ML031260648

Annual Radiological Environmental Operating Report, Table of Contents Through Appendix D, Pages D-1 - 100

ML031260648
Person / Time
Site:	Cook
Issue date:	04/30/2003
From:	Jack Giessner Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
References
-RFPFR, AEP:NRC:3691-03
Download: ML031260648 (180)

Text

ATTACHMENT TO AEP:NRC:3691-03 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Indiana Michigan Power Company Donald C. Cook Nuclear Plant RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM JANUARY 1, 2002 - DECEMBER 31, 2002 DOCKET NO. 50-315,50-316 LICENSE NO. DPR-58, DPR-74

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 TABLE OF CONTENTS

1. EXECUTIVE

SUMMARY

..................... t

2. I T O U T O ....................................................................... ....................

2. INTRODUCtION ................. .. 3 2.1 General Plant Site Information.

........... _._. _ 3 2.2 Program Design............................................................ .............................................. ... ....... ..... ........ ... .3 2.3 Monitoring Zones . . ..... 3 2A Pathways Monitored ..... . . . ........... 3 2.5 Descriptions of Monitoring Pathways ................................ 4 2.5.1 Air Sampling .4 2.5.2 Surface Water Sampling .4 2.5.3 Ground Water Sampling .4 2.5.4 Drinking Water Sampling .4 2.5.5 Sediment Sampling .4 2.5.6 Milk Sampling ............

2.5.7 Fish Sampling.5 2.5.8 Food Product Sampling .5 2.5.9 Broad Leaf Vegetation .5 2.5.10 TLD Monitoring .5 2.6 Samples Collected During 2002 . .. .15

3. RADIOLOGICAL DATA

SUMMARY

TABLES . . .16

4. ANALYSIS OF ENVIRONMENTAL RESULTS ....... 44 4.1 Sampling Program Deviations .................................... 44 4.2 Comparison of Achieved LLD with Requirements . ...... 45 43 Results Compared Against Reporting Levels ...........

4A Data Analysis by Media Type . . . ..... 46 4.4.1 Air Particulate ............. ... 46 4.4.2 Airborne Iodine.47 4.4.3 Ground Water (Well) .48 4.4.4 Drinking Water.51 4.4.5 SurfaceWater.51 4.4.6 Sediment.51 ii

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 J 4.4.7 Milk ...................................................... 52 4.4.8 Food Products ...................................................... 52 4.4.9 Fish ...................................................... 52 4.4.10 Gamma Exposure Rate ...................................................... 52

5. OFF-SITE DOSE EQUIVALENT COMMITMENTS . . ........................................

54

6.

SUMMARY

OF REMP, ODCM AND VENDOR CHANGES ...................................... 55

7. REFERENCES .......................................... 58 APPENDIX A SYNOPSIS OF ANALYSIS TECHNIQUES . . . .A-I APPENDIX B LAND USE CENSUS FOR 2002 . . . .B-I APPENDIX C QUALITY ASSURANCE PROGRAM . . . .C-I APPENDIX D 2002 DATA

SUMMARY

. . . .D-I APPENDIX E PRE-OPERATIONAL PROGRAM . . . .E-I J

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DC Cook Nuclear Plant Units 1&2 Annual Radiological Environrnental Operating Report 2002

1. EXECUTIVE

SUMMARY

Implementation of the DC Cook Nuclear Plant Radiological Environmental Monitoring Program (REMP) continued during the period January through December 2002, in compliance with station Technical Specifications and Off-Site Dose Calculation Manual.

Radiochemical and radiometric analysis of REMP samples was performed to allow for the detection of station-related radioactivity. Samples included air particulate filters and chartoal cartridges, fruit, water (drinking, well and surface), milk, and Lake Michigan fish and sediment. Also, thermoluminescent dosimeters (TLDs) were used to measure direct gamma exposure at various locations up to a distance of 26 miles from the station.

During the evaluation of analyses results, it was necessary to consider the variability of natural and man-made sources of radioactivity, distribution in the environment and uptake in environmental media. The potential variability was dependent on many possible factors including:

• contributions from cosmogenic radioactivity

• ground water dynamics

• station related release rates

• past spatial variability of radioactive fallout from nuclear weapons tests and the on-going redistribution of this fallout

• soil characteristics

• farming practices

• feed type Since these factors had the potential to cause significant variation in sample analysis results, they were considered during the evaluation of detected radioactivity.

Based on the evaluation of analyses results, it was determined that radioactivity detected by the REMP was predominantly from outside sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides. Examples include the following:

• Four of four Lake Sediment samples contained naturally occurring K40 and one of four samples contained naturally occurring AcTh-228.

• Three of three Grape and Broad Leaf samples contained naturally occurring K40 and one of three samples contained naturally occurring Be-7.

• One of eight Lake Michigan fish samples contained Cs-137. Detection of this nuclide has historically been attributed to residual fallout from nuclear weapons tests and the levels detected were consistent with data contained in DC Cook's "Summary of the Preoperational Radiological Monitoring Program".

No instances of detectable radioactivity attributable to 2002 station operation were noted and no sample analysis results exceeded or approached specified reporting levels.

I

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 This report was prepared for the Indiana Michigan Power Company by the Framatome-ANP, Radiological Engineering Group. Sample collection and preparation were performed by DC Cook. The laboratory analyses were performed by Framatome-ANP Environmental Laboratory (FANP).

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DC Cook Nuclear Plant Units 14£2 Annual Radiologicai Environmental Operating Report 2002

2. INTRODUCTION 2.1 General Plant Site Information The Indiana Michigan Power Company DC Cook plant is located on the southeastern shore of Lake Michigan approximately one mile northwest of Bridgman, Michigan. The site consists of two pressurized water reactors: Unit 1, 1095 MWE and Unit 2, 1152 MWE. Unit I achieved initial criticality on January 18, 1975 and Unit 2 on March 10, 1978.

2.2 Program Design The Radiological Environmental Monitoring Program for the DC Cook Nuclear Plant was designed with specific objectives:

- To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by the DC Cook Plant activities.

- To provide assurance to regulatory agencies and the public that the environmental/dose impact of the DC Cook Plant operation is known and within anticipated limits.

- To verify the adequacy and proper functioning of station effluent controls and monitoring systems.

- To comply with regulatory requirements and Station Technical Specifications and provide records to document compliance.

The program was developed to meet the intent of the NRC Regulatory Guide 4.1, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants; NRC Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants; the NRC Branch Technical Position of November 1979, An Acceptable Radiological Environmental Monitoring Program; and NRC NUREG-0472, Radiological Effluent Technical Specifications for PWR's.

The REMP sampling requirements are given in Attachment 3.19 of the ODCM and summarized in Table 2.1 of this report. The identification of the required sampling locations is also provided in Attachment 3.19 of the ODCM and Table 2.2 of this report. The monitoring locations are shown graphically in Figures 2.1 and 2.2.

2.3 Monitoring Zones The REMP is designed to allow comparison of levels of radioactivity in samples from the area potentially influenced by the plant to levels found in areas not influenced by the plant. The first area monitoring locations are designated as indicators and the second area monitoring locations are designated as controls. The distinction between the two areas, for a particular pathway, is based on relative direction and distance from the plant. Analysis of survey data from the two areas is used to differentiate between radiation due to plant activities and that due to other sources such as atmospheric nuclear weapons test fallout or seasonal variations in the natural background.

2.4 Pathways Monitored Four pathway categories; airborne, waterborne, ingestion, and direct radiation are monitored by the REMP. Each of these categories is monitored by the collection of one or more sample types listed and described below.

Airborne Pathway: Air Particulate Sampling Waterborne Pathway: Surface Water Ground Water Drinking Water 3

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 1 Sediment Ingestion Pathway: Food Products (Fruit and Broadleaf Vegetable)

Fish Milk (Broadleaf Vegetation in lieu of Milk, when necessary)

Direct Radiation: TLD Monitoring 2.5 Descriptions of Monitoring Pathways Sample types and frequency of analysis are given in Table 2.1. The sample locations are listed in Table 2.2 and shown in Figures 2.1, 2.2, and 2.3. The program as described in this report includes both ODCM required and additional or supplemental samples. A description of the sampling program follows and a detailed summary of the analytical methodologies employed by the Framatome-ANP lab is provided in Appendix A.

2.5.1 Air Sampling Continuous air samplers are installed at ten locations as required by the ODCM. The sampling oil-less pumps at these locations operate continuously with sample flow rate between 42 to 70 Ipm. Airborne particulates are collected by passing air through a 47-mm glass-fiber filter. Charcoal cartridges are installed downstream of the particulate filters and are used to collect airborne radioiodine. An Automatic Volume Totalizer is used to measure the total volume of air sampled, total unit run time and volumetric flow rate. Both filters are collected weekly, and to allow for the decay of radon daughter products, the particulate filters are held at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> before being analyzed for gross-beta radioactivity (indicated as GR-B in the data tables). The weekly particulate filters are composited by location at the Framatome Lab for a quarterly gamma spectroscopy analysis.

2.5.2 Surface Water Sampling Two 125 milliliter surface water samples are collected from the intake forebay and from two shoreline locations, all within 0.3 miles of the reactors. Samples are composited daily over a month and preserved with nitric acid. All samples receive a gamma isotopic, low level 1-131 and tritium analysis.

2.5.3 Ground Water Sampling Ground water samples are collected quarterly from 14 wells, all within 4300 feet of the reactors. At each well a static water elevation is determined and three well bore volumes are purged from the well using a groundwater pump or -

equivalent. Two 1-liter and one 125mr samples are then collected and the gamma isotopic aliquot is preserved with nitric acid. Gamma isotopic and tritium analyses are performed.

2.5A Drinking Water Sampling One liter samples are collected daily at the intake of the water purification plants for St. Joseph and Lake Township. The daily samples are composited over 14 days and the gamma isotopic aliquot is preserved with nitric acid. The Quarterly composite is analyzed for H-3.

2.535 Sediment Sampling Lake Michigan shoreline sediment samples are collected semiannually at the same two locations as the surface water samples. Two liters of lake sediment are collected using a small dredge in an area covered part time by wave action. The sediment samples are analyzed for gamma isotopic content.

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DC Cook Nuclear Plant Units 18r2 Annual Radiological Environmental Operating Report 2002 2.5.6 Milk Sampling One gallon milk samples are collected from a 500 gallon bulk tank every fourteen days from four farms located between 4.1 and 20.7 miles from the site. A fifth farm is a goat farm located 5.0 miles from the plant site, where no bulk tank is used. The samples are preserved with 40 grams per gallon of sodium bisulfite at the time of collection. Samples are analyzed for low level I-131 and gamma emitting radionuclides.

2.5.7 Fish Sampling Four and one-half pounds of fish are collected two times a year from four locations using gill nets in approximately 20 feet of Lake Michigan water. The edible portions of the fish are analyzed for gamma-emitting radionuclides.

2.5.8 Food Product Sampling Food products are collected annually, at the time of harvest, from three locations. The locations are as close to the site boundary as possible and approximately 20 miles from the site. Each sample consists of at least 300 grams of grapes or broadleafs. The samples are analyzed by gamma isotopic analysis.

2.5.9 Broad Leaf Vegetation Broad Leaf vegetation sampling in lieu of milk collection was discontinued in 2000 due to the re-implementation of the milk sampling program.

2.5.10 TLD Monitoring Direct gamma radiation exposure is continuously monitored with the use of Panasonic UD-801AS I thermoluminescent dosimeters (TLDs). TLDs are posted at 27 locations in the environs surrounding the DC Cook Plant.

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DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 2.1- Sampling Frequency & Type of Analysis ODCM, Rev. 17 Attachment 3.19 Epoure Pathway

' i::;Number of:i:; 'Sampling & Collection -

andor Sample Lcatons Frequency Type of Analysis

1. Gamma Exposure - 27 Quarterly Gamma Dose - Quarterly Environmental TLD

2. Airborne Particulate 10 Continuous sampler - weekly Gross Beta and 1-131 - Weekly filter change Gamma Spectrum - Quarterly on composite (by location) 3a. Ground Water 14 Quarterly Gamma Isotopic and Tritium - Quarterly Well Water 3b. Ground Water 4 Quarterly Gamma Isotopic, Gross Alpha/Beta - Quarterly SG Storage Facility

4. Surface Water 3 Daily Gamma Isotopic - Monthly on composite Tritium - Quarterly on composite

5. Drinking Water 2 Daily Gamma Isotopic, Gross Beta and I-131LL -on 14 day composite. Tritium - Quarterly on composite

6. Sediment 2 Semiannually Gamma Isotopic Lake

7. Milk 5 Once every 15 days or Gamma Isotopic and I131LL - per sample Monthly if animals are fed stored feed.

S. Fish (edible portion) 4 2 per year Gamma Isotopic - per sample

9. Food Products 3 At time of harvest Gamma Isotopic - per sample Grape/Broadleaf Veg.

10. Broadleaf Vegetation - 3 Monthly during growing Gamma Isotopic - per sample (inlieu of milk sampling) season 6

J

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 2.2 - 2001 Environmental Monitoring Program Sampling Types and Locations ExposurePat way' S  ;; ; ndicaDo-r Location Descri tion (Sample Type -C

- Staion ntrol Desig ion) i-;' hat- i t ' - ; ' '.' 'i07 'd ';;;-' i. 'T .' ' ' .E Airborne

a. Filter (AP I CF) ONS-1 I 1945 ft@ t8° from Plant axis ONS-2 I 2338 ft @ 480 from Plant axis ONS-3 I 2407 ft @ 900 from Plant axis ONS-4 I 1852 ft@ 118° from Plant axis ONS-5 I 1895 ft @ 189° from Plant axis ONS-6 I 1917 ft @ 210° from Plant axis NBF C 15.6 mi SSW - New Buffalo, MI SBN C 26.2 mi SE - South Bend, IN DOW C 24.3 mi ENE - Dowagiac, Ml COL C 18.9 mi NNE - Coloma, Ml Waterborne

a. Ground Well (WG) W-1 I 1969 ft @ I I'from Plant axis W-2 I 2302 ft @ 63° from Plant axis W-3 I 3279 ft @ 1070 from Plant axis W-4 I 418 ft @ 3010 from Plant axis W-5 I 404 ft @ 290° from Plant axis W-6 I 424 ft @ 2730 from Plant axis W-7 1895 ft @ 1890 from Plant axis

.I W-8 1274 ft @ 54 from Plant axis I

W.9 1447 ft @ 220 from Plant axis I

W-10 4216fR @ 129° from Plant axis I

W-l1 3206 ft @ 153° from Plant axis I

W-12 2631 ft @ 1620 from Plant axis I

W-13 2152 ft @ 182 from Plant axis I

W-14 1780 ft @ 164° from Plant axis

b. Drinking (WD) STJ C 9 mi NE - St. Joseph Public Intake Station LTW I 0.6 mi S - Lake Twp. Public Intake Station

c. Surface (WS) SWL-I I Condenser Circulating Water Intake 7

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 2.2 - 2001 Environmental Monitoring Program Sampling Types and Locations Exosr

.Pathway. - -lndi;a--

apl I; r/- L:ao Decrpto (Sample Type StaionConro Desi nation)

SWL-2 1 500 ft S of Plant Centerline - Site Boundary SWL-3 I 500 ft N of Plant Centerline - Site Boundary

d. Sediment (SE) SL-2 I 500 ft S of Plant Centerline - Site Boundary SL-3 I 500 ft N of Plant Centerline - Site Boundary

e. Ground (SG) SG.1 I 0.8 mi @ 95? from Plant Axis Steam Generator SG-2 0.7 mi @ 92' from Plant Axis I I

Storage Facility SG-4 0.7 mi @ 93° from Plant Axis I

SG-5 0.7 mi @ 92 from Plant Axis Ingestion

a. Milk (TM) GWF I Determined by Land Use Census, 7.0 mi SSE MR I Determined by Land Use Census, 5.0 mi SE SF I Determined by Land Use Census, 4.1 mi SSE Livinghouse Farm C 20 mi S - La Porte, IN Wyant Farm C 20.7 mi E - Dowagiac

b. Fish (FH) ONS-N I 0.3 mi N, Lake Michigan ONS-S I 0.4 mi S, Lake Michigan OFS-N C 3.5 mi N, Lake Michigan OFS-S C 5.0 mi S, Lake Michigan

c. Food Products (TF) ONS-G I Nearest location to Plant in theland sector with ONS-V I Highest D/Q, OFS-G C In a land sector containing grapes, - 20 mi from the Plant, in one of the less prevalent D/Q land Sectors 8

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 2.2 - 2001 Environmental Monitoring Program Sampling Types and Locations Exposure Pathway Sample lndicator, - Location Description (Sample yeDsignation) Station- Control; Direct Radiation TLD T-1 I 1945 ft @ 18° from Plant axis T-2 I 2338 ft @ 480 from Plant axis T-3 I 2407 ft @90° from Plant axis T4 I 1852 ft @ 118° from Plant axis T-5 I 1895 ft @ 189° fromPlant axis T-6 I 1917 ft @210° from Plant axis T-7 I 2103 ft @36° from Plant axis T-8 I 2208 ft @820 from Plant axis T-9 I 1368 ft @ 149° from Plant axis T-10 I 1390 ft @ 1270 from Plant axis T-1 I I 1969 ft@ 1I'from Plant axis T-12 I 2292 ft @ 630 from Plant axis NBF C 15.6 mi SSW - New Buffalo, MI SBN 26.2 mi SE - South Bend, IN C

DOW 24.3 mi ENE - Dowagiac, MI C

COL 18.9 mi NNE - Coloma, MI C

OFF-I 4.5 mi NE - Pole #B294-44 C

OFr-2 3.6 mi NE - Stevensville Substation C

OFr-3 5.1 mi NE -Pole #B296-13 C

OFF4 4.1 mi E -Pole #B350-72 C

OFT-5 4.2 mi ESE - Pole #B387-32 C

OFT-6 4.9 mi SE - Pole #B426-1 C

OFT-7 2.5 mi S - Bridgman Substation C

OFT-8 4.0 mi S - Pole #B424-20 C

OFT-9 4.4 mi ESE - Pole #B369-214 C

OFT-10 3.8 mi S - Pole #B422-99 C

OFr-I I 3.8 mi S - Pole #B423-12 9

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 2.3 - Environmental Lower Limit of Detection (LLD) Sensitivity Requirements ODCM, Rev. 17 Attachment 3.20 AAnalysis- Food Prod Water Milk : . Air Flter - {Fi . . S diment wet,-

Gross Beta H-3 4*

2000 0.01 J

Mn-54 15 130 Co-58 15 130 Co-60 15 130 Fe-59 30 260 Zn-65 30 260 Zr-95 30 Nb-95 15 1-131 60 1 1 0.07 Cs-134 60 1 15 0.06 130 150 Cs-137 60 18 18 0.06 150 180 Ba-140 60 60 La-140 1S 1S

• Drinking Water LLD

-J I.

J 10

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 2A - Reporting Levels for Radioactivity Concentrations in Environmental Samples ODCM Rev 17, Attachment 3.21 Water V - Milk r ysis FdProd. orne K p we pY/n 3 ___

H-3 20000 Mn-54 1000 30000 Co-58 1000 30000 Co-60 300 10000 Fe-59 400 10000 Zn-65 300 20000 Zr-95 400 . .

Nb-95 400 1-131 100 2 3 0.90 Cs-134 1000 30 60 10 1000 Cs-137 2000 50 70 20 2000 Ba-140 200 300 La-140 200 300 11

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DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 2.6 Samples Collected During 2002 The following table summarizes the number of samples of each type collected during the 2002 reporting period and the number of analyses by station type for each media. A more detailed breakdown of the various analyses performed is provided in the data summary tables in Section 3, Table 3.1.

Table 2.5 REMP Samples Collected in 2002 Sample REMIPSamples type Collected in 2002 K!Total~:. indicator; AControl, Gamma Exposure 108 48 60 Environmental TLD Air Particulate 519 311 208 Charcoal Filter 519 311 208 Ground Water 56 56 Surface Water 32 32 _

Drinking Water 52 26 26 Sediment (Lake) 4 4 Food Products 3 2 1 Milk 125 75 50 Fish 8 4 4 Total All Types 1426 869 557 15

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 -.

3. RADIOLOGICAL DATA

SUMMARY

TABLES This section summarizes the analytical results of the environmental samples that were collected during 2002. These results, shown in Table 3.1, are presented in a format similar to that prescribed in the NRCs Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1). The results are ordered by sample media type and then by radionuclide for the pathways described in Section 2.3. The units for each media type are also given. Table 3.2 provides the same information for TLD direct radiation measurements.

The left-most column contains the radionuclide of interest, the total number of analyses for that radionuclide in 2002, and the number of measurements which exceeded the Reporting Levels found in Table 2.5. The latter are classified as "Non-routine" measurements. The second column lists the required Lower Limit of Detection (LLD) for those radionuclides, which have detection capability requirements specified in Table 2.4. The absence of a value in this column indicates that no LLD is specified in the ODCM for that radionuclide in that media.

For each media type and radionuclide, the remaining three columns summarize the data for the following categories of monitoring locations: (1) the Indicator stations, which are within the range of influence of the plant and which could be affected by plant activities; (2) the station which had the highest mean concentration during 2002, and (3) the Control J stations, which are beyond the influence of the plant. Direct radiation monitoring stations (using TLDs) are grouped into Indicator and Control stations.

In each of these columns, for each radionuclide, the following are given:

• The mean value of all concentrations including negative values and values that are not considered "detectable".

• The lowest and highest concentration.

• The number of detectable measurements divided by the total number of measurements.

A sample is considered a "detectable measurement' when the concentration exceeds three times its associated standard deviation. The standard deviation on each measurement represents only the random uncertainty associated with the radioactive decay process (counting statistics), and not the propagation of all possible uncertainties in the analytical procedure.

The radionuclides reported in this section represent those that: 1) had a LLD requirement in Attachment 3.20 or, a Reporting Level listed in Attachment 3.21 of the ODCM or 2) had a positive measurement of radioactivity, whether it was naturally-occurring or man-made; or 3) were of specific interest for any other reason. The radionuclides that are routinely analyzed and reported by the FANPEL in a gamma spectroscopy analysis are: AcTh-228, Ag-108m, Ag-1 10m, Ba-140/La-140, Be-7, Ce-141, Ce-144, Co-57, Co-58, Co-60, Cr-51, Cs-134, Cs-137, Fe-59, I-131, K40, Mn-54, Ru-103, Ru-106, Sb-124, Sb-125, Se-75, Zn-65 and Zr-95INb-95.

Data from direct radiation measurements made by TLDs are provided in Table 3.2 in a format essentially the same as above. The complete listing of quarterly TLD data is provided in Table 3.3. -

16

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Air Particulates (AP) UNITS: PCI/cubic meter Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine- LLD No. Detected- No. Detected" No. Detected" GR-B (519) 0.01 3.11 -2 ONS-2 3.5E -2 3.0O -2 (0) 2.1 - 72.6)Z -3 ( 2.1 - 72.6)1 -3 1.1 - 5.6)E -2 (310/ 311) (51/ 52) (208/ 208)

Be-7 (40) 1.1E -1 ONS-2 1.21 -1 1.01 -1 (0) 6.3 - 15.0)1 -2 9.2 - 15.0)E -2 6.6 - 13.3)E -2 (24/ 24) (16/ 16)

K-40 (40) 3.61 -4 ONS-2 4.01 -3 1.91 -3 (0) ( -6.5 - 6.0)1 -3 2.5 - 6.0)1 -3 -3.5 - 9.3)E -3 (0/ 24) (0/ 4) (0/ 16)

Cr-51 (40) 1.4Z -3 DOW 1.3E -2 3.51 -3 (0) ( -2.9 - 3.3)1 -2 0.0 - 3.9)E -2 -2.9 - 3.9)Z -2 (0/ 24) (0/ 4) (0/ 16)

Mn-54 (40) -7.6E -5 ONS-1 1.6E -4 O.OZ 0 (0) C-7.8 - 5.2)E -4 -3.2 - 5.2)1 -4 ( -7.3 - 8.1)1 -4 (0/ 24) (0/ 4) (o/ 16)

Co-57 (40) -1.OE -5 NBF 8.7E -S 2.1E -5 (0) ( -2.6 - 1.6)1 -4 1.0 - 26.0)E -5 -2.7 - 2.6)E -4 (0/ 24) (0/ 4) (0/ 16)

Co-58 (40) -1.21 -' NBF 3.21 -4 -5.6z -S (0) ( -9.2 - 6.6)1 -4 -1.0 - 6.9)E -4 C -8.2 - 6.9)1 -4 (0/ 24) (0/ 4) (O/ 16)

Fe-59 (40) 1.61 -4 NSF 1.51 -3 6.81 -5 (0) -3.7 - 6.0)1 -3 -1.5 - 6.0)1 -3 -3.8 - 6.0)1 -3 (O/ 24) (O/ 4) (0/ 16)

Co-60 (40) O.O 0 ONS-5 2.11 -4 -5.71 -5 (0) -3.4 - 4.7)1 -4 -2.4 - 4.4)1 -4 ( -3.5 - 3.3)1 -4 (0/ 24) (0/ 4) (0/ 16)

Zn-65 (40) -4.61 -4 ONSI1 o.o0 0 -6.11 -4 (0) -2.0 - 1.6)1 -3 ( -1.2 - 1.6)1 -3 ( -1.9 - 0.6)E -3 (O/ 24) (O/ 4) (0/ 16) 17

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Air Particulates (AP) UNITS: PCI/cubi meter Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routlhe LLD No. Detected" No. Detected- No. Detected" Se-75 (40) 7.32 -5 0NS-2 2.62 -4 1.02 -4 (0) ( -3.1 - 11.2)2 -4 -8.1 - 11.2)B -4 -3.1 - 6.4)X -4 (Of 24) (0/ 4) (0/ 16) r Zr-95 (40) 2.22 -4 ONS-4 4.22 -4 -1.12 -4 (0) -8.4 - 19.0)B -4 -6.8 - 19.0)2 -4 -1.0 - 0.7)2 -3 (0/ 24) (O0 4) (O 16)

Nb-95 (40) 3.72 -3 SSN 6.6B -4 -1.32 -5 (0) ( -1.9 - 2.3)X -3 ( -2.2 - 23.0)2 -4 ( -2.9 - 2.3)2 -3 (O 24) (0/ 4) (0/ 16)

Ru-103 (40) -1.62 -5 COL 4.32 -4 -1.42 -4 (0) -1.0 - 2.0)3 -3 -1.0 - 1.2)B -3 ( -2.1 - 2.1)2 -3 (O 24) (Of 4) (0/ 16)

Ru-I06 (40) 3.5 -4 ONW4 1.4B -3 -3.32 -4 (0) ( -4.9 - 5.0)B -3 -9.0 - 36.0)2 -4 ( -3.8 - 7.4)B -3 (0/ 24) (O/ 4) (0/ 16)

Ag-10Bm (40) -4.72 -5 SBN 1.12 -4 -1.12 -5 (0) (.-5.5 - 2.6)B -4 0.0 - 1.8)B -4 -2.7 - 1.8)2 -4 (0/ 24) (Of 4) (0/ 16)

Ag-10m (40) 4.62 -5 DOW 3.72 -4 2.42 -5 (0) -6.8 - 7.2)3 -4 -3.3. - 14.8)B -4 9.7 - 14.8)2 -4 (0/ 24) (0/ 4) (O 16)

J Sb-124 (40) 6.12 -4 ONS.1 1.5X -3 -1.12 -3 (0) -2.1 - 4.7)2 -3 -6.0 - 45.0)2 -4 ( -6.5 - 2.5)2 -3 (0/ 24) (O0 4) (0/ 16)

Sb-12S (40) -8.42 -5 ONS-J 3.22 -4 7.82 -5 (0) -9.5 - 10.1)3 -4 -4.9 - 10.1)2 -4 ( -7.4 - 6.2)2 -4 (0/ 24) (O 4) (0 16) 1-131 (40) -2.42 -2 ONS4 1.12 -1 -1.22 -2 (0) ( -5.9 - 3.7)2 -1 8.0 - 370.0)2 -3 ( -4.7 - 2.7)2 -1 (O0 24) (0/ 4) (Of 16) I

-J 18

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Air Particulates (AP) UNITS: oCI/cublc meter Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine- LLD- No. Detected" No. Detected" No. Detected-Cs-134 (40) 0.06 -3.1Z -5 DOW 2.1E -4 1.33 -4 (0) I-8.5 - 2.8)E -4 ( 6.0 - 4*.0)Z -5 ( -2.8 - 4.8)z -4 (0/ 24) (O 4) (0/ 16)

Cs- 137 (40) 0.06 -2.1E -5 ofs-s 2.2E -4 -2.12 -5 (0) -6.1 - 3.9)E -4 -4.0 - 36.0)z -5 I -4.6 - 4.7)Z -4 (0/ 24) (O 4) (0/ 16)

Ba-i40 (40) 2.03 -3 ONS-3 2.23 -2 -6.43 -3 (0) ( -9.8 - 6.1)3 -2 ( -3.4 - 48.0)E -3 ( -5.2 - 4.8)3 -2 (0/ 24) (O0 4) (0/ 16)

Lii-40 (40) 2.43 -3 ONS4 2.53 -2 -7.33 -3 (0) ( -1.1 - 0.7)3 -1 ( -3.9 - 55.0)3 -3 ( -5.9 - 5.5)Z -2 (0/ 24) (O 4) (0/ 16)

Ce-141 (40) 3.63 -4 DoW 1.33 -3 3.3E -4 (0) ( -2.6 - 2.9)3 -3 ( 4.0 - 21.0)3 -4 I -2.0 - 2.6)3 -3 (0/ 24) (Of 4) (0/ 16)

Ce-144 (40) -1. 6Z -4 ONS-4 1.03 -3 -6.83 -4 (0) i -2.6 - 2.1)1 -3 ( 3.2 - 21.0)3 -4 ( -1.9 - 0.6)3 -3 (0/ 24) (O 4) (0/ 16)

Th-232 (40) 1.43 -4 SBN 1.33 -3 -1.73 -5 (0) ( -1.5 - 1.6)1 -3 ( 1.7 - 13.2)3 -4 ( -1.7 - 1.3)3 -3 (0/ 24) (Of 4) (0/ 16)

• Non-Routine refers to radionuclides exceeding the Reporting Levels In ODCM Attachment 3.21 of the ODCM 19

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Charcoal Cartridae (CF) UNITS: PCI/cublc meter Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine* LLD No. Detected" No. Detected" No. Detected-1-131 (519) 0.07 -4.43 -4 SBN 1.41 -3 -2.02 -4 (0) ( -2.3 - 2.1)2 -2 ( -1.8 - 1.5)1 -2 ( -1.9 - 2.2)1 -2 (Ot 311) (o/ 52) (0/ 208)

I Non-Routine refers to radionuclides exceeding the Reporting Levels In ODCM Attachment 3.21 of the ODCM 20

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Ground Water. Well IWG) UNITS: oCI/ka Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine- LLD No. Detected" No. Detected" No. Detected" H-3 (56) 2000 1.9E 2 W-4 7.4Z 2 NO DATA (0) ( -6.7 - 12.0)E 2 ( 5.0 - 10.0)Z 2 (0/ 56) (0O 4)

Be-7 (56) -5.4Z -1 W-12 6.6Z 0 nO DATA (0) -2.6 - 2.3)Z 1 A -2.0 - 11.0)E 0 (0/ 56) (0/ 4)

K-40 (56) 1.4Z 1 W4 8.3E 1 SO DATA (0) -3.3 - 11.7)Z 1 ( 6.5 - 11.7)Z 1 (5/ 56) (3/ 4)

Cr-51 (56) -3.41 0 W-7 7.1E 0 NO DATA (0) -3.4 - 1.1)t 1 ( 2.6 - 10.0)1 0 (0/ 56) (0/ 4)

Mn-54 (56) 15 -2.41 -1 W4 7.3E -1 NO DATA (0) -3.1 - 2.6)Z 0 ( -2.0 - 26.0)E -1 (0/ 56) (0/ 4)

Co-57 (56) -2.81 -2 w-11 4.3E -1 NO DATA (0) -1.7 - 1.9)1 0 -3.9 - 7.3)1 -1 (0/ 56) (0/ 4)

Co-58 - (56) 15 -2.7Z -1 W-1 4.7E -1 NO DATA (0) -2.5 4.4)1 0 -1.3 - 4.4)1 0 (0/ 56) (0/ 4)

Fe-59 (56) 30 1.11 -1 W-14 2.61 0 NO DATA (0) - ( -6.3 - 6.3)1 0 -1.5 - 6.3)Z 0 (0/ 56) (0/ 4)

Co-60 (56) 15 3.11 -1 W.6 1.31 0 NO DATA (0) ( -2.9 - 3.8)E 0 -4.9 - 38.0)1 -1 (0/ 56) (0/ 4)

Zn-65 (56) 30 7.81 -1 W.3 5.5 0 NO DATA (0) ( -9.0 - 13.2)1 0 -9.0 - 13.2)Z 0 (0/ 56) (0/ 4) 21

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant

- (January. December 2002)

MEDIUM: Ground Water. Well (WG) UNITS: vCl/ki Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine- LLD No. Detected- No. Detected" No. Detected" SO-7S (56) 1. 83 -2 YF10 1. 1 0 NO DATA -

(0) ( -2.5 - 2.7)3 0 ( -9.6 - 27.0)3 -1 (0/ 56) (0/ 4)

Zr-95 (55) 15 4.53 -1 W.14 2.03 0 NO DATA (0) ( -4.7 _ 5.5)2 0 -4.0 - 55.0)3 -1 (0/ 56) (Of 4)

Nb-95 (56) 13 -1.12 0 W.7 5.41 -1 NO DATA -

(0) ( -6.6 - 3.4)1 0 -1.1 - 3.4)Z 0 (0f 56) (0/ 4)

Ru-t03 (56) -1.33 0 W-4 -1.53 -1 NO DATA (0) -4.5 - 1.6)3 0 -9.0 - 3.0)3 -1 (O/ 56) (0/ 4)

I Ru-tOS (56) -1.22 0 W-2 5.23 0 NO DATA (0) ( -3.2 _ 2.0)2 1 1.6 - 12.3)3 0 (0/ 56) (O 4)

Ag-1O8rm (56) -1.22 -1 W4 4.83 -1 NO DATA (0) -2.1 - 1.9)3 0 -1.0 - 1.7)j 0 (O 56) (0/ 4)

Ag-1Orm. (56) 3.31 -1 W-1I 1.63 0 NO DATA (0) ( -3.8 - 4.1)3 0 4.0 - 41.0)3 -1 (0/ 56) (0/ 4)

Sb-i124 (56) 1.83 -2 W4 2.41 0 No DATA (0) -7.0 - 7.2)3 0 1.0 - 3.2)1 0 (0/ 56) (0/ 4)

Sb-it25 (56) -5.63 -1 W-11 3.51 0 NO DATA (0) ( -6.7 - 6.7)1 0 ( 4.0 - 62.0)3 -1 (O 56) (0/ 4) 1-131 (56) 1 3.63 -1 W4 2.83 0 NO DATA (0) -9.3 - 6.7)3 0 2.3 - 3.5)3 0 (Of 56) (0/ 4) 22

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Ground Water. Well (WG) UNITS: oCI/kq Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routfne- LLD No. Detected" No. Detected- No. Detected" Cs-134 (56) 15 3.11 -1 W-14 1.31 0 NO DATA (0) -2.6 - 4.0)I 0 ( -6.0 - 40.0)1 -1 (0/ 56) (0/ 4)

Cs-137 (56) 18 -4.1Z -1 W-2 6.01 -1 NO DATA (0) -3.5 - 1.2)1 0 ( 5.0 - 7.0)E -1 (0/ 56) (0/ 4)

Ba-140 (56) 15 -2.51 -1 W-13 1.31 0 NO DATA (0) (-5.2 - 6.7)1 0 ( -1.8 - 3.5)S 0 (0/ 56) (0/ 4)

La- 140 (56) 15 -3.11 -1 W-13 1.51 0 NO DATA (0) (-5.9 - 7.7)S 0 ( -2.0 - 4.0)1 0 (0/ 56) (0/ 4)

Ce-141 (56) -4.11 -1 W4 1.5z 0 NO DATA (0) ( -6.8 - 4.4)1 0 ( -3.0 - 34.0)E -1 (0/ 56) (0/ 4)

Ce-144 (56) -4.31 -1 W-2 4.71 0 NO DATA (0) -1.6 - 1.1)1 1 ( -5.0 - 10.8)E 0 (0/ 56) (0/ 4)

Th-232 (56) 2.21 0 w.11 8.11 0 NO DATA (0) ( -6.9 - 11.4)1 0 9.0 - 114.0)1 -1 (1/ 56) (1/ 4)

• Non-Routine refers to radionuclides exceeding the Reporting Levels in ODCM Attachment 3.21 of the ODCM 23

DC Cook Nuclear Plant Units 1&2 - Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana MIchigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Drinking Water (WD) UNITS: cCI/llter Indicator Stations Station With Highest Mean Control Stations Radionucldes Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine LLD No. Detected" No. Detected- No. Detected-GR-B (52) 4 3.2Z 0 STJ 3.51 0 3.51 0 (0) ( 1.2 - 6.83) 0 -3.1 - 75.1)X -1 -3.1 - 75.1)3 -1 (161 26) (17/ 26) (17/ 26)

H-3 (8) 2000 2.41 2 LTW 2.41 2 1.1 2 (0) ( -1,6 - 7.0)1 2 -1.6 - 7.0)1 2 -1.0 - 2.7)1 2 (O/ 4) (0/ 4) (O/ 4)

B-7 (52) -1.12 0 STJ -6.91 -2 -6.91 -2 (0) ( -2.6 - 2.0)1 1 ( -2.1 - 1.5)B 1 ( -2.1 - 1.5)1 1 (0/ 26) (O/ 26) (0/ 26)

K-40 (52) -3.2B 0 STJ 4.01 0 4.Ox 0 (0) ( -3.0 - 2.7)1 1 -4.4 - 6.2)3 1 -4.4 - 6.2)1 1 (0/ 26) (1/ 26) (1/ 26)

Cr-51 (52) 1.1B 0 LTW 1.13 0 -2.61 0 (0) -2.6 - 2.6)B 1 -2.6 - 2.6)X 1 -2.9 - 3.4)B 1 (O/ 26) (O/ 26) (0/ 26)

Mn-54 (52) 13 -3.13 -1 STJ -1.01 -1 -1.01 -1

• () ( -3.4 - 3.2)1 0 -2.2 - 2.9)B 0 -2.2 - 2.9)1 0 (O/ 26) (0/ 26) (0/ 26)

Co-57 (52) 1.51 -1 STJ 2.42 -1 2.41 -1 (0) -1.4 - 1.7)1 0 -9.1 - 20.0)1 -1 -9.1 - 20.0)1 -1 (O/ 26) (0/ 26) (0/ 26)

Co-Bs (52) 15 -3.61 -1 LTW -3.61 -1 -3.13 -1 (0) -3.3 - 3.0)1 0 -3.3 - 3.0)1 0 ( -2.3 - 2.1)3 0 (0/ 26) (O/ 26) (O/ 26)

Fe-59 (52) 30 1.51 -1 STJ 1.1Z 0 1.1B 0 (0) -7.9 - 7.83) 0 -9.0 - 7.6)3 0 -9.0 - 7.6)1 0 (O/ 26) (O/ 26) (0/ 26)

Co-60 . (52) 15 2.41 -1 LTW 2.41 -1 -1.31 -2

• (0) -1.8 - 2.4)1 0 -1.8 - 2.4)1 0 ( -1.9 - 1.9)X 0 (O/ 26) (O/ 26) (0/ 26) 24

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Drlnkina Water (WD) UNITS: oCliliter Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine' LLD No. Detected" No. Detected- No. Detected-Zn-65 (52) 30 1.71 -1 1.TW 1.7E -1 7.31 -2 (0) -6.5 - 9.2)I 0 -6.5 - 9.2)3 0 -1.3 - .l)Z I (O0 26) (O/ 26) (O/ 26)

Se-75 (52) 1.2E -1 1.TW 1.21 -1 -3.91 -1 (0) ( -3.1 - 2.5)1 0 -3.1 - 2.5)1 0 -4.2 - 1.83) 0 CO/ 26) (O/ 26) (O/ 26)

Zr-95 (52) 30 4.83 -1 1.1W 4.3E -1 1.41 -1

( -3.1 - 4.6)1 0 ( -3.1 - 4.6)Z 0 -2.9 - 4.2)1 0 (0)

(O/ 26) (O/ 26) (O/ 26)

Nb-95 (52) 15 -3.7E -1 STJ -3.21 -1 -3.21 -1

( -S.0 4.5)1 0 ( -2.7 - 3.9)1 0 -2.7 - 3.9)E 0 (0)

(O/ 26) (O/ 26) (O/ 26)

Ru-tO6 (52) -3.7Z 0 STJ -1.3Z 0 -1.31 0

-2.4 - 1.9)1 1 -2.7 - 2.2)E 1 -2.7 - 2.2)1 1 (0)

(O/ 26) (O/ 26) (O/ 26)

Ag-I08m (52) -4.2Z -2 STJ 1.11 -1 1.11 -1

( -2.3 - 1.8)1 0 -1.3 - 2.2)1 0 -1.3 - 2.2)1 0 (0)

(O/ 26) (O/ 26) (O/ 26)

Ag-110m (52) -5.OZ -1 1.1w -5.OE -1 -5.21 -1 (0) -4.3 - 4.O)1 0 -4.3 - 4.0)E 0 ( -3.1 - 1.3)1 0 (O/ 26) (O/ 26) (O/ 26)

Sb-124 (52) -9.3Z -1 Fri -3.21 -1 -3.21 -1 (0) -6.2 - 6.9)1 0 -5.5 - 5.2)1 0 ( -5.5 - 5.2)1 0 (O/ 26) (O/ 26) (O/ 26)

Sb-125 (52) -2.31 -2 1.1w -2.31 -2 -1.5Z -1 (0) -5.4 - 4.C)U 0 -5.4 - 4.8)1 0 ( -8.3 - 5.O)1 0 (O/ 26) (O/ 26) (O/ 26) 1-131 (52) 1 1.7E -1 LTW 1.7E -1 1.51 -1 (0) -3.0 - 3.5)1 -1 -3.0 - 8.3)1 -1 ( -2.2 - 7.4)1 -1 (O/ 26) CO/ 26) (O/ 26) 25

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Drinkino Water IWO) UNITS: oCLAIter Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine^ LLD No. Detected No. Detected No. Detected -. j Cs-i34 (52) 15 2.53 -1 STJ 4.23 -1 4.23 -1 (0) ( -2.2 - 2.3)3 0 ( -1.9 - 3.3)X 0 -1.9 - 3.3)X 0 (Of 26) (O0 26) (0/ 26)

Cs-137 (52) 18 -2.9X -1 LTW -2.93 -1 -1.OZ 0 (0) -2.3 - 1.5)3 0 ( -2.3 - 1.5)X 0 ( -3.2 - 1.0)3 0 (O/ 26) (O0 26) (0/ 26)

Ba-I40 (52) 60 8.O -1 LTW 8.03 -1 2.83 -1 (0) -5.4 - 7.9)3 0 ( -5.4 - 7.9)3 0 -4.4 - 4.7)3 0 (0/ 26) (0/ 26) (0/ 26)

Ba-i40 (52) 15 8.43 -1 LTW 8.43 -1 3.23 -1 (0) -6.2 - 9.1)3 0 ( -6.2 - 9.1)3 0 -5.1 - 3.4)3 0 (0/ 26) (0/ 26) (0/ 26)

Co-141 (52) -7.6Z -1 LTW -7.63 -1 -8.03 -1 (0) -8.3 - 4.8)3 0 -8.3 - 4.8)3 0 ( -5.9 _ 3.8)3 0 (O/ 26) (O 26) (0/ 26)

Ce-144 (52) 6.13 -1 srJ 1.32 0 1.33 0 (0) -6.0 - 16.0)3 0 -1.1 - 1.8)3 1 -1.1 - 1.8)3 1 (0/ 26) (0/ 26) (0/ 26)

Th-232 (52) 1.23 -1 SrTJ 2.43 0 2.63 0 (0) ( -1.3 - 1.3)3 1 ( -7.1 - 16.0)3 0 -7.1 - 16.0)3 0 (0 26) (O 26) (0/ 26)

• Non-Routine refers to radionuclides exceeding the Reporting Levels In ODCM Attachment 3.21 of the ODCM 26

DC Cook Nuclear Plant Units i&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Surface Water (WS) UNITS: yCI/llter Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routlne* LLD No. Detected" No. Detected" No. Detected' H-3 (12) 2000 -1.81 2 SWL4 -6.0 1 NO IDAA (0) ( -1.4 - 0.7)Z 3 ( -5.6 - 4.8)Z 2 (O 12) (Of 4)

Be-7 (32) -1.1Z 0 SWL-1 1.91 0 NO DATA (0) ( -2.2 - 1.1)Z 1 ( -3.9 - 11.1)Z 0 (O/ 32) (0/ 11)

K-40 (32) 3.4Z 0 SWL42 6.53 0 NO DATA (0) ( -1.9 - 3.4)1 1 ( -8.0 - 19.0)1 0 (O 32) (0/ 10)

Cr-51 (32) 1.91 0 SWL-2 4.6Z 0 (0) ( -1.9 - 3.5)r 1 ( -9.0 - 35.0)1 0 (O/ 32) (O/ 10)

Mn-54 (32) 1S -1.11 -1 SWL4 3.6Z -1 NO DATA (0) ( -1.3 - 2.1)1 0 ( -4.9 - 21.1)Z -1 (0/ 32) -(Of 11)

Co-57 (32) 1.4E -1 SWL.1 3.01 -1 NO DATA (0) ( -8.2 - 10.4)Z -1 ( -6.0 - 10.4)3 -1 (0/ 32) (0/ 11)

Co-S8 (32) 1S -4.21 -1 SWL11 -1.1m -1 so DATA (0) ( -2.4 - 1.2)1 0 ( -1.8 - 1.0)1 0 (0/ 32) (O 11)

Fe-59 (32) 30 3.83 -1 SWL4 1.01 0 NO DATA (0) ( -6.2 - 4.8)1 0 ( -1.5 - 4.8)t 0 (0/ 32) (0/ 11)

Co-60 (32) 1S 1.4E -1 SWL-2 5.11 -1 NO DATA (0) ( -1.S - 1.2)1 0 ( -6.0 - 122.0)1 -2 (0/ 32) (O 10)

Zn-65 (32) 30 7.8Z -1 SWL.i 2.53 0 so DATA (0) ( -4.7 - 13.6)1 0 ( -1.5 - 13.6)1 0 I

(O 32) (0/ 11) 27

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Surface Water (WS) UNITS: DCi/Vlter Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine iLD No. Detected- No. Detected" No. Oetected" I

Se-75 (32) 6.13 -2 SWL'- 2.33 -1 NO DATA (0) ( -2.2 - 1.9)X 0 ( -1.6 - 1.9)X 0 (0/ 32) (o/ 11)

Zr-95 (32) 15 2.03 -1 SWL4 4.01 -1 NO DATA (0) ( -3.2 - 3.6)X 0 ( -3.2 - 3.6)X 0 (0/ 32) ( Of 11)

Nb-95 (32) 15 -7.31 -1 SWL-3 -3.7X -1 NO DATA (0) (-3.7 - 1.7)X 0 -_3.7 - 1.7)3 0 Co/ 32) CO/ 11)

Ru-103 (32) -1.13 0 SWL"3 -7.3X -1 no DATA (0) ( -3.7 - 1.4)X 0 I -2.4 - 1.4)3 0 C0/ 32) (O 11)

Ru-106 (32) 5.33 -1 SWL-3 2.0X 0 NO DATA (0) ( -1.6 - 2.4)3 1 ( -1.1 - i.5)3 1 (0/ 32) CO/ 11)

Ag-108m (32) 1.03 -1 SWL-A 3.33 -1 NO DATA (0) ( -1.1 - 1.3)3 0 ( -3.7 - 12.3)3 -1 C0/ 32) (0/ 11)

Ag-110m (32) -2.83 -1 SWL-' -2.33 -2 NO DATA (0) ( -1.8 - 1.2)3 0 ( -1.8 - 1.2)3 0 (O/ 32) (O 11)

Sb-1124 (32) -9.91 -1 SWL-2 -3.73 -1 NO DATA (0) ( -6.3 - 5.7)X 0 ( -1.9 - 3.5)1 0 (0/ 32) (O/ 10)

Sb-125 (32) 3.73 -1 SWL.1 1.21 0 NO DATA (0) ( -6.2 - 4.1)1 0 ( -1.3 - 4.0)3 0 (0/ 32) (O/ 11) 1-131 (32) 1 1.53 0 SWL4 4.91 0 NO DATA (0) I -9.3 - 19.0)1 0 ( -5.4 - 19.0)X 0 (0/ 32) (O/ 11) 28

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002) amcnilm-A ... 4 ar~s IeNk IghtrTIM. -.- IAZ#-.

Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine- LLD No. Detected" No. Detected- No. Detected-Cs-t34 (32) 15 4.31 -1 SWL-2 5.61 -1 NO DATA (0) ( -1.& - 1.8)E 0 -1.0 - 1.4)5 0 (O/ 32) (0/ 10)

Cs-137 (32) 1i -i.1.E -1 SWL-4 -1.11 -2 No DATA (0) ( -2.2 - 1.4)E 0 -2.2 - 1.4)1 0 (0/ 32) (0/ 11)

Ba-140 (32) 1S 3.2z -1 SWL-2 2.01 0 N0 DATA (0) -4.1 - 7.1)E 0 -1.5 - 7.1)1 0 (0/ 32) (0/ 10)

La-140 (32) 15 3.8Z -1 SWL-2 2.31 0 NO DATA (0) -4.8 - a.2)E 0 ( -1.7 - 3.2)5 0 (0/ 32) (0/ 10)

Ce-i41 (32) -7.21 -1 SWL-1 _-41 -1 N0 DATA (0) ( -6.9 - 2.7)E 0 -3.8 - 1.5)1 0 (0/ 32) (0/ 11)

Ce-t44 (32) -1.1E 0 SWL-2 -1.91 -1 N0 DATA (0) ( -1.3 - 0.7)E 1 -9.8 - 6.6)E 0 (O0 32) (0/ 10)

Th-232 (32) 1.6E 0 SWL4 2.11 0 N0 DATA (0) -4.7 - 9.9)r 0 ( -4.2 - 6.3)2 0 (0/ 32) (0/ 11)

• Non-Routine refers to radionuclides exceeding the Reporting Levels in ODCM Attachment 3.21 of the ODCM 29

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radlological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Sediment (SE) UNITS: oCUkq dr Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range -s Non-Routine' LLD No. Detected- No. Detected- No. Detected-Be-7 (4) 7.43 1 SL-2 1.31 2 NO DATA (0) -2.5 - 15.1)1 1 (1.1 - 1.3)Z 2 (Of 4) (0/ 2)

K-40 (4) 6.61 3 SL34 6.81 3 NO DATA (0) 5.9 - 7.0)1 3 6.6 - 7.0)3 3 (4/ 4) (2/ 2)

Cr-51 (4) -1.2Z 1 SLS3 -7.01 0 NO DATA (0) ( -5.7 - 3.4)1 1 -4.8 - 3.4)1 1 (0/ 4) (0/ 2)

Mn-54 (4) -1.4X 0 SL2 3.51 -1 son DATl (0) -6.1 - 1.6)1 0 1.0 - 16.0)1 -1 (O/ 4) (0/ 2)

Co-57 (4) 2.91 0 SL-2 3.01 0 NO DATA (0) -1.9 - 7.3)1 0 2.6 - 3.5)X 0 (0/ 4) (0/ 2)

Co-58 (4) -5.01 0 SLY. -3.31 0 No DATA (0) -1.2 - -0.2)1 1 -4.6 - -1.9)3 0 (0/ 4) (0/ 2)

Fe-59 (4) 4.51 0 SL-3 2.01 1 NO DATA (0) -3.0 - 2.2)3 1 1.7 - 2.2)1 1 (0/ 4) C0/ 2)

Co-60 (4) 5.81 -1 SL-3 2.31 0 NO DATA (0) -5.5 - 5.5)1 0 ( -9.0 - 55.0)X -1 (0/ 4) (0/ 2)

Zn-65 (4) -1.81 0 SL-2 6.01 0 NO DATA (0) -2.1 - 1.6)1 1 -4.0 - 16.0)1 0 (0/ 4) (0/ 2)

S.-75 (4) 3.91 0 SL-2 6.8Z 0 NO DATA (0) -5.0 - 71.0)X -1 6.5 - 7.1)X 0 (0/ 4) (0/ 2) 30

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002.

Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Sediment (SE) UNITS: DCIkQ dry Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine' LLD No. Detected" No. Detected- No. Detected" Zr-95 (4) -4.4E 0 SL4 -2.OE 0 NO DATA (0) I -1.2 - 0.6)e 1 -1.0 - 0.6)e 1 (O/ *) (0/ 2)

Nb-95 (4) -1.23 1 SL4 -7.53 0 NO DATA (0) ( -1.6 - 0.1)1 1 (-1.6 - O.1)e 1 (O/ 4) (O/ 2)

Ru-103 (4) 4.2K 0 SL4 4.5E 0 NO DATA (0) ( 1.5 - 7.4)3 0 1.5 - 7.4)3 0 (O/ 4) (0/ 2)

Ru-106 (4) 1.6Z 1 SL-2 4.8Z 1 NO DATA (0) -1.1 - 0.8)3 2 1.5 - 8.0)e 1 (O/ 4) (O/ 2)

Ag-108m (4) 3.2e -1 SL4 6.3e 0 NO DATA (0) -7.7 - 7.4)3 0 5.1 3 - 7.4)E 0 (0/ 4) (O/ 2)

Ag-110m (4) -2.2z 0 SL-2 -3.53 -1 NO DATA (0) -1.2 - 0.4)3 1 C -3.1 - 2.4). 0 (O/ 4) (O/ 2)

Sb-124 (4) 4.23 0 SL-2 1.O 1 NO DATA (0) ( -4.0 - 23.0)3 0 ( -2.1 - 23.0)3 0 (O/ 4) (O/ 2)

Sb-125 (4) 2.1C 0 SL-4 5.53 0 No DATA (0) -1.2 - 2.3)3 1 -1.2 - 2.3)E 1 (O/ 4) (O/ 2) 1-131 (4) 1.33 1 SL-W 1.s5 1 NO DATA (0) ( -8.1 - 38.0)E 0 -8.1 - 38.0)3 0 (O/ 4) (0/ 2)

Cs-134 (4) 1SO -1.2e 1 S2J -3.4E 0 NO DATA (0) ( -4.0 - -0.1)3 1 ( -5.4 - -1.3)3 0 (0/ 4) (0/ 2) 31

DC Cook Nuclear Plant Units 1&2 - Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmentil Program Summary Indiana Michigan Power Co, DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Sediment (SE} UNITS: oCikq dry Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine' LLD No. Detected" No. Detected- No. Detected Cs-137 (4) ISO 4.93 0 SL-2 8.23 0 NO DATA (0) ( 5.0 - $3.0)3 -1 ( 7.9 - 3.5)3 0 (0/ 4) (0/ 2)

Ba-140 (4) 2.0 0 SL2 6.03 0 NO DATA (0) ( -1.7 - 1.3)3 1 ( 5.0 - 7.0)3 0 (0/ 4) (0/ 2)

La-140 (4) 2.7X -1 SL2 4.53 0 NO DATA (0) ( -8.0 - 13.1)3 0 ( -4.0 - 13.1)X 0 (0/ 4) (0/ 2)

Co-141 (4) 3.33 0 SWL 1.13 1 NO DATA (a) ( -9.8 - 13.0)3 0 ( 4.0 - 18.0)3 0 (O 4) (0/ 2)

Co-144 (4) 1.3X 1. S12 2.93 1 NO DATA (0) ( -2.5 - 5.1)3 1 ( 7.0 - 31.0)3 0 (0/ 4) (0/ 2)

Th-232 (4) 7.33 1 SL43 S.43 1 NO DATA (0) ( 6i3 - 8.6)3 1 ( 8.1 - 8.6)X 1 (1/ 4) (0/ 2)

• Non-Routine refers to radionuclides exceeding the Reporting Levels in ODCM Attachment 3.21 of the ODCM 32

-s

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January- December 2002)

MEDIUM: Milk (TM) UNITS: vCl/ka Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine' LLD No. Detected- No. Detected No. Detected" Be-7 (125) 1.5S 0 MR 3.0E 0 6.7E -1 (0) ( -1.9 - 3.5)3 1 ( -1.7 - 3.5)E 1 ( -2.9 - 2.2)E 1 (Of 75) (0/ 25) (0/ 50)

K-40 (125) 1.35 3 MR 1.9E 3 1.43 3 (0) ( 1.2 - 2.1)1 3 ( 1.6 - 2.1)E 3 1.2 - 1.5)3 3

-(75/ 75) (23/ 25) (50/ 50)

Cr-51 (125) 2.9Z 0 MR 5.2E 0 -1.3E 0 (0) ( -2.2 - 3.7)E 1 ( -2.2 - 3.7)E 1 ( -2.4 - 3.5)3 1 (0/ 75) (0/ 25) (0/ 50)

Mn-54 (125) -2.2E -1 LF 3.1E -1 1.1E -1 (0) ( -3.6 - 2.8)E 0 ( -1.7 - 2.5)3 0 -2.1 - 3.8)E 0 (0/ 75) (0/ 25) (0/ 50)

Co-57 (125) 2.1E -2 UR 1.73 -1 -2.3E -1 (0) ( -3.2 - 2.3)3 0 ( -1.2 - 1.8)3 0 ( -2.7 - 1.7)3 0 (0/ 75) (0/ 25) (0/ 50)

Co-So (125) -3.1E -1 SF -1.4E -2 -4.73 -1 (0) ( -4.8 - 3.5)3 0 -4.2 - 2.8)3 0 -2.7 - 3.1)3 0

-(0/ 75) (0/ 25) (0/ 50)

Fe-59 (125) -4.83 -1 WF 9.23 -1 4.13 -1 (0) ( -1.4 - 0.8)3 1 -1.3 - 0.5)3 1 -1.3 - 0.8)3 1 (0/ 75) (0/ 25) (0/ 50)

Co6-0 (125) 1.63 -1 WF 7.03 -1 5.43 -1 (0) ( -3.6 - 4.9)Z 0 ( -3.0 - 2.2)Z 0 -

_3.0 - 3.7)r 0 (0/ 75) (0/ 25) (Of 50)

Zn-55 (125) -1.8Z 0 LF 2.03 -1 -8.7E -1 (0) ( -1.5 - 2.1)3 1 ( -9.0 - 9.8)E 0 ( -1.5 - 1.0)3 1 (0/ 75) (0/ 25) (0/ 50)

Se-75 (125) 1.13 -1 MR 3.8E -1 -2.83 -2 (0) ( -4.9 - 4.3)E 0 ( -2.4 - 4.3)E 0 ( -3.4 - 3.4)3 0 (0/ 75) (0/ 25) (0/ 50) 33

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Milk (TM) UNITS: oCI/ka Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine- LLD No. Detected- No. Detected- No. Detected-zr-95 (125) -1.43 -1 WF 3.43 -1 4.42 -2 (0) -6.7 - 4.6)1 0 ( -4.1 - 4.3)3 0 ( -4.7 - 4.3)X 0 (0/ 75) (0/ 25) (Of 30)

-d Nb-S (125) -7.73 -1 -4.13 -1 -6.33 -1 (0) ( -5.8 - 4.7)3 0 ( -3.6 - 4.7)3 0 ( -4.9 - 3.5)X 0 (0/ 75) (0/ 25) (0/ 50)

Ru-103 (125) -8.51 -1 WF -5.63 -1 -1.01 0 (0) ( -5.1 - 4.3)X 0 ( -4.1 - 1.8)X 0 ( -4.1 - 1.8)X 0 (0/ 75) (0/ 25) (0/ 50)

Ru-106 (125) -1.1X 0 SF -5.71 -1 -2.21 0 (0) -3.1 - 3.0)3 1 ( -2.2 - 2.0)3 1 -2.6 - 2.2)X 1 (0/ 75) (0/ 25) (0/ 50)

Ag-108m (125) -2.33 -2 UR 6.4X -2 -2.43 -1 (0) -2.1 - 3.2)X 0 ( -1.5 - 3.2)1 0 -2.2 - 1.7)X 0 (0/ 75) (0/ 25) (Of 50)

Ag-11Om (125) -3.83 -1 MR -2.41 -2 -2.63 -1 (9) -6.2 - 6.1)3 0 ( -3.8 - 6.1)X 0 -5.9 - 3.0)3 0 (0/ 75) (0/ 25) (0/ 50)

Sb-124 (125) -9.31 -1 LF 2.21 -1 -1.73 -1 (0) -1.2 - O.6)3 I -9.9 _ 5.4)3 0 -1.3 - 0.8)3 1 (0/ 75) (0/ 25) (0/ 30)

Sb-125 (125) 8.33 -2 GTF 9.93 -1 -5.31 -1 (0) ( -8.6 - 7.4)3 0 -6.9 - 5.7)3 0 ( -8.5 - 5.8)X 0 (0/ 75) (Of 25) (0/ 50) 1131 (12S) l. 1.63 -l MR 1.83 -1 1.73 -1 (0) -2.1 - 8.0)3 -1 -1.2 - 8.0)X -1 -2.4 - 9.0)1 -1 (0/ 75) (0/ 25) (O 50)

Cs-134 (125) 15 1.73 -1 GTF 4.03 -1 -1.63 -1 (0) -4.3 - 4.9)3 0 -1.6 - 2.1)3 0 -4.3 - 2.8)X 0 (0/ 75) (0/ 25) (O/ 50) 34

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Milk (TM) UNITS: eCiika Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine LLD No. Detected No. Detected" No. Detected-Cs- 137 (125) i8 2.93 -1 UR 7.6Z -1 4.O0 -1 (a) ( -3.9 - 3.6)3 0 ( -2.5 - 3.6)Z 0 ( -3.9 - 3.8)3 0 (O/ 75) (Of 25) (O 50)

Ba-140 (125) 15 2.73 -1 UR 8.2E -1 7.2Z -2 (0) -6.2 - 5.7)3 0 ( -3.4 - 5.0)3 0 X -3.9 - 5.6)E 0 (C/ 75) (Of 25) (O 50)

La- 140 (125) 15 3.0Z -1 UR 9.33 -1 6.43 -2 (0) -7.1 - 6.5)3 0 ( -3.9 - 5.8)3 0 ( -4.5 - 6.4)3 0 (0/- 75) (Of 25) (O 50)

Ce-141 (125) -3.83 -1 MR -2.43 -1 -8.83 -1 (0) -7.5 - 5.6)3 0 ( -5.9 - 5.6)3 0 -7.3 - 4.7)3 0 (O 75) (Of 25) (Of 50)

Ce-I" (125) 1.8Z 0 PR 2.3X 0 8.03 -2 (0) -2.2 - 2.3)3 1 ( -1.7 - 2.5)3 1 -2.0 - 1.3)3 1 (O 75) (Of 25) (O/ 50)

Th-232 (125) 1.33 0 UR 4.03 0 1.83 0 (0) -2.0 - 2.2)X 1 ( -7.0 - 22.0)3 0 -1.1 - 1.0)/5 (Of 75) (Of 25) COf 30)

• Non-Routine refers to radionuclides exceeding the Reporting Levels In ODCM Attachment 3.21 of the ODCM 35

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Food Products ITF1 UNITS: oCI/ka wet Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine LLD No. Detected" No. Detected" No. Detected" -

B5-7 (3) 5.93 2 ONS.V D 1.13 3 -2.73 1 (0) ( 4.4 - 113.0)3 1 (1/ 2) (1/ 1) (O 1)

K-40 (3) 2.43 3 ONS-V D 2.63 3 2.03 3 (0) ( 2.2 - 2.6)3 3 (2/ 2) (1/ 1) (1/ 1)

Cr41 (3) 1.13 1 OFSa J 3.83 1 3.83 1 (0) X -1.3 - 3.5)3 1 (0/ 2) (Of 1) (Of 1)

Mn-54 (3) -1.13 0 ONSV D 0.03 0 -3.1X 0 (0) -2.1 - 0.0)3 0 (0f 2) (Of 1) (O 1)

Co-57 (3) 1.03 -1 ONS.V D 2.92 0 -9.03 -1 (0) -2.7 - 2.9)3 0 (0/ 2) (Of 1) (0o 1)'

Co-58 (3) 1.53 0 ONS-V D 5.23 0 3.03 -1 (0) ( -2.3 - 3.2)3 0 (0/ 2) (Of 1) (0/ 1)

Fe-59 (3) -1.53 1 ONS-0 D 1.33 1 -4.43 0 (0) ( -4.3 - 1.3)X 1 (0/ 2) to/ 1) t0/ 1)

Co-60 (3) -6.53 0 OFSG0 J 3.73 0 3.73 0 (0) ( -1.5 - 0.2)3 1 (0/ 2) (Of 1) (Of 1)

Zn-65 (3) 2.93 1 ONS-V 0 4.53 1 2.43 1 (0) 1 1.3 - 4.5)3 1 (0/ 2) (0/ 1) (0t 1)

SS-75 (3) 2.8X 0 ONS-V 0 3.43 0 1.83 0 (0) 2.1 - 3.4)3 0 (0/ 2) (0/ 1) (0/ 1) 36

DC Cook Nuclear Plant Units l&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January- December 2002)

MEDIUM: Food Products (TF) UNITS: oCI/ka wet Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine' LLD No. Detected- No. Detected- No. Detected-zr-95 (3) 1.25 1 ONS-V D 1.7E 1 4.4E 0 (0) 6.7 - 17.0)5 0 (0 2) (0/ 1) (0/ 1)

Nb-95 (3) -3.7E 0 OFS-G J 6.2E 0 6.2Z 0

- (0) -4.4 - -3.0)E 0 (0/ 2) (0/ 1) (0/ 1)

Ru-103 (3) -4.15 0 ONS-V D -1.2E 0 -4.35 0 (0) ( -7.1 - -1.2)E 0 (0/ 2) (0/ 1) (0/ 1)

Ru-106 (3) 3.15 1 ONS-V D S.6Z 1 -3.75 1 (0) C 5.0 - 56.0)5 0 (0/ 2) (0/ 1) (O/ 1)

Ag-108m (3) 1.15 0 ONS-V D 3.35 0 -5.SZ 0 (0) ( 5.0 - 33.0)5 -1 (O/ 2) (0/ 1) (0/ 1)

Ag-110m (3) -1.7Z 1 OFS-GJ 1.35 0 1.35 0 (0) ( -3.3 - -0.1)5 1 (0/ 2) (0/ 1) (0/ 1)

Sb-it24 (3) -1.35 1 ONSG 0 5.2E 0 -4.7Z 0 (0) -3.2 - O.S)E 1 (0/ 2) (0/ 1) (0/ 1)

Sb-125 (3) 1.15 1 ONS-V 3.05 1 -1.45 0 (0) -7.8 - 30.0)E 0 (0/ 2) (0/ 1) (0/ 1) 1-131 (3) 60 4.35 0 ONSV 0 1.85 1 1.0 0 (0) -9.3 - 1.0)Z 0 (0/ 2) (0/ 1) (0/ 1)

Cs-134 (3) 60 3.35 0 0ONS-VD 1.15 1 6.5E 0 (0) -4.0 - 10.7)E 0 (0/ 2) (0/ 1) (0/ 1) 37

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Food Products CTM) UNITS: oCIka wet Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine' LLD No. Detected" No. Detected No. Detected" Cs-137 (3) 60 -9.63 0 OFS-0 J -3.62 0 -3.63 0 (0) -9.9 - -9.2)3 0 (O 2) (Of 1) (Of 1)

Ba-140 (3) 6.33 0 ONS-V D 1.43 1 -1.8X 0 (0) -1.3 - 14.0)3 0 (0/ 2) (Of 1) (O 1)

La-140 (3) 7.33 0 ONS.V D 1.63 1I -2.13 a -

(0) -1.3 - 16.0)3 0 (0/ 2) (Of 1) (Of 1)

C-141 (3) 1.8X 0 ONS-0 D 1.33 1 2.93 0 (0) -9.0 - 12.5)X 0 (0/ 2) (Of 1) (O/ 1)

C-144 (3) -3.13 1 OFS- J -4.03 0 -4.o0 0 (0) -3.4 - -2.7)3 1 (0/ 2) (O/ 1) (Of 1)

Th-232 (3) -1.93 1 ONS-G D 3.3X 1 S.03 0 (0) -7.0 - 3.3)3 1 (0/ 2) (Of 1) (Of 1)

• Non-Routine refers to radionuclides exceeding the Reporting Levels in ODCM Attachment 3.21 of the ODCM 38

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Fish (FH1 UNITS: nCl/ka Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine' LLD No. Detected" No. Detected" No. Detected-Be-7 (8) 2.31 1 ONS.S 3.8BE 1 -2.51 1 3.8Z) I (0) ( -5.4 - 13.0)Z 1 -5.4 - 13.0)Z 1 (0/ 4) (0/ 2) (0/ 4)

K-40 (8) 3.01 3 OFS-N 3.5E 3 3.13 3 (0) ( 2.9 - 3.3)1 3 3.2 - 3.9)1 3 2.7 - 3.9)2 3 (4/ 4) (2/ 2)

Cr-51 (8) 4.91 1 OFS-S 1.31 2 (0) ( -5.0 - 21.0)E 1. 5.0 - 20.0)E 1 S(4/

5-7.6 - 20.0)14)

(0/ 4) (0/ 2) (0/ 4)

Mn-64 (8) 130 4.61 0 OFS-N 5.3Z 0 36.41

-4.51 01

( 0.0 - 9.9). 0 3.6 - 7.0)1 0 -1.7 - 0.7)1 1 (0)

(0/ 4) (0/ 2) (0/ 4)

Co-57 (B) -4.31 0 OFS-S 3.4E 0 -1.71 1 (0) ( -1.7 - 0.8)1 1 2.3 - 4.4)1 0 (-7.0 - 0.4)1 1 (0/ 4) (0/ 2) (0/ 4)

Co-5B (8) 130 9.21 -1 ONS-N 7.51 0 -6.01 0

-2.1 - 17.0)1 0 -1.4 - 0.2)1 1 (0) ( -1.5 - 1.7)1 1 (0/ 4)

(0/ 4) (0/ 2) 3.71 1 1.21 1 Fe-59 (8) 260 -1.01 1 OFS-S 1 -2.4 - 7.3)Z 1 (0) ( -5.1 - 0.9)1 1 0.0 - 7.3)1 (0/ 4)

(0/ 4) (0/ 2)

Co-60 (8) 130 3.3Z 0 ONS-N 6.51 0 1.11 0 (0) ( -2.0 - 14.0)Z 0 -1.0 - 14.0)1 0 (0/ 4) (0/ 2) (0/ 4) 1.51 0 -1.71 1 Zn-65 (8) 260 -1.01 1 3.0)1 0 -6.8 - 0.6)1 1 (0) ( -4.3 - 0.3)1 1 0.0 -

(0/ 4)

(0/ 4) (0/ 2) 6.3Z 0 -1.07 1 Se-75 (8) 5.7Z 0 ONS-N 4.0 .6)1 0 -3.2 - -0.2)E 1 (0) ( -1.2 - 2.2)1 1 -

(0/ 2) (0/ 4)

(0/ 4) 39

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Fish (FiHI UNITS: oCi/a Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-RoutIns LLD No. Detected- No. Detected" No. Detected" Zr-95 (8) -1.71 1 OFS-S 1.11 1 1.01 0 (0) -2.6 - -0.9)3 1 2.0 - 19.0)3 0 (0/ 4) (0/ 2) (0/ 4)

-d Nb-95 (8) 2.43 0 ONS. 2.01 1 -1.11 1 (0) (,-2.3 - 2.2)3 1 1.8 - 2.2)1 1 ( -3.0 - 2.1)3 1 (0/ 4) (0/ 2) (0/ 4)

Ru-103 (8) 5.01 -1 ONS-N 9.53 0 5.01 -1 (0) ( 11-1.4)3 1 5.0 - 14.0)1 0 ( -1.2 - 1.0)X 1 (0/ 4) (0/ 2) (0/ 4)

Ru-106 (8) -8.31 0 ONS-S 1.51 1 -1.1X 2 (0) -5.0 - 4.0)1 1 ( -1.0 - 4.0)1 1 ( -2.1 - 0.1)1 2 (0/ 4) (0/ 2) (0/ 4)

Ag-1O8m (8) 1.11 0 ON5S 2.21 0 -3.11 0 (0) -1.3 - 1.7)X 1 -1.3 - 1.7)X 1 ( -1.3 - 0.2)1 1 (0/ 4) (0/ 2) (0/ 4)

Ag-1im (8) -5.41 0 OFS-S 8.03 0 -3.S 0 (0) -1.9 - 0.5)1 1 -3.0 - 19.0)3 0 -2.9 - 1.9)X 1 (0/ 4) (0/ 2) (0/ 4)

Sb-i24 (8) 1.31 1 OFS-N 3.61 1 2.51 -1 (0) -1.6 - 6.5)1 1 2.9 - 4.2)3 1 ( -3.6 - 4.2)1 1 (0/ 4) (0/ 2) (0/ 4)

Sb-i125 (8) 7.51 0 ONS-S 8.01 0 -1.71 1 (0) -5.0 - 19.0)1 0 5.0 - 11.0)X 0 -5.1 - 1.1)X 1 (O/ 4) (0/ 2) (0/ 4) 1-131 (8) -2.9X 1 OFS-S 8.33 1 4.01 1 (0) -1.1 - 0.4)1 2 1.0 - 15.3)1 1 -1.4 - 15.5)X 1 (0/ 4) (0/ 2) (0/ 4)

Cs-134 (8) 130 3.21 0 OFS-N 6.51 0 -2.51 -2 (0) ( -3.0 - 100.0)1 -1 -3.1 - 16.0)1 0 -1.1 - 1.6)1 1 (0/ 4) (0/ 2) (0/ 4) 40

DC Cook Nuclear Plant Units 1&2 Annual Radiologicat Environmental Operating Report 2002 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January - December 2002)

MEDIUM: Fish (FH) UNITS: oC/Uka Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine- LLD No. Detected- No. Detected- No. Detected-Cs-137 (8) IS0 2.61 1 ONS.S 4.2Z 1 -4.21 0 (0) ( 4.8 - 49.0)1 0 ( 3.4 - 4.9)Z 1 ( -9.5 - 0.0)1 0 (1/ 4) (1/ 2) (O/ 4)

Ba-140 (8) -3.71 1 OFS-N 2.6Z 1 2.4Z 1 (0) ( -8.7 - -0.5)Z 1 ( 0.0 - 5.1)1 1 ( -1.4 - S.9)1 1 (O/ 4) (0/ 2) (O/ 4)

La-140 (8) -4.2Z 1 OFS-N 3.01 1 2.81 1 (0) ( -1.0 - -0.1)1 2 ( 0.0 - 5.9)1 1 ( -1.7 - 6.8)Z 1 (O 4) (0/ 2) (0/ 4)

Ce-141 (8) 1.0z 0 OFS-S 5.51 0 -1.71 1 (0) ( -1.9 - 1.5)Z 1 ( 3.0 - 8.0)1 0 ( -5.5 - O.8)1 1 (0/ 4) (0/ 2) (0/ 4)

Ce-44 (8) 1.1Z 1 OFS-N 3.9Z 1 1.51 1 (0) ( -5.0 - 6.5)Z 1 ( -3.0 - 80.0)1 0 ( -2.9 - 8.O)Z 1 (O/ 4) (O/ 2) (0/ 4)

Th-232 (8) 1.51 1 ONS-S 5.21 1 1.01 0 (0) ( -8.1 - 5.3)1 1 ( 5.0 - 5.3)r 1 ( -4.3 - 8.3)1 1 (O/ 4) (0/ 2) (O/ 4)

• Non-Routine refers to radionuclides exceeding the Reporting Levels In ODCM Attachment 3.21 of the ODCM 41

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.2 Environmental TLD Measurements 2002 WDICATOR ILa CONTROLQTLDS RHGHEST MEAN SBN MEAN MEAN MEAN RANGE RANGE RANGE (NO. MEASUREMENTS) (N0. MEASUREMENTS) (NO. MEASUREMENTS)*

52 +/- 0.4 5.8 +/- 0.7 7.0

• 0.3 4.1 - 6.0 4.4 - 7.3 6.8 - 7.3 (48) (60) (4)

• Each "measurenmet is based on quaerly readings from five TLD elenmts. Units are micr-R per hour.

42

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 3.3 ENVIRONMENTAL TLD DATA

SUMMARY

2002 (Micro-R per hour) 1ST QUARTER 2ND QUARTER 3RD QUARTER 4TH QUARTER Annal Station Average Nume Esu SD Exoum & Pxposure ii Expsure M Exposur T-l 5.2

• 0.5 5.1 a 0.2 5.1 a 0.3 5.4

• 0.3 5.2 T-2 5.2 t 0.2 5.1 a 0.2 5.0 a 0.3 5.3 a 0.3 5.2 T-3 4.6

• 0.1 4.2 a 0.2 4.1 0.2 5.0 a 0.2 4.5 T-4 5.9

• 0.1 5.3 t 0.2 5.4 a 0.4 6.0 0.2 5.7 T-5 5.3 a 0.2 5.1 a 0.2 5.0 a 0.3 5.5 a 0.2 5.2 T-6 5.2 t 0.1 5.0 a 0.2 5.0 a 0.2 5.3

• 0.2 5.1 T-7 5.1 t 0.3 5.0 a 0.2 5.1 a 0.3 5.4 0.2 5.2 T-8 5.5 a 0.2 5.1 a 0.2 5.2 a 0.2 5.6 a 0.3 5.3 T-9 5.4

• 0.2 5.0 a 0.3 4.8 a 0.3 5.5 0.2 5.1 T-10 5.8 t 0.3 5.2

• 0.4 5.2

• 0.3 5.5 a 0.3 5.3 T-1l 5.4 a 0.2 5.0

• 0.2 5.3 a 0.8 5.5 a 0.2 5.3 T-12 5.4

• 0.2 5.2 t 0.2 5.0 0.2 5.7 0.3 5.3 NBF 6.0

• 0.2 6.4 a 0.2 5.6 a 0.2 6.0 a 0.3 6.0 SBN 6.9 a 0.2 6.8 0.4 6.8 a 0.3 7.3 0.2 7.0 DOW 5.2 t 0.2 5.1 0.3 4.6 0.2 5.4 0.2 5.0 COL 5.2 a 0.4 4.7 0.2 4.4 0.2 5.2 0.2 4.8 OFT-I 6.0 a 1.17 5.2 0.2 '5.1 0.2 5.9 0.2 5.4 OFT-2 5.2 a 0.3 5.0 a 0.2 4.8 a 0.3 5.4 0.3 5.1 OFr-3 5.8 a 0.2 5.3 a 0.2 5.2 a 0.3 5.8 a 0.2 5.4 OF1-4 5.8 a 0.2 5.6

• 0.2 5.5 0.3 6.0 a 0.2 5.7 OFT-S 6.3 a 0.2 5.4 t 0.2 5.8 a 0.4 6.0 0.4 5.7 OFr-6 6.9 a 0.2 6.3 a 0.3 6.8 a 0.3 7.3 a 0.3 6.8 OFr-7 5.4 t 0.1 5.2 a 0.2 5.4 a 0.3 5.7 a 0.2 5.4 0FI-8 6.6

• 0.4 5.2 t 0.2 6.7 t 0.5 6.8

• 0.3 6.2 OFr-9 6.0 2 0.3 5.7 0.2 5.6 a 0.3 6.0 0.4 5.8 OFr-10 5.5 : 0.2. 5.0 0.3 5.1 a02 6.0

• 0.3 5.4 OFT-II 6.5

• 0.4 6.4 a 0.2 6.3 t 0.5 6.7

• 0.3 6.5 43

DC Cook Nuclear Plant Units 1&21 Annual Radiological Environmental Operating Report 2002

4. ANALYSIS OF ENVIRONMENTAL RESULTS 4.1 Sampling Program Deviations I

The Off-Site Dose Calculation Manual (ODCM) states in Section 3.5 that the environmental sampling and analysis program shall be conducted as specified in Attachments 3.19 at the locations specified in the same attachment. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment or other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period.

All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Section 3.5.2 of the ODCM. The following deviations are noted for the 2002-sampling program:

1. 1-2-02 to 1-9-02: Air Sample Station, ONS-1/AVS-28 number 5501 - found off and replaced. Failure of automatic sampling equipment, no condition report required 1AW procedure RPP-632.

2. 1-4-02 to 1-9-02: Surface Water, SWL-2/SWL not collected due to hazardous conditions (ice).

3. 3-10-02: Surface Water, SWL-2/SWL not collected due to hazardous conditions (ice and waves).

4. 6-5-02 to 6-26-02: Air Sample Station, ONS Fire in the 345 KV yard and failure of automatic sampling equipment delayed the collection of media on 6-12-02 (8 days versus the 7 day collection requirement).

5. 6-12-02 to 6-19-02: Air Sample Station, ONS sample affected by the failure of automatic sampling equipment.

No Condition Report generated in accordance with procedure RPP-632, step 3.3. Actual run time was 156:54 hours versus a typical 168:00 hours. No additional actions were taken at this time.

6. 6-19-02 to 6-26-02: Air Sample Station, ONS sample affected by the failures of automatic sampling equipment.

No Condition Report generated in accordance with procedure RPP-632, step 3.3. Actual run time was 144:26 hours versus a typical 168:00 hours. Air sampler was replaced to avoid recurrence.

7. 7/10/02 to 7/17/02: Air Sample Station, DOW - power supply interrupted (run time 154:52) documented in Condition Report (CR) 02227013. Condition was evaluated as likely weather related. Off-Site Dose Calculation Manual (ODCM) required LLDs were satisfied. No additional actions were taken at this time. J

8. 7/31/02 to 87/02: Air Sample Station, ONS power supply interrupted (run time 37:22) documented in CR 02220030. Condition was evaluated as likely weather related. ODCM required LLDs were not satisfied. No additional actions were taken at this time.

9. 8/7/02 to 8/14/02: Air Sample Station, DOW - power supply interrupted (run time 31:23) documented in CR 02227013. Condition was evaluated as likely weather related. ODCM required LLDs were not satisfied. No additional actions were taken at this time.

10. 8/14/02 to 8/21/02: Air Sample Station, COL - power supply interrupted (run time 69:08) evaluated as likely weather related. Per section 3 of 12-THP-6010-RPP-632 "Collection of Environmental Air Samples" no CR required for malfunction of automatic sampling equipment. ODCM required LLDs were satisfied. No additional actions were taken at this time.

11. 8/21/02 to 8128/02: Air Sample Station, ONS power supply interrupted and no sample was collected therefore ODCM required LLDs were not satisfied. Documented in CR 02233051 and determined to be 44

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 dirty upstream power supply breaker contacts which reduced voltage to a value below the minimum required to operate sampling equipment.

12. 9/3/02: ONS-6 and DOW air samplers remained in service after calibration due dates had been exceeded due to human performance failures. Affected equipment was promptly replaced with calibrated samplers. "As Found" testing indicated this equipment had been functioning properly and an evaluation of air sample analysis results noted no anomalous values. In order to avoid recurrence of this issue, the personnel involved were counseled using appropriate plant processes (example: "Management Action Response Checklists"). Condition Report CR 02246015 was issued.

13. 12/111/02tol2119/02:ONS-3 air samples were not collected every seven days as required by the ODCM due to potential for switching evolutions in the 345 KV yard (i.e. possible hazardous conditions).

Actual collection interval was eight days which is within the allowed 25% grace period. No additional action was taken at this time.

4.2 Comparison of Achieved LLD with Requirements Attachment 3.20 ODCM (Table 2.4 in this report) lists the required Lower Limits of Detection (LLDs) for routine environmental sample analyses. As discussed in section 3.5.2 Bases, on occasion, an LLD is not achieved due to situations such as a low sample volume. In such a case, the ODCM requires the identification and discussion of the contributing factors in the Annual Radiological Environmental Operating Report, these are summarized below. Typical sensitivities achieved in the lab analysis are at least 2.5 to 3 times better than that required by the ODCM. For each analysis having an LLD requirement the a posteriorior after the fact LLD calculated for that analysis was compared with the required LLD.

1. 12/27/01 to 1/9/02: STJ and LTW drinking water samples La-140 MDC not met due to lab error on reference date. Issue was documented in DC Cook condition report 02169079. No additional actions were taken at this time.

2. 7/25/02 to 8/21/02: LTW and STJ (Lake Township and Saint Joseph) ODCM required LLDs for 1-131 were not met due to incorrect reference date errors entered at the analytical laboratory. Lab Sample ID numbers L-3637-01 and L-3627-02 were affected. This issue was documented in Cook Plant CR 03007022 and lab CR 03-01(current status: open) In order to avoid recurrence of this issue, DC Cook Personnel involved were counseled using appropriate plant processes (example: "Management Action Response Checklists").

3. 7/31/02 to 8n1/02: ONS-5 Air Sample Station power supply interrupted (run time 37:22) documented in CR 02220030. Condition was evaluated as likely weather related. ODCM required LLDs were not satisfied. No additional actions taken at this time.

4. 8n/02 to 8/14/02: DOW Air Sample Station power supply interrupted (run time 31:23) documented in CR 02227013. Condition was evaluated as likely weather related. ODCM required LLDs were not satisfied. No additional actions taken at this time.

5. 8/21/02 to 8/28/02: ONS-4 Air Sample Station power supply interrupted. No sample collected therefore ODCM required LLDs were not satisfied. Documented in CR 02233051 and evaluated to be dirty upstream power supply breaker contacts which reduced voltage to a value below the minimum required to operate sampling equipment.

45

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 4.3 Results Compared Against Reporting Levels _

ODCM Section 3.5.2 requires a discussion in the Annual Radiological Environmental Operating Report of any instance that a radionuclide concentration exceeds the reporting levels given in Attachment 3.21 (Table 2A in this report).

Reporting Levels are the environmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, -

Appendix L. It should be noted that environmental concentrations are averaged over calendar quarters for the purposes of this comparison, and that Reporting Levels apply only to measured levels of radioactivity due to plant effluents. During 2002, no Reporting Levels were exceeded.

4.4 Data Analysis by Media Type.

The 2002 REMP data for each media type are discussed below. These are arranged in the same order as in Table 3. 1, and are further categorized by pathway. Graphical plots of monitoring data are also shown in Figures 4.1 to 4.5. With respect to data plots, all 2002 results are plotted, whether they are "detectable" or "non-detectable."

4.4.1 Air Particulate Air particulates are collected weekly on 47 mm glass fiber filters at six indicator locations and four control locations, and are analyzed for gross beta radioactivity. Gamma isotopic analyses are performed on the quarterly composites of each location.

As shown in figure 4.1, there is no difference between the average monthly gross beta concentration at the indicator stations and the control stations. Notable in the graph is the distinct annual cycle. The gross beta concentration is seen to fluctuate over the year due to seasonal changes in the naturally occurring airborne radioactivity. The gross beta concentrations at the indicator stations are similar to the control station and fluctuate in the same manner. The step increase in the concentration is most likely due to the use of a new analytical laboratory in 2002 and differences in the equipment calibration.

The quarterly composites of the weekly air particulate filters were analyzed for gamma radioactivity. The results, shown in Tables 3.1, indicate the presence of naturally occurring Be-7, which is produced by cosmic processes. No positive results were observed for any other isotopes.

46

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Figure 4.1 AVERAGE MONTHLY GROSS BETA IN AIR PARTICULATES 45 40 35 a.Ii 30 I 25 L'i I. I x I a; i #0 uLkluM5Aw2LI IV 20 15 01.1 b.J %Ytv4

- F . Wlb fi 9" r 8~* 103/4/ 00V~'t FXJ '

A5r V 1t 10 S

0

-4Indicators Controls 4.4.2 Airborne Iodine Airborne iodine samples are collected weekly in conjunction with the air particulate filters. The charcoal cartridges are analyzed for Iodine-131. No iodine was detected in any of the Indicator or Control samples.

C-l 47

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 4.4.3 Ground Water (Well)

Ground water samples are collected from fourteen well locations and analyzed for gamma isotopic and tritium. K-40 was identified in five samples and AcTh-228 was identified in one sample, both nuclides are naturally occurring and may be present in ground water. No tritium was identified in any of the samples during 2002. Figures 4.2, 4.3 and 4.4 plot the tritium in ground water since 1980.

Figure 4.2 TRITIUM IN GROUNDWATER 20000 18000 16000 C

Pi t 14000 co 12000 d 10000 0

5 8000 S

0.

M

" 6000 4000 2000 l+Weli-l 0 well-2 +Well-3 C.I <

48

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Figure 4.3 TRITIUM IN GROUNDWATER 20000 18000 16000 20

@ 14000

0. 12000 X~

A d 10000 6

0

- 8000 6000 I0 lAVA~

K 4000 o--

\M IA i/\l Ahn A 0~e! ee Iee I"e Ac e°Ne p lbGe e ~e.:GeSSeGe e xe H eO ° s° b

-Well4 +-Well-5 4 Well-fl Well--7 c- &J 49

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Figure 4.4 TRITIUM INGROUNDWATER 20000 18000 16000 14000 o12000 0

0 0

ci 10000 /\

-- 000 -

-S 6000 A 4000 0.

2000 -

l+Wel1-8 ~wellq A-well-lo -well-11 W~Well-12 +Welff-13Wll-C-0?

50

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 4.4.4 Drinking Water Drinking water samples are collected from one indicator and one control station and analyzed for gamma isotopic, gross beta radioactivity and a quarterly composite for tritium. A specific Iodine 131 low-level analysis, performed on all samples to achieve a MDC of I pCi/kg, indicated that no Iodine- 131 was present. During 2002, gross beta radioactivity was found in 16 indicator and 17 control samples, leading to the conclusion that the gross beta activity is due to naturally occurring nuclides. While no tritium was identified in any 2002 samples, one control sample did contain naturally occurring K-40 . Figure 4.5 shows a plot of the tritium data since 1989. Of note for 2002 is the fact that all data is plotted, whether the results are negative or positive as described above in section 4.4.

Figure 4.5 TRITIUM INDRINKING WATER 1200 1000 800 800 400 200 0

-200

-400 '

qp cp c' qN # # 0 <P q c.? 0 0 0 0 qA 5g 0 5P 0 c.P <' 1 0

' sy "c Y V) S' V "o S' 'Ipt o .e 3y S3, ' S s, l-- Lake Township - St. Joseph 4.4.5 SurfaceWater In 2002, surface water samples are collected from three locations and analyzed for gamma emitting radionuclides and a quarterly tritium. A specific Iodine-131 low-level analysis, performed on all samples to achieve a MDC of I pCi/kg, indicated that no Iodine-131 was present. Table 3.1 shows that no gamma emitting nuclides or tritium were detected in any of the samples collected in 2002.

4.4.6 Sediment Semiannual samples of lake sediments are collected from two indicator stations and analyzed for gamma emitting nuclides. During 2002, naturally occurring K-40 was detected in all samples and AcTh-228 was detected in one sample.

5C1 c6

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 4A.7 Milk Milk samples were collected bi-weekly from three indicator and two control stations during 2002. Typical levels of K-40, ranging from 1200 to 2100 pCi/Kg, was detected in the samples. An iodine-131 specific analysis performed to achieve a MDC of 1 pCi/Kg did not detect any I-131 in the samples.

4A.8 Food Products Vegetable samples (grapes/broad leaf) analyzed for gamma emitting nuclides indicate only the presence of naturally occurring K-40 and Be-7. No other gamma emitting nuclides were detected in any of the samples 4.4.9 Fish Fish samples were collected semiannually at two indicator and two control locations. Cs-137 was observed in one indicator sample and K-40 was detected in all the samples. Although the presence of Cs-137 in this media is historically attributed to residual weapons fallout, the Cs-137 in fish is treated conservatively and an assessment of the dose consequence is provided in Section 5.

4.4.10 Gamma Exposure Rate Direct radiation is continuously measured at 27 locations surrounding the DC Cook Plant with thermoluminescent dosimeters (TLDs). All TLDs are collected quarterly for readout at the FANPEL.

The results in Tables 3.2 and 3.3 show that the mean exposure rates for the Indicator and Control categories are not significantly different in 2002. As shown in Figure 4.6, there is a distinct annual cycle at both indicator and control locations. The lowest point of the cycle occurs during the winter months. This is due primarily to the attenuating effect of the snow cover on radon emissions and on direct irradiation by naturally-occurring radionuclides in the soil. Differing amounts of these radionuclides in the underlying soil, rock or nearby building materials result in different radiation levels between one field site and another.

52

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Figure 4.6 DIRECT RADIATION - QUARTERLY TLD RESULTS 9

f 'YI I Is 'I 'I1I) ~ I I) '

-TLD Controls -- TLD Indicators In 2002 the calibration and processing of the TLD's was conducted by the Framatome ANP Laboratory. The Panasonic 802s (UD-814) TLD's which had historically been used to measure direct radioactivity around DC Cook were replaced with Panasonic model UD-804 ASI TLD.

53

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002

5. OFF-SITE DOSE EQUIVALENT COMMITMENTS The purpose of this section is to evaluate off-site dose consequences (dose equivalent commitments) associated with the stations' radioactive liquid and airborne effluents. The method utilizes Regulatory Guide 1.109 / REMODCM models and actual measurements of the concentrations of radioactivity in environmental media to compute the dose consequences resulting from the consumption of these foods.

The standards for the maximum dose to an individual of the general public, taken from 40CFR190, is 25 mRem to the whole body, 75 mRem to the thyroid and 25 mRem to any other organ. These standards are a fraction of the average USA background radiation of 300 mRem per year given in NRCP94.

During 2002, Cs-137 was measured in one out of four fish samples and although attributed to weapons fallout a potential annual dose commitment to a maximum exposed individual of 0.04 mRem (Teen Liver) has been estimated using conservative assumptions regarding consumption rate and a constant Cs-1 37 concentration in fish of 49.0 pCi/kg. This dose is 0.16% of the maximum allowed dose of 25 mRem.

54

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 L

6.

SUMMARY

OF REMP, ODCM AND VENDOR CHANGES DC Cook procedure 12-THP-6010-RPP-639, "Annual Radiological Environmental Operating Report Preparation and Submittal, requires DC Cook to provide a summary of REMP, ODCM and Vendor changes. A summary of procedures revised in 2002 follows:

DC COOK: REMP Procedures, ODCM, Process Control Procedures:

1. 12-THP-6010-RPP-639, "Annual Radiological Environmental Operating Report (AEROR) Preparation and Submittal", revision 2b.

• Administrative updates to reflect requirements in PMP-2010-PRC-001, Procedure Writing.

2. 12-THP-6010-RPP-640, "Land Use Census", revision 2.

• Added section and steps in Data Sheet to identify the closest livestock for human consumption. Option in ODCM/MIDAS as potential dose pathway.

• Added section on "Notification and Updates".

• Added source reference to Technical Specifications.

• Added section providing guidance for distance measuring guidance. Used by the MIDAS system in dose calculation.

• Administrative updates to reflect requirements in PMP-2010-PRC-001, Procedure Writing.

3. 12-THP-6010-RPP-643, "Quarterly Review of Radiological Environmental Monitoring Program (REMP) Data".

• Note added to improve direction to prevent delay of reviews per CR 02115019.

4. PMP-6010-OSD-001, "Off-Site Dose Calculation Manual", revision 17

• Section 3.2.1 of Bases, Description of NRC Commitment 1010, was added.

• Reference to the NRC Commitment 1010 was inserted into ODCM 5.2.lgg.

• Attachment 3.16, worst case X/Q and D/Q values changed due to ODCM required evaluation of 2001 meteorological data.

• Attachment 3.19, Expanded wording in Footnote "Ingestion - Milk" to reflect guidance in NUREG 1301 on sampling frequency if animals are fed stored feed vs feeding on pasture. Clarification of off-site TLD station description.

5. PMP-6010-PCP-900, "Radioactive Waste Process Control Program", revision 4b

• Reference removed in section 1.1 to reflect Correction Criteria:b.

• Added terms and meaning for waste acceptance criteria and/or guidance.

• The discussion on sorting and segregation of DAW was expanded and moved to sections 3.7.2/3.8.2 and removed from section 3.1.12.

• Administrative changes throughout procedure.

• Wording change in section 3.3.3 from restricted area to radiologically controlled area.

• Expanded sections 3.9.2 and 3.10.1 to clarify information on Class A waste filters ) waste.

• Removed a Source Reference as an NRC Commitment from section 5.2.1 t as this item had been incorrectly categorized as an NRC Commitment. A Correction was made and the source was closed.

• Attachment I changed to reflect the current department with responsibilities for the processing of waste filters.

55

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Table 6.1 FRAMATOME ANP ENVIRONMENTAL LABORATORY UPDATED PROCEDURES ISSUED DURING CALENDAR YEAR 2002 PROC. NO. lTILE ENO.l EDATE

SUMMARY

OF CHANGES Added sections necessary to address NELAC rules.

14 Corrected references to a Form, removed unnecessary notes 010 DE&S Environmental 15 05/07102 on Forms.

Pbrtoc nurs a16 Updated all references to Framatome ANP from Duke Procedures__Engineering.

120 Sample Storage and IS 09/30102 Long-Term storage activities were modified to ease the Accountability process of holding and tracking samples until disposal.

200 Sample Receipt and General 18 01/29102 Added requirements for NELAC processing.

Chain-Of-Custody Enhanced instructions on entering samples in the LIMS.

201 S usple Usind CIn o 0/11/02 Deleted long-term storage steps that are also contained in Procedure 120. Tech Spec sample validation was removed.

Preparation of Environmental 305 and Bioassay Media for is 102702 Updated all references to Framatome ANP from Duke Analysis of Gamma Ray Engineering.

Emitters Preparation and Analysis of Air 310 Particulate and Smear Samples 14 06121102 References to equations were updated due to software for Gross Alpha and/or Gross changes. LIMS data entry steps were clarified.

Beta Radioactivity Preparation and Analysis of Environmental Water and 19 01/29/02 Added NELAC required sections to the Procedure.

320 Soil/Sediment/Sludge Samples 20 06121/02 References to equations were updated due to software for Gross Alpha andtor Gross changes. LIMS data entry steps were clarified.

Beta Radioactivity The Determination of Iodine-340 131 in Environmental Media 22 01/29/02 Added NELAC required sections to the Procedure.

Using Anion Exchange Chromatography The Determnination of Sr-89,90 e DAdded steps for LIMS processing and added section to 368 in Environmental Media Via 10 -03/01/02 r o clarify the separation and purification of water samples.

Cerenkov Counting Determination of Elements by Added clarifying steps for startup, profiling the optics and Spectroflame Modula 369 Inductively Coupled P 3 09/13/02 standardizing. QC frequency was increased to one for every InductivelySoupletrometern five samples (vice ten).

(ICP) Spectrometer The Determination of Tritium Added section to permit screening analysis of waters 371 in Environmental and Bioassay 19 01/25/02 without performance of distillation.

Matrices 56

DC Cook Nuclear Plant Units 1 c2 Annual Radiological Environmental Operating Report 2002 PROC. NO. TITLE RNEOV. DATE

SUMMARY

OF CHANGES Operation and Calibration of Modifications to Forms made to reflect current calibration 422 the Tennelec Model LB5500 8 05/28/02 tcnqe.Rfrne oLM eeudtd Low Sstemtechniques.

Bckgrund References to LIMS were uIpdated.

Low Background System _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Added the ability to count samples using Alpha Only and Operation and Calibration of Alpha Then Beta methods, clarified steps to end or reload

-. 0 423Lthe Tn ackgMonde L4 1samples, updated Procedure for LIMS and Framatome ANP W Low Background System references.

Updated company references to Framatome ANP from Optheertionaand Caibrioence ofDuke Engineering, incorporated use of QC trending 430 the Beta-Gamma Coincidence 12 11/30102 software, modified the required number of calibration Units for 1-131 points.

Operation and Calibration of Modified to incorporate steps to initiate counting using 490 the LKB Model 1415 Liquid 4 01/07/02 either the LKB 1414 or 1415 model counter.

Scintillation Counter Permits electronic version of the Sample Submission Form Record Keeping and 12 01/2902 and adds documentation of the time of sample receipt.

605 Reporting: Sample Submission 13 09/20102 Sample Submission Form updated for LIMS program.

Form Records Procedure was separated into Environmental and Part 50161 sections for clarification.

Record Keeping and Reporting: Radiological Updated to implement LIMS calculations for reporting 661 Environmental Monitoring 6 06/01102 levels.

Program Reporting Levels 682 Integration of a New Client 0 0611102 New procedure for implementation of LIMS.

into LIMS 683 Integration of a New Product in 0 06/12/02 New procedure for implementation of LIMS.

to LIMS 688 Environmental and Bioassay 0 06/11/02 New procedure for implementation of LIMS.

Data Entry Using LIMS 692 Report Generation Using LIMS 1 06/11/02 Enhanced instructions for generating reports from LIMS.

Added Instrument Repair History Form, steps for 710 Quality Control of Laboratory 18 01/29/02 acceptance of balance repair services, added NELAC Instrumentation required controls. -

Added NELAC required controls, required all personnel to 750 Laboratory Training And 10 01/24/02 perform Read & Sign training, added hazardous waste Qualification Guideline training for chemists, added ethics training, and added NEACL Demonstration of Capability forms.

Laboratory Quality Assurance 0 0129/02 New procedure to direct detailed actions on handling and Control Programs dosimetry and radiochemistry QC samples.

57

DC Cook Nuclear Plant Units I&2 Annual Radiological Environmental Operating Report 2002

7. REFERENCES

1. USNRC Radiological Assessment Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.

2. NCRP Report No. 94, Exposure of the Population in the United States and Canada from Natural Background Radiation, National Council on Radiation Protection and Measurements, 1987.

3. Ionizing Radiation: Sources and Biological Effects, United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), 1982 Report to the General Assembly.

4. Kathren, Ronald L., Radioactivity and the Environment - Sources. Distribution, and Surveillance. Harwood Academic Publishers, New York, 1984.

5. NRC Generic Letter 89-01,

Subject:

Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program. Dated January 31, 1989.

58

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 APPENDIX A SYNOPSIS OF ANALYSIS TECHNIQUES

-4 A-I

DC Cook Nuclear Plant Units l&2 Annual Radiological Environmental Operating Report 2002 GROSS ALPHA/BETA ANALYSIS Air particulate samples, collected on a weekly basis aid in verifying the in-plant controls used for monitoring the release of radioactive materials. The samples are transmitted to the laboratory for gross beta and/or gross alpha radioactivity analysis. Air particulate samples are analyzed on a low background alpha/beta gas proportional counting unit, for a predetermined amount of time, following a delay of a 100-hour minimum to allow for the decay of Radon products.

Blank filters, either provided by the client, or of the same size and type as the client filters are used for background subtraction. If the beta activity concentration is greater than 0.2 pCi/m 3, the sample may need to be analyzed for individual gamma emitters. Each sample is composited by sampling location and held until the end of the quarter for a gamma isotopic analysis.

Environmental water samples are also analyzed for gross alpha and/or gross beta radioactivity. Measurable amounts of alpha and beta emitting radionuclides, either naturally occurring or artificially produced, are found in most environmental water samples. Gross alpha and gross beta measurements are rapid screening methods which may indicate the need for a more detailed isotopic analysis. Samples are evaporated to near dryness and quantitatively transferred to concentric ring, stainless steel planchets, where the evaporation is completed. A gas proportional counter is used for the measurement of gross alpha/gross beta radioactivity. Solid deposition is an interference in this method and must be accounted for during instrument calibration.

No decay is accounted for in the gross alpha/beta activity concentration calculations since the radionuclides of origin are not known. The minimum detectable concentration depends on sample size, counting system characteristics, background, and counting time. Typical counting times for gross alpha/beta analyses are seventy five minutes for waters and sixty minutes for air particulate filters.

GAMMA SPECTROMETRY The following media are typically analyzed: gamma isotopic content; milk, water, charcoal cartridges, airborne particulate filters, biological material (which includes aquatic animals, plants, and terrestrial vegetation), and sediment or soil samples. Samples are prepared by various controlled methods (blending, drying, milling) in order to maximize the volume which can be analyzed, and to achieve sample homogeneity. In order to ensure the precision and accuracy of the gamma measurements, specific counting containers are used to load sample media in a reproducible manner. Sample spectra are collected via high purity germanium based gamma ray spectrometry detection systems. The gamma spectrometry software can account for baseline corrections, background peak interferences, and photopeak multiplet resolution. Detected photopeaks are identified using a comprehensive library, specifically tailored for environmental monitoring around nuclear power facilities. Typical counting times for gamma spectrometry analyses vary from 7,200 to 30,000 seconds.

Decay corrections are typically made from the time of count to the end of collection. Exceptions are as follows:

composite water samples, which may be decayed to the mid-point of sampling, and charcoal cartridges and air particulate composites, for which a "decay during sampling" calculation is included. All gamma spectrometry analyses account for decay during the counting interval.

Serial decay corrections are required for parent/daughter radionuclide relationships. Milk and water samples requiring analysis for Ba-140/La-140 are held for eight days after collection, before analysis, in order to allow most of the unsupported La-140 (present at the time of collection) to decay and in order for the La-140 to achieve transient equilibrium with Ba-140. The La-140 concentration is then calculated from the parent, Ba-140. The Nb-95 A-2

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 concentration, however, is assumed to be unsupported, and is calculated independently of its parent Zr-95, as long as Zr-95 is not detected in the sample. If Zr-95 is detected, the supported Nb-95 is calculated and subtracted from the total Nb-95, to yield the unsupported Nb-95 concentration.

LOW LEVEL IODINE ANALYSIS The low required detection limit for 1-131 in milk and water samples can only be achieved by radiochemical separation and concentration of the iodine. Milk samples may be preserved with sodium bisulfate or refrigerated after collection and are treated as soon as they arrive at the Laboratory with formaldehyde and methimazole (if preservation was not performed in the field). Vegetation samples are treated with NAOH. A known amount of stable iodide is added to the sample to quantify the final recovery. When Iodine-131 activity is observed or anticipated, the original iodide content of the sample is also quantified via an Orion EA 940 Expandable Ion Analyzer. The technique for initially isolating the iodine in a sample depends on its biological or physical form.

Vegetation is leached with sodium hydroxide, baked to an ash, and filtered; the iodide is then confined on anion exchange resin. Soil is leached with sodium hydroxide, then filtered. Drinking water, estuary, river, and ground water is treated with bleach, then reduced using hydroxylamine hydrochloride and sodium bisulfite to convert any form of iodine to iodide which is then confined on anion exchange resin. Preserved milk undergoes anion exchange.

Now isolated, the sample's iodine content is ready to be oxidized to periodate by bleach, treated with nitric acid, then extracted in toluene, wherein it is reduced to elemental iodine by hydroxylamine hydrochloride, reduced to iodide by sodium bisulfite, and finally precipitated as cuprous iodide for I- 13 1 measurement by beta-gamma coincidence counting.

The beta-gamma coincidence system combines a plastic scintillator beta detector and associated electronics with a well-type Na(l) gamma detector. The amplified outputs from the detector assemblies are processed by timing single channel analyzers (TSCA). The gamma TSCA is optimized for the full width at tenth maximum of the 364.5 keV gamma photon of I-131. The resulting signal from each TSCA is relayed to a coincidence analyzer. The beta transition and prompt 364.5 keV gamma transition from I-13 1 register a coincidence count. Beta gamma coincidence counting allows for a very low background since the system is optimized for I-131. A typical counting time for low level iodine analysis is two hundred minutes.

H-3 ANALYSIS The determination of tritium in environmental matrices basically involves a sample preparation step followed by distillation and analysis of the pure distillate by liquid scintillation spectrometry. The tritium counting efficiency is determined using an efficiency curve generated as a function of sample quench. A set of NIST traceable standards is used for calibration.

The sample preparation step may involve extracting H-3 from the matrix in the presence of NaOH and KMnO 4 or in the presence of HCI and H2 02 and allowing for sufficient equilibration time so that a complete transposition of tritium with stable hydrogen has occurred.

A window is set on the multi-channel analyzer associated with the liquid scintillation counting system which is optimized for the tritium beta energy. Additional widows are also set and evaluated to ensure that the distilled samples are free of interferences. A typical counting time for H-3 analysis is fifteen minutes.

A-3

DC Cook Nuclear Plant Units I&2 Annual Radiological Environmental Operating Report 2002 SR-89/90 ANALYSIS The determination of Sr-89,90 in environmental media is achieved primarily by pre-concentration followed by separation and purification. Strontium is pre-concentrated as the carbonate (SrCO3 ). SrCO3 is dissolved in nitric acid and the solution containing pure Sr-89,90 is analyzed for total Sr using the Cerenkov counting technique. The chemical recovery for total Sr is determined using Sr-85 as an internal radio tracer. After yttrium(Y)-90 in-growth, Sr-90 is separated and the Y-90 fraction is analyzed by Cerenkov counting. The Cerenkov radiation, resulting from the interactions of the Sr-89 and Y-90 beta emissions in the liquid scintillation counter is detected and processed by the multi-channel analyzer. The concentrations of each strontium isotope are resolved mathematically based on the two measured results. A typical combined counting time for Sr-89,90 analysis is two hundred ten minutes.

A-4

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 APPENDIX B LAND USE CENSUS FOR 2002 B-I

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 2002 Land Use Census Assessment The Land Use Census is performed annually to identify significant changes in land usage in the area surrounding Cook Plant, which could affect exposure pathways. Any identified changes are evaluated to determine whether modifications should be made to the REMP or other related programs. The following is a summary of the results of the 2002 census.

Dair' Farm Survey (See Attachments land 2)

The dairy farm survey was performed to update the list of dairy farms located in the plant area (Berrien County), to identify the nearest animal whose milk is used for human consumption. The milk farm survey for the Cook Plant was conducted on September 24 through 27 and on September 30, 2002.

There were no changes in the dairy farm list from the Michigan Department of Agriculture between July 1, 2001 and July 1, 2002. No new dairy farms were located in the County during this year's door-to-door survey.

At the present time, there are four farms/residence with dairy animals used for milk consumption within eight miles of the plant (Shuler, Monroe, Glen-Troy, & John Warmbein). The REMP milk-sampling program remains in effect at this time.

Therefore the collection of monthly broadleaf samples (in lieu of milk samples) has been discontinued (per 12THP-6010.RPP.635 "Collection of Milk Samples").

The closest milk-producing animals (for human consumption) are milk cows at the Shuler & Son Farm located at 2791 Snow Road in Baroda.

Residential Survey From June 1, 2001 to June 1, 2002, three (3) residential building permits were issued for construction in Lake Township for sections 5, 6, 7, and 8. These sections border the Cook Plant property. None of the permits change which residence in each sector is closest to the Cook Plant. In addition, none of these permits were issued to the residences, which are the closest in each sector. Therefore, none of the construction permits will affect the Plant's radiological evaluation of residential households.

Grape and Broadleaf Survey In accordance with the Offsite Dose Calculation Manual PMP-6010-OSD-001 and 12-THP-6010.RPP.638 "Collection of Grape and Broadleaf Samples" vegetation sampling is performed in lieu of a garden census. Broadleaf sampling is performed to monitor for plant impact on the environment. The samples were obtained as close to the site boundary as possible in a land sector, with sample media, with the highest average deposition factor (D/Q). Control samples were also obtained in a less prevalent sector approximately 20 miles for the site boundary.. These locations were the B. Kunde vineyard at 3316 Linco Road in Stevensville, in the vicinity of well water sample station W-l, and the Eldridge residence at 6156 Fail Road in LaPorte, respectively. The analytical results for the grape and broadleaf samples obtained on September 12, 2002, were less than ODCM LLDs (60 Pico-curies/kg for Cs-134, Cs-137, and I-13 1).

B-2

DC Cookc Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Attachment 1: 2002 Land Use Census - Operating Dairy Farms In Berrien County Name and Address Township Section Sector/Distance Andrews University Oronoko 12 E / 10.5 miles (55,440 ft)

Dairy Road Berrien Springs, 49103 Brohman Farm Oronoko 29 F 1 8.5 miles (44,880 t) -

1637 Mt Tabor Rd.

Berrien Springs, 49103 Glen Troy Farm Weesaw 10 H / 7.0 miles (36,960 ft)

Mel Freehling 2221 Glendora Rd.

Buchanan, 49107 Koebel Farm Three Oaks 36 J / 10.6 miles (55,970 ft) 16318 Avery Rd.

Three Oaks, 49128 Dean Lozmack Weesaw 23 H / 9.2 miles (48,580 Rt) 14843 Cleveland Rd.

Galien, 49218 Paul Lozmack Weesaw 30 J / 10.3 miles (54,390 Rt) 4193 Elm Valley Three Oaks, 49128 William Nimtz Pipestone 07 D /13.5 miles (71,280 ft) 3445 Park Rd.

Eau Claire, 49111 Howard Payne Weesaw 31 J / 10.9 miles (57,552 ft)

RFD 2 Box 148 Three Oaks, 49128 Powers Farm Buchanan 31 H /12.7 miles (67,060 Ct) 16402 Wells Rd Buchanan, 49107 Shuler Farm Lake 28 G & H / 4.1 miles (21,648 Rt) 2791 Snow Rd.

Baroda, 49101 Wagner Farms Berrien 35 F1 16.5 miles (87,120 Rt)

Carl Wagner, Jr.

8523 Chapel Rd.

Carl Wagner, Sr. Berrien 26 F/ 17.0 miles (89,760 Rt) 11215 Pucker St.

Niles, 49120 John Warmbein Weesaw 19 J /8.5 miles (44,880 ft)

RFD 2 Box 180 (Old Mill Rd.)

Three Oaks, 49128 The above farms are Michigan Department of Agriculture Grade A approved.

B-3

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Attachment 1: 2002 Land Use Census - Operating Dairy Farms In Berrien County (The following farmstresidences have steers/cows (Holstein or Jersey)/goats which are not used for milking at this time but should be verified annually.)

Name and Address Township Section Sector/Distance Arthur Phillips Bainbridge 31 D / 14.0 miles (73,920 ft) 2414 Park Rd.

Eau Claire, 49111 Nelson Farm Oronoko 14 F 10.5 miles (55,440 ft)

Shawnee Rd.

Berrien Springs, 49103 Roger Tumbleson Bertrand 19 G/ 19.0 miles (100,320 ft) 3120 Mayflower Rd.

Niles, 49120 Chad White Lake 14 F 4.5 miles (23,760 ft) 1558 W. Shawnee Rd Baroda, 49101 Name: Unknown Three Oaks 16 K/ 14.5 miles (76,560 ft)

Forest Lawn Rd. West of S. Witt Three Oaks, 49128 41 degrees, 46.541 minutes North 86 degrees, 38.555 minutes West Name: Unknown (Emu) Bainbridge 7 C/ 16.2 miles (87,120 ft)

Boyer Rd. North of N. Branch Millburg, 49038 42 degrees, 07.845 minutes North 86 degrees, 19.852 minutes West Creekside Farm and Kennels Pipestone 16 D/ 15.3 miles (80,0784 ft)

(Llama, Jacob sheep) 7196 Naomi Rd.

Sodus, 49126 42 degrees, 02.583 minutes North 86 degrees, 17.015 minutes West Name: Unknown Pipestone 11 D/ 17.2 miles (90,816 ft)

Noami Rd. East of M-140 Sodus, 49126 41 degrees, 46.541 minutes North 86 degrees, 38.555 minutes West Name: Unknown Lincoln 26 K/ 5.2 miles (27,456 ft)

Lincoln Av. N. of Rocky Weed Derby, 49127 42 degrees, 00.249 minutes North 86 degrees, 28.526 minutes West The above farms are Michigan Department of Agriculture Grade A approved.

B-4

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Attachment 1: 2002 Land Use Census - Operating Dairy Farms In Berrien County (The farn ris listed below are not MI Department of Agriculture approved farms.)

Name and Address Township Section Sector/Distance Arvon Arent 463-6546 Bainbridge 3 C/19.2 miles (101,380 ft) 2300 Angling Rd.

Watervliet, MI 49098 Harvey Hoffman Watervliet 35 C/20.3 miles (107,180 ft) 2533 N M-140 Hwy.

Watervliet, 49098 Jeff Monroe Lake 27 G / 5.0 miles (26,400 ft) 10627 Miller Rd.

Baroda, 49 101 Dr. Ken Seifert Niles 12 F/19.3 miles (101,900 ft)

Town & Country (Vet Clinic) 3127 N. Fifth St. (M-51)

Niles, 49120 Tony Waldo Chickaming 13 J/7.8 miles (41,180 ft) 14255 Minnich Rd.

Sawyer, 49125 Jerry Warrabein Weesaw 18 J / 7.7 miles (40,660 ft) 14143 MiNO Rd.

Three Oaks, 49128 Robert ZebeD Three Oaks 33 & 34 K / 12.0 miles (63,360 ft) 7819 Kruger Road Three Oaks, 49128 Zeiger Farm Three Oaks 25 J / 9.4 miles (49,630 ft) 5692 Warren Woods Rd.

Three Oaks, 49128 -J B-5

DC Cook Nuclear Plant Units l&2 Annual Radiological Environmental Operating Report 2002 Attachment 1: 2002 Land Use Census - Operating Dairy Farms In Berrien County (The farms listed below are not MI Department of Agriculture approved farms.)

(The following farms/residences have steers/cows (Holstein or Jersey)/goats which are not used for milking at this time but should be verified annually.)

Name and Address Township Section Sector/Distance Devries Weesaw 10 G / 7.8 miles (41,180 ft) 1847 Gardner Rd.

Buchanan, 49107 William Haase Lake 27 G / 4.5 miles (23,760 ft) 10276 Miller Rd.

Baroda, 49101 Richard Leneway Bertrand 14 G/ 17.1 miles (90,290 ft) 2650 Red Bud Tr.

Niles, 49120 Patyno Weesaw 10 H / 7.2 miles (38,020 ft) 2629 Glendora Rd.

Buchanan, 49107 B-6

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Attachment 2: 2002 Land Use Census - Dairy List For Berrien County FARMPERMITNUM FARMCO FARMTWP FARMSEC FARMNAME FARMPHILNAME FARMPHIFNAME FARMPHIADDRESS FARMPHICITY FARMPHIST FARMPHIZIP FARMPHIPHONE F6.16 11 15 31 PAYNEHOWARD Howard Payne 16557 MILL RD THREE OAKS Mi 49128 616 426-4367 F646 11 10 07 NIMTZ WILLIAM ) William 3 Nimtz 3445 PARK RD EAU CLAIRE Ml 49111 616 944-1902 F651 11 19 36 KOEBEL JERRY ]etry Koebel 16315 AVERY RD THREE OAKS Ml 49128 616 756.9497 F907 11 15 19 WARMtEIN JOHN John Warmbein 14560 MILL RD THREE OAKS Mi 49128 616 426-4036 viss it 16 31

• POWERS NICK L & BARBARA A Nick L & Barbara A Powers 16402 WELLS RD BUCHANAN Ml 49017 616 695-3741 V156 11 15 10 GLEN TROY FARMS Glen Troy Farms 2221 GLENDORA RD BUCHANAN Mi 49107 VIS7 1t 15 23. LOZMACK DEAN Dean Loaznack 14543 CLEVELAND RD GALIEN Mi 49216 616 545-3625 V162 11 12 29 . BROHMAN KEITH & CHAS Keith & Chas Brohman 1637 MT TABOR RD BERRIEN SPRINGS Ml 49103 616 473-6323 VI63 11 12 12

• ANDREWS UNIV DAIRY DEPT Andrews Univ Dairy Dept DAIRY RD BERRIEN SPRINGS Ml 49104 616 471-3224 V164 11 11 26 . SHULER FARMS Shulbr Farms 2791 SNOW RD EARODA Ml 49101 V664 it 15 30 LOZMACK PAUL Lozmack Paul 4193 ELM VALLEY THREE OAKS Ml 49125 WOIl it 13 616 426-5235 35

• WAGNER CARL JR Wagner Jr Carl 5523 CHAPEL RD NILES V438 Mi 49120 616 684-6067 11 13 26 WAGNER CARL R JR Carl R Wagner Jr 5S23 CHAPEL RD NILES Hi 49120 616 684-6067 B-7

(. l I . ( L I ( t 1- ( (I I I

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 APPENDIX C Quality Assurance Program C-I

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmnental Operating Report 2002 J OUALITY ASSURANCE PROGRAM The quality assurance program at the Framatome ANP Environmental Laboratory (FANPEL) is designed to serve two overall purposes: 1) Establish a measure of confidence in the measurement process to assure the licensee, regulatory -

agencies and the public that analytical results are accurate and precise; and 2) Identify deficiencies in the sampling and/or measurement process to those responsible for these operations so that corrective action can be taken. Quality assurance is applied to all steps of the measurement process, including the collection, measurement and reporting of data, as well as the record keeping of the final results. Quality control, as part of the quality assurance program, provides a means to control and measure the characteristics of the measurement equipment and processes, relative to established requirements. -

The FANPEL employs a comprehensive quality assurance program designed to monitor the quality of analytical processing to ensure reliable environmental monitoring data. The program includes the use of controlled procedures for all work activities, a nonconformance and corrective action tracking system, systematic internal audits, audits by external groups, a laboratory quality control program, and a staff training program. Monitoring programs include the Intralaboratory Quality Control Program administered by the Laboratory QA Officer (used in conjunction with the National Institute of Standards and Technology Measurement Assurance Program, NIST MAP) and a third party cross check program administered by Analytics, Inc. Together these programs are targeted to supply QC/QA sources at 5% of the client sample analysis load. In addition the Laboratory Quality Control Audit Committee administers a blind duplicate program conducted through client environmental monitoring programs.

This summary reports all interlaboratory and third party results received by FANPEL on or before December 31, 2002.

Quality Assurance sample results that were not available for inclusion in this report will be evaluated and reported in accordance with DC Cook Plant procedures.

Intralaboratorv Oualitv Control Program The FANPEL QA Officer administers an extensive intralaboratory quality control program in which process check samples are submitted for analysis. These samples are submitted either in duplicate to evaluate the precision of a measurement process or are "spiked" with a known amount of radioactive material to assess the bias in the measurement.

Table C.1 provides the summary of the process check results for January to December 2002. Of the 510 analyses, 99.2%

passed the bias criteria and 97.4% of the results evaluated for precision were acceptable.

Third Party Cross Check Program The FANPEL participates in a third party cross check program managed by Analytics Inc. to satisfy the requirement of the Environmental Technical SpecificationlODCM. The FANPEL Analytics program was originally used to augment the EPA Intercomparison Program that it now replaces. The current program is designed to be comparable to the pre-1996 EPA PE Program in terms of the number of samples, matrices and nuclides. The results for the 4th quarter 2001 through the Yd 3 quarter 2002 are summarized in Table C.2. Each sample is analyzed in triplicate and the results are evaluated against the internal acceptance criteria described in the FANPEL Manual 100-Laboratory Quality Assurance Plan. This acceptance protocol is used for all interlaboratory programs with no pre-set acceptance criteria. When results fall outside of the acceptance criteria, an investigation is initiated to determine the cause of the problem and if appropriate, corrective measures are taken. The FANPEL internal acceptance criteria are summarized at the end of Table C.2.

C-2

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 Environmental TLD Ouality Assurance Program Performance documentation of the routine processing of the Panasonic environmental TLDs (thermoluminescent dosimeter) program at the FANPEL is provided by the dosimetry quality assurance testing program. This program includes the National Voluntary Laboratory Accreditation Program, independent third party performance testing by Battelle Pacific Northwest Labs and internal performance testing conducted by the Laboratory QA Officer. Under these programs, dosimeters are irradiated to ANSI specified testing criteria and submitted for processing to the Dosimetry Services Group as "unknowns". The bias and precision of TLD processing is measured against this standard and is used to indicate trends and changes in performance. Instrumentation checks, although routinely performed by the Dosimetry Services Group and representing between 5-10% of the TLDs processed, are not presented in this report because they do not represent a true process check sample since the doses are known to the processor.

Eighty-four performance tests were conducted in 2002 by FANPEL and the third party tester. Of these, 100% of the dosimeter evaluations met the FANPEL Internal Acceptance Criteria for bias (+/- 20.1%) and precision (+/-12.8%). In addition 14 TLD test sets passed the control limits set by the LQCAC in 1998 to evaluate the sum of the bias and precision values. A tolerance limit of +/- 30% applies to environmental dosimeters. Third Party QC results are summarized below.

Percentage of Individual Analyses which passed FANPEL Internal Criteria Dosimeter Type Number Shallow (7mg/cm 2 )

Tested  % passed bias criteria  % passed precision criteria Panasonic Environmental 84 100 100 Summary of Third Party Testing Dosimeter Type Exposure Period NVLAB Category Shallow (7mg/cm 2 )

% (Bias +/- SD) IBI + S*

Panasonic Environmental Q1/2002 IV, high energy 5.6 +/- 1.2 0.068 Q2/2002 IV, high energy 8.8 +/- 1.1 0.099

.. Q3/2002 IV, high energy 7.1 +/- 3.1 0.102 Note: Results are expressed as the delivered exposure for environmental TLD. NVLAB Category IV,High energy photons (Cs-137 or Co-60).

• American National Standards Institute (ANSI) Performance Statistic as referenced in the Dosimetry Services Semi-Annual QA Status Report.

C-3

DC Cook Nuclear Plant Units 1&2

• Annual Radiological Environmental Operating Report 2002 TABLE C.1 FANPEL RESULTS IN THE INTRALABORATORY PROCESS CONTROL PROGRAM January - December 2002 Media . .Bias Crteria (I)  :- *Precision Criteria (2)

[m..Analysis  : 1 2 3 4 I 3 4 I. Air Charcoal Gamma 85 14 0 H. Air Filter Alpha Beta 221 9 0 Gamma III. Milk Gamma 6 0 6 Iodine-LL 3 2 5 Strontium-89 0 1 3 Strontium-90 IV. Water Gross Alpha 10 11 5 Gross Beta 33 9 10 Gamma 18 12 36 Iodine-LL Ni-63 0 3 Radium 226 8 8 4 Radium-228 -

Tritium 10 0 10 U-234 4 1 5 U-235 3 2 5 U-238 4 I 5 V. Sediment/Soil Gamma

-S Pu-239 0 0 0 Am-241 0 0 0 VI. Vegetation Gamma Total Number in Range 408 70 28 4 97 7 7 3 Percentage of Total 80.0 13.7 5.5 0.8 85.1 6.1 6.1 2.6 ProcessedA Sum of Analyses _1 114_

(1) Percent Bias Criteria by Bias Category (2) Percent Precision Criteria by Precision Category Bias Category = I > 0% and < = 5% Precision Category = I > 0% and < = 5%

Bias Category = 2 > 5% and < = 10% Precision Category = 2 > 5% and < = 10%

Bias Category = 3 > 10% and < = 15%, or Precision Category = 3 > 10% and < = 15%, or within 2 sigma of known within 2 sigma of mean Gross alpha and beta, Sr 89/90 > 10% and < = 25% Precision Category = 4 Outside Criteria Transuranics > 10% and < = 20%

Bias Category = 4 Outside Criteria C-4

DC Cook Nuclear Plant Units 1 &2 Annual Radiological Environmental Operating Report 2002 TABLE C.2 FANPEL RESULTS IN THE ANALYTICS INC. CROSS CHECK PROGRAM Quarter 4, 2001 - Quarter 3, 2002

>'Sample" Samp Nuclide Reported ,Kno. ' {Rat 'Quarter,

'vautin Number,¢ Yeara E LA,/

- - -- ,Aalytics~'

E2901-162 4u/01 Water H-3 13510 14060 0.96 Agreement E2903-162 40I01 Flter Gross a 14 16 0.88 Agreement Gross p 50 48 1.04 Agreement E2902A-162 4l/01 Fiter Sr-89 66 82 0.80 Agreement E2902A-162 4F101 Filter Sr-90 54 61 0.89 Agreement E2904-162 4"/01 Milk 1-131 62 61 1.02 Agreement Ce-141 384 379 1.01 Agreement Cr-51 527 497 1.06 Agreement Cs-134 198 199 0.99 Agreement Cs-137 325 318 1.02 Agreement Co-58 94 90 1.04 Agreement Mn-54 158 149 1.06 Agreement Fe-59 109 102 1.07 Agreement Zn-65 231 206 1.12 Agreement Co-60 353 353 1.00 Agreement E3096-186 1*102 Milk 1i131LL 99 90 1.09 Agreement Ce-141 32 29 1.10 Agreement Cr-51 262 241 1.09 Agreement Cs-134 103 110 0.94 Agreement Cs-137 248 240 1.03 Agreement Mn-54 224 202 1.11 Agreement Fe-59 112 104 1.08 Agreement Zn-65 215 199 1.08 Agreement Co-60 144 142 1.01 Agreement E3097-186 1I"/02 Charcoal 1-131 74 77 0.96 Agreement E3098-186 1"/02 Charcoal 1-131 65 69 0.94 Agreement E3099-186 1'/02 Charcoal 1-131 91 87 1.05 Agreement E3023-162 1/02 Water Gross a 56.7 53 1.08 Acceptable Gross p 310.3 313 0.99 Acceptable E3024-162 1i"/02 Water 1-131 54.5 61 0.90 Acceptable 1-131LL 63.4 61 1.04 Acceptable Ce-141 239.4 242 0.99 Acceptable Cr-51 175.7 198 0.89 Acceptable Cs-134 87.8 91 0.97 Acceptable Cs-137 197.7 197 1.01 Acceptable Mn-54 168.5 166 1.02 Acceptable Fe-59 87.6 86 1.02 Acceptable Zn-65 157.2 164 0.96 Acceptable Co-60 114.6 117 0.98 Acceptable

• pCi/Liter (Filters in pCi)

C-5

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 TABLE C.2 FANPEL RESULTS IN THE ANALYTICS INC. CROSS CHECK PROGRAM -I Quarter 4, 2001 - Quarter 3, 2002 Sample Quater sample Nucide Reported I Known-' Ratio - Ealuat' n .-j Nu er . i Yar  ; Medla .. Valu . Valu' A. ; Eu .

_ _ _ _ _ _ _ _ _ _ _.Analytlc! _ _ _ _

E3025-162 tt02 Soil Ce-141 350.7 383 0.92 Acceptable AcTh-228 448.3 .

Cr-51 274 314 0.87 Acceptable Cs-134 136.8 143 0.96 Acceptable Cs-137 405.7 439 0.92 ' Acceptable Mn-54 245.8 263 0.94 Acceptable Fe-59 140.2 136 1.03 Acceptable Zn-65 248.1 259 0.96 Acceptable Co-60 168.1 185 0.91 Acceptable E3026-162 1't/02 Filter Gross Alpha 21.8 23 0.96 Acceptable Gross Beta 149 136 1.1 Acceptable E3027-162 1't/02 Milk 1-131 87.9 92 0.96 Acceptable 1-13tLL 93 92 1.01 Acceptable Ce 141 317.8 326 0.98 Acceptable Cr-5i 277 267 1.04 Acceptable Cs-134 119 122 0.98 Acceptable Cs-137 271.2 266 1.02 Acceptable Mn-54 231.2 224 1.03 Acceptable Fe-59 123.6 116 1.07 Acceptable Zn-65 225.9 221 1.02 Acceptable Co-60 152.9 158 0.97 Acceptable E3028-162 1'/02 Milk Sr-89 79.9 83 0.96 Acceptable Sr-90 24.7 27 0.93 Acceptable E3148-162 2^'/02 Water H-3 6970 6970 1.00 Acceptable E3149-162 2 nd/0 2 Water Sr-89 42 64 0.66 Unacceptable(1)

Sr-90 36 39 0.92 Acceptable E3150-162 2/02 Filter Gross Alpha (2) (2) (2) (2) -

Gross Beta (2) (2) (2) (2)

E3151-162 2"eI02 Filter Ce-141 59 61 0.97 Acceptable Cr-51 165 160 1.03 Acceptable Cs-134 77 82 0.94 Acceptable Cs-137 64 62 1.03 Acceptable C>58 68 68 1.00 Acceptable Mn-54 69 65 1.06 Acceptable Fe-59 62 55 1.13 Acceptable Zn-65 131 122 1.07 Acceptable Co-60 82 85 0.96 Acceptable E3152-162 e 2 102 Filter Sr-90 41 48 0.85 Acceptable

• Units in pCi/Liter (filter in pCi)

(l) - CR 02-43 issued to investigate failures for Sr-89 (2) - Filter damaged during sample preparation. No results issued.

C-6

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 TABLE C.2 FANPEL RESULTS IN THE ANALYTICS INC. CROSS CHECK PROGRAM Quarter 4, 2001 - Quarter 3, 2002 Sape Q rtrSampe - Nucllide ~Reored Knw .'-Ratio Evauaio Number' Lz ear LMedia ,vallue Vle E LA-E3153-162 gm/02 Milk 1-131 88 87 1.01 Acceptable 1-131 LL 85 87 0.98 Acceptable Ce-141 86 90 0.96 Acceptable Cr-51 230 235 0.98 Acceptable Cs-134 121 120 1.01 Acceptable Cs-137 89 91 0.98 Acceptable Co-58 100 100 1.00 Acceptable Mn-54 97 95 1.02 Acceptable Fe-59 83 81 1.02 Acceptable Zn-65 179 180 0.99 Acceptable Co-60 127 125 1.02 Acceptable E3288-162 3 '/ 02 Water Gross Alpha 73 92 0.79 Acceptable Gross Beta 204 239 0.85 Acceptable E3289-162 3'd/02 Water 1-131 68 79 0.86 Acceptable 1-131LL 77 79 0.97 Acceptable Ce-141 209 214 0.98 Acceptable Cr-51 289 304 0.95 Acceptable Cs-134 169 176 0.96 Acceptable Cs-137 167 169 0.99 Acceptable Co-58 129 130 0.99 Acceptable Mn-54 206 204 1.01 Acceptable Fe-59 118 119 0.99 Acceptable Zn-65 251 251 1.00 Acceptable Co-60 187 199 1.04 Acceptable E3291-162 3 d/02 Filter Gross Alpha 58 59 0.98 Acceptable Gross Beta 144 155 0.93 Acceptable E3292-162 3rd/02 Milk 1-131 79 80 0.99 Acceptable 1-131 LL 77 80 0.96 Acceptable Ce-141 156 160 0.98 Acceptable Cr-51 231 227 1.02 Acceptable Cs-I 34 128 132 0.97 Acceptable Cs-137 122 127 0.96 Acceptable Co-58 95 97 0.98 Acceptable Mn-54 151 152 0.99 Acceptable Fe-59 94 89 1.06 Acceptable Zn-65 180 187 0.96 Acceptable Co-60 142 149 0.95 Acceptable E 3293-162 3'/02 Milk Sr-89 84 92 0.91 Acceptable Sr-90 36 39 0.92 Acceptable

• Units in pCi/Liter (filter in pCi)

Bias Acceptance Criteria +/- 15%, or as noted below: Precision Acceptance Criteria +/- 15%, or as noted below:

Gross alpha and beta, Sr 89/90 +/- 25% Gross alpha and beta, Sr 89/90 +/- 23%

Transuranics and Radium +/- 20% or, Transuranics and Radium +/- 20%

If known value falls within 2 sigma range acceptance criteria is met C-7

DC Cook Nuclear Plant Units 1&2 Annual Radiological Environmental Operating Report 2002 I APPENDIX D 2002 Data Summary J

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dcv. MDC (pCi/l 3 ) (pCi/ m3) (pCi/m 3)

AP ONS-1 LA600-01 01 GROSS BETA 3.85E-02 1.80E-03 3.SOE-03

• ONS-2 L4600-02 01 GROSS BETA 3.46E-02 1.70E-03 3.20E-03

• ONS-3 L4600-03 01 GROSS BETA 3.76E-02 1.70E-03 3.OOE-03

• ONS-4 L4600-04 01 GROSS BETA 4.06E-02 1.80E-03 3.40E-03

• ONS-S L4600-05 01 GROSS BETA 4.3IE-02 1.90E-03 3.40E-03

• ONS-6 L4600-06 01 GROSS BETA 4.20E-02 1.90E-03 3.40E-03

• NBF L4600-07 01 GROSS BETA 4.OOE-02 1.90E-03 3.60E-03

• SBN L4600-08 01 GROSS BETA 4.05E-02 1.90E-03 3.70E-03

• DOW LA600-09 01 GROSS BETA 4.25E-02 2.00E-03 3.80E-03

• COL L4600-10 01 GROSS BETA 3.98E-02 1.90E-03 3.60E-03

• ONS-1 L2054-01 02 GROSS BETA 4.60E-02 2.30E-03 5.20E-03

• ONS-2 L2054-02 02 GROSSBETA 4.15E-02 1.60E-03 3.20E-03

• ONS-3 L2054-03 02 GROSS BETA 3.86E-02 1.60E-03 3.20E-03

• ONS-4 L20S4-04 02 GROSS BETA 4.37E-02 1.60E-03 3.20E-03

• ONS-5 L2054-05 02 GROSSBETA 5.04E-02 1.70E-03 3.20E-03

• ONS-6 L2054-06 02 GROSS BETA 4.15E-02 1.60E-03 3.20E-03

• NBF L2054-07 02 GROSS BETA 4.IOE-02 1.60E-03 3.20E-03

• SBN L2054-08 02 GROSS BETA 4.46E-02 1.70E-03 3.30E-03

• DOW L2054-09 02 GROSS BETA 4.36E-02 1.70E-03 3.30E-03

• COL L2054-10 02 GROSS BETA 4.09E-02 1.60E-03 3.20E-03

• ONS-1 L2084-01 03 GROSS BETA 2.49E-02 1.60E-03 4.OOE-03

• ONS-2 L2084-02 03 GROSS BETA 2.67E-02 1.60E-03 4.10E-03

• ONS-3 L2084-03 03 GROSS BETA 2.42E-02 1.60E-03 4.10E-03

• ONS-4 L2084-04 03 GROSS BETA 2.49E-02 1.60E-03 4.10E-03

• ONS-5 L2084-05 03 GROSSBETA 2.82E-02 1.60E-03 4.00E-03

• ONS-6 L2084-06 03 GROSS BETA 2.69E-02 1.60E-03 4.00E-03

• NBF L2084-07 03 GROSS BETA 2.43E-02 1.60E-03 4.OOE-03

• SBN L2084-08 03 GROSS BETA 2.84E-02 1.60E-03 4.10E-03

• DOW L2084-09 03 GROSS BETA 2.97E-02 1.70E-03 4.1OE-03

• COL L2084-10 03 GROSS BETA 2.42E-02 1.60E-03 4.00E-03

• ONS-I L2119-01 04 GROSS BETA 3.51E-02 1.50E-03 3.20E-03

• ONS-2 L2119-02 04 GROSSBETA 4.56E-02 1.70E-03 3.20E-03

• ONS-3 L2119.03 04 GROSS BETA 3.96E-02 1.60E-03 3.20E-03

• ONS-4 L2119-04 04 GROSS BETA 3.99E-02 1.60E-03 3.20E-03 *

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-2

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m3 ) (pCi/ mI3 ) (pCi/m 3 )

ONS-5 L2119-05 04 GROSSBETA 4.21E-02 1.60E-03 3.10E-03

• ONS-6 L2119-06 04 GROSSBETA 4.03E-02 1.60E-03 3.10E-03

• NBF L2119-07 04 GROSS BETA 3.91E-02 1.60E-03 3.10E-03

• SBN L2119-08 04 GROSSBETA 4.23E-02 1.60E-03 3.10E-03

• DOW L2119-09 04 GROSSBETA 4.35E-02 1.70E-03 3.20E-03

• COL L2119-10 04 GROSS BETA 3.99E-02 1.60E-03 3.20E-03

• ONS-1 L2161-01 05 GROSS BETA 3.54E-02 1.50E-03 3.OOE-03

• ONS-2 L2161-02 05 GROSSBETA 4.03E-02 1.60E-03 2.90E-03

• ONS-3 L2161-03 05 GROSSBETA 3.61E-02 1.50E-03 3.00E-03

• ONS-4 L2161-04 05 GROSS BETA 3.84E-02 1.50E-03 3.OOE-03

• ONS-S L2161-05 05 GROSS BETA 4.28E-02 1.60E-03 2.90E-03

• ONS-6 L2161-06 05 GROSS BETA 3.70E-02 1.50E-03 2.90E-03

• NBF L2161-07 05 GROSS BETA 3.68E-02 1.50E-03 2.80E-03

• SBN L2161-08 05 GROSSBETA 3.34E-02 1.40E-03 2.90E-03

• DOW L2161-09 05 GROSS BETA 3.61E-02 1.50E-03 3.OOE-03

• COL L2161-10 05 GROSS BETA 3.49E-02 1.50E-03 3.OOE-03

• ONS-1 L2185-01 06 GROSS BETA 2.81E-02 1.40E-103 3.10E-03

• ONS-2 L2185-02 06 GROSS BETA 3.52E-02 1.50E-103 3.10E-03

• ONS-3 L2185-03 06 GROSS BETA 3.17E-02 1.50E-I 03 3.IOE-03

• ONS-4 L2185-04 06 GROSS BETA 3.71E-02 1.60E-403 3.10E-03

• ONS-5 L2185-05 06 GROSS BETA 3.97E-02 1.60E-443 3.10E-03

• ONS-6 L2185-06 06 GROSS BETA 3.48E-02 1.50E 43 3.10E-03

• NBF L2185-07 06 GROSSBETA 2.98E-02 1.40E.403 2.90E-03

• SBN L2185-08 06 GROSSBETA 3.09E-02 1.50E-I03 3.20E-03

• DOW L2185-09 06 GROSS BETA 3.32E-02 1.50E-i03 3.1OE-03

• COL L2185-10 06 GROSS BETA 3.53E-02 1.50E-103 3.10E-03

• ONS-1 L2225-01 07 GROSS BETA 2.84E-02 1.40E-I03 3.20E-03

• ONS-2 L2225-02 07 GROSS BETA 3.45E-02 1.50E-103 3.20E-03

• ONS-3 L2225-03 07 GROSSBETA 2.97E-02 1.50E&03 3.20E-03

• ONS-4 L2225-04 07 GROSS BETA 3.27E-02 1.50E-I03 3.20E-03

• ONS-5 L2225-05 07 GROSSBETA 3.40E-02 1.50Ed03 3.10E-03

• ONS-6 L2225-06 07 GROSS BETA 3.47E-02 1.50E-i03 3.20E-03

• NBF L2225-07 07 GROSS BETA 3.16E-02 1.50E-i 03 3.10E-03

• SBN L2225-08 07 GROSSBETA 3.35E-02 1.50E-I03 3.30E-03

• DOW L2225-09 07 GROSSBETA 3.38E-02 1.50E&03 3.30E-03

• COL L2225-10 07 GROSS BETA 3.28E-02 1.50E& 03 3.20E-03 *

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-3

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC 3 3 3 (pCi/rn ) (pCi/ m ) (pCi/m )

ONS-1 L2259-01 08 GROSS BETA 2.42E-02 1.50E-03 3.60E-03

• ONS-2 L2259-02 08 GROSS BETA 2.35E-02 1.50E-03 3.60E-03

• ONS-3 L2259-03 08 GROSS BETA 2.23E-02 1.40E-03 3.60E-03

• ONS-4 L2259-04 08 GROSS BETA 2.22E-02 1.40E-03 3.60E-03

• ONS-5 L2259-05 08 GROSS BETA 2.24E-02 1.40E-03 3.50E-03

• ONS-6 L2259-06 08 GROSS BETA 2.38E-02 I .50E-03 3.60E-03

• NBF L2259-07 08 GROSS BETA 2.18E-02 I .40E-03 3.50E-03

• SBN L2259-08 08 GROSS BETA 2.38E-02 I .50E-03 3.60E-03

• DOW L2259-09 08 GROSS BETA 2.49E-02 I .50E-03 3.70E-03

• COL L2259-10 08 GROSS BETA 1.97E-02 I .40E-03 3.60E-03

• ONS-I L2321-01 09 GROSS BETA 1.13E-02 I .30E-03 3.90E-03

• ONS-2 L2321-02 09 GROSS BETA I .45E-02 1.40E-03 3.90E-03

• ONS-3 L2321-03 09 GROSS BETA 1.20E-02 1.30E-03 3.80E-03

• ONS-4 L2321-04 09 GROSS BETA I. 15E-02 1.30E-03 3.90E-03

• ONS-5 L2321-05 09 GROSS BETA 8.40E-03 1.30E-03 3.90E-03

• ONS-6 L2321-06 09 GROSS BETA 1.41E-02 1.40E-03 3.80E-03

• NBF L2321-07 09 GROSS BETA 1.1I E-02 1.30E-03 3.80E-03

• SBN L2321-08 09 GROSS BETA 1.43E-02 1.40E-03 3.90E-03

• DOW L2321-09 09 GROSS BETA 1.28E-02 1.40E-03 3.90E-03

• COL L2321-10 09 GROSS BETA 1.26E-02 1.40E-03 3.90E-03

• ONS-1 L2365-01 10 GROSS BETA 3. 14E-02 1.50E-03 3.OOE-03 ONS-2 L2365-02 10 GROSS BETA 3.45E-02 1.50E-03 3.00E-03

• ONS-3 L2365-03 10 GROSS BETA 3.1 5E-02 1.50E-03 3.OOE-03

• ONS4 L2365-04 10 GROSS BETA 3.35E-02 1.50E-03 3.00E-03

• ONS-5 L2365-05 10 GROSS BETA 3.47E-02 1.50E-03 3.OOE-03

• ONS-6 L2365-06 10 GROSS BETA 3.23E-02 1.50E-03 3.00E-03

• NBF L2365-07 10 GROSS BETA 3.57E-02 1.50E-03 2.90E-03

• SBN L2365-08 10 GROSS BETA 3.27E-02 1 .50E-03 3.OOE-03

• DOW L2365-09 10 GROSS BETA 3.24E-02 1.50E-03 3.00E-03

• COL L2365-10 10 GROSS BETA 3.01E-02 1.40E-03 3.OOE-03

• ONS-I L2401-01 11 GROSSBETA 3.37E-02 1.60E-03 3.60E-03

• ONS-2 L2401-02 11 GROSS BETA 4.05E-02 1.60E-03 3.50E-03

• ONS-3 L2401-03 11 GROSS BETA 3.58E-02 1.60E-03 3.60E-03

• ONS-4 L2401-04 11 GROSS BETA 3.75E-02 1.60E-03 3.60E-03 *

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-4

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCilm3 ) (pCi/ n3) (pCilm 3

)

ONS-5 L2401-05 11 GROSS BETA 3.88E-02 1.60E-03 3.50E-03

• ONS-6 L2401-06 11 GROSSBETA 3.87E3-02 1.60E-03 3.60E-03

• NBF L2401-07 11 GROSSBETA 3.94E-02 1.60E-03 3.50E-03

• SBN L2401-08 11 GROSSBETA 3.901E-02 1.70E-03 3.60E-03

• DOW L2401-09 11 GROSS BETA 3.95E-02 1.70E-03 3.60E-03

• COL L2401-10 11 GROSSBETA 3.8 1E-02 1.60E-03 3.50E-03

• ONS-1 L2449-01 12 GROSS BETA 2.67E3-02 I1.50E3-03 3.60E-03

• ONS-2 L2449-02 12 GROSS BETA 3. 121-02 1.501E-03 3.60E3-03

• ONS-3 L2449-03 12 GROSSBETA 2.721E-02 1.50E-03 3.601E-03

• ONS4 L2449-04 12 GROSS BETA 3.0612-02 1.50E-03 3.60E-03

• ONS-5 L2449-05 12 GROSS BETA 3.37E1-02 1.60E3-03 3.50E-03

• ONS-6 L2449-06 12 GROSS BETA 3.08E-02 1.60E-03 3.60E3-03

• NBF L2449-07 12 GROSS BETA 2.7213-02 1.501-03 3.5013-03

• SBN L2449-08 12 GROSS BETA 2.7 1E-02 1.501E-03 3.60E-03

• DOW L2449-09 12 GROSSBETA 3.141E-02 i.60E-03 3.60E2-03

• COL L2449-10 12 GROSS BETA 3.29E-02 I1.60E-03 3.60E-03

• ONS-I L2506-01 13 GROSS BETA 3.42E-02 1.60E-t 33 3.80E-03

• ONS-2 L2506-02 13 GROSS BETA 3.59E-02 1.60E-( *3 3.70E-03

• ONS-3 L2506-03 13 GROSS BETA 3.05E-02 1.60E14 33 3.70E-03

• ONS-4 L2506-04 13 GROSSBETA 3.37E-02 1.60E-( *3 3.70E-03

• ONS-5 L2506-05 13 GROSS BETA 3.34E-02 1.60E-1 *3 3.70E-03

• ONS-6 L2506-06 13 GROSSBETA 3.06E-02 1.60E-( *33 3.80E-03

• NBF L2506-07 13 GROSS BETA 3.65E-02 1.60E-( *3 3.60E-03

• SBN L2506-08 13 GROSS BETA 3.72E-02 1.70E-1 *3 3.70E-03

• DOW L2506-09 13 GROSS BETA 3.55E-02 1.60E14 03 3.80E-03

• COL L2506-10 13 GROSS BETA 3.35E-02 1.60E-( 33 3.70E-03

• ONS-I L2534-01 14 GROSS BETA 2.27E-02 1.40E-( *3 3.50E-03

• ONS-2 L2534-02 14 GROSSBETA 2.53E-02 1.40E-I 33 3.40E-03

• ONS-3 L2534-03 14 GROSS BETA 2.28E-02 1.30E-4 03 3.10E-03

• ONS-4 L2534-04 14 GROSS BETA 2.56E-02 1.40E14 03 3.40E-03

• ONS-5 L2534-05 14 GROSS BETA 2.50E-02 1.40E14 33 3.40E-03

• ONS-6 L2534-06 14 GROSS BETA 2.09E-02 1.40E-i 33 3.40E-03

• NBF L2534-07 14 GROSS BETA 2.67E-02 1.40E-( 33 3.30E-03

• SBN L2534-08 14 GROSS BETA 2.39E-02 1.40E-( 33 3.20E-03

• DOW L2534-09 14 GROSS BETA 2.41E-02 1.40E14 33 3.50E-03

• COL L2534-10 14 GROSS BETA 2.35E-02 1.40E-403 3.50E-03 *

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-5

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3 ) (pCil m3 ) (pCi/m3 )

ONS-1 L2610-01 15 GROSS BETA 2.56E3-02 1.50E-03 3.50E-03

• ONS-2 L2610-02 15 GROSS BETA 2.98E3-02 1.50E-03 3.30E-03

• ONS-3 L2610-03 15 GROSS BETA 2.47E-02 1.30E-03 2.90E-03

• ONS-4 L2610-04 15 GROSS BETA 2.541E-02 1.40E-03 3.20E43

• ONS-5 L2610-05 15 GROSS BETA 2.781E-02 1.40E-03 3.30E-03

• ONS-6 L2610-06 15 GROSS BETA 2.69E-02 1.40E-03 3.30E-03

• NBF L2610-07 15 GROSS BETA 2.67E-02 1.40E-03 3.20E-03

• SBN L2610-08 15 GROSS BEIA 2.85E3-02 1.40E-03 3.10E-03

• DOW L2610-09 15 GROSS BETA 2.45E-02 1.40E-03 3.40E-03

• COL L2610-10 15 GROSS BETA 2.411E-02 1.40E-03 3.30E-03

• ONS-1 U2637-01 16 GROSS BETA 2.60E3-02 1.50E-03 3.60E-03

• ONS-2 L2637-02 16 GROSS BETA 3.08E-02 1.50E-03 3.50E-03

• ONS-3 L2637-03 16 GROSS BETA 2.65E-02 1.30E-03 3.00E43

• ONS-4 L2637-04 16 GROSS BETA 2.72E-02 1.50E-03 3.40E43

• ONS-5 L2637-05 16 GROSS BETA 2.90E-02 1.50E-03 3.40E-03

• ONS-6 L2637-06 16 GROSS BETA 2.61E-02 1.50E-03 3.50E-03

• NBF L2637-07 16 GROSS BETA 2.70E-02 1.40E-03 3.40E43

• SBN L2637-08 16 GROSS BETA 2.54E-02 1.30E-03 3.10E-03

• DOW L2637-09 16 GROSS BETA 2.571E-02 1.50E-03 3.SOE-03

• COL L2637-10 16 GROSS BETA 2.601E-02 1.40E-03 3.40E-03

• ONS-I L2661-01 17 GROSS BETA 2.01E-02 I1.30E-03 2.901E-03

• ONS-2 U2661-02 17 GROSS BETA 1.99E-02 I1.20E-03 2.801E-03

• ONS-3 L2661-03 17 GROSS BETA 2.08E-02 1.1OE-03 2.50E-03

• ONS-4 12661-04 17 GROSS BETA 1.98E-02 1.20E-03 2.701E-03

• ONS-5 L2661-05 17 GROSS BETA 2.41AE-02 I1.30E-03 2.80E-03

• ONS-6 U2661-06 17 GROSS BErA 2.41E-02 1.30E3-03 2.801E-03

• NBF L2661-07 17 GROSS BETA 2.12E-02 1.20E-03 2.60E-03

• SBN U2661-08 17 GROSS BETA 1.94E-02 1.20E1-03 2.60E-03

• DOW U2661-09 17 GROSS BETA 2.44E-02 1.301E-03 2.90E3-03

• COL L2661-10 17 GROSS BETA 2.13E-02 1.3013-03 2.80E-03

• ONS-1 L2760-01 18 GROSS BETA 2.18E-02 1.40E-1*03 3.30E-03

• ONS-2 12760-02 18 GROSS BETA 2.21E-02 1.40E-( *3 3.40E-03

• ONS-3 12760-03 18 GROSS BETA 2.38E-02 1.40E-1*3 3.40E-03

• ONS-4 12760-04 18 GROSS BETA 2.36E-02 1.40E-( *3 3.30E-03 *

• Radioactivity detected In sample (i.e., concentration > 3 X standard deviation)

D-6

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCihm3) (pCi/ m3) (pCilm3)

ONS-5 L2760-05 18 GROSS BETA 2.49E-02 1.40E-03 3.404-03

• ONS-6 L2760-06 I8 GROSS BETA 2.39E-02 1.40E-03 3.30-03

• NBF L2760-07 18 GROSS BETA 2.51E-02 1.40E-03 3.30E-03

• SBN L2760-08 18 GROSS BETA 2.55E-02 1.40E-03 3.30E-03

• DOW L2760-09 18 GROSS BETA 2.45E-02 1.40E-03 3.30E-03

• COL L2760-10 18 GROSS BETA 2.23E-02 1.404-03 3.40E-03

• ONS-I L2796-01 19 GROSS BETA 1.75E-02 1.40E-03 3.20E-03

• ONS-2 L2796-02 19 GROSS BETA 1.92E-02 1.50E-03 3.30E-03

• ONS-3 L2796-03 19 GROSS BETA 2.08E-02 1.50E-03 3.30E-03 * -

ONS-4 L2796-04 19 GROSS BETA 1.88E-02 1.404-03 3.20E-03

• ONS-5 L2796-05 19 GROSS BETA 2.08E-02 1.50E-03 3.304-03

• ONS-6 L2796-06 19 GROSS BETA 2.08E-02 1.50E-03 3.302-03

• NBF L2796-07 19 GROSSBETA 1.98E-02 1.40E-03 3.20E-03

• SBN L2796-08 19 GROSS BETA 2.31E-02 1.50E-03 3.10E-03

• DOW L2796-09 19 GROSS BETA 1.81E-02 1.40E-03 3.10E-03

• COL L2796-10 19 GROSS BETA 1.96E-02 1.40E-03 3.20E-03

• ONS-I L2858-01 20 GROSS BETA 2.87E-02 1.40E-03 3.10E-03

• ONS-2 L2858-02 20 GROSS BETA 2.96E-02 1.50E-03 3.20E-03

• ONS-3 L2858-03 20 GROSSBETA 2.56E-02 1.40E-03 3.20E-03

• ONS-4 L2858-04 20 GROSS BETA 2.62E-02 1.302-03 3.00E-03

• ONS-5 L2858-05 20 GROSS BETA 2.88E-02 1.404-03 3.204-03

• ONS-6 L2858-06 20 GROSS BETA 2.84E-02 1.404-03 3.10E-03

• NBF L2858-07 20 GROSS BETA 2.61E-02 1.30E-03 3.OOE-03

• SBN L2858-08 20 GROSS BETA 2.71E-02 1.302-03 3.00E-03

• DOW L2858-09 20 GROSS BETA 2.44E-02 1.30E-03 3.00E-03

• COL L2858-10 20 GROSS BETA 2.59E-02 1.40E-03 3.IOE-03

• ONS-I L2929-01 21 GROSSBETA 1.84E-02 1.30E-03 3.304-03

• ONS-2 L2929-02 21 GROSS BETA 2.03E-02 1.30E-03 3.20E-03

• ONS-3 L2929-03 21 GROSS BETA 1.54E-02 1.30E-03 3.402-03

• ONS-4 L2929-04 21 GROSSBETA 1.944-02 1.30E-03 3.20E-03

• ONS-5 L2929-0S 21 GROSS BETA 2.074-02 1.30E-03 3.202-03

• ONS-6 L2929-06 21 GROSS BETA I1.77E-02 1.30E-03 3.202-03

• NBF L2929-07 21 GROSS BETA 1.94E-02 1.304-03 3.20E-03

• SBN 12929-08 21 GROSS BETA 1.70E-02 1.202-03 3.00E-03

• DOW 12929-09 21 GROSS BETA 1.724-02 1.202-03 3.10E-03

• COL U2929-10 21 GROSS BETA 1.67E-02 1.302-03 3.20E-03 *

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-7

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pci/m3) (pCi/ mI) (pCi/m3 )

ONS-1 L2984-01 22 GROSS BETA 2.04E-02 1.40E-03 3.40E-03

• ONS-2 L2984-02 22 GROSS BETA 2.23E-02 1.30E-03 3.30E-03

• ONS-3 L2984-03 22 GROSS BETA I .78E-02 1.40E-03 3.60E-03

• ONS-4 L2984-04 22 GROSS BETA 1.80E-02 1.30E-03 3.SOE-03

• ONS-5 L2984-05 22 GROSS BETA 2.09E-02 1.30E-03 3.30E-03

• ONS-6 L2984-06 22 GROSS BETA I .94E-02 1.40E-03 3.40E-03

• NBF L2984-07 22 GROSS BETA 1.88E-02 1.30E-03 3.40E-03

• SBN L2984-08 22 GROSS BETA 1.98E-02 1.30E-03 3.1OE-03

• DOW L2984-09 22 GROSSBETA 1.89E-02 1.30E-03 3.30E-03

• COL L2984-10 22 GROSS BETA 1.74E-02 1.30E-03 3.30E-03

• ONS-1 L3031-01 23 GROSS BETA 2.42E-02 1.40E-03 3.30E-03

• ONS-2 L3031-02 23 GROSS BETA 2.66E-02 1.40E-03 3.30E-03

• ONS-3 L3031-03 23 GROSS BETA 2.42E-02 1.40E-03 3.30E-03

• ONS-4 L3031-04 23 GROSSBETA 2.46E-02 1.40E-03 3.30E-03

• ONS-5 U2031-05 23 GROSS BETA 2.72E-02 1.40E-03 3.20E-03

• ONS-6 L3031-06 23 GROSS BETA 2.29E-02 1.40E-03 3.30E-03

• NBF L3031-07 23 GROSS BETA 2.68E-02 1.40E-03 3.30E-03

• SBN L3031-08 23 GROSS BETA 2.32E-02 1.30E-03 3.OOE-03

• DOW L3031-09 23 GROSS BETA 2.15E-02 1.30E-03 3.20E-03

• COL L303 1-10 23 GROSS BETA 2.13E-02 1.30E-03 3.30E-03

• ONS-1 l1115-01 24 GROSS BETA 2.63E-02 1.50E-03 3.50E-03

• ONS-2 12115-02 24 GROSS BETA 2.87E-02 1.50E-03 3.50E-03

• ONS-3 l1115-03 24 GROSS BETA 2.28E-02 1.30E-03 3.10E-03

• ONS-4 12115-04 24 GROSS BETA 2.48E-02 1.50E-03 3.50E-03

• ONS-5 L3115-05 24 GROSS BETA 2.62E-02 1.40E-03 3.40E-03

• ONS-6 12115-06 24 GROSS BETA 2.28E-02 1.40E-03 3.60E-03

• NBF 1l115-07 24 GROSSBETA 2.39E-02 1.40E-03 3.30E-03

• SBN 12115-08 24 GROSSBETA 2.47E-02 1.30E-03 3.10E-03

• DOW 13115-09 24 GROSS BETA 2.20E-02 1.30E-03 3.20E-03

• COL 12115-10 24 GROSSBETA 2.04E-02 1.30E-03 3.30E-03

• ONS-I L3151-01 25 GROSS BETA 1.49E-02 1.20E-03 3.30E-03

• ONS-2 L3151-02 25 GROSS BE-A 2.09E-02 1.30E-03 3.1OE-03

• ONS-3 L3151-03 25 GROSS BETA 1.92E-02 1.40E-03 3.60E-03

• ONS-4 l2151-04 25 GROSS BETA 1.67E-02 I1.20E-03 3.10E-03 *

• Radioactivity detected In sample (i.e., concentration > 3 X standard deviation)

D-8

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCitmr) (pCi/ mI) (pCi/m3)

ONS-5 L3151-05 25 GROSS BETA 1.70E-02 1.20E-03 3.OOE-03

• ONS-6 L3151-06 25 GROSS BETA I1.68E-02 1.20E-03 3.10E-03

• NBF L3151-07 25 GROSS BETA 1 .72E3-02 1.20E-03 3.10E-03

• SBN L3151-08 25 GROSSBETA 1.551-02 1.20E-03 3.OOE-03

• DOW L3151-09 25 GROSSBETA 1.63E-02 1.30E-03 3.30E-03

• COL L315I-10 25 GROSS BETA 1 .541E-02 1.20E-03 3.00E-03

• ONS-I L3191-01 26 GROSS BETA 4.32E-02 1.SOE-03 2.50E-03

• ONS-2 L3191-02 26 GROSS BETA 5.011E-02 1.60E-03 2.60E-03

• ONS-3 L3191-03 26 GROSS BETA 4.03E-02 1.60E403 2.90E-03

• ONS-4 L3191-04 26 GROSS BETA 4.241E-02 1.50E403 2.40E-03

• ONS-5 L3191-05 26 GROSS BETA 4.53E-02 I .40E-03 2.20E-03

• ONS-6 L3191-06 26 GROSS BETA 4.061E-02 I .50E-03 2.50E-03

• NBF L3 191-07 26 GROSS BETA 4.2313-02 1.50E-03 2.40E-03

• SBN UL191-08 26 GROSS BETA 3.8 1E-02 1.40E-03 2.50E-03

• DOW L3191-09 26 GROSS BETA 4.47E3-02 1.50E4-03 2.60E-03

• COL L3191-10 26 GROSS BETA 3.92E-02 I .40E-03 2.30E-03

• ONS-1 L3251-01 27 GROSSBETA 2.58E-02 I .60E-03 3.30E-03

• ONS-2 L3251-02 27 GROSS BETA 3.23E-02 1.70E-03 3.40E-03

• ONS-3 13251-03 27 GROSS BETA 2.79E3-02 1.70E-03 3.50E-03

• ONS4 L3251-04 27 GROSS BETA 2.75E-02 1.70E-03 3.50B-03

• ONS-S L3251-05 27 GROSS BETA 2.87E-02 1.70E-03 3.30E-03

• ONS-6 L3251-06 27 GROSS BETA 2.78E-02 I .70E-03 3.60E-03

• NBF L3251-07 27 GROSSBETA 2.80E-02 I .60E-03 3.30E-03

• SBN L3251-08 27 GROSS BETA 2.441E-02 1.60E-03 3.30E-03

• DOW L3251-09 27 GROSS BETA 2.60E3-02 1.60E-03 3.40E-03

• COL L3251-10 27 GROSSBETA 2.38E-02 1.60B-03 3.30E-03

• ONS-I L3297-01 28 GROSS BETA 2.20E-02 I .50E-03 3.40E-03

• ONS-2 L3297-02 28 GROSS BETA 3.061E-02 1.70E-03 3.40E-03

• ONS-3 L3297-03 28 GROSS BETA 2.5913-02 1.60E-03 3.40E-03

• ONS4 L3297-04 28 GROSS BETA 2.41 E-02 1.60E-03 3.50B-03

• ONS-5 L3297-05 28 GROSSBETA 2.701E-02 1.60E-03 3.40E-03

• ONS-6 L3297-06 28 GROSS BETA 2.37E1-02 1.60E-03 3.60E-03

• NBF L3297-07 28 GROSSBETA 2.59E-02 1.60E-03 3.50E-03

• SBN L3297-08 28 GROSSBETA 2.36E-02 1.60E-03 3.40E-03

• DOW L3297-09 28 GROSS BETA 2.45E-02 1.60E-03 3.50E-03

• COL L3297-10 28 GROSS BETA 2.25E3-02 1.50E-03 3.40E-03 *

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-9

Indiana Michigan Power Co., t)C Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3) (pCi/ M3) (pCi/m 3)

ONS-I U3355-01 29 GROSSBETA 3.03E-02 1.70E-03 3.70E-03

• ONS-2 12355-02 29 GROSS BETA 3.87E-02 1.90E-03 3.80E-03

• ONS-3 L3355-03 29 GROSS BETA 3.111E-02 1.80E-03 3.80E-03

• ONS4 U3355-04 29 GROSS BETA 2.84E-02 1.70E-03 3.80E-03

• ONS-5 L3355-05 29 GROSS BETA 2.99E-02 1.70E-03 3.80E-03

• ONS-6 U3355-06 29 GROSS BETA 3.35E-02 1.80E-03 3.80E-03

• NBF U3355-07 29 GROSS BETA 3.12E-02 1.80E-03 3.80E-03

• SBN U3355-08 29 GROSS BETA 2.74E-02 1.60E-03 3.70E-03

• DOW L3355-09 29 GROSS BETA 2.58E-02 1.80E-03 4.20E-03

• COL U3355-10 29 GROSS BETA 2.67E-02 1.60E-03 3.70E-03

• ONS-I U3393-01 30 GROSS BETA 4.36E-02 1.60E-03 3.10E-03

• ONS-2 L3393-02 30 GROSS BETA 5.40E-02 1.80E-03 3.30E-03

• ONS-3 U3393-03 30 GROSS BETA 3.951E-02 1.60E-03 3.30E-03

• ONS4 L3393-04 30 GROSS BETA 4.03E-02 1.60E-03 3.30E-03

• ONS-5 U2393-05 30 GROSS BETA 4.40E3-02 1.60E-03 3.10E-03

• ONS-6 12393-06 30 GROSS BETA 4.17E-02 1.SOE-03 3.10E-03

• NBF U3393-07 30 GROSS BETA 4.32E-02 1.60E-03 3.30E-03

• SBN 12393-08 30 GROSS BETA 4.3 IE-02 1.60E-03 3.20E-03 *

• DOW 13393-09 30 GROSS BETA 4.3 1E-02 1.60E-03 3.10E-03

• COL U3393-10 30 GROSS BETA 3.58E-02 1.20E-03 2.30E-03

• ONS-1 12453-01 31 GROSS BETA 2.86E-02 1.40E-03 3.30E-03

• ONS-2 L3453-02 31 GROSS BETA 3.55E-02 1.60E-03 3.50E-03

• ONS-3 13453-03 31 GROSS BETA 3.03E-02 1.50E-03 3.30E-03

• ONS4 L3453-04 31 GROSS BETA 2.63E-02 1.40E-03 3.20E-03

• ONS-5 L3453-05 31 GROSS BETA 2.78E-02 1.30E-03 3.OOE-03

• ONS-6 L3453-06 31 GROSS BETA 2.90E-02 1.40E-03 3.30E-03

• NBF L3453-07 31 GROSS BETA 2.73E-02 1.40E-03 3.20E-03

• SBN L3453-08 31 GROSS BETA 2.13E-02 1.30E-03 3.10E-03

• DOW L3453-09 31 GROSS BETA 2.56E-02 1.40E-03 3.40E-03

• COL U3453-10 31 GROSS BETA 3.09E-02 1.80E-03 4.20E-03

• ONS-1 U3513-01 32 GROSS BETA 2.76E3-02 1.50E-03 3.40E-03

• ONS-2 12513-02 32 GROSS BETA 3.53E-02 I1.60E3-03 3.40E-03

• ONS-3 12513-03 32 GROSS BETA 2.70E-02 1.40E-03 3.30E-03

• ONS-4 12513-04 32 GROSS BETA 2.44E 1.30E-03 3.IOE-03 *

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-10

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/l 3 ) (pCi/ m3) (pCi/m 3 )

ONS-5 L3513-05 32 GROSSBETA 4.91E-02 5.40E-03 1.50E-02

• ONS-6 L3513-06 32 GROSSBETA 2.68E-02 1.40E-03 3.20E-03

• NBF L3513-07 32 GROSSBETA 3.011E-02 1.50E-03 3.40E-03

• SBN L3513-08 32 GROSSBETA 3.311E-02 1.50E-03 3.30E-03

• DOW L3513-09 32 GROSS BETA 2.83E-02 1.40E-03 3.308-03

• COL L3513-10 32 GROSSBETA 3.42E-02 1.808-03 4.30E-03

• ONS-1 L3569-01 33 GROSS BETA 2.97E-02 1.408-03 2.80E-03

• ONS-2 L3569-02 33 -GROSS BETA . 3.68E-02 1.50E-03 2.90E-03

• ONS-3 L3569-03 33 GROSS BETA 3.06E-02 1.40E-03 2.70E-03

• ONS-4 L3569-04 33 GROSS BETA - 2.75E-02 1.30E-03 2.70E-03

• ONS-5 L3569-05 33 GROSS BETA 3.01E-02 1.40E-03 2.80E-03

• ONS-6 L3569-06 33 GROSSBETA 3.06E-02 1.40E-03 2.70E-03

• NBF L3569-07 33 GROSS BETA 2.85E-02 1.40E-03 2.80E-03

• SBN L3569-08 33 GROSS BETA 3.04E-02 1.40E-03 2.808-03

• DOW L3569-09 33 GROSS BETA 1.57E-02 5.008-03 1.50E-02

• COL L3569-10 33 GROSS BETA 2.68E-02 1.30E-03 2.608-03

• ONS-1 13613-01 34 GROSS BETA 1.96E-02 1.30E-03 3.30E-03

• ONS-2 L3613-02 34 GROSS BETA 2.60E-02 1.408-03 3.30E-03

• ONS-3 L3613-03 34 GROSS BETA 2.12E-02 1.30E-03 3.20E-03

• ONS-4 L3613-04 34 GROSSBETA 1.988-02 1.40E-03 3.40E-03

• ONS-5 L3613-05 34 GROSS BETA 2.36E-02 1.40E-03 3.40E-03

• ONS-6 L3613-06 34 GROSS BETA 1.79E-02 1.30E-03 3.408-03

• NBF L3613-07 34 GROSS BETA 2.40E-02 1.408-03 3.30E-03

• SBN L3613-08 34 GROSS BETA 1.998-02 1.30E-03 3.30E-03

• DOW L3613-09 34 GROSS BETA 2.03E-02 1.408-03 3.408-03

• COL L3613-10 34 GROSS BETA 1.89E-02 2.50E-03 7.208-03

• ONS-I L3697-01 35 GROSS BETA 2.26E-02 1.80E-03 4.40E-03

• ONS-2 L3697-02 35 GROSS BETA 3.29E-02 1.908-03 4.308-03

• ONS-3 L3697-03 35 GROSS BETA 2.12E-02 1.708-03 4.20E-03

• ONS-5 L3697-05 35 GROSS BETA 2.41E-02 1.808-03 4.50E-03

• ONS-6 L3697-06 35 GROSS BETA 2.18E-02 1.808-03 4.50E-03

• NBF L3697-07 35 GROSS BETA 2.43E-02 1.80E-03 4.30E-03

• SBN L3697-08 35 GROSS BETA 2.64E-02 1.808-03 4.308-03

• DOW U3697-09 35 GROSS BETA 2.68E-02 1.808-03 4.408-03

• COL L3697-10 35 GROSS BETA 2.038-02 1.70E-03 4.40E-03 *

• Radioactivity detected in sample (iLe, concentration > 3 X standard deviation)

D-11

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m3) (pCi/ m3 ) (pCi/m 3 )

ONS-1 L3743-01 36 GROSS BETA 2.59E-02 1.80E-03 4.30E-03

• ONS-2 L3743-02 36 GROSS BETA 3.42E-02 1.90E-03 4.40E-03

• ONS-3 L3743-03 36 GROSS BETA 2.40E-02 1.70E-03 4.20E-03

• ONS-4 L3743-04 36 GROSS BETA 2.53E-02 1.80E-03 4.30E-03

• ONS-5 L3743-05 36 GROSS BETA 3.08E-02 1.90E-03 4.30E-03

• ONS-6 L3743-06 36 GROSS BETA 2.53E-02 1.80E-03 4.30E-03

• NBF L3743-07 36 GROSS BETA 2.95E-02 1.80E-03 4.10E-03

• SBN L3743-08 36 GROSS BETA 3.13E-02 1.90E-03 4.30E-03 0 DOW L3743-09 36 GROSS BETA 2.69E-02 2.OOE-03 5.OOE-03

• COL L3743-10 36 GROSS BETA 2.1 IE-02 1.70E-03 4.40E-03

• ONS-I L3804-01 38 GROSS BETA 4.73E-02 1.60E-03 2.80E-03

• ONS-2 L3804-02 38 GROSS BETA 4.95E-02 1.70E-03 2.80E-03

• ONS-3 L3804-03 38 GROSS BETA 4.03E-02 1.50E-03 2.80E-03

• ONS-4 L3804-04 38 GROSSBETA 3.58E-02 1.50E-03 2.80E-03

• ONS-5 L3804-05 38 GROSS BETA 4.16E-02 1.50E-03 2.80E-03

• ONS-6 L3804-06 38 GROSS BETA 3.83E-02 1.50E-03 2.80E-03

• NBF L3804-07 38 GROSSBETA 4.28E-02 1.50E-03 2.70E-03

• SBN L3804-08 38 GROSS BETA 3.86E-02 1.50E-03 2.70E-03

• DOW L3804-09 38 GROSS BETA 3.38E-02 1.30E-03 2.40E-03

• COL L3804-10 38 GROSS BETA 3.18E-02 1.40E-03 2.80E-03

• ONS-I L3869-01 38 GROSS BETA 3.67E-02 1.60E-03 3.40E-03

• ONS-2 L3869-02 38 GROSS BETA 4.50E-02 1.70E-03 3.50E-03

• ONS-3 L3869-03 38 GROSS BETA 3.51E-02 1.50E-03 3.30E-03

• ONS-4 L3869-04 38 GROSS BETA 3.22E-02 I.SOE-03 3.50E-03 ONS-5 L3869-05 38 GROSS BETA 3.89E-02 1.60E-03 3.30E-03 ONS-6 L3869-06 38 GROSS BETA 3.44E-02 1.60E-03 3.40E-03

• NBF L3869-07 38 GROSS BETA 3.86E-02 1.60E-03 3.30E-03

• SBN L3869-08 38 GROSS BETA 3.95E-02 1.60E-03 3.40E-03

• DOW L3869-09 38 GROSS BETA 3.38E-02 1.50E-03 3.40E-03

• COL L3869-10 '38 GROSS BETA 3.50E-02 1.60E-03 3.40E-03

• ONS-1 L3952-01 39 GROSSBETA 2.24E-02 1.SOE-03 3.30E-03 -*

ONS-2 L3952-02 39 GROSSBETA 2.86E-02 1.70E-03 3.40E-03

• ONS-3 L3952-03 39 GROSS BETA 2.35E-02 1.60E-03 3.40E-03

• ONS-4 L3952-04 39 GROSS BETA 2.09E-02 1.SOE-03 3.30E-03

• ONS-5 L3952-05 39 GROSS BETA 2.38E-02 1.5SE-03 3.30E-03

• ONS-6 L3952-06 39 GROSS BETA 2.61E-02 1.60E-03 3.40E-03 *

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-12

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3 ) (pCi/ m3) (pCi/m3)

-d I

NBF L3952-07 39 GROSS BETA 2.04E3-02 1.50E-03 3.30E-03

• SBN L3952-08 39 GROSS BETA 2.341E-02 1.60E-03 3.40E-03

• DOW U3952-09 39 GROSS BETA 2.22E.-02 1.60E-03 3.40E3-03

• COL L3952-10 39 GROSS BETA 2.101E-02 1.50E-03 3.40E-03

• ONS-I U3976-01 40 GROSS BETA 3.99E-02 1.90E-03 4.10E-03

• ONS-2 L3976-02 40 GROSS BETA 6.03E-02 2.30E-03 4.50E-03

• ONS-3 L3976-03 40 GROSS BETA 4.70E-02 2.20E-03 4.60E-03

• ONS-4 L3976-04 40 GROSS BETA 4.211E-02 2.10E-03 4.60E-03

• ONS-5 L3976-05 40 GROSS BETA 4.25E3-02 2.10E-03 4.50E-03

• ONS-6 L3976-06 40 GROSS BETA 4.091E-02 1.90E-03 4.10E-03

• NBF L3976-07 40 GROSS BETA 4..76E-02 2.10E-03 4.30E-03

• SBN L3976-08 40 GROSS BETA 4.62E3-02 2.20E-03 4.60E-03

• DOW L3976-09 40 GROSS BETA 4.74E-02 2.20E-03 4.70E-03

• COL U2976-10 40 GROSS BETA 4.221E-02 2.10E-03 4.50E-03

• ONS-1 L4032-01 41 GROSS BETA 3.171E-02 1 .701E-03 3.10E-03

• IONS-2 L4032-02 41 GROSS BETA 3.84E-02 1.801E-03 3.1OE-03

• ONS-3 L4032-03 41 GROSS BETA 3.121E-02 I1.60E3-03 3.10E-03

• ONS-4 L4032-04 41 GROSS BETA 3. 14E-02 1.60E-03 2.90E-03

• ONS-5 L4032-05 41 GROSS BETA 2.63E3-02 I1.601E-03 3.10E-03

• IONS-6 L4032-06 41 GROSS BETA 3.15E1-02 I1.70E1-03 3.10E-03

• NBF L4032-07 41 GROSS BETA 2.93E3-02 1.601E-03 3.00E-03 *-

SBN L4032-08 41 GROSS BETA 2.67E3-02 1.501E-03 2.90E-03

• DOW L4032-09 41 GROSS BETA 3.021E-02 1.60E-03 3.OOE-03

• COL L4032-10 41 GROSS BETA 2.80E,02 1.60E-03 3.1OE-03

• ONS-I L4106-01 42 GROSS BETA 3.69E-02 1.90E-03 3.50E-03

• ONS-2 L4106-02 42 GROSS BETA 4.331E-02 2.00E-03 3.50E-03

• ONS-3 L4106-03 42 GROSS BETA 3.72E3-02 1.90E-03 3.50E-03

• ONS-4 IA106-04 42 GROSS BETA 3.231E-02 1.70E-03 3.40E-03

• ONS-5 L4106-05 42 GROSS BETA 3.441E-02 1.80E-03 3.40E-03

• ONS-6 L4106-06 42 GROSS BETA - 3.421E-02 1.80E-03 3.50E-03

• NBF LA106-07 42 GROSS BETA 3.82E3-02 1.80E-03 3.30E-03

• SBN L4106-08 42 GROSS BETA 3.74t-02 1.80E-03 3.20E-03

• DOW I4106-09 42 GROSS BETA 3.331E-02 1.80E-03 3.50E-03

• COL L4106-10 42 GROSS BETA 3.271E-02 1.80E-03 3.50E-03 *

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-13

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3) (pCi/ mI3 ) (pCi/m 3)

ONS-I LU166-41 43 GROSSBETA 2.20E-02 1.40E-03 3.60E-03

• ONS-2 LU166-02 43 GROSSBETA 2.73E-02 1.50E-03 3.60E-03

• ONS-3 LU166-03 43 GROSS BETA 2.09E-02 1.40E-03 3.50E-03

• ONS4 LU166-04 43 GROSS BETA 2.13E-02 I .40E-03 3.60E-03

• ONS-5 LA166-05 43 GROSS BETA 1.80E-02 1.40E-03 3.60E-03

• ONS-6 LA166-06 43 GROSS BETA 2.01E-02 1.40E-03 3.SOE-03

• NBF LA166-07 43 GROSS BETA 2.58E-02 I .50E-03 3.SOE-03

• SBN LA166-08 43 GROSS BETA 2.04E-02 1.40E-03 3.60E-03

• DOW LA166-09 43 GROSS BETA 2.06E-02 1.40E-03 3.60E-03

• COL L4166-10 43 GROSS BETA 2.07E-02 1.40E-03 3.50E-03

• ONS-1 L4223-01 44 GROSS BETA 2.76E-02 1.50E-03 3.40E-03

• ONS-2 LA223-02 44 GROSS BETA 3.84E-02 1.60E-03 3.40E-03

• ONS-3 UA223-03 44 GROSS BETA 2.99E-02 1.40E-03 3.20E-03

• ONS-4 LA223-04 44 GROSS BETA 2.75E-02 1.40E-03 3.30E-03

• ONS-5 LA223-05 44 GROSS BETA 2.80E-02 1.40E-03 3.30E-03

• ONS-6 UA223-06 44 GROSS BETA 2.88E-02 1.40E-03 3.10E-03

• NBF LA223-07 44 GROSS BETA 3.16E-02 1.50E-03 3.30E-03 SBN LA223-08 44 GROSS BETA 3.1 IE-02 1.50E-03 3.30E-03

• DOW LA223-09 44 GROSS BETA 2.46E-02 1.40E-03 3.40E-03

• COL LA223-10 44 GROSS BETA 2.86E-02 1.SOE-03 3.40E-03

• ONS-1 L4259-41 45 GROSS BETA 5.26E-02 2.10E-03 3.SOE-03

• ONS-2 L4259-02 45 GROSS BETA 7.26E-02 2.40E-03 3.60E-03

• ONS-3 L4259-03 45 GROSS BETA 5.77E-02 2.20E-03 3.50E-03

• ONS-4 L4259-04 45 GROSS BETA 4.73E-02 2.OOE-03 3.50E-03

• ONS-5 L4259-05 45 GROSS BETA 4.65E-02 2.OOE-03 3.50E-03

• ONS-6 L4259-06 45 GROSS BETA 5.OOE-42 2.OOE-03 3.50E-03

• NBF U4259-07 45 GROSS BETA 5.62E-02 2.10E-03 3.50E-03

• SBN L4259-08 45 GROSS BETA 4.62E-02 2.00E-03 3.50E-03

• DOW LA259-09 45 GROSS BETA 5.36E-02 2. 1OE-03 3.60E-03

• COL LA259-10 45 GROSS BETA 5. 17E-02 2.10E-03 3.40E-03

• ONS-1 LA299-01 46 GROSS BETA 4.55E-02 2.00E-03 4.10E-03

• ONS-2 LA299-02 46 GROSS BETA 6.60E-02 2.20E-03 4.10E-03

• ONS-3 LA299-03 46 GROSS BETA 5.36E-02 2.10E-03 4. IOE-03

• ONS-4 LA299-04 46 GROSS BETA 4.74E-02 2.20E-03 4.60E-03

• ONS-5 LA299-05 46 GROSS BETA 4.55E-02 2. 1OE-03 4.50E-03

• ONS-6 LA299-06 46 GROSS BETA 4.79E-02 2.10E-03 4.50E-03 *

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-14

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC

.(pCi/rn3 ) (Pci/ MI) (pCi/m 3 )

NBF LU299-07 46 GROSS BETA 5.58E-02 2.20E-03 4.30E-03

• SBN L4299-08 46 GROSS BETA 5.59E-02 2.30E-03 4.50E-03

• DOW LA299-09 46 GROSS BETA 4.79E-02 2.OOE-03 4.002-03

• COL L4299-10 46 GROSS BETA 4.62E-02 2.10E-03 4.50E-03

• ONS-1 L4365-01 47 GROSSBETA 1.95E-02 1.60E-3 4.00E-03

• ONS-2 L4365-02 47 GROSSBETA 3.38E-02 1.80E-03 4.10E-03 * -

ONS-3 LU365-03 47 GROSS BETA 2.79E-02 1.70E-03 4.10E-03

• ONS-4 LA365-04 47 GROSSBETA 2.40E-02 1.70E-03 4.20E-03

• ONS-5 LU365-05 47 GROSS BETA 2.81E-02 1.80E-03 4.30E-03

• ONS-6 LA365-06 47 GROSS BETA 2.33E-02 1.70E-03 4.40E-03

• NBF LA365-07 47 GROSS BETA 3.03E2-02 1.90E-03 4.40E-03

• SBN LU365-08 47 GROSS BETA' 2.52E-02 I.80E-03 4.40E-03

• DOW LA365-09 47 GROSS BETA 2.78E-02 1.70E-03 4.10E-03

• COL LU365-10 47 GROSS BETA 2.60E-02 1.90E-03 4.60E-03

• ONS-1 L4411-01 48 GROSS BETA 2.04E-02 1.40E-03 3.00E-03

• ONS-2 L4411-02 48 GROSS BETA 2.77E-02 1.70E-03 3.30E-03

• ONS-3 LA411-03 48 GROSS BETA 2.12E-02 1.50E-03 3.10E-03

• ONS4 L4411-04 48 GROSS BETA 1.96E-02 1.40E-03 3.00E-03

• ONS-5 L4411-05 48 GROSS BETA 2.14E-02 1.40E-03 3.10E-03

• ONS-6 L4411-06 48 GROSS BETA 1.96E-02 1.50E-03 3.30E-03

• NBF L4411-07 48 GROSS BETA 2.45E-02 1.50E-03 3.00E-03

• SBN L4411-08 48 GROSS BETA 2.47E-02 1.50E-03 3.20E-03

• DOW LA411-09 48 GROSS BETA 2.35E-02 1.50E-03 3.10E-03

• COL LA411-10 48 GROSS BETA 2.25E-02 1.50E-03 3.20E-03

• ONS-I LU448-01 49 GROSS BETA 2.23E-02 1.70E-03 4.50E-03

• ONS-2 L4448-02 49 GROSS BETA 3.32E-02 1.90E-03 4.50E-03

• ONS-3 LA448-03 49 GROSS BETA 2.74E-02 1.802-03 4.502-03

• ONS-4 L4448-04 49 GROSS BETA 2.34E-02 1.80E-03 4.50E-03

• ONS-5 LA448-05 49 GROSS BETA 2.32E-02 1.70E-03 4.30E-03

• ONS-6 L4448-06 49 GROSSBETA 2.36E-02 1.702-03 4.30E-03

• NBF L4448-07 49 GROSS BETA 2.44E-02 1.80E-03 4.50E-03

• SBN L4448-08 49 GROSSBETA 2.44E-02 1.80E-03 4.70E-03

• DOW L4448-09 49 GROSS BETA 2.00E-02 1.80E-03 4.70E-03

• COL L4448-10 49 GROSS BETA 2.083-02 1.80E-03 4.90E-03 *

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-15

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m3 ) (pCit m3 ) (pCi/m 3)

ONS-1 L4496-01 50 GROSS BETA 4.021E-02 1.90E-03 3.701E-03

• ONS-2 LU496-02 50 GROSS BETA 3.911E-02 I1.90E-03 3.70E-03

• ONS-3 L4496-03 50 GROSS BETA 4.39E3-02 2.OOE-03 3.80E3-03

• ONS4 L4496-04 50 GROSS BETA 4.231E-02 2.OOE-03 3.70E-03

• ONS-5 U4496-05 50 GROSS BETA 4.061E-02 2.OOE-03 3.70E3-03

• ONS-6 L4496-06 50 GROSS BETA 4.371E-02 1.90E-03 3.40E-03

• NBF L4496-07 50 GROSS BETA 4.60E3-02 2.OOE-03 3.701E-03

• SBN L4496-08 50 GROSS BETA 4.451E-02 2.00OE-03 3.601E-03

• DOW L4496-09 50 GROSS BETA 4.38E-02 2.OOE-03 3.601E-03

• COL U4496-10 50 GROSS BETA 3.951E-02 I1.90E-03 3.60E-03

• ONS-1 LA544-01 51 GROSS BETA 4.47E-02 1.60E-03 2.901E-03

• ONS-2 LA544-02 SI GROSS BETA 4.901E-02 2.10E-03 4.001E-03

• ONS-3 LA544-03 51 GROSS BETA 3.64E-02 1.40E-03 2.601E-03

• ONS-4 LA544 04 S1 GROSS BETA 4. 16E-02 1.60E-03 2.90E3-03

• ONS-5 L4544-05 51 GROSS BETA 4. 17E-02 1.60E-03 2.901E-03

• ONS-6 LA544-06 51 GROSS BETA 4.20E3-02 1.50E-03 2.601E-03

• NBF L4544-07 51 GROSS BETA 4.52E3-02 1.60E-03 2.801E-03

• SBN LA544-08 51 GROSS BETA 4.51E-02 1.60E-03 2.80E-03

• DOW LA544-09 51 GROSS BETA 4.36E3-02 1.60E-03 2.801E-03

• COL LA544-10 51 GROSS BETA 4.46E-02 1.60E-03 2.801E-03

• ONS-1 L4569-01 52 GROSS BETA 2.78E-02 1.80E-03 4.20E-03

• ONS-2 L4569-02 52 GROSS BETA 2. IOE-03 1.40E-03 4.50E-03 ONS-3 L4569-03 52 GROSS BETA 2.01E-02 1.60E-03 4.20E-03

• ONS-4 L4569-04 52 GROSS BETA 2.57E-02 1.70E-03 4.10E-03

• ONS-5 L4569-05 52 GROSS BETA 2.28E-02 1.60E-03 4.10E-03

• ONS-6 L4569-06 52 GROSS BETA 2.75E-02 I.70E-03 4.10E-03

• NBF L4569-07 52 GROSS BETA 3.32E-02 1.90E-03 4.30E-03

• SBN L4569-08 52 GROSS BETA 3.16E-02 1.90E-03 4.40E-03

• DOW L4569-09 52 GROSS BETA 2.89E-02 1.90E-03 4.50E-03

• COL L4569-10 52 GROSS BETA 2.93E-02 1.90E-03 4.50E-03

• ONS-1 L2889-01 Ql AcTh-228 -4.OOE-04 8.60E-04 4.OOE-03 ONS-1 L2889-01 Ql Ag-108m -5.OOE-05 - 1.5SOE-04 6.401E-04 ONS-1 L2889-01 Ql Ag-1 10m 3.30E-04 2.40E-04 4.50E-04 ONS-1 L2889-01 Ql Ba-140 1.60E-02 1.60E3-02 4.30E-02 ONS-1 L2889-01 QI Be-7 7.40E3-02 1.50E-02 3.60E-02

• ONS-1 L2889-01 Qi Ce-141 3.OOE-04 1.30E-03 4.90E-03

• Radioactivity detected In sample (i.e., concentration > 3 X standard deviation)

D-16

Indiana Michigan Power Co., DC Cook Nuclear Plant _

Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC 3

(pCi/m3) (pCi/ M ) (pCi/im3 )

ONS-1 L2889-01 Ql Cc-144 7.00E-04 1.00E-03 3.60E-03 ONS-1 L2889-01 Ql Co-57 1.00-04 1.20E-04 4.20E-04 ONS-1 L2889-01 Ql Co-58 -2.80E-04 6.40E-04 2.90E-03 ONS-1 L2889-01 Ql Co-60 -8.40E-04 4.30E-04 2.20E-03 ONS-1 L2889-01 Ql Cr-51 7.00E-03 1.60E-02 5.90E-02 ONS-1 L2889-01 Ql Cs-134 -2.50E-04 3.202-04 1.30E-03 ONS-I L2889-01 Ql Cs-137 -6.10E-04 3.40E-04 1.50E-03 ONS-1 L2889-01 Q1 Fe-S9 -2.10E-03 4.002-03 1.80E-02 ONS-I L2889-01 Ql 1-131 -3.10E-01 1.80E-01 8.402-01 ONS-I L2889-01 Ql K-40 3.10E-03 3.30E-03 1.20E-02 ONS-I L2889-01 Q1 La-140 1.80E-02 1.80E-02 5.002-02 ONS-1 L2889-01 Ql Mn-54 -3.20E-04 2.40E-04 1.30E-03 ONS-1 L2889-01 Ql Nb-95 -6.00E-04 1.50E-03 6.702-03 ONS-1 L2889-01 Ql Ru-103 -3.101E-04 8.10E-04 3.702-03 ONS-1 L2889-01 Ql Ru-106 2.90E-03 2.30E-03 7.90E-03 ONS-1 L2889-01 Ql Sb-124 4.50E-03 2.30E-03 3.10E-03 ONS-1 L2889-01 Ql Sb-125 -1.60E-04 4.70E-04 2.10E-03 ONS-I L2889-01 Ql Se-75 7.10E-04 4.002-04 1.302-03 ONS-I L2889-01 Ql Zn-65 6.103-04 4.30E-04 8.30E-04 ONS-I L2889-01 Ql Zr-95 6.00E-04 1.20E-03 4.50E-03 -

ONS-2 L2889-02 Q1 AcTb-228 1.10E-03 1.102-03 3.80E-03 ONS-2 L2889-02 Ql Ag-108m 2.OOE-04 2.002-04 6.90E-04 ONS-2 L2889-02 Ql Ag-l Orm -1.60E-04 3.70E-04 1.80E-03 ONS-2 L2889-02 Q1 Ba-140 1.50E-02 2.70E-02 1.IOE-01 ONS-2 L2889-02 Ql Be-7 1.19E-01 1.50E-02 2.602-02 ONS-2 L2889-02 Q1 Ce-141 2.90E-03 1.60E-03 5.30E-03 ONS-2 L2889-02 Q1 Ce-144 -1.51E-03 9.60E-04 4.10E-03 ONS-2 L2889-02 Ql Co-57 7.00E-05 1.30E-04 4.60E-04 ONS-2 L2889-02 Ql Co-58 8.00E-05 5.00E-04 2.20E-03 ONS-2 L2889-02 -Q0 Co-60 2.80E-04 2.002-04 3.802-04 ONS-2 L2889-02 Q1 Cr-51 -7.00OE-03 1.50E-02 6.202-02 ONS-2 L2889-02 QI Cs-134 -1.20E-04 2.002-04 9. 102-04 ONS-2 L2889-02 Q0 Cs-137 -2.40E-04 2.802-04 1.20E-03 ONS-2 L2889-02 Ql Fe-59 -1 .90E-03 3.30E-03 1.60E-02 ONS-2 L2889-02 Ql 1-131 1.40E-01 2.102-01 7.60E-01 ONS-2 L2889-02 QI K-40 4.80E-03 4.502-03 1.602-02 ONS-2 L2889-02 Q0 La-140 1.80E-02 3.102-02 1.30E-01 ONS-2. L2889-02 Q0 Mn-54 -2.10E-04 2.10E-04 - 1.102-03 ONS-2 L2889-02 Ql Nb-95 3.00E-04 1.40E-03 5.70E-03 ONS-2 L2889-02 Ql Ru-103 -3.101E-04 5.30E-04. 2.802-03 -

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-17

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC 3

(pCi/rn ) (pCi/ m3) (pCi/M 3)

ONS-2 L2889-02 Q1 Ru-106 4.60E-03 2.30E-03 6.20E-03 ONS-2 L2889-02. Ql Sb-124 -I.IOE-03 1.90E-03 I.OOE-02 ONS-2 L2889-02 Q1 Sb-125 O.OOE+00 7.50E-04 2.90E-03 ONS-2 L2889-02 Ql Se-75 -8.10E-04 4.30E-04 1.90E-03 ONS-2 L2889-02 Ql Zn-65 -3.OOE-04 7.90E-04 3.60E-03 ONS-2 12889-02 Ql Zr-95 1.40E-03 1.20E-03 4.OOE-03 ONS-3 L2889-03 Ql Ac-h-228 -1.52E-03 9.40E-04 4.60E-03 ONS-3 L2889-03 Ql Ag-108m -1.30E-04 1.60E-04 7.OOE-04 ONS-3 12889-03 Q1 Ag-110m l.lOE-04 3.50E-04 1.50E-03 ONS-3 L2889-03 Ql Ba-140 2.70E-02 1.90E-02 3.70E-02 ONS-3 L2889-03 Ql Be-7 1.16E-01 1.50E-02 2.50E-02 ONS-3 L2889-03 Ql Ce-141 -6.OOE-04 2.00E-03 7.40E-03 ONS-3 L2889-03 Ql Ce-144 -2.OOE-04 1.40E-03 5.30E-03 ONS-3 L2889-03 Ql Co-57 8.00E-05 1.90E-04 6.80E-04 ONS-3 L2889-03 Ql Co-58 -5.90E-04 5.20E-04 2.60E-03 ONS-3 L2889-03 Ql Co-60 -2.50E-04 2.50E-04 1.30E-03 ONS-3 L2889-03 Ql cr-Si 3.30E-02 1.90E-02 6.20E-02 ONS-3 L2889-03 Ql Cs-134 O.OOE+00 3.60E-04 1.30E-03 ONS-3 L2889-03 Ql Cs-137 -5.10E-04 3.00E-04 1.40E-03 ONS-3 L2889-03 Ql Fe-59 6.00E-03 3.60E-03 I.IOE-02 ONS-3 L2889-03 Ql 1-131 L.OOE-02 2.30E-01 8.70E-01 ONS-3 L2889-03 Ql K-40 8.OOE-04 3.80E-03 1.50E-02 ONS-3 L2889-03 Ql La-140 3.10E-02 2.20E-02 4.20E-02 ONS-3 L2889-03 Ql Mn-54 4.70E-04 2.60E-04 7.50E-04 ONS-3 L2889-03 Ql Nb-95 -5.OOE-04 1.20E-03 5.50E-03 ONS-3 L2889-03 Ql Ru-103 3.OOE-04 I.OOE-03 4.OOE-03 ONS-3 L2889-03 Ql Ru-106 5.OOE-03 2.90E-03 9.30E-03 ONS-3 L2889-03 Ql Sb-124 4.70E-03 2.60E-03 7.30E-03 ONS-3 L2889-03 Ql Sb-125 -2.OOE-05 5.OOE-04 2.OOE-03 ONS-3 L2889-03 Q! Se-75 9.60E-04 4.50E-04 1.40E-03 ONS-3 L2889-03 Ql Zn-65 -3.OE-04' 1.OOE-03 4.1OE-03 ONS-3 L2889-03 Ql Zr-95 -3.60E-04 9.60E-04 4.40E-03 ONS-4 L2889-04 Ql AcTh-228 6.OOE.04 8.90E-04 3.40E-03 ONS-4 L2889-04 Ql Ag-108m 1.40E-04 1.40E-04 5.10E-04 ONS-4 L2889-04 Ql Ag-110m -3.20E-04 5.60E-04 2.40E-03 ONS-4 L2889-04 Ql Ba-140 . 1.50E-02 2.70E-02 I.IOE-0O ONS-4 L2889-04 Ql Be-7 1.04E-01 1.40E-02 2.40E-02 ONS-4 L2889-04 Ql Cc-141 I.OOE-03 1.30E-03 4.70E-03 ONS-4 L2889-04 Ql Cc-144 3.20E-04 9.30E-04 3.40E-03 ONS-4 L2889-04 Ql Co-57 -2.OOE-05 1.30E-04 5.OOE-04

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-18

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program

- Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3 ) (pCi/ m3) (pCi/n 3)

ONS-4 L2889-04 Q1 Co-58 -4.20E-04 7.10E-04 3.108-03 ONS-4 L2889-04 Ql Co-60 -1.60E-04 1.60E-04 1.108-03 ONS-4 L2889-04 Q1 Cr-51 1.00-02 1.50E-02 5.40E,02 ONS-4 L2889-04 Ql Cs-134 -4.20E-04 2.50E-04 1.20E-03 ONS-4 L2889-04 Ql Cs-137 I.90E-04 2.50E-04 9. IOE-04 ONS-4 L2889-04 Ql Fe-59 -3.00E-03 2.10E-03 1.30E-02 ONS-4 L2889-04 Q1 1-131 0.OOE+00 1.70E-01 6.80E-01 ONS-4 L2889-04 Ql K-40 -9.008-04 3.40E-03 1.508-02 ONS-4 L2889-04 Q1 La-140 1.808-02 3.IOE-02 1.30E-01 ONS-4 L2889-04 Ql Mn-54 I.OOE-04 2.30E-04 9.60E-04 ONS-4 L2889-04 Q1 Nb-95 1.30E-03 1.60E-03 6.008-03 ONS-4 L2889-04 Ql Ru-103 -8.80E-04 9.80E-04 4.40E-03 ONS-4 L2889-04 Ql Ru-106 3.50E-03 2.40E-03 7.60E-03 ONS-4 L2889-04 Q1 Sb-124 O.OOE+00 2.20E-03 1.008-02 ONS-4 L2889-04 Q1 Sb-125 -3.00E-04 4.80E-04 2.10E-03 ONS-4 L2889-04 Ql Se-75 -6.10E-04 3.70E-04 1.608-03 ONS-4 L2889-04 Q1 Zn-65 5.90E-04 7.20E-04 2.70E-03 ONS-4 L2889-04 Q1 Zr-95 -6.80E-04 4.80E-04 3.40E-03 ONS-5 L2889-05 Q1 AcTh-228 -1.20E-03 1.108-03 5.108-03 ONS-5 L2889-05 Q1 Ag-108m -1.00-04 1.50E-04 6.90E-04 ONS-5 L2889-05 Ql Ag-llOmn -1.60E-04 2.80E-04 1.50E-03 ONS-5 L2889-05 Ql Ba-140 0.00+00 0.00+00 4.108-02 ONS-5 L2889-05 Q1 Be-7 1.50E-01 1.708-02 2.40E-02 ONS-5 L2889-05 Q1 Cc-141 2.10E-03 1.60E-03 5.301-03 ONS-5 L2889-05 Q1 Ce-144 4.00E-04 1.20E-03 4.20E-03 ONS-5 L2889-05 Ql Co-57 -4.00E-05 1.40E-04 5.20E-04 ONS-5 L2889-05 Ql Co-58 1.IOE-04 5.70E-04 2.40E-03 ONS-5 L2889-05 Ql Co-60 4.20E-04 2.408-04 3.80E-04 ONS-5 L2889-05 Q1 Cr-51 -1.OOE-02 1.008-02 4.80E-02 ONS-5 L2889-05 Ql Cs-134 7.00E-05 2.808-04 I.1OE-03 ONS-5 L2889-05 Q1 Cs-137 2.00E-04 2.50E-04 9.30E-04 ONS-5 L2889-05 Q1 Fe-59 2.70E-03 1.908-03 3.70E-03 ONS-5 L2889-05 Q0 1-131 2.20E-01 1.608-01 5.408-01 ONS-5 L2889-05 Q1 K-40 -8.OOE-04 3.50E-03 1.608-02 ONS-5 L2889-05 Ql La-140 0.00+00 0.00+00 4.80E-02 ONS-5 L2889-05 Ql Mn-54 -4.20E-04 3.90E-04 1.80E-03 ONS-5 L2889-05 Q1 Nb-95 6.OOE-04 1.108-03 4.40E-03 ONS-5 L2889-05 Ql Ru-103 O.OOE+00 8.608-04 3.60E-03 ONS-5 L2889-05 Q1 Ru- 106 -9.00-04 3.10E-03 1.30E-02 ONS-5 L2889-05 Q0 Sb-124 1.10-03 1.908-03 7.90E-03

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-19

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/rn3) (pCi/ m 3 ) (pCi/m 3 )

ONS-5 L2889-05 Ql Sb-125 -9.50E-04 5.90E-04 2.70E-03 ONS-5 L2889-05 QI Se-75 -8.00E-05 4.30E-04 1.70E-03 ONS-5 L2889-05 Q1 Zn-65 -8.90E-04 7.80E-04 3.90E-03 ONS-5 L2889-05 Ql Zr-95 1.00E1-04 7.50E-04 3.50E-03 ONS-6 L2889-06 Ql AcTh-228 1.38E-03 8.20E-04 2.50E-03 ONS-6 L2889-06 Q1 Ag-108m -2.00E-04 1.80E-04 7.90E-04 ONS-6 L2889-06 Ql Ag-I 10m 2.20E-04 4.90E-04 1.90E-03 ONS-6 L2889-06 Ql Ba-140 -3.70E-02 4.50E-02 2.IOE-01 ONS-6 L2889-06 Q1 Be-7 8.90E-02 1.40E-02 3.OOE-02

• ONS-6 L2889-06 Ql Ce-141 2.20E-03 2.10E-03 7.OOE-03 ONS-6 L2889-06 Ql Ce-144 -1.20E-03 1.40E-03 5.40E-03 ONS-6 L2889-06 Ql Co-57 -2.60E-04 1.90E-04 7.40E-04 ONS-6 L2889-06 Ql Co-58 -2.OOE-04 5.30E-04 2.40E-03 ONS-6 L2889-06 Ql Co-60 -1.20E-04 2.80E-04 1.30E-03 ONS-6 L2889-06 Ql Cr-51 1.80E-02 1.80E-02 6.20E-02 ONS-6 L2889-06 Ql Cs-134 -9.OOE-05 1.60E-04 8.70E-04 ONS-6 L2889-06 Ql Cs-l`37 2.20E-04 2.40E-04 8.70E-04 ONS-6 L2889-06 Ql Fe-59 3.70E-03 2.80E-03 9.10E-03 ONS-6 L2889-06 Ql 1-131 1.20E-01 2.30E-01 8.50E-01 ONS-6 L2889-06 Ql K-40 -6.50E-03 3.30E-03 1.80E02 ONS-6 L2889-06 Ql La-140 -4.30E-02 5.20E-02 2.40E-01 ONS-6 L2889-06 Ql Mn-54 -4.60E-04 3.OOE-04 1.50E-03 ONS-6 L2889-06 Ql Nb-95 -I.OOE-03 1.80E-03 7.60E-03 ONS-6 L2889-06 Ql Ru-103 2.00E-03 1.30E-03 4.40E-03 ONS-6 L2889-06 Ql Ru-106 3.60E-03 2.90E-03 1.00E-02 ONS-6 L2889-06 Ql Sb-124 1.90E-03 1.40E-03 2.60E-03 ONS-6 L2889-06 Ql Sb-125 -2.OOE-04 6.60E-04 2.60E-03 ONS-6 L2889-06 Ql Sc-75 -I.OOE-05 5.30E-04 2.OOE-03 ONS-6 L2889-06 Ql Zn-65 -1.30E-04 7.60E-04 3.30E-03 ONS:6 L2889-06 Ql Zr-95 4.OOE-04 1.20E-03 4.90E-03 NBF L2889-07 Ql AcTh-228 -6.00E-05 7.40E-04 3.30E-03 NBF L2889-07 Ql Ag-108m -2.30E-04 1.50E-04 7.30E-04 NBF L2889-07 Ql Ag-I tOm -3.20E-04 2.20E-04 1.50E-03 NBF L2889-07 Ql Ba-140 -3.40E-02 2.40E42 1.60E-01 NBF L2889-07 Ql Be-7 1.1 IE-01 1.50E-02 2.40E-02 NBF L2889-07 Ql Ce-141 1.20E-03 1.30E-03 4.50E-03 NBF L2889-07 Ql Ce-144 1.00E-04 .OOE-03 3.80E-03 NBF L2889-07 Ql Co-57 1.00E-05 1.20E-04 4.50E-04 NBF L2889-07 Ql Co-58 6.90E-04 5.40E-04 1.80E3 NBF L2889-07 QI Co-60 O.OOE+00 O.OOE+00 3.70E-04

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-20

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program ISummary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3) (PCi/ mI) (pCi/m3)

NBF L2889-07 Ql Cr-51 1.70E-02 1.70E-02 5.80E-02 NBF L2889-07 Q1 Cs-134 3.40E-04 2.90E-04 9.90E-04 NBF L2889-07 QI Cs-137 4.00E-05 2.10E-04 8.90E-04 NBF L2889-07 QI Fe-59 -1.50E-03 l.50E-03 I.1OE-02 NBF L2889-07 Ql 1-131 -I.OOE-0O 2.00E-01 8.30E-01 NBF L2889-07 QI K-40 -9.00E-04 3.30E-03 1.502-02 NBF L2889-07 QI La-140 -3.90E-02 2.70E-02 L.802-01 I NBF L2889-07 QI Mn-54 8.10E-04 3.80E-04 1.102-03 NBF L2889-07 Q1 Nb-95 -1.20E-03 1.20E-03 6.10E-03 NBF L2889-07 Q1 Ru-103 2.08E-03 8.90E-04 2.20E-03 NBF L2889-07 Q1 Ru-106 4.00E-04 2.10E-03 8.702-03 NBF L2889-07 Ql Sb-124 -L.IOE-03 2.40E-03 1.202-02 NBF L2889-07 Ql Sb-125 -5.90E-04 5.60E-04 2.50E-03 NBF L2889-07 Q1 Se-75 4.50E-04 3.40E-04 1.10E-03 NBF L2889-07 QI Zn-65 -2.90E-04 6.502-04 3.102-03 NBF L2889-07 Ql Zr-95 -5.90E-04 8.802-04 4.302-03 SBN L2889-08 Ql Aclh-228 1.81E-03 9.70E-04 2.802-03 SBN L2889-08 Ql Ag-108m 0.00Q+00 1.60E-04 6.402-04 SBN L2889-08 Qi Ag-l Orm 6.60E-04 4.00E-04 1.20E-03 SBN U2889-08 QI Ba-140 1.70E-02 3.80E-02 1.602-01 I SBN L2889-08 Ql Bc-7 1.09E-01 1.502-02 2.90E-02 SBN L2889-08 QI Ce-141 2.60E-03 1.40E-03 4.40E-03 SBN L2889-08 Ql Ce-144 -9.90E-04 9.90E-04 4.00E-03 SBN L2889-08 Q1 Co-57 1.40E-04 1.402-04 4.70E-04 SBN L2889-08 Qi Co-5S -6.00E-05 6.80E-04 2.90E-03 SBN L2889-08 Ql Co-60 l.lOE-04 3.30E-04 1.402-03 SBN L2889-08 Qi Cr-SI -4.00E-03 1.90E-02 7.50E-02 SBN L2889-08 QI Cs-134 2.20E-04 2.00E-04 7.20E-04 SBN L2889-08 QI Cs-137 -3.00E-04 2.40E-04 1.102-03 SBN L2889-08 Ql Fe-59 -2.00E-04 2.10E-03 l.OE-02 SBN L2889-08 Qi 1-131 1.60E-01 1.90E-01 7.00E-01 SBN L2889-08 QI K-40 2.002-03 3.50E-03 1.40E-02 SBN L2889-08 Ql La-140 2.00E-02 4.40E-02 1.80E-01 SBN L2889-08 Q1 Mn-54 1.10-04 3.20E-04 1.30E-03 SBN L2889-08 Ql Nb-95 2.30E-03 1.50E-03 4.60E-03 SBN L2889-08 Qi Ru-103 -3.20E-04 9.50E-04 4.102-03 SBN L2889-08 QI Ru-106 -2.30E-03 2.70E-03 1.20E-02 SBN L2889-08 Ql Sb-124 1.102-03 1.90E-03 8.20E-03 SBN L2889-08 QI Sb-125 -3.20E-.04 5.00E-04 2.20E-03 SBN L2889-08 QI Se-75 0.OOE+00 4.30E-04 1.602-03

• Radioactivity detected In sample (i.e., concentration > 3 X standard deviation)

D-21

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3) (pCil m3 ) (pCi/m 3 )

SBN L2889-08 QI Zn-65 6.OOE-04 8.SOE-04 3.20E-03 SBN L2889-08 Ql Zr-95 -2.00E-04 I.IOE-03 5.OOE-03 DOW L2889-09 QI AcTh-228 7.00E-04 I.IOE-03 4.00E-03 DOW L2889-09 Ql Ag-108m 0.OOE+O0 1.70E-04 6.80E-04 DOW L2889-09 Ql Ag-I lOm 1.48E-03 5.80E-04 1.50E-03 DOW L2889-09 Ql Ba-140 -3.70E-02 4.00E-02 2.OOE-OI DOW L2889-09 Ql Be-7 1.04E-0O I.50E-02 3.10E-02 DOW L2889-09 Ql Ce-141 4.00E-04 2.OOE-03 7.20E-03 DOW L2889-09 Ql Ce-144 -9.00E-04 1.40E-03 5.30E-03 DOW L2889-09 Ql Co-57 -I.10E-04 1.70E-04 6.40E-04 DOW L2889-09 Ql Co-58 -8.20E-04 5.OOE-04 2.70E-03 DOW L2889-09 Ql Co-60 -2.50E-04 2.50E-04 1.40E-03 DOW L2889-09 Ql Cr-51 l.lOE-02 I.90E-02 6.90E-02 DOW L2889-09 Qi Cs-134 4.80E-04 3.SOE-04 1.20E-03 DOW L2889-09 QI Cs-137 O.OOE+00 2.60E-04 I.OOE-03 DOW L2889-09 Ql Fe-59 -3.80E-03 2.20E-03 1.40E-02 DOW L2889-09 Ql 1-131 -2.20E-01 2.10E-01 9.20E-01 DOW 12889-09 Ql K-40 3.40E-03 3.40E-03 1.20E-02 DOW L2889-09 QI La-140 -4.30E-02 4.60E-02 2.30E-01 DOW L2889-09 Ql Mn-54 3.30E-04 3.80E-04 1.40E-03 DOW L2889-09 QI Nb-95 -2.90E-03 1.80E-03 8.SOE-03 DOW L2889-09 QI Ru-103 -9.00E-04 1.20E-03 S.OOE-03 DOW L2889-09 Ql Ru-106 -2.20E-03 2.40E-03 1.IOE-02 DOW L2889-09 Ql Sb-124 -6.50E-03 2.70E-03 I.SOE-02 DOW L2889-09 Ql Sb-125 2.30E-04 6.90E-04 2.60E-03 DOW L2889-09 QI Se-7S 6.40E-04 5.60E-04 1.90E-03 DOW L2889-09 Ql Zn-65 -1.88E-03 9.40E-04 4.60E-03 DOW L2889-09 QI Zr-95 0.OOE+0O 1.30E-03 5.30E-03 COL L2889-10 Ql AcTh-228 -6.OOE-05 6.00E-04 2.90E-03 COL L2889-10 Ql Ag-108m -S.OOE-05 1.40E-04 6.20E-04 COL L2889-10 QI Ag-i lOm O.OOE+00 4.00E-04 1.70E-03 COL L2889-10 QI Ba-140 -5.20E-02 3.80E-02 2.10E-01 COL L2889-10 QI Be-7 1.03E-01 1.30E-02 1.50E-02 COL L2889-10 Ql Ce-141 -2.OOE-03 1.30E-03 5.SOE-03 COL L2889-10 QI Ce-144 -2.00E-04 I.OOE-03 3.90E-03 COL L2889-10 Ql Co-57 -2.70E-04 1.20E-04 5.20E-04 COL L2889-10 Ql Co-58 -5.70E-04 3.30E-04 2.20E-03 COL L2889-10 Ql Co-60 -3.20E-04 2.20E-04 1.40E-03 COL L2889-10 QI Cr-51 1.70E-02 1.80E-02 6.20E-02 COL L2889-10 Q1 Cs-134 -4.00E-05 2.80E-04 1.20E-03 Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-22

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m3 ) (pCil m3) (pCi/m 3)

COL L2889-10 Q1 Cs-137 -3.20E-04 2.80E-04 1.30E-03 COL L2889-10 QI Fe-59 -3.70E-03 4.30E-03 2.00E-02 COL L2889-1O Ql 1-131 2.00E-01 2.30E-01 8.1OE-01 COL L2889-10 Q1 K-40 -3.50E-03 3.30E-03 1.70E-02 COL L2889-10 Ql La-140 -5.90E-02 4.40E-02 2.40E-01 COL L2889-10 Ql Mn-54 7.30E-04 2.80E-04 2.80E-04 COL L2889-10 Ql Nb-95 1.20E-03 1.20E-03 4.50E-03 i COL L2889-10 QI Ru-103 1.20E-03 I.IOE-03 4.OOE-03 COL L2889-10 Ql Ru-106 4.OOE-04 2.20E-03 8.90E-03 COL L2889-10 Ql Sb-124 -4.40E-03 2.70E-03 1.50E-02 COL L2889-10 Ql Sb-125 4.60E-04 5.50E-04 2.00E-03 COL L2889-10 Ql Se-75 1.50E-04 3.80E-04 1.40E-03 COL L2889-10 Ql Zn-65 -1.48E-03 6.60E-04 3.90E-03 COL L2889-10 Ql Zr-95 -9.OOE-04 I.IOE-03 5.20E-03 -. j ONS-1 L3476-01 Q2 AcTh-228 -1 .90E-04 8.60E-04 3.80E-03 ONS-1 L3476-01 Q2 Ag-108m 0.OOE+00 1.90E-04 7.40E-04 ONS-1 L3476-01 Q2 Ag-1 10m 0.OOE+00 3.30E-04 1.50E-03 ONS-1 L3476-01 Q2 Ba-140 -9.80E-02 4.90E-02 2.90E-0O ONS-1 L3476-01 Q2 Be-7 1.44E-01 I.90E-02 4.20E-02 ONS-1 L3476-01 Q2 Ce-141 9.00E-04 1.70E-03 6.101E-03 ONS-1 L3476-01 Q2 Ce-144 1.20E-03 L.OOE-03 3.50E-03 ONS-1 L3476-01 Q2 Co-57 -2.00E-05 1.20E-04 4.50E-04 ONS-I L3476-01 Q2 Co-58 5.1OE-04 5.40E-04 2.00E-03 ONS-I L3476-01 Q2 Co-60 9.00E-05 2.90E-04 1.20E-03 ONS-1 L3476-01 Q2 Cr-51 -2.90E-02 2.20E-02 9.20E-02 J

ONS-1 L3476-01 Q2 Cs-134 -5.OOE-05 2.50E-04 1.1IOE-03 ONS-I L3476-01 Q2 Cs-137 4.00E-05 2.20E-04 9.00E-04 ONS-1 L3476-01 Q2 Fe-59 2.90E-03 3.20E-03 1.20E-02 ONS-I L3476-01 Q2 1-131 -9.OOE-02 4.40E-01 1.70E+00 ONS-I L3476-01 Q2 K-40 -L.OOE-04 3.80E-03 1.60E-02 ONS-1 L3476-01 Q2 La-140 -L.13E-OI 5.60E-02 3.40E-01 ONS-1 L3476-01 Q2 Mn-54 5.20E-04 3.10E-04 9.70E-04 ONS-I L3476-01 Q2 Nb-95 -I.OOE-03 1.70E-03 7.80E-03 ONS-I L3476-01 Q2 Ru-103 1.70E-03 1. IOE-03 3.70E-03 ONS-I L3476-01 Q2 Ru-106 2.00E-03 2. 1OE-03 7.70E-03 ONS-I L3476-01 Q2 Sb-124 1.20E-03 1.20E-03 3.20E-03 ONS-1 L3476-01 Q2 Sb-12S O.OOE+00 6.OOE-04 2.40E-03 ONS-1 L3476-01 Q2 Se-75 -8.OOE-05 4.30E-04 1.60E-03

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-23 i

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3 ) (pCi/ MI 3

) (pCi/mr)

ONS-I L3476-01 Q2 Zn-65 -1.19E-03 8.40E-04 4.20E-03 ONS-1 L3476-01 Q2 Zr-95 -2.00E-04 I.OOE-03 4.70E-03 ONS-2 L3476-02 Q2 Ac-h-228 1.26E-03 9.20E-04 3.1OE-03 ONS-2 L3476-02 Q2 Ag-108m -1.40E-04 1.40E-04 6.30E-04 ONS-2 L3476-02 Q2. Ag-lOrm O.OOE+00 2.80E-04 1.20E-03 ONS-2 L3476-02 Q2 Ba-140 O.OOE+00 2.30E-02 1.20E-01 ONS-2 L3476-02 Q2 Be-7 1.22E-01 1.50EM-02 2.80E-02 ONS-2 L3476-02 Q2 Ce-141 -1.30E-03 1.80E-03 7.OOE-03 ONS-2 L3476-02 Q2 Ce-144 -2.60E-03 L.IOE-03 4.SOE-03 ONS-2 L3476-02 Q2 Co-57 3.00E-05 1.20E-04 4.60E-04 ONS-2 L3476-02 Q2 Co-58 5.90E-04 5.60E-04 2.00E-03 ONS-2 L3476-02 Q2 Co-60 2.10E-04 2.60E-04 9.60E-04 ONS-2 L3476-02 Q2 Cr-SI 1.30E-02 2.10E-02 7.60E-02 ONS-2 L3476-02 Q2 Cs-134 2.80E-04 2.80E-04 L.OOE-03 ONS-2 L3476-02 Q2 Cs-137 7.OOE-05 1.90E-04 7.40E-04 ONS-2 L3476-02 Q2 Fe-59 -3.70E-03 3.OOE-03 1.40E-02 ONS-2 L3476-02 Q2 1-131 7.OOE-02 3.70E-01 1.40E+00 ONS-2 L3476-02 Q2 K-40 2.50E-03 3.20E-03 1.20E-02 ONS-2 L3476-02 Q2 La-140 0.OOE+00 2.60E-02 1.40E-0I ONS-2 L3476-02 Q2 Mn-54 -7.OOE-05 2.50E-04 l. 1OE-03 ONS-2 U2476-02 Q2 Nb-95 -1.90E-03 1.30E-03 6.30E-03 ONS-2 L3476-02 Q2 Ru-103 -3.OOE-04 1.OOE-03 4.10E-03 ONS-2 L3476-02 Q2 Ru-106 -2.40E-03 2.20E-03 9.8OE-03 ONS-2 L3476-02 Q2 Sb-124 0.OOE+00 1.50E-03 7.1OE-03 ONS-2 L3476-02 Q2 Sb-125 -7.IOE-04 5.50E-04 2.40E-03 ONS-2 L3476-02 Q2 Se-75 1.12E-03 4.60E-04 1.40E-03 ONS-2 L3476-02 Q2 Zn-65 -2.04E-03 8.20E-04 4.OOE-03 ONS-2 L3476-02 Q2 Zr-95 1.34E-03 9.40E-04 3.10E-03 ONS-3 L3476-03 Q2 AcTh-228 1.46E-03 9.30E-04 2.90E-03 ONS-3 L3476-03 Q2 Ag-108m -5.OOE-05 I.90E-04 7.60E-04 ONS-3 L3476-03 Q2 Ag-110m O.OOE+00 3.30E-04 I .50E-03 ONS-3 L3476-03 Q2 Ba-140 4.80E-02 3.40E-02 6.50E-02 ONS-3 L3476-03 Q2 Be-7 1.23E-01 1.60E-02 2.SOE-02 ONS-3 L3476-03 Q2 Cc-141 1.50E-03 1.90E-03 6.60E-03 ONS-3 L3476-03 Q2 Ce-144 -7.OOE-04 1.1OE-03 4.20E-03 ONS-3 L3476-03 Q2 Co-57 -4.OOE-05 1.20E-04 4.60E-04 ONS-3 L3476-03 Q2 Co-58 .- 9.20E-04 7.00E-04 3.40E-03 ONS-3 L3476-03 Q2 Co-60 4.70E-04 3.OOE-04 9.40E-04 ONS-3 L3476-03 Q2 Cr-51 8.00E-03 2.10E-02 7.80E-02 ONS-3 L3476-03 Q2 Cs-134 -I.IOE-04 1.60E-04 9.20E-04

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-24

Indiana Michigan Power Co., DC Cook Nuclear Plant.

Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m3) (pCi/ m3 ) (pCi/m3 )

ONS-3 L3476-03 Q2 Cs-137 -5.40E-04 2.20E-04 1.20E-03 ONS-3 L3476-03 Q2 Fe-59 -1.90E-03 2.90E-03 1.50E-02 ONS-3 L3476-03 Q2 1-131 3.70E-01 4.60E-01 1.60E+00 ONS-3 L3476-03 Q2 K-40 4.70E-03 4.30E-03 - .50E-02 ONS-3 L3476-03 Q2 La-140 5.50E-02 3.90E-02 7.50E-02 ONS-3 L3476-03 Q2 Mn-54 I.1OE-04 3.20E-04 1.30E-03 ONS-3 L3476-03 Q2 Nb-95 2.50E-03 1.80E-03 6.OOE-03 ONS-3 L3476-03 Q2 Ru-103 -3.50E-04 7.80E-04 3.70E-03 ONS-3 L3476-03 Q2 Ru-106 L.OOE-04 2.80E-03 1.IOE-02 ONS-3 L3476-03 Q2 Sb-124 0.OOE+00 0.00E+00 3.20E-03 ONS-3 L3476-03 Q2 Sb-125 7.80E-04 6.80E-04 2.30E-03 ONS-3 L3476-03 Q2 Se-75 0.00E+00 3.90E-04 1.50E-03 ONS-3 L3476-03 Q2 Zn-65 I.19E-03 7.30E-04 2.20E-03 ONS-3 L3476-03 Q2 Zr-95 -2.00E-04 1.20E-03 5.20E-03 ONS-4 L3476-04 Q2 AcTh-228 -1.17E-03 9.50E-04 4.50E-03 ONS-4 L3476-04 Q2 Ag-108m 2.60E-04 2.40E-04 8.40E-04 ONS-4 L3476-04 Q2 Ag-lOim -6.80E-04 4.OOE-04 2.1OE-03 ONS-4 L3476-04 Q2 Ba-140 6.1OE-02 4.80E-02 1.60E-01 ONS-4 L3476-04 Q2 Be-7 8.50E-02 1.40E-02 2.90E-02 ONS-4 L3476-04 Q2 Ce-141 2.90E-03 2.40E-03 8.OOE-03 ONS-4 L3476-04 Q2 Ce-144 6.00E-04 1.40E-03 4.80E-03 ONS-4 L3476-04 Q2 Co-57 -I.OOE-04 1.60E-04 6.OOE-04 ONS-4 L3476-04 Q2 Co-58 4.20E-04 6.60E-04 2.50E-03 ONS-4 L3476-04 Q2 Co-60 -2.70E-04 2.60E-04 1.30E-03 ONS-4 L3476-04 Q2 Cr-51 3.10E-02 2.50E-02 8.40E-02 ONS-4 L3476-04 Q2 Cs-134 -8.50E-04 3.20E-04 1.70E-03 ONS-4 L3476-04 Q2 Cs-137 -4.90E-04 2.50E-04 1.20E-03 ONS-4 L3476-04 Q2 Fe-59 -1.30E-03 3.00E-03 1.40E-02 ONS-4 L3476-04 Q2 1-131 -5.90E-01 4.20E-01 1.80E+00 ONS-4 L3476-04 Q2 K-40 1.40E-03 4.30E-03 1.70E-02 ONS-4 L3476-04 Q2 La-140 7.1OE-02 5.60E-02 1.90E-01 ONS-4 L3476-04 Q2 Mn-54 -7.80E-04 3.80E-04 1.80E-03 ONS-4 L3476-04 Q2 Nb-95 1.OOE-04 1.60E-03 6.70E-03 ONS-4 L3476-04 Q2 Ru-103 3.00E-04 1.20E-03 4.50E-03 ONS-4 L3476-04 Q2 Ru-106 3.50E-03 2.70E-03 9.20E-03 ONS-4 L3476-04 Q2 Sb-124 2.00E-03 1.40E-03 2.80E-03 ONS-4 L3476-04 Q2 Sb-125 -2.00E-05 7.10E-04 2.70E-03 ONS-4 L3476-04 Q2 Se-75 1.40E-04 4.60E-04 1.70E-03 ONS-4 L3476-04 Q2 Zn-65 -1.09E-03 8.90E-04 4.10E-03 ONS-4 L3476-04 Q2 Zr-95 1.90E-03 1.20E-03 3.60E-03

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-25

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pci/m 3) (pCiI M3 ) (pCi/l 3 )

ONS-5 L3476-05 Q2 AcTh-228 1.40E-03 l.OOE-03 3.30E-03 ONS-5 L3476-05 Q2 Ag-108m 1.40E-04 2.10E-04 7.50E-04 ONS-5 L3476-05 Q2 Ag-1 10m 4.70E-04 3.50E-04 1.20E-03 ONS-5 L3476-05 Q2 Ba-140 O.OOE+00 O.OOE+O0 6.40E-02 ONS-5 L3476-05 Q2 Be-7 1.03E-01 1.50E-02 3.1OE-02 ONS-5 L3476-05 Q2 Ce-141 -4.OOE-04 1.80E-03 6.90E-03 ONS-5 L3476-05 Q2 Ce-144 -5.OOE-04 I.IOE-03 4.OOE-03 ONS-5 L3476-05 Q2 Co-57 -1.50E-04 1.20E-04 4.90E-04 ONS-5 L3476-05 Q2 Co-58 6.60E-04 3.80E-04 6.OOE-04 ONS-5 L3476-05 Q2 Co-60 2.10E-04 3.OOE-04 1.20E-03 ONS-5 L3476-05 Q2 Cr-SI 7.OOE-03 1.70E-02 6.50E-02 ONS-5 L3476-05 Q2 Cs-134 1.20E-04 2.1OE-04 8.50E-04 ONS-5 L3476-05 Q2 Cs-137 3.60E-04 2.OOE-04 5.90E-04 ONS-5 L3476-05 Q2 Fe-59 1.30E-03 2.70E-03 1.20E-02 ONS-5 L3476-05 Q2 1-131 -4.40E-01 3.60E-01 1.60E+00 ONS-S L3476-05 Q2 K-40 -2.80E-03 3.10E-03 1.60E-02 ONS-5 L3476-05 Q2 La-140 O.OOE+00 O.OOE+00 7.40E-02 ONS-5 L3476-05 Q2 Mn-54 O.OOE+00 3.20E-04 1.30E-03 ONS-5 L3476-05 Q2 Nb-95 I.lOE-03 1.50E-03 5.90E-03 ONS-S L3476-05 Q2 Ru-103 3.30E-04 7.30E-04 3.10E-03 ONS-5 L3476-05 Q2 Ru-106 2.40E-03 2.70E-03 9.70E-03 ONS-5 L3476-05 Q2 Sb-124 O.OOE+00 1.60E-03 8.50E-03 ONS-5 L3476-05 Q2 Sb-125 O.OOE+00 5.10E-04 2.10E-03 ONS-5 L3476-05 Q2 Se-75 -8.OOE-05 3.70E-04 1.40E-03 ONS-5 L3476-05 Q2 Zn-65 -6.OOE-04 I.IOE-03 4.60E-03 ONS-5 L3476-05 Q2 Zr-95 -2.OOE-04 L.OOE-03 4.60E-03 ONS-6 L3476-06 Q2 AcTh-228 1.20E-04 8.90E-04 3.50E-03 ONS-6 L3476-06 Q2 Ag-108m -2.50E-0(4 1.70E-04 7.30E-04 ONS-6 L3476-06 Q2 Ag-110m 6.90E-04 4.OOE-04 1.20E-03 ONS-6 L3476-06 Q2 Ba-140 -1.60E-02 2.80E-02 1.50E-OI ONS-6 L3476-06 Q2 Be-7 1.03E-01 1.40E-02 3.10E-02 ONS-6 L3476-06 Q2 Ce-141 -2.60E-03 1.60E-03 6.50E-03 ONS-6 L3476-06 Q2 Ce-i1 5.50E-04 9.60E-04 3.50E-03 ONS-6 L3476-06 Q2 Co-57 3.OOE-05 1.20E-04 4.50E-04 ONS-6 L3476-06 Q2 Co-58 -3.40E-04 5.OOE-04 2.30E-03 ONS-6 U3476-06 Q2 Co-60 5.OOE-05 2.30E-04 9.60E-04 ONS-6 L3476-06 Q2 Cr-SI O.OOE+00 1.80E-02 6.70E-02 ONS-6 L3476-06 Q2 Cs-134 2.50E-04 2.10E-04 7.30E-04 ONS-6 [3476-06 Q2 Cs-137 1.20E-04 2.20E-04 8.1OE-04 ONS-6 [3476-06 Q2 Fe-59 2.80E-03 2.80E-03 I.OOE-02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-26

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m3 ) (pCi/ mI) (pCi/m )

ONS-6 L3476-06 Q2 1-131 -2.90E-01 3.70E-01 1.50E+00 ONS-6 L3476-06 Q2 K-40 7.OOE-04 3.00E-03 1.20E-02 ONS-6 L3476-06 Q2 La-140 -1.80E-02 3.20E-02 1.70E-01 ONS-6 L3476-06 Q2 Mn-54 -2.20E-04 2.70E-04 1.20E-03 ONS-6 L3476-06 Q2 Nb-95 -1I.OOE-03 l.5OE-03 6.60E-03 ONS-6 L3476-06 Q2 Ru-103 -1.04E-03 6.40E-04 3.40E-03 ONS-6 L3476-06 QZ Ru-106 -9.00E-04 2.70E-03 L.IOE-02 ONS-6 L3476-06 Q2 Sb-124 1.50E-03 1.101E-03 2. 1OE-03 ONS-6 L3476-06 Q2 Sb-125 -8.30E-04 5.40E-04 2.40E-03 ONS-6 L3476-06 Q2 Se-75 2.60E-04 4.70E-04 1.60E-03 ONS-6 L3476-06 Q2 Zn-65 '1.23E-03 7.70E-04 3.60E-03 ONS-6 L3476-06 Q2 Zr-95 6.00E-04 1.20E-03 4.50E-03 NBF L3476-07 Q2 AcTh-228 - 1.44E-03 7.20E-04 4. IOE-03 NBF L3476-07 Q2 Ag-108m -5.OOE-05 1.80E-04 7.40E-04 NBF L3476-07 Q2 Ag-110m -4.80E-04 4.20E-04 2.10E-03 NBF L3476-07 Q2 Ba-140 -4.80E-02 3.40E-02 2.20E-01 NBF L3476-07 Q2 Be-7 1.33E-01 1.70E-02 3.20E-02

• NBF L3476-07 Q2 Ce-141 -1.90E-03 1.60E-03 6.70E-03 NBF L3476-07 Q2 Cc-I" -1.95E-03 9.40E(-04 4.20E-03 NBF L3476-07 Q2 Co-57 2.60E-04 1.30E-04 4.IOE-04 NBF L3476-07 Q2 Co-58 5.10E-04 5.30E-04 2.00E-03 NBF L3476-07 Q2 Co-60 -3.00E-05 2.50E-04 1.20E-03 NBF L3476-07 Q2 Cr-51 -2.OOE-02 1.80E-02 7.70E-02 NBF L3476-07 Q2 Cs-134 1.20E-04 2.90E-04 L.IOE-03 NBF L3476-07 Q2 Cs-137 1.00E-04 2.60E-04 1.00E-03 NBF L3476-07 Q2 Fe-59 6.OOE-03 3.OOE-03 4.OOE-03 NBF L3476-07 Q2 1-131 -4.70E-01 2.50E-01 1.30E+00 NBF L3476-07 Q2 K-40 -7.OOE-04 2.70E-03 1.30E-02 NBF L3476-07 Q2 La-140 -5.50E-02 3.90E-02 2.60E-01 NBF L3476-07 Q2 Mn-54 -2.10E-04 2.50E-04 1.20E-03 NBF L3476-07 Q2 Nb-95 1.80E-03 1.50E-03 5.1OE-03 NBF L3476-07 Q2 Ru-103 -2. IOE-03 1.20E-03 5.70E-03 NBF L3476-07 Q2 Ru-106 9.00E-04 2.80E-03 1.LOE-02 NBF L3476-07 Q2 Sb-124 -I.IOE-03 1.IOE-03 8.50E-03 NBF L3476-07 Q2 Sb-125 1.50E-04 5.50E-04 2.20E-03 NBF L3476-07 Q2 Sc-75 -1.60E-04 4.30E-04 1.70E-03 NBF L3476-07 Q2 Zn-65 -5.80E-04 5.80E-04 3.10E-03 NBF L3476-07 Q2 Zr-95 -6.30E-04 9.50E-04 4.70E-03 SBN L3476-08 Q2 AcTh-228 1.20E-03 1.OOE-03 3.60E-03 SBN L3476-08 Q2 Ag-108m 7.00E-05 1.30E-04 5.10E-04

• Radioactivity detected in sample (L.e., concentration > 3 X standard deviation)

D-27

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3) (pCi/ mI) (pCi/m3 )

SBN L3476-08 Q2 Ag-ll0m -5.20E-04 4.50E-04 2.10E-03 SBN L3476-08 Q2 Ba-140 2.00E-02 2.OOE-02 5.50E-02 SBN L3476-08 Q2 Be-7 9.60E-02 1.50E-02 3.00E-02

• SBN L3476-08 Q2 Ce-141 -2.OOE-04 2.20E-03 8.10E-03 SBN L3476-08 Q2 Ce-144 -1.50E-03 1.20E-03 4.80E-03 SBN L3476-08 Q2 Co-57 -1.60E-04 1.70E-04 6.60E-04 SBN L3476-08 Q2 Co-58 -5.90E-04 5.90E-04 2.80E-03 SBN L3476-08 Q2 Co-60 -8.OOE-05 1.70E-04 9.OOE-04 SBN L3476-08 Q2 Cr-51 L.OOE-03 2.OOE-02 7.50E-02 SBN L3476-08 Q2 Cs-134 -2.80E-04 2.20E-04 .LIOE-03 SBN L3476-08 Q2 Cs-137 1.30E-04 1.60E-04 6.20E-04 SBN L3476-08 Q2 Fe-59 1.30E-03 3.80E-03 1.50E-02 SBN L3476-08 Q2 1-131 -1.40E-01 3.40E-01 1.40E+00 SBN L3476-08 Q2 K-40 2.OOE-04 3.20E403 1.40E-02 SBN L3476-08 Q2 La-140 2.30E-02 2.30E-02 6.30E-02' SBN L3476-08 Q2 Mn-54 5.OOE-05 2.90E-04 1.20E-03 SBN L3476-08 Q2 Nb-95 6.OOE-04 2.00E-03 7.80E-03 SBN L3476-08 Q2 Ru-103 -1.20E-03 lIOE-03 4.80E-03 SBN L3476-08 Q2 Ru-106 7.40E-03 2.60E-03 6.20E-03 SBN L3476-08 Q2 Sb-124 -2. IOE-03 1.50E-03 9.50E-03 SBN L3476-08 Q2 Sb-125 6.20E-04 4.60E-04 1.50E-03 SBN L3476-08 Q2 Se-75 -7.OOE-05 4.00E-04 1.50E-03 SBN L3476-08 Q2 Zn-65 -1.28E-03 8.10E-04 3.90E-03 SBN L3476-08 Q2 Zr-95 7.40E-04 9.10E-04 3.40E-03 DOW L3476-09 Q2 AcTh-228 -1.14E-03 7.80E-04 4.10E-03 DOW L3476-09 Q2 Ag-108m -2.70E-04 1.40E-04 7.20E-04 DOW L3476-09 Q2 Ag-lOrm O.OOE+00 4.50E-04 1.90E-03 DOW L3476-09 Q2 Ba-140 -2.40E-02 4.20E-02 2.20E-0I DOW L3476-09 Q2 Be-7 1.08E-01 1.50E-02 2.90E-02

• DOW 12476-09 Q2 Ce-141 1.40E-03 1.70E-03 5.90E-03 DOW L3476-09 Q2 Ce-144 -1.45E-03 8.80E-04 3.80E-03 DOW L3476-09 Q2 Co-57 -9.OOE-05 1.20E-04 4.70E-04 DOW L3476-09 Q2 Co-58 -6.OOE-05 6.90E-04 2.90E-03 DOW L3476-09 Q2 Co-60 I.OOE-04 2.10E-04 9.30E-04 DOW L3476-09 Q2 Cr-51 3.90E-02 2.10E-02 6.60E-02 DOW L3476-09 Q2 Cs-134 1.40E-04 2.50E-04 9.90E-04 DOW L3476-09 Q2 Cs-137 -2.90E-04 2.20E-04 I.OE-03 DOW L3476-09 Q2 Fe-59 3.OOE-03 2.10E-03 4.1OE-03 DOW L3476-09 Q2 1-131 2.70E-01 3.70E-01 1.40E+O0 DOW L3476-09 Q2 K-40 5.10E-03 4.20E-03 1.40E-02

• Radioactivity detected in sample (i.e, concentration > 3 X standard deviation)

D-28

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m3) (pCi/ mI) (pCi/lm)

DOW L3476-09 Q2 La-140 -2.80E-02 4.80E-02 2.60E-01 DOW L3476-09 Q2 Mn-54 3.10E-04 3.40E-04 1.20E-03 DOW L3476-09 Q2 Nb-95 -. OOE-03 1.50E-03 7.10E-03 DOW L3476-09 Q2 Ru-103 -3.00E-04 1.IOE-03 4.70E-03 DOW L3476-09 Q2 Ru-106 9.00E-04 2.80E-03 I.IOE-02 DOW L3476-09 Q2 Sb-124 -3.50E-03 2.00E-03 1.30E-02 DOW L3476-09 Q2 Sb-125 -7.40E-04 6.10E-04 2.70E-03 DOW L3476-09 Q2 Se-75 2.30E-04 3.70E-04 1.40E-03 DOW L3476-09 Q2 Zn-65 -9.OOE-04 1.IOE-03 4.60E-03 DOW L3476-09 Q2 Zr-95 -1.04E-03 8.40E-04 4.60E-03 COL L3476-10 Q2 Acnh-228 -8.OOE-04 1.I1OE-03 4.80E-03 COL L3476-10 Q2 Ag-108m- 1.40E-04 1.70E-04 6.20E-04 COL L3476-10 Q2 Ag-ll0m 1.60E-04 4.80E-04 I.90E-03 COL L3476-10 Q2 Ba-140 4.80E-02 4.80E-02 1.80E-0O COL L3476-10 Q2 Be-7 1.33E-01 1.80E-02 3.50E-02 COL L3476-10 Q2 Ce-141 1.80E-03 I.90E-03 6.60E-03 COL L3476-10 Q2 Cc-144 -1.90E-03 I.OOE-03 4.30E-03 COL L3476-10 Q2 Co-57 1.40E-04 1.40E-04 4.70E-04 COL L3476-10 Q2 Co-58 -2.80E-04 6.60E-04 3.OOE-03 COL L3476-10 Q2 Co-60 9.OOE-05 2.80E-04 1.20E-03 COL L3476-10 Q2 Cr-51 -2.90E-02 2.OOE-02 8.50E-02 COL L3476-10 Q2 Cs-134 4.20E-04 3.30E-04 1.IOE-03 COL L3476-10 Q2 Cs-137 -4.60E-04 2.30E-04 1.20E-03 COL L3476-10 Q2 Fc-59 -3.40E-03 2.40E-03 1.50E-02 COL L3476-10 Q2 1-131 1.90E-0O 4.00E-0I 1.50E+00 COL L3476-10 Q2 K-40 2.OOE-03 2.70E-03 1.1OE-02 COL L3476-10 Q2 La-140 5.50E-02 5.50E-02 2.00E-0O COL L3476-10 Q2 Mn-54 -7.30E-04 3.40E-04 1.70E-03 COL L3476-10 Q2 Nb-95 2.00E-04 1.60E-03 6.60E-03 COL L3476-10 Q2 Ru-103 I.OOE-03 1.IOE-03 4.101E-03 COL L3476-10 Q2 Ru-106 -I.OOE-03 3.30E-03 1.30E-02 COL L3476-10 Q2 Sb-124 -3.40E-03 2.OOE-03 1.20E-02 COL L3476-10 Q2 Sb-125 4.60E-04 6.70E-04 2.40E-03 COL L3476-10 Q2 Se-75 O.OOE+00 4.00E-04 1.50E-03 COL L3476-10 Q2 Zn-65 -3.00E-04 I.IOE-03 4.40E-03 COL L3476-10 Q2 Zr-95 2.00E-04 1.IOE-03 4.70E-03 ONS-1 L4147-01 Q3 AcTh-228 1.20E-04 9.10E-04 3.80E-03 ONS-I L4147-01 Q3 Ag-108m 9.OOE-05 1.70E-04 6.40E-04

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-29

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pci/m3 ) (pCiI m )3 (pci/m3 )

ONS-1 L4147-01 Q3 Ag-l 10m 2.90E-04 3.50E-04 1.30E-03 ONS-1 L4147-01 Q3 Ba-140 -6.80E-03 4.80E-03 3.20E-02 ONS-I L4147-01 Q3 Be-7 1.05E-01 1.20E-02 1.90E-02 ONS-I L4147-01 Q3 Ce-141 -7.90E-04 7.60E-04 3.10E-03 ONS-1 L4147-01 Q3 Cc-144 3.50E-04 8.90E-04 3.30E-03 ONS-I L4147-01 Q3 Co-57 -9.00E-06 9.40E-05 3.70E-04 ONS-I L4147-01 Q3 Co-58 -3.30E-04 4.80E-04 2.20E-03 ONS-I L4147-01 Q3 Co-60 -4.30E-04 3.40E-04 1.70E-03 ONS-I L4147-01 Q3 Cr-51 -1.60E-03 8.OOE-03 3.10E-02 ONS-I UA147-01 Q3 Cs-134 -1.40E-04 2.20E-04 1.10E-03 ONS-I L4147-01 Q3 Cs-137 3.OOE-05 1.80E-04 7.70E-04 ONS-I L4147-01 Q3 Fe-59 2.20E-03 1.60E-03 5.10E-03 ONS-1 L4147-01 Q3 1-131 4.OOE-02 1.60E-02 4.30E-02 ONS-I L4147-01 Q3 K-40 -4.30E-03 3.80E-03 1.90E-02 ONS-I L4147-01 Q3 La-140 -7.90E-03 5.60E-03 3.70E-02 ONS-1 L4147-01 Q3 Mn-54 3.80E-04 3.30E-04 L.IOE-03 ONS-I L4147-01 Q3 Nb-95 -7.50E-04 7.80E-04 3.70E-03 ONS-1 L4147-01 Q3 Ru-103 1.80E-04 3.90E-04 1.60E-03 ONS-1 L4147-01 Q3 Ru-106 -2.80E-03 2.30E-03 1.LOE-02 ONS-1 U4147-01 Q3 Sb-124 7.70E-04 7.70E-04 2. IOE-03 ONS-I L4147-01 Q3 Sb-125 -2.90E-04 5.OOE-04 2.20E-03 ONS-1 L4147-01 Q3 Se-75 -6.OE-05 2.90E-04 L.1OE-03 ONS-I L4147-01 Q3 Zn-65 -1.05E-03 6.50E-04 3.50E-03 ONS-1 L4147-01 Q3 Zr-95 3.50E-04 6.OOE-04 2.40E-03 ONS-2 L4147-02 Q3 AcTh-228 1.56E-03 7.30E-04 2.00E-03 ONS-2 L4147-02 Q3 Ag-108m -4.OOE-05 1.70E-04 6.60E-04 ONS-2 L4147-02 Q3 Ag-1loin O.OOE+00 3.30E-04 1.40E-03 ONS-2 L4147-02 Q3 Ba-140 -1.15E-02 6.10E-03 3.20E-02 ONS-2 L4147-02 Q3 Be-7 1.50E-01 1.20E-02 1.80E-02 ONS-2 L4147-02 Q3 Ce-141 -5.90E-04 7.30E-04 2.90E-03 ONS-2 L4147-02 Q3 Cc-144 -3.80E-04 8.30E-04 3.30E-03 ONS-2 L4147-02 Q3 Co-57 -7.OOE-05 L.IOE-04 4.40E-04 ONS-2 L4147-02 Q3 Co-58 -1.60E-04 3.OOE-04 1.40E-03 ONS-2 L4147-02 Q3 Co-60 -L.OOE-05 2.20E-04 9.40E-04 ONS-2 L4147-02 Q3 Cr-51 -2.70E-03 8.60E-03 3.30E-02 ONS-2 L4147-02 Q3 Cs-134 -4.OOE-05 1.70E-04 7.90E-04 ONS-2 L4147-02 Q3 Cs-137 -1.50E-04 1.50E-04 7.40E-04 ONS-2 L4147-02 Q3 Fe-59 -1.60E-03 1.20E-03 5.90E-03 ONS-2 L4147-02 Q3 1-131 2.60E-02 1.50E-02 4.90E-02 ONS-2 L4147-02 Q3 K-40 2.60E-03 3.20E-03 1.20E-02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-30

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m3 ) (pCi/ mI) (pCi/mr)

ONS-2 L4147-02 Q3 La-140 -1.32E-02 7.00E-03 3.70E-02 ONS-2 L4147-02 Q3 Mn-54 2.10E-04 3.00E-04 1.IOE-03 ONS-2 UA147-02 Q3 Nb-95 -7.80E-04 7.40E-04 3.30E-03 ONS-2 L4147-02 Q3 Ru-103 -2.80E-04 5.50E-04 2.30E-03 ONS-2 L4147-02 Q3 Ru-106 2.20E-03 2.20E-03 7.60E-03 ONS-2 L4147-02 Q3 Sb-124 O.OOE+00 7.30E-04 3.80E-03 ONS-2 L4147-02 Q3 Sb-125 8.10E-04 4.50E-04 1.40E-03 ONS-2 L4147-02 Q3 Se-75 5.00E-05 3.30E-04 1.20E-03 ONS-2 L4147-02 Q3 Zn-65 -1.67E-03 6.70E-04 3.40E-03 ONS-2 L4147-02 Q3 Zr-95 -6.60E-04 6.10E-04 2.90E-03 ONS-3 L4147-03 Q3 Acnh-228 -5.20E-04 7.90E-04 3.80E-03 ONS-3 L4147-03 Q3 Ag-108m -5.00E-05 1.50E-04 6.40E-04 ONS-3 L4147-03 Q3 Ag-1 10m 4.30E-04 4.30E-04 1.60E-03 ONS-3 L4147-03 Q3 Ba-140 -3.40E-03 5.90E-03 3.20E-02 ONS-3 L4147-03 Q3 Be-7 1.34E-01 1.30E-02 1.80E-02 ONS-3 L4147-03 Q3 Ce-141 1.44E-03 8.40E-04 2.70E-03 ONS-3 L4147-03 Q3 Cc-144 -1.22E-03 9.00E-04 3.70E-03 ONS-3 L4147-03 Q3 Co-57 -7.00E-OS 1.20E-04 4.70E-04 ONS-3 UA147-03 Q3 Co-58 4.00E-05 3.00E-04 1.40E-03 ONS-3 1A147-03 Q3 Co-60 3.40E-04 2.70E-04 9.20E-04 ONS-3 UA147-03 Q3 Cr-SI -6.40E-03 7.IOE-03 3.00E-02 ONS-3 L4147-03 Q3 Cs-134 0.OOE+00 O.OOE+00 2.60E-04 ONS-3 UA147-03 Q3 Cs-137 3.40E-04 2.00E-04 6.1OE-04 ONS-3 14147-03 Q3 Fe-59 -I.IOE-03 1.60E-03 7.30E-03 ONS-3 U4147-03 Q3 1-131 8.00E-03 1.80E-02 6.60E-02 ONS-3 UA147-03 Q3 K-40 -1.80E-03 3.40E-03 1.60E-02 ONS-3 UA147-03 Q3 La-140 -3.90E-03 6.80E-03 3.60E-02 ONS-3 L4147-03 Q3 Mn-54 -2.80E-04 2.80E-04 1.30E-01 ONS-3 14147-03 Q3 Nb-95 6.20E-04 9.30E-04 3.50E43 ONS-3 L4147-03 Q3 Ru-103 1.80E-04 5.80E-04 2.30E-03 ONS-3 L4147-03 Q3 Ru-106 -3.40E-03 1.90E-03 1.OOE-02 ONS-3 14147-03 Q3 Sb-124 -8.OOE-04 1.30E-03 7.10E-03 ONS-3 L4147-03 Q3 Sb-125 I.OIE-03 6.60E-04 2.20E-03 ONS-3 14147-03 Q3 Se-75 -3.20E-04 2.90E-04 1.20E-03 ONS-3 147-03 Q3 Zn-65 -5.30E-04 9.10E-04 4.00E-03 ONS-3 14147-03 Q3 Zr-95 -I.1OE-04 7.90E-04 3.40E-03 ONS-4 14147-04 Q3 AcTh-228 5.00E-04 1.30E-03 4.90E-03 ONS-4 14147-04 Q3 Ag-108m 0.OOE+-00 1.80E-04 7.30E-04 ONS-4 14147-04 Q3 Ag-Il0m -1.60E-04 5.30E-04 2.30E-03 ONS-4 14147-04 Q3 Ba-140 3.70E-03 8.30E-03 3.40E-02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-31

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Station LSN Week Nuclide Conc Std. Dev. MDC Media (pci/n 3) (pCi/ M3) (pCi/m3 )

ONS-4 L4147-04 Q3 Be-7 8.70E-02 l.IOE-02 I.90E-02 ONS-4 L4147-04 Q3 Ce-141 -4.20E-04 8.20E-04 3.20E-03 ONS-4 L4147-04 Q3 Ce-14 2.1OE-03 1.20E-03 3.80E-03 ONS-4 L4147-04 Q3 Co-57 5.OOE-05 1.20E-04 4.60E-04 ONS-4 L4147-04 Q3 Co-58 2.OOE-04 2.90E-04 1.20E-03 ONS-4 L4147-04 Q3 Co-60 -1.60E-04 2.40E-04 1.30E-03 ONS-4 L4147-04 Q3 Cr-51 -1.80E-03 8.OOE-03 3.20E-02 ONS-4 L4147-04 Q3 Cs-134 1.20E-04 1.80E-04 7.40E-04 ONS-4 L4147-04 Q3 Cs-137 3.90E-04 2.60E-04 8.40E-04 ONS-4 L4147-04 Q3 Fe-59 1.80E-03 L.IOE-03 1.70E-03 ONS-4 L4147-04 Q3 1-131 O.OOE+00 1.70E-02 6.80E-02 ONS-4 L4147-04 Q3 K-40 -5.00E-04 2.1OE-03 .LIOE-02 ONS-4 L4147-04 Q3 LA-140 4.30E-03 9.50E-03 4.OOE-02 ONS-4 L4147-04 Q3 Mn-54 O.OOE+00 2.IOE-04 9.80E-04 ONS4 LA147-04 Q3 Nb-95 2.00E-04 I.OOE-03 4.1OE-03 ONS-4 L4147-04 Q3 Ru-103 -4.00E-04 7.50E-04 3.20E-03 ONS-4 L4147-04 Q3 Ru-106 -4.90E-03 2.90E-03 1.40E-02 ONS-4 L4147-04 Q3 Sb-124 1.70E-03 1.70E-03 6.10E-03 ONS-4 L4147-04 Q3 Sb-125 -6.60E-04 6.60E-04 2.90E-03 ONS-4 L4147-04 Q3 Se-75 3.60E-04 3.90E-04 1.40E-03 ONS-4 L4147-04 Q3 Zn-65 -5.80E-04 7.1OE-04 3.50E-03 ONS-4 L4147-04 Q3 Zr-95 4.30E-04 7.90E-04 3.1OE-03 ONS-5 L4147-05 Q3 AcTh-228 -7.70E-04 8.90E-04 3.90E-03 ONS-5 L4147-05 Q3 Ag-108m O.OOE+00 1.30E-04 5.30E-04 ONS-5 UA147-05 Q3 Ag-llOm 2.20E-04 4.10E-04 1.50E-03 ONS-5 L4147-05 Q3 Ba-140 4.80E-03 4.80E-03 1.70E-02 ONS-5 L4147-05 Q3 Be-7 1.28E-01 I.1OE-02 1.60E-02 ONS-5 - U147-05 Q3 Ce-141 -7.OOE-05 8.30E-04 3.1OE-03 ONS-5 L4147-05 Q3. Cc-144 -8.1OE-04 9.80E-04 3.90E-03 ONS-5 L4147-05 Q3 Co-57 -5.00E-05 1.20E-04 4.70E-04 ONS-5 L4147-05 Q3 Co-58 -9.OOE-04 4.20E-04 2.1OE-03 ONS-5 L4147-05 Q3 Co-60 4.40E-04 2.30E-04 6.50E-04 ONS-5 L4147-05 Q3 Cr-51 6.80E-03 8.30E-03 2.90E-02 ONS-S L4147-05 Q3 Cs-134 1.40E-04 2.70E-04 I.OOE-03 ONS-5 14147-05 Q3 Cs-137 3.60E-04 2.50E-04 8.40E-04 ONS-5 L4147-05 Q3 Fe-59 O.OOE+00 5.70E-04 3.OOE-03 ONS-S L4147-05 Q3 1-131 3.70E-02 1.80E-02 5.60E-02 ONS-5 L4147-05 Q3 K-40 -3.80E-03 2.90E-03 1.40E-02 ONS-5 L4147-05 Q3 La-140 5.50E-03 5.50E-03 2.OOE-02 ONS-5 L4147-05 Q3 Mn-54 -7.00E-05 2.40E-04 I.OOE-03

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-32

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3 ) (pCi/ m3) (pCi/m 3)

ONS-5 L4147-05 Q3 Nb-95 -3.80E-04 8.20E-04 3.50E-03 ONS-5 LA147-05 Q3 Ru-103 -8.60E-04 6.40E-04 2.80E-03 ONS-5 L4147-05 Q3 Ru-106 -2.50E-03 2.30E-03 1.00-02 ONS-5 14147-05 Q3 Sb-124 -2. 10E-03 1.50E-03 7.50E-03 ONS-5 U4147-05 Q3 Sb-125 -2.40E-04 5.1OE-04 2.10E-03 ONS-5 L4147-05 Q3 Se-75 1.70E-04 2.90E-04 1.00-03 ONS-5 UA147-05 Q3 Zn-65 7.70E-04 7.20E-04 2.50E-03 ONS-5 L4147-05 Q3 Zr-95 1.60E-04 7.00E(-04 2.80E-03 ONS-6 UA147-06 Q3 AcTh-228 7.60E-04 7.90E-04 2.90E-03 ONS-6 UA147-06 Q3 Ag-lO8m -5.50E-04 1.70E-04 8.90E-04 ONS-6 L4147-06 Q3 Ag-l lOm 0.OOE+00 2.902-04 1.30E-03 ONS-6 UA147-06 Q3 Ba-140 0.00+00 O.OOE+00 9.40E-03 ONS-6 UA147-06 Q3 Be-7 1.21E-01 1.202-02 1.30E-02 ONS-6 L4147-06 Q3 Ce-141 -1.06E-03 8.402-04 3.40E-03 ONS-6 L4147-06 Q3 Cc-144 -1.60E-04 8.302-04 3.20E-03 ONS-6 14147-06 Q3 Co-57 -I .OOE-05 1.IOE-04 4.102-04 ONS-6 14147-06 Q3 Co-58 -6.70E-04 3.70E-04 2,10E-03 ONS-6 L4147-06 Q3 Co-60 -1.70E-04 2.502-04 1.302-03 ONS-6 14147-06 Q3 Cr-5 I -9.602-03 7.20E-03 3.10E-02 ONS L4147-06 Q3 Cs-134 1.20E-04 2.10E-04 8.30E-04 ONS-6 14147-06 Q3 Cs-137 2.00E-05 2.102-04 8.90E-04 ONS-6 1A 47-06 Q3 Fe-59 -2.20E-03 1.40E-03 7.302-03 ONS-6 L4147-06 Q3 1-131 2.00E-02 2.10E-02 7.40E,-02 ONS-6 UA147-06 Q3 K-40 7.00E-04 3.502-03 1.50E-02 ONS-6 UA147-06 Q3 La-140 0.00+00 0.002+00 1.1OE-02 ONS-6 L4147-06 Q3 Mn-54 -5.70E-04 2.702-04 1.402-03 ONS-6 14147-06 Q3 Nb-95 1.00-04 L.OOE-03 4.002-03 ONS-6 L4147-06 Q3 Ru-103 1.80E-04 5.302-04 2.10E-03 ONS-6 14147-06 Q3 Ru-106 3.102-03 2.402-03 8.20E-03 ONS-6 14147-06 Q3 Sb-124 -8.00E-04 1.70E-03 8.302-03 ONS-6 L4147-06 Q3 Sb-125 -1.50E-04 5.202-04 2.202-03 ONS-6 14147-06 Q3 Se-75 -5.10E-04 3.70E-04 1.50E-03 ONS-6 UA147-06 Q3 Zn-65 -1.592-03 6.502-04 3.702-03 ONS-6 U4147-06 Q3 Zr-95 2.10E-04 9.202-04 3.702-03 NBF 14147-07 Q3. AcTh-228 -8.80E-04 7.302-04 3.802-03 NBF L4147-07 Q3 Ag-108m 0.00E+00 1.302-04 5.702-04 NBF U1l47-07 Q3 Ag-I lOm -5.90E-04 4.10E-04 2.102-03 NBF 14147-07 Q3 Ba-140 6.90E-03 6.90E-03 2.50E-02 NBF L4147-07 Q3 Be-7 9.40E-02 1.10E-02 1.90E-02 NBF L4147-07 Q3 Ce-141 -4.10E-04 8.50E-04 3.30E-03

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-33

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/mn3 ) (pCil m3 ) (pCi/m3)

NBF LU147-07 Q3 Ce-144 3.90E-04 9.60E-04 3.SOE-03 NBF L4147-07 Q3 Co-57 2.OOE-05 1.20E-04 4.50E-04 NBF L4147-07 Q3 Co-58 -1.OOE-04 3.30E-04 1.60E-03 NBF L4147-07 Q3 Co-60 - I .50E-04 1.50E-04 I .OOE-03 NBF L4147-07 Q3 Cr-51 6.70E-03 6.70E-03 2.40E-02 NBF L4147-07 Q3 Cs-134 -4.OOE-05 2.70E-04 I .20E-03 NBF L4147-07 Q3 Cs-137 3.OOE-05 2.50E-04 l.OOE-03 NBF L4147-07 Q3 Fe-59 1.12E-03 7.90E-04 1.50E-03 NBF L4147-07 Q3 1-131 9.OOE-03 I.90E-02 7.1OE-02 NBF L4147-07 Q3 K-40 9.30E-03 4.80E-03 1.40E-02 NBF L4147-07 Q3 La-140 8.OOE-03 8.OOE-03 2.90E-02 NBF L4147-07 Q3 Mn-54 -1.OOE-04 2.90E-04 1.30E-03 NBF L4147-07 Q3 Nb-95 3.60E-04 6.IOE-04 2.50E-03 NBF L4147-07 Q3 Ru-103 -3.70E-04 6.90E-04 2.90E-03 NBF L4147-07 Q3 Ru-106 -3.20E-03 3.10E-03 1.30E-02 NBF L4147-07 Q3 Sb-124 O.OOE+00 L1.OE-03 5.60E-03 NBF LU147-07 Q3 Sb-125 O.OOE+00 5.20E-04 2. IOE-03 NBF L4147-07 Q3 Se-75 2.70E-04 4.30E-04 1.50E-03 NBF L4147-07 Q3 Zn-65 -8.OOE-04 5.90E-04 3.20E-03 NBF L4147-07 Q3 Zr-95 l.lOE-04 6.70E-04 2.90E-03 SBN L4147-08 Q3 AcTh-228 1.70E-04 7.80E-04 3. 1OE-03 SBN L4147-08 Q3 Ag-108m 1.80E-04 1.30E-04 4.30E-04 SBN L4147-08 Q3 Ag- lOin l.OOE-04 2.70E-04 I. lOE-03 SBN L4147-08 Q3 Ba-140 2.30E-03 6.80E-03 2.70E-02 SBN L4147-08 Q3 Be-7 1.04E-OI I.OOE-02 1.50E-02 SBN L4147-08 Q3 Ce-141 -1.60E-04 7.90E-04 3.OOE-03 SBN L4147-08 Q3 Ce-144 -2.OOE-05 8.80E-04 3.30E-03 SBN L4147-48 Q3 Co-57 -L.OOE-04 1.30E-04 4.90E-04 SBN L4147-08 Q3 Co-58 6.90E-04 3.1OE-04 7.80E-04 SBN L4147-08 Q3 Co-60 2.50E-04 2.50E-04 8.90E-04 SBN L4147-08 Q3 Cr-SI -l.30E-03 7.OOE-03 2.70E-02 SBN L4147408 Q3 Cs-134 2.60E-04 2.50E-04 9.OOE-04 SBN L4147-08 Q3 Cs-137 4.70E-04 2.20E-04 6.50E-04 SBN L4147-08 Q3 Fe-S9 4.OOE-04 .LIOE-03 4.60E-03 SBN L4147-08 Q3 1-131 -2.30E-02 1.80E-02 7.50E-02 SBN L4147-08 Q3 K-40 2.40E-03 2.90E-03 l.lOE-02 SBN L4147-08 Q3 La-140 2.60E-03 7.80E-03 3. 1OE-02 SBN L4147-08 Q3 Mn-54 -3.40E-04 2.20E-04 1.lOE-03 SBN L4147-08 Q3 Nb-95 -5.OOE-05 6.30E-04 2.70E-03 SBN L4147-08 Q3 Ru-103 2.70E-04 5.40E-04 2.OOE-03

• Radioactivity detected In sample (i.e., concentration > 3 X standard deviation)

D-34

Indiana Michigan Power Co., DC Cook Nuclear Plant >

Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pci/m3 ) (pCiI m) (pci/m3 )

SBN L4147-08 Q3 Ru-106 I.1OE-03 2.00E-03 7.40E-03 SBN UA147-08 Q3 Sb-124 O.OOE+00 I.OOE-03 4.70E-03 SBN L4147-08 Q3 Sb-125 2.30E1-04 5.00E-04 1.90E-03 SBN L4147-08 Q3 Se-75 4.70E-04 3.1OE-04 IOOE-03 SBN L4147-08 Q3 Zn-65 -1.09E-03 6.30E-04 3.OOE-03 SBN L4147-08 Q3 Zr-95 -2.30E-04 6.60E-04 2.80E-03 DOW L4147-09 Q3 Aclb-228 -1.70E-03 1.IOE-03 5.30E-03 DOW LA147-09 Q3 Ag-108m -1.00-04 1.60E-04 7.30E-04 DOW 14147-09 Q3 Ag-llOm 3.20E-04 4.50E-04 1.70E-03 DOW L4147-09 Q3 Ba-140 3.80E-03 8.40E-03 3.50E-02 DOW L4147-09 Q3 Be-7 1.18E-01 1.40E-02 2.40E-02 _

DOW L4147-09 Q3 Cc-141 1.1IE-03 9.70E-04 3.302-03 DOW L4147-09 Q3 Ce-144 -7.30E-04 8.80E-04 3.60E-03 DOW L4147-09 Q3 Co-57 3.00E-05 1.40E-04 5.lIOE-04 DOW L4147-09 Q3 Co-58 -4.20E-04 4.20E-04 2.1OE-03 DOW L4147-09 Q3 Co-60 -3.50E-04 3.20E-04 1.70E-03 DOW L4147-09 Q3 Cr-51 0.OOE+00 9.40E-03 3.60E-02 DOW L4147-09 Q3 Cs-134 1.50E-04 2.702-04 1.IOE-03 DOW 14147-09 Q3 Cs-137 1.90E-04 2.90E-04 I.1OE-03 DOW 14147-09 Q3 Fe-59 6.OOE-04 1.60E-03 6.602-03 DOW L4147-09 Q3 1-131 2.30E-02 1.90E-02 6.60E-02 DOW L4147-09 Q3 K-40 -5.00E-04 2.10E-03 1.IOE-02 DOW L4147-09 Q3 La-140 4.304-03 9.70E-03 4.00E-02 DOW 14147-09 Q3 Mn-54 -3.20E-04 1.80E-04 1.102-03 DOW L4147-09 Q3 Nb-95 -4.70E-04 7. 10E-04 3.50E-03 DOW 14147-09 Q3 Ru-103 O.OOE+00 4.00E-04 I.90E-03 DOW L4147-09 Q3 Ru-106 -8.00E-04 2.90E-03 1.20E402 DOW 14147-09 Q3 Sb-124 2.504-03 1.50E-03 2.30E-03 DOW L4147-09 Q3 Sb-25 1.60E-04 6.802-04 2.602-03 DOW L4147-09 Q3 Se-75 2.20E-04 3.602-04 1.30E-03 DOW L4147-09 Q3 Zn-65 -5.80E-04 4. 1OE-04 2.702-03 DOW L4147-09 Q3 Zr-95 3.20E-04 3.202-04 8.50E-04 COL L4147-10 Q3 Aclb-228 -1.47E-03 6.30E-04 3.502-03 COL L4147-10 Q3 Ag-108m -4.00Q-05 1.30E-04 5.60E-04 COL 14147-10 Q3 Ag-I lOm -9.70E-04 3.20E-04 1.80E-03 COL L4147-10 Q3 Ba-140 2.40E-03 5.302-03 2.20E-02 COL L4147-lQ Q3 Be-7 1.134-01 1.IOE-02 1.80E-02 COL L4147-10 Q3 Ce-141 S.20E-04 6.502-04 2.30E-03 COL L4147-10 Q3 Cc-144 -2.90E-04 8.104-04 3.20E-03 COL L4147-10 Q3 Co-57 2.60E-04 9.70E-05 2.70E-04

. Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-35

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m3 ) (pCi/ m3) (pCi/m 3 )

COL L4147-10 Q3 Co-58 7.OOE-05 3.50E-04 1.40E-03 COL L4147-10 Q3 Co-60 -1.30E-04 2.30E-04 l.1OE-03 COL L4147-10 Q3 Cr-SI -1.40E-03 7.40E-03 2.80E-02 COL L4147-10 Q3 Cs-134 1.70E(-04 2.OOE-04 7.30E-04 COL L4147-10 Q3 Cs-137 -L.OOE-04 1.70E-04 7.60E-04 COL L4147-10 Q3 Fe-59 1.20E-03 1.20E-03 4.30E-03 COL L4147-10 Q3 1-131 -3.OOE-03 1.70E-02 6.60E-02 COL L4147-10 Q3 K-40 2.70E-03 3.30E-03 1.20E-02 COL L4147-10 Q3 La-140 2.70E-03 6. 1OE-03 2.50E-02 COL L4147-10 Q3 Mn-54 -1.40E-04 2.OOE-04 9.30E-04 COL L4147-10 Q3 Nb-95 2.70E-04 4.60E-04 1.90E-03 COL L4147-10 Q3 Ru-103 -L.OOE-03 5.IOE-04 2.50E-03 COL L4147-10 Q3 Ru-106 -3.80E-03 2.60E-03 1.1OE-02 COL L4147-10 Q3 Sb-124 5.30E-04 9.10E-04 3.90E-03 COL L4147-10 Q3 Sb-125 -3.60E-04 5.40E-04 2.20E-03 COL UA147-10 Q3 Se-75 -2.20E-04 3.30E-04 1.30E-03 COL L4147-10 Q3 Zn-65 3.80E-04 4.70E-04 1.80E-03 COL L4147-10 Q3 Zr-95 3.20E-04 6.1OE-04 2.40E-03 ONS-1 L4839-01 Q4 AcTh-228 -2.40E-04 8.10E-04 3.20E-03 ONS-1 LA839-01 Q4 Ag-108m -1.90E-04 1.70E-04 6.70E-04 ONS-1 L4839-01 Q4 Ag-il10m 7.20E-04 3.30E-04 9.80E-04 ONS-1 L4839-01 Q4 Ba-140 -1.20E-02 1.20E-02 5.40E-02 ONS-1 L4839-01 Q4 Be-7 7.80E-02 8.90E-03 1.90E4-02 ONS-1 14839-01 Q4 Ce-141 -1.50E-03 1.20E-03 4.30E-03 ONS-1 14839-01 Q4 Ce-144 1.20E-03 1.10E-03 3.80E-03 ONS-1 L4839-01 Q4 Co-57 5.OOE-05 1.40E-04 4.80E-04 ONS-I L4839-01 Q4 Co-58 0.00E+(0 3.40E-04 1.40E-03 ONS-I 14839-01 Q4 Co-60 -1.80E-04 2.20E-04 9.60E-04 ONS-I L4839-01 Q4 Cr-51 -2.60E-03 9.50E-03 3.50E-02 ONS-I 14839-01 Q4 Cs-134 1.60E-04 2.30E-04 8.50E-04 ONS-1 L4839-01 Q4 Cs-137 -2.70E-04 2.20E-04 8.90E-04 ONS-I L483901 Q4 Fe-59 -I.OOE-04 1.10E-03 4.50E-03 ONS-I L4839-01 Q4 1-131 1.80E-02 4.70E-02 1.70E-01 ONS-I L4839-01 Q4 K-40 -3.70E-03 3.1OE-03 1.30E-02 ONS-I L4839-01 Q4 La-140 -1.40E-02 1.40E-02 6.20E-02 ONS-1 14839-01 Q4 Mn-54 6.OOE-05 2.10E-04 8.1OE-04 ONS-I L4839-01 Q4 Nb-95 7.OOE-04 1.20E-03 4.10E-03 ONS-I L4839-01 Q4 Ru-103 -7.1OE-04 7.60E-04 3.OOE-03

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-36

Indiana Michigan Power Co., DC Cook Nuclear Plant -j Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/n 3 ) (pCi/ M3) (pCi/m3 )

ONS-I L4839-01 Q4 Ru-106 -4.80E-03 1.90E- 03 8.70E-03 ONS-1 L4839-01 Q4 Sb-124 -6.OOE-04 1.00E- 03 4.90E-03 ONS-1 L4839-01 Q4 Sb-125 1.OOE-04 5.20E- 04 1.90E-03 ONS-I L4839-01 Q4 Se-75 4.OOE-05 3.60E- 04 1.30E-03 ONS-1 L4839-01 Q4 Zn-65 1.60E-03 1.20E- 03 3.90E-03 ONS-I L4839-01 Q4 Zr-95 -8.40E-04 7.70E- 04. 3.30E-03 ONS-2 LA839-02 Q4 Ac7b-228 9.20E-04 5.50E- 04 1.70E-03 ONS-2 L4839-02 Q4 Ag-108m -1.30E-04 1.20E- 04 5.OOE-04 ONS-2 L4839-02 Q4 Ag-1 10m 0.OOE+00 3.40E- 04 1.30E-03 ONS-2 L4839-02 Q4 Ba-140 -7.90E-03 9.60E- 03 4.70E-02 ONS-2 L4839-02 Q4 Be-7 9.19E-02 9.40E- 03 1.70E-02 ONS-2 L4839-02 Q4 Ce-141 -2.30E-04 8.OOE- 04 2.90E-03 ONS-2 L4839-02 Q4 Ce-i44 4.70E-04 7.20E-04 2.50E-03 ONS-2 L4839-02 Q4 Co-57 4.20E-05 8.70E- 05 3.10E-04 ONS-2 L4839-02 Q4 Co-58 -3.20E-04 2.90E- 04 1.403-03 ONS-2 L4839-02 Q4 Co-60 -5.00E-05 2.50E- 04 l.OOE-03 ONS-2 L4839-02 Q4 Cr-SI -1.51E-02 8.90E- 03 3.60E-02 -. j ONS-2 L4839-02 Q4 Cs-134 -3.OOE-05 1.40E- 04 6.102-04 ONS-2 1.839-02 Q4 Cs-137 1.80E-04 1.60E- 04 5.60E-04 ONS-2 L4839-02 Q4 Fe-59 7.70E-04 9.40E- 04 3.60E-03 ONS-2 L4839-02 Q4 1-131 7.00E-03 3.80E1- 02 1.402-01 ONS-2 L4839-02 Q4 K40 6.00E-03 3.40E- 03 L.IOE-02 ONS-2 L4839-02 Q4 La-140 -9.OOE-03 1.10E- 02 5.40E-02 ONS-2 L4839-02 Q4 Mn-54 -1.70E-04 1.50E- 04 7.20E-04 ONS-2 L4839-02 Q4 Nb-95 1.50E-04 6.70E 04 2.70E-03 ONS-2 L4839-02 Q4 Ru-103 1.30E-04 5.20E- 04 2.OOE-03 ONS-2 1.839-02 Q4 Ru-106 -4.OOE-03 2.30E- 03 9.80E-03 ONS-2 L4839-02 Q4 Sb-124 -1.00-03 1.40E- 03 6.60E-03 ONS-2 L4839-02 Q4 Sb-125 0.OOE+00 4.20E- 04 1.60E-03 ONS-2 L4839-02 Q4 Se-75 7.OOE-04 3.00E- 04 9.30E-04 ONS-2 L4839-02 Q4 Zn-65 -9.30E-04 4.402- 04 2.30E-03 ONS-2 14839-02 Q4 Zr-95 -7.10E-04 6.10E- 04 2.80E-03 ONS-3 L4839-03 Q4 Aclh-228 1.OOE-05 8. 1OE- 04 3.10E-03 ONS-3 L4839-03 Q4 Ag-108m 1.40E-04 1.30E- 04 4.50E-04 ONS-3 L4839-03 Q4 Ag-I1om -8.00E-05 3.OOE- 04 1.204-03 ONS-3 L4839-03 Q4 Ba-140 1.49E-02 9.20E- 03 2.70E-02 ONS-3 14839-03 Q4 Be-7 6.32E-02 8.20E- 03 1.70E-02 ONS-3 L4839-03 Q4 Ce-141 -3.80E-04 7.20E- 04 2.70E-03 ONS-3 14839-03 Q4 Cc-144 5.00E-05 6.70E- 04 2.40E-03 ONS-3 L4839-03 Q4 Co-57 3.30E-05 7.90E 45 2.80E-04

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-37

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pci/m3 ) (pCit mI3 ) (pci/m3 )

ONS-3 L4839-03 Q4 Co-S8 -1.40E-04 2.60E-04 1.20E-03 ONS-3 L4839-03 Q4 Co-60 2.30E-04 2.30E-04 8.30E-04 ONS-3 UA839-03 Q4 Cr-St 3.80E-03 6.50E-03 2.40E-02 ONS-3 L4839-03 Q4 Cs-134 2.20E-04 2.30E-04 8.30E-04 ONS-3 L4839-03 Q4 Cs-137 1.20E-04 1.80E-04 6.50E-04 ONS-3 L4839-03 Q4 Fc-59 4.00E-04 1.20E-03 4.90E-03 ONS-3 L4839-03 Q4 1-131 4.20E-02 3.70E-02 1.30E-01 ONS-3 L4839-03 Q4 K-40 3.30E-03 3.30E-03 1.20E-02 ONS-3 L4839-03 Q4 La-140 I.70E-02 1.IOE-02 3.20E-02 ONS-3 L4839-03 Q4 Mn-54 -S.OOE-05 1.90E-04 8.10E-04 ONS-3 L4839-03 Q4 Nb-95 -3.80E-04 7.20E-04 3.1OE-03 ONS-3 L4839-03 Q4 Ru-103 1.20E 5.40E-04 2.10E-03 ONS-3 L4839-03 Q4 Ru-106 9.00E-04 1.40E-03 5.20E-03 ONS-3 L4839-03 Q4 Sb-124 9.70E-04 6.80E-04 1.30E-03 -.

ONS-3 L4839-03 Q4 Sb-125 -4.90E-04 3.90E-04 1.70E-03 ONS-3 L4839-03 Q4 Se-75 -4.70E-04 2.70E-04 1.10E4-03 ONS-3 L4839-03 Q4 Zn-65 -4.50E-04 4.OOE-04 2.00E-03 ONS-3 L4839-03 Q4 Zr-95 4.30E-04 4.90E-04 1.80E-03 ONS-4 L4839-04 Q4 AcTh-228 4.20E-04 4.70E-04 1.70E-03 ONS-4 L4839-04 Q4 Ag-108m -4.00E-05 I.10.E-04 4.30E-04 ONS-4 L4839-04 Q4 Ag-1 10m 1.20E-04 2.80E-04 I .OOE-03 ONS-4 L4839-04 Q4 Ba-140 5.OOE-03 5.OOE-03 1.80E-02 ONS-4 L4839-04 Q4 Be-7 8.07E-02 8.20E-03 1.80E-02 ONS-4 L4839-04 Q4 Cc-141 1.12E-03 7.30E-04 2.40E-03 ONS-4 L4839-04 Q4 Ce-144 1.06E-03 7.20E-04 2.40E-03 ONS-4 L4839-04 Q4 Co-57 -1.03E-04 8.30E-05 3.20E-04 ONS4 L4839-04 Q4 Co-58 1.60E-04 3.1OE-04 1.101E-03 ONS4 L4839-04 Q4 Co-60 1.501E-04 1.90E-04 6.80E-04 ONS4 L4839-04 Q4 Cr-51 -2.00E-03 7.30E-03 2.70E-02 ONS4 L4839-04 Q4 Cs-134 7.OOE-0S 1.30E-04 4.90E-04 ONS-4 L4839-04 Q4 Cs-137 -2.OOE-04 1.70E-04 7.00E-04 ONS-4 L4839-04 Q4 Fe-59 -2.60E-04 6.90E-04 3. IOE-03 ONS-4 L4839-04 Q4 1-131 1.60E-02 3.50E-02 1.30E-01 ONS-4 L4839-04 Q4 K40 7.00E-04 2.101E-03 8.1 OE-03 ONS4 L4839-04 Q4 La-140 5.80E-03 5.80E-03 2.103E-02 ONS-4 L4839-04 Q4 Mn-54 -4.OOE-05 1.90E-04 7.50E-04 ONS-4 L4839-04 Q4 Nb-95 -5.00E-05 6.90E-04 2.70E-03 ONS-4 L4839-04 Q4 Ru-103 -4.70E-04 4.30E-04 1.80E-03 ONS-4 L4839-04 Q4 Ru-106 -1.20E-03 1.50E-03. 6.101E-03 ONS-4 L4839-04 Q4 Sb-124 3.20E-04 8.50E-04 3.50E-03

• Radioactivity detected in sample (Le., concentration > 3 X standard deviation)

D-38

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3) (pCil i) (pCi/m3)

ONS-4 LA839-04 Q4 Sb-125 -6.00E-05 3.40E-04 1.30E-03 ONS4 L4839-04 Q4 Se-75 -3.20E-04 2.20E-04 8.80E-04 ONS4 LA839-04 Q4 Zn-6S -2.1OE-04 4.20E-04 1.70E-03 ONS-4 LA839-04 Q4 Zr-95 2.00E-05 5.OOE-04 2.OOE-03 ONS-5 U4839-05 Q4 AcTh-228 -9.90E-04 9.20E-04 3.70E-03 ONS-5 LA839-05 Q4 Ag-108m -2.OOE-05 1.60E-04 5.80E-04 ONS-5 L4839-05 Q4 Ag-ll0m -6.OOE-04 4.00E-04 1.70E-03 ONS-5 L4839-05 Q4 Ba-140 2.30E-02 1.30E-02 3.90E-02 ONS-S L4839-05 Q4 Be-7 7.59E-02 8.60E-03 1.70E-02 ONS-5 L4839-05 Q4 Ce-141 8.OOE-04 1.lOE-03 3.80E-03 ONS-5 L4839-05 Q4 Cc-144 -2.20E-03 1.IOE-03 4.30E-03 ONS-5 L4839-05 Q4 Co-57 1.60E-04 1.40E-04 4.70E-04 ONS-5 LA839-05 Q4 Co-58 -6.40E-04 4.60E-04 2.OOE-03 ONS-5 L4839-05 Q4 Co-60 -2.40E-04 2.IOE-04 9.60E-04 ONS-5 L4839-05 Q4 Cr-51 -1.80E-02 l.OOE-02 4.OOE-02 ONS-5 UA839-05 Q4 Cs-134 -1.40E-04 2.10E-04 8.90E-04 ONS-S LA839-05 Q4 Cs-137 -4.OOE-05 2.20E-04 8.50E-04 ONS-5 L4839-05 Q4 Fe-S9 -1.166E-03 8.90E-04 4.50E-03 ONS-5 UA839-05 Q4 1-131 2.1OE-02 4.50E-02 1.60E-O1 ONS-5 U4839-05 Q4 K-40 -1.70E-03 3.1OE-03 1.20E-02 ONS-S LA839-05 Q4 La-140 2.60E-02 1.40E-02 4.40E-02 ONS-S LA839-05 Q4 Mn-54 1.40E-04 2.50E-04 9.OOE-04 ONS-5 L4839-05 Q4 Nb-95 8.OOE-04 I.IOE-03 3.80E-03 ONS-5 L4839-05 Q4 Ru-103 4.70E-04 7.30E-04 2.60E-03 ONS-S LA839-05 Q4 Ru-106 2.60E-03 1.90E-03 6.20E-03 ONS-S LA839-05 Q4 Sb-124 -2.OOE-04 1.30E-03 5.SOE-03 ONS-S L4839-05 Q4 Sb-125 5.20E-04 5.OOE-04 1.70E-03 ONS-5 LA839-05 Q4 Se-75 2.20E-04 3.80E-04 1.30E-03 ONS-5 L4839-05 Q4 Zn-65 -3.00E-04 1.20E-03 4.30E-03 ONS-S L4839-05 Q4 Zr-95 1.1 8E-03 7.70E-04 2.50E-03 ONS-6 LA839-06 - Q4 AcTh-228 -1.20E-03 6.80E-04 3.20E-03 ONS-6 L4839-06 Q4 Ag-108m -1.50E-04 1.IOE-04 4.90E-04 ONS-6 LA839-06 Q4 Ag-1 10m -3.30E-04 3.30E-04 1.40E-03 ONS-6 L4839-06 Q4 Ba-140 7.60E-03 9.30E-03 3.50E-02 ONS-6 L4839-06 Q4 Be-7 7.67E-02 8.50E-03 1.60E-02, ONS-6 L4839-06 Q4 Ce-141 1.46E-03 7.50E-04 2.40E-03 ONS-6 L4839-06 Q4 Ce-144 -1.28E-03 7.40E-04 2.90E-03 ONS-6 L4839-06 Q4 Co-57 5.OOE-05 7.70E-05 2.70E-04 ONS-6 UA839-06 Q4 Co-58 2.70E-04 3.50E-04 1.30E-03 ONS-6 UA839-06 Q4 Co-60 L.IOE-04 1.90E-04 7.50E-04

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-39

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCilm3 ) (pCi/ m3) (pCi/m 3)

ONS-6 L4839-06 Q4 Cr-51 1.20E-03 8.OOE-03 2.90E-02 ONS-6 L4839-06 Q4 Cs-134 -S.OOE-05 2.OOE-04 8.20E-04 ONS-6 L4839-06 Q4 Cs-137 -1.00E-04 1.70E-04 7.20E-04 ONS-6 L4839-06 Q4 Fe-59 -4.00E-04 l.1OE-03 4.90E-03 ONS-6 L4839-06 Q4 1-131 -2.70E-02 4.10E-02 1.60E-01 ONS-6 L4839-06 Q4 K-40 4.20E-03 2.80E-03 8.90E-03 ONS-6 L4839-06 Q4 La-140 9.00E-03 L.1OE-02 4.10E-02 ONS-6 L4839-06 Q4 Mn-54 -1.60E-04 1.90E-04 8.50E-04 ONS-6 L4839-06 Q4 Nb-95 7.70E-04 7.80E-04 2.80E-03 ONS-6 L4839-06 Q4 Ru-103 -3.70E-04 5.OOE-04 2.10E-03 ONS-6 L4839-06 Q4 Ru-106 -1.00-04 1.60E-03 6.50E-03 ONS-6 L4839-06 Q4 Sb-124 5.OOE-04 1.50E-03 5.90E-03 ONS-6 L4839-06 Q4 Sb-125 -1.60E-04 4.20E-04 1.70E-03 ONS-6 L4839-06 Q4 Se-75 3.70E-04 2.60E-04 8.80E-04 ONS-6 L4839-06 Q4 Zn-65 47.50E-04 5.80E-04 2.60E-03 ONS-6 L4839-06 Q4 Zr-95 1.60E-04 6.30E-04 2.50E-03 NBF U4839-07 Q4 Aclh-228 3.70E-04 6.50E.04 2.50E-03 NBF L4839-07 Q4 Ag-108m 1.50E-04 1.30E-04 4.40E-04 NBF L4839-07 Q4 Ag-l 10m 3.40E-04 3.40E-04 1.20E-03 NBF LA839-07 Q4 Ba-140 -1.16E-02 8.70E-03 4.70E-02 NBF LU839-07 Q4 Be-7 8.622-02 9.00E-03 1.60E-02 NBF L4839-07 Q4 Ce-141 -8.80E-04 8.30E-04 3.20E-03 NBF UA839-07 Q4 Ce-144 -9.10E-04 6.80E-04 2.70E-03 NBF L4839-07 Q4 Co-57 6.30E-05 9.30E-05 3.30E-04 NBF L4839-07 Q4 Co-58 1.80E-04 3.50E-04 1.30E-03 NBF L4839-07 Q4 Co-60 -6.00E-05 2.60E-04 1.IOE-03 NBF LA839-07 Q4 Cr-51 3.90E-03 8. IOE-03 2.90E-02 NBF LA839-07 Q4 Cs-134 1.00E-04 1.90E-04 7.20E-04 NBF 1A839-07 Q4 Cs-137 0.00E+00 2.30E-04 8.90E-04 NBF L4839-07 Q4 Fe-59 4.00E-04 1.00E-03 4.102-03 NBF 14839-07 Q4 1-131 -3.60E-02 4.40E-02 1.70E-01 NBF L4839-07 Q4 K-40 1.00E-04 2.50E-03 1.00E-02 NBF 14839-07 Q4 La-140 -1.30E-02 1.00E-02 5.40E-02 NBF U4839-07 Q4 Mn-54 -6.00E-05 2.10E-04 8.70E-04 NBF U4839-07 Q4 Nb-95 -7.00E-04 8.80E-04 3.70E-03 NBF LA839-07 Q4 Ru-103 -3.80E-04 6.70E-04 2.70E-03 NBF LA839-07 Q4 Ru-106 -7.00E-04 2.00E-03 7.80E-03 NBF L4839-07 Q4 Sb-124 -5.00E-04 1.30E-03 5.90E-03 NBP L4839-07 Q4 Sb-125 0.00+E00 4.60E-04 1.70E-03 NBF UA839-07 Q4 Se-75 8.00E-05 2.60E-04 9.60E-04

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-40

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m3) (pCi/ m3 ) (pCi/m3 )

NBF L4839-07 Q4 Zn-65 -6.10E-04 5.70E-04 2.60E-03 NBF UA839-07 Q4 Zr-95 -2.OOE-05 6.20E-04 2.60E-03 SBN L4839-08 Q4 AcTh-228 1.82E-03 6.40E-04 1.70E-03 SBN L4839-08 Q4 Ag-108m 1.79E-04 9.60E-05 3.OOE-04 SBN L4839-08 Q4 Ag-l lOm 1.20E-04 2.50E-04 9.50E-04

- SBN L4839-08 Q4 Ba-140 2.60E-03 5.80E-03 2.40E-02 SBN L4839-08 Q4 Be-7 9.61E-02 8.40E-03 1.50E-02 SBN L4839-08 Q4 Ce-141 3. 1OE-04 8.20E-04 2.90E-03 SBN L4839-08 Q4 Ce-144 5.50E-04 6.40E-04 2.20E-03 SBN L4839-08 Q4 Co-57 -9.OOE-06 8.20E-05 3.OOE-04 SBN L4839-08 Q4 Co-58 -1.1OE-04 3.10E-04 1.20E-03 SBN L4839-08 Q4 Co-60 -2.30E-04 1.80E-04 8.10E-04 SBN L4839-08 Q4 Cr-51 I.72E-02 6.90E-03 2.1OE-02 SBN L4839-08 Q4 Cs-134 -6.00E-05 1.60E-04 6.50E-04 SBN L4839-08 Q4 Cs-137 1.OOE-04 1.70E-04 5.90E-04 SBN LU839-08 Q4 Fe-59 2.60E-04 9.50E-04 3.70E-03 SBN L4839-08 Q4 1-131 5.60E-02 3.50E-02 1.20E10 SBN L4839-08 Q4 K-40 2.60E-03 2.20E-03 7.40E-03 SBN L4839-08 Q4 La-140 3.OOE-03 6.60E-03 2.80E-02 SBN L4839-08 Q4 Mn-54 -2.00E-04 2.20E-04 9.OOE-04 SBN L4839-08 Q4 Nb-95 -2.20E-04 6.60E-04 2.60E-03 SBN LA839-08 Q4 Ru-103 -5.70E-04 5.20E-04 2. IOE-03 SBN L4839-08 Q4 Ru-106 -2.50E-03 1.50E-03 6.60E-03 SBN L4839-08 Q4 Sb-124 3.30E-04 9.80E-04 3.90E-03 SBN L4839-08 Q4 Sb-125 I.90E-04 3.20E-04 1.20E-03 SBN L4839-08 Q4 Se-75 -4.00E-05 2.40E-04 8.80E-04 SBN L4839-08 Q4 Zn-65 3.20E-04 4.40E-04 1.60E-03 SBN L4839-08 Q4 Zr-95 -1.30E-04 4.60E-04 1.90E-03 DOW L4839-09 Q4 AcTh-228 I.OIE-03 7.40E-04 2.50E-03 DOW L4839-09 Q4 Ag-108m -6.00E-05 1.40E-04 5.50E-04 DOW L4839-09 Q4 Ag-lOim -3.30E-04 3.40E-04 1.40E-03 DOW L4839-09 Q4 Ba-140 2.00E-03 I.IOE-02 4.40E-02 DOW L4839-09 Q4 Be-7 6.58E-02 8.OOE-03 1.60E-02 DOW L4839-09 Q4 Ce-141 2.101E-03 I.1OE-03 3.60E-03 DOW L4839-09 Q4 Ce-144 -I.80E-04 9.60E-04 3.50E-03 DOW L4839-09 Q4 Co-57 8.OOE-05 1.20E-04 4.20E-04 DOW L4839-09 Q4 Co-58 O.OOE+0O 4.20E-04 1.60E-03 DOW L4839-09 Q4 Co-60 -I .90E-04 I.90E-04 8.90E-04 DOW L4839-09 Q4 Cr-51 I .OOE-03 8.60E-03 3.1OE-02 DOW L4839-09 Q4 Cs-134 6.00E-05 I.90E-04 7.30E-04

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-41

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m3) (pCi/ in') (pCi/rn)

DOW L4839-09 Q4 Cs-137 4.00E-05 1.90E-04 7.10E-04 DOW L4839-09 Q4 Fe-59 2.00E-04 1.20E-03 4.90E-03 DOW L4839-09 Q4 1-131 -8.101E-02 4.60E-02 1.90E-0l DOW L4839-09 Q4 K-4o 2.10E-03 3.20E-03 1.20E-02 DOW L4839-09 Q4 La-140 2.00E-03 1.20E-02 5.00E-02 DOW L4839-09 Q4 Mn-54 -4.00E-04 2.70E-04 1.10E-03 DOW L4839-09 Q4 Nb-95 -5.70E-04 9.10E-04 3.70E-03 DOW LA839-09 Q4 Ru-103 -1.20E-04 6.20E-04 2.40E-03 DOW L4839-09 Q4 Ru-106 -I.IOE-03 2.00E-03 8.00E-03 DOW L4839-09 Q4 Sb-124 -4.OOE-05 6.50E-04 3.40E-03 DOW L4839-09 Q4 Sb-125 1.80E-04 4.50E-04 1.60E-03 DOW L4839-09 Q4 Se-75 -I.OOE-04 3.40E-04 1.30E-03 DOW L4839-09 Q4 Zn-65 -8.90E-04 6.30E-4" 2.80E-03 DOW L4839-09 Q4 Zr-95 3.40E-04 8.00E-04 3.00E-03 -

COL L4839-10 Q4 AcTh-228 2.OOE-04 8.30E-04 3.20E-03 COL L4839-10 Q4 Ag-108m -8.00E-05 1.I1OE-04 4.50E-04 COL L4839-10 Q4 Ag-1 10m 4.20E-04 2.80E-04 9.1OE-04 COL L4839-10 Q4 Ba-140 0.00E+00 9.70E-03 4.30E-02 COL L4839-10 Q4 Be-7 8.67E-02 8.60E-03 1.30E-02 COL LA839-10 Q4 Cc-141 2.00E-04 7.30E-04 2.60E-03 COL L4839-10 Q4 Ce-144 -9.20E-04 7.00E-04 2.80E-03 COL L4839-10 Q4 Co-57 6.50E-05 8.90E-05 3.10E-04 COL L4839-10 Q4 Co-58 -3.00E-05 3.10E-04 1.30E-03 COL L4839-10 Q4 Co-60 3.30E-04 1.80E-04 5.20E-04 COL L4839-10 Q4 Cr-51 -2.50E-03 6.40E-03 2.504-02 COL L4839-10 Q4 Cs-134 2.00E-05 1.30E-04 5.50E-04 COL L4839-10 Q4 Cs-137 4.00E-05 1.80E-04 7.00E-04 COL L4839-10 Q4 Fe-59 -8.00E-04 1.20E-03 5.40E-03 COL L4839-10 Q4 1-131 -2.80E-02 3.70E-02 1.50E-01 COL L4839-10 Q4 K-40 4.30E-03 2.70E-03 8.40E-03 COL L4839-10 Q4 La-140 0.OOE+00 1.10E-02 4.904-02 COL L4839-10 Q4 Mn-54 2.20E-04 1.90E-04 6.60E-04 COL L4839-10 Q4 Nb-95 1.80E-04 7.30E-04 2.90E-03 COL L4839-10 Q4 Ru-103 5.1OE-04 5.60E 2.OOE-03 COL L4839-10 Q4 Ru-106 1.20E-03 1.70E-03 6.30E-03 COL L4839-l0 Q4 Sb-124 0.00E+00 1.00E-03 4.70E-03 COL L4839-10 Q4 Sb-125 5.80E-04 3.60E-04 1.20E-03 COL L4839-10 Q4 Se-75 -3.101E-04 2.20E-04 9.10E-04 COL L4839-10 Q4 Zn-65 -3.101E-04 5.80E-04 2.50E-03 COL L4839-10 Q4 Zr-95 -1.20E-04 3.80E-04 1.804-03

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-42

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3) (pCil m3 ) (pCi/m 3)

CF ONS-1 L4599-01 01 1-131 1.70E-03 8.10E-03 3.1OE-02 ONS-2 L4599-02 01 1-131 0.OOE+00 6.10E-03 2.40E-02 ONS-3 L4599-03 01 1-131 8.80E-03 7.20E-03 2.40E-02 ONS-4 L4599-04 01 1-131 3.30E-03 6.60E-03 2.50E-02 ONS-5 UA599-05 01 1-131 0.00E+00 6.90E-03 2.70E-02 ONS-6 L4599-06 01 1-131 6.70E-03 8.50E-03 3.OOE-02 NBF L4599-07 01 1-131 5.30E-03 8.40E-03 3.1OE-02 SBN LA599-08 01 1-131 7.20E-03 8.50E-03 3.OOE-02 DOW L4599-09 01 1-131 2.00E-02 1.OOE-02 3.1OE-02 COL L4599-10 01 1-131 1.80E-03 9.30E-03 3.50E-02 ONS-1 L2055-01 02 1-131 -6.00E-03 I.J0E-02 4.90E-02 ONS-2 L2055-02 02 1-131 -9.30E-03 8.50E-03 3.40E-02 ONS-3 L2055-03 02 1-131 -4.OOE-03 9.101E-03 3.40E-02 ONS4 L2055-04 02 1-131 -1.70E-02 9.50E-03 3.80E-02 ONS-5 L2055-05 02 1-131 1.30E-03 9.70E-03 3.50E-02 ONS-6 L2055-06 02 1-131 2.60E-03 9.10E-03 3.30E-02 NBF L2055-07 02 1-131 1.40E-03 9.40E-03 3.40E-02 SBN L2055-08 02 1-131 7.OOE-03 1.00E-02 3.60E-02 DOW L2055-09 02 1-131 -8.30E-03 9.60E-03 3.70E-02 COL L2055-10 02 1-131 -1.63E-02 9.40E-03 3.80E-02 ONS-I L2083-01 03 1-131 1.30E-03 9.OOE-03 3.30E-02 ONS-2 L2083-02 03 1-131 1.30E-03 9.20E-03 3.30E-02 ONS-3 L2083-03 03 1-131 -2.60E-03 8.70E-03 3.30E-02 ONS-4 L2083-04 03 1-131 0.OOE+00 7.90E-03 3.OOE-02 ONS-5 L2083-05 03 1-131 -1.04E-02 9.50E-03 3.70E-02 ONS-6 L2083-06 03 1-131 -5.20E-03 8.60E-03 3.30E-02 NBF L2083-07 03 1-131 1.30E-03 7.60E-03 2.80E-02 SBN L2083-08 03 1-131 -1.40E-03 8.90E-03 3.30E-02 DOW L2083-09 03 1-131 0.00E+00 8.80E-03 3.30E-02 COL L2083-10 03 1-131 -1.30E-03 8.10E-03 3.00E-02 ONS-1 L2118-01 04 1-131 -3.60E-03 7.50E-03 2.90E-02 ONS-2 L2118-02 04 1-131 -3.60E-03 7.1OE-03 2.80E-02 ONS-3 L2118-03 04 1-131 -4.80E-03 7.50E-03 2.90E-02 ONS-4 L2118-04 04 1-131 -6.00E-03 8.30E-03 3.20E-02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-43

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev.. MDC (pCi/m3 ) (pCi/ m3) (pCilr 3 )

ONS-5 L2118-05 04 1-131 O.OOE+00 7.70E-03 2.90E-02 --

ONS-6 L2118-06 04 1-131 4.70E-03 7.90E-03 2.80E-02 NBF L2118-07 04 1-131 -1.20E-03 7.50E-03 2.80E-02 SBN L2118-08 04 1-131 -1.20E-03 7.80E-03 2.90E-02 DOW L2118-09 04 1-131 3.80E-03 8.10E-03 2.90E-02 COL L2118-10 04 1-131 4.90E-03 6.30E-03 2.20E-02 ONS-I L2160-01 05 1-131 -1.50E-02 1.20E-02 4.70E-02 ONS-2 L2160-02 05 1-131 1.39E-02 9.80E-03 3.30E-02 ONS-3 L2160-03 05 1-131 -5.60E-03 9.1OE-03 3.50E-02 -

ONS-4 L2160-04 05 1-131 -2.80E-03 7.70E-03 3.OOE-02 ONS-5 L2160-05 05 1-131 4.OE-03 8.90E-03 3.20E-02 ONS-6 L2160-06 05 1-131 1.40E-03 8.40E-03 3.10E-02 NBF L2160-07 05 1-131 1.OOE-03 1.OOE-02 3.70E-02 SBN L2160-08 05 1-131 1.54E-02 9.20E-03 3.00E-02 DOW L2160-09 05 1-131 -1.50E-03 8.10E-03 3. 10E-02 COL L2160-10 05 1-131 -1. 16E-02 9.60E-03 3.80E-02 ONS-1 L2184-01 06 1-131 -1.20E-03 7.80E-1D3 2.90E-02 ONS-2 L2184-02 06 1-131 9.70E-03 8.90E-(33 3.00E-02 ONS-3 L2184-03 06 1-131 1.20E-03 8.00E4 D3 2.90E-02 ONS-4 L2184-04 06 1-131 1.20E-03 7.00-4 33 2.60E-02 ONS-5 12184-05 06 1-131 -9.70E-03 7.301-4 33 3.00E-02 -

ONS-6 L2184-06 06 1-131 4.90E-03 8.40E-( 33 3.00E-02 NBF L2184-07 06 1-131 -1.67E-02 7.30E-(33 3.10E-02 SBN L2184-08 06 1-131 7.70E-03 7.20E-(33 2.50E-02 DOW L2184 06 1-131 7.60E-03 6.90E-4 2.40E-02 COL L2184-10 06 1-131 6.20E-03 8.20E4 2.90E-02 ONS-1 L2224-01 07 1-131 1.OIE-02 5.40E-( 1.70E-02 ONS-2 L2224-02 07 1-131 9.00E-04 6.00E-t 2.20E-02 ONS-3 L2224-03 07 1-131 -1.55E-02 5.50E-( 33 2.40E-02 ONS-4 L2224-04 07 1-131 -3.70E-03 5.40E4 2.10E-02 ONS-5 L2224-05 07 1-131 O.OOE+00 5.90E-t 2.20E-02 ONS-6 L2224-06 07 1-131 7.30E-03 5.90E-( 2.00E-02 NBF L2224-07 07 1-131 -9.OOE-04 6.1OE4 33 2.30E-02 SBN L2224-08 07 1-131 0.OOE+00 4.901-4 1.90E-02 DOW L2224-09 07 1-131 -3.802-03 6.20E4 2A40E-02 33 COL L2224-10 07 1-131 6.60E-03 5.90E4 2.00E-02

• Radioactivity detected in sample (i.e, concentration > 3 X standard deviation)

D-44

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/n 3 ) (pCi/ m3) (pCi/m 3)

ONS-I L2258-01 08 1-131 O.OOE+00 5.80E-03 2.20E-02 ONS-2 L2258-02 08 1-131 4.70E-03 6.30E-03 2.20E-02 ONS-3 L2258-03 08 1-131 1.13E-02 5.70E-03 1.80E-02 ONS-4 L2258-04 08 1-131 2.80E-03 4.90E-03 1.80E-02 ONS-5 L2258-05 08 1-131 2.80E-03 5.50E-03 2.00E-02 ONS-6 L2258-06 08 1-131 2.90E-03 5.30E-03 1.90E-02 NBF L2258-07 08 1-131 -3.80E-03 6.20E-03 2.40E-02 SBN L2258-08 08 1-131 O.OOE+00 6.30E-03 2.30E-02 DOW L2258-09 08 1-131 l.OOE-02 5.30E-03 1.70E-02 COL L2258-10 08 1-131 -7.80E-03 6.10E-03 2.50E-02 ONS-1 L2320-01 09 1-131 -6.OOE-03 1I.OE-02 4.10E-02 ONS-2 L2320-02 09 1-131 -1.50E-03 9.IOE-03 3.40E-02 ONS-3 L2320-03 09 1-131 -1.52E-02 9.40E-03 3.90E-02 ONS4 L2320-04 09 1-131 -3.1OE-03 9.70E-03 3.70E-02 ONS-5 L2320-05 09 1-131 -4.60E-03 9.10E-03 3.50E-02 ONS-6 L2320-06 09 1-131 -1.99E-02 9.30E-03 4.OOE-02 NBF L2320-07 09 1-131 O.OOE+00 8.40E-03 3.20E-02 SBN L2320-08 09 1-131 O.OOE+00 I.1IOE-02 4.00E-02 DOW L2320-09 09 1-131 -1.45E-02 9.50E-03 3.90E-02 COL L2320-10 09 1-131 4.80E-03 7.60E-03 2.80E-02 ONS-1 L2364-01 10 1-131 1.20E-03 7.30E-03 2.70E-02 ONS-2 L2364-02 10 1-131 0.OOE+00 6.70E-03 2.60E-02 ONS-3 L2364-03 10 1-131 6.10E-03 7.40E-03 2.60E-02 ONS-4 L2364-04 10 1-131

• 3.70E-03 6.60E-03 2.40E-02 ONS-5 L2364-05 10 1-131 -3.70E-03 7.20E-03 2.80E-02 ONS-6 L2364-06 10 1-131 -2.50E-03 6.50E-03 2.50E-02 NBF L2364-07 10 1-131 1.12E-02 7.60E-03 2.50E-02 SBN L2364-08 10 1-131 -6.40E-03 7.60E-03 3.00E-02 DOW L2364-09 10 1-131 -1.27E-02 7.60E-03 3.20E-02 COL L2364-10 10 1-131 -1.65E-02 7.SOE-03 3.20E-02 ONS-I L2400-01 11 1-131 -7.10E-03 6.90E&03 2.80E-02 ONS-2 L2400-02 11 1-131 3.50E-03 7.00E 03 2.50E-02 ONS-3 L2400-03 11 1-131 0.OOE+00 6.00E 03 2.30E-02 ONS-4 L2400-04 11 1-131 4.80E-03 6.70E-I03 2.40E-02

• Radioactivity detected In sample (i.e., concentration > 3 X standard deviation)

D-45

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (Pci/rn3 ) (pCi/ m3 ) (pCi/m3 )

ONS-5 L2400-05 11 1-131 L.20E-03 7.40E-03 2.70E-02 ONS-6 L2400-06 11 1-131 7.20E-03 6.40E-03 2.20E-02 NBF L2400-07 11 1-131 -1.09E-02 7.60E-03 3.10E-02 SBN L2400-08 11 1-131 7.40E-03 6.80E-03 2.30E-02 DOW L2400-09 11 1-131 3.70E-03 6.60E-03 2.40E-02 COL L2400-10 11 1-131 -9.80E-03 7.30E-03 3.00E-02 ONS-I L2448-01 12 1-131 -3.50E-03 7.10E-03 2.70E-02 ONS-2 L2448-02 12 1-131 6.70E-03 7. 1OE-03 2.50E-02 ONS-3 L2448-03 12 1-131 -8.00E-03 7.80E-03 3.10E-02 ONS-4 L2448-04 12 1-131 -9.30E-03 6.70E-03 2.80E-02 ONS-5 L2448-05 12 1-131 3.30E-03 7.20E-03 2.60E-02 ONS-6 L2448-06 12 1-131 -1.40E-02 6.90E-03 3.00E-02 NBF L2448-07 12 1-131 -4.70E-03 6.90E-03 2.70E-02 SBN L2448-08 12 1-131 -1.25E-02 8.00E-03 3.30E-02 DOW L2448-09 12 1-131 3.70E-03 9.00E-03 3.20E-02 COL L2448-10 12 1-131 -L.OOE-02 L.OOE-02 4.40E-02 ONS-I L2505-01 13 1-131 -6.20E-03 6.20E-03 2.60E-02 ONS-2 L2505-02 13 1-131 -4.90E-03 6.50E-03 2.60E-02 ONS-3 L2505-03 13 1-131 -1.1OE-02 6.60E-03 2.80E-02 ONS-4 L2505-04 13 1-131 1.23E-02 6.SOE-03 2.00E-02 ONS-S L2505-05 13 1-131 1.20E-03 7.00E-03 2.60E-02 ONS-6 L2505-06 13 1-131 -3.70E-03 6.90E-03 2.70E-02 NBF L2505-07 13 1-131 -9.70E-03 6.20E-03 2.70E-02 SBN L2505-08 13 1-131 -5.tOE-03 7.80E-03 3.10E-02 DOW L2505-09 13 1-131 -7.60E-03 7.40E-03 3.00E-02 COL L2505-10 13 1-131 1.30E-03 7.70E-03 2.80E-02 ONS-I L2532-01 14 1-131 -1.42E-02 6. 1OE-03 2.60E-02 ONS-2 L2532-02 14 1-131 1.IOE-02 S.40E-03 1.70E-02 ONS-3 L2532-03 14 1-131 2.50E-03 4.70E-03 L.70E-02 ONS-4 L2532-04 14 1-131 -4.50E-03 5.50E-03 2.20E-02 ONS-S L2532-05 14 1-131 -2.80E-03 5.50E-03 2. 1OE-02 ONS-6 L2532-06 14 1-131 -1.80E-03 5.20E-03 2.00E-02 NBF L2532-07 14 1-131 -1.OOE-02 5.80E-03 2.40E-02 SBN L2532-08 14 1-131 5.40E-03 5.70E-03 2.00E-02 DOW L2532-09 14 1-131 O.OOE+O0 S.30E-03 2.OOE-02 COL L2532-10 14 1-131 3.80E-03 5.OOE-03 L.80E-02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-46

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3 ) (pCi/ m3 ) (pCi/mr)

ONS-I L2609-01 15 1-131 2.05E-02 9.00E-03 2.80E-02 ONS-2 L2609-02 15 1-131 9.80E-03 7.50E-03 2.50E-02 ONS-3 L2609-03 15 1-131 -2.40E-03 7.90E-03 3.00E-02 ONS4 L2609-04 15 1-131 2.70E-03 7.80E-03 2.90E-02 ONS-5 L2609-05 15 1-131 * -2.80E-03 7.40E-03 2.90E-02 ONS-6 L2609-06 15 1-131 8.40E-03 8.101E-03 2.80E-02 NBF L2609-07 15 1-131 . I.IIE-02 8.10E-03 2.70E-02 SBN L2609-08 15 1-131 6.70E-03 8.00E-03 2.80E-02 DOW L2609-09 15 1-131 -5.90E-03 8.80E-03 3.40E-02 COL L2609-10 15 1-131 -1.40E-03 9.00E-03 3.40E-02 ONS-1 L2636-01 16 1-131 6.20E-03 6.40E-03 2.20E-02 ONS-2 L2636-02 16 1-131 -3.10E-03 7.70E-03 2.90E-02 ONS-3 L2636-03 16 1-131 1.70E-03 5.60E-03 2.00E-02 ONS-4 L2636-04 16 1-131 4.00E-03 5.80E-03 2. 1OE-02 ONS-5 L2636-05 16 1-131 -1I.OIE-02 5.50E-03 2.30E-02 ONS-6 L2636-06 16 1-131 -1.IOE-03 6.70E-03 2.50E-02 NBF L2636-07 16 1-131 5.OOE-03 6.60E-03 2.30E-02 SBN . L2636-08 16 1-131 -7.90E-03 5.50E-03 2.30E-02 DOW L2636-09 16 1-131 9.90E-03 6.90E-03 2.30E-02 COL L2636-10 16 1-131 -1.38E-02 6.70E-03 2.80E-02 ONS-1 L2660-01 17 1-131 -8.70E-03 9.60E-03 4.30E-02 ONS-2 L2660-02 17 1-131 -6.00E-03 1.OOE-02 4.40E-02 ONS-3 L2660-03 17 r-131 -1.20E-02 7.20E-03 3.60E-02 ONS-4 L2660-04 17 1-131 -5.SOE-03 7.70E-03 3.60E-02 ONS-5 1L2660-05 17 1-131 3.70E-03 5.80E-03 2.00E-02 ONS-6 L2660-06 17 1-131 O.OOE+00 5.20E-03 2.OOE-02 NBF L2660-07 17 1-131 -1.07E-02 6.00E-03 2.SOE-02 SBN L2660-08 17 1-131 4.40E-03 5.00E-03 1.80E-02 DOW L2660-09 17 1-131 8.70E-03 5.70E-03 1.90E-02 COL ' L2660-10 17 1-131 1.90E-03 5.00E-03 1.80E-02 ONS-1 L2759-01 18 1-131 -6.40E-03 6.90E-03 2.80E-02 ONS-2 L2759-02 18 1-131 0.00E+00 7.40E-03 2.80E-02 ONS-3 L2759-03 18 1-131 -1.68E-02 7.40E-03 3.20E-02 ONS-4 L2759-04 18 1-131 -1.30E-03 7.00E-03 2.70E-02

• Radioactivity detected In sample (i.e7 concentration > 3 X standard deviation)

D-47

Indiana Michigan Power Co., DC Cook Nuclear Plant J Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/l 3 ) (pCi mi )3 (pCi/m 3)

ONS-5 L2759-05 18 1-131 -1.30E-03 8.80E-03 3.30E-02 ONS-6 L2759-06 18 1-131 7.80E-03 6.90E-03 2.30E-02 NBF L2759-07 18 1-131 3.90E-03 8.00E-03 2.90E-02 SBN L2759-08 18 1-131 -5.10E-03 6.80E-03 2.70E-02 -

DOW L2759-09. 18 1-131 -6.40E-03 6.90E-03 2.80E-02 COL L2759-10 18 1-131 2.70E-3 6.80E-03 2.50E-02 ONS-I L2795-01 19 1-131 3.50E-03 5.50E-03 1.90E-02 ONS-2 L2795-02 19 1-131 6.30E-03 5.00E-03 1.70E-02 ONS-3 L2795-03 19 1-131 O.OOE+00 5.40E-03 2.OOE-02 ONS-4 L2795-04 19 1-131 O.OOE+00 5.OOE-03 1.90E-02 ONS-5 L2795-05 19 1-131 -1.09E-02 5.60E-03 2.30E-02 ONS-6 L2795-06 19 1-131 3.60E-03 5.OOE-03 1.80E-02 NBF L2795-07 19 1-131 3.60E-03 4.80E-03 1.70E-02 SBN L2795-08 19 1-131 -1.07E-02 5.50E-03 2.30E-02 DOW L2795-09 19 1-131 3.50E-03 4.10E-03 1.50E-02 COL L2795-10 19 1-131 2.70E-03 5.10E-03 1.80E-02 ONS-1 L2857-01 20 1-131 2.14E-02 8.20E-03 2.40E-02 ONS-2 L2857-02 20 1-131 5.20E-03 7.50E-03 2.70E-02 ONS-3 L2857-03 20 1-131 -3.80E-03 8.00E-03 3.10E-02 ONS-4 L2857-04 20 1-31 7.30E-03 6.OOE-03 2.00E-02 ONS-5 L2857-05 20 1-131 -1.30E-03 7.10E-03 2.70E-02 ONS-6 L2857-06 20 1-131 1.02E-02 6.OOE-03 1.90E-02 NBF L2857-07 20 1-131 -3.80E-03 6.30E-03 2.50E-02 SBN L2857-08 20 1-131 7.40E-03 7.20E-03 2.50E-02 DOW L2857-09 20 1-131 1.30E-03 7.70E-03 2.90E-02 COL L2857-10 20 1-131 -9.OOE-03 8.90E-03 3.50E-02 ONS-1 L2928-01 21 1-131 1.07E-02 8.70E-03 3.00E-02 ONS-2 L2928-02 21 1-131 -5.30E-03 3.70E-03 1.30E-02 ONS-3 L2928-03 21 1-131 1.26E-02 &90E-03 3.00E-02 ONS-4 L2928-04 21 1-131 -3.00E-03 9.00E-03 3.50E-02 ONS-5 L2928-05 21 1-131 9.10E-03 9.80E-03 3.40E-02 ONS-6 L2928-06 21 1-131 6.00E-03 9.80E-03 3.50E-02 NBF L2928-07 21 1-131 O.OOE+00 9.00E-03 3.40E-02 SBN L2928-08 21 1-131 1.40E-03 7.80E-03 2.90E-02 DOW L2928-09 21 1-131 -4.40E-03 9.50E-03 3.60E-02 COL L2928-10 21 1-131 2.16E-02 9.20E-03 2.80E-02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-48

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program

- Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3 ) (pCi/ mI) (pCi/lm)

ONS-1 L2983-01 22 1-131 7.20E-03 8.30E-03 2.90E-02 ONS-2 L2983-02 22 1-131 -4.10E-03 8.80E-03 3.40E-02 ONS-3 L2983-03 22 1-131 3.OOE-03 9.OOE-03 3.30E-02 ONS-4 L2983-04 22 1-131 1.50E-03 7.80E-03 2.90E-02 ONS-5 L2983-05 22 1-131 -1.40E-03 8.20E-03 3.1OE-02 ONS-6 L2983-06 22 1-131 1.40E-03 8.30E-03 3.1OE-02 NBF L2983-07 22 1-131 1.50E-03 7.90E-03 3.OOE-02 SBN L2983-08 22 1-131 8.OOE-03 7.30E-03 2.50E-02 DOW L2983-09 22 1-131 O.OOE+00 8.20E-03 3.1OE-02 COL L2983-10 22 1-131 O.OOE+00 8.40E-03 3.20E-02 ONS-I L3030-01 23 1-131 -3.50E-03 5.80E-03 2.30E-02 ONS-2 L3030-02 23 1-131 -1.20E-03 5.80E-03 2.30E-02 ONS-3 L3030-03 23 1-131 3.60E-03 7.OOE-03 2.50E-02 ONS-4 L3030-04 23 1-131 -5.90E-03 6.40E-03 2.60E-02 ONS-5 L3030-05 23 1-131 8.OOE-03 5.70E-03 1.90E-02 ONS-6 L3030-06 23 1-131 -1.20E-03 6.20E-03 2.40E-02 NBF L3030-07 23 1-131 8.50E-03 5.60E-03 1.80E-02 SBN L3030-08 23 I-131 1.IOE-03 6.70E-03 2.50E-02 DOW L3030-09 23 1-131 -8.20E-03 6.1OE-03 2.60E-02 COL L3030-10 23 1-131 -1.20E-03 5.80E-03 2.30E-02 ONS-1 L3114-01 24 1-131 -7.90E-03 7.20E-03 2.80E-02 ONS-2 L3114-02 24 1-131 -1.40E-03 7.10E-03 2.70E-02 ONS-3 L3114-03 24 1-131 1.OOE-03 5.50E-03 2.1OE-02 ONS-4 L3114-04 24 1-131 -9. 1OE-03 6.90E-03 2.80E-02 ONS-5 L3114-05 24 1-131 -1.49E-02 7.40E-03 3.10E-02 ONS-6 L3114-06 24 1-131 -1.26E-02 5.90E-03 2.60E-02 NBF L3114-07 24 1-131 -5.OOE-03 6.30E-03 2.50E-02 SBN L3114-08 24 1-131 -4.70E-03 7.50E-03 2.90E-02 DOW L3114-09 24 1-131 -3.70E-03 7.OOE-03 2.70E-02 COL L3114-10 24 1-131 -5.60E-03 6.40E-03 2.50E-02 ONS-1 L3150-01 25 1-131 1.80E-03 5.10E-03 I.90E-02 ONS-2 L3150-02 25 1-131 7.70E-03 5.70E-03 1.90E-02 ONS-3 L3150-03 25 1-131 O.OOE+00 6.1OE-03 2.30E-02 ONS-4 L3150-04 25 1-131 4.30E-03 5.10E-03 1.80E-02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-49

Indiana Michigan Power Co., DC Cook Nuclear Plant. -.

Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCim 3) (pCi/ mI 3)

(pCi/n 3 )

ONS-5 L3150-05 25 1-131 8.OOE-04 5.10E-03 1.90E-02 ONS-6 L3150-06 25 1-131 O.OOE+00 4.80E-03 1.80E-02 NBF L3150-07 25 1-131 1.80E-03 4.70E-03 1.70E-02 SBN L3150-08 25 1-131 -1.13E-02 6.00E-03 2.50E-02 DOW L3150-09 25 1-131 -. OOE-03 6.10E-03 2.30E-02 COL L3150-10 25 1-131 -3.50E-03 5.50E-03 2.10E-02

-J ONS-I L3190-01 26 1-131 -I.IOE-03 6.30E-03 2.40E-02 ONS-2 L3190-02 26 1-131 -2.20E-03 6.30E-03 2.40E-02 ONS-3 L3190-03 26 1-131 1.55E-02 7.40E-03 2.302-02 ONS-4 L3190-04 26 1-131 -4.20E-03 5.20E-03 2.10E-02 ONS-5 L3190-05 26 1-131 3.70E-03 5.70E-03 2.00E-02 ONS-6 L3190-06 26 1-131 -1.27E-02 6.30E-03 2.70E-02 NBF L3190-07 26 1-131 6.40E-03 7.30E-03 2.50E-02 SBN L3190-08 26 1-131 -6.70E-03 5.80E-03 2.40E-02 DOW L3190-09 26 1-131 I.IOE-03 7.30E-03 2.70E-02 COL L3190-10 26 1-131 -6.OOE-03 6.302-03 2.50E-02 ONS-I L3250-01 27 1-131 -1.63E-02 7.90E-03 3.50E-02 ONS-2 L3250-02 27 1-131 6.1OE-03 6.90E-03 2.40E-02 ONS-3 L3250-03 27 1-131 -4.30E-03 7.20E-03 2.70E-02 ONS-4 L3250-04 27 1-131 5.00E-03 1.IOE-02 4.20E-02 ONS-S L3250-05 27 1-131 -3.20E-03 9.30E-03 3.70E-02 ONS-6 L3250-06 27 1-131 -. OOE-03 I.OOE-02 4.00E-02 NBF L3250-07 27 1-131 -5.40E-03 6.90E-03 3.10E-02 SBN L3250-08 27 1-131 1. 16E-02 9.10E-03 3.10E-02 DOW L3250-09 27 1-131 -5.40E-03 8.70E-03 3.70E-02 COL L3250-10 27 1-131 -3.20E-03 8.40E-03 3.50E-02 ONS-1 1U296-01 28 1-131 -5.80E-03 6.50E-03 2.60E-02 ONS-2 L3296-02 28 1-131 -1.512-02 6.50E-03 2.90E-02 ONS-3 L3296-03 28 1-131 -1.20E-03 7.10E-03 2.70E-02 ONS-4 L3296-04 28 1-131 3.70E-03 7.50E-03 2.70E-02 ONS-5 12296-05 28 1-131 6.10E-03 7.OOE-03 2.40E-02 ONS-6 12296-06 28 1-131 9.10E-03 7.90E-03 2.70E-02 NBF L3296-07 28 1-131 O.OOE+00 6.50E-03 2.50E-02 SBN L3296-08 28 1-131 1.38E-02 6.30E-03 1.90E-02 DOW L3296-09 28 1-131 -9.OOE-03 8.20E-03 3.30E-02 COL L3296-10 28 1-131 3.70E-03 7.90E-03 2.80E-02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-50

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3) (pCi/ m3 ) (pCi/m 3)

ONS-I L3354-01 29 1-131 -2.70E-03 7.10E-03 2.80E-02 ONS-2 L3354-02 29 1-131 -4.IOE-03 7.30E-03 2.90E-02 ONS-3 L3354-03 29 1-131 O.OOE+00 7.30E-03 2.80E-02 ONS-4 L3354-04 29 1-131 9.70E-03 8.60E-03 3.OOE-02 ONS-5 L3354-05 29 1-131 1.40E-03 8.80E-03 3.20E-02 ONS-6 L3354-06 29 1-131 8.50E-03 8.50E-03 3.OOE-02 NBF L3354-07 29 1-131 2.90E-03 6.70E-03 2.50E-02 SBN L3354-08 29 1-131 -2.80E-03 8.70E-03 3.30E-02 DOW L3354-09 29 1-131 O.OOE+00 8.90E-03 3.30E-02 COL L3354-10 29 1-131 -1.24E-02 6.90E-03 3.00E-02 ONS-1 L3392-01 30 1-131 -3.50E-03 5.60E-03 2.30E-02 ONS-2 L3392-02 30 1-131 -5.50E-03 5.30E-03 2.101E-02 ONS-3 L3392-03 30 1-131 9.OOE-04 5.30E-03 2.OOE-02 ONS-4 L3392-04 30 1-131 -2.80E-03 6.00E-03 2.30E-02 ONS-5 L3392-05 30 1-131 3.40E-03 5.20E-03 1.80E-02 ONS-6 L3392-06 30 1-131 1.70E-03 5.40E-03 2.00E-02 NBF L3392-07 30 1-131 9.OOE-04 5.60E-03 2.10E-02 SBN L3392-08 30 1-131 -8.30E-03 5.10E-03 2.101E-02 DOW L3392-09 30 1-131 1.13E-02 5.70E-03 1.80E-02 COL L3392-10 30 1-131 -2.OOE-03 4.30E-03 1.60E-02 ONS-1 L3452-01 31 1-131 1.OOE-02 6.00E-03 1.90E-02 ONS-2 L3452-02 31 1-131 9.40E-03 6.20E-03 2.00E-02 ONS-3 L3452-03 31 1-131 -7.80E-03 6.40E-03 2.60E-02 ONS-4 L3452-04 31 1-131 -9.60E-03 6.30E-03 2.60E-02 ONS-5 L3452-05 31 1-131 I .OOE-03 5.80E-03 2.101E-02 ONS-6 L3452-06 31 1-131 -4.50E-03 5.70E-03 2.30E-02 NBF L3452-07 31 1-131 0.OOE+O0 6.00E-03 2.30E-02 SBN L3452-08 31 1-131 3.20EM-0 5.60E-03 2.OOE-02 DOW L3452-09 31 1-131 1.06E-02 5.90E-03 1.90E-02 COL L3452-10 31 1-131 1.75E-02 8.50E-03 2.60E-02 ONS-1 L3512-01 32 1-131 3.80E-03 3.80E-03 1.40E-02 ONS-2 L3512-02 32 1-131 -3.90E-03 5.20E-03 2.10E-02 ONS-3 L3512-03 32 1-131 -4.80E-03 4.90E-03 2.00E-02 ONS-4 L3512-04 32 1-131 9.OOE-04 4.40E-03 1.70E-02

• Radioactivity detected In sample (i.e., concentration > 3 X standard deviation)

D-51

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3) (pCi/ m3 ) (pCi/M3 )

ONS-S L3512-05 32 1-131 -5.90E-03 9.30E-03 3.30E-02 ONS-6 L3512-06 32 1-131 -6.50E-03 6.10E-03 2.50E-02 NBF L3512-07 32 1-131 1.20E-03 5.30E-03 2.00E-02 SBN L3512-08 32 1-131 4.50E-03 5.802-03 2.00E-02 DOW L3512-09 32 1-131 -I.lOE-03 5.40E-03 2.10E-02 COL L3512-10 32 1-131 2.90E-03 6.90E-03 2.60E-02 ONS-1 L3568-01 33 1-131 5.80E-03 4.70E-03 1.60E-02 ONS-2 L3568-02 33 1-131 -8.90E-03 6.O0E-03 2.50E-02 ONS-3 L3568-03 33 1-131 7.50E-03 5.OOE-03 1.60E-02 ONS-4 L3568-04 33 1-131 -9.00-04 4.80E-03 1.80E-02 ONS-5 L3568-05 33 1-131 5.80E-03 4.90E-03 1.70E-02 ONS-6 U3568-06 33 1-131 -3.80E-03 5.00-03 2.00E-02 NBF L3568-07 33 1-131 -3.OOE-03 5.50E-03 2.20E-02 SBN L3568-08 33 1-131 1.OIE-02 5.70E-03 1.80E-02 DOW L3568-09 33 1-131 -1.70E-03 7.10E-03 2.40E-02 COL L3568-10 33 1-131 1.02E-02 5.00E-03 1.50E-02 ONS-1 L3612-01 34 1-131 -1.70E-03 6.402-03 2.40E-02 ONS-2 L3612-02 34 I-131 8.00E3-04 5.10E-03 I.90E-02 ONS-3 L3612-03 34 1-131 -8.00E-04 4.602-03 1.80E-02 ONS-4 L3612-04 34 1-131 6.10E-03 4.802-03 1.60E-02 ONS-5 L3612-05 34 1-131 4.30E-03 4.80E-03 1.70E-02 ONS-6 L3612-06 34 1-131 1.70E-03 4.60E-03 1.70E-02 NBF L3612-07 34 1-131 3.50E-03 4.90E-03 1.70E-02 SBN L3612-08 34 1-131 1.702-03 5.302-03 1.90E-02 DOW L3612-09 34 1-131 -3.502-03 5.30E-03 2.10E-02 COL L3612-10 34 1-131 4.00E-03 I.IOE-02 4.002-02 ONS-1 L3696-01 35 1-131 8.30E-03 5.60E-03 1.902-02 ONS-2 L3696-02 35 1-131 9.00E-04 5.30E-03 2.002-02 ONS-3 L3696-03 35 1-131 -1.70E-03 4.80E-03 1.90E-02 ONS-5 L3696-05 35 1-131 -2.80E-03 4.802-03 1.90E-02 ONS-6 L3696-06 35 1-131 7.50E-03 4.602-03 1.502-02 NBF L3696-07 35 1-131 9.00E-04 4.50E-03 1.70E-02 SBN L3696-08 35 1-131 -1.90E-03 5.10E-03 2.00E-02 DOW L3696-09 35 1-131 9.40E-03 5.70E-03 1.80E-02 COL L3696-10 35 1-131 -2.80E-03 3.60E-03 1.60E-02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-52

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3) (pCi/ rn) (pCi/rn)

ONS-1 L3742-01 36 1-131 -7. IOE-03 7.30E-03 2.90E-02 ONS-2 L3742-02 36 1-131 -1.44E-02 7.60E-03 3.20E-02 ONS-3 L3742-03 36 1-131 4.60E-03 6.90E-03 2.40E-02 ONS-4 U3742-04 36 1-131 -2.40E-03 7.90E-03 3.OOE-02 ONS-5 L3742-05 36 1-131 -4.70E-03 6.50E-03 2.60E-02 ONS-6 L3742-06 36 1-131 4.80E-03 7.OOE-03 2.50E-02 NBF L3742-07 36 1-31 -3.50E-03 6.70E-03 2.60E-02 SBN L3742-08 36 1-131 7AOE-03 7.40E-03 2.50E-02 DOW L3742-09 36 1-131 -8.90E-03 9.20E-03 3.60E-02 COL L3742-10 36 1-131 -3.70E-03 6.40E-03 2.60E-02 ONS-1 12803-01 38 1-131 -2.50E-02 1.20E-02 5.40E-02 ONS-2 L3803-02 38 1-131 O.OOE+00 I.OOE-02 4.00E-02 ONS-3 L3803-03 38 1-131 7.OOE-03 1.IOE-02 3.90E-02 ONS-4 L3803-04 38 1-131 -7.OOE-03 l.lOE-02 4.50E-02 ONS-5 L3803-05 38 1-131 1.50E-02 I.OOE-02 3.40E-02 ONS-6 L3803-06 38 1-131 I.OOE-02 7.90E-03 2.70E-02 NBF L3803-07 38 1-131 -7.OOE-03 .IOE-02 4.60E-02 SBN L3803-08 38 1-131 7.OOE-03 l.OE-02 4.1OE-02 DOW L3803-09 38 1-131 -9.OOE-03 1.20E-02 4.80E-02 COL U3803-10 38 1-131 -5.OE-03 9.50E-03 4.OOE-02 ONS-1 L3868-01 38 1-131 - 1.19E-02 7.90E-03 3.40E-02 ONS-2 L3868-02 38 1-131 4.OOE-04 7.90E-03 3.OOE-02 ONS-3 L3868-03 38 1-131 1.90E-03 7.10E-03 2.70E-02 ONS4 L3868-04 38 1-131 -7.30E03 7.10E-03 3.OOE-02 ONS-5 L3868-05 38 1-131 -5.40E-03 7.80E-03 3.101E-02 ONS-6 L3868-06 38 1-131 -1. IOE-03 9.1OE-03 3.40E-02 NBF L3868-07 38 1-131 6.50E-03 7.IOE-03 2.50E-02 SBN L3868-08 38 1-131 -1.OOE-03 8.50E-03 3.20E-02 DOW L3868-09 38 1-131 1.74E-02 7.IOE-03 2.10E-02 COL L3868-10 38 1-131 8.10E-03 8.90E-03 3.1OE-02 ONS-1 L3950-01 39 1-131 4.20E-03 8.50E-03 3.10E-02 ONS-2 L3950-02 39 1-131 -1.72E-02 9.30E-03 3.80E-02 ONS-3 L3950-03 . 39 1-131 7.OOE-03 L.OOE-02 3.SOE-02 ONS-4 L3950-04 39 1-131 1.40E-03 7.30E-03 2.80E-02 ONS-5 L3950-05 39 1-131 -1.39E-02 6.80E-03 3.10E-02 ONS-6 L3950-06 39 1-131 -8.80E-03 9.30E-03 3.70E-02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-53

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m3 ) (pCi/ m3) (pCi/n 3 )

NBF L3950-07 39 1-131 -4.30E-03 7.70E-03 3.00E-02 SBN L3950-08 39 1-131 -1.77E-02 8.10E-03 3.50E-02 DOW L3950-09 39 1-131 '.L I8E-02 7.80E-03 3.30E-02 COL L3950-10 39 1-131 8.80E-03 7.20E-03 2.50E-02 ONS-1 L3975-01 40 1-131 -4.30E-03 6.90E-03 2.80E-02 ONS-2 L3975-02 40 1-131 6.50E-03 6.50E-03 2.30E-02 ONS-3 L3975-03 40 1-131 -1.60E-03 5.90E-03 2.40E-02 ONS-4 L3975-04 40 1-131 8.102-03 7.10E43 2.40E-02 ONS-5 L3975-05 40 1-131 0.002+00 6.OOE-03 2.40E-02 ONS-6 L3975-06 40 1-131 7.302-03 5.70E-03 1.90E-02 NBF L3975-07 40 1-131 1.26E-02 7.00E-03 2.20E-02 SBN L3975-08 40 1-131 1.07E-02 6.10E-03 1.90E-02 DOW L3975-09 40 1-131 3.60E-03 8.90E-03 3.30E-02 COL L3975-10 40 1-131 -3.50E-03 7.40E-03 3.10E-02 ONS-1 L4031-01 41 1-131 1.20E-03 4.40E-03 1.60E-02 ONS-2 L4031-02 41 1-131 -1.37E-02 6.40E-03 2.70E-02 ONS-3 L4031-03 41 1-131 -3.80E-03 5.20E-03 2.10E-02 ONS-4 L4031-04 41 1-131 -2.90E-03 4.30E-03 1.60E-02 ONS-5 L4031-05 41 1-131 -1.14E-02 6.40E-03 2.70E-02 ONS-6 L4031-06 41 1-131 -7.30E-03 6.30E-03 2.60E-02 NBF L4031-07 41 1-131 0.00E+00 6.00E-03 2.20E-02 SBN L4031-08 41 1-131 1.42E-02 5.80E-03 1.70E-02 DOW L4031-09 41 1-131 -6.60E-03 6.70E-03 2.70E-02 COL L4031-10 41 1-131 1.50E-03 5.80E-03 2.20E-02 ONS-1 L4104-01 42 1-131 2.20E-03 4.70E-03 1.70E-02 ONS-2 L4104-02 42 1-131 -2.90E-03 4.10E-03 1.60E-02 ONS-3 L4104-03 42 1-131 -7.00E-04 4.40E-03 1.70E-02 ONS-4 L4104-04 42 1-131 2.20E-03 4.30E-03 1.50E-02 ONS-5 L4104-05 42 1-131 -2.20E-03 4.50E-03 1.70E-02 ONS-6 L4104-06 42 1-131 -4.50E-03 4.00E-03 1.70E-02 NBF L4104-07 42 1-131 -5.00E-03 4.60E-03 1.80E-02 SBN L4104-08 42 1-131 1.40E-03 3.90E-03 1.40E-02 DOW [4104-09 42 1-131 -6.00E-03 3.802-03 1.60E-02 COL L4104-10 42 1-131 3.802-03 4.00E-03 1.40E-02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-54

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/l 3 ) (pCi/ m3) (pCi/m 3)

ONS-I L4165-01 43 1-131 3.OOE-03 8.30E-03 3.00E-02 ONS-2 L4165-02 43 1-131 -11.OOE-03 7.20E-03 2.80E-02 ONS-3 LA165-03 . 43 1-131 -6.20E-03 7.20E-03 2.90E-02 ONS-4 L4165-04 43 1-131 5.OOE-03 1.OOE-02 3.60E-02 ONS-5 L4165-05 43 1-131 5.OOE-03 1.IOE-02 3.90E-02 ONS-6 L4165-06 43 1-131 -3.OOE-03 9.90E-03 3.90E-02 NBF L4165-07 43 1-131 -1.90E-02 1I.OOE-02 4.40E-02 SBN IA165-08 43 1131 -9.20E-03 8.70E-03 3.80E-02 DOW L4165-09 43 1-131 5.OOE-03 1.20E-02 4.20E-02 COL L4165-10 43 1-131 1.IOE-02 1.OOE-02 3.60E-02 ONS-1 L4222-01 44 1-131 -3.20E-03 8.40E-03 3.50E-02 ONS-2 L4222-02 44 1-131 1.50E-03 9.10E-03 3.60E-02 ONS-3 L4222-03 44 1-131 -1.41E-02 9.90E-03 4.30E-02 ONS-4 L4222-04 44 1-131 -1.45E-02 9.70E-03 4.30E-02 ONS-5 L4222-05 44 1-131 -7.70E-03 8.30E-03 3.70E-02 ONS-6 L4222-06 44 1-131 -1.82E-02 8.20E-03 4.00E-02 NBF L4222-07 44 1-131 -3.20E-03 7.10E-03 3.20E-02 SBN L4222-08 44 1-131 1.50E-03 9.80E-03 3.80E-02 DOW LA222-09 44 1-131 6.00E-03 1.20E-02 4.20E-02 COL L4222-10 44 1-131 -5.60E-03 8.90E-03 3.80E-02 ONS-1 L4258-01 45 1-131 5.50E-03 6.80E-03 2.40E-02 ONS-2 L4258-02 45 1-131 -5.60E-03 6.80E-03 2.80E-02 ONS-3 LA258-03 45 1-131 6.80E-03 5.30E-03 1.80E-02 ONS-4 L4258-04 45 1-131 4.10E-03 8.10E4-03 2.90E-02 ONS-5 L4258-05 45 1-131 -1.40E-03 6.80E-03 2.70E-02 ONS-6 L4258-06 45 1-131 1.40E-03 6.90E-03 2.60E-02 NBF L4258-07 45 1-131 0.OOE+O0 7.90E-03 3.00E-02 SBN L4258-08 45 1-131 7.10E-03 7.1OE-03 2.50E-02 DOW L4258-09 45 1-131 2.90E-03 7.80E-03 2.90E-02 COL L4258-10 45 1-131 -5.50E-03 6.101E-03 2.60E-02 ONS-I L4298-01 46 1-131 8.40E-03 3.50E-03 I.OOE-02 ONS-2 L4298-02 46 1-131 -2.40E-03 3.60E-03 1.40E-02 ONS-3 LA298-03 46 1-131 -4.50E-03 7.20E-03 3.20E-02 ONS-4 L4298-04 46 1-131 l.02E-02 7,20E-03 2.40E-02 ONS-5 L4298-05 46 1-131 2.50E-03 8.40E-03 3.30E-02 ONS-6 L4298-06 46 1-131 I.OOE-02 7.9OE-03 2.70E-02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-55

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m 3) (pCi/ m3 ) (pCi/m 3)

NBF L4298-07 46 1-131 O.OOE+OO 8.40E-03 3.40E-02 SBN L4298-08 46 1-131 1.29E-02 7.70E-03 2.40E-02 DOW L4298-09 46 1-131 6.70E-03 5.90E-03 2.10E-02 COL L4298-10 46 1-131 -2.50E-03 6.70E-03 3.OOE-02 ONS-I L4364-01 47 1-131 -4.20E-03 5.50E-03 2.30E-02 ONS-2 L4364-02 47 1-131 -3.10E-03 6.40E-03 2.50E-02 ONS-3 L4364-03 47 1-131 1.60E-03 6.50E-03 2.40E-02 ONS-4 L4364-04 47 1-131 -3.20E-03 6.80E-03 2.60E-02 ONS-5 L4364-05 47 1-131 4.OOE-04 5.40E-03 2.10E-02 ONS-6 L4364-06 47 1-131 -3.30E-03 5.60E-03 2.30E-02 NBF L4364-07 47 1-131 5.OOE-04 6.80E-03 2.60E-02 SBN L4364-08 47 1-131 5.OOE-04 6.20E-03 2.40E-02 DOW L4364-09 47 1-131 2.80E-03 6.lOE-03 2.20E-02 COL L4364-10 47 1-131 5.90E-03 6.80E-03 2.40E-02 ONS-I L4410-01 48 1-131 4.50E-03 7.OOE-03 2.50E-02 ONS-2 L4410-02 48 1-131 -1.20E-03 7.50E-03 2.80E-02 ONS-3 L4410-03 48 1-131 -1.20E-03 8.30E-03 3.10E-02 ONS-4 L4410-04 48 1-131 4.60E-03 7.20E-03 2.60E-02 ONS.5 L4410-05 48 1-131 O.OOE+00 6.80E-03 2.60E-02 ONS-6 L4410-06 48 1-131 1.17E-02 7.90E-03 2.60E-02 NBF L4410-07 48 1-131 -I.IOE-02 1.50E-02 6.20E-02 SBN L4410-08 48 1-131 4.OOE-03 L.OOE-02 3.80E-02 DOW L4410-09 48 1-131 1.80E-03 7.10E-03 2.80E-02 COL L4410-10 48 1-131 O.OOE+OO 6.10E-03 2.50E-02 ONS;I L4447-01 49 1-131 -5.20E-03 7.30E-03 3.40E-02 ONS-2 L4447-02 49 1-131 -2.60E-03 8.60E-03 3.70E-02 ONS-3 L4447-03 49 1-131 6.40E-03 5.30E-03 1.80E-02 ONS-4 L4447-04 49 1-131 -1.30E-03 5.40E-03 2.20E-02 ONS-5 L4447-05 49 1-131 -1.20E-03 6.50E-03 2.50E-02 ONS-6 L4447-06 49 1-131 3.80E-03 5.20E-03 1.90E-02 NBF L4447-07 49 1-131 -9.20E-03 6.30E-03 2.70E-02 SBN L4447-08 49 1-131 5.60E-03 5.90E-03 2.1OE-02 DOW L4447-09 49 1-131 1.40E-03 6.30E-03 2.40E-02 COL L4447-10 49 1-131 -8.60E-03 7.60E-03 3.IOE-02

• Radioactivity detected in sample (i.e, concentration > 3 X standard deviation)

D-56

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/m3 ) (pCil m3 ) (pCi/m3 )

ONS-1 L4495-41 50 1-131 -2.80E-03 7.OOE-03 3.OOE-02 ONS-2 LA495-02 50 1-131 1.83E-02 8.20E-03 2.30E-02 ONS-3 L4495-03 50 1-131 -2.90E-03 8.40E-03 3.50E-02 ONS-4 L4495-04 50 1-131 -2.80E-03 5.60E-03 2.60E-02 ONS-s L4495-05 50 1-131 5.70E-03 6.40E-03 2.40E-02 ONS-6 L4495-06 50 1-131 -2.60E-03 6.40E-03 2.80E-02 NBF L4495-07 50 1-131 1.50E-03 7.80E-03 3.10E-02 SBN U4495-08 50 1-131 1.OOE-02 8.30E-03 2.80E-02 DOW U4495-09 50 1-131 -7.00E-04 9.30E-03 3.70E-02 COL LA495-10 50 1-131 -1.53E-02 6.90E-03 3.50E-02 ONS-1 L4543-01 51 1-131 1.90E-02 1.20E402 3.80E-02 ONS-2 L4543-02 51 1-131 O.OOE+00 1.20E-02 5.OOE-02 ONS-3 L4543-03 51 1-131 4.10E-03 7.10E-03 2.70E-02 ONS-4 L4543-04 51 1-131 9.50E-03 8.20E-03 2.90E-02 ONS-5 L4543-05 51 1-131 -7.00E-03 I.OOE-02 4.40E-02 ONS-6 L4543-06 51 1-131 -4.40E-03 8.80E-03 3.70E-02 NBF LA543-07 51 1-131 -7.00E-03 .LIOE-02 4.40E-02 SBN L4543-08 51 1-131 -1.40E-02 1I.OE-02 4.80E-02 DOW L4543-09 51 1-131 -1.OOE-02 I.OOE-02 4.30E-02 COL LA543-10 51 1-131 2.40E-03 9.80E-03 3.80E-02 ONS-1 L4568-01 52 1-131 -7.90E-03 5.90E-03 2.60E-02 ONS-2 L4568-02 52 1-131 6.90E-03 7.70E-03 2.70E-02 ONS-3 L4568-03 52 1-131 -9.20E-03 6.60E-03 2.80E-02 ONS-4 L4568-04 52 1-131 -5.20E-03 7.30E-03 2.90E-02 ONS-5 L4568-05 52 1-131 1.40E-02 6.80E-03 2.10E-02 ONS-6 L4568-06 52 1-131 2.60E-03 6.101E-03 2.30E-02 NBF L4568-07 52 1-131 -4.20E-03 6.60E-03 2.70E-02 SBN L4568-08 52 1-131 -5.70E-03 7.50E-03 3.0QE-02 DOW L4568-09 52 1-131 O.OOE+00 8.40E-03 3.20E-02 COL L4568-10 52 1-131 -2.80E-03 6.60E-03 2.70E-02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-57

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

FH OFS-N L3334-01 28 AcTh-228 8.30E+01 6.70E+01 2.20E+02 OFS-N L3334-01 28 Ag-10Sm -3.OOE+00 1.50E+01 5.30E+01 OFS-N L3334-01 28 Ag-ll0m -2.90E+01 2.50E+01 9.80E+01 OFS-N L3334-01 28 Ba-140 5.IOE+01 6.30E+01 2.30E+02 OFS-N L3334-01 28 Be-7 -2.00E+01 1.70E+02 6.10E+02 OFS-N L3334-01 28 Ce-141 -5.50E+01 7.30E+01 2.50E+02 OFS-N L3334-01 28 Cc-144 8.00E+01 2.OOE+02 6.90E+02 OFS-N L3334-01 28 Co-57 -7.00E+01 2.70E+01 9.50E+0O OFS-N L3334-01 28 Co-58 -6.00E+00 1.70E+01 6.50E+01 OFS-N L3334-01 28 Co-60 -1.50E+01 1.40E+01 6.1OE+0O OFS-N L3334-01 28 Cr-51 8.OOE+01 2.70E+02 9.30E+02 OFS-N L3334-01 28 Cs-134 1.60E+01 1.70E+01 5.90E+01 OFS-N L3334-01 28 Cs-137 -5.OOE+00 1.50E+01 5.90E+Ol OFS-N L3334-01 28 Fe-59 -2.40E+01 5.20E+01 2.IOE+02 OFS-N L3334-01 28 1-131 I.OOE+01 1.30E+02 4.80E+02 OFS-N L3334-01 28 K-40 3.88E+03 4.10E+02 6.00E+02 OFS-N L3334-01 28 La-140 5.90E+01 7.202+01 2.60E+02 OFS-N L3334-01 28 Mn-54 7.00E+00 1.50E+01 5.40E+0O QFS-N L3334-01 28 Nb-95 2.10E-+01 2.30E+01 8.00E+01 OFS-N L3334-01 28 Ru-103 -1.20E+01 2.30E+01 8.50E+01 OFS-N L3334-01 28 Ru-106 -2.10E+02 1.40E+02 5.70E+02 OFS-N L3334-01 28 Sb-124 2.90E+01 4.90E+01 1.80E+02 OFS-N L3334-01 28 Sb-125 -5.10E+01 4.20E+01 1.60E+02 OFS-N L3334-01 28 Se-75 -3.20E+01 3.00E+O0 1.10+02 OFS-N L3334-01 28 Zn-65 -1.20E+01 4.OOE+01 1.50E+02 OFS-N L3334-01 28 Zr-95 -I.IOE+01 3.60E+01 1.40E+02 ONS-N L3334-02 28 AcTh-228 3.80E+01 4.80E+OI 1.70E+02 ONS-N L3334-02 28 Ag-108m -4.70E+00 8.10E+00 3.20E+01 ONS-N L3334-02 28 Ag-ll0m -4.00E+00 1.80E+0I 7.10E+01 ONS-N L3334-02 28 Ba-140 -4.90E+01 5.40E+01 2.40E+02 ONS-N L3334-02 28 Be-7 4.10E+01 8.60E+01 3.20E+02 ONS-N L3334-02 28 Ce-141 1.20E+01 1.60E+01 5.50E+01 ONS-N L3334-02 28 Ce-144 -1.80E+01 4.90E+01 1.80E+02 ONS-N L3334-02 28 Co-57 -5.20E+00 5.80E+00 2.20E+01 ONS-N U3334-02 28 Co-58 1.70E+01 1.10E+01 3.50E+01 ONS-N L3334-02 28 Co-60 1.40E+01 1.30E+01 4.50E+01 ONS-N L3334-02 28 Cr-51 8.00E+01 1.30E+02 4.60E+02 ONS-N L3334-02 28 Cs-134 1.OOE+00 1.20E+01 4.60E+01 ONS-N L3334-02 28 Cs-137 1.60E+01 1.20E+01 4.20E+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-58

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

ONS-N L3334-02 28 Fe-59 -5.10E+O1 5.OOE+O1 2.20E+02 ONS-N L3334-02 28 1-131 -1.05E+02 7.90E+01 3.20E+02 ONS-N L3334-02 28 K-40 3.31E+03 3.80E+02 5.20E+02 ONS-N 13334-02 28 La-140 -5.60E+01 6.20E+01 2.80E+02 ONS-N L3334-02 28 Mn-54 8.OOE+O0 I.OOE+01 3.80E+0O ONS-N L3334-02 28 Nb-95 -2.30E+01 1.60E+01 7.30E+0O ONS-N 13334-02 28 Ru-103 1.40E+01 1.20E+01 4.20E+0O ONS-N L3334-02 28 Ru-106 -5.OOE+01 1.20E+02 4.60E+02 ONS-N L3334-02 28 Sb-124 6.50E+01 3.40E+01 9.SOE+0O ONS-N L3334-02 28 Sb-125 I.90E+01 2.80E+01 9.90E+0O ONS-N L3334-02 28 Se-75 4.OOE+00 1.30E+01 4.SOE+0O ONS-N L3334-02 28 Zn-65 O.OOE+O0 2.40E+01 9.70E+0O ONS-N L3334-02 28 Zr-95 -9.OOE+00 2.20E+01 9.10E+0O ONS-S L3334-03 28 AcTh-228 5.30E+01 4.OOE+01 1.40E+02 ONS-S L3334-03 28 Ag-108m 1.72E+01 9.70E+00 3.1OE+0O ONS-S L3334-03 28 Ag-1 10m -4.O0E+00 1.60E+01 6.70E+0O ONS-S L3334-03 28 Ba-140 -8.70E+01 4.60E+01 2.50E+02 ONS-S 12334-03 28 Be-7 1.30E+02 1.IOE+02 3.90E+02 ONS-S 12334-03 28 Ce-141 -1.90E+01 2.10E+01 7.90E+0I ONS-S L3334-03 28 Ce-14 6.50E+01 6.00E+01 2.OOE+02 ONS-S 12334-03 28 Co-57 8.10E+00 7.OOE+00 2.40E+0I ONS-S L3334-03 28 Co-58 4.OOE+00 1.40E+0 5.50E+0O ONS-S L3334-03 28 Co-60 4.OOE+00 1.20E+01 4.80E+01 ONS-S 12334-03 28 Cr-51 2.10E+02 I.SOE+02 S.IOE+02 ONS-S L3334-03 28 Cs-134 2.OOE+00 1.30E+01 4.90E+0I ONS-S L3334-03 28 Cs-137 4.90E+01 1.60E+01 4.60E+01 ONS-S L3334-03 28 Fe-59 7.OOE+00 4.40E+01 1.80E+02 ONS-S U3334-03 28 1-131 -2.90E+01 7.90E+01 3.10E+02 ONS-S L3334-03 28 K-40 2.88E+03 3.70E+02 5.60E+02 ONS-S 12334-03 28 La-140 -I.OOE+02 5.30E+01 2.80E+02 ONS-S 12334-03 28 Mn-54 O.OOE+OO 1.30E+O1 5.OOE+0I ONS-S L3334-03 28 Nb-95 1.80E+01 2.10E+01 7.30E+0O ONS-S L3334-03 28 Ru-103 -6.OOE+00 1.40E+OI 5.70E+0O ONS-S L3334-03 28 Ru-106 -I.OOE+01 l.OOE+02 4.OOE+02 ONS-S L3334-03 28 Sb-124 1.40E+01 3.10E+01 1.30E+02 ONS-S L3334-03 28 Sb-125 I.IOE+01 2.40E+01 8.80E+0O ONS-S L3334-03 28 Se-75 2.20E+01 1.40E+01 4.80E+0I ONS-S L3334-03 28 Zn-65 O.OOE+O0 3.00E+01 1.20E+02 ONS-S L3334-03 28 Zr-95 -1.90E+01 1.50E+01 7.80E+0I OFS-S L3334-04 28 Acil-228 -1.40E+01 3.60E+01 1.40E+02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-59

- s Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

OFS-S L3334-04 28 Ag-108m I.IOE+00 7.70E+00 2.80E+01 OFS-S L3334-04 28 Ag-I lOm -3.00E+00 1.40E+0O 5.40E+01 OFS-S L3334-04 28 Ba-140 5.90E+01 3.40E+01 1.IOE+02 OFS-S L3334-04 28 Be-7 5.80E+01 8.80E+0O 3.10E+02 OFS-S L3334-04 28 Ce-141 8.00E+00 1.90E+01 6.60E+01 OFS-S L3334-04 28 Ce-144 l.OOE+0 5.OOE+0l 1.802+02 OFS-S L3334-04 28 Co-57 4.40E+00 6.70E+00 2.30E+01 OFS-S L3334-04 28 Co-58 2.10E+00 9.50E+00 3.60E+01 OFS-S L3334-04 28 Co-60 -8.80E+00 9.50E+00 4.10E+01 OFS-S L3334-04 28 Cr-51 5.00E+01 1.20E+02 4.30E+02 OFS-S L3334-04 28 Cs-134 -1.90E+00 9.101E+00 3.60E+01 OFS-S L3334-04 28 Cs-137 -9.50E+00 9.90E+00 3.90E+01 OFS-S L3334-04 28 Fe-59 7.30E+01 3.10E+01 8.80E+01 OFS-S L3334-04 28 1-131 1.55E+02 7.40E+01 2.30E+02 OFS-S L3334-04 28 K-40 2.69E+03 2.80E+02 5.00E+02 OFS-S L3334-04 28 La-140 6.80E+01 3.90E+01 1.20E+02 OFS-S L3334-04 28 Mn-54 -1.70E+01 I.OOE+01 4.20E+01 OFS-S L3334-04 28 Nb-95 -3.00E+01 1.60E+01 6.60E+01 OFS-S L3334-04 28 Ru-103 4.00E+00 1.30E+01 4.60E+01 OFS-S L3334-04 28 Ru-106 -1.462+02 8.90E+01 3.70E+02 -

OFS-S L3334-04 28 Sb-124 -3.60E+01 2.60E+01 1.202+02 OFS-S L3334-04 28 Sb-125 -3.00E+00 2.30E+01 8.70E+01 OFS-S L3334-04 28 Se-75 -3.00E+00 1.30E+01 4.70E+01 OFS-S L3334-04 28 Zn-65 -6.80E+01 2.60E+01 l.tOE+02 OFS-S L3334-04 28 Zr-95 2.00E+00 1.70E+01 6.50E+01 OFS-N L3941-01 39 AcTh-228 4.30E+01 2.20E+O1 8.80E+01 OFS-N L3941-01 39 Ag-108m 2.30E+OO 5.I1OE+0 1.80E+01 OFS-N L3941-01 39 Ag-llOm 0.OOE+00 8.10E+OO 3.00E+01 OFS-N L3941-01 39 Ba-140 O.OOE+OO+ 1.40E+01 5.40E+01 OFS-N L3941-01 39 Be-7 -4.00E+OI1 5.80E+O1 2.10E+02 OFS-N L3941-01 39 Ce-141 -2.40E+OI 1.lOE+01 4.10E+01 OFS-N L3941 -01 39 Ce-144 -3.OOE+OO 3.30E+01 1.20E+02 OFS-N L3941-01 39 Co-57 -6.10E+OO 4.10E+00 1.50+01 OFS-N L3941-01 39 Co-58 -6.60E+OO 6.60E+OO 2.50E+01 OFS-N L3941-01 39 Co-60 1.022+01 7.20E+OO 2.40E+01 OFS-N L3941-01 39 Cr-51 -7.60E+01 7.20E+01 2.60E+02 OFS-N L3941-01 39 Cs-134 -3.10E+O0 7.10E+00 2.60E+01 OFS-N L3941-01 39 Cs- 13? -2.30E+OO 7.40E+00 2.60E+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-60

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

OFS-N L3941-01 39 Fe-59 -I.OOE+00 1.70E+01 6.00E+01 OFS-N L3941-01 39 1-131 -1.40E+01 3.20E+01 1.10+02 OFS-N L3941-01 39 K-40 3.17E+03 1.80E+02 2.10E+02 OFS-N L3941-01 39 La-140 0.OOE+00 1.60E+01 6.20E+01 OFS-N L3941-01 39 Mn-54 3.60E+00 6.00E+00 2.10E+01 OFS-N L3941-01 39 Nb-95 -9.1OE+00 8.90E+00 3.30E+01 OFS-N L3941-01 39 Ru-103 0.OOE+00 7.60E+00 2.70E+0O OFS-N L3941-01 39 Ru-106 -8.OOE+01 5.50E+01 2.1OE+02 OFS-N L3941-01 39 Sb-124 4.20E+01 1.70E+01 5.202+01 OFS-N U3941-01 39 Sb-125 -2.30E+01 1.SOE+01 5.70E+01 OFS-N L3941-01 39 Se-75 -2.10E+00 7.80E+00 2.70E+01 OFS-N U3941-01 39 Zn-65 8.00E+00 2.00E+01 6.90E+01 OFS-N L3941-01 39 Zr-95 -6.00E+00 I.IOE+01 4.20E+01 ONS-N L3941-02 39 AcTh-228 -8.IOE+01 2.302+01 I.OOE+02 ONS-N L3941-02 39 Ag-108m 4.60E+00 5.00E+00 1.70E+01 ONS-N L3941-02 39 Ag-lOrm -1.85E+01 8.80E+00 3.60E+01 ONS-N L3941-02 39 Ba-140 -6.002+00 1.60E+01 6.30E+01 ONS-N L3941-02 39 Be-7 -2.50E+01 6.20E+01 2.30E+02 ONS-N L3941-02 39 Ce-141 -4.OOE+00 I.IOE+01 3.90E+01 ONS-N L3941-02 39 Ce-144 4.70E+01 3.30E+01 I.IOE+02 ONS-N L3941-02 39 Co-57 -3.30E+00 4.30E+00 1.SOE+01 ONS-N L3941-02 39 Co-58 -2.1OE+00 6.90E+00 2.60E+01 ONS-N L3941-02 39 Co-60 -1.OOE+0O 6.70E+00 2.50E+01 ONS-N L3941-02 39 Cr-51 -4.SOE+01 7.80E+01 2.80E+02 ONS-N L3941-02 39 Cs-134 -3.OOE-01 6.20E+00 2.30E+01 ONS-N L3941-02 39 Cs-137 4.80E+00 7.00E+00 2.40E+0I ONS-N L3941-02 39 Fe-59 9.00E+00 1.60E+01 5.70E+01 ONS-N L3941-02 39 1-131 4.30E+01 3.40E+01 I.IOE+02 ONS-N L3941-02 39 K-40 2.87E+03 1.90E+02 2.90E+02 ONS-N L3941-02 39 La-140 -7.00E+00 1.80E+01 7.20E+01 ONS-N L3941-02 39 Mn-54 6.00E-01 5.502+00 2.00E+01 ONS-N L3941-02 39 Nb-95 -7.50E+00 9.00E+00 3.40E+01 ONS-N L3941-02 39 Ru-103 5.OOE+00 7.60E+00 2.60E+01 ONS-N L3941-02 39 Ru-106 -1.30E+01 6.50E+01 2.30E+02 ONS-N L3941-02 39 Sb-124 -1.30E+01 1.70E+01 7.00E+01 ONS-N L3941-02 39 Sb-125 -5.00+00 1.70E+01 6.10E+01 ONS-N L3941-02 39 Se-75 8.60E+00 6.80E+00 2.30E+01 ONS-N L3941-02 39 Zn-65 -4.30E+01 1.60E+01 6.70E+01 ONS-N L3941-02 39 Zr-95 -1.40E+01 1.40E+01 5.40E+01 ONS-S L3941-03 39 AcTh-228 5.00+01 3.80E+01 1.302+02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-61

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC

- (pCi/kg) (pCi/kg) (pCi/kg)

ONS-S L3941-03 39 Ag-108m -1.28E+01 6.80E+00 2.70E+0O ONS-S L3941-03 39 Ag-l lim 5.OOE+00 1.40E+01 4.80E+01 ONS-S L3941-03 39 Ba-140 -5.OOE+00 2.60E+01 1.OOE+02 ONS-S L3941-03 39 Bc-7 -5.40E+01 9.50E+01 3.50E+02 ONS-S L3941-03 39 Ce-141 1.50E+01 1.80E+01 6.20E+01 ONS-S L3941-03 39 Cc-144 -5.00E+0t 5.50E+01 1.90E+02 ONS-S L3941-03 39 Co-57 -1.68E+01 6.90E+00 2.50E+01 ONS-S L3941-03 39 Co-5& -1.52E+01 9.40E+00 3.80E+01 ONS-S L3941-03 39 Co-60 -2.00E+00 8.90E+00 3.40E+01 ONS-S L3941-03 39 Cr-51 -5.00E+0O I.1OE+02 3.80E+02 ONS-S L3941-03 39 Cs-134 I.OOE+01 I.OOE+0O 3.40E+01 ONS-S L3941-03 39 Cs-137 3.40E+01 1.30E+01 3.90E+01 ONS-S L3941-03 39 Fe-59 -5.00E+00 2.30E+0l 8.50E+01 ONS-S L3941-03 39 1-131 -2.60E+01 4.50E+01 1.60E+02 ONS-S L3941-03 39 K-40 2.88E+03 2.40E3+02 3.80E+02 ONS-S L3941-03 39 La-140 -6.OOE+00 2.90E+01 1.20E+02 ONS-S L3941-03 39 Mn-54 9.90E+00 9.00E+00 3.10E+0l -

ONS-S L3941-03 39 Nb-95 2.20E+0O 1.90E+01 6.60E+01 ONS-S L3941-03 39 Ru-103 -1.10+01 l.lOE+0I 4.10E+01 ONS-S L3941-03 39 Ru-106 4.00E+01 7.90E+01 2.80E+02 ONS-S L3941-03 39 Sb-124 -1.60E+01 2.30E+01 9.60E+01 ONS-S . L3941-03 39 Sb-125 5.00E+00 2.20E+01 7.70E+01 ONS.S L3941-03 39 Se-75 -1.20E+01 1.20E+01 4.40E+01 ONS-S L3941-03 39 Zni-65 3.00E+00 3.60E+01 1.30E+02 ONS-S L3941-03 39 Zr-95 -2.60E+01 1.90E+01 7.30E+01 OFS-S L3941-04 39 Acnh-228 -2.20E+01 3.20E+01 1.30E+02 OFS-S L3941-04 39 Ag-108m -1.30E+01 7.30E+00 2.90E+01 OFS-S L3941-04 39 Ag-lOnm 1.90E+01 1.30E+01 4.30E+01 OFS-S L3941-04 39 Ba-140 -1.40E+01 3.10E+01 1.30E+02 OFS-S L3941-04 39 Be-7 -9.60E+01 8.10E+01 3.20E+02 OFS-S L3941-04 39 Ce-141 3.00E+00 1.30E+01 4.70E+01 OFS-S L3941-04 39 Cc-144 -2.90E+01 4.00E+01 1.40E+02 OFS-S L3941-04 39 Co-57 2.30E+00 5.00E+00 1.70E+01 OFS-S L3941-04 39 Co-58 -1.35E+01 9.40E+00 3.90E+01 OFS-S L3941-04 39 Co-60 1.80E+01 1.30E+01 4.20E+01 OFS-S L3941-04 39 Cr-51 2.00E+02 I.OOE+02 3.40E+02 OFS-S L3941-04 39 Cs-134 -1.1IE+0 9.60E1+00 3.90E+0 OFS-S L3941-04 39 Cs-137 0.00+00 1.10+01 3.90E+01 OFS-S L3941-04 39 Fe-59 0.OOE+00 2.20E+01 8.302+01 OFS-S L3941-04 39 1-131 1.00+01 5.00E+01 1.80E+02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-62

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

OFS-S L3941-04 39 K-40 2.72E+03 2.60E+02 4.1OE+02 OFS-S L3941-04 39 La-140 -1.70E+01 3.50E+01 1.40E+02 OFS-S L3941-04 39 Mn-54 -1.17E+01 8.80E+00 3.60E+01 OFS-S L3941-04 39 Nb-95 -2.70E+01 1.30E+01 5.50E+0O OFS-S L3941-04 39 Ru-103 1.OOE+01 1.1OE+01 3.70E+01 OFS-S L3941-04 39 Ru-106 1.30E+01 8.80E+01 3.20E+02 OFS-S L3941-04 39 Sb-124 -3.40E+01 2.70E+01 1.20E+02 OFS-S 12941-04 39 Sb-125 1.1OE+0O 2.30E+01 8.10E+01 OFS-S L3941-04 39 Se-75 -4.00E+00 l.OOE+01 3.60E+01 OFS-S L3941-04 39 Zn-65 6.OOE+00 4.40E+01 1.60E+02 OFS-S L3941-04 39 Zr-95 1.90E+0O 1.50E+01 5.20E+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-63

Indiana Michigan Power Co., DC Cook Nuclear Plant I Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

SE SL-2 L2602-01 15 Acnh-228 8.30E+01 1.60E+01 6.10E+01 SL-2 L2602-O1 15 Ag-108m -1.I1OE+00 3.OOE+00 1.IOE+01 SL-2 L2602-01 15 Ag-lOrm 2.40E+00 5.40E+00 2.00E+01 SL-2 L2602-01 15 Ba-140 5.001+00 1.70E+01 6.00E+01 SL-2 L2602-01 15 Be-7 1.10+02 4.10E+01 1.30E+02 SL-2 L2602-01 15 Ce-141 -9.80E+00 6.30E+00 2.30E+01 SL-2 L2602-01 15 Cc-144 5.10E+01 4.70E+0O 1.50E+02 SL-2 L2602-01 15 Co-57 3.50E+00 3.40E+00 1.OE+01 SL-2 L2602-01 15 Co-S8 -1.SOE+00 3.80E+00 1.40E+01 SL-2 L2602-01 15 Co-60 -5.SOE+OO 4.40E+00 1.808+01 SL-2 L2602-01 15 Cr-SI 2.30E+01 3.50E+01 1.20E+02 S-2 L2602-01 15 Cs-134 -4.00E+01 2.20E+01 7.40E+01 SL-2 L2602-01 15 Cs-137 8.50E+00 4.60E+00 1.50E+01 SL-2 L2602-01 15 Fe-59 9.00EOE0 1.40E+01 4.90E+01 SL-2 L2602-01 15 1-131 -8. 1OE+00 5.80E+00 2.30E+01 SL-2 L2602-01 15 K-40 6.67E+03 2.30E+02 1.80E+02 SL-2 L2602-01 15 La-140 1.31E+0O 8.80E+00 2.90E+01 SL2 L2602-01 15 Mn-54 1.60E+00 4.10E+00 1.508+01 SL-2 L2602-01 15 Nb-95 -1.528+01 4.60E+00 2.00E+01 SL-2 L2602-01 15 Ru-103 4.80E+00 3.50E+00 1.208+01 SL-2 L2602-01 15 Ru-106 1.50E+01 3.50E+01 1.30E+02 SL-2 L2602-01 15 Sb-124 -2.10E+00 5.40E+00 2.50E+01 SL-2 L2602-01 15 Sb-125 -3.50E+00 9.30E+00 3.40E+01 SL-2 L2602-01 15 Se-75 6.50E+00 4.80E+00 1.60E+01 SL-2 L2602-01 15 Zn-65 -4.008+00 1.40E+01 5.108+01 SL-2 L2602-01 15 Zr-95 -1.SOE+00 8.20E+00 3.00E+01 SL3 L2602:02 15 AcTh-228 8.60E+01 3.50E+01 1.108+02 SW3 L2602-02 15 Ag-108m- 5.10E+00 4.50E+00 1.50E+01 SL3 L2602-02 15 Ag-llOm -1.20E+01 1.OOE+01 4.008+01 SL3 L2602-02 15 Ba-140 1.30E+01 2.70E+01 9.80E+01 SL3 L2602-02 15 Be-7 5.90E+01 4.80E+01 1.608+02 SL3 L2602-02 15 Ce-141 4.00E+00 8.20E+00 2.80E+01 SL3 L2602-02 15 Ce-144 2.OOE+01 3.30E+01 1.10E+02 S-3 L2602-02 15 Co-57 -1.90E+00 4.00E+00 1.408+01 SL3 L2602-02 15 Co-58 -4.60E+00 5.80E+00 2.30E+01 SL3 L2602-02 15 Co-60 5.50E+00 8.20E+00 3.00E+01 SW3 L2602-02 15 Cr-51 -4.80E+0O 4.20E+01 1.60E+02 SL3 L2602-02 15 Cs-134 -1.30E+00 4.908+00 1.90E+01 SW3 L2602-02 15 Cs-137 2.90E+00 5.60E+00 2.00E+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-64

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

SL-3 L2602-02 15 Fe-59 2.20E+O1 2.10E+01 7.IOE+0O SL-3 L2602-02 15 1-131 -l.IOE+O0 8.80E+00 3.20E+01 SLW3 L2602-02 15 K-40 6.98E+03 3.30E+02 2.80E+02 SL-3 L2602-02 15 La-140 -8.OOE+00 1.40E+01 S.SOE+01 SL-3 L2602-02 15 Mn-54 -6.10E+O0 S.80E+00 2.30E+01 SL-3 L2602-02 15 Nb-95 l .lOE+O0 6.80E+00 2.50E+O1 SLW3 L2602-02 15 Ru-103 7.40E+O0 5.IOE+00 1.70E+0O SL-3 L2602-02 15 Ru-106 -1.08E+02 4.90E+01 2.10E+02 SL-3 L2602-02 15 Sb-124 -4.OOE+O0 I.IOE+OI 1.90E+02 SL-3 L2602-02 15 Sb-125 2.30E+O1 1.50E+01 5.OOE+01 SLW3 L2602-02 15 Se-75 2.60E+OO 7.10E+00 2.50E+01 SL3 L2602-02 15 Zn-65 -2.1OE+O1 1.60E+01 6.40E+O1 SL-3 L2602-02 15 Zr-95 6.OOE+00 l.IOE+01 3.90E+O1 SL2 L4055-01 41 Aclh-228 6.30E+01 3.20E+01 I.OOE+02 SL-2 L4055-01 41 Ag-108m -7.70E+00 4.30E+00 1.80E+01 SL2 L4055-01 41 Ag-lOrm -3.10E+00 8.70E+00 3.40E+01 SL2 L4055-01 41 Ba-140 7.OOE+00 5.OOE+01 1.80E+02 SL-2 LU55-01 41 Be-7 1.S1E+02 5.20E+01 1.50E+02 SL-2 L4055-01 41 Ce-141 I.OOE+O0 I.IOE+01 3.80E+O1 SL-2 L4055-01 41 Ce-144 7.OOE+00 3.30E+0O I.IOE+02 SL.2 UA055-01 41 Co-57 2.60E+00 4.20E+O0 -. SOE+O1 SL-2 U4055-01 41 Co-58 -1.21E+01 6.OOE+00 2.60E+OI SL-2 UAO55-01 41 Co-60 3.20E+00 6.60E+00 2.40E+O1 SL-2 UA055-01 41 Cr-51 -5.70E+01 6.IOE+01 2.30E+02 SL-2 LU055-01 41 Cs-134 -1.60E+O0 5.20E+00 2.OOE+O1 SL-2 UO0S-01 41 Cs-137 7.90E+00 6.90E+00 2.40E+O1 SL-2 L4055-01 41 Fe-59 -3.OOE+01 1.70E+01 7.20E+O1 SL-2 L4055-01 41 1-131 3.80E+01 2.30E+01 7.70E+O1 SL-2 L4055-01 41 K-40 5.93E+03 3.10E+02 2.1OE+02 SL-2 UO055-01 41 La-140 -4.OOE+00 2.20E+01 8.30E+01 SL2- 14055-01 41 Mn-54 I.OOE-01 5.70E+00 2.20E+01 SL-2 14055-01 41 Nb-95 -1.59E+01 8.10E+00 3.40E+01 SL-2 LA055-01 41 Ru-103 3.OOE+O0 5.SOE+00 2.OOE+O1 SL-2 UA055-01 41 Ru-106 8.OOE+01 4.SOE+01 1.40E+02 SL-2 UA055-01 41 Sb-124 2.30E+01 I.OOE+01 1.30E+01 SL-2 UA055-01 41 Sb-125 I.OOE+O0 1.40E+01 5.1OE+01 SL-2 UA055-01 41 Se-75 7.IOE+00 7.10E+00 2.40E+0I SL-2 UA055-01 41 Zn-65 1.60E+01 1.80E+01 6.20E+0O

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-65

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC

- (pCi/kg) (pCi/kg) (pCi/kg)

SL-2 L4055-01 41 Zr-95 -1.20E+01 9.50E+00 4.10E+01 SL-3 L4055-02 41 AcTh-228 8.10E+01 2.80E+01 8.40E+O1 SL-3 L4055-02 41 Ag-108m 7.40E+00 4.00E+00 1.30E+O1 SL-3 L4055-02 41 Ag-llOm 4.101E+00 5.60E+00 2.00E+01 SLW3 L4055-02 41 Ba-140 -1.70E+01 3.60E+01 1.40E+02 SL-3 L4055-02 41 Be-7 -2.50E+01 3.40E+01 1.30E+02 SL-3 L4055-02 41 Ce-141 1.80E+01 1.OOE+01 3.30E+01 SL-3 L4055-02 41 Ce-144 -2.50E+01 2.90E+0l 1.lOE+02 SL-3 L4055-02 41 Co-57 7.30E+00 4.OOE+00 1.30E+01 SL-3 L4055-02 41 Co-58 -1.90E+00 4.90E+00 1.90E+01 SL-3 L4055-02 41 Co-60 .9.OOE-01 6.00E+00 2.30E+01 -

SL-3 L4055-02 41 Cr-51 3.40E+01 4.70E+0O 1.60E+02 SL-3 L4055-02 41 Cs-134 -5.40E+00 3.90E+00 1.60E+01 SL-3 L4055-02 41 Cs-137 5.OOE-01 S.1OE+00 1.90E+01 SL-3 L4055-02 41 Fe-59 1.70E+01 1.30E+01 4.30E+01 SL-3 L4055-02 41 1-131 2.30E+01 1.80E+01 6.20E+01 SL3 L4055-02 41 K-40 6.63E+03 2.60E+02 9.20E+01 SL-3 L4055-02 41 La-140 O.OOE+00 1.80E+01 6.70E+01 SL3 L4055-02 41 Mn-54 -1.40E+00 3.80E+00 1.50E+O1 SL-3 L4055-02 41 Nb-95 -1.60E+0l 5.20E+00 2.40E+01 SL-3 L4055-02 41 Ru-103 1.50E+00 4.20E1+00 1.50E+0O SL-3 L4055-02 41 Ru-106 7.80E+01 4.20E+01 1.40E+02 SLW3 L4055-02 41 Sb-124 Q.OOE+00 4.30E+00 2.20E+01 SL-3 L4055-02 41 Sb-125 -1.20E+0O 1.20E+01 4.50E+01 SL-3 L4055-02 41 Se-75 -5.OOE-01 5.00E+00 1.80E+01 SL-3 L4055-02 41 Zn-65 2.00E+00 I.20E+0O 4.50E+0l SLW3 L4055-02 41 Zr-95 -1.OOE+01 l.IOE+0l 4.1OE+0O -O

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-66

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC.

(pCi/kg) (pCi/kg) (pCi/kg)

TM GTF L2085-01 03 AcTh-228 -2.80E+00 7.40E+00 2.80E+0O GTF L2085-01 03 Ag-108m -1.70E+00 1.30E+00 5.10E+00 GTF L2085-01 03 Ag-i lOm l.50E+00 2.60E+00 9.20E+00 GTF L2085-01 03 Ba-140 -6.OOE-01 2.50E+00 I.OOE+0O GTF L2085-01 03 Be-7 -4.OOE+00 1.30E+01 4.80E+0O GTF L208541 03 Cc-141 3.20E+00 2.70E+00 9.OOE+00 GTF L2085-01 03 Ce-144 -7.00E+00 I.OOE+01 3.60E+0O GTF L2085-01 03 Co-57 -8.OOE-01 1.20E+00 4.40E+00 GTF L2085-01 03 Co-58 3.50E+00 1.90E+00 6.IOE+00 GTF L2085-01 03 Co-60 -3.30E+00 2.40E+00 9.70E+00 GTF L2085-01 03 Cr-SI -I.1OE+0 1.70E+01 6.1OE+01 GTF L2085-01 03 Cs-134 9.00E-01 2.00E+00 7.OOE+00 GTF L2085-01 03 Cs-137 -1.30E+00 2.OOE+00 7.40E+00.

GTF L2085-01 03 Fe-59 3.90E+00 6.40E+00 2.30E+OI GTF L2085-01 03 1-131 -1.47E-01 9.00E-02 6.90E41-GTF L2085-01 03 K-40 1.26E+03 7.30E+01 8.50E+I0

• GTF L2085-01 - 03 La-140 -7.OOE-01 2.80E+00 1.20E+01 GTF L2085-01 03 Mn-54 0.OOE+00 2.00E+00 7.20E+00 GTF L2085-01 03 Nb-95 1.60E+00 1.80E+00 6.30E+00 GTF L2085-01 03 Ru-103 -9.OOE-01 1.60E+00 6.20E+00 GTF L2085-01 03 Ru-106 -5.OOE+00 1.70E+01 6.IOE+OI GTF L2085-01 03 Sb-124 O.OOE+00 4.20E+00 1.70E+OI GIT L2085-01 03 Sb-125 4.20E+00 4.OOE+00 1.40E+01 GTF L2085-01 03 Se-75 0.OOE+00 2.10E+00 7.SOE+00 GTF L2085-01 03 Zn-65 -8.60E+00 4.30E+00 1.80E+0O GTF L2085-01 03 Zr-95 -3.70E+00 2.80E+00 1.20E+01 MR L2085-02 03 AcTh-228 2.20E+01 7.40E+00 2.10E+01 MR L2085-02 03 Ag-108m O.OOE+00 1.30E+00 4.70E+00 MR L2085-02 03 Ag-I lOm 2.70E+00 2.30E+00 7.90E+00 MR L2085-02 03 Ba-140 5.OOE+00 2.SOE+00 7.50E+00 MR L2085-02 03 Be-7 -3.OOE+00 1.40E+01 5.30E+01 MR L2085-02 03 Ce-141 -2.70E+00 2.70E+00 9.60E+00 MR L2085-02 03 Ce-144 -4.00E-01 9.80E+00 3.40E+0O MR L2085-02 03 Co-57 -1.IOE+00 1.30E+00 4.60E+O0 MR L2085-02 03 Co-58 1.IOE+00 1.80E+00 6.50E+00 MR L2085-02 03 Co-60 2.00E-01 2.OOE+00 7.70E+00 MR L208S-02 03 Cr-SI 1.90E+01 1.60E+01 5.40E+01 MR L2085-02 03 Cs-134 2.OOE-01 1.80E+00 6.60E+00 MR L2085-02 03 Cs-137 2.80E+00 1.60E+00 5.IOE+00 Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-67

Indiana Michigan Power Co., DC Cook Nuclear Plant _J Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC

' (pCi/kg) (pCi/kg) (pCi/kg)

MR L2085-02 03 Fe-59 2.30E+00 7.OOE+00 2.50E+01 MR L2085-02 03 1-131 2.90E-01 2.OOE-0l 6.10E-01 MR L2085-02 03 K-40 2.06E+03 9.20E+01 9.70E+0I

• MR L2085-02 03 La 140 5.80E+00 2.90E+00 8.70E+00 MR L2085-02 03 Mn-54 -1.80E+00 1.80E+00 6.90E+00 MR L2085-02 03 Nb-95 -2.70E+00 1.80E+00 7.20E+00 MR L2085-02 03 Ru-103 -2.20E+00 1.70E+00 6.70E+00 MR L2085-02 03 Ru-106 -3.OOE+00 I.90E+01 6.80E+01 MR L2085-02 03 Sb-124 5.20E+00 4.OOE+00 1.40E+01 MR L2085-02 03 Sb-12S -5.OOE-01 4.20E+00 l.50E+Ol MR L2085-02 03 Se-75 -7.OOE-01 2.30E+00 8.20E+00 MR L2085-02 03 Zn-65 -1.12E+01 4.20E+00 1.80E+01 MR L2085-02 03 Zr-95 -5.30E+00 3.30E+00 1.30E+01 SF L2085-03 03 AcTh-228 -4.30E+00 4.60E+00 1.80E+01 SF L2085-03 03 Ag-108m l.OOE-01 I.OOE+00 3.70E+00 SF L2085-03 03 Ag-llOm -8.OOE-01 1.80E+00 6.70E+00 SF L2085-03 03 Ba-140 -2.30E+00 1.90E+00 7.80E+00 SP L2085-03 03 Be-7 -2.OOE+00 1.1OE+01 3.80E+0O SF L2085-3 03 Ce-141 -2.90E+00 2.OOE+00 7.10E+00 SF L2085-03 03 Ce-144 6.80E+00 8.OOE+00 2.70E+0O SF L2085-03 03 Co-57 2.OOE-01 1.1OE+00 3.70E+00 SF L2085-03 03 Co-58 1.50E+00 1.20E+00 4.OOE+00 SF L2085-03 03 Co-60 -2.70E+O0 I.50E+00 6.OOE+00 SF L2085-03 03 Cr-51 5.OOE+00 1.20E+01 4.20E+01 SF L2085-03 03 Cs-134 6.OOE-01 1.30E+00 4.60E+00 SF L2085-03 03 Cs-137 1.30E+00 1.40E+00 4.60E+00 SF L2085-03 03 Fe-59 -6.60E+00 4.OOE+00 1.60E+OI SF L2085-03 03 1-131 -1.22E-01 9.OOE-02 5.60E-01 SF L2085-03 03 K-40 1.36E+03 5.40E+01 5.30E+01 SF L2085-03 03 La-140 -2.60E+00 2.20E+00 9.OOE+00 SF L2085-03 03 Mn-54 -1.30E+00 1.20E+00 4.50E+00 SF L2085-03 03 Nb-95 -1.70E+00 1.30E+00 4.90E+00 SF L2085-03 03 Ru-103 -8.OOE-01 1.30E+00 4.70E+00 SF L2085-03 03 Ru-106 -2.20E+01 1.20E+01 4.60E+OI SF L2085-03 03 Sb-124 -5.80E+00 2.50E+00 1.20E+0O SF L2085-03 03 Sb-125 1.90E+00 3.10E+00 I.IOE+0O SF L2085-03 03 Sc-75 -2.OOE-01 1.60E+00 5.80E+00 SF L2085-03 03 Zn-65 -1.80E+00 2.80E+00 I.OOE+01 SF L2085-03 03 Zr-95 2.60E+00 2.10E+00 6.90E+00 LP L2085-04 03 Aclh-228 -2.10E+00 4.80E+00 1.80E+0l

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-68

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCilkg) (pCi/kg)

LF L2085-04 03 Ag-108m -2.20E+00 9.90E-01 3.90E+00 LF L2085-04 03 Ag- lOim -8.OOE-01 1.70E+00 6.30E+00 LF L2085-04 03 Ba-140 3.OOE-01 1.70E+00 6.30E+00 LF L2085-04 03 Be-7 3.OOE+OO 1.OOE+01 3.60E+0O LF L2085-04 03 Ce-141 -3.60E+00 2.20E+C0 7.90E+CO LF L2085-04 03 Ce-14 -6.1OE+00 8.10E+00 2.90E+0I LF L2085-04 03 Co-57 -7.OOE-0I I.IOE+00 3.70E+00 LF L2085-04 03 Co-58 -2.70E+00 1.40E+00 5.40E+00 LF L2085-04 03 Co-60 4.OOE-01 1.20E+00 4.40E+00 LF L2085-04 03 Cr-SI -1.70E+01 I.IOE+01 4.OOE+0O LF L2085-04 03 Cs-134 -3.OOE-0I 1.SOE+00 5.40E+00 LF L2085-04 03 Cs-137 1.70E+00 1.40E+00 4.70E3+00 LF L2085-04 03 Fe-59 -2.70E+00 3.70E+00 1.40E+01 LF L2085-04 03 1-131 4.00E-02 I.IOE-0I 4.90E-0O LF L2085-04 03 K-40 1.45E+03 S.50E+0I 5.70E+01 LF L2085-04 03 La-140 4.OOE-00 1 .90E+00 7.20E+00 LF L2085-04 03 Mn-54 -7.OOE-01 1.40E+00 5.OOE+00 LF L2085-04 03 Nb-95 -2.OOE-01 1.40E+00 5.OOE+00 LF L2085-04 03 Ru-103 -1.30E+00 1.30E+00 4.70E+00 LF L2085-04 03 Ru-106 -4.OOE+00 1.20E+01 4.40E+01 LF L2085-04 03 Sb-124 1.40E+00 2.90E+00 I.IOE+01 LF L2085-04 03 Sb-125 O.OOE+00 3.OOE+00 1.1OE+01 LF L2085-04 03 Se-75 2.20E+00 1.90E+00 6.20E+00 LF L2085-04 03 Zn-65 -4.50E+00 3.80E+00 1.40E+0O LF L2085-04 03 Zr-95 -2.OOE-01 2.OOE+00 7.20E+00 WF L2085-05 03 AcTh-228 -3.OOE+00 4.20E+00 1.60E+01 WF L2085405 03 Ag-108m -8.50E-01 9.80E-01 3.60E+00 WF L2085-05 03 Ag-I lOm -2.OOE-01 1.50E+00 5.40E+0O WF L2085-05 03 Ba-140 -2.50E+00 1.40E+00 6.30E+00 WF L2085-05 03 Be-7 -7.80E+00 8.90E+00 3.30E+01 WF L2085-05 03 Ce-141 -8.OOE-01 1.90E+00 6.70E+00 WF L2085-05 03 CC-14 1.12E+01 7.20E+00 2.40E+0O WF L2085-05 03 Co-57 -7.90E-01 9.30E-01 3.30E+00 WF L2085-05 03 Co-S8 4.OOE-01 I.IOE+00 3.80E+00 WF L2085-05 03 Co-60 1.70E+00 1.20E+00 4.20E+00 WF L2085-05 03 Cr-51 -1.OOE+01 1.20E+01 4.1OE+OI WF L2085-05 03 Cs-134 -I.OOE+00 1.20E+00 4.50E+00 WF L2085-05 03 Cs-137 O.OOE+OO 1.40E+00 4.80E+OO WF L2085-05 03 Fe-59 1.OOE-0O 3.5OE+00 1.30E+O1 WF L2085-05 03 1-131 5.OOE-02 1.30E-01 5.60E-01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-69

Indiana Michigan Power Co., DC Cook Nuclear Plant J Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

WF L2085-05 03 K-40 1.38E+03 5.30E+01 5.502+01

• WF L2085-05 03 La-140 -2.80E+00 1.60E+00 7.20E+00 WF L2085 03 Mn-54 -4.00E-01 I.lOE+00 4.IOE+00 WF L2085-05 03 Nb-9S 2.00E-0l 1.20E+00 4.20E+00 -

WF L2085-05 03 Ru-103 -.OOE-01 1.20E+O0 4.101E+OO WF L2085-05 03 Ru-106 -1.OOE+01 I.1OE-,.0 4.10E+01 WF L2085-05 03 Sb-124 -1.00+00 2.50E+00 9.80E+00 WP L2085-05 03 Sb-12S 9.OOE-01 2.80E+00 9.70E+00 WP L2085-05 03 Se-7S I.50E+00 1.40E+00 4.60E+00 WF L2085-05 03 Zn-65 -3.30E+00 2.60E+00 1.00E+01 WF L2085-05 03 Zr-95 -7.OOE-0O 1.80E+00 6.90E+00 GTP L2162-01 05 AcTh-228 2.20E+00 5.30E+00 1.80E+01 GTP L2162-01 05 Ag-108m 5.IOE-01 9.40E-01 3.20E+00 GTF L2162-01 05 Ag-l1lm. 8.00E-01 1.80E+00 6.40E+00 GTP L2162-01 05 Ba-140 -I.OOE-01 2.10E+00 7.90E+00 GTF L2162-01 05 Be-7 1.60E+01 I.IOE+0O 3.80E+01 GTF L2162-01 05 Ce-141 -6.OOE+00 2.70E+00 9.40E+00 GTF L2162-01 05 Ce-144 9.70E+00 9.102+00 3.OOE+01 GTF L2162-01 05 Co-57 -8.00E-01 1.20E+00 4.102+00 GTF L2162-01 05 Co-58 1.60E+00 1.30E+00 4.40E+00 GTF L2162-01 05 Co-60 8.00E-01 1.30E+00 4.60E+00 GTF L2162-01 05 Cr-SI -1.40E+01 1.30E+01 4.70E+01 GTF L2162-01 05 Cs-134 4.00E401 1.30E+00 4.50E+00 GTF L2162-01 05 Cs-137 I.IOE+00 1.30E+00 4.40E+00 GTF L2162-01 05 Fe-59 -2.80E+00 3.90E+00 1.50E+01 GTF L2162-01 05 1-131 3.50E-01 1.70E-01 4.90E-01 GTF L2162-01 05 K-40 1.44E+03 5.20E+01 6.20E+01 L2162-01 05 La-140 -2.OOE-01 2.40E+00 9.1OE+00 GTF GTP L2162-01 05 Mn-54 1.30E+00 1.20E+00 4.20E+00 GTF L2162-01 05 Nb-95 -1.OOE-01 1.40E+00 5.10E+00 GTP L2162-01 05 Ru-103 -1.70E+00 1.50E+00 5.30E+00 GTF L2162-01 05 Ru-106 -9.OOE+00 1.00+01 3.70E+01 GTF L2162-01 05 Sb-124 -7.OOE-01 2.70E+00 1.00E+01 GTF L2162-01 05 Sb-125 5.70E+00 2.80E+00 9.20E+00 GTF L2162-01 05 Se-75 -3.OOE+00 1.70E+00 6.10E+00 L2162-01 05 Zn-65 -5.60E+00 2.80E+00 1.10E+01 GTF L2162-01 05 Zr-95 2.00E-01 2.10E+00 7.50E+00 MR L2162-02 05 AcTh-228 -4.30E+00 5.60E+00 2.10E+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-70

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Sumrnmary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

MR L2162-02 05 Ag-108m 11.OOE+00 1.10+00 3.60E+00 MR L2162-02 05 Ag-l lOm -3.40E+00 1.80E+00 7.20E+00 MR L2162-02 05 Ba-140 -3.40E+00 2.1OE+O0 9.OOE+00 MR L2162-02 05 Be-7 -1.30E+01 1.10+01 4.20E+01 MR L2162-02 05 Ce-141 -2. IOE+00 2.50E+00 8.70E+00 MR L2162-02 05 Ce-144 -8.40E+00 8.60E+00 3.OOE+01 MR L2162-02 05 Co-57 -9.OOE-01 1.1OE+00 3.90E+00 MR L2162-02 05 Co-58 -2.00E+00 1.50E+00 5.70E+00 MR L2162-02 05 Co-60 1.302+00 1.50E+00 5.30E+00 MR L2162-02 05 Cr-SI -9.00E+00 1.40E+01 5.00E+01 MR L2162-02 05 Cs-134 5.OOE-01 1.30E+00 4.50E+00 MR L2162-02 05 Cs-137 3.60E+00 1.50E+00 4.70E+00 MR L2162-02 05 FC-59 3.20E+00 4.60E+00 1.60E+01 MR L2162-02 05 1-131 6.40E-01 3.30E-01 9.20E-01 MR L2162-02 05 K-40 1.93E+03 6.40E+0l 5.80E+01 MR L2162-02 05 La-140 -3.90E+00 2.40E+00 1.00E+01 MR L2162-02 05 Mn-54 -3.00E-01 1.20E+00 4.50E+00 MR L2162-02 05 Nb-95 -6.00E-01 1.60E+00 5.90E+00 MR L2162-02 05 Ru-103 l.OOE-01 1.40E+O0 4.90E+00 MR L2162-02 05 Ru-106 -8.00E+00 1.40E+01 4.90E+01 MR L2162-02 05 Sb-124 -3.40E+00 2.40E+OO 1.10E+01 MR L2162-02 05 Sb-125 2.50E+00 3.60E+OO 1.20E+01 MR L2162-02 05 Se-75 0.00+00 1.80E+00 6.20E+00 MR L2162402 05 Zn-6S 4.00E-01 3.40E+00 1.20E+01 MR L2162-02 05 Zr-95 1.OOE+00 2.50E+00 8.60E+00 SF L2162-03 05 AcTh-228 -5.30E+00 4.20E+OO 1.60E+01 SF L2162-03 05 Ag-108m I.IOE+OO I.OOE+OO 3.50E+00 SF L2162-03 05 Ag-l lm -1.20E+00 1.80E+OO 6.80E+00 SF L2162-03 05 Ba-140 0.00+00 1.80E+00 7.1OE+OO SF L2162-03 05 Be-7 8.002E+0 1.IOE+01 3.70E+0O SF L2162-03 05 Cc-141 -1.20E+00 2.40E+OO 8.50E+00 SF L2162-03 05 Cc-144 -7.30E+00 8.50E+00 3.00E+01 SF L2162-03 05 Co-57 -I.OOE+00 1.IOE+0O 3.80E+00 SF L2162-03 05 Co-58 -4.20E+00 1.30E+00 5.502+00 SF L2162-03 05 Co-60 -2.00E-01 1.40E+OO 5.102+00 SF L2162-03 05 Cr-SI 2.00E+00 1.40E+0O 4.70E+01 SF L2162-03 05 Cs-134 O.OOE+00( 1.40E+00 5.10E+00 SF L2162-03 05 Cs-137 9.00E-01 1.10+00 3.902+00 SF L2162-03 05 Fe.59 3.70E+00 4.10+00 1.40E+01 SF L2162-03 05 1-131 2.40E-01 1.50E-01 4.80E-01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-71

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data J

Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

SF L2162-03 05 K-40 1.46E+03 5.60E+01 6.00E+OI SF L2162-03 05 La-140 0.00+00 2.10E+00 8.20E+00 SF L2162-03 05 Mn-54 2.40E+00 1.20E+00 4.OOE+00 SF L2162-03 05 Nb-95 -4.00E-01 1.40E+00 5.00E+00 SF L2162-03 05 Ru-103 -8.OOE-O1 1.40E+00 5.OOE+00 SF L2162-03 05 Ru-106 1.OOE+00 1.10+01 4.00E+01 SP L2162-03 05 Sb-124 -2.80E+00 2.60E+00 1.IOE+01 SF L2162-03 05 Sb-125 -4.30E+OO 2.90E+00 I.IOE+01 SF L2162-03 05 Se-75 5.00E-01 1.70E+00 6.OOE+00 SF L2162-03 05 Zn-65 l.OOE-01 4.30E+00 1.50E+0I SF L2162-03 05 Zr-95 -8.00E-0O 2.20E+00 8.10E+00 --. O LF L2162-04 05 AcTh-228 6.00E-01 4.30E+00 1.60E+01 LF L2162-04 05 Ag-108m 3.80E-01 9.10E-01 3.20E+00 LF L2162-04 05 Ag-I lOm -1.80E+00 1.70E+00 6.40E+00 LF L2162-04 05 Ba-140 5.40E+00 2.10E+00 6.10E+00 LF L2162-04 05 Be-7 -2.00E+00 1.OOE+01 3.60E+01 LF L2162-04. 05 Ce-141 4.70E+00 2.20E+00 7.00E+00 LF L2162-04 05 Ce-144 1.29E+01 7.50E+00 2.50E+01 LF L2162-04 05 Co-57 6.OOE-01 l.OOE+00 3.40E+00 LF L2162-04 05 Co-58 1.00+00 1.20E+00 4.20E+00 LF L2162-04 05 Co-60 -I.OOE-01 1.20E+00 4.60E+00 LF L2162-04 05 Cr-51 1.70E+01 1.20E+01 3.80E+01 LF L2162-04 05 Cs-134 2.20E+00 1.202+00 3.80E+00 LF L2162-04 05 Cs-137 l.00-01 1.20£+00 4.3013+00 LF L2162-04 05 Fe-59 -1.70E+00 4.00E+00 1.502+01 LF L2162-04 05 1-131 3.00E-02 l.OOE-0I 4.50E-01 LF L2162-04 05 K-40 1.45E3+03 5.40E+01 5.90E+01 LF L2162-04 05 La-140 6.20E+00 2.402+00 7.002+00 LF L2162-04 05 Mn-S4 -1.60E+00 1.20E+00 4.50E+00 LF L2162-04 05 Nb-95 -3.OOE-0I 1.30E+00 4.80E+00 LF L2162-04 05 Ru-103 -3.40E+00 1.302+00 5.102+00 LF L2162-04 05 Ru-106 -8.30E+00 9.80E+00 3.702+01 LF L2162-04 05 Sb-124 5.00E-01 2.50E+00 9.40E+00 LF L2162-04 05 Sb-125 -9.OOE-01 2.802+00 1.00E+01 LF L2162-04 05 Sc-75 9.OOE-01 1.40E+00 4.70E+00 LF L2162-04 05 Zn-65 -1.70E+00 2.80E+00 I.OOE+01 LF L2162-04 05 Zr-95 1.80E+OO 1.90E+00 6.60E+00

.WF L2162-05 05 AcTh-228 -7.60E+00 7.40E+00 2.80E+01 WF L2162-05 05 Ag-108m -2.10E+00 1.40E+00 5.20E+00 WF L2162-05 05 Ag-llOm 1.20E+00 2.60E+00 9.00E+00

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-72

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCilkg) (pCi/kg)

WF L2162-05 05 Ba-140 I.90E+00 2.80E+00 l.OOE+O1 WF L2162-05 05 Be-7 -9.OOE+00 1.50E+0 5.40E+01 WF L2162-05 05 Ce-141 -6.COE-01 3.60E+C0 1.20E+01 WF L2162-05 05 Ce-14 9.00E+00 1.20E+01 4.10E+01 WF L2162-05 05 Co-57 -2.00E-01 1.SOE+00 5.30E+00 WF L2162-05 05 Co-58 7.00E-01 1.80E+00 6.40E+00 WF L2162-05 05 Co-60 -3.OOE-0l 1.70E+00 6.SOE+00 WF L2162-05 05 Cr-51 -1 .50E+01 I.70E+01 6.IOE+0 WF L2162-05 05 Cs-134 -2.90E+00 1.SOE+00 6.30E+00 WF L2162-05 05 Cs-137 -6.00E-01 1.80E+00 6.70E+00 WF L2162-05 05 Fe-59 -I .25E+01 5.OOE+00 2.20E+0O WF L2162-05 05 1-131 -1.16E-01 8.60E-02 5.40E-01 WF L2162-05 05 K-40 1.31E+03 6.40E+01 7.40E+01 WF L2162-05 05 La-140 2.20E+00 3.20E+00 1.20E+0O WF L2162-05 05 Mn-54 9.OOE-01 1.70E+00 6.10E+00 WF L2162-05 05 Nb-95 I .70E+00 2.00E+00 7.OOE+00 WF L2162-05 05 Ru-103 -7.00E-01 1.90E+00 6.80E+00 WF L2162-05 05 Ru-106 -2.60E+0O 1.60E+01 6.OOE+0O WF L2162-05 05 Sb-124 -I.IOE+00 4.50E+00 1.70E+01 WF L2162-05 05 Sb-1W 3.20E+00 4.OOE+00 2.80E+01 WF L2162-05 05 Se-75 -6.00E-01 2.20E+00 7.80E+00 WF L2162-05 05 Zn-65 -4.80E+00 4.SOE+00 1.70E+01 WF L2162-05 05 Zr-95 1.IOE+O0 2.90E+00 l.OOE+0O GTF L2223-01 07 AcTh-228 3.50E+00 5.70E+00 l.90E+01 GTF L2223-01 07 Ag-108m -I.OOE-01 I.OOE+00 3.60E+00 GTF L2223-01 07 Ag-Ilm -9.OOE-01 1.90E+00 6.70E+00 GTF L2223-01 07 Ba-140 -7.00E-01 1.70E+00 6.40E+00 GTF L2223-01 07 Be-7 1.80E+0 I.OOE+0 3.40E+01 GTF L2223-01 07 Ce-141 1.IOE+00 I.80E+00 6.OOE+00 GTF L2223-01 07 Ce-144 3. IOE+00 6.80E+00 2.30E+01 GTF L2223-01 07 Co-57 -1.17E+00 9.00E-01 3.10E+00 GTF L2223-01 07 Co-58 4.00E-01 1.20E+00 4.30E+00 GTF L2223-01 07 Co-6o 5.OOE-01 1.60E+00 5.50E+O0 GTF L2223-01 07 Cr-51 I.40E+01 1.20E+01 4.IOE+O1 GTF L2223-01 07 Cs-134 2.IOE+00 1.40E+00 4.50E+00 GTF L2223-01 07 Cs-137 5.OOE-0 1.40E+00 4.70E+00 GTF L2223-01 07 Fe-59 l.OOE+00 3.90E+00 1.40E+0O GTF L2223-01 07 1-131 0.OOE+00 1.SOE-01 8.80E-01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-73

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

GTF L2223-01 07 K-40 1.53E+03 5.IOE+01 6.50E+01 GTF L2223-01 07 La-140 -8.00E-01 2.00E+00 7.40E+00 GTF L2223-01 07 Mn-54 9.OOE-01 1.30E+00 4.40E+00 GTF 12223-01 07 Nb-95 -3.00E-01 1.50E+00 5.20E+00 -J GTP L2223-01 07 Ru-103 -3.OOE-01 1.308+00 4.50E+00 GTP L2223-01 07 Ru-106 5.OOE+00 1.20E+01 4.00E+01 GTF L2223-01 07 Sb-124 0.OOE+00 3.30E+00 1.20E+01 GTP L2223-01 07 Sb-125 3.90E+00 3.20E+00 1.1OE+01 GTF L2223-01 07 Se-75 -I.OOE+00 1.50E+00 5.30E+00 GTF L2223-01 07 Zn-65 -4.50E+00 2.90E+00 1.lIOE+01 GTP L2223-01 07 Zr-95 1.60E+00 2.00E+00 6.80E+00 MR L2223-02 07 AcTh-228 9.90E+00 4.90E+00 1.60E+01 MR L2223-02 07 Ag-108m -1.10e+00 l.OOE+00 3.70E+00 MR L2223-02 07 Ag-l lim -1.40E+00 1.90E+00 6.80E+00 MR L2223-02 07 Ba-140 3.60E+00 1.90E+00 6.20E+00 MR L2223-02 07 Be-7 -1.30E+01 I.IOE+01 4.00E+01 MR L2223-02 07 Cc-141 -2.50E+00 3.20E+00 1.1OE+01 MR L2223-02 07 Cc-144 -1.70E+00 7.50E+00 2.60E+01 MR L2223-02 07 Co-57 4.30E-01 9.60E-01 3.20E+00 MR L2223-02 07 Co-58 -1.40E+00 1.40E+00 5.10E+00 MR L2223-02 07 Co-60 -7.00E-0O 1.40E+00 5.108+00 MR L2223-02 07 Cr-51 2.00E+00 1.20E+01 4.00E+01 MR L2223-02 07 Cs-134 -l.OOE-01 1.50E+00' 5.10E+00 MR L2223-02 07 Cs-137 1.70E+00 1.60E+00 5.20E+00 MR L2223-02 07 Fe-59 -2.00E+00 4.00E+00 1.40E+01 MR L2223-02 07 1.131 -3.80E-02 6.30E-02 3.30E-01 MR L2i23-02 07 K-40 2.09E+03 5.80E+01 6.50E+01 MR L2223-02 07 La-140 4.10E+00 2.20E+00 7.10E+00 MR L2223-02 07 Mn-54 l.OOE+00 1.40E+00 4.80E+00 MR L2223-02 07 Nb-95 7.00E-01 1.50E+00 5.20E+00 MR L2223-02 07 Ru-103 -1.40E+00 1.40E+00 4.90E+00 MR L2223-02 07 Ru-106 -1.00E+01 1.30E+01 4.50E+01 MR L2223-02 07 Sb-124 4.00E-01 2.80E+00 I.OOE+0I MR L2223-02 07 Sb-125 4.70E+00 3.20E+00 1.1OE+01 MR L2223-02 07 Se-75 8.00E-01 1.60E+00 5.30E+00 MR L2223-02 07 Zn-65 -4.80E+00 3.30E+00 1.208+01 MR L2223-02 07 Zr-95 2.00E-01 2.20E+00 7.70E+00 SF L2223-03 07 AcTh-228 -7.50E+00 5.30E+00 1.90E+01 SF L2223-03. 07 Ag-108m -2.004-01 9.60E-01 3.40E+00 SF L2223-03 07 Ag-l lOm -1.30E+00 1.70E+00 6.20E+00

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-74

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

SF L2223-03 07 Ba-140 -2.00E-01 1.70E+00 6.20E+00 SF L2223-03 07 Be-7 1.02E+01 8.80E+00 2.90E+0O SF L2223-03 07 Ce-141 -2.OOE+00 1.70E+00 6.OOE+00 SF L2223-03 07 Ce-144 4.60E+00 6.1OE+00 2.00E+01 SF L2223-03 07 Co-57 -1.30E-01 8.10E-01 2.80E+00 SF L2223-03 07 Co-58 -9.OOE-01 I.IOE+00 4.10E+0O SF L2223-03 07 Co-60 -1.OOE+00 1.50E+00 5.50E+00 SF L2223-03 07 Cr-51 2.30E+01 I.1OE+01 3.50E+01 SF L2223-03 07 Cs-134 -2.10E+00 1.20E+00 4.60E+00 SF L2223-03 07 Cs-137 -3.OOE-01 1.30E+00 4.70E+00 SF L2223-03 07 Fe-59 1.20E+00 4.10E+00 1.40E+0O SF L2223-03 07 1-131. 7.OOE-02 9.40E-02 3.60E-01 SF L2223-03 07 K-40 1.21E+03 4.SOE+01 6.30E+0I SF L2223-03 07 La-140 -2.OOE-01 1.90E+00 7.10E+00 SF L2223-03 07 Mn-54 -7.OOE-01 1.20E+00 4.40E+00 SF L2223-03 07 Nb-95 9.OOE-01 1.20E+00 4.10E+O0 SF L2223-03 07 Ru-103 -L.OOE-0 t.lOE+00 4.00EOE00 SF L2223-03 07 Ru-106 8.OOE+00 1.IOE+0 3.80E+0 SF L2223-03 07 Sb-124 -I.SOE+00 3.OOE+00 1.1OE+0 SF L2223-03 07 Sb-125 4.40E+00 3.00E+00 I.OOE+01 SF L2223-03 07 Se-75 3.00E-01 1.30E+00 4.30E+00 SF L2223-03 07 Zn-65 1.70E+00 2.70E+00 9.30E+00 SF L2223-03 07 Zr-95 4.40E+00 I.90E+00 6.20E+00 LF L2223-04 07 AcTh-228 1.60E+00 6.50E+00 2.30E+0O LF L2223-04 07 Ag-108m 1.70E+00 I.1OE+00 3.80E+00 LF L2223-04 07 Ag-lOrm -1.70E+00 2.00E+00 7.30E+00 LF L2223-04 07 Ba-140 I.OOE-0 2.20E+00 8.20E+00 LF L2223-04 07 Be-7 2.OOE+00 1.20E+01 4.IOE+0O LF - L2223-04 07 Ce-141 -1.40E+00 2.20E+00 7.60E+00 LF L2223-04 07 Ce-144 3.SOE+00 7.80E+00 2.70E+01 LF L2223-04 07 Co-57 -2.00E-01 I.OOE+00 3.SOE+00 LF L2223-04 07 Co-58 6.00E-01 1.501E+00 5.30E+00 LF L2223-04 07 Co-60 8.OOE-01 1.70E+00 6.OOE+00 LF L2223-04 07 Cr-SI 7.00E+00 1.30E+01 4.60E+0I LF L2223-04 07 Cs-134 -1.30E+00 1.40E+00 5.30E+00 LF L2223-04 07 Cs-137 -5.OOE-01 1.50E+00 S.40E+00 LF L2223-04 07 Fe-59 5.OOE+00 4.90E+00 1.70E+0I LF L2223-04 07 1-131 7.00E-02 1.20E-01 5.40E-01 LF L2223-04 07 K-40 1.46E+03 5.90E+01 7.50E+01 LF L2223-04 07 La-140 .00E-01 2.50E+00 9.50E+00

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-75

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

LF L2223-04 07 Mn-54 2.00E-01 1.30E+00 4.50E+00 LF L2223-04 07 Nb-95 -1.70E+00 1.50E+00 5.70E+00 LF L2223-04 07 Ru-103 -2.50E+00 1.50E+00 5.60E+00 LF L2223-04 07 Ru-106 -I.IOE+01 1.30E+0I 4.80E+01 LP L2223-04 07 Sb-124 0.OOE+00 3.40E+00 1.30E1+0I LF L2223-04 07 Sb-125 5.40E+00 3.60E+00 1.20E+01 LF L2223-04 07 Se-75 -2.30E+00 1.50E+00 5.60E+00 LF L2223-04 07 Zn-65 9.80E+00 6.40E+00 2.t0E+OI LP L2223-04 07 Z,-95 -1.70E+00 2.80E+00 1.OOE+01 WP L2223-05 07 AcTh-228 7.60E+00 4.10E+00 1.30E+01 WF L2223-05 07 Ag-108m 8.60E-01 8.70E-01 2.90E+00 -

WFI L2223-05 07 Ag-I lOIm -2.00E-01 1.50E+00 S.IOE+00 WF L2223-05 07 Ba-140 1.80E+00 2.IOE+00 7.30E+00 WF L2223-05 07 Be-7 -1.60E+00 9.30E+00 3.20E+01 WF L2223-05 07 Ce-141 4.00E-01 1.60E+00 5.60E+00 WF L2223-05 07 Cc-144 1.lOE+00 5.60E+00 1.90E+01 WF L2223-05 07 Co-57 -4.90E-01 7.50E-01 2.60E+O0 WF L2223-05 07 Co-58 -0.OOE+00 I.IOE+00 3.80E+O0 WF L2223-05 07 Co-60 2.10E+00 I.IOE+00 3.70E+00 WF L2223-05 07 Cr-SI l.lOE+01 I.IOE+01 3.70E+01 WF L2223-05 07 Cs-134 1.OOE-01 1.I1OE+00 3.70E+00 WF L2223-05 07 Cs-137 9.00E-01 1.lOE+00 3.90E+00 WF L2223-05 07 Fe-59 2.50E+00 3.60E+00 1.20E+01 WF L2223-05 07 1-131 4.40E-02 8.50E-02 3.70E-0I WF L2223-05 07 K-40 1.25E+03 3.90E+01 5.40E+01 WP L2223-05 07 La-140 2.10E+00 2.40E+00 8.40E+00 WP L2223-05 07 Mn-54 L.OOE-01 l.OOE+00 3.60E+00 -

WF L2223-05 07 Nb-9S 4.90E+00 1.50E+00 5.60E+00 WF L2223-05 07 Ru-103 -1.80E+00 1.1OE+00 4.10E+00 WF L2223-05 07 Ru-106 -9.OOE+00 1.OOE+01 3.60E+01 WF L2223-05 07 Sb-124 5.70E1+00 2.30E+00 7.20E+00 WF L2223-05 07 Sb-125 -2.60E+00 2.70E+00 9.60E+00 WF L2223-05 07 Sc-75 8.OOE-01 1.40E+00 4.70E+00 WF L2223-05 07 Zn-65 4.80E+00 2.30E+00 8.70E+00 WP L2223-05 07 Zr-95 -1.50E+00 2.OOE+00 7.00E+00 GTF L2298-01 09 AcTh-228 - -4.30E+00 6.50E+00 2.40E+01 GTP L2298-01 09 Ag-108m -2.00E-01 1.20E+00 4.IOE+00 GTF L2298-01 09 Ag-llOim 1.40E+00. 1.SOE+00 5.OOE+00

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-76

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

GTF L2298-01 09 Ba-140 1.60E+00 2.40E+00 8.70E+00 GTF L2298-01 09 Be-7 -4.OOE+00 1.IOE+01 4. lOE+0l GTF L2298-01 09 Ce-141 6.OOE-01 1.90E+00 6.SOE+00 GTF L2298-01 09 Cc-144 5.OOE+00 7.20E+W0 2.40E+01 GTF L2298-01 09 Co-57 7.00E-01 9.20E-01 3.IOE+00 GTF L2298-01 09 Co-58 0.OOE+00 1.60E+00 5.70E+00 GTF L2298-01 09 Co-60 4.OOE-01 1.80E+00 6.50E+00 GTF L2298-01 09 Cr-51 -7.00E+00 1.30E+01 4.40E+0I GTF L2298-01 09 Cs-134 2.OOE+00 1.60E+00 5.30E+00 GTF L2298-01 09 Cs-137 6.OOE-01 I.5OE+00 5.20E+O0 GTF L2298-01 09 Fe-59 -6.70E+00 5.70E+00 2.101E+01 GTF L2298-01 09 1-131 -1.36E-01 2.20E-02 5.40E-01 GTF L2298-01 09 K-40 1.44E+03 6.10E+01 7.90E+I01 GTF L2298-01 09 La-140 1.80E+00 2.80E+00 1.OOE+01 GTF L2298-01 09 Mn-54 -1.90E+00 1.60E+00 6.10E+00 GTF L2298-01 09 Nb-95 -2.60E+00 1.70E+00 6.30E+OO GTF L2298-01 09 Ru-103 -I.lOE+W0 1.50E+00 5.50E+00 GTF L2298-01 09 Ru-106 2.OOE+00 1.40E+01 4.90E+01 GTF L2298-01 09 Sb-124 -1.90E+00 3.OOE+00 1.20E+01 GTF L2298-01 09 Sb-125 5.OOE-01 3.60E+00 1.30E+01 GTF L2298-01 09 Se-75 -1.30E+00 1.70E+00 S.90E+O0 GTF L2298-01 09 Zn-65 -9.60E+00 4.1OE+00 1.60E+01 GTF L2298-01 09 Zr-95 -4.60E+00 2.60E+00 1.OOE+01 MR L2298-02 09 AcTh-228 I.OOE+00 6.70E+00 2.40E+01 MR L2298-02 09 Ag-108m 4.00E-01 I.IOE+00 3.90E+00 MR L2298-02 09 Ag- lOrm 3.OOE+00 2.40E+00 8.20E+O0 MR L2298-02 09 Ba-140 2.OOE+00 1.90E+00 6.60E+00 MR L2298-02 09 Be-7 -2.OOE+00 1.20E+01 4.30E+01 MR L2298-02 09 Ce-141 2.70E+00 2.IOE+00 6.80E+O0 MR L2298-02 09 Cc-144 -4.OOE+00 7.60E+00 2.60E+01 MR L2298-02 09 Co-57 1.46E+00 9.70E-01 3.20E+OO MR L2298-02 09 Co-58 -1.30E+00 1.SOE+00 5.60E+OO MR L2298-02 09 Co-60 -4.00E-01 1.90E+00 7.OOE+OO MR L2298-02 09 Cr-51 1.60E+01 1.40E+01 4.60E+0I MR L2298-02 09 Cs-134 -7.OOE-01 1.80E+00 6.60E+OO MR L2298-02 09 Cs-137 -2.50E+00 1.70E+00 6.30E+OO MR L2298-02 09 Fe-59 2.OOE+00 S.SOE+00 l.90E+0I MR L2298-02 09 1-131 -9.80E-02 2.OOE-02 5.10E-0I MR L2298-02 09 K-40 2.15E+03 7.40E+01 8.30E+01 MR L2298-02 09 La-140 2.30E+00 2.20E+00 7.60E+OO

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-77

Indiana Michigan Power Co., DC Cook Nuclear Plant -

Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

MR L2298-02 09 Mn-54 2.70E+00 1.70E+00 5.60E+OO MR L2298-02 09 Nb-95 -2.00E-01 1.70E+00 6.101E+00 MR L2298-02 09 Ru-103 -1.OOE-01 1.50E+00 5.30E+00 MR L2298-02 09 Ru-106 -2.00E+01 1.40E+01 5.30E+0I MR L2298-02 09 Sb-124 6.00E-01 3.90E+00 1.40E+01 MR L2298-02 09 Sb-125 1.40E+00 3.60E+00 1.20E+Ol MR L2298-02 09 Se-75 2.40E+00 1.80E+00 5.90E+OO -

MR L2298-02 09 Zn-65 -2.30E+00 5.70E+00 2.00E-+0I MR L2298-02 09 Zr-95 l.5OE+OO 2.80E+00 9.60E+00 SP L2298-03 09 Acih-228 9.00E-01 5.00E+00 1.80E+01 SF L2298-03 09 Ag-108m -1.30E+00 1.00+00 3.70E+00 SF L2298-03 09 Ag- lOnm 6.00E-01 1.70E+00 6.00E+00 SF L2298-03 09 Ba-140 5.OOE-01 1.90E+00 6.90E+00 SF L2298-03 09 Be-7 -1.5013+01 I.OOE+01 3.70E+01 SP L2298-03 09 Cc-141 -2.00E-01 2.OOE+00 6.70E+00 SP L2298-03 09 Ce-144 2.90E+00 7.1OE+00 2.40E+01 SF L2298-03 09 Co-57 3.30E-01 9.202-01 3.102+00 SF L2298-03 09 Co-58 -2.10E+00 1.302+00 5.002+00 SF L2298-03 09 Co-60 -4.004-01 1.302+00 4.602+00 SF L2298-03 09 Cr-51 -6.00E+00 1.20E+01 4.102+01 SP L2298-03 09 Cs-134 -3.70E+00 1.402+00 5.40E+00 SF L2298-03 09 Cs-137 O.OOE+00 1.30E+00 4.60E+00 SF L2298-03 09 Fc-59 -6.40E+00 3.90E+00 1.502+01 SF L2298-03 09 1-131 9.00E-02 1.10-01 4.10E-01 SF L2298-03 09 K-40 1.42E+03 4.90E+01 6.402+01 SF L2298-03 09 La-140 6.00E-01 2.20E+00 7.90E+00 SP L2298-03 09 Mn-54 -3.00E-01 1.20E+00 4.402+00 SF L2298-03 09 Nb-95 5.00E-01 1.40E+00 4.702+00 SF 12298-03 09 Ru-103 -9.00-01 1.202+00 4.30E+O0 SF L2298-03 09 Ru-106 -7.00E+00 1.20E+01 4.302+01 SF L2298-03 09 Sb-124 3.20E+00 2.90E+00 1.OOE+01 SF L2298-03 09 Sb-125 -3.40E+00 3.20E+OO I.IOE+01 SP L2298-03 09 Se-75 -1.00E-01 1.50E+00 5.10E+00 SF L2298-03 09 Zn-65 -1.20E+00 3.30E+00 1.20E+01 SP L2298-03 09 Zr-95 -1.80E+00 2.002+00 7.202+00 LF L2299-04 09 AcTh-228 -1.132+01 5.10E+OO 1.902+01 LF L2298-04 09 Ag-108m -1.30E-01 8.902-01 3.10E+00 LF L2298-04 09 Ag-l l0m -I.OOE+O 1.60E+00 5.80E+00 LF L2298-04 09 Ba-140 1.50+00 1.60E+00 5.402+00 LP L2298-04 09 Be-7 4.80E+00 9.102+00 3.10E+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-78

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

LF L2298-04 09 Cc-141 4.30E+00 1.60E+00 5.20E+00 LF L2298-04 09 Cc-144 8.80E+00 6.20E+00 2.OOE+0I LF L2298-04 09 Co-57 -5.60E-01 7.60E-01 2.60E+OO LF L2298-04 09 Co-58 4.OOE-01 1.20E+00 4.OOE+OO LF L2298-04 09 Co-60 -7.OOE-01 1.30E+00 4.90E+OO LF L2298-04 09 Cr-51 -4.OOE+OO l.OOE+OI 3.60E+0l LF L2298-04 09 Cs-134 2.80E+00 1.30E+00 4.IOE+OO LF L2298-04 09 Cs-137 2.OOE+00 1.20E+00 3.90E+OO LF L2298-04 09 Fe-59 -5.IOE+00 3.70E+00 1.40E+0O LF L2298-04 09 1-131 2.50E-01 1.50E-01 4.50E-0O LU L2298-04 09 K-40 1.41E+03 4.70E+01 5.80E+Ol LF L2298-04 09 La-140 1.70E+00 1.80E+00 6.20E+OO LF L2298-04 09 Mn-54 -6.OOE-01 l.IOE+OO 3.80E+OO LF L2298-04 09 Nb-95 -2.SOE+00 1.30E+00 4.90E+00 LF L2298-04 09 Ru-103 -1.60E+00 1.60E+OO 5.70E+OO LF L2298-04 09 Ru-106 -1.OOE+01 1.lOE+01 4.OOE+0I LF L2298-04 09 Sb-124 -3.OOE+00 2.40E+00 9.70E+OO LF L2298-04 09 Sb-125 2.OOE+00 2.70E+00 9.20E+OO LF L2298-04 09 Se-75 -6.OOE-01 1.20E+00 4.20E+OO LF L2298-04 09 Zn-65 1.70E+00 2.70E+00 9.40E+00 LF L2298-04 09 Zr-95 -I.SOE+OO 2.1OE+00 7.60E+OO WF L2298-05 09 AcTh-228 O.OOE+OO 5.OOE+OO 1.70E+Ol WF L2298-05 09 Ag-108m O.OOE+OO 9.20E-01 3.20E+OO WF L2298-05 09 Ag-I lOm 6.OOE-01 1.60E+00 5.SOE+00 WF L2298-05 09 Ba-140 -1.70E+00 1.70E+00 6.60E+00 WF L2298-05 09 Be-7 -1.25E+01 8.90E+00 3.30E+01 WP L2298-05 09 Ce-141 -3.40E+00 1.80E+00 6.30E+00 WF L2298-05 09 Cc-144 4.70E+00 6.30E+00 2.10E+0O WF L2298-05 09 Co-57 -5.50E-01 8.OOE-01 2.80E+00 WF L2298-05 09 Co-58 -I.OOE+00 1.IOE+00 4.10E+00 WF L2298-05 09 Co-60 I.OOE-0 1.30E+00 4.70E+00 WF L2298-05 09 Cr-51 -1.80E+00 9.90E+00 3.40E+0O WF L2298-05 09 Cs-134 I.OOE+00 1.20E+00 4.OOE+00 WF L2298-05 09 Cs-137 -6.OOE-01 1.30E*00 4.70E+00 WF L2298-05 09 Fe-59 4.30E+00 3.80E+00 1.30E+0O WF L2298-05 09 1-131 -I.IOE-0 4.70E-02 3.80E-0 WF L2298-05 09 K-40 1.29E+03 4.50E+01 5.60E+0I WF L2298-05-- 09 La-140 -1.90E+00 1.90E+00 7.60E+00 WF L2298-05 09 Mn-54 O.OOE+00 I.IOE+00 3.80E+00 WF L2298-05 09 Nb-95 -5.OOE-01 1.40E+00 4.80E+OO

• Radioactivity detected in sample (Le, concentration > 3 X standard deviation)

D-79

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

WF L2298-05 09 Ru-103 -6.00E-01 1.20E+00 4.30E+00 WF L2298-05 09 Ru-106 1.00+00 1.10E+01 3.70E+O1 WF L2298-OS 09 Sb-124 -2.30E+00 2.60E+00 l.OOE+01 WF L2298-05 09 Sb-125 3.80E+00 2.90E+00 9.70E+00 WF L2298-05 09 Se-75 8.00E-01 1.20E+00 4.20E+00 WF L2298-05 09 Zn-65 2.00E 3.40E+00 1.20E+01 WF L2298-O5 09 Zr-95 -1.5OE+CO 2.20E+OO 8.OOE+00 GTF L2389-01 11 AcTh-228 -7.00E-01 9.50E+00 3.50E+01 GTF 12389-01 11 Ag-108m 2.30E+00 1.80E+00 5.90E+00 GTF L2389-01 11 Ag-l lOm -5.OOE-01 2.80E+00 1.10E+01 GTF L2389-01 11 Ba-140 2.20E+00 2.90E+00 1.10+01 GTF L2389-01 11 Bc-7 3.00E+00 1.90E+01 6.70E+01 GTF L2389-01 11 Ce-141 1.80E+00 3.30E+00 1.20E+01 GTF L2389-01 11 Ce-144 -9.OOE+00 1.20E+01 4.40E+01 GTF L2389-01 11 Co-57 -2.00E-01O 1.70E+00 6.00E+00 GTF L2389-01 11 Co-58 -2.80E+00 2.70E+00 1.IOE+01 GTF L2389-01 11 Co-60 9.00E-01 2.80E+00 1.00E+01 GTF L2389-01 11 Cr-51 l.lOE+01 2.20E+01 7.50E+01 GTF L2389-01 11 Cs-134 1.00m-0 2.30E+00 8.70E+00 GTF L2389-01 11 Cs-137 5.0011-01 2.30E+00 8.40E+00 GTF L2389-01 11 Fe-59 2.20E+00 7.20E+00 2.70E+01 GTF L2389-01 11 1-131 3.30E-01 1.70E-01 4.70E-01 GTF L2389-01 11 K-40 1.46E+03 9.20E+01 l.OOE+02 GTF L2389-01 11 La-140 2.50E+00 3.30E+00 1.206+01 GTF L2389-01 11 Mn-54 -5.00E-01 2.20E+00 8.30E+00 GTF L2389-01 11 Nb-95 -5.80E+00 2.80E+00 1.20E+01 GTF L2389-01 11 Ru-103 -3.00E-01 2.OOE+00 7.60E+00 GTF L2389-01 11 Ru-106 -1.OOE+01 2.40E+01 8.90E+01 GTF L2389-01 11 Sb-124 -1.15E+01 4.50E+00 2.406+O1 -

GTF L2389-01 11 Sb-125 3.80E+00 6.30E+00 2.20E+01 GTF L2389-01 11 Se-75 4.90E+00 2.30E+00 9.30E+00 GTF L2389-01 11 Zn-65 -9.30E+00 6.60E+00 2.60E+01 GTF L2389-01 11 Zr-95 -6.70E+00 4.70E+00 1.90E+01 MR L2389-02 11 AcTb-228 9.60E+00 6.60E+00 2.20E+01 MR L2389-02 11 Ag-108m -7.00E-0I 1.30E+00. 4.40E+OO MR L2389-02 11 Ag-l lOm -1.60E+00 2.20E+00 8.00E+00 MR L2389-02 11 Ba-140 9.00E-01 2.60E+00 9.10E+00 MR L2389-02 11 Be-7 *3.00E+00 1.30E+01 4.50E+O1

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-80

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

MR L2389-02 11 Ce-141 4.00E-01 2.60E+00 8.90E+00 MR L2389-02 11 Ce-144 2.51E+01 9.80E+00 3.202+01 MR L2389-02 II Co-57 -5.002-01 1.20E+00 4.10E+00 MR L2389-02 I1 Co-58 -2.10E+00 1.60E+00 S.90E+00 MR L2389-02 11 Co-60 -2.OOE+00 1.80E+00 6.70E+00 MR L2389-02 11 Cr-51 -2.20E+01 1.50E+01 5.10E+01 MR L2389-02 11 Cs-134 3.50+00 1.80E+00 5.90E+00 MR L2389-02 II Cs-137 9.00E-01 1.60E+00 5.40E+00 MR L2389-02 11 Fe-59 9.004-01 4.60E+00 1.60E+01 MR L2389-02 11 1-131 9.00E-02 1.70E-01 8.704-01 MR L2389-02 11 K-40 1.93E+03 6.20E+01 8.50E+01 MR L2389-02 11 La-140 I.OOE+00 2.90E+00 I.OOE+01 MR L2389-02 11 Mn-54 1.50E+00 1.70E+00 5.70E+00 MR L2389-02 11 Nb-95 6.00E-01 1.80E+00 6.20E+00 MR L2389-02 11 Ru-103 -7.00E-01 1.602+00 5.70E+00 MR L2389402 11 Ru-106 -8.002+00 1.40E+01 4.90E+01 MR L2389-02 11 Sb-124 -2.30E+00 3.60E+00 1.40E+01 MR L2389-02 11 Sb-125 -5.30E+00 3.802+00 1.402+01 MR L2389-02 11 Se-75 l.50E+00 2.002+00 6.60E+00 MR L2389-02 11 Zn-65 2.13E+01 7.40E+00 2.40E+0O MR L2389-02 11 Zr-95 2.00E-01 2.602+00 9.10E+00 SF L2389-03 11 AcTh-228 1.70E+00 6.00E+00 2.10E+01 SF L2389-03 11 Ag-108m -1.30E+00 1.202+00 4.10E+00 SF L2389-03 II Ag-ll1m -2.902+00 2.10E+00 7.90E+00 SF L2389-03 11 Ba-140 5.70E+00 2.30E+00 6.90E+00 SF L2389-03 1i Be-7 -1.70E+01 1.10E+01 4.002+01 SF L2389-03 11 Ce-141 -5.002-01 1.90E+00 6.60E+00 SF L2389-03 11 Ce-144 -3.10E+00 6.80E+00 2.302+01 SF L2389-03 11 Co-57 -7.30E-01 8.50E-01 2.902+00 SF L2389-03 11 Co-58 1.30E+00 1.40E+00 4.80E+00 SF L2389-03 11 Co-60 O.OOE+00 1.80E+00 6.60E+00 SF L2389-03 11 Cr-51 6.002+00 1.202+01 4.20E+01 SF L2389-03 11 Cs-134 -1.OOE-01 1.40E+00 5.102+00 SF L2389-03 11 Cs-137 -1.30E4+C0 1.602+00 5.70E+00 SF L2389-03 11 Fe-S9 8.202+00 4.702+00 1.50E+01 SF L2389-03 11 1-131 2.10E-01 2.30E-01 9.10E-01 SF L2389-03 11 K-40 1.40E+03 5.602+01 7.40E+01 SF L2389-03 11 La-140 6.50E+00 2.60E+00 8.00E+00 SF L2389-03 11 Mn-54 -1.002-01 1.60E+00. 5.502+00 SF L2389-03 11 Nb-95 1.00+00 2.60E+00 8.60E+00

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-81

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

SF L2389-03 11 Ru-103 -3.OOE+00 1.50E+OO 5.50E+00 SF L2389-03 - 11 Ru-106 -1.50E+01 1.40E+O1 4.90E+01 SF L2389-03 11 Sb-124 -1.60E+00 3.00E+OO 1.20E+01 SF L2389-03 11 Sb-125 -2.30E+00 3.60E+OO 1.30E+01 SF L2389-03 11 Sc-75 6.00-E01 1.60E+O0 5.40E+OO SF L2389-03 11 Zn-65 1.02E+01 6.40E+00 2.10E+01 SP L2389-03 11 Zr-95 -1.20E+00 2.50E+OO 8.90E+O0 LF L2389-04 11 Aclb-228 -2.00E-01 6.40E+O0 2.20E+O1 LF L2389-04 11 Ag-108m -2.OOE-0I 1.20E+00 4.002+O0 LF L2389-04 11 Ag-l lOmn -I. IOE+00 2.20E+O0 8.00E+00 LF L2389-04 11 Ba-140 3.60E+O0 2.60E+0O 8.70E+OO LF L2389-04 11 Be-7 1.80E+01 1.1OE+01 3.70E+01 LF L2389-04 11 Ce-141 -6.50E+00 3.10E+OO l.1OE+01 LF L2389-04 11 Cc-144 7.40E+00 7.102+O0 2.40E+01 LF L2389-04 11 Co-57 9.80E-01 9.00E-01 3.00E+00 LF L2389-04 11 Co-5S -1.60E+OO 1.50E+00 5.50E+00 LF L2389-04 11 Co-60 1.10+00 1.70E+O0 5.80E+00 LF L2389-04 11 Cr-SI 3.40E+0I 1.30E+01 4.20E+OI LF L2389-04 11 Cs-134 -4.30E+OO 1.602+00 6.20E+00 LF L2389-04 11 Cs-137 2.OOE-0O 1.50E+00 5.30E+00 LF L2389-04 11 Fe-59 8.40E+OO 4.90E+00 1.60E+OI LF L2389-04 11 1-131 -2.70E-02 9.50E-02 6.00E-01 LF L2389-04 11 K-40 1.27E+03 5.30E+01 7.60E+01 LF L2389-04 11 La-140 4.20E+OO 3.00E+O0 l.OOE+01 LF L2389-04 11 Mn-54 1.40E+00 1.502+00 5.20E+OO LF L2389-04 11 Nb-95 1.90E+00 1.60E+00 5.30E+00 LF L2389-04 11 Ru-103 -2.40E+OO 1.40E+00 5.30E+00 LF L2389-04 11 Ru-106 -I.OOE+01 1.30E+0I 4.70E+01 LF L2389-04 11 Sb-124 -9.90E+OO 3.30E+00 1.50E+01 LF L2389-04 11 Sb-125 -8.50E+OO 3.40E+00 1.30E+OI LF L2389-04 11 Se-75 -6.0E-01 1.70E+OO 5.70E+00 LF L2389-04 11 Zn-6S 2.80E+OO 7.40E+00 2.50E+01 LF L2389-04 11 Zr-95 -2.10E+00 2.60E+OO 9.30E+OO WF L2389-05 11 AcTh-228 5.00E+00 5.80E+O0 2.00E+OI WF L2389-05 11 Ag-108m -1.40E+OO 1.20E+00 4.20E+00 WF L2389-05 11 Ag- lOnm -1.70E+O0 1.90E+00 7.00E+00 WF L2389-05 11 Ba-140 1.80E+OO 2.10E+00 7.102+O0 WF L2389-05 11 Be-7 4.00E+00 1.1OE+01 3.90E+01 WF L2389-05 11 Cc-141 2.OOE-01 2.102+00 7.20E+00 WF L2389-05 11 Cc-144 2.10E+OO 7.70E+OO 2.60E+01

• Radioactivity detected In sample (i.e., concentration > 3 X standard deviation)

D-82

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media .Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) . (pCi/kg)

WF L2389-05 11 Co-57 -1.40E+00 1.OOE+00 3.SOE+O0 WF L2389-05 11 Co-S8 -5.OOE-0O 1.40E+00 4.80E+00 WF L2389-05 11 Co-60 -3.00E+00 1.70E+00 6.40E+00 WF L2389-05 11 Cr-51 2.10E+01 1.30E+01 4.30E+01 WF L2389-05 11 Cs-134 8.OOE-01 1.40E+00 4.70E+00 WF L2389-05 11 Cs-137 -3.90E+00 1.60E+00 6.OOE+00 WF L2389-05 If Fe-59 5. 1OE+00 4.00E+00 1.30E+0O WF L2389-05 11 1-131 4.20E-01 2.30E-01 5.90E-01 WF L2389-05 11 K-40 1.32E+03 4.80E+01 6.60E+01 WF L2389-05 11 La-140 2.10E+00 2.40E+00 8.20E+00 WF L2389-05 11 Mn-54 5.00E-01 l.SOE+00 5.10E+00 WF L2389-05 11 Nb-95 3.50E+00 2.40E+00 8.OOE+00 WF L2389-05 11 Ru-103 -2.OOE-01 1.40E+00 4.90E+00 WF L2389-05 11 Ru-106 1.40E+01 1.30E+01 4.50E+0O WF L2389-05 11 Sb-124 8.10E+00 3.OOE+00 9.10E+00 WF L2389-05 11 Sb-125 -5.50E+00 3.60E+00 1.30E+01 WF L2389-05 11 Se-75 Q.OOE+00 1.80E+00 6.20E+OQ WF L2389-05 11 Zn-65 -2.80E+00 7.10E+00 2.40E+01 WF L2389-05 11 Zr-95 2.30E+00 2.30E+00 7.80E+00 GTF L2498-01 13 AcTh-228 1.11E+01 3.80E+00 1.20E+01 GTF L2498-01 13 Ag-108m -4.80E-01 8.30E-01 2.90E+00 GTF L2498-01 13 Ag-llOm -1.20E+00 1.40E+00 4.90E+00 GTE L2498-01 13 Ba-140 O.OOE+00 2.00E+00 7.10E+00 GTF L2498-01 13 Be-7 1.30E+00 8.90E+00 3.10E+01 GTF L2498-01 13 Ce-141 -6.OOE-01 1.70E+00 5.70E+00 GTF L2498-01 13 Ce-14 3.80E+00 5.90E+00 2.OOE+01 GTF L2498-01 13 Co-57 -3.101E-O1 7.40E-01 2.50E+00 GTF L2498-01 13 Co-58 -2.40E+00 1.lOE+00 4.10E+00 GTF L2498-01 13 Co-60 6.OOE-01 l.O1E+00 3.70E+00 GTF L2498-01 13 Cr-51 5.00E+00 1.1OE+0O 3.60E+0I GTF L2498-01 13 Cs-134 6.00E-0O 1.IOE+00 3.70E+00 GTF L2498-01 13 Cs-137 -I.OOE+00 1.OOE+00 3.70E+00 GTF L2498-01 13 Fe-59 -3.90E+00 3.20E+00 1.20E+01 GTF L2498-01 13 1-131 9.00E-02 1.50E-01 6.30E-01 GTF L2498-01 13 K-40 1.45E+03 3.80E+01 5.30E+0I GTF L2498-01 13 La-140 O.OOE+00 2.30E+00 8.20E+00 GTF L2498-01 13 Mn-54 -2.70E+00 l.OOE+00 3.80E+00 GTF L2498-01 13 Nb-95 3.80E+00 2.1OE+00 6.70E+00

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-83

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

GTF L2498-01 13 Ru-103 -8.004-01 1.102+00 3.80E+00 GTF L2498-01 13 Ru-106 2.70E+00 8.70E+00 3.00E+01 GTF L2498-01 13 Sb-124 -1.40E+00 2.50E+00 9.00E+O0 GTF L2498-01 13 Sb-125 -5.00E-01 2.50E+00 8.70E+00 GTF L2498-01 13 Se-75 3.30E+00 1.30E+00 4.10E+00 GTF L2498-01 13 Zn-65 8.50E+00 5.00E+00 1.60E+01 GTF L2498-01 13 Zr-95 2.002-01 1.90E+00 6.40E+00 MR L2498-02 13 AcTh-228 3.10E+00 4.80E+00 1.90E+01 MR L2498-02 13 Ag-108m -1.09E+00 9.50E-01 3.40E+O0 MR L2498-02 13 Ag-l lOm -3.00E-01 1.80E+00 6.40E+00 MR L2498-02 13 Ba-140 -1.40E+00 2.30E+00 8.70E+00 MR L2498-02 13 Be-7 -l.OOE+00 I.OOE+01 3.70E+01 MR L2498-02 13 Cc-141 -1.80E+00 2.OOE+00 6.90E+00 MR L2498-02 13 Ce-144 3.00-01 6.30E+00 2.10E+01 MR L2498-02 13 Co-57 -6.90B-01 8.30E-01 2.90E+00 MR L2498-02 13 Co-58 -1.50E+00 1.20E+00 4.60E+00 MR L2498-02 13 Co-60 -2.30E+00 1.50E+00 5.80E+00 MR L2498-02 13 Cr-51 -3.OOE+00 1.20E+01 4.20E+01 MR L2498-02 13 Cs-134 4.OOE-01 1.40E+OO 4.80E+00 MR L2498-02 13 Cs-137 3.101E+00 1.30E+00 4.30E+00 MR L2498-02 13 Fe-59 -8.1OE+00 4.30E+00 1.60E+01 MR L2498-02 13 1-131 3.00E-02 1.30E-01 6.50E-01 MR L2498-02 13 K-40 1.91E+03 5.60E+01 7.10E+OI MR L2498-02 13 La-140 -1.60E+00 2.60E+00 1.OOE+01 MR L2498-02 13 Mn-54 -1.70E+00 1.lIOE+00 4.30E+00 MR L2498-02 13 Nb-95 1.30E+00 1.40E+00 4.60E+00 MR L2498-02 13 Ru-103 -1.80E+00 1.30E+00 4.90E+00 MR L2498-02 13 Ru-106 1.20E+01 1.20E+01 4.10E+01 MR L2498-02 13 Sb-124 -1.60E+00 2.90E+00 1.102+01 MR L2498-02 13 Sb-125 -4.00E-01 3.00E+00 1.00E+01 MR L2498-02 13 Sc-75 -1.20E+00 1.30E+00 4.70E+00 MR L2498-02 13 Zn-65 -1.50E+00 3.40E+00 1.20E+01 MR L2498-02 13 Zr-95 1.90E+00 2.30E+00 7.80E+00 SF L2498-03 13 AcTh-228 -1.95E+01 5.20E+00 2.10E+01 SF L2498-03 13 Ag-108m 4.00E-0 I.OOE+00 3.50E+00 SF L2498-03 13 Ag-lOrm -2.40E+00 1.80E+00 6.80E+00 SF L2498-03 13 Ba-140 3.00E-01 2.50E+00 8.90E+00 SF L2498-03 13 Bc-7 -1.90E+01 1.20E+01 4.40E+01 SF L2498-03 13 Cc-141 3.30E+00 2.20E+00 7.40E+00 SF L2498-03 13 Cc-144 3.80E+00 7.80E+00 2.60E+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-84

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

SF L2498-03 13 Co-57 9.00E-OI I.OOE+00 3.30E+00 SF L2498-03 13 Co-58 -2.10E+00 1.40E+00 5.IOE+00 SF L2498-03 13 Co-60 3.OOE-01 1.40E+00 4.90E+00 SF L2498-03 13 Cr-SI 2.30E+01 1.40E+01 4.60E+0O SF L2498-03 13 Cs-134 -I.IOE+0O IAOE+00 5.10E+00 SF L2498-03 13 Cs-137 1.OOE+00 1.40E+00 4.80E+00 SF L2498-03 13 Fe-59 -6.20E+00 4.50E+00 1.70E+0O SF L2498-03 13 1-131 1.OOE-02 1.30E-01 6.70E-0O SF L2498-03 13 K-40 1.30E+03 4.80E+01 6.60E+0I SF L2498-03 13 La-140 4.OOE-01 2.80E+OO I.OOE+0O SF L2498-03 13 Mn-54 3.00E-01 1.30E+00 4.SOE+0O SF L2498-03 13 Nb-95 4.70E+00 2.40E+00 7.70E+OO SF L2498-03 13 Ru-103 -L.OOE+OO 1.40E+00 4.90E+00 SF L2498-03 13 Ru-106 2.OOE+01 1.20E+01 4.OOE+0O SF L2498-03 13 Sb-124 O.OOE+00 2.90E+00 I.IOE+0O SF L2498-03 13 Sb-125 7.40E+00 3.20E+OO I.OOE+0O SF L2498-03 13 Se-75 -1.70E+00 1.70E+00 6. 10E+00 SF L2498-03 13 Zn-65 8.50E+00 6.SOE+00 2. 10E+0O SF L2498-03 13 Zr-95 -3.OOE-01 2.30E+00 8.20E+00 LF L2498-04 13 AcTh-228 5.10E+00 5.70E+00 I.90E+01 LF L2498-04 13 Ag-108m 3.OOE-OI I.1OE+00 3.60E+00 LF L2498-04 13 Ag-l lOim 1.70E+00 1.80E+00 6.10E+00 LF L2498-04 13 Ba-140 -7.OOE-01 2.60E+00 9.40E+00 LF L2498-04 13 Be-7 -3.00E+O 1.1IOE+O1 3.90E+01 LF L2498-04 13 Ce-141 6.00E-01, 3.10E+00 I.OOE+OI LF L2498-04 13 Ce-144 -1.04E+01 7.60E+00 2.60E+0O LF L2498-04 13 Co-57 4.40E-01 9.50E-01 3.20E+00 LF L2498-04 13 Co-58 -7.OOE-01 1.40E+00 5.20E+00 LF L2498-04 13 Co-60 -2.80E+00 1.30E+00 5.30E+00 LF L2498-04 13 Cr-5SI -1.OOE+00 1.30E+01 4.60E+0I LF L2498-04 13 Cs-134 2.80E+00 1.50E+00 4.90E+00 LF L2498-04 13 Cs-137 8.00E-01 1.40E+00 4.70E+00 LF L2498-04 13 Fe-59 3.00E+00 4.1OE+00 1.40E+0O LF L2498-04 13 1-131 1.20E-01 1.60E-01 6.60E-0O LF L2498-04 13 K-40 1.38E+03 4.90E+01 6.80E+0I LF L2498-04 13 La-140 -8.OOE-01 *2.90E+00 I.IOE+0I LF . L2498-04 13 Mn-54 -7.00E-01 1.40E+00 4.90E+00 LF L2498-04 13 Nb-95 -1.70E+00 1.80E+00 6.40E+00 LF L2498-04 13 Ru-103 -1.40E+00 1.40E+00 4.90E+00 LF L2498-04 13 Ru-106 -2.OOE+0I I.IOE+0I 4.IOE+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-85

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide . Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

LF L2498-04 13 Sb-124 -2.50E+00 3.30E+00 1.30E+01 LF L2498-04 13 Sb-125 -1.30E+00 3.30E+00 1.IOE+0O LF L2498-04 13 Se-75 2.00E1- 1.70E+00 5.80E+00 LF L2498-04 13 Zn-65 -6.60E+00 6.50E+00 2.30E+01 -

LF L2498-04 13 Zr-95 -4.40E+00 2.40E+00 8.90E+00 WF L2498-05 13 AcTh-228 I.soe+00 5.30E+00 1.80E+01 WF L2498-05 13 Ag-108m -2.60E-0I 9.60E-01 3.40E+00 WF L2498-05 13 Ag-IOnm -6.00E-0l 1.60E+00 5.60E+00 WF L2498-05 13 Ba-140 -1.90E+00 2.IOE+00 8.30E+00 WF L2498-05 13 Be-7 -1.30E+01 l.OOE+0 3.80E+01 WF L2498-05 13 Ce-141 -6.50E+00 3.IOE+OO I.IOE+01 WF L2498-05 13 Ce-144 -4.50E+00 6.20E+00 2.20E+0I WF L2498-05 13 Co-57 -2.70E-0O 8.OOE-01 2.80E+00 WF L2498-05 13 Co-58 -7.00E-01 1.20E+00 4.20E+00 WP L2498-05 13 Co-60 8.001-01 1.20E+00 4.00OE+00 WF L2498-0S 13 Cr-SI -5.OOE+00 1.20E+0 4.30E+01 WF L2498-0S 13 Cs-134 2.00E-0O 1.20E+00 4.20E+O0 WF L2498-05 13 Cs-137 1.50E3+00 1.30E+00 4.30E+00 WF L2498-05 13 Fe-59 3.20E+00 4.30E+00 1.50E+01 WIF L2498-05 13 1-131 -6.70E-02 9.80E-02 6.70E-01 WF L2498-05 13 K-40 1.43E+03 4.90E+01 7.10E+OI WIT L2498-05 13 La-140 -2.20E+00 2.40E+00 9.50E+00 WF L2498-0S 13 Mn-54 l.OOE-01 l.lOE+00 4.00E+00 i WF L2498-0S 13 Nb-95 -5.00E-01 1.40E+00 5.10E+00 WFI L2498-05 13 Ru-103 -8.00E-0O 1.30E+00 4.70E+00 WF.

WIF L2498-OS 13 Ru-106 l.OOE+01 1.10E+01 3.60E+01 WF L2498-05 13 Sb-124 1.60E+00 2.40E+00 8.60E+00 WF L2498-05 13 Sb-125 S.30E+00 3.10E+00 I.OOE+01 WF L2498-05 13 Sc-75 -2.OOE+00 1.30E+00 4.60E+00 WF L2498-05 13 Zn-65 -8.30E+00 2.90E+00 I.IOE+01 WGF L2498-05 13 Zr-95 1.80E+00 2.10E+00 7.30E+00 GTF L2589-01 15 AcTh-228 1.27E+0I 5.90E+00 2.30E+0O GTF L2589-01 15 Ag-108m 8.00E-01 1.30E+00 4.40E+00 GTF L2589-01 15 Ag-lOrm -4.20E+00 2.40E+00 9.10E+00 GTF L2589-01 15 Ba-140 3.20E+00 2.60E+00 8.90E+00 GTF L2589-01 15 Be-7 -I.OOE+0O 1.30E+01 4.80E+01 GTF L2589-01 15 Ce-141 -I.IOE+00 2.80E+00 9.70E+00 GTF L2589-01 15 Ce-144 -6.70E+00 9.80E+00 3.40E+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-86

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

GTF L2589-01 15 Co57 -4.OOE-01 1.30E+00 4.30E+00 GTF L2589-01 15 Co-S8 8.00E-01 1.60E+00 5.40E+00 GTF L2589-01 15 Co-60 0.OOE+00 I.90E+00 6.70E+0O GTF L2589-01 15 Cr-SI 5.OOE+00 1.50E+01 5.10E+0O GTF L2589-01 15 Cs-134 1.50E+00 1.80E+00 6.00E+00 GTF L2589-01 15 Cs-137 -3.80E+00 1.70E+00 6.30E+00 GTF L2589-01 15 Fe-59 -7.10E+00 5.OOE+00 I.90E+OI GTF L2589-01 15 1-131 2.30E-02 9.60E-02 5.30E-O1 GTF L2589-01 15 K-40 1.46E+03 6.10E+01 8.30E+0I GTF L2589-01 15 La-140 3.70E+00 3.OOE+00 I.OOE+01 GTF L2589-01 15 Mn-54 -1.30E+00 1.60E+00 5.90E+00 GTF L2589-01 15 Nb-95 -6.OOE-01 1.80E+00 6.30E+00 GTF L2589-01 15 Ru-103 -2.20E+00 1.80E+00 6.40E+00 GTF L2589-01 15 Ru-106 2.50E+01 1.40E+01 4.50E+01 GTF L2589-01 15 Sb-124 -2.10E+00 4.40E+00 1.60E+01 GTF L2589-01 15 Sb-125 I.IOE+OO 3.80E+00 1.30E+0I GTF L2589-01 15 Se-75 -1.OOE+00 2.OOE+00 7.OOE+00 GTF L2589-01 15 Zn-65 -7.60E+00 4.30E+00 1.60E+01 GTF L2589-01 15 Zr-95 2.60E+00 2.70E+00 9.30E+O00 MR L2589-02 15 AcTh-228 -3.OOE-01 5.30E+00 I.90E+0I MR L2589-02 15 Ag-108m -1.50E+00 1.10E+00 3.80E+00 MR L2589-02 15 Ag-I lOm -3.20E+00 1.80E+00 6.90E+OO MR L2589-02 15 Ba-140 -2.OOE-01 2.00E+00 7.40E+00 MR L2589-02 15 Be-7 6.50E+00 9.70E+00 3.30E+01 MR L2589-02 15 Ce-141 -2.60E+00 I.90E+00 6.80E+00 MR L2589-02 15 Ce-14 -1.13E+01 7.30E+00 2.60E+0O MR 12589-02 15 Co-57 2.80E-01 9.30E-01 3.20E+OO MR L2589-02 15 Co-58 -9.OOE-01 1.30E+00 4.80E+00 MR L2589-02 15 Co-60 3.OOE-01 1.40E+00 4.90E+00 MR L2589-02 15 Cr-51 -1.1OE+01 1.20E+01 4.10E+0I MR L2589-02 15 Cs-134 1.80E+00 1.50E+00 5.OOE+00 MR L2589-02 15 Cs-137 1.40E+00 1.30E+00 4.30E+00 MR L2589-02 15 Fe-59 5.OOE-01 3.60E+00 1.30E+01 MR L2589-02 15 1-131 L.IOE-02 8.20E-02 4.70E-01 MR L2589-02 15 K-40 1.79E+03 5.40E+01 6.30E+01 MR L2589-02 15 La-140 -3.OOE-01 2.40E+00 8.50E+00 MR L2589-02 15 Mn-54 -1.40E+00 1.30E+(0 4.70E+00 MR L2589-02 15 Nb-95 Q.OOE+OO 1.50E+00 5.30E+00 MR L2589-02 15 Ru-103 -1.70E+00 1.30E+00 4.60E+00 MR L2589-02 15 Ru-106 -3.10E+01 1.20E+01 4.60E+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-87

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

MR L2589-02 15 Sb-124 -3.00E+00 2.90E+(DO 1.IOE+01 MR L2589-02 15 Sb-125 -1.903+00 3.30E+4DO 1.20E+01 MR L2589-02 15 Se-75 2.50E+00 1.60E+(DO 5.30E+00 MR L2589-02 15 Zn-65 -I.OOE+00 4.80E+( DO 1.70E+01 MR L2589-02 15 Zr-95 1.30E+00 2.20E14 DO 7.508+00 SF L2589-03 15 AcTh-228 -6.50E+00 7.00E+(DO 2.60E+01 SF L2589-03 15 Ag-108m -2.10E+00 1.30E+4DO 4.808+00 SF L2589-03 15 Ag-ll0m -3.00E-01 2.20E+4DO 8.10E+00 SF L2589-03 15 Ba-140 -5.40E+00 2.70E+4DO 1.IOE+0I SF L2589-03 15 Be-7 -1.00O+01 1.30E+4 4.60E+01 SF L2589-03 15 Ce-141 -3.90E+00 3.401+4 DO 1.20E1+01 SF L2589-03 15 Ce-144 6.90E+00 8.00E+(DO 2.70E+01 SF L2589-03 15 Co-57 -1.50E+00 1.60E+(DO 5.508+00 SF L2589-03 15 Co-58 2.00E-01 1.50E+( DO 5.408+00 SF L2589-03 15 Co-60 -I.OOE-01 2.10E+4 7.60E+00 SF L2589-03 15 Cr-SI 1.20E+01 1.40E+4DO 4.608+01 SP L2589-03 15 Cs-134 -5.00-01 2.00E+(DO 7.10E+00 SF L2589-03 15 Cs-137 0.00+00 1.80E+4DO 6.40E1+00 SF L2589-03 15 Fe-59 3.00M-1 5.60E+4Dl 2.008+01 SF L2589-03 15 1-131 1.20E-01 1.401-4 DO 5.50E-01 -

SF L2589-03 15 K-40 1.19E+03 6.208+4 DO 9.108+01 SF L2589-03 15 La-140 -6.208+00 3.108+4 DO 1.30E+01 SF L2589-03 15 Mn-54 2.00E-01 1.80E+4DO 6.50E+00 SF L2589-03 15 Nb-95 -2.70E+00 1.80E+4DO 6.908+00 SF L2589-03 15 Ru-103 -1.IOE+00 1.50E+4 5.60E+00 SF L2589-03 15 Ru-106 -1.90E+01 1.60E14 DO 6.008+01 SF L2589-03 15 Sb-124 -2.90E+00 3.90E+4DO 1.60E+01 SF L2589-03 15 Sb-125 -4.60E+00 3.80E+4DO 1.40E+01 SF L2589-03 15 Se-75 1.50E+00 1.90E+4DO 6.308+00 SF L2589-03 15 Zn-65 -6.40E+00 4.30+44DO 1.608+01 SF L2589-03 I5 Zr-95 2.0001 2.70E+4DO 9.70E+00 LF L2589-04 15 AcTh-228 -1.70E+00 5.50E+4 DO 1.90E+01 LF L2589-04 15 Ag-108m -5.70E-01 9.408E4 DO 3.40E+00 LF L2589-04 15 Ag-I lOm 1.70E+00 1.708+4 DO 5.60E+00 LF L2589-04 15 Ba-140 -5.00-01 1.80E+(DO 6.60E+00 LF L2589-04 15 Be-7 2.22E+01 9.90E+4DO 3.20E+01 LF L2589-04 15 Ce-141 -9.00-01 1.70E+( DO 6.00E+00 LF L2589-04 15 Ce-144 -1.44E+01 6.50E+4DO 2.30E+01 LF L2589-04 15 Co-57 -1.30E-01 8.60E-( 3.00E+00 LF L2589-04 15 Co-58 -2.40E+00 1.20E+4 DO 4.70E+00

• Radioactivity detected in sample (L.e, concentration > 3 X standard deviation)

D-88

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC

(;Cilkg) (pCilkg) (pCi/kg)

---

. ~------------

L2589-04 15 Co-60 -6.OOE-01 1.40E+00 5.20E+00 LF L2589-04 15 Cr-51 1.20E+0I I.IOE+01 3.80E+0I LF L2589-04 15 Cs-134 5.OOE-01 1.30E+00 4.40E+00 LF L2589-04 15 Cs-137 3.OOE-01 1.40E+00 4.80E+00 LF L2589-04 15 Fe-59 5.80E+00 3.60E+00 1.20E+0O LF L2589-04 15 1-131 8.OOE-02 L.IOE-01 4.50E-0O LF L2589-04 15 K-40 1.39E+03 4.90E+01 6.50E+01 LF L2589-04 15 La-140 - -6.OOE-01 2.OOE+00 7.60E+00 LP L2589-04 15 Mn-54 -5.OOE-01 1.30E+00 4.50E+00 LF L2589-04 15 Nb-95 -2.70E+00 1.50E+00 5.60E+00 LF L2589-04 15 Ru-103 8.OOE-01 1.30E+00 4.30E+00 LF L2589-04 15 Ru-106 3.OOE+00 1.20E+01 4.IOE+0I LF L2589-04 15 Sb-124 2.40E+00 2.50E+00 8.60E+00 LF L2589-04 15 Sb-125 1.50E+00 3.20E+00 l.lOE+0O LF L2589-04 15 Se-75 -7.OOE-01 1.60E+00 5.40E+00 LF L2589-04 15 Zn-65 -9.OOE+00 3.80E+00 1.50E+0O LF L2589-04 15 Zr-95 1.SOE+00 2.10E+00 7.20E+00 WF L2589-05 15 AcTh-228 4.40E+00 5.90E+00 2.OOE+01 WF L2589-05 15 Ag-108m 4.OOE-0O I.IOE+00 3.80E+00 WF L2589-05 15 Ag-llOm -7.OOE-01 1.80E+00 6.60E+00 WF L2589-05 15 Ba-140 6.OOE-01 2.00E+00 7.40E+00 WF L2589-05 15 Be-7 -3.OOE+00 I.IOE+01 3.90E+01 WF L2589-05 15 Ce-141 9.OOE-01 2.10E+00 6.90E+00 WF L2589-05 15 Ce-44 -5.40E+00 7.20E+00 2.50E+01 WF L2589-05 15 Co-57 -1.27E+00 9.50E-01 3.30E+00 WF L2589-05 15 Co-58 -6.OOE-01 1.30E+00 4.70E+00 WF L2589-05 15 Co-60 I.OOE+00 1.60E+00 5.70E+00 WF L2589-05 15 Cr-51 l.OOE+00 1.20E+01 4.20E+01 WF L2589-05 15 Cs-134 2.OOE-01 1.40E+00 4.90E+00 WF L2589-05 15 Cs-137 -8.OOE-01 1.50E+00 5.50E+00 WF L2589-05 15 Fe-59 3.70E+00 4.60E+00 1.60E+01 WF L2589-05 15 1-131 1.60E-02 9.40E-02 5.30E-01 WF L2589-05 15 K-40 1.50E+03 5.30E+01 6.40E+OI WF L2589-05 15 La-140 7.OOE-01 2.40E+00 8.50E+OO WF L2589-05 15 Mn-54 -1.70E+00 1.40E+00 5.OOE+00 WF L2589-05 15 Nb-95 -4. IOE+00 1.70E+00 6.5OE+00 WF L2589-05 15 Ru-103 3.OOE-01 1.40E+00 4.90E+OO WF L2589-05 15 Ru-106 6.OOE+00 1.20E+01 4.10E+O1 WF L2589-05 15 Sb-124 3.60E+00 3.40E+OO l.lOE+0I WF L2589-05 15 Sb-125 l.OOE+OO 3.SOE+00 1.20E+0O

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-89

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

WP L2589-05 15 Se-75 3.OOE-0O 1.70E+O0 5.90E+00 WP L2589-05 15 Zn65 2.60E+00 3.30E+OO l.IOE+0O WP L2589-05 15 Zr-9S 4.00E-01 2.50E+O0 8.80E+O0 GTF L2681-01 17 AcTh-228 -7.OOE+OO 5.10E+O0 I.90E+01 GTF L2681-01 17 Ag-108m O.OOE+O0 l1.OOE+O0 3.60E+00 GTF L2681-01 17 Ag-llOm -2.50E+O0 1.90E+O0 7.OOE+00 GTF L2681-01 17 Ba-140 -8.00E-OI 2.OOE+OO 7.40E+00 GTF L2681-01 17 Be-7 -3.OOE+O0 1.OOE+01 3.60E+01 GTP L2681-01 17 Ce-141 4.OOE-01 1.80E+O0 6.00E+00 J GTF L2681-01 17 Ce-144 5.OOE-01 7.OOE+00 2.40E+01 GTF L2681-01 17 Co-57 -4.OOE-02 8.90E-01 3.00E+00 GTF L2681-01 17 Co-58 -2.OOE+O0 1.20E+O0 4.60E+00 L2681-01 17 Co-60 -1.1OE+00 1.40E+00 5.40E+00 GTF L2681-01 17 Cr-51 -1.70E+01 1.20E+OI 4.30E+01 GTP L268I-01 17 Cs-134 2.OOE-01 1.30E+O0 4.50E+00 GTF L2681-01 17 Cs-137 1.60E+O0 1.50E+O0 5.OOE+00 GTF L2681-01 17 Fe-59 -4.90E+O0 4.20E+00 1.60E+01 GTP L2681-01 17 1-131 l.OOE-01 1.70E-0O 7.80E-0O 17 K-40 1.43E+03 5.OOE+OI 6.60E+01

• GTF L2681-01 GTF L2681-01 17 La-140 -9.OOE-01 2.30E+OO 8.50E+00 GTP L2681-01 17 Mn-54 3.OOE-01 1.30E+00 4.70E+00 L2681-01 17 Nb-95 -2.70E+00 1.50E+O0 5.60E+00 GTF L2681-01 17 Ru-103 -2.OOE-01 1.30E+O0 4.60E+00 GTF L2681-01 17 Ru-106 -1.IOE+01 1.30E+01 4.50E+0O L2681-01 17 Sb-124 -4. 10E+O0 3.OOE+OO 1.20E+01 J GTP L2681-01 17 Sb-12S 4.1OE+OO 3.20E+00 l.10E+01 GTP L2681-01 17 Se-75 -9.OOE-01 1.60E+OO 5.60E+00 L2681-01 17 Zn-65 -1.30E+O0 4.OOE+OO 1.40E+0O GTF L2681-01 17 Zr-95 1.40E+00 2.20E+O0 7.50E+00 MR L2681-02 17 Aclb-228 1.15E+01 5.30E+00 1.70E+01 MR L2681-02 17 Ag-108m -6.OOE-01 1.20E+O0 4.101E+O0 MR L2681-02 17 Ag-ll0m 2.OOE+00 1.80E+O0 6.20E+00 MR L2681-02 17 Ba-140 -1.50E+O0 2.30E+00 8.40E+00 MR L2681-02 17 Be-1 7.OOE+00 l.IOE+01 3.80E+01 MR L2681-02 17 Ce-141 -5.90E+OO 2.10E+O0 7.60E+00 MR L2681-02 17. Ce-144 -1.68E+0I 7.60E+00 2.70E+O1 MR L2681-02 17 Co-57 -4.IOE-01 9.90E-01 3.40E+00 MR L2681-02 17 Co-58 6.OOE-0O 1.40E+00 4.90E+00

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-90

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN . Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

MR L2681-02 17 Co-60 -1.70E+00 1.40E+00 5.40E+OO MR L2681-02 17 Cr-SI l.OOE+01 1.20E+01 4.OOE+01 MR L2681-02 17 Cs-134 1.50E+00 1.50E+00 5.20E+00 MR L2681-02 17 Cs-137 -1.20E+00 1.40E+00 5.IOE+00 MR L2681-02 17 Fc-59 1.80E+00 4.20E+00 1.40E+01 MR L2681-02 17 1-131 2.40E-01 2.50E-01 9.20E-01 MR L2681-02 17 K-40 1.64E+03 5.20E+01 6.40E+01 MR L2681-02. 17 La-140 -1.80E+00 2.60E+00 9.70E+00 MR L2681-02 17 Mn-54 -5.OOE-01 1.40E+00 5.OOE+00 MR L2681-02 17 Nb-95 -5.OOE-01 1.70E+00 6.00E+00 MR L2681-02 17 Ru-103 -1.80E+00 1.30E+00 4.70E+00 MR L2681-02 17 Ru-106 5.OOE+00 1.30E+01 4.40E+01 MR L2681-02 17 Sb-124 -2.40E+00 3.10E+00 1.20E+01 MR L2681-02 17 Sb-125 -4.OOE+00 3.50E+00 1.20E+01 MR L2681-02 17 Se-75 3.OOE-01 1.80E+00 6.OOE+00 MR L2681-02 17 Zn-65 4.10E+00 7.10E+00 2.40E+01 MR L2681-02 17 Zr-95 I.OOE+00 2.20E+00 7.80E+00 SF L2681-03 17 AcTh-228 -5.90E+00 5.80E+00 2.10E+01 SF L2681-03 17 Ag-108m -1.20E+00 I.IOE+00 4.10E+O0 SF L2681-03 17 Ag-HOm 4.OOE-01 2.OOE+00 7.OOE+O0 SF L2681-03 17 Ba-140 -1.50E+00 2.OOE+00 8.10E+O0 SF L2681-03 17 Be-7 2.OOE+00 I.IOE+0I 3.70E+01 SF L2681-03 17 Ce-141 -5.30E+00 2.20E+00 7.90E+O0 SF L2681-03 17 Ce-144 -5.50E+00 7.OOE+00 2.50E+01 SF L2681-03 17 Co-57 -1.20E+O0 I.OOE+00 3.60E+00 SF L2681-03 17 Co-58 -1.30E+00 1.40E+00 5.30E+00 SF L2681-03 17 Co-60 -3.60E+00 1.70E+00 6.80E+00 SF L2681-03 17 Cr-51 2.10E+01 1.30E+01 4.40E+I01 SF L2681-03 17 Cs-134 -1.20E+O0 I.50E+00 5.40E+00 SF L2681-03 17 Cs-137 -6.OOE-01 1.50E+00 S.30E+00 SF L2681-03 17 Fe-59 -4.80E+00 4.50E+00 1.70E+0I SF L2681-03 17 1-131 1.90E-01 2.OOE-01 7.50E-01 SF L2681-03 17 K-40 1.45E+03 5.70E+01 7.70E+01

• SF L2681-03 17 LA-140 -1.80E+00 2.30E+00 9.30E+00 SF L2681-03 17 Mn-54 -1.60E+00 I.IOE+00 4.40E+00 SF L2681-03 17 Nb-95 8.00E-01 1.60E+00 S.60E+00 SF L2681-03 17 Ru-103 -1.70E+00 1.40E+OO 5.IOE+OO SF L2681-03 17 Ru-106 8.OOE+00 1.40E+01 4.8OE+01 SF L2681-03 17 Sb-124 -1.60E+00 2.90E+00 1.20E+01 SF L2681-03 17 Sb-125 -8.60E+00 3.50E+00 1.30E+0O

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-91

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCifkg) (pCi/kg) (pCi/kg)

SP L2681-03 17 Se-75 -2.1OE+0O 1.50E+00 5.30E+00 SF L2681-03 17 Zn-6S -3.60E+00 3.20E+00 1.20E+01 SF L2681-03 17 Zr-95 -2.20E+00 2.60E+00 9.70E+00 LF L2681-04 17 AcTh-228 -5.80E+00 6.50E+00 2.40E+01 LU L2681-04 17 Ag-108m -1.20E+00 1.40E+00 5.lOE+OO LF L2681-04 17 Ag-lOrn 1.90E+00 2.402+00 8.30E+OO LF L2681-04 17 Ba-140 -1.1OE+0O 3.00E+00 1.20E+01 LF L2681-04 17 Be-7 -1.30E+O1 1.50OE+01 5.40E+OI LF L2681-04 17 Ce-141 -6.50E+00 4.30E+00 1.50E+01 LF L2681-04 17 Ce-144 2.OOE+00 1.OOE+01 3.40E+O1 LF L2681-04 17 Co-57 2.00E-01 1.30E+00 4.30E+OO LF L2681-04 17 Co-58 4.002-01 1.80E+00 6.40E+OO LF L2681-04 17 Co-60 -1.10+OO 1.80E+00 6.80E+OO LF L2681-04 17 Cr-51 .9.00E+00 1.70E+01 6.002+01 LF L2681-04 17 Cs-134 1.70E+O0 1.90E+00 6.50E+OO LF L2681-04 17 Cs-137 -6.OOE-01 1.80E+00 6.70E+OO LF L2681-04 17 Fe-59 6.00E-01 5.10+0O 1.802+01 LF L2681-04 17 1-131 -6.00E-02 1.30E-01 8.50E-01 LF L2681-04 17 K-40 1.40E+03 6.50E+01 8.90E+OI 0

LP L2681-04 17 La-140 -1.20E+00 3.50E+00 1.30E+01 LF L2681-04 17 Mn-54 -1.70E+00 1.80E+00 6.70E+00 LF L2681-04 17 Nb-95 -4.00E-01 2.202+00 7.80E+00 LF 12681-04 17 Ru-103 -9.00E-01 1.80E+00 6.60E+OO LF L2681-04 17 Rtu-106 4.00E+00 1.50E+01 5.302+01 UF L2681-04 17 Sb-124 2.90E+00 3.80E+00 1.40E+01 LF L2681-04 17 Sb-125 -4.20E+00 4.40E+00 1.60E+01 LF L2681-04 17 Se-7S -4.00E-01 2.102+00 7.402+00 LF L2681-04 17 Zn-65 -I.OOE+O0 4.50E+00 1.60E+01 LF L2681-04 17 Zr-95 -1.80E+00 3.OOE+OO 1.IOE+01 WF L2681-05 17 AcTh-228 - 2.70E+00 6.702+00 2.402+01 WF L2681-05 17 Ag-108m 0.OOE+00 1.40E+00 4.90E+00 WF L2681-05 17 Ag-lOrm 6.00E-01 2.30E+00 8.202+00 WF L2681-05 17 Ba-140 1.30E+S0 2.70E+00 l.OOE+01 WF L2681-05 17 Be-7 1.30E+01 1.40E+01 4.60E+01 WF L2681-05 17 Cc-141 -6.70E+00 2.60E+00 9.80E+00 WF L2681-05 17 Ce-144 -2.20E+00 9.10E+00 3.20E+01 WF L2681-05 17 Co-57 -1.60E+00 1.30E+00 4.50E+00 WF. L2681-05 17 Co-58 -2.30E+00 1.70E+00 6.60E+00 WF L2681-05 17 Co-60 4.00E-01 2.10E+00 7.50E+00 WF L2681-05 17 Cr-51 -2.00E+01 1.70E+01 6.20E+0I

• Radioactivity detected In sample (i.e, concentration > 3 X standard deviation)

D-92

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

WF L2681-05 17 Cs-134 -4.OOE-01 1.80E+00 6.50E+00 WF L2681-05 17 Cs-137 1.70E+O0 1.80E+00 6.20E+00 WF L2681-05 17 Fe-59 -1.80E+O0 6.OOE+00 2.20E+01 WF L2681-05 17 1-131 -4.OOE-02 1.20E-01 8.OOE-01 WF L2681-05 17 K-40 1.47E+03 6.90E+01 9.OOE+01 WF L2681-05 17 La-140 1.40E+OO 3.10E+00 1.20E+01 WF L2681-05 17 Mn-54 9.OOE-01 1.60E+00 5.60E+0O WF L2681-05 17 Nb-9S -1.40E+00 2.1OE+00 7.90E+00 WF L2681-05 17 Ru-103 1.70E+00 1.80E+00 6.OOE+00 WF L2681-05 17 Ru-106 1.OOE+00 I.SOE+01 5.30E+01 WF L2681-05 17 Sb-124 -1.26E+01 3.90E+00 1.90E+01 WF. L2681-05 17 Sb-125 O.OOE+00 4.OOE+00 1.40E+01 WF L2681-05 17 Se-75 3.40E+00 1.80E+00 5.70E+O0 WF L2681-05 17 Zn-65 -8.50E+O0 4.60E+00 1.80E+01 WF L2681-05 17 Zr-95 -3.60E+00 3.20E+00 1.20E+01 GTF L2812-01 19 AcTh-228 1.02E+01 7.20E+00 2.40E+01 GTF 12812-01 19 Ag-108m -3.OOE-01 1.40E+0O 5.OOE+00 GTF L2812-01 19 Ag-llOm -2.20E+00 2.80E+00 1.OOE+01 GTF L2812-01 19 Ba-140 -2.OOE+00 3.20E+00 1.20E+01 GTF L2812-01 19 Be-7 -1.30E+01 1.40E+01 5.OOE+01 GTF L2812-01 19 Ce-141 -1.70E+0O 2.50E+00 8.50E+0O GTF L2812-01 19 Cc-144 -2.90E+00 8.60E+00 3.OOE+01 GTF L2812-01 19 Co-57 -5.OOE-01 1.10E+00 3.80E+0O GTF L2812-01 19 Co-58 -6.OOE-01 1.70E+00 6.20E+00 GTF L2812-01 19 Co-60 2.OOE+00 2.20E+00 7.70E+0O GTF L2812-01 19 Cr-51 3.OOE+00 1.60E+01 5.40E+01 GTF L2812-01 19 Cs-134 -I.OOE-01 1.90E+00 6.90E+00 GTF L2812-01 19 Cs-137 2.80E+00 1.90E+00 6.40E+00 GTF L2812-01 19 Fe-59 1.70E+00 5.30E+0O 1.90E+01 GTF L2812-01 19 1-131 -I.OOE-02 1.30E-01 6.90E-01 GTF L2812-01 19 K-40 1.42E+03 7.OOE+01 1.OOE+02 GTF L2812-01 19 La-140 -2.30E+00 3.60E+C0 1.40E+01 GTF L2812-01 19 Mn-54 -6.OOE-01 1.80E+C0 6.60E+OO GTF L2812-01 19 Nb-95 -2. 1OE+C0 2.20E+C0 8.10E+OO GTF L2812-01 19 Ru-103 -5.OOE-01 I.70E+C0 5.90E+OO GTF 12812-01 19 Ru-106 O.OOE+OO 1.60E+01 5.50E+01 GTF 12812-01 19 Sb-124 -3.10E+00. 4.30E+C0 1.70E+O1 GTF L2812-01 19 Sb-125 -2.70E+00 4.30E+00 1.50E+O1

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-93

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCilkg) (pCi/kg)

GTF L2812-01 19 Se-75 1.40E+00 2.OOE+00 6.90E+00 GTF L2812-01 19 Zn-6S 1.60E+01 8.40E+00 2.70E+01 GTF L2812-01 19 Zr-95 -3.60E+00 3.OOE+00 1.20E+0I MR L2812-02 19 AcTh-228 -7.OOE-01 7.70E+00 2.70E+01 MR L2812-02 19 Ag-108m 2.OOE-01 1.40E+00 4.70E+00 MR L2812-02 19 Ag-lOnm -3.80E+00 2.80E+00 L.IOE+01 MR L2812-02 19 Ba-140 4.OOE+00 3.30E+00 I.IOE+01 MR L2812-02 19 Be-7 4.OOE+00 1.30E+01 4.70E+O1 MR L2812-02 19 Cc-141 2.1QE+00 2.30E+00 7.80E+00 MR L2812-02 19 Cc-144 1.13E+01 8.30E+00 2.80E+01 MR L2812-02 19 Co-57 -3.OOE-01 1.10E+00 3.80E+00 MR L2812-02 19 Co-58 7.OOE-01 1.70E+00 6.OOE+00 MR L2812-02 19 Co-60 3.50E+00 2.20E+00 7.IOE+00 MR L2812-02 19 Cr-SI -9.OOE+00 1.60E+0O 5.60E+01 MR L2812-02 19 Cs-134 -3.OOE-01 2.OOE+00 7.20E+00 MR L2812-02 19 Cs-137 1.70E+00 1.80E+00 6.20E+00 MR L2812-02 19 Fc-59 -1.43E+01 6.10E+00 2.50E+0I J MR L2812-02 19 1-131 -1.17E-01 9.90E-02 7.20E-01 MR L2812-02 19 K-40 1.68E+03 7.40E+01 9.90E+01 MR L2812-02 19 La-140 4.60E+00 3.80E+00 1.30E+01 MR L2812-02 19 Mn-54 -7.OOE-01 1.80E+00 6.60E+00 MR L2812-02 19 Nb-95 8.OOE-01 2.OOE+00 6.90E+00 MR L2812-02 19 Ru-103 -9.OOE-01 1.80E+00 6.60E+00 MR L2812-02 19 Ru-106 3.OOE+01 1.60E+01 5.20E+0I MR L2812-02 19 Sb-124 3.90E+00 5.10E+00 1.80E+01 MR L2812-02 19 Sb-125 -5.50E+00 4.40E+00 1.60E+01 MR L2812-02 19 Se-75 2.10E+00 2.OOE+00 6.60E+00 MR L2812-02 19 Zn-65 -4.30E+00 4.70E+00 1.70E+01 MR L2812-02 19 Zr-95 -1.IOE+00 3.10E+00 1.IOE+01 SF L2812-03 19 AcTh-228 5.IOE+00 4.OOE+00 1.30E+01 SP L2812-03 19 Ag-108m -9.OOE-02 7.90E-01 2.70E+OO SP L2812-03 19 Ag-llOm -5.OOE-01 1.40E+00 4.90E+OO SF L2812-03 19 Ba-140 8.OOE-01 1.70E+00 6.20E+OO SF L2812-03 19 Be-7 3.IOE+00 8.20E+00 2.80E+01 SF L2812-03 19 Ce-141 -1.60E+00 1.80E+00 6.20E+OO SF L2812-03 19 Ce-144 -9.OOE+00 5.10E+00 1.80E+01 SF L2812-03 19 Co-57 -1.70E-01 8.40E-01 2.80E+OO SF L2812-03 19 Co-58 -S.90E-01 9.80E-01 3.50E+OO SF L2812-03 19 Co-60 8.OOE-01 I.OOE+OO 3.5OE+OO SF L2812-03 19 Cr-51 -4.OOE+OO I.OOE+01 3.50E+0O

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-94

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

SF L2812-03 19 Cs-134 O.OOE+00 I.OOE+OO 3.60E+OO SF L2812-03 19 Cs-137 -5.70E-0O 9.90E-01 3.50E+OO SF L2812-03 19 Fe-59 2.60E+00 3.40E+00 1.20E+01 SF L2812-03 19 1-131 4.OOE-02 1.70E-01 8.20E-0O SF L2812-03 19 K-40 1.38E+03 4.OOE+OI 5.40E+0O

• SF L2812-03 19 La-140 9.OOE-01 2.OOE+00 7.IOE+OO SF L2812-03 19 Mn-54 4.30E-01 9.20E-01 3.20E+OO SF L2812-03 19 Nb-95 1.40E+O0 1.20E+00 4.10E+OO SF L2812-03 19 Ru-103 -L.OOE-01 l.IOE+OO 3.70E+OO SF L2812-03 19 Ru-106 9.OOE-01 9.5OE+00 3.30E+O1 SF L2812-03 19 Sb-124 -2.90E+O0 2.IOE+00 8.30E+OO SF L2812-03 19 Sb-125 7.OOE-01 2.5OE+00 8.60E+OO SF L2812-03 19 Se-75 -7.OOE-01 I.lOE+OO 3.70E+OO SF L2812-03 19 Zn-65 -1.IOE+00 2.5E+00 8.80E+OO SF L2812-03 19 Zr-95 -2.20E+00 l.90E+00 6.90E+OO LF L2812-04 19 Aclb-228 2.40E+00 6.50E+00 2.20E+O1 LF L2812-04 19 Ag-108m -1.40E-01 9.90E-01 3.SOE+OO LF L2812-04 19 Ag-l lOm O.OOE+00 l.90E+00 6.50E+OO LF L2812-04 19 Ba-140 -1.50E+00 2.OOE+00 7.5OE+OO LF L2812-04 19 Be-7 l.OOE+01 l.OOE+0 3.5OE+01 LF L2812-04 19 Cc-141 -1.20E .00 2.30E+00 8.OOE+OO LF L2812-04 19 Ce-144 5.40E+00 7.OOE+00 2.30E+01 LF L2812-04 19 Co-57 1.23E+00 9.20E-01 3.00E+OO LF L2812-04 19 Co-58 -I.IOE+00 1.40E+OO 5.OOE+OO LF L2812-04 19 Co-60 l.OOE+OO 1.40E+00 4.70E+OO LF L2812-04 19 Cr-SI 5.OOE+00 1.20E+01 4.00E+O1 LF L2812-04 19 Cs-134 -2.OOE-01 1.40E+00 4.80E+OO LF L2812-04 19 Cs-137 -7.OOE-01 1.40E+OO 5.OOE+OO LF L2812-04 19 Fe-59 -8.OOE-0O 3.80E+00 1.40E+01 LF L2812-04 19 1-131 -8.OOE-02 1.30E-01 8.90E-01 LF L2812-04 19 K-40 1.48E+03 5.OOE+I01 6.20E+0l1 LF L2812-04 19 La-140 -1.80E400 2.30E+00 8.70E+OO LF L2812-04 19 Mn-54 7.OOE-0O 1.30E+00 4.40E+OO LF L2812-04 19 Nb-95 l.OOE+OO 1.SOE+OO 5.20E+OO LF L2812-04 19 Ru-103 3.OOE-0O 1.30E+00 4.40E+QO LF L2812-04 19 Ru-106 O.OOE+OO 1.20E+01 4.IOE+01 LF L2812-04 19 Sb-124 O.OOE+OO 2.70E+00 9.80E+OO LF L2812-04 19 Sb-125 2.30E+OO 3.10E+OO I.OOE+OI LF L2812-04 19 Se-75 -1.5OE+OO 1.50E+OO 5.30E+OO LF L2812-04 19 Zn-65 -8.40E+00 3.50E+00 1.30E.01

• Radioactivity detected In sample (i.e., concentration > 3 X standard deviation)

D-95

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

LF L2812-04 19 Zr-95 1.60E+00 2. 10E+00 7.10E+00 WF L2812-05 19 AcTh-228 4.50E+0O 5.20E+00 1.80E+01 WF L2812-05 19 Ag-108m 1.06E+0O 9.60E-01 3.20E+00 WF L2812-05 19 Ag-i lOm -3.00E+00 1.70E+00 6.20E+00 WF L2812-05 19 Ba-140 2.00E-01 1.80E+00 6.40E+00 WF L2812-05 19 Be-7 -1.59E+01 8.80E+00 3.30E+0I WF L2812-O5 19 Ce-141 -4.00E+00 2.00E+00 6.90E+00 WF L2812-05 19 Ce-144 -3.10E+00 6.30E+00 2.20E+01 WF L2812-05 19 Co-57 9.00E-01 9.50E-01 3.20E+00 WF L2812-05 19 Co-58 -1.60E+00 1.20E+00 4.30E+00 WF L2812-05 19 Co-60 7.00E-01 1.30E+00 4.50E+00 WF L2812-0S 19 Cr-SI -6.00E+00 I.IOE+01 3.90E+01 WF L2812-05 19 Cs-134 7.00E-01 1.20E+00 4.30E+00 WF L2812-05 19 Cs-137 1.30E+00 1.20E+00 4.202+00 -

WF L2812-05 19 Fe-59 6.00E-01 3.70E+00 1.30E+01 WF L2812-05 19 1-131 -1.46E-01 9.40E-02 7.00E-01 WF L2812-05 19 K-40 1.45E+03 4.90E+01 6.40E+01 WF L2812-05 19 La-140 3.00E-01 2.00E+00 7.40E+00 WF L2812-05 19 Mn-54 -6.OOE-01 1.202+00 4.402+00 WF L2812-05 19 Nb-95 8.00E-OI 1.30E+00 4.50E+00 WF L2812-05 19 Ru-103 -1.70E+O0 1.20E+00 4.30E+00 WF L2812-05 19 Ru-106 -130E+01 1.202+01 4.20E+01 WF L2812-05 19 Sb-124 1.90E+00 2.70E+00 9.40E+00 WF L2812-05 19 Sb-125S 2.60E+O0 2.90E+00 9.70E+00 WF L2812-05 19 Se-75 1.10E+00 1.30E+00 4.30E+00 WF L2812-05 19 Zn-65 -5.90E+00 3.70E+00 1.40E+01 1.WF L2812-05 19 Zr-95 1.80E+00 2.10E+00 7.10E+00 GTF L2916-01 21 AcTh-228 1.40E+00 7.10E+00 2.50E+01 GTF L2916-01 21 Ag-S08m -8.00E-01 1.40E+00 4.90E+00 GTF L2916-01 21 Ag-l lOm -3.30E+00 2.50E+00 9.60E+00 GTF L2916-01 21 Ba-140 -2.40E+00 3.00E+00 1.20E+01 GTF L2916-01 21 Be-7 -4.00E+00 1.302+01 4.80E+01 GTF L2916-01 21 Ce-141 3.00E+00 2.20E+00 7.20E+00 GTF L2916-01 21 Co-144 6.00E-01 8.1OE+00 2.802+01 GTF L2916-01 21 Co-57 -4.00E-01 I.OOE+00 3.60E+00 GTF L2916-01 21 Co-58 2.00E-01 1.80E+00 6.30E+00 GTF L2916-01 21 Co-60 -1.30E+00 1.90E+00 7.20E+00 GTF L2916-01 21 Cr-51 1.70E+01 1.40E+01 4.70E+01

• Radioactivity detected in sample (i~e., concentration > 3 X standard deviation)

D-96

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

---

-K----------------------------- --------

GTF L2916-01 21 Cs-134 1.30E+00 1.90E+00 6.60E+00 GTF L2916-01 21 Cs-137 -6.00E-01 1.80E+00 6.60E+00 GTF L2916-01 21 Fe-59 2.10E+OO S.50E+00 2.00E+01 GTF L2916-01 21 1-131 -1.20E-01 1.30E-01 7.70E-01 GTF L2916-01 21 K-40 1.29E+03 6.60E+01 9.90E+01 GTF L2916-01 21 La-140 -2.70E+00 3.50E+00 1.40E+O1 GTF L2916-01 21 Mn-54 2.OOE-01 1.90E+00 6.80E+OO GTF L2916-01 21 Nb-95 -6.OOE-01 l.90E+00 6.90E+OO GTF L2916-01 21 Ru-103 -1.SOE+0O 1.80E+00 6.60E+OO GTF L2916-01 21 Ru-106 1.20E+01 1.50E+01 5.1OE+01 GTF L2916-01 21 Sb-124 -4.60E+00 4.10E+00 1.70E+01 GTF L2916-01 21 Sb-125 3.IOE+00 4.40E+OO 1.50E+01 GTF L2916-01 21 Se-7S 4.OOE+00 2.OOE+00 6.40E+OO GTF L2916-01 21 Zn-65 1.40E+00 4.30E+OO 1.50E+01 GTF L2916-01 21 Zr-95 -1.60E+00 2.90E+OO I.IOE+Ol MR L2916-02 21 AcTh-228 -5.50E+00 6.20E+00 2.30E+0O MR L2916-02 21 Ag-108m 2.00E-01 1.20E+00 4.20E+OO MR L2916-02 21 Ag-I lOm 2.90E+00 2.30E+00 7.80E+OO MR L2916-02 21 Ba-140 3.80E+00 2.70E+00 9.IOE+OO MR L2916-02 21 Be-7 6.OOE+00 1.20E+01 4.20E+01 MR L2916-02 21 Ce-141 5.60E+00 2.20E+00 6.90E+00 MR L2916-02 21 Ce-144 -1.70E+00 8.40E+00 2.90E+01 MR L2916-02 21 Co-57 -1.OOE+00 1.OOE+00 3.50E+00 MR L2916-02 21 Co-58 1.OOE+00 I.50E+00 5.IOE+00 MR L2916-02 21 Co-60 -I.OOE-01 1.80E+00 6.60E+00 MR L2916-02 21 Cr-SI -6.OOE+00 1.40E+01 4.80E+01 MR L2916-02 21 Cs-134 9.00E-01 1.50E+00 5.30E+00 MR L2916-02 21 Cs-137 1.60E+00 1.60E+0O 5.50E+00 MR L2916-02 21 Fe-59 -7.OOE-01 4.70E+00 1.70E+0O MR L2916-02 21 1-131 -L.OOE-O1 1.lOE-01 7.50E-01 MR L2916-02 21 K-40 1.88E+03 6.50E+01 7.30E+01 MR L2916-02 21 La-140 4.30E+00 3.IOE+00 1.OOE+Ol MR L2916-02 21 Mn-54. O.OOE+00 1.60E+00 5.60E+00 MR L2916-02 21 Nb-95 -3.00E+00 1.80E+00 6.70E+00 MR L2916-02 21 Ru-103 -6.OOE-01 1.50E+00 5.40E+00 MR L2916-02 21 Ru-106 -3.OOE+00 1.50E+0 5.30E+01 MR - L2916-02 21 Sb-124 l.IOE+00 3.20E+00 1.20E+01 MR L2916-02 21 Sb-125 4.40E+00 3.80E+00 1.30E+0l MR L2916-02 21 Se-75 -2.20E+00 1.80E+00 6.40E+00 MR L2916-02 21 - Zn-65 I.IOE+00 3.60E+00 1.30E+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-97

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dcv. MDC (pCi/kg) (pCi/kg) (pCi/kg)

MR L2916-02 21 Zr-9S 2.00E+00 2.70E+00 9.30E+00 SF L2916-03 21 AcTh-228 4.20E+00 5.80E+00 2.00E+01 SF L2916-03 21 Ag-108m 0.OOE+00 1.20E+00 4.20E+00 SF L2916-03 21 Ag-llOm 2.00E-01 2.10E+00 7.302+00 SP L2916-03 21 Ba-140 -1.30E+00 2.20E+00 8.60E+00 SF L2916-03 21 Be-7 2.20E+01 1.20E+01 3.80E+01 SF L2916-03 21 Ce-141 2.70E+00 3.10E+00 I.OOE+01 -d SF L2916-03 21 Cc-144 -2.23E+01 8.402+00 3.102+01 SF L2916-03 21 Co-57 5.00E-01 I.IOE+00 3.70E+00 SF L2916-03 21 Co-58 7.00E-01 1.70E+00 5.80E+00 SF L2916-03 21 Co-60 l.lOE+00 1.60E+00 5.70E+00 SF L2916-03 21 Cr-51 -2.00E+00 1.402+01 4.90E+01 SF L2916-03 21 Cs-134 -6.00E-01 1.70E+00 6.20E+00 SF L2916-03 21 Cs-137 -7.00E401 1.60E+00 5.60E+00 SF L2916-03 21 Fe- 59 -9.30E+00 4.OOE+00 1.60E+01 SF L2916-03 21 1-131 -1.60E-01 1.40E-01 8.40E-01 SF L2916-03 21 K-40 1.46E+03 5.80E+01 8.10E+OI+

SF L2916-03 21 La-140 -1.50E+10 2.60E-00 9.90E+OO SF L2916-03 21 Mn-54 2.80E+00 1.50E+00 4.90E+OO SF L2916-03 21 Nb-95 -3.40E+00 1.70E+00 6.40E+OO SF L2916-03 21 Ru-103 l.OOE-01 1.50E+00 5.40E+OO SF L2916-03 21 Ru-106 9.00E+00 1.40E+01 4.802+O1 SF L2916-03 21 Sb-124 1.30E+00 3.30E+00 1.20E+01 SF L2916-03 21 Sb-125 9.OOE-01 4.OOE+00 1.40E+01 SF L2916-03 21 Se-75 -7.00E-01 1.802+00 6.40E+OO SF L2916-03 21 Zn-65 -4.IOE+00 5.60E+00 2.00E+01 SF L2916-03 21 Zr-95 3.90E+00- 2.50+00 8.40E+OO LF L2916-04 21 AcTh-228 3.50E+00 5.80E+00 2.002+01 LF L2916-04 21 Ag-108m -1.50E+00 I.IOE+OO 4.20E+OO LP L2916-04 21 Ag-llOm -I.0E0+00 1.90E+00 7.OOE+OO LF L2916-04 21 Ba-140 -1.60E+00 1.80E+00 7.40E+OO LF L2916-04 21 Be-7 -3.00E+O0 1-.1OE+01 3.90E+01 LF L2916-04 21 Ce-141 -6.002-01 1.90E+00 6.70E+00 LF L2916-04 21 Cc-144 1.12E+01 7.00E+00 2.30E+01 LF L2916-04 21 Co-57 -3.20E-01 9.402-01 3.30E+O0 LF L2916-04 21 Co-58 -1.40E+00 1.20E+00 4.80E+00 LF L2916-04 21 Co-60 -1.70E+00 1.60E+00 6.00E+O0 LF L2916-04 21 Cr-51 6.00E+00 1.20E+01 4.202+01 LF L2916-04 21 Cs-134 -1.90E+00 1.40E+00 5.40E+O0 LF L2916-04 21 Cs-137 -4.00E-01 1.50E+O0 5.30E+O0

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

D-98

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

LF L2916-04 21 Fe-59 -4.50E+00 4.70E+00 1.80E+0I LF L2916-04 21 1-131 9.OOE-02 1.90E-01 8.30E-01 LF L2916-04 21 K-40 1.46E+03 5.60E+01 6.30E+0I LF L2916-04 21 La-140 -1.90E+00 2.10E+00 8.50E+00 LF L2916-04 21 Mn-54 2. IOE+00 1.30E+00 4.20E+00 LF L2916-04 21 Nb-95 2.50E+00 1.40E+00 4.70E+00 LF L2916-04 21 Ru-103 -1.40E+0O 1.50E+00 5.30E+00 LF L2916-04 21 Ru-106 4.OOE+00 1.40E+01 4.80E+01 LF L2916-04 21 Sb-124 1.60E+00 2.50E+00 9.1OE+00 LF L2916-04 21 Sb-125 -3. IOE+00 3.40E+00 1.20E+01 LF L2916-04 21 Se-75 -2.30E+00 1.40E+00 5.30E+00 LF L2916-04 21 Zn-65 -4.80E+00 3.50E+00 1.30E+01 LF L2916-04 21 Zr-95 O.OOE+00 2.30E+00 8.40E+00 WF L2916-05 21 AcTh-228 7.30E+00 6.90E+00 2.30E+0O WF L2916-05 21 Ag-108m -3.OOE-01 1.20E+00 4.20E+00 WF L2916-05 21 Ag-l1lm -I.OOE+00 2.40E+00 8.60E+OO WF L2916-05 21 Ba-140 -1.30E+00 2.80E+00 1.00E+0O WF L2916-05 21 Be-7 1.40E+0O 1.40E+01 4.70E+0O WF L2916-05 21 Cc-141 7.OOE-01 2.80E+00 9.30E+00 WF L2916-05 21 Cc-144 7.20E+00 9.80E+00 3.30E+0O IWF L2916-05 21 Co-57 -2.70E+00 1.20E+00 4.30E+00 WF L2916-05 21 Co-58 -I.OOE+00 1.60E+00 5.70E+00 WF L2916-05 21 Co-60 1.50E+00 1.70E+00 6.OOE+00 WF L2916-05 21 Cr-SI 9.OOE+00 l.50E+01 5.IOE+01 WF L2916-05 21 Cs-134 7.00E-O1 1.90E+00 6.50E+00 WF L2916-05 21 Cs-137 6.00E-01 1.60E+00 5.40E+00 WF L2916-05 21 Fe-59 O.OOE+00 4.90E+00 1.80E+0O WF L2916-05 21 1-131 O.OOE+00 1.50E-OI 6.50E-01 WF L2916-05 21 K-40 1.41E+03 5.80E+01 8.70E+01 WF L2916-05 21 La-140 -1.50E+00 3.20E+00 1.20E+0O WF L2916-05 21 Mn-54 5.OOE-01 1.70E+00 5.90E+00 WF L2916-05 21 Nb-95 -2.00E+00 1.90E+00 7.OOE+00 WF L2916-05 21 Ru-103 9.OOE-01 1.70E+00 5.80E+00 WF L2916-05 21 Ru-106 I .50E+01 1.40E+01 4.80E+0O WF L2916-05 21 Sb-124 1.70E+00 3.70E+00 1.30E+01 WF L2916-05 21 Sb-125 0.OOE+00 3.40E+00 1.20E+01 WF L2916-05 21 Se-75 1.IOE+00 2.OOE+00 6.60E+00 WF L2916-05 21 Zn-65 1.OOE+00 4.OOE+00 1.40E+01 WF L2916-05 21 Zr-95 I .70E+00 2.90E+00 9.90E+00

• Radioactivity detected In sample (i.e., concentration > 3 X standard deviation)

D-99

Indiana Michigan Power Co., DC Cook Nuclear Plant Radiological Environmental Monitoring Program Summary of 2002 Data Media Station LSN Week Nuclide Conc Std. Dev. MDC (pCi/kg) (pCi/kg) (pCi/kg)

GTP L3037-01 23 AcTh-228 -8.20E+00 5.30E+00 2.OOE+0O GTF L3037-01 23 Ag-108m -5.30E-01 9.30E-01 3.30E+00 GTF L3037-01 23 Ag-I lOm -I.OOE+00 1.70E+00 6.1OE+00 GTF L3037-01 23 Ba-140 3.80E+00 1.90E+00 6.10E+00 GTP L3037-01 23 Be-7 7.00E-01 9.70E+00 3.40E+0I GTF L3037-01 23 Ce-141 -2.10E+00 1.70E+00 5.90E+00 -d GTP L3037-01 23 Ce-144 4.1OE+00 6.50E+00 2.20E+01 GTP L3037-01 23 Co-57 -3.10E-01 9.20E-01 3.20E+00 GTF L3037-01 23 Co-58 2.OOE-01 1.20E+00 4.1OE+00 GTF L037-01 23 Co-60 6.0OE-01 1.30E+00 4.60E+00 GTF L3037-01 23 Cr-5I 1.1OE+01 1.10E+01 3.70E+01 GTF L3037-01 23 Cs-134 4.OOE-01 1.20E+00 4.20E+00 GTF L3037-01 23 Cs-137 2.00E-01 1.30E+00 4.50E+00 GTF L3037-01 23 Fe-59 -5.IOE+00 4.OOE+00 1.50E+01 GTF L3037-01 23 1-131 2.30E-01 2.20E-01 8.00E-01 GTF L3037-01 23 K-40 1.45E+03 4.802+01 6.OOE+0I GTF L3037-01 23 La-140 4.40E+00 2.20E+00 7.OOE+00 GTF L3037-01 23 Mn-54 -3.001-01 1.10E+00 4.OOE+00 GTP L3037-01 23 Nb-95 -5.00E-01 1.20E+00 4.30E+00 GTF L3037-01 23 Ru-103 -6.00E-01 1.20E+00 4.30E+00 GTF L3037-01 23 Ru-106 1.OOE+00 I.1OE+0I 3.90E+01 GTF L3037-01 23 Sb-124 -4.30E+00 2.80E+00 I.IOE+0I GTF L3037-01 23 Sb-125 3.40E+00 2.90E+00 9.90E+00 GTF L3037-01 23 Sc-75 2.20E+00 1.30E+00 4.1OE+00 GTF L3037-01 23 Zn-65 -4.90E+00 2.80E+00 I.IOE+01 GTF L3037-01 23 Zr-95 -1.10E+00 2.40E+00 8.70E+00 MR L3037-02 23 AcTh-228 1.35E+01 7.40E+00 2.40E+01 MR L3037-02 23 Ag-108m 1.40E+00 1.30E+00 4.20E+00 MR L3037-02 23 Ag-llOm -3.60E+00 2.60E+00 9.90E+00 MR L3037-02 23 Ba-140 -6.OOE-01 3.40E+00 1.30E+01 MR U3037-02 23 Be-7 l.OOE+O1 1.50E+O1 5.202+01 MR L3037-02 23 Ce-141 2.20E+00 2.30E+00 7.90E+00 MR L3037-02 23 Ce-144 -1.60E+00 8.30E+00 2.90E+01 MR L3037-02 23 Co-57 3.OOE-01 1.00E+00 3.50E+OO MR L3037-02 23 Co-58 -2.00E+00 1.80E+00 6.80E+00 MR L3037-02 23 Co-60 -1.30E+00 2.20E+00 8.30E,+OO MR L3037-02 23 Cr-SI 3.70E+01 1.60E+01 S.00E+01 MR L3037-02 23 Cs-134 4.00E-01 2.10E+00 7.40E+O0

• Radioactivity detected in sample (i.e, concentration > 3 X standard deviation)

D-100