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{{#Wiki_filter:W LF CREEK'NUCLEAR OPERATING CORPORATION Gautam Sen Manager Regulatory Affairs April 26, 2012 RA 12-0053 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555  
{{#Wiki_filter:W LF CREEK 'NUCLEAR OPERATING CORPORATION Gautam Sen Manager Regulatory Affairs                                                   April 26, 2012 RA 12-0053 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555


==Subject:==
==Subject:==
Docket No. 50-482: 2011 Annual Radiological Environmental Operating Report Gentlemen:
Docket No. 50-482: 2011 Annual Radiological Environmental Operating Report Gentlemen:
The purpose of this letter is to submit the enclosed Annual Radiological Environmental Operating Report, which is being submitted pursuant to Wolf Creek Generating Station (WCGS) Technical Specification 5.6.2. This report covers radiological environmental monitoring around WCGS for the period of January 1, 2011, through December 31, 2011.Also enclosed are corrected pages from the 2009 and 2010 reports that reflect administrative changes that were found necessary during preparation of the 2011 report. The changes are marked with revision bars. Wolf Creek Nuclear Operating Corporation apologizes for any inconvenience this may cause.This letter contains no commitments.
The purpose of this letter is to submit the enclosed Annual Radiological Environmental Operating Report, which is being submitted pursuant to Wolf Creek Generating Station (WCGS) Technical Specification 5.6.2.                     This report covers radiological environmental monitoring around WCGS for the period of January 1, 2011, through December 31, 2011.
If you have any questions concerning this matter, please contact me at (620) 364-4175, or Mr. William Muilenburg, at (620) 364-8831, ext. 4511.Sincerely, Gautam Sen GS/rlt  
Also enclosed are corrected pages from the 2009 and 2010 reports that reflect administrative changes that were found necessary during preparation of the 2011 report. The changes are marked with revision bars. Wolf Creek Nuclear Operating Corporation apologizes for any inconvenience this may cause.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4175, or Mr. William Muilenburg, at (620) 364-8831, ext. 4511.
Sincerely, Gautam Sen GS/rlt


==Enclosure:==
==Enclosure:==
2011 Annual Radiological Environmental Operating Report Corrected pages from 2009 and 2010 reports (3 pages) cc: E. E. Collins (NRC), w/e J. R. Hall (NRC), w/e N. F. O'Keefe (NRC), w/e Senior Resident Inspector (NRC), w/e P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HC/VET


2011 Annual Radiological Environmental Operating Report Corrected pages from 2009 and 2010 reports (3 pages)cc: E. E. Collins (NRC), w/e J. R. Hall (NRC), w/e N. F. O'Keefe (NRC), w/e Senior Resident Inspector (NRC), w/e P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HC/VET WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION 2011 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT A V April 15, 2012 TABLE OF CONTENTS List of Tables ii List of Figures ii List of Charts ii Executive Summary 1 Introduction 1 I. Program Description 1 II. Discussion of Results 4 Ill. Program Revisions/Changes 10 IV. Program Deviations 10 V. Interlaboratory Comparison Program Results 11 VI. Comparison to the Radioactive Effluents Release Program 11 Tables 12 Figures 20 Charts 25 Appendix A -Interlaboratory Comparison Program Results A-1 Appendix B -Summary Tables B-1 Appendix C -Individual Sample Results C-1 Air Particulate and Charcoal Filters C-I Quarterly Air Particulate  
WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION 2011 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT A
-Gamma C-1 3 Surface Water C-20 Ground Water C-28 Drinking Water C-44 Quarterly Drinking Water -Tritium C-52 Shoreline Sediment C-54 Fish C-57 Food/Garden C-62 Feed and Forage C-.70 Bottom Sediment C-73 Aquatic Vegetation C-89 Terrestrial Vegetation C-91 Soil C-92 Deer C-93 Appendix D -Land Use Census Report D-1 LIST OF TABLES 1 Radiological Environmental Monitoring Program Description 12 2 Sample Location Identifiers, Distances (Miles) and Directions (Sectors) 17 3 OSL Dosimeter Results 19 LIST OF FIGURES 1 Airborne Pathway Sampling Locations 20 2 Direct Radiation Pathway Sampling Locations 21 3 Waterborne Pathway Sampling Locations 22 4 Ingestion Pathway Sampling Locations 23 5 Distant Sampling Locations 24 LIST OF CHARTS 1 Airborne Gross Beta Weekly Results 25 2 Historical Airborne Smoothed Indicator and Control Gross Beta 26 3 OSL Dosimeters  
V April 15, 2012
-Indicator and Control Locations mR per Standardized 90-day 27 Quarter 4 Historical TLD Nearsite Locations and Control Locations 28 5 Coffey County Lake Surface Water Tritium Data 29 6 Drinking Water Gross Beta (5 years) 30 7 Detected Co-60 Activity in Coffey County Lake Discharge Cove Bottom Sediment 31 8 Detected Cs-1 37 Activity in Bottom Sediment 32 ii EXECUTIVE  
 
TABLE OF CONTENTS List of Tables                                                     ii List of Figures                                                   ii List of Charts                                                     ii Executive Summary                                                 1 Introduction                                                       1 I. Program Description                                           1 II. Discussion of Results                                         4 Ill. Program Revisions/Changes                                   10 IV. Program Deviations                                           10 V. Interlaboratory Comparison Program Results                   11 VI. Comparison to the Radioactive Effluents Release Program       11 Tables                                                           12 Figures                                                           20 Charts                                                           25 Appendix A - Interlaboratory Comparison Program Results     A-1 Appendix B - Summary Tables                                 B-1 Appendix C - Individual Sample Results                     C-1 Air Particulate and Charcoal Filters     C-I Quarterly Air Particulate - Gamma       C-1 3 Surface Water                           C-20 Ground Water                             C-28 Drinking Water                           C-44 Quarterly Drinking Water - Tritium       C-52 Shoreline Sediment                       C-54 Fish                                     C-57 Food/Garden                             C-62 Feed and Forage                         C-.70 Bottom Sediment                         C-73 Aquatic Vegetation                       C-89 Terrestrial Vegetation                   C-91 Soil                                     C-92 Deer                                     C-93 Appendix D - Land Use Census Report                         D-1
 
LIST OF TABLES 1 Radiological Environmental Monitoring Program Description                   12 2 Sample Location Identifiers, Distances (Miles) and Directions (Sectors)     17 3 OSL Dosimeter Results                                                       19 LIST OF FIGURES 1 Airborne Pathway Sampling Locations                                         20 2 Direct Radiation Pathway Sampling Locations                                 21 3 Waterborne Pathway Sampling Locations                                       22 4 Ingestion Pathway Sampling Locations                                         23 5 Distant Sampling Locations                                                   24 LIST OF CHARTS 1 Airborne Gross Beta Weekly Results                                           25 2 Historical Airborne Smoothed Indicator and Control Gross Beta               26 3 OSL Dosimeters - Indicator and Control Locations mR per Standardized 90-day 27 Quarter 4 Historical TLD Nearsite Locations and Control Locations                     28 5 Coffey County Lake Surface Water Tritium Data                               29 6 Drinking Water Gross Beta (5 years)                                         30 7 Detected Co-60 Activity in Coffey County Lake Discharge Cove Bottom Sediment 31 8 Detected Cs-1 37 Activity in Bottom Sediment                                 32 ii
 
EXECUTIVE  


==SUMMARY==
==SUMMARY==
Plant-related activation, corrosion, or fission products were not detected during 2011 in airborne particulate and radioiodine filters, ground water, drinking water, broadleaf vegetation, shoreline sediment, crops, aquatic vegetation, bottom sediment, or soil samples. Activation, corrosion or fission products attributable to plant operation were detected during 2011 in surface water, fish, and deer samples.Activity was detected from the radioactive material released from Dai-lchi, Fukushima following the March 22, 2011 earthquake and subsequent tsunami.Nuclides detected in Radiological Environmental Monitoring Program (REMP) samples were below applicable NRC reporting levels.Based upon the radiological environmental monitoring program results, it was concluded that station operations had no significant radiological impact on the health and safety of the public or the environment.
 
INTRODUCTION The 2011 Annual Radiological Environmental Operating Report for Wolf Creek Generating Station (WCGS) covers the period from January 1 through December 31, 2011. WCGS is located in Coffey County, Kansas, approximately five miles northeast of Burlington, Kansas.Fuel loading commenced at WCGS on March 12, 1985. The operational phase of the REMP began with initial criticality on May 22, 1985, and the first detectable quantities of radioactivity were reported in plant effluents in June 1985.This report contains a description of the REMP conducted by Wolf Creek Nuclear Operating Corporation (WCNOC), a discussion of monitoring program results, the revisions or changes to the program, program deviations, the Interlaboratory Comparison Program and a comparison to the Radioactive Effluents Release Program. The Interlaboratory Comparison Program results, a summary of results in the Nuclear Regulatory Commission (NRC) Branch Technical Posi'Non specified format, the individual sample results, and the Land Use Census Report are included as appendices.
Plant-related activation, corrosion, or fission products were not detected during 2011 in airborne particulate and radioiodine filters, ground water, drinking water, broadleaf vegetation, shoreline sediment, crops, aquatic vegetation, bottom sediment, or soil samples. Activation, corrosion or fission products attributable to plant operation were detected during 2011 in surface water, fish, and deer samples.
I. PROGRAM DESCRIPTION Radiological environmental monitoring samples were collected according to the schedule in WCGS procedure AP 07B-004, Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program).
Activity was detected from the radioactive material released from Dai-lchi, Fukushima following the March 22, 2011 earthquake and subsequent tsunami.
Radiological environmental monitoring program samples were collected by the WCGS Environmental Management group and were analyzed by Environmental, Inc.Landauer, Inc. processed the environmental optically stimulated luminescence (OSL)dosimeters.
Nuclides detected in Radiological Environmental Monitoring Program (REMP) samples were below applicable NRC reporting levels.
Table 1 identifies the exposure pathway/sample type, number of samples/sample locations, sample collection frequency and type/frequency of analysis.
Based upon the radiological environmental monitoring program results, it was concluded that station operations had no significant radiological impact on the health and safety of the public or the environment.
Table 2 lists each sample location's distance and direction from the plant. Samples in addition to those required by the WCGS Offsite Dose Calculation Manual (ODCM) were also obtained and analyzed.The following is a description of the sampling and analysis program by individual pathways.2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 1 of 32 A. Airborne Pathway Low volume air sampling pumps with digital flow meters continuously collected particulate and radioiodine samples on 47 mm glass fiber filters and charcoal canisters, respectively.
INTRODUCTION The 2011 Annual Radiological Environmental Operating Report for Wolf Creek Generating Station (WCGS) covers the period from January 1 through December 31, 2011. WCGS is located in Coffey County, Kansas, approximately five miles northeast of Burlington, Kansas.
The filters and charcoal canisters were changed out weekly, labeled, and shipped to Environmental, Inc. for analyses.Gross beta analyses of the air particulate filters were performed after a nominal 72-hour period to allow the radon and thoron daughter products to decay.Weekly air particulate filters were combined into quarterly composites for each location and analyzed for gamma emitting isotopes.Charcoal canisters were routinely counted to determine the presence or absence of 1-131.Positive indication of 1-131 would have resulted in analysis of each individual charcoal canister.Air samples were collected from six locations.
Fuel loading commenced at WCGS on March 12, 1985. The operational phase of the REMP began with initial criticality on May 22, 1985, and the first detectable quantities of radioactivity were reported in plant effluents in June 1985.
The five indicator locations sampled included 2, 18, 32, 37 and 49. A control location near the intersection of 20th Road and Yearling Road (location
This report contains a description of the REMP conducted by Wolf Creek Nuclear Operating Corporation (WCNOC), a discussion of monitoring program results, the revisions or changes to the program, program deviations, the Interlaboratory Comparison Program and a comparison to the Radioactive Effluents Release Program. The Interlaboratory Comparison Program results, a summary of results in the Nuclear Regulatory Commission (NRC) Branch Technical Posi'Non specified format, the individual sample results, and the Land Use Census Report are included as appendices.
: 53) was also sampled. Indicator locations are shown in Figure 1 and the control location is shown in Figure 5.B. Direct Radiation Pathway Optically stimulated luminescence (OSL) dosimeters were used at 43 locations during the sample year to measure direct radiation.
I. PROGRAM DESCRIPTION Radiological environmental monitoring samples were collected according to the schedule in WCGS procedure AP 07B-004, Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program). Radiological environmental monitoring program samples were collected by the WCGS Environmental Management group and were analyzed by Environmental, Inc.
The OSLs were typically positioned roughly 3 to 4 feet above the ground in plastic thermostat boxes. Three OSLs were placed at each designated location.
Landauer, Inc. processed the environmental optically stimulated luminescence (OSL) dosimeters. Table 1 identifies the exposure pathway/sample type, number of samples/sample locations, sample collection frequency and type/frequency of analysis. Table 2 lists each sample location's distance and direction from the plant. Samples in addition to those required by the WCGS Offsite Dose Calculation Manual (ODCM) were also obtained and analyzed.
The OSLs were changed out quarterly.
The following is a description of the sampling and analysis program by individual pathways.
Transit dose was measured and subtracted from the ambient dose. Indicator OSL sample locations are illustrated in Figure 2 and control locations are shown in Figure 5. Control locations were 39 (Beto Junction) and 53 (near the intersection of 20th Road and Yearling Road).C. Waterborne Pathway All water samples were analyzed to determine whether gamma emitters were present. In addition to gamma isotopic analysis, radiochemical analysis for 1-131 was performed on drinking water and ground water samples. Gross beta analysis was also performed on drinking water samples. Tritium analysis was performed monthly by liquid scintillation for surface water and quarterly for drinking water. Tritium analysis was also performed on ground water samples. Two surface water samples from the Coffey County Lake Spillway (SP) location and two surface water samples from the John Redmond Reservoir (JRR) location were also analyzed for Fe-55. Water sampling locations are shown in Figures 3 and 5.Monthly grab samples of surface water were collected from John Redmond Reservoir (JRR) as a control location and from the SP location, which is located near the spillway of Coffey County Lake, formerly known as Wolf Creek Lake, as an indicator location.2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 2 of 32 Quarterly grab samples of ground water were collected from seven wells. Location B-12 is hydrologically up gradient from the site and was used as a control location.
2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station                                                 Page 1 of 32
Six locations (C-10, C-49, F-i, G-2, J-1 and J-2) are hydrologically down gradient from the site and were used as indicator sample locations.
 
Drinking water was sampled at the water treatment facilities for the towns of Burlington (control location BW-15) and Iola (indicator location IO-DW). The Burlington facility is located upstream and the Iola facility is located downstream of the confluence of the discharge from Coffey County Lake and the Neosho River. Composite samples were obtained monthly from automatic samplers at each location that collected approximately 27 ml. of drinking water every two hours.Shoreline sediments were sampled semiannually.
A. Airborne Pathway Low volume air sampling pumps with digital flow meters continuously collected particulate and radioiodine samples on 47 mm glass fiber filters and charcoal canisters, respectively. The filters and charcoal canisters were changed out weekly, labeled, and shipped to Environmental, Inc. for analyses.
Gamma isotopic analyses were performed on the shoreline sediment samples. Shoreline sediment sample locations were the Coffey County Lake discharge cove (DC) indicator location and the JRR control location.D. Ingestion Pathway Because no sampling locations that produce milk for human consumption were identified within five miles of the plant during the Land Use Census, milk was not collected during the sample year.Fish were sampled semiannually from the tail waters of JRR (control, Figure 4) and from Coffey County Lake (indicator, Figure 4). Gamma isotopic analyses were performed on the boneless meat portions of the fish. Several species of game fish and rough fish were sampled. Fish were also analyzed for tritium.Broadleaf vegetation samples were collected monthly when available during the growing season from four gardens. Three indicator (B-i, N-1 and Q-6) gardens (Figure 4) and one control (D-2) garden (Figure 5) were sampled. Gamma isotopic analyses were performed on all samples.Crop samples were obtained from two indicator locations (NR-D1 and NR-D2) downstream of the confluence of Wolf Creek and the Neosho River. Two crop samples were obtained from control location NR-U1. Gamma isotopic analysis was performed on each sample. Crop sample locations are identified on Figure 5.E. Additional Samples Collected (not required by ODCM)Quarterly, duplicate ground water grab samples were obtained from indicator location C-49 and were labeled L-49. These duplicate samples served as laboratory quality checks. The ground water samples were analyzed for gamma emitters, 1-131, and tritium.Bottom sediment samples were collected from indicator locations at the Coffey County Lake discharge cove (DC), Environmental Education Area (EEA), Make-Up Discharge Structure (MUDS), Ultimate Heat Sink (UHS), Essential Service Water (ESW) channel and the control location (JRR). Gamma isotopic analyses were performed on the bottom sediment samples.Samples obtained from DC, ESW and UHS were also analyzed for Fe-55. Some of the bottom sediment samples were collected as part of a cooperative sampling effort with the Kansas 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 3 of 32 Department of Health and Environment (KDHE). The sample locations are identified on Figure 3.A shoreline sediment sample was collected from indicator location EEA. Gamma isotopic analysis was performed on the sample. This sample was collected as part of a cooperative sampling effort with the KDHE. The sample location is identified on Figure 3.Aquatic vegetation was collected from indicator locations DC ALT and MUDS. Gamma isotopic analyses were performed on the aquatic vegetation samples. These samples were collected as part of a cooperative sampling effort with the KDHE. The sample locations are identified on Figure 3.Terrestrial vegetation (grass) was sampled from the MUDS indicator location.
Gross beta analyses of the air particulate filters were performed after a nominal 72-hour period to allow the radon and thoron daughter products to decay.
Gamma isotopic analyses were performed on the grass samples. These samples were collected as part of a cooperative sampling effort with the KDHE. The sample location is identified on Figure 4.Soil was sampled from the MUDS indicator location.
Weekly air particulate filters were combined into quarterly composites for each location and analyzed for gamma emitting isotopes.
Gamma isotopic analysis was performed on the soil sample. This sample was collected as part of a cooperative sampling effort with the KDHE. The sample location is identified on Figure 4.Deer were sampled from indicator locations C.36 and Q1.4. Gamma isotopic analyses and tritium analyses were performed.
Charcoal canisters were routinely counted to determine the presence or absence of 1-131.
These samples were collected as part of a cooperative sampling effort with the KDHE. The sample locations are identified on Figure 4.II. DISCUSSION OF RESULTS Analysis results for all pathways are summarized in Appendix B using the format described in Radiological Assessment Branch Technical Position, Revision 1, November 1979 (NRC Generic Letter 79-065). Results for individual samples are listed in Appendix C.In this section, results are discussed by pathway and analysis type. Monitoring results are compared with control data, preoperational values, sources of radioactivity, and effluent releases when applicable.
Positive indication of 1-131 would have resulted in analysis of each individual charcoal canister.
Trends or seasonal effects are discussed.
Air samples were collected from six locations. The five indicator locations sampled included 2, 18, 32, 37 and 49. A control location near the intersection of 20th Road and Yearling Road (location 53) was also sampled. Indicator locations are shown in Figure 1 and the control location is shown in Figure 5.
A. Airborne Pathway Chart 1 graphically illustrates weekly gross beta results for the sample year. Chart 2 represents the historical smoothed averages of indicator locations and the control locations gross beta data. Charts 1 and 2 demonstrate how closely the indicator and control locations tracked together.
B. Direct Radiation Pathway Optically stimulated luminescence (OSL) dosimeters were used at 43 locations during the sample year to measure direct radiation. The OSLs were typically positioned roughly 3 to 4 feet above the ground in plastic thermostat boxes. Three OSLs were placed at each designated location. The OSLs were changed out quarterly. Transit dose was measured and subtracted from the ambient dose. Indicator OSL sample locations are illustrated in Figure 2 and control locations are shown in Figure 5. Control locations were 39 (Beto Junction) and 53 (near the intersection of 20th Road and Yearling Road).
Chart 2 reveals a seasonal cyclic trend in which gross beta values peak in the winter months (December or January) and decrease to a low point in the spring months (May or June).This trend is expected and is attributed to seasonal meteorological changes, i.e., changes in prevailing winds and precipitation.
C. Waterborne Pathway All water samples were analyzed to determine whether gamma emitters were present. In addition to gamma isotopic analysis, radiochemical analysis for 1-131 was performed on drinking water and ground water samples. Gross beta analysis was also performed on drinking water samples. Tritium analysis was performed monthly by liquid scintillation for surface water and quarterly for drinking water. Tritium analysis was also performed on ground water samples. Two surface water samples from the Coffey County Lake Spillway (SP) location and two surface water samples from the John Redmond Reservoir (JRR) location were also analyzed for Fe-55. Water sampling locations are shown in Figures 3 and 5.
The gross beta results of 2011 were compared to pre-operational monitoring results of 1983 and 1984. The weekly gross beta analyses range for 1983 and 1984 was 0.0064 to 0.084 pCi/m3, The 2011 weekly gross beta analyses range for all indicator locations was 0.008 to 0.056 pCi/m 3 , which was within the 1983 and 1984 pre-operational range. Additionally, the annual mean for indicator locations for 2011 (0.026 pCi/m 3) was lower than the annual mean for 1983 (0.032 pCi/m 3).2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 4 of 32 The gross beta results for the indicator locations were also compared to the control location.The annual mean for indicator locations for 2011 (0.026 pCi/m 3) was slightly lower than the annual mean of the control location (0.027 pCi/m 3). The indicator location with the highest gross beta annual mean was location 49 (0.027 pCi/m 3), which was the same as the annual mean of the control location (0.027 pCi/m 3).Naturally occurring Be-7 activity was detected, as was the case during pre-operational monitoring.
Monthly grab samples of surface water were collected from John Redmond Reservoir (JRR) as a control location and from the SP location, which is located near the spillway of Coffey County Lake, formerly known as Wolf Creek Lake, as an indicator location.
In 1984, the range for Be-7 detected activity was 0.024 to 0.211 pCi/m 3 for indicator locations and the annual mean for indicator locations was 0.069 pCi/m 3.In 2011, the range for Be-7 detected activity was 0.063 to 0.118 pCi/m 3 for indicator locations and the annual mean for indicator locations was 0.080 pCi/m 3.The control location annual mean for Be-7 detected activity (0.079 pCi/m 3) was slightly lower than the annual mean of the indicator locations (0.080 pCi/m 3).1-131 activity was detected in all charcoal filter samples collected from the indicator and control locations with collection start dates of 03-21-2011 and 03-28-2011.
2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station                                                 Page 2 of 32
Since the 1-131 activity was detected in the indicator samples as well as the control samples, the atypical detection of this radionuclide is attributed to the transport of airborne releases from Dai-lchi, Fukushima following the March 11, 2011 Tohoku earthquake and is not related to the operations of the Wolf Creek Generating Station.The ODCM required lower limits of detection were met. Plant-related activation, corrosion, or fission products were not detected during 2011 in airborne particulate and radioiodine filters and no unusual trends were noted.B. Direct Radiation Pathway Quarterly OSL dosimeter results for each location are shown in Table 3. Measured values have been converted to a standardized 90-day quarter.The annual mean of all indicator locations in 2011 was 19.5 mR per standardized 90-day quarter. The annual mean of the control locations in 2011 was 20.1 mR per standardized 90-day quarter.For pre-operational comparison, in 1981, the annual mean of all indicator locations was 18.9 mR per standardized 90-day quarter and the annual mean for the control locations was 17.1 mR per standardized 90-day quarter. It should be noted that WCGS changed from thermoluminescence dosimeters (TLD) to optically stimulated luminescence (OSL) dosimeters in 2008.The indicator location with the highest annual mean was 47 (25.1 mR per standardized 90-day quarter).
 
The close proximity of location 47 to the Radwaste Building is likely the reason direct radiation levels are higher at this location.Based upon Condition Report 00027489, improvements were made in measuring and subtracting transit dose in 2010. As expected, the OSL results have increased for all locations since 2010. Chart 3 visibly displays the increase of the OSL results. Chart 3 also displays how closely the indicator and control location OSL dosimeter results are for 2011.2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 5 of 32 Chart 4 displays the TLD nearsite locations (1, 2, 7-9, 11-14, 18, 26, 27, 29, 30, 37 and 38) and the control locations (locations 39 and 48) for the preoperational years through 2007.C. Waterborne Pathway (1) Surface Water Tritium, attributable to WCGS operation, was detected in all surface water samples collected from the Coffey County Lake Spillway (SP) indicator location during 2011. The annual mean for detected tritium activity at the SP location was 12,848 pCi/L and the range was 9,847 to 15,523 pCi/L. Chart 5 illustrates the yearly averages of surface water tritium data for the spillway location.
Quarterly grab samples of ground water were collected from seven wells. Location B-12 is hydrologically up gradient from the site and was used as a control location. Six locations (C-10, C-49, F-i, G-2, J-1 and J-2) are hydrologically down gradient from the site and were used as indicator sample locations.
Chart 5 indicates that the average tritium concentration of the Coffey County Lake spillway location may have reached equilibrium.
Drinking water was sampled at the water treatment facilities for the towns of Burlington (control location BW-15) and Iola (indicator location IO-DW). The Burlington facility is located upstream and the Iola facility is located downstream of the confluence of the discharge from Coffey County Lake and the Neosho River.           Composite samples were obtained monthly from automatic samplers at each location that collected approximately 27 ml. of drinking water every two hours.
Tritium activity was not detected in samples obtained from the control location (JRR).During pre-operational radiological environmental monitoring, measured radiological activity was not detected in surface water samples.The ODCM required lower limits of detection were met. Radionuclides were not detected by the gamma isotopic analyses or by Fe-55 analyses.Tritium was the only activity detected in surface water samples and no unusual trends were noted.(2) Ground Water ODCM required lower limits of detection were met for 1-131, tritium and gamma isotopic analyses.
Shoreline sediments were sampled semiannually. Gamma isotopic analyses were performed on the shoreline sediment samples. Shoreline sediment sample locations were the Coffey County Lake discharge cove (DC) indicator location and the JRR control location.
Radioactivity was not detected in any ground water samples. No unusual trends were noted. Plant-related activation, corrosion or fission products were not detected during 2011 in ground water samples.(3) Drinking Water Gross beta activity was detected in all drinking water samples collected from the indicator location and nearly all samples collected from the control location.
D. Ingestion Pathway Because no sampling locations that produce milk for human consumption were identified within five miles of the plant during the Land Use Census, milk was not collected during the sample year.
The annual mean of the indicator location gross beta activity (2.6 pCi/L) was slightly lower when compared to the annual mean of the control location gross beta activity (2.7 pCi/L). The 2011 annual means of gross beta activity for both the indicator and control locations were lower than those of the pre-operational monitoring year of 1984. In 1984, the annual mean of the indicator location gross beta activity was 7.5 pCi/L and the annual mean of the control location gross beta activity was 6.4 pCi/L.Chart 6 illustrates the drinking water gross beta results for the last five years and how closely the gross beta results compared for the indicator and control locations.
Fish were sampled semiannually from the tail waters of JRR (control, Figure 4) and from Coffey County Lake (indicator, Figure 4). Gamma isotopic analyses were performed on the boneless meat portions of the fish. Several species of game fish and rough fish were sampled. Fish were also analyzed for tritium.
ODCM required lower limits of detection were met. Additionally, radionuclides were not detected by the 1-131, Tritium, or gamma isotopic analyses.Plant-related activation, corrosion, or fission products were not detected during 2011 in drinking water samples and no unusual trends were noted.2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 6 of 32 (4) Shoreline Sediment Naturally occurring K-40 was detected in all shoreline sediment samples collected from the DC (indicator) and JRR (control) locations.
Broadleaf vegetation samples were collected monthly when available during the growing season from four gardens. Three indicator (B-i, N-1 and Q-6) gardens (Figure 4) and one control (D-2) garden (Figure 5) were sampled. Gamma isotopic analyses were performed on all samples.
K-40 was also detected during pre-operational shoreline sediment monitoring.
Crop samples were obtained from two indicator locations (NR-D1 and NR-D2) downstream of the confluence of Wolf Creek and the Neosho River. Two crop samples were obtained from control location NR-U1. Gamma isotopic analysis was performed on each sample. Crop sample locations are identified on Figure 5.
Cs-137 activity (144.5 +/- 37.7 pCi/kg, dry) was detected in one shoreline sediment sample obtained from the DC indicator location.
E. Additional Samples Collected (not required by ODCM)
Cs-137 activity was also detected in pre-operational shoreline sediment samples. Cs-137 activity detected in shoreline sediment samples collected from the DC location from 1982 to 1984 was in the range of 224 to 437 pCi/kg, dry. The decay corrected range of pre-operational Cs-137 activity detected is approximately 121 to 236 pCi/kg, dry. The detected Cs-137 activity in the shoreline sediment sample collected at the DC indicator location in 2011 was likely due to fallout since the measured activity is within the decay corrected range of pre-operational Cs-137 detected activity and Cs-137 activity has also been detected in the past at the control location.ODCM required lower limits of detection were met. Plant-related activation, corrosion, or fission products were not detected during 2011 in shoreline sediment samples and no unusual trends were noted.D. Ingestion Pathway (1) Milk Milk was not collected during the sample year since no indicator locations within five miles of the plant were identified during the Land Use Census.(2) Fish Naturally occurring K-40 activity was detected in all fish samples obtained from the CCL indicator location and the JRR control location.
Quarterly, duplicate ground water grab samples were obtained from indicator location C-49 and were labeled L-49. These duplicate samples served as laboratory quality checks. The ground water samples were analyzed for gamma emitters, 1-131, and tritium.
K-40 activity was also detected during pre-operational fish monitoring.
Bottom sediment samples were collected from indicator locations at the Coffey County Lake discharge cove (DC), Environmental Education Area (EEA), Make-Up Discharge Structure (MUDS), Ultimate Heat Sink (UHS), Essential Service Water (ESW) channel and the control location (JRR). Gamma isotopic analyses were performed on the bottom sediment samples.
Fish samples were also analyzed for tritium. All fish samples taken from Coffey County Lake had tritium activity detected (8,230 pCi/kg annual mean). The detected tritium activity was attributable to plant operation.
Samples obtained from DC, ESW and UHS were also analyzed for Fe-55. Some of the bottom sediment samples were collected as part of a cooperative sampling effort with the Kansas 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station                                               Page 3 of 32
An adult consuming 21 kilograms of fish, at the maximum measured tritium concentration (9,461 pCi/kg), would receive a committed effective dose equivalent of 0.013 mRem.Tritium activity was not detected in the control samples collected from JRR.No other radionuclides were detected in fish during the year. The ODCM required lower limits of detection were met and no unusual trends were noted.2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 7 of 32 (3) Broadleaf Vegetation Gamma analyses of broadleaf vegetation samples obtained from indicator and control locations detected naturally occurring gamma emitters Be-7 and K-40. Be-7 and K-40 activity were also detected pre-operationally.
 
No other radionuclides were detected in broadleaf vegetation during the year. The ODCM required lower limits of detection were met and no unusual trends were noted. Plant-related activation, corrosion, or fission products were not detected during 2011 in broadleaf vegetation samples.(4) Crop Samples Gamma analysis detected naturally occurring K-40 activity to be present in all of the samples.K-40 activity was also detected during pre-operational crop monitoring.
Department of Health and Environment (KDHE).           The sample locations are identified on Figure 3.
K-40 was the only activity detected in crop samples. The ODCM required lower limits of detection were met.Plant-related activation, corrosion, or fission products were not detected during 2011 in crop samples and no unusual trends were noted.E. Additional Samples Collected (not required by ODCM)(1) Bottom Sediment Naturally occurring K-40 was detected in all of the bottom sediment samples obtained from the indicator locations and the control locations.
A shoreline sediment sample was collected from indicator location EEA. Gamma isotopic analysis was performed on the sample. This sample was collected as part of a cooperative sampling effort with the KDHE. The sample location is identified on Figure 3.
K-40 activity was also detected during pre-operational bottom sediment monitoring.
Aquatic vegetation was collected from indicator locations DC ALT and MUDS. Gamma isotopic analyses were performed on the aquatic vegetation samples. These samples were collected as part of a cooperative sampling effort with the KDHE. The sample locations are identified on Figure 3.
Cs-137 activity was detected in ten out of the seventeen samples obtained from indicator locations (range 66 to 120 pCi/kg, dry). Cs-137 activity was also detected in one sample obtained from the control location (91 pCi/kg, dry).Cs-1 37 activity was detected in pre-operational samples, and the results for 2011 indicator bottom sediment samples were within the pre-operational range. (Cs-137 activity detected in 1981 and 1982 was in the range of 79 to 953 pCi/kg. The decay corrected range of pre-operational Cs-1 37 activity detected is approximately 40 to 479 pCi/kg.)The detected Cs-1 37 activity in the samples collected from the indicator locations was likely due to fallout since the measured activity is within the decay corrected range of pre-operational Cs-1 37 detected activity and Cs-1 37 activity has also been detected in samples collected at the control location.Chart 8 plots the Cs-137 detected activity from the discharge cove indicator location and JRR control location bottom sediment samples. The detected Cs-137 activity measured from the discharge cove location reflects a decreasing trend. The Chart 8 trend line indicates that as expected, Cs-137 activity detected at the JRR control location has also been decreasing.
Terrestrial vegetation (grass) was sampled from the MUDS indicator location. Gamma isotopic analyses were performed on the grass samples. These samples were collected as part of a cooperative sampling effort with the KDHE. The sample location is identified on Figure 4.
Fe-55 activity was not detected in the fourteen samples obtained from indicator locations.
Soil was sampled from the MUDS indicator location. Gamma isotopic analysis was performed on the soil sample. This sample was collected as part of a cooperative sampling effort with the KDHE. The sample location is identified on Figure 4.
No other radionuclides were detected in bottom sediment samples.2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 8 of 32 Plant-related activation, corrosion, or fission products were not detected in bottom sediment samples and no unusual trends were noted.(3) Aquatic Vegetation Naturally occurring Be-7 and K-40 activity were detected in all aquatic vegetation samples.Be-7 and K-40 activity were also detected during pre-operational monitoring.
Deer were sampled from indicator locations C.36 and Q1.4. Gamma isotopic analyses and tritium analyses were performed. These samples were collected as part of a cooperative sampling effort with the KDHE. The sample locations are identified on Figure 4.
No other radionuclides were detected.
II. DISCUSSION OF RESULTS Analysis results for all pathways are summarized in Appendix B using the format described in Radiological Assessment Branch Technical Position, Revision 1, November 1979 (NRC Generic Letter 79-065). Results for individual samples are listed in Appendix C.
Plant-related activation, corrosion, or fission products were not detected during 2011 in aquatic vegetation samples and no unusual trends were noted.(4) Shoreline Sediment Naturally occurring K-40 activity was detected in the shoreline sediment sample obtained from the EEA indicator location.
In this section, results are discussed by pathway and analysis type. Monitoring results are compared with control data, preoperational values, sources of radioactivity, and effluent releases when applicable. Trends or seasonal effects are discussed.
K-40 activity was also detected during pre-operational monitoring.
A. Airborne Pathway Chart 1 graphically illustrates weekly gross beta results for the sample year. Chart 2 represents the historical smoothed averages of indicator locations and the control locations gross beta data. Charts 1 and 2 demonstrate how closely the indicator and control locations tracked together. Chart 2 reveals a seasonal cyclic trend in which gross beta values peak in the winter months (December or January) and decrease to a low point in the spring months (May or June).
Cs-137 activity (250.5 pCi/kg, dry) was detected in the shoreline sediment sample obtained from the EEA indicator location.
This trend is expected and is attributed to seasonal meteorological changes, i.e., changes in prevailing winds and precipitation.
Cs-137 activity was also detected in pre-operational shoreline sediment samples. Cs-137 activity detected in shoreline sediment samples collected from the DC location from 1982 to 1984 was in the range of 224 to 437 pCi/kg, dry. The decay corrected range of pre-operational Cs-137 activity detected is approximately 121 to 236 pCi/kg, dry. The detected Cs-137 activity in the shoreline sediment sample collected at the EEA indicator location in 2011 was likely due to fallout since the result is very near the pre-operational decay corrected range. Additionally, Cs-137 activity is routinely detected in soil and sediment samples collected from the control locations and this shoreline sediment sample was obtained following the release of radioactive material from the Fukushima nuclear plant after the March 11, 2011 earthquake and tsunami.No other radionuclides were detected.
The gross beta results of 2011 were compared to pre-operational monitoring results of 1983 and 1984. The weekly gross beta analyses range for 1983 and 1984 was 0.0064 to 0.084 pCi/m3, The 2011 weekly gross beta analyses range for all indicator locations was 0.008 to 0.056 pCi/m 3, which was within the 1983 and 1984 pre-operational range. Additionally, the annual mean for indicator locations for 2011 (0.026 pCi/m 3) was lower than the annual mean for 1983 (0.032 pCi/m 3).
Plant-related activation, corrosion, or fission products were not detected and no unusual trends were noted.(5) Soil Naturally occurring K-40 activity was detected in the MUDS indicator location soil sample. K-40 activity was also detected during pre-operational soil monitoring.
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The gross beta results for the indicator locations were also compared to the control location.
The annual mean for indicator locations for 2011 (0.026 pCi/m 3) was slightly lower than the annual mean of the control location (0.027 pCi/m 3). The indicator location with the highest gross beta annual mean was location 49 (0.027 pCi/m 3), which was the same as the annual mean of the control location (0.027 pCi/m 3).
Naturally occurring Be-7 activity was detected, as was the case during pre-operational monitoring. In 1984, the range for Be-7 detected activity was 0.024 to 0.211 pCi/m 3 for indicator locations and the annual mean for indicator locations was 0.069 pCi/m 3 . In 2011, the range for Be-7 detected activity was 0.063 to 0.118 pCi/m 3 for indicator locations and the annual mean for indicator locations was 0.080 pCi/m 3. The control location annual mean for Be-7 detected activity (0.079 pCi/m 3) was slightly lower than the annual mean of the indicator locations (0.080 pCi/m 3).
1-131 activity was detected in all charcoal filter samples collected from the indicator and control locations with collection start dates of 03-21-2011 and 03-28-2011. Since the 1-131 activity was detected in the indicator samples as well as the control samples, the atypical detection of this radionuclide is attributed to the transport of airborne releases from Dai-lchi, Fukushima following the March 11, 2011 Tohoku earthquake and is not related to the operations of the Wolf Creek Generating Station.
The ODCM required lower limits of detection were met. Plant-related activation, corrosion, or fission products were not detected during 2011 in airborne particulate and radioiodine filters and no unusual trends were noted.
B. Direct Radiation Pathway Quarterly OSL dosimeter results for each location are shown in Table 3. Measured values have been converted to a standardized 90-day quarter.
The annual mean of all indicator locations in 2011 was 19.5 mR per standardized 90-day quarter. The annual mean of the control locations in 2011 was 20.1 mR per standardized 90-day quarter.
For pre-operational comparison, in 1981, the annual mean of all indicator locations was 18.9 mR per standardized 90-day quarter and the annual mean for the control locations was 17.1 mR per standardized 90-day quarter.           It should be noted that WCGS changed from thermoluminescence dosimeters (TLD) to optically stimulated luminescence (OSL) dosimeters in 2008.
The indicator location with the highest annual mean was 47 (25.1 mR per standardized 90-day quarter). The close proximity of location 47 to the Radwaste Building is likely the reason direct radiation levels are higher at this location.
Based upon Condition Report 00027489, improvements were made in measuring and subtracting transit dose in 2010. As expected, the OSL results have increased for all locations since 2010. Chart 3 visibly displays the increase of the OSL results. Chart 3 also displays how closely the indicator and control location OSL dosimeter results are for 2011.
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Chart 4 displays the TLD nearsite locations (1, 2, 7-9, 11-14, 18, 26, 27, 29, 30, 37 and 38) and the control locations (locations 39 and 48) for the preoperational years through 2007.
C. Waterborne Pathway (1) Surface Water Tritium, attributable to WCGS operation, was detected in all surface water samples collected from the Coffey County Lake Spillway (SP) indicator location during 2011. The annual mean for detected tritium activity at the SP location was 12,848 pCi/L and the range was 9,847 to 15,523 pCi/L. Chart 5 illustrates the yearly averages of surface water tritium data for the spillway location. Chart 5 indicates that the average tritium concentration of the Coffey County Lake spillway location may have reached equilibrium. Tritium activity was not detected in samples obtained from the control location (JRR).
During pre-operational radiological environmental monitoring, measured radiological activity was not detected in surface water samples.
The ODCM required lower limits of detection were met. Radionuclides were not detected by the gamma isotopic analyses or by Fe-55 analyses.
Tritium was the only activity detected in surface water samples and no unusual trends were noted.
(2) Ground Water ODCM required lower limits of detection were met for 1-131, tritium and gamma isotopic analyses. Radioactivity was not detected in any ground water samples. No unusual trends were noted. Plant-related activation, corrosion or fission products were not detected during 2011 in ground water samples.
(3) Drinking Water Gross beta activity was detected in all drinking water samples collected from the indicator location and nearly all samples collected from the control location. The annual mean of the indicator location gross beta activity (2.6 pCi/L) was slightly lower when compared to the annual mean of the control location gross beta activity (2.7 pCi/L). The 2011 annual means of gross beta activity for both the indicator and control locations were lower than those of the pre-operational monitoring year of 1984. In 1984, the annual mean of the indicator location gross beta activity was 7.5 pCi/L and the annual mean of the control location gross beta activity was 6.4 pCi/L.
Chart 6 illustrates the drinking water gross beta results for the last five years and how closely the gross beta results compared for the indicator and control locations.
ODCM required lower limits of detection were met. Additionally, radionuclides were not detected by the 1-131, Tritium, or gamma isotopic analyses.
Plant-related activation, corrosion, or fission products were not detected during 2011 in drinking water samples and no unusual trends were noted.
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(4) Shoreline Sediment Naturally occurring K-40 was detected in all shoreline sediment samples collected from the DC (indicator) and JRR (control) locations. K-40 was also detected during pre-operational shoreline sediment monitoring.
Cs-137 activity (144.5 +/- 37.7 pCi/kg, dry) was detected in one shoreline sediment sample obtained from the DC indicator location. Cs-137 activity was also detected in pre-operational shoreline sediment samples. Cs-137 activity detected in shoreline sediment samples collected from the DC location from 1982 to 1984 was in the range of 224 to 437 pCi/kg, dry. The decay corrected range of pre-operational Cs-137 activity detected is approximately 121 to 236 pCi/kg, dry. The detected Cs-137 activity in the shoreline sediment sample collected at the DC indicator location in 2011 was likely due to fallout since the measured activity is within the decay corrected range of pre-operational Cs-137 detected activity and Cs-137 activity has also been detected in the past at the control location.
ODCM required lower limits of detection were met. Plant-related activation, corrosion, or fission products were not detected during 2011 in shoreline sediment samples and no unusual trends were noted.
D. Ingestion Pathway (1) Milk Milk was not collected during the sample year since no indicator locations within five miles of the plant were identified during the Land Use Census.
(2) Fish Naturally occurring K-40 activity was detected in all fish samples obtained from the CCL indicator location and the JRR control location. K-40 activity was also detected during pre-operational fish monitoring.
Fish samples were also analyzed for tritium. All fish samples taken from Coffey County Lake had tritium activity detected (8,230 pCi/kg annual mean). The detected tritium activity was attributable to plant operation. An adult consuming 21 kilograms of fish, at the maximum measured tritium concentration (9,461 pCi/kg), would receive a committed effective dose equivalent of 0.013 mRem.
Tritium activity was not detected in the control samples collected from JRR.
No other radionuclides were detected in fish during the year. The ODCM required lower limits of detection were met and no unusual trends were noted.
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(3) Broadleaf Vegetation Gamma analyses of broadleaf vegetation samples obtained from indicator and control locations detected naturally occurring gamma emitters Be-7 and K-40. Be-7 and K-40 activity were also detected pre-operationally.
No other radionuclides were detected in broadleaf vegetation during the year. The ODCM required lower limits of detection were met and no unusual trends were noted. Plant-related activation, corrosion, or fission products were not detected during 2011 in broadleaf vegetation samples.
(4) Crop Samples Gamma analysis detected naturally occurring K-40 activity to be present in all of the samples.
K-40 activity was also detected during pre-operational crop monitoring. K-40 was the only activity detected in crop samples. The ODCM required lower limits of detection were met.
Plant-related activation, corrosion, or fission products were not detected during 2011 in crop samples and no unusual trends were noted.
E. Additional Samples Collected (not required by ODCM)
(1) Bottom Sediment Naturally occurring K-40 was detected in all of the bottom sediment samples obtained from the indicator locations and the control locations. K-40 activity was also detected during pre-operational bottom sediment monitoring.
Cs-137 activity was detected in ten out of the seventeen samples obtained from indicator locations (range 66 to 120 pCi/kg, dry). Cs-137 activity was also detected in one sample obtained from the control location (91 pCi/kg, dry).
Cs-1 37 activity was detected in pre-operational samples, and the results for 2011 indicator bottom sediment samples were within the pre-operational range. (Cs-137 activity detected in 1981 and 1982 was in the range of 79 to 953 pCi/kg. The decay corrected range of pre-operational Cs-1 37 activity detected is approximately 40 to 479 pCi/kg.)
The detected Cs-1 37 activity in the samples collected from the indicator locations was likely due to fallout since the measured activity is within the decay corrected range of pre-operational Cs-1 37 detected activity and Cs-1 37 activity has also been detected in samples collected at the control location.
Chart 8 plots the Cs-137 detected activity from the discharge cove indicator location and JRR control location bottom sediment samples. The detected Cs-137 activity measured from the discharge cove location reflects a decreasing trend. The Chart 8 trend line indicates that as expected, Cs-137 activity detected at the JRR control location has also been decreasing.
Fe-55 activity was not detected in the fourteen samples obtained from indicator locations. No other radionuclides were detected in bottom sediment samples.
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Plant-related activation, corrosion, or fission products were not detected in bottom sediment samples and no unusual trends were noted.
(3) Aquatic Vegetation Naturally occurring Be-7 and K-40 activity were detected in all aquatic vegetation samples.
Be-7 and K-40 activity were also detected during pre-operational monitoring.
No other radionuclides were detected. Plant-related activation, corrosion, or fission products were not detected during 2011 in aquatic vegetation samples and no unusual trends were noted.
(4) Shoreline Sediment Naturally occurring K-40 activity was detected in the shoreline sediment sample obtained from the EEA indicator location. K-40 activity was also detected during pre-operational monitoring.
Cs-137 activity (250.5 pCi/kg, dry) was detected in the shoreline sediment sample obtained from the EEA indicator location. Cs-137 activity was also detected in pre-operational shoreline sediment samples. Cs-137 activity detected in shoreline sediment samples collected from the DC location from 1982 to 1984 was in the range of 224 to 437 pCi/kg, dry. The decay corrected range of pre-operational Cs-137 activity detected is approximately 121 to 236 pCi/kg, dry. The detected Cs-137 activity in the shoreline sediment sample collected at the EEA indicator location in 2011 was likely due to fallout since the result is very near the pre-operational decay corrected range. Additionally, Cs-137 activity is routinely detected in soil and sediment samples collected from the control locations and this shoreline sediment sample was obtained following the release of radioactive material from the Fukushima nuclear plant after the March 11, 2011 earthquake and tsunami.
No other radionuclides were detected. Plant-related activation, corrosion, or fission products were not detected and no unusual trends were noted.
(5) Soil Naturally occurring K-40 activity was detected in the MUDS indicator location soil sample. K-40 activity was also detected during pre-operational soil monitoring.
Cs-137 activity (112 pCi/kg) was also detected in the MUDS indicator location soil sample. This activity is likely due to fallout. Data was reviewed for soil samples collected pre-operationally.
Cs-137 activity (112 pCi/kg) was also detected in the MUDS indicator location soil sample. This activity is likely due to fallout. Data was reviewed for soil samples collected pre-operationally.
The detected Cs-137 activity range from February of 1985 was 255 to 2,160 pCi/kg, dry. The decay corrected range of pre-operational Cs-1 37 activity detected in soil is approximately 139 to 1,181 pCi/kg. The detected Cs-137 activity in soil sampled in 2011 is lower than the decay corrected pre-operational range.Plant-related activation, corrosion, or fission products were not detected during 2011 in this soil sample and no unusual trends were noted.2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 9 of 32 (6) Deer Naturally occurring K-40 activity was detected in the deer samples obtained from the indicator locations.
The detected Cs-137 activity range from February of 1985 was 255 to 2,160 pCi/kg, dry. The decay corrected range of pre-operational Cs-1 37 activity detected in soil is approximately 139 to 1,181 pCi/kg. The detected Cs-137 activity in soil sampled in 2011 is lower than the decay corrected pre-operational range.
Plant-related activation, corrosion, or fission products were not detected during 2011 in this soil sample and no unusual trends were noted.
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(6) Deer Naturally occurring K-40 activity was detected in the deer samples obtained from the indicator locations.
The deer samples were also analyzed for tritium. The average mean for detected tritium was 748 pCi/kg. The detected tritium activity was attributable to plant operation.
The deer samples were also analyzed for tritium. The average mean for detected tritium was 748 pCi/kg. The detected tritium activity was attributable to plant operation.
No other radionuclides were detected.
No other radionuclides were detected. No unusual trends were identified.
No unusual trends were identified.
Ill. PROGRAM REVISIONS/CHANGES Based upon Condition Report 00027489, during the second quarter of 2011, the number of dosimeters was increased from two to three per sample location and the number of transit dosimeters was increased from four to five. Additionally, the method for calculating and subtracting transit dose was revised.
Ill. PROGRAM REVISIONS/CHANGES Based upon Condition Report 00027489, during the second quarter of 2011, the number of
Based upon Condition Report 00029165, during the third quarter of 2011, quarterly Fe-55 analysis was added for surface water samples collected from John Redmond Reservoir (JRR) and the Discharge Cove (DC). Additionally, Fe-55 analysis was added for bottom sediment samples collected from the DC and the Ultimate Heat Sink (UHS).
IV. PROGRAM DEVIATIONS Air Samples The following air sample location failed to meet the requirement for "continuous sampler operation." As described in footnote (1) of procedure AP 07B-004, Offsite Dose Calculation Manual (RadiologicalEnvironmental Monitoring Program), Table 5-1, deviations are permitted from the required sampling schedule due to malfunction of sampling equipment and other legitimate reasons. Discrepancies greater than five percent between Total Military Time and Total Digital Flow Meter Time, which resulted in a loss of air sample collected, are listed in the following
c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).
c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).
d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive".
d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.
MAPEP does not provide control limits.e Result of a repeat analysis was still unacceptable.
e Result of a repeat analysis was still unacceptable. ERA crosschecks for Am-241 were acceptable, but biased low.
ERA crosschecks for Am-241 were acceptable, but biased low.Matrix spikes were prepared, ( 5.17 and 51.7 pCi/L), to verify method; results were acceptable, 4.4 and 47.5 pCi/L.Am-241 has been added to the internal spike and blank program for 2012.An error in percent recovery was found, result of recalculation, 427.3 +/- 18.8 Bq/kg dry.9 No errors found in calculation or procedure, results of reanalysis; 1.73 Bq/filter.
Matrix spikes were prepared, ( 5.17 and 51.7 pCi/L), to verify method; results were acceptable, 4.4 and 47.5 pCi/L.
h The analyses were repeated through a strontium column; mean result of triplicate analyses, 304.2 Bq/kg.The lab does not currently analyze soil for Tc-99, but is evaluating the procedure.
Am-241 has been added to the internal spike and blank program for 2012.
After consultation with Eichrom, the analysis was repeated using a matrix spike correction.
An error in percent recovery was found, result of recalculation, 427.3 +/- 18.8 Bq/kg dry.
Mean result of triplicate reanalyses; 183.3 Bq/kg.A6-3 TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result ' Result d Limits Acceptance STAP-1230 STAP-1230 STAP-1230 STAP-1230 STAP-1230 STAP-1230 STAP-1 230 STAP-1230 STAP-1230 STAP-1230 STAP-1230 STAP-1230 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 Am-241 Co-60 Cs-1 34 Cs-137 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 STAP-1231 03/21/11 Gr. Alpha STAP-1231 03/21/11 Gr. Beta STSO-1232 STSO-1232 STSO-1 232 STSO-1 232 STSO-1232 STSO-1232 STSO-1 232 STSO-1232 STSO-1232 STSO-1232 STSO-1232 STSO-1232 STSO-1232 STSO-1232 STSO-1232 STSO-1 232 STSO-1232 STSO-1232 STSO-1232 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 Ac-228 Am-241 Bi-212 Bi-214 Co-60 Cs-134 Cs-137 K-40 Mn-54 Pb-212 Pb-214 Pu-238 Pu-239/40 Sr-90 Th-234 U-233/4 U-238 Uranium Zn-65 46.0 + 1.8 401.2 +/- 12.1 268.2 +/- 24.8 345.3 +/- 24.9< 1.9 76.1 +/- 3.2 70.50 +/- 3.10 208.40 +/- 18.70 56.10 +/- 2.10 58.90 +/- 2.60 118.50 +/- 5.52 312.60 +/- 23.40 88.40 +/- 3.70 85.10 +/- 2.80 1327.8 +/- 97.5 662.8 +/- 88.1 1396.2 +/- 185.3 841.1 +/- 33.2 2423.7 +/- 27.1 2481.3 +/- 42.2 2108.2 +/- 30.2 11497.3 +/- 276.6< 17.4 994.7 +/- 30.0 918.3 +/- 42.6 1593.6 +/- 156.7 1428.9 +/- 143.4 8638.0 +/- 442.8 1350.1 +/- 180.0 748.0 +/- 94.4 909.0 +/- 104.9 1690.8 +/- 104.9 2356.2 +/- 57.1 62.5 390,0 279.0 312.0 0.0 69.0 65.5 185.0 61.5 61.0 125.0 279.0 74.3 69.5 1490.0 914.0 1400.0 725.0 2220.0 2450.0 1920.0 11500.0 0.0 1440.0 805.0 1420.0 1400.0 7590.0 962.0 972.0 962.0 1980.0 1990.0 36.6 -85.7 302.0 -487.0 182.0 -345.0 234.0 -410.0 47.4 -90.7 47.5 -85 81.4-288 38.7 -91 39.0-87 63.9-199 193.0 -386 38.5-112 42.8 -102 958.0 -2100.0 546.0 -1170.0 368.0 -2090.0 445.0 -1040.0 1620.0 -2980.0 1580.0 -2950.0 1470.0 -2490.0 8320.0 -15600.0 931.0 -2030.0 482,0 -1200.0 813.0 -2000.0 956.0 -1860.0 2740.0 -12400.0 305.0 -1830.0 616.0 -1210.0 588.0 -1220.0 1130.0 -2670.0 1580.0 -2670.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A7-1 TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result C Result d Limits Acceptance STVE-1233 STVE-1233 STVE-1233 STVE-1 233 STVE-1233 STVE-1233 STVE-1233 STVE-1233 STVE-1233 STVE-1233 STVE-1233 STVE-1233 STVE-1233 STVE-1233 STW-1234 STW-1234 STW-1234 STW-1234 STW-1234 STW-1234 STW-1234 STW-1234 STW-1234 STW-1234 STW-1234 STW-1234 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/11 03/21/ 11 03/21/ 1/t 03/21/11 Am-241 Cm-244 Co-60 Cs-134 Cs-137 K-40 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 Am-241 Co-60 Cs-134 Cs-137 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 2377.5 +/- 83.2 602.9 +/- 38.4 810.2 +/- 32.4 849.4 +/-54.5 889.9 +/- 36.3 28146.70 +/- 698.80< 19.3 3068.10 +/- 170.70 3180.00 +/- 88.90 8549.20 +/- 675.00 2418.60 +/- 142.50 2417.00 +/- 142.50 4929.80 +/- 142.50 962.40 +/- 62.50 100.0 +/- 6.4 401.6 +/- 7.2 222.7 +/- 12.3 410.3 +/- 9.5<3.0 130.9 +/- 5.5 113.0 +/-5.0 739.6 +/- 13.0 83.4 +/- 3.8 85.5 +/- 3.9 172.0 +/- 8.5 114.5 +/- 10.8 97.6 +/- 2.9 99.6 +/- 2.0 16307.0 +/- 377.0 3200.0 812.0 733.0 770.0 829.0 25800.0 0.0 2990.0 3100.0 7890.0 2610.0 2590.0 5320.0 799.0 135.0 411.0 231.0 417.0 0.0 131.0 119.0 773.0 94.3 93.5 192.0 111.0 112.0 99.8 1820.0 -4400.0 400.0 -1260.0 496.0 -1050.0 441.0 -1070.0 608.0 -1150.0 18500.0 -36500 1610.0 -4380 1920.0 -4230 4410.0 -10500 1790.0 -3460 1820.0 -3270 3660.0 -6860 577.0 -1090 92.5 -182.0 358.0 -486.0 171.0 -265.0 354.0 -500.0 99.1 -162.0 92.1 -147.0 491.0 -1030.0 71.1 -122.0 71.4 -116.0 138.0 -256.0 94.1 -138.0 49.7 -166.0 58.4 -146.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STW-1235 03/21/11 Gr. Alpha STW-1235 03/21/11 Gr. Beta STW-1236 03/21/11 H-3 15200.0 9900.0 -22500.0 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).b Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).
9 No errors found in calculation or procedure, results of reanalysis; 1.73 Bq/filter.
Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg).c Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
hThe analyses were repeated through a strontium column; mean result of triplicate analyses, 304.2 Bq/kg.
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. A known value of "zero" Indicates an analysis was included in the testing series as a "false positive".
The lab does not currently analyze soil for Tc-99, but is evaluating the procedure. After consultation with Eichrom, the analysis was repeated using a matrix spike correction. Mean result of triplicate reanalyses; 183.3 Bq/kg.
Control limits are not provided.A7-2 Appendix B Summary Tables in the format of NRC Radiological Assessment Branch Technical Position Revision 1, November 1979 Page B-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
A6-3
 
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L) b Lab Code b     Date         Analysis         Laboratory           ERA         Control Result '         Result   d     Limits         Acceptance STAP-1230     03/21/11      Am-241            46.0 + 1.8          62.5      36.6 -85.7            Pass STAP-1230     03/21/11      Co-60          401.2  +/- 12.1         390,0      302.0 -487.0          Pass STAP-1230     03/21/11     Cs-1 34        268.2  +/- 24.8        279.0      182.0 -345.0          Pass STAP-1230      03/21/11     Cs-137          345.3  +/- 24.9        312.0      234.0 - 410.0          Pass STAP-1230      03/21/11     Mn-54                  < 1.9            0.0                            Pass STAP-1230      03/21/11     Pu-238            76.1 +/- 3.2            69.0      47.4 -90.7            Pass STAP-1 230    03/21/11     Pu-239/40      70.50  +/- 3.10          65.5      47.5 -85              Pass STAP-1230      03/21/11     Sr-90          208.40  +/- 18.70        185.0      81.4-288              Pass STAP-1230      03/21/11     U-233/4        56.10  +/- 2.10          61.5      38.7 -91              Pass STAP-1230      03/21/11    U-238           58.90  +/- 2.60          61.0      39.0-87              Pass STAP-1230      03/21/11     Uranium        118.50  +/- 5.52          125.0      63.9-199              Pass STAP-1230      03/21/11     Zn-65          312.60  +/- 23.40        279.0      193.0 -386            Pass STAP-1231      03/21/11    Gr. Alpha      88.40 +/- 3.70            74.3      38.5-112              Pass STAP-1231      03/21/11    Gr. Beta        85.10 +/- 2.80            69.5      42.8 -102            Pass STSO-1232     03/21/11    Ac-228        1327.8  +/- 97.5        1490.0    958.0 -2100.0          Pass STSO-1232     03/21/11     Am-241          662.8  +/- 88.1        914.0      546.0 -1170.0          Pass STSO-1 232    03/21/11     Bi-212        1396.2  +/- 185.3        1400.0    368.0 -2090.0          Pass STSO-1 232    03/21/11     Bi-214          841.1  +/- 33.2        725.0      445.0 -1040.0          Pass STSO-1232      03/21/11     Co-60          2423.7  +/- 27.1        2220.0  1620.0  -2980.0          Pass STSO-1232      03/21/11     Cs-134        2481.3  +/- 42.2        2450.0    1580.0 -2950.0          Pass STSO-1 232    03/21/11     Cs-137        2108.2  +/- 30.2        1920.0    1470.0 - 2490.0        Pass STSO-1232      03/21/11     K-40          11497.3  +/- 276.6      11500.0    8320.0  -15600.0        Pass STSO-1232      03/21/11     Mn-54                  < 17.4            0.0                            Pass STSO-1232      03/21/11     Pb-212          994.7  +/- 30.0        1440.0    931.0 -2030.0          Pass STSO-1232      03/21/11     Pb-214          918.3  +/- 42.6        805.0      482,0 - 1200.0        Pass STSO-1232      03/21/11    Pu-238         1593.6  +/- 156.7        1420.0     813.0 -2000.0          Pass STSO-1232      03/21/11    Pu-239/40      1428.+/- 143.4        1400.0    956.0 -1860.0          Pass STSO-1232      03/21/11    Sr-90          8638.+/- 442.8        7590.0  2740.0  -12400.0        Pass STSO-1232    03/21/11      Th-234        1350.+/- 180.0        962.0      305.0 -1830.0          Pass STSO-1 232    03/21/11      U-233/4        748.+/- 94.4        972.0      616.0 - 1210.0        Pass STSO-1232    03/21/11      U-238          909.+/- 104.9        962.0      588.0 -1220.0          Pass STSO-1232    03/21/11      Uranium        1690.+/- 104.9        1980.0    1130.0 -2670.0          Pass STSO-1232    03/21/11      Zn-65          2356.2 +/- 57.1        1990.0    1580.0 -2670.0         Pass A7-1
 
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L) b Lab Code    b    Date              Analysis              Laboratory          ERA            Control Result C        Result  d        Limits            Acceptance STVE-1233          03/21/11          Am-241              2377.+/- 83.2        3200.0     1820.0   - 4400.0         Pass STVE-1233          03/21/11          Cm-244                602.9 +/- 38.4        812.0       400.0   - 1260.0         Pass STVE-1233          03/21/11          Co-60                810.2  +/- 32.4        733.0       496.0   - 1050.0         Pass STVE-1 233        03/21/11          Cs-134                849.4  +/-54.5         770.0       441.0   - 1070.0         Pass STVE-1233          03/21/11          Cs-137                889.9  +/- 36.3        829.0       608.0   - 1150.0         Pass STVE-1233          03/21/11          K-40              28146.70  +/- 698.80    25800.0     18500.0   - 36500          Pass STVE-1233          03/21/11          Mn-54                        < 19.3          0.0                                 Pass STVE-1233          03/21/11          Pu-238              3068.10 +/- 170.70      2990.0     1610.0   - 4380            Pass STVE-1233          03/21/11          Pu-239/40          3180.00 +/- 88.90        3100.0      1920.0   - 4230            Pass STVE-1233          03/21/11          Sr-90              8549.20  +/- 675.00    7890.0     4410.0   - 10500          Pass STVE-1233          03/21/11          U-233/4            2418.60  +/- 142.50    2610.0     1790.0   - 3460            Pass STVE-1233          03/21/11          U-238              2417.00  +/- 142.50    2590.0     1820.0   -3270            Pass STVE-1233          03/21/11          Uranium            4929.80  +/- 142.50    5320.0     3660.0   - 6860            Pass STVE-1233          03/21/11          Zn-65                962.40  +/-  62.50      799.0       577.0   - 1090            Pass STW-1234          03/21/11          Am-241                100.0 +/- 6.4          135.0       92.- 182.0           Pass STW-1234          03/21/11          Co-60                401.6  +/- 7.2          411.0      358.0  - 486.0          Pass STW-1234          03/21/11          Cs-134                222.7  +/- 12.3        231.0      171.0  -265.0            Pass STW-1234          03/21/11          Cs-137                410.3  +/- 9.5          417.0      354.0  - 500.0          Pass STW-1234          03/21/11          Mn-54                        <3.0            0.0                                Pass STW-1234          03/21/11          Pu-238                130.9  +/- 5.5          131.0        99.1  - 162.0          Pass STW-1234          03/21/11          Pu-239/40            113.0  +/-5.0          119.0        92.1   - 147.0          Pass STW-1234          03/21/11          Sr-90                739.6  +/- 13.0        773.0      491.0  -1030.0          Pass STW-1234           03/21/11          U-233/4                83.4 +/- 3.8          94.3        71.1  -122.0            Pass STW-1234           03/21/ 11          U-238                  85.5 +/- 3.9          93.5        71.4  -116.0            Pass STW-1234           03/21/ 1/t        Uranium              172.0  +/- 8.5          192.0      138.0 - 256.0            Pass STW-1234           03/21/11           Zn-65                114.5  +/- 10.8        111.0        94.1 - 138.0            Pass STW-1235          03/21/11           Gr. Alpha              97.6 +/- 2.9          112.0        49.7 - 166.0            Pass STW-1235          03/21/11           Gr. Beta                99.6 +/- 2.0          99.8        58.4 - 146.0            Pass STW-1236          03/21/11           H-3                16307.0 +/- 377.0      15200.0      9900.0 -22500.0            Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).
b Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg).
c Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. A known value of "zero" Indicates an analysis was included in the testing series as a "false positive". Control limits are not provided.
A7-2
 
Appendix B Summary Tables in the format of NRC Radiological Assessment Branch Technical Position Revision 1, November 1979 Page B-1
 
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
Name of Facility:
 
Wolf Creek Generating Station Docket No.: 50-482 Location of Facility:
Name of Facility: Wolf Creek Generating Station       Docket No.: 50-482 Location of Facility: Coffey County, Kansas       Reporting Period: Annual 2011 Medium of                             ODCM         All Indicator     Indicator Location with                 Control Locations Pathway         Analysis and         Lower         Locations         Highest Annual Mean                                       Number of Sampled         Total Number of       Limit of                       Name                                                       Nonroutine (Unit of         Analysis Performed   Detection     ** Mean (f)       Distance and         ** Mean (f)       ** Mean (f)       Reported Measurement)                           (LLD)         ** Range         Direction             ** Range         ** Range           Measurements **
Coffey County, Kansas Reporting Period: Annual 2011 Medium of ODCM All Indicator Indicator Location with Control Locations Pathway Analysis and Lower Locations Highest Annual Mean Number of Sampled Total Number of Limit of Name Nonroutine (Unit of Analysis Performed Detection  
Air Particulate                                                                                               Station 53 (pCi/m 3 )       Gross Beta (317)         0.01      0.026 (264/264)   49                    0.027 (53/53)     0.027 (53/53)     0 (0.008 - 0.056)   0.8 miles NNE        (0.008 - 0.049)   (0.011 - 0.052)
** Mean (f) Distance and ** Mean (f) ** Mean (f) Reported Measurement) (LLD) ** Range Direction  
Gamma (24)
** Range ** Range Measurements  
Be-7                  -        0.080 (20/20)    32                    0.087 (4/4)       0.079 (4/4)       0 (0.063 - 0.118)   3.1 miles WNW         (0.067 - 0.118)   (0.068 - 0.087)
**Air Particulate (pCi/m 3)Gross Beta (317)Gamma (24)Be-7 Air Radioiodine (pCi/m 3)Direct Radiation Dosimeters (mR per std.90-day Qtr.)Surface Water (pCi/I)0.01 0.026 (264/264)(0.008 -0.056)-0.080 (20/20)(0.063 -0.118)0.07 0.115 (10/264)(0.094 -0.131)-19.5 (164/164)(10.1 -29.5)49 0.8 miles NNE 32 3.1 miles WNW 18 3.0 miles SSE 0.027 (53/53)(0.008 -0.049)0.087 (4/4)(0.067 -0.118)0.117 (2/53)(0.103 -0.131)25.1 (4/4)(17.6 -29.5)Station 53 0.027 (53/53)(0.011 -0.052)0.079 (4/4)(0.068 -0.087)Station 53 0.131 (2/53)(0.124 -0.138)Stations 39 & 53 0 0 0 1-131 (317)Gamma Dose (172)Gamma (24)Tritium (24)47 0.16 miles S 20.1 (8/8)(16.9 -25.9)0-(0/12)N/A N/A 3,000 12,848 (12/12)(9,847 -15,523)SP 3.2 miles SSE 12,848 (12/12)(9,847 -15,523)Fe-55 (4)1-131 (32)--(0/2)1 -(0/28)Ground Water (pCi/I)N/A N/A N/A N/A N/A N/A N/A N/A JRR-(0/12)-(0/12)-(0/2)B-12-(0/4)-(0/4)-(0/4)0 0 0 0 0 0 Gamma (32)Tritium (32)-(0/28)2,000 -(0/28)Page B-2** Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)
Air Radioiodine                                                                                                Station 53 (pCi/m 3)         1-131 (317)            0.07      0.115 (10/264)   18                    0.117 (2/53)     0.131 (2/53)       0 (0.094 - 0.131)   3.0 miles SSE        (0.103 - 0.131)   (0.124 - 0.138)
Direct Radiation                                                                                              Stations 39 & 53 Dosimeters (mR per std. Gamma Dose                -        19.5 (164/164)    47                    25.1 (4/4)       20.1 (8/8)          0 90-day Qtr.)     (172)                               (10.1 - 29.5)     0.16 miles S         (17.6 - 29.5)     (16.9 - 25.9)
Surface Water                                                                                                  JRR (pCi/I)          Gamma (24)                          - (0/12)         N/A                   N/A             -  (0/12)          0 Tritium (24)            3,000       12,848 (12/12)    SP                    12,848 (12/12)   -  (0/12)          0 (9,847 - 15,523) 3.2 miles SSE         (9,847 - 15,523)
Fe-55 (4)                 -       - (0/2)           N/A                  N/A              - (0/2)           0 B-12 Ground Water (pCi/I)         1-131 (32)                1        - (0/28)          N/A                   N/A             - (0/4)           0 Gamma (32)                         - (0/28)         N/A                  N/A              - (0/4)           0 Tritium (32)           2,000      -(0/28)           N/A                  N/A              - (0/4)           0 Page B-2
** Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)
 
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
Name of Facility:
 
Wolf Creek Generating Station Docket No.: 50-482 Location of Facility:
Name of Facility: Wolf Creek Generating Station         Docket No.: 50-482 Location of Facility: Coffey County, Kansas       Reporting Period: Annual 2011 Medium of                             ODCM         All Indicator     Indicator Location with                 Control Locations Pathway         Analysis and         Lower         Locations         Highest Annual Mean                                       Number of Sampled         Total Number of       Limit of                       Name                                                       Nonroutine (Unit of         Analysis Performed   Detection     ** Mean (f)       Distance and         ** Mean (f)       ** Mean (f)       Reported Measurement)                           (LLD)         ** Range         Direction             ** Range         ** Range         Measurements **
Coffey County, Kansas Reporting Period: Annual 2011 Medium of ODCM All Indicator Indicator Location with Control Locations Pathway Analysis and Lower Locations Highest Annual Mean Number of Sampled Total Number of Limit of Name Nonroutine (Unit of Analysis Performed Detection  
Drinking                                                                                                       BW-1 5 Water           1-131 (24)                 1        -(0/12)           N/A                  N/A              - (0/12)           0 (pCi/I)
** Mean (f) Distance and ** Mean (f) ** Mean (f) Reported Measurement) (LLD) ** Range Direction  
Gross Beta (24)            4       2.6 (12/12)       IO-DW                 2.6 (12/12)       2.7 (11/12)       0 (1.9-3.9)         26.1 miles SSE        (1.9- 3.9)       (1.7- 3.5)
** Range ** Range Measurements  
Gamma (24)                         - (0/12)         N/A                   N/A               - (0/12)         0 Tritium (8)            2,000      -(0/4)           N/A                  N/A              - (0/4)           0 Shoreline       Gamma (5)                                                                                    JRR Sediment (pCi/kg dry)         K-40                           9,611 (3/3)       EEA                   10,655 (1/1)     7,928 (2/2)       0 (7,582 - 10,655)  3.0 miles NNW                          (6,479 - 9,377)
**Drinking Water (pCi/I)1-131 (24)Gross Beta (24)1 -(0/12)4 2.6 (12/12)(1.9-3.9)N/A IO-DW 26.1 miles SSE N/A BW-1 5-(0/12)2.7 (11/12)(1.7- 3.5)2.6 (12/12)(1.9- 3.9)Gamma (24)Tritium (8)Gamma (5)-(0/12)N/A N/A N/A N/A-(0/12)-(0/4)2,000 -(0/4)0 0 0 0 0 0 Shoreline Sediment (pCi/kg dry)K-40 9,611 (3/3)(7,582 -10,655)EEA 3.0 miles NNW EEA 3.0 miles NNW 10,655 (1/1)250.5 (1/1)JRR 7,928 (2/2)(6,479 -9,377)Cs-1 37 180 197.5 (2/3)(144.5 -250.5)-(0/2)Fish (pCi/kg wet)Gamma (17)JRR 3,138 (6/6)(2,319 -3,534)K-40 3,125(11/11)
Cs-1 37               180       197.5 (2/3)       EEA                  250.5 (1/1)       - (0/2)           0 (144.5 - 250.5)   3.0 miles NNW Fish            Gamma (17)                                                                                   JRR (pCi/kg wet)
(1,955 -3,538)8,230 (11/11)(7,513 -9,461)CCL 0.6 miles E to NNW CCL 0.6 miles E to NNW 3,125(11/11)
K-40                           3,125(11/11)     CCL                  3,125(11/11)     3,138 (6/6)        0 (1,955 - 3,538)   0.6 miles E to       (1,955 - 3,538)   (2,319 - 3,534)
(1,955 -3,538)8,230 (11/11)(7,513 -9,461)0 0 Tritium (17)-(0/6)Page B-3** Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)
NNW Tritium (17)                        8,230 (11/11)     CCL                  8,230 (11/11)     -(0/6)            0 (7,513 - 9,461)   0.6 miles E to        (7,513 - 9,461)
NNW Page B-3
** Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)
 
RADIOLOGICAL ENVIRONMENtAL MONITORING PROGRAM  
RADIOLOGICAL ENVIRONMENtAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
Name of Facility:
 
Wolf Creek Generating Station Docket No.: 50-482 Location of Facility:
Name of Facility: Wolf Creek Generating Station       Docket No.: 50-482 Location of Facility: Coffey County, Kansas       Reporting Period: Annual 2011 Medium of                             ODCM         All Indicator     Indicator Location with                 Control Locations Pathway         Analysis and         Lower         Locations         Highest Annual Mean                                       Number of Sampled         Total Number of       Limit of                       Name                                                       Nonroutine (Unit of         Analysis Performed   Detection     ** Mean (f)       Distance and         ** Mean (f)     ** Mean (f)       Reported Measurement)                           (LLD)         ** Range         Direction             ** Range         ** Range           Measurements **
Coffey County, Kansas Reporting Period: Annual 2011 Medium of ODCM All Indicator Indicator Location with Control Locations Pathway Analysis and Lower Locations Highest Annual Mean Number of Sampled Total Number of Limit of Name Nonroutine (Unit of Analysis Performed Detection  
Food and         Gamma (18)                                                                                    D-2 Garden (pCi/kg wet)       Be-7                             1,145 (12/12)     Q-6                  1,863 (4/4)       848 (6/6)         0 (382 - 4,453)     2.4 miles NW         (713 - 4,453)     (402 - 1,253)
** Mean (f) Distance and ** Mean (f) ** Mean (f) Reported Measurement) (LLD) ** Range Direction  
K-40                    -       4,625 (12/12)     B-1                   9,049 (1/1)     6,453 (6/6)         0 (2,562 - 9,049)  0.8 miles NNE                          (3,532 - 12,023)
** Range ** Range Measurements  
NR-U1 Crops           Gamma (4)
**Food and Garden (pCi/kg wet)Gamma (18)Be-7 K-40 1,145 (12/12)(382 -4,453)-4,625 (12/12)(2,562 -9,049)Q-6 2.4 miles NW B-1 0.8 miles NNE 1,863 (4/4)(713 -4,453)9,049 (1/1)D-2 848 (6/6)(402 -1,253)6,453 (6/6)(3,532 -12,023)0 0 NR-U1 Crops (pCi/kg wet)Bottom Sediment (pCi/kg dry)Gamma (4)K-40 14,794 (2/2)(14,440-15,148)
(pCi/kg wet)
NR-D1 8.9 miles S 15,148 (1/1)Gamma (19)7,795 (2/2)(3,379- 12,212)JRR 11,826 (2/2)(11,650 -12,002)0 K-40-10,600 (17/17)(8,906- 12,271)DC 0.8 miles WNW 11,185 (2/2)(10,099-12,271)
K-40                             14,794 (2/2)     NR-D1                 15,148 (1/1)     7,795 (2/2)       0 (14,440-15,148)  8.9 miles S                            (3,379- 12,212)
Cs-1 37 Fe-55 (14)-97 (10/17)(66-120)--(0/14)UHS 0.6 miles E 105 (6/10)(84-120)91(1/2)0 0 0 N/A N/A Page B-4** Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)
Bottom          Gamma (19)                                                                                  JRR Sediment (pCi/kg dry)
K-40                   -       10,600 (17/17)   DC                    11,185 (2/2)      11,826 (2/2)      0 (8,906- 12,271)   0.8 miles WNW         (10,099-12,271)  (11,650 - 12,002)
Cs-1 37                 -       97 (10/17)       UHS                  105 (6/10)        91(1/2)            0 (66-120)         0.6 miles E           (84-120)
Fe-55 (14)                -        -(0/14)           N/A                   N/A                                 0 Page B-4
** Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)
 
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
Name of Facility:
 
Wolf Creek Generatinq Station Docket No.: 50-482 Location of Facility:
Name of Facility: Wolf Creek Generatinq Station          Docket No.: 50-482 Location of Facility: Coffey County, Kansas      Reporting Period: Annual 2011 Medium of                            ODCM          All Indicator    Indicator Location with                Control Locations Pathway        Analysis and          Lower        Locations        Highest Annual Mean                                        Number of Sampled          Total Number of      Limit of                        Name                                                      Nonroutine (Unit of        Analysis Performed    Detection    ** Mean (f)      Distance and          ** Mean (f)      ** Mean (f)        Reported Measurement)                          (LLD)        ** Range          Direction            ** Range          ** Range          Measurements **
Coffey County, Kansas Reporting Period: Annual 2011 Medium of ODCM All Indicator Indicator Location with Control Locations Pathway Analysis and Lower Locations Highest Annual Mean Number of Sampled Total Number of Limit of Name Nonroutine (Unit of Analysis Performed Detection
Aquatic          Gamma (3)                                                                                    No Control Vegetation (pCi/kg wet)        Be-7                            1,269 (3/3)      MUDS                  1,748 (2/2)                          0 (289 - 3,208)    1.5 miles WNW        (289 - 3,208)
** Mean (f
K-40                            2,960 (3/3)      DC-ALT                3,630 (1/1)                          0 (2,612 - 3,630)  1.5 miles NW Terrestrial      Gamma (2)                                                                                    No Control Vegetation (pCi/kg wet)        Be-7                            3,765 (2/2)      MUDS                  3,765 (2


==SUMMARY==
==SUMMARY==
The 2011 Land Use Census Report has been revised to re-calculate the D/Qs for the broadleaf vegetation locations.
 
The rental property located at R2.08-NALN1650 is now vacant. The D/Qs have been re-calculated, omitting the R2.08-NALN1650 location.The annual Land Use Census of rural residents within five miles of the Wolf Creek Generating Station (WCGS) has been completed for 2011 in accordance with AP 07B-004, [Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)].
The 2011 Land Use Census Report has been revised to re-calculate the D/Qs for the broadleaf vegetation locations. The rental property located at R2.08-NALN1650 is now vacant. The D/Qs have been re-calculated, omitting the R2.08-NALN1650 location.
No program changes are necessary regarding milk locations.
The annual Land Use Census of rural residents within five miles of the Wolf Creek Generating Station (WCGS) has been completed for 2011 in accordance with AP 07B-004, [Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)].
Again, no milk sampling locations were identified.
No program changes are necessary regarding milk locations. Again, no milk sampling locations were identified.
The two broadleaf vegetation locations with the highest calculated annual average D/Q rankings are Q2.35-MILA1619 and N2.38-RODR9.
The two broadleaf vegetation locations with the highest calculated annual average D/Q rankings are Q2.35-MILA1619 and N2.38-RODR9. The landowners of these gardens have agreed to participate in the 2012 sample program.
The landowners of these gardens have agreed to participate in the 2012 sample program.BACKGROUND Section 5.2, Attachment A, of the ODCM procedure (AP 07B-004), directs that "a Land Use Census shall be conducted annually during the growing season to identify the nearest (1) milk animal, (2) residence, and (3) garden of greater than 500 square feet producing broadleaf vegetation in each of the 16 meteorological sections within five miles of the WCGS site" and"the results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report." Table 5-1, Attachment A, of the ODCM (AP 07B-004) requires that broadleaf vegetation samples be collected from "two indicator locations (using the criteria from the "Land Use Census" section) with highest calculated annual average D/Q." Table 5-1, Attachment A, of the ODCM (AP 07B-004) also requires that milk samples be collected from "three indicator locations within 5 miles of the site having the highest dose potential." METHODOLOGY Over two hundred surveys were mailed to the rural residents living within five miles of WCGS.A follow-up survey was sent to residents who did not respond. The survey excluded the residents of New Strawn, Burlington, and a trailer park north of Burlington.
BACKGROUND Section 5.2, Attachment A, of the ODCM procedure (AP 07B-004), directs that "a Land Use Census shall be conducted annually during the growing season to identify the nearest (1) milk animal, (2) residence, and (3) garden of greater than 500 square feet producing broadleaf vegetation in each of the 16 meteorological sections within five miles of the WCGS site" and "the results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report."
These locations were excluded due to the large number of households and the low likelihood that information gained from these residences would affect the locations chosen for REMP sampling.
Table 5-1, Attachment A, of the ODCM (AP 07B-004) requires that broadleaf vegetation samples be collected from "two indicator locations (using the criteria from the "Land Use Census" section) with highest calculated annual average D/Q."
Drive-by information was collected for the nearest residences that did not return surveys.The information collected was compiled and the results are identified in Tables 1-3.Calculations were performed so that garden locations could be ranked by their respective D/Q.These results are contained in Table 4.2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D -2 RESULTS NOTE: A Global Positioning System was used to verify residence distances and sectors.Three changes were noted for the nearest occupied residences in each sector. Those changes were in sectors E, F, and N.Seven location changes were noted for the nearest garden producing broadleaf vegetation.
Table 5-1, Attachment A, of the ODCM (AP 07B-004) also requires that milk samples be collected from "three indicator locations within 5 miles of the site having the highest dose potential."
These changes are identified in Table 3.There were no changes regarding milk sample locations.
METHODOLOGY Over two hundred surveys were mailed to the rural residents living within five miles of WCGS.
Again, no locations were identified that routinely milked animals for human consumption.
A follow-up survey was sent to residents who did not respond. The survey excluded the residents of New Strawn, Burlington, and a trailer park north of Burlington. These locations were excluded due to the large number of households and the low likelihood that information gained from these residences would affect the locations chosen for REMP sampling. Drive-by information was collected for the nearest residences that did not return surveys.
2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D -3 TABLE 1 2011 Land Use Census Data Location of Nearest: Sector A B C D E F G H J K L M N P Q R Residence A2.60-17TEl 520 B3.53-QURD1755 C1.92-16RD1655 D2.03-QULA1571 El.78-QULA1451 F1.84-QULA1419 G3.03-13RD1820 H3.09-12RD1711 J3.70-1 1 RD1540 K2.70-12LA1439 L2.10-NARD 1339 M2.34-14RD1330 N2.08-15RD1350 P2.76-HW751534 Q2.35-MILA1619 R2.08-NALN1650 Milkinq Animals None None None None None None None None None None None None None None None None Broadleaf Garden A4.91-OXRD1940 None C4.63-RERD1825 D2.41 -RERD 1541 None F2.39-14RD1802 G3.77-12RD1831 H3.30-QURD1 1.75 J4.00-PLRD1080 K4.10-NARD1120 None M3.10-13LA1 290 N2.38-RODR9 P2.76-HW751534 Q2.35-MILA1619 None Identifiers are based upon the following protocol: EXAMPLE: A1.4-16RD1525"A" = Sector A"1.4" = 1.4 miles from the reactor"16RD1525" = address 2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D -4 TABLE 2 SECTOR 2010 NEAREST 2011 NEAREST RESIDENCE RESIDENCE A A2.60-17TE1520 A2.60-17TE1520 B B3.53-QURD1755 B3.53-QURD1755 C C1.92-16RD1655 C1.92-16RD1655 D D2.03-QULA1571 D2.03-QULA1571 E E1.77-QULA1485 E1.78-QULA1451 F F2.28-14RD1785 F1.84-QULA1419 G G3.03-13RD1820 G3.03-13RD1820 H H3.09-12RD1711 H3.09-12RD1711 J J3.70-11RD1540 J3.70-11 RD1540 K K2.70-12LA1439 K2.70-12LA1439 L L2.10-NARD 1339 L2.10-NARD 1339 M M2.34-14RD1330 M2.34-14RD1330 N N1.71-NARD1441 N2.08-15RD1350 P P2.76-HW751534 P2.76-HW751534 Q Q2.35-MILA1619 Q2.35-MILA1619 R R4.43-NARD1891 R4.43-NARD1891 NOTE: Entries underlined indicate changes from the 2010 Land Use Census.Locations are identified based upon the following protocol: EXAMPLE: A1.4-16RD1525 First letter is based upon sector, thus "A" designates this residence is in sector A.The number immediately following the first letter designates the distance (in miles) from the reactor.The characters following the dash represent a unique identifier based upon location address.The example is in sector A, 1.4 miles from the reactor, at 1525 16th Road.2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D -5 TABLE 3 2011 Land Use Census Milk and Garden Data SECTOR 2010 2011 2010 CLOSEST 2011 CLOSEST MILKING MILKING GARDEN GARDEN ANIMALS ANIMALS PRODUCING PRODUCING BROADLEAF BROADLEAF VEGETATION VEGETATION A None None None A4.91-OXRD1940 B None None None None C None None C4.89-18RD1859 C4.63-RERD1825 D None None D3.00-16RD1829 D2.41-RERD1541 E None None None None F None None F2.44-RERD1391 F2.39-14RD1802 G None None G3.77-12RD1831 G3.77-12RD1831 H None None H3.30-QURD1175 H3.30-QURD1175 J None None J3.90-11RD1531 J4.00-PLRD1080 K None None None K4.10-NARD 1120 L None None L2.39-NARD1309 None M None None M3.10-13LA1290 M3.10-13LA1 290 N None None N2.38-RODR9 N2.38-RODR9 P None None P2.76-HW751534 P2.76-HW751534 Q None None Q2.35-MILA1619 Q2.35-MILA1619 R None None None None NOTE: Underlined entries indicate changes from the 2010 Land Use Census.Locations are identified based upon the following protocol: EXAMPLE: A1.4-16RD1525 First letter is based upon sector, thus "A" designates this residence is in sector A.The number immediately following the first letter designates the distance (in miles) from the reactor.The characters following the dash represent a unique identifier based upon location address.The example is in sector A, 1.4 miles from the reactor, at 1525 16th Road.2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Pzge D -6 TABLE 4 Information Used for D/Q Calculations FROM LAND FROM USE CENSUS SA-10-004 Eval.DIST CALC NEAR NEAR FAR FAR SECTOR SECTOR (MI) (METERS) DIST D / Q DIST D / Q CALC RANKING A 4.91 7902 7000 6.53E-10 8000 5.27E-10 5.39E-10 5 B C 4.63 7451 7000 1.66E-10 8000 1.34E-10 1.52E-10 12 D 2.41 3879 3000 4.46E-10 4000 2.67E-10 2.89E-10 11 E F 2.39 3846 3000 7.22E-10 4000 4.33E-10 4.78E-10 6 G 3.77 6067 6000 3.57E-10 7000 2.65E-10 3.51E-10 9 H 3.30 5311 5000 7.01E-10 6000 5.16E-10 6.43E-10 3 J 4.00 6437 6000 4.33E-10 7000 3.22E-10 3.84E-10 8 K 4.10 6598 6000 3.82E-10 7000 2.84E-10 3.23E-10 10 L I M 3.10 4989 4000 5.73E-10 5000 3.90E-10 3.92E-10 7 N 2.38 3830 3000 1.25E-09 4000 7.51E-10 8.36E-10 2 P 2.76 4442 4000 6.88E-10 5000 4.68E-10 5.91E-10 4 Q 2.35 3782 3000 1.53E-09 4000 9.17E-10 1.05E-09 1 R I I I Originated by: Verified by: Date: 3/13/12 Date: 3/20/12 2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D -7 WOLF CREEK GENERATING STATION 2011 LAND USE CENSUS REPORT A Prepared by: Peer Review: Teresa L. Rice Dan E. Haines 11/3/11 Date 11/3/11 Date 11/3/11 Date Approved by: Robert A. Hammond 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D -8 EXECUTIVE  
The information collected was compiled and the results are identified in Tables 1-3.
Calculations were performed so that garden locations could be ranked by their respective D/Q.
These results are contained in Table 4.
2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 2
 
RESULTS NOTE: A Global Positioning System was used to verify residence distances and sectors.
Three changes were noted for the nearest occupied residences in each sector. Those changes were in sectors E, F, and N.
Seven location changes were noted for the nearest garden producing broadleaf vegetation.
These changes are identified in Table 3.
There were no changes regarding milk sample locations. Again, no locations were identified that routinely milked animals for human consumption.
2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 3
 
TABLE 1 2011 Land Use Census Data Location of Nearest:
Sector         Residence                  Milkinq Animals Broadleaf Garden A       A2.60-17TEl 520                       None    A4.91-OXRD1940 B      B3.53-QURD1755                       None            None C        C1.92-16RD1655                       None    C4.63-RERD1825 D        D2.03-QULA1571                       None    D2.41 -RERD 1541 E        El.78-QULA1451                       None            None F        F1.84-QULA1419                       None    F2.39-14RD1802 G        G3.03-13RD1820                       None    G3.77-12RD1831 H        H3.09-12RD1711                       None    H3.30-QURD1 1.75 J        J3.70-1 1 RD1540                     None    J4.00-PLRD1080 K        K2.70-12LA1439                       None    K4.10-NARD1120 L        L2.10-NARD 1339                       None            None M        M2.34-14RD1330                       None    M3.10-13LA1 290 N        N2.08-15RD1350                       None      N2.38-RODR9 P      P2.76-HW751534                        None    P2.76-HW751534 Q        Q2.35-MILA1619                       None    Q2.35-MILA1619 R        R2.08-NALN1650                       None           None Identifiers are based upon the following protocol:
EXAMPLE: A1.4-16RD1525 "A" = Sector A "1.4" = 1.4 miles from the reactor "16RD1525" = address 2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D -4
 
TABLE 2 SECTOR                2010 NEAREST            2011 NEAREST RESIDENCE                RESIDENCE A                A2.60-17TE1520            A2.60-17TE1520 B                B3.53-QURD1755          B3.53-QURD1755 C                C1.92-16RD1655            C1.92-16RD1655 D                D2.03-QULA1571            D2.03-QULA1571 E                E1.77-QULA1485            E1.78-QULA1451 F                F2.28-14RD1785            F1.84-QULA1419 G                G3.03-13RD1820            G3.03-13RD1820 H                H3.09-12RD1711            H3.09-12RD1711 J                J3.70-11RD1540            J3.70-11 RD1540 K                K2.70-12LA1439            K2.70-12LA1439 L                L2.10-NARD 1339          L2.10-NARD 1339 M                M2.34-14RD1330            M2.34-14RD1330 N                N1.71-NARD1441            N2.08-15RD1350 P                P2.76-HW751534            P2.76-HW751534 Q                Q2.35-MILA1619            Q2.35-MILA1619 R                R4.43-NARD1891          R4.43-NARD1891 NOTE: Entries underlined indicate changes from the 2010 Land Use Census.
Locations are identified based upon the following protocol:
EXAMPLE: A1.4-16RD1525 First letter is based upon sector, thus "A" designates this residence is in sector A.
The number immediately following the first letter designates the distance (in miles) from the reactor.
The characters following the dash represent a unique identifier based upon location address.
The example is in sector A, 1.4 miles from the reactor, at 1525 16th Road.
2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 5
 
TABLE 3 2011 Land Use Census Milk and Garden Data SECTOR        2010          2011        2010 CLOSEST          2011 CLOSEST MILKING      MILKING          GARDEN                GARDEN ANIMALS      ANIMALS        PRODUCING              PRODUCING BROADLEAF              BROADLEAF VEGETATION            VEGETATION A         None          None              None            A4.91-OXRD1940 B        None          None              None                  None C        None          None        C4.89-18RD1859        C4.63-RERD1825 D        None          None        D3.00-16RD1829        D2.41-RERD1541 E        None          None            None                  None F        None          None      F2.44-RERD1391        F2.39-14RD1802 G        None          None      G3.77-12RD1831        G3.77-12RD1831 H        None           None     H3.30-QURD1175        H3.30-QURD1175 J        None           None       J3.90-11RD1531        J4.00-PLRD1080 K        None           None             None            K4.10-NARD 1120 L        None          None      L2.39-NARD1309              None M        None         None       M3.10-13LA1290        M3.10-13LA1 290 N        None         None         N2.38-RODR9            N2.38-RODR9 P        None         None       P2.76-HW751534        P2.76-HW751534 Q        None           None       Q2.35-MILA1619        Q2.35-MILA1619 R        None           None             None                   None NOTE: Underlined entries indicate changes from the 2010 Land Use Census.
Locations are identified based upon the following protocol:
EXAMPLE: A1.4-16RD1525 First letter is based upon sector, thus "A" designates this residence is in sector A.
The number immediately following the first letter designates the distance (in miles) from the reactor.
The characters following the dash represent a unique identifier based upon location address.
The example is in sector A, 1.4 miles from the reactor, at 1525 16th Road.
2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Pzge D -6
 
TABLE 4 Information Used for D/Q Calculations FROM LAND                      FROM USE CENSUS                  SA-10-004 Eval.
DIST  CALC      NEAR NEAR          FAR    FAR              SECTOR SECTOR (MI) (METERS) DIST              D/Q      DIST    D/Q      CALC RANKING A      4.91  7902      7000 6.53E-10    8000  5.27E-10 5.39E-10      5 B
C      4.63  7451      7000 1.66E-10    8000  1.34E-10 1.52E-10    12 D      2.41  3879      3000 4.46E-10    4000  2.67E-10 2.89E-10    11 E
F      2.39  3846      3000 7.22E-10     4000 4.33E-10 4.78E-10      6 G        3.77  6067      6000 3.57E-10     7000 2.65E-10 3.51E-10       9 H      3.30  5311      5000 7.01E-10     6000 5.16E-10 6.43E-10       3 J      4.00  6437      6000 4.33E-10     7000 3.22E-10 3.84E-10       8 K      4.10   6598      6000 3.82E-10     7000 2.84E-10 3.23E-10     10 L                                              I M        3.10  4989      4000  5.73E-10   5000 3.90E-10 3.92E-10       7 N      2.38  3830      3000  1.25E-09  4000 7.51E-10 8.36E-10       2 P      2.76  4442      4000 6.88E-10   5000 4.68E-10 5.91E-10       4 Q        2.35  3782      3000   1.53E-09   4000 9.17E-10 1.05E-09      1 R                            I          I      I Originated by:                                              Date:      3/13/12 Verified by:                                            Date:      3/20/12 2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 7
 
WOLF CREEK GENERATING STATION 2011 LAND USE CENSUS REPORT A
Prepared by:
11/3/11 Teresa L. Rice          Date Peer Review:
11/3/11 Dan E. Haines            Date Approved by:
11/3/11 Robert A. Hammond          Date 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 8
 
EXECUTIVE  


==SUMMARY==
==SUMMARY==
The annual Land Use Census of rural residents within five miles of the Wolf Creek Generating Station (WCGS) has been completed for 2011 in accordance with AP 07B-004, [Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)].
The annual Land Use Census of rural residents within five miles of the Wolf Creek Generating Station (WCGS) has been completed for 2011 in accordance with AP 07B-004, [Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)].
No program changes are necessary regarding milk locations.
No program changes are necessary regarding milk locations. Again, no milk sampling locations were identified.
Again, no milk sampling locations were identified.
Changes may be necessary for the Radiological Environmental Monitoring Program (REMP) broadleaf vegetation sample locations for 2012. The two broadleaf vegetation locations with the highest calculated annual average D/Q rankings are R2.08-NALN1650 and Q2.35-MILA1619. AP 07B-004 specifies that an "alternate location may be used to provide continued monitoring". The third-ranked garden is N2.38-RODR9. Prior to the 2012 growing season the residents should be contacted and based upon their cooperation, the program should be changed accordingly.
Changes may be necessary for the Radiological Environmental Monitoring Program (REMP)broadleaf vegetation sample locations for 2012. The two broadleaf vegetation locations with the highest calculated annual average D/Q rankings are R2.08-NALN1650 and Q2.35-MILA1619.
BACKGROUND Section 5.2, Attachment A, of the ODCM procedure (AP 07B-004), directs that "a Land Use Census shall be conducted annually during the growing season to identify the nearest (1) milk animal, (2) residence, and (3) garden of greater than 500 square feet producing broadleaf vegetation in each of the 16 meteorological sections within five miles of the WCGS site" and "the results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report."
AP 07B-004 specifies that an "alternate location may be used to provide continued monitoring".
Table 5-1, Attachment A, of the ODCM (AP 07B-004) requires that broadleaf vegetation samples be collected from "two indicator locations (using the criteria from the "Land Use Census" section) with highest calculated annual average D/Q."
The third-ranked garden is N2.38-RODR9.
Table 5-1, Attachment A, of the ODCM (AP 07B-004) also requires that milk samples be collected from "three indicator locations within 5 miles of the site having the highest dose potential."
Prior to the 2012 growing season the residents should be contacted and based upon their cooperation, the program should be changed accordingly.
METHODOLOGY Over two hundred surveys were mailed to the rural residents living within five miles of WCGS.
BACKGROUND Section 5.2, Attachment A, of the ODCM procedure (AP 07B-004), directs that "a Land Use Census shall be conducted annually during the growing season to identify the nearest (1) milk animal, (2) residence, and (3) garden of greater than 500 square feet producing broadleaf vegetation in each of the 16 meteorological sections within five miles of the WCGS site" and"the results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report." Table 5-1, Attachment A, of the ODCM (AP 07B-004) requires that broadleaf vegetation samples be collected from "two indicator locations (using the criteria from the "Land Use Census" section) with highest calculated annual average D/Q." Table 5-1, Attachment A, of the ODCM (AP 07B-004) also requires that milk samples be collected from "three indicator locations within 5 miles of the site having the highest dose potential." METHODOLOGY Over two hundred surveys were mailed to the rural residents living within five miles of WCGS.A follow-up survey was sent to residents who did not respond. The survey excluded the residents of New Strawn, Burlington, and a trailer park north of Burlington.
A follow-up survey was sent to residents who did not respond. The survey excluded the residents of New Strawn, Burlington, and a trailer park north of Burlington. These locations were excluded due to the large number of households and the low likelihood that information gained from these residences would affect the locations chosen for REMP sampling. Drive-by information was collected for the nearest residences that did not return surveys.
These locations were excluded due to the large number of households and the low likelihood that information gained from these residences would affect the locations chosen for REMP sampling.
The information collected was compiled and the results are identified in Tables 1-3.
Drive-by information was collected for the nearest residences that did not return surveys.The information collected was compiled and the results are identified in Tables 1-3.Calculations were performed so that garden locations could be ranked by their respective D/Q.These results are contained in Table 4.2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D -9 RESULTS NOTE: A Global Positioning System was used to verify residence distances and sectors.Four changes were noted for the nearest occupied residences in each sector. Those changes were in sectors E, F, N, and R.Seven location changes were noted for the nearest garden producing broadleaf vegetation.
Calculations were performed so that garden locations could be ranked by their respective D/Q.
These changes are identified in Table 3.There were no changes regarding milk sample locations.
These results are contained in Table 4.
Again, no locations were identified that routinely milked animals for human consumption.
2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 9
2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D -10 TABLE I 2011 Land Use Census Data Location of Nearest: Sector A B C D E F G H J K L M N P Q R Residence A2.60-17TE1520 B3.53-QURD1755 C1.92-16RD1655 D2.03-QULA1571 El.78-QULA1451 Fl.84-QULA1419 G3.03-13RD1820 H3.09-12RD1711 J3.70-1 1 RD1540 K2.70-12LA1 439 L2.10-NARD 1339 M2.34-14RD1330 N2.08-15RD1350 P2.76-HW751534 Q2.35-MILA1619 R2.08-NALN 1650 Milking Animals None None None None None None None None None None None None None None None None Broadleaf Garden A4.91 -OXRD1940 None C4.63-RERD1825 D2.41 -RERD 1541 None F2.39-14RD1802 G3.77-12RD1831 H3.30-QURD1 175 J4.00-PLRD1080 K4.10-NARD1120 None M3.10-13LA1290 N2.38-RODR9 P2.76-HW751534 Q2.35-MILA1619 R2.08-NALN1650 Identifiers are based upon the following protocol: EXAMPLE: A1.4-16RD1525"A" = Sector A"1.4" = 1.4 miles from the reactor"16RD1525" = address 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D- 11 TABLE 2 SECTOR 2010 NEAREST 2011 NEAREST RESIDENCE RESIDENCE A A2.60-17TE1520 A2.60-17TE1520 B B3.53-QURD1755 B3.53-QURD1755 C C1.92-16RD1655 C1.92-16RD1655 D D2.03-QULA1571 D2.03-QULA1571 E E1.77-QULA1485 E1.78-QULA1451 F F2.28-14RD1785 F1.84-QULA1419 G G3.03-13RD1820 G3.03-13RD1820 H H3.09-12RD1711 H3.09-12RD1711 J J3.70-11RD1540 J3.70-11RD1540 K K2.70-12LA1439 K2.70-12LA1439 L L2.10-NARD1339 L2.10-NARD1339 M M2.34-14RD1330 M2.34-14RD1330 N N1.71-NARD1441 N2.08-15RD1350 P P2.76-HW751534 P2.76-HW751534 Q Q2.35-MILA1619 Q2.35-MILA1619 R R4.43-NARD1891 R2.08-NALN1650 NOTE: Entries underlined indicate changes from the 2010 Land Use Census.Locations are identified based upon the following protocol: EXAMPLE: A1.4-16RD1525 First letter is based upon sector, thus "A" designates this residence is in sector A.The number immediately following the first letter designates the distance (in miles) from the reactor.The characters following the dash represent a unique identifier based upon location address.The example is in sector A, 1.4 miles from the reactor, at 1525 16th Road.2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D -12 TABLE 3 2011 Land Use Census Milk and Garden Data SECTOR 2010 2011 2010 CLOSEST 2011 CLOSEST MILKING MILKING GARDEN GARDEN ANIMALS ANIMALS PRODUCING PRODUCING BROADLEAF BROADLEAF VEGETATION VEGETATION A None None None A4.91-OXRD1940 B None None None None C None None C4.89-18RD1859 C4.63-RERD1825 D None None D3.00-16RD1829 D2.41-RERD1541 E None None None None F None None F2.44-RERD1391 F2.39-14RD1802 G None None G3.77-12RD1831 G3.77-12RD1831 H None None H3.30-QURD 1175 H3.30-QURD 1175 J None None J3.90-11RD1531 J4.00-PLRD1080 K None None None K4.10-NARD1120 L None None L2.39-NARD1309 None M None None M3.10-13LA1290 M3.10-13LA1290 N None None N2.38-RODR9 N2.38-RODR9 P None None P2.76-HW751534 P2.76-HW751534 Q None None Q2.35-MILA1619 Q2.35-MILA1619 R None None None R2.08-NALN1650 NOTE: Underlined entries indicate changes from the 2010 Land Use Census.Locations are identified based upon the following protocol: EXAMPLE: A1.4-16RD1525 First letter is based upon sector, thus "A" designates this residence is in sector A.The number immediately following the first letter designates the distance (in miles) from the reactor.The characters following the dash represent a unique identifier based upon location address.The example is in sector A, 1.4 miles from the reactor, at 1525 16th Road.2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D -13 TABLE 4 Information Used for D/Q Calculations FROM LAND FROM USE CENSUS SA-10-004 Eval.DIST CALC NEAR NEAR FAR FAR SECTOR SECTOR (MI) (METERS) DIST D / Q DIST D / Q CALC RANKING A 4.91 7902 7000 6.53E-10 8000 5.27E-10 5.39E-10 6 C 4.63 7451 7000 1.66E-10 8000 1.34E-10 1.52E-10 13 D 2.41 3879 3000 4.46E-10 4000 2.67E-10 2.89E-10 12 E F 2.39 3846 3000 7.22E-10 4000 4.33E-10 4.78E-10 7 G 3.77 6067 6000 3.57E-10 7000 2.65E-10 3.51E-10 10 H 3.30 5311 5000 7.01E-10 6000 5.16E-10 6.43E-10 4 J 4.00 6437 6000 4.33E-10 7000 3.22E-10 3.84E-10 9 K 4.10 6598 6000 3.82E-10 7000 2.84E-10 3.23E-10 11 L M 3.10 4989 4000 5.73E-10 5000 3.90E-10 3.92E-10 8 N 2.38 3830 3000 1.25E-09 4000 7.51E-10 8.36E-10 3 P 2.76 4442 4000 6.88E-10 5000 4.68E-10 5.91E-10 5 Q 2.35 3782 3000 1.53E-09 4000 9.17E-10 1.05E-09 2 R 2.08 3347 3000 2.61E-09 4000 1.57E-09 2.25E-09 1 Originated by: Verified by: Date: 11/03/11 Date: 11/3/11 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D -14 Enclosure to Letter RA 12-0053 Corrected pages from 2009 and 2010 reports (3 pages)
 
A. Airborne Pathway Low volume air sampling pumps with digital flow meters continuously collected particulate and radioiodine samples on 47 mm glass fiber filters and charcoal canisters, respectively.
RESULTS NOTE: A Global Positioning System was used to verify residence distances and sectors.
The filters and charcoal canisters were changed out weekly, labeled, and shipped to Environmental, Inc. for analyses.Gross beta analyses of the air particulate filters were performed after a nominal 72-hour period to allow the radon and thoron daughter products to decay.Weekly air particulate filters were combined into quarterly composites for each location and analyzed for gamma emitting isotopes.Charcoal canisters were routinely counted to determine the presence or absence of 1-131.Positive indication of 1-131 would have resulted in analysis of each individual charcoal canister.Air samples were collected from six locations.
Four changes were noted for the nearest occupied residences in each sector. Those changes were in sectors E, F, N, and R.
Indicator locations 2, 37 and 18 are located in the three sectors with the highest ground level deposition constants (D/Q). Air sampling stations are also located in the community of New Strawn (indicator location 32) and a control location near the intersection of 20th Road and Yearling Road (location 53). Supplemental indicator location (location
Seven location changes were noted for the nearest garden producing broadleaf vegetation.
: 49) was also sampled during the year. Indicator locations are shown in Figure 1 and the control location is shown in Figure 5.B. Direct Radiation Pathway Optically stimulated luminescence (OSL) dosimeters were used at 44 locations during the sample year to measure direct radiation.
These changes are identified in Table 3.
The OSLs were typically positioned roughly 3 to 4 feet above the ground in plastic thermostat boxes. Two OSLs were placed at each designated location.
There were no changes regarding milk sample locations. Again, no locations were identified that routinely milked animals for human consumption.
The OSLs were changed out quarterly.
2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 10
Transit dose was measured and subtracted from the ambient dose. Indicator OSL sample locations are illustrated in Figure 2 and control locations are shown in Figure 5. Control locations were 39 (Beto Junction), 48 (Harris) and 53 (near the intersection of 2 0 th Road and Yearling Road).C. Waterborne Pathway All water samples were analyzed to determine whether gamma emitters were present. In addition to gamma isotopic analysis, radiochemical analysis for 1-131 was performed on drinking water and ground water samples. Gross beta analysis was also performed on drinking water samples. Tritium analysis was performed monthly by liquid scintillation for surface water and quarterly for drinking water. Tritium analysis was also performed on ground water samples. Water sampling locations are shown in Figures 3 and 5.Monthly grab samples of surface water were collected from John Redmond Reservoir (JRR) as a control location and from the "SP" location, which is located near the spillway of Coffey County Lake, formerly known as Wolf Creek Lake, as an indicator location.Quarterly grab samples of ground water were collected from seven wells. Location B-12 is hydrologically up gradient from the site and was used as a control location.
 
Six locations (C-10, C-49, F-1, G-2, J-1 and J-2) are hydrologically down gradient from the site and were used as indicator sample locations.
TABLE I 2011 Land Use Census Data Location of Nearest:
2009 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 2 of 32 A. Airborne Pathway Low volume air sampling pumps with digital flow meters continuously collected particulate and radioiodine samples on 47 mm glass fiber filters and charcoal canisters, respectively.
Sector         Residence                  Milking Animals Broadleaf Garden A         A2.60-17TE1520                      None      A4.91 -OXRD1940 B      B3.53-QURD1755                       None            None C        C1.92-16RD1655                       None      C4.63-RERD1825 D      D2.03-QULA1571                       None      D2.41 -RERD 1541 E        El.78-QULA1451                       None            None F        Fl.84-QULA1419                       None      F2.39-14RD1802 G        G3.03-13RD1820                       None      G3.77-12RD1831 H        H3.09-12RD1711                       None      H3.30-QURD1 175 J        J3.70-1 1RD1540                      None      J4.00-PLRD1080 K        K2.70-12LA1 439                     None      K4.10-NARD1120 L        L2.10-NARD 1339                     None            None M        M2.34-14RD1330                       None      M3.10-13LA1290 N        N2.08-15RD1350                       None        N2.38-RODR9 P      P2.76-HW751534                        None      P2.76-HW751534 Q        Q2.35-MILA1619                       None      Q2.35-MILA1619 R        R2.08-NALN 1650                     None     R2.08-NALN1650 Identifiers are based upon the following protocol:
The filters and charcoal canisters were changed out weekly, labeled, and shipped to Environmental, Inc. for analyses.Gross beta analyses of the air particulate filters were performed after a nominal 72-hour period to allow the radon and thoron daughter products to decay.Weekly air particulate filters were combined into quarterly composites for each location and analyzed for gamma emitting isotopes.Charcoal canisters were routinely counted to determine the presence or absence of 1-131.Positive indication of 1-131 would have resulted in analysis of each individual charcoal canister.Air samples were collected from six locations.
EXAMPLE: A1.4-16RD1525 "A" = Sector A "1.4" = 1.4 miles from the reactor "16RD1525" = address 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D- 11
Indicator locations 2, 37, and 18 are located in the three sectors with the highest ground level deposition constants (D/Q). Air sampling stations are also located in the community of New Strawn (indicator location 32) and a control location near the intersection of 2 0 th Road and Yearling Road (location 53). Supplemental indicator location (location
 
: 49) was also sampled during the year. Indicator locations are shown in Figure 1 and the control location is shown in Figure 5.B. Direct Radiation Pathway Optically stimulated luminescence (OSL) dosimeters were used at 44 locations during the sample year to measure direct radiation.
TABLE 2 SECTOR                2010 NEAREST            2011 NEAREST RESIDENCE                RESIDENCE A                A2.60-17TE1520            A2.60-17TE1520 B                B3.53-QURD1755          B3.53-QURD1755 C                C1.92-16RD1655            C1.92-16RD1655 D                D2.03-QULA1571            D2.03-QULA1571 E                E1.77-QULA1485            E1.78-QULA1451 F                F2.28-14RD1785            F1.84-QULA1419 G                G3.03-13RD1820            G3.03-13RD1820 H                H3.09-12RD1711            H3.09-12RD1711 J                J3.70-11RD1540            J3.70-11RD1540 K                K2.70-12LA1439            K2.70-12LA1439 L                L2.10-NARD1339            L2.10-NARD1339 M                M2.34-14RD1330            M2.34-14RD1330 N                N1.71-NARD1441            N2.08-15RD1350 P                P2.76-HW751534            P2.76-HW751534 Q                Q2.35-MILA1619            Q2.35-MILA1619 R                R4.43-NARD1891            R2.08-NALN1650 NOTE: Entries underlined indicate changes from the 2010 Land Use Census.
The OSLs were typically positioned roughly 3 to 4 feet above the ground in plastic thermostat boxes. Two OSLs were placed at each designated location.
Locations are identified based upon the following protocol:
The OSLs were changed out quarterly.
EXAMPLE: A1.4-16RD1525 First letter is based upon sector, thus "A" designates this residence is in sector A.
Transit dose was measured and subtracted from the ambient dose. Indicator OSL sample locations are illustrated in Figure 2 and control locations are shown in Figure 5. Control locations were 39 (Beto Junction), 48 (Harris) and 53 (near the intersection of 2 0 th Road and Yearling Road).C. Waterborne Pathway All water samples were analyzed to determine whether gamma emitters were present. In addition to gamma isotopic analysis, radiochemical analysis for 1-131 was performed on drinking water and ground water samples. Gross beta analysis was also performed on drinking water samples. Tritium analysis was performed monthly by liquid scintillation for surface water and quarterly for drinking water. Tritium analysis was also performed on ground water samples. One surface water sample from the SP location was also analyzed for Fe-55. Water sampling locations are shown in Figures 3 and 5.Monthly grab samples of surface water were collected from John Redmond Reservoir (JRR) as a control location and from the "SP" location, which is located near the spillway of Coffey County Lake, formerly known as Wolf Creek Lake, as an indicator location.2010 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 2 of 32 TABLE 2 (Cont.)SAMPLE LOCATION IDENTIFIERS, DISTANCES (Miles) AND DIRECTIONS (Sectors)Sample Type Location Distance from Direction Sector Identifier Reactor Dosimeters 46 1.6 WNW P 47 0.16 S J 48 14.7 ENE D 49 0.8 NNE B 50 3.6 ENE D 51 4.0 S J 52 3.6 SW L 53 10.8 ENE D Surface Water JRR 3.7 W N SP 3.2 SSE H Ground Water B-12 1.9 NNE B C-10 2.7 W N C-49/L-49 2.8 SW L F-1 2.5 ESE F G-2 3.6 SE G J-1 3.8 S J J-2 4.3 S J Drinking Water BW-15 3.9 SW L 1O-DW 26.1 SSE H Shoreline Sediment DC 0.8 WNW P EEA 3.0 NNW R JRR 3.6 W N Fish CCL 0.6 E to NNW E to R JRR 3.7 W N Food/Garden D-2 14.8 ENE D H-2 3.0 SSE H N-1 2.4 W N Q-6 2.4 NW Q Crops NR-D1 8.9 S J NR-D2 11.5 S J NR-U1 4.0 SSW K Bottom Sediment DC 0.9 WNW P JRR 3.7 W N MUDS 1.5 WNW P UHS 0.6 E E Aquatic Vegetation DC ALT 1.5 NW Q EEA 3.0 NNW R Soil EEA 3.0 NNW R MUDS 1.5 WNW P Meat (Alligator)
The number immediately following the first letter designates the distance (in miles) from the reactor.
CCL 1.5 WNW P Meat (Deer) R2.5 2.5 NNW R 2010 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 18 of 32}}
The characters following the dash represent a unique identifier based upon location address.
The example is in sector A, 1.4 miles from the reactor, at 1525 16th Road.
2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 12
 
TABLE 3 2011 Land Use Census Milk and Garden Data SECTOR        2010          2011      2010 CLOSEST            2011 CLOSEST MILKING      MILKING          GARDEN                GARDEN ANIMALS      ANIMALS        PRODUCING              PRODUCING BROADLEAF              BROADLEAF VEGETATION              VEGETATION A         None          None              None            A4.91-OXRD1940 B        None          None              None                  None C        None          None        C4.89-18RD1859        C4.63-RERD1825 D        None          None        D3.00-16RD1829        D2.41-RERD1541 E        None          None              None                  None F        None          None        F2.44-RERD1391        F2.39-14RD1802 G        None         None       G3.77-12RD1831        G3.77-12RD1831 H        None         None       H3.30-QURD 1175        H3.30-QURD 1175 J        None         None       J3.90-11RD1531        J4.00-PLRD1080 K        None           None             None           K4.10-NARD1120 L        None           None       L2.39-NARD1309              None M        None           None       M3.10-13LA1290        M3.10-13LA1290 N        None           None       N2.38-RODR9            N2.38-RODR9 P        None           None       P2.76-HW751534        P2.76-HW751534 Q        None           None       Q2.35-MILA1619        Q2.35-MILA1619 R        None           None             None           R2.08-NALN1650 NOTE: Underlined entries indicate changes from the 2010 Land Use Census.
Locations are identified based upon the following protocol:
EXAMPLE: A1.4-16RD1525 First letter is based upon sector, thus "A" designates this residence is in sector A.
The number immediately following the first letter designates the distance (in miles) from the reactor.
The characters following the dash represent a unique identifier based upon location address.
The example is in sector A, 1.4 miles from the reactor, at 1525 16th Road.
2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 13
 
TABLE 4 Information Used for D/Q Calculations FROM LAND                      FROM USE CENSUS                  SA-10-004 Eval.
DIST  CALC      NEAR NEAR        FAR    FAR                SECTOR SECTOR (MI) (METERS) DIST            D/Q    DIST    D /Q    CALC RANKING A     4.91  7902      7000 6.53E-10 8000    5.27E-10 5.39E-10      6 C      4.63  7451      7000 1.66E-10 8000    1.34E-10 1.52E-10      13 D      2.41  3879      3000 4.46E-10 4000    2.67E-10 2.89E-10       12 E
F      2.39    3846      3000  7.22E-10 4000 4.33E-10 4.78E-10         7 G      3.77  6067      6000  3.57E-10 7000 2.65E-10 3.51E-10       10 H      3.30  5311      5000  7.01E-10 6000 5.16E-10 6.43E-10       4 J      4.00  6437      6000 4.33E-10 7000 3.22E-10 3.84E-10         9 K      4.10   6598      6000  3.82E-10 7000 2.84E-10 3.23E-10       11 L
M      3.10  4989      4000 5.73E-10   5000  3.90E-10 3.92E-10       8 N      2.38  3830      3000 1.25E-09  4000  7.51E-10 8.36E-10       3 P      2.76  4442      4000 6.88E-10   5000 4.68E-10 5.91E-10       5 Q      2.35  3782      3000 1.53E-09   4000 9.17E-10 1.05E-09      2 R      2.08  3347      3000 2.61E-09   4000 1.57E-09 2.25E-09       1 Originated by:                                           Date:       11/03/11 Verified by:                                          Date:       11/3/11 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 14
 
Enclosure to Letter RA 12-0053 Corrected pages from 2009 and 2010 reports (3 pages)
 
A. Airborne Pathway Low volume air sampling pumps with digital flow meters continuously collected particulate and radioiodine samples on 47 mm glass fiber filters and charcoal canisters, respectively. The filters and charcoal canisters were changed out weekly, labeled, and shipped to Environmental, Inc. for analyses.
Gross beta analyses of the air particulate filters were performed after a nominal 72-hour period to allow the radon and thoron daughter products to decay.
Weekly air particulate filters were combined into quarterly composites for each location and analyzed for gamma emitting isotopes.
Charcoal canisters were routinely counted to determine the presence or absence of 1-131.
Positive indication of 1-131 would have resulted in analysis of each individual charcoal canister.
Air samples were collected from six locations. Indicator locations 2, 37 and 18 are located in the three sectors with the highest ground level deposition constants (D/Q). Air sampling stations are also located in the community of New Strawn (indicator location 32) and a control location near the intersection of 20th Road and Yearling Road (location 53). Supplemental indicator location (location 49) was also sampled during the year. Indicator locations are shown in Figure 1 and the control location is shown in Figure 5.
B. Direct Radiation Pathway Optically stimulated luminescence (OSL) dosimeters were used at 44 locations during the sample year to measure direct radiation. The OSLs were typically positioned roughly 3 to 4 feet above the ground in plastic thermostat boxes. Two OSLs were placed at each designated location. The OSLs were changed out quarterly. Transit dose was measured and subtracted from the ambient dose. Indicator OSL sample locations are illustrated in Figure 2 and control locations are shown in Figure 5. Control locations were 39 (Beto Junction), 48 (Harris) and 53 (near the intersection of 2 0 th Road and Yearling Road).
C. Waterborne Pathway All water samples were analyzed to determine whether gamma emitters were present. In addition to gamma isotopic analysis, radiochemical analysis for 1-131 was performed on drinking water and ground water samples. Gross beta analysis was also performed on drinking water samples. Tritium analysis was performed monthly by liquid scintillation for surface water and quarterly for drinking water. Tritium analysis was also performed on ground water samples. Water sampling locations are shown in Figures 3 and 5.
Monthly grab samples of surface water were collected from John Redmond Reservoir (JRR) as a control location and from the "SP" location, which is located near the spillway of Coffey County Lake, formerly known as Wolf Creek Lake, as an indicator location.
Quarterly grab samples of ground water were collected from seven wells. Location B-12 is hydrologically up gradient from the site and was used as a control location. Six locations (C-10, C-49, F-1, G-2, J-1 and J-2) are hydrologically down gradient from the site and were used as indicator sample locations.
2009 Annual Radiological Environmental Operating Report Wolf Creek Generating Station                                                 Page 2 of 32
 
A. Airborne Pathway Low volume air sampling pumps with digital flow meters continuously collected particulate and radioiodine samples on 47 mm glass fiber filters and charcoal canisters, respectively. The filters and charcoal canisters were changed out weekly, labeled, and shipped to Environmental, Inc. for analyses.
Gross beta analyses of the air particulate filters were performed after a nominal 72-hour period to allow the radon and thoron daughter products to decay.
Weekly air particulate filters were combined into quarterly composites for each location and analyzed for gamma emitting isotopes.
Charcoal canisters were routinely counted to determine the presence or absence of 1-131.
Positive indication of 1-131 would have resulted in analysis of each individual charcoal canister.
Air samples were collected from six locations. Indicator locations 2, 37, and 18 are located in the three sectors with the highest ground level deposition constants (D/Q). Air sampling stations are also located in the community of New Strawn (indicator location 32) and a control location near the intersection of 2 0 th Road and Yearling Road (location 53). Supplemental indicator location (location 49) was also sampled during the year. Indicator locations are shown in Figure 1 and the control location is shown in Figure 5.
B. Direct Radiation Pathway Optically stimulated luminescence (OSL) dosimeters were used at 44 locations during the sample year to measure direct radiation. The OSLs were typically positioned roughly 3 to 4 feet above the ground in plastic thermostat boxes. Two OSLs were placed at each designated location. The OSLs were changed out quarterly. Transit dose was measured and subtracted from the ambient dose. Indicator OSL sample locations are illustrated in Figure 2 and control locations are shown in Figure 5. Control locations were 39 (Beto Junction), 48 (Harris) and 53 (near the intersection of 2 0 th Road and Yearling Road).
C. Waterborne Pathway All water samples were analyzed to determine whether gamma emitters were present. In addition to gamma isotopic analysis, radiochemical analysis for 1-131 was performed on drinking water and ground water samples. Gross beta analysis was also performed on drinking water samples. Tritium analysis was performed monthly by liquid scintillation for surface water and quarterly for drinking water. Tritium analysis was also performed on ground water samples. One surface water sample from the SP location was also analyzed for Fe-55. Water sampling locations are shown in Figures 3 and 5.
Monthly grab samples of surface water were collected from John Redmond Reservoir (JRR) as a control location and from the "SP" location, which is located near the spillway of Coffey County Lake, formerly known as Wolf Creek Lake, as an indicator location.
2010 Annual Radiological Environmental Operating Report Wolf Creek Generating Station                                                  Page 2 of 32
 
TABLE 2 (Cont.)
SAMPLE LOCATION IDENTIFIERS, DISTANCES (Miles) AND DIRECTIONS (Sectors)
Sample Type               Location     Distance from Direction     Sector Identifier       Reactor Dosimeters                             46             1.6       WNW             P 47             0.16         S           J 48             14.7       ENE           D 49             0.8       NNE           B 50             3.6       ENE           D 51             4.0         S           J 52             3.6         SW           L 53             10.8       ENE           D Surface Water                         JRR             3.7         W             N SP             3.2       SSE           H Ground Water                           B-12             1.9       NNE           B C-10             2.7         W             N C-49/L-49           2.8         SW           L F-1             2.5       ESE           F G-2             3.6         SE           G J-1             3.8         S           J J-2             4.3         S           J Drinking Water                       BW-15             3.9         SW           L 1O-DW             26.1       SSE           H Shoreline Sediment                     DC             0.8       WNW             P EEA             3.0       NNW           R JRR             3.6         W             N Fish                                   CCL             0.6     E to NNW       E to R JRR             3.7         W             N Food/Garden                           D-2             14.8       ENE           D H-2             3.0       SSE           H N-1             2.4         W             N Q-6             2.4         NW           Q Crops                               NR-D1             8.9         S           J NR-D2             11.5         S           J NR-U1             4.0       SSW           K Bottom Sediment                         DC             0.9       WNW             P JRR             3.7         W             N MUDS               1.5       WNW             P UHS             0.6         E           E Aquatic Vegetation                   DC ALT             1.5         NW           Q EEA             3.0       NNW           R Soil                                   EEA             3.0       NNW           R MUDS               1.5       WNW             P Meat (Alligator)                       CCL             1.5       WNW             P Meat (Deer)                           R2.5             2.5       NNW           R 2010 Annual Radiological Environmental Operating Report Wolf Creek Generating Station                                     Page 18 of 32}}

Latest revision as of 15:34, 6 February 2020

Annual Radiological Environmental Operating Report
ML12128A401
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 04/26/2012
From: Sen G
Wolf Creek
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA 12-0053
Download: ML12128A401 (173)


Text

W LF CREEK 'NUCLEAR OPERATING CORPORATION Gautam Sen Manager Regulatory Affairs April 26, 2012 RA 12-0053 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Docket No. 50-482: 2011 Annual Radiological Environmental Operating Report Gentlemen:

The purpose of this letter is to submit the enclosed Annual Radiological Environmental Operating Report, which is being submitted pursuant to Wolf Creek Generating Station (WCGS) Technical Specification 5.6.2. This report covers radiological environmental monitoring around WCGS for the period of January 1, 2011, through December 31, 2011.

Also enclosed are corrected pages from the 2009 and 2010 reports that reflect administrative changes that were found necessary during preparation of the 2011 report. The changes are marked with revision bars. Wolf Creek Nuclear Operating Corporation apologizes for any inconvenience this may cause.

This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4175, or Mr. William Muilenburg, at (620) 364-8831, ext. 4511.

Sincerely, Gautam Sen GS/rlt

Enclosure:

2011 Annual Radiological Environmental Operating Report Corrected pages from 2009 and 2010 reports (3 pages) cc: E. E. Collins (NRC), w/e J. R. Hall (NRC), w/e N. F. O'Keefe (NRC), w/e Senior Resident Inspector (NRC), w/e P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HC/VET

WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION 2011 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT A

V April 15, 2012

TABLE OF CONTENTS List of Tables ii List of Figures ii List of Charts ii Executive Summary 1 Introduction 1 I. Program Description 1 II. Discussion of Results 4 Ill. Program Revisions/Changes 10 IV. Program Deviations 10 V. Interlaboratory Comparison Program Results 11 VI. Comparison to the Radioactive Effluents Release Program 11 Tables 12 Figures 20 Charts 25 Appendix A - Interlaboratory Comparison Program Results A-1 Appendix B - Summary Tables B-1 Appendix C - Individual Sample Results C-1 Air Particulate and Charcoal Filters C-I Quarterly Air Particulate - Gamma C-1 3 Surface Water C-20 Ground Water C-28 Drinking Water C-44 Quarterly Drinking Water - Tritium C-52 Shoreline Sediment C-54 Fish C-57 Food/Garden C-62 Feed and Forage C-.70 Bottom Sediment C-73 Aquatic Vegetation C-89 Terrestrial Vegetation C-91 Soil C-92 Deer C-93 Appendix D - Land Use Census Report D-1

LIST OF TABLES 1 Radiological Environmental Monitoring Program Description 12 2 Sample Location Identifiers, Distances (Miles) and Directions (Sectors) 17 3 OSL Dosimeter Results 19 LIST OF FIGURES 1 Airborne Pathway Sampling Locations 20 2 Direct Radiation Pathway Sampling Locations 21 3 Waterborne Pathway Sampling Locations 22 4 Ingestion Pathway Sampling Locations 23 5 Distant Sampling Locations 24 LIST OF CHARTS 1 Airborne Gross Beta Weekly Results 25 2 Historical Airborne Smoothed Indicator and Control Gross Beta 26 3 OSL Dosimeters - Indicator and Control Locations mR per Standardized 90-day 27 Quarter 4 Historical TLD Nearsite Locations and Control Locations 28 5 Coffey County Lake Surface Water Tritium Data 29 6 Drinking Water Gross Beta (5 years) 30 7 Detected Co-60 Activity in Coffey County Lake Discharge Cove Bottom Sediment 31 8 Detected Cs-1 37 Activity in Bottom Sediment 32 ii

EXECUTIVE

SUMMARY

Plant-related activation, corrosion, or fission products were not detected during 2011 in airborne particulate and radioiodine filters, ground water, drinking water, broadleaf vegetation, shoreline sediment, crops, aquatic vegetation, bottom sediment, or soil samples. Activation, corrosion or fission products attributable to plant operation were detected during 2011 in surface water, fish, and deer samples.

Activity was detected from the radioactive material released from Dai-lchi, Fukushima following the March 22, 2011 earthquake and subsequent tsunami.

Nuclides detected in Radiological Environmental Monitoring Program (REMP) samples were below applicable NRC reporting levels.

Based upon the radiological environmental monitoring program results, it was concluded that station operations had no significant radiological impact on the health and safety of the public or the environment.

INTRODUCTION The 2011 Annual Radiological Environmental Operating Report for Wolf Creek Generating Station (WCGS) covers the period from January 1 through December 31, 2011. WCGS is located in Coffey County, Kansas, approximately five miles northeast of Burlington, Kansas.

Fuel loading commenced at WCGS on March 12, 1985. The operational phase of the REMP began with initial criticality on May 22, 1985, and the first detectable quantities of radioactivity were reported in plant effluents in June 1985.

This report contains a description of the REMP conducted by Wolf Creek Nuclear Operating Corporation (WCNOC), a discussion of monitoring program results, the revisions or changes to the program, program deviations, the Interlaboratory Comparison Program and a comparison to the Radioactive Effluents Release Program. The Interlaboratory Comparison Program results, a summary of results in the Nuclear Regulatory Commission (NRC) Branch Technical Posi'Non specified format, the individual sample results, and the Land Use Census Report are included as appendices.

I. PROGRAM DESCRIPTION Radiological environmental monitoring samples were collected according to the schedule in WCGS procedure AP 07B-004, Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program). Radiological environmental monitoring program samples were collected by the WCGS Environmental Management group and were analyzed by Environmental, Inc.

Landauer, Inc. processed the environmental optically stimulated luminescence (OSL) dosimeters. Table 1 identifies the exposure pathway/sample type, number of samples/sample locations, sample collection frequency and type/frequency of analysis. Table 2 lists each sample location's distance and direction from the plant. Samples in addition to those required by the WCGS Offsite Dose Calculation Manual (ODCM) were also obtained and analyzed.

The following is a description of the sampling and analysis program by individual pathways.

2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 1 of 32

A. Airborne Pathway Low volume air sampling pumps with digital flow meters continuously collected particulate and radioiodine samples on 47 mm glass fiber filters and charcoal canisters, respectively. The filters and charcoal canisters were changed out weekly, labeled, and shipped to Environmental, Inc. for analyses.

Gross beta analyses of the air particulate filters were performed after a nominal 72-hour period to allow the radon and thoron daughter products to decay.

Weekly air particulate filters were combined into quarterly composites for each location and analyzed for gamma emitting isotopes.

Charcoal canisters were routinely counted to determine the presence or absence of 1-131.

Positive indication of 1-131 would have resulted in analysis of each individual charcoal canister.

Air samples were collected from six locations. The five indicator locations sampled included 2, 18, 32, 37 and 49. A control location near the intersection of 20th Road and Yearling Road (location 53) was also sampled. Indicator locations are shown in Figure 1 and the control location is shown in Figure 5.

B. Direct Radiation Pathway Optically stimulated luminescence (OSL) dosimeters were used at 43 locations during the sample year to measure direct radiation. The OSLs were typically positioned roughly 3 to 4 feet above the ground in plastic thermostat boxes. Three OSLs were placed at each designated location. The OSLs were changed out quarterly. Transit dose was measured and subtracted from the ambient dose. Indicator OSL sample locations are illustrated in Figure 2 and control locations are shown in Figure 5. Control locations were 39 (Beto Junction) and 53 (near the intersection of 20th Road and Yearling Road).

C. Waterborne Pathway All water samples were analyzed to determine whether gamma emitters were present. In addition to gamma isotopic analysis, radiochemical analysis for 1-131 was performed on drinking water and ground water samples. Gross beta analysis was also performed on drinking water samples. Tritium analysis was performed monthly by liquid scintillation for surface water and quarterly for drinking water. Tritium analysis was also performed on ground water samples. Two surface water samples from the Coffey County Lake Spillway (SP) location and two surface water samples from the John Redmond Reservoir (JRR) location were also analyzed for Fe-55. Water sampling locations are shown in Figures 3 and 5.

Monthly grab samples of surface water were collected from John Redmond Reservoir (JRR) as a control location and from the SP location, which is located near the spillway of Coffey County Lake, formerly known as Wolf Creek Lake, as an indicator location.

2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 2 of 32

Quarterly grab samples of ground water were collected from seven wells. Location B-12 is hydrologically up gradient from the site and was used as a control location. Six locations (C-10, C-49, F-i, G-2, J-1 and J-2) are hydrologically down gradient from the site and were used as indicator sample locations.

Drinking water was sampled at the water treatment facilities for the towns of Burlington (control location BW-15) and Iola (indicator location IO-DW). The Burlington facility is located upstream and the Iola facility is located downstream of the confluence of the discharge from Coffey County Lake and the Neosho River. Composite samples were obtained monthly from automatic samplers at each location that collected approximately 27 ml. of drinking water every two hours.

Shoreline sediments were sampled semiannually. Gamma isotopic analyses were performed on the shoreline sediment samples. Shoreline sediment sample locations were the Coffey County Lake discharge cove (DC) indicator location and the JRR control location.

D. Ingestion Pathway Because no sampling locations that produce milk for human consumption were identified within five miles of the plant during the Land Use Census, milk was not collected during the sample year.

Fish were sampled semiannually from the tail waters of JRR (control, Figure 4) and from Coffey County Lake (indicator, Figure 4). Gamma isotopic analyses were performed on the boneless meat portions of the fish. Several species of game fish and rough fish were sampled. Fish were also analyzed for tritium.

Broadleaf vegetation samples were collected monthly when available during the growing season from four gardens. Three indicator (B-i, N-1 and Q-6) gardens (Figure 4) and one control (D-2) garden (Figure 5) were sampled. Gamma isotopic analyses were performed on all samples.

Crop samples were obtained from two indicator locations (NR-D1 and NR-D2) downstream of the confluence of Wolf Creek and the Neosho River. Two crop samples were obtained from control location NR-U1. Gamma isotopic analysis was performed on each sample. Crop sample locations are identified on Figure 5.

E. Additional Samples Collected (not required by ODCM)

Quarterly, duplicate ground water grab samples were obtained from indicator location C-49 and were labeled L-49. These duplicate samples served as laboratory quality checks. The ground water samples were analyzed for gamma emitters, 1-131, and tritium.

Bottom sediment samples were collected from indicator locations at the Coffey County Lake discharge cove (DC), Environmental Education Area (EEA), Make-Up Discharge Structure (MUDS), Ultimate Heat Sink (UHS), Essential Service Water (ESW) channel and the control location (JRR). Gamma isotopic analyses were performed on the bottom sediment samples.

Samples obtained from DC, ESW and UHS were also analyzed for Fe-55. Some of the bottom sediment samples were collected as part of a cooperative sampling effort with the Kansas 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 3 of 32

Department of Health and Environment (KDHE). The sample locations are identified on Figure 3.

A shoreline sediment sample was collected from indicator location EEA. Gamma isotopic analysis was performed on the sample. This sample was collected as part of a cooperative sampling effort with the KDHE. The sample location is identified on Figure 3.

Aquatic vegetation was collected from indicator locations DC ALT and MUDS. Gamma isotopic analyses were performed on the aquatic vegetation samples. These samples were collected as part of a cooperative sampling effort with the KDHE. The sample locations are identified on Figure 3.

Terrestrial vegetation (grass) was sampled from the MUDS indicator location. Gamma isotopic analyses were performed on the grass samples. These samples were collected as part of a cooperative sampling effort with the KDHE. The sample location is identified on Figure 4.

Soil was sampled from the MUDS indicator location. Gamma isotopic analysis was performed on the soil sample. This sample was collected as part of a cooperative sampling effort with the KDHE. The sample location is identified on Figure 4.

Deer were sampled from indicator locations C.36 and Q1.4. Gamma isotopic analyses and tritium analyses were performed. These samples were collected as part of a cooperative sampling effort with the KDHE. The sample locations are identified on Figure 4.

II. DISCUSSION OF RESULTS Analysis results for all pathways are summarized in Appendix B using the format described in Radiological Assessment Branch Technical Position, Revision 1, November 1979 (NRC Generic Letter 79-065). Results for individual samples are listed in Appendix C.

In this section, results are discussed by pathway and analysis type. Monitoring results are compared with control data, preoperational values, sources of radioactivity, and effluent releases when applicable. Trends or seasonal effects are discussed.

A. Airborne Pathway Chart 1 graphically illustrates weekly gross beta results for the sample year. Chart 2 represents the historical smoothed averages of indicator locations and the control locations gross beta data. Charts 1 and 2 demonstrate how closely the indicator and control locations tracked together. Chart 2 reveals a seasonal cyclic trend in which gross beta values peak in the winter months (December or January) and decrease to a low point in the spring months (May or June).

This trend is expected and is attributed to seasonal meteorological changes, i.e., changes in prevailing winds and precipitation.

The gross beta results of 2011 were compared to pre-operational monitoring results of 1983 and 1984. The weekly gross beta analyses range for 1983 and 1984 was 0.0064 to 0.084 pCi/m3, The 2011 weekly gross beta analyses range for all indicator locations was 0.008 to 0.056 pCi/m 3, which was within the 1983 and 1984 pre-operational range. Additionally, the annual mean for indicator locations for 2011 (0.026 pCi/m 3) was lower than the annual mean for 1983 (0.032 pCi/m 3).

2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 4 of 32

The gross beta results for the indicator locations were also compared to the control location.

The annual mean for indicator locations for 2011 (0.026 pCi/m 3) was slightly lower than the annual mean of the control location (0.027 pCi/m 3). The indicator location with the highest gross beta annual mean was location 49 (0.027 pCi/m 3), which was the same as the annual mean of the control location (0.027 pCi/m 3).

Naturally occurring Be-7 activity was detected, as was the case during pre-operational monitoring. In 1984, the range for Be-7 detected activity was 0.024 to 0.211 pCi/m 3 for indicator locations and the annual mean for indicator locations was 0.069 pCi/m 3 . In 2011, the range for Be-7 detected activity was 0.063 to 0.118 pCi/m 3 for indicator locations and the annual mean for indicator locations was 0.080 pCi/m 3. The control location annual mean for Be-7 detected activity (0.079 pCi/m 3) was slightly lower than the annual mean of the indicator locations (0.080 pCi/m 3).

1-131 activity was detected in all charcoal filter samples collected from the indicator and control locations with collection start dates of 03-21-2011 and 03-28-2011. Since the 1-131 activity was detected in the indicator samples as well as the control samples, the atypical detection of this radionuclide is attributed to the transport of airborne releases from Dai-lchi, Fukushima following the March 11, 2011 Tohoku earthquake and is not related to the operations of the Wolf Creek Generating Station.

The ODCM required lower limits of detection were met. Plant-related activation, corrosion, or fission products were not detected during 2011 in airborne particulate and radioiodine filters and no unusual trends were noted.

B. Direct Radiation Pathway Quarterly OSL dosimeter results for each location are shown in Table 3. Measured values have been converted to a standardized 90-day quarter.

The annual mean of all indicator locations in 2011 was 19.5 mR per standardized 90-day quarter. The annual mean of the control locations in 2011 was 20.1 mR per standardized 90-day quarter.

For pre-operational comparison, in 1981, the annual mean of all indicator locations was 18.9 mR per standardized 90-day quarter and the annual mean for the control locations was 17.1 mR per standardized 90-day quarter. It should be noted that WCGS changed from thermoluminescence dosimeters (TLD) to optically stimulated luminescence (OSL) dosimeters in 2008.

The indicator location with the highest annual mean was 47 (25.1 mR per standardized 90-day quarter). The close proximity of location 47 to the Radwaste Building is likely the reason direct radiation levels are higher at this location.

Based upon Condition Report 00027489, improvements were made in measuring and subtracting transit dose in 2010. As expected, the OSL results have increased for all locations since 2010. Chart 3 visibly displays the increase of the OSL results. Chart 3 also displays how closely the indicator and control location OSL dosimeter results are for 2011.

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Chart 4 displays the TLD nearsite locations (1, 2, 7-9, 11-14, 18, 26, 27, 29, 30, 37 and 38) and the control locations (locations 39 and 48) for the preoperational years through 2007.

C. Waterborne Pathway (1) Surface Water Tritium, attributable to WCGS operation, was detected in all surface water samples collected from the Coffey County Lake Spillway (SP) indicator location during 2011. The annual mean for detected tritium activity at the SP location was 12,848 pCi/L and the range was 9,847 to 15,523 pCi/L. Chart 5 illustrates the yearly averages of surface water tritium data for the spillway location. Chart 5 indicates that the average tritium concentration of the Coffey County Lake spillway location may have reached equilibrium. Tritium activity was not detected in samples obtained from the control location (JRR).

During pre-operational radiological environmental monitoring, measured radiological activity was not detected in surface water samples.

The ODCM required lower limits of detection were met. Radionuclides were not detected by the gamma isotopic analyses or by Fe-55 analyses.

Tritium was the only activity detected in surface water samples and no unusual trends were noted.

(2) Ground Water ODCM required lower limits of detection were met for 1-131, tritium and gamma isotopic analyses. Radioactivity was not detected in any ground water samples. No unusual trends were noted. Plant-related activation, corrosion or fission products were not detected during 2011 in ground water samples.

(3) Drinking Water Gross beta activity was detected in all drinking water samples collected from the indicator location and nearly all samples collected from the control location. The annual mean of the indicator location gross beta activity (2.6 pCi/L) was slightly lower when compared to the annual mean of the control location gross beta activity (2.7 pCi/L). The 2011 annual means of gross beta activity for both the indicator and control locations were lower than those of the pre-operational monitoring year of 1984. In 1984, the annual mean of the indicator location gross beta activity was 7.5 pCi/L and the annual mean of the control location gross beta activity was 6.4 pCi/L.

Chart 6 illustrates the drinking water gross beta results for the last five years and how closely the gross beta results compared for the indicator and control locations.

ODCM required lower limits of detection were met. Additionally, radionuclides were not detected by the 1-131, Tritium, or gamma isotopic analyses.

Plant-related activation, corrosion, or fission products were not detected during 2011 in drinking water samples and no unusual trends were noted.

2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 6 of 32

(4) Shoreline Sediment Naturally occurring K-40 was detected in all shoreline sediment samples collected from the DC (indicator) and JRR (control) locations. K-40 was also detected during pre-operational shoreline sediment monitoring.

Cs-137 activity (144.5 +/- 37.7 pCi/kg, dry) was detected in one shoreline sediment sample obtained from the DC indicator location. Cs-137 activity was also detected in pre-operational shoreline sediment samples. Cs-137 activity detected in shoreline sediment samples collected from the DC location from 1982 to 1984 was in the range of 224 to 437 pCi/kg, dry. The decay corrected range of pre-operational Cs-137 activity detected is approximately 121 to 236 pCi/kg, dry. The detected Cs-137 activity in the shoreline sediment sample collected at the DC indicator location in 2011 was likely due to fallout since the measured activity is within the decay corrected range of pre-operational Cs-137 detected activity and Cs-137 activity has also been detected in the past at the control location.

ODCM required lower limits of detection were met. Plant-related activation, corrosion, or fission products were not detected during 2011 in shoreline sediment samples and no unusual trends were noted.

D. Ingestion Pathway (1) Milk Milk was not collected during the sample year since no indicator locations within five miles of the plant were identified during the Land Use Census.

(2) Fish Naturally occurring K-40 activity was detected in all fish samples obtained from the CCL indicator location and the JRR control location. K-40 activity was also detected during pre-operational fish monitoring.

Fish samples were also analyzed for tritium. All fish samples taken from Coffey County Lake had tritium activity detected (8,230 pCi/kg annual mean). The detected tritium activity was attributable to plant operation. An adult consuming 21 kilograms of fish, at the maximum measured tritium concentration (9,461 pCi/kg), would receive a committed effective dose equivalent of 0.013 mRem.

Tritium activity was not detected in the control samples collected from JRR.

No other radionuclides were detected in fish during the year. The ODCM required lower limits of detection were met and no unusual trends were noted.

2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 7 of 32

(3) Broadleaf Vegetation Gamma analyses of broadleaf vegetation samples obtained from indicator and control locations detected naturally occurring gamma emitters Be-7 and K-40. Be-7 and K-40 activity were also detected pre-operationally.

No other radionuclides were detected in broadleaf vegetation during the year. The ODCM required lower limits of detection were met and no unusual trends were noted. Plant-related activation, corrosion, or fission products were not detected during 2011 in broadleaf vegetation samples.

(4) Crop Samples Gamma analysis detected naturally occurring K-40 activity to be present in all of the samples.

K-40 activity was also detected during pre-operational crop monitoring. K-40 was the only activity detected in crop samples. The ODCM required lower limits of detection were met.

Plant-related activation, corrosion, or fission products were not detected during 2011 in crop samples and no unusual trends were noted.

E. Additional Samples Collected (not required by ODCM)

(1) Bottom Sediment Naturally occurring K-40 was detected in all of the bottom sediment samples obtained from the indicator locations and the control locations. K-40 activity was also detected during pre-operational bottom sediment monitoring.

Cs-137 activity was detected in ten out of the seventeen samples obtained from indicator locations (range 66 to 120 pCi/kg, dry). Cs-137 activity was also detected in one sample obtained from the control location (91 pCi/kg, dry).

Cs-1 37 activity was detected in pre-operational samples, and the results for 2011 indicator bottom sediment samples were within the pre-operational range. (Cs-137 activity detected in 1981 and 1982 was in the range of 79 to 953 pCi/kg. The decay corrected range of pre-operational Cs-1 37 activity detected is approximately 40 to 479 pCi/kg.)

The detected Cs-1 37 activity in the samples collected from the indicator locations was likely due to fallout since the measured activity is within the decay corrected range of pre-operational Cs-1 37 detected activity and Cs-1 37 activity has also been detected in samples collected at the control location.

Chart 8 plots the Cs-137 detected activity from the discharge cove indicator location and JRR control location bottom sediment samples. The detected Cs-137 activity measured from the discharge cove location reflects a decreasing trend. The Chart 8 trend line indicates that as expected, Cs-137 activity detected at the JRR control location has also been decreasing.

Fe-55 activity was not detected in the fourteen samples obtained from indicator locations. No other radionuclides were detected in bottom sediment samples.

2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 8 of 32

Plant-related activation, corrosion, or fission products were not detected in bottom sediment samples and no unusual trends were noted.

(3) Aquatic Vegetation Naturally occurring Be-7 and K-40 activity were detected in all aquatic vegetation samples.

Be-7 and K-40 activity were also detected during pre-operational monitoring.

No other radionuclides were detected. Plant-related activation, corrosion, or fission products were not detected during 2011 in aquatic vegetation samples and no unusual trends were noted.

(4) Shoreline Sediment Naturally occurring K-40 activity was detected in the shoreline sediment sample obtained from the EEA indicator location. K-40 activity was also detected during pre-operational monitoring.

Cs-137 activity (250.5 pCi/kg, dry) was detected in the shoreline sediment sample obtained from the EEA indicator location. Cs-137 activity was also detected in pre-operational shoreline sediment samples. Cs-137 activity detected in shoreline sediment samples collected from the DC location from 1982 to 1984 was in the range of 224 to 437 pCi/kg, dry. The decay corrected range of pre-operational Cs-137 activity detected is approximately 121 to 236 pCi/kg, dry. The detected Cs-137 activity in the shoreline sediment sample collected at the EEA indicator location in 2011 was likely due to fallout since the result is very near the pre-operational decay corrected range. Additionally, Cs-137 activity is routinely detected in soil and sediment samples collected from the control locations and this shoreline sediment sample was obtained following the release of radioactive material from the Fukushima nuclear plant after the March 11, 2011 earthquake and tsunami.

No other radionuclides were detected. Plant-related activation, corrosion, or fission products were not detected and no unusual trends were noted.

(5) Soil Naturally occurring K-40 activity was detected in the MUDS indicator location soil sample. K-40 activity was also detected during pre-operational soil monitoring.

Cs-137 activity (112 pCi/kg) was also detected in the MUDS indicator location soil sample. This activity is likely due to fallout. Data was reviewed for soil samples collected pre-operationally.

The detected Cs-137 activity range from February of 1985 was 255 to 2,160 pCi/kg, dry. The decay corrected range of pre-operational Cs-1 37 activity detected in soil is approximately 139 to 1,181 pCi/kg. The detected Cs-137 activity in soil sampled in 2011 is lower than the decay corrected pre-operational range.

Plant-related activation, corrosion, or fission products were not detected during 2011 in this soil sample and no unusual trends were noted.

2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 9 of 32

(6) Deer Naturally occurring K-40 activity was detected in the deer samples obtained from the indicator locations.

The deer samples were also analyzed for tritium. The average mean for detected tritium was 748 pCi/kg. The detected tritium activity was attributable to plant operation.

No other radionuclides were detected. No unusual trends were identified.

Ill. PROGRAM REVISIONS/CHANGES Based upon Condition Report 00027489, during the second quarter of 2011, the number of dosimeters was increased from two to three per sample location and the number of transit dosimeters was increased from four to five. Additionally, the method for calculating and subtracting transit dose was revised.

Based upon Condition Report 00029165, during the third quarter of 2011, quarterly Fe-55 analysis was added for surface water samples collected from John Redmond Reservoir (JRR) and the Discharge Cove (DC). Additionally, Fe-55 analysis was added for bottom sediment samples collected from the DC and the Ultimate Heat Sink (UHS).

IV. PROGRAM DEVIATIONS Air Samples The following air sample location failed to meet the requirement for "continuous sampler operation." As described in footnote (1) of procedure AP 07B-004, Offsite Dose Calculation Manual (RadiologicalEnvironmental Monitoring Program), Table 5-1, deviations are permitted from the required sampling schedule due to malfunction of sampling equipment and other legitimate reasons. Discrepancies greater than five percent between Total Military Time and Total Digital Flow Meter Time, which resulted in a loss of air sample collected, are listed in the following table.

Location Sample Period Percent Explanation of Deviation/

Discrepancy/ Condition Report Number/

Hours Comments Unavailable 2 01/31/11 - 02/07/11 Unknown Power Outage / Equipment Malfunction Condition Report 00033233 Ground Water Protection The following information is being provided in association with the Nuclear Energy Institute (NEI) Groundwater Protection Industry Initiative:

Describe offsite ground water or surface water sample results that exceeded the REMP reporting criteria that were voluntarily communicated to State/Local officials during the calendar year - None.

2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 10 of 32

V. INTERLABORATORY COMPARISON PROGRAM RESULTS During 2011, Environmental, Inc., Midwest Laboratory was contracted to perform radiological analysis of environmental samples for WCNOC. The lab participated in the intercomparison studies administered by Environmental Resources Associates. Appendix A is the Interlaboratory Comparison Program Results for Environmental, Inc., Midwest Laboratory.

Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also contained in Appendix A.

VI. COMPARISON TO THE RADIOACTIVE EFFLUENTS RELEASE PROGRAM As described in the section discussing radioisotopes found in fish from Coffey County Lake, dose that may be received as a result of tritium released from WCGS is comparable with the theoretical doses calculated by the Radioactive Effluent Release Program.

The theoretical doses calculated by the Radioactive Effluent Release Program assume that a person drinks the water from Coffey County Lake and eats the fish from Coffey County Lake.

Based upon these assumptions the dose to man from both pathways was calculated to be 0.219 mRem for 2011.

Using sample data obtained from the REMP, an adult drinking 2 liters per day of surface water from Coffey County Lake, using the average tritium activity (12,848 pCi/L), would receive a committed effective dose equivalent of 0.587 mRem per year. For an adult eating 21 kg of fish per year from Coffey County Lake, using the average tritium activity (8,230 pCi/kg), would receive a committed effective dose equivalent of 0.011 mRem per year. Based upon the REMP results, the dose from both pathways was calculated to be 0.598 mRem per year.

It should be noted that the Coffey County Lake is not a drinking water source. Calculating the dose to man for tritium detected in the Coffey County Lake surface water is for comparison purposes only.

The tritium dose values are being compared on a qualitative basis. It is not expected that the annual doses, as calculated in the Radioactive Effluent Release Report, would compare directly to those calculated from the REMP. The Radioactive Effluent Release Report provides a 'snap shot' of potential dose resulting from the year's releases. The REMP data indicates the accumulated result of releasing tritium into the lake since the start of plant operation.

2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 11 of 32

TABLE 1 2011 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DESCRIPTION (SAMPLE COLLECTION SPECIFIED BY ODCM)

EXPOSURE NUMBER OF SAMPLE COLLECTION TYPE AND PATHWAY/ SAMPLES AND FREQUENCY FREQUENCY OF SAMPLE TYPE SAMPLE LOCATIONS ANALYSIS AIRBORNE (See Figures 1 & 5)

Radioiodine and Samples from six Continuous sampler Analyze radioiodine Particulates locations operation with sample canister weekly for collection weekly, or more 1-131 frequently if required, by dust loading.

Samples from locations Analyze particulate near the site boundary filter weekly for in three sectors having gross beta activity; the highest calculated perform quarterly annual average D/Q gamma isotopic (Locations 2, 37, 49 analysis composite and supplemental (by location) location 18 on Figure 1)

Sample from the vicinity of a community having the highest calculated annual average D/Q (Location 32 on Figure 1, New Strawn)

Sample from a control location 9.5 to 18.5 miles distant in a low ranked D/Q sector (Location 53 on Figure 5) 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 12 of 32

TABLE I (Cont.)

EXPOSURE NUMBER OF SAMPLE COLLECTION TYPE AND PATHWAY/ SAMPLES AND FREQUENCY FREQUENCY OF SAMPLE TYPE SAMPLE LOCATIONS ANALYSIS DIRECT (See Figures 2 & 5)

RADIATION 40 routine monitoring Quarterly Gamma dose stations with two or quarterly more dosimeters measuring dose continuously, placed as follows:

An inner ring of stations, one in each meteorological sector 0-3 mile range from the site (Locations 1, 7, 9, 11-13, 18, 26, 27, 29, 30, 37, 38, 46, 47, & 49 on Figure 2).

An outer ring of stations, one in each meteorological sector in the 3 to 5 mile range from the site (Locations 4, 5, 15-17, 19, 22-25, 32, 34-36, 50 & 51 on Figure 2). Four sectors

[A, B, G & J] contain an additional station (Locations 2, 8, 14 &

20).

The balance of the stations to be placed in special interest areas such as population centers (Locations 23, 32 & 52), nearby residences 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 13 of 32

TABLE I (Cont.)

EXPOSURE NUMBER OF SAMPLE COLLECTION TYPE AND PATHWAY/ SAMPLES AND FREQUENCY FREQUENCY OF SAMPLE TYPE SAMPLE LOCATIONS ANALYSIS DIRECT RADIATION (cont.)

(many locations are riear a residence),

sschools (Locations 23

, 52), Environmental EEducation Area (44),

'CL Public Fishing a,rea (46) and in two ireas to serve as c;ontrol stations 10-20 rniles distant from the site (Locations 39 and i3 on Figure 5).

WATERBORNE See Figure 3)

Surface One sample upstream Monthly grab sample Monthly gamma (Location JRR on isotopic analysis and Figure 3) and one composite for tritium sample downstream analysis quarterly (Location SP on Figure 3).

Ground Samples from one or Quarterly grab sample Quarterly gamma two sources only if isotopic and tritium likely to be affected. analysis Indicator samples at locations hydrologically down gradient of the site (Locations C-10, C-49, F-1, G-2, J-1 and J-2 on Figure 3);

control sample at a location hydrologically up gradient of the site (Location B-12 on Figure 3).

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TABLE I (Cont.)

EXPOSURE NUMBER OF SAMPLE COLLECTION TYPE AND PATHWAY/ SAMPLES AND FREQUENCY FREQUENCY OF SAMPLE TYPE SAMPLE LOCATIONS ANALYSIS WATERBORNE (cont.)

Drinking Sample of municipal Monthly Composite Monthly gamma water supply at an isotopic analysis and indicator location gross beta analysis downstream of the site of composite (Location 1O-DW on sample. Quarterly Figure 5); control tritium analysis of sample from location composites.

upstream of the site (Location BW-15 on Figure 3).

Shoreline One sample from the Semiannually Semiannual gamma Sediment vicinity of Coffey isotopic analysis County Lake discharge cove (Location DC on Figure 3); control sample from John Redmond Reservoir (Location JRR on Figure 3).

INGESTION (See Figures 4 & 5)

Milk Samples from milking Semimonthly April to Gamma isotopic animals at three November; monthly analysis and 1-131 indicator locations December-March analysis of each within 5 miles of the sample site having the highest dose potential (currently there are no locations producing milk for human consumption within 5 miles of the site); one sample from a control location greater than 10 miles from the site if indicator locations are sampled.

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TABLE I (Cont.)

EXPOSURE NUMBER OF SAMPLE COLLECTION TYPE AND PATHWAY/ SAMPLES AND FREQUENCY FREQUENCY OF SAMPLE TYPE SAMPLE LOCATIONS ANALYSIS INGESTION (cont.)

Fish Indicator samples of 1 Semiannually Gamma isotopic to 3 recreationally analysis on edible important species from portions Coffey County Lake; control samples of similar species from John Redmond Reservoir spillway (Figure 4).

Broadleaf Samples of available Monthly when available Gamma isotopic Vegetation broadleaf vegetation analysis on edible from two indicator portions locations (using the criteria from the "Land Use Census" section) with highest calculated annual average D/Q (Locations Q-6 and N-1 and alternate locations B-1, H-2 and R-2 on Figure 4); sample of similar broadleaf vegetation from a control location 9.5 to 18.5 miles distant in a low ranked D/Q sector (Location D-2 on Figure 5).

Irrigated Crops Sample of crops At time of harvest Gamma isotopic irrigated with water analysis on edible from the Neosho River portions downstream of the Neosho River - Wolf Creek confluence (Location NR-D1 and NR-D2 on Figure 5).

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TABLE 2 SAMPLE LOCATION IDENTIFIERS, DISTANCES (Miles) AND DIRECTIONS (Sectors)

Sample Type Location Distance from Direction Sector Identifier Reactor Air Particulates and Radioiodine 2 2.7 N A 18 3.0 SSE H 32 3.1 WNW P 37 2.0 NNW R 49 0.8 NNE B 53 10.8 ENE D Dosimeters 1 1.4 N A 2 2.7 N A 4 4.1 NNE B 5 4.1 NE C 7 2.1 NE C 8 1.7 NNE B 9 2.0 ENE D 11 1.7 E E 12 1.9 ESE F 13 1.6 SE G 14 2.5 SE G 15 4.6 ESE F 16 4.3 E E 17 3.7 SE G 18 3.0 SSE H 19 3.9 SSE H 20 3.3 S J 22 3.9 SSW K 23 4.3 SW L 24 4.1 WSW M 25 3.4 W N 26 2.4 WSW M 27 2.2 SW L 29 2.7 SSW K 30 2.5 W N 32 3.1 WNW P 34 4.4 NW Q 35 4.6 NNW R 36 4.2 N A 37 2.0 NNW R 38 1.2 NW Q 39 13.1 N A 41 0.8 NNW R 42 0.8 SSE H 43 0.7 WNW P 44 3.0 NNW R 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 17 of 32

TABLE 2 (Cont.)

SAMPLE LOCATION IDENTIFIERS, DISTANCES (Miles) AND DIRECTIONS (Sectors)

Sample Type Location Distance from Direction Sector Identifier Reactor Dosimeters 46 1.6 WNW P 47 0.16 S J 49 0.8 NNE B 50 3.6 ENE D 51 4.0 S J 52 3.6 SW L 53 10.8 ENE D Surface Water JRR 3.7 W N SP 3.2 SSE H Ground Water B-12 1.9 NNE B

_C-10 2.7 W N

_C-49/L-49 2.8 SW L F-1 2.5 ESE F G-2 3.6 SE G J-1 3.8 S J J-2 4.3 S J Drinking Water BW-15 3.9 SW L IO-DW 26.1 SSE H Shoreline Sediment DC 0.8 WNW P EEA 3.0 NNW R JRR 3.6 W N Fish CCL 0.6 E to NNW E to R JRR 3.7 W N Food/Garden B-1 0.8 NNE B D-2 14.8 ENE D N-1 2.4 W N Q-6 2.4 NW Q Crops NR-D1 8.9 S J NR-D2 11.5 S J NR-U1 4.0 SSW K Bottom Sediment DC 0.9 WNW P EEA 3.0 NNW R ESW 0.5 E E JRR 3.7 W N MUDS 1.5 WNW P UHS 0.6 E E Aquatic Vegetation DC ALT 1.5 NW Q MUDS 1.5 WNW P Terrestrial Vegetation MUDS 1.5 WNW P Soil MUDS 1.5 WNW P Meat (Deer) C.36 .36 NE C Q1.4 1.4 NW Q 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 18 of 32

TABLE 3 OSL Dosimeter Results mR/Standardized 90-day Quarter)

Location Qtr. I Qtr. 2 Qtr. 3 Qtr. 4 Total Annual (M (mR) (mR) (mR)L Exposure (mR) 1 21.1 20.2 22.9 20.1 84.4 2 20.2 16.4 19.6 19.6 75.9 4 16.3 21.0 23.9 20.0 81.2 5 21.4 18.0 21.3 15.9 76.6 7 21.6 18.0 21.9 20.0 81.6 8 22.1 17.5 24.4 19.5 83.4 9 18.3 18.2 20.4 17.9 74.9 11 25.4 19.1 23.9 16.9 85.2 12 19.7 19.6 18.5 21.0 78.9 13 21.6 18.5 20.4 20.4 81.0 14 18.3 19.1 20.9 19.5 77.9 15 18.6 17.7 19.5 19.0 74.7 16 19.1 19.9 22.9 18.5 80.3 17 21.6 18.5 22.3 20.5 82.9 18 19.8 17.5 19.0 20.0 76.2 19 23.3 19.9 21.5 22.0 86.6 20 18.7 18.4 17.0 20.7 74.7 22 22.4 20.6 24.4 19.6 87.0 23 20.1 20.4 19.6 19.6 79.7 24 19.6 20.9 18.5 19.4 78.5 25 15.0 13.8 17.7 18.9 65.4 26 17.7 17.7 18.5 17.9 71.7 27 19.1 19.9 23.9 18.4 81.3 29 15.9 13.8 15.5 16.5 61.7 30 20.0 21.0 20.5 18.9 80.4 32 19.3 18.5 20.0 19.4 77.3 34 20.5 19.5 25.4 17.4 82.8 35 21.2 19.7 23.9 17.5 82.3 36 19.7 20.0 20.0 19.8 79.5 37 19.3 17.5 19.0 17.5 73.3 38 21.6 20.0 19.0 19.1 79.7 39 17.7 18.8 19.7 16.9 73.0 41 19.3 19.6 23.9 19.1 82.0 42 13.1 11.1 10.1 13.6 47.8 43 11.2 10.7 12.1 11.8 45.8 44 19.6 18.7 22.0 18.0 78.4 46 19.6 18.2 23.4 17.4 78.6 47 27.0 26.4 29.5 17.6 100.5 49 16.9 19.1 19.9 19.7 75.6 50 21.8 20.4 24.9 21.0 88.2 51 18.6 18.0 20.5 14.1 71.3 52 24.2 20.9 23.4 21.5 90.1 53 20.9 19.5 25.9 21.6 87.9 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 19 of 32

FIGURE 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 20 of 32

FIGURE 2 DIRECT RADIATION PATHWAY SAMPLING LOCATIONS

FIGURE 3 WATERBORNE PATHWAY SAMPLING LOCATIONS 0 = DRINKING WATER A = SURFACE WATER 0 = GROUND WATER * = SHORELINE SEDIMENT

FIGURE 4 INGESTION PATHWAY SAMPLING LOCATIONS A = FISH (JRR) I= BROADLEAF VEGETATION

FIGURE 5 A

  • = Dosimeter

= AIRBORNE PARTICULATE &RADIOIODINE 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 24 of 32

CHART 1 2011 Airborne Gross Beta Weekly Results 0.060 0.050

+

E 0.040 U

-I 0.030 -+

U '~\

C-)

0~ 9 m 0.020 %A - I i (D

AA AI 0.010 0 0.000 0 4 8 12 16 20 24 28 32 36 40 44 48 52 Week Number 0 Location 2

CHART 2 0.060 E

0.050 C-)

Cn co) 0 0.040 C)

Cl) 0.030

-0 a) 4-r 0

0) 0.020 Co) 0.010 0R 0

- - - Smoothed Avg. Indicator Locations Smoothed Avg. Control Location (40)

- Smoothed Avg. Control Location (48) Smoothed Avg. Control Location (53) 2011 Annual Radiological Environmental Operating Report - Wolf Creek Generating Station Page 26 of 32

CHART 3 OSL Dosimeters - Indicator and Control Locations mR per Standardized 90-Day Quarter 24.0 22.0 - OSL Transit Dose methodology was changed in 2010 based upon Condition Report 00027489.

20.0 -

18.0 -

16.0 -

14.0 -

12.0 -

10.0-8.0 -

6.0-4.0 2008/1 2008/2 2008/3 2008/4 2009/1 2009/2 2009/3 2009/4 2010/1 2010/2 2010/3 2010/4 2011/1 2011/2 2011/3 2011/4 Year/Quarter

--- Indicator Locations Standardized 90-Day Quarter (mR)

--- Control Locations Standardized 90-Day Quarter (mR) 2011 Annual Radiological Environmental Operating Report - Wolf Creek Generating Station Page 27 of 32

CHART 4 Historical TLD Nearsite Locations and Control Locations 32.0 A

30.0 Elevated results due to unusually 28.0 longer exposure duration.

26.0 24.0 22.0 20.0 *4 of I 0 18.0 , 5 0A 4 A 16.0- An4 A A 14.0 A 12.0 ,

1980 1982 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 20063 e Avg. of Nearsite Locations A Avg. of Control Locations

-Moving Avg. of Nearsite Locations (2 period) - - - Moving Avg. of Control Locations (2 period) 2011 Annual Radiological Environmental Operating Report - Wolf Creek Generating Station Page 28 of 32

CHART 5 Coffey County Lake Surface Water Tritium Data 16,000 14,000 12,000 10,000 CL 8,000 6,000 4,000 2,000 04-1987 1992 1997 2002 2007 1--- Yearly Average of Spillway Location - Polynomial Trendline 2011 Annual Radiological Environmental Operating Report - Wolf Creek Generating Station Page 29 of 32

CHART 6 Drinking Water Gross Beta (5 years) 6 5

Q.

4 ci)

U) 3 2

1

-B (Cntol W 5j -z (Indicator) zD 2011 Annual Radiological Environmental Operating Report - Wolf Creek Generating Station Page 30 of 32

CHART 7 Detected Co-60 Activity in Coffey County Lake Discharge Cove Bottom Sediment 2,500 2,000 1,500 "0) 03 03 1,000 500 0

rl- 00 ) -O o q- O (0- Io cc1 0 0 - 03 It LV) (,. - 0c 0) cO 0c cO ") M M" ) M 0") O) a) 0) O) 0 0 0 0 0 0 0 0 0 0 M) a) M *0 ) 0) 0C) M 0) 0) 0" C) 0 0 0 0 0 0 0 0 0 0 N Q -~ C4- - - N N N N Nq N N1 (0) '0 C'0 '0 C) C') Z6) C0 CD) 0" C") C) C") C") C") 80) C") 80) C) C") 0" C-) C8)

L.Co-60 -Polynomial Trendlinej 2011 Annual Radiological Environmental Operating Report - Wolf Creek Generating Station Page 31 of 32

CHART 8 Detected Cs-1 37 Activity in Bottom Sediment 1,000 900 800 700 600 c 500 0

0~

400 300 200 100 0

-(N (N LO N-_ w N O N M0 M 0a N (N M 1' LO (,D I,- I" M MO O MO

0) 03 N- N- (0(00 M M O r- M C).

M0( (0 (N C N 0'-

M- ~ N -'

LO LO LO' (D) 0) CD- M -

LO - W -

(0 LO a 0 0 M) - '

Polynomial Trendline (DC) -----------

2011 Annual Radiological Environmental Operating Report - Wolf Creek Generating Station Page 32 of 32

14,TI Environmental, Inc.

Midwest Laboratory 700 Landwehr Road - Northbrook, IL 60062-23 t0 phone (847) 564-0700- fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A.TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January through December, 2011

Appendix A Interlaboratory Comparison Proqram Results Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.

Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.

Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

Table A-2 lists results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.

Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.

Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.

Table A-5 lists REMP specific analytical results from the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors.

Complete analytical data for duplicate analyses is available upon request.

The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.

Results in Table A-7 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).

Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is set at +/- 2 sigma.

Out-of-limit results are explained directly below the result.

Al

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES8 One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter

> 100 pCi/liter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter

> 50 pCi/liter or kg 10% of known value Strontium-90b 2 to 30 pCi/liter or kg 5.0 pCi/liter

> 30 pCi/liter or kg 10% of known value Potassium-40 ->0.1 g/liter or kg 5% of known value Gross alpha < 20 pCi/liter 5.0 pCi/liter

> 20 pCi/liter 25% of known value Gross beta -<100 pCi/liter 5.0 pCi/liter

> 100 pCi/liter 5% of known value Tritium < 4,000 pCi/liter + lo =

00 933 169.85 x (known) _

> 4,000 pCi/liter 10% of known value Radium-226,-228 > 0.1 pCi/liter 15% of known value Plutonium >-0.1 pCi/liter, gram, or sample 10% of known value Iodine-131, < 55 pCi/liter 6 pCi/liter Iodine-129b > 55 pCi/liter 10% of known value Uranium-238, < 35 pCi/liter 6 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter

> 100 pCi/liter 10% of known value Other Analyses b 20% of known value From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-60014-81-004.

b Laboratory limit.

A2

TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance STW-1243 04/04/11 Sr-89 68.2 +/- 5.8 63.2 51.1 -71.2 Pass STW-1243 04/04/11 Sr-90 44.3 +/- 2.4 42.5 31.3 -48.8 Pass STW-1244 04/04/11 Ba-133 69.8 +/- 3.9 75.3 63.0 - 82.8 Pass STW-1244 04/04/11 Co-60 87.9 +/- 3.8 88.8 79.9 -100.0 Pass STW-1244 04/04/11 Cs-134 69.5 +/- 3.7 72.9 59.5 - 80.2 Pass STW-1244 04/04/11 Cs-137 77.9 +/- 5.3 77.0 69.3 - 87.4 Pass STW-1244 04/04/11 Zn-65 105.2 + 8.4 98.9 89.0 - 118.0 Pass STW-1245 04/04/11 Gr. Alpha 41.5 +/- 2.3 50.1 26.1 -62.9 Pass STW-1245 04/04/11 Gr. Beta 48.9 +/- 1.8 49.8 33.8 - 56.9 Pass STW-1246 04/04/11 1-131 26.6 +/- 1.7 27.5 22.9 - 32.3 Pass STW-1247 04/04/11 Ra-226 13.2 +/- 0.6 12.1 9.0 - 14.0 Pass STW-1247 04/04/11 Ra-228 11.2 +/- 0.6 11.6 7.6 - 14.3 Pass STW-1247 04/04/11 Uranium 36.4 +/- 0.6 39.8 32.2 - 44.4 Pass STW-1248 04/04/11 H-3 10322 +/-285 10200.0 8870 -11200 Pass STW-1256 10/07/11 Sr-89 68.7 +/- 6.0 69.7 56.9 - 77.9 Pass STW-1256 10/07/11 Sr-90 36.9 +/- 2.4 41.1 30.2 - 47.2 Pass STW-1257 10/07/11 Ba-133 88.2 +/- 7.8 96.9 81.8 - 106.0 Pass STW-1257 10/07/11 Co-60 116.5 +/-7.1 119.0 107.0 - 133.0 Pass STW-1257 10/07/11 Cs-134 38.8 +/- 8.0 33.4 26.3 - 36.7 Fail STW-1257 10/07/11 Cs-137 45.6 +/- 7.3 44.3 39.4 -51.7 Pass STW-1257 10/07/11 Zn-65 84.9 +/- 15.4 76.8 68.9 - 92.5 Pass STW-1258 10/07/11 Gr. Alpha 35.7 +/- 3.8 53.2 27.8 - 66.6 Pass STW-1258 10/07/11 Gr. Beta 36.1 +/- 3.3 45.9 30.9 - 53.1 Pass STW-1 259 10/07/11 1-131 25.0 +/- 1.1 27.5 22.9 - 32.3 Pass STW-1260 10/07/11 Ra-226 12.2 +/- 0.6 11.6 8.7 - 13.4 Pass STW-1260 10/07/11 Ra-228 11.5 +/- 1.7 10.3 6.7 - 12.8 Pass STW-1260 10/07/11 Uranium 46.6 +/- 0.5 48.6' 39.4 - 54.0 Pass STW-1261 10/07/11 H-3 17435 +/-382 17400 15200 - 19100 Pass 8 Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

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

d The sample was reanalyzed. Result of reanalysis was acceptable, 32.9 +/- 7.4 pCi/L.

Al-1

TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO4 : Dy Cards).

mR Lab Code Date Known Lab Result Control Description Value + 2 sigma Limits Acceptance Environmental, Inc.

2010-2 12/13/2010 100 cm. 4.94 4.65 +/- 0.57 3.46 -6.42 Pass 2010-2 12/13/2010 110 cm. 4.09 3.50 +/- 0.74 2.86 -5.32 Pass 2010-2 12/13/2010 120 cm. 3.43 2.68 +/- 0.36 2.40 -4.46 Pass 2010-2 12/13/2010 150 cm. 2.2 1.75 +/- 0.42 1.54 -2.86 Pass 2010-2 12/13/2010 180 cm. 1.53 1.32 +/- 0.52 1.07 -1.99 Pass 2010-2 12/13/2010 40 cm. 30.89 38.56 +/- 2.11 21.62 -40.16 Pass 2010-2 12/13/2010 50 cm. 19.77 23.35 +/- 1.82 13.84 -25.70 Pass 2010-2 12/13/2010 60 cm. 13.73 14.53 +/- 1.24 9.61 - 17.85 Pass 2010-2 12/13/2010 60 cm. 13.73 15.84 +/- 1.53 9.61 - 17.85 Pass 2010-2 12/13/2010 80 cm. 7.72 8.33 +/- 0.74 5.40 - 10.04 Pass 2010-2 12/13/2010 90 cm. 6.1 5.93 +/- 0.73 4.27 - 7.93 Pass Environmental, Inc.

2011-1 7/6/2011 100 cm. 6.71 5.64 +/- 0.30 4.70 -8.72 Pass 2011-1 7/6/2011 110 cm. 5.54 4.60 +/- 0.46 3.88 -7.20 Pass 2011-1 7/6/2011 120 cm. 4.66 4.68 +/- 0.29 3.26 -6.06 Pass 2011-1 7/6/2011 150 cm. 2.98 2.93 +/- 0.66 2.09 -3.87 Pass 2011-1 7/6/2011 180 cm. 2.07 2.05 +/- 0.18 1.45 -2.69 Pass 2011-1 7/6/2011 40 cm. 41.92 52.36 +/- 3.08 29.34 - 54.50 Pass 2011-1 7/6/2011 45 cm. 33.12 41.83 +/- 3.46 23.18 - 43.06 Pass 2011-1 7/6/2011 50 cm. 26.83 28.61 +/- 2.63 18.78 - 34.88 Pass 2011-1 7/6/2011 60 cm. 18.63 21.00 +/- 1.15 13.04 - 24.22 Pass 2011-1 7/6/2011 70 cm. 13.69 13.24 +/- 1.76 9.58-17.80 Pass 2011-1 7/6/2011 80 cm. 10.48 12.18 +/- 0.65 7.34 -13.62 Pass 2011-1 7/6/2011 90 cm. 8.28 7.95 +/- 0.82 5.80 - 10.76 Pass A2-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=lc Activity Limits d Acceptance SPW-202 1/17/2011 U-238 4.19 +/- 0.19 4.17 0.00 - 16.17 Pass W-20111 2/1/2011 Ra-226 16.32 +/- 0.47 16.77 11.74 - 21.80 Pass W-20711 2/7/2011 Gr. Alpha 23.02 +/- 0.45 20.00 10.00 - 30.00 Pass W-20711 2/7/2011 Gr. Beta 46.59 +/- 0.41 45.20 35.20 - 55.20 Pass XWW-331 2/11/2011 Ba-133 144.30 +/- 8.50 144.40 129.96 - 158.84 Pass XWW-331 2/11/2011 Cs-134 22.20 +/- 3.70 21.50 11.50 - 31.50 Pass XWW-331 2/11/2011 Cs-137 64.70 +/- 7.40 61.00 51.00 -71.00 Pass XWW-331 2/11/2011 H-3 13399 +/- 334 12538 10030 -15046 Pass SPAP-567 2/14/2011 Gr. Beta 46.90 +/- 0.11 48.10 28.86 - 67.34 Pass SPAP-569 2/14/2011 Cs-134 7.70 +/- 1.70 7,49 0.00 - 17.49 Pass SPAP-569 2/14/2011 Cs-137 102.47 +/- 3.20 106.79 96.11 -117.47 Pass SPAP-571 2/14/2011 H-3 75815 +/- 542 73230 58584 - 87876 Pass SPW-581 2/15/2011 Cs-1 34 39.91 +/- 1.38 37.45 27.45 - 47.45 Pass SPW-581 2/15/2011 Cs-137 56.28 +/- 2.28 53.39 43.39 - 63.39 Pass SPW-581 2/15/2011 Sr-89 112.92 +/- 5.61 121.42 97.14 - 145.70 Pass SPW-581 2/15/2011 Sr-90 47.80 +/- 2.02 42.07 33.66 - 50.48 Pass SPMI-583 2/15/2011 Cs-137 57.04 +/- 2.76 53.39 43.39 - 63.39 Pass SPMI-583 2/15/2011 Sr-90 36.27 +/- 1.47 42.07 33.66 - 50.48 Pass SPW-602 2/17/2011 U-238 3.98 +/- 0.19 4.17 0.00 -16.17 Pass SPW-686 2/25/2011 Ni-63 167.41 +/- 3.05 208.11 145.68 - 270.54 Pass SPF-1113 3/17/2011 Cs-137 2369 +/- 22 2170 1953 -2387 Pass XWW-1602 3/21/2011 Ba-133 26.83 +/- 6.35 28.58 18.58 -38.58 Pass XWW-1602 3/21/2011 Cs-134 18.90 +/- 4.06 16.30 6.30 - 26.30 Pass XWW-1602 3/21/2011 Cs-137 33.98 +/- 5.88 30.50 20.50 - 40.50 Pass XWW-1602 3/21/2011 H-3 7348 +/- 248 7617 6094 -9140 Pass XWW-2537 4/4/2011 Ba-133 43.40 +/- 4.26 42.70 32.70 - 52.70 Pass XWW-2537 4/4/2011 Cs-1 34 13.50 +/- 2.40 11.90 1.90 -21.90 Pass XWW-2537 4/4/2011 Cs-137 68.30 +/- 5.90 60.70 50.70 - 70.70 Pass XWW-2537 4/4/2011 H-3 7134 +/- 257 7234 5787 - 8681 Pass SPW-2877 5/3/2011 Ra-228 25.23 +/- 2.48 31.62 22.13 - 41.11 Pass SPMI-3167 5/24/2011 Cs-134 33.04 +/- 8.25 34.19 24.19 -44.19 Pass SPMI-3167 5/24/2011 Cs-137 51.53 +/- 8.63 53.06 43.06 - 63.06 Pass SPMI-3167 5/24/2011 Sr-89 90.89 +/- 4.30 93.47 74.78 - 112.16 Pass SPMI-3167 5/24/2011 Sr-90 41.17 +/- 1.53 41.80 33.44 -50.16 Pass W-52411 5/24/2011 Ra-226 17.90 +/- 0.42 16.80 11.76 - 21.84 Pass W-60711 6/7/2011 Gr. Alpha 23.00 +/- 0.49 20.00 10.00 -30.00 Pass W-60711 6/7/2011 Gr. Beta 43.27 +/- 0.42 45.20 35.20 - 55.20 Pass SPAP-4167 7/7/2011 Cs-134 6.92 +/- 1.45 6.57 0.00 - 16.57 Pass SPAP-4167 7/7/2011 Cs-137 108.02 +/- 2.84 105.80 95.22 -116.38 Pass SPW-4169 7/7/2011 Cs-134 34.52 +/- 4.79 32.84 22.84 - 42.84 Pass SPW-4169 7/7/2011 Cs-137 58.29 +/- 6.19 52.92 42.92 - 62.92 Pass A3-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)8 Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 Activity Limitsc Acceptance SPW-4169 7/7/2011 Sr-89 66.12 +/- 4.18 69.64 55.71 -83.57 Pass SPW-4169 7/7/2011 Sr-90 41.72 +/- 1.79 41.68 33.34 - 50.02 Pass SPW-4171 7/7/2011 H-3 70582 +/- 767 71646 57317 - 85975 Pass SPW-4180 7/7/2011 Tc-99 95.69 +/- 1.65 97.02 67.91 -126.13 Pass SPW-41821 7/7/2011 Ra-228 32.57 +/- 2.63 30.63 21.44 - 39.82 Pass SPW-4241 7/7/2011 Ni-63 403.01 +/- 4.66 415.20 290.64 - 539.76 Pass SPW-4180 7/8/2011 Tc-99 100.30 +/- 1.75 97.02 67.91 - 126.13 Pass SPW-5029 7/29/2011 C-1 4 3991 +/- 17 4739 2843 - 6634 Pass SPW-5031 7/29/2011 Fe-55 13801 +/-331 14895 11916 -17874 Pass W-91411 9/14/2011 Gr. Alpha 21.58 +/- 0.44 20.00 10.00 -30.00 Pass W-91411 9/14/2011 Gr. Beta 43.02 +/- 0.40 45.20 35.20 - 55.20 Pass SPW-91511 9/15/2011 Tc-99 29.92 +/- 1.07 32.34 20.34 - 44.34 Pass W-91911 9/19/2011 Ra-226 17.06 +/- 0.42 16.80 11.76 -21.84 Pass W-100711 10/7/2011 Gr. Alpha 22.05 +/- 0.45 20.00 10.00 -30.00 Pass W-100711 10/7/2011 Gr. Beta 45.51 +/- 0.41 45.20 35.20 - 55.20 Pass W-101111 10/11/2011 Ra-226 16.02 +/- 0.40 16.80 11.76 - 21.84 Pass XWW-7220 11/17/2011 Ba-133 25.11 +/- 4.36 27.47 17.47 - 37.47 Pass XWW-7220 11/17/2011 Cs-134 14.09 +/- 3.11 16.60 6.60 - 26.60 Pass XWW-7220 11/17/2011 Cs-137 35.59 +/- 4.28 29.98 19.98 - 39.98 Pass W-113011 11/30/2011 Ra-226 16.12 +/- 0.39 16.80 11.76 -21.84 Pass W-120111 12/1/2011 Gr. Alpha 21.34 +/- 0.43 20.00 10.00 -30.00 Pass W-120111 12/1/2011 Gr. Beta 45.55 +/- 0.41 45.20 35.20 - 55.20 Pass SPW-41823 12/9/2011 Ra-228 26.98 +/- 2.38 29.40 20.58 - 38.22 Pass SPMI-8906 12/22/2011 Cs-134 29.11 +/- 3.52 28.14 18.14 - 38.14 Pass SPMI-8906 12/22/2011 Cs-137 58.27 +/- 7.62 52.36 42.36 - 62.36 Pass SPW-8916 12/22/2011 Cs-134 31.74 +/- 3.63 28.14 18.14 -38.14 Pass SPW-8916 12/22/2011 Cs-137 56.48 +/- 6.12 52.36 42.36 - 62.36 Pass SPAP-8902 12/23/2011 Gr. Beta 45.72 +/- 0.11 47.11 28.27 - 65.95 Pass SPAP-8904 12/23/2011 Cs- 134 5.19 +/- 0.63 5.63 0.00 - 15.63 Pass SPAP-8904 12/23/2011 Cs-137 101.21 +/- 2.55 104.71 94.24 - 115.18 Pass SPW-8918 12/23/2011 H-3 136759 +/- 1056 137638 110110 -165166 Pass SPW-8922 12/23/2011 Ni-63 202.21 + 3.75 206.88 144.82 - 268.94 Pass SPW-8924 12/23/2011 Tc-99 126.10 +/- 1.86 129.36 90.55 - 168.17 Pass SPF-8926 12/23/2011 Cs- 134 0.34 +/- 0.01 0.33 0.20 - 0.47 Pass SPF-8926 12/23/2011 Cs-137 2.34 +/- 0.02 2.09 1.25 -2.93 Pass 3

a Liquid sample results are reported In pCi/Liter, air filters( pCi/filter), charcoal (pCi/ra ), and solid samples (pCi/g).

Laboratory codes as follows: W (water), MI (milk), AP (air filter), SO (soil), VE (vegetation),

CH (charcoal canister), F (fish), U (urine).

Results are based on single determinations.

d Control limits are established from the precision values listed in Attachment A of this report, adjusted to +/- 2a.

NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.

A3-2

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results (4.66y) Acceptance Type LLD Activityc Criteria (4.66 a)

SPW-202 Water 1/17/2011 U-238 0.10 0.12 t 0.12 W-20111 Water 2/1/2011 Ra-226 0.04 0.05 +/- 0.03 1 W-20711 Water 2/7/2011 Gr. Alpha 0.44 -0.02 +/- 0.29 W-20711 Water 2/7/2011 Gr. Beta 0.75 -0.03 +/- 0.53 3.2 SPAP-566 Air Filter 2/14/2011 Gr. Beta 0.64 2.24 +/- 0.61 3.2 SPAP-568 Air Filter 2/14/2011 Cs-1 34 2.34 100 SPAP-568 Air Filter 2/14/2011 Cs-1 37 1.56 100 SPAP-570 Air Filter 2/14/2011 H-3 103.20 -49.40 +/- 52.50 200 SPW-580 Water 2/15/2011 Cs-1 34 2.68 10 SPW-580 Water 2/15/2011 Cs-137 2.84 10 SPW-580 Water 2/15/2011 Sr-89 0.73 0.24 +/- 0.57 5 SPW-580 Water 2/15/2011 Sr-90 0.57 0.02 +/- 0.27 1 SPMI-582 Milk 2/15/2011 Cs-134 3.49 10 SPMI-582 Milk 2/15/2011 Cs-137 3.54 10 SPMI-582 Milk 2/15/2011 1-131(G) 4.14 20 SPMI-582 Milk 2/15/2011 Sr-89 0.71 0.16 +/- 0.67 5 SPMI-582 Milk 2/15/2011 Sr-90 0.55 0.59 +/- 0.32 1 SPW-601 Water 2/17/2011 U-238 0.20 0.09 +/- 0.17 1 SPW-685 Water 2/25/2011 Ni-63 1.61 0.05 +/- 0.98 20 SPF-1112 Fish 3/17)2011 Cs-134 6.74 100 SPF-1112 Fish 3/17/2011 Cs-137 5.45 100 BKW-401 11 Water 4/1/2011 1-131 4.16 10 BKW-401 11 Water 4/1/2011 Co-60 3.11 10 BKW-401 11 Water 4/1/2011 Cs-1 34 4.73 10 BKW-401 11 Water 4/1/2011 Cs-1 37 5.04 10 SPW-2887 Water 5/3/2011 Ra-228 0.72 0.46 +/- 0.39 2 W-52411 Water 5/24/2011 Ra-226 0.04 0.05 +/- 0.03 1 W-60711 Water 6/7/2011 Gr. Alpha 0.51 0.00 +/- 0.36 W-60711 Water 6/7/2011 Gr. Beta 1.58 0.38 +/- 1.12 3.2 SPAP-4164 Air Filter 7/7/2011 Gr. Beta 0.72 1.04 +/- 0.48 3.2 SPW-4168 Water 7/7/2011 Cs-1 34 3.41 10 SPW-4168 Water 7/7/2011 Cs-137 2.45 10 SPW-4168 Water 7/7/2011 Sr-89 0.72 0.40 +/- 0.50 5 SPW-4168 Water 7/7/2011 Sr-90 0.51 -0.19 +/- 0.21 1 SPW-4171 Water 7/7/2011 H-3 152.00 37.10 +/- 81.80 200 SPW-41811 Water 7/7/2011 Ra-228 0.77 0.51 +/- 0.42 2 A4-1

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysis) Laboratory results (4.66a) Acceptance Type LLD Activityc Criteria (4.66 o)

SPW-4241 Water 7/7/2011 Ni-63 1.70 0.09 +/- 1.03 20 SPW-4179 Water 7/8/2011 Tc-99 1.20 -0.96 +/- 0.71 10 SPW-5028 Water 7/29/2011 C-14 109.80 61.90 +/- 59.20 200 SPW-5031 Water 7/29/2011 Fe-55 140.60 0.00 +/- 85.30 1000 W-91411 Water 9/14/2011 Gr. Alpha 0.48 -0.06 +/- 0.33 1 W-91411 Water 9/14/2011 Gr. Beta 0.78 -0.43 +/- 0.53 3.2 SPW-91511 Water 9/15/2011 Tc-99 1.11 -0.62 +/- 0.66 10 W-91911 Water 9/19/2011 Ra-226 0.03 0.04 +/- 0.02 1 W-100711 Water 10/7/2011 Gr. Alpha 0.44 -0.26 +/- 0.28 1 W-100711 Water 10/7/2011 Gr. Beta 0.76 -0.43 +/- 0.52 3.2 W-10111 Water 10/11/2011 Ra-226 0.04 0.05 +/- 0.03 1 W-113011 Water 11/30/2011 Ra-226 0.03 0.04 +/- 0.02 1 W-120111 Water 12/1/2011 Gr. Alpha 0.41 -0.20 +/- 0.27 W-120111 Water 12/1/2011 Gr. Beta 0.75 -0.10 +/- 0.53 3.2 SPW-41813 Water 12/9/2011 Ra-228 0.71 0.17 +/- 0.35 2 SPMI-8905 Milk 12/22/2011 Cs-134 3.27 10 SPMI-8905 Milk 12/22/2011 Cs-137 3.38 10 SPMI-8905 Milk 12/22/2011 1-131(G) 2.17 20 SPW-8915 Water 12/22/2011 Cs-134 3.37 10 SPW-8915 Water 12/22/2011 Cs-1 37 3.45 10 SPW-8915 Water 12/22/2011 1-131(G) 3.38 20 SPAP-8901 Air Filter 12/23/2011 Gr. Beta 0.78 0.50 +/- 0.46 3.2 SPAP-8903 Air Filter 12/23/2011 Cs-1 34 1.65 100 SPAP-8903 Air Filter 12/23/2011 Cs-137 2.41 100 SPW-8917 Water 12/23/2011 H-3 150.20 -3.04 +/- 78.80 200 SPW-8921 Water 12/23/2011 Ni-63 16.92 -4.60 +/- 10.16 20 SPW-8923 Water 12/23/2011 Tc-99 5.66 -5.45 +/- 3.34 10 SPF-8925 Fish 12/23/2011 Cs-1 34 7.15 100 SPF-8925 Fish 12/23/2011 Cs-137 9.73 100 8 Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

1-131(G); iodine-131 as analyzed by gamma spectroscopy.

c Activity reported is a net activity result, For gamma spectroscopic analysis, activity detected below the LLD value is not reported.

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-20, 21 1/3/2011 Be-7 0.24 +/- 0.14 0.34 +/- 0.17 0.29 +/- 0.11 Pass CF-20, 21 1/3/2011 K-40 10.37 +/- 0.43 9.76 +/- 0.68 10.07 +/- 0.40 Pass CF-20, 21 1/3/2011 Sr-90 0.01 +/- 0.01 0.01 +/- 0.01 0.01 +/- 0.00 Pass WW-65, 66 1/6/2011 H-3 321.91 +/- 97.19 345.76 +/- 98.16 333.83 +/- 69.06 Pass BS-165, 166 1/11/2011 Cs-137 0.13 +/- 0.02 0.15 +/- 0.02 0.14 +/- 0.01 Pass BS-165, 166 1/11/2011 H-3 286.00 +/- 80.00 284.00 +/- 80.00 285.00 +/- 56.57 Pass BS-165, 166 1/11/2011 K-40 14.11 +/- 0.52 13.79 +/- 0.60 13.95 +/- 0.40 Pass BS-176, 177 1/11/2011 H-3 391.00 +/- 92.00 332.00 +/- 89.00 361.50 +/- 64.00 Pass BS-176, 177 1/11/2011 K-40 9.06 +/- 0.44 8.28 +/- 0.81 8.67 00.46 Pass BS-197, 198 1/11/2011 Cs-137 0.14 +/- 0.03 0.15 +/- 0.04 0.15 +/- 0.03 Pass BS-197, 198 1/11/2011 H-3 459.00 +/- 103.00 283.00 +/- 95.00 371.00 + 70.06 Pass BS-197, 198 1/11/2011 K-40 14.40 +/- 0.77 14.16 +/- 1.23 14.28 +/- 0.73 Pass WW-358, 359 1/17/2011 H-3 331.44 +/- 93.05 407.65 +/- 95.91 369.55 - 66.81 Pass DW-20009, 20010 1/19/2011 Ra-226 3.66 +/- 0.57 2.74 +/- 0.43 3.20 +/- 0.36 Pass DW-20009, 20010 1/19/2011 Ra-228 1.51 +/- 0.64 1.36 +/- 0.60 1.44 +/- 0.44 Pass WW-337, 338 1/25/2011 H-3 21986.00 +/- 402.00 21896.00 +/- 401.00 21941.00 +/- 283.90 Pass W-491, 492 1/27/2011 Ra-226 6.70 +/- 0.50 6.10 +/- 0.50 6.40 +/- 0.35 Pass W-491, 492 1/27/2011 Ra-228 6.60 +/- 1.30 8.40 +/- 1.40 7.50 +/- 0.96 Pass DW-20014, 20015 1/28/2011 Gr. Alpha 1.91 +/- 0.71 2.34 +/- 0.80 2.13 - 0.53 Pass SWU-447,448 1/31/2011 Gr. Beta 7.42 +/- 1.17 6.85 +/- 1.11 7.14 +/- 0.81 Pass W-694, 695 2/7/2011 H-3 628.26 +/- 104.30 692.37 +/- 106.89 660.32 +/- 74.67 Pass DW-20022, 20023 2/9/2011 Ra-228 0.71 +/- 0.47 1.13 +/- 0.54 0.92 +/- 0.36 Pass SW-626, 627 2/16/2011 H-3 1268.17 +/- 129.52 1144.65 +/- 125.39 1206.41 +/- 90.14 Pass LW-825, 826 2/24/2011 Gr. Beta 2.65 +/- 0.82 2.45 +/- 0.74 2.55 +/- 0.55 Pass SWT-845, 846 3/1/2011 Gr. Beta 1.11 +/- 0.39 0.80 +/- 0.37 0.96 +/- 0.27 Pass MI-998, 999 3/7/2011 K-40 1760.10 +/- 127.50 1708.50 +/- 131.60 1734.30 +/- 91.62 Pass W-1024, 1025 3/7/2011 H-3 489.83 +/- 101.09 581.39 +/- 105.06 535.61 +/- 72.90 Pass WW-1156, 1157 3/16/2011 Gr. Beta 1.79 +/- 0.78 0.47 +/- 0.66 1.13 +/- 0.51 Pass P-1198, 1199 3/17/2011 H-3 504.00 +/- 133.00 597.00 +/- 136.00 550.50 +/- 95.11 Pass SW-1434, 1435 3/28/2011 H-3 15523.00 +/- 359.00 15968.00 +/- 364.00 15745.50 +/- 255.63 Pass WW-1588, 1589 3/28/2011 Gr. Beta 1.81 +/- 1.23 2.81 +/- 1.38 2.31 +/- 0.92 Pass SG-1714, 1715 3/28/2011 Gr. Alpha 8.82 +/- 0.81 8.58 +/- 0.74 8.70 +/- 0.55 Pass SG-1714, 1715 3/28/2011 Gr. Beta 13.78 +/- 0.65 12.76 +/- 0.58 13.27 +/- 0.44 Pass AP-1862, 1863 3/28/2011 Be-7 0.09 +/- 0.02 0.08 +/- 0.02 0.08 +/- 0.01 Pass W-2143, 2144 3/28/2011 H-3 536.40 +/- 99.37 466.79 +/- 96.46 501.59 +/- 69.25 Pass AP-2269, 2270 3/28/2011 Be-7 0.07 +/- 0.01 0.08 +/- 0.01 0.07 +/- 0.01 Pass DW-20061, 20062 3/28/2011 Gr. Alpha 2.82 +/- 1.33 3.89 +/- 1.26 3.36 +/- 0.92 Pass SWU-1455, 1456 3/29/2011 Gr. Beta 2.50 +/- 0.75 2.75 +/- 0.83 2.62 +/- 0.56 Pass SWU-1522, 1523 3/29/2011 Gr. Beta 1.36 +/- 0.87 2.14 - 0.96 1.75 +/- 0.65 Pass PM-1543, 1544 3/29/2011 Gr. Beta 13.81 +/- 0.26 13.67 +/- 0.27 13.74 +/- 0.19 Pass PM-1543, 1544 3/29/2011 Sr-90 8.12 +/- 3.20 7.71 +/- 3.25 7.91 +/- 2.28 Pass A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SWT-5885, 5886 3/29/2011 Gr. Beta 1.21 +/- 0.54 0.77 +/- 0.54 0.99 +/- 0.38 Pass AP-1883,1884 3/30/2011 Be-7 0.07 +/- 0.01 0.09 +/- 0.02 0.08 +/- 0.01 Pass AP-2248, 2249 3/30/2011 Be-7 0.06 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 Pass DW-20066, 20067 3/30/2011 Ra-226 2.14 +/- 0.16 2.10 +/- 0.16 2.12 +/- 0.11 Pass DW-20066, 20067 3/30/2011 Ra-228 2.55 +/- 0.65 1.78 +/- 0.62 2.17 +/- 0.45 Pass P-1567, 1568 4/1/2011 H-3 289.00 +/- 103.00 296.00 +/- 103.00 292.50 +/- 72.83 Pass MI-1609, 1610 4/4/2011 1-131 0.85 +/- 0.17 0.91 +/- 0.18 0.88 +/- 0.13 Pass MI-1609, 1610 4/4/2011 K-40 1323.80 +/- 112.00 1323.20 +/- 96.22 1323.50 +/- 73.83 Pass MI-1609, 1610 4/4/2011 Sr-90 0.85 +/- 0.33 0.97 +/- 0.34 0.91 +/- 0.24 Pass S-1651, 1652 4/4/2011 Ac-228 0.88 +/- 0.08 1.03 +/- 0.22 0.96 +/- 0.12 Pass S-1651, 1652 4/4/2011 Pb-214 1.09 +/- 0.12 0.84 +/- 0.16 0.97 +/- 0.10 Pass AP-1841, 1842 4/7/2011 Be-7 0.12 +/- 0.02 0.12 +/- 0.01 0.12 +/- 0.01 Pass AP-1841, 1842 4/7/2011 Cs-137 0.00 +/- 0.00 0.00 +/- 0.00 0.00 +/- 0.00 Pass AP-1841, 1842 4/7/2011 1-131(G) 0.02 +/- 0.00 0.03 +/- 0.00 0.03 +/- 0.00 Pass S-1990, 1991 4/7/2011 Ac-228 15.83 +/- 0.39 16.12 +/- 0.64 15.98 +/- 0.37 Pass S-1990, 1991 4/7/2011 Pb-214 11.21 +/- 0.23 11.81 +/- 1.22 11.51 +/- 0.62 Pass WW-2552, 2553 4/7/2011 H-3 761.09 +/- 116.48 759.04 +/- 116.41 760.07 +/- 82.34 Pass PM-1904,1905 4/11/2011 K-40 13585.00 +/- 611.00 14278.00 +/- 648.00 13931.50 +/- 445.32 Pass PM-1904, 1905 4/11/2011 Sr-90 9.94 +/- 3.05 5.62 +/- 2.52 7.78 +/- 1.98 Pass P-2011, 2012 4/11/2011 H-3 670.00 +/- 108.00 619.00 +/- 106.00 644.50 +/- 75.66 Pass WW-2053, 2054 4/13/2011 H-3 220.20 +/- 86.50 246.80 +/- 87.80 233.50 +/- 61.63 Pass BS-2095, 2096 4/13/2011 K-40 12.88 +/- 0.72 13.56 +/- 1.08 13.22 +/- 0.65 Pass DW-20099, 20100 4/13/2011 U-233/4 1.64 +/- 0.40 1.31 +/- 0.34 1.48 +/- 0.26 Pass DW-20099, 20100 4/13/2011 U-238 1.49 +/- 0.39 1.28 +/- 0.33 1.39 +/- 0.26 Pass WW-2416,2417 4/19/2011 H-3 217.10 +/- 97.00 184.90 +/- 95.60 201.00 +/- 68.10 Pass P-2185, 2186 4/20/2011 H-3 405.00 +/- 93.00 504.00 +/- 98.00 454.50 +/- 67.55 Pass WW-2353,2354 4/20/2011 H-3 525.54 +/- 119.74 399.41 +/- 115.99 462.48 +/- 83.35 Pass DW-20115, 20116 4/26/2011 U-233/4 11.94 +/- 2.34 10.71 +/- 1.19 11.33 +/- 1.31 Pass DW-20115, 20116 4/26/2011 U-238 2.70 +/- 1.15 3.89 +/- 0.72 3.30 +/- 0.68 Pass SO-2960, 2961 4/27/2011 K-40 22.63 +/- 1.36 22.90 +/- 0.03 22.77 +/- 0.68 Pass MI-2657, 2658 5/2/2011 K-40 1319.30 +/- 101.30 1403.20 +/- 131.60 1361.25 +/- 83.04 Pass DW-20130, 20131 5/2/2011 U-233/4 7.59 + 0.90 7.62 +/- 0.83 7.61 +/- 0.61 Pass DW-20130, 20131 5/2/2011 U-238 4.67 +/- 0.72 4.84 +/- 0.66 4.76 +/- 0.49 Pass DW-20148, 20149 5/3/2011 U-233/4 6.64 +/- 0.83 6.35 +/- 0.81 6.50 +/- 0.58 Pass DW-20148, 20149 5/3/2011 U-238 6.11 +/- 0.83 5.18 +/- 0.73 5.65 +/- 0.55 Pass PM-2810, 2811 5/4/2011 Cs-134 18.64 + 12.16 33.33 +/- 11.86 25.99 +/- 8.49 Pass PM-2810,2811 5/4/2011 Cs-137 28.99 +/- 14.92 21.17 +/- 12.16 25.08 +/- 9.62 Pass PM-2810,2811 5/4/2011 K-40 14368.00 +/- 720.00 14309.00 +/- 638.00 14338.50 +/- 481.00 Pass WW-3065, 3066 5/16/2011 H-3 280.51 +/- 86.98 179.46 +/- 82.83 229.98 +/- 60.05 Pass WW-3086,3087 5/16/2011 H-3 341.14 +/- 85.94 377.97 +/- 87.43 359.56 +/- 61.30 Pass A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SG-3134, 3135 5/16/2011 Ac-228 11.19 +/- 0.82 12.50 +/- 0.84 11.85 +/- 0.59 Pass SG-3134, 3135 5/16/2011 Pb-214 9.12 +/-0.17 9.37 +/- 0.42 9.25 +/- 0.23 Pass F-3221, 3222 5/23/2011 K-40 2.73 +/- 0.39 2.81 +/- 0.42 2.77 +/- 0.29 Pass SS-3434,3435 5/25/2011 K-40 11533.00 +/- 563.70 11236.00 +/- 566.10 11384.50 +/- 399.45 Pass AP-3329, 3330 5/26/2011 Be-7 0.24 +/- 0.11 0.23 +/- 0.13 0.24 +/- 0.08 Pass WW-3350, 3351 6/1/2011 H-3 235.37 +/- 83.98 173.12 +/- 81.05 204.25 +/- 58.36 Pass G-3413, 3414 6/1/2011 Be-7 0.28 +/- 0.10 0.25 +/- 0.09 0.27 +/- 0.07 Pass G-3413, 3414 6/1/2011 Gr. Beta 11.04 +/- 0.31 10.85 +/- 0.31 10.95 +/- 0.22 Pass G-3413,3414 6/1/2011 K-40 6.80 +/- 0.33 6.71 +/- 0.38 6.76 +/- 0.25 Pass AP-3602, 3603 6/3/2011 Be-7 0.20 +/- 0.08 0.25 +/- 0.10 0.22 +/- 0.07 Pass SO-3797, 3798 6/8/2011 Ac-228 0.99 +/- 0.05 1.00 +/- 0.06 1.00 +/- 0.04 Pass SO-3797, 3798 6/8/2011 Bi-212 1.10 +/- 0.12 1.08 +/- 0.17 1.09 +/- 0.10 Pass SO-3797, 3798 6/8/2011 Bi-214 0.87 +/- 0.02 0.86 +/- 0.02 0.87 +/- 0.01 Pass SO-3797, 3798 6/8/2011 Cs-1 37 0.41 +/- 0.01 0.39 +/- 0.01 0.40 +/- 0.01 Pass SO-3797, 3798 6/8/2011 K-40 16.08 +/- 0.26 16.27 +/- 0.29 16.18 +/- 0.19 Pass SO-3797, 3798 6/8/2011 Pb-212 0.98 +/- 0.10 0.93 +/- 0.02 0.96 +/- 0.05 Pass SO-3797, 3798 6/8/2011 Pb-214 0.95 +/- 0.02 0.91 +/- 0.02 0.93 +/- 0.01 Pass SO-3797, 3798 6/8/2011 Th-232 0.47 +/- 0.05 0.49 +/- 0.04 0.48 +/- 0.03 Pass SO-3797, 3798 6/8/2011 U-233/4 0.16 +/- 0.02 0.15 +/- 0.02 0.16 +/- 0.01 Pass SO-3797, 3798 6/8/2011 U-238 0.16 +/- 0.02 0.13 +/- 0.02 0.15 +/- 0.01 Pass MI-3935, 3936 6/20/2011 K-40 1764.60 +/- 119.40 1843.10 +/- 136.50 1803.85 +/- 90.68 Pass BS-4172, 4173 6/21/2011 Cs-137 51.50 +/- 23.78 48.57 +/- 17.06 50.04 +/- 14.63 Pass BS-4172, 4173 6/21/2011 K-40 11730.00 +/- 679.60 11120.00 +/- 512.30 11425.00 +/- 425.53 Pass DW-20183, 20184 6/21/2011 U-233/4 10.00 +/- 1.00 8.40 +/- 0.90 9.20 +/- 0.67 Pass DW-20183, 20184 6/21/2011 U-238 6.70 +/- 0.80 6.10 +/- 0.80 6.40 +/- 0.57 Pass WW-4019,4020 6/24/2011 Gr. Beta 3.56 +/- 1.20 3.16 +/- 1.21 3.36 +/- 0.85 Pass PM-4193, 4194 6/30/2011 K-40 14795.00 +/- 759.00 14660.00 +/- 750.00 14727.50 +/- 533.52 Pass LW-4235, 4236 6/30/2011 Gr. Beta 2.70 +/- 0.72 2.11 +/- 0.78 2.41 +/- 0.53 Pass AP-4367, 4368 7/7/2011 Be-7 0.17 +/- 0.10 0.19 +/- 0.11 0.18 +/- 0.07 Pass MI-4416, 4417 7/11/2011 K-40 1342.40 +/- 91.49 1447.00 +/- 114.80 1394.70 +/- 73.40 Pass W-4914,4915 7/11/2011 H-3 576.36 +/- 110.35 584.67 +/- 110.67 580.52 +/- 78.14 Pass MI-4438, 4439 7/12/2011 K-40 1280.60 +/- 107.50 1381.20 +/- 112.70 1330.90 +/- 77.87 Pass VE-4481, 4482 7/13/2011 K-40 4452.60 +/- 332.40 4767.90 +/- 349.70 4610.25 +/- 241.24 Pass AP-4677, 4678 7/15/2011 Be-7 0.18 +/- 0.08 0.23 +/- 0.09 0.20 +/- 0.06 Pass W-5537,5538 7/18/2011 H-3 650.13 +/- 105.19 695.39 +/- 106.94 672.76 +/- 75.00 Pass P-4764, 4765 7/19/2011 H-3 179.82 +/- 84.81 138.72 +/- 82.79 159.27 +/- 59.26 Pass WW-5211, 5212 7/24/2011 H-3 191.94 +/- 85.50 136.22 +/- 82.76 164.08 +/- 59.50 Pass A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-4998, 4999 7/25/2011 Be-7 543.90 +/- 158.20 488.30 +/- 163.80 516.10 +/- 113.86 Pass VE-4998, 4999 7/25/2011 K-40 2562.20 +/- 319.80 2414.00 +/- 350.00 2488.10 +/- 237.05 Pass DW-20258, 20259 7/25/2011 U-233/4 21.34 +/- 1.52 24.93 +/- 2.93 23.14 +/- 1.65 Pass DW-20258, 20259 7/25/2011 U-235 0.57 +/- 0.26 0.69 +/- 0.26 0.63 +/- 0,18 Pass DW-20258, 20259 7/25/2011 U-238 14.11 +/- 1.24 15.81 +/- 1.23 14.96 +/- 0.87 Pass DW-20269, 20270 7/25/2011 U-233/4 4.93 +/- 0.73 4.65 +/- 0.68 4.79 +/- 0.50 Pass DW-20269, 20270 7/25/2011 U-238 3.26 +/- 0.60 2.53 +/- 0.50 2.90 +/- 0.39 Pass DW-20280, 20281 7/25/2011 U-233/4 3.58 +/- 0.58 3.33 +/- 0.56 3.46 +/- 0.40 Pass DW-20280, 20281 7/25/2011 U-238 1.64 +/- 0.40 2.11 +/-0.45 1.88 +/- 0.30 Pass MI-5019, 5020 7/26/2011 K-40 1348.50 +/- 101.00 1347.40 +/- 109.70 1347.95 +/- 74.56 Pass W-5447,5448 7/26/2011 H-3 246.31 +/- 99.19 241.99 +/- 99.02 244.15 +/- 70.08 Pass G-5124,5125 7/28/2011 Gr. Beta 7.48 +/- 0.20 7.17 +/- 0.19 7.33 +/- 0.14 Pass AP-5232, 5233 7/28/2011 Be-7 0.15 +/- 0.08 0.22 +/- 0.13 0.19 +/- 0.08 Pass SL-5169, 5170 8/1/2011 Be-7 2.37 +/- 0.16 2.17 +/- 0.17 2.27 +/- 0.12 Pass SL-5169, 5170 8/1/2011 Gr. Beta 4.74 +/- 0.45 3.94 +/- 0.39 4.34 +/- 0.30 Pass SL-5169, 5170 8/1/2011 K-40 3.12 +/- 0.16 2.96 +/- 0.21 3.04 +/- 0.13 Pass G-5190, 5191 8/1/2011 Be-7 3.14 +/- 0.30 3.44 +/- 0.27 3.29 +/- 0.20 Pass G-5190, 5191 8/1/2011 Gr. Beta 8.07 +/- 0.28 7.86 +/- 0.27 7.97 +/- 0.19 Pass G-5190, 5191 8/1/2011 K-40 5.51 +/- 0.46 5.57 +/- 0.44 5.54 +/- 0.32 Pass DW-20291, 20292 8/2/2011 U-233/4 3.24 +/- 0.54 2.60 +/- 0.50 2.92 +/- 0.37 Pass DW-20291, 20292 8/2/2011 U-238 1.59 +/- 0.38 2.00 +/- 0.43 1.80 +/- 0.29 Pass SG-5342,5343 8/5/2011 Ac-228 14.41 +/- 0.36 14.13 +/- 0.48 14.27 +/- 0.30 Pass SG-5342, 5343 8/5/2011 Bi-212 4.14 +/- 0.65 4.73 +/- 1.21 4.44 +/- 0.69 Pass SG-5342, 5343 8/5/2011 K-40 7.67 +/- 0.92 7.95 +/- 1.21 7.81 +/- 0.76 Pass SG-5342, 5343 8/5/2011 Pb-214 10.72 +/- 0.21 10.67 +/- 0.28 10.70 +/- 0.18 Pass SG-5342, 5343 8/5/2011 TI-208 0.96 +/- 0.06 1.00 +/- 0.06 0.98 +/- 0.04 Pass MI-5405, 5406 8/8/2011 K-40 1545.30 +/- 116.00 1388.00 +/- 98.20 1466.65 +/- 75.99 Pass DW-20301, 20302 8/9/2011 Gr. Alpha 6.36 +/- 1.09 5.30 +/- 1.08 5.83 +/- 0.77 Pass DW-20301, 20302 8/9/2011 Gr. Beta 14.36 +/- 0.92 13.51 +/- 0.89 13.94 +/- 0.64 Pass DW-5603, 5604 8/16/2011 Ra-228 1.68 +/- 0.88 2.26 +/- 0.91 1.97 +/- 0.63 Pass VE-5753, 5754 8/22/2011 Be-7 0.78 +/- 0.20 0.75 +/- 0.23 0.77 +/- 0.15 Pass VE-5753, 5754 8/22/2011 K-40 6.16 +/- 0.51 6.63 +/- 0.57 6.40 +/- 0.38 Pass S-5801, 5802 8/29/2011 Ac-228 0.43 +/- 0.09 0.38 +/- 0.07 0.41 +/- 0.06 Pass S-5801, 5802 8/29/2011 K-40 6.54 +/- 0.51 5.96 +/- 0.49 6.25 +/- 0.35 Pass S-5801, 5802 8/29/2011 Pb-212 0.31 +/- 0.03 0.36 +/- 0.03 0.34 +/- 0.02 Pass S-5801, 5802 8/29/2011 Pb-214 0.28 +/- 0.04 0.25 +/- 0.04 0.27 +/- 0.03 Pass S-5801, 5802 8/29/2011 TI-208 0.14 +/- 0.02 0.12 +/- 0.02 0.13 +/- 0.01 Pass S-5801, 5802 8/29/2011 U-235 0.05 +/- 0.02 0.04 +/- 0.01 0.05 +/- 0.01 Pass ME-5996, 5997 9/1/2011 Gr. Alpha 0.03 +/- 0.02 0.03 +/- 0.02 0.03 +/- 0.01 Pass ME-5996, 5997 9/1/2011 Gr. Beta 2.55 +/- 0.07 2.62 +/- 0.07 2.58 +/- 0.05 Pass ME-5996, 5997 9/1/2011 K-40 2.66 +/- 0.35 2.24 +/- 0.58 2.45 +/- 0.34' Pass A5-4

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SL-6017, 6018 9/6/2011 Be-7 0.47 +/- 0.17 0.51 +/- 0.19 0.49 +/- 0.13 Pass SL-6017, 6018 9/6/2011 Gr. Beta 4.23 +/- 0.16 3.94 +/- 0.15 4.09 +/- 0.11 Pass SL-6017, 6018 9/6/2011 K-40 4.43 +/- 0.55 4.24 +/- 0.53 4.34 +/- 0.38 Pass VE-6038, 6039 9/7/2011 Sr-90 1.86 +/- 0.98 2.30 +/- 0.92 2.08 +/- 0.67 Pass SW-6059, 6060 9/8/2011 H-3 219.75 +/- 97.52 177.41 +/- 95.76 198.58 +/- 68.34 Pass VE-6302, 6303 9/13/2011 Be-7 0.76 +/- 0.24 0.85 +/- 0.20 0.81 +/- 0.16 Pass VE-6302, 6303 9/13/201 1 Gr. Beta 27.00 +/- 1.02 25.50 +/- 0.95 26.25 +/- 0.70 Pass VE-6302, 6303 9/13/2011 H-3 6966.00 +/- 249.00 6947.00 +/- 249.00 6956.50 +/- 176.07 Pass VE-6302, 6303 9/13/2011 K-40 20.62 +/- 0.68 20.63 +/- 0.64 20.63 +/- 0.47 Pass W-7098,7099 9/19/2011 H-3 586.61 +/- 103.06 525.71 +/- 100.63 556.16 +/- 72.02 Pass W-6407,6408 9/20/2011 Ra-228 1.61 +/- 0.94 0.79 +/- 0.81 1.20 +/- 0.62 Pass MI-6479, 6480 9/27/2011 K-40 1384.10 +/- 111.10 1411.40 +/- 105.00 1397.75 +/- 76.43 Pass W-6579,6580 9/27/2011 H-3 287.97 +/- 99.68 285.95 +/- 99.60 286.96 +/- 70.45 Pass AP-7015, 7016 9/27/2011 Be-7 0.08 +/- 0.02 0.09 +/- 0.02 0.08 +/- 0.01 Pass AP-6105, 6106 9/28/2011 Be-7 0.11 +/- 0.02 0.09 +/- 0.02 0.10 +/- 0.01 Pass LW-6603, 6604 9/28/2011 Gr. Beta 2.15 +/- 1.04 1.65 +/- 0.90 1.90 +/- 0.69 Pass AP-7056, 7057 9/29/2011 Be-7 0.08 +/- 0.02 0.06 +/- 0.01 0.07 +/- 0.01 Pass G-6730,6731 10/3/2011 Be-7 4.24 +/- 0.36 4.47 +/- 0.37 4.36 +/- 0.26 Pass G-6730, 6731 10/3/2011 Gr. Beta 8.27 +/- 0.33 7.93 +/- 0.31 8.10 +/- 0.23 Pass G-6730, 6731 10/3/2011 K-40 6.46 +/- 0.56 5.41 +/- 0.50 5.94 +/- 0.38 Pass AP-7077, 7078 10/3/2011 Be-7 0.08 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 Pass AP-7077, 7078 10/3/2011 Be-7 0.08 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 Pass VE-6798, 6799 10/4/2011 K-40 11.76 +/- 0.65 11.91 +/- 0.62 11.84 +/- 0.45 Pass AP-6820, 6821 10/6/2011 Be-7 0.22 +/- 0.08 0.18 +/- 0.10 0.20 +/- 0.06 Pass W-7755,7756 10/9/2011 H-3 261.92 +/- 96.52 221.92 +/- 94.80 241.92 +/- 67.65 Pass BS-7944, 7945 10/10/2011 Cs-137 291.17 +/- 34.00 330.68 +/- 36.40 310.93 +/- 24.90 Pass BS-7944, 7945 10/10/2011 K-40 14237.00 +/- 686.40 15359.00 +/- 703.80 14798.00 +/- 491.55 Pass BS-7140, 7141 10/13/2011 K-40 2.59 +/- 0.35 2.58 +/- 0.52 2.59 +/- 0.31 Pass AP-7168, 7169 10/13/2011 Be-7 0.25 +/- 0.09 0.25 +/- 0.11 0.25 +/- 0.07 Pass DW-20349, 20350 10/13/2011 U-233/4 1.77 +/- 0.41 2.25 +/- 0.77 2.01 +/- 0.44 Pass DW-20349, 20350 10/13/2011 U-238 0.28 +/- 0.19 0.31 +/- 0.33 0.30 +/- 0.19 Pass WW-7667,7668 10/19/2011 H-3 1049.11 +/- 116.32 1071.39 +/- 117.10 1060.25 +/- 82.53 Pass WW-7381, 7382 10/21/2011 H-3 1904.40 +/- 145.45 1813.62 +/- 142.91 1859.01 +/- 101.95 Pass SS-7495, 7496 10/26/2011 K-40 10.16 +/- 0.55 9.56 +/- 0.49 9.86 +/- 0.37 Pass W-7516,7517 10/27/2011 H-3 191.46 +/- 84.47 224.05 +/- 86.03 207.76 +/- 60.28 Pass VE-7537, 7538 10/28/2011 K-40 2.08 +/- 0.23 2.41 +/- 0.21 2.24 +/- 0.16 Pass MI-7622, 7623 10/31/2011 K-40 1386.20 +/- 116.80 1407.90 +/- 116.50 1397.05 +/- 82.48 Pass DW-20399, 20400 10/31/2011 U-233/4 5.70 +/- 0.70 5.70 +/- 0.70 5.70 +/- 0.49 Pass DW-20399, 20400 10/31/2011 U-238 3.10 +/- 0.50 3.70 +/- 0.70 3.40 +/- 0.43 Pass BS-7600, 7601 11/1/2011 Gr. Beta 6.83 +/- 1.44 5.31 +/- 1.35 6.07 +/- 0.98 Pass A5-5

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SG-8471, 8472 11/1/2011 Gr. Alpha 13.63 +/-2.32 11.13 +/- 2.00 12.38 +/-1.53 Pass SG-8471, 8472 11/1/2011 Gr. Beta 20.30 +/- 1.43 17.65 +/- 1.42 18.98 +/- 1.01 Pass DW-20424, 20425 11/7/2011 U-233/4 5.90 +/- 0.80 6.10 +/- 0.80 6.00 +/- 0.57 Pass DW-20424, 20425 11/7/2011 U-235 0.10 +/- 0.10 0.30 +/- 0.20 0.20 +/- 0.11 Pass DW-20424, 20425 11/7/2011 U-238 4.30 +/- 0.70 3.70 +/- 0.60 4.00 +/- 0.46 Pass DW-20424, 20425 11/7/2011 U-238 10.30 +/- 1.00 10.10 +/- 1.00 10.20 +/- 0.71 Pass DW-20435, 20436 11/8/2011 U-233/4 11.00 +/- 1.10 10.60 +/- 0.80 10.80 +/-0.68 Pass DW-20435, 20436 11/8/2011 U-238 5.90 +/- 0.80 4.90 +/- 0.60 5.40 +/- 0.50 Pass SG-7902, 7903 11/10/2011 Ac-228 21.38 +/- 0.47 20.48 +/- 0.52 20.93 +/- 0.35 Pass SG-7902, 7903 11/10/2011 K-40 9.72 +/- 1.04 9.53 +/- 0.92 9.63 +/- 0.69 Pass SG-7902, 7903 11/10/2011 Pb-212 3.99 +/- 0.10 3.99 +/- 0.10 3.99 +/- 0.07 Pass SG-7902, 7903 11/10/2011 Pb-214 9.15 +/-0.23 9.14 +/-0.21 9.15 +/-0.16 Pass BS-8033, 8034 11/11/2011 Cs-137 0.03 +/- 0.02 0.03 +/- 0.02 0.03 +/- 0.01 Pass LW-8075, 8076 11/16/2011 Gr. Beta 1.93 +/- 0.62 2.55 +/- 0.64 2.24 +/- 0.44 Pass AP-8193, 8194 11/17/2011 Be-7 0.21 +/- 0.11 0.26 +/- 0.13 0.24 +/- 0.08 Pass F-8663, 8664 11/19/2011 Cs-137 0.03 +/- 0.02 0.03 +/- 0.02 0.03 +/- 0.01 Pass F-8663, 8664 11/19/2011 Gr. Beta 3.55 +/-+0.10 3.71 +/- 0.10 3.63 +/- 0.07 Pass F-8663, 8664 11/19/2011 K-40 3.04 +/- 0.42 3.05 +/- 0.35 3.05 +/- 0.27 Pass DW-20449, 20450 11/28/2011 U-233/4 0.70 +/- 0.20 0.80 +/- 0.20 0.75 +/- 0.14 Pass DW-20449, 20450 11/28/2011 U-238 0.60 +/- 0.20 0.60 +/- 0.20 0.60 +/- 0.14 Pass SWU-8388, 8389 11/29/2011 Gr. Beta 1.66 +/- 0.57 1.65 +/- 0.59 1.66 +/- 0.41 Pass AP-8841, 8842 12/15/2011 Be-7 0.23 +/- 0.12 0.19 +/- 0.09 0.21 +/- 0.07 Pass W-8886, 8887 12/15/2011 Gr. Alpha 0.83 +/- 0.81 1.58 +/- 0.99 1.21 +/- 0.64 Pass W-8886, 8887 12/15/2011 Gr. Beta 6.80 +/- 1.25 5.94 +/- 1.22 6.37 +/- 0.87 Pass W-8886, 8887 12/15/2011 Ra-226 0.23 +/- 0.15 0.41 +/- 0.16 0.32 +/- 0.11 Pass SO-8958, 8959 12/21/2011 K-40 14.58 +/- 0.86 15.07 +/- 0.87 14.83 +/- 0.61 Pass AP-8907, 8908 12/22/2011 Be-7 0.15 +/-0.06 0.11 +/-0.07 0.13 +/-0.05 Pass AP-9196, 9197 12/28/2011 Be-7 0.06 +/- 0.01 0.07 +/- 0.01 0.06 +/- 0.01 Pass LW-9091, 9092 12/29/2011 Gr. Beta 1.97 +/- 0.63 1.74 +/- 0.60 1.86 +/- 0.44 Pass Note: Duplicate analyses are performed on eVEry twentieth sample receiVEd in-house. Results are not listed for those analyses with activities that measure below the LLD.

a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, VEgetation, SOil, sediment (pCi/g).

A5-6

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentration b Known Control Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STW-1237 e 02/01/11 Am-241 0.35 +/- 0.10 0.53 0.37 - 0.69 Fail STW-1237 02/01/11 Co-57 < 0.2 0.00 Pass STW-1237 02/01/11 Co-60 24.10 +/- 0.40 24.60 17.20 -32.00 Pass STW-1237 02/01/11 Cs-134 19.80 +/- 0.40 21.50 15.10 - 28.00 Pass STW-1237 02/01/11 Cs-137 29.40 +/- 0.50 29.40 20.60 - 38.20 Pass STW-1237 02/01/11 H-3 238.90 +/- 8.80 243.00 170.00 - 316.00 Pass STW-1237 02/01/11 K-40 95.40 +/- 3.10 91.00 64.00 - 118.00 Pass STW-1237 02/01/11 Mn-54 32.50 +/- 0.60 31.60 22.10 - 41.10 Pass STW-1237 02/01/11 Ni-63 16.30 +/- 0.60 18.60 13.00 - 24.20 Pass STW-1237 02/01/11 Pu-238 1.11 +/- 0.12 1.06 0.75 - 1.38 Pass STW-1237 02/01/11 Pu-239/40 0.88 +/- 0.12 0.81 0.57 - 1.05 Pass STW-1237 02/01/11 Sr-90 8.70 +/- 0.70 8.72 6.10 -11.34 Pass STW-1237 02/01/11 Tc-99 7.60 +/- 0.60 8.99 6.29-11.69 Pass STW-1237 02/01/11 Zn-65 <0.5 0.00 Pass STW-1238 02/01/11 Gr. Alpha 0.82 +/- 0.07 1.14 0.34-1.93 Pass STW-123B 02/01/11 Gr. Beta 2.82 +/- 0.07 2.96 1.48 - 4.44 Pass STVE-1239 02/01/11 Co-57 11.27 +/- 0.21 9.94 6.96 - 12.92 Pass STVE-1239 02/01/11 Co-60 4.95 +/- 0.16 4.91 3.44 - 6.38 Pass STVE-1 239 02/01/11 Cs-134 5.18 +/- 0.19 5.50 3.85 -7.15 Pass STVE-1239 02/01/11 Cs-137 < 0.09 0.00 Pass STVE-1239 02/01/11 Mn-54 6.91 +/- 0.25 6.40 4.48 - 8.32 Pass STVE-1239 02/01/11 Zn-65 3.10 +/- 0.32 2.99 2.09 - 3.89 Pass STSO-1240 02/01/11 Co-57 984.10 +/- 4.10 927.00 649.00 - 1205.00 Pass STSO-1240 02/01/11 Co-60 540.70 +/- 3.00 482.00 337.00 - 627.00 Pass STSO-1240 02/01/11 Cs-1 34 726.70 +/- 5.92 680.00 476.00 - 884.00 Pass STSO-1240 02/01/11 Cs-137 883.10 +/- 4.70 758.00 531.00 - 985.00 Pass STSO-1240 02/01/11 K-40 622.70 +/- 16.70 540.00 378.00 - 702.00 Pass STSO-1240 02/01/11 Mn-54 -0.30 +/- 1.00 0.00 Pass STSO-1240 02/01/11 Ni-63 384.00 +/- 16.90 582.00 407.00 - 757.00 Fail STSO-1240 02/01/11 U-233/4 166.60 +/- 7.30 176.00 123.00 - 229.00 Pass STSO-1240 02/01/11 U-238 172.00 +/- 7.40 184.00 129.00 -239.00 Pass STSO-1240 02/01/11 Zn-65 1671.00 +/- 13.10 1359.00 951.00 - 1767.00 Pass STAP-1241 02/01/11 Am-241 0.00 +/- 0.01 0.00 -0.10 -0.10 Pass STAP-1241 02/01/11 Co-57 3.48 +/- 0.06 3.33 2.33 - 4.33 Pass STAP-1241 02/01/11 Co-60 0.00 +/- 0.02 0.00 -0.10 -0.10 Pass STAP-1241 02/01/11 Cs-1 34 3.44 +/- 0.27 3.49 2.44 - 4.54 Pass STAP-1241 02/01/11 Cs-1 37 2.46 +/- 0.27 2.28 1.60 -2.96 Pass A6-1

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentration b Known Control Lab Code C Date Analysis Laboratory result Activity Limits d Acceptance STAP-1241 02/01/11 Gr. Alpha 0.39 +/- 0.05 0.66 0.20 -1.12 Pass STAP-1241 02/01/11 Gr. Beta 1.54 +/- 0.07 1.32 0.66 - 1.99 Pass STAP-1241 02/01/11 Mn-54 2.90 +/- 0.10 2.64 1.85 -3.43 Pass STAP-1241 02/01/11 Pu-238 0.07 +/- 0.02 0.10 0.07 -0.13 Pass STAP-1241 02/01/11 Pu-239/40 0.06 +/- 0.02 0.08 0.05 -0.10 Pass STAP-1241 g 02/01/11 Sr-90 1.89 +/- 0.15 1.36 0.95 - 1.77 Fail STAP-1241 02/01/11 U-233/4 0.13 +/- 0.02 0.18 0.13 -0.23 Pass STAP- 1241 02/01/11 U-238 0.14 +/- 0.02 0.19 0.13 -0.24 Pass STAP-1241 02/01/11 Zn-65 3.80 +/- 0.18 3.18 2.23 -4.13 Pass STW-1249 08/01/11 1-129 7.32 +/- 0.30 9.50 6.70 - 12.40 Pass STVE-1250 08/01/11 Co-57 0.01 +/- 0.02 0.00 Pass STVE-1250 08/01/11 Co-60 3.57 +/- 0.13 3.38 2.37 - 4.39 Pass STVE-1250 08/01/11 Cs-134 -0.02 +/- 0.04 0.00 -0.10 -0.10 Pass STVE-1250 08/01/11 Cs-137 5.28 +/- 0.20 4.71 3.30 - 6.12 Pass STVE-1250 08/01/11 Mn-54 6.48 +/- 0.22 5.71 4.00 - 7.42 Pass STVE-1250 08/01/11 Zn-65 7.35 +/- 0.34 6.39 4.47 - 8.31 Pass STSO-1 251 08/01/11 Co-57 1333.90 +/- 4.20 1180.00 826.00 -1534.00 Pass STSO-1251 08/01/11 Co-60 701.30 +/- 3.40 644.00 451.00 -837.00 Pass STSO-1251 08/01/11 Cs-134 0.71 +/- 1.05 0.00 Pass STSO-1251 08/01/11 Cs-1 37 1106.00 +/- 5.60 979.00 685.00 - 1273.00 Pass STSO-1251 08/01/11 K-40 749.20 +/- 19.00 625.00 438.00 -813.00 Pass STSO-1251 08/01/111 Mn-54 984.30 +/- 5.40 848.00 594.00 -1102,00 Pass STSO-1251 08/01/11 Ni-63 0.11 +/- 1.21 0.00 Pass STSO-1251 08/01/11 Pu-238 97.90 +/- 7.40 93.60 65.50 -121.70 Pass STSO-1251 08/01/11 Pu-239/40 78.80 +/- 6.40 77.40 54.20 -100.60 Pass h

STSO-1251 08/01/11 Sr-90 219.40 +/- 16.70 320.00 224.00 -416.00 Fail STSO-1251' 08/01/11 Tc-99 110.00 +/- 8.00 182.00 127.00 -237.00 Fail STSO-1251 08/01/11 U-233/4 267.00 +/- 10.20 263.00 184.00 -342.00 Pass STSO-1251 08/01/11 U-238 280.30 +/- 10.40 274.00 192.00 -356.00 Pass STSO-1251 08/01/11 Zn-65 1639.90 +/- 11.40 1560.00 1092.00 -2028.00 Pass STAP-1252 08/01/11 Co-57 5.06 +/- 0.08 5.09 3.56 - 6.62 Pass STAP-1252 08/01/11 Co-60 3.13 +/- 0.09 3.20 2.24 -4.16 Pass STAP-1252 08/01/11 Cs-134 0.01 +/- 0.03 0.00 -0.10 -0.10 Pass STAP-1252 08/01/11 Cs-137 2.61 +/- 0.09 2.60 1.82 -3.38 Pass STAP- 1252 08/01/11 Mn-54 0.01 +/- 0.03 0.00 -0.10 -0.10 Pass STAP-1252 08/01/11 Pu-238 0.13 +/- 0.02 0.12 0.08 -0.15 Pass STAP-1252 08/01/11 Pu-239/40 0.15 +/- 0.02 0.14 0.10 -0.18 Pass STAP-1252 08/01/11 Sr-90 1.65 +/- 0.16 1.67 1.17 -2.17 Pass A6-2

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentration b Known Control Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STAP-1252 08/01/11 U-233/4 0.17 +/- 0.02 0.16 0.11 -0.21 Pass STAP-1252 08/01/11 U-238 0.17 +/- 0.02 0.17 0.12 -0.22 Pass STAP-1252 08/01/11 Zn-65 4.46 +/- 0.23 4.11 2.88 -5.34 Pass STW-1254 08/01/11 Co-57 37.20 +/- 0.50 36.60 25.60 - 47.60 Pass STW-1254 08/01/11 Co-60 28.80 +/- 0.40 29.30 20.50 - 38.10 Pass STW-1254 08/01/11 Cs-134 18.00 +/- 0.60 19.10 13.40 -24.80 Pass STW-1254 08/01/11 Cs-137 0.06 +/- 0.13 0.00 - Pass STW-1254 08/01/11 H-3 1039.90 +/- 17.90 1014.00 710.00 - 1318.00 Pass STW-1254 08/01/11 K-40 161.40 +/- 4.10 156.00 109.00 - 203.00 Pass STW-1254 08/01/11 Mn-54 25.70 +/- 0.50 25.00 17.50 -32.50 Pass STVV-1254 08/01/11 Ni-63 0.60 +/- 2.00 0.00 - Pass STW-1254 08/01/11 Pu-238 0.04 +/- 0.02 0.02 0.00 - 1.00 Pass STW-1254 08/01/11 Pu-239/40 2.27 +/- 0.14 2.40 1.68 -3.12 Pass STW-1254 08/01/11 Sr-90 15.60 +/- 1.80 14.20 9.90 - 18.50 Pass STW-1254 08/01/11 Tc-99 -0.30 +/- 0.50 0.00 - Pass STW-1254 08/01/11 U-233/4 2.78 +/- 0.20 2.78 1.95 -3.61 Pass STW-1254 08/01/11 U-238 2.86 +/- 0.21 2.89 2.02 -3.76 Pass STW-1254 08/01/11 Zn-65 30.20 +/- 0.90 28.50 20.00 -37.10 Pass STW-1255 08/01/11 Gr. Alpha 0.72 +/- 0.12 0.87 0.26 -1.47 Pass STW-1255 08/01/11 Gr. Beta 4.71 +/- 0.15 4.81 2.41 -7.22 Pass Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

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

e Result of a repeat analysis was still unacceptable. ERA crosschecks for Am-241 were acceptable, but biased low.

Matrix spikes were prepared, ( 5.17 and 51.7 pCi/L), to verify method; results were acceptable, 4.4 and 47.5 pCi/L.

Am-241 has been added to the internal spike and blank program for 2012.

An error in percent recovery was found, result of recalculation, 427.3 +/- 18.8 Bq/kg dry.

9 No errors found in calculation or procedure, results of reanalysis; 1.73 Bq/filter.

hThe analyses were repeated through a strontium column; mean result of triplicate analyses, 304.2 Bq/kg.

The lab does not currently analyze soil for Tc-99, but is evaluating the procedure. After consultation with Eichrom, the analysis was repeated using a matrix spike correction. Mean result of triplicate reanalyses; 183.3 Bq/kg.

A6-3

TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result ' Result d Limits Acceptance STAP-1230 03/21/11 Am-241 46.0 + 1.8 62.5 36.6 -85.7 Pass STAP-1230 03/21/11 Co-60 401.2 +/- 12.1 390,0 302.0 -487.0 Pass STAP-1230 03/21/11 Cs-1 34 268.2 +/- 24.8 279.0 182.0 -345.0 Pass STAP-1230 03/21/11 Cs-137 345.3 +/- 24.9 312.0 234.0 - 410.0 Pass STAP-1230 03/21/11 Mn-54 < 1.9 0.0 Pass STAP-1230 03/21/11 Pu-238 76.1 +/- 3.2 69.0 47.4 -90.7 Pass STAP-1 230 03/21/11 Pu-239/40 70.50 +/- 3.10 65.5 47.5 -85 Pass STAP-1230 03/21/11 Sr-90 208.40 +/- 18.70 185.0 81.4-288 Pass STAP-1230 03/21/11 U-233/4 56.10 +/- 2.10 61.5 38.7 -91 Pass STAP-1230 03/21/11 U-238 58.90 +/- 2.60 61.0 39.0-87 Pass STAP-1230 03/21/11 Uranium 118.50 +/- 5.52 125.0 63.9-199 Pass STAP-1230 03/21/11 Zn-65 312.60 +/- 23.40 279.0 193.0 -386 Pass STAP-1231 03/21/11 Gr. Alpha 88.40 +/- 3.70 74.3 38.5-112 Pass STAP-1231 03/21/11 Gr. Beta 85.10 +/- 2.80 69.5 42.8 -102 Pass STSO-1232 03/21/11 Ac-228 1327.8 +/- 97.5 1490.0 958.0 -2100.0 Pass STSO-1232 03/21/11 Am-241 662.8 +/- 88.1 914.0 546.0 -1170.0 Pass STSO-1 232 03/21/11 Bi-212 1396.2 +/- 185.3 1400.0 368.0 -2090.0 Pass STSO-1 232 03/21/11 Bi-214 841.1 +/- 33.2 725.0 445.0 -1040.0 Pass STSO-1232 03/21/11 Co-60 2423.7 +/- 27.1 2220.0 1620.0 -2980.0 Pass STSO-1232 03/21/11 Cs-134 2481.3 +/- 42.2 2450.0 1580.0 -2950.0 Pass STSO-1 232 03/21/11 Cs-137 2108.2 +/- 30.2 1920.0 1470.0 - 2490.0 Pass STSO-1232 03/21/11 K-40 11497.3 +/- 276.6 11500.0 8320.0 -15600.0 Pass STSO-1232 03/21/11 Mn-54 < 17.4 0.0 Pass STSO-1232 03/21/11 Pb-212 994.7 +/- 30.0 1440.0 931.0 -2030.0 Pass STSO-1232 03/21/11 Pb-214 918.3 +/- 42.6 805.0 482,0 - 1200.0 Pass STSO-1232 03/21/11 Pu-238 1593.6 +/- 156.7 1420.0 813.0 -2000.0 Pass STSO-1232 03/21/11 Pu-239/40 1428.9 +/- 143.4 1400.0 956.0 -1860.0 Pass STSO-1232 03/21/11 Sr-90 8638.0 +/- 442.8 7590.0 2740.0 -12400.0 Pass STSO-1232 03/21/11 Th-234 1350.1 +/- 180.0 962.0 305.0 -1830.0 Pass STSO-1 232 03/21/11 U-233/4 748.0 +/- 94.4 972.0 616.0 - 1210.0 Pass STSO-1232 03/21/11 U-238 909.0 +/- 104.9 962.0 588.0 -1220.0 Pass STSO-1232 03/21/11 Uranium 1690.8 +/- 104.9 1980.0 1130.0 -2670.0 Pass STSO-1232 03/21/11 Zn-65 2356.2 +/- 57.1 1990.0 1580.0 -2670.0 Pass A7-1

TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result C Result d Limits Acceptance STVE-1233 03/21/11 Am-241 2377.5 +/- 83.2 3200.0 1820.0 - 4400.0 Pass STVE-1233 03/21/11 Cm-244 602.9 +/- 38.4 812.0 400.0 - 1260.0 Pass STVE-1233 03/21/11 Co-60 810.2 +/- 32.4 733.0 496.0 - 1050.0 Pass STVE-1 233 03/21/11 Cs-134 849.4 +/-54.5 770.0 441.0 - 1070.0 Pass STVE-1233 03/21/11 Cs-137 889.9 +/- 36.3 829.0 608.0 - 1150.0 Pass STVE-1233 03/21/11 K-40 28146.70 +/- 698.80 25800.0 18500.0 - 36500 Pass STVE-1233 03/21/11 Mn-54 < 19.3 0.0 Pass STVE-1233 03/21/11 Pu-238 3068.10 +/- 170.70 2990.0 1610.0 - 4380 Pass STVE-1233 03/21/11 Pu-239/40 3180.00 +/- 88.90 3100.0 1920.0 - 4230 Pass STVE-1233 03/21/11 Sr-90 8549.20 +/- 675.00 7890.0 4410.0 - 10500 Pass STVE-1233 03/21/11 U-233/4 2418.60 +/- 142.50 2610.0 1790.0 - 3460 Pass STVE-1233 03/21/11 U-238 2417.00 +/- 142.50 2590.0 1820.0 -3270 Pass STVE-1233 03/21/11 Uranium 4929.80 +/- 142.50 5320.0 3660.0 - 6860 Pass STVE-1233 03/21/11 Zn-65 962.40 +/- 62.50 799.0 577.0 - 1090 Pass STW-1234 03/21/11 Am-241 100.0 +/- 6.4 135.0 92.5 - 182.0 Pass STW-1234 03/21/11 Co-60 401.6 +/- 7.2 411.0 358.0 - 486.0 Pass STW-1234 03/21/11 Cs-134 222.7 +/- 12.3 231.0 171.0 -265.0 Pass STW-1234 03/21/11 Cs-137 410.3 +/- 9.5 417.0 354.0 - 500.0 Pass STW-1234 03/21/11 Mn-54 <3.0 0.0 Pass STW-1234 03/21/11 Pu-238 130.9 +/- 5.5 131.0 99.1 - 162.0 Pass STW-1234 03/21/11 Pu-239/40 113.0 +/-5.0 119.0 92.1 - 147.0 Pass STW-1234 03/21/11 Sr-90 739.6 +/- 13.0 773.0 491.0 -1030.0 Pass STW-1234 03/21/11 U-233/4 83.4 +/- 3.8 94.3 71.1 -122.0 Pass STW-1234 03/21/ 11 U-238 85.5 +/- 3.9 93.5 71.4 -116.0 Pass STW-1234 03/21/ 1/t Uranium 172.0 +/- 8.5 192.0 138.0 - 256.0 Pass STW-1234 03/21/11 Zn-65 114.5 +/- 10.8 111.0 94.1 - 138.0 Pass STW-1235 03/21/11 Gr. Alpha 97.6 +/- 2.9 112.0 49.7 - 166.0 Pass STW-1235 03/21/11 Gr. Beta 99.6 +/- 2.0 99.8 58.4 - 146.0 Pass STW-1236 03/21/11 H-3 16307.0 +/- 377.0 15200.0 9900.0 -22500.0 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

b Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg).

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

d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. A known value of "zero" Indicates an analysis was included in the testing series as a "false positive". Control limits are not provided.

A7-2

Appendix B Summary Tables in the format of NRC Radiological Assessment Branch Technical Position Revision 1, November 1979 Page B-1

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Wolf Creek Generating Station Docket No.: 50-482 Location of Facility: Coffey County, Kansas Reporting Period: Annual 2011 Medium of ODCM All Indicator Indicator Location with Control Locations Pathway Analysis and Lower Locations Highest Annual Mean Number of Sampled Total Number of Limit of Name Nonroutine (Unit of Analysis Performed Detection ** Mean (f) Distance and ** Mean (f) ** Mean (f) Reported Measurement) (LLD) ** Range Direction ** Range ** Range Measurements **

Air Particulate Station 53 (pCi/m 3 ) Gross Beta (317) 0.01 0.026 (264/264) 49 0.027 (53/53) 0.027 (53/53) 0 (0.008 - 0.056) 0.8 miles NNE (0.008 - 0.049) (0.011 - 0.052)

Gamma (24)

Be-7 - 0.080 (20/20) 32 0.087 (4/4) 0.079 (4/4) 0 (0.063 - 0.118) 3.1 miles WNW (0.067 - 0.118) (0.068 - 0.087)

Air Radioiodine Station 53 (pCi/m 3) 1-131 (317) 0.07 0.115 (10/264) 18 0.117 (2/53) 0.131 (2/53) 0 (0.094 - 0.131) 3.0 miles SSE (0.103 - 0.131) (0.124 - 0.138)

Direct Radiation Stations 39 & 53 Dosimeters (mR per std. Gamma Dose - 19.5 (164/164) 47 25.1 (4/4) 20.1 (8/8) 0 90-day Qtr.) (172) (10.1 - 29.5) 0.16 miles S (17.6 - 29.5) (16.9 - 25.9)

Surface Water JRR (pCi/I) Gamma (24) - (0/12) N/A N/A - (0/12) 0 Tritium (24) 3,000 12,848 (12/12) SP 12,848 (12/12) - (0/12) 0 (9,847 - 15,523) 3.2 miles SSE (9,847 - 15,523)

Fe-55 (4) - - (0/2) N/A N/A - (0/2) 0 B-12 Ground Water (pCi/I) 1-131 (32) 1 - (0/28) N/A N/A - (0/4) 0 Gamma (32) - (0/28) N/A N/A - (0/4) 0 Tritium (32) 2,000 -(0/28) N/A N/A - (0/4) 0 Page B-2

    • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Wolf Creek Generating Station Docket No.: 50-482 Location of Facility: Coffey County, Kansas Reporting Period: Annual 2011 Medium of ODCM All Indicator Indicator Location with Control Locations Pathway Analysis and Lower Locations Highest Annual Mean Number of Sampled Total Number of Limit of Name Nonroutine (Unit of Analysis Performed Detection ** Mean (f) Distance and ** Mean (f) ** Mean (f) Reported Measurement) (LLD) ** Range Direction ** Range ** Range Measurements **

Drinking BW-1 5 Water 1-131 (24) 1 -(0/12) N/A N/A - (0/12) 0 (pCi/I)

Gross Beta (24) 4 2.6 (12/12) IO-DW 2.6 (12/12) 2.7 (11/12) 0 (1.9-3.9) 26.1 miles SSE (1.9- 3.9) (1.7- 3.5)

Gamma (24) - (0/12) N/A N/A - (0/12) 0 Tritium (8) 2,000 -(0/4) N/A N/A - (0/4) 0 Shoreline Gamma (5) JRR Sediment (pCi/kg dry) K-40 9,611 (3/3) EEA 10,655 (1/1) 7,928 (2/2) 0 (7,582 - 10,655) 3.0 miles NNW (6,479 - 9,377)

Cs-1 37 180 197.5 (2/3) EEA 250.5 (1/1) - (0/2) 0 (144.5 - 250.5) 3.0 miles NNW Fish Gamma (17) JRR (pCi/kg wet)

K-40 3,125(11/11) CCL 3,125(11/11) 3,138 (6/6) 0 (1,955 - 3,538) 0.6 miles E to (1,955 - 3,538) (2,319 - 3,534)

NNW Tritium (17) 8,230 (11/11) CCL 8,230 (11/11) -(0/6) 0 (7,513 - 9,461) 0.6 miles E to (7,513 - 9,461)

NNW Page B-3

    • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)

RADIOLOGICAL ENVIRONMENtAL MONITORING PROGRAM

SUMMARY

Name of Facility: Wolf Creek Generating Station Docket No.: 50-482 Location of Facility: Coffey County, Kansas Reporting Period: Annual 2011 Medium of ODCM All Indicator Indicator Location with Control Locations Pathway Analysis and Lower Locations Highest Annual Mean Number of Sampled Total Number of Limit of Name Nonroutine (Unit of Analysis Performed Detection ** Mean (f) Distance and ** Mean (f) ** Mean (f) Reported Measurement) (LLD) ** Range Direction ** Range ** Range Measurements **

Food and Gamma (18) D-2 Garden (pCi/kg wet) Be-7 1,145 (12/12) Q-6 1,863 (4/4) 848 (6/6) 0 (382 - 4,453) 2.4 miles NW (713 - 4,453) (402 - 1,253)

K-40 - 4,625 (12/12) B-1 9,049 (1/1) 6,453 (6/6) 0 (2,562 - 9,049) 0.8 miles NNE (3,532 - 12,023)

NR-U1 Crops Gamma (4)

(pCi/kg wet)

K-40 14,794 (2/2) NR-D1 15,148 (1/1) 7,795 (2/2) 0 (14,440-15,148) 8.9 miles S (3,379- 12,212)

Bottom Gamma (19) JRR Sediment (pCi/kg dry)

K-40 - 10,600 (17/17) DC 11,185 (2/2) 11,826 (2/2) 0 (8,906- 12,271) 0.8 miles WNW (10,099-12,271) (11,650 - 12,002)

Cs-1 37 - 97 (10/17) UHS 105 (6/10) 91(1/2) 0 (66-120) 0.6 miles E (84-120)

Fe-55 (14) - -(0/14) N/A N/A 0 Page B-4

    • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Wolf Creek Generatinq Station Docket No.: 50-482 Location of Facility: Coffey County, Kansas Reporting Period: Annual 2011 Medium of ODCM All Indicator Indicator Location with Control Locations Pathway Analysis and Lower Locations Highest Annual Mean Number of Sampled Total Number of Limit of Name Nonroutine (Unit of Analysis Performed Detection ** Mean (f) Distance and ** Mean (f) ** Mean (f) Reported Measurement) (LLD) ** Range Direction ** Range ** Range Measurements **

Aquatic Gamma (3) No Control Vegetation (pCi/kg wet) Be-7 1,269 (3/3) MUDS 1,748 (2/2) 0 (289 - 3,208) 1.5 miles WNW (289 - 3,208)

K-40 2,960 (3/3) DC-ALT 3,630 (1/1) 0 (2,612 - 3,630) 1.5 miles NW Terrestrial Gamma (2) No Control Vegetation (pCi/kg wet) Be-7 3,765 (2/2) MUDS 3,765 (2/2) 0 (2,559 - 4,972) 1.5 miles WNW (2,559 - 4,972)

K-40 3,735 (2/2) MUDS 3,735 (2/2) 0 (3,310 -4,161) 1.5 miles WNW (3,310-4,161)

Soil Gamma (1) No Control (pCi/kg dry)

K-40 10,054 (1/1) MUDS 10,054 (1/1) 0 1.5 miles WNW Cs-1 37 112(1/1) MUDS 112(1/1) 0 1.5 miles WNW Deer Gamma (2) No Control (pCi/kg wet)

K-40 2,940 (2/2) C.36 3,124(1/1) 0 (2,756 - 3,124) .36 miles NE Tritium (2) 748 (2/2) Q1.4 1,370 (1/1) 0 (126 - 1,370) 1.4 miles NW Page B-5

    • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)

Air Particulate and Charcoal Filters Location: 002 Collection Collection Volume Gross Beta 1-131 Duplicate 3

Start Date End Date m Concentration Concentration Analysis (pCi/m 3 ) (pCi/m 3 )

27-DEC-10 03-JAN-i 1 303 0.033 +1- 0.004 0.010 03-JAN-i 1 10-JAN- 1l 299 0.026 +1- 0.004 0.010 10-JAN-i 1 17-JAN- 1l 315 0.055 +1- 0.005 0.011 10-JAN-1 1 17-JAN-11 315 0.048 +1- 0.005 ReCount 17-JAN-i 1 24-JAN-I 1 304 0.039 +1- 0.004 < 0.015 24-JAN-i 1 31-JAN-l 1 292 0.031 +1- 0.004 < 0.015 07-FEB-i 1 15-FEB-11 328 0.029 +1- 0.004 < 0.007 15-FEB-11 21-FEB-11 257 0.017 +1- 0.004 < 0.014 21-FEB-11 01-MAR- 1l 339 0.021 +1- 0.003 < 0.007 01-MAR-11 07-MAR-i 1 260 0.033 +1- 0.005 < 0.011 07-MAR-i 1 14-MAR- 1l 295 0.018 +1- 0.004 < 0.012 14-MAR-11 21-MAR-11 302 0.017 +1- 0.004 < 0.023 21-MAR-11 28-MAR-1i1 305 0.030 +1- 0.004 0.099 +/- 0.029 28-MAR-i 1 04-APR-i 1 295 0.035 +1- 0.004 0.128 +/- 0.027 04-APR-i 1 11-APR-11 291 0.023 +1- 0.004 < 0.023 11-APR-11 19-APR- 1l 345 0.024 +1- 0.004 < 0.013 19-APR-11 25-APR-i 1 252 0.009 +1- 0.004 < 0.020 25-APR-i 1 02-MAY-i 1 310 0.013 +1- 0.004 < 0.011 02-MAY-i 1 09-MAY-i 1 293 0.021 +1- 0.004 < 0.012 09-MAY-1i1 16-MAY-11 305 0.014 +1- 0.004 < 0.010 16-MAY-11 23-MAY-1i1 297 0.016 +1- 0.004 < 0.010 23-MAY-i 1 31-MAY- 11 347 0.017 +1- 0.003 < 0.006 31-MAY- 11 06-JUN-11 247 0.025 +1- 0.005 < 0.013 31-MAY- 11 06-JUN-11 247 0.027 +1- 0.005 Duplicate 06-JUN-i 1 14-JUN-11 343 0.025 +1- 0.004 < 0.019 06-JUN-11 14-JUN-11 343 0.029 +1- 0.004 Duplicate 14-JUN-11 20-JUN-11 253 0.026 +1- 0.004 < 0.010 14-JUN-11 20-JUN-i 1 253 0.024 +1- 0.004 Duplicate 20-JUN-11 27-JUN-11 303 0.012 +1- 0.004 < 0.011 27-JUN-11 05-JUL-11 341 0.023 +1- 0.004 < 0.010 05-JUL-11 11-JUL-11 246 0.025 +1- 0.005 < 0.013 11-JUL-11 18-JUL-11 292 0.023 +1- 0.004 < 0.020 11-JUL-11 18-JUL-11 292 0.022 +1- 0.004 Duplicate 18-JUL-11 25-JUL-11 292 0.020 +1- 0.004 < 0.012 25-JUL-11 01-AUG-11 291 0.024 +1- 0.004 < 0.017 01-AUG-11 08-AUG-i 1 297 0.022 +1- 0.004 < 0.015 08-AUG-i 1 15-AUG-11 289 0.023 +1- 0.004 < 0.011 15-AUG- 1l 22-AUG-i 1 292 0.028 +1- 0.004 < 0.013 22-AUG-i 1 30-AUG-1i1 351 0.036 +1- 0.004 < 0.007 30-AUG-i 1 06-SEP-i 1 301 0.038 +1- 0.004 < 0.011 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - I

Air Particulate and Charcoal Filters Location: 002 Collection Collection Volume 3

Gross Beta 1-131 Duplicate m

Start Date End Date Concentration Concentration Analysis (pCi/m 3 ) (pCi/m 3) 06-SEP-i 1 12-SEP-11 259 0.023 +1- 0.004 0.009 12-SEP-11 19-SEP-11 292 0.021 +1- 0.004 0.014 19-SEP-11 26-SEP-i 1 301 0.026 +1- 0.004 0.019 26-SEP-i 1 03-OCT-1i1 295 0.031 +1- 0.004 0.011 26-SEP-i 1 03-OCT-i 1 295 0.027 +1- 0.004 Duplicate 03-OCT-i 1 10-OCT- 1l 297 0.031 +1- 0.004 0.013 10-OCT-11 17-OCT-11 292 0.026 +1- 0.004 0.013 17-OCT-1 I 24-OCT-i 1 299 0.031 +1- 0.004 0.008 24-OCT-1i1 31-OCT-11 296 0.031 +1- 0.004 0.015 31-OCT-11 07-NOV-i 1 300 0.041 +1- 0.004 0.013 07-NOV-i 1 14-NOV-11 314 0.024 +1- 0.004 0.014 14-NOV-i 1 21-NOV-11 303 0.023 +1- 0.004 0.017 21-NOV-11 28-NOV-i 1 304 0.040 +1- 0.005 0.013 28-NOV-i 1 05-DEC-i 1 310 0.026 +1- 0.004 0.017 05-DEC-i 1 12-DEC-11 299 0.046 +1- 0.005 0.010 12-DEC-11 19-DEC-11 285 0.042 +1- 0.005 0.013 19-DEC- 1l 27-DEC- 11 353 0.025 +1- 0.004 0.011 27-DEC-i 1 03-JAN-12 305 0.020 +1- 0.004 0.010 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 2

Air Particulate and Charcoal Filters Location: 018 Collection Collection Volume Gross Beta 1-131 Duplicate Start Date End Date m3 Concentration Concentration Analysis (pCi/m 3 ) (pCi/m 3 )

27-DEC-10 03-JAN-i 1 301 0.033 +1- 0.004 0.010 03-JAN-i 1 10-JAN-11 310 0.023 +1- 0.004 0.010 10-JAN- 1i 17-JAN-11 301 0.053 +1- 0.005 0.012 10-JAN- 1i 17-JAN- 1l 301 0.054 +1- 0.005 ReCount 17-JAN- 11 24-JAN-i 1 303 0.042 +1- 0.005 < 0.015 24-JAN-i 1 31-JAN-11 229 0.023 +1- 0.005 < 0.019 31-JAN-11 07-FEB-i 1 320 0.021 +1- 0.004 < 0.008 07-FEB-1i1 15-FEB-11 336 0.026 +1- 0.003 < 0.007 15-FEB-11 21-FEB-11 260 0.019 +1- 0.004 < 0.014 21-FEB-11 01-MAR-11 345 0.024 +1- 0.004 < 0.007 01-MAR-11 07-MAR-1i1 259 0.031 +1- 0.005 < 0.011 07-MAR-i 1 14-MAR-i 1 288 0.020 +1- 0.004 < 0.012 14-MAR-i 1 21-MAR-11 298 -0.021 0.004 < 0.028 21 -MAR- 1l 28-MAR-i 1 309 0.032 +1- 0.004 0.103 +/- 0.023 28-MAR-i 1 04-APR-i 1 288 0.037 +1- 0.005 0.131 +/-0.026 04-APR-i 1 11-APR-11 297 0.026 +1- 0.004 < 0.022 11-APR-11 19-APR- 1l 337 0.022 +1- 0.004 < 0.015 19-APR-11 25-APR-i 1 250 0.010 +1- 0.004 < 0.019 25-APR-i 1 02-MAY-1i1 305 0.012 +1- 0.004 < 0.011 02-MAY-i 1 09-MAY-i 1 296 0.023 +1- 0.004 < 0.012 09-MAY-i 1 16-MAY-11 306 0.014 +1- 0.004 < 0.010 16-MAY-11 23-MAY-i 1 297 0.011 +1- 0.004 < 0.010 23-MAY-1 1 31 -MAY- 1i 351 0.016 +1- 0.003 < 0.006 23-MAY-i 1 31 -MAY- 1i 351 0.013 +1- 0.003 Duplicate 31-MAY-11 06-JUN-11 250 0.023 +1- 0.005 0.013 06-JUN-11 14-JUN-11 344 0.023 +1- 0.004 0.019 14-JUN-11 20-JUN-11 261 0.019 +1- 0.004 0.009 20-JUN-11 27-JUN-11 305 0.011 +1- 0.003 0.011 27-JUN-11 05-JUL-i 1 346 0.024 +1- 0.004 0.010 05-JUL-1i1 11-JUL-11 257 0.027 +1- 0.005 0.012 11-JUL-11 18-JUL-11 295 0.020 -I-I- 0.004 0.020 18-JUL-11 25-JUL-11 296 0.021 +1- 0.004 0.012 25-JUL-11 01-AUG-11 295 0.023 +1- 0.004 0.017 01-AUG-11 08-AUG-i 1 298 0.019 +1- 0.004 0.015 08-AUG-1 1 15-AUG-11 292 0.025 +1- 0.004 0.011 15-AUG-11 22-AUG-i 1 300 0.035 +1- 0.004 0.012 22-AUG-i 1 30-AUG-i 1 344 0.031 +1- 0.004 0.007 30-AUG-i 1 06-SEP-1i1 300 0.037 +1- 0.004 0.011 06-SEP-i 1 12-SEP-11 259 0.026 +1- 0.005 0.009 12-SEP-11 19-SEP-11 293 0.020 +1- 0.004 0.014 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 3

Air Particulate and Charcoal Filters Location: 018 Collection Collection Volume Gross Beta 1-131 Duplicate m3 Concentration Analysis Start Date End Date Concentration (pCi/m 3 ) (pCi/m 3 )

19-SEP-11 26-SEP-11 307 0.025 +1- 0.004 0.019 26-SEP-i 1 03-OCT-i 1 297 0.030 +1- 0.004 0.011 03-OCT-i 1 10-OCT-11 300 0.030 +1- 0.004 0.013 10-OCT- 11 17-OCT-11 295 0.020 +1- 0.004 0.013 17-OCT- 11 24-OCT-1i1 309 0.033 +1- 0.004 0.008 24-OCT-1i1 31-OCT-11 296 0.030 +1- 0.004 0.015 24-OCT-1i1 31-OCT-11 296 0.028 +1- 0.004 Duplicate 31-OCT-11 07-NOV-i 1 301 0.035 +1- 0.004 0.013 07-NOV-i 1 14-NOV-1 1 311 0.024 +1- 0.004 0.014 14-NOV-i 1 21-NOV-11 306 0.024 +1- 0.004 0.016 21-NOV-11 28-NOV-i 1 297 0.038 -i-I- 0.005 0.013 28-NOV-1i1 05-DEC-i 1 314 0.031 +1- 0.004 0.017 05-DEC-i 1 12-DEC-1 1 301 0.048 +1- 0.005 0.010 12-DEC-11 19-DEC- 1i 277 0.045 +1- 0.005 0.014 19-DEC-1i1 27-DEC-i 1 357 0.026 +1- 0.004 0.011 27-DEC-i 1 03-JAN-12 305 0.017 +1- 0.004 0.010 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 4

Air Particulate and Charcoal Filters Location: 032 Collection Collection Volume3 Gross Beta 1-131 Duplicate Start Date End Date m Concentration Concentration Analysis (pCi/m 3 ) (pCi/m 3) 27-DEC-10 03-JAN-i 1 291 0.030 +1- 0.004 < 0.010 03-JAN-i 1 10-JAN- 1l 309 0.022 +1- 0.004 < 0.010 10-JAN-1 1 17-JAN- 1l 313 0.056 +1- 0.005 < 0.011 10-JAN-1 1 17-JAN- 1l 313 0.053 +1- 0.005 ReCount 17-JAN-11 24-JAN-11 306 0.041 +1- 0.004 < 0.015 24-JAN-i 1 31-JAN-11 291 0.027 +1- 0.004 < 0.015 31-JAN-11 07-FEB-i 1 312 0.019 +1- 0.004 < 0.008 07-FEB-i 1 15-FEB-11 331 0.030 +1- 0.004 < 0.007 15-FEB-11 21-FEB-11 263 0.021 +1- 0.004 < 0.014 21-FEB-11 01-MAR-11 349 0.020 +1- 0.003 < 0.007 01-MAR-11 07-MAR-i 1 267 0.032 +1- 0.004 < 0.011 07-MAR-1 1 14-MAR-11 299 0.018 +1- 0.004 < 0.012 14-MAR-i 1 21-MAR-11 298 0.018 +1- 0.004 < 0.017 21-MAR-11 28-MAR-i 1 314 0.034 +1- 0.004 0.110 +/- 0.022 28-MAR-i 1 04-APR-1i1 288 0.044 +1- 0.005 0.120 +1-0.032 04-APR-i 1 11-APR-11 297 0.021 +1- 0.004 < 0.024 11-APR-11 19-APR-11 346 0.023 +1- 0.004 < 0.018 19-APR-11 25-APR-i 1 258 0.011 +1- 0.004 < 0.019 25-APR-i 1 02-MAY-1i1 311 0.019 +1- 0.004 < 0.011 02-MAY-i 1 09-MAY-i 1 295 0.023 +1- 0.004 < 0.012 09-MAY-i 1 16-MAY- 1l 308 0.012 +1- 0.003 < 0.010 09-MAY-i 1 16-MAY- 1l 308 0.012 +1- 0.003 Duplicate 16-MAY- 1l 23-MAY-i 1 302 0.014 +1- 0.004 < 0.010 23-MAY-i 1 31-MAY-11 359 0.018 +1- 0.003 < 0.006 31-MAY-11 06-JUN-11 252 0.022 +1- 0.005 < 0.013 06-JUN-11 14-JUN-11 345 0.029 +1- 0.004 < 0.019 14-JUN-11 20-JUN-11 265 0.020 +1- 0.004 < 0.009 20-JUN-11 27-JUN-11 306 0.015 +1- 0.004 < 0.010 27-JUN-1 1 05-JUL-11 342 0.023 +1- 0.004 < 0.010 05-JUL-11 11-JUL-11 254 0.030 +1- 0.005 < 0.012 11-JUL-11 18-JUL-11 296 0.021 +1- 0.004 < 0.019 18-JUL-11 25-JUL-11 296 0.022 +1- 0.004 < 0.012 25-JUL-11 01-AUG-11 296 0.025 +1- 0.004 < 0.017 01-AUG-11 08-AUG-1i1 298 0.025 -I-I- 0.004 < 0.015 01-AUG-11 08-AUG-i 1 298 0.025 +1- 0.004 Duplicate 08-AUG-i 1 15-AUG-11 297 0.024 +1- 0.004 < 0.011 15-AUG-11 22-AUG-i 1 301 0.036 +1- 0.004 < 0.012 22-AUG-i 1 30-AUG-I 1 352 0.033 +1- 0.004 < 0.007 30-AUG-i 1 06-SEP-i 1 311 0.038 +1- 0.004 < 0.010 06-SEP-i 1 12-SEP-11 254 0.027 +1- 0.005 < 0.010 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 5

Air Particulate and Charcoal Filters Location: 032 Collection Collection Volume Gross Beta 1-131 Duplicate Start Date End Date m3 Concentration Concentration Analysis (pCi/m 3 ) (pCi/m 3 )

12-SEP-11 19-SEP-11 294 0.020 +1- 0.004 < 0.014 19-SEP-11 26-SEP-i 1 304 0.026 +1- 0.004 < 0.019 19-SEP-11 26-SEP-i 1 304 0.024 +1- 0.004 Duplicate 26-SEP-i 1 03-OCT-1i1 306 0.036 +1- 0.004 0.010 03-OCT-i 1 10-OCT- 1l 293 0.030 +1- 0.004 0.013 10-OCT- 11 17-OCT-11 296 0.021 +1- 0.004 0.013 17-OCT-i 1 24-OCT-i 1 301 0.037 +1- 0.004 0.008 24-OCT-1i1 31-OCT-11 298 0.036 +1- 0.004 0.015 31-OCT-11 07-NOV-i 1 300 0.040 +1- 0.004 0.013 07-NOV-i 1 14-NOV-11 313 0.025 +1- 0.004 0.014 14-NOV-11 21-NOV-11 306 0.024 +1- 0.004 0.016 21 -NOV- 1i 28-NOV-i 1 303 0.040 +1- 0.005 0.013 28-NOV-i 1 05-DEC-i 1 311 0.029 +1- 0.004 0.017 05-DEC-i 1 12-DEC-11 301 0.047 +1- 0.005 0.010 12-DEC-11 19-DEC-11 285 0.038 +1- 0.005 0.013 19-DEC-11 27-DEC-1i1 356 0.025 +1- 0.004 0.011 19-DEC- 1l 27-DEC-1i1 356 0.030 +1- 0.004 Duplicate 27-DEC-1i1 03-JAN-1 2 307 0.015 +1- 0.004 < 0.010 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 6

Air Particulate and Charcoal Filters Location: 037 Collection Collection Volume3 Gross Beta 1-131 Duplicate m

Start Date End Date Concentration Concentration Analysis (pCi/m 3 ) (pCi/m 3 )

27-DEC-10 03-JAN-1i1 290 0.031 +1- 0.004 < 0.010 03-JAN-i 1 10-JAN- 1l 314 0.023 +1- 0.004 < 0.010 03-JAN-1 i 10-JAN- 1l 314 0.025 +1- 0.004 Duplicate 10-JAN- 1 17-JAN-11 326 0.053 +1- 0.005 < 0.011 10-JAN- 1 17-JAN-11 326 0.058 +1- 0.005 ReCount 17-JAN-1i 24-JAN-i 1 316 0.044 +1- 0.004 < 0.015 24-JAN-i 1 31-JAN-11 299 0.023 +1- 0.004 < 0.015 31-JAN-1 I 07-FEB-i 1 313 0.021 +1- 0.004 < 0.008 07-FEB-1 i 15-FEB-11 328 0.028 +1- 0.003 < 0.007 15-FEB-1i 21-FEB-11 254 0.018 +1- 0.004 < 0.014 21-FEB-1i 01-MAR-11 348 0.024 +1- 0.004 < 0.007 21-FEB-1i 01-MAR-11 348 0.022 +1- 0.003 Duplicate 01-MAR-1i 07-MAR-i 1 266 0.031 +1- 0.004 < 0.011 07-MAR-i 1 14-MAR-i 1 290 0.020 +1- 0.004 < 0.012 14-MAR-1i 21-MAR-11 300 0.018 +1- 0.004 < 0.020 21-MAR-1i 28-MAR-i 1 316 0.034 +1- 0.004 0.105 +/-0.021 28-MAR-i 1 04-APR-i 1 291 0.031 +1- 0.004 0.127 +/- 0.031 04-APR-i 1 11-APR-11 299 0.025 +1- 0.004 < 0.026 04-APR-i 1 11-APR-11 299 0.023 +1- 0.004 Duplicate 11-APR-11 19-APR-11 347 0.025 +1- 0.004 < 0.018 19-APR- 1l 25-APR-i 1 256 0.008 +1- 0.004 < 0.019 25-APR-i 1 02-MAY-11 314 0.014 +1- 0.004 < 0.011 25-APR-i 1 02-MAY-i 1 314 0.015 +1- 0.004 Duplicate 02-MAY-i 1 09-MAY-i 1 298 0.024 +1- 0.004 < 0.012 09-MAY-i 1 16-MAY- 1l 315 0.013 +1- 0.003 < 0.009 16-MAY-1i 23-MAY-i 1 295 0.015 +1- 0.004 < 0.010 16-MAY-1i 23-MAY-i 1 295 0.013 +1- 0.004 Duplicate 23-MAY-i 1 31-MAY-11 353 0.018 +1- 0.003 < 0.006 31 -MAY-1i 06-JUN-11 248 0.020 +1- 0.004 < 0.013 06-JUN-11 14-JUN-11 338 0.022 +1- 0.004 < 0.020 14-JUN-11 20-JUN-11 261 0.019 +1- 0.004 < 0.009 20-JUN-i 1 27-JUN-11 309 0.011 +1- 0.003 < 0.010 27-JUN-11 05-JUL-11 347 0.023 +1- 0.003 < 0.010 05-JUL-11 11-JUL-11 249 0.024 +1- 0.005 < 0.013 11-JUL-11 18-JUL-11 294 0.015 +1- 0.004 < 0.020 18-JUL-11 25-JUL-i 1 296 0.018 +1- 0.004 < 0.012 25-JUL-11 01-AUG-11 295 0.021 +1- 0.004 < 0.017 01-AUG-11 08-AUG-i 1 297 0.020 +1- 0.004 < 0.015 08-AUG-i 1 15-AUG-11 293 0.021 +1- 0.004 < 0.011 08-AUG-i 1 15-AUG-11 293 0.023 +1- 0.004 Duplicate 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 7

Air Particulate and Charcoal Filters Location: 037 Collection Collection Volume3 Gross Beta 1-131 Duplicate Start Date End Date m Concentration Concentration Analysis (pCi/m 3 ) (pCi/m 3) 15-AUG- 1l 22-AUG-1i1 301 0.031 +1- 0.004 0.012 22-AUG-i 1 30-AUG-i 1 352 0.030 +1- 0.004 0.007 30-AUG-i 1 06-SEP-11 306 0.032 +1- 0.004 0.011 06-SEP-i 1 12-SEP-11 253 0.024 +1- 0.005 0.010 12-SEP-1i1 19-SEP-11 292 0.017 +1- 0.004 0.014 19-SEP-11 26-SEP-i 1 300 0.028 +1- 0.004 0.019 26-SEP-i 1 03-OCT-i 1 307 0.025 +1- 0.004 0.010 03-OCT-i 1 10-OCT- 1l 293 0.032 +1- 0.004 0.013 10-OCT-11 17-OCT-11 299 0.018 +1- 0.004 0.013 17-OCT-11 24-OCT-i 1 299 0.033 +1- 0.004 0.008 24-OCT-i 1 31-OCT-11 301 0.033 -I-I- 0.004 0.015 31-OCT-11 07-NOV-I 1 299 0.036 +1- 0.004 0.013 07-NOV-i 1 14-NOV-11 308 0.025 +1- 0.004 0.014 14-NOV-11 21-NOV- 1l 303 0.026 +1- 0.004 0.017 21-NOV- 1l 28-NOV-i 1 304 0.038 +1- 0.005 0.013 28-NOV-i 1 05-DEC-i 1 311 0.030 +1- 0.004 0.017 05-DEC-i 1 12-DEC-11 299 0.045 +1- 0.005 0.010 12-DEC-11 19-DEC-11 286 0.043 +1- 0.005 0.013 19-DEC- 1l 27-DEC-i 1 353 0.030 +1- 0.004 0.011 27-DEC-i 1 03-JAN- 12 306 0.017 +1- 0.004 0.010 27-DEC-1 1 03-JAN-1 2 306 0.015 +1- 0.004 Duplicate 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 8

Air Particulate and Charcoal Filters Location: 049 Collection Collection Volume Gross Beta 1-131 Duplicate Start Date m3 Concentration End Date Concentration Analysis (pCi/m 3 ) (pCi/m 3 )

27-DEC-10 03-JAN-i 1 313 0.030 +1- 0.004 < 0.010 27-DEC-10 03-JAN-i 1 313 0.027 +1- 0.004 Duplicate 03-JAN-i 1 10-JAN- 1l 314 0.034 +1- 0.004 < 0.010 10-JAN-1 1 17-JAN- 1l 318 0.049 +1- 0.005 < 0.011 10-JAN- 11 17-JAN- 1l 318 0.053 +1- 0.005 ReCount 17-JAN- 11 24-JAN-1i1 309 0.045 +1- 0.005 < 0.015 24-JAN-i 1 31-JAN-11 292 0.028 +1- 0.004 < 0.015 31-JAN-11 07-FEB-i 1 316 0.020 +1- 0.004 < 0.008 07-FEB-1i1 15-FEB-11 332 0.027 +1- 0.003 < 0.007 15-FEB-11 21;-FEB-11 264 0.016 +1- 0.004 < 0.014 21-FEB-11 01-MAR-11 343 0.023 +1- 0.004 < 0.007 01-MAR-11 07-MAR-i 1 262 0.033 +1- 0.005 < 0.011 07-MAR-i 1 14-MAR-11 294 0.021 +1- 0.004 < 0.012 14-MAR-11 21-MAR-11 307 0.022 +1- 0.004 < 0.017 21-MAR-11 28-MAR-i 1 306 0.034 +1- 0.004 0.094 +/- 0.028 28-MAR-i 1 04-APR-i 1 294 0.039 +1- 0.005 0.131 +/-0.032 04-APR-i 1 11-APR-11 287 0.027 +1- 0.004 < 0.028 11-APR-11 19-APR-11 343 0.025 +1- 0.004 < 0.020 11-APR-11 19-APR- 1l 343 0.026 +1- 0.004 Duplicate 19-APR- 1l 25-APR-i 1 258 0.008 +1- 0.004 < 0.023 19-APR-11 25-APR-i 1 258 0.010 +1- 0.004 Duplicate 25-APR-i 1 02-MAY-i 1 311 0.014 +1- 0.004 < 0.011 02-MAY-i 1 09-MAY-i 1 298 0.023 +1- 0.004 < 0.012 09-MAY-1i1 16-MAY- 1l 302 0.013 +1- 0.004 < 0.010 16-MAY- 1l 23-MAY-1i1 298 0.016 +1- 0.004 < 0.010 23-MAY-i 1 31-MAY-11 350 0.016 +1- 0.003 < 0.006 31-MAY-11 06-JUN-11 251 0.023 +1- 0.005 < 0.013 06-JUN-11 14-JUN-11 344 0.026 +1- 0.004 < 0.019 14-JUN-1i1 20-JUN-11 260 0.023 +1- 0.004 < 0.009 20-JUN-11 27-JUN-i 1 313 0.011 +1- 0.003 < 0.010 27-JUN-i 1 05-JUL-11 342 0.025 +1- 0.004 < 0.010 27-JUN-11 05-JUL-11 342 0.023 +1- 0.004 Duplicate 05-JUL-11 11-JUL-11 250 0.026 +1- 0.005 < 0.013 11-JUL-11 18-JUL-11 294 0.023 +1- 0.004 < 0.020 18-JUL-11 25-JUL-11 296 0.025 +1- 0.004 < 0.012 25-JUL-11 01-AUG-11 297 0.022 +1- 0.004 < 0.017 01-AUG-11 08-AUG-i 1 298 0.021 +1- 0.004 < 0.015 08-AUG-i 1 15-AUG-11 295 0.028 +1- 0.004 < 0.011 15-AUG- 1l 22-AUG-i 1 299 0.032 +1- 0.004 < 0.012 15-AUG- 1l 22-AUG-1 1 299 0.032 +1- 0.004 Duplicate 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 9

Air Particulate and Charcoal Filters Location: 049 Collection Collection Volume Gross Beta 1-131 Duplicate Start Date End Date m3 Concentration Concentration Analysis (pCi/m 3 ) (pCi/m 3 )

22-AUG-i 1 30-AUG-1i1 349 0.033 +1- 0.004 < 0.007 30-AUG-i 1 06-SEP-1i1 298 0.036 +1- 0.004 < 0.011 06-SEP-1i1 12-SEP-11 262 0.028 +1- 0.005 < 0.009 12-SEP-1i1 19-SEP-11 298 0.021 +1- 0.004 < 0.014 19-SEP-11 26-SEP-1i1 302 0.027 +1- 0.004 < 0.019 26-SEP-i 1 03-OCT-i 1 299 0.030 +1- 0.004 < 0.011 03-OCT-1i1 10-OCT-l1 308 0.028 +1- 0.004 < 0.012 10-OCT-i 1 17-OCT- 1l 295 0.020 +1- 0.004 < 0.013 17-OCT- 1l 24-OCT-11 309 0.035 +1- 0.004 < 0.008 24-OCT-i 1 31-OCT-11 300 0.036 +1- 0.004 < 0.015 31-OCT-11 07-NOV-i 1 302 0.036 +1- 0.004 < 0.013 07-NOV-I 1 14-NOV-11 317 0.025 +1- 0.004 < 0.014 14-NOV-11 21-NOV-i 1 318 0.025 +1- 0.004 < 0.016 21-NOV-11 28-NOV-1i1 304 0.040 +1- 0.005 < 0.013 28-NOV-I 1 05-DEC-1i1 312 0.032 +1- 0.004 < 0.017 28-NOV-i 1 05-DEC-1i1 312 0.028 +1- 0.004 Duplicate 05-DEC-i 1 12-DEC-1i1 298 0.049 +1- 0.005 0.010 12-DEC-11 19-DEC-1i1 285 0.045 +1- 0.005 0.013 19-DEC- 1l 27-DEC-i 1 359 0.030 +1- 0.004 0.011 27-DEC-i 1 03-JAN-1 2 312 0.016 +1- 0.004 0.010 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 10

Air Particulate and Charcoal Filters Location: 053 Collection Collection Volume Gross Beta 1-131 Duplicate Start Date End Date m3 Concentration Concentration Analysis (pCi/m 3 ) (pCi/m 3) 27-DEC-10 03-JAN-11 295 0.031 +1- 0.004 0.010 03-JAN-i 1 10-JAN- 1l 309 0.029 +1- 0.004 0.010 10-JAN- 11 17-JAN- 1l 317 0.052 +1- 0.005 0.011 10-JAN-11 17-JAN-11 317 0.056 +1- 0.005 Duplicate 10-JAN-11 17-JAN- 11 317 0.053 +1- 0.005 ReCount 17-JAN- 1i 24-JAN-11 303 0.048 +1- 0.005 < 0.015 24-JAN-11 31-JAN-11 298 0.028 +1- 0.004 < 0.015 31-JAN-11 07-FEB-i 1 302 0.022 +1- 0.004 < 0.008 07-FEB-11 15-FEB-11 333 0.030 +1- 0.004 < 0.007 15-FEB-11 21-FEB-11 241 0.019 +1- 0.004 < 0.015 21-FEB-11 01-MAR-11 344 0.023 +1- 0.004 < 0.007 01-MAR-11 07-MAR-1 1 263 0.030 +1- 0.004 < 0.011 07-MAR-11 14-MAR-11 287 0.018 +1- 0.004 < 0.012 14-MAR-11 21-MAR-11 297 0.018 +1- 0.004 < 0.023 21-MAR-11 28-MAR-i 1 329 0.030 +1- 0.004 0.124 +/- 0.026 28-MAR-i 1 04-APR-i 1 295 0.035 +1- 0.004 0.138 +/- 0.035 04-APR-1i1 11-APR-11 291 0.025 +1- 0.004 < 0.021 11-APR-11 19-APR-11 349 0.024 +1- 0.004 < 0.016 19-APR- 1l 25-APR-11 257 0.011 +1- 0.004 < 0.034 25-APR-1i1 02-MAY-i 1 319 0.013 +1- 0.003 < 0.010 02-MAY-1 1 09-MAY-i 1 306 0.020 +1- 0.004 < 0.012 09-MAY-1 1 16-MAY-11 312 0.011 +1- 0.003 < 0.009 16-MAY- 11 23-MAY-1 1 299 0.015 +1- 0.004 < 0.010 23-MAY-i 1 31-MAY-11 335 0.017 +1- 0.003 < 0.006 31-MAY- 11 06-JUN-11 249 0.026 +1- 0.005 < 0.013 06-JUN-1 1 14-JUN-11 343 0.027 +1- 0.004 < 0.019 14-JUN-11 20-JUN-11 261 0.022 +1- 0.004 < 0.009 20-JUN-11 27-JUN-11 303 0.014 +1- 0.004 < 0.011 27-JUN-11 05-JUL-11 344 0.031 +1- 0.004 < 0.010 05-JUL-11 11-JUL-11 255 0.027 +1- 0.005 < 0.012 11-JUL-11 18-JUL-11 289 0.018 +1- 0.004 < 0.020 18-JUL-11 25-JUL-11 297 0.020 +1- 0.004 < 0.012 25-JUL-11 01-AUG-11 296 0.024 +1- 0.004 < 0.017 01-AUG-11 08-AUG-i 1 299 0.022 +1- 0.004 < 0.015 08-AUG-1 1 15-AUG-11 296 0.025 +1- 0.004 < 0.011 15-AUG- 1l 22-AUG-11 305 0.029 +1- 0.004 < 0.012 22-AUG-i 1 30-AUG-1i1 351 0.034 +1- 0.004 < 0.007 30-AUG-i 1 06-SEP-i 1 301 0.037 -I-I- 0.004 < 0.011 06-SEP-11 12-SEP-11 257 0.026 +1- 0.005 < 0.009 12-SEP-11 19-SEP-11 296 0.020 +1- 0.004 < 0.014 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 11

Air Particulate and Charcoal Filters Location: 053 Collection Collection Volume Gross Beta 1-131 Duplicate Start Date End Date m3 Concentration Concentration Analysis (pCi/m 3 ) (pCi/m 3 )

19-SEP-11 26-SEP-i 1 305 0.025 +1- 0.004 0.019 26-SEP-i 1 03-OCT-i 1 297 0.030 +1- 0.004 0.011 03-OCT-i 1 10-OCT-11 302 0.035 +1- 0.004 0.013 10-OCT- 1l 17-OCT-11 295 0.020 +1- 0.004 0.013 17-OCT- 1l 24-OCT-i 1 306 0.032 +1- 0.004 0.008 24-OCT-i 1 31-OCT-11 299 0.033 +1- 0.004 0.015 31-OCT-11 07-NOV-i 1 302 0.034 +1- 0.004 0.013 07-NOV-i 1 14-NOV-11 307 0.026 +1- 0.004 0.014 14-NOV-11 21-NOV-11 298 0.026 +1- 0.004 0.017 21-NOV-11 28-NOV-i 1 302 0.041 +1- 0.005 0.013 21-NOV-11 28-NOV-i 1 302 0.040 +1- 0.005 Duplicate 28-NOV-i 1 05-DEC-i 1 303 0.031 +1- 0.004 0.017 05-DEC-1i1 12-DEC-11 307 0.044 +1- 0.005 0.009 12-DEC-11 19-DEC-1i1 287 0.044 +1- 0.005 0.013 19-DEC-11 27-DEC-i 1 350 0.028 +1- 0.004 0.011 27-DEC-i 1 03-JAN-1 2 305 0.023 +1- 0.004 0.010 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 12

Quarterly Air Particulate - Gamma Location: 002 28-MAR-11 Nuclide Concentration (pCi/m 3 )

BE-7 0.066+/- 0.013 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.002 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-1 37 < 0.001 27-JUN-11 3 Nuclide Concentration (pCi/m )

BE-7 0.092+/- 0.016 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.001 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-1 34 < 0.001 CS-1 37 < 0.001 03-OCT-1 I 3 Nuclide Concentration (pCi/m )

BE-7 0.087+/- 0.016 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.001 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-137 < 0.001 03-JAN-1 2 3 Nuclide Concentration (pCi/m3 )

BE-7 0.081+/- 0.013 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.001 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-137 < 0.001

Quarterly Air Particulate - Gamma Location: 018 28-MAR-1 I Nuclide Concentration (pCi/m 3 )

BE-7 0.064+/- 0.013 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.001 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-137 < 0.001 27-JUN-11 3 Nuclide Concentration (pCilm )

BE-7 0.084+/- 0.013 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.002 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-1 34 < 0.001 CS-137 < 0.001 03-OCT-1I 3 Nuclide Concentration (pCi/m )

BE-7 0.088+/- 0.015 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.002 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-137 < 0.001 03-JAN-12 3 Nuclide Concentration (pCi/m )

BE-7 0.063+/- 0.011 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.001 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-1 37 < 0.001

Quarterly Air Particulate - Gamma Location: 032 28-MAR-1I Nuclide Concentration (pCi/m 3 )

BE-7 0.067+/- 0.013 BE-7 0.067+/- 0.019 MN-54 < 0.001 MN-54 < 0.001 CO-58 < 0.001 CO-58 < 0.001 FE-59 < 0.001 FE-59 < 0.002 CO-60 < 0.001 CO-60 < 0.001 ZN-65 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-134 < 0.001 CS-137 < 0.001 CS-1 37 < 0.001 27-JUN-11 3 Nuclide Concentration (pCi/m )

BE-7 0.090+/- 0.020 BE-7 0.093+/- 0.014 MN-54 < 0.001 MN-54 < 0.001 CO-58 < 0.001 CO-58 < 0.001 FE-59 < 0.001 FE-59 < 0.002 CO-60 < 0.001 CO-60 < 0.001 ZN-65 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 ZR-NB-95 < 0.001 CS-1 34 < 0.001 CS-134 < 0.001 CS-137 < 0.001 CS-1 37 < 0.001

Quarterly Air Particulate - Gamma Location: 032 03-OCT-11 Nuclide Concentration (pCi/m 3 )

BE-7 0.118+/- 0.016 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.002 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-137 < 0.001 03-JAN-12 3 Nuclide Concentration (DCi/m )

BE-7 0.071+/- 0.012 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.002 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-137 < 0.001

Quarterly Air Particulate - Gamma Location: 037 28-MAR-11 3 Nuclide Concentration (pCi/m )

BE-7 0.079+/- 0.018 MN-54

  • 0.001 CO-58 < 0.001 FE-59 < 0.002 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-137 < 0.001 27-JUN-11 3 Nuclide Concentration (pCi/m )

BE-7 0.092+/- 0.015 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.001 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-137 < 0.001 03-OCT-11 3 Nuclide Concentration (pCi/m )

BE-7 0.075+/- 0.013 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.002 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-1 37 < 0.001 03-JAN-1 2 3 Nuclide Concentration (pCi/m )

BE-7 0.073+/- 0.013 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.001 CO-60 < 0.001 ZN-65 < 0.002 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-137 < 0.001

Quarterly Air Particulate - Gamma Location: 049 28-MAR-1I Nuclide Concentration (pCiIm 3 )

BE-7 0.071+/- 0.015 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.001 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-1 34 < 0.001 CS-1 37 < 0.001 27-JUN-11 3 Nuclide Concentration (pCi/m )

BE-7 0.087+/- 0.017 MN-54 < 0.001 CO-58

  • 0.001 FE-59 < 0.003 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-134
  • 0.001 CS-1 37 < 0.001 03-OCT-1I 3 Nuclide Concentration (pCi/m )

BE-7 0.082+/- 0.011 MN-54

  • 0.001 CO-58 < 0.001 FE-59 < 0.001 CO-60 < 0.001 ZN-65
  • 0.001 ZR-NB-95
  • 0.001 CS-1 34 < 0.001 CS-137 < 0.001 03-JAN-12 Nuclide Concentration (pCi/m 3 )

BE-7 0.068+/- 0.012 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.001 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-137 < 0.001

Quarterly Air Particulate - Gamma Location: 053 28-MAR-1I Nuclide Concentration (pCi/m33 )

BE-7 0.068+/- 0.014 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.001 CO-60 < 0.001 ZN-65 < 0.002 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-137 < 0.001 27-JUN-11 3 Nuclide Concentration (pCi/m3 )

BE-7 0.087+/- 0.014 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.001 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-137 < 0.001 03-OCT-1 I 3 Nuclide Concentration (pCi/m3 )

BE-7 0.085+/- 0.014 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.001 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-134 < 0.001 CS-137 < 0.001 03-JAN-12 3 Nuclide Concentration (pCi/m3 )

BE-7 0.075+/- 0.011 MN-54 < 0.001 CO-58 < 0.001 FE-59 < 0.001 CO-60 < 0.001 ZN-65 < 0.001 ZR-NB-95 < 0.001 CS-1 34 < 0.001 CS-1 37 < 0.001

Exposure Pathway - Waterborne Surface Water Location JRR Gamma Spectrum & H-3 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 31-JAN- 1 MN-54 3.0 31-JAN- 1 CO-58 2.1 31-JAN- 1 FE-59 5.9 31-JAN- 1l CO-60 3.1 31-JAN-i 1 ZN-65 3.4 31-JAN- 1 ZR-NB-95 2.4 31-JAN-i 1 1-131 4.3 31-JAN- 1 CS-134 3.1 31-JAN- 1 CS-1 37 2.3 31-JAN- 1l BA-LA-140 1.4 31-JAN-i 1 H-3 143.0 21-FEB-i 1 MN-54 2.1 21-FEB-i 1 CO-58 2.1 21-FEB-i 1 FE-59 2.9 21-FEB-i 1 CO-60 2.2 21-FEB-i 1 ZN-65 4.7 21-FEB-i 1 ZR-NB-95 2.9 21-FEB-1l 1-131 2.4 21-FEB-1l CS-1 34 2.5 21-FEB-i 1 CS-137 2.5 21-FEB-i 1 BA-LA- 140 2.4 21-FEB-i 1 H-3 147.0 28-MAR-i 1 MN-54 2.6 28-MAR-i 1 CO-58 3.7 28-MAR-i 1 FE-59 4.3 28-MAR-i 1 CO-60 1.9 28-MAR-i 1 ZN-65 5.1 28-MAR-i 1 ZR-NB-95 3.6 28-MAR-i 1 1-131 5.9 28-MAR-i 1 CS-134 3.9 28-MAR-1i1 CS-137 4.1 28-MAR-1i1 BA-LA-140 5.3 28-MAR-1i1 H-3 146.0 20-APR-i 1 MN-54 2.9 20-APR-i 1 CO-58 1.5 20-APR-i 1 FE-59 3.6 20-APR-i 1 CO-60 2.6 20-APR-1i1 ZN-65 4.3 20-APR-i 1 ZR-NB-95 3.4 20-APR-i 1 1-131 6.6 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 20

Exposure Pathway - Waterborne Surface Water Location JRR Gamma Spectrum & H-3 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 20-APR-i 1 CS-134 4.0 20-APR-i 1 CS-1 37 2.7 20-APR-i 1 BA-LA- 140 3.7 20-APR-11 H-3 141.0 19-MAY- 1l MN-54 2.2 19-MAY-11 CO-58 1.8 19-MAY- 1l FE-59 3.7 19-MAY- 1i CO-60 1.0 19-MAY- 1i ZN-65 4.3 19-MAY-1 1 ZR-NB-95 3.1 19-MAY- 1l 1-131 6.4 19-MAY- 1l CS-134 2.8 19-MAY-i l CS-137 2.4 19-MAY- 1l BA-LA-140 2.9 19-MAY- 1l H-3 141.0 20-JUN-11 MN-54 2.2 20-JUN-11 CO-58 1.8 20-JUN-1i1 FE-59 4.0 20-JUN-11 CO-60 2.5 20-JUN-11 ZN-65 3.9 20-JUN-11 ZR-NB-95 3.7 20-JUN-11 1-131 5.7 20-JUN-1i1 CS-1 34 2.7 20-JUN-i 1 CS-1 37 2.8 20-JUN-11 BA-LA- 140 1.6 20-JUN-11 H-3 148.0 18-JUL-1i1 MN-54 5.2 18-JUL-i 1 CO-58 4.2 18-JUL-1i1 FE-59 10.4 18-JUL-11 CO-60 1.1 18-JUL-1i1 ZN-65 3.6 18-JUL-11 ZR-NB-95 2.4 18-JUL-1i1 1-131 5.6 18-JUL-i 1 CS-134 3.7 18-JUL-i 1 CS-137 4.9 18-JUL-1i1 BA-LA- 140 2.7 18-JUL-1i1 H-3 152.0 08-AUG-1i1 MN-54 2.9 08-AUG-1i1 CO-58 2.2 08-AUG-1i1 FE-59 3.4 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 21

Exposure Pathway - Waterborne Surface Water Location JRR Gamma Spectrum & H-3 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 08-AUG-i 1 CO-60 2.7 08-AUG-i 1 ZN-65 4.0 08-AUG-I 1 ZR-NB-95 2.7 08-AUG-i 1 1-131 3.3 08-AUG-i 1 CS-134 2.8 08-AUG-i 1 CS-1 37 2.6 08-AUG-i 1 BA-LA-1 40 3.4 08-AUG-i 1 H-3 185.0 08-AUG-1i1 FE-55 158.0 14-SEP-11 MN-54 2.8 14-SEP-i 1 CO-58 1.7 14-SEP-i 1 FE-59 4.4 14-SEP-11 CO-60 2.2 14-SEP-i 1 ZN-65 2.6 14-SEP-1 1 ZR-NB-95 1.9 14-SEP-1 1 1-131 5.2 14-SEP-11 CS-134 2.4 14-SEP-1i1 CS-137 3.0 14-SEP-i 1 BA-LA- 140 1.7 14-SEP-1 1 H-3 144.0 17-OCT- 11 MN-54 2.0 17-OCT- 11 CO-58 2.7 17-OCT-1 1 FE-59 5.2 17-OCT-i 1 CO-60 1.5 17-OCT-11 ZN-65 4.1 17-OCT- 1l ZR-NB-95 2.8 17-OCT- 1l 1-131 4.1 17-OCT-11 CS-134 2.3 17-OCT-11 CS-1 37 1.7 17-OCT- 1l BA-LA-140 2.0 17-OCT- 1l H-3 145.0 21-NOV-11 MN-54 3.7 21-NOV-11 CO-58 6.3 21-NOV-11 FE-59 10.9 21-NOV-11 CO-60 5.9 21-NOV-11 ZN-65 5.3 21-NOV- 1l ZR-NB-95 3.5 21-NOV-11 1-131 10.5 21-NOV-11 CS-134 4.1 21-NOV-11 CS-137 3.9 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 22

Exposure Pathway - Waterborne Surface Water Location JRR Gamma Spectrum & H-3 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 21-NOV-11 BA-LA- 140 < 6.7 21-NOV-11 H-3 < 137.0 21-NOV-11 FE-55 < 177.0 21-DEC-11 MN-54 < 2.3 21-DEC-11 CO-58 < 2.8 21-DEC-il FE-59 < 2.9 21-DEC-11 CO-60 < 2.6 21-DEC-11 ZN-65 < 2.0 21-DEC-11 ZR-NB-95 < 3.2 21-DEC-11 1-131 < 5.9 21-DEC-11 CS-134 < 3.3 21-DEC-11 CS-137 < 3.4 21-DEC-11 BA-LA-140 < 2.0 21-DEC-l1 H-3 < 151.0 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 23

Exposure Pathway - Waterborne Surface Water Location SP Gamma Spectrum & H-3 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 31-JAN-11 MN-54 1.8 31-JAN- 1l CO-58 2.4 31-JAN-11 FE-59 3.3 31-JAN-11 CO-60 1.0 31-JAN-11 ZN-65 5.8 31-JAN-11 ZR-NB-95 1.8 31-JAN-11 1-131 4.2 31-JAN-11 CS-134 2.5 31-JAN-11 CS-1 37 3.5 31-JAN-11 BA-LA-140 2.7 31-JAN-11 H-3 13,458+1 330.0 21-FEB-11 MN-54 1.5 21-FEB-11 CO-58 1.9 21-FEB-11 FE-59 3.8 21-FEB-11 CO-60 0.9 21-FEB-11 ZN-65 2.7 21-FEB-11 ZR-NB-95 2.9 21-FEB-11 1-131 3.0 21-FEB-11 CS-134 2.4 21-FEB-11 CS-1 37 2.7 21-FEB-11 BA-LA-140 2.8 21-FEB-11 H-3 13,787+1 349.0 28-MAR-i 1 MN-54 2.6 Duplicate 28-MAR-i 1 MN-54 2.8 28-MAR-i 1 CO-58 1.7 Duplicate 28-MAR-i 1 CO-58 2.8 28-MAR-i 1 FE-59 5.8 Duplicate 28-MAR-i 1 FE-59 6.3 28-MAR-i 1 CO-60 1.9 Duplicate 28-MAR-i 1 CO-60 3.9 28-MAR-i 1 ZN-65 3.6 Duplicate 28-MAR-i 1 ZN-65 4.3 28-MAR-i 1 ZR-NB-95 1.9 Duplicate 28-MAR-i 1 ZR-NB-95 3.2 28-MAR-i 1 1-131 4.5 Duplicate 28-MAR-i 1 1-131 5.4 28-MAR-i 1 CS-134 2.1 Duplicate 28-MAR-i 1 CS-134 5.5 28-MAR-i 1 CS-1 37 4.2 Duplicate 28-MAR-i 1 CS-1 37 3.5 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 24

Exposure Pathway - Waterborne Surface Water Location SP Gamma Spectrum & H-3 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 28-MAR-i 1 BA-LA-140 4.2 Duplicate 28-MAR-i 1 BA-LA-140 5.9 28-MAR-i 1 H-3 15,968+/ 364.0 Duplicate 28-MAR-i 1 H-3 15,523 +/- 359.0 20-APR-1i1 MN-54 2.9 20-APR-1i1 CO-58 2.3 20-APR-i 1 FE-59 2.5 20-APR-i 1 CO-60 3.2 20-APR- 11 ZN-65 3.4 20-APR-1i1 ZR-NB-95 3.2 20-APR-1i1 1-131 5.3 20-APR-1i1 CS-134 2.7 20-APR-1i1 CS-1 37 2.2 20-APR-1i1 BA-LA-140 3.0 20-APR-i 1 H-3 14,785+- 354.0 19-MAY- 1i MN-54 1.7 19-MAY- 1i CO-58 2.6 19-MAY- 1i FE-59 7.0 19-MAY- 1i CO-60 1.1 19-MAY-i 1 ZN-65 3.6 19-MAY-i 1 ZR-NB-95 2.5 19-MAY-11 1-131 5.1 19-MAY- 1i CS-134 3.1 19-MAY- 1i CS-137 3.3 19-MAY- 11 BA-LA-140 1.7 19-MAY- 1l H-3 14,066+1 340.0 20-JUN-i 1 MN-54 2.4 20-JUN-11 CO-58 2.5 20-JUN-11 FE-59 4.8 20-JUN-11 CO-60 1.9 20-JUN-11 ZN-65 3.1 20-JUN-11 ZR-NB-95 3.1 20-JUN-11 1-131 4.6 20-JUN-11 CS-134 2.6 20-JUN-11 CS-137 2.1 20-JUN-11 BA-LA-140 5.0 20-JUN-11 H-3 14,374+1 353.0 18-JUL-11 MN-54 2.3 18-JUL-11 CO-58 2.3 18-JUL-11 FE-59 4.8 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 25

Exposure Pathway - Waterborne Surface Water Location SP Gamma Spectrum & H-3 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 18-JUL-11 CO-60 2.5 18-JUL-11 ZN-65 2.6 18-JUL-11 ZR-NB-95 3.1 18-JUL-11 1-131 2.5 18-JUL-11 CS-134 2.4 18-JUL-11 CS-137 2.0 18-JUL-11 BA-LA- 140 2.1 18-JUL-11 H-3 12,794+1 334.0 08-AUG-i 1 MN-54 2.5 08-AUG-i 1 CO-58 3.3 08-AUG-i 1 FE-59 4.5 08-AUG-1 1 CO-60 1.7 08-AUG-i 1 ZN-65 4.1 08-AUG-i 1 ZR-NB-95 4.7 08-AUG-i 1 1-131 6.3 08-AUG-i 1 CS-134 3.0 08-AUG-1i1 CS-137 4.3 08-AUG-i 1 BA-LA-140 4.8 08-AUG-1 I H-3 12,670+- 336.0 08-AUG-i 1 FE-55 161.0 14-SEP-11 MN-54 2.5 14-SEP-11 CO-58 3.9 14-SEP-11 FE-59 5.5 14-SEP-11 CO-60 2.0 14-SEP-11 ZN-65 8.7 14-SEP-11 ZR-NB-95 5.1 14-SEP-1i1 1-131 6.6 14-SEP-i 1 CS-134 2.9 14-SEP-11 CS-137 3.7 14-SEP-11 BA-LA-140 4.2 14-SEP-11 H-3 11,590+- 315.0 17-OCT-11 MN-54 4.1 17-OCT-i 1 CO-58 3.2 17-OCT-11 FE-59 7.5 17-OCT- 1l CO-60 4.0 17-OCT-11 ZN-65 3.9 17-OCT- 1l ZR-NB-95 4.7 17-OCT- 1l 1-131 3.9 17-OCT-11 CS-134 5.6 17-OCT-11 CS-137 5.2 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 26

Exposure Pathway - Waterborne Surface Water Location SP Gamma Spectrum & H-3 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 17-OCT-11 BA-LA-140 5.4 17-OCT-11 H-3 11,095 +/- 307.0 21-NOV-11 MN-54 3.1 21-NOV-11 CO-58 3.9 21-NOV-11 FE-59 5.5 21-NOV-11 CO-60 2.8 21-NOV-11 ZN-65 5.0 21-NOV-11 ZR-NB-95 3.3 21-NOV-11 1-131 8.2 21-NOV-11 CS-134 3.9 21-NOV-11 CS-137 4.3 21-NOV-11 BA-LA-140 5.7 21-NOV-1I H-3 9,847+1 292.0 21-NOV-11 FE-55 176.0 21-DEC-ll MN-54 2.0 21-DEC-11 CO-58 2.5 21-DEC-11 FE-59 4.2 21-DEC-11 CO-60 1.8 21-DEC-11 ZN-65 3.6 21-DEC-11 ZR-NB-95 3.0 21-DEC-11 1-131 4.6 21-DEC-11 CS-134 2.2 21-DEC-11 CS-137 2.1 21-DEC-11 BA-LA-140 1.7 21-DEC-11 H-3 10,186+1 299.0 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 27

Exposure Pathway - Waterborne Ground Water Location B-12 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 28-FEB-11 MN-54 2.5 28-FEB-1i1 CO-58 1.6 28-FEB-i 1 FE-59 2.5 28-FEB-i 1 CO-60 2.1 28-FEB-i 1 ZN-65 2.8 28-FEB-i 1 ZR-NB-95 2.6 28-FEB-1i1 CS-134 2.9 28-FEB-1i1 CS-137 3.2 28-FEB-i 1 BA-LA- 140 2.9 28-FEB-11 H-3 152.0 28-FEB-1i1 1-131 (CHEM) 0.347 23-MAY-i 1 MN-54 4.1 23-MAY-1i1 CO-58 3.6 23-MAY-1i1 FE-59 4.4 23-MAY-1i1 CO-60 2.7 23-MAY-1i1 ZN-65 5.7 23-MAY-1i1 ZR-NB-95 2.8 23-MAY-i 1 CS-134 4.0 23-MAY-1i1 CS-137 4.3 23-MAY-i 1 BA-LA-140 6.2 23-MAY-1i1 H-3 141.0 23-MAY-1i1 1-131 (CHEM) 0.457 08-AUG-i 1 MN-54 2.6 08-AUG-1i1 CO-58 2.5 08-AUG-1i1 FE-59 4.4 08-AUG-1i1 CO-60 3.0 08-AUG-1i1 ZN-65 3.1 08-AUG-1i1 ZR-NB-95 3.0 08-AUG-i 1 CS-134 3.3 08-AUG-1i1 CS-137 3.4 08-AUG-1i1 BA-LA-140 1.7 08-AUG-1i1 H-3 185.0 08-AUG-1i1 1-131 (CHEM) 0.179 21-NOV-11 MN-54 3.2 21-NOV-1i1 CO-58 1.8 21-NOV-1 1 FE-59 3.3 21-NOV-i 1 CO-60 1.8 21-NOV-11 ZN-65 3.0 21-NOV-11 ZR-NB-95 3.2 21-NOV-11 CS-134 2.9 21-NOV-11 CS-137 4.1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 28

Exposure Pathway - Waterborne Ground Water Location B-12 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 21-NOV-11 BA-LA-140 < 2.8 21-NOV-11 H-3 < 137.0 21-NOV-11 1-131 (CHEM) < 0.264 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 29

Exposure Pathway - Waterborne Ground Water Location C-10 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 28-FEB-i 1 MN-54 2.5 28-FEB-i 1 CO-58 2.7 28-FEB-i 1 FE-59 4.1 28-FEB-i 1 CO-60 2.5 28-FEB-i 1 ZN-65 4.1 28-FEB-1i1 ZR-NB-95 2.5 28-FEB-i 1 CS-134 2.3 28-FEB-i 1 CS-137 2.4 28-FEB-i 1 BA-LA- 140 1.4 28-FEB-i 1 H-3 152.0 28-FEB-i 1 1-131 (CHEM) 0.364 23-MAY-i 1 MN-54 1.7 23-MAY-i 1 CO-58 2.2 23-MAY-i 1 FE-59 2.7 23-MAY-1i1 CO-60 2.7 23-MAY-1i1 ZN-65 4.5 23-MAY-1i1 ZR-NB-95 2.5 23-MAY-i 1 CS-134 3.5 23-MAY-1i1 CS-137 3.3 23-MAY-i 1 BA-LA-140 3.6 23-MAY-i 1 H-3 141.0 23-MAY-1i1 1-131 (CHEM) 0.449 08-AUG-1i1 MN-54 2.8 08-AUG-1i1 CO-58 3.4 08-AUG-1i1 FE-59 5.8 08-AUG-1i1 CO-60 1.9 08-AUG-1i1 ZN-65 3.6 08-AUG-i 1 ZR-NB-95 2.9 08-AUG-i 1 CS-134 3.4 08-AUG-i 1 CS-1 37 3.3 08-AUG-i 1 BA-LA-140 3.9 08-AUG-i 1 H-3 185.0 08-AUG-1i1 1-131 (CHEM) 0.247 21-NOV-11 MN-54 2.7 21-NOV- 1l CO-58 2.0 21-NOV-11 FE-59 4.9 21-NOV-11 CO-60 2.4 21-NOV-1 1 ZN-65 3.2 21-NOV-11 ZR-NB-95 3.2 21-NOV-11 CS-134 1.8 21-NOV-11 CS-137 2.4 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 30

Exposure Pathway - Waterborne Ground Water Location C-10 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 21-NOV-11 BA-LA- 140 < 2.3 21-NOV-11 H-3 < 137.0 21-NOV-11 1-131 (CHEM) < 0.306 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 31

Exposure Pathway - Waterborne Ground Water Location C-49 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 28-FEB-i 1 MN-54 < 3.7 28-FEB-i 1 CO-58 < 1.8 28-FEB-11 FE-59 < 3.9 28-FEB-11 CO-60 < 1.4 28-FEB-i 1 ZN-65 < 5.1 28-FEB-11 ZR-NB-95 < 2.2 28-FEB-i 1 CS-134 < 2.4 28-FEB-i 1 CS-137 < 3.5 28-FEB-11 BA-LA-140 < 1.5 28-FEB-i 1 H-3 < 152.0 28-FEB-I 1 1-131 (CHEM) < 0.426 23-MAY-i 1 MN-54 < 2.4 23-MAY-i 1 CO-58 < 1.8 23-MAY-1i1 FE-59 < 3.5 23-MAY-i 1 CO-60 < 1.6 23-MAY-1i1 ZN-65 < 3.7 23-MAY-1i1 ZR-NB-95 < 3.5 23-MAY-1i1 CS-134 < 2.4 23-MAY-1i1 CS-1 37 < 2.1 23-MAY-1i1 BA-LA-140 < 3.7 23-MAY-1 I H-3 < 141.0 23-MAY-i 1 1-131 (CHEM) < 0.486 08-AUG-1i1 MN-54 < 2.2 08-AUG-i 1 MN-54 < 5.6 Duplicate 08-AUG-1i1 CO-58 < 2.2 08-AUG-1i1 CO-58 < 2.9 Duplicate 08-AUG-1i1 FE-59 < 4.6 08-AUG-i 1 FE-59 < 5.9 Duplicate 08-AUG-i 1 CO-60 < 2.3 08-AUG-1i1 CO-60 < 3.9 Duplicate 08-AUG-i 1 ZN-65 < 7.6 08-AUG-1i1 ZN-65 < 9.1 Duplicate 08-AUG-1i1 ZR-NB-95 < 3.8 08-AUG-1i1 ZR-NB-95 < 5.3 Duplicate 08-AUG-1i1 CS-134 < 2.2 08-AUG-1i1 CS-134 < 4.2 Duplicate 08-AUG-1i1 CS-1 37 < 2.6 08-AUG-1i1 CS-137 < 5.3 Duplicate 08-AUG-1i1 BA-LA-140 < 2.6 08-AUG-1i1 BA-LA- 140 < 4.5 Duplicate 08-AUG-i 1 H-3 < 185.0 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 32

Exposure Pathway - Waterborne Ground Water Location C-49 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 08-AUG-i 1 H-3 185.0 Duplicate 08-AUG-i 1 1-131 (CHEM) 0.26 08-AUG-i 1 1-131 (CHEM) 0.301 Duplicate 21-NOV-11 MN-54 1.9 21-NOV-11 CO-58 1.5 21-NOV-11 FE-59 4.9 21-NOV-11 CO-60 1.7 21-NOV-11 ZN-65 2.1 21-NOV-11 ZR-NB-95 3.6 21-NOV-11 CS-134 2.2 21-NOV-11 CS-137 3.6 21-NOV-11 BA-LA-1 40 4.1 21-NOV-11 H-3 137.0 21-NOV-11 1-131 (CHEM) 0.315 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 33

Exposure Pathway - Waterborne Ground Water Location F-1 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 28-FEB-i 1 MN-54 3.1 28-FEB-i 1 CO-58 1.8 28-FEB-i 1 FE-59 4.0 28-FEB-1i1 CO-60 2.4 28-FEB-i 1 ZN-65 3.5 28-FEB-i 1 ZR-NB-95 2.5 28-FEB-i 1 CS-134 2.7 28-FEB-1i1 CS-137 2.8 28-FEB-1i1 BA-LA- 140 1.3 28-FEB-1i1 H-3 152.0 28-FEB-1i1 1-131 (CHEM) 0.379 23-MAY-1i1 MN-54 2.1 23-MAY-i 1 CO-58 1.7 23-MAY-1i1 FE-59 2.8 23-MAY-1i1 CO-60 1.1 23-MAY-1i1 ZN-65 2.0 23-MAY-1i1 ZR-NB-95 3.4 23-MAY-1i1 CS-134 2.4 23-MAY-1i1 CS-1 37 2.0 23-MAY-1i1 BA-LA-140 1.7 23-MAY-1i1 H-3 141.0 23-MAY-i 1 1-131 (CHEM) 0.339 08-AUG-1i1 MN-54 3.0 08-AUG-1i1 CO-58 3.0 08-AUG-1i1 FE-59 3.5 08-AUG-1i1 CO-60 1.6 08-AUG-1i1 ZN-65 4.9 08-AUG-1i1 ZR-NB-95 2.2 08-AUG-1i1 CS-134 2.5 08-AUG-1i1 CS-137 3.5 08-AUG-1i1 BA-LA-140 1.5 08-AUG-1i1 H-3 185.0 08-AUG-1i1 1-131 (CHEM) 0.215 21-NOV-1 1 MN-54 4.8 21-NOV-11 CO-58 3.3 21-NOV-1i1 FE-59 9.9 21-NOV- 1i CO-60 6.0 21-NOV- 1i ZN-65 7.4 21-NOV-1 1 ZR-NB-95 6.0 21-NOV-11 CS-134 4.8 21-NOV-11 CS-137 5.4 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 34

Exposure Pathway - Waterborne Ground Water Location F-1 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 21-NOV-11 BA-LA-140 < 3.4 21-NOV-11 H-3 < 137.0 21-NOV-11 1-131 (CHEM) < 0.257 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 35

Exposure Pathway - Waterborne Ground Water Location G-2 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 28-FEB-i 1 MN-54 1.9 28-FEB-i 1 CO-58 2.6 28-FEB-11 FE-59 5.9 28-FEB-i 1 CO-60 1.4 28-FEB-i 1 ZN-65 4.8 28-FEB-i 1 ZR-NB-95 1.6 28-FEB-i 1 CS-134 2.4 28-FEB-1i1 CS-1 37 2.6 28-FEB-1i1 BA-LA-140 2.4 28-FEB-i 1 H-3 152.0 28-FEB-i 1 1-131 (CHEM) 0.379 23-MAY-i 1 MN-54 1.9 23-MAY-i 1 CO-58 1.7 23-MAY-i 1 FE-59 4.6 23-MAY-1i1 CO-60 1.5 23-MAY-i 1 ZN-65 3.5 23-MAY-1i1 ZR-NB-95 2.4 23-MAY-i 1 CS-134 2.0 23-MAY-i 1 CS-137 3.0 23-MAY-i 1 BA-LA- 140 2.3 23-MAY-1i1 H-3 141.0 23-MAY-i 1 1-131 (CHEM) 0.402 08-AUG-1i1 MN-54 2.8 08-AUG-1i1 CO-58 4.2 08-AUG-i 1 FE-59 8.8 08-AUG-1i1 CO-60 2.9 08-AUG-1i1 ZN-65 8.2 08-AUG-i 1 ZR-NB-95 7.7 08-AUG-1i1 CS-134 3.5 08-AUG-i 1 CS-137 3.4 08-AUG-1i1 BA-LA-140 4.5 08-AUG-i 1 H-3 185.0 08-AUG-i 1 1-131 (CHEM) 0.199 21-NOV-11 MN-54 1.9 21-NOV-11 CO-58 2.0 21-NOV-11 FE-59 5.0 21-NOV-11 CO-60 2.4 21-NOV-11 ZN-65 3.4 21-NOV-11 ZR-NB-95 3.0 21-NOV-11 CS-1 34 2.9 21-NOV-11 CS-137 2.3 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 36

Exposure Pathway - Waterborne Ground Water Location G-2 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 21-NOV-11 BA-LA-140

Exposure Pathway - Waterborne Ground Water Location J-1 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 28-FEB-i 1 MN-54 3.4 28-FEB-i 1 MN-54 5.5 Duplicate 28-FEB-1i1 CO-58 2.8 28-FEB-11 CO-58 6.4 Duplicate 28-FEB-i 1 FE-59 6.4 28-FEB-1i1 FE-59 7.5 Duplicate 28-FEB-i 1 CO-60 3.2 28-FEB-i 1 CO-60 4.3 Duplicate 28-FEB-i 1 ZN-65 6.1 28-FEB-i 1 ZN-65 11.2 Duplicate 28-FEB-i 1 ZR-NB-95 5.2 28-FEB-1i1 ZR-NB-95 6.6 Duplicate 28-FEB-1i1 CS-134 4.8 28-FEB-1i1 CS-1 34 5.2 Duplicate 28-FEB-i 1 CS-137 2.6 28-FEB-11 CS-137 6.0 Duplicate 28-FEB-1i1 BA-LA- 140 4.3 28-FEB-i 1 BA-LA- 140 5.7 Duplicate 28-FEB-1i1 H-3 152.0 28-FEB-1i1 H-3 152.0 Duplicate 28-FEB-1i1 1-131 (CHEM) 0.459 28-FEB-1i1 1-131 (CHEM) 0.467 Duplicate 23-MAY-1i1 MN-54 3.8 23-MAY-1i1 CO-58 3.4 23-MAY-1i1 FE-59 5.5 23-MAY-1i1 CO-60 2.7 23-MAY-1i1 ZN-65 6.6 23-MAY-1i1 ZR-NB-95 2.5 23-MAY-1i1 CS-134 3.6 23-MAY-1i1 CS-137 3.4 23-MAY-i 1 BA-LA- 140 5.6 23-MAY-i 1 H-3 141.0 23-MAY-1i1 1-131 (CHEM) 0.367 08-AUG-1i1 MN-54 2.4 08-AUG-1i1 CO-58 2.2 08-AUG-1i1 FE-59 2.6 08-AUG-1i1 CO-60 2.2 08-AUG-1i1 ZN-65 5.3 08-AUG-1i1 ZR-NB-95 5.7 08-AUG-1i1 CS-134 3.2 08-AUG-1i1 CS-i37 2.8 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 38

Exposure Pathway - Waterborne Ground Water Location J-1 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 08-AUG-i 1 BA-LA-140 3.7 08-AUG-i 1 H-3 185.0 08-AUG-1i1 1-131 (CHEM) 0.261 21-NOV-11 MN-54 4.3 21-NOV-11 CO-58 2.3 21-NOV-i 1 FE-59 8.5 21-NOV-11 CO-60 4.4 21 -NOV- 11 ZN-65 8.5 21-NOV-11 ZR-NB-95 5.3 21-NOV-11 CS-134 3.7 21-NOV-11 CS-137 4.8 21-NOV-11 BA-LA-140 4.5 21-NOV-11 H-3 137.0 21-NOV-11 1-131 (CHEM) 0.265 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 39

Exposure Pathway - Waterborne Ground Water Location J-2 Collection Nuclide Concentration Duplicate Date (pCilLiter) Analysis 28-FEB-i 1 MN-54 3.9 28-FEB-i 1 CO-58 3.1 28-FEB-i 1 FE-59 6.7 28-FEB-i 1 CO-60 4.1 28-FEB-1i1 ZN-65 10.0 28-FEB-i 1 ZR-NB-95 2.7 28-FEB-i 1 CS-134 3.2 28-FEB-1i1 CS-137 5.0 28-FEB-i 1 BA-LA- 140 2.5 28-FEB-i 1 H-3 152.0 28-FEB-i 1 1-131 (CHEM) 0.395 23-MAY-i 1 MN-54 3.8 23-MAY-i 1 CO-58 2.2 23-MAY-i 1 FE-59 5.2 23-MAY-1i1 CO-60 2.5 23-MAY-i 1 ZN-65 6.8 23-MAY-i 1 ZR-NB-95 5.2 23-MAY-1i1 CS-134 2.8 23-MAY-1i1 CS-137 3.3 23-MAY-i 1 BA-LA-140 3.1 23-MAY-i 1 H-3 141.0 23-MAY-i 1 1-131 (CHEM) 0.205 08-AUG-i 1 MN-54 3.3 08-AUG-1i1 CO-58 1.9 08-AUG-1i1 FE-59 4.5 08-AUG-1i1 CO-60 2.8 08-AUG-1i1 ZN-65 4.6 08-AUG-1i1 ZR-NB-95 3.7 08-AUG-1i1 CS-134 2.7 08-AUG-i 1 CS-137 3.5 08-AUG-1i1 BA-LA-140 4.7 08-AUG-1i1 H-3 185.0 08-AUG-1i1 1-131 (CHEM) 0.23 21-NOV-1i1 MN-54 3.6 21-NOV-11 CO-58 2.3 21-NOV- 1l FE-59 7.4 21-NOV- 11 CO-60 2.7 21-NOV-11 ZN-65 11.4 21-NOV-1 1 ZR-NB-95 5.9 21-NOV-1i1 CS-134 3.0 21-NOV-11 CS-137 5.2 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 40

Exposure Pathway - Waterborne Ground Water Location J-2 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 21-NOV-1 1 BA-LA-140 < 7.7 21-NOV-11 H-3 < 137.0 21-NOV-11 1-131 (CHEM) < 0.276 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 41

Exposure Pathway - Waterborne Ground Water Location L-49 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 28-FEB-i 1 MN-54 5.1 28-FEB-i 1 CO-58 6.4 28-FEB-i 1 FE-59 9.1 28-FEB-i 1 CO-60 1.9 28-FEB-11 ZN-65 10.2 28-FEB-1i1 ZR-NB-95 5.4 28-FEB-1i1 CS-134 5.9 28-FEB-i 1 CS-137 3.7 28-FEB-i 1 BA-LA-140 6.7 28-FEB-i 1 H-3 152.0 28-FEB-i 1 1-131 (CHEM) 0.376 23-MAY-1i1 MN-54 2.9 23-MAY-i 1 CO-58 4.3 23-MAY-1i1 FE-59 5.4 23-MAY-1i1 CO-60 3.1 23-MAY-i 1 ZN-65 9.7 23-MAY-1i1 ZR-NB-95 2.8 23-MAY-1i1 CS-134 3.5 23-MAY-i 1 CS-1 37 4.3 23-MAY-i 1 BA-LA-140 4.1 23-MAY-1i1 H-3 141.0 23-MAY-1i1 1-131 (CHEM) 0.194 08-AUG-1i1 MN-54 2.4 08-AUG-1i1 CO-58 1.6 08-AUG-i 1 FE-59 2.5 08-AUG-1i1 CO-60 1.9 08-AUG-1i1 ZN-65 3.7 08-AUG-1i1 ZR-NB-95 3.0 08-AUG-1i1 CS-134 2.6 08-AUG-1i1 CS-137 2.5 08-AUG-1i1 BA-LA-140 2.5 08-AUG-1i1 H-3 185.0 08-AUG-1i1 1-131 (CHEM) 0.257 21-NOV-1i1 MN-54 2.2 21-NOV-1i1 CO-58 2.6 21 -NOV- 1i FE-59 5.7 21 -NOV- 1i CO-60 0.9 21-NOV-1i1 ZN-65 2.6 21-NOV-1 1 ZR-NB-95 3.4 21-NOV-1 1 CS-134 2.4 21-NOV-11 CS-137 2.5 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 42

Exposure Pathway - Waterborne Ground Water Location L-49 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 21-NOV-11 BA-LA- 140 < 3.2 21-NOV-11 H-3 < 137.0 21-NOV-11 1-131 (CHEM) < 0.272 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 43

Exposure Pathway - Waterborne Drinking Water Location BW-15 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 07-FEB-11 MN-54 < 2.8 07-FEB-i 1 CO-58 < 2.9 07-FEB-i 1 FE-59 < 4.6 07-FEB-i 1 CO-60 < 3.1 07-FEB-1i1 ZN-65 < 5.6 07-FEB-i 1 ZR-NB-95 < 2.2 07-FEB-11 CS-134 < 4.0 07-FEB-i 1 CS-137 4.2 07-FEB-i 1 BA-LA- 140 2.4 07-FEB-i 1 GROSS BETA 2.904+/- 0.501 07-FEB-11 1-131 (CHEM) < 0.301 07-MAR- 11 MN-54 < 2.3 07-MAR-i 1 CO-58 < 3.8 07-MAR-1i1 FE-59 < 4.7 07-MAR-1i1 CO-60 < 2.9 07-MAR-i 1 ZN-65 < 4.0 07-MAR-i 1 ZR-NB-95 < 3.3 07-MAR-1i1 CS-134 < 2.3 07-MAR-1i1 CS-1 37 4.5 07-MAR-1i1 BA-LA-140 1.8 07-MAR-1i1 GROSS BETA 2.280+/- 0.638 07-MAR-11 1-131 (CHEM) 0.369 04-APR-i 1 MN-54 2.4 04-APR-i 1 CO-58 1.9 04-APR-i 1 FE-59 2.7 04-APR-i 1 CO-60 1.9 04-APR-I 1 ZN-65 3.8 04-APR-i 1 ZR-NB-95 1.7 04-APR-i 1 CS-134 2.1 04-APR-I 1 CS-137 2.8 04-APR-i 1 BA-LA-1 40 2.6 04-APR-i 1 GROSS BETA 2.209+/- 0.337 04-APR-1 1 1-131 (CHEM) 0.398 02-MAY-i 1 MN-54 4.6 02-MAY-i 1 CO-58 3.5 02-MAY-i 1 FE-59 7.2 02-MAY-i 1 CO-60 3.1 02-MAY-i 1 ZN-65 7.6 02-MAY-i 1 ZR-NB-95 4.5 02-MAY-i 1 CS-134 3.7 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 44

Exposure Pathway - Waterborne Drinking Water Location BW-15 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 02-MAY-i 1 CS-137 3.7 02-MAY-i 1 BA-LA-140 4.3 02-MAY-i 1 GROSS BETA 3.268 +/- 0.835 02-MAY-i 1 1-131 (CHEM) 0.163 06-JUN-i 1 MN-54 2.7 06-JUN-11 CO-58 3.8 06-JUN-11 FE-59 8.9 06-JUN-11 CO-60 3.5 06-JUN-11 ZN-65 12.8 06-JUN-11 ZR-NB-95 5.4 06-JUN-11 CS-134 5.2 06-JUN-11 CS-137 2.8 06-JUN-11 BA-LA-140 5.7 06-JUN-11 GROSS BETA 3.490+/- 1.109 06-JUN-11 1-131 (CHEM) 0.287 05-JUL-11 MN-54 2.2 05-JUL-1i1 CO-58 2.6 05-JUL-i 1 FE-59 5.5 05-JUL-11 CO-60 2.8 05-JUL-11 ZN-65 3.5 05-JUL-11 ZR-NB-95 3.4 05-JUL-i 1 CS-134 2.4 05-JUL-1i1 CS-1 37 2.9 05-JUL-11 BA-LA-140 3.4 05-JUL-11 GROSS BETA 3.319 +/- 0.981 05-JUL-11 1-131 (CHEM) 0.351 01-AUG-11 MN-54 2.5 01-AUG-11 CO-58 2.3 01-AUG-11 FE-59 2.4 01-AUG-11 CO-60 1.4 01-AUG-11 ZN-65 3.5 01-AUG-11 ZR-NB-95 1.7 01-AUG-11 CS-134 2.5 01-AUG-11 CS-137 2.8 01-AUG-11 BA-LA- 140 2.5 01-AUG-11 GROSS BETA 2.243+/- 0.617 01-AUG-11 1-131 (CHEM) 0.391 06-SEP-11 MN-54 2.0 06-SEP-i 1 CO-58 1.4 06-SEP-i 1 FE-59 4.5 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 45

Exposure Pathway - Waterborne Drinking Water Location BW-15 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 06-SEP-i 1 CO-60 < 2.2 06-SEP-I 1 ZN-65 < 3.2 06-SEP-11 ZR-NB-95 < 1.5 06-SEP-i 1 CS-134 < 2.4 06-SEP-11 CS-1 37 < 3.1 06-SEP-1i1 BA-LA-140 < 2.2 06-SEP-i 1 GROSS BETA 2.375+/- 0.639 06-SEP-11 1-131 (CHEM) < 0.318 03-OCT-1i1 MN-54 < 2.6 03-OCT-1i1 CO-58 < 1.7 03-OCT-1i1 FE-59 < 3.4 03-OCT-1i1 CO-60 < 1.8 03-OCT-i 1 ZN-65 < 4.5 03-OCT-1i1 ZR-NB-95 < 2.1 03-OCT-1i1 CS-134 < 2.3 03-OCT-1i1 CS-137 < 2.7 03-OCT-1i1 BA-LA- 140 < 3.9 03-OCT-1i1 GROSS BETA 2.650+/- 0.663 03-OCT-1i1 1-131 (CHEM) < 0.402 07-NOV-1i1 MN-54 < 3.2 07-NOV-1i1 CO-58 < 2.5 07-NOV-i 1 FE-59 < 4.9 07-NOV-1i1 CO-60 < 1.8 07-NOV-1i1 ZN-65 < 3.6 07-NOV-i 1 ZR-NB-95 < 2.2 07-NOV-1i1 CS-134 < 2.7 07-NOV-1i1 CS-137 < 3.5 07-NOV-1i1 BA-LA- 140 < 3.3 07-NOV-1i1 GROSS BETA < 1.74 07-NOV-1i1 1-131 (CHEM) < 0.315 05-DEC-1i1 MN-54 < 2.7 05-DEC-i 1 CO-58 < 0.7 05-DEC-1i1 FE-59 < 3.6 05-DEC-1i1 CO-60 < 1.4 05-DEC-1i1 ZN-65 < 4.7 05-DEC-1i1 ZR-NB-95 < 1.9 05-DEC-i 1 CS-134 < 1.7 05-DEC-1i1 CS-137 < 1.7 05-DEC-1i1 BA-LA-140 < 1.8 05-DEC-1i1 GROSS BETA 2.820 +/- 0.488 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 46

Exposure Pathway - Waterborne Drinking Water Location BW-1 5 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 05-DEC-i 1 1-131 (CHEM) 0.412 03-JAN- 12 MN-54 2.6 03-JAN-1 2 CO-58 2.1 03-JAN- 12 FE-59 4.6 03-JAN- 12 CO-60 0.9 03-JAN-12 ZN-65 4.9 03-JAN-1 2 ZR-NB-95 2.3 03-JAN-12 CS-134 3.0 03-JAN-1 2 CS-1 37 2.7 03-JAN- 12 BA-LA-140 2.0 03-JAN- 12 GROSS BETA 1.650+/- 0.585 03-JAN-12 1-131 (CHEM) 0.325 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 47

Exposure Pathway - Waterborne Drinking Water Location IO-DW Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 07-FEB-i 1 MN-54 3.2 07-FEB-i 1 CO-58 2.1 07-FEB-i 1 FE-59 5.7 07-FEB-i 1 CO-60 2.7 07-FEB-i 1 ZN-65 5.1 07-FEB-11 ZR-NB-95 3.4 07-FEB-i 1 CS-134 2.7 07-FEB-i 1 CS-137 3.7 07-FEB-i 1 BA-LA-1 40 4.0 07-FEB-i 1 GROSS BETA 2.969+/- 0.538 07-FEB-I 1 1-131 (CHEM) 0.296 07-MAR-1 I MN-54 3.1 07-MAR-i 1 CO-58 3.0 07-MAR-i 1 FE-59 3.7 07-MAR-i 1 CO-60 2.9 07-MAR-i 1 ZN-65 7.9 07-MAR-1i1 ZR-NB-95 2.0 07-MAR-i 1 CS-134 3.1 07-MAR-i 1 CS-137 3.9 07-MAR-1i1 BA-LA- 140 2.1 07-MAR-1i1 GROSS BETA 2.086 +/- 0.63 07-MAR-i 1 1-131 (CHEM) 0.388 04-APR-i 1 MN-54 1.9 04-APR-i 1 CO-58 1.8 04-APR-1i1 FE-59 3.6 04-APR-i 1 CO-60 1.8 04-APR-1i1 ZN-65 2.7 04-APR-1i1 ZR-NB-95 2.1 04-APR-1i1 CS-134 2.7 04-APR-i 1 CS-137 3.3 04-APR-1i1 BA-LA- 140 2.8 04-APR-i 1 GROSS BETA 1.894+/- 0.363 04-APR-i 1 1-131 (CHEM) 0.422 02-MAY-1i1 MN-54 2.9 02-MAY-i 1 CO-58 2.2 02-MAY-i 1 FE-59 5.2 02-MAY-1i1 CO-60 3.4 02-MAY-1i1 ZN-65 6.0 02-MAY-i 1 ZR-NB-95 1.5 02-MAY-i 1 CS-134 3.7 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 48

Exposure Pathway - Waterborne Drinking Water Location IO-DW Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 02-MAY-i 1 CS-1 37 3.9 02-MAY-i 1 BA-LA-140 3.9 02-MAY-i 1 GROSS BETA 2.229+/- 0.876 02-MAY-i 1 1-131 (CHEM) 0.292 06-JUN-11 MN-54 2.9 06-JUN-1i1 CO-58 3.2 06-JUN-i 1 FE-59 3.3 06-JUN-i 1 CO-60 2.6 06-JUN-11 ZN-65 6.5 06-JUN-11 ZR-NB-95 2.9 06-JUN-1i1 CS-134 3.6 06-JUN-1i1 CS-137 4.0 06-JUN-1i1 BA-LA- 140 3.4 06-JUN-i 1 GROSS BETA 3.910 +/- 1.044 06-JUN-11 1-131 (CHEM) 0.384 05-JUL-11 MN-54 1.7 05-JUL-i 1 CO-58 1.8 05-JUL-11 FE-59 4.9 05-JUL-11 CO-60 2.4 05-JUL-11 ZN-65 2.9 05-JUL-1i1 ZR-NB-95 2.2 05-JUL-11 CS-134 3.1 05-JUL-1i1 CS-137 2.5 05-JUL-11 BA-LA- 140 2.9 05-JUL-11 GROSS BETA 1.992+/- 0.629 05-JUL-11 1-131 (CHEM) 0.483 01-AUG-11 MN-54 2.1 01-AUG-11 CO-58 1.9 01-AUG-11 FE-59 4.6 01-AUG-11 CO-60 1.6 01-AUG-11 ZN-65 2.4 01-AUG-11 ZR-NB-95 2.7 01-AUG-11 CS-134 2.7 01 -AUG- 1l CS-137 2.7 01-AUG-11 BA-LA-1 40 2.9 01-AUG-11 GROSS BETA 2.587 +/- 0.702 01-AUG-11 1-131 (CHEM) 0.397 06-SEP-i 1 MN-54 2.5 06-SEP-i 1 CO-58 2.0 06-SEP-i 1 FE-59 5.9 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 49

Exposure Pathway - Waterborne Drinking Water Location 10-DW Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 06-SEP-i 1 CO-60 < 2.0 06-SEP-I 1 ZN-65 < 3.9 06-SEP-i 1 ZR-NB-95 < 1.5 06-SEP-i 1 CS-134 < 3.7 06-SEP-1i1 CS-137 < 3.4 06-SEP-1i1 BA-LA-140 < 1.4 06-SEP-i 1 GROSS BETA 2.838 +/- 0.686 06-SEP-i 1 1-131 (CHEM) < 0.305 03-OCT-i 1 MN-54 < 4.4 03-OCT-i 1 CO-58 < 2.9 03-OCT-1i1 FE-59 < 6.1 03-OCT-i 1 CO-60 2.1 03-OCT-i 1 ZN-65 2.5 03-OCT-i 1 ZR-NB-95 3.5 03-OCT-i 1 CS-134 3.5 03-OCT-i 1 CS-137 3.7 03-OCT-1i1 BA-LA-1 40 5.0 03-OCT-i 1 GROSS BETA 3.055 +/- 0.695 03-OCT-1i1 1-131 (CHEM) 0.418 07-NOV-i 1 MN-54 3.3 07-NOV-i 1 CO-58 1.8 07-NOV-i 1 FE-59 < 4.9 07-NOV-i 1 CO-60 < 2.0 07-NOV-1i1 ZN-65 < 4.2 07-NOV-1i1 ZR-NB-95 < 3.4 07-NOV-i 1 CS-134 < 2.4 07-NOV-1i1 CS-137 < 3.0 07-NOV-i 1 BA-LA-140 < 2.8 07-NOV-1i1 GROSS BETA 2.299+/- 1.04 07-NOV-i 1 1-131 (CHEM) < 0.348 05-DEC-i 1 MN-54 < 2.6 05-DEC-1i1 CO-58 < 2.3 05-DEC-1i1 FE-59 < 5.7 05-DEC-i 1 CO-60 < 2.3 05-DEC-1i1 ZN-65 < 5.8 05-DEC-1i1 ZR-NB-95 < 2.5 05-DEC-1i1 CS-134 < 2.8 05-DEC-1i1 CS-137 < 4.1 05-DEC-1i1 BA-LA-140 < 3.5 05-DEC-i 1 GROSS BETA 2.827+/- 0.529 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 50

Exposure Pathway - Waterborne Drinking Water Location 1O-DW Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 05-DEC-i 1 1-131 (CHEM) 0.422 03-JAN-12 MN-54 5.0 03-JAN-12 CO-58 4.1 03-JAN-12 FE-59 7.2 03-JAN-1 2 CO-60 3.6 03-JAN-12 ZN-65 4.1 03-JAN-12 ZR-NB-95 4.3 03-JAN-12 CS-134 3.0 03-JAN-12 CS-1 37 3.7 03-JAN-1 2 BA-LA- 140 4.3 03-JAN-12 GROSS BETA 2.562 +/- 0.671 03-JAN-12 1-131 (CHEM) 0.347 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 51

Exposure Pathway - Waterborne Drinking Water Quarterly Tritium Analysis Location BW-1 5 Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 04-APR-i 1 H-3 < 141 05-JUL-i 1 H-3 < 148 03-OCT-i 1 H-3 < 143 03-JAN-12 H-3 < 144 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 52

Exposure Pathway - Waterborne Drinking Water Quarterly Tritium Analysis Location 1O-DW Collection Nuclide Concentration Duplicate Date (pCi/Liter) Analysis 04-APR-i 1 H-3 < 141 05-JUL-11 H-3 < 148 03-OCT-i 1 H-3 < 143 03-JAN-12 H-3 < 144 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 53

Exposure Pathway - Waterborne Shoreline Sediment Location DC Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 28-JUN-11 K-40 10,597.0 +/- 653.9 28-JUN-11 MN-54 26.6 28-JUN-11 CO-58 23.3 28-JUN-11 FE-59 32.7 28-JUN-11 CO-60 24.9 28-JUN-11 ZN-65 41.6 28-JUN-11 CS-134 22.5 28-JUN-i 1 CS-137 i44.5+- 37.7 23-NOV-11 K-40 7,581 .8+- 496.8 23-NOV-1i1 MN-54 18.9 23-NOV-1i1 CO-58 19.0 23-NOV-1i1 FE-59 36.8 23-NOV-1i1 CO-60 10.0 23-NOV-1i1 ZN-65 47.3 23-NOV-1i1 CS-134 17.5 23-NOV-1i1 CS-137 20.2 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 54

Exposure Pathway - Waterborne Shoreline Sediment Location EEA Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 12-APR- 1l K-40 10,655.0 +/- 663.3 12-APR-11 MN-54

  • 27.6 12-APR-1i1 CO-58
  • 18.4 12-APR-11 ZN-65
  • 49.0 12-APR- 1l CS-134

Exposure Pathway - Waterborne Shoreline Sediment Location JRR Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 30-JUN-11 K-40 9,377.3 +/- 973.6 30-JUN-1i1 MN-54

  • 40.1 30-JUN-1I CO-58
  • 24.1 30-JUN-11 ZN-65
  • 74.6 30-JUN-11 CS-134

Exposure Pathway - Ingestion Fish Location CCL Collection Sample Nuclide Gamma Spectrum & H-3 Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 26-JUL-I 1 CHANNEL CATFISH K-40 3,538.1 +/- 413.7 26-JUL-11 CHANNEL CATFISH MN-54 7.8 26-JUL-i 1 CHANNEL CATFISH CO-58 8.0 26-JUL-1 1 CHANNEL CATFISH FE-59 19.4 26-JUL-i 1 CHANNEL CATFISH CO-60 11.3 26-JUL-11 CHANNEL CATFISH ZN-65 32.5 26-JUL-11 CHANNEL CATFISH 1-131 23.3 26-JUL-i 1 CHANNEL CATFISH CS-134 10.6 26-JUL-11 CHANNEL CATFISH CS-137 7.7 26-JUL-11 CHANNEL CATFISH H-3 9,461 .0 +/- 262.0 26-JUL-11 COMMON CARP K-40 3,215.8 +/- 398.9 26-JUL-11 COMMON CARP MN-54 8.5 26-JUL-11 COMMON CARP CO-58 4.3 26-JUL-11 COMMON CARP FE-59 21.1 26-JUL-11 COMMON CARP CO-60 10.3 26-JUL-11 COMMON CARP ZN-65 21.4 26-JUL-11 COMMON CARP 1-131 19.4 26-JUL-i 1 COMMON CARP CS-134 8.5 26-JUL-i 1 COMMON CARP CS-137 12.6 26-JUL-11 COMMON CARP H-3 9,032.0 +/- 255.0 26-JUL-i 1 SMALLMOUTH BASS K-40 3,228.5 +1- 417.1 26-JUL-11 SMALLMOUTH BASS MN-54 9.2 26-JUL-11 SMALLMOUTH BASS CO-58 7.6 26-JUL-11 SMALLMOUTH BASS FE-59 20.4 26-JUL-i 1 SMALLMOUTH BASS CO-60 11.4 26-JUL-11 SMALLMOUTH BASS ZN-65 18.4 26-JUL-i 1 SMALLMOUTH BASS 1-131 13.1 26-JUL-11 SMALLMOUTH BASS CS-134 9.1 26-JUL-11 SMALLMOUTH BASS CS-137 10.0 26-JUL-11 SMALLMOUTH BASS H-3 8,149.0 +1- 243.0 26-JUL-11 WHITE BASS K-40 3,329.4 +1- 382.3 26-JUL-11 WHITE BASS MN-54 9.1 26-JUL-11 WHITE BASS CO-58 11.1 26-JUL-11 WHITE BASS FE-59 23.9 26-JUL-i 1 WHITE BASS CO-60 10.1 26-JUL-1 1 WHITE BASS ZN-65 10.6 26-JUL-11 WHITE BASS 1-131 17.4 26-JUL-11 WHITE BASS CS-1 34 10.3 26-JUL-11 WHITE BASS CS-137 14.1 26-JUL-11 WHITE BASS H-3 8,807.0 +/- 249.0 18-OCT-11 BLUE CATFISH K-40 2,553.2 +/- 468.5 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 57

Exposure Pathway - Ingestion Fish Location CCL Collection Sample Nuclide Gamma Spectrum & H-3 Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 18-OCT- 1l BLUE CATFISH MN-54 16.6 18-OCT-1I BLUE CATFISH CO-58 17.9 18-OCT- 1l BLUE CATFISH FE-59 45.1 18-OCT- 1l BLUE CATFISH CO-60 19.7 18-OCT- 1l BLUE CATFISH ZN-65 35.3 18-OCT- 1l BLUE CATFISH 1-131 98.5 18-OCT-11 BLUE CATFISH CS-134 13.7 18-OCT-11 BLUE CATFISH CS-137 14.7 18-OCT- 1l BLUE CATFISH H-3 8,021.0 +/- 240.0 18-OCT- 1l CHANNEL CATFISH K-40 3,268.3 +/- 358.1 Duplicate 18-OCT- 1l CHANNEL CATFISH K-40 3,531 .4 +/- 455.5 18-OCT- 1l CHANNEL CATFISH MN-54 17.6 Duplicate 18-OCT-11 CHANNEL CATFISH MN-54 12.5 18-OCT- 1l CHANNEL CATFISH CO-58 18.6 Duplicate 18-OCT- 1l CHANNEL CATFISH CO-58 8.2 18-OCT- 1l CHANNEL CATFISH FE-59 40.2 Duplicate 18-OCT-11 CHANNEL CATFISH FE-59 36.8 18-OCT-11 CHANNEL CATFISH CO-60 14.0 Duplicate 18-OCT- 1l CHANNEL CATFISH CO-60 10.4 18-OCT- 1l CHANNEL CATFISH ZN-65 19.0 Duplicate 18-OCT- 1l CHANNEL CATFISH ZN-65 14.7 18-OCT-11 CHANNEL CATFISH 1-131 99.3 Duplicate 18-OCT- 1l CHANNEL CATFISH 1-131 65.9 18-OCT- 1l CHANNEL CATFISH CS-134 12.4 Duplicate 18-OCT- 1l CHANNEL CATFISH CS-134 9.6 18-OCT- 1l CHANNEL CATFISH CS-137 14.9 Duplicate 18-OCT- 1l CHANNEL CATFISH CS-137 10.5 18-OCT-11 CHANNEL CATFISH H-3 8,129.0 +1- 240.0 Duplicate 18-OCT- 1l CHANNEL CATFISH H-3 8,069.0 +1- 239.0 18-OCT- 1l COMMON CARP K-40 3,117.9 +/- 390.1 18-OCT- 1l COMMON CARP MN-54 16.9 18-OCT- 1l COMMON CARP CO-58 17.5 18-OCT- 1l COMMON CARP FE-59 48.1 18-OCT- 1l COMMON CARP CO-60 12.1 18-OCT- 1l COMMON CARP ZN-65 29.2 18-OCT- 1l COMMON CARP 1-131 116.3 18-OCT-11 COMMON CARP CS-134 13.8 18-OCT- 1l COMMON CARP CS-137 20.5 18-OCT-11 COMMON CARP H-3 7,879.0 +/- 235.0 18-OCT- 1l RIVER CARPSUCKER K-40 1,955.3 +/- 564.4 18-OCT- 11 RIVER CARPSUCKER MN-54 9.7 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 58

Exposure Pathway - Ingestion Fish Location CCL Collection Sample Nuclide Gamma Spectrum & H-3 Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 18-OCT- 1l RIVER CARPSUCKER CO-58 16.1 18-OCT- 1l RIVER CARPSUCKER FE-59 37.3 18-OCT-11 RIVER CARPSUCKER CO-60 7.3 18-OCT-1i1 RIVER CARPSUCKER ZN-65 21.6 18-OCT-i 1 RIVER CARPSUCKER 1-131 125.6 18-OCT-11 RIVER CARPSUCKER CS-134 11.6 18-OCT- 1l RIVER CARPSUCKER CS-137 11.8 18-OCT- 1l RIVER CARPSUCKER H-3 7,513.0 +1- 217.0 18-OCT- 1l WALLEYE K-40 3,385.1 +1- 373.5 18-OCT- 1l WALLEYE MN-54 8.4 18-OCT- 1l WALLEYE CO-58 9.8 18-OCT-11 WALLEYE FE-59 34.5 18-OCT-11 WALLEYE CO-60 12.4 18-OCT- 1l WALLEYE ZN-65 29.3 18-OCT- 1l WALLEYE 1-131 144.6 18-OCT- 1l WALLEYE CS-134 12.2 18-OCT-11 WALLEYE CS-137 16.4 18-OCT-11 WALLEYE H-3 7,583.0 +1- 230.0 18-OCT-11 WHITE BASS K-40 3,294.5 +/- 350.4 18-OCT-11 WHITE BASS MN-54 11.8 18-OCT-11 WHITE BASS CO-58 13.5 18-OCT- 1l WHITE BASS FE-59 35.3 18-OCT- 1l WHITE BASS CO-60 9.9 18-OCT-11 WHITE BASS ZN-65 22.3 18-OCT-11 WHITE BASS 1-131 150.5 18-OCT-11 WHITE BASS CS-134 12.0 18-OCT-11 WHITE BASS CS-137 12.9 18-OCT- 1l WHITE BASS H-3 8,289.0 +/- 238.0 18-OCT-11 WHITE CRAPPIE K-40 3,230.1 +/- 342.9 18-OCT- 1l WHITE CRAPPIE MN-54 12.6 18-OCT-11 WHITE CRAPPIE CO-58 16.6 18-OCT-11 WHITE CRAPPIE FE-59 32.4 18-OCT- 1l WHITE CRAPPIE CO-60 11.1 18-OCT- 1l WHITE CRAPPIE ZN-65 15.9 18-OCT-11 WHITE CRAPPIE 1-131 125.1 18-OCT-11 WHITE CRAPPIE CS-134 12.0 18-OCT-11 WHITE CRAPPIE CS-137 14.1 18-OCT-11 WHITE CRAPPIE H-3 7,726.0 +/- 232.0 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 59

Exposure Pathway - Ingestion Fish Location JRR Collection Sample Nuclide Gamma Spectrum & H-3 Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 30-JUN-I 1 COMMON CARP K-40 3,310.9 +/- 398.1 30-JUN-i 1 COMMON CARP MN-54 < 8.6 30-JUN-i 1 COMMON CARP CO-58 < 8.3 30-JUN-11 COMMON CARP FE-59 < 21.3 30-JUN-11 COMMON CARP CO-60 < 10.9 30-JUN-11 COMMON CARP ZN-65 < 9.6 30-JUN-11 COMMON CARP 1-131 < 19.4 30-JUN-11 COMMON CARP CS-134 < 6.3 30-JUN-11 COMMON CARP CS-137 < 9.6 30-JUN-i 1 COMMON CARP H-3 < 116.0 30-JUN-i 1 SMALLMOUTH BUFFALO K-40 3,454.1 +/- 379.2 30-JUN-i 1 SMALLMOUTH BUFFALO MN-54 < 12.3 30-JUN-11 SMALLMOUTH BUFFALO CO-58 < 7.9 30-JUN-11 SMALLMOUTH BUFFALO FE-59 < 18.8 30-JUN-11 SMALLMOUTH BUFFALO CO-60 < 7.9 30-JUN-i 1 SMALLMOUTH BUFFALO ZN-65 < 23.7 30-JUN-i 1 SMALLMOUTH BUFFALO 1-131 < 37.1 30-JUN-11 SMALLMOUTH BUFFALO CS-134 < 12.8 30-JUN-11 SMALLMOUTH BUFFALO CS-1 37 < 10.7 30-JUN-11 SMALLMOUTH BUFFALO H-3 < 114.0 30-JUN-11 WHITE CRAPPIE K-40 3,052.4 +/- 367.5 30-JUN-11 WHITE CRAPPIE MN-54 < 11.3 30-JUN-i 1 WHITE CRAPPIE CO-58 < 9.0 30-JUN-i 1 WHITE CRAPPIE FE-59 < 19.3 30-JUN-i 1 WHITE CRAPPIE CO-60 < 8.5 30-JUN-i 1 WHITE CRAPPIE ZN-65 < 16.9 30-JUN-i 1 WHITE CRAPPIE 1-131 < 19.4 30-JUN-11 WHITE CRAPPIE CS-134 < 10.8 30-JUN-11 WHITE CRAPPIE CS-1 37 < 11.8 30-JUN-11 WHITE CRAPPIE H-3 < 116.0 23-NOV-i 1 CHANNEL CATFISH K-40 3,533.6 +/- 333.0 23-NOV-i 1 CHANNEL CATFISH MN-54 < 5.2 23-NOV-1i1 CHANNEL CATFISH CO-58 < 8.7 23-NOV-i 1 CHANNEL CATFISH FE-59 < 11.7 23-NOV-i 1 CHANNEL CATFISH CO-60 < 13.1 23-NOV-i 1 CHANNEL CATFISH ZN-65 < 22.1 23-NOV-1i1 CHANNEL CATFISH 1-131 < 24.5 23-NOV-i 1 CHANNEL CATFISH CS-134 < 10.0 23-NOV-i 1 CHANNEL CATFISH CS-137 < 11.7 23-NOV-i 1 CHANNEL CATFISH H-3 < 110.0 23-NOV-i 1 COMMON CARP K-40 3,156.6 +/- 358.0 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 60

Exposure Pathway - Ingestion Fish Location JRR Collection Sample Nluclide Gamma Spectrum & H-3 Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 23-NOV-i 1 COMMON CARP MN-54 6.5 23-NOV-i 1 COMMON CARP CO-58 11.3 23-NOV-i 1 COMMON CARP FE-59 23.9 23-NOV-1i1 COMMON CARP CO-60 8.3 23-NOV-i 1 COMMON CARP ZN-65 28.8 23-NOV-i 1 COMMON CARP 1-131 23.1 23-NOV-i 1 COMMON CARP CS-134 11.5 23-NOV-1i1 COMMON CARP CS-1 37 13.2 23-NOV-1i1 COMMON CARP H-3 110.0 23-NOV-1i1 SMALLMOUTH BUFFALO K-40 2,318.5 +/- 375.5 23-NOV-i 1 SMALLMOUTH BUFFALO MN-54 8.3 23-NOV-1i1 SMALLMOUTH BUFFALO CO-58 16.4 23-NOV-i 1 SMALLMOUTH BUFFALO FE-59 29.5 23-NOV-1i1 SMALLMOUTH BUFFALO CO-60 14.1 23-NOV-1i1 SMALLMOUTH BUFFALO ZN-65 19.5 23-NOV-1i1 SMALLMOUTH BUFFALO 1-131 31.6 23-NOV-i 1 SMALLMOUTH BUFFALO CS-134 16.3 23-NOV-i 1 SMALLMOUTH BUFFALO CS-137 11.2 23-NOV-1i1 SMALLMOUTH BUFFALO H-3 113.0 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 61

Exposure Pathway - Ingestion Food/Garden Location B-1 Collection Sample Nuclide Gamma Spectrum Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 28-NOV-i 1 HORSERADISH LEAVES BE-7 1,028.1 +/- 285.1 28-NOV-1i1 HORSERADISH LEAVES K-40 9,049.2 +/- 695.0 28-NOV-i 1 HORSERADISH LEAVES MN-54 27.4 28-NOV-i 1 HORSERADISH LEAVES CO-58 18.9 28-NOV-11 HORSERADISH LEAVES FE-59 46.3 28-NOV-1i1 HORSERADISH LEAVES CO-60 16.1 28-NOV-i 1 HORSERADISH LEAVES ZN-65 49.2 28-NOV-i 1 HORSERADISH LEAVES ZR-NB-95 25.7 28-NOV-i 1 HORSERADISH LEAVES 1-131 42.2 28-NOV-1 I HORSERADISH LEAVES CS-134 26.1 28-NOV-1 1 HORSERADISH LEAVES CS-137 23.9 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 62

Exposure Pathway - Ingestion Food/Garden Location D-2 Collection Sample Nuclide Gamma Spectrum Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 25-APR-i 1 HORSERADISH LEAVES BE-7 402.2 +/- 144.5 25-APR-i 1 HORSERADISH LEAVES K-40 3,531.7 +/- 410.4 25-APR-i 1 HORSERADISH LEAVES MN-54 13.9 25-APR-i 1 HORSERADISH LEAVES CO-58 8.2 25-APR-i 1 HORSERADISH LEAVES FE-59 23.1 25-APR-i 1 HORSERADISH LEAVES CO-60 9.3 25-APR-1i1 HORSERADISH LEAVES ZN-65 21.9 25-APR-1i1 HORSERADISH LEAVES ZR-NB-95 8.3 25-APR-1i1 HORSERADISH LEAVES 1-131 19.7 25-APR-i 1 HORSERADISH LEAVES CS-134 11.2 25-APR-1i1 HORSERADISH LEAVES CS-137 11.5 25-MAY-1i1 HORSERADISH LEAVES BE-7 822.0+1 230.2 25-MAY-11 HORSERADISH LEAVES K-40 4,303.3+1 419.7 25-MAY-1i1 HORSERADISH LEAVES MN-54 18.4 25-MAY-11 HORSERADISH LEAVES CO-58 12.1 25-MAY-i 1 HORSERADISH LEAVES FE-59 26.4 25-MAY-1i1 HORSERADISH LEAVES CO-60 12.3 25-MAY-1i1 HORSERADISH LEAVES ZN-65 33.9 25-MAY-1i1 HORSERADISH LEAVES ZR-NB-95 18.2 25-MAY-i 1 HORSERADISH LEAVES 1-131 26.8 25-MAY-i 1 HORSERADISH LEAVES CS-134 16.2 25-MAY-i 1 HORSERADISH LEAVES CS-1 37 12.1 29-JUN-11 HORSERADISH LEAVES BE-7 870.0+1 188.5 29-JUN-11 HORSERADISH LEAVES K-40 5,609.7+- 501.8 29-JUN-i 1 HORSERADISH LEAVES MN-54 18.0 29-JUN-11 HORSERADISH LEAVES CO-58 17.9 29-JUN-11 HORSERADISH LEAVES FE-59 32.2 29-JUN-11 HORSERADISH LEAVES CO-60 15.4 29-JUN-i 1 HORSERADISH LEAVES ZN-65 19.2 29-JUN-11 HORSERADISH LEAVES ZR-NB-95 10.7 29-JUN-11 HORSERADISH LEAVES 1-131 28.7 29-JUN-11 HORSERADISH LEAVES CS-134 18.0 29-JUN-11 HORSERADISH LEAVES CS-137 14.4 25-JUL-11 HORSERADISH LEAVES BE-7 992.4 238.1 25-JUL-11 HORSERADISH LEAVES K-40 6,336.9+1 537.9 25-JUL-11 HORSERADISH LEAVES MN-54 15.1 25-JUL-11 HORSERADISH LEAVES CO-58 14.5 25-JUL-11 HORSERADISH LEAVES FE-59 22.1 25-JUL-i 1 HORSERADISH LEAVES CO-60 16.5 25-JUL-11 HORSERADISH LEAVES ZN-65 34.1 25-JUL-11 HORSERADISH LEAVES ZR-NB-95 25.3 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 63

Exposure Pathway - Ingestion Food/Garden Location D-2 Collection Sample Nuclide Gamma Spectrum Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 25-JUL-11 HORSERADISH LEAVES 1-131 19.5 25-JUL-11 HORSERADISH LEAVES CS-134 16.6 25-JUL-i 1 HORSERADISH LEAVES CS-137 15.3 22-AUG-1i1 HORSERADISH LEAVES BE-7 746.2 +1- 176.0 22-AUG-1i1 HORSERADISH LEAVES K-40 6,915.9 +1- 477.9 22-AUG-1i1 HORSERADISH LEAVES MN-54 12.2 22-AUG-i 1 HORSERADISH LEAVES CO-58 9.0 22-AUG-i 1 HORSERADISH LEAVES FE-59 26.3 22-AUG-1i1 HORSERADISH LEAVES CO-60 7.9 22-AUG-1i1 HORSERADISH LEAVES ZN-65 36.3 22-AUG-i 1 HORSERADISH LEAVES ZR-NB-95 16.7 22-AUG-1i1 HORSERADISH LEAVES 1-131 21.1 22-AUG-1i1 HORSERADISH LEAVES CS-134 16.1 22-AUG-1i1 HORSERADISH LEAVES CS-137 15.1 26-SEP-1i1 HORSERADISH LEAVES BE-7 1,253.2 +1- 157.7 26-SEP-i 1 HORSERADISH LEAVES K-40 12,023.0 +1- 416.7 26-SEP-i 1 HORSERADISH LEAVES MN-54 12.2 26-SEP-1 I HORSERADISH LEAVES CO-58 14.7 26-SEP-i 1 HORSERADISH LEAVES FE-59 32.3 26-SEP-i 1 HORSERADISH LEAVES CO-60 12.4 26-SEP-11 HORSERADISH LEAVES ZN-65 33.8 26-SEP-i 1 HORSERADISH LEAVES ZR-NB-95 16.9 26-SEP-i 1 HORSERADISH LEAVES 1-131 33.1 26-SEP-i 1 HORSERADISH LEAVES CS-134 8.7 26-SEP-i 1 HORSERADISH LEAVES CS-137 11.7 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 64

Exposure Pathway - Ingestion Food/Garden Location N-1 Collection Sample Nuclide Gamma Spectrum Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 25-APR-i 1 HORSERADISH LEAVES BE-7 381.6 +1- 138.5 25-APR-I 1 HORSERADISH LEAVES K-40 2,772.9 +1- 350.9 25-APR-i 1 HORSERADISH LEAVES MN-54 11.9 25-APR-i 1 HORSERADISH LEAVES CO-58 6.5 25-APR-i 1 HORSERADISH LEAVES FE-59 27.0 25-APR-11 HORSERADISH LEAVES CO-60 10.9 25-APR-I 1 HORSERADISH LEAVES ZN-65 16.9 25-APR-i 1 HORSERADISH LEAVES ZR-NB-95 3.8 25-APR-i 1 HORSERADISH LEAVES 1-131 9.3 25-APR-i 1 HORSERADISH LEAVES CS-134 7.3 25-APR-i 1 HORSERADISH LEAVES CS-137 7.0 25-MAY-i 1 HORSERADISH LEAVES BE-7 747.9 +1- 238.5 25-MAY-i 1 HORSERADISH LEAVES K-40 3,757.3 +1- 454.4 25-MAY-i 1 HORSERADISH LEAVES MN-54 14.3 25-MAY-i 1 HORSERADISH LEAVES CO-58 12.4 25-MAY-i 1 HORSERADISH LEAVES FE-59 28.2 25-MAY-i 1 HORSERADISH LEAVES CO-60 12.8 25-MAY-i 1 HORSERADISH LEAVES ZN-65 31.8 25-MAY-1i1 HORSERADISH LEAVES ZR-NB-95 19.7 25-MAY-i 1 HORSERADISH LEAVES 1-131 33.0 25-MAY-i 1 HORSERADISH LEAVES CS-134 12.5 25-MAY-i 1 HORSERADISH LEAVES CS-137 19.0 29-JUN-i 1 HORSERADISH LEAVES BE-7 840.9 +1- 211.9 29-JUN-i 1 HORSERADISH LEAVES K-40 3,271.6 +1- 385.5 29-JUN-11 HORSERADISH LEAVES MN-54 16.3 29-JUN-i 1 HORSERADISH LEAVES CO-58 15.3 29-JUN-11 HORSERADISH LEAVES FE-59 34.9 29-JUN-11 HORSERADISH LEAVES CO-60 14.0 29-JUN-11 HORSERADISH LEAVES ZN-65 25.4 29-JUN-11 HORSERADISH LEAVES ZR-NB-95 12.8 29-JUN-11 HORSERADISH LEAVES 1-131 18.7 29-JUN-11 HORSERADISH LEAVES CS-134 12.4 29-JUN-i 1 HORSERADISH LEAVES CS-137 18.6 25-JUL-11 HORSERADISH LEAVES BE-7 488.3 +1- 163.8 Duplicate 25-JUL-11 HORSERADISH LEAVES BE-7 543.9 +1- 158.2 25-JUL-i 1 HORSERADISH LEAVES K-40 2,414.0 +1- 350.0 Duplicate 25-JUL-11 HORSERADISH LEAVES K-40 2,562.2 +1- 319.8 25-JUL-11 HORSERADISH LEAVES MN-54 16.8 Duplicate 25-JUL-11 HORSERADISH LEAVES MN-54 11.6 25-JUL-11 HORSERADISH LEAVES CO-58 15.3 Duplicate 25-JUL-11 HORSERADISH LEAVES CO-58 11.8 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 65

Exposure Pathway - Ingestion Food/Garden Location N-1 Collection Sample Nuclide Gamma Spectrum Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 25-JUL-11 HORSERADISH LEAVES FE-59 26.9 Duplicate 25-JUL-11 HORSERADISH LEAVES FE-59 23.7 25-JUL-11 HORSERADISH LEAVES CO-60 11.0 Duplicate 25-JUL-11 HORSERADISH LEAVES CO-60 10.2 25-JUL-i 1 HORSERADISH LEAVES ZN-65 22.8 Duplicate 25-JUL-1i1 HORSERADISH LEAVES ZN-65 19.0 25-JUL-11 HORSERADISH LEAVES ZR-NB-95 15.6 Duplicate 25-JUL-11 HORSERADISH LEAVES ZR-NB-95 14.7 25-JUL-11 HORSERADISH LEAVES 1-131 28.2 Duplicate 25-JUL-11 HORSERADISH LEAVES 1-131 14.8 25-JUL-11 HORSERADISH LEAVES CS-134 17.3 Duplicate 25-JUL-11 HORSERADISH LEAVES CS-1 34 12.1 25-JUL-i 1 HORSERADISH LEAVES CS-1 37 19.6 Duplicate 25-JUL-i 1 HORSERADISH LEAVES CS-1 37 14.3 22-AUG-1i1 HORSERADISH LEAVES BE-7 739.1 +1- 168.3 22-AUG-i 1 HORSERADISH LEAVES K-40 3,782.0 +1- 403.2 22-AUG-i 1 HORSERADISH LEAVES MN-54 8.3 22-AUG-1i1 HORSERADISH LEAVES CO-58 13.5 22-AUG-i 1 HORSERADISH LEAVES FE-59 31.8 22-AUG-1i1 HORSERADISH LEAVES CO-60 9.3 22-AUG-i 1 HORSERADISH LEAVES ZN-65 27.3 22-AUG-i 1 HORSERADISH LEAVES ZR-NB-95 13.0 22-AUG-i 1 HORSERADISH LEAVES 1-131 16.6 22-AUG-i 1 HORSERADISH LEAVES CS-134 12.8 22-AUG-i 1 HORSERADISH LEAVES CS-137 18.3 26-SEP-i 1 HORSERADISH LEAVES BE-7 1,238.3 +1- 108.9 26-SEP-i 1 HORSERADISH LEAVES K-40 4,349.9 +1- 220.5 26-SEP-1i1 HORSERADISH LEAVES MN-54 6.8 26-SEP-1i1 HORSERADISH LEAVES CO-58 4.5 26-SEP-1i1 HORSERADISH LEAVES FE-59 13.9 26-SEP-1i1 HORSERADISH LEAVES CO-60 4.9 26-SEP-I 1 HORSERADISH LEAVES ZN-65 20.3 26-SEP-11 HORSERADISH LEAVES ZR-NB-95 11.9 26-SEP-i 1 HORSERADISH LEAVES 1-131 26.8 26-SEP-i 1 HORSERADISH LEAVES CS-134 7.4 26-SEP-i 1 HORSERADISH LEAVES CS-137 8.3 24-OCT-1i1 HORSERADISH LEAVES BE-7 765.7 +1- 196.6 24-OCT-1i1 HORSERADISH LEAVES K-40 4,056.3 +1- 412.6 24-OCT-1i1 HORSERADISH LEAVES MN-54 15.0 24-OCT-i 1 HORSERADISH LEAVES CO-58 16.1 24-OCT-1 1 HORSERADISH LEAVES FE-59 31.7 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 66

Exposure Pathway - Ingestion Food/Garden Location N-1 Collection Sample Nuclide Gamma Spectrum Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 24-OCT-1i1 HORSERADISH LEAVES CO-60 10.1 24-OCT-i 1 HORSERADISH LEAVES ZN-65

  • 28.3 24-OCT-i 1 HORSERADISH LEAVES ZR-NB-95
  • 20.3 24-OCT-i 1 HORSERADISH LEAVES 1-131
  • 36.6 24-OCT-i 1 HORSERADISH LEAVES CS-134
  • 12.5 24-OCT-1i1 HORSERADISH LEAVES CS-1 37

Exposure Pathway - Ingestion Food/Garden Location Q-6 Collection Sample Nuclide Gamma Spectrum Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 29-JUN-11 HORSERADISH LEAVES BE-7 1,509.6 +/- 230.6 29-JUN-i 1 HORSERADISH LEAVES K-40 4,649.0 +1- 443.8 29-JUN-11 HORSERADISH LEAVES MN-54 12.8 29-JUN-i 1 HORSERADISH LEAVES CO-58 10.7 29-JUN-11 HORSERADISH LEAVES FE-59 24.0 29-JUN-11 HORSERADISH LEAVES CO-60 10.0 29-JUN-11 HORSERADISH LEAVES ZN-65 <1 29.7 29-JUN-i 1 HORSERADISH LEAVES ZR-NB-95 +< 19.0 29-JUN-i 1 HORSERADISH LEAVES 1-131 19.4 29-JUN-11 HORSERADISH LEAVES CS-134 15.2 29-JUN-1i1 HORSERADISH LEAVES CS-137 12.8 25-JUL-11 SQUASH LEAVES BE-7 712.8 222.4 25-JUL-1i1 SQUASH LEAVES K-40 6,477.5 553.8 25-JUL-11 SQUASH LEAVES MN-54 <1 13.3 25-JUL-1 I SQUASH LEAVES <1 20.3 CO-58 25-JUL-11 SQUASH LEAVES FE-59 45.8 25-JUL-11 SQUASH LEAVES CO-60 19.5 25-JUL-1I SQUASH LEAVES ZN-65 17.6

+1-25-JUL-1i1 SQUASH LEAVES ZR-NB-95 20.0 25-JUL-11 SQUASH LEAVES 1-131 31.1 25-JUL-11 SQUASH LEAVES CS-134 14.5 25-JUL-11 SQUASH LEAVES CS-137 17.8 22-AUG-i 1 SQUASH LEAVES BE-7 746.4 228.4 Duplicate 22-AUG-i 1 SQUASH LEAVES BE-7 777.5 199.8 22-AUG-i 1 SQUASH LEAVES K-40 6,631.1 571.0 Duplicate 22-AUG-i 1 SQUASH LEAVES K-40 6,156.8 512.6 22-AUG-1 1 SQUASH LEAVES MN-54 22.8 Duplicate 22-AUG-1i1 SQUASH LEAVES MN-54 10.2 22-AUG-i 1 SQUASH LEAVES CO-58 20.9 Duplicate 22-AUG-i 1 SQUASH LEAVES CO-58 13.1 22-AUG-i 1 SQUASH LEAVES FE-59 42.9 Duplicate 22-AUG-i 1 SQUASH LEAVES FE-59 26.4 22-AUG-i 1 SQUASH LEAVES CO-60 21.3 Duplicate 22-AUG-i 1 SQUASH LEAVES CO-60 11.8 22-AUG-i 1 SQUASH LEAVES ZN-65 27.7 Duplicate 22-AUG-i 1 SQUASH LEAVES ZN-65 28.5 22-AUG-i 1 SQUASH LEAVES ZR-NB-95 21.2 Duplicate 22-AUG-i 1 SQUASH LEAVES ZR-NB-95 14.5 22-AUG-1i1 SQUASH LEAVES 1-131 37.1 Duplicate 22-AUG-i 1 SQUASH LEAVES 1-131 25.1 22-AUG-i 1 SQUASH LEAVES CS-1 34 16.5 Duplicate 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 68

Exposure Pathway - Ingestion Food/Garden Location Q-6 Collection Sample Nuclide Gamma Spectrum Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 22-AUG-i 1 SQUASH LEAVES CS-134 < 11.6 22-AUG-11 SQUASH LEAVES CS-137 23.5 Duplicate 22-AUG-1i1 SQUASH LEAVES CS-137 11.0 26-SEP-I 1 SQUASH LEAVES BE-7 4,453.3 +/- 260.0 26-SEP-11 SQUASH LEAVES K-40 4,610.7 +/- 362.4 26-SEP-11 SQUASH LEAVES MN-54 9.9 26-SEP-11 SQUASH LEAVES CO-58 6.0 26-SEP-1 1 SQUASH LEAVES FE-59 30.1 26-SEP-i 1 SQUASH LEAVES CO-60 12.0 26-SEP-11 SQUASH LEAVES ZN-65 21.9 26-SEP-i 1 SQUASH LEAVES ZR-NB-95 11.8 26-SEP-11 SQUASH LEAVES 1-131 15.6 26-SEP-11 SQUASH LEAVES CS-134 11.4 26-SEP-i 1 SQUASH LEAVES CS-1 37 12.2 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 69

Exposure Pathway - Ingestion Feed and Forage Location NR-D1 Collection Sample Nuclide Gamma Spectrum Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 14-OCT-i 1 IRRIGATED SOYBEANS BE-7 70.1 14-OCT-i 1 IRRIGATED SOYBEANS K-40 15,148.0 +/- 611.2 14-OCT-11 IRRIGATED SOYBEANS MN-54 7.2 14-OCT-11 IRRIGATED SOYBEANS CO-58 < 8.0 14-OCT-I 1 IRRIGATED SOYBEANS FE-59 < 22.9 14-OCT-I 1 IRRIGATED SOYBEANS CO-60 < 11.0 14-OCT-i 1 IRRIGATED SOYBEANS ZN-65 < 28.9 14-OCT-11 IRRIGATED SOYBEANS ZR-NB-95 < 10.4 14-OCT-11 IRRIGATED SOYBEANS 1-131 < 17.4 14-OCT-11 IRRIGATED SOYBEANS CS-134 < 7.9 14-OCT-11 IRRIGATED SOYBEANS CS-137 < 15.5 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 70

Exposure Pathway - Ingestion Feed and Forage Location NR-D2 Collection Sample Nuclide Gamma Spectrum Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 05-OCT-i 1 IRRIGATED SOYBEANS BE-7 < 129.6 05-OCT-i 1 IRRIGATED SOYBEANS K-40 14,440.0 +/- 634.3 05-OCT-i 1 IRRIGATED SOYBEANS MN-54 < 13.0 05-OCT-11 IRRIGATED SOYBEANS CO-58 < 13.4 05-OCT-i 1 IRRIGATED SOYBEANS FE-59 < 34.3 05-OCT-i 1 IRRIGATED SOYBEANS CO-60 < 19.3 05-OCT-i 1 IRRIGATED SOYBEANS ZN-65 < 34.6 05-OCT-i 1 IRRIGATED SOYBEANS ZR-NB-95 < 12.5 05-OCT-i 1 IRRIGATED SOYBEANS 1-131 < 29.2 05-OCT-i 1 IRRIGATED SOYBEANS CS-134 < 14.2 05-OCT-1i1 IRRIGATED SOYBEANS CS-1 37 < 14.3 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 71

Exposure Pathway - Ingestion Feed and Forage Location NR-UI Collection Sample Nuclide Gamma Spectrum Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 02-SEP-i 1 IRRIGATED CORN BE-7 40.2 02-SEP-i 1 IRRIGATED CORN K-40 3,378.6 +/- 162.0 02-SEP-i 1 IRRIGATED CORN MN-54 4.3 02-SEP-i 1 IRRIGATED CORN CO-58 4.5 02-SEP-i 1 IRRIGATED CORN FE-59 7.9 02-SEP-1i1 IRRIGATED CORN CO-60 4.4 02-SEP-1i1 IRRIGATED CORN ZN-65 9.1 02-SEP-i 1 IRRIGATED CORN ZR-NB-95 6.2 02-SEP-i 1 IRRIGATED CORN 1-131 11.3 02-SEP-11 IRRIGATED CORN CS-1 34 4.8 02-SEP-1i1 IRRIGATED CORN CS-1 37 4.0 01-OCT-11 IRRIGATED SOYBEANS BE-7 85.1 01-OCT-11 IRRIGATED SOYBEANS K-40 12,2i12.0 +/- 488.4 01-OCT-11 IRRIGATED SOYBEANS MN-54 9.1 01-OCT-11 IRRIGATED SOYBEANS CO-58 14.3 01-OCT-11 IRRIGATED SOYBEANS FE-59 23.5 01-OCT-11 IRRIGATED SOYBEANS CO-60 6.2 01-OCT-11 IRRIGATED SOYBEANS ZN-65 32.8 01-OCT-11 IRRIGATED SOYBEANS ZR-NB-95 14.7 01-OCT-11 IRRIGATED SOYBEANS 1-131 31.9 01-OCT-11 IRRIGATED SOYBEANS CS-134 6.9 01-OCT-11 IRRIGATED SOYBEANS CS-1 37 8.5 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 72

Exposure Pathway - Aquatic Bottom Sediment Location DC Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 28-JUN- 11 K-40 10.,099.0 +/- 1,028.0 28-JUN-11 MN-54 < 45.4 28-JUN-11 CO-58 < 41.9 28-JUN-11 FE-59 < 79.2 28-JUN-i 1 CO-60 < 52.6 28-JUN-11 ZN-65 < 98.2 28-JUN-11 CS-134 < 30.8 28-JUN-11 CS-137 99.0 +/- 48.2 28-JUN-11 FE-55 < 14,545.2 23-NOV-i 1 K-40 12 ,271.0 +/- 1,040.0 23-NOV-i 1 MN-54 < 40.7 23-NOV-1i1 CO-58 < 51.0 23-NOV-1i1 FE-59 < 117.1 23-NOV-i 1 CO-60 < 32.4 23-NOV-i 1 ZN-65 < 78.0 23-NOV-i 1 CS-134 < 39.8 23-NOV-i 1 CS-137 107.1 +/- 42.1 23-NOV-i 1 FE-55 < 16,337.0 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 73

Exposure Pathway - Aquatic Bottom Sediment Location EEA Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 12-APR-11 K-40 11,062.0 +/- 622.5 12-APR- 1l MN-54 < 24.3 12-APR-11 CO-58 < 25.7 12-APR-11 FE-59 < 52.7 12-APR- 1l CO-60 < 12.7 12-APR- 1l ZN-65 < 42.2 12-APR- 1l CS-134 < 17.7 12-APR-11 CS-1 37 66.4 +/- 33.1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 74

Exposure Pathway - Aquatic Bottom Sediment Location ESW 2011-1 Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 28-JUN-i 1 K-40 11,888.0 +/- 1,065.0 28-JUN-i 1 MN-54 < 35.9 28-JUN-11 CO-58 < 48.0 28-JUN-11 FE-59 < 136.3 28-JUN-i 1 CO-60 < 27.8 28-JUN-11 ZN-65 < 93.8 28-JUN-1i1 CS-134 < 45.0 28-JUN-11 CS-137 67.2 +/- 35.7 28-JUN-11 FE-55 < 14,684.7 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 75

Exposure Pathway - Aquatic Bottom Sediment Location ESW 2011-2 Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 07-DEC-i 1 K-40 10,184.0 +/- 1,128.0 07-DEC-i 1 MN-54 < 42.2 07-DEC-i 1 CO-58 < 47.3 07-DEC-1i1 FE-59 < 92.7 07-DEC-i 1 CO-60 < 34.7 07-DEC-i 1 ZN-65 < 77.5 07-DEC-i 1 CS-134 < 32.1 07-DEC-1i1 CS-137 < 38.2 07-DEC-i 1 FE-55 < 17,084.1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 76

Exposure Pathway - Aquatic Bottom Sediment Location JRR Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 30-JUN-11 K-40 11,650.0 +/- 1,074.0 30-JUN-11 MN-54 < 43.6 30-JUN-11 CO-58 < 56.7 30-JUN-11 FE-59 < 42.1 30-JUN-11 CO-60 < 29.3 30-JUN-I 1 ZN-65 < 76.2 30-JUN-1i1 CS-1 34 < 41.3 30-JUN-i 1 CS-137 < 62.5 23-NOV-11 K-40 12,002.0 +/- 1,002.0 23-NOV-i 1 MN-54 < 54.6 23-NOV-i 1 CO-58 < 19.7 23-NOV-i 1 FE-59 < 84.6 23-NOV-i 1 CO-60 < 12.6 23-NOV-i 1 ZN-65 < 96.0 23-NOV-i 1 CS-134 < 38.9 23-NOV-11 CS-137 91.2 +/- 49.4 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 77

Exposure Pathway - Aquatic Bottom Sediment Location MUDS Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 22-JUN-11 K-40 9,567.9 +/- 580.1 22-JUN-i 1 MN-54 26.5 22-JUN-i 1 CO-58 29.3 22-JUN-11 FE-59 66.3 22-JUN-11 CO-60 19.1 22-JUN-i 1 ZN-65 52.4 22-JUN-1i1 CS-134 24.5 22-JUN-i 1 CS-137 27.0 06-SEP-1i1 K-40 9,989.6+1 659.4 06-SEP-i 1 MN-54 28.9 06-SEP-i 1 CO-58 19.8 06-SEP-1i1 FE-59 18.9 06-SEP-i 1 CO-60 11.1 06-SEP-11 ZN-65 41.5 06-SEP-1i1 CS-134 23.5 06-SEP-i 1 CS-137 20.7 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 78

Exposure Pathway - Aquatic Bottom Sediment Location UHS 2011-1 Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 28-JUN-i 1 K-40 11,598.0 +/- 1,156.0 28-JUN-11 MN-54 < 46.7 28-JUN-11 CO-58 < 42.8 28-JUN-11 FE-59 < 48.6 28-JUN-i 1 CO-60 < 27.0 28-JUN-i 1 ZN-65 < 83.9 28-JUN-11 CS-134 < 44.9 28-JUN-11 CS-137 119.5 +/- 53.5 28-JUN-11 FE-55 < 14,458.7 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 79

Exposure Pathway - Aquatic Bottom Sediment Location UHS 2011-2 Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 28-JUN-i 1 K-40 9,608.0 +/- 868.4 28-JUN-11 MN-54 < 42.5 28-JUN-11 CO-58 < 38.2 28-JUN-11 FE-59 < 53.1 28-JUN-i 1 CO-60 < 39.4 28-JUN-11 ZN-65 < 73.1 28-JUN-11 CS-134 < 32.1 28-JUN-11 CS-1 37 89.6 +/- 47.9 28-JUN-11 FE-55 < 14,528.1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 80

Exposure Pathway - Aquatic Bottom Sediment Location UHS 2011-3 Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 28-JUN-i 1 K-40 11,466.0 +/- 994.4 28-JUN-11 MN-54 < 42.3 28-JUN-11 CO-58 < 37.2 28-JUN-11 FE-59 < 87.1 28-JUN-i 1 CO-60 < 41.1 28-JUN-1i1 ZN-65 < 87.6 28-JUN-11 CS-134 < 28.8 28-JUN-11 CS-137 < 36.1 28-JUN-11 FE-55 < 14,398.4 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 81

Exposure Pathway - Aquatic Bottom Sediment Location UHS 2011-4 Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 28-JUN-11 K-40 10,420.0 +/- 968.6 28-JUN-11 MN-54 < 47.8 28-JUN-11 CO-58 < 45.4 28-JUN-i 1 FE-59 < 68.2 28-JUN-i 1 CO-60 < 38.9 28-JUN-11 ZN-65 < 99.6 28-JUN-11 CS-1 34 < 42.2 28-JUN-i 1 CS-137 83.8 +/- 44.8 28-JUN-11 FE-55 < 14,787.2 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 82

Exposure Pathway - Aquatic Bottom Sediment Location UHS 2011-5 Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 07-DEC-i 1 K-40 8,906.0 +/- 845.9 07-DEC-11 MN-54 < 37.1 07-DEC-i 1 CO-58 < 19.0 07-DEC-i 1 FE-59 < 36.6 07-DEC-i 1 CO-60 < 21.5 07-DEC-i 1 ZN-65 < 76.9 07-DEC-i 1 CS-134 < 29.3 07-DEC-i 1 CS-1 37 < 36.4 07-DEC-i 1 FE-55 < 16,710.3 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 83

Exposure Pathway - Aquatic Bottom Sediment Location UHS 2011-6 Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCiIKg Dry) 07-DEC-11 K-40 10,735.0 +/- 1,048.0 07-DEC-I 1 MN-54 < 41.8 07-DEC-1i1 CO-58 < 33.3 07-DEC-i 1 FE-59 < 132.9 07-DEC-11 CO-60 < 29.6 07-DEC-i 1 ZN-65 < 70.9 07-DEC-i 1 CS-1 34 < 40.7 07-DEC-i 1 CS-137 < 45.6 07-DEC-1i1 FE-55 < 16,970.5 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 84

Exposure Pathway - Aquatic Bottom Sediment Location UHS 2011-7 Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 07-DEC-1 I K-40 10,245.0 +/- 1,029.0 07-DEC-i 1 MN-54 < 31.8 07-DEC-i 1 CO-58 < 49.2 07-DEC-i 1 FE-59 < 104.1 07-DEC-1i1 CO-60 < 20.4 07-DEC-i 1 ZN-65 < 104.2 07-DEC-i 1 CS-134 < 37.5 07-DEC-i 1 CS-1 37 < 48.6 07-DEC-1i1 FE-55 < 15,818.6 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 85

Exposure Pathway - Aquatic Bottom Sediment Location UHS 2011-8 Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 07-DEC-i 1 K-40 10,843.0 +/- 1,017.0 07-DEC-i 1 MN-54 < 49.5 07-DEC-i 1 CO-58 < 33.2 07-DEC-1i1 FE-59 < 110.2 07-DEC-i 1 CO-60 < 22.1 07-DEC-1i1 ZN-65 < 63.0 07-DEC-i 1 CS-134 < 34.3 07-DEC-1 1 CS-137 114.5 +/- 57.4 07-DEC-1i1 FE-55 < 16,880.1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 86

Exposure Pathway - Aquatic Bottom Sediment Location UHS HS-1 Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 28-JUN-11 K-40 12,059.0 +/- 1,126.0 28-JUN-11 MN-54 < 49.9 28-JUN-11 CO-58 < 35.2 28-JUN-11 FE-59 < 86.8 28-JUN-11 CO-60 < 51.5 28-JUN-11 ZN-65 < 98.2 28-JUN-11 CS-134 < 47.1 28-JUN-11 CS-1 37 109.1 +/- 40.6 28-JUN-11 FE-55 < 14,258.7 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 87

Exposure Pathway - Aquatic Bottom Sediment Location UHS HS-2 Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 07-DEC-i 1 K-40 9,261.6 +/- 888.0 07-DEC-i 1 MN-54 < 49.0 07-DEC-I 1 CO-58 < 59.0 07-DEC-i 1 FE-59 < 79.9 07-DEC-i 1 CO-60 < 40.4 07-DEC-i 1 ZN-65 < 73.5 07-DEC-11 CS-134 < 35.6 07-DEC-i 1 CS-137 113.1 +/- 61.9 07-DEC-1i1 FE-55 < 16,923.5 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 88

Exposure Pathway - Aquatic Vegetation Location DC-ALT Collection Sample Nuclide Gamma Spectrum Duplicate Date Description Concentration Sample (pCi/Kg Wet) 27-JUL-11 AMERICAN LOTUS BE-7 309.3 +/- 127.1 27-JUL-i 1 AMERICAN LOTUS K-40 3,629.9 +/- 310.3 27-JUL-11 AMERICAN LOTUS MN-54 < 10.3 27-JUL-11 AMERICAN LOTUS CO-58 < 9.3 27-JUL-11 AMERICAN LOTUS FE-59 < 21.3 27-JUL-11 AMERICAN LOTUS CO-60 < 11.8 27-JUL-I 1 AMERICAN LOTUS ZN-65 < 23.2 27-JUL-11 AMERICAN LOTUS ZR-NB-95 < 11.3 27-JUL-i 1 AMERICAN LOTUS 1-131 < 18.4 27-JUL-11 AMERICAN LOTUS CS-134 < 8.4 27-JUL-1i1 AMERICAN LOTUS CS-137 < 9.9 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 89

Exposure Pathway - Aquatic Vegetation Location MUDS Collection Sample Nuclide Gamma Spectrum Duplicate Date Description Concentration Sample (pCi/Kg Wet) 22-JUN-i 1 ALGAE BE-7 3,207.8 +1- 241.2 22-JUN-11 ALGAE K-40 2,611.7 +1- 328.9 22-JUN-11 ALGAE MN-54 10.5 22-JUN-11 ALGAE CO-58 6.1 22-JUN-1i1 ALGAE FE-59 16.2 22-JUN-i 1 ALGAE CO-60 11.1 22-JUN-11 ALGAE ZN-65 25.4 22-JUN-11 ALGAE ZR-NB-95 12.7 22-JUN-1i1 ALGAE 1-131 24.6 22-JUN-11 ALGAE CS-134 13.4 22-JUN-11 ALGAE CS-137 16.4 06-SEP-i 1 PONDWEED BE-7 288.7 +1- 132.1 06-SEP-I 1 PONDWEED K-40 2,637.7 +1- 316.1 06-SEP-1i1 PONDWEED MN-54 11.6 06-SEP-i 1 PONDWEED CO-58 8.2 06-SEP-11 PONDWEED FE-59 20.4 06-SEP-i 1 PONDWEED CO-60 8.4 06-SEP-1i1 PONDWEED ZN-65 12.2 06-SEP-i 1 PONDWEED ZR-NB-95 12.0 06-SEP-i 1 PONDWEED 1-131 19.1 06-SEP-i 1 PONDWEED CS-134 13.5 06-SEP-i 1 PONDWEED CS-1 37 13.4 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 90

Exposure Pathway - Terrestrial Vegetation Location MUDS Collection Sample Nuclide Gamma Spectrum Duplicate Date Description Concentration Analysis (pCiIKg Wet) 22-JUN-i 1 GRASS BE-7 4,971.5 +/- 426.5 22-JUN-11 GRASS K-40 4,160.7 +/- 478.1 22-JUN-11 GRASS MN-54 20.5 22-JUN-11 GRASS CO-58 9.9 22-JUN-11 GRASS FE-59 31.9 22-JUN-11 GRASS CO-60 10.3 22-JUN-11 GRASS ZN-65 33.6 22-JUN-11 GRASS ZR-NB-95 22.1 22-JUN-11 GRASS 1-131 40.4 22-JUN-11 GRASS CS-134 18.2 22-JUN-i 1 GRASS CS-137 21.6 06-SEP-i 1 GRASS BE-7 2,558.7 +/- 309.3 06-SEP-i 1 GRASS K-40 3,310.2 +/- 480.8 06-SEP-i 1 GRASS MN-54 18.9 06-SEP-i 1 GRASS CO-58 13.9 06-SEP-I 1 GRASS FE-59 38.7 06-SEP-11 GRASS CO-60 12.9 06-SEP-i 1 GRASS ZN-65 20.1 06-SEP-1i1 GRASS ZR-NB-95 23.1 06-SEP-i 1 GRASS 1-131 41.1 06-SEP-11 GRASS CS-1 34 20.0 06-SEP-i 1 GRASS CS-1 37 27.4 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 91

Exposure Pathway - Terrestrial Soil Location MUDS Collection Nuclide Gamma Spectrum Duplicate Date Concentration Analysis (pCi/Kg Dry) 07-JUN-11 K-40 10,054.0 +/- 609.3 07-JUN-i 1 MN-54 < 27.3 07-JUN-1i1 CO-58 < 25.2 07-JUN-11 FE-59 < 90.0 07-JUN-i 1 CO-60 < 23.4 07-JUN-11 ZN-65 < 51.4 07-JUN-1i1 CS-134 < 17.4 07-JUN-11 CS-137 112.3 +/- 21.7 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 92

Exposure Pathway - Ingestion Meat Location C.36 Collection Sample Nuclide Gamma Spectrum & H-3 Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 29-JUN-11 DEER K-40 3,124.4+/- 360.6 29-JUN-i 1 DEER MN-54 < 7.2 29-JUN-11 DEER CO-58 < 9.8 29-JUN-11 DEER FE-59 < 22.1 29-JUN-11 DEER CO-60 < 8.0 29-JUN-i 1 DEER ZN-65 < 11.7 29-JUN-11 DEER CS-1 34 < 10.0 29-JUN-11 DEER CS-1 37 < 8.4 29-JUN-11 DEER H-3 126.0 +/- 63.0 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C - 93

Exposure Pathway - Ingestion Meat Location Q1.4 Collection Sample Nuclide Gamma Spectrum & H-3 Duplicate Date Description Concentration Analysis (pCi/Kg Wet) 02-OCT-11 DEER K-40 2,756.1 +/- 379.9 02-OCT-i 1 DEER MN-54 < 10.4 02-OCT-I 1 DEER CO-58 < 5.8 02-OCT-i 1 DEER FE-59 < 24.9 02-OCT-i 1 DEER CO-60 < 8.7 02-OCT- 11 DEER ZN-65 < 20.0 02-OCT-i 1 DEER CS-134 < 11.7 02-OCT-i 1 DEER CS-137 < 11.2 02-OCT-i 1 DEER H-3 1,529.0+/- 102.0 ReCount 02-OCT-i 1 DEER H-3 1,370.0 +/- 104.0 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page C- 94

WOLF CREEK GENERATING STATION 2011 LAND USE CENSUS REPORT Revision I V

Prepared by:

3/13/12 Teresa L. Rice Date Peer Review:

3/20/12 Dan E. Haines Date Approved by:

3/21/12 Robert A. Hammond Date 2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 1

EXECUTIVE

SUMMARY

The 2011 Land Use Census Report has been revised to re-calculate the D/Qs for the broadleaf vegetation locations. The rental property located at R2.08-NALN1650 is now vacant. The D/Qs have been re-calculated, omitting the R2.08-NALN1650 location.

The annual Land Use Census of rural residents within five miles of the Wolf Creek Generating Station (WCGS) has been completed for 2011 in accordance with AP 07B-004, [Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)].

No program changes are necessary regarding milk locations. Again, no milk sampling locations were identified.

The two broadleaf vegetation locations with the highest calculated annual average D/Q rankings are Q2.35-MILA1619 and N2.38-RODR9. The landowners of these gardens have agreed to participate in the 2012 sample program.

BACKGROUND Section 5.2, Attachment A, of the ODCM procedure (AP 07B-004), directs that "a Land Use Census shall be conducted annually during the growing season to identify the nearest (1) milk animal, (2) residence, and (3) garden of greater than 500 square feet producing broadleaf vegetation in each of the 16 meteorological sections within five miles of the WCGS site" and "the results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report."

Table 5-1, Attachment A, of the ODCM (AP 07B-004) requires that broadleaf vegetation samples be collected from "two indicator locations (using the criteria from the "Land Use Census" section) with highest calculated annual average D/Q."

Table 5-1, Attachment A, of the ODCM (AP 07B-004) also requires that milk samples be collected from "three indicator locations within 5 miles of the site having the highest dose potential."

METHODOLOGY Over two hundred surveys were mailed to the rural residents living within five miles of WCGS.

A follow-up survey was sent to residents who did not respond. The survey excluded the residents of New Strawn, Burlington, and a trailer park north of Burlington. These locations were excluded due to the large number of households and the low likelihood that information gained from these residences would affect the locations chosen for REMP sampling. Drive-by information was collected for the nearest residences that did not return surveys.

The information collected was compiled and the results are identified in Tables 1-3.

Calculations were performed so that garden locations could be ranked by their respective D/Q.

These results are contained in Table 4.

2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 2

RESULTS NOTE: A Global Positioning System was used to verify residence distances and sectors.

Three changes were noted for the nearest occupied residences in each sector. Those changes were in sectors E, F, and N.

Seven location changes were noted for the nearest garden producing broadleaf vegetation.

These changes are identified in Table 3.

There were no changes regarding milk sample locations. Again, no locations were identified that routinely milked animals for human consumption.

2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 3

TABLE 1 2011 Land Use Census Data Location of Nearest:

Sector Residence Milkinq Animals Broadleaf Garden A A2.60-17TEl 520 None A4.91-OXRD1940 B B3.53-QURD1755 None None C C1.92-16RD1655 None C4.63-RERD1825 D D2.03-QULA1571 None D2.41 -RERD 1541 E El.78-QULA1451 None None F F1.84-QULA1419 None F2.39-14RD1802 G G3.03-13RD1820 None G3.77-12RD1831 H H3.09-12RD1711 None H3.30-QURD1 1.75 J J3.70-1 1 RD1540 None J4.00-PLRD1080 K K2.70-12LA1439 None K4.10-NARD1120 L L2.10-NARD 1339 None None M M2.34-14RD1330 None M3.10-13LA1 290 N N2.08-15RD1350 None N2.38-RODR9 P P2.76-HW751534 None P2.76-HW751534 Q Q2.35-MILA1619 None Q2.35-MILA1619 R R2.08-NALN1650 None None Identifiers are based upon the following protocol:

EXAMPLE: A1.4-16RD1525 "A" = Sector A "1.4" = 1.4 miles from the reactor "16RD1525" = address 2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D -4

TABLE 2 SECTOR 2010 NEAREST 2011 NEAREST RESIDENCE RESIDENCE A A2.60-17TE1520 A2.60-17TE1520 B B3.53-QURD1755 B3.53-QURD1755 C C1.92-16RD1655 C1.92-16RD1655 D D2.03-QULA1571 D2.03-QULA1571 E E1.77-QULA1485 E1.78-QULA1451 F F2.28-14RD1785 F1.84-QULA1419 G G3.03-13RD1820 G3.03-13RD1820 H H3.09-12RD1711 H3.09-12RD1711 J J3.70-11RD1540 J3.70-11 RD1540 K K2.70-12LA1439 K2.70-12LA1439 L L2.10-NARD 1339 L2.10-NARD 1339 M M2.34-14RD1330 M2.34-14RD1330 N N1.71-NARD1441 N2.08-15RD1350 P P2.76-HW751534 P2.76-HW751534 Q Q2.35-MILA1619 Q2.35-MILA1619 R R4.43-NARD1891 R4.43-NARD1891 NOTE: Entries underlined indicate changes from the 2010 Land Use Census.

Locations are identified based upon the following protocol:

EXAMPLE: A1.4-16RD1525 First letter is based upon sector, thus "A" designates this residence is in sector A.

The number immediately following the first letter designates the distance (in miles) from the reactor.

The characters following the dash represent a unique identifier based upon location address.

The example is in sector A, 1.4 miles from the reactor, at 1525 16th Road.

2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 5

TABLE 3 2011 Land Use Census Milk and Garden Data SECTOR 2010 2011 2010 CLOSEST 2011 CLOSEST MILKING MILKING GARDEN GARDEN ANIMALS ANIMALS PRODUCING PRODUCING BROADLEAF BROADLEAF VEGETATION VEGETATION A None None None A4.91-OXRD1940 B None None None None C None None C4.89-18RD1859 C4.63-RERD1825 D None None D3.00-16RD1829 D2.41-RERD1541 E None None None None F None None F2.44-RERD1391 F2.39-14RD1802 G None None G3.77-12RD1831 G3.77-12RD1831 H None None H3.30-QURD1175 H3.30-QURD1175 J None None J3.90-11RD1531 J4.00-PLRD1080 K None None None K4.10-NARD 1120 L None None L2.39-NARD1309 None M None None M3.10-13LA1290 M3.10-13LA1 290 N None None N2.38-RODR9 N2.38-RODR9 P None None P2.76-HW751534 P2.76-HW751534 Q None None Q2.35-MILA1619 Q2.35-MILA1619 R None None None None NOTE: Underlined entries indicate changes from the 2010 Land Use Census.

Locations are identified based upon the following protocol:

EXAMPLE: A1.4-16RD1525 First letter is based upon sector, thus "A" designates this residence is in sector A.

The number immediately following the first letter designates the distance (in miles) from the reactor.

The characters following the dash represent a unique identifier based upon location address.

The example is in sector A, 1.4 miles from the reactor, at 1525 16th Road.

2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Pzge D -6

TABLE 4 Information Used for D/Q Calculations FROM LAND FROM USE CENSUS SA-10-004 Eval.

DIST CALC NEAR NEAR FAR FAR SECTOR SECTOR (MI) (METERS) DIST D/Q DIST D/Q CALC RANKING A 4.91 7902 7000 6.53E-10 8000 5.27E-10 5.39E-10 5 B

C 4.63 7451 7000 1.66E-10 8000 1.34E-10 1.52E-10 12 D 2.41 3879 3000 4.46E-10 4000 2.67E-10 2.89E-10 11 E

F 2.39 3846 3000 7.22E-10 4000 4.33E-10 4.78E-10 6 G 3.77 6067 6000 3.57E-10 7000 2.65E-10 3.51E-10 9 H 3.30 5311 5000 7.01E-10 6000 5.16E-10 6.43E-10 3 J 4.00 6437 6000 4.33E-10 7000 3.22E-10 3.84E-10 8 K 4.10 6598 6000 3.82E-10 7000 2.84E-10 3.23E-10 10 L I M 3.10 4989 4000 5.73E-10 5000 3.90E-10 3.92E-10 7 N 2.38 3830 3000 1.25E-09 4000 7.51E-10 8.36E-10 2 P 2.76 4442 4000 6.88E-10 5000 4.68E-10 5.91E-10 4 Q 2.35 3782 3000 1.53E-09 4000 9.17E-10 1.05E-09 1 R I I I Originated by: Date: 3/13/12 Verified by: Date: 3/20/12 2011 Land Use Census Report, Revision 1 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 7

WOLF CREEK GENERATING STATION 2011 LAND USE CENSUS REPORT A

Prepared by:

11/3/11 Teresa L. Rice Date Peer Review:

11/3/11 Dan E. Haines Date Approved by:

11/3/11 Robert A. Hammond Date 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 8

EXECUTIVE

SUMMARY

The annual Land Use Census of rural residents within five miles of the Wolf Creek Generating Station (WCGS) has been completed for 2011 in accordance with AP 07B-004, [Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)].

No program changes are necessary regarding milk locations. Again, no milk sampling locations were identified.

Changes may be necessary for the Radiological Environmental Monitoring Program (REMP) broadleaf vegetation sample locations for 2012. The two broadleaf vegetation locations with the highest calculated annual average D/Q rankings are R2.08-NALN1650 and Q2.35-MILA1619. AP 07B-004 specifies that an "alternate location may be used to provide continued monitoring". The third-ranked garden is N2.38-RODR9. Prior to the 2012 growing season the residents should be contacted and based upon their cooperation, the program should be changed accordingly.

BACKGROUND Section 5.2, Attachment A, of the ODCM procedure (AP 07B-004), directs that "a Land Use Census shall be conducted annually during the growing season to identify the nearest (1) milk animal, (2) residence, and (3) garden of greater than 500 square feet producing broadleaf vegetation in each of the 16 meteorological sections within five miles of the WCGS site" and "the results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report."

Table 5-1, Attachment A, of the ODCM (AP 07B-004) requires that broadleaf vegetation samples be collected from "two indicator locations (using the criteria from the "Land Use Census" section) with highest calculated annual average D/Q."

Table 5-1, Attachment A, of the ODCM (AP 07B-004) also requires that milk samples be collected from "three indicator locations within 5 miles of the site having the highest dose potential."

METHODOLOGY Over two hundred surveys were mailed to the rural residents living within five miles of WCGS.

A follow-up survey was sent to residents who did not respond. The survey excluded the residents of New Strawn, Burlington, and a trailer park north of Burlington. These locations were excluded due to the large number of households and the low likelihood that information gained from these residences would affect the locations chosen for REMP sampling. Drive-by information was collected for the nearest residences that did not return surveys.

The information collected was compiled and the results are identified in Tables 1-3.

Calculations were performed so that garden locations could be ranked by their respective D/Q.

These results are contained in Table 4.

2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 9

RESULTS NOTE: A Global Positioning System was used to verify residence distances and sectors.

Four changes were noted for the nearest occupied residences in each sector. Those changes were in sectors E, F, N, and R.

Seven location changes were noted for the nearest garden producing broadleaf vegetation.

These changes are identified in Table 3.

There were no changes regarding milk sample locations. Again, no locations were identified that routinely milked animals for human consumption.

2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 10

TABLE I 2011 Land Use Census Data Location of Nearest:

Sector Residence Milking Animals Broadleaf Garden A A2.60-17TE1520 None A4.91 -OXRD1940 B B3.53-QURD1755 None None C C1.92-16RD1655 None C4.63-RERD1825 D D2.03-QULA1571 None D2.41 -RERD 1541 E El.78-QULA1451 None None F Fl.84-QULA1419 None F2.39-14RD1802 G G3.03-13RD1820 None G3.77-12RD1831 H H3.09-12RD1711 None H3.30-QURD1 175 J J3.70-1 1RD1540 None J4.00-PLRD1080 K K2.70-12LA1 439 None K4.10-NARD1120 L L2.10-NARD 1339 None None M M2.34-14RD1330 None M3.10-13LA1290 N N2.08-15RD1350 None N2.38-RODR9 P P2.76-HW751534 None P2.76-HW751534 Q Q2.35-MILA1619 None Q2.35-MILA1619 R R2.08-NALN 1650 None R2.08-NALN1650 Identifiers are based upon the following protocol:

EXAMPLE: A1.4-16RD1525 "A" = Sector A "1.4" = 1.4 miles from the reactor "16RD1525" = address 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D- 11

TABLE 2 SECTOR 2010 NEAREST 2011 NEAREST RESIDENCE RESIDENCE A A2.60-17TE1520 A2.60-17TE1520 B B3.53-QURD1755 B3.53-QURD1755 C C1.92-16RD1655 C1.92-16RD1655 D D2.03-QULA1571 D2.03-QULA1571 E E1.77-QULA1485 E1.78-QULA1451 F F2.28-14RD1785 F1.84-QULA1419 G G3.03-13RD1820 G3.03-13RD1820 H H3.09-12RD1711 H3.09-12RD1711 J J3.70-11RD1540 J3.70-11RD1540 K K2.70-12LA1439 K2.70-12LA1439 L L2.10-NARD1339 L2.10-NARD1339 M M2.34-14RD1330 M2.34-14RD1330 N N1.71-NARD1441 N2.08-15RD1350 P P2.76-HW751534 P2.76-HW751534 Q Q2.35-MILA1619 Q2.35-MILA1619 R R4.43-NARD1891 R2.08-NALN1650 NOTE: Entries underlined indicate changes from the 2010 Land Use Census.

Locations are identified based upon the following protocol:

EXAMPLE: A1.4-16RD1525 First letter is based upon sector, thus "A" designates this residence is in sector A.

The number immediately following the first letter designates the distance (in miles) from the reactor.

The characters following the dash represent a unique identifier based upon location address.

The example is in sector A, 1.4 miles from the reactor, at 1525 16th Road.

2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 12

TABLE 3 2011 Land Use Census Milk and Garden Data SECTOR 2010 2011 2010 CLOSEST 2011 CLOSEST MILKING MILKING GARDEN GARDEN ANIMALS ANIMALS PRODUCING PRODUCING BROADLEAF BROADLEAF VEGETATION VEGETATION A None None None A4.91-OXRD1940 B None None None None C None None C4.89-18RD1859 C4.63-RERD1825 D None None D3.00-16RD1829 D2.41-RERD1541 E None None None None F None None F2.44-RERD1391 F2.39-14RD1802 G None None G3.77-12RD1831 G3.77-12RD1831 H None None H3.30-QURD 1175 H3.30-QURD 1175 J None None J3.90-11RD1531 J4.00-PLRD1080 K None None None K4.10-NARD1120 L None None L2.39-NARD1309 None M None None M3.10-13LA1290 M3.10-13LA1290 N None None N2.38-RODR9 N2.38-RODR9 P None None P2.76-HW751534 P2.76-HW751534 Q None None Q2.35-MILA1619 Q2.35-MILA1619 R None None None R2.08-NALN1650 NOTE: Underlined entries indicate changes from the 2010 Land Use Census.

Locations are identified based upon the following protocol:

EXAMPLE: A1.4-16RD1525 First letter is based upon sector, thus "A" designates this residence is in sector A.

The number immediately following the first letter designates the distance (in miles) from the reactor.

The characters following the dash represent a unique identifier based upon location address.

The example is in sector A, 1.4 miles from the reactor, at 1525 16th Road.

2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 13

TABLE 4 Information Used for D/Q Calculations FROM LAND FROM USE CENSUS SA-10-004 Eval.

DIST CALC NEAR NEAR FAR FAR SECTOR SECTOR (MI) (METERS) DIST D/Q DIST D /Q CALC RANKING A 4.91 7902 7000 6.53E-10 8000 5.27E-10 5.39E-10 6 C 4.63 7451 7000 1.66E-10 8000 1.34E-10 1.52E-10 13 D 2.41 3879 3000 4.46E-10 4000 2.67E-10 2.89E-10 12 E

F 2.39 3846 3000 7.22E-10 4000 4.33E-10 4.78E-10 7 G 3.77 6067 6000 3.57E-10 7000 2.65E-10 3.51E-10 10 H 3.30 5311 5000 7.01E-10 6000 5.16E-10 6.43E-10 4 J 4.00 6437 6000 4.33E-10 7000 3.22E-10 3.84E-10 9 K 4.10 6598 6000 3.82E-10 7000 2.84E-10 3.23E-10 11 L

M 3.10 4989 4000 5.73E-10 5000 3.90E-10 3.92E-10 8 N 2.38 3830 3000 1.25E-09 4000 7.51E-10 8.36E-10 3 P 2.76 4442 4000 6.88E-10 5000 4.68E-10 5.91E-10 5 Q 2.35 3782 3000 1.53E-09 4000 9.17E-10 1.05E-09 2 R 2.08 3347 3000 2.61E-09 4000 1.57E-09 2.25E-09 1 Originated by: Date: 11/03/11 Verified by: Date: 11/3/11 2011 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page D - 14

Enclosure to Letter RA 12-0053 Corrected pages from 2009 and 2010 reports (3 pages)

A. Airborne Pathway Low volume air sampling pumps with digital flow meters continuously collected particulate and radioiodine samples on 47 mm glass fiber filters and charcoal canisters, respectively. The filters and charcoal canisters were changed out weekly, labeled, and shipped to Environmental, Inc. for analyses.

Gross beta analyses of the air particulate filters were performed after a nominal 72-hour period to allow the radon and thoron daughter products to decay.

Weekly air particulate filters were combined into quarterly composites for each location and analyzed for gamma emitting isotopes.

Charcoal canisters were routinely counted to determine the presence or absence of 1-131.

Positive indication of 1-131 would have resulted in analysis of each individual charcoal canister.

Air samples were collected from six locations. Indicator locations 2, 37 and 18 are located in the three sectors with the highest ground level deposition constants (D/Q). Air sampling stations are also located in the community of New Strawn (indicator location 32) and a control location near the intersection of 20th Road and Yearling Road (location 53). Supplemental indicator location (location 49) was also sampled during the year. Indicator locations are shown in Figure 1 and the control location is shown in Figure 5.

B. Direct Radiation Pathway Optically stimulated luminescence (OSL) dosimeters were used at 44 locations during the sample year to measure direct radiation. The OSLs were typically positioned roughly 3 to 4 feet above the ground in plastic thermostat boxes. Two OSLs were placed at each designated location. The OSLs were changed out quarterly. Transit dose was measured and subtracted from the ambient dose. Indicator OSL sample locations are illustrated in Figure 2 and control locations are shown in Figure 5. Control locations were 39 (Beto Junction), 48 (Harris) and 53 (near the intersection of 2 0 th Road and Yearling Road).

C. Waterborne Pathway All water samples were analyzed to determine whether gamma emitters were present. In addition to gamma isotopic analysis, radiochemical analysis for 1-131 was performed on drinking water and ground water samples. Gross beta analysis was also performed on drinking water samples. Tritium analysis was performed monthly by liquid scintillation for surface water and quarterly for drinking water. Tritium analysis was also performed on ground water samples. Water sampling locations are shown in Figures 3 and 5.

Monthly grab samples of surface water were collected from John Redmond Reservoir (JRR) as a control location and from the "SP" location, which is located near the spillway of Coffey County Lake, formerly known as Wolf Creek Lake, as an indicator location.

Quarterly grab samples of ground water were collected from seven wells. Location B-12 is hydrologically up gradient from the site and was used as a control location. Six locations (C-10, C-49, F-1, G-2, J-1 and J-2) are hydrologically down gradient from the site and were used as indicator sample locations.

2009 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 2 of 32

A. Airborne Pathway Low volume air sampling pumps with digital flow meters continuously collected particulate and radioiodine samples on 47 mm glass fiber filters and charcoal canisters, respectively. The filters and charcoal canisters were changed out weekly, labeled, and shipped to Environmental, Inc. for analyses.

Gross beta analyses of the air particulate filters were performed after a nominal 72-hour period to allow the radon and thoron daughter products to decay.

Weekly air particulate filters were combined into quarterly composites for each location and analyzed for gamma emitting isotopes.

Charcoal canisters were routinely counted to determine the presence or absence of 1-131.

Positive indication of 1-131 would have resulted in analysis of each individual charcoal canister.

Air samples were collected from six locations. Indicator locations 2, 37, and 18 are located in the three sectors with the highest ground level deposition constants (D/Q). Air sampling stations are also located in the community of New Strawn (indicator location 32) and a control location near the intersection of 2 0 th Road and Yearling Road (location 53). Supplemental indicator location (location 49) was also sampled during the year. Indicator locations are shown in Figure 1 and the control location is shown in Figure 5.

B. Direct Radiation Pathway Optically stimulated luminescence (OSL) dosimeters were used at 44 locations during the sample year to measure direct radiation. The OSLs were typically positioned roughly 3 to 4 feet above the ground in plastic thermostat boxes. Two OSLs were placed at each designated location. The OSLs were changed out quarterly. Transit dose was measured and subtracted from the ambient dose. Indicator OSL sample locations are illustrated in Figure 2 and control locations are shown in Figure 5. Control locations were 39 (Beto Junction), 48 (Harris) and 53 (near the intersection of 2 0 th Road and Yearling Road).

C. Waterborne Pathway All water samples were analyzed to determine whether gamma emitters were present. In addition to gamma isotopic analysis, radiochemical analysis for 1-131 was performed on drinking water and ground water samples. Gross beta analysis was also performed on drinking water samples. Tritium analysis was performed monthly by liquid scintillation for surface water and quarterly for drinking water. Tritium analysis was also performed on ground water samples. One surface water sample from the SP location was also analyzed for Fe-55. Water sampling locations are shown in Figures 3 and 5.

Monthly grab samples of surface water were collected from John Redmond Reservoir (JRR) as a control location and from the "SP" location, which is located near the spillway of Coffey County Lake, formerly known as Wolf Creek Lake, as an indicator location.

2010 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 2 of 32

TABLE 2 (Cont.)

SAMPLE LOCATION IDENTIFIERS, DISTANCES (Miles) AND DIRECTIONS (Sectors)

Sample Type Location Distance from Direction Sector Identifier Reactor Dosimeters 46 1.6 WNW P 47 0.16 S J 48 14.7 ENE D 49 0.8 NNE B 50 3.6 ENE D 51 4.0 S J 52 3.6 SW L 53 10.8 ENE D Surface Water JRR 3.7 W N SP 3.2 SSE H Ground Water B-12 1.9 NNE B C-10 2.7 W N C-49/L-49 2.8 SW L F-1 2.5 ESE F G-2 3.6 SE G J-1 3.8 S J J-2 4.3 S J Drinking Water BW-15 3.9 SW L 1O-DW 26.1 SSE H Shoreline Sediment DC 0.8 WNW P EEA 3.0 NNW R JRR 3.6 W N Fish CCL 0.6 E to NNW E to R JRR 3.7 W N Food/Garden D-2 14.8 ENE D H-2 3.0 SSE H N-1 2.4 W N Q-6 2.4 NW Q Crops NR-D1 8.9 S J NR-D2 11.5 S J NR-U1 4.0 SSW K Bottom Sediment DC 0.9 WNW P JRR 3.7 W N MUDS 1.5 WNW P UHS 0.6 E E Aquatic Vegetation DC ALT 1.5 NW Q EEA 3.0 NNW R Soil EEA 3.0 NNW R MUDS 1.5 WNW P Meat (Alligator) CCL 1.5 WNW P Meat (Deer) R2.5 2.5 NNW R 2010 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 18 of 32