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D. C. Cook, Units 1 and 2 - Annual Radiological Environmental Operating Report
	ML11145A226
Person / Time
Site:	Cook
Issue date:	05/13/2011
From:	Gebbie J P; Indiana Michigan Power Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	AEP-NRC-2011-32
	Download: ML11145A226 (362)
	v • d • e

INDIANA MICHIGAN Indiana Michigan Power POWEMR One Cook Place Bridgman, MI 49106 A unit of American Electric Power Indiana Michigan Power.c om May 13, 2011 AEP-NRC-2011-32 10 CFR 50, Appendix I Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Enclosed is the Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report. This report covers the period from January 1, 2010, through December 31, 2010, and was prepared in accordance with the requirements of Technical Specification 5.6.2 and 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.This letter contains no new or modified regulatory commitments.

Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.Sincerely, Joel P. Gebbie Site Vice President DMB/jmr

Enclosure:

Annual Radiological Environmental Operating Report c: J. T. King, MPSC, w/o enclosure S. M. Krawec, Ft. Wayne AEP, w/o enclosure MDEQ -WHMD/RPS NRC Resident Inspector M. A. Satorius, NRC Region III P. S. Tam, NRC, Washington DC ENCLOSURE TO AEP-NRC-2011-32 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Annual Radiological Environmental Operating Report Indiana Michigan Power Company Donald C. Cook Nuclear Plant RADIOLOGICAL ENVIRONMENTAL-MONITORING PROGRAM January 1, 2010- December 31, 2010 Docket No. 50-315, 50-316 License No. DPR-58, DPR-74 AREVA Doc 47-9159327-001 Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 TABLE OF CONTENTS Pa..e 1.0 EXECUTIVE

SUMMARY

........................................................................

4

2.0 INTRODUCTION

......................................................................................................

5 2.1 General Plant Site Information

..............................................................................

5 2.2 Program Design ....................................................................................................

5 2.3 Monitoring Zones ...............................................................................................

6 2.4 Pathways Monitored

........................................................................................

6 2.5 Descriptions of Monitoring Pathways ...................................................................

6 2.5.1 Air ......................................................................................................

7 2.5.2 Surface W ater ......................................................................................

7 2.5.3 Groundwater

........................................................................................

7 2.5.4 Drinking Water ......................................................................................

7 2.5.5 Sediment ...............................................................................................

8 2.5.6 Milk ....................................................................................................

8 2.5.7 Fish ....................................................................................................

8 2.5.8 Food Product ........................................................................................

8 2.5.9 Broadleaf Vegetation

.............................................................................

8 2.5.10 TLD Monitoring

......................................................................................

9 2.5.11 Additional Groundwater Sample Analysis (non-ODCM required)

....... 9 2.5.12 Additional Groundwater Sample Analysis (NEI Groundwater Protection In itia tiv e ) ................................................................................................................

9 2.6 Samples Collected During 2010 .....................................................................

19 3.0 RADIOLOGICAL DATA

SUMMARY

TABLES ............................................................

20 4.0 ANALYSIS OF ENVIRONMENTAL RESULTS ..........................................................

55 4.1 Sampling Program Deviations

.........................................................................

55 4.2 Comparison of Achieved LLD with Requirements

...........................................

58 4.3 Results Compared Against Reporting Levels .................................................

58 4.4 Data Analysis by Media Type -Discussion

...................................................

59 4.4.1 Air Particulate

......................................................................................

59 4.4.2 Airborne Iodine ...................................................................................

60 4.4.3 Groundwater (Well) ..............................................................................

60 Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 TABLE OF CONTENTS (continued)

Paqe 4.4.4 D rinking W ater ....................................................................................

63 4.4.5 S urface W ater ....................................................................................

64 4 .4 .6 S edim ent .............................................................................................

65 4 .4 .7 M ilk ...................................................................................................

..65 4.4.8 Food Products & Vegetation

..............................................................

65 4 .4 .9 F ish ...................................................................................................

..66 4.4.10 Gamma Exposure Rate .......................................................................

66 4.4.11 Additional Sample Analysis (non-ODCM required samples) ...............

67 4.4.12 Additional Sample Analysis (NEI Groundwater Protection Initiative)

....... 69 5.0 OFF-SITE DOSE EQUIVALENT COMMITMENTS

...................................................

75 6.0

SUMMARY

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

76 7 .0 R E F E R E N C E S ................................................................................................................

83 APPENDIX A: SYNOPSIS OF ANALYSIS TECHNIQUES

..................................................

A-1 APPENDIX B: 2010 LAND USE CENSUS ..........................................................................

B-1 APPENDIX C: QUALITY ASSURANCE PROGRAM ............................................................

C-1 APPENDIX D: 2010 DATA

SUMMARY

....................................................................................

D-1 APPENDIX E: PRE-OPERATIONAL RADIOLOGICAL MONITORING PROGRAM ................

E-1 Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 1.0 EXECUTIVE

SUMMARY

Implementation of the Donald C. Cook Nuclear Plant (CNP) Radiological Environmental Monitoring Program (REMP) continued during the period January through December 2010, in accordance with station Technical Specifications and Off-Site Dose Calculation Manual (ODCM).Radiochemical and radiometric analyses of REMP samples were performed to allow for detection and quantification of station-related radioactivity.

A variety of potential exposure pathways were monitored by analyzing air, fruit, vegetation, water, milk, fish and sediment samples. Thermoluminescent dosimeters (TLDs) were also utilized to monitor for gamma radiation exposure that in turn might be attributed to plant activities.

Evaluation of sample analyses results considered the variability of natural or man-made radioactivity sources including their distribution and uptake in the environment and environmental media. This variability depends on several possible factors such as:* contributions from cosmogenic radioactivity,* groundwater 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, and* feed type.Since these factors had the potential to cause considerable variation in sample analysis results, they were considered during the evaluation of sample analysis results.Based on an evaluation of sample analyses results, it was determined that non-tritium radioactivity detected by the REMP was 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 K-40, one sample contained naturally occurring Th-228 and one contained the naturally occurring Th-232.* Naturally-occurring K-40 was detected in all eight fish samples.* Both indicator and ,control Food Products samples (grapes) contained naturally-occurring K-40. One indicator sample contained naturally occurring Be-7. All samples of broadleaf vegetation contained naturally-occurring K-40, with 26 of 33 indicator samples and all control samples containing naturally-occurring Be-7. Two samples contained naturally occurring Pb-210 and one contained naturally occurring Th-232 as indicated by AcTh-228.

Additionally there were two indicator samples that contained Cs-137. The source of the nuclide in these Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 samples is likely to be past weapons testing in the atmosphere given the media and concentration.

19 of 142 water samples (drinking, ground, and surface) indicated the presence of naturally-occurring K-40 and five of 142 contained the naturally-occurring Th-232 decay series, as indicated by AcTh228. Tritium was detected in six of 68 ground water samples. Site tritium modeling has indicated that the activity in all of these samples is the result of tritium recapture via precipitation through gaseous releases out the unit vent. Tracking of well activity is performed at CNP via the REMP and Groundwater Protection Programs.

This activity has no impact on public health and safety and is the result of effluent releases performed via licensed released paths and are well within NRC limits.All 78 milk samples, from both indicator and control locations, detected naturally-occurring K-40. One indicator sample detected naturally occurring Th-228. Two samples detected naturally occurring Th-232, indicated by AcTh-228.No sample analysis results exceeded or approached specified reporting levels.This report was prepared for Indiana Michigan Power Company by AREVA NP, Inc.Sample collection and preparation were performed by CNP. Laboratory analyses were performed by the AREVA NP Environmental Laboratory (E-LAB) for the first half of the year, and GEL Laboratories for the second half.

2.0 INTRODUCTION

2.1 General

Plant Site Information Indiana Michigan Power Company's CNP is located on the southeastern shore of Lake Michigan approximately one mile north of Bridgman, Michigan.

The site consists of two pressurized water reactors:

Unit 1, 1084 MWe (Net Design Electrical Rating) and Unit 2, 1107 MWe (Net Design Electrical Rating). Unit 1 achieved initial criticality on January 18, 1975, and Unit 2 on March 10, 1978.2.2 Program Design The REMP for CNP was designed with specific objectives:

-To provide an early indication of the appearance or accumulation of radioactive material in the environment possibly caused by CNP activities.

-To provide assurance to regulatory agencies and the public that the environmental/dose impact of the CNP 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.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 The program was developed to meet the intent of NRC Regulatory Guide 4.1 (Revision 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, "Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors".

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 -2.3.2.3 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. Generally, monitoring zones are designated as"indicator" or "control" locations.

For a particular pathway, the distinction between these designations is based on relative direction and distance from the plant. Sample analysis data from the two zones is evaluated and used to differentiate between radiation due to plant activities and that due to other sources (examples:

nuclear weapons test fallout and seasonal background variations).

2.4 Pathways

Monitored Four pathway categories (airborne, waterborne, ingestion, and direct radiation) were monitored by the REMP. Each of these categories was monitored by the collection of one or more sample types listed and described below.Airborne Pathway: Air Waterborne Pathway: Surface Water Groundwater Drinking Water Sediment Ingestion Pathway: Milk Fish Food Product (Fruit and Broad Leaf Vegetation)

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 -2.3. The program as described in this report includes both ODCM required and additional or Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 supplemental samples. A description of the sampling program follows, and a detailed summary of the analytical methodologies employed by the AREVA NP Environmental Laboratory is provided in Appendix A.2.5.1 Air Air samplers were installed at ten locations as required by the ODCM.These samplers operated continuously (except during weekly sample media replacement) within the specified sample flow rate range of 42 to 70 liters per minute (LPM). An Automatic Volume Totalizer was used to measure the total volume of air sampled, total unit run time and volumetric flow rate.Airborne particulates were collected by passing air through a 47-mm glass-fiber filter. Charcoal cartridges were installed downstream of the particulate filters and were used to collect airborne radioiodine.

Both types of sample media were collected weekly, and to allow for the decay of radon daughter products, the particulate filters were held at least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months before being analyzed for gross-beta radioactivity.

The particulate filters were composited by location as part of the quarterly gamma spectroscopy analysis.2.5.2 Surface Water Two 125-milliliter surface water samples were collected from shoreline locations approximately 500 feet north and south of the plant centerline.

Samples were composited daily over a month, and the gamma aliquot was preserved with nitric acid. All samples receive a gamma isotopic analysis.

A tritium analysis was performed on a quarterly composite from each of the sample points.2.5.3 Groundwater Groundwater samples were collected quarterly from 17 wells, all within 4300 feet of the reactors.

At each well, a static water elevation was determined and three well bore volumes were purged from the well using a groundwater pump or equivalent.

Two 1-liter and one 125-ml samples were then collected and the gamma isotopic aliquot was preserved with nitric acid. Gamma isotopic and tritium analyses were performed.

2.5.4 Drinking

Water One-liter samples were collected daily at the intake of the water purification plants for St. Joseph and Lake Township.

The daily samples were composited over 14 days and the gamma isotopic/gross beta aliquot was preserved with nitric acid. The 14-day composite samples were analyzed for gross beta, gamma isotopic and Iodine (1-131). A quarterly composite was analyzed for Tritium (H-3).

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 2.5.5 Sediment Lake Michigan shoreline sediment samples were collected semi-annually approximately 500 feet north and south of the plant centerline.

A 1-liter sample was collected from an area covered part time by wave action at each location.

The sediment samples were analyzed for gamma isotopic content.2.5.6 Milk At least once every fifteen days, a one-gallon milk sample was collected from the three remaining available farms located between 4.4 and 21 miles from the site. Two of these farms (cow) utilize a "bulk" storage tank arrangement while the third farm (goat) does not. All samples were preserved with 40 grams per gallon of sodium bisulfite at the time of collection.

Samples were analyzed for low level 1-131 and gamma-emitting radionuclides.

Due to the retirement of Glen Troy Farm's operator, the required number of indicator milk locations was not met in 2010. Though milk samples were collected at the remaining farms, the milk sampling program was considered suspended in 2010. Environmental personnel implemented broadleaf collection per the ODCM during the growing season as a result of not meeting the required number of milk indicator farms.2.5.7 Fish Approximately four pounds of fish were collected two times a year from four locations using gill nets in Lake Michigan.

The edible portions of the fish were analyzed for gamma-emitting radionuclides.

2.5.8 Food Product Two food product samples (grapes) were collected annually at the time of harvest. Samples consist of at least 300 grams of media and were collected from the highest deposition factor land sectors near CNP, with media present, and at an approximate distance of 20 miles from the plant in one of the less prevalent deposition factor land sectors. Samples were analyzed for gamma-emitting radionuclides.

2.5.9 Broadleaf

Vegetation Broadleaf vegetation sampling in lieu of milk collection was reinstated on December 16, 2004, and continued through 2010. This occurrence was necessitated by the retirement of an "indicator" milk farm operator and the inability to locate a suitable replacement farm via a special milk farm survey along with subsequent Annual Land Use Surveys. Two indicator and one control location were sampled monthly during the growing season (May -September).

Samples consisted of at least 300 grams of media and were collected from different locations within 8 miles of the plant in the highest deposition factor land sectors with media present, and at an approximate distance of 20 miles from the plant in one of the less Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 prevalent deposition factor land sectors. Samples were analyzed for gamma-emitting radionuclides and 1-131.2.5.10 TLD Monitoring Direct gamma radiation exposure was continuously monitored with the use of Panasonic UD-814 AS4 thermoluminescent dosimeters (TLDs).TLDs were posted at 27 locations in the environs surrounding CNP.2.5.11 Additional Groundwater Sample Analysis (non-ODCM required)During 2010, additional groundwater samples not required by the ODCM were collected for informational purposes.

These samples were collected at several onsite locations in 2010 and analyzed for tritium by the CNP Chemistry Department, AREVA NP and GEL laboratories.

One liter samples were collected at Steam Generator (SG) designated wells quarterly during 2010 and analyzed for gamma isotopic for informational purposes.2.5.12 Additional Groundwater Sample Analysis (NEI Groundwater Protection Initiative)

The Groundwater Protection Initiative (GPI) Sample Data for 2010 indicates no groundwater contamination in excess of the reporting threshold of 2.OOE-5 iLCi/mL for tritium.The LLD value used for counting of the samples varied between 8.17E-7 and 9.60E-7 liCi/mL, depending on which scintillation counter was used.This is well below the required minimum LLD value of 2.OOE-6 jiCi/mL.Values found above the LLD were not abnormal, unexpected, or inconsistent with past sampling history. The samples from Well #15, #24 and #27 were expected results from the release of tritiated water into the Absorption Pond. This release was through a licensed pathway and the well samples were anticipated.

The remaining results above the LLD were only slightly above the LLD and were located in areas identified to have recapture deposition of tritium from licensed radioactive gaseous release points.The sample data indicates that no radioactive spills or unidentified leaks have occurred in 2010 impacting groundwater.

The sample results indicate proper well placement to ensure the protection of the groundwater and early identification of any abnormal conditions involving groundwater.

This is validated by the demonstrated ability to monitor percolation from the Absorption Pond, with flow direction and behavior acting as described in the plant licensing documents.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 2.1 Sampling Frequency

& Type of Analysis Based on ODCM, Rev. 23, Attachment 3.19 Exposure Pathway Number of Sampling &and/or Sample Locations Collection Type of Analysis Frequency 1. Gamma Exposure-27 Quarterly Direct Radiation

-Quarterly Continuous Gross Beta and 1-131 -Weekly 2. Airborne 10 sampler -weekly Gamma Isotopic -Quarterly on filter change composite (by location)3.Groundwater 1Gamma Isotopic and Tritium -(Well Water) 17 Quarterly Quarterly Once per calendar Gamma Isotopic -Monthly on 4. Surface Water 2 dOc e aleda composite 4S2day Tritium -Quarterly on composite Gamma Isotopic, Gross Beta 5. Once per calendar and 1-131 Low Level (LL) -on day 14 day composite.

Tritium -Quarterly on composite 6. Sediment 2 Semiannually Gamma Isotopic Lake Once every 15 7. Milk 4 days or Monthly if Gamma Isotopic and 1-131 Low (if available) animals are fed Level (LL) -per sample stored feed.8. Fish (edible portion) 4 2 per year Gamma Isotopic -per sample Food Products-2 At time of harvest Gamma Isotopic -per sample Grape Broadleaf Monthly when Gamma Isotopic and 1-131 Low 10. Vegetation

-(in lieu 3 available Level (LL) -per sample of milk sampling)

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 2.2 2010 Radiological Environmental Monitoring Program Sampling Types and Locations Exposure Pathway Sample Indicator/(Sample Type Station Control Location Description Designation)

Airborne a. Filter (AP / CF) ONS-1 I 1945 feet @ 180 from Plant axis ONS-2 I 2338 feet @ 480 from Plant axis ONS-3 I 2407 feet @ 900 from Plant axis ONS-4 I 1852 feet @ 1180 from Plant axis ONS-5 I 1895 feet @ 1890 from Plant axis ONS-6 I 1917 feet @ 2100 from Plant axis NBF C 15.6 miles SSW- New Buffalo, MI SBN C 26.2 miles SE -South Bend, IN DOW C 24.3 miles ENE -Dowagiac, MI COL C 18.9 miles NNE -Coloma, MI Waterborne

a. Ground Well (WG) W-1 I 1969 feet @ 110 from Plant axis W-2 I 2302 feet @ 630 from Plant axis W-3 I 3279 feet @ 1070 from Plant axis W-4 I 418 feet @ 3010 from Plant axis W-5 I 404 feet @ 2900 from Plant axis W-6 I 424 feet @ 2730 from Plant axis W-7 I 1895 feet @ 1890 from Plant axis W-8 I 1274 feet @ 540 from Plant axis W-9 I 1447 feet @ 220 from Plant axis W-10 I 4216 feet @ 1290 from Plant axis W-11 I 3206 feet @ 1530 from Plant axis W-12 I 2631 feet @ 1620 from Plant axis W-13 I 2152 feet @ 1820 from Plant axis W-14 I 1780 feet @ 1640 from Plant axis W-1 5 I 725 feet @ 202 0 from Plant axis MW-20 I 2200 feet @ 208 0 from Plant axis (W-16)MW-21 1 2200 feet @ 180 0 from Plant axis (W-17)b. Drinking (WD) STJ C 9 miles NE -St. Joseph Public Intake Station LTW I 0.6 mile S -Lake Twp. Public Intake I Station Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 2.2 2010 Radiological Environmental Monitoring Program Sampling Types and Location (continued)

Exposure Pathway Sample Indicator/

Location Description (Sample Type Station Control Designation)

c. Surface (WS) SWL-2 500 feet S of Plant Centerline

-Site Boundary SWL-3 I 500 feet N of Plant Centerline

-Site Boundary d. Sediment (SE) SL-2 500 feet S of Plant Centerline

-Site Boundary SL-3 I 500 feet N of Plant Centerline

-Site Boundary Ingestion a. Milk (TM) MR I 4.8 miles* SE -Baroda, MI SF I 4.4 miles* SSE -Baroda, MI LF C 21 miles* S -La Porte, IN b. Fish (FH) ONS-N I 0.3 mile N, Lake Michigan ONS-S I 0.4 mile S, Lake Michigan OFS-N C 3.5 miles N, Lake Michigan OFS-S C 5.0 miles S, Lake Michigan c. Food Products ONS-G I Nearest sample to Plant in the (TF) highest D/Q land sector containing grapes.OFS-G C In a land sector containing grapes,-20 miles from the Plant, in one of the less prevalent D/Q land Sectors d. Vegetation (TV) ONSI-V I Within 8 mi. in highest annual[broadleaf vegetation ONS2-V I Wvthige D/Q land Sector taken in lieu of milk] ONS3-V I WELL-Sec A I Backup location only (Not used in 2010)OFS-V C -20 miles from the Plant, in one of the less prevalent land wind directions

Values measured with Garmin City Navigatore North America software.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 2.2 2010 Radiological Environmental Monitoring Program Sampling Types and Location (continued)

Direct Radiation T-1 I 1945 feet @ 180 from Plant axis TLD T-2 I 2338 feet @ 480 from Plant axis T-3 I 2407 feet @ 900 from Plant axis T-4 I 1852 feet @ 1180 from Plant axis T-5 I 1895 feet @ 1890 from Plant axis T-6 I 1917 feet @ 2100 from Plant axis T-7 I 2103 feet @ 360 from Plant axis T-8 I 2208 feet @ 820 from Plant axis T-9 I 1368 feet @ 1490 from Plant axis T-10 I 1390 feet @ 1270 from Plant axis T-11 I 1969 feet @ 110 from Plant axis T-12 I 2292 feet @ 630 from Plant axis NBF C 15.6 miles SSW- New Buffalo, MI SBN C 26.2 miles SE -South Bend, IN DOW C 24.3 miles ENE -Dowagiac, MI COL C 18.9 miles NNE -Coloma, MI OFT-1 C 4.5 miles NE -Pole #B294-44 OFT-2 C 3.6 miles NE -Stevensville Substation OFT-3 C 5.1 miles NE -Pole #B296-13 OFT-4 C 4.1 miles E -Pole #B350-72 OFT-5 C 4.2 miles ESE -Pole #B387-32 OFT-6 C 4.9 miles SE -Pole #B426-1 OFT-7 C 2.5 miles S -Bridgman Substation OFT-8 C 4.0 miles S -Pole #B424-20 OFT-9 C 4.4 miles ESE -Pole #B369-214 OFT-10 C 3.8 miles S -Pole #B422-99 OFT-11 C 3.8 miles S- Pole #B423-12 Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 2.3 Environmental Lower Limit of Detection (LLD) Sensitivity Requirements ODCM, Rev. 23, Attachment 3.20 Food Prod. Water Milk Air Filter Fish Sediment Analysis (pCilkg, (pCi/L) (pCi/L) (pCi/m 3) (pCilkg, (pCi/kg, wet) wet) dry)Gross Beta 4 0.01 H-3 2000 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 15 15 0.06 130 150 Cs-137 60 18 18 0.06 150 180 Ba-140 60 60 La-140 15 15* LLD for drinking water Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 2.4 Reporting Levels for Radioactivity Concentrations in Environmental Samples ODCM Rev. 23, Attachment 3.21 Food Prod. Water Milk Airborne Fish Analysis (pCi/kg, (pCilL) (pCi/L) Filter (pCi/kg, wet) (pCi/m 3) wet)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-1 37 2000 50 70 20 2000 Ba-140 200 300 La-140 200 300 Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Figure 2.1 Donald C. Cook Nuclear Plant Sampling Locations

-1 Mile Radius (See Table 2.2 for information on sampling locations)

Donald C. Cook Nuclear Plant ON-SITE REMP LOCATIONS

-I MILE RADIUS Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Figure 2.2 Donald C. Cook Nuclear Plant Sampling Locations

-10 Mile Radius (See Table 2.2 for information on sampling locations)

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Figure 2.3 Donald C. Cook Nuclear Plant Sampling Locations

-26 Mile Radius (See Table 2.2 for information on sampling locations)

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 2.6 Samples Collected During 2010 Table 2.5 below summarizes the number of samples of each type collected during the 2010 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 2010 REMP Samples Collected in 2010 Sample Type Total Indicator Control Gamma Exposure 107 48 59 Environmental TLD Air Particulate 519 311 208 Charcoal Filter 519 311 208 Groundwater 68 68 0 Surface Water 22 22 0 Drinking Water 52 26 26 Sediment (Lake) 4 4 0 Food Products 2 1 1 (grapes)Vegetation 39 33 6 (broadleaf)

Milk 78 52 26 Fish 8 4 4 Total All Types 1,418 880 538 Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 3.0 RADIOLOGICAL DATA

SUMMARY

TABLES This section summarizes the analytical results of the environmental samples that were collected during 2010. These results, shown in Table 3.1, are presented in a format similar to that prescribed in the NRC's Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1). The results are ordered by sample media type and then by radionuclide for the monitoring zones described in Section 2.3.The units for each media type are also given. Table 3.2 provides information for TLD direct radiation measurements.

The left-most column of Table 3.1 contains the radionuclide of interest, the total number of analyses for that radionuclide in 2010, and the number of measurements that exceeded the Reporting Levels found in Table 2.4. The latter are classified as"Non-routine" measurements.

The second column lists the required Lower Limit of Detection (LLD) for those radionuclides that have detection capability requirements specified in Table 2.3. 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 were 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 2010, and (3) the Control stations, which were beyond the influence of the plant. Direct radiation monitoring stations (using TLDs) were grouped into Indicator and Control stations.These are shown in Table 3.2.In each of these columns, for each radionuclide, the following are given: The mean value of all concentrations including negative values and values that were not considered "detectable".

The lowest and highest concentration.

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

A sample was considered a "detectable measurement" when the concentration exceeded 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 an LLD requirement in Attachment 3.20 or a Reporting Level listed in Attachment 3.21 of the ODCM, (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 were routinely analyzed and reported by the AREVA NP Environmental Laboratory in a gamma spectroscopy analysis were: AcTh-228, Ag-108m, Ag-11im, Ba-140/La-140, Be-7, Ce-141, Ce-144, Co-57, Co-58, Co-60, Cr-51, Cs-1 34, Cs-137, Fe-59, 1-131, K-40, Mn-54, Ru-103, Ru-106, Sb-124, Sb-125, Se-75, Zn-65 and Zr-95/Nb-95.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 The radionuclides that were routinely analyzed and reported by GEL Laboratory in a gamma spectroscopy analysis were Ac-228, Th-228, Ag-1 08m, Ag-11im, Ba-140, La-140, Be-7, Ce-141, Ce-144, Co-57, Co-58, Co-60, Cr-51, Cs-134, Cs-137, Fe-59, 1-131, K-40, Mn-54, Ru-103, Ru-106, Sb-124, Sb-125, Se-75, Zn-65, Zr-95 and Nb-95.GEL Laboroatories has been analyzing the environmental samples since June 2010, when the AREVA ELAB discontinued operations.

During this transitional period there were slight differences in how the labs treated the measurement data. The main differences were the treatment of the Th-232 decay series, the Ba-140 decay series, and the Zr-95 decay series. Where the AREVA ELAB used one daughter nuclide to infer the decay series, GEL Labs measures each of the nuclides independently.

Both analysis methods meet or exceed the reporting requirements as detailed in the ODCM. One other important difference between the laboratories analysis methods is the determination of a statistically significant positive concentration.

The AREVA ELAB has historically flagged concentrations above three time the uncertainty in the measurement, or 3a. GEL Labs maintains a check on concentrations above the MDC. In measurements that meet the AREVA ELAB 3a, but do not count above the MDC, a footnote has been added to the summary table, Table 3-1, to indicate this. All measurement information is also contained in Appendix D.Data from TLD direct radiation measurements was provided in Table 3.2. The complete listing of quarterly TLD data is provided in Table 3.3.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Air Particulates (AP) UNITS: pCi/cubic meter Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-GR-B (519)(0)Be-7 (40)(0)K-40 (40)(0)Cr-51 (40)(0)Mn-54 (40)(0)Co-57 (40)(0)Co-58 (40)(0)Fe-59 (40)(0)Co-6o (40)(0)Zn-65 (40)(0)Se-75 (40)(0)Nb-95 (40)(0)0.01 3.4E -2 ( 3.0 -823.0)E -4 (310/ 311)1.3E -1 ( 1.1 -1.6)E -1 (24/ 24)2.2E 2.3 -9.1)E -3 (1/ 24)1.9E 9.2 -15.0)E -3 (0/ 24)4.2E 4.7 -4.4)E -4 (0/ 24)-1.2E 2.9 -1.7)E -4 (0/ 24)1.1E 8.3 -6.7)E -4 (1/ 24) t-2.4E 3.5 -1.1)E -3 (0/ 24)3.6E 2.6 -6.9)E -4 (0/ 24)6.8E 1.1 -2.7)E -3 (0/ 24)2.1E -5 ( -3.8 -7.3)E -4 (0/ 24)2.OE -4 ( -1.5 -1.8)E -3 (0/ 24)COL ONS-5 0NS-2 0NS-4 ONS-2 ONS-l ONS-5 DOW NBF ONS-4 ONS-4 DOW 4. 1E -2 6.9 -4400.0)E -4 (50/ 52)I.4E -1 1.3 -1.6)E -1 (4/ 4)3.6E -3 3.2 -91.0)E -4 (0/ 4)3.9E 1.4 -9.2)E -3 (0/ 4)9.8z 2.5 -3.6)E -4 (0/ 4)6.0E -5 0.0 -8.3)E -5 (0/ 4)3.OE -4 8.2 -67.0)E -5 (0/ 4)2.1E 2.1 -2.2)E -3 (0/ 4)3.1E -4 6.4 -64.0)E -5 (0/ 4)6.1E 1.1 -2.7)E -3 (0/ 4)2.6E 2.5 -7.3)E -4 (0/ 4)9.7E -4 ( 1.8 -18.0)E -4 (0/ 4)3.6E -2 6.9 -4400.0)E -4 (206/ 208)1.2E -1 1.1 -1.5)E -1 (16/ 16)3.8E 5.2 -4.9)E -3 (0/ 16)-2.9E 1.7 -2.0)E -2 (0/ 16)-7.4E 9.1 -2.5)E -4 (0/ 16)-2.1E 1.9 -1.9)E -4 (0/ 16)-3.0E 6.4 -6.1)E -4 (0/ 16)-4.2E 2.1 -2.2)E -3 (0/ 16)1.2E 4.7 -6.4)E -4 (0/ 16)-2.5E 1.0 -1.0)E -3 (0/ 16)2.2E -5 ( -7.4 -4.8)E -4 (1/ 16) t 1.6E -4 ( -8.0 -18.0)E -4 (0/ 16)

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Air Particulates (API UNITS: pCi/cubic meter Indicator Stations Station With Highest Mean Control Stations Radionuclides (No. Analyses)Non-Routine*

Zr-95 (40)(0)Ru-103 (40)(0)Ru-106 (40)(0)Ag-108m (40)(0)Ag-I10m (40)(0)Sb-124 (40)(0)Sb-125 (40)(0)1-131 (40)(0)Cs-134 (40)(0)Cs-137 (40)(0)Ba-140 (40)(0)La-140 (40)(0)Mean Required Range LLD No. Detected--1.1E 7.9 -5.5)E -4 (0/ 24)-2.7E 1.1 -1.1)E -3 (0/ 24)5.5E 2.7 -3.1)E -3 (0/ 24)1.4E 3.5 -2.7)E -4 (0/ 24)-1.9E 5.6 -5.6)E -4 (0/ 24)-6.9E 4.8 -4.4)E -3 (0/ 24)-1.3E 1.2 -0.8)E -3 (0/ 24)-2.7E 2.5 -1.8)E -1 (0/ 24)0.06 -1.8E 3.3 -2.5)E -4 (0/ 24)0.06 -1.7E 7.5 -2.6)E -4 (0/ 24)4.4E 1.3 -5.2)E -2 (0/ 24)5.1E 1.3 -1.9)E -2 (0/ 24)Station Mean Range No. Detected-COL 4.9E 2.7 -9.0)E -4 (0/ 4)ONS-4 3.8E 2.8 -11.0)E -4 (0/ 4)ONS-6 1.5E -3 8.2 -270.0)E -5 (0/ 4)ONS-6 1.OE -4 4.0 -26.0)E -5 (0/ 4)ONS-6 2.1E 1.0 -5.5)E -4 (0/ 4)ONS-2 6.8E 1.0 -4.4)E -3 (0/ 4)DOW 3.5E -4 0.0 -6.9)E -4 (0/ 4)ONS-2 6.9E -2 1.1 -13.1)E -2 (0/ 4)COL 2.2E 2.7 -44.0)E -5 (0/ 4)ONS-2 1.4E 1.5 -26.0)E -5 (0/ 4)DOW 1.4E 8.0 -55.0)E -3 (0/ 4)ONS-1 7.0E 1.1 -16.4)E -3 (0/ 4)Mean Range No. Detected-1.7E 1.0 -0.9)E -3 (0/ 16)3.7E 8.4 -8.2)E -4 (0/ 16)-6.7E 3.3 -3.9)E -3 (0/ 16)-5.9E 3.5 -1.7)E -4 (0/ 16)-2.8E 5.5 -5.7)E -4 (0/ 16)0.0E 0-1.4 -1.6)E -3 (0/ 16)-1.1E 1.7 -0.7)E -3 (0/ 16)-1.7E 1.7 -1.7)E -1 (0/ 16)7.2E 2.0 -4.4)E -4 (0/ 16)-3.3E 3.8 -3.4)E -4 (0/ 16)4.1E -3 ( -5.1 -6.3)E -2 (0/ 16)-1.5E 2.7 -1.9)E -2 (0/ 16)

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Air Particulates (API UNITS: pCI/cubic meter Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-Ce-141 (40)(0)Ce-144 (40)(0)Th-228 (40)(0)Th-232 (20)(0)9.9E 1.0 -1.9)E -3 (0/ 24)-3.2E 2.9 -1.3)E -3 (0/ 24)5.2E -5 ( -1.0 -1.6)E -3 (0/ 24)9.3E 2.3 -2.5)E -3 (0/ 12)ONS-1 NBF DOW ONS-3 1.OE -3 1.3 -19.1)E -4 (0/ 4)3.8E 8.9 -17.0)E -4 (0/ 4)7.0E 1.2 -16.1)E -4 (0/ 4)1.4E -3 ( 3.6 -25.0)E -4 (0/ 2)-7.8E -5 ( -1.3 -1.4)E -3 (0/ 16)-1.8E -4 ( -2.7 -1.7)E -3 (0/ 16)1.4E -4 ( -8.0 -16.1)E -4 (0/ 16)2.3E -4 ( -3.5 -7.1)E -4 (0/ 8)* Non-Routine refers to radionuclides exceeding the Reporting Levels in ODCM Attachment 3.21 of the ODCM The fraction of sample analyses yielding detectable measurements (i.e., > 3 standard deviations) is shown in parentheses.

t The measured concentration was below the a postenor calculated MDC.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Charcoal Cartridge (CF) UNITS: pCi/cubic meter Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-1-131 (519) 0.07 (0)-4.1E 1.8 -1.3)E -2 (0/ 311)ONS-4 6.4E 9.8 -12.8)E -3 (0/ 52)-1.1E -2 ( -2.4 -0.0)E 0 (1/ 208) '* Non-Routine refers to radionuclides exceeding the Reporting Levels in ODCM Attachment 3.21 of the ODCM The fraction of sample analyses yielding detectable measurements (i.e., > 3 standard deviations) is shown in parentheses.

t The measured concentration was below the a posteriori calculated MDC.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -.December 2010)MEDIUM: Ground Water (INGI UNITS: nCilliter.... .... .. .. .. .. Ground Wate..r ........ n iltt Indicator Stations Station With Highest Mean Control Stations Radionuclides (No. Analyses)Non-Routine*

H-3 (68)(0)Be-7 (68)(0)K-40 (68)(0)Cr-51 (68)(0)Mn-54 (68)(0)Co-57 (68)(0)Co-58 (68)(0)Fe-59 (68)(0)Co-60 (68)(0)Zn-65 (68)(0)Se-75 (68)(0)R Mean equired Range LLD No. Detected-2000 1.5E 2-5.2 -19.2)E 2 (6/ 68)-9.5E 6.6 -2.8)E 1 (0/ 68)1.9E 1-5.4 -9.7)E 1 (11/ 68)-1.5E 0-4.6 -2.8)E 1 (0/ 68)15 -4.0E 5.4 -2.2)E 0 (1/ 68) t 5.1E 1.9 -1.7)E 0 (0/ 68)15 -4.1E 4.8 -3.3)E 0 (0/ 68)30 1.9E 8.0 -6.4)E 0 (0/ 68)15 -4.5E 3.5 -2.4)E 0 (0/ 68)30 -1.OE 0 ( -8.8 -13.6)E 0 (0/ 68)-1.3E -1 ( -4.2 -3.1)E 0 (0/ 68)Station Mean Range No. Detected-W-4 9.0E 2 6.8 -12.8)E 2 (2/ 4)MW-21 1.2E 1-4.9 -25.0)E 0 (0/ 4)W-9 5.8E 1 1.6 -8.5)E 1 (3/ 4)W-2 1.2E 1-2.8 -23.0)E 0 (0/ 4)W-10 7.8E 5.9 -22.1)E -1 (1/ 4) t W-14 5.9E -1 3.0 -130.0)E -2 (0/ 4)W-12 7.3E 5.0 -33.0)E -1 (0/ 4)W-1O 2.3E 0 7.9 -40.0)E -1 (0/ 4)W-11 1.5E 0-2.7 -2400.0)E -3 (0/ 4)W-6 1.4E 0-2.5 -6.5)E 0 (0/ 4)W-15 9.4E -1 2.7 -20.0)E -1 (0/ 4)Mean Range No. Detected-NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Ground Water (WG) UNITS: pCilliter Indicator Stations Radionuclides (No. Analyses)Non-Routine*

Nb-96 (68)(0)Zr-95 (68)(0)Ru-103 (68)(0)Ru-106 (68)(0)Ag-108m (68)(0)Ag-11m (68)(0)Sb-124 (68)(0)Sb-125 (68)(0)1-131 (68)(0)Cs-134 (68)(0)Cs-137 (68)(0)Ba-140 (68)(0)La-140 (68)(0)Required LLD 15 30 1 15 18 60 Mean Range No. Detected--1.2E 6.7 -3.0)E 0 (0/ 68)-2.1E 7.1 -6.9)E 0 (0/ 68)-8.4E 4.6 -5.2)E 0 (0/ 68)-1.8E 0-4.3 -3.1)E 1 (0/ 68)2.9E 2.5 -2.0)E 0 (0/ 68)-1.8E 6.3 -3.0)E 0 (0/ 68)-3.0E 9.8 -8.6)E 0 (0/ 68)1.3E 5.9 -6.3)E 0 (1/ 68) t-2.3E 9.2 -13.9)E 0 (0/ 68)1.9E 3.1 -4.0)E 0 (0/ 68)-1.3E -1 ( -4.7 -4.0)E 0 (0/ 68)3.6E -1 ( -1.0 -1.3)E 1 (0/ 68)Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-W-7 W-1o W-1o W-6 MW-21 W-8 W-11I 1.0E 0 3.9 -16.0)E -1 (0/ 4)1.3E 0-7.8 -47.0)E -1 (0/ 4)2.1E 2.2 -5.2)E 0 (0/ 4)7.6E 0 3.9 -15.0)E 0 (0/ 4)8.3E 9.2 -20.0)E -1 (0/ 4)1.1E 0-3.8 -27.0)E -1 (0/ 4)2.9E 0 5.5 -47.0)E -1 (0/ 4)3.OE 0 4.0 -5280.0)E -3 (0/ 4)1.9E 0-5.3 -85.0)E -1 (0/ 4)1.3E 0 4.0 -400.0)E -2 (0/ 4)7.6E 3.0 -22.0)E -1 (0/ 4)3.3E 0 0.0 -6.1)E 0 (0/ 4)NO NO NO NO NO NO NO NO NO NO NO NO DATA DATA DATA DATA DATA DATA DATA DATA DATA DATA DATA DATA W-2 W-3 W-2 W-13 W-12 15 -8.0E -2 ( -1.0 -1.3)E 1 (0/ 68)2.3E 0-4.0 -12.6)E 0 (0/ 4)NO DATA Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Ground Water (WG) UNITS: pCi/liter Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-Ce-141 (68)(0)Ce-144 (68)(0)Th-228 (68)(0)Th-232 (34)(0)-2.6E -1 ( -8.4 -4.8)E 0 (1/ 68) t-1.4E -1 ( -1.7 -1.7)E 1 (0/ 68)7.2E 7.4 -12.0)E 0 (4/ 68)2.5E 0-1.1 -1.5)E 1 (0/ 34)W-1O W-1O W-14 W-2 1.SE 0-5.2 -38.0)E -1 (0/ 4)7.4E 0-8.1 -17.0)E 0 (0/ 4)3.3E 0-1.7 -90.4)E -1 (1/ 4)9.6E 0 ( 3.8 -15.3)E 0 (0/ 2)NO DATA NO DATA NO DATA NO DATA* Non-Routine refers to radionuclides exceeding the Reporting Levels in ODCM Attachment 3.21 of the ODCM The fraction of sample analyses yielding detectable measurements (i.e., > 3 standard deviations) is shown in parentheses.

t The measured concentration was below the a posteriori calculated MDC.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Steam Generator Facility Water (SG) UNITS: pCiliter Indicator Stations Station With Highest Mean Control Stations Radionuclides (No. Analyses)Non-Routine*

GR-A (16)(0)GR-B (16)(0)H-3 (4)(0)Be-7 (16)(0)K-40 (16)(0)Cr-51 (16)(0)Mn-54 (16)(0)Co-57 (16)(0)Co-58 (16)(0)Fe-59 (16)(0)Co-60 (16)(0)Zn-65 (16)(0)Mean Required Range LLD No. Detected-6.4E 1.6 -2.0)E 0 (0/ 16)4.OE 1 2.8 -190.5)E 0 (15/ 16)2000 6.2E 1-8.4 -18.l)E 1 (0/ 4)-4.6E 0-3.9 -1.8)E 1 (0/ 16)2.8E 1-5.1 -12.9)E 1 (4/ 16)8.9E 1.7 -2.0)E 1 (0/ 16)15 -3.8E 2.3 -1.7)E 0 (0/ 16)1.9E 1.8 -2.2)E 0 (0/ 16)15 -3.OE 2.0 -2.1)E 0 (0/ 16)30 3.2E 5.1 -6.9)E 0 (0/ 16)15 4.8E 1.7 -2.4)E 0 (0/ 16)30 -2.9E 0-7.3 -1.5)E 0 (0/ 16)Station Mean Range No. Detected-SG-4 9.6E -1 1.9 -20.5)E -1 (0/ 4)SG-6 1.3E 2 ( 6.9 -19.1)E 1 (4/ 4)SG-4 1.8E 2 (0/ 1)SG-2 4.3E 0-4.2 -18.0)E 0 (0/ 4)SG-6 1.1E 2 8.8 -12.9)E 1 (4/ 4)S--I 8.0E 0-3.5 -20.0)E 0 (0/ 4)SG-4 1.4E 8.3 -17.0)E -1 (0/ 4)SG-4 5.4E 8.7 -14.0)E -1 (0/ 4)SG-2 9.0E 6.6 -210.0)E -2 (0/ 4)SG-1 1.9E 0-8.9 -46.0)E -1 (0/ 4)SG-4 8.4E -1 ( -3.2 -240.0)E -2 (0/ 4)SC-4 -1.3E 0 ( -4.0 -1.5)E 0 (0/ 4)Mean Range No. Detected-NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO NO DATA DATA Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Steam Generator Facility Water (SG) UNITS: PCi/iiter Indicator Stations Station With Highest Mean Control Stations Radionuclides (No. Analyses)Non-Routine*

Se-75 (16)(0)Nb-95 (16)(0)Zr-95 (16)(0)Ru-103 (16)(0)Ru-106 (16)(0)Ag-108m (16)(0)Ag-110m (16)(0)Sb-124 (16)(0)Sb-125 (16)(0)1-131 (16)(0)Cs-134 (16)(0)Mean Required Range LLD No. Detected-2.0E 1.9 -3.4)E 0 (0/ 16)15 -2.5E 5.2 -1.4)E 0 (0/ 16)30 -5.4E 6.1 -3.3)E 0 (0/ 16)-1.2E 0-4.6 -2.7)E 0 (0/ 16)1.5E 0-1.3 -3.0)E 1 (0/ 16)-1.5E 2.5 -2.7)E 0 (0/ 16)-2.6E 5.6 -1.7)E 0 (0/ 16)9.OE 7.1 -4.4)E 0 (0/ 16)1.6E 2.3 -7.0)E 0 (0/ 16)-4.4E 9.2 -3.0)E 0 (0/ 16)15 3.7E 1.3 -2.5)E 0 (0/ 16)Station Mean Range No. Detected-SG-5 1.3E 0 7.3 -24.0)E -1 (0/ 4)SG-5 3.6E 1.4 -1.4)E 0 (0/ 4)SG-1 3.OE 1.5 -3.3)E 0 (0/ 4)SG-1 -5.5E 3.7 -2.7)E 0 (0/ 4)S-2 6.7E 0-4.3 -30.0)E 0 (0/ 4)SG-4 2.1E 1.4 -2.7)E 0 (0/ 4)SG-2 6.3E -1 ( 0.0 -1.7)E 0 (0/ 4)sc-2 1.4E 0-3.5 -44.0)E -1 (0/ 4)SG-6 5.1E 1.9 -4.0)E 0 (0/ 4)SG-1 4.8E 3.2 -3.0)E 0 (0/ 4)SG-5 1.1E 0 ( 5.2 -20.3)E -1 (0/ 4)Mean Range No. Detected-NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Steam Generator Facility Water (SG) UNITS: pCi/liter Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-Cs-137 (16)(0)Ba-140 (16)(0)La-140 (16)(0)Ce-14 (16)(0)Ce-144 (16)(0)Ac-228 (16)(0)Th-232 (8)(0)18 -4.5E 3.0 -2.3)E 0 (0/ 16)60 4.OE 5.8 -6.0)E 0 (0/ 16)15 4.OE 3.5 -5.6)E 0 (0/ 16)-2.4E 0-1.5 -0.9)E 1 (0/ 16)-2.4E 0-1.5 -0.9)E 1 (0/ 16)-6.OE 6.8 -4.1)E 0 (0/ 16)9.8E 0-6.5 -54.0)E 0 (1/ 8)SG-1 SG-4 SG-5 SG-2 SG-2 SG-6 SG-4 5.8E 1.0 -2.3)E 0 (0/ 4)1.2E 0-1.1 -5.6)E 0 (0/ 4)1.4E 0-1.0 -29.6)E -1 (0/ 4)1.3E 0-2.2 -8.5)E 0 (0/ 4)1.3E 0-2.2 -8.5)E 0 (0/ 4)1.1E 0-1.8 -4.1)E 0 (0/ 4)3.2E 1 1.0 -5.4)E 1 (1/ 2)NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA* Non-Routine refers to radionuclides exceeding the Reporting Levels in ODCM Attachment 3.21 of the ODCM The fraction of sample analyses yielding detectable measurements (i.e., > 3 standard deviations) is shown in parentheses.

t The measured concentration was below the a posteriori calculated MDC.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Drinking Water fWDI UNITS: pCi/liter Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-GR-B (52)(0)H-3 (8)(0)Be-7 (52)(0)K-40 (52)(0)Cr-51 (52)(0)Mn-54 (52)(0)Co-57 (52)(0)Co-58 (52)(0)Fe-59 (52)(0)Co-60 (52)(0)Zn-65 (52)(0)2.5E 0 ( -3.3 -52.0)E -1 (10/ 26)3.6E 1 ( -1.9 -2.4)E 2 (0/ 4)2000-1.1E 0-1.5 -1.3)E 1 (0/ 26)5.8E 0-2.4 -5.1)E 1 (4/ 26)**2.0E 1.5 -1.4)E 1 (0/ 26)15 -4.7E 2.6 -1.6)E 0 (0/ 26)2.8E 1.7 -2.4)E 0 (0/ 26)15 -5.2i 2.8 -2.9)E 0 (0/ 26)30 2.7E 2.3 -2.9)E 0 (0/ 26)15 -3.5E 2.8 -3.4)E 0 (0/ 26)30 -1.1E 0 ( -6.5 -5.4)E 0 (0/ 26)LTW LTW LTW LTW LTW STJ L.TW LTW STJ STJ STJ 2.5E 0 ( -3.3 -52.0)E -1 (10/ 26)3.6E 1 ( -1.9 -2.4)E 2 (0/ 4)-1.1E 0 ( -1.5 -1.3)E 1 (0/ 26)5.8E 0 ( -2.4 -5.1)E 1 (4/ 26)2.0E 1.5 -1.4)E 1 (0/ 26)-2.1E 2.0 -2.2)E 0 (0/ 26)2.8E 1.7 -2.4)E 0 (0/ 26)-5.2E 2.8 -2.9)E 0 (0/ 26)5.7E 3.9 -5.1)E 0 (0/ 26)6.2E 2.4 -2.3)E 0 (0/ 26)-5.0E -1 ( -5.4 -4.8)E 0 (0/ 26)2.3E 0 ( 2.4 -510.0)E -2 (7/ 26)-2.OE 1-3.8 -2.0)E 2 (0/ 4)-1.7E 0-1.8 -1.9)E 1 (0/ 26)5.0E 0-2.8 -3.6)E 1 (1/ 26)-3.6E 0-3.9 -3.7)E 1 (0/ 26)-2.1E 2.0 -2.2)E 0 (0/ 26)-1.6E 2.7 -1.8)E 0 (0/ 26)-6.4E 2.8 -1.0)E 0 (0/ 26)5.7E 3.9 -5.1)E 0 (0/ 26)6.2E -2 ( -2.4 -2.3)E 0 (0/ 26)-5.0E -1 ( -5.4 -4.8)E 0 (0/ 26)

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Drinking Water IWD) UNITS: pCiliter Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean-Station Mean Range No. Detected-Control Stations Mean Range No. Detected-Se-75 (52)(0)Nb-95 (52)(0)Zr-95 (52)(0)Ru-103 (52)(0)Ru-106 (52)(0)Ag-108m (52)(0)Ag-110m (52)(0)Sb-124 (52)(0)Sb-125 (52)(0)1-131 (52)(0)Cs-1 34 (52)(0)Cs-1 37 (52)(0)1.5E 2.1 -1.8)E 0 (0/ 26)15 -6.4E 6.8 -3.5)E 0 (0/ 26)30 6.3E 6.4 -2.4)E 0 (0/ 26)-1.4E 0-3.7 -0.4)E 0 (0/ 26)9.8E 1.1 -2.0)E 1 (0/ 26)-1.4E 3.4 -2.7)E 0 (0/ 26)-4.3E 3.7 -4.1)E 0 (0/ 26)2.1E 3.3 -6.6)E 0 (0/ 26)-9.6E 4.2 -3.7)E 0 (0/ 26)9.9E 3.6 -4.8)E -1 (0/ 26)15 -5.2E 1.9 -1.4)E 0 (0/ 26)18 -1.1E 2.2 -1.4)E 0 (0/ 26)STJ STJ STJ LTW LTW STJ LiW LTW STJ LTW STJ LTW 4.3E 1.9 -5.6)E 0 (0/ 26)-1.6E 2.4 -1.8)E 0 (0/ 26)5.8E 2.4 -7.6)E 0 (0/ 26)-1.4E 0-3.7 -0.4)E 0 (0/ 26)9.8E 1.1 -2.0)E 1 (0/ 26)1.0E 1.3 -2.9)E 0 (0/ 26)-4.3E 3.7 -4.1)E 0 (0/ 26)2.1E 3.3 -6.6)E 0 (0/ 26)6.1E 3.8 -7.3)E 0 (0/ 26)9.9E 3.6 -4.8)E -1 (0/ 26)2.0E 2.6 -2.2)E 0 (0/ 26)-1.1E 2.2 -1.4)E 0 (0/ 26)4.3E 1.9 -5.6)E 0 (0/ 26)-1.6E 2.4 -1.8)E 0 (0/ 26)5.8E 2.4 -7.6)E 0 (0/ 26)-1.6E 0-7.5 -0.7)E 0 (0/ 26)-1.1E 2.0 -1.7)E 1 (0/ 26)1.0E 1.3 -2.9)E 0 (0/ 26)-9.6E 3.3 -3.6)E 0 (0/ 26)-7.0E 4.4 -3.4)E 0 (0/ 26)6.1E 3.8 -7.3)E 0 (0/ 26)-1.4E 3.9 -4.1)E -1 (0/ 26)2.0E 2.6 -2.2)E 0 (0/ 26)-3.9E 3.0 -2.5)E 0 (0/ 26)

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Drinkina Water IWD) UNITS: pCi/liter Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-Ba-140 (52)(0)La-140 (52)(0)Ce-141 (52)(0)Ce-144 (52)(0)Th-228 (56)(0)Th-232 (24)(0)60 2.9E 8.8 -6.2)E 0 (0/ 26)15 -4.8E 8.8 -6.2)E 0 (0/ 26)-3.OE 6.9 -3.0)E 0 (0/ 26)4.4E 8.1 -10.9)E 0 (0/ 26)-1.1E 0-1.1 -0.7)E 1 (0/ 28)1.4E 0-8.8 -10.0)E 0 (0/ 12)LIW LTW LTW LTW STJ LiW 2.9E 8.8 -6.2)E 0 (0/ 26)-4.8E 8.8 -6.2)E 0 (0/ 26)-3.0E 6.9 -3.0)E 0 (0/ 26)4.4E 8.1 -10.9)E 0 (0/ 26)-1.0Z 0-1.2 -0.6)E 1 (0/ 28)1.4E 0-8.8 -10.0)E 0 (0/ 12)2.2E 7.1 -5.8)E 0 (0/ 26)-1.1E 4.5 -3.9)E 0 (0/ 26)-8.9E 9.2 -2.8)E 0 (0/ 26)-2.0E 0-3.2 -0.7)E 1 (0/ 26)-1.0E 0-1.2 -0.6)E 1 (0/ 28)5.9E 1.1 -1.3)E 1 (U/ 12)* Non-Routine refers to radionuclides exceeding the Reporting Levels in ODCM Attachment 3.21 of the ODCM The fraction of sample analyses yielding detectable measurements (i.e., > 3 standard deviations) is shown in parentheses.

t The measured concentration was below the a postenoni calculated MDC.#f Two samples were below the a posterori calculated MDC.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Surface Water tWISt UNITS: n)Ci/liter

.... .... .... .. .. Surface Wate..r .......: n I/~t Indicator Stations Station With Highest Mean Control Stations Radionuclides (No. Analyses)Non-Routine*

H-3 (8)(0)Be-7 (22)(0)K-40 (22)(0)Cr-51 (22)(0)Mn-54 (22)(0)Co-57 (22)(0)Co-58 (22)(0)Fe-59 (22)(0)Co-60 (22)(0)Zn-65 (22)(0)Nb-95 (22)(0)R.Mean equired Range LLD No. Detected-2000 2.2E 2-1.5 -58.0)E 1 (0/ 8)2.7E 0-6.3 -7.4)E 1 (0/ 22)2.3E 0 ( -5.0 -4.9)E 1 (0/ 22)4.6E 1.4 -2.3)E 1 (0/ 22)15 -2.2E -1 ( -1.0 -2.6)E 0 (0/ 22)-1.4E 1.9 -1.1)E 0 (0/ 22)15 3.9E 1.3 -9.2)E 0 (0/ 22)30 5.9E 1.0 -0.7)E 1 (0/ 22)15 3.6E 8.2 -8.0)E 0 (0/ 22)30 -2.7E 0-4.2 -0.7)E 1 (0/ 22)15 6.7E -1 ( -1.9 -5.1)E 0 (0/ 22)Station Mean Range No. Detected-SWL-3 2.4E 2-1.5 -58.0)E 1 (0/ 4)SWL-3 8.9E 0-6.9 -74.0)E 0 (0/ 11)SWL-2 3.1E 0-2.5 -4.9)E 1 (0/ 11)SWL-2 1.8E 0-6.0 -22.5)E 0 (0/ 11)SWL-3 -2.1E 1.0 -0.8)E 0 (0/ 11)SWL-2 1.1E 1.9 -1.1)E 0 (0/ 11)SWL-3 7.1E 1.3 -9.2)E 0 (0/ 11)SWL-2 1.6E 0-2.0 -7.0)E 0 (0/ 11)SWL-3 8.5E 1.4 -8.0)E 0 (0/ 11)SWL-3 -6.4E 3.2 -7.0)E 0 (0/ 11)SWL-2 7.3E 1.9 -5.1)E 0 (0/ 11)Mean Range No. Detected-NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA Donald C. Cook Nuclear Plan t Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)Illl:llll IU- /IAIO t I IhIrrQ. III4t..lwl .. ,.JlW ll. l ffKI qJll ..........

l~i;Indicator Stations Radionuclides (No. Analyses)Non-Routine*

Se-75 (22)(0)Zr-95 (22)(0)Ru-103 (22)(0)Ru-106 (22)(0)Ag-108m (22)(0)Ag-I10m (22)(0)Sb-124 (22)(0)Sb-125 (22)(0)1-131 (22)(0)Cs-134 (22)(0)Cs-1 37 (22)(0)Ba-140 (22)(0)Mean Required Range LLD No. Detected-2.8E 2.4 -3.4)E 0 (0/ 22)30 7.1E 2.7 -9.7)E 0 (0/ 22)-7.5E 3.6 -9.0)E 0 (0/ 22)1.8E 0-7.9 -28.0)E 0 (0/ 22)-7.1E 1.5 -1.3)E 0 (0/ 22)-7.8E 7.5 -0.9)E 0 (0/ 22)1.2E 3.4 -17.0)E 0 (0/ 22)7.3E 6.0 -4.8)E 0 (0/ 22)-1.0E 0-5.2 -1.8)E 1 (0/ 22)15 -3.0E 3.1 -1.1)E 0 (0/ 22)18 1.1E 1.6 -1.6)E 0 (0/ 22)60 -6.9E 1.1 -0.4)E 1 (0/ 22)Station With Highest Mean Station Mean Range No. Detected-SWL-3 1.2E 1.3 -3.4)E 0 (0/ 11)SWL-2 8.4E 2.0 -6.8)E 0 (0/ 11)SWL-2 -3.5E 3.6 -9.0)E 0 (0/ 11)SWL-3 3.4E 0-3.5 -28.0)E 0 (0/ 11)SWL-2 5.9E 1.5 -0.5)E 0 (0/ 11)SWL-3 -4.4E 3.1 -0.9)E 0 (0/ 11)SWL-2 1.5E 3.0 -2.8)E 0 (0/ 11)SWL-2 1.4E 0-1.7 -4.8)E 0 (0/ 11)SWL-2 1.9E 0-7.5 -18.0)E 0 (0/ 11)SWL-2 -2.4E 2.3 -1.1)E 0 (0/ 11)SWL-2 2.5E 1.4 -1.6)E 0 (0/ 11)SWL-2 3.5E 3.0 -4.3)E 0 (0/ 11)Control Stations Mean Range No. Detected-NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA La-140 (22)(0)15 -3.3E 1.1 -0.4)E 1 (0/ 22)SWL-2 3.2E -1 ( -3.0 -4.3)E 0 (0/ 11)NO DATA Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Surface Water (WS) UNITS: pCi/liter Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-Ce-141 (22)(0)Ce-144 (22)(0)Ac-228 (28)(0)Th-232 (8)(0)-1.2E -1 ( -4.6 -3.6)E 0 (0/ 22)-1.3E 0 ( -1.6 -0.6)E 1 (0/ 22)1.1E -1 ( -7.8 -5.9)E 0 (0/ 28)3.6E 0 ( -4.5 -16.0)E 0 (0/ 8)SWL-2 SWL-2 SWL-2 SWL-2-7.6E 3.7 -3.6)E 0 (0/ 11)-8.6E 7.5 -6.4)E 0 (0/ 11)5.5E 5.5 -5.9)E 0 (0/ 14)5.0E 0-4.5 -16.0)E 0 (0/ 4)NO DATA NO DATA NO DATA NO DATA* Non-Routine refers to radionuclides exceeding the Reporting Levels in ODCM Attachment 3.21 of the ODCM The fraction of sample analyses yielding detectable measurements (i.e., > 3 standard deviations) is shown in parentheses.

t The measured concentration was below the a postenori calculated MDC.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Sediment (SE)UNITS: DCIIkO dri Indicator Stations Radionuclides (No. Analyses)Non-Routine*

Be-7 (4)(0)K-40 (4)(0)Cr-51 (4)(0)Mn-54 (4)(0)Co-57 (4)(0)Co-58 (4)(0)Fe-59 (4)(0)Co-60 (4)(0)Zn-65 (4)(0)Se-75 (4)(0)Nb-95 (4)(0)Mean Required Range LLD No. Detected-1.6E 1-3.4 -6.0)E 1 (0/ 4)8.6E 3 8.2 -8.9)E 3 (4/ 4)4.2E 1-4.0 -99.9)E 0 (0/ 4)-2.6E 0-1.4 -0.7)E 1 (0/ 4)6.8E 0-1.1 -15.1)E 0 (0/ 4)4.1E 0-2.5 -20.9)E 0 (0/ 4)-4.4E 1-1.3 --0.1)E 2 (0/ 4)-1.5E 1.3 -1.5)E 1 (0/ 4)-2.1E 1-1.1 -0.2)E 2 (0/ 4)-6.9E 1.1 -1.2)E 1 (0/ 4)-1.8E 0-2.3 -4.3)E 1 (0/ 4)Station With Highest Mean Station Mean Range No. Detected-SL-3 1.9E 1 8.0 -29.6)E 0 (0/ 2)SL-2 8.7E 3 8.5 -8.9)E 3 (2/ 2)SL-3 4.8E 1-4.0 -99.9)E 0 (0/ 2)SL-2 -2.0E 0-6.4 -2.4)E 0 (0/ 2)SL-2 1.0E 1 ( 5.4 -15.1)E 0 (0/ 2)SL-3 9.2E 0-2.5 -20.9)E 0 (0/ 2)SL4 -1.8E 1-2.6 --0.9)E 1 (0/ 2)SL-2 5.5E 0-3.5 -14.6)E 0 (0/ 2)SL-3 1.4E 0-1.2 -1.5)E 1 (0/ 2)SL-2 6.0E 1.1 -1.2)E 1 (0/ 2)SL-3 1.OE 1-2.3 -4.3)E 1 (0/ 2)Control Stations Mean Range No. Detected-NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA Donald C. Cook Nuclear Plan t Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Sediment (SE) UNITS: pCi/kq dry Indicator Stations Station With Highest Mean Control Stations Radionuclides (No. Analyses)Non-Routine*

Zr-95 (4)(0)Ru-103 (4)(0)Ru-106 (4)(0)Ag-108m (4)(0)Ag-110m (4)(0)Sb-124 (4)(0)Sb-125 (4)(0)1-131 (4)(0)Cs-134 (4)(0)Cs-1 37 (4)(0)Ba-140 (4)(0)La-140 (4)(0)Ce-141 (4)(0)Mean Required Range LLD No. Detected-3.6E 0-1.9 -2.6)E 1 (0/ 4)-9.1E 0-3.8 -1.1)E 1 (0/ 4)-1.3E 1-6.4 -2.3)E 1 (0/ 4)-8.1E 9.2 -11.2)E 0 (0/ 4)-5.1E 0-1.7 -0.6)E 1 (0/ 4)-1.1E 1-2.7 -0.2)E 1 (0/ 4)1.5E 1-1.3 -7.7)E 1 (0/ 4)-1.3E 1-1.3 -0.6)E 2 (0/ 4)150 1.5E 1 ( 5.5 -28.6)E 0 (0/ 4)180 7.7E 0 1.6 -11.6)E 0 (0/ 4)3.4E 1-5.4 -13.8)E 1 (0/ 4)1.4E 0-3.7 -3.7)E 1 (0/ 4)-2.4E 0-2.2 -1.6)E 1 (0/ 4)Station Mean Range No. Detected-SL-2 1.OE 1-5.0 -25.6)E 0 (0/ 2)SL-3 -1.7E 0-1.5 -1.1)E 1 (0/ 2)SL-2 -4.8E 0-2.6 -1.6)E 1 (0/ 2)SL-2 1.OE 0-9.2 -11.2)E 0 (0/ 2)SL-2 -3.3E 0-1.2 -0.6)E 1 (0/ 2)SL-3 -6.2E 0-1.4 -0.2)E 1 (0/ 2)SL-2 4.0E 1 4.0.- 76.5)E 0 (0/ 2)SLW 5.0E 1 ( 3.6 -6.4)E 1 (0/ 2)SL-2 1.8E 1 ( 7.5 -28.6)E 0 (0/ 2)SL-2 9.8E 0 7.9 -11.6)E 0 (0/ 2)SL-2 9.1E 1 ( 4.3 -13.8)E 1 (0/ 2)SL-3 3.1E 1 ( 2.6 -3.7)E 1 (0/ 2)SL-2 2.3E 0-1.2 -1.6)E 1 (0/ 2)Mean Range No. Detected-NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Sediment (SE) UNITS: pCi/kq dry Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-ce-14 (4)(0)Th-228 (4)(0)Th-232 (2)(0)-2.6E 0-4.4 -4.8)E 1 (0/ 4)1.3E 2 ( 9.8 -16.5)E 1 (U/ 4)1.1E 2 ( 8.5 -13.1)E 1 (1/ 2)SL-2 SL-3 SL-2 3.2E 1 ( 1.7 -4.8)E 1 (0/ 2)1.4E 2 ( 1.2 -1.7)E 2 (0/ 2)1.3E 2 NO DATA NO DATA NO DATA (U/ 1)Non-Routine refers to radionuclides exceeding the Reporting Levels in ODCM Attachment 3.21 of the ODCM The fraction of sample analyses yielding detectable measurements (i.e., > 3 standard deviations) is shown in parentheses.

t The measured concentration was below the a posteriori calculated MDC.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Milk (TM) UNITS: pCI/liter Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-Be-7 (78)(0)K-40 (78)(0)Cr-51 (78)(0)Mn-54 (78)(0)Co-57 (78)(0)Co-58 (78)(0)Fe-59 (78)(0)Co-60 (78)(0)Zn-65 (78)(0)Se-75 (78)(0)Nb-95 (78)(0)-1.7E 0-3.3 -2.5)E 1 (0/ 52)1.7E 3 ( 1.3 -2.1)E 3 (52/ 52)-6.1E 3.0 -3.3)E 1 (0/ 52)9.5E 3.6 -3.9)E 0 (0/ 52)2.2E 1.9 -2.8)E 0 (0/ 52)-2.1E 3.8 -3.4)E 0 (0/ 52)6.4E 5.6 -11.4)E 0 (0/ 52)5.4E 5.6 -3.9)E 0 (0/ 52)-1.7E 0-1.4 -1.1)E 1 (0/ 52)-2.8E 5.8 -4.5)E 0 (0/ 52)1.6E 6.9 -4.4)E 0 (1/ 52) t LF MR SF SF MR SF MR SF LF SF MR 1.1E 4.2 -3.4)E 1 (0/ 26)1.8E 3 ( 1.5 -2.1)E 3 (26/ 26)-3.8E 1.5 -3.3)E 1 (0/ 26)2.6E 3.6 -3.9)E 0 (0/ 26)3.4E 1.9 -2.8)E 0 (0/ 26)1.8E 3.8 -2.5)E 0 (0/ 26)1.2E 0-4.8 -11.4)E 0 (0/ 26)4.8E 2.2 -2.7)E 0 (0/ 26)-1.OE 0-8.4 -12.4)E 0 (0/ 26)-2.7E 5.8 -1.7)E 0 (0/ 26)1.7E 4.3 -2.4)E 0 (0/ 26)1.1E 4.2 -3.4)E 1 (0/ 26)1.5E 3 ( 1.3 -1.6)E 3 (26/ 26)-4.3E 0-3.0 -2.0)E 1 (0/ 26)-1.2E 3.7 -5.2)E 0 (0/ 26)3.8E 2.8 -2.6)E 0 (0/ 26)-9.9E 3.8 -4.3)E 0 (0/ 26)7.1E 8.6 -9.3)E 0 (0/ 26)4.3E 2.2 -3.3)E 0 (0/ 26)-1.OE 0-8.4 -12.4)E 0 (0/ 26)-5.3E 8.6 -3.2)E 0 (0/ 26)-1.OE -1 ( -4.0 -5.8)E 0 (0/ 26)

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Milk (TM) UNITS: pCi/liter Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-Zr-95 (78)(0)Ru-103 (78)(0)Ru-106 (78)(0)Ag-108m (78)(0)Ag-110m (78)(0)Sb-124 (78)(0)Sb-125 (78)(0)1.131 (78)(0)Cs-1 34 (78)(0)Cs-137 (78)(0)Ba-140 (78)(0)La-140 (78)(0)Ce-141 (78)(0)-5.4E 7.9 -7.2)E 0 (0/ 52)-8.4z 4.5 -3.6)E 0 (0/ 52)-3.OE 0-3.5 -2.9)E 1 (0/ 52)-2.8E 4.0 -3.2)E 0 (0/ 52)-5.9E 7.1 -6.3)E 0 (0/ 52)3.5E 6.3 -11.9)E 0 (0/ 52)-3.2E 1.9 -0.9)E 1 (0/ 52)5.4E 3.8 -6.5)E -1 (0/ 52)15 -1.4E 2.8 -3.0)E 0 (0/ 52)18 2.3E 5.0 -5.0)E 0 (1/ 52) t 60 5.4E 5.6 -8.3)E 0 (0/ 52)15 4.0E 5.6 -8.3)E 0 (0/ 52)-9.3E 9.0 -4.9)E 0 (0/ 52)LF SF LF LF SF SF SF MR SF MR LF LF MR 1.3E 0-4.7 -8.8)E 0 (0/ 26)-7.1Z 4.4 -3.6)E 0 (0/ 26)-9.1E 2.8 -1.4)E 1 (0/ 26)1.9E 2.0 -5.4)E 0 (0/ 26)-2.0E 5.6 -4.8)E 0 (0/ 26)5.9E 4.9 -11.9)E 0 (0/ 26)3.OE 9.2 -7.4)E 0 (0/ 26)6.OE 2.8 -6.5)E -1 (0/ 26)-1.0E 2.8 -3.0)E 0 (0/ 26)6.6E 3.0 -5.0)E 0 (1/ 26) t 1.8E 0-4.2 -10.0)E 0 (0/ 26)8.7E 4.2 -10.0)E 0 (0/ 26)-6.5E 9.0 -4.9)E 0 (0/ 26)1.3E 0-4.7 -8.8)E 0 (0/ 26)-1.2E 0-7.4 -1.5)E 0 (0/ 26)-9.1E 2.8 -1.4)E 1 (0/ 26)1.9E 2.0 -5.4)E 0 (0/ 26)-6.9E 6.7 -5.3)E 0 (0/ 26)-9.3E 1.3 -0.8)E 1 (0/ 26)-5.0E 1.4 -0.9)E 1 (0/ 26)-4.5E 4.3 -4.7)E -1 (0/ 26)-1.6E 3.7 -3.6)E 0 (0/ 26)-3.4E 5.8 -3.1)E 0 (0/ 26)1.8E 0-4.2 -10.0)E 0 (0/ 26)8.7E 4.2 -10.0)E 0 (0/ 26)-1.4E 0-9.5 -3.0)E 0 (0/ 26)

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Milk (TM) UNITS: pCi/liter Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-Ce-144 (78)(0)Th-228 (78)(0)Th-232 (39)(0)1.3E 0-1.9 -2.4)E 1 (0/ 52)1.1E 0 C -7.5 -18.1)E 0 (3/ 52)-5.5E 1.9 -2.0)E 1 (0/ 26)SF MR LF 1.4E 0-1.7 -2.4)E 1 (0/ 26)1.3E 0-7.5 -18.1)E 0 (3/ 26)5.2E 7.6 -11.4)E 0 (0/ 13)-1. 4E 0-1.5 -1.0)E 1 (0/ 26)1.OE 5.3 -8.2)E 0 (0/ 26)5.2E 7.6 -11.4)E 0 (0/ 13)* Non-Routine refers to radionuclides exceeding the Reporting Levels in ODCM Attachment 3.21 of the ODCM The fraction of sample analyses yielding detectable measurements (i.e., > 3 standard deviations) is shown in parentheses.

t The measured concentration was below the a posteriori calculated MDC.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)Radionuclides (No. Analyses)Non-Routine*

Be-7 (8)(0)K-40 (8)(0)Cr-51 (8)(0)Mn-54 (8)(0)Co-57 (8)(0)Co-S8 (8)(0)Fe-59 (8)(0)Co-60 (8)(0)Zn-65 (8)(0)Se-75 (8)(0)Nb-95 (8)(0)Zr-95 (8)(0)MEDIUM: Fish (FHI Indicator Stations Mean Station Required Range LLD No. Detected-1.6E 1 OFS-S ( 0.0 -3.3)E 1 (0/ 4)2.7E 3 ONS-S ( 2.0 -3.3)E 3 (4/ 4)-3. 1E 1 OFS-S-7.0 -0.7)E 1 (0/ 4)130 2.8E 0 ONS-N-2.2 -15.0)E 0 (0/ 4)-2.1E 0 OFS-S-5.6 -1.9)E 0 (0/ 4)130 -1.1E 0 ONS-S ( -1.0 -0.5)E 1 (0/ 4)260 6.9E -1 ONS-S-2.4 -2.7)E 1 (0/ 4)130 3.8E 0 ONS-N-7.5 -18.0)E 0 (0/ 4)260 1.7E 0 ONS-N-1.2 -2.2)E 1 (0/ 4)2.8E 0 ONS-N-1.3 -14.0)E 0 (0/ 4)-4.8E 0 'OFS-S ( -1.1 -0.2)E 1 (0/ 4)-1.2E 1 OFS-N ( -2.5 -0.5)E 1 (0/ 4)UNITS: pCi/kq wet Station With Highest Mean Mean Range No. Detected-2.8E 1-2.5 -8.1)E 1 (0/ 2)3.2E 3 3.2 -3.3)E 3 (2/ 2)4.4E 1 3.1 -5.6)E 1 (0/ 2)6.4E 0-2.2 -15.0)E 0 (0/ 2)-1.1E 0-3.0 -0.7)E 0 (0/ 2)3.6E 0 2.7 -4.6)E 0 (0/ 2)1.2E 1-2.9 -27.0)E 0 (0/ 2)8.3E 0-1.4 -18.0)E 0 (0/ 2)7.8E 0-6.3 -22.0)E 0 (0/ 2)6.4E 0-1.2 -14.0)E 0 (0/ 2)3.5E -1 ( -1.3 -2.0)E 0 (0/ 2)-6.2E 0 ( -7.0 --5.4)E 0 (0/ 2)Control Stations Mean Range No. Detected-2.5E 1-3.3 -8.1)E 1 (0/ 4)2.7E 3 ( 2.3 -3.0)E 3 (4/ 4)2.9E 1 ( 1.2 -5.6)E 1 (0/ 4)3.5E 3.3 -2.0)E 0 (0/ 4)-1.9E 0-4.4 -0.7)E 0 (0/ 4)-3.8E 0-9.0 -1.4)E 0 (0/ 4)-1.3E 1-3.0 --0.3)E 1 (0/ 4)-1.9E 0-6.9 -2.0)E 0 (0/ 4)-3.9E 0-1.3 -0.6)E 1 (0/ 4)-1.5E 0-3.0 -1.5)E 0 (0/ 4)-3.9E 0 ( -1.1 -0.2)E 1 (0/ 4)-7.4E 0 ( -1.9 -0.2)E 1 (0/ 4)

Donald C. Cook Nuclear Plant t Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)U .tIU ;in I~l I lurr rl;)ll rN[ ~ tl L Radionuclides (No. Analyses)Non-Routine*

Ru-103 (8)(0)Ru-106 (8)(0)Ag-108m (8)(0)Ag-110m (8)(0)Sb-124 (8)(0)Sb-125 (8)(0)1-131 (8)(0)Cs-134 (8)(0)Cs-137 (8)(0)Ba-140 (8)(0)La-140 (8)(0)Ce-141 (8)(0)Indicator Stations Mean Required Range LLD No. Detected*-

-3.8E 0-1.6 -0.9)E 1 (0/ 4)-2.2E 1-9.0 -0.2)E 1 (0/ 4)-6.1E 0-2.2 -0.3)E 1 (0/ 4)-6.7E 6.3 -9.0)E 0 (0/ 4)4.6E 0 0.0 -1.3)E 1 (0/ 4)-7.8E 0-1.6 --0.3)E 1 (0/ 4)-7.4E 0-5.1 -1.4)E 1 (0/ 4)130 5.4E 0 ( 8.9 -140.0)E (0/ 4)150 9.4E 0 ( 7.0 -13.0)E 0 (0/ 4)1.7E 1 0.0 -4.9)E 1 (0/ 4)9.1E 0 0.0 -2.0)E 1 (0/ 4)-1.1E 1-2.6 -0.2)E 1 (0/ 4)-1 Station With Highest Mean Station Mean Range No. Detected-ONS-S 1. 9E 0-4.8 -8.7)E 0 (0/ 2)ONS-N 9.3E -1 ( 0.0 -1.9)E 0 (0/ 2)ONS-S -2.6E 0-5.8 -0.7)E 0 (0/ 2)OFS-N 3.2E 0-5.6 -12.0)E 0 (0/ 2)ONS-S 6.7E 0 4.6 -130.0)E -1 (0/ 2)OFS-N 3.9E 0 8.0 -70.0)E -1 (0/ 2)OFS-S 2.58 1 1.3 -3.8)E 1 (0/ 2)ONS-N 8.2E 0 2.5 -14.0)E 0 (0/ 2)ONS-N 1.OE 1 7.0 -13.0)E 0 (0/ 2)ONS-S 3.5E 1 2.0 -4.9)E 1 (0/ 2)ONS-S 1.5E 1 1.1 -2.0)E 1 (0/ 2)OFS-S -1.8E 0-3.6 -0.0)E 0 (0/ 2)Control Stations Mean Range No. Detected"-3.4E 0-7.2 -0.7)E 0 (0/ 4)-2.4E 1-7.2 -1.5)E 1 (0/ 4)-5.3E 0-8.3 --1.9)E 0 (0/ 4)-1.8E 0-1.1 -1.2)E 1 (0/ 4)-1.3E 1-3.1 -1.1)E 1 (0/ 4)-8.2E 0-3.8 -0.7)E 1 (0/ 4)2.1E 1-5.4 -40.0)E 0 (0/ 4)5.AE 2.9 -6.8)E 0 (0/ 4)2.4E 0-8.0 -26.5)E 0 (1/ 4)1.6E 1 0.0 -4.0)E 1 (0/ 4)5.6E 0 0.0 -1.1)E 1 (0/ 4)-7.0E 0-2.4 -0.0)E 1 (0/ 4)

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Fish (FH) UNITS: pCi/kq wet Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-Ce-144 (8)(0)Th-228 (8)(0)Th-232 (4)(0)2.6E 1 ( -1.0 -7.1)E 1 (0/ 4)5.2E 0 ( -5.9 -28.2)E 0 (0/ 4)6.7E 1 ( 4.2 -9.2)E 1 (0/ 2)ONS-N ONS-S ONS-N 4.5E 1 ( 1.9 -7.1)E 1 (0/ 2)1.1E 1 ( -5.9 -28.2)E 0 (0/ 2)9.2E 1-1.3E 1 ( -3.4 -0.4)E 1 (0/ 4)-2.9E 0 ( -1.7 -0.8)E 1 (0/ 4)-4.5E 1 ( -5.0 --3.9)E 1 (0/ 2)(0/ 1)* Non-Routine refers to radionuclides exceeding the Reporting Levels in ODCM Attachment 3.21 of the ODCM The fraction of sample analyses yielding detectable measurements (i.e., > 3 standard deviations) is shown in parentheses.

t The measured concentration was below the a postenon calculated MDC.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)III. I

= t't: II. ..... I, IVIEJUIVI.

rUUU VIoUUUIEI

~I I *I URI10 I .iIFUn we Indicator Stations Radionuclides (No. Analyses)Non-Routine*

Be-7 (2)(0)K-40 (2)(0)Cr-51 (2)(0)Mn-54 (2)(0)Co-57 (2)(0)Co-58 (2)(0)Fe-59 (2)(0)Co-60 (2)(0)Zn-65 (2)(0)Se-75 (2)(0)Nb-95 (2)(0)Mean Required Range LLD No. Detected-3.3E 1 (0/1.6E 3 (1/5.3E 0 (0/-2.4E 0 (0/1.OE 0 (0/6.OE -1 (0/2.5E 0 (0/8.9E -2 (0/-1.2E 1 (0/2.4E 0 (0/Station With Highest Mean Station Mean Range No. Detected-OFS-G 1. 1E 2 (1/ 1)OFS-G 2.3E 3 (1/ 1)OFS-G 1.9E 1 (0/ 1)OFS-G 2.4E 0 (0/ 1)ONS-G 1. 0E 0 (o/ 1)ONS-G 6.0E -1 (0/ 1)ONS-G 2.5E 0 (0/ 1)OFS-G 2.3E 0 (0/ 1)OFS-G -4. 1E 0 (0/ 1)ONS-G 2.4E 0 (0/ 1)Control Stations Mean Range No. Detected-1.1E 2 (1/2.3E 3 (1/1.9E 1 (0/2.4E 0 (0/4.7E -1 (0/-6.1E -1 (0/-5.7E 0 (0/2.3E 0 (0/-4.1E 0 (0/-1.3E -1 (0/-9.1E -2 7.4E -1 ONS-G 7.4E -1 (0/ 1)(0/ 1)(0/ 1)

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Food Products (TF) UNITS: pCi/kaq wet Indicator Stations Station With Highest Mean Control Stations Radionuclides (No. Analyses)Non-Routine*

Zr-95 (2)(0)Ru-1 03 (2)(0)Ru-106 (2)(0)Ag-108m (2)(0)Ag-110m (2)(0)Sb-124 (2)(0)Sb-125 (2)(0)1-131 (2)(0)Cs-134 (2)(0)Cs-137 (2)(0)Ba-140 (2)(0)La-140 (2)(0)Ce-141 (2)(0)Mean Required Range LLD No. Detected--4.0E -1 (0/-1.6E 0 (0/-2.6E 1 (0/-1. 4E 0 (0/-2.6E 0 (0/5.OE 0 (0/6.8E 0 (0/60 -2.2E 0 (0/60 3.8E 0 (0/60 -6.8E -1 (0/8.4E 0 (0/6.8E -1 (0/2.5E 0 (0/Station Mean Range No. Detected-ONS-G -4.OE -1 (C OFS-G -1.2E 0 (C OFS-G -1. 4E 1 (C OFS-G -1.2E 0 (C OFS-G 3.6E -1 (C ONS-G 5.0E 0 (C ONS-G 6.8E 0 (C OFS-G -1.2E -1 (C ONS-G 3.8E 0 (C OFS-G 2.OE 0 (o ONS-G 8.4E 0 (C ONS-G 6.8E -1 (C ONS-G 2.5E 0 I, I, I, I, I, I'I, I, I, I,'I Mean Range No. Detected--6.8E 0 1) (0/-1.2E 0 1) (0/-1.4E I 1) (0/-1.2E 0 1) (0/3.6E -1 1) (0/-1.4E 0 1) (0/4.3E 0 1) (0/-1.2E -1 1) (0/-5.5E 0 1) (0/2.0E 0 1) (0/-4.5E -1 1) (0/-3.3E 0 1) (0/-2.5E 0 1) (0/(0 Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Food Products (TF) UNITS: pCI/kq wet Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-Ce-14 (2)(0)Th-228 (4)(0)-2.7E 0 (0/ 1)-6.3E 0-1.4 -0.1)E 1 (0/ 2)ONS-G OFS-G-2.7E 0-6.8E 0 (0/ 1)3.2E 0 ( 2.1 -4.3)E 0 (0/ 2)(0/ 1)3.2E 0 ( 2.1 -4.3)E 0 (0/ 2)Non-Routine refers to radionuclides exceeding the Reporting Levels in ODCM Attachment 3.21 of the ODCM The fraction of sample analyses yielding detectable measurements (i.e., > 3 standard deviations) is shown in parentheses.

t The measured concentration was below the a posterion calculated MDC.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)NAMrl"M %I- -ýff I IlE'TO. .^4/lI. ...^.*f:ILlI aUJ~fl~I onI VI U,. IC q'1I we Indicator Stations Radionuclides (No. Analyses)Non-Routine*

Be-7 (39)(0)K-40 (39)(0)Cr-51 (39)(0)Mn-54 (39)(0)Co-57 (39)(0)Co-58 (39)(0)Fe-59 (39)(0)Co-60 (39)(0)Zn-65 (39)(0)Se-75 (39)(0)Nb-95 (39)(0)Mean Required Range LLD No. Detected-1.5E 3 ( 0.0 -4.5)E 3 (26/ 33)3.0E 3 ( 1.2 -6.8)E 3 (33/ 33)-1.3E 1 ( -5.7 -2.8)E 2 (0/ 33)3.4E -1 ( -1.0 -2.6)E 1 (0/ 33)5.5E -1 (-1.1 -0.6)E 1 (0/ 33)-7.5E" --2.9 -3.1)E 1 (0/ 33)-2.5E 0-4.7 -6.3)E 1 (0/ 33)-2.1E -2 ( -2.3 -3.2)E 1 (0/ 33)-5.6E 0 ( -3.7 -6.6)E 1 (0/ 33)1.3E -3 ( -1.3 -1.6)E 1 (0/ 33)2.9E 0 ( -3.1 -4.1)E 1 (0/ 33)Station With Highest Mean Station Mean Range No. Detected-ONS3-V 1.7E 3 ( 0.0 -4.5)E 3 (14/ 16)ONS2-V 5.4E 3 (1/ 1)ONS2-V 2.1E 2 (0/ 1)ONS2V 8. OE 0 (0/ 1)ONS2-V 3.6E 0 (0/ 1)OFS-V 4.3E 0-7.0 -28.0)E 0 (0/ 6)ONS1-V 5.0E 3.9 -6.3)E 1 (0/ 16)ONS2-V 7.OE 0 (0/ 1)ONS2-V 8.0E 0 (0/ 1)ONSS-V 1.9E 0 C -1.0 -1.6)E 1 (0/ 16)Control Stations Mean Range No. Detected-1.5E 3 5.6 -24.7)E 2.(6/ 6)3.6E 3 1.7 -5.1)E 3 (6/ 6)-3.8E 1-1.6 -0.5)E 2 (0/ 6)-8.4E 6.2 -6.0)E 0 (0/ 6)1.2E 0-7.2 -17.6)E 0 (0/ 6)4.3E 0-7.0 -28.0)E 0 (0/ 6)-1.3E 1-4.1 -0.7)E 1 (0/ 6)4.1E 5.0 -4.0)E 0 (0/ 6)5.4E 3.8 -5.4)E 1 (0/ 6)-4.0E 0-1.6 -0.2)E 1 (0/ 6)3.3E -3 ( -7.0 -5.5)E 0 (0/ 6)ONS2-V 6.0E 0 (0/ 1)

Donald C. Cook Nuclear Plan t Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Vegetation (TV) UNITS: pCilkg wet Indicator Stations Radionuclides (No. Analyses)Non-Routine*

Zr-95 (39)(0)Ru-103 (39)(0)Ru-106 (39)(0)Ag-108m (39)(0)Ag-110m (39)(0)Sb-124 (39)(0)Sb-125 (39)(0)1-131 (39)(0)Cs-134 (39)(0)Cs-1 37 (39)(0)Ba-140 (39)(0)La-140 (39)(0)Ce-141 (39)(0)Mean Required Range LLD No. Detected--1.2E 0-6.0 -2.2)E 1 (0/ 33)-2.1E 0-4.7 -1.8)E 1 (0/ 33)-8.5E 0-1.2 -1.3)E 2 (0/ 33)-4.OE 1.3 -0.7)E 1 (0/ 33)1.7E 2.5 -3.3)E 1 (0/ 33)-5.7E 0-8.2 -3.6)E 1 (0/ 33)7.2E 3.5 -5.6)E 1 (1/ 33) t 60 2.7E 0-2.0 -2.9)E 1 (0/ 33)60 1.2E 0-2.0 -2.3)E 1 (0/ 33)60 8.5E 0-3.3 -13.5)E 1 (3/ 33) *-1.5E 1-2.6 -0.8)E 2 (0/ 33)-1.7E 1-2.6 -0.8)E 2 (0/ 33)-3.9E 4.4 -2.9)E 1 (0/ 33)Station With Highest Mean Station Mean Range No. Detected-OFS-V 6.7E 0-8.0 -25.0)E 0 (0/ 6)ONS1-V 1.9E 0-6.7 -18.0)E 0 (0/ 16)ONS3-V -2.8E 0-1.0 -1.3)E 2 (0/ 16)ON5l-V -2.4E 6.1 -4.7)E 0 (0/ 16)OFS-V 2.6E 0-1.0 -2.7)E 1 (0/ 6)ONS3-V -6.2E 3.7 -3.6)E 1 (0/ 16)ONS1-V 1.8E 0-2.0 -5.6)E 1 (1/ 16) t OFS-V 6.41E 0-9.6 -17.0)E 0 (0/ 6)ONS2-V 4.0E 0 (0/ 1)ONS3-V 1.1E 1 ( -3.3 -13.5)E 1 (2/ 16)OFS-V 1.0E 1 ( -1.9 -3.2)E 1 (0/ 6)OFS-V 8.4E 0 ( -2.5 -32.0)E 0 (0/ 6)ONS2-V 2.9E 1 (0/ 1)Control Stations Mean Range No. Detected-6.7E 0-8.0 -25.0)E 0 (0/ 6)4.7E 3.0 -5.0)E 0 (0/ 6)-5.5E 1-1.5 -0.0)E 2 (0/ 6)-2.5E 0-7.7 -4.8)E 0 (0/ 6)2.6E 0-1.0 -2.7)E 1 (0/ 6)-3.0E 0-1.7 -1.1)E 1 (0/ 6)-9.7E 0-5.4 -3.4)E 1 (0/ 6)6.4E 0-9.6 -17.0)E 0 (0/ 6)-2.2E 0-1.4 -0.8)E 1 (0/ 6)3.8E 0-5.0 -18.1)E 0 (0/ 6)1.0E 1-1.9 -3.2)E 1 (0/ 6)8.4E 0 1 -2.5 -32.0)E 0 (0/ 6)-7.3E 0-2.1 -0.4)E 1 (0/ 6)

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.1 Radiological Environmental Program Summary Indiana Michigan Power Co., DC Cook Nuclear Plant (January -December 2010)MEDIUM: Vegetation (TV) UNITS: pCi/kq wet Radionuclides (No. Analyses)Non-Routine*

Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-Ce-14 (39)(0)Pb-210 (2)(0)Ac-228 (56)(0)Th-232 (11)(0)4.3E 0 ( -3.7 -6.3)E 1 (0/ 33)8.6E 2 ( 6.3 -11.0)E 2 (2/ 2)1.OE 1 ( -4.1 -16.8)E 1 (1/ 48)1.8E 1 ( -5.3 -6.3)E 1 (0/ 9)ONS2-V ONS3-V 0NS3-V ONS2-V 7.OE 0 (0/ 1)8.6E 2 ( 6.3 -11.0)E 2 (2/ 2)2.3E 1 ( -4.1 -16.8)E 1 (1/ 24)-1. 5E 1-8.3 -4.1)E 1 (0/ 6)NO DATA 1.9E 1-4.5 -114.0)E 0 (0/ 8)-7.5E 0-1.2 --0.3)E 1 (0/ 2)5.OE 1 (0/ 1)* Non-Routine refers to radionuclides exceeding the Reporting Levels in ODCM Attachment 3.21 of the ODCM The fraction of sample analyses yielding detectable measurements (i.e., > 3 standard deviations) is shown in parentheses.

t The measured concentration was below the a posteriori calculated MDC.f The measured concentration of one of these samples was below the a posteriori calculated MDC.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.2 2010 Environmental TLD Exposure Rate Measurements (pR/hr)Indicator TLDs Control TLDs Highest Mean (SBN)Mean 5.2 +/- 0.4 5.8 +/- 0.7 7.3 +/- 0.4 Range 4.4- 6.0 4.8 -7.8 7.0 -7.8 No. of Measurements*

48 59 4 Each measurement was based on quarterly readings from three TLD elements.Units are pR (micro-roentgen) per hour.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 3.3 2010 ENVIRONMENTAL TLD DATA

SUMMARY

Exposure Rate (pR/hr +/- 1 std. dev.)Average Annual Station First Second Third Fourth Exposure Rate Number Quarter Quarter Quarter Quarter (pjRhr)T-01 5.2 +/- 0.2 5.1 +/- 0.1 4.8 +/- 0.2 5.7 +/- 0.3 5.2 T-02 5.5 +/- 0.3 5.2 +/- 0.3 4.9 +/- 0.3 5.5 +/- 0.2 5.3 T-03 4.7 +/- 0.3 4.5 +/- 0.2 4.4 +/- 0.2 4.7 +/- 0.3 4.6 T-04 5.7 +/- 0.3 5.8 +/- 0.2 5.7 +/- 0.3 6.0 +/- 0.3 5.8 T-05 5.4 +/- 0.3 5.1 +/- 0.2 4.8 +/- 0.3 5.5 +/- 0.2 5.2 T-06 5.6 +/- 0.4 5.2 +/- 0.3 5.2 +/- 0.4 5.2 +/- 0.2 5.3 T-07 5.1 +/- 0.3 5.2 +/- 0.2 4.9 +/- 0.3 5.4 +/- 0.2 5.2 T-08 5.2 +/- 0.2 5.2 +/- 0.2 4.7 +/- 0.2 5.7 +/- 0.2 5.2 T-09 5.1 +/- 0.2 5.0 +/- 0.2 4.6 +/- 0.3 5.4 +/- 0.2 5.0 T-10 5.3+/-0.3 5.2+/-0.2 5.0+/-0.2 5.8+/-0.3 5.3 T-11 5.4+/-0.3 5.1-+/-0.1 5.2+/-0.3 5.7 +/-0.2 5.4 T-12 5.3 +/- 0.3 4.9 +/- 0.2 5.2 +/- 0.3 5.7 +/- 0.2 5.3 NBF 6.0 +/- 0.4 5.6 +/- 0.3 5.3 +/- 0.2 5.6 +/- 0.2 5.6 SBN 7.0 +/- 0.3 7.4 +/- 0.4 7.0 +/- 0.2 7.8 +/- 0.3 7.3 DOW 5.1 +/- 0.2 5.0 +/- 0.1 4.8 +/- 0.3 5.4 +/- 0.2 5.1 COL 5.0 +/- 0.2 4.8 +/- 0.2 4.9 +/- 0.2 5.2 +/- 0.2 5.0 OFT-I 5.1 +/- 0.3 5.2 +/- 0.2 5.0 +/- 0.2 5.5 +/- 0.2 5.2 OFT-2 5.4 +/- 0.3 5.5 +/- 0.4 5.1 +/- 0.2 6.1 +/- 0.2 5.5 OFT-3 5.4 +/- 0.3 5.5 +/- 0.2 5.2 +/- 0.2 6.0 +/- 0.3 5.5 OFT-4 5.8 +/- 0.4 5.6 +/- 0.2 5.4 +/- 0.3 6.1 +/- 0.2 5.7 OFT-5 5.2 +/- 0.3 5.7 +/- 0.2 5.2 +/- 0.2

5.4 OFT-6 6.8+/-0.4 6.8+/-0.3 6.5+/-0.2 7.1 +/-0.2 6.8 OFT-7 5.5 +/-0.3 5.7 +/-0.3 5.0 +/-0.2 6.1 +/-0.3 5.6 OFT-8 6.2+/-0.3 6.3+/-0.3 6.1 +/-0.3 6.9+/-0.2 6.4 OFT-9 5.6 +/- 0.3 6.1 +/- 0.2 5.6 +/- 0.2 6.8 +/- 0.2 6.0 OFT-10 5.6+/-0.3 5.4+/-0.2 5.4+/-0.5 6.1 +/-0.2 5.6 OFT-11 6.6 +/- 0.3 6.3 +/- 0.2 6.2 +/- 0.2 6.9 +/- 0.3 6.5* Sample lost and is documented in section 4.1 as a deviation.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 4.0 ANALYSIS OF ENVIRONMENTAL RESULTS 4.1 Sampling Program Deviations 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 Attachment 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 were noted for the 2010 sampling program: 1. 1/2/10 to 3/6/10, 12/13/2010 and 12/18/2010 tol2/31/2010:

Due to personnel safety/seasonal unavailability issues (extremely harsh weather conditions and/or ice buildup along the shoreline) routine sampling of Lake Michigan Surface Water at SWL-2 and SWL-3 was not performed.

Data sheet 1, Documentation of Unavailable samples, of 12-THP-6010-RPP-630 was written to document this event. Actions to prevent recurrence of this issue are not practical at this time.2. 1/1/10 to 12/31/10:

The required number of indicator milk samples (minimum of three) was not collected due to the retirement of Glen Troy Farm's operator and failure to locate a suitable replacement farm.This occurrence was documented using data sheet 1 (Documentation of Unavailable Samples) to 12-THP-6010-RPP-630 and in plant Condition Report 04351048.Environmental Section personnel implemented OSD-001 required broadleaf sampling (monthly when available) per 12-THP-6010-RPP-638 "Collection of Grape and Broadleaf Samples" on 10/19/05.The REMP Coordinator determined:

a. Milk sampling would remain in effect at the three remaining locations (2 Indicator, 1 Control) in anticipation that an additional indicator farm or other suitable sampling regimen would be identified.

b. Actions to prevent recurrence of this issue are not practical at this time.3. 1/1/10 to 3/31/10 and 10/1/10 to 12/31/10:

Due to the seasonal unavailability of suitable vegetation, "Broadleaf In Lieu Of Milk" vegetation samples were not collected during these two periods. No actions to prevent recurrence of this issue were identified at this time.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 4. 01/25/2010

-On Sunday 1/24/2010 at 13:24, the REMP Coordinator received notification from the Telemetric Monitoring System that REMP air sampling station ONS-4 (on site # 4) had lost power. The REMP Coordinator checked the air station on Monday 1/25/10, and found that the air sample pump was not running. The REMP coordinator reset the ground fault interrupter and the pump restarted at 09:22. The power outage and loss of runtime was 19 hours2.199074e-4 days 0.00528 hours 3.141534e-5 weeks 7.2295e-6 months and 30 minutes. The AVT-100 totalizer maintained and displayed all of the data recorded up to the power outage. When the power was restored, the totalizer picked up where it had left off and continued to perform its function as designed.

The run time shortage due to the power outage has been documented on data sheet 1 of THP-6010-RPP-630 "Documentation of Unavailable Samples" to ensure this information is captured in the Annual Radiological Environmental Operating Report. Cook Nuclear Plant (CNP) Action Request (AR) 00863807 was generated to track this incident.5. 3/24/2010

-During regular weekly sampling of REMP Air Stations (12-THP-601 0-RPP-632), it appears that no sample was collected at ONS-4. It was noted upon removal of the sample media clamshell that the particulate filter was completely white. (After a normal week's worth of air being purged through the particulate filter, the filter appears "medium" gray in color.) The sample pump had been replaced the previous week on 3-17-2010 and that sample appeared normal. Further investigation showed that the suction tubing was not fully connected to the pump's quick disconnect.

Data sheet 1 of THP-6010-RPP-630"Documentation of Unavailable Samples" was generated to ensure this information is captured in the Annual Radiological Environmental Operating Report. CNP AR 2010-2044 was generated to track this issue.6. 4/24/2010

-The sampling time for location ONS-2 was 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months less than expected.

Data sheet 1 of THP-601 0-RPP-630 "Documentation of Unavailable Samples" was generated to ensure this information is captured in the Annual Radiological Environmental Operating Report. No CNP AR was written.7. 5/5/2010 -It was discovered at the COL station that the air sampling pump was not operational and no electrical power was available.

Data sheet 1 of THP-6010-RPP-630 "Documentation of Unavailable Samples" was generated to ensure this information is captured in the Annual Radiological Environmental Operating Report. No CNP AR was written.8. 5/12/2010

-AC power loss to Air Station COL due to a tripped ground fault protection after a storm. Cook Nuclear Plant (CNP) Action Request (AR) 2010-4542 was generated to track this incident.9. 6/23/2010 -The NBF station had sampling time that was 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months less than expected.

Data sheet 1 of THP-6010-RPP-630 "Documentation of Unavailable Samples" was generated to ensure this information is captured in the Annual Radiological Environmental Operating Report. No CNP AR was written.10. 6/30/2010

-It was discovered at the SBN station that the sample pump was running, but the display was blank. Cook Nuclear Plant (CNP) Action Request (AR) 2010-6521 was generated to track this incident.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 11.6/30/2010

-It was discovered at the COL station that the sample pump was running, but the display was incorrect.

Cook Nuclear Plant (CNP) Action Request (AR) 2010-6526 was generated to track this incident.12. W1 Through W1 7- Groundwater samples for the third quarter were collected

>92 days from the prior collection (99 days) due to a lack of Environmental technician resources.

These samples were collected within the allowable extension of the surveillance period (25%). No condition report was written.13. 7/28/2010

-It was noted that at the ONS-1 station the run time was approximately 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months shorter than expected.

This was due to a power outage.Data sheet 1 of THP-601 0-RPP-630 "Documentation of Unavailable Samples" was generated to ensure this information is captured in the Annual Radiological Environmental Operating Report. No CNP AR was written.14. 8/11/2010

-It was discovered that station SBN was without power for approximately 46 hours5.324074e-4 days 0.0128 hours 7.60582e-5 weeks 1.7503e-5 months . The condition was not flagged by Telemetrics.

Cook Nuclear Plant (CNP) Action Request (AR) 2010-8224 was generated to investigate this incident.15. 9/1/2010 -It was noted that the AVS controller at the SBN sample pump had malfunctioned.

The sample was obtained and Cook Nuclear Plant (CNP) Action Request (AR) 2010-9046 was generated to document and correct the problem.16. 9/22/2010

-Sample station ONS-1 was without power from a storm the previous evening. Cook Nuclear Plant (CNP) Action Request (AR) 2010-9820 was generated to resolve issues of excess foliage in the area of the power supply.17. 12/15/2010

-It was noted that air station ONS-5 did not have power. An attempt was made to re-energize the station, but power was unavailable.

Transmission and Distribution personnel were immediately contacted to repair the problem.Power was restored on December 17. It was determined in the investigation that the power was most likely lost on December 13. When the telemetry vendor was contacted as to why the installed unit did not generate a loss of AC power signal, it appeared that something changed the unit's setpoints on December 13, rendering them useless. This is most likely when the power outage/surge occurred.

Total run time for the ONS-5 sample collected on 12/15 is unknown, therefore voiding the sample (sample would have been part of the 268877 work order). Condition report 2010-13690 was written. On 1/5/2011, REMP personnel verified operability of the telemetry units on the other 9 air stations.

Telemetry was verified to be satisfactory and operable.18. The TLD located at OFT-5 (near corner of Lemon Creek and Shawnee) was blown away from its location by inclement weather systems and subsequently lost. The TLD was later recovered, but far too late for inclusion in these results.AWAY #2010-13773 was initiated to investigate the methods used to fasten TLDs in their various locations and to improve these methods as necessary.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 4.2 Comparison of Achieved LLD with Requirements Attachment 3.20 from the 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 of the ODCM, on occasion, an LLD may not be 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 factors are summarized below.Actual AREVA E-LAB analyses were typically 2.5 to 3 times more "sensitive" than the LLDs required by the ODCM. For each analysis having an LLD requirement, the a posteriori or "after the fact" LLD calculated for that analysis was compared with the required LLD. Appendix D includes flags in the far right hand margin for any occurrences of exceeded MDC's (note that the terms LLD and Minimum Detectable Concentration (MDC) are used interchangeably in this assessment).

During 2010, there were 14 cases where the MDC exceeded the LLD requirement, at 4 sampling stations.The COL air sample station had insufficient run time on the 5/12/2010 sample due to a tripped ground fault circuit interrupt.

The air sample filter did not meet the specified counting requirements as a result. MDC values were not met for I-131 or gross beta counts. AR 2010-4542 was written to document the occurrence.

The STJ drinking water sample from November 11 has a calculated MDC of 1.17 pCi/L for 1-131. This exceeds the required MDC of 1.00 pCi/L. GEL Labs has generated CARRi 10412-563 to investigate the issue.SWL-2 and SWL-3 samples had insufficient volume for the 1/16/2010 period. As a result the required MDC was not met for Fe-59, Co-60, Zn-65, Nb-95, Ba-140, La-140 in the SWL-2 sample and Fe-59, Co-60, Zn-65, Nb-95 and La-140 in the SWL-3 sample. Surface water samples during this period were not safely retrievable.

These unavailable samples are documented by 12-THP-6010-RPP-630.4.3 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 2.4 in this report). Reporting Levels are the environmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, Appendix I. It should be noted that environmental concentrations were 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 2010, no Reporting Levels were exceeded.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 4.4 Data Analysis by Media Type -Discussion The 2010 REMP data for each media type are discussed below. Media types were arranged in the same order as in Table 3.1. Graphical plots of monitoring data are also shown in Figures 4.1 to 4.5. With respect to data plots, all results were plotted, whether they were "detectable" or "non-detectable." 4.4.1 Air Particulate Air particulates were collected weekly on 47 mm glass fiber filters at six indicator locations and four control locations, and analyzed for gross beta radioactivity.

On a quarterly basis, a gamma isotopic analysis was performed on the composite of each location's weekly particulate sample media.Figure 4.1 shows the gross beta concentrations in air particulate filters collected for the operating period from 1989 though 2010. While gross beta concentrations were detectable on all but one particulate samples and at all locations, there was no significant difference between the average monthly gross beta concentration at the indicator stations and the control stations during 2010 as shown in Figure 4.1.Notable in the graph is a distinct annual cycle. The gross beta concentration fluctuations over the year were attributed to seasonal changes in the naturally-occurring airborne radioactivity levels. This conclusion was based on the similarity in fluctuations noted in gross beta concentrations at both the indicator stations and control stations.Results for gamma isotopic analyses performed on quarterly composites of the weekly particulate samples have been listed in Table 3.1. The presence of naturally occurring Be-7 was detected in all of the indicator and control samples. One sample contained naturally occurring K-40.One gamma emitting nuclide was identified at the AREVA ELAB positive detection criterion of 3a, but did not meet GEL Labs positive detection criterion of greater than the MDC which were in effect at the time.Analyzing laboratories were changed in June of this year. Full details of all measurements can be found in Appendix D.In summary, the information detailed above was evaluated and found to be consistent with data obtained during the conduct of CNP's"Pre-Operational Radiological Monitoring Program" (PRMP) [see Appendix E]. Also, no significant difference was noted between the average monthly gross beta concentration at the indicator and the control stations.

Therefore, the results were not due to plant operations.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Figure 4.1 AVERAGE MONTHLY GROSS BETA IN AIR PARTICULATES 60 50 S40 30 20 10 0--- Indicators

Controls 4.4.2 Airborne Iodine Airborne iodine sample media were collected weekly in conjunction with the air particulate sample media replacement.

These media were analyzed for Iodine-131.

No iodine was detected in any of the Indicator or Control samples above the MDC. One control sample detected 1-131 at the 3a criterion, but the concentration was below the MDC. This is likely due to the change in analyzing laboratory in June of this year. Full details of all measurements can be found in Appendix D.The information detailed above was evaluated and found to be consistent with data obtained during the conduct of CNP's PRMP.4.4.3 Groundwater (Well)Groundwater samples were collected from seventeen well locations on a quarterly frequency and analyzed for gamma isotopic and tritium.The presence of naturally-occurring K-40 was identified in eleven samples out of sixty-eight collected.

The presence of K-40 in groundwater samples is attributed to natural occurrences since it is not a fission or activation product related to plant operations.

Three other gamma emitting nuclides were identified at the AREVA ELAB positive Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 detection criterion of 3a, but did not meet GEL Labs positive detection criterion of greater than the MDC which were in effect at the time.Analyzing laboratories were changed in June of this year. Th-228 was detected in four of the sixty-eight samples collected.

The presence of Th-228 in groundwater samples is attributed to the natural occurrence of thorium in the environment.

Tritium was detected above the associated MDC in six groundwater samples. CNP Action Request AR 848816848816was generated to track these occurrences.

These occurrences are detailed in Table 4.1. The low level activity in all of these samples were in areas identified to have recapture via precipitation of gaseous releases through licensed, radioactive, gaseous release points. Tritium activity in these wells is being tracked by the CNP groundwater protection initiative (GPI). Figures 4.2, 4.3 and 4.4 plot the tritium levels (both "detectable" and "non-detectable")

for groundwater.

Table 4.1 Tritium Concentrations Measured Above MDC Location Concentration (pCi/I) Reference Date W-4 842 8-11-10 W-5 713. 8-11-10 W-6 1240 8-11-10 W-14 529 8-10-10 W-15 1920 8-11-10 W-4 677 11-4-10 The information detailed above was evaluated and found to be consistent with data obtained during the conduct of CNP's PRMP. While the low level tritium activity listed above is believed to be from plant operations, it is well below action levels and has no significant impact on public health and safety.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Figure 4.2 TRITIUM IN GROUNDWATER 4000 3500 3000 E2500 r 2000 1500 a 1000 500.-4--Well-I -Well-2

---Well-3]Figure 4.3 TRITIUM IN GROUNDWATER 10000 9000.8000.7000.6000..9 5000 4000 3000a 2000-00 o .S.§. ..S .0--- 0--5 4' 4WelAý 5' 0& S. Wel-7 1-4-!NeI-4 Well-S --*-Well-6 Wl-Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Figure 4.4 TRITIUM IN GROUNDWATER 20000 15000- -10000 0..0 0 0-5000 1-4--Well-8 -a-- Well-9 -WeII-10 -- Well-11 ----Well-12 -Welj-13

--+--Well-14

--e--MW-20 --MW-21 4.4.4 Drinking Water Drinking water samples were 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 indicated that no Iodine-1 31 was present.Figure 4.5 shows a plot of the tritium data since 1989. Starting in 2002, all data was plotted, whether the results were negative or positive as described in Section 4.4. No tritium was detected in drinking water samples in 2010.During 2010, the presence of gross beta radioactivity was identified in 11 indicator and 7 control samples, with activity levels similar to those observed in recent years. One control sample and two indicator samples contained the naturally-occurring K-40 at levels above the MDC. Two additional indicator samples had K-40 measured at the AREVA ELAB positive detection criterion of 3cr, but did not meet GEL Labs positive detection criterion of greater than the MDC which were in effect at the time. Analyzing laboratories were changed in June of this year. The Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 naturally occurring Th-232 decay series, as indicated by AcTh-228, was detected in one control sample.No tritium or other gamma-emitting nuclides were identified in any 2010 samples.While drinking water sampling was not performed as part of CNP's PRMP, the information detailed above was evaluated and found to be consistent with data obtained during the plant's operational history.This information, coupled with the identification of detectable levels of gross beta activity in both the indicator and control samples, supported the conclusion that these occurrences were not attributable to plant operations.

Figure 4.5 TRITIUM IN DRINKING WATER 1500 1000 0 0 500-500-1000--#--Lake Township --F- St. Joseph]4.4.5 Surface Water Surface water samples were collected from two locations and analyzed for gamma-emitting radionuclides and tritium (quarterly).

No gamma-emitting nuclides were detected in any of the samples collected in 2010.No tritium was detected in any of the samples collected in 2010.The information detailed above was evaluated and found to be consistent with data obtained during the conduct of CNP's PRMP and past Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 operational periods. There has been no impact to this sample medium from plant operations.

4.4.6 Sediment

Semiannual samples of lake sediments were collected from two indicator' stations and analyzed for gamma-emitting nuclides.

During 2010, naturally-occurring K-40 was detected in all sediment samples. One indicator sample had Th-228 and another indicator sample detected Th-232, as indicated by the detection of AcTh-228.

These nuclides are expected as part of the naturally occurring thorium decay series. No other gamma-emitting nuclides were detected in any of the samples collected in 2010. Unlike past operational and pre-operational periods where traces of Cs-1 37 were found, no detectable Cs-1 37 was identified in 2010 samples.The information detailed above was evaluated and found to be consistent with data obtained during the conduct of CNP's PRMP and the presence of a naturally-occurring nuclide (K-40, Ac-228 & Th-232) was not attributed to plant operation.

4.4.7 Milk Milk samples were collected bi-weekly from two indicator and one control station during 2010.Results of all sample analyses identified the presence of naturally-occurring K-40, ranging in concentration from 1324 to 2130 pCi/liter, which falls into a similar range as found in previous years.The naturally occurring nuclide Th-228 was detected in three samples.This nuclide is expected as part of the naturally occurring thorium decay series.lodine-131 specific low level detection analyses detected no 1-131.The information detailed above was evaluated and found to be consistent with data obtained during the conduct of CNP's PRMP and the presence of naturally-occurring K-40 and Th-228 was not attributed to plant operation.

4.4.8 Food Products & Vegetation Vegetation samples (broad-leaf) analyzed for gamma-emitting nuclides identified the presence of naturally occurring K-40 and Be-7, Pb-210, and Ac-228. Two samples detected Cs-137 above the MDC within the range of 36-135 pCi/kg. One sample detected Cs-137 was identified at the AREVA ELAB positive detection criterion of 3a, but did not meet GEL Labs positive detection criterion of greater than the MDC which were in effect at the time. Analyzing laboratories were changed in June of this year. The presence of Cs-1 37 is not representative of historical data. The previous months (summer 2009) as well as previous years 2005, 2008 and 2009 were reviewed as well. There were no other instances noted where Cs-137 was present. The pre-operati6nal samplings were Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 examined, unfortunately there were no broadleaf samples collected before D.C. Cook Plant construction.

The presence of Cs-137 in one of the October broadleaf samples was entered into the Cook Plant corrective action program, the number of this report is 2011-1494.

The evaluation of 2011-1494 concluded that the Cs-137 result was due to atmospheric weapons testing. No other gamma-emitting nuclides were detected in any of the samples.An annual sample of food products (grapes) was analyzed for gamma-emitting radionuclides.

Analysis identified only the presence of naturally-occurring Be-7 and K-40. While food product sampling was not performed as part of CNP's PRMP, the information detailed above was evaluated and found to be consistent with data obtained during the plant's operational history. The presence of detected radionuclides was not attributed to plant operations.

4.4.9 Fish Fish samples were collected on two occasions at two indicator and two control locations.

Naturally-occurring K-40 was detected in all the samples. Trace levels of Cs-1 37 was observed in the control sample from September.

The presence of Cs-1 37 is consistent with historical and pre-operational data. The presence of detected radionuclides was not attributed to plant operations.

The information detailed above was evaluated and found to be consistent with data obtained during the conduct of CNP's PRMP and during the plant's operational history.4.4.10 Gamma Exposure Rate Direct radiation was continuously measured at 27 locations surrounding CNP with thermoluminescent dosimeters (TLDs). All TLDs were collected quarterly and processed at the AREVA NP Environmental Laboratory.

The results in Tables 3.2 and 3.3 show that the mean exposure rates for the Indicator and Control categories were not significantly different in total for 2010. As shown in Figure 4.6, there is a similar annual cycle at both indicator and control locations.

The lowest point of the cycle typically occurred during the winter months. This was attributed primarily to the attenuating effect of the snow cover and frozen ground on radon emissions and on direct irradiation by naturally-occurring radionuclides in the soil. Also contributing to the variation in radiation levels at different field sites was the varying distribution of radionuclides in the underlying soil, rock or nearby building materials.

Figure 4.6 also illustrates that the average trend line over the last five years for the control stations runs slightly higher than that for the in-close indicator stations, suggesting that there is no detectable plant component of direct radiation that can be seen above the natural background exposure rate.In 2002, the AREVA NP Laboratory assumed responsibility for calibration and processing of the TLDs used for these activities.

The Panasonic 802 Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 (UD-814) TLDs that had historically been used to measure direct radioactivity around CNP were replaced with Panasonic Model UD-814 AS4 TLDs.The information detailed above was evaluated and found to be consistent with data obtained during the conduct of CNP's PRMP.Figure 4.6 DIRECT RADIATION

-QUARTERLY TLD RESULTS 9 U 8 0 0 6 6*0 U)0 0.1 0 a T T 9 9 9 ' 9 9 9 9 M' M' W~ a 0 0W 0W a 0a W W 0 0 W I--e-TLD Controls ---TLD Indicators I 4.4.11 Additional Sample Analysis (non-ODCM required samples)Groundwater (Radioactive Equipment Storage Facility, Steam Generator wells) -Two one-liter well water samples were taken at 4 locations periodically.

These samples were analyzed for gamma isotopic and gross alpha/beta by the AREVA NP Laboratory.

All samples indicated the presence of gross beta activity, which is consistent with operational history.Informational Groundwater Wells -Samples were collected at several locations during 2010 and analyzed for tritium by the CNP Chemistry Department and AREVA NP. Activity ranged from less than the MDC to 1640 pCi/L. Figure 4.7 shows a plot of the tritium concentration in these additional groundwater wells. Tritium activity in these wells is being tracked by the CNP Groundwater Protection Program and the REMP.This activity is believed to be the result of tritium recapture via Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 precipitation through gaseous releases from the unit vent exhausts and then pooling around site buildings.

This low level tritium activity has no significant environmental impact on public health and safety.Figure 4.7 TRITIUM IN INFORMATIONAL GROUNDWATER WELLS 350 300 250 200 CL 15.-100 50 O0 01N .-50-1uuu +----OW-1 -OW-2 -OW-4 W-4 -*--W-5 ----W-6 Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 4.4.12 Additional Sample Analysis (NEI Groundwater Protection Initiative)

The results of the additional samples for the NEI Groundwater Protection initiative, as described in Section 2.5.12, is as follows.Table 4.2 Groundwater Protection Initiative Data for Location W-1 -W-8 Samples analyzed for tritium. Values noted are in microcuries per milliliter (uCi/mL)Lower Limit of Detection

= LLD Date W-1 W-2 W-3 W-4 W-5 W-6 W-7 W-8 01/26/2010

<LLD <LLD 01127/2010

<LLD <LLD <LLD 01/28/2010 8.39E-7 9.24E-7 1.07E-6 04/26/2010

<LLD <LLD 04/27/2010

<LLD <LLD 04/29/2010

<LLD <LLD <LLD <LLD 08/08/2010

<LLD 08/10/2010

<LLD <LLD 08/11/2010

<LLD 9.12E-7 9.70E-7 <LLD 11/02/2010

<LLD ___ <LLD <LLD 11/03/2010

<LLD <LLD 11/04/2010 I <LLD 1.55E-6 1.04E-6 Table 4.3 Groundwater Protection Initiative Data for Location MW-22D, MW-22M, MW-22S, MW-24D, MW-24M, MW-24S, MW-25D and MW-25M Samples analyzed for tritium. Values noted are in microcuries per milliliter (uCi/mL)Lower Limit of Detection

= LLD MW- MW- MW- MW- MW-Date MW-24D MW-24S MW-25M 22D 22M 22S 24M 25D 01/14/2010

<LLD <LLD <LLD 01/20/2010

<LLD <LLD <LLD 01/26/2010

<LLD <LLD <LLD 02/02/2010

<LLD <LLD <LLD 8.72E-7 1.26E-6 <LLD 02/05/2010

<LLD <LLD <LLD 02/10/2010

<LLD <LLD <LLD <LLD <LLD 02/19/2010

<LLD <LLD <LLD 03/09/2010

<LLD <LLD <LLD 03/10/2010

<LLD <LLD 03/13/2010

<LLD <LLD <LLD 04/27/2010

<LLD <LLD <LLD 04/29/2010 9.09E-6 <LLD <LLD 04/30/2010

<LLD <LLD 05/03/2010 7.49E-6 <LLD <LLD 05/04/2010 7.93E-6 <LLD <LLD 05/06/2010 6.87E-6 <LLD <LLD 05/14/2010 5.19E-6 <LLD <LLD 05/17/2010 5.1OE-6 <LLD <LLD <LLD <LLD 05/18/2010 5.80E-6 <LLD <LLD 05/19/2010

<LLD <LLD <LLD 05/26/2010 2.62E-6 <LLD <LLD 06/04/2010 1.77E-6 <LLD <LLD 06/10/2010 2.88E-6 <LLD <LLD 06/18/2010 1.96E-6 <LLD <LLD 06/25/2010

<LLD <LLD <LLD <LLD <LLD Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 4.3 (Continued)

Groundwater Protection Initiative Data for Location MW-22D, MW-22M, MW-22S, MW-24D, MW-24M, MW-24S, MW-25D and MW-25M Samples analyzed for tritium. Values noted are in microcuries per milliliter (uCi/mL)Lower Limit of Detection

= LLD Date MW-22D MW-22M MW-22S MW-24D MW-24M MW-24S MW-25D MW-25M 06/30/2010

<LLD <LLD <LLD 07106/2010

<LLD <LLD <LLD 07/21/2010

<LLD <LLD <LLD 07/26/2010

<LLD <LLD 07/30/2010

<LLD <LLD <LLD 08/06/2010

<LLD <LLD <LLD 08/10/2010

<LLD <LLD 08/11/2010

<LLD <LLD <LLD 08/12/2010

<LLD <LLD 08/21/2010

<LLD <LLD <LLD 08/24/2010

<LLD <LLD <LLD 08/30/2010

<LLD <LLD <LLD 09/02/2010

<LLD <LLD <LLD 09/08/2010

<LLD <LLD <LLD 09/10/2010

<LLD <LLD 09/14/2010

<LLD <LLD <LLD 09/22/2010

<LLD <LLD <LLD 09/30/2010

<LLD <LLD <LLD 10/01/2010

<LLD <LLD <LLD 10/04/2010

<LLD <LLD <LLD 10/19/2010

<LLD <LLD 10/20/2010

<LLD <LLD 10/23/2010 8.56E-7 <LLD 10/28/2010

<LLD <LLD <LLD 10/29/2010

<LLD <LLD <LLD 10/30/2010

<LLD <LLD 11/06/2010

<LLD <LLD 11/08/2010

<LLD 8.57E-7 11/11/2010

<LLD <LLD <LLD 11/15/2010

<LLD 8.56E-7 11/16/2010

<LLD <LLD <LLD 11/19/2010

<LLD <LLD <LLD 11/26/2010

<LLD <LLD 12/01/2010

<LLD <LLD <LLD <LLD <LLD 12/06/2010

<LLD <LLD 12/17/2010

<LLD <LLD <LLD 12/20/2010

<LLD <LLD 12/27/2010

<LLD <LLD <LLD <LLD <LLD Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 4.4 Groundwater Protection Initiative Data for Location MW-25S, MW-26D, MW-26M, MW-26S, MW-27D, MW-27M, MW-27S Samples analyzed for tritium. Values noted are in microcuries per milliliter (uCi/mL)Lower Limit of Detection

= LLD Date MW-25S MW-26D MW-26M MW-26S MW-27D MW-27M MW-27S 02/10/2010

<LLD <LLD <LLD <LLD <LLD <LLD <LLD 03/10/2010

<LLD <LLD <LLD <LLD <LLD <LLD <LLD 04/30/2010

<LLD <LLD <LLD <LLD <LLD <LLD <LLD 05/17/2010

<LLD <LLD <LLD <LLD <LLD <LLD <LLD 06/25/2010

<LLD <LLD <LLD <LLD <LLD <LLD <LLD 07/26/2010

<LLD <LLD <LLD. <LLD <LLD <LLD <LLD 08112/2010

<LLD <LLD <LLD <LLD <LLD <LLD <LLD 09/10/2010

<LLD <LLD <LLD <LLD <LLD <LLD <LLD 10/19/2010 9.50E-7 <LLD <LLD <LLD 9.85E-7 <LLD 1.04E-6 10/20/2010 9.93E-7 <LLD 8.52E-7 <LLD 2.43E-6 <LLD <LLD 10/23/2010

<LLD <LLD <LLD <LLD 2.42E-6 1.09E-6 1.31E-6 10/28/2010

<LLD <LLD <LLD 10/30/2010

<LLD <LLD <LLD <LLD 3.06E-6 1.46E-6 1.13E-6 11/06/2010

<LLD <LLD <LLD <LLD 2.56E-6 1.68E-6 <LLD 11/08/2010

<LLD <LLD <LLD <LLD 3.66E-6 1.68E-6 1.22E-6 11/11/2010 3.39E-6 2.20E-6 1.09E-6 11/15/2010

<LLD <LLD <LLD <LLD 3.36E-6 1.83E-6 1.55E-6 11/19/2010 1.85E-6 <LLD <LLD 11/22/2010 1.47E-6 <LLD <LLD 11/26/2010

<LLD <LLD <LLD <LLD 1.73E--6 <LLD <LLD 12/01/2010

<LLD <LLD <LLD <LLD 2.08E-6 1.42E-6 1.32E-6 12/04/2010

<LLD <LLD <LLD 12/06/2010

<LLD <LLD <LLD <LLD <LLD <LLD <LLD 12/09/2010 2.02E-6 9.93E-7 1.81E-6 12/13/2010 1.92E-6 9.89E-7 1.67E-6 12/20/2010 1.36E-6 8.54E-7 <LLD <LLD 2.38E-6 1.50E-6 1.36E-6 12/23/2010 1.18E-6 <LLD 1.04E-6 12/27/2010 1.22E-6 <LLD <LLD 8.53E-7 1.31E-6 1.18E-6 1.17E-6 12/30/2010 1.22E-6 1.18E-6 <LLD (Note: Wells MW-22 through MW 27 are new multi-port wells installed three sample points placed at different depths. S= Shallow M= Middle in the Fall of 2009, with D= Deep.)(Note: A .*" symbol following a sample result denotes a gamma count was performed.

Any gamma results above LLD will be additionally flagged and documented in the analysis section.)

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 4.5 Groundwater Protection Initiative Data for Location W-9 -W-1 5 and OW-1 Samples analyzed for tritium. Values noted are in microcuries per milliliter (uCi/mL)Lower Limit of Detection

= LLD Date W-9 W-10 W-11 W-12 W-13 W-14 W-15 OW-1 01/05/2010

<LLD <LLD 01/14/2010

<LLD <LLD 01/15/2010

<LLD 01/20/2010

<LLD 0112612010

<LLD <LLD <LLD <LLD <LLD <LLD 01/27/2010

<LLD <LLD 02/02/2010

<LLD 02/18/2010

<LLD 02/19/2010

<LLD <LLD 03/09/2010

<LLD 03/13/2010

<LLD <LLD 04/26/2010

<LLD <LLD <LLD <LLD 04/27/2010

<LLD <LLD <LLD 05/04/2010 8.38E-7 05/06/2010

<LLD 05/14/2010

<LLD 05/17/2010 9.05E-7 05/18/2010

<LLD 05/19/2010

<LLD <LLD 05/26/2010

<LLD 06/04/2010 9.01 E-7 06/11/2010 1.20E-6 06/18/2010 1.48E-6 06/25/2010 8.70E-7 06/30/2010

<LLD <LLD 07/06/2010

<LLD 07/21/2010

<LLD <LLD 07/30/2010 1.16E-6 08/06/2010 1.29E-6 08/10/2010

<LLD <LLD <LLD <LLD <LLD 08/11/2010

<LLD 1.55E-6 08/21/2010 2.49E-6 08/24/2010 2.87E-6 09/02/2010 3.62E-6 09/08/2010 2.93E-6 09/14/2010 2.47E-6 09/22/2010 2.55E-6 *09/30/2010

<LLD <LLD 10/12/2010

<LLD 10/13/2010 1 9.47E-7 10/27/2010

<LLD <LLD <LLD <LLD (Note: A .*" symbol following a sample result denotes a gamma count was performed.

Any gamma results above LLD will be additionally flagged and documented in the analysis section.)

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 4.5 (Continued)

Groundwater Protection Initiative Data for Location W-9 -W-1 5 and OW-1 Samples analyzed for tritium. Values noted are in microcuries per milliliter (uCi/mL)Lower Limit of Detection

= LLD Date W-9 W-10 W-11 W-12 W-13 W-14 W-15 OW-1 11/02/2010

<LLD <LLD <LLD <LLD 11/03/2010

<LLD <LLD 8.53E-7 11/11/2010

<LLD 11/16/2010

<LLD 11/23/2010

<LLD 12/01/2010

<LLD 12/09/2010

<LLD 12/17/2010

<LLD <LLD 12/20/2010

<LLD 12/27/2010

<LLD Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 4.6 Groundwater Protection Initiative Data for Location OW-2 -OW-4, EW-18, EW-19, MW-20, MW-21 and 95-11A Samples analyzed for tritium. Values noted are in microcuries per milliliter (uCi/mL)Lower Limit of Detection

= LLD Date OW-2 OW-3 OW-4 EW-18 EW-19 MW-20 MW-21 95-11 A 01/05/2010

<LLD 01/14/2010

<LLD 01/26/2010

<LLD <LLD 01/27/2010

<LLD <LLD 04/26/2010

<LLD 04/27/2010

<LLD <LLD <LLD 04/29/2010 1.OOE-6 05/04/2010

<LLD 08/10/2010

<LLD <LLD 10/20/2010 9.58E-7 10/27/2010

<LLD 11/02/2010

<LLD <LLD 11/08/2010 1.04E-6 Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 5.0 OFF-SITE DOSE EQUIVALENT COMMITMENTS The purpose of this section is to evaluate off-site dose consequences (dose equivalent commitments) associated with CNP radioactive liquid and airborne effluents.

The method utilizes Regulatory Guide 1.109/ODCM 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 dose commitment calculated in this section is compared to the ALARA dose objectives of 10CFR50 Appendix I for liquid and/or gaseous effluents.

These standards are a fraction of the average USA background radiation of 300 mrem per year given in NCRP 94 (Reference 2).During 2010, Cs-1 37 was measured in 2 samples at the same location.

Although the Cs-137 is most likely attributed to weapons fallout, a potential dose commitment to an maximum exposed individual of 0.048 mrem total body (adult) and 0.089 mrem maximum organ (child, bone) using conservative assumptions regarding consumption rate, and a constant Cs-137 concentration in leafy vegetation for September and October (because none was detected before October, and there were no vegetation samples to consume after October).

This dose was only 1.6 percent of the 10 CFR 50 Appendix I, total body dose limit of 3 mrem/year, and was 0.9 percent of the 10 mrem/yr 10 CFR 50 Appendix I organ dose limit.Cs-137 was also measured in one of eight fish samples at a control location.

Although the Cs-137 is attributed to weapons fallout, a potential annual dose commitment to a maximum exposed individual of 0.040 mrem total body (adult) and 0.063 mrem maximum organ (teen, liver) using conservative assumptions regarding consumption rate and a constant Cs-137 concentration of 26.5 pCi/kg in all fish. This dose was only 1.3 percent of the 10 CFR 50 Appendix I total body dose limit of 3 mrem/year, and was 0.6 percent of the 10 mrem/yr 10 CFR 50 Appendix I organ dose limit.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 6.0

SUMMARY

OF REMP, ODCM, AND VENDOR CHANGES The ODCM had no revisions in 2010. REMP procedure changes for 2010 are detailed below.Procedure No: 12-THP-6010-RPP-630 Title: Collection of REMP Surface Water Samples Revision No: 7 Alteration Justification Step 4.1.1- Added apostrophe to the word Grammar. This is a correction per"Coordinator's." PMP-2010-PRC-002.

Steps 4.3.1 -4.3.4, changed to bullet steps. Format. PMP-2010-PRC-002.

Step 4.3.1 (old), new first bullet -change The current REMP lab requires less than the from "125 ml" to "25 ml." D.C. Cook procedure requirement.

By reducing the sample volume, we will save on shipping and material costs. GT 00852173 Step 4.4.3 -Rewording.

Per discussion with the AREVA Environmental Lab, a 125 mL composite sample is all they need to run a quarterly composite analysis.

Currently we are sending them three, one liter sample bottles.This is a waste of time and resources.

GT 00850791 10 CFR 50.59 is not applicable to this procedure revision per definition in Attachment 1 of PMP-201 0-PRC-002:

Managerial or administrative procedure, or administrative change governing the conduct of facility operations.

Procedure No: 12-THP-6010-RPP-634 Title: Collection of REMP Groundwater Samples Revision No: 11 Alteratiog Justification Step 4.6.2 -Changed reference step from Typo. This is a correction per"4.2.2" to "4.4.2." PMP-2010-PRC-002.

GT 2010- 2014 Attachment 1 -under Well# MW-20 cross Typo. This is a correction per referenced to the ODCM changed from PMP-2010-PRC-002.

GT 2010- 00863454"(W-18)" to "(W-16)." Attachment 1 -under Well# MW-21 cross Typo. This is a correction per referenced to the ODCM changed from PMP-2010-PRC-002.

GT 2010- 00863454"(W-19)" to "(W-17)." 10 CFR 50.59 is not applicable to this procedure revision per definition in Attachment 1 of PMP-2010-PRC-002:

Managerial or administrative procedure, or administrative change governing the conduct of facility operations.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 6.1 below summarizes the changes made by the AREVA NP Environmental Laboratory to the procedures it uses for the Donald C. Cook Nuclear Plant REMP.Table 6.1 AREVA NP ENVIRONMENTAL LABORATORY DURES ISSUED DURING MONTHS JANUARY -304 Environmental Sample Compositing 1 02/02/10 Minor editonal cnanges. Added apparatus for clarification of composite preparation.

The Determination of Minor editorial changes. Also, the entire 368 Env ir nt section A.9. was revised to incorporate a 368 Environmental Media 14 04/29/10 Via Cerenkov larger sample weight for fish and to allow Counting for ashing the sample.Determination of Elements by 369 Spectroflame 5 02/18/10 Minor editorial changes. Also rearranged Modula Inductively the steps in Section B.4.Coupled Plasma (ICP) Spectrometer The Determination of Updated the information in the counting 371 Tritium in 25 04/02/10 section to reflect current methods, and to Environmental and require a background and analytical Bioassay Matrices blank with every batch.Operation and Calibration of the 480 EG&G Ortec Octete- 9 04/16/10 Minor editorial changes. Also updated PC Alpha the apparatus used.Spectrometry Detector System Operation and Calibration of the The five year technical review was 512 Reuter-Stokes 6 06/29/10 performed.

There were no changes.Pressurized Ion Chamber (PIC)683 Integration of a New 2 01/19/10 Removed the apparatus section. It was Product into LIMS not applicable to this procedure.

Minor editorial changes. Also, revised Data Entry Using 2 02the procedure to include all types of 688 LIMS 2 02/18/10 laboratory samples. This included changing the procedure title and references for various sample analyses.715 Preparation of 22 04/22/10 Added tolerance chart parameters for Tolerance Charts multi-volume pipettes.760 Chemical and 14 05/07/10 Made where deemed necessary to meet Reagent Control the revision cycle.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Revised the signature requirements for FORM 790.1 and 790.2. Combined the duplicate and matrix spike creation Laboratory Batch sections.

Added the requirement to 790 Quality Control 3 05/05/10 provide the QA Officer with a copy of the Handling QC Evaluation.

Added flexibility to deliver batch QC fractions directly to the chemistry Labs. Added instruction on evaluating an "out-of-tolerance" result.Generation of 1022 Element Correction 10 01/15/10 Minor editorial changes.Factors for Panasonic TLDs The Determination of Carbon-14 by Re-titled the procedure; added a section 1114 Oxidative Distillation 16 02/12/10 on C-14 determination for environmental and Liquid samples.Scintillation Spectrometry Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Table 6.2 GEL Laboratories, LLC Updated Procedures for support of Nuclear Power Plants Calendar Year 2010 GL-LB-E-002 taiances Kevision t: upaaxea revision number on SOP header to list the current revision and added history section.GL-QS-B-001 Quality Assurance Plan 23 3/2010 Revised instrument list, SOP list, preservation list, floor plan.GL-RAD-A-001B The Determination of Gross 15 12/2010 Technical updates Alpha And Gross Non-Volatile made as part of annual Beta in Soil, Filters, Solid review.Matrices and Direct Count Air Filters GL-RAD-A-004 The Determination of Strontium 14 4/2010 Updated the volume 89/90 in Water, Soil, Milk, concentration of Nitric Filters, Vegetation and Tissues acid used in section 11.7.6. Inserted New NOTE: If excessive ammonium hydroxide was used during actinide scavenge then additional oxalic acid will need to ensure complete color change of indicator.

Sample should be pink at this_time.GL-RAD-A-009 The Determination of Radium- 16 4/2010 Update method 228 in Water and Solids recovery from 25% to 15%. Replace nonconformance reports to data exception reports.GL-RAD-A-01 1 The Isotopic Determination of 20 11/2010 Updated reagent Americium, Curium, Plutonium, section. Notes added and Uranium after section 11.1.3.2 and 11.7.9 regarding Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 Pu-241 analysis if run in tandem. Omitted cookdown procedure for Americium and Uranium. Updated sections 11.4 and 11.6, microprecipitation.

steps. Added Appendix 6: Sample Cleanup from an Alpha Spec Filter.GL-RAD-A-013 The Determination of Gamma 20 12/2010 SOP revised for SC Isotopes DHEC drinking water certification.

GL-RAD-A-015 Digestion for Soil 12 6/2010 Updated section 11.2 If samples are to be ashed, weigh an appropriate aliquot (0.1 to 1.0 g) into a glass container.

GL-RAD-A-018 The Determination of Lead-210 10 .2/2010 Added Reference in Liquid and Solid Matrices Clarification.

GL-RAD-A-019 Determination of Phosphorus-32 8 7/2010 Updates made as part in Soil and Water of annual review.GL-RAD-A-030 Determination of Radium-228 in 13 4/2010 Correction made to Aqueous Samples section 9.1.8 Dissolve 192.13 g C 6 H 8 0 7.GL-RAD-A-032 The Isotopic Determination of 15 5/2010 Added step to Neptunium/Thorium appendix 1.GL-RAD-A-035 The Isotopic Determination of 13 9/2010 Changed limit from 25-Plutonium-241 125% to 15-125% in section 12.2.2.GL-RAD-A-036 The Isotopic Determination of 9 3/2010 Made technical Americium, Curium, and changes to section Plutonium in Large Soil Samples 9.1.13. 2 M Nitric acid/ 1 M Aluminum nitrate: Dissolve 375.13 g of aluminum nitrate nonhydrate, AI(NO 3)3-9H 2 0 in 300 mL of DI water. Add 125 mL of concentrated nitric acid]to the DI water. Allow Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 to cool and dilute to 1 L with DI water.GL-RAD-A-041 The Determination of Total 10 8/2010 Updated SOP to reflect Activity in Solids and Liquids the accurate amount of nitric acid used in procedure.

Replaced 20 mL of Ultima Gold LLT with 10 mL of DI water and 10 mL Ecoscint Ultra in sections 11.4.1 and 11.4.2.GL-RAD-A-043 The Determination of Plutonium, 6 4/2010 Technical changes Uranium and Thorium made to sections 6.5, Pu-236 decays to U-232 therefore Pu-236 may not be used as a tracer for this method, unless mathematically compensated for in the processing 9.2.1, NIST traceable standards:

U-232, U-238, Pu-242, Pu-239, Pu-236, Th-229, Th- 232 11.1.3.2, and 11.2.2.2.For the determination of isotopic Thorium, Th-229 is typically used as the tracer and Th-232 is typically used as the spike.GL-RAD-A-048 The Determination of Calcium- 5 9/2010 Replaced 45 in Soils and Waters Polypropylene filters (25 mm) with 25 mm diameter pre-weighted ,filters.GL-RAD-A-050 The Determination of Tritium in 5 4/2010 Updated section 3.0 for Drinking Water Samples clarification.

Changed"nonconformance report" to "data exception report" throughout.

GL-RAD-D-005 REMP Quality Control Package 1 6/2010 Annual Review: Assembly Updated SOP to I _comply with new SPC Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 system.GL-RAD-1-009

...Alpha Spectroscopy "System 11 11/2010 Annual review: Updated SOP throughout.

GL-RAD-I-012 Managing Statistical Data in the 20 3/2010 Updated information in..........

Radiochemistry Laboratory

,,_ Appendix 1: GL-RAD-S-003 Administration of the 7 2/2010 Removed step 5.2.3: Radioactive Material License "Edit the container Inventory volume/mass to match the actual provided by client." GL-RAD-S-006 Radiation Worker Training 5 2/2010 Updated for acronym"ALARA." GL-RAD-S-010 The Handling of Biological 4 11/2010 Removed section 5.5 Materials as part of procedural change.GL-RAD-S-015 The Acceptance and 2 2/2010 Revision 2: Classification of Radioactive Grammatical typos Material corrected.

Donald C. Cook Nuclear Plant Annual Radiological .Environmental Operating Report 2010

7.0 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.

Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 APPENDIX A SYNOPSIS OF ANALYSIS TECHNIQUES A-1 Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 ELab (January 2010- September 2010)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 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 that 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 as described in EPA Method 900.0. 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 for gamma-emitting radionuclide activity:

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 that 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.A-2 Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 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 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 detection limit required 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 bisulfite 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 Four Star 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 and then filtered.Drinking water, estuary, river, and groundwater are treated with bleach, and 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, and 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 1-131 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 1-131.The resulting signal from each TSCA is relayed to a coincidence analyzer.

The beta transition and prompt 364.5 keV gamma transition from 1-131 register a coincidence count. Beta gamma coincidence counting allows for a very low background since the system is optimized for 1-131.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 H 2 0 2 and allowing for sufficient equilibration time so that a complete transposition of tritium with stable hydrogen has occurred.A-3 Donald C. Cook Nuclear Plant Annual Radiological Environmental Operating Report 2010 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 windows 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.GEL Labs (June 2010- December 2010)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 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 to allow for the decay of radon products.