L-MT-08-028, Annual Radiological Environmental Operating Report

Annual Radiological Environmental Operating Report

ML081060237
Person / Time
Site:	Monticello
Issue date:	04/11/2008
From:	O'Connor T Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
FOIA/PA-2010-0209, L-MT-08-028
Download: ML081060237 (60)

Text

N omm mitred to NUCI Monticello Nuclear Generatinq Plant Operated by Nuclear Management Company, LLC April 11, 2008 L-MT-08-028 Technical Specification 5.6.1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 2007 Annual Radiological Environmental Operating Report In accordance with the Monticello Nuclear Generating Plant Technical Specification 5.6.1, the Nuclear Management Company, LLC is submitting the Annual Radiological Environmental Operating Report for the year 2007.

This letter contains no new NRC commitments, nor does it modify any prior commitments.

Timothy J. O'Connor Site Vice President, Monticello Nuclear Generating Plant Nuclear Management Company, LLC Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce 2807 West County Road 75 Monticello, Minnesota 55362-9637 Telephone: 763-295-5151 Fax: 763-295-1454

ENCLOSURE I ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION, RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM, JANUARY 1 TO DECEMBER 31,2007 58 pages follow

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Environmental, Inc.

/ Midwest Laboratorv

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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, 2007 Prepared under Contract by ENVIRONMENTAL, Inc.

Midwest Laboratory Project No. 8010 Approved:

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 Nuclear Management Company, LLC for XCEL Energy Corporation. This report was prepared by Environmental, Inc., Midwest Laboratory.

TABLE OF CONTENTS Preface ...............................................................................................................................ii List of Tables ...................................................................................................................... iv List of Figures .....................................................................................................................v INTRODUCTION..........................................................................................................1

SUMMARY

..........................................................................................................................2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) ......................3 3.1 Program Design and Data Interpretation ...............................................................3 3.2 Program Description .............................................................................................. 4 3.3 Program Execution ................................................................................................. 5 3.4 Laboratory Procedures ..........................................................................................6 3.5 Program Modifications ...........................................................................................6 3.6 Land Use Census .................................................................................................. 6 RESULTS AND DISCUSSION ........................................................................................... 7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents ....................................7 4.2 Summary of Preoperational Data ..........................................................................7 4.3 Program Findings .................................................................................................. 8 FIGURES AND TABLES ...................................................................................................12 REFERENCES .................................................................................................................. 24 APPENDICES A InterlaboratoryComparison Program Results ....................................................................A-1 B Data Reporting Conventions .............................................................................................B-I C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area .............................................................C-I D Sampling Location Maps ...................................................................................................D.1

LIST OF TABLES

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No. Title 5.1 Sample Collection and Analysis Program ......................................................................13 5.2 Sampling Locations ........................................................................................................

14 5.3 Missed Collections and Analyses ................................................................................16 5.4 Radiation Environmental Monitoring Program Summary ...............................................19 The following tables are in the Appendices:

Appendix A A-1 Interlaboratory Comparison Program Results ...........................................................A l - I A-2 Thermoluminescent dosimeters (TLDs) ......................................................................A2-1 A-3 In-house Spiked Samples ...........................................................................................A3-1 A-4 In-house "Blank" Samples ...........................................................................................A4-1 A-5 In-house "Duplicate" Samples ................................................................................A5-1 A-6 Department of Energy MAPEP comparison results ...................................................A6-1 Attachment A: Acceptance criteria for spiked samples ....................................................A2 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas ........................................................................C-2

LIST OF FIGURES No.

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Title Paae 5-1 Offsite Ambient Radiation (TLDs), inner versus outer ring locations..........................................17 5-2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location .............................................................................................. 18 Appendix D D-I Sample collection and analysis program: TLD locations, Inner Ring ...............................................................................................................................

D-2 D-2 Sample collection and analysis program: TLD locations, Outer Ring ............................................................................................................................. 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 sampling locations ........................................................................................................... D-5 D-5 Sample collection and analysis program: Radiation Environmental Monitoring Program, Milk, Sludge, Ground water and Shoreline sampling locations ...............................................D-6

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, 2007.

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, 2007a) 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, and operated by Nuclear Management Company, LLC. Initial criticality was achieved on December 10, 1970. Full power was achieved March 5, 1971 and commercial operation began on June 30, 1971.

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 2007 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.

No effect on the environment due to the operation of the Monticello Nuclear Generating Plant is indicated.

3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

Prosram 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-137, cerium-144, 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.

Program Design and Data Interpretation (continued)

Other means 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 Descri~tion 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-131. Quarterly composites of particulate filters from each location are determined by gamma spectroscopy. One of the five locations is a control (M-I), 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 DIQ sector).

Ambient gamma radiation is monitored at forty locations, using CaS0,: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.

Milk samples are collected monthly from three farms (two indicator and one control). There are currently only two milk producers within the indicator area. Milk is collected biweekly during the growing season (May - October), because the animals may be on pasture. Samples are analyzed for iodine-131 and gamma-emitting isotopes.

Leafy green vegetables (cabbage) are collected annually from the highest DIQ garden and a control location and analyzed for iodine-131. 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. The samples are analyzed for tritium and gamma-emitting isotopes.

Twelve on-site monitoring wells were added to the program and sampled for tritium and gamma isotopic analyses. Four of the wells (M-29 to M-32) are deep water drinking wells and were only sampled until the shallow monitoring wells (M-36 to M-40) could be completed The four deep drinking wells are no longer sampled as part of the analyses program 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.

Procrram 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-131, 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 Proqram Execution The Program was executed as described in the preceding section with the following exceptions:

(1) Air Particulates IAir Iodine:

No air particulate Iair iodine samples were available from location M-4 for the week ending Sept. 5, 2007. There was no power to the substation.

Milk samples were not available from M-24 (Weinand Farm) for the November 14 and December 12 collection. The herd has been sold.

Milk samples were not available from M-28 (Hoglund Farm) June 14th through October 25th, 2007. Dairy operations were temporarily discontinued. Collections were resumed on Nov. 14,2007.

(3) Thermoluminescent Dosimeters:

The TLD for location M-1-08 was missing in the field for the second quarter, 2007.

TLDs for location M-04C and Neutron Control B were missing in the third quarter, 2007.

The TLDs for locations M-1-01 through M-1-13 and ISFSI-01 through ISFSI-10 neutron dosimeters were not installed for the third quarter, 2007, due to ISFSl construction.

TLDs for location M-12A and ISFSI-14 neutron were missing in the fourth quarter, 2007.

The TLDs for locations M-1-01 through M-1-10 and ISFSI-01 through ISFSI-10 neutron dosimeters were not installed for the fourth quarter, 2007, due to ISFSl construction.

(4) Invertebrates:

The fall collection for invertebrates was missed due to river conditions. The water was too high to safely collect samples.

(5) Ground Water:

Plant Well # I 1 could not be sampled for the second quarter, 2007, due to site problems.

A substitute sample was taken from Well #12.

Deviations from the program are summarized in Table 5.3.

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

3.5 Pronram Modifications Well Water, analysis for tritium and gamma-emitting isotopes.

Five onsite monitoring wells (M-36 through M-40) were added to the program in the fourth quarter of 2007. (Tables 5.1, 5.2).

3.6 Land Use Census In accordance with the MNGP Chemistry Manual, Procedure 1.05.41, "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 2007 land use census was conducted between September 10 and September 18,2007.

There were no sectors in which the highest DIQ value increased by greater than 20%. No changes to the sampling procedures are required.

In summary, the highest DIQ locations for nearest resident, garden and nearest milk animal did not change from the 2006 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.

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 2007. The last reported test was made by the People's Republic of China on October 16, 1980.

4.2 Summaw of Preo~erationalData 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 ra$ioactive fallout from the atmosphere. Gross 2

beta measurements in fallout averaged 20,600 pCiIm in 1969 and 12,000 pCi1m in 1970. These levels are reflected throughout the various media tested.

In the air environment, ambient gamma radiation (TLDs) averaged 9.1 mRemI4 weeks during preoperational studies (1970). Gross beta in air particulates in31969 and 1970 averaged 0.20 3

pCi1m . Present day levels have stabilized at around 0.025 pCiIm . 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-137 and Sr-90 were detected. Cs-137 levels averaged 16.7 pCilL.

Soybean crop measurements in 1969 averaged 35.5 pCilg for gross beta and 0.3 pCiIg for Cs-137. Gross beta measured in soil averaged 51.7 pCilg . 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 pCiIL. Present day environmental samples measure below detection levels. Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCilL 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 pCiIg for both upstream and downstream samples. Cs-137 activity averaged 0.10 pCiIg 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 pCilg in 1968 and 1969. Cs-137, measured in 1969 and 1970, averaged 0.044 pCilg. Gross beta background levels, in 1970, for aquatic vegetation, algae, and periphyton samples measured 86.7 pCiIg, 76.5 pCiIg, and 28.1 pCiIg respectively.

4.3 Proqram Findinns 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 (16.1 and 15.1 mRem191 days, respectively). The mean for special interest locations was 14.7 mRem191 days and the mean for the control locations was 15.5 mRem191 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1992 through 2006 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).

Ambient gamma radiation as measured by therrnolurninescentdosimetry.

Average quarterly dose rates, Inner vs. Outer Ring locations

Airborne Particulates The average annual gross beta concentrations in airborn: particulates were almost identical at indicator and control locations (0.027 and 0.028 pCi/m , respectively) and similar to levels observed from 1992 through 2006. The results are tabulated below.

Average annual gross beta concentrations in airborne particulates A spring peak in beta activity had been observed almost annually for many years (Wilson et a/.,

1969). It had been attributed to fallout of nuclides from the stratosphere (Gold et a/., 1964). It was pronounced in 1981, occurred to a lesser degree in 1982, and has not occurred since 1983.

The highest averages usually occur during the months of January and December, and the first and fourth quarters, as seen in 1992 through 2006.

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(Arnoldand Al-Salih, 1955) was detected in all samples, with an average activity of 0.077 pCi/m for all locations. All other gamma-emitting isotopes were below their respective LLD limits.

Airborne iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCi/m3 in all samples.

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Milk iodine-131 activity measured below the detection limit of 0.5 pCi1L in all samples.

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

In summary, the milk data for 2007 show no radiological effects of the plant operation.

River Water and Drinkincl Water Tritium activity measured below the LLD of 500 pCi/L in all samples. Gross beta activity in Minneapolis drinking water averaged 2.8 pCilL and was similar to average levels observed from 1992 through 2006. Gross beta averages are tabulated below.

I Year Gross Beta (pCi1L) Year Gross Beta (pCilL)

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 pCilL in all samples. Gamma isotopic results were below detection limits. The data for 2007 were consistent with previous years results and no plant operational effects were indicated.

In three of the forty-nine monitoring well samples tested, tritium was detected at an average concentration of 591 pCilL. No gamma-emitting isotopes attributable to plant operation were detected.

Cabbage was collected in September from two locations and analyzed for iodine-131. Levels of 1-131 measured below 0.034 pCi1g wet weight in both samples. Other gamma-emitting isotopes were below respective LLD levels. There was no indication of a plant effect.

There were no crops irrigated from the Mississippi River within 5 miles of the plant in 2007; therefore, no corn or potato samples were collected for analysis from irrigated fields.

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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 (3.32 and 2.77 pCilg wet weight, respectively). All gamma-emitting isotopes were below their respective LLD levels. There was no indication of a plant effect.

lnvertebrates Samples were collected in the third quarter of 2007, and analyzed for gamma-emitting isotopes.

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 May and October and analyzed for gamma-emitting isotopes. Low levels of cesium-137 were detected in three of four downstream samples, averaging, 0.083 pCi/g dry weight, and 0.030 pCi1g dry weight in one of two control samples. 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.

5.0 FIGURES AND TABLES 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 ~ r e q u e n c ~ ~FrequencyC Ambient radiation CIQ Ambient gamma (TLDs)

Airborne Particulates CNV GB, GS (QC of each location)

Airborne Iodine CNV 1-131 Milk 3 M-10 (C), M-24, M-28 Surface water GNV GS(MC), H-3(QC)

Drinking water GNV GB(MC), 1-131(MC)

GS (MC), H-3 (QC)

Well water GIQ H-3, GS On-site monitoring wells Edible cultivated crops -

Come 1 M-19 GIA GS Leafy Vegetable 2 M-27, GIA 1-131 St. Cloud Farmer's Mkt. (C) 1 M-21 GIA GS Fish (one species, edible portion)

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

Collection type is coded as follows: CI = continuous, GI = 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.

Milk is collected biweekly during the grazing season (May - October), if milch animals are on pasture.

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

Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.

Distance and Direction from Code Typea Collection Site Sample ~ y p e ~ Reactor C Air Station M-I AP, Al 11.0 mi @ 307"INW Air Station M-2 AP, Al 0.8 mi @ 14O0ISE Air Station M-3 AP, Al 0.6 mi @ 104"IESE Air Station M-4 AP, Al 0.8 mi @ 147"ISSE Air Station M-5 AP, Al 2.6 mi @ 134"ISE C Upstream of Plant Intake SW, SS, BO, F < 1000' upstream Downstream of Plant Discharge SW, SS, BO, F < 1000' downstream C Campbell Farm M, WW 10.6 mi @ 357"IN City of Monticello WW 3.3 mi @ 127"ISE Plant Well # I WW 0.26 mi @ 252"ISW City of Minneapolis DW 37.0 mi @ 13Z01SE Montissippi Park SS 1.27 mi @ 114"IESE River Irrigated Corn FieldC River lrrigated Potato FieldC Weinand Farm M 4.7 mi @ 18O0IS Wise residence (Highest DIQ Garden) VE, WW 0.64 mi @ 207"ISSW

a. Available Producer VE > 10.0 mi.

Hoglund Farm M 3.8 mi @ 30OoNVNW Warehouse #5 WW 276' @ 32"INNE Receiving Warehouse WW 0.27 mi @ 156"ISSE Site Administration Building WW 424' @ 192"ISSW Shooting Range WW 0.33 mi @ 111"IESE Monitoring Well # I WW 593' @ 299"NVNW Monitoring Well #2 WW 749' @ 301"NVNW Monitoring Well #3 WW 770' @ 304"INW Monitoring Well #4 WW 0.1 mi @ 335"INNW Monitoring Well #5 WW 0.1 mi @ 253"NVSW Monitoring Well #6 WW 229' @ 228"ISW Monitoring Well #7 WW 0.2 mi @ 66"IENE Monitoring Well #8 WW 0.3 mi @ 15O0ISSE General Area of the Site Boundary M-OIA Sherburne Ave. So. TLD M-02A Sherburne Ave. So. TL D M-03A Sherburne Ave. So. TLD M-04A Biology Station Road TLD M-05A Biology Station Road TLD M-06A Biology Station Road TLD M-07A County Road 75 TLD M-08A County Road 75 TLD M-09A County Road 75 TLD M-1OA County Road 75 TLD M-1 1A County Road 75 TLD M-12A County Road 75 TLD M-13A North Boundary Road TLD M-14A North Boundary Road TLD

Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.

Distance and Direction from Code Typea Collection Site Sample ~~~e~ Reactor Approximately 4 to 5 miles Distant from the Plant M-OIB Sherco # I Air Station TLD M-02B County Road 11 TLD M-03B County Road 73 & 81 TLD M-04B County Road 73 (196th St.) TLD M-05B City of Big Lake TLD M-06B County Road 14 and 196th St. TLD M-07B Monte Industrial Drive TLD M-08B Residence, Hwy 25 & Davidson Ave. TLD M-09B Weinand Farm TLD M-1OB Reisewitz Farm, Acacia Ave. TLD M-1 1B Vanlith Farm, 97th Ave. TLD M-12B Lake Maria State Park TLD M-13B Bridgewater Station TLD M-14B Anderson Residence, Cty Rd. 111 TLD M-15B Red Oak Wild Bird Farm TLD M-16B Sand Plain Research Farm TLD S ~ e c i aInterest l Locations Osowski Fun Market TLD Krone Residence TLD Big Oaks Park TLD Pinewood School TLD Rivercrest Christian Academy TLD Monte Public Works TLD C Kirchenbauer Farm TLD C County Roads 4 and 15 TLD C County Rd 19 and Jason Ave. TLD C Maple Lake Water Tower TLD

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a "C" denotes control location. All other locations are indicators.

Sample Codes:

AP Airborne particulates F Fish Al Airborne Iodine M Milk BS Bottom (river) sediments RW River Water BO Bottom organisms SS Shoreline Sediments DW Drinking Water VE Vegetation I vegetables WW Well Water Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields.

Table 5.3. Missed coilections and analyses at the Monticello Nuclear Generating Plant.

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 APIA1 Beta, M-04 91512007 No power to substation. None required.

1-131 MI Gamma, M-28 611412007 Hoglund Dairy temporarily out Hoglund will inform the MNGP 1-131 through of business for the summer. upon resumption of operation.

10125/2007 Operation resumed 11114/07.

MI Gamma, M-24 11/14/2007 Weinand Farm no longer None required.

1-131 1211212007 in the dairy business.

TLD Ambient M-1-08 2nd. Qtr. Missing in the field None required.

Gamma 2007 BO Gamma M-08 3rd. Qtr. Missed collection due to None required.

M-09 2007 unsafe river conditions.

TLD Ambient M-04C 3rd. Qtr. Missing in the field None required.

Gamma M-1-01 to 2007 Not installed due to ISFSl M-1-13 construction.

Neutron Control B 3rd. Qtr. Missing in the field Dosimetry ISFSI-01 to 2007 Not installed due to ISFSl ISFSI-10 construction.

TLD Ambient M-12A 4th. Qtr. Missing in the field None required.

Gamma M-1-01 to 2007 Not installed due to ISFSl M-1-10 construction.

Neutron ISFSI-14 4th. Qtr. Missing in the field Dosimetry ISFSI-01 to 2007 Not installed due to ISFSl ISFSI-10 construction.

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

1 1 - - Inner Ring 1

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

-

- r - Indicators (M-2, 3 , 4 , 5)

Control (M-I )

N r 9 b m c o t - c o m O r N ~ ~ ~ ~ ~

m m m m m m m m o o o o o o o o Z Z Z Z  ? Z  ? Z Z 8 Z E Z Z Z Z

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, 2007

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD~ Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analysesa RangeC ~ocation" RangeC RangeC Resultse TLD (Inner R~ng, Gamma 55 3.0 16.1 (55155) M-11A 18.1 (4 14) (See Control 0 General Area at ( 12.6-20.1) 0.4 mi @ 25O0NVSW (15.6-20.1) below.)

Site Boundary) mReml91 days)

TLD (Outer Ring, Gamma 64 3.0 15.1 (64164) M-079 16.5 (4 14) (See Control 0 4-5 mi. distant) ( 12.6-18.9) 4.4 mi @ 135"ISE (15.2-18.3) below.)

mReml91 days)

TLD (Special Gamma 24 3.0 14.7 (24124) M-06S, Mont. Pub. Wks. 16.8 (4 14) (See Control 0 Interest Areas) ( 10.7-18.0) 2.7 mi @ 136"ISE (15.9-18.0) below.)

mReml91 days)

TLD (Control) Gamma 15 3.0 None M-03C, County Rd.19 & 16.7 (414) 15.5 (15115) 0 mReml91 days) Jason, 11.6 mi. @ 13Oo1SE (14.9-17.7) ( 13.7-17.9)

Airborne GB 259 0.005 0.027 (2071207) M-I (C) 0.028 (52 152) 0.028 (52152) 0 Particulates (0.010-0.084) 11.0 mi @ 307"INW (0.010-0.083) (0.010-0.083)

(p~ilrn~)

GS 20 Be-7 0.015 0.076 (16116) M-5, Air Stat~on 0.087 (414) 0.078 (414) 0 (0.045-0.101) 2.6 mi @ 134"ISE (0.058-0.101) (0.065-0.093)

Mn-54 0.0009 < LLD < LLD 0 CO-58 0.0008 < LLD < LLD 0 Co-60 0.001 1 < LLD 4 LLD 0 Zn-65 0.0014 < LLD < LLD 0 Zr-Nb-95 0.0013 < LLD < LLD 0 Ru-103 0.0013 < LLD < LLD 0 Ru-106 0.0063 < LLD < LLD 0 CS-134 0.0009 < LLD < LLD 0 CS-137 0.0007 < LLD < LLD 0 Ba-La-140 0.0047 < LLD < LLD 0 Ce-141 0.0024 < LLD < LLD 0 Ce-144 0.0043 < LLD < LLD 0 Airborne Iodine 1-131 259 0.03 < LLD < LLD 0 (pci1m3)

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, 2007

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analysesa RangeC ~ocation~ Rangec RangeC Resultse Milk (pCilL) 1-131 45 0.5 < LLD < LLD 0 GS 45 K-40 200 1339 (26126) M-28 1394 (9 19) 1389 (19119) 0 (1190-1445) Hoglund Farm (1279-1445) (1313-1513)

CS-134 5 < LLD < LLD 0 CS-137 5 < LLD < LLD 0 Ba-La-140 5 < LLD < LLD 0 R~verWater H-3 8 500 < LLD < LLD 0 (pCilL)

GS 24 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 45 < LLD < LLD 0

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, 2007

( County, State )

Indicator Locat~onwith Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD~ Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analysesa RangeC ~ocat~on~ ~ange' RangeC Resultse Drinking Water GB 12 1.0 2.8 (12112) M-14, Minneapolis 2.8 (12112) None 0 (pCilL) (1.7-4.8) 37.0 mi. @ 132" ISE (1.7-4.8) 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 38 < LLD None 0 Well Water H-3 65 500 591(3165) Monitoring Well #3 634 (216) < LLD 0 (pCilL) (505-732) 770' @304" INW (535-732)

GS 65 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 54 < LLD < LLD 0 Crops - Cabbage GS 2 (pcilgwet) 1-131 0.034 < LLD < LLD 0 CS-134 0.020 < LLD < LLD 0 CS-137 0.028 < LLD < LLD 0

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, 2007

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD~ Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analysesa RangeC ~ocation~ RangeC RangeC Resultse Fish GS 4 (pCilg wet) K-40 0.10 2.77 (212) M-08, Upstream 3.32 (212) 3.32 (212) 0 (2.51-3.03) < 1000' of discharge (3.21-3.42) (3.21-3.42)

Mn-54 0.015 4 LLD < LLD 0 Fe-59 0.031 < LLD < LLD 0 CO-58 0.017 < LLD < LLD 0 Co-60 0.014 < LLD c LLD 0 Zn-65 0.033 < LLD c LLD 0 Zr-Nb-95 0.024 < LLD < LLD 0 CS-134 0.013 < LLD < LLD 0 CS-137 0.016 < LLD < LLD 0 Ba-La-140 0.087 < LLD < LLD 0 Ce-144 0.10 < LLD < LLD 0 Invertebrates GS 2 (pCilg wet) Be-7 0.76 < LLD < LLD 0 K-40 1.14 < LLD c LLD 0 Mn-54 0.063 c LLD < LLD 0 Fe-59 0.11 < LLD < LLD 0 CO-58 0.084 < LLD < LLD 0 Co-60 0.062 < LLD < LLD 0 Zn-65 0.13 < LLD < LLD 0 Zr-Nb-95 0.1 1 < LLD < LLD 0 Ru-103 0.11 < LLD < LLD 0 Ru-106 0.53 < LLD < LLD 0 CS-134 0.046 < LLD < LLD 0 CS-137 0.047 < LLD < LLD 0 Ba-La-140 0.68 < LLD < LLD 0 Ce-144 0.34 < LLD < LLD 0

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, 2007

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD~ Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analysesa ~ange' ~ocation~ ~ange' RangeC Resultse Shoreline GS 6 Sediments Be-7 0.19 0.42 (114) M-15, Montissippi Park 0.42 (112) c LLD 0 (pCi19 dry) 1.27 mi @ 114"lESE K-40 0.10 10.80 (414) M-08, Upstream 10.85 (212) 10.85 (212) 0 (9.86-11.79) < 1000' of discharge (9.67-12.03) (9.67-12.03)

Mn-54 0.020 < LLD c LLD 0 Fe-59 0.070 c LLD c LLD 0 CO-58 0.021 < LLD < LLD 0 Co-60 0.014 c LLD c LLD 0 Zn-65 0.045 < LLD < LLD 0 Nb-95 0.028 < LLD c LLD 0 Zr-95 0.037 < LLD c LLD 0 Ru-103 0.026 c LLD < LLD 0 Ru-106 0.16 < LLD < LLD 0 CS-134 0.016 < LLD < LLD 0 Cs-137 0.01 6 0.083 (314) M-09, Downstream 0.120 (112) 0.030 (112) 0 (0.043-0.120) < 1000' of discharge Ba-La-140 0.062 c LLD c LLD 0 Ce-I 44 0.10 < LLD < LLD 0 a GB = gross beta, GS = gamma scan.

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

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

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

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.

6.0 REFERENCES

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

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

Environmental, Inc., Midwest Laboratory.

2001a through 2008a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2007.

2001b through 2008b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000 through 2007.

2003. Quality Assurance Program Manual, Rev. 1, 01 October 2003.

2005. Quality Control Procedures Manual, Rev. 0, 17 September 2005.

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

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

Hazleton Environmental Sciences Corporation.

1979a through 1983a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.

1979b through 1983b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.

Hohenemser, C. M. Deicher, A. Emst, H. Hofsass, G. Lindner, E. Racknagel, 1986. "Chernobyl," Chemtech, October 1986, pp. 596-605.

National Center for Radiological Health, 1968. Radiological Helath 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.

Northern States Power Company.

Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S.

Nuclear Regulatory Commission, January 1, to December 31, 1977 through 1982 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

1984 through 2000. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1983 through 1999 (prepared by Teledyne Brown Engineering Environmental Services, Midwest Laboratory). Northbrook, Illinois

REFERENCES CITED (continued)

Teledyne Brown Engineering Environmental Services, Midwest Laboratory.

1984a to 2000a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.

1984b to 2000b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.

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-60014-80-032).

1984. Eastem Environmental Radiation Facility, Radiochemistry Procedures Manual, Montgomery, Alabama (EPA-52015-84-006).

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.

2008. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2000 through 2007. (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois

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700 Landwehr Road Northbock, 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 through December, 2007

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

The results in Table A-2 list results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and 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 NlST traceable sources. Data for previous years available upon request.

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

Table A-5 lists REMP specific analytical results from the in-house "duplicate" program for the past twelve month:

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 acceptance criteria for "spiked" samples.

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

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One standard deviation Analvsis Level for sinale determination Gamma Emitters 5 to 100 pcilliter or kg 5.0 pcilliter

> 100 pcilliter or kg 5% of known value 5.0 pcilliter 10% of known value 5.0 pcilliter 10% of known value Potassium40 2 0.1 glliter or kg 5% of known value Gross alpha 5.0 pcilliter 25% of known value Gross beta 5.0 pCi1liter 5% of known value Tritium *lo =

169.85 x ( k n o ~ n ) ~ . ~ ~ ~ ~

1O0/0 of known value 15% of known value Plutonium r 0.1 pcilliter, gram, or sample 10% of known value 6.0 pcilliter 10% of known value 6.0 pcilliter 15% of known value 10 pcilliter 10% of known value 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program, Fiscal Year, 1981-1982, EPA-60014-81-004.

Laboratory limit.

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

Concentration (pCilL)

Lab Code Date Analysis Laboratory ERA Control

~esult~ ResultC Limits Acceptance STW-1121 Sr-89 +

30.7 4.3 35.4 26.7 - 44.1 Pass STW-1121 Sr-90 +

39.3 1.8 42.1 33.4 - 50.8 Pass STW-1122 Ba-133 +

30.0 2.4 29.3 20.6 - 38.0 Pass STW-1122 Co-60 118.5 ? 3.9 119.0 109.0 - 129.0 Pass STW-1122 CS-134 +

52.6 2.3 54.3 45.6 - 63.0 Pass STW-1122 CS-137 +

49.5 3.8 50.3 41.6 - 59.0 Pass STW-I 122 Zn-65 +

91.7 6.3 88.6 73.3 - 104.0 Pass STW-1123 Gr. Alpha +

33.8 3.5 56.5 32.0 - 81.O Pass STW-1123 Gr. Beta 24.2 f 2.3 25.3 16.6 - 34.0 Pass STW-1124 1-131 +

19.2 1.2 18.9 13.7 - 24.1 Pass STW-1125 H-3 +

7540.0 255.0 8060.0 6660.0 - 9450.0 Pass STW-1125 Ra-226 +

13.0 0.6 13.4 9.9 - 16.9 Pass STW-1125 Ra-228 +

19.9 2.7 18.2 10.3 - 26.1 Pass STW-1125 Uranium +

4.5 0.2 4.6 0.0 - 9.8 Pass Sr-89 Pass Sr-90 Pass Ba-133 Pass Co-60 Pass Cs-134 Pass Cs-137 Pass Zn-65 Pass Gr. Alpha Pass Gr. Beta Pass Ra-226 Pass Ra-228 Pass Uranium Pass Sr-89 Pass Sr-90 Pass Ba-133 Pass Co-60 Pass CS-134 Pass CS-137 Pass Zn-65 Pass Gr. Alpha Pass Gr. Beta Pass 1-131 Pass H-3 Pass Ra-226 Pass Ra-228 Pass Uranium Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for profic~ency testing in drinking water conducted by Environmental Resources Associates (ERA).

+

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.

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

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

30 cm. Pass 40 cm. Pass 50 cm. Pass 60 cm. Pass 70 cm. Pass 80 cm. Pass 90 cm. Pass 100 cm. Pass 110 cm. Pass 120 cm. Pass 150 cm. Pass Environmental. Inc.

2007-2 1111212007 30 cm. Pass 2007-2 1111212007 40 cm. Pass 2007-2 1111212007 60 cm. Pass 2007-2 1111212007 70 cm. Pass 2007-2 1111212007 80 cm. Pass 2007-2 1111212007 90 cm. Pass 2007-2 1111212007 110 cm. Pass 2007-2 1111212007 120 cm. Pass 2007-2 1111212007 120 cm. Pass 2007-2 1111212007 150 cm. Pass 2007-2 1111212007 180 cm. Pass

TABLE A-3. In-House "Spike" Samples Concentration I D C ~ / L ) ~

Lab Code iabowioiy iesiiils Known Conlroi 2s, n=l Activity Limits Acceptance Gr. Alpha Pass Gr. Beta Pass Cs-I 34 Pass CS-137 Pass H-3 Pass Tc-99 Pass CS-134 Pass CS-137 Pass I-131(G) Pass 1-131 Pass 1-131 Pass Cs-134 Pass Cs-137 Pass 1-131(G) Pass 1-131 Pass 1-131 Pass 1-131(G) Pass CS-134 Pass CS-137 Pass 1-131(G) Pass Cs-134 Pass CS-137 Pass 1-131(G) Pass 1-131(G) Pass 1-131 Pass Sr-89 Pass Sr-89 Pass 1-131 Pass Fe-55 Fail H-3 Pass Gr. Beta Pass CS-134 Pass CS-137 Pass Cs-134 Pass CS-137 Pass Ni-63 Pass Gr. Alpha Pass Gr. Beta Pass Tc-99 Pass Ni-63 Pass Gr. Alpha Pass Gr. Beta Pass

TABLE A-3. In-House "Spike" Samples Concentration (PC~IL)~

Date Anaiysis Laboratory resuits Known Coniroi 2s, n=lb Activity LimitsC Acceptance SPW-6880 Tc-99 Pass W-111007 Gr. Alpha Pass W-111007 Gr. Beta Pass SPAP-7742 Cs-134 Pass SPAP-7742 CS-137 Pass SPAP-7744 Gr. Beta Pass SPMI-7746 Cs-134 Pass SPM 1-7746 CS-137 Pass SPMI-7746 Sr-90 Pass SPW-7748 Cs-134 Pass SPW-7748 Cs-I 37 Pass SPW-7748 Sr-90 Pass SPW-7752 Fe-55 Pass SPW-7758 H-3 Pass SPF-7760 Cs-134 Pass SPF-7760 CS-137 Pass SPW-8034 Ni-63 Pass a Liquid sample results are reported in pCilLiter, air filters( pcilfilter), charcoal (p~ilm3),

and solid samples (pcilg).

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

CH (charcoal canister), F (fish).

Results are based on single determinations.

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

Sample recount: 12557 f 335.

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

TABLE A-4. In-House "Blank" Samples

-- -

Concentration ( D C ~ / L ) ~

Lab Code Sample Date ~nal~sis~ Laboratory results (4.660) Acceptance Type LLD ActivityC Criteria (4.66 o)

W-30707 water 3/7/2007 Gr. Alpha 0.40 +

0.01 0.28 2 W-30707 water 3/7/2007 Gr. Beta 0.75 0.06 r 0.53 4 SPAP-1567 Air Filter 3/23/2007 Cs-134 0.79 100 SPW-1567 Air Filter 3/23/2007 Cs-137 1.01 100 SPW-I 568 water 3/23/2007 H-3 176.10 -26.16 + 91.62 200 water Cs-134 water Cs-137 water 1-131 water 1-131(G)

Milk Cs-I 34 Milk Cs-137 Milk 1-131 Milk I-131(G)

Charcoal Canister 1-131(G) water CS-134 water Cs-137 water I-131(G)

Milk Cs-I 34 Milk CS-I37 Milk 1-131(G) water 1-131 water Sr-89 water Sr-90 Milk 1-131 Milk Sr-89 Milk Sr-90 Air Filter Gr. Beta Air Filter Cs-134 Air Filter Cs-137 Fish CS-I34 Fish CS-137 water Ni-63 water Gr. Alpha water Gr. Beta water 7118/2007 Tc-99 6.41 -3.12 It 3.84 water 811712007 Ni-63 1.48 +

4.38 1.01 water 9/21/2007 Gr. Alpha 0.41 +

0.09 0.29 water 9/21/2007 Gr. Beta 0.75 +

-0.26 0.51

TABLE A-4. In-House "Blank" Samples Concentration [DC~IL)~

Lab Code Sample Date ~nalysis~ Laboratory results (4.660) Acceptance Type LLD ActivityC Criteria (4.66 0) water Tc-99 Air Filter Gr. Beta Milk CS-134 Milk CS-137 Milk 1-131(G)

Milk Sr-90 water CS-134 water Cs-I 37 water 1-131(G) water Sr-90 water Fe-55 water H-3 Fish CS-134 Fish Cs-137 water Ni-63 water Gr. Alpha water Gr. Beta a Liquid sample results are reported in pCilLiter, air filters( pcilfilter), charcoal (pcilcharcoal canister), and solid samples (pcilkg).

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

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

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

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

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance Gr. Beta Pass K-40 Pass Gr. Beta Pass K-40 Pass Sr-90 Pass H-3 \\ Pass Gr. Beta Pass Gr. Alpha Pass Gr. Alpha Pass Gr. Alpha Pass Gr. Alpha Pass Gr. Beta Pass Gr. Alpha Pass Gr. Alpha Pass Gr. Beta Pass Gr. Alpha Pass K-40 Pass Gr. Beta Pass H-3 Pass K-40 Pass Gr. Alpha Pass Gr. Beta Pass Gr. Alpha Pass Gr. Alpha Pass Gr. Beta Pass Gr. Alpha Pass Gr. Alpha Pass Gr. Beta Pass Gr. Alpha Pass Gr. Beta Pass Gr. Alpha Pass Gr. Beta Pass Gr. Alpha Pass Gr. Beta Pass Gr. Beta Pass Gr. Alpha Pass Gr. Beta Pass H-3 Pass K-40 Pass Gr. Alpha Pass Gr. Alpha Pass Gr. Beta Pass Gr. Beta Pass

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

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance K-40 Pass Sr-90 Pass Be-7 Pass H-3 Pass Be-7 Pass Be-7 Pass Gr. Alpha Pass Gr. Beta Pass Gr. Alpha Pass Gr. Beta Pass Gr. Alpha Pass Gr. Beta Pass H-3 Pass Gr. Alpha Pass Gr. Beta Pass Gr. Alpha Pass Gr. Beta Pass Gr. Alpha Pass Gr. Alpha Pass H-3 Pass Gr. Beta Pass Gr. Beta Pass Be-7 Pass CS-137 Pass K-40 Pass Gr. Alpha Pass Gr. Beta Pass Sr-90 Pass H-3 Pass K-40 Pass Gr. Beta Pass Cs-137 Pass K-40 Pass K-40 Pass Gr. Beta Pass 1-131 Pass CS-137 Pass Gr. Beta Pass K-40 Pass K-40 Pass Be-7 Pass K-40 Pass

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

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance Be-7 Pass Gr. Beta Pass K-40 Pass Gr. Beta Pass H-3 Pass Gr. Alpha Pass Gr. Beta Pass Be-7 Pass Be-7 Pass CS-137 Pass Gr. Beta Pass K-40 Pass Gr. Beta Pass Gr. Alpha Pass Gr. Beta Pass Be-7 Pass Be-7 Pass Be-7 Pass Cs-137 Pass Gr. Alpha Pass Gr. Beta Pass K-40 Pass Gr. Beta Pass Gr. Alpha Pass H-3 Pass K-40 Pass Be-7 Pass Gr. Beta Pass K-40 Pass Gr. Alpha Pass Gr. Beta Pass 1-131 Pass CS-137 Pass Gr. Alpha Pass Gr. Beta Pass K-40 Pass H-3 Pass Gr. Beta Pass H-3 Pass H-3 Pass

TABLE A-5. In-House "Duplicate" Samples Concentration (PC~IL)~

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance K-40 Pass H-3 Pass Gr. Beta Pass Gr. Alpha Pass Be-7 Pass K-40 Pass Gr. Beta Pass K-40 Pass K-40 Pass Sr-90 Pass Gr. Alpha Pass Gr. Beta Pass H-3 Pass CS-137 Pass Gr. Beta Pass K-40 Pass Gr. Beta Pass Gr. Beta Pass K-40 Pass Gr. Beta Pass H-3 Pass Gr. Alpha Pass Gr. Beta Pass Be-7 Pass H-3 Pass H-3 Pass Gr. Alpha Pass Gr. Beta Pass K-40 Pass Gr. Beta Pass K-40 Pass Gr. Beta Pass K-40 Pass Sr-90 Pass K-40 Pass H-3 Pass K-40 Pass H-3 Pass Gr. Alpha Pass CS-I37 Pass Gr. Beta Pass K-40 Pass

TABLE A-5. In-House "Duplicate" Samples Concentration (DC~IL)~

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance Cs-137 Pass K-40 Pass Gr. Beta Pass Gr. Beta Pass K-40 Pass Gr. Alpha Pass Gr. Beta Pass K-40 Pass 1-131 Pass K-40 Pass Gr. Beta Pass Gr. Beta Pass Gr. Beta Pass H-3 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 pCilL, except for air filters (pCiIFilter), food products, vegetation, soil, sediment (pCi1g).

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

Concentration iinown Controi Lab CodeC Date Analysis Laboratory result Activity Limits Acceptance STW-1110 01101107 Gr. Alpha +

0.45 0.08 0.33 0.00 - 0.65 Pass STW-1110 01101/07 Gr. Beta 0.90 -1 0.14 0.85 0.43 - 1.28 Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STSO-1 112 ' 01/01/07 Am-241 46.40 + 9.00 34.80 24.40 - 45.20 Fail STSO-1112 01/01/07 CO-57 501.20 +_ 2.90 471.20 329.80 - 612.60 Pass STSO-1112 01101107 CO-60 285.90 + 2.10 274.70 192.30 - 357.10 Pass STSO-1 112 01101107 Cs-134 325.90 + 7.40 327.40 229.20 - 425.60 Pass STSO-1112 01/01/07 CS-I37 855.70 + 4.60 799.70 559.80 - 1039.60 Pass STSO-1112 01/01107 Mn-54 750.90 + 4.70 685.20 479.60 - 890.80 Pass STAP-1113 01/01107 Gr. Alpha 0.27 + 0.04 0.60 0.00 - 1.20 Pass STAP-1113 01101107 Gr. Beta 0.57 _+ 0.05 0.44 0.22 - 0.66 Pass STAP-1114 Pass STAP-1114 Pass STAP-1114 Pass STAP-1114 Pass STAP-1114 Pass STAP- 1114 Pass STAP-1114 Pass STAP-1114 Pass STAP-1114 Pass STAP-1114 Pass STAP- 1114 Pass STAP-1114 Pass

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

Concentration "

Known Control Lab CodeC Date Analysis Laboratory result Activity Limits Acceptance STVE-1115 01/01/07 Co-57 8.90 k 0.20 8.19 5.73 - 10.64 Pass SNE-1115 01/01/07 CO-60 6.50 k 0.20 5.82 4.08 - 7.57 Pass SNE-1115 01/01/07 Cs-134 +

6.90 0.30 6.21 4.35 - 8.07 Pass SNE-1125 01101/07 CS-137 8.20 k 0.30 6.99 4.90 - 9.09 Pass SNE-1115 01/01/07 Mn-54 10.10 k 0.30 8.46 5.91 - 10.98 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a part~cipantin the Department of Energy's Mixed Analyte Performance Evaluation Program, ldaho Operations office, ldaho Falls, ldaho Results are reported in units of Bqlkg (soil), BqlL (water) or Bqltotal sample (filters, vegetation).

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

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

Result of reanalysis, 2.08 f 0.13 pCilL.

'The test samples were recounted on lower background detectors. Result of the recounts: 41.4

• 6.3 Bqlkg.

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

Concentration (pCilL)

Lab Code Date Analysis Laboratory ERA Control Result Result a Limits Acceptance Gr. Alpha Pass Gr. Beta Pass Am-241 Pass Co-60 Pass Cs-134 Pass CS-137 Fail Fe-55 Pass Mn-54 Pass Pu-238 Pass Pu-239140 Pass Sr-90 Pass U-23314 Pass U-238 Pass Uranium Pass Zn-65 Pass Ac-228 Pass Am-241 Pass Bi-212 Pass Co-60 Pass CS-134 Pass CS-137 Pass K-40 Pass Mn-54 Pass Pb-212 Pass Pb-214 Pass Pu-238 Pass Pu-239140 Pass S r-90 Pass Th-234 Pass U-23314 Pass U-238 Pass Uranium Pass Uranium Pass Zn-65 Pass

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

Concentration (pCilL)

Lab Code Date Analysis Laboratory ERA Control Result Result a Limits Acceptance Am-241 Pass Cm-244 Pass Co-60 Pass Cs-134 Pass CS-137 Pass K-40 Pass Mn-54 Pass Pu-238 Pass Pu-239140 Pass Sr-90 Pass U-23314 Pass U-238 Pass Uranium Pass Zn-65 Pass Am-241 Pass Co-60 Pass Cs-134 Pass CS-137 Pass Fe-55 Pass Mn-54 Pass Pu-238 Pass Pu-239140 Pass Sr-90 Pass U-23314 Pass U-238 Pass Uranium Pass Zn-65 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

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

Unless otherwise indicated, the laboratory result is given as the mean k 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.

'A high bias (- 20%) was observed in gamma results for air filters. A composite filter geometry was used in the calculations vs. a single filter geometry. Result of recalculation. Cs-137, 305.8 f 6.0 pcilfilter.

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

APPENDIX B DATA REPORTING CONVENTIONS

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

2.0. Sinale Measurements Each single measurement is reported as follows: x fs where: x = value of the measurement; s = 20 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 4.660 uncertainty for a background sample.

3.0. Duplicate analyses 3.1 Individual results: For two analysis results; x, f s, and x, f s, Reported result: x k s; where x = (112) (x, + x,) and s = (112) dm 3.2. Individual results: '4 , < L~ Reported result: < L, where L = lower of L, and L, 3.3. Individual results: xfs,<L Reported result: x +s if x r L; < L otherwise.

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

4.2 Values below the highest lower limit of detection are not included in the average.

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

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

4.5 In rounding off, the following rules are followed:

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

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

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

Table C-I Maximurr! permissib!e cnncentratisns c? radieactivity in air and water a b s e i i ~ t i i i a l background in unrestricted areasa.

- --

Air ( p ~ i l m 3 ) Water (pCilL)

Gmss alpha Ix 10-3 Strontium-89 Gross beta 1 Strontium-90 b

Iodine-I 31 2.8 x lo-' Cesium-137 Barium-140 Iodine-I 31 Potassium-40 Gross alpha Gross beta Tritium a

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

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

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

C A natural radionuclide.

APPENDIX D Sampling Location Maps

Figure D-I, Sample Coliection and Analysis program: TLD locations, Inner ring (Table 5.2).

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

D-3

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

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