Text

Submittal of 2008 Annual Radiological Environmental Monitoring Program (REMP) Report, Technical Specification) 5.6.2, Appendix a
	ML091340147
Person / Time
Site:	Prairie Island
Issue date:	05/13/2009
From:	Grob B, Wadley M; Environmental, Northern States Power Co, Xcel Energy
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	FOIA/PA-2010-0209, L-PI-09-058
	Download: ML091340147 (76)
	v • d • e

c> Xcel Energy' U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie lsland Nuclear Generating Plant Units I and 2 Dockets 50-282, 50-306 and 72-1 0 License Nos. DPR-42, DPR-60 and SNM-2506 2008 Annual Radiological Environmental Monitoring Program (REMP) Report Pursuant to Prairie lsland Nuclear Generating Plant (PINGP) Technical Specification (TS) 5.6.2, Appendix A to Operating Licenses DPR-42 and DPR-60, and PINGP Independent Spent Fuel Storage Installation Technical Specification (ISFSI TS) 6.2, Appendix A to Materials License SNM-2506, the Northern States Power Company, a Minnesota corporation (NSPM) submits one copy of the Annual Radiological Environmental Monitoring Program report for the period January 1, 2008 through December 31, 2008.

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

Michael D. Wadley Site Vice President, Prairie lsla 1 d Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc:

Regional Administrator, USNRC, Region Ill Project Manager, Prairie lsland Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector, Prairie lsland Nuclear Generating Plant Steve Orth, USNRC, Region Ill Director of NMSS, USNRC Department of Health, State of Minnesota PI Dakota Community Environmental Coordinator 171 7 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1 121

ENCLOSURE 1 Annual Report to the United States Nuclear Regulatory Commission Radiological Environmental Monitoring Program January 1,2008 through December 31,2008 74 pages follow

Midwest ~aboratotv

/

an Allepheny Technologies Co. '

700 Landwehr ROad Northbmok, IL 60062-2310 ph. (847) 564-0700 fax (847) 564-4517 XCEL ENERGY CORPORATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT ANNUAL REPORT To the UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31,2008 Docket No. 50-282 License No. DPR-42 50-306 DPRBO ISFSl Docket No.72-10 SNM-2506 Prepared under Contract by ENVIRONMENTAL, Inc.

MIDWEST LABORATORY Project No. 801 0 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 Northern States Power Co. -Minnesota, for XCEL Energy Corporation.

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

Section TABLE OF CONTENTS Pane Preface..................................................................................................................................................

ii List of Tables.........................................................................................................................................

iv List of Figures..........................................................................................................................................

v

1.0 INTRODUCTION

...................................................................................................................................... I 2.0

SUMMARY

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

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

......................................................... 3 3.2 Program Description...................................................................................................................... 4 3.3 Program Execution........................................................................................................................ 5 3.4 Laboratory Procedures..................................................................................................................

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

6 3.6 Land Use Census.......................................................................................................................... 6 4.0 RESULTS AND DISCUSSION.................................................................................................................

7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents............................................................ 7 4.2 Summary of Preoperational Data................................................................................................ 7 4.3 Program Findings...........................................................................................................................

8 5.0 FIGURES AND TABLES........................................................................................................................

12

6.0 REFERENCES

CITED...........................................................................................................................

25 APPENDICES A

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

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

A-2 B

Data Reporting Conventions................................................................................................................

B-1 C

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

C-I D

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

D-I E

Special Well and Surface Water Samples........................................................................................... E-1

LIST OF TABLES No. -

T&

Paae 5.1 Sample Collection and Analysis Program.................................................................................................

15 5.2 Sampling Locations 16 5.3 Missed Collections and Analyses..............................................................................................................

19 5.4 Radiological Environmental Monitoring Program Summary 20 In addition. the following tables can be found in the Appendices:

Appendix A A-1 Interlaboratory Comparison Crosscheck Program. Environmental Resources Associates (ERA)

Al-1 A-2 Crosscheck Program Results; Thermoluminescent Dosimetry. (TLD. CaS04:Dy Cards)..................... A2-1 A-3 In-house "Spiked" Samples A3-1 A-4 In-house "Blank" Samples A4-1 A-5 In-house "Duplicate" Samples A5-1 A-6 Dep't of Energy. Mixed Analyte Performance Evaluation Program (MAPEP A6-1 A-7 Interlaboratory Comparison Crosscheck Program. Environmental Resources Associates (ERA)........ A7-1 C-I Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas................................................................................... C-2 Appendix E E-4.1 Sample collection and analysis program................................................................................................. E-6 E-4.2 Sampling locations..................................................................................................................................

E-7 E-4.3 REMP Summary...................................................................................................................................... E-8 E-4.4 REMP Complete Data Table...................................................................................................................

E-9

LIST OF FIGURES No. -

Title Paae 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control..........................................................................................................................

13 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6) versus control location (P-I) 14 In addition, the fclllowing figure can be found in the Appendices:

E-I Onsite Tritium Sampling Well locations..............................................................................................

E-13

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiological 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, 2008. 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, 2009b) 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 Northern States Power Co.-Minnesota. 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. Unit 2 achieved initial criticality on 17 December 1974. Commercial operation at full power began on 21 December 1974.

2.0

SUMMARY

The Radiological Environmental Monitoring Program (REMP) required by the U.S.

Nuclear Regulatory Commission (NRC) Offsite Dose Calculation Manual for the Prairie Island Nuclear Generating Plant and the Independent Spent Fuel Storage Installation (ISFSI) is described. Results for 2008 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.

3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM lREMP) 3.1 Proararn Desian and Data lnter~retation The purpose of the Radiological 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 )

Natural background radiation arising from cosmic rays and primordial radionuclides;

( 2 )

Fallout from atmospheric nuclear detonations; (3)

Releases from nuclear power plants; (4)

Industrial and medical radioactive waste; and (ti)

Fallout from nuclear accidents.

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

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

An additional interpretive technique involves analyses for specific radionuclides present in the environ~nental samples collected from the plant site. The plant's monitoring program includes analyses for tritium and iodine-131. Most samples are analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-.I 37 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope.

They were chosen as calibration monitors and should not be considered radiological impact indicators.

The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt48 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.

3.1 Proqram Desiqn and Data Interpretation (continued)

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

3.2 Proqram Description 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 ISFSl 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, 2008). Maps of fixed sampling locations are included in Appendix D.

To monitor the air environment, airborne particulates are collected on membrane filters by continuo'us 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 ar~e analyzed for gross beta activity and charcoal filters for iodine-1 31. Quarterly composites of particulate filters from each location are determined by gamma spectroscopy. One of the five locations is a control (P-1), and four are indicators (P-2, P-3, P-4, and P-6).

Offsite ambient gamma radiation is monitored at thirty-four locations, using CaS04: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.

Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI) Facility by twenty CaS04: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 five farms (four indicator and one control) and analyzed for iodine-131 and gamma-emitting isotopes. The milk is collected biweekly during the growing season (May - October), because the milk animals may be on pasture.

For additional monitoring of the terrestrial environment, green leafy vegetables (cabbage) are collecteti annually from the highest D/Q garden and a control location (P-38), and analyzed for gamma-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.

3.2 Proqram Descri~tion (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 Program Execution The Program was executed as described in the preceding section with the following exceptions:

(1 )

,4ir Particulates / Air Iodine:

,9 partial sample was collected from location P-3 for the week ending 06-25-08. The

sampler pump failed and was replaced.

A partial sample was collected from location P-2 for the week ending 10-14-08, due to ian open fuse. The sampler pump was replaced.

b partial sample was collected from location P-2 for the week ending 10-28-08. The sampler pump failed and was replaced.

110 milk was available from location P-44 for the months of January, February, April, I\\lovember and December, 2008. Goats dry for the season.

(3)

!Neil Water:

Testing for gamma-emitting isotopes was missed on well water samples in the third quarter, 2008. The samples were analyzed for low-level tritium.

(4)

rhermoluminescent Dosimeters:

The TLD for location P-06s was missing for the third quarter, 2008. The TLD was lost in the field.

Deviations from the program are summarized in Table 5.3.

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

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

Levels of iodine-1 31 in cabbage and natural vegetation and concentrations of airborne iodine-1 31 in charcoal samples were determined by gamma spectroscopy.

Tritium concentrations are determined by liquid scintillation.

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

Procedures are based on those prescribed by the Hlealth 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 cornprehensive quality control/quality assurance program designed to assure the reliability of data, obtained. Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2003 ). The QA Program includes participation in lnterlaboratory Comparison (crosscheck) Programs. Results obtained in the crosscheck programs are presented in Appendix A.

3.5 Proqram Modifications There were no modifications to the REMP in 2008.

3.6 Land Use Census In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census is conducted in order to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft2 producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. 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 required locations per the ODCM, then the new locations are added to the radiation environmental monitoring program wi,thin 30 days, and sampling locations having lower calculated doses or a lower dose commitmeni. 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 tht? radiation environmental monitoring program should sampling locations change within the 5 mile radius from the plant.

The Land Use Census was completed in October, 2008. There were no changes to any of the highest D/Q locations for nearest residence, milk animal or garden sites.

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

Therefore, no corn samples were collected for analy.sis.

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 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 2008.

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 2008.

4.2 Summary of Preoperational Data 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, ias 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 from the atmosphere. Gross beta measurements in 2

2 fallout declined yearly from a level of 12,167 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 durinp preoperational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 pCi/m.

3 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 Sr-90 were detected. Cs-137 levels declined from 16.5 to 8.6 pCi/L. Present day measurements for both Cs-137 and 1-131 are below detection levels. Agricultural crop measurements averaged !57.7 pCi/g 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 steadily from an average concentration of 1020 pCi/L to 490 pCi/L. Present day environmental levels of tritium are below detection limits. Values for gross beta, measured from 1970 to 1973, averaged 9.9 pCi/L in downstream Mississippi River water, 8.2 pCi/L f'or 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 51.0 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 pCi/g, and 13.6 pCi/g, respectively.

4.3 Proqram Findinas Results obtained show background levels of radioactivity in the 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 mR/91 days at inner ring locatioris to 17.3 mR/91 days at outer ring locations.

The mean at special interest locations was 16.6 mR/91 days and 17.1 mR/91 days at the control location. Dose rates measured at the inner and outer ring and the control locations were similar to those observed from 1993 through 2007. The results are tabulated below. No plant effect on ambient gamma radiation measurements was indicated (Figure 5-1).

Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates (mRl91 days).

1 year ISFSl Facility Operations Monitorinq Ambient radiation was measured inside the ISFSl earth berm, outside the ISFSl earth berm and at two special locations between the plant ISFSl and the Prairie lsland Indian Community. The mean dose rates averaged 107.0 mR/91 days inside the ISFSl earth berm and 21.1 mR/91 days outside the ISFSl earth berm. No additional casks were placed on the ISFSl pad in 2008, a total of twenty-four 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.

Average (Inner and Outer Rinqs)

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 ISFSl Safety Analysis Report, Table 7A-7, "Total Skyshine Dose Rate". The cumulative average of the two special Prairie Island lndian Community TLDs measured 16.2 and 15.8 mR/91 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 ISFSl SAR Report, Table 7A-4, "TN-40 Dose Rates at Short Distances". Therefore, the sk,yshine 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).

Control

'Year Average (Inner and Outer Rincls.1 Control

Airborne Particulates Typically, the highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1993 through 2006. The elevated activity observed in 2007 was attributed to construction activity in the area, the consequent increase in dust and heavier particulate filter loading.

Average annual gross beta concentrations in airborne particulates were nearly identical at the 3

3 indicators versus control locations (0.028 pCi/m and 0.027 pCi/m, respectively) and similar to levels observed from 1993 through 2006. The results are tabulated below.

Average of Indicators Average annual gross beta concentrations in airborne particulates.

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold ancl Al-Salih, 1955) was detected in all samples, with an average activity of 0.070 pCiIm3 for all locations. All other gamma-emitting isotopes were below their respective LLD limits.

Airborne Iodine Weekly levels of airborne iodine-131 were belc~w the lower limit of detection (LLD) of 0.03 pCi/m3 in all samples. There was no indication of a plant effect.

Iodine-131 results were below the detection limit of 0.5 pCi/L in all samples.

Trace Cs-137 was detected in one of thirteen milk samples tested from location P-44, at a level of 10.3 pCi/L. The most likely source of the cesiurn is the feed, consistent with findings of the National Center for Radiological Health, most radiocontaminants in feed do not find their way into milk, exceptions being radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968). All other samples tested below the LLD level of 5 pCi/L. No other gamma-emitting isotopes, except naturally-occurring potassium-40, were detected in any milk samples The milk data for 2008 show no radiological effects of the plant operation.

Drinkinq Water In drinking water from the City of Red Wing well, tritium activity measured below the LLD level of 178 pCi/L in all samples.

Gross beta concentrations averaged 11.6 pCi/L throughout the year, ranging from 6.0-1 3.1 pCi1L. These concentrations are consistent with levels observed from 1993 through 2007. 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 2008 data of any effect of plant operation.

Gross Beta 1

YOrr I

1 (pci/Ll 1

L I

I I

Average annual concentrations; Gross beta in drinking water.

River Water For 2008, no measurable tritium activity was detected in river water composites, above the concentration level of 178 pCi/L.

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

Well Water At control well, P-43 (Peterson Farm) and the 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 a concentration level of 181 pCi/L.

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

In summary, well water data for 2008 show no radiological effects of the plant operation.

Two samples of broadleaf vegetation, cabbage leaves, were collected in September and analyzed for gamma-emitting isotopes, including io'dine-131. The 1-131 level was below 0.017 pCiIg wet weight in all samples. With the exception of naturally-occurring 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 frorn the Prairie Island Plant. The collection and analysis of corn samples was not required.

Fish were collected in May and September, 2008 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.

Aquatic Insects or Periphvton Aquatic insects (invertebrates) or periphyton were collected in June and September, 2008 and analyzed for gamma-emitting isotopes. All gamma-emitting isotopes were below detection limits.

There was no indication of a plant effect.

Bottom and Shoreline Sediments Upstream, downstream and downstream re~reatio~nal area shoreline sediments were sampled in June and September, 2008 and analyzed for gamma-emitting isotopes. Cesium-137 was detected in one of four downstream samples, measuring 0.071 pCilg dry, usually 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.

5.0 FIGURES AND TABLES

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

N N

N w

w w

o o

w w

a w

a 0

0 0

0 w

P m

a 4

m m

~

8 0

0 0

0 N

W P

V I

a 4

C o

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

I --c-Indicators (P-2,3,4,6) /

PRAIRIE ISLANCI Table 5.1. Sample collection and analysis program, Prairie Island Nuclear Generating Plant.

Collection Analysis Location Type and

~ i p e and Medium No.

Codes (and ~ y p e ) ~

~requency~

~requency' Ambient radiation (TLD's) 54 P-OIA-P-10A P-OIB - P-15B P-OIS - Pa85 P-OlIA - P-081A P611B - P-081B P-OIIX-P-O41X, P-OlC Airborne Particulates Airborne Iodine Milk River water Drinking water Well water Edible cultivated crops -

leafy green vegetables 5

P-18, P-37, P-42, P-44, P-43 (C) 5 P-6, P-8, P-9, P-24, P-43 (C)

Fish (one species, edible portion) 2 P-19(C), P-23 Periphyton or invertebrates 2

P40(C), P-6 Bottom sediment 2

P-20(C), P-6 Shoreline sediment 1 P-12 c/Q Ambient gamma c/w GB, GS (QC of each location)

G/w GB(MC), I-131(MC)

GS (MC), H-3 (QC) a Location codes are defined in Table D-2. Control stations are indicated by (C). All other stations are indicators.

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

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

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

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

Milk is collected biweekly during the grazing season (May - October).

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

Code

~ y p e ~

Collection Site Distance and Direction from Sample ~

~

p e

~

Reactor C

Air Station P - I Air Station P-2 Air Station P-3 Air Station P-4 C

Upstream of Plant Lock and Dam #3 &Air Station P-6 Community Center Plant Well #2 Red Wing Service Center Downstream of Plant Downstream of Plant Christiansen Farm C

Upstream of Plant C

Upstream of Plant Suter Residence Welsch Farm C

Cain Residence C

Upstream of Plant Rother Farm C

Peterson Farm Yoemans Farm Glazier Residence General Area of the Slte Boundary P-OIA P-02A P-03A P-04A P-05A P-06A P-07A P-08A P-09A P-1OA Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line AP, A1 AP, Al AP, Al AP, Al R W AP, Al, RW WW, BS, BOC WW WW DW SS F=

TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 3.8 mi @ 88'/E 1.3 mi @ OO/N 0.9 mi @ 45'/NE 0.6 mi @ 158'/s~E 4.1 mi @ 8 7 ' / ~

14.2 m i @ 35g0/N 0.4 mi @ O'/N 4.3 mi. @ 2 6 4 ' / ~

13.9 mi. @ 355'/N 2.0 mi. @ 2 1 4 ' / ~ ~

0.6 mi. @ 341°/NNw

PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).

Code Typea Collection Site Distance and Direction from Sample ~ y p e ~

Reactor t?pproximatelv 4 to 5 miles Distant from the Plant Thomas Killian Residence Roy Kinneman Residence Wayne Anderson Farm Nelson Drlve (Road)

County Road E and Coulee William Hauschiblt Residence Red Wing Public Works David Wnuk Residence Highway 1 9 South Cannondale Farm Wallace Weberg Farm Ray Gergen Farm Thomas O'Rourke Farm David J. Anderson Farm Holst Farms Special Interest Locations Federal Lock & Dam #3 Charles Suter Residence Carl Gustafson Farm Richard Burt Residence Kinney Store Earl Flynn Farm lndian Community Indian Community C

Robert Kinneman Farm TLD 4.7 m i Q 355O/N TLD 4.8 m i @ 17O/NNE TLD 4.9 m i @ ~ ~ O / N E TLD 4.2 m i Q 61°/ENE TLD 4.2 m i @ ~ O Z ~ / E S E TLD 4.4 m i Q ~

~

O

/

E S

E TLD 4.7 m i Q 140°/SE TLD 4.1 m i @ 165'/SS~

TLD 4.2 m i @ 187'/S TLD 4.9 m i @ ~ O O ~ / S S W TLD 4.5 m i Q 221°/sw TLD 4.6 m i @ 25I0/WSW TLD 4.4 m i @ 270°/w TLD 4.9 m i @ 306O/NW TLD 3.8 m i @ 345O/NNW TLD TLD TLD TLD TLD TLD TLD TLD TLD

PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).

Code Typea Collection Site Approximate Type of Distance and Direction samplea from ISFSl Center.

ISFSl Area Inside Earth Berm ISFSl Nuisance Fence ISFSl Nuisance Fence ISFSl Nuisance Fence lSFSl Nuisance Fence ISFSl Nuisance Fence ISFSl Nuisance Fence ISFSl Nuisance Fence ISFSI Nuisance Fence ISFSl Nuisance Fence ISFSl Nuisance Fence ISFSl Nuisance Fence ISFSl Nuisance Fence ISFSl Area Outside Earth Berm ISFSl Berm Area ISFSl Berm Area ISFSl Berm Area lSFSl Berm Area ISFSl Berm Area ISFSl Berm Area ISFSl Berm Area ISFSl Berm Area TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD

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

Sample Codes:

AP Airborne particulates F

Fish Al Airborne Iodine M

Milk BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms SW Surface Water (periphyton or macroinvertebrates)

VE Vegetation/vegetables DW Drinking water WW Well water I Distance and direction data for flsh and bottom organisms are approximate since availability of sample specimen may vary at any one location.

Table 5.3. Missed collections and analyses at the Prairie Island Nuclear Generating Plant.

All required samples were collected and analyzed as scheduled with the following exceptions:

Location P-44 P-06s P-06, P-08, P-09, P-24, P-43 P-03 P-02 P-02 Sample Type MI TL D WW APIA1 APIA1 APIA1 Plans for Preventing Recurrence Goat milk is available during the grazing season.

None required.

Sign off on completion of sampling emphasized with

~ ~ l l e ~ t ~ r ~.

Sampler pump replaced.

Collection Date or Period Jan, Feb, Apr, Nov, Dec, 2008 3rd. Qtr.

2008 3rd. Qtr.

2008 6/25/2008 10/14/2008 10/28/2008 Analysis

Gamma, 1-131 Ambient Gamma Gamma Gross Beta, 1-1 31 Gross Beta, 1-131 Gross Beta, 1-131 Reason for not conducting REMP as required Goats were dry.

TLD lost in field.

Locations were collected and tested for low level tritium in August, 2008. Gamma -

isotopic analyses missed.

Only 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months run-time logged Approx. 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months run-time lost.

Approx. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months run-time lost.

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, 2008

( County, State )

Sample Type (Units)

TLD (Inner Ring, Area at Site Boundary) mRl91 days)

TLD (Outer Ring, 4-5 mi. dtstant) mRl91 days)

TLD (Special Interest Areas) mR191 days)

TLD (Control) mRl91 days)

Airborne Particulates (pCilm ')

Airborne Iodine (pcilm'i Type and Number of Analysesa Gamma 40 Gamma 60 Gamma 31 Gamma 4

GB 260 GS 20 Be-7 Mn-54 CO-58 CO-60 Zn-65 Zr-Nb-95 Ru-1 03 Ru-1 06 CS-134 CS-137 Ba-La-140 Ce-141 Ce-144 1-131 260 L L D ~

3.0 3.0 3.0 3.0 0.005 0.01 5 0.0007 0.0006 0.0007 0.0013 0.001 1 0.0009 0.0076 0.0006 0.0007 0.0047 0.0016 0.0043 0.03 Indicator Locations Mean (F)'

RangeC 16.3 (40140)

( 12.6-19.9) 17.3 (60160)

( 13.2-21.8) 16.6 (31131)

( 13.6-21.3)

None 0.028 (2081208)

(0.004-0.075) 0.072 (1 6/16)

(0.056-0.099)

< LLD

< LLD Number Non-Routine Resultse 0

0 0

Control Locations Mean (F)'

RangeC (See Control below.)

(See Control below.)

17.1 (414)

(15.8-19.0) 0.027 (52152)

(0.013-0.068) 0.068 (414)

(0.050-0.075)

< LLD

< LLD Location with Annual Mean

~ocation~

P-07A 0.4 mi @ 268"NV P-04B, Nelson Dr.,

4.2 mi @ 61 "IENE P-03S, Gustafson Farm, 2.2 mi @ 173"/S P-OIC, R. Kinneman, 11.1 mi@33Io/NNW P-02, Air Station 0.5 mi @ 294"iWNW P-03, Air Station 0.8 mi @ 313"lNW Highest Mean (F)'

RangeC 17.6 (414)

(1 5.9-19.9) 19 (414)

(1 5.7-21.8) 19.1 (414)

(16.9-21.3) 1 7.1 (414)

(15.8-19.0) 0.028 (52 152)

(0.004-0.075) 0.082 (414)

(0.067-0.099)

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

50-282, 50-306 ILocation of Facility Goodhue, Minnesota Reporting Period January-December, 2008

( County, State )

Sample Type (Units)

Milk (pCi/L)

River Water (pCi/Lj Type and Number of Analysesa 1-131 85 GS 85 K-40 CS-134 Cs-1 37 Ba-La-140 H-3 8

GS 24 Mn-54 Fe-59 CO-58 Co-60 Zn-65 Zr-Nb-95 CS-134 CS-1 37 Ba-La-140 Ce-I 44 Control Locations Mean (F)'

RangeC

< LLD 1405 (1811 8)

(1219-1555)

< LLD

< LLD c LLD

< LLD

< LLD L L D ~

0.5 200 5

5 5

178 10 30 10 10 30 15 10 10 15 46 Number Non-Routine Resultse 0

0 0

0 Indicator Locations Mean (F)'

RangeC

< LLD 1465 (67167)

(1078-2021)

< LLD 10.3 (1167)

< LLD c LLD

< LLD

< LLD c LLD

< LLD c LLD c LLD

< LLD

< LLD Location with Highest Annual Mean

~ocation~

P-44, Yoemans Farm 2.0 mi @ 214"ISW P-44, Yoemans Farm 2.0 mi @ 214"ISW Mean (F)'

RangeC 1736 (1 3 11 3)

(1078-2021) 10.3 (1 11 3)

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, 2008

( County, State )

Sample Type (Units!

Drinking Water (pCilL)

Well Water (pCiIL)

Crops - Cabbage (pcilgwet)

Control Locations Mean (F)'

RangeC None None None None None None None None None None None None None

< LLD

< LLD Number Non-Routine Resultse 0

0 0

Type and Number of Analysesa GB 12 1-131 12 H-3 4

GS 12 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1 34 Cs-137 Ba-La-140 Ce-144 H-3 20 GS 20 Mn-54 Fe-59 CO-58 Co-60 Zn-65 Zr-Nb-95 CS-1 34 Cs-137 Ba-La-140 Ce-I 44 1-131 2

L L D ~

1.0 1.0 178 10 30 10 10 30 15 10 10 15 42 181 10 30 10 10 30 15 10 10 15 40 0.017 Indicator Locations Mean (F)'

RangeC 116(12/12)

(6.0-13.1)

< LLD

< LLD Location with Annual Mean

~ocation~

P-11,RedWingS.C.

3.3 mi @ 158"ISSE Highest Mean (F)'

RangeC 11.6(12/12)

(6.0-13.1)

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, 2008

( County, State )

Sample Type (Units)

F~sh (pCi1g wet)

Inverlebrates (pCi/g wet)

Type and Number of Analysesa GS 4

K-40 Mn-54 Fe-59 CO-58 Co-60 Zn-65 Zr-Nb-95 CS-1 34 CS-1 37 Ba-La-140 GS 4

Be-7 K-40 Mn-54 CO-58 Co-60 Zn-65 Zr-Nb-95 Ru-1 03 Ru-1 06 CS-I 34 CS-1 37 Ba-La-140 Ce-141 Ce-144 L L D ~

0.10 0.013 0.070 0.020 0.016 0.020 0.029 0.015 0.014 0.29 0.54 0.82 0.036 0.041 0.031 0.062 0.076 0.062 0.25 0.027 0.033 0.28 0.12 0.21 Indicator Locations Mean (F)'

RangeC 2.52 (212)

(2.46-2.58)

< LLD

< LLD LLD

< LLD

<LLD

< LLD Location with Highest Control Locations Mean (F)'

RangeC 2.61 (2/2)

(2.43-2.80) 4 LLD

< LLD

< LLD Annual Mean

~ocation~

P-19, Upstream 1.3 mi @ O"/N Number Non-Routine Resultse 0

0 0

0 Mean (F)'

RangeC 2.61 (212)

(2.43-2.80)

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, 2008

( County, State )

" GB = gross beta, GS = gamma scan.

"LD

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

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

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

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

Sample Type (Units)

Bottom and Shoreline Sediments (pCi/g dry)

Type and Number of Analysesa GS 6

Be-7 K-40 Mn-54 CO-58 CO-60 Zn-65 Zr-Nb-95 Ru-103 Ru-106 CS-134 Cs-137 Ba-La-140 Ce-141 Ce-144 L L D ~

0.28 0.10 0.021 0.028 0.01 7 0.058 0.067 0.038 0.17 0.020 0.024 0.34 0.1 1 0.14 Indicator Locations Mean (F)'

RangeC 1.35 (114) 7.94 (414)

(6.1 5-10.64)

< LLD

< LLD 0.071 (114)

< LLD

< LLD Location with Highest Control Locations Mean (F)'

RangeC

< LLD 10.25 (212)

(9.48-1 1.02)

< LLD

< LLD Annual Mean

~ocation~

P-6, Lock and Dam #3 1.6 mi @ 1 ~ ~ O / S E P-20, Upstream 0.9 mi. @ 45"INE P-6, Lock and Dam #3 1.6 mi @ 1 2g0/SE Number Non-Routine Resultse 0

0 0

0 Mean (F)'

RangeC 1.35 (112) 1 0.25 (212)

(9.48-1 1.02) 0.071 (112)

6.0 REFERENCES

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

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

Environmental, Inc., Midwest Laboratory 2001a through 2009a. Radiological Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2008.

2001 b through 2009b. Radiological Environmental Monitoring for Prairie lsland Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000-2008.

2003.

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

2005.

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

2003.

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

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

Hazleton Environmental Sciences Corporation.

1979a to 1983a.

Radiological Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.

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

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

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

Northern States Power Company.

1972 through 1974. Prairie lsland Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1, 1971 to December 31, 1971,1972, 1973. Minneapolis, Minnesota.

1979 to 2006. Prairie lsland Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 2005.

Minneapolis, Minnesota.

Prairie lsland Nuclear Generating Plant, 2006. Radiological Environmental Monitoring for Prairie lsland Nuclear Generating Plant, Radiation Protection Implementing Procedures, 4700 series.

Teledyne Brown Engineering Environmental Services, Midwest Laboratory.

1984a to 2000a. Radiological Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January

- December, 1983 through 1999.

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

6.0 REFERENCES

CITED (continued)

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

U.S. Environmental Protection Agency 1980. Prescribed Procedures for Measurement of Radioactivity in Drinking Water, Cincinnati, Ohio (EPA-60014-80-032).

1984.

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

2007.

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

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

Xcel Energy Corporation. 2009. Monticello Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois

Midwest ~aborator~

an Allegheny Technologies Co.

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

fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE:

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

January, 2008 through December, 2008

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

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

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

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

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

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

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

Complete analytical data for duplicate analyses is available upon request.

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

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

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

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

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One standard deviation Analysis Level for single determination Gamma Emitters 5.0 pCi1liter 5% of known value 5.0 pcilliter 10% of known value 5.0 pCi/liter 10% of known value Potassium-40 2 0.1 glliter or kg 5% of known value Gross alpha 5.0 pCi1liter 25% of known value Gross beta 5.0 pCi1liter 5% of known value Tritium t l o =

169.85 x 10% of known value Radium-226,-228 2 0.1 pcilliter 15% of known value Plutonium r 0.1 pcilliter, gram, or sample 10% of known value 6 pcilliter 10% of known value 6 pcilliter 15% of known value 10 pCi1liter 10% of known value Other Analyses 20% of known value

" Frorn EPA publication. "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981 -1982, EPA-60014-81-004.

"aboratory lim~t

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control I3esultb ResultC Limits Acceptance STW - 1 1 48 03/24/08 Sr-89 50.6 2 2.4 60.4 48.6 - 68.2 Pass STW -1 148 03/24/08 Sr-90 42.4 ? 1.4 39.2 28.8 - 45.1 Pass STW - 1 1 49 03/24/08 Ba-133 56.9 f 5.4 58.3 48.3 - 64.3 Pass STW -1 1 49 03/24/08 Co-60 73.9 i7 1.6 76.6 68.9 - 86.7 Pass STW-1149 03/24/08 Cs-1 34 50.2 + 1.9 46.6 37.4 - 51.3 Pass STW-I 149 03/24/08 Cs-1 37 97.7 + 2.2 102.0 91.8 - 115.0 Pass STW - 1 1 49 03/24/08 Zn-65 109.9 f 5.8 106.0 95.4 - 126.0 Pass STW-1150 03/24/08 Gr. Alpha 43.7 + 7.5 50.8 26.5 - 63.7 Pass STW-1150 03/24/08 Gr. Beta 36.4 ? 1.8 51.4 35.0 - 58.4 Pass STW-1151 03/24/08 1-131 29.3 t 1.4 28.7 23.9 - 33.6 Pass STW - 1 152 03/24/08 Ra-226 15.0 2 1.1 15.3 11.4 - 17.6 Pass STW - 1 1 52 03/24/08 Ra-228 18.4 f 1.8 17.0 11.4 - 20.4 Pass STW-1152 03/24/08 Uranium 23.4 t 1.3 24.6 19.8 - 27.6 Pass STW-1153 03/24/08 H-3 12551.O 5 207.0 12000.0 10400.0 - 13200.0 Pass STW-1154 STW-1154 STW-I 155 STW-1155 STW-1155 STW-1155 STW-1155 STW-1156 STW-1156 STW-1157 STW-1157 STW-1157 STW-1164 STW-1164 STW-1165 STW-1165 STW-1165 STW-1165 STW-1165 STW-1 166 STW-I 166 STW-I 167 STW-1168 STW-1168 STW-1168 STW-1169 Sr-89 Sr-90 Ba-133 CO-60 Cs-134 CS-137 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium Sr-89 Sr-90 Ba-133 CO-60 Cs-134 CS-1 37 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 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 a Results obtaned by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

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

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

rnR Lab Code Date Known Lab Result Control Description Value

-1 2 sigma Limits Acceptance Environmental. Inc.

Env~ronmental, Inc.

2008-2 1 111 712008 2008-2 1 111 712008 2008-2 1 111 712008 2008-2 1 1 I1 712008 2008-2 1 111 712008 2008-2 1 111 712008 2008-2 1 1 11 712008 2008-2 1 111 712008 2008-2 1 1 11 712008 2008-2 1 111 712008 2008-2 1 111 712008 2008-2 1 111 712008 2008-2 1 111 712008 2008-2 1 111 712008 2008-2 1 111 712008 2008-2 1 111 712008 2008-2 1 111 712008 40 cm.

50 crn.

60 crn.

70 cm.

80 cm.

90 cm.

100 cm.

120 crn.

150 cm.

180 cm.

30 crn.

40 crn.

50 cm.

60 cm.

70 cm.

75 crn.

80 cm.

90 cm.

100 cm.

I 1 0 crn.

120 crn.

120 cm.

150 cm.

180 cm.

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

TABLE A-3. In-House "Spike" Samples Lab Code Date Analysis SPW-111 SPW-298 W-I 1708 SPW-711 SPAP-881 SPAP-881 SPAP-883 SPMI-885 SPW-887 SPW-889 W-31808 W-31808 SPMI-885 SPMI-885 SPW-887 SPW-887 SPW-1282 W-40308 SPW-5580 SPW-1562 SPW-1560 SPW-1621 W-51508 W-51508 SPAP-2673 SPAP-2673 SPAP-2674 SPF-2745 SPF-2745 SPMI-2677 SPMI-2677A SPW-2677 SPW-2677 SPMI-2679 SPMI-2679 SPMI-2679 SPMI-2679A SPVE-2681 SPW-2683 S PW-2685 SPW 2689 Tc-99 Ni-63 Ra-226 U-238

'3-134 CS-1 37 Gr. Beta 9-90 Sr-90 H-3 Gr. Alpha Gr. Beta CS-1 34 CS-137 CS-1 34 Cs-137 U-238 Ra-226 H-3 Ra-228 Tc-99 Fe-55 Gr. Alpha Gr. Beta CS-1 34 Cs-137 Gr. Beta Cs-134 Cs-137 Cs-137 1-131 CS-1 34 1-131 (G)

CS-134 CS-1 37 1-1 31 (G) 1-131 1-131 (G)

Ni-63 H-3 C-14 Concentration (pCiIL)=

Laboratory results Known 2s, n=l Activity Control Limits 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

TABLE A-3. In-House "Spike" Samples Lab Code W-112008 W-I 12008 SPAP-6839 SPAP-6839 SPAP-6841 SPW-6843 SPW-6845 S PW -6847 SPW-6849 SPW-6851 SPF-6859 SPF-6859 SPW-7059 SPMI-7061 Concentration (pCi/L)=

Date Analysis Laboratory results Known Control 2s, n=l Activity LimitsC Acceptance 811 412008 Ra-226 12.98 2 0.35 12.69 8.88 - 16.50 Pass 811 412008 Ra-228 29.09 2 2.46 30.51 21.36 - 39.66 Pass 811 812008 U-238 42.59 f 1.96 41.70 29.19 - 54.21 Pass 811 812008 Gr. Alpha 21.36 f 0.42 20.08 10.04 - 30.1 2 Pass 8/18/2008 Gr. Beta 49.33 f 1.O1 45.68 35.68 - 55.68 Pass Gr. Alpha Gr. Beta CS-1 34 CS-1 37 Gr. Beta C-14 Fe-55 Tc-99 Ni-63 H-3 CS-1 34 Cs-137 Sr-90 3-90 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Liquid sample results are reported in pCiILiter, air filters( pcilfilter), charcoal (p~i/m3),

and solid samples (pCi1g).

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

CH (charcoal canister), F (fish).

Results are based on single determinations.

Control limits are established from the precision values listed in Attachment A of this report, adjusted to f 20.

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

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

TABLE A-4. In-House "Blank" Samples Concentration (PC~/L)~

Lab Code Sample Date

~ n a l ~ s i s ~ Laboratory results (4.660)

Acceptance Type LLD ActivityC Criteria (4.66 o)

W-40308 SPW-1563 SPW-1561 SPW-1621 SPW-2451 SPW--2676 SPW-2676 SPW-2676 SPW--2677 SPW-2677 SPW-2677 SPF-2744 SPF-2744 SPW-2676 SPMI-2678 SPVE-2680 Water Water Water Air Filter Air Filter Water Water Water Milk Milk Water Water Water Water Water Water Water Water Water Water Water Fish Fish Water Milk Vegetation U-238 Tc-99 Ra-226 CS-1 34 CS-1 37 H-3 Gr. Alpha Gr. Beta CS-1 34 Cs-137 Ra-226 Ra-228 Tc-99 Fe-55 U-238 CS-1 34 CS-1 34 Cs-137 CS-1 34 1-1 31 (G) 1-131 (G)

CS-1 34 CS-1 37 1-131 1-131 1-131 (G)

SPW-3581 Water 711 412008 U-238 0.10 0.13

0.12 1

W-80708 Water 8/7/2008 Gr. Alpha 0.63

-0.02 + 0.44 1

W-80708 Water 8/7/2008 Gr. Beta 1.43

-0.47

0.99 3.2 W-81408 Water 811 412008 Ra-226 0.06 0.14 + 0.04 1

SPW-1563 Water 811 412008 Ra-228 0.79 0.89 + 0.47 2

SPW-81808 Water 811 812008 U-238 0.18 0.04 f 0.13 1

TABLE A-4. In-House "Blank" Samples Concentration (PC~/L)~

Lab Code Sample Date

~ n a l ~ s i s ~ Laboratory results (4.660)

Acceptance Type LLD ActivityC Criteria (4.66 o)

W-112008 Water 11/20/2008 Gr. Alpha 0.40 0.02 + 0.28 1

W-I12008 Water 1 1 /20/2008 Gr. Beta 0.75

-0.1 6 + 0.52 3.2 SPAP-6838 Air Filter 12/5/2008 Cs-1 34 1.01 100 SPAP-6838 Air Filter 12/5/2008 Cs-1 37 0.95 100 SPAP-6840 Air Filter 12/5/2008 Gr. Beta 0.96 2.69 2 0.64 3.2 SPW-6842 Water 1 2/5/2008 C-14 7.79

-3.04 k 4.05 200 SPW-6844 Water 12/5/2008 Fe-55 715.10 21.70 + 435.10 1000 SPW-6846 Water 12/5/2008 Tc-99 1.36

-0.47 2 0.82 10 SPW-6848 Water 12/5/2008 Ni-63 1.94 3.08 2 1.23 20 SPF-6858 Fish 1 2/5/2008 Cs-1 34 1.53 100 SPF-6858 Fish 12/5/2008 Cs-1 37 3.92 100 SPW-7058 Water 1211 912008 Cs-1 34 2.62 10 SPW-7058 Water 12/19/2008 Cs-1 37 2.39 10 SPW-7058 Water 1211 912008 Sr-90 0.65

-0.28 2 0.26 1

SPMI-7060 Milk 1211 912008 Cs-1 34 2.18 10 SPMI-7060 Milk 1211 912008 Cs-1 37 3.87 10 SPMI-7060 Milk 12/19/2008 1-1 31 (G) 2.80 20 SPMI-7060 Milk 1211 912008 Sr-90 0.53 0.76 2 0.34 1

" L~quid sample results are reported in pCitLiter, air filters( pcitfilter), charcoal (pCi1charcoal canister), and solid samples (pcitkg).

1-131 (G); lodine-131 as analyzed by gammaspectroscopy.

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

Low levels of Sr-90 are st111 detected in the environment. A concentration of (1-5 pCi/L) in milk is not unusual.

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

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance Be-7 Gr. Beta K-40 Gr. Alpha Beta-K40 CS-1 37 Gr. Alpha Gr. Alpha K-40 Gr. Alpha Gr. Beta K-40 Gr. Beta Ra-226 Ra-228 Gr. Alpha Gr. Beta Gr. Beta Gr. Beta Gr. Alpha Gr. Beta Ra-226 Ra-228 Gr. Alpha Ra-226 Ra-228 Uranium Gr. Beta Ra-226 Ra-228 K-40 Sr-90 Gr. Alpha Ra-226 Ra-228 U-23314 Pb-214 U-23314 U-238 Gr. Beta 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 Pass Pass Pass Pass Pass Pass AP-1519, 1520 41212008 Be-7 0.07 t 0.01 0.08 + 0.01 0.08 k 0.01 Pass W-1565.7566 41212008 Gr. Alpha 0.82 t 0.64 1.58 +_ 0.72 1.20 + 0.48 Pass W-1565. 1566 4/2/2008 Gr. Beta 3.73 f 0.86 5.51 + 1.09 4.62 + 0.69 Pass

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

Lab Code Date Analysis Ra-226 Ra-228 Gr. Alpha Ra-226 Ra-228 K-40 Ra-226 Ra-228 Gr. Beta Gr. Beta Gr. Beta Gr. Beta Ac-228 Gr. Beta Pb-214 CS-1 37 Ra-226 Ra-228 K-40 Be-7 CS-1 37 Gr. Alpha Gr. Beta K-40 Ra-226 Ra-228 Gr. Alpha U-23314 CS-1 37 H-3 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Be-7 CS-1 37 Gr. Alpha Gr. Beta K-40 Gr. Beta Gr. Beta Gr. Beta Averaged First Result Second Result Result Acceptance 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

TABLE A-5. In-House "Duplicate" Samples Lab Code Date Analvsis Concentration (PC~/L)~

Averaged First Result Second Result Result Acceotance Gr. Beta Gr. Beta Be-7 Be-7 Be-7 Gr. Beta Gr. Beta Ra-226 Be-7 CS-1 37 Gr. Alpha Gr. Beta K-40 Ra-226 Ra-228 Ra-226 Ra-228 Ra-226 Ra-228 K-40 K-40 Gr. Beta Gr. Beta Gr. Beta Gr. Beta Be-7 Gr. Beta K-40 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Ra-226 Ra-228 108.84 f 44.1 4 91.I0 f 22.32 99.97 f 24.73 Pass 952.18 f 52.78 941.56 f 13.61 946.87 f 27.25 Pass 2.96 f 0.32 2.71 f 0.30 2.84 _+ 0.22 Pass 2.96 f 0.32 2.71 f 0.30 2.84 f 0.22 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

TABLE A-5. In-House "Duplicate" Samples Lab Code Date Analvsis Concentration (PC~/L)~

Averaged First Result Second Result Result Acce~tance Gr. Alpha Ra-226 Ra-228 Be-7 CS-1 37 K-40 Ra-226 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Gr. Alpha U-23314 Ra-226 Ra-228 Ra-226 Ra-228 K-40 Gr. Beta Gr. Beta K-40 Be-7 CS-1 37 Gr. Alpha Gr. Beta K-40 Be-7 K-40 Gr. Alpha Gr. Beta 1-1 31 K-40 Gr. Beta Gr. Beta K-40 U-23314 U-238 Gr. Alpha Ra-226 Ra-228 Be-7 Gr. Beta K-40 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

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

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance Be-7 Gr. Alpha Gr. Beta Gr. Alpha Ra-228 Gr. Alpha Gr. Beta Ra-226 Ra-228 Gr. Alpha K-40 K-40 Gr. Alpha Ra-226 Ra-228 Gr. Alpha Gr. Alpha Gr. Beta u-23314 Ra-226 Ra-228 Gr. Beta K-40 K-40 Ra-226 Ra-228 Gr. Beta 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 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 pCiIL, except for air filters (pCiIFilter), food products, vegetation, soil, sediment (pCi1g).

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

Concentration Known Control Lab CodeC Date Analysis Laboratory result Activity Limits Acceptance STW-1137 STW-1137 STW-1137 STW-1137 STW-1137 STW-1137 STW-1137 STW-1137 STW-1137 STW-1137 STW-1137 STW-1137 STW-1137 STW 1 137 STW-1137 STW-1137 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STW-1138 01/01/08 Gr. Alpha 0.96 f 0.14 1.40 0.00 - 2.80 Pass STW-1138 01/01/08 Gr. Beta 2.30 + 0.1 5 2.43 1.22 - 3.65 Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Fail Pass STAP-1140 01/01/08 Gr. Alpha 0.1 1 + 0.03 0.35 0.00 - 0.70 Pass STAP-1140 01/01/08 Gr. Beta 0.34 + 0.04 0.29 0.14 - 0.43 Pass STVE-1141 01/01/08 Co-57 8.30 + 0.1 8 6.89 4.82 - 8.96 Pass STVE-1141 01/01/08 Co-60 3.03 + 0.1 3 2.77 1.94 - 3.60 Pass STVE-1141 01/01/08 Cs-134 6.53 + 0.29 6.28 4.40 - 8.16 Pass STVE-1141 01/01/08 Cs-137 3.90 f 0.19 3.41 2.39 - 4.43 Pass STVE-1141 01/01/08 Mn-54 5.43 + 0.21 4.74 3.32 - 6.16 Pass STVE-1141 01/01/08 Zn-65 0.033 4 0.1 0 0.00 0.00 - 1.OO Pass

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

Concentration Known Control Lab CodeC Date Analysis Laboratory result Activity Limits

Acceptance STSO-1 1 42 STSO-1 142 STSO-1 142 STSO-I 142 STSO-1 142 STSO-1 142 STSO-1 142 STSO-1 142 STSO-1 142 STSO-1 142 STSO-1 142 STSO-1 158 STSO-I 158 STSO-1 158 STSO-1 158 STSO-1 158 STSO-1 158 STSO-1 158 STSO-1 1 58 STSO-I 158 STSO-1 1 58 STSO-1 158 STSO-I I58 '

STSO-1 1 58 STSO-1 1 58 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 STVE-1159 08/01 108 Co-57 8.52 f. 0.23 7.10 5.00 - 9.20 Pass STVE-1159 08/01/08 Co-60 5.08 f 0.19 4.70 3.30 - 6.10 Pass STVE-1 159 08/01 108 Cs-1 34 5.26 + 0.1 8 5.50 3.90 - 7.20 Pass STVE-1159 08/01 108 Cs-1 37 0.01 f 0.14 0.00 0.00 - 1.OO Pass STVE-1 159 08/01/08 Mn-54 6.39 -1 0.28 5.80 4.10 - 7.50 Pass STVE-1159 08/01/08 Zn-65 7.73 + 0.45 6.90 4.80 - 9.00 Pass

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a concentration Known Control Lab CodeC Date Analysis Laboratory result Activity Limits Acceptance Fail Pass Pass Pass Pass Pass Pass Pass Fail Fail Pass Pass Fail Pass Pass Pass STW-1163 08/01/08 Gr. Alpha 0.08 ? 0.04 0.00 0.00 - 0.56 Pass STW-1163 08/01/08 Gr. Beta 0.12 2 0.05 0.00 0.00 - 1.85 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, ldaho Operations office, ldaho Falls, ldaho Results are reported in units of Bqlkg (soil), BqIL (water) or Bqltotal sample (filters, vegetation).

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

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

The results of a repeat analysis were still unacceptable. A spiked air filter was prepared (known activity 4.17 pcilfilter) to verify the methodology; results of the spike analysis were acceptable, 4.64 pCiMilter.

' Corrected result. An error in calculation was found.

lncluded in the testing series as a "false positive". Result of reanalysis, 0.04 f 0.01 Bq/L.

Included in the testing series as a "false positive". Result of reanalysis, 3.78 f 2.03 BqIL.

'The reason for the deviation is unknown. Result of the original sample recount: 0.47 ? 0.07 Bq/L The analys~s was then repeated from the beginning. Result of reanalysis: 0.51 f 0.07 BqIL.

'The lower result was due to a higher than average background count used in the calculation. Average background result:, 4.1 1 f 0.61

TABLE A-7. lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)=.

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result Result Limits Acceptance STAP-1143 STAP-1143 STAP-1143 STAP-1143 STAP-1143 STAP-1143 STAP-1143 STAP-1143 STAP-I 143 STAP-1143 STAP-1143 STAP-1143 STAP-1143 Am-241 Co-60 Cs-134 CS-1 37 Fe-55 Mn-54 Pu-238 Pu-239140 Sr-90 U-23314 U-238 Uranium Zn-65 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STAP-1144 03/24/08 Gr. Alpha 13.08 + 1.09 8.8 4.56 - 13.2 Pass STAP-1144 03/24/08 Gr. Beta 99.90 t 3.09 92.2 56.80 - 135.0 Pass Ac-228 Am-241 Bi-212 Bi-214 CO-60 Cs-134 Cs-137 K-40 Mn-54 Pb-212 Pb-214 Sr-90 Th-234 U-23314 U-238 Uranium Zn-65 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result Result Limits Acceptance STVE-1146 STVE-I 146 STVE-1 146 STVE-1146 STVE-1 146 STVE-1146 STVE-1146 STVE-1146 STVE-1146 STVE-1 146 STVE-1146 STVE-I 146 STW-1147 STW-1147 STW-I 147 STW-1147 STW-I 147 STW-1147 STW-1147 STW-1147 STW-I 147 STW -1 147 STW-1147 STW-1147 STW-1147 STW-1120 STW-1120 Am-241 Cm-244 CO-60 CS-1 34 CS-1 37 K-40 Mn-54 Sr-90 U-23314 U-238 Uranium Zn-65 Am-241 CO-60 CS-1 34 CS-1 37 Fe-55 Mn-54 Pu-238 Pu-239140 Sr-90 U-23314 U-238 Uranium Zn-65 Uranium Zn-65 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

-~

a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency test~ng administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

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

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

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

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

' The analys~s was repeated by leaching and total dissolution methods. Total dissolution yielded results within expected range.

Results of the reanalysis: U-233,4, 1655 ? 95 pCilkg. U-238 1805 ? 97 pCilkg.

APPENDIX B DATA REPORTING CONVENTIONS

Data Re~ortina Conventions 1.O. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.

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

x + s where:

x = value of the measurement; s = 20 counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is less than the lower limit of detection L, it is reported as: < L, where L = the lower limit of detection based on 4.660 uncertainty for a background sample.

3.0. Duplicate analyses 3.1 Individual results: For two analysis results; x, i s, and x, i s, Reported result:

x i s; where x = (112) (x, + x,)

and s = (1R) d s j + s:

3.2.

Individual results:

< L~, < L2 Reported result: < L, where L = lower of L, and L, 3.3.

Individual results:

x + s, < L Reported result:

x f s if x 2 L; < L otherwise.

4.0. Com~utation of Averaqes and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example,

- an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x,, x2... xn are defined as follows:

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

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

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

4.5 In rounding off, the following rules are followed:

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

4.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 1 1.45.

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

Table C-1.

Maximum permissible concentrations of radioactivity in air and water above natural a

background in unrestricted areas.

Air (p~i/m3)

Water (pCi/L)

Gross alpha 1 x 1 i3 Gross beta 1

b Iodine-1 31 2.8 x 16' Strontium-89 Strontium-90 Cesium-1 37 Barium-1 40 Iodine-1 31 Potassium-40 Gross alpha Gross beta Tritium a

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

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

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

C A natural radionuclide.

APPENDIX D Sampling Location Maps

TLO LOCATIONS ONE MILE RADIUS PLANT AREA ENLARGED PLAN E1.00 MILE

-- RADIUS]

[NO SCALE3 MONITORING LEGEND:

@ PCIAiRIE ISLAND I ' i D POihTS

TLD LOCATIONS

",/

2.7 W1.

\\ --. '-4 i /

-L1"

'7-

/

f;-v.

p!

v-'

+--- L.J "-C,..:.-

L..A,-!.-.

I-!

OlC ig 1 I

! 5

,/

-1

---i I

i.

\\

I...

.-..a,.......

CONTROL POINTS PRESCOTT, WISCONSIN ISFSI AREA TLD LOCATIONS MONITORING LEGEND:

@ PRAIRIE ISLANG T t D POINTS :

TLD LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:

@ PRAIRIE ISLAND TLD POINTS

ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS J

PLANT AREA ENLARGED PLAN C1.OO MILE RADIUS1

[NO SCALE1 M;LK SAMPLING POiNT ID NUMBERS 2 - t 4, F-i8. P-37, P-42, P-43, P-44 FISH SAMPL!M; POINT ID NUMBERS P-13, P-19 WOTEH SaWPIING P3IVT iG NbYBERS t&)

SEDIMENT SAPPL.IFVG POlNT 10 NUMBERS P-5, P-6, P-8, P-9.

D - i l. P-2c. F-43 P-6. P-12. P-20

,lEGElay:ON / VEGE-@G'ES ID NUMBERS

"-24, P-38, "-45

ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS MONITORING LEGEND MILK SaMPLING POIST 10 NUMBERS P-14, P-18. P-37. P-42. P-43. P-44 01R SAMPLING POINT !O NUMBERS

- P-I, P-2. P-3. P-4. F - 6 WnTER 56YPLIUG POINT 10 NUMBERS 9

3-5. 5-(;. 3-8. P-9, P-il. P-24. P-43 FISH SAMPLING POINT I D NUMBERS P-13, P-19 INVERTEBRA:ES POINT 10 NUMBERS P-6, P-40 SEGIMENT SAMPL.INfl POfNT I D NUMBERS P-E. 0-12. P-211 1

VEGETATION / VEGETABLES !D NUMBERS

.-J P-24. P-38. P-45

,~.

it-:

I 5.E

---_--x__---.-~---_l----.-.-.---~.-.-

SAMPi33.DGN J I F.?...

.,,.&A?

- *,. ? ? -..

1 C

i @@ P-41, Huppert Farm, W10430 St Rd 29, River Falls, Wl 1

P43, Peterson Farm, W10322 St Rd 29, River Falls, WI f

P38, Caln Residence, N7395 950th St, Rlver Falls, WI CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND

@ MILK SAMPLING POINT ID NUMBERS P-14, P-18, P-37, P-41, P-42, P43, P-44 AIR SAMPLING,lNT 0

NUMBERS P-I, P-2, P-3, P4, P-6 WATER SAMPLING POINT ID NUMBERS Q

P4. ~ - 6,

pa. P-9, P~I, ~ 4 3 VEGETATION / VEGETABLES ID NUMBERS P-24. P-38, P46

APPENDIX E Special Well and Surface Water Samples

1.0 INTRODUCTION

This appendix to the Radiological Environmental Monitoring Program Annual Report to the United States Nuclear Regulatory Commission summarizes and interprets results of the special well and surface water samples taken at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 2008. This supplemental special sampling program was established in December of 1989 when higher than expected levels of tritium were detected in a nearby residence well sample.

Tabulations of the special sampling program individual analyses made during the year are included in this appendix. A summary table of tritium analyses is also included in this appendix.

2.0

SUMMARY

This special sampling program was established following the detection of tritium in a residence well water sample south of the PlNGP during 1989. This program is described and the results for 2008 are summarized and discussed.

Program findings for 2008 detect low levels of tritium in nearby residence wells and ground water surface samples at or near the expected natural background levels with the exception of sample wells P-10 and MW-8. The 2008 sample results (except for P-10 and MW-8) ranged from 4 9 pCi/L to 112 pCi/L. Sample well P-10 ranged from 58 pCi/L to 2060 pCi/L. Sample well MW-8 ranged from 359 pCi/L to 781 pCi/L. All tritium results are far below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L and present no harm to any members of the public.

3.0 Special Tritium Samplina Proaram 3.1 Proaram Desian and Data Interpretation The purpose of this sampling program is to assess the impact of any tritium leaching into the environment (ground water system) from the PINGP. For this purpose, special water samples are collected and analyzed for tritium content.

3.2 Proqram Description The sampling and analysis schedule for the special water sampling program is summarized in Table E-4.1 and briefly reviewed below. Table E-4.2 defines the additional sample locations and codes for the special water sampling program.

Special well and surface water samples were collected quarterly at one location, monthly at five locations, semi-annually at 6 locations, and annually at thirty-two locations. The Peterson (P-43) and Hanson (SW-1) farm wells are used as control locations for these special samples.

To detect low levels of tritium at or below natural background levels, analyses of the samples have been contracted to a laboratory (University of Waterloo Laboratories) capable of detecting tritium concentrations down to 19 pCi/L. Waterloo Laboratories report tritium analyses results in Tritium Units (1 TU = 3.2 pCiIL). The tritium results in this report are indicated in pCi/L.

3.3 Proqram Execution The special water sampling was executed as described in the preceding section.

3.4 Proqram Modifications Changes to the program in 2008 include:

sampling was not performed at station P-4 because it was inaccessible sampling was not performed at the STA house (SW-2) because it was dry added semi-annual sampling of onsite storage tanks, 11 CST (Condensate Storage Tank),

21 CST, 22 CST, Unit 1 demineralizer header, and Unit 2 demineralizer header (the September Unit 2 demineralizer header sample was not obtained) 3.5 Results and Discussion Results obtained show tritium in well water and ground water samples at or near expected natural background levels except the P-10 and MW-8 sample wells. Table E-4.4 provides the complete data table of results for each period and sampling location.

Results and Discussion (continued)

The tritium level annual averages have shown a downward trend since the special sampling begun in 1989.

Except for sample wells P-10 and MW-8, the 2008 sample results are within the range of expected background tritium levels in shallow ground water and surface water due to tritium concentrations measured in precipitation. Sampling points in North America have shown tritium concentrations in precipitation ranging from 5 pCi/L to 157 pCi/L (Environmental lsotope Data No. 10; World Survey of lsotope Concentration in Precipitation (1 988-1 991 )).

The higher level results at the Suter residence and Birch Lake in 1989 were possibly due to seepage from the PlNGP discharge canal water into the ground water. This is thought to occur due to the elevation difference between the Vermillion River and the discharge canal. The Suter residence is located between the discharge canal and Birch Lake, which connects to the Verrnillion River. The PlNGP discharge canal piping was lengthened during 1991, so that liquid discharges from the plant are released near the end of the discharge canal, diffused and discharged to the Mississippi River. In 1992, the underground liquid discharge pipe from the plant to the discharge canal piping was replaced with a double walled leak detectable piping system. This year's sample results continue to indicate that these modifications have eliminated the suspected radioactive effluent flow into the local ground water.

The elevated tritium levels in sample wells P-10 and MW-8 in 2008 may be due to prior leakage from the PlNGP liquid radwaste discharge pipe or discharge of turbine building sump water into the landlocked area. The liquid radwaste discharge pipe was replaced in 1992 and the discharge to the landlocked area has been minimized by administrative controls.

Table E-4.1 Sample collection and analysis program for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2008.

" Location codes are defined in table D-4.2. Control Stations are indicated by (C). All other stations are indicators.

Collection type is codes as follows: G/ = grab. Collection frequency is coded as follows: M = monthly; Q =

quarterly; S= semiannually: A = annually.

I Analysis type is coded as follows: H-3 = tritium.

Analysis type H-3 H-3 H-3 H-3 H-3 Location S-6 issampled semi-annually.

Collection typeb and frequency G/A G/Q G/M G/A G/S Medium Well Water Annual Well Water quarterly Well Water monthly Surface Water Storage Tank No.

29 1

5 6

5 Location codes and type a P-2, P-3, P-4, P-5, P-6, P-7, P-8, P-9, P-1 1, P-26, P-30, P-6 (REMP),

PllC-02, PllC-22, PllC-26, PZ-1, PZ-2, PZ-3, PZ-4, PZ-5, PZ-7, PZ-8, MW-4, MW-5, MW-6, SW-2, SW-3, SW-4, SW-5 P-24D P-43(C), SW-1 (C),

MW-7, MW-8, P-10 S-1, S-2, S-3, S-4, S-5, S-6 11 CST, 21 CST, 22 CST, U1 demin hdr, U2 demin hdr

1 Sample codes: WW = Well water; SW = Surface Water: ST = Storage Tank.

Table E-4.2. Sampling locations for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2008.

Distance and direction from reactor 1.O mi. @ 321 "NVNW 1.6 mi. @ 1 2g0/SE 1.4 mi. @ 315"INW 1 mi. @ 315"INW 1 mi. @ 315"INW 0.6 mi. @ 158"JSSE 13.9 mi. @ 355"JN 2.2 mi. @ 315"INW See map See map See map See map See map See map See map See map See map Type of sample a WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW Code P-8 REMP P-6 PllC-02 PllC-22 PllC-26 P-24D P-43 SW-1 P-2 P-3 P-4 P-5 P-6 P-7 P-10 P-11 PZ-l Collection site PI Community well Lock & Dam #3 well 2077 Other Day Road 1773 Buffalo Slough Rd 1771 Buffalo Slough Rd Suter residence Peterson Farm (Control)

Hanson Farm (Control)

Sample well Sample well Sample well Sample well Sample well Sample well Sample well Sample well Sample well

Table E-4.3 Radiological Environmental Monitoring Program Summary: Special well, storage tank, and surface water samples.

Name of Facility W e l s l a n d Nuclear Power Station Docket No.

50-282, 50-306 Location of Facility Goodhue, Minnesota OOOOOOO.............~

Reporting Period Ja>ary

- December 2008 (County, State) a H-3 =tritium LLD = Nominal lower limit of detection based on 4.66 sigma error for background sample. Value shown is lowest for the period.

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

Locations are specified by code.

Non-routine results are those which exceed ten times the control station value.

Control Locations Mean ( F ) ~

Range 40 (6124)

(24-59) 40 (6124)

(24-59)

Number Non-Routine Resultse 0

17 0

0 Indicator Locations Mean (F)'

~ange' 42 (711 1)

(20-56) 332 (49157)

(23-2060) 58 (717)

(31-92) 45 (819)

(31 -56)

Sample Type (Units)

Offsite Well Water

( pCilL)

Onsite Well Water (pCilL)

Onsite Surface Water (pCi/L)

Onsite Storage Tank (pCilL)

Location with Highest Annual

~ o c a t i o n ~

PllC-26 P-10 S-1 21 CST Type and Number of

,,,nalysesa H-3 35 H-3 81 H-3 31 H-3 23 Mean Mean (F)C

~ a n g e ~

51 ( I l l )

(51) 727 (12112)

(58-2060) 92 (111)

(92) 55 (212)

(54-56)

L L D ~

19 19 19 19

Table E-4 4 Radiolog~cal Environmental Monltor~ng Program Complete Data Table, 2008 P-8 P-6 (REMP)

PllC-02 PllC-22 PllC-26 P-24D P-43 SW-1 PI Comm Well Lock & Dam #3. Well 2077 Other Day Rd 1773 Buffalo Slough Rd 1771 Buffalo Slough Rd Suter res~dence Peterson Farm (Control)

Hanson Farm (Control)

<I9 41 9

<I9

<I9 4 9

<I9 a 9 3 1 42

<I9

<I9 32

<I9 4 9 52

~-

39 4 9 20

<I9 4 9 49 5 1

<I9 29

<I9 46 4 9 56 24 59

<I9 4 9

<I9

Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2008, continued P-2 P-3 P-5 P-6 P-7 P-10 P-11 PZ-l PZ-2 PZ-4 PZ-5 PZ-7 PZ-8 MW-4 MW-5 MW-6 MW-7 MW-8 P-26 P-30 SW-3 P-9 SW-4 SW-5 Sample Well Sample Well Sample Well Sample Well Sample Well Sample Well Sample Well Sample Well Sample Well Sample Well Sample Well Sample Well Sample Well Sample Well Sample Well Sample Well Sample Well Sample Well PlTC Well Env lab Well CT pump Plant Well # 2 New Adm~n Pln Scrnhs 479 48 419 58 37 61 1 120 48 501 138 53 78 1 1341 44 754 1536 36p 496 44 112 69 5 1 48 2060 52 51

<19 51 50

<I9 35 4 9

<I9

<19 66 412 1374 39 457 60 4 9 25 4 9 23 4 9 736 24 487 384 83 451 300 50 359 1

115 84 586

Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2008, continued S-I S-2 S-3 S-4 S-5 S-6 M~ss~ss~pp~

R~ver upstream Rec~rculat~onllntake canal Cooling water canal D~scharge Canal (end)

D~scharge Canal (mtdway)

Stormwater runoff 88 92 36 28 3 1 45 89

Table E-4 4 Radlolog~cal Env~ronmental Mon~tortng Program. Complete Data Table 2008. continued 22 CST U1 Demin Header U2 Demin Header Storage tank Storage tank Storage tank 3 1 52 40 38 43 I

L-PI-09-058, Submittal of 2008 Annual Radiological Environmental Monitoring Program (REMP) Report, Technical Specification) 5.6.2, Appendix a

Contents

Text

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

Navigation menu

L-PI-09-058, Submittal of 2008 Annual Radiological Environmental Monitoring Program (REMP) Report, Technical Specification) 5.6.2, Appendix a

Text

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

Navigation menu

Search