Text

Annual Radiological Environment Environmental Monitoring Program (REMP) Report
	ML062190037
Person / Time
Site:	Prairie Island
Issue date:	05/06/2006
From:	Thomas J. Palmisano; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	FOIA/PA-2010-0209, L-PI-06-037
	Download: ML062190037 (61)
	v • d • e

Prairie Island Nuclear Generating Plant Operated by Nuclear Management Company, LLC MAY 0 6 2006 L-PI-06-037 TS 5.6.2 ISFSI TS 6.2 U S Nuclear Regulatory Commission AlTN: Document Control Desk Washington, DC 20555 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282, 50-306 and 72-10 License Nos. DPR-42, DPR-60 and SNM-2506 2005 Annual Radioloqical Environmental Monitorinq Proqram (REMP) ReDort Pursuant to Prairie Island Nuclear Generating Plant (PINGP) Technical Specification (TS) 5.6.2, Appendix A to Operating Licenses DPR-42 and DPR-60, and pursuant to Prairie Island Independent Spent Fuel Storage Installation Technical Specification (ISFSI TS) 6.2, Appendix A to Materials License SNM-2506, the Nuclear Management Company, LLC submits one copy of the Annual Radiological Environmental Monitoring Program report for the period January 1,2005 through December 31,2005.

Summan, of Commitments This letter contains no new commitments and no revisions to existing commitments.

Thomas J. Palmisano Site Vice President, Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC Enclosure (1) cc:

Regional Administrator, USNRC, Region 111 Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector - Prairie Island Nuclear Generating Plant Dr. John House, USNRC, Region 111 Director of NMSS, USNRC Tim Donakowski, State of Minnesota PI Dakota Community Environmental Coordinator 1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1121

ENCLOSURE 1 Annual Report to the United States Nuclear Regulatory Commission Radiation Environmental Monitoring Program January 1.2005 through December 31,2005 59 pages to follow

Midwest Laboratory

/ M Y ~ T e d m d w & S c D.

XCEL ENERGY CORPORATLON PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306 DPRSO ISFSI Docket No.72-10 SNM-2506 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1 to December 31,2005 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 members of the staff of the Prairie Island Nuclear Generating Plant, operated by Nuclear Management Company, LLC for XCEL Energy Corporation.

The report was prepared by Environmental, Inc., Midwest Laboratory.

il

TABLE OF CONTENTS Preface.............................................................................................................................................

ii List of Tables................................................................................................................................... iv List of Figures...................................................................................................................................

v 1.O INTRODUCTION..............................................................................................................................

1 2.0

SUMMARY

2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP)............................................

3 3.1 Program Design and Data Interpretation................................................................................

3 3.3 Program Execution.................................................................................................................

5 3.4 Laboratory Procedures............................................................................................................

5 3.5 Program Modifications....................................................................................................

3.6 Land Use Census...................................................................................................................

6 4.0 RESULTS AND DISCUSSION....................................................

7 3.2 Program Descrlption............................................................................................................... 4 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents.....................................................

7 4.2 Summary of Preoperational Data............................................................................................

7 4.3 Program Findings...............................................................

8 5.0

6.0 REFERENCES

CITED................................................................................................................... 2 5 FIGURES AND TABLES................................................................................................................

12 APPENDICES A

Interlaboratory Comparison Program Results..................................

A-1, Acceptance Criteria for "Spiked" Samples....

B Data Reporting Conventions

............... 8-1 C

Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas...................................

D Sampling Location Maps............................................................................

iii

LIST OF TABLES No.

Title 5.1 Sample Collection and Analysis Program..........................................................................................

15 5.2 Sampling Locations............................................................................................................................

16 5.3 Missed Collections and Analyses.......................................................................................................

19 5.4 Radiation Environmental Monitoring Program Summary...................................................................

20 In addition. the following tables are in the Appendices:

ADDendix A A-I A-2 A-3 A 4 A-5 A-6 Environmental Resources Associates. Crosscheck Program Results..........................................

AI-I Program Results; (TLDs)................................................................................................................. - 1 In-house "Spiked" Samples...........................................................................................................

A3-1 In-house "Blank" Samples..............................................................................................................

A4-1 In-house "Duplicate" Samples........................................................................................................

A5-1 Department of Energy MAPEP comparison results.......................................................................

A6-1 ADDendix C C-I Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas...........................................................................

C-2 iv

LIST OF FIGURES No.

Title 5.1 Offsite Ambient Radiation (TLDs). average of inner and outer ring indicator 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control......................................................................................................................

13 locations (P-2,3,4,6) versus control location (P-I)..............................................................................

14 V

1.O INTRODUCTION This report summarizes and interprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 2005. 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.

Tabulations 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, 2006b) available at Prairie Island Nuclear Generating Plant.

Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, owned by Xcel Energy Corporation and operated by Nuclear Management Company, LLC. The plant has two 575 MWe pressurized water reactors. Unit 1 achieved initial criticality on 1 December 1973. Commercial operation at full power began on 16 December 1973.

Commercial operation at full power began on 21 December 1974.

Unit 2 achieved initial criticality on 17 December 1974.

1

2.0

SUMMARY

The Radiation Environmental Monitoring Program (REMP) required by the US. Nuclear Regulatory Commission (NRC) Technical Specifications for the Prairie Island Nuclear Generating Plant and the Independent Spent Fuel Storage Installation (ISFSI) is described.

Results for 2005 are summarized and discussed.

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

2

3.0 g )

3.1 Program Desian and Data Interpretation The purpose of the Radiation Environmental Monitoring Program (REMP) at the Prairie Island 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 (TLDs).

Sources of environmental radiation include the following:

(1)

(2)

(3)

(4)

(5)

Fallout from nuclear accidents.

Natural background radiation arising from cosmic rays and primordial radionuclides; Fallout from atmospheric nuclear detonations; Releases from nuclear power plants; Industrial and medical radioactive waste; and In interpreting the data, effects due to the plant must be distinguished from those due to other A major interpretive aid in assessment of these effects is the design of the monitoring program at the Prairie Island Plant which is based on the indicatorcontrol 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 the 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-I 37, 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 potassium40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered 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-%. 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.

sources.

3

3.1 Proaram Desian and Data Intemretation (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.9.. atmospheric nuclear detonations.

3.2 Proaram DescriDtion The sampling and analysis schedule for the radiation environmental monitoring program at Prairie Island 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 reactor site or ISFSI facility, as appropriate. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Prairie Island Nuclear Generating Plant, 2005). Maps of fixed 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. Airborne iodine Is collected by continuous pumping through charcoal filters at these same 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 (P-l), and four are indicators (P-2, P-3, P-4, and P-6).

Offsite ambient gamma radiation is monitored at thirty-four locations, using CaS0,:Dy dosimeters with four sensitive areas at each location: ten in an inner ring in the general area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one control location, 11.1 miles distant from the plant. They are replaced and measured quarterly. Also, a complete emergency set of TLDs for the inner ring, outer ring and special interest locations are placed in the The emergency set is returned to ElML quarterlyfor annealing and repackaging.

Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI) Facility by hventy CaS0,:Dy dosimeters. Twelve dosimeters are located inside of the earthen berm in direct line of sight from the storage casks and eight dosimeters are located outside of the earthen berm. They are replaced and measured quarterly.

Milk samples are collected monthly from six farms (five indicator and one control) and analyzed For iodine-131 and gamma-emitting isotopes. The milk is collected biweekly during the growing field at the same time as regular sets.

season (May - October), because the milk animals may be on pasture.

For additional monitoring of the terrestrial environment, green leafy vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-38), and analyzed for gamrna-emitting isotopes, including iodine-131. Corn is collected annually only if fields are irrigated with river water and analyzed for gamma-emitting isotopes. Well water and ground water are collected quarterly from four locations near the plant and analyzed for tritium and gamma-emitting isotopes.

River water is collected weekly at two locations. one upstream of the plant (P-5) and one downstream (P-6. Lock and Dam No.3). Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

A

3.2 Proaram DescriDtion (continued)

Drinking water is collected weekly from the City of Red Wing well. 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, periphyton or invertebrates, and bottom sediments. Shoreline sediment is collected semi-annually from one location.

All samples are analyzed for gamma-emitting isotopes.

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

(1) No milk was available from location P-44 for the months of January, February, March, November and December, 2005.

Deviations from the program are summarized in Table 5.3.

3.4 Laboratow Procedures Analyses for iodine-131 in milk and drinking water utilize a sensitive radiochemical procedure involving the separation of the element by ion-exchange and subsequent beta counting. Gamma-spectroscopic analysis is performed using a high-purity germanium (HPGe) detector. Levels of airborne iodine-1 31 in charcoal samples are measured by gamma spectroscopy.

Levels of iodine-131 in cabbage are determined by gamma spectrometry Tritium levels are determined by liquid scintillation technique.

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 the data obtained. Details of the Quality Assurance Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2003). The program includes participation in Interlaboratory Comparison (Crosscheck) programs and results are presented in Appendix A.

5

3.5 Proaram Modifications The Yoernans Farm (P-44) was added to the program in January, 2005, as an indicator location for goat milk.

3.6 Land Use Census In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calcuiation Manual, H4, (ODCM) a land use census is conducted in order to identify the location of2the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 R producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. This census is conducted at least once per 12 months between the dates of May 1 and October 31. If new locations yield a calculated dose or dose equivalent (via the same exposure pathway) twenty percent greater than the requited locations per the ODCM, then the new locations are added to the radiation environmental monitoring prcgram 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.

This land use census insures the updating of the radiation environmental monitoring program should sampling locations change within the 5 mile radius from the plant.

The Land Use Census was completed in August and September, 2005. There were no changes to any of the highest DIQ locations for nearest residence, milk animal or garden sites. A goat dairy location was established in 2005 with a higher DIQ than the other dairy farms. The critical receptor location did not change in 2005. based on the results of the land use census.

No downstream irrigation of corn was discovered within 5 miles of the Prairie Island Plant.

Therefore, no corn samples were collected for analysis.

6

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

The 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 AtmosDheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 2005.

The last reported test was conducted on October 16, 1980 by the People's Republic of China. There were no reported accidents involving a release to the environment at nuclear reactor facilities in 2005.

4.2 S

p The following constitutes a summary of preoperational studies conducted at the Prairie Island Nuclear Power Plant during the years 1970 to 1973, 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, since background levels of radiation were much higher in these years due to radioactive fallout fromJhe atmosphere.

beta measurements in fallout declined yearly from a level of 12.187 pCi/m to 1,020 pCi/m, and these declining values are reflected throughout the various media tested.

in the air environment, ambient gamma radiation (TLDs) averaged 9.4 mR/4 weeks during preoperational studies. Gross beta in air particulates declined from leyels of 0.38 to 0.037 pCi/m3. Average present day levels have stabilized at around 0.025 pCi/m. Airborne radioiodine remained below detection levels.

In the terrestrial environment of 1970 to 1973, milk, agricultural crops, and soil were monitored.

in milk samples, low levels of Cs-137, 1-131, and 9-90 were detected. Cs-137 levels declined from 16.5 to 8.6 pCi/L. Present day measurements for both Cs-I37 and 1-131 are below detection levels. Agricultural crop measurements averaged 57.7 pCig for gross beta and 0.47 pCi/g for Cs-137. Gross beta measured in soil averaged 52 pCi/g.

The aqueous environment was monitored by testing of river, well and lake waters, 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 eight separate locations, declined steadlly from an average concentration of 1020 pCiL to 490 pCilL. Present day environmental levels of tritium are below detection limits. Values for gross beta, measured from 1970 to 1973, averaged 9.9 pCilL in downstream Mississippi River water. 8.2 pCi/L for well water, and 11.0 pCi/L for lake water.

Gamma emitters were below the lower limit of detection (LLD). In bottom sediments, gross beta background levels were determined at 51.O pCi/g. Cs-137 activity during preoperational studies in 1973 measured 0.25 pCi/g upstream and 0.21 pCi/g downstream. The lower levels occasionally observed today can still be attributed to residual activity from atmospheric fallout.

Gross beta in fish, measured in both flesh and skeletal samples, averaged 7.3 and 11.7 pCi/g.

respectively. Gross beta background levels in aquatic vegetation. algae and periphyton samples measured 76.0 pCi/g,46.0 pCig. and 13.6 pCi/g, respectively.

7

4.3 Proqram Findinas Slight tritium activity was detected in two downstream river water composites (pg. 11). It was determined that the collections coincided with planned radioactive discharges from the plant. All other results indicate background levels of radioactivity in environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.

Ambient Radiation (TLDs)

Ambient radiation was measured in the general area of the site boundary, at the outer ring 4 - 5 mi distant from the Plant, at special interest areas and at one control location. The means ranged from 16.3 mW91 days at inner ring locations to 17.2 mW91 days at outer ring locations. The mean at special locations was 16.1 mW91 days and 16.3 mW91 days at the control location.

Dose rates measured at the inner and outer ring and the control locations were similar to those observed from 1990 through 2004. The results are tabulated below. No plant effect on ambient gamma radiation was indicated (Figure 5-1).

I i i Average (Inner and Year 4 Average (Inner and Year Outer Rinasl Control Outer Rinas)

Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates (mFU91 days).

ISFSI Facilitv ODerations Monitoring Ambient radiation was measured inside the ISFSI earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFSl and the Prairie Island Indian Communrty. The mean dose rates measured 86.2 mW91 days inside the ISFSI earth berm and 20.2 mW91 days outside the ISFSI earth berm. Three additional casks were placed on the ISFSl pad in 2005, a total of twenty loaded casks remain. The higher levels inside the earth berm are expected, due to the loaded spent fuel casks being in direct line-of-sight of the TLDs.

Ambient radiation levels measured outside the earth berm show a slight increase as compared to other offsite dose rates around the plant. If the dose rates outside the earth berm are an indication of gamma skyshine from the casks, they are consistent with predictions given in the ISFSI Safety Analysis Report, Table 7A-7. "Total Skyshine Dose Rate". The cumulative average of the two special Prairie Island Indian Community TLDs measured 15.9 and 15.5 mW91 days.

Although the skyshine neutron dose rates are not directly measured, the neutron levels measured next to the casks are below the levels predicted in the ISFSI SAR Report, Table 7A-4. "TN-40 Dose Rates at Short Distances". Therefore, the skyshine dose rates at farther distances from the casks should be at or below the calculated dose rates. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1).

8

Airborne Particulates Average annual gross beta concentrations in airborne particulates were slightly higher at indicator versus control locations (0.027 pCim and 0.025 pCim, respectively) and similar to levels observed from 1990 through 2004. The results are tabulated below.

3 3

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.

Typically, the highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1990 through 2005.

Two pieces of evidence indicate conclusively that the elevated activity observed during the winter months was not attributable to the Plant operation. In the first place. elevated activity of similar size occurred simultaneously at both indicator and control locations. Secondly. an identical pattern was observed at the Monticello Nuclear Generating Plant, about 100 miles distant from the Prairie Island Nuclear Generating Plant (Xcel Energy Corp., 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 radiation (Arnold and AI-Salih, 1955), was detected in all samples. 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. There was no indication of a plant effect.

9

Iodine-131 results were below the detection limit of 0.5 pCi/L in all samples. Cs-137 results were below the LLD level of 5 pCilL in all samples. No other gamma-emitting isotopes, except naturally-occurring potassium-40, were detected in any milk samples. This is consistent with the findings of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium. and iodine (National Center for Radiological Health, 1968).

In summary. the milk data for 2005 show no radiological effects of the plant operation.

Drinkina Water In drinking water from the City of Red Wing well, tritium activity measured below the LLD level of 179 pCilL in all samples.

Gross beta concentrations averaged 11.5 pCilL throughout the year, ranging from 8.3-14.0 pCi/L. These concentrations were similar to or slightly higher than levels observed from 1990 through 2004. The most likely contribution is the relatively high levels of naturally-occurring radium. Gamma spectroscopy indicates the presence of lead and bismuth isotopes, which are daughters of the radium decay chain. There is no indication from the 2005 data of any effect of plant operation.

Gross Beta (pCi/L)

&&r 2003 2004 2005 I

I 11.5 I

Average annual concentrations; Gross beta in drinking water, 10

River Water For the first and fourth quarters of 2005, measurable tritium was detected in downstream river water composites, at concentrations of 478 and 214 pCVL, respectively. This is well below the Environmental Protection Agency's drinking water standard of 20,000 pCilL. For the remaining upstream and downstream collections. tritium levels measured below the LLD level of 173 pCilL.

Gamma-emitting isotopes were below detection limits in all samples.

Well Water At the control well P-43. Huppert Farm and four indicator wells (P-8. Community Center, P-6.

Lock and Dam No. 3, P-9, Plant Well No. 2 and P-24, Suter Farm ) no tritium was detected above the LLD level of 194 pCilL. Gamma-emitting isotopes were below detection limits in all samples.

In summary, well water data for 2005 show no radiological effects of the plant operation.

Three samples of broadleaf vegetation, cabbage leaves, were collected in July and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.013 pCi/g wet weight in all samples. With the exception of naturally-occuning potassium-40. all other gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect.

Field sampling personnel conducted an annual land use survey and found no river water taken for irrigation into fields within 5 miles downstream from the Prairie Island Plant. The collection and analysis of corn samples was not required.

Fish Fish samples were collected in May and September, 2005 and analyzed for gamma emitting isotopes. Only naturally-occurring potassium-40 was detected, and there was no significant difference between upstream and downstream results. There was no indication of a plant effect.

Aauatic Insects or Periohvton Aquatic insects (invertebrates) or periphyton were collected in May and September, 2005. With the exception of naturally occurring potassium-40. all gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect.

Bottom and Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were.

made in May and September, 2005 and analyzed for gamma-emitting isotopes. Trace levels of cesium-I37 were detected in two of the six samples collected, measuring 0.026 pWg dry weight in one downstream sample and one control sample, indicating 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.

11

5.0 FIGURES AND TABLES 12

Figure 5-1. Offsite Ambient Radiation (TLDs); average of inner and outer ring indicator locations versus control location.

1990 1991 1992 1993 1994 1995 1896 1997 1998 1999 2000 2001 2002 2003 2004 2005 13

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

[+Indicators (P-2.3.4.6) 1 1990 1991 1992 1993 1994 1995 1996 1997 I998 1999 2000 2001 2002 2W3 2004 2W5

'+control L-- ( P - I ~

1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 14

PRAIRIE ISLAND Table 5.1. Sample collection and analysis program. Pralrle Island Nuclear Generating Plant.

Collection Analysis Location Type and Type and Medium No.

Codes (and Type)'

Frequency' Frequency' Ambient radiation (TLDs) 54 Airborne Partlculates 5

Alrborne Iodine Milk River water Drinking water 5

5 2

1 Well water 5

Edlble cultivated crops -

2 leafy green vegetables Fish (one specles, edlble portion) 2 Periphyton or Invertebrates 2

Bottom sedlment 2

Shoreline sediment 1

W1A - P-lOA P-OlB - P-SB wis - POas P-OlIA - P-081A P-OllB - POBIB P-OlIX-po4u(, P-OlC P-UC). P-2, Pa, P-4, P6 P-UC), P2, P-3. P-4. P-6 P-14, P-18, P-37, P-42, P a,

p-43 (C)

P-qc). P-6 P-11 P-6, Pa, P-9, P-24, P-43 (C)

P-3WC). P-24 PlYC), Pi3 P-4WC). P-6 P-ZWC), P-6 P-I2 Amblent gamma GB. GS (QC of each location) 1-131 Cl3L GS GS (Ci31)

GS GS GS GS

~

~~

~

' Location codes are detlned in Table D2. Control statlcnc am indlcatsd by (C). Ail other statlw are Indlcaton.

' Colledlon type Is Cwed as toilowt: C/ - wnllnuous, W - grab. Cdlectlon frequency is coded as lollows:

Analysls type Is coded as follow OB - gross beta. GS - gamma spectmxopy. K3 - trltlurn. C U I - ladlne43L W-wwhly. M - monthly, Q - quarterly. SA - wmlannually, A - annually.

AnaMls freqwncy Is mded as tollows: MC - m t M y comporlte. QC - quarterly comporlte.

Milk Is collected blweeWy durlng the grazlng wason (May. October).

15

PRAIRIE ISLAND Table 5.2. Sampling locations. Prairie island Nuclear Generating Plant.

Code Type' Collection Site Distance and Direction from Sample Type' Reactor P-I C

P-2 P-3 P-4 P-5 C

P-6 P-8 P-9 P-11 P-I2 P-13 P-14 P-18 P-19 C

P-20 C

P-24 P-37 P-38 C

P-40 C

P-42 P-43 C

P-44 Air Station P-I Air Station P-2 Air Station P-3 Air Station P-4 Upstream of Piant Lock and Dam #3 &Air Station P-6 Community Center Plant Well 12 Red Wing Service Center Downstream 01 Piant Downstream of Piant Gustafson Farm Christiansen Farm Upstream of Piant Upstream of Plant Suter Residence Weisch Farm Cain Residence Upstream of Piant Rother Farm Peterson Farm Yoemans Farm Genera w

P-om Property Line P02A Property Line P-03A Property Line P-04A Property Line P05A Properly Line P06A Property Line P-07A Propelty Line P-OBA Property Line P09A Property Line P-IOA Property Line AP. AI AP. Ai AP, A i AP. AI AP. Ai, RW WW. BS, BO' WW WW DW ss F'

m m

FQ BS VE, ww M

VE BO' M

M. ww M

RW TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 11.8 mi @ 316*/NNW 0.5 mi @ 294'/WNW 0.8 mi @ 313'/NW 0.4 mi @ 359'/N 1.8 mi @ 11'/N 1.6 mi @ 129'/SE 1.0 mi @ 32Io/WNW 0.3 mi @ 306*/NW 3.3 mi @ 158'/SSE 3.0 mi @ l16°/ESE 3.5 mi @ 113'/ESE 2.3 mi @ 173'/S 3.8 mi @ 88'/E 1.3 mi @ O'/N 0.9 mi @ 45'/NE 0.6 mi @ 158'/SSE 4.1 mi @ 87'/E 14.2 mi @ 359'/N 0.4 mi @ O'/N 4.3 mi. @ 264'/W 13.9 mi. @ 355'/N 2.0 mi. @ 214O/SW 0.4 mi @ 359'/N 0.3 mi @ IO*/N 0.5 ml @ 183'/S 0.4 mi @ 204'/SW 0.4 mi @ 225'/SW 0.4 mi @ 249O/WSW 0.4 mi @ 268'//w 0.4 mi @ 29Io/WNW 0.7 mi @ 317'/NW 0.5 mi @ 333'/NNW 16

PRAIRIE ISLAND Table 5.2. Sampling locations. Prairie bland Nuclear Genarating Plant, (continued).

Code Type' Collection Site Distance and Direction from Sample Type' Reactor Aooroximateiv 4 to 5 miles D POlB P-028 P-030 PO48 PO5B PO60 P-078 P-08B P-098 P-100 P-118 P-UB P-WB P-140 P-158 Thomas Kiiiian Residence Roy Kinneman Residence Wayne Anderson Farm Nelron Drive (Road)

County Road E and Coulee Wlliiam Hauschibit Residence Red Wing Public Works David Wnuk Residence Highway 19 South Cannondale Farm Wallace Weberg Farm Ray Gergen Farm Thomas O'Rourke Farm David J. Anderson Farm Hoist Farms m i a i interest bcat ion6 P O S P-025 PO35 P-045 P-055 PO65 P-075 P-08-S P4lC Federal Lock & Dam 13 Charles Suter Residence Carl Gustafson Farm Richard Burl Residence Kinney Store Earl Fiynn Farm Indian Community Indian Community C

Robert Kinneman Farm Tu)

TLD TLD TU)

TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD n o TLD TLD TLD TLD TLD TLD 4.7 mi B 355'/N 4.8 mi B 17'/NNE 4.9 mi 46'/NE 4.2 mi B 6l'/ENE 4.2 mi B 102'/ESE 4.4 mi B 11Z'/ESE 4.7 mi B 140°/5E 4.1 mi B 165'/SSE 4.2 mi 187'/S 4.9 mi 20o0/SSw 4.5 mi B 22lo/5W 4.6 mi 251°/W5W 4.4 ml Q 270°/W 4.9 mi B 306'/NW 3.8 mi Q 34S0/NNW F6 mi @ 129'/5E 0.5 mi B 155'//5SE 2.2 mi B 173'/5 2.0 mi @ 202'//55~

2.0 mi 0 270'/W 2.5 mi 0 299'/WNW 0.7 mi @ 271n/W 0.7 mi @ 287'/NWW ll.1 m i 0 331*/NNW 17

PRAIRIE ISLAND Table 5.2. Sampllng locations, Prairie Island Nuclear Generating Plant, (contlnued).

Code Type' Collection Site Approximate Type of Distance and Direction Sample' from ISFSi Center.

ISFSi Area I nslde Earth Be rm P-OIIA M21A P-03iA P-O4IA P-O5IA P46IA P471A P-OBIA POllX PO2iX P431X P441X EFSl NuIsance Fence iSFSl Nultance Fence iSFSl Nulsance Fence ISFSI Nuisance Fence lSFSl Nuisance Fence iSFSi Nuisance Fence ISFSI Nulsance Fence SFSl Nulsance Fence LSFSI Nultance Fence iSFSl Nulsance Fence LSFSI Nuisance Fence lSFSl Nuisance Fence JSFSI Area Outslde Earl h W

P-OllB PO210 P431B PO41B P051B P-O61B PO718 POBIB ISFSI ~ e r m Area SFSi Berm Area iSFSi Berm Area iSFSl Berm Area ISFSI Berm Area ISFSl Berm Area ISFSI Berm Area SFSl Berm Area TLD TLD TLD TLD Tu)

Tu)

TLD TLD TLD TLD TU)

TLD lLD lLD lLD TLD TW TLD TU)

TLD 190' B 45*/NE 360 B 82'/E 370' B IOOo/E 200' 0 134'/SE 180' B 219*/SW 320' 8 25B'/WSW 320' B 2Bl0/WNW 190' Q 318'/NW 310' B 27O0/W 140' Q Oo/N 360' B 9O0/E 140' B IBO'/S 340 B 3'/N 3BO'B 2B0/NNE 560' B 85'/E 590' B 165*/SSE 690' 0 186'/S 720' 0 201'/SSW 610' B 27l0/W 360 0 332'/NNW "c" denotes control location. Ail other loatlona are indicators.

' Sample Codes:

AP Alrborne particulates F

Fish AI Airborne iodine m

Milk BS Bottom (river) Kdlmenls 55 Shorellne Sediments BO Boltom organisms sw Surface Water OW Drlnking water ww Well water (periphyton or macrolnvertebrates)

VE Vegetation/vegetabler

' Distance and direction data for fish and bottom organisms are approximate since avallabliity of sample specimen may vary at any one location.

18

Table 5.3. Missed collections and analyses at the Prairie island Nuclear Generating Plant Sample Type All required samples were collected and analyzed as scheduled with the following exceptions:

Collection Reason for not Analysis Location Date or conducting REMP Plans for Preventing Period as required Recurrence MI

Gamma, P-44 Jan. - Mar, 2005 Goats were dry.

None, The goat milk is available during 1-131 the grazing season.

MI 19

~

Gamma, P-44 Nov. - Dec. 2005 Goats were dry.

None, The goat milk is available durins 1-131 the grazing season.

Table 5.4 Radiological Envirwmental Monitoring Program Summary Name or Facility Prairie inland Nuclear Power Station Docket No.

50-282. M-306 Location of Facility Goodhue. Mlnnesota Rewrtirg Period January-December. 2005

( Cwnty. Stale )

Sample Type (units)

LD (Inner Ring Area at Site Boundary) mW91 days)

LD (Outer Ring 1-5 mi. distant) mW91 days)

TLD (Special lnlerest Areas) mW91 days)

TLD (Conlral) mW91 days)

Airborne Parlicuiales (pCi/m')

hirbome Iodine (pcllrn')

Type and Number of Analyses' imma 40 vnma 60 imma 32 mma 4

3 26!

3 20 Be-7 Mtl-54 cc-58 CO-60 Zn-65 Zr-Nb-95 Ru-103 Ru-106 cs-134 Cs-137 Ea-La-141 Ce-141 Ce-144 1-131 26 LLD~ -

3.0 3.0 3.0 3.0 -

0.W5 0.015 LO008 1.0006 I.wO6 1.0008

).OWE 1.000a

).0052

).0007

).OW7 1.0017 1.0015 1.0041 -

0.03 -

Indicator Locations Mean (F)'

Range=

16.3 (40140)

( 13.2-17.9) 17.2 (60160)

( 14.1-19.6) 16.1 (32132)

( 13.9-19.3)

None LO27 (212/21i (0.009-0.069) 0.068 (16116)

(0.0350.091)

LLD

< LLD

< LLD c LLD Location with Highest Annual Ms LocBtion' PGA 0.4 mi @ 249' Nvsw w28. Roy Kinneman, 4.0 mi @ 17'INNE

'-03s.

Gustafson Farm.

2.2 mi Q 173' IS P-01C. R. Kinneman.

.1 mi@ 331'1NNW P a, Air Station 1.6 mi @ 129'1SE P03. AIr Station 0.8 mi Q 313' INW Mean (F)'

Range' 17.5 (414)

(17.5.17.5) 19.0 (414)

(18.6-19.6) 18.6 (414)

(1 8.4-1 9.3) 16.3 (414)

(15.4-16.9) 0.027 (53 153)

(0.01 14.066) 0.072 (U4)

(0.0434.091)

Cantrol Locations Mean (F)'

Range=

(See conhi below.)

(see control below.)

(See Control below.)

16.3 (414)

(15.4-16.9) 0.025 (53533 (0.011-0.061) 0.060 (414)

(0.032-0.085) c LLD

< LLD

< LLD LLD LLD

< LLD

~~

LLD llumber Now

?wtlne e

0 0

0 20

Table 5.4 Radiological Environmental Monitoring Pmgram SUmmaW Indicator Location with Highest Sample Tyw and Locations Annual Mean Type Number of LLDb Mean (Ff Mean (F)'

(units)

Analyses' Ranee' Locaiond Range' Name of Facility h8Me Island ~uclear Paver SMon Docket No.

50-282.50-306 Location of Facility Gc-adhw. Minnesota Reporting Penod (County. Slate )

Contml Number Locatlms Not+

Mean (F)'

Routine Range' Results.

H-3 8

GS 24 Mn-54 Fa59 cc-58 CO60 Zn-65 Zr-Nb-95 cs-134 cs-137 Ba-La-140 Ce-144 1474 (8985)

P-44.Yoemens F a n 1973 (13/13)

(121%2191) 2.omi. ISW (1800-2191)

< LLD

< LLD 179 10 30 10 10 30 15 10 10 15 50 1382(18/18) 0 (1 284-1 532)

LLD 0

< LLD 0

I I

I

<LLD I O I 1

Ba-La-140(

15 I

<LLD River Water (PCW I

cLLD I O

P-8. Lock and Dam #3 346 (214)

(214-478)

I (214-478) 1.6 mi @ 129'/SE c LLD c LLD c LLD

< LLD c LLD

< LLD

< LLD C LLD

< LLD

< LLD C LLD c LLD

< LLD

< LLD 0

0 0

0 21

Table 5.4 Radiological Environmental Monitoring Program Summary Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Type Number of LLD' Mean (F)'

Mean (F)'

Mean (Fr (Units)

Analyses' RangeC Locationd Range' Range' Drinking Water GB 12 1.0 11.5(12/12)

P-1l.RedWingS.C.

11.5(12/12)

None (PCW (8.3-14.0) 3.3 ml a 1%' lSSE (8.3-14.0) 1-131 12 1.0 c LLD Nons None GS 12 Mn-54 10

< LLD NOM Fe-59 30 c LLD None

-58 10

< LLD None CO44 10 c LLD None Zn-65 30

< LLD NOne Zr-Nb-95 15

< LLD None cs-134 10 c LLD None Cs-137 10

< LLD None Ba-La-140 15 c LLD None ce-144 46

< LLD None Well Water H-3 20 194 c LLD c LLD (pCilL)

GS 20 Mn-54 I O c LLD

< LLD Fe-59 30

< LLD c LLD cc-58 10 c LLD c LLD co60 10 c LLD

< LLD Zn-65 30 c LLD

< LLD Zr-Nb-95 15 LLD c LLD cs-134 10

< U D

< LLD Cs-137 10 c LLD c LLD Ba-La-140 15 c LLD c LLD Ce144 53

< LLD c LLD Name of Facility Prairie Island Nuclear Power Station Docket No.

50282,50306 Location of Facility Goodhue. Minnesota Repofling Perhi January-December, 2005

( County. State )

Number Now Routine Results' 0

0 O

1 0

0 0

IH-3 4 I 179 1 cLLD I I

Crops - Cabbage (PCI~SWt) 1-131 3

0.013 c LLD

< LLD 0

22

Table 5.4 Radiological Environmental Monitoring Pmgram Summary LLD~

0.10 0.018 0.049 0.022 0.013 0.034 0.027 0.018 0.019 0.047 0.51 0.90 0.047 0.047 0.047 0.10 0.09 0.076 0.41 0.054 0.046 0.18 0.13 0.25 Name of Facility Prairie Island Nudear Power Station Docket No.

50-282.50.306 Location of Fadllty Gmdhue. Minrmota Reporting Period January-December. 2005

( C w m S!ats )

Indicator Locations Mean (F)'

Range' 2.92(2/2)

(2.743.04) 4 LLD CLLD r: LLD

LLD r; LLD cLLD

<LLD eLLD cLLD c LLD 0.96 (1/2)

<LLD

.:LLD eLLD SLLD CLLD CLLD C LLD c LLD

<LLD C LLD

< LLD C LLD Type and Number of Analyses' iS 4

K-40 Mn-54 F e 5 9 co-58 CC-60 Zn-65 Zr-Nb-95 CS-134 cs-137 Ba-La-140 P-19. Upstream 1.3 mi @ O'lN S

4 Be-7 K-40 Mn-54 CC-58 Co-60 Zn-65 Zr-Nb-95 Ru-103 Ru-106 cs-134 Cs-137 Ba-La-140 Ce141 Ce-144 3.26 (2Q)

(3.163.35)

Location' P-6. Lock and Dam #3 1.6 mi @ 129"ISE 0.96 (In) 3.26 (22)

(3.163.35)

< LLD c U D

< LLD

< LLD c U D

< LLD

~~

< LLD

-z LLD c LLD

< LLD

< LLD c LLD

< LLD

< LLD c LLD c LLD c LLD c LLD c LLD

< LLD 0

0 0

0 23

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No.

50-282. 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December. 2005

( County, Stale )

Sample (Units)

Bottom and Shoreline Sediments (PCilg dry)

Type Type and Number of Analyses' is 6

Be-7 K 4 0 Mn-54 CO-58 CO-60 Zn-65 Zr-Nb-95 Ru-103 Ru-106 cs-134 Cs-I37 Ba-La-14C Ce-141 Ce-144 L L D ~

0.22 0.10 0.016 0.021 0.015 0.061 0.025 0.030 0.12 0.015 0.023 0.058 0.061 0.13 -

indicator Locations Mean (F)'

Range' 0.40 (1/4) 7.48 (414)

(6.01-8.74)

< LLD c LLD c LLD

< LLD c LLD

< LLD

< LLD c LLD 0.026 (112) c LLD LLD c LLD Location with Annual hi Location' P-20. Upstream D.9 mi. @ 45'1NE P-20, Upstream 0.9 mi. @ 45' /NE P-06, P-20 ihest I

Mean (F)'

Range' 0.48 (112) 10.33 (Z2)

(8.67-11.98) 0.026 (112)

Control Locations Mean (F)'

Range' 0.48 (112) 10.33 (212)

(8.67-1 1.98) c LLD c LLD C LLD

< LLD

< LLD c LLD

< LLD 0.026 (1/2)

C LLD

< LLD C LLD dumbel Non-3outine LesuIk' -

0 0

0 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 E 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 vaiue. if no cnntrol station value is available. the result is considered non-routine if it exceeds ten time the typical preoperationaf value for the medium or location.

24

6.0 REFERENCES

CITED c.

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 and 276.

Environmental. Inc.. Midwest Laboratory 2001a through 2006a. Radiation Environmental Monitoring for Monticello Nuclear 2001 b through 2006b. Radiation Environmental Monitoring for Prairie Island Nuclear 2003.

Quality Assurance Program Manual, Rev. 0, 01 October 2003.

2005.

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

2003.

Quality Control Program, Rev. 0, 21 August 2003.

Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2005.

Generating Plant. Complete Analysis Data Tables, January - December, 2000-2005.

Gold, S., H. W. Barkhau, B. Shlein, and 8. Kahn, 1964.

Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Chicago, Illinois.

369-382.

Hadeton Environmental Sciences Corporation.

1979a to 1983a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, 1979b to 1983b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating 1986. "Chernobyl,"

Complete Analysis Data Tables, January - December 1978 through 1982.

Plant, Complete Analysis Data Tables, January - December 1978 through 1982.

Chemtech, October 1986. pp. 596-605.

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

National Center for Radiological Health, 1968. Radiological Health and Data Reports, VoI. 9. No. 12, 730-746.

Northern States Power Company 1972.

Prairie Island Nuclear Generating Plant. Environmental Monitoring and Ecological Studies Program, January 1,1971 to December 31,1971, Minneapolis, Minnesota.

Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1. 1972 to December 31, 1972. Minneapolis, Minnesota.

Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, Volume 1, January 1,1973 to December 31,1973. Minneapolis, Minnesota.

Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the US. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 2002. Minneapolis, Minnesota.

1973.

1974.

1979 to 2003.

25

6.0 REFERENCES

CITED fcontinued)

Prairie Island Nuclear Generating Plant, 2005. Radiological Environmental Monitoring for Prairie Island Nuclear Generating Plant, Radiation Protection Implementing Procedures, 4700 series.

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.

19Mb to 2000b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.

US. 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).

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. 2006. Monticello Nudear Generating Plant, Annual Radiation Environmental Monitoring Report to the US. Nuclear Regulatory Commission, January 1 to December 31, 2005 (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 26

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 US. EPA Environmental Monnoring Systems Laboratory. Las Vegas, Nevada. Results are reported in Appendix A. TLD lntercomparison 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, 2005 through December, 2005

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

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

Attachment A lists acceptance criteria for "spiked" samples Out-of-limit results are explained directly below the result.

A I

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES.

One standard deviation Analysis Level for single determination Gamma Emitters Strontium-8gb Potassium40 Gross alpha Gross beta Tritium Radium-226.-228 Plutonium Iodine-131, Iodine-12gb Uranium-238, Nickel-63b Technetium-9gb 1ron-55~

Othersb 5 to 100 pCiiliter or kg

> 100 pCiiter or kg 5 to 50 pCiniter or kg

> 50 pCilIiter or kg 2 to 30 pCi/liter or kg

> 30 pCi/liter or kg b 0.1 g/liter or kg 5 20 pCi/liter

> 20 pCiniter 5 100 pCi/liter

> 100 pCiiliter 5 4,000 pCilliter

> 4,000 pCi/liter b 0.1 pCi/liter L 0.1 pcilliter, gram, or sample 5 55 pCi1liter

> 55 pCi1liter 5 35 pCi/liter

> 35 pCiiliter 50 to 100 pciniter

> 100 DCIlliter 5.0 pCi/liter 5% of known value 5.0 pCi/liter 10% of known value 5.0 pCi/liter 10% of known value 5% of known value 5.0 pCiliter 25% of known value 5.0 pCi/liter 5% of known value f l o = (pcilliter) =

10% of known value 15% of known value 10% of known value 6.0 pCi/liter 10% of known value 6.0 pCi/liter 15% of known value 169.85 x 10 pCi/liter 10% of known value 20% of known value From EPA publication. 'Environmental Radioamvity Laboratory intercompanson Studies Program. Fiscal Year. 1981-1982, EPA-60014-81404.

' Laboralwy limit A2

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Limits Acceptance Result Result' STW-1051 STW-1051 STW-1052 STW-1052 STW-1052 STW-1052 STW-1052 STW-1053 STW-1053 SNV-1054 STW-1054 STW-1054 STW-1055 STW-1055 STW-1056 STW-1056 STW-1056 STW-1056 STW-1056 STW-1057 STW-1057 STW-1058 STW-1059 STW-1059 STW-1059 STW-1060 STW-1067 STW-1067 STW-1068 STW-1068 STW-1068 STW-1068 STW-1068 STW-1069 STW-1069 STW-1070 SNV-1070 STW-1070 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 05/17/05 0511 7/05 05H 7/05 05/17/05 05/17/05 031 7/05 091 7/05 0511 7/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 08/16/05 06/16/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 06/16/05 08/16/05 08116/05 08/16/05 08/16/05 Sr-89 Sr-90 Ea-133

'20-60 cs-134 cs-137 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium Sr-89 9-90 Ea-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 Sr-89 Sr-90 Ba-133 c0-60 Cs-134 cs-137 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium 28.0 f 1.2 25.1 f0.7 52.9 f 2.8 54.4

0.4 67.7 f 1.8 39.6 f 1.8 159.7 f 3.0 55.1 f 1.8 46.8

1.3 13.7 + 1.5 13.3 f 0.6 5.1 iO.2 45.1 f 4. 1 7.5 f 0.9 87.1 f2.0 38.4 f 0.8 75.3 f 0.7 201.0 f 8.4 130.0 f 6.7 42.7 f 2.9 34.0 f 0.4 14.7 f 0.5 6.6 f 0.1 19.3 f 0.7 9.6 f 0.1 24100.0 f 109.0 29.1 f 3.0 36.0 f 0.6 107.0 f 1.7 15.2

0.2 89.1 i 0.3 72.1 f 1.0 67.4 f 1.4 44.3 f 1.5 58.4 f 2.1 16.6 f 1.5 6.2 i 0.3 4.5 f 0.1 29.4 24.4 53.4 56.6 64.9 40.2 161.0 67.9 51.1 14.1 13.7 5.0 41.3 5.9 88.4 37.0 78.6 194.0 118.0 37.0 34.2 15.5 7.6 18.9 10.1 24400.0 28.0 33.8 106.0 13.5 92.1 72.7 65.7 55.7 61.3 16.6 6.2 4.5 20.7 - 38.1 15.7

~ 33.1 44.2 - 62.6 47.9 - 65.3 56.2 - 73.6 31.5 -48.9 133.0 - 189.0 38.5 - 97.3 38.5 - 97.3 10.4 - 17.8 7.8 - 19.6 0.0 - 10.2 32.6 - 50.0 0.0 - 14.6 73.1 - 104.0 69.9 - 87.3 184.0 -218.0 97.6 - 138.0 21.O - 53.0 25.5

~ 42.9 10.3 - 20.7 5.6 - 9.5 10.7 -21.1 4.9 - 15.3 20200.0 - 28600.0 19.3 - 36.7 25.1 -42.5 4.8 - 22.2 83.4 - 101.0 64.0 - 81.4 54.3 - 77.1 31.6 - 79.8 44.0 - 78.6 12.3 - 20.9 3.5 - 8.9 0.0 - 9.7 28.3 - 45.7 87.7 - 124.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Ai-1

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratoiy ERA Control ResulP Result' Limits Acceptance STW-1072 11/15/05 STW-1072 11/15/05 STW-1073 11/15/05 STW-1073 11/15/05 STW-1073 11/15/05 STW-1073 11/15/05 STW-1074 11/15/05 STW-1074 11/15/05 STW-1075 11/15/05 STW-1076 11/15/05 STW-1076 11/15/05 STW-1076 11/15\\05 STW-1077 11/15/05 s ~ w - i a 7 3 ii/is/05 Sr-89 Sr-90 Ba-133 Co-60 cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 20.6 f 0.4 15.0 f 0.3 31.8 f 1.8 85.0 f 1.4 37.2 f 2.1 27.8 f 0.7 109.0 f 1.0 41.1 f 1.2 42.7 f 0.5 20.5 f 0.6 7.8 f 0.6 5.5 f 0.6 15.5 f 0.3 12500.0 f 238.0 19.0 16.0 31.2 84.1 33.9 28.3 105.0 23.3 39.1 17.4 8.3 3.5 16.1 12200.0 10.3 - 27.7 Pass 7.3 -24.7 Pass 22.5 - 39.9 Pass 75.4 - 92.8 Pass 25.2 - 42.6 Pass 19.6 ~ 37.0 Pass 86.6 - ~ 3. a Pass 13.2 - 33.4 Fail 30.4 - 47.8 Pass 12.2 - 22.6 Pass 6.2 - 10.5 Pass 2.0 - 5.0 Fail 10.9 - 21.3 Pass 10100.0 - 14300.0 Pass

' Results obtained by Environmental. Inc.. Midwest Labwatory as a participant in the crosscheck program for proficiency

' Unless otherwise indicated. the laboratory result is given as the m a n testing in drinking water conducted by Environmental Resources Associates (ERA).

standard deviation for three determinations.

Results are presented as the known values, expected iaboratory precision (1 sigma. 1 determination) and control limits The original samples were calculated using an Am-241 emciency. The samples were spiked with TM32. Samples as provided by ERA.

were recounted and calculated using the -232 sficiency. Results of the recount: 27.01 f 2.35 pCI/L.

The reporled result was the average of the first cycle of 100 rnifwtes. the average of the second cycle counts was 4.01 PCilL

'Decay of shod-lived radium daughters contributed to a higher cwnting rate. Delay of counting for 100 minutes provided bener results.

A1-2

TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry. (TLD. CaS04: Dy Cards) mR Lab Code Date Known Lab Result Control Description Value f 2 sigma Limits Acceptance Environmental. Inc.

2005-1 4/4/2005 2005-1 4/4/2005 2005-1 4/4/2005 2005-1 4/4/2005 2005-1 4/4/2005 2005-1 4/4/2005 2005-1 4/4/2005 2005-1 4/4/2005 2005-1 4/4/2005 Environmental, Inc.

2005-2 9/12/2005 2005-2 9/12/2005 2005-2 9/12/2005 2005-2 9/12/2005 2005-2 9/12/2005 2005-2 9/12/2005 2005-2 9/12/2005 20052 9/12/2005 2005-2 9/12/2005 30 cm 60 cm 60 cm 90 cm 90 cm 120 cm 120 cm 150 cm 180 cm 30 cm 60 cm 75 cm 90 cm 90 cm 120 cm 150 cm 150 cm 180 cm 55.01 13.75 13.75 6.11 6.11 3.44 3.44 2.2 1.53 54.w 13.71 8.77 6.09 6.09 3.43 2.19 2.19 1.52 64.02 f 2.86 15.43 f 1.02 14.98 f 0.80 6.24 f 0.16 5.45 i 0.48 3.50 f 0.35 3.15 f 0.18 2.31 iO.25 1.65 f 0.41 59.30 f 2.66 17.55 f 1.30 8.24 f 0.38 5.94 f 0.49 5.93 f 0.37 3.42 f 0.18 1.71 f 0.14 1.58 i 0.99 1.87 i 0.27 38.51 -71.51 9.63 - 17.88 9.63 - 17.88 4.28 - 7.94 2.41 -4.47 2.41 -4.47 1.54 - 2.86 1.07 - 1.99 4.28 - 7.94 38.39 - 71 2 9 9.60 - 17.82 6.14 - 11.40 4.26 - 7.92 4.26 - 7.92 2.40 - 4.46 1.53 - 2.85 1.53 - 2.85 1.06 - 1.98 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A2-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)'

Lab Code Date Analysis Laboratory results Known Control 2s. n=l Activity Limits Acceptance W - I l l 0 5 W-11105 SPW-764 SPAP-766 STW-2887 W-30105 W-30105 SPW-1836 SPW-1836 SPMI-1838 SPMI-1838 SPMI-1838 SPMI-1838 SPMI-1638 SPMI-1838 SPVE-1932 SPCH-1935 SPAP-1966 SPAP-1966 SPAP-1966 SPAP-1968 SPAP-1968 SPW-2098 SPW-2922 SPW-2922 SPW-2922 SPW-2922 SPAP-2892 SPW-2895 w-60105 w-60105 SPF-3089 SPF-3089 SPW-SPW-47731 SPW-47732 SPW-4775 SPMI-4834 SPMI-4834 SPMI-4834 SPMI-4834 111 1/2005 Gr. Alpha 1/11/2005 Gr. Beta 2/18/2005 Gr. Beta 2/28/2005 Tc-99 3/1/2005 Gr. Alpha 3/1/2005 Gr. Beta 4/15/2005 1-131 4/15/2005 I-131(G) 4/15/2005 Cs-134 411 5/2005 Cs-137 4/15/2005 1-131 4/15/2005 I-131(G) 4/15/2005 Sr-89 4/15/2005 Sr-90 4/18/2005 I-I31(G) 4/18/2005 1-131 4/18/2005 Cs-134 4/18/2005 Cs-134 4/18/2005 Cs-134 4/18/2005 0-137 4/26/2005 Fe-55 5/31/2005 cs-134 5/31/2005 Cs-134 5/31/2005 Sr-89 5/31/2005 Sr-90 6/1/2005 Gr. Beta 6/1/2005 H-3 6/1/2005 Gr. Alpha 6/1/2005 Gr. Beta 6/7/2005 Cs-134 6/7/2005 Cs-137 7/1/2005 NI-63 8/24/2005 C-14 8/24/2005 C-14 8/24/2005 Fe-55 8/30/2005 Cs-134 8/30/2005 Cs-137 8/30/2005 Sr-89 8/30/2005 Sr-90 211 6/2005 H-3 4/18/2005 CS-137 24.05 f 1.01 81.59 f l. l l 77595.00 f 764.00 416.08 f 5.52 32.91 f 1.23 25.22 f 0.45 82.27 f 0.48 109.79 f 0.94 110.25 f9.68 25.94 f 1.28 59.31 f 3.66 97.71 f 0.81 109.45 f 3.06 104.44 f 2.89 8.97 f 0.79 1.oo f 0.04 382.40 f 14.95 52.10 f 7.27 57.28 f 13.47 124.88 i 18.41 52.10 f 7.27 116.79 f 14.00 2565.20 i 63.66 27.01 f 1.09 85.38 f 2.92 107.90 f 3.60 11.11 f1.13 420.32 f 5.55 75271.00 f 724.00 23.69 f 0.52 60.08 f 0.57 1.OB i 0.05 2.54 fO.10 20.57 i 1.10 2112.30 f9.13 2294.10 f 10.37 2633.50 f 62.40 49.27 f 4.88 58.17 f8.16 66.39 f3.13 11.15 f 1.13 20.06 65.70 80543.00 463.00 32.98 20.08 65.73 106.30 106.30 26.60 60.90 106.30 106.30 108.20 7.53 0.73 328.64 53.35 53.35 121.77 53.35 121.77 3017.60 25.54 60.71 113.90 6.90 448.00 78676.00 20.06 65.73 1.02 2.43 16.75 2370.80 2370.80 2777.50 47.02 60.37 65.90 9.60 10.04 - 30.12 55.70 - 75.70 64434.40 - 96651.60 370.40 - 509.30 20.96 - 44.98 10.04 -30.12 55.73 - 75.73 85.04 - 127.56 95.67 - 116.93 16.60 - 36.60 50.90 - 70.90 85.04 - 127.56 95.67 - 116.93 86.56 - 129.84 0.00 - 17.53 0.44 - 1.02 262.91 - 394.37 43.35 - 83.35 43.35 - 63.35 109.59 - 133.95 43.35 - 63.35 109.59 - 133.95 2414.08 - 3621.12 15.54 - 35.54 50.71 -70.71 91.12 - 136.68 0.00 - 16.90 358.40 - 492.80 62940.80

~ 94411.20 10.04 -30.12 55.73 - 75.73 0.61 - 1.43 1.46 - 3.40 10.05 - 23.45 1422.48 - 3319.12 1422.48 - 3319.12 2222.00 - 3333.00 37.02 - 57.02 50.37 - 70.37 52.72 - 79.08 0.00 - 19.60 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A3-1

TABLE A-3. in-House "Spike" Samples Concentration (pCi/L)

Lab Code Date Analysis Laboratory results Known Control 26, n=ib Activity Limits' Acceptance SPW-4836 SPW-4836 SPW-4836 SPW-4836 SPW-5014 W-90705 W-90705 SPW-5237 SPW-5508 SPW-6019 SPF-6293 SPF-6293 SPAP-6309 SPAP-6309 SPAP-6311 SPW-6451 W-120105 W-I20105 SPW-7440 SPW-7440 SPMI-7442 SPMI-7442 8/30/2005 Cs-134 8/30/2005 Sr-89 8/30/2005 Sr-90 8/30/2005 H-3 9/7/2005 Gr. Alpha 9/7/2005 Gr. Beta 9/22/2005 C-14 9/26/2005 Ni-63 10/24/2005 Tc-99 11/4/2005 Cs-134 11/4/2005 Cs-137 11/7/2005 Cs-134 11/7/2005 Cs-137 11/7/2005 Gr. Beta 11/10/2005 H-3 12/1/2005 Gr. Alpha 12/1/2005 Gr. Beta 12/30/2005 0-134 12/30/2005 Cs-137 12/31/2005 0-134 12/31/2005 Cs-137 8/30/2005 Cs-137 47.35 f 5.19 62.91 f 9.08 11.04 f0.98 65.89 f 2.79 77518.20 f 753.80 24.61 f 0.48 58.35 0.49 2387.40 f 11.OO 20.64 f 1.23 547.99 f 6.69 941.30 f44.10 2570.40 i 105.30 41 2 4 i 1.91 114.03 f 5.01 1.58 f 0.02 77126.00 f 747.00 25.16 f0.45 74.58 f 0.81 42.67 f 4.22 61.19 f 7.20 40.41 f 5.66 60.05 f 7.80 47.02 60.37 9.60 65.90 77602.52 20.08 65.73 2370.80 16.70 539.22 886.00 2400.00 44.03 120.24 1.42 76749.00 20.08 65.73 42.03 59.91 42.03 59.91 37.02 - 57.02 50.37 - 70.37 0.00 - 19.60 52.72 - 79.08 62082.02 - 93123.02 10.04 -30.12 55.73 - 75.73 1422.48 - 3319.12 10.02 - 23.38 377.45 - 700.99 797.40 - 974.60 2160.00 - 2640.00 34.03 - 54.03 108.22 - 132.26 1.14 -11.42 61399.20 - 92098.80 10.04 -30.12 55.73 - 75.73 32.03 - 52.03 49.91 -69.91 32.03 - 52.03 49.91 - 69.91 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Liquid sample results are reported in pCIILlter. air fillen( pclmlter). charcnal (pCllm3). and solid samples (pcilg).

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

Results are based on single determinations.

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

b CH (charcoal canister), F (fish).

d NOTE: For fish, Jell0 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)'

Lab Code Sample Date Analysis Laboratory results (4.660)

Acceptance Type LLD Activiq Criteria (4.66 (I)

W-11105 W-11105 SPW-765 SPAP-766 STW-2888 W-30105 W-30105 SPW-1637 SPW-1837 SPW-1837 SPW-1837 SPMI-1839 SPMI-1839 SPMI-1839 SPCH-1934 SPW-2097 SPW-2923 SPW-2923 SPW-2896 W-60105 w-60105 SPF-3090 SPF-3090 SPW-SPW-4774 SPW-4776 SPMI-4635 SPM1-4835 SPMI-4835 SPMI-4635 SPM1-4835 SPMI-4835 SPW-4837 SPW-4837 SPW-4837 SPW-4837 SPW-4837 SPW-5015 s P w - 5 2 3 8 water water water Air Filter water water water water water water water Milk Milk Milk Charcoal water water water water water water Fish Fish water water water Milk Milk Milk Milk Milk Milk water water water water water water water 1/11/2005 Gr. Alpha 111 1/2005 Gr. Beta 2/16/2005 H-3 2/18/2005 Gr. Beta 2/28/2005 Tc-99 3/1/2005 Gr. Alpha 3/1/2005 Gr. Beta 4/15/2005 Cs-134 4/15/2005 1-131 4/15/2005 I-l31(G) 4/15/2005 1-131 4/1 5/2005 Sr-89 4/15/2005 Sr-90 4/26/2005 Fe-55 5/31/2005 Cs-134 5/31/2005 Cs-137 6/1/2005 H-3 6/1/2005 Gr. Alpha 6/1/2005 Gr. Beta 6/7/2005 0-134 6/7/2005 Cs-137 7/1/2005 Ni-63 8/24/2005 C-I 4 8/24/2005 Fe-55 8/30/2005 Ca-60 8/30/2005 Cs-134 8/30/2005 Cs-137 8/30/2005 Sr-89 8/30/2005 Sr-90 8/30/2005 Co-60 8/30/2005 Cs-134 8/30/2005 Cs-137 8/30/2005 Sr-89 8/30/2005 Sr-90 8/30/2005 H-3 9/22/2005 C-14 4/15/2005 Cs-137 4/18/2005 I-l31(G) 6/30/2005 I-l31(G) 0.055 0.15 165.8 0.72 1.32 0.067 0.16 4.66 5.38 0.30 6.56 0.26 0.54 0.53 2.34 859.0 3.29 3.87 138.30 0.061 0.16 15.69 11.71 1.60 12.18 833 4.42 4.18 6.25 5.37 0.66 0.66 2.46 3.85 3.00 0.63 0.63 142.8 17.10 0.00 f 0.038

-0.018 f 0.10 7.4 f 82.5 0.29 f 0.48 0.45 f 0.81

-0.007 f 0.043

-0.04 f 0.1 1 0.13 kO.16 0.083 f 0.14

-0.069 f 0.56 0.88 f 0.34 96.1 f 528.4 48.1 f85.9 0,002 f 0.043 0.056 f 0.11 0.79 f 0.99 2.84 f 6.45 275 f 525

-0.23 f 0.65 1.02 f 0.41 0.25 f 0.53

-0.035 f 0.29 168 f 93 3.02 f 9.04 1

3.2 200 3.2 10 1

3.2 10 10 0.5 20 0.5 5

1 9.6 1000 10 10 200 1

3.2 100 100 20 200 1000 10 10 10 20 5

1 10 10 10 5

1 200 200 A4-1

TABLE A-4. In-House "Blank" Samples Concentration (pci/L)'

Lab Code Sample Date Analysis Laboratory results (4.66~)

Acceptance LLD ACtNi Criteria (4.66 C )

W-90705 water W-90705 water SPW-5238 water SPW-5509 water SPW-6020 water SPF-6294 Fish SPF-6294 Fish SPAP-6310 Air Filter SPAP-6310 Air Filter SPAP-6312 Air Filter W-120105 water W-120105 water SPMi-7419 Milk SPMI-7419 Milk SPMI-7419 Milk SPW-7421 water SPW-7421 water SPW-7441 water SPW-7441 water SPMI-7443 Milk SPMI-7443 Milk 9/7/2005 Gr. Alpha 9/7/2005 Gr. Beta 9/22/2005 C-14 9/26/2005 Ni-63 10/24/2005 To99 11/4/2005 Cs-134 11/4/2005 Cs-137 11/7/2005 Cs-134 11/7/2005 Cs-137 11/7/2005 Gr. Beta 12/1/2005 Gr. Alpha 12/1/2005 Gr. Beta 12/22/2005 C0-60 12/22/2005 Cs-137 12/22/2005 I-l31(G) 12/22/2005 Co-60 12/22/2005 Cs-137 12/30/2005 Cs-134 12/30/2005 Cs-137 12/30/2005 Cs-134 12/30/2005 Cs-737 0.056 0.16 17.10 1.25 4.81 18.60 12.99 3.23 3.86 1.22 0.05 0.15 7.24 5.61 10.96 2.43 3.12 4.25 1.63 4.74 8.53 0.034 f 0.04 0.082 f 0.11 3.02 f 9.04 1.23 f 0.79

-1.75 f 2.90

-0.64 f 0.64 0.033 f 0.04

-0.043 f 0.11 1

3.2 200 20 10 100 100 100 100 3.2 1

3.2 10 10 20 10 10 10 10 10 10 a Liquid sample results are reported In pCilLlter. air flitem( pCIIRker). charcoal (pCilcharcoa canister). and solid samples (pcilg).

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

' I-l31(G): iodine131 as analyzed by gamma spectroscopy.

Low levels of 3-90 are still detected in the environment. A mcerttratlon of (1-5 pCiIL) in milk is not unusual.

A4-2

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

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SW-62.63 SW-62.63 CF-95, 96 CF-95. 96 AP-791,792 ww-353. 354 SO-383,384 LW-431,432 Ml-486.487 SW-511. 512 TD-628.629 DW-538.539 MI-564. 565 DW-50134.5 swu-893.894 SW-925,926 SW-950,951 SW-950,951 DW-50248. 9 DW-1264,1265 AP-1955. 1956 AP-1890. 1891 AP-2025,2026 Mi-1346, 1347 AP-2048,2049 sw-973.974 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/14/2005 1/19/2005 1/19/2005 1/27/2005 2/1/2005 2/1/2005 2/1/2005 2/3/2005 2/8/2005 2/11/2005 2/22/2005 2/25/2005 3/1/2005 3/1/2005 3/1/2005 3/16/2005 3/19/2005 312812005 3/29/2005 3/29/2005 3/30/2005 3/30/2005 AP-2081, 2082 3/30/2005 SWU-1521. 1522 3/31/2005 W-1738. 1739 4/5/2005 SW-1857. 1858 4/13/2005 LW-1911. 1912 4/14/2005 F-1976. 1977 4/18/2005 MI-2111, 2112 4/26/2005 SWU-2158. 2159 4/26/2005 DW-2349, 2350 4/29/2005 S0-2305,2306 5/2/2005 SO-2305. 2306 5/2/2005 SO-2305. 2306 5/2/2005 S0-2305,2306 5/2/2005 SO-2305,2306 5/2/2005 MI-2260, 2261 5/3/2005 F-2630, 2631 5/5/2005 VE-2502. 2503 5/10/2005 Gr. Beta K-40 Gr. Beta K-40 Be-7 Gr. Beta H-3 Gr. Beta K-40 1-131 H-3 Gr. Beta K-40 Gr. Beta Gr. Beta Gr. Beta Gr. Beta Gr. Beta 1-131 Gr. Alpha 1-131 Be-7 Be-7 Be-7 K-40 B e 7 Be7 Gr. Beta Gr. Beta Gr. Beta Gr. Beta K-40 K40 Gr. Beta 1-131 cs-137 Gr. Alpha Gr. Beta K-40 Sr-90 K-40 K-40 Gr. Alpha 3.01 f0.57 2.00 f 0.20 6.26 f 0.23 5.68 f 0.59 0.057 f 0.017 8.37 f 1.21 453.50 f 107.20 2.45 f 0.54 1319.40 f 163.60 0.37 f 0.22 489663 f 1918 3.93 f 1.18 1316.20 f 171.10 16.41 f0.96 4.00 f 0.96 5.97 f 1.51 0.92 f 0.27 2.06 f 0.40 1.08 f 0.19 5.27 f 1.06 0.54 f 0.21 0.071 fO.009 0.060 f 0.013 0.063 f 0.012 1252.80 f 120.50 0.075 f 0.018 0.073 f 0.016 2.83 f 1.16 11.44 f 1.17 7.04 f 1.71 2.50 f 0.63 3.09 f 0.60 1291.50 f 177.90 3.69 f 0.74 0.58 f 0.27 0.11 f 0.05 28.74 f 2.57 21.51 f 1.22 32.90 f 9.90 1028.10 f 99.36 3.08 f 0.46 0.06 f 0.03 7.55 f 2.68 2.39 f 0.58 2.10 f 0.20 6.28 f 0.23 5.37 f 0.48 0.07 f 0.04 10.28 f 1.34 417.90 f 106.00 2.20 f 0.54 1177.20 f 179.70 0.44 f 0.23 491225 f 1915 3.62 f 1.10 1292.60 f 154.40 16.76 f 0.98 4.20 f 0.72 6.14 f 1.55 1.21 f 0.27 2.29 f 0.44 0.92 f 0.18 4.17 f 0.90 0.73 f 0.20 0.071 f0.009 0.069 f 0.013 0.071 f 0.011 1334.10 f 106.60 0.071 f0.015 0.061 f0.018 3.46 f 1.23 11.14 f 1.62 9.96 f 1.65 3.23 f 0.67 3.33 f 0.40 1323.70 f 108.80 3.54

0.66 0.49 f 0.27 0.1 1 f 0.04 12.41 f 3.38 28.17 f 2.52 21.42 f 1.24 29.60 f 13.90 1206.70 f 118.50 3.04 f 0.51 0.07 f 0.04 2.70 f 0.41 2.05 f 0.14 6.27 f 0.16 5.53 f 0.38 0.06 f 0.02 9.32 f 0.90 435.70 f 75.38 2.33 f 0.38 1248.30 f 121.51 0.40 f 0.16 490444 f 1355 3.78 f 0.81 1304.40 f 115.23 17.59 f 0.69 4.10 f 0.60 6.06 f 1.08 1.07 f 0.19 2.18 f 0.30 1.00 f 0.13 4.72 f 0.70 0.63 f 0.15 0.071 f 0.006 0.065 f 0.009 0.067 f 0.008 1293.45 f 80.44 0.073 f 0.012 0.067 f 0.012 3.14 f 0.85 1129 f 1.00 8.50 f 1.19 2.86 i 0.46 3.21 f 0.36 1307.60 t 104.27 3.62 f 0.50 0.53 f 0.19 0.11 iO.03 9.98

2.22 28.46 f 1.80 21.47 i 0.67 31.25 f 8.53 1 117.40 t 77.32 3.06 f 0.34 0.07 i 0.03 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass AS-1

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

~-

Concentration (pCii)'

Averaged Acceptance Lab Code Date Analysis First Result Second Result Result VE-2502,2503 5/10/2005 VE-2502,2503 5/10/2005 G-2546.2547 5/11/2005 G-2546.2547 5/11/2005 SS-2767.2788 5/18/2005 SS-2787. 2788 5/18/2005 SO-3056, 3057 5/19/2005 SO-3056.3057 ' 5/19/2005 SS-3175,3176 5/23/2005 SO-2665, 2666 5/25/2005 SO-2865. 2666 5/25/2005 SO-2865. 2666 5/25/2005 DW-2935.2936 5/27/2005 SWU-3103, 3104 6/1/2005 G-2958. 2959 6/1/2005 G-2956.2959 ' 6/1/2005 G-2958.2959 6/1/2005 BS-4069,4090 6/3/2005 BS-4089.4090 6/3/2005 DW-50527.8 6/8/2005 VE-3278. 3279 6/13/2005 MI-3299, 3300 6/15/2005 BS3-3348,3349 6/17/2005 883348. 3349 6/17/2005 BS-3346, 3349 6/17/2005 OW-3466.3467 6/28/2005 SWT-3631, 3632 6/28/2005 W-3507. 3506 8/29/2005 VE-3555. 3556 6/29/2005 VE-3555. 3556 6/29/2005 AP-3781, 3782 6/29/2005 LW-3610, 3611 6/30/2005 SW-3760,3761 6/30/2005 E-3654.3655 7/5/2005 E-3654,3655 7/5/2005 MI-3676, 3677 7/5/2005 DW-3739. 3740 7/5/2005 W-3808,3809 7/6/2005 DW-3938.3939 7/8/2005 VE-3896. 3897 7/12/2005 MI-3963, 3964 7/13/2005 DW-4068.4069 7/15/2005 Gr. Beta K-40 Be-7 K 4 0 cs-137 K-40 cs-1 37 K-40 K-40 CS-137 Gr. Beta K-40 1-131 Gr. Beta Be-7 Gr. Beta K-40 Co-60 CS-137 Gr. Alpha K 4 0 K-40 CO-60 Cs-137 K40 Gr. Beta Gr. Beta H-3 Gr. Beta K-40 Be-7 Gr. Beta Gr. Beta Gr. Beta K-40 K-40 1-131 H-3 1-131 K-40 K-40 1-131 3.81 50.10 3.79 f 0.40 0.81 f 0.39 9.43 f 1.00 0.13 f 0.04 12.44 f 0.76 0.18 f 0.04 20.06 f 1.10 6.06 t 0.44 0.18 f 0.04 32.95 f 2.48 21.93 f 0.97 0.51 f0.34 3.29 f 0.49 1.06 f 0.40 8.06 f 0.07 5.93 f 0.73 0.11 t 0.02 0.60 f 0.05 11.58 f 1.31 6.34 t 0.59 1215.40 f 110.20 0.20 i 0.04 2.59 f 0.10 11.57 f0.81 0.97 f 0.54 2.12 f 0.53 36717 f 362 7.53 f0.18 5.70 f 0.52 0.09 f 0.02 1.37 f 0.35 9.70 f 1.63 1.76 f 0.07 1.49 f 0.25 1383.90 i 116.20 1.93 f 0.24 4189.61 f 196.68 1.11 fO.30 3.44 f 0.62 1438.70 f 102.80 0.64 f 0.27 3.86 f 0.10 4.30 t 0.59 1.25 t 0.38 7.96 f 0.85 0.14 f 0.05 13.33 f 0.83 0.17 f 0.01 21.73 t 0.36 5.96 t 0.61 0.18 f 0.03 33.88 f 2.36 22.32 f 0.98 0.56 f 0.30 3.75 f 0.66 1.21 f 0.26 7.79 i 0.07 6.05 f 0.26 0.10 f 0.02 0.62 f 0.05 13.52 f 1.43 7.29 f 0.68 1250.70 f 106.70 0.22 f 0.04 2.51 f 0.07 11.82 f 0.76 1.87 f 0.58 1.62 f 0.56 38017 f 535 7.56 f 0.18 5.64 f 0.53 0.08 f 0.02 1.40 f 0.36 9.77 f 1.61 1.69 f 0.07 1.05 f 0.21 1428.20 f 125.40 2.18 f 0.23 4438.33 f 201.39 1.26 f 0.31 3.60 f 0.36 1351.80 f 100.80 0.91 fO.28 3.83 f 0.07 4.04 f 0.36 1.03 f 0.27 8.70 f 0.66 0.13 f 0.03 12.88 f 0.56 0.18 f 0.02 20.90 f 0.58 6.01 f 0.38 0.18 f 0.02 33.41 f 1.71 22.13 f 0.69 0.53 f 0.23 3.52 f 0.41 1.14 f0.24 7.93 f 0.05 5.99 f 0.39 0.11 f 0.02 0.61 fO.04 12.55 f 0.97 6.81 f0.45 1233.05 f 76.70 0.21 f 0.03 11.69 f 0.56 1.32 f 0.40 1.87 f 0.39 38367 f 329 7.55 f 0.13 5.67 f 0.37 0.09 f 0.01 1.39 f 0.25 9.73 f 1.15 2.55 f 0.06 1.72 f 0.05 1.27 f 0.16 1406.05 f 85.48 2.05 f 0.17 4313.97 f 140.75 1.18 f 0.22 3.52 f 0.36 0.78 f 0.20 1395.25 f 71.99 Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCiiL)'

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-4290, 4291 7/26/2005 VE-4290.4291 7/26/2005 SWU-4311.4312 7/26/2005 SWU-4311.4312 7/26/2005 64383.4384 8/1/2005 G-4383.4384 8/1/2005 G-4383.4384 8/1/2005 Ml-4425.4426 8/1/2005 TD-4446. 4447 8/1/2005 SL-4473.4474 8/4/2005 SL-4473, 4474 8/4/2005 VE-4532. 4533 6/5/2005 VE-4618,4619 8/9/2005 VE-4618,4619 8/9/2005 VE-4618.4619 8/9/2005 F-4639.4640 8/11/2005 F4639.4640 8/11/2005 F-4639, 4640 8/1 WOO5 DW-4730.4731 8/12/2005 Ml-4855.4856 8/28/2005 Ml-4855.4856 8/28/2005 Ml-4945.4946 8/31/2005 M1-4945,4946 8/31/2005 TD-4921.4922 9/1/2005 VE-4900.4901 9/2/2005 VE-4900.4901 9/2/2005 DW-50769,50770 9/2/2005 VE-4990. 4991 9/6/2005 MI-501 1,5012 9/8/2005 VE-5119, 5120 9/12/2005 VE-5119,5120 9/12/2005 VE-5119, 5120 9/12/2005 LW-5361, 5362 9/12/2005 SW-5098, 5099 9/13/2005 LW-5178, 5179 9/14/2005 DW-5239. 5240 9/16/2005 CF-5432. 5433 9/19/2005 CF-5432. 5433 9/19/2005 Ml-5292,5293 9/21/2005 885340,5341 9/23/2005 BS-5340,5341 9/23/2005 Gr. Alpha Gr. Beta Gr. Beta H-3 Be-7 Gr. Beta K-40 K-40 H-3 Gr. Beta K-40 Gr. Beta Gr. Alpha Gr. Beta K-40 cs-137 Gr. Beta K-40 1-131 K-40 Sr-90 K-40 Sr-90 H-3 Gr. Beta K-40 Gr. Alpha K-40 K-40 Gr. Alpha Gr. Beta K-40 Gr. Beta 1-131 Gr. Beta 1-131 Be-7 K-40 K-40 Be-7 Cs-137 0.1 1 f 0.04 4.55 f 0.13 2.62 f 0.64 192.30 f 92.90 2.06 f 0.49 8.78 f 0.22 6.74 f 0.64 1358.10 f 169.20 563.00 f 252.00 2.91 f0.83 31.20 f 1.20 0.09 f 0.05 4.60 f 0.13 4.19 f 0.46 0.05 f 0.02 3.33

0.11 2.62 f 0.57 0.82 f 0.23 1341.50 f 107.70 0.77 f 0.37 1388.90 f 158.90 0.67 f 0.34 5737.00 f 266.00 3.40 f 0.06 2.15 f 0.27 6.17 f 1.42 18.81 f 1.12 1584.00 f 194.00 0.10 f 0.06 6.05 f 0.16 4.81 f0.48 1.09 f 0.33 0.44 f 0.22 2.92 f 0.56 0.45 f 0.27 0.91 f 0.40 1.43 f 0.34 1228.80 f 78.13 1286.10 f 550.80 726.97 f 76.24 5.44 i 0.48 0.05 f 0.03 4.69 f 0.14 1.67 f 0.37 304.60 f 97.40 1.76 f 0.29 8.40 f 0.20 6.88 f 0.92 1267.90 f 164.40 529.00 f 251.00 4.57 f 0.42 2.74 f 0.54 31.70 f 1.20 0.09 f 0.04 4.54 f 0.12 4.34 f 0.47 0.05 f 0.02 3.37 fO.10 2.58 f 0.59 0.83 f 0.25 1340.00 f 114.70 0.87 f 0.37 1307.50 f 165.20 0.82 f 0.36 5860.00 f 269.00 3.51 f 0.06 2.27 f 0.24 6.08 f 1.46 19.52 f 0.86 1707.60 f 173.00 0.09 f 0.05 5.92 f 0.17 4.74 f 0.69 1.16 f0.34 0.31 f0.20 2.95 f 0.59 0.55 f 0.29 0.64 f 0.30 1.38 f 0.43 1297.00 f 81.03 1222.90 f 394.40 677.49 f 70.03 0.08 f 0.03 4.62 f 0.09 2.15 i 0.37 248.45 f 67.30 1.91 f 0.28 8.58 f 0.15 6.81 f 0.56 1313.00 f 117.96 546.00 f 177.84 5.00 f 0.32 2.62 f 0.49 31.45 f 0.85 0.09 f 0.03 4.57 f 0.09 4.27 f 0.33 0.05 f 0.02 3.35 f 0.07 2.60 f 0.41 0.83 f 0.17 1340.75 f 78.67 1348.20 f 114.61 0.75 f 0.25 5798.50 f 189.15 3.45 f 0.04 2.21 f0.18 6.13 f 1.02 19.17 f 0.71 1645.80 f 129.97 0.10 f 0.04 5.98 f 0.12 4.68 f 0.41 1.1 3 f 0.24 0.38 f 0.15 2.93 f 0.41 0.50 f 0.20 0.78 f 0.25 1.41 f0.27 1262.90 f 56.28 1254.50 f 338.72 702.23 f 51.76 0.82 i 0.26 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-3

TABLE A-5. In-House 'Duplicate" Samples Concentration ( p c i ) '

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance Pass 855340,5341 9/23/2005 K-40 12404 f 1154 13033 f 983 DW-5382. 5383 9/23/2005 1-131 0.79 f 0.31 0.53 f 0.31 0.66 f 0.22 Pass Ml-5405,5406 9/27/2005 K-40 1324.80 f 112.20 1366.80 f99.44 1345.80 f74.96 Pass AP-5769,5770 9/27/2005 Be-7 0.08 f 0.01 0.09 f 0.02 0.08 f 0.01 Pass AP-5983.5984 9/27/2005 Be-7 0.08 f 0.01 0.08 f 0.01 0.08 f 0.01 Pass AP-5878.5879 9/29/2005 Be-7 0.06 f 0.01 0.07 f 0.01 0.07 f 0.01 Pass 12719 f 758 G-5526, 5527 10/3/2005 G-5526.5527

%0/3/2005 G-5526.5527 10/3/2005 VE-5721.5722 10/10/2005 VE-5721. 5722 10/10/2005 VE-5721, 5722 10/10/2005 CF-5695,5696 1 O H 112005 CF-5695. 5696 10/11/2005 LW-6129,6130 10/11/2005 LW-8129,6130 10/11/2005 DW-50844. 5 10/11/2005 LW-5748. 5749' 10/12/2005 AP-6485.6486 10/20/2005 SWU-6156,6157 10/25/2005 VE-6186. 6187 10/28/2005 LW-6203,6204 10/27/2005 SO-6270, 6271 10/28/2005 SO-6270.6271 10/28/2005 SO-6270, 6271 10/28/2005 TD-6320,6321 11/1/2005 S0-6605.6606 11/11/2005 CF-6509. 6510 11/14/2005 SW6638.6639 11/22/2005 SO-6887.6888 11/22/2005 SO-6887.6888 11/22/2005 SO-6887.6888 11/22/2005 SVVT-6721.6722 11/29/2005 VE-6775. 6776 11/29/2005 LW-6743.6744 11/30/2005 DW-51023.4 12/2/2005 SVVT-7282.7283 12/27/2005 Be-7 Gr. Beta K-40 Gr. Alpha Gr. Beta K-40 Be-7 K-40 Gr. Beta H-3 Gr. Beta Gr. Beta Be-7 Gr. Beta K-40 Gr. Beta

'3-137 Gr. Beta K-40 H-3 Gr. Beta K-40 1-131 Gr. Alpha Gr. Beta K-40 Gr. Beta Gr. Beta Gr. Beta Gr. Alpha Gr. Beta 4.03 f 0.62 8.10 f 0.30 4.93 f 0.87 0.07 f 0.05 5.09 f 0.15 4.27 f 0.43 2.70 f 0.37 11.79 f 0.86 304.35 f 95.31 5.30 f 1.50 1.09 f 0.25 0.10 f 0.03 4.69 f 1.34 2.90 f 0.49 2.92 f 0.82 0.33 f 0.03 26.85 f 2.78 13.67 f 0.74 444202 f 1770 18.22 f 2.23 0.85 f 0.14 0.95 f 0.35 6.80 f 2.92 19.27 f 2.16 14.29 f 1.11 0.98 f 0.31 12.75 f 0.28 3.19 f 0.47 0.55 f 1.40 1.62 f 0.37 1.34 f 0.25 4.07 f 0.80 8.80 f 0.40 6.00 f 0.72 0.08 f 0.06 5.00 f 0.16 4.20 f 0.34 2.80 f 0.34 13.11 f 0.68 1.85 f 0.29 369.23 f 97.88 4.20 f 1.40 1.89 f 0.28 0.09 f 0.03 4.18 f 1.34 2.83 f 0.51 3.09 f 0.66 0.34 f 0.04 22.25 f 2.41 14.02 f 0.76 446633 f 1775 18.47 f 2.22 0.99 i 0.22 0.67 f 0.31 10.27 f 3.26 18.43 f 2.21 13.78 f 0.78 0.87 f 0.31 13.16 f0.21 2.50 i 0.44 2.21 f 1.31 1.85 f 0.38 4.05 f 0.51 8.41 f 0.24 5.47 f 0.49 0.08 f 0.04 5.05 f 0.11 4.23 f 0.27 2.75 f 0.25 12.45 f 0.55 1.59 f0.19 336.79 f 68.31 4.75 f 1.03 1.49 f 0.19 0.09 f 0.02 4.44 f 0.95 2.87 f 0.35 3.01 f 0.45 0.33 f 0.03 13.85 f 0.53 445418 f 1253 18.35 f 1.57 0.92

0.13 0.81 f 0.23 8.53 f 2.19 18.85 f 1.54 14.03 f 0.68 0.93 f 0.22 12.96 f 0.18 2.85 f 0.32 1.38 f 0.96 1.74 f 0.27 24.55 t 1.84 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 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.

Results are reported in units of pCi/L. except for air filters (pCi/Filter). food products vegetation. soil, sediment (pCi/g) 600 minute count time or longer, resulting in lower error.

Recount of W-5748. 2.38 f 0.85 pCi/L Averaged result; 2.14 f 0.45 pCi/L A54

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

concentration Known Control Lab Code' Date Analysis Laboratory result Activity Limits

Acceptance STW-1045 STW-1045 STW-1046 STW-1046 STW-1046 STW-1046 STW-1046 STW-1046 STW-1046 STW-1046 STW-1046 STW-1046 STW-1046 STW-1046 STW-1046 STW-1046 STW-1046 STW-1046 STVE-1047 STVE-1047 STVE-1047 STVE-1047 STVE-1047 STVE-1047 STSO-1 048 STSO-1048 STSO-1048 STSC-1048 STSC-1048 STSO-1048 STSO-1048 STSC-1048 STSO-1048 STSO-1048 STSO-1048 STSO-1048 STSO-1048 STSO-1048 STAP-1050 STAP-1050 01/01/05 Gr. Alpha 01/01/05 Gr. Beta 01/01/05 Am-241 01/01/05 Co-57 01/01/05 CO-60 01/01/05 CS-134 01/01/05 Cs-137 01/01/05 Fe-55 01/01/05 H-3 01/01/05 Mn-54 01/01/05 Ni-63 01/01/05 Pu-238 01/01/05 Pu-239/40 01/01/05 Sr-90 01/01/05 Tc-99 01/01/05 U-233/4 01/01/05 U-238 01/01/05 211-65 01/01/05 CO-57 01/01/05 Cc-60 01/01/05 Cs-137 01/01/05 Mn-54 01/01/05 211-65 01/01/05 Am241 01/01/05 Cc-57 01/01/05 Co-60 01/01/05 Cs-134 01/01/05 CS-137 01/01/05 K-10 01/01/05 Mn-54 01/01/05 Ni-63 01/01/05 Pu-239/40 01/01/05 Sr-90 01/01/05 U-233/4 01/01/05 U-238 01/01/05 Zn-65 01/01/05 Gr. Alpha 01/01/05 Gr. Beta 01/01/05 Cs-134 01/01/05 PU-236 0.45 f 0.10 1.90 f 0.10 1.62 f 0.12 239.40 f 1.20 248.70 f 1.00 115.50 f 1.80 328.50 i 1.70 64.90 f 7.00 304.00 f 9.70 334.80 f 1.90 7.10 f 1.60 0.01 f 0.02 2.50 f 0.14 0.70 f 0.80 43.20 f 1.40 3.31 f0.20 3.38 f 0.20 538.40 f 3.80 10.60 f 0.20 3.00 f 0.20 4.80 f 0.40 4.10 i 0.30 5.10 f 0.30 6.20 f 0.50 96.60 f 10.00 264.00 f 2.00 226.50

2.20 760.60 f 3.70 336.20 f 3.60 663.70 f 18.00 541.30 i 3.90 924.30 f 17.20 0.60 f 0.80 78.00 f 4.80 514.60 f 18.70 47.90 f 4.00 226.30 f 8.60 851.30 f 7.30 0.11 i 0.03 0.38 f 0.05 0.53 1.67 1.72 227.00 251.00 127.00 332.00 75.90 280.00 331.OO 9.00 0.02 2.40 0.00 42.90 3.24 3.33 496.00 9.88 3.15 5.00 4.11 5.18 6.29 109.00 242.00 212.00 759.00 315.00 604.00 485.00 1220.00 0.48 89.50 640.00 62.50 249.00 810.00 0.23 0.30 0.00 - 1.05 0.84 - 2.51 1.20 - 2.24 158.90 -295.10 175.70 - 326.30 88.90 - 165.10 232.40 - 431 6 0 53.13 ~ 98.67 196.00 - 364.00 231.70 - 430.30 0.00 - 20.00 0.00 - 1.oo 1.68 -3.12 0.00 - 5.00 30.03 - 55.77 2.27 - 4.21 2.33 - 4.33 347.20 - 644.80 6.92 - 12.84 2.21 -4.10 3.50 - 6.50 2.88 - 5.34 3.63 - 6.73 4.40 - 8.18 76.30 - 141.70 169.40 - 314.60 148.40 - 275.60 531.30 - 986.70 220.50 ~ 409.50 422.80 - 785.20 339.50 - 630.50 854.00 - 1586.00 0.00 - 1.00 62.65 - 116.35 448.00 - 832.00 43.75

~ 81.25 174.30 - 323.70 567.00 - 1053.00 0.00 - 0.46 0.15 - 0.45 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A6-I

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

Concentration '

Known Control Lab Code' Date Analysis Laboratory result Activity Limits Acceptance STAP-1049 STAP-1049 STAP-1049 STAP-1049 STAP-1049 STAP-1049 STAP-1049 STAP-1049 STAP-1049' STAP-1049 STAP-1049 STAP-1049 STW-1061 STW-1061 STW-1061 STW-1061 STW-1061 STW-1061 STW-1061 STW-1061 STW-1061 STW-1061 STW-106 1 STW-1061 STW-1061 STW-1061 STW-1061 STW-1061 STW-1062 STW-1062 STSO-1063 '

STSO-1063 STSO-1063 STSO-1063 STSO-1063 STSO-1063 STSO-1063 STSO-1063 STSO-1 063 STSO-1063 STSO-1063 STSO-1063 STSO-1 063 STSO-1063 01/01/05 01 /O 1 /05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 Am241 co-57 co-60 cs-134 Gs-f37 Mn-54 Pu-238 Pu-239/40 Sr-90 01/01/05 U-23314 01/01/05 U-238 01/01/05 Z k 6 5 07/01/05 Am241 07/01/05 Cc-57 07/01/05 Co-60 07/01/05 cs-134 07/01/05 cs-137 07/01/05 Fe-55 07/01/05 H-3 07/01/05 Mn-54 07/01/05 Ni-63 07/01/05 Pu-238 07/01/05 Pu-239140 07/01/05 Sr-90 07/01/05 Tc-99 07/01/05 U-233/4 07/01/05 U-238 07/01/05 211-65 07/01/05 Gr. Alpha 07/01/05 Gr. Beta 07/01/05 07/01/05 0710 1 /05 07/01 105 07/01/05 07/01/05 07/01/05 07/01/05 07/01 /05 07/01/05 07/01/05 07/01 /05 07/01 105 0 7 / 0 ~ n 5 Am-241 Go-57 Co-60 cs-I 34 cs-137 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 u-23314 U-238 Zn-65 0.10 f 0.04 4.76 f 0.64 2.84 f 0.22 3.54 f 0.37 2.20 f 0.27 3.15 f 0.21 0.16 f 0.04 0.17 f 0.02 2.24 f 0.34 0.34 f 0.02 0.35 f 0.02 3.12 f0.15 2.21 f 0.13 293.20 f 7.30 275.70 f 1.30 171.80 f4.00 342.10 f 2.20 167.80 f 9.30 514.20 f 12.60 437.00

2.50 105.10 f 3.60 1.64 f 0.12 2.32 f 0.13 9.20 f 1.30 72.30 f 2.30 4.11 fO.18 4.14 t 0.18 364.60 t 4.90 0.57 f 0.05 1.36 f 0.05 48.40 t 3.90 608.30 f 2.80 322.70 f 2.40 632.10 f 5.20 512.40 f4.20 720.50 f 19.00 516.80 f 5.10 366.50 f 13.30 68.80 t 15.00 0.00 f 0.00 602.90 f 17.20 61.50 f 1.00 164.50 f 16.70 874.70 f 8.40 0.10 4.92 3.03 3.51 2.26 3.33 0.20 0.17 1.35 0.34 0.35 3.14 2.23 272.00 261.OO 167.00 333.00 196.00 527.00 418.00 100.00 1.91 2.75 8.98 66.50 4.10 4.26 330.00 0.79 1.35 81.10 524.00 287.00 568.00 439.00 604.00 439.00 445.00 60.80 0.00 757.00 52.50 168.00 823.00 0.07 - 0.13 3.44

~ 6.40 2.12 - 3.94 2.46 - 4.56 1.58 - 2.94 2.33 - 4.33 0.14 - 0.25 0.14 - 0.25 0.95 - 1.76 0.24 - 0.44 0.25 - 0.46 2.20 - 4.08 1.56 - 2.90 190.40 ~ 353.60 182.70 - 339.30 116.90 -217.10 233.10 - 432.90 137.20 - 254.80 368.90 - 685.10 292.60 - 543.40 70.00 - 130.00 1.34 - 2.48 1.93 - 3.58 6.29 - 1 I

.67 46.55 - 86.45 2.87 - 5.33 2.98 - 5.54 231.00

~ 429.00 0.21 - 1.38 0.85 - 1.92 56.77

~ 105.43 366.80 - 681.20 200.90 - 373.10 397.60 - 738.40 307.30 - 570.70 422.80 - 785.20 307.30 ~ 570.70 311.50 - 578.50 42.56 - 79.04 0.00 - 0.00 529.90 - 984.10 36.75 - 68.25 117.60 -218.40 576.10 - 1070.00 Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A-2

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

Concentration Known Control Lab Code' Date Analysis Laboratory result Activity Limits Acceptance STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 SNE-1064 STAP-1065 STAP-1065 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 07/01/05 Am241 07/01/05 Co-57 07/01/05 C0-60 07/01/05 Cs-134 07/01/05 Cs-137 07/01/05 Mn-54 07/01/05 Pu-238 07/01/05 Pu-239/40 07/01/05 Sr-90 07/01/05 U-233/4 07/01/05 U-238 07/01/05 Zn-65 07/01/05 Gr. Alpha 07/01/05 Gr. Beta 07/01/05 Am-241 07/01/05 Co-57 07/01/05 Cc-60 07/01/05 Cs-134 07/01/05 Cs-137 07/01/05 Mn-54 07/01/05 Pu-238 07/01/05 Pu-239/40 07/01/05 Sr-90 07/01/05 U-233/4 07/01/05 U-238 07/01/05 Zn-65 0.18 f0.03 0.23 15.90 i 0.20 13.30 4.80 f 0.10 4.43 4.60 f 0.20 4.09 5.90 f 0.30 5.43 7.20 f 0.20 6.57 0.04 f 0.02 0.00 0.13 f 0.02 0.16 2.80 f 0.30 2.42 0.28 f 0.03 0.33 0.33 f 0.04 0.35 11.OO f 0.50 10.20 0.30 f 0.04 0.48 0.97 f 0.06 0.83 0.14 f 0.03 0.16 5.81 f0.17 6.20 2.79 f 0.14 2.85 3.67 f 0.12 3.85 2.93 f 0.23 3.23 4.11 f0.26 4.37 0.11 f 0.02 0.10 0.10 fO.01 0.09 2.25 f 0.29 2.25 0.28 f 0.02 0.27 0.28 i 0.02 0.28 4.11 f 0.26 4.33 0.16 - 0.30 9.31 - 'l7.29 3.10 - 5.76 2.86 - 5.32 3.80 - 7.06 4.60 - 8.54 0.00 - 1.00 0.11 -0.21 1.69 -3.15 0.23 - 0.43 0.24 - 0.45 7.14 - 13.26 0.00 - 0.80 0.55 - 1.22 0.11 -0.21 4.34 - 8.06 2.00 - 3.71 2.70 - 5.01 2.26 - 4.20 3.06 - 5.66 0.07

~ 0.13 0.06 - 0.12 1.58 - 2.93 0.19 - 0.35 0.20 - 0.37 3.06 - 5.68 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass

Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's

' Results are reported in units of Bq/kg (soil). Bq/L (water) or Bq/total sample (filters. vegetation) as requested by the

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

Mixed Analyie Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho Department of Energy.

MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination)

The strontium carbonate precipitates were redissolved and processed. The average of the three analyses was 1.34 I although the recovery was only 30%. The result of a new analysis was 1.56 pCi/L.

Incorrect sample weight used in calculation. Result of recalculation: 97.0 f 7.8 Bq/kg.

0 and control limits as defined by the MAPEP.

1 A6-3

APPENDIX B DATA REPORTING CONVENTIONS B-1

Data ReDortino Conventions 1.O. All activities. except ~rnss*aIpha'?~~lfl gross beta, are decay corrected to collection time or the end of the collection period.

2.0. Sinqle Measurements Each single measurement is reported as follows:

x i s where:

x =value of the measurement; s = 2 0 counting uncertainty (CoKespondIng to the 95% wnfdence level)

In cases where the activity is less than the lower limlt of detection L, it is reported as: c L, where L = the lower limit of detection based on 4. 6 6 ~

uncertainty for a background sample 3.0. DuDlicate analyses 3.1 Individual results: For two analysis results; x, i S, and x2 i S2 Reoorted result:

x i s; where x = (112) (x, + x2) and s = (112) 3.2. Individual results:

L,,

L, ReDorted result: c L, where L = lower of L, and L, 3.3.

Individual results:

X k S. < L ReDorted result:

x k s if x 2 L; CL otherwise 4.0. Comuutation of Averapes 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 and standard deviation s of a set of n numbers xl, x2... xn are defined as follows:

1 x =- n 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-1

Table C-1.

Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas.

Air (pCi/rn3)

Water (pCilL)

Gross alpha 1 x loJ Gross beta 1

b iodine-131 2.8 x io Strontium49 Strontium-90 Cesium-137 Barium-140 Iodine-131 Potassium-40 Gross alpha Gross beta Tritium 8,000 500 1,000 8,000 1,000 4,000 2

10 1 x I O 6 a

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

Concentations 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 airgrass-cow-milk-child pathway, A natural radionuclide.

b c-2

APPENDIX D Sampling Location Maps

TLO LOCATIONS ONE MILE RADIUS 0 PRAIRIE ISLAND TLD POINTS I

A I

J PLANT AREA ENLARGED PLAN E1.OO MILE RADIUS3

[NO SCbLEl MONITORING LEGEND:

TLD LOCFITIONS CONTROL PRINTS PRESCOTT. WISCONSIN ISFSI ARE& TLD LOCATIONS MONITORING LEGEND:

@ PRPlIRIE ISLFINO TLD POINT!

TLD LOCATIONS FIVE MILE RFIDIUS MONITORING LEGEND:

0 PRAIRIE ISLAND TLD POINTS

ENVIRONMENTAL SAMPLING POINTS

. +ONE MILE AAOIUS

... ~~.

SAMP0l.DGN c-5 REV 1

,-_^,^., ^...^ ^. ^^.. " ^....

^^^L^l --.--..

\\

n I

J PLANT AREA ENLARGED PLAN C1.00 MILE RADIUS1

[NO SCALE1 HDNITDRINC LEGEND MILK y y l ~ l N G POINT 10 W E R S FISH m l f f i POIN1 10 N W R S P-1% P-19 WYERlEQR~TES POINT IO fUWlERS A 4IR YIWLaG PDINI IO UMBERS P-6. P-40 P-1.P-2.P-lP-4.P-6 Y4TER B ~ I f f i POINT IO WUIBERS SmlMENl S&'WLM POINT 10 YEGEI~TIW I VEGETMLES IO W E R 5 P-24. P-38. P-45 Q

P-5.P-& P-8.P-9.P-ll. P-24.P.43 P-k P-12. P-ZB a

SEDIMENT SPlMPLIM: POlNT IO NUHBERS WLITER S4MRlffi POINT ID HUMSERS P-5. P-6. P-0.P-9. P-l1.P-24. P-43 P-6. P-12. P-20 MGETATIDN I VEGETRBLE5 ID WWRS P-24, P-38. P-45 REV 1 DB SAMP03.DGN

.--~.

^..^...^_I.,^..

"1 ^^ L- -..

ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS HONl TORING LEGEND MILK YInRlNG POINT 10 M I H E R S 0

P-14. P-18. P-37. P-42. P-43. P-44 PllR SAWLING WIN1 ID NUHEERS P-I. P-2. P-3. P-4. P-6 A

im Flyl SRWl.INt POINT ID MJneERS P-I3.P-19 e

INVERTEBRPlTES POINT ID ti7HBERS P-6. P-48

ENWRONMENTAL SAMPLING POINTS MONITORIN G LFGENQ MILK W P U N Q POINT ID WUYllERLl 0

P.14. P-16. PJ7. P41,P42, P U, PU WATER SMUINO m

m NUMBERS 0

P4. Pa, P I. P,.

Pll. P4a p a. PJI. P41 a M O R A l W N I VeOETbNJS D NUMBERS

L-PI-06-037, Annual Radiological Environment Environmental Monitoring Program (REMP) Report

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L-PI-06-037, Annual Radiological Environment Environmental Monitoring Program (REMP) Report

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