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Annual Radiological Environmental Operating Report for 2006
	ML071290126
Person / Time
Site:	Duane Arnold
Issue date:	12/31/2006
From:	; Environmental
To:	; Office of Nuclear Reactor Regulation
References
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	Download: ML071290126 (61)
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. Environmental, Inc.

Midwest Laboratory an Allegheny Technologles Co.

700 Landwehr Road

Northbrook, IL 60062-2310 ph. (847) 564-0700 ° fax (847) 564-4517 DUANE ARNOLD ENERGY CENTER CEDAR RAPIDS, IOWA DOCKET NO. 50-331 REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Annual Radiological Environmental Operating Report January I to December 31, 2006 Prepared and submitted by ENVIRONMENTAL, Inc.

Midwest Laboratory Project No. 8001 Approved :

Loborva anager

PREFACE Staff members of the Environmental, Inc., Midwest Laboratory were responsible for the acquisition of data presented in this report, with the exception of Appendices D and E, which were completed by DAEC personnel. All environmental samples, with the exception of aquatic, were collected by personnel of DAEC. Aquatic samples were collected by the University of Iowa Hygienic Laboratory.

The report was prepared by Environmental, Inc., Midwest Laboratory, with the exception of Appendices D and E, which were prepared by DAEC personnel.

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TABLE OF CONTENTS No. Page P R E F AC E ...................................................................................................................... ii List of Tables ........................................................................................................ v List o f F igu re s ................................................................................ .............................. v i

1.0 INTRODUCTION

..................................................................................................... 1 2.0

SUMMARY

.................................................................................................................... 2 3.0 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM .............................. 3 3.1 Program Design and Data Interpretation ......................................................... 3 3.2 Program Description .................................................................................... 4 3.3 Program Execution ...................................................................................... 5 3.4 Laboratory Procedures ............................................................................... 6 3.5 Program Modifications ................................................................................. 7 4.0 RESULTS AND DISCUSSION ................................................................................ 8 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents .......................... 8 4.2 Program Findings ........................................................................................ 8 5.0 TABLES AND FIGURES ....................................................................................... 12

6.0 REFERENCES

CITED .......................................................................................... 29 APPENDICES A Interlaboratory Comparison Program Results .................................................... A-1 B Data Reporting Conventions ............................................................................... B-1 C Effluent Concentration Limits for Radioactivity in Air and Water Above Background in Unrestricted Areas ......................................................... C-1 D Summary of the Land Use Census ...................................................................... D-1 E Annual Radiation Dose Assessment .................................................................... E-1

TABLE OF CONTENTS (continued)

PART II Paqe Data Tabulations and Analyses ..................................................................................... i iv

LIST OF TABLES No. Pae 5.1 Characteristic Properties of Isotopes Quantified in Gamma-spectroscopic A na lyse s ................................................................................................ . . 13 5.2 Sample Collection and Analysis Program .............................................................. 14 5.3 Sampling Locations, DAEC .................................................................................... 17 5.4 Type and Frequency of Collections ....................................................................... 19 5.5 Sample Codes Used in Table 5.4 .......................................................................... 20 5.6 Missed Collections and Analyses .......................................................................... 21 5.7 Radiological Environmental Monitoring Program Summary ....................................... 22 In addition, the following tables are in the Appendices:

Appendix A A-1 Interlaboratory Comparison Program Results .................................................... A1-1 A-2 Interlaboratory Comparison Program Results, Thermoluminescent Dosimeters (TLDs) ...................................................................................... A2-1 A-3 In-house Spiked Samples ......................................................................................... A3-1 A-4 In-house "Blank" Samples ........................................................................................ A4-1 A-5 In-house "Duplicate" Samples ............................................................................. A5-1 A-6 Department of Energy MAPEP comparison results .................................................. A6-1 Attachment A: Acceptance criteria for spiked samples ............................................ A-2 Appendix C C-1 Effluent Concentration Limits for Radioactivity in Air and Water Above Background in Unrestricted Areas ............................................................... C-2 v

LIST OF FIGURES No. PaQe 5.1 Radiological Environmental Monitoring Program Sampling Stations near the Duane Arnold Energy Center .................................................................... 27 5.2 Radiological Environmental Monitoring Program Sampling Stations Outside 0 .5 Mile s ................................................................................................ . . 28 vi

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiological Environmental Monitoring Program conducted by Environmental, Inc., Midwest Laboratory at the Duane Arnold Energy Center, Palo, Iowa, during the period January - December, 2006. This Program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the Plant on its surroundings.

Tabulation of the individual analyses made during the year are included in Part II of this report.

The Duane Arnold Energy Center (DAEC) is a boiling water reactor, located in Linn.County, Iowa, on the Cedar River, and owned and operated by FPL Energy. Initial criticality was attained on March 23, 1974. The reactor reached 100% power on August 12, 1974. Commercial operation began on February 1, 1975.

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2.0

SUMMARY

The Radiological Environmental Monitoring Program, as required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Duane Arnold Energy Center, is herein described. Results for the year 2006 are summarized and discussed.

Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Duane Arnold Energy Center.

No effect on the environment is indicated in the areas surrounding the Site of the Duane Arnold Energy Center.

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3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.1 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program at the Duane Arnold Energy Center (DAEC) is to assess the impact of the plant on its environment. For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).

Sources of environmental radiation include the following:

(1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; and (4) Industrial and medical radioactive waste.

In interpreting the data, effects due to the DAEC operation must be distinguished from those due to other sources.

A major interpretive aid in assessment of these effects is the design of the monitoring program at the DAEC which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream). A station effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.

An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the DAEC site. The DAEC's monitoring program includes analyses for strontium-90 and iodine-131, which are fission products, and tritium, which is produced by cosmic rays, atmospheric nuclear detonations, and also by nuclear power plants.

Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, and cerium-144. These three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products ten (10) days after reactor shutdown. On the other hand, ten (10) days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud,1963). The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the next group, manganese-54, cobalt-58 and-60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of nuclear power plant effluents, but are not produced in significant quantities by nuclear detonations. Nuclides of the final group, beryllium-7, which is of cosmogenic origin, and potassium-40, a naturally-occurring isotope, were chosen as calibration monitors and should not be considered radiological impact indicators.

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3.1 Program Design and Data Interpretation (continued)

Characteristic properties of isotopes quantified in gamma-spectroscopic analysis are presented in Table 5.1. Other means of distinguishing sources of environmental radiation can be employed in interpreting the data. Current radiation levels can be compared with previous levels, including those measured before the Plant became operational. Results of the DAEC's Monitoring Program can be related to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the. environment, e.g., atmospheric nuclear detonations.

3.2 Program Description The sampling and analysis schedule for the environmental radiological monitoring program at the DAEC is summarized in Table 5.2 and is briefly reviewed below. Table 5.3 defines the sampling location codes used in Table 5.2 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site. The types of samples collected at each location and the frequency of collections are presented in Table 5.4 using codes defined in Table 5.5.

To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at eight locations. Airborne iodine is collected by continuous pumping through charcoal filters. Seven of the eight locations are indicators and one is a control (D-13).

Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity. If gross beta activity exceeds ten times the yearly mean of the control samples, gamma isotopic analysis is performed. Quarterly composites of airborne particulates from each location are analyzed for gamma emitting isotopes.

Charcoal filter samples are analyzed weekly for iodine-1 31.

Ambient gamma radiation is monitored at the eight air sampling locations. In addition, gamma radiation is monitored at thirty-four special interest locations: eighteen in a circle within a 0.5 mi.

radius from the DAEC stack; six in 22.50 sectors within 1 mi. from the DAEC stack; ten in 22.50 sectors between 1 and 3 miles from the DAEC stack and four locations greater than 3 miles from the DAEC stack. TLDs are placed at each location and are exchanged and analyzed quarterly.

Precipitation is collected monthly from one location and analyzed for gamma-emitting isotopes.

Quarterly composites are analyzed for tritium.

Milk samples are collected monthly from one indicator and one control location during the non-grazing season, October through April, and biweekly during the grazing season, May 1 through September 30. The samples are analyzed for iodine-131 and gamma-emitting isotopes.

For additional monitoring of the terrestrial environment, grain, hay and broad leaf vegetation samples are collected annually, as available, from seven locations: one control (D-108) and six indicators (D-16, D-57, D-58, D-72, D-96, and D-109). Grain, hay and broad leaf (green leafy) vegetation samples are analyzed for gamma-emitting isotopes and at least one broad leaf vegetation is analyzed for iodine-131.

If cattle are, slaughtered for home use, a meat sample is collected annually, during or immediately following a grazing period from animals grazing on-site. The sample is analyzed for gamma-emitting isotopes.

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Program Description (continued)

Potable ground water is collected quarterly from a treated municipal water system (D-53), the inlet to the municipal water treatment system (D-54), three additional indicator locations (D-55, D-57, D-58) and one control location, (D-72). An additional six site monitoring wells were added to the program in 2006. The samples are analyzed for gross beta and tritium. If gross beta activity exceeds ten times the yearly mean of the control samples, gamma isotopic, strontium-89 and strontium-90 analyses are performed.

Soil samples are collected once per year at two indicator locations (D-15 and D-16). The samples are analyzed for strontium-90 and gamma-emitting isotopes.

Surface water is collected monthly from two river locations, D-50 (Inlet, control) and D-51 (Discharge). The sewage effluent location (D-107) is also monitored. All monthly samples are analyzed for gamma-emitting isotopes. Tritium analyses are performed on quarterly composites from each location.

The aquatic environment is also monitored by upstream and downstream (D-49 and D-61) semiannual collections of fish. River bottom sediment is collected semiannually at the plant's intake and discharge (D-50 and D-51) and downstream of the sewage plant (D-1 07). The samples are analyzed for gamma-emitting isotopes.

3.3 Proqram Execution The program was executed as described in the preceding section with the following exceptions.

(1) Air Particulates / Air Iodine:

No air particulate / air iodine sample was available from location D-07 for the week ending 03-09-06. The air sampler station was relocated.

The air particulate filter from location D-16 was missing for the week ending 08-23-06.

The filter was lost in the field.

(2) Milk:

No milk was available from location D-96 for all of 2006. The herd has been sold.

No milk was available from location D-101 for all of 2006. The location has been removed from the program.

(3) Vegqetation No forage or broadleaf vegetation samples were available from the locations D-58, D-96 and D-109 for the October, 2006 collection.

(4) Thermoluminescent Dosimeters:

TLD for location D-1 was missing for the first quarter, 2006. The TLD was lost in the field.

TLD, location D-2 was missing for the second quarter, 2006. The TLD was lost in the field.

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3.3 Proaram Execution (continued)

(5) Sediments River sediments taken 07/19/06 did not meet the required six month collection frequency and should be characterized as missed samples.

(6) Corrections to the 2005 Report:

Section 3.3 states, that samples were not collected from location D-01, D-02, D-08 and D-10 after the week ending 12 March 2005. The date specified in the report should have been 12 May 2005 not 12 March 2005.

The date specified in the report for the first milk sample collected at sample location D-101 was 01-06-04. The date of collection should have been 01-04-05.

An Airborne Iodine sample taken on 12/8/05 was not received at the laboratory until 12/22/2005. The sample should have been characterized as a "missed analyses" due to the extended delay.

River sediments taken 06/27/05 did not meet the required six month collection frequency and should be characterized as missed samples, due to the delay.

Table 5.6 and Part II, Section 2.0 should have indicated that milk samples from sample location D 101 were not collected for the entire year.

Table 5.6 and Part II, Section 2.0 should have indicated that milk samples from sample location D 96 were not available after 9/7/2005.

3.4 Laboratory Procedures The iodine-131 analyses in milk were made using a sensitive radiochemical procedure involving separation of the iodine using an ion-exchange method, solvent extraction and subsequent beta counting.

Gamma-spectroscopic analyses were performed using high-purity germanium (HPGe) detectors.

Levels of iodine-131 in vegetation and concentrations of airborne iodine-131 in charcoal samples were also determined by gamma spectroscopy.

Tritium was measured by liquid scintillation.

Analytical Procedures used by Environmental, Inc. are on file and are available for inspection.

Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.

Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2003 ). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs. Results obtained in crosscheck programs are presented in Appendix A.

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3.5 Program Modifications Milk Milk from location D-96 was no longer available after September 7, 2005. The location was removed from the program in 2006.

Goat milk was not available from location D-101 for 2005 and 2006.The goat was sold. The location was removed from the program in July, 2006.

Surface water Surface water collections at location D-61, (0.5 mi. from Plant discharge) were initiated in November of 2006. The samples are analyzed for tritium and gamma emitting isotopes.

Ground water Ground water monitoring of six on-site wells was added to the REMP in the third quarter, 2006, for analysis of gross beta and tritium. Analyses for strontium-89, strontium-90 and gamma emitting isotopes will be performed if the gross beta activity exceeds ten times the yearly mean of the potable water well control.

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4.0 RESULTS AND DISCUSSION All collections and analyses were made as scheduled, except for the listing in Table 5.6.

Results are summarized in Table 5.7 as recommended by the Nuclear Regulatory Commission. For each type of analysis and sample medium, the table lists the mean and range of all indicator and control locations, as well as that location with the highest mean and range.

Tabulated results of measurements are not included in this section, although reference to these results will be made in discussion. A complete tabulation of results for 2006 is contained in Part II of the Annual Report on the Radiological Environmental Monitoring Program for the Duane Arnold Energy Center.

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 2006.

4.2 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in 2006.

Airborne Particulates The average annual gross beta concentrations in airborne particulates were similar at indicator 3

and control locations (0.029 and 0.027 pCi/m , respectively) and similar to levels observed from 1991 through 2005. The results are tabulated below.

Year Indicators Controls Year Indicators Contrls 3 3 Concentration ( pCi/rm) Concentration ( pCi/rn) 1991 0.023 0.022 1999 0.026 0.027 1992 0.022 0.023 2000 0.026 0.027 1993 0.022 0.023 2001 0.026 0.026 1994 0.023 0.024 2002 0.027 0.027 1995 0.025 0.024 2003 0.029 0.029 1996 0.024 0.023 2004 0.028 0.028 1997 0.023 0.023 2005 0.031 0.031 1998 0.024 0.024 2006 0.029 0.027 Average annual gross beta concentrations in airborne particulates.

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and AI-Salih, 1955) was detected in all samples, with an average activity of 0.075 pCi/mn for all locations. All other gamma-emitting isotopes were below their respective LLD limits.

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Proaram Findinos (continued)

Airborne Iodine 3

Weekly levels of airborne iodine-1 31 were below the lower limit of detection (LLD) of 0.03 pCi/m in all samples.

Ambient Radiation (TLDs)

At twelve air sampling locations, the TLD readings averaged 17.5 and 17.4 mR/quarter for indicator and control locations, respectively. At locations within a half mile, one mile and three mile radius of the stack, measurements averaged 19.1 mR/quarter, 19.9 mR/quarter and 17.3 mR/quarter, respectively. The average for all locations was 18.4 mR/quarter. This is lower than the estimated average natural background radiation for Middle America, 19.5 mR/quarter, which is based on data on Pages 71 and 108 of the report, "Natural Background Radiation in the United States" (National Council on Radiation Protection and Measurements, 1975). The terrestrial absorbed dose (uncorrected for structural and body shielding) ranges from 8.8 to 18.8 mrad/quarter and, averages 11.5 mrad/quarter for Middle America. Cosmic radiation and cosmogenic radionuclides contribute 8.0 mrad/quarter for a total average of 19.5 mrad/quarter.

No plant effect is indicated.

Precipitation Precipitation from an on-site location was analyzed for tritium and gamma-emitting isotopes.

No tritium activity was measured above the LLD of 182 pCi/L in any precipitation sample tested.

No gamma-emitting isotopes were detected.

During October, 2006, an additional twenty-seven samples were collected in closer proximity to the reactor building vent shaft release point. Downwind of the release point, concentrations of tritium measured from 158 to 2,666 pCi/L. No tritium was detected in the upwind samples. In no case did concentrations exceed the threshold for reportability of 30,000 pCi/L. Results of the testing are listed in Part II, Appendix A, Supplemental Analyses.

Milk Iodine-1 31 results were below the detection limit of 0.5 pCi/L in all samples.

No gamma-emitting isotopes, except naturally occurring potassium-40, were detected in any milk samples. This is consistent with the finding of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).

In summary, milk data for 2006 show no radiological effects of plant operation.

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Proaram Findinas (continued)

Ground Water (potable)

The annual mean for gross beta activity averaged 3.5 pCi/L, similar to levels observed from 1991 through 2005. The location, with the highest mean (4.4 pCi/L) was D-58, a farm 1.0 mile distant from the plant.

Tritium activity measured below the LLD of 193 pCi/L in all samples. No effect from plant operation is indicated.

Ground Water (Site Monitoring Wells)

Analysis of water from six on-site monitoring wells was initiated in 2006. Three of the six wells are shallow wells and the other three are of intermediate depth.

The annual mean for gross beta activity for the intermediate depth wells measured 2.1 pCi/liter and was 4.4 pCi/liter in the shallow wells.

No tritium was identified in samples taken from the intermediate depth wells. Tritium was identified in two of six samples taken from the shallow wells and has been attributed to "washout" of tritium from gaseous effluents. (See Program Findings for Precipitation)

Ve~getation Iodine-131 concentrations in broadleaf vegetation were below the LLD level of 0.060 pCi/g wet weight in allsamples.

Except for potassium-40, which was observed in all vegetation samples ( broadleaf, grain, and forage), all other gamma-emitting isotopes were below detection limits. No effect from plant operation is indicated.

Soil Strontium-90 concentrations in soil were below the LLD level of 0.016 pCi/g dry weight in all samples. Cesium-137 activity measured 0.13 pCi/g dry weight in one of two on-site locations.

The cesium-137 activity is similar or less than levels observed from 1991 through 2005, these levels are generally attributable to deposition of fallout from previous decades.

Naturally-occurring potassium-40 averaged 12.23 pCi/g dry weight. No effect from the plant operation is indicated.

Surface Water Measurable tritium was detected on site in one of the four D-107 (sewage effluent) composites, at an average concentration of 287 pCi/L. This is below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L. For all remaining surface water collections, tritium levels were measured below the LLD level of 193 pCi/L.

All gamma-emitting isotopes were below their respective LLDs.

No plant effect on surface water is indicated.

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Pro.gram Findings (continued)

Fish All gamma-emitting isotopes, except naturally-occurring potassium-40, in edible portions were below detection limits. The potassium-40 level was similar at both indicator and control locations (3.19 and 3.27 pCi/g wet, respectively). No plant effect on the fish population is indicated.

River Sediments River sediments were collected in July and September, 2006, and analyzed for gamma-emitting isotopes. Potassium-40 activity ranged from 4.86 - 9.68 pCi/g dry weight and averaged 7.71 pCi/g dry weight.

Trace Cs-137 activity was detected in the control sample (D-50) at a concentration of 0.033 pCi/gdry weight.

All other gamma-emitting isotopes were below detection limits. There is no indication of a plant effect.

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5.0 TABLES AND FIGURES 12

Table 5.1 Characteristic properties of isotopes quantified in gamma-spectroscopic analyses.

Designation Comment Isotope Half-life8

1. Naturally Occurring A. Cosmogenic Produced by interaction of cosmic Be-7 53.2 d rays with atmosphere B. Terrestrial Primordial K-40 1.26 x 109 y II. Fission Products b Nuclear accidents and detonations constitute the major environmental source.

A. Short-lived 1-131 8.04 d Ba-140 12.8 d B. Other than Short-lived Nb-95 35.15 d Zr-95 65 d Ru-1 03 39.35 d Ru-106 368.2 d Cs-1 34 2.061 y Cs-137 30.174 y Ce-141 32.5 d Ce-144 284.31 d Ill. Activation Products Typically found in nuclear power plant Mn-54 312.5 d effluents Fe-59 45.0 d Co-58 70.78 d Co-60 5.26 y Zn-65 245 d a

Half-lives are taken from Appendix E of Environmental Quarterly, 1 January 1978, EML-334 (U. S. Department of b Energy, 1978).

Includes fission-product daughters.

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Table 5.2 Sample collection and analysis program.

Sampling Location Exposure Pathway and/or Sample Description Sampling and Collection Type and Frequency Sample Type Point Frequency of Analysisa Airborne 3 Hiawatha Continuous operation of Analyze for gross beta activity Particulates 5 Palo sampler with sample more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after filter 6 Center Point collection at least once per change. Perform gamma isotopic 7 Shellsburg week or as required by dust analysis on each sample having 11 Toddville loading gross beta activity greater than ten 13 Alburnett (C) times the yearly mean of the 15 On-site North control samples.

16 On-site South Composite weekly samples to form a quarterly composite (by location). Analyze quarterly composite for gamma isotopic.

Airborne Iodine 3 Hiawatha Continuous operation of Analyze each cartridge for iodine-5 Palo sampler with sample 131.

6 Center Point collection at least once per 7 Shellsburg week.

11 Toddville 13 Alburnett (C) 15 On-site North 16 On-site South Ambient 1-2 (C), One dosimeter continuously Read gamma radiation dose Radiation 8, 10 at each location, quarterly.

Dosimeters are changed at 3, 5-7, Air Particulate least quarterly.

11, 13, Locations 15, 16 17-23, < 0.5 mi. of Stack 28-32, 43-48 < 1.0 mi. of Stack 82-86, 91 33-42 -<3.0 mi. of Stack Surface Water 50 Plant Intake (C) Once per month. Tritium and gamma isotopic 51 Plant Discharge analyses of each sample (by location).

61 0.5 mi. downstream 107 Plant Sewage Dischange (C) Denotes control location. All other locations are indicators.

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Table 5.2 Sample collection and analysis program, (continued).

Sampling Location Exposure Pathway and/or Sample Description Sampling and Collection Type and Frequency Sample Type Point Frequency of Analysisa Ground Water 53 Treated Municipal Grab sample at least Gross beta and tritium activity (potable) 54 Inlet to Municipal once per quarter analysis on quarterly sample. If Water Treatment gross beta is greater than ten System times the yearly mean of control 55 On-site well samples, perform gamma 57, 58 Wells off-site and isotopic and Sr-89 and Sr-90 72 (C) within 4 km of DAEC analyses.

Ground Water D-111 On-site wells MW-01A (Monitoring B (SSE)

Wells) D-1 12 On-site wells MW-02A B (ESE)

D-1 13 On-site wells MW-03A B (NW)

River 50 Plant Intake (C) At least once every Gamma isotopic analysis of each Sediment 51 Plant Discharge six months, sample.

107 Sewage Effluent Canal (on-site)

Vegetation 16, 57, Farms that raise food Annually at harvest Gamma isotopic analysis of 58, 72, crops time. One sample of edible portions.

94, 96, each: grain, green 109 leafy, and forage. At 1-131 analysis on broadleaf least one sample vegetation.

108 (C) should be broadleaf vegetation.

Fish 49 Cedar River upstream One sample per 6 Gamma isotopic analysis on of DAEC not months (once during edible portions.

influenced by effluent January through July (C) and once during August through 61 Downstream of DAEC December).

in influence of effluent Milkb 108 (C) Control Farm At least once per two During the grazing season:

weeks during the Gamma isotopic and iodine-131 grazing season. analyses of each sample.

109 Dairy Farm within 10 At least once per Duringq the non-.qrazing season:

miles of Site month during the Gamma isotopic and iodine-1 31 non-grazing season. analyses of each sample.

(C) denotes control location. All other locations are indicators.

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Table 5.2 Sample collection and analysis program, (continued).

Sampling Location Exposure Pathway and/or Sample Description Sampling and Collection Type and Frequency Sample Type Point Frequency of Analysis3 Precipitation On-site Monthly Gamma isotopic on all samples.

Tritium on quarterly composites.

Meatc On-site Annually Gamma Isotopic Soil 15, 16 On-site Annually Gamma Isotopic and Sr-90.

Gamma isotopic analysis and analysis for gamma-emitting nuclides refer to high resolution gamma ray spectrum analysis. Any radionuclide detected at a concentration greater than the lower limit of detection (LLD) should be reported quantitatively; conversely, any radionuclide concentration less than the LLD should not be reported.

The grazing season is considered to be May I through September 30.

C Meat was not collected in 2006; no animals slaughtered for home use.

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Table 5.3 Sampling locations, Duane Arnold Energy Center.

Sampling Location Code Type Sampling Location Description Distance and Direction Point from Site Stack D-1 C 1 Cedar Rapids 11 mi @ 135* SE D-2 C 2 Marion 11 mi @ 125' ESE D-3 3 Hiawatha 7 mi@ 130' SE D-5 5 Palo 3 mi @ 2000 SSW D-6 6 Center Point 7 mi @0' N D-7 7 Shellsburg 6 mi @ 2550 W D-8 8 Urbana 10 mi @ 3450 NW D-10 10 Atkins 9 mi @ 2100 SSW D-11 11 Toddville 4 mi @ 90' E D-13 C 13 Alburnett 9 mi @ 700 ENE D-15 15 On-site, Northwest 0.5 mi @ 3050 NW D-1 6 16 On-site, South 0.5 mi @ 1900 SSE D-17 17 On-site, N 0.5 mi N D-1 8 18 On-site, NNE 0.5 mi NNE D-19 19 On-site, NE 0.5 mi NE D-20 20 On-site, ENE 0.5 mi ENE D-21 21 On-site, ENE 0.5 mi ENE D-22 22 On-site, E 0.5 mi E D-23 23 On-site, ESE 0.5 mi ESE D-28 28 On-site, WSW 0.5 mi WSW D-29 29 On-site, W 0.5 mi W D-30 30 On-site, WNW 0.5 mi WNW D-31 31 On-site, NW 0.5 mi NW D-32 32 On-site, NNW 0.5 mi NNW D-33 33 3 miles N 3.0 mi N D-34 34 3 miles NNE 3.0 mi NNE D-35 35 3 miles NE 3.0 mi NE D-36 36 3 miles ENE 3.0 mi ENE D-37 37 3 miles E 3.0 mi E D-38 38 3 miles ESE 3.0 mi ESE D-39 39 3 miles SE 3.0 mi SE D-40 40 3 miles SSE 3.0 mi SSE D-41 41 3 miles S 3.0 mi S D-42 42 3 miles SSE 3.0 mi SSE D-43 43 1 mile SSw 1.0 mi SSW D-44 44 1 mile WSW 1.0 mi WSW D-45 45 1 mile W 1.0 mi W D-46 46 1 mile WNW 1.0 mi WNW 17

Table 5.3 Sampling locations, Duane Arnold Energy Center (continued).

Sampling Location Code Type Sampling Location Description Distance and Direction Point from Site Stack D-47 47 1 mile WNW 1.0 mi WNW D-48 48 1 mile NW 1.0 mi NW D-49 C 49 Lewis Access, upstream of DAEC 4.0 mi NNW D-50 C 50 Plant Intake D-51 51 Plant Discharge D-53 53 Treated Municipal Water D-54 54 Inlet, Municipal Water Treatment System D-55 55 On-site Well D-57 57 Farm (Off-site Well) 1.0 mi WSW D-58 58 Farm (Off-site Well) 0.5 mi WSW-SW D-61 61 0.5 mi downstream of plant discharge D-72 C 72 Farm 2.0 mi SSW D-82 82 On-site, SE 0.5 mi SE D-83 83 On-site, SSE 0.5 mi SSE D-84 84 On-site, S 0.5 mi S D-85 85 On-site, SSW 0.5 mi SSW D-86 86 On-site, SW 0.5 mi SW D-91 91 On-site, N 0.5 mi N D-94 94 Farm 2.7 mi N D-96 96 Farm 8.0 mi SSW D-101 101 Farm 4.0 mi E D-107 107 Sewage Effluent Canal On-site D-108 C 108 Farm 17.3 mi. SW D-109 109 Farm 3.6 mi. SW D-111 110 Monitoring wells, MW-01A, B On-site, 210m SSE D-1 12 111 Monitoring wells, MW-02A, B On-site, 280m ESE D-113 112 Monitoring wells, MW-03A, B On-site, 190m NW "C" denotes control location. All other locations are indicators.

18

Table 5.4 Type and Frequency of collection.

Location Location Type Weekly Monthly Quarterly Semiannually Annually D-1 C AP TLD D-2 C AP, Al TLD D-3 AP, Al TLD D-5 AP, Al TLD D-6 AP, Al TLD D-7 AP, Al TLD D-8 AP, Al TLD D-10 AP TLD D-11 AP, Al TLD D-13 C AP, Al TLD D-15 AP, Al TLD SO D-16 AP, Al TLD SO, G D-17 to D-23 TLD D-28 to D-42 TLD D-43 to D-48 TLD D-49 C F D-50 C SW RS D-51 SW RS D-53 WW D-54 WW D-55 WW D-57 WW G D-58 WW G D-61 SWb F D-72 C WW G D-82 to D-86 TLD D-91 TLD D-94 G D-96 G D-107 SW RS D-108 C MI G D-109 MI G On-site P ME D-1 11 to D-1 13 a WW "C" denotes control location. All other locations are indicators.

a Locations added third quarter, 2006.

b Location added in November, 2006.

19

Table 5.5. Sample codes used in 5.4.

Code Description AP Airborne Particulates Al Airborne Iodine TLD Thermoluminescent Dosimeter P Precipitation Ml Milk WW Well Water G Vegetation ME Meat SO Soil SW Surface Water F Fish BS River Sediment 20

Table 5.6. Missed collections and analyses, Duane Arnold Energy Center.

Sample Collection Date Type Analysis Location(s) or Period Comments M! Gamma, 1-131 D-96 2006 No sample; herd sold.

Ml Gamma, 1-131 D-101 2006 No sample; goat sold.

AP/I Beta, 1-131 D-07 03-09-06 Electric off due to relocation.

TLD Ambient Gamma D-1 1st Qtr TLD missing in field.

TLD Ambient Gamma D-2 2nd Qtr TLD missing in field.

BS a Gamma D-50, D-51, 07-19-06 Sediments were collected, but sampling D-107 frequency requirements were not met.

AP Beta D-16 08-23-06 Filter lost in field.

VE Gamma D-58 10-02-06 No broadleaf or forage sample received.

VE Gamma D-96 10-02-06 No vegetation samples received.

VE Gamma D-109 10-02-06 No broadleaf sample received.

Constitutes a missed sample per the minimum requirements specified by the ODAM.

21

Table 5.7 Radiological Environmental Program Summary.

Name of Facility Duane Arnold Energy Center Docket No. 50-331 Location of Facility Linn, Iowa Reporting Period January-December, 2006 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDD Mean (F)c Mean (F)' Mean (F)c Routine3 (Units) Analyses' Rangec Location" Rangec Rangec Results Airborne GB 414 0.004 0.029 (361/362) D-3, Hiawatha 0.030 (52/52) 0.027 (52/52) 0 Particulates (0.006-0.097) 7 mi. SE (0.008-0.097) (0.010-0.053)

(pCi/me) GS 31 Be-7 0.020 0.074 (27/27) D-3, Hiawatha 0.087 (4/4) 0.069 (4/4) 0 (0.046-0.094) 7 mi. SE (0.058-0.105) (0.047-0.092)

Nb-95 0.0022 < LLD < LLD 0 Zr-95 0.0031 < LLD < LLD 0 Ru-103 0.0016 < LLD < LLD 0 Ru-106 0.0089 < LLD < LLD 0 Cs-134 0.0010 < LLD < LLD 0 Cs-137 0.0010 < LLD < LLD 0 Ce-141 0.0028 < LLD < LLD 0 Ce-144 0.0057 < LLD < LLD. 0 Airborne Iodine 1-131 414 0.030 < LLD < LLD 0 (pCi/ma)

TLD, AP Locations Gamma 46 1.0 17.5 (36/36) D-8, Urbana 21.2 (4/4) 17.4 (10/10) 0 (mR/quarter) (12.7-21.8) 10 mi. NW (20.2-21.8) (13.3-22.4)

TLD, within 0.5 mi. from Stack Gamma 72 1.0 19.1 (72/72) D-31, On-site 23.1 (4/4) None 0 (mR/quarter) (12.5-25.5) 0.5 mi. NW (21.2-25.5)

TLD, within 1.0 mi. from Stack Gamma 24 1.0 19.9 (24/24) D-48, 22.1 (4/4) None 0 (mR/quarter) (14.2-23.9) 1 mi. NW (20-23.9)

TLD, within 3.0 mi. from Stack Gamma 40 1.0 17.3 (40/40) D-37, 21.5 (4/4) None 0 (mR/quarter) (13.5-22.7) 3 mi. E (19.5-22.7)

Precipitation (pCi/L) H-3 4 182 < LLD < LLD 0 GS 12 Mn-54 15.7 < LLD < LLD 0 Fe-59 26.2 < LLD < LLD 0 Co-58 12.2 < LLD < LLD 0 Co-60 16.9 < LLD < LLD 0 Zn-65 30.3 < LLD < LLD 0 Nb-95 19.2 < LLD < LLD 0 Zr-95 33.5 < LLD < LLD 0 1-131 35.7 < LLD < LLD 0 Cs-134 22.5 < LLD < LLD 0 Cs-137 16.5 < LLD < LLD 0 Ba-140 105.2 < LLD < LLD 0 La-140 25.6 < LLD < LLD 0 22

Table 5.7 Radiological Environmental Program Summary.

Name of Facility Duane Arnold Energy Center Docket No. 50-331 Location of Facility Linn, Iowa Reporting Period January-December, 2006 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD" Mean (F)c Mean (F)' Mean (F)c Routine (Units) Analyses' Rangec Location' Rangec Rangec Resultse Milk (pCi/L) 1-131 36 0.5 < LLD < LLD 0 GS 36 K-40 100 1298 (18/18) D-108, Farm 1368 (18/18) 1368 (18118) 0 (1152-1439) 17.3 mi. SW (1139-1657) (1139-1657)

Cs-134 5 < LLD < LLD 0 Cs-137 5 < LLD < LLD 0 Ba-140 60 < LLD < LLD 0 La-140 5 < LLD < LLD 0 Ground Water, GB 24 1.3 3.5 (13/20) D-58, Farm 4.4 (4/4) < LLD 0 potable (pCi/L) (1.4-5.7) 1 mi. WSW-SW (2.5-5.7)

H-3 24 330 < LLD < LLD 0 Monitoring GB 12 1.3 3.2 (12/12) MW-2A, shallow 4.7 (2/2) None 0 wells (pCi/L) (1.4-6.0) Onsite, 280m ESE (3.4-6.0)

H-3 12 330 489 (2/12) MW-01A (shallow) 489 (2/2) None 0 (473-504) Onsite, 210m SSE (473-504)

Broadleaf 1-131 3 0.060 < LLD < LLD 0 Vegetation (pCi/g wet) GS 3 K-40 0.5 6.75 (2/2) D-58, Farm 6.77(1/1) 6.29(1/1) 0 (6.73-6.77) 1 mi. WSW-SW Mn-54 0.030 < LLD < LLD 0 Co-58 0.043 < LLD < LLD 0 Co-60 0.057 < LLD < LLD 0 Nb-95 0.039 < LLD < LLD 0 Zr-95 0.110 < LLD < LLD 0 Ru-1 03 0.039 < LLD < LLD 0 Ru-106 0.28 < LLD < LLD 0 Cs-134 0.027 < LLD < LLD 0 Csý137 0.030 < LLD < LLD 0 Ce-141 0.074 < LLD < LLD 0 Ce-144 0.24 < LLD < LLD 0 23

Table 5.7 Radiological Environmental Program Summary.

Name of Facility Duane Arnold Energy Center Docket No. 50-331 Location of Facility Linn, Iowa Reporting Period January-December, 2006 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDO Mean (F)C Mean (F)' Mean (F)c Routine (Units) Analysesa Range' Location' Rangec Rangec Results' Vegetation GS 11 (Grain) K-40 0.5 4.28 (9/9) D-16, On-site 8.03 (2/2) 2.89 (2/2) 0 (pCi/g wet) (1.97-13.63) 0.5 mi. SSE (2.42-13.63) (2.46-3.32)

Mn-54 0.068 <.LLD < LLD 0 Co-58 0.072 < LLD < LLD 0 Co-60 0.072 < LLD < LLD 0 Nb-95 0.077 < LLD - < LLD 0 Zr-95 0.17 < LLD - < LLD 0 Ru-103 0.073 < LLD - < LLD 0 Ru-106 0.45 < LLD - < LLD 0 Cs-134 0.057 < LLD - < LLD 0 Cs-137 0.057 < LLD - < LLD 0 Ce-141 0.127 < LLD - < LLD 0 Ce-144 0.40 < LLD - < LLD 0 Soil Sr-90 2 0.016 < LLD - None 0 (pCi/g dry)

GS 2 K-40 0.5 12.23 (2/2) D-16, On-site 14.63 (1/1) None 0 (9.83-14.63) 0.5 mi. SSE Mn-54 0.035 < LLD - None 0 Fe-59 0.050 < LLD - None 0 Co-58 0.038 < LLD - None 0 Co-60 0.025 < LLD - None 0 Zn-65 0.082 < LLD - None 0 Nb-95 0.034 < LLD - None 0 Zr-95 0.037 < LLD - None 0 Ru-103 0.034 < LLD - None 0 Ru-106 0.31 < LLD - None 0 Cs-134 0.049 < LLD - None 0 Cs-137 0.060 0.13(1/1) D-15, On-site 0.13 (1/1) None 0 0.5 mi. NW Ce-141 0.053 < LLD - None 0 Ce-144 0.23 < LLD - None 0 24

Table 5.7 Radiological Environmental Program Summary.

Name of Facility Duane Arnold Energy Center Docket No. 50-331 Location of Facility Linn, Iowa Reporting Period January-December, 2006 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDO Mean (F)' Mean (F)' Mean (F)c Routine (Units) Analysesa Rangec Location' Rangec Rangec Results' Surface Water H-3 38 193 287 (1/26) D-107, Onsite 287 (1/12) < LLD 0 (pCi/L) Sewage Effluent GS 38 Mn-54 10 < LLD < LLD 0 Fe-59 30 < LLD < LLD 0 Co-58 10 < LLD < LLD 0 Co-60 10 < LLD < LLD 0 Zn-65 30 < LLD - < LLD 0 Nb-95 15 < LLD - < LLD 0 Zr-95 30 < LLD - < LLD 0 1-131 15 < LLD - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 10 < LLD - - < LLD 0 Ba-140 60 < LLD - - < LLD 0 La-140 15 < LLD - - < LLD 0 Sediments GS 6 (pCi/g dry) K-40 1.0 7.00(4/4) D-50, 9.14 (2/2) 9.14(2/2) 0 (4.86-8.89) Plant Intake (8.60-9.68) (8.60-9.68)

Mn-54 0.017 < LLD < LLD 0 Fe-59 0.038 < LLD < LLD 0 Co-58 0.019 < LLD < LLD 0 Co-60 0.019 < LLD < LLD 0 Zn-65 0.041 < LLD < LLD 0 Nb-95 0.027 < LLD < LLD 0 Zr-95 0.032 < LLD < LLD 0 Ru-103 0.024 < LLD < LLD 0 Ru-106 0.17 < LLD < LLD 0 Cs-1 34 0.025 < LLD < LLD 0 Cs-1 37 0.021 < LLD D-50, 0.033 (1/2) 0.033 (1/2) 0 Plant Intake Ce-141 0.045 < LLD < LLD 0 Ce-144 0.12 < LLD < LLD 0 25

Table 5.7 Radiological Environmental Program Summary.

Name of Facility Duane Arnold Energy Center Docket No. 50-331 Location of Facility Linn, Iowa Reporting Period January-December, 2006 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDO Mean (F)c Mean (F)' Mean (F)c Routine (Units) Analyses' Rangec Location' Rangec Rangec Resultse Fish GS 8 (pCi/g wet) K-40 1.0 3.19 (4/4) D-49, 3.27(4/4) 3.27 (4/4) 0 (2.92-3.50) Upstream (2.93-3.45) (2.93-3.45)

Mn-54 0.017 < LLD - < LLD 0 Fe-59 0.049 < LLD - < LLD 0 Co-58 0.019 < LLD -< LLD 0 Co-60 0.020 < LLD - < LLD 0 Zn-65 0.042 < LLD - < LLD 0 Nb-95 0.025 < LLD < LLD 0 Zr-95 0.048 < LLD < LLD 0 Ru-103 0.028 < LLD < LLD 0 Ru-106 0.16 < LLD < LLD 0 Cs-134 0.017 < LLD < LLD 0 Cs-137 0.024 < LLD < LLD 0 Ce-141 0.061 < LLD < LLD 0 Ce-144 0.15 < LLD < LLD 0 GB = Gross beta; GS = Gamma spectroscopy LLD = Nominal lower limit of detectionbased on 4.66 sigma counting error for the background sample.

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

d Locations are specified by: (1) Name and code (Table 5.3); and (2) distance, direction and sector relative to reactor site.

e Non-routine results are those which exced ten times the control station value for the location. If a control station value is not available, the result is considered non-routine if it exceeds ten times the preoperational value for the location.

26

Figure 5.1 Radiological Environmental Monitoring Program Sampling Stations near the Duane Arnold Energy Center.

4 L_

BARRICA kDE I N DE--- - -17 -

I Ir m 32 18 I.

31 I, I- 19<

30 I7 20 107 _

57 29 2j 58 2000 feet See Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.

27

Figure 5.2 Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles.

CEDAR RIVER,.

108 RAPIDS on.

See Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.

28

6.0 REFERENCES

CITED Arnold, J. R. and H. A. Al-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.

Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275-276.

Environmental, Inc., Midwest Laboratory. 2001 - 2005. Environmental Radiological Monitoring Program for the Duane Arnold Energy Center, Annual Report - Part II, Data Tabulations and Analyses, January - December, 2001 - 2004.

2003. Quality Assurance Program Manual, Rev. 1, 21 October 2003.

2005. Quality Control Procedures Manual, Rev. 1, 17 September 2005.

2003. Quality Control Program, Rev. 1, 21 August 2003.

Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Chicago, Illinois, 369-382.

Hazleton Environmental Sciences . 1982 - 1984. Environmental Radiation Monitoring for the Duane Arnold Energy Center, Annual Report - Part II, Data Tabulations and Analyses, January -

December 1981 - 1983.

Hohenemser, C. M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel. 1986. "Chernobyl,"

Chemtech, October 1986, pp. 596-605.

National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-746.

Teledyne Brown Engineering Environmental Services, Midwest Laboratory. 1984 - 2000. Environmental Radiological Monitoring Program for the Duane Arnold Energy Center, Annual Report - Part II, Data Tabulations and Analyses, January - December, 1983 - 1999.

Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.

29

Environmental, Inc.

Midwest Laboratory

an Allegheny Technologies Co.

700 Landwehr Road

Northbrook, IL60062-2310 ph. (847) 564-0700

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

January, 2006 through December, 2006

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

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

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

The results in Table A-2 list results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internallaboratory testing.

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

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

Table A-5 list results of the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous 'years available upon request.

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

Attachment A lists acceptance criteria for "spiked" samples.

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

Al

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

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

> 50 pCi/liter or kg 10% of known value*

Strontium-90b 2 to 30 pCi/liter or kg 5.0 pCi/liter

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

> 20 pCi/liter 25% of known value Gross beta 5 100 pCi/liter 5.0 pCi/liter

> 100 pCi/liter 5% of known value Tritium 5 4,000 pCi/liter 1lo = (pCi/liter) =

0 0 933 169.85 x (known)

> 4,000 pCi/liter 10% of known value Radium-226,-228 > 0.1 pCi/liter 15% of known value Plutonium Ž 0.1 pCi/liter, gram, or sample 10% of known value Iodine-1 31, ; 55 pCi/liter 6.0 pCi/liter Iodine-129b > 55 pCi/liter 10% of known value Uranium-238, < 35 pCi/liter 6.0 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter

> 100 pCi/liter 10% of known value Othersb 20% of known value From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.

A2

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1 078 01/16/06 .Sr-89 49.9 +/- 3.5 50.2 41;5 -58.9 Pass STW-1078 01/16/06 Sr-90 31.5 +/- 1.5 30.7 22.0 - 39.4 Pass STW-1079 01/16/06 Ba-133 86.5 +/- 4.1 95.0 78.6 - 111.0 Pass STWN-1079 01/16/06 Co-60 96.3 +/- 4.1 95.3 86.6 - 104.0 Pass STW-1 079 01/16/06 Cs-134 22.6 +/- 3.0 23.1 14.4 -31.8 .Pass STW-1 079 01/16/06 Cs-1 37 109.0 +/- 5.9 111.0 101.0 - 121.0 Pass STW-1 079 01/16/06 Zn-65 198.0 +/- 11.2 192.0 159.0 -225.0 Pass STW-1 080 01/16/06 Gr. Alpha 10.8 +/- 1.4 9.6 1.0 -18.3 Pass STW-1 080 01/16/06 Gr. Beta 56.9 +/- 1.9 61.9 44.6 -79.2 Pass STW-1 081 01/16/06 Ra-226 4.3 +/- 0.4 4.6 3.4 -5.8 Pass STW-1 081 01/16/06 Ra-228 7.1 +/-1.8 6.6 3.7 -9.5 Pass STW-1 081 01/16/06 Uranium 20.7 +/- 0.5 22.1 16.9 -27.3 Pass STW-1088 04/10/06 Sr-89 29.0 +/-1.8 32.4 23.7 -41,1 Pass 04/10/06 Sr-90 8.7 +/- 1.0 9.0. 0.3 - 17.7 STW-1088 Pass STW-1089 04/10/06 Ba-I 33 10.3 +/- 0.4 10.0 1.3 - 18.7 Pass STW-1 089 04/10/06 Co-60 114.0 +/- 2.8 113.0 103.0 - 123,0 Pass STW-1 089 04/10/06 Cs-1 34 41.9 +/- 1.4 43.4 34.7 -52.1 Pass STW-1 089 04/10/06 Cs-1 37 208.0 +/- 1.1 214.0 195.0 - 233.0 Pass STW-1 089 04/10/06 Zn-65 154.0 +/- 0.8 152.0 126.0 - 178.0 Pass STW-1 090 04/10/06 Gr. Alpha 13.4 +/- 1.1 21.3 12.1 - 30.5 Pass STW-1090 04/10/06 Gr. Beta 27.7 +/- 2.1 23.0 14.3 -31.7 Pass STW-1 091 04/10/06 1-131 22.0 +/- 0.3 19.1 13.9 -24.3 Pass STW-1092 04/10/06 H-3 7960,0 +/- 57,0 8130.0 6720.0 - 9540.0 Pass STW-1092 04/10/06 Ra-226 2.9 +/- 0.4 3.0 2.2 -3.8 Pass STW-1092 04/10/06 Ra-228 20.9 +/- 1.2 19.1 10.8 - 27.4 Pass STW-1 092 04/10/06 Uranium 68.6 +/- 3.4 69.1 57.1 -81.1 Pass STW-1094 07/10/06 Sr-89 15.9 +/- 0.7 19.7 11.0 - 28.4 Pass STW-1094 07/10/06 Sr-90 24.3 +/- 0.4 25.9 17.2 - 34.6 Pass STW-1 095 07/10/06 Ba-1 33 94.9 +/- 8.9 88.1 72.9 - 103.0 Pass STW-1095 07/10/06 Co-60 104.0 +/- 1.8 99.7 91.0 - 108.0 Pass STW-1 095 07/10/06 Cs-134 48.7 +/- 1.3 54.1 45.4 - 62.8 Pass STW-1 095 07/10/06 Cs-137 236.0 +/- 310 238.0 217.0 - 259.0 Pass STW-1 095 07/10/06 Zn-65 126;0 +/- 8.0 121.0 100.0 - 142.0 Pass STW-1096 07/10/06 Gr. Alpha 10.9 +/- 1.0 10.0 1.3 - 18.6 Pass STW-1096 07/10/06 Gr. Beta 9.7 +/- 0.4 8.9 0.2 -17.5 Pass STW-1 097 07/10/06 Ra-226 11.0 +/-0.5 10.7 7.9 - 13.5 Pass STW-1 097 07/10/06 Ra-228 12.2 +/- 0.8 10.7 6.1 - 15.3 Pass STW-1097 07/10/06 Uranium 43.4 +/- 0.1 40.3 33.3 - 47.3 Pass Al-1

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1104 10/06/06 Sr-89 38.4 +/- 1.3 39.9 31.2 -45.7 Pass STW-1104 10/06/06 Sr-90 15.5 +/- 0.5 16.0 7.3 -24.7 Pass STW-1 105 10/06/06 Ba-1 33 64.9 +/- 2.8 70.2 58.1 - 82.3 Pass STW-1105 .10/06/06 Co-60 61.6 +/- 1.0 62.3 53.6 -71.0 Pass

STW-1105 10/06/06. Cs-134 29.0 +/- 0.9 29.9 21.2 -.38.6 Pass STW-1105 10/06/06 Cs-137 77.8 +/- 2.4 78:2 69.5 -86.9 Pass STW-1 105 '10/06/06 Zn-65 293.0 +/- 2.4 277.0 229.0 - 325.0 Pass STW-1106 10/06/06 Gr. Alpha 23.9 +/- 2.5 28.7 16.3 -41.1 Pass STW-1106 10/06/06 Gr. Beta 23.7 +/- 1.4 20.9 12.2 -29.6 Pass STW-1 107 d 10/06/06 1-131 28.4 +/- 1.2 22.1 16.9 -27.3 Fail STW-1 108 10/06/06 Ra-226 14.5 +/- 0.5 14.4 10.7 - 18.1 Pass STW-1 108 10/06/06 Ra-228 6.6 +/- 0.4 5.9 3.3 - 824 Pass STW-1 108 10/06/06 Uranium 2.9 +/- 0.1 3.2 0.0 -8.4 Pass STW-1 109 10/06/06 H-3 3000.0 +/-+142.0 3050.0 2430.0 -3670.0 Pass Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

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

d The reported result was an average of three analyses, results ranged from 25.36 to 29.23 pCi/L.

A fourth analysis was performed, result of analysis, 24.89 pCi/L.

Al -2

TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards).

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

2006-1 6/5/2006 30.cm 54.81 70.73 +/- 0.69 38.37 -71.25 Pass

2006-1 6/5/2006 60 cm 13.70 16.71 +/- 1.89 9.59 - 17.81 Pass 2006-1 6/5/2006 60 cm 13.70 16.69 +/- 0.94 9.59 - 17.81 Pass 2006-1 6/5/2006 90 cm 6.09 6.57 +/- 0.82 4.26 - 7.92 Pass 2006-1 6/5/2006 120 cm 3.43 3.65 +/- 0.22 2.40 - 4.46 Pass 2006-1 6/5/2006 120 cm 3.43 3.09 +/- 0.33 2.40 - 4.46 Pass 2006-1 6/5/2006 150 cm 2.19 2.35 +/- 0.38 1.53 -2.85 Pass 2006-1 6/5/2006 150 cm 2,19 1.98 +/- 0.10 1.53 - 2.85 Pass 2006-1 6/5/2006 180 cm 1.52 1.56 +/- 0.26 1.06 -1.98 Pass Environmental, Inc.

2006-2 11/6/2006 30 cm. 55.61 60.79 +/- 1.32 38.93 - 72.29 Pass 2006-2 11/6/2006 40 cm. 31.28 35.93 +/- 3.70 21.90 -40.66 Pass 2006-2 11/6/2006 50 cm. 20.02 21.55 +/- 1.20 14.01 - 26.03 Pass 2006-2 11/6/2006 60 cm. 13.90 14.90 +/- 1.42 9.73 - 18.07 Pass 2006-2 11/6/2006 75 cm. 8.90 8.03 +/- 0.51 6.23 -11.57 Pass 2006-2 11/6/2006 90 cm. 6.18 6.88 +/- 0.68 4.33 - 8.03 Pass 2006-2 11/6/2006 120 cm. 3.48 2.90 +/- 0.20 2.44 - 4.52 Pass 2006-2 11/6/2006 150 cm. 2.22 1.99 +/- 0.07 1.55 -2.89 Pass 2006-2 11/6/2006 180 cm. 1.54 1.79 +/- 0.94 1.08 - 2.00 Pass A2-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPW-301 1/20/2006 Fe-55 2700.10 +/- 70.00 2502.50 2002.00 .-3003.00 Pass SPAP-1224 3/7/2006 Cs-134 37.13 +/- 3.70 39.52 29.52 -49.52 Pass SPAP-1224 3/7/2006 Cs-137 118.25 +/- 8.97 119.30 107.37 -131.23 Pass SPAP-1224 3/7/2006 Gr. Beta 520.32 +/- 7.42 455.00 364.00 - 637.00 Pass SPW-1 228 3/7/2006 H-3 70891.00 +/- 719.00 75394.00 60315.20 - 90472.80 Pass SPW-1 230 3/7/2006 Cs-1 34 38.58 +/- 2.10

39.51 29.51 - 49.51 Pass SPW-1 230 3/7/2006 Cs-137 59.44 +/- 4.51 59.65 49.65 -69.65 Pass SPMI-1232 3/7/2006 Cs-134 41.20 +/- 1.33 39.51 29.51 -49.51 Pass SPMI-1232 3/7/2006 Cs-137 57.82 +/- 3.96 59.65 49.65 - 69.65 Pass W-30906 3/9/2006 Gr. Alpha 24.24 +/- 0.47 20.08 10.04 - 30.12 Pass W-30906 3/9/2006 Gr. Beta 63.79 +/- 0.48 65.73 55.73 - 75,73 Pass SPW-2750 4/27/2006 Ni-63 116.00 +/- 2.49 100.00 60.00 - 140.00 Pass SPW-2869 5/1/2006 Fe-55 19473.00 +/- 188.00 23332.00 18665.60 - 27998.40 Pass SPAP-2871 5/1/2006 Cs-134 33.97 +/- 1.10 37.50 27.50 - 47.50 Pass SPAP-2871 5/1/2006 Cs-1 37 114.44 +/- 2.8.1 118.90 107.01 - 130.79 Pass SPW-2875 5/1/2006 H-3 71057.00 +/- 730.20 75394.00 60315.20 - 90472.80 Pass STSO-3155 5/1/2006 Co-60 7950.80 +/- 67.29 7750.00 6975.00 - 8525.00 Pass STSO-3155 5/1/2006 Cs-1 34 12.49 +/- 0.13 11.59 1.59 -21.59 Pass STSO-3155 5/1/2006 Cs-137 14.10 +/- 0.12 11.63 1.63 -21.63 Pass SPAP-2873 5/2/2006 Gr. Beta 1724.80 +/- 4.51 1744.00 1395.20 -2441.60 Pass SPF-3183 5/10/2006 Cs-137 2.47 +/- 0.03 2.38 1.43 -3.33 Pass SPF-3183 5/10/2006 Cs-134 0.73 +/- 0.01 0.74 0.44 -1.04 Pass SPW-3460 5/26/2006 C-14 4009.60 +/- 14.43 4741.00 2844.60 - 6637.40 Pass W-60606 6/6/2006 Gr.'Alpha 21.94 +/- 0.46 20.08 10.04 -30.12 Pass W-60606 6/6/2006 Gr. Beta .58.17 +/- 0.49 65.73 55.73 - 75.73 Pass SPW-3988 6/16/2006 Cs-1 34 35.56 +/- 1.40 36.00 26.00- 46.00 Pass SPW-3988 6/16/2006 Cs-1 37 60.23 +/- 2.72 59.27 49.27 - 69.27 Pass SPW-3988 6/16/2006 1-131(G) 94.01 +/- 4.38 99.30 89.30 - 109.30 Pass SPW-3988 6/16/2006 Sr-89 52.40 +/- 4.23 58.16 46.53 - 69.79 Pass SPW-3988 6/16/2006 Sr-90 45.35 +/- 1.95 41.21 32.97 - 49.45 Pass SPMI-3990 6/16/2006 Cs-1 34 35.52 +/- 5.05 36.00 26.00 - 46.00 Pass SPMI-3990 6/16/2006 Cs-137 56.78 +/- 3.86 59.27 49.27 - 69.27 Pass SPMI-3990 6/16/2006 1-131(G) 95.04 +/- 5.05 99.30 89.30 - 109.30 Pass SPMI-3991 6/16/2006 1-131 96.55 +/- 0,87 99.30 79.44 -119.16 Pass SPW-4356 7/5/2006 1-131 80.88 +/- 1.09 77.23 61,78 -92.68 Pass W-90506 9/5/2006 Gr. Alpha 23.11 +/- 0.45 20.08 10.04 -30.12 Pass W-90506 9/5/2006 Gr. Beta 65.01 +/- 051 65.73 55.73 - 75.73 Pass SPAP-6950 9/30/2006 Cs-1 34 28.93 +/- 1.56 32.65 22.65 -42.65 Pass SPAP-6950 9/30/2006 Cs-1 37 116.62 +/- 2.97 117.75 105.98 - 129,53 Pass SPAP-6952 9/30/2006 Gr. Beta 52.96 +/- 0.14 53.50 42.80 - 74.90 Pass A3-1

TABLEA-3. In-House "Spike" Samples Concentration (pCi/L)

Lab Code Date Analysis Laboratory results Known Control 2s, n=1b Activity Limitsc Acceptance SPW-6954 9/30/2006 Cs-134 63.29 +/- 8.24 65.30 55.30 - 75.30 Pass SPW-6954 9/30/2006 Cs-137 60.41 +/- 7.53 58.87 48.87 - 68.87 Pass SPMI-6956 9/30/2006 Cs-134 69.26 +/- 4.85 65.31 55.31 - 75.31 Pass SPMI-6956 9/30/2006. Cs-1 37 61.35 +/- 7.62 58.87 48.87 - 68.87 Pass W-1 20106 12/1/2006 Gr. Alpha 22.40 +/- 1.03 20.08 10.04 -30.12 Pass W-1 20106 12/1/2006 Gr. Beta 63.70 +/- 1.14 65.73 55.73 - 75.73 Pass SPAP-9476 12/29/2006 Gr. Beta 57.51 +/- 0.14 53.16 42.53 - 74.42 Pass SPAP-9478 12/29/2006 Cs-134 26.84 +/- 1.23 30.06 20.06 -40.06 Pass SPAP-9478 12/29/2006 Cs-1 37 110.54 +/- 3.12 117.10 105.39 - 128.81 Pass SPWr9480 12/29/2006 H-3 68972.20 +/- 748.00 72051.60 57641.28 -86461.92 Pass SPW-9483 12/29/2006 Tc-99 29.43 +/- 0.84 32.98 20.98 -44.98 Pass SPW-9488 12/29/2006 Cs-1 34 61.35 +/- 1.65 60.10 50.10 -70.10 Pass SPW-9488 12/29/2006 Cs-1 37 60.30 +/- 2.76 56.80 46.80 - 66.80 Pass SPMI-9490 12/29/2006 Cs-134 58.99 +/- 5.43 60.10 50.10 -70.10 Pass SPMI-9490 12/29/2006 Cs-137 54.16 +/- 7.85 56.80 46.80 -66.80 Pass SPF-9492 12/29/2006 Cs-134 0.64 +/- 0.01 0.60 0.36 - 0.84 Pass SPF-9492 12/29/2006 Cs-137 2.61 +/- 0.03 2.34 1.40 - 3.28 Pass 3

' Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/m ), and solid samples (pCi/g).

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

CH (charcoal canister), F (fish).

c Results are based on single determinations.

d Control limits are based on Attachment A, Page A2 of this report.

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

A3-2

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

SPW-302 water 1/20/2006 Fe-55 21.21 -1.82 +/- 12.75 1000 SPAP-1225 Air Filter 3/7/2006 Gr. Beta 1.16 -0.512 +/- 51.20 3.2 SPW-1231 water 3/7/2006 Cs-134 2.71 10 SPW-1231 water 3/7/2006 Cs-1 37 2.05 10 W-30906 WatWr 3/9/2006 Gr. Alpha 0.037 0.005 +/- 0.026 1 W-30906 water 3/9/2006 Gr. Beta 0.076 -0.016 +/- 0.052 3.2 SPW-2751 water 4/27/2006 Ni-63 1.48 0.37 +/- 0.91 20 SPW-2868 water 5/1/2006 Fe-55 18.07 4.33 +/- 11.27 1000 SPW-2874 water 5/1/2006 H-3 166.00 -8.3 +/- 86.9 200 SPAP-2872 Air Filter 5/2/2006 Gr, Beta 1.18 -3.65 +/- 0.64 3.2 SPF-3154 Fish 5/10/2006 Cs-134 16.4 100 SPF-3154 Fish 5/10/2006 Cs-137 13.7 100 SPW-3461 water 5/26/2006 C-14 10.20 -7.9 +/- 5.20 200 W-60606 water 6/6/2006 Gr. Alpha 0.05 0.013 +/- 0.037 1 W-60606 water 6/6/2006 Gr. Beta 0.16 -0.044 +/- 0.11 3.2 SPW-3989 water 6/16/2006 Cs-1 34 3.00 10 SPW-3989 water 6/16/2006 Cs-1 37 3.65 10 SPW-3989 water 6/16/2006 1-131 0.21 0.045 +/- 0.14 0.5 SPW-3989 water 6/16/2006 1-131(G) 8.34 20 SPW-3989 water 6/16/2006 Sr-89 0.54 0.005 +/- 0.45 5 SPW-3989 water 6/16/2006 Sr-90 0.58 -0.079 +/- 0.26 1 SPMI-3991 Milk 6/16/2006 Cs-134 4.42 10 SPMI-3991 Milk 6/16/2006 Cs-137 3.88 10 SPMI-3991 Milk 6/16/2006 1-131 0.28 -0.22 +/- 0.19 0.5 SPMI-3991 Milk 6/16/2006 1-131(G) 3.76 20 SPMI-3991 Milk 6/16/2006 Sr-89 0.61 -0.25 +/- 0.76 5 SPMI-3991 d Milk 6/16/2006 Sr-90 0.52 0.88 +/- 0.34 1 W-90506 water 9/5/2006 Gr. Alpha 0.06 0.00 +/- 0.04 1 W-90506 water 9/5/2006 Gr, Beta 0.16 0.05 +/-0.11 3.2 SPMI-6383 Milk 9/14/2006 Sr-89 0.97 -0.18 +/- 0.92 5 SPMI-6383 d Milk 9/14/2006 Sr-90 0.57 0.65 +/- 0.33 1 SPAP-6949 Air Filter .9/30/2006 Cs-134 0.89 100 SPAP-6949 Air Filter 9/30/2006 Cs-1 37 0.91 100 SPAP-6951 Air Filter 9/30/2006 Gr. Beta 1.12 -0.54 +/- 0.64 3.2 SPW-6953 water 9/30/2006 Cs-134 3.91 10 SPW-6953 water 9/30/2006 Cs-137 5.61 10 SPW-6953 water 9/30/2006 Sr-89 0.79 -0.14 +/- 0.64 5 SPW-6953 water 9/30/2006 Sr-90 0.60 0.11 +/-0.29 1 A4-1

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

SPMI-6955 Milk 9/30/2006 Cs-1 34 2.86 10 SPMI-6955 Milk 9/30/2006 Cs-137 2.39 10 SPMI-6955 Milk 9/30/2006 1-131(G) 9.98 0.5 W-120106 water 12/1/2006 Gr. Alpha 0.11 0.066 +/- 0.072 1 W-1 20106 water 12/1/2006 Gr. Beta 0.30 0.093 +/- 0.16 3.2 SPAP-9477 Air Filter 12/29/2006 Gr. Beta 1.13 -0.37 +/- 0.66 3.2 SPAP-9479 Air Filter 12/29/2006 Cs-137 0.87 100 SPW-9481 water 12/29/2006 H-3 146.2 63.2 +/- 80.1 200 SPW-9483 water 12/29/2006 Tc-99 0,95 -1.20 +/- 0.56 10 SPW-9489 water 12/29/2006 Cs-134 2.30 10 SPMI-9491 Milk 12/29/2006 Cs-134 3.10 10 SPMI-9491 Milk 12/29/2006 Cs-137. 2.90 10 SPMI-9491 Milk 12/29/2006 1-131(G) 8.00 20 SPF-9493 Fish 12/29/2006 Cs-134 7.6 100 SPF-9493 Fish 12/29/2006 Cs-137 7.9 100 a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

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

' Activity reported is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported d Low levels of Sr-90 are still detected in the environment. A concentration of (1-5 pCi/L) in milk is not unusual.

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-7466, 7467 1/3/2006 Be-7 0.053 +/- 0.015 0.057 +/- 0.011 0.055 +/- 0.009 Pass AP-7513, 7514 1/3/2006 Be-7 0.033 +/- 0.008 0.036 +/- 0.008 0.035 +/- 0.006 Pass AP-7555, 7556 1/3/2006 Be-7 0.053 +/- 0.007 0.054 +/- 0.008 0.053 +/- 0.005 Pass MI-154, 155 1/10/2006 K-40 1254.20 +/- 87.75 1369.60 +/-+102.80 1311.90 +/- 67.58 Pass MI-217, 218 1/11/2006 K-40 1258.00 +/- 118.00 1313.00 +/- 98.00 1285.50 +/- 76.69 Pass MI-217, 218 1/11/2006 Sr-90 1.27 +/- 0.37 0.92 +/- 0.33 1.10 +/- 0.25 Pass MI-287, 288 1/17/2006 K-40 1383.10 +/- 110.90 1457.80 +/- 119.10 1420.45 +/- 81.37 Pass MI-287, 288 1/17/2006 Sr-90 0.74 +/- 0.38 0.94 +/- 0.37 0.84 +/- 0.27 Pass WW-314, 315 1/19/2006 Gr. Beta 9.21 +/- 1.72 11.52 +/- 1.93 10.37 +/- 1.29 Pass WW-314, 315 1/19/2006 H-3 168.64 +/- 94.94 210.12 +/- 96.51 189.38 +/- 67.69 Pass SWT-577, 578 1/31/2006 Gr. Beta 3.06 +/- 0.66 3.68 +/- 0.64 3.37 +/- 0.46 Pass SWU-598, 599 1/31/2006 Gr. Beta 2.03 +/- 0.39 1.97 +/- 0.40 2.00 +/- 0.28 Pass SWU-598, 599 1/31/2006 H-3 260.10 +/- 98.20 134.10 +/- 93.50 197.10 +/- 67.80 Pass F-3311, 3 3 1 2 b 2/9/2006 Gr. Beta 4.12 +/- 0.14 3.82 +/- 0.13 3.97 +/- 0.10 Fail F-3311, 3312 2/9/2006 K-40 2.68 +/- 0.37 2:76 +/- 0.39 2.72 +/- 0.27 Pass SW-780, 781 2/14/2006 Gr. Alpha 4.09 +/- 1.52 3.22 +/- 1.37 3;66 +/- 1.03 Pass SW-780, 781 2/14/2006 Gr. Beta 5.91 +/- 0.90 5.89 +/- 0.92 5.90 +/- 0.64 Pass DW-934, 935 2/17/2006 1-131 0.35 +/- 0.22 0.31 +/- 0.25 0.33 +/- 0.16 Pass DW-1024, 1025 2/24/2006 1-131 0.24 +/- 0.26 0.53 +/- 0.24 0.39 +/- 0.18 Pass MI-1078, 1079 3/1/2006 Sr-90 1.42 +/- 0.39 1.30 +/- 0.62 1.36 +/- 0.37 Pass F-1357, 1358 3/10/2006 Gr. Beta 3.77 +/- 0.07 3.71 +/- 0.07 3.74 +/- 0.05 Pass F-1357, 1358 3/10/2006 K-40 2.46 +/- 0.32 2.32 +/- 0.44 2.39 +/- 0.27 Pass MI-1469, 1470 3/14/2006 K-40 1396.30 +/- 120.80 1335.60 +/- 113.80 1365.95 +/- 82.98 Pass CF-1538, 1539 3121/2006 K-40 13.66 +/- 0.81 13.97 +/- 0.68 13.81 +/- 0.53 Pass WW-1 583, 1584 3/22/2006 Gr. Beta 7.66 +/- 0.73 8.87 +/- 0.75 8.26 +/- 0.52 Pass DW-1955, 1956 3/27/2006 Gr. Beta 2.25 +/- 0.60 3.15 +/- 0.59 2.70 +/- 0.42 Pass MI-1760, 1761 3/29/2006 K-40 1271.00 +/- 89.00 1378.00 +/- 113.00 1324.50 +/- 71.92 Pass AP-2603, 2604 3/29/2006 Be-7 0.067 +/- 0.015 0.056 +/- 0.010 0.062 +/- 0.009 Pass E-1997, 1998 4/3/2006 Gr. Beta 1.82 +/- 0.07 1.87 +/- 0.07 1.85 +/- 0.05 Pass E-1997, 1998 4/3/2006 K-40 1.28.+/- 0.15 1.24 +/- 0.21 1.26 +/- 0.13 Pass AP-2818, 2819 4/3/2006 Be-7 0.06 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 Pass SWU-2863, 2864 4/3/2006 Gr. Beta 3.20 +/- 1.26 4.77 +/- 1.30 3.99 +/- 0.91 Pass SS-2389, 2390 4/11/2006 Gr. Beta 10.53 +/- 0.96 9.38 +/- 0.84 9.96 +/- 0.64 Pass SS-2389, 2390 4/11/2006 K-40 5.51 +/- 0.42 5.79 +/- 0.40 5.65 +/- 0.29 Pass DW-2773, 2774 4/21/2006 1-131 0.74 +/- 0.23 0.53 +/- 0.40 0.63 +/- 0.23 Pass SL-2932, 2933 5/1/2006 Be-7 1.28 +/- 0.19 1.27 +/- 0.17 1.28 +/- 0.13 Pass SL-2932, 2933 5/1/2006 Gr. Beta 6.09 +/- 0.33 5.65 +/- 0.31 5.87 +/- 0.23 Pass SL-2932, 2933 5/1/2006 K-40 3.13 +/- 0.41 3.09 +/- 0.36 3.11_+/- 0.27 Pass BS-3103, 3104 5/1/2006 Gr. Beta 8.27 +/- 1.46 9.03 +/- 1.59 8.65 +/- 1.08 Pass BS-3103, 3104 5/1/2006 K-40 6288.20 +/- 585.20 5643.70 +/- 599.80 5965.95 +/- 418.99 Pass MI-3037, 3038 5/2/2006 K-40 1238.90 +/- 98.59 1301.00 +/- 103.90 1269.95 +/- 71.62 Pass MI-3037, 3038 5/2/2006 Sr-90 1.76 +/- 0.42 1.48 +/- 0.42 1.62 +/- 0.29 Pass A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance MI-3124, 3125 5/9/2006 K-40 1032.30 +/- 91.1.2 1103.60 +/- 120.50 1067.95 +/- 75.54 Pass SW-3145, 3146 5/9/2006 Gr. Alpha 4.85 +/- 1.68 4.12 +/- 1.62 4.48 +/- 1.17 Pass SW-3145, 3146 5/9/2006 Gr. Beta 8.94 +/- 1.46 9.14 +/- 1.36 9.04 +/- 1.00 Pass MI-3236, 3237 5/10/2006 K-40 1412.40 +/- 119.10 1427.90 +/- 127.70 1420.15 +/- 87.31 Pass F-3422, 3423 5/19/2006 H-3 8175.00 +/- 252.00 8268.00 +/- 253.00 8221.50 +/- 178.54 Pass G-3491, 3492 5/24/2006 Gr. Beta 8.89 +/- 0.18 9.03 +/- 0.19 8.96 +/- 0.13 Pass G-3491, 3492 5/24/2006 K-40 5.60 +/- 0.71 6.30 +/- 0.78 5.95 +/- 0.53 Pass SO-3539,3540 5/24/2006 Gr. Beta 19.57 +/- 1.99 18.98 +/- 1.91 19.27 +/- 1.38 Pass SO-3539,3540 5/24/2006 K-40 12.55 +/- 0.89 11.49 +/- 0.59 12.02 +/- 0.53 Pass WW-3751, 3752 5/25/2006 Gr. Beta 9.85 +/- 0.79 8.96 +/- 0.74 9.41 +/- 0.54 Pass F-3617, 3618 *5/30/2006 K-40 2.42 +/- 0:38 2.53 +/- 0.37 2.47 +/- 0.27 Pass SL-3641, 3642 6/1/2006 Be-7 1.41 +/- 0.19 1.31 +/- 0.27 1.36 +/- 0.17 Pass SL-3641, 3642 6/1/2006 Gr. Beta 5.03 +/- 0.18 5.30 +/- 0.19 5.17 +/- 0.13 Pass SL-3641, 3642 6/1/2006 K-40 2.21 +/- 0.26 2.14 +/- 0.37 2.18 +/- 0.23 Pass MI-3886, 3887 6/12/2006 K-40 1424.20 +/- 118.20 1318.80 +/- 110.50 1371.50 +/- 80.90 Pass VE-3949, 3950 6/13/2006 Gr. Alpha 0.13 +/- 0.06 0.16 +/- 0.07 0.15 +/- 0.05 Pass VE-3949, 3950 6/13/2006 Gr. Beta 4.53 +/- 0.19 4.47 +/- 0.18 4.50 +/- 0.13 Pass VE-3949, 3950 6/13/2006 K-40 6.02 +/- 0.66 5.33 +/- 0.66 5.67 +/- 0.47 Pass BS-4016, 4017 6/13/2006 Co-60 0.18 +/- 0.03 0.15 +/- 0.03 0.16 +/- 0.02 Pass BS-4016, 4017 6/13/2006 Cs-1 37 1.97 +/- 0.09 2.01 +/- 0.09 1.99 +/- 0.06 Pass BS-4016, 4017 6/13/2006 K-40 11.03 +/- 0.76 10.45 +/- 0.78 10.74 +/- 0.54 Pass MI-3992, 3993 6/14/2006 K-40 1358.50 +/- 166.40 1395.80 +/- 122.70 1377.15 +/- 103.37 Pass LW-4175, 4176 6/16/2006 H-3 482.11 +/- 90.25 397.50 +/- 86.88 439.81 +/- 62.63 Pass W-4130,4131 6/21/2006 H-3 401.50 +/- 87.85 236.28 +/- 80.89 318.89 +/- 59.71 Pass AV-4330, 4331 6/26/2006 K-40 1717.10 +/- 244.30 1893.10 +/- 223.30 1805.10 +/- 165.49 Pass SWU-4489, 4490 6/27/2006 Gr. Beta 1.70 +/- 0.38 1.93 +/- 0.38 1.82 +/- 0.27 Pass AP-4909, 4910 6/29/2006 Be-7 0.11 +/- 0.01 0.11 +/- 0.02 0.11 +/- 0.01 Pass AP-4952, 4953 6/29/2006 Be-7 0.08 +/- 0.02 0.10 +/- 0.02 0.09 +/- 0.01 Pass AP-4930, 4931 7/3/2006 Be-7 0.08 +/- 0.02 0.07 +/- 0.01 0.08 +/- 0.01 Pass E-4399, 4400 7/5/2006 Gr. Beta 1.85 +/- 0.05 1.85 +/- 0.05 1.85 +/- 0.04 Pass E-4399, 4400 7/5/2006 K-40 1.25 +/- 0.19 1.24 +/- 0.18 1.25 +/- 0.13 Pass G-4420,4421 7/5/2006 Be-7 0.82 +/- 0.20 0.61 +/- 0.14 0.72 +/- 0.12 Pass G-4420, 4421 7/5/2006 Gr. Beta 13.20 +/- 0.40 14.00 +/- 0.40 13.60 +/- 0.28 Pass G-4420,4421 7/5/2006 K-40 9.96 +/- 0.44 10.06 +/- 0.82 10.01 +/- 0.47 Pass DW-60432, 60433 7/6/2006 Gr. Alpha 3.24 +/- 1.35 2.49 +/- 1.33 2.87 +/- 0.95 Pass DW-60514, 60515 7/10/2006 Gr. Alpha 3.70 +/- 1.12 3.09 +/- 1,16 3.40 +/- 0.81 Pass DW-60449, 60450 7/11/2006 Gr. Alpha 6.87 +/- 1.26 4.77 +/- 1.09 5.82 +/- 0.83 Pass MI-4599, 4600 7/12/2006 K-40 1403.50 +/- 118.80 1330.40 +/- 116:50 1366.95 +/- 83.20 Pass MI-4599, 4600 7/12/2006 Sr-90 0.59 +/- 0.34 0.70 +/- 0.35 0.65 +/- 0.24 Pass MI-4667, 4668 7/12/2006 K40 1286.60 +/- 92.62 1358.60 +/- 158.40 1322.60 +/- 91.75 Pass LW-4823, 4824 7/14/2006 Gr. Beta 1.75 +/- 0.60 2.51 +/- 0.59 2.13 +/- 0.42 Pass A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)8 Averaged Lab Code' Date Analysis First Result Second Result Result Acceptance DW-60502, 60503 7/19/2006 Gr. Alpha 16.27 +/- 2.49 21.41 +/- 3.21 18.84 +/- 2.03 Pass DW-60526, 60527 7/21/2006 Gr. Alpha 14.06 +/- 1.82 15.57 +/- 1.77 14.82 +/- 1.27 Pass DW-60539, 60540 7/21/2006 Gr. Alpha 5.09 +/- 0.95 6.23 +/- .1.05 5.66 +/- 0.71 Pass MI-5125, 5126 7/25/2006 K-40 1480.60 +/- 118.30 1402.60 +/- 120.80 -1441.60 +/- 84.54 Pass DW-60609, 60610 7/26/2006 Gr. Alpha 1.00 +/- 1.10 2.70 +/- 1.30 1.85 +/- 0.85 Pass

DW-60621, 60622 7/31/2006 Gr. Alpha 3.70 +/- 1.00 1.90 +/- 0.80 2.80 +/- 0.64 Pass SL-5265, 5266 8/1/2006 Be-7 1.10 +/- 0.46 1.38 +/- 0.52 1.24 +/- 0.35 Pass SL-5265, 5266 8/1/2006 Sr-90 0.10 +/- 0.03 0.16 +/- 0.03 0.13 +/- 0.02 Pass SL-5265, 5266 8/1/2006 Gr. Beta 4:41 +/- 0.41 3.46 +/- 0.57 3.94 +/- 0.35 Pass SL-5265, 5266 8/1/2006 K-40 1.19 +/- 0.52 0.87 +/- 0.52 1.03 +/- 0.37 Pass VE-5286, 5287 8/1/2006 Be-7 1.21 +/- 0.30 1.32 +/- 0.20 1.27 +/- 0.18 Pass VE-5286, 5287 8/1/2006 Gr. Beta 9.67 +/- 0.35 9.37 +/- 0.35 9.52 +/- 0.25 Pass VE-5286, 5287 8/1/2006 K-40 6.25 +/- 0.81 6.50 +/- 0.48 6.38 +/- 0.47 Pass SW-5383, 5384 8/8/2006 Gr. Alpha 3.24 +/- 1.35 2.94 +/- 1.35 3.09 +/- 0.96 Pass SW-5383,5384 8/8/2006 Gr. Beta 4.86 +/- 0.86 5.46 +/- 0.87 5.16 +/- 0.61 Pass SW-5971, 5972 8/8/2006 H-3 119.90 +/- 78.14 144.41 +/- 79.23 132.15 +/- 55.64 Pass VE-5404, 5405 8/10/2006 Be-7 0.77 +/- 0.24 1.01 +/- 0.26 0.89 +/- 0.18 Pass VE-5404, 5405 8/10/2006 K-40 4.71 +/- 0.63 4.01 +/- 0.58 4.36 +/- 0.43 Pass DW-5480, 5481 8/11/2006 H-3 169.08 +/- 85.52 133.65 +/-.83.96 151.36 +/- 59.92 Pass DW-60645, 60646 8/15/2006 Gr. Alpha 10.41 +/- 1.78 10.97 +/- 1.85 10.69 +/- 1.28 Pass W-5602,5603 8/16/2006 H-3 2118.79 +/- 151.55 2181.82 +/- 153.09 2150.30 +/- 107.71 Pass DW-60634, 606.35 8/18/2006 Gr. Alpha 12.99 +/- 1.84 9.67 +/- 1.61 11.33 +/- 1.22 Pass DW-60634, 60635 8/18/2006 Gr. Beta 10.51 +/- 1.33 8.61 +/- 1.18 9.56 +/- 0.89 Pass MW-5793, 5794 8/22/2006 K-40 1264.00 +/- 115.00 1377.00 +/- 121.00 1320.50 +/- 83.47 Pass SWU-6150, 6151 8/29/2006 Gr. Beta 1.84 +/- 0.28 1.81 +/- 0.28 1.82 +/- 0.20 Pass DW-60657, 60658 8/29/2006 Gr. Alpha 2.33 +/- 0.80 2.90 +/- 0.78 2.62 +/- 0.56 Pass CF-7450, 7451 9/5/2006 Be-7 0.78 +/- 0.45 0.78 +/- 0.27 0.78 +/- 0.26 Pass SL-6085, 6086 9/5/2006 Co-60 0.22 +/- 0.03 0.21 +/- 0.02 0.22 +/- 0.02 Pass SL-6085, 6086 9/5/2006 Gr. Beta 5.47 +/- 0.69 4.63 +/- 0.58 5.05 +/- 0.45 Pass SL-6085, 6086 9/5/2006 K-40 1.91 +/- 0.28 2.06 +/- 0.41 1.99 +/- 0.25 Pass DW-60695, 60696 9/11/2006 Gr. Alpha 3.93 +/- 1.17 4.62 +/- 1.12 4.28 +/- 0.81 Pass LW-6266, 6267 9/13/2006 Gr. Beta 3.09 +/- 0.48 2.98 +/- 0.48 3.03 +/- 0.34 Pass MI-6424, 6425 9/19/2006 Sr-90 0.78 +/- 0.38 1.11 +/- 0.37 0.95 +/- 0.27 Pass DW-60715, 60716 9/19/2006 Gr. Alpha 1.30 +/-1.00 2.23 +/- 1.01 1.77 +/- 0.71 Pass SO-6597, 6598 9/22/2006 Cs-1 37 0.18 +/- 0.04 0.18 +/- 0.04 0.18 +/- 0.03 Pass SO-6597, 6598 9/22/2006 K-40 10.25 +/- 0.66 10.11 +/- 0.64 10.18 +/- 0.46 Pass SWU-6718, 6719 9/26/2006 Gr. Beta 3.45 +/- 1.21 2.78 +/- 1.19 3.12 +/- 0.85 Pass SO-6668, 6669 9/27/2006 Cs-1 37 0.13 +/- 0.04 0.13 +/- 0.02 0.13 +/- 0.02 Pass SO-6668, 6669 9/27/2006 K-40 13.04 0.90 12.41 +/- 0.54 12.72 +/- 0.53 Pass A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance MI-6760, 6761 10/2/2006 K-40 1413,10 +/- 113.20 1187,30 +/- 155.20 1300.20 +/- 96.05 Pass G-6797, 6798 10/2/2006 Be-7 4.70 +/- 0.31 4.56 +/- 0.41 4.63 +/- 0.26 Pass G-6797, 6798 10/2/2006 Gr. Beta 6.89 +/- 0.26 7.04 +/- 0.24 6.97 +/- 0.18 Pass G-6797, 6798 b 10/2/2006 K-40 5.39 +/- 0.35 4.36 +/- 0.47 4.88 +/- 0.29 Fail AP-7531, 7532 10/3/2006 Be-7 0,07 +/- 0.01 0.08 +/- 0.01 0.08 +/- 0.01 Pass AP-7552, 7553 10/3/2006 Be-7 0.08 +/- 0.02 0.08 +/- 0.01 0.08 +/- 0.01 Pass AP-7573, 7574 10/3/2006 Be-7 0.08 +/- 0.02 0.08 +/- 0.01 0.08 +/- 0.01 Pass SO-7103, 7104 10/4/2006 Cs-1 37 0.25 +/- 0.05 0.27 +/-+0.06 0.26 +/- 0.04 Pass SO-7103, 7104 10/4/2006 K-40 12.95 +/- 1.12 12.22 +/- 1:07 12.58 +/- 0.77 Pass DW-60759, 60760 10/5/2006 Gr. Alpha 4.93 +/- 0.97 5.04 +/- 1.03 4.99 +/- 0.71 Pass MI7037, 7038 10/10/2006 K-40 1326.10 +/- 115.20 1251.40 +/- 115.70 1288.75 +/- 81.64 Pass VE-7058, 7059 10/10/2006 Gr. Alpha 0.18 +/- 0.11 0.32 +/- 0.14 0.25 +/- 0.09 Pass VE-7058, 7059 10/10/2006 Gr. Beta 9.21 +/- 0.34 8.83 +/- 0.36 9.02 +/- 0.25 Pass VE-7058, 7059 10/10/2006 K-40 10.90 +/- 0.65 10.42 +/- 0.80 10.66 +/- 0.52 Pass SS-7079, 7080 10/10/2006 Cs-1 37 0.04 +/- 0.01 0.04 +/- 0.02 0.04 +/- 0.01 Pass SS-7079, 7080 10/10/2006 Gr. Beta 12.23 +/- 2.46 11.76 +/- 2.23 11.99 +/- 1.66 Pass SS-7079, 7080 10/10/2006 K-40 7.23 +/-+0.36 7.37 +/- 0.40 7.30 +/- 0.27 Pass MI-7208, 7209 10/11/2006 K-40 1295.20 +/- 116.90 1386.90 +/- 119.10 1341.05 +/- 83.44 Pass CF-7450, 7451 10/18/2006 K-40 20.40 +/- 0.84 19.54 +/- 0.99 19.97 +/- 0.65 Pass LW-7945, 7946 10/26/2006 Gr. Beta 1.30 +/- 0.37 1,44 +/- 0.36 1.37 +/- 0.26 Pass F-7971, 7972 10129/2006 K-40 3.63 +/- 0.54 3.33 +/- 0.43 3.48 +/- 0.34 Pass SWU-8194, 8195 10/31/2006 Gr. Beta 1.84 +/- 0.28 1.43 +/- 0.28 1.64 +/- 0.20 Pass BS-8017, 8018 11/1/2006 Gr. Beta 10.54 +/- 1.72 10.17 +/- 1.73 10.36 +/- 1.22 Pass BS-8017, 8018 11/1/2006 K-40 10.00 +/- 0.53 9.60 +/- 0.69 9.80 +/- 0.44 Pass LW-8215, 8216 11/1/2006 Gr. Beta 2.23 +/- 0.61 1.64 +/- 0.37 1.93 +/- 0.35 Pass F-8345, 8346 11/2/2006 K-40 2.84 +/- 0.42 2.89 +/- 0.40 2.86 +/- 0.29 Pass BS-8366, 8367 11/2/2006 K-40 13.69 +/- 0.66 13.61 +/- 0.78 13.65 +/- 0.51 Pass MI-8083, 8084 11/6/2006 K-40 1295.00 +/- 121.20 1374.80 +/- 162.80 1334.90 +/- 101.48 Pass

.WW-8259, 8260 11/7/2006 H-3 337.00 +/- 95.00 295.00 +/- 93.00 316.00 +/- 66,47 Pass MI-8484, 8485 11/22/2006 K-40 1405.80 +/- 87.06 1390.70 +/- 103.60 1398.25 +/- 67.66 Pass SO-8619, 8620 11/27/2006 Cs-1 37 0.74 +/- 0.08 0.69 +/- 0.06 0.71 +/- 0.05 Pass SO-8619, 8620 11/27/2006 Gr. Alpha 16.54 +/- 5.65 12.24 +/- 4.90 .14.39 +/- 3.74 Pass SO-8619, 8620 11/27/2006 Gr. Beta 24.99 +/- 3.88 28.66 +/- 3.95 26.82 +/- 2.77 Pass SO-8619, 8620 11/27/2006 K-40 12.21 +/- 1.11 12.92 +/- 0.83 12.57 +/- 0.69 Pass SWT-8641, 8642 11/29/2006 Gr. Beta 2.83 +/- 0.47 2.89 +/- 0.45 2.86 +/- 0.33 Pass SWT-9436, 9437 12/26/2006 Gr. Beta 2.39 +/- 0.64 2.25 +/- 0.60 2.32 +/- 0.44 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

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

b 200 minute count time or longer, resulting in lower error.

A5-4

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)3 .

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STVE-1082 01/01/06 Am-241 0.16 +/- 0.06 0.16 0.11 -0.20 Pass STVE-1 082 01/01/06 Co-57 10.40 +/- 0.20 8.58 6.00 -11.15 Pass STVE-1082 01/01/06 Co-60 5.00 +/- 0.20 4.52 3.16 -5.88 Pass STVE-1082 e 01/01/06 Cs-134 < 0.20 0.00 Pass STVE-1082 01/01/06 Cs-1 37 3.40 +/- 0.20 3.07 2.15 -4.00 Pass STVE-1082 01/01/06 Mn-54 6.90 +/- 0.20 6.25 4,37 -8.12 Pass STVE-1082 01/01/06 Pu-238 0.08 +/- 0.03 0.14 0.10 -0.18 Fail STVE-1082 01/01/06 Pu-239/40 0.17 +/- 0.03 0.16 0.11 -0.21 Pass STVE-1 082 01/01/06 Sr-90 1.40 +/- 0.20 1.56 1.09 -2.03 Pass STVE-1 082 01/01/06 U-233/4 0.24 +/- 0.05 0.21 0.15 -0.27 Pass STVE-1 082 01/01/06 U-238 0.19 +/- 0.04 0.22 0.15 -0.28 Pass STVE-1082 01/01/06 Zn-65 11.10 +/- 0.50 9.80 6.86 - 12.74 Pass STSO-1083 01/01/06 Am-241 54.60 +/- 5.50 57.08 39.96 - 74.20 Pass STSO-1083 01/01/06 Co-57 762.90 +/- 12.70 656.29 459.40 -853.18 Pass STSO-1083 01/01/06 Co-60 504.90 +/- 3.10 447.10 312.97 -581.23 Pass STSO-1083 e 01/01/06 Cs-134 < 1.70 0.00 Pass STSO-1083 01/01/06 Cs-1 37 406.50 +/- 3.70 339.69 237.78 -441.60 Pass STSO-1083 01/01/06 K-40 719.20 +/- 18.40 604.00 422.80 - 785.20 Pass STSO-1 083 01/01/06 Mn-54 415.60 +/- 4.80 346.77 242.74 -450.80 Pass STSO-1083 01/01/06 Ni-63 261.40 +/- 14.70 323.51 226.46 -420.56 Pass STSO-1083' 01/01/06 Pu-238 14.60 +/- 2.90 61.15 42.81 -79.50 Fail STSO-1083 01/01/06 Pu-239/40 14.60 +/- 2.40 45.85 32.09 -59.61 Fail STSO-1083 01/01/06 U-233/4 13.50 +/- 1.70 37.00 25.90 -48.10 Fail STSO-1083 01/01/06 U-238 15.40 +/- 1.80 38.85 27.20 - 50.50 Fail STSO-1083 01/01/06 Zn-65 783.40 +/- 7.00 657.36 460.15 - 854.57 Pass STAP-1084 01/01/06 Gr. Alpha 0.26 +/- 0.02 0.36 0.00 - 0.72 Pass STAP-1 084 01/01/06 Gr. Beta 0.51 +/- 0.03 0.48 0.24 - 0.72 Pass STAP-1085 01/01/06 Am-241 0.12 +/- 0.02 0.09 0.07 -0.12 Pass STAP-1085 01/01/06 Co-57 4.32 +/- 0.10 4.10 2.87 - 5.32 Pass STAP-1085 01/01/06 Co-60 2.24 + 0.16 2.19 1.53 -2.84 Pass STAP-1 085 01/01/06 Cs-134 2.96 +/- 0.19 2.93 2.05 - 3.81 Pass STAP-1 085 01101/06 Cs-137 2.64 +/- 0.20 2.53 1.77 -3.29 Pass STAP-1085' 01/01/06 Pu-238 0.03 +/- 0.01 0.07 0.05 - 0.09 Fail STAP-1 085e 01/01/06 Pu-239/40 < 0.01 0.00 Pass STAP-i085 01/01/06 Sr-90 0.77 +/- 0.21 0.79 0.55 - 1.03 Pass STAP-1 085 01/01/06 U-233/4 0.03 +/- 0.01 0.02 0.01 - 0.03 Pass STAP-1085 01/01/06 U-238 0.02 +/- 0.01 0.02 0.01 - 0.03 Pass STAP-1 085 01/01/06 Zn-65 3.94 +/- 0.44 3.42 2.40 - 4,45 Pass A6-1

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

b Concentration Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STW-1086 01/01/06 Am-241 1.29 +/- 0.05 1.30 0.91 -1.69 Pass STW- 1086 01/01/06 Co-57 177.10 +/--1.00 166.12 116.28 -215.96 Pass STW-1086 01/01/06 Co-60 158.30+/- 1.00 153.50 107.45 - 199.55 Pass STW-1086 01/01/06 Cs-134 96.40 +/- 1.50 95.10 66.57 -123.63 Pass STW-1086 e 01/01/06 Cs-137 < 0.80 0.00 Pass STW-1086 01/01/06 Fe-55 102.50 +/- 18.10 129.60 90.72 - 168.48 Pass STW-1086 01/01/06 H-3 956.60 +/- 16.50 952.01 666.41 - 1238.00 Pass STW-1086 01/01/06 Mn-54 335.30 +/- 2.20 315.00 220.50 -409.50 Pass STW-1 086 01/01/06 Ni-63 62.90 +/- 3.60 60.34 42.24 - 78.44 Pass STW-1086 01/01/06 Pu-238 0.96 +/- 0.07 0.91 0.70 -1.30 Pass STW- 1086 01/01/06 Pu-239/40 < 0.20 0.00 Pass STW-1086 01/01/06 Sr-90 12.80 +/- 1.60 13.16 9.21 -17.11 Pass STW-1086 01/01/06 Tc-99 22.30 +/- 1.20 23.38 16.37 - 30.39 Pass STW-1 086 01/01/06 U-233/4 2.02 +/- 0.12 2.09 1.46 - 2.72 Pass STW-1 086 01/01/06 U-238 2.03 +/- 0.12 2.17 1.52 -2.82 Pass STW-1 086 01/01/06 Zn-65 249.50 +/- 3.40 228.16 159.71 -296.61 Pass STW-1087 01/01/06 Gr. Alpha 0.59 +/- 0.10 0.58 0.00 -1.16 Pass STW-1087 01/01/06 Gr. Beta 1.69 +/- 0.07 1.13 0.56 - 1.70 Pass STVE-1098 e 07/01/06 Co-57 <0.14 0.00 Pass STVE-1098 g 07/01/06 Co-60 6.89 +/- 0.17 5.81 4.06 - 7.55 Pass

ýTVE-1098 07/01/06 Cs-1 34 8.46 +/- 0.16 7.49 5.24 - 9.73 Pass STVE-1098 07/01/06 Cs-1 37 6.87 +/- 0.29 5.50 3.85 -7.14 Pass STVE-1098 07/01/06 Mn-54 10.36 +/- 0.29 8.35 5.85 - 10.86 Pass STVE-1098 07/01/06 Zn-65 7.46 +/- 0.50 5.98 4.19 -7.78 Pass STSO-1099 07/01/06 Am-241 130.00 +/- 11.60 105.47 73.83 - 137.11 Pass STSO-1 099 07/01/06 Coý57 784.90 +/- 3.80 676.33 473.43 - 879.23 Pass STSO-1 099 07/01/06 Co-60 2.10 +/- 0.90 1.98 0.00 - 5.00 Pass STSO-1 099 07/01/06 Cs-134 500.70 +/- 7.40 452.13 316.49 - 587.77 Pass STSO-1 099 07/01/06 Cs-1 37 624.20 +/- 4.90 525.73 368.01 - 683.45 Pass STSO-1099 07/01/06 K-40 701.30 +/- 3.40 604.00 423.00 - 785.00 Pass STSO-1099 07/01/06 Mn-54 699.20 +/- 5.20 594.25 415,98 - 772.52 Pass STSO-1099 07/01/06 Ni-63 614.40 +/- 17.10 672.30 470.60 - 874.00 Pass STSO-1099 07/01/06 Pu-238 79.90 +/- 5.80 82,00 57.00 - 107.00 Pass STSO-1099 e 07/01/06 Pu-239/40 <0.70 0.00 Pass STSO-1099 07/01/06 U-233/4 150.50 +/- 5.90 152.44 106.71 -198.17 Pass STSO-1 099 07/01/06 U-238 151.60 +/-6.00 158.73 111.11 -206.35 Pass STSO-1099 07/01/06 Zn-65 1021.90 +/- 9.20 903.61 632.53 -1175.00 Pass STAP-1100 07/01/06 Am-241 0.16 + 0.03 0.14 0.10 -0.19 Pass STAP-1100 07/01/06 Co-57 2.17 +/- 0.06 2.58 1.81 - 3.36 Pass STAP-1 100 07/01/06 Co-60 1.38 + 0,07 1.58 1.10 -2.05 Pass STAP- 1100 07/01/06 Cs-134 2.52 + 0.13 3.15 2.20 - 4.09 Pass A6-2

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

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STAP- 1100 07/01/06 Cs-137 1.64 +/- 0.08 1.81 1.26 -2.35 Pass STAP-1100 07/01/06 Mn-54 1.76 +/- 0.18 1.92 1.34 -.2.50 Pass STAP-1100 07/01/06 Pu-238 0.09 +/- 0;02 0.12 0.08 -0.15 Pass STAP-1100 07/01/06 Sr-90 0.66 +/- 0,21 0.62 0.43 -0.81 Pass STAP-1100 07/01/06 U-233/4 0,15 +/- 0.02 0.13 0.09 -0.17 Pass STAP-1100 07/01/06 U-238 0.13 + 0.02 0.14 0.10 -0.18 Pass STAP- 1100 e 07/01/06 Zn-65 < 0.07 0.00 Pass STAP-1 101 07/01/06 Gr. Alpha 0.08 +/- 0.03 0.29 0.00 - 0.58 Pass STAP-1 101 07/01/06 Gr. Beta 0.41 +/- 0.05 0.36 0.18 '0.54 Pass STW-1 102 07/01/06 Gr. Alpha 0,76 +/- 0.07 1.03 0.00 - 2.07 Pass STW-1102 07/01/06 Gr. Beta 1.23 +/-0.06 1.03 0.52 -1.54 Pass STW-1103 07/01/06 Am-241 1.86 +/- 0.09 2.31 1.62 -3.00 Pass STW-1103 07/01/06 Co-57 224.10 +/- 1.20 213.08 149.16 -277.00 Pass STW-1 103 07/01/06 Co-60 49.40 +/- 0.50 47.50 33.20 - 61.80 Pass STW-1103 07/01/06 Cs-134 112.70 +/- 0.90 112.82 78.97 -146.66 Pass STW-1103 07/01/06 Cs-137 206.60 +/- 1.40 196.14 137.30 -254.98 Pass STW-1103 07/01/06 Fe-55 .138.40 +/- 5.40 165.40 115.80 -215.00 Pass STW-1103 07/01/06 H-3 446.50 +/- 11.80 428.85 300.20 -557.50 Pass STW-1103e 07/01/06 Mn-54 < 0.30 0.00 Pass STW-1103 07/01/06 Ni-63 116.70 +/- 3.60 118.62 83.03 - 154.21 Pass STW-1103 07/01/06 Pu-238 1.27 +/- 0.07 1.39 0.97 -1.81 Pass STW-1103 07/01/06 Pu-239/40 1.67 +/- 0.08 1.94 1.36 -2.52 Pass STW-1103 07/01/06 Sr-90 16.40 +/- 1.90 15.69 10.98 - 20.40 Pass STW-1103 07/01/06 Tc-99 29.40 +/- 1.10 27.15 19.00 -35.29 Pass STW-1 103 07/01/06 U-233/4 1.97 +/- 0.08 2.15 1.50 -2.80 Pass STW-1103 07/01/06 U-238 1.97 +/- 0.08 2.22 1.55 -2.89 Pass STW-1103 07/01/06 Zn-65 192.50 +/- 2.40 176.37 123.46 -229.28 Pass Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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

MAPEP results are presented as the known values and expected laboratory precision (1 sigma, I determination) and control limits as defined by the MAPEP.

Included inthe MAPEP as a false positive.

f Difficulties with the analyses for transuranics isotopes in solid samples (Filters, Soil and vegetation),

were attributed to incomplete dissolution of the samples. Soil samples were repeated, results of reanalyses:

Pu-238, 53.1 +/- 5.3 bq/kg. Pu-239/240, 42.4 +/-4.7 bq/kg, U-233/4, 33.3 +/-3.5 bq/kg. U-238, 35.5 +/- 3.6 bq/kg.

The July vegetation sample was provided in two separate geometries, (100 ml. and 500 ml.). Results reported here used the 500 ml. standard size geometry. Results for the 100 ml. geometry showed approximately a 15% higher bias.

A6-3

APPENDIX B DATA REPORTING CONVENTIONS B-1

Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.

2.0. Single Measurements Each single measurement is reported as follows: x+s where: x = value of the measurement; s = 2ca counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is less than the lower limit of detection L, it is reported as: < L, where L = the lower limit of detection based on 4.66a uncertainty for a background sample.

3.0. Duplicate analyses 3.1 Individual results: For two analysis results; x 1 + s, and x2 +/- s2 Reported result: x +s; where x= (1/2) (x1 +x 2) ands= (1/2)s+s2 3.2. Individual results: < L 1 , <L 2 Reported result: < L, where L = lower of Li and L2 3.3. Individual results: x +/- s, < L Reported result: " x +/- s if x > L; <L otherwise.

4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x1, x2 . . xn are defined as follows:

x=j n x S= n-4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.

4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.

4.5 In rounding off, the following rules are followed:

4.5.1. If the number following those to be retained is less than 5, the number is dropped, and the retained number s are kept unchanged. As an example, 11.443 is rounded off to 11.44.

4.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45.

B-2

APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-1

Table C-A. Maximum permissible concentrations a of radioactivity in air and water above natural background in unrestricted areas Air (pCi/m3) Water (pCi/L)

-3 Gross alpha 1 x 10 Strontium-89 8,000 Gross beta 1 Strontium-90 500 b -1 Iodine-1 31 2.8 x 10 Cesium-1 37 1,000 Barium-140 8,000 lodine-131 1,000 C

Potassium-40 4,000 Gross alpha 2 Gross beta 10 6

Tritium 1 x 10 a

Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.

b Concentrations may be averaged over a period not greater than one year.

Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.

c A natural radionuclide.

C-2

APPENDIX D

SUMMARY

OF THE LAND USE CENSUS D-1

Appendix D Summary of the Land Use Census The Duane Arnold Energy Land Use Census for 2006 was completed during September of 2006. All milk animals, residences and gardens greater than 500 square feet were identified within three miles for each of the 16 meteorological sectors. If none were identified within the three mile range, additional surveys were performed out to a distance of five miles. The Cedar River was surveyed by boat on July 18th of 2006 for water use downstream of the DAEC to Cedar Rapids.

There were 172 vegetable gardens identified during the performance of the 2006 Census. This number is less than the number of gardens found in the 2005 survey by 6. There were no changes to the nearest vegetable receptor in any of the sixteen direction sectors.

The locations of the nearest resident for each sector remained the same and there were no changes in the milk animal locations within the 3 mile radius of the plant in the past year.

16 new homes were built or were under construction within three miles of the DAEC, compared to 45 new homes identified in 2005 and 31 new homes in 2004.

Most of the new houses built are located in the town of Palo (SSW).

The Cedar River survey revealed no new withdrawals of river water compared to previous surveys. Irrigation of the strawberry farm in Palo and fishing remain the only food pathway uses of river water between the DAEC and Cedar Rapids.

Pursuant to ESP4.4, no changes were observed offsite that could adversely affect the safe operation of the DAEC or that would warrant a UFSAR update such as new gas pipelines, toxic gas installations or airfield strips.

D-2

APPENDIX E ANNUAL RADIATION DOSE ASSESSMENT E-1

Appendix E Annual Radiation Dose Assessment The annual offsite radiation dose to a MEMBER OF THE PUBLIC was determined by assessment of environmental dosimeter results and by calculations based on monitored effluent releases.

Section A. Dose Contribution from Direct Radiation Direct radiation dose from the operation of the DAEC was reported by TLDs placed at locations in the surrounding environment as described in the Offsite Dose Assessment Manual (ODAM).

1. Pre-operational and 2006 TLD results were compared using a paired difference test. No significant differences in the TLD populations were observed for the 0.5 mile and one mile TLD populations using a confidence level of 99%.

2. As stated in Part 1 of this report, no plant effect was indicated by the TLDs when dose results were compared to the estimated average natural background for Middle America.

Section B. Estimated Offsite Dose from Effluent Releases

" The contribution of dose to a member of the public most likely to be exposed from liquid and gaseous effluent releases was calculated with the Meteorological Information and Dose Assessment System (MIDAS) computer program in accordance with ODAM. The calculation methods follow those prescribed by Reg. Guide 1.109.

Because there were no nuclides detected in the environment at or beyond the site boundary that were due to the operation of the DAEC, no comparison of calculated dose from gaseous or liquid releases and dose calculated from environmental contamination was performed.

Following calculation of offsite doses, the appropriateness of REMP sampling station types and locations was reviewed. The current sampling scheme was determined to be more than adequate for the identified receptors.

" Results of the MIDAS dose calculations are displayed below.

1. The maximally exposed organ due to liquid effluents was the liver of a child, with an estimated dose equivalent of 8.22E-06 mrem.

2. The whole body dose equivalent to the maximally exposed individual due to liquid effluents was 8.22E-06 mrem.

3. The maximum dose to air at the site boundary from noble gases released was 2.69E-03 mrad from gamma radiation at 455 meters South.

E-2

4. The maximum dose to air at the site boundary from noble gases released was 9.07E-02 mrad beta radiation at 535 meters SSW.

5. The whole body dose equivalent to the maximally exposed individual from noble gases was 1.36E-03 mrem, at 805 meters West.

6. The skin dose equivalent to the maximally exposed individual from noble gases was 1.84E-03 mrem, at 805 meters West.

7. The maximally exposed organ due to airborne iodines and particulates with half-lives greater than eight days was the skin of a child at 805 meters West, with an estimated dose equivalent of 6.68E-03 mrem.

Conclusion:

No measurable dose due to the operation of the DAEC was detected by environmental TLDs in 2006. The calculated doses are below the regulatory limits stated in Appendix I to 10 CFR 50 and in 40 CFR 190.

Estimated Maximum Offsite Individual Doses for 2006 0

Group (meters) Equivalent 10 CFR 50, (mrem) Appendix I Limit Direct Radiation (as measured by None TLDs)

Liquid Releases Whole Body Dose Child S 8.22E-06 mrem 3 mrem Organ Dose Liver- S 8.22E-06 mrem 10 mrem Noble Gas Gamma Air Dose 455 S 2.69E-03 mrad 10 mrad Beta Air Dose 535 SSW 9.07E-02 mrad 20 mrad Whole Body All 805 W 1.36E-03 mrem 5 mrem Skin All 805 W 1.84E-03 mrad 15 mrem Particulates & lodines Organ Dose Skin 805 W 6.68E-03 mrem 15 mrem

k There is no Appendix I limit for direct radiation. It is listed here to demonstrate compliance with 40 CFR 190 limits of 25 mrem whole body and 75 mrem thyroid.

E-3

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1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

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 =Text=
-{{#Wiki_filter:.Environmental, Inc.Midwest Laboratory an Allegheny Technologles Co.700 Landwehr Road
+{{#Wiki_filter:. Environmental, Inc.
-* Northbrook, IL 60062-2310 ph. (847) 564-0700 &deg; fax (847) 564-4517 DUANE ARNOLD ENERGY CENTER CEDAR RAPIDS, IOWA DOCKET NO. 50-331 REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Annual Radiological Environmental Operating Report January I to December 31, 2006 Prepared and submitted by ENVIRONMENTAL, Inc.Midwest Laboratory Project No. 8001 Approved : Loborva anager PREFACE Staff members of the Environmental, Inc., Midwest Laboratory were responsible for the acquisition of data presented in this report, with the exception of Appendices D and E, which were completed by DAEC personnel.
+Midwest Laboratory an Allegheny Technologles Co.
-All environmental samples, with the exception of aquatic, were collected by personnel of DAEC. Aquatic samples were collected by the University of Iowa Hygienic Laboratory.
+Landwehr Road
+* Northbrook, IL 60062-2310 ph. (847) 564-0700 &deg; fax (847) 564-4517 DUANE ARNOLD ENERGY CENTER CEDAR RAPIDS, IOWA DOCKET NO. 50-331 REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Annual Radiological Environmental Operating Report January I to December 31, 2006 Prepared and submitted by ENVIRONMENTAL, Inc.
+Midwest Laboratory Project No. 8001 Approved :
+Loborva            anager
+PREFACE Staff members of the Environmental, Inc., Midwest Laboratory were responsible for the acquisition of data presented in this report, with the exception of Appendices D and E, which were completed by DAEC personnel. All environmental samples, with the exception of aquatic, were collected by personnel of DAEC. Aquatic samples were collected by the University of Iowa Hygienic Laboratory.
 The report was prepared by Environmental, Inc., Midwest Laboratory, with the exception of Appendices D and E, which were prepared by DAEC personnel.
-ii TABLE OF CONTENTS No. Page P R E F A C E ......................................................................................................................
+ii
-ii List of Tables ........................................................................................................
-v L ist o f F ig u re s ................................................................................
-..............................
-v i
-==1.0 INTRODUCTION==
+TABLE OF CONTENTS No.                                                                                                                                                 Page P R E F AC E ......................................................................................................................            ii List of Tables ........................................................................................................                        v List o f F igu re s ................................................................................           .............................. v i
-.....................................................................................................
+==1.0    INTRODUCTION==
-2.0
+ .....................................................................................................                             1 2.0
 ==SUMMARY==
-  ....................................................................................................................
+  ....................................................................................................................                  2 3.0    ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ..............................                                                                  3 3.1        Program Design and Data Interpretation .........................................................                                    3 3.2        Program Description ....................................................................................                           4 3.3        Program Execution ......................................................................................                           5 3.4        Laboratory Procedures ...............................................................................                              6 3.5        Program Modifications .................................................................................                            7 4.0    RESULTS AND DISCUSSION ................................................................................                                       8 4.1       Atmospheric Nuclear Detonations and Nuclear Accidents .......................... 8 4.2        Program Findings ........................................................................................                          8 5.0    TABLES AND FIGURES .......................................................................................                                   12
-3.0 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ..............................
-3.1 Program Design and Data Interpretation
+==6.0    REFERENCES==
-.........................................................
+CITED ..........................................................................................                                  29 APPENDICES A     Interlaboratory Comparison Program Results ....................................................                                           A-1 B     Data Reporting Conventions ...............................................................................                                B-1 C     Effluent Concentration Limits for Radioactivity in Air and Water Above Background in Unrestricted Areas .........................................................                                     C-1 D     Summary of the Land Use Census ......................................................................                                     D-1 E     Annual Radiation Dose Assessment ....................................................................                                     E-1
-3.2 Program Description
-....................................................................................
+TABLE OF CONTENTS (continued)
-3.3 Program Execution
+PART II                                                                                                                     Paqe Data Tabulations and Analyses ..................................................................................... i iv
-......................................................................................
-3.4 Laboratory Procedures
-...............................................................................
-3.5 Program Modifications
-.................................................................................
-4.0 RESULTS AND DISCUSSION
-................................................................................
-4.1 Atmospheric Nuclear Detonations and Nuclear Accidents
-..........................
-4.2 Program Findings ........................................................................................
-5.0 TABLES AND FIGURES .......................................................................................
-==6.0 REFERENCES==
+LIST OF TABLES No.                                                                                                                                  Pae 5.1        Characteristic Properties of Isotopes Quantified in Gamma-spectroscopic A na lyse s ................................................................................................ . . 13 5.2        Sample Collection and Analysis Program ..............................................................                      14 5.3        Sampling Locations, DAEC ....................................................................................              17 5.4        Type and Frequency of Collections .......................................................................                  19 5.5        Sample Codes Used in Table 5.4 ..........................................................................                 20 5.6        Missed Collections and Analyses ..........................................................................                21 5.7        Radiological Environmental Monitoring Program Summary .......................................                             22 In addition, the following tables are in the Appendices:
+Appendix A A-1        Interlaboratory Comparison Program Results ....................................................                          A1-1 A-2        Interlaboratory      Comparison                   Program               Results,             Thermoluminescent Dosimeters (TLDs) ......................................................................................        A2-1 A-3        In-house Spiked Samples .........................................................................................        A3-1 A-4        In-house "Blank" Samples ........................................................................................        A4-1 A-5        In-house "Duplicate" Samples .............................................................................               A5-1 A-6        Department of Energy MAPEP comparison results ..................................................                         A6-1 Attachment A: Acceptance criteria for spiked samples ............................................                        A-2 Appendix C C-1        Effluent Concentration Limits for Radioactivity in Air and Water Above Background in Unrestricted Areas ...............................................................                C-2 v
-CITED ..........................................................................................
+LIST OF FIGURES No.                                                                                                                         PaQe 5.1 Radiological Environmental Monitoring Program Sampling Stations near the Duane Arnold Energy Center ....................................................................                  27 5.2 Radiological Environmental Monitoring Program Sampling Stations Outside 0 .5 Mile s ................................................................................................ . . 28 vi
-APPENDICES A Interlaboratory Comparison Program Results ....................................................
-A-1 B Data Reporting Conventions
-...............................................................................
-B-1 C Effluent Concentration Limits for Radioactivity in Air and Water Above Background in Unrestricted Areas .........................................................
-C-1 D Summary of the Land Use Census ......................................................................
-D-1 E Annual Radiation Dose Assessment
-....................................................................
-E-1 TABLE OF CONTENTS (continued)
-PART II Paqe Data Tabulations and Analyses .....................................................................................
-i iv LIST OF TABLES No. Pae 5.1 Characteristic Properties of Isotopes Quantified in Gamma-spectroscopic A na lyse s ................................................................................................
-..13 5.2 Sample Collection and Analysis Program ..............................................................
-5.3 Sampling Locations, DAEC ....................................................................................
-5.4 Type and Frequency of Collections
-.......................................................................
-5.5 Sample Codes Used in Table 5.4 ..........................................................................
-5.6 Missed Collections and Analyses ..........................................................................
-5.7 Radiological Environmental Monitoring Program Summary .......................................
-In addition, the following tables are in the Appendices:
-Appendix A A-1 Interlaboratory Comparison Program Results ....................................................
-A1-1 A-2 Interlaboratory Comparison Program Results, Thermoluminescent Dosimeters (TLDs) ......................................................................................
-A2-1 A-3 In-house Spiked Samples .........................................................................................
-A3-1 A-4 In-house "Blank" Samples ........................................................................................
-A4-1 A-5 In-house "Duplicate" Samples .............................................................................
-A5-1 A-6 Department of Energy MAPEP comparison results ..................................................
-A6-1 Attachment A: Acceptance criteria for spiked samples ............................................
-A-2 Appendix C C-1 Effluent Concentration Limits for Radioactivity in Air and Water Above Background in Unrestricted Areas ...............................................................
-C-2 v LIST OF FIGURES No. PaQe 5.1 Radiological Environmental Monitoring Program Sampling Stations near the Duane Arnold Energy Center ....................................................................
-5.2 Radiological Environmental Monitoring Program Sampling Stations Outside 0 .5 M ile s ................................................................................................
-..2 8 vi
 ==1.0 INTRODUCTION==
-This report summarizes and interprets results of the Radiological Environmental Monitoring Program conducted by Environmental, Inc., Midwest Laboratory at the Duane Arnold Energy Center, Palo, Iowa, during the period January -December, 2006. This Program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the Plant on its surroundings.
+This report summarizes and interprets results of the Radiological Environmental Monitoring Program conducted by Environmental, Inc., Midwest Laboratory at the Duane Arnold Energy Center, Palo, Iowa, during the period January - December, 2006. This Program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the Plant on its surroundings.
-Tabulation of the individual analyses made during the year are included in Part II of this report.The Duane Arnold Energy Center (DAEC) is a boiling water reactor, located in Linn.County, Iowa, on the Cedar River, and owned and operated by FPL Energy. Initial criticality was attained on March 23, 1974. The reactor reached 100% power on August 12, 1974. Commercial operation began on February 1, 1975.1 2.0
+Tabulation of the individual analyses made during the year are included in Part II of this report.
+The Duane Arnold Energy Center (DAEC) is a boiling water reactor, located in Linn.County, Iowa, on the Cedar River, and owned and operated by FPL Energy. Initial criticality was attained on March 23, 1974. The reactor reached 100% power on August 12, 1974. Commercial operation began on February 1, 1975.
+.0
 ==SUMMARY==
-The Radiological Environmental Monitoring Program, as required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Duane Arnold Energy Center, is herein described.
-Results for the year 2006 are summarized and discussed.
+The Radiological Environmental Monitoring Program, as required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Duane Arnold Energy Center, is herein described. Results for the year 2006 are summarized and discussed.
-Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Duane Arnold Energy Center.No effect on the environment is indicated in the areas surrounding the Site of the Duane Arnold Energy Center.2 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.1 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program at the Duane Arnold Energy Center (DAEC) is to assess the impact of the plant on its environment.
+Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Duane Arnold Energy Center.
-For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).Sources of environmental radiation include the following:
+No effect on the environment is indicated in the areas surrounding the Site of the Duane Arnold Energy Center.
-(1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; and (4) Industrial and medical radioactive waste.In interpreting the data, effects due to the DAEC operation must be distinguished from those due to other sources.A major interpretive aid in assessment of these effects is the design of the monitoring program at the DAEC which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream).
-A station effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location.
-The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the DAEC site. The DAEC's monitoring program includes analyses for strontium-90 and iodine-131, which are fission products, and tritium, which is produced by cosmic rays, atmospheric nuclear detonations, and also by nuclear power plants.Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified:
+.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.1 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program at the Duane Arnold Energy Center (DAEC) is to assess the impact of the plant on its environment. For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).
-zirconium-95, cesium-137, and cerium-144.
+Sources of environmental radiation include the following:
-These three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation.
+(1)       Natural background radiation arising from cosmic rays and primordial radionuclides; (2)       Fallout from atmospheric nuclear detonations; (3)       Releases from nuclear power plants; and (4)       Industrial and medical radioactive waste.
-Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products ten (10) days after reactor shutdown.
+In interpreting the data, effects due to the DAEC operation must be distinguished from those due to other sources.
-On the other hand, ten (10) days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud,1963).
+A major interpretive aid in assessment of these effects is the design of the monitoring program at the DAEC which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream). A station effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.
-The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141.
+An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the DAEC site. The DAEC's monitoring program includes analyses for strontium-90 and iodine-131, which are fission products, and tritium, which is produced by cosmic rays, atmospheric nuclear detonations, and also by nuclear power plants.
-These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the next group, manganese-54, cobalt-58 and-60, and zinc-65, are activation products and arise from activation of corrosion products.
+Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, and cerium-144. These three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products ten (10) days after reactor shutdown. On the other hand, ten (10) days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud,1963). The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the next group, manganese-54, cobalt-58 and-60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of nuclear power plant effluents, but are not produced in significant quantities by nuclear detonations. Nuclides of the final group, beryllium-7, which is of cosmogenic origin, and potassium-40, a naturally-occurring isotope, were chosen as calibration monitors and should not be considered radiological impact indicators.
-They are typical components of nuclear power plant effluents, but are not produced in significant quantities by nuclear detonations.
-Nuclides of the final group, beryllium-7, which is of cosmogenic origin, and potassium-40, a naturally-occurring isotope, were chosen as calibration monitors and should not be considered radiological impact indicators.
-3.1 Program Design and Data Interpretation (continued)
+.1       Program Design and Data Interpretation (continued)
-Characteristic properties of isotopes quantified in gamma-spectroscopic analysis are presented in Table 5.1. Other means of distinguishing sources of environmental radiation can be employed in interpreting the data. Current radiation levels can be compared with previous levels, including those measured before the Plant became operational.
+Characteristic properties of isotopes quantified in gamma-spectroscopic analysis are presented in Table 5.1. Other means of distinguishing sources of environmental radiation can be employed in interpreting the data. Current radiation levels can be compared with previous levels, including those measured before the Plant became operational. Results of the DAEC's Monitoring Program can be related to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the. environment, e.g., atmospheric nuclear detonations.
-Results of the DAEC's Monitoring Program can be related to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the. environment, e.g., atmospheric nuclear detonations.
+.2  Program Description The sampling and analysis schedule for the environmental radiological monitoring program at the DAEC is summarized in Table 5.2 and is briefly reviewed below. Table 5.3 defines the sampling location codes used in Table 5.2 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site. The types of samples collected at each location and the frequency of collections are presented in Table 5.4 using codes defined in Table 5.5.
-.2 Program Description The sampling and analysis schedule for the environmental radiological monitoring program at the DAEC is summarized in Table 5.2 and is briefly reviewed below. Table 5.3 defines the sampling location codes used in Table 5.2 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site. The types of samples collected at each location and the frequency of collections are presented in Table 5.4 using codes defined in Table 5.5.To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at eight locations.
+To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at eight locations. Airborne iodine is collected by continuous pumping through charcoal filters. Seven of the eight locations are indicators and one is a control (D-13).
-Airborne iodine is collected by continuous pumping through charcoal filters. Seven of the eight locations are indicators and one is a control (D-13).Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity.
+Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity. If gross beta activity exceeds ten times the yearly mean of the control samples, gamma isotopic analysis is performed. Quarterly composites of airborne particulates from each location are analyzed for gamma emitting isotopes.
-If gross beta activity exceeds ten times the yearly mean of the control samples, gamma isotopic analysis is performed.
+Charcoal filter samples are analyzed weekly for iodine-1 31.
-Quarterly composites of airborne particulates from each location are analyzed for gamma emitting isotopes.Charcoal filter samples are analyzed weekly for iodine-1 31.Ambient gamma radiation is monitored at the eight air sampling locations.
+Ambient gamma radiation is monitored at the eight air sampling locations. In addition, gamma radiation is monitored at thirty-four special interest locations: eighteen in a circle within a 0.5 mi.
-In addition, gamma radiation is monitored at thirty-four special interest locations:
+radius from the DAEC stack; six in 22.50 sectors within 1 mi. from the DAEC stack; ten in 22.50 sectors between 1 and 3 miles from the DAEC stack and four locations greater than 3 miles from the DAEC stack. TLDs are placed at each location and are exchanged and analyzed quarterly.
-eighteen in a circle within a 0.5 mi.radius from the DAEC stack; six in 22.50 sectors within 1 mi. from the DAEC stack; ten in 22.50 sectors between 1 and 3 miles from the DAEC stack and four locations greater than 3 miles from the DAEC stack. TLDs are placed at each location and are exchanged and analyzed quarterly.
+Precipitation is collected monthly from one location and analyzed for gamma-emitting isotopes.
-Precipitation is collected monthly from one location and analyzed for gamma-emitting isotopes.Quarterly composites are analyzed for tritium.Milk samples are collected monthly from one indicator and one control location during the non-grazing season, October through April, and biweekly during the grazing season, May 1 through September
+Quarterly composites are analyzed for tritium.
-: 30. The samples are analyzed for iodine-131 and gamma-emitting isotopes.For additional monitoring of the terrestrial environment, grain, hay and broad leaf vegetation samples are collected annually, as available, from seven locations:
+Milk samples are collected monthly from one indicator and one control location during the non-grazing season, October through April, and biweekly during the grazing season, May 1 through September 30. The samples are analyzed for iodine-131 and gamma-emitting isotopes.
-one control (D-108) and six indicators (D-16, D-57, D-58, D-72, D-96, and D-109). Grain, hay and broad leaf (green leafy)vegetation samples are analyzed for gamma-emitting isotopes and at least one broad leaf vegetation is analyzed for iodine-131.
+For additional monitoring of the terrestrial environment, grain, hay and broad leaf vegetation samples are collected annually, as available, from seven locations: one control (D-108) and six indicators (D-16, D-57, D-58, D-72, D-96, and D-109). Grain, hay and broad leaf (green leafy) vegetation samples are analyzed for gamma-emitting isotopes and at least one broad leaf vegetation is analyzed for iodine-131.
-If cattle are, slaughtered for home use, a meat sample is collected annually, during or immediately following a grazing period from animals grazing on-site. The sample is analyzed for gamma-emitting isotopes.4 Program Description (continued)
+If cattle are, slaughtered for home use, a meat sample is collected annually, during or immediately following a grazing period from animals grazing on-site. The sample is analyzed for gamma-emitting isotopes.
+Program Description (continued)
 Potable ground water is collected quarterly from a treated municipal water system (D-53), the inlet to the municipal water treatment system (D-54), three additional indicator locations (D-55, D-57, D-58) and one control location, (D-72). An additional six site monitoring wells were added to the program in 2006. The samples are analyzed for gross beta and tritium. If gross beta activity exceeds ten times the yearly mean of the control samples, gamma isotopic, strontium-89 and strontium-90 analyses are performed.
-Soil samples are collected once per year at two indicator locations (D-15 and D-16). The samples are analyzed for strontium-90 and gamma-emitting isotopes.Surface water is collected monthly from two river locations, D-50 (Inlet, control) and D-51 (Discharge).
+Soil samples are collected once per year at two indicator locations (D-15 and D-16). The samples are analyzed for strontium-90 and gamma-emitting isotopes.
-The sewage effluent location (D-107) is also monitored.
+Surface water is collected monthly from two river locations, D-50 (Inlet, control) and D-51 (Discharge). The sewage effluent location (D-107) is also monitored. All monthly samples are analyzed for gamma-emitting isotopes. Tritium analyses are performed on quarterly composites from each location.
-All monthly samples are analyzed for gamma-emitting isotopes.
+The aquatic environment is also monitored by upstream and downstream (D-49 and D-61) semiannual collections of fish. River bottom sediment is collected semiannually at the plant's intake and discharge (D-50 and D-51) and downstream of the sewage plant (D-1 07). The samples are analyzed for gamma-emitting isotopes.
-Tritium analyses are performed on quarterly composites from each location.The aquatic environment is also monitored by upstream and downstream (D-49 and D-61)semiannual collections of fish. River bottom sediment is collected semiannually at the plant's intake and discharge (D-50 and D-51) and downstream of the sewage plant (D-1 07). The samples are analyzed for gamma-emitting isotopes.3.3 Proqram Execution The program was executed as described in the preceding section with the following exceptions.
+.3 Proqram Execution The program was executed as described in the preceding section with the following exceptions.
-(1) Air Particulates
+(1)     Air Particulates / Air Iodine:
-/ Air Iodine: No air particulate
+No air particulate / air iodine sample was available from location D-07 for the week ending 03-09-06. The air sampler station was relocated.
-/ air iodine sample was available from location D-07 for the week ending 03-09-06.
+The air particulate filter from location D-16 was missing for the week ending 08-23-06.
-The air sampler station was relocated.
+The filter was lost in the field.
-The air particulate filter from location D-16 was missing for the week ending 08-23-06.The filter was lost in the field.(2) Milk: No milk was available from location D-96 for all of 2006. The herd has been sold.No milk was available from location D-101 for all of 2006. The location has been removed from the program.(3) Vegqetation No forage or broadleaf vegetation samples were available from the locations D-58, D-96 and D-109 for the October, 2006 collection.
+(2)     Milk:
-(4) Thermoluminescent Dosimeters:
+No milk was available from location D-96 for all of 2006. The herd has been sold.
-TLD for location D-1 was missing for the first quarter, 2006. The TLD was lost in the field.TLD, location D-2 was missing for the second quarter, 2006. The TLD was lost in the field.5 3.3 Proaram Execution (continued)
+No milk was available from location D-101 for all of 2006. The location has been removed from the program.
-(5) Sediments River sediments taken 07/19/06 did not meet the required six month collection frequency and should be characterized as missed samples.(6) Corrections to the 2005 Report: Section 3.3 states, that samples were not collected from location D-01, D-02, D-08 and D-10 after the week ending 12 March 2005. The date specified in the report should have been 12 May 2005 not 12 March 2005.The date specified in the report for the first milk sample collected at sample location D-101 was 01-06-04.
+(3)     Vegqetation No forage or broadleaf vegetation samples were available from the locations D-58, D-96 and D-109 for the October, 2006 collection.
-The date of collection should have been 01-04-05.An Airborne Iodine sample taken on 12/8/05 was not received at the laboratory until 12/22/2005.
+(4)     Thermoluminescent Dosimeters:
-The sample should have been characterized as a "missed analyses" due to the extended delay.River sediments taken 06/27/05 did not meet the required six month collection frequency and should be characterized as missed samples, due to the delay.Table 5.6 and Part II, Section 2.0 should have indicated that milk samples from sample location D 101 were not collected for the entire year.Table 5.6 and Part II, Section 2.0 should have indicated that milk samples from sample location D 96 were not available after 9/7/2005.3.4 Laboratory Procedures The iodine-131 analyses in milk were made using a sensitive radiochemical procedure involving separation of the iodine using an ion-exchange method, solvent extraction and subsequent beta counting.Gamma-spectroscopic analyses were performed using high-purity germanium (HPGe) detectors.
+TLD for location D-1 was missing for the first quarter, 2006. The TLD was lost in the field.
+TLD, location D-2 was missing for the second quarter, 2006. The TLD was lost in the field.
+.3 Proaram Execution (continued)
+(5)       Sediments River sediments taken 07/19/06 did not meet the required six month collection frequency and should be characterized as missed samples.
+(6)       Corrections to the 2005 Report:
+Section 3.3 states, that samples were not collected from location D-01, D-02, D-08 and D-10 after the week ending 12 March 2005. The date specified in the report should have been 12 May 2005 not 12 March 2005.
+The date specified in the report for the first milk sample collected at sample location D-101 was 01-06-04. The date of collection should have been 01-04-05.
+An Airborne Iodine sample taken on 12/8/05 was not received at the laboratory until 12/22/2005. The sample should have been characterized as a "missed analyses" due to the extended delay.
+River sediments taken 06/27/05 did not meet the required six month collection frequency and should be characterized as missed samples, due to the delay.
+Table 5.6 and Part II, Section 2.0 should have indicated that milk samples from sample location D 101 were not collected for the entire year.
+Table 5.6 and Part II, Section 2.0 should have indicated that milk samples from sample location D 96 were not available after 9/7/2005.
+.4 Laboratory Procedures The iodine-131 analyses in milk were made using a sensitive radiochemical procedure involving separation of the iodine using an ion-exchange method, solvent extraction and subsequent beta counting.
+Gamma-spectroscopic analyses were performed using high-purity germanium (HPGe) detectors.
 Levels of iodine-131 in vegetation and concentrations of airborne iodine-131 in charcoal samples were also determined by gamma spectroscopy.
 Tritium was measured by liquid scintillation.
 Analytical Procedures used by Environmental, Inc. are on file and are available for inspection.
-Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained.
+Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.
-Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2003 ). The QA Program includes participation in Interlaboratory Comparison (crosscheck)
+Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2003 ). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs.             Results obtained in crosscheck programs are presented in Appendix A.
-Programs.
-Results obtained in crosscheck programs are presented in Appendix A.6 3.5 Program Modifications Milk Milk from location D-96 was no longer available after September 7, 2005. The location was removed from the program in 2006.Goat milk was not available from location D-101 for 2005 and 2006.The goat was sold. The location was removed from the program in July, 2006.Surface water Surface water collections at location D-61, (0.5 mi. from Plant discharge) were initiated in November of 2006. The samples are analyzed for tritium and gamma emitting isotopes.Ground water Ground water monitoring of six on-site wells was added to the REMP in the third quarter, 2006, for analysis of gross beta and tritium. Analyses for strontium-89, strontium-90 and gamma emitting isotopes will be performed if the gross beta activity exceeds ten times the yearly mean of the potable water well control.7 4.0 RESULTS AND DISCUSSION All collections and analyses were made as scheduled, except for the listing in Table 5.6.Results are summarized in Table 5.7 as recommended by the Nuclear Regulatory Commission.
-For each type of analysis and sample medium, the table lists the mean and range of all indicator and control locations, as well as that location with the highest mean and range.Tabulated results of measurements are not included in this section, although reference to these results will be made in discussion.
+.5 Program Modifications Milk Milk from location D-96 was no longer available after September 7, 2005. The location was removed from the program in 2006.
-A complete tabulation of results for 2006 is contained in Part II of the Annual Report on the Radiological Environmental Monitoring Program for the Duane Arnold Energy Center.4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 2006.4.2 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in 2006.Airborne Particulates The average annual gross beta concentrations in airborne particulates were similar at indicator 3 and control locations (0.029 and 0.027 pCi/m , respectively) and similar to levels observed from 1991 through 2005. The results are tabulated below.Year Indicators Controls Year Indicators Contrls 3 3 Concentration ( pCi/rm) Concentration ( pCi/rn)1991 0.023 0.022 1999 0.026 0.027 1992 0.022 0.023 2000 0.026 0.027 1993 0.022 0.023 2001 0.026 0.026 1994 0.023 0.024 2002 0.027 0.027 1995 0.025 0.024 2003 0.029 0.029 1996 0.024 0.023 2004 0.028 0.028 1997 0.023 0.023 2005 0.031 0.031 1998 0.024 0.024 2006 0.029 0.027 Average annual gross beta concentrations in airborne particulates.
+Goat milk was not available from location D-101 for 2005 and 2006.The goat was sold. The location was removed from the program in July, 2006.
-Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations.
+Surface water Surface water collections at location D-61, (0.5 mi. from Plant discharge) were initiated in November of 2006. The samples are analyzed for tritium and gamma emitting isotopes.
-Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and AI-Salih, 1955) was detected in all samples, with an average activity of 0.075 pCi/mn for all locations.
+Ground water Ground water monitoring of six on-site wells was added to the REMP in the third quarter, 2006, for analysis of gross beta and tritium. Analyses for strontium-89, strontium-90 and gamma emitting isotopes will be performed if the gross beta activity exceeds ten times the yearly mean of the potable water well control.
-All other gamma-emitting isotopes were below their respective LLD limits.8 Proaram Findinos (continued)
-Airborne Iodine 3 Weekly levels of airborne iodine-1 31 were below the lower limit of detection (LLD) of 0.03 pCi/m in all samples.Ambient Radiation (TLDs)At twelve air sampling locations, the TLD readings averaged 17.5 and 17.4 mR/quarter for indicator and control locations, respectively.
-At locations within a half mile, one mile and three mile radius of the stack, measurements averaged 19.1 mR/quarter, 19.9 mR/quarter and 17.3 mR/quarter, respectively.
+.0 RESULTS AND DISCUSSION All collections and analyses were made as scheduled, except for the listing in Table 5.6.
-The average for all locations was 18.4 mR/quarter.
+Results are summarized in Table 5.7 as recommended by the Nuclear Regulatory Commission. For each type of analysis and sample medium, the table lists the mean and range of all indicator and control locations, as well as that location with the highest mean and range.
-This is lower than the estimated average natural background radiation for Middle America, 19.5 mR/quarter, which is based on data on Pages 71 and 108 of the report, "Natural Background Radiation in the United States" (National Council on Radiation Protection and Measurements, 1975). The terrestrial absorbed dose (uncorrected for structural and body shielding) ranges from 8.8 to 18.8 mrad/quarter and, averages 11.5 mrad/quarter for Middle America. Cosmic radiation and cosmogenic radionuclides contribute 8.0 mrad/quarter for a total average of 19.5 mrad/quarter.
+Tabulated results of measurements are not included in this section, although reference to these results will be made in discussion. A complete tabulation of results for 2006 is contained in Part II of the Annual Report on the Radiological Environmental Monitoring Program for the Duane Arnold Energy Center.
+.1       Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 2006.
+.2       Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in 2006.
+Airborne Particulates The average annual gross beta concentrations in airborne particulates were similar at indicator 3
+and control locations (0.029 and 0.027 pCi/m , respectively) and similar to levels observed from 1991 through 2005. The results are tabulated below.
+Year         Indicators       Controls          Year         Indicators        Contrls 3                                                3 Concentration ( pCi/rm)                           Concentration ( pCi/rn) 1991           0.023           0.022            1999           0.026            0.027 1992           0.022           0.023            2000           0.026            0.027 1993           0.022           0.023            2001           0.026            0.026 1994           0.023           0.024            2002           0.027            0.027 1995           0.025           0.024            2003           0.029            0.029 1996           0.024           0.023            2004           0.028            0.028 1997           0.023           0.023            2005           0.031            0.031 1998           0.024           0.024            2006           0.029            0.027 Average annual gross beta concentrations in airborne particulates.
+Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and AI-Salih, 1955) was detected in all samples, with an average activity of 0.075 pCi/mn for all locations. All other gamma-emitting isotopes were below their respective LLD limits.
+Proaram Findinos (continued)
+Airborne Iodine 3
+Weekly levels of airborne iodine-1 31 were below the lower limit of detection (LLD) of 0.03 pCi/m in all samples.
+Ambient Radiation (TLDs)
+At twelve air sampling locations, the TLD readings averaged 17.5 and 17.4 mR/quarter for indicator and control locations, respectively. At locations within a half mile, one mile and three mile radius of the stack, measurements averaged 19.1 mR/quarter, 19.9 mR/quarter and 17.3 mR/quarter, respectively. The average for all locations was 18.4 mR/quarter. This is lower than the estimated average natural background radiation for Middle America, 19.5 mR/quarter, which is based on data on Pages 71 and 108 of the report, "Natural Background Radiation in the United States" (National Council on Radiation Protection and Measurements, 1975). The terrestrial absorbed dose (uncorrected for structural and body shielding) ranges from 8.8 to 18.8 mrad/quarter and, averages 11.5 mrad/quarter for Middle America. Cosmic radiation and cosmogenic radionuclides contribute 8.0 mrad/quarter for a total average of 19.5 mrad/quarter.
 No plant effect is indicated.
-Precipitation Precipitation from an on-site location was analyzed for tritium and gamma-emitting isotopes.No tritium activity was measured above the LLD of 182 pCi/L in any precipitation sample tested.No gamma-emitting isotopes were detected.During October, 2006, an additional twenty-seven samples were collected in closer proximity to the reactor building vent shaft release point. Downwind of the release point, concentrations of tritium measured from 158 to 2,666 pCi/L. No tritium was detected in the upwind samples. In no case did concentrations exceed the threshold for reportability of 30,000 pCi/L. Results of the testing are listed in Part II, Appendix A, Supplemental Analyses.Milk Iodine-1 31 results were below the detection limit of 0.5 pCi/L in all samples.No gamma-emitting isotopes, except naturally occurring potassium-40, were detected in any milk samples. This is consistent with the finding of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).In summary, milk data for 2006 show no radiological effects of plant operation.
+Precipitation Precipitation from an on-site location was analyzed for tritium and gamma-emitting isotopes.
-Proaram Findinas (continued)
+No tritium activity was measured above the LLD of 182 pCi/L in any precipitation sample tested.
-Ground Water (potable)The annual mean for gross beta activity averaged 3.5 pCi/L, similar to levels observed from 1991 through 2005. The location, with the highest mean (4.4 pCi/L) was D-58, a farm 1.0 mile distant from the plant.Tritium activity measured below the LLD of 193 pCi/L in all samples. No effect from plant operation is indicated.
+No gamma-emitting isotopes were detected.
-Ground Water (Site Monitoring Wells)Analysis of water from six on-site monitoring wells was initiated in 2006. Three of the six wells are shallow wells and the other three are of intermediate depth.The annual mean for gross beta activity for the intermediate depth wells measured 2.1 pCi/liter and was 4.4 pCi/liter in the shallow wells.No tritium was identified in samples taken from the intermediate depth wells. Tritium was identified in two of six samples taken from the shallow wells and has been attributed to "washout" of tritium from gaseous effluents. (See Program Findings for Precipitation)
+During October, 2006, an additional twenty-seven samples were collected in closer proximity to the reactor building vent shaft release point. Downwind of the release point, concentrations of tritium measured from 158 to 2,666 pCi/L. No tritium was detected in the upwind samples. In no case did concentrations exceed the threshold for reportability of 30,000 pCi/L. Results of the testing are listed in Part II, Appendix A, Supplemental Analyses.
+Milk Iodine-1 31 results were below the detection limit of 0.5 pCi/L in all samples.
+No gamma-emitting isotopes, except naturally occurring potassium-40, were detected in any milk samples. This is consistent with the finding of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).
+In summary, milk data for 2006 show no radiological effects of plant operation.
+Proaram Findinas (continued)
+Ground Water (potable)
+The annual mean for gross beta activity averaged 3.5 pCi/L, similar to levels observed from 1991 through 2005. The location, with the highest mean (4.4 pCi/L) was D-58, a farm 1.0 mile distant from the plant.
+Tritium activity measured below the LLD of 193 pCi/L in all samples. No effect from plant operation is indicated.
+Ground Water (Site Monitoring Wells)
+Analysis of water from six on-site monitoring wells was initiated in 2006. Three of the six wells are shallow wells and the other three are of intermediate depth.
+The annual mean for gross beta activity for the intermediate depth wells measured 2.1 pCi/liter and was 4.4 pCi/liter in the shallow wells.
+No tritium was identified in samples taken from the intermediate depth wells. Tritium was identified in two of six samples taken from the shallow wells and has been attributed to "washout" of tritium from gaseous effluents. (See Program Findings for Precipitation)
 Ve~getation Iodine-131 concentrations in broadleaf vegetation were below the LLD level of 0.060 pCi/g wet weight in allsamples.
 Except for potassium-40, which was observed in all vegetation samples ( broadleaf, grain, and forage), all other gamma-emitting isotopes were below detection limits. No effect from plant operation is indicated.
 Soil Strontium-90 concentrations in soil were below the LLD level of 0.016 pCi/g dry weight in all samples. Cesium-137 activity measured 0.13 pCi/g dry weight in one of two on-site locations.
-The cesium-137 activity is similar or less than levels observed from 1991 through 2005, these levels are generally attributable to deposition of fallout from previous decades.Naturally-occurring potassium-40 averaged 12.23 pCi/g dry weight. No effect from the plant operation is indicated.
+The cesium-137 activity is similar or less than levels observed from 1991 through 2005, these levels are generally attributable to deposition of fallout from previous decades.
-Surface Water Measurable tritium was detected on site in one of the four D-107 (sewage effluent) composites, at an average concentration of 287 pCi/L. This is below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L. For all remaining surface water collections, tritium levels were measured below the LLD level of 193 pCi/L.All gamma-emitting isotopes were below their respective LLDs.No plant effect on surface water is indicated.
+Naturally-occurring potassium-40 averaged 12.23 pCi/g dry weight. No effect from the plant operation is indicated.
-Pro.gram Findings (continued)
+Surface Water Measurable tritium was detected on site in one of the four D-107 (sewage effluent) composites, at an average concentration of 287 pCi/L. This is below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L. For all remaining surface water collections, tritium levels were measured below the LLD level of 193 pCi/L.
-Fish All gamma-emitting isotopes, except naturally-occurring potassium-40, in edible portions were below detection limits. The potassium-40 level was similar at both indicator and control locations (3.19 and 3.27 pCi/g wet, respectively).
+All gamma-emitting isotopes were below their respective LLDs.
-No plant effect on the fish population is indicated.
+No plant effect on surface water is indicated.
-River Sediments River sediments were collected in July and September, 2006, and analyzed for gamma-emitting isotopes.
-Potassium-40 activity ranged from 4.86 -9.68 pCi/g dry weight and averaged 7.71 pCi/g dry weight.Trace Cs-137 activity was detected in the control sample (D-50) at a concentration of 0.033 pCi/gdry weight.All other gamma-emitting isotopes were below detection limits. There is no indication of a plant effect.11 5.0 TABLES AND FIGURES 12 Table 5.1 Characteristic properties of isotopes quantified in gamma-spectroscopic analyses.Designation Comment Isotope Half-life 8 1. Naturally Occurring A. Cosmogenic Produced by interaction of cosmic Be-7 53.2 d rays with atmosphere B. Terrestrial Primordial K-40 1.26 x 109 y II. Fission Products b Nuclear accidents and detonations constitute the major environmental source.A. Short-lived 1-131 8.04 d Ba-140 12.8 d B. Other than Short-lived Nb-95 35.15 d Zr-95 65 d Ru-1 03 39.35 d Ru-106 368.2 d Cs-1 34 2.061 y Cs-137 30.174 y Ce-141 32.5 d Ce-144 284.31 d Ill. Activation Products Typically found in nuclear power plant Mn-54 312.5 d effluents Fe-59 45.0 d Co-58 70.78 d Co-60 5.26 y Zn-65 245 d a Half-lives are taken from Appendix E of Environmental Quarterly, 1 January 1978, EML-334 (U. S. Department of b Energy, 1978).Includes fission-product daughters.
-Table 5.2 Sample collection and analysis program.Sampling Location Exposure Pathway and/or Sample Description Sampling and Collection Type and Frequency Sample Type Point Frequency of Analysisa Airborne 3 Hiawatha Continuous operation of Analyze for gross beta activity Particulates 5 Palo sampler with sample more than 24 hours after filter 6 Center Point collection at least once per change. Perform gamma isotopic 7 Shellsburg week or as required by dust analysis on each sample having 11 Toddville loading gross beta activity greater than ten 13 Alburnett (C) times the yearly mean of the 15 On-site North control samples.16 On-site South Composite weekly samples to form a quarterly composite (by location).
+Pro.gram Findings (continued)
-Analyze quarterly composite for gamma isotopic.Airborne Iodine 3 Hiawatha Continuous operation of Analyze each cartridge for iodine-5 Palo sampler with sample 131.6 Center Point collection at least once per 7 Shellsburg week.11 Toddville 13 Alburnett (C)15 On-site North 16 On-site South Ambient 1-2 (C), One dosimeter continuously Read gamma radiation dose Radiation 8, 10 at each location, quarterly.
+Fish All gamma-emitting isotopes, except naturally-occurring potassium-40, in edible portions were below detection limits. The potassium-40 level was similar at both indicator and control locations (3.19 and 3.27 pCi/g wet, respectively). No plant effect on the fish population is indicated.
-Dosimeters are changed at 3, 5-7, Air Particulate least quarterly.
+River Sediments River sediments were collected in July and September, 2006, and analyzed for gamma-emitting isotopes. Potassium-40 activity ranged from 4.86 - 9.68 pCi/g dry weight and averaged 7.71 pCi/g dry weight.
-, 13, Locations 15, 16 17-23, < 0.5 mi. of Stack 28-32, 43-48 < 1.0 mi. of Stack 82-86, 91 33-42 -< 3.0 mi. of Stack Surface Water 50 Plant Intake (C) Once per month. Tritium and gamma isotopic 51 Plant Discharge analyses of each sample (by location).
+Trace Cs-137 activity was detected in the control sample (D-50) at a concentration of 0.033 pCi/gdry weight.
-0.5 mi. downstream 107 Plant Sewage Dischange (C) Denotes control location.
+All other gamma-emitting isotopes were below detection limits. There is no indication of a plant effect.
-All other locations are indicators.
-Table 5.2 Sample collection and analysis program, (continued).
-Sampling Location Exposure Pathway and/or Sample Description Sampling and Collection Type and Frequency Sample Type Point Frequency of Analysisa Ground Water 53 Treated Municipal Grab sample at least Gross beta and tritium activity (potable) 54 Inlet to Municipal once per quarter analysis on quarterly sample. If Water Treatment gross beta is greater than ten System times the yearly mean of control 55 On-site well samples, perform gamma 57, 58 Wells off-site and isotopic and Sr-89 and Sr-90 72 (C) within 4 km of DAEC analyses.Ground Water D-111 On-site wells MW-01A (Monitoring B (SSE)Wells) D-1 12 On-site wells MW-02A B (ESE)D-1 13 On-site wells MW-03A B (NW)River 50 Plant Intake (C) At least once every Gamma isotopic analysis of each Sediment 51 Plant Discharge six months, sample.107 Sewage Effluent Canal (on-site)Vegetation 16, 57, Farms that raise food Annually at harvest Gamma isotopic analysis of 58, 72, crops time. One sample of edible portions.94, 96, each: grain, green 109 leafy, and forage. At 1-131 analysis on broadleaf least one sample vegetation.
+.0 TABLES AND FIGURES 12
-(C) should be broadleaf vegetation.
-Fish 49 Cedar River upstream One sample per 6 Gamma isotopic analysis on of DAEC not months (once during edible portions.influenced by effluent January through July (C) and once during August through 61 Downstream of DAEC December).
+Table 5.1 Characteristic properties of isotopes quantified in gamma-spectroscopic analyses.
-in influence of effluent Milkb 108 (C) Control Farm At least once per two During the grazing season: weeks during the Gamma isotopic and iodine-131 grazing season. analyses of each sample.109 Dairy Farm within 10 At least once per Duringq the non-.qrazing season: miles of Site month during the Gamma isotopic and iodine-1 31 non-grazing season. analyses of each sample.(C) denotes control location.
+Designation                              Comment                                   Isotope     Half-life8
-All other locations are indicators.
+: 1. Naturally Occurring A. Cosmogenic                      Produced    by interaction  of cosmic     Be-7        53.2 d rays with atmosphere B. Terrestrial                    Primordial                                K-40        1.26 x 109 y II. Fission Products b                   Nuclear accidents and detonations constitute the major environmental source.
-Table 5.2 Sample collection and analysis program, (continued).
+A. Short-lived                                                               1-131       8.04 d Ba-140      12.8 d B. Other than Short-lived                                                    Nb-95       35.15 d Zr-95       65 d Ru-1 03     39.35 d Ru-106      368.2 d Cs-1 34     2.061 y Cs-137      30.174 y Ce-141      32.5 d Ce-144      284.31 d Ill. Activation Products                Typically found in nuclear power plant    Mn-54       312.5 d effluents                                 Fe-59       45.0 d Co-58       70.78 d Co-60       5.26 y Zn-65       245 d a
-Sampling Location Exposure Pathway and/or Sample Description Sampling and Collection Type and Frequency Sample Type Point Frequency of Analysis 3 Precipitation On-site Monthly Gamma isotopic on all samples.Tritium on quarterly composites.
+Half-lives are taken from Appendix E of Environmental Quarterly, 1 January 1978, EML-334 (U. S. Department of b    Energy, 1978).
-Meatc On-site Annually Gamma Isotopic Soil 15, 16 On-site Annually Gamma Isotopic and Sr-90.Gamma isotopic analysis and analysis for gamma-emitting nuclides refer to high resolution gamma ray spectrum analysis.
+Includes fission-product daughters.
-Any radionuclide detected at a concentration greater than the lower limit of detection (LLD) should be reported quantitatively; conversely, any radionuclide concentration less than the LLD should not be reported.The grazing season is considered to be May I through September 30.C Meat was not collected in 2006; no animals slaughtered for home use.16 Table 5.3 Sampling locations, Duane Arnold Energy Center.Sampling Location Code Type Sampling Location Description Distance and Direction Point from Site Stack D-1 D-2 D-3 D-5 D-6 D-7 D-8 D-10 D-11 D-13 D-15 D-1 6 D-17 D-1 8 D-19 D-20 D-21 D-22 D-23 D-28 D-29 D-30 D-31 D-32 D-33 D-34 D-35 D-36 D-37 D-38 D-39 D-40 D-41 D-42 D-43 D-44 D-45 D-46 C C C 1 2 3 5 6 7 8 10 11 13 15 16 17 18 19 20 21 22 23 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 Cedar Rapids Marion Hiawatha Palo Center Point Shellsburg Urbana Atkins Toddville Alburnett On-site, Northwest On-site, South On-site, N On-site, NNE On-site, NE On-site, ENE On-site, ENE On-site, E On-site, ESE On-site, WSW On-site, W On-site, WNW On-site, NW On-site, NNW 3 miles N 3 miles NNE 3 miles NE 3 miles ENE 3 miles E 3 miles ESE 3 miles SE 3 miles SSE 3 miles S 3 miles SSE 1 mile SSw 1 mile WSW 1 mile W 1 mile WNW 11 mi @ 135*11 mi @ 125'7 mi@ 130'3 mi @ 2000 7 mi @0'6 mi @ 2550 10 mi @ 3450 9 mi @ 2100 4 mi @ 90'9 mi @ 700 0.5 mi @ 3050 0.5 mi @ 1900 0.5 mi N 0.5 mi NNE 0.5 mi NE 0.5 mi ENE 0.5 mi ENE 0.5 mi E 0.5 mi ESE 0.5 mi WSW 0.5 mi W 0.5 mi WNW 0.5 mi NW 0.5 mi NNW 3.0 mi N 3.0 mi NNE 3.0 mi NE 3.0 mi ENE 3.0 mi E 3.0 mi ESE 3.0 mi SE 3.0 mi SSE 3.0 mi S 3.0 mi SSE 1.0 mi SSW 1.0 mi WSW 1.0 mi W 1.0 mi WNW SE ESE SE SSW N W NW SSW E ENE NW SSE 17 Table 5.3 Sampling locations, Duane Arnold Energy Center (continued).
-Sampling Location Code Type Sampling Location Description Distance and Direction Point from Site Stack D-47 47 1 mile WNW 1.0 mi WNW D-48 48 1 mile NW 1.0 mi NW D-49 C 49 Lewis Access, upstream of DAEC 4.0 mi NNW D-50 C 50 Plant Intake D-51 51 Plant Discharge D-53 53 Treated Municipal Water D-54 54 Inlet, Municipal Water Treatment System D-55 55 On-site Well D-57 57 Farm (Off-site Well) 1.0 mi WSW D-58 58 Farm (Off-site Well) 0.5 mi WSW-SW D-61 61 0.5 mi downstream of plant discharge D-72 C 72 Farm 2.0 mi SSW D-82 82 On-site, SE 0.5 mi SE D-83 83 On-site, SSE 0.5 mi SSE D-84 84 On-site, S 0.5 mi S D-85 85 On-site, SSW 0.5 mi SSW D-86 86 On-site, SW 0.5 mi SW D-91 91 On-site, N 0.5 mi N D-94 94 Farm 2.7 mi N D-96 96 Farm 8.0 mi SSW D-101 101 Farm 4.0 mi E D-107 107 Sewage Effluent Canal On-site D-108 C 108 Farm 17.3 mi. SW D-109 109 Farm 3.6 mi. SW D-111 110 Monitoring wells, MW-01A, B On-site, 210m SSE D-1 12 111 Monitoring wells, MW-02A, B On-site, 280m ESE D-113 112 Monitoring wells, MW-03A, B On-site, 190m NW"C" denotes control location.
-All other locations are indicators.
+Table 5.2 Sample collection and analysis program.
-Table 5.4 Type and Frequency of collection.
+Sampling Location Exposure Pathway and/or Sample              Description          Sampling and Collection           Type and Frequency Sample Type      Point                                          Frequency                     of Analysisa Airborne         3           Hiawatha                Continuous operation of       Analyze for gross beta activity Particulates   5           Palo                    sampler with sample           more than 24 hours after filter 6           Center Point            collection at least once per  change. Perform gamma isotopic 7           Shellsburg              week or as required by dust   analysis on each sample having 11          Toddville               loading                      gross beta activity greater than ten 13          Alburnett (C)                                        times the yearly mean of the 15          On-site North                                         control samples.
-Location Location Type Weekly Monthly Quarterly Semiannually Annually D-1 C AP TLD D-2 C AP, Al TLD D-3 AP, Al TLD D-5 AP, Al TLD D-6 AP, Al TLD D-7 AP, Al TLD D-8 AP, Al TLD D-10 AP TLD D-11 AP, Al TLD D-13 C AP, Al TLD D-15 AP, Al TLD SO D-16 AP, Al TLD SO, G D-17 to D-23 TLD D-28 to D-42 TLD D-43 to D-48 TLD D-49 C F D-50 C SW RS D-51 SW RS D-53 WW D-54 WW D-55 WW D-57 WW G D-58 WW G D-61 SWb F D-72 C WW G D-82 to D-86 TLD D-91 TLD D-94 G D-96 G D-107 SW RS D-108 C MI G D-109 MI G On-site P ME D-1 11 to D-1 13 a WW"C" denotes control location.
+         On-site South Composite weekly samples to form a quarterly composite (by location). Analyze quarterly composite for gamma isotopic.
-All other locations are indicators.
+Airborne Iodine   3           Hiawatha                Continuous operation of      Analyze each cartridge for iodine-5           Palo                    sampler with sample           131.
-a Locations added third quarter, 2006.b Location added in November, 2006.19 Table 5.5. Sample codes used in 5.4.Code Description AP Airborne Particulates Al Airborne Iodine TLD Thermoluminescent Dosimeter P Precipitation Ml Milk WW Well Water G Vegetation ME Meat SO Soil SW Surface Water F Fish BS River Sediment 20 Table 5.6. Missed collections and analyses, Duane Arnold Energy Center.Sample Collection Date Type Analysis Location(s) or Period Comments M! Gamma, 1-131 D-96 2006 No sample; herd sold.Ml Gamma, 1-131 D-101 2006 No sample; goat sold.AP/I Beta, 1-131 D-07 03-09-06 Electric off due to relocation.
+          Center Point            collection at least once per 7           Shellsburg              week.
-TLD Ambient Gamma D-1 1st Qtr TLD missing in field.TLD Ambient Gamma D-2 2nd Qtr TLD missing in field.BS a Gamma D-50, D-51, 07-19-06 Sediments were collected, but sampling D-107 frequency requirements were not met.AP Beta D-16 08-23-06 Filter lost in field.VE Gamma D-58 10-02-06 No broadleaf or forage sample received.VE Gamma D-96 10-02-06 No vegetation samples received.VE Gamma D-109 10-02-06 No broadleaf sample received.Constitutes a missed sample per the minimum requirements specified by the ODAM.21 Table 5.7 Radiological Environmental Program Summary.Name of Facility Location of Facility Duane Arnold Energy Center Linn, Iowa Docket No.Reporting Period 50-331 January-December, 2006 (County, State)Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDD Mean (F)c Mean (F)' Mean (F)c Routine (Units) Analyses' Rangec Location" Rangec Rangec Results 3 Airborne GB 414 0.004 0.029 (361/362)
+         Toddville 13          Alburnett (C) 15          On-site North 16          On-site South Ambient           1-2 (C),                            One dosimeter continuously   Read gamma radiation dose Radiation      8, 10                               at each location,            quarterly.
-D-3, Hiawatha 0.030 (52/52) 0.027 (52/52) 0 Particulates (0.006-0.097) 7 mi. SE (0.008-0.097)
+Dosimeters are changed at 3, 5-7,     Air Particulate         least quarterly.
-(0.010-0.053)(pCi/me) GS 31 Be-7 0.020 0.074 (27/27) D-3, Hiawatha 0.087 (4/4) 0.069 (4/4) 0 (0.046-0.094) 7 mi. SE (0.058-0.105)
+, 13,     Locations 15, 16 17-23,      < 0.5 mi. of Stack 28-32, 43-48       < 1.0 mi. of Stack 82-86, 91 33-42       -<3.0 mi. of Stack Surface Water    50           Plant Intake (C)        Once per month.              Tritium and gamma isotopic 51           Plant Discharge                                      analyses of each sample (by location).
-(0.047-0.092)
+          0.5 mi. downstream 107         Plant Sewage Dischange (C) Denotes control location. All other locations are indicators.
-Nb-95 0.0022 < LLD < LLD 0 Zr-95 0.0031 < LLD < LLD 0 Ru-103 0.0016 < LLD < LLD 0 Ru-106 0.0089 < LLD < LLD 0 Cs-134 0.0010 < LLD < LLD 0 Cs-137 0.0010 < LLD < LLD 0 Ce-141 0.0028 < LLD < LLD 0 Ce-144 0.0057 < LLD < LLD. 0 Airborne Iodine 1-131 414 0.030 < LLD < LLD 0 (pCi/ma)TLD, AP Locations Gamma 46 1.0 17.5 (36/36) D-8, Urbana 21.2 (4/4) 17.4 (10/10) 0 (mR/quarter)
-(12.7-21.8) 10 mi. NW (20.2-21.8)
-(13.3-22.4)
+Table 5.2 Sample collection and analysis program, (continued).
-TLD, within 0.5 mi. from Stack Gamma 72 1.0 19.1 (72/72) D-31, On-site 23.1 (4/4) None 0 (mR/quarter)
+Sampling Location Exposure Pathway and/or Sample               Description          Sampling and Collection         Type and Frequency Sample Type      Point                                           Frequency                   of Analysisa Ground Water          53    Treated Municipal           Grab sample at least     Gross beta and tritium activity (potable)             54     Inlet to Municipal         once per quarter         analysis on quarterly sample. If Water Treatment                                      gross beta is greater than ten System                                              times the yearly mean of control 55     On-site well                                        samples, perform gamma 57, 58     Wells off-site and                                   isotopic and Sr-89 and Sr-90 72 (C)      within 4 km of DAEC                                analyses.
-(12.5-25.5) 0.5 mi. NW (21.2-25.5)
+Ground Water D-111           On-site wells MW-01A (Monitoring                  B (SSE)
-TLD, within 1.0 mi. from Stack Gamma 24 1.0 19.9 (24/24) D-48, 22.1 (4/4) None 0 (mR/quarter)
+Wells)           D-1 12      On-site wells MW-02A B (ESE)
-(14.2-23.9) 1 mi. NW (20-23.9)TLD, within 3.0 mi. from Stack Gamma 40 1.0 17.3 (40/40) D-37, 21.5 (4/4) None 0 (mR/quarter)
+D-1 13      On-site wells MW-03A B (NW)
-(13.5-22.7) 3 mi. E (19.5-22.7)
+River          50          Plant Intake (C)               At least once every   Gamma isotopic analysis of each Sediment       51          Plant Discharge                six months,           sample.
-Precipitation (pCi/L) H-3 4 182 < LLD < LLD 0 GS 12 Mn-54 15.7 < LLD < LLD 0 Fe-59 26.2 < LLD < LLD 0 Co-58 12.2 < LLD < LLD 0 Co-60 16.9 < LLD < LLD 0 Zn-65 30.3 < LLD < LLD 0 Nb-95 19.2 < LLD < LLD 0 Zr-95 33.5 < LLD < LLD 0 1-131 35.7 < LLD < LLD 0 Cs-134 22.5 < LLD < LLD 0 Cs-137 16.5 < LLD < LLD 0 Ba-140 105.2 < LLD < LLD 0 La-140 25.6 < LLD < LLD 0 22 Table 5.7 Radiological Environmental Program Summary.Name of Facility Location of Facility Duane Arnold Energy Center Docket No.Reporting Period 50-331 January-December, 2006 Linn, Iowa (County, State)Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD" Mean (F)c Mean (F)' Mean (F)c Routine (Units) Analyses' Rangec Location' Rangec Rangec Resultse Milk (pCi/L) 1-131 36 0.5 < LLD < LLD 0 GS 36 K-40 100 1298 (18/18) D-108, Farm 1368 (18/18) 1368 (18118) 0 (1152-1439) 17.3 mi. SW (1139-1657)
+        Sewage Effluent Canal (on-site)
-(1139-1657)
+Vegetation     16, 57,     Farms that raise food          Annually at harvest   Gamma isotopic analysis of 58, 72,     crops                          time. One sample of   edible portions.
-Cs-134 5 < LLD < LLD 0 Cs-137 5 < LLD < LLD 0 Ba-140 60 < LLD < LLD 0 La-140 5 < LLD < LLD 0 Ground Water, GB 24 1.3 3.5 (13/20) D-58, Farm 4.4 (4/4) < LLD 0 potable (pCi/L) (1.4-5.7) 1 mi. WSW-SW (2.5-5.7)H-3 24 330 < LLD < LLD 0 Monitoring GB 12 1.3 3.2 (12/12) MW-2A, shallow 4.7 (2/2) None 0 wells (pCi/L) (1.4-6.0)
+, 96,                                    each: grain, green 109                                        leafy, and forage. At 1-131 analysis on broadleaf least one sample      vegetation.
-Onsite, 280m ESE (3.4-6.0)H-3 12 330 489 (2/12) MW-01A (shallow) 489 (2/2) None 0 (473-504)
+(C)                                    should be broadleaf vegetation.
-Onsite, 210m SSE (473-504)Broadleaf 1-131 3 0.060 < LLD < LLD 0 Vegetation (pCi/g wet) GS 3 K-40 0.5 6.75 (2/2) D-58, Farm 6.77(1/1) 6.29(1/1) 0 (6.73-6.77) 1 mi. WSW-SW Mn-54 0.030 < LLD < LLD 0 Co-58 0.043 < LLD < LLD 0 Co-60 0.057 < LLD < LLD 0 Nb-95 0.039 < LLD < LLD 0 Zr-95 0.110 < LLD < LLD 0 Ru-1 03 0.039 < LLD < LLD 0 Ru-106 0.28 < LLD < LLD 0 Cs-134 0.027 < LLD < LLD 0 Cs&#xfd;137 0.030 < LLD < LLD 0 Ce-141 0.074 < LLD < LLD 0 Ce-144 0.24 < LLD < LLD 0 23 Table 5.7 Radiological Environmental Program Summary.Name of Facility Location of Facility Duane Arnold Energy Center Docket No.Reporting Period 50-331 January-December, 2006 Linn, Iowa (County, State)Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDO Mean (F)C Mean (F)' Mean (F)c Routine (Units) Analysesa Range' Location' Rangec Rangec Results'Vegetation GS 11 (Grain) K-40 0.5 4.28 (9/9) D-16, On-site 8.03 (2/2) 2.89 (2/2) 0 (pCi/g wet) (1.97-13.63) 0.5 mi. SSE (2.42-13.63)
+Fish           49          Cedar River upstream           One sample per 6      Gamma isotopic analysis on of DAEC not                    months (once during   edible portions.
-(2.46-3.32)
+influenced by effluent        January through July (C)                            and once during August through 61          Downstream of DAEC             December).
-Mn-54 0.068 <.LLD < LLD 0 Co-58 0.072 < LLD < LLD 0 Co-60 0.072 < LLD < LLD 0 Nb-95 0.077 < LLD -< LLD 0 Zr-95 0.17 < LLD -< LLD 0 Ru-103 0.073 < LLD -< LLD 0 Ru-106 0.45 < LLD -< LLD 0 Cs-134 0.057 < LLD -< LLD 0 Cs-137 0.057 < LLD -< LLD 0 Ce-141 0.127 < LLD -< LLD 0 Ce-144 0.40 < LLD -< LLD 0 Soil Sr-90 2 0.016 < LLD -None 0 (pCi/g dry)GS 2 K-40 0.5 12.23 (2/2) D-16, On-site 14.63 (1/1) None 0 (9.83-14.63) 0.5 mi. SSE Mn-54 0.035 < LLD -None 0 Fe-59 0.050 < LLD -None 0 Co-58 0.038 < LLD -None 0 Co-60 0.025 < LLD -None 0 Zn-65 0.082 < LLD -None 0 Nb-95 0.034 < LLD -None 0 Zr-95 0.037 < LLD -None 0 Ru-103 0.034 < LLD -None 0 Ru-106 0.31 < LLD -None 0 Cs-134 0.049 < LLD -None 0 Cs-137 0.060 0.13(1/1)
+in influence of effluent Milkb          108 (C)     Control Farm                  At least once per two  During the grazing season:
-D-15, On-site 0.13 (1/1) None 0 0.5 mi. NW Ce-141 0.053 < LLD -None 0 Ce-144 0.23 < LLD -None 0 24 Table 5.7 Radiological Environmental Program Summary.Name of Facility Location of Facility Duane Arnold Energy Center Linn, Iowa Docket No. 50-331 Reporting Period January-December, 2006 (County, State)Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDO Mean (F)' Mean (F)' Mean (F)c Routine (Units) Analysesa Rangec Location' Rangec Rangec Results'Surface Water H-3 38 193 287 (1/26) D-107, Onsite 287 (1/12) < LLD 0 (pCi/L) Sewage Effluent GS 38 Mn-54 10 < LLD < LLD 0 Fe-59 30 < LLD < LLD 0 Co-58 10 < LLD < LLD 0 Co-60 10 < LLD < LLD 0 Zn-65 30 < LLD -< LLD 0 Nb-95 15 < LLD -< LLD 0 Zr-95 30 < LLD -< LLD 0 1-131 15 < LLD -< LLD 0 Cs-134 10 < LLD --< LLD 0 Cs-137 10 < LLD --< LLD 0 Ba-140 60 < LLD --< LLD 0 La-140 15 < LLD --< LLD 0 Sediments GS 6 (pCi/g dry) K-40 1.0 7.00(4/4)
+weeks during the       Gamma isotopic and iodine-131 grazing season.        analyses of each sample.
-D-50, 9.14 (2/2) 9.14(2/2) 0 (4.86-8.89)
+        Dairy Farm within 10          At least once per      Duringq the non-.qrazing season:
-Plant Intake (8.60-9.68)
+miles of Site                 month during the       Gamma isotopic and iodine-1 31 non-grazing season. analyses of each sample.
-(8.60-9.68)
+(C) denotes control location. All other locations are indicators.
-Mn-54 0.017 < LLD < LLD 0 Fe-59 0.038 < LLD < LLD 0 Co-58 0.019 < LLD < LLD 0 Co-60 0.019 < LLD < LLD 0 Zn-65 0.041 < LLD < LLD 0 Nb-95 0.027 < LLD < LLD 0 Zr-95 0.032 < LLD < LLD 0 Ru-103 0.024 < LLD < LLD 0 Ru-106 0.17 < LLD < LLD 0 Cs-1 34 0.025 < LLD < LLD 0 Cs-1 37 0.021 < LLD D-50, 0.033 (1/2) 0.033 (1/2) 0 Plant Intake Ce-141 0.045 < LLD < LLD 0 Ce-144 0.12 < LLD < LLD 0 25 Table 5.7 Radiological Environmental Program Summary.Name of Facility Location of Facility Duane Arnold Energy Center Linn, Iowa Docket No.Reporting Period 50-331 January-December, 2006 (County, State)Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDO Mean (F)c Mean (F)' Mean (F)c Routine (Units) Analyses' Rangec Location' Rangec Rangec Resultse Fish GS 8 (pCi/g wet) K-40 1.0 3.19 (4/4) D-49, 3.27(4/4) 3.27 (4/4) 0 (2.92-3.50)
-Upstream (2.93-3.45)
-(2.93-3.45)
+Table 5.2 Sample collection and analysis program, (continued).
-Mn-54 0.017 < LLD -< LLD 0 Fe-59 0.049 < LLD -< LLD 0 Co-58 0.019 < LLD -< LLD 0 Co-60 0.020 < LLD -< LLD 0 Zn-65 0.042 < LLD -< LLD 0 Nb-95 0.025 < LLD < LLD 0 Zr-95 0.048 < LLD < LLD 0 Ru-103 0.028 < LLD < LLD 0 Ru-106 0.16 < LLD < LLD 0 Cs-134 0.017 < LLD < LLD 0 Cs-137 0.024 < LLD < LLD 0 Ce-141 0.061 < LLD < LLD 0 Ce-144 0.15 < LLD < LLD 0 GB = Gross beta; GS = Gamma spectroscopy LLD = Nominal lower limit of detectionbased on 4.66 sigma counting error for the background sample.Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).d Locations are specified by: (1) Name and code (Table 5.3); and (2) distance, direction and sector relative to reactor site.e Non-routine results are those which exced ten times the control station value for the location.
+Sampling Location Exposure Pathway and/or Sample               Description            Sampling and Collection               Type and Frequency Sample Type        Point                                          Frequency                          of Analysis3 Precipitation                  On-site                       Monthly                    Gamma isotopic on all samples.
-If a control station value is not available, the result is considered non-routine if it exceeds ten times the preoperational value for the location.26 Figure 5.1 Radiological Environmental Monitoring Program Sampling Stations near the Duane Arnold Energy Center.4 N I 57 BARRICA L_r m I 32 I.31 I-I7 30 2 9 2j kDE I DE--- --17 -18 I, 19<20 107 _58 2000 feet See Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.
+Tritium on quarterly composites.
-Figure 5.2 Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles.CEDAR RIVER,.108 RAPIDS on.See Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.
+Meatc                          On-site                       Annually                   Gamma Isotopic Soil               15, 16      On-site                       Annually                   Gamma Isotopic and Sr-90.
+Gamma isotopic analysis and analysis for gamma-emitting nuclides refer to high resolution gamma ray spectrum analysis. Any radionuclide detected at a concentration greater than the lower limit of detection (LLD) should be reported quantitatively; conversely, any radionuclide concentration less than the LLD should not be reported.
+The grazing season is considered to be May I through September 30.
+C Meat was not collected in 2006; no animals slaughtered for home use.
+Table 5.3 Sampling locations, Duane Arnold Energy Center.
+Sampling Location Code              Type       Sampling   Location Description              Distance and Direction Point                                          from Site Stack D-1                 C             1     Cedar Rapids                       11 mi @ 135* SE D-2                 C            2      Marion                             11 mi @ 125' ESE D-3                              3      Hiawatha                            7 mi@ 130' SE D-5                               5     Palo                                3 mi @ 2000 SSW D-6                              6      Center Point                        7 mi @0'      N D-7                              7      Shellsburg                          6 mi @ 2550 W D-8                              8      Urbana                             10 mi @ 3450 NW D-10                            10      Atkins                              9 mi @ 2100 SSW D-11                            11      Toddville                           4 mi @ 90' E D-13                C           13      Alburnett                           9 mi @ 700 ENE D-15                            15      On-site, Northwest                0.5 mi @ 3050 NW D-1 6                           16      On-site, South                    0.5 mi @ 1900 SSE D-17                            17      On-site, N                        0.5 mi N D-1 8                           18      On-site, NNE                      0.5 mi NNE D-19                            19      On-site, NE                       0.5  mi NE D-20                            20      On-site, ENE                      0.5  mi ENE D-21                            21      On-site, ENE                      0.5  mi ENE D-22                            22      On-site, E                        0.5  mi E D-23                            23      On-site, ESE                      0.5 mi ESE D-28                            28      On-site, WSW                      0.5 mi WSW D-29                            29      On-site, W                        0.5 mi W D-30                            30      On-site, WNW                      0.5 mi WNW D-31                            31      On-site, NW                       0.5  mi NW D-32                            32      On-site, NNW                      0.5  mi NNW D-33                            33      3 miles N                         3.0  mi N D-34                            34      3 miles NNE                       3.0  mi NNE D-35                            35      3 miles NE                        3.0 mi NE D-36                            36      3 miles ENE                       3.0 mi ENE D-37                            37      3 miles E                         3.0 mi E D-38                            38      3 miles ESE                       3.0 mi ESE D-39                            39      3 miles SE                        3.0 mi SE D-40                           40       3 miles SSE                       3.0 mi SSE D-41                           41       3 miles S                         3.0 mi S D-42                           42       3 miles SSE                       3.0 mi SSE D-43                           43       1 mile SSw                        1.0 mi SSW D-44                           44       1 mile WSW                        1.0 mi WSW D-45                           45       1 mile W                          1.0 mi W D-46                           46       1 mile WNW                        1.0 mi WNW 17
+Table 5.3 Sampling locations, Duane Arnold Energy Center (continued).
+Sampling Location Code                  Type        Sampling      Location Description                     Distance and Direction Point                                                   from Site Stack D-47                                  47        1 mile WNW                                1.0 mi WNW D-48                                  48        1 mile NW                                 1.0 mi NW D-49                    C             49        Lewis Access, upstream of DAEC            4.0 mi NNW D-50                    C             50        Plant Intake D-51                                  51        Plant Discharge D-53                                  53       Treated Municipal Water D-54                                  54        Inlet, Municipal Water Treatment System D-55                                  55        On-site Well D-57                                  57        Farm (Off-site Well)                    1.0 mi WSW D-58                                  58        Farm (Off-site Well)                    0.5 mi WSW-SW D-61                                 61        0.5 mi downstream of plant discharge D-72                    C             72        Farm                                    2.0 mi SSW D-82                                 82        On-site, SE                              0.5 mi SE D-83                                 83        On-site, SSE                             0.5 mi SSE D-84                                 84        On-site, S                               0.5 mi S D-85                                 85        On-site, SSW                             0.5 mi SSW D-86                                 86        On-site, SW                              0.5 mi SW D-91                                 91        On-site, N                               0.5 mi N D-94                                 94        Farm                                     2.7 mi N D-96                                 96        Farm                                     8.0 mi SSW D-101                               101        Farm                                     4.0 mi E D-107                               107        Sewage Effluent Canal                    On-site D-108                   C           108        Farm                                     17.3 mi. SW D-109                               109        Farm                                     3.6 mi. SW D-111                               110        Monitoring wells, MW-01A, B              On-site, 210m SSE D-1 12                              111        Monitoring wells, MW-02A, B              On-site, 280m ESE D-113                               112        Monitoring wells, MW-03A, B              On-site, 190m NW "C" denotes control location. All other locations are indicators.
+Table 5.4 Type and Frequency of collection.
+Location             Location Type         Weekly           Monthly Quarterly Semiannually Annually D-1                          C            AP                          TLD D-2                          C            AP, Al                      TLD D-3                                       AP, Al                      TLD D-5                                       AP, Al                      TLD D-6                                       AP, Al                      TLD D-7                                       AP, Al                      TLD D-8                                       AP, Al                      TLD D-10                                      AP                          TLD D-11                                      AP, Al                      TLD D-13                         C            AP, Al                      TLD D-15                                      AP, Al                      TLD                  SO D-16                                      AP, Al                      TLD                  SO, G D-17 to D-23                                                          TLD D-28 to D-42                                                          TLD D-43 to D-48                                                          TLD D-49                         C                                                     F D-50                         C                                SW                  RS D-51                                                           SW                 RS D-53                                                                  WW D-54                                                                  WW D-55                                                                  WW D-57                                                                  WW                       G D-58                                                                  WW                       G D-61                                                          SWb                  F D-72                         C                                        WW                       G D-82 to D-86                                                          TLD D-91                                                                  TLD D-94                                                                                           G D-96                                                                                           G D-107                                                          SW                 RS D-108                        C                                 MI                              G D-109                                                          MI                              G On-site                                                         P                              ME D-1 11 to D-1 13 a                                                    WW "C" denotes control location. All other locations are indicators.
+a Locations added third quarter, 2006.
+b Location added in November, 2006.
+Table 5.5. Sample codes used in 5.4.
+Code                       Description AP                        Airborne Particulates Al                       Airborne Iodine TLD                        Thermoluminescent Dosimeter P                        Precipitation Ml                       Milk WW                         Well Water G                        Vegetation ME                        Meat SO                        Soil SW                         Surface Water F                        Fish BS                        River Sediment 20
+Table 5.6. Missed collections and analyses, Duane Arnold Energy Center.
+Sample                                              Collection Date Type            Analysis           Location(s)         or Period                         Comments M!          Gamma, 1-131           D-96            2006         No sample; herd sold.
+Ml          Gamma, 1-131          D-101            2006         No sample; goat sold.
+AP/I           Beta, 1-131          D-07          03-09-06       Electric off due to relocation.
+TLD         Ambient Gamma           D-1            1st Qtr       TLD missing in field.
+TLD         Ambient Gamma           D-2            2nd Qtr       TLD missing in field.
+BS a            Gamma            D-50, D-51,      07-19-06       Sediments were collected, but sampling D-107                         frequency requirements were not met.
+AP               Beta              D-16          08-23-06       Filter lost in field.
+VE             Gamma               D-58          10-02-06       No broadleaf or forage sample received.
+VE             Gamma               D-96          10-02-06       No vegetation samples received.
+VE             Gamma              D-109          10-02-06       No broadleaf sample received.
+Constitutes a missed sample per the minimum requirements specified by the ODAM.
+Table 5.7      Radiological Environmental Program Summary.
+Name of Facility               Duane Arnold Energy Center                     Docket No.       50-331 Location of Facility           Linn, Iowa                                     Reporting Period January-December, 2006 (County, State)
+Indicator             Location with Highest              Control     Number Sample             Type and                       Locations                Annual Mean                    Locations     Non-Type             Number of      LLDD            Mean (F)c                             Mean (F)'         Mean (F)c    Routine3 (Units)           Analyses'                       Rangec          Location"             Rangec            Rangec     Results Airborne         GB         414       0.004   0.029 (361/362)    D-3, Hiawatha         0.030 (52/52)    0.027 (52/52)      0 Particulates                                     (0.006-0.097)       7 mi. SE           (0.008-0.097)    (0.010-0.053)
+(pCi/me)        GS           31 Be-7                 0.020     0.074 (27/27)    D-3, Hiawatha          0.087 (4/4)       0.069 (4/4)      0 (0.046-0.094)       7 mi. SE           (0.058-0.105)    (0.047-0.092)
+Nb-95            0.0022            <  LLD                                                   < LLD         0 Zr-95            0.0031            <  LLD                                                   < LLD         0 Ru-103           0.0016            <  LLD                                                   < LLD         0 Ru-106           0.0089            <  LLD                                                   < LLD         0 Cs-134           0.0010            <  LLD                                                   < LLD         0 Cs-137           0.0010            <  LLD                                                   < LLD         0 Ce-141           0.0028            <  LLD                                                   < LLD         0 Ce-144           0.0057            <  LLD                                                   < LLD.        0 Airborne Iodine        1-131      414    0.030            < LLD                                                    < LLD         0 (pCi/ma)
+TLD, AP Locations        Gamma        46     1.0         17.5 (36/36)     D-8, Urbana            21.2 (4/4)      17.4 (10/10)     0 (mR/quarter)                                        (12.7-21.8)      10 mi. NW            (20.2-21.8)       (13.3-22.4)
+TLD, within 0.5 mi. from Stack Gamma           72     1.0         19.1 (72/72)     D-31, On-site          23.1 (4/4)          None         0 (mR/quarter)                                        (12.5-25.5)      0.5 mi. NW           (21.2-25.5)
+TLD, within 1.0 mi. from Stack Gamma           24     1.0         19.9 (24/24)         D-48,              22.1 (4/4)          None         0 (mR/quarter)                                        (14.2-23.9)       1 mi. NW             (20-23.9)
+TLD, within 3.0 mi. from Stack Gamma           40     1.0         17.3 (40/40)         D-37,              21.5 (4/4)          None         0 (mR/quarter)                                        (13.5-22.7)        3 mi. E            (19.5-22.7)
+Precipitation (pCi/L)        H-3           4    182             < LLD                                                    < LLD        0 GS           12 Mn-54              15.7            < LLD                                                    < LLD        0 Fe-59              26.2            < LLD                                                    < LLD        0 Co-58              12.2            < LLD                                                    < LLD        0 Co-60              16.9            < LLD                                                    < LLD        0 Zn-65              30.3            < LLD                                                    < LLD        0 Nb-95              19.2            < LLD                                                    < LLD        0 Zr-95              33.5            < LLD                                                    < LLD        0 1-131              35.7            < LLD                                                    < LLD        0 Cs-134             22.5            < LLD                                                    < LLD        0 Cs-137             16.5            < LLD                                                    < LLD        0 Ba-140            105.2            < LLD                                                    < LLD        0 La-140             25.6            < LLD                                                    < LLD        0 22
+Table 5.7     Radiological Environmental Program Summary.
+Name of Facility             Duane Arnold Energy Center                         Docket No.       50-331 Location of Facility         Linn, Iowa                                         Reporting Period January-December, 2006 (County, State)
+Indicator                 Location with Highest             Control      Number Sample              Type and                    Locations                      Annual Mean                  Locations      Non-Type              Number of     LLD"          Mean (F)c                                   Mean (F)'       Mean (F)c     Routine (Units)            Analyses'                     Rangec              Location'              Rangec          Rangec      Resultse Milk (pCi/L)         1-131        36   0.5             < LLD                                                      < LLD          0 GS            36 K-40               100        1298 (18/18)           D-108, Farm          1368 (18/18)    1368 (18118)       0 (1152-1439)            17.3 mi. SW          (1139-1657)      (1139-1657)
+Cs-134               5             < LLD                                                      < LLD          0 Cs-137               5             < LLD                                                      < LLD         0 Ba-140              60            < LLD                                                       < LLD         0 La-140               5            < LLD                                                       < LLD         0 Ground Water,         GB            24   1.3         3.5 (13/20)           D-58, Farm             4.4 (4/4)         < LLD         0 potable (pCi/L)                                      (1.4-5.7)         1 mi. WSW-SW             (2.5-5.7)
+H-3           24   330            < LLD                                                       < LLD         0 Monitoring            GB            12   1.3         3.2 (12/12)        MW-2A, shallow            4.7 (2/2)          None         0 wells (pCi/L)                                       (1.4-6.0)       Onsite, 280m ESE           (3.4-6.0)
+H-3           12   330         489 (2/12)        MW-01A (shallow)           489 (2/2)          None         0 (473-504)        Onsite, 210m SSE          (473-504)
+Broadleaf        1-131          3 0.060            < LLD                                                       < LLD         0 Vegetation (pCi/g wet)       GS             3 K-40               0.5          6.75 (2/2)           D-58, Farm            6.77(1/1)        6.29(1/1)       0 (6.73-6.77)        1 mi. WSW-SW Mn-54            0.030            < LLD                                                       < LLD         0 Co-58            0.043            < LLD                                                       < LLD         0 Co-60            0.057            < LLD                                                       < LLD         0 Nb-95            0.039            < LLD                                                       < LLD         0 Zr-95            0.110            < LLD                                                       < LLD         0 Ru-1 03          0.039            < LLD                                                       < LLD         0 Ru-106            0.28            < LLD                                                       < LLD         0 Cs-134           0.027            < LLD                                                       < LLD         0 Cs&#xfd;137           0.030            < LLD                                                       < LLD         0 Ce-141           0.074            < LLD                                                       < LLD         0 Ce-144            0.24            < LLD                                                       < LLD         0 23
+Table 5.7    Radiological Environmental Program Summary.
+Name of Facility             Duane Arnold Energy Center                     Docket No.       50-331 Location of Facility         Linn, Iowa                                     Reporting Period January-December, 2006 (County, State)
+Indicator              Location with Highest             Control      Number Sample            Type and                     Locations                  Annual Mean                  Locations      Non-Type            Number of      LLDO          Mean (F)C                               Mean (F)'       Mean (F)c     Routine (Units)          Analysesa                     Range'            Location'             Rangec          Rangec      Results' Vegetation       GS           11 (Grain)       K-40               0.5          4.28 (9/9)      D-16, On-site           8.03 (2/2)      2.89 (2/2)       0 (pCi/g wet)                                    (1.97-13.63)       0.5 mi. SSE          (2.42-13.63)     (2.46-3.32)
+Mn-54            0.068            <.LLD                                                   < LLD          0 Co-58            0.072            < LLD                                                   < LLD          0 Co-60            0.072            < LLD                                                   < LLD          0 Nb-95            0.077            < LLD                -                                  < LLD          0 Zr-95             0.17            < LLD                -                                  < LLD          0 Ru-103           0.073            < LLD               -                                   < LLD         0 Ru-106            0.45            < LLD               -                                   < LLD         0 Cs-134           0.057            < LLD                -                                  < LLD         0 Cs-137           0.057            < LLD               -                                   < LLD         0 Ce-141           0.127            < LLD               -                                   < LLD         0 Ce-144            0.40            < LLD               -                                   < LLD         0 Soil         Sr-90         2  0.016            < LLD                                     -             None          0 (pCi/g dry)
+GS            2 K-40               0.5         12.23 (2/2)      D-16, On-site         14.63 (1/1)         None          0 (9.83-14.63)       0.5 mi. SSE Mn-54            0.035            < LLD                                     -             None          0 Fe-59            0.050            < LLD                                     -             None          0 Co-58            0.038            < LLD                                     -             None          0 Co-60            0.025            < LLD                                     -             None          0 Zn-65            0.082            < LLD                                     -             None          0 Nb-95            0.034            < LLD                                     -             None          0 Zr-95            0.037            < LLD                                     -             None          0 Ru-103           0.034            < LLD                                     -             None          0 Ru-106            0.31           < LLD                                      -             None          0 Cs-134           0.049            < LLD                                     -             None          0 Cs-137           0.060         0.13(1/1)        D-15, On-site          0.13 (1/1)         None          0 0.5 mi. NW Ce-141           0.053           < LLD                                      -             None          0 Ce-144            0.23           < LLD                                      -             None          0 24
+Table 5.7    Radiological Environmental Program Summary.
+Name of Facility             Duane Arnold Energy Center                        Docket No.       50-331 Location of Facility         Linn, Iowa                                        Reporting Period January-December, 2006 (County, State)
+Indicator                 Location with Highest             Control      Number Sample            Type and                    Locations                      Annual Mean                  Locations      Non-Type            Number of      LLDO         Mean (F)'                                  Mean (F)'        Mean (F)c     Routine (Units)          Analysesa                     Rangec             Location'              Rangec           Rangec      Results' Surface Water      H-3          38    193         287 (1/26)         D-107, Onsite           287 (1/12)         < LLD          0 (pCi/L)                                                       Sewage Effluent GS           38 Mn-54               10           < LLD                                                       < LLD          0 Fe-59               30           < LLD                                                       < LLD          0 Co-58               10           < LLD                                                       < LLD          0 Co-60               10           < LLD                                                       < LLD          0 Zn-65               30           < LLD                    -                                  < LLD          0 Nb-95               15           < LLD                                         -             < LLD          0 Zr-95               30           < LLD                   -                                   < LLD          0 1-131               15           < LLD                                         -             < LLD          0 Cs-134              10           < LLD                   -                     -             < LLD         0 Cs-137              10           < LLD                   -                     -             < LLD         0 Ba-140             60            < LLD                   -                     -             < LLD          0 La-140              15           < LLD                    -                    -             < LLD         0 Sediments        GS            6 (pCi/g dry)     K-40               1.0         7.00(4/4)              D-50,               9.14 (2/2)       9.14(2/2)       0 (4.86-8.89)          Plant Intake          (8.60-9.68)      (8.60-9.68)
+Mn-54            0.017           < LLD                                                       < LLD         0 Fe-59            0.038           < LLD                                                       < LLD         0 Co-58            0.019           < LLD                                                       < LLD         0 Co-60            0.019           < LLD                                                       < LLD         0 Zn-65            0.041           < LLD                                                       < LLD         0 Nb-95            0.027           < LLD                                                       < LLD         0 Zr-95            0.032           < LLD                                                       < LLD         0 Ru-103           0.024           < LLD                                                       < LLD         0 Ru-106            0.17           < LLD                                                       < LLD         0 Cs-1 34          0.025           < LLD                                                       < LLD         0 Cs-1 37          0.021           < LLD                D-50,              0.033 (1/2)      0.033 (1/2)      0 Plant Intake Ce-141           0.045           < LLD                                                       < LLD         0 Ce-144            0.12           < LLD                                                       < LLD         0 25
+Table 5.7     Radiological Environmental Program Summary.
+Name of Facility               Duane Arnold Energy Center                          Docket No.            50-331 Location of Facility           Linn, Iowa                                          Reporting Period      January-December, 2006 (County, State)
+Indicator                Location with Highest                  Control      Number Sample             Type and                       Locations                    Annual Mean                        Locations      Non-Type              Number of      LLDO            Mean (F)c                                 Mean (F)'             Mean (F)c     Routine (Units)            Analyses'                        Rangec            Location'              Rangec                Rangec      Resultse Fish          GS             8 (pCi/g wet)      K-40                1.0            3.19 (4/4)            D-49,               3.27(4/4)             3.27 (4/4)       0 (2.92-3.50)          Upstream             (2.93-3.45)           (2.93-3.45)
+Mn-54             0.017              < LLD                                        -                  < LLD          0 Fe-59             0.049              < LLD                  -                                        < LLD          0 Co-58             0.019              < LLD                  -<                                         LLD          0 Co-60             0.020              < LLD                 -                                         < LLD          0 Zn-65             0.042              < LLD                 -                                         < LLD          0 Nb-95             0.025              < LLD                                                           < LLD          0 Zr-95             0.048              < LLD                                                           < LLD          0 Ru-103            0.028              < LLD                                                           < LLD          0 Ru-106             0.16              < LLD                                                           < LLD          0 Cs-134            0.017              < LLD                                                           < LLD         0 Cs-137            0.024              < LLD                                                           < LLD         0 Ce-141            0.061              < LLD                                                           < LLD         0 Ce-144             0.15              < LLD                                                           < LLD         0 GB = Gross beta; GS = Gamma spectroscopy LLD = Nominal lower limit of detectionbased on 4.66 sigma counting error for the background sample.
+Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
+d Locations are specified by: (1) Name and code (Table 5.3); and (2) distance, direction and sector relative to reactor site.
+e Non-routine results are those which exced ten times the control station value for the location. If a control station value is not available, the result is considered non-routine if it exceeds ten times the preoperational value for the location.
+Figure 5.1     Radiological Environmental Monitoring      Program Sampling Stations near the Duane Arnold Energy Center.
+                                              L_
+BARRICA kDE        I N                                              DE---     - -17         -
+I                        Ir    m 32                                         18 I.
+                                            I, I-                                       19<
+I7                                         20 107     _
+                 29 2j 58 2000 feet See Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.
+Figure 5.2  Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles.
+CEDAR RIVER,.
+RAPIDS         on.
+See Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.
 ==6.0 REFERENCES==
+CITED Arnold, J. R. and H. A. Al-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.
+Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275-276.
+Environmental, Inc., Midwest Laboratory. 2001 - 2005. Environmental Radiological Monitoring Program for the Duane Arnold Energy Center, Annual Report - Part II, Data Tabulations and Analyses, January - December, 2001 - 2004.
+.      Quality Assurance Program Manual, Rev. 1, 21 October 2003.
+.      Quality Control Procedures Manual, Rev. 1, 17 September 2005.
+.      Quality Control Program, Rev. 1, 21 August 2003.
+Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Chicago, Illinois, 369-382.
+Hazleton Environmental Sciences . 1982 - 1984. Environmental Radiation Monitoring for the Duane Arnold Energy Center, Annual Report - Part II, Data Tabulations and Analyses, January -
+December 1981 - 1983.
+Hohenemser, C. M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel.          1986.    "Chernobyl,"
+Chemtech, October 1986, pp. 596-605.
+National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-746.
+Teledyne Brown Engineering Environmental Services, Midwest Laboratory. 1984 - 2000. Environmental Radiological Monitoring Program for the Duane Arnold Energy Center, Annual Report - Part II, Data Tabulations and Analyses, January - December, 1983 - 1999.
+Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.
+Environmental, Inc.
+Midwest Laboratory
+* an Allegheny Technologies Co.
+Landwehr Road
+* Northbrook, IL60062-2310 ph. (847) 564-0700
+* fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE:    Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.
+January, 2006 through December, 2006
+Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory has participated.in interlaboratory comparison (crosscheck) programs since the formulation of it's qualitycontrol program in December 1971, These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.
+Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
+Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
+The results in Table A-2 list results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internallaboratory testing.
+Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.
+Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.
+Table A-5 list results of the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous 'years available upon request.
+The results in table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
+Attachment A lists acceptance criteria for "spiked" samples.
+Out-of-limit results are explained directly below the result.
+Al
+Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One standard deviation Analysis                                   Level                                        for single determination Gamma Emitters                             5 to 100 pCi/liter or kg                     5.0 pCi/liter
+                                             > 100 pCi/liter or kg                      5% of known value Strontium-89b                              5 to 50 pCi/liter or kg                      5.0 pCi/liter
+                                             > 50 pCi/liter or kg                       10% of known value*
+Strontium-90b                              2 to 30 pCi/liter or kg                      5.0 pCi/liter
+                                             > 30 pCi/liter or kg                       10% of known value Potassium-40 .                               0.1 g/liter or kg                          5% of known value Gross alpha                                < 20 pCi/liter                               5.0 pCi/liter
+                                           > 20 pCi/liter                               25% of known value Gross beta                                 5 100 pCi/liter                              5.0 pCi/liter
+                                           > 100 pCi/liter                              5% of known value Tritium                                    5 4,000 pCi/liter                              1lo = (pCi/liter) =
+0 933 169.85 x (known)
+                                           > 4,000 pCi/liter                            10% of known value Radium-226,-228                            > 0.1 pCi/liter                              15% of known value Plutonium                                  &#x17d; 0.1 pCi/liter, gram, or sample             10% of known value Iodine-1 31, ;                               55 pCi/liter                               6.0 pCi/liter Iodine-129b                              > 55 pCi/liter                               10% of known value Uranium-238,                               < 35 pCi/liter                               6.0 pCi/liter Nickel-63b                               > 35 pCi/liter                               15% of known value Technetium-99b Iron-55b                                   50 to 100 pCi/liter                          10 pCi/liter
+                                           > 100 pCi/liter                              10% of known value Othersb                                                                                 20% of known value From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
+b  Laboratory limit.
+A2
+TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource, Associates (ERA)'.
+Concentration (pCi/L)
+Lab Code       Date         Analysis         Laboratory            ERA             Control Resultb            Resultc           Limits           Acceptance STW-1 078      01/16/06    .Sr-89             49.9 +/- 3.5               50.2      41;5  -58.9            Pass STW-1078       01/16/06     Sr-90             31.5 +/- 1.5               30.7      22.0  - 39.4           Pass STW-1079       01/16/06     Ba-133            86.5 +/- 4.1               95.0      78.6  - 111.0          Pass STWN-1079      01/16/06     Co-60             96.3 +/- 4.1               95.3      86.6  - 104.0          Pass STW-1 079      01/16/06     Cs-134            22.6 +/- 3.0               23.1      14.4  -31.8           .Pass STW-1 079      01/16/06     Cs-1 37          109.0 +/- 5.9              111.0     101.0  - 121.0          Pass STW-1 079      01/16/06     Zn-65            198.0 +/- 11.2             192.0     159.0  -225.0           Pass STW-1 080      01/16/06     Gr. Alpha         10.8 +/- 1.4                 9.6       1.0 -18.3            Pass STW-1 080      01/16/06     Gr. Beta          56.9 +/- 1.9               61.9      44.6  -79.2            Pass STW-1 081      01/16/06     Ra-226             4.3 +/- 0.4                 4.6      3.4  -5.8             Pass STW-1 081      01/16/06     Ra-228             7.1 +/-1.8                  6.6      3.7  -9.5             Pass STW-1 081      01/16/06     Uranium           20.7 +/- 0.5               22.1      16.9  -27.3            Pass STW-1088      04/10/06      Sr-89             29.0 +/-1.8                32.4      23.7 -41,1             Pass 04/10/06      Sr-90              8.7 +/- 1.0                 9.0. 0.3 - 17.7 STW-1088                                                                                                Pass STW-1089      04/10/06      Ba-I 33           10.3 +/- 0.4               10.0       1.3 - 18.7            Pass STW-1 089     04/10/06      Co-60            114.0 +/- 2.8              113.0     103.0 - 123,0           Pass STW-1 089     04/10/06      Cs-1 34           41.9 +/- 1.4               43.4      34.7 -52.1             Pass STW-1 089     04/10/06      Cs-1 37         208.0  +/- 1.1              214.0     195.0 - 233.0           Pass STW-1 089     04/10/06      Zn-65            154.0 +/- 0.8              152.0     126.0 - 178.0           Pass STW-1 090     04/10/06      Gr. Alpha         13.4 +/- 1.1               21.3      12.1 - 30.5            Pass STW-1090      04/10/06      Gr. Beta          27.7 +/- 2.1               23.0      14.3 -31.7             Pass STW-1 091     04/10/06      1-131             22.0 +/- 0.3               19.1      13.9 -24.3             Pass STW-1092      04/10/06      H-3            7960,0  +/- 57,0            8130.0   6720.0 - 9540.0           Pass STW-1092      04/10/06      Ra-226             2.9 +/- 0.4                 3.0      2.2 -3.8              Pass STW-1092      04/10/06      Ra-228            20.9 +/- 1.2               19.1      10.8 - 27.4            Pass STW-1 092     04/10/06      Uranium           68.6 +/- 3.4               69.1      57.1 -81.1             Pass STW-1094      07/10/06      Sr-89             15.9 +/- 0.7               19.7      11.0  - 28.4           Pass STW-1094      07/10/06      Sr-90             24.3 +/- 0.4               25.9      17.2  - 34.6           Pass STW-1 095     07/10/06      Ba-1 33           94.9 +/- 8.9               88.1      72.9  - 103.0          Pass STW-1095      07/10/06      Co-60           104.0  +/- 1.8               99.7      91.0  - 108.0          Pass STW-1 095     07/10/06      Cs-134            48.7 +/- 1.3               54.1      45.4  - 62.8           Pass STW-1 095     07/10/06      Cs-137          236.0  +/- 310              238.0    217.0   - 259.0          Pass STW-1 095     07/10/06      Zn-65           126;0  +/- 8.0              121.0     100.0  - 142.0          Pass STW-1096      07/10/06      Gr. Alpha         10.9 +/- 1.0               10.0       1.3  - 18.6           Pass STW-1096      07/10/06      Gr. Beta           9.7 +/- 0.4                 8.9      0.2  -17.5            Pass STW-1 097     07/10/06      Ra-226            11.0 +/-0.5                10.7       7.9  - 13.5           Pass STW-1 097     07/10/06      Ra-228            12.2 +/- 0.8               10.7       6.1  - 15.3           Pass STW-1097      07/10/06      Uranium           43.4 +/- 0.1               40.3      33.3  - 47.3           Pass Al-1
-CITED Arnold, J. R. and H. A. Al-Salih.
+TABLE A-1. Interlabolratory Comparison Crosscheck program, Environmental Resource.Associates (ERA)a.
-. Beryllium-7 Produced by Cosmic
+Concentration (pCi/L)
+Lab Code           Date           Analysis               Laboratory              ERA                  Control Resultb              Resultc                Limits           Acceptance STW-1104           10/06/06       Sr-89
 c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).
-MAPEP results are presented as the known values and expected laboratory precision (1 sigma, I determination) and control limits as defined by the MAPEP.Included in the MAPEP as a false positive.f Difficulties with the analyses for transuranics isotopes in solid samples (Filters, Soil and vegetation), were attributed to incomplete dissolution of the samples. Soil samples were repeated, results of reanalyses:
+MAPEP results are presented as the known values and expected laboratory precision (1 sigma, I determination) and control limits as defined by the MAPEP.
-Pu-238, 53.1 +/- 5.3 bq/kg. Pu-239/240, 42.4 +/- 4.7 bq/kg, U-233/4, 33.3 +/-3.5 bq/kg. U-238, 35.5 +/- 3.6 bq/kg.The July vegetation sample was provided in two separate geometries, (100 ml. and 500 ml.). Results reported here used the 500 ml. standard size geometry.
+Included inthe MAPEP as a false positive.
-Results for the 100 ml. geometry showed approximately a 15% higher bias.A6-3 APPENDIX B DATA REPORTING CONVENTIONS B-1 Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.2.0. Single Measurements Each single measurement is reported as follows: x + s where: x = value of the measurement; s = 2ca counting uncertainty (corresponding to the 95% confidence level).In cases where the activity is less than the lower limit of detection L, it is reported as: < L, where L = the lower limit of detection based on 4.66a uncertainty for a background sample.3.0. Duplicate analyses 3.1 Individual results: For two analysis results; x 1 + s, and x 2 +/- s2 Reported result: x +s; where x= (1/2) (x 1 +x 2) ands= (1/2)s+s2 3.2. Individual results: < L 1 , <L 2  Reported result: < L, where L = lower of Li and L2 3.3. Individual results: x +/- s, < L Reported result: " x +/- s if x > L; <L otherwise.
+f Difficulties with the analyses for transuranics isotopes in solid samples (Filters, Soil and vegetation),
-.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations.
+were attributed to incomplete dissolution of the samples. Soil samples were repeated, results of reanalyses:
-The average x and standard deviation s of a set of n numbers x 1 , x 2 ..xn are defined as follows: x=j n x S= n-4.2 Values below the highest lower limit of detection are not included in the average.4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.4.5 In rounding off, the following rules are followed: 4.5.1. If the number following those to be retained is less than 5, the number is dropped, and the retained number s are kept unchanged.
+Pu-238, 53.1 +/- 5.3 bq/kg. Pu-239/240, 42.4 +/-4.7 bq/kg, U-233/4, 33.3 +/-3.5 bq/kg. U-238, 35.5 +/- 3.6 bq/kg.
-As an example, 11.443 is rounded off to 11.44.4.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45.B-2 APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-1 Table C-A. Maximum permissible concentrations of radioactivity in air and water above natural a background in unrestricted areas Air (pCi/m3) Water (pCi/L)-3 Gross alpha 1 x 10 Strontium-89 8,000 Gross beta 1 Strontium-90 500 b -1 Iodine-1 31 2.8 x 10 Cesium-1 37 1,000 Barium-140 8,000 lodine-131 1,000 C Potassium-40 4,000 Gross alpha 2 Gross beta 10 6 Tritium 1 x 10 a Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
+The July vegetation sample was provided in two separate geometries, (100 ml. and 500 ml.). Results reported here used the 500 ml. standard size geometry. Results for the 100 ml. geometry showed approximately a 15% higher bias.
-Concentrations may be averaged over a period not greater than one year.b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.c A natural radionuclide.
+A6-3
-C-2 APPENDIX D
+APPENDIX B DATA REPORTING CONVENTIONS B-1
+Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.
+.0. Single Measurements Each single measurement is reported as follows:                     x+s where:             x = value of the measurement; s = 2ca counting uncertainty (corresponding to the 95% confidence level).
+In cases where the activity is less than the lower limit of detection L, it is reported as: < L, where L = the lower limit of detection based on 4.66a uncertainty for a background sample.
+.0. Duplicate analyses 3.1     Individual results:  For two analysis results; x 1 + s, and  x2 +/- s2 Reported result:     x +s;    where x= (1/2) (x1 +x 2) ands= (1/2)s+s2 3.2. Individual results:        < L 1 , <L 2        Reported result: < L, where L = lower of Li and L2 3.3. Individual results:        x +/- s, < L          Reported result:  "    x +/- s if x > L; <L otherwise.
+.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x1, x2 . . xn are defined as follows:
+x=j n      x             S=            n-4.2 Values below the highest lower limit of detection are not included in the average.
+.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.
+.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
+.5 In rounding off, the following rules are followed:
+.5.1. If the number following those to be retained is less than 5, the number is dropped, and the retained number s are kept unchanged. As an example, 11.443 is rounded off to 11.44.
+.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45.
+B-2
+APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-1
+Table C-A.       Maximum permissible concentrations  a of radioactivity in air and water above natural background in unrestricted areas Air (pCi/m3)                                                        Water (pCi/L)
+                            -3 Gross alpha          1 x 10                                                    Strontium-89                 8,000 Gross beta           1                                                         Strontium-90                   500 b                 -1 Iodine-1 31         2.8 x 10                                                  Cesium-1 37                  1,000 Barium-140                   8,000 lodine-131                   1,000 C
+Potassium-40                 4,000 Gross alpha                      2 Gross beta                      10 6
+Tritium                    1 x 10 a
+Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
+b Concentrations may be averaged over a period not greater than one year.
+Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.
+c A natural radionuclide.
+C-2
+APPENDIX D
 ==SUMMARY==
-OF THE LAND USE CENSUS D-1 Appendix D Summary of the Land Use Census The Duane Arnold Energy Land Use Census for 2006 was completed during September of 2006. All milk animals, residences and gardens greater than 500 square feet were identified within three miles for each of the 16 meteorological sectors. If none were identified within the three mile range, additional surveys were performed out to a distance of five miles. The Cedar River was surveyed by boat on July 18th of 2006 for water use downstream of the DAEC to Cedar Rapids.There were 172 vegetable gardens identified during the performance of the 2006 Census. This number is less than the number of gardens found in the 2005 survey by 6. There were no changes to the nearest vegetable receptor in any of the sixteen direction sectors.The locations of the nearest resident for each sector remained the same and there were no changes in the milk animal locations within the 3 mile radius of the plant in the past year.16 new homes were built or were under construction within three miles of the DAEC, compared to 45 new homes identified in 2005 and 31 new homes in 2004.Most of the new houses built are located in the town of Palo (SSW).The Cedar River survey revealed no new withdrawals of river water compared to previous surveys. Irrigation of the strawberry farm in Palo and fishing remain the only food pathway uses of river water between the DAEC and Cedar Rapids.Pursuant to ESP4.4, no changes were observed offsite that could adversely affect the safe operation of the DAEC or that would warrant a UFSAR update such as new gas pipelines, toxic gas installations or airfield strips.D-2 APPENDIX E ANNUAL RADIATION DOSE ASSESSMENT E-1 Appendix E Annual Radiation Dose Assessment The annual offsite radiation dose to a MEMBER OF THE PUBLIC was determined by assessment of environmental dosimeter results and by calculations based on monitored effluent releases.Section A. Dose Contribution from Direct Radiation Direct radiation dose from the operation of the DAEC was reported by TLDs placed at locations in the surrounding environment as described in the Offsite Dose Assessment Manual (ODAM).1. Pre-operational and 2006 TLD results were compared using a paired difference test. No significant differences in the TLD populations were observed for the 0.5 mile and one mile TLD populations using a confidence level of 99%.2. As stated in Part 1 of this report, no plant effect was indicated by the TLDs when dose results were compared to the estimated average natural background for Middle America.Section B. Estimated Offsite Dose from Effluent Releases" The contribution of dose to a member of the public most likely to be exposed from liquid and gaseous effluent releases was calculated with the Meteorological Information and Dose Assessment System (MIDAS) computer program in accordance with ODAM. The calculation methods follow those prescribed by Reg. Guide 1.109.* Because there were no nuclides detected in the environment at or beyond the site boundary that were due to the operation of the DAEC, no comparison of calculated dose from gaseous or liquid releases and dose calculated from environmental contamination was performed.
+OF THE LAND USE CENSUS D-1
-* Following calculation of offsite doses, the appropriateness of REMP sampling station types and locations was reviewed.
-The current sampling scheme was determined to be more than adequate for the identified receptors." Results of the MIDAS dose calculations are displayed below.1. The maximally exposed organ due to liquid effluents was the liver of a child, with an estimated dose equivalent of 8.22E-06 mrem.2. The whole body dose equivalent to the maximally exposed individual due to liquid effluents was 8.22E-06 mrem.3. The maximum dose to air at the site boundary from noble gases released was 2.69E-03 mrad from gamma radiation at 455 meters South.E-2
+Appendix D Summary of the Land Use Census The Duane Arnold Energy Land Use Census for 2006 was completed during September of 2006. All milk animals, residences and gardens greater than 500 square feet were identified within three miles for each of the 16 meteorological sectors. If none were identified within the three mile range, additional surveys were performed out to a distance of five miles. The Cedar River was surveyed by boat on July 18th of 2006 for water use downstream of the DAEC to Cedar Rapids.
-: 4. The maximum dose to air at the site boundary from noble gases released was 9.07E-02 mrad beta radiation at 535 meters SSW.5. The whole body dose equivalent to the maximally exposed individual from noble gases was 1.36E-03 mrem, at 805 meters West.6. The skin dose equivalent to the maximally exposed individual from noble gases was 1.84E-03 mrem, at 805 meters West.7. The maximally exposed organ due to airborne iodines and particulates with half-lives greater than eight days was the skin of a child at 805 meters West, with an estimated dose equivalent of 6.68E-03 mrem.Conclusion:
+There were 172 vegetable gardens identified during the performance of the 2006 Census. This number is less than the number of gardens found in the 2005 survey by 6. There were no changes to the nearest vegetable receptor in any of the sixteen direction sectors.
-No measurable dose due to the operation of the DAEC was detected by environmental TLDs in 2006. The calculated doses are below the regulatory limits stated in Appendix I to 10 CFR 50 and in 40 CFR 190.Estimated Maximum Offsite Individual Doses for 2006 0 Group (meters) Equivalent 10 CFR 50, (mrem) Appendix I Limit Direct Radiation (as measured by None TLDs)Liquid Releases Whole Body Dose Child S 8.22E-06 mrem 3 mrem Organ Dose Liver- S 8.22E-06 mrem 10 mrem Noble Gas Gamma Air Dose 455 S 2.69E-03 mrad 10 mrad Beta Air Dose 535 SSW 9.07E-02 mrad 20 mrad Whole Body All 805 W 1.36E-03 mrem 5 mrem Skin All 805 W 1.84E-03 mrad 15 mrem Particulates
+The locations of the nearest resident for each sector remained the same and there were no changes in the milk animal locations within the 3 mile radius of the plant in the past year.
-& lodines Organ Dose Skin 805 W 6.68E-03 mrem 15 mrem*k There is no Appendix I limit for direct radiation.
+new homes were built or were under construction within three miles of the DAEC, compared to 45 new homes identified in 2005 and 31 new homes in 2004.
-It is listed here to demonstrate compliance with 40 CFR 190 limits of 25 mrem whole body and 75 mrem thyroid.E-3}}
+Most of the new houses built are located in the town of Palo (SSW).
+The Cedar River survey revealed no new withdrawals of river water compared to previous surveys. Irrigation of the strawberry farm in Palo and fishing remain the only food pathway uses of river water between the DAEC and Cedar Rapids.
+Pursuant to ESP4.4, no changes were observed offsite that could adversely affect the safe operation of the DAEC or that would warrant a UFSAR update such as new gas pipelines, toxic gas installations or airfield strips.
+D-2
+APPENDIX E ANNUAL RADIATION DOSE ASSESSMENT E-1
+Appendix E Annual Radiation Dose Assessment The annual offsite radiation dose to a MEMBER OF THE PUBLIC was determined by assessment of environmental dosimeter results and by calculations based on monitored effluent releases.
+Section A.               Dose Contribution from Direct Radiation Direct radiation dose from the operation of the DAEC was reported by TLDs placed at locations in the surrounding environment as described in the Offsite Dose Assessment Manual (ODAM).
+: 1. Pre-operational and 2006 TLD results were compared using a paired difference test. No significant differences in the TLD populations were observed for the 0.5 mile and one mile TLD populations using a confidence level of 99%.
+: 2. As stated in Part 1 of this report, no plant effect was indicated by the TLDs when dose results were compared to the estimated average natural background for Middle America.
+Section B.               Estimated Offsite Dose from Effluent Releases
+"    The contribution of dose to a member of the public most likely to be exposed from liquid and gaseous effluent releases was calculated with the Meteorological Information and Dose Assessment System (MIDAS) computer program in accordance with ODAM. The calculation methods follow those prescribed by Reg. Guide 1.109.
+* Because there were no nuclides detected in the environment at or beyond the site boundary that were due to the operation of the DAEC, no comparison of calculated dose from gaseous or liquid releases and dose calculated from environmental contamination was performed.
+* Following calculation of offsite doses, the appropriateness of REMP sampling station types and locations was reviewed. The current sampling scheme was determined to be more than adequate for the identified receptors.
+"    Results of the MIDAS dose calculations are displayed below.
+: 1. The maximally exposed organ due to liquid effluents was the liver of a child, with an estimated dose equivalent of 8.22E-06 mrem.
+: 2. The whole body dose equivalent to the maximally exposed individual due to liquid effluents was 8.22E-06 mrem.
+: 3. The maximum dose to air at the site boundary from noble gases released was 2.69E-03 mrad from gamma radiation at 455 meters South.
+E-2
+: 4. The maximum dose to air at the site boundary from noble gases released was 9.07E-02 mrad beta radiation at 535 meters SSW.
+: 5. The whole body dose equivalent to the maximally exposed individual from noble gases was 1.36E-03 mrem, at 805 meters West.
+: 6. The skin dose equivalent to the maximally exposed individual from noble gases was 1.84E-03 mrem, at 805 meters West.
+: 7. The maximally exposed organ due to airborne iodines and particulates with half-lives greater than eight days was the skin of a child at 805 meters West, with an estimated dose equivalent of 6.68E-03 mrem.
+== Conclusion:==
+No measurable dose due to the operation of the DAEC was detected by environmental TLDs in 2006. The calculated doses are below the regulatory limits stated in Appendix I to 10 CFR 50 and in 40 CFR 190.
+Estimated Maximum Offsite Individual Doses for 2006 0
+Group    (meters)                          Equivalent      10 CFR 50, (mrem)       Appendix I Limit Direct Radiation (as measured by                                                        None TLDs)
+Liquid Releases Whole Body Dose        Child                       S          8.22E-06 mrem          3 mrem Organ Dose             Liver-                      S          8.22E-06 mrem         10 mrem Noble Gas Gamma Air Dose                     455             S           2.69E-03 mrad        10 mrad Beta Air Dose                     535           SSW           9.07E-02 mrad        20 mrad Whole Body            All          805            W            1.36E-03 mrem         5 mrem Skin                  All          805            W            1.84E-03 mrad        15 mrem Particulates & lodines Organ Dose            Skin         805            W           6.68E-03 mrem         15 mrem
+*k There is no Appendix I limit for direct radiation. It is listed here to demonstrate compliance with 40 CFR 190 limits of 25 mrem whole body and 75 mrem thyroid.
+E-3}}

ML071290126: Difference between revisions

Revision as of 06:29, 23 November 2019

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1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

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Conclusion:

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