ML071350508

2006 Annual Environmental Monitoring Report

ML071350508
Person / Time
Site:	Kewaunee
Issue date:	04/18/2007
From:	Hartz L Dominion Energy Kewaunee
To:	Document Control Desk, NRC/NRR/ADRO
References
07-0286, FOIA/PA-2010-0209
Download: ML071350508 (321)

Text

• Dominion Energy Kewaunee, Inc.

N490 Highway 42, Kewaunee, WI 54216-9511 .r Dominion APR 1 8 2007 U. S. Nuclear Regulatory Commission Serial No. 07-0286 Attention: Document Control Desk KPS/LIC/NW: RO Washington, DC 20555 Docket No. 50-305 License No. DPR-43 DOMINION ENERGY KEWAUNEE. INC.

KEWAUNEE POWER STATION 2006 ANNUAL ENVIRONMENTAL MONITORING REPORT Enclosed is the 2006 Annual Environmental Monitoring Report for the Kewaunee Power Plant Station (KPS). This report was prepared by Environmental Inc. and satisfies the requirements of KPS Technical Specification 6.9.b.1.

The results of the 2006 Land Use Census, submitted in accordance with the KPS Radiological Environmental Monitoring Manual, Section 2.2.2/2.3.2, are also included in this report.

Ifyou have questions or require additional information, please feel free to contact Mr.

Mike Hale at 920-388-8103.

Very truly yours, Leslie N. Hartz Site Vice President, Kewaunee Power Station Enclosure Commitments made by this letter: NONE

.ýOý

IF Serial No. 07-0286 Page 2 of 2 cc: Regional Administrator, Region III U. S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, Illinois 60532-4352 NRC Senior Resident Inspector Kewaunee Power Station Ms. M. H. Chernoff Project Manager U.S. Nuclear Regulatory Commission Mail Stop 8 G9A Washington, D. C. 20555 Mr. Don Hendrikse WI Division of Public Health Radiation Protection Section Room 150 Madison, WI 53701-2659 Ms. Deborah Russo American Nuclear Insurers 95 Glastonbury Blvd.

Glastonbury, CT 06033

, Dominiono 2006 Annual Environmental Monitoring Report Kewaunee Power Station Dominion Energy Kewaunee, Inc.

2006 Annual Environmental Monitoring' Report Kewaunee Power Station PartI, Programmatic Review of Sampling Results Dominion Energy Kewaunee, Inc.

- Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road

• Northbrook, KL60062-2310 ph. (847) 564-0700 fax f (847) "56-4517 REPORT TO DOMINION NUCLEAR RADIOLOGICAL MONITORING PROGRAM FOR THE KEWAUNEE POWER STATION KEWAUNEE, WISCONSIN ANNUAL REPORT - PART I

SUMMARY

AND INTERPRETATION January 1 to December 31, 2006 Prepared and submitted by:

ENVIRONMENTAL Inc.

Midwest Laboratory Project No. 8002 f* - hA Approved :

La B r anager ry

!Y JLMchael Hale~

Radiation Protection /

Chemistry Mgr., KPS

PREFACE The staff of Environmental, Inc., Midwest Laboratory were responsible for the acquisition of data presented in this report. Assistance in sample collection was provided by Kewaunee Power Station personnel. The report was prepared by staff members of Environmental, Inc., Midwest Laboratory.

ii

TABLE OF CONTENTS Page Preface .......................................................................................................................................... ii List of Figures ............................................................................................................................... iv List of Tables .................................................. ........... IV 1.0 INTRO DUCTIO N .......................................................................................................................... 1 2.0

SUMMARY

.................................................................................................................................... 2 3.0 RADIOLOGICAL SURVEILLANCE PROGRAM ............................... 3 3.1 Methodology ............................................................................................................... 3 3.1.1 The Air Program ............................................................................................. 3 3.1.2 The Terrestrial Program ................................................................................. 4 3.1.3 The Aquatic Program ..................................................................................... 5 3.1.A Program Execution ........................................................................................ 6 3.1.5 Program Modifications .................................................................................... 6 3.2 Results and Discussion ............................................................................................... 7 3.2.1 Atmospheric Nuclear Detonations and Nuclear Accidents .............. 7 3.2.2 The Air Environm ent ...................................................................................... 7 3.2.3 The Terrestrial Environm ent ............................................................................... 9 3.2.4 The Aquatic Environm ent ................................................................................. 11 3.3 Land Use Census ..................................................................................................... 13 4.0 FIGURES AND TABLES ...................................................... 14

5.0 REFERENCES

........................................................................................................................... 27 APPENDICES A Interlaboratory Com parison Program Results ........................................................ A-1 B Data Reporting Conventions .................................................................................... B-1 C Maximum Permissible Concentrations of Radioactivity in Air and Water above Natural Background in Unrestricted Areas ................................................ C-1

• iii

LIST OF FIGURES No. Caption Paae 4-1 Sampling locations, Kewaunee Power Station .......................................................... 15

-4 LIST OF TABLES No. Title Page

,4.1 Sampling locations' Kewaunee Power Station .......................... 16 4.2 Type and frequency of collection ............................................................................. 17 4.3 Sample codes used in Table 4.2 ............................................................................. 17 4.4 Sampling summary, January- December, 2006 ...................................................... 18 4.5 Environmental Radiological Monitoring Program Summary ..................................... 19 4.6 Land Use Census ...................................................................................................... 25 In addition, the following tables are in the Appendices:

Appendix A A-1 Interlaboratory Comparison Program Results ......................................................... Al-1 A-2 Thermoluminescent dosimeters (TLDs) ....................................................................... A2-1 A-3 In-house Spiked Samples ............................................................................................. A3-1 A-4 In-house "Blank" Samples ........................................................................................... A4-1 A-5 In-house "Duplicate" Samples ...................................................................................... A5-1 A-6 Department of Energy MAPEP comparison results ...................................................... A6-1 Attachment A: Acceptance criteria for spiked samples .................................................. A-2 ...

Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas ............................................. C-2 iv r

1.0 INTRODUCTION

The Kewaunee Power Station is a 598 megawatt pressurized water reactor located on the Wisconsin shore of Lake Michigan in Kewaunee County. The Plant became critical on March 7, 1974. Initial power generation was achieved on April 8, 1974, and the Plant was declared commercial on June 16, 1974. This report summarizes the environmental operation data collected during the period January - December 2006.

Dominion Nuclear, an operating company for the Kewaunee Power Station, assumes the responsibility for the environmental program at the Plant and any questions relating to this subject should be directed to Mr. J. Michael Hale, Radiation -Protection / Chemistry Manager, at (920) 388-8103.

1*

2.0

SUMMARY

Results of sample analyses during the period January - December 2006 are summarized in Table 4.5. Radionuclide concentrations measured at indicator locations are compared with levels measured at control. locations and in preoperational studies. The comparisons indicate background-level radloactivities in all samples collected.

2

3.0 RADIOLOGICAL SURVEILLANCE PROGRAM Following is a description of the Radiological Surveillance Program and its execution.

3.1 Methodolog.y The sampling locations are shown in Figure 4-1. Table 4.1 describes the locations, lists for each direction and distance from the reactor, and indicates which are indicators and which are control locations.

The sampling program monitors the air, terrestrial, and aquatic environments. The types of samples collected at each location, and the frequency of 'collections are presented in Table 4.2, using sample codes defined in. Table 4.3. The collections and analyses that comprise the program are described below. Finally, the execution of the program In the current reporting year is discussed:

3.1.1 The Air Program Airborne Particulates The airborne particulate samples are collected on 47 mm diameter glass fiber filters at a volumetric rate of approximately one cubic foot per minute. The filters are collected weekly from six locations (K-If, K-2, K-7, K-8, K-16 and K-31), and dispatched by mail to Environmental, Inc. for radiometric analysis. The material on the filter is counted for gross beta activity approximately 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or later after collection to allow for decay of naturally-occurring short-lived radionuclides.

Quarterly composites from each sampling location are analyzed for gamma-emitting isotopes on a high-purity germanium (HPGe) detector.

Airborne Iodine Charcoal filters are located at locations K-If, K-2, K-7, K-8, K-1 6 and K-31. The filters are changed bi-weekly and analyzed for iodine-1 31 immediately after arrival at the laboratory.

Ambient Gamma Radiation - TLDs The integrated gamma-ray background is measured at the six air sampling locations (K-If, K-2, K-7, K-8, K-16 and K-31), at four milk sampling locations (K-3, K-5, K-25 and K-39), and four additional sites ( K-15, located 9.25 miles northwest of the plant; K-17, located 4.25 miles west of the plant; K-27, located 1.5 miles northwest of the plant and K-30, located 1.0 miles north of the plant ) by thermoluminescent dosimetry (TLDs). Two TLD cards, each having four main readout areas containing CaSO 4:Dy phosphor, are placed at each location (eight TLDs at each location). One card is exchanged quarterly, the other card is exchanged annually and read only on an emergency basis.

Precipitation Monthly composites of precipitation samples collected at K-1I are analyzed for tritium activity and counted using a liquid scintillation method.

3

3.1.2 The Terrestrial Progqram Milk Milk is collected semimonthly from May through October, and monthly during the rest of the year from five herds that graze within four miles of the reactor site (K-5, K-25, K-34, K-38 and K-39), from one herd grazing between four and ten miles from the reactor site (K-3), and from a dairy in Green Bay (K-28). The samples are analyzed for iodine-131, strontium-89 and strontium-90, cesium-137, barium-lanthanum-140, potassium-40, calcium and stable potassium.

Well Water One gallon of water is collected quarterly from four off-site wells located at K-I 0, K-1 1, K-I 3 and K-25 and from two on-site wells located at K-I g and K-I h.

Gamma spectroscopic analyses, tritium and gross beta on the total residue are performed for each water sample. The concentration of potassium-40 is calculated from the total potassium, on all samples.

Additionally, samples of water from two on-site wells (K-Ig and K-Ih) are analyzed for gross alpha.

Water from the on-site well (K-Ig) is analyzed for strontium-89 and strontium-90.

Domestic Meat Domestic meat samples are obtained annually (in the third quarter) at locations K-24, K-29 and K-32 and ifavailable at locations K-20, K-27 and K-34. The flesh is separated from the bones and. analyzed for gross alpha, gross beta and gamma emitting isotopes.

Eggs are collected quarterly from locations K-24, K-27 (if available) and K-32. Samples are analyzed for gross beta, strontium-89, strontium-90 and gamma-emitting isotopes.

Vegetables Vegetable samples (6 varieties) are collected at locations K-17 and K-26, and two varieties of grain, if available, at location K-23. The samples are analyzed for gross beta, strontium-89, strontium-90 and gamma emitting isotopes.

Grass and Cattle Feed Grass is collected during the second, third and fourth quarters from two on-site locations (K-I b and K-If) and from the dairy farm locations. Cattle feed is collected during the first quarter from the same farms. The samples are analyzed for gross beta, strontium-89 and -90, and gamma emitting isotopes.

Soil Soil samples are collected twice a year on-site at K-If and from the dairy farm locations (K-3, K-5, K-25, K-34, K-38 and K-39). The samples are analyzed for gross alpha, gross beta, strontium-89, strontium-90 and gamma emitting isotopes.

4

3.1.3 The Aquatic Proglram Surface Water One-gallon water samples are taken monthly from three locations on Lake Michigan: 1) at the point where the condenser water is discharged into Lake Michigan (K-Id); 2) Two Creeks Park (K-14) located 2.5 miles south of the reactor site; and 3) at the main pumping station located approximately equidistant from Kewaunee and Green Bay, which pumps water from the Rostok water intake (K-9) located 11.5 miles north of the reactor site. Both raw and tap water are. collected at K-9. One-gallon water samples are taken monthly from three creeks that pass through the site (K-la, K-lb, and K-Ie).

Samples from North and Middle Creeks (K-Ia, K-Ib) are collected near the mouth of each creek.

Samples from the South Creek (K-Ie) are collected about ten feet downstream from the point where the outflow from the two drain pipes meet. Additionally, the drainage pond (K-ik), located approximately 0.6 miles southwest of the plant, is included in the sampling program. Water samples at K-14 are collected and analyzed Induplicate.

The water is analyzed for gammaemitting isotopes, gross beta activity in total residue, dissolved solids and suspended solids, and potassium-40. The concentration of potassium-40 is calculated from total potassium, which is determined by flame photometry. In addition, quarterly composites of the monthly grab samples are analyzed for tritium, strontium-89 and strontium-90.

Fish Fish samples are collected during the second, third and fourth quarters at location K-Id. The flesh is separated from the bones, gamma, scanned and analyzed for gross beta activity. Ashed bone samples are analyzed for gross beta,' stroritium-89 and strontium-90 activities.

Slime Slime samples are collected during the second and third quarters from three Lake Michigan locations (K-Id, K-9 and K-14),"frorh . three creek locations (K-Ia, K-lb .and K-le) and from the drainage pond (K-1 k), if available., Thesamplfs are analyzed for gross beta activity. If the quantity is sufficient, analyses for gamma-emitting isotopes and strontium-89 and strontium-90 activities are performed.

Bottom Sediment Bottom sediments are collected in May and November from five locations (K-Ic, K-Id, K-lj, K-9 and K-14). The samples are analyzed for gross beta, strontium-89, strontium-90 and gamma emitting isotopes. It is known that the measured radioactivity per unit mass of sediment increases with decreasing particle size, and the sampling procedure is designed to assure collection of very fine particles.,

5

3.1.4 Program Execution Program execution is summarized in Table 4.4. The program was executed for the year 2006 as described in the preceding sections, with the following exception:

(1) Vegetable samples were not available at the indicator location K-1 7, Jansky's Farm. The garden has been discontinued. Additional vegetable samples were collected at locations K-34 and K-38.

(2) The surface water from location K-1 k could not be sampled in either March or December.

of 2006. The pond was frozen.

3.1.5 Program Modifications During 2006, no significant changes were made to the Radiological Environmental Monitoring Program.

6

3.2 Results and Discussion The results for the reporting period January to December 2006 are presented in summary form in Table 4.5. For each type of analysis, of each sampled medium, the table shows the annual mean and range for all indicator and control locations. The location with the highest annual mean and the results for this location are also given.

The discussion of the results has been divided into three broad categories: the air, terrestrial, and aquatic environments. Within each category, samples will be discussed in the order listed in Table 4.4.

Any discussion of previous environmental data for the Kewaunee Power Station refers to data collected by Environmental Inc., Midwest Laboratory.

The tabulated results of all measurements made in 2006 are not included in this section, although references to these results will be made In the discussion. A complete tabulation of results is contained in Part II of the 2006 annual report on the Radiological Monitoring Program for the Kewaunee Power Station.

3.2.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no atmospheric nuclear tests or accidents reported in 2006. The last reported test was conducted by the People's Republic of China on October 16, 1980.

3.2.2 The Air Environment Airborne Particulates 3

The annual gross beta concentration in air particulates measured 0.021 pCi/m at both the indicator and control locations. The averages were similar to the means observed from 1995 (and prior to) through 2005. Results are tabulated below.

Average of Average of Year Indicators Controls 3

Concentration (tCi/m) 1995 0.019 0.018 1996 0.020 0.019 1997 0.019 0.019 1998 0.019 0.019 1999 0.022 0.023 2000 0.022 0.021 2001 0.024 0.023 2002 0.023 0.023 2003 0.022 0.022 2004 0.019 0.020 2005 0.023 0.023 2006 0.021 0.021 Average annual gross beta concentrations in airborne particulates.

7

Airborne Particulates (continued)

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, with an average activity of 0.066 pCi/m 3 for all locations. All other gamma-emitting isotopes were below their respective LLD limits.

Airborne Iodine Bi-monthly. levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.030 3'

pCi/m at all locations. There is no indication of an effect of plant operation on the local air environment.

Ambient Gamma Radiation - TLDs Ambient gamma radiation was monitored by TLDs at fourteen locations: eight indicator and six control.

Quarterly TLDs at indicator locations measured a mean dose equivalent of (15.7 mR/91 days), in agreement with the mean at the control locations of (14.3 mR191 days), and were similar to the-means obtained from 1995 (and prior to) through 2005. The results are tabulated below. No plant effect on ambient gamma radiation was indicated These values are. slightly lower than the United States average value of 19.5 mR/91 days due to natural background radiation (National Council on Radiation Protection and Measurements, 1975). The highest annual mean was 19.2 mRI91 days, measured at the indicator location K-7.

Year Average (Indicators) Average (Controls)

Dose rate imRI91 days) 1995 16.7 15.6 1996 15.9, 14.9

'1997 16.0 15.1 1998 16.1 15.5 1999 17.4 16.9 2000 . 18.7 18.2 2001 18.6 18.3 2002 16.1 15.1 2003 14.1 13.7 2004 14.8 14.0 2005 15.7 14.3 2006 16.4 15.0 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates.

Precipitation Precipitation was monitored for tritium at indicator location, K-11. The concentration was below the LLD level of 182 pCi/L in all samples.

8

3.2.3 The Terrestrial Environment Milk Of 126 analyses for iodine-1 31 in milk, all were below the LLD level of 0.5 pCi/L.

Strontium-89 concentrations measured below an LLD level of 1.1 pCi/L in all samples. Low levels of strontium-90 were found In eighty one of the eighty four samples tested. Mean values were almost identical for indicator and control locations (1.1 and 1.0 pCi/L, respectively) and are similar to or less than averages seen from 1990 through 2005.

Barium-lanthanum-140 concentrations were below 15 pCi/L and cesium-134 and cesium-137 concentrations were below 10 pCi/L in all samples. Potassium-40 results were almost identical at both the indicator and control locations (1344 and 1341 pCi/L, respectively), and are comparable to levels observed from 1990 through 2005. There was no Indication of any effect due to the operation of the Kewaunee Power Station.

Due to the chemical similarities between strontium and .calcium, and cesium and potassium, organisms tend to deposit cesium-1 37 In the soft tissue and muscle and strontium-89 and strontium-90 in the bone. Consequently, ratios of Mtrontium-90 activity to the weight of calcium in milk and cesium-137 activity to the weight of potassium. in milk were monitored in order to detect potential environmental accumulation of these radionuclides. The measured concentrations of stable potassium and calcium are in agreement with previously determined values of 1.50 + 0.21 g/L and 1.16i 0.08 g/L, respectively (National Center for Radiological Health, 1968).

Well Water One sample for gross alpha analysis from the two on-site wells (K-I g and K-I h), was measured at the LLD value of 2.8 pCi/L. Gross beta activity, above an LLD of 1.5 pCViL was detected in 16 of the 24 samples tested. Gross beta concentrations averaged 2.6 pCi/L at the indicator locations and 1.6 pCVL for the control location.

Levels of strontium-89 and strontium-90 were measured for the on-site well (K-lg). The concentrations measured below the LLD value of 0.8 and 0.6 pCi/L, respectively.

All samples were tested for tritium and gamma emitting isotopes. Tritium concentrations measured below the LLD of 182 pCi/L. Gamma-emitting isotopes measured below respective LLDs.

Potassium-40 averages are generally in proportion to gross beta measurements and were in agreement with previously measured values. No plant effect was Indicated.

Domestic Meat In domestic meat samples, one sample for gross alpha analysis, from the control location (K-32),

measured 0.11 pCil/gwet, slightly above the lower limit of detection of 0.07 pCVgwet. Gross beta concentration averaged 3.27 pCi/g wet for indicator locations and 2.97 pCi/g wet for the control location. The differences are not significant. Gamma-spectroscopic analyses showed that almost all of the beta activity was due to naturally occurring potassium-40. All other gamma-emitting isotopes were below their respective LLD limits.

9ý

In egg samples, gross beta concentrations averaged 1.85 pCi/g wet for the indicator location and 1.62 pCi/g wet for the control, similar to concentrations of naturally-occurring potassium-40 observed in the samples ( 1.30 and 1.24 pCi/g wet respectively). Other gamma-emitting isotopes were below their respective LLDs. Levels of strontium-89 measured below- the LLD of 0.010 pCi/g wet in all samples, strontium-90 measured below the LLD level of 0.004 pCi/g wet.

Vegetables and Grain In vegetables, gross beta concentrations averaged 2.45 pCi/g wet at the control location K-26, due primarily to potassium-40 activity. All other gamma emitting isotopes measured below respective LLDs. Strontium-89 measured below the LLD level of 0.009 pCi/g wet. Strontium-90 measured below the LLD level of 0.003 pCig wet.,,

In two grain samples (clover and Oats) from location K-23, gross beta concentrations averaged 8.04 pCi/g wet, due primarily to potassium-40 and beryllium-7 activity (5.21 and 1.29 pCilg wet, respectively). Strontium-89 measured below the LLD level of 0.017 pCVg wet, strontium-90 measured below the LLD level of 0.006 pCi/g wet.

Grass and Cattle Feed In grass, mean gross beta concentrations measured 7.80 and 11.39 pCi/g wet at indicator and control locations, respectively, and in all cases was predominantly due to naturally occurring potassium-40 and beryllium-7. All other gamma-emitting isotopes were below their respective LLDs.

Strontium-89 measured below the LLD levels of 0.024. Strontium-90 activity measured below the LLD levels of 0.013 pCVgwet. -

In cattlefeed, the mean gross beta concentration was lower at the control locations (10.37 pCi/g wet) _.

than at indicator locations (15.76 pCi/g wet), and reflected the potassium-40 levels observed in the samples (7.47 and 11.47 pCi/gwet, respectively.). This; pattern is similar to that observed since 1978.

Strontium-89 levels were below the LLD level of 0.032 pCi/g wet in all samples. Low levels of strontium-90 activity, above the LLD value of 0.013 pCi/g wet were detected in five of twelve samples, and averaged 0.017 pCi/g wet, similar or lower than levels observed in 1995 through 2005. The presence of radiostrontium in the environment can still be attributed to fallout from nuclear testing in previous decades.

With the exception of naturally-occurring potassium, gamma-emitting isotopes were below their respective LLD levels.

Soil Gross alpha concentrations in soil samples averaged 8.48 pCi/g dry at the indicator locations and 11.41 pCVg dry at the control location. Mean gross beta levels measured at the indicator and control locations averaged 31.52 and 31.79 pCVg dry, respectively, primarily due to the potassium-40 activity.

Strontium-89 was below the LLD level of 0.076 pCVg dry in all samples. Low levels of strontium-90 activity were detected in eight of the fourteen samples tested and averaged 0.049 pCi/g dry.

Low levels of Cesium-137 were detected in twelve of fourteen soil samples, similar at both indicator and control locations (0.14 and 0.19 pCi/g dry, respectively). Potassium-40 was detected in all samples and averaged 20.36 and 19.72 pCi/g dry at indicator and control locations, respectively. All other gamma-emitting isotopes were below their respective LLD's. These levels of detected activities are similar to those observed from 1989 through 2005. The data suggests no evidence of a plant effect on soil.

10

3.2.4 The Aquatic Environment Surface Water In all surface water samples tested, gross beta activity in suspended solids measured below the LLD level of 1.5 pCi/L. Mean gross beta concentration in dissolved solids was higher at the indicator locations ( 5.5 pCi/L) as compared to the control locations (1.8 pCi/L). The pattern is similar to activity distribution observed from 1978 through 2005. . I .  :

Year Average (Indicators) Average (Controls)

Dose rate ImR/91 days) 1995 4.3 2.2 1996 4.3 2.2, 1997 6.3 2.4 1998 5.9 2.1 1999 5.6 2.2 2000 7.0 2.4 2001 5.9 2.2

.2002. 5.7 2.2-2003 7.3 2.4 2004 6.2 .2.3 2005 5.2 1.7 2006 5.5 1.8 Average annual gross beta concentrations in surface water (DS).

The difference in levels are due in part to the indicator location (K-1 k), a pond formed by drainage of surrounding fields to the southwest. The control sample Is Lake Michigan water, which varies very little in gross beta concentration during the year, while Indicator samples include the two creek locations (K-I a and K-Ie) which are much higher in gross beta concentration and exhibit large month-to-month variations. The K-Ia creek draws its water from the surrounding fields which are heavily fertilized; and the K-le creek draws its water mainly from the Sewage Treatment Plant. In general, gross beta concentrations were high when potassium-40 levels were high and low when potassium-40 levels were low, indicating that the fluctuations in beta concentration were due to variations in potassium-40 concentrations and not to plant operations. The fact that similar fluctuations at these locations were observed in the pre-operational studies conducted prior to 1974 supports this assessment.

No tritium activity was observed above a lower limit of detection (LLD) of 186 pCiIL.

Strontium-89 concentrations were below the LLD of 1.3 pCi/L. Strontium-90 averaged 1.0 pCi/L in two of twenty-eight indicator samples. All other samples measured below an LLD value of 0.7 pCi/L.

Gamma-emitting isotopes were below their respective LLDs in all samples.

11

Fish In fish, gross beta concentration averaged 3.43 pCi/g wet in muscle and 1.99 pCi/g wet in bone fractions. In musde, the gross beta concentration was primarily due to potassium-40 activity.

No cesium-137 activity was observed in muscle samples for 2006, above a detection limit of 0.095 pCi/gwet. This is below levels observed between 1979 and 1991 (average of 0.12 pCi/g wet), and similar to levels seen from 1992 through 2005, averaging 0.060 pCi/gwet.

The strontium-89 concentration was below the LLD of 0.76 pCi/g wet in all samples. Strontium-90 was detected above the LLD Value of 0.05 pCi/g wet and averaged 0.29 pCi/g wet.

Periphyton (Slime) or Aquatic Vegetation In periphyton (slime) and aquatic vegetation samples, mean gross beta concentrations were slightly higher at the control location than at the indicators (5.88 and 4.36 pCi/g wet, respectively), due primarily to combined potassium-40 and beryllium-7 activity (4.46 and 3.65 pCi/g wet, respectively).

Other gamma-emitting isotopes, with the exception of naturally-occurring beryllium-7 and potassium-40, were below their respective LLDs.

The strontium-89 concentration was below the LLD of 0.092 pCi/g wet in all samples. Strontium-90 was not detected above an LLD value of 0.019 pCi/g wet.

Bottom Sediments In bottom sediment samples, the mean gross beta concentrations measured 11.24 pCi/g dry at the indicator locations and 22.03 pCi/g dry at the control location.

Cs-1 34 measured below the LLD level of 0.030 pCi/g dry in all samples. A low level of cesium-1 37 was observed in one of the two control samples tested. The cesium-137 measured 0.080. pCi/g dry.

On average, cesium-137 measurements are lower than or similar to levels observed from 1979 through 2005.

Levels of strontium-89 and strontium-90 measured below respective detection limits of 0.035 pCi/g dry and 0.022 pCi/g in all samples.

12

3.3 Land Use Census The Land Use Census satisfies the requirements of the KPS Radiological Environmental Monitoring Manual. Section 2.2.2 states:

"A land use census shall be conducted and shall identify within a distance of 8 km (5 mi.) the location, in each of the 10 meteorological sectors, of the nearest milk animal, the. nearest residence and the nearest garden of

. 2 2 -

greater than 50m (500 ft ) producing broad leaf vegetation."

The 2006 Land Use Census was completed to identify the presence of the nearest milk animals, gardens and farm crops of the Kewaunee Power Station.

The Land Use Census was completed on September S, 2006. The census is conducted annually during the growing season per Health Physics Procedure HP 1.14.

Results of the 2006 census are summarized in Table 4.6.Changes from the 2005 census are listed by sector.

In summary, the highest D/Q locations for nearest garden, nearest residence and nearest milk animal did not change from the 2005 census.

- . .. . .x,  :

13

4.0 FIGURES AND TABLES 14

I ii U

Figure 4-1. Sampling locations, Kewaunee Power Station 15

KEWAUNEE Table 4.1. Sampling locations, Kewaunee Power Station.

Distance (miles)'

Code Typea and Sector Location K-1 Onsite K-I a 0.62 N North Creek K-I b 0.12 N Middle Creek K-Ic 0.10 N 500' north of condenser discharge K-id 0.10E Condenser discharge K-le 0.12S South Creek K-If 0.12S Meteorological Tower K-Ig 0.06 W. South Well K-I h 0.12 NW North Well K-lJ 0.10S .500' south of condenser discharge K-I k 0.60 SW Drainage Pond, south of plant K-2 C 9.5 NNE WPS Operations Building in Kewaunee K-3 C 6.0 N Lyle and John Siegmund Farm, N2815 Hy 12, Kewaunee K-5 3.5 NNW Ed Paplham Farm, E4160 Old Settlers Rd, Kewaunee K-7 2.75 SSW Ron Zimmerman Farm, 17620 Nero Road, Two Rivers K-8 C 5.0 WSW Saint Isidore the Farmer Church, Tisch Mills K-9 C 11.5 NNE Rostok Water Intake for Green Bay, Wisconsin, two miles north of Kewaunee K-1 0 1.5 NNE Turner Farm, Kewaunee site K-11 1.0 NW Harlan IhIenfeld Farm, N879 Hy 42, Kewaunee K-1 3 3.0 SSW Rand's General Store K-14 2.5S Two Creeks Park, 2.5 miles south of site.

K-1 5 9.25 NW Gas Substation, 1.5 miles north of Stangelville K-1 6 26 NW: WPS Division Office Building, Green Bay, Wisconsin K-17 4.25 W Jansky's Farm, N885 Tk B, Kewaunee K-20 2.5 N Cad Struck Farm, Lakeshore Dr, Kewaunee K-23 0.5 W 0.5 miles west of.plant; Kewaunee site K-24 5.45 N Fectum Farm, N2653-Hy 42, Kewaunee K-25 2.0 WSW Wotachek Farm, 4819 E;Cty Tk BB, Denmark -

K-26 10.7 SSW Bertler's Fruit Stand (8.0 miles south of "BB")

Kewaunee K-27 1.5 NW Schlies Farm, E4298 Sandy Bay Rd, K-28 26 NW Hansen Dairy, Green Bay, Wisconsin-K-29 5.75 W Kunesh Farm, Route 1, Kewaunee K-30 1.OON End of site boundary K-31 6.25NNW E. Krok Substation K-32 11.50 N Piggly Wiggly, 931 Marquette Dr., Kewaunee K-34 2.5 N Leon and Vicki Struck, N1549 Lakeshore Dr., Kewaunee K-38 3.0 ml. WNW Dave Sinkula Farm, N890 Town Hall Road, Kewaunee K-39 3.8 ml. N Francis and Sue Wojta, N1859 Lakeshore Dr., Kewaunee a I = indicator; C = control.

b Distances are measured from reactor stack.

16

KEWAUNEE Table 4.2. Type and frequency of collection.

Location Weekly Biweekly Monthly Quarterly Semiannually Annually K-Ia SW SL K-Ib SW GRO SL K-Ic _ BSý K-1 d SW Flo BSO, SL K-le SW SL K-If AP A] GR', TLD SO K-Ig WW K-I h WW K-lJ BS_

K-I k SW SL K-2 AP AI TLD K-3 MI0 GR_,TLD, CF_ so K-5 MI0 GR', TLD, CFr so K-7 AP Al " TLD K-8 AP Al TLD K-9 _SW BS_, SL K-10 _ WW K-I11 PR WW K-13 WW K-14 _ SW BSSL K-15 "_ TLD K-16 AP A] TLD K-17 TLD VE K-20 DM K-23 .... "__GRN K-24 .. ... EG DM K-25 .....

_MI, GRi, TLD, CFa, WW SO K-26 VE K-27 TLD. EG DM K-28 _ MIC K-29 _ "_ . ... . DM K-30 __ TLD K-31 AP ... Al. I...TLD K-32 _ EG DM K-34 MI0 GRi, CF* SO K-38 MI0 GRa, CFd SO K-39 MIr GRI, TLD, CFr SO

' Three times a year, second, third and fourth quarters. bTo *b collected In May and November.

Monthly from November through April; semimonthly May through October.

aFirst quarter (January, February, March) only.

Table 4.3. Sample Codes:

AP Airbome particulates MI Milk Al Airbome Iodine PR Precipitation BS Bottom (river) sediments SL Slime CF Cattlefeed SO Soil DM Domestic Meat SW Surface water EG Eggs TLD Thermoluminescent Dosimeter FI Fish VE Vegetables GRN Grain WW Well water GR Grass 17

Table 4.4. Sampling Summary, January - December 2006.

Collection Number of Number of Sample Type and Number of Samples Samples Type Frequencya Locations Collected Missed Air Environment Airborne particulates C/W 6 312 0 Airborne Iodine C/BW 6 156 0 TLD's C/Q 14 56 0 Precipitation C/M 1 12 0 Terrestrial Environment Milk (May-Oct) G/SM 7 84 0 (Nov-Apr) G/M 7 42 0 Well water G/Q 6 24 0 Domestic meat G/A 3 3 0 Eggs G/Q 2 8 0 Vegetables - 5 varieties G/A 1 6 0 Grain -oats G/A 1 1 0

- clover G/A 1 1 0 Grass G/TA 8 24 0 Cattle feed G/A 6. 12 0 Soil G/SA 7 14 0 Aquatic Environment Surface water G/M 7-. 106 2 Fish G/TA 14 1I 0 Slime G/SA 7 14 0 Bottom sediments G/SA 5 10 0 a Type of collection is coded as follows: C = continuous; G grab.

Frequency is coded as follows: W = weekly; BW = bi-weekly; SM = semimonthly; M= monthly; Q = quarterly; SA = semiannually; TA = three times per year; A = annually.

18

Table 4.5 Environmental Radiation Monitoring Program Summary.

Name of Facility Kewaunee Power Station Docket No. 50-305 Location of Facility Kewaunee County, Wisconsin Reporting Period January-December, 2006 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)f Mean (F)0 Mean (F)o Routine (Units) Analyses' Range0 Locationd Range= Range0 Results' TLDs (Quarterly) Gamma 56 3.0 16.4 (32/32) K-7, Zimmerman Farm 19.2 (4/4) 15.0 (24/24) 0 (mR/91days) (11.5-19.9) 2.75 ml. SSW (18.1-19.9) (11.8-18.5)

Airborne GB 312 0.002 0.021 (104/104) K-16, WPS Div. Off. 0.022 (52/52) 0.021 (208/208) 0 Particulates (0.008-0.041) 26 ml. NW (0.009-0.038) (0.007-0.038)

(pCI/in 3 ) GS 24 Be-7 0.020 0.066 (8/8) K-2, WPS Bldg. 0.073 (4/4) 0.066 (16116) 0 (0.049-0.083) 9.5 ml. NNE (0.068-0.077) (0.049-0.093)

Nb-95 0.0016 < LLD - < LLD 0 Zr-Nb-95 0.0026 < LLD - < LLD 0 Ru-103 0.0016 < LLD - < LLD 0 Ru-106 0.0085 < LLD -< LLD 0 Cs.134 0.0010 < LLD - < LLD 0 Cs-137 0.0010 < LLD < LLD 0 Ce-141 0.0023 < LLD < LLD 0 Ce-144 0.0047 < LLD < LLD 0 Airborne Iodine (pClrm 3

) 1-131 156 0.03 < LLD < LLD 0 Precipitation (pCI/L) H-3 12 ,-182 < LLD - None 0 Milk 1-131 126 0.5 < LLD < LLD 0 (pCi/L) Sr-89 84 1.1 < LLD < LLD 0 Sr-90 84 0.5 1.0 (57/60) K-3, Siegmund Farm 1.3(12/12) 1.1 (24/24) 0 (0.5-1.8) 6.0 ml. N (0.7-2.6) (0.6-2.6)

GS 126 K-40 50 1344 (90/90) K-34, Struck Farm 1422 (18/18) 1341 (36/36) 0 (1051-1552) 2.5 mi. N (1323-1552) (1182-1530)

Cs-134 10 < LLD < LLD 0 Cs-137 10 < LLD < LLD 0 Ba-La-140 15 < LLD < LLD 0 (g/L) K-stable 84 1.0 1.50 (60/60) K-34, Struck Farm 1.65 (12/12) 1.50 (24/24) 0 (1.22-1.74) 2.5 ml. N (1.57-1.74) (1.37-1.77)

(g/L) Ca 84 0.4 1.17 (60/60) K-5, Paplhain Farm 1.22 (12/12) 1.16 (24/24) 0

.(0.73-1.54) 3.5 mi. NNW (1.03-1.54) (0.98-1.35) 19

Table 4.5 Environmental Radiation Monitoring Program Summary.

Name of Facility Kewaunee Power Station Docket No. 50-305 Location of Facility Kewaunee County, Wisconsin- Reporting Period January-December, 2006 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLP Mean (F)r Mean (F)0 Mean (Ff Routine (Units) Analyse? Rangel' Locationd Rangd= Range= Result?

Well Water GA 8 2.8 2.8(118) K-lh, North Well 2.8(114) None 0 (pCi/L) 0.12 ml. NW GB 24 1.5 2.6(14/20) K-10, Turner Farm 3.6(3/4) 1.6 (2/4) 0 (1.5-5.0) 1.5 mi. NNE (2.8-5.0) (1.5-1.6)

H-3 24 182 < LLD - None 0 K-40(fp) 24 0.87 1.54 (20/20) K-10, Turner Farm 2.12 (4/4) 0.76(4/4) 0 (0.64-3.08) 1.5 mi. NNE (1.38-3.08) (0.67-0.86)

Sr-89 4 0.8 < LiD None 0 Sr-90 4 0.6 < LID None 0 GS 24 Mn-54 15 < LLD <LLD

<- 0 Fe-59 30 < LLD - , < LLD 0 Co-58 15 < LLD - -L <LID 0 Co-60 15 < LLD - - <LLD 0 Zn-65 30 < LLD < LLD 0 Zr-Nb-95 15 < LLD < LiD 0 Cs-134 10 < LLD -- < LLD 0 Cs-137 10 < LLD. - < LLD 0 Ba-La-140 15 < LLD - < LLD 0 Domestic Meat GA 3 0.070 < liD K-32, Grocery 0.11 (111) 0.11 (11) 0

ý11.5 mi. N (pCl/gwet) GB 3 0.030 3.27 (2/2) K-24, Fectum Farm 3.37 (1/1) 2.97 (111) 0' (3.17-3.37) 5.45 mi. N GS 3 Be-7 0.30 < LLD - - <LID 0 K-40 0.50 3.03 (2/2) K-29. Kunesh Farm 3.07(1/1) 2.50 (1/1) 0 (2.99-3.07) 5.75 ml. W -

Nb-95 0.053 < LiD - < LLD 0 Zr-95 0.071 < LLD < LLD 0 Ru-103 0.054 < LLD - < lID 0 Ru-106 0.18 < LLD - < LLD 0 Cs-134 0.018 < LLD < LiD 0 Cs-137 0.021 < LiD < LiD 0 Ce-141 0.11 < LiD - < LiD 0 Ce-144 0.10 < LiD - < LLD 0 Eggs GB 8 0.010 1.85(4/4) K-24, Fectum Farm 1.85(4/4) 1.62(4/4) 0 (pCi/gwet) (1.76&1.91) 5.45 mi. N (1.76-1.91) (1.31-1.85)

Sr-89 8 0.010 < LLD < LiD 0 Sr-90 8 0.004 < LD < LiD 0 GS 8 Be-7 0.097 < LLD < LLD 0 K-40 0.50 1.30(4/4) K-24, Fectum Farm 1.30 (4/4) 1.24(4/4) 0 (1.21-1.42) 5.45 mi. N (1.21-1.42) (1.11-1.32)

Nb-95 0.011 < LID - < LLD 0 Zr-95 0.018 < LiD - < LiD 0 Ru-103 0.011 < LID -- < LiD 0 Ru-106 0.078 < LID - < LLD 0 Cs-134 0.007 < LiD - < LLD 0 Cs-137 0.011 < LLD - < LLD 0 Ce-141 0.023 < LLD - < liD 0 Ce-14 0.077 < LLD < LID 0 20

Table 4.5 Environmental Radiation Monitoring Program Summary.

Name of Facility Kewaunee Power Station

• Docket No. 50-305 Location of Facility Kewaunee County, Wisconsin Reporting Period January-December, 2006 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-0 Mean (F)c Routine Type Number of LLD.P Mean (F) Mean (F).

(Units) Analyses Raner Locationd Range' Rangs Results' Vegetables GB 6 0.010 None K-26, Bert'er's 2.45 (616) 2.45 (6/6) 0 (pCl/gwet) 10.7 mi. SSW (1.82-3.50) (1.82-3.50)

Sr-89 6 0.009 None. < LLD 0 Sr-90 6 0.003 None <LLD 0 0

GS 6 Be-7 0.092 None - LLD 0 K-40 0.50 None K-26, Oertlers 1.75 (616) 1.75 (6/6) 0

- 10.7 mi. SSW (1.16-1.78) (1.16-1.78)

Nb-95 0.010 None - < LLD 0 Zr-95 0.016 None -- ILD L 0 Ru-103 0.010 None "- LLD 0 Ru-106 0.059 None -- .< LLD 0 Cs-134 0.006 None -. < LLD 0 Cs-1 37 0.007 None -- < LD 0 Ce-141 0.020 None <LLD

<- 0 Ce-144 0.055 None < LLD

<- 0 Grain - GB 2 0.010 8.04 (212) K-23, Kewaunee 8.04 (2/2) None 0 Oats & Clover (6.56-9.52). Site, 0.5 ml. W (6.56-9.52)

(pCi/gwet) Sr-89 2 0.017 < LLD - None 0 Sr-90 2 0.006 < LLD - None 0 GS 2 Be-7 0.50 1.29 (2/2) K-23, Kewaunee 1.29 (2/2) None 0 (1.27-1.30)' Site, 0.5 ml. W (1,27-1.30)

K-40 0.50 5.21 (2/2) K-23, Kewaunee 5.21 (212) None 0 b0 (4.03-6.38) Site, 0.5 ml. W (4.03-6.38)

Nb-95 0.021 LLD - - None 0 Zr-95 0.030 < LiD - -, None 0 Ru-103 0.012 < LLD - - None 0 Ru-106 0.18 c LLD - - None 0 Cs-1 34 0.017 < LLD - - None 0 Cs-137 0.017 c LLD - - None 0 Ce-141 0.049 < LLD None 0 Ce-144 0.11 < LLD None 0 Cattlefeed GB 12 0.10 15.76 (10/10) K-5, Paplham Farm 23.22(2/2) 10.37 (212) 0 (pci/gwet) (5.25-34.16) 3.5 ml. NNW (12.28-34.116) (6.06-14.67)

Sr-89 12 0.032 < iD <iD L-. 0 Sr-90 12 0.013 0.017 (5/10) K-5, Paplham Farm 0.023(1/2) <LLD 0 (0.014-0.023) 3.5 ml. NNW GS .12 Be-7 0.39 0.42(1110) K-3, Siegmund Farm 0.62 (112) 0.62(1/2) 0 6.0 ml. N

" K-40 0.10 11.47 (10/10) K-34, Struck Farm 15.64(2/2) 7.47(212) 0 (3.84-21.69) 2.5 mi. N (15.13-16.15) (4.27-10.66) 21

Table 4.5 Environmental Radiation Monitoring Program Summary.

Name of Facility Kewaunee Power Station Docket No. 50-305 Location of Facility Kewaunee County, Wisconsin Reporting Period January-December, 2006 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)0 Mean (F)0 Mean (F)0 Routine (Units) Analyse? . _ Rangd Locationd Rangel Rangd= Result?

Cattlefeed Nb-95 .0.047 <LID - - < LLD 0 (continued) Zr-95 0.070 < LiD - -< LiD 0 Ru-103 0.041 <LiD -< LLD 0 Ru-106 0.25 < LLD - -< LLD 0 Cs-134 0.045 < LLD - -< LLD 0 Cs-137 . 0.030 < LLD < LiD 0 Ce-141 0.082 < LLD < LiD 0 Ce-144 0.24 < LLD -<LLD 0 Grass GB 24 0.10 7.80 (21121) K-3, Siegmund Farm 11.39 (3/3) 11.39(3/3) 0 (pCi/gwet) (4.72-11.46) 6.0 ml. N (10.24-13.57) (10.24-13.57)

Sr-89 24 0.024 < LID < LLD 0 Sr-90 24 0.013 < LiD - < LLD 0 GS 24 Be-7 0.10 2.73 (21121) K-lb, Middle Creek 4.08 (3/3) 3.53 (313) 0 (0.57-7.27) 0.12 mi. N (1.57-7.27) (0.72-5.99)

K-40 0.50 5.99 (21121) K-3, Siegmund Farm 7.74 (3/3) 7.74 (313) 0 (3.60-8.27) 6.0 ml. N (5.68-10.01) (5.68-10.01)

Nb-95 0.043 < LD - < LLiD 0 Zr-95 0.078 < LiD <-LLiD 0 Ru-103 0.043 <LID < LD 0 Ru-106 0.25 < LLD - LiD 0 Cs-134 0.032 < LLD <.LLD 0 Cs-137 0.040 < LLD < LiD 0 Ce-141 0.10 < LLD <-LLiD 0 Ce-144 0.34 < LLD - 'LiDL- 0 Soil GA 14 0.50 8.48 (12/12) K-3, Siegmund Farm 11.4-1 (2/2) 11.41 (2/2) 0 (pCilgdry) (5.06-11.31) 6.0 ml. N (11.04-1,1.77) (11.04A11.77)

GB 14 0.10 31.52 (12/12) K-38, Sinkula Farm 37.02(2/2) 31.79 (2/2) . 0.

(21.91-40.02) 3.8 ml. WNW (34.01-40.02) (30.62-32.95)

Sr-89 14 0.076 < LID < LiD 0 Sr-90 14 0.027 0.053 (6/12) K-38, Sinkula Farm 0.065(2/2) 0.038(2/2) 0 (0.033-0.089) 3.8 ml. WNW (0.040-0.089) (0.034-0.042)

GS 14 Be-7 0.37 0.61 (2/12) K-34, Struck Farm 0.61 (2/12) <LID 0 (0.41-0.80) 2.5 ml. N (0.41-0.80)

K-40 1.4 20.36 (12/12) K-38, Sinkula Farm 23.19(2/2) 19.72(2/2) 0 (14.87-23.79) 3.8 ml. WNW (22.59-23.79) (19.35-20.08)

Nb-95 0.036 < LID - < LiD 0 Zr-95 0.057 < LLD - < LLD 0 Ru-103 0.031 < LID - < LD 0 Ru-106 0.21 < LLD - < LLD 0 Cs-1 34 0.041 < LLD - < LLD 0 Cs-137 0.026 0.14 (10/12) K-38, Sinkula Farm 0.24 (2/2) 0;19 (2/2) 0 (0.078-0.25) 3.8 ml. WNW (0.22-0.25) (0.18-0.19)

Ce-141 0.053 < LID < LLD 0 Ce-144 0.17 < LID < LiD 0 22

Table 4.5 Environmental Radiation Monitoring Program Summary.

Name of Facility Kewaunee Power Station Docket No. 50-305 Location of Facility Kewaunee County, Wisconsin Reporting Period January-December, 2006 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-0 0 Type Number of LLDP Mean (F) Mean (F)' Mean (F) Routine 0 Rangle' Rangdý Results?

(Units) Analyses" Range Locatlond Surface Water GB (SS) 106 1.5 < LLD -< LLD 0 (pCi/L) GB (DS) 106 0.5 5.5(82/82) K-la, North Creek 10.1 (12112) 1.8(24/24) 0 (1.1-22.5) 0.62 mi. N (2.9-17.7) (0.6-3.1)

GB (TR) 106 0.5 5.5 (82182) K-Ia, North Creek 10.1 (12/12) 1.8 (24/24) 0 (1.1-22.5) 0.62 mi. N (2.9-17.7) (0.6-3.1)

GS 106 Mn-54 15 < L.LD < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 15 < LLD - - < LLD 0 Co-60 15 < LLD - - < LLD 0 Zn-65 30 < LLD- - < LLD 0 Zr-Nb-95 15 < LLD .- < LLD 0 Cs-134 10 < LLD <LLD

<- 0 Cs-137 10 < LLD < LLD 0 Ba-La-140 15 < LLD ,LLD <- 0 H-3 36 186 < LLD --<LLD 0 Sr-89 36 1.3 <LLD < LLD 0 Sr-90 36 0.7 1.0 (2/28) K-la, North Creek 1.2 (114) < LLD 0 (0.7-1.2) 0.62 ml. N K-40 106 0.60 3.6(82/82) K-la, North Creek 8.3(12/12) 1.1 (24/24) 0 (0.6-19.5) 0.62 ml. N (3.9-13.8) (0.6-1.5)

Fish (Muscle) GB 4 0.5 3.43 (414)' K-1d, Cond. Discharge 3.43 (414) None 0 (pCI/gwet) (2.69-4.03) 0.10 mi. E (2.69-4.03)

GS 4 K-40 0.5 2.78 (4/4) K-Id, Cond. Discharge 2.78 (4/4) None 0 (2.09-3.33) 0.10 mi. E (2.09-3.33)

Mn-54 0.066 < LLD None 0 Fe-59 0.087 < LLD None 0 Co-58 0.099 < LLD None 0 Co-60 0.062 < LLD None 0 Cs-134 0.12 < LLD - None 0 Cs-137 , 0.095 < LLD None 0 Fish-(Bones) GB 4 1.99 2.18(414) K-Id, Cond. Discharge 2.18 (4/4) None 0 (pCi/gwet) (1.56-2.69) 0.10 mi. E (1.56-2.69)

Sr-89 4 0.76 < ULD -.-- None 0 Sr-90 4 0.050 0.29 (414) K-Id, Cond. Discharge 0.29 (414) None 0 (0.075-0.60) 0.10 ml. E (0.075-0.60) 0 23

Environmental Radiation Monitoring Program Summary.

Name of Facility Kewaunee Power Station Docket No. 50-305 Location of Facility Kewaunee County, Wisconsin Reporting Period January-December, 2006 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)0 Mean (F)0 Mean (F)0 Routine (Units) Analysed? Rangel' Locationd Ranged Rangde Results?

Pedphyton GB 14 0.1 4.36 (12/12) K-la, North Creek 6.15 (2/2) 5.88 (2/2) 0 (Slime) (2.31-6.16) 0.62 mi. N (6.13-6.16) (4.73-7.03)

(pCi/gwet) Sr-89 14 0.092 < LLD < LLD 0 Sr-90 14 0.019 0.094 (2/12) K-lb, Middle Creek 0.13 (1/2) < LLD 0 (0.058-0.13) 0.12 ml. N GS 14 Be-7 0.17 0.96 (11/12) K-14, Two Creeks Park 1.55(2/2) 0.64(1/2) 0 (0.25-1.82) 2.5 mi. S (1.28-1.82)

K-40 0.5 2.69 (12/12) K-la, North Creek 4.19(2/2) 3.82(2/2) 0 (0.86-5.15) 0.62 ml. N (3.60-4.78). (3.4-4.24)

Mn-54 0.034 < LLD - - < LLD 0 Co-58 0.031 < LLD - - < LLD 0 Co-60 0.024 < LLD - < LLD 0 Nb-95 0.948 < LLD - -< LLD 0 Zr-95 0.077 < LLD - - < LLD 0 Ru-103 0.042 < LLD - - < LLD 0 Ru-106 0.23 < LLD - < LLD 0 Cs-134 0.040 < LLD -- < LD 0 Cs-1 37 0.037 < LLD - < LLD 0 Ce-141 0.11 < LLD < LLD 0 Ce-144 0.26 < LLD - . < LLD . 0 Bottom GB 10 1.0 11.24 (81/8) K-9, Rostok Intake 22.03 (2/2) 22.03 (2/2) 0 Sediments (8.66-14.84) 11.5 ml. NNE (17.44-26.61) (17.44-26.61)

(pCi/gdry) Sr-89 10 0.035 < LLD <LLD 0 Sr-90 10 0.022 < LLD < LLD 0 GS 10 K-40 0.5 9.04 (8/8) K-lc, Cond. Discharge 10.75(2/2) 8.67 (2/2) 0 (5.97-11.01) 0.10 mi. N (10.48-11.01) (8.26-9.08)

Co-58 0.000 < LLD <LLD LL Co-60 0.023 < LLD <-LLD 0 Cs-1 34 0.030 < LLD < LLD 0 Cs-1 37 0.026 < LLD K-9, Rostok Intake 0.080 (2/2) 0.080(2/2) 0 11.5 mi. NNE (0.078-0.082) (0.078-0.082)

• GA = gross alpha, GB = gross beta, GS = gamma spectroscopy, SS = suspended solids, DS = dissolved solids, TR = total residue.

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

c Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specified locations Is indicated in parentheses (F).

d Locations are specified by station code (Table 4.1) and 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 times the preoperational value for the location.

24

Table 4.6 Land Use Census 2

The following table lists an Inventory of residence, gardens > 500 ft and milk animals found nearest to the plant in each of the 10 meteorological sectors within a five mile radius of the Kewaunee Power Station.

Sector Township Residence Garden Milk Animals Distance From Location ID No. _ Plant (miles)

A 12 _ _x__ 3.23 A 13 X _ 3.05 A 24 X 1.81 B 18 X 2.69 K-34 B 24 X __1.26 B 24 X 1.47 K-19 R 23  : X 2.21 R 23 X 1.84 R 26 X 1.05 K-1I Q 23 X Xa 1.37 Q 23 _ _X 1.47 K-27 P 20 X 4.20 P 26 X 1.42 P 26 X 1.52 N 26 X __ 1.16 N ,34 X 2.53 N 35- X 1.05 M 34 X 1.58 M 34 X 1.98 K-25 M 35 X 1.42 L 35 X ,_1.05 L 35 X X 1.30 K 15 Xi 3.43 K 35 X X 0.96 11 X X (Note 1) 2.68 Note 1. There were no milk animals located in Sector J within five miles of the Kewaunee Power Station.

a denotes a change from 2005 census data.

25

Land Use Census (continued)

The following is a sector by sector listing of those changes between the 2005 and 2006 census.

Sector A The nearest milk animal was observed at the Stangel Farm, 3.23 mi. in Township 12.

Sector B No changes Sector R No garden was planted in 2006 at the Ihlenfeldt farm. The nearest garden in .the sector is located at the Mueller residence, 1.84 mi. in Township 23.

Sector Q A new garden was observed at the K. Schlies farm, 1.37 mi. in Township 23.

Sector P No changes Sector N No changes Sector M No changes Sector K Englebrecht Farm sold the herd. The nearest milk animal was observed at the Barta farm, 3.43 mi. in Township 15.

Sector J No changes

-,A=

26

5.0 REFERENCES

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.

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

Environmental, Inc., Midwest Laboratory. 2007. Annual Report. Radiological Monitoring Program for the Kewaunee Power Station, Kewaunee, Wisconsin, Final Report, Part II, Data Tabulations and Analysis, January - December 2000 - 2006.

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

2000. Quality Control Procedures Manual, Rev. 0,17 September 2005.

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

Hazelton Environmental Sciences, 1979 through 1983. Annual Reports. Radiological Monitoring for the Kewaunee Power Station, Kewaunee, Wisconsin, Final Report - Part II, Data Tabulations and Analysis, January - December, 1978 through 1982.

Industrial BIO-TEST Laboratories, Inc. 1974. Annual Report. Pre-operational Radiological Monitoring Program for the Kewaunee Power Station. Kewaunee, Wisconsin. January - December 1973.

Industrial BIO-TEST Laboratories, Inc. 1975 Semi-annual Report. Radiological Monitoring Program for the Kewaunee Power Station, Kewaunee; Wisconsin. Jan. - June, 1975.

NALCO Environmental Sciences. 1977, 1978. Annual Report. Radiological Monitoring Program for the Kewaunee Power Station, Kewaunee, Wisconsin, Final Report- Part II, Data Tabulations and Analysis, January - December 1976, 1977.

National Center for Radiological Health. 1968. Section 1. Milk Surveillance. Radiological Health Data Rep.,

December 9: 730-746.

National Council on Radiation Protection and Measurements. 1975. Natural Radiation Background in the United States. NCRP Report No. 45.

Solon, L. R., W. M. Lowder, A. Shambron, and H. Blatz. 1960. Investigations of Natural Environmental Radiation. Science. 131: 903-906.

Teledyne Brown Engineering, Environmental Services, Midwest Laboratory. 1984 through 2000. Annual Reports. Radiological Monitoring Program for the Kewaunee Power Station, Kewaunee, Wisconsin, Final Report, Part II, Data Tabulations and Analysis, January - December 1983 through January -

December 1999.

U.S. Environmental Protection Agency, 2007. RadNet, formerly Environmental Radiation Ambient Monitoring System, Gross Beta In Air (WI) 1981 -2000.

Wilson, D.W., G. M. Ward, and J. E. Johnson, 1969. Environmental Contamination by Radioactive Materials.

International Atomic Energy Agency, p. 125 27

- Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road

• Northbrook. I 60062-2310 Ph. (847) 564-0700 ftax (847) 5%4-4517 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, 2006 through December, 2006

Appendix A Interlaboratory Comparison Pro-ram 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 NIST traceable sources. Data for previous years available upon request.

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

Table A-5 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.

Oufof-limit results are explained directly below the result.

Al

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 5 to 100 pCi/liter or kg 5.0 pCi/liter

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

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

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

> 20 pCi/liter 25% of known value Gross beta 5 100 pCi/liter 5.0 pCi/liter

> 100 pCi/liter 5% of known value Tritium 5 4,000 pCi/liter Ila = (pCi/liter) 169.85 x (known) 0 933 '

> 4,000 pCi/liter 10% of knownvalue Radium-226,-228 a 0.1 pCi/liter .15% of known value Plutonium > 0.1 pCi/liter, gram, or sample -10% of known value lodine-131, < 55 pCi/liter 6.0 pCi/liter Iodine-129b > 55 pCi/liter 10% of known value Uranium-238, 5 35 pCi/liter 6.0 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter

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

b Laboratory limit.

A2

TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)8 .

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultf Limits Acceptance STW-1078 01/16/06 Sr-89 49.9 +/- 3.5 50.2 41.5 -58.9 Pass STW-1078 01116/06 Sr-90 31.5 +/- 1.5 30.7 22.0 - 39.4 Pass STW-1079 01116/06 Ba-133 86.5 +/- 4.1 95.0 78.6 -111.0 Pass STW-1079 01/16/06 Co-60 96.3 +/-4.1 95.3 86.6 - 104.0 Pass STW-1079 01/16/06 Cs-134 22.6 +/- 3.0 23.1 14.4 -31.8 Pass STW-11079 01/16/06 Cs-137 109.0 +/- 5.9 111.0 101.0 - 121.0 Pass STW-1079 01/16/06 Zn-65 198.0 +/- 11.2. 192.0 159.0 - 225.0 Pass STW-1080 01116/06 Gr. Alpha 10.8 +/- 1.4 9.6 1.0 -18.3 Pass STW-1080 01/16/06 Gr. Beta 56.9 +/- 1.9 61.9 44.6 - 79.2 Pass S'TW-1081 01/16/06 Ra-226 4.3 +/- 0.4 4.6 3.4 -5.8 Pass STW-1081 01/16/06 Ra-228 7.1 +/- 1.8 6.6 3.7 -9.5 Pass STW-1081 01/16/06 Uranium 20.7 +/- 0.5 22.1 16.9 -27.3 Pass STW-1088 04/10/06 Sr-89 29.0 +/- 1.8 32.4 23.7 -41.1 Pass STW-1088 04/10106- Sr-90 8.7 +/- 1.0 9.0 0.3 - 17.7 Pass STW-1089 04/10/06 Ba-133 10.3 +/- 0.4 10.0 1.3-18.7 Pass STW-1089 04/10/06 Co-60 114.0 +/- 2.8 113.0 103.0 - 123.0 Pass STW-1089 04/10/06 Cs-134 41.9 +/- 1.4 43.4 34.7 -52.1 Pass STW-1089 04/10/06 Cs-137 208.0 +/- 1.1 214.0 195.0 - 233.0 Pass STW-1089 04/10/06. Zn-65 154.0 +/- 0.8 152.0 126.0 - 178.0 Pass STW-1090 04/10/06 Gr. Alpha 13.4 +/- 1.1 21.3 12.1 -30.5 Pass STW-1090 04/.1.0106 Gr. Beta 27.7 :k2.1 23.0 14.3 -31.7 Pass STW-1091 04/10/06 1-131 22.0 +/- 0.3 19.1 13.9 -24.3 Pass STW-1092 04/10/06 H-3 7960.0 +/- 57.0 8130.0 6720.0 - 9540.0 Pass STW-1092 04/10/06 Ra-226 2.9 +/- 0.4 3.0 2.2 - 3.8 Pass STW-1 092 04110/06 Ra-228 20.9 1.2 19.1 10.8 -27.4 Pass STW-1092 04/10/06 Uranium 68.6 +3.4 69.1 57.1 -81.1 Pass STW-1094 07/10/06 Sr-89 15.9 +/-0.7 19.7 11.0 -28.4 Pass STW-1094 07/10/06 Sr-90 24.3 + 0.4 25.9 17.2 -34.6 Pass STW-11095 07110/06 Ba-133 94.9 +/-8.9 88.1 72.9 - 103.0 Pass STW-1095 07/10/06 Co-60 104.0 + 1.8 99.7 91.0 -108.0 Pass STW-1095 07/10/06 Cs-1 34 48.7 - 1.3 54.1 45.4 - 62.8 Pass STW-1095 07110/06 Cs-1 37 236.0 +/- 3.0 238.0 217.0 - 259.0 Pass STW-1095 07/10/06 Zn-65 126.0 +/- 8.0 121.0 100.0 - 142.0 Pass STW-1096 07/10/06 Gr. Alpha 10.9 k 1.0 10.0 1.3 -18.6 Pass STW-1096 07/10/06 Gr. Beta 9.7 +/- 0.4 8.9 0.2 -17.5 Pass STW-1097 07110/06 Ra-226 11.0 +/- 0.5 10.7 7.9 -13.5 Pass STW-1097 07/10/06 Ra-228 12.2 +/- 0.8 10.7 6.1 -15.3 Pass STW-1097 07/10/06 Uranium 43.4 +/- 0.1 40.3 33.3 - 47.3 Pass A1-1

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1104 10/06/06 Sr-89 38.4 t 1.3 39.9 31.2 -45.7 Pass STW-1104 10/06/06 Sr-90 15.5 +/- 0.5 16.0 7.3 -24.7 Pass STW-1105 10/06/06 Ba-133 64.9 +/- 2.8 70.2 58.1 -82.3 Pass STW-1105 10/06/06 Co-60 61.6 +/- 1.0 62.3 53.6 -71.0 Pass STW-1 105 10/06/06 Cs-1 34 29.0 +/- 0.9 29.9 21.2 -38.6 Pass STW-1105 10/06/06 Cs-137 77.8 +/- 2.4 78.2 69.5 -86.9 Pass STW-1 105 10/06/06 Zn-65 293.0 +/- 2.4 277.0 229.0 - 325.0 Pass STW-1106 10/06/06 Gr. Alpha 23.9 +/- 2.5 28.7 16.3:- 41.1 Pass STW-1 1.06 10/06/06 Gr. Beta 23.7 +/- 1.4 20.9 12.2 -29.6 Pass STW-1 107 d 10/06106 1-131 28.4 +/- 1.2 22.1 16.9 -27.3 Fail STW-1 108 10/06/06 Ra-226 14.5 +/- 0.5 14.4 10.7-18.1 Pass STW-1 108 10/06/06 Ra-228 6.6 +/- 0.4 5.9 3.3 - 8.4 Pass STW-1 108 10/06/06 Uranium 2.9 +/- 0.1 3.2 0.0 - 8.4 Pass STW-1 109 10/06/06 H-3 3000.0 +/- 142.0 3050.0 2430.0 - 3670.0 Pass S Results obtained by Environmental, Inc., Midwest Laboratory as a participant inthe crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

r Results are presented as the known values, expe6ted laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.

d The reported result was an average of three analyses, results ranged from 25.36 to 29.23 pCi/L.

A fourth analysis was performed, result of analysis, 24.89 pCi/L.

A1-2

TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards).

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

2006-1 6/5/2006 30 cm 54.81 70.73 + 0.69 38.37 - 71.25 Pass 2006-1 6/5/2006 60 cm 13.70 16.71 +/- 1.89 9.59 - 17.81 Pass 2006-1 6/5/2006 60cm 13.70 16.69 +/- 0.94 9.59 - 17.81 Pass 2006-1 6/5/2006 90 cm 6.09 6.57 +/- 0.82 4.26 - 7.92 Pass 2006-1 6/5/2006 120 tm 3.43 3.65 +/- 0.22 2.40 - 4.46 Pass 2006-1 6/5/2006 120 cm 3.43 3.09 +/- 0.33 2.40 - 4.46 Pass 2006-1 6/5/2006 150 cm 2.19 2.35 +/- 0.38 1.53 -2.85 Pass 2006-1 6/5/2006 150 cm 2.19 1.98 +/- 0.10 1.53 - 2;85 Pass 2006-1 6/5/2006 180 cm 1.52 1.56 +/- 0.26 1.06 - 1.98 Pass Environmental, Inc.

2006-2 11/6/2006 30 cm. 55.61 60.79 +/- 1.32 38.93 - 72.29 Pass 2006-2 11/6/2006 40 cm. 31.28 35.93 +/- 3.70 21.90 - 40.66 Pass 2006-2 11/6/2006 50 cm. 20.02 21.55 +/- 1.20 14.01 - 26.03 Pass 2006-2 11/6/2006 60 cm. 13.90 14.90 + 1.42 9.73 - 18.07 Pass 2006-2 11/6/2006 75 cm. 8.90 8.03 + 0.51 6.23 - 11.57 Pass 2006-2 11/6/2006 90 cm. 6.18 6.88 +/- 0.68 4.33 - 8.03 Pass 2006-2 11/6/2006 120 cm. 3.48 2.90 +/- 0.20 2.44 -4.52 Pass 2006-2 11/6/2006 150 cm. 2.22 1.99 + 0.07 1.55 - 2.89 Pass 2006-2 11 /6/2006 180 cm. 1.54 1.79 +/- 0.94 1.08 - 2.00 Pass A2-1

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

Lab Code b Date Analysis Laboratory results Known Control 2s. n=1 C Activity Limits d Acceptance SPW-301 1/20/2006 Fe-55 2700.10 +/- 70.00 2502.50 2002.00 - 3003.00 Pass SPAP-1224 3/712006 Cs-134 37.13 +/- 3.70 39.52 29.52 - 49.52 Pass Cs-137 .118.25 +/- 8.97 119.30 107.37 - 131.23 Pass SPAP-1224 3/7/2006 SPAP-1224 3/7/2006 Gr. Beta 520.32 +/- 7.42 455.00 364.00 - 637.00 Pass SPW-1228 3/7/2006 H-3 70891.00 +/- 719.00 75394.00 60315.20 - 90472.80 Pass SPW-1 230 3/7/2006 Cs-134 38.58 +/- 2.10 39.51 29.51 - 49.51 Pass SPW-1230 3/7/2006 Cs-1 37 59.44 +/-4.51 59.65 49.65 - 69.65, Pass SPMI-1232 3/7/2006 Cs-134 41.20 +/- 1.33 39.51 29.51 - 49.51 Pass SPMI-1232 3/7/2006 Cs-1 37 57.82 +/- 3.96 59.65 49.65 - 69.65 Pass W-30906 3/9/20.06 Gr. Alpha 24.24 +/- 0.47 20.08 10.04 - 30.12 Pass W-30906 3/9/2006 - Gr. Beta 63.79 +/- 0.48 65.73 55.73 - 75.73 Pass SPW-2750 4/27/2006 Ni-63 116.00 +/- 2.49 100.00 60.00 - 140.00 Pass SPW-2869 5/1/2006 Fe-55 19473.00 +/- 188.00 23332.00 18665.60 - 27998.40 Pass SPAP-2871 5/1/2006 Cs-1 34 33.97 +/- 1.10 37.50 27.50 -47.50 Pass SPAP-2871 5/1/2006 Cs-137 114.44 +/- 2.81 118.90 107.01 - 130.79 Pass SPW-2875 5/112006 H-3 71057.00 +/- 730.20 75394.00 60315.20 - 90472.80 Pass STSO-3155 5/11/2006 Co-60 7950.80 +/- 67.29 7750.00 6975.00 - 8525.00 Pass STSO-3155 5/1/2006 Cs-134 12.49 +/- 0.13 11.59 1.59 -21.59 Pass STSO-3155 5/1/2006 Cs-137 14.10 +/- 0.12 11.63 1.63 -21.63 Pass SPAP-2873 5/2/2006 Gr. Beta 1724.80 +/- 4.51 1744.00 1395.20 - 2441.60 Pass SPF-3183 5/10/2006 Cs-137 2.47 +/- 0.03 2.38 1.43 -3.33 Pass SPF-3183 5/10/2006 Cs-134 0.73 +/- 0.01 0.74 0.44 - 1.04 Pass SPW-3460 5/26/2006 C-14 4009.60 +/- 14.43 4741.00 2844.60 - 6637.40 Pass W-60606 6/6/2006 Gr. Alpha 21.94 +/- 0.46 20.08 10.04 - 30.12 Pass W-60606 6/6/2006 Gr. Beta 58.17 +/- 0.49 65.73 55.73 - 75.73 Pass SPW-3988 6/16/2006 Cs-134 35.56 +/- 1.40 36.00 26.00 - 46.00 Pass SPW-3988 6/16/2006 Cs-137 60.23 +/- 2.72 59.27 49.27 - 69.27 Pass SPW-3988 6116/2006 1-131(G) 94.01 +/- 4.38 99.30 89.30 - 109.30 Pass SPW-3988 6/16/2006 Sr-89 52.40 +/- 4.23 58.16 46.53 - 69.79 Pass SPW-3988 6/16/2006 Sr-90 45.35 +/- 1.95 41.21 32.97 - 49.45 Pass SPMI-3990 6/16/2006 Cs-134 35.52 +/- 5.05 36.00 26.00 - 46.00 Pass SPMI-3990 6/16/2006 Cs-137 56.78 +/- 3.86 59.27 49.27 - 69.27 Pass SPMI-3990 6/16/2006 1-131(G) 95.04 +/- 5.05 99.30 89.30 - 109.30 Pass SPMI-3991 6/16/2006 1-131 96.55 +/- 0.87 99.30 79.44 - 119.16 Pass SPW-4356 7/5/2006 1-131 80.88 +/- 1.09 77.23 61.78 - 92.68 Pass W-90506 9/512006 Gr. Alpha 23.11 +/- 0.45 20.08 10.04 - 30.12 FOass W-90506 9/5/2006 Gr. Beta 65.01 +/- 0.51 65.73 55.73 - 75.73 Pass SPAP-6950 9/30/2006 Cs-134 28.93 +/- 1.56 32.65 22.65 - 42.65 Pass SPAP-6950 9/30/2006 Cs-137 116.62 +/- 2.97 117.75 105.98 - 129.53 Pass SPAP-6952 9/30/2006 Gr. Beta 52.96 +/- 0.14 53.50 42.80 - 74.90 Pass A3-1

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

Lab Code Date Analysis Laboratory results Known Control 2s, n=lb Activity Limitsc Acceptance SPW-6954 9/30/2006 Cs-134 63.29 +/- 8.24 65.30 55.30 - 75.30 Pass SPW-6954 9/30/2006 Cs-1 37 60.41 +/- 7.53 58.87 48.87 - 68.87 Pass SPMI-6956 9/30/2006 Cs-1 34 69.26 +/- 4.85 65.31 55.81 - 75.31 Pass SPMI-6956 9/30/2006 Cs-1 37 61.35 +/- 7.62 58.87 48'.87 - 68.87 Pass W-120106 12/1/2006 Gr. Alpha 22.40 +/- 1.03 20.08 10.04 - 30.12 Pass W-120106 12/1/2006 Gr. Beta. 63.70 +/- 1.14- 65.73 55.73 - 75.73 Pass SPAP-9476 12/2912006 Gr. Beta 57.51 +/- 0.14 53.16 42*5ý - 74.42 Pass SPAP-9478 12/29/2006 Cs-134 26.84 +/- 1.23 30.06 20.06 - 40.06 Pass SPAP-9478 12/29/2006 Cs-137 110.54 +/- 3.12 117.10 105.39 - 128.81 Pass SPW-9480 12/29/2006 H-3

• 68972.20 +/- 748.00 72051.60 57641.28 - 86461.92 Pass SPW-9483 12/29/2006 Tc-99 29.43 +/- 0.84 32.98 20.98 - 44.98 Pass SPW-9488 12/29/2006 Cs-134 61.35 +/- 1.65 60.10 50.10 - 70.10 Pass SPW-9488 12/29/2006 Cs-137 60.30 +/- 2.76 56.80 46.80 - 66.80 Pass SPMI-9490

• 12/29/2006 Cs-134 58.99 +/- 5.43 60.10 50.10 - 70.10 Pass SPMI-9490 *12/29/2006 Cs-137 54.16 +/- 7.85 56.80 46.80 - 66.80 Pass SPF-9492 12/29/2006 Cs-134 0.64 +/- 0.01 0.60 0.36 - 0.84 Pass SPF-9492 12/29/2006 'Cs-137 2.61 +/- 0.03 2.34 1.40 - 3.28 Pass Liquid sample results are reported In pCI/Lter, air filters( pCi/filter), charcoal (pCi/m 3), and solid samples (pCl/g).

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

CH (charcoal canister), F (fish).

=Results are based on single determinations.

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

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

A3-2

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

Lab Code Sample Date Analysisb Laboratory results (4.66a) Acceptance Type LLD Activity' Criteria (4.66 a)

SPW-302 water 1/20/2006 Fe-55 21.21 -1.82 +/- 12.75 1000 SPAP-1225 Air Filter 3/7/2006 Gr. Beta 1.16 -0.512 +/- 51.20 3.2 SPW-1231 water 3/7/2006 Cs-1 34 2.71 *10 SPW-1231 water 3/7/2006 Cs-I 37 2.05 10 W-30906 water 3/9/2006 Gr. Alpha 0.037 0.005 +/- 0.026 1 W-30906 water 3/9/2006 Gr. Beta 0.076 -0.016 +/- 0.052 3.2 SPW-2751 water 4/27/2006 NI-63 1.48 0.37 +/- 0.91 20 SPW-2868 water 5/1/2006 Fe-55 18.07 4.33 +/- 11.27 1000 SPW-2874 water 5/1/2006 H-3 166.00 -8.3 +/- 86.9 200 SPAP-2872 Air Filter 5/2/2006 Gr. Beta 1.18 -3.65 +/- 0.64 3.2 SPF-3154 Fish 5/10/2006 Cs-1 34 16.4 100 SPF-3154 Fish 5110/2006 Cs-137 13.7 100 SPW-3461 water 5/26/2006 C-14 10.20 -7.9 + 5.20 200 W-60606 water 6/6/2006 Gr. Alpha 0.05 0.013 +/- 0.037 1 W-60606 water 6/6/2006 Gr. Beta 0.16 -0.044 +/- 0.11 3.2 SPW-3989 water 6/16/2006 Cs-1 34 3.00 10 SPW-3989 water 6/16/2006 Cs-137 3.65 10 SPW-3989 water 6/16/2006 1-131 0.21 0.045 + 0.14 0.5 SPW-3989 water 6/16/2006 1-131(G) 8.34 20 SPW-3989 water 6/16/2006 Sr-89 0.54 0.005 + 0.45 5 SPW-3989 water 6/16/2006 Sr-90 0.58 -0.079 + 0.26 1 SPMI-3991 Milk 6/16/2006 Cs-134 4.42 10 SPMI-3991 Milk 6/16/2006 Cs-137 3.88 10 SPMI-3991 Milk 6116/2006 1-131 0.28 -0.22 + 0.19 0.5 SPMI-3991 Milk 6/16/2006 1-131 (G) 3.76 20 SPMI-3991 Milk 6/16/2006 Sr-89 0.61 -0.25 + 0.76 5 SPMI-3991 d Milk 6/16/2006 Sr-90 0.52 0.88 +/-0.34 1 W-90506 water 9/5/2006 Gr. Alpha 0.06 0.00

• 0.04 1 W-90506 water 9/5/2006. Gr. Beta 0.16 0.05 +/- 0.11 32 SPMI-6383 Milk 9/14/2006 Sr-89 0.97 -0.18 +/- 0.92 5 SPMI-6383 Milk 9/14/2006 Sr-90 0.57 0.65 +/- 0.33 1 SPAP-6949 Air Filter 9/30/2006 Cs-1 34 0.89 100 SPAP-6949 Air Filter 9/30/2006 Cs-1 37 0.91 100 SPAP-6951 Air Filter 9/30/2006 Gr. Beta 1.12 -0.54 +/- 0.64 3.2 SPW-6953 water 9/30/2006 Cs-134 3.91 10 SPW-6953 water 9/30/2006 Cs-137 5.61 10 SPW-6953 water 9/30/2006 Sr-89 0.79 -0.14 +/- 0.64 5 SPW-6953 water 9/30/2006 Sr-90 0.60 0.11 +/- 0.29 1 A4-1

TABLE A-4. In-House "Blank" Samples Concentration (pCIIL)8 Lab Code Sample Date Analysisb Laboratory results (4.66cr) Acceptance Type LLD Activityc Criteria (4.66 a)

SPMI-6955 Milk 9130/2006 Cs-134 2.86 10 SPMI-6955 Milk 9/30/2006 Cs-1 37 2.39 10 SPMI-6955 Milk 9/30/2006 16131(G) 9.98 0.5 W-120106 water 12/1/2006 Gr. Alpha 0.11 0.066

• 0.072 1 W-120106 water 12/1/2006 Gr. Beta 0.30 0.093

• 0.16 3.2 SPAP-9477 Air Filter 12/29/2006 Gr. Beta 1.13 -0.37

• 0.66 3.2 SPAP-9479 Air Filter 12/29/2006 Cs-137 0.87 100 SPW-9481 water 12/29/2006 H 146.2 63.2 +/- 80.1 200 SPW-9483 water 12/29/2006 Tc-99 0.95 -1.20 +/- 0.56 10 SPW-9489 water 12/29/2006 Cs-134 2.30 10 SPMI-9491 Milk 12/29/2006 -Cs-134 3.10 10 SPMI-9491 Milk 12/29/2006 Cs-137 2.90 10 SPMI-9491 Milk 12/29/2006 1-131(G) 8.00 20 SPF-9493 Fish 12/29/2006 Cs-134 7.6 100 SPF-9493 Fish 12/29/2006 Cs-137 7.9 100 LUquld-sample results are reported In pCi/Llter, air filters( pCI/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

b 1-131(G); iodine-1 31 as analyzed by gamma spectroscopy.

c Activity reported Is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported d Low levels of Sr-90 are still detected In the environment. A concentration of (1-5 pCI/L) 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 AP-7466, 7467 1/3/2006 Be-7 0.053 + 0.015 0.057 +/- 0.011 0.055 +/- 0.009 Pass AP-7513, 7514 1/3/2006 Be-7 0.033 +0.008 0.036 +/- 0.008 0.035 +/- 0.006 Pass AP-7555, 7556 1/3/2006 Be-7 0.053 + 0.007 0.054 +/- 0.008 0.053 +/- 0.005 Pass MI-154, 155 1/10/2006 K-40 1254.20 + 87.75 1369.60 +/- 102.80 1311.90 +/- 67.58 Pass MI-217, 218 1/11/2006 K-40 1258.00 +/- 118.00 1313.00 +/- 98.00 1285.50 +/- 76.69 Pass MI-217, 218 111112006 Sr-90 1.27 +/- 0.37 0.92 +/- 0.33 1.10 +/- 0.25 Pass MI-287, 288 1/17/2006 K-40 . 1383.10 +/- 110.90 1457.80 +/- 119.10 1420.45 +/- 81.37 Pass MI-287, 288 1/17/2006 Sr-90 0.74 +/-0.38 0.94 +/- 0.37 0.84 +/- 0.27 Pass WW-314, 315 1/19/2006. Gr. Beta. 9.21 + 1.72 11.52 +/- 1.93 10.37 +/- 1.29 Pass WW-314, 315 1/19/2006 H-3 168.64 +/-94.94 210.12 +/- 96.51 189.38 +/- 67.69 Pass SWT-577, 578 1/31/2006 Gr. Beta 3.06 +/- 0.66 3.68 +/- 0.64 3.37 +/- 0.46 Pass SWU-598, 599 1/31/2006 Gr. Beta 2.03 + 0.39 1.97 +/- 0.40 2.00 +/-f0.28 Pass SWU-598, 599 1/3112006 H-3 260.10 + 98.20. 134.10 +/- 93.50 197.10 +/- 67.80 Pass F-3311, 3 3 12 b 2/9/2006 Gr. Beta 4.12 +/-0.14 3.82 +/- 0.13 3.97 +/- 0.10 Fail F-3311, 3312 2/9/2006 K-40 2.68 +/- 0.37 2.76 +/- 0.39 2.72 +/- 0.27 Pass SW-780, 781 2/14/2006 Gr. Alpha 4.09 + 1.52 3.22 +/- 1.37 3.66 +/- 1.03 Pass SW-780, 781 2/14/2006 Gr. Beta 5.91 +/- 0.90 5.89 +/- 0.92 5.90 +/- 0.64 Pass DW-934, 935 2/17/2006 1-131 0.35 + 0.22 0.31 +/- 0.25 0.33 +/- 0.16 Pass DW-1024, 1025 2/24/2006 1-131 0.24 +/- 0.26 0.53 +/- 0.24 0.39 +/- 0.18 Pass MI-1078, 1079 3/1/2006 Sr-90 1.42 +/- 0.39 1.30 +/- 0.62 1.36 +/- 0.37 Pass F-1357, 1358 3/10/2006 Gr. Beta 3.77 +/- 0.07 3.71 +/- 0.07 3.74 +/- 0.05 Pass F-1357, 1358 3/10/2006 K-40 2.46 +/- 0.32 2.32 +/- 0.44 2.39 +/- 0.27 Pass MI-1469, 1470 3/14/2006 K-40 1396.30 + 120.80 1335.60 +/- 113.80 1365.95 +/- 82.98 Pass CF-1538, 1539 3/21/2006 K-40 13.66 +0.81 - 13.97 +/- 0.68 - 13.81 +/- 0.53 Pass WW-1583, 1584 3/22/2006 Gr. Beta 7.66 + 0.73 8.87 +/- 0.75 8.26 +/- 0.52 Pass DW-1955, 1956 3/27/2006 Gr. Beta 2.25 +/- 0.60 3.15 +/- 0.59. 2.70 +/- 0.42 Pass MI-1760, 1761 3/29/2006 K-40 1271.00 +/- 89.00 1378.00 +/- 113.00 1324.50+/-71.92 Pass AP-2603, 2604 3/29/2006 Be-7 0.067 +/- 0.015 0.056 +/- 0.010 0.062 +/- 0.009 Pass E-1997, 1998 4/3/2006 Gr. Beta 1.82 +/- 0.07 1.87 +/- 0.07 1.85 +/- 0.05 Pass E-1997, 1998 4/3/2006 K-40 1.28 +/-0.15 1.24 +/- 0.21 1.26 +/- 0.13 Pass AP-2818, 2819 4/3/2006 Be-7 0.06 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 Pass SWU-2863, 2864" 4/3/2006 Gr. Beta 3.20 +/- 1.26 4.77 +/- 1.30 3.99 +/- 0.91 Pass SS-2389, 2390 4/11/2006 Gr. Beta 10.53 +/- 0.96 9.38 +/- 0.84 9.96 t 0.64 Pass SS-2389, 2390 4/11/2006 K-40 5.51 +/- 0.42 5.79 +/- 0.40 5.65 +/- 0.29 Pass DW-2773, 2774 4/21/2006 1-131 0.74 +/- 0.23 0.53 +/- 0.40 0.63 +/- 0.23 Pass SL-2932, 2933 511/2006 Be-7 1.28 +/- 0.19 1.27 +/- 0.17 1.28 +/- 0.13 Pass SL-2932, 2933 5/1/2006 Gr. Beta 6.09 +/- 0.33 5.65 +/- 0.31 5.87 +/- 0.23 Pass SL-2932, 2933 5/1/2006 K-40 3.13 +/- 0.41 3.09 +/- 0.36 3.11 +/- 0.27 Pass BS-3103, 3104 5/1/2006 Gr. Beta 8.27 +/- 1.46 9.03 +/- 1.59 8.65 +/- 1.08 Pass BS-3103, 3104 5/1/2006 K-40 6288.20 +/- 585.20 5643.70 +/- 599.80 5965.95 +/- 418.99 Pass MI-3037, 3038 5/2/2006 K-40 1238.90 +/- 98.59 1301.00 +/- 103.90 1269.95 +/- 71.62 Pass MI-3037, 3038 5/2/2006 Sr-90 1.76 +/- 0.42 1.48 +/- 0.42 1.62 +/- 0.29 Pass A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)r Averaged Lab Code Date Analysis First Result Second Result - Result Acceptance MI-3124, 3125 5/9/2006 K-40 1032.30 +/- 91.12 1103.60 +/- 120.50 1067.95 +/- 75.54 Pass SW-3145, 3146 5/9/2006 Gr. Alpha 4.85 +/- 1.68 4.12 +/- 1.62 4.48 +/-1.17 Pass SW-3145, 3146 5/9/2006 Gr. Beta 8.94 +/- 1.46 9.14 +/-1.36 9.04 .+/- 1.00 Pass MI-3236, 3237 5/10/2006 K-40 .1412.40 +/- 119.10 1427.90 +/- 127.70 1420,15 +/- 87.31 Pass F-3422, 3423 5119/2006 H-3 8175.00 +/- 252.00 8268.00 +/- 253.00 8221.50 +/- 178.54 Pass G-3491, 3492 5/24/2006 Gr. Beta 8.89 +/- 0.18 9.03 +/- 0.19 8.96 +/- 0.13 Pass G-3491. 3492 5/24/2006 K-40 5.60 +/- 0.71 6.30 +/- 0.78 5.95 +/- 0.53 Pass SO-3539, 3540 5/2412006 Gr. Beta 19.57 +/- 1.99 18.98 +/- 1M91 19.27 +/- 1.38 Pass SO-3539, 3540 5/24/2006 K-40 12.55 +/- 0.89 11.49 +/- 0.59 12.02 +/- 0.53 Pass WW-3751, 3752 5/25/2006 Gr. Beta 9.85 +/-.0.79 8.96 +/- 0.74 9.41 +/- 0.54 Pass F-3617, 3618 5/30/2006 K-40 2.42 +/- 0.38 2.53 +/- 0.37 2.47 +/- 0.27 Pass SL-3641, 3642 6/1/2006 Be-7 1.41 +/-0.19 1.31 +/- 0.27 1.36 +/- 0.17 Pass SL-3641, 3642 6/1/2006 Gr. Beta 5.03 +/- 0.18 5.30 +/-0.19 5.17 +/- 0.13 Pass SL-3641, 3642 6/1/2006 K-40 2.21 +/- 0.26 2.14 +/- 0.37 2.18 +/- 0.23 Pass MI-3886, 3887 6/12/2006 K-40 1424.20 +/- 118.20 1318.80 +/- 110.50 1371.50 +/- 80.90 Pass VE-3949, 3950 6/13/2006 Gr. Alpha 0.13 +/- 0.06 0.16 +/- 0.07 0.15 + 0.05 Pass VE-3949, 3950 6/13/2006 Gr. Beta. 4.53 +/- 0.19 4.47 +/- 0.18 4.50 +/- 0.13 Pass VE-3949, 3950 6/13/2006 K-40 6.02 +/- 0.66 5.33 +/- 0.66 5.67 +/- 0.47 Pass BS-4016, 4017 6/13/2006 Co-60 0.18 +/- 0.03 0.15 +/- 0.03. 0.16 +/-0.02 Pass BS-4016, 4017 6/13/2006 Cs-137 1.97 +/- 0.09 2.01 +/- 0.09 1.99 +/- 0.06 Pass BS-4016, 4017 6/13/2006 K-40 11.03 +/- 0.76 10.45 +/- 0.78 10.74 +/- 0.54 Pass MI-3992, 3993 6/14/2006 K-40 1358.50 +/- 166.40 1395.80 +/- 122.70 1377.15 +/- 103.37 Pass LW-4175, 4176 6/16/2006 H-3 482.11 +/- 90.25 397.50 +/- 86.88 439.81 +/- 62.63 Pass W-4130, 4131 6/21/2006 H-3 ,401.50 +/- 87.85 236.28 +/- 80.89 318.89+/-59.71 Pass AV-4330, 4331 6/26/2006 K-40. - 1717.10 +/- 244.30 1893.10 +/- 223.30 1805.10 +/- 165.49 Pass SWU-4489, 4490 6/27/2006 Gr. Beta 1.70 +/- 0.38 .1.93 +/- 0.38 1.82 +/- 0.27 Pass AP-4909, 4910 6/29/2006 Be-7, 0.11 +/- 0.01 0.11 +/- 0.02 0.11 +/-0.01 Pass AP-4952, 4953 6/29/2006 Be-7 0.08 +/- 0.02 0.10 +/- 0.02 0.09 +/- 0.01 Pass AP-4930, 4931 7/3/2006 Be-7 0.08 +/- 0.02 0.07 +/- 0.01 0.08 +/- 0.01 Pass 7/5/2006 Gr. Beta 1.85 +/- 0.05 1.85 +/- 0.05 1.85 +/- 0.04 Pass E-4399, 4400 7/5/2006 K-40 1.25 +/- 0.19 1.24

• 0.18 1.25 +/- 0.13. Pass E-4399, 4400 7/5/2006 Be-7 0.82 +/- 0.20 0.61 +/- 0.14 0.72 +/- 0.12 Pass G-4420, 4421 G-4420, 4421 7/5/2006 Gr. Beta 13.20 +/- 0.40 14.00 +/- 0.40 13.60 +/- 0.28 Pass G-4420, 4421 7/5/2006 K-40 9.96 +/- 0.44 10.06 +/- 0.82 10.01 +/- 0.47 Pass DW-60432, 60433 7/6/2006 Gr. Alpha 3.24 +/- 1.35 2.49 +/- 1.33 2.87 +/-0.95 Pass Gr. Alpha 3.70 +/- 1.12 3.09 +/- 1.16 3.40 +/- 0.81 Pass DW-60514, 60515 7/10/2006 7/11/2006 Gr. Alpha 6.87 +/- 1.26 4.77 +/- 1.09 5.82 +/- 0.83 Pass DW-60449, 60450 K-40 1403.50 +/- 118.80 1330.40 +/- 116.50 1366.95 +/- 83.20 Pass MI-4599, 4600 . 7/12/2006 Sr-90 0.59 +/- 0.34 0.70 +/- 0.35 0.65 +/- 0.24 Pass MI-4599, 4600 i 7/1212006 K-40 1286.60 +/- 92.62 1358.60 +/- 158.40 1322.60 +/- 91.75 Pass MI-4667, 4668 7/12/2006 Gr. Beta 1.75 +/- 0.60 2.51 +/- 0.59 2.13 +/- 0.42 Pass LW-4823, 4824 7/14/2006 A5-2

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

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance DW-60502, 60503 7/19/2006 Gr. Alpha 16.27 t 2.49 21.41 +/- 3.21 18.84 t 2.03 Pass DW-60526, 60527 7/21/2006 Gr. Alpha 14.06 t 1.82 15.57 +/- 1.77 14.82 +/- 1.27 Pass DW-60539, 60540 7/21/2006 Gr. Alpha 5.09 +/- 0.95 6.23 +/- 1.05 5.66 +/- 0.71 Pass MI-5125, 5126 7/25/2006 K-40 1480.60 +/- 118.30 1402.60 +/- 120.80, 1441.60 +/- 84.54 Pass DW-60609, 60610 7/26/2006 Gr. Alpha 1.00 +/- 1.10 2.70 +/- 1.30 1.85 +/- 0.85 Pass DW-60621, 60622 7131/2006 Gr. Alpha 3.70 +/- 1.00 1.90 +/- 0.80 2.80 +/- 0.64 Pass SL-5265, 5266 8/11/2006 Be-7 1.10 +/- 0.46 1.38 +/- 0.52 1.24 +/- 0.35 Pass SL-5265, 5266 8/1/2006 Sr-90 0.10 +/- 0.03 0.16 +/- 0.03 0.13 +/- 0.02 Pass SL-5265, 5266 8/1/2006 Gr. Beta 4.41 +/- 0.41 3.46 +/- 0.57 3.94 +/- 0.35 Pahs SL-5265, 5266 8/112006 K-40 1.19 +/- 0.52 0.87 +/- 0.52 1.03 +/- 0.37 Pass VE-5286, 5287 8/1/2006 Be-7 1.21 +/- 0.30 1.32 +/- 0.20 1.27 +/- 0.18 Pass VE-5286. 5287 8/1/2006 Gr. Beta 9.67 +/- 0.35 9.37 +/- 0.35 9.52 +/- 0.25 Pass VE-5286, 5287 811/2006 K-40 6.25 +/- 0.81 6.50 +/- 0.48 6.38 +/- 0.47 Pass SW-5383, 5384 8/8/2006 Gr. Alpha 3.24 +/- 1.35 2.94 +/- 1.35 3.09 " 0.96 Pass SW-5383, 5384 8/8/2006 Gr. Beta 4.86 + 0.86 5.46 +/- 0.87 5.16 +/- 0.61 Pass SW-5971, 5972 8/8/2006 H 119.90 +/- 78.14 144.41 +/- 79.23 132.15 +/- 55.64 Pass VE-5404, 5405 8/10/2006 Be-7 0.77 +/- 0.24 1.01 +/- 0.26 0.89 +/- 0.18 Pass VE-5404, 5405 8/10/2006 K-40 4.71 + 0.63 4.01 +/- 0.58 4.36 +/- 0.43 Pass DW-5480, 5481 8/11/2006 H-3 169.08 + 85.52 133.65 +/- 83.96 151.36 +/- 59.92 Pads DW-60645, 60646 8/15/2006 Gr..Alpha 10.41 + 1.78 10.97 +/- 1.85 10.69 + 1.28 Pass W-5602, 5603 8/16/2006 H-3 2118.79 + 151.55 2181.82 +/- 153.09 2150.30 " 107.71 Pass DW-60634, 60635 8/18/2006 Gr. Alpha 12.99 + 1.84 9.67 +/- 1.61 11.33 + 1.22 Pd~s DW-60634, 60635 8/18/2006 Gr. Beta 10.51 +/- 1.33 8.61 +/- 1.18 9.56 +/- 0.89 Pass MI-5793, 5794 8/22/2006 K-40 1264.00 + 115.00 1377.00 +/- 121.00, 1320.50 +/-83.47 Pass SWU-6150, 6151 8/29/2006 Gr. Beta 1.84 +/- 0.28 1.81 +/- 0.28. 1.82 +/- 0.20 Pass DW-60657, 60658 8/29/2006 Gr. Alpha 2.33 +/- 0.80 - 2.90 +/- 0.78 2.62 +/- 0.56 Pass CF-7450, 7451 9/5/2006 Be-7; 0.78 +/- 0.45 0.78 +/- 0.27 0.78 1 0.26 Pass SL-6085, 6086 9/5/2006" Co-60 0.22 +/- 0.03 0.21 +/-0.02- 0.22 +/- 0.02 Pass SL-6085, 6086 9/5/2006 Gr. Beta 5.47 +/- 0.69 4.63 +/- 0.58, 5.05 +/- 0.45 Pass SL-6085, 6086 9/5/2006 K-40 1.91 +/- 0.28 2.06 +/- 0.41 1.99 +/- 0.25 Pass DW-60695, 60696 9/11/2006 Gr. Alpha 3.93 +/- 1.17 4.62 +/- 1.12 4.28 +/- 0.81 Pass LW-6266, 6267 9/13/2006 Gr. Beta 3.09 +/- 0.48 2.98 +/- 0.48 3.03 +/- 0.34 Pass MI-6424, 6425 9/19/2006 Sr-90 0.78 +/- 0.38 1.11 +/- 0.37 0.95 +/- 0.27 Pass DW-60715, 60716 9/19/2006 Gr. Alpha 1.30 +/- 1.00 2.23 +/- 1.01 1.77 +/- 0.71 Pass SO-6597, 6598 9/22/2006 Cs-1 37 0.18 +/- 0.04 0.18 +/- 0.04 0.18 +/-0.03 Pass SO-6597, 6598 9/22/2006 K-40 10.25 +/- 0.66 10.11 +/-0.64 10.18 +/- 0.46 Pass SWU-6718, 6719 9/26/2006 Gr. Beta 3.45 +/- 1.21 2.78 +/- 1.19 *3.12 +/- 0.85 Pass SO-6668, 6669 9/27/2006 Cs-1 37 0.13 +/- 0.04 0.13 +/- 0.02 0.13 +/- 0.02 Pass SO-6668, 6669 9/27/2006 K-40 13.04 +/- 0.90 12.41 +/- 0.54 12.72 +/- 0.53 Pass A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCiVL)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance MI-6760, 6761 10/2/2006 K-40 1413.10 +/- 113.20 1187.30 +/-155.20 1300.20 +/- 96.05 Pass G-6797, 6798 10/212006 Be-7 4.70 +/- 0.31 4.56 +/- 0.41 4.63 +/- 0.26 Pass G-6797, 6798 10/2/2006 Gr, Beta 6.89 +/- 0.26 7.04 +/- 0.24 6.97 +/- 0.18 Pass G-6797, 6798 b 10/2/2006 K-40 5.39 +/- 0.35 4.36 +/- 0.47 4.88 +/- 0.29 Fail AP-7531, 7532 1013/2006 Be-7 0.07 +/- 0.01 0.08 +/- 0.01 0.08 +/- 0.01 Pass AP-7552, 7553 10/3/2006 Be-7 0.08 +/- 0.02 0.08 +/- 0.01 0.08 +/- 0.01 Pass AP-7573, 7574 10/3/2006 Be-7 0.08 +/- 0.02 0.08 +/- 0.01 0.08 +/- 0.01 Pass SO-7103, 7104 10/4/2006 Cs-137 0.25 +/- 0.05 - 0.27 +/- 0.06 0.26 +/- 0.04 Pass SO-7103. 7104 10/4/2006 K-40 12.95 +/- 1.12 12.22 +/- 1.07 12.58 +/- 0.77 Pass DW-60759, 60760 10/5/2006 Gr. Alpha 4.93 +/- 0.97 5.04 +/- 1.03 4.99 +/- 0.71 Pass MI-7037, 7038 10/10/2006 K-40 1326.10 +/- 115.20 1251.40 +/- 115.70 1288.75 +/- 81.64 Pass VE-7058, 7059 10(10/2006 Gr. Alpha 0.18 +/- 0.11 0.32 +/- 0.14 0.25 +/- 0.09 Pass VE-7058, 7059 10/1012006 Gr. Beta

• 9.21 +/- 0.34 8.83 +/- 0.36 9.02 +/- 0.25 Pass VE-7058. 7059 10/10/2006 K-40 10.90 +/- 0.65 10.42 +/- 0.80 10.66 +/- 0.52 Pass SS-7079, 7080 10/10/2006 Cs-137 0.04 +/- 0.01 0.04 +/- 0.02 0.04 +/- 0.01 Pass SS-7079, 7080 10(10/2006 Gr. Beta 12.23 +/- 2.46 11.76 +/- 2.23 11.99 +/- 1.66 Pass SS-7079, 7080 10/10/2006 K-40 7.23 +/- 0.36 7.37 +/- 0.40 7.30 +/- 0.27 Pass MI-7208, 7209 10/11/2006 K-40 1295.20 +/- 116.90' 1386.90 +/- 119.10 1341.05 +/- 83.44 Pass CF-7450, 7451 10/18/2006 K-40 20.40 +/- 0.84 19.54 +/- 0.99 19.97 +/- 0.65 Pass LW-7945, 7946 10/26/2006 Gr. Beta 1.30 +/- 0.37 1.44 +/- 0.36 1.37 +/- 0.26 Pass F-7971, 7972 10/29/2006 K-40 3.63 +/- 0.54 3.33 +/- 0.43. .3.48 +/- 0.34 Pass SWU-8194, 8195 10/3112006 Gr. Beta 1.84 +/- 0.28 1.43 +/- 0.28 .1.64 +/- 0.20 Pass BS-8017, 8018 11/1/2006. Gr. Beta, 10.54 +/- 1.72 10.17 +/- 1.73 10.36 +/- 1.22 Pass

-- BS-8017, 8018 11/1/2006 K'40 10.00 +/- 0.53 9.60 +/- 0.69 9.80 +/- 0.44 Pass LW-8215, 8216 11/1/2006 Gr. Beta 2.23 +/- 0.61 1.64 +/- 0.37 1.93 +/- 0.35 Pass F-8345, 8346 11/2/2006 K-40 2.84 +/- 0.42 2.89 +/- 0.40 2.86 +/- 0.29 Pass BS-8366, 8367 11/2/2006 K40- 13.69 +/- 0.66 13.61 +/- 0.78 13.65 +/- 0.51 Pass MI-8083, 8084 11/6/2006 K-40 1295.00 +/-121.20 1374.80 +/- 162.80 1334.90 +/- 101.48 Pass WW-8259, 8260 1117/2006 H-3

• 337.00 +/- 95.00 295.00 +/- 93.00 316.00 +/- 66.47 Pass MI-8484, 8485 1.1/2212006 K-40 1405.80 +/- 87.06 1390.70 +/- 103.60 1398.25 +/- 67.66 Pass SO-8619, 8620 11/27/2006 Cs-137 0.74 +/- 0.08 0.69 +/- 0.06 0.71 +/- 0.05 Pass 11/27/2006 Gr. Alpha 16.54 +/- 5.65 12.24 +/- 4.90 14.39 +/- 3.74 Pass SO-8619, 8620 11/27/2006 Gr. Beta 24.99 +/- 3.88

• 28.66 +/- 3.95 26.82 +/- 2.77 Pass SO-8619, 8620 SO-8619, 8620 11/27/2006 K-40 12.21 +/- 1.11 12.92 +/- 0.83 12.57 +/- 0.69 Pass 11/2912006 Gr. Beta 2.83 +/- 0.47 2.89 +/- 0.45 2.86 +/- 0.33 Pass SWT-8641, 8642 12/26/2006 Gr. Beta 2.39 :k 0.64 2.25 +/- 0.60 2.32 +/- 0.44 Pass SWT-9436, 94371 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 inunits of pCl/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).

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

A5-4

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

Concentration b Known Control Lab Code' Date Analysis Laboratory result Activity Limits d Acceptance STVE-1082 01/01/06 Am-241 0.16

• 0.06 0.16 0.11 -0.20 Pass STVE-1 082 01/01/06 Co-57 10.40 +/- 0.20 8.58 6.00 -11.15 Pass STVE-1082 01/01/06 Co-60 5.00 +/- 0.20 4.52 3.16 -5.88 Pass STVE-1082 01/01/06 Cs-134 < 0.20 0.00 Pass STVE-1082 01/01/06 Cs-137 3.40 +/- 0.20 3.07 2.15 -4.00 Pass STVE-1082 01/01/06 Mn-54 6.90 +/- 0.20 6.25 4.37 -8.12 Pass STVE-1082 01/01/06 Pu-238 0.08 +/- 0.03 0.14 0.10 -0.18 Fail STVE-1082 01101/06 Pu-239/40 0.17 +/- 0.03 0.16 0.11 -0.21 Pass STVE-1082 01/01/06 Sr-90 1.40 +/- 0.20 1.56 1.09 - 2.03 Pass S1VE-1082 01/01/06 U-233/4 0.24 +/- 0.05 0.21 0.15 - 0.27 Pass' STVE-1082 01/01/06 U-238 0.19 +/- 0.04 0.22 0.15 -0.28 Pass STVE-1082 01/01/06 Zn-65 11.10 +/- 0.50 9.80 6.86 - 12.74 Pass.

STSO-1083 01/01/06 Am-241 54.60 +/- 5.50 57.08 39.96 - 74.20 Pass STSO-1083 01/01/06 Co-57 762.90 +/- 12.70 656.29 459.40 - 853.18 Pass STSO-1083 01/01/06 Co-60 504.90 +/- 3.10 447.10 312.97 - 581.23 Pass STSO-1 083w 01/01/06 Cs-I 34 < 1.70 0.00 Pass STSO-1083 01/01/06 Cs-137 406.50 +/- 3.70 339.69 237.78 - 441.60 Pass STSO-1083 01/01106 K-40 719.20 +/- 18.40 604.00 422.80 - 785.20 Pass STSO-1083 01/01/06 Mn-54 415.60 +/- 4.80 346.77 242.74 - 450.80 Pass STSO-1083 01/01/06 NI-63 261.40 1 14.70 323.51 226.46 - 420.56 Pass STSO-1083f 01/01/06 Pu-238 14.60 +/- 2.90 61.15 42.81-- 79.50 Fall STSO-1083 01/01/06 Pu-239/40 14.60 +/- 2.40 45.85 32.09 - 59.61 Fall STSO-1083 01/01/06 U-233/4 13.50 +/- 1.70 37.00 25.90 -48.10 Fail STSO-1083 01/01/06 U-238 15.40 +/- 1.80 38.85 27.20 - 50.50 Fail STSO-1083 01/01/06 Zn-65 783.40 +/- 7.00 657.36 460.15 - 854.57 Pass STAP-1084 01/01/06 Gr. Alpha .0.26 +/- 0.02 0.36 S0.00 - 0.72 Pass STAP-1084 01/01/06 Gr. Beta 0.51 +/- 0.03 0.48 0.24 - 0.72 Pass STAP-1085 01/01/06 Am-241 0.12 +/- 0.02 0.09 0.07 -0.12 Pass STAP-1085 01/01/06 Co-57 4.32 +/- 0.10 4.10 2.87 - 5.32 Pass STAP-1085 01/01/06 Co-60 2.24 +/- 0.16 2.19 1.53 -2.84 Pass STAP-1085 01/01/06 Cs-134 2.96 +/- 0.19 2.93 2.05 - 3.81 Pass STAP-1085 01/01/06 Cs-I 37 2.64 +/-0.20 2.53 1.77 - 3.29 Pass STAP-1085 01/01/06 Pu-238 0.03 + 0.01 0.07 0.05 - 0.09 Faill STAP-1 085 01/01/06 Pu-239/40 < 0.01 0.00 Pass STAP-1085 01/01/06 Sr-90 0.77 +/- 0.21 0.79 0.55-1.03 Pass STAP-1085 01/01/06 U-233/4 0.03 +/- 0.01 0.02 0.01 - 0.03 Pass STAP-1085 01/01/06 U-238 0.02 +/- 0.01 0.02 0.01 - 0.03 Pass STAP-1085 01/01/06 Zn-65 3.94 +/- 0.44 3.42 2.40 - 4.45 Pass A6-1

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

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STW-1086 01/01/06 Am-241 1.29 + 0.05 1.30 0.91 - 1.69 Pass STW-1086 61/01/06 Co-57 177.10

• 1.00 166.12 116.28 - 215.96 Pass STW-1086 01/01/06 Co-60 158.30 +/- 1.00 153.50 107.45 - 199.55 Pass STW-1086 01/01/06 Cs-1 34 96.40 +/- 1.50 95.10 66.57 - 123.63 Pass STW-1086 01/01/06 Cs-I 37 < 0.80 0.00 Pass STW-1086 01/01/06 Fe-55 102.50 +/- 18.10 129.60 90.72 - 168.48 Pass STW-1 086 01/01/06 H-3 956.60 +/- 16.50 952.01 666.41 - 1238.00 Pass STW-1086 01/01/06 Mn-54 335.30 +/- 2.20. 315.00 220.50 -409.50 Pass STW-1086 01/01/06 Ni-63 62.90 1 3.60 60.34 42.24 - 78.44 Pass STW-1086 01/01/06 Pu-238 0.96 +/- 0.07 0.91 0.70 - 1.30 Pass STW-1086 01/01/06 Pu-239/40 < 0.20 0.00 Pass STW-1086 01/01/06 Sr-90 12.80 +/- 1.60 13.16 9.21 - 17.11 Pass STW-1086 01/01/06 Tc-99 22.30 +/- 1.20 23.38 16.37 - 30.39 Pass STW-1086 01/01/06 U-233/4 2.02 +/- 0.12 2.09 1.46 -2.72 Pass STW-1086 01/01/06 U-238 2.03 +/- 0.12 2.17* 1.52.- 2.82 Pass STW-1086 01/01/06 Zn-65 249.50 +/- 3.40 228.16 159.71 - 296.61 Pass STW-1087 01/01/06 Gr. Alpha. 0.59 + 0.10 0.58 .0.00 -1.16 Pass STW-1087 01/01/06 Gr. Beta 1.69 +/- 0.07 1.13 0.56 - 1.70 Pass STVE-1098 07/01/06. Co-57 <0.14 0.00 Pass STVE-1098 o 07/01/06 Co-60 6.89 +/- 0.17 5.81 4.06 - 7.55 Pass 8TVE-1 098 07/01/06 Cs-134 8.46 +/- 0.16 7.49 5.24 - 9.73 Pass STVE-1 098 07/01/06 Cs-137 6.87 +/- 0.29 5.50 3.85 -7.14 Pass STVE-1 098 07/011/06 Mn-54 10.36 +/- 0.29 8.35 5.85 - 10.86 Pass STVE-1 098 .07/01/06 Zn-65 7.46 +/- 0.50 5.98 4.19 -7.78 Pass STSO-1099 07/01/06 Am-241 130.00 +/- 11.60 105.47 73.83 - 137.11 Pass STSO-1099 07/01/06 Co-57 784.90 +/- 3.80 676.33, 473.43 - 879.23 Pass STSO-1099 07/01/06 Co-60 2.10 +/- 0.90 1.98 0.00 - 5.00 Pass STSO-1099 07/01/06 Cs-134 500.70 +/- 7.40 452.13 316.49 - 587.77 Pass STSO-1099 07/01/06 Cs-137 624.20 +/- 4.90 525.73 368.01 - 683.45 Pass STSO-1 099 07/01/06 K-40 701.30 +/- 3.40 604.00 423.00 - 785.00 Pass STSO-1099 07101/06 Mn-54 699.20 +/- 5.20 594.25 415.98 - 772.52 Pass STSO-1099 07/01/06 NI-63. 614.40 +/- 17.10 672.30 470.60 - 874.00 Pass STSO-1099 07/01/06 Pu-238 79.90 +/- 5.80 82.00 57.00 - 107.00 Pass STSO-1099 07/01/06 Pu-239/40 < 0.70 0.00 Pass STSO-1 099 07/01/06 U-233/4 150.50 +/- 5.90 152.44 106.71 - 198.17 Pass STSO-1099 07/01/06 U-238 151.60 +/- 6.00 158.73 111.11 - 206.35 Pass STSO-1 099 07/01/06 Zn-65 1021.90 +/- 9.20 903.61 632.53 - 1175.00 Pass STAP-1 100 07/01 /06 Am-241 0.16 +/- 0.03 0.14 0.10 -0.19 Pass STAP-1 100 07/01/06 Co-57 2.17 1 0.06 2.58 1.81 -3.36 Pass STAP-1100 07/01/06 Co-60 1.38 +/- 0.07 1.58 1.10-2.05* Pass STAP-1100 07/01/06 Cs-1 34 2.52 +/- 0.13 3.15 2.20 - 4.09 Pass A6-2

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

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STAP-1100 07/01/06 Cs-137 1.64 +/- 0.08 1.81 1.26 -2.35 Pass STAP-1100 07/01/06 Mn-54 1.76 +/- 0.18 1.92 1.34 -.2.50 Pass STAP-1100 07/01/06 Pu-238 0.09 +/- 0.02 0.12 0.08 -0.15 Pass STAP-1100 07/01/06 Sr-90 0.66 +/- 0.21 0.62 0.43 -0.81 Pass STAP-1100 07/01/06 U-233/4 0.15 +/- 0.02 0.13 0.09 -0.17 Pass STAP-1100 07/01/06 U-238 0.13 +/- 0.02 0.14 0.10 -0.18 Pass STAP-1 100

• 07/01/06 Zn-65 < 0.07 0.00 Pass STAP-1 101 07/01/06 Gr. Alpha 0.08 +/- 0.03 0.29 0.00 - 0.58 Pass STAP-1101 07/01/06 Gr. Beta 0.41 +/- 0.05 0.36 0.18 - 0.54 Pass STW-1102 07/01/06 Gr. Alpha 0.76 +/- 0.07 1.03 0.00 -2.07 Pass -s STW-1102 07/01/06 Gr. Beta 1.23 +/- 0.06 1.03 0.52 - 1.54 Pass STW-1103 07/01/06 Am-241 1.86 +/- 0.09 2.31 1.62 -3.00 Pass STW-1103 07/01/06 Co-57 224.10 +/- 1.20 213.08 149.16 -277.00 Pass STW-1103 07/01/06 Co-60 49.40 +/- 0.50 47.50 33.20 - 61.80 Pass STW-1103 07/01/06 Cs-134 112.70 +/- 0.90 112.82 78.97 - 146.66 Pass STW-1103 07/01/06 Cs-137 206.60 +/- 1.40 196.14 137.30 -254.98 Pass STW-1103 07/01106 Fe-55 138.40 +/- 5.40 165.40 115.80 - 215.00 Pass STW-1 103 07/01/06 H-3 446.50 +/- 11.80 428.85 300.20 - 557.50 Pass STW-1103 07/01/06 Mn-54 < 0.30 0.00 Pass STW-1103 07/01/06 NI-63 116.70 +/- 3.60 118.62 83.03 - 154.21 Pass STW-1103 07/01/06 Pu-238 1.27 +/- 0.07 1.39 0.97 -1.81 Pass STW-1103 07/01/06 Pu-239/40 1.67 +/- 0.08 1.94 1.36 -2.52 Pass STW-1103 07/01/06 Sr-90 16.40 +/- 1.90 15.69 .10.98 -20.40 Pass STW-1103 07/01/06 Tc-99 29.40 +/- 1.10 27.15 19.00 -35.29 Pass STW-1103 07/01/06 U-233/4 1.97 +/- 0.08 2.15 1.50 -2.80 Pass STW-1103 07/01/06 U-238 1.97 +/- 0.08 2.22 1.55 -2.89 Pass STW-1 103 07/01/06 Zn-65 192.50 +/- 2.40 176.37 123.46 - 229.28 Pass Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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

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

• Included in the MAPEP as a false positive.

f Difficulties with the analyses for transuranics isotopes In solid samples (Filters, Soil and vegetation),

were attributed to incomplete dissolution of the samples. Soil samples were repeated, results of reanalyses:

Pu-238, 53.1 +/- 5.3 bqikg. Pu-2391240, 42.4 +/- 4.7 bq/kg. U-233/4, 33.3 +/- 3.5 bq/kg. U-238, 35.5 +/- 3.6 bq/kg.

9 The July vegetation sample was provided in two separate geometries, (100 ml. and 500 ml.). Results reported here used the 500 ml. standard size geometry. Results for the 100 ml. geometry showed approximately a 15% higher bias.

-4 A6-3

APPENDIX B DATA REPORTING. CONVENTIONS B-1

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

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

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

3.0. Duollcate analyses 3.1 Individual results: For two analysis results; xi +/- s, and x2 + s2 Reported result: x +/- s; where x = (1/2) (xI + x2) and s= (1/2) 1 +S2 3.2. Individual results: < Ll , < L2 Reported result < L, where L = lower of L1 and L2 3.3. Individual results: x +s, < L Reported 'result: x +/- s if x > L; <L otherwise.

4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x1, x2 . . . x are defined as follows:

7x Sx s- n-i 4.2 Values below the highest lower limit of detection are not included in the average.

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

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

4.5 In rounding off, the following rules are followed:

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

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

B-2

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

Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas.a Air (pCi/m 3) Water (pCi/L)

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

Iodine-1 31 2.8 x 10-1 Cesium-1 37 1,000 Barium-140 8,000 Iodine-1 31 1,000 C

Potassium-40 4,000 Gross alpha 2 Gross beta 10 Tritium l x10 1 a

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

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

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

C A natural radionuclide.

C-2

2006 Annual Environmental Monitoring Report Kewaunee Power Station PartII, Data Tabulations, Graphs and Analyses Dominion Energy Kewaunee, Inc.

- Environmental, Inc.

Midwest Laboratory 1 an Alegheny Technoogs 0o.

700 Landwehr Road

• Nothbrook IL60062-2310 ph. (847) 564-0700

• fax (847) 564-4517 REPORT TO DOMINION NUCLEAR RADIOLOGICAL MONITORING PROGRAM FOR THE KEWAUNEE POWER STATION KEWAUNEE, WISCONSIN ANNUAL REPORT - PART II DATA TABULATIONS AND ANALYSES January 1 to December 31, 2006 Prepared and submitted by ENVIRONMENTAL, Inc.

Midwest Laboratory Project No. 8002 Approved : a LLQQ l

Michael Hale Radiation Protection I Chemistry Mgr., KPS

PREFACE The staff members of Environmental, Inc., Midwest Laboratory were responsible for the acquisition of data presented in this report. Samples were collected by the personnel of Environmental, Inc., Midwest Laboratory and the Kewaunee Power Station.

ii

TABLE OF CONTENTS Section Paae Preface ......... .................... .................................................... ii List of Figures .............................................................................................................................. iv List of Tables ................. ....................................

v

1.0 INTRODUCTION

................................................... ......... ..................................................... I 2.0 GRAPHS OF DATA TRENDS ....................................................................................................... 7 3.0 DATA TABULATIONS ...................................................... .......................................................... 30 Appendices A Radiochemical Analytical Procedures ........................................................................................ A-1 iii

LIST OF FIGURES No. Caption Paae 1 Sampling locations, Kewaunee Power Station 3 2 Airborne particulates, weekly averages; gross beta, Location K-If ........... °.................. 8

.......................... ... 8 3 Location K-2

............................. 9 4 Location K-7

........................... .. 9 5 Location K-8

............................. 10 6 Location K-16

............................. 10 7 Location K-31

............................. 1 1 8 Airborne particulates, gross beta, monthly averages, Location K-If

............................. I I 9 Location K-2

............................. 12 10 Location K-7

............................. 12 11 Location K-8

............................. 13 12 Location K-16

............................. 13 13 Location K-31 14 Well water, gross alpha in total residue, Location k-lg ......... I...... .............. 14 15 Location K-lh ............................. 14

............................. 15 16 Well water, gross beta in total residue, Location K-Ig

......... I.................... 15 17 Location K-Ilh 18 Location K-10 ............................. 16 19 Location K-1 I ........ I.................... 16 20 Location K-25 ...... I...................... 17 21 Location K-13 ............................. 17 22 Milk, strontium-90 activity, Location K-3 ........... ................... 18

........... e ................. 18 23 Location K-5 24 Location K-25 ................... ........... 19 25 Location K-28 ............................. 19

............................. 20 26 Location K-34

............................. 20 27 Location K-38 28 Location K-39 ..... ;......... ............... 21 Surface water, gross beta In suspended and dissolved solids, Location K-I a ............................. 22 29 Location K-lb ............................. 23 31 Location K-ld ..................... .... .... 24 33 35 Location K-le ............................. 25 Location K-9 ............................. 26 37

.......... ................... 27 39 Location K-14a

......................... .... 28 41 Location K-Ik

.- a Location K-I a ..:.......................... 22 30 Surface water, gross beta in total residue, Location K-lb ............................. 23 32 Location K-ld ................ I............ 24 34

............................. 25 36 Location K-le Location K-9 ............................. 26 38

........ *...................... 27 40 Location K-14a

............................. 28 42 Location K-bk Location K-ld ............................. 29 43 Surface water, tritium activity, Location K-14a ............................. 29 44 Location K-9 ............................. 29 45 iv

LIST OF TABLES No. Title Page I Sampling locations, Kewaunee Power Station 4 2 Type and frequency of collection 5 3 Sample codes used in Table 2 5 Airborne particulates and Iodine, analysis for gross beta and iodine-131 4 Location K-If 31 5 Location K-2 32 6 Location K-7 33 7 Location K-8 34 8 Location K-16 35 9 Location K-31 36 10 Airborne particulates, gross beta, monthly averages, minima and maxima 37 11 Airborne particulates, quarterly composites of weekly samples, analysis for gamma- 39 emitting Isotopes 12 Ambient gamma radiation (TLD), quarterly exposure 42 13 Precipitation, collected 'at Location K-11, analysis for tritium 43 14 Milk, analysis for Iodine-131 and gamma emitting Isotopes 44 15 Milk, analysis for strontium-89, 'strontium-90, calcium and potassium-40 48 16 Well water, analysis for gross alpha, gross beta, tritium, strontiurn-89, strontium-90, potassium-40, 52 and gamma-emitting Isotopes.

17 Well water, analysis for gross beta, tritium, potassium-40 and gamma-emitting Isotopes 53 18 Domestic meat, analysis of flesh for gross alpha, gross beta, and gamma-emitting isotopes 56 19 Eggs, analysis for gross beta, strontium-89, strontium-90, and gamma-emitting Isotopes 57 20 Vegetables, analysis for gross beta, strontium-89, strontium-90, and gamma- 58 emitting Isotopes 21 Cattlefeed, analysis for grossbeta, strontium-89, strontium-90, and gamma-emitting isotopes 60 22 Grass, analysis for gross beta, strontium-89, strontium-90, and gamma-emitting isotopes 62 23 Soil, analysis for gross alpha, gross beta, strontium-89, strontium-90 and gamma- 65 emitting Isotopes

. 24 Surface water, analysis for gross beta, potassium-40, and gamma-emitting Isotopes 68 25 Surface water, analysis for tritium, strontium-89, and strontium-90 86

-26 Fish samples, analysis for gross beta, strontium-89, strontium-90, and gamma- 88 emitting Isotopes 27 Slime, analysis for gross beta, strontium-89, strontium-90 and gamma emitting isotopes 90 28 Bottom sediments, analysis for gross beta, strontium-89, strontium-90, and gamma- 92 emitting Isotopes v

1.0 INTRODUCTION

The following constitutes Part II of the final report for the 2006 Radiological Monitoring Program conducted at the Kewaunee Power Station (KPS), Kewaunee, Wisconsin.

Included are tabulations of data for all samples collected in 2006, graphs of data trends and descriptions of radiochemical procedures. A summary and interpretation of the data presented here are published in Part I of the 2006 Annual Report on the Radiological Monitoring Program for the Kewaunee Power Station.

NOTE: Page 2 is intentionally left out.

I

WDIBATI

-_ _ -F 1 K-2 K U U 4f -

E-KIZ m 1.23...

K-14 a If F u .lca Figure 1. Sampling locations, Kewaunee Power Station 3

KEWAUNEE Table 1. Sampling locations, Kewaunee Power Station.

Distance (miles)0 Code Type' and Sector Location K-1I Onsite K-Ta 0.62 N North Creek K-I b 0.12 N Middle Creek K-Ic 0.10 N 500' north of condenser discharge K-ld 0.10 E Condenser discharge K-I e 0.12 S South Creek K-If 0.12S Meteorological Tower K-Ig 0.06 W South Well K-I h 0.12 NW North Well K-lJ 0.10S 500' south of condenser discharge K-I k 0.60 SW Drainage Pond, south of plant K-2 C 9.5 NNE WPS Operations Building in Kewaunee K-3 C 6.0 N Lyle and John Siegmund.Farm, N2815 Hy 12, Kewaunee K-5 3.5 NNW Ed Paplham Farm, E4160 Old Settlers Rd, Kewaunee K-7 2.75 SSW Ron Zimmerman Farm, 17620 Nero Road, Two Rivers K-8 C 5.0 WSW Saint Isidore the Farmer Church, Tlsch Mills K-9 C 11.5 NNE Rostok Water Intake for Green Bay, Wisconsin, two miles north of Kewaunee K-10 1.5 NNE Turner Farm, Kewaunee site K-11 1.0 NW Harlan Ihlenfeld Farm, N879 Hy 42, Kewaunee K-1 3 3.0 SSW Rand's General Store K-14 2.5S Two Creeks Park, 2.5 miles south of site K-1 5 9.25 NW Gas Substation, 1.5 miles north of Stangelville K-1 6 26 NW WPS Division Office Bullaing, Green*Bay, Wisconsin K-17 4.25 W Jansky's Farm, N885 Tk 8, Kewaunee K-20 2.5 N Cad Struck Farm, LakeShore Dr, Kewaunee K-23 0.5W* 0.5 miles west of plant, Kewaunee site K-24 5.45 N Fectum Farm, N2653 Hy 42, Kewaunee K-25 2.0 WSW Wotachek Farm, 4819 E. Cty Tk BB, Denmark K-26 10.7 SSW Bertler's Fruit Stand (8.0 miles south of "BB")

K-27 -1.5 NW Schlies Farm, E4298 Sandy Bay Rd, Kewaunee K-28 26 NW Hansen Dairy, Green Bay, Wisconsin K-29 5*75 W Kunesh Farm, Route 1, Kewaunee K-30 1.00N End of site boundary K-31 6.25NNW E. Krok Substation K-32 11.50 N Piggly Wiggly, 931 Marquette Dr., Kewaunee K-34 2.5 N Leon and Vicki Struck, N1549 Lakeshore Dr., Kewaunee K-38 3.0 ml. WNW Dave Sinkula Farm, N890 Town Hall Road, Kewaunee K-39 3.8 mi. N Francis and Sue Wojta, N1859 Lakeshore Dr., Kewaunee

'I = indicator, C = control.

h Distances are measured from reactor stack.

4

KEWAUNEE Table 2. Type and frequency of collection.

Location Weekly Biweekly Monthly Quarterly Semiannually Annually K-la SW SL K-I b SW GRa SLt K-Ic _S_

K-ld SW Fil BS. SL K-le SW SL K-lf AP Al. GRO. TLD SO K-lg WW K-lh WW K-lI BS_

K-lk SW SL K-2 AP* Al 'TLD _

K-3 MIc GRO, TLD, CFO SO K-5 _._MIl GRa, TLD, CF0 So K-7 AP Al TLD K-8 AP Al TLD -EST. _ _-S K-9 SW BS0 , SL K-10 WW K-1 1 PR WW K-13 WW K-14 SW - BSO, SL K-15 TLD K-16 AP Al TLD K-17 TLD VE K-20 DM K-23 GRN K-24 EG DM K-25 _ MI__ GRR," TLD, CF¶,WW SO K-26 ..... VE K-27 TLD, EG DM K-28 _ _ __ Mic K-29 DM K-30 TLD K-31 AP A] " _ _ _TLD K-32 EG DM K-34 Mir GRO,CFr so K-38 MI' GRa, CFa So K-39 -_MI,' GR', TLD, CFO so I

'Three times a year, second, third and fourth quarters. bTo be collected In May and November.'

c Monthly from November through April; semimonthly May through October.

dFirst quarter (January. February, March) only.

Table 3. Sample Codes:

AP Airborne particulates MI Milk Al Airborne Iodine PR Precipitation BS Bottom (river) sediments SL Slime CF Cattlefeed SO Soil DM Domestic Meat SW Surface water EG Eggs TLD Thermoluminescent Dosimeter FI Fish VE Vegetables GRN Grain WW Well water GR Grass Note: Page 6 Is Intentionally left out 5

KEWAUNEE GRAPHS OF DATA TRENDS Note: Conventions used in trending data.

The following conventions should be used in the interpretation of the graphs of data trends:

1. Both solid and open data points may be used in the graphs. A solid point indicates an activity, an open point, a lower limit of detection (LLD) value.

2. Data points are connected by a solid line. A break in the plot indicates missing data.

7

Kewaunee Air Particulates - Gross Beta 0.100 J F M A M J J A S 0 N D Figure 2. Location K-If (weekly samples, 2006).

0.100 V)

C-,

0.010 0.001 F M F A M s eA. S 0 N D Figure 3. Location K-2 (weekly samples, 2006).

8

Kewaunee Air Particulates - Gross Beta 0.100

+ + + + + + 4 it 0.010 0.001 J F M A M J J A. S 0 N D Figure 4. Location K-7 (weekly samples, 2006).

0.100 Cf) 0.010 0.001 J F M A M J J A S 0 N D Figure 5. Location K-8 (weekly samples, 2006).

9

Kewaunee Air Particulates - Gross Beta 0.100 C.

0.010 0.001 J F M A M J J A S 0 N D Figure 6. Location K-I 6 (weekly samples, 2006).

0.100 "O) 0.

0.010 0.001 J F M A M J J A S 0 N D Figure 7. Location K-31 (weekly samples, 2006).

10

Kewaunee Air Particulates - Gross Beta 0.100 M

C., #4 0.010

.- 0

________ I________ 1 ________ 1 >1 _______

4- .4- 4 +

0.001 4-+-

2002 2003 2004 2005 2006 Figure 8. Location K-If (monthly averages, 2002-2006).

Figure 9. Location K-2 (monthly averages, 2002-2006).

11

Kewaunee Air Particulates Gross Beta 0.100 I 1 I zE CL 0.010 I 4 0.001 2002 2003 2004 2005 2006 Figure 10. Location K-7 (monthly averages, 2002-2006).

0.100-0.0 10-

2. . . . . . . 2 0.. 2 20 21 0 20

-2002 2003 2004 *2005 2006 Figure 11. Location K-8 (monthly averages, 2002-2006).

12

Kewaunee Air Particulates - Gross Beta 0.100

-V 14,

~0.010 0.001 . ... .. ... .. ... .... ... . ... ... .

2002 2003 2004 '2005 2006 Figure 12. Location K-16 (monthly averages, 2002-2006).

0.100 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

-E 0.010-2002 2003 2004 2005' 2006 Figure 13. Location K-31 (monthly averages, 2002-2006).

13

Kewaunee WELL WATER-GROSS ALPHA I

Figure 14. Location.K-lg. Total Residue. Quarterly collection.

10 8

6 CL) 4 2

04--

2002 2003 2004 2005 2006 Figure 15. Location K-lh. Total Residue. Quarterly collection.

14

Kewaunee WELL WATER-GROSS BETA 10 Figure 16. Location K-lg. Total Residue. Quarterly collection.

10.

8.

6-(A\ )

A A NZV 4-2-

04 2002 2003 2004 2005 2006 Figure 17. Location K-lh. Total Residue. Quarterly collection.

15

Kewaunee WELL WATER-GROSS BETA 10 8

6 A r / A

/

4 2

A 2002 2003 2004 2005 2006 Figure 18. Location K-10. Total Residue. Quarterly collection.

2002 2003 2004 2005 2006 Figure 19. Location K-11. Total Residue. Quarterly collection.

16

Kewaunee WELL WATER-GROSS BETA i 10 002 2002 2003 2004 2005 2006 Figure 20. Location K-25. Total Residue. Quarterly collection.

10.

8-6-

-4 4

2 0-2002 2003 2004 2005 2006 Figure 21. Location K-13. Total Residue. Quarterly collection.

17

Kewaunee Milk - Strontium-90 10.0 A

R 1.0. P\ A-AA 1% AA/'-*

ni 1 2002 2003 2004 2005 2006 Figure 22. Milk samples. Location K-3.

10.0 C.

1.0 i v k f 0.1 2002 2003 2004 2005 2006 Figure 23. Milk samples. Location K-5.

18

Kewaunee Milk - Strontium-90 10.0 i I AVV V -kA A k A i i,

0.1 200 2 2003 2004 2.005 2006 Figure 24. Milk samples. Location K-25.

10.0 1.0.

0.1 2002 2003 2004 2005 2006 Figure 25. Milk samples. Location K-28.

'-4 19

Kewaunee Milk - Strontium-90

. ý Figure 26. Milk samples. Location K-34.

10.0 C-,

1.0 1 NA v

n.t 2002 2003 2004 2005 2006 Figure 27. Milk samples. Location K-38.

20

Kewaunee Milk - Strontium-90 1.-j 06 1.0-0.1 2002 2003 2004 2005 2006 Figure 28. Milk samples. Location K-39.

21

Kewaunee Surface Water - Gross Beta Figure 29. Surface water. North Creek, Onsite (K-la).

100.0 II 10.0 k 9'!Wý - *AM n-I 2002 2003 2004 2005 2006 Figure 30. Surface water. North Creek, Onsite (K-la).

Total Residue

.22

Kewaunee Surface Water - Gross Beta 100.0 10.0 1.0 0.1 4-2002 2003 2004 2005 2006 Figure 31. Surface water. Middle Creek, Onsite (K-Ib).

100.0 10.0 aFRI I

.0.

0-1 2002 2003 2004 2005 2006 Figure 3Z., Surface water. Middle Creek, Onsite (K-i b).

Total Residue 23

Kewaunee Surface Water - Gross Beta 100.0 -4*- K-id, DS 0-K-ld, SS 10.0 C.

1.0 0.1 2002 2003 2004 2005 I 2006 Figure 33. Surface water. Lake Michigan, condenser discharge, Onsite (K-Id).

100.0 10.0 40.

ni 1 2002 2003 2004 2005 2006

• Figure 34. Surface water. Lake Michigan, condenser discharge, Onsite (K-Id)..

. Total Residue 24

Kewaunee Surface Water - Gross Beta 100.0 d -+- KI-e, DS 0-K -le, SS I 10.0 CL, 1.0 Al I 2002 2003 2004 2005 2006 Figure 35. Surface water. South Creek, Onsite (K-le).

100.0 4A 10.0 Jk-0t omý C.,

Al 2002 2003 2004 2005 2006 Figure 36. Surface water. South Creek, Onsite (K-le).

Total Residue 25

Kewaunee Surface Water - Gross Beta 100.0 10.0 0.'

1.0 0.14-2002 2003 2004 2005 2006 Figure 37. Surface water (raw). Lake Michigan, Rostok Intake (K-9)

Figure 38. Surface water (raw). Lake Michigan, Rostok Intake (K-9)

Total Residue 26

Kewaunee Surface Water - Gross Beta

-. d Figure 39. Surface water. Lake Michigan, Two Creeks Park (K-14a).

100.0 10.0 7

'V J.0 n1 2002 2003 2004 2005 2006 Figure 40. Surface water. Lake Michigan, Two Creeks Park (K-14a).

Total Residue 27

Kewaunee Surface Water - Gross Beta 100.0 "-- K-1 k, DS -- K-lk, SS 10.0 C.,

C.

1.0 I I I i -4 0.1 1 20CC)2 2003 2004 2005 2006 Figure 41. Surface water. School Forest Pond (K-I k).

100.0 OL 4L L 10.0 i F ib LE J.0 0.

ni 2002 2003 2004 2005 2006 Figure42. Surface water. School Forest Pond (K-Ik).

Total Residue 28

Kewaunee Surface Water - Tritium 10000 1000 0 0 0 100 200'2 2003 2004 2005 2006 Figure 43. Surface water. Lake Michigan, condenser discharge, K-Id. Quarterly collection.

10000 C,

1000, 100 20 02 2003 2004 2005 2006 Figure 44. Surface water. Lake Michigan, Two Creeks Park, K-1 4a. Quarterly collection.

10000 C,

1000 0 0 0

-nn 2002 2003 2004 2005 2006 Figure 45. Surface water. Lake Michigan, Rostok Intake, K-9. Quarterly collection.

Note: Prior to 2006, LLD values were reported as compliant with technical specifications (< 330 pCi/L).

29

KEWAUNEE 6.0 DATA TABULATIONS 30

KEWAUNEE Table 4. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131'.

Location: K-If3 Units: pCI/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected 3 (M ) Gross Beta Collected (M3) Gross Beta Required LLD 0.010 Required LLD 0.010 01-10-06 315 0.017

• 0.003 07-11-06 347 0.020 +/- 0.003 01-17-06 314 0.023

• 0.004 07-18-06 309 0.023 +/- 0.004 01-24-06 305 0.027 + 0.004 07-25-06 305 0.022 +/- 0.003 01-31-06 305 0.020 +/- 0.003 07-31-06 256 0.027 +/- 0.004 02-07-06 303 0.020 +/- 0.004 08-08-06 353 0.025 +/- 0.003 02-13-06 261 0.017 +/- 0.004 08-15-06 298 0.017 +/- 0.003 02-21-06 346 0.027 +/- 0.003 08-22-06 323 0.025 +/- 0.004 02-28-06 308 0.025 +/- 0.004 08-29-06 315 0.028 +/- 0.004 03-07-06 302 0.014 +/- 0.003 09-05-06 324 0.016 +/- 0.003 03-14-06 304 0.020 +/- 0.003 09-12-06 330 0.020 +/- 0.003 03-21-06 303 0.021 +/- 0.003 09-19-06 345 0.026 +/- 0.003 03-28-06 305 0.011 +/- 0.003 09-26-06 352 0.012 +/- 0.003 10-03-06 355 0.016 +/- 0.003 1st Quarter Mean +/- s.d. 0.020 +/- 0.005 .3rd Quarter Mean +/-s.d. 0.021 +/- 0.005 04-04-06 302 0.019 +/- 0.004 10-10-06 355 0.015 +/- 0.003 04-11-06 304 0.018 +/- 0.003 .10-17-06 363 0.017 +/- 0.003 04-18-06 304 0.018 +/- 0.003 10-24-06 346 0.014 +/- 0.003 04-25-06 304 0.013 +/- 0.003 10-31-06 358 0.015 +/- 0.003 05-01-06 260 0.017 +/- 0.004 11-06-06 303 0.026 +/- 0.004 05-09-06 . 347 0.013 +/- 0.003 11-13-06 356 0.024 +/- 0.003 05-17-06 348 0.010 +/- 0.003 11-20-06 354 0.025 +/- 0.003 05-23-06 260 0.008 +/- 0.003 11-28-06 407 0.030 +/- 0.003 05-30-06 304 0.020 +/- 0.003 12-05-06 353 0.025 +/- 0.003 06-06-06 312 0.012 +/- 0.003 12-12-06 354 0.026 +/- 0.003 06-13-06 297 0.013 +/- 0.003 12-19-06 356 0.036 +/- 0.004 06-20-06 299 0.018 +/- 0.003 12-26-06 355 0.023 +/- 0.003 06-27-06 309 0.011 +/- 0.003 01-02-07 356 0.025 +/- 0.003 07-03-06 260 0.021 +/- 0.004 2nd Quarter Mean +/- s.d. 0.015 +/- 0.004 4th Quarter Mean +/- s.d. 0.023 +/- 0.006 Cumulative Average 0.020 Previous Annual Average 0.022 a Iodine-1 31 is sampled biweekly. Concentrations are < 0.03 pCI/m 3 unless otherwise noted.

31

KEWAUNEE Table 5. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-1 31 a Location: K-23 Units: pCI/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (Mi) - Gross Beta Collected (iMn) Gross Beta Required LLD 0.010 Required LLD 0.010 01-10-06 305 0.015 +/- 0.003 07-11-06 347 0.015

• 0.003 01-17-06 304 0.020 +/- 0.003 07-18-06 303 0.026 +/- 0.004 01-24-06 304 0.024 +/- 0.004 07-25-06 312 0.020 +/- 0.003 01-31-06 306 0.018 +/- 0.003 07-31-06 256 0.029 k 0.004 02-07-06 305 0.022 +/- 0.004 08-08-06 347 0.019 **0.003 02-13-06 259 0.018 +/- 0.004 08-15-06 303 0.016 +/- 0.003 02-21-06 345 0.024 +/- 0.003 08-22-06 313 0.027 +/- 0.004 02-28-06 308 0.024 +/- 0.004 08-29-06 295 0.028 +/- 0.004 03-07-06 303 0.016 +/- 0.003 09-05-06 "304 0.016 t 0.003 03-14-06 304 0.023 +/- 0.003 09-12-06 305 0.024 +/- 0.004 03-21-06 303 0.021 +/- 0.003 09-19-06 304 0.027

• 0.004 03-28-06 304 0.011 +/- 0.003 09-26-06 312 0.016 +/- 0.003 10-03-06 324 0.013 +/- 0.003 1st Quarter Mean +/- s.d. 0.020 +/- 0.004 3rd Quarter Mean +/- s.d. 0.021 +/- 0.006 04-04-06 301 0.018 +/- 0.004 10-10-06 318 0.014 +/- 0.003 04-11-06 304 0.018 +/- 0.003 10-17-06 303 0.017 +/- 0.003 305 10-24-06 305 0.016 f 0.003 04-18-06 0.018 ++/-0.004 04-25-06 304 0.015 +/- 0.003 10-31-06 304 0.017 +/- 0.003 05-01-06 263 0.016 +/- 0.004 11-06-06 259 0.029 *0.004 05-09-06 347 0.017 +/- 0.003 11-13-06 305 0.026

• 0.004 05-17-06 317 0.010 +/- 0.003 11-20-06 303 0.030 +/- 0.004 05-23-06 262 0.008 +/- 0.003 11-28-06 351 0.033 +/- 0.004 05-30-06 303 0.023 +/- 0.003 12-05-06 300 0.031 ft 0.004 06-06-06 312 0.014 +/- 0.003 12-12-06 303 0.035 *0.004 06-13-06 297 0.024 +/- 0.004 12-19-06 305 0.037 +/-0.004 06-20-06 301 0.022 +/- 0.003 12-26-06 304 0.027 +/-0.004 06-27-06 307 0.015 +/- 0.003 01-02-07 305 0.024 +/- 0.004 07-03-06 260 0.025 f 0.004 2nd Quarter Mean +/- s.d. 0.017 +/- 0.005 4th Quarter Mean +/- s.d. 0.026 +/- 0.008 Cumulative Average 0.021 Previous Annual Average 0.022 Iodine-131 is sampled biweekly. Concentrations are <0.03 pCi/m 3 unless otherwise noted.

32

KEWAUNEE Table 6. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-I 3 1a.

Location: K-7 3 Units: pCi/m Collection: Continuous, weekly exchange.

Date Volume Date Volume 3

(mn)

Collected (mW) Gross Beta Collected Gross Beta Required LLD 0.010 Required LLD 0.010 01-10-06 304 0.018

• 0.003 07-11-06 *345 0.019 +/- 0.003 01-17-06 307 0.024

• 0.004 07-18-06 306 0.026 +/- 0.004 01-24-06 303 0.026 +/- 0.004 07-25-06 308 0.021 +/- 0.003 01-31-06 307 0.020 +/- 0.003 07-31-06 256 0.029 +/- 0.004 02-07-06 290 0.021 + 0.004 08-08-06 349 0.020 +/- 0.003 02-13-06 261 0.020 + 0.004 08-15-06 300 0.018

• 0.003 02-21-06 348 0.028 + 0.004 08-4-06 311 0.026 + 0.004 02-28-06 336 0.026 +/- 0.004 08-29-06 301 0.026 +/- 0.004 03-07-06 337 0.015

• 0.003 09-05-06 300 0.016 +/- 0.003 03-14-06 351 0.018 +/- 0.003 09-12,06 308 0.020 +/- 0.004 03-21-06 322 0.021 +/- 0.003 09-19-06 305 0.027 +/- 0.004 03-28-06 307 0.009 +/- 0.003 09-26-06 301 0.015 + 0.003 10-03-06 302 0.015

• 0.003 1st Quarter Mean +/- s.d. 0.021 +/- 0.005 3rd Quarter Mean +/- s.d. 0.021 +/- 0.005 04-04-06 304 0.014 +/- 0.003 10-10-06 302 0.014 +/- 0.003 04-11-06 301 0.017 +/- 0.003 10-17-06 305 .0.017 +/- 0.003 04-18-06 304 0.018 +/- 0.004 10-24-06 303 0.017 +/- 0.003 04-25-06 307 0.016 +/- 0.003 10-31-06 311 0.024 +/- 0.004 05-01-06 256 0.017 +/- 0.004 i11-06-06 259 0.028'+/- 0.004 05-09-06 347 0.014 +/- 0.003 11-13-06 306 0.024 +/- 0.004 05-17-06 347 0.012 +/- 0.003 11-20-06 300 0.023 +/- 0.004 05-23-06 261 0.010 +/- 0.003 11-28-06 347 0.041 .+/- 0.004 05-30-06 303 0.023 +/- 0.004 12-05-06 302 0.028 +/- 0.004 06-06-06 315 0.015 +/- 0.003 12-12-06 305 0.027 +/- 0.004 06-13-06 294 0.014 +/- 0.003 12-19-06 308 0.041 +/- 0.004 06-20-06 301 0.023 +/- 0.004 12-26-06 303 0.024 +/- 0.004 06-27-06 311 0.014 +/- 0.003 01-02-07 303 0.024 +/- 0.004 07-03-06 260 0.019 +/- 0.004 2nd Quarter Mean +/- s.d. 0.016 +/- 0.004 4th Quarter Mean +/- s.d. 0.026 +/- 0.008 Cumulative Average 0.021 Previous Annual Average 0.023 a Iodine-I 31 is sampled biweekly. Concentrations are < 0.03 pCI/nM 3 unless otherwise noted.

33

KEWAUNEE Table 7. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-1 318.

Location: K-8 Units: pCil/m3 Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m3) Gross Beta Collected (Mi) Gross Beta Required LLD 0.010 Reaulred LLD 0.010 01-10-06 356 0.015 +/- 0.003 07-11-06 346 0.018 +/- 0.003 01-17-06 348 0.024 +/- 0.003 07-18-06 305 '0.033 +/- 0.004 01-24-06 318 0.026 +/- 0.004 07-25-06 309 0.019 +/- 0.003 01-31-06 312 0.020 + 0.003 07-31-06 265 0.032 +/- 0.004 02-07-06 298 0.023 k 0.004 08-08-06 375 0.020 +/- 0.003 02-13-06 261 0.018 +/- 0.004 08-15-06 313 0.016 +/- 0.003 02-21-06 0.030 +/- 0.004 08-22-06 321 0.025 +/- 0.004 347 02-28-06 336 0.025 +/- 0.003 08-29-06 320 0.024 +/- 0.004 03-07-06 353 0.014 +/- 0.003 09-05-06 321 0.013 +/- 0.003 03-14-06 355 0.021 +/- 0.003 09-12-06 317 0.022 +/- 0.004 03-21-06 323 0,025 +/- 0.003 09-19-06 305 0.025 +/- 0.004 03-28-06 347 0.009 +/- 0.003 09-26-06 301 0.017 +/- 0.003 10-03-06 302 0.017 +/- 0.003 1st Quarter Mean +/- s.d. 0.021 +/-'0.006 3rd Quarter Mean +/- s.d. 0.022 +/- 0.006 04-04-06 .331 0.014 +/- 0.003 10-10-06 303 0.017 +/- 0.003 04-11-06 314 0.020

• 0.003 10-17-06 305 0.017 +/- 0.003 04-18-06 315 0.020 +/- 0.004 10-24-06 303 0.016 +/- 0.003 04-25-06 329 *.6.01"5 +/- 0.003 10-31-06 311 0.018 +/- 0.003 05-01-06 267 0.017 +/- 0.004 11-06-06 259 0.026 +/- 0.004 05-09-06 347 0.014 +/- 0.003 11-13-06 306 0.024 +/- 0.004 05-17-06 349 0.012 +/- 0.003 11-20-06 291 0.026 +/- 0.004 05-23-06 259 0.007 +/- 0.003 11-28-06 357 0.033 +/- 0.004 05-30-06 306 0.028 +/- 0.004 12-05-06 302 0.031 +/- 0.004 06-06-06 314 0.016 +/- 0.003 12-12-06 305 0.032 +/- 0.004 06-13-06 295 0.016 +/- 0.003 12-19-06 308 0.037 +/- 0.004 06-20-06 *300 0.027 +/- 0.004 12-26-06 303 0.023 +/- 0.004 06-27-06 310 0.014 +/- 0.003 01-02-07 304 0.024 +/- 0.004 07-03-06 260 0.025 +/- 0.004 2nd Quarter Mean*+/- s.d. 0.018 +/- 0.006 4th Quarter Mean +/- s.d. 0.025 +/- 0.007 Cumulative Average 0.021 Previous Annual Average 0.023 8 Iodine-131 is sampled biweekly. Concentrations are < 0.03 pCi/rn 3 unless otherwise noted.

34

KEWAUNEE Table 8. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131a.

Location: K-16 3

Units: pCilm Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (ms) Gross Beta Collected (M) Gross Beta Required LLD 0.010 Required LLD 0.010 01-10-06 305 0.015 +/- 0.003 07-11-06 408 0.014 +/- 0.003 01-17-06 304 0.030

• 0.004 07-18-06 352 0.029 +/- 0.004 01-24-06 303 0.025 +/- 0.004 07-25-06 363 0.020 +/- 0.003 01-31-06 306 0.022 +/- 0.004 07-31-06 300 0.027 +/- 0.004 02-07-06 301 0.022 +/- 0.004 08-08-06 403 0.017.+/- 0.003 02-13-06 263 0.019 +/- 0.004 .08-15-06 355 0.016 +/- 0.003 02-21-06 346 0.027 +/- 0.004 08-22-06 294 0.032 +/- 0.004 02-28-06 333 0.027 +/- 0.004 08-29-06 320 0.027.+/- 0.004 b

03-07-06 353 0.016 +/- 0.003 09-05-06 322 0.015 +/- 0.003 b

03-14-06 355 0.019 +/- 0.003 09-12-06 357 0.020 +/- 0.003 b

03-21-06 353 0.023 +/- 0.003 09-19-06 356 0.022 + 0.003 b

03-28-06 359 0.009 +/- 0.003 09-26.06 341 0,019 +/- 0.003 10-03-06 322 0.020 +/- 0.003 1st Quarter Mean +/- s.d. 0.021 +/- 0.006 3rd Quarter Mean +/- s.d. 0.021 +/-:0.006 04-04-06 323 0.019 +/- 0.003 10-10-06 301 .0.018 +/- 0.003 04-11-06 305 0.023 +/- 0.004 10-1.7-06 307 0.017 +/- 0.003 04-18-06 330 .0.019 +/- 0.003 10.,.4-06 302 0.018 +/- 0.003 04-25-06 353 0.015 +/- 0.003 10-31-06 304 0.018 +/- 0.003 05-01-06 267 0.019 +/- 0.004 b ___

11-06-06 268 0.031 +/- 0.004 05-09-06 373 0.016 +/- 0.003 11-13-06 281 0.033 +/- 0.004 05-17-06 ,361 0.010 +/- 0.003 11-20-06 324 0.024 +/- 0.004 05-23-06 260 0.009 +/- 0.003 11-28-06 359 0.035 +/- 0.004 05-30-06 330 0.027 +/- 0.003 12-05-06 305 0.028 +/- 0.004 06-06-06 363 0.018 +/- 0.003 12-12-06 302 0.033 +/- 0.004 06-13-06 349 0.015 +/- 0.003 12-19-06 305 0.038 +/- 0.004 06-20-06 350 0.021 +/- 0.003 12-26-06 303 0.023 t 0.004 06-27-06 357 0.015 +/- 0.003 01-02-07 322 0.024 +/- 0.004 07-03-06 303 0.022 +/- 0.004 2nd Quarter Mean

• s.d. 0.018 +/- 0.005 4th Quarter Mean +/- s.d. 0.026 +/- 0.007 Cumulative Average 0.022 Previous Annual Averacie 0.023 a Iodine-1 31 is sampled biweekly. Concentrations are < 0.03 pCi/m 3 unless otherwise noted.

b Incorrect timer reading, volume is estimated.

35

KEWAUNEE Table 9. Airborne particulates and charcoal canisters, analyses for gross beta and lodine-1 31a.

Location: K-31 Units: pCi/mn Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (mi) Gross Beta Collected (m3) Gross Beta Required LLD 0.010 Requlred LLD 0.010 01-10-06 355 0.013 +/- 0.003 07-11-06 348 0.016 +/- 0.003 01-17-06 340 0.024 +/- 0.003 07-18-06 302 0.027 t 0.004 01-24-06 324 0.027 +/- 0.004 ;07-25-06 313 0.020 +/- 0.003 01-31-06 329 0.015 +/- 0.003 07-31-06 256 0.031 +/- 0.005 02-07-06 315 o 617 +/-0.003 08-08-06 347 0.020 +/- 0.003

.08-15-06 303 0.018 +/- 0.003 02-13-06 260 0.012 +/- 0.004 02-21-06 346 0.022 +/- 0.003 08-22-06 323 0.023 +/- 0.004 02-28-06 307 0.021 +/- 0.004 08-29-06 315 0.024 +/- 0.004 03-07-06 278 0.012 +/- 0.003 09-05-06 324 0.015 +/- 0.003 03-14-06 253 06023' t 0.004 09-12-06 315 0.020 +/- 0.003 03-21-06 253 0'024 +/- 0.004 09-19-06 - 314 0.029 +/- 0.004 03-28-06 254 0.012 +/- 0.004 09-26-06 312 0.017 +/- 0.003 10-03-06 305 0.018 +/- 0.003 1st Quarter Mean +/- s.d. 0.019 +/- 0.006 3rd Quarter Mean +/- s.d. 0.021 +/- 0.005 04-04-06 276 0.01 5 +/- 0.004 10-10-06 306 0.020 +/- 0.004 04-11-06 305 0.015 +/- 0.003 17-06 303 0.019 +/- 0.003 04-18-06 304 0.01* +/- 0.003 10-24-06 306 0.017 +/- 0.003 04-25-06 303 0:012 +/- 0.003 10-31106 320 0.018 +/- 0.003 05-01-06 264 0.017 +/- 0.004 11-06-06 294 0.029 +/- 0.004 05-09-06 347 0.015 +/- 0.003 11-13-06 341 0.027 +/- 0.003 05-17-06 345 0.011 +/- 0.003 11-20-06 324 0.026 +/- 0.004 05-23-06 261 0.009 +/- 0.003 11-28-06 362 0.033 +/- 0.004 05-30-06 304 0.028 +/- 0.004 12-05-06 301 0.034 +/- 0.004 06-06-06 312 0.014 +/- 0.003 12-12-06 303 0.033 +/-0.004 06-13-06 297 0.012 +/- 0.003 12-19-06 314 0.035 +/- 0.004 06-20-06 301 0.022 +/- 0.003 12-26-06 330 0.024 +/- 0.003 06-27-06 306 0.014 +/- 0.003 '011:02-07 336 0.019 +/- 0.003 07-03-06 260 0.025 +/- 0.004 2nd Quarter Mean +/- s.d. 0.016 +/- 0.005 4th Quarter Mean +/- s.d. 0.026 +/- 0.007 Cumulative Average 0.020 Previous Annual Averaae 0.022 Iodine-131 is sampled biweekly. Concentrations are < 0.03 pCi/m 3 unless otherwise noted.

36

KEWAUNEE Table 10. Airborne particulate data, gross beta analyses, monthly averages, minima and maxima.

January April Location Average Minima Maxima Location Average Minima Maxima Indicators 0.022 0.017 0.027 Indicators 0.017 0.013 0.019 K-Ilf 0.022 0.017 0.027 K-lf 0.017 0.013 0.019 K-7 0.022 0.018 0.026 K-7 0.016 0.014 0.018 Controls 0.021 0.013 0.030 Controls 0.017 0.012 0.023 K-2 0.019 0.015, 0.024 K-2 0.017 0.015 0.018 K-8 0.021 0.015 0.026 K-8 0.017 0.014 0.020 K-16 0.023 0.015 0.030 K-16 0.019 0.015 0.023 K-31 0.020 0.013 0.027 K-31 0.015 0.012 0.017 February May Location Average, Minima Maxima Location- Average Minima Maxima Indicators 0.023 0.017 0.028 Indicators 0.014 0'008 0.023 K-if 0.022 0.017 0.027 K-if 0.013 0.008 0.020 K-7 0.024 0.020 0.028 K-7 0.015 0.010 0.023 Controls 0.022 0.012 0.030 Controls 0.0,15 0.007 0.028 K-2 0.022 0.018 0.024 K-2 0.015 0.008 0.023 K-8 0.024 0.018 0.030 K-8 0.015 0.007 0.028 K-1 6 0.024 0.019 0.027 K,16 0.016 0.009 0.027 K-31 0.018 0.012 0.022 K-31 0.016 0.009 0.028 March June Location Average Minima Maxima, Location. Average Minima Maxima Indicators 0.016 0.009 0.021 Indicators K-If 0.017 0.011 0.021 K-Ilf 0.015 0.011 0.021 K-7 0.016 0.009 0.021 K-7 0.017 0.014 0.023 Controls 0.017 0.009 0.025 Controls 0.019 0.012 0.027-K-2 0.018 0.011 0.023 K-2 0.020 0.014 0.025 K-8 0.017 0.009 0.025 K-8 0.020 0.014 0.027 K-16 0.017 0.009 0.023 K-16 0.018 0.015 0.022 K-31 0.018 0.012 0.024 K-31 0.017 0.012 0.025 Note: Samples collected on the first, second or third day of the month are grouped with data of the previous month.

37

KEWAUNEE Table 10. Airborne particulate data, gross beta analyses, monthly averages, minima and maxima.

July October Location Average Minima Maxima Location Average Minima Maxima Indicators 0.023 0.019 0.029 Indicators 0.017 0.014 0.024 K-If 0.023 0.020 0.027 K-If 0.015 0.014 0.017 K-7 0.024 0.019 0.029 K-V 0.018 0.014 0.024 Controls 0.024 0.014 0.033 Controls 0.017 0.014 0.020 K-2 0.023 0.015 0.029 K-2 0.016 0.014 0.017 K-8 0.026 0.018 0.033 K-8 0.017 0.016 0.018 K-16 0.023 0.014 0.029 K-16 0.018 0.017 0.018 K-31 0.024 0.016 0.031 K-31 0.019 0.017 0.020 August - November Location Average Minima Maxima Location Average Minima Maxima Indicators 0.023 0.017 0.028 Indicators 0.028 0.023 0.041 K-If 0.024 0.017 0.028 K-If 0.026 0.024 0.030 K-7 0.023 0.018 0.026 K-7 0.029 0.023 0.041 Controls 0.022 0.016 0.032 Controls 0.029 0.024 0.035 K-2 0.023 0.016 0.028 K-2 0.030 0.026 0.033 K-8 0.021 0.016 0,025 K8 0.027 0.024 0.033 K-16 0.023 0.016 0.032 K-16 0.031 0.024 0.035 K-31 0.021 -0.016 -0.032- K-31 0.029 0.026 0.033 September . December Location Average Minima Maxima Location Average Minima Maxima Indicators -0.018 0.012 0.027 Indicators 0.028 0.023 0.041 K-if 0.018 0.012 0.026 K-If 0.027 0.023 0.036 K-7 0.0190 0.015 0.027 K-7 0.029 0.024 0.041 Controls- 0.019 0.013 0.029 Controls 0.030 0.019 0.038 K-2 0.019 0.013 0.027 K-2 0.031 0.024 0.037 K-8 0.019 0.013 0.025 K-8 0.029 0.023 0.037 K-16 0.019 0.015 0.022 K-1 6 0.029 0.023 0.038 K-31 0.020 0.015 0.029 K-31 0.029 0.019 0.035 Note: Samples collected on the first, second or third day of the month are grouped with data of the previous month.

38

KEWAUNEE Table 11. Airborne particulate samples, quarterly composites of weekly samples, analysis for gamma-emitting isotopes.

Sample Description and Concentration (pCi/m 3) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Indicator K-If Lab Code KAP-2678 KAP-4929 KAP-7571 KAP-9709, 10 3

Volume (M ) 3671 4210 4212 4616 Be-7 0.063 +/- 0.013 0.075 +/- 0.019 0.069 +/- 0.013 0.057 +/- 0.009 Nb-95 < 0.0013 < 0.0010 < 0.0007 < 0.0010 Zr-95 < 0.0026 < 0.0013 < 0.0010 < 0.0008 Ru-103 < 0.0007 < 0.0010 < 0.0007 < 0.0005 Ru-106 < 0.0058 < 0.0067 < 0.0047 < 0.0044 Cs-134 < 0.0006 < 0.0007 < 0.0004 < 0.0005 Cs-I 37 < 0.0006 < 0.0006 < 0.0004 < 0.0006 Ce-141 < 0.0016 < 0.0014 < 0.0017 < 0.0006 Ce-144 < 0.0026 < 0.0030 < 0.0044 < 0.0022 K-7 Lab Code KAP-2680 KAP-4932;. KAP-7573, 4 KAP-9712 3

Volume (M ) 3773 4211 3992 3954 Be-7 0.055 +/- 0.013 0.083 +/- 0.017 0.077 +/- 0.010 0.049 +/- 0.013 Nb-95 < 0.0016 < 0.0006, < 0.0007 < 0.0012 Zr-95 < 0.0014 < 0.0011 < 0.0014 < 0.0012 Ru-103 < 0.0016 < 0.0009 < 0.0004 < 0.0011 Ru-1 06 < 0.0048 < 0.0064, < 0.0039 < 0.0067 Cs-134 < 0.0010 < 0.0007 < 0.0005 < 0.0008 Cs-137 < 0.0006 < 0.0007 < 0.0005 < 0.0003 Ce-141 < 0.0018 < 0.0008 < 0.0010 < 0.0014 Ce-144 < 0.0043 < 0.0037 < 0.0033 < 0.0024 39

KEWAUNEE Table 11. Airborne particulate samples, quarterly composites of weekly samples, analysis for gamma-emitting Isotopes, (continued).

Sample Description and Concentration (pCI/M 3) 1st Quarter. 2nd Quarter 3rd Quarter 4th Quarter Control K-2 Lab Code KAP-2679 KAP-4930, 1; KAP-7572 KAP-9711 3

Volume (M ) 3650 4183 4025 3965 Be-7 0.074 t 0.014 0.077 1 0.010 0.074 1 0.014 0.068 1 0.014 Nb-95 < 0.0014 < 0.0008 < 0.0006 < 0.0014 Zr-95 < 0.0010 < 0.0010 < 0.0018 < 0.0011 Ru-103 < 0.0014 < 0.0007 < 0.0007 < 0.0009 Ru-I 06 < 0.0057 < 0.0042 < 0.0051 < 0.0063 Cs-134 < 0.0006 < 0.0006 < 0.0006 < 0.0007 Cs-137 < 0.0009 < 0.0005 < 0.0007 < 0.0009 Ce-141 < 0.0016 < 0.0014 < 0.0015 < 0.0009 Ce-144 < 0.0040 < 0.0029 < 0.0031 < 0.0032 Lab Code' .KAP-1 631 KAP-4933 KAP-7575 KAP-9713 Volume (M3) 3954 4296 4100 3957 Be-7 0.054

• 0.015 0.076 1 0.015 0.071-

• 0.013 0.051 +/- 0.009 Nb-95 <0.0004 < 0.0009 < 0.0005 < 0.0008 Zr-95 < 0.0009 < 0.0012 < 0.0012 < 0.0011 Ru-103 < 0.0006 < 0.0010 < 0.0007 < 0.0009 Ru-106 < 0:0044" < 0.0060 < 0.0062 < 0.0051 Cs-I 34 < 0.6008 < 0.0006 < 0.0008 < 0.0005 Cs-1 37 < 0.0005 < 0.0004 < 0.0006 < 0.0004 Ce-141 < 0:0012 < 0.0018 < 0.0016 < 0.0009 Ce-144 < 0.0037 < 0.0025 < 0.0022 < 0.0021 40

KEWAUNEE Table 11. Airborne particulate samples, quarterly composites of weekly samples, analysis for gamma-emitting isotopes, (continued).

Sample Description and Concentration (pCi/m 3 )

1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Control K-1i6 Lab Code KAP-2682 KAP-4934 KAP-7576 KAP-9714 Volume (mi3 ) 3881 4624 4493 3983 Be-7 0.060 1 0.016 0.067.+/- 0.013 0.070 +/- 0.014 0.055 +/- 0.017 Nb-95 < 0.0009 < 0.0003 < 0.0010 < 0.0012 Zr-95 < 0.0020 < 0.0014 < 0.0019 < 0.0016 Ru-103 < 0.0015 < 0.0008 < 0.0009 < 0.0008 Ru-106 < 0.0066 < 0.0053 < 0.0031 < 0.0045 Cs-134 < 0.0007 < 0,0007 < 0.0006 < 0.0006 Cs-137 < 0.0005 < 0.0005 < 0.0004 < 0.0007 Ce-141 < 0.0015 < 0.0019 < 0.0015 < 0.0015 Ce-144 < 0.0047 < 0.0047 < 0.0045 < 0.0036 K-31 Lab Code KAP-2683 KAP-4935 KAP-7577 KAP-9715 Volume (Mi) 3614 4185 4077 4140 Be-7 0.049 +/- 0.018 0.061 +/- 0.013 0.093 +/- 0.016 0.050 +/- 0.010 Nb-95 < 0.0013 < 0.0008 < 0.0011 < 0.0007.

Zr-95 < 0.0016 < 0.0011 < 0.0016 < 0.0014 Ru-103 < 0.0013 < 0.0013 < 0.0011 < 0.0011 Ru-106 < 0.0059 < 0.0045 < 0.0085 < 0.0061 Cs-134 < 0.0009 < 0.0007 < 0.0009 < 0.0007 Cs-137 < 0.0004 < 0.0008 < 0.0010 < 0.0006 Ce-141 < 0.0023 < 0.0016 < 0.0013 < 0.0007 Ce-144 < 0.0031 < 0.0046 < 0.0038 < 0.0036 41

KEWAUNEE Table 12. Ambient gamma radiation (TLD), quarterly exposure.

1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Date Placed 01-03-06 04-03-06 07-05-06 Date Removed 04-03-06 07-05-06 10-03-06 mR/91 daysa Indicator Mean~s.d.

K-If 13.3 +/- 0.6 11.5 +/-0.7 13.1

• 0.7 12.9

• 0.8 12.7

• 0.8 K-5 19.7 +/- 0.7 17.8 +/- 0.5 19.1 *0.4 18.8 +/- 0.7 18.9 +/- 0.8 K-7 19.1 + 1.0 18.1 +/-0.8 19.9 +/- 0.6 19.5 + 0.6 19.2

• 0.8 K-1 7 16.9 +/- 0.6 13.0 +/-+0.5 17.7

• 0.2 13.3

• 0.3 15.2

• 2.4 K-25 17.9 +/- 1.0 16.2 *0.5 17.6 +/-0.6 16.6 +/- 0.5 17.1 +/- 0.8 K-27 15.3 +/- 0.7 17.2 +/-1.0 15.8 +/- 0.7 17.7 +/- 0.9 16.5 +/- 1.1 K-30 15.7 +/- 0.8 13.0

• 0.7 16.9 +/- 0.8 13.9 +/- 1.1 14.9 +/-1.8 K-39 16.9 +/- 0.6 15.5 +/- 1.0 17.2

• 0.9 17.2 +/- 0.8 16.7

• 0.8 Mean t s.d. 16.9

• 2.1 15.3 +/- 2.5 17.2 +/- 2.1 16.2

• 2.6 .16.4 +/- 0.8 Control K-2 16.1 +/- 0.4 15.1 +/-0.6 17.0 +/-.0.5 16.6 +/- 0.9 16.2 +/- 0.8 K-3 16.8 +/- 1.1 16.2 +/-0.8 18.5 +/-0.8 17.6 +/- 0.9 17.3 +/- 1.0 K-8I 16.4 1°0.5 14.7 +/-0.5 16.6

• 0.3 15.3

• 0.6 15.8 +/- 0.9 K-1-5 15.6 +/- 0.6 13.9 :k 0.5 15.1 *0.4 15.3 +/- 0.6 15.0

• 0.7 K-1 6 14.5 +/- 0.8 11.8 +/- 0.4 13.5

• 0.6 12.5 +/- 0.5 13.1

• 1.2 K-31 13.3

• 0.4 12.0 +/- 0.7 12.8 t 0.4 13.3 +/- 0.4 12.9 +/-0.6 Mean t s.d. 15.5 +/- 1.3 14.0 +/-1.8 15.6 +/- 2.2 15.1 +/- 1.9 15.0 +/-0.7 aThe uncertainty for each location corresponds to the two-standard deviation error of the average dose of eight dosimeters placed at this location.

42

KEWAUNEE Table 13. Precipitation samples collected at Location K-11; analysis for tritium.

Date Lab H-3 Collected Code pCi/L T.U. (100 T.U. = 320 pCVL) 01/03/06 KP -125 < 153 < 48 01/31/06 -547 < 182 < 57 02/28/06 -1085 < 152 < 48 03/28/06 -1886, 7 < 159 < 50 05/01/06 -3072 < 138. < 43 05/30/06 -3753 < 128 < 40 07/03/06 "4510, 11 < 131 < 41 07/31/06 -5310 < 158 < 49 09/03/06 6120 < 171 < 53 10/03/06 -6926 < 182 < 57 10/31/06 -8042 < 143 < 45 12/05/06 -8822 < 176 < 55 43

KEWAUNEE Table 14. Milk, analyses for iodine-131 and gamma-emitting Isotopes.

Collection: Semimonthly during grazing season, monthly at other times.

Collection Lab Concentration (pCi/L)

Date Code 1-131 Cs-134 Cs-137 Ba-La-140 K-40 Indicators K-5 01-04-06 KMI - 45 < 0.5 <10 <10 <15 1393

• 167 02-01-06 -499 < 0.5 <10 <10 <15 1412 + 107 03-01-06 -1033 < 0.5 <10 <10 <15 1221

• 231 04-03-06 -1990 <0.5 <10 <10 <15 1367

• 166 05-01-06 -2916 < 0.5 <10 <10 <15 1320

• 130 05-16-06 - 3300 <0.5 <10 <10 <15 1304 +/- 102 06-01-06 - 3633 <0.5 <10 <10 <15 1328

• 195 06-20-06 - 4079 < 0.5 <10 <10 <15 1245 +/- 156 07-05-06 - 4393 < 0.5 <10 <10 <15 1334 + 105 07-18-06 -4817 < 0.5 <10 < 10 <15 1383 +/- 178 08-01-06 -5271 < 0.5 <10 <10 <15 1279 +/- 124 08-15-06 -5510 < 0.5 <10 <10 <15 1389

• 121 09-05-06 -6073 < 0.5 <10 <10 <15 1476

• 160 09-19-06 -6418 <0.5 <10 <10 <15 1441 +/- 175 10-02-06 - 6727 < 0.5 <10 <10 <15 1441 +/- 177 10-17-06 -7391 < 0.5 <10 <10 <15 1362 +/- 182 11-02-06 - 7985 < 0.5 <10 <10 <15 1396 +/- 122 12-04-06 - 8698 <0.5 <10 <10 <15 1356 +/- 176 K-25 01-03-06 KMI -46 < 0.5 <10 <10 <15 1298 +/- 172 02-01-06 -500 < 0.5 <10 <10 <15 1297 +/-105 03-02-06 -1034 < 0.5 <10 <10 <15 1051 +/-168 04-03-06 -1991 < 0.5 <10 <10 <15 1288

• 171 05-01-06 -2917 < 0.5 <10 <10 <15 1366 +/-127 05-16-06 -3301 <0.5 <10 <10 <15 1385 +/- 119 06-02-06 -3634 <0.5 <10 <10 <15 1391 +/- 121 06-20-06 - 4080 < 0.5 <10 <10 <15 1272 +/- 115 07-06-06 -4394 < 0.5 <10 <10 <15 1349 +/- 109 07-18-06 -4818 < 0.5 <10 <10 <15 1306 +/- 166 08-01-06 -5272 < 0.5 <10 <10 <15 1339 +/-115 08-15-06 -5511 < 0.5 <10 <10 <15 1416 +/-119 09-06-06 -6074 <0.5 <10 <10 <15 1379 +/- 161 09-19-06 -6419 <0.5 <10 <10 <15 1380 +/- 104 10-03-06 -6728 < 0.5 <10 <10 <15 1443 +/- 165 10-17-06 -7392 < 0.5 <10 <10 <15 1382 +/- 176 11-02-06 - 7986 < 0.5 <10 <10 <15 1388 +/- 112 12-05-06 -8699 < 0.5 <10 <10 <15 1365 +/-178 44

KEWAUNEE Table 14. Milk, analyses for iodine-131 and gamma-emitting isotopes (continued).

Collection Lab Concentration (pCVL)

Date Code (1431 Cs-134 Cs-137 Ba-La-140 K-40 Indicators K-34 01-03-06 KMI -48 <0.5 <10 <10 <15 1490*112 02-01-06 -502 < 0.5 <10 <10 <15 1392

• 103 03-01-06 -1036 < 0.5 <10 <10 <15 1440+/-*123 04-03-06 - 1993 < 0.5 <10 <10 < 15 1504

• 60 05-01-06 -2919 <0.5 <10 <10 <15 1324*118 -,

05-16-06 -3303 < 0.5 <10 <10 <15 1552 139 06-01-06 -3636 <0.5 <10 . <10 <15 1408+/-116 06-20-06 -.4082 < 0.5 <10 <10 <15 1350 122 07-05-06 -4396 < 0.5 <10 <10 <15 1376 123 07-18-06 -4820 <0.5 <10 <10 <15 1342*110 08-01-06 -5274 < 0.5 <10 <10 <15 1413

• 98 08-15-06 -.5513 < 0.5 <10 <10 <15 1513 +/- 128 09-05-06 -6076 < 0.5 <10 <10 <15 1384 +/- 167 09-19-06 -6421 < 0.5 <10 <10 <15 1441 +/- 122 10-02-06 6730 < 0.5 <10 <10 <15 1323 +/-:147 10-17-06 -7394 < 0.5 <10 <10 <15 1508 +/-187 11-01-06 -7988 < 0.5 <10 <10 <15 1409 +/- 125 12-04-06 -8701 < 0.5 <10 <10 <15 1425 +/- 126 45

KEWAUNEE Table 14. Milk, analyses for iodine-131 and gamma-emitting Isotopes (continued).

Collection Lab' Concentration (pCi/L)

Date Code 1-131 Cs-134 Cs-137 Ba-La-140 K-40 Indicators K-38 01-04-06 KMI -49 < 0.5 <10 <10 .< 15 13331108 02-01-06 -503 <0.5 <10 <10 <15 1295t106 03-01-06 -1037 < 0.5 <10 <10 < 15 1252 123 04-04-06 -A1994 <0.5 <10 <10 <15 1225 +/-175 05-02-06 -2920 < 0.5 <10 <10 < 15 1385

• 86 05-16-06 -3304 < 0.5 <10 <10 < 15 1285 t 127 06-01-06 "-3637 < 0.5 <10 <10 < 15 1247

• 183 06-20-06 -4083 <0.5 <10 <10 <15 1374

• 41 07-05-06 -4397 < 0.5 <10 <10 < 15 1328 182 07-18-06 -4821 <0.5 <10 <10 <15 1370 111 08-01-06 -5275 < 0.5 <10 <10 < 15 1371 +/-103 08-15-06 -5514 <0.5 <10 <10 <15 1321 *166 09-05-06 -6077 <0.5 <10 <10 <15 1324*178 09-19-06 -6422 <0.5 <10 <10 <15 .1338+/-105 10-03-06 6731 < 0.5 <10 <10 i< 15 1352

• 153 10-17-06 -7395 ' < 0.5 <10 <10 < 15 1164t+150 11-02-06 1-7989 < 0.5 < 10 <10 < 15 1250 *:167 12-0406 -8702 < 0.5 <10 <10 < 15 1254 +/- 163 K-39 01-04-06 KMI - 50 < 0.5 <10 <10 < 15 1314

• 165 02-01-06 -504 < 0.5 <10 <10 < 15 1362 +/- 116 03-01-06 -1038 < 0.5 <10 <10 < 15 1259 t 179 04-04-06 -1995 <0.5 <10 <10 <15 1137t65 05-02-06 -2921 <0.5 <10 <10 <15 1122*170 05-16-06 -3305 < 0.5 <10 <10 < 15 1348 +/- 121 06-02-06 -3638 < 0.5 <10 <10 < 15 1258

• 140 06-20-06 -4084 < 0.5 <10 <10 < 15 1222 +/- 151 07-05-06 -4398 < 0.5 <10 <10 < 15 1158 +/- 164 07-18-06 -4822 < 0.5 <10 <10 < 15 1317 +/- 118 08-02-06 L5276 < 0.5 <10 <10 < 15 1346

• 108 08-15-06 -5515 < 0.5 <10 <.10 < 15 1454

• 117 09-05-06 -6078 < 0.5 < 10 <10 < 15 1387 +/- 105

.09-19-06 -6423 < 0.5 <10 <10 < 15 1287 +/- 175 10-03-06 -6732 < 0.5 <10 <10 < 15 1465 +/- 161 10-17-06 - 7396 < 0.5 <10 <10 < 15 1326 +/- 160 11-02-06 -7990 < 0.5 <10 <10 < 15 1226 *159 12-04-06 -8703 < 0.5 <10 <10 < 15 1383 +/- 172 46

KEWAUNEE Table 14. Milk, analyses for iodine-131 and gamma-emitting isotopes (continued).

Collection Lab Concentration (pCi/L)

Date Code 1-131 Cs-134 Cs-1 37 Ba-La-I 40 K-40 Control K-3 01-04-06 KMI -44 < 0.5 <10 <10 <15 1383 +/- 177 02-02-06 -498 < 0.5 <10 <10 <15 1354 +/- 91 .- a 03-02-06 -1032 < 0.5 <10 <10 <15 1530 +/- 177 04-04-06 -1989 <0.5 <10 -C10 <15 1344 +/- 109 05-02-06 -2915 <0.5 <10 <10 <15 1237 +/- 189 05-16-06 -3299 <0.5 <10 < 10 *< 15 1334 +/- 104-06-02-06 -3632 < 0.5 <10 < 10 <15 1268 +/- 183 06-20-06 -4078 < 0.5 <10 <10 <15 1448 +/- 194 07-06-06 -4392 < 0.5 <10 <10 <15 1305 +/- 174 07-18-06 -4816 < 0.5 <10 < 10 <15 1396 +/- 114 08-01-06 -5270 <0.5 <10 <10 <15 1329 +/- 119 08-15-06 -5509 <0.5 <10 <10 <15 1426 +/- 126 09-06-06 -6072 <0.5 <10 < 10, <15 1390 +/-167 09-19-06 -6417 < 0.5 <10 < 10 <15 1432 +/-143 10-03-06 -6726 < 0.5 <10 < 10 <15. 1411 +/- 167 10-17-06 -7390 < 0.5 <10 <10 <15 1351 +/- 166 11-02-06 -7984 <0.5 <10 <10 <15 1318 +/- 161 12-05-06 -8697 <0.5 <10 <10 <15 1349 +/- 128 K-28 01-04-06 KMI -47 < 0.5 <10 <10 <15 1306 +/- 181 02-02-06 -501 < 0.5 <10 < 10 <15 1347 +/- 99 03-02-06 -1035 <0.5 <10 <10 <15 1182 +/- 162 04-04-06 -1992 <0.5 <10 <10 <15 1224 +/- 192 05-02-06 -2918 <0.5 <10 < 10 <15 1284 +/- 169 05-16-06 -3302 < 0.5 <10 < 10 <15 1237 +/-121 06-02-06 -3635 < 0.5 <10 < 10, <15 1351 +/- 117 06-20-06 -4081 < 0.5 <10 <10 <15 1331 +/- 161 07-06-06 -4395 < 0.5 < 10 <10 <15 1340 +/- 114 07-18-06 -4819 <0.5 <10 <10 <15. 1361 +/- 118 08-02-06 - 5273 <0.5 <10 <10 <15 1348 +/- 120 08-15-06 -5512 <0.5 <10 < 10 < 15 1376 +/- 114 09-06-06 -6075 < 0.5 <10 <10 <15 1332 +/- 146 09-19-06 -6420 < 0.5 <10 < 10 <15 1278 +/- 107 10-03-06 -6729 < 0.5 <10 <10 <15 1377 +/- 119 10-17-06 -7393 <0.5 <10 <10 <15 1383 +/- 164 11-02-06 -7987 <0.5 <10 <10 <15 1384 +/- 118 12-05-06 -8700 <0.5 <10 <10 <15 1227 +/- 154 47

KEWAUNEE Table 15. Milk, analyses for strontium-89, strontium-90, stable potassium, stable calcium, and ratios of strontium-90 per gram of calcium and cesium-1 37 per gram of potassium.

Collection: Monthly composites.

Ratios Sr-90 Cs-137 Concentration per per Collection Lab Sr-89 Sr-90 K Ca gram gram Perod Code (pCi/L) (pCi/L) (gIL) (g/L) Ca K Indicators

.K-5 January KMI - 45 < 0.7 1.0 +/-0.4 1.61 +/- 0.19 1.18 0.85 <6.21 February -499 < 0.6 1.4 +/-0.4 1.63 +/- 0.12 1.03 1.36 <6.13 March -1033 < 0.7 0.9 +/-0.4 1.41 +/-0.27 1.18 0.76 <7.08 April -1990 <0.6 < 0.6 1.58+/-0.19 1.18 <0.51 <6.33 May -3315 < 0.7 < 0.8 1.52+/-0.13 1.08 <0.74 <6.59 June -4180 < 0.7 1.0 +/- 0.4 1.49+/-0.20 1.17 0.85 <6.72 July -4858 < 0.9 1.0 +/- 0.3 1.57+/-0.16 1.34 0.75 <6.37 August -5552 < 0.8 1.0 +/- 0.4 1.54+/-0.14 1.28 0.78 <6.48 September -6426 < 0.8 0.9 +/- 0.4 1.69+/-0.19 1.26 0.71 <5.93 October -7509 < 0.8 1.1 +/- 0.4 1.62+/-0.21 1.32 0.83 <6.17 November -7985 < 1.1 0.8 +/- 0.3 1.61 +/- 014 1.12 0.71 <6.20 December -8698 < 1.0 0.6 *+/-0.3 1.57 +/- 0.20 1.54 0.39 <6.38 K-25 January KMI - 46 < 0.6 1.3 +/-0.4 1.50 +/- 0.20 0.93 1.40 <6.66 February -500 < 0.6 1.4 +/- 0.4 1.50 +/-0.12 1.29 1.09 <6.67 March -1034 < 0.6 1.1 +/-0.4 1.22 +/-0.19 1.29 0.85 <8.23 April -1991 < 0.8 0.8 +/- 0.4 1.49 +/- 0.20 0.95 0.84 <6.72 May -3316 < 0.6 1.0 +/- 0.3 1.59+/-0.14 1.16 0.86 <6.29 June* -4181 < 0.5 09+/-0.3 1.54 +/-0.14 1.17 0.77 <6.50 July -4859 <0.7 0.8 +/-0.3 "1.53+/-0.16 1.13 0.71 <6.52 August' -5553 < 0.6 0.7 +/- 0.3 1.59 +/-0.14 1.20 0.58 <6.28 September -6427 < 0.6 0.5 +/- 0.3 1.59 +/-0.15 1.34 0.37 <6.27 October -7510 < 0.7 0.9 +/- 0.3 1.63 +/-0.20 1.25 0.72 <6.12 November -7986 < 0.9 1.2 +/- 0.3 1.60+/-0.13 1.20 1.00 <6.23 December -8699 < 0.8 1.3 +/-0.4 1.58 +/- 0.21 1.36 0.96 <6.34 48

KEWAUNEE Table 15. Milk, analyses for strontium-89, strontium-90, stable potassium, stable calcium, and ratios of strontium-90 per gram of calcium and cesium-1 37 per gram of potassium (continued).

Ratios Sr-90 Cs-1 37 Concentration per per Collection Lab Sr-89 Sr-90 K Ca gram gram Period Code (pCi/L) (pCVL) (9/1i) (g/L) Ca K Indicators K-34 January KMI - 48 < 0.7 0.9 +/- 0.3 1.72 + 0.13 0.93 0.97 < 5.81 February -502 < 0.6 0.6 +/- 0.3 1.61 +/- 0.12 1.17 0.51 < 6.21 March -1036 < 0.6 0.9 +/- 0.3 1.66 0.14 1.02 0.88 < 6.01 April - 1993 < 0.5 1.0 +/- 0.3 1.74 +/-.0.07 1.23 0.81 <5.75 May -3318 < 0.6 0.6 +/- 0.3 1.66-+/- 0.15 1.28 0.47 < 6.02 June -4183 < 0.6 0.7 +/- 0.3 1.59 +/- 0.14 0.96 0.73 < 6.R7 July -4861 < 0.7 1.4 +/- 0.4 1.57+/- 0.13 1.01 1.39 < 6.36 August - 5555 < 0.7 1.0 +/- 0.3 1.69 +/- 0.13 1.28 0.78 < 5.91 September -6429 < 0.7 1.1 +/- 0.4 1.63 +/- 0.17 1.14 0.96 < 6.12 October -7512 < 0,9 1.3 +/- 0.4 1.64 +/- 0.19 1.13 1.15 < 6.11 November -7988 < 0.9 1.1 +/-0.3 1.63 +/- 0.14 1.30 0.85 < 6.14 December -8701 < 0.8 1.0 +/-0.3 1.65 +/- 0.15 1.27 0.79 < 6.07 49

KEWAUNEE Table 15. Milk, analyses for strontium-89, strontium-90, stable potassium, stable calcium, and ratios of strontium-90 per gram of calcium and cesium-137 per gram of potassium (continued).

Ratios Sr-90 Cs-137 Concentration per per Collection Lab Sr-89 Sr-90 K Ca gram gram Period Code (pCI/L) (pCi/L) (g/L) (g/L) Ca K Indicators K-38 January KMI - 49 <0.7 0.9 +/-0.4 1.54 +0.12 1.02 0.88 < 6.49 February -503 < 0.6 1.5 +/- 0.4 1.50 +/-0.12 1.19 1.26 < 6.68 March -1037 < 0'6 1.5+/- 0.4 1.45 0.14 1.12 1.34 < 6.91 April - 1994 < 0.7 0.9+/- 0.5 1.42 + 0.20 1.05 0.86 < 7.06 May -3319 <0.6 1.0+/- 0.3 1.54 0.12 1.09 0.92 < 6.48 June -4184 <0.7 1.1 +/- 0.4 1.52 +/-0.13 1.17 0.94 < 6.60 July -4862 <1.0 < 0.8 1.56 10.17 073 < 1.10 < 6.41 August -5556 < 0.7 1.0 +/- 0.4 1.56 +/- 0.16 1.35 0.74 < 6.43 September -6430 < 0.8 0.6 +/- 0.3 1.54 +/- 0.16 1.16 0.52 < 6.50 October -7513 < 0.8 0.9 +/- 0.4 1.45 +/- 0.18 1.27 0.71 < 6.88 November -7989 < 1.1 1.2 +/- 0.4 1.45 +/- 0.19 1.20 1.00 < 6.92 December -8702 < 0.9 1.0 +/- 0.4 1.45 +/- 0.19 1.37 0.73 < 6.90 K-39 January KMI - 50 < 0.7 1.8 +/- 0.4 1.52 +/-0.19 1.01 1.78 < 6.58 February -504 < 0.7 0.8 +/- 0.3 1.57 +/- 0.13 1.09 0.73 < 6.35 March -1038 < 0.7 1.1 +/- 0.4 1.46 +/- 0.21 1.24 0.89 < 6.87 April - 1995 < 0.6 0.9 +/- 0.4 1.31 +/- 0.08 1.30 0.69 < 7.61 May -3320 < 0.8 0.7 +/- 0.4 1.43 +/- 0.17 1.16 0.60 < 7.00 June -4185 < 0.7 0.9 +/- 0.4 1.43 +/- 0.17 1.09 0.83 < 6.98 July -4863 < 0.9 0.9 +/- 0.4 1.43 +/- 0.16 0.92 0.98 < 6.99 August -5557 < 0.8 0.8 +/- 0.4 1.62 +/- 0.13 1.15 0.70 < 6.18 September -6431 < 0.6 0.9 +/- 0.3 1.55 +/- 0.16 1.36 0.66 < 6.47 October -7514 < 0.9 1.2 +/- 0.4 1.61 +/- 0.19 1.14 1.05 < 6.20 November -7990 < 1.1 0.8 +/- 0.3 1.42 +/- 0.18 1.19 0.67 < 7.06 December - 8703 < 0.9 0.9 +/- 0.3 1.60 +/- 0.20 1.34 0.67 < 6.25 50

KEWAUNEE Table 15. Milk, analyses for strontium-89, strontium-90, stable potassium, stable calcium, and ratios of strontium-90 per gram of calcium and cesium-1 37 per gram of potassium (continued).

Ratios Sr-90 Cs-I 37 Concentration per per Collection Lab Sr-89 Sr-90 K Ca gram gram Period Code (pCi/L) (pCi/L) (g/L) (g/L) Ca K Control K-3 January KMI - 44 < 0.8 1.2 +/- 0.5 1.60 +/- 0.20 1.10 1.09 < 6.25 February -498 < 0.6 0.7 +/- 0.3 1.57 +/- 0.11 0.98 0.71 < 6.39 March -1032 < 0.6 1.6 +/- 0.4 1.77 +/- 0.20 1.18 1.36 < 5.65 April -1989 < 0.6 0.9 +/- 0.4 1.55 0.13 1.28 0.70 < 6.44 May -3314 < 0.7 1.0 +/- 0.4 1.49 +/- 0.17 1.11 0.90 < 6.73 June -4179 < 0.6 1.3 +/- 0.4 1.57 +/- 0.22 1.05 1.24 < 6.37 July -4857 < 0.9 1.0 +/- 0.4 1.56 +/- 0.17 1.14 0.88 < 6.41 August - 5551 < 0.7 1.4 t 0.4 1.59 +/- 0.14 1.17 1.20 < 6.28 September -6424, 5 < 0.8 0.9 +/- 0.3 1.63 +/- 0.18 1.14 0.79 <6.13 October -7508 < 0.9 2.6 +/- 0.5 1.60 +/- 0.19 1.35 1.93 < 6.26 November -7984 < 1.1 1.4 +/- 0.4 1.52 +/- 0.19 1.20 1.17 < 6.56 December -8697 < 0.9 1.3 +/- 0.4 1.56 +/- 0.15 1.33 0.98 < 6.41 K-28 January KMI - 47 < 0.6 0.8 +/- 0.3 1.51 +/- 0.21 1.09 0.73 < 6.62 February -501 < 0.6 0.8 +/- 0.3 1.56 +/- 0.11 1.22 0.66 < 6.42 March -1035 < 0.6 1.1 +/- 0.3 1.37 +/- 0.19 1.06 1.04 < 7.32 April -1992 < 0.6 0.6 +/- 0.3 1.42 +/- 0.22 1.07 0.56 < 7.07 May -3317 < 0.7 1.2 +/- 0.4 1.46 +/- 0.17 1.19 1.01 <6.86 June -4182 < 0.5 0.6 +/- 0.3 1.55 +/- 0.16 1.14 0.53 < 6.45 July -4860 < 0.8 1.0 +/- 0.4 1.56 +/- 0.13 1.05 0.95 < 6.41 August -5554 < 0.7 1.1 +/- 0.4 1.57 +/- 0.14 1.31 0.84 < 6.35 September -6428 < 0.7 1.1 +/- 0.3 1.51 +/--0.15 1.09 1.01 < 6.63 October -7511 < 0.8 0.9 +/- 0.4 1.60 +/-0.16 1.30 0.69 < 6.27 November -7987 < 1.0 0.8 +/- 0.3 1.60 - 0.14 1.20 0.67 < 6.25 December -8700 < 0.8 1.0 +/- 0.3 1.42 -0.18 0.99 1.01 < 7.05 51

KEWAUNEE Table 16. Well water, analyses for gross alpha, gross beta, tritium, strontum-898, strontium-90a, potassium-40 and gamma-emitting isotopes.

Collection: Quarterly.

Sample Description and Concentration (pCiIL)

Indicator K-Ig Date Collected 01-03-06 04-03-06 07-05-06 10-02-06 Lab Code KWW-108 KWW-2246 KWW-4412 KWW-6772 Gross alpha < 1.9 2.5 1 1.8 < 2.2 < 2.8 Gross beta 2.6:* 0.9.. 3,0 +/- 1.4 3.6 +/- 1.5 2.3 +/- 1.5 H-3 < 152 < 158 < 139 < 182 Sr-89 < 0.6 < 0.6 *< 0.8 < 0.6 Sr-90 < 0.6 < 0.4 < 0.5 < 0.4 K-40 (ICP) 2.20 2.94 1.82 0.99 Mn-54 < 15. < 15 < 15 < 15 Fe-59 < 30 < 30 < 30 < 30 Co-58 ý< .15 < 15 <15 < 15 Co-60 <15 < 15 <15 < 15 Zn-65 < 30 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 < 15 <15 Cs-134 < 10 < 10 < 10 <10 Cs-137 <10 < 10 < 10 < 10 Ba-La-140 < 15 <15 < 15 <15 K-1_h Date Collected 01-03-06 04-03-06 07-05-06 10-02-06 Lab Code KWW-109 KWW-2247 KWW-4413 KWW-6773 Gross alpha 2.8 +/- 1.8 <2.1 <1.8 2.3

• 1.5 Gross beta 2.2 +/- 1.1 4.6 +/- 1.8 2.4 + 0.9 2.3 +/- 0.9 H-3 < 152 < 158 < 139 < 182 K-40 (ICP) 2.04 2.98 1.89 1.13 Mn-54 < 15 < 15 < 15 < 15 Fe-59 <30 < 30 < 30 <30 Co-58 < 15 < 15 < 15 < 15 Co-60 < 15 < 15 < 15 <15 Zn-65 < 30 < 30 < 30 < 30 Zr-Nb-95 <15 < 15 < 15 < 15 Cs-134 < 10 < 10 <10 < 10 Cs-137 < 10 < 10 < 10 < 10 Ba-La-140 < 15 <15 <15 <15 a Strontium analyses required on samples from K-i g only.

52

KEWAUNEE Table 17. Well water, analyses for gross beta, tritium, potassium-40, and gamma-emitting isotopes.

Collection: Quarterly.

Sample Description and Concentration (pCi/L)

Indicator K-I 0 Date Collected 01-03-06 04-03-06 07-05-06 10-02-06 Lab Code KWW-110 KWW-2248 KWW-4414 KWW-6774 Gross beta 2.9 1 2.0 5.0 +/- 2.1 2.8 +/- 1.5 < 1.5 H-3 < 152 < 158 < 139 < 182 K-40 (ICP) 2.53 3.08 1.38 1.49 Mn-54 <15 < 15 <15 < 15 Fe-59 <30 <30 < 30 < 30 Co-58 <15 < 15 <15 <15-Co-60 < 15 < 15 < 15 <15 Zn-65 < 30 < 30 <30 < 30 Zr-Nb-95 < 15 < 15 <15 < 15 Cs-134 < 10 < 10 < 10 < 10 Cs-137 < 10 < 10 < 10 < 10 Ba-La-140 < 15 < 15 <15 <15 K- 1_

Date Collected 01-03-06 04-03-06 07-05-06 10-02-06 Lab Code KWW-1 11 KWW-2249 KWW-4415 KWW-6775 Gross beta 1.5 +/- 0.6 1.4 +/- 0.4 1.0 + 0.2 0.9 t 0.2 H-3 < 152 < 158 < 139 < 182 K-40 (ICP) 0.67 0.87 0.75 0.64 Mn-54 < 15 <15 < 15 <15 Fe-59 < 30 < 30 < 30 < 30 Co-58 <15 < 15 <15 < 15 Co-60 <15 < 15 <15 < 15 Zn-65 < 30 < 30 < 30 <.30 Zr-Nb-95 <15 < 15 <15 < 15 Cs-134 < 10 < 10 < 10 <*10 Cs-1 37 < 10 < 10 < 10 < 10, Ba-La-1 40 <15 <15 < 15 < 15 53

KEWAUNEE Table 17. Well water, analyses for gross beta, tritium, potassium-40, and gamma-emitting Isotopes.

Sample Description and Concentration (pCi/L)

Indicator K-25 Date Collected 01-03-06 04-03-06 07-05-06 .10-02-06 Lab Code KWW-113 KWW-2251 KWW-4417 KWW-6777 Gross beta 1.8 +/- 0.6 1.8 +/- 0.4 1.0 +/- 0.2 0.7 +/- 0.2 H-3 < 152 < 158 < 141 < 182 K-40 (ICP) 0.74 1.12 0.86 0.73 Mn-54 < 15 <15 <15 < 15 Fe-59 < 30 < 30 < 30 < 30 Co-58 < 15 < 15 < 15 < 15 Co-60 < 15 <15 < 15 <15 Zn-65 <30 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 <15 < 15 Cs-134 < 10 < 10 < 10 < 10 Cs-137 < 10 < 10 < 10 < 10 Ba-La-140 < 15 <15 <15 <15 Control K-1 3 01-03-06 07-05-06 10-02-06 Date Collected 04-03-06 Lab Code KWW-112 KWW-2250 KWW-4416 KWW-6776 Gross beta 1.6 +/- 0.6 1.5 +/- 0.3 0.8 +/- 0.2 1.0 +/- 0.2 H-3 < 152 < 158 < 139 < 182 K-40 (ICP) 0.74 0.86 0.79 0.67 Mn-54 < 15 < 15 < 15 <15 Fe-59 < 30 < 30 < 30 < 30 Co-58 < 15 < 15 <15 < 15 Co-60 < 15 < 15 < 15 < 15 Zn-65 < 30 < 30 < 30 <.30 Zr-Nb-95 < 15 < 15 <15 < 15 Cs-134 < 10 < 10 < 10 <10 Cs-137 < 10 < 10 < 10 < 10 Ba-La-140 <15 < ý15 < 15 <15 Note: Pages 55 is Intentionally left out 54

KEWAUNEE Table 18. Domestic meat samples (chickens), analyses of flesh for gross alpha, gross beta, and gamma-emitting isotopes. Annual collection.

Sample Description and Concentration (pCI/g wet)

Indicator Control Location K-24 K-29 K-20 K-32 Date Collected 09-05-06 09-05-06 09-05-06 Lab Code KME-6055 KME-6056 KME-6057 Gross Alpha < 0.07 < 0.04 0.11 +/- 0.05 Gross Beta 3.37 +/- 0.14 3.17 +/- 0.10 2.97 +/- 0.12 Be-7 < 0.25 < 0.30 < 0.20 K-40 2.99 +/- 0.45 3.07 t 0.41 2.50 +/- 0.34 Nb-95 < 0.053 < 0.030 < 0.047 Zr-95 < 0.071 < 0.044 < 0.064 Ru-103 < 0.036 < 0.054 <0.042 Ru-106 < 0.18 < 0.11 < 0.10 Cs-134 < 0.018 < 0.017 < 0.016 Cs-137 < 0.021 < 0.011 < 0.014 Ce-141 < 0.067 < 0.076 < 0.11 Ce-144 < 0.10 < 0.079 < 0.095 56

KEWAUNEE Table 19. Eggs, analyses for gross beta, strontium-89, strontium-90 and gamma emitting Isotopes.

Collection: Quarterly Sample Description and- Concentration (pCi/g wet)

Location .I K-24 Date Collected 01-03-06 04-03-06 07-05-06 10-02-06 Lab Code KE-93 KE-1996 KE-4399, 400 KE-6791 Gross beta 1.76 +/- 0.06 1.91 + 0.08 1.85 +/- 0.04 1.88 +/- 0.09 Sr-89 < 0.004 < 0.008 < 0.007 < 0.009 Sr-90 < 0.004 < 0.003 < 0.003 < 0.003 Be-7 < 0.097 < 0.042 < 0.054 < 0.026 K-40 1.42 +/- 0.27 1.32 +/- 0.15 1.25 +/- 0.13 1.21 +/- 0.14 Nb-95 < 0.011 < 0.007 < 0.009 < 0.008 Zr-95 < 0.013 < 0.016 <'0.011 < 0.014 Ru-103 < 0.010 < 0.008 < 0.008 < 0.008 Ru-106 < 0.060 < 0.050 < 0.069 < 0.043 Cs-1 34 < 0.007 < 0.006 < 0.006 < 0.006 Cs-1 37 < 0.011 < 0.006 < 0.006 < 0.006 Ce-i 41 < 0.023 < 0.013 < 0.014 < 0.009 Ce-144 < 0.077 < 0.054 < 0.045 < 0.035 Location K-32 Date Collected 01-03-06 04-03-06 07-05-06 10-02-06 Lab Code KE-94 KE-1997, 8 KE-4401 KE-6792 Gross beta 1.31 +/- 0.04 1.85 +/- 0.05 1.69 +/- 0.05 1.64 +/- 0.08 Sr-89 < 0.003 < 0.006 < 0.009 < 0.010 Sr-90 0.003 +/- 0.001 < 0.003 < 0.003 < 0.003 Be-7 < 0.051 < 0.047 < 0.088 < 0.049 K-40 1.27 +/- 0.17 1.26 +/- 0.13 1.32 +/- 0.22 1.11 +/- 0.15 Nb-95 < 0.003 < 0.004 < 0.008 < 0.004 Zr-95 < 0.018 < 0.010 < 0.017 < 0.013 Ru-103 < 0.005 < 0.005 < 0.011 < 0.007 Ru-106 < 0.063 < 0.034 < 0.078 < 0.036 Cs-1 34 < 0.005 < 0.005 < 0.007 < 0.005 Cs-137 < 0.007 < 0.005 < 0.011 < 0.007 Ce-141 < 0.012 < 0.009 < 0.017 < 0.011 Ce-144 < 0.049 < 0.039 < 0.058 < 0.030 57

KEWAUNEE Table 20. Vegetable and grain samples, analyses for gross beta, strontium-89, strontium-90, and gamma-emitting isotopes. Annual collection.

Sample Description and Concentration (pCl/g wet)

Indicator Location K-23 K-34 K-38 Date Collected 08-01-06 08-01-06 10-02-06 10-02-06 Lab Code KVE-5286, 7 KVE-5288 KVE-6928 KVE-6929 Type Oats Clover Pumpkin Pumpkin Gross beta 9.52 + 0.20 6.56 1 0.26 4.74 +/- 0.10 5.15 +/- 0.12 Sr-89 < 0.017 < 0.013 < 0.009 < 0.006 Sr-90 < 0.006 < 0.004 < 0.003 < 0.002 Be-7 1.27

• 0.18 1.30 t 0.23 < 0.084 < 0.11 K-40 6.38 1 0.47 4.03 +/- 0.45 2.36 t 0.23 2.87 +/- 0.33 Nb-95 < 0.021 < 0.018 < 0.014 < 0.014 Zr-95 < 0.030 < 0.017 < 0.025 < 0.023 Ru-103 < 0.010 < 0.012 < 0.011 < 0.008 Ru-106 < 0.18 < 0.11 < 0.089 < 0.047 Cs-134 < 0.016 < 0.017 < 0.006 < 0.011 Cs-137 < 0.017 < 0.011 < 0.010 < 0.008 Ce-141 < 0.049 < 0.031 < 0.027 < 0.026 Ce-144 < 0.11 < 0.083 < 0.079 < 0.10 Location K-26 (control)

Date Collected 09-06-06 09-06-06 09-06-06 09-06-06 Lab Code KVE-6079 KVE-6080 KVE-6081 KVE-6082 Type Cabbage Zucchini Kohlrabi Corn Gross beta 2.09 +/- 0.04 2.05 +/- 0.04 2.72 +/- 0.05 3.50 +/- 0.06 Sr-89 < 0.002 < 0.003 < 0.003 < 0.005 Sr-90 < 0.001 < 0.001 < 0.002 < 0.003 Be-7 < 0.090 < 0.047 < 0.049 < 0.056 K-40 1.44 +/- 0.22 1.39 + 0.19 2.41 +/- 0.10 2.29 +/- 0.21 Nb-95 < 0.010 < 0.008 < 0.010 < 0.006 Zr-95 < 0.022 < 0.014 < 0.012 < 0.016 Ru-103 < 0.010 < 0.007 < 0.009 < 0.007 Ru-106 < 0.099 < 0.066 < 0.042 < 0.045 Cs-134 < 0.011 < 0.006 < 0.003 < 0.003 Cs-137 < 0.012 < 0.007 < 0.003 < 0.007 Ce-141 < 0.025 < 0.011 < 0.021 < 0.010 Ce-144 < 0.072 < 0.045 < 0.030 < 0.032

' Not required by Technical Specifications.

58

KEWAUNEE Table 20. Vegetable and grain samples, analyses for gross beta, strontium-89, strontium-90, and gamma-emitting Isotopes (continued).

Sample Description and Concentration (pCi/g wet)

Location K-26 (control)

Date Collected 09-06-06 10-02-06 Lab Code KVE-6083 KVE,6927 Type Cucumber Pumpkin Gross beta 1.82-+/- 0.03 2.52 +/- 0.07 Sr-89 < 0.001 < 0.004 Sr-90 < 0.001 < 0.001 Be-7 < 0.064 < 0.092 K-40 .1.16 +/- 0.18 1.78 +/- 0.17 Nb-95 < 0.008 < 0.003 Zr-95 < 0.016 < 0.014 Ru-103  :< 0.005 < 0.010 Ru-106 < 0.052 .< 0.059 Cs-134 < 0.004 < 0.006 Cs-1 37 < 0.007 S< 0.006 Ce-141 S< 0.009 < 0.020 Ce-144 S< 0.055 < 0.047 59

KEWAUNEE Table 21. Cattlefeed, analyses for gross beta, strontium-89, strontium-90, and gamma-emitting isotopes.

Collection: First Quarter.

Sample Description and Concentration (pClig wet)

Control Location K-3 K-3 Date Collected 01-04-06 01-04-06 Lab Code KCF-179 KCF-185 Type Hay .Silage Gross beta 14.67

• 0.29 6.06 +/- 0.14 Sr-89 < 0.012 < 0.014 Sr-90 0.011 +/- 0.004 < 0.006 Be-7 0.37 +/- 0.16 0.62 +/- 0.29 K-40 10.66 +/- 0.68 4.27 +/- 0.62 Nb-95 < 0.024 < 0.020 Zr-95 < 0.039 < 0.041 Ru-103 < 0.018 < 0.016 Ru-1 06 < 0.15 < 0.23 Cs-134 < 0.010 < 0.017 Cs-137 < 0.014 < 0.019 Ce-1 41 < 0.036 < 0.050 Ce-144 < 0.13 <0.16 Indicator Location K-5 K-5 K-25 K-25 Date Collected 01-03-06 01-03-06 01-03-06 01-03-06, Lab Code KCF-180 KCF-186 KCF-'181 KCF-187 Type Hay Silage Hay Silage Gross beta 34.16 +/- 0.66 12.28 +/- 0.25 14.83 +/- 0.36 6.92 +/- 0.17 Sr-89 < 0.026 < 0.011 < 0.017 < 0.010 Sr-90 0.023 +/- 0.010 0.008 +/- 0.003 0.014 +/- 0.006 < 0.006 Be-7 < 0.31 < 0,15 < 0.39 < 0.19,,

K-40 21.69 +/- 0.97 8.84 +/- 0.59 10.58 +/- 0.59 5.14 +/- 0.60 Nb-95 < 0.047 < 0.021 < 0.041 < 0.035 Zr-95 < 0.052 < 0.021 < 0.029 < 0.038 Ru-103 < 0.041 < 0.013 < 0.034 < 0.021 Ru-1 06 < 0.18 < 0.093 < 0.20 < 0.19 Cs-134 < 0.037 < 0.016 < 0.045 < 0.018 Cs-137 < 0.030 < 0.016 < 0.021 < 0.021 Ce-141 < 0.067 < 0.027 < 0.082 < 0.020 Ce-144 < 0.14 < 0.14 <0.12 < 0.094 60

-KEWAUNEE Table 21. CattSefeed, analyses for gross beta, strontium-89, strontium-90, and gamma-emitting Isotopes (continued).

Sample Description and Concentration (pCilg wet)

Indicator Location K-34 K-34 K-38 K-38 Date Collected 01-03-06 01-03-06 01-03-06 01-03-06 Lab Code KCF-182 KCF-188 KCF-183 KCF-189 Type Hay Silage Hay Silage Gross beta 22.12 + 0.55 20.96 +/- 0.42 14.68 +/- 0.34 5.25 +/- 0.15 Sr-89 < 0.032 < 0.019 < 0.016 < 0.015 Sr-90 0.020

• 0.009 0.015 + 0.005 0.015 +/- 0.005 < 0.009 Be-7 < 0.28 < 0.24 < 0.27 0.42 +/- 0.25 K-40 15.13

• 0.82 16.15 + 1.26 14.70 +/- 0.91 3.84 +/- 0.56 Nb-95 < 0.036 < 0.044 < 0.033 < 0.027 Zr-95 < 0.037 < 0.043 < 0.033 < 0.053 Ru-103 < 0.028 < 0.038 < 0.028 < 0.025 Ru-106 < 0.13 < 0.25 <0.21 < 0.18 Cs-134 < 0.022 < 0.039 < 0.021 < 0.022 Cs-137 < 0.025 < 0.029 *< 0.027 < 0.022 Ce-141 < 0.05 < 0.053 < 0.044 < 0.031 Ce-144 < 0.21 < 0.14 < 0.14 < 0.15 Location _.. K-39. K-39 Date Collected 01-03-06 01-03-06 Lab Code KCF-184 KCF-190 Type Hay Silage Gross beta 17.95 + 0.44 8.45 +/- 0.20 Sr-89 < 0.027 < 0.013 Sr-90 0.013 0.006 +/- 0.003 Be-7 < 0.29 0.31 +/- 0.17 K-40 12.35

• 0.90 6.26 +/- 0.46 Nb-95 < 0.042 < 0.020 Zr-95 < 0.070 < 0.029 Ru-103 "< 0.040 < 0.011 Ru-106 < 0.20 < 0.10 Cs-1 34 < 0.036 < 0.011 Cs-137 < 0.030 < 0.014 Ce-141 < 0.043 < 0.019 Ce-144 < 0.24 < 0.074 61

KEWAUNEE Table 22. Grass, analyses for gross beta, strontium-89, strontium-90, and gamma-emitting isotopes.

Collection: Quarterly, April through December Units: pCi/g wet

.Sample Description and Concentration Indicator Location K-i b K-lf K-5 K-25 Date Collected 05-01-06 05-01-06 05-01-06 05-01-06 Lab Code KG-3024 KG-3025 KG-3027 KG-3028 ""

Gross beta 6.07 - 0.16 7.19 +/- 0.14 7.79 +/- 0.16 7.85 +/- 0.18 Sr-89 < 0.005 < 0.003. < 0.004 < 0.005 Sr-90 < 0.004 < 0.002 < 0.002 < 0.004 Be-7 3.40

• 0.42 0.57 +/- 0.23 1.60 +/- 0.25 1.57 +/- 0.30 K-40 4.82

• 0.54 5.62 +/- 0.45 6.30 +/- 0.61 6.55 +/- 0.69 Mn-54 < 0.020 < 0.012 < 0.020 < 0.015 -*

Co-58 < 0.014 < 0.008 < 0.020 < 0.021 Co-60 < 0.027 < 0.014 < 0.017 < 0.023 Nb-95 < 0.029 < 0.018 < 0.021 < 0.013- -

Zr-95 < 0.041 < 0.036 < 0.023 < 0.022 Ru-103 < 0.034 < 0.016 <0.016 < 0.015 Ru-106 <0.15 <0.13 <0.17 <0.15 Cs-134 < 0.022 < 0.017 < 0.016 < 0.023 Cs-137 < 0.026 < 0.021 < 0.012 < 0.017 Ce-1 41 < 0.051 < 0.045 < 0.034 < 0.046 Ce-144 < 0.24 <0.13 < 013 <0.16 -*

Indicator Control Location K-34 K-38 K-39 , K-3 Date Collected 05-01-06 05-01-06 05-01-06 05-01-06 Lab Code KG-3029 KG-3030 KG-3031 KG-3026 Gross beta 8.61 : 0.18 8.02 +/- 0.17 4.72 +/- 0.11 10.36 +/- 0.22 Sr-89 <0.005 < 0.007 < 0.003 < 0.006 Sr-90 <0.003 < 0.004 < 0.002 < 0.003 Be-7 1.26 t 0.16 1.41 +/- 0.27 1.91 +/- 0.20 5.99 +/- 0.34 K-40 6.82 t 0.45 5.81 +/- 0.54 3.60 +/- 0.39 5.68 +/- 0.44 Mn-54 < 0.012 < 0.016 < 0.010 <0.010 Co-58 < 0.009 < 0.009 < 0.009 < 0.008 Co-60 < 0.013 < 0.014 <0.012 < 0.009 Nb-95 < 0.009 < 0.008 < 0.007 < 0.013 Zr-95 < 0.030 < 0.019 < 0.012 < 0.033 Ru-103 < 0.009 < 0.017 < 0.010 < 0.011 Ru-106 < 0.086 <0.11 < 0.095 <0.10 Cs-134 < 0.012 < 0.019 < 0.008 < 0.012:

Cs-137 < 0.008 < 0.009 < 0.012 < 0.00 Ce-141 < 0.016 < 0.031 < 0.018 < 0.025 Ce-144 < 0.085 <0.11 < 0.083 < 0.072 62

KEWAUNEE Table 22. Grass samples, analyses for gross beta, strontium-89, strontium-90, and gamma-emitting isotopes (continued).

Sample Description and Concentration Indicator Location K-I b K-If K-5 K-25 Date Collected 07-05-06' 07-05-06 07-05-06 07-05-06 Lab Code KG-4418 KG-4419 KG-4422 KG-4423 Gross beta 8.80

• 0.25 7.84 +/- 0.22 6.03 +/- 0.14 9.26 +/- 0.22 Sr-89 < 0.014 < 0.024, < 0.013 < 0.020 Sr-90 < 0.008 < 0.013 < 0.007 < 0.012 Be-7 1.57 +0.29 0.80 +/- 0.37 1.66 +/- 0.40 2.39 +/- 0.21 K-40 6.80 + 0.55. 6.39 +/- 0.57 5.86 +/- 0.70 6.90 +/- 0.37 Mn-54 < 0.021 < 0.026 < 0.013 < 0.011 Co-58 < 0.021 < 0.020 < 0.029 < 0.012 Co-60 < 0.016 < 0.015 < 0.011 < 0.012 Nb-95 < 0.018 < 0.030 < 0.037 < 0.018 Zr-95 < 0.040 < 0.022 < 0.048 <0.019 Ru-1 03 < 0.019 < 0.014 < 0.032 <0.011 Ru-106 < 0.16 < 0.20 <0.17 <0.15 Cs-134 < 0.016- < 0.017 < 0.027 < 0.012 Cs-137 < 0.016 < 0.024 < 0.034 <0.015 Ce-141 < 0.027 < 0.047. < 0.029 < 0.029 Ce-144 < 0.092 < 0.22 <0.17 < 0.096 Indicator Control Location K-34 K-38 K-39 K-3 Date Collected 07-05-06 07-05-06. 07-05-06 07-05-06 Lab Code KG-4424 KG-4425 KG-4426 KG-4420, 1 Gross beta 8.05 +/- 0.18 6.29 +/- 0.15 8.40 +/- 0.19 13.57 +/- 0.28 Sr-89 < 0.020 < 0.013 < 0.012 < 0.007 Sr-90 < 0.009 < 01008 < 0.007 < 0.004 Be-7 1.58 +/- 0.50 1.09 +/- 0.12 1.20 +/- 0.27 0.72 +/- 0.12 K-40 5.87 +/- 0.91 4.52 +/- 0.26 6.50 +/- 0.59 10.01 +/- 0.47 Mn-54 < 0.030 < 0.007 < 0.025 < 0.011 Co-58 < 0.040 < 0.006 < 0.012 < 0.008 Co-60 < 0.027 < 0.006 < 0.019 < 0.009 Nb-95 < 0.043 < 0.007 < 0.021 < 0.015 Zr-95 < 0.078 < 0.016 < 0033 < 0.027 Ru-1 03 < 0.043 < 0.005 < 0.021 < 0.008 Ru-106 <0.25 < 0.067 < 0.20 < 0.061 Cs-134 < 0.032 < 0.006 < 0.026 < 0.016 Cs-137 < 0.040 < 0.009 < 0.021 <0.015

.Ce-I 41 <0.10 < 0.011 < 0.055 < 0.015 Ce-144 < 0.34 < 0.062 <0.19 < 0.061 63

KEWAUNEE Table 22. Grass samples, analyses for gross beta, strontlum-89, strontium-90, and gamma-emitting Isotopes (continued).

Sample Description and Concentration (pCl~g wet)

Indicator Location K-lb K-If K-5 K-25 Date Collected 10-02-06 10-02-06 10-02-06 10-02-06 Lab Code KG-6793 KG-6794 KG-6796 KG-6797, 8 Gross beta 9.16 +/- 0.27 6.16 +/- 0.18 11.46 +/- 0.41 6.97 +/- 0.18 Sr-89 < 0.016 < 0.006 < 0.015 < 0.016 Sr-90 < 0.006 < 0.003 < 0.005 < 0.005 Be-7 7.27 +/- 0.57 3.25 +/- 0.24. 6.03 t0.37 4.63 +/- 0.26 K-40 5.32 +/- 0.61 4.81 +/- 0.36 7.47 +/- 0.50 4.88 +/- 0.29 Mn-54 < 0.014 < 0.010 < 0.016 < 0.012 Co-58 < 0.013 < 0.014 <0.017 < 0.010 Co-60 < 0.024 < 0.010 < 0.014 < 0.011 Nb-95 < 0.026 < 0.019 < 0.024 < 0.011 Zr-95 < 0.049 < 0.032 < 0. 033 < 0.030 Ru-103 < 0.023 < 0.013 < 0.015 < 0.016 Ru-106 <0.17 <0.11 <0.11 <0.13 Cs-134 < 0.020 <0.010 < 0.013 < 0.013 Cs-137 < 0.020 <0.013 < 0.021 < 0.013 Ce-141 < 0.043 < 0.020 < 0.040 < 0.032 Ce-144 <0.13 < 0.062 <0.12 <0.11 Indicator Control Location K-34 K-38 K-39 K-3 Date Collected 10-02-06 10-02-06 10-02-06 10-02-06 Lab Code KG-6799 KG-6800 KG-6801 KG-6795 Gross beta 11.25 +/- 0.38 6.97 +/- 0.24 6.82 +/- 0.23 10.24 +/- 0.31 Sr-89 < 0.021 < 0.014 < 0.009 <0.008 Sr-90 < 0.004 .< 0.003 0.007 +/- 0.003 0.008 +/- 0.003 Be-7 6.08 +/- 0.39 2.86 +/- 0.32 5.27 +/- 0.43 3.88 +/- 0.32 K-40 6.56 +/- 0.50 6.04 +/- 0.43 ..%8.27+/- 0.58 7.53 +/- 0.51 __O Mn-54 < 0.020 < 0.014 <0.016 < 0.015 Co-58 < 0.017 < 0.020 < 0.014 < 0.015 Co-60 < 0.013 < 0.019 < 0.021 < 0.013 Nb-95 < 0.029 < 0.014 < 0.018 < 0.015 Zr-95 < 0.021 < 0.020 < 0.031 < 0.036 Ru-103 < 0.016 < 0.025 < 0.022 < 0.013 Ru-106 <0.13 <0.14 < 0.20 <0.10 Cs-134 < 0.018 < 0.014 < 0.017 < 0.011 Cs-137 < 0.021 < 0.016 < 0.026 < 0.014 Ce-1 41 < 0.035 < 0.049 < 0.055 < 0.032 Ce-144 <0.12 <0.16 <0.14 <0.12 64

KEWAUNEE Table 23. Soil samples, analyses for gross alpha, gross beta, strontium-89, strontium-90, and gamma-emitting Isotopes.

Collection: Semiannually Sample Description and Concentration (pCi/g dry)

Indicator Location -K-If . K-5 K-25 Date Collected 05-01-06 05-01-06 05-01-06 Lab Code KSO-3044 KSO-3046 KSO-3047 Gross alpha 6.75

• 2.69 9.14 +/- 3.32 5.06 +/- 2.50 Gross beta 21.91

• 2.69 29.26 +/- 3.17 33.20 +/- 3.07 Sr-89 < 0.026 < 0.037 < 0.042 Sr-90 < 0.017 < 0.027 0.047 +/- 0.017 Be-7 < 0.21 < 0.27 < 0.37 K-40 14.87 +/- 0.79 21.47 +/- 1.03 20.98 +/- 0.72 Nb-95 < 0.017 < 0.034 < 0.021 Zr-95 < 0.032 < 0.050 < 0.028 Ru-103 < 0.013 < 0.024 < 0.017 Ru-1 06, <0.10 < 0.11 < 0.14 Cs-134 < 0.031 < 0.041 < 0.026 Cs-137 < 0.021 0.078 +/- 0.035 0.19 +/- 0.033 Ce-141 < 0.041 < 0.037 < 0.033 Ce-144 < 0.11 < 0.15 < 0.12 Location K-If K-5 K-25 Date Collected S1-02-06 10-02-06 10-02-06 Lab Code KSO-6802 KSO-6804 KSO-6805 Gross alpha 10.45

• 3.23 . 11.31 :13.23 8.07 +/- 3.00 Gross beta 31.13

• 2.87 37.42 +/- 2.87 35.26 +/- 3.06 Sr-89 < 0.057 < 0.068 < 0.057 Sr-90 < 0.019 < 0.025 < 0.017 Be-7 < 0.21 < 0.22 < 0.26 K-40 18.58 +/- 0.90 22.68 +/- 1.02 21.55 +/- 0.94 Nb-95 < 0.018 < 0.036 < 0.023 Zr-95 < 0.018 < 0.054 < 0.038 Ru-f 03 < 0.031 < 0.027 < 0.022 Ru-106 < 0.090 < 0.21 < 0.15 Cs-1 34. < 0.019 < 0.026 < 0.018 Cs-137 < 0.026 0.080 +/- 0.035 0.12 +/- 0.028 Ce'141 < 0.053 < 0.043 < 0.051 Ce-144 < 0.16 . < 0.12 < 0.14 65

KEWAUNEE Table 23. Soil samples, analyses for gross alpha, gross beta, strontium-89, strontium-90, and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCi/g dry)

Indicator Location K-34 K-38 K-39 Date Collected 05-01-06 05-01-06 05-01-06 Lab Code KSO-3048 KSO-3049 KSO-3050 Gross alpha 5.49 +/- 2.50 10.45 +/- 3.86 8.45 +/- 3.44 Gross beta 30.37 +/- 3.07 34.01 +/- 3.74 25.03 +/- 3.25 Sr-89 < 0.040 < 0.044 < 0.038 Sr-90

• 0.073 0.020 0.089 + 0.022 0.038 +/- 0.014 Be-7 0.41 + 0.16 < 0.31 < 0.24 K-40 19.78 +/- 0.66 22.59+/- 1.07 17.57 +/- 0.84 Nb-95 < 0.020 < 0.035 < 0.028 Zr-95 < 0.029 < 0.057 < 0.048 Ru-103 < 0.017 < 0.027 < 0.027 Ru-106 < 0.17 < 0.16 < 0.16 Cs-134 < 0.023 < 0.041 < 0.034 Cs-137 0.13 0.026 0.22 +/-,0.044 0.10 +/- 0.036 Ce-141 < 0.037 < 0.041 < 0.050 Ce-144 < 0.17 < 0.17 < 0.17 Location K-34 K-38 K-39 Date Collected 10-02-06 10-02-06 10-02-06 Lab Code KSO-6806 KSO-6807 KSO-6808 Gross alpha 10.15 +/- 2.19 9.45 +/- 3.02 6.97 +/- 3.23 Gross beta 32.98 +/- 2.05 40.02 +/- 2.82 27.67 +/- 3.11 Sr-89 < 0.071 < 0.063 < 0.068 Sr-90 0.033 +/- 0.015 0.040 +/- 0.014 < 0.020 Be-7 0.80 +/- 0.25 < 0.28 < 0.20 K-40 20.21 +/- 0.97 23.79 +/- 1.08 19.11 +/- 0.88 Nb-95 < 0.026 < 0.021 < 0.018 Zr-95 < 0.033 < 0.042 < 0.049 Ru-1 03 < 0.017 < 0.024 < 0.028 Ru-106 < 0.14 < 0.11 < 0.18 Cs-134 < 0.018 < 0.026 < 0.016 Cs-137 0.13 +/- 0.037 0.25 +/- 0.044 0.14 +/- 0.026 Ce-141 < 0.042 < 0.028 < 0.052 Ce-144 < 0.13 < 0.16 < 0.16 66

KEWAUNEE Table 23. Soil samples, analyses for gross alpha, gross beta, strontium-89, strontium-90, and gamma-emitting Isotopes (continued).

Sample Description and Concentration (pCi/g dry)

Control Location K-3 Date Collected 05-01-06 10-02-06 Lab Code KSo-3045 KSO-6803 Gross alpha 11.04 + 3.42 11.77 +/- 2.44 Gross beta 30.62 + 3.10 32.95 + 2.32

• Sr-89 < 0.055 < 0.076 Sr-90 0.042 +/- 0.020 0.034 +/- 0.014 Be-7 <0.17 < 0.23 K-40 19.35 + 0.67 20.08 + 1.01 Nb-95 < 0.021 < 0.022 Zr-95 < 0.016 < 0.031 Ru-103 <,0.018 < 0.025 Ru-106 < 0:13 < 0.19 Cs-134 < 0.027 < 0.020 Cs-137 0.18 :0.029 0.19 + 0.033 Ce-141 <0.032 < 0.028 Ce-144 <0.096 < 0.16 67

KEWAUNEE Table 24. Surface water samples, analyses for gross beta, potassium-40 and gamma-emitting isotopes.

Collection: Monthly Sample Description and Concentration (pCi/L)

Indicator K-1 a Date Collected 01-03-06 02-01-06 03-01-06 Lab Code KSW-95 KSW-508 KSW-1061 _a Gross beta Suspended Solids <0.5 < 0.4 < 0.4 Dissolved Solids 13.0 +/- 1.3 6.3 +/- 0.8 2.9

• 0.3 Total Residue 13.0 t 1.3 6.3 + 0.8 2.9 + 0.3 K-40 (ICP) 7.36 4.55 6.38 Mn-54 < 15 <15 <15 Fe-59 < 30 < 30 <30 Co-58 < 15 < 15 <15 Co-60 <15 <15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 <15 Cs-134 < 10 <10 <10 Cs-137 <10 <10 <10 Ba-La-140 < 15 <15 <15 K-I b Date Collected 01-03-06 02-01-06 03-01-06 Lab Code KSW-96 KSW-509 KSW-1062 Gross beta Suspended Solids < 0.4 < 0.4 < 0.4 Dissolved Solids 5.5 +/- 0.8 3.9 +/- 0.5 2.3 +/- 0.5 Total Residue 5.5 +/- 0.8 3.9 +/- 0.5 2.3 + 0.5 K-40 (ICP) 2.99 1.93 1.94 Mn-54 < 15 < 15 <15 Fe-59 < 30 < 30 < 30 Co-58 <15 < 15 <15 Co-60 < 15 <15 <15 Zn-65 <30 <30 <30 Zr-Nb-95 < 15 < 15 < 15 Cs-1 34 < 10 <10 <10 Cs-137 <10 <10 <10 Ba-La-140 <15 < 15 <15 68

KEWAUNEE Table 24. Surface water samples, analysesfor gross beta, potassium-40, and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCi/L)

Indicator K-1_a Date Collected 04-03-06 05-01-06 06-01-06 Lab Code KSW-2028 KSW-2923 KSW-3689 Gross beta Suspended Solids < 0.4 < 0.4 < 0.4 Dissolved Solids 8.6 + 0.9 14.4 +/- 1.1 8.1 0.8 Total Residue 8.6 f10.9 14.4 +/- 1.1 8.1 +/-0.8 K-40 (ICP) 8.E58 10.90 5.14 Mn-54 < 15 <15 <15 Fe-59 < 30 < 30 <30 Co-58 < 15 <15 <15 Co-60 < 15 < 15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 '<15 <15 <15 Cs-134 <10 <10 < 10 Cs-137 < 10 <10 <10 Ba-La-140 <15 <15 <15 K-1lb Date Collected 04-03-06 05-;01-06 06-01-06 Lab Code' KSW-2029 KSW-2924 KSW-3690 Gross beta

-< 0.4 < 0.3 Suspended Solids < 0.3

, Dissolved Solids 3.6:1t 0.5' 3.7 + 0.6 3.6 +/- 0.5 Total Residue 3.6 +/- 0.5 3.7 +/- 0.6 3.6 +/- 0.5 K-40 (ICP) 3.47 2:40 1.90 Mn-54 < 15 <15 <15 Fe-59 < 30 < 30 < 30 Co-58 < 15 <15 <15 Co-60 < 15 <15 <15 Zn-65 < 30 < 30 < 30

< 15 Zr-Nb-95 <15 <15 Cs-134 < 10 <10 <10 Cs-137 < 10 <10 <10 Ba-La-140 < 15 < 15 <15 69

KEWAUNEE Table 24. Surface water samples, analyses for gross beta, potassium-40, and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCi/L)

Indicator K-i a Date Collected 07-05-06 08-01-06 09-05-06 Lab Code KSW-4403 KSW-5277, KSW-6087 Gross beta Suspended Solids <0.3 < 0.4 . <1.5 Dissolved Solids 6.5 +/- 0.8 4.8 +/- 0.7 17.7 +/- 1.2.

Total Residue 6.5 +/- 0.8 4.8 + 0.7 17.7+/- 1.2

• K-40 (ICP) 3.88 41.20 13.75 Mn-54 <.15 <15 <15 Fe-59 <30 <30 < 30 Co-58 < 15 <15 <15 Co-60 <15 <15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 <15 <15 <15 Cs-134 < 10 <10 <10 Cs-137 < 10 <10 < 10 Ba-La-140 < 15 <15 <15 K-1 b Date Collected 07-05-06 08-01-06 09-05-06.

Lab Code KSW-4404 KSW-5278 KSW-6088 Gross beta Suspended Solids < 0.4 < 0.3 < 0.4 Dissolved Solids 2.9 +/- 0.5 3.0 + 0.5 3.7 +/- 0.4 Total Residue 2.9 +/- 0.5 3.0 0.5 3.7 +/- 0.4 K-40 (ICP) 1.46 2.27 2.23 Mn-54 < 15 <15 <15 Fe-59 < 30 < 30 < 30 Co-58 -<15 <15 <15 Co-60 < 15 <15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 <15 < 15 <15 Cs-134 < 10 < 10 < 10 Cs-137 <10 <10 <10 Ba-La-1 40 <15 < 15 <15 70

KEWAUNEE Table 24. Surface water samples, analyses for gross beta, potassium-40, and gamma-emitting:

isotopes (continued).

Sample Description and Concentration (pCI/L)

Indicator K-Ia Date Collected 10-02-06 11-01-06 12-04-06 Lab Code KSW-6763 KSW-8004 KSW-8689 Gross beta Suspended Solids <0.4 < 0.4 < 0.4 Dissolved Solids 9.9 +/- 0.9 15.5

• 1.2 13.3 +/- 1.1 Total Residue 9.9 1 0.9 15.5

• 1.2 13.3 +/- 1.1 K-40 (ICP) 8.05* 13.84 12.63

< 15 <15 Mn-54 <15 Fe-59 < 30 <30 < 30 Co-58 <15 <15 <15 Co-60 < 15 '< 15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 <15 < 15 <15 Cs-1 34 <10 < 10 < 10 Cs-137 <10 S< 10 < 10 Ba-La-140 <15 <15 <15 K-I b Date Collected 10-02-06 11-01-06 12-04-06 Lab Code- KSW-6764 KSW-8005 KSW-8690 Gross beta k0.4 Suspended Solids <0.3 < 0.3 Dissolved Sblids 3.5 3.6 +/- 0.6 2.9 +/- 0.5 Total Residue 3.5*+/- 0.5 3.6 + 0.6 2.9 +/- 0.5 K-40 (ICP) 2.15 3.08 2.55 Mn-54 < 15 < 15 <15 Fe-59 < 30 < 30 <30 Co-58 < 15 < 15 <15 Co-60 < 15 <15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 <15 Cs-134 <10 <10 <10 Cs-137 <10 '< 10 <10

'<15 <15 Ba-La-1 40 <115 71

KEWAUNEE Table 24. Surface water samples, analysesrfor gross beta, potassium-40 and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCiIL)

Indicator K-id Date Collected 01-03-06 02-01-06 03-01-06 Lab Code KSW-97 KSW-510 KSW-1063 Gross beta Suspended Solids < 0.4 < 0.4 < 0.4 Dissolved Solids 2.7 + 0.5 1.8 ;t 0.3 1.5 +/- 0.1 Total Residue 2.7 + 0.5 1.8 t 0.3 1.5 +/- 0.1 K-40 (ICP) 0.97 1.09 1.30 Mn-54 < 15 < 15 <15 Fe-59 < 30 < 30 < 30 Co-58 < 15 .< 15 <15 Co-60 <15 <15 <15 Zn-65 < 30 <30 < 30 Zr-Nb-95 <15 <15 <15 Cs-134 <10 <10 <10 Cs-137 < 10 <10 <10 Ba-La-1 40 < 15 < 15 <15 K-i e Date Collected 01-03-06 02-01-06 03-01-06 Lab Code KSW-98 KSW-511 KSW-1064 Gross beta Suspended Solids < 0.4 <.0.4 < 0.4 Dissolved Solids 5.2,+/- 1.2 3.1 +/- 0.7 4.0 + 0.4 Total Residue 5.2 +/- 1.2 3.1 +/- 0.7 4.0: 0.4 K-40 (ICP) 2.59 1.82 3.94 -. d Mn-54 <15 <15 <15 Fe-59 < 30 < 30 < 30 Co-58 <15 <15 <15 Co-60 <15 <15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 <15 Cs-134 < 10 <10 <10 Cs-1 37 <10 <10 < 10 Ba-La-140 <*15 <15 <15 72

KEWAUNEE Table 24. Surface water samples, analyses for gross beta, potassium-40, and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCi/L)

Indicator K-ld Date Collected 04-03-06 , 05-01-06 06-01-06 Lab Code KSW-2030 KSW-2925 KSW-3691 Gross beta Suspended Solids <0.3 <0.4 < 0.4 Dissolved Solids 1.2.t 0.3 1.4 +/- 0.3. 1.8 +/- 0.3 Total Residue 1.2+/- 0.3 1.4 +/- 0.3 1.8 +/- 0.3 K-40 (ICP) 1.30 1.16 0.91 Mn-54

• 15 <15 <15 Fe-59 < 30 < 30 < 30 Co-58 <15 <15 <15 Co-60 < 15 <15 < 15 Zn-65 <-30 < 30 < 30 Zr-Nb-95 <15 < 15 < 15 Cs-134 < 10 <10 < 10 Cs-137 < 10 <10 < 10 Ba-La-140 < 15 <15 <15 K-le Date Collected 04-03-06 05-01-06 06-01-06 Lab Code -.. KSW-2031 KSW-2926 KSW-3692 Gross beta Suspended Solids < 0.4 < 0.4 < 0.4 Dissolved Solids 4.5 +/-1.2 3.7 +/-+0.8 2.6 +/- 0.7 4.5 + 1.2 3.7 +/-0.8 2.6 +/- 0.7 Total Residue K-40 (ICP) 3.23 3.38 1.44 Mn-54 < 15 <15 <15 Fe-59 <30 < 30 < 30 Co-58 < 15 <15 <15 Co-60 <15 < 15 <15 Zn-65 < 30 <30 < 30 Zr-Nb-95 < 15 <15 <15 Cs-134 < 10 < 10 <10 Cs-1 37 < 10 < 10 < 10 Ba-La-1 40 <-15 <15 < 15 73

KEWAUNEE Table 24. Surface water samples, analyses for gross beta, potassium-40, and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCiIL)

Indicator K-Id Date Collected 07-05-06 08-01-06 09-05-06 Lab Code KSW-4405 KSW-5279 KSW-6089 Gross beta Suspended Solids < 0.4 < 0.4 < 0.4 Dissolved Solids 1.4 +/- 0.3 1.7 +/- 0.3 2.0 +/- 0.4 Total Residue 1.4 +/- 0.3 1.7 +/- 0.3 2.0 +/- 0.4 K-40 (ICP) 1.10 1.18 1.21 Mn-54 <15 < 15 <15 Fe-59 < 30 < 30 < 30 Co-58 < 15 <15 <15 Co-60 < 15 <15 <15 Zn-65 < 30 <30 < 30 Zr-Nb-95 < 15 <15 <15 Cs-134 < 10 <10 <10 Cs-137 <10 <10 <10 Ba-La-1 40 < 15 <15 < 15 K-I e Date Collected 07-05-06 08-01-06 09-05-06 Lab Code KSw-4406 KSW-5280 KSW-6090 Gross beta Suspended Solids < 0.4 < 0.4 < 0.2 Dissolved Solids 12.7 +/- 1.6 2.9 +/- 1.0 22.5 +/- 2.1 Total Residue 12.7 +/- 1.6 2.9 +/- 1.0 22.5 +/- 2.1 K-40 (ICP) 6.03 2.98 19.55 Mn-54 <15 <15 <15 Fe-59 < 30 <30 <30 Co-58 < 15 <15 <15 Co-60 < 15 <15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 <15 Cs-134 < 10 <10 <10 Cs-137 < 10 <10 - <10 Ba-La-140 < 15 <15 <15 74

KEWAUNEE Table 24. Surface water samples, analyses for gross beta, potassium-40, and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCi/L)

Indicator K-I d Date Collected 10-02-06 11-61-'6 12-04-06 Lab Code KSW-6765 KSW-8006 KSW-8691 Gross beta, Suspended Solids < 0.4 < 0.4 < 0.4 Dissolved Solids 2.8 +/- 0.4 1.1 +/-0.3 1.7 +/- 0.3 Total Residue 2.8 +/- 0.4 1.1 +/-0.3 1.7 + 0.3 K-40 (ICP) 0.80 1.38 1.12 Mn-54 < 15 <15 <15 Fe-59 < 30 < 30 < 30 Co-58 < 15 <15 <15 Co-60 < 15 <15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 <15 Cs-134 ~< 10 <10 <10

<10 Cs-137 <10 <10 Ba-La-140 <15 15 < 15 K-1 e Date Collected 10-02-06 11-01-06. 12-04-06 Lab Code KSW-6766 KSW-8007 KSW-8692 Gross beta Suspended Solids

• 0.4: < 0.4 < 0.4 Dissolved Solids 16.4 +/- 1.6 11.7 + 1.5 5.4 +/- 1.0 Total Residue 16.4 +/- 1.6 11.7

• 1.5 5.4 +/- 1.0 K-40 (ICP) 5.22 9.52 3.56 Mn-54 < 15 <15 <15 Fe-59 < 30 < 30 < 30 Co-58 < 15 <15 <15 Co-60 < 15 <15 <15 Zn-65 < 30 <30 < 30 Zr-Nb-95 < 15 <15 <15 Cs-134 < 10 <10 <10 Cs-137 <.10 <10 <10 Ba-La-140 < 15 <15 <15 75

KEWAUNEE Table 24. Surface water samples, analyses for gross beta, potassium-40 and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCiIL)

Indicator K-i k Date Collected 01-03-06 02-01-06 03-01-06 Lab Code KSW-99 KSW-512 NSO Gross beta Suspended Solids < 0.4 <0.4 Dissolved Solids 12.1 +/- 1.5 8.8 . 1.0 Total Residue 12.1 +/- 1.5 8.8 + 1.0 K-40 (ICP) 7.72 7.06 Mn-54 <15 <15 Fe-59 < 30 <30 Co-58 < 15 <15 Co-60 <15 <15 Zn-65 < 30 -<:30 Zr-Nb-95 < 15 <15 Cs-1 34 < 10 <10 Cs-137 < 10 <10 Ba-La-1 40 < 15 <.15 Date Collected 04-03-06 05-01-06 06-01-06 Lab Code KSW-2032 KSW-2927 KSW-3693 Gross beta Suspended Solids < 0.4 < 0.4 < 1.2 Dissolved Solids 11.2 +/- 1.3 3.4 +/- 0.9 6.0 +/- 0.9 Total Residue 11.2 +/- 1.3 3.4 +/- 0.9 6.0 +/- 0.9 K-40 (ICP) 7.41 0.74 4.36 Mn-54 <15 <15 <15 Fe-59 < 30 < 30 < 30 Co-58 < 15 < 15 <15 Co-60 < 15 <15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 <15 Cs-134 < 10 < 10 < 10 Cs-1 37 < 10 <10 <10 Ba-La-i 40 < 15 <15 <15 a NS= No sample; water frozen.

76

KEWAUNEE Table 24. Surface water samples, analyses for gross beta, potassium-40, and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCi/L)

Indicator K-I k Date Collected 07-05-06 08-01-06 09-05-06 Lab Code KSW-4407 KSW-5281 KSW-6091 Gross beta

< 0.6 -< 0.4 < 0.4 Suspended Solids Dissolved Solids 15.7 +/-£1.3 3.5 +/- 0.7 13.3 +/- 1.6 Total Residue 15.7 +/- 1.3 3.5 +/- 0.7 13.3 +/- 1.6 K-40 (ICP) 2.84 3.12 6.71 Mn-54 <15 <15 <15 Fe-59 <30 <30

< < 30 Co-58 < 15 <15 <15 Co-60 < 15 <15 <15 Zn-65 <30 < 30 < 30 Zr-Nb-95 < 15 ý<15 <15 Cs-134 <10 <10 < 10 Cs-137 < 10 <10 <10 Ba-La-140 < 15 <15 <15 Date Collected 10-02-06 11-01-06 12-04-06 Lab Code KSW-6767 KSW-8008 NS" Gross beta Suspended Solids <0.9 < 0.7 Dissolved Solids 10.8 +/- 1.2 6.0 +/- 0.9 Total Residue 10.8 +/- 1.2 6.0 1 0.9 K-40 (ICP) 2.95 8.01.

Mn-54 < 15 <15 Fe-59 <30 <30 Co-58 <. 15 <15 Co-60 <15 < 15 Zn-65 <30 < 30 Zr-Nb-95 < 15 <15 Cs-134 < 10 < 10 Cs-137 < 10 <10 Ba-La-140 < 15 <15 a NS= No sample; water frozen.

77

KEWAUNEE Table 24. Surface water samples, analyses for gross beta, potassiumA,40 and gamma-emitting isotopes.

Collection: Monthly Sample Description and Concentration (pCi/L)

Indicator K-9 (Raw)

Date Collected 01-03-06 02-01-06 03-01-06 Lab Code KSW-i 00 KSW-513 KSW-1065 Gross beta Suspended Solids < 0.4 < 0.4 < 0.4 Dissolved Solids 2.9 t 0.8 1.3 + 0.4 i.5

• 0.4" Total Residue 2.9 + 0.8 1.3

• 0.4 1.5 : 0.4 K-40 (ICP) 0.84, 1.01 1.13 Mn-54 <15 <15 <15 Fe-59 <30 <30 < 30 Co-58 <15 < 15 <15 Co-60 < 15 <15 <15 Zn-65 < 30 <30 < 30 Zr-Nb-95 <15 < 15 <15 Cs-134 < 10 510 <10 Cs-137 <10 <10 <10 Ba-La-140 <15 <15 <15 K-9 (Tar)

Date Collected 01-03-06 02-01-06 03-01-06 Lab Code KSW-101 KSW-51'4 KSW-1066 Gross beta Suspended Solids < 0.4 < 0.4 < 0.4 Dissolved Solids 2.3 +/- 0.4 1.5 +/- 0.3 1.4 +/- 0.1 Total Residue 2.3 +/- 0.4 1.5 +/- 0.3 1.4 +/- 0.1 K-40 (ICP) 0.87 0.96 1.26 Mn-54 <15 <15 <15 Fe-59 < 30 < 30 < 30 Co-58 <15 <15 <15 Co-60 < 15 <15 <15 Zn-65 < 30 <30 <30 Zr-Nb-95 < 15 <15 < 15 Cs-134 <10 < 10 <10 Cs-137 < 10 <10 <10 Ba-La-140 <15 <15 <15 78

KEWAUNEE Table 24. Surface water samples, analyses for gross beta, potassium-40, and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCi/L)

Indicator K-9 (Raw)

Date Collected 04-03-06 05-01-06 06-01-06 Lab Code KSW-2033 KSW-2928 KSW-3694 Gross beta <0.4 Suspended Solids < 0.4 < 0.4 Dissolved Solids 2.8 +/- 0.8 1.5 +/- 0.4 2.6 +/- 0.5 Total Residue 2.8 +/- 0.8 1.5 +/- 0.4 2.6 +/- 0.5 K-40 (ICP) 1.12 1.31 0.92 Mn-54 <15 <15 <15 Fe-59 <30 <30 < 30 Co-58 < 15 <15 <15 Co-60 <15 <15 <15 Zn-65 <30 < 30 < 30 Zr-Nb-95 < 15 <15 <15 Cs-134 < 10 <10 < 10 Cs-1 37 <10 ' < 10 <10 Ba-La-1 40 <15 <15 <15 K-9 (TA)

Date Collected 04-03-06 05-01-06 06-01-06 Lab Code KSW-2034ý KSW-2929 KSW-3695 Gross beta Suspended Solids C 0.3 < 0.4 < 0.4 Dissolved Solids 3.0 +/- 0.5 1.4 +/- 0.3 2.4 +/- 0.3 Total Residue 3.0 +/- 0.5 1.4+/- 0.3 2.4 +/- 0.3 K-40 (ICP) 1.31 1.32 0.97 Mn-54 < 15 <15 <15 Fe-59 <30 <30 < 30 Co-58 < 15 <15 <15 Co-60 <'15 <15 < 15 Zn-65 < 30 <30 < 30 Zr-Nb-95 < 15 <15 <15 Cs-134 < 10 <10 <10 Cs-137 < 10 <10 <10 Ba-La-140 <15 <15 <15 79

KEWAUNEE Table 24. Surface water samples, analyses for gross beta, potassium-40, and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCi/L)

Indicator K-9 (Raw)

Date Collected 07-05-06 08-01-06 09-05-06 Lab Code KSW-4408 KSW-5282 KSW-6092 Gross beta Suspended Solids < 0.3 < 0.3 < 0.4 Dissolved Solids 1.2 1 0.4 1.5+/-,0.4 ,3.1, +/- 0.7 Total Residue 1.2 +/- 0.4 1.5 +/- 0.4 3.1 +/- 0.7.

K-40 (ICP) 1.18 1.08 1.11 Mn-54 <15 <15 <15 Fe-59 < 30 < 30 < 30 Co-58 <15 <15 <15 Co-60 <15 <15 <15 Zn-65 < 30 < 30 <30 Zr-Nb-95 <15 <15 <15 Cs-134 < 10 <10 <10 Cs-I 37 < 10 < 10 <10 Ba-La-140 <15 <15 <15 K-9 (Tar)

Date Collected 07-05-06 08-01-06 09-05-06 Lab Code KSW-4409 KSW-5283 KSW-6093 Gross beta Suspended Solids < 0.4 < 0.4 < 0.4 Dissolved Solids 0.7 +/- 0.2 1.7 +/- 0.3 2.3

• 0.4 Total Residue 0.7 +/- 0.2 1.7 +/- 0.3 2.3 t 0.4 K-40 (ICP) 1.11 1.07 1.31 Mn-54 <15 <15 <15 Fe-59 <30 *< 30 < 30 Co-58 < 15 <15 <15 Co-60 <15 .. < 15 <15 Zn-65 < 30 <30 < 30 Zr-Nb-95 < 15 <15 <15 Cs-134 < 10 < 10 <10 Cs-137 < 10 <10 < 10 Ba-La-140 < 15 <15 <15 80

KEWAUNEE Table 24. Surface water samples, analyses for gross beta, potassium-40, and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCi/L)

Indicator K-9 (Raw)

Date Collected 10-02-06 11 -0i-06 12-04-06 Lab Code KSW-6768 KSW-8009 KSW-8693 Gross beta Suspended Solids < 0.4 < 0.4 < 0.4 Dissolved Solids 1.7 +/- 0.4' 0.6 +/- 0.4 1.1 +/- 0.4 Total Residue 1.7 +/-:0.4 0.6 +/- 0.4 1.1 +/-+0.4 K-40 (ICP) 0.61 1.35 1.15 Mn-54 < 15 < 15 < 15 Fe-59 < 30 < 30 < 30 Co-58 < 15 < 15 < 15 Co-60 < 15 < 15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 '< 15 < 15 < 15 Cs-134 < 10 < 10 <10 Cs-137 < 10 < 10 < 10 Ba-La-140 < 15 < 15 <15 K-9 (Tan)

Date Collected 10-02-06 11-01-06 12-04-06 Lab Code KSW-6169 KSW-8010 KSW-8694 Gross beta Suspended Solids < 0.4 <0.3 <0.4 Dissolved Solids 1.6 1 0.3 2.7 +/- 0.5 0.7 +/- 0.2 Total Residue 1.6 +/- 0.3 2.7 +/- 0.5 0.7 +/- 0.2 K-40 (ICP) 0.64 1.45 1.14 Mn-54 < 15 <15 < 15 Fe-59 <: 30 < 30 < 30 Co-58 < 15 < 15 < 15 Co-60 < 15 < 15 < 15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 < 15 < 15 < 15 Cs-134 < 10 < 10 < 10 Cs-137 < 10 <10 <10 Ba-La-140 < 15 <15 < 15

• 81

KEWAUNEE Table 24. Surface water, analyses for gross beta, potassium-40 and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCi/L)

Indicator K-14a Date Collected 01-03-06 02-01-06 03-01-06 Lab Code KSW-102 KSW-515 KSW-1067 Gross beta Suspended Solids < 0.4 < 0.4 < 0.4 Dissolved Solids 4.3 1 0.7 2.31+ 0.4 1.5 +/- 0.4 Total Residue 4.3

• 0.7 2.3 00.4 1.5 +/- 0.4 K-40 (ICP) 2.36 1.27 1.31 Mn-54 < 15 <15 <15 Fe-59 < 30 < 30 < 30 Co-58 < 15 <15 <15 Co-60 < 15 <15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 <15 Cs-1 34 <10 <10 <10 Cs-I 37 < 10 < 10 <10 Ba-La-1 40 < 15 <15 <15 K-14b Date Collected 01-03-06 02-01-06 03-01-06 Lab Code KSW-103 KSW-516 KSW-1068 Gross beta Suspended Solids < 0.4 < 0.4 < 0.4 Dissolved Solids 4.8 +/- 0.8 2.6 + 0.4 1.6 +/- 0.4 Total Residue 4.8 +/- 0.8 2.6 +/- 0.4 1.6 +/- 0.4 K-40 (ICP) 2.55 1.47 1.35 Mn-54 <15 <15 <15 Fe-59 <30 < 30 < 30 Co-58 < 15 <15 <15 Co-60 <15 <15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 <15 Cs-134 < 10 < 10 <10 Cs-137 < 10 < 10 <10 Ba-La-1 40 <15 <15 <15 82

KEWAUNEE table 24. Surface water, analyses for gross beta, potassium-40 and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCiIL)

Indicator K-14a Date Collected 04-03-06 05-.01-6 06-01-06 Lab Code KSW-2035 KSW-2930 KSW-3696 Gross beta Suspended Solids < OA < 0.3 < 0.4 Dissolved Solids 4.3 t 0.7 1.8 1 0.4 3.8 +/- 0.5 Total Residue 4.3

• 0.7 1.8 1 0.4 3.8 +/- 0.5 K-40 (ICP) 2.34 1.20 1.60 Mn-54 <15 <15 <15 Fe-59 < 30 < 30 < 30 Co-58 < 15 <15 <15 Co-60 < 15 <15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 < 15 Cs-134 < 10 <10 <10 Cs-137 <-10 < 10 < 10 Ba-La-140 <15 <15 <15 K-14b Date Collected. 04-03-06 05-01-06 06-01-06 Lab Code KSW-2036 KSW-2931 KSW-3697 Gross beta Suspended Solids < 0.4 < 0.4 < 0.3 Dissolved Solids 3.2 +/- 0.5 1.3 +/- 0.3 3.7 +/- 0.7 Total Residue 3.2 +/- 0.5 1.3 +/- 0.3 3.7 +/- 0.7 K-40 (ICP) 2.14 0.86 1.73 Mn-54 < 15 <15 <15 Fe-59 < 30 < 30 < 30 Co-58 < 15 <15 <15 Co-60 <.15 < 15 < 15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 < 15 < 15 < 15 Cs-134 < 10 <10 < 10 Cs-137 "< 10 <10 <10 Ba-La-140 < 15 <15 <15 83

KEWAUNEE Table 24. Surface water, analyses for gross beta, potassium-40 and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCiIL)

Indicator K-14a Date Collected 07-05-06 08-01-06 09-05-06 Lab Code KSW-4410 KSW-5284 KSW-6094 Gross beta Suspended Solids < 0.4 < 0.4 < 0.4 Dissolved Solids 4.7 + 0.6 3.3 +/- 0.5 4.1 +/- 0.4 Total Residue 4.7 +/- 0.6 3.3 +/- 0.5 4.1 +/- 0.4 K-40 (ICP) 1.74 1.53 2.08 Mn-54 <15 < 15 <15 Fe-59 < 30 < 30 < 30 Co-58 <15 <15 <15 Co-60 < 15 <15 <15 Zn-65 < 30 <30 < 30 Zr-Nb-95 <15 <15 <15 Cs-1 34 < 10 <10 < 10 Cs-137 < 10 <10 < 10 Ba-La-140 <15 <15 <15 K-14b Date Collected 07-05-06 08-01-06 09-05-06 Lab Code KSW-4411 KSW-5285 KSW-6095' Gross beta Suspended Solids < 0.4 < 0.7 < 0.9 Dissolved Solids 5.5 + 0.8 7.7 +/- 0.9 4.1 +/- 0.6 Total Residue 5.5 +/- 0.8 7.7 +/- 0.9 4.1 +/- 0.6 K-40 (ICP) 2.28 1.37 2.48 Mn-54 < 15 <15 <15 Fe-59 < 30 <30 < 30 Co-58 <15 -<15 <15 Co-60 <15 <15 <15 Zn-65 < 30 < 30 <30 Zr-Nb-95 *< 15 <15 <15 Cs-134 < 10 <10 <10 Cs-137 < 10 <10 <10 Ba-La-140 < 15 <15 <15 84

KEWAUNEE Table 24. Surface water, analyses for gross beta, potassium-40 and gamma-emitting isotopes (continued).

Sample Description and Concentration (pCVlL)

Indicator K-14a Date Collected 10-02-06 11-01-06 12-04-06 Lab Code KSW-6770 KSW-8011 KSW-8695 Gross beta Suspended Solids < 0.4  ? <0.4 < 0.3 Dissolved Solids 2.5 +/- 0.4 2.4

• 0.6 1.8 +/- 0.4 Total Residue 2.5 +/- 0.4 2.4

• 0.6 1.8 +/- 0.4 K-40 (ICP) 0,56. 1.61 1.32 Mn-54 < 15 <.15 <15 Fe-59 .< 30 <30 <30 Co-58 <.15 <15 <15 Co-60 <15 <15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 <15 Cs-1 34 < 10 <10 <10 Cs-1 37 < 10 < 10 <10 Ba-La-140 < 15 <.15 < 15 K-14b Date Collected 10,02-06 11-01-06 12-04-06 Lab Code-- KSW-6771 KSW-8012 KSW-8696 Gross beta Suspended Solids S<.0.4 < 0.4 < 0.4 Dissolved Solids 1.9 +/- 0.4 2.5 +/- 0.6 1.8 +/- 0.4 Total Residue 1.9 +/- 0.4 2.5 +/- 0.6 1.8 +/- 0.4 K-40 (ICP) 0.61 1.49 1.18 Mn-54 < 15 <15 <15 Fe-59 < 30 < 30 < 30 Co-58 <15 < 15 <15 Co-60 <15 <15 <15 Zn-65 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 < 15 Cs-134 < .10 <10 < 10 Cs-1 37 < 10 <10 <10 Ba-La-1 40 <15 <15 <15 85

KEWAUNEE Table 25. Surface water, analyses for tritium, strontium-89 and strontium-90.

Collection: Quarterly composites of monthly samples.

Location and Concentration pCi/L Collection Period Lab Code H-3 Sr-89 Sr-90 Indicator K-la 1st Quarter KSW -1451 < 158 < 0.9 1.2 +/- 0.4 2nd Quarter -4228 < 131 < 1.3 < 0.5 3rd Quarter -6733 < 186 < 0.9 0.5 +/- 0.3 4th Quarter -9666 < 152 < 1.0 < 0.5 K-I b 1st Quarter KSW -1452 < 158 < 0.9 < 0.5 2nd Quarter -4229 < 131 < 1.0 0.7 +/- 0.3 3rd Quarter -6734 < 186 < 0.9 < 0.4 4th Quarter -9667, 8 < 152 < 1.0 < 0.4 K-Id 1st Quarter KSW -1453 < 158 < 0.9 < 0.5 2nd Quarter -4230 < 174 < 1.0 < 0.4 3rd Quarter -6735 < 186 < 1.0 < 0.4 4th Quarter -9669 < 152 < 1.2 < 0.6 K-I e 1st Quarter KSW -1454 < 158 < 0.8 < 0.4 2nd Quarter -4231 < 131 < 1.0 0.6 +/- 0.3 3rd Quarter -6736 < 180 < 0.9 < 0.5 4th Quarter -9670 < 152 < 1.1 < 0.5 86

KEWAUNEE Table 25. Surface water, analyses for tritium, strontium-89 and strontium-90 (continued).

Location and Concentration pCi/L Collection Period H-3 Sr-89 Sr-90 Indicator K-14a 1st Quarter KSW -1458 < 151 < 0.8 <0.5 2nd Quarter -4235 < 131 < 1.0 < 0.4 3rd Quarter -6741 < 186 < 1.0 0.6 +/- 0.3 4th Quarter -9674 < 152 < 1.1 < 0.5 K-14b 1st Quarter KSW -1459 < 151 < 0.8 < 0.4 2nd Quarter -4236 < 131 < 1.2 < 0.5 3rd Quarter -6742 < 186 < 1.1 < 0.5 4th Quarter -9675 < 152 < 1.2 < 0.5 K-1 k 1st Quarter KSW -1455 < 152 < 1.1 < 0.4 2nd Quarter -4232 < 131 < 1.1 < 0.5 3rd Quarter -6737 < 186 <1.1 0.5 +/- 0.3 4th Quarter -9671 < 152 < 1.2 < 0.7 Control K-9 1st Quarter KSW -1456 (Raw)' < 151 < 0.9 < 0.5

-1457 (Tap) < 151 < 1.0 < 0.6 2nd Quarter -4233 (Raw) < 131 < 1.2 0.5 +/- 0.3

-4234 (Tap) < 131 < 1.0 0.5

• 0.3 3rd Quarter -6738 (Raw) < 186 < 0.8 < 0.5

-6739, 40 (Tap) < 186 < 1.1 < 0.5 4th Quarter -9672 (Raw) < 152 < 1.0 < 0.4

-9673 (Tap) < 152 < 1.0 < 0.5 87

KEWAUNEE Table 26. Fish, collected at K-Id, analyses for gross beta, strontium-89, strontium-90 and gamma-emitting isotopes.

Collection: Three times a year Sample Description and Concentration (pCi~g wet)

Collected 04-14-06 07-21-06 Lab Code KF-2922 KF-5264 Type Lawyer Fish White Sucker Portion Flesh Bones Flesh Bones I .

Gross beta 2.69

• 0. 07 2.69 +/- 0.74 3.12 +/- 0.08 1.56 +/- 0.52 Sr-89 NA! < 0.26 NAa < 0.27 Sr-90 NA 0.34 +/- 0.074 NA 0.60 +/- 0.11 K-40 2.71 +/- 0.90 NAa 2.09 +/- 0.70 NA8 Mn-54 < 0.066 NA < 0.024 NA Fe-59 < 0.087 NA *0.024 NA Co-58 < 0.099 NA < 0.032 NA Co-60 < 0.062 NA < 0.027 NA Cs-1 34 < 0.12 NA

• 0.028 NA Cs-1 37 < 0.095 NA < 0.024 NA Collected 08-04-06 11-30-06 Lab Code KF-8738 KF-8739 Type Sucker Sucker Portion Flesh Bones Flesh Bones Gross beta 4.03 +/- 0.11 2. 44 +/- 0.51 3.87 +/- 0.12 2.02 +/- 0.41 Sr-89 NAB < 0.76 NA' < 0.11 Sr-90 NA 0. 13 +/- 0.048 NA 0.075 +/- 0.029 K-40 2.99 +/- 0.29 NA8 3.33 +/- 0.58 NA8 Mn-54 < 0.017 NA < 0.013 NA Fe-59 < 0.13 NA < 0.039 NA Co-58 < 0'047 NA <0.025 NA Co-60 < 0.009 NA < 0.025 NA Cs-134 < 0.010 NA < 0.020 NA Cs-137 < 0.014 NA < 0.019 NA a NA = Not analyzed; analyses not required.

Note: Page 89 is intentionally left out.

88

KEWAUNEE Table 27. Slime or aquatic vegetation, analyses for gross beta, strontium-89, strontium-90, and Collection: Semiannually Sample Description and Concentration Indicators Control Location K-Ia K-I b K-id K-9 Date Collected 06-01-06 06-01-06 06-01-06 06-01-06 Lab Code KSL-3639 KSL-3640 KSL-3641, 2 KSL-3645 Gross beta 6.16 +/- 0.19 5.90

• 0.16 5.17 t 0.13 4.73 +/- 0.10 Sr-89 < 0.008 < 0.009 <0.011 < 0.002 Sr-90 < 0.005 < 0.006 < 0.008 < 0.002 Be-7 0.25

• 0.06 0.49 1 0.13 1.36 1 0.17 <0.13 K-40 3.60

• 0.21 4.17

• 0.26 2.18 t 0.23 3.40 +/- 0.28 Mn-54 < 0.007 < 0.009 < 0.008 < 0.007 Co-58 < 0.006 < 0.010 < 0.009 < 0.011 Co-60 < 0.003 < 0.009 < 0.012 < 0.013 Nb-95 < 0.005 < 0.010 < 0.007 < 0.006 Zr-95 < 0.013 < 0.014 < 0.020 < 0.017 Ru-103 < 0.005 < 0.011 < 0.005 < 0.012 Ru-106 < 0.061 < 0.010 < 0.089 <0.11 Cs-134 < 0.008 < 0.009 < 0.010 <0.012 Cs-137 < 0.007 < 0.010 < 0.010 < 0.015 Ce-141 <0.015 k0.021 < 0.014 < 0.014 Ce-144 < 0.055 < 0.082 < 0.043 < 0.068 Location K-le K-I k K-14 Date Collected 06-01-06 06-01-06 05-01-06 Lab Code KSL!3643 KSL-3644 KSL-2932, 3 Gross beta 2.31 -, 0.19 3.27 + 0.09 5.87 +/- 0.23 Sr-89 < 0.012 < 0.003 < 0.038 Sr-90 < 0.009 < 0.001 <0.018 Be-7 0.96 +/- 0.09 0.47 +/- 0.08 1.28 t 0.13 K-40 0.86 +/--0.12 2.32 +/- 0.18 3.11 10.27 MRi-54 < 0.004 < 0.008 < 0.009 Co-58 < 0.005 < 0.006 <0.011 Co-60 < 0.005 < 0.005 < 0.010 Nb-95 < 0.006 < 0.007 < 0.012 Zr-95 < 0.009 <0.010 < 0.023 Ru-1 03 < 0.005 < 0.005 < 0.007 Ru-106 < 0.050 < 0.062 <0.10 Cs-134 < 0.008 < 0.008 < 0.011 Cs-137 0.020 1 0.006 < 0.007 0.026 +/- 0.012 Ce-141 < 0.010 < 0.015 < 0.018 Ce-144 < 0.053 < 0.061 < 0.052 90

KEWAUNEE Table 27. Slime or aquatic vegetation, analyses for gross beta, strontium-89, strontium-90, and gamma-emitting isotopes.

Collection: Semiannually Sample Description and Concentration Indicators Control Location K-I a K-i b K-ld K-9 Date Collected 09-05-06 08-01-06 08-01-06 08-01-06 Lab Code KSL-6084 KSL-5265, 6 KSL-5267 KSL-5269 Gross beta 6.13 +/- 0.15 3.94 +/- 0.35 4.15 +/- 0.54 7.03 +/- 0.25 Sr-89 < 0.016 < 0.092 < 0.077 < 0.017 Sr-90 < 0.004 0.13 +/- 0.022 0.058 +/- 0.018 < 0.006 Be-7 1.37 +/- 0.33 1.24 +/- 0.35 <0.17 0.64 +/- 0.20 K-40 4.78 +/- 0.45 1.03 +/- 0.37 3.18 +/- 0.57 4.24 +/- 0.49 Mn-54 < 0.019 < 0.018 < 0.024 < 0.021 Co-58 < 0.009 < 0.027 < 0.024 < 0.011 Co-60 < 0.015 < 0.024 < 0.020 < 0.011 Nb-95 < 0.039 < 0.028 < 0.025 < 0.019 Zr-95 < 0.036 < 0.060 < 0.050 < 0.023 Ru-103 < 0.024 < 0.036 < 0.023 < 0.016 Ru-106 <0.15 <0.16 <0.13 < 0.18 Cs-134 < 0.014 < 0.028 < 0.040 < 0.021 Cs-137 < 0.015 < 0.036 < 0.023 < 0.017 Ce-141 < 0.066 < 0.041 < 0.024 < 0.036 Ce-144 < 0.10 <0.14 < 0.088 <0.13 Location K-i e K-I k K Date Collected 09-05-06 08-01-06 07-05-06 Lab Code KSL-6085, 6 KSL-5268 KSL-4402 Gross beta 5.05 +/- 0.45 4.69 +/- 0.13 5.30 +/- 0.36 Sr-89 < 0.089 < 0.009 < 0.037 Sr-90 <0.019 < 0.004 < 0.014 Be-7 0.78 +/- 0.26 0.86 +/- 0.36 1.82 +/- 0.43 K-40 1.99 +/- 0.25 5.15 +/- 0.81 3.07 +/- 0.56 Mn-54 0.035 +/- 0.019 < 0.034 < 0.013 Co-58 < 0.028 < 0.021 < 0.031 Co-60 0.22 +/- 0.019 < 0.022 <0.019 Nb-95 < 0.041 < 0.048 < 0.041 Zr-95 < 0.065 < 0.077 < 0.072 Ru-103 < 0.033 < 0.028 < 0.042 Ru-106 < 0.076 <0.17 < 0.23 Cs-134 < 0.011 < 0.025 *< 0.028 Cs-137 < 0.017 < 0.037 < 0.022 Ce-141 < 0.042 < 0.069 <0.11 Ce-1 44 < 0.08 < 0.26 <0.12 91

KEWAUNEE Table 28. Bottom sediment samples, analyses for gross beta, strontium-89, strontium-90, and gamma-emitting Isotopes.

Collection: May and November Sample Description and Concentration (pCifg dry)

Indicator Control Location K-Ic K-Id Indicator K-lJ K- 14 K-9 Collection Date 05-01-06 05-01-06 05-01-06 05-01-06 05-01-06 Lab Code KBS-3102 KBS-3103, 4 KBS-3105 KBS-3107 KBS-3106 Gross beta 14.75

• 1.88 8.66 +/- 1.08 10.71 +/- 1.57 14.84 +/- 1.82 17.44 +/- 2.20 Sr-89 < 0.032 < 0.029 < 0.031 < 0.032 < 0.035 Sr-90 < 0.022 < 0.021 < 0.017 < 0.021 0.041 +/- 0.014 K-40 10.48 + 0.73 5.97 +/- 0.42 7.96

• 0.66 10.23 +/- 0.83 9.08 +/- 1.16 Co-58 < 0.018 < 0.017 < 0.023 < 0.023 < 0.050 Co-60 < 0.015 < 0.016 < 0.021 < 0.030 < 0.042 Cs-1 34 < 0.026 < 0.017 < 0.025 < 0.020 < 0.055 Cs-1 37 < 0.028 < 0.018 < 0.021 < 0.030 0.082 +/- 0.047 Location K-Ic K-Id K-lj K-14 K-9 Collection Date 11-01-06 11-01-06 11-01-06 11-01-06 11-01-06 Lab Code KBS-8013 KBS-8014 KBS-8015 KBS-8017,8 KBS-8016 Gross beta 11.95

• 1.80 9.39 +/- 1.63 9.2*4 +/- 1.69 10.36 +/- 1.22 26.61 +/- 2.57 Sr-89 < 0.034 < 0.035 < 0.034 < 0.034 < 0.095 Sr-90 < 0.017 < 0.014 < 0.016 < 0.017 0.053 +/- 0.027 K-40 11.01

• 0.75 8.41 +/- 0.66 8.49:1 0.47 9.80 +/- 0.44 8.26 +/- 0.86 Co-58 < 0.020 < 0.020 <.0.012 < 0.015 < 0.044 Co-60 < 0.026 < 0.025 < 0.013 < 0.015 < 0.031 Cs-134 < 0.026 < 0.024 < 0.017 < 0.020 < 0.036 Cs-137 < 0.025 < 0.023 0.025 +/- 0.011 < 0.015 0.078 +/- 0.039 92

Environmental, Inc.

Midwest Laboratory an AMegheny Tedmnolgles Go.

ANALYTICAL PROCEDURES MANUAL ENVIRONMENTAL, Inc.

MIDWEST LABORATORY prepared for DOMINION NUCLEAR KEWAUNEE POWER STATION Revised 02-08-07 (This information, or any portion thereof, shall not be reproduced In any manner or distributed to any third party without the written permission of Environmental, Inc, Midwest Laboratory.)

Revised 12-17-04 Page 1 of 1 KPS List of Procedures Procedure Revision Revision Date Number Number AB-01 Determination of Gross Alpha and/or Gross Beta in Solid 3 07-07-04 Samples AP-02 Determination of Gross Alpha and/or Gross Beta In Air 1 07-15-91 Particulate Filters AP-03 Procedure for Compositing Air Particulate Filters for 2 07-21-98 Gamma Spectroscopic Analysis CA-01 Determination of Stable Calcium in Milk 07-08-88 COMP-01 Procedure for Compositing Water and Milk Samples 07-09-04 GS-01 Determination of Gamma Emitters by Gamma 02-08-07 Spectroscopy 1-131-01 Determination of 1-131 in Milk by Anion Exchange (Batch 03-16-04 Method) 1-131-02 Determination of 1-131 In Charcoal Cartridges by Gamma 05-07-04 Spectroscopy SP-01 Sample Preparation 01-26-04 SR-02 Determination of Sr-89 and Sr-90 In Water (Clear or 12-15-04 Drinking Water SR-05 Determination of Sr-89 and Sr-90 in Ashed Samples 12-15-04 SR-06 Determination of Sr-89 and Sr-90 In Soil and Bottom 08-05-04 Sediments SR-07 Determination of Sr-89 and Sr-90 In Milk (Ion Exchange 08-18-94 Batch Method)

T-02 Determination of Tritium in Water 01-29-02 TLD-01 Preparation and Readout of Teledyne Isotopes TLD Cards 06-07-01 W(DS)-01 Determination of Gross Alpha and/or Gross Beta In Water 07-21-98 (Dissolved Solids or Total Residue)

W(SS)-02 Determination of Gross Alpha and/or Gross Beta In Water 12-17-04 (Suspended Solids)

-- Environmental, Inc.

Midwest Laboratory an AllgheM Tefdoinges Co.

700 Landwehr Road

• aNook, IL 60062-2310 p&.(847564-070D fax(847)564-4517

'.oY DETERMINATION OF GROSS ALPHA AND/OR GROSS BETA' IN SOLID SAMPLES PROCEDURE NO. AB-01 Prepared by Environmental,lInc.

Midwest Laboratory I Copy No.

Revision # Date P~ages Prepared by Approved b 3 07-07-04 3 B Grob SA Coorlim (This procedure, or any portion thereof, shall not be reproduced In any manner or distributed to any third party without the written permission of Environmental, Inc., Midwest Laboratory.)

EIML-AB-01 Rev. 3, 07-07-04 DETERMINATION OF GROSS ALPHA ANDIOR GROSS BETA IN SOLID SAMPLES Principle of Method 100 mg to 200 mg of sample Is distributed evenly on a 2n ringed planchet, counted in a proportional counter, and concentrations of gross alpha and /or gross beta are calculated.

A. Vegetation. Meat. Fish. and Wildlife Procedure

1. Weigh out accurately in a planchet no more than 100 mg of ashed or dried and ground sample for gross alpha assay and no more than 200 mg for gross beta assay.

NOTE: If both gross alpha and gross beta analyses are required, do not use more than 100mg.

2. Add a few drops of water and spread uniformly over area of the planchet. Dry under a heat lamp.

NOTE: If necessary, a few drops (6-7) of a lucite solution ( 0.5 mg/ml in acetone) may be added to keep residue in place. Dry under an infrared lamp for 10-20 minutes.

4. Store the planchets in a dessicator until counting.

5. Count the gross alpha and gross beta activity in a low background proportional counter.

Calculations Gross alpha / gross beta activity.

A 1sb1, -

(pCVg wet)= A BxCx DxFx2.22 BxCxDxFx2.22 Where:

A = Net alpha I beta counts (cpm)

B = Efficiency for counting alpha / beta activity (cpm/dpm)

C = Weight of sample (grams), ash or dry D = Correction factor for self absorption (See Proc. AB-02)

E* = Counting error of sample plus background Eb = Counting error of background F = Ratio of wet weight to ashed or dry weight

REFERENCES:

Radioassay Procedures for Environmental Samples, U.S. Department of Health, Education and Welfare. Environmental Health Series, January 1967.

2

EIML-AB-01 Rev. 3,07-07-04 B. Gross Alpha and/or Gross beta In Soil and Bottom Sediments Procedure

1. Weigh out accurately In a planchet no more than 100 mg.of a pulverized sample for a gross alpha assay and no more than 200 mg for a gross beta assay.

NOTE: If both gross alpha and gross beta analyses are required, do not use more than 100mg.

2. Add a few drops of water and spread uniformly over area of the planchet. Dry under a heat lamp.

NOTE: If necessary, a few drops (6-7) of a lucite solution ( 0.5 mg/ml in acetone) may be added to keep residue In place. Dry under an Infrared lamp for 10-20 minutes.

3. Store the planchets In a dessicator until counting.

4. Count the gross alpha and gross beta activity In a low background proportional counter.

Calculations' Gross alpha / gross beta activity:

E b (pCi/g dry) =

BxCxDx2.22 BxCxDx2.22 Where: 3 A = Net alpha / beta counts (cpm)

B = Efficiency for counting alpha / beta activity (cpm/dpm)

C =Weight of sample (grams)

D = Correction factor for self absorption (See Proc. AB-02)

Esb = Counting error of sample plus background Eb = Counting error of background

REFERENCES:

Radioassay Procedures for Environmental Samples, U.S. Department of Health, Education and Welfare. Environmental Health Series, January 1967, 3

- Environmental, Inc.

Midwest Laboratory i1~Du~rI700 t~lP . ~an Aiegheny Teo"fofges Co.

Landwehr Poad *NorMtrvoIL, 600Q2-2310 f (847) 5644517 ph. (847) 564-000 tax DETERMINATION OF GROSS ALPHA ANDIOR GROSS BETA IN AIR PARTICULATE FILTERS PROCEDURE NO. AP-02 Prepared by Environmental, Inc.

Midwest Laboratory Copy No.

Revised Pages Revision # Date Pa3es' Prepared by Avoroved by 0 07-11-86 3 B.Arob I N* 4RGob j 2 1 07-15-91 3

_ Reissue 08-18-04 2 any third party without the written (This procedure, or any portion thereof, shall not be reproduced In any manner or distributed to permission of Environmental, Inc., Midwest Laboratory.)

EIML-AP-02 Revision 0, 07-15-91 DETERMINATION OF GROSS ALPHA AND/OR GROSS BETA INAIR PARTICULATE FILTERS Prin ople of Method Air particulate filters are stored for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to allow for the decay of short-lived radon and thoron daughters and then counted in a proportional counter.

Apparatus Forceps Loading Sheet Proportional Counter Stainless Steel Planchets (standard 2" x 1/8")

Procedure

1. Store the filters for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the day of collection.

2. Place filters on a stainlesssteel planchet.

3.. Fill out a sample loading sheet. Fill In the date, counter number, counting time, sample Identification number, sample collection date, and initials.

NOTE: Blanks'are loaded with each batch of samples. Load the counter blank planchet as a last sample.

4. Count In a proportional counter long enough to obtain the required LLDs.

5. After counting Is completed, return the filters to the original enyelopes.

6. Submit counter printout, field collection sheet, and the loading sheet to the dark clerk for calculation.

Calculations Gross alpha (beta) concentration:

_______ 21E.ýb2E (pCIIL) = BxCx2.22A +/- b BxCx2.22 Where:

A = Net alpha (beta) count (cpm)

B = Efficiency for counting alpha (beta) activity (cpm/dpm)

C = Volume of sample E~b = Counting error of sample plus background

-Eb = Counting error of background

REFERENCES:

Radioassay Procedures for Environmental Samples, U.S. Department of Health, Education and Welfare. Environmental Health Series, January 1967, 2

"h --

• Environmental, Inc.

Midwes Laboratory PROCEDURE for COMPOSITING AIR PARTICULATE FILTERS for GAMMA SPECT4 oSCOPIC ANALYSIS PROCEDURE NO. AP-03 Prepared by Environmental Inc.

Midwest Laboratory Copy No.

Revised Paoes Revision # Date Paaes Prepared by Aporoved by 0 12-15-89 3 B. Grob L.G. Huebner 1 03-21-95 3 B. Grob L.G. Huebner 2 07-21-98 3 A. Fayman B. Grob (This procedure, or any portion thereof, shall not be reproduced In any manner or distributed to any third party without the written permission of Environmental Inc., Midwest Laboratory.)

AP-03 Rev. 2, 07-21-98 PROCEDURE FOR COMPOSITING AIR PARTICULATE FILTERS FOR GAMMA SPECTROSCOPIC ANALYSIS Principle of Method AP filters are placed in a Petri dish in chronological order, labeled and submitted to the counting room for analysis by gamma spectroscopy.

Materials Tweezers (long)

Blank filter paper -

Small Petri Dish (50 x 9 mm)

Scotch -Tape Procedure

1. 'In the Recording Book enter

• Sample ID (project)

• Sample No.

• Location

• Collection Period

• Date. Composited

2. Obtain sample numbers from Receiving Clerk.

3. Stack the envelopes with APs from each location In chronological order, starting with the earliest date onthe bottom. After you are done, flip the stack over.

4. Place blank filter paper, "fluffy" side down, in deep half of Petri dish.

5. Beginning from the top of the stack, remove each AP from its envelope and place in the Petri Dish with the deposit facing down.

6. Continue transferring AP's from envelopes intothe Petri Dish.

7. Place blank filter, "fluffy" side down, on top of APs.

8. Cap the Petri Dish using the shallow half (you may use Scotch tape to hold cap in place, (if needed).

Turn the Petri dish over.

9. On the Petri dish and each stack of glassine envelopes (each location kept together by either paperclips or rubber bands) using a black marker write:

• Sample ID

• Sample No.

• Last date of collection

• Collection Period

10. Submit the samples to the counting room.

11. After counting, samples are stored in the warehouse, according to client's requirements.

2

AP-03' Rev. 2, 07-21-98 PROCEDURE for COMPOSITING AIR PARTICULATE FILTERS FOR GAMMA SPECTROSCOPIC ANALYSIS Example

" Sample ID (project) BAP

" Sample No. 2

• Location 1675

• Last Collection Date 03-31-98

• Collection Period 1st Qtr. 1998 Blank APs First week to last week in quarter Side View Top View 3

WTELEDYNE ISOTOPES MIDWEST LABORATORY 700 LANDWEHR ROAD NORTHBROOK, ILWNOIS 80062.2310 (312) 564.07W FAX (312) 564-4517 DETERMINATION OF STABLE CALCIUM IN MILK PROCEDURE NO. TIML-CA-01 Prepared by Teledyne Isotopes Midwest Laboratory Copy No.

Revision No. Date Pages 0 .07-08-88 4 (This procedure, or any portion thereof, shall not be reproduced in any manner or distributed to any third party without the written permission of Teledyne Isotopes Midwest Laboratory.)

TIMLý-CA-O1-O1

Revision o, 07-08-88 TIML-CA-01 Determination of Stable Calcium in Milk Principle of Method Strontium, barium, and calcium are absorbed on the cation-exchange resin, then eluted with sodium chloride solution. An aliquot of the eluate is diluted to reduce the high sodium ion concentration. From this diluted aliquot, calcium oxalate is precipitated, dissolved in dilute hydrochloric acid, and the oxalate is titrated with standardized potassium permaganate.

Reagents A*nmonium hydroxide, NH4 OH: 611 Ammonium oxalate, (NH4 ) 2C2 04 .H20: 0.03N Carrier solutions:

Ba+ 2 as barium nitrate, Ba(NO)2: 20 mgBa+ 2 per2 ml Sr+2 as strontium nitrate, Sr N03)2: 20 mg Sr+ per ml Cation-exchange resin: Dowex 50W-X8 (Na+ form, 50-100 mesh)

Citrate solution: 3N (pH 6.5)

Hydrochloric acid, R-1: 6N Oxalic acid, H2C 2 04 .2H 2 : TN Potassium permanganate, KMnO 4 : 0.05N staridardized Sodium chloride, NaCI: 4N Sodium oxalate, Na2C 2 04:

Apparatus Burette Procedure

1. Follow the TIML-SR-01 or SR-07 procedures, Steps 1-10.

2. Into a 40 ml glass centrifuge tube, pipette 10 ml aliquot of the initial eluate collected in Step 10.

3. Dilute the 10 ml aliquot to approximately 20 ml with D.I. water.

4. Heat in a hot water bath. Add 5 ml of IN oxalic acid, and stir. While hot, adjust to pH 3 with 6N NH4 0H (use a pH meter) to precipitate calcium oxalate. Cool slowly to room temperature, centrifuge, and dis-card the supernate.

TIML-CA-01-02

Revision 0, 07-08-88 TIML-CA-01 Procedure (continued)

5. Thoroughly wash the precipitate and the wall of the centrifuge tube, using not more than 5 ml of 0.03N ammonium oxalate. Centrifuge, and discard the supernatant.

6. Wash the precipitate with 10 ml of hot D.I. water. Cool to room temper-ature, centrifuge, and discard the supernate. (A stirring rod may be used to agitate the. precipitate while it is -being washed. It is im-portant to remove all excess oxalic acid from the precipitate.)

7. Dissolve the precipitate in approximately 2.5 ml of 6N HCl. Heat in hot water bath for 5 minutes. -

8. Dilute the acid solution to approximately 10 ml with D.I. water.

Quantitatively transfer it to a 125 ml Erlenmeyer flask, rinsing the centrifuge tube with D.I. water.

9. Add an additional 1 ml of 6N HCI, and adjust the volume of solution to approximately 25 ml with D.I. water. Heat to near boiling.

10. While hot, titrate with standardized 0.05N KMnO 4 to the first faint pink endpoint which persists for at least 30 seconds.

Calculations Calcium (g/liter) Ax Bx C D

Where:

A= Volume of KMnO 4 solution used for titration (ml)

B= Normality of standardized KMn 4 solution (mg/ml)

C= Milli-equivalent weight of calcium (mg/meg)

D= Sample volume (ml)

Since the sample size is 10 ml and the milli-equivalent weight of calcium is 20 mg, the equation reduces to:

Calcium (g/liter) - A x B x 2 TIML-CA-01-03

Revision 0, 07-08-88 TIML-CA-01 Evaluation of Data The standard deviation of replicate analyses has been determined to be

+/-0.02 g/liter.

Reference:

Radloassay Procedures for Environmental Samples, U.S.

Department of Health, Education and Welfare. Environ-mental Health Series, January 1967.

T2IML-CA-01-04

- Environmental, Inc.

Midwest Laboratory an AMegheny Technoogies Co.

UI COFNRI3LLEUJ 700 Landwehr Road

• Northtbk, IL 60062-2310 ph. (847) 564-o700 fax (847) 64-4517 PROCEDURE FOR COMPOSITING WATER AND MILK SAMPLES PROCEDURE NO. COMP-01 Prepared by Environmental, Inc.

Midwest Laboratory Copy No.

Revision # Date Pages Preopred by AoCroved by 0 11-07-88 2 8 Grob IG Huebner Reissue 07-09-04 2 B Grob SA Cooirum (This procedure, or any portion thereof, shall not be reproduced In any manner or distributed to any third party without the written permission of Environmental, Inc., Midwest Laboratory.)

COMP-01I Reissue, 07-09-04 PROCEDURE FOR COMPOSITING WATER AND MILK SAMPLES Procedure

1. At the beginning of each composite period, (month, quarter, semi-annual), prepare a one-gallon cubitainer for a specific location and time-period.

2. Remove equal aliquots of the original samples (for example, one liter) and transfer to the prepared cubitainer.

3. When the composite Is completed, submit the sample to the receiving clerk to assign a laboratory code number.

4. Analyze according to the client requirements.

2

-Environmental, Inc.

- Midwest Laboratory an Allegheny Technologies Co. 6k 700 Landwehr Road -Northibrook, Lt 60062-2310 ph. (847) 584-0700 *fox (841) 584-451 7 j DETERMINATION OF GAMMA EMITTERS BY GAMMA SPECTROSCOPY GS-01 Prepared by Environmental Inc.

Midwest Laboratory Copy No.

Revised

. Paaes Revision # Date Paaes Prepared by Approved by Reprint 2 07-01-98 3 F. G. Shaw S. A. Coorlim 3 02-03-04 4 S. A. Coorlim B. Grob 4 02-07-07 4 S. A. Coorlim &u.

(This procedure, or any portion thereof, shall not be reproduced In any manner or distributed to any thirdpay without the written permission of Environmental Inc.. Midwest Laboratory.)

GS-01 Rev. 4, 02-08-07 DETERMINATION OF GAMMA EMITTERS BY GAMMA SPECTROSCOPY Principle of Method Samples are weighed or measured into calibrated containers and set directly on an HPGe (high-purity germanium) detector. The sample is counted for a sufficient length of time necessary to reach the required MDA (Minimum Detectable Activity). Results are decay corrected to the date of collection, where appropriate, using a dedicated computer and software.

Refer also to the procedure OP-11, "Operating Procedure for the EG&G ORTEC OMNIGAM Gamma Spectroscopy System".

Procedure A. Milk, Water. and other Liquid Samples

1. Measure with a graduated cylinder, 500 mL, 1.0 L, 2.0 L or 3.5 L of sample into a calibrated sample container (Marinelli beaker). Use the largest volume possible, based on available

-sample quantity.

2. Affix a label to the container cover with the sample number, volume, date and time of collection. Mark "1-131" if analysis for 1-131 by gamma spectroscopy is required.

3. Count for estimated time required to meet the client's specifications. Record file number, sample identification number, date and time counting started, detector number, geometry, sample size, and date and time of collection.

NOTE: Counting priorities should be based on half-life (1-131 / 8.0d, Ba/La-140 / 12.8d, etc.) and MDA requirements of the isotopes to be analyzed for. If possible, samples marked for analysis of 4 1-131 should be counted within two weeks of the collection date.

4. Stop the counting; transfer the spectrum to the disk, and print out the results.

5. Check the results for required MDAs. If the client's specifications are not met, continue the counting.

6. Once the required MDAs have been met, record the counting time.

7. Return the sample to the original container and mark with a red marker.

2

GS-01 Rev. 4, 02-08-07 DETERMINATION OF GAMMA EMITTERS BY GAMMA SPECTROSCOPY (continued)

B. Airborne Particulates

1. Place the air filters in a small Petrie dish following Procedure AP-03.

2'. Place Petrie dish (with marked side up) on the detector and count long enough to meet the client specifications. Record the file number, sample identification number, date and time counting started, detector number, geometry, sample size, and date and time collected.

NOTE: When counting individual filters, place in a labeled Petrie dish with active (deposit) side up.

3. Stop counting and transfer spectrum to the disk. Print out and check the results before removing the sample. If client specifications are not met, continue counting.

4. Once the required MDAs have been met, record the counting time.

5. Replace air filters in the original envelopes for storage or further analyses.

C. Other Sample Types Soil, Sediments, Vegetation, Fish, Prepared Foods and other solid sample types are packed and weighed in the prep lab and delivered to the counting room.

1. Place the sample on the detector and count long enough to meet client's technical specifications.. Record the file number, sample identification number, date and time counting started, detector number, geometry, sample size, and date (and time, if applicable) of collection.

NOTE: Counting priorities should be based on half-life (1-1314 8.0d, Ba/La-140 / 12.8d, etc.) and MDA requirements of the Isotopes to be analyzed for. If possible, samples marked for analysis of 4 1-131 (vegetations, grasses, et al.) should be counted within two weeks of the collection date.

-2. Stop the counting and -transfer the spectrum to the disk. Print out and check the results before removing the sample. If client specifications are not met, continue counting.

3. Once the required MDAs have been met, record the counting time. Mark the container with a red marker and return to the prep lab for transfer to storage or further analyses.

D. Charcoal Cartridges For counting charcoal cartridges, follow Procedure 1-131-02, 1-131-04 or 1-131-05.

3

GS-01 Rev. 4, 02-08-07 DETERMINATION OF GAMMA EMITTERS BY GAMMA SPECTROSCOPY (continued)

CALCULATIONS:

Activity (pCi/L) + the two sigma error for a select gamma peak, region of interest (ROI) =

A 2E 2sb+E 2.22xCxDxGxY 2.22xCxDxGxY where:

A = Net cpm, (ROI)

C = Volume of sample (liter)

G = Efficiency (cpmrldpm)

Y = Abundance (%of gamma disintegrations)

Esb = Counting error of sample plus background Eb = Counting error for background.

e=t or e -0.693 x*

D = Correction for decay to the time of collection tY where:

t = elapsed time from the. time of collection to the counting time (in days) tY2 = half-life MDA (Minimum Detectable Activity) is calculated using the RISO method.

MDA = 4.65 x LT 2.22xCxDxGxY where:

B = Background (cpm)

LT = Live time (min) 4

- Environmental, Inc.

Midwest Laboratory an Allegheny Technologles Co.

DETERMINATION OF 1-13l11N MILK AND WATER BY ANION EXCHANGE (BATCH METHOD)

PROCEDURE NO. 1-131-01 Prepared by Environmental Inc.

Midwest Laboratory Copy No..

Revised Panes Revision # Date Pages brove,,2x AP 9 Reissue - 4 03-16-04 5 sALA..A _  ?+/-

(This procedure, or any portion thereof. shall not be reproduced In any manner or distributed to any third party without the written permission of Environmental Inc., Midwest Laboratory.)

1-131-01 Rev. 4, 03-16-04 Revision History Pages Revision # Date Panes Prepared by Approved by 0 M6-12-85 6 B.Grob L.G. Huebner 2.3.4.L5 1. 04-10-91 L B.Grab L.G. Huebner 42 4-.

23 - 08-14-92 09-24-92 66 B. Grob B, Grob L.G. Huebner L.G. Huebner DETERMINATION OF 1-131 IN MILK AND WATER BY ANION EXCHANGE (BATCH METHOD)

Principle of Method After samples have -been treated to convert all iodine In the sample to a common oxidation state, the iodine is isolated by solvent extraction or a combination of ion exchange and solvent extraction steps.

Iodine, as the iodide, is concentrated by adsorption on an anion resin. Following a NaCI wash, the iodine is eluted with sodium hypochlorite. Iodine in the Iodate form is reduced to 12 and the elemental iodine extracted into CHCI3 , back-extracted Into water then finally precipitated as palladium iodide.

Chemical recovery of the added carrier is determined gravimetrically from the Pdl2 precipitate. 1-131 Is determined by beta counting the Pdl2 .

Reagents Anion Exchange Resin Dowex Ux8 (50-100 mesh), chloride form Chloroform, CHCI3 , reagent grade Hydrochloric Acid: HCL: 1N Hydrochloric Acid: HCL: 3N Wash Solution: H20 - HN03 - NH 2OH HCL, 50 mL H20; 10 mL IM- NH2OH-HCI; 10 mL concentrated HNO 3 Hydroxvlamine Hydrochloride, NH20H HCI - I M Nitric Acid, HNO 3 - concentrated, 6N Palladium Chloride, PdCI2, 7.2 mg Pd /mL (1.2 g PdClj 100 mL of 6N HCI)

Sodium Bisulfite, NaHSO,- 1M Sodium Chloride, NaC!- 2M Sodium Hycochlorite, NaOCI - 5% (Clorox)

Sodium Hydroxide, 12N NaOH Potassium Iodide, KI, ca. 29 mg KI/mL (See Proc. CAR-01 for preparation)

Speclal Apciaratus Chromatographic Column, 20mrm x 150mm (Reliance Glass Cat #R2725T)

Heat Lamp Filter Paper, Whatman #42, 21rmm Mylar pH Meter Polyester Gummed Tape, 11/12, Scotch #853 2

Vacuum Filter Holder, 2.5 cm filter area 2

1-131-01 Rev. 4, 03-16-04 Parta Water Samples:

NOTE: Samples containing suspended matter should be filtered before proceeding to Step 1.

1. Transfer 2 liters (if available) of clear sample to the beaker. Add 1.00 mL of standardized iodide carrier and 5 mL of 5% sodium hypochlorite to each sample. -

2. Add a clean magnetic stirring bar to each sample beaker. Stir each sample for 20 minutes.

3. Add 25 mL of IM hydroxylamine hydrochloride and stir for 2 minutes

4. Add 10 mL of I Msodium bisulfite.

5.' Adjust pH to 6.5 using 12N NaOH or 6N HNO 3.

6. Continue to Step. 10 Milk Samples:

7. Transfer 2 liters (if available) of clear sample to the beaker. Add 1.00 mL of standardized iodide carrier to each sample.

8. Add a clean magnetic stirring bar to each sample beaker. Stir each sample for 5 minutes or longer on a magnetic stirrer. Allow sample to equilibrate at least 1/2 hour. If a milk sample is curdled or lumpy, vacuum filter the sample through a Buchner funnel using a cheesecloth filter. Wash the curd thoroughly with deionized water, collecting the washings with the filtrate. Pour the filtrate back into the original washed and labeled 4 liter beaker and discard the curd.

9. Continue to Step. 10

10. Add approximately 45 grams of Dowex Ix8 (20-50 mesh) anion resin to each sample beaker and stir for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Allow the resin to settle for 10 minutes.

11. Gently decant and discard the milk or water sample. Take care to retain as much resin as possible in the beaker. Add approx. I liter of deionized water to rinse the resin, allow to settle 2 minutes, and pour off the rinse.

12. Using a deionized water wash bottle, transfer the resin to the column marked with the sample number. Allow resin to settle 2 minutes and drain the standing water. Wash resin with 100 mL of 2M NaCI.

13. Measure 50 mL 5% sodium hypochlorite in a graduated cylinder. Add sodium hypochlorite to column in 10-20 mL increments, stirring resin as needed to eliminate gas bubbles and maintain flow rate of 2 mLlmin. Collect eluate in 250 mL beaker and discard the resin.

3

1-131-.01 Rev. 4, 03-16-04 Part B Iodine Extraction Procedure CAUTION: Perform following steps in the fume hood.

1. Acidify the eluate from Step 6 by adding ca. 15 mL of concentrated HNO 3 to make the sample 2-3 N in HNO3 and transfer to 250 mL separatory funnel. (Add the acid slowly with stirring until the vigorous reaction subsides).

2. Add 50 mL of CHCI3 and 10 mL of 1M hydroxylamine hydrochloride (freshly prepared). Extract iodine into organic phase (about 2 minutes equilibration). Draw off the organic phase (lower phase) Into another separatory funnel.

3. Add 25 mL of CHCI3 and 5 mL of IM hydroxylamine hydrochloride to the first separatory funnel and again equilibrate for 2 minutes. Combine the organic phases. Discard the aqueous phase (Upper phase) If no other analyses are required. If Pu, U or Sr Is required on the same sample aliquot, submit the aqueous phase and data sheet to the appropriate laboratory section.

4. Add 20 mL H20-HN0 3-NH 2OH HCI wash solution to the separatory funnel containing the CHCI3 .

Equilibrate 2 minutes. Allow phases to separate and transfer CHCI3 (lower phase) to a clean separatory funnel. Discard the wash solution.

5. Add 25 mL H2O and 10 drops of IM sodium bisulfite. (freshly prepared) to the separatory funnel containing the CHCI8 . Drain aqueous phase (upper phase) into a 100 mL beaker. Proceed to the precipitation of Pdl2 .

Part C Precipitation of Palladium Iodide CAUTION: AMMONIUM HYDROXIDE INTERFERES WITH THIS PROCEDURE

1. Add 10 mL of 3N HCI to the aqueous phase from the Iodine extraction procedure in Step 5.

2. Place the beaker on a stirrer-hot plate. Using the magnetic stirrer, boil and stir the sample until it evaporates to 30 mL or begins to turn yellow.

3. Turn the heat off. Remove the magnetic stirrer, rinse with deionized water.

4. Add, dropwise, to the solution, 2.0 mL of palladium chloride.'

5. Cool the sample to room temperature. Place the beaker with sample on the stainless steel tray and put In the refrigerator overnight.

.6. Weigh a clean 21mm Whatman No. 42 filter which has been dried under the heat lamp.

7. Place the weighed filter in the filter holder. Filter the sample and wash the residue with water and then with absolute alcohol.

8. Remove filter from filter holder and place Itin a labeled Petri dish.

9. Dry under the lamp for 20 minutes.

4

1-131-01 Rev. 4, 03-16-04 Precipitatlon of Palladium Iodide (continued)

10. Weigh the filter with the precipitate and calculate carrier recovery.

11. Cut a 1112" strip of polyester tape and lay it on a clean surface, Gummed side up. Place the filter, precipitate side up, in the center of the tape.

12. Cut a 1112" wide piece of mylar. Using a spatula to press it in place, put It directly over the precipitate and seal the edges to the polyester tape. Trim to about 5mm from the edge of the filter with scissors.

13. Mount the sample on the plastic disc and write the sample number on the back side of the disc.

14. Count the sample on a proportional beta counter.

Calculations Calculate the sample activity using computer program 1-131.

1-131 concentration (pCi/L):

A 242FE2 2.22 xBxCxDxR 2.22xBxCxDxR where:

A = Net cpm, sample B = Efficiency for counting beta 1-131 (cpm/dpm)

C = Volume of sample (liters)

At D = Correction for decay to the time of collection = e-where t = elapsed time from the time of collection to the counting time (in days)

Esb = Counting error of sample plus background Eb = Counting error of background R = Carrier recovery 2.22 = dpm/pCi

REFERENCE:

"DeterminatiOn of 1-131 by Beta-Gamma Coincidence Counting of PdI2". Radiological Science Laboratory. Division of Laboratories and Research, New York State Department of Health, March 1975, Revised February 1977.

5

- Environmental, Inc.

Midwest Laboratory FUDIU DETERMINATION OF AIRBORNE 1-131 IN CHARCOAL CARTRIDGES BY GAMMA SPECTROSCOPY PROCEDURE NO. 1-131-02 Prepared by Environmental Incorporated Midwest Laboratory Copy No.

Revised,-

Revision # Date Paqes d Pleaes 1-4 Reissue 05-07-04 4A pa~ th* the wrltten (This procedure, or any portion thereof, shall not be reproduced Inany manner or distributed to any third permission of Environmental, Inc., Midwest Laboratory.)

1-131-02 Reissue, 05-07-04 DETERMINATION OF AIRBORNE 1-131 IN CHARCOAL CARTRIDGES BY GAMMA SPECTROSCOPY Principle of Method A charcoal cartridge Is placed on the detector (face loaded) and counted for 1-131 by gamma spectroscopy.

Alternatively a abatch" method may be used. Five or six cartridges are mounted (face loaded) in a modified Marinelli holder and placed on the gamma detector. The batch Is typically counted overnight.

The 0.36 MeV peak is used to calculate the concentration at counting time.

Procedure NOTE: Cartridges should be counted for 1-131 within 8 days (one half-life) of the collection date. Count as soon as possible upon receipt.

Individual Cartridge Counting

1. Place the charcoal cartridge on the detector with the rim facing the detector and the air flow Indicator (arrow) pointing away from the detector, (Fig. 1). Count long enough to meet the required Lower Limit of Detection (LLD).

2. Calculate the concentration of 1-131 (pCI/rm). Input lab code, volume and date and time of collection (use the midpoint of collection period). Notify the supervisor immediately of any positive result Batch Method

4. Load the charcoal cartridges In the modified Marinelli holder with the rim facing the detector and the air flow Indicator (arrow) pointing away from the detector (Fig. 2). Use a rubber band.to hold the side mounted cartridges in place.

5. Place the holder on the detector and count long enough for the lowest volume cartridge to meet the required Lower Limit of Detection (LLD). Batch charcoals are typically counted overnight.

6. Calculate the concentration of 1-131 at the time of counting and a volume of 1.0 in. Submit printout to data clerk for final calculations without delay.

Note: A batch method is used for screening only. If 1-131 activity Is detected, each cartridge from the batch must be analyzed individually.

2

1-131-02 Reissue, 05-07-04 Calculations:

A, = 1-131 concentration "A

(pCi/sample) = 2.22 x B, x B2 (at counting time) -,

where:

A = Net count rate of 1-131 in the 0.36 MeV peak (cpm)

B1 = Efficiency for the 1-131 In0.36 MeV peak (cpm/dpm)

B2 = retention efficiency for the 1-131 cartridge.

2.22 = dpm/pCi 1-131 concentration at the time of collection:

3 2j1Eý2 + E, (pCum) dx1 CD CxD where:

C = Volume of sample (Mi)

D = Correction for decay to the time of collection = e 0.693 x t" -0.6862t Exp 8.04 where:

t = the elapsed time from the time of collection to the counting time (in days)

E = Counting error of sample plus background Fb= Counting error of background 3

I ( j~i r - , I I r , - - ( -  !

C Rubber Band CartrIdge rim Air flow indicator Marinelli holder HPGe detector 0 C'

S' C

Figure 2. Face loading of cartridges In C Figure 1. Face loading of the charcoal cartridge. a batch.

C C

-Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road

• Northbrook, L 60062-2310

-ph.(847) 584-0700 -fax (847)564-4517 SAMPLE PREPARATION EIML-SP-01 Prepared by Environmental, Inc.

Midwest Laboratory Copy No.

Revision # Date Paces Prepared by Approved by 5

6 95-07-02

.01-26-04 14 9

S. A. Coorlim S. A. Coorlim B.bcrbb (This procedure, or any portion thereof, shall not be reproduced in any manner or distributed to any third party without the written permission of Environmental, Inc., Midwest Laboratory.)

EIML-SP-01 ReV. 6,01-26-04 TABLE OF CONTENTS Page Principle of Method ..................................... ......................................... I........................................................ 3 Reagents ................................................................................................................................ 3 Apparatus ...................................................................................................................................................... 3 Procedure for Packing Counting Containers ............................................................................................ 4 A. Vegetation (Fruits, Vegetables, Grass) and Cattle Feed (Hay, Silage) .......................................... 5 B. Slim e and Aquatic Vegetation ....................................................................................................... 5 C. Drying and Ashing, Vegetation Samples ................ ...................................................................... 5 D. Fish ............................................................................... I...................................................................... 6 E. W aterfowl, Meat, and W ildlife ........................................................................................................ 6 F. Drying and Ashing, Fish and Meat ............................................................................................... 6 G. Eggs ..................................................................................................................................................... 7 H. Bottom Sedim ents and Soil ............................................................ .............................................. 7 I. Milk........................................................................................................................................................ 8 J. Dry Foods (Powdered Milk, Infant Form ula, Anim al Feed) ............................................................ 8 K. Feces. .................................................................................................................................................. 9 L. Bottom Sediments and Soil, Analysis for Ra-226 by Gamma Spectroscopy .................................. 9 2

EIML-SP-01 Rev. 6, 01-26-04 SAMPLE PREPARATION Principle of Method Different classes of samples require different preparations. In general, food products are prepared as for home use, while others are dried and ashed as received.

Reagents Formaldehyde Apparatus Balance Ceramic Dishes Counting Containers Cutting Board Drying Oven Drying Pans Grinder High Temperature Marking Pen Knives Labels Muffle Furnace Plastic Bags Pulverizer Scissors Spatulas 3

EIML-SP-01 Rev. 6. 01-26-04 PROCEDURE FOR PACKING STANDARD CALIBRATED COUNTING CONTAINERS A. 1.0, 2.0, 3.5 L: Pour 1.0, 2.0, or 3.5 liters of water into corresponding container. Mark the level and empty the container. Fill with the sample to the mark, except for grass. Pack as much as will fit into the container.

B. 250 mL, and 500 mL: Fill to the rim on the inside wall, which Is 1/4" from the top.

C. 4 oz: Fill to the 100 mL mark.

Notes to Procedures:

1. Pack sample containers tightly. For soil, sediments or other dried samples, make sure samples are leveled.

2. A few mL. of formaldehyde may be added to wet samples to prevent spoilage.

3. For tritium analysis, transfer approximately 100 g of wet sample to a 4 oz. container. Label with the sample number and seal.

4. If a gamma scan Is the only required analysis, the drying and ashing steps are skipped.

Transfer the samples to a plastic bag, seal, label, and store In a cooler or freezer until disposal.

5.- If there is sufficient quantity, use surplus sample for drying and ashing instead of waiting for gamma scanning to be completed.

6. US Ecology Inc. samples: record total weight received.

7. US Ecology Inc. and Maxey Flats samples are DRIED before gamma spectroscopic analysis.

8. If 1-131 analysis is required, the sample must be prepared and submitted to the counting room immediately. Mark "i-131" on the tape.

4

EIML-SP-01 Rev. 6, 01-26-04 A. Vegetables. Fruits, Grass, Green Leafy Vegetation and Cattle Feed Note: Do not wash the samples.

1. Cut vegetables and hard fruits into small pieces (about 1/4" cubes). Mash soft fruits. Cut grass and green leafy vegetation into approximately 1"2" long stems. Pack cattle feed and silage as is. Use larger containers ifsufficient amount of sample is available.

2. Transfer sample to a standard calibrated container. Use the largest size possible for the amount of sample available. Pack tightly but DO NOT FILL ABOVE THE MARK. Record the wet weight.

3. Seal with cover. Attach label to the cover recording the sample number, weight, and collection date.

4. Submit to the counting room for gamma spectroscopic analysis without delay or store in a cooler, (for short period), until counting.

5. Proceed to Drying and Ashing, Vegetation Samples B. Slime and Aquatic Vegetation

1. Remove any foreign material. Place the sample in a sieve pan and wash until all sand and dirt is removed (turn the sample over several times). Squeeze out the water by hand.

2. Place the sample in a standard calibrated container. Use the largest size possible for the amount of sample available. Weigh and record wet weight. DO NOT FILL ABOVE THE RIM.

6. Seal with cover. Attach label to the cover recording the sample number, weight, and collection date.

4. Submit to the counting room without delay. Slime decomposes quickly, even with formaldehyde. If gamma scanning must be delayed, freeze.

5. Proceed to Drying and Ashing, Vegetation Samples C. Dryingq and Ashing, Vegetation Samoles

1. After gamma scan is complete, transfer the sample to a drying pan and dry at 1100C.

2. Cool, weigh, and record dry weight.

3. Transfer to a tared ceramic dish, and record dry weight for ashing. Ash in a muffle fumace by gradually Increasing the temperature to 6000C.

NOTE: If ashing is incomplete (black carbon remains), cool the dish, crush the ash with spatula, and continue ashing overnight at 600°C. It is not necessary to increase the temperature gradually.

4. Cool and weigh the ashed sample and record ash weight. Grind and sieve through a 30 mesh screen. Transfer to a 4 oz. container, seal, and label with sample number, weight, analyses required, and date of collection. The sample is now ready for analysis.

5

EIML-SP-01 Rev. 6, 01-26-04 D. Fish

1. Wash the fish.

2. Fillet and pack the fish immediately (to prevent. moisture loss) in a 250 mL, 500 mL, or 4 oz.

standard calibrated container. Use 500 mL size if enough sample is available. 'DO NOT FILL ABOVE THE RIM. Record the wet weight.

3. Proceed to Step 2, Waterfowl, Meat and Wildlife Samples below.

E.-. Waterfowl. Meat, and Wildlife

1. Skin and clean the animal. Remove a sufficient amount of flesh to fill an appropriate standard calibrated container (500 mL, 250 mL, or 4 oz). Weigh without delay (to prevent moisture loss). DO NOT FILL ABOVE THE RIM. Record the wet weight.

2. If bones are to be analyzed, boll remaining flesh and bones In water for about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Clean the bones. Air dry, weigh, and record as wet weight. Dry at 11 OC. Record dry weight. Ash at 8000C, cool, weigh,, and record the ash weight. Grind to a homogeneous sample. The sample Is ready for analysis.

3. Seal with cover. Attach label to the cover recording the sample number, weight, and collection date.

4. Submit to the counting room for gamma spectroscopic analysis without delay or store in a refrigerator, (for short period), until counting.

5. Proceed to Drying and Ashing, Fish and Game Samples F. Drying and Ashingi, Fish and Meat Samples

1. After gamma scan is complete, transfer the sample to a drying pan and dry at 110°C.

2. Cool, weigh, and record dry weight.

3. Transfer to a tared ceramic dish. Record dry weight for ashing.

4. Ash in a muffle furnace by gradually increasing the temperature to 4500C. If considerable amount of carbon remains after overnight ashing, the ash should be crushed with a spatula and placed back In the muffle furnace until ashing Is completed.

5. Cool and weigh the ashed sample and record the ash weight Grind and sieve through a 30 rpesh screen. Transfer to a 4 oz. container, seal, and record sample number, weight, analyses required, and date of collection. The sample is now ready for analysis.

6

IJ EIML-SP-01 Rev. 6, 01-26-04 G. E9aS

1. Remove the egg shells and mix the eggs with a spatula.

2. Transfer the mixed eggs to a standard calibrated 500 mL container. Record the wet weight. DO NOT FILL ABOVE THE RIM.

3. Seal with cover. Attach label to the cover recording the sample number, weight, and collection date.

4. Submit to the counting room for gamma spectroscopic analysis without delay or store in a refrigerator, (for short period), until counting.

5. After the gamma scan is complete, transfer the sample to a drying pan and dry at 1100C..

6. Cool, weigh, and record dry weight.

7. Transfer to tared ceramic dish. Record dry weight for ashing.

8. Cool and weigh the ashed sample and record the weight. Grind and sieve through a 30 mesh screen. Transfer to a 4 oz. container, seal, and record sample number, weight, analyses required, and date of collection. The sample is now ready for analysis.

9. Store the remaining dry sample in a plastic bag.

H. Bottom Sediments and Soll

1. Remove rocks, roots, and any other foreign materials.

2. Place approximately I kg of sample on the drying pan and dry at 1100C.

3. Seal, label, and save remaining sample.

4. Grind or pulverize the dried sample and sieve through a No. 20 mesh screen.

5. For gamma spectroscopic analysis, transfer sieved sample to a standard calibrated 500 mL, 250 mL, or 4 o7. container. DO NOT FILL ABOVE THE RIM. Record dry weight.

6. Seal with cover. Attach label to the top of the cover and record the sample number, weight, and date of collection.

7. Submit to the counting room for gamma spectroscopic analysis without delay.

8. For gross alpha and beta analysis transfer 1-2 g of sample to a 4 oz. container, seal and label with the sample number. For other analysis (i.e., radiostrontium, transuranics etc.,) transfer to a ceramic dish and ash in a muffler fumance at 6000C. Cool and transfer to a 4 oz. container, seal and label with the sample number.

9. Store the remaining sieved sample in a plastic bag.

10. After the gamma scan is complete, transfer the sample to a plastic bag, seal, label, and store until disposal.

7

EIML-SP-01 ERev. 6, 01-26-04 Milk

1. Transfer 25 mL of milk for gross alpha and beta analysis or 100-1000 mL for other analysis into a glass beaker.

2. Dry at 11V0 C.

3. Ash in the muffler fumance by gradually increasing the temperature to 6000C. If a considerable amount of carbon remains (black), cool the beaker, crush the ash with a -spatula and continue ashing until completed (white or light gray in color).

4. Cool and weigh the ashed sample and record the ash weight. Grind and transfer to a 4oz.

container, seal and record the sample number. The sample is now ready for analysis.

J. Dry Foods (Powdered Milk. Infant Formula, Animal Feed)

For gamma isotopic analysis of powdered samples, no preparation is necessary. The samples are transferred to a Marinelli beaker as received.

1. Tare a 250 or 500 ml. Marinelli beaker (with lid), depending on sample size available. Record the tare weight.

2. Transfer sample to the beaker. (Refer to pg. 4, 'PROCEDURE FOR PACKING STANDARD CALIBRATED COUNTING CONTAINERS")

3. Attach a label to the top of the cover and record the sample number, weight and collection date.

4. Submlt to the counting room without delay.

5. Submit to the counting room for gamma spectroscopic analysis without delay.

6. For gross alpha and beta analysis transfer 1-2 g of sample to a 4 oz. container, seal and label with the sample number. For other analysis (i.e., radiostrontlum, transuranics etc.) transfer to a ceramic dish and ash In a muffle furnance at 6000C. Cool and transfer to a 4 oz. container, seal and label with the sample number.

8

EIML-SP-01 Rev. 6, 01-26-04 K. Feces NOTE: Perform Transfer operation in the hood. Wear new plastic gloves and face mask.

1. Take a 600 mL beaker, clean acid etched area and write sample # using HI-Temp marker.

2. Cover the beaker with parafilm and weigh. Record the weight.

3. Transfer the whole sample to the beaker using a new plastic spoon.

4. Cover the beaker with the same parafilm and weigh. Record total weight.

5. Transfer the beaker to the drying oven, remove parafilm and dry the sample overnight at 1100 C.

6. In the morning, turn oven off. Let the exhaust fan run until sample cools to room temperature.

7. Transfer beaker to the muffle furnace. Set temperature to 175 0 C. Gradually increase the temperature to 450 0C and ash the sample overnight.

NOTE: In the morning, carefully open the door and visually inspect the sample. Do not touch or remove the beaker from the furnace. If ashing is incomplete, (black carbon remains), continue ashing for another 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or until the ash Is grey-white.

8. Once ashing is complete, turn the temperature off. Let the exhaust fan run until beaker Is cool.

9. Remove the beaker from the furnace and cover with parafilm. The sample is ready for analysis.

NOTE: Digest the whole ash sample in the same beaker before taking aliquot for analysis. Do not weigh the beaker.

L. Bottom Sediments and Soil. Analysis for Ra-226 by Gamma Spectroscopy

1. Remove rocks, roots and any other foreign materials.

2. Place approximately 1 kg of sample in a drying pan and dry at 11000. Save any remaining sample.

3. Grind or pulverize the dried sample and sieve through a No. 20 mesh screen.

4. Transfer sieved sample to a standard calibrated 500 mL or 250 mL container.

DO NOT FILL ABOVE THE RIM. Record dry weight

5. Seal with cover and electrical tape. Attach label to the top of the cover and record the sample number, weight, and date of collection and date and time the container was sealed.

6. Deliver to counting room for gamma spectroscopic analysis. (The sample Is stored for a minimum of 20 days to allow Pb-214 to come to equilibrium with Ra-226. The Pb-214 peak is then used to calculate the Ra-226 concentration.)

7. Store the remaining sieved sample in a plastic bag for possible future reanalysis.

8. After the gamma scan is completed, transfer sample to a plastic bag, label- and store until disposal.

9

-- K Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

DETERMINATION OF SR-89 AND SR-90 IN WATER (CLEAR OR DRINKING WATER)

PROCEDURE NO. SR-02 Prepared by Environmental Inc.

Midwest Laboratory Copy No.

Revised Pa es Revision # Date Paqes Prepared by Approved by 0 07-23-86 8 J. Kattner Reissue 12-15-04 6 SA Coorlim (This procedure, or any portion thereof, shall not be reproduced in any manner or distributed to any third rthout the written permission of Environmental Inc., Midwest Laboratory.)

SR-02 Reissue, 12-15-04 Determination of Sr-89 and Sr-90 In Water Principle of Method The acidified'sample of. clear water with stable strontium, barium, and calcium carriers is treated with oxalic acid at a pH of 3.0 to precipitate insoluble oxalates. The oxalates are dissolved in nitric acid, and strontium nitrate is separated from calcium as a precipitate in 70% nitric acid. The residue is purified by adding iron and rare earth carriers and precipitating them as hydroxides. After a second strontium nitrate precipitation from 70% nitric acid, the nitrates are dissolved in acid with added yttrium carrier and are stored for ingrowth of yttrium-90. The yttrium is again precipitated as hydroxide and separated from strontium with the strontium being in the supemate. Each fraction is precipitated separately as an oxalate (yttrium) and carbonate (strontium) and collected on No. 42 (2.4 cm) Whatman filter for counting.

Reagents Ammonium acetate buffer: pH 5.0 Ammonium hydroxide, NH40H: concentrated (15N), 6N

.Ammonium oxalate, (NH4)2 C2 04.H20: 0.5%w/v Carrier solutions: ÷Z ÷2 Ba as barium nitrate, Ba(NO3 )2 : 20mg Ba per mL

+2 +2 Ca+2 as calcium nitrate, Ca(NO 3 )2 .H 2O: 40 mg Ca per mL Sr as strontium nitrate, Sr (NO3)2:20 mg Sr 2 per mL

+3.(  : m+3 Y at yttrium nitrate, Y(N0 3)3: .10Mg Y per mL Hydrochloric acid, HCI: concentrated (3N)

Nitric acid, HNO 3 : Fuming (90%), concentrated (16N), 6N Oxalic acid, H2C2O2 .2H20: Saturated at room temperature+3

+3 +4 Scavenger solutions: 20 mg Fe per mL, 10mg each Ce and Zr per mL Fe +3 as ferric chloride, FeCl3 .H2 0 Ce as cerous nitrate, Ce(NO3 )3 .6H2 0

+4 Zr as zirconyl chloride, ZrOCI2.8H 2 0 Sodium carbonate, Na2C03: 3N, 0.N Sodium chromate, Na2CrO 4: 3N Apparatus Analytical balance Low background beta counter pH meter 2

SR-02 Reissue, 12-15-04 Determination of Sr-89 and Sr-90 In Water Procedure

1. Measure 1 liter of acidified water in a 2 liter beaker.

NOTE: Ifthe sample contains foreign matter, such as sand, dirt, etc., filter through a 47mm glass fiber filter using suction flask.

2. To acidified clear water in a 2 liter beaker, add I mL of strontium carrier solution, I mL barium carder solution, and If necessary, 1 mL of calcium carrier solution. (Improved precipitation may be obtained by adding calcium to soft waters.) Stir thoroughly, and while stirring add 125 mL of saturated oxalic acid solution.

3. Using a pH meter, adjust the pH to 3.0 with 15N NH4OH and allow the precipitate to settle for 5-6 hours or overnight.

4. Decant to waste most of the supemate (liquid) and transfer the precipitate to a 250mL centrifuge bottle using deionized water.

t Discard the supernate to waste.

5. Dissolve the precipitate with 1OmL of 6N HNO 3 and transfer to a 250mL beaker. Then use 20mL of 16N HNO 3 to rinse the centrifuge tube and combine it to the solution in the 250mL beaker.

6. Evaporate the solution to dryness. Cool; then add 5OmL 16N HNO 3 and repeat the acid addition and evaporation until the residue is colorless.

7. Transfer the residue to a 40mL centrifuge tube, rinsing with a minimum volume of 16N HNO3.

Cover with parafilm and cool in an ice bath. Centrifuge at 1500-1800 rpm for 10 minutes, and discard the supernate to waste.

8. Dissolve the precipitate in 5mL of 6N HNO3 and then add 30mL of fuming nitric acid. Cover with parafilm , cool in the ice bath, centrifuge, and discard the supernate to waste,

9. Dissolve the nitrate precipitate in about 10mL of deionized water (perform under the hood). Add 1mL of scavenger solution. Adjust the pH of the mixture to 7 with 6N NH4OH. Heat in hot water bath for 10 minutes, stir, and filter through a Whatman.No. 541 filter into another 40mL centrifuge tube. Discard the mixed hydroxide precipitate (filter paper).

10. To the filtrate, add 5 mL of ammonium acetate buffer. Adjust pH with 3N HNO 3 or NH40H to pH 5.5.

NOTE: The pH of the solution at this point is critical.

Add dropwise, while stirring, I mL of 3N Na 2CrO4 solution, stir, and heat in a water bath.

11. Cool and centrifuge. Decant the supemate into another 40mL centrifuge tube. (Save the precipitate for Ba analysis if needed.)

12. Heat the supernate in a water bath. Adjust the pH to 8-8.5 with NH4OH. With continuous stirring, cautiously add 5 mL of 3N Na 2CO 3 solution. Heat gently for 10 minutes. Cool, centrifuge, and decant the supernate to waste. Wash the precipitate with 0.1N Na2C3.. Centrifuge again and decant the supernate to waste.

13. Dissolve the precipitate In no more than 4mL of 3N HNO3. Then add 20-3OmL of fuming HNO 3, cover with parafilm, cool in a water bath, and centrifuge. Decant and discard the supemate.

3

SR-02 Reissue, 12-15-04 Determination of Sr-89 and Sr-90 in Water Procedure (continued)

14. Repeat Step 13. RECORD THE TIME AND DATE AS THE BEGINNING OF YTTRIUM-90 -,

INGROWTH.

15. Dissolve precipitate in a 4mL of 6N HNO 3 and add I mL of yttrium carrier solution.

16. Cover with parafilm and store for 7-14 days.

NOTE: At this point, the sample can be transferred to a glass scintillation vial for ingrowth storage. Use several portions of 6N HNO 3 (a total of not more than 4mL); then add 1mL yttrium carrier to the vial.)

Separation NOTE: If. the sample was stored in the scintillation vial, transfer back into 40mL centrifuge tube using a few drops of 6N HNO 3 as a rinse.

1. After storage (ingrowth period), heat the 40mL centrifuge tube containing the sample in the hot water bath (approximately 90°C) for 10 minutes.

2. Adjust pH to 8 with NH40H, stirring continuously.

3. Cool in a cold water bath and centrifuge for 5 minutes.

4. Decant the supernate into a 40mL centrifuge tube marked with the sample number and "SR-89."

RECORD THE DATE AND TIME OF DECANTATION as the end of Y-90 ingrowth in Sr fraction and the beginning of its decay in Y-90 fraction..

5. Redissolve the precipitate by adding 3-4 drops of 6N HCI and add 5-10mL of DI water while stirring.

6. Repeat Steps 1, 2, and 3.

7, Combine supernate with the one in Step 4.

4

SR-02 Reissue, 12-15-04 Determination of Sr-89 and Sr-90 in Water Determination A. Strontium-90 (Yttrium-90)

1. Add 3 drops of 6N HCI to dissolve the precipitate; then add 5-10mL of water. Heat in a water bath at approximately 900C. Add lmL of saturated oxalic acid solution dropwise with vigorous stirring.

Adjust to a pH of 2-3 with NH40H. Allow the precipitate to digest for about an hour.

NOTE: Do Part "B" while precipitate is digesting,

2. Cool to room temperature in a cold water bath. Centrifuge for 10 minutes and decant most of the supernate. Filter by suction on a weighed 2.5cm filter paper. Wash the precipitate with water and alcohol.

3. Dry the precipitate under the lamp for 30 minutes. Cool and weigh. Mount and count without delay in a proportional counter. (See Part C for mounting.)

B. Strontium-89 (Total Strontium)

1. Heat the solution from Step 7 in water bath.

2. Adjust the pH to 8-8.5 using NH4OH.

3. With continuous stirring, add 5mL of 3N Na2CO3 solution. Stir until precipitate appears. Heat gently for 10 minutes.

4. Cool and filter on a weighed No. 42 (2.4cm) Whatman filter paper.

5. Wash thoroughly with water and alcohol.

6. Mount and count without delay its beta activity as "total radiostrontium" in a proportional counter.

C. Filterinq and Mounting

1. Place filters under heat lamps for 30 minutes before weighing.

2. Use an analytical balance for weighing (accuracy 0.01 mg).

3. Label a clean petri dish with the weight of the filter paper. (After samples are filtered, the filter paper will again be dried and weighed to determine weight of precipitate before mounting.)

4. Mount weighed filter paper and precipitate on nylon disc using 1" transparent tape to hold filter paper and 2" mylar foil placed over precipitate and held In place with slip-ring. Trim off excess mylar foil and place the mounted sample in a labeled petri dish.

5. Fill out corresponding loading sheets and place samples in counting room.

5

SR-02 Reissue, 12-15-04 Determination of Sr-89 and Sr-90 in Water Calculations Part A Strontium-90 Concentration (pCi/liter) = A BCDEF Where:

A = Net beta rate of yttrium-90 (cpm)

B = Recovery of yttrium carrier C = Counter efficiency for counting yttrium-90 or yttrium oxalate mounted on a 2.4cm diameter filter paper (cpm/pCi)

D = Sample volume (liters)

E = Correction factor e-Xt for yttrium-90 decay, where t is the time from the time of decantation (Step 4, Separation) to the time of counting F = Correction factor 1-ext for the degree of equilibrium attained during the yttrium-90 ingrowth period, where t is the time from collection of the water sample to the time of decantation (Step 4, Separation)

Part B Strontium-89 Concentration (pCi/liter)=-i-[E-- F(GH + Ij)l BCL-DE Where:

A = Net beta count rate of "total radiostrontium" (cpm)

B = Counter efficiency for counting strontium-89 as strontium carbonate mounted on a 2.4cm diameter filter paper (cpm/pCi)

C = Correction factor e-Xt for strontium-89 decay, where t is the time from sample collection to the time of counting.

D = Recovery of strontium carrier E = Volume of water sample (liters)

F = Strontium-90 concentration (pCi/L) from PartA G Self-absorption factor for strontium-90 as strontium carbonate mounted on a 2.4cm diameter filter, obtained from a self-absorption curve prepared by plotting the fraction of a 2

standard activity absorbed against density thickness of the sample (mg/cm )

H = Counter efficiency for counting strontium-90 as strontium carbonate mounted on a 2.4cm diameter filter paper (cpm/pCi)

I= Counter efficiency for counting yttrium-90 as yttrium oxalate mounted on a 2.4cm diameter filter paper (cpm/pCi)

J = Correction factor I -e*Xt for yttrium ingrowth, where it is the time from the last decantation of the nitric acid (Step 4, Separation)

REFERENCE:

Radioassay Procedures for Environmental Samples, U. S. Department of Health, Education, and Welfare. Environmental Health Series, January 1967.

6

- K Environmental, Inc.

Midwest Laboratory M

S an Afleghen Technologies Co.

.qi"~~T7i DETERMINATION OF SR-89 AND SR-90 IN ASHED SAMPLES (VEGETATION, FISH, ETC.)

PROCEDURE NO. SR-05 Prepared by Environmental Inc.,

Midwest Laboratory Copy No.

Revised Paaes Revision # Date Paces Prepared by Approved by 0 07-23-86 7 B. Grob Q/ý_uebper Reissue 12-15-04 6 SA Coodrim I (This procedure, or any portion thereof, shall riot be reproduced in any manner or distributed to any third party without the written permission of Environmental Inc., Midwest Laboratory.)

SR-05 Reissue, 12-15-04 DETERMINATION OF SR-89 AND SR-90 IN ASHED SAMPLES (VEGETATION, FISH, ETC.

Principle of Method The sample with stable strontium and barium carriers added is leached in nitric acid and filtered. After filtration, filtrate Is reduced in volume by evaporation. The residue is purified by adding iron and rare earth carriers and precipitating them as hydroxides. After a second strontium nitrate precipitation from 70%

nitric acid, the nitrates are dissolved in acid again with added yttrium carrier and are stored for ingrowth of yttrium-90. The yttrium is precipitated as hydroxide and separated from strontium with the strontium being in the supemate. Each fraction Is precipitated separately as an oxalate (yttrium) and carbonate (strontium) and collected on No. 42 (2.4cm) Whatman filter for counting.

Reagents Ammonium acetate buffer: pH 5.0 Ammonium hydroxide,.2 NH40H: concentrated (15N), 6N ÷2 Carrier solutions: Ba as barium nitrate, Ba(N03)2: 20mg Ba per mL

+2 +2 Sr+3 as. strontium nitrate, 20mg+3-Sr per mL Sr(NO 3)2:M Y as yttrium nitrate, Y(NO3 )3 : 10 mgY per mL Hydrochloric acid, HCI: 6N Nitric acid, HNO 3 : Fuming (90%), concentrated (16N), 6N Oxalic acid, H2C 2O2 -2H2 0: Saturated at room temperature +3 +4.

+3 Scavenqer solutions: 20mg Fe per mL, 10mg each Ce and Zr per mL Fe as ferric chloride, FeCI3.6H 20

+3 Ce as cerous nitrate, Ce(NO3)3 .6H2O

+4 Zr as zirconyl chloride, ZrOC12.8H O Sodium carbonate, Na 2CO 3: 3N, 0.1N Sodium chromate, Na 2CrO 4: 3N Apparatus Analytical balance Low background beta counter pH meter 2

SR-05 Reissue, 12-15-04 DETERMINATION OF SR-89 AND SR-90 IN ASHED SAMPLES (VEGETATION, FISH, ETC.

Procedure

1. Weigh 3g of ash and transfer to the 250mL beaker.

2. Add 50mL concentrated nitric acid.

3. Add 1mL strontium and lmL barium carrier solutions.

4. Place the sample on the moderate hot plate under the hood and cover with the watch glass.

5. Allow to leach for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or longer.

6. Remove sample beaker from the hot plate and allow to cool to room temperature.

7. Add deionized water, filling to 100mL; mark on the beaker.

8. Filter the sample through Whatman No. 541 filter paper.

9. Place the filtrate on the moderate hot plate under the hood and gently evaporate to 5ml.

10. Transfer the sample into 40mL centrifuge tube. Rinse the beaker with 16N HNO3. Add rinsing to the tube.

11. Centrifuge for 10 minutes and discard the supernate to waste.

12. Carefully add 30mL of concentrated HNO 3 to the precipitate. Heat in a hot water bath for about 30 minutes, stirring occasionally. Cool the sample in an ice water bath for about 5 minutes. Centrifuge and discard the supemate.

13. Repeat Step 12.

14. Dissolve the nitrate precipitate in about 10 mL of deionized water (perform under the hood). Add I mL of scavenger solution. Adjust the pH of the mixture to 7 with 6N NH 4OH. Heat in hot water bath for 10 minutes, stir, and filter through a Whatman No. 541 filter into another 40mL centrifuge tube. Discard the mixed hydroxide precipitate (filter paper).

15. Add 5mL of ammonium acetate buffer to the filtrate. Adjust pH with 6N HNO 3 or NH 4OH to pH 5.5.

NOTE: The pH of the solution at this point is critical.

Add dropwise with stirring 1mL of 3N Na 2CrO 4 solution, stir, and heat in a-water bath.

16. Cool and centrifuge. Decant the supernate into another 40mL centrifuge tube. (Save the precipitate for Ba analysis if needed.)

17. Heat the supernate in a water bath. Adjust the pH to 8-8.5 with NH4OH. With continuous stirring, add 5mL of 3N Na2CO3 solution. Heat gently for 10 minutes. Cool, centrifuge, and decant the supernate to'waste. Wash the precipitate with 0.1 N Na2CO 3. Centrifuge again and decant the supernate to waste.

3

SR-05 Reissue, 12-15-04 DETERMINATION OF SR-89 AND SR-90 IN ASHED SAMPLES (VEGETATION, FISH, ETC.

Procedure (continued)

18. Dissolve the precipitate In no more than 4mL of 3N HNO 3 . Then add 20-3OmL of fuming HNO 3, cover with parafilm, cool in a water bath, and centrifuge. Decant and discard the supernate.

19. 'Repeat Step 13. RECORD THE TIME AND DATE AS THE BEGINNING OF YTTRIUM-90 INGROWTH.

20. Dissolve precipitate in 4mL of 6N HNO 3 and add lmL of yttrium carrier solution.

21. Cover with parafilm and store for 7-14 days.

NOTE: At this point, the sample can be transferred to a glass scintillation vial for ingrowth storage. Use several portions of 6N HNO 3 (a total of not more than 4mL); then add 1mL of yttrium carrier to the vial.

Separation NOTE: Ifthe sample was stored in the scintillation vial, transfer back into 40mL centrifuge tube using a few drops of 6N HNO 3 as a rinse.

1. After storage (ingrowth period), heat the,40 mL centrifuge tube containing the sample in the hot water bath (approximately 90°C) for 10 minutes.

2. Adjust pH to 8 with NH4OH, stirring continuously.

3. Cool in a cold water bath and centrifuge for 5 minutes.

4. Decant the supernate into a 40 mL centrifuge tube marked with the sample number and "SR-89".

RECORD THE TIME AND DATE AS THE END OF YTTRIUM-90 INGROWTH in the Sr fraction and the beginning of its decay in Y-90 fraction.

5. Redissolve precipitate by adding 3-4 drops of 6N HCI and add 5-10mL of DI water with stirring.

6. Repeat Steps 1, 2, and 3.

7. Combine supernate with the one in Step 4.

4

SR-05 Reissue, 12-15-04 DETERMINATION OF SR-89 AND SR-90 IN ASHED SAMPLES (VEGETATION, FISH. ETC.

Determination A. Strontium-90 (Yttrium-90)

1. Add 3 drops of 6N HCI to dissolve the precipitate; then add 5-10mL of water. Heat in a water bath to approximately 90°C. Add lmL of saturated oxalic acid solution drop-wise with vigorous stirring.

Adjust to a pH of 2-3 with NH4 0H. Allow the precipitate to digest for about one hour.

NOTE: Do Part "B"while precipitate is digesting.

2. Cool to room temperature in a cold water bath. Centrifuge for 10 min. and decant most of the supernate. Filter by suction on a weighed 2.5cm filter paper. Wash the precipitate with water and alcohol.

3. Dry the precipitate under the lamp for 30 minutes. Cool and weigh. Mount and count without delay in a proportional counter. (See Part C for mounting.)

B. Strontlum-89 (Total Strontium)

1. Heat the solution from Step 7 in water bath.

2. Adjust the pH to 8-8.5 using NH4OH.

3. With continuous stirring, add 5mL of 3N Na2C0 3 solution. Stir until precipitate appears.

Heat gently for 10 minutes.

4. Cool and filter on a weighed No- 42 (2.4cm) Whatman filter paper.

5. Wash thoroughly with water and alcohol.

6. Mount and count without delay its beta activity as "total radiostrontium" in a proportion counter.

C. Filtering and Mounting

1. Place filters under heat lamps for 30 minutes before weighing.

2. Use an analytical balance for weighing (accuracy 0.01 mg).

3. Label a clean petri dish with the weight of the filter paper. (After samples are filtered, the filter paper will again be dried and weighed to determine weight of precipitate before mounting.)

4. Mount weighed filter paper and precipitate on a nylon disc using 1"transparent tape to hold filter paper and 2" mylar foil placed over precipitate and held in place with slip-ring. Trim off excess mylar foil and place the mounted sample in a labeled petri dish.

5. Fill out corresponding loading sheets and place samples in counting room.

5

SR-05 Reissue, 12-15-04 DETERMINATION OF SR-89 AND SR-90 IN ASHED SAMPLES (VEGETATION, FISH. ETC.

Calculations Part A Strontium-90 Concentration (pCi/g Wet) = -bF22+

2.22BCDEFG 2.22BCDEFG Where:

A = Net beta count rate of yttrium-90 (cpm)

B = Recovery of yttrium carier C = Counter efficiency for counting yttrium-90 or yttrium oxalate (cpm/pCi).

D = Sample volume E = Correction factor e"It for yttrium-90 decay, where t Is the time from the time of decantation (Step 4, Separation) to the time of counting F = Correction factor 1- e"It for the Idegree of equilibrium attained during the yttrium-90 ingrowth period, where t is the time from the collection of the water sample to the time of decantation (Step 4, Separation)

G = Ratio of wet weight to ashed weight E b = Counting error of sample plus background Eb = Counting error of background Part B Strontium-89 Concentration (pCilg wet) = 2.22---F(GHIJ++

2.22BC LDEK 2.22BCDEFK Where:

A = Net beta count rate of "total radiostrontium" (cpm)

B = Counter efficiency for counting strontium-89 as strontium carbonate (cpm/pCi).

C = Correction factor e"*t for strontium-89 decay, where t is the time from sample collection to the time of counting D = Recovery of strontium carrier E = Sample size (grams), ash F = Strontium-90 concentration (pCi/g wet) from Part A G = Self-absorption factor for Sr-90 as strontium carbonate, obtained from a self-absorption curve prepared by plotting the fraction2 of a standard activity absorbed against density thickness of the sample (mg/cm)

H = Counter efficiency for counting strontium-90 as strontium carbonate (cpm/pCi).

I = Counteir efficiency for counting yttrium-90 as yttrium oxalate (cpm/pCi).

J = Correction factor 1-e";t for yttrium-90 ingrowth, where t is the time from the last decantation of the nitric acid (Step 4, Separation)

K = Ratio of wet weight to ashed weight

REFERENCE:

Radioassay Procedures for Environmental Samples, U. S. Department of Health,

• Education, and Welfare. Environmental Health Series, January 1967.

6

, Environmental, Inc.

Midwest Laboratory ah Allegheny Technologies Co.

DETERMINATION OF SR-89 AND SR-90 IN SOIL AND BOTTOM SEDIMENTS PROCEDURE NO. SR-06 Prepared by Environmental Inc.

Midwest Laboratory Copy No.

Revised Paaes Revision # Date Pages Prepared by Approved by 0 07-23-86 8 BGrob LG. Huebner 1 _08-05-04 - 7/_ (/A . I-AJ-*.*--

(This procedure, or any portion thereof, shall not be. reproduced In any manner or distributed to any third party without the written permission of Environmental Inc., Midwest Laboratory.)

SR-06 Rev. 1, 08-05-04 DETERMINATION OF SR-89 AND SR-90 IN SOIL AND BOTTOM SEDIMENTS Principle of Method The sample with stable strontium and barium carriers added is leached in hydrochloric acid. After separation from calcium, the residue is purified by adding iron and rare earth carriers and precipitating them as hydroxides. After a second strontium nitrate precipitation from 70% nitric acid, the nitrates are dissolved in acid again with added yttrium carrier and are stored for ingrowth of yttrium-90. The yttrium Is precipitated as hydroxide and separated from strontium with the strontium being in the supernate. Each fraction is precipitated separately as an oxalate (yttrium) and carbonate (strontium) and is collected on No.

42 (2.4cm) What man filter for counting.

Reagents Ammonium acetate buffer: pH 5.0 Ammonium hydroxide, NH4OH: concentrated (15N), 6N Carrier solutions: Ba÷2 as barium nitrate, Ba(N0 3 ) 2: 20mg Ba+2 per mL

+3 as strontium nitrate, Sr(NO 3)2: 20mg+ Sr per mL Sr+2 Y as yttrium nitrate, Y(NO 3)3 : 10 mg Y per mL

-Hydrochloric acid, HCI: 6N Nitric acid, HNO 3 : Fuming (90%), concentrated (16N), 6N Oxalic acid, H2C 20 2 .2H20: Saturated at room temperature Scavenger solutions: 20mg Fe+3 per mL, 10mg each Ce*3 and Zr4 per mL Fe as ferric chloride, FeCI36H20

+3 Ce+4 as cerous nitrate, Ce(NO 3)3.6H 20 Zr as zirconyl chloride, ZrOCI2-8H20 Sodium carbonate, Na 2CO 3: 3N, 0.1N Sodium chromate, Na2CrO4 : 3N Apparatus Analytical balance Centrifuge Hot plate Low background beta counter pH meter Plastic disc and ring Stirrer 2

SR-06 Rev, 1, 08-05-04 DETERMINATION OF SR-89 AND SR-90 IN SOIL AND BOTTOM SEDIMENTS Procedure

1. Weigh out 5 - 50 g sample into a I liter beaker depending on the required LLD. Add ImL of strontium carrier and lmL of Ba carrier.

2. Stir mechanically while slowly adding 200mL of 6N HCI (It may be necessary to add a few drops of octyl alcohol to prevent excessive frothing.) Continue stirring for about 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Allow a minimum of two hours for the insoluble material to settle.

3. Stir the mixture and filter with suction through a 24cm Whatman No. 42 filter paper using a Buchner funnel. Wash the residue with hot water. Wash with 6N HCI and again with hot water until the yellow color of ferric chloride is removed. Discard the residue.

4. Transfer the filtrate to a 1 liter beaker and evaporate to approximately 200mL. Cool and slowly add 200mL of concentrated HNO 3 . (If there is excessive frothing, add a few drops. of octyl alcohol.)

Evaporate to 100-200mL.

5. Add 500mL of water and stir.

6. Add 25 grams of oxalic acid with magnetic stirring until it is completely dissolved.

7. Adjust the pH to 5.5-6.0 with concentrated NH4 OH. (if the brown color of ferric hydroxide persists, add more oxalic acid and readjust.the pH.) The optimum condition Is an excess of oxalic acid in solution without causing crystallization of ammonium oxalate upon cooling.

8. Allow precipitate to settle for 5-6 hours or overnight.

9. Decant most of the supemate (liquid) and transfer the precipitate to a 250mL centrifuge tube using deionized water for rinsing. Add rinsing to the tube. Centrifuge and decant supernate.

10. Wash the precipitate with 50-1OOmL portion of water and centrifuge again.

11. Repeat washing as needed until all the yellow color of the solution has been removed.

12. Cool the precipitate and dissolve it with 6N HNO 3 and transfer it into a 250mL beaker. Rinse the tube with6N HNO 3, making the total volume to 50-100 mL. Add about 6 drops of H20 2 (30%) to facilitate dissolution.

13. Cool to room temperature. If insoluble material is present at this point, filter by suction through a glass fiber filter. Discard the filter and residue.

14. Transfer the solution to an appropriate size beaker and evaporate to dryness. The evaporation must be done slowly to avoid spattering.

15. Dissolve the salt in water and ,perform successive fuming nitric acid separations (the first two separations at concentration slightly greater than 75%) until the strontium has been separated from the bulk of the calcium. Samples with a high calcium content will require five or more separations.

16. The volumes of 75% HNO 3 vary (fuming solutions may be changed as required by the mass of calcium present, keeping In mind that minimum volumes are always best.)

3

SR-06 Rev. 1, 08-05-04 Procedure (continued)

17. If calcium content is still thick, evaporate the solution to dryness and bake.

18. Dissolve the residue with 50mL boiling water and filter. Discard residue.

19. Evaporate the solution to dryness again.

20. Cool and dissolve the residue in a minimum amount of water and add 50 mL of fuming HNO 3.

21. Continue the fuming nitric acid separations until the strontium has been separated from the bulk of calcium.

22. Transfer the solution to a 40mL conical, heavy-duty centrifuge tube, Using a minimum of concentrated HNO 3 to effect the transfer. Cool the centrifuge tube in an ice bath for about. Centrifuge and discard the supernatant.

NOTE: The precipitateconsists of calcium, strontium, and barium-radiumnitrate.

The supernatantcontains part of the sample's calcium and phosphate content.

23. Add 30mL of concentrated HNO 3 to the precipitate. Heat in a hot water bath with stirring for about 10 minutes. Cool the solution in an ice bath, stirring for about 5 minutes. Centrifuge and discard the supematant.

NOTE: Additional calcium is removed from the sample. Nitrate precipitation with 70% HNO3 will afford a partialdecontaminationfrom soluble calcium, while strontium, barium, and radium are completely precipitated.

Separation of calcium is best at 60% HNO ; however, at 60% the precipitationof strontium is not complete. Therefore, it is common practice to precipitate (Sr(N03) 2 with 70% HNO3 which is the concentrationof commercially available 16N HNO3.

Most other fission products, induced activities, and actinides are soluble in concentrated HN0N 3, affording a good "gross"decontaminationstep from a wide spectrum of radionuclides.

The precipitationis usually repeatedseveral times.

24. Repeat Step 23 two (2) more times.

25. Dissolve the nitrate precipitate in about 20mL distilled water. Add 1mL of scavenger solution. Adjust the pH of the mixture to 7 with 6N NH4OH. Heat, stir, and filter through a Whatman No. 541 filter.

Discard the mixed hydroxide precipitate.

26. To the filtrate, add 5mL of ammonium acetate buffer. Adjust pH with 6N HNO 3 or NH4OH to pH 5.5.

NOTE: The pH of the solution at this point is critical.

Add dropwise with stirring lmL of 3N Na 2CrO4 solution, stir and heat in a water bath.

27. Cool and centrifuge. Decant the supernate into another 40mL centrifuge tube. (Save the precipitate for barium analysis if needed.)

4

SR-06 Rev. 1, 08-05-04 Procedure (continued)

28. Heat the supemate In a water bath. Adjust the pH to 8-8.5 with NH4O OH. With continuous stirring, add

• 5mL 3N Na 2CO 3 solution. Heat gently for 10 minutes. Cool, centrifuge, and decant the supermate to waste. Wash the precipitate with 0.1N Na2CO3 . Centrifuge again and decant the supernate to waste.

29. Dissolve the precipitate in no more than 4mL of 6N HNO 3. Add 20-30mL of fuming HNO 3 , cover with parafilm, cool in a water bath, and centrifuge. Decant and discard the supemate.

30. Repeat Step 13. RECORD THE TIME AND DATE AS THE BEGINNING OF YTTRIUM-90 INGROWTH.

31. Dissolve precipitate in 4mL of 6N HNO 3 and add lmL of yttrium carrier solution.

32. Cover with parafilm and store for 7-14 days.

NOTE: At this point, the sample can be transferredto a glass scintillation vial for the ingrowth storage.

Use severalportions of 6N HNO 3 (a total of not more than 4mL); then add lmL ofyttrium carrierto the vial.

Separation NOTE: If the sample was stored in the scintillation vial, transferback into 4OmL centrifuge tube using a few drops of 6N HNO3 as a rinse.

.1. After storage (ingrowth period), heat the 40mL centrifuge tube containing the sample in the hot water bath (approximately 90°C) for 10 minutes.

2. Adjust pH to 8 with NH4OH, stirring continuously.

3. Cool in a cold water bath and centrifuge for 5 minutes.

4. Decant the supernate into a 40 mL centrifuge tube marked with the sample number and "SR-89."

RECORD THE DATE AND TIME OF DECANTATION AS THE END OF Y-90 INGROWTH in Sr fraction and the beginning of its decay in Y-90 fraction.

5. Redissolve the precipitate by adding 3-4 drops of 6N HCI. Add 5-lOmL of deionized water with stirring.

6. Repeat Steps 1, 2, and 3.

7. Combine supemate with the one in Step 4.

5

SR-06 Rev. 1, 08-05-04

-,J Determination A. Strontium-90 (Yttrium-90)

1. Add 3 drops of 6N HCI to dissolve the precipitate; then add 5-10mL of water. Heat in a water bath at approximately 900C. Add lmL of saturated oxalic acid solution dropwise with vigorous ,.

stirring. Adjust to a pH of 2-3 with NH4OH. Allow the precipitate to digest for about an hour.

NOTE: Do Part "B" while precipitateis digesting.

2. Cool to room temperature in a cold water bath. Filter by suction on a weighed 2.5cm filter paper. Wash precipitate with water and alcohol.

3. Dry the precipitate under the lamp for 30 minutes. Cool and weigh. Mount and count without delay in a proportional counter. (See Part C for mounting.)

B. Strontium-89 (Total Strontium)

1. Heat the solution from Step 7 in water bath.

2. Adjust the pH to 8-8.5 using NHOH.-

3. With continuous stirring, add 5mL of 3N Na2CO3 solution. Stir until precipitate appears. Heat gently for 10 minutes.

4. Cool and filter on a weighed No. 42 (2.4cm) Whatman filter paper.

5. Wash thoroughly with water and alcohol.

6. Mount and count without delay its beta activity as "total radiostrontium" in a proportional counter.

C. Filterinq and Mountinq

1. Place filters under heat lamps for 30 minutes before weighing.

2. Use an analytical balance for weighing (accuracy 0.01 mg).

3. Label a clean petri dish with the weight of the filter paper. (After samples are filtered, the filter paper will again be dried and weighed to determine weight of precipitate before mounting.)

4. Mount weighed filter paper and precipitate on nylon disc using INtransparent tape to hold filter paper and 2" mylar foil placed over precipitate and held in place with slip-ring. Trim off excess mylar foil and place the mounted sample in a labeled petri dish.

5. Fill out corresponding loading sheets and place samples in counting room.

6

SR-06 Rev. 1, 08-05-04 Calculations Part A A 2 E 2+

Strontium-90 Concentration (pCilg dry) =

2.22BCDEF +/-*2.22BCDEF Where:

A= Net beta count rate of yttrium-90 (cpm)

B= Recovery of yttrium carrier C= Counter efficiency for counting yttrium-90 or yttrium oxalate mounted on a 2.4cm diameter filter paper (cpm/pCi)

D= Sample weight (grams), dry E= Correction factor e-;t for yttrium-90 decay, where t is the time from the time of decantation (Step 4, Separation) to the time of counting F= Correction factor 1- e-I for the degree of equilibrium attained during the yttrium-90 ingrowth period, where t is the time from the collection of the water sample to the time of decantation (Step 4, Separation)

Esb= Counting error of sample plus background Eb Counting error of background Part B Strontium-89 Concentration (pCilg dry) '11 A F(H*+ IxJ) i2o Bx-C L 2.22xDxE J Where:

A= Net beta count rate of "total radiostrontium" (cpm)

B= Counter efficiency for counting strontium-89 as strontium carbonate mounted on a 2.4cm diameter filter paper (cpm/pCi)

C= Correction factor e-xt for strontium-89 decay, where t Is the time from sample collection to the time of counting D= Recovery of strontium carrier E= Sample weight (grams, dry)

F= Strontium-90 concentration (pClIg) from Part A H= Counter efficiency for counting strontium-90 as strontium carbonate mounted on a 2.4cm diameter filter paper (cpmlpCi)

I= Counter efficiency for counting yttrium-90 as yttrium oxalate mounted on a 2.4cm diameter filter paper (cpm/pCi)

J= Correction factor 1- e-M for yttrium-90 ingrowth, where t is the time from the last decantation of the nitric acId (Step 4, Separation)

REFERENCE:

Radioassay Procedures for Environmental Samples, U. S. Department of Health, Education, and Welfare. Environmental Health Series, January 1967.

7

Environmental, Inc.

• I S"Midwest Laboratory

~an ALeghen Techn~ooies Cc, DETERMINATION OF SR-89 AND SR-90 IN MILK (ION EXCHANGE BATCH METHOD)

PROCEDURE NO. SR-07 Prepared by Environmental inc.

Midwest Laboratory Copy No..

Revised Pages Revision # Date Pages Erepared by Approved by 4 08-18-94 9A.Gd L..1lubrer Reissue- 08-05-04 7 (This procedure, or any portion thereof, shall not be reproduced in any manner or distributed to any third party without the written permission of Environmental Inc., Midwest Laboratory.)

SR-07 Reissue, 08-05-04 DETERMINATION OF SR-89 AND SR-90 IN MILK (ION EXCHANGE BATCH METHOD)

Principle of Method A citrate complex of strontium carrier at the pH of milk is added to the milk sample. Strontium, barium, and calcium are absorbed on the cation-exchange resin.

Strontium, barium, and calcium are eluted from the cation-exchange resin with sodium chloride solution.

Following dilution of the eluate, the alkaline earths are precipitated as carbonates. The carbonates are then converted to nitrates. Strontium is purified by Argonhe method using three grams of extraction material in a chromatographic column. Yttrium carrier is added and a sample is stored for ingrowth of yttrium-90. The yttrium is again precipitated as hydroxide and separated from strontium with the strontium being in the supemate. Each fraction is precipitated separately as an oxalate (yttrium) and carbonate (strontium) and collected on No. 42 (2.4 cm) Whatman filter for counting.

The concentration of Sr-89 is calculated as the. difference between the activity for "total radiostrontium" and the activity due to Sr-90.

Reagents Ammonium hydroxide, NH 4OH: concentrated (15N)

Carrier solutions:

77 - +2 Sr as strontium nitrate, St(NO 3) 2: 20mg Sr per mL Y+3 as yttrium nitrate, Y(NO 3)3 : 10 mg Y 3 per mL Cation-exchange resin: Dowex 50W-X8 (Na+ form, 50-100 mesh)

Citrate solution: pH 6.5 DI water Ethyl alcohol, C 2H5 OH: 95%

Hydrochloric acid, HCh: 6N Nitric acid, HNO 3 : 3N Oxalic acid, H2C 20.2H2 0: 2N Sodium carbonate, Na 2CO3 : 3N Sodium chloride, NaCI: 4N Silver nitrate,AgNO3: IN Strontium Spec Resin 2

SR-07 Reissue, 08-05-04 Apparatus Ion-exchange system:

glass separatory The apparatus for this system Is Illustrated In Figure Sr-07-1. At the top is a I-liter column, a 250 mL glass 5 cm in funnel which serves as the reservoir. Below it is connected column. The column has an extra coarse, diameter and 25 cm long, which services as the cation fritted glass disc at the bottom.

Millipore filtering apparatus Chromatograrhic Column Preparation and regeneration of cation resin:

1. Wash 170 mL of Dowex 50W resin to fill the cation column.

2. Pass 500 mL of 1N NaOH through the column at a flow rate of 10 mL/minute.

3. Rinse with 500-1000 mL of H20.

4. Test effluent with AgNO 3. If effluent is clear, the resin Is ready for milk.

ER * -A SSI R ESERVOIR*_T CATION ftESIN Figure SR-07-01 3

8R-07 Reissue, 08-05-04 DETERMINATION OF SR-89 AND SR-90 IN MILK (ION EXCHANGE BATCH METHOD)

Procedure

1. Place 1 liter of milk in 4 liter beaker.

2. Pipette 1.0 mL of strontium carrier solution into 10 mL of citrate solution. Swirl to mix.

3. Transfer the mixture quantitatively to the milk with 5 mL of DI water.

4. Add a clean magnetic stirring bar to each sample beaker. Stir each sample for 5 minutes or longer on a magnetic stirrer. Allow sample to equilibrate at least 1/2 hour. If a milk sample is curdled or lumpy, vacuum filter the sample through a Buchner funnel using a cheesecloth filter. Wash-the curd thoroughly with deionized water, collecting the washings with the filtrate. Pour the filtrate back into the original washed and labeled 4-liter beaker and discard the curd.

5. Add approximately 170 mL of Dowex 50Wx8 (50-100 mesh) cation resin to each sample beaker.

Stir on a magnetic stirrer for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Turn off the stirrer and allow the resin to settle for 10 minutes.

6. Gently decant and discard the milk sample, taking care to retain as much resin as possible in the beaker. Add approximately 1 liter of deionized water to rinse the resin, allow to settle 2 minutes, and pour off the rinse. Repeat rinsing until all traces of milk are removed from the resin.

7. Using a DI water wash bottle, transfer the resin to the column marked with the sample number.

Allow resin to settle 2 minutes and drain the standing water.

8. Connect 1-liter separatory funnel containing I liter of 4N NaCI to the cation column. Allow solution to flow at 10 mL/minute to elute the alkali metal and alkaline earth ions and to recharge the column.

Collect I liter of eluate into a 2-liter beaker, but leave the resin covered with 2-3 mL of solution.

9. Wash the column with 500 mL of H20 or more to remove excess NaCI. Discard the wash.

10. Remove 20 mL of the NaCl eluate into a small bottle for the determination of stable calcium, if required (see procedure on calcium determination).

11. Dilute the eluate to 1500 mL with DI water.

12. Heat the solution to 85-900 C (near boiling on a hot plate) and add, with constant stirring, 100 mL of 3N Na2C03. Cover with watch glass. Let stand ovemight.

13. Decant most of supemate to waste. Transfer precipitate to a 250 mL centrifuge bottle with DI water.

14. Centrifuge. Pour off the supemate to waste. Dry the precipitate in an oven at 100I C for 1-2 hours.

15. Dissolve the precipitate in 30 mL 3M HNO 3.

16. Place each sample centrifuge tube in front of a corresponding Sr extraction column.

17. Condition columns by passing 30 mL 3M HNO 3 through them with the stopcocks fully open. Catch effluent in a waste beaker.

18. Add sample from the centrifuge tube into the correspondingly numbered column.

NOTE: Use no water to make this transfer. Use only 3M HN0 3 to rinse out the beaker.

Allow the sample to pass through the column. Catch effluent in a waste beaker.

4

SR-07 Reissue, 08-05-04 Procedure (continued)

19. When the column reservoir is drained, measure 70 mL 3M HNO 3 in a graduated cylinder and pass through the column to rinse. Catch effluent in a waste beaker. When the column is drained, RECORD THE DATE AND TIME ON THE WORK SHEET AS THE BEGINNING OF Y-90 INGROWTH.

20. Write the sample number on a clean 150 mL beaker.. Place It under the column after the rinse solution has drained. Discard the contents of the waste beaker.

21. Elute strontium by adding 70 mL DI water to the column. Catch effluent in the 150 mL beaker.

22. When the elution is complete, add 1.00 mL standardized yttrium carrier to the numbered sample beaker using an Eppendorf pipet.

23. Place sample beaker on a moderate hotplate and evaporate gently to approximately 10 mL volume.

Remove beaker from hotplate and allow to cool.

NOTE: If the sample accidentally evaporates to dryness, allow it to cool, then add a few drops 3M HNO3 and approximately 10 mL DI water. Warm gently and swirl to dissolve residue.

24. Mark the sample number on a 40 mL centrifuge tube. Transfer the sample using the minimum amount of DI water.

25. Seal the sample tube with parafilm and place in a rack to stand for a minimum 5-day period for Y-90 ingrowth.

26. Rinse the Sr extraction columns with an additional 70 mL DI water. Catch effluent In a waste beaker. Leave the columns wet with Di water, with the stopcocks closed.

27. Enter column number, date and sample number in the Sr'Column Log.

Separation

1. After storage (ingrowth period), heat the 40mL centrifuge tube containing the sample in the hot water bath (approximately 90°C) for 10 minutes.

2. Adjust pH to 8.0-8.5 with NH4 OH, stirring continuously.

3. Cool in a cold water bath and centrifuge for 5 minutes.

4. Decant the supernate into a 40mL centrifuge tube marked with the sample number and "Sr-89."

RECORD THE DATE AND TIME OF DECANTATION AS THE END OF Y-90 INGROWTH IN SR FRACTION AND THE BEGINNING OF ITS DECAY IN Y-90 FRACTION.

5. Redissolve the precipitate by adding 3-4 drops of 6N HCI and add 5-10 mL of DI water with stirring.

6. Repeat Steps 1, 2, and 3.

7. Combine supemate with the one in Step 4.

8. Wash precipitate twice with 20 mL portions of Di Water. Centrifuge each time and discard supemate.

9. Proceed with Determination.

5

SR-07 Reissue, 08-05-04 DETERMINATION OF SR-89 AND SR-90 IN MILK (ION EXCHANGE BATCH METHOD)

Determination A. Strontium-90 (Yttrium-90)

1. Add 3 drops of 6N HCi to dissolve the precipitate from Step 4, Separation; then add 5-10 mL of DI water. Heat in a water bath at approximately 90°C for about 10. minutes. Add 1 ml of saturated oxalic acid solution dropwise with vigorous stirring. Adjust to a pH of 2-3 with NH4OH. Allow the precipitate to digest for approximately one hour.

NOTE: Do Part "B" while precipitateis digesting. "

2. Cool to room temperature in a cold water bath. Centrifuge for 10 minutes and decant most of the supemate to waste. Filter by suction on a weighed 2.5 cm filter paper. Wash the precipitate with DI water and ethyl alcohol.

3. Dry the precipitate under the lamp for 30 minutes. Cool and weigh. Mount and count in a proportional counter. (See Part C for mounting.)

B. Strontium-89 (Total Strontium)

1. Heat the solution from Step 7, Separation, in water bath.

2. Adjust the pH to 8-8.5 using NH4 OH.

3. With continuous stirring, add 5 mL of 3N Na2CO3 solution. Stir until precipitate appears. Heat gently for 10 minutes.

4. Cool and filter on a weighed No. 42 (2.4 cm) Whatman filter paper.

5. Wash precipitate with water and ethyl alcohol.

6. Dry the precipitate under the lamp for 30 minutes. Cool and weigh. Mount and count in a proportional counter. (See Part C for mounting.)

C. Filtering and Mounting

1. Place filters under heat lamps for 30 minutes before weighing.

2. Weigh the filter papers on an analytical balance (accuracy 0.01 mg).

3. Label a clean petri dish with the weight of the filter paper. (After samples are filtered, the filter paper will again be dried and weighed to determine weight of precipitate before mounting.)

4. Mount weighed filtet paper and precipitate on nylon disc using 1" transparent tape to hold filter paper and 2° mylar foil placed over precipitate and held in place with slip-ring. Trim off excess mylar foil and place the mounted sample in a labeled petd dish.

5. Fill out corresponding loading sheets and place samples in counting room.

6

SR-07 Reissue, 08-05-04 DETERMINATION OF SR-89 AND SR-90 IN MILK (ION EXCHANGE BATCH METHOD)

Calculations A

Strontium-90 Concentration (pCI/L) =

2.22xBxCxDxExFxG Where:

2.22 = dpm/pCi Net beta count rate of yttrium-90 (cpm)

Recovery of yttrium carrier Recovery of strontium carder Counter efficiency for counting yttrium-90 as yttrium oxalate mounted on a 2.4 cm diameter filter paper (cpmldpm)

Sample volume (liters)

Correction factor e"t for yttrium-90 decay, where t is the time from the time of decantation (Step 4, Separation) to the time of counting G= Correction factor 1-e"Xt for the degree of equilibrium attained during the yttrium-90 ingrowth period, where t is the time from the beginning of ingrowth (Step 19, Total Radiostrontium Separation) to the time of decantation (Step 4, Separation)

Lower Limit of Detection (LLD). at 4.66 siama LLD for Sr-90: I pCi/L. LLD is based on the following'typical parameters:

Sample Size: I L Recovery (Sr and Y): 0.6 Decay Factor (Y-90): 0.8 Ingrowth Factor (Y-90): 0.6 Counter Efficiency: 0.4 Counter

Background:

0.3cpm Counting Time: 100 minutes (Changes in any of the above parameters will change. LLD correspondingly.)

7

SR-07 Reissue, 08-05-04 DETERMINATION OF SR-89 AND SR-90 IN MILK (ION EXCHANGE BATCH METHOD)

Calculations Strontium-89 Concentration (pCi/L) 2 1 5[-`

2.22xBxCL[DxE - 2.22x F(G + H x 0]

Where:

2.22 = dpm/pCi A = Net beta count rate of "total radiostrontium" (cpm)

B = Counter efficiency for counting strontium-89 as strontium carbonate mounted on a 2.4 cm diameter filter paper (cpm/dpm)

C = Correction factor ea-t for strontium-89 decay, where t is the time from sample collection to the time of counting D = Recovery of strontium carrier E = Sample volume (liters)

F = Strontium-90 concentration (pCi/liter) from Part A G = Counter efficiency for Counting strontium-90 as strontium carbonate mounted on a 2.4 cm diameter filter paper (cpm/dpm)

H = Counter efficiency for counting yttrium-90 as yttrium oxalate mounted on a 2.4 cm diameter filter paper (cpm/dpm)

= Correction factor 1-e"-t for yttrium-90 ingrowth, where t is the time from the last decantation of the nitric acid (Step 4, Separation) to the time of counting Lower Limit of Detection (LLD), at 4.66 slcima LLD for Sr-89: 2..0 pCVL. LLD is based on the following typical parameters:

Sample Size: 1 L Recovery: 0.7 Decay Factor: 0.5 Counter Efficiency. 0.3 Counter

Background:

0.3 cpm Counting Time, 100 minutes LLD for Sr-90: 1 pCi/L (Changes in any of the above parameters will change LLD correspondingly.)

REFERENCES:

Radioassay Procedures for Environmental Samples, U. S. Department of Health, Education, and Welfare. Environmental Health Series, January 1967.

Horwitz, Dietz, Fisher, Analytical Chemistry, 63 (5), March 1991.

8

- Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road ° Northbrook, IL60062-2310 ph. (847) 564-0700

• tax (847) 564-4517 -

DETERMINATION OF TRITIUM IN WATER (DIRECT METHOD)

PROCEDURE NO. EIML-T-02 Prepared by Environmental Inc., Midwest Laboratory Copy No.

Revision # Date Pages Prepared by Approved by 0 11-22-85 5 B Grob L. G. Huebner 1 09-27-91 4 B Grob L. G. Huebner 2 04-24-95 4 B Grob L. G. Huebner 3 07-07-98 4 D. Rieter B Gn'b 4 06-06-00 4 rn 5 01-29-02 4 /V (This procedure, or any portion thereof, shall not be reproduced In any manner or distributed to any third party without the written permission of Environmental Inc., Midwest Laboratory.)

EIML-T-02 Revision 5, 01-29-02 DETERMINATION OF TRITIUM IN WATER (DIRECT METHOD)

Principle of Method The water sample Is purified by distillation, a portion of the distillate Is transferred to a counting vial and the scintillation fluid added. The contents of the vial are thoroughly mixed and counted in aliquot scintillation counter.

Reagients Scintillation medium, Ultima-Gold LLT, Packard Instruments Co.

Tritium standard solution Dead water Ethyl alcohol Sodium Hydroxide (pellets)

Potassium permanganate (crystals)

Apparatus Condenser Distillation flask, 250-mL capacity Liquid scintillation counter Pipette and disposable tips (0.1ml., 5-10 ml.)

Kimwipes Procedure NOTE: All glassware must be dry. Set drying oven for 100-125°C.

1. Place 60-70 mL of the sample in a 250-mL distillation flask. Add a boiling chip to the flask. Add one NaOH pellet and about 0.02g KMnO4. Connect a side arm adapter and a condenser to the outlet of the flask. Place a receptacle at the outlet of the condenser. Set variac at 70 mark. Heat to boiling to distill. Discard the first 5-10mL of distillate. Collect next 20-25mL of distillate for analysis. Do not distill to dryness.

2. Mark the vial caps with the sample number and date.

NOTE: Use the same type of vial for the whole batch (samples, background and standard.)

3. Mark three vial caps "BKG-1"," BKG-2", "BKG-3", and date.

4. Mark three vial caps "ST-i", "ST-2"," ST-3"; standard number, and date.

5. Dispense 13 mL of sample into marked vials and "dead" water into vials marked BKG-1, BKG-2, BKG-3.

NOTE 1: The Pipette Is set (and calibrated) to deliver 6.5 mL, so pipette twice into each vial.

Use new tip for each sample and new tip (one) for three background samples.

NOTE 2: Make sure the pipette has not been reset. If It has been reset, or if you are not sure, do not use it; check with your supervisor.

NOTE 3: Make sure the plastic tip is pushed all the way on the pipette and is tight. If it is not, the air will be draw in and the volume withdrawn will not be correct (it will be smaller).

2

EIML-T-02 Revision 5, 01-29-02

6. Dispense 13 mL (see Notes 1, 2, and 3, above) of "dead" water into each vial marked "ST-l",

"ST-2" and "ST-3."

7. Using a 0.1 mL pipette, withdraw water from each of the three standard vials. Discard this 0.1 mL of water.

8. Take a new 0.1 mL tip. Dispense 0.1 mL of standard into each of the three vials marked "ST-l,"

"ST-2," and "ST-3."

9. Take all vials containing samples, background, and standard to the counting room.

NOTE: To avoid spurious counts, scintillation fluid should not be added under fluorescent light.

10. Dispense 10 mL of scintillation fluid into each vial (one at a time), cap tightly, and shake VIGOROUSLY for at least 30 seconds. Recheck the cap for tightness.

11. Wet a Kimwipe with alcohol and wipe off each vial in the following order:

Background

Samples Standard

12. Load the vials in the following order:

BKG-1 ST-I Samples BKG -2* *BKG-2 and ST-2 should be approximately ST -2* in the middle of the batch Samples BKG-3 ST -3

13. Let the vials dark- and temperature-adapt for about one hour.

NOTE 1: To check if vials have reached counter temperature, inspect one vial (Bkg). The liquid should be transparent. If the temperature is too high (or too low), the liquid will be white and very viscous.

NOTE 2: The temperature inside the counter should be between 100 and 14=C (check thermometer). In this temperature range, the liquid is transparent.

14. Set the counter for 100-minute counting time and infinite cycles. (Follow manufacturers procedure for setting the counter.)

3

EIML-T-02 Revision 5, 01-29-02

15. Fill out the loading sheet, being sure to indicate the date and time counting started, and your initials.

NOTE 1: Do not count prepared background and standard sets with another batch of samples If plastic vials are used. Prepare new backgrounds and standards for each batch.

NOTE 2: If glass vials are used, the prepared background and standard sets can be counted with other batches up to one month after preparation, provided they are not taken out of the counter (not warmed up) and the same vial type from the same manufacturing batch (the same carton) is used. After one month prepare new sets of backgrounds and standards.

Calculations

.A B FXA B Af~

pCi/ L tl t2A +It't 2.22EVe- , 2. 22EVe "

Where:

A = Total counts, sample B = Total counts, background E = Efficiency, (cprn'dpm)

V = Volume (liter) e = Base of the natural logarithm = 2.71828 0.693

= -- =0.5652 12.26 tl = Counting time, sample t2 = Counting time, background t3 = Elapsed time from the time of collection to the time of counting (in years) 4

- ~ Environmental, Inc.

Midwest -Laboratory anAegheny Technotloes Co.

700 Landwehr Road - Nad'obook. L. 60062-2310 ph. (847) 564-0700

• fax (847) 564-4517 UNCO~IOLLED I I

MEASUREMENT of AMBIENT GAMMA RADIATION by THERMOLUMINESCENT DOSIMETRY (CaSO4 :Dy)

PROCEDURE NO. EIML-TLD-01 Prepared by Environmental, Inc.

Midwest Laboratory Copy No.

Date Approved by 6 B Grob LG Huebner 04~24-9 LG Hluebner 6 6 B Grab

-7.Relssue 06Q07-0 3 SA Coorlim (This procedure, or any portion thereof, shall not be reproduced In any manner or distributed to any third party without the written permission of Environmental, Inc., Midwest Laboratory.)

IEIML-TLD-01 Revision 7, 06-07-01 MEASUREMENT of AMBIENT GAMMA RADIATION by THERMOLUMINESCENT DOSIMETRY (CaSO 4 :Dy)

Princliple of Method The cards are spread out In a single layer on a perforated metal tray and annealed for two hours at 250-26.0 0C. After annealing, the cards are packaged and sent to the field.

Once the cards are returned from the field they are read as soon as possible. After reading, several cards are chosen, annealed and Irradiated with a known dose using a Ra-226 source encapsulated Inan Iridium needle to calculate efficiency. The net exposure Is-calculated after in-transit exposure is subtracted.

1. Equipment & Materials:

TLD Reader: (Teledyne Isotopes Model 8300) Annealing oven TLD Cards (CaSO4:Dy phosphor) Forceps TLD Card Holder with copper shielding Black Plastic bags (pouches)

Transparent plastic bags (6oz and Boz puncture proof Whiri-Pak)

Heat sealer Scotch tape Labels Recording sheet Ra-226 Needle: ("American Radium" No. 37852) Turntable I. Preparation

1. Enter location I.D, dosimeter (card) number, and date annealed on the readout recording sheet.

• As per project requirements, Include cards for In-transits and spares.

2. Spread the cards Ina single layer on the perforated tray.

3. Preheat the annealing oven to 250-260 °C

4. Set the alarm and anneal for two hours. Remove tray from the oven and let cool.

5. Place each card In a black plastic bag (pouch), seal the flap with scotch tape, and place in the card holder.

6 Attach a label Identifying the station, location, and exposure period, on each holder. Place the holders into a transparent plastic bag and heat seal.

7. Ship without delay. Place a "Do Not X-Ray" sticker on the mailing container.

11. Reader Calibration

1. Adjust the nitrogen flow control to 6 SCF per hour.

2. .Open the card drawer.

3. Turn "FUNCTION" switch to "CALIBRATE'. The "WAIT" sign will be Illuminated and the reading will change every three seconds. The reading should be 1000 -10. If not, adjust using the "CALIBRATE" dial.

2

• ""M TLO Revision 7, 06-07-01 Ill. Reader Calibration (continued)

4. Turn OFUNCTION' switch to "OPERATE". Press "START'. When the "READ, signal appears, the reading should be as posted. If not, adjust with "Sensitivity" dial. (Turn clockwise If reading Is low, counterclockwise ifreading is high).

5. Wait for "START" button to light before continuing. Press "START". Continue adjusting "SENSITIVITY" until the reading is as posted. Make and record 5 readings.

6. When the "START" button lights, push in the card drawer to position No. 3. Press "START". Wait for the "READ" signal and record the reading. (dark current I background)

7. Repeatthis step four more times (total of five readings) and record the results.

NOTE: The reading should be as posted on the reader. If not, notify the Lab supervisor.

IV. Readout of TLD Cards

1. After the "START" button lights, pull out card drawer. Take the card out of the holder and Insert in the drawer with printed card number facing d=wn and to the back (away from you).

2. Push drawer Into position No. 1. Push "START" button.

3. When "READ" sign appears, record the reading.

4. When "START" button lights up, push the drawer to position No. 2. Push "START" button.

Repeat steps 2.3 and 2.4 until all positions are read out.

5. Read out and record the reading for the rest of the cards in the same manner.

V. Efficiency Determination NOTE: Perform an efficiency calibration after each field cycle. (i.e. random TLDs from each project are calibrated after every readout of that project.).

1. After readout of a project Is completed, select two to three cards at random.

2. Anneal and package as described In Part II, Steps 2 thru B.

3. Clip the holders (with the freshly annealed cards) on the irradiation turntable. Start rotation.

4. Attach the Ra-226 needle to center of the turntable. Record the time. Irradiate overnight.

5. Remove the needle, record the time, and read out the cards as in Part Ill.

6. Average all the readings, and subtract average dark current reading (Part Ill, Step 6-7).

7. Calculate efficiency (light response) as follows:

(from step 6.)

Efficiency = Net Average Reading Hours of exposure x 2.097

8. Submit the field data and efficiency data sheets to data clerk for calculations.

NOTE:

The calculation program will automatically subtract the in-transit exposure and prorate exposure to a selected number of days (usually 30 or 91). Occasionally, some TLDs are placed and/or removed at different times resulting in a different number of exposure days in the field. Exposure will be prorated for the selected number of days..

3

- .Environmental, Inc.

Midwest Laboratory anAllegheal Tedchnolges Co.

700 Landwehr Road NdoUrtmook IL 60062-2310 ph. (847) 5640700 taxf (8M4) 564-4S17 DETERMINATION of GROSS ALPHA andfor GROSS BETA in WATER (DISSOLVED SOLIDS or TOTAL RESIDUE)

PROCEDURE NO. W(DS)-01 Prepared by Environmental, Inc.

Midwest Laboratory Copy No.

Revision # Date Paaes Prepared by Approved by 4 07-21-.8 4 D Rieter B Grob Reissue 07-23-04 4 SA Coorlim B Grob (This procedure, or any portion thereof, shall not be reproduced Inany manner or distributed to any third party without the written permission of Environmental, Inc., Midwest Laboratory.)

W(DS)-01 Reissue, 07-23-04.

DETERMINATION OF GROSS ALPHA ANDIOR GROSS BETA IN WATER a

(Dissolved Solids or Total Residue)

Principle of Method Water samples containing suspended matter are filtered through a membrane filter and the filtrate is analyzed. The filtered water sample Is evaporated and the residue is transferred to a tared planchet for counting gross alpha and gross beta activity.

Reagents All chemicals should be of "reagent-gradeu or equivalent whenever they are commercially available.

Lucite: 0.5 mg/ml in acetone Nitric acid, HNO3: 16 N (concentrated), I N (62 ml ofN HNO 8 diluted to I liter)

Apparatus Filter, membrane Type AA, 0.08 Filtration equipment Planchets (Standard 2"x1/8" stainless steel , ringed planchet)

Electric hotplate Heat lamp Drying oven Muffle furnace Analytical Balance Dessicator Proportional counter 2

W(DS)-01 Reissue, 07-23-04 Procedure

1. Filter a volume of sample containing not more than 100 mg of dissolved solids for alpha assay, or not more than 200 mg of dissolved solids for beta assay.-a NOTE: For gross alpha and gross beta assay in the same sample, limit the amount of solids to 100 mg.

2. Filter sample through a membrane filter. Wash the sides of the funnel with deionized (D. I.)

water. Discard the filter, unless determining suspended solids also. See procedure W(SS-)02.

3. Evaporate the filtrate to NEAR dryness on a hot plate.

4. Add 20 ml of concentrated HNO 3 and evaporate to NEAR dryness again.

NOTE: If a water samples is known or suspected to contain chloride salts, these salts should be converted to nitrates before the sample residue is transferred to a stainless steel planchet.

(Chldrides will attack stainless steel and increase the sample solids. No correction can be made for these added solids.) Chloride salts can be converted to nitrate salts by adding concentrated HN0 3 and evaporating to near dryness.

5. Transfer quantitatively the residue to a TARED PLANCHET, using an unused plastic -

disposable pipette for each sample,. (not more than I or 2 ml at a time) evaporating each portion to dryness under the lamp. Spread residue uniformly on the planchet.

NOTE: Non-uniformity of the sample residue in the counting planchet interferes with the accuracy and precision of the method.

6. Wash the beaker with DI water several times and combine the washings and the residue in the .

planchet, using the rubber policeman to wash the walls. Evaporate to dryness.

NOTE: Rinse the rubber policeman with DI water between samples.

7. Bake in muffle furnace at 400° C for 45 minutes, cool and weigh.

NOTE: If the sample is very powdery, add a few drops (6-7) of the Lucite solution and dry under the infrared lamp for 10-20 minutes.

8. Store the sample in a dessicator until ready to count since vapors from the moist residue can damage the detector and the window and can cause erratic measurements.

9. Count the gross alpha and/or the gross beta activity in a low background proportional counter.

NOTE: If the gas-flow internal proportional counter does not discriminate for the higher energy alpha pulses at the beta plateau, the activity must be subtracted from the beta plus alpha activity. This is particularly important for samples with high alpha activity.

Samples may be counted for beta activity immediately after baking; alpha counting should be delayed at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (until equilibrium has occurred).

a For analysis of total residue (for clear water), proceed as described above but do not filter the water.

Measure out the appropriate amount and proceed to Step 3.

3

W(DS)-01 Reissue, 07-23-04 DETERMINATION OF GROSS ALPHA ANDIOR GROSS BETA IN WATER (Dissolved Solids or Total Residue)

Calculations Gross alpha (beta) activity:

A 2 pCiIL _________ A + E_____

BxCxDx2.22 BxCxDx2.22 Where:

A = Net alpha (beta) count (cpm)

B = Efficiency for counting alpha (beta) activity (cpm/dpm)

C = Volume of sample (liters)

D = Correction factor for self-absorption (See Proc. AB-02)

Eab = Counting error of sample plus background Eb = Counting error of background

References:

Radio assay Procedures for Environmental Samples, US. Department of Health, Education and Welfare.

Environmental Health Series, Jan. 1967.

EPA Prescribed Procedures for Measurement of Radioactivity in Drinking Water. August 1980.

4

-- °*Environmental, Inc.

Midwest Laboratory an Allegheny Technobloges Co.

.. ~.. .. C CfiPY 0"V4WNPQftxVW1-0ý DETERMINATION OF GROSS ALPHA AND/OR GROSS BETA IN WATER (SUSPENDED SOLIDS)

PROCEDURE NO. W(SS)-02 Prepared by Environmental Inc.

Midwest Laboratory Copy No.

Revised Paoes Revision # Date Pages Prepared by Approved by 0 11-22-85 3 B. Grob LG Huebner 1 08-14-92 3 B. Grob LG Huebner 2 07-21-98 3 SA Coodrim r 3 12-17-04 3 SA Coorlim 1 (This procedure, or any portion thereof, shall not be reproduced In any manner or distributed to any,,wlthout the written permission of Environmental Inc., Midwest Laboratory.)

W(SS)-02 Revision 3, 12-17-04 DETERMINATION of GROSS ALPHA and/or GROSS BETA In WATER (SUSPENDED SOLIDS)

Principle of Method The sample is filtered through a tared membrane filter. The filter containing the solids is placed on a ringless, stainless steel planchet and air dried, then placed in a dessicator until ready for 'weighing.

The gross alpha and gross beta activities are measured in a low background proportional counter.

Reagents Apparatus Filter, membrane, 47mm (0.8pin) 13 Filtration equipment Planchets (Standard 2"x1/8" stainless steel, ringless planchet)

Analytical Balance Dessicator Proportional counter Procedure

1. Filter sample through a TARED membrane Filter. Wash the sides of the funnel with deionized water.

NOTE: If the sample contains sand, place it in a separatory funnel, allow the sand to settle for 30 minutes, then drain off the sand at the bottom. Shake funnel and repeat as above two times.

2. Place the filter on a ringless planchet and air dry for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />..

3. Desiccate to constant weight and weigh. 3

4. Count for gross alpha and gross beta activity using a proportional counter.

5. Submit counts to data clerk for calculation.

2

W(SS)-02 Revision 3, 12-17-04 Calculations Gross alpha (beta) activity:

A 2E E2 (pCiIL) = B + b BxCxDx2.22 Bx C xD x2.22 Where:

2.22 = dpmlpCi A = Net alpha (beta) count (cpm)

B = Efficiency for counting alpha (beta) activity (cpm/dpm)

C = Volume of sample (liters)

D = Correction factor for self-absorption (See Proc. AB-02)

ESb = Counting error of sample plus background Eb = Counting error of background

References:

Radio assay Procedures for Environmental Samples, U.S. Department of Health, Education and Welfare. Environmental Health Series, January 1967.

3

2006 Annual Environmental Monitoring Report Kewaunee Power Station PartIII, ProgramSelf-Assessment and Program Changes Dominion Energy Kewaunee, Inc.

• • PRODUCTION ** Kewaunee Corrective Action System Page l of3 8S State Change History Submit to AR Screen Team AR Pre- Screening Review Create Assignments Initiate Screening Screening 0 Screen Team Que Update Pending Assignments Pending by WAAK, 5/17/2006 12:35:33 0 5/17/2006 0 5/18/2006 0 5/22/2006 15:39:35 16:07:31 by BOWER, 14:46:41 by BOWER.

GREGORY Owner by KARST, Owner KNPP Owner KNPP (None) Owner KNPP RICHARD RICHARD CAP Admin DAVID CAP Admin CAP Admin S Section I1 Activity Request Id: CAP033947 Activity Type: CAP Submit Date: 5/17/2006 12:35:33 One Line

Description:

K-2 air sampler found unplugged.

Detailed

Description:

5/17/2006 12:35:33 - WAAK, GREGORY:

The K-2 air sampler which Is located at the Kewaunee Public Service building was found unplugged. This resulted in an approximate 20 hour2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> shortage on the total run time for the week.

The sampler was plugged back In and immediately returned to operation. Flow and operation was normal.

Initiator: WAAK, GREGORY r C3 Initiator Department: 1200 Chemistry 9 Date/Time of Discovery: 5/17/2006 9:00:00 Date/Time of Occurrence: 5/17/2006 9:00:00 Identified By: Site-identified System: 00 KE Equipment # (1st): NA 4 Equipment Name (1st): Not Applicable Equipment # (2nd): (None) Equipment Name (2nd): (None)

Equipment # (3rd): (None) Equipment Name (3rd): (None)

Site/Unit: Kewaunee Why did this occur?: 5/17/2006 12:35:33 - WAAK, GREGORY:

Unknown. Power cord was unplugged.

Immediate Action Taken: 5/17/2006 16:07:31 - KARST, DAVID:

none.

Recommendations:

0 SRO Review Required?: N 9 Section 2 Operability Status: NA 6 Compensatory Actions: N Basis for Operability: 5/17/2006 16:07:31 - KARST, DAVID:

Discussed with chemistry and this sampler being out of service will be included in the annual' enviromental monitoring report. No other operability or reportability concerns.

0 Unplanned TSAC Entry: N .0 External Notification: N B Section 3 Screened?: Y V.Significance Level: C INPO OE Reqd?: N Potential MRFF?: N 0 QA/Nuclear Oversight?: N 0 Licensing Review?: N Good Catch/Well Doc'd?: NA 8 Section 4 Inappropriate Action:

Process Code: (None) Activity Code: (None)

Human Error Type: (None) Human Perf Failure Mode: (None)

Equip Failure Mode: (None) Process Failure Mode: (None)

Org & Mgmt Failure Mode: (None) Method of Discovery: (None) http://kteamtrack.dominionnet.com/tmtrack/tmtrack.dll?IssuePage&Template-viewbody... 03/21/2007

• • PRODUCTION ** Kewaunee Corrective Action System Page 2 of 3 INPO Performance Objective: (None) 0 Group Causing Prob: UNK Unknown KE Hot Buttons: K-Reportable Environ Event I Section 5 CAP Admin: KNPP CAP Admin CAP Owner: (None) 0 Project: Corrective Action .0 State: Assignments Pending Process (CAP) 0 Active/Inactive: Active :0 Submitter: WAAK, GREGORY 0 Owner. KNPP CAP Admin -, Last Modified Date: 5/26/2006 10:49:35 V Last Modifier: admin 0 Last State Change Date: 5/22/2006 15:39:35 0 Last State Changer: BOWER, RICHARD 0: Close Date:

NUTRK ID:

1. of Children: 0

References:

Update:

Prescreen Comments: 5/17/2006 19:21:21 - LONG, CRAIG:

Sig "C" Cat 4 "reportable to the NRC" CA - 1200 Chemistry This CA should be granted Management Exception from Performance Indicator because it can not be done until May 2007 when the 2006 report is published Import Memo Field:

OPR Completed?: N OLDACTIONNUM:

sub tsid: 0 orlginal-projectjid: 51 orlginal.issue..d: 033947 Site: Kewaunee Cartridge and Frame:

Response: (None) Primary Attribute: (None)

Primary Topic: (None) Secondary Attribute: (None)

Secondary Topic: (None) NMC Process: EC - Environmental Controls NMC Activity: SA - Sampling NMC Human Error Type: (None)

NMC Human Perf Fail Mode: (None) NMC Equip Failure Mode: (None)

NMC Process Fall Mode: (None) NMC OrglMgt Failure Mode: (None) i-] Attachments and Parent/Child Links

&A-$ Principal to CE01 7832: K-2 air sampler found unplugged. by WALESH, DEBRA (5/24/2006 7:10:48)

Linked To CA023938 by admin (5/26/2006 10:49:35) 4 Change History 511712008 16:07:31 by KARST, DAVID Immediate Action Taken Changed From "To '[Appended:l none.'

Operability Status Changed From (None) To NA Basis for Operability Changed From "To '[Appended:] Discussed with chemistry and this sampler being out of service will be included In the annual enviromental monitoring report. No other operability or reportability concerns.'

State Changed From AR Pre-Screen To AR Screening Que Via Transition: Submit to Screening Team Owner Changed From (None) To KNPP CAP Admin Last Modified Date Changed From 5/17/2006 12:35:33 To 5/17/2006 16:07:31 Last Modifier Changed From WAAK, GREGORY To KARST, DAVID http://kteamtrack.dominionnet com/tmtrack/tmtrack.dll?IssuePage&Template-viewbody... 03/21/2007

• • PRODUCTION ** Kewaunee Corrective Action System Page 3 of 3 Last State Change Date Changed From 5/17/2006 12:35:33 To 5/17/2006 16:07:31 Last State Changer Changed From WAAK, GREGORY To KARST, DAVID 6117/2006 19:21:21 by LONG, CRAIG System Changed From (None) To 00 KE Equipment # (1st) Changed From (None) To NA Screened? Changed From N To Y Significance Level Changed From (None) To C NMC Process Changed From (None) To EC - Environmental Controls NMC Activity Changed From (None) To SA - Sampling Group Causing Prob Changed From (None) To UNK Unknown KE Hot Buttons Changed From (None) To K-Reportable Environ Event Last Modified Date Changed From 5/17/2006 16:07:31 To 5/17/2006 19:21:21 Last Modifier Changed From KARST. DAVID To LONG, CRAIG Prescreen Comments Changed From" To '[Appended:] Sig "C" Cat 4 "reportable to the NRC" CA - 1200 Chemistry This CA should be granted Management Exception from Performance Indicator because it can not be done until May 2007 when the 2006 report is published' 6118/2006 14:46:41 by BOWER, RICHARD Last Modifier Changed From LONG, CRAIG To BOWER, RICHARD Last State Change Date Changed From 5/17/2006 16:07:31 To 5/18/2006 14:46:41 Last State Changer Changed From KARST. DAVID To BOWER, RICHARD State Changed From AR Screening Que To Screen Team Review Pending Via Transition: Screening Update Last Modified Date Changed From 5/17/2006 19:21:21 To 5/18/2006 14:46:41 5/22/2006 15:39:35 by BOWER, RICHARD Last Modified Date Changed From 5/18/2006 14:46:41 To 5/22/2006 15:39:35 Last State Change Date Changed From 5/18/2006 14:46:41 To 5/22/2006 15:39:35 State Changed From Screen Team Review Pending To Assignments Pending Via Transition: Create Assignments 6/2412006 7:09:39 by WALESH, DEBRA Last Modified Date Changed From 5/22/2006 15:39:35 To 5/24/2006 7:09:39 Last Modifier Changed From BOWER, RICHARD To WALESH, DEBRA originalprojectid Changed From 0 To 51 original-issuejld Changed From "To '033947' 6/2412006 7:10:48 by WALESH, DEBRA Last Modified Date Changed From 5/24/2006 7:09:39 To 5/24/2006 7:10:48 Attachment Added: Principal to CE017832: K-2 air sampler found unplugged.

6/26/2006 10:49:35 by admin Last Modifier Changed From WALESH. DEBRA To admin Attachment Added: Linked To CA023938 Last Modified Date Changed From 5/24/2006 7:10:48 To 5/26/2006 10:49:35 http://kteamtrack.dominionnetcom/tmtrack/tmtrack.dll?IssuePage&Template-viewbody... 03/21/2007

• • PRODUCTION ** Kewaunee Corrective Action System Page I of 2 9 State Change History O"1 Initiate Assign Work Assign Conduct Work CRICHARD 5/26/2006 10:49:27 O Owner SHANNON, Dan" by BOWER, RICHARD 5/26/2006 14:50:21 Owner ADAMS. RICHARD by ADAMS, ml Section 1 Activity Request Id: CA023938 Activity Type: Corrective Action Submit Date: 5/26/2006 10:49:27 Site/Unit: Kewaunee One Line

Description:

K-2 air sampler found unplugged.

Activity Requested: Ensure the 2006 Annual Environmental Monitoring Report notes that the air sampler at K-2 was found unplugged as identified in the parent CAP to this activity.

Assign to the RP Supervisor - ALARA with a due date of the end of May, 2007 as this is when the report needs to be issued to the NRC.

CATPR:

ni N .* Mode Change Restraint: (None)

Initiator: WAAK, GREGORY Initiator Department: 1200 Chemistry Responsible Group Code: 1100 Radiation Protection Responsible Department: Operations and Maintenance Activity Supervisor: SHANNON. Dan 0 Activity Performer: ADAMS, RICHARD 8 Section 2 Priority: 4 Due Date: 5/31/2007 Management Exception From PI?: Y 0 QAlNuclear oversight?: N 0 Licensing Review?: N NRC Commitment?: N 0 NRC Commitment Date: 0 Significance Level: C 9 Section 3 Activity Completed:

Hot Buttons: (None) 9 Section 4 QA Supervisor: (None) Licensing Supervisor: (None)

-9 Section 5 Project: Corrective Action 0 State: Conduct Work

" Active/inactive: Active 0 Owner: ADAMS, RICHARD

" Submitter: ADAMS, RICHARD Assigned Date: 5/26/2006

• Last Modified Date: 8/2/2006 13:19:06 0 Last Modifier: WALESH, DEBRA

• 0 Last State Change Date: 5/26/2006 14:50:21 0 Last State Changer: BOWER, RICHARD "*

0 Close Date:

NUTRK ID:

Child Number: 0

References:

Update:

Import Memo Field:

CAP Admin: (None) Site: Kewaunee OLD ACTIONNUM:

Cartridge and Frame:

http://kteamtrack.dominionnet comltmtrack/tmtrack.dll?IssuePage&Template-viewbody... 03/21/2007

• • PRODUCTION ** Kewaunee Corrective Action System Page 2 of 2 Response: (None) Primary-Attribute: (None)

Primary Topic: (None) Secondary Attribute: (None)

Secondary Topic: (None) INPO Performance Objective: (None) sub tsld: 883500

" Notes/Comments Pi Exemption by ADAMS, RICHARD (8/2/2006 10:15:06) f This activity has been exempted from the PI for action item age by T. Webb on 8/2/6. This item cannot be completed until the annual report is submitted to the NRC which occurs once each year in/about May. Therefore it cannot be done in accordance with routine activity durations.

S Attachments and Parent/ChIld Links Linked From CAP033947 by admin (5/26/2006 10:49:35)

Change History 5/26/2006 10:49:35 by admin -

Last Modified Date Changed From 5/26/2006 10:49:27 To 5/26/2006 10:49:35 Last Modifier Changed From ADAMS, RICHARD To admin Attachment Added: Linked From CAP033947 6/26/2006 14:50:21 by BOWER, RICHARD State Changed From Assign Work To Conduct Work Via Transition: Assign Owner Changed From SHANNON. Dan To ADAMS. RICHARD Assigned Date Changed From 5/24/2006 To 5/26/2006 Last Modified Date Changed From 5/26/2006 10:49:35 To 5/26/2006 14:50:21 Last Modifier Changed From admin To BOWER, RICHARD Last State Change Date Changed From 5/26/2006 10:49:27 To 5/26/2006 14:50:21 Last State Changer Changed From ADAMS, RICHARD To BOWER, RICHARD 8/2/2006 10:15:06 by ADAMS, RICHARD Last Modified Date Changed From 5/26/2006 14:50:21 To 8/2/2006 10:15:06 Last Modifier Changed From BOWER, RICHARD To ADAMS, RICHARD Attachment Added: PI Exemption 8/212006 13:19:06 by WALESH, DEBRA Management Exception From PI? Changed From NTo Y Last Modified Date Changed From 8/2/2006 10:15:06 To 8/2/2006 13:19:06 Last Modifier Changed From ADAMS, RICHARD To WALESH, DEBRA http://kteamtrack.dominionnet.com/tmtrack/tmtrack.dll?IssuePage&Template=viewbody... 03/21/2007

Kewaunee Power Station RadiologicalEnvironmental MonitoringManual (REMM)

Revision 10 Date APR-* ;0 Reviewed by: Date: zse A4ve-, zcpot%

Plant Ope utionseaCm t Approved by: Date: 312- 1,44 Approved by: Date:

anager, Regulatory Affairs RECORDS APR 0 4 2006

Table of Contents 1.0 Introduction ................................................................................................................... 1-1 1.1 Purpose ............................................................................................................... 1-1 1.2 Scope .................................................................................................................. 1-1 1.3 Implementation .................................................................................................... 1-1 2.0 REMIP Requirements .................................................................................................... 2-1 2.1 Technical Specification Requirements ............................................................... 2-1 2.2 REM M Requirements ........................................................................................ 2-1 REM M 2.2.1/2.3.1 Monitoring Program ............................................................. 2-3 REM M 2.2.2/2.3.2 Land Use Census .................................................................. 2-6 REM M 2.2.3/2.3.3 Interlaboratory Comparison Program ................................. 2-8 REM M 2.4.1 Reporting Requirements ............................................................... 2-9 3.0 REM P Implementation ................................................................................................ 3-1 3.1 Sam pling Requirem ents ...................................................................................... 3-1 3.2 Analysis Methodology ......................................................................................... 3-1 3.3 Detection capability (LLD) Requirements .......................................................... 3-1 3.4 Contracted Vendor (CV) Reporting Requirem ents ............................................. 3-2 3.5 Quality Control Program ..................................................................................... 3-2 3.6 Sample Descriptions ........................................................................................... 3-3 Tables & Figures Table 2.2.1-A Radiological Environmental Monitoring Program Table 2.2.1-B Type and Frequency of Collection Table 2.2.1-C Sampling Locations, Kewaunee Power Station Table 2.2.1-D Reporting Levels for Radioactivity Concentrations in Environmental Samples Table 2.3.1-A Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD)

Figure 1 Environmental Sampling Location Rev. 10 i April 4, 2006

1.0 Introduction 1.1 Purpose The purpose of this document is to define the Radiological Environmental Monitoring Program (REMP) for the Kewaunee Power Station (KPS). The REMP is required by KPS Technical Specification (TS) 6.16.b.2, "Radiological Environmental Monitoring Program."

This document is known as the Radiological Environmental Monitoring Manual (REMM) and is intended to serve as a tool for program administration and as a guidance document for contractors which implement the monitoring program.

1.2 Scope This program defines the sampling and analysis schedule which was developed to provide representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the high potential radiation exposures of MEMBERS OF THE PUBLIC resulting from plant operation. This monitoring program implements Section IV.B.2 of Appendix I to 10CFR Part 50 and thereby verifies that the measurable concentrations of radioactivity and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for the development of this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. This program has been developed in accordance with NUREG 0472.

The program will provide field and analytical data on the air, aquatic, and terrestrial radioecology of the area near the Kewaunee Power Station so as to:

1. Determine the effects of the operation of the Kewaunee Power Station on the environment;

2. Serve as a gauge of the operating effectiveness of in-plant control of waste discharges; and

3. Provide data on the radiation dose to the public by direct or indirect pathways of exposure.

1.3 Implementation This document is considered, by reference, to be part of the Offsite Dose Calculation Manual. This is as required by KPS TS 6.16.b.2. The REMM is controlled as a separate document for ease of revision, use in the field and use by contractors. This format was approved by the NRC as part of TS Amendment No. 64, which provided Radiological Effluent Technical Specifications (RETS) for KPS.

The REMP is setup to be implemented by a vendor and controlled by KPS in accordance with Nuclear Administrative Directive NAD-1.20, "Radiological Environmental Monitoring Program." Monthly reviews of the vendor's progress report are checked and approved by KPS in accordance with Surveillance Procedure SP-63-276. Annual reviews and submittals of the vendor's report and raw data are checked and approved by KPS in accordance with Surveillance Procedure SP-63-280. All sample collection, preparation, and analysis are performed by the vendor except where noted. Surveillance Procedure SP-63-164 outlines the environmental sample collection Rev. 10 1-1 April 4,2006

performed by KPS. Current vendor Quality Control Program Manuals and implementing procedures shall be kept on file at KPS.

Periodic reviews of monitoring data and an annual land use census will be used to develop modifications to the existing monitoring program. Upon approval, these modifications will be incorporated into this document so that it will accurately reflect the current radiological environmental monitoring program in effect for KPS.

I The remainder of this document is divided into two sections. The first section, 2.0 REMP Requirements, describes the different TS and REMM requirements associated with the REMP. The second section, 3.0 REMP Implementation, describes the specific requirements used to implement the REMP.

Rev. 10 1-2 April 4, 2006

2.0 REMP Requirements KPS TS Amendment No. 104 implemented the guidance provided in Generic Letter 89-01, I "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications (RETS)." These changes included:

1. Incorporation of programmaticcontrols in the Administrative Controls section of the TS to satisfy existing regulatory requirements for RETS, and

2. Relocation of the procedural details on radioactive effluents monitoring, radiological environmental monitoring, reporting details, and other related specifications from the TS to the ODCM.

Relocating the procedural details to theODCM allows for revising these requirements using the 10CFR50.59 process instead of requiring prior NRC approval using the TS Amendment process.

The RETS requirements were incorporated verbatim into the ODCM, Revision 6. Several of these requirements pertain only to the environmental monitoring program and therefore have been relocated into this document (REMM, Revision 3 and 4) and are identified as REMM requirements.

2.1. Technical Specification Requirements Technical Specification 6.16.b.2 provides the programmatic control, which requires a program to monitor the radiation and radionuclides in the environs of the plant. This is the reason for the existence of the REMP. TS 6.16.b.2 also provides the programmatic control which requires:

a. The program to perform the monitoring, sampling, analysis, and reporting in accordance with the methodology and parameters in the ODCM,

b. A land use census to be performed, and

c. Participation in an Interlaboratory Comparison Program.

The details of each requirement are described in the REMM requirements stated below.

Technical Specification 6.9.b. 1 requires an "Annual Radiological Environmental Monitoring Report" be submitted to the NRC each year. The specific contents of this report are detailed in REMM 2.4.1. Additional specific reporting requirements are listed in the other REMM requirements.

2.2 REMM Requirements The following REMM requirements include the procedural details that were originally located in the KPS RETS section and then relocated into Revision 6 of the ODCM, as discussed above. These I requirements are specific to the radiological environmental monitoring program and have been relocated into this document for ease of use and completeness.

The REMM requirements for the Monitoring Program, Land Use Census, and the Interlaboratory Comparison Program include a detailed specification (numbered 2.2.1,2.2.2, and 2.2.3 respectively)

Rev. 10 2-1 April 4, 2006

and an associated surveillance requirement (numbered 2.3.1, 2.3.2, and 2.3.3 respectively), along with the basis for the requirement. Reporting requirements are listed in specification REMM 2.4. 1.

General requirements also apply to all ODCM and REMM requirements (specifications 3.01, 3.02, 3.03, 4.01, 4.02, and 4.03). The requirements are located in the ODCM and are repeated here for convenience.

GENERAL SPECIFICATIONS 3.0.1 Compliance with the specifications contained in the succeeding text is required during the conditions specified therein; except that upon failure to meet the specifications, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a Specification shall exist when its requirements and associated ACTION requirements *are not met within the specified time intervals, If the Specification is restored prior to expiration of the specified time intervals, completion of the Action requirements is not required.

3.0.3 When a Specification is not met, except as provided in the associated ACTION requirements, reporting pursuant to TS 6.9.b and REMIM 2.4.1 will be initiated.

SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the conditions specified for individual Specifications unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILIT requirements for a Specification.

Exceptions to these requirements are stated in the individual Specification.

Surveillance Requirements do not have to be performed on inoperable equipment.

Rev. 10 2-2 April 4, 2006

REMM 2.2.1/2.3.1 MonitoringProgram SPECIFICATION 2.2.1 The radiological environmental monitoring program shall be conducted as specified in Table 2.2.1-A.

APPLICABILITY At all times.

ACTION

a. With the radiological environmental monitoring program not being conducted as specified in Table 2.2. 1-A, in lieu of a Licensee Event Report, prepare and submit to the Commission, in the Annual Radiological Environmental Monitoring Report required by TS 6.9.b.1 and REMM 2.4.1, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 2.2. 1-D when averaged over any calendar quarter in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to TS 6.9.b.3, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose' to A MEMBER OF THE PUBLIC is less than the calendar year limits of specifications ODCM 3.3.2, 3.4.2, and 3.4.3. When more than one of the radionuclides in Table 2.2. 1-D are detected in the sampling medium, this report shall be submitted if:

concentration(1) concentration(2) 1.0 reportinglevel (1) reportinglevel (2)

When radionuclides other than those in Table 2.2. 1-D are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose' to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of specifications ODCM 3.3.2, 3.4.2, and 3.4.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event the condition shall be reported and described in the Annual Radiological Environmental Monitoring Report.

'The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report.

Rev. 10 2-3 April 4, 2006

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 2.2.1-A, a sample from an alternative location will be substituted, noting the reason for the unavailability in the Annual Radiological Environmental Monitoring Report. When changes in sampling locations are permanent, the sampling schedule in the RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) will be updated to reflect the new routine and alternative sampling locations and this revision will be described in the Annual Radiological Environmental Monitoring Report.

Rev. 10 2-4 April 4, 2006

SURVEILLANCE REQUIREMENT 2.3.1 The radiological environmental monitoring samples shall be collected pursuant to Table 2.2.1-A from the specific locations given in the table and figure(s) in the -

REMM, and shall be analyzed pursuant to the requirements of Table 2.2.1-A and the detection capabilities required by Table 2.3.1-A.

BASIS The radiological environmental monitoring program required by this specification provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. Program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terns of the lower limits of detection (LLDs). The LLDs required by Table 2.3.1 -A are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques,"

Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Discussion KPS TS 6.16.b.2(a) requires that the monitoring, sampling, analysis, and reporting of radiation and -

radionuclides in the environment be done in accordance with the methodology and parameters in the ODCM.

Rev. 10 2-5 April 4, 2006

REMM 2.2.2/2.3.2 Land Use Census SPECIFICATION 2.2.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 10 meteorological sectors of the nearest milk 2

animal, the nearest residence and the nearest garden 2 of greater than 50 m (500 fe) producing broad leaf vegetation.

APPLICABILITY At all times.

ACTION

a. With a land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in specification ODCM 4.4.3, in lieu of a Licensee Event Report, identify the new location(s) in the next Annual Radiological Environmental Monitoring Report pursuant to TS 6.9.b.1 and REMM 2.4.1.

b. With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with specification REMM 2.2.1, add the new location(s) to the radiological environmental monitoring program within 30 days. The sampling location(s), excluding the control station location, having a lower calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program. In lieu of a Licensee Event Report, identify the new location(s) in the next Annual Radiological Environmental Monitoring Report pursuant to TS 6.9.b. 1 and REMM 2.4.1 and also include in the report a revised figure(s) and table for the REMM reflecting the new location(s).

SURVEILLANCE REQUIREMENT 2.3.2 The land use census shall be conducted during the growing season once per 12 months using reasonable survey methods, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Monitoring Report pursuant to TS 6.9.b. 1 and REMM 2.4.1.

2Sampling of leaf vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 2.2.1-A item 4c shall be followed, including analysis of control samples.

Rev. 10 2-6 April 4, 2006

BASIS This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the door-to-door survey, from aerial survey or from consulting with local agricultural authorities. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR Part 50. Restricting the census to gardens of greater than 50 m 2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made:

1. 20% of the garden was used for growing leafy vegetation (i.e., similar to lettuce and cabbage), and

2. A vegetation yield of 2 kg/mi.

Discussion KPS TS 6.16.b.2(b) requires that a land use census be performed to ensure that changes in the use of I areas at and beyond site boundary are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census.

Rev. 10 2-7 April 4, 2006

REMM 2.2.3/2.3.3 InterlaboratoryComparisonProgram SPECIFICATION 2.2.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.

APPLICABILITY At all times.

ACTION

a. With analyses not being performed as required above, report corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Monitoring Report pursuant to TS 6.9.b.1 and REMM 2.4.1.

SURVEILLANCE REQUIREMENT 2.3.3 The Interlaboratory Comparison Program shall be described in the REMM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Monitoring Report pursuant to TS 6.9.b.1 and REMM 2.4.1.

BASIS The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR Part 50.

Discussion KPS TS 6.16.b.2(c) requires participation in an approved Interlaboratory Comparison Program to ensure that an independent check is performed of the precision and accuracy of radioactive materials measurements.. This will demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR Part 50.

Rev. 10 2-8 April 4, 2006

REMM 2.4.1 ReportingRequirements 2.4.1 The Annual Radiological Environmental Monitoring Report shall include:

a. Summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with pre-operational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by specification REMM 2.2.2.

b. The results of analyses of radiological environmental samples and of environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the Radiological Environmental Monitoring Manual (REMM), as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report when applicable.

c. A summary description of the radiological environmental monitoring program; legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by specification REMM 2.2.3; discussion of all deviations from the sampling schedule of Table 2.2.1-A; and discussion of all analyses in which the LLD required by Table 2.3.1-A was not achievable.

Discussion KPS TS 6.9.b.1 provides the programmatic control, which requires that an Annual Radiological I Environmental Monitoring Report be submitted to the NRC. It also states that this report shall include summaries, interpretations, and analysis of trends of the results of the REMP for the reporting period.

The procedural details of this report are included in this specification. Specifications REMM 2.2.1/2.3.1, 2.2.2/2.3.2, and 2.2.3/2.3.3 also include specific reporting requirements. These specifications reference this REMM specification, along with TS 6.9.b. 1, as the method for reporting deviations from the current program during the reporting period, and require that this information be included in the Annual Radiological Environmental Monitoring Report.

Rev. 10 2-9 April 4, 2006

3.0 REMP Implementation The Radiological Environmental Monitoring Program for KPS is under the direction of a Contracted Vendor (CV). This section describes this program, as required by REMM 2.2.1 and the process the CV uses to perform it.

3.1 Sampling Requirements Table 2.2.1-A identifies the various samples required by the REMP. Identified in the "available sample locations" column in Table 2.2.1-A are the sample locations selected, in conjunction with the vendor, to meet or exceed the REMP requirements. Table 2.2.1-B includes the same requirements as in Table 2.2.1-A but presents the information in a different format by identifying the type of samples required at each location and the collection frequency. Table 2.2.1-C identifies the location and description of each sample location. Figure 1 shows the physical location of each sample point on an area map.

3.2 Analysis Methodology Analytical procedures and counting methods employed by the CV will follow those recommended by the U.S. Public Health Service publication, Radioassay Procedures for Environmental Samples, January 1967; and the U.S. Atomic Energy Commission Health and Safety Laboratory, HASL Procedures Manual (HASL-300), 1972. The manual is also available on-line at www.eml.doe.gov/publications/procman.

Updated copies will be maintained in KPS's vault.

3.3 Detection Capability (LLD) Requirements The required detection capabilities for environmental sample and analysis are tabulated in terms of lower limits of detection (LLDs) in Table 2.3.1-A. The LLDs required by Table 2.3.1-A are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40,586-93 (1968), and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Rev. 10 3-1 April 4, 2006

3.4 ContractedVendor Reporting Requirements Monthly ProgressReports Monthly progress reports will include a tabulation of completed analytical data on samples obtained during the previous 30 day period together with graphic representations where trends are evident, and the status of field collections. One copy of the reports will be submitted within 30 days of the reporting month.

Annual Reports Annual reports will be submitted in two parts. Part I, to be submitted to the NRC, will be prepared in accordance with NRC Regulatory Guide 4.8. It will contain an introductory statement, a summary of results, description of the program, discussion of the results, and summary table. Part I1of the annual report will include tables of analytical data for all samples collected during the reporting period, together with graphic presentation where trends are evident and statistical evaluation of the results. Gamma scan data will be complemented by figures of representative spectra. Draft copies of each annual report will be due 60 days after completion of the annual period. After final review of the draft document, one photoready copy of the revised annual report will be sent to KPS for I, printing.

Non-Routine Reports If analyses of any samples collected show abnormally high levels of radioactivity, KPS will be notified by telephone immediately after data becomes available.

Action Limits The CV will report any radioactive concentrations found in the environmental samples which exceed the reporting levels shown in Table 2.2.1-D, CV to KPS column. These levels are set below the NRC required reporting levels (KPS to NRC column) so actions can be initiated to prevent exceeding the NRC concentration limits.

3.5 Quality ControlProgram To insure the validity of the data, the CV maintains a quality control (QC) program, which employs quality control checks, with documentation, of the analytical phase of its environmental monitoring studies. The program is defined in the CV's QC Program Manual, and procedures are presented in the CV QC Procedures Manual. The program shall be reviewed and meet the requirements of Regulatory Guide 4.15 and 10CFR21. All data related to quality control will be available for review by Dominion Energy Kewaunee upon reasonable prior notification. Proprietary information will be identified so that it may be treated accordingly.

Updated copies of the Quality Control Program Manual and the Quality Assurance Program Manual will be maintained in KPS's vault.

Rev. 10 3-2 April 4, 2006

3.6 Sample Descriptions A description of each of the samples required by this program follows:

Airborne Particulates Airborne particulates are collected at six locations (K-lf, K-2, K-7, K-8, K-16, K-31) on a continuous basis on a 47 mm diameter membrane filter of 0.8 micron porosity at a volumetric rate of approximately one cubic foot per minute (CFM). The filters are changed weekly, placed in glassine protective envelopes, and dispatched by U.S. Mail to the CV for Gamma Isotopic Analysis.

Filter samples are analyzed weekly for gross beta activity after sufficient time (usually 3 to 5 days) has elapsed to allow decay of Radon and Thoron daughters. If gross beta concentration in air particulate samples are greater than ten (10) times the yearly mean of the control samples, gamma isotopic analysis shall be performed on the individual samples. Quarterly composites from each location receive Gamma Isotopic Analysis using a Germanium detector. All identifiable gamma-emitters are quantified. Reporting units are pCi/rn 3.

Airborne Iodine All air samplers are equipped with charcoal traps installed behind the particulate filters for collection of airborne 1-131. The traps are changed once every two weeks. Iodine-131 is measured by Gamma Isotopic Analysis.

Periphyton (Slime) orAquatic Vegetation Periphyton (slime) or aquatic plant samples are collected at or near locations used for surface water sampling. They are collected twice during the year (2nd and 3rd quarter), if available. The samples are analyzed for gross beta activity and, if available in sufficient quantity, for Sr-89, Sr-90, and by Gamma Isotopic Analysis. Reporting units are pCi/g wet weight.

Fish Fish are collected three times per year (second, third, and fourth quarters) near the discharge area (K-id). Flesh is separated from the bones and analyzed for gross beta activity and by Gamma Isotopic Analysis. The bones are analyzed for gross beta activity and Sr-89 and Sr-90. Reporting units are pCi/g wet weight.

Domestic Meat Domestic meat (chickens) may be collected once a year during the 3rd quarter, from six locations in the vicinity of the plant (K-20, K-24, K-27, K-29, K-34, and K-32). Samples may not be available every year at every location due to farmer preference. At least one control and one indicator should be collected. The flesh is analyzed for gross alpha, gross beta, and by Gamma Isotopic Analysis to identify and quantify gamma-emitting radionuclides. Reporting units are pCi/g wet weight.

Rev. 10 3-3 April 4, 2006

Ambient Radiation Two packets of thermoluminescent dosimeters (CaS 04: Dy cards) are placed at forteen locations, six of which are air sampling locations (K-If, K-2, K-7, K-8, K-16, and K-31) and four of which are milk sampling locations (K-3, K-5, K-25, and K-39); the remaining four locations are K -15, K-17, K-27, and K-30. One packet is changed quarterly and one annually. Annual TLDs will serve as an emergency set to be read when needed. They will be exchanged annually (without reading) if not read during the year. To insure the precision of the measurement, each packet will contain two cards with four dosimeters each (four sensitive areas each for a total of eight). For protection against moisture each set of cards is sealed in a plastic bag and placed in a plastic container. --

Each card is individually calibrated for self-irradiation and light response. Fading is guaranteed by the manufacturer (Teledyne Isotopes) not to exceed 20% in one year. Minimum sensitivity for the multi-area dosimeter is 0.5 mR defined as 3 times the standard deviation of the background. Maximum Error (1 standard deviation) - 6OCo Gamma +/-0.2 mR or +/-3%, whichever is greater. The maximum spread between areas on the same dosimeter is 3.5% at 1 standard deviation.

Reporting units for TLDs are mR/91 days for quarterly TLDs and mR/exposure period for annual TLDs.

Tests for uniformity and reproducibility of TLDs as specified in ANSI N545-1981 and NRC Regulatory Guide 4.13, are performed annually.

Well Water One gallon water samples are taken once every three months from four off-site wells, (K-10, K-11, K-13, and K-25) and two on-site wells (K-lh and K-lg). All samples are analyzed for gross beta in the total residue, K-40, tritium, and by Gamma Isotopic Analysis. Samples from one on-site well are analyzed for Sr-89, and Sr-90. Samples from K-lh and K-lg are also analyzed for gross alpha.

Reporting units are pCi/l.

Precipitation A monthly cumulative sample of precipitation is taken at Location K-11. This sample is analyzed for tritium. Reporting units are pCi/l.

Milk Milk samples are collected from two herds that graze within three miles of the reactor site (K-25 and K-34); from four herds that graze between 3-7 miles of the reactor site (K-3, K-5, K-38, and K-39);

and one from a dairy in Green Bay (K-28), 26 miles from the reactor site.

The samples are collected twice per month during the grazing period (May through October) and monthly for the rest of the year. To prevent spoilage the samples are treated with preservative. All samples are analyzed by Gamma Isotopic Analysis and for iodine -131 immediately after they are received at the laboratory. To achieve required minimum sensitivity of 0.5 pCi/1, iodine is separated Rev. 10 3-4 April 4, 2006

on an ion exchange column, precipitated as palladium iodide and beta counted. Monthly samples and monthly composites of semimonthly samples are then analyzed for Sr-89 and Sr-90. Potassium and calcium are determined and the 137Cs/gK and 9°Sr/gCa ratios are calculated. Reporting units are pCi/l except for stable potassium and calcium, which are reported in g/l.

If milk samples are not available, green leafy vegetables will be collected on a monthly basis (when available) from Locations K-10, K-11, and K-26.

Grass Grass is collected three times per year (2nd, 3rd, and 4th quarters) from the six dairy farms (K-3, K-5, K-25, K-34, K-38, and.K-39) and from two on-site locations (K-lb and K-if). The samples are analyzed for gross beta activity, for Sr-89 and Sr-90, and Gamma Isotopic Analysis to identify and quantify gamma-emitting radionuclides. Reporting units are pCi/g wet weight.

Cattlefeed Once per year, during the first quarter when grass is not available, cattlefeed (such as hay or silage) is collected from the six dairy farms. The analyses performed are the same as for grass. Reporting units are pCi/g wet weight.

Vegetables and Grain Annually, during the 3rd quarter, samples of five varieties of vegetables grown and marketed for human consumption are collected from K-17 and/or K-26, depending upon the availability of samples. If samples are not available from these locations, samples may be obtained from any local source so there is some sample of record. The location will be documented. In addition, two varieties of grain, if available, are collected annually from the farmland owned by Dominion Energy Kewaunee (K-23) and rented to a private individual for growing crops. The analyses performed are the same as for grass. Reporting units are pCi/g wet weight.

Eggs Quarterly samples of eggs can be taken from K-24, K-27, and K-32. At least one control and one indicator should be collected. The samples are analyzed for gross beta activity, for Sr-89 and Sr-90, and Gamma Isotopic Analysis to identify and quantify gamma-emitting radionuclides. Reporting units are pCi/g wet weight.

Soil Twice during the growing season samples of the top two inches of soil are collected from the six dairy farms and from an on-site location (K-If). The soil is analyzed for gross alpha and gross beta activities, for Sr-89 and Sr-90, and Gamma Isotopic Analysis to identify and quantify gamma-emitting manmade radionuclides. Reporting units are pCi/g dry weight.

Rev. 10 3-5 April 4, 2006

Surface Water Surface water is sampled monthly from Lake Michigan at the KPS discharge (K-ld), and at Two Creeks Park, 2.5 miles south of the reactor site (K-14). Samples are collected monthly at the Green I

Bay Municipal Pumping station between Kewaunee and Green Bay (K-9). Raw and treated water is collected. Monthly samples are also taken, when available, from each of the three creeks (K-la, K-lb, K-le) that pass through the reactor site and from the drainage pond (K-lk) south of the plant. The samples are taken at a point near the mouth of each creek and at the shore of the drainage pond. The water is analyzed for gross beta activity in:

a. The total residue,

b. The dissolved solids, and

c. The suspended solids.

The samples are also analyzed for K-40 and by Gamma Isotopic Analysis. Quarterly composites from all locations are analyzed for tritium, Sr-89 and Sr-90. Reporting units are pCi/l.

Bottom Sediments Five samples of Lake Michigan bottom sediments, one at the discharge (K-ld), one from 500 feet north of the discharge (K-ic), one from 500 feet south of the discharge (K-lj), and one at the Two Creeks Park (K-14), one at the Green Bay Municipal Pumping Station (K-9) are collected semi-annually (May and November). The samples are collected at the beach in about 2-3 feet of water. All samples are analyzed for gross beta activity, for Sr-89 and Sr-90 and by Gamma isotopic Analysis. Since it is known that the specific activity of the sediments (i.e., the amount of radioactivity per unit mass of sediment) increases with decreasing particle size, the sampling procedure will assure collection of very fine particles. Reporting units are pCi/g dry weight.

Rev. 10 3-6 April 4, 2006

Table 2.2.1-A RadiologicalEnvironmentalMonitoring Program Exposure Pathway Minimum Available Sample Sampling, a b Collection and Type of Analysis And/Or Sample Required Samples j Locations b Analysis Frequency

1. Direct RadiationC 5 Inner Ring locations K-5, K-25, K-27, See Table 2.2.1-B Gamma dose K-7, K-iF, K-30 6 Outer Ring locations K-2, K-3, K-15, K-17, K-8, K-31, K-39 1 Control location K-16 1 Population center K-7 1 Special interest location K-8 1 Nearby resident K-27

2. Airborne Radioiodine 3 samples close to the site K-if, K.2, K-7, K.8, See Table 2.2.1.B Iodine (1-131) by boundary in highest K-31 Continuous Gamma Isotopicf and Particulates average X/Q sampler operation Iodine; charcoal 1 sample fiom the closest K-7 Particulates Particulates; gross community having the See Table 2.2.1-B beta analysis' highest X/Q Gamma isotopic 1 sample from a control K-16d See Table 2.2.1-B of composite (by location location) f

3. Waterborne

a. Surface8 1 Upstream sample K-la, K-9, K-id Grab sample Gross Beta, 1 Downstream sample K-le, K-14, K-lk, K-lb See Table 2.2.1-B Gamma isotopic f Composite of grab samples for tritium, and Sr 89/90

b. Ground 1-2 location likely to be K-ig, K-lhh Grab sample Gamma isotopic',

affected d See Table 2.2. I-B tritium analysis Gross Beta, Gross Alpha, Sr 89/90

c. Drinking 1-3 samples of nearest K-10, K-11, K-13, K-25 Grab sample Gross beta and water supply See Table 2.2.1-B gamma isotopic t analysis. Tritium analysis of the composite of monthly grab samples.

d. Sediment from 1 sample from K-14, K-lc, K-id, Grab sample Gamma isotopic shoreline downstream area with K-lj, K-9 See Table 2.2.1-B analysis potential for recreational Gross Beta, value Sr 89/90 Rev. 10 Page 1 of 3 April 4, 2006

Table 2.2.1-A RadiologicalEnvironmentalMonitoringProgram Exposure Pathway Minimum Available Sample Sampling, Collection and Type of Analysis Required Samples l Locations b And/Or Sample LAnalysis Frequency

4. Ingestion

a. Milk Samples from milking K-5, K-25, K-34 See Table 2.2.1-B 1-131 animals in 3 locations Gamma Isotopic f within 5 km having the highest dose potential. SR 89/90 1 alternate location K-38, K-39 I control location K-3, K-28

b. Fish 3 random samplings of K-id See Table 2.2.1-B Gamma isotopic f commercially and and edible portions recreationally important Gross Beta species in the vicinity of the discharge. Sr 89/90 on bones

c. Food Products Samples of leaf 2 samples nearest See Table 2.2.1-B Gamma isotopic f vegetables grown nearest highest predicted and 1-131 each of two different annual average ground Analysis.

offsite locations within 5 level D/Q. K-10, K-11 miles of the plant if milk sampling is not performed. 1 sample 15-30 km distant if milk sampling is not performed. K-26

5. Miscellaneous samples not identified in NUREG-0472

a. Aquatic Slime None required K-lk See Table 2.2.1-B Gross Beta K-la, K-lb, K-le activity and if available Sr-89, K-14, K-id Sr-90 and Gamma Isotopic!

K-9 (control)

b. Soil None required K-If, K-5, K-25, K-39 Gross Alpha/Beta K-34, K-38 See Table 2.2.1-B Sr-89 and Sr-90 K-3, (control) Gamma Isotopicf

c. Cattlefeed None required K-5, K-25, K-39 Gross Beta K-34, K-38 See Table 2.2.1-B Sr-89 and Sr-90 K-3,(control) Gamma Isotopict

d. Grass None required K-lb, K-If, K-25; K-39 Gross Beta K-5, K-34, K-38 See Table 2.2.1-B Sr-89 and Sr-90 K-3,(control) Gamma Isotopicf

e. Domestic Meat None required K-20, K-24, K-27, K-29 Gross Alpha/Beta See Table 2.2.1-B K-32 (control), K-34 Gamma Isotopicf Rev. 10 Page 2 of 3 April 4,2006

Table 2.2.1-A RadiologicalEnvironmentalMonitoringProgram Exposure Pathway Minimum Available Sample Sampling, a cationsb Collection and Type of Analysis And/Or Sample Required Samples Locations Analysis Frequency I

f. Eggs None required K-27 See Table 2.2.1-B Gross Beta K-32 Sr-89/90 K-24 Gamma Isotopicf

g. Precipitation None required K-11 See Table 2.2.1-B Tritium

h. Vegetables/Grain None required K-17, K-23 See Table 2.2.1-B Gross Beta Sr-89/90 K-26 (control) Gamma Isotopicf Table Notations

a. The samples listed in this column describe the minimum sampling required to meet REMP requirements.

b. Additional details of sample locations are provided in Table 2.2.1-C and Figure 1. The REMP requires that samples to be taken from each of the "available sample locations" listed (see section 3.1). Deviations from the required sampling schedule will occur if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, reasonable efforts shall be made to complete corrective actions prior to the end of the next sampling period.

All deviations from the sampling schedule shall be documented, as required by REMM 2.4.1 .c, in the Annual Radiological Environmental Monitoring Rep6rt. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the REMM. The cause of the unavailability of samples for that pathway and the new location(s) for obtaining replacement samples will be identified in the Annual Radiological Environmental Monitoring Report.

c. For the purposes of this table, each location will have 2 packets of thermoluminescent dosimeters (TLDs). The TLDs are CaSO4: Dy cards with 2 cards/packet and 4 dosimeters/card (four sensitive areas each for a total of eight dosimeters/packet). The NRC guidance of 40 stations is not an absolute number. The number of direct radiation monitoring stations has been reduced according to geographical limitations; e.g., Lake Michigan. The frequency of analysis or readout for TLD systems depends upon the characteristics of the specific system used and selection is made to obtain optimum dose information with minimal fading.

d. The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.

e. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

f. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

g. The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. The "downstream" sample shall be taken in an area near the mixing zone.

h. Ground water samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

Rev. 10 Page 3 of 3 April 4, 2006

Table 2.2.1-B Type and Frequency of Collection Location Weekly Biweekly Monthly Quarterly Semi-Annually ] Annually K-la SW SLO K-lb SW GRa SLf _W BSb K-lc K-ld SW Fa BSb SL' K-le SW SLI K-If AP Al GR" TLD SO K-lg WW K-lh WW BSb K-lj K-lk SW SLI I K-2 AP Al TLD K-3 MIC GR' TLD CFdso K-5 Mr GR' TLD CFd so K-7 AP Al TLD K-8 AP AI TLD K-9 SW BSb SLO K-10 GLV e WW K-I1 PR, WW GLV _ I K-13 WW I K-14 SW BSb SLf K-15 ThD K-16 AP Al TLD K-17 TLD VE K-20 DM K-23 GRN K-24 EG DM K-25 Mr GR' TLD CId WW so K-26 GLVC VE K-27 EG TLD DM K-28 MI K-29 DM K-30 TLD K-31 AP Al TLD K-32 EG DM K-34 MI' GRa CFd SQ DM Rev. 10 Page 1 of 2 April 4, 2006

Table 2.2.1-B Type andFrequency of Collection Location Weekly Biweekly Monthly Quarterly Semi-Annually Annually K-38 UM ORa CF' SO K-39 Mc TLD GRa CFd so

a. Three times a year, second (April, May, June), third (July, August, September), and fourth (October, November, December) quarters

b. To be collected in May and November

c. Monthly from November through April; semimonthly from May through October

d. First (January, February, March) quarter only

e. Alternate if milk is not available

f. Second and third quarters Code Description Code Description Code Description Al Airborne Iodine F1 Fish SO Soil AP Airborne Particulate GR Grass SW Surface Water BS Bottom Sediment GRN Grain TLD Thermoluminescent Dosimeter CF Cattlefeed Mýii Milk VE Vegetables DM Domestic Meat PR Precipitation WW Well Water EG Eggs SL Slime GLV Green Leafy Vegetables Rev. 10 Page 2 of 2 April 4, 2006

Table 2.2.1-C Sampling Locations, Kewaunee Power Station I Distance Code Typea (IMIiles)b and Location Sector K-1 Onsite K-la I 0.62 N North Creek K-lb I 0.12 N Middle Creek K-ic I 0.10 N 500' North of Condenser Discharge K-id I 010 E Condenser Discharge K-le I 0.12S South Creek K-lf I 0.12 S Meteorological Tower K-lg I 0.06 W South Well K-lh I 0.12 NW North Well K-Ij I 0.10 S 500' south of Condenser Discharge K-lk I 0.60 SW Drainage Pond, south of plant K-2 C 9.5 NNE WPS Operations Building in Kewaunee K-3 C 6.0 N Lyle and John Siegmund Farm, N2815 Hy 42, Kewaunee K-4(h) I 3.0 N Tom Stangel Farm, E4804 Old Settlers Rd, Kewaunee K-5 I 3.5 NNW Ed Paplham Farm, E4160 Old Settlers Rd, Kewaunee K-6(e) C 6.7 WSW Novitsky Farm, E1870 Cty Tk BB, Denmark K-7 I 2.75 SSW Ron Zimmerman Farm, 17620 Nero Rd, Two Rivers Saint Isadore the Farmer Church, 18424 Tisch Mills Rd, Tisch I K-8 C 5.0 WSW ls Mills Green Bay Municipal Pumping Station, six miles east of Green K-9 C 11.5 NNE Bay (sample source is Lake Michigan from Rostok Intake 2 miles north of Kewaunee)

K-10 I 1.5 NNE Turner Farm, Kewaunee Site K-11 I 1.0 NW Harlan Ihlenfeld Farm, N879 Hy 42, Kewaunee K-12(i) I 1.5 WSW LeCaptain Farm, N491 Woodside Rd, Kewaunee K-13 C 3.0 SSW Rand's General Store, Two Creeks K-14 I 2.5S Two Creeks Park, 2.5 miles south of site K-15 C 9.25 NW Gas Substation, 1.5 miles north of Stangelville K-16 C 26 NW WPS Division Office Building, Green Bay, Wisconsin K-17 I 4.25 W Jansky's Farm, N885 Cty Tk B, Kewaunee K-19(f) I 1.75 NNE Wayne Paral Farm, N1048 Lakeview Dr., Kewaunee K-20 I 2.5 N Carl Struck Farm, N1596 Lakeshore Dr., Kewaunee K-23 I 0.5 W 0.5 miles west of plant, Kewaunee site Rev. 10 Page 1 of 2 April 4, 2006

Table 2.2.1-C Sampling Locations,Kewaunee Power Station I Distance Code Typea (Miles)b and Location Sector K-24 I .5.45 N Fectum Farm, N2653 Hy 42, Kewaunee K-25 I 2.75 SW Wotachek Farm, E3968 Cty Tk BB, Two Rivers K-26(d) C 10.7 SSW Bertler's Fruit Stand (8.0 miles south of "BB")

K-27 I 1.5 NW Schlies Farm, E4298 Sandy Bay Rd K-28 C 26 NW Hansen Dairy, 1742 University Ave., Green Bay, Wisconsin K-29 I 5.75 W Kunesh Farm, E3873 Cty Tk G, Kewaunee K-30 I 1.00 N End of site boundary K-31 I 6.25 NNW E. Krok Substation, Krok Road K-32 C 11.50 N Piggly Wiggly, 931 Marquette Dr., Kewaunee K-33(g) I 4.25 W Gary and Lynn Holly Farm, E2885 Holly Lane, Tisch Mills K-34 I 2.5 N Leon and Vicky Struck Farm, N1549 Lakeshore Drive, Kewaunee K-35(j) C 6.75 WNW Jean Ducat Farm, N1215 Sleepy Hollow, Kewaunee K-36(j) I Fiala's Fish Market, 216 Milwaukee, Kewaunee K-37 (k) 1 4.00 N Gary and Ann Hardtke Farm, E4282 Old Settlers Road, Kewaunee K-38 I 3.8 WNW Dave Sinkula Farm, N890 Town Hall Road, Kewaunee K-39 I 4.00 N Francis Wotja Farm, N1859 Lakeshore Road, Kewaunee

a. I = indicator; C = control.

b. Distances are measured from reactor stack.

C. Deleted

d. Location K-18 was changed because Schmidt's Food Stand went out of business. It was replaced by Bertler's Fruit Stand (K-26).

e. Replaced by K-33 in summer of 2000. Retired from farming.

f. Replaced by K-34 in summer of 2000. Retired from farming.

g. Replaced by K-35 in fall of 2000.

h. Sold farm in summer of 2000, replaced by K-25

i. Retired from farming in summer of 2000

j. Removed from the program in Fall of 2001

k. Removed from the program in Fall of 2002 Rev. 10 Page 2 of 2 April 4, 2006

Table 2.2.1-D Reporting Levels for Radioactivity Concentrationsin EnvironmentalSamples Reporting Levels Medium Radionuclide CV to KPS_[_ KPS to NRCb I

Airborne Particulate or Gases (pCi/m3) Gross Beta 1 --

1-131 (Charcoal) 0.1 0.9 Cs-134 1 10 Cs- 137 1 20 Precipitation (pCi/i) H-3 1,000 --

Water (pCi/l) Gross Alpha 10 -

Gross Beta 30 -

H-3 10,000 20,OO0C Mn-54 100 1,000 Fe-59 40 400 Co-58 100 1,000 Co-60 30 300 Zr-Nb-95 40 400 Cs-134 10 30 Cs-137 20 50 Ba-La-140 100 200 Sr-89 10 --

Sr-90 10 --

Zn-65 30 300 Milk (pCi/1) 1-131 1.0 3 Cs-134 20 60 Cs-137 20 70 Ba-La-140 100 300 Sr-89 10 Grass, Cattle Feed, and Vegetables (pCi/g Gross Beta 30 --

wet) 1-131 0.1 0.1 Cs-134 0.2 1 Cs-137 0.2 2 Sr-89 1 --

Sr-90 1 --

Rev. 10 Page 1 of 2 April 4,2006

Table 2.2.1-D ReportingLevels for Radioactivity Concentrationsin EnvironmentalSamples Reporting Levels Medium Radionuclide CV to KPS" JlS to NRC" I

Eggs (pCi/g wet) Gross Beta 30 --

Cs-134 0.2 1 Cs-137 0.2 2 Sr-89 1 --

Sr-90 1 --

Soil, Bottom Sediments (pCi/g) Gross Beta 50 - -

Cs-134 5 - -

Cs-137 5 - -

Sr-89 5 --

Sr-90 5 --

Meat (pCi/g wet) Gross Beta (Flesh, 10 - -

Bones)

Cs-134 (Flesh) 1.0 1.0 Cs-137 (Flesh) 2 2.0 Sr-89 (Bones) 2 - -

Sr-90 (Bones) 2 - -

Fish (pCi/g wet) Gross Beta (Flesh, 10 --

Bones)

Mn-54 -- 30.0 Fe-59 -- 10.0 Co-58 -- 30.0 Co-60 -- 10.0 Cs-134 (Flesh) 1 1.0 Cs-137 (Flesh) 2 2.0 Sr-89 (Bones) 2 --

Sr-90 (Bones) 2 --

Zn-65 (Bones) -- 20

a. Radionuclides will be monitored by the CV and concentrations above the listed limits will be reported to KPS.

b. Concentrations above the listed limits will be reported to NRC as required by REMM 2.4.1.

c. For drinking water samples, this is 40CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l may be used.

Rev. 10 Page 2 of 2 April 4,2006

Table 2.3.1-A Detection Capabilitiesfor EnvironmentalSample Anadysis' Lower Limit of Detection (LLD) b,c AnlssParticulate Water Airborne or Fish Milk (pCi/l) Food Products Sediment Analysis (pCi/) Gases (rci/m3) (pCi/kg, wet) (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 H-3 2000d Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zr-Nb-95 15 1-131 le 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 Zn-65 30 260 Rev. 10 Page 1 of 3 April 4, 2006 I I I I . 1,. I I I tý- (. - I - L. t, 1. 1 .. . [. I I

Table Notationsfor Table 2.3.1-A

a. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environment Monitoring Report.

b. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

c. The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD =

E x V x 2.22 x Y x exp(--yAt)

Where:

LLD is the a priori lower limit of detection as defined above, as picocuries per unit mass or volume, Sb is the standard deviation of the background counting rate or of the counting rate of blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size-in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, y is the radioactive decay constant for the particular radionuclide, and At for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting, Typical values of E, V, Y, and At should be used in calculation.

Rev. 10 Page 2 of 3 April 4, 2006

Table Notationsfor Table 2.3.1-A (con't)

It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Monitoring Report.

d. If no drinking water pathway exists, a value of 3,000 pCi/i may be used.

e. LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

Rev. 10 Page 3 of 3 April 4, 2006

FIGURE 1 iK--9 m(GREEN BAY).

K- I

[] K-L*K-2 K-3 b

'Illy 8N

,K-2 K-1 3.1 K.

! al K-4

-* ," ,:K-20

~v I

..... -

• o .*pil 4K200

TRACKING AND PROCESSING RECORD Initiated By: Richard W. Adams Date: 11/21/05 Dept: RP Ext. 8360 Document No.: REMM Current Rev. No.: 9 New Rev. No.: 10

Title:

Radiological Environmental Monitoring Manual Reqesed ue/Required Date n- Activity: El Admin Hold E] Temp Change El One Time Only 0 Revision El New El Deletion Temp Change Signatures 0 N/A Print Sign Date El Technical Review /

W EStaff Approval / _ _ _ _

El SRO Approval /

-* TTRACK / CAP # Date FE] Priority: E Immediate Action El Non-Urgent - Perform Later El Rejected - See Comments Safety El Yes PORC E] Yes SRO Approval - E] Yes NA Related E] No Review [ No Temp Changes LI No Level of Use: E] Continuous Use E] Reference Use El Information Use 0 NA Is Formal Training (InitiallContinuing) Likely Affected? (See Section 6.2.8.6) El Yes 0 No (If yes, forward a copy of Form GNP-03.01.01-4, "Notification of Document Modification," and the new or revised document, or procedure to the Training Department Supervisor for training assessment.) [CAP01 90531 L* Reviewers Required Signatures Print Sign Date Technical / /

El Minor /

Editorial Any ýQie a ii (nf' dk~ f~2o El Validation / f El Cross Discipline

[: Oversight (QC) 0 Yes 50.59 5 Screen Form Attached? [ Yes W olklrl G 50.59 Applicability Form Attached?

50.59 Pre-Screen Form Attached? [ Yes No 50.59 Evaluation Attached? Y I

1) => Process Owner Review Recommendation 2) E] = PORC Review Recommendation A i~r

&J Approval E. Disapproval E] Approval El Disapproval 6 " tJ -

( aive Validation Revi [NK]Yes [1 No Meeting No.

Process Owner Signature (print/sign) Date Plant Manager Signature (print/sign) Date S Effective W

Date: APR 0 4 2M Responsible Manager Review - Directives (print/sign) Date Clears Temp Change/Admin Hold dated:

Form GNP-03.01.01-1 Rev. R Date: OCT 4 2005 Page 37 of 56 INFORMATION USE

DESCRIPTION OF CHANGE SHEET Document No.: REMM Current Rev. No.: 9 New Rev. No.: 10 PaRe 1 of I Describe Change Describe Reason As appropriate, changed WPS to Dominion Energy Reflects the change in plant ownership.

Kewaunee. This change was not made where sample locations are still owned by WPS. Also changed KNPP to KPS.

Added sample type "Well Water (WW))" to This is the location at which the samples are being location 25 in Table 2.2.1-B. taken, as listed in Step 3.6 and shown in Table 2.2.1-A. This is an administrative issue of keeping the many locations this info is kept, up to date.

Table 2.2.1-B removed footnote "e" and relabled Location 25 had been used for domestic meat footnotes "f' and "g". samples only and was replaced by location 29 in 1990 (Rev. 3). Location 25 was again added in Rev. 6 for the current sample types noted.

On Figure 1 changed location K-19 to K-10. K-19 had been discontinued in -2000. K-10 is another site located in this same position.

Table 2.2.1-C, location K-8 name changed to St. Editorial Issue.

Isadore the Farmer Church.

Step 3.6 Well Water -removed wording that the Rev. 9 incorrectly cited a monthly composite. The composite samples are analyzed for tritium, and quarterly samples (no composites are generated) stated that all samples are analyzed for tritium. are analyzed as noted. This is a correction.

Deleted reference for the need for the vendor to be This is an administrative change. Requirements for compliant with Appendix B. This was in Section environmental monitoring sample analysis labs are 3.5. contained in Reg. Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Normal.

Operations) - Effluent Streams and the This change is chaning the QA requirements to a Environment. We have never required the vendor NRC approved document of similar controls of to be App. B compliant contractually. There are no App. B that are very specific to the process it will requirments listed in the ODCM or in Tech Spec be controlling, thus providing more specific 6.16 for complying with 10 CFR 50 Appendix B. controls.

Form GNP-03.01.01-2 Rev. T Date: FEB 23 2006 Page 40 of 58 INFORMATION USE

50.59 APPLICABILITY REVIEW (Is the activity excluded from 50.59 review?)

1. Document/Activity number: REMM Revision 10

2. Brief description of proposed activity (what is being changed and why):

Changing the reference from 10 CFR 50 Appendix B to Reg Guide 4.15, for the vendor to comply with.

Does the proposed activity involve or change any of the following documents or processes? Check YES or NO for EACH applicability review

3. item. Explain in comments if necessary. [Ref. NMC 50.59 Resource Manual, Section 4]

NOTE: If you are unsure if a document or process may be affected, contact the process owner.

Yes No Document or Applicable

%K Process Regulation Contact/Action Process change per NAD-05.14.

0a] Technical Specifications or Operating License 10CFR50.92 Contact Licensing.

Identify NRC letter in comments below. Process b 0i 0 Activity/change previously approved by NRC in 10CFR50.90 change.

license amendment or NRC SER Contact Licensing for assistance.

Activity/change covered by an existing approved Identify screening or evaluation in comments below.

I OCFR50.59 review, screening, or evaluation. Process change, 10CFR50.54(a) Contact QA.

d 0] Quality Assurance d_ _ Program (OOAPD) 0Refer to NAD-O1.07. -a e 00 Emergency Plan 10CFR50.54(q) Contact EP.

C Refer to FP-R-EP-02.

S0 ER Se y Plan Contact Security.

Security Pla0CFR0.54(p) Refer to FP-S-SPE-01.

g 0] [] IST Plan 10CFRS0.55a(f Contact IST process owner.

Refer to NAD-01.24.

h 0] [] ISI Plan 10CFR50.55a(g) Contact ISI process owner.

h 0 0aRefer to NADs 01.03.01.05. and 05.11.

i 0 0 ECCS Acceptance Criteria IOCFR50.46 Contact Licensing.

USAR or any document incorporated by reference - Process USAR change per NEP-05.02.

j 0 CD Check YES only if change is editorial (see IOCFR50.71 Contact USAR process owner for assistance.

Attachment A). ContactUSARprocessownerfo __assistance.

Commitment - Commitment changes associated Contact Licensing.

k0 N with a response to Generic Letters and Bulletins, or IOCFR50 Appendix B Refer to NAD-05.25.

if described in the USAR require a pre-screening.

Maintenance activity or new/revised maintenance IOCFR50.65 Evaluate under Maintenance Rule.

00 ] procedure - Check YES only if clearly maintenance Refer to NAD-08.20 and NAD-08.21.

and equipment will be restored to its as-designed condition within 90 days (see Attachment C).

New/revised administrative or managerial directive/procedure (e.g., NAD, GNP, Fleet M N 0 Procedure) or a change to any procedure or other 10CFR50 Appendix B Process procedure/document revision.

controlled document (e.g., plant drawing) which is clearly editorial/administrative. See Attachments A and B.

4. Conclusion. Check one of the following:

E] All documents'processes listed above are checked NO. IOCFR50.59 applies to the proposed activity. A 50.59 pre-screening shall be performed.

[] One or more of the documents/processes listed above are checked YES, AND controls all aspects of the proposed activity. 10CFR50.59 does NOTf apply. Process the change under the applicable program/process/procedure.

One or more of the documents/processes listed above are checked YES, however, some portion of the proposed activity is not controlled by any of the above processes. IOCFR50.59 applies to that portion. A 50.59 pre-screening shall be performed.

5. Comments:

All aspects of this revision are considered to be editorial except for the change in QA requirements for the vendor laboratory from App. B to Reg Guide 4.15.

6. Print name followed by signature. Attach completed form to document/activity/change package.

Prepared by: Richard W. Adams / * " Date: 3/28/06 (print/sign)

Reviewed by: Date: 0  ?

(print/sign)

Form GNP-04.04.01-1 Rev. F Date: NOV 8 2005 Page 15 of 16 INFORMATION USE

50.59 PRE-SCREENING (is a 50.59 screening required?)

1. Document/Activity number: REMM Revision 10

2. Brief description of proposed activity (what is being changed and why):

Changing reference from 10 CFR 50 App. B to Reg Guide 4.15, for the vendor to comply with.

3. Does the proposed activity involve or change any of the following documents or processes? Explain in Comments if necessary.

Check YES or NO for EACH pre-screening item. [Ref. NMC 50.59 Resource Manual, Section 5.1]

NOTE: If you are unsure if a document or process may be affected, contact the process owner.

NOTE: An asterisk (*) indicates that the document is incorporated by reference in the USAR or is implicitly considered part of the USAR.

NOTE: Check NO if activity/change is considered editorial, administrative, or maintenance as defined in Attachments A, B, and C. Explain in Comments if necessary.

Yes V No V Document/Process Directive?

Procedure a 0 9 Updated Safety Analysis Report (USAR) NEP-05.02 b

• Technical Specifications Bases or Technical Requirements Manual (TRM) NAD-05.14, NAD-03.25 c 5

• Commitments made in response to NRC Generic Letters and Bulletins, and those described in the USAR NAD-05.25 d 5 '

• Environmental Qualification (EQ) Plan NAD-01.08

• [] [

• Regulatory Guide 1.97 (RG 1.97) Accident Monitoring Instrumentation Plan NAD-05.22 f 5 0

• Fire Plan - NAD-01.02 g 5 0

• Appendix R Design Description NAD-01.02 h 5 0

• Fire Protection Program Analysis (FPPA) NAD-01.02 i 0l 0

• Offsite Dose Calculation Manual (ODCM) NAD-05.13 j [0 []

• Radiological Environmental Monitoring Manual (REMM) NAD-05.13 k [] 0

• Station Blackout Design Description 1 ] 0

• Control Room Habitability Study m 5 0 Plant Drawing Changes/Discrepancies NAD-05.01 n Calculations/Evatuations/Analyses/Computer Software - Check YES only if: 1) It affects a method of evaluation Various n] 19 described in the USAR, or 2) It independently (i.e., not part of a modification) affects the licensing or design basis.

o 0] Permanent Plant Physical Changes - All require a screening. NAD-04.03.

p Temporary Plant Physical Changes (TCRs) - Check No only if installed for maintenance AND in effect for less than NAD-04.03

___ _ _1 90 days at power conditions.

q l 0 QA Typing Determinations - Check YES only if reduction in classification, or affects design function as described in USAR. '

NAD-01.01 r 0 0 Setpoint or Acceptance Criteria - Check YES only if change affects plant monitoring, performance, or operation. Various s Plant Procedures/Revisions - Check YES only if the change directly or indirectly involves operating, controlling or NAD-03.01 s to configuring an SSC differently than described or credited in USAR.

t 5 0 Engineering Specifications - Check YES only if a design function or design requirement may be affected. NAD-05.03 u o 0 Operations Night Orders or Operator Work Arounds - Check YES only if SSCs are operated or configured differently than described in USAR.

NAD-12.08 v Temporary plant alterations (e.g., jumpers, scaffolding, shielding, barriers) - Check YES only if installed (or in effect) NAD-08.14,."

o to for maintenance for longer than 90 days at power conditions. GMP-127, HP-04.002, FPP-08-09 w 0l to Temporary plant alterations - Check YES only if not associated with maintenance.

x ED Corrective/Compensatory Actions - Check YES only if degraded/non-conforming plant condition accepted "as-is" or GNP-I 1.08.03 I compensatory action taken.

4. Conclusion. Check one of the following:

1] All of the documents or processes fisted above are checked NO. A 50.59 screening is NOT required. Process change in accordance with the applicable _

program/process/procedure.

0] One or more of the documents or processes listed above are checked YES. A 50.59 screening shall be performed.

5. Comments:

None

6. Print name followed by signature. Either the preparer or reviewer sha 5 59 sceing u liFed. Attach completed form to document/activity/change package.

Prepared by: Richard W. Adams IA!. Date: 3/16/06 (print/sign)

Reviewed by: _ 3.__

D Dae __ 7,,/_ _ __ _ _ _

(print/sign)

Form GNP-04.04.01-2 Rev. F Date: NOV 8 2005 Page 16 of 16 INFORMATION USE

10CFR50.59 SCREENING Page I of 5 Document/Acti vity 06-014-00 REMM Revision 10 SCRN#

Nimber:

PART I: Describe the Proposed Activity and Search the KNPP USAR (Refer to NMC 50.59 Resource Manual Section 5.3.1) 1.1. Describe the proposed activity, and scope of the activity covered by this screening. Appropriate descriptive materials may be attached.

Revision 10 to the REMM is removing the reference requiring the analytical vendor to have a QA program that is compliant with 10 CFR 50 Appendix B and replace this with Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Normal Operations) -- Effluent Streams and the Environment.

1.2. Search the Updated Safety Analysis Report (USAR) including those documents incorporated by reference. Describe relevant function(s), performance requirements, and methods of evaluation of the affected SSCs, and where this information is described in the USAR. In general, any USAR information potentially affected by the activity should be identified (consider both support functions and indirect affects). It is acceptable to attach and highlight applicable portions of the USAR.

USAR Sections 2.8, Environmental Radioactivity Program, 11.1.3, Design Evaluation, and 11.2.3 Radiation Monitoring System were reviewed. These sections each reference either the REMM or the ODCM. None discuss quality assurance methods that are acceptable for performance of an Environmental Monitoring Program (ODCM and REMM). These sections indicate that the ODCM and REMM define the necesssary controls for the program.

The REMM, under section 3.5, Quality Control Program4, states, 'To insure the validity of the data, the CV [Contracted Vendor] maintains a quality control (QC) program, which employs quality control checks, with documentation, of the analytical phase of its environmental monitoring studies. The program is defined in the CV's QC Program Manual, and procedures are presented in the CV QC Procedures Manual. The program shall be reviewed and meet the requirements of 10CFR50 Appendix B and 10CFR21."

1.3. Does the activity involve a change to the Technical Specifications?

(Changes to the Technical Specifications require a License Amendment request.)

El Yes 2 No Form GNP-04.04.02-1 Rev. D Date: JUN 23 2005 Page 14 of 20 INFORMATION USE

10CFR50.59 SCREENING Page 2 of 5 SCRN# 06-014-00 PART II: Determine if the Activity Involves a Design Function (Refer to NMC 50.59 Resource Manual Section 5.3.2)

Compare the proposed activity to the relevant portions of the USAR and answer the following questions:

YES NO QUESTION

1. E= 0D Does the proposed activity involve Safety Analyses or an SSC(s) credited in the Safety Analyses?

2. [J 0 Does the proposed activity involve SSCs that support SSC(s) credited in the Safety Analyses?

. El 3.[] z

[] feedwater, activity involve SSCs whose failure could initiate a transient (e.g., reactor trip, loss of etc) or accident?

Does the proposed

4. El 0 Does the proposed activity involve SSCs whose failure could impact SSC(s) credited in the Safety Analyses?

Does the proposed activity involve USAR-described SSCs or procedural controls that perform functions

5. 0 5 that are required by, or otherwise necessary to comply with, regulations, license conditions, orders, or Technical Specifications?

6. El 0 Does the activity involve a method of evaluation described in the USAR?

7., El 0 Is the activity a test or experiment? (i.e., a non-passive activity which gathers data)

. El a design affectthis basis limit for a fission product barrier

8. [(DBLFPB)? questionorispotentially If thisexceed Does the activity answered YES, activity requires a 10CFR50.59 Evaluation.

If the answer to all of these questions is NO, answer PART III as Not Applicable, and proceed to PART IV. A 10CFR50.59 evaluation is not required.

If any of the above questions are checked YES, identify the specific design function, method of evaluation, or DBLFPB involved:

See Attachment 1 for the basis of the above noted answers.

Form GNP-04.04.02-1 Rev. D Date: JUN 23 2005 Page 15 of 20 INFORMATION USE

10CFR50.59 SCREENING Page 3 of 5 SCRN# 06-014-00 PART III: Determine Whether the Activity Involves Adverse Effects (Refer to NMC 50.59 Resource Manual Section 5.3.3)

If all the questions in Part II were answered NO, then Part III is:

El Not Applicable Answer the following questions to determine if the activity has an adverse effect on a design function. Any YES answer means that a 10CFR50.59 Evaluation is required, except where noted in Question 1I1.3.

111.1. Changes to the Facility or Procedures YES NO QUESTION

a. El 0 Does the activity adversely affect the design function(s) identified in Part H?

b. El Z Does the activity introduce an accident of a different type than previously described in the USAR? (see RM Section 6.2.5)

c. El 0 Does the activity introduce new type of malfunction directly or indirectly affecting an SSC having a design function identified in Part II? (See definition in GNP-04.04.02, Section 3.0)

d. 0 0 Does the activity adversely affect the method of performing or controlling the design function(s) identified in Part II?

If any answer is YES, a 10CFR50.59 Evaluation is required. For each answer given, describe the basis for the conclusion (attach additional discussion, as necessary):

I See Attachment 2 for the basis of the above noted answers.

111.2. Changes to a Method of Evaluation If the activity does not involve a method of evaluation, these questions are:

[0 Not Applicable YES NO QUESTION El El Does the activity use a revised or different method of evaluation for performing safety analyses than that described in the USAR?

El El Does the activity use a revised or different method of evaluation for evaluating SSCs credited in safety analyses than that described in the USAR?

If either answer is YES, a 10CFR50.59 Evaluation is required. For each answer given, describe the basis for the conclusion (attach additional discussion, as necessary):

Form GNP-04.04.02-1 Rev. D Date: JUN 23 2005 Page 16 of 20 INFORMATION USE

10CFR50.59 SCREENING Page 4 of 5 SCRN# 06-014-00 111.3. Tests or Experiments If the activity is not a test or experiment, the questions in m.3.a and III.3.b are:

0 Not Applicable

a. Answer these two questions first:

YES NO QUESTION 51 E5 Is the proposed test or experiment bounded by other tests or experiments that are described in the USAR?

5 E] Are the SSCs affected by the proposed test or experiment isolated from the facility?

If the answer to both questions is NO, continue to III.3.b. For each answer given, describe the basis for the conclusion (attach additional discussion, as necessary):

b. Answer these additional questions only for tests or experiments which do not meet the criteria given above. If the answer to either question in III.3.a is YES, then these three questions are:

E5 Not Applicable YES NO QUESTION Does the activity use or control an SSC in a manner that is outside the reference bounds of the design bases as described in the USAR?

0 0 Does the activity use or control an SSC in a manner that is inconsistent with the analyses or descriptions in the USAR?

0 .0 Does the activity place the facility in a condition not previously evaluated or that could affect the capability of an SSC to perform its intended functions? .

If any answer in mI.3.b is YES, a 10CFR50.59 Evaluation is required. For each answer given, describe the basis for the conclusion (attach additional discussion, as necessary):

Form GNP-04.04.02-1 Rev. D Date: JUN 23 2005 Page 17 of 20 INFORMATION USE

10CFR50.59 SCREENING Page 5 of 5 SCRN# 06-014-00 PART IV: Conclusion (Refer to NMC 50.59 Resource Manual Section 5.3.4)

Check all that apply:

1. A 10CFR50.59 Evaluation is

[] required, OR 0 NOT required

2. A change to the USAR and/or any document incorporated by reference is E] required (Process change in accordance with applicable plant program/process/procedure.),

OR ED NOT required Additional comments:

None.

Print name followed by signature. The preparer and reviewer shall be 50.59 screening or evaluation qualified. The completed screening Coordinator.is part of the document/activity/change package. Provide a copy of 50.59 screening to the 50.59 Process Owner/Program Prepared By: Richard W. Adams / Date: 3/16/06 (print/sign)

Reviewed n/Date:By: ___________

(print/sign)

Form GNP-04.04.02-1 Rev. D Date: JUN 23 2005 . Page 18 of 20 INFORMATION USE

10 CFR 50.59 Screening #06-014-00 Attachment 1 Pagel of 2 The following is provided as the basis for the conclusions relative to Part II, questions 1 through 8:

1. NO - The proposed change in the quality assurance requirements that must be met by the Kewaunee Power Station (KPS) Radiological Environmental Monitoring Manual (REMM) specified contracted vendor does not involve either the Safety Analysis or an SSC credited in the Safety Analysis.

2. NO - There is no SSC that supports an SSC credited in the Safety Analysis that is involved with the proposed change in the quality assurance requirements that must be met by the contracted vendor specified in the KPS REMM.

3. NO - The proposed change in the quality assurance requirements that must be met by the KPS REMM specified contracted vendor does not involve any SSCs whose failure could initiate a transient or accident.

4. NO - There are no SSCs whose failure could impact SSCs credited in the Safety Analysis that are involved with this proposed change in the quality assurance requirements that must be met by the contracted vendor specified in the KPS REMM.

5. YES - This proposed change does involve changing a program specified quality assurance requirement contained in the KPS REMM, from 10 CFR 50 Appendix B to Regulatory Guide 4.15.

6. NO - The proposed change in the quality assurance requirements that must be met by the KPS REMM specified contracted vendor does not involve a method of evaluation described in the USAR.

7. NO - This proposed change in the quality assurance requirements that must be met by the KPS REMM specified contracted vendor is neither a test nor an experiment.

8. NO - No design basis limit for a fission product barrier will be exceeded or potentially affected by this proposed change in the quality assurance requirements that must be met by the KPS REMM specified contracted vendor.

This activity is changing the existing program performance requirements as specified in the REMM (which is part of the KPS USAR as a document incorporated by reference).

The contracted vendor, as identified in the REMM, performs sample collection, analysis and reporting for the Environmental Monitoring Program.

10 CFR 50.59 Screening #06-014-00 Attachment 2 Page Iof 1 The following is provided as the basis for the conclusions relative to Part II. 1, questions a through d:

a. NO - A change to the quality assurance standard the vendor is to implement does not change the expected performance or methods of performing sample collection, analysis, or reporting of environmental sampling. Therefore, this change is not adverse to any design functions identified in Part II.

b. NO - The Environmental Monitoring program does not interface with or provide any inputs to any active plant components, and also has no method of initiating an accident. Therefore, a change in the quality assurance program required to be implemented by the vendor will not introduce an accident of a different type.

c. NO - The Environmental Monitoring program does not interface with or provide any inputs to any active plant components, and has no method of creating a malfunction. Therefore, a change in the quality assurance program required to be implemented by the vendor will not introduce a malfunction.

d. NO - Regulatory guide 4.15 - 1979, Quality Assurance for Radiological Monitoring Programs (Normal Operations) -- Effluent Streams and the Environment, provides equivalent controls to 10 CFR 50 Appendix B, to the extent necessary for the activities completed in the REMM and ODCM. The Reg.

Guide specifically states in its introduction, "This guidance does not identify separately the activities that are within the scope of Appendix B to 10 CFR

50. However, this guidance is intended to be consistent with the requirements of Appendices A and B to 10 CFR 50 in that quality assurance requirements should be consistent with the importance of the activity."

The regulatory guide provides sections that are consistent with the following criteria from 10 CFR 50, App. B:

I, V, X, XI, XVII, and XVIII, with specific directions and considerations for the specific purpose of providing quality results for a Radiological Monitoring Program.

Based on the above, changing the required quality assurance standard that must be met by the vendor does not adversely affect the method of controlling the environmental monitoring program.

Kewaunee Power Station Dominion Operational Quality Assurance Date: 08/04/05 Program Description Rev. 22.b Page 17 of 40 2.0 QUALITY ASSURANCE PROGRAM 2.1 General The Operational Quality Assurance Program complies with the requirements of 10 CFR 50, Appendix B, the provisions of ANSI N18.7-1976 and the Regulatory Guides which endorse the daughter standards required by ANSI N18.7-1976 with the exceptions, interpretations, and qualifications noted in Appendix B of this description. The requirements of the OQAPD apply to those activities which affect the quality of structures, systems, or components that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public. All structures, systems, and components are classified as QA Type 1, 2, 3 or N according to their function and importance in relation to the safe operation of the reactor, with emphasis on the degree of integrity required to protect the public. The OQAPD requirements are mandatory for all QA Type 1 items.

QA Type 2 and 3 items, as determined by management, may require special control and an "X" modifier may be added to the QA2 or QA3 type designation. All components and/or systems which are identified as Nuclear Safety Design Class I in the Updated Safety Analysis Report (USAR) shall be categorized as QA Type 1.

All nuclear fuel and core components shall be categorized as QA Type 1. The definitions and a list of the Nuclear Safety Design Classes for major structures, systems and components are found in the Kewaunee USAR Appendix B.2 and Table B.2-1.

During construction, QA types were established for plant equipment by a QA typing committee. The QA types for equipment subsequently added to the plant are established by the Responsible Engineer who installs the equipment under the Plant Physical Change program. The Plant Physical Change program exists under the requirements of the OQAPD. Therefore, the QA types of equipment added since construction are controlled under the OQAPD and its definitions. A change to an established QA type must be approved by the QA Typing Committee.

St ~~

~e~\s W06 --0oAoo

Kewaunee Power Station Dominion Operational Quality Assurance Date: 08/04/05 Program Description Rev. 221b Page 18 of 40 Designated activities that are not safety-related, but support safe facility operations incorporate portions of this program into their governing documents. In addition to this OQAPD, the following documents further describe application of portions of the Quality Assurance program, where appropriate: the Safety Analysis Reports (SAR),

nuclear design control program, physical security plan, emergency plan, radiological protection plan including radioactive material transport and radioactive waste processing, fire protection plan, station blackout program, nuclear chemistry laboratory quality assurance program, Environmental Qualification (EQ) plan, Fitness-For-Duty (FFD) program, Off-site Dose Calculation Manual (ODCM) and Pressurizer Power Operated Relief Valve (PORV) and blo lve reliability commitments.

2.2 Requirements It is mandatory for applicable employees to comply with the OQAPD. It is the responsibility of the management charged with the implementation of the program to inform personnel working for them that the quality policies, OQAPD manual, and procedures have mandatory requirements which must be implemented and enforced. The Training Manager is responsible for conducting training sessions as necessary to keep individuals informed of policies and changes to the OQAPD. The lesson plans for these training sessions will be prepared under the cognizance of the Nuclear Oversight staff.

The OQAPD shall be applied to all activities affecting safety-related functions and include: physical changes, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, operating, maintaining, repairing, refueling, modifying, engineering, and training. The control over these activities shall be applied to an extent consistent with their importance to safety and shall take into account the need for special controls, processes, tests, equipment, tools, and skills to attain the required quality, and the need for verification of quality by inspection, evaluation, or test.

USA~

2.8 ENVIRONMENTAL RADIOACTIVITY PROGRAM A pre-operational environmental radiological monitoring program was started at the Kewaunee site in September, 1969. Over four years of background data was available before plant startup. From this information it was possible to detect and evaluate changes resulting from plant operation.

1MO S,jcl :effldent-'sý rveillancb- pWogr-"i" as removed . em m ctions 7 ahd 8 the "NW&6i lea" Power Plant Technical' Speifieations, and is lefiledinet heOff-ite Dose

.if.

• anuai (ODCM)J.-

o.9icad e*.riniri Monitbrin*.Manua A4Environental (REMM)defines thie i*dologial effects the pMm of plant operation for samping on te environment j*i ent lto and beyond the site boundary.

Rev. 16 2.8-1 12/01/2000

Auxiliary Shielding The auxiliary shield consists of concrete walls around certain components and piping which process reactor coolant. .In some cases, the concrete block walls are removable to allow personnel access to equipment during maintenance periods. Each equipment compartment is individually shielded so those compartments may be entered without having to shut down the adjacent system for any reason.

The primary shield material provided throughout the Auxiliary Building is concrete. The principal auxiliary shielding provided and the original design parameters are tabulated in Table 11.2-6.

11.2.3 RADIATION MONITORING SYSTEM The Radiation Monitoring System provides continuous radiological surveillance of plant system and working areas. The system performs the following basic functions:

+ Warns operating personnel of radiological health hazards, such as abnormal radiation fields.

+ Provides warning of plant malfunctions, which could lead to* plant damage and/or radiological hazards.

+ Prevents or minimizes inadvertent releases of radioactivity to the environment via automatic action capability.

+ Provides monitoring of controlled radiological plant releases.

Radiation detection instruments are located in areas of the plant, which house equipment containing or processing radioactive fluid. These instruments continually detect, compute, and record operating radiation levels. If the radiation level should rise above the set point for any channel, an alarm is initiated in the Control Room or Radiation Protection Office. Some channels also alarm locally. In stipulated cases, the alarm signal also provides the necessary signal for automatic process controls (e.g., valve closure, damper isolation, etc.). The Radiation Monitoring System operates in conjunction with regular and special radiation surveys and with chemical and radiochemical analyses performed by the plant staff. Adequate information and warning is thereby provided for the continued safe operation of the plant and assurance that personnel exposure does not exceed the limits of 10 CER 20.

Two high range detectors are located in the containment. These two-containment area monitoring channels are the only components in the Radiation Monitoring System designed to operate following a major loss-of-coolant accident.

The components of the Radiation Monitoring System are designed according to the following environmental conditions:

• Temperature - an ambient temperature range as specified in Table 11.2-8.

+ Humidity - 0 to 95% relative humidity.

USAR - Rev. 19 11.2-7 06/0 1/2005

+ Pressure - Components in the Auxiliary Building and Control Room are designed for normal atmospheric pressure. Area Monitoring System components inside the Containment are designed to withstand containment test pressure.

+ Radiation - Process and area radiation monitors are of a non-saturating design so that they "peg" full scale if exposed to radiation levels at over full-scale intensities. Critical process monitors are located in areas where the normal and post-accident background radiation levels will not affect their usefulness. -

The Radiation Monitoring System consists of two types of components, the Process monitors and the Area monitors.

+ The Process Radiation Monitoring System refers to those radiation monitors capable of analyzing fluid (air or water) flow for indication of increasing radiation levels.

+ The Area Radiation Monitoring System monitors the direct radiation in various areas of the plant or indication of increasing radiation levels.

. eTb*eEnvironmental Radiation Monitoring Program,mas dekibed-in. the' Radiological.

Environmental Monitoring Manual (REMM), monitors radiation in various areas surrounding the 1-)

JpT-r..(This istrd ed.

U in ectio8ýn 2g);-":

Main Process Radiation Monitoring System The Main Process Radiation Monitoring System is designed to provide information to plant personnel on:

+ Radioactivity levels present in fluid (air and water) systems.

+ Leakage across boundaries of closed systems.

+ Radioactivity concentrations in liquid and gaseous flow paths that lead to release from the plant.

In conjunction with the design functions spelled out above, the system is capable of initiating automatic actions designed to prevent or minimize any inadvertent/uncontrolled release of radioactivity to the environment.

The Main Process Monitoring System consists of 13 channels of monitoring equipment, 9 of, which are equipped with some level of automatic action upon receipt of a high radiation alarm. Seven of the 13 channels perform engineered safety related functions. The Main Process Monitoring System consists of the following:

Process Monitors

+ R-11 Containment System vent (Air Particulate)

• R-12 Containment System vent (Radioactivity Gas)

+ R-13 Auxiliary Building vent A USAR - Rev. 19 11.2-8 06/01/2005

Valves All valves exposed to gases are carbon steel. Those exposed to liquids are stainless steel. All valves have stem leakage control. Globe valves are installed with flow over the seats when such an arrangement reduces the possibility of leakage.

Isolation valves are provided to isolate each piece of equipment for maintenance, to direct the flow of waste through the system, and to isolate storage tanks for radioactive decay.

Relief valves are provided for tanks containing radioactive wastes to prevent overpressurization by improper operation or component malfunction. Tanks containing wastes, which are normally free of gaseous activity, are vented locally.

11.1.3 DESIGN EVALUATION The radiological impact of power uprate was evaluated for normal operation annual radwaste effluent releases (Reference 5).

Based on this evaluation it was determined that the power uprate to a core power level of 1772 MWt has no significant impact on the expected annual radwaste effluent releases/doses. All doses remain a small percentage of allowable 10CFR50 Appendix I dose limits. Following power uprate the liquid and gaseous radwaste effluent treatment system will remain capable of maintaining normal operation off-site doses within the requirements of IOCFR50 Appendix I (Reference 5).

Liquid Wastes Liquid Wastes are generated primarily by plant maintenance and service operations. Tables 11.1-4 and 11.1-5 contain a summary of the actual historical average annual values of the quantities and activity concentrations of influents to the system during the 1976 through 1981 time frame (which reflects plant operation at the average core power during that period). If the historical data is used to project the future release, core power uprate to 1772 MWt is expected to have minimal impact on the discharge quantities listed in Table 11.1-4.

However, the released radioactivity in Table 11.1-5 could potentially increase by the percentage increase in power level between the uprated conditions and the average core power level during that time period (Reference 4).

Gaseous Wastes Gaseous wastes consist primarily of hydrogen stripped from coolant discharged to the CVCS holdup tanks during boron dilution, nitrogen and hydrogen gases purged from the CVCS volume control when degassing the reactor coolant, and nitrogen from the Closed Gas Blanketing

'System. The original design basis for the gas decay tank capacity allows for storage of collected gaseous waste for at least 45 days prior to release. t e scifica!ioa are~contaier idn the, KNPOff-Site Dose Calcilatiori Manual (ODCM). Table 11.1-6 contains a summary of the USAR - Rev. 19 11.1-12 06/01/2005 0~~<

estimated annual average gaseous release from the plant. Based on the 1986 and 1987 KNPP Semi-Annual Effluent Release Reports, actual typical annual gaseous discharge activity has been averaging less than 25% of the values shown in Table 11.1-6. The values in Table 11.1-6 are representative of a core power level of 1650 MWt. With a core power uprate to 1772 MWt, the Table 11.1-6 values could potentially increase by a maximum of the percentage increase in power level (Reference 4).

Solid Wastes Solid wastes consist of filters, spent resins and miscellaneous materials such as paper and plastic. All solid wastes are packaged as noted under "Solids Processing" for removal to a burial facility. Annual solids, exclusive of solidified resins shipped for burial, averaged 1025 ft3 during the period between 1975 and 1981. Annual average spent resin quantities shipped are 740 ft. More recent solid waste shipments are consistent with or below these volumes.

11.1.4 MINIMUM OPERATING CONDITIONS Verification is made to ensure that dilution flow sufficient to meet the requirements of 10 CFR 20 is available whenever radioactive liquid wastes are released to the Plant Discharge System.

All liquid waste releases are continuously monitored for gross activity during discharges to ensure that the activity limits specified in 10 CFR 20 for unrestricted areas are not exceeded. The Off-Site Dose Calculation Manual provides guidance when continuous monitoring is unavailable.

All batch radioactive liquid wastes are sampled prior to release to the Plant Discharge System.

At least one Auxiliary Building normal mode ventilation fan is in operation whenever radioactive gaseous wastes are released to the Auxiliary Building vent.

The maximum allowable dose rates at the site boundary due to discharges are specified in the Off-Site Dose Calculation Manual.

A record is maintained of the radioactive material contained in all releases.

USAR - Rev. 19 11.1-13 06/01/2005

~1.

Kewaunee Power Station RadiologicalEnvironmental MonitoringManual (REMM)

Revision 11 12-14-2006.

Reviewed by: Tom Webb Date: // ,0!e'v,---

Plant Operations Review Committee Approved by: James M. Hale (ŽeýWA Wi&iM, Date:

Manager, Radiological Protection and Chlnistry Approved by: Thomas Breene Date: /,-1,- /:6 Manager, Regulatory Affairs RECORDS DEC 14 2006

Table of Contents 1.0 Introduction ............................................................................................................ 1-1 1.1 Purpose ................................................................................................................ 1-1 1.2 Scop e ................................................................................................................... 1-1 1.3 Implementation .................................................................................................... 1-1 2.0 REMVIP Requirem ents .................................................................................................... 2-1 2.1 Technical Specification Requirements ................................................................ 2-1 2.2 REM M Requirements ......................................................................................... 2-1 REM M 2.2.1/2.3.1 Monitoring Program ............................................................. 2-3 REMM 2.2.2/2.3.2 Land Use Census .................................................................. 2-6 REM M 2.2.3/2.3.3 Interlaboratory Comparison Program .................................. 2-8 REM M 2.4.1 Reporting Requirements ............................................................... 2-9 3.0 REIMVP Im plem entation ................................................................................................. 3-1 3.1 Sam pling Requirements ...................................................................................... 3-1 3.2 Analysis Methodology ......................................................................................... 3-1 3.3 Detection capability (LLD) Requirements .......................................................... 3-1 3.4 Contracted Vendor (CV) Reporting Requirements ........................ 3-2 3.5 Quality Control Program ...................................... 3-2 3.6 Sample Descriptions ............................................................................................ 3-3 Tables & Figures Table 2.2.1-A Radiological Environmental Monitoring Program Table 2.2.1-B Type and Frequency of Collection Table 2.2.1-C Sampling Locations, Kewaunee Power Station Table 2.2.1-D Reporting Levels for Radioactivity Concentrations in Environmental Samples Table 2.3.1-A Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD)

Figure 1 Environmental Sampling Location Rev. 11 i 12/14/2006

- f 1.0 Introduction 1.1 Purpose The purpose of this document is to define the Radiological Environmental Monitoring Program (REMP) for the Kewaunee Power Station (KPS). The REMP is required by KPS Technical Specification (TS) 6.16.b.2, "Radiological Environmental Monitoring Program."

This document is known as the Radiological Environmental Monitoring Manual (REMM) and is intended to serve as a tool for program administration and as a guidance document for contractors which implement the monitoring program.

1.2 Scope This program defines the sampling and analysis schedule which was developed to provide representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the high potential radiation exposures of MEMBERS OF THE PUBLIC resulting from plant operation. This monitoring program implements Section IV.B.2 of Appendix I to 10CFR Part 50 and thereby verifies that the measurable concentrations of radioactivity and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for the development of this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. This program has been developed in accordance with NUREG 0472.

The program will provide field and analytical data on the air, aquatic, and terrestrial radioecology of the area near the Kewaunee Power Station so as to:

I. Determine the effects of the operation of the Kewaunee Power Station on the environment;

2. Serve as a gauge of the operating effectiveness of in-plant control of waste discharges; and

3. Provide data on the radiation dose to the public by direct or indirect pathways of exposure.

1.3 Implementation This document is considered, by reference, to be part of the Offsite Dose Calculation Manual. This is as required by KPS TS 6.16.b.2. The REMM is controlled as a separate document for ease of revision, use in the field and use by contractors. This format was approved by the NRC as part of TS Amendment No. 64, which provided Radiological Effluent Technical Specifications (RETS) for KPS.

The REMP is setup to be implemented by a vendor and controlled by KPS in accordance with Nuclear Administrative Directive NAD-1.20, "Radiological Environmental Monitoring Program." Monthly reviews of the vendor's progress report are checked and approved by KPS in accordance with Surveillance Procedure SP-63-276. Annual reviews and submittals of the vendor's report and raw data are checked and approved by KPS in accordance with Surveillance Procedure SP-63-280. All sample collection, preparation, and analysis are performed by the vendor except where noted. Surveillance Procedure SP-63-164 outlines the environmental sample collection Rev. 11 1-1 12/14/2006

performed by KPS. Current vendor Quality Control Program Manuals and implementing procedures shall be kept on file at KPS.

Periodic reviews of monitoring data and an annual land use census will be used to develop modifications to the existing monitoring program. Upon approval, these modifications will be incorporated into this document so that it will accurately reflect the current radiological environmental monitoring program in effect for KPS.

The remainder of this document is divided into two sections. The first section, 2.0 REMP Requirements, describes the different TS and REMM requirements associated with the REMP. The second section, 3.0 REMP Implementation. describes the specific requirements used to implement the REMP.

Rev. 11 1-2 12/14/2006

2.0 REMP Requirements KPS TS Amendment No. 104 implemented the guidance provided in Generic Letter 89-01, "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications (RETS)." These changes included:

1. Incorporation of programmaticcontrols in the Administrative Controls section of the TS to satisfy existing regulatory requirements for RETS, and

2. Relocation of the procedural details on radioactive effluents monitoring, radiological environmental monitoring, reporting details, and other related specifications from the TS to the ODCM.

Relocating the procedural details to the ODCM allows for revising these requirements using the 10CFR50.59 process instead of requiring prior NRC approval using the TS Amendment process.

The RETS requirements were incorporated verbatim into the ODCM, Revision 6. Several of these requirements pertain only to the environmental monitoring program and therefore have been relocated into this document (REMM, Revision 3 and 4) and are identified as REMM requirements.

2.1 TechnicalSpecification Requirements Technical Specification 6.16.b.2 provides the programmatic control, which requires a program to monitor the radiation and radionuclides in the environs of the plant. This is the reason for the existence of the REMP. TS 6.16.b.2 also provides the programmatic control which requires:

a. The program to perform the monitoring, sampling, analysis, and reporting in accordance with the methodology and parameters in the ODCM,

b. A land use census to be performed, and

c. Participation in an Interlaboratory Comparison Program.

The details of each requirement are described in the REMM requirements stated below.

Technical Specification 6.9.b.1 requires an "Annual Radiological Environmental Monitoring Report" be submitted to the NRC each year. The specific contents of this report are detailed in REMM 2.4.1. Additional specific reporting requirements are listed in the other REMM requirements.

2.2 REMM Requirements The following REMM requirements include the procedural details that were originally located in the KPS RETS section and then relocated into Revision 6 of the ODCM, as discussed above. These requirements are specific to the radiological environmental monitoring program and have been relocated into this document for ease of use and completeness.

The REMM requirements for the Monitoring Program, Land Use Census, and the Interlaboratory Comparison Program include a detailed specification (numbered 2.2.1, 2.2.2, and 2.2.3 respectively)

Rev. 11 2-1 12/14/2006

and an associated surveillance requirement (numbered 2.3.1, 2.3.2, and 2.3.3 respectively), along with the basis for the requirement. Reporting requirements are listed in specification REMM 2.4.1.

General requirements also apply to all ODCM and REMM requirements (specifications 3.01, 3.02, 3.03, 4.01, 4.02, and 4.03). The requirements are located in the ODCM and are repeated here for convenience.

GENERAL SPECIFICATIONS 3.0.1 Compliance with the specifications contained in the succeeding text is required during the conditions specified therein; except that upon failure to meet the specifications, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a Specification shall exist when its requirements and associated ACTION requirements are not met within the specified time intervals. If the Specification is restored prior to expiration of the specified time intervals, completion of the Action requirements is not required.

3.0.3 When a Specification is not met, except as provided in the associated ACTION requirements, reporting pursuant to TS 6.9.b and REMM 2.4.1 will be initiated.

SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the conditions specified for individual Specifications unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Specification.

Exceptions to these requirements are stated in the individual Specification.

Surveillance Requirements do not have to be performed on inoperable equipment.

Rev. It 2-2 12/14/2006

REMM 2.2.1/2.3.1 Monitoringprogram SPECIFICATION 2.2.1 The radiological environmental monitoring program shall be conducted as specified in Table 2.2.1-A.

APPLICABILITY At all times.

ACTION

a. With the radiological environmental monitoring program not being conducted as specified in Table 2.2.1-A, in lieu of a Licensee Event Report, prepare and submit to the Commission, in the Annual Radiological Environmental Monitoring Report required by TS 6.9.b.1 and REMM 2.4.1, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 2.2.1-D when averaged over any calendar quarter in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to TS 6.9.b.3, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose' to A MEMBER OF THE PUBLIC is less than the calendar year limits of specifications ODCM 3.3.2, 3.4.2, and 3,4.3. When more than one of the radionuclides in Table 2.2.1-D are detected in the sampling medium, this report shall be submitted if:

concentration(1) concentration(2) reportinglevel (1) reportinglevel (2)

When radionuclides other than those in Table 2.2. 1-D are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose' to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of specifications ODCM 3.3.2, 3.4.2, and 3.4.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event the condition shall be reported and described in the Annual Radiological Environmental Monitoring Report.

'The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report.

Rev. 11 2-3 12/14/2006

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 2.2.1 -A, a sample from an alternative location will be substituted, noting the reason for the unavailability in the Annual Radiological Environmental Monitoring Report. When changes in sampling locations are permanent, the sampling schedule in the RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) will be updated to reflect the new routine and alternative sampling locations and this revision will be described in the Annual Radiological Environmental Monitoring Report.

Rev. 11 2-4 12/14/2006

'- I SURVEILLANCE REQUIREMENT 2.3.1 The radiological environmental monitoring samples shall be collected pursuant to Table 2.2.1-A from the specific locations given in the table and figure(s) in the REMM, and shall be analyzed pursuant to the requirements of Table 2.2.1-A and the detection capabilities required by Table 2.3. I-A.

BASIS The radiological environmental monitoring program required by this specification provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. Program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 2.3. 1-A are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques,"

Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Discussion KPS TS 6.16.b.2(A) requires that the monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment be done in accordance with the methodology and parameters in the ODCM.

Rev. 11 2-5 12/14/2006

REMM 2.2.2/2.3.2 Land Use Census SPECIFICATION 2.2.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 10 meteorological sectors of the nearest milk 2 2 animal, the nearest residence and the nearest garden 2 of greater than 50 m (500 ft )

producing broad leaf vegetation.

APPLICABILITY At all times.

ACTION

a. With a land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in ODCM Surveillance Requirement 4.4.3, in lieu of a Licensee Event Report, identify the new location(s) in the next Annual Radiological Environmental Monitoring Report pursuant to TS 6.9.b. 1 and REMM 2.4.1.

b. With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with specification REMM 2.2.1, add the new location(s) to the radiological environmental monitoring program within 30 days. The sampling location(s), excluding the control station location, having a lower calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program. In lieu of a Licensee Event Report, identify the new location(s) in the next Annual Radiological Environmental Monitoring Report pursuant to TS 6.9.b. 1 and REMM 2.4.1 and also include in the report a revised figure(s) and table for the REMM reflecting the new location(s).

SURVEILLANCE REQUIREMENT 2.3.2 The land use census shall be conducted during the growing season once per 12 months using reasonable survey methods, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Monitoring Report pursuant to TS 6.9.b. 1 and REMM 2.4. 1.

2Samplingpof leaf vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted DIQs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 2.2.1-A item 4c shall be followed, including analysis of control samples.

Rev. 11 2-6 12/14/2006

BASIS This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the door-to-door survey, from aerial survey or from consulting with local agricultural authorities. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made:

1. 20% of the garden was used for growing leafy vegetation (i.e., similar to lettuce and cabbage), and

2. A vegetation yield of 2 kg/m 2.

Discussion KPS TS 6.16.b.2(b) requires that a land use census be performed to ensure that changes in the use of areas at and beyond site boundary are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census.

Rev. 11 2-7 12/14/2006

REMM 2.2.3/2.3.3 InterlaboratoryComparison Program SPECIFICATION 2.2.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.

APPLICABILITY At all times.

ACTION

a. With analyses not being performed as required above, report corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Monitoring Report pursuant to TS 6.9.b. 1 and REMM 2.4.1.

SURVEILLANCE REQUIREMENT 2.3.3 The Interlaboratory Comparison Program shall be described in the REMM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Monitoring Report pursuant to TS 6.9.b. 1 and REMM 2.4.1.

BASIS The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR Part 50.

Discussion KPS TS 6.16.b.2(c) requires participation in an approved Interlaboratory Comparison Program to ensure that an independent check is performed of the precision and accuracy of radioactive materials measurements. This will demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR Part 50.

Rev. 11 2-8 12/14/2006

t REMM 2.4.1 ReportingRequirements 2.4.1 The Annual Radiological Environmental Monitoring Report shall include:

a. Summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance -activities for the report period, including a comparison with pre-operational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by specification REMM 2.2.2.

b. The results of analyses of radiological environmental samples .and of environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the Radiological Environmental Monitoring Manual (REMM), as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report when applicable.

c. A summary description of the radiological environmental monitoring program; legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by specification REMM 2.2.3; discussion of all deviations from the sampling schedule of Table 2.2. 1-A; and discussion of all analyses in which the LLD required by Table 2.3.1-A was not achievable.

Discussion KPS TS 6.9.b.1 provides the programmatic control, which requires that an Annual Radiological Environmental Monitoring Report be submitted to the NRC. It also states that this report shall include summaries, interpretations, and analysis of trends of the results of the REMP for the reporting period.

The procedural details of this report are included in this specification. Specifications REMM 2.2.1/2.3.1, 2.2.2/2.3.2, and 2.2.3/2.3.3 also include specific reporting requirements. These specifications reference this REMM specification, along with TS 6.9.b. 1, as the method for reporting deviations from the current program during the reporting period, and require that this information be included in the Annual Radiological Environmental Monitoring Report.

Rev. 11 2-9 12/14/2006

3.0 REMP Implementation The Radiological Environmental Monitoring Program for KPS is under the direction of a Contracted Vendor (CV). This section describes this program, as required by REMM 2.2.1 and the process the CV uses to perform it.

3.1 Sampling Requirements Table 2.2.1-A identifies the various samples required by the REMP. Identified in the "available sample locations" column in Table 2.2.1-A are the sample locations selected, in conjunction with the vendor, to meet or exceed the REMP requirements. Table 2.2.1-B includes the same requirements as in Table 2.2.1-A but presents the information in a different format by identifying the type of samples required at each location and the collection frequency. Table 2.2.1-C identifies the location and description of each sample location. Figure 1 shows the physical location of each sample point on an area map.

3.2 Analysis Methodology Analytical procedures and counting methods employed by the CV will follow those recommended by the U.S. Public Health Service publication, Radioassav Procedures for Environmental Samples, January 1967; and the U.S. Atomic Energy Commission Health and Safety Laboratory, HASL Procedures Manual (HASL-300), 1972. The manual is also available on-line at www.eml.doe.gov/publications/procman.

Updated copies will be maintained in KPS's vault.

3.3 Detection Capability (LLD) Requirements The required detection capabilities for environmental sample and analysis are tabulated in terms of lower limits of detection (LLDs) in Table 2.3.1-A. The LLDs 'required by Table 2.3.1-A are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Rev. 11 3-1 12/14/2006

3.4 ContractedVendor Reporting Requirements Monthly ProgressReports Monthly progress reports will include a tabulation of completed analytical data on samples obtained during the previous 30 day period together with graphic representations where trends are evident, and the status of field collections. One copy of the reports will be submitted within 30 days of the reporting month.

Annual Reports Annual reports will be submitted in two parts. Part I, to be submitted to the NRC, will be prepared in accordance with NRC Regulatory Guide 4.8. It will contain an introductory statement, a summary of results, description of the program, discussion of the results, and summary table. Part II of the annual report will include tables of analytical data for all samples collected during the reporting period, together with graphic presentation where trends are evident and statistical evaluation of the results. Gamma scan data will be complemented by figures of representative spectra. Draft copies of each annual report will be due 60 days after completion of the annual period. After final review of the draft document, one photoready copy of the revised annual report will be sent to KPS for printing.

Non-Routine Reports If analyses of any samples collected show abnormally high levels of radioactivity, KPS will be notified by telephone immediately after data becomes available.

Action Limits The CV will report any radioactive concentrations found in the environmental samples which exceed the reporting levels shown in Table 2.2. 1-D, CV to KPS column. These levels are set below the NRC required reporting levels (KPS to NRC column) so actions can be initiated to prevent exceeding the NRC concentration limits.

3.5 Quality ControlProgram To insure the validity of the data, the CV maintains a quality control (QC) program, which employs quality control checks, with documentation, of the analytical phase of its environmental monitoring studies. The program is defined in the CV's QC Program Manual, and procedures are presented in the CV QC Procedures Manual. The program shall be reviewed and meet the requirements of Regulatory Guide 4.15 and 10CFR2 1. All data related to quality control will be available for review by Dominion Energy Kewaunee upon reasonable prior notification. Proprietary information will be identified so that it may be treated accordingly.

Updated copies of the Quality Control Program Manual and the Quality Assurance Program Manual will be maintained in KPS's vault.

Rev. 11 3-2 12/14/2006

-.4 3.6 Sample Descriptions A description of each of the samples required by this program follows:

Airborne Particulates Airborne particulates are-collected at six locations (K-If, K-2, K-7, K-8, K-16, K-31) on a continuous basis on a 47 mm diameter membrane filter of 0.8 micron porosity at a volumetric rate of approximately one cubic foot per minute (CFM). The filters are changed weekly, placed in glassine protective envelopes, and dispatched by U.S. Mail to the CV for Gamma Isotopic Analysis.

Filter samples are analyzed weekly for gross beta activity after sufficient time (usually 3 to 5 days) has elapsed to allow decay of Radon and Thoron daughters. If gross beta concentration in air particulate samples are greater than ten (10) times the yearly mean of the control samples, gamma isotopic analysis shall be performed on the individual samples. Quarterly composites from each location receive Gamma Isotopic Analysis using a Germanium detector. All identifiable gamma-emitters are quantified. Reporting units are pCi/m 3.

Airborne Iodine All air samplers are equipped with charcoal traps installed behind the particulate filters for collection of airborne 1-131. The traps are changed once every two weeks. Iodine- 131 is measured by Gamma Isotopic Analysis.

Periphyton(Slime) or Aquatic Vegetation Periphyton (slime) or aquatic plant samples are collected at or near locations used for surface water sampling. They are collected twice during the year (2nd and 3rd quarter), if available. The samples are analyzed for gross beta activity and, if available in sufficient quantity, for Sr-89, Sr-90, and by Gamma Isotopic Analysis. Reporting units are pCi/g wet weight.

Fish Fish are collected three times per year (second, third, and fourth quarters) near the discharge area (K-id). Flesh is separated from the bones and analyzed for gross beta activity and by Gamma Isotopic Analysis. The bones are analyzed for gross beta activity and Sr-89 and Sr-90. Reporting units are pCi/g wet weight.

Domestic Meat Domestic meat (chickens) may be collected once a year during the 3rd quarter, from six locations in the vicinity of the plant (K-20, K-24, K-27, K-29, K-34, and K-32). Samples may not be available every year at every location due to farmer preference. At least one control and one indicator should be collected. The fleshi is analyzed for gross alpha, gross beta, and by Gamma Isotopic Analysis to identify and quantify gamuna-emitting radionuclides. Reporting units are pCi/g wet weight.

Rev. II 3-3 12/14/2006

Ambient Radiation Two packets of thermoluminescent dosimeters (CaSO 4 : Dy cards) are placed at forteen locations, six of which are air sampling locations (K-If, K-2, K-7, K-8, K-16, and K-31) and four of which are milk sampling locations (K-3, K-5, K-25, and K-39); the remaining four locations are K -15, K-17, K-27, and K-30. One packet is changed quarterly and one annually. Annual TLDs will serve as an emergency set to be read when needed. They will be exchanged annually (without reading) if not read during the year. To insure the precision of the measurement, each packet will contain two cards with four dosimeters each (four sensitive areas each for a total of eight). For protection against moisture each set of cards is sealed in a plastic bag and placed in a plastic container.

Each card is individually calibrated for self-irradiation and light response. Fading is guaranteed by the manufacturer (Teledyne Isotopes) not to exceed 20% in one year. Minimum sensitivity for the multi-area dosimeter is 0.5 mR defined as 3 times the standard deviation of the background. Maximum Error (I standard deviation) - 6 0Co Gamma +/-0.2 mR or +/-3%, whichever is greater. The maximum spread between areas on the same dosimeter is 3.5% at 1 standard deviation.

Reporting units for TLDs are mR/91 days for quarterly TLDs and mR/exposure period for annual TLDs.

Tests for uniformity and reproducibility of TLDs as specified in ANSI N545-1981 and NRC Regulatory Guide 4.13, are performed annually.

Well Water One gallon water samples are taken once every three months from four off-site wells, (K-10, K-11, K-13, and K-25) and two on-site wells (K-lh and K-ig). All samples are analyzed for gross beta in the total residue, K-40, tritium, and by Gamma Isotopic Analysis. Samples from one on-site well are analyzed for Sr-89, and Sr-90. Samples from K-lh and K-lg are also analyzed for gross alpha.

Reporting units are pCi/1.

Precipitation A monthly cumulative sample of precipitation is taken at Location K-11. This sample is analyzed for tritium. Reporting units are pCi/l.

Milk Milk samples are collected from two herds that graze within three miles of the reactor site (K-25 and K-34); from four herds that graze between 3-7 miles of the reactor site (K-3, K-5, K-38, and K-39);

and one from a dairy in Green Bay (K-28), 26 miles from the reactor site.

The samples are collected twice per month during the grazing period (May through October) and monthly for the rest of the year. To prevent spoilage the samples are treated with preservative. All samples are analyzed by Gamma Isotopic Analysis and for iodine -131 immediately after they are received at the laboratory. To achieve required minimum sensitivity of 0.5 pCi/i, iodine is separated Rev. I1 3-4 12/14/2006

on an ion exchange column, precipitated as palladium iodide and beta counted. Monthly samples and monthly composites of semimonthly samples are then analyzed for Sr-89 and Sr-90. Potassium and calcium are determined and the 137Cs/gK and 90Sr/gCa ratios are calculated. Reporting units are pCi/I except for stable potassium and calcium, which are reported in g/l.

If milk samples are not available, green leafy vegetables will be collected on a monthly basis (when available) from Locations K-10, K-11, and K-26.

Grass Grass is collected three times per year (2nd, 3rd, and 4th quarters) from the six dairy farms (K-3, K-5, K-25, K-34, K-38, and K-39) and from two on-site locations (K-lb and K-If). The samples are analyzed for gross beta activity, for Sr-89 and Sr-90, and Gamma Isotopic Analysis to identify and quantify gamma-emitting radionuclides. Reporting units are pCi/g wet weight.

Cattlefeed Once per year, during the first quarter when grass is not available, cattlefeed (such as hay or silage) is collected from the six dairy farms. The analyses performed are the same as for grass. Reporting units are pCi/g wet weight.

Vegetables and Grain Annually, during the 3rd quarter, samples of five varieties of vegetables grown and marketed for human consumption are collected from K-17 and/or K-26, depending upon the availability of samples. If samples are not available from these locations, samples may be obtained from any local source so there is some sample of record. The location will be documented. In addition, two varieties of grain, if available, are collected annually from the farmland owned by Dominion Energy Kewaunee (K-23) and rented to a private individual for growing crops. The analyses performed are the same as for grass. Reporting units are pCi/g wet weight.

Egsz Quarterly samples of eggs can be taken from K-24, K-27, and K-32. At least one control and one indicator should be collected. The samples are analyzed for gross beta activity, for Sr-89 and Sr-90, and Gamma Isotopic Analysis to identify and. quantify gamma-emitting radionuclides. Reporting units are pCi/g wet weight.

Soil Twice during the growing season samples of the top two inches of soil are collected from the six dairy farms and from an on-site location (K-1f). The soil is analyzed for gross alpha and gross beta activities, for Sr-89 and Sr-90, and Gamma Isotopic Analysis to identify and quantify gamma-emitting manmade radionuclides. Reporting units are pCi/g dry weight.

Rev. II 3-5 12/14/2006

Surface Water Surface water is sampled monthly from Lake Michigan at the KPS discharge-(K-Id), and at Two Creeks Park, 2.5 miles south of the reactor site (K- 14). Samples are collected monthly at the Green Bay Municipal Pumping station between Kewaunee and Green Bay (K-9). Raw and treated water is collected. Monthly samples are also taken, when available, from each of the three creeks (K-la, K-lb, K-le) that pass through the reactor site and from the drainage pond (K-lk) south of the plant. The samples are taken at a point near the mouth of each creek and at the shore of the drainage pond. The water is analyzed for gross beta activity in:

a. The total residue,

b. The dissolved solids, and

c. The suspended solids.

The samples are also analyzed for K-40 and by Gamma Isotopic Analysis. Quarterly composites from all locations are analyzed for tritium, Sr-89 and Sr-90. Reporting units are pCi/l.

Bottom Sediments Five samples of Lake Michigan bottom sediments, one at the discharge (K-Id), one from 500 feet north of the discharge (K-ic), one from 500 feet south of the discharge (K-l j), and one at the Two Creeks Park (K-I4), one at the Green Bay Municipal Pumping Station (K-9) are collected semi-annually (May and November). The samples are collected at the beach in about 2-3 feet of water. All samples are analyzed for gross beta activity, for Sr-89 and Sr-90 and by Gamma isotopic Analysis. Since it' is known that the specific activity of the sediments (i.e., the amount of radioactivity per unit mass of sediment) increases with decreasing particle size, the sampling procedure will assure collection of very fine particles. Reporting units are pCi/g dry weight.

Rev. 11 3-6 12/14/2006

Table 2.2.1-A RadiologicalEnvironmental MonitoringProgram Exposure Pathway Minimum Available Sample Sampling, a b Collection and Type of Analysis And/Or Sample Required Samples =Locations Analysis Frequency

1. Direct Radiation' 5 Inner Ring locations K-5, K-25, K-27, See Table 2.2. 1-B Gamma dose K-7, K-iF, K-30 6 Outer Ring locations K-2, K-3, K-15, K-17, K-8, K-31, K-39 1 Control location K-16 1 Population center K-7 1 Special interest location K-8 I Nearby resident K-27

2. Airborne Radioiodine 3 samples close to the site K-if, K-2, K-7, K-8, See Table 2.2. .B Iodine (1-131) by and Particulates boundary in highest K-31 Continuous Gamma Isotopicf average X/Q sampler operation Iodine; charcoal I sample from the closest K-7 Particulates Particulates; gross community having the See Table 2.2. 1-B beta analysise highest X/Q Gamma isotopic I sample from a control K-16d See Table 2.2. 1-B of composite (by location location) f

3. Waterborne

a. Surfaceg 1 Upstream sample K-la, K-9, K-id Grab sample Gross Beta, I Downstream sample K-le, K-14, K-lk, K-lb See Table 2.2. 1-B Gamma isotopic Composite of grab samples for tritium, and Sr 89/90

b. Ground 1-2 location likely to be K-lg, K-lhh Grab sample Gamma isotopic affected d See Table 2.2. 1-B tritium analysis Gross Beta, Gross Alpha, Sr 89/90

c. Drinking 1-3 samples of nearest K-10, K-11, K-13, K-25 Grab sample Gross beta and water supply See Table 2.2.1-B gamma isotopic r analysis. Tritium analysis of the composite of monthly grab

d. Sediment from 1 sample from shoreline downstream area with potential for recreational value Rev. 11 Page 1 of 3 12/14/2006

Table 2.2.1-A RadiologicalEnvironmentalMonitoringProgram Exposure Pathway Minimum Available Sample Sampling, Type of Analysis And/Or Sample Required Samples *i am Locations b

JAnalysis Frequency Collection and

4. Ingestion

a. Milk Samples from milking K-5, K-25, K-34 See Table 2.2. 1-B 1-131 animals in 3 locations Gamma Isotopic f within 5 km having the highest dose potential. SR 89/90 I alternate location K-38, K-39 I control location K-3, K-28

b. Fish 3 random samplings of K-id See Table 2.2. 1-B Gamma isotopic r commercially and and edible portions recreationally important Gross Beta species in the vicinity of the discharge. Sr 89/90 on bones

c. Food Products Samples of leaf 2 samples neairest See Table 2.2.1-B Gamma isotopic f vegetables grown nearest highest predicted and 1-131 each of two different annual average ground Analysis.

offsite locations within 5 level D/Q. K-10, K-11 miles of the plant if milk sampling is not performed. I sample 15-30 km distant if milk sampling isnot performed. K-26

5. Miscellaneous samples not identified in NUREG-0472

a. Aquatic Slime None required K-lk See Table 2.2.1-B Gross Beta K-la, K-lb, K-Ie activity and if available Sr-89, K-14, K-ld Sr-90 and Gamma Isotopicf K-9 (control)

b. Soil None required K-If, K-5, K-25, K-39 Gross Alpha/Beta K-34, K-38 See Table 2.2. 1-B Sr-89 and Sr-90 K-3, (control) Gamma Isotopicr

c. Cattlefeed None required K-5, K-25, K-39 Gross Beta K-34, K-38 See Table 2.2. 1-B Sr-89 and Sr-90 K-3,(control) Gamma Isotopicf

d. Grass None required K-Ib, K-If, K-25, K-39 Gross Beta K-5, K-34, K-38 See Table 2.2. 1-B Sr-89 and Sr-90 K-3,(control) Gamma Isotopicf

e. Domestic Meat None required K-20, K-24, K-27, K-29 Gross Alpha/Beta K-32 (control), K-34 See Table 2.2.1 -B Gamma Isotopic' Rev. 11 Page 2 of 3 12/1412006

Table 2.2.1-A RadiologicalEnvironmentalMonitoring Program Exposure Pathway Minimum Available Sample Sampling, i S am b Collection and Type of Analysis And/Or Sample Required Samples" Locations fAnalysis Frequency

f. Eggs None required K-27 See Table 2.2.1-B Gross Beta K-32 Sr-89/90 K-24 Gamma Isotopicr

g. Precipitation None required K-i l See Table 2.2. 1-B Tritium

h. Vegetables/Grain None required K-17, K-23 See Table 2.2. 1-B Gross Beta Sr-89/90 K-26 (control) Gamma Isotopicf Table Notations

a. The samples listed in this column describe the minimum sampling required to meet REMP requirements.

b. Additional details of sample locations are provided in Table 2.2.1-C and Figure 1. The REMP requires that samples to be taken from each of the "available sample locations" listed (see section 3.1). Deviations from the required sampling schedule will occur if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, reasonable efforts shall be made to complete corrective actions prior to the end of the next sampling period.

All deviations from the sampling schedule shall be documented, as required by REMM 2.4.1 .c, in the Annual Radiological Environmental Monitoring Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the REMM. The cause of the unavailability of samples for that pathway and the new location(s) for obtaining replacement samples will be identified in the Annual Radiological Environmental Monitoring Report.

c. For the purposes of this table, each location will have 2 packets of thermoluminescent dosimeters (TLDs). The TLDs are CaSO4: Dy cards with 2 cards/packet and 4 dosimeters/card (four sensitive areas each for a total of eight dosimeters/packet). The NRC guidance of 40 stations is not an absolute number. The number of direct radiation monitoring stations has been reduced according to geographical limitations; e.g., Lake Michigan. The frequency of analysis or readout for TLD systems depends upon the characteristics of the specific system used and selection is made to obtain optimum dose information with minimal fading.

d. The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.

e. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

f. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

g. The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. The "downstream" sample shall be taken in an area near the mixing zone.

h. Ground water samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

Rev. 11 Page 3 of 3 12114/2006

Table 2.2.1-B Type and Frequencyof Collection Location Weekly Biweekly Monthly Quarterly ] Semi-Annually Annually K-la SW SLO K-lb SW GR' SLo BSb K-ic K-Id SW Ha BSb SL1 K-ie SW SLf K-If AP Al GRa TLD SO K-Ig WW K-lh WW BSb K-Ij K-lk SW SL' K-2 AP Al TLD K-3 MIC GR' TLD CFd So K-5 MIC GRa TLD CFd so K-7 AP Al TLD K-8 AP Al TLD K-9 SW BSb SLo K-10 GLVC WW K-1 I PR, WW GLVe K-13 WW K-14 SW BSb SLO K-15 TLD K-16 AP AI TLD K-17 TLD VE DM 4 K-20 K-23 GRN K-24 EG DM K-25 MIC GRa TLD CFd WW So K-26 GLV VE K-27 EG TLD DM K-28 MIr K-29 DM K-30 TLD K-31 AP Al TLD K-32 EG DM K-34 MIc GR CFd So DM Rev. II Page 1 of 2 12/14/2006

Table 2.2.1-B Type and Frequency of Collection Location Weekly Biweekly Monthly Quarterly Semi-Annually Annually K-38 MIr GRa CF1d So K-39 Mr I TLD GRa CFd So

a. Three times a year, second (April, May, June), third (July, August, September), and fourth (October, November, December) quarters

b. To be collected in May and November

c. Monthly from November through April; semimonthly from May through October

d. First (January, February, March) quarter only

e. Alternate if milk is not available

f. Second and third quarters Code Description Code Description Code Description Al Airborne Iodine FI Fish SO Soil -d AP Airborne Particulate GR Grass SW Surface Water BS Bottom Sediment GRN Grain TLD Thermoluminescent Dosimeter CF Cattlefeed MI Milk VE Vegetables DM Domestic Meat PR Precipitation WW Well Water EG Eggs SL Slime GLV Green Leafy Vegetables Rev. 11 Page 2 of 2 12/14/2006

Table 2.2.1-C Sampling Locations,Kewaunee Power Station Distance Code Type' (ilesP)b and Location Sector K-1 Onsite K-la I 0.62 N North Creek K-lb I 0.12N Middle Creek K-ic I 0.10 N 500' North of Condenser Discharge K-Id I 0.10 E Condenser Discharge K-le I 0.12 S South Creek K-if I 0.12 S Meteorological Tower K-Ig I 0.06 W South Well K-lh I 0.12 NW North Well K-lj I 0.10 S 500' south of Condenser Discharge K- 1k 1 0.60 SW Drainage Pond, south of plant K-2 C 9.5 NNE WPS Operations Building in Kewaunee K-3 C 6.0 N Lyle and John Siegmund Farm, N2815 Hy 42, Kewaunee K-4(h) 1 3.0 N Tom Stangel Farm, E4804 Old Settlers Rd, Kewaunee K-5 I 3.5 NNW Ed Paplham Farm, E4160 Old Settlers Rd, Kewaunee K-6(e) C 6.7 WSW Novitsky Farm, El 870 Cty Tk BB, Denmark K-7 1 2.75 SSW Ron Zimmerman Farm, 17620 Nero Rd, Two Rivers K-8 C 5.0 WSW Saint Isadore the Farmer Church, 18424 Tisch Mills Rd, Tisch Mills Green Bay Municipal Pumping Station, six miles east of Green K-9 C 11.5 NNE Bay (sample source is Lake Michigan from Rostok Intake 2 miles north of Kewaunee)

K-10 I 1.5 NNE Turner Farm, Kewaunee Site K-Il I 1.0 NW Harlan Ihlenfeld Farm, N879 Hy 42, Kewaunee K- 12(i) I 1.5 WSW LiCaptain Farm, N491 Woodside Rd, Kewaunee K-13 C 3.0 SSW Rand's General Store, Two Creeks K-14 I 2.5 S Two Creeks Park, 2.5 miles south of site K-15 C 9.25 NW Gas Substation, 1.5 miles north of Stangelville K-16 C 26 NW WPS Division Office Building, Green Bay, Wisconsin K-17 I 4.25 W Jansky's Farm, N885 Cty Tk B, Kewaunee K- 19(f) I 1.75 NNE Wayne Paral Farm, N1048 Lakeview Dr., Kewaunee K-20 I 2.5 N Carl Struck Farm, N1596 Lakeshore Dr., Kewaunee K-23 I 0.5 W 0.5 miles west of plant, Kewaunee site Rev. 11 Page 1 of 2 12/14/2006

Table 2.2.1-C Sampling Locations, Kewaunee Power Station Distance Code Typea (Miles)b and Location Sector K-24 1 5.45 N Fectum Farm, N2653 Hy 42, Kewaunee K-25 1 2.75 SW Wotachek Farm, E3968 Cty Tk BB, Two Rivers K-26(d) C 10.7 SSW Bertler's Fruit Stand (8.0 miles south of"BB")

K-27 I 1.5 NW Schlies Farm, E4298 Sandy Bay Rd K-28 C 26 NW Hansen Dairy, 1742 University Ave., Green Bay, Wisconsin K-29 I 5.75 W Kunesh Farm, E3873 Cty Tk G, Kewaunee K-30 I 1.00 N End of site boundary K-31 I 6.25 NNW E. Krok Substation, Krok Road K-32 C 11.50 N Piggly Wiggly, 931 Marquette Dr., Kewaunee K-33(g) 1 4.25 W Gary and Lynn Holly Farm, E2885 Holly Lane, Tisch Mills K-34 I 2.5 N Leon and Vicky Struck Farm, N1549 Lakeshore Drive, Kewaunee K-35(j) C 6.75 WNW Jean Ducat Farm, N1215 Sleepy Hollow, Kewaunee K-36(j) I Fiala's Fish Market, 216 Milwaukee, Kewaunee K-37 (k) 1 4.00 N Gary and Ann Hardtke Farm, E4282 Old Settlers Road, Kewaunee K-38 I 3.8 WNW Dave Sinkula Farm, N890 Town Hall Road, Kewaunee K-39 I 4.00 N Francis Wotja Farm, N 1859 Lakeshore Road, Kewaunee

a. I = indicator; C = control.

b. Distances are measured from reactor stack.

c. Deleted

d. Location K-18 was changed because Schmidt's Food Stand went out of business. It was replaced by Bertler's Fruit Stand (K-26).

e. Replaced by K-33 in summer of 2000. Retired from farming.

f. Replaced by K-34 in summer of 2000. Retired from farming.

g. Replaced by K-35 in fall of 2000.

h. Sold farm in summer of 2000, replaced by K-25

i. Retired from farming in summer of 2000

j. Removed from the program in Fall of 2001

k. Removed from the program in Fall of 2002 Rev. 11 Page 2 of 2 12/14/2006

Table 2.2.1-D ReportingLevels for Radioactivity Concentrationsin EnvironmentalSamples Rd Reporting Levels Medium CV to KPSO KPS to NRCb Airborne Particulate or Gases (pCi/m3) Gross Beta 1 --

1-131 (Charcoal) 0.1 0.9 Cs-134 1 10 Cs- 137 1 20 Precipitation (pCi/I) H-3 1,000 --

Water (pCi/I) Gross Alpha 10 --

Gross Beta 30 --

H-3 10,000 20,000c Mn-54 100 1,000 Fe-59 40 400 Co-58 100 1,000 Co-60 30 300 Zr-Nb-95 40 400 Cs-134 10 30 Cs- 137 20 50 B a-La- 140 100 200 Sr-89 8d-8d Sr-90 Zn-65 30 300 Milk (pCi/l) 1-131 1.0 3 Cs- 134 20 60 Cs- 137 20 70 Ba-La-140 100 300 Sr-89 10 - -

Grass, Cattle Feed, and Vegetables (pCi/g. Gross Beta 30 - -

wet) 1-131 0.1 0.1 Cs-134 0.2 1 Cs-137 0.2 2 Sr-89 I - -

Sr-90 1 --

Rev. 11 Page 1 of 2 12/14/2006

Table 2.2.1-D Reporting Levelsfor Radioactivity Concentrationsin EnvironmentalSamples Medium Radionuclide Reporting Levels CV to KPSý KPS to NRCb Eggs (pCi/g wet) Gross Beta 30 - -

Cs- 134 0.2 1 Cs- 137 0.2 2 Sr-89 I --

Sr-90 1 --

Soil, Bottom Sediments (pCi/g) Gross Beta 50 - -

Cs-134 5 - -

Cs-137 5 --

Sr-89 5 --

Sr-90 5 --

Meat (pCi/g wet) Gross Beta (Flesh, 10 - -

Bones)

Cs- 134 (Flesh) 1.0 1.0*

Cs- 137 (Flesh) 2 2.0 Sr-89 (Bones) 2 Sr-90 (Bones) 2 Fish (pCi/g wet) Gross Beta (Flesh, 10 --

Bones)

Mn-54 -- 30.0 Fe-59 - 10.0 Co-58 - 30.0 Co-60 -- 10.0 Cs- 134 (Flesh) 1 1.0 Cs-137 (Flesh) 2 2.0 Sr-89 (Bones) 2 --

Sr-90 (Bones) 2 -

Zn-65 (Bones) -- 20

a. Radionuclides will be monitored by the CV and concentrations above the listed limits will be reported to KPS.

b. Concentrations above the listed limits will be reported to NRC as required by Specification 2.2.1.b.

c. For drinking water samples, this is 40CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l may be used.

d. The Sr-89/90 values are based on the EPA drinking water standards. See note -f." of Table 2.3. 1-A for further information Rev. 11 Page 2 of 2 12/14/2006

I I ( I [ I . I f " [I - [ ,, f ( , I- r Table 2.3.1-A Detection Capabilitiesfor Environmental b,c Analysis Sample Limit of Detection (LU))

Lower Analysis i Water Airborne Particulate or3 Fish Milk (pCi/l)

Food Products Sediment (pCi/l) Gases (pCi/m ) (pCi/kg, wet) ((pCi/kg, dry)

Gross Beta 4 0.01 2000d H-3 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zr-Nb-95 15 1-131 1 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 Zn-65 30 260 Sr-89/90 5 I Rev. 11 Page I of 3 12/14/2006

0 Table Notationsfor Table 2.3.1-A

a. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environment Monitoring Report.

b. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

c. The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD = 4.66sb E x V x 2.22 x Y x exp(--yAt)

Where:

LLD is the a priori lower limit of detection as defined above, as picocuries per unit mass or volume, Sb is the standard deviation of the background counting rate or of the counting rate of blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, y is the radioactive decay constant for the particular radionuclide, and At for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting, Typical values of E, V, Y, and At should be used in calculation.

Rev. 11 Page 2 of 3 12/14/2006

6 Table Notationsfor Table 2.3.1-A (con 't)

It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Monitoring Report.

d. If no drinking water pathway exists, a value of 3,000 pCi/1 may be used.

e. LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

f. This is NOT a NUREG-0472 required value. It is based on EPA drinking water standards, which tie into the NEI Groundwater Protection Initiative that was implemented at KPS on August 4, 2006.

Rev. 11 Page 3 of 3 12/14/2006

FIGURE 1 WTME<4 U

Off/

Rev. 11 Page 1 of 1 12/14/2006

REMM I ODCM REVISION DOCUMENTATION FORM This is a change to the (circle one):

Current Revision Number: 10 New Revision Number.-.

Initiated by: Re)C( A i.s Date: _/ A__ _.

t-Track Items included in this revision: R,YZ ýLP;0 I MAC~6, pCag g744 I

Describe Change Describe Reason 0 siý-vscwsslo,-, - Wa t-&Lt..ypo. ¶ The AcA4"l T-S k%4

~~~y aW~ as 'tc4% 4 LaA~cc 0

K fA&+09ger OaeY' 0 CA .. -AWA 4lv&W *tekeviCe- Weo~rc.

0 T'-He TJ.Q'M-L cWVia efb. 6iev4V3 ftts wlAth a Vjrt t-

&mIc

&rt,;9*Q 0 u ~ 10,vmksWS iu levot ex-~-S d~ad.4f Cl~ie-A-fxu repsO &41 .-. ~ W&

a ,*- 11vi% "

____ ___ __ Wt;- IJ~itŽ 'A.o, 1A.

-FXVCcT~\J DEC 4 2006 Form NAD-05.13-1 Rev. G Date: APR 11 2006 Page 6 of 7 INFORMATION USE*

REMM I ODCM REVISION DOCUMENTATION FORM Attach Appropriate 50.59 Documentation.

• Attach 50.59 Applicability Review documentation (copy or original, as applicable).

50.59 Applicability Review rM Copy Attached EK Original Attached F1 Attach additional supporting 50.59 documents, as applicable.

50.59 Pre-Screening El Copy Attached [] Original Attached N/A 50.59 Screening El Copy Attached El Original Attached N/A 50.59 Evaluation Ej Copy Attached E] Original Attached N/A Reviewed by: /D Technical Review: I f- Date I ?- q-66 (Print W U Approved by:

RP-Chem Manager Review:

• -- -- /Date:

(Print / Sign)

Reg. Affairs Manager Review:

7dP2~'cE~)Date:

(Print / Sign)

Reviewed and Accepted by PORC at Meeting o e.

Date:

I Aoczaf Ae,- Zsma

,I PORC Chairman (Print / Sign)

Form NAD-05.13-1 Rev. G Date: APR 11 2006 Page 7 of 7 INFORMATION USE

50.59 APPLICABILITY REVIEW (Is the activity excluded from 50.59 review?)

I. Document/Activity number. REMM Revision 11

2. Brief description of proposed activity (what is being changed and why):

Adding information to help implement the NEI Groundwater Protection Initiative adopted 8/4/06/

Does the proposed activity involve or change any of the following documents or processes? Check YES or NO for EACH applicability review 3.

item. Explain in comments if necessary. [Ref. 50.59 Resource Manual, Section 4]

NOTE: If you are unsure if a document or process may be affected, contact the process owner.

Yes No Document or Applicable Contact/Acton v"

• Process Regulation a 0 Technical Specifications or Operating License 10CFR50.92 Process change per NAD-05.14.

Contact Licensing.

Identify NRC letter in comments below. Process b l Activity/change previously approved by NRC in I0CFR50.90 change.

license amendment or NRC SER Contact Licensing for assistance.

Activity/change covered by an existing approved IOCFR50 Append B Identify screening or evaluation in comments below.

c 0 0 0OCFR50.59 review, screening, or evaluation. Process change.

d Dominion Quality Assurance Program Description IOC a) Contact QA.

__ [ (DOM-QA-I) Refer to NO-AA-101.

e 0 0 Emergency Plan IOCF50 . ) Contact EP.

______EmergencyP__anI 0C_ RS0.54(q) Refer to FP-R-EP-02.

f 0 0 Security Plan lOCF;R504(p) Contact Security.

_ _ _Sec __rity__P__an__I 0_ 50.54p)

_ _ Refer to FP-S-SPE-0I.

g E0 0 IST Plan IOCFR50.55a(f) Contact IST process owner.

Refer to NAD-01.24.

h [0 0 ISI Plan IOCFR50.55a(g) Contact ISI process owner.

Refer to NADs 01.03, 01.05, and 05.11.

i 0 ECCS Acceptance Criteria IOCFR50.46 Contact licensing.

USAR or any document incorporated by reference - Process USAR change per NEP.05.02.

j Check YES only if change is editorial (see IOCFRS0.71 Contact USAR process owner for assistance.

Attachment A). _ontatUSARprocessownerfo__ assistance.

Commitment - Commitment changes associated Contact licensing.

k 0 ] with a response to Generic Letters and Bulletins, or IOCFR50 Appendix B Refer to NAD-05.25.

if described in the USAR require a pre-screening.

Maintenance activity or new/revised maintenance procedure - Check YES only if clearly maintenance IOCFR50.65 Evaluate under Maintenance Rule.

and equipment will be restored to its as-designed Refer to HAD-08,20 and NAD-08.21.

condition within 90 days (see Attachment C).

New/revised administrative or managerial directive/procedure (e.g., NAD, GNP, Fleet m E] Procedure) or a change controlled document to any (e.g., procedure plant or other drawing) which is IOCFR50 Appendix B Process procedureldocument revision.

clearly editorial/administrative. See Attachments A and B.

4. Conclusion. Check one of the following-o] All documents/processes listed above.are checked NO. IOCFR50.59 applies to the proposed activity. A 50.59 pre-screening shall be performed.

.0 One or more of the documents/processes listed above are checked YES, AM controls all aspects of the proposed activity. 10CFR50.59 does NQT apply. Process the change under the applicable program/process/procedure.

[J One or more of the documents/processes listed above are checked YES, however, some portion of the proposed activity is not controlled by any of the above processes. IOCFR50.59 applies to that portion. A 50.59 pre-screening shall be performed.

5. Comments:

Changes to values in the REMM were more conservative to assist in implementation of NEI Groundwater Protection itiaitive activities. These are deemed to be adiministrative as the changes are more conservative, and do not change any requirements of the program as described in NUREG-0472.

6. Print name followed by signature. Attach completed form t ukment/activity/change package.

Prepared by: Richard W. Adams \i*J'J4 0"lr Date: 9129/06 (print/sign)

Reviewed by: I s Date: ____" _____

(print/sign)

Form GNP-04.04.01-1 Rev. J Date: AUG 3 2006 Page 15 of 16 INFORMATION USE