Text

Annual Radiological Environmental Operating Report
	ML041280263
Person / Time
Site:	Duane Arnold
Issue date:	04/30/2004
From:	Peifer M; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NG-04-0323
	Download: ML041280263 (61)
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Committed to Nuclear Excellence Duane Arnold Enerav Center Operated by Nuclear Management Company, LLC April 30, 2004 NG-04-0323 10 CFR 50.4 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket 50-331 License No. DPR-49 2003 Annual Radiological Environmental Operating Report Please find attached one (1) copy of the 2003 Annual Radiological Environmental Operating Report for the Duane Arnold Energy Center (DAEC). This report is transmitted in accordance with the DAEC Offsite Dose Assessment Manual (Section 6.4.2) and Technical Specifications (Section 5.6.2) reporting requirements.

\ Mark

- A. Peifer Site Vice President, Duane Arnold Energy Center Nuclear Management Company, LLC

Enclosure:

2003 Annual Radiological Environmental Operating Report cc: D. Beaulieu (NRC-NRR)(w/a)

J. Caldwell (Region 111) (w/a)

NRC Resident Office (wla)

K. Erickson (Linn Co. Health Dept.) (w/a)

Drs. J. Floyd/J. Hess (w/a)

Radiochemistry Supervisor (University of Iowa) (wla)

K. Larson (ANI) (wla)

W. Nestel (INPO) (w/a)

IRMS (w/a) 3277 DAEC Road Palo, Iowa 52324-9785 Telephone: 319.851.761 1

\ I

- 0 -

..... Environmental, Inc.

A Midwest Laboratotv

/ an Allegheny Techndogies Co.

700 Landwehr Rwd Northbrook, I L 60062-2310 ph. (847) 564-0700 f i x (847) 564-4517 DUANE ARNOLD ENERGY CENTER CEDAR RAPIDS, IOWA DOCKET NO.50-331 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1 to December 31,2003 Prepared and submitted by ENVIRONMENTAL,Inc.

Midwest Laboratory Project No. 8001 Approved :

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.

PREFACE...................................................................................................................... ii List of Tables ................................................................................................................. v List of Figures ............................................................................................................... vi 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 ..................................................................................... 6 4.0 RESULTS AND DISCUSSION ..................................................................................... 7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents .............................. 7 4.2 Program Findings ............................................................................................ 7 5.0 TABLES AND FIGURES ............................................................................................ 10

6.0 REFERENCES

CITED ............................................................................................... 27 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-I iii

TABLE OF CONTENTS (continued)

PART I I Data Tabulations and Analyses ...................................................................................... i iv

LIST OF TABLES No .

5.1 Characteristic Properties of Isotopes Quantified in Gamma-spectroscopic Analyses ........................................................................................................ 11 5.2 Sample Collection and Analysis Program .................................................................. 12 5.3 Sampling Locations. DAEC ........................................................................................ 15 5.4 Type and Frequency of Collections ............................................................................ 17 5.5 Sample Codes Used in Table 5.4 ............................................................................... 18 5.6 Missed Collections and Analyses ............................................................................... 19 5.7 Radiological Environmental Monitoring Program Summary ....................................... 20 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) . .

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 A-7 Environmental Measurements Laboratory Quality (EML) Assessment Program comparison results ....................................................................... A7-1

.AttachmentA: 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.

5.1 Radiological Environmental Monitoring Program Sampling Stations near the Duane Arnold Energy Center ......................................................................... 25 5.2 Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles ........................................................................................................ 26 vi

1.O 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, 2003. 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.

Duane Arnold Energy Center (DAEC) is located in Linn County, Iowa, on the Cedar River, owned by IES Utilities, Inc and operated by Nuclear Management Corporation. The Duane Arnold Energy Center is a 565.7 MW(e) boiling water reactor. 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 2003 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 due to the operation of the Duane Arnold Energy Center is indicated.

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3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.1 Proqram Desicln 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 t h e 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-I37 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud,l963).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 Pronram Desiqn and Data InterDretation (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 Proaram DescriDtion 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 twelve locations. Also, airborne iodine is collected by continuous pumping through charcoal filters at six of these locations. Nine of the twelve locations are indicators and three are controls (D-1, D-2, and 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 from six locations (D-2, D-5, D-7, D-8, D-11 and D-15) are analyzed weekly for iodine-131.

Ambient gamma radiation is monitored at twelve air sampling locations. In addition, gamma radiation is monitored at thirty-four special locations: eighteen in a circle within a 0.5 mi. radius of the DAEC stack; six in 22.5" sectors within 1 mi. of the DAEC stack; and ten in 22.5" sectors between 1 and 3 miles of the DAEC stack. Two 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 were collected monthly from four locations during the non-grazing season, October through April, and biweekly during the grazing season, May 1 through September 30. One location (D-108) is a control, the rest are indicators. All 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, 0-58, 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. Also, potable ground water is collected quarterly from a treated municipal water system (D-53),the inlet to the municipal water treatment system (0-54) and four additional ground water locations (D-55, D-57, D-58, and D-72). 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.

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Proqram Description (continued)

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 five river, pond and sewage effluent locations, one control (D-49) and four indicators (D-50, D-51, D-99, and 0-107). All monthly samples are analyzed for gamma-emitting isotopes. Tritium analyses are performed on quarterly composites from each location. In addition, samples from Location D-107 (plant sewage discharge) are analyzed for potassium (ICPanalysis).

The aquatic environment is also monitored by upstream and downstream (D-49 and D-61) semiannual collections of fish. River bottom sediment is also collected semiannually at the plant's intake and discharge (D-50 and D-51) and downstream of the sewage plant (D-107).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.

In no instance did missed analyses affect the minimum sampling requirements as specified in the ODAM.

(1) _Milk:

Milk was not available from location D-101, January through May, November and December of 2003. Goats were dry.

(2) Air particulates / Air Iodine:

No AP/AI sample was available at location D-15 for the week ending June 5, 2003. No power was available at the sampler site.

No AP/AI sample was available at location D-7 for the week ending June 19,2003. Power was not available at the sampler site.

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3.4 Laboratow 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 with HPGe detectors. Levels of iodine-131 in vegetation were determined by gamma spectroscopy. Concentrations of airborne iodine-131 in charcoal samples were also determined by gamma spectroscopy.

Tritium was determined 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 controllquality 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 lnterlaboratory Comparison (crosscheck) Programs. Results obtained in crosscheck programs are presented in Appendix A.

3.5 Proqram Modifications A new indicator location (D-109) was added to the environmental monitoring program in 2003.

Milk and vegetation samples were collected from the Beatty farm (3.6 mi. SW); first collection, January, 2003.

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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.

The tabulated results of all measurements are not included in this section, although references to these results will be made in the discussion. A complete tabulation of results for 2003 is contained in Part II of the Annual Report on the Radiological Environmental Monitoring Program for the Duane Arnold Energy Center.

4.1 AtmosDheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 2003.

4.2 Proqram Findinqs Results obtained show background levels of radioactivity in the environmental samples collected in 2003.

Airborne Particulates The average annual gross beta concentrations in airborne particulates were identical at both indicator and control locations (0.029 pCi/m3) and similar to levels observed from 1988 through 2002. The results are tabulated below.

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 Al-Salih, 1955), was detected in all samples.

All other gamma-emitting isotopes were below their respective LLD limits. No effect from plant operation is indicated.

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Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.07 pCi/m3 in all samples.

Ambient Radiation (TLDs)

At twelve air sampling locations, the TLD readings averaged 17.3 and 15.4 mWquarter for indicator and control locations, respectively. At locations within a half mile, one mile and three mile radius of the stack, measurements averaged 18.3 mWquarter, 19.6 mwquarter and 16.5 mWquarter, respectively. The average for all locations was 17.7 mWquarter. This is lower than the estimated average natural background radiation for Middle America, 19.5 mWquarter, 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 mradlquarter for Middle America. Cosmic radiation and cosmogenic radionuclides contribute 8.0 mrad/quarter for a total average of 19.5 mradlquarter.

No plant effect is indicated.

Precicitation Concentration of tritium in precipitation was below the LLD of 330 pCi/L in all samples. No gamma-emitting isotopes were detected. No plant effect is indicated.

Milk lodine-I31 results were below the detection limit of 1.O 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 2003 show no radiological effects of plant operation.

Ground Water The annual mean for gross beta activity measured 3.5 pCi/L, similar to levels observed from 1988 through 2002. The location with the highest mean (6.1 pCi/L) was D-58, a farm 1.0 mile distant from the plant. Tritium activity measured below the LLD of 330 pCi/L in all samples. No effect from plant operation is indicated.

Veqetation lodine-131 concentrations in broadleaf vegetation were below the LLD level of 0.24 pCVg wet weight in all samples.

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.

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Soil Strontium80 was not detected in soil samples above the LLD level of 0.028 pCi/g dry weight.

Cesium-137 activity averaged 0.14 pCi/g dry weight. Both strontium-90 and cesium-I 37 activities a r e similar to or less than levels observed from 1988 through 2002, these levels a r e generally attributable to deposition of fallout from previous decades.

Naturally-occurring potassium-40 averaged 10.75 pCi/g dry weight. No effect from the plant operation is indicated.

Surface Water Concentrations of tritium measured below the LLD level of 330 pCi/L in all samples. All gamma-emitting isotopes were below their respective LLDs.

Potassium40 w a s measured a t o n e location, D-107 (sewage effluent). T h e concentration ranged from 16.4 to 34.6 pCi/L and averaged 22.5 pCi/L.

No plant effect on surface water is indicated.

Fish All gamma-emitting isotopes, except naturally-occurring potassium-40, in edible portions were below detection limits. T h e potassium-40 level was similar a t both indicator and control locations (2.93 and 3.10 pCi/g wet, respectively). No plant effect on fish is indicated.

River Sediments River sediments were collected in May and September, 2003, and analyzed for gamma-emitting isotopes. Cs-137 w a s detected in samples from both the upstream and downstream locations at a concentration of 0.056 and 0.057 pCi/g dry weight, respectively. Potassium-40 activity ranged from 7.16 - 10.79 pCi/g dry weight and averaged 9.31 pCi/g dry weight.

All other gamma-emitting isotopes were below detection limits.

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5.0 TABLES AND FIGURES 10

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

Designation Comment Isotope Half-lifea I. Naturally Occurring A. Cos-mogenic Produced by interaction of cosmic Be-7 53.2 d rays with atmosphere B. Terrestrial Primordial K-40 1.26x1O9y II. Fission Productsb Nuclear detonations constitute the major environmental source A. Short-lived 1-131 8.04 d Ba-140 12.8d B. Other than Short-lived Nb-95 35.15 d Zr-95 65 d RU-103 39.35 d Ru-106 368.2 d cs-134 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 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 1 Cedar Rapids (C) Continuous operation of Analyze for gross beta activity Particulates 2 Marion (C) sampler with sample more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after filter 3 Hiawatha collection at least once per change. Perform gamma 5 Palo week or as required by dust isotopic analysis on each sample 6 Center Point loading having gross beta activity greater 7 Shellsburg than ten times the yearly mean 8 Urbana of the control samples.

10 Atkins 11 Toddville Composite weekly samples to 13 Alburnett (C) form a quarterly composite (by 15 On-site North location). Analyze quarterly 16 On-site South composite for gamma isotopic.

Airborne Iodine 2 Marion (C) Continuous operation of Analyze each cartridge for 5 Palo sampler with sample iodine-131.

7 Shellsburg collection at least once per 8 Urbana week.

11 Toddville 15 On-site North Ambient 1-2 (C) Air Particulate Two dosimeters Read gamma radiation dose Radiation 3.5-8 Locations continuously at each quarterly.

10,ll location. Both dosimeters 13 (C) are changed at least 15,16 quarterly.

17-23, I 0.5 mi. of Stack 28-32, 82-86, 91 43-48 2 1.O mi. of Stack 3342 5 3.0 mi. of Stack Surface Water 49 Lewis Access (C) Once per month. Gamma isotopic analyses of 50 Plant Intake (C) each sample (by location).

51 Plant Discharge 99 Pleasant Creek Composite monthly samples to 107 Plant Sewage form quarterly composite (by Dischange location). Analyze quarterly composite for tritium.

(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 andlor Sample Description Sampling and Collection Type and Frequency Sample Type Point Frequency of Analysis Ground 53 Treated Municipal Grab sample at least Gross beta and tritium activity Water Water once per quarter analysis on quarterly sample.

(potable) 54 Inlet to Municipal If gross beta is greater than Water Treatment ten times the yearly mean of System control samples, perform gamma isotopic and Sr-89 and 55 On-site well Sr-90 analyses.

57,58 Wells off-site and 72 within 4 km of DAEC 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 Downstream of DAEC August through 61 in influence of effluent December).

b Milk 108 (C) Control Farm At least once per two Durinq the qrazinq season:

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

96, 101 Dairy Farms within 10 At least once per Durinq the non-qrazinq season:

109 miles of Site month during the Gamma isotopic and iodine-I31 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 Analysis Precipitation On-site Monthly Gamma isotopic on all samples.

Tritium on quarterly composites.

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

a 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 1 through September 30.

Meat was not collected in 2003; 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 m i @ 135" SE D-2 C 2 Marion 11 mi@ 125" ESE D-3 3 Hiawatha 7 m i @ 130" SE 0-5 5 Palo 3 mi @ 200" SSW D-6 6 Center Point 7 m i @Oo N D-7 7 Shellsburg 6 mi @ 255" W D-8 8 Urbana 10mi@345" NW D-10 10 Atkins 9mi@210" SSW D-11 11 ToddviI Ie 4mi@90" E D-13 C 13 Alburnett 9mi@70" ENE D-15 15 On-site, Northwest 0.5 mi @ 305" NW D-16 16 On-site, South 0.5 mi @ 190" SSE D-17 17 On-site, N 0.5 mi N D-18 18 On-site, NNE 0.5 mi NNE D-19 19 On-site, NE 0.5 mi NE 0-20 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 0-36 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.O mi SSW D-44 44 1 mile WSW 1.O mi WSW D-45 45 1 mile W 1.0 mi W D-46 46 1 mile WNW 1.O mi WNW 15

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 0-49 C 49 Lewis Access, upstream of DAEC 4.0 mi NNW D-50 C 50 Plant Intake 0-5 1 51 Plant Discharge D-53 53 Treated Municipal Water 0-54 54 Inlet, Municipal Water Treatment System D-55 55 On-site Well D-57 57 Farm (Off-site Well) 1.O mi WSW 0-58 58 Farm (Off-site Well) 0.5 mi WSW-SW D-61 61 0.5 mi downstream of plant discharge D-72 72 Farm 2.0 mi SSW 0-82 82 On-site, SE 0.5 mi SE D-83 83 On-site, SSE 0.5 mi SSE 0-84 84 On-site, S 0.5 mi S 0-85 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-99 99 Pleasant Creek Lake 2.5 mi WNW D-I 01 101 Farm 4.0 mi E D-106 106 Farm 4.5 mi SE D-107 107 Sewage Effluent Canal On-site D-I08 C 108 Farm 17.3 mi. SW D-109 109 Farm 3.6 mi. SW "c"denotes control location. All other locations are indicators.

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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 TLD D-5 AP, Al TLD D-6 AP TLD D-7 AP, Al TLD D-8 AP, Al TLD D-10 AP TLD D-11 AP, Al TLD D-13 C AP TLD D-15 AP, A1 TLD so D-16 AP TLD SO, G D-17 to D-23 TLD 0-28 to D-42 TLD D-43 to D-48 TLD D-49 C sw 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 F D-63 M G D-72 ww G D-82 to D-86 TLD D-9I TLD D-94 G D-96 M D-99 sw D-101 M D-106 M G D-107 sw RS D-108 C M G D-109 M G On-site P ME "C" denotes control location. All other locations are indicators.

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Table 5.5. Sample codes used in 5.4.

Code Description AP Airborne Particulates Al Airborne Iodine TLD Thermoluminescent Dosimeter P Precipitation M Milk ww Well Water G Vegetation ME Meat so Soil sw Surface Water F Fish 0 BS River Sediment 18

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

Sample Collection Date Type Analysis Location(s) or Period Comments MI 1-131, Gamma D-101 01-02-03 Sample not available; goat dry.

MI 1-131, Gamma D-I01 02-04-03 Sample not available; goat dry.

MI 1-131, Gamma D-101 03-04-03 Sample not available; goat dry.

MI 1-131, Gamma D-101 04-01-03 Sample not available; goat dry.

MI 1-131, Gamma D-101 05-06-03 Sample not available; goat dry.

APIA1 Gross Beta, D-I5 06-05-03 No power to sampler.

1-131 APIA1 Gross Beta, D-07 06-19-03 No power to sampler, run-time 1-131 only 21.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

MI 1-131, Gamma D-101 11-14-03 Sample not available: goat dry.

MI 1-131, Gamma 0-101 12-02-03 Sample not available; goat dry.

In no instance did missed analyses affect minimum sampling requirements as specified in the ODAM.

19

Table 5.7 Radiological Environmental Program Summary.

Name of Facility Duane Amold Energy Center Docket No. 50-331 Location of Facility Linn, Iowa Reporting Period January-December, 2003 (County, State)

Indicator Location with Highest Control Jumbel Sample Type and . Locations Annu, Wean Locations Non-Type Number of LLD~ Mean (F)' Mean (F)' Mean (F)' toutine Analysesa (Units) Range' Locationa Rang& Range' -

tesults' Airborne GB 62; 0.002 0.029 (466/466) D-1, Cedar Rapids 0.029 (52/52) 0.029 (156/156) 0 Particulates (0.006-0.054) 11 mi. SE (0.01 8-0.045) (0.013-0.053)

(pCim*) GS 4t Be-7 0.020 0.069 (36136) 0-7, Shellsburg 0.078 (4/4) 0.071 (12/12) 0 (0.044-0.099) 6mi. W (0.050-0.097) (0.042-0.102)

Nb-95 1.0018 < LLD < LLD 0 Zr-95 1.0025 < LLD < LLD 0 Ru-103 1.0014 < LLD < LLD 0 RU-106 1.0099 < LLD < LLD 0 cs-134 1.0009 < LLD < LLD 0 cs-137 1.0058 < LLD < LLD 0 Ce-141 1.0025 < LLD < LLD 0 Ce-144 1.0054 < LLD < LLD 0 irbome Iodine 1-131 31( 0.030 < LLD < LLD 0

pCi/m")

TLD, AP Locations Gamma 4f 1.o 17.3 (36/36) D-8, Urbana 20.9 (4/4) 15.4 (12/12) 0 (mwquarter) (13.1-23.0) 10 mi. NW (17.9-23.0) (10.2-18.5)

TLD, within 0.5 mi. of Stack Gamma 7; 1.o 18.3 (72n2) D-31, On-site 22.6 (4/4) None 0 (mWquarter) (14.4-24.8) 0.5 mi. NW (20.2-24.8)

TLD, within 1.O mi. of Stack Gamma 2~ I.o 19.6 (24124) D-48, 22.1 (4/4) None 0 (mWquarter) (14.3-24.1) Imi. NW (20.6-24.1)

LD, within 3.0 mi. of Stack Gamma 4( 1.o 16.5 (40140) D-37, 21.1 (4/4) None 0 (mWquarter) (12.8-23.6) 3 mi.E (18.4-23.6)

Precipitation (PCiU H-3 1 330 < LLD < LLD 0 GS 1; Wn-54 7.3 < LLD < LLD 0 Fe-59 13.7 < LLD < LLD 0 358 5.2 < LLD < LLD 0 360 5.5 < LLD < LLD 0 Zn-65 14.6 LLD < LLD 0 Vb-95 10.1 < LLD < LLD 0 20

Table 5.7 Radiological EnvironmentalProgram Summary.

Name of Facility Duane Arnold Energy Center Docket No. 50-331 Location of Facility Linn, Iowa Reporting Period January-December, 2003 (County, State)

Indicator Location with Highest Control Jumber Sample Type anc Locations Annu Mean Locations Non-Type Number c LLD~ Mean (F)' Mean (F)' Mean (F)' ioutine (Units) Analyses Range' Location" Range' Range' tesultse Precipitation Zr-95 12.6 < LLD < LLD 0 (PCW 1-131 14.8 LLD < LLD 0 (continued) Cs-134 7.8 < LLD < LLD 0 cs-137 6.6 < LLD < LLD 0 Ba-140 44.6 < LLD < LLD 0 La-140 10.1 < LLD < LLD 0 Milk (pCilL) 1-131 1.o < LLD < LLD 0 GS K-40 100 1468 (47l47) D-101, Farm 1684 (11/11) 1406 (18118) 0 (11581982) 4 mi. E (1441-1982) (11281814) cs-134 15 < LLD < LLD 0 cs-137 18 < LLD < LLD 0 Ba-140 60 < LLD < LLD 0 La-140 15 < LLD < LLD 0

round Water GB 1.1 3.5 (17l24) D-58, Farm 6.1 (4l4) None 0 (pCilL) (1.2-7.0) 1 mi. WSW-SW (5.3-7.0)

H-3 330 < LLD < LLD 0 Broadleaf 1-131 0.24 < LLD < LLD 0 Vegetation (pCilg wet) GS K-40 0.5 11.90 (4l4) D-96, Farm 20.58 ( I l l ) 16.38 (in) 0 (4.13-20.58) 8 mi. SSW Mn-54 0.1 I < LLD < LLD 0 Co-58 0.082 < LLD < LLD 0 Co-60 0.14 < LLD < LLD 0 Nb-95 0.14 < LLD < LLD 0 zr-95 0.20 < LLD < LLD 0 Ru-I03 0.14 < LLD < LLD 0 Ru-I06 1.03 < LLD < LLD 0 cs-134 0.13 ' < LLD < LLD 0 c s - I 37 0.15 I < LLD < LLD 0 Ce-141 0.21 < LLD < LLD 0 Ce-144 0.73 < LLD < LLD 0 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, 2003 (County, state)

Indicator Location with Highest Control dumbel Locations Annu; Wean Locations Non-LLD~ Mean (F)' Mean (F)' Mean (F)' 3outine Range' Location' Range' Range' Zesults' 0.5 8.48 (11/11) D-109,Farm 17.10 (Z2) 11.53 (Z2) 0 (2.32-31.41) 3.6 mi. SW (2.79-31.41) (2.88-20.17) 0.027 < LLD < LLD 0 0.037 < LLD < LLD 0 0.024 < LLD c LLD 0 0.032 < LLD < LLD 0 0.044 < LLD < LLD 0 0.035 < LLD < LLD 0 0.34 < LLD < LLD 0 0.038 < LLD < LLD 0 0.030 < LLD < LLD 0 0.062 < LLD < LLD 0 0.19 < LLD < LLD 0 0.028 < LLD None 0 0.5 10.75 (Z2) D-15,On-site 12.96 (In) None 0 (8.54-12.96) 0.5 mi. NW 0.015 < LLD None 0 0.037 < LLD None 0 0.013 < LLD None 0 0.015 < LLD None 0 0.048 < LLD None 0 0.028 < LLD None 0 0.017 < LLD None 0 0.020 < LLD None 0 0.16 < LLD None 0 0.024 < LLD None 0 0.060 0.14 (Z2) D-15,On-site 0.14 (111) None . 0 (0.13-0.14) 0.5 mi. NW 0.049 < LLD None 0 0.15 < LLD None 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, 2003 (County, State)

Indicator Location with Highest Control GiG Locations Annu, Mean Locations Non-LLD~ Mean (F)' Mean (F)' Mean (F)' 7outine Range' Location" Range' Range' -

lesults' 330 < LLD < LLD 0 0.5 22.5 (12/12) D-107, Onsite 22.5 (12/12) None 0 (16.4-34.6) Sewage Effluent (16.4-34.6) 0 15 < LLD < LLD 0 15 < LLD < LLD 0 30 < LLD < LLD 0 15 < LLD < LLD 0 15 < LLD < LLD 0 30 < LLD < LLD 0 15 < LLD < LLD 0 30 < LLD < LLD 0 15 < LLD < LLD 0 15 < LLD < LLD 0 60 < LLD < LLD 0 15 < LLD < LLD 0 I.o 9.60 (4/4) D-107, Sewage 10.70 ( Z 2 ) 8.73 (Z2) 0 (7.16-10.79) Effluent Canal (10.60-10.79) (7.53-9.93) 0.026 < LLD < LLD 0 0.070 < LLD < LLD 0 0.043 < LLD < LLD 0 0.029 < LLD < LLD 0 0.077 < LLD < LLD 0 0.060 < LLD < LLD 0 0.072 < LLD < LLD 0 0.050 < LLD < LLD 0 0.24 < LLD < LLD 0 0.042 < LLD < LLD 0 0.045 0.057 (1/4) D-51, 0.057 ( I l l ) 0.056 ( l / l ) 0 Plant Discharge 0.095 < LLD < LLD 0 0.17 < LLD < LLD 0 23

Table 5.7 Radiological EnvironmentalProgram Summary.

Name of Facility Duane Arnold Energy Center Docket No. 50-331 Location of Facility Linn, Iowa Reporting Period January-December, 2003 (County, State)

Indicator Location with Highest Control GiiK Sample Type and Locations Annual Mean Locations Non-Type Number of LLD~ Mean (F)' Mean (F)' Mean (F)' ioutine (Units) Analysesa Range' Locationa Range' Range' -

tesults' Fish GS E (pCi/g wet) K-40 1.o 2.93 (4/4) D-49, Upstream 3.10 (414) 3.10 (414) 0 (2.70-3.1 5) 4 mi. NNW (2.70-3.40) (2.70-3.40)

Mn-54 0.049 c LLD c LLD 0 Fe-59 0.059 < LLD < LLD 0 co-58 0.045 c LLD < LLD 0 (20-60 0.045 C LLD c LLD 0 211-65 0.087 c LLD < LLD 0 Nb-95 0.083 < LLD < LLD 0 2-95 0.102 c LLD < LLD 0 Ru-103 0.064 C LLD c LLD 0 Ru-I06 0.36 C LLD c LLD 0 cs-134 0.055 c LLD C LLD 0 CS-137 0.048 c LLD c LLD 0 Ce-141 0.080 < LLD c LLD 0 Ce-144 0.28 c LLD c LLD 0 a GB = Gross beta; GS = Gamma spectroscopy LLD = Nom'inal lower limit of detectionbasedon 4.66 sigma counting error for the background sample.

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

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

'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 preoperationalvalue for the location.

' Required LLDs for 1-131. Cs-I34 and Cs-137 (~0.060, ~0.060and ~0.080pCi/g wet, respectively) could not be achieved for two samples, due to low sample weight (c2-5 grams wet).

24

25 Figure 5.2 Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 miles from the Duane Arnold Energy Center 108 Refer to Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.

26

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 and 276.

Environmental, Inc., Midwest Laboratory. 2001 - 2003. Environmental Radiological Monitoring Program for the Duane Arnold Energy Center, Annual Report - Part II, Data Tabulations and Analyses, January - December, 2001 - 2003.

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

2001. Quality Control Procedures Manual, Rev. 0, 21 September 2000.

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 11, 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.

27

' Mdw es t laboratory an Allegheny Techndoges Co.

7 W L a d v d r R o a l -NOLhbmckIL 4 W Q 2

@4847)Y)44700 fa(841)5544517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparisonstudies administered by EnvironmentalResources Associates, and serves as a replacementfor 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, 2003 through December, 2003

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

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

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

The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via International lntercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2. Results of internal laboratory testing is also listed.

Table A-3 lists results of the analyses on in-house 'spiked" samples for the past twelve months. All samples are prepared using NlST 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. 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.

The results in Table A-7 were obtained through participation in the Environmental Measurement Laboratory Quality Assessment Program.

Attachment A lists acceptance criteria for 'spiked" samples.

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

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 pCiAiter or kg 5.0 pCiAiter

> 100 pCiiliter or kg 5% of known value Strontium-8gb 5 to 50 pCiAiter or kg 5.0 pCiAiter

> 50 pCiiter or kg 10% of known value Strontium-90b 2 to 30 pCiiter or kg 5.0 pcffliter

> 30 pCi/liter or kg 10% of known value Potassium40 > 0.1 gAiter or kg 5% of known value Gross alpha 20 pCiAiter 5.0 pCiAiter

> 20 pCihiter 25% of known value Gross beta 100 pCiniter 5.0 pCiAiter

> 100 pCilliter . 5% of known value Tritium 4,000 pCi/liter 1s = (pCiffliter) =

0.0933 169.85 x (known)

> 4,000 pCiAiter 10% of known value Radium-226,-228 0.1 pCilliter 15% of known value Plutonium 0.1 pCilliter, gram, or sample 10% of known value lodine-131 55 pCiAiter 6.0 pCilliter lodine-12gb > 55 pCihiter 10% of known value Uranium-238, 35 pCi/liter 6.0 pCiAiter Nickel-63b > 35 pCihiter 15% of known value Technetium-9gb 1ron-55~ 50,to 100 pcihiter 10 pCiAiter

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

Laboratorylimit.

A2

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

Concentration (pCilL)

LabCode Date Analysis Laboratory ERA Control Resultb Result' Limits STW-973 02/17/03 Sr-89 17.0 f 0.5 15.9 f5.0 7.2 - 24.6 STW-973 02/17/03 Sr-90 8.9 f 0.3 9.0 f 5.0 0.4 - 17.7 STW-974 02117/03 Ba-133 14.5 f 0.9 19.5 f 5.0 10.8 - 28.2 SW-974 02/17/03 CO-60 37.5 f 0.9 37.4 f 5.0 28.7 - 46.1 STW-974 02/17/03 CS-134 18.2 f 0.6 17.8 f 5.0 9.1 - 26.5 STW-974 02/17/03 CS-137 42.7 f 1.0 44.2 f 5.0 35.5 - 52.9 SW-974 02/17/03 Zn-65 56.8 f 2.2 60.3 f 6.0 49.9 -70.7 STW-975 02/17/03 Gr. Alpha 18.4 f 0.3 37.6 f9.4 21.3 - 53.9 STW-975 02/17/03 Gr. Beta 11.7 f0.5 8.6 f 5.0 0.0 - 17.2 STW-976 02/17/03 Ra-226 4.1 50.1 4.7 *0.7 3.5 - 6.0 STW-976 02/17/03 Ra-228 7.6 f 0.5 6.5 f 1.6 3.7 - 9.3 STW-976 02/17/03 Uranium 52.9 f 1.9 53.7 f 5.4 44.4 - 63.0 STW-983 05119/03 H-3 1290.0 f 25.0 1250.0 f 331.O 678.0 - 1820.0 STW-984 05119/03 1-131 19.7 f 1.3 20.8 f 3.0 15.6 - 26.0 STW-985 05119/03 Gr. Alpha 54.4 f 3 . 0 70.3 f 17.6 39.9 - 101.0 STW-985 05119/03 Ra-226 14.9 f 0.2 16.5 f2.5 12.2 - 20.8 STW-985 05119/03 Ra-228 13.1 f0.6 10.3 f 2.6 5.8 - 14.8 STW-985 05119/03 Uranium 14.5 f 0.4 15.1 f 3 . 0 9.9 -20.3 STW-986 05119/03 CO-60 56.9 f 8.6 63.8 f 5.0 55.1 - 72.5 STW-986 05/19/03 cs-134 61.6 k 6.6 75.7 f 5.0 67.0 - 84.4 STW-986 05119/03 cs-137 143.0 f 1.2 150.0 f 7.5 137.0 - 163.0 STW-986 05119/03 Gr. Beta 309.0 f 2.7 363.0 f 54.5 269.0 - 457.0 STW-986 05119/03 Sr-89 33.1 f0.2 31.3 f 5.0 22.6 - 40.0 STW-986 05119/03 Sr-90 28.8 f 1.3 27.4 f 5.0 18.7 - 36.1 STW-988 08118/03 Ra-226 13.3 k 1.1 13.4 f 2.0 9.9 - 16.9 s~w-988 08118/03 Ra-228 11.5 f 1.0 12.5 f 3.1 7.1 - 17.9 STW-988 08118/03 Uranium 12.3 f 0.4 11.4 f3.0 6.2 - 16.6 STW-989 08118/03 Ba-133 18.1 k 1.9 20.7 f 5.0 12.0 - 29.4 STW-989 08118/03 Co-60 35.9 & 1.3 37.4 f 5.0 28.7 - 46.1 STW-989 oat18/03 cs-134 32.6 f 1.8 32.6 f5.0 23.9 - 41.3 STW-989 08118/03 cs-137 48.3 f 0.6 44.3 f 5.0 35.6 - 53.0 STW-989 08118/03 Zn-65 58.9 f 2.1 60.2 f 6.0 49.8 - 70.6 SM-990 08118/03 Gr. Alpha 41.8 f 3.4 56.2 f 16.3 36.9 - 93.3 STW-990 ' 08118103 Gr. Beta 51.3 f 3.0 31.6 f 5.0 22.9 - 40.3 STW-991 08118/03 Sr-89 57.2 f 4.3 58.8 f 5.0 50.1 -67.5 STW-991 08118/03 Sr-90 21.2 f 0.9 20.6 f 5.0 11.9 - 29.3 A1-1

TABLE A-I. InterlaboratoryComparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCiL)

LabCode Date Analysis Laboratory ERA Control Resultb Result' Limits STW-997 1iiia103 Gr. Alpha 37.0 f 2.0 29.5 f7.4 -

16.7 42.3 STW-997 Iill8/03 Gr. Beta 26.5 f 0.8 26.3 f5.0 -

17.6 35.0 STW-998 11118103 1-131

14.8 0.3 16.5 f 3.0 11.3 -21.7 STW-999 11/18/03 Ra-226 17.2 f 1.1

17.8 2.7 -

13.2 22.4 s ~ w - 9 9 9 1iiiai03 Ra-228 6.6 f 0.3 6.8 f 1.7 -

3.8 9.7 STW-999 11/18/03 Uranium 11.7 f 0.3 11.7 f 3 . 0 -

6.5 16.9 STW-1000 11/18/03 H-3 15900.0 f 174.0 14300.0 f 1430.0 -

11800.0 16800.0 STW-1001 11/18/03 Gr. Alpha 32.9 f 0.3 54.2 i 3 . 0 -

30.7 77.7 STW-1001i i i i a i 0 3 Ra-226 16.5 f0.9 16.1 f2.4 -

11.9 20.3 STW-1001 11/18/03 Ra-228 6.2 f 0 . 5 5.5 i I.4 -

3.1 7.9 STW-1001 ii/ia/o3 Uranium 9.7 f 1.5 9.3 f 13.6 -

4.1 14.5 STW-I002 Iiii8/03 Co-60 27.7 f 1.9 27.7 f5.0 -

19.0 36.4 STW-1002 iiiia103 c s - I34 21.5 f 1.1 23.4 f5.0 -

17.6 29.2 STW-1002 11/18/03 cs-137 66.3 f 2.8 64.2 f 5.0 -

55.5 72.9 STW-1002 1i/ia/o3 Gr. Beta 159.0 f 2.5 168.0 f 5.0 -

124.0 212.0 STW-1002 11118/03 sr-89 48.5 f0.4 50.4 k5.0 -

41.7 59.1 STW-I002 11/18/03 Sr-90 10.1 f3.0 10.2 f 25.2 1.5 - 18.9 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the environmentalsamples crosscheck program operated by Environmental Resources Associates (ERA).

Unless otherwise indicated, the laboratory result is given as the mean f standard deviation for three determinations.

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

' Recount of the original sample still low. The ERA blank was spiked in the lab; known value of 20.1 pCiL, measured 21.5 f 1.1 p C i L No explanationfor ERA test failure.

Lower bias observed for gamma spectroscopic analysis. The undiluted sample was reanalyzed; Results of reanalysis, Co-60: 62.3 pCR., Cs-134: 69.2 pCiR., Cs-137: 152.3 pCR.

'Reason for deviation unknown. A recount of the on'ginal planchets averaged 43.4 pCA.

Cs-137activity by gamma spectroscopy; 28.3 pCX. Result of reanalysis; 29.3 pCR.

A1-2

TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLDs).

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

2003-1 CaS04: Dy Cards 8/8/2003 Reader 1.120 4.69 4.74 f 0.54 3.28 - 6.10 2003-1 CaS04: Dy Cards 8/8/2003 Reader 1.150 3.00 3.02 f 0.20 2.10 - 3.90 2003-1 CaS04: Dy Cards 8/8/2003 Reader 1,180 2.08 1.89 f 0.45 1.46 - 2.70 2003-1 CaS04: Dy Cards 8/8/2003 Reader 1,180 2.08 2.11 f 0.22 1.46 - 2.70 2003-1 CaS04: Dy Cards 8/8/2003 Reader 1,30 75.00 84.40 f4.87 52.50 - 97.50 2003-1 CaS04: Dy Cards 8/8/2003 Reader I, 60 18.75 19.11 kl.86 13.13 - 24.38 2003-1 CaS04: Dy Cards 8/8/2003 Reader I, 60 18.75 22.82 f 5.41 13.13 - 24.38 2003-1 CaS04: Dy Cards 8/8/2003 Reader I, 90 8.33 9.05 f 1.I7 5.83 - 10.83 2003-1 CaS04: Dy Cards 8/8/2003 Reader 1,90 8.33 7.60 f 1.08 5.83 - 10.83 Environmental, Inc.

2003-2 CaS04: Dy Cards 1/12/2004 Reader I, 30 61.96 73.50 f 2.58 43.37 - 80.55 2003-2 CaS04: Dy Cards 1112/2004 Reader I, 60 15.49 19.70 f 0.51 10.84 - 20.14 2003-2 CaS04: Dy Cards 1/12/2004 Reader 1,60 15.49 16.93 f 1.37 10.84 - 20.14 2003-2 CaS04: Dy Cards II1Y2004 Reader 1,90 6.88 8.06 f 0.60 4.82 - 8.94 2003-2 CaS04: Dy Cards 1I1Y2004 Reader 1,90 6.88 6.64 f 0.58 4.82 - 8.94 2003-2 CaS04: Dy Cards Illa2004 Reader 1,120 3.87 4.39 f 0.17 2.71 -5.03 2003-2 CaS04: Dy Cards 1112/2004 Reader 1,150 2.48 2.34 f 0.18 1.74 - 3.22 2003-2 CaS04: Dy Cards 111a2004 Reader 1,150 2.48 2.51 i 0.16 1.74 - 3.22 2003-2 CaS04: Dy Cards Ill212004 Reader 1,180 1.72 2.01 i0.13 1.20 - 2.24

TABLE A-3. ln-House "Spike" Samples Concentration (pCilL)a Lab Code Sample Date Analysis Laboratory results Known Control Type' 2s, n=lb Activity . Limits' SPW-356 water 1/2/2003 Sr-90 34.04 f 1.57 30.93 24.74 - 37.12 W-10303 water 1/3/2003 Gr. Beta 63.24 f 1-20 63.90 -

53.90 73.90 W-11303 water 1/13/2003 Gr. Beta 59.75 f 1.10 63.90 -

53.90 73.90 W-I 2103 water 1121/2003 Gr. Beta 61.56 i 1.59 63.99 -

53.99 73.99 SPAP-446 Air Filter 113112003 Gr. Beta 1.49 f 0.02 1.52 -8.48 - 115 2 SPW-468 water 1131I2003 H-3 95982.00 f 865.00 -

89607.00 71685.60 107528.40 W-20703 water 2/7/2003 Fe-55 9095.00 f 114.00 -

10587.00 8469.60 12704.40 SPU-1347 Urine 3/1/2003 H-3 1724.00 f 412.00 -

1784.33 1101.27 2467.39 DW-30303 water 3/3/2003 Gr. Beta 65.44 f 0.59 63.90 53.90 - 73.90 SPCH-964 Charcoal 3/8/2003 1-131(G) 73.37 f 0.28 69.45 -

59.45 79.45 SPMI-1086 Milk 311312003 cs-137 57.18 f 8.03 49.50 -

39.50 59.50 SPMI-1086 Milk 311312003 1-131 75.13 f 12.01 67.60 -

54.08 81.12 SPMI-1086 Milk 311312003 I-l31(G) 65.81 f 1.06 67.56 -

57.56 77.56 SPW-1088 water 311312003 CO-60 27.16 f 4.79 28.20 18.20 - 38.20 SPW-1088 water 311312003 CS-137 51.74 f 9.15 49.50 -

39.50 59.50 SPW-1088 water 311312003 I-l31(G) 68.14 f 12.92 67.60 57.60 - 77.60 SPW-1088 water 311312003 1-131 76.94 f 1.13 67.56 -

54.05 81.07 SPVE-1110 Vegetation 3114f2003 1-131(G) 122.80 f 16.80 124.00 -

111.60 136.40 SPW1194 water 3/21/2003 CO-60 ' 31.09 f 6.28 28.15 18.15 - 38.15 SPW-I 194 water 3/21/2003 cs-137 55.11 i0.13 49.50 39.50 - 59.50 SPW-1194 water 312 1I2003 I-131(G) 66.17 f 9.15 67.60 57.60 - 77.60 W-32103 water 3/21/2003 (2-14 5201.OO f 16.60 -

4966.00 2979.60 6952.40 SPCH-1429 Charcoal 4/1/2003 1-131(G) 8.83 f 0.11 9.18 -0.82 - 19.18 W-40103 water 411I2003 Gr. Beta 67.74 f 0.52 63.39 -

53.39 73.39 SPF-1407 Fish 4/2/2003 cs-134 0.58 f 0.03 0.59 -

0.35 0.83 SPF-1407 Fish 4/2/2003 cs-137 1.29 f 0.06 1.32 0.79 - 1.85 SPAP-I409 Air Filter 4/2/2003 Gr. Beta 1.44 f 0.02 1.51 -

-8.49 115 1 SPU-41203 Urine 4112/2003 H-3 1798.50 f 409.30 -

1784.33 1101.27 2467.39 SPU-41703 Urine 411712003 H-3 1625.10 f401.30 -

1784.33 1101.27 2467.39 SPW-2022 water 4/25/2003 H-3 89007.00 f 798.00 -

88463.00 70770.40 106155.60 SPW-2053 water 4/28/2003 cs-137 45.70 f 9.44 49.35 39.35 - 59.35 SPW-2053 water 4/28/2003 Sr-90 47.51 f 1.87 44.47 35.58 - 53.36 SPMI-2055 Milk 412812003 CS-137 61.65 f 7.17 65.80 -

55.80 75.80 SPMI-2055 Milk 4/28/2003 Sr-90 38.45 f 1.59 44.74 -

35.79 53.69 W-50603 water 5/6/2003 Gr. Beta 70.95 f 0.53 63.39 -

53.39 73.39 W-60303 water 6/3/2003 Gr. Beta 63.00 f0.51 65.73 -

55.73 75.73 SPW-3960 water 711512003 H-3 88700.00 f 822.00 -

87369.00 69895.20 104842.80 SPMI-4019 Milk 711812003 cs-137 47.17 f 7.22 49.1 1 -

39.1 1 59.11 SPMI-4019 Milk 711812003 Sr-89 40.95 f 4.88 49.49 -

39.49 59.49 SPMl-4019 Milk 711812003 Sr-90 45.30 f 1.73 44.24 -

35.39 53.09 SPW-4023 water 711812003 CS-137 51.92 f 6.24 49.1 1 -

39.11 59.11 SPW-4023 water 711812003 Sr-89 42.49 f 10.23 49.49 -

39.49 59.49 SPW-4023 water 711812003 Sr-90 49.69 f 3.04 44.24 -

35.39 53.09 SPW-4518 water 8/8/2003 Fe-55 8176.00 f 107.00 -

9330.00 7464.00 11196.00 A3-1

TABLE A-3. In-House "Spike" Samples Concentration (pCiL)

Lab Code Sample Date Analysis Laboratory results Known Control Type . 2s, n=Ib Activity . Limits'.

SPW-6197 water I 011612003 TC-99 540.14 i54.00 539.73 377.81 - 701.65 SPAP-3958 Air Filter 1012812003 Gr. Beta 1.45 f 0.02 I.50 -8.50 - 11.50 SPW-6401 water 1012812003 H-3 84867.00 i 826.00 85984.00 68787.20 - 103180.80 SPAP-6403 Air Filter lOl28l2003 Gr. Beta 1.71 f 0.02 1.49 -8.51 - 11.49 SPF-6418 Fish 10l28l2003 cs-134 0.50 f 0.02 0.49 0.29 - 0.69 SPF-6418 Fish I012812003 c s - I37 1.37 f 0.05 1.30 0.78 - 1.82 SPW-6421 water 10128/2003 Fe-55 104.1 8 f 1.26 88.18 68.18 - 108.18 SPMI-7459 Milk 12/12/2003 c s - I 34 41.06 f 2.45 41.88 31.88 - 51.88 SPMI-7459 Milk 12lla2003 c s - I37 48.48 f4.99 48.64 38.64 - 58.64 SPMI-7459 Milk 12l1a2003 Sr-89 55.94 54.12 65.80 52.64 - 78.96 SPMI-7459 Milk 12/12/2003 Sr-90 41.86 f 1.57 43.80 35.04 - 52.56 SPW-7461 water 12/1a2003 CS-134 44.07 f 1.49 4 1.88 31.88 - 51.88 SPW-7461 water lZ1a2003 c s - I 37 50.26 f 2.67 48.64 38.64 - 58.64 SPW-7461 water 12/12/2003 Sr-89 56.41 f4.87 65.80 52.64 - 78.96 SPW-7461 water IZ1Z2003 Sr-90 48.44 f 1.84 43.80 35.04 - 52.56 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 (pCilL)a Lab Code Sample Date Analysis Laboratory results (4.66~) Acceptance Type LLD- Activity" Criteria (4.66 0 )

SPW-357 water 1/2/2003 Sr-90 0.50 0.12 f 0.25 1 W-10303 water 1/3/2003 Gr. Beta 0.12 0.022 f 0.10 3.2 W-11303 water 1I1312003 Gr. Beta 0.14 0.035 f 0.10 3.2 W-12103 water ll2112003 Gr. Beta 0.12 0.029 f 0.09 3.2 SPAP-447 Air Filter 1/31/2003 Gr. Beta 0.00 -0.0034 f 0.00 3.2 SPW-469 water 1/31/2003 H-3 160.20 19.3 f 80.30 200 W-20103 water 21112003 Gr. Beta 0.17 0.0 f 0.12 3.2 W-20703 water u712003 Fe-55 802.00 149 f 498.00 1000 DW-30303 3/3/2003 Gr. Beta 0.15 0.007 f 0.1 1 3.2 SPCH-965 Charcoal Cani: 31812003 1-131(G) 0.01 9.6 SPMI-1087 Milk 311312003 cs-134 7.49 10 SPMI-1087 Milk 311312003 cs-137 7.90 10 SPMI-1087 Milk 311312003 1-131 0.33 -0.013 f 0.18 0.5 SPMI-1087 Milk 311312003 1-131(G) 7.76 20 SPW-1089 water 311312003 CO-60 4.48 10 SPW-1089 water 311312003 CS-134 5.60 10 SPW-1089 water 311312003 CS-137 4.32 10 SPW-1089 water 311312003 1-131 0.29 -0.050 f 0.16 0.5 SPVE-1111 Vegetation 311412003 I-l31(G) 7.53 20 W-32103 water 312112003 C-14 17.50 -0.4 f 9.200 200 SPCH-1430 Charcoal Cani: 41112003 I-l31(G) 0.01 9.6 W-40103 water 4/1/2003 Gr. Beta 0.14 -0.1 1 f 0.100 3.2 SPF-1408 Fish 4/2/2003 cs-134 0.01 100 SPF-1408 Fish 4/2/2003 CS-137 0.01 100 SPAP-1410 Air Filter 4/2/2003 Gr. Beta 0.00 -0.0029 f 0.002 3.2 SPU-41203 Urine 411212003 H-3 653.99 542.28 f 364.780 200 SPU-41703 Urine 4117i2003 H-3 648.35 100.1 f 344.800 200 SPW-2054 water 412812003 cs-137 3.16 10 SPW-2054 water 412812003 Sr-89 0.55 0.45 f 0.50 5 SPW-2054 water 412812003 Sr-90 0.55 0.072 f 0.260 1 SPMI-2056 Milk 412812003 Sr-90 0.77 0.66 f 0.430 1 SPMI-2056 Milk 412812003 CS-137 2.74 10 SPMI-2056 Milk 412812003 I-l31(G) 3.54 20 W-50603 water 5/6/2003 Gr. Beta 0.12 0 *0.090 3.2 W-60303 water 61312003 Gr. Beta 0.14 -0.035 f 0.095 3.2 SPW-3960 water 711512003 H-3 156.60 53.4 f 80.200 200 SPMI-4018 Milk 711812003 CS-137 4.10 10 SPMI-4018 Milk 711812003 Sr-89 0.73 0.39 f 0.880 5 SPMI-4018 Milk 711812003 Sr-90 0.51 0.93 f0.340 1 SPW-4024 water 711812003 Sr-89 0.83 0.21 fO.730 5 SPW-4024 water 711812003 Sr-90 0.62 0.09 f 0.300 1 SPW-4519 water 81812003 Fe-55 527.00 87 f 369.000 1000 SPW-6401 water i012ai2003 H-3 163.80 -23.8 f 85.000 200 A4-1

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysis Laboratory results (4.660) Acceptance Type LLD Activig Criteria (4.66 a)

SPAP-6404 Air Filter 10128/2003 Gr. Beta 0.87 -0.99 *0.440 3.2 SPF-6419 Fish 10128/2003 C S -I 34 0.01 100 SPF-6419 Fish 10128/2003 CS-I37 0.01 100 SPMI-7460 Milk la1a2003 CS-134 4.52 I0 SPMI-7460 Milk la1Z2003 CS-I37 5.77 10 SPMI-7460' Milk la1a2003 Sr-90 0.50 1.26 f 0.370 I a Llquld sample results are reported in pCiRiter, air filters( pCilter), charcoal (pCicharcoa1canister), and solid samples @ C i g ) .

The activity reported Is the net activity result

' Low levels of Sr-90 are still detected in the environment A concentration of (1-5 pCR) in milk is not unusual.

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration ( P C ~ ~ L ) ~

Averaged Lab Code Date Analysis First Result Second Result Result MI-24,25 1/2/2003 K-40 1362.00 f 117.00

1377.00 188.00 1369.50 f 110.72 MI-24,25 1/2/2003 Sr-90 1.45 f 0.40 2.21 fO.50 1.83 f 0.32 CF-47.48 1/2/2003 Gr. Beta

2.72 0.10 2.84 f 0.10 2.78 fO.07 CF-47,48 1/2/2003 K-40 2.61 f0.31 2.32 f 0.12 2.47 f 0.17 AP-8827.8828 1/2/2003 Be-7 0.06 f 0.01 0.05 f 0.02 0.05 f 0.01 AP-8869,8870 1/2/2003 Be-7 0.04 f 0.02 0.05 f 0.02 0.05 f 0.01 MI-119,120 1/8/2003 K-40 1351.90 f 116.10 1234.70 f 108.70 1293.30 f 79.52 MI-l19,120 1/8/2003 Sr-90 2.22 f 0.43 1.88 f 0.40 2.05 f 0.30 MI-213.214 111412003 K-40 1372.30 f 104.80 1303.80 f 109.10 1338.05 f 75.64 MI-213,214 111412003 Sr-90 1.81 f 0.41 2.29 f 0.45 2.05 f 0.31 Ml-262,263 ill 512003 K-40 1399.20 f 200.70 1347.70 f 126.40 1373.45 f 118.59 S-696,697 1/29/2003 Gr. Alpha 24.70 f4.89 23.23 f 4.64 23.97 f 3.37 S-696,697 1/29/2003 Gr. Beta 22.89 f 2.67 22.71 f2.73 22.80 f 1.91 MI-448,449 2/3/2003 K-40 1159.70 f 157.90 1396.40 f 106.20 1278.05 f 95.15 SW-470,471 2/3/2003 Gr. Beta 13.62 f 1.23 15.21 f 1.21 14.42 f 0.86 SW-470,471 2/3/2003 K-40 (ICP) 5.10 f 0.51 5.20 f 0.52 5.15 f 0.36 SW-470,471 2/3/2003 K-40 5.80 f 0.51 5.90 f 0.52 5.85 f 0.36 MI-517,518 2/4/2003 K-40 1437.70 f 125.50 1357.70 f 188.00 1397.70 f 113.02 MI-541,542 2/5/2003 K-40 1443.00 f 194.80 1385.20 f 190.10 1414.10 f 136.09 MI-620.621 2/11/2003 K-40 1294.70 f 115.10 1234.10 f 165.10 1264.40 f 100.63 DW-922,923 3/4/2003 1-131 0.67 f 0.16 0.79 f 0.16 0.73 f 0.1 1 CF-1048,1049 b 311012003 K-40 3.09 f 0.12 2.67 f 0.07 2.88 f 0.07 LW-1152.1153 3/13/2003 H-3 1147.26 f 122.56 1094.42 f 120.92 1120.84 f 86.09 ,

F-1120,1121 3/14/2003 CS-137 0.04 f 0.02 0.05 f 0.01 0.05 f 0.01 F-1120, 1121 3/14/2003 Gr. Beta 2.04 f 0.06 2.11 f0.06 2.08 fO.04 F-1120,1121 3/14/2003 K-40 1.93 f 0.38 1.89 f 0.25 1.91 f 0.23 DW-1278,1279 3/25/2003 1-131 0.37 f 0.22 0.34 f 0.29 0.36 f 0.18 SO-1380,1381 3/25/2003 Gr. Beta 18.60 f 2.68 20.53 f 2.83 19.57 f 1.95 LW-1299,1300 3/27/2003 Gr. Beta 2.35 f 0.55 2.48 f 0.56 2.42 f 0.39 LW-1320,1321 3/27/2003 H-3 487.12 f 104.43 422.00 f 102.00 454.56 f 72.99 W-1403,1404 3/31/2003 Sr-90 0.96 f 0.32 1.10 f0-42 1.03 f 0.26 AP-2019,2020 3/31/2003 Be-7 0.07 f 0.01 0.08 f 0.01 0.07 f 0.01 MI-1422,1423 4/1/2003 K-40 1410.00 f 176.00 1340.00 f 114.00 1375.00 f 104.85 MI-2170,2171 4/1/2003 K-40 1452.30 f 129.10 1472.50 f 191.00 1462.40 f 115.27 Ml-1422,1423 4/2/2003 Sr-90 1.84 f 0.42 1.15 f 0.39 1.50 f 0.29 AP-1633.1634 4/2/2003 Be-7 0.05 f 0.01 0.06 f 0.01 0.06 f 0.01 AP-1871,1872 4/2/2003 Be-7 . 0.07 f 0.01 0.07 f 0.01 0.07 f 0.01 AP-1974,1975 4/2/2003 Be-7 0.08 f 0.02 0.07 f 0.02 0.08 f0.01 LW-1828.1829 411 112003 Gr. Beta 2.49 f 0.58 3.42 f 0.63 2.96 f 0.43 S-1544,1545 411512003 K-40 15.84 f 2.36 15.41 f 2.02 15.63 f 1.55 DW-1913,1914 4/15/2003 1-131 0.29 f 0.21 0.42 f 0.19 0.36 f 0.14 MI-1996,1997 4/21/2003 Sr-90 2.05 f 0.74 3.25 f 0.91 2.65 f 0.58 MI-1996, 1997 4/22/2003 K-40 1580.20 f 118.90 1602.10 f 120.40 1591.15 f 84.61 A5-1

TABLE A-5. In-House Duplicate Samples Concentration ( P C ~ L ) ~

Averaged Lab Code Date Analysis First Result Second Result Result LW-2063,2064 4/28/2003 Gr. Beta 2.33 f 0.66 2.68 f 0.60 2.51 fO.45 SWU-2275,2276 4/28/2003 Gr. Beta 3.62 f 0.67 4.60 f 0.71 4.1 1 f 0.49 G-2149,2150 4/30/2003 Be-7 0.71 f0.19 0.69 f 0.20 0.70 f0.14 TD-2339,2340 51112003 H-3 221.oo f 91.oo 161.OO f 88.00 191.00 f 63.29 SO-2381, 2382 5/1/2003 cs-137 0.1 1 f 0.03 0.10 f 0.02 0.10 f 0.02 SO-2381.2382 511l2003 Gr. Alpha 11.14 f5.15 10.39 f5.60 10.77 f 3.80 S0-2381,2382 51112003 Gr. Beta 35.18 f 4.69 39.66 f 5.24 37.42 f 3.52 SO-2381,2382 5/1/2003 K-40 18.29 f 0.84 17.83 f 0.84 18.06 f 0.59 SO-2381,2382 5/1/2003 Sr-90 0.06 f 0.02 0.10 f 0.02 0.08 50.01 DW-2317,2318 5/6/2003 1-131 1.77 f 0.27 1.47 f 0.26. 1.62 f0.19 882595,2596 51612003 CS-137 0.06 f 0.02 0.06 f 0.02 0.06 f 0.02 BS-2595,2596 5/6/2003 K-40 13.74 f 0.62 14.10 f 0.73 13.92 f 0.48 U-2484,2485 5/9/2003 H-3 512.00 f 100.00 370.00 f 95.00 441.OO f 68.97 SO-2645,2646 511412003 Be-7 1.18 f 0.42 1.21 f 0.35 1.19 f 0.27 SO-2645,2646 511412003 CS-137 0.11 f 0.04 0.09 f 0.05 0.10 f 0.03 SO-2645,2646 511412003 K-40 16.50 f 1.13 15.33 f 1.09 15.91 f 0.79 Ml-2696,2697 511912003 K-40 1320.40 f 124.50 1394.10 f 113.00 +

1357.25 84.07 Ml-2696,2697 511912003 Sr-90 1.49 f 0.47 2.01 50.45 1.75 f 0.32 SO-2787,2788 5/2812003 CS-137 0.27 f 0.04 0.23 f 0.04 0.25 f 0.03 SO-2787,2788 5/28/2003 Gr. Beta -19.62 f 1.73 20.81 f 1.72 20.21 f 1.22 SO-2787,2788 5/28/2003 K-40 14.77 f 1.02 14.41 f1.00 14.59 f 0.71 MI-2840,2841 5/28/2003 K-40 1179.50 f 167.80 1401.70 f 120.20 1290.60 f 103.20 SWU-2864,2865 5/28/2003 Gr. Beta 3.39 & 0.59 3.41 f0.64 3.40 f 0.43 BS-2888,2889 5/29/2003 CS-137 0.05 f 0.02 0.07 f 0.04 0.06 fO.02 BS-2888,2889 5/29/2003 K-40 9.70 f 0.83 10.17 f 0.87 9.93 f 0.60 W-3230,3231 513012003 Gr. Beta 4.33 f 1.00 3.28 f 1.22 3.81 fO.79 TD-3036,3037 6/2/2003 H-3 529.50 f 100.00 585.50 f 102.00 557.50 -+ 71.42 SL-2909,2910 b 6/3/2003 Gr. Beta 7.10 f 0.15 7.60 f 0.16 7.35 f 0.1 1 SL-2909,2910 61312003 K-40 3.90 f 0.67 3.49 f 0.52 3.70 f 0.42 SW-3080,3081 611Ol2003 Gr. Alpha 4.63 f 1.90 4.47 f 1.71 4.55 f 1.28 SW-3080,3081 6/1012003 Gr. Beta 9.07 f 1.29 8.98 f 1.28 9.02 f 0.91 VE-3172,3173 611112003 K-40 2.62 f 0.35 3.17 f 0.58 2.90 f 0.34 F-3742,3743 611112003 Gr. Beta 3.47 f 0.13 3.71 f0.14 3.59 f 0.10 F-3742,3743 611It2003 K-40 2.94 f 0.39 2.70 f 0.40 2.82 f 0.28 SO-3325,3326 6/13/2003 Gr. Beta 20.95 f 1.88 19.97 f 2.01 20.46 f 1.38 Ml-3253,3254 611712003 K-40 1329.40 f 121.80 1417.60 f 130.90 1373.50 f 89.40 Ml-3297,3298 6/17/2003 3-90 2.14 f 0.57 2.27 f 0.50 2.21 f0.38 WW-3380,3381 6/23/2003 Gr. Beta 5.58 f 0.69 5.03 f 0.69 5.31 f0.49 SWT-3403,3404 612412003 Gr. Beta 2.80 f 0.56 2.63 f 0.55 2.72 f 0.39 Ml-3424,3425 6/24/2003 K-40 1422.80 f 185.40 1216.20 f 170.10 1319.50 f 125.80 SW-3862,3863 6/24/2003 Gr. Beta 3.66 f 1.18 3.70 f 1.22 3.68 f 0.85 G-3479,3480 6/25/2003 Be-7 1.52 f 0.25 1.43 f 0.28 1.47 f 0.19 G-3479,3480 6/25/2003 K-40 5.02 f 0.45 5.10 f 0.48 5.06 f 0.33 LW-3809,3810 6l3012003 Gr. Beta 2.12 f 0.76 2.39 & 0.72 2.25 f 0.52 A5-2

TABLE A-5. ln-House "Duplicate" Samples Averaged Lab Code Date Analvsis First Result Second Result Result LW-3809,3810 6/3012003 H-3 2814.09 f 167.99 2812.17 f 167.94 2813.13 f 118.77 AP-4105,4106 613Ol2003 Be-7 0.07 f 0.01 0.07 f 0.01 0.07 f 0.01 G-3572,3573 71112003 Be-7 0.91 f0.24 0.81 fO.28 0.86 f 0.18 G-3572,3573 711I2003 Gr. Beta 6.35 f 0.15 6.35 f0.15 6.35 f 0.11 G3572,3573 7/1/2003 K-40 5.44 f 0.55 5.68 f 0.28 5.56 f 0.31 G-3572,3573 71112003 Sr-90 0.01 *0.00 0.02 fO.00 0.01 *o.oo Ml-3601,3602 7/1/2003 K-40 1318.60 f 117.40 1435.10 f 117.80 1376.85 f 83.16 MI-3601.3602 71112003 Sr-90 0.86 f 0.51 1.74 f 0.60 1.30 f 0.39 AP-3933,3934 71112003 Be-7 0.07 f 0.01 0.07 f 0.01 0.07 f 0.01 AP-4061,4062 7/2/2003 Be-7 0.07 fO.01 0.08 f 0.01 0.08 f 0.01 AP-4147.4148 712l2003 Be-7 0.08 f 0.01 0.07 f 0.01 0.07 f 0.01 AP-4084,4085 7/3/2003 Be-7 0.09 f 0.02 0.08 f 0.02 0.08 f 0.01 LW-3786,3787 7/9/2003 Gr. Beta 2.13 f 0.56 2.93 f 0.62 2.53 f 0.42 WW-4168,4169 711112003 Gr. Beta 3.79 f 1.87 4.48 f 1.98 4.14 f 1.36 CF-3975,3976 711412003 Be-7 1.64 f 0.81 1.66 f 0.57 1.65 f 0.50 CF-3975,3976 711412003 K-40 6.54 f 0.75 6.19 f 0.50 6.36 f 0.45 MI-4020,4021 711612003 K-40 1350.90 f 174.90 1199.80 f 153.20 1275.35 f 116.25 DW-4272,4273 712912003 Gr. Beta 2.35 f 0.92 2.29 fO.89 2.32 f 0.64 SWU-4461,4462 7130/2003 Gr. Beta 2.28 f 0.44 1.93 f 0.43 2.10 kO.31 SL-4398,4399 8/4/2003 Be-7 4.55 f 1.05 4.50 f 1.10 4.53 f0.76 SL-4398.4399 b 8/4/2003 Gr. Beta 3.41 fO.12 3.12 f 0.1 1 3.27 fO.08 SL-4398,4399 a1412003 K-40 2.47 f 0.67 2.44 f 0.87 2.46 f 0.55 G-4419,4420 81412003 Be-7 3.98 f0.63 3.93 f 0.57 3.96 f0.42 G-4419,4420 81412003 Gr. Beta 5.38 f 0.14 5.35 f 0.16 5.37 f 0.11 G-4419.4420 a1412003 K-40 4.42 *0.66 4.32 f 0.74 4.37 f0.50 TD-4550,4551 81412003 H-3 327.30 f 95.10 390.20 f 92.10 358.75 f 66.19 Ml-4482,4483 8/6/2003 K-40 1301.40 f 115.20 1370.30 f 116.80 1335.85 f 82.03 MI-4482,4483 81612003 Sr-90 0.81 fO.30 0.85 f 0.31 0.83 f0.21 G-4526.4527 8/6/2003 Be-7 1.47 f 0.29 1.42 f 0.28 1.45 f 0.20 G-4526,4527 8/6/2003 K-40 5.42 f 0.56 5.21 f0.63 5.31 fO.42 SWU-4609,4610 81612003 Gr. Beta 3.22 f 0.63 2.67 f 0.64 2.95 f 0.45 CW-4694,4695 81612003 Gr. Beta 1.48 f 0.34 1.09 f 0.34 1.29 f 0.24 CW-4694.4695 81612003 H-3 22776.41 f 428.73 21831.75 f 420.10 22304.08 f 300.12 LW-4673,4674 811312003 Gr. Beta 2.86 f0.65 3.75 f 0.71 3.30 f 0.48 MI-4735,4736 811912003 K-40 1396.30 f 127.90 1410.10 f 120.20 1403.20 f 87.76 Ml-4756,4757 811912003 Sr-90 1.66 f 0.47 1.53 f 0.44 1.60 f 0.32 VE-4832,4833 8/2012003 K-40 1.96 f 0.50 1.43 f 0.47 1.70 f 0.34 Ml-4860,4861 8/26/2003 K-40 1312.10 f 191.80 1307.80 f 109.30 1309.95 f 110.38 SO-5082,5083 812812003 CS-137 0.01 f0.00 0.01 fO.00 0.01 f0.00 SO-5082,5083 a12812003 Gr. Beta 20.02 f 1.84 20.92 f 2.03 20.47 f 1.37 CW-5349,5350 813112003 Gr. Beta 1.45 f 0.39 1.55 f 0.45 1.50 f 0.30 CW-5349,5350 a13112003 H-3 24429.50 f 444.42 24744.25 f 447.18 24586.88 f 315.23 ME-4968.4969 9/2/2003 Gr. Beta 4.90 f 0.23 5.18 f 0.24 5.04 f 0.17 ME-4968,4969 9/2/2003 K-40 2.46 f 0.41 2.68 f 0.37 2.57 f 0.28

TABLE A-5. In-House "Duplicate" Samples Concentration ( ~ C i i ) ~

Averaged Lab Code Date Analysis First Result Second Result Result DW-4989,4990 912l2003 Gr. Beta 2.20 f 1.04 3.19 f 1.14 2.70 f 0.77 Ml-5154,5155 91812003 K-40 1365.50 f 116.70 1456.70 f 119.10 1411.10 f 83.37 MI-5154,5155 9/8/2003 Sr-90 1.19 f 0.39 1.39 f 0.39 1.29 f 0.28 AP-6177,6178 9/29/2003 Be-7 0.07 f 0.01 0.06 f 0.01 0.06 f 0.01 swu-5773,5774 913012003 Gr. Beta 2.55 f0.63 2.83 f 0.60 2.69 i 0.44 AP-6102,6103 913012003 Be-7 0.07 f 0.01 0.05 f 0.01 0.06 f 0.01 G-5631,5632 1011I2003 Be-7 1.88 f 0.48 2.21 fO.40 2.05 f 0.31 G-5631,5632 101112003 Gr. Beta 5.87 f 0.09 5.85 i 0.08 5.86 f 0.06 G-5631,5632 101112003 K-40 5.24 f 0.77 5.26 f 0.58 5.25 f 0.48 S0-5660,5661 1Ol112003 cs-137 0.15 f 0.04 0.16 f 0.05

0.16 0.03 SO-5660.5661 1011/2003 Gr. Alpha 12.72 f3.72 14.86 f 3.88 13.79 f 2.69 SO-5660,5661 101112003 Gr. Beta 32.42 f 3.09 33.60 f 3.04 33.01 k2.17 SO-5660,5661 1011l2003 K-40 18.93 f 0.87 18.25 f 1.19 18.59 f 0.74 S0-5660,5661 10/1/2003 Sr-90 0.03 f 0.01 0.03 f 0.01 0.03 f 0.01 AP-6334,6335 101112003 Be-7 0.06 f 0.01 0.06 f 0.01 0.06 f 0.01 _ _ . .. _ .

AP-6363,6364 101212003 Be-7 0.07 f 0.02 0.07 f 0.02 0.07 i 0.01 Ml-5794,5795 1016l2003 3-90 1.37 f 0.37 1.02 f 0.37 1.19 f 0.26 Ml-5838,5839 1018/2003 K-40 1364.30 f 124.10 1414.40 f 110.40 1389.35 f 83.05 Ml-5838,5839 101812003 3-90 0.76 f 0.30 1.OO f 0.34 0.88 f 0.23 BS-5938,5939 101812003 cs-137 0.18 f 0.03 0.20 f 0.05 0.19 f 0.03 BS-5938,5939 10/8/2003 K-40 15.59 f 0.70 16.69 f 0.80 16.14 k 0.53 SS-5959,5960 1011312003 K-40 7.49 f 0.42 7.29 f 0.63 7.39 k 0.38 MI-6011.6012 1011312003 K-40 1165.20 f 118.70 1191.20 f 99.50 1178.20 f 77.44 Ml-6034,6035 10114l2003 3-90 0.86 f 0.33 0.90 f 0.34 0.88 f 0.24 VE-6055,6056 1011512003 Gr. Beta 5.18 50.18 5.33 f 0.18 5.25 f 0.13 VE-6055,6056 1011512003 K-40 5.31 f0.57 4.52 f 0.51 4.92 f 0.38 MI-6291,6292 10121/2003 K-40 1935.60 f 147.70 1936.10 f 116.50 1935.85 f 94.06 Ml-6291,6292 10121I2003 3-90 1.22 f 0.39 1.41 50.37 1.31 f 0.27 SS-6435,6436 10121I2003 cs-137 0.05 f 0.02 0.05 f 0.03 0.05 f 0.02 SS-6435,6436 10121l2003 K-40 14.08 f 0.54 14.28 f 0.80 14.18 f 0.48 CF-6313,6314 10122J2003 K-40 14.56 f 0.45 14.70 f 0.95 14.63 f 0.53 SO-6528,6529 10122l2003 cs-137 0.15 f 0.03 0.16 f 0.05 0.16 f 0.03 SO-6528,6529 10/22/2003 K-40 17.46 f 0.69 17.90 f 1.05 17.68 f 0.63 SO-6393,6394 10125l2003 cs-137 0.09 f 0.03 0.10 f 0.04 0.10 f 0.03 SO-6393,6394 lOl25l2003 Gr. Beta 23.21 f 1.98 21.76 f 1.91 22.48 f 1.38 S0-6393,6394 10/25/2003 K-40 13.98 f 0.80 14.57 f 0.86 14.27 f 0.59 SWT-6507,6508 lOl28l2003 Gr. Beta 2.64 f 0.52 2.63 f 0.53 2.63 f 0.37 DW-6647,6648 10131/2003 1-131 0.46 f 0.27 0.61 50.31 0.53 f 0.21 BS-6603,6604 11/3/2003 cs-137 9.03 f 0.82 8.60 f 1.13 8.82 f 0.70 BS-6603,6604 11/3/2003 Gr.Beta 26.83 f 1.94 27.18 f 1.95 27.01 f 1.38 SO-6670.6671 11/5/2003 cs-137 0.15 f 0.04 0.13 f 0.04 0.14 f 0.03 SO-6670,6671 11/5/2003 K-40 12.96 f 0.66 12.95 f 0.72 12.96 f 0.49 S-7067.7068 11/10/2003 CS-137 0.21 iO.05 0.19 f0.08 0.20 f 0.05 Ml-6818,6819 1111112003 K-40 1695.50 f 129.80 1709.40 f 143.00 1702.45 f 96.56 A5-4

TABLE A-5. In-House "Duplicate" Samples

~

c Concentration (PC~/L)~

Averaged Lab Code Date Analysis First Result Second Result Result MI-6818,6819 1111112003 Sr-90 2.01 f0.41 1.59 f 0.39

1.80 0.28 WL-6987,6988 11/17/2003 Fe-55 603.49 f 53.32 619.65 f 53.97 611.57 f 37.93 SO-7156.7157 11/21/2003 CS-137 0.74 f 0.08 0.77 f 0.07 0.76 f 0.06 SO-7156.71 57 11/21/2003 Gr. Alpha 14.90 f 4.24 19.25 f4.45 17.07 f 3.07 SO-7156,7157 11/21/2003 Gr.Beta 22.97 f 3.12 25.51 f2.98 24.24 f2.16 SO-7156.7157 11/21/2003 K-40 12.51 f 1.06 12.94 f 1.07 12.73 f 0.75 S-7281,7282 11/24/2003 cs-137 0.82 f 0.15 1.16 fO.20 0.99 f 0.12 SWU-7198,7199 11/25/2003 Gr. Beta 2.60 f 0.53 2.54 f 0.55 2.57 0.38 DW-7221,7222 11/25/2003 Gr. Beta 12.32 f 1.40 12.38 f 1.43 12.35 f 1.00 SW-7133,7134 12/1/2003 Gr. Beta 2.10 f 0.23 2.46 f 0.23 2.28 f 0.16 SW-7133,7134 12/1/2003 K-40 1.50 f 0.15 1.40 f 0.14 1.45 f 0.10 W-7519,7520 12/1/2003 Fe-55 3.03 20.65 . 3.12 f 0.64 3.08 f 0.46 sw-7a05,7806 12/1/2003 Sr-90 0.59 f 0.32 0.56 f 0.33 0.58 f0.23 VE-7399,7400 12/9/2003 Gr. Beta 4.99 f 0.15 5.24 f0.15 5.11 f O . l l VE-7399.7400 12/9/2003 K-40 5.04 f 0.46 5.34 f0.74 5.19.f 0.43 SW-7540.7541 12/9/2003 Gr. Alpha 2.64 f 1.36 2.10 f 1.19 2.37 f 0.91 SW-7540,7541 12/9/2003 Gr.Beta 6.62 f 1.22 5.89 f 1.35 6.25 f 0.91 LW-7736,7737 12/26/2003 Gr.Beta 2.62 f 0.54 2.83 fO.56 2.73 f 0.39 AP-7868,7869 12/30/2003 Be-7 0.05 f 0.01 0.04 50.01 0.04 f 0.01 AP-7952,7953 I2/30/2003 Be-7 0.04 f 0.01 0.04 fO.01 0.04 f 0.01 AP-7994,7995 12/31/2003 Be-7 0.05 f 0.02 0.05 f 0.01 0.05 f 0.01 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 pCiiL, except for air filters (pCiFilter). food products, vegetation, soil, sediment (pCi/g).

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

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

Concentrationb Known Control Lab Code Date Analysis Laboratory result Activity Limits' STW-972 -water 12/01102 Am-241 0.56 f 0.06 0.58 f 0.09 0.40 - 0.75 STW-972 water 12/01102 co-57 57.1 0 f 1.90 57.00 f 5.70 39.90 - 74.10 STW-972 water 12/01102 CO-60 ' 38.30 f 0.60 38.20 f 3.82 26.74 - 49.66 STW-972 water 12/01102 CS-134 395.30 f 10.10 421.OO f 42.1 0 294.70 - 547.30 STW-972 water 12/01102 CS-137 316.40 f 5.30 329.00 f 32.90 230.30 - 427.70 STW-972 water 12/01102 Fe-55 94.90 f 24.50 96.00 f 9.60 67.20 - 124.80 STW-972 water 12/01/02 Mn-54 33.40 f 0.10 32.90 f 3.29 23.03 -42.77 STW-972 water 12/01102 Ni-63 123.80 f 5.50 136.50 f 13.70 95.55 - 177.45 STW-972 water 12/01102 PU-238 0.66 f 0.06 0.83 f 0.08 0.58 - 1.08 STW-972 water 12/01102 Pu-239140 0.001 fO.001 0.000 f 0.000 0.000 - 0.005 STW-972 water 12/01102 Sr-90 13.80 f 1.00 12.31 f 1.23 8.62 - 16.00 STW-972 water 12/01102 Tc-99 128.10 f 3.80 132.00 f 13.20 92.40 - 171.60 STW-972 water 12/01102 u-23314 1.60 f 0.09 1.54 f 0.15 1.08 - 2.00 STW-972 water 12/01102 U-238 1.64 f 0.09 1.60 f0.16 1.12 - 2.08 STW-972 water 12101102 Zn-65 540.40 f 9.90 516.00 f 51.60 361.20 - 670.80 STSO-987 soil 01I0 1103 CO-57 534.36 f 2.61 530.00 f 53.00 371.OO - 689.00 STSO-987 soil 0 1101I03 CO-60 442.16 f 2.31 420.00 f 42.00 294.00 - 546.00 STSO-987 soil 01101103 CS-134 211.00 f 2.30 238.00 f 23.80 166.60 - 309.40 STSO-987 soil 01101103 cs-137 849.50 f 3.30 832.00 f 83.20 582.40 - 1081.60 STSO-987 soil 01/01103 K-40 716.50 f 12.80 652.00 f 65.20 456.40 - 847.60 STSO-987 soil 01101103 Mn-54 148.76 f 2.84 137.00 f 13.70 95.90 - 178.10 STSO-987 soil 01101103 Ni-63 597.10 f 23.50 770.00 f 77.00 539.00 - 1001.OO STSO-987 soil 01101103 PU-238 67.05 f 3.10 66.90 f 6.70 46.83 - 86.97 STSO-987 soil 01/01/03 Pu-239140 52.80 f 3.60 52.70 f 5.30 36.90 - 68.50 STSO-987 soil 01101103 Sr-90 609.50 f 9.80 714.00 f 71.40 499.80 - 928.20 STSO-987 soil 0 1101I03 u-23314 99.50 f 7.60 89.00 f 8.90 62.30 - 115.70 STSO-987 soil 0 1101103 U-238 508.60 f 42.20 421.00 i42.10 294.70 - 547.30 STSO-987 soil 01101103 Zn-65 492.70 f 28.10 490.00 f 49.00 343.00 - 637.00

~~ ~~

a 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 All results are in Bqkg or BqlL as requested by the Department of Energy.

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

A6-1

TABLE A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)

Concentrationa EML Control Lab Code Type Date Analysis Laboratory results Result? Limits' STW-977 water 03/01/03 Gr. Alpha 304.30 f 53.10 377.50 0.58 - 1.29 STW-977 water 03/01103 Gr. Beta 615.80 f 14.70 627.50 -

0.61 1.43 STW-978 water 03101lo3 Am-24 1 2.00 f 0.10 2.1 3 -

0.79 1.41 STW-978 water 03/01103 Co-60 221.30 f 1.20 234.00 -

0.80 1.20 STW-978 a water 03/01/03 cs-I34 23.30 f 1.10 30.50 -

0.80 1.30 STW-978 water 03/01103 CS-I37 61.40 f 0.60 63.80 0.80 - 1.22 STW-978 = water 03101103 H-3 341.90 f 22.70 390.00 -

0.78 2.45 STW-978 water 03/01103 PU-238 3.70 f 0.20 3.33 -

0.74 1.20 STW-978 water 03/01103 Pu-239140 4.40 f 0.10 3.92 -

0.79 1.20 STW-978 water 03101lo3 Sr-90 4.60 f 0.30 4.34 -

0.69 1.34 STW-978 water 03/01103 Uranium 5.10 f 0.60 4.29 -

0.75 1.33 STSO-979 soil 03101/03 AC-228 55.60 f 2.50 57.60 0.80 - 1.38 STSO-979 soil 03/01/03 Am-241 12.42 f 0.90 15.60 0.65 - 2.28 STSO-979 soil 03/01103 Bi-212 57.70 f 3.20 60.60 -

0.50 1.34 STSO-979 soil 03101103 Bi-214 60.40 f3.20 67.00 0.78 - 1.42 STSO-979 soil 03101lo3 CS-137 1416.80 f 70.00 1450.00 -

0.80 1.25 STSO-979 soil 03/01/03 K-40 653.80 f 1I.90 636.00 -

0.80 1.32 STSO-979 soil 03/01/03 Pb-212 51.10 f 5.20 57.90 -

0.78 1.32 STSO-979 soil 03/01lo3 Pb-214 64.70 f 5.10 71.10 -

0.76 1.46 STSO-979 soil 03101103 Pu-239140 24.40 f 0.30 23.40 -

0.71 1.30 STSO-979 soil 03/01/03 Sr-90 54.50 f 2.60 64.40 -

0.67 2.90 STSO-979 soil 03/01lo3 Uranium 245.00 f 1.50 249.00 -

0.71 1.32 STVE-980 Vegetation 0310Ilo3 Am-241 3.10 f 0.20 3.51 0.73 - 2.02 STVE-980 Vegetation 03101103 Cm-244 1.40 f 0.50 2.01 0.61 - 1.59 SNE-980 Vegetation 0310I103 Co-60 12.60 f0.40 12.10 0.80 - 1.44 SNE-980 Vegetation 03/01/03 cs-137 449.70 f 6.20 444.00 0.80 - 1.31 SNE-980 Vegetation 03/01/03 K-40 1159.00 f 38.60 1120.00 0.79 - 1.39 SNE-980 Vegetation 03101103 Pu-239/40 4.80 f 0.40 5.1 7 0.69 - 1.31 SNE-980 Vegetation 03101/03 Sr-90 659.70 f 50.40 650.00 0.55 - 1.21 STAP-981 Air Filter 03/01103 Am-241 0.27 f 0.10 0.34 0.70 - 2.34 STAP-981 Air Filter 03/01/03 Co-60 30.20 f 0.30 33.50 0.80 - 1.26 STAP-981 Air Filter 03101I03 CS-137 90.30 f 1.30 99.70 0.80 - 1.32 STAP-981 Air Filter 03101103 Mn-54 41.80 f 0.60 43.80 0.80 - 1.35 STAP-981 Air Filter 03101/03 PU-238 0.52 f 0.10 0.52 0.67 - 1.33 STAP-981 Air Filter 03101103 Pu-239140 0.35 f 0.10 0.33 0.73 - 1.26 STAP-981 Air Filter 03101/03 Sr-90 2.50 f 0.10 2.80 0.53 - 1.84 STAP-981 Air Filter 03/01/03 Uranium 0.51 m0.10 0.50 0.79 -2.10 STAP-982 Air Filter 03101lo3 Gr. Alpha 0.90 f 0.10 1.17 0.73 - 1.43 STAP-982 Air Filter 03/01I03 Gr. Beta 1.50 f 0.10 1.50 0.76 - 1.36 A7-I

TABLE A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)

Concentrationa EML Control Lab Code Type Date Analysis Laboratory results Resultb Limits' STW-992 water 09/02/03 Am-241 9.78 f 0.32 8.76 0.79 - 1.41 The September, 2003 results are preliminary. Control limits used were taken from the March, 2003 data.

Control limits may vary slightly when the final study is published.

STW-992 water 09/02/03 CO-60 468.30 f 4.10 513.00 0.80 20 STW-992 water 09/02/03 cs-134 53.90 f 0.80 63.00 0.80 - 1.30 STW-992 water 09/02/03 CS-137 76.1 0 f 1.40 80.30 0.80 - 1.22 STW-992 water 09/02/03 H-3 355.20 f 12.80 446.30 0.78 - 2.45 STW-992 water 09/02/03 PU-238 1.71 f 0.07 2.07 0.74 - 1.20 STW-992 water 09/02/03 Pu-239/40 4.24 f 0.01 4.99 0.79 - 1.20 STW-992 water 09/02/03 Sr-90 6.70 f 0.50 7.04 0.69 - 1.34 STW-992 water 09/02/03 Uranium 6.03 f 0.14 5.69 0.75 - 1.33 STW-993 water 09/02/03 Gr. Alpha 688.00 f 7.60 622.00 0.58 - 1.29 STW-993 water 09/02/03 Gr. Beta 1985.00 f 111.00 1948.00 0.61 - 1.43 STSO-994 soil 09/02/03 Am-241 19.70 f 1.50 18.40 0.65 - 2.28 STSO-994 soil 09/02/03 cs-137 1928.00 f 19.00 1973.00 0.80 - 1.25 STSO-994 soil 09/02/03 K-40 533.00 f 79.00 488.00 0.80 - 1.32 STSO-994 soil 09/02/03 PU-238 15.30 f 0.80 14.60 0.59 - 2.88 STSO-994 soil 09/02/03 PU-239/40 32.50 f 2.30 30.40 0.71 - 1.30 STSO-994 soil 09/02/03 Sr-90 69.80 f 2.30 80.30 0.67 - 2.90 STSO-994 soil 09/02/03 Uranium 228.30 f 17.10 259.30 0.71 - 1.32 STAP-995 Air Filter 09/02/03 Am-241 0.64 f 0.05 0.44 0.70 - 2.34 STAP-995 Air Filter 09/02/03 CO-60 48.50 f 0.40 55.10 0.80 - 1.26 STAP-995 Air Filter 09/02/03 cs-137 51.20 f 1.10 54.80 0.80 - 1.32 STAP-995 Air Filter 09/02/03 Mn-54 53.70 f 1.10 58.00 0.80 - 1.35 STAP-995 Air Filter 09/02/03 PU-238 0.24 f 0.05 0.23 -

0.67 1.33 STAP-995 Air Filter 09/02/03 Pu-239140 0.41 fO.10 0.40 -

0.73 1.26 STAP-995 Air Filter 09/02/03 Sr-90 1.90 f 0.10 2.06 -

0.53 1.84 STAP-995 Air Filter 09/02/03 Uranium 0.80 f 0.06 0.82 -

0.79 2.10 STAP-996 Air Filter 09/02/03 Gr. Alpha 3.23 f 0.07 3.1 1 -

0.73 1.43 STAP-996 Air Filter 09/02/03 Gr. Beta 4.18 f 0.03 3.89 -

0.76 1.36 a Results are reported in B q L with the following exceptions: Air Filters (Bqffilter), Soil and Vegetation (Bqkg).

The EML result listed is the mean of replicate determinations for each nuclide f the standard error of the mean.

Control limits are reported by EML as the ratio of Reported Value I EML value.

A low bias for Cs-I34 activity bas been observed in the past No errors have been found in the library or efficiency.

Additional spike analyses will be performed and a correction factored into the calculation.

Reporting error.

A7-2

APPENDIX B DATA REPORTING CONVENTIONS B-1

Data Reportina 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. Sinale Measurements Each single measurement is reported as follows: X f S where: x = value of the measurement; s = 2s counting uncertainty (correspondingto 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 4.66s uncertainty for a backgroundsample.

3.0. Duplicate analvses 3.1 Individual results: For two analysis results; x i f s l and x2 f s2 Reported result: x +, s; where x = (112) (xi + x2) and s = (1/2) ,/$ +si 3.2. Individual results: <L1 , 4-2 Reported result: L, where L = lower of L1 and L2 3.3. Individual results: x*s,<L Reported result: x f s if x TL; <L otherwise.

4.0. Computation of Averaaes 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 xi, x2 . Xn are defined as follows:

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-1 . Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areasa.

Air (pci/m3) Water (pCi/L)

Gross alpha 1x Strontium89 8,000 Gross beta 1 Stron tium-90 500 lodine-131 2.8 x 10-1 Cesium-137 1,000 Barium-140 8,000 lodine-131 1,000 Potassium-@ 4,000 Gross alpha 2 Gross beta 10 Tritium 1 x106 a Taken from Table 2 of Appendix B to Code of Federal Regulations Xtle 10, Part 20, and appropriate footnotes.

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-rnilk-child pathway.

A natural radionuclide.

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APPENDIX D

SUMMARY

OF THE LAND USE CENSUS D-1

Appendix D S u m m a w of the Land Use Census The Duane Arnold Energy Land Use Census for 2003 was completed during late September and early October of 2003. 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 3rd, 2003 for water use downstream of the DAEC to Cedar Rapids.

There were 189 vegetable gardens identified during the performance of the 2003 Census.

This number exceeds the number of gardens found in the 2002 survey by 11. A new garden to the WNW of the plant resulted in the vegetable receptor for that sector being moved in from 2560 to 2460 meters. A list of the nearest gardens is attached.

There were no changes in the milk animal locations with in the 3 mile radius of the plant in the past year. Additional milk receptors were identified between 3 and 5 miles. They are noted on attachments 4 and 5.

The locations of the nearest resident for each sector remained the same in 2003.

21 new homes were built or were under construction within three miles of the DAEC, compared to the 37 new homes identified in 2002. Most of the new houses built were located in the sectors between the plant , Palo and Cedar Rapids (SSW to SE). A listing of the newly identified homes is attached.

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.

As a result of this census, adjustments were made to the MlDAS dose projection software model for the more precise receptor distances.

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.

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APPENDIX E ANNUAL RADIATION DOSE ASSESSMENT

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 2003 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, page 8 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 0 The contribution of dose to a member of the public most likely to be exposed from effluent releases was calculated by 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 stack releases and dose calculated from environmental contamination was performed.

0 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.

1.) There were no releases of radioactive material to liquid effluents in 2003.

2.) The maximum dose to air at the site boundary from noble gases released was 2E-03 mrad from gamma radiation at 535 meters SSW.

3.) The maximum dose to air at the site boundary from noble gases released was 6E-02 mrad beta radiation at 535 meters SSW.

4.) The whole body dose equivalent to the maximally exposed individual from noble gases was 2E-03 mrem, at 805 meters West.

5.) The skin dose equivalent to the maximally exposed individual from noble gases was 2E-03 mrem, at 805 meters West.

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6.) The maximally exposed organ due to iodines and particulates with half-lives greater than eight days was the skin of a child at 974 meters SW, with an estimated dose equivalent of 5E-02 mrem.

==

Conclusion:==

No measurable dose due to the operation of the DAEC was detected by environmental TLDs in 2003. 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 2003 TYPe Age Distance Direction Dose or Dose Annual 10 CFR Group (meters) Equivalent 50, Appendix I (mrem) Limit Direct Radiation (as measured by TLDs)

None

Liquid Releases None Gamma Air Dose 535 ssw 2E-03 m a d 10 mrad Beta Air Dose 535 ssw 6E-02 mrad 20 m a d Whole Body All 805 W 2E-03 mrem 5 mrem Skin All 805 W 2E-03 mrad 15 mrem Child-Organ Dose Skin 974 sw 5E-02 mrem 15 mrem

No Appendix I limit but is used to determine compliance with 40 CFR 190 limits of 25 mrem whole body and 75 mrem thyroid.

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NG-04-0323, Annual Radiological Environmental Operating Report

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NG-04-0323, Annual Radiological Environmental Operating Report

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