ML041120043

Annual Radiological Environmental Operating Report

ML041120043
Person / Time
Site:	Wolf Creek
Issue date:	04/15/2004
From:	Moles K Wolf Creek
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA 04-0038
Download: ML041120043 (189)

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- -

• WOLF-CREEK-

'NUCLEAR OPERATING CORPORATION Kevin J. Moles

Manager RegulatoryAffairs APR 1 2004 RA 04-0038

- U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Docket No. 50-482: 2003 Annual Radiological Environmental Operating Report Gentlemen:

Enclosed is the Annual Radiological Environmental Operating Report, which is being submitted pursuant to Wolf.Creek Generating Station (WCGS) Technical Specification 5.6.2. This report covers radiological environmental monitoring around WCGS -for the period of January 1, 2003, through December 31, 2003.

No commitments are identified in this correspondence. If you have any questions concerning this matter, please contact me at (620) 364-4126, or Mr. William Muilenburg at (620) 364-8831, ext. 4511.

Sincer y, Kevin J. M SQ--

KJM/rIg Enclosure cc: J. N. Donohew (NRC), w/e D. N. Graves (NRC), wle B. S. Mallett (NRC), wle Senior Resident Inspector (NRC), we P.O. Box 411/ Burlington, KS 66839/ Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNVET v

WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION 2003 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT April 15, 2004

TABLE OF CONTENTS List of Tables ii List of Figures ii List of Charts ii Introduction 1

I.

Program Description 1

II. Discussion of Results 4

Ill. Annual Land Use Census Results 10 IV. Program Revisions/Changes 11 V.

Program Deviations 11 VI. Interlaboratory Comparison Program Results 11 VII. Comparison to the Radioactive Effluents Release Program 12 VIII. Supplier Quality Audits or Surveillances 12 Tables 13 Figures 24 Charts 29 Appendix A - Interlaboratory Comparison Program Results A-1 Appendix B - Summary Tables B-1 Appendix C - 2003 Individual Sample Results C-1 Air Particulate Filters C-2 Charcoal Filters C-25 Surface Water C-37 Ground Water C-51 Drinking Water C-73 Shoreline Sediment C-94 Fish C-98 Food/Garden Crops C-105 Feed and Forage C-114 Bottom Sediment C-117 Aquatic Vegetation C-121 Terrestrial Vegetation C-122 Soil C-123 Deer C-1 25 i

LIST OF TABLES 1 Radiological Environmental Monitoring Program Description 13 2

Sample Location Numbers, Distances (Miles) and Directions 18 3 TLD Results 19 4 Land Use Census Data 21 5

Comparison of 2002 and 2003 Land Use Census Milk and Garden Data 22 6

Dosimetry Performance Testing Results 23 LIST OF FIGURES 1 Airborne Pathway Sampling Locations 24 2 Direct Radiation Pathway Sampling Locations 25 3 Waterborne Pathway Sampling Locations 26 4 Ingestion Pathway Sampling Locations 27 5

Distant Sampling Locations 28 LIST OF CHARTS 1 Airborne Gross Beta Weekly Results 29 2 Historical Airborne Smoothed Indicator and Control Gross Beta 30 3 TLD Nearsite Locations and Control Locations 31 4 Wolf Creek Lake Surface Water Smoothed Tritium Data 32 5

Drinking Water Gross Beta, Historical 33 6

Detected Co-60 Activity in Wolf Creek Lake Discharge Cove Bottom Sediment 34 7

Detected Cs-1 37 Activity in Bottom Sediment 35 8

Detected Cs-134 Activity in Wolf Creek Lake Discharge Cove Bottom Sediment 36 9 Tritium Dose in Wolf Creek Lake Surface Water and Released Liquid Tritium 37 Maximum Organ Dose ii

INTRODUCTION The 2003 Annual Radiological Environmental Operating Report for Wolf Creek Generating Station (WCGS) covers the period from January 1 through December31, 2003. WCGS is located in Coffey County, Kansas, approximately five miles northeast of Burlington, Kansas.

Fuel loading commenced at WCGS on March 12, 1985.

The operational phase of the Radiological Environmental Monitoring Program (REMP) began with initial criticality on May 22, 1985, and the first detectable quantities of radioactivity were reported in plant effluents in June 1985.

This report contains a description of the REMP conducted by Wolf Creek Nuclear Operating Corporation (WCNOC), results of sample analyses, a discussion of monitoring program results, a description of revisions to and deviations from the program, and the results of Interlaboratory Comparison Programs.

Individual sample results and a summary of results in the Nuclear Regulatory Commission (NRC) Branch Technical Position specified format are included as appendices.

Plant-related activation, corrosion or fission products were not detected during 2003 in airborne particulate and radioiodine filters, ground water, drinking water, shoreline sediment, broadleaf vegetation, crops, terrestrial vegetation, aquatic vegetation, soil or deer samples. Activation, corrosion or fission products attributable to plant operation were detected during 2003 in surface water, fish, and bottom sediment samples.

Nuclides detected in REMP samples were below applicable NRC reporting levels, and program lower limits of detection were met.

Based upon the radiological environmental monitoring results, it is concluded that station operations has had no significant radiological impact on the health and safety of the public or the environment.

1. PROGRAM DESCRIPTION Radiological environmental samples were collected according to the schedule in WCGS procedure AP 07B-004, Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program).

Environmental samples were collected by the WCGS Environmental Management group and were analyzed by Environmental, Inc.

Detroit Edison processed environmental thermoluminescent dosimeters (TLDs) at the Enrico Fermi 2 plant. Table 1 lists sampling pathways and frequencies of sampling and analysis.

Table 2 lists each sample location's distance and direction from the plant. Samples in addition to those required by the WCGS Offsite Dose Calculation Manual (ODCM) were also obtained.

The following is a description of the sampling and analysis program by individual pathways.

2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 1 of 37

A. Airborne Pathway Low volume air sampling pumps collected particulate and radioiodine samples on 47 mm glass fiber filters and charcoal canisters, respectively.

The filters and charcoal canisters were changed out weekly, labeled, and shipped to Environmental, Inc. for analysis. The volume of air sampled was calculated from the average of initial and final flow rates and the total time of collection. Each pump was equipped with a time totalizer that was checked weekly against the elapsed time to identify electrical power outages.

Gross beta analysis of the air particulate samples was performed after a nominal 72-hour period to allow the radon and thoron daughter products to decay.

Weekly air particulate filters were combined into quarterly composites for each location and analyzed for gamma emitting isotopes.

Charcoal canisters were routinely counted in groups of five to determine the presence or absence of 1-131. Positive indication of 1-131 would have resulted in analysis of each individual charcoal canister.

Air samples were collected from six locations. Indicator locations 2, 18 and 37 are located in the three sectors with the highest ground level deposition constants (D/Q).

Air sampling stations are also located in the community of New Strawn (indicator location 32) and a control location at Harris (location 48). A control location at Hartford (location 40) was eliminated during the sample year. Distances and directions to sampling locations from the plant are listed in Table 2, indicator locations are shown in Figure 1, and the control locations are shown in Figure 5.

B. Direct Radiation Pathway Panasonic UD-814-AQ TLDs were used at 48 locations during the sample year. The TLDs consist of one lithium-borate element and three calcium sulfate elements in a plastic case.

TLDs were typically positioned roughly 3 to 4 feet above the ground in plastic thermostat boxes.

The thermostat boxes protect the TLDs from the elements and tampering. Two TLDs were placed at each designated location. Indicator TLD sample locations are illustrated in Figure 2 and control locations are shown in Figure 5. Table 2 provides the distance and direction of each location from the plant. Control locations were 39 (Beto Junction), 40 (Hartford) and 48 (Harris).

C. Waterborne Pathway All water samples were analyzed to determine whether gamma emitters were present. In addition to gamma isotopic analysis, radiochemical analysis for 1-131 was performed on drinking water and ground water samples. Gross beta analysis was also performed on drinking water samples. Tritium analysis was performed monthly by liquid scintillation for surface water and quarterly for drinking water. Tritium analysis was also performed quarterly on ground water samples. Water sampling locations are listed in Table 2 and are shown in Figures 3 and 5.

Monthly grab samples of surface water were collected from the outfall of John Redmond Reservoir (JRR) as a control location (location MUSH [Make-Up Screen House]) and from the 2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 2 of 37

discharge cove (DC) of Wolf Creek Lake (WCL) as an indicator location. During the sample year, the control location was moved to JRR (location JRR).

Quarterly grab samples of ground water were collected from five wells.

Location B-12 is hydrologically up gradient from the site and was used as a control location. Four locations (C-10, C-49, D-65 and J-1) are hydrologically down gradient from the site and were used as indicator sample locations. During the sample year, location D-65 was eliminated from the program due to sample unavailability. Duplicate samples were obtained from location C-49 and were labeled L-49. These duplicate samples served as laboratory quality checks.

Drinking water was sampled at the water treatment facilities for the towns of Burlington (control location BW-15) and LeRoy (indicator location LW-40).

The Burlington facility is located upstream and the LeRoy facility is located downstream of the confluence of the discharge from Wolf Creek Lake and the Neosho River. Composite samples were obtained monthly from automatic samplers at each location that collected approximately 27 ml of drinking water every two hours.

Shoreline sediments were sampled semiannually for gamma analysis at the Wolf Creek Lake discharge cove (DC) indicator location and at the control location (JRR).

D. Ingestion Pathway Because no sampling locations that produce milk for human consumption were identified within five miles of the plant, milk was not collected during the sample year.

Fish were sampled semiannually from the tail waters of JRR (control, Figure 4) and from Wolf Creek Lake (indicator, Figure 4) for gamma isotopic analysis. Several species of game fish and rough fish were sampled. Gamma isotopic analysis was performed on boneless meat portions of the fish. Fish were also analyzed for tritium.

Broadleaf vegetation samples were collected monthly when available during the growing season from five gardens. Three indicator (G-1, H-1 and N-1) gardens (Figure 4) and two control (D-1 and S-4) gardens (Figure 5) were sampled.

Gamma isotopic analyses were performed on all samples.

Crop samples were obtained from two indicator locations (NR-D1 and NR-D2) downstream of the confluence of Wolf Creek and the Neosho River. The samples were irrigated with water from the Neosho River. One crop sample was obtained from control location NR-U1; however, the sample was not irrigated with Neosho River water.

Gamma isotopic analysis was performed on each sample. Crop sample locations are identified on Figure 5.

E. Additional Samples Collected (not required by ODCM)

Surface water was collected monthly from the spillway (SP) of Wolf Creek Lake as an indicator location.

The water samples were analyzed by gamma isotopic analysis and were also analyzed for tritium. These samples were collected as part of a cooperative sampling effort with the Kansas Department of Health and Environment (KDHE).

The sample location is identified on Figure 3.

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Drinking water indicator location NF-DW (Neosho Falls) was sampled during the year. The drinking water sample was analyzed for gross beta, gamma emitters and 1-131. This sample location was added due to the upcoming closure of the LeRoy drinking water treatment facility and is identified on Figure 5.

Shoreline and bottom sediments were collected for gamma analysis at the Environmental Education Area (EEA) and the Make-up Water Discharge Structure (MUDS). These samples were collected as part of a cooperative sampling effort with the KDHE. The sample locations are identified on Figure 3.

Bottom sediment samples were collected semiannually for gamma analysis at the Wolf Creek Lake discharge cove (DC) indicator location and the control location (JRR). These samples were collected as part of a cooperative sampling effort with the KDHE. The sample locations are identified on Figure 3.

Aquatic vegetation was collected for gamma analysis from indicator location EEA. This sample was collected as part of a cooperative sampling effort with the KDHE. The sample location is identified on Figure 3.

Terrestrial vegetation was sampled from indicator location EEA for gamma isotopic analyses.

This sample was collected as part of a cooperative sampling effort with the KDHE. The sample location is identified on Figure 4.

Soil was sampled from indicator locations MUDS and EEA for gamma isotopic analyses. These samples were collected as part of a cooperative sampling effort with the KDHE. The sample locations are identified on Figure 4.

A road-killed deer was sampled from indicator location A2.1 for gamma isotopic analyses. The sample was split with the KDHE. The sample location is identified on Figure 4.

Distance and direction information for the sampling locations listed in this section are outlined in Table 2.

II. DISCUSSION OF RESULTS Analysis results for all pathways are summarized in Appendix B using the format described in Radiological Assessment Branch Technical Position, Revision 1, November 1979 (NRC Generic Letter 79-065). Results for individual samples are listed in Appendix C.

In this section, results are discussed by pathway and analysis type. Monitoring results are compared with control data, preoperational values, sources of radioactivity, and effluent releases when applicable. Trends or seasonal effects are discussed.

A. Airborne Pathway Chart 1 graphically illustrates weekly gross beta results for the sample year. Chart 2 represents the historical smoothed averages of indicator and control gross beta data.

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Charts 1 and 2 demonstrate how closely the indicator and control locations tracked together.

Chart 2 reveals a seasonal cyclic trend in which gross beta values peak in the winter months (December or January) and decrease to a low point in the spring months (May or June). This trend is expected and is attributed to seasonal meteorological changes, i.e., changes in prevailing winds and precipitation.

The gross beta results of 2003 were compared to pre-operational monitoring results of 1983 and 1984.

The weekly gross beta analyses range for 1983 and 1984 was 0.0064 to 0.084 pCi/M3. The 2003 weekly gross beta analyses range for indicator locations was 0.014 to 0.057 pCiIm3, which was within the 1983 and 1984 pre-operational range. Additionally, the annual mean for indicator locations for 2003 (0.029 pCi/M3) was lower than the annual mean for 1983 (0.032 pCi/M3).

The gross beta results for the indicator locations were also compared to the control locations.

The annual mean for indicator locations for 2003 (0.029 pCi/M3) was similar to the annual mean of the control locations (0.028 pCi/iM3).

Naturally occurring Be-7 activity was detected, as was the case during pre-operational monitoring.

In 1984, the range for Be-7 detected activity was 0.024 to 0.211 pCi/M3 for indicator locations, and the annual mean for indicator locations was 0.069 pCi/M3. In 2003, the range for Be-7 detected activity was 0.044 to 0.084 pCi/M3 for indicator locations, and the annual mean for indicator locations was 0.071 pCi/M3.

The control location annual mean for Be-7 detected activity (0.068 pCi/M3) was similar to the indicator locations annual mean (0.071 pCi/i 3).

Required lower limits of detection were met and 1-131 activity was not detected in the weekly analysis of charcoal filters at any location.

No effects of plant operation were seen via the airborne pathway for the year, and no unusual trends were noted.

B. Direct Radiation Pathway Quarterly gamma exposures measured at each location are shown in Table 3. Measured values have been converted to a standard 90-day quarter.

The annual mean of all indicator locations in 2003 was 0.217 mR/day and the annual mean for the control locations was 0.203 mR/day. These results are similar to the pre-operational results for 1981. In 1981, the annual mean of all indicator locations was 0.21 mR/day and annual mean for the control locations was 0.19 mR/day.

Results from TLDs located near the plant (less than three miles), which would be most affected by changes in plant operation, were combined into quarterly averages.

These nearsite averages, using locations 1, 2, 7-14, 18, 26-30, 37 and 38, are compared to control location results (locations 39 and 40) in Chart 3. Chart 3 also includes preoperational data for comparison.

The nearsite TLD locations have historically trended higher than the control locations both prior to and after WCGS became operational.

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C. Waterborne Pathway (1) Surface Water Tritium, attributable to WCGS operation, was detected in all surface water samples collected from Wolf Creek Lake during 2003. An adult drinking 2 liters per day of surface water collected from the Wolf Creek Lake discharge cove, using the annual mean of detected tritium activity (15,627 pCi/liter), would receive a committed effective dose equivalent of 0.713 mRem per year. An adult drinking 2 liters per day of surface water collected from the Wolf Creek Lake discharge cove, using the highest detected tritium activity which was from the sample collected during August (26,793 pCi/liter), would receive a committed effective dose equivalent of 1.223 mRem per year. It should be noted that Wolf Creek Lake is not a drinking water source. Chart 4 illustrates smoothed tritium data for location DC from startup in May 1985 through 2003.

The discharge cove surface water sample collected during August was taken approximately nine hours after a permitted release was made under the Radioactive Effluent Release Program.

The curies of liquid tritium discharged during the third quarter of 2003 were approximately twice the amount released during the second quarter of 2003 (1st quarter = 311 Ci; 2nd quarter = 324 Ci; 3d quarter = 711 Ci; 4 quarter = 152 Ci). The detected tritium activity in September surface water obtained from the discharge cove returned to the expected lower value (16,721 pCi/liter).

It can be seen in Chart 4 that monthly surface water tritium concentrations have trended upward since plant startup. This is expected until the average tritium concentration of the lake reaches equilibrium.

Required lower limits of detection were met and tritium activity was not detected in samples obtained from the control locations (MUSH & JRR).

During pre-operational environmental radiological monitoring, measured radiological activity was not detected in surface water samples.

Tritium was the only activity detected in surface water samples and no unusual trends were noted.

(2) Ground Water Required lower limits of detection were met and radioactivity was not detected in any ground water samples.

(3) Drinking Water Chart 5 illustrates the historical drinking water gross beta data and how closely the gross beta results compared for the indicator (LW-40) and control (BW-1 5) locations.

Gross beta activity was detected in all drinking water samples. The annual mean of the control location gross beta activity (4.8 pCi/liter) was higher than the annual mean of the indicator locations (4.6 pCi/liter). The 2003 annual means of gross beta activity for both the control and indicator locations were lower than those of the pre-operational monitoring year of 1984. In 2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 6 of 37

1984, the annual mean of the control location gross beta activity was 6.4 pCi/liter, and the annual mean of the indicator location gross beta activity was 7.5 pCi/liter.

Required lower limits of detection were met. Tritium activity was not detected in any drinking water samples. Additionally, radionuclides were not detected by the 1-131 or gamma isotopic analyses.

Activity due to plant operation was not evident in drinking water samples during 2003 and no unusual trends were noted.

(4) Shoreline Sediment Naturally occurring K-40 was detected in samples obtained from indicator locations (10,623-11,677 pCi/kg, dry) and in samples obtained from control locations (4,565-11,960 pCi/kg, dry).

K-40 was also detected during pre-operational shoreline sediment monitoring.

Cs-137 activity was detected in a shoreline sample obtained from indicator location EEA (144.1 pCi/kg, dry). The Cs-137 concentration measured was below concentrations measured pre-operationally. The pre-operational range for Cs-137 detected activity at location discharge cove was 224 pCi/kg to 437 pCi/kg. The decay corrected pre-operational range is 145.5 to 283.9 pCi/kg. Cs-134 activity has not been detected in shoreline sediment samples, bottom sediment samples or soil samples collected from the EEA sample location. The measured Cs-137 activity was likely due to previous fallout and not to a recently produced fission product associated with plant operation.

Required lower limits of detection were met and Cs-137 activity was not detected in samples obtained at the control location.

Activity due to plant operation was not evident in shoreline sediment samples during 2003 and no unusual trends were noted.

D. Ingestion Pathway (1) Milk Milk was not collected during the sample year since no indicator locations within five miles of the plant were identified during the Land Use Census.

(2) Fish Naturally occurring K-40 activity was detected in all fish samples.

K-40 activity was also detected during pre-operational fish monitoring.

During 2003, fish were also analyzed for tritium. All fish samples taken from Wolf Creek Lake had tritium activity detected (8,670.2 pCi/kg annual mean). The detected tritium activity was attributable to plant operation.

An adult consuming 21 kilograms of fish, at the maximum measured tritium concentration for 2003 (11,620 pCi/kg), would receive a committed effective dose equivalent of 0.015 mRem.

Tritium activity was not detected in the control samples collected from JRR.

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No other radionuclides were detected in fish during the year. The ODCM required lower limits of detection were met and no unusual trends were noted.

(3) Broadleaf Vegetation Gamma analyses of broadleaf vegetation samples obtained from indicator and control locations detected naturally occurring gamma emitters Be-7 and K-40. Be-7 and K-40 activity was also detected pre-operationally.

The ODCM required lower limits of detection were met and no unusual trends were noted.

Activity attributable to plant operation was not detected.

(4) Crop Samples Gamma analysis detected naturally occurring K-40 to be present in all of the samples. K-40 activity was also detected during pre-operational crop monitoring. K-40 was the only activity detected in crop samples. The ODCM required lower limits of detection were met and no unusual trends were noted.

E. Additional Samples Collected (not required by ODCM)

(1) Bottom Sediment Naturally occurring K-40 was detected in all of the bottom sediment samples. K-40 activity was also detected during pre-operational bottom sediment monitoring.

Co-60 activity (327.2 and 358.8 pCi/kg) was detected in the samples obtained from the Wolf Creek Lake discharge cove. Co-60 activity was attributable to plant operation and has been identified in plant effluents. Co-60 activity was not detected in pre-operational environmental monitoring and was not detected in samples collected from control location JRR during 2003.

Chart 6 plots the Co-60 detected activity from the discharge cove and reflects a decreasing trend.

Cs-137 activity (237.1 and 310.2 pCi/kg) was detected in the indicator samples obtained from the Wolf Creek Lake discharge cove. A portion of this activity is due to fallout and a portion of this activity is likely plant-related since Cs-134 activity has been detected in the past. Cs-137 activity was detected in pre-operational samples, and the results for 2003 indicator bottom sediment samples were within the pre-operational range. (Cs-137 activity detected in 1981 and 1982 was in the range of 79 to 953 pCi/kg. The decay corrected range of pre-operational Cs-1 37 activity detected is approximately 47 to 572 pCi/kg.) Cs-137 activity has been identified in plant effluents. Cs-137 activity (123.6 and 143.0 pCi/kg) was also detected in the control location samples and in the sample obtained from the indicator location EEA (69.1 pCi/kg).

Chart 7 plots the Cs-137 detected activity from the discharge cove indicator location and JRR control location bottom sediment samples. The detected Cs-137 activity measured from the discharge cove location reflects a decreasing trend. The Chart 7 trend line indicates that as expected, Cs-1 37 activity detected at the JRR control location has been decreasing.

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Cs-134 activity was not detected in 2003 discharge cove bottom sediment samples; however, Chart 8 has been included to display the decreasing trend.

No other radionuclides were detected in bottom sediment samples and no unusual trends were noted.

(2) Aquatic Vegetation Naturally occurring K-40 activity was detected in samples collected in 2003. K-40 activity was also detected during pre-operational monitoring.

No other radionuclides were detected in aquatic vegetation samples and no unusual trends were noted.

(3) Terrestrial Vegetation Naturally occurring Be-7 and K-40 activity were detected in the sample obtained from the EEA sample location. No other radionuclides were detected. No unusual trends were identified.

(4) Soil Naturally occurring K-40 activity was detected in both of the soil samples. K-40 activity was also detected during pre-operational soil monitoring.

Cs-137 (153.7 and 187.9 pCi/kg) activity was detected in the soil samples. The pre-operational Cs-137 results (255 to 2,160 pCi/kg) for soil samples were decay corrected.

The decay corrected pre-operational range is approximately 167 to 1415 pCi/kg. The measured Cs-137 activity of the soil samples obtained during 2003 are within or below the decay corrected pre-operational range. Cs-137 activity was not detected in air samples collected during 2003. The measured Cs-137 activity in the soil sample was likely due to previous fallout and not to a recently produced fission product associated with plant operation.

No unusual trends were identified.

5) Deer Gamma analysis detected naturally occurring K-40 (2,708.1 pCi/kg wet) activity in the deer sample obtained from indicator location A2.1.

K-40 activity was also detected during pre-operational monitoring. K-40 was the only activity detected in the deer sample. No unusual trends were noted.

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Ill. ANNUAL LAND USE CENSUS RESULTS Summary An annual Land Use Census of rural residents within five miles of WCGS was completed during 2003. The two broadleaf vegetation locations with the highest calculated annual average D/Q rankings were GI.6-QURD1384 and Q2.35-MILA1619. AP 07B-004, Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program) specifies that an alternate location may be used to provide continued monitoring". The third-ranked garden was at location N2.38-RRDR9. Tables 4 and 5 contain the summarized results and illustrated changes.

Background

Section 5.2, Attachment A, of the ODCM procedure (AP 07B-004), directs that "a Land Use Census shall be conducted annually during the growing season to identify the nearest (1) milk animal, (2) residence, and (3) garden of greater than 500 square feet producing broadleaf vegetation in each of the 16 meteorological sections within five miles of the WCGS site" and uthe results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report."

Table 5-1, Attachment A, of the ODCM (AP 07B-004) requires that broadleaf vegetation samples be collected from two indicator locations with the highest calculated annual average D/Q.

Table 5-1, Attachment A, of the ODCM (AP 07B-004) also requires that milk samples be collected from three indicator locations within five miles of the site having the highest dose potential.

Methodology One hundred eighty-five surveys were mailed to the rural residents living within five miles of WCGS. A follow-up mailing was sent to residents who did not respond. The survey excluded the residents of New Strawn, Burlington and a trailer park just north of Burlington. These locations were excluded due to the large number of households and the low likelihood that information gained from these residences would affect the locations chosen for REMP sampling. Drive-by information was collected for the nearest residences that did not return surveys.

Results The information collected was compiled and the results are identified in Table 4. Calculations were performed so that garden locations could be ranked by their respective D/Q. These results are contained in Table 5. It should be noted that relative depositions were recently updated by Engineering (Calculation AN-03-027), which likely contributed to some of the changes in the garden D/Q rankings.

Table 4 reflects the nearest residences, milk animals and broadleaf gardens. Table 5 lists the changes as compared to the 2002 Land Use Census results for milk animals and gardens producing broadleaf vegetation.

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Sector Q was the only sector that experienced a change in the nearest residence. There were no changes regarding milk locations. Again, no locations were identified that produced milk for human consumption.

Nine location changes were noted for the nearest garden producing broadleaf vegetation.

IV. PROGRAM REVISIONS/CHANGES A TLD control sample location (location 48) was established in Harris, Kansas. The location was added to provide TLD results at the control air sample location (location 48).

A broadleaf vegetation control sample location (location D-2) was added to the program to allow for an alternate control sample location.

The surface water control location was changed from MUSH to JRR. This change was made for safety reasons and to reduce sample turbidity. Prior to the change, surface water samples were obtained from both locations for six months and the results were compared. Radioactivity was not detected from either sample location. Based upon the comparison, the change would not significantly impact the REMP.

Based upon the results of the 2002 Land Use Census and cooperator participation, the following broadleaf vegetation garden changes for indicator locations were made during 2003:

Garden locations A-2 and L-A were deleted from the program

• Garden locations H-1 and N-I were added to the program Due to sample unavailability, ground water indicator sample location D-65 was deleted from the program. Ground water indicator sample location J-1 was added to the program.

V. PROGRAM DEVIATIONS During 2003, no deviations from the AP 07B-004, Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program) sampling schedule occurred.

VI. INTERLABORATORY COMPARISON PROGRAM RESULTS During 2003, Environmental, Inc. was contracted to perform radiological analysis of environmental samples for WCNOC.

The lab participated in the Environmental Resource Associates (ERA) Proficiency Testing Program. Appendix A is the Interlaboratory Comparison Program Results for Environmental, Inc. TLD intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also contained in Appendix A.

Table 6 is a summary of statistical results of performance testing of TLDs processed at Enrico Fermi 2 by Detroit Edison, which participated in the National Voluntary Laboratory Accreditation Program.

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VII. COMPARISON TO THE RADIOACTIVE EFFLUENTS RELEASE PROGRAM As described in the sections discussing radioisotopes found in the surface water from Wolf Creek Lake, dose that may be received as a result of tritium released from WCGS is consistent with the theoretical doses calculated by the Radioactive Effluent Release Program.

Chart 9 indicates that the dose to a man resulting from drinking surface water from Wolf Creek Lake was within a reasonable expected value. Dose for the surface water was determined using the December tritium activity detected for each calendar year at the discharge cove.

Released tritium maximum organ dose (mRem) values were obtained from Annual Radioactive Effluent Release Reports and are not cumulative (i.e., the values reflected are the totals for the respective years).

An adult drinking 2 liters per day of surface water collected from the Wolf Creek Lake discharge cove, using the 2003 December detected tritium activity from the discharge cove (16,699 pCi/liter), would receive a committed effective dose equivalent of 0.762 mRem per year. This information was derived from radiological environmental monitoring.

The maximum organ dose for tritium released in liquid effluents in 2003 was 0.211 mRem. This information was obtained from the Annual Radioactive Effluent Release Report.

The tritium dose values are being compared on a qualitative basis. It is not expected that the annual doses, as calculated in the Annual Radioactive Effluent Release Report, would compare directly to those calculated from the REMP. The Annual Radioactive Effluent Release Report provides a 'snap shot' of potential dose resulting from the year's releases. The REMP data indicate the accumulated result of releasing tritium into the cooling lake since the start of plant operation.

VIII. SUPPLIER QUALITY AUDITS OR SURVEILLANCES Audit 18558 was conducted April 8 to April 11, 2003 on Environmental, Inc. No findings were generated as a result of the audit.

Surveillance 4924-SO01 was conducted July 18 to July 19, 2003 on the Fermi 2 dosimetry lab.

No findings were generated as a result of the surveillance.

2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 12 of 37

TABLE 1 2003 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DESCRIPTION (SAMPLE COLLECTION SPECIFIED BY ODCM)

EXPOSURE PATHWAY/

SAMPLE TYPE NUMBER OF SAMPLES AND SAMPLE LOCATIONS SAMPLE COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS AIRBORNE (See Figures 1 & 5)

Radioiodine and Particulates Samples from five locations Continuous sampler operation with sample collection weekly, or more frequently if required, by dust loading.

Samples from locations near the site boundary in three sectors having the highest calculated annual average D/Q (Locations 2, 18 and 37 on Figure 1)

Analyze radioiodine canister weekly for 1-131 Analyze particulate filter weekly for gross beta activity; perform quarterly gamma isotopic analysis composite (by location)

Sample from the vicinity of a community having the highest calculated annual average DIQ (Location 32 on Figure 1, New Strawn)

Sample from a control location 9.5 to 18.5 miles distant in the lowest ranked D/Q sector (Location 48 on Figure 5) 2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 13 of 37

TABLE I (Cont.)

EXPOSURE PATHWAY/

SAMPLE TYPE NUMBER OF SAMPLES AND SAMPLE LOCATIONS SAMPLE COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS DIRECT RADIATION (See Figures 2 & 5) 40 routine monitoring stations with two or more dosimeters measuring dose continuously, placed as follows:

Quarterly Gamma dose quarterly An inner ring of stations, one in each meteorological sector 0-3 mile range from the site (Locations 1, 7-9, 11-13, 18, 26, 27, 29-31, 37, 38 and 47 on Figure 2).

An outer ring of stations, one in each meteorological sector in the 3-5 mile range from the site (Locations 4-6, 15-17, 19-25, and 33-36 on Figure 2). Five sectors [A, C, D, G, and L] contain an additional station (Locations 2, 3, 10, 14 and 28).

The balance of the stations to be placed in special interest areas such as population centers (Locations 23 and 32), nearby residences 2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 14 of 37

TABLE I (Cont.)

EXPOSURE PATHWAY/

SAMPLE TYPE NUMBER OF SAMPLES AND SAMPLE LOCATIONS SAMPLE COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS DIRECT RADIATION (cont.)

r S

C r

S e

WATERBORNE C

many locations are iear a residence),

schools (Location 23),

and in two or three areas to serve as

ontrol stations 10-20 niles distant from the ite (Locations 39, 40 and 48 on Figure 5).

See Figure 3)

Surface Ground One sample upstream (Location JRR on Figure 3) and one sample downstream (Location DC on Figure 3).

Samples from one or two sources only if likely to be affected.

Monthly grab sample Quarterly grab sample Monthly gamma isotopic analysis and composite for tritium analysis quarterly Quarterly gamma isotopic and tritium analysis Indicator samples at locations hydrologically down gradient of the site (Locations C-10, C-49 and J-1 on Figure 3); control sample at a location hydrologically up gradient of the site (Location B-12 on Figure 3).

2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 15 of 37

TABLE 1 (Cont.)

EXPOSURE PATHWAY/

SAMPLE TYPE NUMBER OF SAMPLES AND SAMPLE LOCATIONS SAMPLE COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS WATERBORNE (cont.)

Drinking Shoreline Sediment Sample of municipal water supply at an indicator location downstream of the site (Location LW-40 on Figure 5); control sample from location upstream of the site (Location BW-1 5 on Figure 3).

One sample from the vicinity of Wolf Creek Lake discharge cove (Location DC on Figure 3); control sample from John Redmond Reservoir (Location JRR on Figure 3).

Monthly Composite Semiannually Monthly gamma isotopic analysis and gross beta analysis of composite sample. Quarterly tritium analysis of composites.

Semiannual gamma isotopic analysis INGESTION (See Figures 4 & 5)

Milk Samples from milking animals at three indicator locations within 5 miles of the site having the highest dose potential (currently there are no locations producing milk for human consumption within 5 miles of the site); one sample from a control location greater than 10 miles from the site if indicator locations are sampled.

Semimonthly April to November; monthly December-March Gamma isotopic analysis and 1-131 analysis of each sample 2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 16 of 37

TABLE 1 (Cont.)

EXPOSURE PATHWAY/

SAMPLE TYPE NUMBER OF SAMPLES AND SAMPLE LOCATIONS SAMPLE COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS INGESTION (cont.)

Fish Indicator samples of 1 to 3 recreationally important species from Wolf Creek Lake; control samples of similar species from John Redmond Reservoir spillway (Figure 4).

Semiannually Gamma isotopic analysis on edible portions Broadleaf Vegetation Irrigated Crops Samples of available broadleaf vegetation from two indicator locations (using the criteria from the "Land Use Census" section) with highest calculated annual average D/Q (Locations G-1 and N-1 and alternate location H-1 on Figure 4);

sample of similar broadleaf vegetation from a control location 9.5 to 18.5 miles distant in the lowest ranked D/Q sector (Location D-1 and alternate location D-2 on Figure 5).

Sample of crops irrigated with water from the Neosho River downstream of the Neosho River - Wolf Creek confluence (Location NR-D1 and NR-D2 on Figure 5).

Monthly when available At time of harvest Gamma isotopic analysis on edible portions Gamma isotopic analysis on edible portions 2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 17 of 37

TABLE 2 SAMPLE LOCATION NUMBERS, DISTANCES (Miles) AND DIRECTIONS Location Distance/

Location Distance/

Location Number Distance/

Number Direction Number Direction Direction Air Particulates and Radioiodine 2

2.7/N 18 3.0/SSE 32 3.1/WNW 37 2.0/NNW 40 15.4IWNW 48 14.7/ENE TLDs I

1.4/N 17 3.7/SE 33 3.6/WNW 2

2.7/N 18 3.0/SSE 34 4.0/NW 3

3.1/NE 19 3.9/SSE 35 4.6/NNW 4

4.1/NNE 20 3.3/S 36 4.2/N 5

4.1/NE 21 3.8/S 37 2.0/NNW 6

4.6/ENE 22 3.9/SSW 38 1.2/NW 7

2.1/NE 23 4.3/SW 39 13.1/N 8

1.7/NNE 24 4.1/WSW 40 15.4/WNW 9

2.0/ENE 25 3.4/W 41 0.8/NNW 10 2.4/ENE 26 2.4/WSW 42 0.8/SSE 11 1.7/E 27 2.2/SW 43 0.7/WNW 12 1.9/ESE 28 2.6/SW 44 3.0/NNW 13 1.6/SE 29 2.7/SSW 46 1.6/WNW 14 2.5/SE 30 2.5/W 47 0.16/S 15 4.6/ESE 31 3.0/WNW 48 14.7/ENE 16 4.3/E 32 3.1/WNW 49 0.8/NNE Ground water Drinking water Surface water B-12 1.9/NNE BW-15 3.9/SW DC 0.6/WNW C-10 2.7/WSW LW-40 11.3/SSE JRR 3.7/W C-49/L-49 2.8/SW NF-DW 17.5/SSE MUSH 3.6/W D-65 3.9/S SP 3.2/SSE J-1 3.8/S Deer Broadleaf vegetation Crops A2.1 2.1/N D-1 14.7/ENE NR-D1 8.9/S Terrestrial Vegetation G-1 1.6/SE NR-D2 11.5/S EEA 3.0/NNW H-1 3.3/SSE NR-U1 4.0/SSW N-1 2.4/W l S-4 15.4/WNW Fish Shoreline Sediment Aquatic Vegetation WCL 0.6/WNW DC 0.8/WNW EEA 3.0/NNW JRR 3.7/W EEA 3.0/NNW Bottom Sediment JRR 3.6/W DC 0.9/WNW Soil MUDS 1.51WNW EEA 3.0/NNW EEA 3.0/NNW JRR 3.7/W MUDS 1.5/WNW MUDS 1.5/WNW 2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 18 of 37

TABLE 3 TLD Results (mRI90-day atr.)

Location Qtr. 1 Qtr. 1 2-Qtr. 2 Qtr. 2 2-Qtr. 3 Qtr. 3 2-Qtr. 4 Qtr. 4 2-90-Day std. dev. 90-Day std. dev. 90-Day std. dev. 90-Day std. dev.

Avg.

Avg.

Avg.

Avg.

1 2

3 4

5 6

7 8

9 10 31 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 46 47 48 49 23.4 20.6 21.9 23.4 19.3 19.8 19.9 21.5 19.1 21.1 22.0 20.8 22.5 21.5 22.9 21.2 21.8 20.3 22.4 21.0 18.5 21.4 20.6 21.0 20.9 22.0 21.0 19.6 20.1 21.6 21.1 19.2 24.0 23.1 22.2 21.5 22.3 23.1 20.0 19.7 22.3 15.5 16.5 21.3 22.0 23.1 20.2 2.5 1.3 1.3 1.5 1.4 1.1 1.1 1.4 1.2 1.4 2.2 0.6 1.0 1.2 4.2 1.3 1.4 1.4 1.9 1.1 1.4 1.9 1.2 1.1 2.6 3.2 1.2 1.4 2.9 1.0 1.8 1.0 4.9 2.1 1.3 3.4 1.8 2.4 1.5 2.5 3.6 1.5 4.2 1.9 3.9 1.4 1.7 21.4 20.5 19.8 20.2 20.1 19.9 20.1 22.9 18.8 20.6 21.6 20.2 21.2 20.5 20.1 19.8 19.2 19.3 21.1 19.7 17.9 21.4 20.3 19.8 18.7 18.8 19.3 16.8 15.9 20.3 18.5 18.7 20.0 20.9 20.6 20.6 19.1 20.8 18.9 17.0 20.5 16.2 13.9 21.5 18.5 20.0 18.8 1.3 1.3 1.1 0.7 2.7 2.0 1.0 1.0 1.4 2.0 0.6 1.6 0.6 0.8 0.7 1.4 1.2 1.2 1.4 0.6 0.9 1.8 0.9 1.3 1.6 1.1 1.8 1.5 0.5 0.6 0.6 0.9 1.0 1.1 1.1 1.6 1.3 0.8 1.9 0.7 1.0 3.5 0.9 4.1 1.8 1.6 1.0 20.6 16.9 17.4 17.8 16.7 16.0 16.7 17.9 16.4 17.6 19.9 17.8 18.7 17.8 17.7 16.4 17.0 17.2 18.4 18.1 14.9 20.6 17.5 17.4 16.8 16.1 17.8 15.2 14.4 18.7 16.9 16.4 18.2 18.5 18.0 18.5 17.2 19.4 17.2 14.6 18.3 13.1 11.4 19.8 18.6 18.4 16.5 2.8 0.9 1.1 0.8 1.6 1.4 0.7 1.4 0.4 0.9 2.7 1.2 1.3 1.0 1.6 0.8 0.6 1.7 1.9 0.8 1.3 0.8 1.9 1.5 3.2 0.4 0.9 1.0 1.9 1.8 1.5 1.1 0.9 1.2 1.1 1.8 1.1 1.6 1.4 0.9 1.1 1.3 0.8 2.9 0.8 1.8 0.7 21.0 19.7 20.6 20.4 18.9 19.0 19.2 21.1 18.1 20.9 22.0 20.5 20.9 20.9 19.9 19.3 21.7 21.6 22.5 20.6 18.3 22.4 20.8 20.6 17.8 18.6 20.4 17.9 17.0 20.5 19.9 21.0 21.2 22.4 20.8 20.1 18.8 20.7 19.1 18.7 21.3 14.4 13.7 19.9 19.8 22.6 18.7 15.9 0.7 1.3 1.3 0.9 1.3 0.9 0.8 1.3 1.0 1.4 1.3 1.2 0.8 1.1 1.2 1.0 3.4 3.0 0.8 1.4 2.1 1.0 2.1 1.3 1.4 1.1 1.2 1.2 0.9 1.1 1.1 3.6 1.6 2.8 1.7 1.6 1.2 1.2 0.8 1.2 1.5 0.5 0.8 1.6 1.4 1.6 1.0 1.3 2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 19 of 37

TABLE 3 (Cont.)

TLD Results Total Annual Exposure (mR)

Location I mR 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 46 47 48 86.4 77.7 79.7 81.8 75.0 74.7 75.9 83.4 72.4 80.2 85.5 79.3 83.3 80.7 80.6 76.7 79.7 78.4 84.4 79.4 69.6 85.8 79.2 78.8 74.2 75.5 78.5 69.5 67.4 81.1 76.4 75.3 83.4 84.9 81.6 80.7 77.4 84.0 75.2 70.0 82.4 59.2 55.5 82.5 78.9 84.1 74.2 2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 20 of 37

TABLE 4 2003 Land Use Census Data Location of Nearest:

[ Sector l Residence l

Milking Animals Broadleaf Garden A

A2.60-17TE1520 None None B

B3.53-QURD1755 None None C

C1.92-16RD1655 None C1.92-16RD1655 D

D2.03-QULA1571 None D3.00-16RD1829 E

E1.77-QULA1485 None None F

Fl.57-14RD1711 None F2.44-RERD1391 G

GI.56-QURD1384 None Gl.56-QURD1384 H

H3.09-12RD1711 None H3.30-QURD1175 J

J3.70-11RD1540 None J3.84-11RD1499 K

K2.70-12LA1439 None K4.10-NARD1120 L

L2.10-NARD1339 None L2.39-NARD1309 M

M2.47-14RD1322 None M2.49-14RD1321 N

N1.71-NARD1441 None N2.38-RRDR9 P

P2.76-HW751534 None P4.90-DEST342 Q

Q2.35-MILA1 619 None Q2.35-MILA1619 R

R2.08-NALN1650 None None Locations are identified based upon the following protocol:

EXAMPLE:

A1.40-16RD1525 First letter is based upon sector, thus "A" designates this residence is in sector A.

The number immediately following the first letter designates the distance (in miles) from the reactor.

The characters following the dash represent a unique identifier based upon location address.

The example is in sector A, 1.40 miles from the reactor, at 1525 16th Road.

2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 21 of 37

TABLE 5 Comparison of 2002 and 2003 Land Use Census Milk and Garden Data 2002 CLOSEST 2003 CLOSEST 2002 2003 GARDEN GARDEN D/Q SECTOR MILKING MILKING PRODUCING PRODUCING RANKING ANIMALS ANIMALS BROADLEAF BROADLEAF VEGETATION VEGETATION A

None None A4.91-OXRD1940 None B

None None B3.53-QURD1755 None C

None None C3.58-RERD1675 C1.92-16RD1655 4

D None None D3.10-16RD1829 D3.00-16RD1829 11 E

None None E4.40-TRRD1551 None F

None None F2.44-RERD1391 F2.44-RERD1391 8

G None None G1.56-QURD1384 G1.56-QURD1384 1

H None None H3.30-QURD1175 H3.30-QURD1175 6

J None None J3.80-11RD1535 J3.84-11RD1499 9

K None None K4.1-NARD1120 K4.10-NARD1120 10 L

None None L2.83-NARD1250 L2.39-NARD1309 5

M None None M3.00-13LA1290 M2.49-14RD1321 7

N None None N2.38-RRDR9 N2.38-RRDR9 3

P None None P4.70-KARD1675 P4.90-DEST342 12 Q

None None None Q2.35-MILA1619 2

R None None None None NOTE: Entries underlined indicate changes from the 2002 Land Use Census.

2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 22 of 37

TABLE 6 Dosimetry Performance Testing Results NATIONAL VOLUNTARY LABORATORY ACCREDITATION PROGRAM PERSONNEL DOSIMETRY PERFORMANCE TESTING

SUMMARY

OF STATISTICAL RESULTS PROCESSOR NAME:

DETROIT EDISON COMPANY PROCESSOR CODE:

100529 B DOSIMETER DESCRIPTION:

PANASONIC UD-802AS/ISA 820 TEST RESULTS FOR QUARTER:

200204 TESTING STATUS:

RENEWAL TYPE OF DOSIMETER:

WHOLE BODY REPORT PRINTED:

16 January 2003 SHALLOW DEPTH DEEP DEPTH CATEGORY B

S IBI+S L

I B

S IBI+S L

IA IB IC IIA IIB IIC lID IIIA IIIB IIIC IVA IVB IVC V

VI-TOTAL VI-NEUTRON NOT TESTED NOT TESTED NOT TESTED

-0.076 0.053 0.129 NOT TESTED NOT TESTED NOT TESTED

-0.027 0.090 0.117 NOT TESTED NOT TESTED 0.011 0.056 0.067 NOT TESTED NOT TESTED

-0.044 0.107 0.151 NOT TESTED NOT TESTED 0.40 0.40 0.40 0.40

-0.006 0.046 0.052 NOT TESTED NOT TESTED

-0.048 0.082 0.130 NOT TESTED NOT TESTED NOT TESTED NOT TESTED NOT TESTED NOT TESTED 0.017 0.081 0.098 NOT TESTED NOT TESTED 0.002 0.148 0.149

-0.033 0.041 0.074 0.016 0.181 0.197 0.30 0.40 0.40 0.40 0.40 0.40 B = Bias S = Standard Deviation L = Limit The laboratory successfully completed ANSI N13.11(2001)/NVLAP testing in categories IA, IIA, IIIA, IVA, VA and VIC.

2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 23 of 37

FIGURE 1 AIRBORNE PATHWAY SAMPLING LOCATIONS

• =

AIRBORNE PARliCULATE AND RADIQIODINE 2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 24 of 37

FIGURE 2 DIRECT RADIATION PATHWAY SAMPLING LOCATIONS

' TLD LOCATIONS 2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 25 of 37

FIGURE 3 WATERBORNE PATHWAY SAMPLING LOCATIONS

= DRINKING WATER A = SURFACE WATER

= GROUND WATER

= SHORELINE SEDIMENT

= BOTTOM SEDIMENT V

= AQUATIC VEGETATION / ALGAE 2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 26 of 37

FIGURE 4 INGESTION A = FISH (JRR)

PATHWAY SAMPLING LOCATIONS

= BROADLEAF VEGETATION

(

= FISH (WCL)

= TERRESTRIAL VEGETATION AND SOIL

= SOIL

'I

= DEER 2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 27 of 37

FIGURE 5 A

D E

DISTANT SAMPLING LOCATIONS

• - TLD

• - DRINKING WATER

- AIRBORNE PARTICULATE & RAOIOIOOINE

• - BROADLEAF vEGETATIONC IRRIGATED CROPS 2003 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 28 of 37

CHART I 2003 Airborne Gross Beta Weekly Results 0.060 0.050 L..

a)

E 0.040 0

.0

U 0.030 0.

Q) m 0.020 co Cn 0.010 0.000 0

4 8

12 16 20 24 28 Week Number 32 36 40 44 48 52 o Location 2

• Location 18

+ Location 32 A Location 37

-I Location 40 (Discontinued sampling on 10-01-03)

• Location 48 2003 Annual Radiological Environmental Operating Report - Wolf Creek Generating Station Page 29of 37

CHART 2 Historical Airborne Smoothed (Avg of 20) Indicator and Control Gross Beta 0.060

°

° ° N

° 9b zN DN\\

[V\\

o f\\ ox N

<:\\° z6\\ AN zN\\

5N\\° zN N° I\\°I Smoothed Avg. Control Location (40) - - - Smoothed Avg. Indicator Locations 1~

Smoothed Avg. Control Location (48) 2003 Annual Radiological Environmental Operating Report - Wolf Creek Generating Station Page 30 of 37

CHART 3 TLD Nearsite Locations and Control Locations 22.0 20.0 18.0 E

16.0 14.0 I

I I

I II 12.0 1 9 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 o

Avg. of Nearsite Locations

& Avg. of Control Locations Moving Avg. of Nearsite Locations

- - - Moving Avg. of Control Locations 2003 Annual Radiological Environmental Operating Report -Wolf Creek Generating Station Page 31 of 37

CHART 4 Wolf Creek Lake Surface Water Smoothed Tritium Data 17000 15000 13000 L._

a) 00.

11000 9000 7000 5000 3000 v

V I' 1~~ z~

6_

_i

_~ _Z,~

~Z

_ZZZ QQ cN Smoothed DC (avg of 10)

-Logarithmic Trendline 2003 Annual Radiological Environmental Operating Report - Wolf Creek Generating Station Page 32 of 37

CHART 5 Drinking Water Gross Beta, Historical 50 40 Occurred coincident to the sample deviation described in 1990 Annual Report ci) 0 CL 0

V)2D 30 20 10 0

l R
0 9P

CPI SP sc
' s4k & 50-b, 'A 'A s:P (,:p CP RF
sz
RPI S9 S
5 "q,

N(:b Nq q

CP CP N(:b N(:b Ncb (P-x t

t-
Xv

'N,

'0 b A

\\

"
\\

0

'b,

4 I-,N\\
b\\

\\

NZ\\) d)\\ e e

e e

e e

e I---- BW15 (Control)

LW40 (Indicator) I 2003 Annual Radiological Environmental Operating Report - Wolf Creek Generating Station Page 33 of 37

CHART 6 Detected Co-60 Activity in WCL Discharge Cove Bottom Sediment 2500 2000

• 0 C-)

1500 1000 500 0

CO C

C O

O C SO0

)SI0SO)0

)

0SO)SO0) 0 )

0 ) 0 ) 0M0) 0 )

0 )

SO0SO) 0 0 0 0 0 O

0'-

0

-0 V-

-0

0.

Q 0

'0 C'-0 '

0 CD0 '

0 0

a-0 I-4-+-Co-60 -Polynomnial Trendline 2003 Annual Radiological Environmental Operating Report - Wolf Creek Generating StationPae3of7 Page 34 of 37

CHART 7 Detected Cs-137 Activity in Bottom Sediment 1000-900 -

800 -

700 600

-0 U

,)

500 I

00-N 0.

400 200 -

/

100 -

r 0)0)00))0)000O o

OC

)a)0a)a)0a)0CD0)0a)0c

)0a)0a)0 o0o000o0o0 aM M

aM C)

C)

C)

C) 0 oza

)a

)a ua w

)c

)a C-o CD M

CO M--

-o

-o Q

Q Q

Q

-o Q

0 DC Cs-037 00 C1 (00) n omi) Td

( a) 0

--- )

P) 0 (JR I*DC Cs-i137 s

JRR Cs-137 -Polynomial Trendline (DC).......Polynomial Trendline (JRR) 2003 Annual Radiological Environmental Operating Report - Wolf Creek Generating Station Page 35 of 37

CHART 8 Detected Cs-I 34 Activity in WCL Discharge Cove Bottom Sediment 400 350 300 250 200 0

C-150 100 50 !

I I

I I

I I

5P\\

N S

5 C

K Detected Cs-1 34 -Polynomial Trendlinel 2003 Annual Radiological Environmental Operating Report - Wolf Creek Generating Station Page 36 of 37

CHART 9 Tritium Dose in WCL Surface Water and Released Liquid Tritium Maximum Organ Dose 0.800 -

0.700 l-REMP DOSE (SURFACE WATER) l MAX ORGAN DOSE (RELEASED) 0.600 E 0.500 YEA w

O 0.400 0

Z 0.300 - -

z 0.200 -

0.100, 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 20(

YEAR

)1 2002 2003 2003 Annual Radiological Environmental Operating Report -Wolf Creek Generating Station Page 37 of 37

Environmental, hIc.

Mdwest Laboratory I

an NJehtery Technologes Co.

7O L f~a.tfbaj 7COLaldwetroad *-Nobncklo 4SOO25Z (1 47) 540700 tax (847) 54-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE:

Environmental Inc., Midwest Labo ratory 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, 2003 through December, 2003

Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory, formerly Teledyne Brown Engineering Environmental Services.

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 were obtained for Thermoluminescent Dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2. Results of internal laboratory testing is also listed.

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. request.

Table A-5 list results of the in-house Oduplicate' 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.

The results in Table A-7 were obtained through participation in the Environmental Measurement Laboratory Quality Assessment Program.

Attachment A lists acceptance criteria for 'spiked" samples.

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

-Al

0 Analys Gamm Stronti Stronti Potasc Gross Attachment A ACCEPTANCE CRITERIA FOR MSPIKED' SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One standard deviation

is Level for single determination la Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter

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

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

> 30 pCi/liter or kg 10% of known value 3ium-40

> 0.1 g/liter or kg 5% of known value alpha 20 pCi/liter 5.0 pCi/liter

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

> 100 pCi/liter 5% of known value I

4,000 pCi/liter 1s =(pCi/liter) =

169.85 x (known)00933

> 4,000 pCi/liter 10% of known value m-226,-228 0.1 pCi/liter 15% of known value lium 0.1 pCiiter, gram, or sample 10% of known value

-131, 55 pCi/liter 6.0 pCi/liter ie-129b

> 55 pCi/liter 10% of known value im-238, 35 pCi/liter 6.0 pCi/liter

.el-63b

> 35 pCilliter.

15% of known value Gross Tritiuri Radiui Pluton Iodine Iodir Uranit Nick Techi Iron-5 ietiUM.99b 50 to 100 pCi/liter

> 100 pCi/liter 10 pCi/liter 10% of known value Othersb 20% of known value a From EPA publication. Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year. 1981-1982, EPA-60014-81-004.

b Laboratory limit.

A2

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

Concentration (pCVL)

Lab Code Date Analysis Laboratory ERA Control Resultb Result' Limits STW-973 STW-973 STW-974 STW-974 STW-974 STW-974 STW-974 STW-975' STW-975 STW-976 STW-976 S1W-976 02/17/03 02/17/03 02/17/03 02117/03

.02/17/03 02/17/03

• 02117103 1 02/17/03 02/17/03 02/17/03 02117/03 02/17/03 Sr-89 Sr-90

• Ba-133

-Co-60.

Cs-1 34 Cs-137 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium 17.0

• 0.5 8.9* 0.3.

14.5

• 0.9 37.5

• 0.9g 18.2

• 0.6 42.7

• 1.0 56.8

• 2.2 18.4 *0.3 11.7 *0.5 4.1

• 0.1 7.6

• 0.5 52.9

• 1.9 15.9 i 5.0 9.0 +/- 5.0 19.5 +/-5.0 37.4 +/- 5.0 17.8 +/- 5.0 44.2 +/- 5.0 60.3 +/- 6.0 37.6 +/- 9.4 8.6 +/- 5.0 4.7 +/- 0.7 6.5 +/- 1.6 53.7 +/- 5.4 7.2 - 24.6 0.4 - 17.7 10.8 - 28.2 28.7 - 46.1

• 9.1 - 26.5 35.5 - 52.9 49.9 - 70.7 21.3 - 53.9

• 0.0 - 17.2 3.5 - 6.0 3.7 - 9.3 44.4 - 63.0.

STW-983 STW-984 STW-985 STW-985 STW-985 STW-985 STW-986 STW-986 STW-986 STW-986 STW-986 STW-986-STW-988 STW-988 STW-988 STW-989 STW-989 STW-989 STW-989 STW-989 STW-990 STW-990 S1W-991 STW-991 05/19/03 05119103 05/19/03 05/19103 05/19103 05119/03 05/19103 05/19/03 05/19/03 05/19/03 05/19/03 05/19/03 08/18/03 08/18103 08/18/03 08/18/03 08/18/03 08/18103 08/18/03 08/18/03 08118103 08/18/03 08118103 08/18/03 H-3 1-131 Gr. Alpha Ra-226 Ra-228 Uranium Co-60 Cs-I 34 Cs-137 Gr. Beta Sr-89 Sr-90 Ra-226 Ra-228.

Uranium Ba-133 Co-60 Cs-1 34 Cs-137 Zn-65 Gr. Alpha Gr. Beta Sr-89 Sr-90 1290.0

• 25.0 19.7 +/-1.3 54.4

• 3.0 14.9 +/- 0.2 13.1

• 0.6 14.5* 0.4

.56.9 +/- 8.6 61.6 +/- 6.6 143.0

• 1.2 309.0

• 2.7-33.1

• 0.2' 28.8

• 1.3 13.3 *1.1 11.5

• 1.0 12.3 *0.4 18.1 +/-1.9 35.9 1.3 32.6

• 1.8 48.3 *0.6 58.9

• 2.1 41.8 +/-3.4 51.3 *3.0 57.2

• 4.3 21.2 *0.9 1250.0 +/- 331.0 20.8 +/-3.0

-70.3 +/- 17.6 16.5 +/-2.5 10.3 *2.6 15.1 +/-3.0 63.8 +/- 5.0 75.7 +/- 5.0 150.0 +/- 7.5 363.0 +/- 54.5 31.3 +/- 5.0 27.4 +/- 5.0 13.4 +/- 2.0 12.5 +/- 3.1 11.4 *3.0 20.7 +/- 5.0 37.4

• 5.0 32.6 +/- 5.0 44.3 +/- 5.0 60.2 +/- 6.0 56.2 +/- 16.3 31.6 +/- 5.0 58.8 +/- 5.0 20.6 +/- 5.0 678.0 - 1820.0 15.6 - 26.0 39.9 - 101.0 12.2 - 20.8 5.8 -14.8 9.9 - 20.3 55.1 - 72.5 67.0 - 84.4 137.0 - 163.0 269.0 - 457.0 22.6 -40.0 18.7 - 36.1

.9.9 - 16.9 7.1 - 17.9 6.2 - 16.6 12.0 - 29.4 28.7 - 46.1 23.9 - 41.3 35.6 - 53.0 49.8 - 70.6 36.9 - 93.3 22.9 - 40.3

.50.1 - 67.5 11.9 - 29.3 Al-1

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

Concentration (pCiIL)

Lab Code Date Analysis Laboratory ERA Control Resultk Resulte Limits STW-997 11/18/03 Gr. Alpha 37.0 +/- 2.0 29.5 +/-7.4 16.7 -42.3 STW-997 '11/18/03 Gr. Beta' 26.5 +/-0.8 26.3 +/-5.0 17.6 -35.0 STW-998 11/18/03 1-131 14.8 +/-0.3 16.5 +/-3.0 11.3 -21.7 STW-999 11/18/03 Ra-226 17.2 +/-1.1 17.8 +/-2.7 13.2 -22.4 STW-999 11/18/03 Ra-228 6.6 +/- 0.3 6.8 +/-1.7 3.8 -9.7 STW-999 11/18/03 Uranium 11.7 +/- 0.3 '

11.7 +/- 3.0 6.5 - 16.9 STW-1000 11/18/03 H-3 15900.0 +/- 174.0 14300.0 +/-.1430.0 11800.0 -'16800.0 STW-1001 11/18/03 Gr. Alpha 32.9 +/- 0.3 54.2 +/-3.0 30.7 -77.7 STW-100 11/18/03 Ra-226 16.5 +/-0.9 16.1 +/-2.4 11.9 -20.3 STW-1001 11/18/03 Ra-228 6.2 +/-0.5 5.5 +/-1.4 3.1 -7.9 STW-1001 11/18/03 Uranium 9.7 +/-1.5 9.3 +/- 13.6 4.1 - 14.5 STW-1002 11/18/03 Co-60 27.7 +/- 1.9 27.7 +/- 5.0 19.0 - 36.4 STW-1002'11/18/03 Cs-134 21.5+/-1.1 23.4+/-5.0 17.6-29.2 S1W-1002 11/18/03.

Cs-137 66.3 +/-*2.8 64.2 +/-5.0 55.5 -72.9 STW-1002 11/18/03 Gr. Beta 159.0 +/- 2.5 168.0 +/-5.0 124.0 -212.0 ST

6.

+/-

12

.0 1.

STW-1002 11/18/03 Sr-89 48.5 +/-0.4 50.4 +/-5.0 41.7 -59.1 STW-1002 11/18/03 Sr-90 10.1-+/- 3.0 10.2 +/- 25.2 1.5 -18.9

' Results obtained by Environmental. Inc., Midwest Laboratory as a participant in the environmental samples crosscheck program operated by Environmental Resources Associates (ERA).

b Unless otherwise Indicated, the laboratory result Is given as the mean t standard deviation for three determinations.

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

dRecount of the original sample still low. The ERA blank was spiked In the lab; known value of 20.1 pCilL, measured 21.5 +/- 1.1 pCUL No explanation for ERA test failure.

• Lower bias observed for gamma spectroscopic analysis. The undiluted sample was reanalyzed, Results of reanalysis, Co-60: 62.3 pCUL., Cs-134: 69.2 pCUL.. Cs-137: 152.3 pCUL.

'Reason for deviation unknown. A recount of the original planchets averaged 43.4 pCUL.

Cs-137activity by gamma spectroscopy; 28.3 pCfL. Result of reanalysis; 29.3 pCilL.

A1-2

TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLDs).

.mR Lab Code TLD Type Date Known Lab Result Control Description Value

+/-2 sigma Limits Environmental, Inc.

2003-1 2003-1

. 2003-2003-1 2003-1 2003-1 2003-1 2003-1 2003-1 CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards 81812003 8/8/2003 8/8/2003 818/2003 8/8/2003 8/8/2003 8/8/2003 8/8/2003 8/8/2003 Reader 1, 120 Reader 1, 150 Reader1,180 Reader1, 180 Readerl,30 Reader1,60 Reader 1, 60 Reader1,90 Reader 1,90 4.69 3.00 2.08 2.08 75.00 18.75 18.75 8.33 8.33 4.74 +/- 0.54 3.02 +/- 0.20 1.89 +/- 0.45 2.11 +/- 0.22 84.40 +/- 4.87 19.11 +/- 1.86 22.82 +/- 5.41 9.05 +/- 1.17 7.60 +/- 1.08 3.28 - 6.10 2.10 - 3.90 1.46 - 2.70 1.46 - 2.70 52.50 - 97.50 13.13'- 24.38 13.13 - 24.38 5.83 - 10.83 5.83 - 10.83 Environmental. Inc.

2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards 1112/2004 1/12/2004 1112/2004 1/12/2004 1/1212004 1/12/2004 1112/2004 1/12/2004 1/12/2004 Reader 1, 30 Reader 1, 60 Reader 1, 60 Reader 1,90 Reader., 90 Readerl, 120 Reader 1, 150 Reader 1, 150 Reader 1, 180 61.96 15.49 15.49 6.88 6.88 3.87 2.48 2.48 1.72 73.50 +/- 2.58-19.70 +/- 0.51.

16.93 +/- 1.37 8.06 +/- 0.60 6.64 +/- 0.58 4.39 +/- 0.17 2.34 +/- 0.18 2.51 +/- 0.16 2.01 +/- 0.13 43.37 - 80.55 10.84 - 20.14 10.84 - 20.14 4.82 - 8.94 4.82 - 8.94

• 2.71 -5.03 1.74 - 3.22 1.74 - 3.22 1.20 - 2.24 A2-1

TABLE A-3. In-House wSpikew Samples Concentration (pCVL)a Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=1b Activity Limits' SPW-356 W-10303 W-1 1303 W-12103 SPAP-446 SPW-468 W-20703 SPU-1347 DW-30303 SPCH-964 SPMI-1086 SPMI-1086 SPMI-1086 SPW-1088 SPW-1088 SPW-1088 SPW-1088 SPVE-1110 SPW-1194 SPW-1194 SPW-1 194 W-32103 SPCH-1429 W-40103 SPF-1407 SPF-1407 SPAP-1409 SPU-41203 SPU-41703 SPW-2022 SPW-2053 SPW-2053 SPMI-2055 SPMI-2055 W-50603 W-60303 SPW-3960 SPMI-4019 SPMI-4019 SPMI-4019' SPW-4023 SPW-4023 SPW-4023 SPW-4518 water water water water Air Filter water water Urine water Charcoal Milk Milk Milk water water water water Vegetation water water water water

'Charcoal water Fish Fish Air Filter Urine Urine water water water Milk Milk water water water Milk Milk Milk water water water water 1/212003 1/3/2003 1/13/2003 1/21/2003 1/31/2003 1/31/2003 2/7/2003 3/1/2003 3/3/2003 3/8/2003 3/13/2003 3/13/2003 3/13/2003 3/13/2003 3/13/2003 3/13/2003 3/13/2003 3/14/2003 3/21/2003 3/2112003 3/21/2003 3/21/2003 4/1/2003 4/1/2003 4/2/2003 4/2/2003 4/2/2003 4/12/2003'

.4/17/2003 4/25/2003 4/28/2003 4/28/2003 4/28/2003 4/28/2003 5/6/2003 6/3/2003 7/15/2003 7/18/2003, 7/18/2003 7/18/2003 7/18/2003 7/18/2003 7/18/2003 8/8/2003 Sr-90 Gr. Beta Gr. Beta Gr. Beta Gr. Beta H-3 Fe-55 H-3 Gr. Beta 1.131(G)

Cs-137 1-131 1-131(G)

Co-60 Cs-137 1-131 (G) 1-131 1-131 (G)

Co-60 Cs-1 37 1-131(G)

C-14 1-131 (G)

Gr. Beta Cs-134 Cs-137 Gr. Beta H-3' H-3 H-3 Cs-137 Sr-90 Cs-1 37 Sr-90 Gr. Beta Gr. Beta H-3 Cs-137 Sr-89 Sr-90 Cs-1 37 Sr-89 Sr-90 Fe-55

.34.04 +/- 1.57 63.24 +/- 1.20 59.75 +/- 1.10 61.56 +/- 1.59 1.49 +/- 0.02*

95982.00 i 865.00 9095.00 +'114.00 1724.00 +/-412.00 65.44 +/- 0.59 73.37 +/- 0.28 57.18 +/-8.03 75.13 +/- 12.01 65.81 1.06 27.16 +/-4.79 51.74 +/-9.15 68.14 +/-'i2.92 76.94 +/- 1.13 122.80 +/- 16.80 31.09 +/- 6.28.

55.11 +/- 0.13 66.17 +/- 9.15 5201.00 +/- 16.60 8.83 +/- 0.11 67.74 +/- 0.52 0.58 +/- 0.03 1.29 +/- 0.06 1.44 +/- 0.02 1798.50 +/-409.30 1625.10 +/-401.30 89007.00 +/- 798.00

, 45.70 +/- 9.44 47.51 +/- 1.87 61.65 i 7.17 38.45 +/- 1.59 70.95 +/- 0.53 63.00 +/- 0.51 88700.00 +/- 822.00 47.17 +/- 7.22 40.95 +/- 4.88 45.30 +/- 1.73 51.92 +/- 6.24 42.49 +/- 10.23 49.69 +/- 3.04 8176.00 +/- 107.00 30.93 63.90 63.90 63.99 1.52 89607.00 10587.00 1784.33 63.90 69.45 49.50 67.60 67.56 28.20 49.50 67.60 67.56 124.00 28.15 49.50 67.60 4966.00 9.18 63.39 0.59 1.32 1.51 1784.33 1784.33 88463.00 49.35 44.47 65.80 44.74 63.39 65.73 87369.00 49.11 49.49 44.24 49.11 49.49 44.24 9330.00 24.74 - 37.12 53.90 - 73.90 53.90 - 73.90 53.99 -73.99

-8.48 - 11.52 71685.60 - 107528.40 8469.60 - 12704.40 1101.27 - 2467.39 53.90 - 73.90 59A5 - 79.45 39.50 - 59.50 54.08 - 81.12 57.56 - 77.56 18.20 - 38.20

'39.50 - 59.50 57.60 - 77.60 54.05 - 81.07 111.60 - 136.40 18.15 - 38.15 39.50 - 59.50 57.60 - 77.60 2979.60 - 6952.40

-0.82 - 19.18 53.39 - 73.39 0.35 - 0.83 0.79 - 1.85

-8.49 - 11.51 1101.27 - 2467.39 1101.27 - 2467.39 70770.40 - 106155.60

'39.35 - 59.35 35.58 - 53.36 55.80 - 75.80 35.79 - 53.69 53.39 - 73.39 55.73 - 75.73

-69895.20 - 104842.80 39.11 - 59.11 39.49 - 59.49 35.39 - 53.09 39.11 - 59.11 39.49 - 59.49 35.39 - 53.09 7464.00 - 11196.00 A3-1

TABLE A-3. In-House "Spike" Samples Concentration (pCVL)

Lab Code Sample Tvpe Date Analysis Laboratory results

.2s. n=lb Known Activity Control Limitsc SPW-61 97 SPAP-3958 SPW-6401 SPAP-6403 SPF-6418 SPF-6418 SPW-6421 SPMI-7459 SPMI-7459 SPMI-7459

• SPMI-7459 S PW - 4 1 SP-7461 SPW-7461 SPW-7461 water Air Filter water Air Filter Fish Fish water Milk Milk Milk Milk water water water water 10/16w2003 10/28/2003 10128/2003 10/28/2003 10/28/2003 10/28/2003 10/28/2003 12/12/2003-12/12/2003 12/12/2003 12/12/2003 12/1212003 12/12/2003 12/12/2003 12/12/2003 Tc-99 Gr. Beta H-3 Gr. Beta Cs-134 Cs-137 Fe-55 Cs-134 Cs-137.

Sr-89 Sr-90 Cs-i 34 Cs-137 Sr-89 Sr-90 540.14 +/- 54.00 1.45 +/- 0.02 84867.00 i 826.OC 1.71 i 0.02 0.50 i 0.02 1.37 +/-0.05

.104.18 +/-1.26 41.06 +/- 2.45 48.48 +/- 4.99 55.94 +/-4.12 41.86 +/- 1.57 44.07+/- 1 A9 50.26 +/- 2.67 56.41 +/- 4.87 48A4 +/- 1.84 539.73 1.50 1

85984.00 1.49 0.49 1.30 88.18 41.88 48.64 65.80 43.80 41.88 48.64

-65.80 43.80 377.81 - 701.65

-8.50 - 11.50 68787.20 - 103180.80

-8.51 -.11.49 0.29 - 0.69 0.78 - 1.82

.68.18 - 108.18 31.88 - 51.88 38.64 - 58.64 52.64 - 78.96 35.04 - 52.56 31.88 - 51.88 38.64 - 58.64 52.64 - 78.96 35.04 - 52.56 c 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

TABLEA-4. In-House"Blank"Samples Concentration (pCVL)'

Lab Code Sample Date Analysis Laboratory results (4.66a)

Acceptance Type LLD Activityb Criteria (4.66 o)

SPW-357 W-10303 W-11303 W-12103 SPAP-447 SPW-469 W-20103 W-20703 DW-30303 SPCH-965 SPMI-1087 SPMI-1087 SPMI-1087 SPMI-1087 SPW-1089 SPW-1089 SPW-1089 SPW-1089 SPVE-1111 W-32103 SPCH-1430 W-40103 SPF-1408 SPF-1408 SPAP-1410 SPU-41203 SPU-41703 SPW-2054 SPW-2054 SPW-2054 SPMI-2056 SPMI-2056 SPMI-2056 W-50603 W-60303 SPW-3960 SPMI-4018 SPMI-4018 SPMI-4018 '

SPW-4024 SPW-4024 SPW-4519 SPW-6401 water water water water Air Filter water water water 1/2/2003 1/3/2003 1/13/2003 1/21/2003 1/31/2003 1/31/2003 2/1/2003 2[7/2003 3/3/2003 Charcoal Cani: 3/8/2003 Milk Milk Milk Milk water water water water Vegetation water 3/13/2003 3/13/2003 3/13/2003 3/13/2003 3/13/2003 3/1312003 3/13/2003 3/1312003 3/1412003 3121/2003 Charcoal Cani:4/1/2003 water Fish Fish Air Filter Urine

• Urine water water water Milk Milk Milk water water

• water Milk Milk Milk water water water water 4/1/2003 4/212003 4/2/2003 4/2/2003 4(12/2003 4/17/2003 4/28/2003 4/28/2003 412812003 4/28/2003 412812003 4/28/2003 5/6/2003 6/3/2003 7/15/2003 7/1812003 7/18/2003 7/18/2003 7/18/2003 7/18/2003 818/2003 10128/2003 Sr-90 Gr. Beta Gr. Beta Gr. Beta Gr. Beta H-3 Gr. Beta Fe-55 Gr. Beta 1-131(G)

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

Co-60 Cs-134 Cs-137 1-131 1-131(G)

C-1 4 1-131 (G)

Gr. Beta Cs-134 Cs-137 Gr. Beta H-3 H-3 Cs-1 37 Sr-89 Sr-90 Sr-90 Cs-137 11 31(G)

Gr. Beta Gr. Beta H-3 Cs-137 Sr-89 Sr-90 Sr-89 Sr-90 Fe-55 H-3 0.50 0.12 0.14 0.12 0.00 160.20 0.17 802.00 0.15 0.01 7.49 7.90 0.33 7.76 4.48 5.60 4.32 0.29 7.53 17.50 0.01 0.14 0.01 0.01 0.00 653.99 648.35 3.16 0.55 0.55 0.77 2.74 3.54 0.12 0.14 156.60 4.10 0.73 0.51 0.83 0.62 527.00 163.80 0.12 +/- 0.25 0.022 +/- 0.10 0.035 +/- 0.10 0.029 +/- 0.09

-0.0034

• 0.00 19.3 +/- 80.30 0.0 +/-0.12 149 +/- 498.00 0.007 +/- 0.11

-0.013 +/- 0.18

-0.050 +/- 0.16

-0.4 +/- 9.200

-0.11 +/- 0.100

-0.0029 +/- 0.002 542.28 f 364.780 100.1 +/-344.800 0.45 +/- 0.50 0.072 +/- 0.260 0.66 +/- 0.430 0 +/- 0.090

-0.035 +/- 0.095 53.4 +/- 80.200 0.39 +/- 0.880 0.93 +/- 0.340 0.21 +/- 0.730 0.09

• 0.300 87 +/- 369.000

-23.8 +/- 85.000 3

3.2 3.2 3.2 3.2 200 3.2 1000 3.2 9.6

- 10 10 0.5 20 10 10 10 0.5 20 200 9.6 3.2 100 100 3.2 200 200 10 5

1 1

10 20 3.2 3.2 200 10 5

II

.5 1000 200 A4-1

I TABLE A-4. In-House "Blank" Samples Concentration (pCiIL)a Lab Code Sample Date Analysis Laboratory results (4.66a)

Acceptance Type LLD Activityb Criteria (4.66 a)

SPAP-6404 Air Filter 10/28/2003 Gr. Beta 0.87

-0.99 i 0.440 3.2 SPF-6419 Fish 10/28/2003 Cs-1 34 0.01 100 SPF-6419 Fish 10/2812003 Cs-137 0.01 100 SPMI-7460 Milk

.12/1212003 Cs-134 4.52 10 SPMI-7460 Milk 12/12/2003 Cs-137 5.77 10 SPMI-7460W Milk 12112/2003 Sr-90 0.50

.1.26 i 0.370 1

aLiquid sample results are reported In pCI/Liter, air filters( pCI/filter), charcoal (pCI/charcoal canister), and solid samples (pCi/kg).

b.

b'The activity reported Is the net activity result.

c Low levels of Sr-90 are still detected in the environment. A concentration of (1-5 pCut. In milk Is not unusual.

A4-2

TABLEA-5. In-House"Duplicate'Samples Concentration (pCVL)'

Averaged Lab Code Date MI-24,25 1

.212003 MI-24,25 1/2/2003 CF-47,48 1/2/2003 CF-47,48 1/2/2003 AP-8827,8828 1/2/2003 AP-8869, 8870 112/2003 MI-119.120 1/8/2003 MI-119, 120 1/8/2003 MI-213, 214 1/14/2003 MI-213, 214 1/14/2003 MI-262,263 1/15/2003 S-696, 697 1/29/2003 S-696, 697 1/29/2003 MI-448,449 2/312003 SW-470,471 2/312003 SW-470,471 2/3/2003 SW-470,471 2/3/2003 MI-517,518 2/4/2003 MI-541, 542 2/5/2003 MI-620,-621 2/11/2003 DW-922, 923 3/4/2003 CF-1048,1049 b 3/10/2003 LW-1152, 1153 3/13/2003 F-1120,1121 3/14/2003 F-1120,1121 3/14/2003

• F-1120,1121 3/14/2003 DW-1278,1279 3/25/2003 SO-1380,1381 312512003 LW-1299, 1300 3/27/2003 LW-1320, 1321 3/27/2003 W-1403,1404 3/31/2003 AP-2019,2020 3/31/2003 MI-1422,1423 4/1/2003 MI-2170, 2171 4/1/2003 MI-1422,1423 4/2/2003 AP-1633,1634 4/2/2003 AP-1871,1872 4/212003 AP-1974, 1975 4/2/2003 LW-1828,1829 4/11/2003 S-1544,1545 4/15/2003 DW-1913,1914 4/15/2003 MI-1996,1997 4/21/2003 MI-1996,1997 4/22/2003 Analysis K-40 Sr-90 Gr. Beta K-40 Be-7 Be-7 K-40 Sr-9o K-40 Sr-90 K-40 Gr. Alpha Gr. Beta K-40 Gr. Beta K-40 (ICP)

K-40 K-40 K-40 K-40 1-131 K-40 H-3 Cs-I 37 Gr. Beta K-40 1-131 Gr. Beta Gr. Beta H-3 Sr-90 Be-7 K-40 K-40 Sr-90 Be-7

-Be-7 Be-7 Gr. Beta K-40 1-131 Sr-90 K-40 First Result Second Result Result 1362.00

• 117.00 1.45 +/- 0.40 2.72 +/- 0.10 2.61 +/-0.31 0.06 +/- 0.01 0.04 +/- 0.02 1351.90 +/- 116.10 2.22 +/- 0.43 1372.30 +/- 104.80 1.81 +/- 0.41 1399.20 +/- 200.70 24.70 +/- 4.89 22.89 +/- 2.67 1159.70 +/- 157.90 13.62 +/- 1.23 5.10

• 0.51 5.80 +/- 0.51 1437.70 +/- 125.50 1443.00 +/- 194.80 1294.70 +/- 115.10 0.67 +/- 0.16 3.09 +/- 0.12 1147.26

• 122.56 0.04 +/- 0.02 2.04 +/- 0.06 1.93 +/- 0.38 0.37 +/- 0.22 18.60 +/- 2.68

2.35 i 0.55 487.12 I 104.43 0.96 +/- 0.32 0.07 +/- 0.01 1410.00 +/- 176.00 1452.30 +/- 129.10 1.84 +/- 0.42 0.05 i 0.01 0.07 +/- 0.01 0.08 +/- 0.02 2.49 +/- 0.58 15.84 +/- 2.36 0.29 +/- 0.21 2.05 +/- 0.74 1580.20 +/- 118.90 1377.00 +/- 188.00 2.21 +/- 0.50 2.84 +/- 0.10 2.32 +/- 0.12 0.05 +/- 0.02 0.05 +/- 0.02 1234.70 +/- 108.70

.1.88 +/- 0.40 1303.80 +/- 109.10 2.29 +/- 0.45 1347.70 +/- 126.40 23.23

• 4.64 22.71 *2.73 1396.40

• 106.20 15.21 +/- 1.21 5.20 +/- 0.52 5.90 +/- 0.52 1357.70 +/- 188.00 1385.20 +/-190.10 1234.10 +/- 165.10 0.79 +/- 0.16 2.67 +/- 0.07 1094.42 +/-120.92 0.05 +/- 0.01 2.11 +/- 0.06 1.89 +/- 0.25 0.34 +/- 0.29 20.53 +/- 2.83 2.48 +/- 0.56 422.00 +/- 102.00 1.10 +/-0.42 0.08 +/-0.01 1340.00 +/- 114.00 1472.50 +/- 191.00 1.15 +/-0.39 0.06 +/-0.01 0.07 +/- 0.01 0.07 +/- 0.02 3.42 +/- 0.63 15.41 +/- 2.02 0.42 +/- 0.19 3.25+/- 0.91 1602.10 +/- 120.40 1369.50 +/- 110.72 1.83 +/- 0.32 2.i8 +/- 0.07 2.47 +/- 0.17 0.05 +/- 0.01 0.05 +/- 0.01 1293.30 i79.52 2.05 +/- 0.30 1338.05 +/- 75.64 2.05 +/- 0.31

.1373.45 +/- 118.59 23.97 +/- 3.37 22.80 +/- 1.91 1278.05 +/- 95.15 14.42 +/- 0.86.

5.15 +/- 0.36 5.85 +/- 0.36 1397.70 +/-113.02 1414.10 +/-136.09 1264.40 +/- 100.63 0.73+/- 0.11 2.88 +/- 0.07 1120.84 +/- 86.09 0.05 +/- 0.01 2.08 +/- 0.04 1.91 +/- 0.23 0.36 +/-0.18 19.57 +/- 1.95 2.42 +/- 0.39 454.56 + 72.99 1.03 +/- 0.26 0.07 +/- 0.01 1375.00 +/- 104.85 1462.40 +/- 115.27 1.50 +/- 0.29 0.06 +/- 0.01 0.07 +/- 0.01 0.08 +/- 0.01 2.96 +/- 0.43 15.63 +/-1.55 0.36 +/- 0.14 2.65 +/- 0.58 1591.15 i84.61 A5-1

TABLE A-5. In-House "Duplicate" Samples Coniceritration (pCVL)8 Averaged Lab Code Date Analysis First Result Second Result Result LW-2063, 2064 4/28/2003.

SWU-2275, 2276 4/28/2003 G-2149, 2150 4/30/2003 TD-2339, 2340 5/1/2003 SO-2381, 2382 5/1/2003 S0-2381,2382 5/11/2003.

S0-2381, 2382 5/1/2003 SO-2381, 2382 5/112003 SO-2381, 2382 5/1/2003 DW-2317, 2318 5/6/2003 BS-2595, 2596 5/6/2003 BS-2595, 2596 5/6/2003 U-2484, 2485 5/9/2003 SO-2645,2646 5/14/2003 SO-2645, 2646 5114/2003

.S0-2645,2646 5/14/2003 MI-2696, 2697 5/19/2003 MI-2696,2697 5/19/2003 SO-2787i 2788 5/28/2003 SO-2787, 2788 5128/2003 SO-2787, 2788 5/28/2003 MI-2840, 2841 5/28/2003 SWU-2864, 2865 5/28/2003 BS-2888, 2889 5/29/2003 BS-2888, 2889 5/29/2003 W-3230, 3231 5/30/2003 TD-3036,3037 6/2/2003 SL-2909. 2910 b 6/3/2003 SL-2909, 2910 6/312003 SW-3080,3081 6/10/2003 SW-3080.3081 6/10/2003 VE-3172, 3173 6/11/2003 F-3742, 3743 6/11/2003 F-3742, 3743 6/11/2003 SO-3325, 3326 6/13/2003 MI-3253, 3254 6/17/2003 MI-3297, 3298 6/17/2003 WW-3380, 3381 6/23/2003 SWT-3403, 3404 6/2412003 MI-3424, 3425 6/24/2003 SW-3862, 3863 6/24/2003 G-3479. 3480 6/25/2003 G-3479, 3480 6/25/2003 LW-3809, 3810 6/30/2003

• Gr. Beta Gr. Beta Be-7 H-3 Cs-137 Gr. Alpha Gr. Beta K40 Sr-90 1-131 Cs-137 K-40 H-3 Be-7 Cs-137 K-40 K-40 Sr-90 Cs-137 Gr. Beta K-40 K-40 Gr. Beta Cs-1 37 K-40 Gr. Beta H-3 Gr. Beta K-40

• Gr. Alpha Gr. Beta K-40 Gr. Beta K-40 Gr. Beta K-40 Sr-90 Gr. Beta Gr. Beta K-40 Gr. Beta Be-7 K-40 Gr. Beta 2.33 +/- 0.66 3.62 +/- 0.67 0.71 +/-0.19 221.00 +/- 91.00 0.11 +/-0.03 11.14 +/-5.15 35.18 +/- 4.69 18.29 +/- 0.84 0.06 +/- 0.02 1.77 +/- 0.27 0.06 +/- 0.02 13.74 +/- 0.62 512.00 +/- 100.00 1.18 b0.42 0.11 +/-0.04 16.50 +/- 1.13 1320.40 +/-.124.50 1.A9 +/- 0.47

.0.27 +/- 0.04 19.62

• 1.73 14.77 +/- 1.02 1179.50 i 167.80 3.39 +/- 0.59 0.05 +/- 0.02 9.70 +/- 0.83 4.33+/- 1.00 529.50 +/- 100.00 7.10 +/- 0.15 3.90 +/- 0.67 4.63 +/- 1.90 9.07 +/- 1.29 2.62 +/- 0.35 3.47 +/- 0.13 2.94 +/- 0.39.

20.95 +/- 1.88 1329.40 +/- 121.80 2.14 +/- 0.57 5.58 +/- 0.69 2.80 +/- 0.56 1422.80 +/- 185.40 3.66 +/- 1.18 1.52 +/- 0.25 5.02 +/- 0.45 2.12 +/- 0.76 2.68 +/- 0.60 4.60 +/- 0.71 0.69 +/- 0.20 161.00 +/- 88.00 0.10 +/- 0.02 10.39 +/- 5.60 39.66 +/- 5.24 17.83 +/- 0.84 0.10 +/- 0.02 1.47 +/- 0.26 0.06 +/- 0.02 14.10 +/- 0.73 370.00 +/- 95.00 1.21 +/-0.35 0.09 +/- 0.05 15.33 +/- 1.09 1394.10 +/- 113.00 2.01 +/-0.45 0.23 +/- 0.04 20.81 +/- 1.72 14.41 +/- 1.00 1401.70 +/- 120.20 3.41 +/- 0.64 0.07 +/- 0.04 10.17 +/- 0.87 3.28 +/- 1.22 585.50 +/- 102.00 7.60 +/- 0.16 3.49 +/- 0.52 4.47 +/- 1.71 8.98 +/- 1.28 3.17 +/- 0.58 3.71 +/- 0.14 2.70 +/- 0.40 19.97 +/- 2.01 1417.60 +/- 130.90 2.27 +/- 0.50 5.03 +/- 0.69 2.63 +/- 0.55 1216.20 +/- 170.10 3.70 +/- 1.22 1.43 +/- 0.28 5.10 i 0.48 2.39 +/- 0.72 2.51 +/- 0.45 4.11 +/- 0.49 0.70 i 0.14 191.00 +/-63.29 0.10 +/-0.02 10.77 +/- 3.80 37.42 +/- 3.52 18.06 +/- 0.59 0.08 +/- 0.01 1.62 +/- 0.19 0.06 +/- 0.02 13.92 +/- 0.48 441.00 +/- 68.97 1.19 +/- 0.27 0.10 +/- 0.03 15.91 +/- 0.79 1357.25 +/- 84.07 1.75 +/- 0.32 0.25 +/- 0.03 20.21 i 1.22 14.59 +/- 0.71 1290.60 i 103.20.

3.40 i0.43 0.06 +/-0.02 9.93 i 0.60 3.81 0.79 557.50 i 71.42 7.35 +/- 0.11 3.70 i0.42 4.55+/- i1.28 9.02 +/- 0.91 2.90 +/- 0.34 3.59 +/- 0.10 2.82 +/- 0.28 20.46 +/- 1.38 1373.50 +/- 89.40 2.21 +/- 0.38 5.31 +/- 0.49 2.72

• 0.39 1319.50 +/- 125.80 3.68 +/- 0.85 1.47 +/- 0.19 5.06

• 0.33 2.25 +/- 0.52 A5-2

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

Averaged Lab Code Date Analysis First Result Second Result Result LW-3809,3810 AP-4105, 4106 G-3572, 3573 G-3572, 3573 G-3572,3573 G-3572,3573 MI-3601,3602 MI-3601, 3602 AP-3933,3934 AP-4061,4062 AP-4147,4148 AP-4084,4085 LW-3786,3787 WW-4168, 4169 CF-3975.3976 CF-3975, 3976 Ml-4020,4021 DW-4272,4273 SWU-4461, 4462 SL4398,4399 SL-4398,4399 b SL-4398,4399 G-4419,4420 G-4419,4420 G-4419,4420 TD-4550,4551 Ml-4482, 4483 Ml-4482,4483 G-4526,4527 G-4526,4527 SWU-4609,4610 CW4694,4695 CW-4694,4695 LW-4673,4674 Ml-4735,4736 Ml-4756, 4757 VE-4832,4833 Ml-4860,4861 SO-5082, 5083 SO-5082, 5083 CW-5349, 5350 CW-5349, 5350 ME-4968, 4969 ME-4968,4969 6130/2003 6/30/2003 7/112003 7/1/2003 7/1/2003 7/11/2003 7/1/2003 7/1/2003 7/1/2003 7/2/2003 7/212003 7/3/2003 7/9/2003 7/11/2003 7/14/2003 7/14/2003 7/16/2003 7/29/2003 7/30/2003 8/4/2003 8/4/2003 8/4/2003 8/4/2003 8/4/2003 8/4/2003 8/4/2003 8/6/2003 8/6/2003 8/6/2003 8/6/2003 8/6/2003 8/6/2003

-8/6/2003 8/13/2003 8/19/2003 8/19/2003 8/20/2003 8/26/2003 8/28/2003 8/28/2003 8/31/2003 8/31/2003 9/2/2003 9/2/2003 H-3 Be-7 Be-7 Gr. Beta K-40 Sr-90 K-40 Sr-90 Be-7 Be-7 Be-7 Be-7 Gr. Beta Gr. Beta Be-7 K-40 K-40 Gr. Beta Gr. Beta Be-7 Gr. Beta K-40 Be-7 Gr. Beta K-40 H-3 K-40 Sr-90 Be-7 K-40 Gr. Beta Gr. Beta.

H-3 Gr. Beta K-40 Sr-90 K-40 K-40 Cs-137 Gr. Beta Gr. Beta H-3 Gr. Beta K-40 2814.09

• 167.99 0.07 i 0.01 0.91 i 0.24 6.35 +/- 0.15 5.44

• 0.55 0.01 i 0.00 1318.60 +/- 117.40 0.86

• 0.51 0.07

• 0.01 0.07 +/- 0.01 0.08

• 0.01 0.09

• 0.02 2.13 i 0.56 3.79

• 1.87 1.64

• 0.81 6.54

• 0.75 1350.90 *174.90 2.35 + 0.92 2.28 -* 0.44 4.55 i 1.05 3.41 i 0.12 2.47 I 0.67 3.98

• 0.63 5.38

• 0.14 4A2 t 0.66 327.30 +/- 95.10 1301.40+/-

• 115.20 0.81 +/- 0.30 1.47 *0.29 5.42

• 0.56 3.22 +/-0.63 1.48 i 0.34 22776.41 +/-428.73 2.86 6 0.65 1396.30 127.90 1.66 +/- 0.47 1.96 +/- 0.50

1312.10 +/- 191.80 0.01 i 0.00 20.02 + 1.84 1.45 +/- 0.39 24429.50

• 444.42 4.90

• 0.23 2.46 +/- OA1 2812.17 +/- 167.94 0.07 +/- 0.01 0.81

• 0.28 6.35 +/-0.15 5.68 +/- 0.28 0.02

• 0.00 1435.10 +/- 117.80

.1.74 +/- 0.60 0.07 +/- 0.01 0.08

• 0.01 0.07

• 0.01 0.08

• 0.02 2.93

• 0.62 4.48

• 1.98 1.66 +/- 0.57 6.19

• 0.50 1199.80 +/- 153.20 2.29

• 0.89 1.93 +/- 0.43 4.50 +/-1.10 3.12 *0.11 2.44

• 0.87 3.93 +/- 0.57 5.35 +/-0.16 4.32 0.74 390.20 +/- 92.10 1370.30 +/- 116.80 0.85 +/- 0.31 1.42 +/- 0.28 5.21 +/- 0.63 2.67 +/- 0.64 1.09 +/- 0.34 2183i.75 +/- 420.10 3.75 +/- 0.71 1410.10 +/- 120.20 1.53 +/- 0.44 1.43 +/- 0.47 1307.80 +/- 109.30 0.01 +/- 0.00 20.92 +/- 2.03 1.55 +/- 0.45 24744.25 +/- 447.18 5.18 i 0.24 2.68 +/- 0.37 2813:13

• 118.77 0.07 +/- 0.01 0.86 +/- 0.18 6.35 +/- 0.11 5.56

• 0.31 0.01 0.00 1376.85 +/-83.16 1.30 +/- 0.39 0.07 +/- 0.01 0.08

• 0.01 0.07

• 0.01 0.08

• 0.01 2.53 +/- 0.42 4.14 +/- 1.36 1.65 +/- 0.50 6.36 +/- 0.45 1275.35 +/- 116.25 2.32 +/- 0.64 2.10 +/- 0.31 4.53 +/- 0.76 3.27 +/- 0.08 2.46 +/- 0.55 3.96 +/- 0.42 5.37 +/- 0.11 4.37 +/- 0.50 358.75 +/- 66.19 1335.85 +/- 82.03 0.83 +/- 0.21 1.45 +/- 0.20 5.31 +/- 0.42 2.95 +/- 0.45 1.29 +/- 0.24 22304.08 + 300.12 3.30 0.48 1403.20 +/- 87.76 1.60 +/- 0.32 1.70 +/- 0.34 1309.95 +/- 110.38 0.01

• 0.00 20.47 +/- 1.37 1.50 +/- 0.30 24586.88 +/- 315.23 5.04 +/- 0.17 2.57 +/- 0.28 A5-3

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

Averaged Lab Code Date Analysis First Result

- Second Result Result DW-4989,4990 MI-5154, 5155 Ml-5154, 5155 AP-6177, 6178 SWU-5773, 5774 AP-6102, 6103 G-5631, 5632 G-5631, 5632 G-5631, 5632 SO-5660, 5661 SO-5660. 5661 SO-5660, 5661 SO-5660, 5661 SO-5660, 5661 AP-6334, 6335 AP-6363, 6364 MI-5794, 5795 MI-5838, 5839 MI-5838, 5839 BS-5938, 5939 BS-5938, 5939 SS-5959. 5960 MI-6011, 6012 MI-6034, 6035 VE-6055, 6056 VE-6055, 6056 MI-6291, 6292 MI-6291, 6292 SS-6435, 6436 SS-6435, 6436 CF-6313, 6314 SO-6528, 6529 SO-6528, 6529 SO-6393, 6394 S0-6393, 6394 SO-6393, 6394 SWT-6507, 6508 DW-6647, 6648 BS-6603, 6604 BS-6603, 6604 S0-6670, 6671 SO-6670, 6671 S-7067, 7068 Ml-6818, 6819 9/2/2003 9/8/2003 9/8/2003 9129/2003 9/30/2003 9/30/2003 10/11/2003 10/1/2003

.1011/2003 10/112003 10/1/2003 1011/2003 10/1/2003

'10/1/2003 10/1/2003 10/2/2003 10/6/2003 1018/2003 10/8/2003 10/8/2003 10/8/2003 10/1312003 10113/2003 10/1412003 10/1512003 10/15/2003 10/21/2003 10/21/2003 10/21/2003 10121/2003 10/22/2003 10122/2003 10/22/2003 10/25/2003 10/25/2003 10/25/2003 10/28/2003 10/31/2003 11/3/2003 11/3/2003 11/5/2003 11/5/2003 11/1012003 11111/2003 Gr. Beta K-40 Sr-90 Be-7 Gr. Beta Be-7 Be-7 Gr. Beta K-40 Cs-1 37 Gr. Alpha Gr. Beta K-40 Sr-90 Be-7 Be-7 Sr-90 K-40 Sr-90 Cs-137 K-40 K-40 K-40 Sr-90 Gr. Beta K-40 K-40 Sr-90 Cs-137 K-40 K-40 Cs-137 K-40 Cs-1 37 Gr. Beta K-40 Gr. Beta 1-131 Cs-137 Gr. Beta Cs-137 K-40 Cs-137 K-40 2.20 +/- 1.04 1365.50 +/- 116.70 1.19 +/-0.39 0.07 +/-0.01 2.55 +/- 0.63 0.07 +/- 0.01 1.88 +/- 0.48 5.87 +/- 0.09 5.24 +/- 0.77 0.15 *0.04 12.72 +/-3.72 32.42 +/- 3.09 18.93 +/-0.87 0.03 +/- 0.01 0.06 +/- 0.01' 0.07 +/- 0.02 1.37

• 0.37 1364.30

• 124.10 0.76 +/- 0.30 0.18 +/- 0.03 15.59 +/- 0.70 7.49 0.42 1165.20 +/- 118.70 0.86 +/- 0.33 5.18 +/- 0.18 5.31 +/- 0.57 1935.60 +/- 147.70 1.22 +/- 0.39 0.05 +/- 0.02 14.08 +/- 0.54 14.56 +/- 0.45 0.15 +/- 0.03 17.46

• 0.69 0.09 +/- 0.03 23.21 +/- 1.98 13.98 +/- 0.80 2.64 +/- 0.52 0.46 +/- 0.27 9.03 +/- 0.82 26.83 +/- 1.94 0.15 +/- 0.04 12.96

• 0.66 0.21

• 0.05 1695.50 +/- 129.80 3.19 +/- 1.14 1456.70 +/- 119.10 1.39 +/- 0.39 0.06 +/- 0.01 2.83 +/- 0.60 0.05 +/- 0.01 2.21 +/-0.40 5.85 +/- 0.08 5.26 +/- 0.58 0.16 +/- 0.05 14.86

• 3.88 33.60 +/- 3.04 18.25 +/- 1.19 0.03 +/- 0.01.

0.06 +/- 0.01 0.07 +/- 0.02 1.02 +/- 0.37 1414.40 +/- 110.40 1.00 +/- 0.34 0.20 +/- 0.05 16.69 +/- 0.80 7.29 +/- 0.63 1191.20 +/- 99.50 0.90 +/- 0.34 5.33 +/- 0.18 4.52 +/- 0.51 1936.10 +/- 116.50 1A1 +/-0.37 0.05 +/- 0.03 14.28 +/- 0.80 14.70 +/- 0.95 0.16 +/- 0.05 17.90 +/- 1.05 0.10 +/- 0.04 21.76 +/- 1.91 14.57 +/- 0.86 2.63 +/- 0.53 0.61 +/- 0.31 8.60 +/- 1.13 27.18 +/- 1.95 0.13 +/- 0.04 12.95 +/- 0.72 0.19 +/- 0.08 1709.40 +/- 143.00 2.70 +/- 0.77 1411.10 +/- 83.37 1.29 +/- 0.28 0.06 +/- 0.01 2.69 +/- 0.44 0.06 +/- 0.01 2.05 +/- 0.31 5.86 +/- 0.06 5.25 +/- 0.48 0.16

• 0.03 13.79 +/- 2.69 33.01 +/- 2.17 18.59 +/- 0.74 0.03 +/- 0.01 0.06 +/- 0.01 0.07 +/- 0.01 1.19 +/- 0.26 1389.35 +/- 83.05 0.88 +/- 0.23

.0.19 +/- 0.03 16.14 +/- 0.53 7.39 +/- 0.38 1178.20 +/- 77.44 0.88 +/- 0.24 5.25 +/- 0.13 4.92 +/- 0.38 1935.85 +/- 94.06 1.31 + 0.27 0.05 +/- 0.02 14.18 +/- 0.48 14.63 +/- 0.53 0.16 +/- 0.03 17.68 +/-0.63

.0.10 +/- 0.03 22.48 +/-1.38 14.27 +/- 0.59 2.63 +/- 0.37 0.53 +/- 0.21 8.82 +/- 0.70 27.01 +/- 1.38 0.14 +/-0.03 12.96 +/-0.49 0.20 +/- 0.05 1702.45 i 96.56 A5-4

TABLE A-5. In-House 'Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result MI-6818,6819 11/11/2003 Sr-90 2.01 *0.41 1.59 *0.39

.1.80 i0.28 WL-6987,6988 11/17i2003 Fe-55 603.49 *53.32.

619.65 *53.97 611.57 *37.93 SO-7156, 7157 11/21/2003 Cs-137 0.74 +/- 0.08 0.77 *0.07 0.76 *0.06 SO-7156,7157 11/21/2003 Gr. Alpha 14.90 +/- 4.24 19.25 +/- 4.45 17.07 +/-3.07 S0-7156,7157 11/21/2003 Gr. Beta 22.97 +/- 3.12 25.51 +/- 2.98 24.24 *2.16 SO-7156, 7157 11/21/2003 K-40 12.51 i1.06 12.94 *1.07 12.73 +/-0.75 S-7281, 7282 11/24/2003 Cs-137 0.82 +/- 0.15 1.16 +/- 0.20 0.99 +/- 0.12 SWU-7198, 7199 11/25/2003 Gr. Beta 2.60 +/- 0.53 2.54

• 0.55 2.57 +/- 0.38 DW-7221,7222 11/25/2003 Gr. Beta 12.32

1. AO 12.38 +/- 1.43 12.35 +/-E1.00 SW-7133,7134 12/1/2003 Gr. Beta 2.10

• 0.23 2.46 +/- 0.23 2.28 +/- 0.16 SW-7133,7134 1211/2003 K-40 1.50

• 0.15 1.40 +/- 0.14 1.45 +/- 0.10 W-7519,7520 1211/2003 Fe-55

.3.03 +/- 0.65 3.12 +/- 0.64 3.08 OA6 SW-7805,7806 1211/2003 Sr-90

0.59

• 0.32 0.56 +/- 0.33 0.58 +/- 0.23 VE-7399, 7400 12/9/2003 Gr. Beta 4.99 +/- 0.15 5.24 +/- 0.15 5.11. *0.11 VE-7399,7400 12/9/2003 K-40 5.04 +/- 0.46 5.34 +/- 0.74 5.19 +/- 0.43 SW-7540,7541 12/9/2003 Gr. Alpha 2.64 +/- 1.36 2.10 +/- 1.19 2.37 +/- 0.91 SW-7540,7541 12/9/2003 Gr. Beta 6.62

• 1.22 5.89 +/- 1.35 6.25 +/- 0.91' LW-7736,7737 12/26/2003 Gr. Beta 2.62 +/- 0.54 2.83

• 0.56 2.73 +/-0.39 AP-7868, 7869 12130/2003 Be-7 0.05

• 0.01 0.04 +/- 0.01 0.04

• 0.01 AP-7952, 7953 12130/2003 Be-7 0.04 +/- 0.01 0.04 +/- 0.01 0.04 i 0.01 AP-7994, 7995 12/31/2003 Be-7 0.05

• 0.02 0.05*+/- 0.01 0.05 i 0.01 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.

aResults are reported In units of pCiIL, except for air filters (pCV/Filter), food products, vegetation, soil, sediment (pCi/g)..

b200 minute count time or longer, resulting In lower error.

A5-5

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

Concentrationb Known Control Lab Code Type Date Analysis Laboratory result Activity Llmitsc STW-972 water 12/01102 Am-241 0.56 i 0.06 0.58 +/- 0.09 0.40 - 0.75 STW-972 water 12/01/02 Co-57 57.10 +/-1.90 57.00'+/- 5.70 39.90 - 74.10 STW-972 water 12/01/02 Co-60 38.30 +/- 0.60 38.20 +/- 3.82 26.74 - 49.66 STW-972 water:'

12/01/02 Cs-134 395.30 +/- 10.10 421.00 +/- 42.10.

294.70 - 547.30 STW-972 water 12/01/02 Cs-137 316.40 +/- 5.30 329.00 +32.90 230.30 -427.70 STW-972 water 12/01/02 Fe-55 94.90 +/- 24.50 96.00 +/- 9.60 67.20 - 124.80 STW-972 water 12/01/02 Mn-54 33.40 *0.10 32.90 *3.29 23.03 -42.77 STW-972 water 12/01/02 Ni-63

'123.80 +/- 5.50 136.50 +/- 13.70 95.55 - 177.45 STW-972 water 12/01/02 Pu-238 0.66 +/- 0.06 0.83 +/- 0.08 0.58 - 1.08 STW-972 water

..12/01/02 Pu-239/40 0.001++/- 0.001 0.000 +/- 0.000 0.000 - 0.005 S1W-972 water 12/01/02 Sr-90 13.80 +/-1.00

.12.31

+/-1.23 8.62 -16.00 STW-972 water 12/01/02 Tc-99 128.10 +/- 3.80 132.00 +/- 13.20 92.40 - 171.60 STW-972 water 12101/02 U-233/4 1.60 +/-0.09 1.54

• 0.15 1.08 -2.00 STW-972 water 12101/02 U-238 1.64 +/-0.09 1.60 +/- 0.16 1.12 -2.08 STW-972 water 12/01/02 Zn-65 540.40 +/- 9.90 516.00 +/- 51.60 361.20 -670.80 STSO-987 soil 01/01/03 Co-57 534.36

• 2.61 530.00 +/- 53.00 371.00 -689.00 STSO-987 soil 01/01/03 Co-60 442.16

• 2.31 420.00 +/- 42.00 294.00 - 546.00 STSO-987 soil 01/01/03 Cs-134 211.00 *2.30 238.00+/- 23.80 166.60 -309.40 STSO-987 soil 01/01/03 Cs-1 37 849.50

• 3.30 832.00 +/- 83.20 582.40 - 1081.60 STSO-987 soil 01/01/03 K-40 716.50 +/- 12.80 652.00 +/- 65.20 456.40 - 847.60 STSO-987 soil 01/01/03 Mn-54 148.76 +/- 2.84 137.00 +/- 13.70 95.90 - 178.10 STSO-987 soil 01/01/03 Ni-63 597.10 +/- 23.50 770.00

• 77.00 539.00 1-001.00 STSO-987 soil 01101/03 Pu-238 67.05 +/- 3;10 66.90 +/- 6.70 46.83 - 86.97 STSO-987 soil 01/01/03 Pu-239140 52.80 +/- 3.60 52.70

• 5.30 36.90 - 68.50 STSO-987 soil 01/01/03 Sr-90 609.50

• 9.80 714.00

• 71.40.

499.80 - 928.20 STSO-987 soil 01/01/03 U-23314 99.50 +/- 7.60 89.00

• 8.90 62.30 - 115.70 STSO-987 soil 01/01/03 U-238 508.60 +/-42.20 421.00 +/- 42.10 294.70 -547.30 STSO-987 soil 01/01/03 Zn-65 492.70 +/- 28.10 490.00 +/- 49.00 343.00 - 637.00 D 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

. All results are In Bqlkg or Bq/L as requested by the Department of Energy.

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

A6-1

TABLE A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)'

Concentration8 EML ResultQ Control Limits Lab Code.

Tvoe Date Analysis Laboratory results STW-977 water STW-977 water STW-978 water STW-978 water STW-978 a water STW-978 water STW-978 e water STW-978 water STW-978 water STW-978 water STW-978 water STSO-979 soil STSO-979 soil STSO-979 soil STSO-979 soil STSO-979 soil STSO-979 soil STSO-979 soil STSO-979 soil STSO-979 soil STSO-979 soil STSO-979 soil STVE-980 Vegetation S1VE-980 Vegetation STVE-980 Vegetation STVE-980 Vegetation STVE-980 Vegetation STVE-980 Vegetation STVE-980 Vegetation STAP-981 Air Filter STAP-981 Air Filter STAP-981 Air Filter STAP-981 Air Filter STAP-981 Air Filter STAP-981 Air Filter STAP-981 Air Filter STAP-981 Air Filter STAP-982 Air Filter STAP-982 Air Filter 03/01/03 03/01/03 03/01/03 03/01103 03/01/03 03101103 03/01103

-03/01103 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01103 03/01/03 03/01/03 03/01/03 03101/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 Gr. Alpha Gr. Beta Am-241 Co-60 Cs-1 34 Cs-137 H-3 Pu-238 Pu-239/40 Sr-90 Uranium Ac-228 Am-241 Bi-212 81-214 Cs-137 K-40 Pb-212 Pb-214

• Pu-239/40 Sr-90 Uranium Am-241 Cm-244 Co-60 Cs-137 K-40 Pu-239/40 Sr-90 Am-241 Co-60 Cs-137 Mn-54 Pu-238 Pu-239/40 Sr-90 Uranium Gr. Alpha Gr. Beta 304.30 +/- 53.10 615.80 +/- 14.70 2.00 +/- 0.10 221.30+/- i1.20 23.30 +/- 1.10 61.40 +/- 0.60 341.90 +/- 22.70 3.70 +/- 0.20 4.40 +/- 0.10 4.60 +/- 0.30 5.10 +/- 0.60 55.60 +/- 2.50 12.42 +/- 0.90 57.70 +/- 3.20 60.40 +/- 3.20 1416.80 +/- 70.00 653.80 I 11.90 51.10 +/- 5.20 64.70 +/- 5.10 24.40 +/- 0.30 54.50 +/- 2.60 245.00 +/- 1.50 3.10 +/- 0.20 1.40 +/- 0.50 12.60 +/- 0.40 449.70 +/- 6.20 1159.00 +/- 38.60 4.80 +/- 0.40 659.70 + 50.40 0.27 +/-0.10 30.20 +/- 0.30 90.30 +/- 1.30 41.80 +/-0.60 0.52 +/- 0.10 0.35 +/- 0.10 2.50 +/- 0.10 0.51 +/-0.10 0.90 +/- 0.10, 1.50 +/- 0.10 377.50 627.50 2.13 234.00 30.50 63.80 390.00 3.33 3.92

.4.34 4.29 57.60 15.60 60.60 67.00 1450.00 636.00 57.90 71.10 23.40 64.40 249.00 3.51 2.01 12.10 444.00 1120.00 5.17 650.00 0.34 33.50 99.70 43.80 0.52 0.33 2.80 0.50 1.17 1.50 0.58 -1.29 0.61 - 1.43 0.79 - 1.41 0.80 - 1.20 0.80 - 1.30 0.80 - 1.22 0.78 - 2.45 0.74 - 1.20 0.79 - 1.20 0.69 - 1.34 0.75 - 1.33 0.80 - 1.38 0.65 - 2.28 0.50 - 1.34 0.78 - 1.42 0.80 - 1.25 0.80 - 1.32

.0.78 - 1.32 0.76 - 1.46 0.71 - 1.30 0.67 - 2.90 0.71 - 1.32 0.73 - 2.02 0.61 - 1.59.

0.80 - 1.44 0.80 - 1.31 0.79 - 1.39 0.69 - 1.31 0.55 - 1.21 0.70 - 2.34 0.80 -1.26 0.80 - 1.32 0.80 -1.35 0.67 - 1.33 0.73 - 1.26 0.53 - 1.84 0.79 - 2.10 0.73 - 1.43 0.76 - 1.36 A7-1

TABLE A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)

Concentrationa EML Control*

Lab Code Type Date Analysis Laboratory results ResuitP LImitso

• STW-992 water 09102103 Am-241 9.78 +/- 0.32 8.76 0.79 - 1.41 The September, 2003 results are preliminary. Control limits used were taken from the March, 2003 data.

Control limits may vary slightly when the final study Is published.

STW-992 STW-992 STW-992 S1W-992.

STW-992 STW-992 STW-992 STW-992 STW-993 STW-993 STSO994 STSO-994 STSO-994 STSO-994 STSO-994 STSO-994 STSO-994

.,water water water

. water water water water water water water soil soil soil soil soil soil soil 09/02/03 09102/03 09102/03 09102103 09102103 09102/03 09/02103 09/02/03 09/02/03 09/02/03 Co-60

• Cs-134 Cs-137 H-3 Pu-238 Pu-239140 Sr-90 Uranium

• Gr. Alpha Gr. Beta 468.30 +/-4.10 53.90 +/- 0.80 76.10 +/- 1.40 355.20 +/- 12.80 1.71 *'0.07 4.24 +/- 0.01 6.70 +/- 0.50 5.10 +/- 0.60 688.00 +/- 7.60 1985.00' +/- 111.00 513.00 63.00 80.30 446.30

' 2.07 4.99 7.04

' 5.69 622.00 1948.00 0.80 - 1.20 0.80 - 1.30 0.80 - 1.22

-0.78 - 2.45 0.74 - 1.20

• 0.79 - 1.20 0.69 -1.34 0.75 - 1.33 0.58 - 1.29 0.61 - 1.43 09102/03 09/02/03 09/02/03 09102/03 09/02/03 09/02/03 09/02103 Am-241 Cs-137 K-40 Pu-238 Pu-239140 Sr-90 Uranium 19.70 +/- 1.50

'1928.00 +/-19.00 533.00 +/- 79.00 15.30 +/- 0.80 32.50 +/- 2.30 69.80 +/- 2.30 228.30 +/- 17.10 18.40 1973.00 488.00 14.60 30.40 80.30 259.30 0.65 - 2.28 0.80 - 1.25 0.80 - 1.32 0.59 - 2.88 0.71 - 1.30 0.67 - 2.90 0.71 - 1.32 STAP-995 STAP-995 STAP-995 STAP-995 STAP-995 STAP-995 STAP-995 STAP-995 STAP-996 STAP-996 Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter 09/02/03

'09102/03 09/02/03 09/02/03 09/02/03

• 09/02/03 09/02/03 09/02/03 09/02/03 09102/03 Am-241 Co-60 Cs-137 Mn-54 Pu-238 Pu-239/40 Sr-90 Uranium '

Gr. Alpha Gr. Beta

.0.64 +/- 0.05 48.50 +/- 0.40 51.20 +/- 1.10 53.70 +/- 1.10 0.24 +/- 0.05 0.41 +/-0.10 1.90 +/-0.10 0.80 +/- 0.06 3.23 +/- 0.07 4.18 +/- 0.03 0.44 55.10 54.80 58.00 0.23 0.40 2.06 0.82

- 3.11 3.89 0.70 - 2.34 0.80 - 1.26 0.80 - 1.32 0.80 - 1.35 0.67. -1.33 0.73 - 1.26 0.53 - 1.84 0.79 - 2.10 0.73 - 1.43 0.76 - 1.36

• Results are reported In Bq/L with the following exceptions: Air Filters (Bq/Filter), Soil and Vegetation (8qlkg).

b The EML result listed Is the mean of replicate determinations for each nuclide +/- the standard error of the mean.

c Control limits are reported by EML as the ratio of Reported Value / EML value.

d A low bias for Cs-134 activity has been observed In the past. No errors have been found In the library or efficiency.

Additional spike analyses will be performed and a correction factored into the calculation.

Reporting error.

A7-2

Appendix B Summary Tables in the format of NRC Radiological Assessment Branch Technical Position Revision 1, November 1979 Page B-I

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Wolf Creek Generating Station Docket No.: 50-482 Location of Facility: Coffey County, Kansas Reporting Period: Annual 2003 Medium of ODCM All Indicator Indicator Location with Control Locations Pathway Analysis and Lower Locations Highest Annual Mean Number of Sampled Total Number of Limit of Name

. Nonroutine (Unit of Analysis Performed Detection

• • Mean (f)

Distance and

• • Mean (f)

• • Mean (f Reported Measurement)

(LLD)

• • Range Direction

• • Range

• • Range Measurements **

Air Particulate (pCi/M 3)

Gross Beta (299)

Gamma (23)

Be-7 1-131 (299) 0.01 0.029 (208/208)

(0.014-0.057) 0.071 (16/16)

(0.044-0.084) 18 3.0 miles SSE 37 2.0 miles NNW 0.031 (52/52)

(0.014-0.056) 0.073 (4/4)

(0.070-0.076)

Stations 40 & 48 0.028 (91/91)

(0.014-0.053) 0.068 (7/7)

(0.050-0.087)

- (0/91) 0 0

0 0.07

- (0/208)

N/A N/A External Radiation (mR/day)

Stations 39, 40 &

48 0.203 (24/24)

(0.163-0.224)

TLD (378) 0.217 (354/354)

(0.126-0.266) 1i 1.4 miles N 0.240 (8/8)

(0.229-0.260) 0 Surface Water (pC!/I)

JRR & MUSH

-(0/12)

Gamma (36)

-(0/24)

N/A N/A 0

Tritium (36) 3000 14978 (24/24)

(11394-26793)

DC 0.6 miles WNW 15627 (12/12)

(11409-26793)

-(0/12) 0 Ground Water (pCiA) 1-131 (20) 1

-(0/16)

Gamma (20)

-(0/16)

N/A N/A N/A N/A N/A N/A B-12

-(0/4)

-(0/4)

-(0/4) 0 0

0 Tritium (20) 3000

-(0/16)

Page B-2

• • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (e

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Wolf Creek Generating Station Docket No.: 50-482 Location of Facility: Coffey County. Kansas Reporting Period: Annual 2003 Medium of ODCM All Indicator Indicator Location with Control Locations Pathway Analysis and Lower Locations Highest Annual Mean Number of Sampled Total Number of Limit of Name Nonroutine (Unit of Analysis Performed Detection

• • Mean (f)

Distance and

• • Mean (f)

• • Mean (f)

Reported Measurement)

(LLD)

• • Range Direction

• • Range

• • Range Measurements **

Drinking Water (pCin) 1-131 (36)

Gross Beta (36) 1

-(0-24)

N/A NF-DW 17.5 miles SSE N/A BW-15

-(0/12) 4.8 (12/12)

(3.5-5.7) 0 0

4 4.6 (24/24)

(3.1-7.8) 4.9 (12/12)

(3.1-7.8)

Gamma (36)

Tritium (12)

-(0/24)

N/A N/A N/A N/A

-(0/12)

-(0/4) 0 0

2000

-(0/8)

Shoreline Sediment (pCi/kg dry)

Gamma (6)

JRR 8262.9 (2/2)

(4565.7-11960.0)

K-40 11127.8 (4/4)

(10623-11677)

EEA 3.0 miles NNW 11321.0 (1/1) 0 Cs-1 37 144.1 (1/4)

EEA 3.0 miles NNW 144.1 (1/1)

-(0/2)

Fish (pCi/kg wet)

Gamma (16)

K-40 JRR 3109.8 (10/10)

(2504.8-3725.8)

WCL 0.6 miles 3109.8 (10/10)

(2504.8-3725.8) 3200.2 (6/6)

(2734.5-3816.3) 0 Tritium (16) 8670.2 (10/10)

(5852-11620)

WCL 0.6 miles 8670.2 (10/10)

(5852-11620)

-(0/6) 0 Page B-3

• • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Wolf Creek Generating Station Docket No.: 50-482 Location of Facility: Coffey County. Kansas Reporting Period: Annual 2003 Medium of ODCM All Indicator Indicator Location with Control Locations Pathway Analysis and Lower Locations Highest Annual Mean Number of Sampled Total Number of Limit of Name Nonroutine (Unit of Analysis Performed Detection

• • Mean (f Distance and

• • Mean (f

• • Mean (f Reported Measurement)

(LLD)

• • Range Direction

• • Range

• • Range Measurements **

Broadleaf Vegetation (pCi/kg wet)

Gamma (21)

Be-7 D-1 & S-4

-(0/7)

N/A N/A 293.9 (5/14)

(214.1-379.5) 0 K-40 3618.0 (7/7)

(2292.9-4899.8)

N-1 2.4 miles W 3698.1 (2/2)

(3369.5-4026.7) 3587.3 (14/14)

(2110.9-6343.1) 0 NR-UI Crops (pCi/kg wet)

Gamma (4)

K-40 6504.0 (3/3)

(2457-14559)

NR-D2 11.5 miles S 8508.1 (2/2)

(2457-14559) 3540.7 (1/1) 0 Bottom Sediment (pCi/kg dry)

Gamma (6)

JRR K-40 11931.1 (414)

(8981-14629)

DC 0.6 miles WNW 13067.5 (2/2)

(11506-14629) 15948.5 (212)

(14603-17294) 0 Co-60 343.0 (2/4)

(327.2-358.8)

DC 0.6 miles WNW 343.0 (2/2)

(327.2-358.8)

- (0/2) 0 Cs-137 205.5 (3/4)

(69.1-310.2)

DC 0.6 miles WNW 273.7 (2/2)

(237.1-310.2) 133.3 (2/2)

(123.6-143.0) 0 Aquatic Vegetation (pCi/kg wet)

Gamma (1)

K-40 No Control 2440.8 (1/1)

EEA 3.0 miles NNW 2440.8 (1/1) 0 Page B-4

• • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations Is Indicated in parentheses ()

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Wolf Creek Generating Station Docket No.: 50-482 Location of Facility: Coffey County. Kansas Reporting Period: Annual 2003 Medium of ODCM All Indicator Indicator Location with Control Locations Pathway Analysis and Lower Locations Highest Annual Mean Number of Sampled Total Number of Limit of Name Nonroutine (Unit of Analysis Performed Detection

• • Mean (f Distance and

• • Mean (e

• • Mean (f)

Reported Measurement)

(LLD)

• • Range Direction

• • Range

• • Range Measurements **

Terrestrial Vegetation (pCi/kg wet)

Gamma (1)

No Control Be-7 865.1 (1/1)

EEA 3.0 miles NNW 865.1 (1/1) 0 K-40 8657.3 (1/1)

EEA 3.0 miles NNW 8657.3 (1/1)

Soil (pCi/kg dry)

Gamma (2)

No Control K-40 10821.0 (2/2)

(10080-11562)

MUDS 1.5 miles WNW 11562.0 (1/1) 0 Cs-1 37 170.8 (2/2)

(153.7-187.9)

EEA 3.0 miles NNW 187.9 (1/1) 0 Deer (pCi/kg wet)

Gamma (1)

No Control K-40 2708.1 (1/1)

A2.1 2.1 miles N 2708.1 (1/1) 0 Page B-5

• • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (e

Appendix C 2003 Individual Sample Results Page C-1

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 02 Collection Start Collection Stop Volume Gross Beta Date Date M3 Activity (pCUCu.M.)

0102 0108 258 0.026+-0.004 0108

.0115 297 0.026+-0.004 0115 0124 373 0.031+-0.003 0124 0130 231.

0.047+-0.005 0130 0205 264 0.028+-0.004 0205 0213 344 0.029+-0.003 0213 0220 299 0.022+-0.004 0220 0226 250 0.029+-0.004 0226 0307 391 0.044+-0.003 0307 0313 258 0.043+-0.005 0313 0321 345 0.031+-0.003 0321 0326 215 0.023+-0.004 0326 0402 302 0.026+-0.004 0326*

0402 302 0.029+-0.004 0402 0409 305 0.017+-0.003 0409 0415 247 0.035+-0.004 0415 0422 302 0.018+-0.003 0422 0429 297 0.022+-0.003 0429

. 0507 341

. 0.021+-0.003 0507 0513 275 0.021+-0.003 0513 0520 301 0.016+-0.003 0520 0528 354 0.024+-0.003 0528 0604 313 0.017+-0.003 0604 0611 308 0.017+-0.003

• Duplicate Page C - 2

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 02 Collection Start Collection Stop Volume Gross Beta Date Date M3 Activity (pCVCu.M.)

UVl 1 0618 0625 0702 0709 0716 0723 0730 0806 0813 0820 0827 0903 0910 0917 0924 1001 1008 1016 1022 1029 1105 1112 1119 1125 1203 UVlo 0625 0702 0709 0716 0723 0730 0806 0813 0820 0827 0903 0910 0917 0924 1001 1008 1016 1022 1029 1105 1112 1119 1125 1203 1211 azz 302 312 298 298 289 291 309 306 294 296 304 311 327 324 308 330 357 276 325 322 323 322 250 333 335 U.VZ34--U.UUJ 0.024+-0.004 0.018+-0.003 0.025+-0.004 0.025+-0.004 0.021+-0.004 0.033+-0.004 0.028+-0.003 0.034+-0.004 0.029+-0.004 0.045+-0.005 0.018+-0.003 0.035+-0.004 0.022+-0.003 0.026+-0.004 0.022+-0.004 0.035+-0.003 0.025+-0.003 0.039+-0.005 0.025+-0.004 0.027+-0.004 0.050+-0.005 0.016+-0.003 0.036+-0.005 0.029+-0.004 0.033+-0.004

• Duplicate Page C - 3

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 02 Collection Start Collection Stop Volume Gross Beta Date Date M3 Activity (pCVCu.M.)

1U11 1217 1223 1217 1223 1230 Z47 259 295 u.u3B+-U.U05 0.022+-0.004 0.025+-0.003

• Duplicate Page C-*4

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 18 Collection Start Collection Stop Volume Gross Beta Date Date MActivity (pClICu.M.)

0102 0108 0115 0124 0130 0205 0213 0220

• 0226 0307 0313 0321 0326 0402 0402*

0409 0415 0415' 0422 0429 0507 0507*

0513 0520

• 0108 0115 0124 0130 0205 0213 0220

• 0226 0307 0313 0321 0326 0402 0409 0409 0415 0422 0422 0429 0507 0513 0513 0520 0528 265 294 387 249 258 343 309 256 388 261

• 342 218 302 300 300 240

• 296 296 296 335 250 250 295 342 0.030+-0.004 0.026+-0.004 0.035+-0.003 0.047+-0.005 0.036+-0.005 0.031+-0.003 0.017+-0.003 0.030+-0.004 0.044+-0.003 0.043+-0.005 0.025+-0.003 0.026+-0.004 0.030+-0.004 0.018+-0.003 0.016+-0.003 0.037+-0.004 0.016+-0.003 0.014+-0.003 0.021 +-0.003 0.020+-0.003 0.024+-0.004 0.020+-0.003 0.018+-0.003 0.026+-0.003

• Duplicate Page C - 5

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 18 Collection Start Collection Stop Volume Gross Beta Date Date M3 Activity (pCi/Cu.M.)

uVZO 0604 0611 0618 0625 0702 0709 0709*

0716 0723 0730 0806 0813 0820 0827 0903

• 0910 0917 0924 1001 1008 1016 1022 1029 1105 UOU4 0611 0618 0625 0702 0709 0716 0716 0723 0730 0806 0813 0820 0827 0903 0910 0917 0924 1001 1008 1016 1022 1029 1105 1112 289 306 277 283 284 278 278 260 282 288 292 291 315 289 288 288 301 286 297 318 253 295 292 289 U.U1 (1-U.UU 3 0.019+-0.003 0.029+-0.004 0.024+-0.004 0.025+-0.004 0.028+-0.004 0.027+-0.004 0.024+-0.004 0.025+-0.004 0.031+-0.004 0.026+-0.003 0.034+-0.004 0.034+-0.004 0.045+-0.004 0.014+-0.003 0.035+-0.004 0.024+-0.003 0.028+-0.004 0.022+-0.004 0.039+-0.004 0.029+-0.003 0.042+-0.005 0.026+-0.004 0.032+-0.004 0.056+-0.005

• Duplicate Page C-6

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 18 Collection Start Collection Stop Volume Gross Beta Date Date

. M3 Activity (pCVCu.M.)

1112 1119 1125 1203 1211 1217 1223 1119 1125 1203 1211 1217 1223 1230 291 250 328 341 247 260 304 0.023+-0.004 0.034+-0.005 0.032+-0.004 0.037+-0.004 0.035+-0.005 0.022+-0.004 0.023+-0.003

• Duplicate Page C -7

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 32 Collection Start Collection Stop Volume Gross Beta Date Date M3 Activity (pCUCu.M.)

0102 0108 254 0.028+-0.004 0108 0115 289 0.031+-0.004 0115 0124 383 0.031+-0.003 0124 0130 236 0.044+-0.005 0130 0205 261 0.032+-0.004 0205 0213 348 0.033+-0.003 0213 0220 321 0.022+-0.003 0220 0226 265 0.032+-0.004 0226 0307 407 0.0414-0.003 0307 0313 274 0.041+-0.005 0313 0321 360 0.030+-0.003 0321 0326 232 0.024+-0.004 0326 0402 316 0.031+-0.004 0402 0409 320 0.018+-0.003 0409 0415 251 0.033+-0.004 0415 0422 327 0.017+-0.003 0422 0429 318 0.024+-0.003 0429 0507 363 0.025+-0.003 0507 0513 273 0.021+-0.003 0513 0520 303 0.017+-0.003 0520 0528 357 0.024+-0.003 0528 0604 318 0.019+-0.003 0604 0611 312 0.020+-0.003 0611 0618 326 0.026+-0.003

• Duplicate Page C - 8

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 32 Collection Start Collection Stop Volume Gross Beta.

Date Date M3 Activity (pCICu.M.)

U010 0625 0702 0709 0716 -

0723 0730 0806 0813 0820 0827 0903

0910, 0910 0917 0924

• 1001 1008 1016 1022 1029

• 1105 1112 1119 1125 1203 Ub-zz 0702 0709 0716 0723 0730 0806 0813 0820 0827 0903 0910 0917 0917 0924 1001 1008 1016 1022 1029 1105 1112 1119 1125 1203 1211 aUY 313 312 302 275 285 279 272 276 306 301 301 300 300 303 291 312 330 249 294 297 299 291 255 339 349 U.UZZV-U.UVU 0.020+-0.003 0.026+-0.004 0.027+-0.004 0.023+-0.004 0.032+-0.004 0.032+-0.004 0.030+-0.004 0.034+-0.004 0.045+-0.004 0.016+-0.003 0.035+-0.004 0.025+-0.003 0.023+-0.003 0.028+-0.004 0.026+-0.004 0.042+-0.004 0.029+-0.003 0.044+-0.005 0.026+-0.004 0.030+-0.004 0.054+-0.005 0.024+-0.004 0.040+-0.005 0.028+-0.003 0.036+-0.004

• Duplicate Page C -9

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 32 Collection Start Collection Stop Volume Gross Beta Date Date M3 Activity (pCICu.M.)

1211 i217 1223 1217 1223 1230 249 263 299 0.036+-0.005 0.024+-0.004 0.024+-0.003

• Duplicate Page C - 10

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 37 Collection Start Collection Stop Volume Gross Beta Date Date M3 Activity (pCiCu.M.)

0102 0108 255 0.031+-0.004 0108 0115 291 0.027+-0.004 0115 0124 380 0.029+-0.003 0124 0130 236.

0.046+-0.005 0130 0205 263 0.030+-0.004 0205 0213 350 0.030+-0.003 0213 0220

.309 0.019+-0.003 0220*

0226 250 0.031+-0.004 0220 0226 250 0.034+-0.005 0226 0307 390 0.047+-0.004 0307 0313 261 0.042+-0.005 0313 0321 340 0.023+-0.003 0321 0326 218 0.024+-0.004 0326 0402 302 0.030+-0.004 0402 0409 305 0.017+-0.003 0409 0415 247 0.033+-0.004 0415 0422 317 0.015+-0.003 0422 0429 298 0.019+-0.003 0429 0507 335 0.022+-0.003 0507 0513 260 0.021+-0.003 0513 0520 294 0.018+-0.003 0520 0528 340 0.023+-0.003 0528 0604 303 0.018+-0.003 0604 0611 293 0.016+-0.003

• Duplicate Page C - 11

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 37 Collection Start Collection Stop Volume Gross Beta Date Date M3 Activity (pCICu.M.)

0611 0618 302 0.028+-0.004 0618 0625

. 286 0.026+-0.004 0625 0702 303 0.021+-0.004 0702 0709.

289 0.029+-0.004 0709 0716 303 0.024+-0.004 0716 0723 290 0.026+-0.004 0723 0730 297 0.029+-0.004 0730 0806 303 0.029+-0.003 0806 0813 302 0.035+-0.004 0813 0820 289 0.029+-0.004 0820 0827 306 0.047+-0.004 0827 0903 300 0.016+-0.003 0903*

0910 292 0.035+-0.004 0903 0910 292 0.035+-0.004 0910 0917 309 0.023+-0.003 0917 0924 300 0.029+-0.004 0924 1001 293 0.024+-0.004 1001 1008 300 0.043+-0.004 1008 1016 322 0.032+-0.003 1016 1022 254 0.048+-0.005 1022 1029 294 0.027+-0.004 1029 1105 292 0.030+-0.004 1105 1112 292 0.057+-0.005

• 1112 1119 288 0.024+-0.004 1119 1125 246 0.041+-0.005 1125 1203 333 0.038+-0.004

• Duplicate Page C - 12

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 37 Collection Start Collection Stop Volume Gross Beta Date Date M3 Activity (pClICu.M.)

Iz2 1211 1217 1223 1U11 1217 1223 1230 347 243 255 289 U.U35+-U.UU4 0.037+-0.005 0.025*-0.004 0.027+-0.003

• Duplicate Page C - 13

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 40 Collection Start Collection Stop Volume Gross Beta Date Date M3 Activity (pCUCu.M.)

W1 U 0108 0115 0124 0130 0205 0205' 0213 0220 0226 0307 0313 0313*

0321 0326 0402 0409 0415 0422 0429 0507 0513 0520 0528 1MU 0115 0124 0130 0205 0213 0213 0220 0226 0307 0313 0321 0321 0326 0402 0409 0415 0422 0429 0507 0513 0520 0528 0604 zbz 282 370 240 259 347

• 347 299

• 240 388 260 343 343 218 298 295 239

• 302 293 318 249 293 335 293 U.031+-U.UU4 0.030+-0.004 0.034+-0.004 0.051+-0.005 0.030+-0.004 0.034+-0.003 0.034+-0.003 0.021+-0.003 0.030+-0.005 0.044+-0.003 0.045+-0.005 0.029+-0.003 0.026+-0.003 0.026+-0.005 0.028+-0.004 0.017+-0.003 0.036+-0.004 0.014+-0.003 0.019+-0.003 0.026+-0.004 0.019+-0.003 0.018+-0.003 0.029+-0.003 0.020+-0.003

• Duplicate Page C - 14

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 40 Collection Start Collection Stop Volume Gross Beta Date Date M3-Activity (PC iC u.M.

0604 0611 0618 0618' 0625 0702 0702' 0709 0716 0723 0730 0730*

0806 0813 0820 0827 0903.

0910 0917 0924 0611 0618 0625 0625 0702 0709 0709 0716 0723 0730 0806 0806 0813 0820 0827 0903 0910 0917 0924 1001 286 296 275 275 287 285 285 291 270 289 296 296 297 291 316 296 289 302 295 291 0.016+-0.003 0.029+-0.004 0.022+-0.004 0.022+-0.004 0.020+-0.004 0.027+-0.004 0.025+-0.004 0.023+-0.004 0.026+-0.004 0.033+-0.004 0.031+-0.004 0.033+-0.004 0.038+-0.004 0.032+-0.004 0.045+-0.004 0.015+-0.003 0.037+-0.004 0.024+-0.003 0.028+-0.004 0.020+-0.004

• Duplicate Page C - 15

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 48 Collection Start Collection Stop Volume Gross Beta Date Date M 3 Activity (pCUCu.M.)

1UZ 0108 0115 0124 0130 0205 0213 0220 0226 0307 0313 0321 0326 0402 0409 0415 0422 0429 0507 0513 0520 uluo 0115 0124 0130 0205 0213 0220

• 0226 0307 0313 0321

• 0326 0402 0409 0415 0422 0429 0507 0513 0520 0528 Z04 299 380 232 250 331 279 245 364 255 343 218 292 300 237 300 300 336 255 278 336 U.UZL+-U.UU4 0.031+-0.004 0.030+-0.003 0.046+-0.005 0.027+-0.004 0.031+-0.003 0.018+-0.003 0.030+-0.004 0.038+-0.003 0.041 +-0.005 0.024+-0.003 0.027+-0.005 0.029+-0.004 0.016+-0.003 0.040+-0.004 0.015+-0.003 0.021+-0.003 0.022+-0.003 0.021+-0.003 0.020+-0.003 0.026+-0.003

• Duplicate Page C - 16

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 48 Collection Start Collection Stop Volume Gross Beta Date Date M3 Activity (pCiICu.M.)

0528 0604 292 0.018+-0.003 0604 0611 302 0.016+-0.003 0611 0618 306 0.026+-0.004 0618 0625 275 0.023+-0.004 0625 0702 283 0.024+-0.004 0702 0709 286 0.024+-0.004 0709 0716 296 0.025+-0.004 0716 0723 265 0.024+-0.004 0723 0730 288 0.034+-0.004 0730 0806 291 0.033+-0.004 0806 0813 302 0.033+-0.004 0813 0820 301 0.034+-0.004 0820 0827 300 0.040+ 0.004 0827 0903 293 0.016+-0.003 0903 0910 285 0.031+-0.004 0910 0917 296 0.024+-0.003 0917 0924 302 0.026+-0.004 0924 1001 286 0.022+-0.004 1001 1008 292 0.036+-0.004 1008 1016 328 0.028+-0.003 1016 1022 249 0.043+-0.005 1022 1029 284 0.023+-0.004 1029 1105 284 0.029+-0.004

• Duplicate Page C - 17

Wolf Creek Nuclear Operating Corporation Air Particulate Filters STATION NUMBER 48 Collection Start Collection Stop Volume-Gross Beta Date Date

. M3 Activity (pCUCu.M.)

1105 1112 1119 1125 1203 1211 1217 1223 1112 1119 1125 1203 1211 1217 1223 1230 286 281 249 324 305 239 252 282 0.053+-0.005 0.025+-0.004 0.038+-0.005 0.032+-0.004 0.035+-0.004 0.038+10.005 0.022+-0.004 0.026+-0.003

• Duplicate Page C - 18

Wolf Creek Nuclear Operating Corporation Air Particulate Filters Isotopic Analysis on Quarterly Composite (pCi/ Cu.M.)

STATION NUMBER 02 Gamma Spectrum Analysis Dates Listed are Collection Start Dates 0102 BE.7 MN.54 CO058 FE-59 CO60 ZN-65 ZR-95 CS-134 CS-137 0402 BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 AIR PARTICULATES 0.072+-0.011

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001 AIR PARTICIILATES 0.082+-0.015

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001 0702 BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 1001 BE-7 MN-54 CO-58 FE-59.

CO-60 ZN-65 ZR-95 CS-134 CS-137 AIR PARTICULATES 0.075+-0.018

<0.001

<0.001

<0.00!

<0.001

<0.001

<0.001

<0.001

<0.00 I AIR 'ARTICULATES 0.044+-0.010

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001 Page C - 19

0102 BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 0402 BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65

• ZR-95 CS-134 CS-137 AIR PARTICULATES 0.065+-0.014

<0.001

<0.001

<0.001

<0.001

<0.00I

<0.001

<0.001

<0.001 AIR PARTICULATES 0.079+-0.013

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.00!

0702 BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65.

ZR-95 CS-134 CS-137 1001 BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 Wolf Creek Nuclear Operating Corporation Air Particulate Filters Isotopic Analysis on Quarterly Composite (pCi/ Cu.M.)

STATION NUMBER 18 Gamma Spectrum Analysis Dates Listed are Collection Start Dates AIR PARTICULATES 0.084+-0.013

<0.001

<0.001

<0.001

<0.001

<0.00!

• <0.001

<0.001 AIR PARTICULATES 0.062+-0.014

<0.001

<0.00!

<0.00 1

<0.00!

<0.001

<0.001

<0.001

<0.001 Page C - 20

0102 BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 0402 AIR PARTICLATES 0.064+-0.014

<0.001

<0.00 I

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001 AIR PARTICULATES 0.081+-0.016

<0.00 I

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001 0702 BE-7 MN-54 CO-5S FE-59 CO-60 ZN65 ZR-95 CS-134 CS-137

'1001 BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 Wolf Creek Nuclear Operating Corporation Air Particulate Filters Isotopic Analysis on Quarterly Composite (pCi/ Cu.M.)

STATION NUMBER 32 Gamnma Spectrum Analysis Dates Listed are Collection Start Dates AIR PARTICULATES 0.079+-0.017

<0.001

<0.001

<0.00o

<0.001

<0.001

<0.001

<0.001

<0.001 AIR PARTICIULATES 0.056+-0.015

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001 BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 Page C-21

Wolf Creek Nuclear Operating Corporation Air Particulate Filters Isotopic Analysis on Quarterly Composite (pCi/ Cu.M.)

STATION NUMBER 37 Gamma Spectrum Analysis Dates Listed are Collection Start Dates 0102 BE-7 MN-54 C0-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-37 0402 AIR PARTICUJLATES 0.075+-0.012

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001 AIR PARTICIJLATES 0.072+-0.015

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001 0702 BE-7 MN-54 CO-58

.FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 1001 BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 AIR PARTICULATES 0.076+-0.016

<0.001

<0.001

<0.001

<0.001

• <0.001

<0.001

<0.001

<0.001 AIR PARTICIJLATES 0.070+-0.018

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001 BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 Page C - 22

Wolf Creek Nuclear Operating Corporation Air Particulate Filters Isotopic Analysis on Quarterly Composite (pCi/ Cu.M.)

STATION NUMBER 40 Gamna Spectrum Analysis Dates Listed are Collection Start Dates 0102 BE-7 MN-54 C6-58 FE-59 CO-60 ZN-65 ZR-95 CS434 CS-137 0402 BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 AIR PARTICUILATES 0.072+-0.0 12

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001 AIR PARTICULATES 0.083+-0.015

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001 0702.

BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 AIR PARTICULATES 0.087+-0.017

<0.001

<0.001

<0.001

<0.001

<0.001 I

<0.001

<0.001

<0.001 Page C - 23

Wolf Creek Nuclear Operating Corporation Air Particulate Filters Isotopic Analysis on Quarterly Composite (pCi/ Cu.M.)

STATION NUMBER 48 Gamma Spectrum Analysis Dates Listed are Collection Start Dates 0102 BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 0402 BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 AIR PARTICIJLATES 0.056+-0.012

<0.00I

<0.002

<0.001

<0.002

<0.001

<0.00!

<0.001

<0.002 AIR PARTICULATES

.070+-0.0123

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.001

<0.00!

0702 BE-7 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 loo1 BE-7 MN-54 CO-SS FE.59 CO-60 ZN-65 ZR-95 CS-134 CS-137 AIR PARTICULATES 0.057+-0.013

<0.00o

<0.002

• <0.002

<0.001

<0.001

<0.00o

<0.001

<0.002 AIR PARTICULATES 0.050+-0.013

<0.00

<0.00

<0.002

<0.001

<0.001

<0.001

<0.00 I

<0.001 Page C -24

Wolf Creek Nuclear Operating Corporation Charcoal Filters STATION NUMBER 02 Collection Start Collection Stop Volume 1-131 Activity Date Date M3 (pCiICu.M.)

0102 0108 258

<0.011 0108 0115 297

<0.010 0115 0124 373

<0.010 0124 0130 231

<0.018 0130 0205 264

<0.011 0205 0213 344

<0.008 0213 0220

. 299

<0.009 0220 0226 250

<0.012 0226 0307

. 391

<0.008 0307 0313 258

<0.008 0313 0321 345

<0.008 0321 0326 215

<0.015 0326 0402 302

<0.009 0402 0409 305

<0.005 0409.

0415 247

<0.013 0415 0422 302

<0.007 0422 0429 297

<0.010 0429 0507 341

<0.008 0507 0513 275

<0.009 0513 0520 301

<0.010 0520 0528 354

<0.004 0528 0604 313

<0.009 0604 0611

.308

<0.004 0611 0618 322

<0.018 0618 0625 302

<0.018 0625 0702 312

<0.018 0702 0709 298

<0.014 0709 0716 298

<0.014 Page C - 25

Wolf Creek Nuclear Operating Corporation Charcoal Filters STATION NUMBER 02 Collection Start Collection Stop Volume 1-131 Activity Date Date M3(pCiICu.M.)

• 0716 0723 0730 6806 0813 0820 0827 0903 0910 0917 0924 1001 1008 1016 1022 1029 1105 1112 1119.

1125 1203 1211 1217 1223 0723 0730 0806 0813 0820 0827.

0903 0910 0917 0924 1001 1008 1016.

1022 1029 1105 1112 1119 1125 1203 1211 1217 1223 1230 289 291 309 306 294 296 304 311 327 324 308 330 357 276 325 322 323 322 250 333 335 247.

259 295

<0.009

<0.022

<0.016

<0.007

<0.014

<0.011

<0.014

<0.007

<0.010

<0.016

<0.019

<0.010

<0.011

<0.015

<0.011

<0.011*

<0.015

<0.017

<0.024

<0.012

<0.015

<0.023

<0.014

<0.014 Page C - 26

Wolf Creek Nuclear Operating Corporation Charcoal Filters STATION NUMBER 18 Collection Start Collection Stop Volume 1-131 Activity Date Date M 3 (pCi/Cu.M.)

0102 0108 0115 0124 0130 0205 0213 0220 0226 0307 0313 0321 0326 0402 0409 0415 0422 0429 0507 0513 0520 0528 0604 0611 0618 0625 0702 0709 0108 0115 0124 0130 0205 0213 0220 0226 0307 0313 0321 0326 0402 0409 0415 0422 0429 0507 0513 0520 0528 0604

• 0611 0618 0625 0702 0709 0716 265 294 387 249 258 343 309 256 388 261 342 218 302 300 240 296 296 335 250 295 342 302 289 306 277 283 284 278

<0.01 1

<0.010

<0.009

<0.017

<0.012

<0.008

<0.009

<0.01 1

<0.008

<0.008

<0.009

<0.015

<0.009

<0.005

<0.013

<0.007

<0.010

<0.008

<0.010

<0.010.

<0.004

<0.009

<0.005

<0.019

<0.020

<0.020

<0.014

<0.014 Page C - 27

Wolf Creek Nuclear Operating Corporation Charcoal Filters STATION NUMBER 18 Collection Start Collection Stop Volume 1-131 Activity Date Date M3 (pCI/Cu.M.)

. 0716 0723 0730 0806 0813 0820 0827 0903 0910 0917 0924 1001 1008 1016 1022 1029 1105 1112 1119 1125 1203 1211 1217 1223 0723 0730 0806 0813 0820 0827 0903 0910

• 0917 0924 1001 1008 1016 1022 1029 1105 1112 1119 1125 1203 1211 1217 1223 1230 260 282 288 292 291 315 289 288 288 301 286 297 318 253 295 292 289 291 250 328 341 247 260 304

<0.010

<0.023

<0.017

<0.007

<0.014

<0.010

<0.015

• <0.007

• <0.011

<0.018

<0.021

<0.01 1

<0.012

<0.016

<0.013

<0.012

<0.016

<0.018

<0.024

<0.012

<0.015

<0.023

<0.014

<0.013 Page C - 28

Wolf Creek Nuclear Operating Corporation Charcoal Filters STATION NUMBER 32 Collection Start Co.ection Stop Volume 1-131 Activity IDate Date.

3(iCi/Cu.M.)

0102 0108 0115 0124 0130.

0205 0213 0220 0226 0307 0313 0321 0326 0402 0409 0415 0422 0429 0507 0513 0520 0528 0604 0611 0618 0625 0702 0709 0108 0115 0124 0130 0205 0213 0220 0226 0307 0313 0321 0326 0402 0409 0415 0422 0429 0507 0513 0520 0528 0604 0611 0618 0625 0702 0709 0716 254 289 383 236 261 348 321 265 407 274 360 232 316 320 251 327 318 363 273 303 357 318 312 326 309 313 312 302

<0.012

<0.010

<0.010

<0.018

<0.01 1

<0.008

<0.008

<0.011

<0.008

<0.008

<0.008

<0.014

<0.008

<0.005

<0.013

<0.006

<0.010

<0.008

<0.009

<0.010

<0.004

<0.009

<0.004

<0.018

<0.018

<0.018

<0.013

<0.013 Page C - 29

Wolf Creek Nuclear Operating Corporation Charcoal Filters STATION NUMBER 32 Collection Start Collection Stop Volume 1-131 Activity Date Date (pClUCu.M.)

0716 0723 0730.

0806 0813 0820 0827 0903 0910 0917 0924 1001 1008 1016 1022.

1029 1105 1112.

1119 1125 1203 1211 1217 1223 0723 0730 0806 0813 0820 0827 0903 0910 0917 0924 1001 1008 1016 1022 1029 1105 1112 1119 1125 1203 1211 1217 1223 1230 275 285 279 272 276

• 306 301 301 300 303 291 312 330 249 294 297 299 291 255 339 349.

249 263 299 C0.009

<0.023

<0.017

<0.007

<0.015

<0.011

<0.014

<0.007

<0.01 1

<0.018

<0.020

<0.011

<0.012

<0.016

<0.013

<0.012

<0.016

<0.018

<0.023

<0.01 1

<0.015

<0.023

<0.014

<0.014 Page C - 30

Wolf Creek Nuclear Operating Corporation Charcoal Filters STATION NUMBER 37 Collection Start Collection Stop Volume 1-131 Activity Date Date M3 (pClI/Cu.M.)

0102 0108 255

<0.012 0108 0115 291

<0.010 0115 0124 380

<0.010 0124 0130 236

<0.018 0130 0205 263

<0.011 0205 0213 350

<0.008 0213 0220 309

<0.009 0220 0226 250

<0.012 0226 0307 390

<0.008 0307 0313 261

<0.008 0313 0321 340

<0.009 0321 0326 218

<0.015 0326 0402 302

<0.009 0402 0409 305

<0.005 0409 0415 247

<0.013 0415 0422 317

<0.006 0422 0429 298

<0.010 0429 0507 335

<0.008 0507 0513 260

<0.010 0513 0520 294

<0.010 0520 0528 340

<0.004 0528 0604 303

<0.009 0604 0611 293

<0.005 0611 0618 302

<0.019 0618 0625 286

<0.019 0625 0702 303

<0.019 0702 0709 289

<0.014 0709 0716 303

<0.013 Page C - 31

Wolf Creek Nuclear Operating Corporation Charcoal Filters STATION NUMBER 37 Collection Start Collection Stop Volume 1-131 Activity Date Date M3 (pCVCu.M.)

U071 0723 0730 0806 0813 0820 0827 0903*

0903 0910 0917 0924 1001 1008 1016 1022 1029 1105 1112

• 1119 1125

• 1203 1211

• 1217 1223 U143 0730 0806 0813 0820 0827 0903 0910 0910 0917 0924 1001 1008 1016 1022 1029 1105 1112 1119 1125 1203 1211 1217 1223 1230 zuu 297 303 302 289 306 300 292 292 309 300 293 300 322 254 294 292 292 288 246 333.

347 243 255 289 CU.UU9

<0.022

<0.016

<0.007

<0.014

<0.011

<0.014

<0.007

<0.007

<0.010

<0.018

<0.020

<0.011

<0.012

<0.016

<0.013

<0.012

<0.016

<0.019

<0.024

<0.012

<0.015

<0.023

<0.015

<0.014 Page C-32

Wolf Creek Nuclear Operating Corporation Charcoal Filters STATION NUMBER 40 Collection Start Collection Stop Volume.

1-131 Activity Date Date M3 (pCUCu.M.)

n4f

^4flO U IUC 0108

'0115 0124 0130 0205 0213 0220 0226 0307 0313 0321 0326 0402 0409 0415 0422 0429 0507 0513 0520 0528 0604 0611 0618 0625 0702 0709 uvio 0115 0124 0130 0205 0213 0220 0226 0307 0313 0321 0326 0402 0409 0415 0422 0429 0507 0513 0520 0528 0604 0611 0618 0625 0702 0709 0716 282 370 240 259 347 299 240 388 260 343 218 298 295 239 302 293 318 249 293 335 293 286 296 275 287 285 291

.- V.

1

<0.010

<0.010

<0.017

<0.011

<0.008

<0.009

<0.012

<0.008

<0.008

<0.009

<0.015

<0.009

<0.005

<0.013

<0.007

<0.010

<0.009

<0.010

<0.011

<0.004

<0.010

<0.005

<0.020

<0.020

<0.020

<0.014

<0.014 Page C-33

Wolf Creek Nuclear Operating Corporation Charcoal Filters STATION NUMBER 40 Collection Start Collection Stop Volume 1-131 Activity Date Date M3 (pClCu.M.)

0716 0723 0730 0806 0813 0820 0827 0903 0910 0917 0924 0723 0730 0806 0813 0820 0827 0903 0910 0917 0924 1001 270 289 296 297 291 316 296 289 302 295 291

<0.010

<0.023

<0.016

<0.007

<0.014

<0.010

<0.014

<0.007

<0.010

<0.018

<0.020 Page C - 34

Wolf Creek Nuclear Operating Corporation Charcoal Filters STATION NUMBER 48 Collection Start Collection Stop Volume 1-131 Activity Date Date M3 (pClICu.M.)

0102 0108 264

<0.011 0108 0115 299

<0.009 0115 0124 380

<0.010 0124 0130 232

<0.018 0130 0205 250

<0.012 0205 0213 331

<0.008 0213 0220 279

<0.010 0220 0226 245

<0.012 0226 0307 364

<0.009 0307 0313 255

<0.008 0313 0321 343

<0.009 0321 0326 218

<0.015 0326 0402..

292

<0.009 0402 0409 300

<0.005 0409 0415 237

<0.013 0415 0422 300

<0.007 0422 0429 300

<0.010 0429 0507 336

<0.008 0507 0513 255

<0.010 0513 0520 278

<0.011 0520 0528 336

<0.004 0528 0604 292

<0.010 0604 0611 302

<0.004 0611 0618 306

<0.019 0618 0625 275

<0.020 0625 0702 283

<0.020 0702 0709 286

<0.014 0709 0716 296

<0.014 Page C - 35

Wolf Creek Nuclear Operating Corporation Charcoal Filters STATION NUMBER 48 Collection Start Collection Stop Volume 1-131 Activity Date Date M 3 (pC/Cu.M.)

0716 0723 0730 0806 0813 0820 0827 0903 0910 0917 0924 1001 1008 1016 1022.

1029 1105 1112 1119 1125 1203 1211 1217 1223 0723 0730 0806 0813 0820 0827 0903 0910 0917 0924 I 001 1008 1016 1022 1029 1105 1112 1119 1125 1203 1211 1217 1223 1230 265 288 291 302 301 300 293 285 296 302 286 292 328 249 284 284 286 281 249 324 305.

239 252 282

<0.010

<0.023

<0.017

<0.007

<0.013

<0.011

<0.014

<0.008

<0.01 1

<0.018

<0.021

<0.012

<0.012

<0.016

<0.013

<0.013

<0.017

<0.019

<0.024

<0.012

<0.017

<0.024

<0.015

<0.014 Page C - 36

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Surface Water (pCi/Liter).

STATION NUMBER DC Gamma Spectrum and Tritium Analysis SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140.

H-3 0130

<2.8

<3.0

<3.9

<2.4

<4.2

<1.8

<2.8

<2.9

<3.2

<3.8 13599+-334 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0220

<3.7

<3.0

<7.9

<3.1

<5.6

<6.5

<9.6

<5.6

<3.9

<3.3 14233+-330 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0320

<2.9

<4.2

<8.1

<3.3

<3.2

<4.2

<5.6

<4.8

<4.9

<4.3 13543+-329 Page C -37

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Surface Water (pCi/Liter)

STATION NUMBER DC Gamma Spectrum and Tritium Analysis SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0417

<2.6

<3.6

<3.6.

<3.0

<3.1

<1.8

<4.4

<2.6

<3.7

<3.4 12858+-321 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 1H-3 0515

<3.7

<2.5

<4.2

<2.9

<4.7

<3.5

<13.6

<3.2

<4.5

<5.5 13996+-321 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0619

<3.3

<2.8

<5.5

<2.3

<6.9

<3.5

<8.0

<3.9

<4.7

<3.8 11409+-305 Page C - 38

Wolf Creek Nuclear Operating Corporation Exposure Pathway -Waterborne Surface Water (pCi/Liter)

STATION NUMBER DC Gamma Spectrum and Tritium Analysis SURFACF WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0717

<2.8

<2.7

<7.9

<3.3

<3.0

<2.9

<6.8

<4.5

<3.1

<6.8 13040+-326 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-I3 0821

<1.2

<2.1

<3.6

<1.3

<3.2

<2.3

<2.9

<2.2

<1.9

<3.1 26793+-458 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0918

<3.0

<3.3

<5.8

<2.2

<6.7

<4.4

<5.8

<3.1

<4.1

<3.5 16721+-374 Page C-39

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Surface Water (pCi/Liter)

STATION NUMBER DC Gamma Spectrum and Tritium Analysis SURFACE WATER MN-54 CO-58 FE-59 C0-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 1016

<4.0

<3.6

<11.0

<6.3

<6.4

<4.9

<10.6

<5.7

<3.9

<7.4 17551+-385 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR.95 1-131 CS-134 CS-137 BA-140

.-3 1120

<3.0

<3.4

<4.5

<1.9

<5.0

<3.0

<6.6

<3.4

<3.7

<2.2 17087+-373 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 1219

<4.4

<2.7

<6.4

<4.8

<14.6

<3.6

<6.5

<4.1

<5.1

<6.9 16699+-377 Page C - 40

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Surface Water (pCi/Liter).

STATION NUMBER JRR Gamma Spectrum and Tritium Analysis SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140-H-3 0619

<4.0

<3.2

<5.6

<5.0

<4.1

<4.2

<8.9 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 0717

<2.9

<1.8

<4.5

<1.6

<2.1

<2.9 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 1-3 0821

<1.4

<1.9

<2.5

<1.3

<3.1

<1.6

<3.2

<1.9

<1.2

<3.1

<157

<3.4

<6.4

<3.3

<163 CS-134 CS-137 BA-140 H-3

<6.2

<2.5

<2.6

<3.0

<158 Page C - 41

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Surface Water (pCi/Liter)

STATION NUMBER JRR Gamma Spectrum and Tritium Analysis SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0918

<3.5

<5.0

<3.9

<5.0

<8.6

<3.3

<6.7

<3.9.

<4.8

'6.5

<166 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 1016

<4.7

<4.3

<4.7

<3.9

'4.9

<3.6

<6.6

<5.6

<3.3

<3.5

<162 SURFACE WVATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 1120

<2.5

<1.3

<4.6

<2.2

<4.9

<3.3

<4.8

<2.3

<2.5

<2.5

<157 Page C - 42

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Surface Water (pCi/Liter).

STATION NUMBER JRR Gamma Spectrum and Tritium Analysis SURFACE VATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 1219

<2.0

<1.6

<4.6

<2.4

<2.5

<3.1

<5.3 QSURFACE WATER DUP MN-54 CO-58 FE-59 CO-60

. ZN-65 ZR-95 1-131 CS-134.

CS-137 BA-140 H-3 1016

<4.8

<3.4

<7.4

<4.1

<4.7

<3.8

<8.7

<4.1

<5.8

<3.5

<162

<3.6

<3.0

<3.0

<169 Page C - 43

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Surface Water (pCi/Liter)

STATION NUMBER MUSH Gamma Spectrum and Tritium Analysis SURFACE WATER MN-54 CO-58 FE-59 C0-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0130

<3.5

<1.4

<3.8

<4.4

<2.9

<3.0

<5.1

<5.6.

<4.4

<3.2

<160 SURFACE NVATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 0220

<3.0

<1.7

<5.0

<4.6

<4.2

<3.5

<6.7

<1.8

<3.9

<5.9

<136 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0320

<2.8

<3.9

<3.9

<4.9

<5.1

<3.0

<7.0

<2.6

<5.1

<4.3

<161 H-3 Page C - 44

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Surface Water (pCi/Liter)

STATION NUMBER MUSH Gamma Spectrum and Tritium Analysis SURFACE WATER MN-54 CO-58 FE-59 C060 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0417

<4.2

<2.8

<5.4

<4.5

<3.9

<4.3

<6.4

<4.0

<3.3.

<3.7

<156 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0515

<4.5

<5.4

<6.1

<2.9

<5.1

<2.8

<18.4

<5.6

<5.0

<5.1

<128 Page C - 45

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Surface Water (pCi/Liter)

STATION NUMBER SP Gamma Spectrum and Tritium Analysis SURFACE WATER MN-54 CO-58 FE-59 C0-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0130

<5.0

<3.3

<8.5

<5.6

<7.6

<4.2

<7.8

<4.6.

<5.3

<3.9 14300+-342 SURFACE WVATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0220

<5.2

<3.9

<5.8

<3.7

<8.9

<7.3

<8.4

<6.7

<4.5

<8.2 13377+-320 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H13 0320

<5.5

<2.3

<2.9

<3.5

<4.4

<3.6

<7.7

<3.4

<4.1

<8.8 13679+-331 Page C - 46

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Surface Water (pCi/Liter).

STATION NUMBER SP Gamma Spectrum and Tritium Analysis SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140.

H-3 0417

<1.7

<2.2

<2.2

<2.2

<3.7

<i.5

<4.0

<1.9

<2.5

<3.7 12954+-322 SURFACE WVATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0515

<2.6

<3.8

<2.9

<2.1

<2.9

<3.4

<8.9

<2.5

<1.9

<4.7 12372+-303 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 11-3 0619

<2.4

<1.3

<6.1

<2.9

<5.3

<3.2

<4.2

<3.5

<3.5

<2.6 11394+-305 Page C - 47

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Surface Water (pCi/Liter)

STATION NUMBER SP Gamma Spectrum and Tritium Analysis SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0717

<2.3

<2.3

<3.7

<3.0

<4.9

<3.2

<9.3

<2.7

<3.2

<4.5 12960+-325 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 11-3 0821

<1.4

<1.2

<4.4

<1.6

<2.5

<1.3

<4.2

<2.4

<2.6

<0.9 14720+-344 SURFACE WATER MN-54 CO-58 FE-59 CO.60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 0918

<3.0

<2.5

<3.5

<1.4

<5.3

<2.8

<5.7

<2.7

<2.6

<3.5 16308+-369 Page C - 48

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterbome Surface Water (pCi/Liter)

STATION NUMBER SP Gamma Spectrum and Tritium Analysis SURFACF WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131

.CS-134 CS-137 BA-140 H-3 1016

<3.7

<4.5

<6.8

<4.2

<5.0

<3.9

<8.3

<3.3.

<2.8

<6.5 16192+-370 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 1120

<4.8

<4.7

<7.6

<3.8

<9.2

<3.6

<8.4

<5.9

<3.4

<2.9 16419+-366 SURFACE WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 BA-140 H-3 1219

<4.9

<4.6

<11.5

<5.5

<6.8

<5.7

<8.8

<3.9

<3.8

<5.2 17277+-383 Page C - 49

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Surface Water (pCi/Liter)

STATION NUMBER SP Gamma Spectrum and Tritium Analysis SURFACE WATER DUP 0320 MN-54

<2.9 CO-58

<1.9 FE-59

<3.5 CO-60

<2.7 ZN-65

<2.0 ZR-95

<4.5 1-131

<4.9 CS-134

<3.8 CS-137

<2.6 BA-140.

<3.3 H-3 14117+-237 Page C - 50

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER B-12 Gamma Spectrum Analysis GROUND) WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0226

<5.7

<5.5

<6.1

<3.3

<8.4

<6.1

<6.8

<6.6

<7.6 GROUND WATER MN.54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0515

<2.4

<2.6

<3.0

<1.4

<3.5

<3.0

<1.6

<2.9

<2.1 GROUND WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0821

<3.8

<3.0

<5.7

<2.1

<5.7

<3.0

<2.6

<5.5

<3.3 Page C-51

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER B-12 Gamma Spectrum Analysis GROUND WATER 1112 MN-54

<1.8 CO-58

<2.4 FE-59

<3.7 CO-60

<3.1 ZN-65

<5.6 ZR-95

<3.9 CS-134

<3.9 CS-137

<3.5 BA-140

<3.0 Page C - 52

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER C-10 Gamma Spectrum Analysis GROUND WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0226

<6.2

<6.2

<7.8

<4.5

<9.2

<5.8

<6.3

<4.2

<7.4 GROUND WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0515

<2.1

<1.3

<4.3

<2.1

<3.8

<1.9

<2.2

<2.2

<1.6 GROUND WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0821

<5.9

<4.8

<7.6

<2.5

<6.6

<4.0

<4.7

<5.5

<7.0 Page C - 53

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER C-10 Gamma Spectrum Analysis GROUND WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 1112

<2.5

<2.2

<5.7

<3.2

<3.4

<3.4

<1.9

<2.2

<1.6

• GROUND WATER DUP MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95

• CS-134 CS-137 BA-140 1112

<5.1

<5.2

<3.9

<4.4

<12.2

<4.2

<4.9

<5.6

<5.8 Page C - 54

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER C-49 Gamma Spectrum Analysis GROUND WATER MN-54 0226

<3.2 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140

<2.5

<5.7

<2.7

<5.4

<3.1

<3.2

<2.2

<3.9 GROUND WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0515

<3.1

<4.2

<5.3

<4.7

<8.0

<5.1

<3.4

<4.8

<5.1 GROUND WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0821

<4.6

<2.2

<8.7

<2.7

<6.7

<2.9

<2.8

<5.3

<6.4 Page C - 55

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER C49 Gamma Spectrum Analysis GROUND WATER 1112 MN-54

<4.3 CO-58

<4.2 FE-59

<5.7 CO-60

<4.0 ZN-65

<4.9 ZR-95

<3.8 CS-134

<4.4 CS-137

<2.8 BA-140

<4.0 Page C-56

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER D-65 Gamma Spectrum Analysis GROUND WATER 0307 MN-54

<5.8 C0-58

<3.1 FE-59

<6.1 C0-60

<4.0 ZN-65

<6.8 ZR-95

<6.8 CS-134

<4.6 CS-137

<3.9 BA-140

<7.6 Page C - 57

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

- STATION NUMBER J-1 Gamma Spectrum Analysis

• GROUND WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137

• BA-140 0515

<4.2

<2.3

<5.0

<3.7

<4.0

<2.7

<5.3

<4.6

<3.8 GROUND WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0820

<3.1

<2.5

<2.9

<1.6

<3.0

<3.2

<1.9

<3.5

<3.9 GROUND WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 1112

<7.2

<6.2

<10.1

<3.6

<3.5

<7.1

<6.7

<5.7

<8.6 Page C - 58

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER L49 Gamma Spectrum Analysis GROUND WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0226

<2.6

<4.0

<7.5

<4.3

<9.7

<3.3

<1.9

<6.1

<4.9 GROUND WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0515

<3.7

<4.4

<3.7

<3.8

<7.6

<3.4

<2.9

<5.8

<4.4 GROUND WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0821

<2.4

<3.1

<5.3

<2.9

<7.1

<2.8

<2.8

<2.0

<2.3 Page C - 59

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter).

STATION NUMBER L-49 Gamma Spectrum Analysis GROUND WATER 1112 MN-54

<3.5 CO-8

<2.9 FE-59

<6.1 CO-60

<2.4 ZN-65

<4.1 ZR-95

<3.5 CS-134

<5.3 CS-137

<5.6 BA-140

<3.7 Page C - 60

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER B-12 Tritium Analysis Collection Date:

11-3 0226

<130 0515

<128 0821

<157 1112

<162

• Duplicate Page C - 61

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER C-10 Tritium Analysis Collection Date:

H-3 0226

<130 0515

<128 0821

<157 1112*

<162 1112

<162

• Duplicate Page C - 62

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER C49 Tritium Analysis Collection Date:

H-3 0226

<130 0515

<128 0821

<157 1112

<162 Page C - 63

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER D-65 Tritium Analysis Collection Date:

H-3 0307

<160.

Page C -64

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER J-I Tritium Analysis Collection Date:

H-3 0515

<128 0820

<157 1112

<162 Page C - 65

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER L49 Tritium Analysis Collection Date:

H-3 0226

<130 0515

<128 0821

<157 1112

<162

• Duplicate Page C - 66

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER B-12 Radiochernical Analysis Collection Date:

1-131 0226

<0.3 0515

<0.3 0821

<0.3 1112

<0.4

• Duplicate Page C - 67

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Ground Water (pCi/Liter)

STATION NUMBER C-10 Radiochemical Analysis Collection Date:

1-131 0226

<0.3 0515

<0.5 0821

<0.4 1112*

<0.4 1112

<0.4

• Duplicate Page C - 68

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterbome Ground Water (pCi/Liter).

STATION NUMBER C49 Radiochemical Analysis Collection Date 1-131 0226

<0.4 0515

<0.5 0821

<0.3 1112

<0.4 Page C - 69

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterbome Ground Water (pCi/Liter)

STATION NUMBER D-65 Radiochemical Analysis Collection Date 1-131 0307

<0.4 Page C -70

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterbome Ground Water (pCi/Liter)

STATION NUMBER 3-1 Radiochenical Analysis Collection Date 1-131 0515

<0.4 0820

<0.4 1112

<0.2 Page C -71

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterbome Ground Water (pCi/Liter)

STATION NUMBER L49 Radiochemical Analysis Collection Date:

1-131 0226

<0.3 0515

<0.4 0821

<0.4 1112

<0.3

• Duplicate Page C - 72

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter)

STATION NUMBER BW15 Gamma Spectrum Analysis DRINKING WATER 0103 MN-54

<3.5 C0-58

<5.0 FE-59

<6.6 CO-60

<3.7 ZN-65

<4.8 ZR-95

<6.8 CS-134

<5.4 CS-137

<5.5 BA-140

<6.1 1 0205 DRINKING WATER 0205

/ 0307 MN-54

<4.7 C0-58

<4.4 FE-59

<6.2 CO-60

<6.3 ZN-65

<6.9 ZR-95

<6.6

• CS-134

<5.6 CS-137

<6.2 BA-140

<3.5 DRINKING WATER 0307

/ 0402 MN-54

<5.8 C0-58

<3.9 FE-59

<3.3 C0-60

<4.2 ZN-65

<4.5 ZR-95

<6.2 CS-134

<5.0 CS-137

<4.2 BA-140

<3.3 Page C - 73

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter)

STATION NUMBER BW15 Gamma Spectrum Analysis DRINKING WATER 0402 MN-54

<1.9 CQ-58

<1.2 FE-59

<3.9 CO-60

<2.4 ZN-65

<2.9 ZR-95

<1.9 CS-134

<1.6 CS-137

<2.7 BA-140

<0.9

/ 0506 DRINKING WATER 0506

/ 0604 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140

<3.4

<4.7

<8.2

<3.5

<5.2

<2.8

• <4.9

<4.9

<3.2 DRINKING WATER 0604

/ 0702 MN.54

<5.8 CO-58

<4.1 FE-59

<6.5 CO-60

<5.1 ZN-65

<3.1 ZR-95

<3.2 CS-134

<4.1 CS-137

<2.8 BA-140

<5.7 Page C - 74

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter)

STATION NUMBER BWI5 Gamma Spectrum Analysis

• DRINKING WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0702

<2.3

<2.4

<3.7

<2.6

<2.8

<1.9

<2.6

<2.9

<1.6 I 0806 DRINKING WATER MN-54 CO.58 FE-59 C0-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0806

/ 0903

<2.8

<1.5

<4.1

<2.1

<3.0

<2.4

<3.7

<1.8

<2.1 DRINKING WATER 0903

/ 1001 MN-54

- <3.4 C0-58

<2.8 FE-59

<8.3 0.-60

<2.3 ZN-65

<7.3 ZR-95

<3.4 CS-134

<4.5 CS-137

<5.0 BA-140

<3.8 Page C - 75

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter)

STATION NUMBER BW15 Gamma Spectrum Analysis DRINKING WATER 1001

/ 1105 MN-54

<3.3 CO-58

<2.3 FE-59

<6.0 CO-60

<2.9 ZN-65

<2.4 ZR-95

<3.8 CS-134

<3.8 CS-137

<2.9 BA-140

<1.6 DRINKING WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-i 37 BA-140 1105 1203

<3.3

<2.9

<4.7

<1.3

<3.8

<2.8

<3.6

<2.5

<1.8 DRINKING WATER 1203

/ 0107 MN-54

<5.2 CO-58

<2.9 FE-59

<8.6 CO-60

<3.1 ZN-65

<7.6 ZR-95

<4.0 CS-134

<8.1 CS-137

<7.5 BA-140

<6.3 Page C-76

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter)

STATION NUMBER LW40 Gamma Spectrum Analysis DRINKING WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0102

/ 0205

<3.2

<3.9

<5.3

<4.9

<8.0

<5.2

<3.9

<4.2

<3.6 DRINKING WVATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 020

./ 0307

<1.7

<3.4

<8.0

<4.0

<5.3

<4.3

<5.2

<5.9

<4.9 DRINKING NVATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-I34 CS-137 BA-140 0307

/ 0402

<2.4

<3.6

<5.7

<4.6

<8.3

<3.3

<1.8

<4.9

<5.5 Page C-77

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter)

STATION NUMBER LW40 Gamma Spectrum Analysis DRINKING WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0402

/ 0506

<2.4

<2.0

<4.4

<2.2

<2.4

<2.1

• <2.1

<2.1

<2.9 DRINKING WVATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0506

/ 0604

<4.4

<2.5

<7.3

<4.7 DRINKING TATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0604

/ 0702

<2.5

<3.5

<2.8

<1.9

<3.0

<2.6

<2.1

<2.0

<2.9

<4.1

<7.3

<3.1

<4.1 Page C - 78

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter)

STATION NUMBER LW40 Gamnma Spectrum Analysis DRINKING WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0702

/ 0806

<2.6

<1.5

<4.1

<2.5

<6.0

<3.2

<2.4

<1.9

<4.7 DRINKING WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0806

/ 0903 DRINKING WATER

<3.3 MN-54

<4.5 CO-58

<4.8 FE-59

<4.4 CO-60

<5.1 ZN-65

<5.2 ZR-95

<5.5 CS-134

<5.3 CS-137

<4.0 BA-140 0903

<3.6

/ 1ool

<3.7

<10.2

<5.3

<7.0

<3.1

<2.4

<6.7 Page C - 79

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter)

STATION NUMBER LW40 Gamma Spectrum Analysis DRINKING WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 1001

/ 1105

<1.9

<1.4

<5.7

<2.9

<3.4

<2.4

<3.3

<2.9

<2.5 DRINKING WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 1105

/ 1203

<4.7

<3.0

<5.3

<4.6

<6.1

<2.7

<6.9

<3.6

<6.0 DRINKING WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 1203

<5.7

<4.9

<9.8

/ 0107

<6.2

<3.5

<3.1

<5.6

<3.7.

<6.7 Page C - 80

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter)

STATION NUMBER NFDW Gamma Spectrum Analysis DRINKING WATER MN-54 CO-58 FE.59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0102

<2.6

<2.4

<4.7

<2.3

<2.3

<2.7

/ 0205 DRINKING WATER 0205

/ 0307 MN-54

<2.6 CO.58

<3.2 FE-59

<6.8 CO-60

<3.7 ZN-65

<3.0 ZR-95

<1.8 CS-134

<4.4 CS-137

<2.3 1BA-140

<3.5 DRINKING WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0307

• <2.7

<2.5 I 0402

<4.3

<2.8

<3.7

<2.0

<2.7

<3.9

<4.7

<3.1

<2.4

<3.0 Page C - 81

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter)

STATION NUMBER NFDW Gamma Spectrum Analysis DRINKING WATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0402

/ 0506

<2.5

<2.8

<4.6

<5.8

<6.3

<1.9

• <5.0

<4.7

<4.7 DRINKING( WATER 0506

/ 0604 MN-54

<2.7 CO-58

<2.0 FE-59

<5.2 CO-60

<3.3 ZN-65

<3.6 ZR-95

<3.6 CS-134

<3.4 CS-137

<6.0 BA-140

<3.6 DRINKING VATER MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 BA-140 0604

/ 0702

<3.6

<3.0

<9.5

<4.2

<3.7

<2.9

<3.6

<6.4

<5.8 Page C - 82

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter)

STATION NUMBER NFDW Gamma Spectrum Analysis DRINKING WATER 0702 MN-54.

<2.8 CO-58

<2.8 FE-59

<5.0 CO-60

<4.8 ZN-65

<7.2 ZR-95

<4.8 CS-134

<4.9 CS-137

<4.4 BA-140

<4.1

/ 0806 DRINKING WATER 0806

/ 0903 MN-54

<2.7 CO-58

<2.4 FE-59

<6.5 CO-60

<3.1 ZN-65

<3.4 ZR-95

<2.3 CS-134

<2.6 CS-137

<1.9 BA-140

<2.5 DRINKING WATER 0903

/ 1001 MN-54

<2.2 CO-58

<2.9 FE-59

<4.3 CO-60

<2.0 ZN-65

<6.7 ZR-95

<3.7 CS-134

<2.8 CS-137

<3.8 BA-140

<3.0 Page C - 83

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter)

STATION NUMBER NFDW Gamma Spectrum Analysis DRINKING WATER 1001

/ 1105 MN-54

<3.1 CO-58

<5.6 FE-59

<7.4 CO-60

<6.1 ZN-65

<6.0 ZR-95.

<6.2 CS-134

<4.6 CS-137

<6.1

'BA-140

<3.3 DRINKING WATER 1105 MN-54

<3.3 CO-58

<3.3 FE-59

<6.4 CO-60

<3.2 ZN-65

<4.1 ZR-95

<3.5 CS-134

<4.8 CS-137

<4.8 BA-140

<3.4

/ 1203 DRINKING WATER 1203

/ 0107 MN-54

<1.9 CO-58

<2.1 FE-59

<3.9 CO-60

<4.5 ZN-65

<5.0 ZR-95

<3.3 CS-134

<2.6 CS-137

<4.8 BA-140

<3.9 Page C - 84

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter)

STATION NUMBER BWl5 Radiochemical Analysis Start Date:

Stop Date:

GR-B 0103 0205 5.5+-l..

0205 0307 5.5+-1.2 0307 0402 4.0+-1.2 0402 0506 5.0+-1.2 0506 0604 5.7+-1.2 0604 0702 4.8+-1.3 0702 0806 5.0+-1.3 0806 0903 4.4+-1.0 0903 1001 4.9+-1.2 1001 1105 5.2+-I.1 1105 1203 3.5+-1.0 1203 0107 4.1+-I.1

• Duplicate Page C - 85

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborme Drinking Water (pCi/Liter)

STATION NUMBER LW40 Radiochemical Analysis Start Date:

Stop-Date:

GR-B 0102 0205 5.6+-1.1 0205 0307 4.6+-1.2 0307 0402 5.0+-1.3 0402 0506 3.8+-1.2 0506 0604 3.7+-.1.

0604 0702 3.3+-l.l 0702 0806 4.4+-1.2 0806 0903 5.3+-1.1 0903 1001 4.2+-1.2 1001 1105 4.0+4-1.0 1105 1203 3.9+41.0 1203 0107 3.7+-1.2

• Duplicate Page C - 86

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter).

STATION NUMBER NFDW Radiochemical Analysis Start Date:

Stop Date:

GR-B 0102 0205 5.3+-1.1 0205 0307 6.8+-1.4 0307 0402 7.8+-1.3 0402 0506 4.1+-1.1 0506 0604 4.0+-1.1 0604 0702 5.5+-1.2 0702 0806 4.3+-1.1 0806 0903 5.4+-1.1 0903 1001 4.4+-1.2 1001 1105 4.5+-1.0 1105 1203 3.1+-0.9 1203 0107 3.8+-1.1

• Duplicate, Page C -87

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCilLiter)

STATION NUMBER BWI5 Tritium Analysis Start Date:

Stop Date:

H-3 0103 0402

<157 0402 0702

<158 0702 1001

<159 1001 0107

<165 Page C - 88

Wolf Creek Nuclear Operating Corporation Exposure Pathway -Waterborne Drinking Water (pCi/Liter).

STATION NUMBER LW40 Tritiumn Analysis Start Date:

Stop Date:

H-3 0102 0402

<157 0402 0702

<158 0702*

1001

<159 0702 1001

<159 1001 0107

<165

• Duplicate Page C - 89

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter)

STATION NUMBER NFDW Tritium Analysis Start Date:

Stop Date:

H-3 0102 0402

<157 0402 0702 c158 0702 1001

<159 1001 0107

<165 Page C -90

Wolf Creek Nuclear Operating Corporation Exposure Pathway -Waterbome Drinking Water (pCi/Liter)

STATION NUMBER BW15 Radiochemical Analysis Start Date:

Stop Date:

1-131 0103 0205

<0.4 0205 0307

<0.4 0307 0402

<0.3 0402 0506

<0.3 0506 0604

<0.3 0604 0702

<0.3 0702 0806

<0.3 0806 0903

<0.2 0903 1001

<0.4 1001 1105

<0.5 1105 1203

<0.3 1203 0107

<0.3

• Duplicatc Page C - 91

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterbome Drinking Water (pCi/Liter)

STATION NUMBER LW40 Radiochemical Analysis Start Date:

Stop Date:

1-131 0102 0205

<0.4 0205 0307

<0.4 0307 0402

<0.3 0402 0506

<0.3 0506 0604

<0.4 0604 0702

<0.4 0702 0806

<0.3 0806 0903

<0.3 0903 1001

<0.4 1001 1105

<0.3 1105 1203

<0.3 1203 0107

<0.3

• Duplicate Page C - 92

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Drinking Water (pCi/Liter)

STATION NUMBER NFDW Radiochemical Analysis Start Date:

Stop Date:

1-131 0102 0205.

<0.4 0205 0307

<0.3 0307 0402

<0.2 0402 0506

<0.3 0506 0604

<0.4 0604 0702

<0.4.

0702 0806

<0.4 0806 0903

<0.2 0903 1001

<0.4 1001 1105

<0.3 1105 1203

<0.3 1203 0107

<0.4

• Duplicate Page C - 93

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Shoreline Sediment (pCi/KG DRY)

STATION NUMBER DC Gamma Spectrum Analysis 0612 SHORELINE SEDINIENT K-40 10890.0+-811.0 MN-54

<27.5 CO-58

<35.7 FE-59

<51.1 CO-60

<18.1 ZN-65

<72.3 CS-134

<51.9 CS-137

<34.3 1119 S11ORELINE SEDINEFNT K-40 11677.0+-921.2 MN-54

<40.5 CO-58

<38.0 FE-59

<80.5 CO-60

<44.1 ZN-65

<114.7 CS-134

<56.0 CS-137

<43.5 Page C - 94

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Shoreline Sediment (pCi/KG DRY)

STATION NUMBER EEA Gamma Spectrum Analysis 0624 SHORELINE SEDIMENT K-40 11321.0+-1077.0 MN-54

<43.5 CO.58

<37.0 FE-59

<79.3 CO-60

<23.1 ZN-65

< 117.1 CS-134

<59.0 CS-137 144.1+-58.1 Page C - 95

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Shoreline Sediment (pCi/KG DRY)

STATION NUMBER JRR Gamma Spectrum Analysis 0630 SHORELINE SEDIMENT K-40 1 1960.0+-987.7 MN-54

<35.7 CO-58

<59.0 FE-59

<80.5 CO-60

<37.4 ZN-65

<82.5 CS-134

<57.9 CS-137

<36.7 1111 SHIORELINF. SEDIMENT K-40 4565.7+463.3 MN-54

<23.6 CO-58

<24.5 FE-59

<44.6 CO-60

<22.2 ZN-65

<62.4 CS-134

<35.0 CS-137

<28.0.

Page C - 96

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Waterborne Shoreline Sediment

.(pCi/KG DRY)

-STATIONNUMBER.MUDS Gamma Spectrum Analysis SHORELINE SEDIMENT 0612 K-40 10623.0+4-886.4 MN-54

<29.6 CO-58

<28.3 FE-59

<84.3 CO-60

<24.3 ZN-65

<59.8 CS-134

<48.0 CS-137

<29.8 Page C - 97

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Fish (pCi/KG WET)

STATION NUMBER JRR Gamma Spectrum and Tritium Analysis CHANNEL CATFISH K-40 MN-54 C-5s8 FE-59 CO-60 ZN-65 CS-I34 CS-137 H-3 0612 2734.5+-354.1

<10.3

<8.8

<16.6

<10.0

<18.4

<14.3

<16.3

<1 12 CHANNEL CATFISH K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 H-3 1Ill 3220.5+-347.8

<7.9

<9.9

<30.8

<9.4

<16.4

<16.2

<13.2

<88 Page C - 98

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Fish (pCi/KG WET)

STATION NUMBER JRR Gamma Spectrum and Tritium Analysis COMMON CARP K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 -

CS-137 H-3 0612 3118.8+-430.3

<12.0

<17.4

<29.0

<7.9

<18.3

<12.9

<18.7

<118 COMMON CARP K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 H-3 1111 3266.1+-424.3

<13.6

<20.4

<24.6

<14.4

<28.9

<10.4

<10.7.

<128 LIM BASS K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 H-3 0612 3045.0+-272.6

<6.0

<7.8

<9.4

<5.2

<18.1

<9.1

<8.6

<95 Page C-99

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Fish (pCi/KG WET)

STATION NUMBER JRR Gamma Spectrum and Tritium Analysis WHITE CRAPPIE K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 H-3 Illt 381 6.3+-474.2

<14.1

<11.0

<39.0

<13.7

<28.0

<19.6

<8.8

<129 Page C-100

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Fish (pCi/KG WET)

STATION NUMBER WCL Gamma Spectrum and Tritium Analysis CHANNEL CATFISH K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 H-3 0729 3488.7+-405.0

<13.5

<16.3

<28.8

<13.6

<24.3

<15.1

<11..9 9267+-239 CHANNEL CATFISH K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 H-3 1021 2633.4+-588.1

<22.6

<14.6

<32.6

<21.6

<28.2

<24.8

<20.0 7995.0+-188.0 COMMON CARP K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 H-3 0729 2911.5+-345.7

<11.4

<16.6

<37.0

<7.8

<28.0

<7.8

<8.2 6463+-171 Page C - 101

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Fish (pCi/KG WET)

STATION NUMBER WCL Gamma Spectrum and Tritium Analysis FLATHEAD CATFISH K-40 MN-54 CO-58 FE-S9 CO-60 ZN-65 CS-134 CS-137 H-3 0729 3013.0+-305.9

<12.7

<14.8

<29.1

<9.7

<20.4

<7.8

<11.8 6799+- 176 SMI BASS K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 H-3 0729 3101.6+-362.1

<7.1

<9.4

<40.8

<13.9

<20.7

<12.5

<14.6 5852+-161 SM1 BUFFALO K40 MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 11-3 1021 2504.8+-395.1

<10.5

<8.8

<9.8

<13.0

<14.2

<15.9

<10.8 10069.0+-224.0 Page C - 102

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Fish (pCi/KG WET)

STATION NUMBER WCL Gamma Spectrum and Tritiumn Analysis WALLEYE.

K40 MN-54 C0-58 FE-59 CO-60 ZN-65 CS-134 CS-137 H-3 1021 3725.8+-344.7

<5.8

<9.2

<12.6

<9.2

<16.2

<6.6

<8.5 8798.0+-198.0 WIIITE BASS K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 H-3 1021 3001.9+-534.2

<17.7

<12.4

<25.6

<11.2

<33.3

<23.4

<19.1 11620.0+-234.0 WIIITE CRAPPIE K40 MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 H-3 1021 3637.1+-532.7

<22.8

<15.0

<25.4

<7.6

<25.6

<20.6

<16.3 8911.0+-205.0 Page C-103

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Fish (pCi/KG WET)

STATION NUMBER WCL Gamma Spectrum and Tritium Analysis WIPER 1021 K-40 3080.5+-377.0 MN-54

<12.8 CO-58

<14.7 FE-59

<19.4 CO-60

<12.0 ZN-65

<26.4 CS-134

<16.0

.CS-137

<12.3 H-3 10928.0+-243.0 Page C - 104

0515 BE-7 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 0611 BE-7 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 RHUBARB

<153.8 3248.6+-465.6

<14.4

<15.4

<35.9

<16.1

<29.6

<17.5

<25.3

<17.9

<9.3 RHUBARB

<144.7 2584.8+-395.7

<15.9

<14.3

<21.2

<24.9

<33.6

<16.1

<19.6

<15.2

<14.5 Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Food/Garden Crops (pCi/KG WET)

STATION NUMBER D-l Gamma Spectrum Analysis 0709 RIUBARB BE-7

<127.2 K-40 2880.5+-326.3 MN-54

<9.8 CO-58

<10.8 FE-59

<23.5 CO-60

<7.8 ZN.65

<16.5 ZR-95 1-131 CS-134 CS-137 0820 BE-7 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137

<10.3

<17.7

<9.7

<11.7 RHlBARB 286.3+-130.1 2565.2+-275.2 0910 BE-7 K-40 MN-54 CO-58.

FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 1016 BE-7 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 RlllJIIARB

<138.9 2110.9+-309.7

<10.6

<13.5

<15.4

<10.3

<17.0

<9.4

<17.6

<7.9

<12.3 RHUBARB 306.8+-130.9 4769.8+-482.0

<14.1

<13.1

<17.1

<17.1

<22.1

<7.4

<21.3

<15.7

<14.4

<9.5

<7.7

<16.8

<11.3

<15.7

<7.6

<12.9

<10.3

<9.9 Page C -105

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Food/Garden Crops (pCi/KG WET)

STATION NUMBER D-1 Gamma Spectrum Analysis 1112 RHUBARB BE-7

<277.5 K-40 4782.7+-714.5 MN-54

<20.6 CO-58

<22.9 FE-59

<49.1 CO60

<13.5 ZN-65

<48.8 ZR-95

<17.7 1-131

<39.7 CS-134

<13.2 CS-137

<18.6 Page C. 106

0611 BE-7.

K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 0709 BE-7 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 CABBAGE

<146.0 2618.8+-350.0

<10.9

<11.2

<22.4

<8.5

<22.7

<10.7

<15.8

<11.2

<12.1 CABBAGE

<144.2 2292.9+-311.8

<12.0

<6.1

<15.7

<8.8

<24.6

<8.7

<13.1

<16.5

<11.1 Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Food/Garden Crops (pCi/KG WET)

STATION NUMBER G-1 Gamma Spectrum Analysis 0820 TURNIP GREENS BE-7

<194.9 K-40 4652.5+-588.5 MN-54

<21.4 CO-58

<10.9 FE-59

<26.6 CO-60

<17.2 ZN-65

<26.6 ZR.95

<19.4 1-131

<35.7 CS-134

<27.5 CS-137

<17.5 0910 TURNIP GREENS BE-7

<179.0 K-40 4899.8+-504.1 MN-54

<17.0 CO-58

<7.4 FE-59

<19.4 CO-60

<16.7 ZN-65

<27.2 ZR-95

<13.0 1-131

<31.4 CS-134

<14.3 CS-137

<16.7 Page C - 107

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Food/Garden Crops (pCi/KG WET)

STATION NUMBER G-1 (Duplications)

Gamma Spectrum Analysis 0611 CABBAGE DUP BE-7

<169.4 K-40 3173.6+-576.5 MN-54

<12.4 CO-58

<15.9 FE-59

<51.3 CO-60

<8.2 ZN-65

<34.6 ZR-95

<17.5 1-131

<37.5 CS-134

<15.4 CS-137

<13.6 0820 TURNIP GREENS DUP BE-7

<241.6 K-40 4462.4+-610.6 MN-54

<17.2 CO-58

<12.8 FE-59

<30.9 CO-60

<21.4 ZN-65

<60.2 ZR-95

<13.2 1-131

<24.8 CS-134

<16.0 CS-137

<24.5 Page C - 108

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Food/Garden Crops.

(pCi/KG WET)

STATION NUMBER H-I Gamma Spectrum Analysis 0611 LETTUCE BE-7.

<162.9 K-40 3465.6+-373.4 MN-54

<10.4 CO-58

<7.9 FE-59

<17.2 CO-60

<7.8 ZN-65

<2 1.0 ZR-95

<9.6 1-131

<23.4 CS-134

<1 1.2 CS-137

<14.0 Page C - 109

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Food/Garden Crops (pCi/KG WET)

STATION NUMBER N-i Gamma Spectrum Analysis 0611 L.rFUCE BE-7

<149.0 K-40 3369.5+-369.9 MN-54

<10.9 CO-58

<8.9 FE-59

<25.8 CO-60

<11.3 ZN-65.

<25.3 ZR-95

<8.6 1-131

<24.1 CS-134

<12.8 CS-137

<12.3 0820 SOIUASII L.EAVES BE-7

<262.6 K-40 4026.7+-609.2 MN-54

<21.6 CO-58

<18.7.

FE-59

<22.1 CO-60

<9.5 ZN-65

<52.3 ZR-95

<26.4 1-131

<22.4 CS-134

<19.3 CS-137

<23.4 Page C-O110

0515 BE-7 K-40 MN-54 C0-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 0611 BE-7 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 RHUBARB

<204.1 3642.2+-613.3

<7.4

<1 8.0

<13.8

<21.6

<36.5

<16.5

<28.9

<12.3

<16.6 RHUBARB

<180.2 4155.8+-523.3

<8.2

<9.6

<20.5

<6.8

<52.4

<10.9

<24.5

<II.I

<12.2 Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Food/Garden Crops.

(pCi/KG WET)

STATION NUMBER S4 Gamma Spectrum Analysis 0709 RHUBARB BE-7

<166.9 K-40 2364.7+494.3 MN-54

<13.3 CO-58

<12.7 FE-59

<26.1 CO-60

<14.4 ZN-65

<23.0 ZR-95

<8.8 1-131

<30.1 CS-134

<14.9 CS-137

<14.4 0820 RHUBARB BE-7 282.9+-161.2 K40 2495.6+-342.3 MN-54

<9.9 CO-58

<7.5 FE-59

<14.0 CO-60

<10.7 ZN-65

<15.1 ZR-95

<9.2 1-131

<19.2 CS-134

<12.1 CS-137

<12.4 0910 BE-7 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 1016 BE-7 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 RHUBARB 214.1+-116.3 2831.6+-406.0

<12.5

<13.6

<20.7

<10.5

<27.1

<14.7

<29.7

<16.2

<15.7

• RHUBARB

<272.4 5447.2+-774.5

<23.3

<16.4

<46.1

<18.3

<45.2

<18.8

<38.9

<36.4

<29.6 Page C -Ill

Wolf Creek Nuclear Operating Corporation Exposure Pathway-Ingestion Food/Garden Crops (pCi/KG WET)

STATION NUMBER S4 Gamma Spectrum Analysis 1112 RHUBARB BE-7 379.5+-227.6 K-40 6343.1+-533.4 MN-54

<20.1 CO-58

< 1.3 FE-59

<33.7 CO-60

<12.1 ZN-65

<26.8 ZR-95

<10.8 1-131

<38.1 CS-134

<18.5 CS-137

<9.6 Page C - 112

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Food/Garden Crops (pCi/KG WET)

STATION NUMBER S4 (Duplications)

Gamma Spectrum Analysis 0910 RHUBARB DlP BE-7

<201.7 K-40 3156.1+-408.8 MN-54

<15.6 CO-58

<8.1 FE-59

<12.9 CO-60

<13.2 ZN-65

<20.7 ZR-95

<13.0 1-131

<16.5 CS-134

<14.6 CS-137

<13.4 Page C -113

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Feed and Forage (pCi/KG WET)

STATION NUMBER NR-DI Gamma Spectrum Analysis CORN (IRRIGATED)

BE-7 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 0829

<50.6 2495.9+-247.0

<4.3

<6.7

<6.2

<6.3

<6.0

<6.2

<18.4

<4.0

<5.3 Page C -114

CORN (IRRIGATEDj BE-7 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 SOYBEAN (IRRIGATED)

BE-7 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 1-131 CS-134 CS-137 0829

<65.4 2457.1+-238.4

<3.9

<5.0

<11.4

<4.6

<8.5

<5.5

<16.6

<4.7

<5.6 1022

<90.0 14559.0+454.7

<10.2

<8.1

<23.4

<12.4

<33.5

<7.4

<10.3

<10.3

<10.8 Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Feed and Forage (pCi/KG WET)

STATION NUMBER NR-D2 Gamma Spectrum'Analysis SOYBEAN (IRRIGATED) DUP 1022 BE-7

<149.4 K-40 14696.0+-951.9 MN-54

<13.4 CO-58

<20.1 FE-59

<44.3 CO-60

<17.5 ZN-65

<29.3 ZR-95

<14.1 1-131

<26.2 CS-134

<14.3 CS-137

<22.8 Page C -115

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Feed and Forage (pCi/KG WET)

STATION NUMBER NR-UI Gamma Spectrum Analysis CORN 0829 BE-7

<61.2 K-40 3540.7+-365.6 MN-54

<1 1.8 CO-58

<7.6 FE-59

<16.3 CO-60

<9.6 ZN-65

<25.4 ZR-95

<10.3 1-131

<23.1 CS-134

<5.6 CS-137

<1 1.3 Page C-116

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Aquatic Sediment/Silt (pCi/KG DRY)

STATION NUMBER DC Gamma Spectrum Analysis 0612 BOTTOM SEDIMENT K-40 11506.0+-990.5 MN-54

<40.9 CO-58

<38.2 FE-59

<70.3 CO-60 327.2+-47.1 ZN-65

<67.6 CS-134

<56.8 CS-137 237.1+-44.6 1119 BOTTOM SEDIMENT K-40 14629.0+-756.0 MN-54

<31.2 CO-58

<32.7 FE-59

<83.9 CO-60 358.8+-35.5 ZN-65

<64.5

.CS-134

<46.2 CS-137 310.2+40.7 Page C -117

Wolf Creek Nuclear Operating Corporation Exposure Pathway -Aquatic Sediment/Silt (pCi/KG DRY)

STATION NUMBER EEA Gamma Spectrum Analysis 0624 BOTTOIN SDINIENT K-40 12608.0+-1080.0 MN-54

<38.2 CO-58

<37.5 FE-59

<63.5 CO-60

<42.6 ZN-65

<114.9 CS-134

<54.6 CS-137 69.1+-33.8 Page C -118

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Aquatic Sediment/Silt (pCi/KG DRY)

STATION NUMBER JRR Gamma Spectrum Analysis 0718 BOTTOM SEDIMENT K-40 17294.0+-1039.0 MN-54

<42.7 CO-58

<25.6 FE-59

<102.9 CO-60

<35.5 ZN-65

<63.8 CS-134

<53.5 CS-137 143.0+-52.6 1111 BOTTOM SEDIMENT K-40 14603.0+-977.0 MN-54

<23.8 CO-58

<23.8 FE-59

<24.1 CO-60

<28.2 ZN-65

<56.7 CS-134

<38.2 CS-137 123.6+-52.3 Page C - 119

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Aquatic Sediment/Silt (pCi/KG DRY)

STATION NUMBER MUDS Gamma Spectrum Analysis 0612 BOTTOM SEDIMENT K-40 8981.5+-796.7 MN-54

<36.7 CO-58

<26.9 FE-59

<33.1 CO-60

<35.2 ZN-65

<74.7 CS-134

<48.7 CS-137

<41.4 Page C - 120

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Aquatic Vegetation - Aquatic (pCi/KG WET)

STATION NUMBER EEA Gamma Spectrum Analysis 0623 CATTAIL S BE-7

<222.2 K40 2440.8+-584.6 MN-54

<25.2 CO-58

<12.4 FE-59

<55.9 CO-60

<17.0 ZN-65

<22.8 ZR-95

<22.7 1-131

<37.3 CS-134

<25.4 CS-137

<23.0 Page C -121

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Terrestrial Vegetation - Terrestrial (pCi/KG WET)

STATION NUMBER EEA Gamma Spectrum Analysis 0624 PASTURACE BE-7 865.1+-364.2 K-40 8657.3+-698.0 MN-54

<17.7 CO-58

<17.7 FE-59

<51.6 CO-60

<15.4 ZN-65

<31.4 ZR-95

<25.5 1-131

<49.7 CS-134

<23.9 CS-137

<21.5 Page C -122

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Terrestrial Soil (pCi/KG DRY)

STATION NUMBER EEA Gamma Spectrum Analysis 0623 SOIL K40 10080.0+4851.6 MN-54

<3 1.1 CO-58

<32.5 FE-59

<32.1 CO-60

<28.0 ZN-65

<79.9 CS-134

<54.2 CS-137 187.9+48.2 Page C - 123

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Terrestrial Soil (pCi/KG DRY)

STATION NUMBER MUDS Gamma Spectrum Analysis 0624 SOIL K40 1 1562.0+-855.3 MN-54

<3 1.1 CO-58

<39.1 FE-59

<50.5 CO-60

<12.1 ZN-65

<65.9 CS-134

<51.9 CS-137 153.7+-43.6 Page C-124

Wolf Creek Nuclear Operating Corporation Exposure Pathway - Ingestion Deer (pCi/KG WET)

STATION NUMBER A2.1 Ganuna Spectrum DEER K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 1113 2708.1+-320.2

<10.6

<12.6

<15.7

<9.3

<27.9

<7.8

<12.6

-- IEND --

Page C -125