SVPLTR 09-0020, Submittal of 2008 Annual Radiological Environmental Operating Report: Difference between revisions
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{{#Wiki_filter: | {{#Wiki_filter:Exelon Generation Company, LLC Dresden Nuclear Power Station www.exeloncorp.com Exel rn NuCeaT 650o North Dresden Road Morris, IL60450-9765 May 08, 2009 SVPLTR # 09-0020 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 1, 2, and 3 Facility Operating License No. DPR-2 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-010, 50-237, and 50-249 | ||
==Subject:== | ==Subject:== | ||
Dresden Nuclear Power Station 2008 Annual Radiological Environmental Operating Report Enclosed is the Exelon Dresden Nuclear Power Station 2008 Annual Radiological Environmental Operating Report, submitted in accordance with Section 6.9.A.3 of the Unit 1 Dresden Nuclear Power Station Technical Specifications and Section 5.6.2, "Annual Radiological Environmental Operating Report," of the Units 2 and 3 Technical Specifications. | Dresden Nuclear Power Station 2008 Annual Radiological Environmental Operating Report Enclosed is the Exelon Dresden Nuclear Power Station 2008 Annual Radiological Environmental Operating Report, submitted in accordance with Section 6.9.A.3 of the Unit 1 Dresden Nuclear Power Station Technical Specifications and Section 5.6.2, "Annual Radiological Environmental Operating Report," of the Units 2 and 3 Technical Specifications. | ||
This report provides the results of the radiological environmental and meteorological monitoring programs for the 2008 calendar year.In addition, Appendix F of the report contains the results of groundwater monitoring conducted in accordance with Exelon's Radiological Groundwater Protection Program, which is a voluntary program implemented in 2006. This information is being reported in accordance with a nuclear industry initiative. | This report provides the results of the radiological environmental and meteorological monitoring programs for the 2008 calendar year. | ||
Should you have any questions concerning this letter, please contact Stephen Taylor, Regulatory Assurance Manager, at (815) 416-2800.Respectfully, Tim Hanley Site Vice President Dresden Nuclear Power Station Attachment | In addition, Appendix F of the report contains the results of groundwater monitoring conducted in accordance with Exelon's Radiological Groundwater Protection Program, which is a voluntary program implemented in 2006. This information is being reported in accordance with a nuclear industry initiative. | ||
-Annual Radiological Environmental Operating Report cc: Regional Administrator | Should you have any questions concerning this letter, please contact Stephen Taylor, Regulatory Assurance Manager, at (815) 416-2800. | ||
-NRC Region III NRC Senior Resident -Dresden Nuclear Power Station Docket No: 50-010 50-237 50-249 DRESDEN NUCLEAR POWER STATION UNITS 1, 2 and 3 Annual Radiological Environmental Operating Report 1 January Through 31 December 2008 Prepared By Teledyne Brown Engineering Environmental Services Nuclear Dresden Nuclear Power Station Morris, IL 60450 May 2009 Table Of Contents I. Sum m ary and Conclusions | Respectfully, Tim Hanley Site Vice President Dresden Nuclear Power Station Attachment - Annual Radiological Environmental Operating Report cc: Regional Administrator - NRC Region III NRC Senior Resident - Dresden Nuclear Power Station | ||
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1 II. | Docket No: 50-010 50-237 50-249 DRESDEN NUCLEAR POWER STATION UNITS 1, 2 and 3 Annual Radiological Environmental Operating Report 1 January Through 31 December 2008 Prepared By Teledyne Brown Engineering Environmental Services Nuclear Dresden Nuclear Power Station Morris, IL 60450 May 2009 | ||
3 A. Objectives of the REM P ................................................................................... | |||
3 B. Im plem entation of the O bjectives | Table Of Contents I. Sum m ary and Conclusions ........................................................................................... 1 II. Intro d u ctio n ........................................................................................................................ 3 A. Objectives of the REM P ................................................................................... 3 B. Im plem entation of the O bjectives ..................................................................... 3 III. Program Description ..................................................................................................... 4 A. Sam ple Collection ............................................................................................. 4 B. Sam ple Analysis ................................................................................................ 5 C . Data Interpretation ........................................................................................... 6 D. Program Exceptions ........................................................................................ 7 E. Program Changes ............................................................................................. 8 IV. Results and Discussion ............................................................................................... 8 A. Aquatic Environm ent ........................................................................................ 8 | ||
..................................................................... | : 1. Surface W ater ......................................................................................... 8 | ||
3 III. Program Description | : 2. G round W ater ......................................................................................... 9 | ||
..................................................................................................... | : 3. Fish ......................................................................................................... 9 | ||
4 A. Sam ple Collection | : 4. Sedim ent .............................................................................................. 10 B. Atm ospheric Environm ent ............................................................................... 10 | ||
............................................................................................. | : 1. Airborne ............................................................................................... 10 | ||
4 B. Sam ple Analysis ................................................................................................ | : a. Air Particulates .......................................................................... 10 | ||
5 C .Data Interpretation | : b. Airborne Iodine .......................................................................... 11 | ||
........................................................................................... | : 2. Terrestrial ............................................................................................. 12 | ||
6 D. Program Exceptions | : a. Milk ............................... ......... 12 | ||
........................................................................................ | : b. Food Products ...................................... 12 C. Am bient Gam m a Radiation ............................................................................. 12 D. Land Use Survey ........................................................................................... 13 E. Errata Data .................................................................................................... 13 F. Summary of Results - Inter-laboratory Comparison Program ....................... 13 | ||
7 E. Program Changes ............................................................................................. | |||
8 IV. Results and Discussion | Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Dresden Nuclear Power Station, 2008 Appendix B Location Designation, Distance & Direction, and Sample Collection & | ||
............................................................................................... | Analytical Methods Tables Table B-I: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2008 Table B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2008 Figures Figure B-1: Dresden Station Inner Ring TLD Locations, Fish, Water, and Sediment Locations, 2008 Figure B-2: Dresden Station Fixed Air Sampling and TLD Sites, Outer Ring TLD Locations and Milk Location, 2008 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-1.1 Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008. | ||
8 A. Aquatic Environm ent ........................................................................................ | Table C-1.2 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008. | ||
Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008. | |||
Table C-I1.1 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008. | |||
ii | |||
10 B. Atm ospheric Environm ent ............................................................................... | Table C-11.2 Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008. | ||
Table C-111.1 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008. | |||
Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008. | |||
.......................................................................... | Table C-V. 1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008. | ||
Table C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu meter) in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008. | |||
Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008. | |||
............................................................................................. | Table C-VI.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008. | ||
Table C-VII.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008. | |||
......... | Table C-VII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008. | ||
Table C-VIII.1 Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008. | |||
12 C. Am bient | Table C-IX.1 Quarterly TLD Results for Dresden Nuclear Power Station, 2008. | ||
............................................................................. | Table C-IX.2 Mean Quarterly TLD Results for the Inner Ring, Outer Ring, Other and Control Locations for Dresden Nuclear Power Station, 2008. | ||
12 D. Land Use Survey ........................................................................................... | Table C-IX.3 Summary of the Ambient Dosimetry Program for Dresden Nuclear Power Station, 2008. | ||
13 E. Errata Data .................................................................................................... | Figures Figure C-1 Surface Water - Gross Beta - Stations D-51 and D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2008. | ||
13 F. Summary of Results -Inter-laboratory Comparison Program ....................... | Figure C-2 Surface Water - Gross Beta - Stations D-54 (C) and D-57 (C) | ||
Collected in the Vicinity of DNPS, 2002 - 2008. | |||
Figure C-3 Surface Water - Gross Beta - Station D-21 Collected in the Vicinity of DNPS, 2007 - 2008. | |||
-Gross Beta -Stations D- | Figure C-4 Surface Water - Tritium - Stations D-51 and D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2008. | ||
-Gross Beta -Stations D- | Figure C-5 Surface Water - Tritium - Station D-54 (C) and D-57 (C) Collected in the Vicinity of DNPS, 2002 - 2008. | ||
-Gross Beta -Stations D- | iii | ||
-Gross Beta -Stations D- | |||
Figure C-6 Surface Water - Tritium - Station D-21 Collected in the Vicinity of DNPS, 2007 - 2008. | |||
Figure C-7 Ground Water - Tritium - Stations D-23 and D-35 Collected in the Vicinity of DNPS, 2000 - 2008. | |||
Figure C-8 Air Particulate - Gross Beta - Stations D-01 and D-02 Collected in the Vicinity of DNPS, 2000 - 2008. | |||
Figure C-9 Air Particulate - Gross Beta - Stations D-03 and D-04 Collected in the Vicinity of DNPS, 2000 - 2008. | |||
Figure C-10 Air Particulate - Gross Beta - Stations D-07 and D-12 (C) Collected in the Vicinity of DNPS, 2000 - 2008. | |||
Figure C-11 Air Particulate - Gross Beta - Stations D-45 and D-53 Collected in the Vicinity of DNPS, 2000 - 2008. | |||
Figure C-12 Air Particulate - Gross Beta - Stations D-08 and D-10 Collected in the Vicinity of DNPS, 2005 - 2008. | |||
Figure C-13 Air Particulate - Gross Beta - Stations D-13 and D-14 Collected in the Vicinity of DNPS, 2005 - 2008. | |||
Figure C-14 Air Particulate - Gross Beta - Stations D-55 and D-56 Collected in the Vicinity of DNPS, 2006 - 2008. | |||
Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2008 Table D-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2008 Table D-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP) | |||
Teledyne Brown Engineering, 2008 Appendix E Errata Data Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv | |||
: 1. Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Dresden Nuclear Power Station (DNPS) by Exelon covers the period 1 January 2008 through 31 December 2008. During that time period, 1,786 analyses were performed on 1,650 samples. In assessing all the data gathered for this report it was concluded that the operation of DNPS had no adverse radiological impact on the environment. | : 1. Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Dresden Nuclear Power Station (DNPS) by Exelon covers the period 1 January 2008 through 31 December 2008. During that time period, 1,786 analyses were performed on 1,650 samples. In assessing all the data gathered for this report it was concluded that the operation of DNPS had no adverse radiological impact on the environment. | ||
Surface water samples were analyzed for concentrations of gross beta, tritium and gamma emitting nuclides. | Surface water samples were analyzed for concentrations of gross beta, tritium and gamma emitting nuclides. Ground water samples were analyzed for concentrations of tritium and gamma emitting nuclides. No anthropogenic gamma emitting nuclides were detected. Gross beta and tritium activities detected were consistent with those detected in previous years. | ||
Ground water samples were analyzed for concentrations of tritium and gamma emitting nuclides. | Fish (commercially and recreationally important species) and sediment samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected in fish. Sediment samples had Cesium-1 37 concentrations consistent with levels observed in previous years. No plant-produced fission or activation products were found in sediment. | ||
No anthropogenic gamma emitting nuclides were detected. | Air particulate samples were analyzed for concentrations of gross beta and gamma emitting nuclides. Gross beta results at the indicator locations were consistent with those at the control location. No fission or activation products were detected. | ||
Gross beta and tritium activities detected were consistent with those detected in previous years.Fish (commercially and recreationally important species) and sediment samples were analyzed for concentrations of gamma emitting nuclides. | High sensitivity 1-131 analyses were performed on weekly air samples. All results were less than the minimum detectable activity. | ||
No fission or activation products were detected in fish. Sediment samples had Cesium-1 37 concentrations consistent with levels observed in previous years. No plant-produced fission or activation products were found in sediment.Air particulate samples were analyzed for concentrations of gross beta and gamma emitting nuclides. | Cow milk samples were analyzed for concentrations of 1-131 and gamma emitting nuclides. All 1-131 results were below the minimum detectable activity. | ||
Gross beta results at the indicator locations were consistent with those at the control location. | Concentrations of naturally occurring K-40 were found. No fission or activation products were found. | ||
No fission or activation products were detected.High sensitivity 1-131 analyses were performed on weekly air samples. All results were less than the minimum detectable activity.Cow milk samples were analyzed for concentrations of 1-131 and gamma emitting nuclides. | Food product samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected. | ||
All 1-131 results were below the minimum detectable activity.Concentrations of naturally occurring K-40 were found. No fission or activation products were found.Food product samples were analyzed for concentrations of gamma emitting nuclides. | Environmental gamma radiation measurements were performed quarterly using thermoluminescent dosimeters. Levels detected were consistent with those observed in previous years. | ||
No fission or activation products were detected.Environmental gamma radiation measurements were performed quarterly using thermoluminescent dosimeters. | |||
Levels detected were consistent with those observed in previous years. | Intentionally left blank | ||
Intentionally left blank II. Introduction The Dresden Nuclear Power Station (DNPS), consisting of one retired reactor and two operating 912 MWe boiling water reactors owned and operated by Exelon Corporation, is located in Grundy County, Illinois. | |||
Unit No. 1 went critical in 1960 and was retired in 1978. Unit No. 2 went critical on 16 June 1970. Unit No. 3 went critical on 02 November 1971. The site is located in northern Illinois, approximately 12 miles southwest of Joliet, Illinois at the confluence of the Des Plaines and Kankakee Rivers where they form the Illinois River.This report covers those analyses performed by Teledyne Brown Engineering (TBE) Global Dosimetry, and Environmental Inc. Midwest Laboratory (EIML) on samples collected during the period 1 January 2008 through 31 December 2008.An assessment of the station's radioactive effluent monitoring results and radiation dose via the principle pathways of exposure resulting from plant emissions of radioactivity including the maximum noble gas gamma and beta air doses in the unrestricted area, an annual summary of meteorological conditions including wind speed, wind direction, and atmospheric stability, and the result of the 40CFR190 uranium fuel cycle dose analysis for the calendar year are published in the station's Annual Radioactive Effluent Release Report.A. Objective of the Radiological Environmental Monitoring Program (REMP)The objectives of the REMP are to: 1. Provide data on measurable levels of radiation and radioactive materials in the site environs.2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.B. Implementation of the Objectives The implementation of the objectives is accomplished by: 1. Identifying significant exposure pathways.2. Establishing baseline radiological data of media within those pathways.3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment. | II. Introduction The Dresden Nuclear Power Station (DNPS), consisting of one retired reactor and two operating 912 MWe boiling water reactors owned and operated by Exelon Corporation, is located in Grundy County, Illinois. Unit No. 1 went critical in 1960 and was retired in 1978. Unit No. 2 went critical on 16 June 1970. Unit No. 3 went critical on 02 November 1971. The site is located in northern Illinois, approximately 12 miles southwest of Joliet, Illinois at the confluence of the Des Plaines and Kankakee Rivers where they form the Illinois River. | ||
Ill. Program Description A. Sample Collection Samples for the DNPS REMP were collected for Exelon Nuclear by EIML.This section describes the general collection methods used by EIML to obtain environmental samples for the DNPS REMP in 2008. Sample locations and descriptions can be found in Table B-1 and Figures B-1 and B-2, Appendix B. The collection methods used by EIML are listed in Table B-2.Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, ground water, fish, and sediment.Samples were collected from three surface water locations (D-21, D-52 and D-57) and composited for analysis. | This report covers those analyses performed by Teledyne Brown Engineering (TBE) Global Dosimetry, and Environmental Inc. Midwest Laboratory (EIML) on samples collected during the period 1 January 2008 through 31 December 2008. | ||
Control locations were D-52 and D-57. Samples were collected quarterly or more frequently from two well water locations (D-23 and D-35). All samples were collected in new unused plastic bottles, which were rinsed with source water prior to collection. | An assessment of the station's radioactive effluent monitoring results and radiation dose via the principle pathways of exposure resulting from plant emissions of radioactivity including the maximum noble gas gamma and beta air doses in the unrestricted area, an annual summary of meteorological conditions including wind speed, wind direction, and atmospheric stability, and the result of the 40CFR190 uranium fuel cycle dose analysis for the calendar year are published in the station's Annual Radioactive Effluent Release Report. | ||
Fish samples comprising the flesh of channel catfish, largemouth bass, common carp and freshwater drum were collected semiannually at two locations, D-28 and D-46 (Control). | A. Objective of the Radiological Environmental Monitoring Program (REMP) | ||
Sediment samples composed of recently deposited substrate were collected at one location semiannually, D-27.Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, milk, and food products. | The objectives of the REMP are to: | ||
Airborne iodine and particulate samples were collected at thirteen locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-12, D-14, D-45, D-53, D-55 and D-56). The control location was D-12. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. | : 1. Provide data on measurable levels of radiation and radioactive materials in the site environs. | ||
The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The air filters and air iodine samples were replaced weekly and sent to the laboratory for analysis.Milk samples were collected biweekly at one control location (D-25) from May through October, and monthly from November through April. There are no milking animals within 10 km of the site. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite, and shipped promptly to the laboratory. | : 2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure. | ||
Food products were collected annually in September at five locations (D-Control, D-Quad 1, D-Quad 2, D-Quad 3, and D-Quad 4). The control location was D-Control. | B. Implementation of the Objectives The implementation of the objectives is accomplished by: | ||
Various types of samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.Ambient Gamma Radiation Direct radiation measurements were made using CaF 2 and LiF thermoluminescent dosimeters (TLD). Each location consisted of 2 TLD sets. The TLD locations were placed on and around the DNPS site as follows: An inner ring consisting of 16 locations (D-101, D-102, D-103, D-104, D-105, D-106, D-107, D-108, D-109, D-110, D-111, D-112A, D-113, D-114, D-115 and D-116) at or near the site boundary.An outer ring consisting of 16 locations (D-201, D-202, D-203, D-204, D-205, D-206, D-207, D-208, D-209, D-210, D-211, D-212, D-213, D-214, D-215 and D-216) approximately 5 to 10 km from the site.An other set consisting of TLDs at the 12 air sampler locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-14, D-45, D-53, D-55, and D-56).The balance of one location (D-12) representing the control area.Two TLDs -each comprised of two CaF 2 and two LiF thermoluminescent phosphors enclosed in plastic -were placed at each location. | : 1. Identifying significant exposure pathways. | ||
The TLDs were exchanged quarterly and sent to Global Dosimetry for analysis.B. Sample Analysis This section describes the general analytical methodologies used by TBE and EIML to analyze the environmental samples for radioactivity for the DNPS REMP in 2008. The analytical procedures used by the laboratories are listed in Table B-2.In order to achieve the stated objectives, the current program includes the following analyses: 1. Concentrations of beta emitters in surface water and air particulates. | : 2. Establishing baseline radiological data of media within those pathways. | ||
: 2. Concentrations of gamma emitters in ground and surface water, air particulates, milk, fish, sediment and vegetation. | : 3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment. | ||
Ill. Program Description A. Sample Collection Samples for the DNPS REMP were collected for Exelon Nuclear by EIML. | |||
This section describes the general collection methods used by EIML to obtain environmental samples for the DNPS REMP in 2008. Sample locations and descriptions can be found in Table B-1 and Figures B-1 and B-2, Appendix B. The collection methods used by EIML are listed in Table B-2. | |||
Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, ground water, fish, and sediment. | |||
Samples were collected from three surface water locations (D-21, D-52 and D-57) and composited for analysis. Control locations were D-52 and D-57. Samples were collected quarterly or more frequently from two well water locations (D-23 and D-35). All samples were collected in new unused plastic bottles, which were rinsed with source water prior to collection. Fish samples comprising the flesh of channel catfish, largemouth bass, common carp and freshwater drum were collected semiannually at two locations, D-28 and D-46 (Control). Sediment samples composed of recently deposited substrate were collected at one location semiannually, D-27. | |||
Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, milk, and food products. Airborne iodine and particulate samples were collected at thirteen locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-12, D-14, D-45, D-53, D-55 and D-56). The control location was D-12. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The air filters and air iodine samples were replaced weekly and sent to the laboratory for analysis. | |||
Milk samples were collected biweekly at one control location (D-25) from May through October, and monthly from November through April. There are no milking animals within 10 km of the site. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite, and shipped promptly to the laboratory. | |||
Food products were collected annually in September at five locations (D-Control, D-Quad 1, D-Quad 2, D-Quad 3, and D-Quad 4). The control location was D-Control. Various types of samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis. | |||
Ambient Gamma Radiation Direct radiation measurements were made using CaF 2 and LiF thermoluminescent dosimeters (TLD). Each location consisted of 2 TLD sets. The TLD locations were placed on and around the DNPS site as follows: | |||
An inner ring consisting of 16 locations (D-101, D-102, D-103, D-104, D-105, D-106, D-107, D-108, D-109, D-110, D-111, D-112A, D-113, D-114, D-115 and D-116) at or near the site boundary. | |||
An outer ring consisting of 16 locations (D-201, D-202, D-203, D-204, D-205, D-206, D-207, D-208, D-209, D-210, D-211, D-212, D-213, D-214, D-215 and D-216) approximately 5 to 10 km from the site. | |||
An other set consisting of TLDs at the 12 air sampler locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-14, D-45, D-53, D-55, and D-56). | |||
The balance of one location (D-12) representing the control area. | |||
Two TLDs - each comprised of two CaF 2 and two LiF thermoluminescent phosphors enclosed in plastic - were placed at each location. The TLDs were exchanged quarterly and sent to Global Dosimetry for analysis. | |||
B. Sample Analysis This section describes the general analytical methodologies used by TBE and EIML to analyze the environmental samples for radioactivity for the DNPS REMP in 2008. The analytical procedures used by the laboratories are listed in Table B-2. | |||
In order to achieve the stated objectives, the current program includes the following analyses: | |||
: 1. Concentrations of beta emitters in surface water and air particulates. | |||
: 2. Concentrations of gamma emitters in ground and surface water, air particulates, milk, fish, sediment and vegetation. | |||
5- | 5- | ||
: 3. Concentrations of tritium in ground and surface water.4. Concentrations of 1-131 in air and milk.5. Ambient gamma radiation levels at various site environs.C. Data Interpretation For the purpose of this report, Dresden Nuclear Power Station was considered operational at initial criticality. | : 3. Concentrations of tritium in ground and surface water. | ||
In addition, data were compared to previous years' operational data for consistency and trending. | : 4. Concentrations of 1-131 in air and milk. | ||
Several factors were important in the interpretation of the data: 1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) was defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD was intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity. | : 5. Ambient gamma radiation levels at various site environs. | ||
All analyses were designed to achieve the required DNPS detection capabilities for environmental sample analysis.The minimum detectable concentration (MDC) is calculated the same as the LLD with the exception that the measurement is an after the fact estimate of the presence of activity.2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. | C. Data Interpretation For the purpose of this report, Dresden Nuclear Power Station was considered operational at initial criticality. In addition, data were compared to previous years' operational data for consistency and trending. Several factors were important in the interpretation of the data: | ||
Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity effecting a negative number. An MDC was reported in all cases where positive activity was not detected.Gamma spectroscopy results for each type of sample were grouped as follows: For ground and surface water and vegetation 12 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, 1-131, Cs-134, Cs-137, Ba-140, and La-140 were reported.For fish, sediment, dredge spoil, air particulate and milk 11 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140 and La-140 were reported.Means and standard deviations of the results were calculated. | : 1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) was defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD was intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity. All analyses were designed to achieve the required DNPS detection capabilities for environmental sample analysis. | ||
The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty. | The minimum detectable concentration (MDC) is calculated the same as the LLD with the exception that the measurement is an after the fact estimate of the presence of activity. | ||
D. Program Exceptions For 2008 the DNPS REMP had a sample recovery rate in excess of 99%.Sample anomalies and missed samples are listed in the tables below: Table D-1 LISTING OF SAMPLE ANOMALIES Sample Location Collection Reason Type Code Date AP/I D-01 | : 2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity effecting a negative number. An MDC was reported in all cases where positive activity was not detected. | ||
Flow rate was estimated at 60 cfh.Low timer reading of 127.1 hours due to loss of power to the sampler.Low timer reading of 166.1 hours due to recent power restoration. | Gamma spectroscopy results for each type of sample were grouped as follows: | ||
Low timer reading of 139.0 hours due to power outage.Low timer reading of 166.6 hours;cause is unknown.Low timer reading of 159.8 hours due to power outage.Low timer reading of 89.6; cause is unknown.Low timer reading of 164.6 hours due to area power outage.Grab samples taken due to no compositor pump flow.Grab samples taken due to no compositor pump flow. | For ground and surface water and vegetation 12 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, 1-131, Cs-134, Cs-137, Ba-140, and La-140 were reported. | ||
Table D-1 LISTING OF SAMPLE ANOMALIES (continued) | For fish, sediment, dredge spoil, air particulate and milk 11 | ||
Sample Location Collection Reason Type Code Date AP/I D-55 11/28/08 -12/05/08 Low timer reading of 155.5 hours due to area power outage.AP/l D-56 02/08/08 -02/15/08 Low timer reading of 157.8 hours;cause is unknown.Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason Type Code Date There were no missed samples for 2008.Each program exception was reviewed to understand the causes of the program exception. | |||
Sampling and maintenance errors were reviewed with the personnel involved to prevent recurrence. | nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140 and La-140 were reported. | ||
Occasional equipment breakdowns and power outages were unavoidable. | Means and standard deviations of the results were calculated. The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty. | ||
D. Program Exceptions For 2008 the DNPS REMP had a sample recovery rate in excess of 99%. | |||
Sample anomalies and missed samples are listed in the tables below: | |||
Table D-1 LISTING OF SAMPLE ANOMALIES Sample Location Collection Reason Type Code Date AP/I D-01 01/25/08 - 02/01/08 Foreign substance was found on the flow indicator. Flow rate was estimated at 60 cfh. | |||
AP/I D-01 05/16/08 - 05/23/08 Low timer reading of 127.1 hours due to loss of power to the sampler. | |||
AP/I D-01 05/23/08 - 05/30/08 Low timer reading of 166.1 hours due to recent power restoration. | |||
AP/I D-01 12/19/08 - 12/26/08 Low timer reading of 139.0 hours due to power outage. | |||
AP/I D-02 09/19/08 - 09/26/08 Low timer reading of 166.6 hours; cause is unknown. | |||
AP/I D-02 12/19/08 - 12/26/08 Low timer reading of 159.8 hours due to power outage. | |||
AP/I D-03 07/18/08 - 07/25/08 Low timer reading of 89.6; cause is unknown. | |||
AP/I D-10 11/28/08 - 12/05/08 Low timer reading of 164.6 hours due to area power outage. | |||
SW D-21 01/25/08 - 02/29/08 Grab samples taken due to no compositor pump flow. | |||
SW D-21 02/29/08 - 03/28/08 Grab samples taken due to no compositor pump flow. | |||
Table D-1 LISTING OF SAMPLE ANOMALIES (continued) | |||
Sample Location Collection Reason Type Code Date AP/I D-55 11/28/08 - 12/05/08 Low timer reading of 155.5 hours due to area power outage. | |||
AP/l D-56 02/08/08 - 02/15/08 Low timer reading of 157.8 hours; cause is unknown. | |||
Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason Type Code Date There were no missed samples for 2008. | |||
Each program exception was reviewed to understand the causes of the program exception. Sampling and maintenance errors were reviewed with the personnel involved to prevent recurrence. Occasional equipment breakdowns and power outages were unavoidable. | |||
The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation. | The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation. | ||
E. Program Changes There were no program changes for 2008.IV. Results and Discussion A. Aquatic Environment | E. Program Changes There were no program changes for 2008. | ||
: 1. Surface Water Samples were taken weekly and composited for analysis at three locations (D-21, D-52, and D-57). Of these locations only D-21 located downstream, could be affected by Dresden's effluent releases. | IV. Results and Discussion A. Aquatic Environment | ||
: 1. Surface Water Samples were taken weekly and composited for analysis at three locations (D-21, D-52, and D-57). Of these locations only D-21 located downstream, could be affected by Dresden's effluent releases. The following analyses were performed: | |||
Gross Beta Monthly composites from all locations were analyzed for | |||
concentrations of gross beta (Table C-1.1, Appendix C). The values ranged from 3.2 to 19.8 pCi/l. Concentrations detected were consistent with those detected in previous years (Figures C-1, C-2, and C-3, Appendix C). | |||
Tritium Quarterly composites from all locations were analyzed for tritium activity (Table C-1.2, Appendix C). The indicator values ranged from192 to 716 pCi/L. Control values ranged from 890 to 6440 pCi/L. Concentrations detected were consistent with those detected in previous years (Figures C-4, C-5, and C-6, Appendix C). | |||
Gamma Spectrometry Monthly composites from all locations were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). No nuclides were detected, and all required LLDs were met. | |||
: 2. Ground Water Quarterly or more frequent grab samples were collected at two locations (D-23 and D-35). These locations could be affected by Dresden's effluent releases and by sources upstream on the Kankakee River. The following analyses were performed: | |||
Tritium All samples were analyzed for tritium activity (Table C-11.1, Appendix C). D-35 values ranged from <155 to <175 pCi/L. D-23 values ranged from 207 to 525 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-7, Appendix C). | |||
Gamma Spectrometry All samples were analyzed for gamma emitting nuclides (Table C-11.2, Appendix C). No nuclides were detected, and all required LLDs were met. | |||
: 3. Fish Fish samples comprised of channel catfish, largemouth bass, common carp and freshwater drum were collected at two locations | |||
(D-28 and D-46) semiannually. Location D-28 could be affected by Dresden's effluent releases. The following analysis was performed: | |||
Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma emitting nuclides (Table C-lI1.1, Appendix C). | |||
Naturally occurring K-40 was found at all stations and ranged from 2,700 to 3,850 pCi/kg wet. No fission or activation products were detected. | |||
: 4. Sediment Aquatic sediment samples were collected at one location (D-27) semiannually. This downstream location could be affected by Dresden's effluent releases. The following analysis was performed: | |||
Gamma Spectrometry Sediment samples from the location were analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C). Cesium-137 was detected in one sample. | |||
Concentrations of the fission product Cs-1 37 was found in one sample at a concentration of 158 pCi/kg dry. The activity detected was consistent with those detected in previous years and is likely due to fallout from above-ground nuclear weapons testing. No other fission or activation products were detected. | |||
: 5. Dredging Spoils According to the U.S. Army Corps of Engineers in July 2008, no dredging was performed within one mile of Dresden Station in the past year. Therefore, no sampling of dredging spoils was performed. | |||
B. Atmospheric Environment | |||
: 1. Airborne | |||
: a. Air Particulates Continuous air particulate samples were collected from 13 locations on a weekly basis. The 13 locations were separated into four groups: On-site samplers (D-01, D-02, | |||
D-03), Near-field samplers within 4 km of the site (D-04, D-07, D-45, D-53 and D-56), Far-field samplers between 4 and 10 km from the site (D-08, D-10, D-14 and D-55) and the Control sampler between 10 and 30 km from the site (D-12). | |||
The following analyses were performed: | The following analyses were performed: | ||
Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-V.1 and C-V.2, Appendix C). | |||
Detectable gross beta activity was observed at all locations. | |||
Comparison of results among the four groups aid in determining the effects, if any, resulting from the operation of DNPS. The results from the On-Site locations ranged from 6 to 39 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3 . The results from the Near-Field locations ranged from 5 to 48 E-3 pCi/m 3 with a mean of 20 E-3 pCi/m 3 . The results from the Far-Field locations ranyed from <4 to 53 E-3 pCi/m 3 with a mean of 20 E-3 pCi/m . The results from the Control location ranged from 9 to 47 E-3 pCi/m 3 with a mean of 21 E-3 pCi/m 3 . Comparison of the 2008 air particulate data with previous years data indicate no effects from the operation of DNPS. In addition a comparison of the weekly mean values for 2008 indicate no notable differences among the four groups (Figures C-8 through C-14, Appendix C). | |||
Gamma Spectrometry Samples were composited quarterly and analyzed for gamma emitting nuclides (Table C-V.3, Appendix C). | |||
Naturally occurring Be-7 due to cosmic ray activity was detected in 47 of 52 samples and ranged from 43.7 to 123 E-3 pCi/m 3. K-40 was also detected in 4 samples and ranged from 26.4 to 33.3 E-3 pCi/ m3 . No anthropogenic nuclides were detected, and all required LLDs were met. | |||
: b. Airborne Iodine Continuous air samples were collected from 13 locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-12, D-14, D-45, D-53, D-55 and D-56) and analyzed weekly for 1-131 (Table C-VI.1, Appendix C). No nuclides were detected, and all required LLDs were met. | |||
Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-V.1 and C-V.2, Appendix C).Detectable gross beta activity was observed at all locations. | |||
Comparison of results among the four groups aid in determining the effects, if any, resulting from the operation of DNPS. The results from the On-Site locations ranged from 6 to 39 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3.The results from the Near-Field locations ranged from 5 to 48 E-3 pCi/m 3 with a mean of 20 E-3 pCi/m 3.The results from the Far-Field locations ranyed from <4 to 53 E-3 pCi/m 3 with a mean of 20 E-3 pCi/m .The results from the Control location ranged from 9 to 47 E-3 pCi/m 3 with a mean of 21 E-3 pCi/m 3.Comparison of the 2008 air particulate data with previous years data indicate no effects from the operation of DNPS. In addition a comparison of the weekly mean values for 2008 indicate no notable differences among the four groups (Figures C-8 through C-14, Appendix C).Gamma Spectrometry Samples were composited quarterly and analyzed for gamma emitting nuclides (Table C-V.3, Appendix C).Naturally occurring Be-7 due to cosmic ray activity was detected in 47 of 52 samples and ranged from 43.7 to 123 E-3 pCi/m 3.K-40 was also detected in 4 samples and ranged from 26.4 to 33.3 E-3 pCi/ | |||
: 2. Terrestrial | : 2. Terrestrial | ||
: a. Milk There are no indicator locations within 10 kilometers of the station. Samples were collected from one control location (D-25) biweekly May through October and monthly November through April. The following analyses were performed: | : a. Milk There are no indicator locations within 10 kilometers of the station. Samples were collected from one control location (D-25) biweekly May through October and monthly November through April. The following analyses were performed: | ||
Iodine-131 Milk samples from the location were analyzed for concentrations of 1-131 (Table.C-VIl.1, Appendix C). No nuclides were detected, and all required LLDs were met.Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-VII.2, Appendix C).Naturally occurring K-40 activity was found in all nineteen samples. The activities ranged from 1,090 to 1,340 pCi/I.No other nuclides were detected, and all required LLDs were met.b. Food Products Food product samples were collected at five locations (D-Control, D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4)when available. | Iodine-131 Milk samples from the location were analyzed for concentrations of 1-131 (Table.C-VIl.1, Appendix C). No nuclides were detected, and all required LLDs were met. | ||
Four locations, (D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4) could be affected by Dresden's effluent releases. | Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-VII.2, Appendix C). | ||
The following analysis was performed: | Naturally occurring K-40 activity was found in all nineteen samples. The activities ranged from 1,090 to 1,340 pCi/I. | ||
Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-VIII.1, Appendix C). No nuclides were detected, and all required LLDs were met.C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Global Dosimetry 110 Environmental (CaF 2 and LiF) thermoluminescent dosimeters. | No other nuclides were detected, and all required LLDs were met. | ||
Forty-five TLD locations were established around the site. Results of TLD measurements are listed in Tables C-IX.1 to C-IX.3, Appendix C. | : b. Food Products Food product samples were collected at five locations (D-Control, D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4) when available. Four locations, (D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4) could be affected by Dresden's effluent releases. The following analysis was performed: | ||
Most TLD measurements were below 30 mR/quarter, with a range of 16 to 33 mR/quarter. | Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-VIII.1, Appendix C). No nuclides were detected, and all required LLDs were met. | ||
A comparison of the Inner Ring, Outer Ring, and Other locations' data to the Control Location data, indicate that the ambient gamma radiation levels from the Control location (D-12-01, D-12-02) were comparable. | C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Global Dosimetry 110 Environmental (CaF 2 and LiF) thermoluminescent dosimeters. Forty-five TLD locations were established around the site. Results of TLD measurements are listed in Tables C-IX.1 to C-IX.3, Appendix C. | ||
D. Land Use Survey A Land Use Survey conducted on 20 August 2008 around the Dresden Nuclear Power Station (DNPS) was performed by EIML for Exelon Nuclear to comply with Section 12.6.2 of the Dresden Offsite Dose Calculation Manual (ODCM). The purpose of the survey was to document the nearest resident or industrial facility, milk producing animal, and livestock in each of the sixteen 22 1/2 degree sectors within 10 km around the site. There were no changes required to the DNPS REMP as a result of this survey.The results of this survey are summarized below.Distance in Miles from Sector Residence Miles AN 1.5 B NNE 0.8 CNE 0.8 D ENE 0.7 EE 1.1 F ESE 1.0 G SE 0.6 H SSE 0.5 JS 0.5 K SSW 3.3 L SW 3.6 | |||
The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.3. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values.The MAPEP defines three levels of performance: | Most TLD measurements were below 30 mR/quarter, with a range of 16 to 33 mR/quarter. A comparison of the Inner Ring, Outer Ring, and Other locations' data to the Control Location data, indicate that the ambient gamma radiation levels from the Control location (D-12-01, D-12-02) were comparable. | ||
Acceptable (flag ="A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value.Performance is acceptable with warning when a mean result falls in the range from +/-20% to +/-30% of the reference value (i.e., 20% <bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable. | D. Land Use Survey A Land Use Survey conducted on 20 August 2008 around the Dresden Nuclear Power Station (DNPS) was performed by EIML for Exelon Nuclear to comply with Section 12.6.2 of the Dresden Offsite Dose Calculation Manual (ODCM). The purpose of the survey was to document the nearest resident or industrial facility, milk producing animal, and livestock in each of the sixteen 22 1/2 degree sectors within 10 km around the site. There were no changes required to the DNPS REMP as a result of this survey. | ||
For the primary laboratory, 16 out of 18 analytes met the specified acceptance criteria. | The results of this survey are summarized below. | ||
Two samples did not meet the specified acceptance criteria for the following reasons: 1. Teledyne Brown Engineering's Analytics December 2008 Sr-89 in milk result of 18.0 pCi/L was higher than the known value of 12.6 pCi/L, resulting in a found to known ratio of 1.43. NCR 09-02 was initiated to investigate this failure. | Distance in Miles from the DNPS Reactor Buildings Sector Residence Livestock Milk Farm Miles Miles Miles AN 1.5 1.4 B NNE 0.8 6.0 CNE 0.8 5.8 D ENE 0.7 1.7 EE 1.1 F ESE 1.0 G SE 0.6 H SSE 0.5 JS 0.5 16.0 K SSW 3.3 L SW 3.6 11.4 MWSW 5.8 NW 3.5 0.5 P WNW 3.7 0.5 Q NW 2.6 0.5 R NNW 0.8 1.0 E. Errata Data There was no errata data discovered in 2008. | ||
: 2. Teledyne Brown Engineering's Analytics' ERA Quik Response water sample January 2008 Sr-89 result of 37.33 pCi/L exceeded the upper acceptance limit of 25.2 pCi/L. No cause could be found for the failure. Studies bracketing these results, RAD 71 and RAD 72 had acceptable Sr-89 results. NCR 08-03 For the secondary laboratory, all of the 15 analytes met the specified acceptance criteria.The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data. | F. Summary of Results - Inter-Laboratory Comparison Program The primary laboratory analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices | ||
(Appendix D). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria: | |||
: 1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of laboratory results and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the DOE MAPEP criteria. | |||
: 2. ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, NELAC, state specific PT program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document. | |||
: 3. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values. | |||
The MAPEP defines three levels of performance: Acceptable (flag = | |||
"A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value. | |||
Performance is acceptable with warning when a mean result falls in the range from +/-20% to +/-30% of the reference value (i.e., 20% < | |||
bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable. | |||
For the primary laboratory, 16 out of 18 analytes met the specified acceptance criteria. Two samples did not meet the specified acceptance criteria for the following reasons: | |||
: 1. Teledyne Brown Engineering's Analytics December 2008 Sr-89 in milk result of 18.0 pCi/L was higher than the known value of 12.6 pCi/L, resulting in a found to known ratio of 1.43. NCR 09-02 was initiated to investigate this failure. | |||
: 2. Teledyne Brown Engineering's Analytics' ERA Quik Response water sample January 2008 Sr-89 result of 37.33 pCi/L exceeded the upper acceptance limit of 25.2 pCi/L. No cause could be found for the failure. Studies bracketing these results, RAD 71 and RAD 72 had acceptable Sr-89 results. NCR 08-03 For the secondary laboratory, all of the 15 analytes met the specified acceptance criteria. | |||
The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data. | |||
Intentionally left blank APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT | Intentionally left blank APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT | ||
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==SUMMARY== | ==SUMMARY== | ||
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: | FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER GR-B 36 4 10.9 7.4 10.9 D-21 INDICATOR 0 (PCI/LITER) (12/12) (22/24) (12/12) IL RIVER AT EJ&E BRIDGE (3.7/19.8) (3.2/14.3) (3.7/19.8) 1.4 MILES WNW OF SITE H-3 12 2000 454 3665 3665 D-57 CONTROL 0 (2/4) (2/8) (2/4) KANKAKEE RIVER AT WILL ROAD(CONTROL) | ||
(192/716) (890/6440) (890/6440) 2.0 MILES SE OF SITE GAMMA 36 MN-54 15 <LLD <LLD 0 CO-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 CO-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD 0 NB-95 15 <LLD <LLD 0 | |||
TYPES OF | * THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | ||
GR-B | |||
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOR DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: | FOR DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER ZR-95 30 <LLD <LLD 0 (PCI/LITER) 1-131 15 <LLD <LLD 0 CS-134 15 <LLD <LLD 0 k) | ||
CS-137 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD 0 GROUND WATER H-3 16 2000 403 NA 403 D-23 INDICATOR 0 (PCI/LITER) (12/16) (12/12) THORSEN WELL (207/525) (207/525) 0.7 MILES S OF SITE GAMMA 16 MN-54 15 <LLD NA 0 | |||
TYPES OF | * THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | ||
H-3 16 | |||
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: | FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER CO-58 15 <LLD NA 0 (PCI/LITER) | ||
FE-59 30 <LLD NA CO-60 15 <LLD NA 0 ZN-65 30 <LLD NA 0 NB-95 15 <LLD NA ZR-95 30 <LLD NA 0 1-131 15 <LLD NA 0 CS-134 15 <LLD NA 0 | |||
TYPES OF | * THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | ||
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: | FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER CS-137 18 <LLD NA 0 (PCI/LITER) | ||
BA- 140 60 <LLD NA 0 LA- 140 15 <LLD NA 0 FISH GAMMA 8 (PCI/KG WET) MN-54 130 <LLD <LLD 0 CO-58 130 <LLD <LLD 0 FE-59 260 <LLD <LLD 0 CO-60 130 <LLD <LLD 0 ZN-65 260 <LLD <LLD 0 | |||
TYPES OF | * THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | ||
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: | FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS FISH NB-95 NA <LLD <LLD 0 (PCI/KG WET) | ||
ZR-95 NA <LLD <LLD 0 CS-134 130 <LLD <LLD 0 CS-137 150 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 SEDIMENT GAMMA 2 (PCI/KG DRY) MN-54 NA <LLD NA 0 CO-58 NA <LLD NA 0 | |||
TYPES OF | * THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | ||
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: | FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT FE-59 NA <LLD NA 0 (PCI/KG DRY) | ||
CO-60 NA <LLD NA 0 ZN-65 NA <LLD NA 0 NB-95 NA <LLD NA 0 | |||
TYPES OF | ) | ||
ZR-95 NA <LLD NA 0 CS-134 150 <LLD NA 0 CS-137 180 158 NA 158 D-27 INDICATOR (1/2) (1/2) DRESDEN LOCK AND DAM - DOWNSTREAM 0.8 MILES NW OF SITE BA-140 NA <LLD NA 0 | |||
* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | |||
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: | FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT LA-140 NA <LLD NA (PCI/KG DRY) | ||
AIR PARTICULATE GR-B 689 10 20 21 21 D-14 INDICATOR 0 (E-3 PCI/CU.METER) (635/636) (53/53) (53/53) CHANNAHON (5/53) (9/47) (8/53) 3.7 MILES NE OF SITE GAMMA 52 MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD CO-60 NA <LLD <LLD ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 | |||
TYPES OF | * THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | ||
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: | FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATE ZR-95 NA <LLD <LLD 0 (E-3 PCI/CU.METER) | ||
CS-134 50 <LLD <LLD CS-137 60 <LLD <LLD 00 BA- 140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD AIR IODINE GAMMA 689 (E-3 PCI/CU.METER) 1-131 70 <LLD <LLD 0 MILK 1-131 20 I NA <LLD (PCI/LITER) | |||
TYPES OF | * THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | ||
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: | FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK GAMMA 20 (PCI/LITER) MN-54 NA NA <LLD 0 CO-58 NA NA <LLD 0 FE-59 NA NA <LLD 0 CO-60 NA NA <LLD 0 ZN-65 NA NA <LLD 0 NB-95 NA NA <LLD 0 ZR-95 NA NA <LLD 0 CS-134 15 NA <LLD 0 | ||
* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | |||
TYPES OF | |||
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOR DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: | FOR DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK CS-137 18 NA <LLD 0 (PCULITER) | ||
BA-140 60 NA <LLD 0 LA-140 15 NA <LLD | |||
TYPES OF | ,> | ||
VEGETATION GAMMA 10 (PCI/KG WET) MN-54 NA <LLD <LLD CO-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 CO-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 | |||
* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | |||
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | |||
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS VEGETATION NB-95 NA <LLD <LLD 0 (PCI/KG WET) | |||
ZR-95 NA <LLD <LLD 0 1-131 60 <LLD <LLD 0 CS-134 60 <LLD <LLD 0 CS-137 80 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 DIRECT RADIATION TLD-QUARTERLY 360 NA 23.2 22.6 27.5 D-214-1 INDICATOR 0 (MILLI-ROENTGEN/QTR.) (352/352) (8/8) (4/4) | |||
(16/31) (19/33) (25/31) 5.0 MILES WNW | |||
* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | |||
Intentionally left blank APPENDIX B LOCATION DESIGNATION, DISTANCE & | |||
==SUMMARY== | ==SUMMARY== | ||
OF THE AMBIENT DOSIMETRY PROGRAM FOR DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN ANALYZED MINIMUM MAXIMUM +/- 2 S.D. | |||
INNER RING 128 18 30 23.5 +/- 5.5 OUTER RING 128 17 31 23.4 +/- 6.0 OTHER 96 16 28 22.6 +/- 4.8 CONTROL 8 19 33 22.6 +/- 8.9 INNER RING STATIONS - D-101-1, D-101-2, D-102-1, D-102-2, D-103-1, D-103-2, D-104-1, D-104-2, D-105-1, D-105-2, D-106-1, D-106-2, D-107-1, D-107-2, D-108-1, D-108-2, D-109-1, D-109-2, D-110- | |||
Dresden has a domestic water system that is supplied by two deep wells (1500 feet deep) that were installed about 50 years ago south of the P.A. Samples taken from domestic water supply and have never shown any detectable tritium concentration. | Dresden has a domestic water system that is supplied by two deep wells (1500 feet deep) that were installed about 50 years ago south of the P.A. Samples taken from domestic water supply and have never shown any detectable tritium concentration. | ||
Tritium has a half-life of 12.3 years. This means that 40 years from now 90% of the tritium on site today will have decayed away to more stable elements.Given the limited volume of contaminated groundwater on site, radioactive decay, slow groundwater movement, and dilution effects the conclusion of the HIR is that the operation of Dresden Nuclear Power Station had no adverse radiological impact on the environment. | Tritium has a half-life of 12.3 years. This means that 40 years from now 90% of the tritium on site today will have decayed away to more stable elements. | ||
As a result there is little potential for contaminated groundwater on site to affect off-site drinking water. | Given the limited volume of contaminated groundwater on site, radioactive decay, slow groundwater movement, and dilution effects the conclusion of the HIR is that the operation of Dresden Nuclear Power Station had no adverse radiological impact on the environment. As a result there is little potential for contaminated groundwater on site to affect off-site drinking water. | ||
II. Introduction Radiological Groundwater Monitoring Program (RGPP): Dresden has a Radiological Groundwater Monitoring Program (RGPP) that provides long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions. | |||
Dresden uses developed groundwater wells and surface water sample points in the RGPP.The Dresden RGPP was established in 2006 and there have been no significant changes to this program. This program does not impact the operation of the plant and is independent of the REMP.Developed groundwater wells are wells that were installed specifically for monitoring groundwater. | II. Introduction Radiological Groundwater Monitoring Program (RGPP): | ||
These wells are equipped with screens and are properly sealed near the surface to avoid surface water intrusion. | Dresden has a Radiological Groundwater Monitoring Program (RGPP) that provides long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions. | ||
The wells were designed in accordance with appropriate codes and developed in accordance with appropriate standards and procedures. | Dresden uses developed groundwater wells and surface water sample points in the RGPP. | ||
Dresden has groundwater monitoring wells identified as "shallow" (depths from 15 to 35 feet), "Intermediate" (depths from 35 to 55 feet) and "deep" (depths beyond 100 feet). All wells installed to a depth greater than 100 feet ("deep" wells) were found to be dry and removed from the RGPP. Surface water sample points are identified sample locations in the station's canals and cooling pond.There are 71 sampling points in the RGPP:*Dresden has 39 developed groundwater monitoring wells within the Protected Area.Some of these wells form a ring just inside the security fence and the remaining wells were installed near underground plant system piping that contains radioactive water.*Dresden has 26 developed groundwater monitoring wells outside the P.A. the majority of which form a ring just within the perimeter of the property.*Dresden has 6 surface water monitoring locations on the owner-controlled area sampled as part of the Dresden RGPP. These consist of one sample from each of the 5 different canals and one sample from the cooling pond.The Dresden site-specific RGPP procedure identifies the historic 'events' that would affect the individual RGPP sample results. This procedure identifies threshold values for each-sample point, which if exceeded, could be an indication of a new spill from an above ground system or a new leak in an underground pipe containing tritiated water. | The Dresden RGPP was established in 2006 and there have been no significant changes to this program. This program does not impact the operation of the plant and is independent of the REMP. | ||
The RGPP sample points are currently sampled on a frequency of twice per year.During 2008, there were 282 analyses that were performed on 140 samples from 71 sample points.Supplemental Radiological Groundwater Monitoring Program (SRGPP): Dresden also has a Supplemental Radiological Groundwater Monitoring Program (SRGPP) that provides short-term monitoring of a limited selection of monitoring points, mostly within the P.A., intended to identity relatively rapid changes in the groundwater tritium concentrations. | Developed groundwater wells are wells that were installed specifically for monitoring groundwater. These wells are equipped with screens and are properly sealed near the surface to avoid surface water intrusion. The wells were designed in accordance with appropriate codes and developed in accordance with appropriate standards and procedures. Dresden has groundwater monitoring wells identified as "shallow" (depths from 15 to 35 feet), "Intermediate" (depths from 35 to 55 feet) and "deep" (depths beyond 100 feet). All wells installed to a depth greater than 100 feet ("deep" wells) were found to be dry and removed from the RGPP. Surface water sample points are identified sample locations in the station's canals and cooling pond. | ||
Sentinel Wells, sometimes referred to as "baby wells" are wells that were installed to monitor local shallow groundwater; typically in associated with a historic underground pipe leak. These wells are not constructed to code or developed to a standard. | There are 71 sampling points in the RGPP: | ||
Most sentinel wells are from 6 to 12 feet deep and consist of 2" PVC pipe without screens.Many sentinel wells were installed near an underground HPCI suction line and were subsequently removed as part of the excavation and repair of that line.Dresden has two basic storm water runoff sewer systems within the P.A: one sewer-system routes to the east, then north, and discharges into the Unit 1 intake canal, the second sewer-system routes to the west, then north, through a large Oil Separator, and discharges to the hot canal. Both the Unit 1 intake canal and the hot canal eventually route to the cooling pond.A. Objectives of the RGPP The Objective of the RGPP is to provide long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions. | *Dresden has 39 developed groundwater monitoring wells within the Protected Area. | ||
The objective of the SRGPP is to provide indication of short-term changes to groundwater tritium concentrations within the P.A.If isotopic results of groundwater samples exceed the thresholds specified in this procedure it could be an indication of a new spill from an above ground system or a new leak in an underground pipe containing tritiated water.Specific Objectives include: 1. Perform routine water sampling and radiological analysis of water from selected locations. | Some of these wells form a ring just inside the security fence and the remaining wells were installed near underground plant system piping that contains radioactive water. | ||
: 2. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner. | *Dresden has 26 developed groundwater monitoring wells outside the P.A. the majority of which form a ring just within the perimeter of the property. | ||
: 3. Regularly assess analytical results to identify adverse trends.4. Take necessary corrective actions to protect groundwater resources. | *Dresden has 6 surface water monitoring locations on the owner-controlled area sampled as part of the Dresden RGPP. These consist of one sample from each of the 5 different canals and one sample from the cooling pond. | ||
The Dresden site-specific RGPP procedure identifies the historic 'events' that would affect the individual RGPP sample results. This procedure identifies threshold values for each-sample point, which if exceeded, could be an indication of a new spill from an above ground system or a new leak in an underground pipe containing tritiated water. | |||
The RGPP sample points are currently sampled on a frequency of twice per year. | |||
During 2008, there were 282 analyses that were performed on 140 samples from 71 sample points. | |||
Supplemental Radiological Groundwater Monitoring Program (SRGPP): | |||
Dresden also has a Supplemental Radiological Groundwater Monitoring Program (SRGPP) that provides short-term monitoring of a limited selection of monitoring points, mostly within the P.A., intended to identity relatively rapid changes in the groundwater tritium concentrations. | |||
Sentinel Wells, sometimes referred to as "baby wells" are wells that were installed to monitor local shallow groundwater; typically in associated with a historic underground pipe leak. These wells are not constructed to code or developed to a standard. Most sentinel wells are from 6 to 12 feet deep and consist of 2" PVC pipe without screens. | |||
Many sentinel wells were installed near an underground HPCI suction line and were subsequently removed as part of the excavation and repair of that line. | |||
Dresden has two basic storm water runoff sewer systems within the P.A: one sewer-system routes to the east, then north, and discharges into the Unit 1 intake canal, the second sewer-system routes to the west, then north, through a large Oil Separator, and discharges to the hot canal. Both the Unit 1 intake canal and the hot canal eventually route to the cooling pond. | |||
A. Objectives of the RGPP The Objective of the RGPP is to provide long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions. The objective of the SRGPP is to provide indication of short-term changes to groundwater tritium concentrations within the P.A. | |||
If isotopic results of groundwater samples exceed the thresholds specified in this procedure it could be an indication of a new spill from an above ground system or a new leak in an underground pipe containing tritiated water. | |||
Specific Objectives include: | |||
: 1. Perform routine water sampling and radiological analysis of water from selected locations. | |||
: 2. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner. | |||
: 3. Regularly assess analytical results to identify adverse trends. | |||
: 4. Take necessary corrective actions to protect groundwater resources. | |||
B. Implementation of the Objectives | B. Implementation of the Objectives | ||
: 1. Dresden Nuclear Power Station will continue to perform routine sampling and radiological analysis of water from selected locations. | : 1. Dresden Nuclear Power Station will continue to perform routine sampling and radiological analysis of water from selected locations. | ||
: 2. Dresden Nuclear Power Station has implemented procedures to identify and report new leaks, spills, or other detections with potential radiological significance in a timely manner.3. Dresden Nuclear Power Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.4. If an adverse trend in groundwater monitoring analytical results is identified, further investigation will be undertaken. | : 2. Dresden Nuclear Power Station has implemented procedures to identify and report new leaks, spills, or other detections with potential radiological significance in a timely manner. | ||
If the investigation identifies a leak or unidentified spill, corrective actions will be implemented. | : 3. Dresden Nuclear Power Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends. | ||
C. Program Description Dresden has a Radiological Groundwater Monitoring Program (RGPP) that provides long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions. | : 4. If an adverse trend in groundwater monitoring analytical results is identified, further investigation will be undertaken. If the investigation identifies a leak or unidentified spill, corrective actions will be implemented. | ||
Dresden uses 71 developed groundwater wells and surface water sample points in the RGPP.1. Sample Collection Sample locations can be found in Table A-i, Figures A-1 and A-2, and, Appendix A.Groundwater and Surface Water Water samples are collected in accordance with the schedule delineated in the Dresden site-specific RGPP procedures. | C. Program Description Dresden has a Radiological Groundwater Monitoring Program (RGPP) that provides long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions. Dresden uses 71 developed groundwater wells and surface water sample points in the RGPP. | ||
: 1. Sample Collection Sample locations can be found in Table A-i, Figures A-1 and A-2, and, Appendix A. | |||
Groundwater and Surface Water Water samples are collected in accordance with the schedule delineated in the Dresden site-specific RGPP procedures. | |||
Analytical laboratories are subject to internal quality assurance programs, industry crosscheck programs, as well as nuclear industry audits. Station personnel review and evaluate the analytical results. | Analytical laboratories are subject to internal quality assurance programs, industry crosscheck programs, as well as nuclear industry audits. Station personnel review and evaluate the analytical results. | ||
D. Characteristics of Tritium (H-3) | |||
Tritium (chemical symbol H-3) is a radioactive isotope of hydrogen. The most common form of tritium is tritium oxide, which is also called "tritiated water." The chemical properties of tritium are essentially those of ordinary hydrogen. | |||
Tritiated water behaves the same as ordinary water in both the environment and the body. Tritium can be taken into the body by drinking water, breathing air, eating food, |
Revision as of 07:01, 14 November 2019
ML091320040 | |
Person / Time | |
---|---|
Site: | Dresden ![]() |
Issue date: | 05/08/2009 |
From: | Hanley T Exelon Generation Co, Exelon Nuclear |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
FOIA/PA-2010-0209, SVPLTR 09-0020 | |
Download: ML091320040 (129) | |
Text
Exelon Generation Company, LLC Dresden Nuclear Power Station www.exeloncorp.com Exel rn NuCeaT 650o North Dresden Road Morris, IL60450-9765 May 08, 2009 SVPLTR # 09-0020 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 1, 2, and 3 Facility Operating License No. DPR-2 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos.50-010, 50-237, and 50-249
Subject:
Dresden Nuclear Power Station 2008 Annual Radiological Environmental Operating Report Enclosed is the Exelon Dresden Nuclear Power Station 2008 Annual Radiological Environmental Operating Report, submitted in accordance with Section 6.9.A.3 of the Unit 1 Dresden Nuclear Power Station Technical Specifications and Section 5.6.2, "Annual Radiological Environmental Operating Report," of the Units 2 and 3 Technical Specifications.
This report provides the results of the radiological environmental and meteorological monitoring programs for the 2008 calendar year.
In addition, Appendix F of the report contains the results of groundwater monitoring conducted in accordance with Exelon's Radiological Groundwater Protection Program, which is a voluntary program implemented in 2006. This information is being reported in accordance with a nuclear industry initiative.
Should you have any questions concerning this letter, please contact Stephen Taylor, Regulatory Assurance Manager, at (815) 416-2800.
Respectfully, Tim Hanley Site Vice President Dresden Nuclear Power Station Attachment - Annual Radiological Environmental Operating Report cc: Regional Administrator - NRC Region III NRC Senior Resident - Dresden Nuclear Power Station
Docket No: 50-010 50-237 50-249 DRESDEN NUCLEAR POWER STATION UNITS 1, 2 and 3 Annual Radiological Environmental Operating Report 1 January Through 31 December 2008 Prepared By Teledyne Brown Engineering Environmental Services Nuclear Dresden Nuclear Power Station Morris, IL 60450 May 2009
Table Of Contents I. Sum m ary and Conclusions ........................................................................................... 1 II. Intro d u ctio n ........................................................................................................................ 3 A. Objectives of the REM P ................................................................................... 3 B. Im plem entation of the O bjectives ..................................................................... 3 III. Program Description ..................................................................................................... 4 A. Sam ple Collection ............................................................................................. 4 B. Sam ple Analysis ................................................................................................ 5 C . Data Interpretation ........................................................................................... 6 D. Program Exceptions ........................................................................................ 7 E. Program Changes ............................................................................................. 8 IV. Results and Discussion ............................................................................................... 8 A. Aquatic Environm ent ........................................................................................ 8
- 1. Surface W ater ......................................................................................... 8
- 2. G round W ater ......................................................................................... 9
- 3. Fish ......................................................................................................... 9
- 4. Sedim ent .............................................................................................. 10 B. Atm ospheric Environm ent ............................................................................... 10
- 1. Airborne ............................................................................................... 10
- a. Air Particulates .......................................................................... 10
- b. Airborne Iodine .......................................................................... 11
- 2. Terrestrial ............................................................................................. 12
- a. Milk ............................... ......... 12
- b. Food Products ...................................... 12 C. Am bient Gam m a Radiation ............................................................................. 12 D. Land Use Survey ........................................................................................... 13 E. Errata Data .................................................................................................... 13 F. Summary of Results - Inter-laboratory Comparison Program ....................... 13
Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Dresden Nuclear Power Station, 2008 Appendix B Location Designation, Distance & Direction, and Sample Collection &
Analytical Methods Tables Table B-I: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2008 Table B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2008 Figures Figure B-1: Dresden Station Inner Ring TLD Locations, Fish, Water, and Sediment Locations, 2008 Figure B-2: Dresden Station Fixed Air Sampling and TLD Sites, Outer Ring TLD Locations and Milk Location, 2008 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-1.1 Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table C-1.2 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table C-I1.1 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
ii
Table C-11.2 Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table C-111.1 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table C-V. 1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu meter) in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table C-VI.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table C-VII.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table C-VII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table C-VIII.1 Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table C-IX.1 Quarterly TLD Results for Dresden Nuclear Power Station, 2008.
Table C-IX.2 Mean Quarterly TLD Results for the Inner Ring, Outer Ring, Other and Control Locations for Dresden Nuclear Power Station, 2008.
Table C-IX.3 Summary of the Ambient Dosimetry Program for Dresden Nuclear Power Station, 2008.
Figures Figure C-1 Surface Water - Gross Beta - Stations D-51 and D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2008.
Figure C-2 Surface Water - Gross Beta - Stations D-54 (C) and D-57 (C)
Collected in the Vicinity of DNPS, 2002 - 2008.
Figure C-3 Surface Water - Gross Beta - Station D-21 Collected in the Vicinity of DNPS, 2007 - 2008.
Figure C-4 Surface Water - Tritium - Stations D-51 and D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2008.
Figure C-5 Surface Water - Tritium - Station D-54 (C) and D-57 (C) Collected in the Vicinity of DNPS, 2002 - 2008.
iii
Figure C-6 Surface Water - Tritium - Station D-21 Collected in the Vicinity of DNPS, 2007 - 2008.
Figure C-7 Ground Water - Tritium - Stations D-23 and D-35 Collected in the Vicinity of DNPS, 2000 - 2008.
Figure C-8 Air Particulate - Gross Beta - Stations D-01 and D-02 Collected in the Vicinity of DNPS, 2000 - 2008.
Figure C-9 Air Particulate - Gross Beta - Stations D-03 and D-04 Collected in the Vicinity of DNPS, 2000 - 2008.
Figure C-10 Air Particulate - Gross Beta - Stations D-07 and D-12 (C) Collected in the Vicinity of DNPS, 2000 - 2008.
Figure C-11 Air Particulate - Gross Beta - Stations D-45 and D-53 Collected in the Vicinity of DNPS, 2000 - 2008.
Figure C-12 Air Particulate - Gross Beta - Stations D-08 and D-10 Collected in the Vicinity of DNPS, 2005 - 2008.
Figure C-13 Air Particulate - Gross Beta - Stations D-13 and D-14 Collected in the Vicinity of DNPS, 2005 - 2008.
Figure C-14 Air Particulate - Gross Beta - Stations D-55 and D-56 Collected in the Vicinity of DNPS, 2006 - 2008.
Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2008 Table D-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2008 Table D-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)
Teledyne Brown Engineering, 2008 Appendix E Errata Data Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv
- 1. Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Dresden Nuclear Power Station (DNPS) by Exelon covers the period 1 January 2008 through 31 December 2008. During that time period, 1,786 analyses were performed on 1,650 samples. In assessing all the data gathered for this report it was concluded that the operation of DNPS had no adverse radiological impact on the environment.
Surface water samples were analyzed for concentrations of gross beta, tritium and gamma emitting nuclides. Ground water samples were analyzed for concentrations of tritium and gamma emitting nuclides. No anthropogenic gamma emitting nuclides were detected. Gross beta and tritium activities detected were consistent with those detected in previous years.
Fish (commercially and recreationally important species) and sediment samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected in fish. Sediment samples had Cesium-1 37 concentrations consistent with levels observed in previous years. No plant-produced fission or activation products were found in sediment.
Air particulate samples were analyzed for concentrations of gross beta and gamma emitting nuclides. Gross beta results at the indicator locations were consistent with those at the control location. No fission or activation products were detected.
High sensitivity 1-131 analyses were performed on weekly air samples. All results were less than the minimum detectable activity.
Cow milk samples were analyzed for concentrations of 1-131 and gamma emitting nuclides. All 1-131 results were below the minimum detectable activity.
Concentrations of naturally occurring K-40 were found. No fission or activation products were found.
Food product samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected.
Environmental gamma radiation measurements were performed quarterly using thermoluminescent dosimeters. Levels detected were consistent with those observed in previous years.
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II. Introduction The Dresden Nuclear Power Station (DNPS), consisting of one retired reactor and two operating 912 MWe boiling water reactors owned and operated by Exelon Corporation, is located in Grundy County, Illinois. Unit No. 1 went critical in 1960 and was retired in 1978. Unit No. 2 went critical on 16 June 1970. Unit No. 3 went critical on 02 November 1971. The site is located in northern Illinois, approximately 12 miles southwest of Joliet, Illinois at the confluence of the Des Plaines and Kankakee Rivers where they form the Illinois River.
This report covers those analyses performed by Teledyne Brown Engineering (TBE) Global Dosimetry, and Environmental Inc. Midwest Laboratory (EIML) on samples collected during the period 1 January 2008 through 31 December 2008.
An assessment of the station's radioactive effluent monitoring results and radiation dose via the principle pathways of exposure resulting from plant emissions of radioactivity including the maximum noble gas gamma and beta air doses in the unrestricted area, an annual summary of meteorological conditions including wind speed, wind direction, and atmospheric stability, and the result of the 40CFR190 uranium fuel cycle dose analysis for the calendar year are published in the station's Annual Radioactive Effluent Release Report.
A. Objective of the Radiological Environmental Monitoring Program (REMP)
The objectives of the REMP are to:
- 1. Provide data on measurable levels of radiation and radioactive materials in the site environs.
- 2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.
B. Implementation of the Objectives The implementation of the objectives is accomplished by:
- 1. Identifying significant exposure pathways.
- 2. Establishing baseline radiological data of media within those pathways.
- 3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment.
Ill. Program Description A. Sample Collection Samples for the DNPS REMP were collected for Exelon Nuclear by EIML.
This section describes the general collection methods used by EIML to obtain environmental samples for the DNPS REMP in 2008. Sample locations and descriptions can be found in Table B-1 and Figures B-1 and B-2, Appendix B. The collection methods used by EIML are listed in Table B-2.
Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, ground water, fish, and sediment.
Samples were collected from three surface water locations (D-21, D-52 and D-57) and composited for analysis. Control locations were D-52 and D-57. Samples were collected quarterly or more frequently from two well water locations (D-23 and D-35). All samples were collected in new unused plastic bottles, which were rinsed with source water prior to collection. Fish samples comprising the flesh of channel catfish, largemouth bass, common carp and freshwater drum were collected semiannually at two locations, D-28 and D-46 (Control). Sediment samples composed of recently deposited substrate were collected at one location semiannually, D-27.
Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, milk, and food products. Airborne iodine and particulate samples were collected at thirteen locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-12, D-14, D-45, D-53, D-55 and D-56). The control location was D-12. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The air filters and air iodine samples were replaced weekly and sent to the laboratory for analysis.
Milk samples were collected biweekly at one control location (D-25) from May through October, and monthly from November through April. There are no milking animals within 10 km of the site. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite, and shipped promptly to the laboratory.
Food products were collected annually in September at five locations (D-Control, D-Quad 1, D-Quad 2, D-Quad 3, and D-Quad 4). The control location was D-Control. Various types of samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.
Ambient Gamma Radiation Direct radiation measurements were made using CaF 2 and LiF thermoluminescent dosimeters (TLD). Each location consisted of 2 TLD sets. The TLD locations were placed on and around the DNPS site as follows:
An inner ring consisting of 16 locations (D-101, D-102, D-103, D-104, D-105, D-106, D-107, D-108, D-109, D-110, D-111, D-112A, D-113, D-114, D-115 and D-116) at or near the site boundary.
An outer ring consisting of 16 locations (D-201, D-202, D-203, D-204, D-205, D-206, D-207, D-208, D-209, D-210, D-211, D-212, D-213, D-214, D-215 and D-216) approximately 5 to 10 km from the site.
An other set consisting of TLDs at the 12 air sampler locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-14, D-45, D-53, D-55, and D-56).
The balance of one location (D-12) representing the control area.
Two TLDs - each comprised of two CaF 2 and two LiF thermoluminescent phosphors enclosed in plastic - were placed at each location. The TLDs were exchanged quarterly and sent to Global Dosimetry for analysis.
B. Sample Analysis This section describes the general analytical methodologies used by TBE and EIML to analyze the environmental samples for radioactivity for the DNPS REMP in 2008. The analytical procedures used by the laboratories are listed in Table B-2.
In order to achieve the stated objectives, the current program includes the following analyses:
- 1. Concentrations of beta emitters in surface water and air particulates.
- 2. Concentrations of gamma emitters in ground and surface water, air particulates, milk, fish, sediment and vegetation.
5-
- 3. Concentrations of tritium in ground and surface water.
- 4. Concentrations of 1-131 in air and milk.
- 5. Ambient gamma radiation levels at various site environs.
C. Data Interpretation For the purpose of this report, Dresden Nuclear Power Station was considered operational at initial criticality. In addition, data were compared to previous years' operational data for consistency and trending. Several factors were important in the interpretation of the data:
- 1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) was defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD was intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity. All analyses were designed to achieve the required DNPS detection capabilities for environmental sample analysis.
The minimum detectable concentration (MDC) is calculated the same as the LLD with the exception that the measurement is an after the fact estimate of the presence of activity.
- 2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity effecting a negative number. An MDC was reported in all cases where positive activity was not detected.
Gamma spectroscopy results for each type of sample were grouped as follows:
For ground and surface water and vegetation 12 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, 1-131, Cs-134, Cs-137, Ba-140, and La-140 were reported.
For fish, sediment, dredge spoil, air particulate and milk 11
nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140 and La-140 were reported.
Means and standard deviations of the results were calculated. The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty.
D. Program Exceptions For 2008 the DNPS REMP had a sample recovery rate in excess of 99%.
Sample anomalies and missed samples are listed in the tables below:
Table D-1 LISTING OF SAMPLE ANOMALIES Sample Location Collection Reason Type Code Date AP/I D-01 01/25/08 - 02/01/08 Foreign substance was found on the flow indicator. Flow rate was estimated at 60 cfh.
AP/I D-01 05/16/08 - 05/23/08 Low timer reading of 127.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> due to loss of power to the sampler.
AP/I D-01 05/23/08 - 05/30/08 Low timer reading of 166.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> due to recent power restoration.
AP/I D-01 12/19/08 - 12/26/08 Low timer reading of 139.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> due to power outage.
AP/I D-02 09/19/08 - 09/26/08 Low timer reading of 166.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; cause is unknown.
AP/I D-02 12/19/08 - 12/26/08 Low timer reading of 159.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> due to power outage.
AP/I D-03 07/18/08 - 07/25/08 Low timer reading of 89.6; cause is unknown.
AP/I D-10 11/28/08 - 12/05/08 Low timer reading of 164.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> due to area power outage.
SW D-21 01/25/08 - 02/29/08 Grab samples taken due to no compositor pump flow.
SW D-21 02/29/08 - 03/28/08 Grab samples taken due to no compositor pump flow.
Table D-1 LISTING OF SAMPLE ANOMALIES (continued)
Sample Location Collection Reason Type Code Date AP/I D-55 11/28/08 - 12/05/08 Low timer reading of 155.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> due to area power outage.
AP/l D-56 02/08/08 - 02/15/08 Low timer reading of 157.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; cause is unknown.
Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason Type Code Date There were no missed samples for 2008.
Each program exception was reviewed to understand the causes of the program exception. Sampling and maintenance errors were reviewed with the personnel involved to prevent recurrence. Occasional equipment breakdowns and power outages were unavoidable.
The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.
E. Program Changes There were no program changes for 2008.
IV. Results and Discussion A. Aquatic Environment
- 1. Surface Water Samples were taken weekly and composited for analysis at three locations (D-21, D-52, and D-57). Of these locations only D-21 located downstream, could be affected by Dresden's effluent releases. The following analyses were performed:
Gross Beta Monthly composites from all locations were analyzed for
concentrations of gross beta (Table C-1.1, Appendix C). The values ranged from 3.2 to 19.8 pCi/l. Concentrations detected were consistent with those detected in previous years (Figures C-1, C-2, and C-3, Appendix C).
Tritium Quarterly composites from all locations were analyzed for tritium activity (Table C-1.2, Appendix C). The indicator values ranged from192 to 716 pCi/L. Control values ranged from 890 to 6440 pCi/L. Concentrations detected were consistent with those detected in previous years (Figures C-4, C-5, and C-6, Appendix C).
Gamma Spectrometry Monthly composites from all locations were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). No nuclides were detected, and all required LLDs were met.
- 2. Ground Water Quarterly or more frequent grab samples were collected at two locations (D-23 and D-35). These locations could be affected by Dresden's effluent releases and by sources upstream on the Kankakee River. The following analyses were performed:
Tritium All samples were analyzed for tritium activity (Table C-11.1, Appendix C). D-35 values ranged from <155 to <175 pCi/L. D-23 values ranged from 207 to 525 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-7, Appendix C).
Gamma Spectrometry All samples were analyzed for gamma emitting nuclides (Table C-11.2, Appendix C). No nuclides were detected, and all required LLDs were met.
- 3. Fish Fish samples comprised of channel catfish, largemouth bass, common carp and freshwater drum were collected at two locations
(D-28 and D-46) semiannually. Location D-28 could be affected by Dresden's effluent releases. The following analysis was performed:
Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma emitting nuclides (Table C-lI1.1, Appendix C).
Naturally occurring K-40 was found at all stations and ranged from 2,700 to 3,850 pCi/kg wet. No fission or activation products were detected.
- 4. Sediment Aquatic sediment samples were collected at one location (D-27) semiannually. This downstream location could be affected by Dresden's effluent releases. The following analysis was performed:
Gamma Spectrometry Sediment samples from the location were analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C). Cesium-137 was detected in one sample.
Concentrations of the fission product Cs-1 37 was found in one sample at a concentration of 158 pCi/kg dry. The activity detected was consistent with those detected in previous years and is likely due to fallout from above-ground nuclear weapons testing. No other fission or activation products were detected.
- 5. Dredging Spoils According to the U.S. Army Corps of Engineers in July 2008, no dredging was performed within one mile of Dresden Station in the past year. Therefore, no sampling of dredging spoils was performed.
B. Atmospheric Environment
- 1. Airborne
- a. Air Particulates Continuous air particulate samples were collected from 13 locations on a weekly basis. The 13 locations were separated into four groups: On-site samplers (D-01, D-02,
D-03), Near-field samplers within 4 km of the site (D-04, D-07, D-45, D-53 and D-56), Far-field samplers between 4 and 10 km from the site (D-08, D-10, D-14 and D-55) and the Control sampler between 10 and 30 km from the site (D-12).
The following analyses were performed:
Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-V.1 and C-V.2, Appendix C).
Detectable gross beta activity was observed at all locations.
Comparison of results among the four groups aid in determining the effects, if any, resulting from the operation of DNPS. The results from the On-Site locations ranged from 6 to 39 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3 . The results from the Near-Field locations ranged from 5 to 48 E-3 pCi/m 3 with a mean of 20 E-3 pCi/m 3 . The results from the Far-Field locations ranyed from <4 to 53 E-3 pCi/m 3 with a mean of 20 E-3 pCi/m . The results from the Control location ranged from 9 to 47 E-3 pCi/m 3 with a mean of 21 E-3 pCi/m 3 . Comparison of the 2008 air particulate data with previous years data indicate no effects from the operation of DNPS. In addition a comparison of the weekly mean values for 2008 indicate no notable differences among the four groups (Figures C-8 through C-14, Appendix C).
Gamma Spectrometry Samples were composited quarterly and analyzed for gamma emitting nuclides (Table C-V.3, Appendix C).
Naturally occurring Be-7 due to cosmic ray activity was detected in 47 of 52 samples and ranged from 43.7 to 123 E-3 pCi/m 3. K-40 was also detected in 4 samples and ranged from 26.4 to 33.3 E-3 pCi/ m3 . No anthropogenic nuclides were detected, and all required LLDs were met.
- b. Airborne Iodine Continuous air samples were collected from 13 locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-12, D-14, D-45, D-53, D-55 and D-56) and analyzed weekly for 1-131 (Table C-VI.1, Appendix C). No nuclides were detected, and all required LLDs were met.
- 2. Terrestrial
- a. Milk There are no indicator locations within 10 kilometers of the station. Samples were collected from one control location (D-25) biweekly May through October and monthly November through April. The following analyses were performed:
Iodine-131 Milk samples from the location were analyzed for concentrations of 1-131 (Table.C-VIl.1, Appendix C). No nuclides were detected, and all required LLDs were met.
Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-VII.2, Appendix C).
Naturally occurring K-40 activity was found in all nineteen samples. The activities ranged from 1,090 to 1,340 pCi/I.
No other nuclides were detected, and all required LLDs were met.
- b. Food Products Food product samples were collected at five locations (D-Control, D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4) when available. Four locations, (D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4) could be affected by Dresden's effluent releases. The following analysis was performed:
Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-VIII.1, Appendix C). No nuclides were detected, and all required LLDs were met.
C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Global Dosimetry 110 Environmental (CaF 2 and LiF) thermoluminescent dosimeters. Forty-five TLD locations were established around the site. Results of TLD measurements are listed in Tables C-IX.1 to C-IX.3, Appendix C.
Most TLD measurements were below 30 mR/quarter, with a range of 16 to 33 mR/quarter. A comparison of the Inner Ring, Outer Ring, and Other locations' data to the Control Location data, indicate that the ambient gamma radiation levels from the Control location (D-12-01, D-12-02) were comparable.
D. Land Use Survey A Land Use Survey conducted on 20 August 2008 around the Dresden Nuclear Power Station (DNPS) was performed by EIML for Exelon Nuclear to comply with Section 12.6.2 of the Dresden Offsite Dose Calculation Manual (ODCM). The purpose of the survey was to document the nearest resident or industrial facility, milk producing animal, and livestock in each of the sixteen 22 1/2 degree sectors within 10 km around the site. There were no changes required to the DNPS REMP as a result of this survey.
The results of this survey are summarized below.
Distance in Miles from the DNPS Reactor Buildings Sector Residence Livestock Milk Farm Miles Miles Miles AN 1.5 1.4 B NNE 0.8 6.0 CNE 0.8 5.8 D ENE 0.7 1.7 EE 1.1 F ESE 1.0 G SE 0.6 H SSE 0.5 JS 0.5 16.0 K SSW 3.3 L SW 3.6 11.4 MWSW 5.8 NW 3.5 0.5 P WNW 3.7 0.5 Q NW 2.6 0.5 R NNW 0.8 1.0 E. Errata Data There was no errata data discovered in 2008.
F. Summary of Results - Inter-Laboratory Comparison Program The primary laboratory analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices
(Appendix D). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:
- 1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of laboratory results and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the DOE MAPEP criteria.
- 2. ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, NELAC, state specific PT program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.
- 3. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values.
The MAPEP defines three levels of performance: Acceptable (flag =
"A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value.
Performance is acceptable with warning when a mean result falls in the range from +/-20% to +/-30% of the reference value (i.e., 20% <
bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable.
For the primary laboratory, 16 out of 18 analytes met the specified acceptance criteria. Two samples did not meet the specified acceptance criteria for the following reasons:
- 1. Teledyne Brown Engineering's Analytics December 2008 Sr-89 in milk result of 18.0 pCi/L was higher than the known value of 12.6 pCi/L, resulting in a found to known ratio of 1.43. NCR 09-02 was initiated to investigate this failure.
- 2. Teledyne Brown Engineering's Analytics' ERA Quik Response water sample January 2008 Sr-89 result of 37.33 pCi/L exceeded the upper acceptance limit of 25.2 pCi/L. No cause could be found for the failure. Studies bracketing these results, RAD 71 and RAD 72 had acceptable Sr-89 results. NCR 08-03 For the secondary laboratory, all of the 15 analytes met the specified acceptance criteria.
The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data.
Intentionally left blank APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT
SUMMARY
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER GR-B 36 4 10.9 7.4 10.9 D-21 INDICATOR 0 (PCI/LITER) (12/12) (22/24) (12/12) IL RIVER AT EJ&E BRIDGE (3.7/19.8) (3.2/14.3) (3.7/19.8) 1.4 MILES WNW OF SITE H-3 12 2000 454 3665 3665 D-57 CONTROL 0 (2/4) (2/8) (2/4) KANKAKEE RIVER AT WILL ROAD(CONTROL)
(192/716) (890/6440) (890/6440) 2.0 MILES SE OF SITE GAMMA 36 MN-54 15 <LLD <LLD 0 CO-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 CO-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD 0 NB-95 15 <LLD <LLD 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER ZR-95 30 <LLD <LLD 0 (PCI/LITER) 1-131 15 <LLD <LLD 0 CS-134 15 <LLD <LLD 0 k)
CS-137 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD 0 GROUND WATER H-3 16 2000 403 NA 403 D-23 INDICATOR 0 (PCI/LITER) (12/16) (12/12) THORSEN WELL (207/525) (207/525) 0.7 MILES S OF SITE GAMMA 16 MN-54 15 <LLD NA 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER CO-58 15 <LLD NA 0 (PCI/LITER)
FE-59 30 <LLD NA CO-60 15 <LLD NA 0 ZN-65 30 <LLD NA 0 NB-95 15 <LLD NA ZR-95 30 <LLD NA 0 1-131 15 <LLD NA 0 CS-134 15 <LLD NA 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER CS-137 18 <LLD NA 0 (PCI/LITER)
BA- 140 60 <LLD NA 0 LA- 140 15 <LLD NA 0 FISH GAMMA 8 (PCI/KG WET) MN-54 130 <LLD <LLD 0 CO-58 130 <LLD <LLD 0 FE-59 260 <LLD <LLD 0 CO-60 130 <LLD <LLD 0 ZN-65 260 <LLD <LLD 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS FISH NB-95 NA <LLD <LLD 0 (PCI/KG WET)
ZR-95 NA <LLD <LLD 0 CS-134 130 <LLD <LLD 0 CS-137 150 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 SEDIMENT GAMMA 2 (PCI/KG DRY) MN-54 NA <LLD NA 0 CO-58 NA <LLD NA 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT FE-59 NA <LLD NA 0 (PCI/KG DRY)
CO-60 NA <LLD NA 0 ZN-65 NA <LLD NA 0 NB-95 NA <LLD NA 0
)
ZR-95 NA <LLD NA 0 CS-134 150 <LLD NA 0 CS-137 180 158 NA 158 D-27 INDICATOR (1/2) (1/2) DRESDEN LOCK AND DAM - DOWNSTREAM 0.8 MILES NW OF SITE BA-140 NA <LLD NA 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT LA-140 NA <LLD NA (PCI/KG DRY)
AIR PARTICULATE GR-B 689 10 20 21 21 D-14 INDICATOR 0 (E-3 PCI/CU.METER) (635/636) (53/53) (53/53) CHANNAHON (5/53) (9/47) (8/53) 3.7 MILES NE OF SITE GAMMA 52 MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD CO-60 NA <LLD <LLD ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATE ZR-95 NA <LLD <LLD 0 (E-3 PCI/CU.METER)
CS-134 50 <LLD <LLD CS-137 60 <LLD <LLD 00 BA- 140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD AIR IODINE GAMMA 689 (E-3 PCI/CU.METER) 1-131 70 <LLD <LLD 0 MILK 1-131 20 I NA <LLD (PCI/LITER)
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK GAMMA 20 (PCI/LITER) MN-54 NA NA <LLD 0 CO-58 NA NA <LLD 0 FE-59 NA NA <LLD 0 CO-60 NA NA <LLD 0 ZN-65 NA NA <LLD 0 NB-95 NA NA <LLD 0 ZR-95 NA NA <LLD 0 CS-134 15 NA <LLD 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK CS-137 18 NA <LLD 0 (PCULITER)
BA-140 60 NA <LLD 0 LA-140 15 NA <LLD
,>
VEGETATION GAMMA 10 (PCI/KG WET) MN-54 NA <LLD <LLD CO-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 CO-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOF DRESDEN NUCLEAR POWER STATION, 2008 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS VEGETATION NB-95 NA <LLD <LLD 0 (PCI/KG WET)
ZR-95 NA <LLD <LLD 0 1-131 60 <LLD <LLD 0 CS-134 60 <LLD <LLD 0 CS-137 80 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 DIRECT RADIATION TLD-QUARTERLY 360 NA 23.2 22.6 27.5 D-214-1 INDICATOR 0 (MILLI-ROENTGEN/QTR.) (352/352) (8/8) (4/4)
(16/31) (19/33) (25/31) 5.0 MILES WNW
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
Intentionally left blank APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION & ANALYTICAL METHODS
TABLE B-i: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2008 Location Location Description Distance & Direction From Site A. Surface Water D-21 Illinois River at EJ&E Bridge (indicator) 1.4 miles WNW D-52 DesPlaines River, Upstream (control) 1.1 miles ESE D-57 Kankakee River at Will Road (control) 2.0 miles SE B. Ground/Well Water D-23 Thorsen Well (indicator) 0.7 miles S D-35 Dresden Lock and Dam (indicator) 0.8 miles NW C. Milk - bi-weekly / monthly D-25 Biros Farm (control) 11.3 miles SW D. Air Particulates / Air Iodine D-01 Onsite 1 (indicator) 0.8 miles NW D-02 Onsite 2 (indicator) 0.3 miles NNE D-03 Onsite 3 (indicator) 0.4 miles S D-04 Collins Road (indicator) 0.8 miles W D-07 Clay Products (indicator) 2.6 miles S D-08 Prairie Park (indicator) 3.8 miles SW D-10 Goose Lake Village (indicator) 3.5 miles SSW D-12 Lisbon (control) 10.5 miles NW D-14 Channahon (indicator) 3.7 miles NE D-45 McKinley Woods Road (indicator) 1.7 miles ENE D-53 Grundy County Road (indicator) 2.1 miles SSE D-55 Ridge Road (indicator) 4.3 miles N D-56 Wildfeather (indicator) 1.7 miles SE E. Fish D-28 Dresden Pool of Illinois River, Downstream (indicator) 0.9 miles NNW D-46 DesPlaines River, Upstream (control) 1.2 miles ESE F.Sediment D-27 Dresden Lock and Dam, Downstream (indicator) 0.8 miles NW G. Vegetation Quadrant 1 Chris Locknar 2.8 miles NE Quadrant 2 Robert Pagliano 3.2 miles SSE Quadrant 3 Jim Bloom 3.9 miles SSW Quadrant 4 J.D. Carmichael 1.6 miles NNW Control Glasscock Farm 12.8 miles ENE B-1
TABLE B-i: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2008 Location Location Description Distance & Direction From Site H. Environmental Dosimetry - TLD Inner Ring D-101-1 and -2 1.0 miles N D-102-1 and -2 1.3 miles NNE D-103-1 and -2 1.2 miles NE D-104-1 and -2 1.7 miles ENE D-105-1 and -2 1.5 miles E D-1 06-1 and -2 1.1 miles ESE D-107-1 and -2 1.4 miles SE D-108-1 and -2 1.9 miles SSE D-109-1 and -2 0.8 miles S D-1 10-3 and -4 0.9 miles SSW D-111-1 and -2 0.6 miles SW D-112a-1 and -2 0.7 miles WSW D-113-1 and -2 0.9 miles W D-114-1 and -2 0.9 miles WNW D-115-1 and -2 0.8 miles NW D-116-1 and -2 1.0 miles NNW Outer Ring D-201-1 and -2 4.8 miles N D-202-1 and -2 5.1 miles NNE D-203-1 and -2 4.7 miles NE D-204-1 and -2 5.0 miles ENE D-205-1 and -2 4.0 miles E D-206 -1 and -2 3.5 miles ESE D-207-1 and -2 4.2 miles SE D-208-1 and -2 4.9 miles SSE D-209-1 and -2 4.1 miles S D-210-1 and -2 4.9 miles SSW D-211-1 and -2 4.8 miles SW D-212-3 and -4 6.0 miles WSW D-213-1 and -2 4.5 miles W D-214-1 and -2 5.0 miles WNW D-215-1 and -2 4.8 miles NW D-216-1 and -2 4.9 miles NNW Other D-01-1 and-2 Onsite 1 0.8 miles NW D-02-1 and -2 Onsite 2 0.3 miles NNE D-03-1 and -2 Onsite 3 0.4 miles S D-04-1 and -2 Collins Road 0.8 miles W D-07-1 and -2 Clay Products 2.6 miles S D-08-1 and -2 Prairie Park 3.8 miles SW D-10-1 and -2 Goose Lake Village 3.5 miles SSW D-14-1 and -2 Channahon 3.7 miles NE D-45-1 and -2 McKinley Woods Road 1.7 miles ENE D-53-1 and -2 Grundy County Road 2.1 miles SSE D-55-1 and -2 Ridge Road 4.3 miles N D-56-1 and -2 Wildfeather 1.7 miles SE B-2
TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2008 Location Location Description Distance & Direction From Site Control D-12-1 and -2 Lisbon 10.5 miles NW B-3
TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2008 Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Sample Medium Surface Water Gamma Spectroscopy Monthly composite EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2007 Gamma emitting sample or monthly Midwest Laboratory Sampling Procedures radioisotope analysis composite from weekly Manual grab samples.
TBE, TBE-2023 Compositing of samples EIML-COMP-01 procedure for compositing water and milk samples Surface Water Gross Beta Monthly composite EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2008 Gross Alpha and/or sample or monthly Midwest Laboratory Sampling Procedures gross beta activity in various matrices composite from weekly Manual grab samples.
TBE, TBE-2023 Compositing of samples EIML-COMP-01 procedure for compositing water and milk samples Surface Water Tritium Quarterly composite of EIML-SPM-1, Environmental Incorporated 500 ml TBE, TBE-2011 Tritium analysis in monthly composite Midwest Laboratory Sampling Procedures drinking water by liquid scintillation samples. Manual TBE, TBE-2023 Compositing of samples EIML-COMP-01 procedure for compositing water and milk samples Ground Water Gamma Spectroscopy Quarterly grab samples. EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2007 Gamma emitting Midwest Laboratory Sampling Procedures radioisotope analysis Manual Ground Water Tritium Quarterly grab samples. EIML-SPM-1, Environmental Incorporated 500 ml TBE, TBE-2011 Tritium analysis in Midwest Laboratory Sampling Procedures drinking water by liquid scintillation Manual Fish Gamma Spectroscopy Samples collected twice EIML-SPM-1, Environmental Incorporated 1000 grams (wet) TBE-2007 Gamma emitting radioisotope annually via Midwest Laboratory Sampling Procedures analysis electroshocking or other Manual techniques Sediment Gamma Spectroscopy Semi-annual grab EIML-SPM-1, Environmental Incorporated 500 grams (dry) TBE, TBE-2007 Gamma emitting samples Midwest Laboratory Sampling Procedures radioisotope analysis Manual
TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2008 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Dredging Spoils Gamma Spectroscopy Annual grab samples if EIML-SPM-1, Environmental Incorporated 500 grams (dry) TBE, TBE-2007 Gamma emitting dredging occurred within Midwest Laboratory Sampling Procedures radioisotope analysis 1 mile of Dresden Manual Station during the year.
Air Particulates Gross Beta One-week of continuous EIML-SPM-1, Environmental Incorporated I filter (approximately TBE, TBE-2008 Gross Alpha and/or air sampling through Midwest Laboratory Sampling Procedures 280 cubic meters gross beta activity in various matrices glass fiber filter paper Manual weekly)
Air Particulates Gamma Spectroscopy Quarterly composite of TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting each station radioisotope analysis Env. Inc., AP-03 Procedure for compositing air particulate filters for gamma spectroscopic analysis Air Iodine Gamma Spectroscopy One- or two-week EIML-SPM-1, Environmental Incorporated 1 filter (approximately TBE, TBE-2007 Gamma emitting composite of continuous Midwest Laboratory Sampling Procedures 280 cubic meters radioisotope analysis air sampling through Manual weekly) charcoal filter Milk 1-131 Bi-weekly grab sample EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2012 Radioiodine in various May through October. Midwest Laboratory Sampling Procedures matrices Monthly all other times Manual i
61 Milk Gamma Spectroscopy Bi-weekly grab sample EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2007 Gamma emitting May through October. Midwest Laboratory Sampling Procedures radioisotope analysis Monthly all other times Manual Food Products Gamma Spectroscopy Annual grab samples. EIML-SPM-1, Environmental Incorporated 1000 grams TBE, TBE-2007 Gamma emitting Midwest Laboratory Sampling Procedures radioisotope analysis Manual TLD Thermoluminescence Quarterly TLDs EIML-SPM-1, Environmental Incorporated 2 dosimeters Global Dosimetry Dosimetry comprised of two Global Midwest Laboratory Sampling Procedures Dosimetry TLDs, with Manual two CaF 2 elements and two LiF elements in each TLD.
141-10442 114-2 11543 10wo 10542 1134 Pw ftatlolr 0-62 1104 GOOMM E8ea C46 0 lIt IbIW 10843 0 I t1-rs
- -M DOM CALCISAIN IMAM&
U TLO 0i Sediment wxrER sApMP U=AT*HS Figure B-1 Dresden Station Inner Ring TLD Locations, Fish, Water, and Sediment Location, 2008 B-6
aIIt 1 =mU1 12 I-"
N 0 S 10Mon.
0 v0 wgm.mou OWMfI =0 CALC=A= MAI"A WfUD STA=tN Urn 1,2,A3
- Air Samplin L~n~1
- Mik Lxa1Ift F=0D AM VAMPUNISA TLC. SflOUTI a TLD LocatIm RFMI TW CA=MtAM w"~ WGATM Figure B-2 Dresden Station Fixed Air Sampling and TLD Sites, Outer Ring TLD Locations and Milk Location, 2008 B-7
Intentionally left blank APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY
TABLE C-I.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA COLLECTION D-21 D-52 D-57 PERIOD 01/04/08 - 01/25 /08 15 +/- 3.1 14 +/- 2.8 6.3 +/- 1.8 02/01/08 - 02/291/08 9.6 +/- 2.5 13 +/- 3.2 8.2 +/- 2.3 03/07/08 - 03/281/08 3.7 +/- 2.1 9.7 +/- 3.3 4.8 +/- 2.5 04/04/08 - 04/25i/08 20 +/- 3.2 4.3 +/- 1.9 5,2 +/- 2.0 05/02/08 - 05/3C1/08 10 +/- 3.6 <3.4 13 +/- 4.1 06/06/08 - 06/27'/08 8.1 +/- 2.7 7.8 +/- 2.4 10 +/- 2.4 07/04/08 - 07/255/08 8.5 +/- 2.5 5.1 +/- 2.0 6.4 +/- 2.2 08/01/08 - 08/2* )/08 16 +/- 3.2 5.6 +/- 2.5 11 +/- 2.9 09/05/08 - 09/265/08 9.7 +/- 2.4 6.3 +/- 2.0 4.9 +/- 1.9 10/03/08 - 10/31 /08 13 +/- 2.6 8.5 +/- 2.3 5.1 2.0 11/07/08 - 11/281/08 8.4 +/- 2.5 4.9 +/- 2.3 < 3.0 12/05/08 - 12/2( 5/08 9.1 +/- 2.8 3.2 +/- 2.0 4.5 + 2.3 MEAN* 10.9 +/- 8.66 7.53 +/- 7.24 7.24 +/- 5.94 TABLE C-I.2 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED INTHE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION D-21 D-52 D-57 PERIOD
- 01/04/08 - 03/28/08 < 172 < 172 < 178 03/28/08 - 06/27/08 716 +/- 152 < 194 6440 +/- 706 07/04/08 - 09/26/08 < 148 < 146 < 161 10/03/08 - 12/26/08 192 +/- 118 < 179 890 +/- 165 MEAN* 454 +/- 741 3665 +/- 7849
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-1
TABLE C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-21 12/28/07 - 01/25/08 < 2 < 2 < 6 < 2 <4 < 2 < 5 < 13 < 2 < 2 < 38 < 12 01/25/08 - 02/29/08 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 8 < 2 < 2 < 16 < 5 02/29/08 - 03/28/08 <5 < 5 < 13 <6 < 11 < 5 < 8 < 8 < 5 < 6 <23 < 8 03/28/08 - 04/25/08 < 3 < 3 < 6 < 3 <6 < 3 <5 < 5 < 3 < 3 < 15 < 5 04/25/08 - 05/30/08 < 3 < 4 < 8 < 4 < 7 < 4 < 6 < 8 < 3 <4 < 20 < 6 05/30/08 - 06/27/08 < 0 < 0 < 1 < 0 < 1 < 1 < 1 < 1 < 0 < 0 < 3 < 1 06/27/08 - 07/25/08 <4 < 5 <8 < 3 <8 <4 <7 < 14 < 4 <4 < 30 < 9 07/25/08 - 08/29/08 <1 < 1 < 3 < 1 < 3 < 2 < 3 < 12 < 1 < 1 < 18 < 5 08/29/08 - 09/26/08 < 2 < 2 < 5 < 2 <4 < 2 <4 < 15 < 2 < 2 < 24 < 8 09/26/08 - 10/31/08 < 1 < 2 < 5 < 1 < 3 < 2 <3 < 8 < 1 < 1 <48 < 14 10/31/08 - 11/28/08 < 3 < 3 <7 < 3 <6 <4 <5 < 13 < 3 < 3 < 23 < 7 11/28/08 - 12/26/08 <3 < 3 < 7 <2 <7 <4 < 6 < 9 < 3 <3 <22 < 6 MEAN - - - - - - - - - - - -
D-52 01/04/08 - 01/25/08 < I <1 <2 <1 <2 <1 <2 < 15 <1 <1 < 18 < 5 02/01/08 - 02/29/08 < 4 <4 < 9 < 4 < 8 < 4 <7 < 14 < 3 < 3 < 26 < 9 03/07/08 - 03/28/08 < 6 < 5 < 12 < 7 < 9 < 6 < 10 < 10 < 6 < 6 < 27 < 7 04/04/08 - 04/25/08 < 2 <2 <4 < 2 < 4 < 2 <3 < 3 < 2 < 2 < 9 < 3 05/02/08 - 05/30/08 < 5 < 6 < 11 < 5 < 10 < 5 <9 < 14 < 5 < 7 < 26 < 9 06/06/08 - 06/27/08 <0 < 0 < 1 < 1 < 1 < 1 < 1 < 2 < 1 < 0 < 3 < 1 07/04/08 - 07/25/08 <3 <4 < 8 < 3 <6 < 4 <7 < 15 < 3 < 4 <28 < 8 08/01/08 - 08/29/08 < 1 < 1 < 2 < 1 < 2 < 1 < 2 < 9 < 1 < 1 < 13 < 3 09/05/08 - 09/26/08 < 3 < 3 < 7 < 3 < 6 < 3 <5 < 12 < 2 < 3 < 23 < 9 10/03/08 - 10/31/08 < 1 < 1 < 3 < 1 <2 < 1 < 2 < 8 < 1 < 1 <29 < 8 11/07/08 - 11/28/08 < 3 < 3 < 6 < 3 <6 < 4 < 6 < 12 < 3 < 3 < 22 < 8 12/05/08 - 12/26/08 < 3 < 3 < 6 <2 < 6 < 3 <5 < 8 < 3 < 3 < 19 <6 MEAN
TABLE C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-57 12/28/07 - 01/25/08 <1 <1 <3 <1 <2 <1 <2 < 14 <1 <1 < 20 <6 01/25/08 - 02/29/08 <3 <3 <7 <3 <6 <4 <6 < 13 <3 <3 < 26 <7
<5 <12 <6 <9 <7 <5 <6 < 21 <7 02/29/08 - 03/28/08 <6 <4 < 11 03/28/08 - 04/25/08 <2 <2 <4 <2 <4 <2 <4 <3 <2 <2 < 10 <3 04/25/08 - 05/30/08 <4 <4 <8 <5 <9 <4 <8 <8 <4 <4 < 20 <7 05/30/08 - 06/27/08 <1 <1 <1 <0 <1 <1 <1 <1 <0 <1 <3 <1 06/27/08 - 07/25/08 <3 <3 <7 <3 <6 <3 <6 < 13 <3 <3 < 24 <8 07/25/08 - 08/29/08 <1 <2 <3 <1 <3 <2 <3 < 11 <1 <1 < 17 <6 08/29/08 - 09/26/08 <2 <3 <6 <2 <5 <3 <5 <12 <2 <3 < 21 <7 09/26/08 - 10/31/08 <1 <1 <3 <1 <2 <1 <3 <9 <1 <1 < 34 < 11 10/31/08 - 11/28/08 <3 <3 <9 <4 <7 < 4 <6 < 13 <3 <4 < 28 <8 11/28/08 - 12/26/08 <4 <4 <9 <4 <8 <5 <8 <11 <4 <4 < 26 <9 MEAN
TABLE C-I1.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION D-23 D-35 PERIOD 01/11/08 389 +/- 115 < 155 02/08/08 480 +/- 122 03/14/08 525 +/- 129 04/04/08 462 +/- 128 < 170 05/09/08 458 +/- 125 06/13/08 387 +/- 120 07/11/08 354 + 125 < 175 08/07/08 336 + 117 09/12/08 488 +/- 108 10/10/08 207 +/- 118 < 174 11/07/08 333 + 129 12/12/08 422 +/- 130 MEAN 403 +/- 176 C-4
TABLES C-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-1 34 Cs-137 Ba-140 La-140 PERIOD D-23 01/11/08 <6 <6 < 12 <6 < 12 <7 <11 < 12 <6 <6
- 32 < 12 02/08/08 <2 <2 <5 <3 <5 <3 <5 <5 <2 <3 < 13 <4 03/14/08 <1 <2 <3 <1 <3 <1 <3 <4 <1 <1 <9 <3 04/04/08 <5 <7 <13 <6 < 13 <7 < 11 < 12 <6 <7 < 31 <9 05109108 <5 <6 < 14 <7 < 13 <6 < 10 < 12 <5 <6 < 35 <11 06/13/08 <5 <4 <8 <5 <9 <6 <8 <9 <5 <5 < 21 <8 07/11/08 <3 <4 <8 <3 <7 <4 <6
- 14 <3 <3
- 26 <8 08/07/08 <2 <3 <7 <2 <5 <3 <5 < 15 <3 <3
- 21 <8 09/12/08 <4 <3 <8 <4 <7 <4 <7 < 15 <3 <4 < 31 < 10 S 10/10/08 <3 <3 <7 <3 <6 <4 <6 < 13 <3 <3
- 26 <9
-, 11/07/08 <1 <1 <4 <1 <2 <2 <3 < 12 <1 <1 < 43 *15 12/12/08 <3 <3 <8 <3 <6 <3 <6 < 14 <3 <4 < 29 < 12 MEAN D-35 01/11/08 <6 <6
- 14 <6 < 12 <7 < 11 < 14 <6 <7 < 35 < 13 04/04/08 <5 <5 < 12 <7 < 11 <6 < 10 <8 <5 <6 < 25 <8 07/11/08 <4 <4 <8 <3 <8 <4 <7 < 15 <3 <4 < 29 <9 10/10/08 <3 <3 <6 <2 <5 <3 <5 < 13 <2 <3 < 24 <8 MEAN
TABLE C-II1.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD PERIOD D-28 Freshwater Drum 05/20/08 < 46 < 59 < 123 < 26 < 100 < 50 < 94 < 41 < 39 < 1350 < 337 Largemouth Bass 05/20/08 < 33 < 45 < 86 < 28 < 65 < 39 < 86 < 33 < 33 < 1040 < 321 Common Carp 10/14/08 <61 < 78 < 152 < 60 < 153 < 102 < 138 < 59 < 62 < 1590
- 280 Largemouth Bass 10/14/08 < 39 < 42 < 137 < 36 < 108 < 63 < 114 < 40 < 47 < 1010 < 209 MEAN C D-46
<ý'Channel Catfish 05/20/08 < 51 < 72 < 171 < 32
- 116 < 74
- 129 < 45 < 40 < 1570 < 346 Common Carp 05/20/08 < 37 < 41 < 98 < 40 < 74 < 54 < 82 < 31 < 39 < 931 < 285 Common Carp 10/14/08
- 36 <54
- 156 < 49 < 123 < 65
- 126 < 47 < 56 < 1010 < 388 Largemouth Bass 10/14/08 < 48 < 52 < 179 < 54 < 116 < 66 < 120 < 40 < 50 < 1380 < 365 MEAN
TABLE C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PC/KG DRY +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-27 05/16/08 < 45 < 51 < 129 < 41 < 105 < 62 < 98 < 43 158 61 < 392 < 116 10/03/08 < 44 < 62 < 135 < 35 < 119 < 61 < 91 < 38 < 48 < 818 < 269 MEAN 158 0 -
TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUP 11 PERIOD D-01 D-02 D-03 0-04 D-07 0-45 0-53 0-56 12/28/07 -0 1/04/08 26 +/- 5 33 +/- 5 28 +/- 5 35 +/- 5 38 +/-5 34 +/- 5 33 +/- 5 30 +/- 5 01/04/08 -0 1/11/08 20 +/- 4 18 +/- 4 18 +/- 4 23 +/- 5 20 +/-4 18 +/- 4 16 +/- 4 19 +/- 4 01/11/08 -0 1/18/08 36 +/- 5 30 +/- 5 36 +/- 5 40 +/- 6 29 5 38 +/- 6 32 +/- 5 36 +/- 5 01/18/08 -0 1/25/08 24 +/- 5 25 +/- 5 28 +/- 5 28 +/- 5 23 +/-5 32 +/- 5 31 +/- 5 29 +/- 5 01/25/08 -0 2/01/08 30 +/- 5 29 +/- 5 25 +/- 5 30 +/- 5 26 +/-5 21 +/- 5 27 +/- 5 30 +/- 5 02/01/08 -0 2/08/08 18 +/- 4 14 +/- 4 17 +/- 4 17 +/- 4 18 +/-4 15 +/- 4 17 +/- 4 17 +/- 4 02/08/08 -0 2/15/08 31 +/- 5 34 +/- 5 29 +/- 5 34 +/- 5 34 +/- 5 33 +/- 5 33 +/- 5 33 +/- 5 02/15/08 -0 2/22/08 25 +/- 4 21 +/- 4 23 +/- 4 24 +/- 4 22 +/- 4 26 +/- 5 24 +/- 4 23 +/- 4 02/22/08 -0 '2/29/08 20 +/- 4 15 +/- 4 12 +/- 4 19 +/- 4 16 +/-: 4 16 +/- 4 15 +/- 4 17 +/- 4 02/29/08 -0 '3/07/08 22 +/- 4 22 +/- 4 21 +/- 4 27 +/- 5 25 +/-5 24 +/- 5 22 +/- 4 26 +/- 5 03/07/08 -0 3/14/08 23 +/- 5 18 +/- 4 19 +/- 5 21 +/- 5 22 +/-5 21 +/- 5 22 +/- 5 25 +/- 5 03/14/08 0 '3/21/08 16 +/- 4 17 +/- 4 14 +/- 4 15 +/- 4 16 +/-4 15 +/- 4 16 +/- 4 15 +/- 4 03/21/08 - '3/28/08 15 +/- 4 13 +/- 4 16 +/-4 14 +/- 4 15 +/-4 11 +/-4 17 +/- 4 15 +/- 4 03/28/08 -0 4/04/08 15 +/- 4 11 +/-4 14 +/-4 11 +/-4 13 +/-4* 10 +/-4 12 +/- 4 14 +/- 4 04/04/08 0'4/11/08 16 +/- 4 18 +/-4 14 +/-4 15 +/-4 14 +/-4 16 +/-4 16 +/- 4 16 +/- 4 04/11/08 0'4/18/08 14 +/- 4 12 +/-4 12 +/-4 11 +/-4 13 +/-4 13 +/-4 12 +/- 4 11 +/-4 04/18/08.- 0'4/25/08 16 +/- 4 19 +/-5 14 +/-4 18 +/-5 16 +/-4 19 +/-5 17 +/- 4 21 +/-5 04/25/08 0 '5/02/08 19 +/- 4 22 +/-4 18 +/-4 25 +/-4 21 +/-4 20 +/-4 24 +/- 4 19 +/-4 05/02/08 0 '5/09/08 15 +/- 4 12 +/-4 17 +/-4 16 +/-4 15 +/-4 16 +/-4 15 +/- 4 15 +/-4 05/09/08 0 '5/16/08 11 +/-4 8+/-4 10 +/-4 12 +/-4 8+/-4 13 +/-4 14 +/- 4 11 +/-4 05/16/08 0 '5/23/08 11 +/-5 7+/-4 8+/-4 8+/-4 9+/-t4 9+/-4 5+/-3 9+/-4 05/23/08 0 '5/30/08 10 +/-4 10 +/-4 12 +/-4 13 +/-4 10 +/-4 10 +/-4 12 +/-4 10 +/-4 05/30/08 0 '6/06/08 12 +/-4 10 +/-4 12 +/-4 14 +/-4 12 +/-4 11 +/-4 16 +/-4 15 +/-4 06/06/08 0 '6/13/08 10 +/-4 10 +/-4 *10 +/-4 11 +/-4 12 +/- 4 13 +/-4 11 +/-4 13 +/-4 06/13/08 0 '6/20/08 9+/-4 6+/-3 14 +/-4 11 +/-4 11 +/-4 14 +/-4 9+/-4 9+/-4 06/20/08 0 6/27/08 11 +/-4 14 +/-4 15 +/-4 15 +/-4 15 +/-4 16 +/-4 20 +/-4 18 +/-4 06/27/08 0 '7/04/08 11 +/-4 9+/-4 9+/-4 10 +/- 4 10 +/-4 9+/-4 13 +/-4 11 +/-4 07/04/08 0 '7/11/08 13 +/- 4 12 +/-4 14 +/-4 12 +/- 4 14 +/-4 17 +/- 4 13 +/- 4 14 +/- 4 07/11/08 0 17/18/08 13 +/- 4 17 +/-4 17 +/-4 21 +/- 5 22 +/-5 21 +/- 5 21 +/- 5 23 +/- 5 07/18/08 0 7/25/08 13 +/- 4 15 +/-4 12 +/-7 14 +/- 4 16 +/-4 20 +/- 5 15 +/- 4 14 +/- 4 07/25/08 0 8/01/08 17 +/- 5 14 +/-4 18 +/-5 18 +/- 5 17 +/-5 16 +/- 4 16 +/- 5 23 +/- 5 08/01/08 0 8/08/08 18 +/- 4 14 +/-4 20 +/-4 20 +/- 5 15 +/-4 18 +/- 4 16 +/- 4 21 +/- 4 08/08/08 018/15/08 14 +/- 4 9+/-4 11 +/-4 12 +/- 3 14 +/-4 11 +/-4 12 +/- 4 11 +/-4 08/15/08 0 8/22/08 24 +/- 5 23 +/-5 31 +/-5 27 +/- 5 26 +/-5 29 +/-5 26 +/- 5 28 +/-5 08/22/08 0 8/29/08 20 +/- 4 18 +/-4 22 +/-5 24 +/- 5 19 +/-4 22 +/-4 25 +/- 5 28 +/-5 08/29/08 09/05/08 16 +/- 4 15 +/-4 17 +/- 4 17 +/- 4 19 +/-5 16 +/-4 24 +/- 5 21 +/-5 09/05/08 0 19/12/08 21 +/- 5 18 +/-4 19 +/- 4 17 +/- 4 19 +/-4 20 +/-5 19 +/- 4 21 +/-5 09/12/08 0 19/19/08 11 +/-4 9+/-14 13 +/- 4 8+/-4 11 +/-4 16 +/-4 15 +/- 4 15 +/- 4 09/19/08 019/26/08 37 +/-5 34 +/- 5 38 +/- 5 46 +/-6 43 +/-6 43 +/-6 46 +/- 6 48 +/- 6 09/26/08 -1 0/03/08 21 +/-5 21 +/- 5 24 +/- 5 24 +/-5 22 +/-5 24 +/-5 25 +/- 5 25 +/- 5 10/03/08 -1 0/10/08 16 +/-4 14 +/-4 15 +/- 4 17 +/-4 21 +/-4 18 +/-4 21 +/- 4 22 +/- 4 10/10/08 -1 0/17/08 21 +/-4 18 +/-4 21 +/- 4 23 +/-4 22 +/-4 26 +/-5 23 +/- 4 28 +/- 5 10/17/08 - 10/24/08 14 +/- 4 10 +/-4 16 +/- 4 9+/-4 13 +/-4 15 +/-4 15 +/- 4 15 +/- 4 10/24/08 - 10/31/08 16 +/- 4 20 +/-4 19 +/- 4 20 +/-4 18 +/-4 16 +/-4 21 +/- 4 19 +/- 4 10/31/08 - 11/07/08 31 +/- 5 39 +/-5 31 +/- 5 25 +/-5 38 +/-5 28 +/-5 36 +/- 5 31 +/- 5 11/07/08 - 11/14/08 15 +/- 4 17 +/-4 18 +/- 4 15 +/-4 20 +/-4 12 +/-4 15 +/- 4 19 +/- 4 11/14/08 - 11/21/08 14 +/- 4 13 +/-4 15 +/- 4 14 +/-4 '13 +/-4 12 +/-4 17 +/- 4 15 +/- 4 11/21/08 - 11/28/08 24 +/- 5 21 +/- 5 24 +/- 5 23 +/- 5 21 +/-5 22 +/-5 20 +/- 5 21 +/- 5 11/28/08 - 12/05/08 14 +/- 4 16 +/- 4 20 +/- 4 15 +/- 4 12 +/-4 16 +/- 4 13 +/- 4 21 +/- 5 12/05/08 - 12/12/08 23 +/- 5 24 +/- 5 24 +/- 5 21 +/- 4 17 +/-4 28 +/- 5 23 +/- 5 27 +/- 5 12/12/08 - 12/19/08 18 +/- 4 30 +/- 5 27 +/- 5 27 +/- 5 26 +/-5 29 +/- 5 29 +/- 5 30 +/- 5 12/19/08 - 12/26/08 27 +/- 5 29 +/- 5 33 +/- 5 28 +/- 5 32 +/-5 31 +/- 5 35 +/- 5 39 +/- 5 12/26/08 -0 11/02/09 16 +/- 4 28 +/- 5 25 +/- 5 25 +/- 5 24 +/-5 29 +/- 5 24 +/- 5 26 +/- 5 MEAN 18 +/-13 18 +/-16 19 +/- 14 20 +/-16 19 +/- 15 20 +/-16 20 +/-16 21 +/-16 C-8
TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP III GROUP IV PERIOD D-08 D-10 D-14 D-55 D-12 i-I UU - 01/iv/08 31 5 35+/-5 31+/-. 34 +/-5 33 +/-5 01/04/08 - 01/11/08 19+/- 4 19 +/- 5 16 +/- 19 +/- 4 19 +/- 4 01/11108 -
01/18/08 30 +/-5 32 +/- 5 35 +/- 34 +/- 5 31 +/- 5 01/18/08 - 01/25/08 27 +/-5 26 +/- 5 28 +/- 33 +/- 5 25 +/-5 01/25/08 - 02/01/08 30 +5 26 +/- 5 27 +/- 20 +/- 5 27 +/-5 02/01/08 - 02/08/08 17 4 17+/- 4 18 +/- 14 +/- 4 19+/- 4 02/08/08 - 02/15/08 34 +/-5 42 +/-6 37 +/- 35 +/- 5 36 +/-5 02/15/08 - 02/22/08 24 +/-4 22 +/-4 28 +/- 25 +/- 4 21 +/-4 02/22/08 - 02/29/08 19+/- 4 17+/- 4 16 +/- 15 +/- 4 14+/- 4 02/29/08 - 03/07/08 21 +/-4 20 +/-4 30 +/- 26 +/- 5 21 +/-4 03/07/08 - 03/14/08 20+/- 5 20 +5 19-+/- 18 +/- 4 23 +/-5 03/14/08 - 03/21/08 15 +/- 4 15 4 17 +/- 17 +/- 4 16+/- 4 03/21/08 - 03/28/08 13 +/- 4 13+/- 4 15 +/- 15 +/- 4 14+/- 4 03/28/08 - 04/04/08 11 +/-4 13 4 12 +/- 13 +/- 4 13+/- 4 04104/08 - 04/11/08 18+/- 4 16 4 16 +/- 12 +/- 4 16+/- 4 04/11/08 - 04/18/08 12+ 4 13 4 11 +/- 14 +/- 4 11 4 04/18/08 -. 04/25/08 21 -+5 21 +/-5 19++/- 20 +/- 5 18+/- 5 04/25/08 - 05/02/08 24 +/-+5 26 +/-5 24 +/- 20 +/- 4 24 +/-4 05/02/08 - 05/09/08 16+/- 4 15+/- 4 20 +/- 19 +/- 4 15 4 05/09/08 - 05/16/08 10+/- 4 11 +4 12 +/- 14 +/- 4 13+/- 4 05/16/08 - 05/23/08 10 +/- 4 12 +/-+4 8+/-+ 9+/-3 9+/-4 05/23/08 - 05/30/08 12 +/- 4 12+/- 4 12 +/- 12+/- 4 10+/- 4 05/30/08 - 06/06/08 15 +/- 4 12 4 13 +/- 6+/-4 16+/- 4 06/06/08 - 06/13/08 14 +/- 4 11 +/-4 12 _ 11+/- 4 13+/- 4 06/13/08 - 06/20/08 10 +/- 4 15+/- 4 10 + 12+/- 4 10+/- 4 06/20/08 - 06/27/08 15 +/- 4 17+/- 4 16 +/- 18+/- 4 13 4 06/27/08 - 07/04/08 15 +/- 4 14 +/-+4 12 +/- 12 _+4 14 +/-4 07/04/08 - 07/11/08 15 +/- 4 13+/- 4 16 +/- 14+/- 4 13+/- 4 07/11/08 - 07/18/08 21 +/- 5 25 +/-5 20 +/- 22 +/-5 18+/- 4 07/18/08 - 07/25/08 17 +/- 4 14+/- 4 16 +/- 18 4 18+/- 4 07/25/08 - 08/01/08 19 +/- 5 18 +/- 5 17 +/- 22 +/-5 25 +/-5 08/01/08 - 08/08/08 22 +/- 4 17 +/- 4 22 +/- 20 +/- 4 18 +/- 4 08/08/08 - 08/15/08 16 +/- 4 10 +/- 4 12 +/- 13 +/- 4 17 +/- 4 08/15/08 - 08/22/08 27 +/- 5 30 +/- 5 31 +/- 24 +/- 5 22 +/-5 08/22/08 - 08/29/08 21 +/- 4 25 +/- 5 24 +/- 22 +/- 4 24 +/-5 08/29/08 - 09/05/08 19 +/- 5 19 +/- 5 18 +/- 15 +/- 4 22 +/-5 09/05/08 - 09/12/08 22 +/- 5 21 +/- 5 21 +/- 22 +/- 5 24 +/-5 09/12/08 - 09/19/08 11 +/-4 11 +/-4 19 +/- 13 +/- 4 14+/- 4 09/19/08 - 09/26/08 44 +/-6 44 +/- 6 53 +/- 42 +/- 6 47+/- 6 09/26/08 - 10/03/08 26 +/-5 24 +/- 5 30 +/- 24 +/- 5 26 +/-5 10/03/08 - 10/10/08 14+/- 4 17 +/- 4 19 +/- 19 +/- 4 18+/- 4 10/10/08 - 10/17/08 24 +5 21 +/- 4 25 +/- 29 +/- 5 27 +5 10/17/08 - 10/24/08 14 4 13 +/- 4 17 +/- 14 +/- 4 ,18 +/- 5 10/24/08 - 10/31/08 <4 17 +/- 4 15 +/- 18 +/- 4 17_ 4 10/31/08 - 11/07/08 41 +/-6 37 +/- 5 38 +/- 37 +/- 5 33 +/-5 11/07/08 - 11/14/08 17+/- 4 16 +/- 4 17 + 17 +/- 4 19+/- 4 11/14/08 - 11/21/08 15 4 18 +/- 4 16 +/- 16 +/- 4 13+/- 4 11/21/08 - 11/28/08 23 +/-5 19 +/- 5 23 + 27 +/- 5 21 +/-5 11/28/08 - 12/05/08 18 4 17 +/- 4 18 + 18 +/- 5 21 +/-5 12/05/08 - 12/12/08 27 +/- 5 24 +/- 5 29 +/- 26 +/- 5 24 +/- 5 12/12/08 - 12/19/08 23 +/- 5 25 +/- 5 27 +/- 31 +/- 5 32 +/- 5 12/19/08 - 12/26/08 34 +/- 5 34+/-5 40 + 29 +/- 5 42 +/- 5 12/26/08 - 01/02/09 23 +/- 5 21 +/- 4 21 _ 20 +/- 4 25 +/- 5 MEAN 20 +/- 15 20 +/- 16 21 +/- 18 20 +/- 15 21 +/- 16
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-9
TABLE C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA Remember: STDEV is based on all individual results - not the STDEV of the monthly averages GROUP I - ON-SITE LOCATIONS GROUP II - NEAR-FIELD LOCATIONS GROUP III - FAR-FIELD LOCATIONS GROUP IV - CONTROL LOCATION COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN +/- COLLECTION MIN MAX MEAN+/-
2SD PERIOD 2SD PERIOD 2SD PERIOD 2SD PERIOD 12/28/07 - 02/01/08 16 35 27 +/- 12 12/28/07 - 02/01/08 19 33 27 +/- 11 12/28/07 - 02/01/08 18 27 +/- 11 12/28/07 - 02/01/U8 16 40 29 +/- 13 02/01/08 - 02/29/08 12 34 22 +/- 14 02/01/08 - 02/29/08 15 34 22 +/- 14 02/01/08 - 02/29/08 14 42 24 +/- 18 02/01/08 - 02/29/08 14 36 23 +/- 19 02/29108 - 03/28/08 13 23 18 +/- 7 02/29108 - 03/28/08 11 27 19 +/-9 02/29/08 - 03/28/08 13 30 18 +/- 9 02/29/08 - 03/28/08 14 23 18 +/- 9 03/28/08 - 05/02/08 11 22 15 +/- 6 03/28/08 - 05/02/08 10 25 16 +/-8 03/28/08 - 05/02/08 11 26 17 +/- 10 03/28/08 - 05/02/08 11 24 16 +/- 10
- 05/30/08 7 17 11 6 05/02/08 - 05/30/08 5 16 12 +/-6 05/02/08 - 05/30/08 8 20 13 +/- 7 05/02/08 - 05/30/08 9 15 11 +/- 5 05/02/08
- 06/27/08 6 15 11 +/-5 05/30/08 - 06/27/08 9 20 13 +/- 6 05/30/08 - 06/27/08 6 18 13 +/- 6 05/30/08 - 06/27/08 10 16 13 +/- 5 05/30/08 06/27/08 - 08101108 9 18 14 +6 06/27/08 - 08/01/08 9 23 16 +/- 9 06/27/08 - 08/01/08 12 25 17 +/- 7 06/27/08 - 08101/08 13 25 18 +/- 9
- 08/29/08 9 31 19 +/- 12 08101/08 - 08/29/08 11 29 20 +/- 13 08/01/08 - 08/29/08 10 31 21 +/- 12 08/01/08 - 08/29/08 17 24 20 +/- 7 08/01/08 08/29/08 - 10/03/08 9 38 21 +18 08/29/08 - 10/03/08 8 48 24 +/- 23 08/29/08 - 10/03/08 11 53 25 +/- 24 08/29/08 - 10/03/08 14 47 26 +/- 24 10/03/08 - 10/31/08 10 21 17+/- 6 10/03/08 - 10/31/08 9 28 19 +/-9 10/03/08 - 10/31/08 < 4 29 18 +/- 9 10/03/08 - 10/31/08 17 27 20 +/- 10 0
10/31/08 - 11/28/08 13 39 22 +/- 16 10/31/08 - 11/28/08 12 38 21 +/- 15 10/31/08 - 11/28/08 15 41 24 +/- 19 10/31/08 - 11/28/08 13 33 21 +/- 17 11/28/08 - 01/02/09 14 33 24+/- 11 11/28/08 - 01/02/09 12 39 25 +/- 13 11/28/08 - 01/02/09 17 40 25 +/- 13 11/28/08 - 01/02/09 21 42 29 +/- 17 12/28/07- 01/02/09 5 48 20 +/- 16 12/28/07 - 01/02/09 < 4 53 20 +/- 16 12/28/07 - 01/02/09 9 47 21 +/- 16 6 39 18 +/- 14 12/28/07 - 01/02/09
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES
TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS INAIR PARTICULATE SAMPLES COLLECTED INTHE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-01 12/28/07 03/28/08 <3 <3 < 10 <3 <7 <4 <6 <2 <3 < 68 < 25 03/28/08 06/27/08 <2 <3 <7 <3 <7 <3 <5 <3 <2 <84 < 32 06/27/08 10/03/08 <3 <6 < 21 <2 <7 <8 <11 <3 <2 < 2430 < 1130 10/03/08 01/02/09 <3 <4 <8 <3 <8 <3 <7 <4 <4 < 29 < 11 MEAN D-02 12/28/07 03/28/08 <2 <3 <5 <3 <5 <2 <5 <2 <2 < 56 < 20 03/28/08 06/27/08 <4 <5 < 15 <2 <6 <6 <7 <4 <3 < 125 < 37 06/27/08 10/03/08 <3 <7 < 26 <4 <6 <8 < 17 <3 <3 < 3520
- 849 10/03/08 01/02/09 <3 <3 <8 <3 <7 <3 <6 <3 <3 < 28 < 10 MEAN D-03 12/28/07 03/28/08 <2 <3 <7 <2 <6 <2 <5 <3 <2 < 69 < 27 03/28/08 06/27/08 <4 <4 < 10 <2 <6 <4 <8 <3 <2 < 106 < 43 06/27/08 10/03/08 <3 <7 < 23 <3 <8 <7 < 12 <2 <2 < 2650 < 800 10/03/08 01/02/09 <2 <3 <7 <3 <7 <3 <5 <3 <2 < 24 < 12 MEAN D-04 12/28/07 03/28/08 <3 <4 < 11 <3 <8 <4 <7 <3 <3 < 80 < 29 03/28/08 06/27/08 <3 <4 <9 <2 <8 <5 <7 <3 <3 < 94 < 40 06/27/08 10/03/08 <4 <7 < 25 <3 <9 <7 < 13 <3 <3 < 3670 < 1180 10/03/08 01/02/09 <3 <4 <9 <3 <8 <3 <6 <4 <3 < 41 < 12 MEAN
TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-1 34 Cs-1 37 Ba-140 La-140 PERIOD D-07 12/28/07 - 03/28/08 <3 <5 < 12 <3 <9 <4 <7 <3 <3 < 89 < 35 03/28/08 - 06/27/08 <4 <5 < 13. <2 <8 <5 <9 <4 <3 < 120 < 42 06/27/08 - 10/03/08 <2 <5 *19 <3 <7 <6 <11 <2 <2 < 2590 < 714 10/03/08 - 01/02/09 <2 <3 <7 <3 <6 <3 <5 <2 <2 < 26 < 10 MEAN D-08 12/28/07 - 03/28/08 <3 <4 <8 <2 <7 <4 <6 <3 <3 < 62 < 24 03/28/08 - 06/27/08 <3 <4 <8 <3 <7 <3 <7 <3 <3 < 116 < 39 i'
06/27/08 - 10/03/08 <3 <7 < 27 <3 <7 <8 < 12 <3 <2 < 2940 < 599 10/03/08 - 01/02/09 <2 <3 <6 <3 <7 <3 <5 <3 <3 <34 < 15 MEAN D-10 12/28/07 - 03/28/08 <3 <3 <7 <2 <6 <4 <6 <2 <2 < 49 < 29 03/28/08 - 06/27/08 <2 <3 <9 <3 <6 <3 <6 <3 <2 < 83 < 34 06/27/08 - 10/03/08 <3 <4 < 21 <2 <7 <6 < 12 <2 <2 < 3030 < 1150 10/03/08 - 01/02/09 <3 <2 <7 <4 < 5 <3 <6 <2 <2 < 32 < 10 MEAN D-12 12/28/07 - 03/28/08 <3 <4 <9 <2 <8 <4 <7 <4 <3 < 99 < 22 03/28/08 - 06/27/08 <2 <4 <7 <3 <8 <5 <8 <4 <3 < 110 < 38 06/27/08 - 10/03/08 <3 <7 < 34 <3 < 10 <9 < 14 <4 <3 < 3310 < 1310 10/03/08 - 01/02/09 <3 <3 < 10 <3 <8 <4 <9 <4 <3 < 42 < 11 MEAN
TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-1 34 Cs-137 Ba-140 La-140 PERIOD D-14 12/28/07 - 03/28/08 <2 <3 <6 <3 <5 <3 <6 <2 <2 < 57 28 03/28/08 - 06/27/08 <3 <3 <7 <3 <4 <3 <6 <2 <2 < 74 18 06/27/08 - 10/03/08 <3 <6 < 18 <2 <8 <7 < 14 <3 <2 < 2900 1100 10/03/08 - 01/02/09 <3 <3 <6 <3 <7 <3 <6 <4 <3 < 29 14 MEAN D-45 12/28/07 - 03/28/08 <2 <3 <8 <3 <5 <3 <5 <3 <2 < 61 < 23 03/28/08 - 06/27/08 <3 <5 < 10 <4 <9 <4 <9 <4 <3 < 132 < 61 06/27/08 - 10/03/08 <3 <5 < 23 <3 <7 <6 < 12 <2 <2 < 2470 < 1060 10/03/08 - 01/02/09 <3 <3 <8 <3 <7 <4 <6 <3 <3 < 33
- 13 MEAN D-53 12/28/07 - 03/28/08 <2 <3 <8 <2 <7 <3 <5 <3 <2 < 60 < 31 03/28/08 - 06/27/08 <3 <3 < 10 <3 <6 <4 <7 <3 <3 < 84 < 36 06/27/08 10/03/08 <2 <7 < 23 <1 <6 <7 < 13 <3 <3 < 2650 < 1140 10/03/08 - 01/02/09 <3 <4 <6 <4 < 10 <3 <7 <4 <3 < 42 < 18 MEAN D-55 12/28/07 - 03/28/08 <3 <4 < 11 <3 <9 <4 <8 <4 <3 < 76 < 52 03/28/08 - 06/27/08 <2 <4 <6 <3 <7 <4 <5 <3 <3 < 86 < 33 06/27/08 - 10/03/08 <3 <5 < 18 <2 <6 <6 < 12 <3 <2 < 2330 < 1300 10/03/08 - 01/02/09 <3 <3 <7 <2 <6 <3 <5 <2 <2 < 28 < 12 MEAN
TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-1 34 Cs-137 Ba-140 La-140 PERIOD D-56 12/28/07 - 03/28/08 <3 <4 <8 <4 <9 <5 <9 <3 <4 < 107 < 34 03/28/08 - 06/27/08 <3 <4 < 13 <3 <8 <5 <8 <3 <3 < 109 < 63 06/27/08 - 10/03/08 <3 <5 < 28 <2 <6 <6 <11 <2 <2 < 3020 < 1040 10/03/08 - 01/02/09 <3 <3 <7 <3 <8 <4 <5 <4 <3 < 43 < 13 MEAN
TABLE C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA GROUP I I GROUP II COLLECTION PERIOD D-01 D-02 D-03 D-04 D-07 D-45 D-53 D-56 12/28/07 -01/04/08 < 25 < 45 < 45 < 45 < 45 < 62 < 60 < 58 01/04/08 - 01/11/08 < 15 < 30 < 30 < 31 < 30 < 30 < 29 < 29 01/11/08 - 01/18/08 < 21 < 39 < 39 < 38 < 39 < 47 < 47 < 47 01/18/08 -01/25/08 < 11 < 18 < 18 < 18 < 19 < 20 < 20 < 20 01/25/08 -02/01/08 < 19 < 34 < 34 < 33 < 34 < 59 < 56 < 58 02/01/08 -02/08/08 < 26 < 44 < 44 < 43 < 44 < 45 < 44 < 44 02/08/08 -02/15/08 < 52 < 28 < 52 < 52 < 52 < 63 < 63 < 66 02/15/08 -02/22/08 < 23 < 23 < 16 < 23 < 24 < 22 < 22 < 22 02/22/08 -02/29/08 < 12 < 20 < 20 < 20 < 20 < 27 < 27 < 27 02/29/08 -03/07/08 < 22 < 22 < 22 < 13 < 13 < 31 < 30 < 30 03/07/08 -03/14/08 < 11 < 17 < 17 < 17 < 17 < 20 < 19 < 19 03/14/08 -03/21/08 < 41 < 41 < 41 < 41 < 27 < 47 < 46 < 46 03/21/08 -03/28/08 < 21 < 38 < 38 < 38 < 38 < 36 < 56 < 56 03/28/08 -04/04/08 < 20 < 20 < 20 < 20 < 23 < 21 < 20 < 20 04/04/08 -04/11/08 < 37 < 50 < 50 < 51 < 50 < 41 < 40 < 40 04/11/08 -04/18/08 < 32 < 47 < 48 < 47 < 46 < 62 < 65 < 63 04/18/08 -04/25/08 < 29 < 39 < 39 < 39 < 39 < 43 < 36 < 36 04/25/08 -05/02/08 < 22 < 36 < 36 < 36 < 37 < 45 < 43 < 43 05/02/08 -05/09/08 < 17 < 28 < 28 < 28 < 28 < 33 < 35 < 35 05/09/08 -05/16/08 < 22 < 52 < 52 < 52 < 54 < 39 < 34 < 34 05/16/08 -05/23/08 < 26 < 27 < 27 < 27 < 26 < 65 < 64 < 64 05/23/08 -05/30/08 < 18 < 30 < 29 < 29 < 31 < 29 < 46 < 47 05/30/08 -06/06/08 < 22 < 40 < 40 < 40 < 41 < 56 < 55 < 55 06/06/08 -06/13/08 < 15 < 24 < 24 < 24 < 25 < 34 < 35 < 35 06/13/08 -06/20/08 < 27 < 45 < 45 < 45 < 45 < 67 < 60 < 60 06/20/08 -06/27/08 < 23 < 37 < 37 < 37 < 37 < 40 < 45 < 45 06/27/08 -07/04/08 < 43 < 65 < 65 < 65 < 65 < 63 < 63 < 63 07/04/08 -07/11/08 < 17 < 28 < 28 < 28 < 28 < 36 < 38 < 38 07/11/08 -07/18/08 < 17 < 28 < 28 < 28 < 28 < 45 < 43 < 43 07/18/08 -07/25/08 < 17 < 10 < 33 < 17 < 18 < 17 < 15 < 15 07/25/08 -08/01/08 < 14 < 25 < 25 < 25 < 24 < 28 < 28 < 28 08/01/08 -08/08/08 < 32 < 54 < 54 < 69 < 54 < 51 < 50 < 50 08/08/08 -08/15/08 < 17 < 30 < 30 < 26 < 31 < 45 < 44 < 44 08/15/08 -08/22/08 < 23 < 43 < 45 < 43 < 45 < 47 < 67 < 67 08/22/08 -08/29/08 < 26 < 48 < 48 < 48 < 48 < 70 < 47 < 46 08/29/08 -09/05/08 < 31 < 56 < 56 < 56 < 56 < 59 < 66 < 66 09/05/08 -09/12/08 < 29 < 53 < 53 < 53 < 52 < 44 < 49 < 49 09/12/08 -09/19/08 < 37 < 62 < 62 < 62 < 62 < 50 < 52 < 52 09/19/08 -09/26/08 < 18 < 35 < 34 < 33 < 34 < 28 < 43 < 43 09/26/08 -10/03/08 < 34 < 62 < 62 < 62 < 63 < 52 < 60 < 60 10/03/08 -10/10/08 < 35 < 64 < 64 < 63 < 62 < 52 < 55 < 55 10/10/08 -10/17/08 < 16 < 29 < 29 < 29 < 29 < 33 < 50 < 52 10/17/08 -10/24/08 < 43 < 23 < 42 < 43 < 42 < 47 < 45 < 45 10/24/08-10/31/08 < 24 < 44 < 44 < 43 < 44 < 52 < 70 < 69 10/31/08 -11/07/08 < 23 < 42 < 43 < 43 < 44 < 66 < 63 < 63 11/07/08-11/14/08 < 35 < 69 < 69 < 69 < 69 < 60 < 60 < 60 11/14/08 -11/21/08 < 23 < 41 < 41 < 41 < 39 < 41 < 64 < 64 11/21/08 -11/28/08 < 24 < 35 < 35 < 35 < 36 < 40 < 40 < 40 11/28/08-12/05/08 < 43 < 64 < 64 < 64 < 61 < 62 < 60 < 60 12/05/08-12/12/08 < 35 < 63 < 63 < 63 < 63 < 62 < 63 < 63 12/12/08 - 12/19/08 < 26 < 47 < 47 < 47 < 47 < 56 < 63 < 63 12/19/08 - 12/26/08 < 39 < 67 < 65 < 64 < 63 < 69 < 60 < 60 12/26/08 - 01/02/09 < 36 < 70 < 65 < 65 < 67 < 56 < 50 < 50 MEAN - - - - - - - -
C-15
TABLE C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP III IGROUP IV COLLECTION PERIOD D-08 0-1 0 D-14 D-55 0-1 2 12I2b/U t - U/U4/U8 < 32 *<32 < 31 <63 *<32 01/04/08 -01/11/08
- 31
- 33
- 31
- 30
- 31 01/11/08 -01/18/08 < 40
- 40
- 40
- 47
- 40 01/18/08 -01/25/08
- 22
- 21
- 22
- 20
- 22 01/25/08 -02/01/08 *<34
- 34
- 35
- 58
- 34 02/01/08 - 02/08/08
- 40
- 40
- 40
- 45
- 40 02/08/08 -02/15/08
- 51
- 53
- 53
- 63
- 53 02/15/08 -02/22/08
- 64
- 62
- 64
- 22
- 64 02/22/08 -02/29/08
- 32
- 32
- 32
- 28
- 32 02/29/08 -03/07/08
- 30
- 29
- 30
- 31
- 30 03/07/08 - 03/14/08
- 19
- 19
- 19
- 20
- 19 03/14/08 - 03/21/08
- 52
- 52
- 52
- 47
- 52 03/21/08 - 03/28/08
- 28
- 36
- 36
- 55
- 35 03/28/08 - 04/04/08
- 14
- 22
- 22
- 21
- 22 04/04/08 -04/11/08
- 38
- 38
- 38
- 41
- 38 04/11/08 -04/18/08
- 63
- 35
- 62
- 64
- 62 04/18/08 -04/25/08
- 25
- 40
- 43
- 38
- 44 04/25/08 -05/02/08
- 44
- 42
- 43
- 45
- 43 05/02/08 -05/09/08
- 34
- 34
- 20
- 33
- 33 05/09/08 -05/16/08
- 38
- 38
- 39
- 36
- 39 05/16/08 -05/23/08
- 25
- 25
- 25
- 61
- 25 05/23/08 -05/30/08
- 17
- 28
- 29
- 49
- 29 05/30/08 -06/06/08
- 38
- 38
- 38
- 56
- 38 06/06/08 -06/13/08
- 23 *<34
- 34
- 36
- 34 06/13/08 - 06/20/08 < 41
- 67
- 67
- 61
- 67 06/20/08 -06/27/08 < 24
- 39
- 40
- 46
- 40 06/27/08 -07/04/08
- 35
- 63
- 63
- 64
- 63 07/04/08 -07/11/08
- 20
- 36
- 36
- 39
- 36 07/11/08 -07/18/08
- 23
- 45
- 45
- 44
- 45 07/18/08 -07/25/08 <9
- 17
- 17
- 16
- 17 07/25/08 -08/01/08
- 14
- 28
- 28
- 28
- 28 08/01/08 -08/08/08 < 47
- 47
- 48
- 51
- 48 08/08/08 -08/15/08
- 28
- 28
- 28
- 45
- 28 08/15/08 -08/22/08
- 38
- 47
- 47
- 69
- 47 08/22/08 -08/29/08 < 46
- 69
- 70
- 47
- 70 08/29/08 - 09/05/08
- 46
- 57
- 59
- 68
- 58 09/05/08 - 09/12/08
- 34
- 43
- 44
- 50
- 43 09/12/08 - 09/19/08
- 28
- 50
- 50
- 53
- 50 09/19/08 - 09/26/08
- 21
- 27
- 28
- 44
- 27 09/26/08 - 10/03/08 < 42
- 53
- 52
- 61
- 53 10/03/08 - 10/10/08
- 62
- 64
- 61
- 52
- 62 10/10/08 - 10/17/08
- 25
- 32
- 33
- 55
- 30 10/17/08 - 10/24/08
- 43
- 46
- 47
- 44
- 46 10/24/08 - 10/31/08
- 41
- 55
- 52
- 65
- 52 10/31/08 - 11/07/08 < 47
- 47
- 47
- 66
- 47 11/07/08 - 11/14/08
- 52
- 52
- 52
- 60
- 52 11/14/08 - 11/21/08
- 33
- 41
- 41
- 65
- 41 11/21/08 - 11/28/08
- 22
- 40
- 40
- 41
- 40 11/28/08 - 12/05/08
- 69
- 70
- 69
- 67
- 69 12/05/08 - 12/12/08
- 36
- 60
- 60
- 64
- 60 12/12/08 - 12/19/08 < 44
- 55
- 56
- 64
- 56 12/19/08 - 12/26/08
- 38
- 69
- 70
- 61
- 70 12/26/08 - 01/02/09 *<44
- 55
- 56
- 52
- 55 MEAN C-16
TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION CONTROLIFARM PERIOD D-25 01/03/08 < 0.6 02/01/08 < 0.8 03/06/08 < 0.5 04/03/08 < 0.8 05/01/08 < 0.7 05/15/08 < 0.7 05/29/08 < 0.8 06/12/08 < 0.7 06/26/08 < 0.7 07/10/08 < 0.7 07/24/08 < 0.7 08/06/08
- 0.8 08/21/08 < 0.8 09/04/08
- 0.7 09/18/08 < 0.9 10/02/08 < 0.8 10/16/08 < 0.8 10/30/08 < 0.9 11/13/08 < 0.7 12/04/08 < 0.9 MEAN C-17
TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-25 01/03/08 <7 <7 < 13 <7 < 18 <9 < 14 <6 <9 < 31 < 10 02/01/08 <5 <5
- 12 <7 < 13 <6 < 10 <5 <6 <34 < 12 03/06/08 <5 <5 < 12 <6 < 12 <6 <7 <5 <6 < 26 <9 04/03/08 <5 <5 *12 <5 < 13 <5 <8 <5 <5 < 24 <8 05/01/08 <6 <7 < 16 <8 < 17 <7 < 12 <8 <7 < 43 < 11 05/15/08 <7 <7 < 15 <6 < 15 <6 < 12 <6 <6 < 37 < 13 05/29/08 <4 <5 < 11 <4 < 10 <5 <9 <5 <5 < 34 <9 06/12/08 <6 <7 < 16 <6
- 16 <6 < 12 <6 <6 < 40 < 12 06/26/08 <4 <5 < 11 <5 < 11 <5 <9 <4 <5 < 33 < 10 00 07/10/08 <7 <7 < 16 <6 <17 <7 < 14 <6 <7 < 37 < 13 07/24/08 <3 <3 <8 <3 <6 <4 <6 <3 <3 < 43 < 10 08/06/08 <7 <7 <17 <6 < 16 <6 < 13 <5 <7 < 46 <9 08/21/08 <4 <4 <9 <5 <9 <5 <8 <3 <4 < 24 <6 09/04/08 <6 <7 < 17 <6 < 12 <7 < 13 <5 <6 < 52
- 15 09/18/08 <5 <5
- 14 <4 < 11 <6 <9 <4 <4 < 46 < 12 10/02/08 <2 <3 <8 <2 <5 <3 <6 <2 <2 < 51 < 14 10/16/08 <4 <5 < 10 <5 < 10 <5 <9 <4 <5 <44 < 13 10/30/08 <2 <2 <6 <2 <3 <2 <4 <1 <2 < 46 < 15 11/13/08 <1 <2 <5 <1 <3 <2 <3 <1 <1 < 47 < 13 12/04/08 <6 <6 < 14 <5 < 11 <6 <9 <5 <5 < 31 <4 MEAN
TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD U-k,UIN I MUL Cabbage 09/12/08 < 14 < 17 < 38 < 20 < 30 < 17 < 29 < 60 < 13 < 15 <116 <34 Carrots 09/12/08 < 13 < 12 < 34 < 11 < 26 < 14 < 24 < 50 < 12 < 14 < 104 < 24 MEAN D-QUAD 1 Broccoli 09/12/08 < 13 < 13 < 28 < 14 < 33 < 14 < 25 < 55 < 13 < 14 < 96 < 34 Potatoes 09/12/08 < 14 < 16 < 41 < 15 < 38 < 16 < 24 < 55 < 13 < 13 < 110 < 28
(-I MEAN D-QUAD 2 Beet greens 09/12/08 < 12 < 13 < 31 < 12 <<28 < 13 <23 <49 < 11 < 23 < 100 < 22 Beets 09/12/08 < 15 < 17 < 42 < 14 < 31 < 16 < 26 < 59 < 13 < 16 < 123 < 36 MEAN D-QUAD 3 Cabbage 09/12/08 < 10 < 11 < 24 < 8 <24 < 11 < 19 <40 <9 < 9 < 77 < 21 Sweet potatoes 09/12/08 < 11 < 10 < 23 < 10 < 20 < 12 < 17 <41 <8 < 10 < 70 < 20 MEAN D-QUAD 4 Cabbage 09/12/08 <9 < 10 < 24 <9 < 22 < 10 < 15 <40 <8 < 10 < 71 < 25 Onions 09/12/08 < 7 < 12 < 32 < 10 < 20 < 14 < 19 <45 < 9 < 15 < 84 < 31 MEAN
TABLE C-IX.1 QUARTERLY TLD RESULTS FOR DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR-JUN JUL - SEP OCT-DEC CODE +/- 2 S.D.
u-uI-1 23.0 +/- 2.8 24 21 24 D-01-2 22.5 +/- 2.6 24 22 21 23 D-02-1 24.0 +/- 2.8 25 24 22 25 D-02-2 23.8 +/- 3.8 25 24 21 25 D-03-1 20.8 +/- 3.4 20 21 19 23 D-03-2 20.8 +/- 3.4 21 20 19 23 D-04-1 23.3 +/- 3.0 25 22 22 24 D-04-2 23.0 +/- 2.8 25 22 22 23 D-07-1 22.0 +/- 1.6 23 22 21 22 D-07-2 23.3 +/- 5.0 26 23 20 24 D-08-1 23.3 +/- 1.9 24 23 22 24 D-08-2 24.3 +/- 3.0 25 25 22 25 D-10-1 25.0 +/- 4.3 25 23 24 28 D-10-2 22.5 +/- 3.8 25 21 21 23 D-12-1 24.3 +/- 12 23 21 20 33 D-12-2 21.0 +/- 3.7 23 20 19 22 D-14-1 21.3 +/- 3.4 22 21 19 23 D-14-2 21.5 +/- 2.0 22 22 20 22 D-45-1 24.5 +/- 2.6 25 24 23 26 D-45-2 25.8 +/- 4.1 28 26 23 26 D-53-1 19.0 +/- 2.8 20 20 17 19 D-53-2 19.0 +/- 4.3 21 19 16 20
.D-55-1 25.3 +/- 3.4 25 27 23 26 D-55-2 24.5 +/- 5.3 28 23 22 25 D-56-1 20.3 +/- 4.1 23 20 18 20 D-56-2 20.8 +/- 1.9 21 20 20 22 D-101-1 24.0 +/- 2.8 25 25 22 24 D-101-2 23.5 +/- 6.2 25 27 20 22 D-102-1 26.3 +/- 3.8 29 25 25 26 D-102-2 25.8 +/- 6.6 28 24 22 29 D-103-1 23.3 +/- 5.5 26 25 20 22 D-103-2 24.8 +/- 5.3 27 23 22 27 D-104-1 25.0 +/- 2.3 26 24 26 24 D-104-2 23.5 +/- 3.8 26 22 22 24 D-105-1 24.0 +/- 4.0 25 25 21 25 D-105-2 23.0 +/- 2.8 24 23 21 24 D-106-1 21.0 +/- 3.3 23 21 19 21 D-106-2 20.0 +/- 4.3 23 20 18 19 D-107-1 19.5 +/- 2.6 21 19 18 20 D-107-2 20.0 +/- 2.8 21 20 18 21 D-108-1 25.0 +/- 4.3 28 24 23 25 D-108-2 22.5 +/- 3.8 23 21 21 25 D-109-1 25.0 +/- 4.6 27 23 23 27 D-109-2 25.3 +/- 5.3 27 23 23 28 D-110-3 26.8 +/- 5.0 27 26 24 30 D-110-4 25.8 +/- 6.6 28 26 21 28 D-111-1 26.3 +/- 5.5 28 25 23 29 D-111-2 23.5 +/- 2.0 24 24 22 24 D-113-1 20.5 +/- 2.6 22 20 19 21 D-113-2 22.3 +/- 5.3 26 22 21 20 D-114-1 22.0 +/- 4.3 22 21 20 25 D-114-2 21.5 +/- 3.5 23 22 19 22 D-115-1 23.3 +/- 4.4 24 22 21 26 C-20
TABLE C-IX.1 QUARTERLY TLD RESULTS FOR DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC D-115-2 23.8 +/- 3.4 24 23 22 26 D-116-1 26.0 +/- 4.3 29 25 26 24 D-116-2 25.0 +/- 5.2 26 24 22 28 D-201-1 27.3 +/- 5.3 27 26 25 31 D-201-2 26.3 +/- 4.4 29 25 24 27 D-202-1 25.8 +/- 6.6 28 24 22 29 D-202-2 22.3 +/- 1.9 23 22 21 23 D.;203-1 23.5 +/- 4.2 26 24 21 23 D-203-2 22.5 +/- 5.0 26 22 20 22 D-204-1 21.3 +/- 4.1 24 21 19 21 D-204-2 20.8 +/- 3.0 22 22 19 20 D-205-1 24.5 +/- 4.2 24 25 22 27 D-205-2 24.8 +/- 5.3 27 23 22 27 D-206-1 23.8 +/- 3.4 26 22 24 23 D-206-2 24.5 +/- 4.2 27 24 22 25 D-207-1 21.3 +/- 1.9 22 22 20 21 D-207-2 22.3 +/- 4.1 25 22 20 22 D-208-1 20.5 +/- 4.2 23 20 18 21 D-208-2 20.0 +/- 2.8 21 20 18 21 D-209-1 20.5 +/- 4.8 22 23 18 19 D-209-2 20.0 +/- 1.6 21 20 19 20 D-210-1 24.0 +/- 3.3 24 24 22 26 D-210-2 24.0 +/- 3.7 26 23 22 25 D-211-1 25.0 +/- 4.3 28 24 23 25 D-211-2 24.0 +/- 4.3 27 23 22 24 D-212-3 20.8 +/- 2.5 21 21 19 22 D-212-4 21.5 +/- 4.2 24 21 19 22 D-213-1 21.8 +/- 4.4 23 21 19 24 D-213-2 19.8 +/- 5.0 23 19 17 20 D-214-1 27.5 +/- 5.0 27 27 25 31 D-214-2 26.8 +/- 5.7 30 27 23 27 D-215-1 26.8 +/- 5.0 30 26 24 27 D-215-2 25.8 +/- 4.1 27 24 24 28 D-216-1 23.0 +/- 4.3 26 23 21 22 D-216-2 25.5 +/- 5.0 26 26 22 28 D-112A-1 22.0 +/- 3.3 22 22 20 24 D-112A-2 22.3 +/- 3.4 24 23 20 22 C-21
TABLE C-IX.2 MEAN QUARTERLY TLD RESULTS FOR THE INNER RING, OUTER RING, OTHER AND CONTROL LOCATIONS FOR DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER STANDARD DEVIATIONS OF THE STATION DATA COLLECTION INNER RING OUTER RING OTHER CONTROL PERIOD +/- 2 S.D.
JAN-MAR 25.1 +/- 4.7 25.2 +/- 5.2 23.8 +/- 4.4 23.0 +/- 0.0 APR-JUN 23.1 +/- 4.0 23.0 +/- 4.2 22.4 +/- 4.0 20.5 +/- 1.4 JUL-SEP 21.4 + 4.2 21.1 +/-4.5 20.8 +/- 4.0 19.5 +/- 1.4 OCT-DEC 24.4 +/- 5.8 24.2 +/- 6.6 23.5 +/- 4.2 27.5 +/- 15.6 TABLE C-IX.3
SUMMARY
OF THE AMBIENT DOSIMETRY PROGRAM FOR DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN ANALYZED MINIMUM MAXIMUM +/- 2 S.D.
INNER RING 128 18 30 23.5 +/- 5.5 OUTER RING 128 17 31 23.4 +/- 6.0 OTHER 96 16 28 22.6 +/- 4.8 CONTROL 8 19 33 22.6 +/- 8.9 INNER RING STATIONS - D-101-1, D-101-2, D-102-1, D-102-2, D-103-1, D-103-2, D-104-1, D-104-2, D-105-1, D-105-2, D-106-1, D-106-2, D-107-1, D-107-2, D-108-1, D-108-2, D-109-1, D-109-2, D-110-3, D-110-4, D-111-1, D-111-2, D-112A-1, D-112A-2, D-113-1, D-113-2, D-114-1, D-114-2, D-115-1, D-115-2, D-116-1, D-116-2 OUTER RING STATIONS - D-201-1, D-201-2, D-202-1, D-202-2, D-203-1, D-203-2, D-204-1, D-204-2, D-205-1, D-205-2, D-206-1, D-206-2, D-207-1, D-207-2, D-208-1, D-208-2, D-209-1, D-209-2, D-210-1, D-210-2, D-211-1, D-211-2, D-212-3, D-212-4, D-213-1, D-213-2, D-214-1, D-214-2, D-215-1, D-215-2, D-216-1, D-216-2 OTHER STATIONS - D-01-1, D-01-2, D-02-1, D-02-2, D-03-1, D-03-2, D-04-1, D-04-2, D-07-1, D-07-2, D-08-1, D-08-2, D-10-1, D-10-2, D-14-1, D-14-2, D-45-1, D-45-2, D-53-1, D-53-2, D-55-1, D-55-2, D-56-1, D-56-2 CONTROL STATIONS --D-12-1, D-12-2 C-22
Intentionally left blank C-23
FIGURE C-1 SURFACE WATER - GROSS BETA - STATIONS D-51 and D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-51 Dresden Lock & Dam 10.0 0.0 -
01-01-00 12-31-00 12-31-01 12-31-02 12-31-=3 12-30-04 D-52 (C) DesPlaines River 14.0 12.0 10.0 8.0 6.0 4,0 2.0 0.0 4-01-01-00 12-31-0O 12-31-01 12-31-02 12-31-03 12-30-04 C-24
FIGURE C-1 (cont.)
SURFACE WATER - GROSS BETA - STATIONS D-51 and D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2008 D-51 Dresden Lock & Dam 12.0 1 10.0 1 8.0
-J 6.0 0.
4.0 1' 2.0 0.0 I 01-27-05 09-04-05 04-12-06 11-18-06 06-26-07 D-52 (C) DesPlaines River 16.0 14.0 12.0 10.0
.J U 8.0 I
0.
6.0 4.0 2.0 00 .1.
01-27-05 11-10-05 08-24-06 06-07-07 03-20-08 01-01-09 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 D-51 LOCATION REMOVED FROM PROGRAM JUNE 29, 2007 AND REPLACED WITH D-21 C-25
FIGURE C-2 SURFACE WATER - GROSS BETA - STATION D-54 (C)
COLLECTED IN THE VICINITY OF DNPS, 2002 - 2004 D-54 (C) Kankakee River 14.0 -
12.0+
10i +
8.04 6,0 +
4.0O 2,0 0.01 I I I 01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 C-26
FIGURE C-2 (cont.)
SURFACE WATER - GROSS BETA - STATION D-54 (C) and D-57 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2008 D-54 (C) Kankakee River 14.0 12.0 10.0 8.0 1 C.
6.0 4.0 2.0 0.0 I I I 01-27-05 09-04-05 04-12-06 11-18-06 06-26-07 D-57 (C) Kankakee River 32 28 24
,-5 20
- 0. 16 12 8
4 o *I-07-28-06 03-07-07 10-15-07 05-24-08 01-01-09 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 D-54 LOCATION REMOVED FROM PROGRAM JUNE 28, 2007 AND REPLACED WITH D-57 C-27
FIGURE C-3 SURFACE WATER - GROSS BETA - STATION D-21 COLLECTED IN THE VICINITY OF DNPS, 2007 - 2008 D-21 Illinois River 30 25 20
-J 15 o,.
10 5
0 4-04-27-07 08-28-07 12-29-07 04-30-08 08-31-08 01-01-09 D-21 PLACED INTO SERVICE ON MARCH 30, 2007, REPLACED D-51 C-28
FIGURE C-4 SURFACE WATER - TRITIUM - STATIONS D-51 and D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-51 Dresden Lock & Dam 2000 1600-1400 S1000 am0 400 04 I I I I 0 i i i i 4 i 0"1-00 1"t-00 1241-01 12-34-w ta-31-03 12ý30-04 D-52 (C) Des Plalnes River 400-100 0
.-mm It ..~
0.1-0t-co 1"11-60 1241-01 12-11-M 12-:31-03 1Z30-04 C-29
FIGURE C-4 (cont.)
SURFACE WATER - TRITIUM - STATIONS D-51 and D-52 (C) COLLECTED INTHE VICINITY OF DNPS, 2005 - 2008 D-51 Dresden Lock & Dam 2000 1800 1600 1400 1200 1000 800 600 400 200 0
03-31-05 12-29-05 09-28-06 06-28-07 D-52 (C) Des Plaines River 600 500 400
-J 300 200 100 0
03-31-05 12-30-05 09-30-06 07-01-07 03-31-08 12-30-08 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 D-51 LOCATION REMOVED FROM PROGRAM JUNE 29, 2007 AND REPLACED WITH D-21 C-30
FIGURE C-5 SURFACE WATER - TRITIUM - STATION D-54 (C)
COLLECTED IN THE VICINITY OF DNPS, 2002 - 2004 0-54 (C) Kankakee River 3w+
200+4
'100-
%,A,,
04 VIV-011-M 41"1-00 12-31-01 12-31021 12-0-"4 C-31
FIGURE C-5 (cont.)
SURFACE WATER - TRITIUM - STATION D-54 (C) AND D-57 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2008 D-54 (C) Kankakee River 800 700 600 500
-J 400 300 200 100 0
3/31/2005 12/30/2005 9/30/2006 7/1/2007 Location shared with Braidwood Station (BD-10).
D-57 (C) Kankakee River 7000 6000 5000 4000 C.)
" 3000 2000 1000 0
12-20-06 05-18-07 10-14-07 03-11-08 08-07-08 01-03-09 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 D-57 NEW STATION JULY 24, 2006. REPLACED D-54 ON JUNE 28, 2007 C-32
FIGURE C-6 SURFACE WATER - TRITIUM - STATION D-21 COLLECTED IN THE VICINITY OF DNPS, 2007 - 2008 D-21 Illinois River 800 700 600 500
,-
400 a,.
300 200 100 0+
06-29-07 11-14-07 03-31-08 08-16-08 01-01-09 D-21 REPLACED D-51JUNE 29, 2007 C-33
FIGURE C-7 GROUND WATER - TRITIUM - STATIONS D-23 and D-35 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-23 Thorsen low0 -r 80O +
/
600 4O0 /
200 +
n!
0 4 12-31-00 12-31-01 12-31-02 12-31-)3 12-30-04 D-35 Dresden Lock and Dam 400 3o +
200+
!9100*
/
-100+
t200
- I V 01-01 -00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 C-34
FIGURE C-7 (cont.)
GROUND WATER - TRITIUM - STATIONS D-23 and D-35 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2008 D-23 Thorsen IIuu'J 600
-I 0.
400 200 0 1 3/31/2005 12/30/2005 9/30/2006 7/l/2007 3/31/2008 12/30/2008 D-35 Dresden Lock and Dam 400 350 300 250
-.
200 -
100 -
50 0
03-31-05 12-30-05 09-30-06 07-01-07 03-31-08 12-30-08 DUE TO VENDOR CHANGE IN 2005,< VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-35
FIGURE C-8 AIR PARTICULATES - GROSS BETA - STATIONS D-01 and D-02 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D41 Onsite, Station i 1cuQ I1 0' I - --
0101-0 12 -a2 12.3i-Cd, 2ý30ý44
ýD-02Qnsite Staition 2 No s~rr~pI~
~
0Lf- tGIW t21-ll 144 C-36
FIGURE C-8 (cont.)
AIR PARTICULATES - GROSS BETA - STATIONS D-01 and D-02 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2008 D-01 Onsite Station 1 50.0 40.0 30.0 0.
CL 20.0 Lu 0
10.0 0.0 1 01-07-05 09-07-05 05-08-06 01-06-07 09-06-07 05-06-08 01-04-09 D-02 Onsite Station 2 50.0 40.0 C.)
30.0 Q.
uJ 20.0 0
10.0 0.0 09-23-05 03-13-06 08-31-06 02-18-07 08-08-07 01-26-08 07-15-08 01-02-09 D-02 No samples; power was restored on 09-16-05.
DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C-37
FIGURE C-9 AIR PARTICULATES - GROSS BETA - STATIONS D-03 and D-04 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-03 Onsite Station 3 IC&r I 44-013-I1-01 i2~1-~S 12-18-O4 D-04 Collins Road 1o.'a 2-0 12-31-W UxM41 t2ý31,02 12ý31ý0 C-38
FIGURE C-9 (cont.)
AIR PARTICULATES - GROSS BETA - STATIONS D-03 and D-04 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2008 D-03 Onsite Station 3 50.0 40.0 E
30.0 C)
C? 20.0 10.0 0.0 -
01-07-05 09-07-05 05-08-06 01-06-07 09-06-07 05-06-08 01-04-09 D-04 Collins Road 60.0 50.0 40.0 a.
U') 30.0 m
CL 9e 20.0 10.0 0.0 -
01-07-05 09-07-05 05-08-06 01-06-07 09-06-07 05-06-08 01-04-09 DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C-39
FIGURE C-10 AIR PARTICULATES - GROSS BETA - STATIONS D-07 and D-12 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-07 Clay Products iv~ml A40 UXIc44"a 12:1C 2*1Q, 23,4 D-12 (C)Lisbon 10.10 4,O 2,,:,~ - II Vf ILO 0141-00 12~1~3 12~h34~4 C-40
FIGURE C-10 (cont.)
AIR PARTICULATES - GROSS BETA - STATIONS D-07 and D-12 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2008 D-07 Clay Products 60.0 50.0 40.0 E
C.,"30.0 o 20.0 10.0 0.0 -
01-07-05 09-07-05 05-08-06 01-06-07 09-06-07 05-06-08 01-04-09 06/10/05 - 06/17/05 no sample due to pump malfunction D-12 (C) Lisbon 60.0 50.0 m- 40.0 E
M. 30.0 20.0 10.0 0.0 1 1 i i 01-07-05 09-07-05 05-08-06 01-06-07 09-06-07 05-06-08 01-04-09 DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C-41
FIGURE C-11 AIR PARTICULATES - GROSS BETA - STATIONS D-45 and D-53 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D45 McKinley Woods Road' 1QL 4.0 21, D-63 Grunidy Counity Road 9.0]
I C.0 00 ý--
4)141.0 U-31M 1241,101 12-.O-44 C-42
FIGURE C-11 (cont.)
AIR PARTICULATES - GROSS BETA - STATIONS D-45 and D-53 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2008 D-45 McKinley Woods Road 50.0 40.0 E
30.0 C.
a.
, 20.0 Li1I 10.0 0.0 -
01-07-05 09-07-05 05-08-06 01-06-07 09-06-07 05-06-08 01-04-09 D-53 Grundy County Road 82.1 CU 90*..
w01 0.0 I 01-07-05 09-07-05 05-08-06 01-06-07 09-06-07 05-06-08 01-04-09 DUE TO VENDOR CHANGE, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C-43
FIGURE C-12 AIR PARTICULATES - GROSS BETA - STATIONS D-08 and D-10 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2008 D-08 Prairie Park 70.0 60.0 50.0 E 40.0 u..
30.0 IL 2
"- 20.0 10.0 0.07- T 01-07-05 09-07-05 05-08-06 01-06-07 09-06-07 05-06-08 01-04-09 D-10 Goose Lake Village 60.0 50.0 40.0 E
" 30.0 9
20.0 10.0 0.0 I t ti I i 01-07-05 09-07-05 05-08-06 01-06-07 09-06-07 05-06-08 01-04-09 C-44
FIGURE C-13 AIR PARTICULATES - GROSS BETA - STATIONS D-13 and D-14 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2008 D-13 Minooka 50.0 40.0 30.0 9 20.0 Lu 10.0 0.0 -
01-07-05 07-07-05 01-04-06 07-04-06 01-01-07 07-01-07 D-14 Channahon 50.0 40.0
-: 30.0
,,.,
9 20.0 1.I 10.0 0.0 0 I i I I I 01-07-05 09-07-05 05-08-06 01-06-07 09-06-07 05-06-08 01-04-09 D-13 TAKEN OUT OF SERVICE JUNE 29, 2007 AND REPLACED WITH D-55 C-45
FIGURE C-14 AIR PARTICULATES - GROSS BETA - STATIONS D-55 and D-56 COLLECTED IN THE VICINITY OF DNPS, 2006-2008 D-55 Ridge Road 50.0 40.0 30.0 9 20.0 LuI 10.0 0.0 I I I I I 01-06-06 07-07-06 01-05-07 07-06-07 01-04-08 07-04-08 01-02-09 D-56 Wildfeather 50.0 40.0 E 30.0 o.c 9 20.0 10.0 0.0 .I I I I I 07-25-06 12-21-06 05-19-07 10-15-07 03-12-08 08-08-08 01-04-09 D-55 NEW STATION DECEMBER 30, 2005 REPLACED D-13 JUNE 29, 2007 D-56 NEW STATION JULY 25, 2006 C-46
Intentionally left blank APPENDIX D INTER-LABORATORY COMPARISON PROGRAM
TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2008 (PAGE 1 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)
March 2008 E5847-396 Milk Sr-89 pCi/L 83.5 95.8 0.87 A Sr-90 pCi/L 13.9 12.9 1.08 A E5848-396 Milk 1-131 pCi/L 57.3 60.0 0.96 A Ce-141 pCi/L 229 249 0.92 A Cr-51 pCi/L 336 359 0.94 A Cs-1 34 pCi/L 106 125 0.85 A Cs-1 37 pCi/L 141 146 0.97 A Co-58 pCi/L 71.8 70.8 1.01 A Mn-54 pCi/L 98.1 94.2 1.04 A Fe-59 pCi/L 102 102 1.00 A Zn-65 pCi/L 135 137 0.99 A Co-60 pCi/L 230 236 0.97 A E5850A-396 AP Ce-141 pCi 163 157 1.04 A Cr-51 pCi 233 227 1.03 A Cs-134 pCi 72.6 79.0 0.92 A Cs-137 pCi 98.3 92.0 1.07 A Co-58 pCi 46.7 44.7 1.04 A Mn-54 pCi 69.8 59.4 1.18 A Fe-59 pCi 72.2 64.5 1.12 A Zn-65 pCi 106 86.4 1.23 W Co-60 pCi 156 149 1.05 A E5849-396 Charcoal 1-131 pCi 65.5 60.1 1.09 A June 2008 E5971-396 Milk Sr-89 pCi/L 83.9 85.0 0.99 A Sr-90 pCi/L 14.4 15.8 0.91 A E5972-396 Milk 1-131 pCi/L 70.9 71.4 0.99 A Ce-141 pCi/L 157 174 0.90 A Cr-51 pCi/L 159 138 1.15 A Cs-1 34 pCi/L 69.7 76.7 0.91 A Cs-137 pCi/L 115 116 0.99 A Co-58 pCi/L 59.1 61.9 0.95 A Mn-54 pCi/L 139 135 1.03 A Fe-59 pCi/L 98.4 91.7 1.07 A Zn-65 pCi/L 129 127 1.02 A Co-60 pCi/L 101 104 0.97 A E5974-396 AP Ce-141 pCi 206 207 1.00 A Cr-51 pCi 173 164 1.05 A Cs-1 34 pCi 95.9 91.0 1.05 A Cs-137 pCi 142.0 138.0 1.03 A Co-58 pCi 72.0 73.4 0.98 A Mn-54 pCi 180 160.0 1.13 A Fe-59 pCi 108.0 109.0 0.99 A Zn-65 pCi 159 150 1.06 A Co-60 pCi 129 124 1.04 A D-1
TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2008 (PAGE 2 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)
June 2008 E5973-396 Charcoal 1-131 pCi 73.8 84.1 0.88 A September 2008 E6284-396 Milk Sr-89 pCi/L 76.2 73.9 1.03 A Sr-90 pCi/L 12.3 11.0 1.12 A E6285-396 Milk 1-131 pCi/L 65.7 67.9 0.97 A Ce-141 pCi/L 145 161 0.90 A Cr-51 pCi/L 406 421 0.96 A Cs-1 34 pCi/L 196 232 0.84 A Cs-1137 pCi/L 147 162 0.91 A Co-58 pCi/L 167 179 0.93 A Mn-54 pCi/L 165 166 0.99 A Fe-59 pCi/L 161 144 1.12 A Zn-65 pCi/L 305 319 0.96 A Co-60 pCi/L 218 234 0.93 A E6287-396 AP Ce-141 pCi 79.5 76.3 1.04 A Cr-51 pCi 208 199 1.05 A Cs-134 pCi 106 110 0.96 A Cs-137 pCi 79.3 76.7 1.03 A Co-58 pCi 87.7 84.4 1.04 A Mn-54 pCi 90.3 78.6 1.15 A Fe-59 pCi 81.7 68.3 1.20 A Zn-65 pCi 144 151 0.95 A Co-60 pCi 111 111 1.00 A E6286-396 Charcoal 1-131 pCi 93.2 90.0 1.04 A December 2008 E6415-396 Milk Sr-89 pCi/L 98.4 91.9 1.07 A Sr-90 pCi/L 18.0 12.6 1.43 N (1)
E6416-396 Milk 1-131 pCi/L 69.2 79.9 0.87 A Ce-141 pCi/L 177 191 0.93 A Cr-51 pCi/L 231 246 0.94 A Cs-1 34 pCi/L 117 134 0.87 A Cs-137 pCi/L 119 120 0.99 A Co-58 pCi/L 104 104 1.00 A Mn-54 pCi/L 153 152 1.01 A Fe-59 pCi/L 99.6 100 1.00 A Zn-65 pCi/L 177 183 0.97 A Co-60 pCi/L 133 133 1.00 A E6418-396 AP Ce-141 pCi 148 146 1.01 A Cr-51 pCi 202 187 1.08 A Cs-134 pCi 103 102 1.01 A Cs-1 37 pCi 95.4 91.2 1.05 A Co-58 pCi 81.4 79.2 1.03 A Mn-54 pCi 113 116.0 0.97 A Fe-59 pCi 76.5 76.4 1.00 A Zn-65 pCi 122 139 0.88 A Co-60 pCi 108 101 1.07 A D-2
TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2008 (PAGE 3 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)
December 2008 E6417-396 Charcoal 1-131 pCi 65.8 74.1 0.89 A (1) NCR 09-02 initiated to investigate the failure.
(a) Teledyne Brown Engineering reportedresult.
(b) The Analytics known value is equalto 100% of the parameterpresent in the standardas determined by gravimetric and/or volumetric measurements made during standardpreparation.
(c) Ratio of Teledyne Brown Engineering to Analytics results.
(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable. Reported result falls within ratio limits of 0.80-1.20.
W-Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30. N =Not Acceptable. Reported result falls outside the ratio limits of < 0. 70 and > 1.30.
D-3
TABLE D-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2008 (PAGE 1 OF 1)
Identification Reported Known Month/Year Number Media Nuclide Units Value (a) Value (b) Control Limits Evaluation (c)
January 2008 Quiktn Response Water Sr-89 pCi/L .37.33 19.0 11.8-25.2 N (1)
Sr-90 pCi/L 40.40 42.7 31.5 -49.0 A Ba-133 pCi/L 87.8 90.5 76.2 - 99.6 A Cs- 134 pCi/L 80.67 88.9 72.9 - 97.8 A Cs-1 37 pCi/L 222.33 231 208 - 256 A Co-60 pCi/L 98.9 101.0 90.9-113 A Zn-65 pCi/L 352 350 315 -408 A Gr-A pCi/L 13.0 12.7 6.02- 18.7 A Gr-B pCi/L 32.7 36.2 23.8 - 43.8 A H-3 pCi/L 11100 11300 9840-12400 A January 2008 RAD 72 Water Sr-89 pCi/L 69.0 65.3 53.0 - 73.4 A Sr-90 pCi/L 35.6 41.4 30.5 -47.6 A Ba-1 33 pCi/L 25.9 25.7 20.0 - 29.5 A Cs-134 pCi/L 86.5 92.6 76.0- 102 A Cs- 137 pCi/L 155 158 142- 176 A Co-60 pCi/L 16.0 14.4 11.4-18.7 A Zn-65 pCi/L 214 204 184 - 240 A Gr-A pCi/L 13.3 14.8 7.15-21.2 A Gr-B pCi/L 21.2 22.5 13.7-30.6 A 1-131 pCi/L 22.8 23.6 19.6-28.0 A H-3 pCi/L 3390 3540 3000-3910 A April'2008 Rad 73 Water Sr-89 pCi/L 65.47 60.4 48.6 - 68.2 A Sr-90 pCi/L 39.80 39.2 28.8-45.1 A Ba-133 pCi/L 59.63 58.3 48.3-64.3 A Cs-134 pCi/L 45.00 46.6 37.4- 51.3 A Cs-137 pCi/L 97.97 102 91.8- 115 A Co-60 pCi/L 75.47 76.6 68.9 - 86.7 A Zn-65 pCi/L 109 106 95.4- 126 A Gr-A pCi/L 41.03 50.8 26.5 - 63.7 A Gr-B pCi/L 50.20 51.4 35.0 - 58.4 A 1-131 pCi/L 26.67 28.7 23.9 - 33.6 A H-3 pCi/L 11633 12000 10400 - 13200 A (1) Could find no cause for Sr-89 failure. Sample sent to outside lab for verification, but the outside laboratorywas unable to confirm our numbers or ERA numbers. Studies bracketing these results, RAD 71 and RAD 72, had acceptable Sr-89 results. NCR 08-03 (a) Teledyne Brown Engineering reportedresult.
(b) The ERA known value is equal to 100% of the parameterpresentin the standardas determined by gravimetric and/or volumetric measurementsmade during standardpreparation.
(c) ERA evaluation:A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the ControlLimits and outside of the Warning Limit.
D-4
TABLE D-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
TELEDYNE BROWN ENGINEERING, 2008 (PAGE 1 OF 2)
Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)
January 2008 07-MaWi8 Water Cs-1 34 Bq/L -0.26 (1) A Cs-137 Bq/L 0.029 (1) A Co-57 Bq/L 21 22.8 16.0 - 29.6 A Co-60 Bq/L 8.2 8.40 5.88- 10.92 A H-3 Bq/L 473 472 330-614 A Mn-54 Bq/L 12 12.1 8.5-15.7 A Sr-90 Bq/L 10.70 11.4 7.98- 14.82 A Zn-65 Bq/L 15.6 16.3 11.4-21.2 A 07-GrW18 Water Gr-A Bq/L 1.4 1.399 >0.0 - 2.798 A Gr-B Bq/L 3.06 2.43 1.22-3.65 A 07-MaS18 Soil Cs-1 34 Bq/kg 790 854.0 598-1110 Cs-137 Bq/kg 568 545 382 - 709 Co-57 Bq/kg 424 421 295-547 Co-60 Bq/kg 2.307 2.9 (2)
Mn-54 Bq/kg 611 570 399-741 K-40 Bq/kg 6.09 571 400 - 742 Sr-90 Bq/kg 454 493.0 345-641 Zn-65 Bq/kg 0.162 (1) 07-RdF18 AP Cs-134 Bq/sample 2.73 2.5200 1.76 - 3.28 Cs-137 Bq/sample 2.88 2.7 1.89-3.51 Co-57 Bq/sample 3.493 3.55 2.49 - 4.62 Co-60 Bq/sample 1.357 1.31 0.92 - 1.70 Mn-54 Bq/sample 0.006 (1)
Sr-90 Bq/sample 1.61 1.548 1.084 - 2.012 Zn-65 Bq/sample 2.59 2.04 1.43 - 2.65 07-GrF18 AP Gr-A Bq/sample 0.131 0.348 >0.0 - 0.696 Gr-B Bq/sample 0.261 0.286 0.143 - 0.429 January 2008 07-RdV18 Vegetation Cs-134 Bq/sample 5.25 6.28 4.40 - 8.16 Cs-137 Bq/sample 3.13 3.41 2.39-4.43 Co-57 Bq/sample 6.837 6.89 4.82 - 8.96 Co-60 Bq/sample 2.44 2.77 1.94 - 3.60 Mn-54 Bq/sample 4.45 4.74 3.32-6.16 K-40 Bq/sample 61.3 (1)
Sr-90 Bq/sample 1.33 1.273 0.891 - 1.655 Zn-65 Bq/sample 0.085 (1)
August 2008 08-MaW19 Water Cs-134 Bq/L 17.1 19.5 13.7 -25.4 A Cs-137 Bq/L 21.4 23.6 16.5 - 30.7 A Co-57 Bq/L -0.044 (1) A Co-60 Bq/L 10.8 11.6 8.1-15.1 A H-3 Bq/L 334 341 239-443 A Mn-54 Bq/L 13.0 13.7 9.6- 17.8 A Sr-90 Bq/L 6.55 6.45 4.52- 8.39 A Zn-65 Bq/L 16.5 17.1 12.0-22.2 A D-5
TABLE D-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
TELEDYNE BROWN ENGINEERING, 2008 (PAGE 2 OF 2)
Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)
August 2008 08-GrW1 9 Water Gr-A Bq/L 0.0612 <0.56 (3) A Gr-B Bq/L 0.222 <1.85 (3) A 08-MaS 19 Soil Cs-134 Bq/kg 546 581 407-755 A Cs-137 Bq/kg 2.52 2.8 (2) A Co-57 Bq/kg 340 333 233-433 A Co-60 Bq/kg 157 145.0 102-189 A Mn-54 Bq/kg 460 415 291- 540 A K-40 Bq/kg 650 571 399-741 A Sr-90 Bq/kg 1.40 (1) A Zn-65 Bq/kg -1.53 (1) A 08-RdF19 AP Cs-134 Bq/sample 2.46 2.6300 1.84 - 3.42 A Cs-137 Bq/sample 0.0063 (1) A Co-57 Bq/sample 1.36 1.50 1.05- 1.95 A Co-60 Bq/sample 0.0143 (1) A Mn-54 Bq/sample 2.70 2.64 1.85-3.43 A Sr-90 Bq/sample 1.42 1.12 0.78-1.46 W Zn-65 Bq/sample 0.975 0.94 0.66- 1.22 A 08-GrF19 AP Gr-A Bq/sample -0.0037 (4) A Gr-B Bq/sample 0.540 0.525 0.263 - 0.788 A 08-RdV19 Vegetation Cs-134 Bq/sample 4.36 5.5 3.9 - 7.2 W Cs-1 37 Bq/sample -0.03 (1) A Co-57 Bq/sample 6.72 7.1 5.0-9.2 A Co-60 Bq/sample 4.04 4.70 3.3-6.1 A Mn-54 Bq/sample 5.22 5.8 4.1 -7.5 A K-40 Bq/sample 64.4 (1)
Sr-90 Bq/sample 1.62 1.9 1.3-2.5 A Zn-65 Bq/sample 6.160 6.9 4.8 - 9.0 A (1) Not evaluated by MAPEP.
(2) Reported a statisticallyzero result.
(3) Designed to test the Safe Drinking Water screeninglevels. Labs reporting values less than ref values were found to be acceptable.
(4) False positive test.
(a) Teledyne Brown Engineering reported result.
(b) The MAPEP known value is equal to 100% of the parameterpresent in the standard as determinedby gravimetric and/or volumetric measurementsmade during standardpreparation.
(c) DOEIMAPEPevaluation:A=acceptable, W=acceptable with warning, N=not acceptable.
D-6
APPENDIX E ERRATA DATA
There is no errata data for 2008.
E-1
Intentionally left blank APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)
Docket No: 50-010 50-237 50-249 DRESDEN NUCLEAR POWER STATION UNITS 1, 2 and 3 Annual Radiological Groundwater Protection Program Report 1 January Through 31 December 2008 Prepared By Teledyne Brown Engineering Environmental Services Nuclear Dresden Nuclear Power Station Norris, IL 60450 May 2009
Table Of Contents I. Sum m ary and Conclusions ................................................................................................ 1 II. Intro d uctio n ........................................................................................................................ 2 A. Objectives of the RGPP ................................................................................... 3 B. Implem entation of the Objectives ..................................................................... 4 C. Program Description ......................................................................................... 4 D. Characteristics of Tritium (H-3) ....................................................................... 5 II1. Program Description ..................................................................................................... 5 A. Sam ple Analysis ................................................................................................ 5 B. Data Interpretation ........................................................................................... 6 C. Background Analysis ......................................................................................... 7
- 1. Background Concentrations of Tritium .................................................. 7 IV. Results and Discussion ............................................................................................... 9 A. Groundwater Results ......................................................................................... 9 B. Drinking W ater W ell Survey ...................................................................... ......... 10 C. Summary of Results - Inter-laboratory Comparison Program ....................... 10 D. Leaks, Spills, and Releases ............................................................................ 10 E. Trends ............................................................................................................ 11 F. Investigations .................................................................................................. 11 G . Actions Taken ................................................................................................ 11
- i-
Appendices Appendix A Location Designation Tables Table A-1: Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2008 Figures Security-Related Information: Maps of the Dresden Nuclear Power Station have been withheld from public disclosure under 10CFR2.390 and N.J.S.A. 47:1A-1.1 Appendix B Data Tables Tables Table B-1.1 Concentrations of Tritium and Strontium in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table B-1.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table B-11.1 Concentrations of Tritium and Strontium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
Table B-11.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2008.
- ii -
I. Summary and Conclusions Dresden Station is situated on approximately 600 acres of land that borders the Illinois River to the north and the Kankakee River to the east. This land is referred to as the owner-controlled area. The Dresden power plant itself takes up a small parcel of the owner-controlled area and is surrounded by a security fence. The security fence defines what is known as the Protected Area (P.A.).
The Dresden power plant has experienced a number of leaks from underground lines and spills from above ground systems containing radioactive water over its 40-year history. These incidents have created a number of areas of localized contamination within the P.A. Isotopic analyses of groundwater in many of these areas show measurable concentrations of tritium (H-3). In addition, Strontium (Sr-90) was detected just above the Lower Limit of Detectability (LLD) in one of the wells within the P.A.
Dresden participated in a fleetwide hydrogeologic investigation in during the summer of 2006 in an effort to characterized groundwater movement at each site. This investigation also compiled a list of the historic spills and leaks. Combining the tritium concentration in a locally contaminated area with the speed and direction of groundwater in the vicinity can produce a contaminated groundwater plume projection. If the plume of contaminated groundwater passes through the path of a groundwater monitoring well, it can be anticipated that the tritium concentration in this well will increase to some maximum concentration, then decrease over time.
The fleetwide Hydrogeologic Investigation Report (HIR) shows that groundwater movement on the Dresden site is very slow. In addition, there is a confining rock layer, the Maquoketa Shale layer, about 55 feet below the surface that impedes groundwater movement below this depth. The results of the HIR are available on:
[1].
Dresden has a domestic water system that is supplied by two deep wells (1500 feet deep) that were installed about 50 years ago south of the P.A. Samples taken from domestic water supply and have never shown any detectable tritium concentration.
Tritium has a half-life of 12.3 years. This means that 40 years from now 90% of the tritium on site today will have decayed away to more stable elements.
Given the limited volume of contaminated groundwater on site, radioactive decay, slow groundwater movement, and dilution effects the conclusion of the HIR is that the operation of Dresden Nuclear Power Station had no adverse radiological impact on the environment. As a result there is little potential for contaminated groundwater on site to affect off-site drinking water.
II. Introduction Radiological Groundwater Monitoring Program (RGPP):
Dresden has a Radiological Groundwater Monitoring Program (RGPP) that provides long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions.
Dresden uses developed groundwater wells and surface water sample points in the RGPP.
The Dresden RGPP was established in 2006 and there have been no significant changes to this program. This program does not impact the operation of the plant and is independent of the REMP.
Developed groundwater wells are wells that were installed specifically for monitoring groundwater. These wells are equipped with screens and are properly sealed near the surface to avoid surface water intrusion. The wells were designed in accordance with appropriate codes and developed in accordance with appropriate standards and procedures. Dresden has groundwater monitoring wells identified as "shallow" (depths from 15 to 35 feet), "Intermediate" (depths from 35 to 55 feet) and "deep" (depths beyond 100 feet). All wells installed to a depth greater than 100 feet ("deep" wells) were found to be dry and removed from the RGPP. Surface water sample points are identified sample locations in the station's canals and cooling pond.
There are 71 sampling points in the RGPP:
- Dresden has 39 developed groundwater monitoring wells within the Protected Area.
Some of these wells form a ring just inside the security fence and the remaining wells were installed near underground plant system piping that contains radioactive water.
- Dresden has 26 developed groundwater monitoring wells outside the P.A. the majority of which form a ring just within the perimeter of the property.
- Dresden has 6 surface water monitoring locations on the owner-controlled area sampled as part of the Dresden RGPP. These consist of one sample from each of the 5 different canals and one sample from the cooling pond.
The Dresden site-specific RGPP procedure identifies the historic 'events' that would affect the individual RGPP sample results. This procedure identifies threshold values for each-sample point, which if exceeded, could be an indication of a new spill from an above ground system or a new leak in an underground pipe containing tritiated water.
The RGPP sample points are currently sampled on a frequency of twice per year.
During 2008, there were 282 analyses that were performed on 140 samples from 71 sample points.
Supplemental Radiological Groundwater Monitoring Program (SRGPP):
Dresden also has a Supplemental Radiological Groundwater Monitoring Program (SRGPP) that provides short-term monitoring of a limited selection of monitoring points, mostly within the P.A., intended to identity relatively rapid changes in the groundwater tritium concentrations.
Sentinel Wells, sometimes referred to as "baby wells" are wells that were installed to monitor local shallow groundwater; typically in associated with a historic underground pipe leak. These wells are not constructed to code or developed to a standard. Most sentinel wells are from 6 to 12 feet deep and consist of 2" PVC pipe without screens.
Many sentinel wells were installed near an underground HPCI suction line and were subsequently removed as part of the excavation and repair of that line.
Dresden has two basic storm water runoff sewer systems within the P.A: one sewer-system routes to the east, then north, and discharges into the Unit 1 intake canal, the second sewer-system routes to the west, then north, through a large Oil Separator, and discharges to the hot canal. Both the Unit 1 intake canal and the hot canal eventually route to the cooling pond.
A. Objectives of the RGPP The Objective of the RGPP is to provide long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions. The objective of the SRGPP is to provide indication of short-term changes to groundwater tritium concentrations within the P.A.
If isotopic results of groundwater samples exceed the thresholds specified in this procedure it could be an indication of a new spill from an above ground system or a new leak in an underground pipe containing tritiated water.
Specific Objectives include:
- 1. Perform routine water sampling and radiological analysis of water from selected locations.
- 2. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.
- 3. Regularly assess analytical results to identify adverse trends.
- 4. Take necessary corrective actions to protect groundwater resources.
B. Implementation of the Objectives
- 1. Dresden Nuclear Power Station will continue to perform routine sampling and radiological analysis of water from selected locations.
- 2. Dresden Nuclear Power Station has implemented procedures to identify and report new leaks, spills, or other detections with potential radiological significance in a timely manner.
- 3. Dresden Nuclear Power Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.
- 4. If an adverse trend in groundwater monitoring analytical results is identified, further investigation will be undertaken. If the investigation identifies a leak or unidentified spill, corrective actions will be implemented.
C. Program Description Dresden has a Radiological Groundwater Monitoring Program (RGPP) that provides long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions. Dresden uses 71 developed groundwater wells and surface water sample points in the RGPP.
- 1. Sample Collection Sample locations can be found in Table A-i, Figures A-1 and A-2, and, Appendix A.
Groundwater and Surface Water Water samples are collected in accordance with the schedule delineated in the Dresden site-specific RGPP procedures.
Analytical laboratories are subject to internal quality assurance programs, industry crosscheck programs, as well as nuclear industry audits. Station personnel review and evaluate the analytical results.
D. Characteristics of Tritium (H-3)
Tritium (chemical symbol H-3) is a radioactive isotope of hydrogen. The most common form of tritium is tritium oxide, which is also called "tritiated water." The chemical properties of tritium are essentially those of ordinary hydrogen.
Tritiated water behaves the same as ordinary water in both the environment and the body. Tritium can be taken into the body by drinking water, breathing air, eating food, or absorption through skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout the body. Tritium is excreted primarily through urine with a clearance rate characterized by an effective biological half-life of about 14 days. Within one month or so after ingestion, essentially all tritium is cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period.
Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-10 are activated to produce tritium.
Like normal water, tritiated water is colorless and odorless. Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.
Tritium has a half-life of approximately 12.3 years. It decays spontaneously to helium-3 (3He). This radioactive decay releases a beta particle (low-energy electron). The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous radionuclides because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.
I1l. Program Description A. Sample Analysis This section describes the general analytical methodologies used by Teledyne Brown Engineers (TBE) to analyze the environmental samples for radioactivity for the Dresden Nuclear Power Station RGPP in 2008.
In order to achieve the stated objectives, the current program includes the
following analyses:
- 1. Concentrations of gamma emitters in groundwater and surface water.
- 2. Concentrations of strontium in groundwater and surface water.
- 3. Concentrations of tritium in groundwater and surface water.
B. Data Interpretation The radiological data collected prior to Dresden Nuclear Power Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Dresden Nuclear Power Station was considered operational at initial criticality. Several factors were important in the interpretation of the data:
- 1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is specified by federal regulation as a minimum sensitivity value that must be achieved routinely by the analytical parameter.
- 2. Laboratory Measurements Uncertainty The estimated uncertainty in measurement of tritium in environmental samples is frequently on the order of 50% of the measurement value.
Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence. The convention is to report results with a 95% level of confidence. The uncertainty comes from calibration standards, sample volume or weight measurements, sampling uncertainty and other factors. Exelon reports the uncertainty of a measurement created by statistical process (counting error) as well as all sources of error (Total Propagated Uncertainty or TPU). Each result has two values calculated.
Exelon reports the TPU by following the result with plus or minus +
the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.
Analytical uncertainties are reported at the 95% confidence level in
this report for reporting consistency with the AREOR.
Gamma spectroscopy results for each type of sample were grouped as follows:
For groundwater 12 nuclides, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140 and La-140 were reported.
C. Background Analysis A pre-operational radiological environmental monitoring program (pre-operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The environmental media sampled and analyzed during the pre-operational REMP were atmospheric radiation, fall-out, domestic water, surface water, marine life, and foodstuffs. The results of the monitoring were detailed in the report entitled, Environmental Radiological Monitoring for Dresden Nuclear Power Nuclear Power Station, Commonwealth Edison Company, Annual Report 1986, May 1987.
- 1. Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others. Additional detail may be found by consulting references (CRA 2006).
- a. Tritium Production Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and combines with oxygen to form tritiated water, which will then enter the hydrologic cycle. Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.
A major anthropogenic source of tritium and strontium-90 comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and early 1960s, and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere. The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.
- b. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database. GNIP provides tritium precipitation concentration data for samples collected world wide from 1960 to 2006.
RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. from 1960 up to and including 2006. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a gradual decline since that time. Tritium concentrations in Midwest precipitation have typically been below 100 pCi/L since around 1980. Tritium concentrations in wells may still be above the 200-pCi/L detection limit from the external causes described above. Water from previous years and decades is naturally captured in groundwater, so some well water sources today are affected by the surface water from the 1960s that was elevated in tritium.
- c. Surface Water Data Tritium concentrations are routinely measured in large surface water bodies, including Lake Michigan and the Mississippi River. Illinois surface water data were typically less than 100 pCi/L.
The radio-analytical laboratory is counting tritium results to an Exelon specified LLD of 200 pCi/L. Typically, the lowest positive measurement will be reported within a range of 40 -
240 pCi/L or 140 +/- 100 pCi/L. These sample results cannot be distinguished as different from background at this concentration.
IV. Results and Discussion Dresden Station initiated a Radiological Groundwater Protection Program (RGPP) in 2006.
A. Groundwater Results Groundwater Samples were collected from on and off-site wells throughout the year in accordance with Dresden's RGPP. Analytical results and anomalies are discussed below.
Tritium Of the 39 developed groundwater-monitoring wells inside the Protected Area, 23 wells show some level of tritium contamination ranging from just above LLD to 106,000 pCi/L. Of the 26 developed groundwater-monitoring wells outside the Protected Area, 12 wells show tritium contamination ranging from just above LLD to 21,100 pCi/L. One of these wells is located near the radwaste discharge line (about 200 yards north of the plant) that ruptured in 1999. The other well is about 1500 feet south of the Security Check point adjacent to the hot canal that had measurable concentrations of tritium from an upstream source.
Gamma Emitters and Strontium Potassium-40 was detected in four of 64 samples. The concentrations ranged from 29 pCi/liter to 57 pCi/liter. No other gamma emitting nuclides were detected. (Table B-1.2, Appendix B).
B. Surface Water Results Surface Water Samples were collected from six surface water locations throughout the year in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below.
Tritium Samples from all locations were analyzed for tritium activity (Table B-1I.1, Appendix B). Tritium values ranged from the detection limit to 3,580 pCi/I.
The measurable concentrations of tritium are from an upstream source.
Gamma Emitters and Strontium Potassium-40 was detected in one of six samples, with a concentration of 46 pCi/liter. No other gamma emitting nuclides were detected. (Table B-11.2, Appendix B).
C. Drinking Water Well Survey A drinking water well survey was conducted during the summer 2006 by CRA (CRA 2006) around the Dresden Nuclear Power Station. No tritium was detected in the drinking water source.
D. Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE and Environmental Inc. (Midwest Labs) are presented in the AREOR.
E. Leaks, Spills, and Releases In the summer of 2004 elevated tritium concentrations were identified in sentinel wells by the HPCI suction line near the HPCI room. This line was found leaking and about one-half of the line was excavated and replaced.
In January of 2006 there was an increase in tritium concentration in two sentinel wells near the HPCI suction line adjacent to the 2/3B Contaminated Storage Tank (2/3B CST). This suggested that the other half of the HPCI suction line was leaking. The line was excavated and pressure tested. Itwas determined that this line was not leaking. The line did show some indications
of degradation and as a result, this half of the line was replaced.
There have been no incidences of a leaks or spills at Dresden Station in 2008.
F. Trends The tritium concentration in the water found near the 2004 HPCI leak is traveling to the west. Wells in the vicinity show that tritium levels have been trending down slightly.
G. Investigations Following a heavy rain in August of 2007, water was flowing into the Cribhouse basement through an underground electrical penetration. The water contained tritium at a concentration above LLD. Samples taken the next day were showed higher concentrations of tritium suggesting an increasing trend.
Further monitoring showed the tritium concentration was steady for a few days then started decreasing. The flow decrease over the next several days then stopped completely. If this were a leak of an underground piping system we would expect that the flow would continue and the tritium concentration would continue to increase by several orders of magnitude.
There is currently no flow through any Cribhouse electrical penetrations and Dresden continues to monitor in the vicinity of the Cribhouse basement.
H. Actions Taken
- 1. Compensatory Actions No compensatory actions were taken as a result of the RGPP in 2008.
- 2. Actions to Recover/Reverse Plumes No actions were taken by Dresden Station if an effort to reverse plume movement.
Intentionally left blank APPENDIX A LOCATION DISTANCE
TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Dresden Nuclear Power Station, 2008 Site Site Type Location DSP-105 Monitoring Well 30 feet east of the east wall of the EM Shop DSP-106 Monitoring Well 65 feet east of east wall of EM Shop DSP-107 Monitoring Well 9 feet east of the east Unit 1 Fuel Pool wall DSP-108 Monitoring Well 40 ft east of the Unit I Sphere DSP-117 Monitoring Well Northeast of Unit 1 Sphere; 825 feet west of Ross Bridge DSP-121 Monitoring Well 72 feet north of 2/3 Intake Canal fence DSP-122 Monitoring Well 50 feet north of the Radwaste Tank Farm DSP-123 Monitoring Well Northeast corner of the Unit 1 Off-gas Building DSP-124 Monitoring Well 9 feet south of Floor Drain Collector Tank DSP-125 Monitoring Well Northeast corner of the Unit 2/3A CST DSP-126 Monitoring Well 21 feet northwest of the northwest bend in road behind Training Building DSP-147 Monitoring Well 325 feet west of Telemetry Bridge DSP-148 Monitoring Well 130 feet southeast of the Flow Regulating Station building DSP-149R Monitoring Well 35 feet south by southwest of the 138 KV yard fence DSP-150 Monitoring Well 85 feet east of the northeast corner of the Unit 1 Spent Fuel Pool pad DSP-151 Monitoring Well 65 feet north of the northeast corner of the Storeroom DSP-152 Monitoring Well 210 feet south by southeast of the southeast corner of Maintenance Garage DSP-153 Monitoring Well 150 feet east of the southeast corner of liquid hydrogen tank farm fence DSP-154 Monitoring Well 33 feet west of the track; 165 feet east of the Security Checkpoint DSP-156 Monitoring Well 70 feet east by northeast of the northwest corner of 138 KV yard fence DSP-157-1 (M) Monitoring Well 25 feet south of the south edge of the Employee Parking lot DSP-157-S Monitoring Well 25 feet south of the south edge of the Employee Parking lot DSP-158-1 (M) Monitoring Well 53 feet west of the Kankakee River; 33 feet west of the cinder track DSP-158-S Monitoring Well 50 feet west of the Kankakee River; 33 feet west of the cinder track DSP-159-1 (M) Monitoring Well 250 feet west of the Thorsen house; 450 ft south of the plant access gate DSP-159-S Monitoring Well 251 feet west of the Thorsen house; 450 ft south of the plant access gate MW-DN-101-1 Monitoring Well 60 feet north of the Unit 1 Diesel Fuel Storage MW-DN-101-S Monitoring Well 60 feet north of the Unit 1 Diesel Fuel Storage MW-DN-102-1 Monitoring Well 12 feet south of the southeast corner of the MUDS Building MW-DN-102-S Monitoring Well 13 feet south of the southeast corner of the MUDS Building MW-DN-103-1 Monitoring Well 280 feet west of the northwest corner of N-GET Building MW-DN-103-S Monitoring Well 281 feet west of the northwest corner of N-GET Building MW-DN-104-S Monitoring Well 50 feet north of Radwaste Tank Farm MW-DN-105-S Monitoring Well 65 feet north of the northeast corner of the Storeroom MW-DN-106-S Monitoring Well 75 feet north of the 2/3 Intake Canal fence; east of the Unit 1 Intake Canal MW-DN-107-S Monitoring Well 15 feet west by southwest of the Unit 1 CST MW-DN-108-1 Monitoring Well 7 feet southwest of the southwest corner of the Unit 1 Cribhouse MW-DN-109-1 Monitoring Well 8 feet north of Chemistry Building MW-DN-109-S Monitoring Well 8 feet north of Chemistry Building MW-DN-110-1 Monitoring Well 25 feet west of the Waste Water Treatment (WWT) Building MW-DN- 110-S Monitoring Well 25 feet west of the Waste Water Treatment (WWT) Building MW-DN-11i1-S Monitoring Well 9 feet east of the Floor Drain Collector Tank MW-DN-1 12-1 Monitoring Well 100 feet south of the Chemistry Building A-1
TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Dresden Nuclear Power Station, 2008 Site Site Type Location MW-DN-112-S Monitoring Well 100 feet south of the Chemistry Building MW-DN-1 13-1 Monitoring Well 90 feet west of the southwest corner of the Administration Building MW-DN-1 13-S Monitoring Well 91 feet west of the southwest comer of the Administration Building MW-DN-1 14-1 Monitoring Well 50 feet east of the Unit 1 Clean Demineralized Water Tank MW-DN-114-S Monitoring Well 8 feet southwest of the Radiation protection Dept west access doors MW-DN-1 15-1 Monitoring Well 11 feet south of Instrument Maintenance Shop MW-DN-1 15-S Monitoring Well 12 feet south of Instrument Maintenance Shop MW-DN-1 16-1 Monitoring Well 75 feet south of the Calgon Building roll-up door MW-DN-116-S Monitoring Well 75 feet south of the Calgon Building roll-up door MW-DN-1 17-1 Monitoring Well 35 feet east by northeast of the Unit 1 Stack MW-DN-1 18-S Monitoring Well Southeast corner of the Unit 1 Fuel Pool MW-DN-1 19-1 Monitoring Well 20 feet east by northeast of the Unit 1 Sewage Ejector Building MW-DN-119-S Monitoring Well 21 feet east by northeast of the Unit 1 Sewage Ejector Building MW-DN-120-1 Monitoring Well 45 feet north by northeast of the Ross Bridge railing MW-DN-120-S Monitoring Well 46 feet north by northeast of the Ross Bridge railing MW-DN-121-S Monitoring Well 7 feet west of the dirt road; 42 feet east of the 345KV yard fence MW-DN-122-1 Monitoring Well 150 feet north of Heineke Road; northeast of the G.E. Fuel Storage Facility MW-DN-122-S Monitoring Well 150 feet north of Heineke Road; northeast of the G.E. Fuel Storage Facility MW-DN-123-1 Monitoring Well 400 feet west of the Thorsen house; west of the Cold Canal MW-DN-123-S Monitoring Well 400 feet west of the Thorsen house; west of the Cold Canal MW-DN-124-1 Monitoring Well 10 feet south of the liquid nitrogen inerting tanks MW-DN-124-S Monitoring Well 10 feet south of the liquid nitrogen inerting tanks SW-DN-101 Surface Water Unit 2/3 Intake (DSP50) at the Ross Bridge SW-DN-102 Surface Water Unit 2/3 Discharge (DSP20) at the Telemetry Bridge SW-DN-103 Surface Water Unit 2/3 Return Canal at the Discharge to the Intake Canal SW-DN-104 Surface Water Cold Canal (DSP34A) at the Cooling Tower walkway bridge SW-DN-105 Surface Water Hot Canal (DSP34B) at the Cooling Tower walkway bridge SW-DN-106 Surface Water Cooling Pond - Pool IIat the east side of the Covered Bridge A-2
APPENDIX B DATA TABLES
TABLE B-I.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 DSP-105 05/06/08 < 191 DSP-105 10/09/08 300 +/- 109 <1 DSP-106 05/06/08 2780 +/- 356 DSP-106 10/09/08 3120 +/- 371 <1 DSP-107 10/09/08 7130 +/- 769 <1 DSP-108 10/09/08 1530 +/- 218 <1 DSP-117 05/12/08 < 177 DSP-117 10/14/08 < 171 <1 DSP-121 05/12/08 < 175 DSP-121 10/14/08 < 171 <1 DSP-122 05/08/08 3250 +/- 402 DSP-122 10/08/08 2890 +/- 350 <1 DSP-123 05/08/08 11900 +/- 1260 DSP-123 10/08/08 11900 +/- 1250 <1 DSP-124 05/09/08 9070 +/- 981 DSP-124 10/10/08 21100 +/- 2160 DSP-125 05/07/08 207 +/- 123 DSP-125 10/10/08 441 +/- 120 <1 DSP-126 05/05/08 < 189 DSP-126 10/13/08 < 158 <1 DSP-147 05/07/08 < 190 DSP-147 10/13/08 < 162 <1 DSP-148 05/12/08 243 +/- 117 DSP-148 10/15/08 265 +/- 120 <1 DSP-149R 05/12/08 414 +/- 126 DSP-149R 10/15/08 366 +/- 127 <1 DSP-150 05/06/08 < 187 DSP-150 10/09/08 < 162 <1 DSP-151 05/06/08 < 191 DSP-151 10/09/08 < 160 <1 DSP-152 05/05/08 < 185 DSP-152 10/13/08 < 172 <1 DSP-153 05/05/08 < 187 DSP-153 10/13/08 < 170 <1 DSP-154 05/07/08 < 188 DSP-154 10/14/08 < 179 <2 DSP-156 05/12/08 252 +/- 117 DSP-156 10/15/08 190 +/- 120 <2 DSP-157M 05/05/08 < 190 DSP-157M 10/13/08 < 165 <2 DSP-157S 05/05/08 < 187 DSP-157S 10/13/08 < 163 <1 DSP-158M 05/05/08 < 190 DSP-158M 10/14/08 < 163 <2 DSP-158S 05/05/08 < 193 DSP-158S 10/14/08 < 157 <1 DSP-159M 05/12/08 356 +/- 122 DSP-159M 10/14/08 386 +/- 120 <1 DSP-159S 05/12/08 < 177 DSP-159S 10/14/08 < 161 <1 DSP-107 05/06/08 6140 +/- 680 DSP-108 05/06/08 1260 +/- 199 MW-DN-1 031 05/05/08 < 194 B-1
TABLE B-I.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED INTHE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 MW-DN-103S 05/05/08 < 193 MW-DN-1 011 05/05/08 1780 +/- 253 MW-DN-1011 10/08/08 1660 +/- 218 < 1 MW-DN-101S 05/05/08 < 191 MW-DN-101S 10/08/08 < 146 < 1 MW-DN-1021 05/07/08 < 191 MW-DN-1021 10/07/08 230 +/- 110 < 1 MW-DN-102S 05/07/08 < 190 MW-DN-102S 10/07/08 219 +/- 109 1 1
MW-DN-1031 10/13/08 < 157 1
MW-DN-.103S 10/13/08 < 153 MW-DN-104S 05/08/08 < 190 MW-DN-104S 10/08/08 639 +/- 134 <1 MW-DN-105S 05/06/08 < 190 MW-DN-105S 10/09/08 < 145 <1 MW-DN-106S 05/12/08 < 176 MW-DN-106S 10/14/08 < 161 <1 MW-DN-107S 05/07/08 1070 +/- 187 MW-DN-1 07S 10/10/08 2980 +/- 339 <1 MW-DN-1081 05/06/08 < 177 MW-DN-1081 10/08/08 326 +/- 117 <2 MW-DN-1091 05/08/08 < 182 MW-DN-1091 10/07/08 313 +/- 116 <2 MW-DN-109S 05/08/08 320 +/- 128 MW-DN-109S 10/07/08 329 +/- 116 <1 MW-DN-1101 05/08/08 453 +/- 132 MW-DN- 1101 10/07/08 421 +/- 123 <1 MW-DN-110S 05/08/08 < 180 MW-DN-110S 10/07/08 181 +/- 106 <2 MW-DN-111S 05/09/08 259 +/- 122 MW-DN-111S 10/10/08 474 +/- 124 <1 MW-DN-1 121 10/07/08 1550 +/- 207 <2 MW-DN-1 12S 10/07/08 < 157 <1 MW-DN-1131 05/06/08 < 180 MW-DN-1 131 10/07/08 < 155 <1 MW-DN-11 3S 05/07/08 238 +/- 123 MW-DN-1 13S 10/07/08 229 +/- 108 <2 MW-DN- 1141 05/07/08 4530 +/- 516 MW-DN-1 141 10/10/08 9200 +/- 962 <1 MW-DN-1 14S 05/07/08 1620 +/- 234 MW-DN-1 14S 10/10/08 1470 +/- 199 <1 MW-DN-1 151 05/07/08 190 +/- 119 MW-DN-1151 10/09/08 194 +/- 103 <1 MW-DN-11 5S 05/07/08 < 183 MW-DN-11 5S 10/09/08 < 168 <1 MW-DN-1 161 05/08/08 3890 +/- 453 MW-DN-1 161 10/08/08 2870 +/- 354 <1 MW-DN-116S 05/08/08 407 +/- 128 MW-ON-116S 10/08/08 412 +/- 125 <1 MW-DN-1201 05/12/08 < 177 MW-DN-1201 10/14/08 < 161 MW-DN-120S 05/12/08 < 176 B-2
TABLE B-I.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA COLLECTION SITE DATE H-3 SR-90 MW-DN-120S 10/14/08 < 159 <1 MW-DN-121S 10/13/08 < 161 <2 MW-DN-1221 10/13/08 < 157 <1 MW-DN-1 22S 10/13/08 < 155 <1 MW-DN-1231 05/07/08 < 192 MW-DN-1231 10/13/08 < 145 <1 MW-DN-123S 05/07/08 < 191 MW-DN-123S 10/13/08 < 153 <1 MW-DN-1241 05/09/08 106000 +/- 10600 MW-DN-1241 10/10/08 94900 +/- 9550 <1 MW-DN-124S 05/09/08 92300 +/- 9210 MW-DN-124S 10/10/08 101000 +/- 10100 <2 MW-DN-1 171 05/08/08 332 +/- 128 MW-DN-1 171 10/08/08 < 169 <2 MW-DN-1 18S 05/06/08 2420 +/- 310 MW-DN-1 18S 10/09/08 1360 +/- 210 <1 MW-DN-1 191 05/05/08 1180 +/- 192 MW-DN-1 191 10/08/08 1860 +/- 256 <1 MW-DN-1 19S 05/05/08 < 183 MW-DN-1 19S 10/08/08 < 170 <1 MW-DN-121S 05/07/08 < 188 MW-DN-1221 05/07/08 < 188 MW-DN-122S 05/07/08 < 189 B-3
TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 . Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD DSP-105 10/09/08 < 15 <11 <1 <1 <4 <2 <3 <2 <3 < 35 <1 <1 <32 < 11 DSP-106 10/09/08 < 20 <14 <2 <2 <5 <1 <4 <2 <4 < 44 <1 <1 <42 < 12 DSP-107 10/09/08 < 19 <14 <2 <2 <5 <2 <3 <2 <3 < 38 <1 <2 < 41 < 14 DSP-108 10/09/08 < 17 <11 <1 <2 <4 <1 <3 <2 <3 < 40 <1 <1 < 39 < 13 DSP-1 17 10/14/08 < 11 <19 <1 <1 <3 <1 <2 <1 <2 < 58 <1 <1 < 37 < 14 DSP-121 10/14/08 < 12 <19 <1 <1 <3 <1 <2 <1 <2 < 67 <1 <1 <44 <14 DSP-122 10/08/08 < 18 <10 <1 <2 <4 <1 <3 <2 <3 < 45 <1 <1 <38 < 13 DSP-123 10/08/08 < 22 <13 <2 <2 <5 <2 <3 <2 <4 < 56 <1 <1 < 50 < 14 DSP-124 10/10/08 < 21 <14 <2 <2 <5 <2 <3 <2 <4 < 41 <1 <2 <43 < 14 MOSP-125 10/10/08 < 22 <14 <2 <2 <5 <2 <3 <2 <4 < 47 <2 <2 <47 < 14
.*DSP-126 10/13/08 < 11 <5 <1 <1 <3 <1 <2 <1 <2 < 75 <1 <1 <45 < 14 DSP-147 10/13/08 < 11 <22 <1 <1 <3 <1 <2 <1 <2 < 66 <1 <1 <44 < 13 DSP-148 10/15/08 < 10 <17 <1 <1 <2 <1 <1 <1 <2 < 55 <1 <1 <36 < 11 DSP-149R 10/15/08 < 11 <20 <1 <1 <2 <1 <2 <1 <2
- 62 <1 <1 < 37 < 13 DSP-150 10/09/08 < 17 <11 <1 <2 <4 <1 <3 <2 <3
- 40 <1 <1 < 35 < 11 DSP-151 10/09/08 < 17 <32 <1 <2 <5 <1 <2 <2 <3 < 65 <1 <1 <50 < 15 DSP-1 52 10/13/08 < 11 <16 <1 <1 <3 <1 <1 <1 <2 < 64 <1 <1 < 38 < 11 DSP-153 10/13/08 < 10 <5 <1 <1 <3 <1 <1 <1 <2 < 58 <1 <1 <38 < 11 DSP-154 10/14/08 < 9 29 +/-19 < 1 <1 <2 <0 <1 <1 <2 < 57 <1 <1 < 35 < 10 DSP-156 10/15/08 < 13 <23 <1 <1 <3 <1 <2 <1 <2 < 71 <1 <1 <54 < 11 DSP-157M 10/13/08 < 11 <21 <1 <1 <3 <1 <2 <1 <2 < 68 <1 <1 < 43 < 14 DSP-157S 10/13/08 < 11 <5 <1 <1 <3 <1 <1 <1 <2 < 66 <1 <1 <40 < 14 DSP-158M 10/14/08 < 14 <25 <1 <1 <4 <1 <2 <2 <2
- 87 <1 <1 <56 < 14 DSP-158S 10/14/08 < 11 <19 <1 <1 <3 <1 <1 <1 <2
- 67 <1 <1 <39 < 13 DSP-159M 10/14/08 < 12 <6 <1 <1 <3 <1 <2 <1 <2 < 74 <1 <1 <43 < 11 DSP-159S 10/14/08 < 12 <6 <1 <1 <3 <1 <1 <1 <2
- 70 <1 <1 <47 < 12 MW-DN-1011 10/08/08 < 20 <39 <2 <2 <6 <2 <4 <2 <4 < 30 <2 <2 < 36 < 13 MW-DN-101S 10/08/08 < 21 44 +/-28 < 2 <2 <5 <2 <4 <2 <4 <34 <2 <2 < 39 < 11 MW-DN-1021 10/07/08 < 35 <27 <3 <4 <9 <3 <6 <4 <7 < 35 <3 <3 <44 < 15 MW-DN-102S 10/07/08 < 20 <13 <2 <2 <5 <1 <3 <2 <4 < 34 <1 <2 <36 < 11 MW-DN-1031 10/13/08 < 10 <6 <1 <1 <3 <1 <1 <1 <2 < 85 <1 <1 <44 < 14 MW-DN-103S 10/13/08 < 10 <19 <1 <1 <3 <1 <1 <1 <2 < 73 <1 <1 <44 <15 MW-DN-104S 10/08/08 < 25 <16 <2 <2 <6 <2 <4 <3 <5 < 41 <2 <2 <45 < 13
TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD MW-DN-105S 10/09/08 < 21 47 +/- 25 < 2 <2 <5 <2 <4 <2 <4 < 35 <2 <2 < 37 < 12 MW-DN-106S 10/14/08 < 12 < 6 < 1 <1 <2 <1 <1 <1 <2 < 72 <1 <1 <41 < 15 MW-DN-107S 10/10/08 < 22 < 18 < 2 <2 <6 <2 <4 <3 <5 < 32 <2 <2 < 39 < 14 MW-DN-1081 10/08/08 38 + 22 < 16 < 2 <2 <6 <2 <4 <2 <4 < 39 <2 <2 <43 < 13 MW-DN-1091 10/07/08 < 28 < 44 < 3 <3 <7 <3 <5 <3 <6 < 28 <2 <3 < 39 < 13 MW-DN-109S 10/07/08 < 24 57 + 27 < 2 <2 <7 <2 <4 <3 <4 < 44 <2 <2 <49 < 15 MW-DN-1101 10/07/08 < 20 < 14 < 2 <2 <5 <1 <3 <2 <4 < 35 <1 <2 <38 < 12 MW-DN-11OS 10/07/08 < 22 < 16 < 2 <2 <5 <2 <4 <2 <4 < 42 <2 <2 < 41 < 14 MW-DN-111S 10/10/08 < 21 < 14 < 2 <2 <5 <1 <3 <2 <4 < 32 <2 <2 <33 < 11 t1,MW-DN-1121 10/07/08 < 21 < 14 < 2 <2 <5 <2 <3 <2 <4 < 41 <1 <2 < 41 < 14
&VlW-DN-112S 10/07/08 < 20 < 30 < 2 <2 <5 <1 <3 <2 <4 < 42 <1 <2 <41 < 13 MW-DN-1131 10/07/08 < 19 < 37 < 2 <2 <5 <1 <3 <2 <4 < 39 <1 <2 <41 < 12 MW-DN-113S 10/07/08 < 20 < 32 < 2 <2 <5 <2 <3 <2 <4 < 39 <1 <2 <40 < 13 MW-DN-1 141 10/10/08 < 20 < 30 < 2 <2 <5 <1 <3 <2 <3
- 38 <1 <2 < 39 < 11 MW-DN-1 14S 10/10/08 < 19 < 13 < 1 <2 <4 <2 <3 <2 <4 < 36 <1 <2 < 38 < 12 MW-DN-1 151 10/09/08 < 25 < 35 < 2 <2 <6 <2 <4 <3 <5 < 48 <2 <2 <47 < 15 MW-DN-115S 10/09/08 < 21 < 15 < 2 <2 <6 <2 <4 <2 <4 < 41 <2 <2 < 41 < 14 MW-DN-1161 10/08/08 < 22 < 16 < 2 <2 <6 <2 <4 <2 <4 < 49 <2 <2 <46 < 15 MW-DN-116S 10/08/08 < 22 < 35 < 2 <2 <5 <1 <3 <2 <4 < 53 <1 <2 <49 < 13 MW-DN-1171 10/08/08 < 19 < 13 < 1 <2 <4 <1 <3 <2 <3 < 41 <1 <2 <37 < 13 MW-DN-118S 10/09/08 < 21 < 44 <2 <2 <5 <2 <3 <2 <4 <44 <1 <2 < 47 < 15 MW-DN-1191 10/08/08 < 22 < 13 <2 <2 <5 <1 <3 <2 <4 < 49 <1 <1 <46 < 13 MW-DN-119S 10/08/08 < 21 < 14 < 2 <2 <5 <2 <3 <2 <4 < 46 <1 <2 <46 < 14 MW-DN-1201 10/14/08 < 11 < 5 < 1 <1 <3 <1 <1 <1 <2 < 72 <1 <1 <40 < 14 MW-DN-120S 10/14/08 < 11 < 20 < 1 <1 <3 <1 <1 <1 <2 < 73 <1 <1 <45 < 15 MW-DN-121S 10/13/08 < 11 < 17 < 1 <1 <3 <1 <1 <1 <2 < 71 <1 <1 <46 < 14 MW-DN-1221 10/13/08 < 13 < 7 < 1 <1 <3 <1 <1 <1 <2 < 101 <1 <1 <55 < 15 MW-DN-122S 10/13/08 < 12 < 5 < 1 <1 <3 <1 <1 <1 <2 < 89 <1 <1 < 50 < 14 MW-DN-1231 10/13/08 < 11 < 6 < 1 <1 <3 <1 <1 <1 <2 < 87 <1 <1 <44 <14 MW-DN-123S 10/13/08 < 10 < 20 < 1 <1 <3 <1 <2 <1 <2 < 89 <1 <1 <54 <15 MW-DN-1241 10/10/08 < 23 < 37 < 2 <2 <6 <2 <4 <2 <4 < 45 <2 <2 <46 < 13 MW-DN-124S 10/10/08 < 19 < 13 < 2 <2 <4 <1 <3 <2 <3 < 37 <1 <1 <38 < 11
TABLE B-II.1 CONCENTRATIONS OF TRITIUM AND STRONIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 SW-DN-101 05/12/08 3580 +/- 420 SW-DN-101 10/15/08 < 145 <1 SW-DN-102 05/12/08 1550 +/- 223 SW-pDN-1 02 10/15/08 265 +/- 105 <1 SW-DN-103 05/12/08 1450 +/- 213 SW-DN-103 10/15/08 183 +/- 102 <1 SW-DN-104 05/12/08 1470 +/- 215 SW-DN-104 10/15/08 419 +/- 118 <1 SW-DN-105 05/12/08 1540 +/- 222 SW-DN-105 10/15/08 199 +/- 108 <1 SW-DN-106 05/12/08 1240 +/- 195 SW-DN-106 10/15/08 229 +/- 110 <1 B-6
TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD SW-DN-101 10/15/08 < 10 < 18 <1 <1 <2 <1 <1 <1 <2 < 73 <1 <1 < 39 <11 SW-DN-102 10/15/08 < 10 <4 <1 <1 <2 <1 <1 <1 <2 < 66 <1 <1 < 39 < 15 SW-DN-1 03 10/15/08 < 14 46 +/- 27 <1 <1 <3 <1 <2 <1 <2 < 79 <1 <1 < 53 < .13 SW-DN-104 10/15/08 < 11 <6 <1 <1 <2 <1 <1 <1 <2 < 77 <1 <1 < 44 < 12 SW-DN-105 10/15/08 < 13 <6 <1 <1 <3 <1 <2 <1 <2 < 97 <1 <1 < 56 < 14 SW-DN-106 10/15/08 < 10 <7 <1 <1 <3 <1 <2 <1 <2 < 77 <1 <1 < 43 < 15
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