Text

Annual Report to the Us NRC Radiological Environmental Monitoring Program
	ML101390059
Person / Time
Site:	Monticello
Issue date:	12/31/2009
From:	Grob B; Environmental
To:	; Office of Nuclear Reactor Regulation
References
	L-MT-10-032
	Download: ML101390059 (59)
	v • d • e

- , Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road

Northbrook, IL 60062-2310 ph. (847) 564-0700

fax (847) 564-4517 XCEL ENERGY CORPORATION MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2009 Prepared under Contract by ENVIRONMENTAL, Inc.

Midwest Laboratory Project No. 8010 Approved:

B nia r ,M.S.

La orat Manager

PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by personnel of the Monticello Nuclear Generating Plant, operated by Northern States Power Co. -Minnesota for XCEL Energy Corporation. This report was prepared by Environmental, Inc., Midwest Laboratory.

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TABLE OF CONTENTS No. Pae*

P re fa ce ...................................................................................................... ....................... ii List of T a b le s ...................................................................................................................... iv List o f Figu re s .................................................................................................... :................ v

1.0 INTRODUCTION

.... ................................................ 1.....

2 .0 S UMMA RY ................................................... ....................................................................... 2 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) ................. 3 3.1 Program Design and Data Interpretation .......................................................... 3 3.2 Program Description................................................................................ 4 3.3 P rogram Execution ............................................................................................. 5 3.4 Laboratory Procedures ........................................................................................ 6 3.5 Program Modifications .:.......................................... 6 3.6 Land Use C ensus ............................................................................................ 6 4.0 RESULTS AND DISCUSSION ...... .............................................................................. 7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents ............................... 7 4.2 Summary of Preoperational Data ...................................................................... 7 4 .3 P rogram Findings .............................................................................................. 8 5.0 FIGURES AND TABLES .............................................. 12

6.0 REFERENCES

..... ....................... 25 APPENDICES A Interlaboratory Comparison Program Results ............................................................... A-1 B Data Reporting Conventions ........................................................................................ B-1 C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area ........................ ..................... C-1 D S am pling Location Maps ...................................................................... ........................... D-1

LIST OF TABLES No. Title Page 5.1 Sample Collection and Analysis Program ................................................................ 13 5.2 Sampling Locations .................................................................................................. 14 5.3 Missed Collections and Analyses .1................................................................................. 17 5.4 Radiation Environmental Monitoring Program Summary ............................................... 20 The following tables are in the Appendices:

Appendix A A-1 Interlaboratory Comparison Program Results .......................................................... Al-1 A-2 Therm olum inescent dosim eters (TLDs) ........................................................................ A2-1 A-3 In-house Spiked Samples ....................................... A3-1 A-4 In-house "Blank" Samples ............................................ A4-1 A -5 In-house "Duplicate" Sam ples ................................................................... ................... A5-1 A-6 Department of Energy MAPEP comparison results ...................................................... A6-1 A-7 Environmental Resources Associates, Crosscheck Program Results (E ML study replacem ent) .................................................................................. A7-1 Attachment A: Acceptance criteria for spiked samples .............................................. A2 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas ........................................................................ C-2 iv

LIST OF FIGURES No. Title Page 5-1 Offsite Ambient Radiation (TLDs), inner versus outer ring locations .................................... 18 5-2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location ........................................................................................ 19 Appendix D D-1 Sample collection and analysis program: TLD locations, Inner Ring .......................................................................................................... . . . . . . . . D -2 D-2 Sample collection and analysis program: TLD locations, O u te r R in g ....................................................................... ...................................................... D -3 D-3 Sample collection and analysis program: TLD locations, Controls ....................................................... D-4 D-4 Sample collection and analysis program: Radiation Environmental Monitoring Program, Milk sa m pling loca tio ns ........................................................................................................... D -5 D-5 Sample collection and analysis program: Radiation Environmental Monitoring Program, Milk, Sludge, Ground water and Shoreline sampling locations ............................................... D-6 D-6 Sample collection and analysis program: Radiation Environmental Monitoring Program, Ground water, O n-site m onitoring well locations ..................................................................... D-7 v

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory for the Monticello Nuclear Generating Plant, Monticello, Minnesota, during the period January - December, 2009.

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 not included in this report.

These data are included in a reference document (Environmental, Inc., Midwest Laboratory, 2010a) available at the Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.

The Monticello Nuclear Generating Plant is a boiling water reactor with a nominal generating capacity of 620 MWe. It is located on the Mississippi River in Wright County, Minnesota, owned by XceI Energy Corporation and operated by Northern States Power Co.-Minnesota. Initial criticality was achieved on December 10, 1970. Full power was achieved March 5, 1971 and commercial operation began on June 30, 1971.

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2.0

SUMMARY

The Radiological Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications and the Offsite Dose Calculation Manual (ODCM) for the Monticello Nuclear Generating Plant is described. Results for the year 2009 are summarized and discussed.

Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant.

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3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program (REMP) at the Monticello Nuclear Generating Plant 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 (TLD's).

Sources of environmental radiation include the following:

(1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; (4) Industrial and medical radioactive waste; and (5) Fallout from nuclear accidents.

In interpreting the data, effects due to the Plant 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 Monticello Plant 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 plant 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 environmental samples collected from the Plant site. The Plant's monitoring program includes analyses for tritium and iodine-131. Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-1 37, cerium-1 44, beryllium-7, and potassium-40. The first 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 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, .1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered as radiological impact indicators. 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 final group, manganese-54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.

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Procqram Desigqn and Data Interpretation (continued)

Othermeans of distinguishing sources of environmental radiation are employed in interpreting the

' data. Current radiation levels are compared with previous levels, including, those measured before the plant became operational. Results of the Plant's Monitoring Program can be related to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations.

3.2 Program Description The sampling and analysis schedule for the Radiological Environmental Monitoring Program (REMP) at the Monticello Plant is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the plant site. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Monticello Generating Plant REMP Surveillances, Current Revision). Maps of sampling locations are included in Appendix D.

To monitor the air environment, -airborne particulates are collected on membrane filters by continuous pumping at five locations. Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations. Filters are changed and counted weekly.

Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-1 31. Quarterly composites of particulate filters from each location are determined by gamma spectroscopy. One of the five locations is a control (M-1), and four are indicators (M-2, M-3, M-4, M-5). One of the indicators is located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (highest D/Q sector).

Ambient gamma radiation is monitored at forty locations, using CaSO 4:Dy dosimeters with four sensitive areas at each location: fourteen in an inner ring in the general area of the site boundary, sixteen in the outer ring within 4-5 mile radius, six at special interest locations and four control locations, outside a 10 mile radius from the plant. They are replaced and measured quarterly.

The last local dairy went out of business in April, 2008. In September, 2008, triannual collections of pasture grass and vegetation were added to the program. Samples from locations M-41, M-42 and M43 (C) were analyzed for iodine-131 and other gamma emitting isotopes, as substitute for dairy sampling.

Leafy green vegetables (cabbage) are collected annually from the highest D/Q garden and a control location and analyzed for iodine-1 31. Corn and potatoes are collected annually only if the field is irrigated by water in which liquid radioactive effluent has been discharged. Analysis is for gamma-emitting isotopes.

Ground water is monitored by quarterly collections from three off-site locations (one control and two indicators) and one on-site Plant well. To monitor possible sources of groundwater contamination due to plant operations, sixteen on-site wells were established as part of the REMP. The samples are analyzed for tritium and gamma emitting isotopes.

In 2009, six previously drilled temporary wells were filled in. A tritium characterization study was conducted on core samples. Results are detailed in Part II, Appendix A.

Quarterly.collections of storm water runoff were added to monitor another possible pathway to the groundwater aquifer.

River water is collected weekly at two locations, one upstream of the plant and one downstream.

Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

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Program Description (continued)

Drinking water is collected weekly from the City of Minneapolis water supply, which is taken from the Mississippi River downstream of the Plant. Monthly composites are analyzed for gross beta, iodine-1 31, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, invertebrates, and shoreline sediments. Shoreline sediment is also collected semi-annually from one downstream recreational location. All samples are analyzed for gamma-emitting isotopes.

3.3 Program Execution The Program was executed as described in the preceding section with the following exceptions:

(1) Air Particulates / Air Iodine:

No air particulate / air iodine samples were available from location M-1 for the week ending December 9, 2009. The sampler pump failed due to a faulty timer.

(2) Thermoluminescent Dosimeters:

The TLD for location M-01B was missing in the field for the second quarter, 2009.

(3) Surface Water:

Surface water was not collected at location M-08 during the months of January and February, 2009, due to unsafe ice conditions.

Two weeks were missed from the March, 2009 composite water sample. Surface water could not be collected at location M-08 for the weeks ending March 4, 2009 and March 11, 2009, due to unsafe ice conditions.

Four weeks were missed from the December, 2009 composite water sample Surface water could not be collected at location M-08 for the weeks ending December 9, 16, 23 and 30, 2009, due to unsafe ice conditions.

(4) Well Water:

Well water was not collected at location M-12 for the third quarter, 2009. The well was out of service.

Deviations from the program are summarized in Table 5.3.

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3.4 Laboratory Procedures

.-The iodine-131 analyses in milk and drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method'.and solvent extraction and subsequent beta counting.

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

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

Tritium concentrations are 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 control/quality assurance program designed to assure the reliability of data obtained. Details of the QA Program are

.... presented elsewhere (Environmental, Inc., Midwest Laboratory, 2009 ). The QA Program includes

'participation in Interlaboratory Comparison (crosscheck) Programs. Results: obtained in the crosscheck programs are presented in Appendix A.

3.5 Program Modifications Storm water runoff collections were added to the program in 2009. The samples are collected quarterly and analyzed for tritium and gamma emitting isotopes.

Four additional on-site monitoring wells were added to the permanent REMP in 2009. The samples are collected quarterly and analyzed for tritium and gamma emittinggisbtopes.

3.6 Land Use Census In accordance with the MNGP -Chemistry Manual, Procedure 1.05.41,j"Annual Land Use Census and Critical Receptor Identification", a land use census shall be conducted and shall identify the location of.the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft2 producing fresh leafy vegetables, in each of the 16 meteorological sectors within a distance of 5 miles.. The census shall also identify the locations of all milk animals and all 500 ft2 or greater gardens producing broad leaf vegetation in each of the meteorological sectors within a distance of three miles. This census shall be conducted at least once per year between the dates of May 1 and October 31. New locations shall be added to the radiation environmental monitoring program within 30 days and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.

The 2009 land use census was conducted between September 21 and September 25, 2009.

.There was one sector (NNW) in which the highest D/Q value for nearest garden increased by greater than 20%. No changes to the sampling procedures were required.

There are no longer any dairy farms in the area of the Monticello Nuclear Plant. A few farms raise goats, but none for milk. Vegetation sampling was implemented in 2008 to replace the milk sampling requirement. The highest D/Q locations for nearest resident and garden animal did not change from the 2008 census.

Details of the land use census are contained in the Land Use Census and Critical Receptor Report, Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.

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4.0 RESULTS AND DISCUSSION All of the scheduled collections and analyses were made except those listed in Table 5.3.

All results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown.

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents at nuclear facilities and no atmospheric nuclear tests conducted in the year 2000. The last reported test was made by the People's Republic of China on October 16, 1980.

4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Monticello Nuclear Generating Plant during the years 1968 to 1970, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult to make, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross 2 2 beta measurements in fallout averaged 20,600 pCi/m in 1969 and 12,000 pCi/m in 1970. These levels are reflected throughout the various media tested.

In the air environment, ambient gamma radiation (TLDs) averaged 9.1 mRem/4 weeks during preoperational studies (1970). Gross beta in air particulates in 1969 and 1970 averaged 0.20 3 3 pCi/m. Present day levels have stabilized at around 0.025 pCi/m . Airborne radioiodine remained below detection levels.

In the terrestrial environment of 1968 to 1970, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-1 37 and Sr-90 were detected. Cs-137 levels averaged 16.7 pCi/L.

Soybean crop measurements in 1969 averaged 35.5 pCi/g for gross beta and 0.3 pCi/g for Cs-137. Gross beta measured in soil averaged 51.7 pCi/g . Present day measurements for cesium-137 are below detection levels in milk and agricultural crops.

The aqueous environment was monitored by.testing of river water, bottom sediments, fish, aquatic vegetation, and periphyton. Specific location comparison of drinking, river, and well water concentrations for tritium and gross beta are not possible. However, tritium background levels, measured at seven separate locations from 1968 to 1970, averaged 970 pCi/L. Present day environmental samples measure below detection levels. Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCi/L in upstream and downstream Mississippi River water, 4.4 pCi/L for well waters, and 18.6 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In shoreline sediments, gross beta background levels in 1970 averaged 49.8 pCi/g for both upstream and downstream samples. Cs-137 activity averaged 0.10 pCi/g for both upstream and downstream samples. Low levels of Cs-137, occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta levels in fish flesh averaged 5.3 pCi/g in 1968 and 1969. Cs-137, measured in 1969 and 1970, averaged 0.044 pCi/g. Gross beta background levels, in 1970, for aquatic vegetation, algae, and periphyton samples measured 86.7 pCi/g, 76.5 pCi/g, and 28.1 pCi/g respectively.

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4.3 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant.

Ambient Radiation (TLD's)

Ambient radiation was measured in the general area of the site boundary, at an outer ring 4 - 5 mi.

.distant from the Plant, at special interest areas and at four control locations. The means were similar for both inner and outer rings (14.9 and 14.4 mRem/91 days, respectively). The mean for special interest locations was 14.1 mRemI91 days and the mean for the control locations was 15.0 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1994 through 2008 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).

Year Inner Ring Outer Rin Dose rate (mRem/91 days) 1994 14.6 14.0 1995 14.4 13.6 1996 14.0 13.5 1997 13.3 12.8 1998 15.0 14.4 1999 15.1 14.3 2000 15.1 14.5 2001 14.3 .13.7 2002 15.9 14.8 2003 15.6 15.0 2004 16.0 15.4 2005 15.6 15.2 2006 16.5 15.6 2007 16.1 15.1 2008 15.2 14.6 2009 14.9 14.4 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates, Inner vs. Outer Ring locations 8

Airborne Particulates

.The average annual gross beta concentrations in airborne particulates were almost identical at 3

indicator and control locations (0.029 and 0.030 pCi/mr respectively) and similar to levels observed from 1994 through 2008. The results are tabulated below.

Year Indicators Control 3

Concentration(p~i/m) 1994 0.023 0.024 1995 0.024 0.025 1996 0.023 0.023 1997 0.023 0.023 1998 .0.023 0.023 1999 , 0.023 0.025 2000 0.027 0.026 2001 '. 0.027 0.026 2002 p'0.028 0.028 2003 0.027 0.027 2004 0.024 0.024 2005 *0.025 0.025 2006 0.024 0.025 2007 0.027 0.028, 2008 0.028 0.029 2009 0.029 0.030 Average annual gross beta concentrations in airborne particulates.

Typically, the highest average readings occur during the months of January and December, and the first and fourth quarters, as observed in 1994 through 2009.

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 radiation3(Arnbld and AI-Salih, 1955) was detected in all samples, with an average activity of 0.082 pCi/m for all locations. All other gamma-emitting isotopes were below their respective LLD limits.

Airborne Iodine 3

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

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River Water and Drinkino Water Tritium activity measured below the LLD of 500 pCi/L in all samples. Gross beta activity in Minneapolis drinking water averaged 2.3 pCi/L and was similar to average levels observed from 1994 through 2008. Gross beta averages are tabulated below.

Year Gross Beta (pCi/L) Year Gross Beta (pCi/L) 1994 2.0 2002 2.9 1995 2.3 2003 3.0 1996 2.1 1 2004 2.7 1997 2.3 2005 2.8 1998 2.4 2006 2.1 1999 .2.2 2007 2.8 2000 2.5 2008 2.1 2001 2.5 -~-2009 2.3

......... J.

Average annual concentrations; Gross beta in drinking water.

Comparisons with data reported by the USEPA for Minneapolis drinking water samples collected from 1980 through 2005 indicate that concentrations of these nuclides are remaining fairly constant. Gamma-emitting isotopes were below detection limits in all surface water samples.

There was no indication of a plant effect.

Well Water At the four indicator and control locations, tritium measured below the LLD level of 500 pCi/L in all samples. Gamma isotopic results were below detection limits. The data for 2009 were consistent with previous years results and no plant operational effects were indicated.

Monitoring Wells (on-site)

Measurable tritium above the LLD level of 500 pCi/L was detected in 14 of 92 samples collected from thirteen on-site monitoring wells. The activities ranged from 502 to 21,727 pCi/L. The highest activities were observed at well MW-9A.

Gamma isotopic results were below detection limits.

Stormwater Run-off (on-site)

Stormwater. runoff was sampled quarterly in 2009 and analyzed for tritium and gamma emitting isotopes. In the first quarter, 2009, measurable tritium above the LLD level of 500 pCi/L was.

detected at a level of 985 pCi/L.

Gamma isotopic results were below detection limits.

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Pasture Grass Three new locations for the sampling of grass and vegetation were established in 2008, as substitute. for unavailable dairy: farms; Pasture grass was collected in July, August and September, 2009. 1-131. concentrations measured below 0.027 pCi/g wet weight in all samples.

With the exceptions of naturally-occurring beryllium-7 and potassium-40, no other gamma-emitting isotopes were detected.

crops Cabbage was collected in September from two locations and analyzed for iodine-131. Levels of 1-131 measured below 0.017 pCi/g wet weight in both samples. With the exceptions of naturally-occurring beryllium-7 and potassium-40, no other gamma-emitting isotopes were detected.

No crops within five miles of the plant, were found using irrigation water from the Mississippi River. There was no indication of any plant effect.

Fish Fish samples were collected in May and .October. Flesh was separated from the bones and analyzed by gamma spectroscopy. Naturally-occurring potassium-40 was found to be similar in upstream and downstream samples (3.23 and 2.92 pCi/g wet weight, respectively). All gamma-emitting isotopes were below their respective LLD levels. There was no indication of a plant effect.

Invertebrates Samples were collected in June and September of 2009, and analyzed by gamma spectroscopy.

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

Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in June and September of 2009 and analyzed for gamma-emitting isotopes. Low levels of cesium-137 were detected in one downstream sample, measuring 0.037 pCi/g dry weight. Similar levels of activity and distribution have been observed since 1978, and are indicative of the influence of fallout deposition. The only other gamma-emitting isotopes detected were naturally-occurring beryllium-7 and potassium-40. There was no indication of a plant effect.

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5.0 FIGURES AND TABLES 12

Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant.

Collection Analysis Location Type and Type and Medium No. Codes (and Type)a Frequencyb Frequencyc Ambient radiation 40 M-01A - M-14A, M-01B - M-16B C/Q Ambient gamma (TLDs) M-01S - M-06S, M-01C - M-04C Airborne Particulates 5 M-I(C), M-2, M-3, M-4, M-5 C/W GB, GS (QC of each location)

Airborne Iodine 5 M-I(C), M-2, M-3, M-4, M-5 CAN 1-131 Pasture grass, Vegetation d 3 M-41, M-42, M-43(C) 3x/year GS Surface water 2 M-8(C), M-9 G/W GS(MC), H-3(QC)

Drinking water 1 M-14 GIW GB(MC), I-131(MC)

GS (MC), H-3 (QC)

Well water 4 M-1O(C), M-11, M-12, M-27 G/Q H-3, GS On-site monitoring wells 16 M-33 to M-40, M-44 to M-51 Edible cultivated crops -

Corn e 1 M-19 G/A GS Leafy Vegetable 2 M-27, G/A 1-131 Available Producer (C)

Potatoes e 1 M-21 G/A GS Fish 2 M-8(C), M-9 G/SA GS (one species, edible portion)

Periphyton or invertebrates 2 M-8(C), M-9 G/SA GS Shoreline sediment 3 M-8(C), M-9, M-15 G/SA GS a Location codes are defined in Table 5.2. Control stations are indicated by (C). All other stations are indicators.

b Collection type is coded as follows: C/= continuous, G/ = grab. Collection frequency is coded as follows:

W-= weekly, M = monthly, Q = quarterly, SA = semiannually, A = annually.

Analysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131 =

iodine 131. Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.

d Pasture grass and vegetation collections added to supplement dairy sampling.

aCollected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields.

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Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.

Distance and Code Type'. Collection Site Sample Typeb Direction from Reactor M-1 C Air Station M-1 AP, Al 11.0 mi @ 307°/NW M-2 Air Station M-2 AP, Al 0.8 mi @ 140°/SE M-3 Air Station M-3 AP, Al 0.6 mi @ 104°/ESE M-4 Air Station M-4 AP, Al 0.8 mi @ 147°/SSE M-5 Air Station M-5 AP, Al 2.6 mi @ 134°/SE M-8 C Upstream of Plant Intake SW, SS, BO, F < 1000' upstream M-9 Downstream of Plant Discharge SW, SS, BO, F < 1000' downstream M-10 C Campbell Farm WW 10.6 mi @ 357°/N M-11 City of Monticello WW 3.3 mi @ 127°/SE M-12 Plant Well #1 WW 0.26 mi @ 252°/SW M-14 City of Minneapolis DW 37.0 mi @ 132°/SE M-15 Montissippi Park SS 1.27 mi @ 114°/ESE M-19 River Irrigated Corn Fieldc M-21 River Irrigated Potato Fieldc M-27 Wise residence (Highest D/Q Garden) VE, WW 0.64 mi @ 207°/SSW

a. Available Producer VE > 10.0 mi.

M-33 Monitoring Well #1 ww 593' @ 299°/WNW M-34 Monitoring Well #2 ww 749' @ 301°/WNW M-35 .Monitoring Well #3 WW 770' @ 304°/NW M-36 Monitoring Well #4 WW 0.1 mi @ 25°1NNE M-37 Monitoring Well #5 ww 0.1 mi @ 253°/WSW M-38 Monitoring Well #6 WW 229' @ 228°/SW M-39 Monitoring Well #7 WW 0.2 mi @ 66°/ENE M-40 Monitoring Well #8 WW 0.3 mi @ 150°/SSE M-41 Training Center VE 0.8 mi @ 151 */SSE M-42 Biology Station Road VE 0.6 mi @ 134°/SE M-43 C. Imholte Farm VE 12.3 mi @ 313°/NW M-44 Monitoring Well #9 WW 0.1 mi @ 310°/NW M-45 Monitoring Well #10 WW 0.1 mi @ 292°/WNW M-46 Monitoring Well #11 WW 0.1 mi @ 283°/WNW M-47 Monitoring Well #12A WW 0.1 mi @ 330°/NW M-48 Monitoring Well #12B WW 0.1 mi @ 326°/NW M-49 Monitoring Well #13A WW 0.12 mi @ 316°/NW M-50 Monitoring Well #13B WW 0.12 mi @ 316°/NW M-51 Monitoring Well #9B 0.1 mi @ 310°/NW WW Storm water Runoff 0.1 mi @ 27°/NE 14

Table .5.2. Sampling locations, Monticello Nuclear Generating Plant.

Distance and Code Typea Collection Site Sample Typeb Direction from Reactor General Area of the Site Boundary M-01A Sherburne Ave. So. TLD 0.75 mi @ 353°/N M-02A Sherbume Ave. So. TLD 0.79 mi @ 23°/NNE M-03A Sherburne Ave. So. TLD 1.29 mi @ 55°/NE M-04A Biology Station Road TLD 0.5 mi @ 86°/E M-05A Biology Station Road TLD 0.48 mi @ 118°/ESE M-06A Biology Station Road. TLD 0.54 mi @ 135°1SE M-07A County Road 75 TLD 0.5 mi @ 155°/SSE M-08A County Road 75 TLD 0.48 mi @ 1720/S Approximately 4 to 5 miles Distant from the Plant M-09A County Road 75 TLD 0.38 mi. @ 209°/SSW M-10A County Road 75 TLD 0.38 mi @ 226°/SW M-11A County Road 75 TLD 0.4 mi @ 239°/WSW M-12A County Road 75 TLD 0.5 mi @ 262°/W M-13A North Boundary Road TLD 0.89 mi @ 324°/NW M-14A North Boundary Road TLD 0.78 mi @ 334°/NNW M-01B Sherco #1 Air Station TLD 4.66 mi @ 02°/N M-02B County Road 11 TLD 4.4 mi @ 18°/NNE M-03B County Road 73 & 81 TLD 4.3 mi @ 57°/NE M-04B County Road 73 (196th St.) T"LD 4.2 mi @ 67°/ENE M-05B City of Big Lake TLD 4.3 mi @ 89°/E M-06B County Road 14 and 196th St. TLD 4.3 mi @ 117°/ESE M-07B Monte Industrial Drive TLD 4.3 mi @ 136°/SE M-08B Residence, Hwy 25 & Davidson Ave. TLD 4.6 mi @ 162°/SSE M-09B Weinand Farm TLD 4.7 mi @ 178°/S M-10B Reisewitz Farm, Acacia Ave. TLD 4.2 mi @ 204°/SSW M-11B Vanlith Farm, 97th Ave. TLD 4.0 mi @ 228°/SW M-12B Lake Maria State Park TLD 4.2 mi @ 254°/WSW M-13B Bridgewater Station TLD 4.1 mi @ 270°/W M-14B Anderson Residence, Cty Rd. 111 TLD 4.3 mi @ 289°/WNW M-15B Red Oak Wild Bird Farm TLD 4.3 mi @ 309°/NW M-16B Sand Plain Research Farm TLD 4.4 mi @ 341°/NNW 15

Table 5.2. Samplinglocations, Monticello Nuclear Generating Plant.

Distance and Code - Typea Collection Site Sample Typeb Direction from Reactor Special Interest Locations M-01S Osowski Fun Market TLD 0.66 mi @ 242°/WSW M-02S Krone Residence TLD 0.5 mi @ 224°/SW M-03S Big Oaks Park TLD 1.53 mi @ 102°/ESE M-04S Pinewood School TLD 2.3 mi @ 131 */SE M-05S Rivercrest Christian Academy TLD 3.0 mi @ 118°/ESE M-06S Monte Public Works TLD 2.6 mi @ 134°/SE M-01C C Kirchenbauer Farm TLD 11.5 mi @ 323°/NW M-02C C County Roads 4 and 15 TLD 11.2 mi @ 47°/NE M-03C C County Rd 19 and Jason Ave. TLD 11.6 mi @ 130°/SE M-04C C Maple Lake Water Tower TLD 10.3 mi @ 2260/ SW Protected Area ISFSI-1 ISFSI-1 (neutron) and 1-01 (gamma) TLD NE corner of ISFSI ISFSI-2 ISFSI-2 (neutron) and 1-02 (gamma) TLD North side of ISFSI, center ISFSI-3 ISFSI-3 (neutron) and 1-03 (gamma) TLD NW corner of ISFSI ISFSI-4 ISFSI-4 (neutron) and 1-04 (gamma) TLD West side of ISFSI, middle ISFSI-5 ISFS155 (neutron) and 1-05 (gamma) TLD West side of ISFSI, at center of array ISFSI-6 ISFSI-6 (neutron) and 1-06 (gamma) TLD SW corner of ISFSI ISFSI-7 ISFSI-7 (neutron) and 1-07 (gamma) TLD South side of ISFSI, center ISFSI-8 ISFSI-8 (neutron) and 1-08 (gamma), TLD SE corner of ISFSI ISFSI-9 ISFSI-9 (neutron) and 1-09 (gamma) TLD East side of ISFSI, at center of array ISFSI-10 .SFSI-10 (neutron) and 1-10 (gamma) TLD East side of ISFSI, middle ISFS1-1 1 ISFSI-1 1 (neutron) and I-11 (gamma) TLD OCA fence south, on exit road ISFSI-12. ISFSI-12 (neutron) and 1-12 (gamma) TLD OCA fence middle, on exit road

ISFSI-13 . ISFSI-13 (neutron) and 1-13 (gamma) TLD OCA fence north, on exit road ISFSI-14 ISFSI-14 (neutron) TLD Posted withTLD M12A ISFSI-15 ISFSI-15 (neutron) TLD Posted.with TLD M10A ISFSI-16 ISFSI-16 (neutron) TLD Posted with TLD M02S

.Neutron Control A C TLD Posted with TLD M03C Neutron Control B C TLD Posted with TLD M04C Neutron Control C C- TLD Posted with TLD M02C Neutron Control D C TLD Posted with TLD M01C a "C" denotes control location. All other locations are indicators.

o Sample Codes: AP Airborne particulates F Fish Al Airborne Iodine SW RiverWater BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms VE Vegetation / vegetables DW Drinking Water WW Well Water c Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields, 16

Table 5.3 MISSED COLLECTIONS AND ANALYSES All required samples were collected and analyzed as scheduled with the following exceptions:

Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence SW Gamma M-08 Jan, 2009 Missed due to unsafe ice. None required.

SW Gamma M-08 Feb, 2009 Missed due to unsafe ice. None required.

SW Gamma M-08 314/2009 Missed due to unsafe ice. None required.

3/11/2009 SW Gamma M-08 12/9/2009 Missed due to unsafe ice. None required.

12/16/2009 12/23/2009 12/30/2009 TLD Ambient M-01B 2nd. Qtr. Missing in the field New TLD installed.

Gamma 2009 WW Gamma M-12 3rd. Qtr. Well Out of Service Initiated work request, 2009 sampled #12 well.

AP/AI Gross Beta / M-01 12/9/2009 No sample due to faulty timer. Replaced timer.

1-131 17

Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations.

-U- Inner f 20 -- Outer-19 18 1

.152 14 10" 0

M 'IT~o.

(0 0 tN Lo 0

00 0

a 0 0 0 0

) CD 0

M 0 0 ON0 0 0

- OD 0

0) 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

- 0" 1- 04N(N ( N (N N (N (N C14 18

Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.

0.035 0.033 0.031 0.029 0.025 0.025 0.023 Om 0.02 1 0.019 0.017 0,015 O ( r- C Cý

) CD F M~ V,) 0 wf -

r0 w M)

0) 0) C) C) ) 0") 0 0 0 0 0 0 0 0 0 0 O) C) ) C) C) 0C) 0 0 0 0 0 0 0 0 0 N' e (N C. (NJ (N N~ (NJ (N (NJ (N 19

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period January-December, 2009

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse TLD (Inner Ring, Gamma 56 3.0 14.9 (56/56) M-1 1A, County Rd 75, 15.8 (4/4) (See Control 0 General Area at (11.2-17.4) 0.4 mi @ 250°/WSW (14.4-17.3) below.)

Site Boundary) mRem/91 days)

TLD (Outer Ring, Gamma 63 3.0 14.4 (63/63) M-05B, Big Lake, 15.6(4/4) (See Control 0 4-5 mi. distant) (11.3-17.3) 4.4 mi @ 87°/ESE (13.8-17.3) below.)

mRem/91 days)

TLD (Special Gamma 24 3.0 14.1 (24/24) M-06S, Mont. Pub. Wks. 16.3(4/4) (See Control 0 Interest Areas) (9.8-17.0) 2.7 mi @ 136°/SE (15.5-17.0) below.)

mRem/91 days)

TLD (Control) Gamma 16 3.0 None M-03C, Rte. 19 & Jason, 15.0 (16/16) 15.0 (16/16) 0 mRem/91 days) 11.6 mi. @ 130°/SE (12.8-16.2) (12.8-16.2)

Airborne GB 259 0.005 0.029 (208/208) M-2, Air Station 0.031 (52/52) 0.030 (51/51) 0 Particulates . (0.008-0.076) 0.8*mi @ 140°/SE (0.009-0.075) (0.008-0.101) 3 (pCi/m )

GS 20 Be-7 0.015 0.081 (16/16) M-1 (C), Air Station 0.085 (4/4) 0.085 (4/4) 0 (0.053-0.101) 11.0 mi @ 307°/NW (0.069-0.097) (0.069-0.097)

Mn-54 0.0007 < LLD - < LLD 0 Co-58 0.0008 < LLD - < LLD 0 Co-60 0.0010 < LLD - < LLD 0 Zn-65 0.0010 < LLD - < LLD 0 Zr-Nb-95 0.0010 < LLD - < LLD 0 Ru-103 0.0009 < LLD - < LLD 0 Ru-1 06 0.0074 < LLD - < LLD 0 Cs-134 0.0006 < LLD - < LLD 0 Cs-137 0.0007 < LLD - < LLD 0 Ba-La-140 0.0024 < LLD - < LLD 0 Ce-141 0.0014 < LLD - < LLD 0 Ce-1 44 0.0049 < LLD - < LLD 0 Airborne Iodine 1-131 259 0.03 < LLD < LLD 0 (pCi/mi) 20

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota ) Reporting Period January-December, 2009 County, State

(( County, State )

Indicator . Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse River Water (pCi/L) H-3 8 500 < LLD -< LLD 0 GS 22 Mn-54 10 < LLD < LLD 0 Fe-59 30 < LLD - < LLD 0 Co-58 10 < LLD < LLD 0 Co-60 10 < LLD < LLD 0 Zn-65 30 < LLD .. - <LLD 0 Zr-Nb-95 15 < LLD - < LLD 0 Cs-134 10 < LLD - < LLD 0 Cs-137 10 < LLD < LLD 0 Ba-La-140 15 < LLD - < LLD 0 Ce-144 34 < LLD -< LLD 0 Drinking Water GB 12 1.0 2.3 (12/12) M-14, Minneapolis 2.3 (12/12) None 0 (pCi/L) (1.3-3.7) 37.0 mi. @ 132'/SE (1.3-3.7) 1-131 12 1.0 < LLD None 0 H-3 4 500 < LLD None 0 GS 12 Mn-54 10 < LLD None 0 Fe-59 30 < LLD None 0 Co-58 10 < LLD None 0 Co-60 10 < LLD None 0 Zn-65 30 < LLD None 0 Zr-Nb-95 15 < LLD - None 0 Cs-134 10 < LLD - None 0 Cs-137 10 < LLD - None 0 Ba-La-140 15 < LLD - None 0 Ce-144 36 < LLD - None 0 21

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location. of Facility Wright, Minnesota Reporting Period January-December, 2009

( County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analyses' Rangec Locationd Rangec Rangec Resultse Well Water H-3 16 500 < LLD < LLD 0 (pCi/L) GS 16 Mn-54 10 < LLD <LLD 0 Fe-59 30 < LLD < LLD 0 Co-58 10 < LLD e LLD 0 Co-60 10 < LLD -< LLD 0 Zn-65 30 < LLD < LLD 0 Zr-Nb-95 15 < LLD - LLD 0 Cs-134 10 < LLD <LLD

<- 0 Cs-137 10 < LLD - . < LLD 0 Ba-La-140 15 < LLD - < LLD 0 Ce-144 47 < LLD < LLD 0 Groundwater H-3 92 500 5721 (14/92) MW-9A, Onsite, 12079(6/8) none 5 Monitoring Wells (502-21727) 0.1 mi @ 310°/NW (2145-21727)

(pCi/L) GS 92 Mn-54 10 < LLD none 0 Fe-59 30 < LLD none 0 Co-58 10 < LLD none 0 Co-60 10 < LLD none 0 Zn-65 30 < LLD none 0 Zr-Nb-95 15 < LLD none 0 Cs-134 10 < LLD none 0 Cs-137 10 < LLD none 0 Ba-La-140 15 < LLD none 0 Ce-144 49 < LLD - none 0 Stormwater H-3 4 500 985 (1/4) On-site, 985 (1/4) none 0 Runoff 0.1 mi @ 27°/NE (pCiIL) GS 4 Mn-54 10 < LLD none 0 Fe-59 30 < LLD - none 0 Co-58 10 < LLD -.- none 0 Co-60 10 < LLD - none 0 Zn-65 30 < LLD - none 0 Zr-Nb-95 15 < LLD - none 0 1-131 30 <.LLD - none 0 Cs-134 10 < LLD - none 0 Cs-137 10 < LLD - none 0 Ba-La-140 15 < LLD - none 0 Ce-144 43 < LLD - none 0 22

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period January-December, 2009 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse Crops - Cabbage GS 2 (pCi/gwet)

Mn-54 0.000 < LLD < LLD 0 Fe-59 0.000 < LLD < LLD 0 Co-58 0.000 < LLD < LLD 0 Co-60 0.000 < LLD < LLD 0 Zn-65 0.000 < LLD < LLD 0 Nb-95 0.000 < LLD < LLD 0 1-131 0.000 < LLD < LLD 0 Cs-1 34 0.000 <LLD <LLD 0 Cs-137 0.000 < LLD < LLD 0 Vegetation GS 9 (Pasture Grass, Weeds, Leaves) Mn-54 0.016 < LLD < LLD 0 Fe-59 0.040 < LLD - < LLD 0 Co-58 0.013 < LLD < LLD 0 (pCi/gwet) Co-60 0.013 < LLD < LLD 0 Zn-65 0.036 < LLD < LLD 0 Nb-95 0.018 < LLD -< LLD 0 1-131 0.027 < LLD < LLD 0 Cs-134 0.014 < LLD < LLD 0 Cs7137 0.017 < LLD < LLD 0 Fish GS 4 (pCi/g wet) K-40 0.10 3.23 (212) M-09, Downstream 3.23 (2/2) 2.92 (2/2) 0 (3.02-3.43) < 1000' of discharge (3.02-3.43) (2.73-3.11)

Mn-54 0.025 < LLD < LLD 0 Fe-59 0.047 < LLD < LLD 0 Co-58 0.017 < LLD < LLD 0 Co-60 0.017 < LLD < LLD 0 Zn-65 0.026 < LLD < LLD 0 Zr-Nb-95 0.027 < LLD < LLD 0 Cs-1 34 0.018 < LLD < LLD 0 Cs-1 37 0.020 < LLD < LLD 0 Ba-La-140 0.038 < LLD < LLD 0 Ce-144 0.13 < LLD < LLD 0 23

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263

.Location of Facility Wright, Minnesota Reporting Period January-December, 2009 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)8 Mean (F), Mean (F)8 Routine (Units) Analysesa Range' Locationd Range' Range' Resultse Invertebrates GS 2 (pCi/g wet) Be-7 0.64 < LLD < LLD 0 K-40 1.89 < LLD < LLD 0 Mn-54 0.070 < LLD - < LLD 0 Fe-59 0.090 < LLD - < LLD 0 Co-58 0.070 < LLD - < LLD 0 Co-60 0.070 < LLD - < LLD 0 Zn-65 0.14 < LLD - < LLD 0 Zr-Nb-95 0.090 < LLD <- LLD 0 Ru-103 0.070 < LLD - < LLD 0 Ru-106 0.45 < LLD - < LLD 0 Cs-134 0.060 < LLD - < LLD 0 Cs-137 0.070 < LLD - < LLD 0 Ba-La-140 0.17 < LLD - < LLD 0 Ce-144 0.37 < LLD < LLD 0 Shoreline GS 6 Sediments Be-7 0.23 0.37(114) M-15, Montissippi Park 0.37 (1/2) < LLD 0 (pCi/g dry) 1.27 mi @ 114°/ESE K-40 0.10 9.57(4/4) M-15, Montissippi Park 9.74 (2/2) 9.40 (2/2) 0 (9.26-10.07) 1.27 mi @ 114°/ESE (9.41-10.07) (9.21-9.58)

Mn-54 0.028 < LLD < LLD 0 Fe-59 0.049 < LLD < LLD 0 Co-58 0.021 < LLD < LLD 0 Co-60 0.021 < LLD < LLD 0 Zn-65 0.057 < LLD < LLD 0 Nb-95 0.028 < LLD < LLD 0 Zr-95 0.048 < LLD < LLD 0 Ru-103 0.024 < LLD < LLD 0 Ru-106 0.18 < LLD < LLD 0 Cs-134 0.024 < LLD < LLD 0 Cs-137 0.032 0.039 (1/4) M-15, Montissippi Park 0.039 (1/2) < LLD 0 1.27 mi @ 114°/ESE Ba-La-140 0.018 < LLD < LLD 0 Ce-144 0.15 < LLD < LLD 0 GB = gross beta, GS gamma scan.

b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.

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

d Locations are specified: (1) by name, and/or station code (Table 2) and (2) by distance (miles) and direction relative to reactor site.

e Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten time the typical preoperational value for the medium or location.

24

6.0 REFERENCES

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

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

Environmental, Inc., Midwest Laboratory.

2001a through 2010a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2009.

2001b through 2010b. *Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000 through 2009.

1984a to 2000a. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory) 1__

Radiation Environmental Monitoring, for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.

___ 1984b to 2000b. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)

Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.

__ 1979a to 1983a. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Monticello Nuclear Generating' Plant, Complete Analysis Data Tables, January - December, 1978 through 1982.

1979b to 1983b. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -

December, 1978 through 1982.

2009. Quality Assurance Program Manual, Rev. 2, 10 November 2009.

2009. Quality Control Procedures Manual, Rev. 2, 08 July 2009.

2009. Quality Control Program, Rev. 2, 12 November 2009.

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, Illinois, 369-382.

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

Northern States Power Company.

1969 through 1971. Monticello Nuclear Generating Plant, Environmental Radiation Monitoring Program, Annual Report, June 18, 1968 to December 31, 1968, 1969, 1970. Minneapolis, Minnesota.

1978 through 2008. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, to December 31, 1977 through 2007.

25

6.0 REFERENCES

CITED (continued)

U.S. Dep't of Energy 1997 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY.

U.S. Environmental Protection Agency.

1980. Prescribed Procedures for Measurement of Radioactivity in Drinking Water, Cincinnati, Ohio (EPA-600/4-80-032).

1984. Eastern Environmental Radiation Facility, Radiochemistry Procedures Manual, Montgomery, Alabama (EPA-520/5-84-006).

2007. RadNet, formerly Environmental Radiation Ambient Monitoring System, Gross Beta in Air, Gross Beta in Drinking Water (MN) 1981- 2005.

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

Xcel Energy Corporation.

-_ 2009 to 2010. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 and 2009. Minneapolis, Minnesota.

2009to2010. Prairie Island Nuclear. Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 and 2009.

Minneapolis, Minnesota.

26

- ! Environmental, Inc.

Midwest Laboratory anAliegheny Technologies Co.

700 Landwehr Road Northbrook, IL 60062-2310 ph. (847) 564-0700

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

January, 2009 through December, 2009

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

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

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

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

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

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

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

Complete analytical data for duplicate analyses is available upon request.

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

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

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

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

Al

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

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

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

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

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

> 100 pCi/liter 5% of known value Tritium g 4,000 pCilliter +/- lG 169.85 x (known)0 0 933

> 4,000 pCi/liter 10% of known value Radium-226,-228 > 0.1 pCi/liter 15% of known value Plutonium ? 0,1 pCi/liter, gram, or sample 10% of known value Iodine-131, s 55 pCi/liter 6 pCi/liter Iodine-129b > 55 pCi/liter 10% of known value Uranium-238, S 35 pCi/liter 6 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Techneti UM~99b Iron-55 b 50 to 100 pCi/liter 10 pCi/liter

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

b Laboratory limit.

A2

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory - ERA Control Resultb Resultc Limits Acceptance STW-1181 04106/09 Sr-89 41.0 +/- 5.8 48.3 37.8 - 55.7 Pass STW-1181 04/06109 Sr-90 32.4 +/- 2.4 31.4 22.9 - 36.4 Pass STW-1182 04/06109 Ba-133 44.6 +/- 3.1 52.7 43.4 - 58.3 Pass STW-1 182 04106/09 Co-60 81.0 +/-3.1 88.9 80.0 - 100.0 Pass STW-1 182 04/06/09 Cs-134 65.6 + 5.2 72.9 59.5 - 80.2 Pass STW-1182 .04106/09 Cs-137 147.7 +/- 5.3 168.0 151.0 - 187.0 Fail STW-1 182 04106/09 Zn-65 79.8 + 7.5 84.4 76.0 - 101.0 Pass STW-1183. 04/06/09 Gr. Alpha 47.6 + 2.1 54.2 28.3 - 67.7 Pass STW-1 183 04/06/09 Gr. Beta 38.5 + 1.3 43.5 29.1 - 50.8 Pass STW-1 184 04/06/09 1-131 24.4 +/- 2.5 26.1 21.7 -30.8 Pass STW-1185 04/06/09 Ra-226 14.0 +/- 0.7 15.1 11.2 -17.3 Pass STW-1185 04/06/09 Ra-228 14.3 +/-2.1 13.6 9.0 - 16.6 Pass STW-1 185 04/06/09 Uranium 25.0 +/- 0.2 25.7 20.6 - 28.8 Pass STW-1 186 e 04/06/09 H-3 22819.0 +/- 453.0 20300.0 17800.0 - 22300.0 Fail STW-1 193 10/05/09 Sr-89 53.0 +/- 6.0 62.2 50.2 - 70.1 Pass STW-1 193 10105/09 Sr-90 31.1 +/- 2.2 30.7 22.4 - 35.6 Pass STW-1 194 10/05/09 Ba-133 82.5 +/- 3.5 92.9 78.3 - 102.0 Pass STW-1 194 10/05/09 Co-60 116.8 +/-3.3 117.0 105,0 - 131.0- Pass STW-1 194 10/05/09 Cs-134 78.8 +/- 5.7 78.8 65.0 -87.3 Pass STW-1 194 10/05/09 Cs-137 54.2 +/- 3.7 54.6 49.1 - 62.9 Pass STW.1 194 10/05/09 Zn-65 102.5 +/- 6.2 99.5 89.6 -119.0 Pass STW-1 195 10/05/09 Gr. Alpha 20.3 +/- 2.0 23.2 11.6 -31.1, Pass STW-1 195 10/05/09 Gr. Beta 23.7 +/- 1.4 26.0 16.2 - 33.9 Pass STW-1 196 10/05/09 1-131 22.4 +/- 1.4 22.2 18,4 - 26.5 Pass STW-1197. 10105/09 Ra-226 15.0 +/-0.7 13.9 10.4 -16.0 Pass STW-1197 10/05/09 Ra-228 17.4 +/-2.0 14.9 10.0 - 18.0 Pass STW-1197 10/05/09 Uranium 32.5 +/- 0.4 33.8 27.3 - 37.8 Pass STW-1198 10/05109 H-3 17228.0 +/- 694.0 16400.0 14300.0 - 18000.0 Pass Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

0

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

0All gamma -emitters showed a low bias. A large plastic burr found on the base of the Marinelli kept the beaker from sitting directly on the detector. Result of recount in a different beaker, Cs-137, 155.33 +/- 14.55 pCi/L.

Samples were recounted and also reanalyzed. A recount of the original vials averaged 23,009 pCi/L.

Reanalysis results were acceptable, 19,170 pCi/L.

Al-1

TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLD, CaSO 4 : Dy Cards).

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

2009-1 7/6/ 2009 40 cm. 41.82 45.43 +/- 3.66 29.27 - 54.37 Pass 2009-1 7/6t 2009 50 cm. 26.76 32.17 +/- 1.52 18.73 - 34.79 Pass 2009-1 7/6/ 2009 60 cm. 18.58 20.23 +/- 1.60 13.01 -24.15 Pass 2009-1 7/6/ 2009 70 cm. 13.65 15.28 +/- 0.79 9.56 - 17.75 Pass 2009-1 7/6/ 2009 90 cm. 8.26 7.97 +/- 0.40 5.78 -10.74 Pass 2009-1 7/6/2009 90 cm. 8.26 7.37 +/- 0.49 5.78 - 10.74 Pass 2009-1 7/612009 100 cm. 6.69 6.16 +/- 0.64 4.68 - 8.70 Pass 2009-1 7/6/ 2009 110 cm. 5.53 4.38 +/- 0.24 3.87 -7.19 Pass 2009-1 7/6//2009 120 cm. 4.65 4.34 +/- 0.23 3.26 - 6.05 Pass 2009-1 7/6/'2009 150 cm. 2.97 2.92 +/- 0.25 2.08 - 3.86 Pass Environmental, Inc.

2009-2 12/2 7/2009 40 cm. 44.83 51.38 +/- 2.69 31.38 -58.28 Pass 2009-2 12/2 7/2009 50 cm. 28.69 31.65 +/- 2.81 20.08 - 37.30 Pass 2009-2 12/2 7/2009 60 cm. 19.92 21.38 +/- 1.19 13.94 -25.90 Pass 2009-2 12/2 7/2009 60 cm. 19.92 22.30 +/- 0.50 13.94 -25.90 Pass 2009-2 12/2 7/2009 75 cm. 12.75 13.48 +/- 1.02 8.93 -16.58 Pass 2009-2 12/2 7/2009 90 cm. 8.85 9.62_+/- 0,74 6.20 -11.51 Pass 2009-2 12/2 7/2009 90 cm. 8.85 8.39 +/- 0.86 6.20 -11.51 Pass 2009-2 12/2 7/2009 100 cm. 7.17 6.65 +/- 0.96 5.02 - 9.32 Pass 2009-2 12/2 7/2009 120 cm. 4.98 4.89 +/- 0.53 3.49 - 6.47 Pass 2009-2 12/2 7/2009 120 cm. 4.98 4.92 +/- 0.58 3.49 - 6.47 Pass 2009-2 1212 7/2009 150 cm. 3.19 2.74 +/- 0.39 2.23 -4.15 Pass 2009-2 12/2 7/2009 180 cm. 2.21 1.65 +/- 0.33 1.55 -2.87 Pass 2009-2 12/2 7/2009 180 cm. 2.21 2.12 +/- 0.69 1.55 -2.87 Pass A2-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 Activity Limits d Acceptance W-12009 1/20/2009 Ra-226 12.88 +/- 0.41 12.69 8.88 - 16.50 Pass W-12009 1/27/2009 Gr. Alpha 20.20 +/- 0.40 20.08 10.04 - 30.12 Pass W-12709 1/27/2009 Gr. Beta 46.26 +/- 0.42 45.60 35.60 - 55.60 Pass SPW-5553 1/27/2009 Ra-228 29.11 +/- 2.53 28.66 20.06 - 37.26 Pass SPW-217 1/29/2009 U-238 44.98 +/- 2.30 41.70 29.19 - 54,21 Pass SPW-539 2/24/2009 Ni-63 167.93 +/- 3.79 211.00 147.70 - 274.30 Pass SPW-718 3/6/2009 C-14 4893.50 +/- 21.69 4740.20 2844.12 -6636.28 Pass SPMI-814 .3/16/2009 Cs-134 34.91 +/- 3.85 35.70 25.70 - 45.70 Pass SPMI-814 3/16/2009 Cs-137 59.17 +/- 6.70 55.60 45.60 - 65.60 Pass SPMI-814 3/16/2009 Sr-90 40.82 +/- 1.59 44.07 35.26 - 52.88 Pass SPMI-815 3/16/2009 1-131 70.99 +/- 0.62 69.60 55.68 - 83.52 Pass SPMI-815 3/16/2009 1-131(G) 63.08 +/- 7.12 69.60 59.60 - 79.60 Pass SPW-817 3/16/2009 1-131 62.11 +/- 0.59 69.60 55.68 - 83.52 Pass SPW-817 3/16/2009 1-131(G) 64.55 +/- 8.32 69.60 59.60 - 79.60 Pass SPW-818 3/16/2009 Co-60 50.84 +/- 4.70 51.99 41.99 - 61.99 Pass SPW-818 ,3/16/2009 Cs-134 33.78 +/- 3.42 35.70 25.70 - 45.70 Pass SPW-81 8 .3/16/2009 Cs-137 61.27 +/- 7.18 55.64 45,64 - 65.64 Pass SPW-818 3/16/2009 Sr-90 47.26 +/- 1.89 44.07 35.26 - 52.88 Pass

SPAP-903 3/23/2009 Cs- 134 13.29 +/- 2.89 14.19 4.19 -24.19 Pass 3/23/2009 Cs-137 SPAP-903 103.24 +/- 7.54 111.23 100.11 -122.35 Pass SPCH-916 3/24/2009 1-131(G) 0.22 +/- 0.02 0.22 0.13 -0.31 Pass SPVE-888 4/1/2009 1-131(G) 0.40 +/- 0.08 0.35 0.21 - 0.49 Pass SPF-820 4/7/2009 Cs-134 0.58 +/- 0.02 0.56 0.34 - 0.78 Pass W-40909 4/9/2009 Gr. Alpha 19.26 +/- 0.40 20.08 10.04 -30.12 Pass W-40909 4/9/2009 Gr. Beta 48.04 +/- 0.42 45.60 35.60 - 55.60 Pass SPW-12641 4/10/2009 Ra-228 40.06 +/- 2.79 40.54 28.38 - 52,70 Pass SPW-1267 4/10/2009 U-238 41.71 +/- 2.25 41.70 29.19 - 54.21 Pass TWW-2124 4/21/2009 H-3 7932.00 +/- 279.00 7063.00 5650.40 -*8475.60 Pass W-42809 4/28/2009 Ra-226 14.49 +/- 0.53 16.78 11.75 - 21,81 Pass SPMI-2186 5/12/2009 Cs-134 32.55 +/- 1.26 33.89 23.89 - 43.89 Pass SPMI-2186 5/12/2009 Cs-137 54.27 +/- 2.60 55.60 45.60 - 65.60 Pass SPMI-2186 5/12/2009 1-131 60.81 +/- 0.63 52.40 40.40 - 64.40 Pass SPMI-2186 5/12/2009 1-131(G) 56.89 +/- 2.56 52.40 42.40 - 62.40 Pass SPMI-2186 5/1212009 Sr-90 43.88 +/- 1.68 52.40 41.92 - 62.88 Pass SPW-2497 5/27/2009 Fe-55 2472.37 +/- 10.76 2106.35 1685.08 - 2527.62 Pass SPW-3448 7/14/2009 Cs-137 171.06 +/- 9.21 166.10 149.49 - 182.71 Pass SPW-3497 7/15/2009 Ni-63 179.99 +/- 3.06 210.40 147.28 - 273.52 Pass

SPW-3499 7/15/2009 Tc-99 29.61 +/- 0.81 32.34 20.34 - 44.34 Pass

SPMI-3582 7/17/2009 Cs-134 32.86 +/- 3,72 31.89 21.89 -41.89 Pass SPMI-3582 7/17/2009 Cs-137 182.49 +/- 10.54 166.10 149.49 - 182.71 Pass SPAP-3595 7/17/2009 Cs-134 13.01 +/- 3.00 12.75 2.75 - 22.75 Pass SPAP-3595 7/17/2009 Cs-137 110.63 +/- 6.58 110.73 99.66 - 121.80 Pass A3-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 Activity Limitsc Acceptance SPF-3597 7/17/2009 Cs-134 0.53 +/- 0.03 0.51 0.31 - 0.71 Pass SPF-3597 7/17/2009 Cs-137 2.43 +/- 0.05 2.22 1.33 -3.10 Pass SPW-3599 7/17/2009 H-3 63246.00 +/- 725.00 62495.00 49996.00 - 74994.00 Pass SPW-1 2643 8/3/2009 Ra-228 38.18 +/- 2.72 40.54 28.38 - 52.70 Pass W-80709 8/7/2009 Ra-226 16.28 +/- 0.41 16.77 11.74 -21.80 Pass W-81 009 8/10/2009 Gr. Alpha 20.58 +/- 0.44 20.08 10.04 -30.12 Pass W-81009 8/10/2009 Gr. Beta 44.44 +/- 0.40 45.60 35.60 - 55.60 Pass W-100109 10/1/2009 Ra-226 15.68 +/- 0.41 16.77 11.74 -21.80 Pass W-1 02709 10/27/2009 Gr. Alpha 21.50 +/- 0.43 20.08 10.04 - 30.12 Pass W-102709 10/27/2009 Gr. Beta 44.83 +/- 0.40 45.60 35.60 - 55.60 Pass SPW-5964 10/28/2009 U-238 40.20 +/- 1.87 41.70 29.19 -54.21 Pass SPW-12647 11/6/2009 Ra-228 44.49 +/- 3.33 40.54 28.38 - 52.70 Pass SPAP-6769 12/14/2009 Gr. Beta 45.43 +/-0.11 49.48 29.69 - 69.27 Pass SPAP-6774 12/14/2009 Cs-1 34 10.32 +/- 0.83 11.11 1.11 -21.11 Pass SPAP-6774 12/14/2009 Cs-137 106.58 +/- 2.51 109.70 98.73 - 120.67 Pass SPF-6776 12/14/2009 Cs-1 34 0.43 +/- 0.02 0.44 0.26 - 0.62 Pass SPF-6776 12/14/2009 Cs-1 37 2.33 +/- 0.05 2.19 1.31 - 3.07 Pass SPW-6780 12/14/2009 Tc-99 30.71 +/- 1.09 32.34 20.34 - 44.34 Pass SPMI-6782 12/14/2009 Co-60 74.30 +/- 5.41 72.81 62.81 - 82.81 Pass SPMI-6782 12/14/2009 Cs-134 58.82 +/- 3.75 55.54 45.54 - 65.54 Pass SPMI-6782 12/14/2009 Cs-1 37 178.18 +/- 9.68 164.55 148.10 - 181.01 Pass SPW-6784 12/14/2009 Co-60 74.03 +/- 4.64 72.81 62.81 -82.81 Pass SPW-6784 12/14/2009 Cs-134 54.84 +/- 3.83 55.54 45.54 - 65.54 Pass SPW-6784 12/14/2009 Cs-1 37 180.06 +/- 8.81 164.55 148.10 - 181.01 Pass 8 Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/m 3), and solid samples (pCi/g).

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

CH (charcoal canister), F (fish).

c Results are based on single determinations..

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

e Control limits based on the laboratory limit, Attachment A ("Other Analyses").

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

A3-2

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

W-12009 Water 1/20/2009 Ra-226 0.05 0.06 +/- 0.04 1 SPW-5554 Water 1/27/2009 Ra-228 0.08 0.17 +/- 0.40 2 W-12709 Water 1/27/2009 Gr. Alpha 0.35 0.22 +/- 0.27 1 W-12709 Water 1/27/2009 Gr. Beta 0.74 -0.08 +/- 0.51 3.2 SPW-218 Water 1/29/2009 U-238 0.19 -0.06 +/- 0.09 1 SPW-538 Water 2/24/2009 Ni-63 7.91 4.96 +/- 4.93 20 SPW-717

Water 3/6/2009 C-14 7.66 3.03 +/- 4.71 200 SPMI-816 Milk 3/16/2009 Cs-134 3.24 10 SPMI-816 Milk 3/16/2009 Cs-1 37 3.38 10 SPMI-816 Milk 3/16/2009 1-131 0.31 0.04 +/- 0.17 0.5 SPMI-816 Milk 3/16/2009 1-131(G) 3.65 20 SPMI-816 Milk 3/16/2009 Sr-90 0.48 0.41 +/- 0.27 1 SPW-819 Water 3/16/2009 Co-60 3.02 10 SPW-819 Water 3/16/2009 Cs-134 2.25 10 SPW-819 Water 3/16/2009 Cs-137 2.03 10 SPW-819 Water 3/16/2009 1-131 0.42 -0.06 +/- 0.19 0.5 SPW-819 Water 3/16/2009 1-131(G) 3.02 20 SPW-819 Water 3/16/2009 Sr-90 1.10 -0.63 +/- 0.44 SPAP-902 Air Filter 3/23/2009 Gr. Beta 0.003 0.006 +/- 0.002 3.2 SPAP-904 Air Filter 3/23/2009 Cs-134 1.68 100 SPAP-904 Air Filter 3/23/2009 Cs-137 2.62 100 SPW-32709 Water 3/23/2009 Ni-63 2.84 1.37 +/- 1.75 20 SPF-821 Fish 4/712009 Cs-1 34 3.12 100 SPF-821 Fish 4/7/2009 Cs-137 3.93 100 W-40909 Water 4/9/2009 Gr. Alpha 0.40 -0.25 +/- 0.26 1 W-40909 Water 4/9/2009 Gr. Beta 0.77 -0.30 +/- 0.53 3.2 SPW-12651 Water 4/10/2009 Ra-228 0.77 0.77 +/- 0.45 2 SPW-1268 Water 4/10/2009 U-238 0.11 0.24 +/- 0.17 1 W-42809 Water 4/28/2009 Ra-226 0.04 0.09 +/- 0.04 1 SPMI-2186 Milk 5/12/2009 Sr-90 0.43 0.52 +/- 0.26 1 SPMI-2187 Milk 5(12/2009 Cs-134 3.61 10 SPMI-2187 Milk 5/12/2009 Cs-137 3.13 10 SPMI-2187 Milk 5/12/2009 1-131 0.15 -0.02 +/- 0.10 0.5 SPMI-2187 Milk 5/12/2009 1-131(G) 3.77 20 Water Ni-63 1.60 0.00 +/- 0.97 SPW-2498 5/27/2009 20 A4-1

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

SPW-3497 Water 7/15/2009 Ni-63 1.55 -0.24 +/- 0.94 20 S PW-3500 Water 7/15/2009 Tc-99 0.90 -1.71 +/- 0.53 10 SPMI-3589 Milk 7/17/2009 1-131(G) 5.75 20 SPAP-3594 Air Filter 7/17/2009 Cs-134 1.14 100 SPAP-3594 Air Filter 7/17/2009 Cs-1 37 2.47 100 SPF-3596 Fish 7/17/2009 Co-60 5.00 100 SPF-3596 Fish 7/17/2009 Cs1'134 8.00 100 SPF-3596 Fish 7/17/2009 Cs-137 11.50 100 SPW-3598 Water 7/17/2009 H-3 148.40 0.69 +/- 73.60 200 SPW-12653 Water 8/3/2009 Ra-228 0.76 1.46 +/- 0.51 2 W-80709 Water 8/7/2009 Ra-226 0.04 0.08 +/- 0.03 1 W-81009 Water 8/10/2009 Gr. Alpha 0.44 0.08 +/- 0.31 1 W-81009 Water 8/10/2009 Gr. Beta 0.75 -0.31 +/- 0.52 3.2 W-100109 Water 10/1/2009 Ra-226 0.04 0.09 +/- 0.03 1 W-102709 Water 10/27/2009 Gr. Alpha 0.38 0.33 +/- 0.30 1 W-102709 Water 10/27/2009 Gr. Beta 0.81 -0.59 +/- 0.55 3.2 SPW-5965 Water 10/28/2009 U-238 0.15 0.09 +/- 0.13 1 SPW-12657 Water 11/6/2009 Ra-228 0.86 0.80 +/- 0.50 2 SPAP-6769 Air Filter 12/14/2009 Gr. Beta 0.003 0.010 +/- 0.002 3.2 SPAP-6773 Air Filter 12/14/2009 Cs-137 1.31 100 SPF-6775 Fish 12/14/2009 Cs-134 5.70 100 SPF-6775 Fish 12/14/2009 Cs-137 4.18 100 SPW-6777 Water 12/14/2009 Ni-63 2.29 0.25 +/- 1.38 20 SPW-6779 Water 12/14/2009. Tc-99 1.16 -0.98 +/- 0.69 10 SPMI-6781 Milk 12/14/2009 Cs-134 2.62 10 SPMI-6781 Milk 12/14/2009 Cs-137 3.29 10 SPMI-6781 Milk 12/14/2009 1-131(G) 2.65 20 SPW-6783 Water 12/14/2009 Cs-134 2.18 10 SPW-6783 Water 12/14/2009 Cs-137 2.90 10 12/14/2009 1-131(G) 2.30 20 SPW-6783 Water Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

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

c Activity reported is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported, A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)'

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-7464, 7465 1/1/2009 Be-7 0.063 +/- 0.012 0.065 +/- 0.010 0.064 +/- 0.008 Pass E-20, 21 1/5/2009 K-40 1.34 +/- 0.21 1.13 +/- 0.13 1.24 +/- 0.12 Pass CF-67, 68 1/5/2009 Be-7 0.34 +/- 0.12 0.39 +/- 0.08 0.37 +/- 0.07 Pass CF-67, 68 1/5/2009 Gr. Beta 4.34 +/- 0.11 4.38 +/- 0.12 4.36 +/- 0.08 Pass CF-67, 68 1/5/2009 K-40 3.16 +/- 0.26 3.00 + 0.16 3.08 +/- 0.15 Pass DW-90010, 90011 1/9/2009 Ra-226 2.97 +/- 0.22 2.76 +/- 0.21 2.87 +/- 0.15 Pass DW-90010, 90011 1/9/2009 Ra-228 3.13 +/- 0.71 3.55 +/- 0.81 3.34 +/- 0.54 Pass SG-198, 199 1/23/2009 Gr. Alpha 101.90 +/- 6.50 101.70 +/- 6.10 101.80 +/- 4.46 Pass SG-198, 199 1/23/2009 Gr. Beta 97.80 +/- 3.50 94.00 +/- 3.20 95.90 +/- 2.37 Pass SW-308, 309 1/27/2009 Gr. Beta 1.43 +/- 0.58 1.41 + 0.54 1.42 +/- 0.40 Pass LW-330, 331 1/27/2009 Gr. Beta 2.09 +/- 0.58 2.33 +/- 0.63 2.21 +/- 0.43 Pass SW-308, 309 1/29/2009 Gr. Beta 1.51 +/- 0.56 1.61 +/- 0.57 1.56 +/- 0.40 Pass DW-375, 376 2/4/2009 Gr. Beta 2.72 +/- 0.65 3.06 +/- 0.69 2.89 +/- 0.47 Pass SWU-606,607 2/24/2009 Gr. Beta 2.66 +/- 0.68 2.16 +/- 0.67 2.41 +/- 0.48 Pass U-651, 652 2/27/2009 Beta-K40 3.90 +/- 2.30 1.70 +/- 2.50 2.80 +/- 1.70 Pass U-651, 652 2/27/2009 H-3 597.00 +/- 292.00 507.00 +/- 288.00 552.00 +/- 205.07 Pass SG-739, 740 3/2/2009 Ra-226 8.20 +/- 0.20 8.30 +/- 0.20 8.25 +/- 0.14 Pass MI-875, 876 3/17/2009 K-40 1286.50 +/- 111.60 1471.70 +/- 111.50 1379.10 +/- 78.88 Pass MI-875, 876 3/17/2009 Sr-90 0.67 +/- 0.31 0.36 +/- 0.36 0.52 +/- 0.24 Pass WW-970, 971 3/24/2009 Gr. Beta 13.59 +/- 2.32 17.33 +/- 2.69 15.46 +/- 1.78 Pass XWW-980, 981 3/24/2009 H-3 7143.00 + 262.00 7262.00 +/- 264.00 7202.50 +/- 185.97 Pass AP-1441, 1442 3/30/2009 Be-7 0.076 +/- 0.012 0.075 +/- 0.014 0.076 +/- 0.009 Pass SWT-1123, 1124 3/31/2009 Gr. Beta 1.40 +/- 0.55 1.86 +/- 0.62 1.63 +/- 0.41 Pass WW-1102, 1103 4/1/2009 Gr. Beta 2.13 +/- 1.34 2.30 +/- 1.32 2.22 +/- 0.94 Pass XWW-1174, 1175 4/1/2009 H-3 2814 +/- 176 2787 +/- 176 2801 +/- 124 Pass AP-1462, 1463 4/2/2009 Be-7 0.085 +/- 0.014 0.10 +/- 0.016 0.091 +/-0.011 Pass SL-2024, 2025 5/4/2009 Be-7 0.80 +/- 0.18 0.82 +/- 0.13 0.81 +/-0.11 Pass SL-2024, 2025 5/4/2009 Gr. Beta 2.41 +/- 0.19 2.68 +/- 0.21 2.55 +/- 0.14 Pass SL-2024, 2025 5/4/2009 K-40 1.20 +/- 0.21 1.30 +/- 0.15 1.25 +/-0.13 Pass SO-2045, 2046 5/4/2009 Gr. Alpha 6.22 +/- 2.87 6.50 +/- 3.26 6.36 + 2.17 Pass SO-2045, 2046 5/4/2009 Gr. Beta 28.85 +/- 3.15 30.39 +/- 3.34 29.62 +/- 2.30 Pass SO-2045, 2046 5/4/2009 Sr-90 0.036 +/- 0.010 0.024 +/- 0.010 0.030 +/- 0.007 Pass mi-2251,2252 5/14/2009 K-40 1220.60 +/- 155.10 1455.50 +/- 118.20 1338.05 +/- 97.50 Pass mi-2381, 2382 5/19/2009 K-40 1472.50 +/- 122.90 1412.80 +/- 117.40 1442.65 +/- 84.98 Pass SWT-2534, 2535 5/26/2009 Gr. Beta 1.12 +/- 0.57 1.66 + 0.58 1.39 +/- 0.41 Pass G-2626, 2627 5/28/2009 Gr.Beta 6.32 +/- 0.19 6.18 +0.19 6.25 +/- 0.13 Pass G-2626, 2627 5/28/2009 K-40 4.13 +/- 0.35 4.05 +/- 0.34 4.09 +/- 0.24 Pass WW-2732, 2733 6/1/2009 H-3 240.73 +/- 93.21 190.39 +/- 90.81 215.56 +/- 65.07 Pass A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SO-3141, 3142 6/22/2009 Ac-228 1.07 +/- 0.06 1.06 +/- 0.05 1.07 +/- 0.04 Pass SO-3141, 3142 6/22/2009 Be-7 0.55 +/- 0.14 0.62 +/- 0.08 0.59 +/- 0.08 Pass SO-3141, 3142 6/22/2009 Bi-212 1.16 +/- 0.17 1.14 +/-+0.16 1.15 +/- 0.12 Pass SO-3141, 3142 6/22/2009 Bi-214 0.96 +/- 0.03 1.01 + 0.03 0.99 +/- 0.02 Pass SO-3141, 3142 6/22/2009 Cs-137 0.72 +/- 0.07 0.76 + 0.08 0.74 +/- 0.05 Pass SO-3141, 3142 6/22/2009 Pb-212 1.00 +/- 0.02 1.03 + 0.02 1.02 +/- 0.01 Pass SO-3141, 3142 6/22/2009 Pb-214 1.01 +/- 0.03 1.04 + 0.03 1.03 +/- 0.02 Pass SO-3141, 3142 6/22/2009 Pu-239/40 0,022 +/- 0.008 0.030 +/- 0.009 0.026 +/- 0.006 Pass SO-3141, 3142 6/22/2009 .Th-232 0.51 +/- 0.04 0.48 +/- 0.05 0.50 +/- 0.03 Pass SO-3141, 3142 6/22/2009 TI-208 0.35 +/- 0.02 0.36 +/- 0.02 0.36 +/- 0.01 Pass SO-3141, 3142 6/2212009 U-233/4 0.16 +/- 0.02 0.18 +/- 0.02 0.17 00.01 Pass SO-3141, 3142 6/22/2009 U-238 0.14 +/- 0.02 0.18 +/- 0.03 0.16 + 0.02 Pass SG-3187, 3188 6/25/2009 Ac-228 11.07 +/- 0.33 10.88 +/- 0.33 10.97 +/- 0.24 Pass SG-3187, 3188 6/25/2009 Pb-214 26.54 +/- 0.23 26.17 +/- 0.25 26.36 0.17 0 Pass SL-3297, 3298 7/1/2009 Be-7 1.15 +/-0.13 1.15 +/- 0.12 1.15 - 0.09 Pass SL-3297, 3298 7/1/2009 Gr. Beta 3.38 +/- 0.23 3.37 +/- 0.12 3.38 +/- 0.13 Pass SL-3297, 3298 7/1/2009 K-40 1.43 +/-0.18 1.50 +/- 0.19 1.47 +/- 0.13 Pass AP-3944, 3945 7/1/2009 Be-7 0.064 +/- 0.009 0.068 +/- 0.010 0.066 +/- 0.007 Pass DW-90222, 90223 7/15/2009 Ra-226 5.36 +/-0.60 4.62 +/- 0.51 4.99 +/- 0.39 Pass DW-90222, 90223 7(15/2009 Ra-228 2.91 +/- 0.73 2.80 +/- 0.70 2.86 +/- 0.51 Pass DW-90237, 90238 7/17/2009 Gr. Alpha 3.54 +/- 0.99 4.22 +/- 1.09 3.88 - 0.74 Pass F-3790, 3791 7/21/2009 K-40 1.10 +/- 0.35 1.41 +/- 0.44 1.26 +/- 0.28 Pass DW-90250, 90251 7/22/2009 Ra-226 14.58 +/- 0.39 15.13 +/- 0.40 14.86 +/- 0.28 Pass DW-90250, 90251 7/22/2009 Ra-228 6.71 +/- 1.05 6.10 +/- 1.01 6.41 +/- 0.73 Pass VE-3965, 3966 7/28/2009 K-40 1.48 +/- 0,16 1.56 0.19 1.52 +/- 0.13 Pass VE-4098, 4099 8/3/2009 Be-7 0.54 +/- 0.16 0.58 +/-0.16 0.56 +/- 0.11 Pass VE-4098, 4099 8/3/2009 Gr. Beta 5.15 +/- 0.17 5.07 00.18 5.11 +/-0.12 Pass VE-4098, 4099 8/3/2009 K-40 4.91 +/- 0.49 5.17 +0.15 5.04 +/- 0.26 Pass SO-4325, 4326 8/14/2009 Be-7 0.59 +/- 0.21 0.68 +/- 0.28 0.64 _ 0.18 Pass SO-4325, 4326 8/14/2009 Cs-137 0.29 +/- 0.05 0.28 - 0.05 0.28 +/- 0.03 Pass SO-4325, 4326 8/14/2009 K-40 13.41 +/- 0.77 13.46 +/- 0.80 13.43 + 0.56 Pass SG-4283, 4284 8/17/2009 Ac-228 7.16 +/- 0.28 7.10 + 0.26 7.13 + 0.19 Pass SG-4283, 4284 8/17/2009 Pb-214 6.27 +/- 0.13 6.21 +/-0.13 6.24 +/- 0.09 Pass VE-4436, 4437 8/25/2009 K-40 2.28 +/- 0.28 2.67 +/- 0.26 2.48 +/- 0.19 Pass SL-4589, 4590 9/1/2009 Be-7 1.25 +/- 0.22 1.25 +/- 0.16 1.25 +/- 0.14 Pass SL-4589, 4590 9/1/2009 K-40 2.96 +/- 0.30 2.70 +/- 0.27 2.83 +/- 0.20 Pass AV-4882, 4883 9/8/2009 Be-7 0.93 +/- 0.18 0.95 +/- 0.17 0.94 +/- 0.12 Pass AV-4882, 4883 9/8/2009 K-40 2.50 +/- 0.26 2.47 +/- 0.29 2.49 +/- 0.20 Pass A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab.Code Date Analysis First Result Second Result Result Acceptance WW-4721,4722 9/9/2009 H-3 19191.00 +/- 404.00 18677.00 +/- 399.00 18934.00 +/- 283.91 Pass WW-4903,4904 9/11/2009 H-3 1075.00 +/- 130.00 1281.00 +/- 136.00 1178.00 +/- 94.07 Pass BS-5119, 5120 9/16/2009 Be-7 2067.50 +/- 327.90 2225.40 +/- 371.10 2146.45 + 247.61 Pass BS-5119,5120 9/16/2009 Cs-137 86.24 +/- 35.40 145.10 1 31.54 115.67 +23.71 Pass BS-5119, 5120 9/16/2009 K-40 16.85 +/- 0.90 17.27 +/- 0.79 17.06 +/- 0.60 Pass SS-5188, 5189 9/23/2009 Be-7 1.02 +/- 0.31 1.04 +/- 0.43 1.03 +/- 0.26 Pass SS-5188, 5189 9/23/2009 K-40 10.21 +/- 0.65 9.94 +/- 0.93 10.07 +/- 0.57 Pass AP-3944, 3945 9/29/2009 Be-7 0.09 +/- 0.02 0.09 +/- 0.02 0.09 +/- 0.01 Pass E-5251, 5252 10/1/2009 Gr. Beta 2.30 +/- 0.10 2.10 +/- 0.10 2.20 +/- 0.07 Pass E-5251 5252' 10/1/2009 K-40 1.18 +/- 0.24 1.15 +/- 0.18 1.17 +/- 0.15 Pass G-5272, 5273 10/1/2009 Be-7 3.31 +/- 0.29 - 3.60 +/- 0.26 3.46 +/- 0.19 Pass G-5272, 5273 10/1/2009 Gr. Alpha 19,81 +/- 0.80 21.10 +/- 0.74 20.46 +/- 0.54 Pass G-5272, 5273 10/1/2009 K-40. 16.47 +/- 0.75 17.00 +/- 0.74 16.74 +/- 0.53 Pass F-5690, 5691 10/15/2009 H-3 8895.00 +/- 250.00 9051.00 +/- 252.00 8973.00 +/- 177.49 Pass F-5690, 5691 10/15/2009 K-40 3.62 +/- 0.40 3.09 +/- 0.48 3.36 +/- 0.31 Pass DW-90396, 90397 10/16/2009 Ra-226 0.54 +/- 0.09 0.42 +/- 0.08 0.48 +/- 0.06 Pass DW-90396, 90397 10/16/2009 Ra-228. 1.44 +/- 0.56 0.94 +/- 0.51 1.19 +/- 0.38 Pass DW-90408, 90409 10/19/2009 Ra-226 0.99 +/- 0.12 1.10 +/- 0.14 1.05 +/- 0.09 Pass DW-90408, 90409 10/19/2009 Ra-228 2.76 +/- 0.66 1.38 +/- 0.92 2.07 +/- 0.57 Pass DW-90420, 90421 10/21/2009 Ra-226 .1.95 +/-0.17 1.77 +/- 0.15 1.86 +/-+0.11 Pass DW-90420, 90421 10/21/2009 Ra-228 3.10 +/- 0.73 3.32 +/- 0.80 3.21 +/- 0.54 Pass SG-5962, 5963 10/22/2009 Ac-228 16.39 +/- 0.79 16.51 +/- 0.63 16.45 +/- 0.51 Pass SG-5962, 5963 10/22/2009 Pb-214 18.03 +/- 0.41 17.74 +/- 0.42 17.89 + 0.29 Pass DW-90423, 90424 10/27/2009 Gr. Alpha 12.04 +/- 1.68 15.28 +/- 1.97 13.66 +/- 1.29, Pass ME-6116,6117 11/3/2009 Gr. Beta 0.86 +/- 0.03 0.83 +/- 0.03 0.85 +/- 0.02 Pass ME-6116, 6117 11/3/2009 K-40 2.57 +/- 0.08 2.65 +/- 0.08 2.61 +/- 0.06 Pass F-6567, 6568 11/6/2009 Gr. Beta 2.72 +/- 1.05 3.04 +/- 0.92 2.88 +/- 0,70 Pass F-6567, 6568 11/6/2009 Sr-90 0.09 +/- 0.03 0.12 +/- 0.04 0.11 +/-0.02 Pass W-6495,6496 11/8/2009 H-3 2638.00 +/- 173.00 2451.00 +/- 168.00 2544.50 +/- 120.57 Pass WW-6313,6314 11/9/2009 H-3 1514.00 +/- 137.00 1483.00 +/- 136.00 1498.50 +/- 96.52 Pass SWU-6611, 6612 11/24/2009 Gr. Beta 1.88 +/- 0.60 1.67 +/- 0.59 1.78 +/- 0.42 Pass DW-90446, 90447 12/30/2009 Ra-226 0.30 +/- 0.10 0.54 +/- 0.14 0.42 +/- 0.09 Pass DW-90446, 90447 12/30/2009 Ra-228 2.60 +/- 0.64 2.65 +/- 0.65 2.63 +/- 0.46 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

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

A5-3

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

Concentration b Known Control Lab Code C Date Analysis Laboratory result Activity Limits d Acceptance STW-1170 01/01/09 Am-241 1.15 +/- 0.06 0.64 0.45 - 0.83 Fail STW-1170 01/01/09 Co-57 19.60 +/- 0.40 18.90 13.20 - 24.60 Pass STW-1170 01/01/09 Co-60 16.60 +/- 0.30 17.21 12.05 - 22.37 Pass STW-1 170 01/01/09 Cs-134 20.40 +/- 0.50 22.50 15.80 - 29.30 Pass STW-1170 e 01/01/09 Cs-137 0.10 +/- 0.20 0.00 0.00 - 1.00 Pass STW-1170 01/01/09 Fe-55 51.60 +/- 20.60 48.20 33.70 -62.70 Pass STW-1170 01/01/09 H-3 359.90 +/- 33.90 330.90 231.60 - 430.20 Pass STW-1170 01/01/09 Mn-54 15.00 +/- 0.40 14.66 10.26 - 19,06 Pass STW-1170 01/01/09 Ni-63 50.50 +/- 3.25 53.50 37.45 - 69.55 Pass STW-1170 01/01/09 Pu-238 1.17 +/- 0.04 1.18 0.83 - 1.53 Pass STW-1170 01/01/09 Pu-239/40 0.74 +/- 0.03 0.85 0.60-1.11 Pass STW-1170 01/01/09 Sr-90 7.87 +/- 1.39 7.21 5.05 - 9.37 Pass STW-1170 01/01/09 Tc-99 12.70 + 0.80 14.46 10.12 - 18.80 Pass STW-1170 01/01/09 U-233/4 2.78 + 0.07 2.77 1.94 m3.60 Pass STW-1 170 01/01/09 U-238 2.87 + 0.07 2.88 2.02 3.74 Pass 01/01/09 Zn-65 STW-1170 14.00 +/-0.70 13.60 9.50 717.70 Pass STW-1171 01/01/09 Gr. Alpha 0.56 + 0.06 0.64 0.00 - 1.27 Pass STW-1171 01/01/09 Gr. Beta 1.29 +/- 0,05 1.27 0.64 - 1,91 Pass STSO-1 172 e 01/01/09 Co-57 0.00 +/- 0.00 0.00 0.00 - 1,00 Pass STSO-1172 01/01/09 Cs-134 458.60 +/- 7.40 467.00 327.00 - 607.00 Pass STSO-1 172 01/01/09 Cs-137 652.30 +/- 3.50 .605.00 424.00 - 787.00 Pass STSO-1 172 01/01/09 K-40 636.40 +/- 9.50 570.00 360.40 - 669.40 Pass STSO-1 172 01/01/09 Mn-54. 346.40 +/- 3.10 307.00 215.00 - 399.00 Pass STSO-1 172 01/01/09 Pu-238 28.60 +/- 2.20 25.30 17.70 - 32.90 Pass STSO- 1172 e 01/01/09 Pu-239/40 0.50 +/- 0.40 0.00 0.00-1.00 Pass STSO-1 172 01/01/09 Sr-90 180.60 +/- 12.10 257.00 180.00 - 334.00 Pass STSO-1 172 01/01/09 U-233/4 152.20 +/- 4.30 149.00 104.00 - 194.00 Pass STSO-1 172 01/01/09 U-238 154.90 +/- 4.40 155.00 109.00 - 202.00 Pass STSO-1 172 01/01/09 Zn-65 268.30 +/- 4.00 242.00 169.00 - 315.00 Pass STVE-1 173 01/01/09 Co-57 2.75 +/- 0.11 2.36 1.65 -3.07 Pass STVE-1173 01/01/09 Co-60 0.06 +/- 0.09 0.00 0.00 - 1.00 Pass STVE-1173 01/01/09 Cs-134 3.49 +/- 0.22 3.40 2.38 - 4.42 Pass STVE-1 173 01/01/09 Cs-137 1.01 +/- 0.11 0.93 0.65 - 1.21 Pass STVE-1 173 01/01/09 Mn-54 2.52 +/- 0.14 2.30 1.61 -2.99 Pass STVE-I 173 01/01/09 Zn-65 1.52 +/- 0.18 1.35 0.95 -1.76 Pass A6-1

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

b Concentration Known Control Lab Code C Date Analysis Laboratory result Activity Limits d Acceptance STAP-1174 g 01/01/09 Am-241 0.29 +/- 0.03 0.21 0.14 - 0.27 Fail STAP-1 174 01/01/09 Co-57 1.25 +/- 0.05 1.30 0.91 - 1.69 Pass STAP-1174 01/01/09 Co-60 1.17 +/- 0.06 1.22 0.85 - 1.59 Pass STAP-1174 01/01/09 Cs-134 2.67 +/- 0.14 2.93 2.05 - 3.81 Pass STAP-1174 01/01/09 Cs-137 1.53 +/- 0.08 1.52 1.06-1.98 Pass STAP-1 174 01/01/09 Mn-54 2.34 +/- 0.09 2.27 1.59 - 2.95 Pass STAP-1174 h 01101/09 Sr-90 0.93 +/- 0.14 0.64 0.45 - 0.83 Fail STAP-1174 01/01/09 Zn-65 1.44 +/- 0.14 1.36 0.95 - 1.77 Pass STAP-1175 01/01/09 Gr. Alpha 0.22 +/- 0.03 0.35 0.00 - 0.70 Pass STAP-1175 01/01/09 Gr. Beta 0.36 +/- 0.04 0.28 0.14 - 0.42 Pass STSO-1188 07/01/09 Co-57 674.60 +/- 9.00 586.00 410.00 - 762.00 Pass STSO-1 188 07/01/09 Co-60 356.40 +/- 6.30 327.00 229.00 - 425.00 Pass STSO-1 188 07/01/09 Cs-134 0.20 +/- 1.90 0.00 0.00 - 1.00 Pass STSO-1 188 07/01/09 Cs-137 767.50 +/- 12.00 669.00 468.00 - 870.00 Pass STSO-1188 07/01/09 K-40 433.00 +/- 37.20 375.00 263.00 - 488.00 Pass STSO-1 188 07/01/09 Mn-54 931.60 +/- 14.10 796.00 557.00 - 1035.00 Pass STSO-1 188 07/01/09 Pu-238 53,10 +/- 9.00 63.20 44.20 - 82.20 Pass STSO-1 188 07/01/09 Pu-239/40 107.10 +/- 12.60 116.30 81.40 -151.20 Pass STSO-1188' 07/01/09 Sr-90 310.50 +/- 12.20 455.00 319.00 - 592.00 Fail STSO-1 188 07/01/09 U-233/4 188.20 +/- 11.90 209.00 146.00 - 272.00 Pass STSO-1188 07/01/09 U-238 197.40 +/- 12.20 217.00 152.00 -282.00 Pass STSO-1 188 07/01/09 Zn-65 1433.90 +/- 25.20 1178.00 825.00 - 1531.00 Pass STAP-1189 07/01/09 Gr. Alpha 0.33 +/- 0.04 0.66 0.00 - 1.32 Pass STAP-1189 07/01/09 Gr. Beta 1.57 +/- 0.07 1.32 0.66 -1.98 Pass STAP-i 190 07/01/09 Am-241 0.01 +/- 0.02 0.00 0.01 - 0.05 Pass STAP- 1190 07/01/09 Co-57 6.78 +/- 0.27 6.48 4.54 - 8.42 Pass STAP-1 190 07/01/09 Co-60 1.06 +/- 0.18 1.03 0.72 -1.34 Pass STAP-1 190 07/01/09 Cs-134 0.01 +/- 0.06 0.00 0.01 -0.05 Pass STAP-1 190 07/01/09 Cs-137 1.49 +/- 0.27 1.40 0.98 -1.82 Pass STAP-1 190 07/01/09 Mn-54 6.00 +/- 0.45 5.49 3.84 - 7.14 Pass STAP-1 190 07/01/09 Sr-90 0.79 +/- 0.13 0.84 0.59 - 1.09 Pass STAP-1 190 07/01/09 Zn-65 4.55 +/- 0.66 3.93 2.75 - 5.11 Pass STVE-1 190 07/01/09 Co-57 8.90 +/- 0.60 8.00 5.60 - 10.40 Pass STVE-1 190 07/01/09 Co-60 2.50 +/- 0.36 2.57 1.80 - 3.34 Pass STVE-1 190 07/01/09 Cs-134 0.01 +/- 0.11 0.00 0.00 -0.10 Pass STVE- 1190 07/01/09 Cs-137 2.42 +/- 0.16 2.43 1.70 -3.16 Pass STVE-1 190 07/01/09 Mn-54 8.35 +/- 0.70 7.90 5.50 - 10.30 Pass STVE-1 190 07/01/09 Zn-65 0.01 +/- 0.26 0.00 0.00 -0.10 Pass A6-2

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

Concentration b Known Control Lab Code Date Analysis Laboratory result Activity Limits d Acceptance STW-1191 07/01/09 Gr. Alpha 0.88 +/- 0.07 1.05 0.00 -2.09 Pass STW-1191 07/01/09 Gr. Beta 7.29 +/- 0.10 7,53 3.77 -11.30 Pass STW-1192 07/01/09 Am-241 0.88 +/- 0.08 1.04 0.73 -1.35 Pass STW-1192 07/01/09 Co-57 37.20 +/- 1.50 36.60 25.60 -47.60 Pass STW-1192 07/01/09 Co-60 t15.10 0.90 15.40 10.80 - 20.00 Pass STW-1192 07/01/09 Cs-134 30.30_+/- 2.10 32.20 22.50 - 41.90 Pass STW-1192 07/01/09 Cs-137 41.90 +/- 1.80 41.20 28.80 - 53.60 Pass STW-1192 07/01/09 Fe-55 54.50 +/- 15.50 60.80 42.60 -79.00 Pass STW-1192 07101109 H-3 680.30 +/- 33.60 634.10 443.90 - 824.30 Pass STW-1192e 07/01/09 Mn-54 0.01 +/- 0.26 0.00 0.00-1.00 Pass STW-1 192 07/01/09 Ni-63 38.70 +/- 2.60 44.20 30.90 - 57.50 Pass STW-1 192 07/01/09 Pu-238 0.02 +/- 0.01 0.02 0.00 - 0.05 Pass

STW-1192 07/01/09 Pu-239/40 1.70 +/- 0.10 1.64 1.15 -2.13 Pass STW-1192 07/01/09 Sr-90 12.90 +/- 1.70 12.99 9.09 -16.89 Pass STW-1192 07/01/09 Tc-99 7.60 +/- 0.40 10.00 7.00 -13.00 Pass STW-1 192 07/01/09 Tc-99 7.60 +/- 0.40 10.00 7.00 -13.00 Pass STW-1192 07/01/09 U-233/4 2.90 t 0.10 2.96 2.07 -3.85 Pass

.STW-1192 07/01/09 U-238 3.00 + 0.10 3.03 2.12 -3.94. Pass STW-1192 07/01/09 Zn-65 28.50 +/- 2.40 26.90 18.80 -35.00 Pass Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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

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

included in the testing series as a "false positive".

f No errors were found in procedure or calculation. There was not enough sample for a reanalysis. Americium-241 in water was included in the ERA studies (Tbl. A-7) and also in the second round of MAPEP testing. Both analysis results were acceptable.

One determination was eliminated from the average, due to poor recovery. Average of three determinations, 0.25 +/- 0.03 pCi/filter.

h No reason was determined for the initial high results. The analysis was repeated; result of reanalysis; 0.54 + 0.12 Bq/filter.

Incomplete separation of strontium from calcium could result in a higher recovery percentage and consequently lower reported activity. The analysis was repeated; result of reanalysis 363.3 +/- 28.6 Bq/kg.

A6-3

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

Concentration (pCi/L)

Lab Code b. Date Analysis Laboratory ERA Control Result c Result

Limits Acceptance STAP-1 176 03t23109 Am-241 47.20 +/- 3.10 55.4 32.4 - 76.0 Pass STAP-1176 03/23/09 Co-60 543.60 +/- 8.90 490.0 379.0 - 612.0 Pass STAP-1176 03123109 Cs-134 941.30 +/- 30.70 865.0 563.0 - 1070.0 Pass STAP-1 176 03123/09 Cs-137 850.60 +/- 19.40 724.0 544.0 - 951.0 Pass STAP-1176 e 03/23/09 Mn-54 0.00 +/- 0.00 0.0 0.0 - 0.0 Pass

.STAP-1176 03/23/09 Pu-238 64.50 +/- 3.60 57.4 39.4 - 75.5 Pass STAP-1176 03/23/09 Pu-239/40 88.50 +/- 4.20 78.2 56.7 - 101.0 Pass STAP-1 176 03/23/09 Sr-90 93.90 +/- 10.00 95.3 41.9 - 148.0 Pass STAP-1176 03/23/09 U-233/4 50.00 +/- 2.47 53.5 33.7 - 79.3 Pass STAP-1176 .03/23109 U-238 50.40 +/- 2.48 53.1 34.0 - 75.4 Pass STAP-1 176 03/23/09 Uranium 101.60 +/- 5.30 109.0 55.7 - 173.0 Pass STAP-1 176 "03/23/09 Zn-65 237.30 +/- 23.70 185.0 128.0 - 256.0 Pass STAP-1 177. 03/23/09 Gr. Alpha 76.30 +/- 3.47 63.8 33.1 - 96.0 Pass STAP-1177 03/23/09 Gr. Beta 98.50 +/- 3.04 80.7 49.7 - 118.0 Pass STSO-1178 03/23/09 Ac-228 1370.00 +/- 121.00 1330.0 860.0 -1880.0 Pass STSO-1178 .03/23/09 Am-241 1853.00 +/- 185.50 1660.0 992.0 -2130.0 Pass STSO-1 178 03/23/09 Bi-212 1449.00 +/- 308.80 1550.0 406.0 -2310.0 Pass STSO-1178 .03/23/09 Bi-214 1355.00 +/- 66.20 1420.0 872.0 - 2050.0 Pass STSO-1 178 03123109 Co-60 7475.00 +/- 46.40 7520.0 5470.0 -10100.0 Pass STSO-1 178 03/23/09 Cs-134 5073.00 +/- 74.70 5170.0 3330.0 - 6220.0 Pass SSTSO-1178 03123/09 Cs- 137 5040.00 +/- 49.70 4970.0 3800.0 - 6460.0 Pass STSO-1 178 03/23/09 K-40 10884.00 +/- 292.70 11200.0 8060.0 -15100.0 Pass STSO-1 178 03/23109 Mn-54 0.00 +/- 0.00 0.0 0.0 -20.0 Pass STSO-1178 03/23/09 Pb-212 1259.00 +/- 28.40 1260.0 820.0 - 1780.0 Pass STSO-1178 03123/09 Pb-214 1464.00 +/- 56.80 1510.0 902.0 -2260.0 Pass STSO-1 178 03/23/09 Pu-238 1853.00 +/- 185.50 1590.0 910.0 -2240.0 Pass STSO-1178 03/23/09 Pu-239/40 1516.50 +/- 168.30 1360.0 928.0 - 1800.0 Pass STSO-1178 03/23/09 Sr-90 5270.90 +/- 290.20 5750.0 2080.0 - 9380.0 Pass STSO-1 178 03/23/09 U-233/4 1452.30 +/- 114.40 1600.0 1010.0 - 1990.0 Pass STSO-1178 03123/09 Uranium 3013.70 +/- 131.10 3270.0 1860.0 -4410.0 Pass STSO-1178 03/23/09 Zn-65 2083.00 +/- 59.00 1940.0 1540.0 - 2600.0 Pass A7-1

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

Concentration (pCi/L)

Lab Code b Date Analysis Laboratory ERA Control Result C Result d Limits Acceptance STVE-1 179 03/23/09 Am-241 2849.70 +/- 237.60 3660.0 2090.0 - 5030.0 Pass STVE-1 179 03/23/09 Cm-244 808.00 +/- 85.70 954.0 470.0 - 1480.0 Pass STVE-1 179 03/23/09 Co-60 1546.80 +/- 31.60 1710.0 1160.0 -2460.0 Pass STVE-i 179 03/23/09 Cs-134 1706.00 +/- 59.20 1880.0 1080.0 -2600.0 Pass STVE-1 179 03/23/09 Cs-137 1940.50 +/- 44.80 1800.0 1320.0 -2500.0 Pass STVE-1 179 03/23/09 K-40 30107.30 +/- 598.00 30800.0 22300.0 - 43700,0 Pass STVE-1 179 03/23/09 Mn-54 0.00 +/- 0.00 0.0 0.0 - 0.0 Pass STVE-1 179 03/23/09 Sr-90 6604.80 +/- 440.10 8860.0 4950.0 - 11800.0 Pass STVE-1179 03/23/09 U-233/4 1718.00 +/- 128.90 2040.0 1400.0 - 2710.0 Pass STVE-1 179 03/23/09 U-238 1718.30 +/- 128.80 2020.0 1420.0 - 2550.0 Pass STVE-1 179 03/23/09 Uranium 3499.40 +/- 371.00 4150.0 2850.0 - 5360.0 Pass STVE-1179 03/23/09 Zn-65 869.40 +/- 63.60 878,0 634.0 - 1200.0 Pass STW-1180 03/23/09 Am-241 127.50 +/- 5.10 132.0 90.4 - 178.0 Pass STW-1 180 03/23/09 Co-60 1174.10 +/- 11.70 1230.0 1070.0- 1450.0 Pass STW-1 180 03/23/09 Cs-134 742.20 +/- 18.30 790.0 584.0 - 907,0. Pass STW-1180 03/23/09 Cs-137 887.50 +/- 14.00 913.0 776.0 - 1090.0 Pass STVW-1180 03/23/09 Fe-55 323.00 +/- 362.00 492.0 286.0 - 657.0 Pass STW-1180 03/23/09 Mn-54 0.00 +/- 0.00 0.0 0.0 - 0.0 Pass STW-1180 03/23/09 Pu-238 96,60 +/- 2.20 108.0 81.7 -134.0 Pass STW-1180 03/23/09 Pu-239/40 89.50 +/- 2.10 86.3 66.8 -107.0 Pass STW-1180 03/23/09 Sr-90 763,20 +/- 12.90 834.0 530.0 -1120.0 Pass STW-1180 03/23/09 U-233/4 95,00 +/- 1.80 96.6 72.8 - 124.0 Pass STW-1180 03/23/09 U-238 97.40 +/- 1.80 95.8 73.2 -119.0 Pass STW-1180 03/23/09 Uranium 195.50 +/- 3.70 *197.0 142.0 -262.0 Pass STW-1180 03/23/09 Zn-65 653.10 +/- 24.10 631.0 535.0 - 786.0 Pass 8 Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

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

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

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

e Included in the testing series as a "false positive". No activity expected.

The analysis was repeated by leaching and total dissolution methods. Total dissolution yielded results within expected range.

Results of the reanalysis: U-233,4, 1655 +/- 95 pCi/kg. U-238 1805 +/- 97 pCi/kg.

A7-2

APPENDIX B DATA REPORTING CONVENTIONS B-1

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

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

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

3.0. Duplicate analyses If duplicate analyses are reported, the convention is as follows.

3.1 Individual results: For two analysis results; x1 +/- si and x2 +/- s2 Reported result: x +/- s; where x (1/2) (x1 + x2 ) and s = (1/2) s +2 3.2. Individual results: <L 1 , < L2 Reported result: < L, where L = lower of L1 and L2 3.3. Individual results: x +/- s, < L Reported result: x +/- s if x 2!L; < L otherwise.

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

- 1

-*Zx x s=1 x=~ ~xn-1 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 numbers 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-I

Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas.a Air (pCi/m3) Water (pCi/L)

-3 Gross alpha 1 x 10 Strontium-89 8,000 Gross beta Strontium-90 500 b

Iodine-1 31 2.8 x 10-1 Cesium-1 37 1,000 Barium-140 8,000 Iodine-1 31 1,000 Potassium-40 4,000 Gross alpha 2 Gross beta 10 6

Tritium 1 x 10 Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.

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

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

C A natural radionuclide.

C-2

MNGP APPENDIX D Sampling Location Maps D-1l

§ki IH Figure D-1, Sample Collection and Analysis program: TLD locations, Inner ring (Table 5.2).

D-2

I I

~

itI

@000 Figure D-2. Sample Collection and Analysis program: TLD locations, Outer ring (Table 5.2).

0-3

900 Figure D-3. Sample Collection and Analysis program: TLID locations, Controls (Table 5.2).

D-4

I Figure D-4. Sample Collection and Analysis Program: Radiation Environmental Monitoring Program, Milk sampling locations. (Table 5.2)

D-5

ii Figure D-5. Sample Collection and Analysis Program: Radiation Environmental Monitoring Program, Milk, Sludge, Ground Water and Shoreline sampling locations (Table 5-2.)

D-6

In 2f

-80 Nj L M/ISSIS/PPI RMIER 904.40 (september 09, 2009)

Figure D-6. Sample Collection and Analysis Program: Radiation Environmental Monitoring Program, Groundwater, Onsite monitoring well locations.

D-7

L-MT-10-032, Annual Report to the Us NRC Radiological Environmental Monitoring Program

Contents

Text

1.0 INTRODUCTION

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

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L-MT-10-032, Annual Report to the Us NRC Radiological Environmental Monitoring Program

Text

1.0 INTRODUCTION

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

6.0 REFERENCES

Navigation menu

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