activity Results in pCi per liter Activity               Number of             Number of I
L L -- -- --01/03/13 02/05/13 02/28/13 04/02/13 04/30/13 06/03/13 07/01/13 07/31/13 09/03/13 10/01/13 11/01/13 12/01/13 02/05/13 02/28/13 04/02/13 04/30/13 06/03/13 07/01/13 07/31/13 09/03/13 10/01/13 11/01/13 12/01/13 12/31/13-2.95E-01 7.35E-01-1.56E+00-1.56E+00 1.04E+00 1.53E+00 4.47E-01-1.09E+00-1.77E-1 6 2.28E+00 3.1OE+00-1.43E-01+.++++++++++8.16E-01"8.49E-01 1.12E+00 1.46E+00 1.04E+00 1.1.8E+00 1 .24E+00 1.13E+00 7.76E-01 1.56E+00 1.80E+00 1.52E+00 3.39E+00 3.31 E+00 3.88E+00 5.21 E+00 3.80E+00 4.1OE+00 5.14E+00 4.19E+00 3.83E+00 5.24E+00 5.87E+00 6.24E+00-3.41 E-01 1.42E+00-9.29E-01-2.21 E+00 3.71 E+00 0.OOE+00-8.30E-01-1.06E+00 1.19E+00 5.63E-01 3.34E-01-2.95E+00++++++++++++9.45E-01 9.65E-01 1.99E+00 2.08E+00 1.22E+00 1.94E+00 8.61 E-01 1.57E+00 1.OOE+00 1.56E+00 1.80E+00 2.32E+00 3.93E+00 3.21 E+00 7.78E+00 7.40E+00 3.83E+00 8.20E+00 3.18E+00 6.11 E+00 3.58E+00 6.48E+00 7.26E+00 8.02E+00 TABLE B-5.2 GROSS ALPHA IN SANITARY WASTE TREATMENT WATER -
Activity               Low.'           High                   Samples             Positive IDs 9.87E+02           1.28E+02 "-       4.95E+03                 . '   12                   8 I
I RQ = Results Qualifier. Ifblank, result is less than detection limit. If "+", result is above detection limit.             Page 1 of 1 1
 
TABLE B-5.1 GROSS ALPHA IN-SANITARY:WASTE TREATMENT WATER Results in pCi pe&liter
                                              .,ST*102A.                                              ST 102B Collection Period   L RO ' Activity             Error         MDA IRO L   --
Activity Error      MDA 01/03/13         02/05/13         -2.95E-01 + 8.16E-01           3.39E+00            -3.41 E-01 +        9.45E-01   3.93E+00 02/05/13         02/28/13         7.35E-01 .+ "8.49E-01          3.31 E+00             1.42E+00 +         9.65E-01   3.21 E+00 02/28/13          04/02/13        -1.56E+00          1.12E+00     3.88E+00             -9.29E-01 +       1.99E+00    7.78E+00 04/02/13          04/30/13      -1.56E+00 + 1.46E+00             5.21 E+00           -2.21 E+00 +       2.08E+00   7.40E+00 04/30/13          06/03/13          1.04E+00 + 1.04E+00           3.80E+00             3.71 E+00 +        1.22E+00    3.83E+00 06/03/13          07/01/13          1.53E+00 + 1.1.8E+00           4.1OE+00             0.OOE+00 +        1.94E+00   8.20E+00 07/01/13          07/31/13          4.47E-01 + 1.24E+00           5.14E+00             -8.30E-01 +         8.61 E-01 3.18E+00 07/31/13          09/03/13        -1.09E+00 + 1.13E+00             4.19E+00           -1.06E+00 +        1.57E+00    6.11 E+00 09/03/13          10/01/13        -1.77E-1 6 + 7.76E-01           3.83E+00             1.19E+00 +       1.OOE+00    3.58E+00 10/01/13          11/01/13        2.28E+00 + 1.56E+00             5.24E+00             5.63E-01 +        1.56E+00   6.48E+00 11/01/13          12/01/13        3.1OE+00 + 1.80E+00             5.87E+00             3.34E-01 +       1.80E+00   7.26E+00 12/01/13          12/31/13        -1.43E-01 + 1.52E+00           6.24E+00           -2.95E+00 +         2.32E+00   8.02E+00 TABLE B-5.2 GROSS ALPHA IN SANITARY WASTE TREATMENT WATER -  


==SUMMARY==
==SUMMARY==
Results in pCi per liter Average Activity Activity Activity Low High Number of Samples Number of.Positive.IDs Location ST 102A ST 102B 3.74E-01 -1.56E+00 3.1OE+00-9.18E-02  
 
-2.95E+00 3.71E+00 12 12 0 0..TABLE B-6.1 GROSS BETA IN SANITARY WASTE TREATMENT WATER Results in pCi per liter ST 102A ST 102B Collection Period RO Activity Error MDA RQ Activity Error MDA 01/03/13 02/05/13 02/28/13 04/02/13 04/30/13 06/03/13 07/01/13 07/31/13 09/03/13 10/01/13 11/01/13 12/01/13 02/05/13 02/28/13 04/02/13 04/30/13 06/03/13 07/01/13 07/31/13 09/03/13 10/01/13 11/01/13 12/01/13 12/31/13++++++++++++4.95E+00 6.78E+00 3.64E+00 5.83E+00 7.50E+00 6.05E+00 1.40E+01 1.41 E+01 1.57E+01 1.63E+01 2.17E+01 2.67E+01++++++++++++9.97E-01 1.15E+00 9.18E-01 1.08E+00 1.13E+00 1.18E+00 1.56E+00 1.38E+00 1.39E+00 1.44E+00 1.60E+00 1.74E+00 2.68E+00 2.99E-+00 2.59E+00 2.82E+00 2.75E+00 3.03E+00 3.26E+00 2.81 E+00 2.45E+00 2.59E+00 2.53E+00 2.48E+00++++++++++++1.89E+01 1.78E+01 2.23E+01 2.19E+01 2.81 E+01 1.96E+01'1.46E+01 1.36E+01 1.81 E+01 1.95E+01 1.97E+01 2.19E+01++++++++++++1.52E+00 1.54E+00 1.68E+00 1.68E+00 1.93E+00 1.79E+00 1.41E+00 1.41E+00 1.47E+00 1.57E+00 1.56E+00 1.63E+00 2.74E+00 2.98E+00 2.85E+00 2.95E+00 3.16E+00 3.33E+00 2.75E+00 2.94E+00 2.43E+00 2.66E+00 2.60E+00 2.56E+00 TABLE B-6.2 GROSS BETA IN SANITARY WASTE TREATMENT WATER -
Results in pCi per liter Number          Number of Average           Activity     Activity                   of          .Positive.
Location          Activity           Low           High             Samples               IDs ST 102A             3.74E-01       -1.56E+00 3.1OE+00                       12              0 ST 102B            -9.18E-02       -2.95E+00 3.71E+00                       12               0
                                                  .. TABLE B-6.1 GROSS BETA IN SANITARY WASTE TREATMENT WATER Results in pCi per liter ST 102A                                               ST 102B Collection     Period     RO     Activity           Error         MDA       RQ Activity                 Error       MDA 01/03/13         02/05/13   +    4.95E+00 + 9.97E-01             2.68E+00 +            1.89E+01 +        1.52E+00  2.74E+00 02/05/13         02/28/13   +     6.78E+00 + 1.15E+00             2.99E-+00 +           1.78E+01 +         1.54E+00  2.98E+00 02/28/13          04/02/13  +     3.64E+00 + 9.18E-01             2.59E+00 + 2.23E+01 +                    1.68E+00   2.85E+00 04/02/13          04/30/13  +    5.83E+00 + 1.08E+00             2.82E+00 + 2.19E+01 +                   1.68E+00   2.95E+00 04/30/13          06/03/13  +    7.50E+00 + 1.13E+00             2.75E+00 + 2.81 E+01 +                   1.93E+00   3.16E+00 06/03/13          07/01/13  +     6.05E+00 + 1.18E+00             3.03E+00 +           1.96E+01' +       1.79E+00  3.33E+00 07/01/13          07/31/13  +     1.40E+01 + 1.56E+00            3.26E+00 +           1.46E+01 +        1.41E+00  2.75E+00 07/31/13          09/03/13  +     1.41 E+01 + 1.38E+00          2.81 E+00 +          1.36E+01 +        1.41E+00  2.94E+00 09/03/13          10/01/13  +     1.57E+01 + 1.39E+00           2.45E+00 +            1.81 E+01 +       1.47E+00   2.43E+00 10/01/13          11/01/13  +    1.63E+01 + 1.44E+00             2.59E+00 +            1.95E+01 +         1.57E+00   2.66E+00 11/01/13          12/01/13  +     2.17E+01 + 1.60E+00             2.53E+00 +            1.97E+01 +         1.56E+00   2.60E+00 12/01/13          12/31/13  +    2.67E+01 + 1.74E+00             2.48E+00 + 2.19E+01 +                   1.63E+00   2.56E+00 TABLE B-6.2 GROSS BETA IN SANITARY WASTE TREATMENT WATER -  


==SUMMARY==
==SUMMARY==
Results in pCi per liter Average Activity Activity Activity Low High Number Number of of Positive Samples IDs Location ST 102A ST 102B 1.19E+01 3.64E+00 2.67E+01 1.97E+01 1.36E+01 2.81E+01 12 12 12 12 RQ = Results Qualifier.
 
If blank, result is less than detection limit: If "+", result is above detection limit.Page 1 of 1 Table 8-7.1 GAMMA SPECTROMETRY.
Results in pCi per liter Number          Number of Average            Activity    Activity                  of          Positive Location          Activity            Low          High              Samples              IDs ST 102A            1.19E+01          3.64E+00 2.67E+01                        12              12 ST 102B            1.97E+01          1.36E+01 2.81E+01                        12              12 RQ = Results Qualifier. If blank, result is less than detection limit: If"+", result is above detection limit.          Page 1 of 1
RESULTS OF SANITARY WASTE TREATMENT WATER STATION 102A Results in pCi/liter, corrected for decay during collection period Nuciide K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140 BI-214 Nuclide
 
I Table 8-7.1 GAMMA SPECTROMETRY. RESULTS OF SANITARY WASTE TREATMENT WATER I
STATION 102A Results in pCi/liter, corrected for decay during collection period I
Location 102a collected                2/5/2013                                  Location 102a collected 2/28/2013 MDA Nuciide RQ Activity K-40 CR-51 1.34E+01 + 3.05E+01
 


==SUMMARY==
==SUMMARY==
Results in pCi per liter, corrected for decay during collection period Location 102A.Nuclide K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-1 34 CS-1 37 BALA140 BI-214 Average Activity 4.74E+00 5.24E-01-8.34E-02-9.47E-02 6.02E-01 3.39E-02-1.60E+00 6.43E-01 8.95E-01-1.53E+00 1.73E-01 9.14E-01 6.75E+00-1.59E+01-3.23E+00:.1.87E.-01 1.42E-01 4.95E-01 4.12E-01-4.14E-02-8.28E-01 4.73E+01-1.36E+00-4.14E-01-6.60E-02 7.61 E+00 Activity Activity Low High-3.OOE+01 6.22E+01-1.27E+01 1.59E+01-1.24E+00 8.45E-01-1.27E+00 1.81 E+00-4.92E+00 3.23E+00-2.55E+00 2.17E+00-5.77E+00 1.33E+00-3.64E+00 3.13E+00-8.35E+00 9.83E+00-4.77E+00 2.35E-01-1.40E+00 2.52E+00-2.31 E+00 5.07E+00 1.42E+00 1.58E+01 Average MDA 6.28E+01 5.59E+01 4.27E+00 4.62E+00 1.13E+01 4.49E+00 1.05E+01 9.20E+00 1.59E+01 4.88E+00 4.62E+00 9.77E+00 1.26E+01 6.76E+01 6.24E+01 4.71 E+00 5.11E+00 1.18E+01 4.18E+00 1.03E+01 9.19E+00 2.02E+01 6.16E+00 5.02E+00 1.10E+01 1.34E+01 Number of Samples 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 Number of Positive IDs 1 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 0 0 1 0 0 0 1 U I I I I I I I I I I I I I I I I I I 102B K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-1 34 CS-1 37 BALA140 BI-214-3.48E+01-1.88E+01-1 .80E+00-1.05E+00-3.25E+00-1.47E+00-5.21 E+00-3.47E+00-2.55E+00-4.05E+00-1.91 E+00-2.27E+00 1.68E+00 1.03E+01 1.14E+01.3.78E+00 2.02E+00 4.78E+00 1.60E+00 5.05E+00 2.42E+00 5.31 E+02 1.53E+00 2.52E+00 3.36E+00 3.18E+01 Page 1 of 1 TABLE B-8.1 TRITIUM IN SANITARY WASTE TREATMENT WATER Resultsin O~ijper liter, MDA for all samples is 300 pCi/I Location Description Collection Period RQ Activity Error 102A FFTF-Effluent 01/03/13&#xfd;02/05/13 02/28/13 04/02/13 04/30/13 06/03/13 07/01/13 07/31/13 09/03/13 10/01/13 11/01/13 12/01/13-02/05/13-02/28/13-04/02/13-04/30/13-06/03/13-07/01/13-07/31/13-09/03/13-10/01/13-11/01/13-12/01/13 12/31/13+++++++++++1.61 E+03 1.78E+03 1.64E+03 1.62E+03 1.56E+03 8.70E+02 9.48E+02 1.38E+03 1.37E+03 1.45E+03 1.59E+03 1.43E+03++-++..I-++I+-++++-+-1.29E+02 1.38E+02 1.34E+02 1.34E+02 1.32E+02 1.08E+02 1.21 E+02 1.26E+02 1 .27E+02 1.31E+02 1.35E+02 1.33E+02 9.78E+01 1.03E+02 1.09E+02 1.04E+02 9.90E+01 9.18E+01 1.01E+02 9.40E+01 9.60E+01 9.64E+01 1.01E+02 1.02E+02 102B Monthly Headworks 01/03/13 02/05/13 02/28/13 04/02/13 04/30/13 06/03/13 07/01/13 07/31/13 09/03/13 10/01/13 11/01/13 12/01/13 02/05/13 02/28/13 04/02/13 04/30/13 06/03/13 07/01/13 07/31/13 09/03/13 10/01/13 11/01/13 12/01/13 12/31/13+ 4.42E+02+ 3.58E+02+ 5.16E+02+ 3.58E+02 2.84E+02+ 3.13E+02 1.52E+02 1.48E+02 2.03E+02 1.60E+02 2.18E+02 1.82E+02 TABLE B-8.2 TRITIUM IN SANITARY WASTE TREATMENT WATER -
 
I Results in pCi per liter, corrected for decay during collection period Average          Activity          Activity        Average        Number of Number of I
Location .Nuclide     Activity            Low              High            MDA          Samples  Positive IDs 102A      K-40         4.74E+00        -3.OOE+01          6.22E+01        6.28E+01          12        1          I CR-51         5.24E-01      -1.27E+01          1.59E+01        5.59E+01          12        0 MN-54 CO-58
                      -8.34E-02
                      -9.47E-02
                                        -1.24E+00
                                        -1.27E+00 8.45E-01       4.27E+00           12        0          I 1.81 E+00        4.62E+00           12        0 FE-59 CO-60 6.02E-01 3.39E-02
                                        -4.92E+00
                                        -2.55E+00 3.23E+00 2.17E+00 1.13E+01 4.49E+00 12 12 0
0 I
ZN-65 ZRNB-95
                      -1.60E+00 6.43E-01
                                        -5.77E+00
                                        -3.64E+00 1.33E+00 3.13E+00 1.05E+01 9.20E+00 12 12 0
0 I
1-131 CS-1 34 8.95E-01
                      -1.53E+00
                                        -8.35E+00
                                        -4.77E+00 9.83E+00 2.35E-01 1.59E+01 4.88E+00 12 12 0
0 I
CS-1 37 BALA140 1.73E-01 9.14E-01
                                        -1.40E+00
                                        -2.31 E+00 2.52E+00 5.07E+00 4.62E+00 9.77E+00 12 12 0
0 I
BI-214      6.75E+00         1.42E+00           1.58E+01         1.26E+01          12        2 I
102B      K-40        -1.59E+01         -3.48E+01          1.03E+01         6.76E+01          12        0          I CR-51      -3.23E+00         -1.88E+01          1.14E+01         6.24E+01           12        0 MN-54        :.1.87E.-01      -1.80E+00         .3.78E+00       4.71 E+00           12        0          I CO-58          1.42E-01      -1.05E+00           2.02E+00        5.11E+00           12        0 FE-59          4.95E-01        -3.25E+00           4.78E+00        1.18E+01           12       0           I CO-60          4.12E-01        -1.47E+00          1.60E+00        4.18E+00            12      0 ZN-65 ZRNB-95
                      -4.14E-02
                      -8.28E-01
                                        -5.21 E+00
                                        -3.47E+00 5.05E+00 2.42E+00 1.03E+01 9.19E+00 12 12 0
0 I
1-131 CS-1 34 4.73E+01
                      -1.36E+00
                                        -2.55E+00
                                        -4.05E+00 5.31 E+02 1.53E+00 2.02E+01 6.16E+00 12 12      0 1
I CS-1 37 BALA140
                      -4.14E-01
                      -6.60E-02
                                        -1.91 E+00
                                        -2.27E+00 2.52E+00 3.36E+00 5.02E+00 1.10E+01 12 12 0
0 I
BI-214        7.61 E+00        1.68E+00           3.18E+01        1.34E+01           12        1 I
I Page 1 of 1 I
 
TABLE B-8.1 TRITIUM IN SANITARY WASTE TREATMENT WATER Resultsin O~ijper liter, MDA for all samples is 300 pCi/I Location           Description               Collection Period                   RQ       Activity           Error 102A               FFTF-Effluent       01/03/13&#xfd;     -    02/05/13                     1.61 E+03    +    1.29E+02
                                                                -    02/28/13             +                    +-
02/05/13                                       1.78E+03           1.38E+02
                                                                                          +                    +
02/28/13     -   04/02/13                     1.64E+03          1.34E+02
                                                                -   04/30/13             +
04/02/13                                       1.62E+03          1.34E+02
                                                                -   06/03/13             +
04/30/13                                       1.56E+03           1.32E+02
                                                                -    07/01/13            +                         1.08E+02 06/03/13                                        8.70E+02
                                                                -    07/31/13            +
07/01/13                                        9.48E+02     +   1.21 E+02
                                                                -    09/03/13            +                         1.26E+02 07/31/13                                        1.38E+03     ..I 10/01/13            +
09/03/13      -                                 1.37E+03      -+   1.27E+02
                                                                -    11/01/13            +
10/01/13                                        1.45E+03      +1.31E+02
                                                                -    12/01/13            +
11/01/13                                        1.59E+03      +1.35E+02
                                                                                          +                          1.33E+02 12/01/13          12/31/13                    1.43E+03 102B      Monthly Headworks            01/03/13          02/05/13            +       4.42E+02         9.78E+01 02/05/13          02/28/13            +       3.58E+02           1.03E+02 02/28/13           04/02/13             +      5.16E+02           1.09E+02 04/02/13           04/30/13             +      3.58E+02      +    1.04E+02 04/30/13           06/03/13                     2.84E+02          9.90E+01 06/03/13           07/01/13             +      3.13E+02          9.18E+01 07/01/13           07/31/13                     1.52E+02           1.01E+02 07/31/13           09/03/13                     1.48E+02      +    9.40E+01 09/03/13           10/01/13                     2.03E+02      +    9.60E+01 10/01/13           11/01/13                     1.60E+02      +-  9.64E+01 11/01/13           12/01/13                     2.18E+02     +1.01E+02 12/01/13          12/31/13                    1.82E+02           1.02E+02 TABLE B-8.2 TRITIUM IN SANITARY WASTE TREATMENT WATER -  


==SUMMARY==
==SUMMARY==
Results in pCi per liter Location Description Average Activity Activity Activity Number of Low High Samples Number of Positive IDs 102A FFTF Effluent 1.44E+03 102B Monthly Headworks 2.78E+02 8.70E+02 1.78E+03 1.48E+02 5.16E+02 12 12 12 5 RQ= results Qualifier.
 
If blank, result is less than detection limit. If "+", result is above the detection limit.Page 1 of 1 TABLE B-10J, 1 I GAMMA SPECTROMETRY RESULTS OF GROUNDWATER MONITORING WELL SAMPLES Results in pCi per liter Station MW-3 collected Nuclide RQ Activity Error 1/28/2013 Station MW-9 collected MOA ... Nuciide , RQ- -- Activity .-Error 2/4/2013 MDA- 'i K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140 BI-214 Nuclide K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALA140 BI-214-2.60E+01
Results in pCi per liter Number of Location              Average            Activity        Activity  Number of          Positive Description            Activity              Low            High      Samples              IDs 102A FFTF Effluent 1.44E+03                    8.70E+02        1.78E+03        12                12 102B Monthly Headworks 2.78E+02                        1.48E+02 5.16E+02                12                  5 RQ= results Qualifier. If blank, result is less than detection limit. If "+", result is above the detection limit.          Page 1 of 1
+-3.03E+
 
TABLE B-10J, GAMMA SPECTROMETRY RESULTS OF GROUNDWATER MONITORING WELL SAMPLES 1
I Results in pCi per liter Nuclide Station MW-3 collected                          1/28/2013                            Station MW-9 collected                2/4/2013 MDA- 'i I
K-40 MN-54 RQ        Activity
                          -2.60E+01
                          -3.03E+00 Error
                                          + 8.78E+01
                                          + 5.66E+00 MOA ...
1.12E+02 9.01 E+00 Nuciide , RQ- --Activity K-40 MN-54.
1.64E+01 +
                                                                                                                *-2.31 E-02 +
                                                                                                                              .-Error 4.62E+01 3.74E+00 8.36E+01 6.15E+00 I
CO-58              3.25E+00        _+ 3.31E+


==SUMMARY==
==SUMMARY==
Results in pCi/liter Average Activity , Activity Average Number of Number of Nuclide Activity Low High MDA Samples Positive IDs BALA140 1.14E-01 -2.48E+00 3.84E+00 8.47E+00 40 0 BI-214 1.65E+02 4.14E+00 5.78E+02 1.72E+01 40 36 CO-58 -1.64E-01  
 
-3.65E+00 3.25E+00 6.33E+00 40 0 CO-60 -1.51E-01  
Results in pCi/liter Average       Activity ,   Activity         Average     Number of Number of Nuclide     Activity       Low         High             MDA       Samples   Positive IDs BALA140       1.14E-01   -2.48E+00     3.84E+00         8.47E+00       40           0 BI-214     1.65E+02     4.14E+00     5.78E+02         1.72E+01       40         36 CO-58     -1.64E-01   -3.65E+00     3.25E+00         6.33E+00       40           0 CO-60     -1.51E-01   -2.72E+00     3.77E+00         6.58E+00       40           0 CS-134     -5.73E-01   71.11E+01   .2.65E+00         9.22E+06 . 40           0 CS-137     -2.15E-01   -3.65E+00     3.20E+00         6.86E+00       40           0 FE-59     2.23E-01   -3.33E+00     5.39E+00         1.43E+01'     40           0 1-131   -8.74E-02 -' -3.36E+00     5.35E+00         8.44E+00       40           0 K-40   -3.09E+01     -9.33E+01     1.64E+01         9.88E+01       40           0 MN-54       3.23E-02   -3.03E+00     3.76E+00
-2.72E+00 3.77E+00 6.58E+00 40 0 CS-134 -5.73E-01 71.11E+01  
* 6.46E+00       40           0 ZN-65   -2.74E+00     -1.10E+01     5.51 E+00         1.43E+01       40           0 ZRNB-95   :. 1.26E-01   -4.58E+00     6.33E+00         1.08E+01       40           0 Page 1 of 1
.2.65E+00 9.22E+06 .40 0 CS-137 -2.15E-01  
 
-3.65E+00 3.20E+00 6.86E+00 40 0 FE-59 2.23E-01 -3.33E+00 5.39E+00 1.43E+01' 40 0 1-131 -8.74E-02  
I TABLE B-11.1 TRITIUM IN GROUNDWATER MONITORING WELL SAMPLES                                               i Results in pCi per. liter Location                 Collection Date         RQ       Activity               Error               i MW-3                     01/28/13              +, . 1.23E+03                1.24E+02 04/24/13 07/22/13
-' -3.36E+00 5.35E+00 8.44E+00 40 0 K-40 -3.09E+01  
                                                                          + - *-!-.45E+03
-9.33E+01 1.64E+01 9.88E+01 40 0 MN-54 3.23E-02 -3.03E+00 3.76E+00
                                                                          +      1.59E+03 1.29E+02 1.30E+02 I
* 6.46E+00 40 0 ZN-65 -2.74E+00  
11/06/13               +      1.49E+03              1.32E+02 MW-5                      01/28/13..
-1.10E+01 5.51 E+00 1.43E+01 40 0 ZRNB-95 :. 1.26E-01 -4.58E+00 6.33E+00 1.08E+01 40 0 Page 1 of 1 TABLE B-11.1 TRITIUM IN GROUNDWATER MONITORING WELL SAMPLES Results in pCi per. liter Location Collection Date RQ Activity Error MW-3 MW-5 MW-6 MW-8 MW-9 MW-i0 MW-11 MW-12 MW-13 MW-14 01/28/13 04/24/13 07/22/13 11/06/13 01/28/13..
04/24/13
04/24/13 07/22/13 11/06/13 01/28/13 04/24/1 3 07/22/13, 11/06/13.-
                                                                          +
02/04/13 05/01/13 07/24/13 11/13/13 02/04/13 05/01/13 07/24/13 11/13/13 02/04/13 05/01/13 07/24i 3 11/13/13 02/04/13 05/01/1.3 07/24/13 11/13/13 02/04/13 05/01/13 07/24/13 11/13/13+, .1.23E+03+ -
                                                                          +
+ 1.59E+03+ 1.49E+03+ 1.49E+04+ 1.50E+04+ 1.54E+04+ 1.50E+04+ 5.69E+03+ 5.79E+03+ 5.39E+03+ 5.20E+03+ 7.75E+02+ 7.38E+02+ 2.47E+03+ 2.04E+03 1.86E+02 2.35E+02+ 3.42E+02 1.77E+02 1.24E+02 1.29E+02 1.30E+02 1.32E+02 3.08E+02 3.09E+02 3.. 7E+02 3.14E+02 2.03E+02 2.04E+02 1.99E+02 1.99E+02 1.13E+02 1.11E+02 1.50E+02 1.44E+02 9.67E+01 9.84E+01 9.72E+01 9.75E+01.9.95E+01 1.02E+02 1.02E+02 1.02E+02 1.14E+02 1.17E+02 1.24E+02 1.21E+02 1.06E+02 1.08E+02 1.10E+02 1.10E+02 2.74E+02 2.78E+02 2.79E+02 2.82E+02 9.68E+01 1.02E+02 1.02E+02 1.01E+02 I i i I I I I I I I I I I I I I i I I++++4+4-+++++++4-+2.82E+02 3.85E+02 4.74E+02 3.40E+02 8.06E+02 9.01 E+02 1.26E+03 1.OOE+03 5.12E+02 5.93E+02 7.45E+02 6.32E+02 1.13E+04 1.17E+04 1.19E+04 1.19E+04 2.17E+02 4.10E+02 3.10E+02 3.23E+02 01/28/13 04/24/13 07/22/13 11/06/13 01/28/13 04/24/13 07/22/13 11/06/13 RQ= results Qualifier.
1.49E+04 1.50E+04 3.08E+02 3.09E+02 I
If blank, result is less than detection limit. If "+', result is above the detection limit.Page 1 of 1 TABLE B- 12.1 GAMMA SPECTROMETRY RESULTS OF CGS STORM DRAIN POND SOIL Surface Soil Sample Results Results in pCi/kilogram dry mass : Location & Date SDP location B Nuciide --RQ Activity Error BE-7 K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 CS-1 34 CS-1 37 BALA140 BI-214+ 7.78E+03 ++ 6.95E+03 +8.21 E+01 +3.06E+01 +-3.32E+00
1.54E+04              3.. 7E+02 07/22/13 11/06/13
+1.85E+01 ++ 1.80E+03 +8.29E+01 +-2.65E+00
                                                                          +
+1.80E+01 ++ 1.72E+02 +-5.19E+00
                                                                          +      1.50E+04             3.14E+02              I MW-6                      01/28/13               +      5.69E+03              2.03E+02 04/24/1 3 07/22/13,
++ 3.21E+02 +4.24E+02 4.94E+02 1.88E+02 2.46E+01 2.43E+01 4.56E+01 5.43E+01 6.07E+01 4.30E+01 2.22E+01 3.OOE+01 2.98E+01 5.85E+01 6/6/2013 MDA 3.02E+02 3.26E+02 3.04E+02 3.82E+01 3.97E+01 7.24E+01 4.13E+01 9.39E+01 7.05E+01 3.54E+01 3.12E+01 4.82E+01 8.OOE+01 6/6/2013 MDA Location & Date SDP location H I Nuclide RQ Activity Error 6/6/2013 MDA -]BE-7 K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 CS-1 34 CS-1 37 BALA140 BI-214+ 2.71E+03 ++ 3.67E+03 +6.72E+01 +3.70E+01 +1.89E+01 +-2.90E+01
                                                                          +
++ 1.48E+03 ++ 1.04E+02 +-1.81E-02
                                                                          +
+3.11E+01 ++ 1.66E+02 +0.00E+00 +9.26E+01 +3.94E+02 4.58E+02 2.52E+02 2.80E+01 2.49E+01 7.01 E+01 5.68E+01 6.65E+01 4.98E+01 2.62E+01 3.58E+01 5.89E+01 6.18E+01 3.91 E+02 3.39E+02 4.1OE+02 4.30E+01 3.91 E+01 1.12E+02 4.48E+01 1.01E+02 8.20E+01 4.09E+01 3.82E+01 9.82E+01 1.02E+02 6/6/2013 MDA Location & Date Nuclide RQd BE-7 + 1 K-40 + 2 CR-51 -4 MN-54 -CO-58 FE-59 -1 CO-60 +ZN-65 -1 ZRNB-95 4 CS-1 34 -2 CS-137 2 BALA140 C BI-214 + 4 SDP location K Location & Date I Nuclide RQ Activity SDP location J Error Activity Error.12E+03 +2.82E+03 +.85E+01 +1.92E-01 +9.08E-02 +.44E+00 +3.34E+02 +.78E+01 +.30E+01 +2.74E+01 +2.52E+01 +).OOE+00 +.-54E+02 +2.36E+02 3.22E+02 1.60E+02 1.61 E+01 1.42E+01 2.72E+01 2.44E+01 3.40E+01 2.67E+01 1.92E+01 1.77E+01 2.55E+01 6.16E+01 2.49E+02 2.41 E+02 2*60E+02 2.65E+01 2.34E+01 4.44E+01 2.53E+01 5.39E+01 3.91E+01 2.98E+01 2.69E+01 4.25E+01 6.17E+01 BE-7 K-40 CR-51 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 CS-1 34 CS-1 37 BALA140 BI-214+ 2.56E+03 ++ 5.38E+03 +-1.31E+02
                                                                          +
++ 4.56E+01 +9.17E+00 +-7.73E+00
5.79E+03 5.39E+03 5.20E+03 2.04E+02 1.99E+02              I 11/06/13.-                                          1.99E+02 MW-8                      02/04/13 05/01/13
++ 1.86E+03 ++ 1.19E+02 +2.51E+01 +2.53E+01 ++ 1.17E+02 +-1.34E+01
                                                                          +
++ 2.20E+02 +3.61 E+02 4.52E+02 1.99E+02 2.67E+01 2.71E+01 4.62E+01 5.74E+01 6.85E+01 4.88E+01 2.36E+01 3.13E+01 4:42E+01 5.96E+01 3.59E+02 2.65E+02 3.18E+02 4.04E+01 4.38E+01 7.47E+01 3.73E+01 1.04E+02 7.82E+01 3.72E+01 4.39E+01 7.07E+01 9.03E+01 RQ = Results Qualifier.
                                                                          +
If blank, result is less than detection limit. If "+', result is above detection limit.Page 1 of I}}
7.75E+02 7.38E+02 1.13E+02 1.11E+02 I
07/24/13              +     2.47E+03             1.50E+02 11/13/13              +     2.04E+03              1.44E+02 I
MW-9                      02/04/13                      1.86E+02              9.67E+01 05/01/13 07/24/13 11/13/13
                                                                          +
2.35E+02 3.42E+02 1.77E+02 9.84E+01 9.72E+01 9.75E+01 I
MW-i0                      02/04/13 05/01/13 2.82E+02 3.85E+02
                                                                                                      .9.95E+01 1.02E+02 I
07/24i 3                      4.74E+02             1.02E+02 MW-11 11/13/13 02/04/13 3.40E+02 8.06E+02 1.02E+02 I
1.14E+02 I
                                                                          +
05/01/1.3                     9.01 E+02             1.17E+02
                                                                          +
07/24/13                      1.26E+03              1.24E+02
                                                                          +
11/13/13                      1.OOE+03              1.21E+02 MW-12                      02/04/13 05/01/13
                                                                          +4
                                                                          +4
                                                                          -+
5.12E+02 5.93E+02 1.06E+02 1.08E+02 I
07/24/13                      7.45E+02              1.10E+02 MW-13 11/13/13 01/28/13
                                                                          +
                                                                          +
6.32E+02 1.13E+04 1.10E+02 2.74E+02 I
                                                                          +
04/24/13                      1.17E+04            2.78E+02 07/22/13 11/06/13
                                                                          +
                                                                          +
1.19E+04 1.19E+04 2.79E+02 2.82E+02 I
MW-14                      01/28/13 04/24/13 07/22/13
                                                                          +
4-2.17E+02 4.10E+02 3.10E+02 9.68E+01 1.02E+02 1.02E+02 i
I
                                                                          +
11/06/13                      3.23E+02              1.01E+02 RQ= results Qualifier. If blank, result is less than detection limit. If "+', result is above the detection limit. Page 1 of 1 I
 
TABLE B- 12.1 GAMMA SPECTROMETRY RESULTS OF CGS STORM DRAIN POND SOIL Surface Soil Sample Results Results in pCi/kilogram dry mass                  :
Location & Date                  SDP location B            6/6/2013            Location & Date                SDP location H  6/6/2013 Nuciide --RQ Activity                      Error          MDA                I Nuclide RQ          Activity        Error    MDA      -]
BE-7          +     7.78E+03       +     4.24E+02         3.02E+02             BE-7             +    2.71E+03  + 3.94E+02   3.91 E+02 K-40          +     6.95E+03      +     4.94E+02         3.26E+02             K-40            +    3.67E+03  +  4.58E+02    3.39E+02 CR-51                8.21 E+01     +    1.88E+02          3.04E+02              CR-51                6.72E+01 +  2.52E+02    4.1OE+02 MN-54                3.06E+01      +     2.46E+01          3.82E+01              MN-54                3.70E+01  +  2.80E+01    4.30E+01 CO-58              -3.32E+00      +    2.43E+01          3.97E+01              CO-58                 1.89E+01  + 2.49E+01    3.91 E+01 FE-59                1.85E+01      +     4.56E+01         7.24E+01             FE-59                -2.90E+01  + 7.01 E+01   1.12E+02 CO-60          + 1.80E+03           +     5.43E+01         4.13E+01              CO-60            + 1.48E+03    + 5.68E+01    4.48E+01 ZN-65                8.29E+01      +     6.07E+01          9.39E+01              ZN-65            +    1.04E+02 +  6.65E+01    1.01E+02 ZRNB-95            -2.65E+00      +     4.30E+01         7.05E+01             ZRNB-95              -1.81E-02 + 4.98E+01   8.20E+01 CS-1 34              1.80E+01       +    2.22E+01         3.54E+01             CS-1 34              3.11E+01  + 2.62E+01    4.09E+01 CS-1 37        + 1.72E+02          +     3.OOE+01         3.12E+01             CS-1 37          + 1.66E+02    +  3.58E+01    3.82E+01 BALA140            -5.19E+00      +    2.98E+01         4.82E+01              BALA140              0.00E+00  +  5.89E+01    9.82E+01 BI-214        + 3.21E+02          +    5.85E+01          8.OOE+01              BI-214                9.26E+01  +  6.18E+01    1.02E+02 Location & Date                  SDP location K             6/6/2013            Location & Date                SDP location J  6/6/2013 Nuclide RQd Activity                        Error          MDA                I Nuclide RQ Activity                  Error    MDA BE-7          +    1 .12E+03      +     2.36E+02          2.49E+02              BE-7            +   2.56E+03  +   3.61 E+02  3.59E+02 K-40          +     22.82E+03      +    3.22E+02          2.41 E+02            K-40            +   5.38E+03 + 4.52E+02    2.65E+02 CR-51              -4 .85E+01     +     1.60E+02         2*60E+02              CR-51                -1.31E+02  +   1.99E+02  3.18E+02 MN-54                - 1.92E-01    +     1.61 E+01       2.65E+01             MN-54            +    4.56E+01 +  2.67E+01   4.04E+01 CO-58                  9.08E-02    +     1.42E+01         2.34E+01             CO-58                9.17E+00  +   2.71E+01   4.38E+01 FE-59              -1.44E+00      +     2.72E+01          4.44E+01             FE-59                -7.73E+00  +   4.62E+01   7.47E+01 CO-60          + 3.34E+02           +     2.44E+01         2.53E+01             CO-60            +     1.86E+03 +   5.74E+01  3.73E+01 ZN-65              -1.78E+01      +    3.40E+01          5.39E+01              ZN-65           +    1.19E+02 +  6.85E+01  1.04E+02 ZRNB-95             4.30E+01      +    2.67E+01          3.91E+01              ZRNB-95              2.51E+01  +   4.88E+01  7.82E+01 CS-1 34            -22.74E+01      +     1.92E+01        2.98E+01             CS-1 34              2.53E+01 +   2.36E+01  3.72E+01 CS-137              22.52E+01     +     1.77E+01         2.69E+01             CS-1 37          +    1.17E+02 +   3.13E+01   4.39E+01 BALA140              C).OOE+00 +         2.55E+01          4.25E+01              BALA140              -1.34E+01  +   4:42E+01   7.07E+01 BI-214        +    4 .-54E+02 +         6.16E+01         6.17E+01             BI-214          +   2.20E+02  +   5.96E+01   9.03E+01 RQ = Results Qualifier. If blank, result is less than detection limit. If "+', result is above detection limit.                 Page 1 of I}}

Latest revision as of 20:06, 5 February 2020

and ISFSI - 2013 Annual Radiological Environmental Operating Report
ML14135A376
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Site: Columbia  Energy Northwest icon.png
Issue date: 05/06/2014
From: Sawatzke B
Energy Northwest
To:
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References
G02-14-073
Download: ML14135A376 (156)


Text

Bradley J. Sawatzke ENERGY Columbia Generating Station P.O. Box 968, PE08 NORTHWEST Richland, WA 99352-0968 Ph. 509.377.4300 1F. 509.377.4150 bjsawatzke @energy-northwest.com May 6, 2014 G02-14-073 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Energy Facility Site Evaluation Council ATTN: EFSEC Manager P.O. Box 43172 Olympia, WA 98504-3172

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 INDEPENDENT SPENT FUEL STORAGE INSTALLATION, DOCKET NO. 72-35 2013 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

References:

1. Columbia Generating Station Technical Specification 5.6.1
2. Independent Spent Fuel Storage Installation Technical Specification 5.4.b
3. EFSEC Resolution No. 332, February 21, 2012

Dear Sir or Madam:

In accordance with the requirements of References 1-3, the subject report is submitted as an enclosure to this letter. If you have questions regarding this information, please contact TE Northstrom at (509) 377-8462.

Respectfully, BJ Sawatzke Vice President, Nuclear Generation & Chief Nuclear Officer Enclosure cc: NRC Region IV Administrator Director, SFPO-NRC NMSS NRC NRR Project Manager M. Priddy (WDOH)

NRC Sr. Resident Inspector (988C) L. Albin (WDOH)

MA Jones - BPA/1 399 L. Vigue (WDFW)

WA Horin (Winston & Strawn) JM Ayres (WDOE)

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I O ENERGY NORTHWEST

  • COLUMBIA GENERATING STATION I

I OP RAT NG REPORT FOR THE COLUMBIA I EEAIN TTO I

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ENERGY NORTHWEST People- Vision. Solutions COLUMBIA GENERATING STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2013 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT For Calendar Year 2013 Preparation Date: April 2014 Submitted Date: May 2014 Authored BM: EN:W Evi/ i /LQ-Q David Mee, ENW Environmental Services Reviewed By:

Elisa Nguyen, ENW Envir nentdlServices Approved By: Auevio Terry Northstrom, ENW'Enviromnental Services Supervisor

TABLE OF CONTENTS SECTION PAGE 1.0 EXECUTIVE

SUMMARY

1-1 2.0 DEFINITIONS 2-1

3.0 INTRODUCTION

3-1 3.1 Site Description 3-1 3.2 Program Background 3-1 3.3 Program Objectives 3-2 4.0 PROGRAM DESCRIPTION 4-1 4.1 Sample Locations 4-1 4.2 Independent Spent Fuel Storage Installation (ISFSI) 4-1 4.3 Land Use Census 4-2 4.4 Sampling Methods 4-2 4.4.1 Direct Radiation 4-2 4.4.2 Airborne - Particulate/Iodine 4-2 4.4.3 Water 4-3 4.4.4 Soil 4-4 4.4.5 Sediment 4-4 4.4.6 Fish 4-4 4.4.7 Milk 4-5 4.4.8 Garden Produce 4-5 4.5 Sample Analyses 4-5 4.5.1 Analysis of TLDs 4-5 4.5.2 Gross Beta Activity on Air Particulate Filters 4-6 4.5.3 Measurement of Gamma Emitting Radionuclides 4-6 4.5.4 Gross Alpha and Gross Beta Activity in Water 4-6 4.5.5 Tritium in Water 4-7 4.5.6 Strontium-89/90, Iron-55, and Nickel-63 4-7 4.5.7 Low Level Radioiodine in Milk and Water 4-7 2013 Annual Radiological Environmental Operating Report i Energy Northwest/Columbia Generating Station

TABLE OF CONTENTS SECTION PAGE 4.6 Data Analysis Methods 4-7 4.7 Changes to the Sampling Program in 2013 4-8 3 5.0 RESULTS AND DISCUSSION 5-1 5.1 Direct Radiation 5-1 5.2 Airborne Particulate/Iodine 5-3 5.3 Water 5-5 5.3.1 Surface Water 5-5 U 5.3.2 Ground Water 5-6 5.4 Soil 5-7 5.5 River Sediment 5-7 3 5.6 Fish 5-7 5.7 Milk 5-8 1 5.8 Garden Produce 5-8 3 5.9 Special Interest Stations 5-8 5.9.1 Storm Drain Pond (Station 101) 5-8 3 5.9.2 Sanitary Waste Treatment Facility (Station 102) 5-9 5.9.3 Cooling System Sediment Disposal Area (Station 119) 5-10 3 5.9.4 Spray Pond Drain Field (Station 120) 5-11 5.9.5 Independent Spent Fuel Storage Installation 5-11 3 5.9.6 Additional Air Sample and TLD Locations 5-12 5.10 2013 Sample Deviations 5-12 3 3

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2013 Annual Radiological Environmental Operating Report ii Energy Northwest/Columbia Generating Station

TABLE OF CONTENTS SECTION PAGE 6.0 QUALITY ASSURANCE AND QUALITY CONTROL 6-1 6.1 Quality Control for the Energy Northwest Environmental TLD Program 6-1 6.2 Quality Control for the Environmental Sample Program 6-1 6.2.1 Sample Collection Quality Control 6-2 6.2.2 Laboratory Instruments Quality Control 6-2 6.2.3 Sample Batch Quality Control 6-2 6.3 Laboratory Intercomparison Program Participation and Results 6-3 6.4 Laboratory Quality Control Program Problems and Improvements 6-3

7.0 REFERENCES

7-1 8.0 ERRATA 8-1 APPENDIX A. Data Tables A and B 2013 Annual Radiological Environmental Operating Report 111 Energy Northwest/Columbia Generating Station

LIST OF TABLES TABLE PAGE 3 4-1 Radiological Environmental Monitoring Program Sampling Plan 4-9 4-2 REMP Sample Stations and Requirements 4-11 1 4-3 2013 Five Mile Land Use Census Results 4-15 3 4-4 Comparison of Laboratory Nominal Lower Limits of Detection With Offsite Dose Calculation Manual Requirements 4-16 3 5-la REMP Sample Deviations for 2013 5-12 5-lb CGS REMP Air Sample Percent in Service Time for 2013 5-14 1 5-2 Radiological Environmental Monitoring Program Summary 5-15 5-3 Quarterly TLD Data Summary with Comparison to Preoperational and I Operational Periods 5-25 6-1 2013 Environmental Spiked Dosimeter Results 6-4 1 6-2 ENW REMP Program Cross Check Performance Results 6-5 3 I

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Operating Report iv Energy Northwest/Columbia Generating Station 2013 Annual Radiological Environmental Annual Radiological Environmental Operating Report iv Energy Northwest/Columbia Generating Station

LIST OF FIGURES FIGURE PAGE 4-1 Select REMP Sampling Locations Within 0.8 Miles of CGS 4-17 4-2 Select REMP Sampling Locations Between 0.8 and 2.8 Miles 4-18 4-3 Select REMP Sampling Locations Beyond 2.8 Miles 4-19 4-4 ISFSI TLD Stations Layout 4-20 5-1 "S" Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean by Sector 5-1 5-2 Near Plant Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean by Sector 5-2 5-3 Remote Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean by Sector 5-2 5-4 1985-2012 Weekly Hi/Low/Mean and 2013 Weekly Mean Gross Beta in Air-Near Plant Stations 5-4 5-5 1985-2012 Weekly Hi/Low/Mean and 2013 Weekly Mean Gross Beta in Air-Remote Stations 5-4 5-6 Gross Beta in River/Drinking (Stations 26 & 29) and Plant Discharge Water (Station 27) for 2013 5-5 5-7 Tritium in River/Drinking (Stations 26 & 29) and Plant Discharge Water (Station 27) for 2013 5-6 5-8 Cooling System Sediment Activity Levels for Disposals Made in 2013 5-10 5-9 ISFSI TLD Trend at CGS 5-11 2013 Annual Radiological Environmental Operating Report V Energy Northwest/Columbia Generating Station

1.0 EXECUTIVE

SUMMARY

1.0 EXECUTIVE

SUMMARY

The primary purpose of the Energy Northwest Radiological Environmental Monitoring Program (REMP) is to evaluate the radiological impact that Columbia Generating Station (CGS) operation may have on the environment. Sampling is performed as specified in the Offsite Dose Calculation Manual (ODCM) and agreements made with the State of Washington Energy Facility Site Evaluation Council (EFSEC).

Additional sampling is also performed to meet Nuclear Energy Institute (NEI) guidelines or as an Energy Northwest initiative. The program also serves to validate CGS effluent measurements and exposure pathway models and to provide a documented, historical record of CGS impact on the environment. This report serves to document and communicate the program results and findings for calendar year 2013.

A variety of environmental samples are routinely collected and analyzed by the REMP. The types of samples collected include air, water, soil, sediment, milk, fish, and garden produce. Additionally, the program continuously monitors direct radiation at numerous locations surrounding CGS. Analysis results are trended and compared to results from control locations, results obtained in previous operational and pre-operational periods, and regulatory limits.

The results contained in this report indicate that CGS operation in 2013 had minimal radiological impact on the environment. The only identified radiological impact to areas outside the CGS controlled area consisted of low level tritium in one plant discharge water sample that is attributed to recapture of CGS gaseous effluent tritium. All other identified radiological impact was limited to areas within the CGS controlled area. Sample results are consistent with the results obtained from control locations, results from the preoperational period, and historical results collected since CGS began commercial operation.

With the exception of the one tritium sample result, all radioactive material identified outside the CGS controlled area was of natural origin or known to be present in the environment around CGS in the quantities identified. The results are consistent with and verify CGS effluent measurements and modeling of the exposure pathways.

Below is a summary of the 2013 results by exposure pathway:

Direct Radiation - No impact was identified at locations beyond the CGS controlled area. Within the controlled area, the only impact identified was at locations known to be influenced by the Independent Spent Fuel Storage Installation (ISFSI) or radiation from the turbine building during operation.

Airborne - No impact due to CGS operation was identified. The radionuclide activity identified in soil samples were consistent with activity levels known to exist in Hanford area soils.

Waterborne - No significant impact was identified. Low level tritium was identified in storm drain water and radionuclides related to CGS operation were identified in storm drain soil and cooling system sediment. Low level tritium was identified in one plant discharge water sample. All activity identified at these locations is attributed to recapture of CGS effluents. The 2013 data supports the longer term observation that storm drain tritium may be influencing groundwater tritium at locations near the storm drain pond. Tritium identified in sanitary waste water is attributed to discharges made from facilities operated by the Department of Energy. Tritium activity identified in groundwater was at levels consistent with levels known to exist in Hanford groundwater. Radionuclide activity identified in river sediment is consistent with activity levels known to exist in Hanford area sediment and soils.

Ingestion - No impact was identified in any of the food sample results.

2013 Annual Radiological Environmental Operating Report 1-1 Energy Northwest/Columbia Generating Station

2.0 DEFINITIONS 2.0 DEFINITIONS a priori: refers to a "before the fact" limit that Curie (Ci): A measure of radioactivity; equal to 3.7 x represent the capabilities of a measurement system and 1010 disintegrations per second, or 2.22 x 1012 not a limit for a particular measurement. disintegrations per minute.

a posteriori: refers to an "after the fact" limit Direct Radiation Monitoring: The measurement of determined for a particular measurement and not a radiation dose at various distances from the plant is limit for a measurement system. assessed using thermoluminescent dosimeters and Airborne Activity Sampling: Continuous sampling of pressurized ionization chambers.

air through the collection of particulates and radionuclides on filter media. Periodic soil samples are DOE: U.S. Department of Energy.

collected for gamma isotopic analysis to provide information on deposition to the soil from airborne DOH: Washington State Department of Health.

releases.

EFSEC: Energy Facility Site Evaluation Council.

Alpha Particle (o): A charged particle emitted from the nucleus of an atom having a mass and charge equal in FFTF: Fast Flux Test Facility. This facility is referred magnitude of a helium nucleus. to as the DOE 400 area throughout this report.

Becquerel (Bq): One disintegration per second. One Flow Proportional Sampling: Sample collection picocurie (pCi) equals 0.037 becquerel. volume or frequency determined as a function of the flow rate of the water being sampled.

Beta Particle (0): Charged particle emitted from the nucleus of an atom with a mass and charge equal in Grab Sample: A single discrete sample drawn at one magnitude to that of an electron. point in time.

Blank Sample: A sample of the same media as the IDC: Energy Northwest Industrial Development field sample being analyzed but without any Complex, formerly referred to as the WNP- I and WNP-radionuclide(s) being measured. It enables correction 4 sites.

for the inherent sample background.

Indicator Station: A sampling location that is likely to CGS: Columbia Generating Station, formerly referred be affected by plant effluents due to its proximity and/or to as WNP-2. direction from the Columbia Generating Station.

CGS Controlled Area: The area within a 1.2 mile Ingestion Pathway Monitoring: The ingestion radius of the CGS reactor building and a narrow pathway includes milk, fish, and garden produce. Also corridor extending from CGS east to the Columbia sampled (under special circumstances) are other media River. such as vegetation and animal products such as eggs and meat when additional information about particular Composite Sample: A series of single collected radionuclides is needed.

portions (aliquots) analyzed as one sample. The aliquots making up the sample are collected at time ISFSI: Independent Spent Fuel Storage Installation.

intervals that are very short compared to the composite period. Lower Limit of Detection (LLD): The smallest concentration of radioactive material in a sample that Control Station: A sampling station in a location not will yield a net count (above system background) that likely to be affected by plant effluents due to its will be detected with 95% probability with a 5%

distance and/or direction from the Columbia probability of a false conclusion that a blank Generating Station. observation represents "real" signal.

Counting Error: An estimate of the two-sigma Mean: The average, i.e., the sum of results divided by uncertainty associated with the sample results based on the number of results.

respective count times.

+ / - 24F(SampleCPM/CountTine+ BkgCPM/CouniTime) Microcurie: 3.7 x 10a disintegrations per second, or 2.22 x 106 disintegrations per minute.

Report Operating Report 2-1 Energy Northwest/Columbia Generating Station 2013 Annual Radiological 2013 Annual Environmental Operat.ing Radiological Environmental 2-1 Energy Northwest/Columbia Generating Station

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Milliroentgen (mR): 1/1000 Roentgen; a unit of Site Certification Agreement (SCA): The initial exposure to X or gamma radiation.

MDA: Minimum Detectable Activity.

Columbia Generating Station licensing agreement with the State of Washington. The REMP sampling commitments in the SCA have been modified by I

MDC: Minimum Detectable Concentration.

EFSEC agreements.

Spiked Sample: A sample that has had a known I

NEI: Nuclear Energy Institute quantity of radionuclide(s) added for the purposes of NIST: National Institute of Standards and Technology.

assessing analytical performance.

Standard Deviation: A measure of the scatter of a set U

NPDES: National Pollutant Discharge Elimination System.

of observations (or samples) around their mean value.

Indicated by "a". I NRC: U.S. Nuclear Regulatory Commission. Standard Error of the Mean: An estimate of the ODCM: Offsite Dose Calculation Manual. Licensing document that contains the offsite radiological uncertainty associated with the mean of observation (or sample) averages. Also known as the standard I

deviation.

requirements.

Picoeurie (pCi): 1 x 10-2 Curie or 2.22 disintegrations SE=

S*

S-n I

per minute, one millionth of a microcurie. where S2, the variance is Radioiodine: Radioisotopes of iodine. For commercial nuclear reactors, iodine-131 to iodine-135 are the S2 =--n(Xi-X)2 ni (n-I)

I principle radioiodines of concern. Due to its longer half-life, iodine- 131 is the most probable radioiodine identifiable in the environment.

SWTF: Sanitary Waste Treatment Facility. The sanitary waste processing facility for the Columbia I

Generating Station, the IDC, and the Department of REMP: Radiological Environmental Monitoring Program.

Energy's 400 Area.

TEDA: triethylene diamine U

Range: The difference between the smallest and largest results. Thermoluminescent Dosimeter (TLD): A TLD is a phosphor that stores energy from exposure to radiation I

Restricted Area: Any area to which access is and emits that energy in the form of light when heated.

controlled for purposes of protection of individuals from exposure to radiation and radioactive materials. I Roentgen: Unit of exposure to ionizing radiation in air.

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3.0 INTRODUCTION

3.0 INTRODUCTION

3.1 Site Description The Columbia Generating Station (CGS) is a 1230 MWe commercial nuclear power plant that achieved initial criticality on January 19, 1984. The plant is located in a sparsely populated shrub-steppe region within the Department of Energy (DOE) Hanford Site in southeastern Washington. The plant is approximately three miles west of the Columbia River and is surrounded on all sides by uninhabited desert land. The nearest large population centers are Richland, Pasco and Kennewick, which are 12 miles south, 18 miles southeast, and 21 miles southeast, respectively. The nearest privately owned lands are located approximately four miles east-northeast of the plant, across the Columbia River. The site has a bimodal wind pattern with winds primarily from the northwest and south. (1) The primary region of focus for REMP sampling is the farming region east of the plant.

Naturally occurring radionuclides exist in detectable quantities throughout the world and are seen in many of the samples collected for the REMP. Some examples of naturally occurring radionuclides that are frequently seen in samples are potassium-40, beryllium-7, actinium-228 (present as a decay product of radium-228), and radium-226. Additionally, some relatively long lived anthropogenic radioisotopes, such as strontium-90 and cesium-137, are also seen in some REMP samples; these radionuclides exist in measurable quantities 12 throughout the world as a result of fallout from atmospheric nuclear weapons testing. ' 3)

Due to the location of CGS on the Hanford Site, there are other sources of reactor produced radionuclides in close proximity to the plant. CGS is unique in the U.S. commercial nuclear power industry in this respect. Hanford related radionuclides, most notably tritium, are identified in some CGS REMP samples. Though the presence of these radionuclides in the vicinity of CGS are not necessarily reflective of CGS activity, changes in the levels of these radionuclides are monitored to assess any contribution that CGS may be making to the established background. The DOE has an active REMP program for the Hanford Site that overlaps the CGS REMP.

3.2 Program Background The CGS REMP is designed to conform to the Nuclear Regulatory Commission (NRC) Regulatory Guides 4.1,4) 4.8,(5) and the Radiological Assessment Branch Technical Position. 61 In addition, the REMP also meets the requirements of 10 CFR 72.44(d)(2) for coverage of the ISFSI.

The quality assurance aspects of the sampling program and the thermoluminescent dosimetry are conducted in accordance with Regulatory Guides 4.15(71 and 4.13.(8) The REMP also adheres to the requirements of the Washington Energy Facility Site Evaluation Council,(9 ) the Columbia Generating Station Technical Specifications,(10 .)and the Offsite Dose Calculation Manual"1 1 ) These requirements cover the environmental sampling and sample analysis aspects of the program, and also the reporting and quality assurance requirements.

2013 Annual Radiological Environmental Operating Report 3-1 Energy Northwest/Columbia Generating Station

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The preoperational phase of the program, which lasted from March 1978 until initial criticality in January 1984, provided a baseline of background environmental data. Variability in the background levels of radioactivity over time is due to differences in geologic composition, meteorological I

conditions, decay of nuclear testing fallout material in the environment, and seasonal changes.

Variability in results may also have been introduced by changing analytical contractors and the use of different correction factors over the years.

I The Energy Northwest Environmental Services Laboratory performed all routine REMP sampling and analyses in 2013. Thermoluminescent dosimeters (TLDs) used in the REMP were processed by U

the Hanford External Dosimetry Program (HEDP) operated by Mission Support Alliance (MSA).

In addition to evaluating the environmental concentrations against regulatory limits, the REMP may I

also compare results to state standards.1 12. 13) The results may also be evaluated by comparing them to similar measurements made during the preoperational and previous operational periods and to the detection capabilities associated with the current methods of analysis.

I 3.3 Program Objectives I

The REMP provides an independent mechanism for determining the levels of radioactivity in the plant environs in order to empirically quantify and qualify any radiological effect plant operation may be making on the environment. The program serves to ensure that any accumulation of I radionuclides in the environment resulting from station operation will be identified promptly and before they become significant or exceed established limits.

While in-plant monitoring programs are used to ensure that 10 CFR 20(14) and 10 CFR 50(15) criteria I

for releases of radioactive effluents are met, the REMP further verifies that the measured concentrations of radioactive material and levels of radiation observed in the environment are not higher than expected based on CGS effluent measurements and modeling of the exposure pathways.

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2013 Annual Radiological Environmental Operating Report 3-2 Energy Northwest/Columbia Generating Station I

4.0 PROGRAM DESCRIPTION 4.0 PROGRAM DESCRIPTION The ODCM contains the CGS licensing based sampling requirements for the REMP. Additional sampling requirements are specified in resolutions with the Washington State Energy Facility Site Evaluation Council (EFSEC) or are self-initiated in response to site specific or industry wide concerns.

The sampling plan presented in Table 4-1 gives an overview of the REMP sampling routine, a summary of the sample locations, the specified collection frequency, and the types of analyses to be performed.

The methods of sampling and sampling frequencies utilized in the program are mostly dictated by regulatory requirements. Factors such as nuclide half-lives and the major exposure pathways for the radionuclides potentially released from the plant have been taken into account in determining the sampling methodology.

4.1 Sample Locations One hundred and ten sampling locations (referred to as 'stations') are included in the monitoring program. More than one sample type may be collected at a sample station. One hundred and one indicator and three control stations are located within a 10-mile radius of CGS. Six additional stations are located beyond the ten mile radius of the plant, two are indicator locations and four are control locations.

Sample stations are listed in Tables 4-1 and 4-2. Most station locations are shown in Figures 4-1 to 4-4.

The locations of most sample stations have been selected on the basis of an exposure pathway analysis. The exposure pathway analysis was based on factors such as weather patterns, anticipated emissions, likely receptors, and land use in the surrounding areas. Samples collected from stations located in areas that potentially could be influenced by CGS operation are used as indicators.

Samples collected from locations that are not likely to be influenced by CGS operation serve as controls. Results from indicator stations are compared to the results from control stations and results obtained during the previous operational and preoperational years of the program in order to assess the impact CGS operation may be having on the environment.

4.2 Independent Spent Fuel Storage Installation (ISFSI)

The Independent Spent Fuel Storage Installation (ISFSI) is a fenced, secured area constructed to provide a storage location for spent nuclear fuel. The spent fuel is stored in HI-STORM dry storage casks which are placed on concrete pads inside the facility. The pads are 30-feet wide by 135-feet long and each pad can hold up to 18 casks. The ISFSI is located approximately 500 meters north-northwest of the reactor building. Three security fences surround the ISFSI facility.

Direct radiation monitoring of the ISFSI is performed using TLDs placed at 10 different locations on the second of three security fences that surround the facility. The TLDs are exchanged quarterly. In addition, two other TLD stations, Station 121 located approximately 200 meters north of the turbine building and Station 122 located approximately 100 meters north of the ISFSI, were installed to monitor ISFSI direct radiation. Figure 4-1 shows the ISFSI location in relation to CGS and the position of the 2 additional TLD locations. Figure 4-4 shows the location of the 10 TLD stations located around the ISFSI. This arrangement of TLDs in conjunction with the radiological surveys conducted by the CGS Radiation Protection Department serve as the radiological monitoring program for the ISFSI.

Operating Report 4-1 Energy NorthwestlColumbia Generating Station 2013 2013 Annual Radiological Environmental Annual Radiological Environmental Operating Report 4-1 Energy Northwest/Columbia Generating Station

I 4.3: Land Use Census I A land use census covering the areas within a five mile radius of CGS is performed annually. The objective of the land use census is to identify the locations of the nearest milk animal, residence, and garden greater than 500 ft2 producing broadleaf vegetation. This information is used to determine whether any site located during the census has a calculated dose or dose commitment greater than the sites currently monitored for the same exposure pathway. If a new location with a higher dose commitment was found, routine sampling of that dose pathway would be initiated at that new site. The I

results of the 2013 five miles land use census are presented in Table 4-3. No significant changes from the 2012 land use census were observed.

4.4 Sampling Methods 3 Energy Northwest personnel collect environmental samples in accordance with the program plan outlined in Table 4-1. Methods of sample collection and TLD handling are specified in REMP specific procedures. All routine REMP samples collected in 2013 were prepared for analysis at the Energy Northwest Environmental Services Laboratory located in Richland, WA. The section 4.4 subsections I

below give a general overview of the sampling methods used in the REMP. Generic descriptions of the REMP sample analysis methods are given in section 4.5. I 4.4.1 Direct Radiation Direct radiation dose levels are monitored with Harshaw Model 8807 thermoluminescent dosimeters (TLDs). The TLDs are placed in the field between three and five feet above the ground. TLDs are wrapped in aluminum foil and sealed in plastic bags to prevent damage. TLDs are exchanged on a quarterly basis.

The locations of the TLD stations are listed in Table 4-2 and are shown in Figures 4-1 through 4-4.

Station 9A near Sunnyside, WA serves as the environmental TLD control location. Station 11 9C serves as the control for Station 119B (the cooling system sediment disposal basin). The remaining TLDs deployed in the field serve as indicator TLDs. U The TLDs are arranged in a series of rings that encircle CGS. The innermost ring of TLD stations, referred to as the "S" stations, are located inside the CGS site boundary at distances that range from 0.3-0.8 miles from the reactor building centerline. The second ring of TLDs, referred to as the "near plant" I stations, are located at distances ranging from 0.9 to 2.1 miles from the reactor building. The outer ring of TLDs are located at distances that range from a little under three miles to around ten miles. A MicroRem dose rate meter is available as a backup device and to take real time readings as needed.

4.4.2 Airborne - Particulate/Iodine Weekly air particulate and radioiodine (Iodine -131) samples are obtained through the use of low volume (1.5 cfm), constant flow-rate sampling units located at 1.2 locations. The samples collected at Station 9A (Figure 4-3) serve as controls, the samples collected at all other locations (Figures 4-1, 4-2, and 4-3) are indicators. Air particulate samples are collected using 47mm diameter glass fiber filters, air iodine 3

samples are collected using Radeco CP- 100 TEDA impregnated charcoal cartridges. The air particulate filter and charcoal cartridge are placed in tandem, particulate filter first, in a holder that attaches to the air inlet of the sampler unit. The sampler units are placed in ventilated metal weatherproof housings mounted on elevated platforms at each air sample location. The filter media are changed weekly. Four 4-2 U

2013 Annual Radiological Environmental Operating Report Energy Northwest/Columbia Generating Station

additional air sample monitor locations are available to monitor work at the DOE 618-11 burial site if needed.

4.4.3 Water Water sampling is performed to meet ODCM and State of Washington EFSEC requirements, comply with NEI guidelines, or as a CGS initiative. REMP water sampling can be categorized as follows:

  • Intake-River/Drinking Water; two locations (Stations 26 and 29)
  • Deep Groundwater; three locations (Stations 52, 31 and 32)
  • Shallow Groundwater; ten locations (MW-3, 5, 6 and MW-8 through MW-14)
  • Plant Discharge Water; one location (Station 27)
  • Storm Drain Water; one location (Station 101)
  • Sanitary Wastewater; two locations (Stations 102A and 102B)

The sample at Station 26 is obtained using a composite sampler that draws water from the plant intake water system (TMU). The source of this water is the Columbia River. The station serves as a control location, as it is upstream of the plant discharge location, and also as a drinking water location as drinking water for CGS comes from this source. Station 29 is a composite sampler located at the City of Richland Water Treatment Plant located 11 miles downstream of the plant discharge. Station 29 is an indicator station for both river and drinking water.

The ODCM requirement for a downstream water sample "near but beyond the mixing zone" is conservatively met by Station 27, a composite sampler that collects water from the cooling tower discharge line just prior to final discharge into the Columbia River. This sample reflects the radioactivity present in the plant discharge prior to any river dilution, rather than the concentrations that would be found after dilution in the mixing zone. Composite samples from Stations 26, 27, and 29 are collected monthly and analyzed for gamma emitting radionuclides, gross beta, and tritium.

Three drinking water wells on Energy Northwest property are used to provide deep groundwater samples. These wells are greater than 400 feet deep and provide samples from the confined aquifer.

under CGS. Station 52 is a deep well located 0.1 mile north of the CGS reactor building. Station 31 and 32 are deep wells at the IDC (ENW Industrial Development Complex) located 1.2 miles down gradient from CGS. Water from Station 52 can be used as a backup source for drinking water and fire protection. The IDC wells supply water for drinking and. fire protection at the IDC site. All of these wells are considered indicator locations. Quarterly grab samples are collected from each well and analyzed for gamma emitting radionuclides and tritium.

Station 101 is a composite sampler that collects a representative sample of water flowing into the storm drain pond located east of CGS. The main sources of water to the pond are discharges from the potable water and plant makeup water demineralizer treatment systems. Storm water runoff from the CGS site is also directed to this location. Water discharges from CGS that have been verified to meet radiological environmental discharge limits are another potential source of water to the storm drain pond. Water is collected monthly using a flow-proportional composite sampler and analyzed for gross beta, gamma emitting radionuclides, and tritium.

4-3 Energy Northwest/Columbia Generating Station Radiological Environmental Annual Radiological 2013 Annual Operating Report Environmental Operating 4-3 2013 Report Energy Northwest/Columbia Generating Station

The Sanitary Waste Treatment Facility (SWTF) receives sanitary waste water from CGS, the IDC (ENW I Industrial Development Complex), the Kootenai Building, and the DOE 400 area. Discharge standards and monitoring requirements for the SWTF are established in EFSEC ResolutionNo. 300. (16) Station 102A is a flow meter and composite sampler located on the DOE 400 area sewer line before it ties into the sewer lines coming from Energy Northwest facilities. Water used at the DOE 400 area is drawn from aquifers that are known to be contaminated with tritium as a result of past DOE activities on the Hanford Site, consequently, the water sampled at Station 102A has tritium concentrations normally around 1500-3 2000 pCi/liter. Station 102B is a composite sampler that collects a representative sample of water flowing into the head works at the SWTF. The sample obtained here contains water from all the Energy Northwest facilities mentioned above and the DOE 400 area. Monthly samples are collected at both 3

Stations 102A and 102B and analyzed for gross alpha, gross beta, tritium, and gamma emitting radionuclides.

Routine quarterly grab samples are taken as part of the REMP from 10 shallow groundwater monitoring wells surrounding CGS. The monitoring well locations are shown in Figure 4-1. The shallow groundwater wells are all less than 100 feet deep and allow samples to be obtained from the unconfined I

aquifer under CGS. None of the wells are used for drinking water. Sampling from these locations is performed to meet NEI 07-07 guidelines (17) and requirements in the CGS NPDES permit.

4.4.4 Soil I Annual soil samples are a requirement of EFSEC Resolution No. 332.(9) For 2013, two soil samples were collected from locations near CGS, two samples from farmland in Franklin County east of CGS, and one sample from a control location near Sunnyside, WA. Each sample was collected from an area of I approximately one square foot to a depth of approximately one inch. About two kilograms of soil was collected for each sample. Soil samples are analyzed for gamma activity on a dry weight basis.

4.4.5 Sediment River sediment samples are collected semiannually as required by the ODCM and EFSEC Resolution No. 332.(9) The upstream sediment sample location (Station .33) is approximately two miles upriver from the plant discharge. The downstream sample (Station.34) is collected approximately one mile downstream from the plant discharge. Each sample consists of approximately two kilograms of shallow surface sediment scooped from areas known to be underwater during high water periods and where the potential for sediment accumulation is likely. Sediment samples are dried in an oven and then analyzed for gamma emitting radionuclides on a dry weight basis.

Cooling system sediment samples are collected and analyzed whenever cooling system sediment is added to the disposal cells (Station 1 19B, Figure 4-1). Disposal of cooling system sediment is made in accordance with EFSEC Resolution No. 299.(18) Pre-disposal samples are collected and analyzed prior to ,

transfer to ensure the material will be within the limits specified in the EFSEC resolution. Following transfer, the material is allowed to dry and a post-disposal sample is collected and analyzed. 3 4.4.6 Fish Annual fish sampling is usually performed in the fall. Fish samples collected from the Columbia River (Station 30) serve as indicator samples, whereas fish collected on the Snake River (Station 38) serve as 3

control samples. Only edible portions of the fish are used to prepare the samples for analysis. Fish 2013 Annual Radiological Environmental Operating Report 4-4 Energy Northwest/Columbia Generating Station I

samples are analyzed for gamma emitting radionuclides on a wet weight basis. Three species of fish are collected; an anadromous species (salmon or steelhead), and two other species generally considered edible or potentially edible (typically carp, catfish, sucker, or whitefish). The same species are collected at each location. Electroshock techniques have historically been used for fish collection. Anadromous species are usually collected at fish hatcheries.

4.4.7 Milk Milk samples are collected monthly during the fall and winter months (October through March).

During the spring and summer months when cows are more likely to be grazing or on fresh feed, milk samples are collected twice per month. Raw milk samples are collected within a few hours of milking and the samples are normally prepared and analyzed within four days. Milk samples were collected in 2013 from two locations. Station 36 in Franklin County serves as the indicator location and is the only known dairy within a ten mile radius of CGS. Station 9B near Sunnyside, WA serves as the control location.

4.4.8 Garden Produce Samples of local garden produce are collected monthly during the growing season when the produce is readily available. Three types of garden produce are typically collected; root crops, fruits, and leafy vegetables. Control samples (Station 9C) are usually obtained from the lower Yakima Valley. Indicator samples (Station 37) are primarily collected from areas downstream of the CGS discharge where crops are irrigated with Columbia River water. The Riverview area of Pasco is the principle collection location for fruit and root crops. Collection of leafy vegetables is primarly made from locations that could potentially be influenced by CGS gaseous emissions. Vegetation samples may also be collected from locations closer to CGS; however none were collected in 2013. Garden and vegetable samples are typically purded in a food processor and then analyzed for gamma emitting radionuclides on a wet weight basis. Only edible portions are used for analysis.

4.5 Sample Analyses General descriptions of the procedures used to analyze REMP samples are provided in the following sections. All REMP TLDs in 2013 were processed by Mission Support Alliance (MSA) at the Hanford External Dosimetry Program (HEDP) facility located in Richland, WA. All routine REMP field samples were collected and analyzed by Energy Northwest Environmental Services personnel. Samples are normally collected and analyzed within a short time period to ensure required detection sensitivities are met and to provide timely results. Sample count times are conservatively calculated to ensure required a priori LLDs are achieved. Table 4-4 lists the ODCM required LLDs and the nominal target LLD used in the Energy Northwest REMP program.

4.5.1 Analysis of TLDs REMP TLDs are analyzed on a Harshaw Model 8800 hot gas reader. The reader is calibrated weekly and immediately prior to processing the environmental TLDs. The reader is calibrated with TLDs that have been given a known exposure from a cesium- 137 source. Each group of environmental TLDs is processed with blank (freshly annealed) TLDs and spiked TLDs that have been given a known exposure.

Exposure received by the field TLDs during transport is monitored with a set of 'trip' control dosimeters that accompany the field dosimeters to and from the field locations and while they are in storage.

2013 Annual Radiological Environmental Operating Report 4-5 Energy Northwest/Columbia Generating Station

I Another set of TLDs, the building controls, are used to determine~the exposure of the TLDs at the storage I location. The TLD exposure during transport to and from the field was determined from the difference between the building control results and the trip control results. i 4.5.2 Gross Beta Activity on Air Particulate Filters Air particulate filters are counted directly in a gas flow proportional counter after a delay of several days to allow for the decay of radon and its progeny. Samples were counted using a Protean WPC-9550 instrument which allows automated sample counting and simultaneous alpha/beta determination. If gross beta activity is identified significantly above the mean of the control, gamma isotopic analysis is performed on the individual samples.

I 4.5.3 Measurement of Gamma Emitting Radionuclides 3 Gamma isotopic analysis allows identification and quantification of gamma-emitting radionuclides that may be attributable to CGS effluents. Shielded, high purity. germanium (HPGe) detectors are used to j assay environmental samples for gamma emitting radionuclides. All samples are counted in standardized, calibrated geometries.

" Liquids - Measured aliquots of the liquid samples are poured into appropriately sized I Marinelli beakers or plastic canisters. Sample results are corrected for decay during the collection period if applicable. Results are reported in pCi/liter. I

" Solids - Soil, sludge, and sediment samples are dried and if needed ground. Foodstuff, biota (fish), and vegetation, are chopped finely or pureed and then analyzed wet (no drying is done). For foodstuff (including fish), only the edible portion of the sample is used. Sample aliquots are placed in tared containers and weighed. Results are reported in pCi/kg.

  • Charcoal Cartridges - Typically four charcoal cartridges are counted simultaneously using a cartridge holding jig that positions the cartridges in a standardized geometry to the side of the detector. Detector calibration files are maintained for both face count and side count positions. If radioiodines are identified in the assay of a group, each charcoal cartridge in the group is assayed separately. Results are corrected for decay during the sample collection period. Results are I

reported in pCi/m 3 . 3

  • Air Particulate Filters - At the end of each quarter, air particulate filters are composited on a station by station basis. The filters are stacked in a Petri dish and analyzed by gamma spectroscopy. Results are reported in pCi/m 3 and represent the total quarterly gamma activity collected at each station. Results are decay corrected to the midpoint of the sample collection I

period. If a radionuclide related to CGS operation is positively identified, the filters are separated and counted individually. I 4.5.4 Gross Alpha and Gross Beta Activity in Water g A measured aliquot of each sample is evaporated to a small volume then quantitatively transferred to a ribbed, stainless steel planchet. Final evaporation is normally done under a heat lamp. Residue mass is determined by weighing the planchet before and after mounting the sample. The planchet is counted for gross alpha and beta activity using a Protean WPC-9550 automatic gas flow proportional 3

counter which allows automated sample counting and simultaneous alpha/beta determination. Results 2013 Annual Radiological Environmental Operating Report 4-6 Energy Northwest/Columbia Generating Station l

are corrected for sample self-absorption: using the sample residue mass values. Results are reported in pCi/liter.

4.5.5 Tritium in Water The sample is distilled, then 8.0mL of the distillate is mixed with 12.OmL of scintillation cocktail.

The sample mixture is analyzed on a Packard Tri-Carb 2900TR automatic liquid scintillation counter.

Results are reported in pCi/liter..

4.5.6 Strontium-89/90, Iron-55, and Nickel-63 These "hard to detect" analytes are not routinely analyzed as part of the CGS REMP. When needed, these analyses are performed under contract by Teledyne- Brown Environmental Services Laboratory located in Knoxville, TN using the vendor's standard analysis procedures.

4.5.7 Low Level Radioiodine in Milk and Water Four liters of sample are first equilibrated with stable iodide carrier. Anion exchange resin is then added and mixed for a period sufficient to allow any iodine present in the sample to be captured by the resin.

The resin is then isolated from the liquid sample and transferred to a small counting container. The radioiodine content is determined by gamma spectroscopy analysis. Results are reported in pCi/liter.

4.6 Data Analysis Methods Counting results for low level samples are often within the counting error of the background determination; consequently results. for these samples can be positive or negative values. Though most REMP analytical results are belowthe detection limit, an actual calculated value has been reported. In some cases the reported value is zero or a negative number. Reporting results in this manner is the preferred practice for low level environmental analyses as it gives an indication of positive or negative biases that may be present and prevents loss of individual results inherent in the use of "less than" (<)

values. Also reported in most cases are the aposterioriMDA values. Anuclide is flagged as positively identified if its calculated value is greater than the MDA. A listing of the Energy Northwest nominal target LLDs (apriori)for each sample type is provided in Table 4-4; the ODCM required LLDs are also included for a comparison.

Data is trended following analysis for many of the sample types analyzed. For analyses such as .gross beta on air particulate filters where results are normally above the detection limit, indicator results are plotted with the control results for better comparison. Analysis results that are normally below detection limits are plotted against historical data .to monitor if trends may be evident.

Thermoluminescent dosimeter (TLD) data is presented in both units of mR/day and mR/standard quarter.

TLD results in mR/day are calculated by taking the total exposure (in mR) determined for each TLD, correcting for storage background and any transit (or trip) exposure received during distribution and retrieval, then dividing by the number of days the TLD was in the field. The mR/standard quarter values are calculated by multiplying the mR/day value by 91.25 days (365/4). All TLD results are reported in units of exposure (Roentgen) and not in units of dose (Rem).

2013 Annual Radiological Environmental Operating Report 4-7 Energy Northwest/Columbia Generating Station

I 4.7 Changes to the Sampling Program in 2013 i

There were no major changes made to ODCM or EFSEC Resolution No. 332(9) mandated sampling in 2013. Sampling and analysis of shallow groundwater wells around CGS was continued as a routine I

part of the REMP. No samples were obtained from one of the shallow groundwater wells (MW-7) in 2013 due to lack of water. The last sample obtained from this location was in the third quarter 2012.

Sampling -from Station 102A was terminated at the end of December. This station consisted of a i

composite water sampler that sampled the sanitary effluent line coming from the DOE 400 area. The effluent line was plugged in mid-December and ENW is no longer accepting sanitary waste from this location. One TLD location, Station 73, was moved in October to a new location due to construction activities. The new location is in the same geographical sector and approximately 175 feet from the old location. I i

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4-8 i

2013 Annual Radiological Environmental Operating Report Energy Northwest/Columbia Generating Station

TABLE 4-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING PLAN SAMPLE METHOD AND SAMPLE STATION (b' COLLECTION TYPE AND FREQUENCY OF SAMPLE TYPE'a. NUMBER FREQUENCY* 1 ANALYSIS AIRBORNE Particulates and 1, 4-8, 9A, 21, 23,40, 48, Continuous sampling; weekly Weekly air filters gross beta and Radioiodine (6/1 2 )1d) and 57' collection. iodine cartridge gamma isotopic.

Quarterly air filter composite gamma isotopic.

DIRECT RADIATION TLD1 g)(34/79) 1-8, 9A, 10-25, 40-47, 49- Continuous monitoring, quarterly Radiation exposure monitoring 51, 53-56, 58, 65, 71-90, collection. processed on a quarterly 119B, 119C, 120-129, frequency.

136A-138A, 150-151.

WATERBORNE River/Drinking Waterh) 26, 27 and 29 Composite aliquots1'; monthly Monthly gamma isotopic, gross (3/3) collection, beta, and tritium. lodine-1310) as required.

Storm Drain Water (0/1) 101 Composite aliquots°', monthly Monthly gamma isotopic, tritium, collection. and gross beta.

Sanitary Waste 102A, 102B Composite aliquots"), monthly Monthly gamma isotopic, gross Treatment Facility collection. beta, gross alpha, and tritium.

Water (0/2)

Ground Water ( 2 / 3 )(k1 31, 32, and 52 Grab sample performed quarterly. Quarterly gamma isotopic and tritium.

Ground Water MW-3, 5, 6, 8-14 Grab sample performed quarterly. Quarterly gamma isotopic and Monitoring (0/I10)" tritium.

SOIL AND SEDIMENT Soi1l"(0/5) 9A, 7, 8, 23, 48 Grab sample performed annually. Annual gamma isotopic.

0 Strontium-90' as required.

River Sediment (1/2)(1) 33 and 34 Grab sample performed Semiannual gamma isotopic.

semiannually.

Cooling System 119B, 119C Grab sample of dried sediment Gamma Isotopic. After disposal.

Sediment Disposal Area within 30 days of disposal date.

(0/2)

INGESTION Milk'* (2/2) 9B, 36 Grab sample collected Gamma isotopic, Iodine-131 each semimonthly during grazing sample. Strontium-90.'n) as season, monthly at other times. required Fish'0 ' (2/2) 30, 38 Grab samples collected annually. Gamma isotopic each sample.

Garden Produce(')(l/2) 9C, 37 Grab samples collected monthly or Gamma isotopic each sample.

at time of harvest.

Report 4-9 Energy Northwest/Columbia Generating Station 2013 Annual Radiological 2013 Annual Environmental Operating Radiological Environmental Operating Report 4-9 Energy Northwest/Columbia Generating Station

I TABLE 4-1 FOOTNOTES:

(a) -The fraction in parentheses for each sample type indicates the ratio of ODCM-required sample locations tothe total number of sample locations currently being monitored in the surveillance program. Additional sampling is perforimed to meet EFSEC Resolution 332 requirements or as an ENW initiative.

(b) The underlined sample location designates a control station.

(c) Sample collection is performed at a frequency specified in the ODCM and EFSEC resolutions. Some sampling referenced in Table 4-1 is performed at CGS initiative. Sample deviations are permitted if samples are unobtainable due to hazardous 5

conditions, seasonal availability, malfunction of automatic sampling equipment, or other legitimate reasons.

(d) The ODCM specifies six air sample locations and EFSEC Resolution 332 specifies nine. Two of the air sample stations are maintained at CGS initiative and are not requirements of either the ODCM or EFSEC Resolution 332. I (e) Sampling is performed to meet NEI 07-07 guidelines and NPDES requirements.

(t) Soil samples are collected from five locations to satisfy EFSEC Resolution 332 requirements. Two samples are collected from locations near CGS, two from locations in Franklin County, and one collected from a control location. Sample locations listed in 3

Table 4-1 are the location sampled in 2013. EFSEC 332 requires strontium-90 analysis be performed if gamma analysis results (g) are greater than a specified threshold.

TLD Stations 71-86 are not included among the 34 TLD stations required by the ODCM. Alternate designations for these

£ stations are I S-I 6S. EFSEC Resolution 332 requires 25 or more TLD stations to be located within a 10-mile radius of CGS.

Other instruments, such as a pressurized ion chamber (PlC), may be used in place of or in addition to TLDs as per ODCM table 6.3.1-1 (b). CGS REMP maintains a uRem meter for this purpose.

(h) The term "river/drinking water" is used throughout this report because the drinking water is taken from the Columbia River.

Station 26, CGS makeup water intake from the Columbia River is both an upstream water sample and the drinking water sample location. Station 29 is a downstream drinking water sample location. The Station 27 sample, which is drawn from the plant discharge line, is taken in place of a "downstream" water sample near but beyond the mixing zone. It reflects the radioactivity present in the plant discharge prior to any river dilution. EFSEC Resolution 332 requires samples from at least one downstream I

drinking water location and samples from the plant intake and discharge water systems.

(i) Composite samples are collected using automatic sampling equipment that collects samples based on a flow proportional or timed interval basis. If timed interval sampling is used, the interval period is short (e.g. hourly) relative to the compositing period 3

(e.g. monthly).

When the dose calculated via ODCM methodology for consumption of water exceeds I mrem per year, low level iodine-I 31 analyses are performed on the drinking water samples.

(k) Sampling from these locations fulfills ODCM table 6.3.1-1 3b requirements. EFSEC Resolution 332 requires sampling from at least one deep well used for fire protection and/or as a backup drinking water sources.

(I) Downstream sampling fulfills ODCM table 6.3.1-1 3d requirements. EFSEC Resolution 332 requires annual sediment samples upstream and downstream of the plant discharge.

(m) ODCM table 6.3.1-1 4a milk collection requirements cannot strictly be met due to the lack of milking animals near CGS. Milk samples are collected from the nearest dairy potentially impacted by CGS operation and also from a control location at the I

frequency specified in the ODCM. EFSEC Resolution 332 specifies sampling from at least one milk location within the 10-mile radius of CGS and also from a control location. Broadleaf vegetation can be sampled in lieu of milk if a representative milk sample is not available.

(n) ODCM table 6.3. 1-1 (k) requires that if cesium-134 or cesium-137 is measured in an individual milk sample in excess of 30 pCi/l iter, then a strontium-90 analysis will also be performed.

(o) Station 30 is the Columbia River and station 38 is the Snake River. If an impact is indicated, sampling will be conducted semiannually per ODCM table 6.3.1-1 (i). There are no species fished commercially in the Hanford Reach of the Columbia I

River. The most recreationally important species in the area are anadromous, which ascend rivers from the ocean for breeding.

Anadromous fish species are normally obtained from hatcheries; Snake River samples are obtained from the Lyons Ferry Fish Hatchery, and Columbia River samples are obtained at the Ringold Fish Hatchery.

(p) Garden produce is obtained from farms or gardens that use Columbia River water for irrigation. One sample of a root crop, leafy vegetable, and a fruit is typically collected each sample period, when available. EFSEC Resolution 332 further specifies fruit and vegetable sampling from locations potentially impacted by CGS gaseous emissions.

2013 Annual Radiological Environmental Operating Report 4-10 Energy Northwest/Columbia Generating Station a

TABLE 4-2 REMP SAMPLE STATIONS AND REQUIREMENTS STATION DISTANCE SECTORW NUMBER"' MILES"' ODCM"d' STATE"' OTHER")

N (1) 52 0.07 DGW DGW 71(1S) 0.28 TLD 47 0.70 TLD 57 0.70 AP/AI 18 1.16 TLD TLD 53 7.54 TLD NNE (2) 72(2S) 0.32 TLD 2 1.45 TLD TLD 54 6.08 TLD NE (3) 73(3S) 0.54 TLD 19 1.74 TLD TLD 48 4.59 AP/AI AP/AI 46 4.99 TLD MW-9 0.22 SGW ENE (4) 74(4S) 0.38 TLD 21 1.45 TLD, SO AP/AI 20 1.93 TLD TLD 11 3.16 TLD 33 3.44 SE 45 4.45 TLD 44 5.90 TLD 101 0.22 SW MW-8 0.26 SGW MW-I1 0.10 SGW E (5) 75(5S) 0.37 .TLD 22 2.08 TLD 10 3.16 TLD TLD 26 3.19 SW, DW SW 27 3.19 SW DIS W 30") 3.5 FI FI 43 5.16 TLD 151 (Site 4) 0.83 TLD MW-12 0.12 .. SGW ESE (6) 76(6S) 0.42 TLD 31 1.06 DGW 32 1.27 DGW 51 2.14 TLD 2013 Annual Radiological Environmental Operating Report 4-11 Energy Northwest/Columbia Generating Station

I TABLE 4-2 (cont.)

REMP SAMPLE STATIONS AND REQUIREMENTS a

SECTORa STATION NUMBERb' DISTANCE MILES"' ODCM"' STATE"' OTHER"'

I ESE (6)(cont.) 34 3.32 SE SE 23 8

3.03 4.39 TLD, AP/AI TLD, AP/AI. SO TLD, AP/AI I

42 36 5.85 7.33 TLD MI MI S 5 7.72 TLD AP/AI 38(g) 150 (Site 1) 26 0.90 Fl FI TLD U

SE (7) 77(7S) 24 3

0.57 1.87 2.06 TLD TLD TLD TLD I

41 40 5.79 6.51 TLD TLD, AP/AI AP/AI I

MW-14 0.58 SGW SSE (8) 119C 120 0.28 0.32 TLD TLD, SE I

102B 102G 0.50 0.56 SFW GP/VE i 78(8S) 0.81 TLD 25 55 1.50 6.05 TLD TLD TLD I

I 4 9.57 TLD, AP/AI TLD, AP/AI 29 11.57 DW DW 37 h) 16 GP GP MW-6 MW-13 0.33 0.52 SGW SGW £ S(9) 119B 0.31 TLD, SE 102A 79(9S) 0.67 0.76 SFW TLD I

I 1 1.25 TLD TLD, AP/AI, SO 6 7.72 TLD TLD, AP/AI 65 8.87 TLD SSW (10) 80(10S) 50 0.83 1.26 TLD TLD TLD 1

56 6.65 TLD MW-3 0.31 SGW I

I 2013 Annual Radiological Environmental Operating Report 4-12 Energy Northwest/Columbia Generating Station I

TABLE 4-2 (cont)

REMP SAMPLESTATIONS AND REQUIREMENTS STATION DISTANCE SECTOR"a NUMBER'b) MILES") ODCM") STATE"' OTHER"'

SW (11) 13 1.26 TLD TLD 81(11S) 0.74 TLD 103A 0.63 VE goo, 0.62 TLD, Al/AP MW-5 0.43 SGW WSW (12) 82(12S) 0.57 TLD 14 1.26 TLD TLD 9A 28.35 TLD, AP/AI TLD, AP/AI, SO 9B 32.82 MI MI 9C'i) 32 GP 890' 0.23 TLD, Al/AP 58 0.44 TLD W (13) 83(13S) 0.52 TLD 15 1.24 TLD TLD WNW (14) 84(14S) 0.55 TLD 16 -1.21 TLD TLD 7 2.83 TLD TLD, AP/AI, SO 886, 0.17 TLD, AUAP MW-10 0.07 SGW NW (15) 85(15S) 0.43 TLD 49 1.19 TLD TLD 870' 0.20 TLD, AL/AP NNW (16) 121 0.12 TLD 122 0.31 TLD 123 0.29 TLD 124 0.28 TLD 125 0.28 TLD 126 0.28 TLD 127 0.26 TLD 128 0.25 TLD 129 0.17 TLD 136A 0.29 TLD 137A 0.24 TLD 138A 0.17 TLD 86(16S) 0.31 TLD 17 1.19 TLD TLD 12 6.74 TLD 2013 Annual Radiological Environmental Operating Report 4-13 Energy Northwest/Columbia Generating Station

I TABLE 4-2 (cont.)

REMP SAMPLE STATIONS AND REQUIREMENTS I TABLE 4-2 SAMPLE TYPE KEY I

p AP/AI - Air Particulate/Air Iodine DW - Drinking Water Dis W - Discharge Water FI - Fish GP - Garden/Orchard Produce DGW - Deep Ground Water MI - Milk SE - Sediment SFW - Sanitation Facility Water SW - Surface Water VE - Vegetation SO - Soil TLD - Thermoluminescent Dosimeter SGW - Shallow Ground Water I

I TABLE 4-2 FOOTNOTES:

I (a) The area in the vicinity of CGS is separated into 16 sectors for reporting purposes. The 16 sectors cover 360 degrees in equal 22.5 degree sections, beginning with sector I (N) at 348.75 to 11.25 degrees and continuing clockwise through sector 16 (NNW). I (b) Alternate designations for station are given in parentheses; i.e., TLD Stations 71-86 are also referred to as I S-16S.

(c) Distances are from GPS positions for each location as a radial distance from CGS reactor building.

I (d) ODCM - Offsite Dose Calculation Manual Table 6.3.1-1 requirement.

(e) STATE - State of Washington EFSEC Resolution requirement. 3 (f) OTHER -Special study stations. TLD Stations: 121 through 129 and 136A through 138A satisfy ISFSI monitoring requirements 10CFR72.44(d)(2). Sampling at MW locations performed to meet NEI 07-07 guidelines and NPDES requirements. Stations 102G and 103A are locations near CGS where vegetation samples have been collected in the past. No samples were collected from these locations in 2013.

I (g) Station 30 is the Columbia River at the vicinity of the plant discharge. Actual distance of fish collection locations from plant are variable, distance listed is approximation. Station 38 is the Snake River. Control resident fish are typically collected at variable locations in area below Ice Harbor Dam, distance listed is approximation. Control I

anadromous fish are typically collected at Lyons Ferry Fish Hatchery.

(h) Fruit and Vegetable indicator samples are typically collected from farms and gardens in the Riverview area of Pasco. Distance listed here is general distance of Riverview area to CGS. Station 37 designation is also used for I

any samples collected in Franklin County that could potentially be affected by CGS liquid or gaseous effluents.

(i) Station 9C is the designation given for control fruits and vegetables. Distance listed is general distance to the Sunnyside-Grandview area where the majority of the control fruits and vegetables are obtained.

I 0.) Stations 87-90 were installed at CGS initiative to monitor remediation work at the DOE 618-11 burial ground. No remediation work that affected CGS was performed in 2013 and no air samples were obtained from these locations in 2013. See Section 5.9.6 for further discussion.

I I

I 2013 Annual Radiological Environmental Operating Report 4-14 Energy Northwest/Columbia Generating Station I

TABLE 4-3 2013 FIVE MILE LAND USE CENSUS RESULTS NEAREST GARDEN~d)

SECTORta) RESIDENT(" (>5 00 ft) DAIRY ANIMALS LIVESTOCK(b'c)

NE 4.50 none none none ENE 3.88 none none 4.95 E 4.64 none none 4.64 ESE 4.26 none none 4.49 SE none none none none FOOTNOTES (a) Within a five-mile radius of the plant, only the five sectors listed above contain activities related to land use census requirements. The other eleven sectors lay fully within the federally owned Hanford Site. Only those sectors containing potential land use census activities are presented here.

(b) Estimated distances in miles from CGS Reactor Building based on GPS readings. Actual locations are same as identified in previous years, distance values may differ from those reported in past due to updated GPS data.

(c) 25 to 30 beef cattle were identified in a pasture in the ENE sector. The western edge of the pasture is just within the 5 mile radius. Additional feed appears to be provided at this location. 5 cows, 2 calves, 3 horses, and some chickens were observed in a small fenced area near a residence in the E sector. The animals were observed to be fed hay. A single horse was observed in the ESE sector. There is no pasture at this location and the horse appears to be fed hay.

(d) Though no gardens > 500 fi2 were identified, commercial agriculture is extensively practiced in some parts of the sectors identified in Table 4-3. Agricultural activities observed were primarily apple and soft fruit orchards, corn, alfalfa, and grape vineyards.

2013 Annual Radiological Environmental Operating Report 4-15 Energy Northwest/Columbia Generating Station

TABLE 4-4 I

COMPARISON OF LABORATORY NOMINAL LOWER LIMITS OF DETECTION WITH OFFSITE DOSE CALCULATION MANUAL REQUIREMENTS I

MEDIA (UNITS) ANALYSIS ENERGY NORTHWEST LLDs(a)

ODCM REQUIRED LLDs I

Air Gross Beta 0.002 0.01 (pCi/M3) Cs-134 Cs-137 1-131 0.001 0.001 0.03 0.05 0.06 0.07 I

Water:

(pCi/liter)

Gross Beta Tritium Sr-90 2.4 300 1

4 20001b, I Ni-63 Fe-55 I-131(.c 200 5

1 I

Mn-54 7 15 Fe-59 Co-58 Co-60 10 7

7 30 15 15 I

Zn-65 Zr-Nb-95 Cs- 134 10 7

7 30 15 15 I

Cs-137 7 18 Soil/Sediment:

(pCi/kg dry)

Ba-La-140 Mn-54 Co-60 10 20 20 15 I

Zn-65 Cs-134 Cs-137 30 20 20 150 180 U

Sr-90 10 Fish:

(pCi/kg wet)

Mn-54 Fe-59 Co-58 25 100 35 130 260 130 I

Co-60 Zn-65 Cs-134 25 50 30 130 260 130 I

Cs-137 25 150 Milk:

(pCi/liter) 1-31 (c)

Cs-134 Cs-137 0.5 7

7 1

15 18 I

Garden Produce:

Ba-La- 140 Sr-90 Cs- 134 10 1

10 15 60 I

(pCi/kg wet) Cs-137 10 80 1-131 12 60

() These are the nominal target LLDs (a priori) for analyses performed in the Energy Northwest Environmental Services Laboratory I

and are based on conservative assumptions. These calculations included corrections for decay during the collection period and delay prior to analysis using factors that are normally encountered for the different media types. Actual LLDs (a posteriori ) may be higher or lower for specific samples.

colIf no drinking water pathway exists, a value of 3,000 pCi/liter may be used.

I

(') This ENW Iodine- 131 LLD achieved by anion resin separation and does not represent a direct analysis of the sample media.

I 2013 Annual Radiological Environmental Operating Report 4-16 Energy Northwest/Columbia Generating Station

0 0 05 1 I

1 L

Miles A

A 72 73 3L-AVZ] " 9 vvA v-v A74 275 83 82 W2 A 119C A j W5 119B 12016 W4 0 wf4 77 W-13 0b ** ..

81 102a A A A 80 79 78 E Water Sample Sediment Facilities N A TLD Security Barrier DOE Burial Ground

  • Air Sample

, Deep Well Reactor Building ISFSI Shallow Well City Limits Water FIGURE 4-1 SELECT REMP SAMPLING LOCATIONS WITHIN 0.8 MILES OF CGS 2013 Annual Radiological Environmental Operating Report 4-17 Energy Northwest/Columbia Generating Station

I 0 05 1 2 3 4 1 1 1 I I EA Miles L I g I g I I

E ] I gg II Ig COW"*~ law 2 19 A

A 18 17 20 A

49 A A 16 11 N-, A 15 W°31 L

\, 4W27 22 A

102a 5A A

13 23 50 0 3

A 25 24

~--~-

0 Water Sample Sediment Facilities N A TLD Security Barrier DOE Burial Ground Air Sample Deep Well Reactor Building

  • ISFSI Shallow Well City Limits Water FIGURE 4-2 SELECT REMP SAMPLING LOCATIONS BETWEEN 0.8 AND 2.8 MILES Operating Report 4-18 Energy Northwest/Columbia Generating Station 2013 Environmental Operating 2013 Annual Radiological Environmental Report 4-18 Energy Northwest/Columbia Generating Station

FIGURE 4-3 SELECT REMP SAMPLING LOCATIONS BEYOND 2.8 MILES 2013 Annual Radiological Environmental Operating Report 4-19 Energy Northwest/Columbia Generating Station

250 f r -- - -- --- -- -- - .- - - - - - - - - - -*7 -r

- -0,-. -,_


ST.123 ----------- ST.124----------

... ST.125

+ - i Isoltion Fence I I Security Fence I I~ ~------------------------------------------------------------------- I Electrical Cntrl Bldg

tT12 135tIt

,ST. 1261 T.__71

+0 _ _ _

Dry Fuel Cask I I ST.128' 0 0T. 21 000000000 I i -I I - - - -I

.. L... I,__

ST. 136A ST.137A ST. 1 .38A I---------------------+----------------------------

Cr

+ REMP TLD 0 FIGURE 4-4 ISFSI TLD STATION LAYOUT 2013 Annual Radiological Environmental Operating Report 4-20 Energy Northwest/Columbia Generating Station

5.0 RESULTS AND DISCUSSION 5.0 RESULTS AND DISCUSSION The Columbia Generating Station environmental TLDs were collected by Energy Northwest Environmental Services personnel and analyzed by the Hanford External Dosimetry Program (HEDP) operated by Mission Support Alliance (MSA). All other CGS REMP samples were collected and analyzed by the Energy Northwest Environmental Services Laboratory located in Richland, WA. Table 5-2 provides a summary of the ODCM required REMP sample and CGS groundwater monitoring analysis results in the format specified in Regulatory Guide 4.8. Results for naturally occurring radionuclides that are not related to CGS operations have not been included in the summary table. The lower limits of detection (LLDs) listed in Table 5-2 are the ODCM required detection limits and are not the method detection limits listed in Table 4-4. Analytical results for all REMP samples are presented in Appendix A of this volume and summarize the results in greater detail.

5.1 Direct Radiation Direct radiation is monitored at 79 TLD locations surrounding CGS. TLDs are exchanged on a quarterly frequency at all locations. The 16 locations designated as "S"stations are located between 0.3 and 0.8 miles from the CGS reactor building and all are inside the property boundary, see Figure 4-1 for station locations. Figure 5-1 shows the 2013 "S"station mean quarterly TLD results separated into 16 geographical sectors around the plant. Figure 5-1 also shows the pre-operational mean and the high, low, and mean results in each sector for the 1984 - 2012 operational period for comparison. The 2013 "S" station TLD results were lower than the pre-operational mean in 11 of the 16 sectors and lower than the operational mean in 13 of the 16 sectors. TLD results from the N, NNE, and NNW sectors are slightly higher than the other "S" station locations as a result of being physically closer to the ISFSI and the CGS turbine building. Excluding the NNW sector, the average deviation relative to the pre-operational period was -1.40%; in 2012 the average deviation was -1.65%. The NNW sector is the closest "S" station to the ISFSI and the higher result here is attributed to the stations close proximity to this facility.

0.36 S-Stations 0.33 0.30

>, 0.27 of 0.24 0.21 0.18 0.15 N NNE NE ENE E ESE SE SSE S SSW SWWSW W WNWNW NNW o Pre-Operational Mean -& 2013 Mean - 1984-2012 High/Low/Mean Figure 5-1 "S" Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean by Sector Operating Report 5-1 Energy Northwest/Columbia Generating Station 2013 2013 Annual Radiological Environmental Annual Radiological Environmental Operating Report 5-1 Energy Northwest/Columbia Generating Station

U The 19 locations designated as near plant stations are located at distances between 0.9 and 2.1 miles from the CGS reactor building, see Figure 4-2 for station locations. Figure 5-2 shows the exposure rates for the near plant TLD locations separated into sixteen geographical sectors around the plant.

Figure 5-2 also shows the pre-operational mean and the high, low, and mean results in each sector for I

the 1984-2012 operational period for comparison. The 2013 near plant TLD results were lower than the pre-operational mean in 12 of the 16 sectors and less than or equal to the operational mean in 14 of the 16 sectors. The average deviation relative to the pre-operational period was -1.7%, in 2012 the average I

deviation was -3.2%.

I 0.36 Near Plant Stations 0.33 I

>1 0.30 0.27 I

E 0.24 I 0.21 0.18 I 0.15 N NNE NE ENE o

E Pre-Operational Mean ESE SE SSE


2013 Mean S

SSW SWWSW W WNWNW NNW 1984-2012 HiglVLow/Mean I

Figure 5-2 Near Plant Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean by Sector I

0.36 Remote Stations Remote Stations I

0.33 I 0.29 0.26 I

E 0.22 I 0.19 0.15 I

N NNE NE ENE E ,ESE SE SSE S SSW WSW WNW NNW 0 Pre Operational Mean - 1984-2012 HighlLow/Mean 6 2013 Mean I Figure 5-3 Remote Stations Quarterly TLDs 1984-2012 Hi/Low/Mean and 2013 Mean By Sector I

2013 Annual Radiological Environmental Operating Report 5-2 Energy Northwest/Columbia Generating Station I

The 22 TLD locations designated as remote locations are located between 2.83 and 28.35 miles from the CGS reactor building; see Figure 4-3 for station locations. Figure 5-3 shows the exposure rates for the remote TLD locations separated into geographical sectors around the plant. Figure 5-3 also shows the pre-operational mean and the high, low, and mean results by sector for the 1984-2012 operational period for comparison. The 2013 remote TLD results were lower than the pre-operational mean in 9 of the 13 sectors and lower than the operational mean in 11 of 13 sectors. Station 46 in the Wahluke Reserve (NE sector) remained the remote location with the highest exposure rate. This has been the case since the pre-operational measurement phase and is attributed to differences in the underlying rock and soil composition in this area. The 2013 average deviation relative to the pre-operational period was -3.7%; the average deviation in 2012 was -3.5%.

Offsite direct radiation monitoring results are consistent with previous years. The 2013 results indicate no observable dose contributions due to plant operations at locations outside the CGS controlled area. Dose contributions inside the CGS controlled area are limited to those locations known to be influenced by the Independent Spent Fuel Storage Installation (ISFSI) and/or radiation from the turbine building during operation. Environmental radiation exposure rates for 2013, the pre-operational period, and the long term operational period are summarized in Tables 5-3. See also Appendix A, Tables A-1.1 and B-1.1 for the 2013 quarterly TLD results. TLD results for special interest locations are discussed in further detail in Section 5.9. "

5.2 Airborne Particulate/Iodine Air samples are collected weekly from 11 sample stations located around CGS. Additionally, an air sample station located 28 miles WSW of CGS is used as a control for comparison. Air particulate filters are analyzed for gross beta and iodine cartridges for radioiodines on a weekly basis. Air filters are also composited and analyzed for gamma emitting nuclides quarterly.

The 2013 mean weekly particulate filter gross beta results for the five stations located within three miles of CGS are plotted in Figure 5-4 (See also Appendix A, Tables A-2.1, A-2.2). Results for these near plant stations are similar to results from the remote locations and closely follow the trend of the control location.

Figure 5-5 is a plot of the 2013 mean weekly particulate filter gross beta results for the 6 sample stations located between 3 and 9.6 miles from CGS (See also Appendix A, Tables A-2. 1, A-2.2). Results for these remote stations are similar to results from the near plant stations and closely follow the trend of the control location. No correlation between air gross beta activity and proximity to CGS was observed.

For both near and remote air station locations, higher results and greater variability in air gross beta activity have historically been observed during fall and winter months due to weather induced background fluctuations. Gross beta levels typically increase during periods of inversion due to natural decay products being frapped near the earth surface. Gross beta results plotted over a period of several years typically show a cyclical pattern with higher results observed in the fall and winter compared to the spring and summer. Gross beta results above the normal trend range were observed in January, October, November, and December. The increases were observed at all sample locations including the control and are attributed to weather phenomena and not the result of CGS operation. The results for weeks 48-50 were among the highest gross beta air results observed by the CGS REMP. Weather conditions for this period were typical. of an inversion with below normal temperatures, overcast skies, and little to no winds. The smaller spike observed in week 43 occurred during a period when fog and blowing dust was noted.

2013 Annual Radiological Environmental Operating Report 5-3 Energy Northwest/Columbia Generating Station

I The quarterly particulate filter gamma isotopic results identified the presence of only naturally occurring I

radionuclides (See Appendix A, Tables A-3.1, A-3.2). Beryllium -7 was positively identified in all samples at both the indicator and control locations.

I Near Plant Stations 0.14 Data from 1986 weeks 19-23 not included due to Chernobyl I 0.12 I

0.10 E 0.08 I

a. 0.06 0.04 I 0.02 011TTITTITTT~kd.

0.00 '--

1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 I

WEEK

- HIGH/LOW/MEAN 1985-2012 A-MEAN 2013 -<)-Control 2012 I

Figure 5-4 1985-2012 Weekly Hi/Low/Mean and 2013 Weekly Mean Gross Beta in Air - Near Plant Stations I

Remote Stations 0.14 I 0.12 0.10 I 0.08 0-0.06 I 0.04 0.02 I

0.00 .....*.. -.

WEEK 1 3

5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 HIGH/LOW/MEAN 1985-2012 -A- MEAN 2013 -Control 2012 I Figure 5-5 1985-2012 Weekly Hi/Low/Mean and 2013 Weekly Mean Gross Beta in Air - Remote Stations I

The 2013 weekly iodine cartridge isotopic results showed no indication of radioiodines in any of the samples. Results for iodine- 131 were in all cases below the lower limit of detection. (See Appendix A, Tables A-4. 1,A-4.2).

I I

5-4 I

2013 Annual Radiological Environmental Operating Report Energy Northwest/Columbia Generating Station

The 2013 air particulate and iodine sample results show no evidence of measurable environmental radiological air quality impact that can be attributed to CGS plant operation.

5.3 Water 5.3.1 Surface Water Composite water samples are collected from 6 surface water locations monthly and analyzed for tritium, gross beta, and gamma emitters. A plot of the 2013 gross beta results for the plant intake, plant discharge, and river/drinking water stations are shown in Figure 5-6.

Gross Beta in Water 2013 14.0 12.0t 10.0 8.0

=6.0 CL 40

-2.0 0.0

-2.0 1 2 3 4 5 6 7 8 9 10 11 12 Month o Station 26 ---o- Staion 27 Stan 29 S

Figure 5-6 Gross Beta in River/Drinking ( Stations 26 & 29) and Plant Discharge Water (Station 27) for2013 All drinking and river water (Stations 26 and 29) gross beta results were below the analysis detection limits (See Appendix A, Tables A-5. 1, A-5.2). Gross beta levels in the plant discharge water (Station 27) were above the detection limits in ten of the twelve samples. Positive results for this location are expected due to the scrubbing action of the cooling towers which incorporates atmospheric particulate material into the discharge water and the concentration of natural radioactivity in the water by evaporative loss. Historically, higher gross beta results at Station 27 have been observed during periods when CGS circulating water was maintained at higher levels of concentration. The lower gross beta values for Station 27 during the summer months corresponds to a time period during and immediately after an outage. The Station 27 sample results are representative of the radioactivity present in plant discharge water before any mixing with river water occurs.

Monthly tritium results for all plant intake, plant discharge, and river/drinking water samples were below the analysis method a prioriLLD except for one plant discharge water sample. Tritium results for the three sample locations are plotted in Figure 5-7, quarterly averages for the locations are listed in Appendix A, Tables A-6. 1, A-6.2. The cause of the positive tritium activity in the March plant discharge water sample could not be identified; it is suspected that the activity was from recapture of CGS effluent tritium in the cooling water system.

2013 Annual Radiological Environmental Operating Report 5-5 Energy Northwest/Columbia Generating Station

U Gamma spectroscopy results for all plant intake, plant discharge, and river/drinking samples showed no I

indication of gamma-emitting radionuclides of interest being present (See Appendix A, Tables A-7. 1, A-7.2).

I 600 500 Tritium in Water 2013 3

400 300 I

S200 I

0

-100 I

1 2 3 4 5 6 7 8 9 10 11 12 Month

--o- Station 26 --- Station 27 a Station 29 - Tritium LLD (300 pQiA) I Figure 5-7 Tritium in River/Drinking ( Stations 26 & 29) and Plant Discharge Water (Station 27) for 2013 I

Analysis results for the plant intake, plant discharge, and river/drinking water samples showed only negligible impact to the environment due to CGS plant operations in 2013. Composite water samples are I also taken from two sanitary waste sample locations and one storm drain location. Analysis results for these samples are discussed in further detail in Section 5.9.

I 5.3.2 Ground Water Samples from 3 deep wells were collected quarterly to meet ODCM and EFSEC Resolution No. 332(9) requirements. Quarterly samples were also collected from ten shallow groundwater monitoring wells I

located near CGS as part of the CGS groundwater monitoring program. All well samples were analyzed for tritium and gamma emitting radionuclides. Well locations sampled are shown in Figures 4-1 and 4-2. U Analytical results for the three deep water wells were consistent with results seen in previous years.

Tritium results were below detection limits and no gamma emitting radionuclides related to CGS operation were identified in any of the samples (See Appendix A, Tables A-6.1, A-6.2, A-7.1, and A-I 7.2).

The CGS ground water monitoring program is conducted to meet the Nuclear Energy Institute (NEI)

I Groundwater Protection Initiative (NEI 07-07) (17)guidelines and to support NPDES requirements.

Ten shallow wells are routinely used to sample water from the unconfined aquifer around the CGS site. None of these monitoring wells are used as a source of drinking water. CGS is unique in the I

commercial nuclear power industry in that it is located in an area where the unconfined aquifer under the site is known to be contaminated with tritium as a result of past DOE activities on the Hanford Site.(19) The CGS groundwater program is intended to assess any contribution CGS may be making to I

the known groundwater contamination issue.

I 5-6 Energy Northwest/Columbia Generating Station I

2013 Annual Radiological Environmental Operating Report

Gamma Spectroscopy results for the ten shallow monitoring wells did not identify any gamma emitting radionuclides of interest(See Appendix A, Tables B- 10.1, and B- 10.2). Tritium concentrations at these locations ranged from < LLD to 15,400 pCi/liter (See Appendix A, Table B-11.1). Tritium results from each well were consistent during the year and within the trend range observed in previous years. The highest tritium concentrations were consistently measured at MW-5 which is hydraulically up-gradient of CGS. No samples were obtained from MW-7 in 2013 due to lack of water in the well. In 2011, ENW identified a possible correlation between tritium levels at the CGS storm drain pond and tritium levels at two nearby well locations (MW-7 and MW-8). Tritium results for 2013 showed a similar trend. Tritium activity in the storm drain pond is attributed to recapture of CGS effluents, see section 5.9.1 for more discussion. No other correlations between groundwater tritium and CGS operation weire identified. With the exception of the MW-8 tritium.

results, there is no evidence that CGS operation made a measurable radiological impact on groundwater.

5.4 Soil Gamma spectroscopy analysis was performed on soil samples from 5 different locations in 2013 (See Appendix A, Tables A-8. 1, A-8.2). Two of the samples were from locations near CGS, two were from locations east of CGS in Franklin County, and one was from a control location. Naturally occurring radionuclides (potassium- 40 and bismuth- 214) were identified in all samples. Cesium-137 was identified in one of the samples near CGS. The level of cesium-137 identified was within the range historically observed in local soil samples and within the range considered normal background in Hanford area soils.(20' 21,22) The cesium-137 level was well below the level that would require strontium-90 analysis to be performedi 91 The soil sample results indicate no measurable impact from CGS plant operation.

5.5 River Sediment Gamma spectroscopy results of river sediment identified naturally occurring radionuclides (potassium-40, bismuth- 214) and cesium-137 (See Appendix A, Tables A-9.1, 9.2). Relative to the circulating water discharge point, cesium-137 was detected in one of the upstream samples (Station 33) and both of the downstream samples (Station 34). The downstream cesium- 137 activity levels were similar to the levels identified in previous years and within the range known to be present in Hanford area sediment and soil.(21) Cesium-137 was not identified in any samples of plant cooling water discharged to the Columbia River. CGS has not made a radioactive discharge to the Columbia River since 1998. The sediment sample results indicate no measurable impact from CGS plant operation.

5.6 Fish The gamma spectroscopy results of fish samples identified low level cesium -137 in the anadromous fish collected from the Columbia River. The level identified was just above the analysis detection limit and substantially below the ODCM specified lower level of detection. Cesium -137 is occasionally identified in this media and has been identified at low levels in Columbia River fish by the CGS REMP and in other studies (23) in past years. The cesium -137 is not believed to represent an impact from CGS operation. Results of the other fish samples collected in 2013 identified only the presence of naturally occurring radionuclides (See Appendix A, Tables A-10.1, 10.2). Only two of the three ODCM required fish species were collected from both the control and indicator locations in 2013, see section 5.10 for further discussion.

2013 Annual Radiological Environmental Operating Report 5-7 Energy Northwest/Columbia Generating Station

I 5.7 Milk . - . I No radioiodine activity was identified in any of the milk samples collected in 2013 (See Appendix A, Tables A- 11.1, A- 11.2). Gamma spectroscopy results of milk radionuclides other than radioiodine did not identify the presence of any radionuclides of interest. (See Appendix A, Tables A- 12.19 A- 12.2).

Naturally occurring potassium-40 was identified in all milk samples.

5.8 Garden Produce Garnma analysis was performed on ten different types of fruits and vegetables in 2013 (See Appendix A, Tables A-15.1, A-15.2, A-16.1, A-16.2, A-17.1, A-17.2). No radionuclides of interest were identified in any of the samples. Naturally occurring potassium-40 was identified in all samples.

5.9 Special Interest Stations i Sampling and analysis is performed at the locations covered in this section to comply with EFSEC requirements or is performed at CGS initiative. The storm drain pond and the Sanitary Waste Treatment Facility (SWTF) were incorporated into the routine sampling schedule in 1992. In 1995, the cooling tower sediment disposal area was added. TLDs were placed around the spray pond drain field (Station 120) in June 1995. TLD monitoring in the vicinity of the planned Independent Spent Fuel Storage I Installation (ISFSI) was first performed in 1998 to collect background data and TLD monitoring was established on the ISFSI fence line after construction was completed in 2002. Additional air monitoring and TLDs stations were established in 2008/2009 to monitor remediation work at the DOE 618-11 burial ground west of CGS. Discussions of the results from each of the locations are given in the following I

sections. i 5.9.1 Storm Drain Pond (Station 101)

The storm drain pond (NPDES Outfall 002) is located approximately 1500 feet northeast of CGS. i Water is sent to the pond through an 18-inch diameter pipe that discharges into a 300-foot long earthen channel that leads to a 100-foot diameter pond. The pond is a shallow, unlined percolation/evaporation basin. Water at the storm drain outfall is sampled using a flow proportional automatic sampler to collect monthly composite samples. The storm drain pond area is fenced and access is restricted.

Monthly water samples were analyzed for gamma emitting radionuclides, tritium, and gross beta.

Gamma spectroscopy results did not identify the presence of any gamma emitting radionuclides of interest (See Appendix A, Tables B-2.1, B-2.2). Gross beta was not positively identified in any of the monthly samples (See Appendix A, Tables B-3.1, B-3.2). Tritium was detected in eight of the twelve samples (See Appendix A, Tables B-4. 1, B-4.2). The samples with higher tritium levels were all from colder, wetter months which is consistentwith results seen in previous years. The source of the tritium in storm drain pond water is attributed to recapture of tritium from CGS gaseous effluents which is more likely to occur during cooler, rainier periods.

Four soil samples were collected from the CGS storm drain pond in 2013 and analyzed for gamma emitting radionuclides. The samples were collected from surface soil locations that were identified as having higher levels of activity in a 2011 storm drain pond soil characterization study. (24) Analysis of the 2013 samples identified many of the same radionuclides identified in the 2011 study but at levels generally lower than observed in 2011 (See Appendix A, Tables B- 12.1).

2013 Annual Radiological Environmental Operating Report 5-8 Energy NorthwestlColumbia Generating Station 3

I

5.9.2 Sanitary Waste Treatment Facility (Station 102)

The Sanitary Waste Treatment Facility (SWTF) is located approximately 0.5 miles south-southeast of the CGS. The facility processes sanitary: waste water from CGS, the ENW Industrial Development Complex (formerly referred to as WNP- I and WNP-4), the Kootenai Building, and the DOE 400 Area. Station 102B receives water from all these locations; Station 102A receives water only from the DOE 400 Area.

Discharge standards and monitoring requirements for the SWTF are established in EFSEC Resolution No. 300.(16)

Gross beta results for Station' 102B (SWTF head works) were consistent with results seen in previous years. Gross beta results for Station 102A (DOE 400 Area effluent ) showed an increase over the course of the year rising from a level of less than 10 pCi/l in'the first half of the year to greater than 20 pCi/l in November and December. The increase is attributed to changes in the waste stream composition coming from the DOE 400 area and corresponds to decreasing discharge volumes from that facility. The sanitary sewer line from the DOE 400 area was plugged in mid-December 2013 and ENW is no longer accepting sanitary waste from this location. Gross alpha was not positively identified in any of the 102A or 102B samples. (See Appendix A, Tables B-5.1, B-5.2, B-6.1, B-6.2).

Gamma spectroscopy results of the monthly SWTF water samples identified iodine- 131 in the January Station 102B composite sample. CR 278601 was written to document the finding. As no additional radioisotopes were identified in the sample, the source of the radioiodine was attributed to a medically administered treatment and not the result of CGS operation. No other gamma emitting radionuclides of interest were detected in any of the other SWTF samples analyzed in' 2013 (See Appendix A, Tables B-7.1, B-7.2).

Tritium activity was identified in all twelve 102A and five of the twelve 102B samples (See Appendix A, Tables B-8. 1, B-8.2). Tritium levels in the 102A samples were similar to the levels seen in previous years. The potable water used at the DOE 400 area is obtained from a groundwater well that is known to be contaminated with tritium as a result of past DOE activities on the Hanford site.(17)

Tritium concentrations in the 102B sampleswere no more than 2 times the LLD of the analysis.

Tritium activity in the station 102B samples is attributed to DOE 400 area discharges; 102B tritium values trending below the LLD during the second half of the year correspond to smaller discharge volumes from the DOE 400 area. Tritium levels in all sanitary waste samples remained well below the 20,000 pCi/liter action limits of EFSEC Resolution No. 300.16)

SWTF water from stabilization pond B was discharged to ground in March 2013. Grab samples were taken at CGS initiative during discharge and used to create a composite sample that was analyzed for gamma isotopic and tritium content. Gamma isotopic analyses of the composite sample did not identify any radioisotopes related to CGS operation. Tritium activity of the composite sample was determined to be 529 pCi/l. A total of 1.4 million gallons of SWTF water was discharged to ground in March 2013.

Report 5-9 Energy Northwest/Columbia Generating Station 2013 Annual 2013 Environmental Operating Radiological Environmental Annual Radiological Operating Report 5-9 Energy Northwest/Colunibia Generating Station

I 5.9.3 Cooling System Sediment Disposal Area (Station 119)

EFSEC Resolution No. 299(18) authorizes the onsite disposal of asdime nts from plant cooling systems I

containing low levels of radionuclides. The disposal area for these sediments is located just south of the CGS cooling towers. EFSEC Resolution No. 299( 8)requires direct radiation monitoring using quarterly TLDs in the vicinity of the disposal cells and the collection and analysis of a dry composite sediment I

sample from the disposal cell within thirty days following each cleaning to confirm that the disposal criteria outlined in the resolution have not been exceeded. I Cleaning of the CGS cooling towers was performed in May and October 2013. Disposal of the material removed resulted in an estimated 51.5 cubic meters of dry sediment being placed in the disposal cell.

Figure 5-8 summarizes theestimated mass and radionuclide content of cooling tower sediment that was I

placed in the disposal area in 2013. For those isotopes listed in the table that were not positively identified, the MDA value obtained from the sample analysis was used in the table calculations. As such, the total activity reported is a conservative estimate.

I In addition to cooling tower sediment, ENW performed cleaning operations of the Standby Service Water (SSW) ponds in 2013. Material removed from the SSW ponds was temporarily Stored in bags in a lined basin south of the SSW ponds. Initial characterization of the material identified cobalt -60 in the I

400-3000 pCi /kg range. Transfer of the SSW sediment to the established cooling system disposal area was initiated in December 2013 and completed in January 2014. Final determination of the volume, density and radionuclide content of this material will be reported in the 2014 annual report.

I Figure 5-8 shows that the cooling tower sediment results were well below the disposal concentration limits specified in EFSEC Resolution No. 299."1" Cesium -137 levels identified in 2013 were similar to I

levels identified in previous years and within the range normally seen in Hanford area soils. Positive identification of cobalt -60 has been made in this media in past years and at level similar to those shown in Figure 5-8. I I

2013 Cooling System Sediment Disposal Data Disposal Date May 2013 October 2013 I

Pit ID: 2007 Pit 2007 Pit Mass, kg Density, g/cc

39,720' 0.8.1 1,725 0.81 I

Analytical Analytical Nuclide Limit (pCi/kg)

Result (pCi/kg).

Result (p~i/g) Total Curies I

Co-60 5.OOE+03 < 3.66E+01 2.79E+02 1.94E-06 Mn-54 Zn-65 3.OOE+04 5.00E+04

< 3.40E+01

<7.62E+01

<5.07E+01

< 9.14E+01

< 1.4"4E7-06

< 3.18E-06.

I Cs-134 Cs-137 1.00E+04 2.00E+04

<3.56E+01 1.91E+02

< 5.99E+01 2.91E+02

<1.52E-06 8.09E-06 I 1.62E-05 Figure 5-8 Cooling System Sediment Activity Levels For Disposals Made In 2013 I 2013 Annual Radiological Environmental Operating Report 5-10 Energy Northwest/Columbia Generating Station K

Measurements of direct radiation at the disposal pit area was taken using TLDs. Two locations were used, an indicator location next to the collection area (Station 1199B) and a control location approximately 100 yards to the east (Station 119C). The mean quarterly TLD results agree well with results from previous operational years. The negligible difference between the indicator and the control TLDs indicate that there was no measureable dose contribution above background due to material in the disposal cells.

(See Tables 5.3 and Appendix A, Tables B-1.1).

5.9.4 Spray Pond Drain Field (Station 120)

There were no discharges to the Spray Pond Drain Field (NPDES Outfall 003) in 2013. The TLD results at Station 120 in 2013 are in agreement with those seen in previous operational years (See Table 5-3 and Appendix A, Tables B- 1.1).

5.9.5 Independent Spent Fuel Storage Installation The Independent Spent Fuel Storage Installation (ISFSI) is a fenced, secured area north northwest of CGS. Ten TLD stations, stations 123-129 and stations 136A-138A, are located on the second of three security fences that surround the ISFSI. TLD station 122 is just north of the ISFSI between the ISFSI and the plant access road. TLD station 121 is located approximately 0.1 mile north of the plant between the Transformer Yard and the ISFSI. Refer to Figure 4-4 for ISFSI TLD locations.

Radiological exposure rates inside the ISFSI security fence line are elevated and access to the area requires radiological dosimetry and security notification. In addition to the TLD monitoring program, quarterly radiological surveys of the ISFSI are conducted by the CGS Radiation Protection Department.

Trend of Exposure Rates at ISFSI Fence Line 2.6 2.2 E 1.4-1.0_

'07 'QO '07ý 9? 'Q ?'QO 7 9O V7 'QO 'QQO V7~ '9? V'QO 'Q' '9? V'Q 'Q?'0 '9? IQ'PO a-125 --- 126 -- 127 .. 128 -- o-129 -+/-:136A - 137A -138A -o-123 &124 Figure 5-9 ISFSI TLD Trend at CGS 2013 Annual Radiological Environmental Operating Report 5-11 Energy Northwest/Columbia Generating Station

I No new spent fuel or additional storage casks. were added to::the ISFSI during 2013. As shown in I Figure 5-9, exposure rates at the ISFSI fence line have followed a downward trend since 2008.

Station 122 TLD results show a similar pattern with the long term trend for this location correlating to the overall ISFSI TLD trend but at a lower level. Station 12 1 TLD trend results show large I decreases during periods when CGS was shut down; this location has historically been influenced more by. turbine building radiation levels than by the ISFSI (See Table 5-3 and Appendix A, Tables B-

1. 1, 13-1.2). I 5.9.6 Additional Air Sample and TLD Locations Four air sample locations (Stations 87-90) and 5 TLD stations (Stations 58, 87-90) were established in I

2008/2009 in order to monitor air quality and direct radiation during remediation work at the DOE 618-11 burial ground located just west of CGS (See Figure 4-1). No air samples were taken from these locations in 2013 as no work was performed at the 618-11 site that had the potential of impacting CGS.

I Quarterly TLDs were exchanged at all five locations in 2013. Three of the TLD stations (stations 87-89) had results higher than background due to the stations close proximity to the turbine building (See Appendix A, Table B- 1.1).

I 5.10 2013 Sample Deviations I A summary of REMP sample deviations encountered during 2013 is listed below in Table 5-1 a. All known deviations from the sampling schedule (i.e. sample was not obtained) or analyses where the ODCM specified lower limit of detection was not achieved are included. For locations where composite I

or continuous samples are collected, any known period greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during which samples were not collected have been included. Not all locations listed in Table 5-1a are required by the ODCM or EFSEC resolutions. Table 5-lb lists information regarding air sample station sampling requirements.

I TABLE 5-1a I

SAMPLE DATE LOCATION REMP Sample Deviations for 2013 CR ID PROBLEM / COMMENTS I

MEDIA Air Sampler 4/3/13 to 4/9/13 Station 1

[Pump found off with blown fuse, station OOS for- 6 282272 days. Station returned to service after pump replaced.

I INo sample collected, LLD requirements not met.

Air Sampler 5/29/13 to 5/30/13 Station 57 Station OOS for - 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> due to power outage.

286627 Station back in service when power restored. Sufficient sample volume obtained to meet LLD.

I Air Sampler 7/14/13 to 7/16/13 Station 48 Pump found off with blown fuse, Station OOS for - 41 290058 hours. Fuse replaced, pump restarted. Sufficient sample volume obtained to meet LLD.

I 8/19/13 Station OOS for -9.5 days due to power outage. No Air Sampler to 8/28/13 Station 23 292376 sample collected or LLD meet week of 8/20 to 8/27.

Station back in service after power restored.

I I

5 2013 Annual Radiological Environmental Operating Report 5-12 Energy Northwest/Columbia Generating Station I

TABLE 5-1a (cont)

REMP Sample Deviations for 2013 SAMPLE DATE LOCATION CR ID PROBLEM / COMMENTS MEDIA 1/14/.13 Composite sampler OOS for - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during planned Water to Station 29 277478 maintenance activities. Sampler returned to service and 1/15/13 1verified operable.

Circ water blow down samplers CBD-SR- 1 and 2 inoperable due to no signal from CW-LCV-1, blow 284853 down performed using temporary pumps. Daily grab 5/13/13 285305 samples taken 5/20 to 5/25. CBD-SR-1 and 2 declared Water to Station 27 285021 operational 5/25 following logic circuit modification.

5/31/13 286652 On 5/31, samplers determined not to be functional due to no valid flow indication signal and samplers -in proportional mode. Samplers placed in timed mode and verified operable on 5/31.

On 7/8, TMU-SR-1 determined to have been OOS since 6/30 when sample supply pump was taken out of.

288978 service. Daily grab samples taken 7/10 to 7/15. A 6/30/13 289504 temporary sampler was installed on 7/12 and Water to Station 26 291368 continuous composite sampling initiated. Temporary 7/12/13 294453 composite sampler in service until 1'2/9/13. TMU-SR-1 297177 returned to service on 12/7/13 following adjustments to samplesupply pump. Procedure revised to identify PWC-P-5 supplies water to TMU-SR- 1.

9/2/13 In service Circ. water blow down sampler CBD-SR-1 WaterWtrto 921 Statdeclared non-functional on 9/3. CBD-SR-2 placed in Station 27 293107 service and verified operational. Samplers estimated to 9/3/13 have been OOS for 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />..

9/29/13 LCO Circ water blow down samplers CBD-SR-1 and 2 Water 1Wtro9to Station 227 St LCO declared non-functional due to planned power outage.

10/3/13 Log 16673 Samplers returned to service and verified operable when power restored. Sample racks OOS for 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br />.

TMU temporary composite water sampler found 11/20/13 without power on 11/25, sampler last confirmed Water to Station 26 298462 operational on 11/20. Investigation found GF1C circuit 11/26/13 was tripped. Power restored and sampler verified

-operable.

Only 2 of the 3 required fish species were obtained Stations 30 from the control and indicator locations. ENW was not Fish Annual 300634 permitted to use electroshock fishing techniques in and 38 2013. Permission to electroshock or other means of fish collection is to be investigated. .

7/1/13 All Environmental TLDs were exchanged 2 weeks late due TLD to ll 289107 to issue obtaining TLDs from vendor. Contract issues 7/17/13 Locations . causing delay resolved.

2013 Annual Radiological Environmental Operating Report 5-13 Energy Northwest/Columbia Generating Station

I Table 5-lb below shows the percent time in service for the 12 air sample locations. The table shows I

that overall availability was greater than 99% for all ODCM required locations.

I TABLE 5-1b CGS REMP Air Sample Percent in Service Time for 2013 I Station ID ODCM Required EFSEC Required Percent Time in Service 1

4 x x

x 98.2%

99.8% I 5 99.8%

6 7

x x

99.9%

99.8%

I 8 x x 99.9%

9 21 x x 99.9%

99.7%

I 23 x 97.2%

40 48 x

x x

x 99.8%

99.2%

I 57 x 99.6%

I I

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U i

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2013 Annual Radiological Environmental Operating Report 5-14 I

Energy Northwest/Columbia Generating Station

TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 mR/std.

Medium: Environmental Direct Radiation TLD) Units: quarter Location With Highest Annual Total Lower Limit of Indicator Locations Mean Control Locations Number of Analysis Type Analyses Detection Mean (f)a Location Mean (f)a Mean (f)' Nonroutine Performed (LLD) Range Location Information Man

.Range Range Measurements TLD Quarterly 228 21.5 (224 / 224) 86 27.9 (4/4) 20.5 (4/4) 0 (18.2-29.7) NNW 0.3 miles (26.0-29.7) (18.9-21.7)

a. (f) is the number of positive measurements I total measurements at specified location.

Reference Appendix A, Tables A-1.1, A-1.2 TABLE 5-2 (cont)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 mR/std.

Medium: ISFSI Direct Radiation (TLD) Units: quarter Indicator Location With Highest Annual Total Lower Limit Mean Control Locations Number of Analysis Type Analyses of Detection Locations Mean (f)- Nonroutine Performed (LLD) Range Information Range Range Measurements 109.9 (40 / 40) 137A 146.4(4/4) --- (0/0)

TLD Quarterly 401 (67.9-148.3) NNW 0.24 miles (142.1-148.3)

a. (f) is the number of positive measurements / total measurements at specified location.

Reference Appendix A, Tables B-1.1, B-1.2 ISFSI TLDs are Stations 123 to 129 and 136A to138A 2013 Annual Radiological Environmental Operating Report 5-15 Energy Northwest/Columbia Generating Station

U I

TABLE 5-2 (cont)

I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION Benton County, Washington DOCKET NO. 50-397 Calendar Year 2013 I

Medium: Air Particulate/Air Radioiodine Total Lower Limit Indicator Units: PCi/m Location With Highest Annual Mean 3

Control Locations Number of I

Analysis Analyses of Detection Locations (f)a Mean (f)' Nonroutine Type Performed (LLD)' Mean (f nLocation I

Meange Range Measurements Range Information Range 4

0.0218 (570/570) S 0.0239 (52/52) 0.0189(52/52)

Gross Beta 622 0.01 (0.00299-0.139) SSE 9.57 miles (0.00409 - 0.125)

I (0.00322 - 0.106) 1-131 622 0.07 --- (0 / 570) --- --- (0 / 52) 0 Cs-134 48 0.05 --- (0/44) --- --- (0/4) 0 I

Cs-137 48 0.06 --- (0/44) --- (0/4) 0

a. (f) is the number of positive measurements / total measurements at specified location.
b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.

I Reference Appendix A, Tables A-2.1, A-2.2, Tables A-3.1, A-3.2, and Tables A- 4.1, A-4.2.

I I

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I 2013 Annual Radiological Environmental Operating Report 5-16 Energy Northwest/Columbia Generating Station I

TABLE 5-2 (cont)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING. STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: Water-River/Drinking Units: pCi/L Total Lower Limit Indicator Location With Highest Annual Mean Analysis Analyses of Detection Locations Control Locations Number of Type Performed (LLD)'c Mean (f)0 Location Mean (f)R Mea surem Range Information Range Range Measurements Gross Beta 24 4.0 --- (0 / 24) -b) --- --- (0/12) 0 H-3 8 2000 --- (0 8 )(b) - --- --- (0/4) 0 Mn-54 24 15 --- (0/ 24 )(b) --- (0/12) 0 Fe-59 24 30 --- ( 0 / 2 4 )(b) --- --- (0/12) 0 Co-58 24. 15 --- (0/ 24 )(b- --- --- (0 / 12) 0 Co-60 24 15 --- ( 0 / 2 4 )(b) --- (0/12) 0 Zn-65 24 30 --- ( 0 / 2 4 )(b) --- (0/12) 0 Zr/Nb-95 24 15 --- (0 / 2 4 )(b) --- --- (0 / 12) 0 Cs-134 24 15 --- (0 / 2 4 )(b) --- --- (0 / 12) 0 Cs-137 24 18 --- (0/ 24 ) b) --- --- (0 / 12) 0 Ba/La-140 24 15 --- (0 / 2 4 ) (b) --- --- (0 / 12) 0

a. (f) is the number of positive measurements / total measurements at specified location.
b. This includes the control sample for this group; the control (Station 26) is also a drinking water sample.
c. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.

Reference Appendix A, Tables A-5.1,A-5.2, Tables A-6.1, A-6.2, and Tables A-7.1, A-7.2 2013 Annual Radiological Environmental Operating Report 5-17 Energy Northwest/Coluinbia Generating Station

TABLE 5-2 (cont)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: Water-Discharge Units: pCi/L Indicator Location With Highest Annual Mean Analysis Total Lower Limit Locations Control Locations Number of Type Analyses of Detection a Location Mean (0a Mean (f)0 Nonroutine (LLD) b RPerformed ange Information Range Range Measurements Gross Beta 12 4.0 5.83 (10 /12)

(1.2-11.8) E 3.227miles 5.83 (10 /12)

(1.2-11.8)) ---(0/0) 0 H-3 4 2000 --- (0/4) --- --- (0/0) 0 Mn-54 12 15 --- (0/12) --- --- (0/0) 0 Fe-59 12 30 --- (0/12) - --- --- (0/0) 0 Co-58 12 15 --- (0/12) --. --- (0/0) 0 Co-60 12 15 --- (0/12) --- --- (0/0) 0 Zn-65 12 30 --- (0/12) --- --- --- (0/0) 0 Zr/Nb-95 12 15 --- (0 / 12) --- --- --- (0/0) 0 Cs-134 12 15 --- (0/12) --- --- (0/0) 0 Cs-137 12 18 --- (0/12) --- --- --- (0/0) 0 Ba/La-140 12 15 --- (0/12) ...--- 1- (0/0) 0

a. (f) is the number of positive measurements / total measurements at specified location.
b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.

Reference Appendix A, Tables A-5.1,A-5.2, Tables A-6.1, A-6.2, and Tables A-7.1, A-7.2 Report 5-18 Energy Northwest/Columbia Generating Siation 2013 2013 Annual Environmeniat Operating Radiological Environmental Annual Radiological Operating Report 5-18 Energy Northwest/Columbia Generating Station

TABLE 5-2 (cont)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: Water- Deep Ground Units: pCi/L Location With Highest Annual Mean Analysis Aaye Total ofettin Lower Limit Locations.CotoLoain Indicatorns Nubrf Analyses of Detection Mean (f Location Mean (f)0 Mean (f)' Nonroutine Type Performed (LLD)b Range Information Range Range Measurements H-3 12 2000 --- (0/12) --- - (0 /0) 0 Mn-54 12 15 --- (0/12) --- ---(0/0) 0 Fe-59 12 30 --- (0/12) --- (0/0) 0 Co-58 12 15 --- (0/12) --- (0/0) 0 Co-60 12 15 --- (0/12) ------ (0/0) 0 Zn-65 12 30 --- (0/12) --- --- (0/0) 0 Zr/Nb-95 12 15 --- (0/12) --- (0/0) 0 Cs-134 12 15 --- (0/12) --- --- --- (0/0) 0 Cs-137 12 18 --- (0/12) --- (0 / 0) 0 Ba/La-140 12 15 --- (0 / 12) --- (0 / 0) 0

a. (f) is the number of positive measurements / total measurements at specified location.
b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.

Reference Appendix A, Tables A-6.1, A-6.2, and Tables A-7.1, A-7.2 Report 5-19 Energy North~vest./Columbia Generating Station 2013 Annual 2013 Environmental Operating Radiological Environmental Annual Radiological Operating Report 5-19 Energy Northwest/Columbia Generating Station

TABLE 5-2 (cont)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION. DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: Water- Shallow Ground Units: pCi/L Location With Highest Annual Mean Total Lower Limit Indicator Control Locations Number of Analysis Analyses of Detection .. Locations Type Performed (LLD) b LoMean (f )ean (f)R Mean Range Information Range Range(f) M Nonroutine Measurements H-3 40 2000 3777.7 (35 / 40) MW-5 15,100 (4/4) --- (0/0) 0 (177-15,420) SW 0.43 miles (14,900-15,400)

Mn-54 40 15 --- (0/40) --- --- --- (0/0) 0 Fe-59 40 30 --- (0 /40) --- --- (0/0) 0 Co-58 40 15 --- (0/40) --- --- --- (0/0) 0 Co-60 40. 15 --- (0/40) --- --- --- (0/0) 0 Zn-65 40 30 --- (0/40) --- --- --- (0/0) 0 Zr/Nb-95 40 15 --- (0/40) ------ (0/0) 0 Cs-134 40 15 --- (0/40) --- --- --- (0/0) 0 Cs-137 40 18 --- (0/40) --- --- --- (0/0) 0 Ba/La-140 40 15 --- (0/40) --- --- --- (0/0) 0

a. (f) is the number of positive measurements / total measurements at specified location.
b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.

Reference Appendix A, Tables B-10.1, B-10.2, and B-11.1.

2013 Annual Radiological Environmental Operating Report 5-20 Energy Northwest/Columbia Generating Station

TABLE 5-2 (cont)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: River Sediment Units: pCi/kg Indicator Location With Highest Annual Mean AnalysisLocations Total Lower Limit Control Locations Number of Analysis Analyses of Detection Mean (f]I Nonroutine Type Performed (LLD) b Mean (f)M Location Mean (f)a Range Measurements Range Information Range Cs-134 4 150 --- (0/2) - --- (0/2) 0 Cs-137 4 180 121 (2/2) 34 121 (2/2) 42.2(1/2) 0 (121-122) ESE 3.32 Miles (121-122) (34.6-49.8)

Co-60 4 --- --- (0/2) --- --- (0/2) 0

a. (f) is the number of positive measurements / total measurements at specified location.
b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.

Reference Appendix A, Tables A-9.1, A-9.2.

2013 Annual Radiological Environmental Operating Report 5-21 Energy Northwest/Columbia Generating Station

I I

TABLE 5-2 (cont) .

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

I COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calender Year 2013 I Medium: Roots Units: pCi/kg Analysis Total Analyses Lower Limit of Detection Indicator Idcator L

Location With Highest Annual Mean Control Locations Mean (f)a Number of Nonroutine I

Type Performed (LLD) b Mean (f)' Location Mean (f)I Range Measurements 1-131 6 60 Range

--- (0/5)

Information Range (0/1) 0 I

Cs-134 6 60 --- (0/5) --- --- --- (0/1) 0 i Cs-137 6 80 --- (0/5) --- (0/1) 0

a. (f) is the number of positive measurements / total measurements at specified location. I
b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.

Reference Appendix A, Tables A-15.1, A-15.2.

TABLE 5-2 (cont)

I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION Benton County, Washington DOCKET NO. 50-397 Calendar Year 2013 I

Medium: Fruits Units: pCi/kg Location With Highest Annual Mean i

Total Lower Limit ndcator Control Locations Number of Type Analyses Performed of Detection (LLD) b Mean (f)0Locations Location Range Information Mean (f)g Range Mean (f)

Range MNonroutine Measurements I 1-131 Cs-134 9

9 60 60

--- (0/8)

--- (0/8)

--- (0/1)

--- (0/1) 0 0

I Cs-137 9 80 --- (0/8) ..---

a. (f) is the number of positive measurements / total measurements at specified location.

--- (0/1) 0 I

b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.

Reference Appendix A, Table A-16.1, A-16.2. I I

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2013 Annual Radiological Environmental Operating Report 5-22 Energy Northwest/Columbia Generating Station I

TABLE 5-2 (cont)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: Vegetables and Vegetation Units: pCi/kg Location With Highest Annual Mean Analysis Total Lower Limit Indicator Locations Control Locations Number of Type Analyses of Detection Mean (f)a Location Mean (f)' Mean (f)a Nonroutine Performed (LLD) b Range Information Range Range Measurements 1-131 12 60 --- (0/11) --- (0/1) 0 Cs-134 12 60 --- (0/11) --- --- --- (0/1) 0 Cs-137 12 80 --- (0/11) --- (0/1) 0

a. (f) is the number of positive measurements / total measurements at specified location.
b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.

Reference Appendix A, Table A-17.1, A-17.2.

TABLE 5-2 (cont)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2013 Medium: Fish Units: pCilkg Location With Highest Annual Mean Analysis Total Lower Limit Indicator Locations Control Locations Number of Location Mean (f)a Mean (f) Nonroutine Type Analyses Performed of (LLD)

Detection Range(f)'

Mean b (LDbInformation Range Range Measurements Mn-54 4 130 --- (0/2) --- (0/2) 0 Fe-59 4 260 --- (0/2) --- --- --- (0/2) 0 Co-58 4 130 --- (0/2) --- --- --- (0/2) 0 Co-60 4 130 --- (0/2) --- --- --- (0/2) 0 Zn-65 4 260 --- (0/2) --- --- (0/2) 0 Cs-134 4 130 --- (0/2) --- --- --- (0/2) 0 Cs-137 4 150 10.6(1/2) 30 10.6(1/2) --- (0/2) 0 (2.19-19.1) E 3.5 miles (2.19-19.1)

a. (f) is the number of positive measurements / total measurements at specified location.
b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4.

Reference Appendix A, Table A-10.1, A-10.2.

2013 Annual Radiological Environmental Operating Report 5-23 Energy Northwest/Columbia Generating Station

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TABLE 5-2 (cont)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

I COLUMBIA GENERATING STATION Benton County, Washington DOCKET NO. 50-397 Calendar Year 2013 I Medium: Milk Analysis Total Analyses ofLower Limit Indicator Locationst Detection Man (

Units: pCi/L Location With Highest Annual Mean Control Mean Locations (f)* Number of Nonroutine I

Type Aaye Performed ofDtcin Ma(f Location Mean (f age Masrmet (LLD) b Range oationRange Range 1-131 36 1.0 --- (0/18)

Information

---(0/18)

Measurements 0

I Cs-134 36 15 --- (0/18) --- --- --- (0/18) 0 I Cs-137 Ba/La-140 36 36 18 15

--- (0/ 18)

--- (0/18)

--- (0/18)

--- (0 / 18) 0 0

I

a. (f)is the number of positive measurements / total measurements at specified location.
b. These are the ODCM specified LLDs, actual method LLDs will be lower. See Table 4-4. I Reference Appendix A, Tables A-1 1.1, A-1 1.2, Tables A-12.1, A-12.2.

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I 2013 Annual Radiological Environmental Operating Report 5-24 Energy Northwest/Columbia Generating Station I

TABLE 5-3 QUARTERLY TLD DATA

SUMMARY

WITH COMPARISON TO PREOPERATIONAL AND OPERATIONAL PERIODS Results in mR!Standard Quarter Pre-OPerational Operational to 2012 2013 Operational Station Mn Max StdDev MEAN Mn Max StdDev MEAN min max StdDev MEAN 1 19.16 23.73 2.07 21.90 18.25 27.38 1.66 22.13 21.32 22.75 0.61 22.10 2 17.34 22.81 2.09 21.10 16.43 25.55 1.56 21.64 19.88 22.16 1.04 21.40 3 18.25 21.90 1.46 20.42 16.43 24.64 1.69 20.86 19.12 21.36 1.03 20.36 4 15.51 23.73 2.65 19.96 14.60 22.81 1.67 *. 19.56 18.50 19.89 0.66 19.14 5 18.25 22.81 1.74 20.76 16.43 23.73 1.64 20.04 18.67 20.16 0.62 19.51 6 18.25 21.90 1.50 20.19 16.43 23.73 1.56 20.17 18.64 19.86 0.50 19.23 7 19.16 22.81 1.69 21.33 16.43 24.64 1.71 21.09 20.05 21.37 0.74 20.71 8 21.90 25.55 1.50 23.84 15.51 27.38 1.95 23.26 22.46 23.82 0.68 23.18 9 15.51 21.90 2.00 19.85 16.43 23.73 1.67 19.76 18.92 21.66 1.15 20.53 10 19.16 22:81 1.38 _ 20.99 16.43 24.64 1.65 20.96 19.50 21.37 0.96 20.38 11 19.16 22.81 1.38 21.44 16.43 24.64 1.47 21.55 20.24 21.74 0.65 21.01 12 20.99 24.64 1.60 23.04 18.25 26.46 1.70 23.14 21.61 23.80 1.04 22.63 13 19.16 22.81 1.54 , 21.44 17.34 27.38 1.78 21.32 19.89 21.43 0.87 20.67 14 19.16 24.64 2.07 21.90 17.34 25.55 1 1.50 21.47 20.24 21.72 0.78 20.96 15 20.99 25.55 1.37 23.15 17.34 27.38 1.69 23.05 21.29 23.82 1.05 22.44 16 20.08 23.73 1.52 22.13 16.43 26.46 1.79 21.95 19.92 22.71 1.24. 21.32 17 19,16 23.73 1.62 22.81 17.34 26.46 1.60 22.51 20.80 23.73 1.23 22.51 18 20.08 23.73 1.27 22.13 16.43 25.55 1.66 22.00 21.05 23.49 1.06 22.58 19 20.08 23.73 1.24 22.01 17.34 25.55 1.57 22.15 21.15 23.19 0.91 22.37 20 19.16 23.73 1.76 21.44 17.34 25.55 1.63 21.80 20.08 22.57 1.25 21.51 21 19.16 21.90 1.25 20.68 15.51 23.73 .1.43 20.32 18.93 20.61 0.81 19.76 22 19.16 23.73 1.58 22.01 16.43 25.55 1.49 21.73 19.97 21.76 0.93 20.88 23 20.08 23.73 1.49 21.60 17.34 25.55 1.62 21.15 19.68 22.23 1.11 21.08 24 20,99 23.73 1.09 . 21.90 17.34 50.50 3.19 22.10 20.13 22.24 0.97 21.13 25 20,99 . 24.64 1.46 23.15 17.34 27.38 1.91 22.76 21.44 24.88 1.46 22.80 40 17.34 21.90 1.70 19.94 , 15.51 24.64 1.74 20.05 18.18 19.42 0.55 18.88 41 20.08 25.55 2.00 23.73 17.34 27.38 2.03 22.44 20.46 22.72 0.97 21.35 42 20.08 23.73 1.61 . 22.36 17.34 26.46 1.93 21.98 20.01 21.41 0.65 20.73 43 20,99 24.64 1.49 23.12 16.43 27.38 2.12 22.60 21.14 22.84 0.72 21.85 44 19.16 22.81 1.34 21.12 15.51 24.64 1.95 20.80 19.36 20.06 0.30 19.73 45 19.16 22.81 1.37 21.25 16.43 25.55 1.80 21.18 18.85 21.39 1.06 20.01 46 22,81 28.29 2.10 26.10 19.16 31.94 2.14 26.49 24.74 27.33 1.27 26.26 47 17.34 20.99 1.73 . 19.85 15.51 26.28 1.71 20.23 18.59 20.38 0.91 19.47 49 21.90 21.90 - 21.90 16.43 25.55 1.55 21.92 19.97 22.18 1.06 21.25 50 20.08 20.08 20.08 16.43 26.46 1.75 21.60 19.54 22.28 1.16 20.80 51 19.16 21.90 1.18 20.53 16.43 24.64 1.62 21.08 19.56 21.39 1.02 20.48 53 24.64 24.64 - 24.64 18.25 29.57 2.04 23.36 20.17 21.59 0.58 20.88 54 23.73 23.73 23.73 18.18 26.46 1.98 22.07 20.30 22.80 1.19 21.40 55 20.99 20.99 20.99 16.43 25.55 1.49 21.45 20.01 22.24 0.93 21.28 56 21.90 21.90 21.90., 16.43 25.55 1.74 21.39 21.29 23.10 0.75 22.12 58 - 18.07 20.53 0.61 19.17 18.59 21.73 1.41 20.53 65 " 17.73 22.72 1.20 19.90 18.50 20.33 0.87 19.53 Report 5-25 Energy Northwest/Columbia Generating Station 2013 Annual 2013 Environmental Operating Radiological Environmental Annual Radiological Operating Report 5-25 Energy Northwest/Columbia Generating Station

I TABLE 5-3 (cont)

QUARTERLY TLD DATA

SUMMARY

WITH COMPARISON TO I PREOPERATIONAL AND OPERATIONAL PERIODS Pre-Operational Results in mR/Standard Quarter I

Operational to 2012 2013 Operational Station 71(1S) 72(2S)

Min 20.08 21.90 Max 22.81 23.73 Std Dev MEAN 1.58 0.91 21.90 22.81 Min 18.25 18.25 Max 30.39 29.65 Std Dev MEAN 2.45 1.96 25.26 24.33 min 22.52 21.65 max 26.85 26.04 Std Dev MEAN 2.06 1.89 24.76 24.08 I

73(3S) 74(4S) 75(5S) 20.08 23.73 19.16 21.90 24.64 21.90 0.91 0.53 1.39 20.99 24.03 20.38 16.43 18.25 15.51 24.64 28.29 26.46 1.54 1.87 1.85 21.25 23.38 22.29 19.70 1 23.94 21.56 21.19 24.51 23.14 1.84 1.52 0.95 21.77 23.10 22.22 I

I 76(6S) 20.99 22.81 0.91 21.90 17.34 26.46 1.69 22.04 20.29 22.83 1.07 21.37 77(7S) 21.90 23.73 0.91 22.81 17.34 25.55 1.59 22.02 20.29 22.55 0.94 21.46 78(8S) 21.90 23.73 1.05 22.51 17.34 25.55 1.56 21.51 20.30 21.79 0.65 20.99 79(9S) 22.81 23.73 0.53 23.12 17.34 25.55 1.63 21.85 20.40 22.54 1.05 21.40 80(10S) 81(11S) 20.99 20.08 22.81 23.73 0.91 1.90 21.90 22.20 16.43 17.34 25.55 25.55 1.74 1.52 20.99 21.52 19.72 19.96 22.41 21.89 1.15 0.91 21.24 20.65 I

82(12S) 21.90 24.64 1.39 23.42 17.34 26.46 1.55 22.42 21.07 23.05 0.94 22.19 83(13S) 84(14S) 21.90 20.99 23.73 22.81 0.91 1.05 22.81 22.20 17.34 16.43 26.46 27.17 1.84 1.76 22.29 22.26 20.35 20.52 22.51 24.25 0.90 1.77 21.42 22.14 I

85(15S) 21.90 24.64 1.58 23.73 17.34 27.83 1.87 23.09 21.48 24.17 1.17 22.67 86(16S) 87 88 21.90 23.73 0.91 22.81 18.25 19.34 17.05 31.28 34.34 31.67 2.61 4.76 4.18 26.16 28.82 26.08 26.04 23.74 20.91 29.71 32.32 26.25 1.70 3.53 2.36 27.91 28.34 I 24.24 89 90 119B 19.25 18.26 19.24 29.38 20.48 25.64 2.85 0.57 1.46 25.92 18.95 22.13 22.83 17.53 20.24 27.62 19.56 23.26 2.17 0.96 1.30 25.59 18.85 21.87 I

119Ctrl 120East 121 (ISFSI) 19.53 19.78 19.52 26.55 31.12 130.27 1.38 1.81 23.63 21.83 22.43 76.58 20.53 20.99 44.90 23.46 23.70 71.44 1.28 1.38 11.99 22.08 22.31 62.36 I

122 (ISFSI) - 19.62 42.49 7.28 U

30.98 32.30 35.74 1.68 34.26 123 (ISFSI) - 24.99 160.33 38.26 116.91 103.88 111.07 3.66 107.91 124 (ISFSI) - 26.89 201.05 48.67 144.92 120.51 130.90 4.81 124.68 125 (ISFSI) - 26.46 135.52 29.35 102.63 91.21 96.33 2.19 93.25 126 (ISFSI) 127 (ISFSI) 26.00 28.97 145.68 102.08 32.15 19.71 85.18 66.18 90.80 67.89 97.65 73.92 2.80 2.84 94.20 72.12 U

128 (ISFSI) - 25.64 187.25 48.29 100.11 114.89 122.42 3.47 117.86 129 (ISFSI) 136A (ISFSI 137A (ISFSI 30.16 28.99 29.47 138.08 205.64 238.74 33.14 62.50 71.26 79.99 101.87 112.61 88.01 129.75 142.11 93.64 137.21 148.32 2.54 3.49 2.92 91.70 132.57 146.44 I

138A (ISFSI Site 1 Site 4 28.28 11.92 17.02 196.68 20.19 32.44 54.19 1.43 2.80 93.08 18.16 18.94 113.80 17.74 17.27 121.21 19.52 19.68 3.09 0.77 1.18 118.02 18.48 19.03 I

Table 5-3 Notes:

The preoperational mean is from 1982-1983 data. Station 65 was added in 1997.

I Stations 119B, 119Ctd, and 120 were added in 1995. Stations 121 and 122 were added in 1998 for the ISFSI.

Stations 123-129 and 136A-138A were added in the 2nd quarter of 2002. Stations Site 1 and Site 4 were added in 2006.

Stations 58 and 87 to 90 were added in 2008 to monitor remediation work at DOE 618-11 burial site.

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2013 Annual Radiological Environmental Operating Report 5-26 Energy Northwest/Columbia Generating Station I

6.0 QUALITY ASSURANCE AND QUALITY CONTROL 6.0 QUALITY ASSURANCE AND QUALITY CONTROL The REMP is designed to meet the quality assurance (QA) and quality control (QC) criteria of the NRC Regulatory Guide 4.15 7)and 10 CFR 50 Appendix B1 15). The contractors used for sample analysis, Energy Northwest Environmental Services, and Mission Support Alliance, maintain quality control programs to ensure that analytical results are accurate, precise, and defensible. The following sections summarize the quality assurance and quality control aspects of the TLD, sample collection, and sample analysis components of the REMP.

6.1 Quality Control for the Energy Northwest Environmental TLD Program The Quality Control program for the environmental TLD program covers the preparation, transportation, deployment, collection, storage, processing, and evaluation of the environmental TLDs and is designed to meet the requirements of NRC Regulatory Guides 4.13(8) and 4.15. (7 From the time the TLDs are annealed to the time they are placed in the field, they are stored and transported with control TLDs. Two sets of control TLDs are used, the building controls and the transportation (trip) controls. The building controls monitor the exposure that the TLDs receive while being transported to and from the TLD vendor and while in storage awaiting deployment and analysis.

The trip controls accompany the field TLDs when transported to and from the vendor and also during deployment and collection in the field. The building controls and trip controls are stored in a low background lead shield while the field TLDs are deployed. If the trip control results are greater than the building control results, the difference between the two is subtracted from the field dosimeters to account for exposure during transit.

Reader QC dosimeters serve as checks that the dosimeter reader calibration is satisfactory and that the TLDs were processed correctly. These TLDs are annealed and then given a known exposure (typically 100 mR) to a cesium-137 source. The number of QC dosimeters used during each processing is generally 10% of the number of field dosimeters. Evaluation of the 2013 reader QC dosimeter results indicated satisfactory agreement for all periods. The quarterly average reader QC results are presented in Table 6-1.

TLDs designated as spikes are prepared by the Energy Northwest Radiation Protection Department by exposing the TLDs to a calibrated source to produce a known exposure. The spiked dosimeters are submitted and processed with the field dosimeters to further verify the accuracy and precision of the environmental TLD results. Quarterly spikes receive a target exposure of 22 mR. Evaluation of the 2013 spiked dosimeter results indicated satisfactory agreement for all periods. Spiked TLD results are presented in Table 6-1.

6.2 Quality Control for the Environmental Sample Program Quality control for the environmental sample program encompasses both the sample collection and sample analysis processes. Results are reviewed for correctness, reasonableness, and data entry errors.

Sample results that are suspect are normally investigated. A crosscheck program utilizing blind samples supplied by an outside vendor is maintained for all sample media routinely analyzed.

2013 Annual Radiological Environmental Operating Report 6-1 Energy Northwest/Columbia Generating Station

I 6.2.1 Sample Collection Quality Control I Duplicate samples are collected and submitted for analysis when practical. The duplicate samples are used to assess the repeatability of the sample collection process and the precision of the analytical method.

I 6.2.2 Laboratory Instruments Quality Control 3 Analytical Balances - Analytical balances used in the laboratory for sample preparations are calibrated every six months. Performance checks are performed prior to use and span the range of intended use. Performance check results are documented on the sample preparation forms and kept with the analytical results.

Analytical Instruments - Analytical instruments used for determining radioactive emissions in samples are calibrated for efficiency annually using standard reference material traceable to the I

National Institute of Standards and Technology (NIST). Below is a summary of the routine QC practices for the different analytical instruments.

  • Gas-flow Proportional Counter: Background and performance checks are performed daily when in use. Control charts are maintained with two and three-sigma limits specified; the checks must fall within the two-sigma warning limits prior to use. Mid-batch QC and end of batch performance checks are typically performed.
  • Gamma Spectrometers: Performance checked daily for efficiency, energy per channel relationship, peak resolution, and background when in use. The checks are performed and plotted for both a low and high energy peak.. Efficiency checks are held within two-sigma control limits. Long duration background checks are performed quarterly. A low level batch QC check is typically analyzed with each set of samples.
  • Liquid Scintillation Counter: Background and performance checks are performed daily when in use. A performance check standard of the same matrix as the samples is analyzed and results trended. A control chart with acceptance limits specified is maintained. A low level batch QC check is typically analyzed with each set of samples.

6.2.3 Sample Batch Quality Control Sample batch analysis is normally performed with sample blanks and known-addition samples (or i spiked samples) included. The type of known addition sample used is dictated by the sample media being analyzed, the primary analytes of interest, and the method being used. The following is a summary of sample batch QC activities.

Iodine-131 Cartridges - At least one known-addition sample is analyzed with each batch. A charcoal cartridge of the same type used for sample collection but spiked with barium-133 is used.

The 356 keV peak of barium-133 serves as a proxy for the 364 keV peak of iodine-131. Samples from the control location serve as blanks. i Gross Beta Filters - At least one unused blank air particulate filter and at least one known-addition air particulate filter is analyzed with each batch. 3 Aqueous Samples - In most cases, samples collected from the control locations are analyzed as blanks. A known-addition sample is typically analyzed with each batch of samples. i 2013 Annual Radiological Environmental Operating Report 6-2 Energy Northwest/Columbia Generating Station I

Gross Alpha/Beta in Water - Blank samples were prepared from reagent grade water and analyzed with each batch of samples. One known addition sample and one replicate sample is normally analyzed with each batch.

Tritium in Water - A blank and a low level known addition sample is typically analyzed with each batch. A replicate sample is prepared and analyzed inside of each batch in most cases.

6.3 Laboratory Intercomparison Program Participation and Results Participation in cross check intercomparison studies is mandatory for' laboratories performinig analyses of CGS REMP samples. Intercomparison studies provide a consistent and effective means to evaluate the accuracy and precision of analyses performed by a laboratory. Study results should fall within specified control limits. Results that fall outside the control limits are investigated and corrective action taken.

The Energy Northwest Environmental Services Laboratory participated in three proficiency testing studies involving radioactive measurements provided by Environmental Resource Associates (ERA) during 2013. The Laboratory's intercomparison program was further supplemented by additional cross check media provided by ERA. The Laboratory's intercomparison program results for 2013 are shown in Table 6-2. All 2013 Laboratory intercomparison program results were within acceptable limits. Participation in the ERA studies serves to meet the intercomparison program requirements specified in the ODCM.

In addition to the studies noted above, the CGS REMP maintains a split sample program with the State of Washington Department of'Health. Split samples are sent to a State of Washington Lab on a scheduled frequency where they are independently analyzed. This program provides an additional check on the accuracy and precision of the results reported in this document.

6.4 Laboratory Quality Control Program Problems and Improvements No issues with REMP sampling and analyses were identified by the QC and intercomparison programs in 2013.

Operating Report 6-3 Energy Northwest/Columbia Generating Station 2013 Radiological Environmental Annual Radiological 2013 Annual Environmental Operating Report 6-3 Energy Northwest/Columbia Generating Station

I TABLE 6-1 2013 ENVIRONMENTAL SPIKED DOSIMETER.RESULTS I KNOWN

-EXPOSURE REPORTED EXPOSURE I PERIOD SPIKE ID (mR) (mR) BIAS (%)

1st Quarter ENW Spike 22 21.6 -1.8%

I ENW Spike 22 21.2 -3.6%

ENW Spike PNNL Avg. Reader 22 100 21.2.

99.1

-3.6%

-0.9% I 2nd Quarter ENW Spike ENW Spike 22 22 21.5 21.1

-2.3%,

-4.1%

I ENW Spike 22 21.4 -2.7%

PNNL Avg. Reader 100 99.3 -0.1% I 3rd Quarter ENW Spike ENW Spike 22 22 22.2 22.2 0.9%

0.9%

I ENW Spike 22 22.3 1.4%

PNNL Avg. Reader 100 100.8 0.8%

U 4th Quarter ENW ENW Spike Spike ,

ENW Spike 22 22, 22 21.8 21.5 21.9

-0.9%

-2.3%

-0.5%

I PNNL Avg. Reader 100 97.4 -2.6%

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2013 Annual Radiological Environmental Operating Report 6-4 Energy Northwest/Columbia Generating Station I

TABLE 6-2 ENW REMP PROGRAM: CROSS CHECK PERFORMANCE RESULTS ERA MRAD-18 Results Spring 2013 Reported Assigned Acceptance Performance StandardlAnalyte Units Value - Value Limits Evaluation Air Filter Radionuclides Americium-241 pCi/Filter 72 66.8 41.2-90.4 Acceptable -

Cesium-134 pCi/Filter 1047 1110 706- 1380 Acceptable Cesium-137 pCi/Filter 1173 940 706 - 1230 Acceptable Cobalt-60 pCi/Filter 246 214 166 - 267 Acceptable Zinc-65 pCi/Filter, 275 199 142 - 275 Acceptable Air Filter Gross Alpha/Beta Gross Alpha pCi/Filter 44 + 42.3 14.2 - 65.7 Acceptable Gross Beta pCi/Filter 21 25.1 :15.9 - 36.6 Acceptable Water Radionuclides Americium-241 pCi/L 117 118 79.5 - 158 Acceptable Cesium-134 pCi/L 1255 1400 1030-1610 Acceptable Cesium-1 37 pCi/L 1923 1880 1600 -2250 Acceptable Cobalt-60 pCi/L 2229 2270 1970 - 2660 Acceptable Zinc-65 pCi/L 418 384 320 -484 Acceptable Water Gross Alpha/Beta Gross Alpha IpCi/L 97 130 46.2 - 201 =Acceptable Gross Beta pCi/L 56 78.9 45.2 - 117 Acceptable Water Tritium Tritium pCi/L 11873 12300 8240 - 17500 Acceptable Soil Radionuclides Actinium-228 pCi/kq 1152 1240 795- 1720 Acceptable Bismuth-212 pCi/kg 1133 1240 330-1820 Acceptable Bismuth-214 pCi/kq 3035 3660 2200 - 5270 Acceptable Cesium-1 34 pCi/kg 6105 6370 4160- 7650 Acceptable Cesium-1 37 pCi/kg 6414 6120 4690- 7870 Acceptable Cobalt-60 pCi/kg 8089 7920 5360 - 10900 Acceptable Lead-212 pCi/kg 1162 1240 812 - 1730 Acceptable Lead-214 pCi/kq 3334 3660 2140 - 5460 Acceptable Potassium-40 pCi/kg 10890 10300 7520 - 13800 Acceptable Zinc-65 pCi/kg 1530 1400 1110 - 1860 Acceptable 2013 Annual Radiological Environmental Operating Report 6-5 Energy Northwest/Columbia Generating Station

I TABLE 6-2 (cont)

ENW REMP PROGRAM CROSS CHECK PERFORMANCE RESULTS I ERA MRAD-19 Results Fall 2013 Reported Assigned Acceptance Performance I

StandardlAnalyte Units Value- Value' Limits Evaluation Americium-241 pCi/Filter Air Filter Radionuclides 72 66.4 40.9 - 89:8 Acceptable I Cesium-134 pCi/Filter 811 868 552-1080 Acceptable Cesium-137 Cobalt-60 Manganese-54 pCi/Filter pCi/Filter pCi/Filter 734 556

< 10 602 494

< 50.0 452- 791 382 - 617 0.00- 50.0 Acceptable Acceptable Acceptable I

Zinc-65 Gross Alpha pCi/Filter

[pCi/Filter 573 419-Air Filter Gross Alpha/Beta 84 [ 83 300 - 578 J 27.8-129 [ Acceptable Acceptable I

1 Gross Beta Americium-241 pCi/Filter pCi/L 47 56.3 Water Radionuclides 102 126 35.6-82.2 84.9- 169 Acceptable Acceptable I

Cesium-1 34 Cesium-137 Cobalt-60 pCi/L pCi/L pCi/L 1987 2801 1869 2180 2760 1890 1600-2510 2340-3310 1640 - 2210 Acceptable Acceptable Acceptable I

Manganese-54 pCi/L < 20 < 100 0.00 - 100 Acceptable Zinc-65 pCi/L 1505 1370 Water Gross AlphalBeta 1140-1730 Acceptable I Gross Alpha pCi/L 88 96.6 34.3 - 150 Acceptable Gross Beta pCi/L 56 84.5 Water Tritium 48.4- 125 I Acceptable I Tritium pCi/L 1 19762 [ 19800 113300- 282001 Acceptable

,ctinium-228 pCi/kg Soil Radionuclides 1247 1240 795- 1720 Acceptable I

Bismuth-212 pCi/kg 983 1220 325 - 1790 Acceptable Bismuth-214 Cesium-1 34 pCi/kg pCi/kg 3593 2858 3740 2820 2250 - 5380 1840- 3390 Acceptable Acceptable I

Cesium-137 pCi/kg 4422 4130 3160- 5310 Acceptable Cobalt-60 Lead-212 pCi/kg pCi/kg 5819 1146 5680 1220 3840 - 7820 799- 1700 Acceptable Acceptable I

Lead-214 pCi/kg 3835 3740 2180 - 5580 Acceptable Manganese-54 Potassium-40 pCi/kg pCi/kg

< 100 10630

< 1000 12400 0.00 - 1000 9080 - 16700 Acceptable Acceptable I Zinc-65 pCi/kg 3686 3160 2520-4200 Acceptable I

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I 2013 Annual Radiological Environmental Operating Report 6-6 Energy Northwest/Columbia Generating Station I

TABLE 6-2 (cont)

ENW REMP PROGRAM CROSS CHECK PERFORMANCE RESULTS

.2013 ERA Crosscheck Result Iodine-131 Charcoal Cartridge Acceptance Performance Sample ID Analysis Units Result. Ref Value Limits Evaluation 03131390A Iodine-131 pCi/Filter 1174 1006 775-1328 Acceptable 09141205A Iodine-131 pCi/Filter 332 289 223 - 382 Acceptable 2013 ERA RAD Results Iodine-131 in Milk

___ _ Acceptance Performance Sample ID Analysis Units Result Ref Value Limits Evaluation RAD-94 Iodine-1 31 pCi/L 21.6 24.3 20.2-28.8 Acceptable 2013 Annual Radiological Environmental Operating Report 6-7 Energy Northwest/Columbia Generating Station

7.0 REFERENCES

7.0 REFERENCES

1. Energy Northwest, "Columbia Generating Station Final Safety Analysis Report," Section 2.3.1.1.
2. Nuclear Regulatory Commission Fact Sheet "Fact Sheet on Radiation Monitoring at Nuclear Power Plants and the "Tooth Fairy" Issue", NRC Library, www.nrc.gov/reading-rm/doc-collections/fact-sheets/.
3. The National Council on Radiation Protection and Measurements, 2006, "Cesium-137 in the Environment: Radioecology and Approaches to Assessment and Management", Report 154, NCRP, Bethesda, MD.
4. U.S. Nuclear Regulatory Commission, "Programs For Monitoring Radioactivity in the Environs of Nuclear Power Plants," Regulatory Guide 4.1, Revision 1, April 1975.
5. U.S. Nuclear Regulatory Commission, "Environmental Technical Specifications For Nuclear Power Plants," Regulatory Guide 4.8, December 1975.
6. U.S. Nuclear Regulatory Commission, "An Acceptable Radiological Environmental Monitoring Program," Assessment Branch Technical Position Revision 1, November 1979.
7. U.S. Nuclear Regulatory Commission, "Quality Assurance For Radiological Environmental Monitoring Program (Normal Operations), Effluent Streams and the Environment,"

Regulatory Guide 4.15, Revision 1, February 1979.

8. U.S. Nuclear Regulatory Commission, "Performance, Testing and Procedural Specifications For Thermoluminescence Dosimetry-Environmental Applications," Regulatory Guide 4.13, Revision 1, July 1977.
9. Energy Facility Site Evaluation Council, Resolution No. 332, approved February 21, 2012.
10. Energy Northwest Nuclear Columbia Generating Station, Operating License NPF-21, "Technical Specifications" Sections 5.5.1 and 5.6.1
11. Columbia Generating Station Offsite Dose Calculation Manual (ODCM).
12. Washington Administrative Code 173-200-040, "Water Quality Standards for Ground Water of the State of Washington - Criteria."
13. Washington Administrative Code 173-201A, "Water Quality Standards for Surface Waters of the State of Washington."
14. Code of Federal Regulations, Title 10 Part 20, "Standards for Protection against Radiation."
15. Code of Federal Regulations, Title 10 Part 50, "Domestic Licensing of Production and Utilization Facilities."

2013 Annual Radiological Environmental Operating Report 7-1 Energy Northwest/Columbia Generating Station

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16. Energy Facility Site Evaluation Council, Resolution No. 300, approved September 10, 2001.
17. Nuclear Energy Institute, "Industry Ground Water Protection Initiative - Final Guidance I

Document", NEI 07-07, Nuclear Energy Institute, 1776 I Street N. W., Suite 400, Washington D.C. I

18. Energy Facility Site Evaluation Council, Resolution No. 299, approved August 13, 2001.
19. PNNL, 2007, "Summary of Hydrogeology and Evaluation of Existing Groundwater I Monitoring Wells for Outfalls 002 and 003 at the Columbia generating Station", PNWD-3845, Pacific Northwest National Laboratory, Richland, WA.

I

20. PNNL, 2009, "Hanford Site Environmental Monitoring Report for Calendar Year 2008",

PNNL-18427, Pacific Northwest National Laboratory, Richland, WA

21. US DOE, 2013, "Hanford Site Environmental Report for Calendar Year 2012", DOE/RL-I 2013-18 Rev 0, US Dept. of Energy, Richland, WA
22. US DOE, 1995, "Hanford Site

Background:

Evaluation of Existing Soil Radionuclide Data",

I DOE/RL-95-55, US Dept. of Energy, Richland, WA.

23. PNNL, 2006, "Hanford Site Environmental Monitoring Report for Calendar Year 2005",

PNNL-15892, Pacific Northwest National Laboratory, Richland, WA i

24. Energy Northwest, 2012, "Soil and Vegetation Sampling Results of the Columbia I

Generating Station Storm Drain Pond For Samples Collected August 2011 ".

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2013 Annual Radiological Environmental Operating Report 7-2 Energy Northwest/Columbia Generating Station I

8.0 ERRATA 8.0 ERRATA Revisions to the 2012 Annual Radiological Environmental Operating Report for the Columbia Generating Station are listed below.

In Section 4.2, second paragraph, annual TLDs are incorrectly identified as being used to monitor exposure rates at the Independent Spent Fuel Storage Installation (ISFSI). No annual TLDs were used to monitoi this facility in 2012, only quarterly TLDs were used.

2013 Annual Radiological Environmental Operating Report 8-1 Energy Northwest/Columbia Generating Station

ENERGY NORTHWEST People. Vision. Solutions APPENDIX A 2013 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT COLUMBIA GENERATING STATION DATA TABLES A and B Covers Sample Collection Period Starting January 2013 Through December 2013 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Prepared by:

Energy Northwest - Environmental Services Staff Richland, WA

APPENDIX A - TABLE OF CONTENTS TABLE A: ROUTINE RESULTS A-1 .1 2013 Quarterly TLD Results A-1.2 2013 Quarterly TLD Results - Summary A-2.1 Gross Beta on Air Particulate Filters A-2.2 Gross Beta on Air Particulate Filters - Summary A-3.1 Gamma Spectrometry Results of Air Particulate Filters A-3.2 Gamma Spectrometry Results of Air Particulate Filters - Summary A-4.1 Gamma Spectrometry Results of Iodinel3l on Charcoal Filters A-4.2 Gamma Spectrometry Results of Iodinel3l on Charcoal Filters - Sunmary A-5.1 Gross Beta in Water A-5.2 Gross Beta in Water - Summary A-6.1 Tritium in Water A-6.2 Tritium in Water - Summary A-7.1 Gamma Spectrometry Results of Water A-7.2 Gamma Spectrometry Results of Water - Summary A-8.1 Gamma Spectrometry Results of Soil A-8.2 Gamma Spectrometry Results of Soil - Summary A-9.1 Gamma Spectrometry Results of Sediment A-9.2 Gamma Spectrometry Results of Sediment - Summary A-10.1 Gamma Spectrometry Results of Fish A-10.2 Gamma Spectrometry Results of Fish - Summary A-11.1 Iodine 131 in Milk A-11.2 Iodine 131 in Milk - Summary A-12.1 Gamma Spectrometry Results of Milk A-12.2 Gamma Spectrometry Results of Milk - Summary A- 15.1 Gamma Spectrometry Results of Root Crops A-15.2 Gamma Spectrometry Results of Root Crops - Summary A-16.1 Gamma Spectrometry Results of Fruits A-16.2 Gamma Spectrometry Results of Fruits - Summary A-17.1 Gamma Spectrometry Results of Vegetables A-17.2 Gamma Spectrometry Results of Vegetables - Summary i

APPENDIX A - TABLE OF CONTENTS -

TABLE B: SPECIAL INTEREST SAMPLE RESULTS 3 B-1.1 2013 Quarterly Special Interest TLD Results 5 B-1.2 2013 Quarterly Special Interest TLD Results - Summary B-2.1 Gamma Spectrometry Results of Storm Drain Water n B-2.2 Gamma Spectrometry Results of Storm Drain Water - Summary B-3.1 Gross Beta in Storm Drain Water 5 B-3.2 Gross Beta in Storm Drain Water - Summary B-4.1 Tritium in Storm Drain Water B-4.2 Tritium in Storm Drain Water - Summary B-5.1 Gross Alpha in Sanitary Waste Treatment Water £ B-5.2 Gross Alpha in Sanitary Waste Treatment Water - Summary B-6.1 Gross Beta in Sanitary Waste Treatment Water 3 B-6.2 Gross Beta in Sanitary Waste Treatment Water - Summary B-7.1 Gamma Spectrometry Results of Sanitary Waste Treatment Water 3 B-7.2 Gamma Spectrometry Results of Sanitary Waste Treatment Water - Summary B-8.1 Tritium in Sanitary Waste Treatment Water B-8.2 Tritium in Sanitary Waste Treatment Water - Summary B-10.1 Gamma Spectrometry Results of Groundwater Monitoring Well Samples 3 B-10.2 Gamma Spectrometry Results of Groundwater Monitoring Well Samples - Summary B-11.1 Tritium in Groundwater Monitoring Well Samples 3 B-12-1 Gamma Spectrometry Results of CGS Storm Drain Pond Soil I

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FORWARD Since mid-1984, the results of the REMP analyses have been presented as net results calculated from total counts minus the observed background counts of the detection method. Counting results for low level samples are often within the counting error of the background determination; consequently results can range from negative to positive values, in these samples. Though most of the analytical results presented in this Appendix are below the detection limit, listing the actual calculated value, even when it is negative or below the detection limit, prevents positive biases and loss of individual results inherent in the use of "less than" (<) values. It is recommended practice to report radiological environmental data in this manner.

Most results listed in this Appendix are accompanied by a plus or minus (+) error value. In most cases the error value represents the two sigma counting uncertainty determined for that particular analysis. These error values are in the same units as the listed activity values. The two sigma error value represents the range that a recount of the same sample would be expected to fall within 95%.of the time, based on the statistics encountered in the original count.

Also included in most cases are the analysis specific, minimum detectable activity (MDA) values.

Though similar in concept to the LLD, these values are based on the statistics encountered in the specific sample count itself and not a blank determination. As such, they are a aposteriori(after the fact) determination where the LLD is a a priori(before the fact) determination. These values were included as they represent the level of activity that would have needed to be present in the sample for a positive identification to be made. .

iii

TABLE A-1.1 2013 QUARTERLY TLD RESULTS Results in milli-Roentgen (mR) per Standard Quarter Quarterly Station ID 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Sum 1 22.0 21.3 22.4 22.8 88.4 2 21.6 19.9 22.0 22.2 85.6 3 19.1 19.9 21.4 21.0 81.4 4 18.5 18.7 19.5 19.9 76.6 5 19.7 18.7 19.6 20.2 78.0 6 19.1 18.6 19.3 19.9 76.9 7 20.1 20.1 21.4 21.3 82.8 8 22.7 22.5 23.7 23.8 92.7 9 20.8 18.9 21.7 20.7 82.1 10 19.6 19.5 21.0 21.4 81.5 11 20.8 20.2 21.3 21.7 84.1 12 21.9 21.6 23.8 23.2 90.5 13 19.9 19.9 21.4 21.4 82.7 14 20.2 20.3 21.6 21.7 83.9 15 21.3 22.2 22.5 23.8 89.7 16 19.9 20.7 21.9 22.7 85.3 17 20.8 22.6 22.9 23.7 90.1 18 23.5 21.0 22.9 22.9 90.3 19 22.2 21.1 23.2 22.9 89.5 20 20.1 20.8 22.5 22.6 86.0 21 19.2 18.9 20.6 20.3 79.0 22 20.0 20.2 21.6 21.8 83.5 23 20.8 19.7 21.7 22.2 84.3 24 20.1 20.5 21.6 22.2 84.5 25 21.4 22.5 22.4 24.9 91.2 40 18.7 18.2 19.2 19.4 75.5 41 20.5 21.0 21.3 22.7 85.4 42 20.4 20.0 21.1 21.4 82.9 43 21.6 21.1 22.8 21.8 87.4 44 19.4 20.1 19.9 19.6 78.9 45 18.8 19.7 20.1 21.4 80.1 46 24.7 25.7 27.3 27.3 105.0 47 18.6 18.8 20.4 20.1 77.9 49 20.0 20.8 22.1 22.2 85.0 50 19.5 20.4 21.0 22.3 83.2 51 19.6 19.6 21.4 21.3 81.9 53 20.8 20.2 21.0 21.6 83.5 54 20.3 20.5 22.0 22.8 85.6 55 21.4 20.0 22.2 21.5 85.1 56 21.3 22.0 22.1 23.1 88.5 65 19.1 18.5 20.2 20.3 78.1 71 23.5 22.5 26.1 26.9 99.0 72 23.7 21.6 26.0 25.0 96.3 Page 1 of 2

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TABLE A-1.1,  :

i 2013 QUARTERLY TLD RESULTS Results in milli-Roentgen (mR) per Standard Quarter Quarterly I

Station ID 73 1st Quarter 21.0 2nd Quarter 19.7 3rd Quarter 22.5 4th Quarter 23.9 Sum 87.1 I

74 75 76 22.0 21.6 21.0 21.6 21;2 20.3 24.3,-

23.1 22.8 24.5 22.9 21.4 92.4 88.9 85.5 i

77 21.3 20.3 22.5 21.7 85.8 78 79 20.3 20.6

-20.7 20.4 21.2 22.0 21.8 22.5 84.0 85.6 i

80 21.1 19.7 22.4 21.8 85.0 81 82 20.0 21.8 20.0 21.1 20.8 22.9 21.9 23.0 82.6 88.8 I

83 21.2 20.4 21.6 22.5 85.7 84 85 86 20.5 21.5

.27.0 20.8 22.1 26.0 24.2 23.0 29.7 23.0 24.2 28.9 88.6 90.7 111.6 I

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TABLE A-1.2 2013 QUARTERLY TLD RESULTS-

SUMMARY

Results in milli-Roentgen (mR) per Standard Quarter I

Average Activity Activity Number of Location Activity Low High Samples I

Quarterly Indicator TLDs 21.5 18.2 29.7 224 Quarterly Control TLDs 20,5 18.9 21.7 4 I I

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Page 2 of 2 I

TABLE A-2.1 GROSS BETA ON AIR PARTICULATE FILTERS

.; - .. .., .Results in pCi per Cubic Meter Station 01 Station 04 Station 05 Collection Period Result Error Result Error Result Error 01/02/13 - 01/08/13 5.13E-02 + 1.50E-03 5.06E-02 + 1.51E-03 4.23E-02 + 1.38E-03 01/08/13 - 01/15/13 1.73E-02 + 8.1OE-04 1.79E-02 + 8*47E-04 1.80E-02 + 8.38E-04 01/15/13 - 01/22/13 5.49E-02 + 1.46E-03 6.04E-02 + 1.56E-03 5.39E-02 + 1.46E-03 01/22/13 - 01/29/13 5.46E-02 + 1.46E-03 5.42E-02 + 1.48E-03 5.06E-02 + 1.42E-03 01/29/13 - 02/05/13 1.18E-02 + 6.86E-04 9.99E-03 + 6.48E-04 9.43E-03 + 6.31E-04 02/05/13 - 02/12/13 1.28E-02 + 7.14E-04 1.85E-02 + 8.53E-04 9.07E-03 + 6.27E-04 02/12/13 - 02/19/13 1.51E-02 + 7.69E-04 7.28E-02 + 1.75E-03 8.66E-03 + 6.19E-04 02/19/13 - 02/26/13 4.93E-03 + 4.93E-04 1.41E-02 + 7.69E-04 5.93E-03 + 5.09E-04 02/26/13 - 03/05/13 6.79E-03 + 5.48E-04 9.93E-03 + 6.62E-04 7.51E-03 + 5.55E-04 03/05/13 - 03/12/13 9.31E-03 + 6.24E-04 8.37E-03 + 5.86E-04 7.43E-03 + 5.59E-04 03/12/13 - 03/19/13 7.06E-03 + 5.50E-04 1.03E-02 + 6.36E-04 6.43E-03 + 5.08E-04 03/19/13 - 03/26/13 1.17E-02 + 6.88E-04 1.16E-02 + 6.77E-04 9.64E-03 + 6.1OE-04 03/26/13 - 04/02/13 2.08E-02 + 8.97E-04 2.06E-02 + 8.94E-04 1.89E-02 + 8.57E-04 04/02/13 - 04/09/13 NVS 8.51E-03 + 5.98E-04 6.85E-03 + 5.59E-04 04/09/13 - 04/16/13 5.46E-03 + 5.08E-04 6.04E-03 + 5.09E-04 6.29E-03 + 5.39E-04 04/16/13 - 04/23/13 1.13E-02 + 6.86E-04 9.19E-03 + 6.1OE-04 9.12E-03 + 6.34E-04 04/23/13 - 04/30/13 1.45E-02 + 7.61E-04 1.50E-02 + 7.74E-04 1.13E-02 + 6.92E-04 04/30/13 - 05/07/13 1.37E-02 + 7.43E-04 1.49E-02 + 7.73E-04 1.46E-02 + 7.72E-04 05/07/13 - 05/14/13 2.30E-02 + 9.17E-04 2.32E-02 + 9.52E-04 2.21E-02 + 9.05E-04 05/14/13 - 05/21/13 6.53E-03 + 5.16E-04 8.05E-03 + 5.97E-04 7.26E-03 + 5.55E-04 05/21/13 - 05/28/13 4.71E-03 + 4.65E-04 4.22E-03 + 4.71E-04 4.39E-03 + 4.66E-04 05/28/13 - 06/04/13 4.64E-03 + 4.39E-04 6.15E-03 + 5.12E-04 4.88E-03 + 4.71E-04 06/04/13 - 06/11/13 1.08E-02 + 6.33E-04 1.23E-02 + 7.04E-04 1.07E-02 + 6.53E-04 06/11/13 - 06/18/13 7.29E-03 + 5.40E-04 7.35E-03 + 5.56E-04 6.09E-03 + 5.32E-04 06/18/13 - 06/25/13 6.05E-03 + 5.12E-04 4.09E-03 + 4.54E-04 4.22E-03 + 4.81E-04 06/25/13 - 07/02/13 1.33E-02 + 7.1OE-04 1.29E-02. + 7.18E-04 1.23E-02 + 7.27E-04 07/02/13 - 07/09/13 1.44E-02 + 7.41E-04 1.36E-02 + 7.25E-04 1.34E-02 + 7.44E-04 07/09/13 - 07/16/13 1.29E-02 + 6.95E-04 1.30E-02 + 7.08E-04 1.15E-02 + 6.71E-04 07/16/13 - 07/23/13 1.54E-.02 + 7.45E-04 1.76E-02 + 8.20E-04 1.50E-02 + 7.68E-04 07/23/13 - 07/30/13 1.38E&02 + 7.19E-04 1.53E-02 + 7.61E-04 1.47E-02 + 7.36E-04 07/30/13 - 08/06/13 1.72E-02 + 8.02E-04 1.72E-02 + 8.10E-04 1.72E-02 + 8.08E-04 08/06/13 - 08/13/13 1.88E-02 + 8.35E-04 2.07E-02 + 8.77E-04 1.84E-02 + 8.26E-04 08/13/13 - 08/20/13 1.47E-02 + 7.31E-04 1.71E-02 + 8.04E-04 1.43E-02 + 7.36E-04 08/20/13 - 08/27/13 1.56E-02 + 7.53E-04 1.55E-02 + 7.73E-04 1.38E-02 + 7.14E-04 08/27/13 - 09/03/13 1.53E-02 + 7.57E-04 1.49E-02 + 7.55E-04 1.62E-02 + 7.89E-04 09/03/13 - 09/10/13 1.24E-02 + 6.92E-04 1.19E-02 + 6.98E-04 1.22E-02 + 6.90E-04 09/10/13 - 09/17/13 2.89E-02 + 1.04E-03 3.46E-02 + 1.18E-03 2.92E-02 + 1.08E-03 09/17/13 - 09/24/13 9.75E-03 + 6.13E-04 1.16E-02 + 6.76E-04 1.01E-02 + 6.36E-04 09/24/13 - 10/01/13 7.47E-03 + 5.44E-04 7.69E-03 + 5.65E-04 5.74E-03 + 4.91E-04 10/01/13 - 10/08/13 1.45E-02 + 7.28E-04 1.60E-02 + 7.74E-04 1.47E-02 + 7.40E-04 10/08/13 - 10/15/13 1.54E-02 + 7.66E-04 1.70E-02 + 8.16E-04 1.61E-02 + 7.93E-04 10/15/13 - 10/22/13 3.92E-02 + 1.18E-03 4.OOE-02 + 1.22E-03 3.82E-02 + 1.18E-03 10/22/13 - 10/29/13 4.88E-02 + 1.31E-03 4.88E-02 + 1.33E-03 4.35E-02 + 1.27E-03 10/29/13 - 11/05/13 1.39E-02 + 7.09E-04 1.69E-02 + 7.89E-04 1.43E-02 + 7.37E-04 11/05/13 - 11/12/13 1.30E-02 + 7.06E-04 1.52E-02 + 7.79E-04 1.58E-02 + 7.86E-04 11/12/13 - 11/19/13 1.44E-02 + 7.42E-04 1.73E-02 + 8.30E-04 1.42E-02 + 7.60E-04 11/19/13 - 11/26/13 4.87E-02 + 1.33E-03 5.33E-02 + 1.43E-03 5.05E-02 + 1.36E-03 11/26/13 - 12/03/13 1.26E-01 + 2.20E-03 1.25E-01 + 2.25E-03 1.16E-01 + 2.12E-03 12/03/13 - 12/10/13 4.28E-02 + 1.22E-03 4.39E-02 + 1.26E-03 4.04E-02 + 1.22E-03 12/10/13 - 12/17/13 8.92E-02 + 1.85E-03 8.93E-02 + 1.86E-03 7.68E-02 + 1.71E-03 12/17/13 - 12/23/13 2.61E-02 + 1.08E-03 2.69E-02 + 1.09E-03 2.22E-02 + 1.OOE-03 12/23/13 - 12/31/13 3.15E-02 + 1.02E-03 3.11E-02 + 1.01E-03 3.OOE-02 + 1.01E-03 NVS = Valid sample not obtained due to sampler failure.

Average MDA for analyses in Table A-2.1 was 9.OOE-04. Page 1 of 4

TABLE A-2:1 :

I GROSS BETA ON AIR PARTICULATE FILTERS, Results in pCi per Cubic Meter Station 06 Station 07 Station 08 Collection Period 01/02/13 -

01/08/13 -

01/08/13 01/15/13 Result 4.85E-02 + 1.43E-03 1.93E-02 + 8.45E-04 Error Result Error 5.11E-02 + 1.50E-03 1.74E-02 + 8.07E-04 Result Error 4.80E-02 + 1.46E-03 1.78E-02 + 8.24E-04 I

01/15/13 -

01/22/13 -

01/29/13 -

01/22/13 01/29/13 02/05/13 5.34E-02 + 1.42E-03 5.60E-02 + 1.45E-03 1.17E-02 + 6.64E-04 5.56E-02 + 1.45E-03 5.90E-02 + 1.49E-03 1.29E-02 + 7.02E-04 5.45E-02 + 1.47E-03 5.39E-02 + 1.46E-03 1.22E-02 + 7.02E-04 i

02/05/13 - 02/12/13 1.38E-02 + 7.23E-04 1.33E-02 + 7.17E-04 1.02E-02 + 6.40E-04 02/12/13 - 02/19/13 1.32E-02 + 7.15E-04 .1.33E-02 + 7.15E-04 1.39E-02 + 7.44E-04 02/19/13 - 02/26/13 7.20E-03 + 5.61E-04 6.13E-03 + 5.23E-04 5.78E-03 + 5.29E-04 02/26/13 - 03/05/13 7.79E-03 + 5.74E-04 8.40E-03 + 5.90E-04 7.22E-03 + 5.66E-04 03/05/13 - 03/12/13 8.71E-03 + 6.07E-04 8.68E-03 + 6.01E-04 7.28E-03 + 5.75E-04 03/12/13 -

03/19/13 -

03/19/13 03/26/13 6.88E-03 + 5.36E-04 1.16E-02 + 6.88E-04 7.50E-03 + 5.56E-04 1.18E-02 + 6.81E-04 6.83E-03 + 5.47E-04 1.16E-02 + 6.97E-04 I

03/26/13 - 04/02/13 1.95E-02 + 8.88E-04 2.02E-02 + 8.78E-04 1.84E-02 + 8.32E-04 04/02/13 -

04/09/13 -

04/16/13 -

04/09/13 04/16/13 04/23/13 6.03E-03 + 5.36E-04 7.01E-03 + 5.66E-04 9.13E-03 + 6.34E-04 6.33E-03 + 5.22E-04 6.57E-03 + 5.23E-04 1.OOE-02 + 6.28E-04 7.12E-03 + 5.45E-04 5.54E-03 + 4.83E-04 8.39E-03 + 5.88E-04 I

04/23/13 - 04/30/13 1.28E-02 + 7.12E-04 1.43E-02 + 7.46E-04 1.32E-02 + 7.13E-04 04/30/13 -

05/07/13 -

  • 05/14/13 -

05/07/13 05/14/13 05/21/13 1.47E-02 + 7.66E-04 2.25E-02 + 9.49E-04 7.18E-03 + 5.68E-04 1.35E-02 + 7.35E-04 2.20E-02 + 9.30E-04 8.24E-03 + 6.03E-04 1.44E-02 + 7.65E-04 2.32E-02 + 9.24E-04 8.58E-03 + 5.88E-04 I,

05/21/13 -

05/28/13 -

06/04/13 -

05/28/13 06/04/13 06/11/13 4.77E-03 + 4.92E-04 6.18E-03 + 5.20E-04 1.20E-02 + 7.05E-04 3.66E-03 + 4.49E-04 4.78E-03 + 4.67E-04 1.03E-02 + 6.43E-04 4.34E-03 + 4.67E-04 6.60E-03 + 5.23E-04 1.02E-02 + 6.29E-04 I

06/11/13 - 06/18/13 8.75E-03 + 5.95E-04 6.94E-03 + 5.54E-04 7.18E-03 + 5.49E-04 06/18/13 -

06/25/13 -

07/02/13 -

06/25/13 07/02/13 07/09/13 4.36E-03 + 4.61E-04 1.38E-02 + 7.20E-04 1.28E-02 + 6.98E-04 4.13E-03 + 4.57E-04 1.28E-02 + 7.27E-04 1.36E-02 + 7.35E-04 4.28E-03 +. 4.60E-04 1.31E-02 +. 7.20E-04 1.35E-02 + 7.18E-04 I

07/09/13 - 07/16/13 1.20E-02 + 6.66E-04 1.23E-02 + 7.02E-04 1.26E-02 + 6.98E-04 07/16/13 -

07/23/13 -

07/23/13 07/30/13 1.55E-02 + 7.50E-04 1.50E-02 + 7.33E-04 1.69E-02 + 8.04E-04 1.39E-02 + 7.45E-04 1.91E-02 + 8.62E-04 1.47E-02 + 6.75E-04 I

07/30/13 - 08/06/13 1.68E-02 + 8.11E-04 1.69E-02 + 8.17E-04 1.70E-02 + 8.04E-04 08/06/13 -

08/13/13 -

08/20/13 -

08/13/13 08/20/13 08/27/13 1.91E-02 + 8.56E-04 1.50E-02 + 7.62E-04 1.42E-02 + 7.56E-04 2.11E-02 + 9.01E-04 1.77E-02 + 8.31E-04 1.57E-02 + 7.84E-04 1.90E-02 + 8.24E-04 1.48E-02 + 7.32E-04 1.74E-02 + 7.89E-04 I

08/27/13 - 09/03/13 1.57E-02 + 7.85E-04 1.58E-02 + 7.84E-04 1.55E-02 + 7.43E-04 09/03/13 -

09/10/13 -

09/17/13 -

09/10/13 09/17/13 09/24/13 1.25E-02 + 7.22E-04 3.11E-02 + 1.11E-03 1.12E-02 + 6.80E-04 1.31E-02 + 7.22E-04 2.98E-02 + 1.08E-03 1.14E-02 + 6.41E-04 2.87E-02 + 1.01E-03 t

9.21E-03 + 6.09E-04 1.16E-02 + 6.40E-04

.09/24/13 - 10/01/13 7.08E-03 + 5.49E-04 6.68E-03 + 5.28E-04 6.70E-03 + 5.16E-04 10/01/13 - 10/08/13 1.52E-02 + 7.69E-04 1.41E-02 + 7.25E-04 1.51E-02 + 7.40E-04 10/08/13 - 10/15/13 1.39E-02 + 7.63E-04 1.76E-02 + 8.21E-04 1.68E-02 + 8.09E-04 10/15/13 - 10/22/13 4.03E-02 + 1.24E-03 4.14E-02 + 1.22E-03 3.77E-02 + 1.16E-03 10/22/13 -

10/29/13 -

11/05/13 -

10/29/13 11/05/13 11/12/13 5.OOE-02 + 1.37E-03 1.53E-02 + 7.62E-04 1.37E-02 + 7.42E-04 4.89E-02 + 1.33E-03 1.54E-02 + 7.54E-04 1.50E-02 + 7.59E-04 4.64E-02 + 1.30E-03 1.53E-02 + 7.58E-04 1.62E-02 + 7.86E-04 I

11/12/13 - 11/19/13 1.58E-02 + 7.94E-04 1.63E-02 + 7.90E-04 1.57E-02 + 7.79E-04 11/19/13 - 11/26/13 4.84E-02 + 1.38E-03 5.23E-02 + 1.40E-03 5.46E-02 + 1.44E-03 11/26/13 -

12/03/13 -

12/10/13 --

12/03/13 12/10/13 12/17/13 1.18E-01 + 2.19E-03 4.31E-02 + 1.27E-03 9.07E-02 + 1.91E-03 1.27E-01 + 2.25E-03 4.57E-02 + 1.28E-03 9.07E-02 + 1.83E-03 1.21E-01 + 2.19E-03 4.40E-02 + 1.27E-03 8.60E-02 + 1.82E-03 I

12/17/13 - 12/23/13 2.52E-02 + 1.08E-03 3.OOE-02 + 1.13E-03 2.52E-02 + 1.05E-03 12/23/13 - 12/31/13 3.02E-02 + 1.02E-03 3.41E-02 + 1.05E-03 2.96E-02 + 9.81E-04 NVS = Valid sample not obtained due to sampler failure.

Average MDA for analyses in Table A-2.1 was 9.OOE-04. Page 2 of 4 I

TABLE A-2.1 GROSS BETAON AIR PARTICULATE FILTERS Results in pCi per Cubic Meter Station 09 Station 21 Station 23 Collection Period ' Result Error Result Error Result Error 01/02/13 - 01/08/13 4.19E-02 + 1.35E-03 4.61E-02 + 1.41E-03 4.88E-02 + 1.45E-03 01/08/13 - 01/15/13 1.43E-02 +F 7.57E-04 1.66E-02 + 7.90E-04 1.69E-02 + 7.94E-04 01/15/13 - 01/22/13 4.OOE-02 + 1.26E-03 5.11E-02 + 1.41E-03 5.38E-02 + 1.42E-03 01/22/13 - 01/29/13 5.23E-02 + 1.44E-03 5.75E-02 + 1.48E-03 5.75E-02 + 1.49E-03 01/29/13 - 02/05/13 8.70E-03 + 6.03E-04 1.16E-02 +- 6.80E-04 1.32E-02 + 7.23E-04 02/05/13 - 02/12/13 5.77E-03 + 5.31E-04 1.10E-02 + 6.53E-04 1.43E-02 + 7.42E-04 02/12/13 - 02/19/13 7.41E-03 +. 5.75E-04 9.16E-03 + 6.26E-04 1.21E-02 + 6.91E-04 02/19/13 - 02/26/13 4.54E-03 + 4.87E-04 5.98E-03 + 5.19E-04 7.06E-03 + 5'.59E-04 02/26/13 - 03/05/13 7.33E-03 + 5.58E-04 8.21E-03 + 5.88E-04 8.02E-03 + 5.82E-04 03/05/13 - 03/12/13 6.34E-03 + 5.31E-04 9.27E-03 + 6.33E-04 8.37E-03 + 6.06E-04 03/12/13 - 03/19/13 7.31E-03 + 5.53E-04 6.53E-03 + 5.33E-04 6.83E-03 + 5.49E-04 03/19/13 - 03/26/13 1.04E-02 + 6.51E-04 1.19E-02 + 6.93E-04 1.24E-02 + 7.12E-04 03/26/13 - 04/02/13 1.82E-02 + 8.43E-04 1.94E-02 + 8.70E-04 2.1OE-02 + '9.18E-04 04/02/13 - 04/09/13 5.77E-03 + 5.16E-04 7.65E-03 + 5.77E-04 8.13E-03 + 6.03E-04 04/09/13 - 04/16/13 5.49E-03 + 4.92E-04 5.15E-03 + 4.88E-04 4.84E-03 + 4.58E-04 04/16/13 - 04/23/13 9.01E-03 + 6.01E-04 1.02E-02 + 6.48E-04 1.02E-02 + 6.32E-04 04/23/13 - 04/30/13 1.21E-02 + 6.85E-04 1.51E-02 + 7.73E-04 1.37E-02 + 7.32E-04 04/30/13 - 05/07/13 1.38E-02 + 7.07E-04 1.41 E-02 + 7.56E-04 1.56E-02 + 7.86E-04 05/07/13 - 05/14/13 2.03E-02 + 8.68E-04 2.48E-02 + 9.12E-04 2.25E-02 + 9.13E-04 05/14/13 - 05/21/13 7.23E-03 + 5.32E-04 7.30E-03 + 5.47E-04 7.67E-03 + 5.60E-04 05/21/13 - 05/28/13 3.22E-03 + 4.14E-04 2.99E-03 + 4.01E-04 4.29E-03 + 4.58E-04 05/28/13 - 06/04/13 5.54E-03 + 4.64E-04 6.92E-03 + 5.08E-04 6.03E-03 + 4.98E-04 06/04/13 - 06/11/13 9.59E-03 + 6.12E-04 1:11E-02 + 6.58E-04 1.22E-02 + 6.83E-04 06/11/13 - 06/18/13 6.34E-03 + 5.04E-04 7.47E-03 + 5.67E-04 7.62E-03 + '5.62E-04 06/18/13 - 06/25/13 3.73E-03 + 4.41E-04 5.01E-03 + 5.02E-04 5.04E-03 + 4.94E-04 06/25/13 - 07/02/13 1.13E-02 + 6.59E-04 1.21E-02 + 6.96E-04 1.35E-02 + 7.33E-04 07/02/13 - 07/09/13 1.20E-02 + 6.86E-04 1.34E-02 + 7.27E-04 1.38E-02 + 7.42E-04 07/09/13 - 07/16/13 1.07E-02 + 6.54E-04 1.20E-02 + 6.98E-04 1.11E-02 + 6.71E-04 07/16/13 - 07/23/13 1.66E-02 + 7.89E-04 1.75E-02 + 8.24E-04 1.73E-02 + 8.30E-04 07/23/13 - 07/30/13 1.36E-02 + 7.33E-04 1.39E-02 + '7.45E-04 1.51E-02 + 7.87E-04 07/30/13 - 08/06/13 1.58E-02 + 7.76E-04 1.55E-02 + 7.83E-04 1-54E-02 + 7.90E&04 08/06/13 - 08/13/13 2.06E-02 + 8.92E-04 2.08E-02 + 9.12E-04 2.07E-02 + 9.23E-04 08/13/13 - 08/20/13 1.38E-02 + 7.28E-04 1,.58E-02. + 7.88E-04 1.52E-02 + 8.34E-04 08/20/13 - 08/27/13 1.55E-02 + 7.78E-04 1'.47E-02 + 7.67E-04 . NVS 08/27/13 - 09/03/13 1.38E-02 + 7.19E-04 1.48E-02 + 7.69E-04 1.60E-02 + 8.85E:04 09/03/13 - 09/10/13 1.31E-02 + 7.21E-04 1.38E-02 + 7.57E-04 1.21E-02 + 7.16E-04 09/10/13 - 09/17/13 2.78E-02 + 1.03E-03 3.13E-02 + 1.12E-03 2.93E-02 + 1.09E-03 09/17/13 - 09/24/13 7.62E-03 + 5.66E-04 9.59E-03 + 6.43E-04 1.04E-02 + 6.54E-04 09/24/13 - 10/01/13 5.84E-03 + 5.04E-04 6.84E-03 + 5.26E-04 6.60E-03 + 5.35E-04 10/01/13 - 10/08/13 1.12E-02 + 6.53E-04 1.42E-02 +' 7.26E-04 1.50E-02 + 7.64E-04 10/08/13 - 10/15/13 1.54E-02 + 7.77E-04 1.72E-02 + 8.08E-04 1.75E-02 + 8.44E-04 10/15/13 - 10/22/13 3.28E-02 + 1.11E-03 4.17E-02 + 1.22E-03 3.96E-02 + 1.23E-03 10/22/13 - 10/29/13 4.47E-02 + 1.28E-03 4.70E-02 + 1.29E-03 4.60E-02 + 1.32E-03

  • 10/29/13 - 11/05/13 1.40E-02 + 7.19E-04 1.56E-02 4- 7.45E-04 1.59E-02 + 7.82E-04 11/05/13 - 11/12/13 1.46E-02 + 7.64E-04 1.53E-02 + 7.61E-04 1.52E-02 + 7.92E-04 11/12/13 - 11/19/13 1.23E-02 + 6.99E-04 1.89E-02 + 8.45E-04 1.94E-02 + 9.01E-04 11/19/13 - 11/26/13 4.06E-02 + 1.23E-03 5.18E-02 + 1.39E-03 4.96E-02 + 1.35E-03 11/26/13 - 12/03/13 ,1.06E-01 + 2.03E-03 1.26E-01 + 2.22E-03 1.26E-01 + 2.22E-03 12/03/13 - 12/10/13 3.80E-02 + 1.16E-03 4.70E-02 + 1.32E-03 4.32E-02 + 1.25E-03 12/10/13 - 12/17/13 7.24E-02 + 1.67E-03 9.22E-02 + 1.89E-03 8.86E-02 + 1.85E-03 12/17/13 - 12/23/13 2.37E-02 + 1.03E-03 2.74E-02 + 1.1OE-03 2.43E-02 + 1.06E-03 12/23/13 - 12/31/13 3.08E-02 + 1.OOE-03 3.36E-02 + 1.06E-03 2.98E-02 + 1.00E-03 NVS = Valid sample not obtained due to sampler failure.

Average MDA for analyses in Table A-2.1 was 9.OOE-04. Page 3 of 4

U TABLE A-2.1 GROSS BETA ON AIR PARTICULATE FILTERS I

Results in pCi per Cubic Meter Collection Period Station 40 Result Error j Station48 Result ,,Error Station 57 Result Error I

01/02/13 - 01/08/13 4.65E-02 + 1.40E-03 4.84E-02 + 1.44E-03 5.15E-02 + 1.49E-03 01/08/13 -

01/15/13 -

01/15/13 01/22/13 1.82E-02 + 8.22E-04 5.76E-02 + 1.47E-03 1.82E-02 + 8.06E-04 5.28E-02 + 1.40E-03 1.87E-02 + 8.33E-04 5.63E-02 + 1.47E-03 I

01/22/13 - 01/29/13 5.21E-02 + 1.40E-03 5.25E-02 + 1.39E-03 5.88E-02 + 1.53E-03 01/29/13 -

02/12/13 -

02/05/13 02/05/13 -. .02/12/13 02/19/13 1.13E-02 + 6.61E-04 8.31E-03 + 5.77E-04 8.96E-03 + 6.09E-04 1.19E-02 + 6.74E-04 1.20E-02 + 6.78E-04 8.27E-03 + 5.81E-04 1.07E-02 + 6.53E-04 1.15E-02 + 6.79E-04 1.17E-02 + 6.88E-04 02/19/13 - 02/26/13 6.89E-03 "+ 5.58E&04 7.59E-03 + 5.65E-04 7.07E-03 + 5.67E-04 02/26/13 -

03/05/13 -

03/12/13 -

03/05/13 03/12/13 03/19/13 6.83E-03 + 5.44E-04 7.05E-03 + 5.60E-04 7.23E-03 + 5.53E-04 7.67E-03 + 5.60E-04 6.87E-03 + 5.48E-04 7.39E-03 + 5.45E-04 8.54E-03 + 6.07E-04 9.86E-03 + 6.55E-04

!1 7.30E-03 + 5.68E-04 03/19/13 -

03/26/13 -

04/02/13 -

03/26/13 04/02/13 04/09/13 1.18E-02 + 6.97E-04 1.91E-02 + 8.49E-04 5.95E-03 + 5.08E-04 1.27E-02 + 6.94E-04 1.84E-02 + 8.33E-04 7.75E-03 + 5.63E-04 1.13E-02 + 6.93E-04 1.99E-02 + 8.61E-04 6.80E-03 + 5.30E-04 I

04/09/13 - 04/16/13 5.30E-03 + 4.78E-04 5.41E-03 + 4.92E-04 4.78E-03 + 4.56E-04 04/16/13 -

04/23/13 -

04/30/13 -

04/23/13 04/30/13 05/07/13 9.11E-03 + 6.08E-04 1.36E-02 + 7.28E-04 1.52E-02 + 7.78E-04 9.78E-03 + 6.35E-04 1.28E-02 + 7.02E-04 1.28E-02 + 7.04E-04 9.95E-03 + 6.26E-04 1.51E-02 + 7.59E-04 1.62E-02 + 8.08E-04 I

05/07/13 -

05/14/13 -

05/21/13 -

05/14/13 05/21/13 05/28/13 2.30E-02 + 9.24E-04 5.96E-03 + 5.04E-04 3.25E-03 + 4.18E-04 2.13E-02 + 8.96E-04 7.24E-03 + 5.58E-04 3.51E-03 + 4.27E-04 2.27E-02 + 9.07E-04 8.31E-03 + 5.81E-04 4.05E-03 + 4.44E-04 I

05/28/13 - 06/04/13 5.46E-03 + 4.76E-04 5.56E-03 + 4.84E-04 6.77E-03 + 5.74E-04 06/04/13 -

06/11/13 -

06/18/13 -

06/11/13 06/18/13 06/25/13 1.14E-02 + 6.63E-04 6.70E-03 + 5.28E-04 4.76E-03 + 4.77E-04 1.OOE-02 + 6.22E-04 6.98E-03 + 5.43E-04 4.OOE-03 + 4.51E-04 1.13E-02 + 6.82E-04 7.37E-03 + 5.78E-04 3.89E-03 + 4.59E-04 U

06/25/13 - 07/02/13 1.30E-02 + 7.27E-04 1.24E-02 + 7.03E-04 1.20E-02 + 7.19E-04 07/02/13 -

07/09/13 -

07/09/13 07/16/13 1.23E-02 + 7.06E-04 1.19E-02 + 6.90E-04 1.19E-02 + 6.79E-04 9.68E-03 + 7.24E-04 1.20E-02 + 7.1OE-04 1.18E-02 + 7.02E-04 I

07/16/13 - 07/23/13 1.64E-02 + 7.99E-04 1.37E-02 + 7.17E-04 1.63E-02 + 8.08E-04 07/23/13 -

07/30/13 -

08/06/13 -

07/30/13 08/06/13 08/13/13 1.43E-02 + 7.58E-04 1.51E-02 + 7.80E-04 1.93E-02 + 8.74E-04 1.34E-02 + 7.11E-04 1.63E-02 + 7.98E-04 1.86E-02 + 8.48E-04 1.32E-02 + 7.12E-04 1.70E-02 + 8.03E-04 2.11E-02 + 8.90E-04 I

08/13/13 - 08/20/13 1.62E-02 + 8.21E-04 1.29E-02 + 7.06E-04 1.72E-02 + 8.03E-04 08/20/13 -

08/27/13 -

09/03/13 -

08/27/13 09/03/13 09/10/13 1.48E-02 + 7.17E-04 1.47E-02 + 7.46E-04 1.28E-02 + 6.93E-04 1.46E-02 + 7.40E-04 1.50E-02 + 7.65E-04 1.33E-02 + 7.26E-04 1.60E-02 + 7.84E-04 1.51E-02 + 7.67E-04 1.44E-02 + 7.54E-04 i

09/10/13 -

09/17/13 -

09/24/13 -

09/17/13 09/24/13 10/01/13 2.62E-02 + 9.76E-04 1.07E-02 + 6.30E-04 6.91E-03 + 5.27E-04 3.25E-02 + 1.18E-03 8.37E-03 + 5.83E-04 6.58E-03 + 5.41E-04 3.23E-02 + 1.12E-03 1.02E-02 + 6.44E-04 6.61E-03 + 5.36E-04

'I 10/01/13 - 10/08/13 1.37E-02 + 6.90E-04 1.48E-02 + 7.71E-04 1.50E-02 + 7.61E-04 10/08/13 -

10/15/13 -

10/22/13 -

10/15/13 10/22/13 10/29/13 1.68E-02 + 7.79E-04 4.OOE-02 + 1.16E-03 4.57E-02 + 1.30E-03 1.61E-02 + 8.18E-04 3.81E-02 + 1.21E-03 4.23E-02 + 1.27E-03 1.85E-02 + 8.64E-04 4.18E-02 + 1.26E-03 4.74E-02 + 1.34E-03 I

10/29/13 - 11/05/13 1.44E-02 + 7.43E-04 1.61E-02 + 8.13E-04 1.62E-02 + 7.86E-04 11/05/13 -

11/12/13 -

11/12/13 11/19/13 1.53E-02 + 7.88E-04 1.58E-02 + 7.96E-04 1.79E-02 + 8.63E-04 1.36E-02 + 7.71E-04 1.45E-02 + 7.65E-04 1.70E-02 + 8.21E-04 I

11/19/13 - 11/26/13 5.04E-02 + 1.35E-03 4.96E-02 + 1.35E-03 5.16E-02 + 1.36E-03 11/26/13 -

12/03/13 -

12/10/13 -

12/03/13 12/10/13 12/17/13 1.16E-01 + 2.07E-03 4.24E-02 + 1.26E-03 8.06E-02 + 1.77E-03 1.23E-01 + 2.20E-03 4.35E-02 + 1.28E-03 8.59E-02 + 1.86E-03 1.39E-01 + 2.35E-03 4.70E-02 + 1.29E-03 9.60E-02 + 1.89E-03 12/17/13 - 12/23/13 2.29E-02 + 1.02E-03 2.56E-02 + 1.07E-03 2.70E-02 + 1.05E-03 12/23/13 - 12/31/13 2.96E-02 + 1.01E-03 2.85E-02 + 9.64E-04 3.38E-02 + 1.03E-03 U

NVS = Valid sample not obtained due to sampler failure.

Average MDA for analyses in Table A-2.1 was 9.OOE-04. Page 4 of 4 I

TABLE A-2.2 GROSS BETA ON.AIR PARTICULATE FILTERS -

SUMMARY

Results in pCi per cubic meter Average Activity Activity Number of Number of LOCATION Activity Low High Samples Positive IDs Gross Beta Indicators 2.18E-02 2.99E-03 1.39E-01 570 570 Gross Beta Controls 1.89E-02 3.22E-03 1.06E-01 52 52 Page 1 of 1

I TABLE A-3.1 GAMMA SPECTROMETRY RESULTS OF AIR PARTICULATEFILTERS Results in pCi/cubic meter, results decay corrected to midpoint of the sample collection period I

Location and Quarter FN-uciide RQ' Activity Station 1 Error 1stQ 2013 MDA Location and Quarter Nuclide.**Q**-Activity.

Station 1 Error 2nd Q 2013 MDA I

BE-7 K-40 MN-54 FE-59

+ 7.16E-02 4.58E-04 3.61E-05 4.31E-04

+

+

+

+

1.49E-02 4.95E-03 5.73E-04 2.60E-03 1.11 E-02 9.02E-03 9.32E-04 4.10E-03 BE-7

.K-40 MN-54 FE-59

+ 1.O0E-0t +

3.14E-03 1.56E-04 1.73E-03

+

+

+

1.59E-02 6.73E-03 5.18E-04 2.71 E-03 9.41 E-03 1.09E-02 7.98E-04 3.68E-03 I

CO-60 ZN-65 ZRNB-95 7.77E-05 0.OOE+00

-1.75E-04

+

+

+

4.62E-04 2.18E-03 1.33E-03 7.24E-04 3.59E-03 2.13E-03 CO-60 ZN-65 ZRNB-95

-8.41 E-05 3.17E-04 +

5.26E-04 +

+ 6.24E-04 1.23E-03 1.57E-03 9.97E-04 1.90E-03 2.42E-03 I

CS-134 0.OOE+00 + 5.87E-04 .9.64E-04 CS-1 34 8.78E-05 + 3.45E-04 5.34E-04 CS-1 37 BALA140 RU-106

-4.16E-06 0.OOE+00 0.OOE+00

+

+

+

3.89E-04 1.45E-02 4.14E-03 6.38E-04 2.38E-02 6.80E-03 CS-137 BALA140 RU-106 0.00E+00 +

-5.04E-03.+

6.59E-04 +

3.17E-04 1.49E-02 4.76E-03 5.21 E-04 2.31 E-02 7.64E-03 I

Location and Quarter Nuclide RQ Activity BE-7 + 1.44E-01 +

Station 1 Error 1.67E-02 3rd Q 2013 MDA 8.63E-03. BE-7 Location and Quarter

.Nuclide RQ Activity

+ 8.15E-02

. Station 1 4th Q 2013

+

Error 1.46E-02 MDA 7.97E-03 I

K-40 -5.49E-04 + 6.58E-03 9.99E-03 K-40 -2.36E-03 + 9.45E-03 5.82E-03 MN-54 FE-59 CO-60 0.OOE+00 0.00E+00 4.01E-05

+

+

+

3.68E-04 8.05E-04 3.51 E-04 6.05E-04

. 1.32E-03 6.01 E-04 MN-54 FE-59 CO-60 2.45E-04 0.OOE+00 0.OOE+00

+ 5.47E-04

+ 1.01E-03

+ 1.70E-04 8.22E-04 1.65E-03 2.80E-04 I

ZN-65 -4.58E-04 + 1.24E-03 1.91 E-03 ZN-65 -4.04E-05 + 9.93E-04 1.61 E-03 ZRNB-95 CS-1 34.

CS-137 0.OOE+00

-6.99E-05 4.29E-05

+

+

+

1.35E-03 3.31 E-04 3.43E-04

  • 2.23E-03 5.25E-04 5.52E-04 ZRNB-95 CS-134 CS-137

-3.14E-04 0.OOE+00

-6.76E-05

+ 1.61 E-03

+ 7.07E-04

+ 5.04E-04 2.55E-03 1.16E-03 8.10E-04 I

1.05E-02 BALA140 + 1.38E-02 2.1OE-02 I

BALA140 4.35E-03 + 8.48E-03 .- 3.76E-03 RU-106 -4.34E-04 + 3.18E-03 5.10E-03 RU-106- 8.19E-04 + 4.30E-03 6.82E-03 Location and Quarter Station 4. 1st Q 2013 Location and Quarter Station 4 2nd Q 2013

.MDA

Nuclide BE-7 K-40 RQ Activity

+ 1.O0E-01 +

-2.51E-03 +

Error 1.61 E-02 1.01E-02 MDA 1.01 E-02 6.19E-03

+ 9.70E-02 4.57E-03

+

+

Error 1.67E-02 5.83E-03 1.16E-02 8.73E-03 I

MN-54 0.OOE+00-+ 5.37E-04 8.83E-04 MN-54 -1.44E-04 + 5.85E-04 9.20E-04 FE-59 CO-60 ZN-65

.- 5.20E:-04 +

8.62E-05 +

-2.33E-04 +

3.19E-03 5.37E-04 1.50E-03 5.06E-03 8.49E-04 2.40E-03 FE-59 CO-60 ZN-65 0.OOE+00 0.OOE+00

-4.36E-04

+

+

+

5.81 E-03 6.02E-04 1.36E-03 9.56E-03 9.90E-04 2.09E-03 I

ZRNB-95 -2.98E-04 ,+ 1.45E-03 2.29E-03 ZRNB-95 -4.82E-04 + 1.67E-03 2.62E-03

.CS-134

  • CS-137 BALA140

-6.36E-05 +

-7.33E-05 +

4.28E-03 +

5.11E-04 5.42E-04 1.05E-02 8.24E-04 8.71 E-04 1.55E-02 CS-134 CS-1 37 BALA140 7.84E-05 9.76E-05

-1.27E-03

+

+

+

3.82E-04 4.50E-04 1.10E-02 6.03E-04 7.09E-04 1.76E-02 I

RU-106 1.01E-03 + 4.43E-03 6.99E-03 RU-106 0.OOE+00 + 6.82E-03 1.12E-02 Location and Quarter Nuclide RQ Activity Station 4 Error 3rd Q 2013 MDA Location and Quarter Nuclide RQ Activity Station 4 Error 4th Q 2013 MDA I

BE-7 + 1.38E-01 + 1.70E-02 9.39E-03 BE-7 7.56E-03

+ 9.64E-02 + 1.59E-02 K-40 MN-54 FE-59

-3.64E-04

-5.1OE-05 1.42E-05

+

+

+

5.19E-03 4.18E-04 2.84E-03 9.02E-03 6.71 E-04 4.67E-03 K-40 MN-54 FE-59 1.42E-06 2.04E-04 1.87E-03

+

+

+

5.67E-03 4.91 E-04 2.28E-03 1.03E-02 7.33E-04 2.57E-03 I

3.16E-04 0.OOE+00 +

-1.01E-04 +

I S.CO-60 4.06E-04 CO-60 8.56E-04 1.41E-03 ZN-65 -4.54E-04 + 1.49E-03 2.35E-03 ZN-65 3.73E-04 + 1.22E-03 1.86E-03 ZRNB-95 1.39E-04 + 1.37E-03 2.22E-03 ZRNB-95 0.OOE+00 + 1.46E-03 2.41 E-03 CS-1 34 0.OOE+00 + 6.34E-04 1.04E-03 CS-134 2.36E-05 + 4.90E-04 8.OOE-04 CS-137 .

  • BALA140 RU-106 2.67E-05 0.OOE+00 1.20E-03

+

+

+

2.85E-04 2.17E-02 3.33E-03 4.59E-04 3.57E-02 5.12E-03 CS-1 37 BALA1 40 RU-106

-1.19E-04 +.

0.OOE+00 +

-1.30E-04 +

5.08E-04 2.21 E-02 4.23E-03 8.01 E-04 3.63E-02 6.92E-03 I

RQ = Results Qualifier. If blank, result is less than detection limit. If "+",. result is above detection limit.

I 1st Q 1/2/13 to 4/2/13 - 2nd Q 4/2/13 to 7/2/13 - 3rd Q 7/2/13 to 10/1/13 - 4th Q 10/1/13 to 12/31/13 Page 1 of 6 I

i " TABLE A-3.1 GAMMA SPECTROMETRY-RESULTS OF AIR PARTICULATE FILTERS Results in pCi/cubic meter,; results decay corrected to mid point of the sample collection period Location and Quarter , Station 5 1st Q 2013 Location and Quarter; Station 5 2nd Q 2013 lucide RQ Activity Error MDA Nucliide-- RQ Activity "Error MDA BE-7 + 9.77E-02 + 1.51E-02 8.41 E-03 BE-7 + 1.04E-01 + 1.58E-02 8.87E-03 K-40 4.93E-04 +* 6.39E-03 1.12E-02 K-40 -2.49E-03 -+ 5.66E-02 1.44E-02 MN-54 2.23E-04 + 5.61E-04 8.54E-04 MN-54 ,-1.12E-04 + 5.31 E-04 8.37E-04 FE-59 -1.01E-05 + 3.08E-03 5.05E-03 FE-59 -5.58E-04 + 3.56E-03 5.67E-03 CO-60 2.30E-05 + 4.70E-04 7.63E-04 CO-60 0.OOE+00 + 1.78E-04 2.93E-04 ZN-65 -1.46E-04 + 1.20E-03 1.92E-03 ZN-65 4.96E-06 + 1.03E-03 1.69E-03 ZRNB-95 6.14E-04 + 1.32E-03 1.96E-03 ZRNB-95 -7.40E-05 + 1.59E-03 2.60E-03 CS-1 34 4.67E-05 + 4.69E-04 7.59E-04 CS-134 -8.79E-05 + 2.75E-04 4.12E-04 CS-1 37 -7.65E-05 + 5.35E-04 8.59E-04 CS-1 37 -1.83E-04 + 6.11E-04 9.61 E-04 BALA140 0.OOE+00 + 1.45E-02 2.38E-02 BALA140- -1.46E-03 + 1.20E-02 1.92E-02 RU-106 1.13E-03 + 4.12E-03 6.42E-03 RU-106 4.50E-04 + 5.14E-03 8.33E-03 Location and Quarter Station 5 3rd Q 2013 Location and Quarter- Station 5 4th Q 2013 Activity Nuclide RO Activity Error MDA Nuclide RQ Error MDA BE-7 + 1.61E-01 + 2.20E-02 1.19E-02 BE-7 + 9.35E-02 + 1.65E-02 -8.71 E-03 K-40 -2.40E'03 + 9.46E-02 2.27E-02 K-40 3.88E-03 + 7.63E-03 1.21 E-02 MN-54 2.14E-04 + 5.09E-04 7.63E-04 MN-54 -1.51E-04 + 5.71 E-04 8.94E-04 FE-59 -7.75E-05 + 3.76E-03 6.16E-03 FE-59 9.42E-05 + 2.11E-03 3.42E-03 CO-60 3.21E-04 + 4.65E-04 6.11E-04 CO-60 0.00E+00 + 1.75E-04 2.88E-04 ZN-65 .- 2.55E-05 + 1.1OE-03 1.79E-03 ZN-65 -6.22E-04 + 1.70E-03 2.63E-03 ZRNB-95 3.73E-04 + 1.47E-03 2.29E-03 ZRNB-95 1.28E-05 + 1.61 E-03 2.64E-03 CS-134 -5.41 E-05 + 6.53E-04 1.06E-03 CS-134 4.49E-07 + 4.74E-04 7.78E-04 CS-137 -1.76E-04 + 5.65E-04 8.85E-04 CS-1 37 -1.16E-04 + 5.52E-04 8.76E-04 BALA1 40 -6.19E-03 + 2.21 E-02 3.40E-02 BALA140 0.OOE+00 + 8.20E-03 1.35E-02 RU-1 06 -1.42E-03 + 4.99E-03 7.83E-03 RU-106 -5.14E-04 + 4.64E-03 7.48E-03 Location and Quarter Station 6 1st Q 2013

  • Location and Quarter Station 6 2nd Q 2013 Nuclide RQ Activity Error MDA Nuclide RG Activity Error MDA BE-7 + 7.05E-02 + 1.37E-02 1.02E-02 BE-7 + 1.03E-01 + 1.59E-02 1.02E-02 K-40 -2.42E-03 + 9.69E-03 5.97E-03 K-40 7.38E-04 + 6.30E-03 1.10E-02 MN-54 1.26E-04 + 5.90E-04 9.34E-04 MN-54 -6.51E&05 + 6.95E-04 1.13E-03 FE-59 ' 0.OOE+00 + 3.33E-03 5.48E-03 FE-59 -1.11E-03 + 3.76E-03 5.86E-03 1.04E-03 CO-60 -4.55E-05 + 4.14E-04 6.58E-04 CO-60 1.52E-04 + 6.63E-04 ZN-65 3.82E-04 + 1.38E-03 2.14E-03 ZN-65 -4.61E-04 + 2.OOE-03 3.18E-03 ZRNB-95 0.OOE+00 + 1.97E-03 3.24E-03 ZRNB-95 -1.24E-04 + 1.54E-03 2.50E-03 CS-1 34 -1.34E-05 + 4.34E-04, 7.10E-04 CS-1 34 -4.32E-04 + 7.24E-05 1.68E-04 CS-137 -2.97E-05 + 5.51E-04 8.98E-04 CS-1 37 -2.85E-05 + 3.40E-04 5.47E-04 BALA 140 1.23E-03 + 8.56E-03 1.35E-02 BALA140 9.60E-04 + 1.04E-02 1.67E-02 RU-106 0.OOE+00 + 2.71 E-03 4.46E-03 RU-106 0.OOE+00 + 2.77E-03 4.55E-03 Location and Quarter Staation 6 3rd Q 2013 Location and Quarter Station 6 4th Q 2013

'Nuciide RQ Activity Error MDA Nuclide RQ Activity Error MDA

+

BE-7 + 1.52E-01 + 1.77E-02 9.13E-03 BE-7 8.43E-02 + 1.67E-02 1.06E-02 K-40 6.97E-04 + 4.70E-03 9.04E-03 K-40 1.65E-03 + 6.32E-03 1.07E-02 MN-54 -2.03E-05 + 4.30E-04 7.01 E-04 MN-54 -1.10E-05 + 5.97E-04 9.78E-04 FE-59 -2.25E-04 + 2.61 E-03 4.21 E-03 FE&59 0.OOE+00 + 1.07E-03 1.75E-03 CO-60 -1.36E-04 + 2.78E-03 7.25E-04 CO-60 0.OOE+00 + 8.78E-04 1.44E-03 ZN-65 0.OOE+00 + 2.29E-03 3.76E-03 ZN-65 0.OOE+00 + 2.63E-03 4.32E-03 ZRNB-95 1.22E-04 + 1.08E-03 1.73E-03 ZRNB-95 -4.84E-04 + 1.80E-03 2.83E-03 CS-134 -2.1OE-04 + 4.46E-04 6.91 E-04 CS-134 7.09E-05 + 4.58E-04 7.34E-04 CS-137 *0.OOE+00 + 3.88E-04 6.37E-04 CS-137 1.98E-04 + 4.16E-04 6.10E-04 BALA140 -3.44E-05 + 1.24E-02 2.04E-02 BALA140 0.OOE+00 +_ 2.29E-02 3.76E-02 RU-106 2.08E-03 + 3.40E-03 4.97E-03 RU-106 -1.10E-03 + 5.23E-03 8.32E-03 RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit.

1st Q 1/2/13 to 4/2/13 - 2nd Q 4/2/13 to 7/2/13 - 3rd Q 7/2/13 to 10/1/13 - 4th Q 10/1/13 to 12/31/13 -Page 2 of 6

I TABLE A-3.1 GAMMA SPECTROMETRY RESULTS OF. AIRPARTICULATE; FILTERS Results in pCi/cubic meter, results decay corrected to midpoint of the sample collection period I

Location and Quarter *Station.7

'Nucide RQ Activity

  • Error 1st Q 2013 MDA Location and.Quarter.

!Nuciide RQ, Activity .

Station 7 2nd Q 2013 Error MDA I

BE-7 + 9.34E-02 + 1.48E-02 8.51 E-03 BE-7 + 9.61E-02+ 1.58E-02 1.02E-02 K-40 MN-54 FE-59

-6.19E-04 + 1.06E-02

-3.97E-05 + 5.17E-04 2.12E-03. + 2.57E-03 1.13E-02 8.37E-04 3.24E-03 K-40 MN-54

  • FE-59 4.23E-03 + 6.85E-03 7.08E-05 + 5.52E-04

-8.43E-04 + 3.17E-03 1.07E-02 8.86E-04 4.91E-03 I

CO-60 -1.41E-04 + 5.56E-04 8.62E-04 ZN-65 ZRNB-95 CS-1 34 2.14E-04 + 1.25E-03

-1.09E-05 + 1.05E-03 0.00E+00 + 8.28E-04 1.98E-03 1.72E-03 1.36E-03 CO-60 ZN-65 ZRNB-95

-1.11E-04 + 7.30E-04 0.OOE+00. + 3.06E-03

  • -3.78E-04 + 1.60E-03 1.17E-03 5.03E-03 2.53E-03 I

CS-1 34 -2.23E-04 + 6.14E-04 9.66E-04 CS-137 BALA140 RU-106 2.69E-05 + 4.98E-04 0.00E+00 + 1.43E-02

-1.37E-06 + 3.37E-03 8.10E-04 2.36E-02 5.53E-03 CS-137.

BALA140 RU-106

-1.40E-05 + 4.58E-04

-6.08E-04' + 9.23E-03

  • 5.19E-04 + 4.49E-03 7.49E-04 1.49E-02 7.23E-03 I

BE-7 Location and Quarter

!Nuclide

  • RQ Activity

+ 1.50E-0 1 +

Station 7 Error 1.71 E-02 3rd Q 2013 MDA 7.41 E-03 BE-7 Location and Quarter Nuciide RQ Activity

+ 8.40E-02 +

Station 7 4th Q 2013 Error 1.61 E-02 MDA 1.01 E-02 I

K-40 1.56E-0.3+ 4.43E-03 8.43E-03 K-40 -2.38E-03 + 9.51 E-03 5.86E-03 MN-54

0.OOE+0' 0+

2.68E-0. 5+

3.75E-04 3.04E-03 4.14E-04 6.15E-04 4.99E-03 7.08E-04 MN-54 FE-59 CO-60 1.42E-04

-8.27E&04 2.03E-04

+

+

+

5.64E-04 2.92E-03 6.50E-04 8.86E-04 4.45E-03 1.01 E-03 I

ZN-65 3.66E-0 4+ 9.17E-04 1.37E-03 ZN-65 -2.05E-04 +

1.09E-03 1.71 E-03 ZRNB-95 CS-134 CS-1 37

-3.23E-0 4+

3.OOE-0 5+

0.OOE+O00+

1.47E-03 3.40E-04 3.93E-04 2.33E-03 5.50E-04 6.45E-04 ZRNB-95 CS-1 34 CS-1 37 6.36E-04 1.33E-05

-1.08E-05

+

+

+

1.06E-03 3.91 E-04 4.68E-04

.1.45E-03 6.38E-04 7.66E-04 I

BALA140 0.OOE+0 0+ 2.21 E-02 3.63E-02 BALA 40 -2.54E-03 +

1.66E-02 2.63E-02 RU-106 -2.65E-0, 4_+

Location and Quarter 3.01 E-03 Station 8 4.86E-03 1st Q 2013 RU-106 2.16E-05 Location and Quarter

+

4.15E-03 Station 8 6.82E-03 2nd Q 2013 I

Nuclide RQ Activity Error MDA Nuclide RQ Activity, Error MDA BE-7 XK-40

+ 9.93E-02 +

3.27E-03 +

1.60E-02 6.95E-03 9.50E-03 1.12E-02 BE-7 K-40

+ 8.89E-02 +

1.18E-03 +

1.46E-02 6.07E-03 8.60E-03 1.04E-02 I

MN-54 -3.15E-04 + 7.43E-04 1.15 E-03 MN-54 2.49E-04 + 4.94E-04 7.26E-04 FE-59 CO-60 ZN-65

-1.16E-03 0.OOE+00

-4.26E&04

+

+

+

3.68E-03 6.15E-04 1.59E-03 5.69E-03

.101 E-03 2.50E-03 FE-59 CO-60 ZN-65 1.24E-03 2.43E-04 0.OOE+00

+

+

+

2.40E-03 5.88E-04 1.22E-03 3.36E-03 8.81 E-04 2.01 E-03 I

ZRNB-95 0.OOE+00 + 9.17E-04 1:51E-03 ZRNB-95 2.04E-04 + 1.53E-03 2.46E-03 CS-134.

CS-1 37 BALA140 1.14E-04 1.99E-04 3.15E-03

+

+

+

3.91 E-04 5.04E-04 1.19E-02 6.07E-04 7.70E-04 1.84E-02 CS-1 34 CS-137 BALA140 1.96E-05 1.49E-04

-4.55E-04

+

+

+

4.40E-04 5.20E-04 1.22E-02 7.18E-04 8.15E-04 1.98E-02 I

RU-106 6.61E-05 + 5.06E-03' 8.30E-03 RU-106 -1.52E-03 + 4.97E-03 7.78E-03 Location and Quarter

-Nuclide RQ Activity Station 8 Error 3rd Q 2013 MDA Location and Quarter Nuclide RQ Activity Station 8 Error 4th Q 2013 MDA I

BE-7 + 1.56E-01 + 1.94E-02 6.69E-03 BE-7 + 7.79E-02 + 1.44E-02 7.90E-03 K-40 MN-54 FE-59

-2.77E-03

-1.59E&04 0.OOE+00

+

+

+

8.18E-02 5.38E-04 3.87E-03 1.42E-02 8.36E-04 6.36E-03 K-40 MN-54 FE-59 1.10E-03 2.17E-04

-1.42E-03

+

+

+

6.76E-03 5.65E-04 4.23E-03 1.15E-02 8.62E-04 6.54E-03 I

CO-60 1.58E-05 + 5.12E-04 8.36E-04 CO-60 . -1.02E-04 + 5.12E-04 8.01 E-04 ZN-65 ZRNB-95 CS-1 34

-2.13E-04

-3.69E-04

-5.50E-05

+

+

+

1.44E-03 1.50E-03 4.40E-04 2.31 E-03 2.35E-03 7.1 OE-04 ZN-65 ZRNB-95 CS-134 0.OOE+00 0.OOE+00 0.OOE+00

+

+

+

2.53E-03 1.52E-03 6.31 E-04 4.16E-03 2.50E-03 1.04E-03 I

1.72E-05 + 7.34E-04 CS-137 -7.42E-05 + 8.50E-04 I

CS-137 4.49E-04 5.29E-04 BALA140 -6.18E-03 + 2.24E-02 3 46E-02 BALA140 0.OOE+00 + 5.18E-03 8.52E-03 RU-106 1.45E-05 + 3.81 E-03, 6.26E-03 RU-106 -7.17E-04 + 4.09E-03 6.51 E-03 RQ = Results Qualifier. If blank, result is less than detection limit. If '+", result is above detection limit. I 1st Q 1/2/13 to 4/2/13 - 2nd Q 4/2/13 to 7/2/13 - 3rd Q 7/2/13 to 10/1/13 - 4th Q 10/1/13 to 12/31/13 Page 3 of 6 I

TABLE A-3.1 GAMMA'SPECTROMETRY RESULTS OF AIR PARTICULATE FILTERS Results in pCi/cubic meter, results decay corrected to mid point of the sample collection period Location and Quarter St*ation 9 1st Q 2013 Location and Quarter 'Station 9 2nd Q 2013 Nuiclde- R-Q -Act-iity- Error-.- MDA -1 Nuclide RQ Activity-- Error .MDA BE-7 + 6.87E-02 + 1.38E-02 9.97E-03 BE-7 + 9.72E-02 + 1.50E-02 8.30E-03 K-40 -2.50E-03 + 1.00E-02 6.. 7E-03 K-40 -5.77E-05 + 5.63E-03 9.72E-03 MN-54 -6.71E-05 + 5.68E-04 9.13E-04 MN-54 5.16E-07 + 4.39E-04 7.22E-04 FE-59 -4.42E-04 + 3.38E-03 5.40E-03 FE-59 3.68E-05 + 2.94E-03 4.83E-03 CO-60 3.35E-04 + 6.04E-04 8.70E-04 CO-60 -1.79E-05 + 3.71E-04 6.OOE-04 ZN-65 -2.70E-04 + 1.42E-03 2.24E-03 ZN-65 1.30E-05 + 1.26E-03 2.06E-03 ZRNB-95 -7.18E-04 + 1.70E-03 2.61 E-03 ZRNB-95 6.83E-04 + 1.25E-03 1.82E-03 CS-134 1.79E-06 + 5.39E-04. 8.85E-04 CS-1 34 4.41 E-05 + 4.08E-04 6.58E-04 CS-1 37 2.60E-05 + 5.04E-04 8.21 E-04 CS-1 37 -1.38E-06 + 5.03E-04 8.26E-04 BALA140 0.OOE+00 + 1.55E-02 2.55E-02 BALA140 -1.45E-04 + 8.62E-03 1.41 E-02 RU-106 -1.05E-05 + 3.88E-03 6.37E-03 RU-1 06 5.89E-04 + 3.56E-03 5.65E-03 .

Location and Quarter Station 9 3rd Q 2013 Location and Quarter Station 9 4th Q 2013

,!Nuclide RQ Activity Error MDA ;Nuclide RQ Activity Error MDA BE-7 + 1.36E-01 + 1.60E-02 5.95E-03 BE-7 + 9.62E-02 + 1.86E-02 1.17E-02 K-40 -1.06E-03 + 5.77E-03 8.25E-03 K-40 * -1.25E-03 + 2.24E-02 1.28E-02 MN-54 0.00E+00 + 4.34E-04 7.13E-04 MN-54 2.53E-04 + 6.42E-04 9.87E-04 FE-59 2.09E-04 + 2.20E-03 3.52E-03 FE-59 -6.31 E-04 + 4.31 E-03 6.91 E-03 CO-60 -1.01E-04 + 4.05E-04 3.15E-04 CO-60 0.OOE+00 + 5.99E-04 9.84E-04 ZN-65 -2.89E-04 + 1.18E-03 1.86E-03 ZN-65 -1.45E-03 + 2.70E-03 4.20E-03 ZRNB-95 0.OOE+00 + 1.14E-03 1.88E-03 ZRNB-95 -1.74E-04 +

  • 1.87E-03 3.03E-03 CS-1 34 -1.72E-05 + 3.29E-04 5.36E-04, CS-134 -1.51 E-04 + 6.25E-04 9.99E-04 CS-1 37 -1.19E-04 + 4.05E-04 6.34E-04 CS-137 -1.47E-04 +
  • 4.68E-04 7.24E-04 BALA140 0.00E+00 + 3.09E-02 5.08E-02 BALA140 5.78E-03 + 1.99E-02 3.08E-02 RU-106 -7.41 E-05 + 3.17E-03 5.19E-03 RU-106 1.17E-03 + 5.20E-03 8.25E-03 Location and Quarter Station 21 lstQ 2013 Location and Quarter " Station 21 2nd Q 2013 Nu;clidhe RQ Activity Error MDA Nuclide RQ Activity Error MDA BE-7 + 7.94E-02 + 1.44E-02 9.45E-03 BE-7 + 9.28E-02 + 1.57E-02 1.05E-02 K-40 2.15E-03 + 7.12E-03 1.18E-02 K-40
  • 8.62E-04 + 6.88E-03 1-.18E-02 MN-54 2.55E-04 + 4.87E-04 7.08E-04 MN-54 -3.90E-05 + 5.15E-04 8.35E-04 FE-59 -1.24E-03 + 3.58E-03 5.50E-03 FE-59 0.OOE+00 + .3.34E-03 5.48E-03 CO-60 -1.79E-04 + 5.33E-04 8.05E-04 CO-60 8.28E-05 + 5.58E-04 8.88E-04 ZN-65 -7.80E-05 + 1.13E-03 1.83E-03 ZN-65 -1.90E-04 + 1.60E-03 2.58E-03 ZRNB-95. 2.01E-05 + 1.23E-03 2.01E-03 ZRNB-95 1.85E-04 + 1.53E-03 2.47E-03 CS-1 34 1.61E-04 + 4.38E-04 6.75E-04 CS-1 34 0.OOE+00 + 9.83E-04 1.62E-03 CS-137 2.80E-04 + 4.72E-04 6.86E-04 CS-137 -8.96E-05 + 5.04E-04 8.04E-04 BALA140 -8.83E-04 + 1.03E-02. 1.65E-02 BALA140 -1.24E-03 + 9.85E-03 1.57E-02 RU-1 06 1.26E-03 _+ 4.86E-03 7.65E-03 RU-106 8.28E-04 + 3.30E-03 5.11E-03 Location and Quarter Station 21 3rd Q 2013 Location and Quarter Station 21 4th Q 2013 Nuclide "Ra Activity Error MDA Nuclide RQ Activity Error - MDA BE-7 + 1.48E-01 + 2.16E-02 1.16E-02 BE-7 + 8.26E-02 + 1.57E-02 8.64E-03 K-40 8.68E-04 + 6.55E-03 1.13E-02 K-40 -2.65E-03 + 1.44E-01 1.39E-02 MN-54 -2.13E-04 + 7.23E-04 1.14E-03 MN-54 0.OOE+00 + 7.64E-04 1.26E-03 FE-59 0.OOE+00 + 1.16E-03 1.91 E-03 FE-59 -2.08E-04 + 3.17E-03 5.13E-03 CO-60 9.37E-05 + 4.28E-04 6.57E-04 CO-60 -6.48E-05 + 6.72E-04 1.08E-03 ZN-65 1.24E-04 + 1.14E-03 1.83E-03 ZN-65 0.OOE+00 + 4.34E-03 7.14E-03 ZRNB-95 -4.55E-04 + 1.67E-03 2.61 E-03 ZRNB-95 -3.10E-04 + 1.41 E-03 2.21 E-03 CS-1 34 0.OOE+00 + 7.43E-04 1.22E-03 CS-134 -2.21E-05 + 4.34E-04 7.08E-04 CS-137 * -9.56E-05 + 5.23E-04 8.32E-04 CS-1 37 1.52E 04 + 4.50E-04 6.91 E-04 BALA140 -4.92E-03 + 2.48E-02 3.90E-02 BALA140 0.OOE+00 + 5.34E-03 8.78E-03 RU-106 -6.64E05 + 1.95E-03 6.48E-03 RU-1 06 2.OOE-03 + 4.95E-03 7.61 E-03 RQ = Results Qualifier. If blank, result is less than detection limit. If "4", result is above detection limit.

.st Q 1/2/13 to 4/2/13 - 2nd Q 4/2/13 to 7/2/13 - 3rd Q 7/2/13 to 10/1/13 - 4th Q 10/1/13 to 12/31/13 Page 4 of 6

I TABLE A-3.1 GAMMA SPECTROMETRY RESULTS OF AIR PARTICULATE FILTERS Results in pCi/cubic meter, results decay corrected to mid point of the sample collection period I

Location and Quarter

'Nuclide Rd Activity Station 23 1st Q 2013 Error., MDA Location and Quarter,

Nuclide RQ' Activity .

Station 23 *2nd Q 2013 Error . MDA I

BE-7 + 8.11E-02 + 1.40E-02 8.19E-03 BE-7 + 9.46E-02 + 1.46E-02 6.76E-03 K-40 MN-54 FE-59 1.40E-03

-1.98E-04

-7.65E-04

+

+

+

7.59E-03 7.03E-04 3.60E-03 1.28E-02 1.11E-03 5.69E-03 K-40 MN-54 FE-59 3.77E-03 + 6.17E-03

-3.49E-05'+

0.00E+00 + 4.79E-03 5.76E-04 9.64E-03 9.37E-04 7.88E-03 I

CO-60 0.00E+00 + 6.06E-04 9.96E-04 -5.53E-05 + 4.92E-04 7.85E-04 I

CO-60 ZN-65 0.00E+00 + 2.18E-03 3.58E-03 ZN-65 5.05E-04.+ 1.30E-03 1.96E-03 ZRNB-95 6.14E-04 + 1.28E-03 1.88E-03 ZRNB-95 1.65E-05 + 1.23E-03 2.02E-03 CS-134 1.45E-04 + 4.48E-04 6.98E-04 CS-1 34 -1.37E-04 + 5.04E-04 7.96E-04 CS-1 37 BALA140 RU-106

-1.93E-04 1.49E-03 1.92E-03

+

+

+

5.76E-04 7.70E-03 4.52E-03 8.97E-04 1.18E-02 6.88E-03 CS-1 37 BALA140 RU-106 2.23E-05 + 5.11E-04 3.86E-04 + 1.35E-02 1.27E-03 + 4.20E-03 8.35E-04 2.21 E-02 6.51 E-03 I

BE-7 Location andQuarter Nuclide RQ Activity

+ 1.63E-01 +

Station 23 3rd Q 2013 Error ý MDA 1.90E-02 6.80E-03 BE-7 Location and Quarter Nuclide RQ Activity

+ 7.88E-02 +

Station 23 4th Q 2013 Error 1.46E-02 MDA 7.35E-03 I

K-40 1.88E-03 + 6.93E-03 1.24E-02 K-40 2.28E-03 .+ 6.64E-03 1.10E-02 MN-54 FE-59 CO-60

-1.09E-04 +

-1.51E-04 +

7.01E-05+

5.80E-04 2.93E-03 5.18E-04 9.26E-04 4.75E-03 8.69E-04 MN-54 FE-59 CO-60 1.45E-04 0.OOE+00 0.OOE+00

+

+

+

5.13E-04 3.96E-03 6.16E-04 7.93E-04 6.52E-03 1.01E-03 I

ZN-65 6.96E-04 + 1.18E-03 1.70E-03 ZN-65 -1.26E-03 + 2.24E-03 3.42E-03 ZRNB-95 CS-134 CS-137 1.11 E-04, +

-1.63E-05 +

1.56E-04 +

1.34E-03 4.09E-04 4.38E-04 2.17E-03 6.68E-04 6.74E-04 ZRNB-95 CS-134 CS-137 7.03E-04

-4.57E-04 1.52E-04

+

+

+

1.49E-03 7.37E-04 5.38E-04 2.22E-03 1.13E-03 8.42E-04 I

BALA1 40 0.OOE+00 + 6.33E-03 1.04E-02 BALA140 2.43E-03 + 2.1 OE-02 3.38E-02 RU-106 -3.22E-06 + 4.24E-03 Location and Quarter. Station 40 1st Q2013 6.97E-03 RU-106 -2.56E-05 Location and Quarter

+ 4.79E-03 7.87E-03

'Station 40 2nd Q2013 I

Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA BE-7 K-40

+ 9.81E-02 + 1.58E-02 1.24E-03 + 6.49E-03 9.91 E-03 1.11E-02 BE-7 K-40

+ 9.29E-02

-2.02E-04

+ 1.52E-02

+ 6.16E-03 9.08E-03 9.57E-03 I

MN-54 2.92E-04 .+ 5.12E-04 7.43E-04 MN-54 -2.48E-04 + 6.86E-04 1.07E-03 FE-59 CO-60 ZN-65

-5.67E-05 + 2.82E-03

-1.74E-04 + 7.1 OE-04

-5.47E-04 + 1.58E-03 4.61 E-03 1.12E-03 2.44E-03 FE-59

.CO-60 ZN-65 0.OOE+00

-4.07E-05

-3.31 E-04

+ 3.37E-03

+ 4.94E-04

+ 1.15E-03

5. 54E-03 7.96E-04 1.77E-03 I

ZRNB-95 4.40E-04 + 1.09E-03 1.62E-03 ZRNB-95 5.81 E-04 + 1.35E-03 2.04E-03 CS-134 CS-1 37 BALA140

-4.94E-05 + 3.70E-04 0.OOE+00 + 6.27E-04 0.OOE+00 + 1.52E-02 5.93E-04 1.03E-03 2.50E-02 CS-1 34

.CS-137 BALA140:

.- 6.87E-05 0.OOE+00

-3.26E-03

+ 4.64E-04

+ 6.83E-04

+ 1.22E-02 7.45E-04 1.12E-03 1.89E-02 I

RU-1 06 -2.74E-04 + 4.08E-03 6.62E-03 RU-106 2.50E-04 + 3.76E-03 6.1OE-03 Location and Quarter Nuclide RQ. Activity Station 40 3rd Q 2013 Error MDA Location and Quarter

Nuclide RQ Activity

. Station 40 Error 4th 0 2013 MDA I

BE-7 + 1.51E-01 + 1.93E-02 5.24E-03 BE-7 + 8.65E-02 + 1.63E-02 1.08E-02 K-40 MN-54 FE-59

-1.31E-04 +

3.94E-05 +

-1.61E-03 +

5.78E-03 5.03E-04 4.46E-03 9.54E-03 8.14E-04 6:84E-03 K-40 MN-54 FE-59

-3.64E-04 9.32E-05 0.OOE+00

+

+

+

8.28E-03 6.16E-04 1.04E-03 1.10E-02 9.87E-04 1.70E-03 I

CO-60 2.80E-05 + 3.71E-04 . 5.94E-04 CO-60 2.69E-04 + 6.70E-04 1.02E-03 ZN-65 ZRNB-95 CS-134 1.02E-04 0.OOE+00

-3.51E-06

+

+

+

1.12E-03 1.61E-03 4.36E-04 1.81E-03 2.64E-03 7.16E-04 ZN-65 ZRNB-95 CS-134 2.64E-04

-5.04E-04

-3.72E-04

+

+

+

8.48E-04 1.52E-03 6.82E-04 1.25E-03 2.34E-03 1.06E-03 I

CS-137 -1.09E-04 + 5.90E-04 9.44E-04 I

CS-137 -1.81 E-04 + 6.18E-04 9.75E-04 BALA140 5.17E-03 + 1.51E-02 2.18E-02 BALA140 5.76E-04 + 1.60E-02 2.61E-02 RU-1 06 2.32E-05 + 3.04E-03 4.98E-03 RU-106 -2.78E-04 + 5.24E-03 8.55E-03 RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit.

I 1st Q 1/2/13 to 4/2/13 - 2nd Q 4/2/13 to 7/2/13 - 3rd Q 7/2/13 to 10/1/13 -4th Q 10/1/13 to 12/31/13 Page 5 of 6 I

1'ý". TABLE A-3.1 GAMMA SPECTROMETRY RESULTS OF AIR PARTICULATE FILTERS Results in pCi/cubic meter, results decay corrected to mid point of the sample collection period Location-and Quarter Station 48 1st Q 2013 Location and Quarter Station 48 2nd Q 2013 Nu*de R-Q Activity -- ~rror - " D - Nuclide RQ Activity Error . DA BE-7 + 9.45E-02 + 1.47E-02 7.21 E-03 BE-7 + 9.07E-02 + 1.56E-02 1.01 E-02 K-40 1.29E-04 + 6.46E-03 1.14E-02 K-40 -2.38E-03 + 9.53E-03 5.88E-03 MN-54 -1.29E-04 + 6.29E-04 1.00E-03 MN-54 1.46E-04 + 4.05E-04 6.05E-04 FE-59 0.OOE+00 + 3.32E-03 5.45E-03 FE-59 1.17E-03 + 2.70E-03 3.94E-03 CO-60 1.42E-04 + 5.45E-04 8.44E-04 CO-60 3.06E-04 + 5.03E-04 6.95E-04 ZN-65 0.OOE+00 + 2.11E-03 3.46E-03 ZN-65 0.00E+00 + 2.75E-03 4.52E-03 ZRNB-95 8.42E-05 + 1.18E-03 1.90E ZRNB-95 0.OOE+00 + 1.73E-03 2.85E-03 CS-134 -4.55E-05 + 3.98E 6.42E-04 CS-134 -1.77E-04 + 5.77E-04 9.13E-04 CS-1 37; -7.98E-06 + 5.07E-04 8.32E-04 CS-137 -1.10E-05 + 4.51E-04 7.38E-04 BALA1 40 2.19E-03 + 1.07E-02 1.68E-02 BALA140 -2.56E-03 + 1.10E-02 1.69E-02 RU-1 06 -1.92E-03 -+ 5.28E-03 8.22E-03 RU-106 0.00E+00 + 5.52E-03 9.08E-03 Location and Quarter Station 48 3rd Q 2013 Location and Quarter Station 48. 4th Q 2013

'Nuclide RQI Activity Error MDA *Nucide RQ Activity Error- MDA BE-7 + 1.31E-01 + 1.63E-02 7.69E-03 BE-7 + 8.65E-02 + 1.67E-02 9.32E-03 K-40 3.85E-04 + 4.36E-03 8.73E-03 K-40 -2.45E-03 + 6.34E-01 1.41 E-02 MN-54 -1.35E-05 + 4.19E-04 6.85E-04 MN-54 1.34E-04 + 3.71 E-04 5.44E-04 FE-59 -6.69E-04 + 2.96E-03 4.64E-03 FE-59 0.OOE+00 + 4.02E-03 6.61 E-03 CO-60 -1.20E-04 + 6.35E-03 8.21 E-04 CO-60 -9.42E-08 + 6.39E-04 1.02E-03 ZN-65 5.58E--05 + 9.37E-04 1.52E-03 ZN-65 -7.95E-04 + 2.16E-03 3.37E-03 ZRNB-95 -6.05E-05 + 1.07E-03 1;73E-03 ZRNB-95 1.89E-05 + 1.31E-03 2.14E-03 CS-1 34 1.40E-04 + 3.21 E-04 4.86E-04 CS-134 -1.87E-04 + 5.51 E-04 8.63E-04 CS-1 37 8.85E-05 + 3.23E-04 5.02E-04 CS-1 37 3.08E-05 + 4.45E-04 7.22E-04 BALA140 -5.41 E-04 + 1.25E-02 2.03E-02 BALA140 0.00E+00 + 5.68E-03 9.34E-03 RU-106 6.46E-04 " 3.07E-03 4.84E-03 .RU-106 -1.23E-03 + 4.29E-03 6.65E-03 Location and Quarter Station 57 1st Q 2013 Location and Quarter Station 57 2nd Q 2013 Nuclide RQ Activity Error MDA - Nuclide RQ Activity Error MDA BE-7 + 9.13E-02 + 1.52E-02 9.21 E-03 BE-7 + 1.12E-01 + 1.70E-02 1.01 E-02 K-40 1.48E-03 + 6.42E-03 1.09E-02 K-40 4.81 E-04 + 6.25E-03 1.10E-02 MN-54 2.38E-04 + 5.05E-04 7.46E-04 MN-54 8.59E-05 + 4.65E-04 7.33E-04 FE-59 -4.08E-04 + 2.49E-03 3.90E-03 FE-59 1.84E-04 + 3.06E-03 4.96E-03 CO-60 -5.24E-05 + 6.29E-04 1.02E-03 CO-60 0.OOE+00 _+ 6.02E-04 9.90E-04 ZN-65 0.OOE+00 + 2.85E-03 4.69E-03 ZN-65 -1.11E-03+ 2.05E-03 3.13E-03 ZRNB-95 O.OOE+00 + 9.30E-04 1.53E-03 ZRNB-95 6.03E-05 + 1.30E-03 2.11E-03 CS-1 34 -6.26E-05 + 4.32E-04 6.92E-04 CS-1 34 1.59E-04 + 4.67E-04 7.26E-04 CS-1 37 -1.20E-04 + 4.64E-04 7.25E-04 CS-137 -9.69E-06 + 3.91 E-04 6.40E-04 BALA140 0.OOE+00 + 3.81 E-03 6.27E-03. BALA140 -4.05E-03 + 1.31E-02 2.OOE-02 RU-1 06 -1.72E-03 + 5.53E-03 8.68E-03 RU-106 -6.74E-04 + 4.32E-03 6.90E-03 Location and Quarter Station 57 3rd Q 2013 Location and Quarter Station 57. 4th Q 2013 Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA BE-7 + 1.52E-01 + 2.06E-02 8.19E-03 BE-7 + 9.73E-02 + 1.77E-02 1.03E-02 K-40 -4.15E-03 + 3.12E-02 1.41 E-02 K-40 -2.91 E-03 + 6.62E-02 1.18E-02 MN-54 -1.44E-04 + 5.53E-04 8.63E-04 MN-54 0.OOE+00 + 1.43E-04 2.36E-04 FE-59 0.OOE+00 + 5.91 E-03 9.71 E-03 FE-59 5.04E-04 + 2.22E-03 3.36E-03 CO-60 -9.83E-05 +/- 5.85E-04 9.26E-04 CO-60 1.05E-04 + 5.03E-04 7.83E-04 ZN-65 -8.67E-05 + 1.42E-03 2.31 E-03 ZN-65 0.OOE+00 + 2.19E-03 3:60E-03 ZRNB-95 1.34E-04 + I1.68E-03 ZRNB-95 2.72E-03 -2.42E-04 + 1.65E-03 2.64E-03 CS-134 6.33E-05 + 3.59E-04 5.69E-04 CS-134 -1.76E-04 + 5.20E-04 8.14E-04 CS-137 -2.22E-05 + 3.86E-04 6.26E-04 CS-1 37 1.53E-06 + 4.17E-04 6.84E-04 BALA1 40 -3.77E-03 + 1.43E-02 2.11 E-02 BALA140 0.00E+00 + 5.45E-03 8.96E-03 RU-106 -4.79E-04 + 4.85E-03 7.84E-03 RU-106 6.53E-04 + 4.18E-03 6.67E-03 RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit.

1st Q 1/2/13 to 4/2/13 - 2nd Q 4/2/13 to 7/2/13 - 3rd Q 7/2/13 to 10/1/13 - 4th Q 10/1/13 to 12/31/13 Page 6 of 6

TABLE A-32' '

GAMMA SPECTROMETRY RESULTS OF AIR PARTICULATE FILTERS -

SUMMARY

Results in pCi/cubic meter, results decay corrected to midlpoint of the sample collection period I

Nuclide Average Activity Activity Low Activity . Average High MDA Number of Number of Samples Positive IDs I

BALA140 Ind -5.13E-04 -6.19E-03 5.17E-03 2.08E-02 44 0 BALA140 Cntl 1.41 E-03 ,-1 .45E-04 5.78E-03 3.03E-02 .4 0 BE-7 Ind 1.06E-01 7.05E-02 1.63E-01 9.07E-03 44 44 BE-7 CntI 9.96E-02 6.87E-02 1.36E-01 8.99E-03 4 4 CO-60 -Ind 1.78E-05 -1.79E-04 3.21 E-04 8.40E-04 44 0 CO-60 Cntl 5.38E-05 -1.01E-04 3.35E-04 6.93E-04 4 0 CS-134 Ind -4.16E-05 -4.57E-04 1.61 E-04 7.88E-04 44 0 CS-134 CntI -3.06E-05 -1.51 E-04 4.41 E-05 7.69E-04 4 0 CS-137 CS-1 37 Ind -3.87E-06 CntI -6.04E-05

-1.93E-04

-1.47E-04 2.80E-04 2.60E-05 7.63E-04 7.51 E-04 44 4

0 0

I FE-59 Ind -5.69E-05 -1.61 E-03 2.12E-03 4.86E-03 44 0 FE-59 Cntl -2.07E-04 -6.31 E-04 2.09E-04 5.16E-03 .4 0 K-40 Ind 2.22E-04 -4.15E-03 4.57E-03 1.08E-02 44 0 K-40 CntI -1.22E-03 -2.50E-03 -5.77E-05 9.23E-03 4 0 MN-54 Ind 2.54E-05 -3.15E-04 2.92E-04 8.40E-04 44 0 MN-54 Cntl 4.65E-05 -6.71 E-05 2.53E-04 8.34E-04 4 0 RU-1 06 Ind 9.20E-05 -1.92E-03 2.08E-03 6.87E-03 44 0 RU-106 .CntI 4.18E-04 -7.41 E-05 1.17E-03 6.37E-03 4 0 ZN-65 Ind -1.07E-04 -1.26E-03 6.96E-04 2.69E-03 44 0 ZN-65 Cntl -4.99E-04 -1.45E-03 1.30E-05 2.59E-03 4 0 ZRNB-95 Ind 2.25E-05 -5.04E-04 7.03E-04 2.26E-03 44 0 ZRNB-95 CntI -5.23E-05 -7.18E-04 6.83E-04 2.33E-03 4 0 I

I I

I Ind = Indication Stations Cntl = Control Stations Page 1 of 1

TABLE A-4.1 GAMMA SPECTROMETRY RESULTS. OF IODINE 131 ON CHARCOAL FILTERS Results in pCi/cubic meter, corrected for decay during collection period I'Station I Station 9 Collection Period RQ Activity Error MDA RQ Activity Error MDA 1/1/2013 - 1/8/2013 5.34E-03 + 9.07E-03 1.36E-02 6.42E-04 + 6.42E-03 1.03E-02 1/8/2013 - 1/15/2013 5.71E-03 + 8.44E-03 1.26E-02 3.22E-03 + 8.29E-03 1.29E-02 1/15/2013 - 1/22/2013 2.63E-03 + 6.75E-03 1.04E-02 ,-1.05E-03 + 8.74E-03 1.41E-02 1/22/2013 - 1/29/2013 O.OOE+00 + 1.34E-02 2.21E-02 -1.84E-03 + 1.12E-02 1.80E-02 1/29/2013 - 2/5/2013 2.97E-03 + .9.86E-03 1.55E-02 2.32E-03 + 1.09E-02 1.75E-02 2/5/2013 - 2/12/2013 -9.20E-04 + 8.77E-03 1.42E-02 -1.13E-03 + 8.58E-03 1.38E-02 2/12/2013 - 2/19/2013 -1.94E-03 + 8.42E-03 1.34E-02 -1.58E-03 + 8.28E-03 1.32E-02 2/19/2013 - 2/26/2013 1.58E-04 + 5.32E-03 8.70E-03 3.21E-03 + 8.75E-03 1.37E-02 2/26/2013 - 3/5/2013 1.15E-03 + 8.47E-03 1.37E-02 -4.39E-03 + 1.11E-02 1.75E-02 3/5/2013 - 3/12/2013 0.OOE+00 + 9.31E-03 1.53E-02 -1.68E-03 + 8.56E-03 1.37E-02 3/12/2013 - 3/19/2013 3.43E-05 + 8.35E-03 1.37E-02 -4.37E-04 + 7.79E-03 1.27E-02 3/19/2013 - 3/26/2013 -2.59E-04 + 7.93E-03 1.30E-02 2.31E-03 + 6.54E-03 1.01E-02 3/26/2013 - 4/2/2013 4.56E-03 + 7.68E-03 1.15E-02 2.75E-05 + 7.58E-03 1.25E-02 4/2/2013 - 4/9/2013 NVS 2.79E-03 + 7.81E-03 1.21E-02 4/9/2013 - 4/16/2013 -3.24E-04 + 8.15E-03 1.33E-02 O.OOE+00 + 6.33E-03 1.04E-02 4/16/2013 - 4/23/2013 -2.41E-03 + 1.01E-02 1.62E&02 2.61E-03 + 6.57E-03 1.01E-02 4/23/2013 - 4/30/2013 6.96E-05 + 7.61E-03 1.25E-02 0.OOE+00 + 1.05E-02 1.73E-02 4/30/2013 - 5/7/2013 3.45E-04 + 7.80E-03 1.27E-02 -1.08E-03 + 8.OOE-03 1.29E-02 5/7/2013 - 5/14/2013 0.OOE+00 + 6.85E-03 1.13E-02 3.31E-03 + 6.59E-03 9.91E-03 5/14/2013 - 5/21/2013 -2.11E-03 + 8.32E-03 1.32E-02 2.92E-03 + 7.03E-03 1.08E-02 5/21/2013 - 5/28/2013 -6.OOE-05 + 6.12E-03 1.OOE-02 0.OOE+00 + 9.27E-03 1.52E-02 5/28/2013 - 6/4/2013 -5.82E-05 + 6.25E-03 1.03E-02 -5.77E-04 + 6.69E-03 1.08E-02 6/4/2013 - 6/11/2013 0.OOE+00 + 9.70E-03 1.60E-02 4.48E-03 + 7.25E-03 1.07E-02 6/11/2013 - 6/18/2013 -1.06E-03 + 5.90E-03 9.38E-03 -1.05E-03 + 7.13E-03 1.15E-02 6/18/2013 - 6/25/2013 7.13E-04 + 7.20E-03. 1.17E-02 4.55E-03 + 7.31E-03 1.09E-02 6/25/2013 - 7/2/2013 -6.97E-05 + 6.26E-03 1.03E-02 -5.71E-04 + 6.72E-03 1.09E-02 7/2/2013 - 7/9/2013 4.90E-05 + 7.23E-03 1.19E-02 8.80E-04 + 7.60E-03 1.23E-02 7/9/2013 - 7/16/2013 3.22E-03 + 5.65E-03 8.23E-03 -1.53E&03 + 6.74E-03 1.07E-02 7/16/2013 - 7/23/2013 -2.36E-03 + 8.44E-03 1.34E-02 -5.36E-04 + 7.29E-03 1.18E-02 7/23/2013 - 7/30/2013 -2.15E-04 + 7;02E-03 1.15E-02 -4.50E-04 + 6.74E-03 1.1OE-02 7/30/2013 - 8/6/2013 7.46E-05 + 5.66E-03 9.28E-03 -2.51E-05 + 6.55E-03 1.08E-02 8/6/2013 - 8/13/2013 -5.35E-04 + 6.44E-03 1.04E-02 -3.58E-04 + 7.52E-03 1.23E-02 8/13/2013 - 8/20/2013 -4.38E-04 + 7.66E-03 1.25E-02 3.24E-03 + 7.64E-03 1.18E-02 8/20/2013 - 8/27/2013 0.OOE+00 + 1.15E-02 1.89E-02 -2.12E-03 + 8.27E-03 1.31E-02 8/27/2013 - 9/3/2013 -1.20E-03 + 7.85E-03 1.26E-02 -1.39E-03 + 7.64E-03 1.22E-02 9/3/2013 - 9/10/2013 3.65E-03 + 8.16E-03 1.26E-02 1.34E-03 + 7.16E-03 1.14E-02 9/10/2013 - 9/17/2013 1.88E-03 + 7.82E-03 1.24E-02 -6.85E-04 + 6.84E-03 1.11E-02 9/17/2013 - 9/24/2013 -8.62E-04 + 7.30E-03 1.18E-02 2.73E-03 + 7.84E-03 1.22E-02 9/24/2013 - 10/1/2013 -3.88E-04 + 7.79E-03 1.27E-02 0.OOE+00 + 9.20E-03 1.51E-02 10/1/2013 - 10/8/2013 -2.01E-03 + 8.60E-03 1.37E-02 5.91E-04 + 8.14E-03 1.32E-02 10/8/2013 - 10/15/2013 -1.06E-03 + 8.34E-03 1.35E-02 -3.35E-03 + 8.79E-03 1.37E-02 10/15/2013 - 10/22/2013 1.16E-03 + 7.32E-03 1.18E-02 6.56E-05 + 1.06E-02 1.74E-02 10/22/2013 - 10/29/2013 2.20E-03 + 7.78E-03 1.23E-02 -1.76E-03 + 7.97E-03 1.27E-02 10/29/2013 - 11/5/2013 3.61E-04 + 1.07E-02 1.75E-02 4.84E-03 + 8.55E-03 1.28E-02 11/5/2013 - 11/12/2013 -2.71E-05 + 8.55E-03 1.41E-02 -2.72E-04 + 5.52E-03 8.98E-03 11/12/2013 - 11/19/2013 -2.51E-03 + 8.27E-03 1.30E-02 0.OOE+00 + 9.66E-03 1.59E-02 11/19/2013 - 11/26/2013 -1.12E-04 + 9.11E-03 1.50E-02 -3.05E-03 + 1.04E-02 1.66E-02 11/26/2013 - 12/3/2013 -9.61E-04 + 8.04E-03 1.30E-02 1.41E-03 + 7.83E-03 1.25E-02 12/3/2013 - 12/10/2013 3.85E-03 + 1.06E-02 1.68E-02 4.95E-03 + 8.99E-03 1.38E-02 12/10/2013 - 12/17/2013 8.24E-03 + 9.07E-03 1.32E-02 0.OOE+00 + 8.65E-03 1.42E-02 12/17/2013 - 12/23/2013 4.78E-04 + 9.97E-03 1.63E-02 1.1OE-03 + 1.05E-02 1.70E-02 12/23/2013 - 12/31/2013 2.81E-03 + 7.14E-03 1.1OE-02 8.09E-04 + 7.71E-03 1.25E-02 NVS = Valid sample not obtained due to sampler failure.

RQ= Results Qualifer. If blank, result is less than detection limit. If "+', result is above detection limit. Page 1 of 6

I TABLE A-4.1 GAMMA SPECTROMETRY. RESULTS OF IODINE .131 ON CHARCOAL FILTERS Results in pCi/cubic meter, corrected for decay during collection period U

Station 4 Station 21 Collection Period RQ Activity Error MDA RQ Activity Error MDA 1/1/2013 - 1/8/2013 5.52E-03 + 9.36E-03 1.41E-02 6.30E-04 + 6.29E-03 1.01E-02 1/8/2013 -

  • 1/15/2013 -

1/22/2013 -

1/15/2013 1/22/2013 1/29/2013 6.01E-03 +

2.72E-03 +

0.OOE+00 +

8.89E-03 1.33E-02 6.98E-03 1.07E-02 1.39E-02 2.28E-02

. 3.07E-03 +

-1.02E-03: +

-1.75E-03 +

7.89E-03 8.51E-03 1.06E-02 1.23E-02 1.38E-02 1.71E-02 I

1/29/2013 -

2/5/2013.-

2/12/2013 -

2/5/2013 2/12/2013 2/19/2013 3.07E-03 +

-9.39E-04 +

-2.01E-03 +

1.02E-02 1.60E-02 8.95E-03 1.45E-02 8.71E-03 1.39E-02 2.34E-03 +

-1.02E-03 +

-1.57E-03 +

1.10E-02 7.77E-03 8.23E-03 1.75E-02 1.25E-02 1.32E-02 I

2/19/2013 - 2/26/2013 1.64E-04 + 5.52E-03 9.02E-03 3.05E-03 + 8.31E-03 1.30E-02 2/26/2013 -

3/5/2013 -

.3/12/2013 -

3/5/2013 3/12/2013 3/19/2013 1:.21E-03 +

0.OOE+00 +

3.31E-05 +

8.91E-03 1.44E-02 9.00E-03 1.48E-02 8.07E-03 1.33E-02

-4.40E-03 +

-1.73E-03 +

-4.39E-04 +

1.11E-02 8.81E-03 7.82E-03 1.75E-02 1.41E-02 1.28E-02 I

3/19/2013 - 3/26/2013 -2.56E-04 + 7.82E-03 1.28E-02 2.31E-03 + 6.54E-03 1.01E-02 3/26/2013 -

4/2/2013 -

4/2/2013 4/9/2013 4.55E-03 +

0.OOE+00 +

7.67E-03 1.15E-02 1.02E-02. 1.68E-02 2.75E-05 +

2.79E-03 +

7.58E-03 7.82E-03 1.25E-02 1.21E-02 I

4/9/2013 - 4/16/2013 -3.08E-04. + 7.73E-03 1.26E-02 0.OOE+00 + 6.64E-03 1.09E-02 4/16/2013 -

4/23/2013 -

4/30/2013 -

4/23/2013 4/30/2013 5/7/2013

-2.28E-03 +

.6.97E-05 +

3.45E-04 +,

9.58E-03' 1.53E-02 7.62E-03' 1.25E-02 7.80E-03 1.27E-02 2.73E-03 +

0.OOE+00 +

-1.20E-03 +

6.88E-03 1.09E-02 8.93E-03 1.06E-02 1.79E-02 1.44E-02 I

5/7/2013 - 5/14/2013 0.OOE+00 + 7.31 E-03 1.20E-02 2.99E-03 + 5.97E-03 8.97E-03 5/14/2013 -

5/21/2013 -

5/28/2013 -

5/21/2013 5/28/2013 6/4/2013

-2.33E-03 +

-6.53E-05 +

-6.24E-05 +

9.19E-03 1.46E-02 6.66E-03 1.09E-02 6.71E-03 1.1OE-02 3.05E-03 +

0.OOE+00 +

-5.69E-04 +

7.35E-03 9.16E-03 6.59E-03 1.13E-02 1.51E-02 I

1.07E-02 6/4/2013 -

6/11/2013 -

6/18/2013 -

6/11/2013 6/18/2013 6/25/2013 0.OOE+00 +

-1.10E-03 +

7.27E-04 +

1.05E-02 1.73E-02 6M11E-03 9.72E-03 7.35E-03 1.19E-02 4.55E-03 +

-1.15E-03 +

.4.79E-03 +

7.37E-03 7.75E-03 7.70E-03 1.09E-02 1.25E-02 1.14E-02 I

6/25/2013 - 7/2/2013 -7.29E-05 + 6.55E-03 1.08E-02 -5.98E-04 + 7.04E-03 1.14E-02

-7/2/2013 -

7/9/2013 -

7/16/2013 -

7/9/2013 7/16/2013

.7/23/2013 4.90E-05 +

3.28E-03 +

-2.51E-03 +

7.23E-03 1.19E-02 5.76E-03 8.38E-03 8.96E-03 1.42E-02 8.92E-04 +

-8.32E-04 +

-5.57E-04 +

7.71E-03 7.92E-03 7.57E-03 1.25E-02 1.28E-02 1.23E-02 I

'7/23/2013 - 7/30/2013 -2.18E-04 + 7.1OE-03 .1.16E-02 -4.59E-04 + 6.88E-03 1.12E-02 7/30/2013 8/6/2013 8/6/2013 8/13/2013

. 7.55E-05 +

.- 5.36E-04 +

5.73E-03. 9.39E-03 6.45E-03 1.05E-02

-2.61E-05 +

-3.70E-04 +

6.82E-03 7.77E-03 1.12E-02 1.27E-02 I

8/13/2013 - 8/20/2013 -4.53E-04 + 7.93E-03 1.29E-02 3.35E-03 + 7.88E-03 1.21E-02 8/20/2013 8/27/2013 9/3/2013 8/27/2013 9/3/2013 9/10/2013 0.OOE+00 +

-1.23E-03 +

3.82E-03 +

1.21E-02 1.98E-02 8.07E-03 1.30E-02 8.56E-03 1.32E-02

-2.16E-03 +

-1.47E-03 +

1.40E-03 +

8.40E-03 8.07E-03 7.47E-03 1.33E-02 1.29E-02 1.19E-02 I

9/10/2013 - 9/17/2013 2.02E-03 + 8.39E-03 1.33E-02 -7.19E-04 + 7.18E-03 1.16E-02 9/17/2013 9/24/2013 9/24/2013 10/1/2013

-8.94E-04 +

-4.07E-04 +

7.57E-03 1.22E-02 8.17E-03 1.33E-02 2.83E-03 +

0.OOE+00 +

8.14E-03 9.01E-03 1.27E-02 1.48E-02 I

.10/1/2013 - 10/8/2013 .-2.08E-03 + 8.89E-03 1.42E-02 5.83E-04 + 8.03E-03 1.31E-02 10/8/2013 10/15/2013 10/22/2013 10/15/2013 .

10/22/2013 10/29/2013

-1.09E-03 +

1.22E-03 +

2.27E-03 +

8.62E-03 1.39E-02 7.70E-03 1.24E-02 8.02E-03 1.27E-02

-3.29E-03 +

6.24E-05 +

-1.70E-03 +

8.61E-03 1.01E-02 7.72E-03 1.35E-02 1.65E-02 1.23E-02 I

10/29/2013 - 11/5/2013 3.72E-04 + .1.11E-02 1.81E-02 4.69E-03 + 8.30E-03 1.24E-02 11/5/2013 11/12/2013 11/19/2013 11/12/2013 11/19/2013 11/26/2013

-2.85E-05 +

-2.65E-03 +

-1.17E-04 +

9.02E-03 1.48E-02 8.70E-03 1.37E-02 9.58E-03 1.57E-02

-2.60E-04 +

0.OOE+00 .+

-3.04E-03 +

5.27E-03 9.60E-03 1.04E-02 8.58E-03 1.58E-02 1.66E-02 I

11/26/2013 - 12/3/2013 -1.01E-03 + 8.45E-03 1.37E-02 1.39E-03 +

12/3/2013 12/10/2013 12/10/2013 12/17/2013 3.98E-03 +

8.39E-03 +

1.09E-02 1.73E-02 9.23E-03 1.34E-02 5.17E-03 +

0.OOE+00 +

7.71E-03 9.39E-03 8.52E-03 1.24E-02 1.44E-02 1.40E-02 I

12/17/2013- 12/23/2013 4.70E-04 + 9.82E-03 1.60E-02 1.11E-03 + 1.05E-02 1.71E-02 12/23/2013- 12/31/2013 2.76E-03 + 7.01E-03 1.08E-02 8.26E-04 + 7.87E-03 1.28E-02 I

NVS = Valid sample not obtained due to sampler failure.

RQ= Results Qualifer. If blank, result is less than detection limit. If '"+, result is above detection limit. Page 2 of 6 U

TABLE A-4.1 GAMMA SPECTROMETRY RESULTS OF IODINE 131 ON CHARCOAL FILTERS Results in pCi/cubic meter, corrected for decay during collection period Station 5 Station 23 Collection -Period RQ Activity. Error MDA RQ Activity 2 Error. . MDA 1/1/2013 -, 1/8/2013 5.58E-03 + 9.46E-03. 1.42E-02 -9.36E-05 +. 9.56E-03 1.57E-02 1/8/2013 - 1/15/2013 5.87E-03 + 8.67E-03 1.30E-02 3.88E-03 + 8.43E-03 1.30E-02 1/15/2013 - 1/22/2013 2.67E-03 + 6.86E-03 1.05E-02 -8.15E-04 + 9.04E-03 1.47E-02 1/22/2013 - 1/29/2013 0.00E+00 + 1.37E-02 2.25E-02 3.62E-03 + 1.05E-02 1.65E-02 1/29/2013 - :2/5/2013 3.05E-03 + 1.01E-02 1.59E-02 1.73E-03 + 1.39E-02 2.26E-02 2/5/2013 -. 2/12/2013 -9.62E-04 + 9.17E-03 1.49E-02 0.OOE+00 + 7.95E-03 1.31E-02 2/12/2013 - 2/19/2013 -2.05E-03 + 8.88E-03 1.41E-02. 3.68E-03 + 7.99E-03 1.22E-02 2/19/2013 - 2/26/2013 1.51E-04 + 5.06E-03 8.27E-03 7.83E-04 + 7.99E-03 1.29E-02 2/26/2013 - 3/5/2013 1.09E-03 + 8.03E-03 1.30E-02 5.31E-05 + 8.77E-03 1.44E-02 3/5/2013 - 3/12/2013 0.00E+00 + 8.95E-03 1.47E-02 3.20E-04 + 6.58E-03 1.07E-02 3/12/2013 - 3/19/2013 3.18E-05 + 7.73E-03 1.27E-02 5.72E-04 + 8.40E-03 1.37E-02 3/19/2013- 3/26/2013 -2.46E-04 + 7.54E-03 1.23E-02 3.14E-04 + 7.15E-03 1A17E-02 3/26/2013 - 4/2/2013 4.56E-03 + 7.67E-03 1.1.5E-02 -2.37E-03 + 9.20E-03 1.46E-02 4/2/2013- . 4/9/2013 0.OOE+00 + 1.06E-02 1.75E-02 1.56E-03 + 8.23E-03 1.31E-02 4/9/2013 - 4/16/2013 ý3.28E-04 + 8.23E-03 1.35E-02 9.07E-04 + 6.34E-03 1.02E-02 4/1.6/2013 4/23/2013 -2.47E-03 + 1.04E-02 1.66E-02 -2.02E-03 + 9.06E-03 1.45E-02 4/23/2013 - 4/30/2013 7.16E-05 +. 7.83E-03 1.29E-02 6.15E-04 + 6.44E-03 1.04E-02 4/30/2013 - 5/7/2013 3.54E-04 + 8.OOE-03 1.31E-02 2.44E-03 + 7.79E-03 1.22E-02 5/7/2013 - 5/14/2013 0.OOE+00 + 6.89E-03 1.13E-02 -1.69E-03 + 7.60E-03 1.21E-02 5/14/2013 - 5/21/2013 -2.20E-03 + 8.68E-03 1.38E-02 -5.48E-04 + 8.04E-03 1.31E-02 5/21/2013 - 5/28/2013 -6.25E-05 + 6.37E-03 1.05E-02 1.53E-03 + 7.46E-03 1.19E&02 5/28/2013 6/4/2013 -6.29E-05 + 6.76E-03 1.11E-02 2.98E-03 + 7.21E-03 1.1OE-02 6/4/2013- 6/11/2013 0.OOE+00 + 1.02E-02 1.68E-02 1.22E-03 + 8.29E-03 1.33E-02 6/11/2013- 6/18/2013 -1.17E-03 + 6.51E-03 1.04E-02 4.22E-03 + 7.59E-03 1.14E-02 6/18/2013- 6/25/2013 7.85E-04 + 7.92E-03 .1'28E-02 -2.73E-03. + 8.39E-03 1.32E-02 6/25/2013- 7/2/2013 -7.74E-05 + 6.95E-03 1.14E-02 -1.04E-03 + 7.90E-03 1.27E-02 7/2/2013 - 7/9/2013 5.25E-05 + 7.74E-03 1.27E-02 .- 1.36E-03 + 6.96E-03 1.11E-02 7/9/2013 - 7/16/2013 3.31E-03 + 5.81.E-03 8.46E-03 -8.32E-04 + 7.92E-03 1.28E-02 7/16/2013- 7/23/2013 -2.55E-03 + 9.12E-03 1.45E-02 -6.65E-04 + 8.70E-03 1.41E-02 7/23/2013 7/30/2013 -2.11E-04 + 6.90E-03 1.13E-02 -3.68E-05 + 7.94E-03 1.31E-02 7/30/2013 - 8/6/2013 7.58E-05 + 5.75E-03 9.43E-03 -2.34E-03 + 7.67E-03 1.20E-02 8/6/2013 - 8/13/2013 -5.33E-04 + 6.42E-03. 1.04E-02 2.25E-03 + 7.88E-03 1.24E-02

.8/13/2013 - 8/20/2013 -4.51E-04 + 7.89E-03 1.29E-02 3.61E-03 + 9.38E-03. 1.45E-02 8/20/2013 - 8/27/2013 0.OOE+00 + 1.15E-02 1.90E-02 NVS

.8/27/2013 - 9/3/2013 -1.23E-03 + 8.06E-03 1.30E-02 0.OOE+00 + 1.07E-02 1.76E-02 9/3/2013 - 9/10/2013 3.66E-03 + 8.19E-03 1.26E-02 -5.09E-04 + 8.74E-03 1.43E-02 9/10/2013 - 9/17/2013 2.OOE-03 + 8.31E-03 1.32E-02 -2.70E-03 + 8.22E-03 1.28E-02 9/17/2013 - 9/24/2013 -8.86E-04 + 7.50E-03 1.21E-02 -6.29E-05 + 9.30E-03 1.53E-02 9/24/2013 - 10/1/2013 -3.94E-04 + 7.92E-03 1.29E-02 -1.76E-03 + 8.80E-03 1.41E-02 10/1/2013 - 10/8/2013 -2.04E-03 + 8.72E-03 1.39E-02 -2.35E-03 + 8.58E-03 1.35E-02 10/8/2013 - 10/15/2013 -1.09E-03 + 8.56E-03 1.38E-02 5.11E-05 + 8.25E-03 1.35E-02 10/15/2013 - 10/22/2013 1.19E-03 + 7.52E-03 1.21E-02: -2..30E-03 + 8.73E-03 1.38E-02 10/22/2013 - 10/29/2013 2.32E-03 + 8.18E-03 1.29E-02 -2.83E-03 + 1.09E-02 1.74E-02 10/29/2013 - 11/5/2013 3.79E-04 + 1.13E-02 1.84E-02 -2.61E-03 + 1.14E-02 1.82E-02 11/5/2013 - 11/12/2013 -2.82E-05 + 8.91E-03 1.46E-02 -3.44E-03 + 1.03E-02 1.63E-02 11/12/2013 - 11/19/2013 -2.66E-03 + 8.74E-03 1.38E-02 -1.90E-03 + 9.12E-03 1.46E-02 11/19/2013 - 11/26/2013 -1.12E-04 + 9.13E-03 1.50E-02 -1.75E-03 + 9.08E-03 1.46E-02 11/26/2013 - 12/3/2013 -9.81E-04 + 8.21E-03 1.33E-02 1.17E-03 + 8.83E-03 1.43E-02 12/3/2013 -12/10/2013 4.05E-03 + 1.11E-02 1.76E-02 2.09E-03 + 8.45E-03 1.34E-02 12/10/2013- 12/17/2013 8.32E-03 + 9.16E-03 1.33E-02 -7.87E-04 + 9.62E-03 1.57E-02 12/17/2013- 12/23/2013 5.16E-04 + 8.49E-03 1.38E-02 1.14E-03 + 1.09E-02 1.77E-02 12/23/2013 - 12/31/2013 -9.15E-05 + 8.42E-03 1.38E-02 8.42E-04 + 8.02E-03 1.30E-02 NVS = Valid sample not obtained due to sampler failure.

RQ= Results Qualifer. If blank, result is less than detection limit. If "'", result is above detection limit. Page 3 of 6

I TABLE A-4.1 GAMMA SPECTROMETRY RESULTS OF IODINE 131 ON.CHARCOAL FILTERS Results in pCi/cubic meter, corrected for decay during collection period I

Collection Period RQ Activity Station 6 Error MDA 1 :I RQ Activity,'

Station 40 Error MDA I

1/1/2013 1/8/2013 5.16E-03 8.76E-03 1.32E-02 -9.20E-05 +"1 9.40E-03 1.54E-02 1/8/2013 1/15/2013 1/22/2013 1/15/2013 1/22/2013 1/29/2013 5.62E-03 2.54E-03 0.OOE+00 8.30E-03 6152E-03 1.28E-02 1.24E-02 1.OOE-02 2.1OE-02 3.89E-03 +-

-8.02E-04 3.50E-03 4-8.43E-03 1.30E-02 8.89E-03 1.45E-02 1.02E-02 1.60E-02 I

1/29/2013 1.67E-03 +4 2/5/2013 2/12/2013 2/5/2013 2/12/2013 2/19/2013 2.82E-03

-8.92E-04

-1.91E-03 9.37E-03 8.50E-03 8.27E-03 1.47E-02

.1.38E-02 1.32E-02 0.OOE+00 +-

3.74E-03 +-

1.35E-02 2.19E-02 7.81 E-03 1.28E-02 8.12E-03 1.25E-02 I

2/19/2013 2/26/2013 1.56E-04 5.24E-03 8.56E-03 7.96E-04 +- 8.12E-03 1.32E-02 2/26/2013 3/5/2013 3/12/2013 3/5/2013 3/12/2013 3/19/2013 1.13E-03 0.OOE+00 3.37E-05 8.30E-03 9.31 E-03 8.21 E-03 1.34E-02 1.53E-02 1.35E-02 5.30E-05 ..I 3.16E-04 +-

5.62E-04 +-

8.74E-03 1.43E-02 6.51 E-03 1 .06E-02 8.25E-03 1.34E-02 I

3/19/2013 3/26/2013 -2.65E-04 8.10E-03 1.32E-02 3.14E-04 +- 7.15E-03 .1.17E-02 3/26/2013 4/2/2013 4/2/2013 4/9/2013 4.72E-03 0.OOE+00 7.95E-03 1.08E-02 1.19E-02 1.77E-02

-2.21 E-03 ..I 1.43E-03 +-

8.58E-03 1.36E-02 7.52E-03 1.20E-02 I

  • 4/9/2013 4/16/2013 -- 3.30E-04 -8.29E-03 1.35E-02 9.25E-04 +- 6.46E-03 1.03E-02 4/16/2013

. 4/23/2013 4/30/2013 4/23/2013 4/30/2013 5/7/2013

-2.45E-03 6.85E-05 3.45E-04 1.03E-02

'7.49E-03 7.80E-03 1.64E-02 1.23E-02 1.27E-02

-2.03E-03 +-

6.11 E-04 4-2.44E-03 +-

9.13E-03 1.46E-02 6.40E-03 .1.03E-02 7.81 E-03 1.22E-02 I

5/7/2013 5/14/2013 0.OOE+00 7.44E-03 1.22E-02 -1.70E-03 +- 7.68E-03 .1.22E-02 5/14/2013

. 5/21/2013 5/28/2013 5/21/2013 5/28/2013 6/4/2013

-2.33E-03

-6.53E-05

-6.35E-05 9.19E-03 6.66E-03 6.83E-03 1.46E-02 1.09E-02 1.12E-02

-5.44E-04 1.51E-03 +-

2.99E-03 ..+

+-

7.98E-03 1.30E-02 7.39E-03 1.18E-02 7.24E-03 1.11 E-02 I

1.22E-03 +-

6/4/2013 6/11/2013 6/18/2013 6/11/2013 6/18/2013 6/25/2013 0.OOE+00

-1.10E-03 7.27E-04 1.07E-02

.6.12E-03 7.35E-03 1 ;76E-02 9.73E-03 1.19E-02 4.15E-03 +-

-2.69E-03 +-

8.28E-03 1.33E-02 7.46E-03 1.12E-02 8.28E-03 1.30E-02 I

6/25/2013 7/2/2013 -6.85E-05, 6.15E-03 1.01 E-02 -1.04E-03 +- 7.94E-03 1.28E-02 7/2/2013 7/9/2013 7/16/2013 7/9/2013 7/16/2013 7/23/2013 4.82E-05 3.14E-03

-2.38E-03

7. 11E-03 5.50E-03 8.50E-03 1.17E-02 8.01 E-03 1.35E-02

-1.36E-03 +-

-1.55E-03

-5.92E-04 6.93E-03 1.10E-02 6.83E-03 1.08E-02 7.74E-03 1.26E-02 I

'7/23/2013 7/30/2013 -2.08E-04 6.78E-03 1.11E-02 -3.64E-05 7.84E-03 1.29E-02 7/30/2013 8/6/2013

  • 8/6/2013 8/13/2013 7.81E-05

-5.54E-04 5.92E-03 6.67E-03 9.71 E-03 1.08E-02

-2.33E-03 2.18E-03 7.63E-03 1.19E-02 7.63E-03 1.20E-02 I

8/13/2013 8/20/2013 -4.61 E-04 8.06E-03 1.32E-02 3.30E-03 .+ 8.57E-03 1.33E-02 8/20/2013 8/27/2013 9/3/2013 8/27/2013 9/3/2013 9/10/2013 0.OOE+00

-1.25E-03 3.88E-03 1.25E-02 8'22E-03 8.68E-03 2.05E-02 1.32E-02 1.34E-02 3.14E-04 0.OOE+00

-4.60E-04 6.35E-03 1.04E-02 8.41 E-03 1.38E-02 7.91 E-03 1.29E-02 I

9/10/2013 9/17/2013 1.98E-03 8.21 E-03 1.30E-02 -2.44E-03 7.40E-03 1.15E-02 9/17/2013

.9/24/2013

.10/1/2013 9/24/2013 10/1/2013 10/8/2013

-9.27E-04

-4.14E-04

-2.15E-03 7.85E-03 8.31 E-03 9.21 E-03 1.27E-02 1.36E-02 1.47E-02'

-5.73E-05 +

-1.64E-03

-2.08E-03 8.47E-03 1.39E-02 8.22E-03 1.31 E-02 7.62E-03 1.20E-02 I

10/8/2013 10/15/2013 10/22/2013 10/15/2013 10/22/2013 10/29/2013

-1.13E-03 1.24E-03,

'2.35E-03 8.92E-03 7.83E-03 8.30E-03 1.44E-02 1.26E-02 1.31 E-02 4.60E-05

-2.03E-03 +

-2.76E-03 +-

7.42E-03 1.22E-02 7.74E-03 1.23E-02 1.06E-02 1.70E-02 I

10/29/2013 11/5/2013 3.78E-04 1.12E-02 1.84E-02 -2.60E-03 1.14E-02 1.81E-02 11/5/2013 11/12/2013 11/19/2013 11/12/2013 11/19/2013 11/26/2013

-2.85E-05

-2.65E-03

-1.19E-04 9.02E-03 8.70E-03 9.75E-03 1.48E-02

-1.37E-02 1.60E-02

-3.38E-03

-1.81 E-03

-1.72E-03 1.01 E-02 1.59E-02 8.69E-03 1.39E-02 8.95E-03 1.44E-02 I

11/26/2013 12/3/2013 -1.03E-03 8.59E-03 1.39E-02 12/3/2013 12/10/2013 12/10/2013 12/17/2013 4.12E-03 8.68E-03 1.13E-02 9.55E-03 1.79E-02 1.39E-02 1.11E-03 2.15E-03

-7.95E-04 +

8.40E-03 1.36E-02 8.69E-03 1.38E-02 9.72E-03. 1.58E-02 I

12/17/2013 12/23/2013 4.87E-04 1.02E-02 1.66E-02 5.16E-04 8.49E-03 1.38E-02 12/23/2013 12/31/2013 .2.91E-03 7.39E-03 1.14E-02 -9.40E-05 8.66E-03 1.42E-02 I

NVS = Valid sample not obtained due to sampler failure.

RQ= Results Qualifer. If blank, result is less than detection limit. If "+", result is above detection limit. Page 4 of 6 I

TABLE A-4.1 GAMMA SPECTROMETRY RESULTS'OF 'IODINE 131 ON CHARCOAL FILTERS Results in pCi/cubic meter, corrected for decay during collection period Collection *Period JStation Cltn o IRO Activity..:

7 Error .MDA IRQ Station 48 Activity. Error MDA 1/1/2013 - 1/8/2013 6.40E-04. 6.40E-03 1.03E-02 -9.28E-05 +

9.48E-03 1.56E-02 1/8/2013 - +

1/15/2013

  • 3.07E-03. .7.89E-03 1.23E-02 3.74E-03 8.11 E-03 1.25E-02 1/15/2013 - 1/22/2013 * -9.81E-04 + 8.18E-03 1.32E-02 -8.02E-04 +

8.89E-03 1.45E-02

+

1/22/2013 - +

1/29/2013 -1.72E-03 +* 1.04E-02 1.68E-02 3.44E-03 1.OOE-02 1.57E-02 1/29/2013 - +

2/5/2013 2.24E-03. + 1.05E-02 1.68E-02 1.65E-03 1.33E-02 2.16E-02 2/5/2013 - +

2/12/2013 -1.03E-03 + 7.88E-03 1.27E-02 0.OOE+00 7.76E-03 1.28E-02 2/12/2013 - 2/19/2013 -+

-1.50E-03 7.86E-03 1.26E-02

  • 3.68E-03 7.99E-03 1.22E-02 2/19/2013 - 2/26/2013 3.OOE-03 + 8.17E-03 1.27E-02 7.70E-04 +

7.85E-03 1.27E-02 2/26/2013 - .3/5/2013 -4.39E-03 -I 1.11E-02 1.75E-02 5.14E-05 +

8.48E-03 1.39E-02 3/5/2013 - 3/12/2013 -1.67E-03 + 8.54E-03 1.37E-02 .3.08E-04 -I 6.33E-03 1.03E-02

.3/12/2013 - 3/19/2013 -4.31E-04 +-. 7.69E-03 1.25E-02 5.38E-04 +

7.90E-03 1.29E-02 3/19/2013 - 3/26/2013 2.27E-03 + 6.43E-03 9.91 E-03 2.98E-04 6.79E-03 1.t1E-02 3/26/2013 - 4/2/2013 2.70E-05 -I 7.45E-03 .1.22E-02 -2.21 E-03 +

8.58E-03 1.36E-02 4/2/2013.- 4/9/2013 2.69E-03 + 7.54E-03. 1.17E-02 1.44E-03 .+

7.61 E-03 1.21 E-02 4/9/2013 - 4/16/2013 0.OOE+00 -I 6.32E-03 1.04E-02 9.64E-04 + 6.73E-03 1.08E-02 4/16/2013 4/23/2013 2.61E-03 + 6.57E-03 1.01 E-02 -2.1 OE-03 9.43E-03 1.51 E-02 4/23/2013 - 4/30/2013 0.OOE+00 + 1.07E-02 1.75E-02 6.02E-04 + 6.30E-03 1.02E-02 4/30/2013 - 5/7/2013 * -1.18E-03 8.77E-03 1 *42E-02 2.34E-03 + 7.49E-03 1.17E&02 5/7/2013 - 5/14/2013 3.51 E-03 7.OOE-03 1.05E-02 * -1.72E-03 7.73E-03 1*23E-02

.5/14/2013 - 5/21/2013 3.28E-03 + 7.89E-03 1.22E-02 -5.62E-04 8.25E-03 1.34E-02 5/21/2013 5/28/2013 0.OOE+00 + 9.93E-03 1.63E-02 1.51 E-03 7.40E-03 1.18E-02 5/28/2013 - 6/4/2013 -6.28E-04 + 7.28E-03 .1 18E-02 3.01 E-03 +.

7.28E-03 1.12E-02

+

6/4/2013 6/11/2013 4.61 E-03 7.47E-03 1.11E-02

  • 1.21 E-03 8.21 E-03 1.32E-02 6/11/2013 - .6/18/2013 .- 1.15E-03 + 7.74E-03. 1.24E-02 4.25E-03 +

7.64E-03 1.14E-02 6/18/2013 - 6/25/2013 4.64E-03 -t 7.45E-03 1.11 E-02 -2.67E-03 +

8.20E-03 1.29E-02 6/25/2013 7/2/2013 -6.16E-04 + 7.24E-03 1.17E-02 -1.03E-03 -t- 7.81 E-03 1.26E-02 7/2/2013 - 7/9/2013

  • 9.07E-04 -I 7.84E-03 1.27E-02 41.31 E-03 6.70E-03 1.06E-02 7/9/2013 - 7/16/2013 +

-8.32E-04 + 7.92E-03 1.28E-02 -1.96E-03 8.66E-03 1.37E-02 7/16/2013 - 7/23/2013 +

-5.49E-04 + 7.46E-03 1.21 E-02 -5.69E-04 7.44E-03 1.21E-02 7/23/2013 - 7/30/2013 -4.58E-04 + 6.85E-03 1.11E-02 -3.37E-05 ..+

7.27E-03 1.20E-02 7/30/2013 +

8/6/2013 -2.60E-05 6.80E-03 1.12E-02 *-2.28E-03 7.45E-03 1.17E-02

+

8/6/2013 - 8/13/2013 * -3.54E-04 7.43E-03 1.21 E-02 2.11 E-03 7.40E-03 1.16E-02 8/13/2013 8/20/2013 -t

- 3.36E-03 7.91 E-03 1.22E-02 3.05E-03 7.93E-03. 1 '23E-02 8/20/2013 - 8/27/2013 * -2.12E-03: 8.26E-03 -1.31E-02 3.36E-04 + 6&80E-03 1.11 E-02 8/27/2013 9/3/2013 -1.45E-03 +. 7.92E-03 1.27E-02 0.OOE+00 + 8.71 E-03 1.43E-02 9/3/2013 - 9/10/2013 1.33E-03 7.14E-03 1..14E-02 -4.85E-04 .8.32E-03 1.36E-02 9/10/2013 - 9/17/2013 -6.97E-04 6.96E-03. 1.12E-02 -2.86E-03 8.68E-03 1.35E-02 9/17/2013 - 9/24/2013 2.68E-03 + 7.71 E-03 1.20E-02 -6.04E-05 8.92E-03 1.47E-02 9/24/2013 10/1/2013 0.OOE+00 9.20E-03 1.51 E-02 +

- -1.78E-03 8.92E-03 1.42E702 10/1/2013 10/8/2013 5.83E-04 +

- 8.03E-03 1.31 E-02 -2.39E-03 8.74E-03 1.38E-02 10/8/2013 10/15/2013 -3.35E-03 + +

- 8.79E-03 1.37E-02 5.17E-05 8.33E-03 1.37E-02 10/15/2013 10/22/2013 6.34E-05 ..+ 1.02E-02 1.68E-02 +

- -2.32E-03 8.84E-03 1.40E-02 10/22/2013 10/29/2013 -1.73E-03 + .7.84E-03 1.25E-02 +.

- r2.85E-03 1.1OE-02 1.76E-02 10/29/2013 - 11/5/2013 4.87E-03 8.61 E-03 1.29E-02 -2.77E-03 1.21 E-02 1.93E-02 11/5/2013 - 11/12/2013 -2.63E-04 5:34E-03 8.69E-03 -3.54E-03 1.06E-02 1.67E-02 11/12/2013 - 11/19/2013 -1.73E-03 + 8.30E-03 1-.33E-02 0.OOE+00 .+ 1.06E-02 1.73E&02 11/19/2013 - 11/26/2013 -3.06E-03 1.05E-02 1.67E-02 -1.76E-03 9.14E-03 .1.47E-02 11/26/2013 - 12/3/2013 1.41 E-03 + 7.84E-03 1.26E-02 1.18E-03 +

8.92E-03 1.44E-02 12/3/2013 .12/10/2013 5.01E-03 9.10E-03 1.39E-02 2.16E-03 8.70E-03 1.38E-02 12/10/2013 - 12/17/2013 0.OOE+00 8.11E-03 1.33E-02 -8.24E-04 1.01 E-02 1.64E-02 12/17/2013 - 12/23/2013 4.54E-04 9.47E-03 1.55E-02 5.14E-04 8.47E-03 1'.38E-02 12/23/2013;- 12/31/2013 2.76E-03 7.01 E-03 1.08E-02 -8.83E-05 8.13E-03 1.33E-02 NVS = Valid sample not obtained due to sampler failure.

RQ= Results Qualifer. If blank, result is less than detection limit. If "+", result is above detection limit. Page 5 of 6

TABLE A-4.1 I

GAMMA SPECTROMETRY RESULTS OF IODINE 131 ON CHARCOAL FILTERS Results in pCi/cubic meter, corrected for decay during collection period. I Station 8 Station 57 Collection 1/1/2013 -

Period 1/8/2013 RQ Activity 6.57E-04 +

Error 6.57E-03 MDA 1.06E-02 RQ Activity

-9.35E-05 +

Error 9.55E-03 MDA 1.57E-02 I

1/8/2013 -

1/15/2013 -

1/22/2013 -

1/15/2013 1/22/20i3 1/29/2013 3.15E-03 +

-1.03E-03 +

-1.81E-03 +

8.10E-03 8.59E-03 1.10E-02 1.26E-02 1.39E-02 1.77E-02 3.89E -8.28E-04. +

3.68E-03 +

8.43E-03 9.19E-03 1.07E-02 1.30E-02 1.49E-02 1.68E-02 U

1/29/2013 - 2/5/2013 2.34E-03 + 1.10E-02 1.75E-02 1.70E-03 + 1.37E-02 2.22E-02 2/5/2013 -

2/12/2013 -

2/12/2013 2/19/2013

-1.04E-03 +

-1.55E-03 +

7.96E-03 8.13E-03 1.28E-02 1.30E-02 0.OOE+00 +

3.81E-03 +

8.08E-03 8.27E-03 1.33E-02 1.27E-02 I

2/19/2013 - 2/26/2013 3.16E-03 + 8.60E-03 1.34E-02 8.1OE-04 + 8.26E-03 1.34E-02 2/26/2013 -

3/5/2013 -

3/12/2013 -

3/5/2013 3/12/2013 3/19/2013

-4.55E-03 +

-1.74E-03 +

-4.42E-04 +

1.15E-02 8.90E-03 7.89E-03 1.82E-02 1.43E-02 1.29E-02 5.48E-05 +

3.28E-04 +

5.82E-04 +

9.04E-03 6.73E-03 8.54E-03 1.48E-02 1.1OE-02 1.39E-02 I

3/19/2013 - 3/26/2013 2.39E-03 + 6.75E-03 1.04E-02 3.26E-04 + 7.41E-03 1.21E-02 3/26/2013 -

4/2/2013 -

4/9/2013 -

4/2/2013 4/9/2013 2.66E-05 +

2.67E-03 +

7.33E-03 7.48E-03 1.20E-02 1.16E-02

-2.21E-03 +

1.43E-03 +

8.58E-03 7.54E-03 1.36E-02 1.20E-02 I

4/16/2013 0.OOE+00 + 6.27E-03 1.03E-02 9.24E-04 + 6.45E-03 1.03E-02 4/16/2013 -

4/23/2013 -

4/30/2013 -

4/23/2013 4/30/2013 5/7/2013 2.67E-03 +

0.OOE+00 +

-1.20E-03 +

6.72E-03 1.04E-02 8.91E-03 1.03E-02 1.71E-02 1.44E-02

-2.02E-03 +

6.05E-04 +

2.50E-03 +

9.06E-03 6.33E-03 8.OOE-03 1.45E-02 1.02E-02 1.25E-02 I

5/7/2013 - 5/14/2013 3.29E-03 + 6.56E-03 9.87E-03 -1.67E-03 + 7.52E-03 1.20E-02 5/14/2013 -

5/21/2013 -

5/28/2013 -

5/21/2013 5/28/2013 6/4/2013 3.08E-03 +

0.OOE+00 +

-6.21E-04 +

7.42E-03 9.70E-03 7.19E-03 1.14E-02 1.60E-02 1.17E-02

-5.49E-04 +

1.50E-03 +

3.50E-03 +

8.06E-03 7.34E-03 8.46E-03 1.31E-02 1.17E-02 1.30E-02 I

6/4/2013 -

6/11/2013 -

6/18/2013 -

6/11/2013 6/18/2013 6/25/2013 4.43E-03 +

-1.12E-03 +

4.59E-03 +

7.18E-03 7.54E-03 7.38E-03 1.06E-02 1.21E-02 1.1OE-02 1.30E-03 +

4.52E-03 +

-2.79E-03 +

8.84E-03 8.12E-03 8.57E-03 1.42E-02 1.22E-02 1.35E-02 I

6/25/2013 - 7/2/2013 -5.96E-04 + 7.OOE-03 1.14E-02 -1.10E-03 + 8.34E-03 1.35E-02 7/2/2013 -

7/9/2013 -

7/16/2013 -

7/9/2013 7/16/2013 7/23/2013 8.76E-04 +

-1.52E-03 +

-5.61E-04 +

7.57E-03 6.69E-03 7.62E-03 1.22E-02 1.06E-02 1.24E-02

-1.41E-03 +

-8.62E-04 +

-6.1OE-04 +

7.18E-03 8.20E-03 7.97E-03 1.14E-02 1.33E-02 1.30E-02 I

7/23/2013 - 7/30/2013 -3.61E-04 + 5.40E-03 8.78E-03 -3.40E-05 + 7.33E-03 1.20E-02 7/30/2013 -

8/6/2013 -

8/6/2013 8/13/2013

-2.53E-05 +

-3.28E-04 +

6.62E-03 6.88E-03 1.09E-02 1.12E-02

-2.22E-03 +

2.07E-03 +

7.28E-03 7.26E-03 1.14E-02 1.14E-02 I

8/13/2013 - 8/20/2013 3.11E-03 + 7.33E-03 1.13E-02 3.02E-03 + 7.84E-03 1.21E-02 8/20/2013 -

8/27/2013 -

9/3/2013 -

8/27/2013 9/3/2013 9/10/2013

-1.96E-03 +

-1.33E-03 +

1.20E-03 +

7.65E-03 7.31E-03 6.44E-03 1.21E-02 1.17E-02 1.03E-02 3.45E-04 +

0.OOE+00 +

-4.87E-04 +

6.99E-03 8.65E-03 8.36E-03 1.14E-02 1.42E-02 1.36E-02 I

9/10/2013 - 9/17/2013 -6.35E-04 + 6.34E-03 1.03E-02 -2.62E-03 + 7.96E-03 1.24E-02 9/17/2013 -

9/24/2013 -

10/1/2013 -

9/24/2013 10/1/2013 10/8/2013 2.41E-03 +

0.OOE+00 +

5.73E-04 +

6.95E-03 8.87E-03 7.89E-03 1.08E-02 1.46E-02 1.28E-02

-6.17E-05 +

-1.76E-03 +

-2.31E-03 +

9.12E-03 8.80E-03 8.43E-03 1.50E-02 1.41E-02 1.33E-02 I

10/8/2013 -

10/15/2013 -

10/22/2013 -

10/15/2013 10/22/2013 10/29/2013

-3.37E-03 +

6.31E-05 +

-1.76E-03 +

8.84E-03 1.02E-02 7.97E-03 1.38E-02 1.67E-02 1.27E-02 5.11E-05 +

-2.30E-03 +

-2.80E-03 +

8.24E-03 8.75E-03 1.08E-02 1.35E-02 1.39E-02 1.73E-02 I

10/29/2013 - 11/5/2013 4.95E-03 + 8.76E-03 1.31E-02 -2.61E-03 + 1.14E-02 1.82E-02 11/5/2013 -

11/12/2013 -

11/19/2013 -

11/12/2013 11/19/2013 11/26/2013

-2.65E-04 +

-1.75E-03 +

-3.11E-03 +

5.39E-03 8.39E-03 1.07E-02 8.76E-03 1.34E-02 1.70E-02

-3.32E-03 +

0.OOE+00 +

-1.69E-03 +

9.95E-03 9.95E-03 8.80E-03 1.57E-02 1.64E-02 1.41E-02 I

11/26/2013 - 12/3/2013 1.43E-03 + 7.93E-03 1.27E-02 1.17E-03 + 8.82E-03 1.43E-02 12/3/2013 -

12/10/2013 -

12/17/2013 -

12/10/2013 12/17/2013 12/23/2013 5.15E-03 +

0.OOE+00 +

9.35E-03 8.47E-03 1.43E-02 1.39E-02 2.03E-03 +

-7.49E-04 +

8.18E-03 9.16E-03 1.30E-02 1.49E-02 I

5.06E-04 + 8.32E-03 1.36E-02 1.03E-03 + 9.84E-03 1.60E-02 12/23/2013 - 12/31/2013 -8.84E-05 + 8.13E-03 1.34E-02 7.72E-04 + 7.36E-03 1.19E-02 I

NVS = Valid sample not obtained due to sampler failure.

RQ= Results Qualifer. If blank, result is less than detection limit. If "+', result is above detection limit. Page 6 of 6 I

TABLE A-4.2 GAMMA SPECTROMETRY RESULTS OF IODINE 131 ON CHARCOAL FILTERS -

SUMMARY

Results in pCi per cubic meter, corrected for decay during collection period Average Activity Activity Average Number of Number of Nuclide Activity Low High MDA Samples Positive IDs 1-131 Ind 3.40E-04 -4.55E-03: 8.68E-03 1.33E-02 570 0 1-131 Cntl 4.51E-04 -4.39E-03 4.95E-03 1:29E-02 52 0 Ind = Indicator Stations Cntl = Control Station Page 1 of 1

I TABLE A-5.1',

GROSS BETA IN WATER 1

Results in pCi per liter I

ST 26 River/Drinking Cnti ST 29 River/Drinking Ind Collection 01/02/13.-

01/31/13-Period 01/31/13 02/28/13 RQ Activity 5.76E-02 + 7.08E-01 2.81E-01 + 8.01E-01 Error MDA 2.56E+00 2.77E+00 RQ Activity Error 3.68E-01 + 7.42E-01

-4.66E-01 + 8.02E-01 MDA 2.56E+00 2.77E+00 I

02/28/13 -

04/01/13 -

04/30/13.-

04/01/13 04/30/13 05/31/1.3

-5.85E-01 + 7.25E-01

-1.60E+00 + 8.22E-01 9.72E-01 + 7.75E-01 2.49E+00 2.64E+00 2.61E+00

-1.15E-01 + 6.96E-01

-4.64E-01 +- 7.60E-01 1.33E-01 + 7.31E-01 2.50E+00 2.64E+00 2.61E+00 i

05/31/13 - 07/01/13 6.33E-01 + 6.94E-01 2.38E+00 4.01E-01 + 6.85E-01 2.38E+00 07/01/13 -

08/01/13 -

08/01/13 09/02/13

.2.87E-01 + 6.91E-01 5.71E-01 + 7.69E-01 2.43E+00 2.61E+00

-3.19E-01 + 6.86E-01 1.01E+00 + 7.88E-01 2.43E+00 2.61E+00 i

09/02/13 - 09/30/13 1.99E+00 + 7.39E-01 2.23E+00 4.29E-01 + 6.41E-01 2.22E+00 09/30/13 -

11/01/13 -

12/02/13 -

11/01/13 12/02/13 01/02/14 7.76E-01 + 7.03E-01 9.24E-01 + 7.21E-01 5.77E-01 + 6.54E-01 2.34E+00 2.31E+00 2.25E+00 1.08E+00 + 7.59E-01 5.83E-01 + 6.64E-01

-2.02E-01 + 6.32E-01 2.34E+00 2.27E+00 2.25E+00 i

Collection Period IRQ ST 27 CW Discharge Activity Error MDA i

01/02/13 -. 01/31/13 + 6.02E+00 + 1.17E+00 3.06E+00 01/31/13.-

02/28/13 -

02/28/13 04/01/13

+

+

3.73E+00 + 1.09E+00 6.86E+00 + 1.20E+00 3.20E+00 3.04E+00 I 04/01/13 - 04/30/13 + 5.22E+00 + 1.16E+00 3.16E+00 04/30/13 -

05/31/13 -.

07/01/13 -

05/31/13 07/01/13 08/01/13

+

+

5.05E+00 + 1.1OE+00 1.20E+00 + 7.51E-01 3.77E+00 + 1.04E+00 3.03E+00 2.42E+00 2.94E+00 I

08/01/13 - 09/02/13 2.90E+00 + 1.01E+00 3.04E+00 09/02/13 -

09/30/13 -

09/30/13 11/01/13

+

+

7.05E+00 + 1.1OE+00 8.41E+00 + 1.27E+00 2.57E+00 2.94E+00 I

11/01/13 - 12/02/13 + 7.95E+00 + 1.20E+00 2.76E+00 12/02/13 - 01/02/14 + 1.18E+01 + 1.33E+00 2.68E+00 I

S.. " TABLE A-5.2 GROSS BETA IN WATER -

SUMMARY

I Results in pCi per liter Number Number of i

Average Activity Activity of Positive Location Activity Low High Samples IDs i n

ST 26 Control ST 29 Indicator 4.07E-01 2.03E-01

-1.60E+00

-4.66E-01 1.99E+00 1.08E+00 12 12 0

0 I

ST 27 Discharge 5.83E+00 1.20E+00, 1.18E+01 12 10 I

I RQ = Results Qualifier. If blank, result is less thandetection limit. If "+', result is above detection limit. Page 1 of 1 I

TABLE A-6.1 TRITIUM IN WATER Results in pCi peqrliter, MDA for all samnples is 300 pCi/I Location Description Collection Period RQ Activity Error 26 River/Drinking Control 01/02/13 04/01/13 1.48E+02 9.39E+01

'04/01/1.3 07/01/13. 1.68E+02 .9.41 E+01 07/01/13 -' 11/01/13 8.28E+01 9.44E+01 11/01/13 01/02./14 7.77E+01 9.69E+01 29 River/Drinking Indicator 01/02/13 04/01/13 1.35E+02 9.51 E+01 04/01/13 07/01/13 1.67E+02 9.44E+01 07/01/13 11/01/13 1.16E+02 9.53E+01 11/01/13 01/02/14 9.01E+01 9.69E+01 27 Plant Discharge 01/02/13 04/01/13 2.45E+02 9.80E+01 04/01/13 07/01/13 2.24E+02 9.55E+01 07/0.1/13 11/01/13 1.57E+02 9.59E+01 11/01/13 01/02/14 1.87E+02 9.97E+01 31 Ground Water Well 1 03/06/13 1.02E+02 9.75E+01 06/05/13 1.01 E+02, 9.18E+01 09/04/13 8.33E+01 9.32E+01 12/16/13 1.71E+02 9.86E+01 32 Ground Water Well 2 03/06/13 3.94E+01 -9.25E+01 06/05/13 1.55E+02 9.35E+01 09/04/13 -3.38E+00 8.05E+01 12/11/13 6.76E+01 9.52E+01 52 Ground Water Well 3 03/06/13 9.57E+00 9.78E+01 06/05/13 1.19E+02 9.16E+01 09/04/13 9.01 E+01 9.26E+01 9.56E+01 12/1.1/13 7.15E+01 TABLE A-6.2 TRITIUM IN WATER - Summary Results in pCi'per liter Number of Average Activity Activity Number of Positive Location Descriotion Activity Low High Samples IDs River/Drinking Control 1.19E+02 7.77E+01 1.68E+02 4 0 River/Drinking Indicator 1.27E+02 9.01E+01 1.67E+02 4 0 Discharge Indicator 2.03E+02 1.57E+02 2.45E+02 4 0 Ground Water Indicator 8.38E+01 . -3.38E+00 1.71E+02 12 0 Quarterly tritium values reported for ST-26, 27, and 29 are average of monthly analysis values.

RQ= results Qualifier. If blank, result is less than detection limit. If "+", result is above the detection limit. Page 1 of I

I Table A-7.1 GAMMA SPECTROMETRYsRESULTS OFWATER I

STATION 26 - RiverlDrinking Control Results in pCi/liter, corrected for decay during collection period I

Location 26 collected 1/31/2013 . Location 26 collected 2/28/2013 Nuclide RQ Activity K-40 CR-51

-3.29E+01 + 7.76E+01

-5.75E+00 + 2.43E+01 Error MDA 4.97E+01 3.95E+01 Nuclide -RQ Activity K-40 CR-51

-3.45E+01 +

-6.73E+00 +

. Error 9.64E+01 2.55E+01 MDA!

5.38E+01 4.13E+01 U

)

MN-54 1.37E+00 + 1.75E+00 2.64E+00 MN-54 2.05E+00 + 1.84E+0C) 2.71 E+00 CO-58 FE-59 1.09E-01 + 1.93E+00 2.15E+00 + 5'.49E+00 3.16E+00 8.57E+00 CO-58 FE-59 1.06E+00

-1.87E-01

_+ 2.01E+0C)

+ 5.11E+0C 3.14E+00 8.36E+00 I

CO-60 -7.24E-01 + 7100E+00 3.48E+00 CO-60 -1.27E+00 + 5.27E+01 ) 3.96E+00 ZN-65 ZRNB-95 1-131

-2.92E-01 + 3.79E+00 2.41 E-02 + 3.42E+00 3.02E+00 + 6.45E+00 6.17E+00 5.61 E+00 1.03E+01 ZN-65 ZRNB-95 1-131 9.36E-01

-1.79E+00

-5.48E-01

+ 2.64E+0C)

+ 4.32E+0C)

+ :7.29E+0C) 4.08E+00 6.88E+00 1.19E+01 I

CS-1 34 -2.86E-01 + 1.81 E+00 2.94E+00 CS-134 -7.05E-02 + 1.93E+0C) 3.16E+00 CS-137 BALA140

-7.72E-01 + 2.07E+00

-2.46E-01 + 4.93E+00

+ 1.08E+01 + 4.99E+00 3.30E+00 8.05E+00 CS-1 37 BALA 40 1.38E+00 3.28E-01

+ 1.64E+0C)

+ 3.92E+0C) 2.46E+00 6.35E+00 I

BI-214 8.18E+00 BI-214 + 4.22E+01 + 7.45E+0C 8.73E+00 Location 26 collected 4/1/2013 Location 26 collected 4/30/2013 I

, Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 CR-51 MN-54

-1.72E+01 6.30E+00 6.22E-01

+

+

+

3.69E+01 1.73E+01 1.85E+00 4.54E+01 2.77E+01 2.95E+00 K-40 CR-51 MN-54

-2.87E+01 +

-4.79E+00 +

-1.01E+00 +

6.40E+01 2.22E+01 2.09E+00 4.92E+01 3.61 E+01 3.30E+00 I

CO-58 FE-59 CO-60

-4.49E-01 0.00E+00

-3.70E-01

+

+

+

2.02E+00 6.50E+00 3.69E+00 3.25E+00 1.07E+01 3.60E+00 CO-58 FE-59 CO-60 9.34E-01 +

7.29E-02 +

  • -1.13E+00 +

1.55E+00 5.13E+00 3.16E+01 2.36E+00 8.41 E+00 3.34E+00 I

ZN-65 0.OOE+00 + 7.36E+00 1.21 E+01 ZN-65 -1.19E+00 + 4.41 E+00 7.06E+00 ZRNB-95 1-131 CS-134

-2.13E+00 2.76E-01 6.59E-01

+

+

+

4.12E+00 6.59E+00 1.89E+00 6.49E+00 1.08E+01 3.03E+00 ZRNB-95 1-131,,

CS-134

-1.56E+00 +

1.33E-01 4-

.-6.08E-01 +

3.90E+00 5.17E+00 1.87E+00 6.19E+00 8.48E+00 3.00E+00 i

CS-137 1.71 E+00 2.80E+00 3.20E-01 +

BALA140 BI-214 8.39E-02

-1.26E+00 4.66E+00

+

_+

+

5.08E+00 4.55E+00 8.09E+00 8.06E+00 CS-137 BALA140 BI-214 9.45E-01 +

+ 1.29E+01 +

1.92E+00 4.77E+00 5.25E+00 3.11iE+00 7.66E+00 8.43E+00 I

Nuclide RQ Location 26 c ollected Activity Error 5/31/2013 MDA Nuclide RQ Location 26 Activity collected Error 7/1/2013 MDA I

K-40 -4.65E+01 + 1.88E+02 5.45E+01 K-40 -5.01E+01 + 1.14E+02 5.85E+01 CR-51 MN-54

-1.06E+00 + 2 .55E+01 1.42E-01 + 1.84E+00 4.19E+01 2.99E+00 CR-51 MN-54

-6.84E-01 +

4.16E-02 +

2.28E+01 2.18E+00 3.74E+01 3.57E+00 I

CO-58 -1.05E-01 + 2 .03E+00 3.32E+00 CO-58 1.37E-01 + 1.90E+00 3.1 OE+00 FE-59 CO-60 ZN-65 3.82E-01 + 6 .51E+00

-1.65E-01 + 2 .74E+00 0.OOE+00 + 7.32E+00 1.06E+01 3.74E+00 1.20E+01 FE-59 CO-60 ZN-65

-2.03E+00 +

-5.12E-01 +

4.47E-02 +

6.53E+00 2.15E+00 4.91 E+00 1.03E+01 3.43E+00 8.06E+00 I

ZRNB-95 1.63E+00 + 3 .69E+00 5.77E+00 ZRNB-95 -1.61 E+00 + 4.58E+00 7.30E+00 1-131 CS-134 CS-137

-1.39E+00 + 7 .35E+00

-8.95E-02 + 2 .30E+00

-2.60E-01 + 1.98E+00 1.19E+01 3.77E+00 3.22E+00 1-131 CS-1 34 CS-1 37

-1.83E+00 +

-4.30E-02 +

1.55E-01 +

6.80E+00 2.05E+00 1.99E+00 1.10E+01 3.37E+00 3.25E+00 I

-3.43E+00 +

BALA140 BI-214

-2.85E+00 + 7 .02E+00 1.59E+00 + 5 .25E+00 1.10E+01 9.53E+00 BALA140 BI-214 4.77E-01 +'

6.30E+00 4.71 E+00 9.69E+00 8.84E+00 I I

RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit. Page 1 of 8 I

Table A-7.1 GAMMA SPECTROMETRY RESULTS OF WATER STATION 26 - River/Drinking Control Results in pCi/liter, corrected for decay during collection period Location 26 collected 8/1/2013 Location 26 collected 9/2/2013 Nuclide Rd Activity _ Eror - -- kNuclide -RQ Activity- " Error MDA K-40 -3.10E+01 + 6.56E+01 6.06E+01 K-40 -3.75E+01 + 6.19E+01 5.38E+01 CR-51 -3.78E+00 + .2.63E+01 4.29E+01 CR-51 -1.21E+00 + 2.86E+01 4.69E+01 MN-54 1.85E+00 +' 1.98E+00 2.93E+00 MN-54* 1.21E-01 + 2.21 E+00 3.62E+00 CO-58 -3.70E-01 + 2.18E+00 3.52E+00 CO-58 8.58E-01 + 2.21 E+00 3.49E+00 FE-59 4.60E-01 + 7.36E+00 1.20E+01 FE-59 5.38E-01 + 7.23E+00 1.18E+01 CO-60 -1.10E-01 + 2.06E+00 3.36E+00 CO-60 -4.91 E-02 + 2.01 E+00 3.30E+00 ZN-65 -1.95E+00 + 5.OOE+00 7.91E+00 ZN-65 1.46E-01 + 3.83E+00 6.26E+00 ZRNB-95 -1.34E+00 + 4.32E+00 6.89E+00 ZRNB-95 -1.40E+00 + 4.23E+00 6.74E+00 1-131 3.47E+00 + 7.12E+00 1.13E+01 1-131

  • 7.91E-01 + 6.89E+00 1.12E+01 CS-134 0.OOE+00 +, 3.40E+00 5.59E+00 CS-1 34 -7.93E-01 + 2.37E+00 3.81 E+00 CS-137 -1..16E+00 + 2.39E+00 3.77E+00 CS-1 37 1.07E+00 + 2.19E+00 3.45E+00 BALA 140 0.OOE+00 +, 1.14E+00 1.87E+00 BALA140 -1.83E+00 + 6.04E+00 9.55E+00 BI-214 5.03E+00 + 5.17E+00 9.08E+00 BI-214 -1.74E+00 + 7.36E+00 9.93E+00 Location 26 collected 9/30/2013 Location 26 collected 11/1/2013 Nuclide RQ Activity Error MDA Nuclide RO Activity Error MDA.

K-40 -3.21 E+01 .+ 5.64E+01 5.51 E+01 K-40 -3.95E+01 + 1.10E+02 5.27E+01 CR-51 -8.79E+00 + 2.53E+01 4.08E+01 CR-51 -1.05E+01 + 2.74E+01 4.39E+01 MN-54 3.75E-02 + 1.86E+00 3.06E+00 MN-54 0.OOE+00 + 2.59E+00 4.25E+00 CO-58 9.71E-01 +' 2.18E+00 3.43E+00 CO-58 6.64E-01 + 2.31 E+00 3.69E+00 FE-59 0.OOE+00 + 4.96E+00 8.15E+00 FE-59 2.66E+00 + 6.45E+00 9.99E+00 CO-60 1.95E-01 + 2.04E+00 3.32E+00 CO-60 -6.08E-01 + 6.03E+00 3.85E+00 ZN-65 -1.09E+00 + 4.45E+00 7.12E+00 ZN-65 -1.02E+00 + 4.54E+00 7.27E+00 ZRNB-95 -3.63E-01 + 3.89E+00 6.33E+00 ZRNB-95 0.OOE+00 + 5.51 E+00 9.07E+00 1-131 2.04E+00 + 5.61 E+00 8.99E+00 1-131 .4.07E+00 + 9.74E+00 1.56E+01 CS-134 -4.25E-01 + 2.25E+00 3.65E+00 CS-134 .1.40E-01 + 2.56E+00 4.20E+00 CS-137 1.07E-01 + 2.10E+00 3.44E+00 CS-1 37 -4.58E-01 + 2.14E+00 3.44E+00 BALA140 -1.76E+00 +. 5.39E+00 8.50E+00 BALA140 1.OOE+00 + 6.09E+00 9.75E+00 BI-214 1.96E+00 + 4.93E+00 9.02E+00 BI-214 2.77E+00 + 4.84E+00 8.81 E+00 Location 26 collected 12/2/2013 *Location 26 collected 1/2/2014 Nuclide- RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 -4.71E+01 + 1.01E+02 5.83E+01 K-40 -2.49E+01 + 4.41 E+01 5.34E+01 CR-51 -3.50E+00 + 2.66E+01 4.34E+01 CR-51 -5.90E+00 + 3.05E+01 4.96E+01 MN-54 2.69E-01 + 2.09E+00 3.40E+00 MN-54 -6.04E-01 + 2.14E+00 3.42E+00 CO-58 3.86E-01 + 2.07E+00 3.34E+00 CO-58 2.58E-01 + 2.33E+00 3.79E+00 FE-59 -1.32E+00 + 5.95E+00 9.50E+00 FE-59 -1.62E+00 + 6.92E+00 1.11E+01 CO-60 -2.43E-01 + 1.98E+00 3.211E+00 CO-60 -4.51E-01 + 2.40E+00 3.87E+00 ZN-65 -1.89E+00 + 5.38E+00 8.55E+00 ZN-65 9.68E-01 + 3.45E+00 5.44E+00 ZRNB-95 1.75E-02 + 3.75E+00 6.16E+00 ZRNB-95 -1.12E-02 + 2.91 E+00 4.79E-00 1-131 1.68E-01 + 5.84E+00 9.58E+00 1-131 2.93E+00 + 9.39E+00 1.51E+01 CS-134 -8.03E-01 + 2.36E+00 3.79E+00 CS-1 34 -8.62E-01 + 2.07E+00 3.30E+00 CS-1 37 1.28E+00 + 2.26E+00 3.54E+00 CS-137 -7.43E-01 + 2.40E+00 3.84E+00 BALA140 -2.52E+00 + 5.90E+00 9.17E+00 BALA140 3.51E-02 + 5.83E+00 9.59E+00 BI-214 5.38E+00 + 5.37E+00 9.36E+00 BI-214 .1.15E+00 + 4.97E+00 9.15E+00 RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit. Page 2 of 8

I Table A-7.1 GAMMA SPECTROMETRY RESULTS OF WATER I

STATION 29 - River/Drinking Indicator Results in pCi/liter, corrected for decay during collection period I

Location 29 collected 1/31/2013 Location 29 collected 2/28/2013 Nuclide K-40 CR-51 RQ Activity -

-5.21 E+01 + 1.23E+02 1.25E+00 + 2.32E+01 Error . MDA.

5.65E+01 3.80E+01 I Nuclide K-40 CR-51 RQ Activity

-3.16E+01 +

1.36E+01 +

Error 6.32E+01 MDA 5.88E+01 2.31E+01 *) 3.65E+01 I

MN-54 5.74E-01 + 1.50E+00 2.37E+00 MN-54 -3.63E-02 + 2.07E+0C) 3.40E+00 CO-58 FE-59 3.64E-01 + 2 .10E+00

-1.97E+00 + 6.80E+00 3.41 E+00 1.09E+01 CO-58 FE-59 3.99E-01 +

-1.84E+00 +

2.32E+0C*) 3.75E+00 7.16E+00 *) 1.14E+01 I

CO-60 -5.92E-01 + 2.17E+00 3.48E+00 CO-60 8.45E-01 + 1.91E+0C) 2.95E+00 ZN-65 ZRNB-95 1-131

-5.10E-01 + 3.62E+00 1.41 E+00 + 3.89E+00

-4.43E+00 + 8.36E+00 5.87E+00 6.22E+00 1.34E+01 ZN-65 ZRNB-95 1-131 0.OOE+00 +

2.19E+00 +

2.28E+00 +

6.01E+0C) 9.88E+00 4.13E+0C) 6.44E+00 7.41E+0C) 1.19E+01 I

CS-134 -1.75E+00 + 2.23E+00 3.52E+00 CS-134 -1.79E+00 + 2.71E+0C) 4.28E+00 CS-137 BALA140 BI-214

-7.57E-01 + 2.25E+00 8.39E-01 + 3.79E+00 5.22E-01 + 4.44E+00 3.62E+00 6.01E+00 8.24E+00 CS-1 37 BALA140 BI-214

-2.34E-01 +

-7.50E-01 +

5.84E-01 +

2.41E+0C) 3.94E+00 6.15E+0C) 9.95E+00 5.54E+0C 1.OOE+01 I

Location 29 collected 4/1/2013 Location 29 collected 4/30/2013 I

Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 CR-51 MN-54

-2.84E+01 +

1.28E+01 +

-4.OOE-01 +

5.31 E+01 2.33E+01 2.27E+00 5.611E+01 3.70E+01 3.67E+00 K-40 CR-51 MN-54

-2.51E+01 +

7.04E+00 +

9.24E-01 +

4.55E+01 2.29E+01 1.88E+00 5.41 E+01 3.70E+01 2.93E+00 I

CO-58 FE-59 CO-60

-5.59E-01 +

-1.23E+00 +

8.60E-01 +

2.39E+00 6.44E+00 2.08E+00 3.85E+00 1.03E+01 3.24E+00 CO-58 FE-59 CO-60

-7.32E-02 +

.2.09E+00 +

0.OOE+00 +

2.08E+00 5.82E+00 2.36E+00 3.41 E+00 9.12E+00 3.88E+00 I

ZN-65 2.10E+00 + 4.77E+00 7.48E+00 ZN-65 -8.56E-03 + 4.80E+00 7.88E+00 ZRNB-95 1-131 CS-134

-9.58E-01 +

3.44E-01 +

-1.27E+00 +

4.17E+00 7.83E+00 2.53E+00 6.71E+00 1.29E+01 4.03E+00 ZRNB-95 1-131 CS-134 0.OOE+00 +

-2.30E+00 +

-1.OOE+00 +

3.57E+00 5.96E+00 2.05E+00 5.87E+00 9.55E+00 3.24E+00 I

CS-137 -7.23E-01 + 2.29E+00 3.67E+00 CS-137 1.02E+00 + 1.96E+00 3.05E+00 BALA140 BI-214

-2.09E+00 _+

4.80E+00 +

4.94E+00 5.31 E+00 7.61 E+00 9.31 E+00 BALA140 BI-214

-1.43E+00 +

4.20E+00 +

5.76E+00 4.67E+00 9.19E+00 8.41 E+00 I

Nuclide RQ Activity Location 29 collected Error 5/31/2013 MDA. Nuclide RQ Location 29 collected Activity . Error ,

7/1/2013 MDA a

K-40 RQ -3.21 E+01 + 5.33E+01 5.07E+01 K-40 -3.88E+01 + 7.19E+01 5.66E+01 CR-51 MN-54 CO-58

-1.14E+01 + 2.54E+01 1.61 E+00 + 2.17E+00

  • -4.80E-01 + 2.27E+00 4.09E+01 3.39E+00 CR-51 MN-54

-4.64E+00 + 2.79E+01 9.20E-01 + 2.01 E+00 4.54E+01 3.15E+00 I

3.68E+00 CO-58 -6.56E-01 + 2.45E+00 3.93E+00 FE-59 CO-60 ZN-65 1.13E+00 + 6.20E+00

-2.44E-01 + 1.73E+00

-7.85E-02 + 4:09E+00 1.OOE+01 2.81 E+00 6.71 E+00 FE-59 CO-60 ZN-65 1.67E+00 + 6.91 E+00

-5.51 E-02 + 2.23E+00

-2.39E+00 + 4.68E+00 1.10E+01 3.66E+00 7.27E+00 I

ZRNB-95 2.91 E-02 + 3.39E+00 5.58E+00 ZRNB-95 -1.69E+00 + 4.42E+00 7.OOE+00 1-131 CS-1 34 CS-137 1.90E-02 + 7.44E+00

-6.73E-01 + 2.06E+00 9.29E-01 + 2.15E+00 1.22E+01 3.32E+00 3.44E+00 1-131 CS-134 CS-1 37 1.28E+00 + 9.33E+00

-1.54E+00 + 2.48E+00 7.14E-01 + 2.17E+00 1.52E+01 3.91 E+00 3.46E+00 I

BALA140 -8.19E-02 + 5.01E+00 BI-214 -4.83E+00 + 1-.07E+01 8.22E+00 8.83E+00 BALA140 BI-214

-1.98E+00 + 8.09E+00 3.74E+00 + 5.50E+00 1.29E+01 9.71 E+00 I I

RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit. Page 3 of 8 I

Table A-7.1 GAMMA SPECTROMETRY RESULTS OF WATER STATION 29 -, River/Drinking Indicator Results in pCi/liter, corrected for decay during collection period Location 29 collected 8/1/2013 Location 29 collected 9/3/2013 Nuclide RQ Activity . -Error MDA- 1 Nuclide RO Activity Error MDA K-40 -3.42E+01 + 9.62E+01 5.65E+01 K-40 -3.20E+01 + 5.65E+01 5.52E+01 CR-51 4.58E+00 + 2.37E+01 3.84E+01 CR-51 1.65E+00 + 2.48E+01 4.06E+01 MN-54 -1.16E+00 + 2.39E+00 3.76E+00 MN-54 -1.1OE+00 + 2.32E+00 3.65E+00 CO-58 4.82E-02 + 1.56E+00 2.56E+00 CO-58 1.12E+00 + 2.08E+00 3.22E+00 FE-59 0.OOE+00 + 8.09E+00 1.33E+01 FE-59 -1.54E+00 + 6.05E+00 9.61 E+00 CO-60 -3.39E-01 + 3.66E+00 3.79E+00 CO-60 4.55E-01 + 2.09E+00 3.34E+00 ZN-65 -3.62E-01 + 4.02E+00 6.53E+00 ZN-65 .-4.18E-01 + 3.92E+00 6.36E+00 ZRNB-95 -1.00E-01 + 4.04E+00 6. 63E+00 ZRNB-95 -1.38E+00 + 4.87E+00 7.83E+00 1-131 -5.95E+00 + 8.54E+00 1.34E+01 1-131 -3.42E+00 + 8.56E+00 1.38E+01 CS- 134 -3.44E-01 + 2.26E+00 3.67E+00 CS-134 -6.55E-01 + 2.29E+00 3.68E+00 CS-137 -1.48E+00 + 2.55E+00 3.99E+00 CS-137 -2.70E-02 + 9.87E-01 1.61E+00 BALA140 -1.08E+00 + 5.62E+00 8.97E+00 BALA140 0.OOE+00 + 1.70E+00 2.79E+00 BI-214 -5.31E-01 + 5.45E+00 9.27E+00 BI-214 6.79E+00 + 5.78E+00 9.87E+00 Location 29 collected 9/30/2013 Location 29 collected 11/1/2013 Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 -1.45E+01 + 3.59E+01 5.43E+01 K-40 -4:87E+01 + 1.12E+02 5.97E+01 CR-51 -2.78E-01 + 2.OOE+01 3.28E+01 CR-51 5.93E-02 + 2.61E+01 ) 4.29E+01 MN-54 -4.65E-01 + 1.87E+00 2.99E+00 MN-54 7.64E-01 + 1.98E+00 ) 3.13E+00 CO-58 4.05E-01 + 2.02E+00 3.25E+00 CO-58 -1.33E-01 + 2.35E+00 ) 3.85E+00 FE-59 -6.38E-01 + 5.71 E+00 9.25E+00 FE-59 -9.02E-01 + 6.64E+00 ) 1.07E+01 CO-60 0.OOE+00 + 2.33E+00 3.84E+00 CO-60 1.78E+00 + 1.94E+00 ) 2.80E+00 ZN-65 1.01 E+00 + 4.12E+00 6.59E+00 ZN-65 -1.57E+00 + 4.90E+00 ) 7.80E+00 ZRNB-95 1.48E+00 + 3.78E+00 5.97E+00 ZRNB-95 -2.OOE+00 + 4.53E+00 7.13E+00 1-131 2.30E+00 + 5.15E+00 8.20E+00 1-131 -7.32E-02 + 1.25E+01 ) 2.05E+01 CS-134 1.03E-02 + 2.21 E+00 3.63E+00 CS-1 34 -8.49E-02 + 2.15E+00 ) 3.53E+00 CS-137 -6.49E-01 + 2.55E+00 4.12E+00 CS-1 37 -3.06E-01 + 2.17E+00 ) 3.52E+00 BALA140 -1.55E+00 +' 5.17E+00 8.18E+00 BALA140 -7.57E-01 + 8.78E+00 ) 1.43E+01 BI-214 ,1.80E-01 + 5.22E+00 9.40E+00 BI-214 1.37E+00 + 5.03E+00 9.22E+00 Location 29 collected 12/2/2013

  • Location 29 collected 1/2/2014 Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 -3.18E+01 + 6.02E+01 5.71 E+01 K-40 -2.76E+01 + 5.73E+01 5.91E+01 CR-51 1.58E+01 + 2.30E+01 3.61E+01 CR-51 -1.83E+01 + 3.06E+01 4.87E+01 MN-54
  • 4.76E-01 + 2.03E+00 3.25E+00 MN-54 7.37E-01 + 2.03E+00 3.22E+00 CO-58 1.62E+00 + 2.19E+00 3.32E+00 CO-58 -.1.51E-01 + 2.34E+00 3.82E+00 FE-59 0.OOE+00 + 6.50E+00 1.07E+01 FE-59 1.45E+00 + 6.09E+00 9.68E+00 CO-60 1.07E+00 + 1.90E+00 2.89E+00 CO-60 -2.18E-01 + 2.06E+00 3.34E+00 ZN-65 -1.07E+00 + 4.43E+00 7.09E+00 ZN-65 1.64E-01 + 4.48E+00 7.34E+00 ZRNB-95 -7.79E-02 + 3.79E+00 6.22E+00 ZRNB-95 -1.45E+00 + 4.24E+00 6.74E+00 1-131 2.75E+00 + 6.16E+00 9.80E+00 1-131 2.49E+00 + 1.OOE+01 1.62E+01 CS-1 34 0,00E+00 + 3.50E+00 5.75E+00 CS-1 34 -7.18E-01 + 2.38E+00 3.83E+00 CS-137 2.98E-01 + 2.30E+00 3.75E+00 CS-137 -8.15E-03 + 2.24E+00 3.69E+00 BALA140 1.37E+00 + 5.31 E+00 8.41 E+00 BALA140 1.29E+00 + 6.88E+00 1.10E+01 BI-214 4.10E+00 + 4.92E+00 8.79E+00 BI-214
  • 1.64E+00 + 5.OOE+00 9.16E+00 RQ = Results Qualifier. If blank, result is less than detection limit. If "÷", result is above detection limit. Page 4 of 8

I Table A-7.1 GAMMA SPECTROMETRY-RESULTS OF WATER I

STATION 27 - Plant Discharge Water Indicator Results in pCi/liter, corrected for decay during collection period Location 27 collected Location.27 collected I

1/31/2013 2/28/2013

  • Nuciide Rd K-40 CR-51 Activity

-8.30E+00 +. 3.25E+01

-5.60E-01 + 2.26E+01 Error j, MDA,'

4.96E+01 3.71E+01 Nuclide RQ -Activity K-40.

CR-51 Error

-3.08E+01 +. 6.03E+01 2.49E+00 + 2.26E+01 MDA -

5.81 E+01 3.68E+01 U

MN-54 3.64E-01 + 1.69E+00 2.71 E+00 MN-54 5.06E-01 + 2.04E+00 3.28E+00 CO-58 FE-59

-2.14E-01 + 1.98E+00

-1.80E-01 + 6.1OE+00 3.22E+00 9.99E+00 CO-58 FE-59

  • 5.02E-01 + 1.94E+00

-1.28E+00 + 6.79E+00 3.10E+00 1.09E-01 I

CO-60 -5.86E-01 + 5.31 E+00 3.52E+00 CO-60 7.72E-02 + 1.67E+00 2.72E+00 ZN-65 ZRNB-95 1-131

-1.38E+00 + 4.09E+00

-1.88E+00 + 4.23E+00 3.46E-01 + 7.53E+00 6.49E+00 6.71 E+00 1.23E+01 ZN-65 ZRNB-95 1-131

-1.80E+00 + 5.09E+00 0.OOE+00 + 4.45E+00

-4.48E+00 + 7.88E+00 8.08E+00 7.31 E+00 1.25E+01 I,

CS-134 -2.18E-01 + 2.04E+00 3.34E+00 CS-1 34 -1.16E+00 + 2.41 E+00 3.83E+00 CS-137 BALA1 40 BI-214 0.OOE+00 + 2.33E+00

-1.55E+00 + 5.75E+00 3.68E+00 + 4.32E+00 3.84E+00 9.15E+00 7.80E+00 CS-1 37 BALA140 BI-214 3.46E-02 + 2.03E+00 7.06E-01 + 5.44E+00 4.73E+00 + 5.15E+00 3.34E+00 8.78E+00 9.08E+00 U

Location 27 collected 4/1/2013 Location 27 collected 4/30/2013 I

Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 CR-51 MN-54

-2.52E+01 + 5.OOE+01 8.07E+00 + 2.46E+01 9.80E-01 + 2.33E+00 5.67E+01 3.96E+01 3.69E+00 K-40 CR-51 MN-54

-2.59E+01 + 5.OOE+01

-9.90E+00 + 2.26E+01 2.05E+00 + 1.87E+00 5.62E+01 3.61 E+01 2.70E+00 I

CO-58 6.24E-02 + 1.93E+00 3.16E+00 CO-58 FE-59 CO-60

-7.03E-02 + 5.22E+00 6.34E-02 + 1.89E+00 8.57E+00 3.09E+00 FE-59 CO-60

-4.47E-01 + 2.19E+00 8.40E-01 + 4.05E+00

  • 2;10E-01 + 1.88E+00 3.53E+00 6.40E+00 3.05E+00 I

ZN-65 -1.31 E+00 + 4.58E+00 7.30E+00 ZN-65 -2.30E+00 + 5.33E+00 8.41 E+00 ZRNB-95 1-131 CS-134 4.96E-01 + 4.03E+00

-4.60E-01 + 6.29E+00 0.OOE+00 + 3.28E+00 6.54E+00 1.03E+01 5.39E+00 ZRNB-95 1-131 CS-134

-6.21E-02 + 3.67E+00

-6.14E-01 + 5.38E+00 9.09E-01 + 2.10E+00 6.02E+00 8.77E+00 3.34E+00 I

CS-137 1.51 E+00 + 1.91E+00 2.88E+00 CS-1 37 -1.04E+00 + 2.27E+00 3.58E+00 BALA140 BI-214

-1.83E+00 + 5.95E+00

-1.37E+00 + 6.95E+00 9.42E+00 9.99E+00 BALA 40 BI-214

-9.13E-01 +. 5.29E+00 3.39E+00 + 5.08E+00 8.51E+00 9.1 OE+00 I

Nuclide RQ Location 27 collected A ctivity Error 5/31/2013 MDA:. Nuclide RQ Location 27 collected Activity .Error 7/1/2013 MDA I

K-40 .- 2. 85E+01 + 5.32E+01 5.61 E+01 K-40 -3.28E+01 + 5 .84E+01 5.55E+01 CR-51 MN-54 CO-58

-2 .43E-01 + 2.50E+01 8 .01E-02 + 2.39E+00 7 .06E-01 + 2.36E+00 4.11E+01 3.92E+00 3.77E+00 CR-51 MN-54 CO-58 9.54E-02 + 2 .34E+01

-9.21E-01 + 2 .27E+00

-2.34E-01 + 1 .91E+00 3.85E+01 3.60E+00 3.09E+00 I

FE-59 CO-60 ZN-65

-1 .03E-01 + 5.68E+00 7 .69E-01 + 2.OOE+00

-2 .08E-01 + 3.61E+00 9.32E+00 3.14E+00 5.89E+00 FE-59 CO-60 ZN-65 4.70E-03 + 6 .11E+00

-2.09E-01 + 2 .23E+00 0.OOE+00 +. 9 .32E+00 1.OOE+01 3.62E+00 1.53E+01 I

ZRNB-95 -1. 42E+00 + 4.12E+00 6.55E+00 ZRNB-95 -2.08E-01 + 3 .64E+00 5.95E+00 1-131 CS-134 CS- 137

4. 45E+00 + 6.13E+00

.-8 .41E-01 + 2.41E+00

-4 .68E-02 + 2.11E+00 9.50E+00 3.88E+00 3.47E+00 1-131 CS-134 CS-137

-7.36E-01 + 6 .24E+00

-6.68E-01 + 2 .05E+00

-1.84E-02 + 1 .96E+00 1.02E+01 3.28E+00 3.22E+00 I

BALA140 0. OOE+00 + 4.63E+00 7.62E+00 BALA140 1.42E+00 +. 4 .75E+00 Bl214 8. 35E+00 + 5.26E+00 8.89E+00 BI-214 3.06E+00 + 5 .04E+00 7.44E+00 9.08E+00 I I

RQ = Results Qualifier. If blank, result is less than detection limit, If "+", result is above detection limit. Page 5 of 8 I

Table A-7.1 GAMMASPECTROMETRY RESULTS OF WATER STATION 27 - Plant Discharge Water Indicator Results in pCi/liter, corrected for decay during collection period Location 27 collected 8/1/2013 Location 27 collected 9/2/2013 i Nuclide- RQ Activity - Error MDA -Nuc6ide RQ Activity ... Error " MDA' K-40 -2.55E+01 + 5.08E+01 5.69E+01 K-40 -9.95E-01 4- 2.87E+0i 5.47E+01 CR-51 -1.17E+00 + 2.42E+01 3.97E+01 CR-51 1.63E+01 + 2.53E+01 3.99E+01 MN-54 -1.48E-02 + 1.92E+00 3.16E+00 MN-54 -4.73E-01 + 2.19E+00 3.52E+00 CO-58 -1.40E+00 + 2.67E+00 4.18E+00 CO-58 -4.33E-01 + 2.33E+00 3.76E+00 FE-59 -3,38E+00 + 7.74E+00 1.21E+01 FE-59 2.81E+00 + 6.72E+00 1.05E+01 CO-60 1.17E-01 + 2.04E+00 3.34E+00 CO-60 -3.17E-01 + 3.74E+00 3.97E+00 ZN-65 -1.89E-02 + 5.51 E+00 9.05E+00 ZN-65 1..46E+00 + 4.33E+00 6.83E+00 ZRNB-95 -1.76E-01 + 4.34E+00 7.1OE-+00 ZRNB-95 1.34E+00 + 3.80E+00 6.01 E+00 1-131 -3.42E+00 + 9.29E+00 1.49E+01 1-131 -2.01E+00 + 7.51 E+00 1.21E+01 CS- 134 7.65E-02 + 2.44E+00 4.OOE+00 CS-1 34 1.45E+00 + 2.01 E+00 3.11 E+00 CS-137 1.20E+00 + 1.76E+00 2.68E+00 CS-137 2.79E-02 + 1.98E+00 3.25E+00 BALA 140 1.33E+00 + 5.18E+00 8.15E+00 BALA140 -3.29E+00 + 6.99E+00 1.08E+01 BI-214 1.79E+00 + 5.41 E+00 9.76E+00 BI-214 1.17E-01 + 4.94E+00 9.23E+00 Location 27 collected 9/30/2013 Location 27 collected 11/1/2013

' Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 -9.16E+00 + 3.44E+01 5.68E+01 K-40 -1.49E+01 + 3.81E+01 5.59E+01 CR-51 1.46E+01 + 2.22E+01 3.49E+01 CR-51 -1.38E+01 + 3.OOE+01 4.81 E+01 MN-54 3.30E-01 + 2.10E+00 3.41 E+00 MN-54

  • 5.64E-01 + 2.13E+00 3.42E+00 CO-58 -1.05E-01 + 2.09E+00 3.41 E+00 CO-58 7.13E-01 + 2.29E+00 3.64E+00 FE-59 -1.49E+00 + 6.74E+00 1.08E+01 FE-59 -9.39E-02 + 5.66E+00 9.28E+00 CO-60 -5.28E-01 + 2.08E+00 3.31 E+00 CO-60 -2.47E-01 + 2.23E+00 3.62E+00 ZN-65 -3.03E+00 + 5.62E+00 8.81 E+00 ZN-65 -3.58E-01 + 4.47E+00 7.28E+00 ZRNB-95 2.68E-01 + 4.30E+00 7.03E+00 ZRNB-95 -1.20E+00 +" 4.39E+00 7.03E+00 1-131 -2.20E+00 +' 6.78E+00 1.09E+01 1-131 4.42E+00 + 9.24E+00 1.47E+01 CS-134 1.10E-04 + 2.48E+00 3.80E+00 CS-134 -1.44E+00 + 2.67E+00 4.25E+00 CS-137 -1.01E+00 + 2.02E+00 3.17E+00 CS-137 5.95E-01 + 2.12E+00 3.40E+00 BALA140 0.OOE+00 + 4.68E+00 7.71 E+00 BALA140 0.OOE+00 + 8.14E+00 1.34E+01 BI-214 5.44E+00 + 4.59E+00 8.15E+00 BI-214 4.58E+00 + 5.53E+00 9.68E+00 Location 27 collected 12/2/2013 Location 27 collected 1/2/2014 Nuclide RQ - Activity Error MDA
  • Nuclide RO Activity Error MDA K-40 -1.01E+01 + 3.65E+01 5.35E+01 K-40 -9.13E+00 + 3.32E+01 5.15E+01 CR-51 3.91 E+00 + 2.49E+01 4.05E+01 CR-51 6.94E+00 + 2.66E+01 4.31E+01 MN-54 9.38E-01 + 1.95E+00 3.04E+00 MN-54 -4.59E-01 + 2.24E+00 3.61 E+00 CO-58 -1.34E-01 + 1.92E+00 3.14E+00 CO-58 -6.69E-01 + 2.34E+00 3.74E+00 FE-59 5.63E-01 + 6.23E+00 1.01 E+01 FE-59 6.13E-01 + 6.82E+00 1.11E+01 CO-60 -2.67E-01 + 3.OOE+00 3.53E+00 CO-60 2.17E-01 + 1.88E+00 3.33E+00 ZN-65 -1.31E+00 + 4.95E+00 7.91 E+00 ZN-65 1.68E-01 + 4.98E+00 8.15E+00 ZRNB-95 -4.36E-01 +. 3.97E+00 6.45E+00 ZRNB-95 -9.96E-01 + 4.36E+00 7.01 E+00 1-131 -2.34E+00 + 6.92E+00 1.11E+01 1-131 -5.72E-01 + 1.10E+01 1.80E+01 CS-134 -8.97E-02 + 2.18E+00 3.58E+00 CS-134 -9.31E-01 + 2.18E+00 3.47E+00 CS-1 37 2.91E-01 + 1.23E+00 1.95E+00 CS-137 -8.42E-03 + 2.05E+00 3.36E+00 BALA 140 3.73E-01 + 4.53E+00 7.34E+00 BALA140 0.OOE+00 + 1.66E+00 2.73E+00 BI-214 4.47E+00 + 5.23E+00 9.22E+00 BI-214 -4.06E-01 + 5.61E+00 9.67E+00 RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit. Page 6 of 8

I Table A-7.1 GAMMA SPECTROMETRY RESULTS' OF WATER I

Deep Ground Water Wells - Stations 31., 32, 52 Results in pCi/liter I

Location 31 collected 3/6/2013 . Location 31 collected 6/5/2013 INuclide RQ Activity K-40 CR-51 2.32E+00 + 5.59E+01

-1.70E+01 + 4.38E+01 Error MDA.

1.07E+02 7.09E+01 Nuclide RQ Activity K-40 CR-51 Error

-1.45E+01 + 7.02E+01 2.05E+01 + 2.66E+01 MDA , i 9.69E+01 4.06E+01 I

MN-54 -6.16E-01 + 3.57E+00 5.78E+00 MN-54 0.OOE+00 + 5.17E+00 8.51 E+00 CO-58 FE-59

-1.34E+00 + 3.29E+00

-1.58E-01 + 9.65E+00 5.19E+00 1.58E+01 CO-58 FE-59

-8.28E-02 + 3.79E+00

-2.77E+00 + 1.05E+01 6.22E+00 1.66E+01 I

CO-60 -1.36E+00 + 1.36E+01 8.06E+00 CO-60 1.18E+00 +, 3.98E+00 6.25E+00 ZN-65 ZRNB-95 1-131

-1.12E+01 + 1.24E1+01

-1.65E+00 + 8.25E+00 8.94E-02 + 5.11 E+00 1.92E+01 1.34E+01 8.39E+00 ZN-65 ZRNB-95 1-131

-1.33E+00 + 2.89E+01

-5.87E-01 + 5.82E+00 9.62E-01 + 3.54E+00 4.74E+01 9.44E+00 5.66E+00 I

CS-134 4.62E-01 + 8.32E+00 1.37E+01 CS-1 34 1.46E+00 + 3.31E+00 5.17E+00 CS-137 BALA140 BI-214

-1.54E-01 4- 5.28E+00 0.00E+00 + 4.59E+00

+ 3.63E+02 + 2.35E+01 8.67E+00 7.55E+00 1.88E+01 CS-1 37 BALA1 40 BI-214 0.OOE+00 + 5.85E+00 2.78E-02 + 4.32E+00

+ 1.62E+02 + 1.81E+01 9.63E+00 7.1 OE+00 1.55E+01 I

Location 31 collected 9/4/2013 Location 31 collected 12/16/2013 I

Nuclide RQ Activity , Error MDA Nuclide RQ Activity Error MDA K-40 CR-51 MN-54

-4.94E+00 + 5.81 E+01

-2.91E+01 + 4.95E+01

-3.86E-02 + 3.99E+00 1.14E+02 7.90E+01 6.56E+00 K-40 CR-51 MN-54

-2.98E+01 +

-3.66E+00 +

-1.56E-01 +

8.14E+01 2.63E+01 2.77E+00 7.77E+01 4.30E+01 4.53E+00 I

-1.79E+00 + 4.37E+00 CO-58 FE-59 CO-60 1.94E+00 + .1.01E+01 0.OOE+00 + 3.73E+00 6.93E+00 1.63E+01 6.14E+00 CO-58 FE-59 CO-60

-1.17E+00 +

-1.36E+00 +

-2.89E-01 +

2.63E+00 7.73E+00 3.12E+00 4.12E+00 1.24E+01 5.08E+00 I

ZN-65 -2.39E+00 + 9.04E+00 1.45E+01 ZN-65 -5.48E+00 + 8.78E+00 1.37E+01 ZRNB-95 1-131 CS-1 34

-2.81 E+00 + 8.85E+00 0.OOE+00 + 8.96E+00 0OOE+00 + 1.11E+01 1.42E+01 1.47E+01 1.82E+01 ZRNB-95 1-131 CS-134

-1.78E+00 +

1.09E+00 +

4.67E-01 +

5.44E+00 3.16E+00 4.94E+00 8.69E+00 5.09E+00 8.08E+00 I

CS-1 37 . 1.49E+00 + 4.93E+00 7.91 E+00 CS-1 37 -1.29E+00 + 3.35E+00 5.33E+00 BALA1 40 BI-214 0.OOE+00 + 8.27E+00

+ 4.74E+01 + 1.52E+01 1.36E+01 2.35E+01 BALA140 BI-214 1.14E-01 +

+ 1.14E+02 +

2.89E+00 1.35E+01 4.72E+00 1.30E+01 I

Nuclide RQ :Activity Location 32 collected Error 3/6/2013 MDA Nuclide RQ Activity Location 32 collected Error.,

6/5/2013 MDA I

K-40 -3.56E+01 + 1.09E+02 1.20E+02 K-40 1.66E+01 + 5.38E+0i 9.62E+01 CR-51 MN-54 CO-58 1.12E+00

-5.59E-01 3.25E+00

+

+

+

5.73E+01 5.19E+00 5.49E+00 9.42E+01 8.47E+00 8.69E+00 CR-51 MN-54 1.46E+01 +

-1.68E+00 +

-2.78E+00 +

3.21E+01 4.33E+00 5.12E+01 6.83E+00 7.18E+00 I

CO-58 4.64E+00 FE-59 CO-60 ZN-65 4.47E-01 1.33E-03 3.57E+00

+-.

+

+

1.02E+01 5.67E+00 6.01 E+01 1.68E+01 9.59E+00 9.87E+01 FE-59 CO-60 ZN-65

-2.08E+00 +

-1.17E+00 +

3.61E+00 +

9.94E+00 1.27E+02 2.95E+01 1.58E+01 8.17E+00 4.83E+01 I

ZRNB-95 1.61E-01 + 9.35E+00 1.54E+01 ZRNB-95 -1.44E+00 + 6.23E+00 9.95E+00 1-131 CS-134 CS-137

-1.77E+00

-5.98E-01 2.63E+00

+

+

+

7.70E+00 6.27E+00 4.79E+00 1.25E+01 1.03E+01 7.56E+00 1-131 CS-1 34 CS-1 37

-1.65E+00 +

-3.05E-01 +

1.49E+00 +

4.91 E+00 1.12E+01 4.11 E+00 7.90E+00 1.84E+01 6.50E+00 U

BALA140 0.OOE+00 + 7.28E+00 1.20E+01 BALA140 1.09E+00 + 5.02E+00 7.96E+00 BI-214 + 8.28E+02 + 3.56E+01 2.41E+01 BI-214 + 4.63E+02 + 2.84E+01 1.41E+01 I I

RQ = Results Qualifier. If blank, result is less than detection limit. If '+, result is above detection limit. Page 7 of 8 i

Table A-7.1 GAMMA SPECTROMETRY RESULTS OF WATER Deep'Ground Water Wells - Stations 31, 32, 52 Results in pCi/liter Location 32 collected 9/4/2013 Location 32 collected 12/11/2013 1 Nuclide- RQ Activity Error MDA Nuclide RQ Activity Error MDA ,

K-40 -5.62E+01 + 1.07E+02 1.20E+02 K-40 6.40E+00 + 3.88E+01 7.65E+01 CR-51 -5.64E-01 + 5.22E+01 8.58E+01 CR-51 -1.02E+01 + 3.43E+01 5.51 E+01 MN-54 2.47E+00 + 3.66E+00 5.58E+00 MN-54 -1.09E+00 + 4.13E+00 6.60E+00 CO-58 1.19E+00 + 4.74E+00 7.63E+00 CO-58 -1.OOE+00 + 3.55E+00 5.61 E+00 FE-59 5.05E+00 + 9.79E+00 1.50E+01 FE-59 3.89E+00 + 8.39E+00 1.26E+01 CO-60 1.34E+00 + 5.18E+00 8.33E+00 CO-60 -5.97E-02 + 3.89E+00 6.16E+00 ZN-65 -2.22E-01 + 9.20E+00 1.51 E+01 ZN-65 1.43E+00 + 6.89E+00 1.10E+01 ZRNB-95 -2.35E+00 + 9.27E+00 1.50E+01 ZRNB-95 -1..69E+00 + 5.37E+00 8.41 E+00 1-131 4.59E+00 + 8.69E+00 1.39E+01 1-131: -9.73E-01 + 5.09E+00 8.22E+00 CS- 134 9.25E-01 + 1.72E+01 2.82E+01 CS-1 34 -4.85E-01 + 3.38E+00 5.47E+00 CS-137 4.67E-01 + 5.62E+00 9.18E+00 CS-1 37 -1.37E+00 + 3.79E+00 5.97E+00 BALA140 2.08E-01 + 6.48E+00 1.06E+01 BALA140 -2.92E-01 + 5.96E+00 9.72E+00 BI-214 + 1.94E+02 + 2.23E+01 2.13E+01 BI-214 + 7.96E+01 + 1.34E+01 1.32E+01 Location 52 collected 3/6/2013 Location 52 collected 6/5/2013 Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 -1.45E+01 + 5.46E+01 9.17E+01 K-40 -4.08E+00 + 4.24E+01 8.20E÷01 CR-51 -1.58E+01 + 3.97E+01 6.40E+01 CR-51 -2.77E+00 + 2.01E+01 3.25E+01 MN-54 -4.35E-01 + 3.37E+00 5.48E+00 MN-54 -5.70E-01 + 3.13E+00 5.OOE+00 CO-58 -4.46E-01 + 3.18E+00 5.15E+00 CO-58 1.33E+00 + 2.85E+00 4.33E+00 FE-59 0.OOE+00 + 1.04E+01 1.71 E+01 FE-59 -7.19E-01 + 7.70E+00 1.24E+01 CO-60 -1.02E+00 + 8.11 E+00 6.75E+00 CO-60 -1.46E+00 + 3.79E+00 5.85E+00 ZN-65 -1.65E+00 + 8.29E+00 1.34E+01 ZN-65 1.82E+00 + 6.64E+00 1.04E+01 ZRNB-95 2.50E+00 + 6.91 E+00 1.10E+01 ZRNB-95 4.73E-01 + 4.76E+00 7.69E+00 1-131 0.OOE+00 + 6.49E+00 1.07E+01 1-131 5.77E-01 + 3.03E+00 4.88E+00 CS-134 2.20E+00 + 3.93E+00 6.22E+00 CS-.134 --3.37E-01 + 3.19E+00 5.18E+00 CS-1 37 -2.14E-02 + 4.01 E+00 6.59E+00 CS-137 .0.OOE+00 + 3.86E+00 6.34E+00 BALA140 -5.86E-01 + 5A6E+00 8.85E+00 BALA140 *-2.29E+00 t 5.05E+00 7.67E+00 BI-214 7.54E+00 + 1.04E+01 1.85E+01 BI-214 -2.23E+00 + 1.02E+01 1.33E+01 Location 52 collected 9/4/2013 Location 52 collected 12/11/2013

!Nuclide- RO Activity . Error MDA Nuclide RQ Activity Error MDA K-40 -6.28E+01 + 1.06E+02 1.14E+02 K-40 -3.55E+01 + 8.90E+01 7.48E+01 CR-51 -2.98E+01 + 4.82E+01 7.67E+01 CR-51 7.20E-02 + 2.74E+01 4.50E+01 MN-54 -1.73E-01 + 3.78E+00 6.18E+00 MN-54 3.75E-01 + 2.56E+00 4.14E+00 CO-58 2.25E+00 + 3.94E+00 6.11 E+00 CO-58 -1.21E-02 + 2.68E+00 4.40E+00 FE-59 0.OOE+00 + 1.39E+01 2.28E+01 FE-59 -1.30E-01 + 6.81 E+00 1.12E+01 CO-60 -1.39E+00 + 4.69E+00 7.49E+00 CO-60 5.53E-01 + 2.65E+00 4.22E+00 ZN-65 -1.41E-01 + 7.84E+00 1.29E+01 ZN-65 8.74E-01 + 5.69E+00 9.18E+00 ZRNB-95 -3.39E+00 + 8.69E+00 1.39E+01 ZRNB-95 3.52E+00 + 4.73E+00 7.14E+00 1-131 2.17E+00 + 7.17E+00 1.16E+01 1-131 2.65E+00 + 4.04E+00 6.32E+00 CS-134 -2.34E+00 + 5.91 E+00 9.52E+00 CS-134 -1.02E+00 + 2.65E+00 4.21 E+00 CS-137 1.56E+00 + 5.18E+00 8.34E+00 CS-137 -9.15E-02 + 2.91 E+00 4.77E+00 BALA140 5.33E-01 + 6.46E+00 1.05E+01 BALA140 -9.70E-01 + 5.71 E+00 9.21 E+00 BI-214 7.63E+00 + 1.25E+01 2.22E+01 BI-214 1.31E+00 + 6.63E+00 1.21E+01 RQ = ResultsQualifier. If blank, result is less than detection limit. If "+". result is above detection limit. Page 8 of 8

TABLE A-7.2 GAMMA SPECTROMETRY RESULTS OF WATER -

SUMMARY

RIVER/DRINKING WATER Average Activity Activity Average Number of Number of Nuclide Activity Low High, MDA Samples Positive IDs BALA140 Ind -5.19E-01 -2.09E+00 1.37E+00 8.96E+00 12 BALA140 Cntl -9.65E-01 -3.43E+00 1.OOE+00 8.27E+00 12 BI-214 Ind 1.85E+00 -4.83E+00 6.79E+00 9.19E+00 12 BI-214 Cntl 7.27E+00 -1.74E+00 4.22E+01 8.93E+00 12 CO-58 Ind 1.59E-01 -6.56E-01 1.62E+00 3.50E+00 12 CO-58 CntU 3.71 E01 -4.49E-01 1.06E+00 3.30E+00 12 CO-60 Ind 2.97E-01 -5.92E-01 1.78E+00 3.33E+00 12 CO-60 Cntl -4.53E-01. -1.27E+00 1.95E-01 3.54E+00 12 CR-51 Ind 1.84E+00 -1.83E+01 1.58E+01 3.95E+01 12 CR-51 Cntl -3.87E+00 -1.05E+01 6.30E+00 4.10E+01 12 CS-134 Ind -8.18E-01 -1.79E+00 1.03E-02 3.87E+00 12 CS-134 Cntl -2.65E-01 -8.62E-01 6.59E-01 3.63E+00 12 CS-137 Ind -1.03E-01 -1.48E+00 1.02E+00 3.49E+00 12 CS-1 37 Cntl 8.31 E-02 -1.16E+00 1.38E+00 3.30E+00 12 FE-59 Ind -1.48E-01 -1.97E+00 2.09E+00 1.05E+01 12 FE-59 Cntl 9.23E-02 -2.03E+00 2.66E+00 9.96E+00 12 1-131 Ind -3.93E-01 -5.95E+00 2.75E+00 1.31E+01 12 1-131 Cntl 1.09E+00 -1.83E+00 4.07E+00 1.13E+01 12 K-40 Ind -3.31 E+01 -5.21 E+01 -1.45E+01.' 5.62E+01 12 K-40 Cntl -3.52E+01 -5.01E+01 -1.72E+01 5.38E+01 12 MN-54 Ind 2.37E-01 -1.16E+00 1.61E+00 3.24E+00 12 MN-54 Cntl 4.07E-01 -1.01E+00. 2.05E+00 3.24E+00 12 ZN-65 Ind -2.61 E-01 -2.39E+00 2.10E+00 7.23E+00 12 ZN-65 Cntl -4.44E-01 -1.95E+00 9.68E-01 7.67E+00 12 ZRNB-95 Ind -2.52E-01 -2.00E+00 2.19E+00 6.58E+00 12 ZRNB-95 Cntl -7.72E-01 -2.13E+00 1.63E+00 6.58E+00 12 I

Ind = Indicator Stations Cntl = Control Stations Page 1 of 2

",1ý."., -- !,TABLE A-7.2 GAMMA SPECTROMETRY RESULTS OF WATER -

SUMMARY

"* -- PLANT DISCHARGE WATER Average , Activity: Activity : Average Number of Number of Nuclide Artivitu:7 Lnw Hinh MDA qamnlAq Pnqitivp In-c K-40 Ind -1.84E+01 -3.28E+01 -9.95E-01 5.51 E+01 12 CR-51 Ind 2.23E+00 -1.38E+01 1.63E+01 3.96E+01 12 MN-54 Ind 3.29E-01 -9.21 E-01 2.05E+00 3.34E+00 12 CO-58 Ind -1.38E-01 -1.40E+00 7.13E-01 3.48E+00 12 FE-59 Ind -1.47E-01 -3.38E+00 2.81 E+00 9.92E+00 12 CO-60 Ind -5.84E-02 -5.86E-01 7.69E-01 3.35E+00 12 ZN-65 Ind -8.41 E-01 -3.03E+00 1.46E+00 8.30E+00 12 ZRNB-95 Ind -6.31 E-01 -3.03E+00 1.34E+00 6.79E+00 12 1-131 Ind -6.34E-01 -4.48E+00 4.45E+00 1.21 E+01 12 CS-134 Ind -2.43E-01 -1.44E+00 1.45E+00 3.77E+00 12 CS-137 Ind 1.28E-01 -1.04E+00 1.51 E+00 3.18E+00 12 BALA140 Ind -3.12E-01 -3.29E+00 1.42E+00 8.42E+00 12 BI-214 Ind 3.15E+00 -1.37E+00 8.35E+00 9.14E+00 12 GAMMA SPECTROMETRY RESULTS OF WATER -

SUMMARY

DEEP GROUNDWATER Average Activity Activity Average Number of Number of Nuclide Hinh MflA, Sim nl*p PnitivA I1l*

Hinh MDA Samples Positive 1Ds K-40 Ind -19.38077 -62.777645 16.6067629 97.5524836 12 0 CR-51 Ind -6.037893 -29.751329 20.5078375 61.4939589 12 0 MN-54 Ind -0.206022 -1.6769018 2.47087422 6.13858406 12 0 CO-58 Ind -0.051158 -2.782062 3.24538865 5.96320343 12 0 FE-59 Ind 0.3411166 -2.7710836 5.04771367 15.4107107 12 0 CO-60 Ind -0.305927 -1.4593424 1.34175508 6.8394515 12 0 ZN-65 Ind -0.930563 -11.24672 3.6068 26.1367431 12 0 ZRNB-95 Ind -1.099699 -3.388893 3.51811696 11.3710584 12 0 1-131 Ind 0.6442229 -1.7730388 4.59444964 9.15610574 12 0 CS-134 Ind 0.0350725 -2.3448187 2.19801189 11.0457449 12 0 CS-137 Ind 0.3926454 -1.3682563 2.63397583 7.23204641 12 0 BALA140 Ind -0.180296 -2.2908818 1.09289922 9.12374882 12 0 BI-214 Ind 188.91926 -2.2283558 828.447891 17.4645986 12 8 Ind = Indicator Stations Cntl = Control Stations Page 2 of 2

TABILEA-8.1 GAMMA SPECTROMETRY RESULTS OF SOIL Results in pCi/kilogram I

Location & Date Station 7 6/11/2013 - Location,& Date Station 8 6/11/2013 I

Nuclide RQ Activity Error MDA Nuclide RQ. Activity Error MDA ,

BE-7 K-40 2.07E+02 +

+ 1.53E+04 +

1.64E+02 8.90E+02 2.42E+02 2.84E+02 BE-7 K-40

+ 2.73E+02 + 1.84E+02

.+ 1.90E+04 + 1.13E+03 2.60E+02 2.91 E+02 I

CR-51 2.69E+01 + 1.65E+02 2.68E+02 CR-51 -7.62E+01 + 2.05E+02 3.29E+02 MN-54 CO-58 FE-59

-8.15E+00 +

0.00E+00 +

-1.97E+01 +

2.23E+01 2.56E+01 5.82E+01.

3.56E+01 4.27E+01 9.25E+01 MN-54 CO-58 FE-59 1.33E+00 + 1.86E+01 3.47E-01 + 2.26E+01 3.00E+01 + 5.91 E+01 3.03E+01 3.71 E+01 9.06E+01 I

CO-60 1.35E+01 + 2.26E+01 3.49E+01 CO-60 -1.OOE+01 + 5.52E+01 4.57E+01 ZN-65 ZRNB-95

-2.53E+01 +

1.24E+01 +

5.68E+01 2.85E+01 9.02E+01 4.45E+01 ZN-65 ZRNB-95

-3.02E+01 + 6.28E+01 1.17E+01 + 3.52E+01 9.87E+01 5.56E+01 I

CS-134 -4.61E-01 + 2.24E+01 3.67E+01 CS-1 34 1.12E+01 + 1.50E+01 2.22E+01 CS-137 BALA140 BI-214 3.00E+01 +

3.47E-01 +

+ 4.81E+02 +

2.31 E+01 1.77E+01 6.90E+01 3.38E+01 2.90E+01 7.28E+01 CS-1 37 BALA140 BI-214 2.12E+01 + 2.55E+01

-2.47E+00 + 2.47E+01

+ 5.94E+02 + 8.51 E+01 3.85E+01 3.99E+01 7.73E+01 I

Location & Date Station 9a 6/11/2013 Location & Date Station 23 6/11/2013 I

Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA BE-7 K-40 +

-1.86E+01 1.31E+04

+ 2.76E+02

+ 1.12E+03 4.51 E+02 4.55E+02 BE-7 K-40 1.11E+02 + 1.38E+02

+ 1.45E+04 + 9.03E+02 2.09E+02 2.41 E+02 I

CR-51 0.00E+00 + 2.52E+02 4.20E+02 CR-51 6.41E+01 + 1.52E+02 2.43E+02 MN-54 CO-58 FE-59 7.61 E+00 1.94E-02 7.30E-01

+ 2.85E+01

+ 2.56E+01

+ 7.87E+01 4.55E+01 4.21E+01 1.29E+02 MN-54 CO-58 FE-59 1.34E+01 + 1.77E+01

-3.92E+00 + 1.83E+01 1.88E+01 + 5.08E+01 2.65E+01 2.95E+01 7.96E+01 I

CO-60 -4.16E+00 + 3.45E+01 5.60E+01 CO-60 -3.50E+00 + 1.20E+02 ZN-65 ZRNB-95

-3.15E+01

-2.11E+00

+ 8.20E+01

+ 4.49E+01 1.30E+02 7.34E+01 ZN-65 ZRNB-95

-3.69E+00 + 3.94E+01 1.27E+01 + 3.02E+01 2.48E+01 6.40E+01 4.73E+01 I

CS-134 -1.99E+01 + 3.24E+01- 5.04E+01 CS-134 0.00E+00 + 2.11E+01 3.51E+01 CS-1 37 BALA140 BI-214 2.89E+01 1.50E+00

+ 4.42E+02

+ 2.98E+01

+ 2.67E+01

+ 8.75E+01 4.35E+01 4.34E+01 9.13E+01 CS-1 37 BALA140 BI-214

+ 5.30E+01 + 2.50E+01

-5.09E+00 + 2.01 E+01

+ 5.11E+02 + 8.89E+01 3.35E+01 3.15E+01 I 7.19E+01 Location & Date Station 48 6/11/2013 I

Nuclide RQ Activity Error MDA BE-7 K-40 2.31 E+02

+ 1.47E+04

+

+

2.63E+02 1.17E+03 3.98E+02 3.41 E+02 I

CR-51 1.30E+02 + 2.51 E+02 3.96E+02 MN-54 CO-58 FE-59

-1.37E+00

-4.02E-01

-5.05E+00

+

+

+

3.08E+01 3.06E+01 7.98E+01 5.03E+01 5.03E+01 1.30E+02 I

CO-60 6.05E+00 + 3.69E+01 ZN-65 ZRNB-95

-9.19E+00 2.46E+01

+

+

8.09E+01 5.23E+01 5.95E+01 1.32E+02 8.13E+01 I

CS-134 0.OOE+00 + 7.10E+01 1.18E+02 CS-137 BALA140 BI-214 1.77E+01

-9.06E+00

+ 6.09E+02

+

+

+

3.48E+01 3.30E+01 5.43E+01 5.16E+01 I 1.OOE+02 9.37E+01 I

RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit. Page 1 of 1

I ýý..TABLE A-8.2 GAMMASPECTROMETRY RESULTS OF SOIL -

SUMMARY

..Results in pCi/kilogram Average Activity Activity Average Number of Number of Nuclide Activity CLw High MDA Samples Positive IDs BALA140 Ind -4.07E+00 -9.06E+00 3.47E-01 -4.07E+00 4 0 BALA140 CntI 1.50E+00 1.50E+00 1.50E+00 4.34E+01 1 0 BE-7 Ind 2.05E+02 1.11E+02 2.73E+02 2.05E+02 BE-7 Cntl -1.86E+01 -1.86E+01 -1.86E+01 4.51 E+02 BI-2 14 Ind 5.48E+02 4.81 E+02 6.09E+02 5.48E+02 BI-214 Cntl 4.42E+02 4.42E+02 4.42E+02 9.13E+01 CO-58 Ind -9.93E-01 -3.92E+00 3.47E-01 -9.93E-01 CO-58 CntI 1.94E-02 1.94E-02 1.94E-02 4.21 E+01 CO-60 Ind 1.52E+00 -1.00E+01 1.35E+01 1.52E+00 CO-60 Cntl -4.16E+00 -4.16E+00 -4.16E+00 5.60E+01 CR-51 Ind 3.62E+01 -7.62E+01 1.30E-+02 3.62E+01 CR-51 CntI 0.OOE+00 0.00E+00 0.OOE+00 4.20E+02 CS-1 34 Ind 2.68E+00 -4.61 E-01 1.12E+01 2.68E+00 CS-1 34 Cntl -1.99E+01 -1.99E+01 -1.99E+01 5.04E+01 CS-137 Ind 3.05E+01 1.77E+01 5.30E+01 3.05E+01 CS-137 Cntl 2.89E+01 2.89E+01 2.89E+01 4.35E+01 FE-59 Ind 6.00E+00 -1.97E+01 3.OOE+01 6.OOE+00 FE-59 CntI 7.30E-01 7.30E-01 7.30E-01 1.29E+02 K-40 Ind 1.59E+04 1.45E+04 1.90E+04 1.59E+04 K-40 CntI 1.31 E+04 1.31E+04 1.31E+04 4.55E+02 MN-54 Ind 1.31 E+00 -8.15E+00 1.34E+01 1.31 E+00 MN-54 CntI 7.61 E+00 7.61 E+00 7.61 E+00 4.55E+01 ZN-65 Ind -1.71 E+01 -3.02E+01 -3.69E+00 -1.71E+01 ZN-65 CntI -3.15E+01 -3.15E+01 -3.15E+01 1.30E+02 ZRNB-95 Ind 1.54E+01 1.17E+01 2.46E+01 1.54E+01 ZRNB-95 CntI -2.11E+00 -2.11 E+00 -2.11E+00 7.34E+01 Ind =.Indicator Stations Cntl = Control StationsP Page 1 of 1

I TABLE A=9.1."'

GAMMA SPECTROMETRY RESULTS-OF SEDIMENT Results in pCi/kilogram dry material I

Station 33 Upstream Control I Location & Date Station 33 3/8/2013 Location & Date Station 33 10/21/2013 Nuclide: Rd- Activity BE-7 2.42E+02

+ 1.67E+04

+

+

Error 2.52E+02 MDA 3.88E+02 Nuclide RQ BE-7 t Activity

-1.02E+00 + 1.98E+02

+ 1.71E+04+

Error MDA 3.26E+02 U K-40 9.81 E+02 2.93E+02 K-40 9.81 E+02 2.82E+02 CR-51 MN-54 CO-58

-6.49E+01 1.45E+01 7.86E+00

+

+

+

1.98E+02 2.35E+01 2.12E+01 3.18E+02 3.64E+01 3.35E+01 CR-51 MN-54 CO-58 2.23E+01 + 1.94E+02 1.62E+01 + 2.14E+01 9.05E+00 + 1.87E+01 3.17E+02 3.25E+01 2.90E+01 I

FE-59 2.02E+00 + 6.88E+01 1.13E+02 FE-59 -1.44E-01 + 5.91E+01 9.71 E+01 CO-60 ZN-65

-6.03E+00

-1.37E+01

+

+

2.97E+01 6.74E+01 4.79E+01 1.09E+02 CO-60 ZN-65

-6.71E+00 + 2.63E+01

-3.66E+01 + 7.07E+01 4.21 E+01 1.12E+02 I

ZRNB-95 9.15E+00 + 5.04E+01 8.17E+01 ZRNB-95 1.03E+01 + 3.42E+01 5.45E+01 CS-134 CS-1 37 BALA140

-1.16E+01 3.46E+01

-1.98E+01

+

+

+

3.06E+01 3.07E+01 4.71E+01 4.92E+01 4.64E+01 7.34E+01

.CS-134 CS-137 BALA140

-5.06E+00 + 8.01 E+01

+ 4.98E+01 + 2.50E+01

-2.78E+00 + 2.15E+01 2.59E+01 3.36E+01 3.46E+01 I

+ 8.21E+02 BI-214 + 9.11E+01 8.14E+01 BBI-214 + 7.67E+02 + 9.03E+01 8.24E+01 I

Station 34 Downstream Indicator I Nuclide BE-7 Location & Date RQ Activity

+ 4.62E+02 +

Station 34 Error 2.58E+02 3/8/2013 MDA 3.71 E+02 Nuclide BE-7 Location & Date RQ Activity 0.OOE+00 +

Station 34 Error 2.54E+02 10/21/2013

,MDA 4.23E+02 I

K-40 CR-51

+ 1.57E+04 0.OOE+00

+

+

9.76E+02 2.59E+02 3.27E+02 4.31 E+02 K-40 CR-51

+ 1.51E+04 5.94E+01 +

+ 9.38E+02 2.53E+02 3.43E+02 4.11E+02 I

MN-54 9.13E+00 + 2.16E+01 3.40E+01 MN-54 3.85E+01 + 2.89E+01 4.31 E+01 CO-58 FE-59 CO-60

-6.26E+00

-8.43E+00 7.22E+00

+

+

+

2.34E+01 6.17E+01 2.69E+01 3.75E+01 9.97E+01 4.3.1E+01 CO-58 FE-59 CO-60

-9.03E+00 1.06E+01

-1.14E+00

+

+

+

2.45E+01 5.59E+01 3.05E+01 3.90E+01 8.99E+01 5.OOE+01 I

ZN-65 ZRNB-95 CS-134 2.71E+01

-2.91E+00 3.65E+00

+

+

+

3.75E+01 4.19E+01 2.17E+01 5.51E+01 6.84E+01 3.51 E+01 ZN-65 ZRNB-95 CS-134 2.80E+01 0.OOE+00

-2.99E+01

+

+

+

4.14E+01 4.81E+01 3.42E+01 6.29E+01 8.01 E+01 5.37E+01 I

CS-137 + 1.22E+02 + 3.72E+01 3.39E+01 CS-137 + 1.21E+02 + 3.33E+01 3.18E+01 BALA140 BI-214

-4.40E+00

+ 7.39E+02

+

+

4.42E+01 9.21E+01 7.16E+01 6.29E+01 BALA140 BI-214

-1.09E+01

.+ 1.13E+03

+

+

2.85E+01 1.05E+02 4.46E+01 9.75E+01 I

I I

I I

RQ = Results Qualifier. If blank, result is less than detection limit. If '+", result is above detection limit. Page 1 of 1 I

TABLE A-9.2 GAMMA SPECTROMETRY RESULTS OF SEDIMENT -

SUMMARY

Results in pCi/kilogram dry material Average Activity Activity Average Number of Number of Nuclide Activity Low High MDA Samples Positive IDs BALA140 Ind -7.64E+00 -1.09E+01 -4.40E+00 5.81E+01 2 0 BALA140 CntI -1.13E+01 -1.98E+01 -2.78E+00 5.40E+01 2 0 BE-7 Ind 2.31 E+02 0.OOE+00 4.62E+02 3.97E+02 2 1 BE-7 CntI 1.21E+02 -1.02E+00 2.42E+02 3.57E+02 2 0 BI-214 Ind 9.36E+02 7.39E+02 1.13E+03 8.02E+01 2 2 BI-214 CntI 7.94E+02 7.67E+02 8.21E+02 8.19E+01 2 2 CO-58 Ind -7.64E+00 -9.03E+00 -6.26E+00 3.82E+01 2 0 CO-58 CntI 8.45E+00 7.86E+00 9.05E+00 3.13E+01 2 0 CO-60 Ind 3.04E+00 -1.14E+00 7.22E+00 4.66E+01 2 0 CO-60 CntI -6.37E+00 -6.71 E+00 -6.03E+00 4.50E+01 2 0 CR-51 Ind 2.97E+01 0.OOE+00 5.94E+01 4.21E+02 2 0 CR-51 CntI -2.13E+01 -6.49E+01 2.23E+01 3.18E+02 2 0 CS-134 Ind -1.31E+01 -2.99E+01 3.65E+00 4.44E+01 2 0 CS-134 CntI -8.31E+00 -1.16E+01 -5.06E+00 3.76E+01 2 0 CS-137 Ind 1.21E+02 1.21E+02 1.22E+02 3.29E+01 2 .2 CS-1 37 CntI 4.22E+01 3.46E+01 4.98E+01 4.00E+01 2 1 FE-59 Ind 1.1OE+00 -8.43E+00 1.06E+01 9.48E+01 2 0 FE-59 Cnti 9.40E-01 -1.44E-01 2.02E+00 1.05E+02 2 0 K-40 Ind 1.54E+04 1.51E+04 1.57E+04 3.35E+02 2 2 K-40 CntI 1.69E+04 1.67E+04 1.71E+04 2.88E+02 2 2 MN-54 Ind 2.38E+01 9.13E+00 3.85E+01 3.85E+01 2 0 MN-54 Cntl 1.53E+01 1.45E+01 1.62E+01 3.45E+01 2 0 ZN-65 Ind 2.75E+01 2.71E+01 2.80E+01 5.90E+01 2 0 ZN-65 CntI -2.52E+01 -3.66E+01 -1.37E+01 1.11E+02 2 0 ZRNB-95 Ind -1.45E+00 -2.91E+00 0.00E+00 7.43E+01 2 0 ZRNB-95 CntI 9.72E+00 9.15E+00 1.03E+01 6.81E+01 2 0 Ind = Indicator Stations Cntl = Control Stations .Page 1 of 1

I TABLE A-10.1 GAMMA SPECTROMETRY RESULTS OF FISH:

Station 30 Columbia River - Station 38 Snake River I

Results in pCi/kilogram (wet)

I Location & Collection Species Date Nuclide RQ Activity Error MDA I Steelhead Station 30 10/08/13 K-40 MN-54 2.66E+03 5.38E-01 3.22E+02 8.52E+00 1.93E+02 1.39E+01 I

Indicator CO-58 -4.27E+00 1.38E+01 2.16E+01 FE-59 CO-60 ZN-65

-7.48E+00 5.94E+00

-5.63E+00 5.16E+01 1.32E+01 2.61E+01 8.29E+01 2.13E+01 4.17E+01 I

ZRNB-95 CS-134 CS-137 +

1.83E+00 5.51 E+00 1.91 E+01 2.44E+01 8.63E+00 1'14E+01 3.97E+01 1.30E+01 1.48E+01 I

Bi-214 -3.20E+00 2.51 E+01 3.92E+01 White Fish Station 30 12/22/13 K-40 MN-54

+ 2.89E+03

-1.87E+00 4.14E+02 1.21 E+01 3.03E+02 1.94E+01 I

Indicator CO-58 FE-59 CO-60

-2.32E+00

-1.28E+01 2.19E+00 1.37E+01 4.93E+01 1.58E+01 2.19E+01 7.83E+01 2.65E+01 I

ZN-65 8.11 E+00 3.03E+01 4.79E+01 ZRNB-95 CS-134

-3.57E-01 1.53E+00 2.02E+01 1.30E+01 3.30E+01 2.10E+01 I

CS-137 2.19E+00 1.30E+01 2.09E+01 Steelhead 10/08/13 Bi-214 K-40 +

-1.20E+00 3.19E+03 3.26E+01 3.49E+02 5.71E+01 1.91E+02 I

Station 38 MN-54 -5.08E-01 9.76E+00 1.59E+01 Control CO-58 FE-59

-4.OOE+00

-1.70E+01 1.26E+01 4.85E+01 1.97E+01 7.50E+01 CO-60 -3.82E-01 1.27E+01 1.80E+01 ZN-65 ZRNB-95 CS-134

-8.07E+00

-5.13E+00 0.OOE+00 2.73E+01 2.53E+01 1.47E+01 4.31E+01 4.04E+01 2.41E+01 I

CS-137 Bi-214 9.50E+00 2.14E+01 1.10E+01 2.33E+01 1.62E+01 3.98E+01 I White Fish 12/21/13 K-40 + 3.08E+03 3.77E+02 2.19E+02 Station 38 Control MN-54 CO-58 FE-59 7.05E+00

-4.20E-01 8.98E+00 1.10E+01 1.25E+01 1.80E+01 I

-2.86E+00 3.30E+01 5.34E+01 CO-60 ZN-65 ZRNB-95

-6.27E+00

-2.54E+00 3.03E-01 8.92E+01 3.02E+01 1.81E+01 2.66E+01 4.91E+01 2.97E+01 I

CS-134 9.82E+00 8.94E+00 1.22E+01 CS-137 Bi-214 5.16E+00 9.03E+00 1.17E+01 2.85E+01 1.81E+01 5.13E+01 I

I RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit. Page 1 of 1 I

U U TABLE A-10.2 GAMMA SPECTROMETRY RESULTS OF FISH -

SUMMARY

Results in pCi/kilogram (wet)

Average Activity Activity Average Number of . Number of Nuclide Activity Low .High MDA Samples Positive IDs Bi-214 Ind -2.20E+00 -3.20E+00 -1.20E+00 4.81E+01 Bi-214 Cntl 1.52E+01 9.03E+00 2.14E+01 4.56E+01 CO-58 Ind -3.30E+00 -4.27E+00 -2.32E+00 2.18E+01 CO-58 Cntl -2.21 E+00 -4.OOE+00 -4.20E-01; 1.89E+01 CO-60 Ind 4.06E+00 2.19E+00 5.94E+00 2.39E+01 CO-60 Cntl -3.33E+00 -6.27E+00 -3.82E-01 2.23E+01 CS-134 Ind 3.52E+00 1.53E+00 5.51 E+00 1.70E+01 CS-134 CntI 4.91E+00 Q.OOE-OO 9.82E+00 1.82E+01 CS-1 37 Ind 1.06E+01 2.19E+00 1.91 E+01 1.78E+01 CS-137 Cntl 7.33E+00 5.16E+OO 9.50E+00 1.71 E+01 FE-59 Ind -1.01E+01 -1.28E+01 -7.48E+00 8.06E+01 FE-59 Cntl -9.95E+00 -1.70E+01 -2.86E+00 6.42E+01 K-40 Ind 2.77E+03 2.66E+03 2.89E+03 2.48E+02 K-40 Cntl 3.14E+03 3.08E+03 3.19E+03 2.05E+02 MN-54 Ind -6.67E-01 -1.87E+00 5.38E-01 1.66E+01 MN-54 Cntl 3.27E+00 -5.08E-01 7.05E+00 1.42E+01 ZN-65 Ind 1.24E+00 ,-5.63E+00 8.11E+00, 4.48E+01 ZN-65 Cnti -5.30E+00 -8.07E+00 -2.54E+00 4.61 E+01 ZRNB-95 Ind 7.39E-01 -3.57E-01 1.83E+00 3.64E+01 2 0 ZRNB-95 Cntl -2.41E+00 -5.13E+00 3.03E-01 3.51E+01 2 0 Ind = Indicator Stations Cntl = Control Stations Page 1 of 1

I TABLE A-11.1 IODINE 131 IN MILK Results in pCi/liter, decay corrected to sample collection time I

Station 9b Control Station 36 Indicator I

1-131 1-131 1-131 1-131 Collection, Date RQ Activity Error MDA RQ Activity Error MDA I 01/08/13 -1.01E-01 + 2.01E-01 3.25E-01 -5.77E-02 + 2.12E-01 3.46E-01 02/05/13 03/12/13

-6.51E-02 5.61E-02

+

+

3.10E-01 1.93E-01 5.06E-01 3.15E-01 4.72E-02

-1.27E-01

+

+

1.93E-01 2.20E-01 3.14E-01 3.56E-01 I

04/09/13 -2.24E-02 + 2.16E-01 3.55E-01 0.OOE+00 + 1.97E-01 3.24E-01 04/23/13 05/07/13 05/21/13 7.29E-02

-5.76E-03

-8.19E-02

+

+

+

2.14E-01 2.31E-01 2.23E-01 3.48E-01 3.79E-01 3.61E-01 1.41E-02

-1.90E-02 1.09E-01

+

+

+

1.90E-01 1.45E-01 1.76E-01 3.11E-01 2.37E-01 2.83E-01 I

06/04/13 06/18/13 07/09/13

-6.82E-03

-2.48E-02 7.33E-03

+

+

+

2.24E-01 2.23E-01 2.95E-01 3.69E-01 3.65E-01 4.85E-01 5.18E-02 4.02E-02

-3.60E-02

+

+

+

1.85E-01 1.94E-01 1.81E-01 3.OOE-01 3.17E-01 2.95E-01 I

07/23/13 -4.33E-02 + 2.11E-01 3.45E-01 -9.16E-02 + 2.09E-01 3.39E-01 08/06/13 08/20/13 1.05E-01

-3.48E-02

+

+

2.01E-01 1.97E-01 3.25E-01 3.22E-01 5.75E-03

-2.95E-02

+

+

2.13E-01 2.19E-01 3.50E-01 3.59E-01 I 09/03/13 1.30E-02 + 1.64E-01 2.69E-01 8.73E-04 + 1.78E-01 2.93E-01 09/17/13 10/15/13 11/05/13

-1.41E-02 5.23E-02 2.42E-02

+

+

+

2.02E-01 1.70E-01 1.90E-01 3.31E-01 2.77E-01 3.11E-01

-1.39E-02 3.71E-02

-2.74E-02

+

+

+

2.07E-01 2.20E-01 2.27E-01 3.39E-01 3.59E-01 3.71E-01 I

12/10/13 4.69E-02 + 1.68E-01 2.73E-01 7.OOE-02 + 1.80E-01 2.91E-01 I

TABLE A-1 1.2 IODINE 131 IN MILK Summary Results in pCi/liter, decay corrected to sample collection time I

Number I

Average Activity Activity Average Number Positive Location Activity Low High .MDA Samples IDs I

Indicator- St 36 -1.47E-03 -1.27E-01 1.09E-01 3.21 E-01 18 0 Control - St 9b -1.23E-03 -1.01E-01 1.05E-01 3.48E-01 18 0 I I

I I

I RQ = Results Qualifier. If blank, result is less than detection limit. If "+". result is above detection limit. Page 1 of 1 U

TABLE A-12.1 GAMMA SPECTROMETRY RESULTS OF MILK STATION 9b - CONTROL Results in pCi per liter Collection Date: 1/8/2013 Collection Date: 2/5/2013 Nuclide RQ Activity Error MDA i Nuclide RQ Activity. Error MDA . i BA-133 -7.71E-01 + 3.55E+00 5.72E+00 BA-133 1.30E+00 + 3.77E+00 6.07E+00 CO-60 -1.66E+00 + 3.25E+01 7.64E+00. CO-60 7669E-01 + 3.32E+00 5.32E+00 ZN-65 6.29E-01 + 7.80E+00 1.27E+01 ZN-65 8.30E-01 + 4.82E+00 7.74E+00 MN-54 1.02E-01 + 3.22E+00 5.27E+00 MN-54 -1.20E+00 + 3.37E+00 5.37E+00 CS-134 -5.12E-01 + 2.79E+00 4.50E+00 CS-134 -1.08E+00 + 2.93E+00 4.68E+00 CS-137 -7.58E-02 + 3.20E+00 5.25E+00 CS-137 0.OOE+00 + 3.20E+00 5.26E+00 BALA140 .- 7.24E-01 + 3.64E+00 5.76E+00 BALA140 -5.81E-01 + 3.03E+00 4.83E+00 K-40 + 1.53E+03 + 1.33E+02 6.63E+01 K-40 + 1.35E+03 + 1.13E+02 7.30E+01 FE-59 -2.23E-01 + 8.63E+00 1.41E+01 FE-59 1.02E+00 + 7.59E+00 1.23E+01 ZRNB-95 0.00E+00 + 6.19E+00 1.02E+01 ZRNB-95 3.98E-02 + 5.17E+00 8.49E+00 BE-7 0.00E+00 + 2.31 E+01 3.80E+01 BE-7 -2.89E+00 + 2.53E+01 4.13E+01 Collection Date: 3/12/2013 Collection Date: 4/9/2013 Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA --

BA-133 5.24E-01 + 3.46E+00 5.61 E+00 BA-133 3.90E+00 + 3.93E+00 5.78E+00 CO-60 2.41E+00 + 4.31 E+00 6.88E+00 CO-60 5.02E-01 + 3.94E+00 6.35E+00 ZN-65 8.39E-01 + 6.24E+00 1.01E+01 ZN-65 0.OOE+00 + 1.55E-+01 2.55E+01 MN-54 1.22E+00 + 2.98E+00 4.64E+00 MN-54 -1.76E-01 + 3.85E+00 6.29E+00 CS-1 34 -4.34E-01 + 2.58E+00 4.16E+00 CS-134 -7.14E-01 + 3.82E+00 6.16E+00 CS-137 -1.79E-01 + 3.OOE+00 4.90E+00 CS-137 -2.91E-01 + 3.77E+00 6.14E+00 BALA140 2.27E-02 + 2.69E+00 4.42E+00 BALA140 -6.59E-01 + 5.33E+00 8.60E+00 K-40 + 1.46E+03 + 1.28E+02 6.21 E+01 K-40 + 1.44E+03 + 1.44E+02 8.56E+01 FE-59 -3.37E+00 + 9.24E+00 1.44E+01 FE-59 -1.90E-01 + 8.82E+00 1.45E+01 ZRNB-95 -1.12E+00 + 5.54E+00 8.90E+00 ZRNB-95 -7.90E-01 + 6.99E+00 1.13E+01 BE-7 1.96E+00 + 2.05E+01 3.34E+01 BE-7 3.63E-02 + 2.61 E+01 4.30E+01 Collection Date: 4/23/2013 Collection Date: 5/7/2013 Nuclide RQ Activity Error MDA Nuclide RQ Activity Error *"MDA-:

BA-133 -1.56E-01 + 3.93E+00 6.43E+00 BA-1 33 1.86E+00 + 2.68E+00 3.92E+00 CO-60 -7.39E-02 + 4.66E+00 7.65E+00 CO-60 4.05E-01 + 4.06E+00 6.58E+00 ZN-65 5.51E-01 + 8.09E+00 1.32E+01 ZN-65 8.27E-03 + 8.84E+00 1.46E+01 MN-54 -6.14E-01 + 3.65E+00 5.88E+00 MN-54 2.27E+00 + 3.85E+00 5.87E+00 CS-134 -1.82E+00 + 4.01 E+00 6.30E+00 CS-134 -4.31E-01 + 3.09E+00 4.99E+00 CS-137 8.04E-01 + 3.54E+00 5.65E+00 CS-137 -6.65E-02 + 3.68E+00 6.04E+00 BALA140 2.14E+00 + 3.62E+00 5.12E+00 BALA140 -1.41E+00 + 5.01 E+00 7.86E+00 K-40 + 1.50E+03 + 1.46E+02 8.29E+01 K-40 + 1.42E+03 + 1.42E+02 8.41E+01 FE-59 -1.06E+00 + 1.05E+01 1.69E+01 FE-59 -2.79E+00 + 9.87E+00 1.55E+01 ZRNB-95 -2.06E-02 + 5.76E+00 9.47E+00 ZRNB-95 6.32E-01 + 5.47E+00 8.84E+00 BE-7 -1.75E+00 + 2.70E+01 4.40E+01 BE-7 1.64E+01 + 2.62E+01 3.99E+01 RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit. Page 1 of 6

I TABLE A- 12.1 GAMMA: SPECTROMETRY'RESULTS'OF MILK STATION 9b - CONTROL I

Results in pCi per liter Nuclide RQ, Activity-.

Collection Date: 5/21/201 3 Collection Date: 6/4/2013 I

Errorn., MDA,  :*Nuclide- RQ" Activity Error MDA- I BA-1 33 CO-60 ZN-65 0.O0E+00 + 3.14E+00

-1.57E+00 + .4.52E+01 4.95E+00 + 6.54E+00 5.16E+00 8.62E+00 9.32E+00 BA-133 CO-60 ZN-65

-1.08E+00 + 4.38E+00 0.00E+00 + 5.63E+00 0.00E+00 + 1.04E+01 7.04E+00 9.25E+00 1.70E+01 I

MN-54 -1.03E+00 + 3.72E+00 .MN-54 CS-134 CS-137

-1.72E+00 + 3.28E+00

-1.40E+00 + 3.67E+00 5.91 E+00 5.08E+00 5.75E+00 CS-134 CS-137 0.00E+00 + 4.83E+00

-2.15E+00 + 4.46E+00 7.30E-01 + 4.26E+00 7.94E+00 7.03E+00 6.87E+00 I

BALA140 -9.03E-01 + 3.96E+00 6.20E+00 BALA140 0.00E+00 + .1.13E+00 1.86E+00 K-40 FE-59 ZRNB-95 i.40E+03 + 1.39E+02 1,+

2.72E+00 + 9.12E+00 6.95E-01 + 5.52E+00 7.54E+01 1.43E+01 K-40 FE-59

+ 1.55E+03 + 1.46E+02 2.01E+00 + 881 E+00 7.81 E+01 1.39E+01 I 8.92E+00 ZRNB-95 -3.27E-02 + 5.96E+00 9.80E+00 BE-7 1.66E+00 + 2.08E+01 3.38E+01 BE-7 -9.45E+00 + 2.72E+01 4.29E+01 I

Collection Date: 6/18/2013 Collection Date: 7/9/2013 Nuclide RQ Activity BA-133 -1.96E-01 + 3.45E+00 Error MDA 5.64E+00 Nuclide BA-133 RQ Activity Error

-6.50E-01 + 4.66E+00 MDA 7.58E+00 I

CO-60 3.08E+00 + 4.80E+00 7.26E+00 CO-60 3.56E-01 + 4.25E+00 7.18E+00 ZN-65 MN-54 CS-134 3.18E-02 + 8.45E+00

-6.56E-01 + 3.44E+00 0.OOE+00 + 4.63E+00 1.39E+01 5.50E+00 7;62E+00 ZN-65 MN-54 CS-134 2.81E+00 + 6.38E+00

-1.28E+00 + 3.49E+00

  • 1.90E+00 + 3.42E+00 9.69E+00 5.47E+00 5.30E+00 I

1.61E+00 + 3.48E+00 CS-137 BALA140 K-40 6.60E-01 + 4.24E+00

+ 1.46E+03 + 1.40E+02 5.36E+00 6.76E+00 7.29E+01 CS-137 BALA140 K-40

-1.09E+00 + 3.51E+00 5.32E-01 + 3.80E+00

+ 1.54E+03 + 1.44E+02 5.55E+00 6.06E+00 7.24E+01 I

FE-59 -1.27E+00 + 9.53E+00 1.53E+01 FE-59 4.75E+00 + 9.51 E+00 1.44E+01 ZRNB-95 BE-7 3.09E+00 + 6.28E+00 1.51E+01 + 2.41 E+01 9.67E+00 3.64E+01 ZRNB-95 BE-7 1.06E+00 + 5.81 E+00

-5.25E-01 + 2.81E+01 9.32E+00 4.62E+01 I

Nuclide RQ Activity Collection Date:

Error 7/23/2013 MDA- Nuclide RQ Activity Collection Date:

Error 8/6/2013 MDA I

BA-133 CO-60 ZN-65 0.OOE+00

-2.28E+00

-2.24E-01

+

+

+

4.99E+00 5.55E+00 7.30E+00 8.20E+00 8.72E+00 1.20E+01 BA-133 CO-60 ZN-65

-7.70E-01 + 3.31 E+00

-1.26E+00 + 5.91E+01

-i.19E+00 + 8.32E+00 5.30E+00 1.12E+01 1.34E+01 I

MN-54 1.26E+00 + 3.18E+00 4.92E+00 MN-54 -7.33E-01 + 3.64E+00 5.84E+00 CS-134 CS-137 BALA140

-2.06E+00 0.00E+00

-4.08E-01

+

+

+

4.09E+00 3.98E+00 3.28E+00 6.40E+00 6.55E+00 5.22E+00 CS-134 CS-137 BALA140 1.44E+00 + 3.01 E+00 2.59E-01 + 3.08E+00

-8.63E-01 + 3.94E+00 4.66E+00 5.01 E+00 6.19E+00 I

K-40 FE-59 ZRNB-95

+ 1.45E+03

-4.45E-01

-1.57E+00

+

+

+

1.41 E+02 1.12E+01 6.51 E+00 7.65E+01 1.83E+01 1l.04E+01 K-40 FE-59 ZRNB-95

+ 1.30E+03 + 1.32E+02

-1.38E+00 + 9.89E+00 0.OOE+00 + 6.20E+00 7.06E+01 1.59E+01 1.02E+01 I

BE-7 -3.46E+00 + 2.74E+01 4.44E+01 BE-7 9.27E+00 + 3.08E+01 4.92E+01 I

I RQ.= Results Qualifier. If blank, result is less than detection limit._lf "+", result is above detection limit. Page 2 of 6 I

TABLEA-12.1

,GAMMASPECTROMETRY RESULTS OF MILK STATION 9b - CONTROL Results in pCi per liter Collection Date: 8/20/2013 Collection Date: 9/3/2013

! Nuclide RQ Activity ... .Error J MDA ' Nuclide RQ Activity Error MDA BA-133 3.63E-02 + 3.85E+00 6.32E+00 BA-133 -2.03E+00 +. 4.32E+00 6.79E+00 CO-60 -1.24E+00 + 4.20E+02 7.1OE+00 CO-60 . 4.81E-01 + 4.53E+00 7.35E+00 ZN-65 -3.87E-01 + 7.28E+00 1.19E+01 ZN-65 -4.87E+00 + 9.28E+00 1.43E+01 MN-54 8.84E-02 + 3.31 E+00 5.41 E+00 MN-54 1.03E+00 + 3.34E+00 5.26E+00 CS-1 34 -7.97E-02 + 2.92E+00 4.78E+00 CS-134 8.25E-01 + 2.64E+00 4.15E+00 CS-1 37 -2.74E-01 + 3.38E+00 5.50E+00 CS-1 37 5.61E-01 + 3.50E+00 5.64E+00 BALA140 3.02E-01 + 4.14E+00 6.70E+00 BALA140 -1.35E-01 + 3.97E+00 6.48E+00 K-40 + 1.44E+03 + 1.37E+02 6.31E+01 K-40 + 1.41E+03 +, 1.42E+02 8.53E+01 FE-59 -4.29E-01 + 9.77E+00 1.60E+01 FE-59 .4.16E+00 + 9.94E+00 1.53E+01 ZRNB-95 -1.01E+00 + 5.83E+00 9.37E+00 ZRNB-95 -1.30E+00 + 6.47E+00 1.04E+01 BE-7 1.37E+01 + 2.24E+01 3.39E+01 BE-7 -1.15E+01 + 2.92E+01 4.60E+01 Collection Date: 9/3/2013 Collection Date: 10/15/2013 Nuclide RQ ACtiVity Error MDA Nuclide RQ Activity Error MDA BA-133 -2.16E+00 + 4.77E+00 7.53E+00 BA-133 3.03E-01 + 3.25E+00 5.28E+00 CO-60 1.08E-01 + 4.32E+00 7.07E+00 CO-60 -1.96E+00 + 1.87E+01 7.06E+00 ZN-65 0.OOE+00 + 8.98E+00 1.48E+01 ZN-65 1.55E-01 + 7.59E+00 1.24E+01 MN-54 -7.72E-01 + 3.27E+00 5.20E+00 MN-54 -1.05E+00 + 4.07E+00 6.50E+00 CS-134 1.34E+00 + 3.81 E+00 6.05E+00 CS-134 3.05E-01 + 4.01 E+00 6.55E+00 CS-137 5.93E-01 + '3.67E+00 5.91 E+00 CS-137 -6.17E-01 + 3.71 E+00 5.99E+00 BALA140 0.00E+00 + 4.84E+00 7.96E+00 BALA140 *.1.60E+00 + 3.46E+00 5.04E+00 K-40 + 1.50E+03 + .:1.42E+02 7.29E+01 K-40 + 1.47E+03 + 1.42E+02 7.30E+01 FE-59 2.28E-01 + 9.50E+00 1.56E+01 FE-59 -4.29E+00 + 1.13E+01 1.78E+01 ZRNB-95 1.65E-01 + 6.1OE+00 9.99E+00 ZRNB-95 -6.73E-01 + 5.38E+00 8.69E+00 BE-7 -1.77E+00 + 2.46E+01 4.OOE+01 BE-7 1.75E+01 + 2.44E+01 3.66E+01 Collection Date: 11/5/2013 Collection Date: 12/10/2013 Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA BA-133 -5.36E-01 + 3.78E+00 6.12E+00 BA-133 -5.43E-01 + 3.74E+00 6.06E+00 CO-60 4.70E-01 + 4.48E+00 7.53E+00 CO-60 -2.84E-01 + 4.30E+00 7.01 E+00 ZN-65 -1.08E+00 + 7.03E+00 1.13E+01 ZN-65 -1.76E+00 + 9.83E+00 1.58E+01 MN-54 0.OOE+00 + 2.57E+00 4.23E+00 MN-54 1.48E-01 + 3.49E+00 5.70E+00 CS-134 1.15E+00 + 2.84E+00 4.43E+00 CS-134 -1.33E+00 + 4.1OE+00 6.53E+00 CS-137 -2.87E-03 + 3.46E+00 5.66E+00 CS-137 5.47E-01 + 3.70E+00 5.97E+00 BALA1 40 -9.58E-02 + 3.51 E+00 5.74E+00 BALA1 40 .8.52E-01 + 3.52E+00 5.43E+00 K-40 + 1.41E+03 + 1.46E+02 8.95E+01 K-40 + 1.42E+03 + 1.46E+02 9.09E+01 FE-59 2.29E+00 + 9.03E+00 1.42E+01 FE-59 1.43E+00 + 9.33E+00 1.50E+01 ZRNB-95 -7.02E-01 + 5.41 E+00 8.74E+00 ZRNB-95 -3.41E+00 + 6.78E+00 1.05E+01 BE-7 3.22E+00 + -2.40E+01 3.89E+01 BE-7 1.44E+01 + 2.36E+01 3.56E+01 RQ = Results Qualifier. If blank, result is less than detection limit. If "+'. result is above detection limit. Page 3 of 6

I TABLE 'A-12.1 I

GAMMA SPECTROMETRY RESULTS OF, MILK STATION 36 - INDICATOR Results in pCi per liter I Collection Date: 1/8/2013 Collection Date:

Nuclide BA-133 RQ Activity

-5.29E-02 + .3.07E+00

Error MDA, 5.04E+00 Nuclide BA-133.

RQ Activity Error 0.00E+00 + 4.04E+00 2/5/2013 MDA 6.65E+00 I

CO-60 , 4.94E-01 + 4.18E+00 6.76E+00 CO-60 -1.26E+00 + 6.40E+01 1.03E+01 ZN-65 MN-54

-2.63E+00 + 1.01 E+01 4.62E-01 + 2.72E+00 1.60E+01 4.34E+00 ZN-65 MN-54

-2.75E+00, + 7.96E+00 2.08E-01 + 3.29E+00 1.26E+01 5.37E+00 I

CS-134 -1.22E+00 + 3.51 E+00 5.56E+00 CS-134 -7.13E-01 + 3.25E+00 5.24E+00 CS-137 BALA140 K-40 0.OOE+00 + 4.20E+00 0.OOE+00 + 5.08E+00

+ 1.46E+03 + 1.45E+02 6.91 E+00 8.35E+00 8.65E+01 CS-137 BALA140 K-40 8.69E-01 + 2.98E+00

-3.56E-01 + 4.26E+00

+ 1.58E+03 +, 1.35E+02 4.72E+00 6.90E+00 6.98E+01 I

FE-59 72.90E+00 + 1.12E+01 1.78E+01 FE-59 2.07E+00 + 7.31 E+00 1.14E+01 ZRNB-95 BE-7

-2.12E-01 + 5.83E+00

-6.15E-01 + 2.57E+01 9.54E+00 4.22E+01 ZRNB-95 BE-7

-1.83E-03 + 4.64E+00 2.54E+00 + 2.28E+01 7.64E+00 3.71E+01 I

Nuclide RQ Activity Collection Date:

Error 3/12/2013 MDA Nuclide RQ Activity Collection Date:

Error 4/9/2013 MDA I

BA--133 CO-60 ZN-65

-2.53E+00 + 4.26E+00 1.05E-01 + 4.15E+00 0.00E+00 + 1.64E+01 6.61 E+00 6.79E+00 2.69E+01 BA-1 33 CO-60 ZN-65

-1.49E+00 + 3.90E+00 1.98E+00 + 3.94E+00

-3.41 E+00 + 7.51 E+00 6.22E+00 6.33E+00 1.17E+01 I

MN-54 7.42E-01 + .2.52E+00 3.92E+00 MN-54 -1.81E-01 + 2.77E+00 4.52E+00 CS-134 CS-1 37

-1.17E+00 + 3.46E+00 6.74E-01 + 3.92E+00 5.48E+00 6.31 E+00 CS-1 34.

CS-1 37

-3.80E-01 + 2.89E+00 5.12E-01 + 2.64E+00 4.69E+00 4.22E+00 I

BALA140 5.15E-01 + 3.76E+00 6.OOE+00 BALA140 -5.72E-01 + 3.79E+00 6.06E+00 K-40 FE-59 ZRNB-95

+ 1.39E+03 + 1.40E+02

.-6.26E-01 + 9.94E+00 3.87E+00 + 5.82E+00 8.13E+01 1.62E+01 8.67E+00 K-40 FE-59 ZRNB-95

+ 1.30E+03 + 1.23E+02 2.79E+00 + 8.85E+00 4.90E-01 + 4.81 E+00 6.59E+01 1.39E+01 7.80E+00 I

BE-7 1.12E+01 + 2.62E+01 4.10E+01 BE-7 -1.84E-01 + 2.37E+01 3.90E+01 4/23/2013 I

Collection Date: Collection Date: 5/7/2013 Nuclide BA-133 CO-60 RQ Activity

-1.39E+00 + 3.85E+00

-2.61 E+00 + 1.22E+01

-.Error *MDA 6.14E+00 Nuclide BA-133 RQ. Activity Error 4.51E-03 + 4.OOE+00 MDA 6.56E+00 I

7.20E+00 CO-60 -2.18E-01 + 5.98E+00 7.25E+00 ZN-65 MN-54 CS-134 8.87E-01 + 5.82E+00

-4.16E-01 + 3.03E+00

-1.27E+00 + 3.37E+00 9.33E+00 4.90E+00 5.36E+00 ZN-65 MN-54 CS-1 34

-1.10E+00 + 8.39E+00 6.18E-01 + 3.20E+00 4.08E-01 + 2.66E+00 1.36E+01 5.12E+00 4.28E+00 I

CS-137 .2.08E-01 + 2.19E+00 3.55E+00 CS-137 1.63E+00 + 3.34E+00 5.14E+00 BALA140 K-40

-1.18E+00 + 3.57E+00

+ 1.40E+03 + 1.34E+02 5.49E+00 8.21E+01 BALA140 K-40

-7.89E-01 + 4.35E+00

+ 1.52E+03 + 1.42E+02 6.91 E+00 6.85E+01 I

FE-59 2.96E+00 + 7.86E+00 1.21E+01 FE-59 5.58E+00 + 9.26E+00 1.37E+01 ZRNB-95 BE-7

-3.06E+00 + 6.77E+00 1.05E+01 + 2.08E+01 1.07E+01 3.22E+01 ZRNB-95 BE-7

-1.40E-01 + 4.41 E+00

-4.47E+00 + 2.47E+01 7.22E+00 3.98E+01 I I

I RQ = Results Qualifier. If blank, result is less than detection limit. If "+". result is above detection limit. Page 4 of 6 I

TABLE A-12.1

.GAMMAkSPECTROMETRY RESULTS OF MILK

- STATION 36 -INDICATOR

  • Results in pCi per liter Collection Date: 5/21/2013  : " .Collection Date: 6/4/2013 Nuclide

. Error -MDA" *,MD=A...

RQ Activity Nuclide RQ Activity Error BA-133 -1.64E+00 + 4.29E+00 6.82E+00 BA-i 33! .-1.53E+00 + 4.1OE+00 6.50E+00 CO-60 -2.14E+00 + 1.48E+01 6.71 E+00 CO-60 1.55E+00 + 4.30E+00 7.01 E+00

,-9.19E-02 +

ZN-65 -1.91E+00 + 8.71 E+00 1.39E+01 ZN-65 7.29E+00 1.20E+01 MN-54 0.00E+00 + 4.24E+00 6.97E+00 MN-54 -8.37E-01 + 3.38E+00 5.38E+00 CS-i 34 -3.30E-01 .+ 2.11 E+00 3.38E+00 CS-134  : 4.81E-01 + 2.97E+00 4.78E+00 CS-1 37 0.00E+00 .+ 3.79E+00 CS-137 6.23E+00 -5.37E-01 +* 3.63E+00 5.86E+00 BALA1 40 0.00E+00 + 1.19E+00 1.95E+00 BALA140 0.OOE+00 + 4.73E+00 7.78E+00 K-40 + 1.56E+03 + 1.44E+02 6.87E+01 K-40 + il.42E+03 + 1.37E+02 6.71E+01 FE-59 -8.75E-01 + 1.01E+01 1.63E+01 FE-59 .2-54E+00 + 8.21 E+00 1.27E+01 ZRNB-95 2.03E+00 + 5.66E+00 8.85E+00 ZRNB-95 -2.06E-01 + 5.74E+00 9.39E+00 BE-7 1.03E+00 + 2.51E+01 4.11E+01 BE-7 1.77E+01 + 2.62E+01 3.98E+01

ct iCollecti4on Date: 6/18/2013 Collection Date: 7/9/2013 Nuclide- RQ -Activity Error MDA Nuclide RQ Activity Error .MDA BA-133 -4.92E-01 + 3 .78E+00 6.13E+00 BA-133 -1.47E+00 + 3.57E+00 5.62E+00 CO-60 -6.14E-01 + 1.27E+01 7.59E+00 CO-60 -3.23E-02 + 4.76E+00 7'69E+00 ZN-65 4.03E+00 + 9 .16E+00 1.43E+01 ZN-65 1.68E+00 + 7.48E+00 1.19E+01 MN-54 -7.32E-01 + 3 .08E+00 4.88E+00 MN-54 0.OOE+00 + 3.22E+00 5.29E+00 CS-134 1.11E+00 + 3 .07E+00 4.83E+00 CS-134 3.17E+00 + 3.06E+00 4.38E+00 CS-137 0.OOE+00 + 3 .73E+00 6.13E+00 CS-137 0.OOE+00 + 5.44E+00 8.95E+00 BALA1 40 1.99E-02 + 4 .53E+00 7.44E+00 BALA140 0.OOE+00 + 4.74E+00 7.79E+00 K-40 + 1.40E+03 + 1.44E+02 8.51E+01 K-40 + 1.49E+03 + 1.44E+02 7.74E+01 FE-59 2.93E-01 + .7.35E+00 1.20E+01 FE-59 -3.55E-01 + 7.94E+00 1.30E+01 ZRNB-95 -5;55E-02 + 5 .84E+00 9.59E+00 ZRNB-95 0.OOE+00 + 6.83E+00 i.12E+01 BE-7. -5.09E+00 + 2 .43E+01 3.90E+01 BE-7 5.47E+00 + 2.47E+01 3.96E+01 Collection Date: 7/23/2013 Collection Date: 8/6/2013 Nuclide RQ Activity Error MDA Nuclide RQ Activity
  • Error MDA, BA-133, .3.10E+00 + 3.57E+00 5.28E+00 BA-133 -1.31E+00 + 4.26E+00 6.79E+00 CO-60 1.08E+00 + 4.73E+00 7.55E+00 CO-60 -1.07E-01 + 4.36E+00 7.14E+00 ZN-65 1.95E-02 + 9.03E+00 1.48E+01 ZN-65 -3.94E+00 + 9.95E+00 1.56E+01 MN-54 0.OOE+00 + 4.46E+00 7.33E+00 MN-54 -1.O0E-01 + 3.07E+00 5.02E+00 CS-134 1.71 E+00 + 4.02E+00 6.34E+00 CS-134 -2.26E-01 + 3.47E+00 5.66E+00 CS-137 2.36E-01 + 3.79E+00 6.18E+00 CS-137 0.OOE+00 + 3.48E+00 5.72E+00 BALA140 -2.09E-01 + 3.81 E+00 6.19E+00 BALA140 7.20E-01 + 4.03E+00 6.39E+00 K-40 + 1.36E+03 + '1.35E+02 7.29E+01 K-40 + 1.41E+03 + i.45E+02 8.95E+01 FE-59 -3.27E-01 + 8.10E+00 1.32E+01 FE-59 -2.65E+00 + 9.99E+00 1.58E+01 ZRNB-95 -5.50E-01 + 6.04E+00 9.82E+00 ZRNB-95 0.OOE+00 + 7.89E+00 1.30E+01 BE-7 6.48E+00 + 2.53E+01 4.03E+01 BE-7 -3.99E+00 + 2.58E+01 4.17E+01 RQ = Results Qualifier. If blank, result is less than detection limit. If '+', result is above detection limit. Page 5 of 6

I TABLE A-12.1 GAMMA SPECTROMETRY RESULTS OF MILK STATION 36 - INDICATOR..

I Results in pCi per liter Collection Date:

I Nuclide RQ` Activity- 1, Error 8/20/2013 MDA Nuclide Collection Date: 9/3/2013 I

- RQ Activity Error -- MDA BA-1 33 CO-60 ZN-65

-1.20E-01 + 4.21 E+00

+

0.OOE+00 + 3:86E+00

-2.59E-01 + 9.1OE+00 6.90E+00 6.35E+00 1.49E+01 BA-1 33 CO-60 ZN-65

-1.09E+00 + 4.39E+00

--1.49E+00 + 5.31E+00 2.43E-01 + 6.29E+00 7.06E+00 8.45E+00 1.03E+01 I

MN-54 1.40E+00 + 3.14E+00 CS-134 CS-137

-8.36E-01 + 3.37E+00 3.52E-02 + 3.54E+00 4.82E+00 5.39E+00 5.81 E+00 MN-54 CS-134 CS-1 37 6.13E-02 + 4.37E+00 2.71E-01 + 3.55E+00

-6.45E-01 + 4.04E+00 7.17E+00 5.78E+00 6.53E+00 I

BALA140 -1.05E+00 + 4.27E+00 6.69E+00 BALA140 -1.84E+00 + 4.94E+00 7.61 E+00 K-40 FE-59 ZRNB-95

+ 1.43E+03 + 1.38E+02

-8.53E-01 + 9.77E+00

-9.06E-01 7.29E+01 1.58E+01 K-40 FE-59

+ 1.44E+03.+ 1.46E+02 0.OOE+00 + 9.63E+00 8.79E+01 1.58E+01 I 5.94E+00 9.56E+00 ZRNB-95 0.OOE+00 '+ 5.98E+00 9.83E+00 BE-7 -6.65E+00 + 2.79E+01 4.46E+01 BE-7 -3.91E-01 + 2.13E+01 3.49E+01 I

Collection Date: 9/3/2013 Collection Date: 10/15/2013 Nuclide BA-133 RQ Activity

-4.43E-01 + 3.77E+00 Error MDA 6.13E+00 Nuclide RQ Activity BA-133 Error

-7.23E-02 + 4.OOE+00 MDA 6.56E+00 I

CO-60 -9.71E-01 + 3.07E+01 7.01 E+00 CO-60 -7.48E-01 + 5.25E+00 8.50E+00 ZN-65 MN-54 CS-1 34

-1.55E+00 + 7.97E+00 0.OOE+00 + 3.88E+00

-4.61E-01 + 3.06E+00 1.28E+01 6.39E+00 4.94E+00 ZN-65 MN-54 CS-134 1.34E+00 + 8.14E+00 1.OOE-01 + 3.30E+00

-1.41E-01 + 3.03E+00 1.31E+01 5.40E+00 4.96E+00 I

CS-137 BALA140 K-40 2.49E-01 + 3.23E+00

-1.11E+00 + 4.67E+00

+ 1.29E+03 + 1.32E+02 5.26E+00 7.36E+00 7.12E+01 CS-137 BALA140 K-40 +

1.14E+00 + 3.49E+00

-3.39E-01 + 4.50E+00 1.39E+03 + 1.41 E+02 5.48E+00 7.30E+00 8.27E+01 I

FE-59 -1.38E+00 + 9.69E+00 1.56E+01 FE-59 1.32E-01 + 8.68E+00 1.42E+01 ZRNB-95

  • 1.99E-02 + 5.68E+00 9.33E+00 ZRNB-95 -4.79E-01 + 5.50E+00 8.93E+00 BE-7 -1.93E+00 + 2.29E+01 3.73E+01 BE-7 -3.68E+00 + 2.46E+01 3.97E+01 Collection Date: 11/5/2013 Collection Date: 12/10/2013 I

Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA BA-133 CO-60

-1.18E+00 + 4.16E+00 2.58E+00 + 4.06E+00 6.65E+00 6.04E:-00 BA-133 CO-60

-1.03E-01 + 4.48E+00

-1.71E-01 + 4.92E+00 7.36E+00 8.06E+00 I ZN-65 MN-54 CS-134

-1.76E-01 + 7.96E+00

-3.20E-01 + 3.75E+00 5.99E-02 + 3.23E+00 1.30E+01 6.1OE+00 5.29E+00 ZN-65 MN-54 CS-134 0.OOE+00 + 1.72E+01 0.OOE+00 + 4.83E+00

-1.71E+00

+ 3.66E+00 2.82E+01 7.94E+00 5.73E+00 I

CS-137 1.79E+00 + 3.18E+00 4.80E+00 CS-137 -9.56E-01 + 4.18E+00 6.70E+00 BALA140 K-40 0.OOE+00 + 1.14E+00

+ 1.41E+03 + 1.42E+02 1.87E+00 8.35E+01 BALA140 K-40 0.OOE+00 + 1.13E+00

+ 1.29E+03 + 1.35E+02 1.87E+00 8.08E+01 i

FE-59 5.71E-01 + 9.01 E+00 1.47E+01 FE-59 -3.04E+00 + 1.09E+01 1.72E+01 ZRNB-95 BE-7

-1.76E+00 + 6.63E+00

-1.22E+00 + 2.57E+01 1.06E+01 4.20E+01 ZRNB-95 BE-7 1.83E-01 + 6.14E+00 1.60E+01 + 2.45E+01 1.01E+01 3.70E+01 I I

I RQ = Results Qualifier. If blank, result is less than detection limit. If "+". result is above detection limit. Page 6 of 6 I

TABLE A-12.2 GAMMA SPECTROMETRY RESULTS OF MILK -

SUMMARY

Results in pCi per liter Number Number of Average- Aictivity Activity Average of Positive Nuclide Activity Low High MDA Samples IDs BA- 133 Ind -6.56E-01 -2.53E+00 3.1OE+00 6.05E+O( 0 18 0 BA-133 Cntl -5.33E-02 -2.16E+00 3.90E+00 5.82E+Q( 18 0 0'

BALA140 Ind -3.44E-01 -1.84E+00 7.20E-01 5.79E+O( 0 18 0 BALA140 (Cntl 1.84E-02 -1.41 E+00 2.14E+00 5.59E+O( 18 0 BE-7 Ind 2.37E+00 -6.65E+00 1.77E+01 3.73E+O0 18 0 BE-7 CntI 2.41E+00 -1.15E+01 1.75E+01 3.81 E+O' 1 18 0 CO-60 Ind -1.43E-01 -2.61 E+00 2.58E+00 6.99E+O0 18 0 CO-60 Cntl -9.68E-02 -2.28E+00 3.08E+00 7.15E+O0 18 0 0

CS-1 34. Ind. -6.87E-02 -1.71 E+00 3.17E+oO 4.85E+O010 18 0 CS-1 34 Cntl -2.98E-01 -2.15E+00 1.90E+00 5.23E+O00 18 0 CS-1 37 Ind 2.89E-01 -9.56E-01 1.79E+00 5.50E+04 18 0 CS-137 Cntl .6.16E-02 -1.40E+00 1.61E+00 5.42E+04 18 0 FE-59 Ind 2.19E-01 -3.04E÷00 5.58E+00 1.38E+O 0 18 0 FE-59 Cntl 1.76E-01 -4.29E+00 4.75E+00 1.44E+O 18 0 0.

1*

K-40 Ind . 1.42E+03 1.29E+03 1.58E+03 7.34E+O 01] 18 18 K-40 Cntl 1.45E+03 1.30E+03 1.55E+03 7.23E+O 18 18 MN-54 Ind 5.58E-02 -8.37E-01 1.40E+00 5.31E+O01 18 0 MN-54 Cntl -7.71 E-02 -1.28E+00 2.27E+00 5.33E+O0 18 0 ZN-65 Ind -5.35E-01 -3.94E+00 4.03E+'00 1.39E-0 0 18 0 ZN-65 CntI 7.17E-02 -4.87E+00 4.95E+00. 1.26E+O 18 ZRNB-95 Ind .-4.39E-02 -3.06E+00 3.87E+00 9.03E+O0 18 0 ZRNB-95 Cntl -2.75E-01 -3.41E+00 3.09E+00 9.11E+00. 18 .0 Ind = Indicator Stations Cntl = Control Stations Page 1 of 1

I TABLE A-45.1 GAMMA SPECTROMETRY RESULTS OF ROOTCROPS, Results in pCi/ kilogram (wet)

I Station 37 is Indicator - Station 9c is Control I Station 37 Potato collected 7/2/2013 Station 37 Potato collected 8/27/2013 Nuclide RQ Activity K-40 + 3.20E+03 +

Error 3.29E+02 MDA-1.48E+02 Nuclide R-Q Activity K-40 + 3.40E+03 +

Error 2.92E+02 MDA 1.87E+02 i

MN-54 -1.57E-01 6.25E+00 1.02E+01 MN-54 0.OOE+00 + 9.97E+00 1.64E+01 CO-58 FE-59 CO-60 2.70E+00 +

3.76E-02 3.84E+00 +

4.78E+00 1.73E+01 9.03E+00 6.79E+00 2.84E+01 1.38E+01 CO-58 FE-59 CO-60

-8.67E-01 +

1.35E+00 +

-2.17E+00 +

7.13E+00 2.14E+01 2.53E+01 1.16E+01 3.50E+01 1.52E+01 I

ZN-65 1.29E+00 + 1.68E+01 2.73E+01 ZN-65 2.05E+00 + 1.96E+01 ZRNB-95 1-131

-3.54E-01 ÷

-2.49E+00 9.43E+00 6.34E+00 1.54E+01 9.92E+00 ZRNB-95 1-131 9.05E+00 +

-1.38E+00 +

1.54E+01 7.87E+00 3.19E+01 2.39E+01 1.28E+01 I

CS-134 2.25E+00 4.54E+00 6.73E+00 CS-1 34 2.82E+00 + 6.88E+00 1.09E+01 CS-137 BALA140 3.92E+00 +

-1.46E+00 6.95E+00 8.21 E+00 1.04E+01 1.29E+01 CS-137 BALA140 4.42E+00 +

-1.87E-01 +

8.66E+00 8.84E+00 1.36E+01 1.45E+01 I Station 37 Onion collected 7/16/2013 Station 37 Onion collected 8/27/2013 I

Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 MN-54

+ 7.65E+02

-6.13E+00

+

+

2.03E+02 1.01E+01 2.29E+02 1.56E+01 K-40 MN-54

+ 1.64E+03 +

3.47E+00 +

2.40E+02 8.34E+00 2.39E+02 1.31E+01 I

+

CO-58 2.45E+00 7.73E+00 1.22E+01 CO-58 -5.26E+00 + 1.10E+01 1.74E+01 FE-59 CO-60 3.76E+00

-9.91E-01

+

2.25E+01 1.41E+01 3.61 E+01 1.73E+01 FE-59 CO-60

-9.18E+00 +

-1.44E+00 +

2.84E+01 8.93E+00 4.51E+01 1.44E+01 I

ZN-65 5.51 E+00 1.99E+01 3.17E+01 ZN-65 -8.32E+00 + 2.46E+01 3.92E+01 I

+

ZRNB-95 5.70E-02 1.34E+01 2.20E+01 ZRNB-95 -2.30E+00 + 1.66E+01 2.69E+01

+

1-131 0.OOE+00 1.02E+01 1.68E+01 1-131 -3.72E+00 + 1.13E+01 1.82E+01

+

CS-134 5.27E+00 8.90E+00 1.39E+(1 CS-134 -6.33E+00 + 1.31 E+01 2.10E+01

+

CS-137 1.78E+00 9.33E+00 1.50E+01 CS-1 37 -2.55E+00 + 1.04E+01 1.67E+01 BALA140 2.01E-01 +

1.04E+01 1.71 E+01 BALA140 8.72E-02 + 9.30E+00 1.53E+01 I

Station 37 Potato colle,cted 7/30/2013 Station 9c Potato collected 8/9/2013 I

Nuclide RQ Activity Error MDA Nuclide RQ Activity Error K-40 MN-54

+ 4.31E+03 +

0.OOE+00 +

4.20E+02 1.47E+01 3.24E+02 2.42E+01 K-40 MN-54

+ 3.78E+0 3+

1.08E-0 1+

3.60E+02 9.07E+00 MDA 2.74E+02 1.49E+01 I

CO-58 2.34E+00 + 1.20E+01 1.94E+01 CO-58 -1.51E+0 0+ 1.11E+01 1.81E+01 FE-59 CO-60 0.OOE+00 +

-1.72E+00 +

3.39E+01 1.15E+01 5.57E+01 1.86E+01 FE-59 CO-60 7.26E-0 1+

-3.70E+0 0+

2.89E+01 1.37E+01 4.74E+01 2.19E+01 I

ZN-65 -1.39E+01 + 3.48E+01 5.55E+01 ZN-65 -1.28E+0 1+ 2.74E+01 4.32E+01 ZRNB-95 1-131 CS-1 34

-3.70E+00 +

-5.81 E+00 +

-6.37E+00 +

2.43E+01 1.29E+01 1.62E+01 3.94E+01 2.05E+01 2.61E+01 ZRNB-95 1-131 CS-134

-6.99E+0 0+

-5.93E+0 0+

-3.69E+0 0+

2.08E+01 1.43E+01 1.37E+01 3.32E+01 2.29E+01 2.23E+01 I

CS-137 -7.99E+00 + 1.56E+01 2.46E+01 CS-137 -2.75E+0 0+ 1.30E+01 2.11E+01 BALA140 6.69E+00 + 1.26E+01 1.91E+01 BALA140 2.32E-0 1+ 1.25E+01 2.05E+01 I I

RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit. Page 1 of 1 I

. ; ;TABLE'A- 15.2 GAMMA SPECTROMETRY RESULTS OF ROOT CROPS -

SUMMARY

Results in pCi/ kilogram (wet)

Average Activity Activity Average Number of Number of Nuclide Activity Low High MDA Samples Positive IDs BALA140 Ind 1.07E+00 -1.46E+OO 6.69E+00 1.58E+01 5 0 BALA140 cntl 2.32E-01 2.32E-01 2.32E-01 2.05E+01 1 0 CO-58 Ind 2.72E-01 -5.26E+00 2.70E+00 1.35E+01 5 0 CO-58 cntl -1.51 E+00 -1.51E+00 -1.51EOO 1.81E+01 1 , 0 CO-60 Ind -4.96E-01 -2.17E+00 3.84E+00 1.58E+01 5 0 CO-60 cntl -3.70E+00 -3.70E+00 -3.70E+00 2.19E+01 1 0 CS-1 34 Ind -4.74E-01 -6.37E+00 5.27E+00 1.57E+01 5 0 CS-134 cntl -3.69E+00 -3.69E+00 -3.69E+00 2.23E+01 1 0 CS-137 Ind -8.42E-02 -7.99E+00 4.42E+00 1.61E+01 5 0 CS-137 cntl -2.75E+00 -2.75E+00 -2.75E+00 2.11E+01 1 0 FE-59 Ind -8.08E-01 -9.18E+00 3.76E+00 4.01E+01 5 ,0 FE-59 entl 7.26E-0i 7.26E-01 7.26E-01 4.74E+01 1 0 1-131 Ind -2.68E+00 -5.81 E+00 0.00E+00 1.56E+01 5 0 1-131 cntl -5.93E+00 -5.93E+00 -5.93E+00 2.29E+01 1 0 K-40 Ind 2.66E+03 7.65E+02 4.31 E+03 2.26E+02 5 5 K-40. cntl 3.78E+03 3.78E+03 3.78E+03 2.74E+02 1 1 MN-54 Ind -5.64E-01 -6.13E+00 3.47E+00 1.59E+01 5 0 MN-54 cntl 1.08E-01 1.08E-01 1.08E-01 1.49E+01 1 0 ZN-65 Ind -2.68E+00 -1.39E+01 5.51 E+00 3.71E+01 5 0 ZN-65 cntl -1.28E+01 -1.28E+01 -1.28E+01 4.32E+01 1 0 ZRNB-95 Ind 5.51 E-01 -3.70E+00 9.05E+00 2.55E+01 5 0 ZRNB-95 cntl -6.99E+00 -6.99E+00 -6.99E+00 3.32E+01 1 0 Ind = Indicator Stations Cntl = Control Stations Page 1 of 1

I TABLEA*-6.1 GAMMA SPECTROMETRY RESULTS- OFFRUITS Results in pCi/ kilogram. (wet)

I Station 37 is Indicator r Station 9c isControl I Station,37, Peaches collected 7/12/2013 Station 37 Apples collected 8/14/2013

-Nuclide R-K-40 Activity

+ 1..42E+03 +

Error-2.10E+02 MDA 1.34E+02 Nu cli1de Rd.-- Alctivity-K-40 -. 1.21E+03 +

.,Error'.

2.68E+02 MDA 3.30E+02 i

MN-54 -1.86E+00 + 6.48E+00 1.02E+01 MN-54 " 8.18E-01 + 1.25E+01 2.04E+01 CO-58 FE-59 CO-60 0.OOE+00 +-

2.07E+00. +

3.06E+00 +

1'.05E+01.

1.89E+01 5.73E+00 1.73E+01 3.04E+01 8.25E+00 C.0-58 FE-59 CO-60

.0;00E+00

-1.62E+01

-7.15E-01

+

+/-

+

1.27E+01 4.12E+01 1.39E+01.,.,

2.09E+01 6.49E+01 2.28E+01 I

ZN-65 -1.15E-01 + 1.43E+0V 2.34E+01 ZN-65., -4.40E+00 + 2.93E+01 , 4.74E+01 ZRNB-95 1-131 0.OOE+00 +

-2.40E+00 +

1.14E+01, 7.21 E+00 1.58E+01 1.14E+01 ZRNB-95 1-131.

2.75E+00

-8.94E+00

+

+

2.43E+01 3.10E+01 3.96E+01 5.OOE+01 I

CS-134 -2.61 E+00 + 6.73E+00 1.05E+01 CS-134 -1.04E+01 + 1.86E+01 2.96E+01 CS-137 BALA140

-1.50E+00 +

0.00E+00 +

5.07E+00 1.17E+01 7.83E+00 1.92E+01 CS-137 BALA140

-2.67E+00 7.26E+00 +

+ 1.42E+01*

2.20E+01 2.30E+01 3.44E+01 I Station 37 Peaches collected 7/30/2013 Station 37 Peaches collected 8/27/2013 I

'Nuclide Rd -Activity- -... ..Error MDA -Nuclide _ROQ- Acti-vity -..- . :, Error. MDA K-40 MN-54

+ 1.92E+03 + 2.42E+02 6.46E+00 + 7.45E+00 1.94E+02 1.10E+01 K-40 MN-54

+ 1.46E+03 +

2.15E+00 +

.1.96E+02 7.40E+00 1.91 E+02 1.18E+01 I

CO-58 0.OOE+00 + 6.45E+00 1.06E+01 CO-58 5.96E+00 + 7.55E+00 -1.15E+01 FE-59 CO-60 ZN-65

-5.65E+00 + 2.30E+01 8.88E-01 + 9.06E+00 1.44E+01 + 1.72E+01 3.67E+01 1.56E+01 2.53E+01 FE-59 CO-60:

'ZN-65

-7.52E-01 +

-2.15E-01 +

1.90E+01 7.38E+00 0.OOE+00 + .2.77E+01 3.11E+01 1.21 E+01 4.56E+01 I

ZRNB-95 1-131 CS-134 7.49E-01 +

4.68E+00 + 8.88E+00 0.OOE+00 +

1.23E+01 1.02E+01 2.OOE+01 1.41 E+01 1.68E+01 ZRNB-95 1-131 CS-134 4.32E-01 +- 1.28E+01

-5.40E+00 +' 9.01 E+00 6.29E-01 + 8.86E+00

.2.09E+01 1.43E+01 1.45E+01 I

CS-137 -3.43E+00 + 9.20E+00 1.46E+01 CS-137 -1.74E+00 + 8.33E+00 11.35E+01 BALA140 0.OOE+00 + 8.73E+00 1.44E+01 BALA140 .4.17E-01 + 5.91 E+00 9.59E+00 U

Nuclide Station 37 Apples collected Ro -Activity .. .Err-or 8/9/2013 MDA -Nuclide- Ro Station 37 Applescollected Actifvify Error 9/10/2013 MDA- -

I K-40 + 1.19E+03 + 2.46E+02 2.65E+02 K-40 + 1.53E+03 + 2.30E+02 2.11E+02 MN-54 CO-58 1.86E+00 +

-3.45E-02 +

1.09E+01 1.23E+01 1.76E+01 2.02E+01 MN-54 CO-58

-2.99E+00

-3.05E+00

+

+

9.79E+00 8.28E+00 1.56E+01 1.30E+01 I

FE-59 -6.43E+00 + 2.97E+01 4.74E+01 FE-59 7.20E-01 + 2.03E+01 3.32E+01 CO-60 ZN-65 ZRNB-95

-5.24E-01 +

-5.75E+00 +

-3.22E+00 +

1.47E+01 2.67E+01 1.69E+01 2.21 E+001 4.29E+01 2.71 E+01 CO-60 ZN-65 ZRNB-95 1.72E+00 2.22E+00

-2.04E-02

+

+

+

1.06E+01 2.11E+01 1.51 E+01 1.80E+01 3.43E+01 2.48E+01 I

1-131 CS-134 CS-137 5.24E+00 +

-3.49E+00 +

3.37E+00 +

1.05E+01 1.42E+01 1.02E+01 1.64E+01 2.30E+01 1.60E+01 1-131 CS-134 CS-137 6.69E-01

-3.13E+00

-4.95E+00

+

+

+

9.81 E+00 1.05E+01 1.09E+01 1.60E+01 1.70E+01 1.72E+01 1

BALA1 40 5.88E+00 + 1.37E+01 2.07E+01 BALA140 1.63E+00 + 1.23E+01 1.99E+01 I

I RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit. Page 1 of 2 I

,TABLE A-1 6.1 GAMMA- SPECTROMETRY RESULTS,,OFz FRUITS

  • 'Results in pCi/ kilogram (wet)

Station 37 is Indicator - Station 9c.is 'Cbntrol Station 37 wine grapes collected 9/10/2013 Statiorn 37 wine grapes collected 9/10/2013 FNuclide--RQ -Activity - Er-r J* MDA .Activity '; -Error' MDA- -1 K-40 + 2.36E+03 + 2.46E+02 1.04E+02 K-40ý + 2.55E+03 + 2.89E+02 2.44E+02 MN-54 -8.07E-03 + 5.57E+00 9.15E+00 MN-54 1.90E-01 + 9.78E+00 1.60E+01 CO-58 -1.25E-01 + 5.64E+00 9.25E+00 4.32E+00 +

CO-58 8.70E+00 1.36E+01 FE-59 -5.28E-01 + 1.78E+01 2.91 E+01 FE-59 2.02E-01 + 1.94E+01 3.19E+01 CO-60 1.60E+00 + 5.76E+00, 8.93E+00 CO-60 -3.38E+00 + 1.04E+01 1.66E+01 ZN-65 1.02E+01 + 1.41E+01 2.05E+01 ZN-65 -5.03E+00 + 2.05E+01 3.28E+01 ZRNB-95 -9.69E-02 + 5.08E+00 8.31 E+00 ZRNB-95 3.96E+00 + 1.42E+01 2.26E+01

.1-131

'2.54E+00 + 4.78E+00 7.23E+00 1-131 3.26E+00 + 9.97E+00 1.60E+01 0CS-134 8.35E-02'+ 4.63E+00, 7.59E+00 CS-134 - 1.72E+00 + 1.09E+01 1.77E+01 CS-137 2.01E-01 +- 4.62E+00 7.54E+00 CS-137 -2.05E+00 + 1.04E+01 1.69E+01 BALA140 -1.38E+00 + 5.95E+00 9.12E+00 BALA140 2.78E+00 + 1.05E+01 .1.66E+01 IStation 9c Apples collected 9/6/2013 r-Niide RQ Ac-tvity . V Error MD-A...

K-40 + 1.01E+03 + 1.94E+02 1.98E+02 MN-54 -1.51 E+00 _+ 7.00E+00 1.,12E+01 CO-58 -2.18E+00 + 7.84E+00 1.25E+01 FE-59 ,-1.10E+00 _+ 2.01 E+01 3.29E+01 CO-60 6.61E-01 + 8.93E+00 1.54E+01 ZN-65 -5.40E+00 + 2.15E+01 3.45E+01 ZRNB-95 .-5.05E-01 + 1.17E+01 1.91 E+01 1-131 6.72E-0.1 + :1.13E+01 1.85E+01 0CS-134 -3.63E+00 + 9.61 E+00 1:54E+01 CS-137 -2.50E.+00 + 8.19E+00 1.31 E+01

!BALA140 -3.34E-01 + - 1.08E+01 1.77E+01 RO = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit. Page 2 of 2

I TABLEA,- 16.2 GAMMA SPECTROMETRY RESULTS OF FRUITS-

SUMMARY

Results in.pCi/ kilogram (wet)

I Average Activity Activity Average Number of Number of Nuclide Activity Low High MDA Samples Positive IDs BALA 40 Ind 2.07E+00 -1.38E+00 7.26E+00 1.80E+01 0 BALA140 CntI -3.34E-01 -3.34E-01 -3.34E-01 1.77E+01 0 CO-58 CO-58 Ind CntI 8.84E-01

-2.18E+00

-3.05E+00

-2.18E+00 5.96E+00

-2.18E+00 1.45E+01 1.25E+01 0

0 I CO-60 Ind 3.04E-01 -3.38E+00 3.06E+00 1.56E+01 0 CO-60 CntI 6.61 E-01 6.61 E-01 6.61E-01 1.54E+01 0 CS-134 Ind -2.15E+00 -1.04E+01 1.72E+00 1.71E+01 0 CS-134 CntI -3.63E+00 -3.63E+00 -3.63E+00 1.54E+01 0 CS-137 Ind -1.60E+00 -4.95E+00 3.37E+00 1.46E+01 0 CS-137 Cnti -2.50E+00 -2.50E+00 -2.50E+00 1.31E+01 0 FE-59 Ind -3.32E+00 -1.62E+01 2.07E+00 3.81 E+01 0 FE-59 Cnti -1.10E+00 -1.10E+00 -1.10E+00 3.29E+01 0 1-131 Ind -4.32E-02 -8.94E+00 5.24E+00 1.82E+01 0 1-131 CntI 6.72E-01 6.72E-01 6.72E-01 1.85E+01 0 K-40 Ind 1.70E+03 1.19E+03 2.55E+03 2.09E+02 8 K-40 CntI 1.01 E+03 1.01E+03 1.01 E+03 1.98E+02 1 MN-54 Ind 8.28E-01 -2.99E+00 6.46E+00 1.40E+01 0 MN-54 CntI -1.51 E+00 -1.51 E+00 -1.51 E+00 1.12E+01 0 ZN-65 Ind 1.44E+00 -5.75E+00 1,44E+01 3.40E+01 0 ZN-65 CntI -5.40E+00 -5.40E+00 -5.40E+00 3.45E+01 0 ZRNB-95 Ind 5.68E-01 -3.22E'+00 3.96E+00 2.28E+01 0 ZRNB-95 CntI -5.05E-01 -5.05E-01 -5.05E-01 1.91 E+01 0 I

I I

Ind = Indicator Stations Cntl = Control Stations Page 1 of1

TABLE A-17.1 GAMMA,SPECTROM ETRY. RESUILTS OF VEGETABLES "Results in pCi/ kilogram (wet)

Station 37 is Indicator - Station 9c is Control Station 37 Asparagus collected 4/16/2013 Station 37 Green Bean collected 7/16/2013 MDA--1 Nuclide RQ Activity Error MDA " Nucl"ide RQ Activity Error -

K-40 + 2.57E+03 + 2.93E+02: 2.24E+02 I K-40 + 3.62E+03 + 4.OOE+02 3.38E+02 MN-54 -5.86E-01 + 9.96E+00 1.63E+01 MN-54 -8.64E+00 + 1.72E+01 2.71 E+01 CO-58 -7.03E-01 + 7.39E+00 1.20E+01 CO-58 5.13E+00 + 1.31E+01 2.06E+01 FE-59 -7.71E+00 + 2.57E+01 4.06E+01 FE-59 0.OOE+00 + 2.80E+01 4.60E+01 CO-60 1.68E+00 + 9.58E+00 1.66E+01 CO-60 -6.58E+00 + 1.77E+01 2.81E+01 ZN-65 -5.05E+00 + 2.48E+01 4.OOE+01 ZN-65 0.OOE+00 + 3.64E+01 5.98E+01 ZRNB-95 -7.OOE-01 + 1.83E+01 2.99E+01 ZRNB-95 3.24E-01 + 2.30E+01 3.78E+01 1-131 -3.70E+00 + 1.11E+01 1.78E+'01 .1-131. -7.31E+00 + 1.68E+01 2.69E+01 CS-134 1.84E+00 + 9.87E+00 1.60E+01 CS-134 -1.25E+00 + 1.44E+01 2.36E+01 CS-137 -3.22E+00 + 1.02E+01 1.62E+01 CS-137 -4.68E+00 + 1.64E+01 2.63E+01 BALA140 -2.22E+00 + 1.35E+01 2.17E+01 BALA140 2.06E-01 + 1.63E+01 2.67E+01 Station 37 Asparagus collected 5/14/2013 Station 37 Bell Peppers collected 7/30/2013 Nuclide RQ Activity Error MDA Nuclide RQ Activity Error ..,MDA K-40 + 2.25E+0:3 + 3.22E+02 3.18E+02 K-40 + 1.46E+0 3+ 2.64E+02 2.66E+02 MN-54 -2.50E+0' 0 ..I 1.06E+01 1.69E+01 MN-54 4.51 E-0 1+ 7.92E+00 1.29E+01 CO-58 5.77E+O00 ..I 1.13E+01 1.77E+01 CO-58 1.46E-0 2+ 1.06E+01 1.73E+01 FE-59 1.13E+0 1 + 2.99E+01. 4.69E+01 FE-59 7.75E-0 1+ 2.77E+01 4.53E+01

+

CO-60 -1.06E+0I0 + 1.35E+01 2.21E+01 CO-60 2.16E+0 0+ 1.07E+01 1.86E+01 ZN-65 -3.38E+010 + 2.70E+01 4.38E+01 ZN-65 -2.75E+0 0+ 2.68E+01 4.35E+01 ZRNB-95 6.82E+0' 0 + 2.09E+01 3.33E+01 ZRNB-95 -4.05E+0 0+ 2.10E+01 3.39E+01 1-131 -1.84E+O00 ..+ 1.34E+01 2.18E+01 1-131 -8.94E+0 0+ 1.39E+01 2.19E+01 CS-1 34 -6.74E+0'0 + 1.49E+0,1 2.38E+01.. CS-134 7.15E+0 0+ l.15E+01 1.79E+01 CS-1 37 8.19E+0' 0 + 1.1.7E+01 1.78E+01 CS-137 7.17E+0 0+ 1.25E+01 1.94E+01 BALA140 7.45E+0I0 1.52E+01 2.32E+01 BALA140 1.92E+0 0+ 1.56E+01 2.52E+01 Station 37 Broad Leaf Vegtable collected 6/14/2013 Station 37 Broad Leaf Vegtable collected. , 8/9/2013 Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 + 5.39E+0.3 + 6.65E+02 3.52E+02 K-40 + 4.81 E+03 + 5.69E+02 4.45E+02 MN-54 5.22E+0' 0 + 1.61E+01 2.50E+01 MN-54 9.32E-01 + 1.82E+01 2.98E+01 CO-58 6.72E-0 1 + 1.22E+01 1.98E+01 CO-58 1.64E-01 + 1.64E+01 2.70E+01 FE-59 -7.OOE+0' 0 + 4.75E+01 7.60E+01 FE-59 -1.44E+01 + 5.22E+01 8.28E+01 CO-60 -2.86E+0'0 + 2.42E+01 3.91 E+01 CO-60 1.20E+01 + 2.07E+01 3.39E+01 ZN-65 1.33E+0 1 + 2.60E+01 3.68E+01 ZN-65 3.99E-01 + 4.64E+01 7.61E+01 ZRNB-95 -1.96E+0' 0 + 2.48E+01 4.02E+01 ZRNB-95 -4.34E+00 + 3.38E+01 5.48E+01 1-131 5.16E-0 1 + 1.39E+01 2.27E+01 1-131 2.35E+01 + 2.26E+01 3.41E+01 CS-1 34 -3.06E+0'0 + 1.55E+01 2.47E+01 CS-134 6.57E+00 + 2.06E+01 3.30E+01 CS-1 37 0.OOE+0' 0 + 1.62E+01 2.67E+01 CS-137 -1.74E+00 + 2.02E+01 3.29E+01 BALA140 3.40E+0' 0 + 2.03E+01 3.18E+01 BALA140 -1.80E+00 + 2.66E+01 4.33E+01 RQ = Results Qualifier. If blank, result is less than detection limit. If '+", result is above detection limit. Page 1 of 2

I TABLEA-,17.1 GAMMASPECTROMETRYRESULTS OF VEGETABLES

.Results in pCi/ kilogram (wet)

I Station 37 is Indicator - Station 9c is Control I Station 37 Broad Leaf Vegtable collected 6/28/2013 SNuclile* :RQ* Station 37 corn collected 8/27/2013

-Nuclide RQ --Activity .

K-40 + 4.75E+03 +

Error' 6.50E+02 MDA 3.90E+02 K-40 MN-54

- Activity.

+ 2.16E+03

-7.97E-01

+

+

Error 2.55E+02 9.90E+00 MDA ---

1.93E+02 1.62E+01 I

MN-54 -3.40E+00 + 1.85E+01 2.95E+01 CO-58 FE-59 CO-60 1.99E+00 +

0.00E+00 +

1.33E+00 +

1.54E+01 1.29E+01 1.93E+O1 2.47E+01 2.12E+01 3.14E+01 CO-58 FE-59 CO-60 1.52E+00 5.43E+00 1.1OE+00

+

+

+

8.67E+00 2.12E+01 1.12E+01 1.40E+01 3.36E+01 1.91E+01 I

ZN-65 0.OOE+00 + 9.27E+01 1.52E+"02 ZN-65 1.85E+00 + 1.98E+01 3.21 E+01 ZRNB-95 1-131

-3.78E+00 + 2.95E+01 1.79E-01 + 1.58E+01 4.75E+01 2.59E+01 ZRNB-95 1-131

-2.88E+00 4.78E+00

+

+

1.59E+01 8.79E+00 2.57E+01 1.38E+01 I

CS-134 1.41 E+00 + 1.67E+01 2.71E+01 CS-134 -1.30E+00 + 6.93E+00 1.11E+01 CS-137 BALA140 7.36E+00 +

-6.63E+00 + 2.29E+01 1.73E+01 2.62E+01 3.53E+01 CS-137 BALA140 1.59E-01

-1.22E+00

+

+

8.83E+00 1.02E+01 S1.45E+01 1.64E+01 I Station 37 Corn collected 7/2/2013 Station 37 Broad Leaf Vegtable collected 9/17/2013 I

Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 MN-54 CO-58

+ 2.32E+03 + 2.93E+02

-2.83E+00 +

3.48E+00 + 8.81 E+00 1.12E+01 2.47E+02 1.79E+01 1.38E+01 K-40 MN-54 CO-58

+ 2.65E+03

-1.65E+00 4.73E+00

+

+

+

4.08E+02 1.36E+01 1.29E+01 3.71 E+02 2.20E+01 2.02E+01 I

FE-59 CO-60 ZN-65 4.59E-01 + 2.51E+01 4.54E-01 +

-6.18E+00 + 2.39E+01 1.16E+01 4.11E+01 2.00E+01 3.83E+01 FE-59 CO-60 ZN-65

-3.30E+00 2.69E+00

-1.52E+00

+

+

+

3.10E+01 1.75E+01 2.57E+01 5.01 E+01 3.OOE+01 4.18E+01 I

ZRNB-95 2.57E+00 + 1.74E+01 2.81E+01 ZRNB-95 5.04E-01 + 2.47E+01 4.06E+01 1-131 CS-1 34 3.98E-01 +

-5.15E+00 +

9.87E+00 1.11 E+01 1.62E+01 1.76E+01 1-131 CS-1 34 0.00E+00

-7.85E+00

+

+

1.89E+01 1.78E+01 3.11E+01 2.83E+01 I CS-1 37 -1.35E+00 + 1.09E+-01 1.77E+01 CS-137 -2.38E-01 + 1.65E+01 2.71 E+01 BALA140 -4.91 E+00 + 1.38E+01 2.16E+01 BALA140 -6.62E-02 + 1.88E+01 3.10E+01 I

Station 37 Broad Leaf Vegtable collected Nuclide RQ Activity Error 7/12/2013 MDA - Nuclide RQ Activity

+

Station 9c Corn collected Error 8/9/2013 MDA I K-40 + 3.96E+03 + 4.92E+02 2.73E+02 K-40 2.37E+03 + 2.90E+02 2.56E+02 MN-54 CO-58 FE-59

-2.32E+00 +

3.93E+00 +

1.16E+01 +

1.47E+01 1.18E+01 3.68E+01 2.37E+01 1.83E+01 5.69E+01 MN-54 CO-58 FE-59 5.03E-02 + 9.43E+00 8.04E-01 + 8.34E+00 4.04E+00 + 2.50E+01 1.55E+01 1.36E+01 4.03E+01 I

CO-60 -4.66E+00 + 1.74E+01 2.75E+01 CO-60 -1.59E-01 + 1.10E+01 1.81 E+01 ZN-65 ZRNB-95

-3.11E+00 +

-3.OOE+00 +

2.94E+01 1.88E+01 4.74E+01 3.OOE+01 ZN-65 ZRNB-95 3.28E-01 +

4.52E+00 +

2.57E+01 1.61E+01 4.22E+01 2.58E+01 I

1-131 0.OOE+00 + 1.34E+01 2.20E+01 1-131 7.70E+00 + 1.06E+01 1.65E+01 CS-134 CS-137 BALA140 3.17E+00 +

5.86E+00 +

9.68E-03 +

1.23E+01 1.26E+01 1.25E+01 1.95E+01 1.91E+01 2.05E+01 CS-134 CS-137 BALA140

-4.90E+00 +

-2.05E+00 +

5.09E-01 +

1.03E+01 1.05E+01 1.23E+01 1.64E+01 1.70E+01 2.OOE+01 I

U i

RQ = Results Qualifier. If blank, result is less than detection limit. If '+", result is above detection limit. Page 2 of 2 I

TABLE A - 17.2 GAMMA SPECTROMETRYRESULTS OF VEGETABLES-

SUMMARY

. Results in pCi/ kilogram (wet)

Average Activity Activity Average Number of Number of Nuclide Activity Low High' MDA Samples Positive IDs BALA1 40 Ind -3.51 E-01 -6.63E+00 7.45E+00 2.70E+01 1.1 BALA140 Cntl 5.09E-01 5.09E-01 5.09E-01 2.OOE+01 11 CO-58 Ind 2.43E+00 -7.03E-01 5.77E+00 1.87E+01 CO-58 CntI 8.04E-01 8.04E-01 8.64E-01 1.36E+01 11 1

CO-60 Ind 5.72E-01 -6.58E+00 1.20E+01 2.60E+01 CO-60 CntI -1.59E-01 -1.59E-01 -1.59E-01 1.81E+01 11 1

CS-134 Ind -4.74E-01 -7.85E+00 7.15E+00 2.20E+01 CS-134 Cnti -4.90E+00 -4.90E+00 -4.90E+00 1.64E+01 11 CS- 137 Ind 1.59E+00 -4.68E+00 8.19E+00 2.22E+01 11 CS-137 CntI -2.05E+00 -2.05E+00 -2.05E+00 1.70E+01 11 FE-59 Ind . -2.63E-01 -1.44E+01 1.16E+01 4.91E+01 11 FE-59 CntI 4.04E+00 4.04E+00 4.04E+00 4.03E+01 11 1-131 Ind 6.93E-01 -8.94E+00 2.35E+01 2.31E+01 I1*

1-131 CntI 7.70E+00 7.70E+00 7.70E+00 1.65E+01 11 K-40 Ind 3.27E+03 1.46E+03 5.39E+03 3.11 E+02 11 K-40 Ontl 2.37E+03 2.37E+03 2.37E+03 2.56E+02 1"

MN-54 Ind -1.47E+00 -8.64E+00 5.22E+00 2.16E+01 11 MN-54 CntI 5.03E-02 5.03E-02 5.03E-02 1.55E+01 11 ZN-65 Ind -5.84E-01 -6.18E+00 1.33E+01 5.57E+01 11 ZN-65 CntI 3.28E-01 3.28E-01 3.28E-01 4.22E+01 11 ZRNB-95 Ind -9.54E-01 -4.34E+00 6.82E+00, 3.65E+01 0 ZRNB-95 Cntl 4.52E+00 4.52E+00 4.52E+00 2.58E+01 0 Ind = Indicator Stations Cntl = Control Stations Page 1 of 1

I TABLE B-1.11 I

2013 QUARTERLY SPECIAL INTEREST TLD-RESULTS Results in milli-Roentgen (mR) per Standard Quarter Quarterly I

Station ID 1st Quarter 2nd Quarter 58 21.4 18.6 3rd Quarter. 4th Quarter 21.7 20.4 Sum.

82.1 I

87 32.3 23.7 28.9 28.4 113.4 88 89 24.3 24.9 20.9 22.8 26.3 27.6 25.5 27.0 96.9 102.4 I

90 18.8 17.5 19.6 19.6 75.4 119B 119C 21.5 21.6 20.2 20.5 22.5 23.5 23.3 22.7 8725 88.3 I

120 (East) 21.3 21.0 23.3 23.7 89.3 121 122 64.4 33.4 44.9 32.3.

71.4 35.7 68.7 35.6 249.5 137.1 I 123 105.7 103.9 110.9 111.1 431.6 124 125 126 126.0 92.4 94.4 121.3 91.2 90.8 130.9 96.3 97.6 120.5 93.0 94.0 498.7 373.0 376.8 I

127 128 129 73.2 114.9 93.1 67.9 115.4 88.0 73.9 118.7 92.1 73.4 122.4 93.6 288.5 471.4 366.8 I

136A 137.2 130.0 133.3 129.7 530.3

.137A 138A 148.0 118.7 142.1 113.8 147.3 121.2 148.3 118.4 585.7 472.1 i

150 (Site 1) 18.1 17.7 18.6 19.5 73.9 151 (Site 4) 19.6 17.3 19.7-. 19.6 76.1 I

TABLE B-1.2 2013 QUARTERLY SPECIAL INTEREST TLD RESULTS-

SUMMARY

I Results in milli-Roentgen (mR) per Standard Quarter

. Location Average Activity Activity Low Activity High Number of Samples I

ISFSI Quarterly Ind 109.9 67.9 148.3 40 I SITE 1 & 4 Quarterly Ind 18.8 17.3 19.7 8 Quarterly Control TLDs 20.5 18.9 21.7 4 I

Ind = Indicator Station Cntl = Control Station I

Stations 123 through 138A are locationed on the middle ISFSI fence.

Stations 58 and 87 to 90 were established in 2009 to monitor exposure from remediation work at the DOE 618-11 burial site.

Station 121 results high due to location being near transformer yard. Staion 122 results influenced by ISFSI.  !

Quarterly Control TLD location is ST-9. See Table A-1.1 I

Page 1 of 1 I

Table B-2.1 GAMMA SPECTROMETRY RESULTS OF STORM DRAIN WATER STATION i01 Results in pCi/lite r, corrected for decay during collection period Location 101 collected 2/5/2013 Location 101 collected 2/28/2013 i Nuclide- RQ -Actilty. Error. MDA rNu-cli RQ 11e Activity Error MDA -

K-40 -1.35E+01 + 3.35E+01 4.58E+01 K-40 -4.23E+01 + 8.27E+01 5.74E+01 CR-51 -1.09E+00 + 1.94E+01 3.18E+01 CR-51 3.98E+00 + 2.10E+01 3.41E+01 MN-54 3.13E-01 + 1.75E+00 2.83E+00 MN-54 -1.33E-01 + 2.25E+00 3.68E+00 CO-58 -6.17E-01 + 2.OOE+00 3.19E--00 CO-58 O.OOE+00 + 1.89E+00 3.11E+00 FE-59 7.84E-02 + 5.1OE+00 8.37E+00 FE-59 1.97E+00 + 5.29E+00 8.22E+00 CO-60 -1.27E+00 + 4.65E+01 3.59E+00 CO-60 1.79E+00 + 2.22E+00 3.31 E+00 ZN-65 3.38E+00 + 4.41 E+00 6.71 E+00 ZN-65 -3.71E-01 + 4.60E+00 7.50E+00 ZRNB-95 -7.11 E-02 + 3.17E+00 5.20E+00 ZRNB-95 -2.06E+00 + 4.44E+00 7.01 E+00 1-131 1.84E+00 + 6.22E+00 1.OOE+01 1-131 -2.22E+00 + 6.30E+00 1.01E+01 CS-134 -1.75E-01 + 1.60E+00 2.61 E+00 CS-134 -1.52E-01 + 3.39E+00 5.57E+00 CS-137 8.26E-01 + 1.57E+00 2.43E+00 CS-137 -5.32E-01 + 2.29E+00 3.70E+00 BALA140 -6.32E-01 + 5.28E+00 8.55E+00 BALA1 40 5.42E-01 + 4.64E+00 7.50E+00 BI-214 2.92E+00 + 4.47E+00 8.09E+00 BI-214 2.03E+00 + 4.67E+00 8.63E+00 Location 101 collected 4/2/2013 Location 101 col!ected 4/30/2013 Nuclide RQ Activity Error MDA i Nuclide RQ Activity Error MDA K-40 -3.01 E+01 + 6.OOE+01 5.85E+01 K-40 -1.82E+01 + 4.12E+01 5.59E+01 CR-51 -1.50E+00 + 2.50E+01 4.10E+01 CR-51 -9.22E+00 + 2.52E+01 4.06E+01 MN-54 6.91 E-01 + 1.91E+00 3.01 E+00 MN-54 5.22E-01 + 1.93E+00 3.09E+00 CO-58 1.22E+00 + 2.24E+00 3.48E+00 CO-58 -3.41E-02 + 1.70E+00 2.78E+00 FE-59 -9.63E-01 + 6.31 E+00 1.02E+01 FE-59 -1.30E+00 + 5.93E+00 9.47E+00 CO-60 2.05E-01 + 2.OOE+00 3.24E+00 CO-60 -3.49E-01 + 1.51 E+00 2.39E+00 ZN-65 -6.64E-01 + 4.44E+00 7.18E+00 ZN-65 1.18E+00 + 4.22E+00 6.72E+00 ZRNB-95 1.14E+00 + 3.39E+00 5.35E+00 ZRNB-95 2.80E+00 + 3.58E+00 5.38E+00 1-131 4.05E+00 + 6.11E+00 9.58E+00 1-131 1.47E+00 + 5.07E+00 8.15E+00 CS-134 -8.36E-01 + 2.50E+00 4.02E+00 CS-1 34 -8.91E-01 + 2.1IE+00 3.34E+00 CS-137 1.64E+00 + 1.50E+00 2.1OE+00 CS-137 -6.05E-01 + 2.19E+00 3.51 E+00 BALA140 -1.12E+00 + 4.74E+00 7.51 E+00 BALA140 -2.23E702 + 4.23E+00 6.95E+00 BI-214 + 1.34E+01 + 5.55E+00 8:86E+00 BI-214 + 9.39E+00 + 5.13E+00 8.57E+00 Location 101 collected 6/3/2013 Location 101 collected 7/1/2013 Nuclide MDA Nuclide RQ Activity Error MDA RQ Activity Error K-40 -9.32E+00 + 3.10E+01 5.32E+01 K-40 -9.87E+00 + 3.33E+01 5.52E+01 CR-51 5.68E+00 + 2.02E+01 3.25E+01 CR-51 1.32E+00 + 2.13E+01 3.48E+01 MN-54 1.45E+00 + 2.04E+00 3.12E+00 MN-54 7.25E-02 + 2.12E+00 3.47E+00 CO-58 9.32E-02 + 1.63E+00 2.65E+00 CO-58 -2.21 E-02 + 2.33E+.00 3.83E+00 FE-59 -7.03E-01 + 7.03E+00 1.14E+01 FE-59 1.34E+00 + 4.24E+00 6.57E+00 CO-60 -1.94E-01 + 2.05E.+00 3.33E+00 CO-60 0.OOE+00 + 2.33E+00 3.84E+00 ZN-65 1.56E+00 + 4.15E+00 6.51 E+00 ZN-65 -1.76E+00 + 4.48E+00 7.05E+00 ZRNB-95 7.98E-02 + 3.93E+00 6.44E+00 ZRNB-95 -8.28E-01 + 3.22E+00 5.14E+00 1-131 3.02E+00 + 6.51 E+00 1.04E+01 1-131 1.04E-01 + 5.29E+00 8.67E+00 CS-134 -1.42E-01 + 2.50E+00 4.09E+00 CS-1 34 5.24E-02 + 2.15E+00 3.53E+00 CS-137 -4.84E-01 + 2.31 E+00 3.73E+00 CS-1 37 1.46E+00 + 2.28E+00 3.55E+00 BALA 140 1.64E-02 + 4.81 E+00 7.90E+00 BALA140 -2.99E-01 + 4.56E+00 7.43E+00 BI-214 3.91 E+00 + 5.26E+00 9.33E+00 BI-214 5.72E+00 + 5.OOE+00 8.75E+00 RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit. Page 1 of 2

I Table B-2.1 GAMMA SPECTROMETRY RESULTS OF STORM DRAIN WATER I

STATION 101 Results in pCilliter, corrected for decay during collection period I

Location 101 collected 7/31/2013 Location 101 collected 9/3/2013 SNuclide K-40 CR-51 RQ Activity

-1.96E+01 + 4.27E+01

-7.14E+00 + 2.65E+01 Error MDA 5.60E+01 4.29E+01 I Nuclide K-40 CR-51 RQ Activity

-7.61 E+00 1.71E+01

+

+

Error 2.89E+01 2.44E+01 MDA 4.85E+01 3.84E+01 I

-1.09E-01 + 2.19E+00 MN-54 CO-58 FE-59

-4.27E-02 + .1.62EE+00

-3.70E-01 + 6.38E+00 3.59E+00 2.66E+06:'

1.04E+01 MN-54 CO-58 FE-59

-1.60E-03

-6.89E-01 0.OOE+00

+

+

+

2.12E+00 2.34E+00 2.98E+00 3.47E+00 3.74E+00 4.90E+00 I

CO-60 4.78E-02 + 1.95E+00 3.20E+00 CO-60 -2.82E-01 + 2.88E+00 3.34E+00 ZN-65 ZRNB-95 1-131 1.64E+00 + 3.95E+00

-7.56E-02 + 4.48E+00 8.80E-01 + 7.96E+00 6.15E+00 7.36E+00 1.30E+01 ZN-65 ZRNB-95 1-131 1.81 E-02

-1.87E+00

-5.66E-01

+

+

+

3.31 E+00 4.45E+00 4.58E+00 5.43E+00 7.03E+00 7.44E+00 I

CS-134 -1.82E+00 + 2.57E+00 4.04E+00 CS-134 -2.88E-02 + 2.02E+00 3.32E+00 CS-137 BALA140

-8.59E-01 + 2.53E+00

-1.41E+00 + 6.69E+00 4.05E+00 1.07E+01 CS-1 37 BALA 40

-3.47E-01

-8.12E-01

+

+

2.OOE+00 4.98E+00 3.23E+00 7.97E+00 I

BI-214 5.45E+00 + 5.12E+00 8.97E+00 BI-214 5.88E-01 + 4.84E+00 9.04E+00 Location 101 collected 10/1/2013 Location 101 collected 11/1/2013 I

Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 CR-51

-3.25E+01

-1.12E-01

+ 7.92E+01

+ 2.31 E+01 5.31 E+01 3.79E+01 K-40 CR-51

-3.22E+01 +

-3.63E+00 +

6.33E+01 2.82E+01 5.84E+01 4.60E+01 I

MN-54 6.30E-01 + 1.97E+00 3.13E+00 MN-54 2.65E-01 + 1.88E+00 3.04E+00 CO-58 FE-59 CO-60

-3.31E-01

-4.19E-01

-4.91E-01

+ 1.85E+00

+ 6.88E+00

+ 4.31 E+00 2.98E+00 1.12E+01 3.50E+00 CO-58 FE-59 CO-60

-2.62E-01 +

3.64E+00 +

-3.08E-01 +

2.15E+00 6.34E+00 2.13E+00 3.48E+00 9.62E+00 3.45E+00 I

ZN-65 7.18E-02 + 5.07E+00 8.32E+00 ZN-65 -1.98E+00 + 5.25E+00 8.32E+00 ZRNB-95 1-131 CS-134 0.OOE+00

-1.64E+00

-7.66E-01

+ 4.74E+00

+ 8.73E+00

+ 2.27E+00 7.80E+00 1.42E+01 3.64E+00 ZRNB-95 1-131 CS-1 34

-1.13E-01 +

2.09E+00 +

-1.27E-02 +

4.12E+00 9.48E+00 2.53E+00 6.75E+00 1.54E+01 4.16E+00 I

CS-137 BALA140 BI-214

-9.25E-01

.- 6.54E-01 1.23E+00

+ 2.41 E+00

+ 6.25E+00

+ 5.04E+00 3.84E+00 1.01E+01 9.26E+00 CS-1 37 BALA140 BI-214

-5.89E-01 +

4.21 E-02 +

2.05E+00 +

2.63E+00 6.39E+00 5.36E+00 4.25E+00 1.05E+01 9.66E+00 I

Nuclide RQ Location 101 collected Activity Error 12/1/2013 MDA Nuclide RQ Location 101 collected Activity Error 12/31/2013 MDA I

K-40 CR-51 MN-54

-4.19E+01 1.18E+00

-5.O0E-01

+

+

+

8.92E+01 2.96E+01 1.86E+00 6.OOE+01 4.86E+01 2.97E+00 K-40 CR-51 MN-54

-2.42E+01 + 3.30E+01

-3.82E-01 +

6 1.58E-01 + !.50E+01

.00E+00 5.61 E+01 4.12E+01 3.22E+00 I

CO-58 2.64E-01 + 2.21 E+00 3.59E+00 CO-58 3.54E-01 + '.03E+00 3.27E+00 FE-59 CO-60 ZN-65

-2.26E+00

-3.51E-01

-8.72E-01

+

+

+

6.54E+00 2.21 E+00 4.39E+00 1.03E+01 3.57E+00 7.07E+00 FE-59 CO-60 ZN-65 9.11E-01 + k.41E+00

-4.80E-01 + ,.54E+00 2.18E-02 + 2,.08E+00 1.03E+01 3.71E+00 6.71E+00 I

ZRNB-95 -1.40E+00 + 4.47E+00 7.14E+00 ZRNB-95 -1.39E+00 + 1*.59E+00 7.33E+00 1-131 CS-134 CS-137

-1.79E-01

-1.46E+00 8.14E-01

+

+

+

6.66E+00 2.35E+00 1.09E+01 3.70E+00 1-131 CS-134

-2.73E+00 + 4i

-2.39E-02 +

l.62E+00

.22E+00 1.55E+01 3.65E+00 I

2.05E+00 3.25E+00 CS-137 3.72E-01 + .80E+00 2.89E+00 BALA140 BI-214

-1.50E+00 7.62E+00

+

+

4.81 E+00 5.17E+00 7.53E+00 8.82E+00 BALA140 BI-214

-6.59E-02 + *.97E+00 5.34E+00 + .15E+00 8.15E+00 9.02E+00 I I

RQ = Results Qualifier. If blank, result is less than detection limit, If "+', result is above detection limit. Page 2 of 2 I

TABLE B-2.2 GAMMA SPECTROMETRY RESULTS OF STORM DRAIN WATER -

SUMMARY

STATION 101 Results in pCi/liter, corrected for decay during collection period Number of Average Activity Activity Average Number of Positive Nuclide Activity Low High, MDA Samples IDs K-40 -2.35E+01 -4.23E+01 -7.61E+00 5.48E+01.. 12 0 CR-51 5.65E-01 -9.22E+00 1.71E+01*, 3.92E+01 12 0 MN-54 2.35E-01 -5.00E-01 1.45E+00 3.22E+00 12 0 CO-58 -5.83E-03 -6.89E-01 1.22E+00 3.23E+00 12 0 FE-59 1.60E-01 -2.26E+00 3.64E+00 9.25E+00 12 0 CO-60 -1.40E-01 -1.27E+00 1.79E+00 3.37E+00 12 0 ZN-65 1.86E-01 -1.98E+00 3.38E+00 6.97E+00 12 0 ZRNB-95 -3.09E-01 -2.06E+00 2.80E+00 6.54E+00 12 0 1-131 5.11E-01 -2.73E+00 4.05E+00 1.11E+01 12 0 CS-134 -5.21E-01 -1.82E+00 5.24E-02 3.81E+00 12 0 CS-1 37 6.38E-02 -9.25E-01 1.64E+00 3.38E+00 12 0 BALA140 -4.92E-01 -1.50E+00 5.42E-01 8.40E+00 12 0 BI-214 4.97E+00 5.88E-01 1.34E+01 8.92E+00 12 2 Page 1 of 1

I TABLE B-3.1. -, I- -

GROSS BETA IN STORM D.RIN. WATER.:

Results in pCi per liter I

Location ST-1i01 Collection Period 01/03/13:. 02/05/13 RQ Activity ,.,

.6.70E-01 Error

. 7.92E-01 MDA 2.63E+00 I

02/05/13 02/28/13 7.88E *8.82E-01 2.95E+00 02/28/13 04/02/13 04/30/13 04/02/13 04/30/13 06/03/13

.1.12S +0 +

1.75E+00 +

..7.20E-01 +

8.01 E-01 8.46E-01 7.88E-01 2.55E+00 2.70E+00 2.65E+00 I

06/03/1.3 07/01/13 1.99E+00 '+ 8.29E-01 2.44E+00 07/01/13 07/31/13 01/31/13 09/03Mi3

-3.07E '7.29E-01 3.23E-01 + 7.58E-01 2.49E+00 2.67E+00 I

09/03/13 10/01/13, 1.81E+00 + 7.43E-01 2.29E+00 10/01/13 11/01/13 12/01/13 11/01/13 12/01/13 12/31/13 1.36E+00 +

8.62E-01 +

1.83E+00 +

7.52E-01 7.10E-01 7.46E-01 2240E+00 2.36E+00 2.30E+00 I

TABLE B-3.2 GROSS BETA IN STORM DRAIN WATER -

SUMMARY

Results in pCi: Per liter.

Average, .

Activity Activity Low Activity High Number of Samp!es Number of Positive IDs I

1.09E+00 -3.07E-01 1,99E+00 12 . 0- I TABLE B-4.1 TRITIUM IN STORM DRAIN WATER I

Resutts in pC- per liter .

Location ST-101 Collection Period 01/03/13 - 02/05/13 RQ

+

Activity 4.95E+03 +

Error 1.89E+02 I

02/05/13.- 02/28/13 02/28/13. - 04?02/13 04/02/13 - 04/30/13

.+

+

+

i11E+03 T.

1.30E+03

.3.42E+02

+

+

+

1.24E+02 1.26E+02 1.04E+02 I

04/30/13.- 06/03/13 1.78E+02 +. 9.57E+01 06/03/..13 - 07101/13.

07/01/13 - 07/31113 -

07/31/13 - 09/03/13:-

+ 3.44E+02 1.28E+02 2.43E+02

+

+

+

9.36E+01 9.97E+01 9.62E+01 I

09/03/13 - 10/01/13 4.31E+02 + 1.04E+02 I

+

10/01/13 - 11/01/13 . .63E+02 + 9.85E+01 11/01/13 - 12/01/13 + 9.53E+02 + 1.21 E+02 12/01/13 - 12/31/13 + 1.69E+03 + 1.39E+02 TABLE B-4.2 I

TRITIUM IN STORM DRAIN WATER -

SUMMARY

Average Activity Results in pCi per liter Activity Number of Number of I

Activity Low.' High Samples Positive IDs 9.87E+02 1.28E+02 "- 4.95E+03 . ' 12 8 I

I RQ = Results Qualifier. Ifblank, result is less than detection limit. If "+", result is above detection limit. Page 1 of 1 1

TABLE B-5.1 GROSS ALPHA IN-SANITARY:WASTE TREATMENT WATER Results in pCi pe&liter

.,ST*102A. ST 102B Collection Period L RO ' Activity Error MDA IRO L --

Activity Error MDA 01/03/13 02/05/13 -2.95E-01 + 8.16E-01 3.39E+00 -3.41 E-01 + 9.45E-01 3.93E+00 02/05/13 02/28/13 7.35E-01 .+ "8.49E-01 3.31 E+00 1.42E+00 + 9.65E-01 3.21 E+00 02/28/13 04/02/13 -1.56E+00 1.12E+00 3.88E+00 -9.29E-01 + 1.99E+00 7.78E+00 04/02/13 04/30/13 -1.56E+00 + 1.46E+00 5.21 E+00 -2.21 E+00 + 2.08E+00 7.40E+00 04/30/13 06/03/13 1.04E+00 + 1.04E+00 3.80E+00 3.71 E+00 + 1.22E+00 3.83E+00 06/03/13 07/01/13 1.53E+00 + 1.1.8E+00 4.1OE+00 0.OOE+00 + 1.94E+00 8.20E+00 07/01/13 07/31/13 4.47E-01 + 1.24E+00 5.14E+00 -8.30E-01 + 8.61 E-01 3.18E+00 07/31/13 09/03/13 -1.09E+00 + 1.13E+00 4.19E+00 -1.06E+00 + 1.57E+00 6.11 E+00 09/03/13 10/01/13 -1.77E-1 6 + 7.76E-01 3.83E+00 1.19E+00 + 1.OOE+00 3.58E+00 10/01/13 11/01/13 2.28E+00 + 1.56E+00 5.24E+00 5.63E-01 + 1.56E+00 6.48E+00 11/01/13 12/01/13 3.1OE+00 + 1.80E+00 5.87E+00 3.34E-01 + 1.80E+00 7.26E+00 12/01/13 12/31/13 -1.43E-01 + 1.52E+00 6.24E+00 -2.95E+00 + 2.32E+00 8.02E+00 TABLE B-5.2 GROSS ALPHA IN SANITARY WASTE TREATMENT WATER -

SUMMARY

Results in pCi per liter Number Number of Average Activity Activity of .Positive.

Location Activity Low High Samples IDs ST 102A 3.74E-01 -1.56E+00 3.1OE+00 12 0 ST 102B -9.18E-02 -2.95E+00 3.71E+00 12 0

.. TABLE B-6.1 GROSS BETA IN SANITARY WASTE TREATMENT WATER Results in pCi per liter ST 102A ST 102B Collection Period RO Activity Error MDA RQ Activity Error MDA 01/03/13 02/05/13 + 4.95E+00 + 9.97E-01 2.68E+00 + 1.89E+01 + 1.52E+00 2.74E+00 02/05/13 02/28/13 + 6.78E+00 + 1.15E+00 2.99E-+00 + 1.78E+01 + 1.54E+00 2.98E+00 02/28/13 04/02/13 + 3.64E+00 + 9.18E-01 2.59E+00 + 2.23E+01 + 1.68E+00 2.85E+00 04/02/13 04/30/13 + 5.83E+00 + 1.08E+00 2.82E+00 + 2.19E+01 + 1.68E+00 2.95E+00 04/30/13 06/03/13 + 7.50E+00 + 1.13E+00 2.75E+00 + 2.81 E+01 + 1.93E+00 3.16E+00 06/03/13 07/01/13 + 6.05E+00 + 1.18E+00 3.03E+00 + 1.96E+01' + 1.79E+00 3.33E+00 07/01/13 07/31/13 + 1.40E+01 + 1.56E+00 3.26E+00 + 1.46E+01 + 1.41E+00 2.75E+00 07/31/13 09/03/13 + 1.41 E+01 + 1.38E+00 2.81 E+00 + 1.36E+01 + 1.41E+00 2.94E+00 09/03/13 10/01/13 + 1.57E+01 + 1.39E+00 2.45E+00 + 1.81 E+01 + 1.47E+00 2.43E+00 10/01/13 11/01/13 + 1.63E+01 + 1.44E+00 2.59E+00 + 1.95E+01 + 1.57E+00 2.66E+00 11/01/13 12/01/13 + 2.17E+01 + 1.60E+00 2.53E+00 + 1.97E+01 + 1.56E+00 2.60E+00 12/01/13 12/31/13 + 2.67E+01 + 1.74E+00 2.48E+00 + 2.19E+01 + 1.63E+00 2.56E+00 TABLE B-6.2 GROSS BETA IN SANITARY WASTE TREATMENT WATER -

SUMMARY

Results in pCi per liter Number Number of Average Activity Activity of Positive Location Activity Low High Samples IDs ST 102A 1.19E+01 3.64E+00 2.67E+01 12 12 ST 102B 1.97E+01 1.36E+01 2.81E+01 12 12 RQ = Results Qualifier. If blank, result is less than detection limit: If"+", result is above detection limit. Page 1 of 1

I Table 8-7.1 GAMMA SPECTROMETRY. RESULTS OF SANITARY WASTE TREATMENT WATER I

STATION 102A Results in pCi/liter, corrected for decay during collection period I

Location 102a collected 2/5/2013 Location 102a collected 2/28/2013 MDA Nuciide RQ Activity K-40 CR-51 1.34E+01 + 3.05E+01

-5.07E+00 + 3.05E+01 Error MDA 5.94E+01 4.98E+01 Nuc-ide K-40 CR-51 RQ Activity Error

  • -1.82E-01 + 2.82E+01

-1.14E+01 + 3.19E+01 5.73E+01 5.18E+01 I

MN-54 -5.35E-01 + 2.54E+00 4.13E+00 MN-54 -4.53E-02 + 2.04E+00 3.34E+00 CO-58 FE-59

-1.27E+00 + 2.84E+00 2.30E+00 + 6.19E+00 4.56E+00 9.87E+00 C0-58 FE-59

-2.58E-01 + 2.65E+00 2.41E+00 + 7.19E+00 4.33E+00 1.15E+01 I

CO-60 -4.90E-01 + 3.35E+00 4.18E+00 CO-60 -4.07E-01 + 3.4611+00 4.53E+00 ZN-65 ZRNB-95 1-131 9.59E-02 + 5.00E+00 8.96E-01 + 4.91E+00 7.87E-01 + 7.21E+00 8.21 E+00 8.OOE+00 1.18E+01 ZN-65 ZRNB-95 1-131

-2.56E+00 + 6.06E+00

. 2.60E+00 + 5.38E+00

.2.51E+00 + 8.50E+00 9.75E+00 8.65E+00 1.38E+01 I

CS-134 2.35E-01 + 2.70E+00 4.42E+00 CS-134 -1.70E+00 + 3.06E+00 4.94E+00 CS-137 BALA140 BI-214

-6.87E-01 + 2.77E+00 7.92E-01 + 4.70E+00 3.94E+00 + 6.49E+00 4.51 E+00 7.61 E+00 1.17E+01 CS-137 BALA140 BI-214 2.27E-01 + 2.83E+00 3.43E+00 + 5.4.7E+00 5.40E+00 + 6.83E+00 4.64E+00 8.53E+00 1.22E+01 I

Location 102a collected 4/2/2013 Location 102a collected 4/30/2013 I

Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 CR-51 MN-54

-1.04E+00

-8.73E-01 1.05E-01

+ 3.16E+01

+ 3.36E+01

+ 2.28E+00 6.40E+01 5.51 E+01 3.73E+00 K-40 CR-51 MN-54

-6.31E+00

-8.07E+00

-1.17E+00

+

+

+

3.19E+01 3.18E+01 2.61 E+00 6.OOE+01 5.18E+01 4.19E+00 I

CO-58 FE-59 CO-60

-6.23E-01 3.23E+00

-6.88E-01

+ 3.03E+00

+ 7.59E+00

+ 2.58E+00 4.93E+00 1.22E+01 4.17E+00 CO-58 FE-59 CO-60 1.81E+00 1.59E+00 1.69E+00

+

+

+

2.61 E+00 6.46E+00 2.67E+00 4.1.OE+00 1.04E+01 4.51 E+00 I

ZN-65 -5.77E+00 + 6.71 E+00 1.06E+01 ZN-65 1.33E+00 + 5.07E+00 8.18E+00 ZRNB-95 1-131 CS-1 34

-1.98E+00 1.79E+00

-3.19E+00

+ 6.30E+00

+ 7.21 E+00

+ 3;29E+00 1.02E+01 1.17E+01 5.25E+00 ZRNB-95 1-131 ,

CS-1 34 2.02E+0O"

-2.35E+00

-1.40E+00

+

+

+

5.39E+00 8.18E+00 3.02E+00 8.68E+00 1.33E+01 4.87E+00 I

CS-137 5.68E-01 + 2.73E+00 4.45E+00 CS-1 37 1.19E+00 + 2.70E+00 BALA140 B1-214 3.86E+00

+ 1.58E+01

+ 6.22E+00

+ 7.24E+00 9.80E+00 1.24E+01 BALA140 BI-214 5.07E+00 3.38E+00

+

+

4.90E+00 7.03E+00 4.34E+00 7.21 E+00 1.27E+01 I

Nuclide RQ Activity Location 102a collected Error 6/3/2013 MDA Nuclide RQ Location 102a collected Activity Error 7/1/2013 MDA I

K-40 -3.OOE+01 + 4.51 E+01 6.86E+01 K-40 -8.05E+00 + 3.80E+01 7.06E+01 CR-5i MN-54 CO-58

.1.14E+01 + 3.54E+01 1.11E-01 + 2.85E+00

-6.69E-01 + 3.15E+00 5.76E+01 4.67E+00 CR-51 MN-54

-5.99E+00 + 3.42E+01 2.37E-01 + 2.97E+00 5.60E+01 4.87E+00 I

5.13E+00 CO-58 6.85E-01 + 2.66E+00 4.30E+00 FE-59 CO-60 ZN-65 1.21E-01 + 6.19E+00 1.60E+00 + 2.66E+00 3.99E-01 + 8.38E+00 1.02E+01 4.20E+00 1.37E+01 FE-59 CO-60 ZN-65

-4.92E+00 + 6.80E+00 2.17E+00 + 2.60E+00

-2.44E+00 + 5.71 E+00 1.06E+01 4.05E+00 9.16E+00 I

ZRNB-95 -1.52E+00 + 5.77E+00 9.37E+00 ZRNB-95 2.77E+00 + 5.56E+00 8.93E+00 1-131 CS-1 34 CS-1 37 8.80E-01 + 9.84E+00

-4.05E+00 + 3.68E+00 2.52E+00 + 2.99E+00 1.61 E+01 5.85E+00 4.72E+00 1-131 CS-134 CS-i 37 7.96E-02 + 8.22E+00

-2.45E+00 + 3.67E+00 2.34E+00 + 3.12E+00 1.35E+01 5.91 E+00 4.96E+00 I

BALA 140 2.42E+00 + 5.69E+00 BI-214 3.57E+00 + 7.63E+00 9.04E+00 1.37E+01 BALA140 BI-214 3.06E-01 + 4.16E+00 6.47E+00 + 7.48E+00 6.79E+00 1.33E+01 I I

RQ = Results Qualifier. If blank, result is less than detection limit. If '+', result is above detection limit. Page 1 of 4 I

Table B-7.1 GAMMA SPECTROMETRY RESULTS OF SANITARY WASTE TREATMENT WATER STATION 102A Results in pCi/liter, corrected for decay during collection period Location 102a collected 7/31/2013 Location 102a collected 9/3/2013

-Nuclide RQ -Acivity -- Error Nuclide- RQ Activity. Error MDA K-40 6.12E+00 + 3.14E+01 6.23E+01 K-401 1.91E+01 + 3.23E+01 6.25E+01 CR-51 -1.27E+01 + 3.70E+01 6.02E+0i CR-51 1'.35E+01 + 3.45E+01 5.59E+01 MN-54 1.88E-01 + 2.62E+00 4.29E+00 MN-54 3.22E-01 + 2.84E+00 4.65E+00 CO-58 -2.03E-01 + 3.16E+00 5.17E+00 CO-58 -1.01E+00 + 3.05E+00 4.93E+00 FE-59 5.42E-01 + 6.62E+00 1.08E+01 FE-59 -1.04E+00 + 7.29E+00 1.19E+01 CO-60 -5.32E-01 + 3.97E+00 4.75E+00 CO-60 1.77E-01 + 2.81 E+00 4.88E+00 ZN-65 1.18E+00 + 5.73E+00 9.31 E+00 ZN-65 * -3.15E+00 + 5.81 E+00 9.23E+00 ZRNB-95 6.29E-01 + 5.79E+00 9.47E+00 ZRNB-95 1.86E-02 + 5.56E+00 9.13E+00 1-131 -8.35E+00 + 1.17E+01 1.87E+01 1-131

  • 2.26E+00 + 9.32E+00 1.52E+01 CS- 134 -7.13E-01 + 2.65E+00 4.30E+00 CS-1 34 4.35E-02 + 2.99E+00 4.91 E+00 CS-137 -4.35E-02 + 2.43E+00 4.OOE+00 CS-137 4.58E-01 + 2.65E+00 4.32E+00 BALA 140 -4.OOE-02 + 6.39E+00 1.05E+01 BALA140 -8.51E-01 + 6.21 E+00 1:01 E+01 BI-214 1.84E+00 + 7.04E+00 1.28E+01 BI-214 1.42E+00 + 6.87E+00 1.26E+01 Location 102a collected 10/1/2013 Location 102a collected 11/1/2013 Nuciide RQ Activity Error MDA Nuclide RQ Activity Error *MDA K-40 -2.41 E+01 + 3.85E+01 6.29E+01 K-40 1.39E+01 + 3.16E+01 6.20E+01 CR-51 1.59E+01 + 3.26E+01 5.28E+01 CR-51 i.25E+01 + 4.02E+01 6.53E+01 MN-54 -3.67E-01 + 2.49E+00 4.06E+00 MN-54 8.45E-01 + 2.52E+00 4.06E+00 CO-58 -8.78E-01 + 3.01E+00 4.88E+00 CO-58 1.43E+00 + 2.82E+00 4.48E+00 FE-59 3.21 E+00 + 6.75E+00 1.07E+01 FE-59 -1.09E+00 + 8.44E+00 1.37E-+01 CO-60 2.54E-01 + 2.40E+00 3.92E+00 CO-60 -2.55E+00 + 8.83E+01 5.93E+00 ZN-65 -3.64E+00 + 6.82E+00 1.10E+01 ZN-65 0.OOE+00 + 1.03E+01 1.69E+01 ZRNB-95 3.43E+00 + 5.23E+00 8.35E+00 ZRNB-95 '1.87E+00 + 5.97E+00 9.65E+00 1-131 6.84E-01 + 8.22E+00 1.35E+01 1-131 9.83E+00 + 1.62E+01 2.60E+01 CS- 134 -4.77E+00 + 3.59E+00 5.68E+00 CS-1 34 2.20E-01 + 2.94E+00 4.82E+00 CS-137 -6.67E-01 + 3.09E+00 5.03E+00 CS-1 37 -1.21E+00 + 3.27E+00 5.29E+00 BALA140 -2.31 E+00 + 6.33E+00 1.02E+01 BALA140 -1.09E+00 + 9.71 E+00 1.58E-+01 BI-214 8.39E+00 + 7.16E+00 1.26E+01 BI-214 5.61E+00 + 7.08E+00 1.26E+01 Location 1026 collected 12/1/2013 Location 102a collected 12/31/2013 Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 1.17E+01 + 3.14E+01 6.33E+01 K-40 + 6.22E+01 + 3.38E+01 6.12E+01 CR-51 -1.54E+00 + 3.29E+01 5.41 E+01 CR-51 -1.45E+00 + 3.69E+01 6.05E+01 MN-54 -1.24E+00 + 2.84E+00 4.58E+00 MN-54 5.54E-01 + 2.90E+00 4.72E+00 CO-58 -1.94E-01 + 2.27E+00 3.71 E+00 CO-58 4.84E-02 + 2.96E+00 4.87E+00 FE-59 1.97E+00 + 7.30E+00 1.18E+01 FE-59 -1.11E+00 + 7.38E+00 1.20E+01 CO-60 1.22E+00 + 2.51 E+00 4.01 E+00 CO-60 -2.04E+00 + 1.72E+01 4.71 E+00 ZN-65 -5.28E-01 + 5.97E+00 9.78E+00 ZN-65 -4.11E+00 + 6.60E+00 1.05E+01 ZRNB-95 3.13E+00 + 4.98E+00 7.'94E+00 ZRNB-95 9.16E-01 + 5.77E+00 9.41 E+00 1-131 -7.51E-01 + 1.02E+01 1.67E+01 1-131 3.37E+00 + 1.25E+01 2.03E+01 CS-1 34 -6.53E-01 + 1.86E+00 2.99E+00 CS-1 34 6.75E-02 + 2.85E+00 4.68E+00 CS-137 -1.22E+00 + 2.86E+00 4.62E+00 CS-1 37 -1.40E+00 + 2.85E+00 4.57E+00 BALA140 1.48E+00 + 5.55E+00 8.94E+00 BALA140 -2.08E+00 + 7.92E+00 1.27E+01 BI-214 + 1.29E+01 + 7'.23E+00 1.25E+01 B1-214 1.23E+01 + 7.15E+00 1.24E+01 RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit. Page 2 of 4

I Table B-7.1 GAMMA SPECTROMETRY'RESULTS OF SANITARY WASTE TREATMENT WATER I

STATION 102B Results in pCi/liter, corrected for decay during collection period I Location 102b collected 2/5/2013 Location 102b collected 2/28/2013 Nuclide RQ " Activity K-40 CR-51 1.03E+01 + 2.97E+01

,3.18E+00 + 3.54E+01 Error MDA' 5.85E+01 5.81 E+01 Nuctide RQ K-40 CR-51 Activity

-1.47E+01 2.87E-01

+

+

Error 3.90E+01 3.65E+01 )

MDA 6.82E+01 6.01 E+01 I

MN-54 CO-58.

FE-59

-1.14E-01 + 2.48E+00 2.02E+00 +* 2.43E+00 4.78E+00 + 6.79E+00 4.07E+00 3.79E+00 1.06E+01 MN-54 CO-58 FE-59

-3.03E-01 4.95E-01 4.46E-01

+

+

+

2.69E+00 )

3.26E+00 )

7.06E+00 )

4.39E+00 5.33E+00 1.16E+01 I

CO-60 8.95E-01 + 2.44E+00 4.20E+00 CO-60 0.OOE+00 + 2.85E+00 ) 4.68E+00 ZN-65 ZRNB-95 1-131 5.05E+00 + 4.97E+00 2.58E-02 + 3.93E+00

+ 5.31E+02 + 2.13E+01 7.63E+00 6.46E+00 1.54E+01 ZN-65 ZRNB-95 1-131 2.52E+00

-1.42E+00

  • 8.76E+00

+..

+.

+

4.69E+00 )

5.93E+00 1.04E+01 )

7.44E+00 9.66E+00 1.67E+01 I

CS-134 CS-137 BALA1 40 1.53E+00 + 2.66E+00

-6.24E-01 + 2.70E+00 7.79E-01 + 5.12E+00 4.28E+00 4.39E+00 8.29E+00 CS-1 34 CS-1 37 BALA140

-3.26E+00 1.25E-01

-8.33E-02

+.

+

+

3.46E+00 )

3.12E+00 )

5.67E+00 )

5.53E+00 5.13E+00 9.32E+00 I

BI-214 2.26E+00 + 6.50E+00 1.18E+01 BI-214 6.09E+00 + 7.59E+00 1.34E+01 Location 102b collected 4/2/2013 Location 102b collected 4/30/2013 I

Nuclide RQ Activity Error MDA Nuclide RQ Activity *Error MDA K-40 CR-51

-2.53E+01 + 4.02E+01

-1.70E+00 + 3.51 E+01 6.41 E+01 5.75E+01 K-40 CR-51 3.06E+00 +

2.11E+00 +

3.59E+01 3.43E+01 7.14E+01 5.62E+01 I

MN-54 2.44E-01 + 2.77E+00 4.53E+00 MN-54 3.78E+00 + 2.92E+00 4.50E+00 CO-58 FE-59 CO-60

-9.94E-01 + 3.14E+00

-3.25E+00 + 7.92E+00 1.37E+00 + 2.36E+00 5.09E+00 1.27E+01 3.74E+00 CO-58 FE-59 CO-60

-1.29E-01 +

1.69E+00 +

,1.59E+00 +

3.27E+00 7.09E+00 2.50E+00 5.36E+00 1.15E+01 3.94E+00 I

ZN-65 2.91 E+00 + 6.37E+00 1.03E+01 ZN-65 4.20E+00 + 4.78E+00 7.38E+00 ZRNB-95 1-131 CS-134 2.42E+00 + 5.40E+00 3.69E+00 + 1.06E+01

-1.38E+00 + 3.56E+00 8.70E+00 1.73E+01 5.78E+00 ZRNB-95 1-131 CS-1 34 3.57E-02 +

3.61 E+00 +

0.OOE+00 +

5.31 E+00 9.33E+00 5.12E+00 8.72E+00 1.51 E+01 8.42E+00 I

CS-1 37 BALA140 BI-214

-4.28E-01 + .3.06E+00

-5.17E-01 + 5.68E+00 4.70E+00 + 7.44E+00 5.01 E+00 9.27E+00 1.32E+01 CS-1 37 BALA140 BI-214

-5.17E-01 +

-6.05E-02 +

1.20E+01 +

3.08E+00 6.18E+00 7.99E+00 5.03E+00 1.02E+01 1.38E+01 I

Nuclide RQ Location 102b collected Activity Error 6/3/2013 MDA ý Nuclide RQ Location 102b collected Activity Error 7/1/2013 MDA I

K-40 CR-51 MN-54

-3.OOE+01 +

1.14E+01 +

1.11E-01 +

4.51 E+01 3.54E+01 2.85E+00 6.86E+01 5.76E+01 4.67E+00 K-40 CR-51 MN-54

-2.23E+01

-6.64E+00 0.OOE+00

+ 4.30E+01

+ 3.55E+01

+ 3.64E+00 6.98E+01 5.81E+01 5.98E+00 I

CO-58 -6.69E-01 + 3.15E+00 5.13E+00 CO-58 8.36E-03 + 2.97E+00 4.88E+00 FE-59 CO-60 ZN-65 1.21 E-01 +

1.60E+00 +

3.99E-01 +

6.19E+00 2.66E+00 8.38E+00 1.02E+01 4.20E+00 1.37E+01 FE-59 CO-60 ZN-65 1.05E+00 2.16E-01

-3.26E+00

+ 7.39E+00

+ 2.46E+00

+ 6.79E+00 1.20E+01 4.03E+00 1.09E+01 I

ZRNB-95 -1.52E+00 + 5.77E+00 9.37E+00 ZRNB-95 -1.56E+00 + 5.76E+00 9.35E+00 1-131 CS-134 8.80E-01 +

-4.05E+00 +

9.84E+00 3.68E+00 1.61 E+01 5.85E+00 1-131 CS-134

-2.55E+00 1.77E-01

+ 8.24E+00

+ 3.64E+00 1.34E+01 5.98E+00 I

CS-137 2.52E+00 + 2.99E+00 4.72E+00 CS-1 37 -7.44E-01 + 2.71 E+00 4.39E+00 BALA140 BI-214 2.42E+00 +

3.57E+00 +

5.69E+00 7.63E+00 9.04E+00 1.37E+01 BALA140 BI-214

-3.76E-01 1.68E+00

+ 4.50E+00

+ 7.59E+00 7.34E+00 1.37E+01 I I

RQ = Results Qualifier. If blank, result is less than detection limit. If '+', result is above detection limit. Page 3 of 4 I

Table B-7.1 GAMMA SPECTROMETRY RESULTS OF SANITARY WASTE TREATMENT WATER STATION 102B Results in pCi/liter, corrected for decay during collection period Location 1 02b collected 7/31/2013 Location 102b collected 9/3/2013 Nuclide RQ Activity Error -M-DA<- iNuclide RQ .Activity Error MDA K-40 -3.40E+01 + 4.63E+01 6.80E+01 K-40 -2.44E+01 + 4.40E+01 6.98E+01 CR-51 -4.25E-01 + 3.91 E+01 6.43E+01 CR-51 -1.85E+00 + 3.78E+01 6.21E+01 MN-54 -2.17E-01 + 3.06E+00 5.01 E+00 MN-54 2.94E-01 + 2.97E+00 4.86E+00 CO-58 -2.57E-01 + 3.40E+00 5.56E+00 CO-58 -5.73E-01 + 3.29E+00 5.36E+00 FE-59 1.05E+00 + 6.23E+00 1.01E+01 FE-59 3.83E-02 + 6.97E+00 1.14E+01 CO-60 -7.45E-02 + 2.48E+00 4.07E+00 CO-60 4.09E-02 + 2.54E+00 4.17E+00 ZN-65 1.23E-01 + 5.34E+00 8.77E+00 ZN-65 -3.41 E+00 + 6.72E+00 1.08E+01 ZRNB-95 0.00E+00 + 6.19E+00 1.02E+01 ZRNB-95 -9.60E-01 + 6.30E+00 1.03E+01 1-131 4.OOE+00 + 1.36E+01 2.22E+01 1-131 -2.44E+00 + 1.16E+01 1.89E+01 CS- 134 -4.00E+00 + 3.71 E+00 5.90E+00 CS-1 34 -2.16E+00 + 3.71 E+00 5.99E+00 CS-137 -8.17E-01 + 3.32E+00 5.40E+00 CS-1 37 -1.91E+00 + 3.37E+00 5.41 E+00 BALA 140 -1.17E+00 + 8.39E+00 1.37E+01 BALA140 -1.58E+00 + 6.81 E+00 1.10E+01 BI-214 7..64E+00 + 7.68E+00 1.36E+01 BI-214 8.06E+00 + 7.77E+00 1.37E+01

. Location 102b collected 10/1/2013 Location 102b collected 11/1/2013 Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 -2.67E+01 + 4.27E+01 6.76E+01 K-40 -3.48E+01 + 4.93E+01 7.02E+01 CR-51 -1.61 E+01 + 3.80E+01 6.17E+01 CR-51 -1.88E+01 + 4.97E+01 8.08E+01 MN-54 7.01E-01 + 3.03E+00 4.92E+00 MN-54 -3.97E-02 + 2.17E+00 3.57E+00 CO-58. -1.05E+00 + 3.22E+00 5.21 E+00 CO-58 1.68E+00 + 3.39E+00 5.43E+00 FE-59 -2.54E+00 + 7.72E+00 1.24E+01 FE-59 0.OOE+00 + 8.70E+00 1.43E+01 CO-60 2.79E-01 + 2.53E+00 4.13E+00 CO-60 -1.47E+00 + 2.96E+00 4.73E+00 ZN-65 -2.29E+00 + 6.06E+00 9.76E+00 ZN-65 -5.21E+00 + 7.11E+00 1.13E+01 ZRNB-95 -2.37E+00 + 5.86E+00 9.44E+00 ZRNB-95 * -3.47E+00 + .6.18E+00 9.88E+00 1-131 -2.52E+00 + 1.36E+01 2.22E+01 1-131 1.18E+01 + 2.45E+01 3.97E+01 CS-134 5.75E-01 + 3.14E+00 5.12E+00 CS-1 34 -4.49E-01 + 6.18E+00 1.01E+01 CS-137 -1.40E+00 + 3.27E+00 5.29E+00 CS-137 -6.18E-01 + 3.01 E+00 4.91 E+00 BALA140 -2.27E+00 + 7.71 E+00 1.24E+01 BALA140 3.36E+00 + 1.06E+01 1;69E+01 BI-214 5.32E+00 + 7.47E+00 1.34E+01 BI-214 + 3.18E+01 + 8.25E+00 1.33E+01 Location 102b collected 12/1/2013 Location 102b collected 12/31/2013 Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 7.30E+00 + 3.23E+01 6.35E+01 K-40 3.05E-01 + 3.54E+01 7.09E+01 CR-51 -9.06E+00 + 3.38E+01 5.51 E+01 CR-51 -1.12E+00 + 4.72E+01 7.76E+01 MN-54 -4.17E-01 + 2.78E+00 4.53E+00 MN-54 -1.80E+00 + 3.44E+00 5.53E+00 CO-58 6.48E-01 + 3.03E+00 4.92E+00 CO-58 5.17E-01 + 3.25E+00 5.31 E+00 FE-59 3.54E+00 + 7.03E+00 1.11E+01 FE-59 -9.68E-01 + 8.19E+00 1.34E+01 CO-60 4.27E-01 + 2.45E+00 4.29E+00 CO-60 6.92E-02 + 2.45E+00 4.02E+00 ZN-65 -1.55E+00 + 5.58E+00 9.OOE+00 ZN-65 0.OOE+00 + 1.01 E+01 1.66E+01 ZRNB-95 -3.60E-01 + 5'07E+00 8;31 E+00 ZRNB-95 -8.45E-01 + 5.91 E+00 9.65E+00 1-131 -4.97E-01 + 1.01E+01 1.65E+01 1-131 1.11E+01 + 1.81E+01 2.91 E+01 CS-134 -3.07E-01 + 2.98E+00 4.89E+00 CS-1.34 -2.95E+00 + 3.73E+00 5.98E+00 CS-137 0.OOE+00 + 3.19E+00 5.24E+00 CS-1 37 -5.48E-01 + 3.27E+00 5.34E+00 BALA 140 -1.01E+00 + 6.61 E+00 1.07E+01 BALA140 -2.83E-01 +. 8.31 E+00 1.36E+01 BI-214 3.80E+00 + 7.06E+00 1.27E+01 BI-214 4.50E+00 + 7.84E+00 1.40E+01 RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit. Page 4 of 4

U TABLE B-7.2 ,

GAMMA SPECTROMETRY RESULTS OF SANITARY WASTE TREATMENT WATER -

SUMMARY

I Results in pCi per liter, corrected for decay during collection period Average Activity Activity Average Number of Number of I

Location .Nuclide Activity Low High MDA Samples Positive IDs 102A K-40 4.74E+00 -3.OOE+01 6.22E+01 6.28E+01 12 1 I CR-51 5.24E-01 -1.27E+01 1.59E+01 5.59E+01 12 0 MN-54 CO-58

-8.34E-02

-9.47E-02

-1.24E+00

-1.27E+00 8.45E-01 4.27E+00 12 0 I 1.81 E+00 4.62E+00 12 0 FE-59 CO-60 6.02E-01 3.39E-02

-4.92E+00

-2.55E+00 3.23E+00 2.17E+00 1.13E+01 4.49E+00 12 12 0

0 I

ZN-65 ZRNB-95

-1.60E+00 6.43E-01

-5.77E+00

-3.64E+00 1.33E+00 3.13E+00 1.05E+01 9.20E+00 12 12 0

0 I

1-131 CS-1 34 8.95E-01

-1.53E+00

-8.35E+00

-4.77E+00 9.83E+00 2.35E-01 1.59E+01 4.88E+00 12 12 0

0 I

CS-1 37 BALA140 1.73E-01 9.14E-01

-1.40E+00

-2.31 E+00 2.52E+00 5.07E+00 4.62E+00 9.77E+00 12 12 0

0 I

BI-214 6.75E+00 1.42E+00 1.58E+01 1.26E+01 12 2 I

102B K-40 -1.59E+01 -3.48E+01 1.03E+01 6.76E+01 12 0 I CR-51 -3.23E+00 -1.88E+01 1.14E+01 6.24E+01 12 0 MN-54  :.1.87E.-01 -1.80E+00 .3.78E+00 4.71 E+00 12 0 I CO-58 1.42E-01 -1.05E+00 2.02E+00 5.11E+00 12 0 FE-59 4.95E-01 -3.25E+00 4.78E+00 1.18E+01 12 0 I CO-60 4.12E-01 -1.47E+00 1.60E+00 4.18E+00 12 0 ZN-65 ZRNB-95

-4.14E-02

-8.28E-01

-5.21 E+00

-3.47E+00 5.05E+00 2.42E+00 1.03E+01 9.19E+00 12 12 0

0 I

1-131 CS-1 34 4.73E+01

-1.36E+00

-2.55E+00

-4.05E+00 5.31 E+02 1.53E+00 2.02E+01 6.16E+00 12 12 0 1

I CS-1 37 BALA140

-4.14E-01

-6.60E-02

-1.91 E+00

-2.27E+00 2.52E+00 3.36E+00 5.02E+00 1.10E+01 12 12 0

0 I

BI-214 7.61 E+00 1.68E+00 3.18E+01 1.34E+01 12 1 I

I Page 1 of 1 I

TABLE B-8.1 TRITIUM IN SANITARY WASTE TREATMENT WATER Resultsin O~ijper liter, MDA for all samples is 300 pCi/I Location Description Collection Period RQ Activity Error 102A FFTF-Effluent 01/03/13ý - 02/05/13 1.61 E+03 + 1.29E+02

- 02/28/13 + +-

02/05/13 1.78E+03 1.38E+02

+ +

02/28/13 - 04/02/13 1.64E+03 1.34E+02

- 04/30/13 +

04/02/13 1.62E+03 1.34E+02

- 06/03/13 +

04/30/13 1.56E+03 1.32E+02

- 07/01/13 + 1.08E+02 06/03/13 8.70E+02

- 07/31/13 +

07/01/13 9.48E+02 + 1.21 E+02

- 09/03/13 + 1.26E+02 07/31/13 1.38E+03 ..I 10/01/13 +

09/03/13 - 1.37E+03 -+ 1.27E+02

- 11/01/13 +

10/01/13 1.45E+03 +I 1.31E+02

- 12/01/13 +

11/01/13 1.59E+03 +- 1.35E+02

+ 1.33E+02 12/01/13 12/31/13 1.43E+03 102B Monthly Headworks 01/03/13 02/05/13 + 4.42E+02 9.78E+01 02/05/13 02/28/13 + 3.58E+02 1.03E+02 02/28/13 04/02/13 + 5.16E+02 1.09E+02 04/02/13 04/30/13 + 3.58E+02 + 1.04E+02 04/30/13 06/03/13 2.84E+02 9.90E+01 06/03/13 07/01/13 + 3.13E+02 9.18E+01 07/01/13 07/31/13 1.52E+02 1.01E+02 07/31/13 09/03/13 1.48E+02 + 9.40E+01 09/03/13 10/01/13 2.03E+02 + 9.60E+01 10/01/13 11/01/13 1.60E+02 +- 9.64E+01 11/01/13 12/01/13 2.18E+02 +- 1.01E+02 12/01/13 12/31/13 1.82E+02 1.02E+02 TABLE B-8.2 TRITIUM IN SANITARY WASTE TREATMENT WATER -

SUMMARY

Results in pCi per liter Number of Location Average Activity Activity Number of Positive Description Activity Low High Samples IDs 102A FFTF Effluent 1.44E+03 8.70E+02 1.78E+03 12 12 102B Monthly Headworks 2.78E+02 1.48E+02 5.16E+02 12 5 RQ= results Qualifier. If blank, result is less than detection limit. If "+", result is above the detection limit. Page 1 of 1

TABLE B-10J, GAMMA SPECTROMETRY RESULTS OF GROUNDWATER MONITORING WELL SAMPLES 1

I Results in pCi per liter Nuclide Station MW-3 collected 1/28/2013 Station MW-9 collected 2/4/2013 MDA- 'i I

K-40 MN-54 RQ Activity

-2.60E+01

-3.03E+00 Error

+ 8.78E+01

+ 5.66E+00 MOA ...

1.12E+02 9.01 E+00 Nuciide , RQ- --Activity K-40 MN-54.

1.64E+01 +

  • -2.31 E-02 +

.-Error 4.62E+01 3.74E+00 8.36E+01 6.15E+00 I

CO-58 3.25E+00 _+ 3.31E+00 4.90E+00 CO-58 *-1.38E+00 + 3167E+00 5.79E+00 FE-59 CO-60 ZN-65 5.39E+00 1.71 E+00

-7.95E+00

+ 1.03E+01

+ 4.56E+00

+ 1.29E+01 1.60E+01 7.65E+00 2.03E+01 FE'-59 CO-60 ZN-65

-1.71 E+00 +

-1.26E+00 +

-4.51 E+00 +

9.12E+00 3.05E+01 1.05E+01 1.46E+01 5.40E+00 1.66E+01 I

ZRNB-95 1.44E+00 + 9.41 E+00 1.53E+01 ZRNB-95 -3.54E-01 + 5.44E+00 8.87E+00 1-131 CS-134 CS-137

-1.92E+00 2.31E-01

-2.32E+00

+ ,5.54E+00

+ 9.64E+00

+ 5.77E+00 8.97E+00 1.58E+01 9.26E+00 1-131 CS-134 CS-1 37

-7.01E-01 +

2.70E-01 +

-3.89E-01 +

4.01 E+00 1.OOE+00 3.30E+00 6.52E+00 1.88E+00 5,36E+00 I

BALA140 0.00E+00 + 1.23E+00 2.02E+00 BALA140 -1.11E+00 + 4.71 E+00 7.48E+00 BI-214 + 5.56E+02 Station MW-5 collected

+ 2.86E+01 2.02E+01 1/28/2013 BI-214 + 3.16E+02 +

Station MW-10 collected 2.19E+01 1.32E+01 2/4/2013 I

Nuclide RQ Activity Error *MDA MDA K-40 MN-54

-1.19E+01 +

1.07E+00 + 4.01E+00 6.37E+01 1.04E+02 6.45E+00 Nuclide RQ Activity K-40 MN-54

-2.88E+01 +

-1.97E-01 +

  • Error 7.57E+01 2.94E+00 7.56E+01 4.81 E+00 I

CO-58 -9.60E-03 + 3.73E+00 6.12E+00 CO-58 4.50E-01 + 2.38E+00 3,83E+00 FE-59 CO-60 ZN-65

-3.20E+00 + 1.OOE+01

-2.54E-61 + 4.33E+00

-2.15E+00 + 9.49E+00 1.59E+01 6.44E+00 1.53E+01 FE-59

.CO-60 ZN-65

.1.75E+00 +.

6.01E-01 +..

-5.07E+00 +

6.60E+00 2.85E+00 9.14E+00 1.04E+01 4.57E+00 1.44E+01 I

ZRNB-95 -5.29E-01 + 7.56E+00 1.24E+01 ZRNB-95 3.17E-01 + 4.71 E+00 7.69E+00 1-131 CS-134 CS-137 1.41 E+00 + 4.69E+00 6.05E-01 + 4;61 E+00

-1.05E-01 + 4.62E+00 7.59E+00 7.52E+00 7.59E+00 1-131 CS-134 CS-137

-8.47E-01 +

1.50E+00 +

1.67E-01 +

3.96E+00 2.50E+00 3.10E+00 6.43E+00 3.97E+00 5.07E+00 I

BALA140 -6.16E-02 + 4.70E+00 7.71 E+00 BALA140 7.92E-01 + 4.23E+00 6.79E+00 BI-214 + 1.79E+02 + 1.90E+.01 Station MW-6 collected 1.91E+01 1/28/2013 BI-214 + 9.55E+01 +

Station MW-11 collected 1.29E+01 1.25E+01 2/4/2013 I

Nuclide RQ Activity Error, *MDA; Nuclide RQ Activity Error MDA K-40 MN-54

-1.36E+00 + 5.20E+01 1.31E+00 + 3.60E÷00

-1.72E-02 + 3.77E+00 1.00E+02 5.72E-,00 K-40 MN-54

-5.98E+01 +

5.96E-01 +

6.18E+03 2.78E+00 8.09E+01 4.43E+00 I

CO-58 6.19E+00 CO-58 1.69E+00 + 2.96E+00 4.48E+00 FE-59

  • CO-60 ZN-65 0.OOE+00 + 9.11 E+00

-1.78E+00 + 1.96E+01

-8.67E-01 + 3.75E+01 1.50E+01 7.49E+00 7.24E+00 FE-59 CO-60 ZN-65

.-1.51E+00 +

-1.73E+00 +

1:20E+00 +

8.03E+00 2.13E+01 4.12E+00 1.28E+01 5.98E+00 6.46E+00 I

ZRNB-95 3.60E+00 + 6.71 E+00 1.05E+01 ZRNB-95 -3.74E-02 + 4.41 E+00 7.24E+00 1-131 CS-134 CS-137 1.83E-01 + 5.53E+00 2.65E+00 + 5.11 E÷00 2.20E+00 + 5.09E+00 9.07E+00 8.16E+00 8.13E+00 1-131 CS-134 CS-137 1.39E+00 +

-5.66E-03 +

-1.09E+00 +

4.20E+00 2.78E+00 3.44E+00 6.65E+00 4.57E+00 5.46E+00 I

BALA1440 2.19E+00 + 4.43E+00 6.82E+00. BALA140 -3.59E-02 + 4.86E+00 7.98E+00 BI-214 + 2.88E+02 + 2.13E+01 Station MW-8 collected 1.82E+01 2/4/2013 BI-214 + 6.14E+01 +

Station MW-12 collected 1.08E+01 1.20E+01 2/4/2013 I

Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 MN-54 CO-58

-4.01E+01 + 2.16E+02

-1.10E-01 + 3.77E+00 5.44E-02 + 3.20E+00 8.65E+01 6.18E+00 5.24E+00 K-40 MN-54 CO-58

-5.91E+01 +

-7.17E-01 +

-5.79E-01 +

1.32E+03 3.29E+00 3.18E+00 7.55E+01 5.27E+00 5.12E+00 I

FE-59 -6.84E-01 + 7.89E+00 1.28E+01 FE-59 -2.69E+00 +

CO-60 ZN-65 ZRNB-95

.-7.27E-01 + 1.60E+01

-1.02E+00 + 3.67E+01

-1.48E+00 + 6.21 E+00 7.38E+00 2.98E+00 9.96E+00 CO-60 ZN-65

-1.19E+00 +

-8.30E+00 +

9.07E+00 9.96E+01 1.09E+01 1.42E+01 5.72E+00 1.67E+01 I

ZRNB-95 0.OOE+00 + 6.55E+00 1.08E+01 1-131 CS-134 CS-137 5.86E-01 + 3.82E+00 0.OOE+00 + 1.02E+01 1..12E+00 + 4.31 E+00 6.22E+00 1.67E+01 6.92E+00 1-131 CS-134 CS-1 37

-1.05E+00 +

2.71E-01 +

-4.83E-01 +

4.94E+00 3.50E+00 2.85E+00 7.97E+00 5.72E+00 4.59E+00 I

BALA140 8.38E-01 + 4.91 E+00 7.88E+00 BALA140 2.69E-01 + 4.50E+00 7.30E+00 BI-214 + 3.30E+02 + 2.43E+01 1.72E+01 BI-214 + 6.71E+01 + 1.12E+01 1.21E+01 I

RQ = Results Qualifier. If blank, result is less than detection limit. If '+", result is above detection limit. Page 1 of 5 I

TABUE B-10.1 GAMMA SPECTROMETRYRE-$(LTS-OFG.ROUNDWATER MONITORING WELL SAMPLES-,

Results in-pCi per liter Station MW-13 collected 1/28/2013 Station MW-6 collect ed 4/24/2013 fINuclide RQ Activity tErrorfi MbA - 1 f-N-ucilide- -Rkq- -A ctivity ...... Error M-D-A1 K-40 1.06E+01 + 5.16E+01 9.98E+01 K-40 '-3.54E+01 + 1.03E+02 8.85E+01 MN-54 1.75E+00 + 4.08E+00 6.48E+00 MN-54 -1.20E+00 + 3.56E+00 5.59E+00 CO-58 -3.16E-01 + 5.01 E+00 8.20E+00 CO-58 1.23E-01 + 3.20E+00 5.22E+00 FE-59 3.08E+00 + 8.55E+00 1.34E+01 FE-59 1.25E-01 + 6.22E+00 1.02E+01 CO-60 -8.56E-01 + 7.70E+00 7.18E+00 CO-60 3.OOE-01 + 2.82E+00 4.53E+00 ZN-65 -1.02E+01 + 1.16E+01 1.79E+01 ZN-65 -1.38E+00 + 6.70E+00 1.06E+01 ZRNB-95 5.78E-01 + 7.68E+00 1.26E+01 ZRNB-95 -6.63E-01 + 6.22E+00 1.01E+01 1-131 1.09E+00 + 4.38E+00 7.08E+00 .1-131 0.00E+00 + 3.66E+00 6.03E+00 CS-134 -1.91E+00 + 4.53E+00 7.27E+00 CS-134 -7.14E-01 + 3.14E+00 5.03E+00 CS-137 0.OOE+00 + 5.56E+00 9.15E+00 CS-137 -9.42E-01 + 3.97E+00 6.35E+00 BALA140 2.46E+00 + 4.38E+00 6.64E+00. BALA140 0:00E+00 + 1.48E+00 2.44E+00 BI-214 + 1.59E+02 + 1:97E+01 2.06E+01 BI-214 + 1.42E+01 + 8.69E+00 1.38E+01 Station MW-14 collected 1/28/2013 Station MW-8 collected 5/1/2013 I Nuclide Ra-- Activ-ity " E-rror MDA - Nuclide RO Activity Error MDA K-40 1.26E+01 + 4.90E+01 9.59E+01 K-40 -8.83E+01 + 1.40E+02 1.12E+02 MN-54 3.76E+00 + 4.08E+00 6.20E+00 MN-54 1.49E-02 + 3.88E+00 6.37E+00 CO-58 1.40E+00 + 3.59E+00 5.68E+00 CO-58 0.OOE+00 + 5.63E+00 9.25E+00 FE-59 -2.67E+00 + 1.02E+01 1.64E+01 FE-59 2.84E+00 + 9.39E+00 1.50E+01 CO-60 -1.85E+00 + 2.19E+01 7.59E+00 CO-60 9.53E-01 + 4,34E+00 6.99E+00 ZN-65 0.OOE+00 + 7.14E+00 1.18E+01 ZN-65 5.51E+00 + 9.1OE+00 1.:42E+01 ZRNB-95 -1.30E+00 + 7.30E+00 1.18E+01 ZRNB-95 -4.58E+00 + .8.68E+00 1;38E+01 1-131 -2.93E+00 + 5.25E+00 8.38E+00 1-131 -1.74E-02 + 5.60E+00 9.21 E+00 CS-134 .-9.84E-01 + 4.85E+00 7.88E+00 CS-134

  • 1:59E+00 + 1.84E+01 7.55E+00 CS-137 -2.09E+00 + 4.89E+00 7.80E+00 CS-137 2.40E-03 + 4.84E+00 7.99E+00 BALA140 -8;10E-03 + 3.65E+00 6.OOE+00 BALA140 -5.04E-01 + 5.18E+00 8.44E+00 BI-214 + 1.30E+02 + 1.70E+01 1.85E+01 BI-214 + 3.09E+02 + 2.53E+01 2.23E+01 Station MW-3 collected '4/24/2013 Station MW-9 collect.ed 5/1/2013 FNuciide RQ Activity Error MDA Nuclide RQ Activity  : Error MDA K-40 -6.30E+00 + 4.54E+01 7.41 E+01 K-40 *-4.58E+01 + 9.32E+01 1.14E+02 MN-54 6.53E-01 + 2.37E+00 3.73E+00 MN-54 -1.99E-01 + 4.92E+00 8.07E+00 CO-58 -5.13E-02 + 278E+00 4.56E:00 CO-58 -2.10E+00 + 4.53E+00 7.21 E+00 FE-59 -2.50E-01 + 6.19E+00 1.01E+01 FE-59 -1.17E-01 + 9.21 E+00 1.51E+01 CO-60 -1.26E+00 + 5.04E+00 2.55E+00 CO-60 -2.94E-01 + 4.26E+00 6.95E+00 ZN-65 -3.79E+00 + 9.67E+00 1.53E+01 ZN-65 '2.01E-01 + 1.13E+01 1.86E+01 ZRNB-95 -8.13E-01 + 4.77E+00 7.66E+00 ZRNB-95 0.OOE+00 + 9.68E+00 :1.59E+01 1-131 -8.49E-01 + 4.06E+00 6.54E+00 1-131 4.67E-01 + 6.51 E+00 1.07E+01 CS-134 -3.45E-02 + 2.99E+00 4.91 E+00 CS-134 .- 2.56E-01 + 1.47E+01 2.42E+01 CS-137 5.43E-03 + 2.96E+00 4.86E+00 CS-137 2.30E+00 + 4.19E+00 6.59E+00 BALA140 -3.98E-01 + 5.57E+00 9.06E+00 BALA140 -2.22E+00 + 5.29E+00 8.33E+00 BI-214 + 1.83E+01 + 8.28E+00 1.26E+01 BI-214 + 1.82E+02 + 1.91E+01 1.93E+01 Station MW-5 collected ' 4/24/2013 Station MW-10 collected 5/1/2013

}Nuclide RQ Activity E-rror MDA Nuclide RQ Activity Error MDA K-40 -5.86E+01 + 2.74E+02 9.25E+01 K-40 -3.89E+01 + 7.86E+01 1.07E+02 MN-54 -1.21E+00 + 3.77E+00 5.94E+00 MN-54 2.08E-01 + 4.25E+00 6;96E+00 CO-58 -3.89E-01 + 3.26E+00 5.26E+00 CO-58 7.94E-02 + 4.OOE+00 6.57E+00 FE-59 -1.14E+00 + 7.83E+00 1.25E+01 FE-59 7.08E-01 +/- 9.47E+00 1.54E+01 CO-60 1.01E+00 + 3.20E+00 4.96E+00 CO-60 0.OOE+00 + 5.47E+00 500E+00 ZN-65 -2.89E+00 + 8.54E+00 1.34E+01 ZN-65 -8.59E+00 + 1.19E+01 1.87E+01 ZRNB-95 -1.85E+00 + 5.67E+00 8.87E+00 ZRNB-95 -3.29E+00 + 7.44E+00 1.18E+01 1-131 -7.24E-01 + 4.39E+00 7.09E+00 1-131 1.30E+00 + 5.68E+00 9.23E+00 CS-134 0.OOE+00 + 5.91 E+00 9.71 E+00 CS-134 6.15E-03 + 5.21E+00 8.54E+00 CS-137 -2.39E-01 + 2.79E+00 4.52E+00 CS-137 -1.56E+00 +/- 4.65E+00 7.47E+00 BALA140 -2.48E+00 + 6.37E+00 9.80E+00 BALA140 -2.23E-01 + 5.32E+00 8.70E+00 BI-214 1.05E+01 + 8.73E+00 1.44E+01 BI-214 + 1.08E+02 + 1.52E+01 1.80E+01 RQ = Results Qualifier. If blank, result is less than detection limit. If '+", result is above detection limit. Page 2 of 5

TABLE B-ID4,j I GAMMA SPECTROMETRY RESULTS OF GROUNDWATER MONITORING. WELL SAMPLES Results in pCi per liter Station MW- 1 collected 5/1/2013 Station MW-3 collected 7/22/2013 I

-Nucide RQ Acvi ty K-40 MN-54

-5.02E+01 + 1.02E+02 1.35E+00 + 3.62E+00 Error MDA 1.21 E+02 5.72E+00

.1 Nuclide' -RQ K740 MN-54 Activity

-2.62E+01 +

-:2.78E+00+

Error 7.84E+01 6.80E+00 MDA -- 1 1.20E+02 1.09E+01 I

CO-58 8.32E-02 + 3.65E+00 5.99E+00 CO-58 -3.65E+00 + 5.95E+00 9.42E+00 FE-59 CO-60 ZN-65 4.09E-01 + 1.02E+01 1.57E+00 + 3.98E+00

-1.08E+00 + 2.29E+01 1.67E+01 6.25E+00 7.32E+00 FE-59 CO-60 ZN-65 1.11E+00 +

3.77E+00 +

4.02E+00 +

9.13E+00 3.85E+00 6.48E+00 1.48E+01 5.56E+00 9.74E+00 I

ZRNB-95 -1.17E-01 + 7.23E+00 1.19E+01. ZRNB-95 6.33E+00 + 9.09E+00 1.42E+01 1-131 CS-134 CS-137

-3.36E+00 + 8.25E+00 2.55E-01 + 5.88E+00 1.42E+00 + 5.32E+00 1.33E+01 9.64E+00 8.58E+00 1-131 CS-1 34 CS-1 37 2.68E+00 +

8.43E-01 +

-1.12E+00 +

6.50E+00 5.26E+00 7.16E+00 1.05E+01 8.57E+00 1.17E+01 I

BALA140 1.84E+00 + 6.32E+00 1.OOE+01 BALA140 -1.20E+00 + 6.69E+00 1.08E+01 BI-214 + 1.04E+02 + 1.86E+01 Station MW-12 collected 2.15E+01 5/1/2013 BI-214 + 5.78E+02 +

Station MW-5 .collected 3.28E+01 2.41E+01 7/22/2013 I

Nuclide RO Activity

" K-40 MN-54

-3.65E+01 +

2.12E+00 + 4.48E+00 Error.

1.17E+02 7.07E+00

' Nuclide RO Activity K-40 MN-54

-9.33E+01 +

-4.07E-01 +

Error 1.93E+02 7.09E+00 MDA 1.29E+02 1.16E+01 CO-58 3.07E+00 4- 3.94E+00 5.97E+00 CO-58 -6.78E-01 +/- 4.36E+00 7.08E+00 FE-59 CO-60 ZN-65 2.11E+00 +- 1.06E+01 0.OOE+00 +- 5.33E+00

-1.42E+00 +- 8.59E+00 1.70E+01 8.76E+00 1.39E+01 FE-59 CO-60 ZN-65 2.85E+00 +

m6.14E-02 +

0.OOE+00 +

9.62E+00

.4.88E+00 7.33E+00 1.53E+01 8.01E+00 1.21E+01 i

ZRNB-95 9.92E-01 +- 8.25E+00 1.34E+01 ZRNB-95 4.48E+00 + 7.09E+00 1.10E+01 1-131 CS-1 34 CS-137 5.35E+00 + 7.71 E+00

-5.56E+00 +- 7.02E+00

-7.73E-02 +- 4.94E+00 1.22E+01 1.11E+01 8.11 E+00 1-131 CS-134 CS-137 2.OOE+00 +

1.63E+00 +/-

-3.65E+00 +

5.43E+00 4.35E+00 6.36E+00 8.75E+00 6.97E+00 1.01E+01 I

BALA140 -5.06E-01 +- 6.12E+00 9.95E+00 BALA140 3.46E-01 +/- 4.95E+00 8.07E+00 BI-214 + 1.01E+02 + 2.07E+01 Station MW-1 3 collec.ted 2.32E+01 4/24/2013 BI-214 + 1.96E+02 +

Station MW-6 collected 2.31E+01 2.26E+01 7/22/2013 I

Nuclide RQ Error MDA Nuclide RQ Activity EError MDA K-40 MN-54 Activity

-4.85E+01

  • 0.OOE+00

+ 1.50E+02

+ 4 .51E+00 8.68E+01 7.41E+00 K-40 MN-54

-4.OOE+01 +

-1.75E-01 +

9 .60E+01 4 .66E+00 1.25E+02 7.64E+00 I

CO-58 -1.74E-02 + .3.08E+00 5.06E+00 CO-58 -9.81E-01 +/- 5 .32E+00 8.63E+00 FE-59 CO-60 ZN-65

-1.83E+00 2.04E-01

-1.50E+00

+ 8 .53E+00

+ 3 .43E+00

+ ",7 .10E+00 1.35E+01 5.58E+00 1.13E+01 FE-59 CO-60 ZN-65

-2.02E+00 +

1.69E+00 +

2.13E+00 +/-

1 .13E+01 4 .81 E+00 4 .36E+01 1.83E+01 7.65E+00 1.50E+01 I

ZRNB-95 1.31E-01 + 4 .61E+00 7.55E+00 ZRNB-95 -6.12E-01 + 9 .09E+00 1.49E+01

-2.43E+00

-1.56E+00 2.45E-01

+ 5 .10E+00

+ 4 .13E+00

+ 3 .12E+00 7.96E+00 6.55E+00 5.07E+00 1-131 CS-134 CS-1 37 5.60E-04 +

-1.11E+01 +

-.1.90E+00 +

5 .25E+00 8 .61 E+00 6 .73E+00 8.76E+00 1.35E+01 1.09E+01 I

BALA140 0.OOE+00 + 6 .45E+00 1.06E+01 BALA140 0.OOE+00 +/- 4 .38E+00 7.20E+00 BI-214 4:14E+00 Station MW-14 collected

+ 8 .43E+00 1.48E+01 4/2412013 BI-214 + 4.45E+02 + . 2.93E+01 Station MW-8 collected 2.36E+01 7/24/2013 I

Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 MN-54 CO-58

-5.12E+01 + 1.50E+02 2.93E-02 + 2.63E+00 1.62E-02 + 2.19E+00 7.52E+01 4.32E+00 3.60E+00 K-40 MN-54 CO-58

-2.76E+01 +

-1.51E-01 +/-

-1.32E+00 +

7.66E+01 4.67E+00 4.99E+00 1.04E+02 7.66E+00 8.04E+00 I

FE-59 CO-60 ZN-65

-1.48E+00 + 7.87E+00 1.79E-02 + 2.79E+00

-5.86E-02 + 5.06E+00 1.26E+01 4.58E+00 8.31 E+00 FE-59 CO-60 ZN-65

-2.92E-01 +

1.60E-01 +

3.25E+00 +/-

1.13E+01 5.11E+00 5.79E+00 1.85E+01 8.79E+00 1.78E+01 I

ZRNB-95 -9.18E-01 + 4.38E+00 7.03E+00 ZRNB-95 3.61 E+00 + 7.84E+00 1.24E+01 1-131 CS-134 CS-1 37

-1.23E+00 + 4.81 E+00

-8.27E-01 + 2.75E+00 1.21E-01 + 2.39E+00 7.78E+00 4.40E+00 3.90E+00 1-131 CS-134 CS-137 1.20E-01 +

-1.07E+00 +

-2.28E+00 +

5.15E+00 4.09E+00 5.47E+00 8.46E+00 6.58E+00 8.72E+00 I

BALA140 1.22E+00 + 4.99E+00 7.92E+00 BALA1 40 3.84E+00 + 5.51 E+00 8.25E+00 BI-214 4.58E+00 + 6.21 E+00 1.11E+01 BI-214 + 2.47E+02 + 2.21E+01 1.99E+01 t

RQ = Results Qualifier, If blank, result is less than detection limit. If "+'., result is above detection limit. Page 3 of 5 I

TABK.E B-10.1 GAMMA SPECTROMETR'YRESULTST3OF',GROUNDWATER MONITORING WELL SAMPLES Results in pCi per liter Station MW-9 collected 7/24/2013 Station MW-13 collected 7/22/2013 I Nuclide RQ - Activityv Error "M-DA VNucli-e.-R ActMity ..... Error MDA I K-40 -1.18E+01 + 6.06E+01 1.04E+02 K-40 -3.62E+01 + 1.02E+02 8.02E+01 MN-54 1;02E-01 + 3.91E+00 6.41 E+00 MN-54 2.51E+00 + 2.59E+00 3.78E+00 CO-58 1.54E+00 + 5.03E+00 8.07E+00 CO-58 8.97E-02 + 2.54E+00 4.16E+00 FE-59 -1.01E+00 +

  • 1.16E+01 1.89E+01 FE-59 1.84E+00 + 8.64E+00 1.39E+01 CO-60 -2.72E+00 + 3.13E+03 7.69E+00 CO-60 1.28E+00 + 3.21 E+00 5.04E+00 ZN-65 -4.36E+00 + 1.21E+01 1.92E+01 ZN-65 -6.92E+00 + 9.97E+00 1.56E+01 ZRNB-95 5.75E-01 + 6.76E+00 1.10E+01 ZRNB-95 8.66E-02 + 4.65E+00 7.63E+00 1-131 6.91E-01 + 5.80E+00 9.48E+00  : 1-131 -2.10E+00 + 3.97E+00 6.34E+00 CS-134 9.32E-02 + .3.59E+00 5.90E+00 CS-134 0.OOE+00 + 1.19E+01 1.95E+01 CS-137 2.51E+00 + 4.84E+00 7.61 E+00 CS-i 37 8.77E-02 + 3.56E+00 5.85E+00 BALA140 -2.27E+00 + 6.47E+00 1.02E+-01 BALA1 40 0.OOE+00 + 4.65E+00 7.65E+00 I BI-214 .+ 2.09E+02 + 2.18E+01 2.04E+01 BI-214 + 2.15E+02 + 1.77E+01 1.41E+01 Station MW-10 colIlected 7/24/2013 Station MW-14 collected 7/22/2013 cNuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 -1.03E+00 + 5.16E+01 1.03E+02 K-40 -2.94E+01 + 8.46E+01 1.09E+02 MN-54 -1.68E+00 + 4.39E+00 6.96E+00 MN-54 -1.48E+00 + 5.07E+00 8.15E+00 CO-58 4.43E-01 + 4.20E+00 6.83E+00 CO-58 4.44E-02 + 4.29E+00 7.04E+00 FE-59 0.OOE+00 + 8.23E+00 1.35E+01 FE-59 3.19E-01 + 1.05E+01 1.72E+01 CO-60 6.45E-01 + 4.47E+00 7.72E+00 CO-60 -1.14E+00 + 1.04E+01 7.72E+00 ZN-65 -3.02E+00 + 1.05E+01 1.68E+01 ZN-65 -3.02E+00 + 1.03E+01 1.65E+01 ZRNB-95 -1.75E+00 + 6.70E+00 1.07E+01 ZRNB-95 -2.71 E+00 + 7.85E+00 1.25E+01 1-131 2.40E+00 + 6.30E+00 1.01E+01 1-131 6.04E-03 + 5.40E+00 8.88E+00 CS-134 6.30E-03 + 4.94E+00 8.11E+00 CS-134 2.48E+00 + 4.80E+00 7.61 E+00 CS-137 2.94E-01 + 4.33E+00 7.07E+00 CS-137 -1.10E+00 + 4.95E+00 7.99E+00 BALA140 1.56E+00 + 7.12E+00 1.14E+01 BALA140 -7.37E-01 + 4.94E+00 7.94E+00 BI-214 + 6.72E+01 + 1.52E+01 2.16E+01 BI-214 + 1.72E+02 + 2.09E+01 2.07E+01 Station MW-11 collected 7/24/2013 Station MW-3 collected 11/1/2013 Nuclide RQ Activity Error MDA__7 Nuclide RQ Activity Error MDA K-40 -3.77E+01 + 9.43E+01 1.25E+02 K-40 -7.74E+01 + 2.02E+03 9.97E+01 MN-54 1.54E+00 + 4.60E+00 7.36E+00 MN-54 6.64E-01 + 3:OOE+00 4.75E+00 CO-58 0.OOE+00 + '5.86E+00 9.63E+00 CO-58 -9.OOE-01 + 3.44E+00 5.44E+00 FE-59 2.01E+00 + 9.99E+00 1.60E+01 FE-59 4.25E+00 + 7.71 E+00 1.10E+01 CO-60 -1.77E-01 + 4.17E+00 6.82E+00 CO-60 1.18E+00 + 3.13E+00 4.78E+00 ZN-65 -9.42E+00 + 1.49E+01 2.36E+01 ZN-65 -2.95E+00 + 8.95E+00 1.41E+01 ZRNB-95 2.12E-01 + 8.31 E+00 1.36E+01 ZRNB-95 -7.98E-01 + 6.52E+00 i1.05E+01 1-131 -5.94E-01 + 8.88E+00 1.45E+01 1-131 .- 6.49E-01 + 7.26E+00 1.18E+01 CS-134 -6.17E-01 + 1.72E+01 2.82E+01 CS-134 2.94E-01 + 2.90E+00 4.70E+00 CS-137 3.20E+00 + 4.99E+00 7.79E+00 CS&137 -9.51E-01 + :3.26E+00 5.14E+00 BALA140 1.25E+00 + 6.48E+00 1.04E+01 BALA140 -5.09E-01 + 8.66E+00 1.41E+01 BI-214 + 1.65E+02 + 2.03E+01 2.09E+01 BI-214 + 2.25E+01 + 9.23E+00 1.34E+01 Station MW-1 2 collected 7/24/2013 tation MW-5 collecte d 11/6/2013 Nuclide RQ Activity Error MDA Nuclide FRQ Activity Error MDA, "

K-40 -3.22E+01 + 8.16E+01 1.19E+02 K-40 -1.25E+01 + 5.88E+01 8.92E+01 MN-54 -2.15E+00 + 5.24E+00 8.37E+00 MN-54 6.23E-01 + 3.08E+00 4:91 E+00 CO-58 7.02E-01 + 3.98E+00 6.44E+00 CO-58 '-1.70E+00 + 3.95E+00 6.15E+00 FE-59 -2.26E-01 + 1.18E+01 1.93E+01 FE-59 0.OOE+00 + 8.1 OE+00 1.33E+01 CO-60 -6.63E-01 + 4.70E+00 7.62E+00 CO-60 -2.27E-01 + 2.92E+00 4.73E+00 ZN-65 8.36E-01 + 5.67E+00 9.13E+00 ZN-65 1.73E+00 + 7.42E+00 1.18E+01 ZRNB-95 0.OOE+00 + 9.60E+00 1.58E+01 ZRNB-95 -1.26E+00 + 6.09E+00 9.73E+00 1-131 2.28E-01 + 8.45E+00 1.39E+01 1-131 1.75E-01 + 4.55E+00 7.45E+00 CS-134 -4.99E+00 + 6.70E+00 11.06E+01 CS-134. -1.85E-01 + 4.26E+00 6.97E+00 CS-1 37 5.15E-01 + 4.50E+00 7.32E+00 CS-137 2.64E-01 + 3.80E+00 6.19E+00 BALA140 2.39E+00 + 6.52E+00 1.02E+01 BALA140 2.44E+00 + 5.73E+00 8.65E+00 BI-214 + 8.14E+01 + 1.93E+01 2.30E+01 BI-214 + 2.57E+01 + 9.60E+00 1.36E+01 RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit. .Page 4 of 5

TABLE B-10.1 I GAMMA SPECTROMETRY RESULTS OF GROUNDWATER MONITORING WELL SAMPLES I

Results in pCi per liter Station MW-6 collected .11/6/2013 *Station-MW-11 collected 11/13/2013 AWD ýý-b Nu-cfide-K-40 MN-54 R-&" Activty

-3.33E+01 + 1.10E+02 5.34E-01 + 3.13E+00

" Ertror MDA 7 9.48E+01 5.02E+00 Nuclide -Q -

K-40 MN-54 A--

-Xc-ty-. -.

-1.42E+01 +

0.OOE+00 +

El--rdr 8.28E+01 5.49E+00 9.70E+01 9.02E+00 I

CO-58 -2.53E-01 + 3.54E+00 5.76E+00 CO-58 -1.45E+00 + 4.04E+00 6.38E+00 FE-59 CO-60 ZN-65 0.OOE+00

-1.27E-01 + 3.56E+00

-5.41 E+00 + 1.07E+01 8.12E+00 1.34E+01 5.82E+00 1.66E+01 FE-59 CO-60 ZN-65

.1.52E+00 +

-2.38E+00 +

-2.38E+00 +

7.74E+00 1.42E+01 8.46E+00 1.23E+01 7.47E+00 1.34E+01 I

ZRNB-95 -7.70E-01 + 5.97E+00 9.64E+00 ZRNB-95 3.58E+00 + 6.OOE+00 9.1 OE+00 1-131 CS-134 CS-1 37

-8.1 0E-03 + 4.42E+00

-2.62E+00 + 4.23E+00 9.74E-01 + 2.92E+00 7.27E+00 6.57E+00 4.55E+00 1-131 CS-134 CS-1 37 3.02E-02 +

2.15E-01 +

-1.01E+00 +

3.51 E+00 3.52E-01 4.24E+00 5.77E+00 8.18E-01 6.81 E+00 I

BALA140 -3.52E-01 + 5.95E+00 9.69E+00 BALA140 -1.27E+00 + 4.96E+00 7.81 E+00 BI-214 + 3.84E+01 + 1.11E+01 Station MW-8 collected 1.46E+01 11/13/2013 B 1-214 + 2.39E+02 + 2.13E+01 Station MW-12 collected 1.48E+01 I

11/13/2013 Nuclide RQ Activity K-40 MN-54

-3.93E+01 + 1.56E+02

-9.64E-01 + 4.22E+00 Error MDA 1.05E+02 6.77E+00 Nuclide RQ Activity K-40 MN-54

-1.76E+01 +

-9.25E-01 +

Error 8.60E+01 4.43E+00 MDA 9.17E+01 7.12E+00 I

CO-58 0.OOE+00 + 5.06E+00 8.32E+00 CO-58 -1.18E+00 + 3.95E+00 6.27E+00 FE-59 CO-60 ZN-65 0.00E+00 + 1.22E+01 9.15E-01 + 4.12E+00

-9.43E+00 + 1.46E+01 2.01E+01 6.56E+00 2.27E+01 FE-59 CO-60 ZN-65

-7.47E-01 +

-1.26E+00 +

-1.86E+00 +

9.29E+00 4.92E+01 7.63E+00 1.51E+01 9.47E+00 1.21E+01 I

ZRNB-95 2.13E-02 + 6.34E+00 1.04E+01 ZRNB-95 4.92E-01 + 6.35E+00 1.03E+01 1-131 CS-1 34 CS-1 37

-1.66E+00 + 4.42E+00 7.18E-01 + 1.42E+01

-1.67E+00 + 4.56E+00 7.06E+00 2.33E+01 7.22E+00 1-131 CS-1 34 CS-1 37 7.76E-01 +

3.05E-01 +

4.20E-01 +

3.85E+00 1.05E+01 3.61 E+00 6.23E+00 1.73E+01 5.86E+00 I

BALA140 0.00E+00 + 6.90E+00 1.13E+01 BALA140 -1.98E-01 +/- 4.62E+00 7.53E+00 BI-214 + 2.24E+02 + 2.11E+01 Station MW-9 collected 1.45E+01 11/13/2013 BI-214 + 2.54E+02 + 2.14E+01 Station MW-13 collected 1.42E+01

.11/6/2013 I

  • Nuclide RQ Activity Error MDA I

MDA Nuclide RQ Activity Error K-40 -1.21E+01 + 7.67E+01 9.67E+01 K-40 -5.54E+00 + 5.26E+01 8.55E+01 MN-54 1.02E-02 + 3.15E+00 5.17E+00 MN-54 9.99E-02 + 2.88E+00 4.72E+00 CO-58 0.OOE+00 + 3.84E+00 6.32E+00 CO-58 0.OOE+00 + 4.03E+00 6.63E+00 FE-59 CO-60 ZN-65

-3.33E+00 + 8.80E+00

-8.53E-01 + 1.91E+01

-1.10E+01 + 1.40E+01 1.36E+01 6.55E+00 2.17E+01 FE-59 CO-60 ZN-65 0.OOE+00 +

-1.50E+00 +

-6.56E-02 +

2.18E+00 4.63E+01 9.23E+00 3.58E+00 7.02E+00 1.52E+01 I

ZRNB-95 -1.34E+00 + 6.32E+00 1.01E+01 ZRNB-95 -1.04E+00 + 4.55E+00 7.18E+00 1-131 CS-1 34 CS-137 0.OOE+00 + 3.39E+00

-1.91E+00 + 4.20E+00

-8.65E-01 + 3.43E+00 5.57E+00 6.64E+00 5.46E+00 1-131 CS-134 CS-137

-2.03E+00 +

-1.50E+00 +

-9.15E-01 +

5.43E+00 3.10E+00 3.27E+00 8.63E+00 4.81 E+00 5.18E+00 I

BALA140 -1.18E+00 + 5.49E+00 8.73E+00 BALA140 -1.13E+00 + 5.81 E+00 9.20E+00 BI-214 + 2.23E+02 + 2.01 E+01 Station MW-10 colleccted 1.48E+01 11/13/2013 BI-214 1.33E+01 + 8.37E+00 Station MW-14 collected 1.34E+01 11/6/2013 i

Nuclide RQ Activity Error MDA Nuclide RQ Activity Error MDA K-40 MN-54 CO-58

-1.93E+01

-8.21E-02

-1.01E+00

+ 7'.76E+01

+ 3 .35E+00

+ 33.93E+00 8.26E+01 5.49E+00 6.27E+00 K-40 MN-54 CO-58

-2.32E+01 +

-1.63E-01 +

-1.63E+00 +

7.62E+01 2.97E+00 3.88E+00 8.94E+01 4.85E+00 6.03E+00 I

+ 7'.93E+00 FE-59 CO-60 ZN-65 3.46E+00 7.47E-01

-4.04E+00

+ 3 .75E+00

+ 9l.13E+00 1.20E+01 6.29E+00 1.42E+01 FE-59 CO-60 ZN-65 7.37E-02 +/-

-4.74E-01 +

-3.71E+00 +/-

7.77E+00 3.92E+00 8.98E+00 1.28E+01 6.33E+00 1.40E+01 I

ZRNB-95 9.21E-01 + 5 .25E+00 8.41 E+00 ZRNB-95 3.86E+00 + 5.76E+00 8.50E+00 1-131 CS-134 CS-1 37

-5.03E-01

-4.52E-01 6.72E-02

+ 3 .40E+00

+ 3*.34E+00

+ 2_.82E+00 5.51 E+00 5.41E+00 4.62E+00 1-131 CS-134 CS-137

-7.90E-01 +

-5.66E-01 +

2.46E-01 +

4.76E+00 3.38E+00 3.39E+00 7.68E+00 5.46E+00 5.52E+00 I

BALA140 -7.72E-01 + 5*.50E+00 8.85E+00 BALA140 2.74E-01 + 5.29E+00 8.61 E+00 BI-214 + 1.34E+02 + 1 .62E+01 1.45E+01 B 1-214 + 2.04E+01 + 9.20E+00 1.37E+01 I

RQ = Results Qualifier. If blank, result is less than detection limit. If "+", result is above detection limit. Page 5 of 5 I

Table B-10.2 GAMMA SPECTROMETRY RESULTSOF GROUNDWATER MONITORING WELL SAMPLES -

SUMMARY

Results in pCi/liter Average Activity , Activity Average Number of Number of Nuclide Activity Low High MDA Samples Positive IDs BALA140 1.14E-01 -2.48E+00 3.84E+00 8.47E+00 40 0 BI-214 1.65E+02 4.14E+00 5.78E+02 1.72E+01 40 36 CO-58 -1.64E-01 -3.65E+00 3.25E+00 6.33E+00 40 0 CO-60 -1.51E-01 -2.72E+00 3.77E+00 6.58E+00 40 0 CS-134 -5.73E-01 71.11E+01 .2.65E+00 9.22E+06 . 40 0 CS-137 -2.15E-01 -3.65E+00 3.20E+00 6.86E+00 40 0 FE-59 2.23E-01 -3.33E+00 5.39E+00 1.43E+01' 40 0 1-131 -8.74E-02 -' -3.36E+00 5.35E+00 8.44E+00 40 0 K-40 -3.09E+01 -9.33E+01 1.64E+01 9.88E+01 40 0 MN-54 3.23E-02 -3.03E+00 3.76E+00

  • 6.46E+00 40 0 ZN-65 -2.74E+00 -1.10E+01 5.51 E+00 1.43E+01 40 0 ZRNB-95  :. 1.26E-01 -4.58E+00 6.33E+00 1.08E+01 40 0 Page 1 of 1

I TABLE B-11.1 TRITIUM IN GROUNDWATER MONITORING WELL SAMPLES i Results in pCi per. liter Location Collection Date RQ Activity Error i MW-3 01/28/13 +, . 1.23E+03 1.24E+02 04/24/13 07/22/13

+ - *-!-.45E+03

+ 1.59E+03 1.29E+02 1.30E+02 I

11/06/13 + 1.49E+03 1.32E+02 MW-5 01/28/13..

04/24/13

+

+

1.49E+04 1.50E+04 3.08E+02 3.09E+02 I

1.54E+04 3.. 7E+02 07/22/13 11/06/13

+

+ 1.50E+04 3.14E+02 I MW-6 01/28/13 + 5.69E+03 2.03E+02 04/24/1 3 07/22/13,

+

+

+

5.79E+03 5.39E+03 5.20E+03 2.04E+02 1.99E+02 I 11/06/13.- 1.99E+02 MW-8 02/04/13 05/01/13

+

+

7.75E+02 7.38E+02 1.13E+02 1.11E+02 I

07/24/13 + 2.47E+03 1.50E+02 11/13/13 + 2.04E+03 1.44E+02 I

MW-9 02/04/13 1.86E+02 9.67E+01 05/01/13 07/24/13 11/13/13

+

2.35E+02 3.42E+02 1.77E+02 9.84E+01 9.72E+01 9.75E+01 I

MW-i0 02/04/13 05/01/13 2.82E+02 3.85E+02

.9.95E+01 1.02E+02 I

07/24i 3 4.74E+02 1.02E+02 MW-11 11/13/13 02/04/13 3.40E+02 8.06E+02 1.02E+02 I

1.14E+02 I

+

05/01/1.3 9.01 E+02 1.17E+02

+

07/24/13 1.26E+03 1.24E+02

+

11/13/13 1.OOE+03 1.21E+02 MW-12 02/04/13 05/01/13

+4

+4

-+

5.12E+02 5.93E+02 1.06E+02 1.08E+02 I

07/24/13 7.45E+02 1.10E+02 MW-13 11/13/13 01/28/13

+

+

6.32E+02 1.13E+04 1.10E+02 2.74E+02 I

+

04/24/13 1.17E+04 2.78E+02 07/22/13 11/06/13

+

+

1.19E+04 1.19E+04 2.79E+02 2.82E+02 I

MW-14 01/28/13 04/24/13 07/22/13

+

4-2.17E+02 4.10E+02 3.10E+02 9.68E+01 1.02E+02 1.02E+02 i

I

+

11/06/13 3.23E+02 1.01E+02 RQ= results Qualifier. If blank, result is less than detection limit. If "+', result is above the detection limit. Page 1 of 1 I

TABLE B- 12.1 GAMMA SPECTROMETRY RESULTS OF CGS STORM DRAIN POND SOIL Surface Soil Sample Results Results in pCi/kilogram dry mass  :

Location & Date SDP location B 6/6/2013 Location & Date SDP location H 6/6/2013 Nuciide --RQ Activity Error MDA I Nuclide RQ Activity Error MDA -]

BE-7 + 7.78E+03 + 4.24E+02 3.02E+02 BE-7 + 2.71E+03 + 3.94E+02 3.91 E+02 K-40 + 6.95E+03 + 4.94E+02 3.26E+02 K-40 + 3.67E+03 + 4.58E+02 3.39E+02 CR-51 8.21 E+01 + 1.88E+02 3.04E+02 CR-51 6.72E+01 + 2.52E+02 4.1OE+02 MN-54 3.06E+01 + 2.46E+01 3.82E+01 MN-54 3.70E+01 + 2.80E+01 4.30E+01 CO-58 -3.32E+00 + 2.43E+01 3.97E+01 CO-58 1.89E+01 + 2.49E+01 3.91 E+01 FE-59 1.85E+01 + 4.56E+01 7.24E+01 FE-59 -2.90E+01 + 7.01 E+01 1.12E+02 CO-60 + 1.80E+03 + 5.43E+01 4.13E+01 CO-60 + 1.48E+03 + 5.68E+01 4.48E+01 ZN-65 8.29E+01 + 6.07E+01 9.39E+01 ZN-65 + 1.04E+02 + 6.65E+01 1.01E+02 ZRNB-95 -2.65E+00 + 4.30E+01 7.05E+01 ZRNB-95 -1.81E-02 + 4.98E+01 8.20E+01 CS-1 34 1.80E+01 + 2.22E+01 3.54E+01 CS-1 34 3.11E+01 + 2.62E+01 4.09E+01 CS-1 37 + 1.72E+02 + 3.OOE+01 3.12E+01 CS-1 37 + 1.66E+02 + 3.58E+01 3.82E+01 BALA140 -5.19E+00 + 2.98E+01 4.82E+01 BALA140 0.00E+00 + 5.89E+01 9.82E+01 BI-214 + 3.21E+02 + 5.85E+01 8.OOE+01 BI-214 9.26E+01 + 6.18E+01 1.02E+02 Location & Date SDP location K 6/6/2013 Location & Date SDP location J 6/6/2013 Nuclide RQd Activity Error MDA I Nuclide RQ Activity Error MDA BE-7 + 1 .12E+03 + 2.36E+02 2.49E+02 BE-7 + 2.56E+03 + 3.61 E+02 3.59E+02 K-40 + 22.82E+03 + 3.22E+02 2.41 E+02 K-40 + 5.38E+03 + 4.52E+02 2.65E+02 CR-51 -4 .85E+01 + 1.60E+02 2*60E+02 CR-51 -1.31E+02 + 1.99E+02 3.18E+02 MN-54 - 1.92E-01 + 1.61 E+01 2.65E+01 MN-54 + 4.56E+01 + 2.67E+01 4.04E+01 CO-58 9.08E-02 + 1.42E+01 2.34E+01 CO-58 9.17E+00 + 2.71E+01 4.38E+01 FE-59 -1.44E+00 + 2.72E+01 4.44E+01 FE-59 -7.73E+00 + 4.62E+01 7.47E+01 CO-60 + 3.34E+02 + 2.44E+01 2.53E+01 CO-60 + 1.86E+03 + 5.74E+01 3.73E+01 ZN-65 -1.78E+01 + 3.40E+01 5.39E+01 ZN-65 + 1.19E+02 + 6.85E+01 1.04E+02 ZRNB-95 4.30E+01 + 2.67E+01 3.91E+01 ZRNB-95 2.51E+01 + 4.88E+01 7.82E+01 CS-1 34 -22.74E+01 + 1.92E+01 2.98E+01 CS-1 34 2.53E+01 + 2.36E+01 3.72E+01 CS-137 22.52E+01 + 1.77E+01 2.69E+01 CS-1 37 + 1.17E+02 + 3.13E+01 4.39E+01 BALA140 C).OOE+00 + 2.55E+01 4.25E+01 BALA140 -1.34E+01 + 4:42E+01 7.07E+01 BI-214 + 4 .-54E+02 + 6.16E+01 6.17E+01 BI-214 + 2.20E+02 + 5.96E+01 9.03E+01 RQ = Results Qualifier. If blank, result is less than detection limit. If "+', result is above detection limit. Page 1 of I