Text

Annual Radiological Environmental Operating Report for the Period January 1, 2006 Through December 31, 2006
	ML071420088
Person / Time
Site:	Indian Point
Issue date:	05/15/2007
From:	Jones T; Entergy Nuclear Indian Point 2, Entergy Nuclear Indian Point 3
To:	; Document Control Desk, NRC/FSME
References
	FOIA/PA-2007-0324, NL-07-064
	Download: ML071420088 (132)
	v • d • e

Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 fBuchanan, N.Y. 10511-0249 Entffffl Tel (914) 734-6670 T.R. Jones Manager, Licensing IPEC May 15, 2007 Re: Indian Point Units 1, 2 & 3 Docket Nos. 50-3, 50-247, 50-286 NL-07-064 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Indian Point Nuclear Power Plants Units 1, 2 and 3 Annual Radiological Environmental Operating Report for 2006 Dear Sir or Madam; Enclosed please find one copy of the Indian Point Site Annual Radiological Environmental Operating Report for the period January 1, 2006 to December 31, 2006. No commitments are being made by this report.

This report is submitted in accordance with facility Technical Specification section 5.6.2 for DPR-5, DPR-26, and DPR-64, Indian Point Unit Nos.1, 2 and 3 respectively.

Should you or your staff have any questions, please contact Mr. Dennis Loope, Radiation Protection Manager at 914-736-8401.

Sincere T. . Jon~es Manager, Lice /sing Entergy, Indian Point Energy Center Enclosure cc: See next page

NL-07-064 Docket Nos. 50-3, 50-247, 50-286 Page 2 of 2 cc:

Mr. John P. Boska, Senior Project Manager, NRC NRR DORL Mr. Samuel J. Collins, Regional Administrator, NRC Region I NRC Resident Inspector's Office, Indian Point 2 Mr. Paul Eddy, NYS Department of Public Service Director, Spent Fuel Project Office, NRC ONMSS

Internal cc:

D. Loope, IPEC Rad Protection Mgr.

S. Meighan, Rad Protection Records & Documents

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ENTERGY NUCLEAR NORTHEAST INDIAN POINT NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 Docket No.50-003 Indian Point Unit 1 (IP1)

Docket No. 50-247 Indian Point Unit 2 (IP2)

Docket No. 50-286 Indian Point Unit 3 (IP3)

January 1 - December 31, 2006

TABLE OF CONTENTS Page 1.0 EXECUTIVE

SUMMARY

1-1

2.0 INTRODUCTION

2-1 2.1 Site Description 2-1 2.2 Program Background 2-1 2.3 Program Objectives 2-1 3.0 PROGRAM DESCRIPTION 3-1 3.1 Sample Collection 3-1 3.2 Sample Analysis 3-1 3.3 Sample Collection and Analysis Methodology 3-1 3.3.1 Direct Radiation 3-1 3.3.2 Airborne Particulates and Radioiodine 3-2 3.3.3 Hudson River Water 3-2 3.3.4 Drinking Water 3-2 3.3.5 Hudson River Shoreline Soil 3-2 3.3.6 Broad Leaf Vegetation 3-3 3.3.7 Fish and Invertebrates 3-3 3.3.8 Hudson River Aquatic Vegetation 3-3 3.3.9 Hudson River Bottom Sediment 3-3 3.3.10 Precipitation 3-4 3.3.11 Soil 3-4 3.3.12 Special Water Samples 3-4 3.3.13 Land Use Census 3-5 3.4 Statistical Methodology 3-5 3.4.1 Lower Limit of Detection and Critical Level 3-5 3.4.2 Determination of Mean and Propagated Error 3-6 3.4.3 Table Statistics 3-7 3.5 Program Units 3-8

TABLE OF CONTENTS (continued)

Page 4.0 RESULTS AND DISCUSSION 4-1 4.1 Direct Radiation 4-4 4.2 Airborne Particulates and Radioiodine 4-4 4.3 Hudson River Water 4-5 4.4 Drinking Water 4-6 4.5 Hudson River Shoreline Soil 4-6 4.6 Broad Leaf Vegetation 4-6 4.7 Fish and Invertebrates 4-7 4.8 Aquatic Vegetation 4-7 4.9 Hudson River Bottom Sediment 4-7 4.10 Precipitation 4-8 4.11 Soil 4-8 4.12 Special Water 4-8 4.13 Land Use Census 4-9 4.14 Conclusion 4-10

5.0 REFERENCES

5-1 APPENDICES:

A. ENVIRONMENTAL SAMPLING AND ANALYSIS REQUIREMENTS A-1 B. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM B-1 RESULTS

SUMMARY

C. HISTORICAL TRENDS C-1 D. INTERLABORATORY COMPARISON PROGRAM D-1 ii

LIST OF FIGURES FIGURE TITLE Page A-1 Sampling Locations (Within Two Miles) A-5 A-2 Sampling Locations (Greater Than Two Miles) A-6 A-3 Additional Sampling Locations A-7 C-1 Direct Radiation, 1996 to 2006 C-3 C-2 Radionuclides in Air - Gross Beta, 1996 to 2006 C-5 C-3 Hudson River Water-Tritium, 1996 to 2006 C-7 C-4 Drinking Water - Tritium, 1996 to 2006 C-9 C-5 Radionuclides in Shoreline Soil, 1996 to 2006 C-11 C-6 Broad Leaf Vegetation - Cs-137, 1996 to 2006 C-13 C-7 Fish and Invertebrates - Cs-1 37, 1996 to 2006 C-15 iii

LIST OF TABLES TABLE TITLE Paqe A-1 Indian Point REMP Sampling Station Locations A-2 A-2 Lower Limit of Detection Requirements for Environmental Sample Analysis A-8 A-3 Reporting Levels for Radioactivity Concentrations in Environmental Samples A-9 B-1 Summary of Sampling Deviations, 2006 B-2 B-la 2006 Air Sampling Deviations B-3 B-i b 2006 TLD Deviations B-3 B-I c 2006 Other Media Deviations B-3 B-2 Annual Summary, 2006 B-4 B-3 2006 Direct Radiation, Quarterly Data B-8 B-4 Direct Radiation, 1999 through 2006 Data B-9 B-5 2006 Direct Radiation, Inner and Outer Rings B-10 B-6 Gross Beta Activity in Airborne Particulate Samples, 2006 B-I 1 B-7 Concentrations of Gamma Emitters in Quarterly Composites of Air Particulate Samples, 2006 B-1 5 B-8 1-131 Activity in Charcoal Cartridge Samples, 2006 B-23 B-9 Concentrations of Gamma Emitters in Hudson River Water Samples, 2006 B-24 B-10 Concentrations of Tritium in Hudson River Water Samples, 2006 B-26 B-11 Radioactivity Concentrations in Drinking Water Samples, 2006 B-27 B-12 Concentrations of Tritium in Drinking Water Samples, 2006 B-29 B-13 Concentrations of Radionuclides in Shoreline Soil Samples, 2006 B-30 B-14 Concentrations of Gamma Emitters in Broad Leaf Vegetation, 2006 B-31 iv

LIST OF TABLES (Continued)

TABLE TITLE Page B-1 5 Concentrations of Gamma Emitters in Fish and Invertebrate Samples, 2006 B-35 B-16 Concentrations of Gamma Emitters in Aquatic Vegetation Samples, 2006 B-39 B-17 Concentrations of Radionuclides in Bottom Sediment, 2006 B-40 B-1 8 Concentrations of Radionuclides in Precipitation 2006 B-41 B-19 Concentrations of Gamma Emitters in Soil, 2006 B-42 B-20 Special Water Samples - Existing ODCM Locations, 2006 B-43 B-21 Special Water Samples - New ODCM Locations, 2006 B-50 B-22 Milch Animal Census, 2006 B-52 B-23 Land Use Census, 2006 B-53 C-1 Direct Radiation Annual Summary, 1996 to 2006 C-2 C-2 Radionuclides in Air, 1996 to 2006 C-4 C-3 Radionuclides in Hudson River Water, 1996 to 2006 C-6 C-4 Radionuclides in Drinking Water, 1996 to 2006 C-8 C-5 Radionuclides in Shoreline Soil, 1996 to 2006 C-10 C-6 Radionuclides in Broad Leaf Vegetation, 1996 to 2006 C-12 C-7 Radionuclides in Fish and Invertebrates, 1996 to 2006 C-14 D-1 2006 QA Program Schedule D-2 D-2 Ratio of Agreement D-3 D-3 2006 Co-58 Results D-6 D-4 2006 Co-60 Results D-8 D-5 JAF (EML) Environmental Laboratory Summary D-9 D-6 Interlaboratory Comparison Program D-10 V

SECTION I EXECUTIVE

SUMMARY

1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report (AREOR) contains descriptions and results of the 2006 Radiological Environmental Monitoring Program (REMP) for the Indian Point site. The Indian Point site consists of Units 1, 2 and 3.

Units 1, 2 and 3 are owned by Entergy Nuclear Northeast. Unit 1 was retired as a generating facility in 1974, and as such, its reactor is no longer operated.

The REMP is used to measure the direct radiation and the airborne and waterborne pathway activity in the vicinity of the Indian Point site. Direct radiation pathways include radiation from buildings and plant structures, airborne material that might be released from the plant, cosmic radiation, fallout, and the naturally occurring radioactive materials in soil, air and water. Analysis of thermoluminescent dosimeters (TLDs), used to measure direct radiation, indicated that there were no increased radiation levels attributable to plant operations.

The airborne pathway includes measurements of air, precipitation, drinking water, and broad leaf vegetation samples. The airborne pathway measurements indicated that there was no increased radioactivity attributable to 2006 Indian Point Station operation.

The waterborne pathway consists of Hudson River water, fish and invertebrates, aquatic vegetation, bottom sediment, and shoreline soil. Measurements of the media comprising the waterborne pathway indicated that there was no adverse radiological impact to the surrounding environment attributed to Indian Point Station operations.

This report contains a description of the REMP and the conduct of that program as required by the IPEC Offsite Dose Calculation Manuals, herein referred to as ODCM.

This 2006 AREOR also contains summaries and discussions of the results of the 2006 program, trend analyses, potential impact on the environment, land use census, and interlaboratory comparisons.

During 2006, a total of 1342 analyses were performed. Table B-1 presents a summary of the collected sample results. The actual sampling frequency in 2006 was higher than required, due to the inclusion of additional sample locations and media.

An investigation of groundwater contamination with tritium and other radionuclides has been ongoing since 2005 and continued throughout 2006. This investigation of potential onsite sources of contamination is not the focus of this Annual Radiological Environmental Operating Report; however, in 2006, Entergy agreed to several changes in the REMP to assure that all pathways were being evaluated.

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Specifically, two groundwater sample wells (non-drinking water) were designated as "boundary wells" and were sampled as special water samples for tritium and strontium-90. These wells were designated as REMP sample stations 104 and 105.

In addition, a change was made to the existing fish and invertebrate samples and shoreline sediment samples. The locations and frequency remained the same; however, strontium-90 was added to the required analyses. These additions were committed to in 2006 and the sampling/analysis was conducted in 2006. Starting in 2007, these changes will be identified in the ODCM.

Based on recent site hydrology evaluations and the addition of a number of groundwater sampling wells, two new groundwater wells (MW-40 and MW-51)were installed. These wells were specifically designed for groundwater monitoring and were placed in locations that would be representative of groundwater near the site boundary. Since the installation of these new wells, the remaining four locations (REMP sampling stations 99, 100,101, and 102) sampled as "special water" were no longer considered as necessary, because they did not provide optimal information on groundwater concentrations. These four locations continued to be sampled throughout 2006, but will be eliminated as REMP sample locations starting in 2007.Special water sample results for 2006 are summarized in Tables B-20 and B-21.

In summary, the levels of radionuclides in the environment surrounding Indian Point were within the historical ranges, i.e., previous levels resulting from natural and anthropogenic sources for the detected radionuclides. Further, Indian Point operations in 2006 did not result exposure to the public greater than environmental background levels.

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SECTION 2 INTRODUCTION

2.0 INTRODUCTION

2.1 Site Description The Indian Point site occupies 239 acres on the east bank of the Hudson River on a point of land at Mile Point 42.6. The site is located in the Village of Buchanan, Westchester County, New York. Three nuclear reactors, Indian Point Unit Nos. 1, 2 and 3, and associated buildings occupy approximately 35 acres. Unit 1 has been retired as a generating facility. Units 1, 2, and 3 are owned and operated by Entergy Nuclear Northeast.

2.2 Program Background Environmental monitoring and surveillance have been conducted at Indian Point since 1958, which was four years prior to the start-up of Unit 1. The pre-operational program was designed and implemented to determine the background radioactivity and to measure the variations in activity levels from natural and other sources in the vicinity, as well as fallout from nuclear weapons tests. Thus, as used in this report, background levels consist of those resulting from both natural and anthropogenic sources of environmental radioactivity. Accumulation of this background data permits the detection and assessment of environmental activity attributable to plant operations.

2.3 Program Obiectives The current environmental monitoring program is designed to meet two primary objectives:

1. To enable the identification and quantification of changes in the radioactivity of the area, and

2. To measure radionuclide concentrations in the environment attributable to operations of the Indian Point site.

To identify changes in activity, the environmental sampling schedule requires that analyses be conducted for specific environmental media on a regular basis. The radioactivity profile of the environment is established and monitored through routine evaluation of the analytical results obtained.

The REMP designates sampling locations for the collection of environmental media for analysis. These sample locations are divided into indicator and control locations. Indicator locations are established near the site, where the 2-1

presence of environmental radioactivity of plant origin is most likely to be detected. Control locations are established farther away (and upwind/upstream, where applicable) from the site, where the level would not generally be affected by plant discharges. The use of indicator and control locations enables the identification of potential sources of detected radioactivity, thus meeting one of the program objectives.

Verification of expected radionuclide concentrations resulting from effluent releases attributable to the site is another program objective. Verifying projected concentrations through the REMP is difficult since the environmental concentrations resulting from plant releases are consistently too small to be detected. Plant related radionuclides were detected in 2006; however, residual radioactivity from atmospheric weapons tests and naturally occurring radioactivity were the predominant sources of radioactivity in the samples collected. Analysis of the 2006 REMP sample results supports the premise that radiological effluents were well below regulatory limits.

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SECTION 3 PROGRAM DESCRIPTION

3.0 PROGRAM DESCRIPTION To achieve the objectives of the REMP and ensure compliance with the ODCM, sampling and analysis of environmental media are performed as outlined in Table A-1 and described in section 3.3.

3.1 Sample Collection Entergy Nuclear Northeast Nuclear Environmental Monitoring (NEM) personnel perform collection of environmental samples for the Indian Point site.

Assistance in the collection of fish and invertebrate samples was provided by a contracted environmental vendor, Normandeau Associates, Inc.

3.2 Sample Analysis The analysis of Indian Point environmental samples is performed by the James A. Fitzpatrick Nuclear Power Plant (JAFNPP) Environmental Laboratory in Fulton, New York. The JAFNPP lab at Fulton currently analyzes all samples. In addition, some water and well samples were analyzed at another EPA certified laboratory.

3.3 Sample Collection and Analysis Methodology 3.3.1 Direct Radiation Direct gamma radiation is measured using integrating calcium sulfate thermoluminescent dosimeters (TLDs), which provide cumulative measurements of radiation exposure (i.e., total integrated exposures in milliroentgen, mR) for a given period. The area surrounding the Indian Point site is divided into 16 compass sectors. Each sector has two TLD sample locations. The inner ring is located near the site boundary at approximately 1 mile (1.6 km). The outer ring is located at approximately 5 miles (8 km) from the site (6.7- 8.0 km), see Figures A-1 and A-2.

An additional TLD sample site is located at Roseton (20.7 miles north) as a control, and there are eight other TLD sample locations of special interest.

In total, there are 41 TLD sample sites, designated DR-1 through DR-41, with two TLDs at each site. TLDs are collected and processed on a quarterly basis. The results are reported as mR per standard quarter (91 days). The mR reported is the average of the two TLDs from each sample site.

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3.3.2 Airborne Particulates and Radioiodine Air samples were taken at nine locations varying in distance from 0.28 to 20.7 miles (0.4 to 33 km) from the plant. These locations represent one control at sampling station 23 (A5) and eight indicator locations. These indicator locations are at sampling stations 4 (Al), 5 (A4), 22, 27, 29, 44, 94 (A2), and 95 (A3). The locations are shown on Figures A-I, A-2, and A-3. The air samples are collected continuously by means of fixed air particulate filters followed by in-line charcoal cartridges. Both are changed on a weekly basis.

The filter and cartridge samples are analyzed for gross beta and radioiodine, respectively. In addition, gamma spectroscopy analysis (GSA) is performed on quarterly composites of the air particulate filters.

3.3.3 Hudson River Water Hudson River water sampling is performed continuously at the intake structure (sampling station 9, Wal) and at a point exterior to the discharge canal where Hudson River water and water from the discharge canal mix (sampling station 10, .Wa2); see Figure A-I. An automatic sampling apparatus is used to take representative samples. On a weekly basis, accumulated samples are taken from both sample points. These weekly river water samples are composited for monthly gamma spectroscopy analysis, and quarterly for tritium analysis.

3.3A4 Drinkingq Water Samples of drinking water are collected monthly from the Camp Field Reservoir (3.4 miles NE, sample station 7, sample designation Wbl) and New Croton Reservoir (6.3 Mi SE, sample station 8); see Figure A-3. Each monthly sample is approximately 4 liters and is analyzed for gamma-emitting radionuclides, gross beta, and 1-131. They are also composited quarterly and analyzed for tritium.

3.3.5 Hudson River Shoreline Soil Shoreline soil samples are collected at three indicator and two control locations along the Hudson River. The indicator locations are at sampling stations 53 (Wcl), 28, and 17. The control locations are at sampling stations 50 (Wc2) and 84. Figures A-1, A-2, and A-3 show these locations. The samples are gathered at a level above low tide and below high tide and are approximately 2-kg grab samples. These samples are collected at greater than 90 days apart and are analyzed by gamma spectroscopy and for strontium-90.

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3.3.6 Broad Leaf Vegetation Broad leaf vegetation samples are collected from three locations during the growing season. The indicator locations are sampling stations 94 (Ic2) and 95 (Icl), and the control location is at Roseton, sampling station 23 (Wc3).

See Figures A-1 and A-2. The samples are collected monthly, when available, and analyzed by gamma spectroscopy. These samples consist of at least 1 kg of leafy vegetation and are used in the assessment of the food product and milk ingestion pathways.

3.3.7 Fish and Invertebrates Fish and invertebrate samples are obtained from the Hudson River at locations upstream and downstream of the plant discharge. The indicator location (downstream sample point) is designated as sampling station 25 (Ibl) and the control location (upstream) is at Roseton, sampling station 23 (Ib2). See Figures A-1 and A-2. These samples are collected in season or semiannually if they are not seasonal. The fish and invertebrates sampled are analyzed by gamma spectroscopy and for strontium-90.

3.3.8 Hudson River Aquatic Vegetation During the spring and summer, aquatic vegetation samples are collected from the Hudson River at two indicator locations (sampling stations 17 and 28) and one control location (84); see Figure A-3. Samples of aquatic vegetation are obtained depending on sample availability. These samples are analyzed by gamma spectroscopy.

3.3.9 Hudson River Bottom Sediment Bottom sediment and benthos are sampled at four locations, three indicator locations (sampling stations 10, 17, and 28) and one control location (84),

along the Hudson River, once each spring and summer; see Figure A-3.

These samples are obtained using a Peterson grab sampler or similar instrument. The bottom sediment samples are analyzed by gamma spectroscopy. Although not required, in 2006, four samples were also analyzed for Sr-90.

3.3.10 Precipitation Precipitation samples are continuously collected at one indicator location (sampling station 44) and one control location (23); see Figure A-3. They are collected in sample bottles designed to hinder evaporation. They are composited quarterly and analyzed for tritium. They are also analyzed by gamma spectroscopy.

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3.3.11 Soil Soil samples are collected from two indicator locations (sampling stations 94 and 95), and one control location (23) on an annual basis; see Figure A-3.

They are approximately 2 kg in size and consist of about twenty 2-inch deep cores. The soil samples are analyzed by gamma spectroscopy.

3.3.12 Special Water Samples Six locations were sampled as "special water" in 2006. These locations include four locations that were sampled in 2006, but will be eliminated from the sample matrix starting in 2007. Based on recent site hydrology evaluations and the addition of a number of groundwater sampling wells, two new groundwater wells (MW-40 and MW-51) were installed. These wells were specifically designed for groundwater monitoring and were placed in locations that would be representative of groundwater near the site boundary.

Since the installation of these new wells, the remaining four locations sampled as "special water" were no longer considered as necessary, because they did not provide optimal information on groundwater concentrations.

These four locations continued to be sampled throughout 2006, but will be eliminated as REMP sample locations starting in 2007. These sample locations are described as follows: the Algonquin outfall (non-drinking surface water, location 99), the gypsum plant outfall (non-drinking surface water, location 100), the Trap Rock Quarry (non-drinking surface water, location 101), and the 5 th Street Well (non-drinking ground water, location 102). The above special water locations were sampled monthly and analyzed for tritium and gamma spectroscopy.

Two groundwater sample wells (non-drinking water) were installed and developed in 2006. These wells were designated as "boundary wells" and were sampled as special water samples for tritium and strontium-90 on a quarterly basis. These wells were designated as REMP sample stations 104 (MW-40) and 105 (MW-51). The locations of the special water samples are shown in Figure A-3.

3.3.13 Land Use Census Each year a land use census consisting of milch animal and residence surveys is conducted during the growing season to determine the current utilization of land within 5 miles (8 km) of the site. These surveys are used to determine whether there are changes in existing conditions that warrant changing the sampling program.

The milch animal census is used to identify animals producing milk for human consumption within 5 miles (8 km) of Indian Point. The census consists of visual field surveys of the areas where a high probability of milch animals 3-4

exists and confirmation through personnel such as feed suppliers who deal with farm animals and dairy associations (See Tables B-22 and B-23).

Although there are presently no animals producing milk for human consumption within 5 miles (8 km) of the site, the census is performed to determine if a milk-sampling program needs to be conducted.

A residence census is also performed to identify the nearest residence(s) to the site in each of the 16 sectors surrounding Indian Point. See Table B-23.

A garden census was not performed, as the ODCM allows sampling of vegetation in two sectors near the site boundary in lieu of a garden census.

3.4 Statistical Methodology There are a number of statistical calculation methodologies used in evaluating the data from the Indian Point REMP. These methods include determination of Lower Limits of Detection (LLD) and Critical Levels (Lc), and estimation of the mean and associated propagated error.

3.4.1 Lower Limit of Detection (LLD) and Critical Level (Lc)

The LLD is a predetermined concentration or activity level used to establish a detection limit for the analytical procedures.

The Nuclear Regulatory Commission (NRC) specifies the maximum acceptable LLDs for each radionuclide in specific media. The LLDs are determined by taking into account overall measurement methods. The equation used to calculate the LLD is:

LLD = 4.66 K Sb, where: Sb = standard deviation of the background count rate, and K consists of variables, which account for such parameters as:

- Instrument characteristics (e.g., efficiency)

- Sample size

- Counting time

- Media density (self-absorption)

- Radioactive decay

- Chemical yield In the ODCM program, LLDs are used to ensure that minimum acceptable detection capabilities for the counting system are met with specified statistical confidence levels (95% detection probability with 5% probability of a false negative). The LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement process and not as an "a 3-5

posteriori" (after the fact) limit for a particular measurement. Table A-2 presents the RETS required LLDs for specific media and radionuclides as specified by the NRC. The LLDs actually achieved are usually much lower since the RETS required LLDs represent the maximum allowed.

The critical level (Lc) is defined as that net sample counting rate which has a 5% probability of being exceeded when the actual sample activity is zero (e.g., when counting background only). It is determined using the following equation.

Lc = ka Sb (1 + T1/TS)°5 in cpm where: ka = 1.645 (corresponds to a 95% confidence level)

Sb = standard deviation of the background count rate = (Rb/Tb)° 5 Rb = background count rate (cpm)

Tb = background count time (min)

T, = sample count time (min)

For the REMP, net sample results which are less than the Lc value are considered not detected, and the Lc value is reported as the "less than" value, unless otherwise noted. Values above the Lc are considered positively detected radioactivity in the environmental media of interest (with a 5%

chance of false positive).

3.4.2 Determination of Mean and Propagated Error In accordance with program policy, recounts of positive samples are performed. When the initial count reveals the presence of radioactivity, which may be attributed to plant operations, at a value greater than the L, two recounts are performed to verify the positive results. The recounts are not performed on; air samples with positive results from gross beta analysis, since the results are always positive due to natural background radioactive material in the air, or tritium in water samples, since an outside contractor provides these activities. When a radionuclide is positively identified in two or more counts, the analytical result for the radionuclide is reported as the mean of the positive detections and the associated propagated error for that mean.

In cases where more than one sample result is available, the mean of the sample results and the estimated error for the mean are reported in the Annual Report.

The mean (X) and propagated error (PE) are calculated using the following equations:

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N X-5Exi i=1 N

where: X= value of each individual observation N = number of observations ZN* (ERR1,)2 PE=

N where: ERR1 = 1 sigma error of the individual analysis N = number of observations 3.4.3 Table Statistics The averages shown in the summary table (Table B-2) are the averages of the positive values in accordance with the NRC's Branch Technical Position (BTP) to Regulatory Guide 4.8 (Reference 11). Samples with "<" values are not included in the averages.

It should be noted that this statistic for the mean using only positive values tends to strongly bias the average high, particularly when only a few of the data are measurably positive. The REMP data show few positive values; thus the corresponding means are biased high. Exceptions to this include direct radiation measured by TLDs and gross beta radioactivity in air, which show positive monitoring results throughout the year.

In the data tables B-6 through B-21, values shown are based on the L, value, unless otherwise noted. If a radionuclide was detected at or above the L, value in two or more counts, the mean and error are calculated as per Section 3.4.2, and reported in the data table. Values listed as "<" in the data tables are the Lc values for that sample, unless otherwise noted. If multiple counts were performed on a sample and a radionuclide's values are "< Lc " each time, the largest critical level is reported in the data table.

The historical data tables contain the annual averages of the positive values for each year. The historical averages are calculated using only the positive values presented for 1996 through 2006. The 2006 average values are included in these historic tables for purposes of comparison.

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3.5 Pro-gram Units The Radiological Environmental Monitoring Program uses standard radiological units to express program results, described as follows:

Becquerel is a measure of radioactive material, abbreviated Bq, from the International System of Units (SI). A Becquerel is one atom disintegration per second. A Becquerel will normally be used with a volume or mass to express the radioactive concentration of some sample material.

Cubic meter is a metric volume slightly larger than a cubic yard. It is abbreviated m3 and is used in this report as the unit for the volume of air.

Curie is the basic unit used to describe the intensity of radioactivity. The curie is equal to 37 billion disintegrations per second.

Kilogram is a metric unit of mass; it is equivalent to 2.2 pounds. Kilogram is abbreviated kg and can be expressed as kg-wet or kg-dry. The wet or dry designation denotes whether the sample is dried or not before it is counted.

Liter is a metric unit of volume slightly larger than a quart. It is abbreviated L and is used as the volume for liquids.

Microsievert (uSv) is the SI unit for measure of radiation dose to humans. It is equal to 0.1 mrem.

Millirem is a measure of radiation dose to humans, abbreviated mrem; it is 1/1000 of a rem. Millirem expressed for some period of time is the dose rate.

Milliroentgen is different in that it is a measure of radiation in air. Normal background radiation dose is approximately 300 mrem per year.

Milliroentgenis a measure of radiation exposure, abbreviated mR; it is 1/1000 of a roentgen. Milliroentgen for some period of time is the exposure rate.

Milliroentgen (mR) per standard quarter is used for direct radiation or Thermoluminescent Dosimeter (TLD) results.

Picocurieis a measure of radioactive material (pCi). A picocurie is 2.22 atom disintegrations per minute. A picocurie will normally be used with a volume or mass to express the radioactive concentration of some sample material.

Picocuriesper cubic meter (pCi/m 3 ) is the concentration for air samples.

Picocuries per kilogram (pCi/kg) is the expression used to express concentration for REMP vegetation, soil, shoreline soil, and bottom sediment samples.

Picocuriesper liter(pCi/L) is used to express concentration for liquid samples such as, precipitation, drinking water, and river water samples.

Standardquarteris a measure of time (91 days). It is used as the unit of time for expression of mR for the direct radiation measurements from TLDs.

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SECTION 4 RESULTS AND DISCUSSION 4.0 RESULTS AND DISCUSSION The 2006 Radiological Environmental Monitoring Program (REMP) was conducted in accordance with Indian Point's Offsite Dose Calculation Manuals ODCM. The ODCM contains requirements for the number and distribution of sampling locations, the types of samples to be collected, and the types of analyses to be performed for measurement of radioactivity.

The REMP at Indian Point includes measurements of radioactivity levels in the following environmental pathways.

Hudson River-water Shoreline soil Fish and invertebrates Aquatic vegetation Bottom sediment Airborne Particulates and Radioiodine Precipitation Drinking Water Terrestrial Broad Leaf Vegetation Direct Gamma Radiation Soil Special Water (groundwater or surface water)

An annual land use and milch animal census is also part of the REMP.

To evaluate the contribution of plant operations to environmental radioactivity levels, other man-made and natural sources of environmental radioactivity, as well as the aggregate of past monitoring data, must be considered. It is not merely the detection of a radionuclide, but the evaluation of the location, magnitude, source, and history of its detection that determines its significance. Therefore, we have reported the data collected in 2006 and assessed the significance of the findings.

A summary of the results of the 2006 REMP is presented in Table B-2. This table lists the mean and range of all positive results obtained for each of the media sampled at ODCM indicator and control locations. Discussions of these results and their evaluations are provided below.

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The radionuclides detected in the environment can be grouped into three categories:

(1) naturally occurring radionuclides; (2) radionuclides resulting from weapons testing and other non-plant related, anthropogenic sources; and (3) radionuclides that could be related to plant operations.

Naturally Occurring Radionuclides The environment contains a broad inventory of naturally occurring radionuclides which can be classified as, cosmic ray induced (e.g., Be-7, H-3) or geologically derived (e.g., Ra-226 and progeny, Th-228 and progeny, K-40). These radionuclides constitute the majority of the background radiation source and thus account for a majority of the annual background dose detected. Since the detected concentrations of these radionuclides were consistent at indicator and control locations, and unrelated to plant operations, their presence is noted only in the data tables and will not be discussed further.

Residual Radioactivity from Atmospheric Weapons Testing The second group of radionuclides detected in 2006 consists of those resulting from past weapons testing in the earth's atmosphere. Such testing in the 1950's and 1960's resulted in a significant atmospheric radionuclide inventory, which, in turn, contributed to the concentrations in the lower atmosphere and ecological systems.

Although reduced in frequency, atmospheric weapons testing continued into the 1980's. The resultant radionuclide inventory, although diminishing with time (e.g.,

through radioactive decay and natural dispersion processes), remains detectable.

Cs-1 37 is present in the environment from atmospheric weapons testing and to a lesser extent from the Chernobyl accident in 1986. Cs-1 34 is produced by weapons testing in much lower quantities. Because Cs-1 34 has a short half-life relative to Cs-137, Cs-1 34 from Chernobyl is not likely to be present in 2006.

Strontium-90 (Sr-90) is also present in the environment from atmospheric testing debris. There is also Sr-90 in the environment from the Chernobyl accident in 1986; however, this quantity is not significant compared to atmospheric weapons testing (Reference 31).

According to Eisenbud and Gesell (Reference 3), tap water in New York City was monitored during the period of weapons testing and reached a peak of 2.12 pCi/liter in 1963. The U.S. EPA Environmental Radiation Ambient Monitoring System program monitors concentrations of Sr-90 in drinking water at 78 sites. For 1995, the U.S. EPA reported Sr-90 concentrations at 78 locations, and the mean of the positive values (13 of 78) was 0.32 pCi/liter. Sites with above-average concentrations included Detroit and Niagara Falls, with Sr-90 concentrations of 0.4 and 0.5 pCi/liter, respectively (Reference 32).

4-2

Radioactivity Potentially of Plant Origin The final group of radionuclides detected through the 2006 REMP comprises those that may be attributable to current plant operations. During 2006, Cs-137, Sr-90, and tritium (H-3) were the only potentially plant-related radionuclides detected in some environmental samples.

H-3 may be present in the local environment due to either natural occurrence, other man-made sources, or as a result of plant operations. Small amounts of H-3 were detected in one of four quarterly composite samples from the discharge mixing zone (386 pCi/Liter). This composite sample was detected at a value lower than the required Lower Limit of Detection (3000 pCi/Liter).

In 2006, the detected radionuclide(s) attributable to past atmospheric weapons testing consisted of Cs-1 37 and Sr-90 in some media. The levels detected for Cs-137 were consistent with the historical levels of radionuclides resulting from weapons tests as measured in previous years. Prior to 2006, Sr-90 analysis had not been conducted since the 1984, so comparison to recent historical levels is not possible.

However, the low levels detected in the environment are consistent with decayed quantities of activity from atmospheric weapons testing.

Sr-90 was detected in 4 fish and invertebrate samples, 3 in the control samples and one in the indicator samples. Since the levels detected were comparable in the indicator and control location samples, atmospheric weapons' testing is the likely cause. Five out of 18 special water samples indicated Sr-90 at levels close to the level of detection, at an average of 0.78 pCi/liter. All of these detections are considered to be due to residual atmospheric weapons tests.

1-131 is also produced in fission reactors, but can result from non-plant related anthropogenic sources, e.g., medical administrations, such as in previous annual reports. 1-131 was not detected in 2006.

Co-58 and Co-60 are activation/corrosion products also related to plant operations.

They are produced by neutron activation in the reactor core. As Co-58 has a much shorter half-life, its absence "dates" the presence of Co-60 as residual from releases of both nuclides in the past. When significant concentrations of Co-60 are detected but no Co-58, there is an increased likelihood that the Co-60 is due to residual Co-60 from past operations. There was no Co-58 or Co-60 detected in the 2006 REMP, though they (Co-58 and Co-60) can be observed in historical tables.

In the following sections, a summary of the results of the 2006 REMP is presented by sample medium, and the significance of any positive findings discussed. It should be noted that naturally occurring radionuclides are omitted from the summary table (Table B-2) and further discussion.

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4.1 Direct Radiation The environmental TLDs used to measure the direct radiation were TLDs supplied and processed by the JAFNPP Environmental Laboratory. The laboratory uses a Panasonic TLD system. In 2006, the TLD program produced a consistent picture of ambient background radiation levels in the vicinity of the Indian Point Station. A summary of the annual TLD data is provided in Table B-2 and all the TLD data are presented in Tables B-3, B-4 and B-5. TLD sample site DR-40 is the control site for the direct radiation (DR) series of measurements.

Table B-3 provides the quarterly and annual average reported doses in mR per standard quarter for each of the direct radiation sample points, DR-1 through DR-41. The table also provides the sector for each of the DR sample points. Table B-4 provides the mean, standard deviation, minimum and maximum values in mR per standard quarter for the years 1996 through 2005. The 2006 means are also presented in Table B-4. Table B-5 presents the 2006 TLD data for the inner ring and outer ring of TLDs.

The 2006 mean value for the direct radiation sample points was 14.1 mR per standard quarter. The mean value for the period 2000 through 2006 was 14.2 mR per standard quarter. At those locations where the 2006 mean value was higher, they are within historical bounds for the respective locations.

The DR sample locations are arranged so that there are two concentric rings of TLDs around the Indian Point site. The inner ring (DR-1 to DR-1 6) is close to the site boundary. The outer ring (DR-17 to DR-32) has a radius of approximately 5 miles from the three Indian Point units. The results for these two rings of TLDs are provided in Table B-5. The annual average for the inner ring was 13.9 mR per standard quarter and also average for the outer ring was 14.3 mR per standard quarter. The control location average for 2006 was 17.5 mR per standard quarter.

Table C-1 and Figure C-1 present the 10-year historical averages for the inner and outer rings of TLDS. The 2006 averages are consistent with the historical data. The 2006 and previous years' data show that there is no measurable direct radiation in the environment due to the operation of the Indian Point site.

4.2 Airborne Particulates and Radioiodine An annual summary of the results of the 2006 air particulate filter and charcoal cartridge analyses is presented in Table B-2. As shown, there were no radionuclides detected in the air attributable to plant operations.

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The results of the analyses of weekly air particulate filter samples for gross beta activity are presented in Table B-6, and the results of the gamma spectroscopy analyses of the quarterly composites of these samples are in Table B-7.

Gross beta activity was found in air particulate samples throughout the year at all indicator and control locations. The average gross beta activity for the eight indicator air sample locations was 0.013 pCi/m 3 and the average for the control location was 0.013 pCi/m 3 . The activities detected were consistent for all locations, with no significant differences in gross beta activity in any sample due to location. Gamma spectroscopy analyses of the quarterly composite air samples showed that no reactor-related nuclides were detected and that only naturally-occurring radionuclides were present at detectable levels.

The mean annual gross beta concentrations and Cs-1 37 concentrations in air for the past 10 years are presented in Table C-2. From this table and Figure C-2, it can be seen that the average 2006 gross beta concentration was consistent with historical levels. Cs-1 37 has not been detected since 1987. This is consistent with the trend of decreasing ambient Cs-137 concentrations in recent years.

The charcoal cartridge analytical results are presented in Table B-8. "Less than" values are presented as sample critical level (Lc). There was no 1-131 detected (LLD = 0.07 pCi/m 3) in the charcoal cartridge samples, which is consistent with historical trends.

From the data, it can be seen that no airborne radioactivity attributable to the operation of Indian Point was detected in 2006.

4.3 Hudson River Water A summary of the radionuclides detected in the Hudson River water is contained in Table B-2. Data resulting from analysis of monthly Hudson River water samples for gamma emitters, and H-3 analysis of quarterly composites, are presented in Tables B-9 and B-10, respectively.

No radionuclides other than those that are naturally occurring and tritium were detected in the Hudson River Water samples. Tritium, whose presence is likely to be due to plant operations, has been detected in the past as depicted in Table C-3, and was detected in one of four composite samples from the discharge canal at 386 +/- 136 pCi/I, slightly above LLD. These tritium levels are well below the required LLD of 3000 pCi/L. Additionally, table C-3 indicates the absence of Cs-1 37 which is consistent with historical data.

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4.4 Drinking Water The annual program summary table (Table B-2) contains a summary of the 2006 drinking water sample analysis results. Results of the gamma spectroscopy analyses of the monthly drinking water samples are in Table B-11 and results of tritium analysis of quarterly composites are in Table B-1 2.

Other than naturally occurring radionuclides, no radionuclides were detected in drinking water samples.

A summary and illustration of historic trends of drinking water are provided in Table C-4 and Figure C-4, respectively. An examination of the data indicates that operation of the Indian Point units had no detectable radiological impact on drinking water.

4.5 Hudson River Shoreline Soil A summary of the radionuclide concentrations detected in the shoreline soil samples is contained in Table B-2. Table B-13 contains the results of the gamma spectroscopic and strontium-90 analyses of the shoreline soil samples.

In addition to the naturally occurring nuclides, Cs-137 was identified in the Hudson River shoreline soil samples in 2006. Cs-137 was detected at the Verplank location in both samples from that location, for a total of two positive values out of eight samples from indicator locations. Cs-1 37 was detected at the control location (Manitou Inlet) in one out of two samples. The average concentration for the indicator locations that had positive indication of Cs-1 37 was 147 pCi/kg-dry with a maximum concentration of 158 pCi/kg-dry. The control location with one positive sample indicated 65 pCi/kg-dry.

An historical look at Cs-1 37 detected in shoreline soil at indicator and control locations can be viewed in Table C-5 and Figure C-5. Cs-137 has been and continues to be present in this media, both at indicator and control locations, at a consistent level over the past ten years. Cs-1 34 and Cs-1 37 are both discharged from the plant in similar quantities. The lack of Cs-1 34 activity is an indication that the primary source of the Cs-137 in the shoreline soil is legacy contamination from weapons fallout.

4.6 Broad Leaf Vegetation Table B-2 contains a summary of the broad leaf vegetation sample analysis results. Data from analysis of the 2006 samples are presented in Table B-14.

Analyses of broad leaf vegetation samples revealed only naturally occurring nuclides.

4-6

Table C-6 contains an historical summary and Figure C-6 is an illustration of the broad leaf vegetation analysis results. The detection of low levels of Cs-137 has occurred sporadically at both indicator and control locations at relatively low concentrations for the past ten years; however, Cs-1 37 was not detected in 2006.

4.7 Fish and Invertebrates A summary of the fish and invertebrate sample analysis results is presented in Table B-2. Table B-15 contains the results of the analysis of fish and invertebrate samples for 2006. Sr-90 was added to the analyte list in 2006, and it was detected in one indicator sample (fish) and three control samples (2 fish, 1 invertebrate). Other than these detections, fish and invertebrate samples showed only radionuclides of natural origin. Because the Sr-90 detection was both at the indicator and control locations, and the values at the control station, approximately 20 miles upstream, were approximately the same as that of the indicator station, the source of the Sr-90 is considered to be residual fallout from weapons testing.

A summary of historical fish and invertebrate analytical data is presented in Table C-7 and illustrated in Figure C-7. Data are consistent with historical trends.

4.8 Aquatic Vegetation A summary of the aquatic sample analysis results is presented in Table B-2.

Table B-1 6 contains the results of the analysis of aquatic vegetation samples for 2006. Cs-1 37 was detected at one of 4 indicator station samples, and at one of 3 control station samples. The concentration of Cs-1 37 in the indicator sample was slightly higher than that of the control, but was almost the same value. Cs-1 34 was not detected in any aquatic vegetation samples. While it is possible that the Cs-1 37 is from plant origin, the lack of Cs-1 34 suggests that the primary source of the Cs-1 37 is residual weapons test fallout.

This detection of Cs-137 in aquatic vegetation at both indicator and control locations is consistent with historical levels.

4.9 Hudson River Bottom Sediment A summary of the Hudson River bottom sediment analysis results is presented in Table B-2. Table B-17 contains the results of the analysis of bottom sediment samples for 2006. Cs-137 was detected at 7 of 10 indicator station samples, and at one of 3 control station samples. Cs-134 was not detected in any bottom sediment samples. The lack of Cs-1 34 suggests that the primary source of the Cs-137 in bottom sediment is from historical plant releases at least several years old and from residual weapons test fallout.

4-7

While not required by the ODCM, Sr-90 was analysis was conducted at 3 indicator locations and one control location in August 2006. Sr-90 was not identified in any of the samples.

This detection of Cs-1 37 in bottom sediment has been generally decreasing over the last 10 years, and Cs-1 34 has not been detected in bottom sediment since 2002. The data for 2006 are consistent with but slightly lower than historical levels.

4.10 Precipitation A summary of the precipitation sample analysis results is presented in Table B-2. Table B-18 contains the results of the precipitation samples for 2006.

Other than naturally occurring radionuclides, no radionuclides were detected in precipitation samples.

A review of historical data over the last 10 years indicates tritium had been detected in both indicator and control precipitation samples in 1997; however, there have been no instances of positive values since that time.

4.11 Soil A summary of the soil sample analysis results is presented in Table B-2.

Table B-19 contains the results of the soil samples for 2006. Other than naturally occurring radionuclides, no radionuclides were detected in precipitation samples. This is consistent with historical results over the last 10 years.

4.12 Special Water A summary of the special water samples for 2006 is contained in Table B-2.

Data resulting from analysis of the special water samples for gamma emitters, tritium analysis, and Sr-90 are presented in Table B-20 for existing ODCM sample locations and in Table B-21 for those ODCM locations that will be effective in 2007.

Eighteen samples were analyzed for Sr-90, and 5 of these showed detectable Sr-90. All of these results (range 0.49 - 1.26 pCi/liter) were well below the reporting level. As described in Section 4.0, all of these detections are considered to be due to residual atmospheric weapons tests. Other than the above, only naturally occurring radionuclides were detected in the special water samples.

4-8

4.13 Land Use Census Environmental Monitoring Land Use Census Methodology:

A comprehensive survey of the of the 5 mile (8 kilometer) area surrounding the Indian Point Site was conducted during the 2006 Spring, Summer and Fall months in accordance with the ODCM.

Visual inspections were made of the 5-mile area around the Indian Point Site during routine sample collections and emergency plan equipment inspections in the area throughout the year.

Information was obtained from the New York Agricultural Statistic Service on milching animals within the 5-mile area surrounding Indian Point Energy Center.

An extensive land survey was conducted of the 5-mile area in an attempt to identify new residential areas, commercial developments and to identify milch animals in pasture. Previous locations were visited and verified by dispatching Nuclear Environmental Technicians to the various locations.

Note: These actions were taken while performing quarterly environmental badge change out and field inspections through out the 4 surrounding counties.

Orange County was surveyed during through the summer and fall.

Rockland County was surveyed during summer and fall.

" Putnam County was surveyed during the summer and fall.

Westchester County was surveyed during the spring and summer and fall.

Note: An aerial survey was not conducted of the 5-mile area this year.

Results:

A census was performed in the vicinity of Indian Point in 2006. This census consisted of a milch animal and a residence census. Results of this census are presented in Tables B-22 and B-23.

The results of the 2006 census were generally same as the 2005 census results. There were no animals producing milk for human consumption found within 5 miles (8 km) of the plant or listed in the New York Agricultural Statistic 4-9

Service. The second part of this census revealed that the two nearest residences in different sectors are located 0.44 miles (0.71 km) ESE and 0.73 miles (1.13 km) S of the plant. The 2006 land use census indicated there were no new residences that were closer in proximity to IPEC.

The Indian Point REMP does not include a garden census. ODCM allows the sampling of broad leaf vegetation in two sectors at the site boundary in lieu of performing a garden census. Analysis results are discussed in section 4.6 and presented in Table B-14, Table C-6 and Figure C-6.

4.14 Conclusion The Radiological Environmental Monitoring Program is conducted each year to determine the radiological impact of Indian Point operations on the environment. The preceding discussions of the results of the 2006 REMP reveal that operations at the station did not result in an adverse impact on the environment.

The 2006 REMP results demonstrate the relative contributions of different radionuclide sources, both natural and anthropogenic, to the environmental concentrations. The results indicate that the fallout from previous atmospheric weapons testing continues to cause sporadic detection of Cs-1 37 and Sr-90 in environmental samples. There are infrequent detections of plant related radionuclides in the environs; however, the radiological effects are very low and are significantly less than those from natural background and other anthropogenic sources.

4-10

SECTION 5 REFERENCES

5.0 REFERENCES

1. Entergy Nuclear Northeast, Nuclear Environmental Monitoring Procedures, Radiological Support Procedures, Indian Point Station.

2. U.S Nuclear Regulatory Commission. Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants, December 1975.

3. Eisenbud, M, and Gesell, T, Environmental Radioactivity - From Natural, Industrial, and Military Sources, 4th Edition, Academic Press, NY, 1997.

4. Glasstone, S., and W. H. Jordan, Nuclear Power and Its Environmental Effects, American Nuclear Society, La Grange Park, IL, 1980.

5. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I, U.S. NRC Regulatory Guide 1.109, Revision 1, 1977.

6. Cohen N., and Eisenbud M., Radiological Studies of the Hudson River, Progress Report Institute of Environmental Medicine, New York University Medical Center, December 1983.

7. U.S. Nuclear Regulatory Commission. Regulatory Guide 4.15, Revision 1, Quality Assurance for Radiological Monitoring Programs (Normal Operations)

- Effluent Streams and the Environment February 1979.

8. J. W. Poston, Cesium-1 37 and Other Man-Made Radionuclides in the Hudson River: A Review of the Available Literature, Applied Physical Technology, Inc., report to NYPA, September 1977.

9. U.S. Environmental Protection Agency Report EPC-520/1 80-012, Upgrading Environmental Radiation Data, August 1980.

10. Andrews, Howard L. and Lapp, Ralph E. Nuclear Radiation Physics, Prentice-Hall, Inc., Englewood Cliffs, New Jersey, 1972.

11. U.S. Nuclear Regulatory Commission, Branch Technical Position to Regulatory Guide 4.8, An Acceptable Radiological Environmental Monitoring Program, November 1979.

12. Eichholz, Geoffrey G., Environmental Aspects of Nuclear Power, Lewis Publishers, Inc., Chelsea, Michigan, 1985.

13. Kelly, J. J. (Ed.), Effluent and Environmental Radiation Surveillance, ASTM STP #698, Philadelphia, PA, 1978.

14. Entergy Nuclear Northeast, James A. FitzPatrick Nuclear Power Plant, Radiological and Environmental Services Department Environmental Surveillance Procedures.

15. Knoll, Glenn F., Radiation Detection and Measurement, first edition, John Wiley and Sons, New York, 1979.

16. Dixon, Wilfred J., Introduction to Statistical Analysis, third edition, McGraw-Hill Inc., 1969.

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

18. National Council on Radiation Protection. NCRP Report No. 62, Tritium in the Environment, March 1979.

19. IPEC Offsite Dose Calculation Manuals, Units 1,2 and 3

20. Kuhn, W.,et al., The Influence of Soil Parameters on Cs-137 Uptake by Plants from Long-Term Fallout on Forest Clearings and Grasslands, Health Physics Journal, 46(5), p. 1083, May 1984.

21. Garner, J.,et al., High Radiocesium Levels in Granite Outcrop Vegetation and Reductions Through Time, Health Physics Journal, 60(4), p. 533, April 1991.

22. McGee, E., et al., The Variability in Fallout Content of Soils and Plants and the Design of Optimum Field Sampling Strategies, Health Physics Journal, 68(3), March 1995.

23. Consolidated Edison Company of New York, Safety Evaluation for Amendment #45 to Unit 1 Provisional Operating License, January 1996.

24. Nuclear Regulatory Commission, Regulatory Guide 4.13, Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, November 1979.

25. Office of Environmental Management, Semi-Annual Report of the Department of Energy, Quality Assessment Program, EML 617, June 2003.

26. Office of Environmental Management, Semi-Annual Report of the Dept. of Energy, Quality Assessment Program, EML 618, December 2003.

27. McFarland, R.C., et al., The Counting Room: Special Edition, Radioactivity and Radiochemistry, Caretaker Publications, Atlanta, Georgia, 1994.

28. Bevington, P.R., Data Reduction and Error Analysis for the Physical Sciences, McGraw Hill, 1969.

29. ENN-LI-102, Corrective Action Process

30. Technical Information Document 2003-011 "Justification for the Removal of the Radiological Environ. Monitoring Blind Spike Program at IPEC"

31. UNSCEAR (2000), Sources and Effects of Ionizing Radiation. United Nations Scientific Committee on the Effects of Atomic Radiation 2000 report to the general assembly with scientific annexes. New York, United Nations.

32. Environmental Protection Agency Department of Radiation and Indoor Air, Report 84, October to December 1995.

5-2

APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS REQUIREMENTS APPENDIX A Environmental media are sampled at the locations specified in Table A-1 and shown in Figures A-i, A-2, and A-3. The samples are analyzed according to criteria established in the ODCM. These requirements include: methods of sample collection; types of sample analysis; minimum sample size required; lower limit of detection, which must be attained for each medium, sample, or analysis type, and environmental concentrations requiring special reports.

Table A-1 provides the sampling station number, location, sector, distance from Indian Point, sample designation code, and sample type. This table gives the complete listing of sample locations used in the 2006 REMP.

Three maps are provided to show the locations of REMP sampling. Figure A-1 shows the sampling locations within two miles of Indian Point. Figures A-2 and A-3 show the sampling locations within ten miles of Indian Point.

The ODCM required lower limits of detection (LLD) for Indian Point sample analyses are presented in Table A-2. These required lower limits of detection are not the same as the lower limits of detection or critical levels actually achieved by the laboratory. The laboratory's lower limits of detection and critical levels must be equal to or lower than the required levels presented in Table A-2.

Table A-3 provides the reporting level for radioactivity in various media. Sample results that exceed these levels and are due to plant operations require that a special report be submitted to the NRC.

In addition to the sampling outlined in Table A-i, there is an environmental surveillance requirement that an annual land use and milch animal census be performed. See Tables B-22 and B-23 for the milch animal and land use census.

A-1

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS Onsite 3 DR8 Service Center Building Direct Gamma 0.35 Mi (SSE) at 1580 All . Onsite - 0.28 Mi (SW) at Air Particulate Al 2340 Radioiodine A4 Air Particulate 5 A4 NYU Tower at 2080o- 0.88 Mi (SSW)

Onsite Radioiodine DR10 Direct Gamma 7 Wbl Camp Field Reservoir 3.4 Mi (NE) at 51 0 Drinking Water 8 ** New Croton Reservoir 6.3 Mi (SE) at 1240 Drinking Water 9 Wal Plant Inlet (Hudson River Intake)* Onsite - HR Water 0.16 Mi (W) at 2730HR Water Discharge Canal (Mixing Zone) Onsite - HR Water 10 0.3 Mi (WSW) at 2490 HR Bottom Sediment 14 DR7 Water Meter House Onsite - Direct Gamma 0.3 Mi (SE) at 1330

- HR Aquatic Vegetation 17 ** Off Verplanck 1.5 Mi (SSW) at 202.50 HR Shoreline Soil

- HR Bottom Sediment Cortlandt Yacht Club 20 DR38 (AKA Montrose (AKA Mnt Marna Marina) 1.5 Mi (S) at 1800 Direct Gamma

- Air Particulate 22 Lovett Power Plant 1.6 Mi (WSW) at 2440

- __Radioiodine

- Precipitation A5 Air Particulate, A5 Radioiodine 23 DR40 Roseton* 20.7 Mi (N) at 3570 Direct Gamma Ic3 Broad Leaf Vegetation

- Soil Ib2 Fish & Invertebrates 25 Ibl Downstream Downstream Fish & Invertebrates

- Air Particulate 27 ** Croton Point 6.36 Mi (SSE) at 1560 Radioiodine DR41 Direct Gamma

- HR Shoreline Soil 28 Lent's Cove 0.45 Mi (ENE) at 0690 Direct Gamma 8** HR Bottom Sediment

- HR Aquatic Vegetation

- Air Particulate 29 Grassy Point 3.37 Mi (SSW) at 1960 Radioiodine DR39 Direct Gamma

= Control location

= Locations listed do not have sample designation locations specified in the ODCM HR = Hudson River R/S = Reuter Stokes A-2

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS 33 DR33 Hamilton Street (Substation) 2.88 Mi (NE) at 0530 Direct Gamma 34 DR9 South East Corner of site OnsiteDirect Gamma 0.52 Mi (S) at 1790 35 DR5 Broadway & Bleakley Avenue Onsite - Direct Gamma 0.37 Mi (E) at 0920 Drc am 38 DR34 Furnace Dock (Substation) 3.43 Mi (SE) at 141 0 Direct Gamma

- Precipitation 44 ** Peekskill Gas Holder Bldg 1.84 Mi (NE) at 0520 Air Particulate

- Radioiodine 50 Wc2 Manitou Inlet* 4.48 Mi (NNW) at 3470 HR Shoreline Soil Wcl HR Shoreline Soil 53 White Beach 0.92 Mi (SW) at 2260 DR1 1 Direct Gamma 56 DR37 Verplanck - Broadway & Sixth Street 1.25 Mi (SSW) at 2020 Direct Gamma 57 DR1 Roa Hook 2 Mi (N) at 0050 Direct Gamma 58 DR17 Route 9D - Garrison 5.41 Mi (N) at 3580 Direct Gamma 59 DR2 Old Pemart Avenue 1.8 Mi (NNE) at 0320 Direct Gamma 60 DR18 Gallows Hill Road & Sprout Brook 5.02 Mi (NNE) at 0290 Direct Gamma Road 61 DR36 Lower South Street & Franklin Street 1.3 Mi (NE) at 0520 Direct Gamma Westbrook Drive 62_DR19_(near the Community Center) 5.03 Mi (NE) at 0620 Direct Gamma Lincoln Road - Cortlandt 64 DR20 (School Parking Lot) 4.6 Mi (ENE) at 0670 Direct Gamma 66 DR21 Croton Avenue - Cortlandt 4.87 Mi (E) at 0830 Direct Gamma 67 DR22 Colabaugh Pond Road - Cortlandt 4.5 Mi (ESE) at 1140 Direct Gamma 69 DR23 Mt. Airy & Windsor Road 4.97 Mi (SE) at 1270 Direct Gamma 71 DR25 Warren Ave - Haverstraw 4.83 Mi (S) at 1880 Direct Gamma 72 DR26 Railroad Avenue & 9W - Haverstraw 4.53 Mi (SSW) at 2030 Direct Gamma 73 DR27 Willow Grove Road & Captain 4.97 Mi (SW) at 2260 Direct Gamma Faldermeyer Drive 74 DR12 West Shore Drive - South 1.59 Mi (WSW) at 2520 Direct Gamma 75 DR28 Palisades Parkway 4.65 Mi (NW) at 3100 Direct Gamma 76 DR13 West Shore Drive - North 1.21 Mi (W) at 2760 Direct Gamma 77 DR29 Palisades Parkway 4.15 Mi (W) at 2720 Direct Gamma 78 DR14 Rt. 9W across from R/S #14 1.2 Mi (WNW) at 2950 Direct Gamma

= Control location

= Locations listed do not have sample designation locations specified in the ODCM HR = Hudson River R/S = Reuter Stokes A-3

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS 79 DR30 Anthony Wayne Park 14.57 Mi (WNW) at 2960 Direct Gamma 80 DR15 Route 9W South of Ayers Road 1.02 Mi (NW) at 3170 Direct Gamma 81 DR31 Palisades Pkwy - Lake Welch Exit 4.96 Mi (WSW) at 2550 Direct Gamma 82 DR16 Ayers Road 1.01 Mi (NNW) at 3340 Direct Gamma 83 DR32 Route 9W - Fort Montgomery 4.82 Mi (NNW) at 3390 Direct Gamma

- HR Aquatic Vegetation 84 ** Cold Spring

10.88 Mi (N) at 3560 HR Shoreline Soil

- HR Bottom Sediment 88 DR6 R/S Pole #6 0.32 Mi (ESE) at 1180 Direct Gamma 89 DR35 Highland Ave & Sprout Brook Road 2.89 Mi (NNE) at 0250 Direct Gamma 89 _DR35_ i(near rock cut) 90 DR3 Charles Point 0.88 Mi (NE) at 0470 Direct Gamma 92 DR24 Warren Road - Cortlandt 3.84 Mi (SSE) at 1490 Direct Gamma A2 Air Particulate A2 Onsite- 0.39 Mi (S) at Radioiodine 9c2 1930 Broad Leaf Vegetation

- Soil A3 Air Particulate A3 Onsite - Radioiodine Icl 0.46 Mi (SSW) at 2080 Broad Leaf Vegetation

- Soil 99 (a) Algonquin Outfall Onsite - Special Water

__________ ~~0.34 Mi (SW) at 2370SpcaWte 100 (a) Gypsum Plant Outfall Onsite - Special Water 0.34 Mi (SW) at 2370SpcaWte 101 (a) ** 5th Street Well - Verplanck 1 .3 Mi (S) at 2020 Special Water 102 (a) ** Trap Rock Quarry 0.7 Mi (SSW) at 2080 Special Water 104(b)** MW-40 Boundary Well, lower parking Onsite - 0.21 mi (SW) Special Water 104_ (b)lot 105(b) MW-i5 Boundary Well, middle Onsite - 0.18 mi (SSW) Special Water 105_(b)parking

_ lot (a) Location was eliminated from the required sample list at the end of 2006 (b) Location was sampled in 2006 and was added to the ODCM as a required boundary groundwater sample location starting in 2007.

= Control location

= Locations listed do not have sample designation locations specified in the ODCM HR = Hudson River R/S = Reuter Stokes A-4

FIGURE A-1 SAMPLING LOCATIONS Within Two Miles of Indian Point N

Peekskill Westchester County Rockland County Indian )(

1 1 mile Ibi ED~I 1 Hudson IiclrM0 River 1 1 Ic2Q Bucl Verplanck 38 Key: A - Waterborne: Surface (HR) Wa# Ic# - Broadleaf Vegetation o - Direct Radiation Sample Location DR# Ibi - Fish and Invertebrates (where available downstream) 0l - Air Particulate & Radioiodine A#

- HR Shoreline Sediment Wc#

A-5

FIGURE A-2 SAMPLING LOCATIONS Within 10 Miles of Indian Point N

Roseton (20.7 mi. N): E] @ c3 Upstream: Ib2 Orange County Putnam County

0 00 0 iO L 0 I 5 miles Rockland County Westchester County Key: O - Direct Radiation Sample Location DR# Ic3 - Broadleaf Vegetation

[] - Air Particulate & Radioiodine A# Ib2 - Fish and Invertebrates

<- HR Shoreline Sediment Wc# (where available upstream) 3 - Waterborne: Drinking Wb#

A-6

FIGURE A-3 SAMPLING LOCATIONS Additional Sampling Locations N

Orange County V Roseton (20.7 mi. N): 23 : p +

Putnam County Cold Spring (10.88 mi. N) : 84 V Bear Mountain Bridge

28:V 10: 40 99: sp 17: V 104 / 105: sp 29: U 101 :sp Westchester County Rockland County

8: dw 27: E 5 miles Key: 0 - Air Particulate & Radioiodine -- HR Shoreline Sediment V - Aquatic Vegetation * - Soil

- HR Bottom Sediment sp - Special Water p - Precipitation dw - Drinking Water A-7

TABLE A-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLE ANALYSIS (a)(b) uross p 4 U.Uol t_ _ _ _

H-3 2,000 (c)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1 (d) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 Sr-90 1(e) 5(e) 5,000(e)

(a) This list shows required LLD's, but other radionuclides are considered. Other identifiable peaks from gamma spectroscopy shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

(b) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13 (Reference 27).

(c) LLD for drinking water samples. If no drinking water pathway exists, a value of 3000 pCi/L may be used.

(d) LLD for drinking water samples. If no drinking water pathway exists, a value of 15 pCi/L may be used.

(e) The requirement to analyze for Sr-90 in fish/invertebrates and shoreline soil was committed to and accomplished in 2006. The ODCM did not list the required LLD's or reporting criteria until after the end of calendar year 2006.

The Sr-90 water LLD is only for special water samples locations 104 and 105 (see Table A-i)

The 5 pCi/kg LLD is for fish and invertebrates, and the 5000 pCi/kg LLD is for shoreline sediment.

A-8

TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES H-3 20,000 ,a, Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2 (b) 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 Sr-90 (c) 8 40 1 (a) For drinking water samples. This is the 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/L may be used.

(b) If no drinking water pathway exists, a value of 20 pCi/L may be used.

(c) The requirement to analyze for Sr-90 in selected special water samples, fish/invertebrates, and shoreline soil was committed to and accomplished in 2006. The ODCM did not list the required LLD's or reporting criteria until after the end of calendar year 2006.

A-9

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS

SUMMARY

APPENDIX B B.1 2006 Annual Radiological Environmental Monitoring Program Summary The results of the 2006 radiological environmental sampling program are presented in Tables B-2 through B-21. Table B-2 is a summary table of the sample results for 2006. The format of this summary table conforms to the reporting requirements of the ODCM, NRC Regulatory Guide 4.8 (Reference 2), and NRC Branch Technical Position to Regulatory Guide 4.8 (Reference 11). In addition, the data obtained from the analysis of samples are provided in Tables B-3 through B-21.

REMP samples were analyzed by various counting methods as appropriate. The methods are; gross beta, gamma spectroscopy analysis, liquid scintillation, radiochemical analysis, and TLD processing. Gamma spectroscopy analysis was performed for the following radionuclides; Be-7, K-40, Mn-54, Co-58, Co-60, Fe-59, Zn-65, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Cs-134, Cs-137, Ba/La-140, Ce-141, Ce-144, Ra-226 and Ac/Th-228. Radiochemical analyses were performed for 1-131 and Sr-90 for specific media and locations as required in the ODCM.

B.2 Land Use Census In accordance with Sections IP2-D3.5.2 and IP3-2.8 of the ODCM, a land use census was conducted to identify the nearest milch animal and the nearest residence. The results of the milch animal and land use censuses are presented in Tables B-22 and B-23, respectively. In lieu of identifying and sampling the nearest garden of greater than 50m2 , at least three kinds of broad leaf vegetation were sampled near the site boundary in two sectors and at a designated control location (results are presented in Table B-14).

B.3 Sampling Deviations During 2006, environmental sampling was performed for 12 media types addressed in the ODCM and direct radiation. A total of 1342 samples/measurements were obtained. Of the scheduled samples, 98.5% were collected and analyzed for the program. Sampling deviations are summarized in Table B-i; discussions of the reasons for the deviations are provided in Table B-i a for air samples, B-i b for TLDs and B-ic for other environmental media.

B.4 Analytical Deviations There were no analytical deviations for 2006.

B.5 Special Reports No special reports were required under the REMP.

B-1

TABLE B-1

SUMMARY

OF SAMPLING DEVIATIONS 2006 MEDIA PARTICULATES IN AIR 466 97.9% See Table B-lb CHARCOAL FILTER 464 97.8% See Table B-i b TLD 164 100% N/A HUDSON RIVER WATER 32 96.9% N/A DRINKING WATER 48 100% N/A SHORELINE SOIL 10 100% N/A BROAD LEAF 54 100% N/A VEGETATION FISH & INVERTEBRATES 20 100% N/A AQUATIC VEGETATION 7 100% N/A HUDSON RIVER BOTTOM 13 100% N/A SEDIMENT SOIL 3 100% N/A PRECIPITATION 8 100% N/A SPECIAL WATER 74 100% N/A SAMPLES TOTALS 1363 21 98.5%

TOTAL NUMBER OF ANALYSES REPORTED = 1342

Samples not collected or unable to be analyzed.

B-2

TABLE B-la / B-lb/B-Ic I TABLE B-la 2006 Air Sampling Deviations V - 1/2WEEK< w::ist

' PROBLEM ACTIONS JTO PREVENT[5EgURRENCE <4<

LOVETT 1/9/2006 The hour meter stopped working. Meter replaced.

The air sample at Lovett Power Station lost 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months sometime this past LOVETT 1/23/2006 week. When we changed the air sample everything was working as it should.

When we went to change out the weekly air sample at N.Y.U. location the pump was not running. After investigation we found out that the fuse was N.Y.U. 6/612006 blown. We replaced the fuse and restarted the air sample, it is back in service.

We lost 4.61 days of sample.

The air sample at IPEC training center lost 20.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months sometime this past IPEC training center 7/11/2006 week. The air sample ran for 171.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months out of 192 hours0.00222 days 0.0533 hours 3.174603e-4 weeks 7.3056e-5 months for the week. When we changed the air sample everything was working as it should.

The air sample at Lovett Power Station lost power last Monday at 1030. We lost the entire week of sample. The power was isolated by plant personnel to

_OVETT 7/17/2006 shut off two space heaters. They did not realize that the air sample was on the same circuit. The power was restored to the sampler. Coaching performed to prevent reoccurrence.

The Roseton air sample lost about 68 hours7.87037e-4 days 0.0189 hours 1.124339e-4 weeks 2.5874e-5 months of sample last week when the ROSETON 7/31/2006 GFI malfunctioned.

The Grassy Point air sample lost 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months of sample last week. The most likely GRASSY POINT 8/21/2006 scenario is that the air sampler lost power.

The Lovett air sample lost 113 hours0.00131 days 0.0314 hours 1.868386e-4 weeks 4.29965e-5 months of sample time last week, When LOVETT 10/10/2006 investigating we found that circuit breaker was tripped. The Lovett operator reset the breaker.

The air sample at Lovett Power Station lost 36.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months sometime this past LOVETT 11/6/2006 week. When we changed the air sample everything was working as it should.

The Grassy Point air sample lost 93.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of sample last week. The most GRASSY POINT 11/27/2006 likely scenario is that the air sampler lost power.

TABLE B-1 b 2006 TLD Deviations STATION NOEUNARTONR'IRIIBWLM I AlTONS T6PREVENT RECURIENCE None NONE NONE TABLE B-Ic 2006 Other Media Deviations _

STATION .i AJPLE46CEDULE PRýOILEM ACfTI=OWTO Pik ET>EQREC

ýI HudsnRierItak 4..14. 6 The Hudson River Intake sample pump failed some time during the week Hudson River Intake 4/14./2006 so we had to take a grab sample and then replace the pump.

B-3

TABLE B-2 ODCM ANNUAL

SUMMARY

- 2006 DIRECT RADIATION Palisades Parkway 4.65 Mi TLD Reads 14.0 (160/160) / 17.5 (4/4) /

(mR / standard quarter) N/A (NW) at 3100 DR28 0 164 9.3- 19.9 16.0- 18.8 B-3 19.3 (4/4)118.8 - 19.8 AIR PARTICULATES #22 Lovett Power Plant AND RADIOIODINE GB (466) 0.013 (414(416)W 16M(SW)at244 0.013(52/52) /0 3 0.001 - 0.028 0.013 (51/52) / 0.005-0.026 0.003-0.024 (pCi/m ) B-6, B-7, B-8 1-131 (419) 0.07 <Lc <Lc <Lc 0 GSA (36) 0.05 <Lc <Lc <Lc 0 Cs-1 34 GSA (36) 0.06 <Lc <Lc <Lc 0 Cs-1 37 SURFACE HUDSON 386 (1/4) #10 DISCHARGE CANAL RIVER WATER (pCi/L) H-3 (8) 3000 (c) 386 (MIXING ZONE) <Lc 0 B-9, B-10 386 (1(4) 1 386 GSA (24)

Mn-54 15 <Lc <Lc <Lc 0 Co-58 15 <Lc <Lc <Lc 0 Fe-59 30 <Lc <Lc <Lc 0 Co-60 15 <Lc <Lc <Lc 0 Zn-65 30 <Lc <Lc <Lc 0 Zr/Nb-95 15 <Lc <Lc <Lc 0 1-131 15 <Lc <Lc <Lc 0 Cs-134 15 <Lc <Lc <Lc 0 Cs-137 18 <Lc <Lc <Lc 0 Ba/La-140 15 <Lc <Lc <Lc 0 (a) Positive values above L, (b) Required apriori LLD; see Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCi/L B-4

TABLE B-2 ODCM ANNUAL

SUMMARY

- 2006 2.59 (24/24)/

ryew LroTon Keservoir DRINKING WATER 6.3 Mi (SE) at 1240 N/A 0 GB (48) 4 1.68-4.10 (pCi/L) B-11, B-12 2.74 (12112)1 2.00 - 4.10 H-3 (8) 1 2000 <Lc <Lc i N/A _ __

GSA (12)

Mn-54 15 <Lc <Lc N/A 0 Co-58 15 <Lc <Lc N/A 0 Fe-59 30 <Lc <Lc N/A 0 Co-60 15 <Lc <Lc N/A 0 Zn-65 30 <Lc <Lc N/A 0 Zr/Nb-95 15 <Lc <Lc N/A 0 1-131 15 <Lc <Lc N/A 0 Cs-134 15 <Lc <Lc N/A 0 Cs-137 18 <Lc <Lc N/A 0 15 <1 r <Lr- N/A n Ba/La-140 SHORELINE SOIL (pCi/kg - dry) B-13 Cs-134 150 <Lc <Lc <Lc 0 Cs-137 180 147 (2/8)1 Mi Off 1.5#17 Verplanck (SSW) at 202.5' 64.9(1/2)1 64.9-64.90 147 (2/2)/ 135.9 - 158.0 Sr-90 5000 <Lc <Lc <Lc 0 (a) Positive values above Lc (b) Required a priori LLD; see Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCi/L B-5

TABLE B-2 ODCM ANNUAL

SUMMARY

- 2006 VEGETATION GSA (54)

(pCi/kg - wet) B-14 1-131 60 <Lc <Lc <Lc 0 Co-60 N/A <Lc <Lc <Lc 0 Cs-1 34 60 <Lc <Lc <Lc 0

<1Lr 0 Cs-1 37 80 <Lc <Lc FISH AND INVERTEBRATES GSA (20)

(pCi/kg - wet) B-15 Mn-54 130 <Lc <Lc <Lc 0 Co-58 130 <Lc <Lc <Lc 0 Fe-59 260 <Lc <Lc <Lc 0 Co-60 130 <Lc <Lc <Lc 0 Zn-65 260 <Lc <Lc <Lc 0 Cs-134 130 <Lc <Lc <Lc 0 Cs-137 150 <Lc <Lc <Lc 0

23 Roseton35

10. i N at

25 Downstream Sr-90 (19) 518.8 (1/10) 18.8 (1/10)/ 10.9 Mi (N) at 356.9 18.8- 18.8 18.8- 18.8 18.5 (319)/ 13.9-24.5 AQUATIC VEGETATION GSA(7)

(pCi/kg - WET)

Co-60 NONE <Lc <Lc <Lc 0 1-131 100 <Lc <Lc <Lc 0 Cs-134 100 <Lc <Lc <Lc 0

84 Cold Spring

28 Lents Cove#8CodSrn 28.2 (1/4) / #2 et oe 20.7 Mi (N) at 3560 Cs-137 100 28.2-28.2 0.45 Mi (ENE) at 069 24 0 28.2-28.2 28.2 (1/2) / 28.2 - 28.2 24.6 (1/3) / 24.6 -

24.6 (a) Positive values above L, (b) Required a priori LLD; see Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCi/L B-6

TABLE B-2 ODCM ANNUAL

SUMMARY

- 2006 I Il VIVI o'-ulIIVIr-IN I GSA(1 3)

(pCi/kg - DRY)

Co-60 NONE <Lc <Lc <Lc 0 Cs-1 34 150 <Lc <Lc <Lc 0

28 Lents Cove #84 Cold Spring 282 (7/10) /

Cs-1 37 180 0.45 Mi (ENE) at 0690 20.7 Mi (N) at 3560 0 136- 449 317 (2/3) / 259 - 375 66 (1/3) 1/66 - 66 SOIL (pCi/kg - DRY) GSA(3)

Co-60 NONE <Lc <Lc <Lc 0 Cs-134 150 <Lc <Lc <Lc 0 Cs-137 180 <Lc <Lc <Lc 0 PRECIPITATION GSA(8)

(pCi/L)

H-3 3000 (c) <Lc <Lc <Lc 0 Co-60 15 <Lc <Lc <Lc 0 Cs-134 15 <Lc <Lc <Lc 0 Cs-137 18 <Lc <Lc <Lc 0 SPECIAL WATER GSA(74)

(pCi/L)

H-3 (66) 3000 (c) <Lc <Lc N/A 0 Co-60 (74) 15 <Lc <Lc N/A 0 Cs-134 (74) 15 <Lc <Lc N/A 0 Cs-137 (74) 18 <Lc <Lc N/A 0 0.78 (5118) /#105 Monitoring Well #51 Sr-90 (18) 1 0.49 1.26 Onsite N/A 0 0.84 (1/9) / 0.84- 0.84 (a) Positive values above L, (b) Required a priori LLD; see Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCi/L B-7

TABLE B-3 2006 DIRECT RADIATION, QUARTERLY DATA (mR per STANDARD QUARTER)

I1.Z +/- -+/-

DR-02 NNE 13.1 +/- 0.7 15.4 1.0 13.0 +/- 0.7 14.8 - 0.7 14.1 56 DR-03 NE 10.4 +/- 0.5 12.2 +/- 0.6 11.0 +/- 0.5 12.2 +/- 1.1 11.4 46 DR-04 ENE 12.1 +/- 0.7 13.7 +/- 0.8 12.7 +/- 0.6 13.7 + 0.8 13.0 52 DR-05 ENE 12.3 +/- 0.7 13.8 +/- 0.6 13.0 +/- 0.6 15.0 - 1.1 13.5 54 DR-06 ESE 12.2 +/- 0.8 13.9 +/- 0.7 13.1 +/-- 0.6 14.8 - 0.8 13.5 54 DR-07 SE 14.0 +/- 0.8 15.8 +/- 0.9 14.7 +/- 0.6 16.8 +/- 0.9 15.3 61 DR-08 SSE 11.7 +/- 0.7 13.1 +/- 1.0 11.8 +/- 0.6 13.7 +/- 0.7 12.6 50 DR-09 S 11.7 +/- 0.8 13.1 +/- 0.8 12.5 +/- 0.5 14.2 +/- 1.6 12.9 51 DR-10 SSW 13.0 +/- 0.8 14.7 +/- 0.6 13.7 +/- 0.7 14.9 +/- 0.9 14.1 56 DR-11 SW 9.3 +/- 0.6 11.5 + 0.6 10.5 +/-- 0.8 11.2 - 0.7 10.6 43 DR-12 WSW 16.9 +/- 0.8 16.5 +/- 0.9 16.4 +/- 0.6 17.6 +/- 1.2 16.9 67 DR-13 WSW 19.3 +/- 2.1 18.4 +/- 0.9 18.3 +/- 1.3 19.9 +/- 1.2 19.0 76 DR-14 WNW 13.0 +/- 0.9 13.4 +/- 0.9 13.1 +/- 0.7 13.2 +/- 0.6 13.2 53 DR-15 NW 12.7 +/- 1.0 13.0 + 0.9 13.2 +/- 0.5 13.2 - 0.6 13.0 52 DR-16 NNW 14.8 +/- 0.8 14.7 +/- 0.9 15.0 +/- 0.9 14.2 +/- 1.0 14.7 59 a a &

DR-1 7 N 15.2 +/- 0.7 14.9 0.7 16.2 +/- 1.5 15.0 +/- 0.7 15.3 61 DR-18 NNE 13.4 + 0.7 15.0 0.8 13.5 +/- 0.7 15.5 +/- 0.9 14.4 57 DR-19 NE 13.8 +/-- 0.6 15.4 +/- 1.1 13.8 +/- 0.6 15.7 +/- 0.7 14.7 59 DR-20 ENE 11.9 +/-- 0.8 13.3 + 0.5 12.3 +/-- 0.6 14.8 +/-- 1.1 13.1 52 DR-21 E 12.8 + 0.6 14.5 0.9 12.9 +/-- 0.6 14.8 - 0.9 13.7 55 DR-22 ESE 10.1 + 0.6 12.1 +/- 0.5 11.4 +/- 0.4 12.3 + 0.6 11.5 46 DR-23 SE 12.9 +/- 0.8 14.1 +/- 0.6 13.5 +/- 0.7 16.0 +/- 1.7 14.1 56 DR-24 SSE 13.0 +/- 0.8 15.2 +/- 0.8 14.2 +/- 0.7 14.5 +/- 0.7 14.3 57 DR-25 S 11.5 + 0.6 12.9 +/- 0.8 12.5 +/-- 0.7 11.9 - 0.6 12.2 49 DR-26 SSW 13.3 +/- 0.9 13.7 +/- 0.9 13.8 +/- 0.7 13.9 +/- 0.6 13.7 55 DR-27 SW 13.3 +/- 0.7 13.9 +/- 0.6 13.4 +/- 0.5 13.4 +/- 0.8 13.5 54 DR-28 NW 19.3 +/- 1.1 18.8 +/-- 1.1 19.1 +/- 0.6 19.8 +/- 1.3 19.3 77 DR-29 W 14.0 +/- 0.7 14.1 + 1.0 13.9 +/- 0.6 14.3 +/- 0.6 14.1 56 DR-30 SNS 14.6 +/- 0.9 14.2 +/- 1.1 14.5 +/- 0.8 14.5 +/- 0.8 14.4 58 DR-31 WSW 18.2 +/- 1.2 18.4 +/- 1.1 16.2 +

0.7 16.5 + 0.9 17.3 69 DR-32 12.5 +/- 0.7 12.9 + 0.6 12.8 +/- 0.6 13.4 +/- 0.7 12.9 52 NNW DR-33 NE 12.7 +/- 0.7 14.3 +/- 0.8 12.5 +/- 0.6 14.8 +/- 1.1 13.6 54 DR-34 SE 12.1 +/- 1.1 13.1 +/- 1.0 11.9 +/- 0.6 13.7 +/- 0.7 12.7 51 DR-35 NNE 12.7 +/- 0.8 14.3 +/- 0.8 12.4 +/- 0.8 14.1 +/- 0.8 13.4 54 DR-36 NE 13.2 +/- 0.7 15.5 +/- 0.9 14.3 +/- 1.6 15.8 +/- 0.8 14.7 59 DR-37 SSW 12.2 +/- 0.5 13.2 +/- 0.9 12.3 +/- 0.5 14.3 +/- 0.9 13.0 52 DR-38 S 11.8 +/- 0.5 13.8 +/- 0.8 12.5 +/- 0.6 14.3 +/- 0.9 13.1 52 DR-39 SSW 14.5 +/- 0.7 14.6 +/- 0.6 14.6 +/- 0.8 15.4 +/- 0.9 14.8 59 DR N 160 +/- 0 17 6 + 1.0 17.7. +/- 0.7 18.8 + 0.9 17.5 70 DR-41 SSE 12.3 +/- 1.4 13.1 +/- 0.5 12.0 +/- 0.7 13.7 +/- 0.8 12.8 51 AVERAGE 13.3 +/-1 14.3 +/-1 13.6 +/-1 14.7 +/- 14.0 56 Data not available Control Location B-8

TABLE B-4 DIRECT RADIATION, 1996 THROUGH 2006 DATA (mR per Standard Quarter)

UK-U1 1b.b Ilb.3j DR-02 16.5 2.8 12.3 23.3 14.1 DR-03 12.0 1.0 9.3 14.4 11.4 DR-04 13.4 1.4 11.1 16.3 13.0 DR-05 13.6 1.1 11.4 15.6 13.5 DR-06 13.4 1.3 10.8 16.3 13.5 DR-07 15.9 1.8 13.0 21.7 15.3 DR-08 13.0 1.2 10.1 16.3 12.6 DR-09 12.8 2.4 0.1 16.7 12.9 DR-1 0 13.7 2.1 5.3 16.8 14.1 DR-11 11.3 1.2 9.5 15.6 10.6 DR-12 16.4 1.6 12.7 19.8 16.9 DR-1 3 18.9 1.7 15.3 24.6 19.0 DR-14 13.6 1.4 11.1 17.4 13.2 DR-15 13.6 1.7 11.4 19.0 13.0 DR-1 6 14.7 1.6 11.4 18.4 14.7 4 4

4 I DR-1 7 14.7 1.5 11.5 18.0 15.3 DR-1 8 14.2 1.4 10.8 17.4 14.4 DR-19 15.0 1.5 12.2 18.2 14.7 DR-20 13.6 1.4 11.4 16.8 13.1" DR-21 13.8 1.3 11.4 18.0 13.7 DR-22 11.7 1.3 9.6 15.9 11.5 DR-23 14.0 1.3 11.4 17.1 14.1 DR-24 13.8 1.4 10.8 16.2 14.3 DR-25 12.4 1.1 9.9 14.9 12.2 DR-26 13.8 1.2 11.7 17.0 13.7 DR-27 13.7 1.3 10.2 16.8 13.5 DR-28 15.7 1.9 12.2 22.5 19.3 DR-29 17.0 2.5 9.0 21.9 14.1 DR-30 16.1 2.3 9.9 23.8 14.4 DR-31 18.2 2.4 12.3 24.6 17.3 DR-32 13.3 1.5 9.9 17.7 12.9 DR-33 11.0 2.3 7.2 15.6 13.6 DR-34 13.4 1.5 9.9 17.6 12.7 DR-35 14.4 1.6 11.1 18.0 13.4 DR-36 15.4 2.2 12.3 25.5 14.7 DR-37 13.8 1.4 11.7 18.0 13.0 DR-38 12.9 1.4 10.3 17.9 13.1 DR-39 15.6 1.5 12.7 19.4 14.8 DRAO** 1K5.6< 1.9 \2ý6 1 2G 3.T AR-41ag5 Average 4.21.8 14.2 11 10.8 19.4 12.8 14.1 Data not available con-t'r'o Location B-9

TABLE B-5 2006 DIRECT RADIATION INNER AND OUTER RINGS (mR per Standard Quarter)

DR-02 DR-I18 NNE 14.1 14.4 DR-03 DR-19 NE 11.4 14.7 DR-04 DR-20 ENE 13.0 13.1 DR-05 DR-21 E 13.5 13.7 DR-06 DR-22 ESE 13.5 11.5 DR-07 -~ DR-23 SE +

15.3 I 14.1 4 -

DR-08 DR-24 SSE 12.6 14.3 DR-09 DR-25 S 12.9 12.2 DR-10 DR-26 SSW 14.1 13.7 DR-11 DR-27 SW 10.6 13.5 DR-12 DR-28 WSW 16.9 19.3 DR-13 DR-29 W 19.0 14.1 DR-14 DR-30 WNW 13.2 14.4 DR-15 DR-31 NW 13.0 17.3 DR-16 DR-32 NNW 14.7 12.9 Average 13.9 14.3 B-1 0

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2006 (pCi/m 3 +/- 1a)

STATION #

Week EndD*taO e 4 5, 94 .. . , 95

........... 23 1 01/10/06 0.013 +-0.001 0.011 +-0.001 0.008 +-0.001 0.009 +-0.001 0.008 +-0.001 2 01/17/06 0.011 +-0.001 0.011 +-0.001 0.012 +-0.001 0.012 +-0.001 0.013 +-0.001 3 01/24/06 0.012 +-0.001 0.014 +-0.001 0.011 +-0.001 0.012 +-0.001 0.017 +-0.002 4 01/31/06 0.014 +-0.001 0.017 +-0.001 0.012 +-0.001 0.011 +-0.001 0.015 +-0.001 5 02/07/06 0.009 +-0.001 0.007 +-0.001 0.009 +-0.001 0.010 +-0.001 0.009 +-0.001 6 02/14/06 0.010 +-0.001 0.009 +-0.001 0.011 +-0.001 0.012 +-0.001 0.016 +-0.001 7 02/21/06 0.016 +-0.001 0.014 +-0.001 0.016 +-0.001 0.015 +-0.001 0.024 +-0.002 8 02/28/06 0.021 +-0.002 0.017 +-0.001 0.017 +-0.001 0.019 +-0.001 0.016 +-0.002 9 03/06/06 0.009 +-0.001 0.009 +-0.001 0.007 +-0.001 0.008 +-0.001 0.012 +-0.001 10 03/14/06 0.011 +-0.001 0.009 +-0.001 0.013 +-0.001 0.008 +-0.001 0.009 +-0.001 11 03/21/06 0.011 +-0.001 0.012 +-0.001 0.011 +-0.001 0.012 +-0.001 0.015 +-0.001 12 03/28/06 0.007 +-0.001 0.006 +-0.001 0.007 +-0.001 0.006 +-0.001 0.006 +-0.001 13 04/04/06 0.017 +-0.001 0.020 +-0.002 0.020 +-0.002 0.020 +-0.001 0.020 +-0.002 14 04/11/06 0.011 +-0.001 0.010 +-0.001 0.013 +-0.001 0.013 +-0.001 0.011 +-0.001 15 04/18/06 0.011 +-0.001 0.011 +-0.001 0.010 +-0.001 0.010 +-0.001 0.011 +-0.001 16 04/25/06 0.006 +-0.001 0.005 +-0.001 0.006 +-0.001 0.006 +-0.001 0.008 +-0.001 17 05/02/06 0.010 +-0.001 0.012 +-0.001 0.012 +-0.001 0.013 +-0.001 0.013 +-0.001 18 05/09/06 0.012 +-0.001 0.007 +-0.001 0.012 +-0.001 0.013 +-0.001 0.009 +-0.001 19 05/16/06 0.003 +-0.001 0.001 +-0.001 0.005 +-0.001 0.003 +-0.001 0.004 +-0.001 20 05/23/06 0.006 +-0.001 0.004 +-0.001 0.005 +-0.001 0.005 +-0.001 0.005 +-0.001 21 05/30/06 0.015 +-0.001 0.016 +-0.001 0.014 +-0.001 0.014 +-0.001 0.015 +-0.001 22 06/06/06 0.011 +-0.001 0.014 +-0.003 0.009 +-0.001 0.007 +-0.001 0.007 +-0.001 23 06/13/06 0.003 +-0.001 0.002 +-0.001 0.002 +-0.001 0.003 +-0.001 0.005 +-0.001 24 06/20/06 0.013 +-0.001 0.012 +-0.001 0.012 +-0.001 0.012 +-0.001 0.012 +-0.001 25 06/27/06 0.013 +-0.001 0.014 +-0.001 0.012 +-0.001 0.012 +-0.001 0.010 +-0.001 26 07/03/06 0.013 +-0.001 0.011 +-0.001 0.012 +-0.001 0.013 +-0.001 0.012 +-0.001

Sample deviation.

- Control location. B-11

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2006 (pCi/m3 +/- 1y)

STATION #

We27ek End Date, 1 4- 5 94+ 95. 1 0. 23+

27 7/11/2006 0.016 +-0.001 0.018 +-0.001 0.013 +-0.001 0.016 +-0.001 0.015 +- 0.001 28 07/18/06 0.016 +-0.001 0.014 +-0.001 0.016 +-0.001 0.012 +-0.001 0.015 +- 0.001 29 07/25/06 0.014 +-0.001 0.013 +-0.001 0.014 +-0.001 0.012 +-0.001 0.015 +- 0.001 30 08/01/06 0.016 +-0.001 0.013 +-0.001 0.016 +-0.001 0.013 +-0.001 0.009 +- 0.002 31 08/08/06 0.018 +-0.002 0.020 +-0.002 0.018 +-0.001 0.017 +-0.001 0.013 +- 0.002 32 08/15/06 0.013 +-0.001 0.013 +-0.001 0.012 +-0.001 0.016 +-0.001 0.015 +- 0.001 33 08/22/06 0.014 +-0.001 0.011 +-0.001 0.011 +-0.001 0.013 +-0.001 0.015 +- 0.001 34 08/29/06 0.014 +-0.001 0.014 +-0.001 0.012 +-0.001 0.011 +-0.001 0.014 +- 0.001 35 09/05/06 0.005 +-0.001 0.005 +-0.001 0.003 +-0.001 0.005 +-0.001 0.006 +- 0.001 36 09/12/06 0.015 +- 0.001 0.014 +-0.001 0.018 +-0.001 0.015 +-0.001 0.016 +-0.002 37 09/19/06 0.008 +-0.001 0.009 +-0.001 0.011 +-0.001 0.008 +-0.001 0.010 +- 0.001 38 09/26/06 0.014 +-0.001 0.012 +-0.001 0.013 +-0.001 0.013 +-0.001 0.015 +- 0.001 39 10/03/06 0.013 +-0.002 0.012 +-0.002 0.016 +-0.002 0.015 +-0.002 0.014 +- 0.002 40 10/10/06 0.020 +-0.002 0.019 +-0.002 0.021 +-0.002 0.019 +-0.002 0.017 +- 0.002 41 10/17/06 0.014 +-0.001 0.015 +-0.001 0.014 +-0.001 0.015 +-0.001 0.012 +- 0.001 42 10/24/06 0.012 +-0.001 0.010 +-0.001 0.010 +-0.001 0.011 +-0.001 0.015 +- 0.001 43 10/31/06 0.010 +-0.001 0.010 +-0.001 0.008 +-0.001 0.006 +-0.001 0.003 +- 0.001 44 11/07/06 0.026 +-0.002 0.024 +-0.002 0.020 +-0.001 0.023 +-0.002 0.020 +- 0.002 45 11/14/06 0.019 +-0.001 0.013 +-0.001 0.015 +-0.001 0.013 +-0.001 0.021 +- 0.002 46 11/20/06 0.015 +-0.002 0.009 +-0.002 0.014 +-0.002 0.013 +-0.002 0.010 +- 0.001 47 11/28/06 0.022 +-0.001 0.017 +-0.001 0.018 +-0.001 0.019 +-0.001 0.017 +- 0.001 48 12/05/06 0.017 +-0.001 0.019 +-0.002 0.022 +-0.002 0.019 +-0.002 0.024 +- 0.002 49 12/12/06 0.026 +-0.002 0.028 +-0.002 0.024 +-0.002 0.027 +-0.002 0.022 +- 0.002 50 12/19/06 0.022 +-0.002 0.021 +-0.002 0.024 +-0.002 0.020 +-0.002 0.024 +- 0.002 51 12/26/06 0.013 +-0.001 0.017 +-0.001 0.016 +-0.001 0.018 +-0.002 0.018 +- 0.001 52 01/02/07 0.012 +-0.001 0.013 +-0.001 0.015 +-0.001 0.010 +-0.001 0.014 +- 0.001

Sample deviation.

- Control location. B-12

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2006 (pCi/m 3 +/- 1o')

STATION #

W e'k Fad D. te.. 22, ,29:<

27 __ 44_,,,_:-

1 01/09/06 0.007 +- 0.001 0.008 +-0.001 0.009 +- 0.001 0.009 +- 0.001 2 01/17/06 0.012 +- 0.001 0.011 +-0.001 0.010 +- 0.001 0.015 +- 0.001 3 01/23/06 0.010 +- 0.001 0.009 +-0.001 0.012 +- 0.001 0.016 +- 0.002 4 01/30/06 0.013 +- 0.001 0.011 +-0.001 0.012 +- 0.001 0.012 +- 0.001 5 02/06/06 0.008 +- 0.001 0.009 +-0.001 0.007 +- 0.001 0.007 +- 0.001 6 02/13/06 0.012 +- 0.001 0.011 +-0.001 0.012 +- 0.001 0.008 +- 0.001 7 02/21/06 0.015 +- 0.001 0.019 +-0.001 0.010 +- 0.001 0.018 +- 0.001 8 02/27/06 0.022 +- 0.002 0.019 +-0.001 0.020 +- 0.001 0.020 - 0.002 9 03/06/06 0.010 +- 0.001 0.010 +-0.001 0.012 +- 0.001 0.012 +- 0.001 10 03/13/06 0.009 +- 0.001 0.012 +-0.001 0.010 +- 0.001 0.011 +- 0.001 11 03/20/06 0.011 +- 0.001 0.013 +-0.001 0.013 +- 0.001 0.011 +- 0.001 12 03/27/06 0.006 +- 0.001 0.007 +-0.001 0.005 +- 0.001 0.006 +- 0.001 13 04/03/06 0.016 +- 0.001 0.018 +-0.001 0.017 +- 0.001 0.021 +- 0.002 14 04/10/06 0.010 +- 0.001 0.010 +-0.001 0.010 +- 0.001 0.013 +- 0.001 15 04/17/06 0.011 +- 0.001 0.011 +-0.001 0.013 +- 0.001 0.011 +- 0.001 16 04/24/06 0.006 +- 0.001 0.008 +-0.001 0.006 +- 0.001 0.007 +- 0.001 17 05/01/06 0.013 +- 0.001 0.011 +-0.001 0.009 +- 0.001 0.008 +- 0.001 18 05/08/06 0.010 +- 0.001 0.008 +-0.001 0.010 +- 0.001 0.008 +- 0.001 19 05/15/06 0.006 +- 0.001 0.003 +-0.001 0.006 +- 0.001 0.004 +- 0.001 20 05/22/06 0.007 +- 0.001 0.006 +-0.001 0.008 +- 0.001 0.006 +- 0.001 21 05/30/06 0.014 +- 0.001 0.015 +-0.001 0.014 +- 0.001 0.012 +- 0.001 22 06/05/06 0.011 +- 0.001 0.009 +-0.001 0.008 +- 0.001 0.008 +- 0.001 23 06/12/06 0.005 +- 0.001 0.004 +-0.001 0.004 4- 0.001 0.005 +- 0.001 24 06/19/06 0.012 +- 0.001 0.016 +-0.001 0.013 +- 0.001 0.011 +- 0.001 25 06/26/06 0.017 +- 0.001 0.012 +-0.001 0.014 +- 0.001 0.014 +- 0.001 26 07/03/06 0.009 +- 0.001 0.011 +-0.001 No Sample 0.012 +- 0.001

Sample deviation.

- Control location. B-1 3

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2006 (pCi/rn 3 +/- lo)

STATION #

W~eek Etnd Date 22 77 2 ,29 44"A~'K 27 07/10/06 0.016 +- 0.001 0.015 +-0.001 0.016 +- 0.001 0.016 +- 0.001 28 07/17/06 No Sample 0.015 +-0.001 0.014 +- 0.001 0.016 +- 0.001 29 07/24/06 0.015 +-0.001 0.013 +-0.001 0.017 +- 0.001 0.015 +- 0.001 30 07/31/06 0.016 +-0.001 0.017 +-0.001 0.015 +- 0.001 0.015 +-0.001 31 08/07/06 0.019 +-0.002 0.018 +-0.0011 0.018 +- 0.001 0.021 +-0.002 32 08/14/06 0.014 +-0.001 0.016 +-0.001 0.013 +- 0.001 0.012 -'-0.001 33 08/21/06 0.014 +-0.002 0.012 +-0.001 0.015 +- 0.001 0.014 +-0.001 34 08/28/06 0.017 +-0.002 0.014 +-0.001 0.014 +- 0.001 0.013 +-0.001 35 09/05/06 0.006 +-0.001 0.006 +-0.001 0.005 -. 0.001 0.006 +-0.001 36 09/11/06 0.017 +-0.002 0.013 +-0.001 0.013 +- 0.001 0.015 +- 0.002 37 09/18/06 0.011 +-0.001 0.010 +-0.001 0.011 +- 0.001 0.008 +- 0.001 38 09/25/06 0.016 +-0.001 0.013 +-0.001 0.011 +- 0.001 0.013 +- 0.001 39 10/02/06 0.016 +-0.002 0.016 +-0.002 0.014 +- 0.001 0.016 +-0.002 40 10/10/06 0.026 +-0.005 0.018 +-0.002 0.016 +- 0.001 0.018 +-0.002 41 10/16/06 0.011 +-0.001 0.014 +-0.001 0.016 +- 0.001 0.015 +-0.002 42 10/23/06 0.015 +-0.001 0.015 +-0.001 0.013 +- 0.001 0.015 +-0.001 43 10/30/06 0.005 +-0.001 0.009 +-0.001 0.006 +- 0.001 0.007 +-0.001 44 11/06/06 0.021 +-0.002 0.020 +/--0.001 0.018 +- 0.001 0.021 +-0.002 45 11/13/06 0.020 +-0.002 0.014 +-0.001 0.017 +- 0.001 0.019 +-0.001 46 11/20/06 0.012 +-0.002 0.015 +-0.002 0.010 +- 0.001 0.012 +-0.002 47 11/27/06 0.020 +-0.002 0.020 +-0.001 0.015 +- 0.002 0.015 +.0.001 48 12/04/06 0.022 +-0.002 0.022 +-0.002 0.023 +- 0.001 0.023 +-0.002 49 12/11/06 0.022 +-0.002 0.028 +-0.002 0.024 +- 0.001 0.024 +-0.002 50 12/18/06 0.021 +-0.002 0.021 +-0.002 0.023 +- 0.001 0.023 +-0.002 51 12/26/06 0.015 +-0.001 0.015 +-0.001 0.015 +/-- 0.001 0.016 -- 0.001 52 01/02/07 0.016 +-0.001 0.014 +-0.001 0.016 +- 0.001 0.012 +- .001

Sample deviation.

- Control location. B-i14

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES - 2006 (RESULTS IN UNITS OF pCi/m3 (x 10-3) _ 1C) 1ST QUARTER 2006 ALGONQUIN NYU TOWER CROTON PT IPEC TRAINING MET TOWER ISOTOPE STA-4 STA-5 STA-27 STA-94 STA-95 Be-7* 64.97+/-12.4 103.3+/-12.89 102.1+/-11.61 101.4+/-11.93 88.52+/-11.1 K-40* <8.04 <5.73 <3.99 41.33+/-9.01 <3.8 Mn-54 <0.51 <0.45 <0.36 <0.77 <0.56 Co-58 <1.01 <1.09 <0.36 <1.00 <1.05 Fe-59 <3.13 <2.61 <2.58 <3.84 <2.86 Co-60 <0.80 <0.65 <0.56 <1.19 <0.72 Zn-65 <2.55 <1.3 <1.39 <1.91 <1.54 Zr-95 <1.63 <1.6 <1.69 <0.78 <0.93 Nb-95 <0.94 <1.07 <1.24 <0.91 <0.76 Ru-103 <1.16 <0.96 <0.46 <1.17 <1.13 Ru-106 <4.54 <7.66 <5.32 <4.15 <7.94 1-131 <7 <4.29 <6.27 <7.59 <5.73 Cs-134 <0.73 <0.44 <0.58 <1.1 <0.83 Cs-137 <0.63 <0.42 <0.38 <0.65 <0.43 BaLa-140 <7.11 <4.34 <4.08 <4.70 <5.76 Ce-141 <1.18 <1.35 <1 <1.14 <1.39 Ce-144 <2.19 <2.58 <1.93 <2.37 <2.84 Ra-226* <7.63 <7.83 <6.41 <8.89 <7.44 Ac/Th-228* <1.89 <2.18 <2.06 <1.78 <1.03 BOLD PRINT INDICATES REPORTED LLD VALUES

Indicates naturally occurring.

Less than" values expressed as Critical Level (Lc),

unless otherwise noted.

Reported as sample LLD. B-1 5

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES - 2006 (RESULTS IN UNITS OF pCi/m3 (x 10-3) + lo) 1ST QUARTER 2006 LOVETT ROSETON GRASSY PT PEEKSKILL ISOTOPE STA-22 STA-23 STA-29 STA-44 Be-7* 91.6+/-11.63 85.03+/-10.28 72.7+/-6.14 91.21+/-11.82 K-40* <6.28 <3.75 15.52+/-3.76 36.81+/-10.13 Mn-54 <0.56 <0.48 <0.22 <0.8 Co-58 <0.97 <0.76 <0.32 <0.92 Fe-59 <2.86 <3.19 <1.43 <2.29 Co-6O <0.62 <0.49 <0.22 <0.5 Zn-65 <1.41 <1.56 <0.83 <1.25 Zr-95 <1.28 <0.75 <0.66 <2.56 Nb-95 <0.86 <0.58 <0.49 <1.48 Ru-103 <1.29 <0.52 <0.38 <1.38 Ru-106 <7.48 <4.92 <3.07 <4.27 1-131 <4.13 <6.73 <3.58 <7.23 Cs-134 <0.47 <0.63 <0.28 <0.8 Cs-137 <0.4 <0.32 <0.09 <0.48 BaLa-140 <6.99 <3.41 <3.01 <5.00 Ce-141 <1.06 <1 <0.53 <1.41 Ce-144 <11.511 <2.19 <0.95 <11.78 Ra-226" <6.76 <6.18 <3.19 <8.82 Ac/Th-228* <1.57 <1.35 <0.8 <2.59 BOLD PRINT INDICATES REPORTED LLD VALUES

Indicates naturally occurring.

".Less than" values expressed as Critical Level (Lc),

unless otherwise noted.

Reported as sample LLD. B-1 6

TABLE B-7 CONCENTRATIONS OF GAMMA EMI'TERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES - 2006 (RESULTS IN UNITS OF pCi/m3 (x 10-3) + lo) 2ND QUARTER 2006 IPEC TRAINING MET TOWER J

ALGONQUIN NYU TOWER CROTON PT ISOTOPE STA-4 STA-5 STA-27 STA-94 STA-95 Be-7* 88.81+/-12.92 105.7+/-15.52 109+/-10.01 82.66+/-12.08 84.12+/-11.52 K-40* <6.31 <10.51 <4.34 <5.51 <4.81 Mn-54 <0.44 <0.67 <0.44 <0.36 <0.43 Co-58 <0.88 <0.69 <0,62 <0.72 <0.75 Fe-59 <3.62 <3 <2.15 <2.55 <2.25 Co-60 <0.64 <0.70 <0.33 <0.95 <0.77 Zn-65 <1.92 <1.32 <1.4 <0.97 <2.24 Zr-95 <1.9 <1.14 <0.82 <1.56 <1.08 Nb-95 <0.9 <0.94 <0,82 <1.05 <1.41 Ru-103 <1.65 <0.84 <0.79 <1.02 <1.47 Ru-106 <7.1 <6.17 <3.92 <4.72 <8.06 1-131 <8.76 <7.57 <5.29 <6.06 <7.04 Cs-134 <1.18 <1.02 <0.3 <0.88 <1.28 Cs-137 <0.81 <0.63 <0,37 <0.59 <0.65 BaLa-140 <8.68 <6.25 <4.92 <5.61 <4.42 Ce-141 <1.81 <1.44 <0,79 <1.14 <1.56 Ce-144 <3.27 <1.77 <1.44 <2.09 <3.32 Ra-226" <11.21 <8.33 <6.17 <8.95 <8.54 Ac/Th-228* <1.6 <1.55 <1.56 <1.55 <3.14 BOLD PRINT INDICATES REPORTED LLD VALUES Indicates naturally occurring.

"Less than" values expressed as Critical Level (Lc),

unless otherwise noted.

Reported as sample LLD. B-17

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES - 2006 (RESULTS IN UNITS OF pCi/m3 (x 10-3) 1 (y) 2ND QUARTER 2006 LOVETT ROSETON GRASSY PT PEEKSKILL ISOTOPE STA-22 STA-23 STA-29 STA-44 Be-7* 73.28+/-10.34 97.65+/-13.18 91.57+/-10.43 102.7+/-13 K,40* <4.27 <5.69 18.51+/-6.84 <4.44 Mn-54 <0.39 <0.45 <0.59 <0.61 Co-58 <0.65 <0.45 <0.43 <0.76 Fe-59 <2.12 <3.93 <1.87 <3.61 Co-60 <0.4 <0.84 <0.4 <0.77 Zn-65 <1.13 <0.99 <1.23 <1.21 Zr-95 <0.86 <2.1 <0.93 <2.05 Nb-95 <1.16 <1.1 <0.94 <1.11 Ru-103 <0.94 <1.11 <0.99 <1.31 Ru-106 <5.01 <5.83 <2.43 <8.62 1-131 <4.56 <4.24 <4.01 <10.82 Cs-134 <0.47 <0.55 <0.53 <1.03 Cs-137 <0.72 <0.66 <0.47 <0.66 BaLa-140 <4.64 <5.32 <4.14 <4.52 Ce-141 <0.87 <1 <0.84 <1.91 Ce-l44 <1.48 <1.67 <11.90 <3.35 Ra-226* <5.16 <8.84 <8.79 <11.32 Ac/Th-228* <1.09 <1.26 <2.33 <1.94 BOLD PRINT INDICATES REPORTED LLD VALUES

Indicates naturally occurring.

".Less than" values expressed as Critical Level (Lc),

unless otherwise noted.

Reported as sample LLD. B-1 8

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES - 2006 (RESULTS IN UNITS OF pCi/m3 (x 10-3) +/- 1C) 3RD QUARTER 2006 ALGONQUIN NYU TOWER CROTON PT IPEC TRAINING MET TOWER ISOTOPE STA-4 STA-5 STA-27 STA-94 STA-95 Be-7* 133.3+/-14.18 86+/-12.25 119.1+/-13.87 113+/-13.88 108.4+/-15.98 K-40* <4.21 <4.93 <5.28 <4.26 <8.25 Mn-54 <0.78 <0.79 <0.6 <0.59 <0.57 Co-58 <1.03 <0.79 <0.98 <1.19 <0.86 Fe-59 <4.54 <2.31 <2.47 <4.04 <3.55 Co-6O <0.48 <0.7 <1.05 <0.43 <0.88 Zn-65 <0.85 <1.42 <1.32 <2.02 <2.01 Zr-95 <1.25 <1.35 <0.87 <1.3 <2.24 Nb-95 <0.73 <1.58 <0.72 <11.64 <1.07 Ru-103 <1.15 <1.23 <0.86 <11.07 <1.32 Ru-106 <6.15 <4.19 <4.52 <6.8 <4.34 1-131 <4.61 <6.81 <5.9 <7.79 <7.44 Cs-134 <0.6 <0.72 <0.85 <1.04 <0.66 Cs-137 <0.62 <0.39 <0.5 <0.5 <0.81 BaLa-140 <4.92 <7 <7.47 <7.33 <8.44 Ce-141 <1.28 <1.09 <1.52 <2.13 <1.25 Ce-144 <2.44 <2.30 <2.22 <3.23 <1.98 Ra-226" <9.03 <5.88 <9.31 <8.3 <7.14 Ac/Th-228* <1.66 <2.21 *<2.74 <2.65 <2.1 BOLD PRINT INDICATES REPORTED LLD VALUES

Indicates naturally occurring.

".Less than" values expressed as Critical Level (Lc),

unless otherwise noted.

Reported as sample LLD. B-19

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES - 2006 (RESULTS iN UNITS OF pCi/m3 (x 10-3) 1 CT) 3RD QUARTER 2006 LOVETT ROSETON GRASSY PT PEEKSKILL ISOTOPE STA-22 STA-23 STA-29 STA-44 Be-7* 108.4+/-14.94 140.4+/-15.98 100.8+/-10.6 122.1+/-14 K-40* <7.05 <5.49 31.17+/-7.32 <4.94 Mn-54 <0.55 <0.5 <0.53 <0.45 Co-58 <0.56 <0.71 <0.54 <0.92 Fe-59 <3.06 <2.77 <2.38 <2.70 Co-60 <0.8 <0.63 <0.5 <0.57 Zn-65 <1.97 <1.03 <0.89 <1.41 Zr-95 <1.23 <1.48 <1.73 <1.66 Nb-95 <1.03 <1.23 <1.54 <2.11 Ru-103 <1.36 <1.34 <0.78 <1.01 Ru-106 <4.15 <3.51 <2.86 <5.11 1-131 <5.45 <8.26 <6.35 <8.02 Cs-134 <0.39 <0.66 <0.62 <0.84 Cs-137 <0.51 <0.33 <0.41 <0.47 BaLa-140 <5.97 <6.28 <3.79 <5.15 Ce-141 <1.1 <1.32 <1.07 <1.23 Ce-1 44 <2.64 <1.49 <1.47 <2.19 Ra-226* <7.84 <9.43 <7.67 <7.16 Ac/Th-228* <3.1 <2.42 <1.5 <1.27 BOLD PRINT INDICATES REPORTED LLD VALUES

Indicates naturally occurring.

Less than" values expressed as Critical Level (Lc),

unless otherwise noted.

Reported as sample LLD. B-20

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES - 2006 (RESULTS IN UNITS OF pCi/m3 (x 10-3) +/- l)

REPORTING UNITS IN: pCi/m3Nxl0-3) 4TH QUARTER 2006 ALGONQUIN NYU TOWER CROTON PT IPEC TRAINING MET TOWER ISOTOPE STA-4 STA-5 STA-27 STA-94 STA-95 Be-7* 87.84+/-15.74 88.35+/-12.34 83.57+/-11.09 90.58+/-11.41 98.61+/-12.11 K-40* <8.1 <5.42 <5.56 47.12+/-9.24 <5.40 Mn-54 <0.55 <0.35 <0.53 <0.48 <0.37 Co-58 <0.78 <1.19 <0.86 <0.8 <1.01

<5.9 <2.86 <3.3 <2.93 <1.38

<2.46 Fe-59 <1.4

<0.87 <0.5 <1.26

<0.88 <0.78 <0.92

<0.7 Co60 <1.33

<1.43 <1.03

<1.54 <1.78 <1.01

<1.74 Zn-65 <1.96

<1.25 <1.01 <1.13 Zr-95 <1.17 <0.92 <2.98

<1.19 <7.68 Nb-95 <0.91 <6.81 <5.47

<2.09 <5.15 Ru-103 <4.49 <0.32

<6.01 <4.55 <0.62 Ru-106 <4.7 <0.66 <0.47

<7.62 <0.45 1-131 <1.03 <0.49 <8

<0.92 <4.30 Cs-134 <0.72 <4.2 <1.34

<0.69 <1.1 Cs-137 <4.76 <1.34 <2.06

<7.74 <2.78 BaLa-140 <1.21 <9.33

<1.61 <2.24 <8.07 Ce-141 <2.45 <6.55 <2.21

<1.58 < 1.9 Ce-144 <7.43 <1.72

<10.4 < 1.95 Ra-226" iTh-228*

<2.91 Ac LLD VALUES REPORTED INDICATES BOLD PRINT

Indicates naturally occurring.

".Less than" values expressed as Critical Level (Lc),

unless otherwise noted.

Reported as sample LLD. B-21

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES - 2006 (RESULTS IN UNITS OF pCi/m3 (x 10-3) +/- l) 4TH QUARTER 2006 LOVETT ROSETON GRASSY PT PEEKSKILL ISOTOPE STA-22 STA-23 STA-29 STA-44 Be-7* 90.24+/-14.29 92.86+/-14.9 93.31+/-10.07 96.03+/-12.34 K-40* <4.92 <7.94 <3.51 <6.33 Mn-54 <0.48 <0.77 <0.23 <0.29 Co-58 <0.96 <1.33 <0.71 <0.4 Fe-59 <3.22 <3.91 <2.45 <2.21 Co-6o <0.49 <0.85 <0.33 <0.68 Zn-65 <1.63 <1.36 <0.93 <1.67 Zr-95 <1.9 <1.43 <0.66 <1.46 Nb-95 <1.56 <1.01 <0.58 <0.98 Ru-103 <1.71 <0.88 <0.49 <1.07 Ru-106 <10.06 <5.89 <4.14 <7.02 1-131 <9.32 <7.57 <4.39 <8.68 Cs-134 <1.38 <0.64 <0.5 <0.88 Cs-137 <0.81 <0.39 <0.21 <0.46 BaLa-140 <6.49 <7.68 <3.65 <4 Ce-141 <2.14 <2.04 <0.83 <0.93 Ce-144 <3.48 <2.06 <1.72 <1.83 Ra-226" <10.14 <9.72 <5.81 <4.66 Ac/Th-228* <2.48 <3.49 <2.01 <3.23 BOLD PRINT INDICATES REPORTED LLD VALUES

Indicates naturally occurring.

".Less than" values expressed as Critical Level (Lc),

unless otherwise noted.

Reported as sample LLD. B-22

TABLE B-8 1-131 ACTIVITY IN CHARCOAL CARTRIDGE SAMPLES - 2006*

(pCi/m3 +/- 10)

W 1EndDte1 4 9 I22 1 95 23- 2* [ ..

1 1/10/2006

0.008 < 0.010

0.008 < 0.009 < 0.021 < 0.008 < 0.011 < 0.012

0.010 2 1/17/2006

0.013

0.011

0.014

0.007 < 0.017 < 0.008 < 0.012

0.004

0.010 3 1/24/2006 < 0.009 < 0.008 < 0.006

0.007 < 0.015 < 0.012 < 0.011

0.010

0.012 4 1/31/2006

0.012

0.009 < 0.005 < 0.016 < 0.009 < 0.008 < 0.010 < 0.009

0.013 5 2/7/2006 < 0.014 < 0.019

0.021 < 0.020 < 0.010 < 0.008

0.007 < 0.006

0.006 6 2/14/2006 < 0.015 < 0.009 < 0.009

0.004 < 0.011

0.009 <0.007

0.004

0.010 7 2/21/2006

0.015 <0.014 < 0.013

0.006 < 0.013 < 0.009 < 0.007

0.007

0.007 8 2/28/2006

0.011 <0.009 < 0.010 < 0.012 < 0.011 < 0.006 < 0.012

0.013

0.009 9 3/6/2006 < 0.013 < 0.009 < 0.013 < 0.023 < 0.016 < 0.010 < 0.017 < 0.007

0.013 10 3/14/2006 < 0.009 <0.005 < 0.013 < 0.010 < 0.015 < 0.011 <0.006 < 0.012

0.012 11 3/21/2006 < 0.013 < 0.012 < 0.007 < 0.013 < 0.014 < 0.008 <0.010

0.012

0.006 12 3/28/2006

0.013 < 0.012 < 0.010 < 0.007 < 0.008 < 0.007 < 0.012

0.010

0.008 13 4/4/2006 < 0.014 < 0,013 < 0.009

0.014 < 0.013 < 0.009

0.012 < 0.006

0.014 14 4/11/2006 < 0.011 <0.009 < 0.010

0.007 < 0.008 < 0.006

0.007 < 0.004

0.012 15 4/18/2006 < 0.013 < 0.010 < 0.011 < 0.008 < 0.013 < 0.006 < 0.010

0.010

0.012 16 4/25/2006 < 0.008 < 0.004 < 0.010 < 0.007 < 0.009 < 0.008 < 0.008

0.004

0.010 17 5/2/2006 < 0.008 < 0.007 < 0.009 < 0.010 < 0.006 < 0.010 < 0.012 <0.008

0.009 18 5/9/2006 < 0.006 < 0.010 <0.009

0.008 < 0.013 < 0.015 < 0.005 < 0.008

0.011 19 5/16/2006 < 0.008 < 0.010 <0.011

0.009 < 0.011 < 0.006 < 0.007 < 0.010

0.011 20 5/23/2006 < 0.012 < 0.014 <0.012 < 0.007 < 0.012 < 0.009 < 0.007 < 0.006

0.009 21 5/30/2006 < 0.013 < 0.010 < 0.008 < 0.009 < 0.007 < 0.011 < 0.008 < 0.005

0.008 22 6/6/2006

0.014 < 0.016 < 0.009

0.008 < 0.017 < 0.007 < 0.009 < 0.007

0.012 23 6/13/2006 < 0.012 < 0.008 < 0.009

0.010 < 0.008 < 0.010 < 0.008 < 0.004

0.009 24 6/20/2006 < 0.007 < 0.009 < 0.005 < 0.005 < 0.008 < 0.011 < 0.009 < 0.004

0.005 25 6/27/2006 < 0.015 < 0.011 <0.006 < 0.004 < 0.014 < 0.011 < 0.011

0.006

0.012 26 7/3/2006 < 0.011 < 0.013 < 0.016

0.010 < 0.019 < 0.010 < 0.017 < 0.004 < 0.009 27 7/11/2006 < 0.009 < 0.011 < 0.012

0.008 < 0.006 < 0.007 < 0.007 < 0.008

0.013 28 7/18/2006 < 0.011 < 0.012 < 0.014 < 0.011 < 0.010 No Sampl< 0.008 < 0.008

0.011 29 7/25/2006

0.007 < 0.006 < 0.008 < 0.006 < 0.010 < 0.007 < 0.005 < 0.009 < 0.007 30 8/1/2006 < 0.008 < 0.005 < 0.005

0.014 < 0.017 < 0.019 < 0.008 < 0.007 < 0.008 31 8/8/2006 < 0.014 < 0.009 < 0.005 < 0.011 < 0.010 < 0.008 < 0.007 < 0.012

0.010 32 8/15/2006 < 0.011 < 0.016 < 0.012 <0.011 < 0.019 < 0.019 < 0.014 < 0.012

0.017 33 8/22/2006

0.005 < 0.011 < 0.009 < 0.007 < 0.015 < 0.014 < 0.015 < 0.008 < 0.008 34 8/29/2006 <0.008 < 0.009 < 0.009 < 0.015 < 0.008 < 0.011 < 0.010 < 0.006 < 0.011 35 9/5/2006 < 0.012 < 0.008 < 0.005 < 0.008 < 0.007 < 0.006 < 0.008 < 0.007 < 0.009 36 9/12/2006 < 0.008 < 0.009 < 0.013 < 0.006 < 0.011 < 0.010 < 0.010 < 0.004 < 0.011 37 9/19/2006 <0.014 < 0.016 < 0.010 < 0.010 < 0.013 < 0.008 < 0.009 < 0.009 < 0.012 38 9/26/2006 < 0.012 < 0.015 < 0.012 < 0.018 < 0.012 < 0.015 < 0.025 < 0.007 < 0.013 39 10/3/2006 < 0.012 < 0.008 < 0.006 < 0.012 < 0.006 < 0.009 < 0.010 < 0.007 < 0.004 40 10/10/2006 < 0.009 < 0.009 < 0.008 < 0.006 < 0.009 < 0.028 < 0.010 < 0.003 < 0.010 41 10/17/2006 < 0.010 < 0.007 < 0.009 < 0.012 < 0.010 < 0.015 < 0.009 < 0.007 < 0.011 42 10/24/2006 < 0.008 < 0.013 < 0.006 < 0.011 < 0.012 < 0.012 < 0.006 < 0.005 < 0.011 43 10/31/2006 < 0.011 < 0.012 < 0.006 < 0.009 < 0.012 < 0.013 < 0.007 < 0.004 < 0.009 44 11/7/2006 < 0.011 < 0.011 < 0.006 < 0.008 < 0.017 < 0.015 < 0.009 < 0.007 < 0.010 45 11/14/2006 < 0.012 < 0.010 < 0.008 < 0.004 < 0.010 < 0.010 < 0.014 < 0.008 < 0.012 46 11/20/2006 < 0.012 < 0.011 < 0.012 < 0.014 < 0.010 < 0.010 < 0.014 < 0.008 < 0.013 47 11/28/2006 < 0.006 < 0.008 < 0.009 < 0.010 < 0.016 < 0.015 < 0.013 < 0.014 < 0.010 48 12/512006 < 0.009 < 0.011 < 0.011 < 0.008 < 0.009 < 0.009 < 0.013 < 0.004 < 0.014 49 12/12/2006 < 0.009 < 0.012 < 0.014 < 0.004 < 0.011 < 0.009 < 0.015 < 0.011 < 0.023 50 12/19/2006 < 0.013 < 0.007 < 0.014 < 0.011 < 0.005 < 0.005 < 0.012 < 0.007 < 0.009 51 12/26/2006 < 0.007 < 0.011 < 0.013 < 0.013 < 0.011 < 0.006 < 0.014 < 0.006 < 0.011 52 1/2/2007 < 0.026 < 0.010 < 0.009 < 0.007 < 0.011 < 0.009 < 0.009 < 0.008 < 0.008

- . - . - . - S - S - *- S - S - S - S -

"Less than" values expressed as sample Critical Level (L,) unless otherwise noted.

Sample deviation.

- Control location. B-23

TABLE B-9 CONCENTRATIONS OF GAMMA EMMITERS IN HUDSON RIVER WATER SAMPLES** - 2006 (pCi/L +/- lo)

9 PLANT INLET (HUDSON RIVER INTAKE)

Radionuclide' Janua Februa , Mb Mach wriI* May JunIe Be-7* <17.03 <13.26 <14.94 <18.32 <10.49 <8.19 K-40* 170.2+/-21.74 95.44+/-13.69 172+/-15.9 331.8+/-27.21 84.52+/-13.06 125.4+/-6.91 Mn-54 <1.87 <1.25 <1.21 <2.14 <1.13 <0.69 Co-58 <1.93 <1.34 <1.69 <1.61 <1.26 <0.82 Fe-59 <6.14 <4.17 <4.72 <6.46 <4.89 <2.32 Co-60 <2.05 <1.31 <1.27 <2.47 <1.35 <0.7 Zn-65 <4.3 <3.08 <2.91 <4.98 <2.99 <0.98 Zr-95 <3.6 <2.39 <2.99 <3.69 <2.72 <1.56 Nb-95 <2.23 <1.74 <2.23 <2.28 <1.61 <1.12 Ru-103 <2.53 <1.78 <2.15 <2.42 <1.95 <0.77 Ru-106 <17.51 <12.07 < 14.46 <22.94 <12.45 <7.37 1-131 <7.04 <4.74 <7.12 <6.42 <5.18 <6.04 Cs-134 <1.49 <1.32 <1.63 <1.36 <1.35 <0.51 Cs-137 <1.78 <1.18 <1.37 <1.62 <1.15 <0.65 Ba/La-140 <6.58 <4.1 <4.8 <5.42 <4.39 <2.72 Ce-141 <3.31 <2.9 <3.19 <3.89 <1.72 <2.36 Ce-144 <9.26 <8.68 <9.8 <13.1 <8.9 <6.4 Ra-226* 182.3+/-27.36 181.2+/-24.34 81.02+/-26.68 120.9+/-37.51 125.8+/-20.15 101.9+/-13.22 Ac/Th-228* 14.53+/-5.36 <4.42 <4.8 <6.15 <3.52 9.34+/-1.79

10 DISCHARGE CANAL (MIXING ZONE)

Radinru*clilde January February March AprIl May June*

Be-7* <13.61 <16.36 <10.51 <14.29 <14.01 <11.95 K-40* 159.5+/-15.7 411.4+/-21.56 138.5+/-10.67 137.7+/-16.18 309.6+/-21.35 118.8+/-11.85 Mn-54 <1.31 <1.61 <1.08 <1.27 <1.52 <0.97 Co-58 <1.58 <1.59 <1.21 <1.72 <1.79 <1.17 Fe-59 <4.42 <4.86 <3.36 <4.37 <4.37 <4.12 Co-60 <1.32 <1.57 <0.9 <1.21 <1.67 <1.13 Zn-65 <3.45 <3.5 <1.34 <1.91 <3.34 <2.11 Zr-95 <2.9 <2.93 <2.05 <2.51 <3 <2.46 Nb-95 <1.87 <2.24 <1.41 <1.81 <2.06 <1.77 Ru-103 <1.79 <2.24 <1.54 <2.04 <2.21 <1.76 Ru-106 <13.78 <14.05 <10.93 <15 <16.18 <10.83 1-131 <5.44 <6.72 <5.74 <5.73 <5.89 <7.0 Cs-134 <0.79 <1.01 <0.73 <1.07 <1.02 <1.07 Cs-137 <1.25 <1.53 <1 <1.3 <1.37 <1.11 Ba/La-140 <3.98 <4.84 <3.4 <3.38 <5.01 <4.86 Ce-141 <3.06 <3.66 <2.9 <3.81 <3.22 <2.76 Ce-144 <9.66 <11.5 <9.49 <12.3 <10.5 <7.49 Ra-226* <32.63 49.22+/-28.57 86.53+/-21.17 112.6+/-28.44 93.7+/-28.84 47.16+/-20.35 Ac/Th-228* <4.61 13.88+/-4.37 13.31+/-2.98 13.52+/-4.21 9.57+/-4.26 <3.66

Indicates naturally occurring. B -24

".Less than" values expressed as Critical Level (L.).

TABLE B-9 CONCENTRATIONS OF GAMMA EMMITERS IN HUDSON RIVER WATER SAMPLES** - 2006 (pCi/L +/- 1a)

9 PLANT INLET (HUDSON RIVER INTAKE)

Radionuclilde July Au9 6"S't Sed"te m'b e r October November Declembr Be-7* <15.9 <12.9 <13 <14.68 <15.84 <12.90 K-40* 134.6+/-16.74 154.3+/-12.19 189.8+/-15.24 181.2+/-17.99 136.6+/-17.32 180 +/- 16.4 Mn-54 <1.45 <1.09 <1.13 <1.2 <1.59 <1.39 Co-58 <1.88 <1.37 <1.31 <1.61 <1.64 <1.58 Fe-59 <5.54 <3.58 <3.58 <4.69 <5.27 <4.42 Co-60 <1.42 <1.1 <1.08 <1.46 <1.67 <1.47 Zn-65 <3.3 <2.98 <2.48 <3.48 <3.64 <3.04 Zr-95 <2.72 <2.42 <2.52 <3.02 <2.89 <2.65 Nb-95 <2.07 <1.54 <2 <2.09 <2.35 <2.18 Ru-103 <2.14 <1.81 <1.91 <2.08 <2.36 <2.10 Ru-106 <13.93 <13.49 <14.33 <14.3 <15.74 <15.90 1-131 <5.76 <5.63 <6.61 <6.61 <6.94 <7.12 Cs-134 <1.64 <0.91 <1.49 <1.57 <1.62 <1.52 Cs-137 <1.45 <1.2 <1.35 <1.75 <1.62 <1.50 Ba/La-140 <5.1 <3.22 <4.7 <4.47 <5.22 <4.82 Ce-141 <3.33 <3.28 <2.97 <2.14 <2.35 <3.17 Ce-144 <10.7 <10.8 <8.58 <10.6 <11.2 <9.54 Ra-226* 59.63+/-28.26 101+/-20.57 77.36+/-20.66 53.11+/-26.67 <33.13 53.5 +/- 24.5 AciTh-228* <4.39 9.06+/-3.23 <4.11 7.7+/-4.12 <5.12 11.1 +/- 3.36

10 DISCHARGE CANAL (MIXING ZONE) 0Radionuclide. 2. J ul . >Au t Setember Oct-obder November GDecemffber Be-7* <15.62 <15.69 <14.99 <14.36 <13.13 <15.80 K-40* 126.2+/-16.7 295.8+/-22.76 347.8+/-20.57 138.4+/-14.44 148.3+/-14.33 295 +/- 17.6 Mn-54 <1.42 <1.49 <1.32 <1.55 <1.27 <1.12 Co-58 <1.65 <1.86 <1.73 <1.47 <1.36 <1.59 Fe-59 <5.53 <5.47 <4.59 <4.56 <4.19 <5.06 Co-60 <1.94 <1.65 <1.32 <1.14 <1.27 <1.20 Zn-65 <3.76 <4.52 <3.14 <1.82 <2.64 <3.45 Zr-95 <2.94 <3.36 <3.02 <2.68 <2.87 <2.73 Nb-95 <2.28 <2.28 <2.43 <1.93 <1.99 <2.02 Ru-103 <2.38 <2.37 <2.31 <2.1 <1.9 <2.23 Ru-106 <16.34 <17.14 <14.7 <14.39 <15.13 <14.00 1-131 <7.02 <7.05 <6.84 <6.62 <6.53 <7.01 Cs-134 <1.77 <1.94 <1.46 <1.13 <1.0 <1.45 Cs-137 <1.59 <1.53 <1.43 <1.28 <1.36 <1.50 Ba/La-140 <4.65 <4.84 <4.22 <3.57 <4.7 <4.45 Ce-141 <3.47 <3.54 <3.63 <4.11 <2.86 <2.57 Ce-144 <10.8 <11.4 <11.2 <12.4 <9.07 <10.6 Ra-226* 78.97+/-28.82 103.6+/-30.38 87.23+/-24.55 113.8+/-25.15 62.18+/-21.31 61.9 +/- 27.8 Ac/Th-228* <5.23 <5.34 7.4+/-3.48 16.16+/-3.59 7.61+/-3.43 9.51 +/- 3.40 Indicates naturally occurring. B-25

".Less than" values expressed as Critical Level (La).

TABLE B-10 CONCENTRATION OF TRITIUM IN HUDSON RIVER WATER SAMPLES*- 2006 (QUARTERLY COMPOSITES)

(pCiIL +/- 1a)

9 PLANT INLET (HUDSON RIVER INTAKE)

(Control Location)

Radin*u-lid, TRITIUM 2006 1ST Quarte. 2ND Quarter 3<3Quarter I 4TH Quar5er

<457 I

10 DISCHARGE CANAL (MIXING ZONE)

I RaionucM Id1 Quarter5 <Quart I 3D Qrter I 4TH Quarter I TRITIUM 2006 <453 <453 1 386 +/- 136 <457

"Less than" values expressed as Critical Level (L). B-26

TABLE B-11 RADIOACTIVITY CONCENTRATIONS IN DRINKING WATER SAMPLES - 2006 (pCi/L +/- 1a)

Camp Field Reservoir ISOTOPE January February March April May June Gross Beta 1.71 +/- 0.50 1.68 i 0.45 2.78 +/- 0.49 2.4 +/- 0.5 2.9 +/- 0.5 2.4 +/- 0.5 Be-7* <33.55 <22.46 <22.07 <20.82 <20.93 <24.49 K-40*- 166+/-51.42 166.2+/-28.4 162.1+/-34 120.5+/-27.54 175.3+/-30.6 330.7+/-42.76 Mn,54 <5.58 <2.28 <2.63 <2.53 <2.64 <2.46 Co-58 <4.62 <2.37 <2.87 <2.26 <2.48 <2.71 Fe-59 <9.7 <6.46 <9.14 <5.17 <6.76 < 10.46 Co-60 <2.83 <2.09 <2.81 <3.35 <2.51 <3.41 Zn-65 <7.81 <6.02 <5.76 <2.62 <6.74 <7.14 Zr-95 <6.14 <4.16 <3.45 <3.91 <4.22 <5.1 Nb-95 <4.94 <3.07 <2.4 <2.7 <2.97 <3.68 Ru-103 <3.74 <2.86 <3.28 <2.94 <2.73 <3.33 Ru-106 <41.74 <30.42 <26.55 <28.24 <25.35 <22.67 1-131 <0.233 <0.509 <0.302 <0.306 <0.306 <0.287 Cs-134 <4.76 <3.11 <2.89 <2.76 <2.87 <3.53 Cs-137 <3.1 <2.01 <2.76 <2.59 <2.49 <2.71 Ba/La-140 <4.73 <3.31 <3.55 <2.67 <2.76 <3.6 Ce-141 <5.43 <4.61 <4.9 <3.7 <4.13 <4.6 Ce-14 <26.5 <19.5 <19.9 <16.1 <17.4 <19.9 Ra-226* <83.16 131.3+/-50.11 <65.89 121.3+/-48.55 <61.11 <61.89 Ac-228 < 13.22 <7.6 <9.48 <9.03 <10.34 < 13,17 Results reported as < are CL values Camp Field Reservoir ISOTOPE July August September October November December Gross Beta 2.3 +/- 0.5 3.4 +/- 0.5 2.8 +/- 0.5 1.9 +/- 0.5 3.2 +/- 0.5 1.8 +/- 0.5 Be-7* <21.26 <20.21 <27.38 <22.41 <23.65 <26.11 K-40* 240.4+/-39.47 <35.25 <32.7 189+/-32.67 208.4+/-35.35 163+/-36.44 Mn-54 <3.25 <2.54 <3.14 <2.8 <2.72 <3.49 Co-58 <3.4 <3.11 <3.15 <2.15 <2.65 <3.13 Fe-59 <10.58 <6.47 <9.58 <5.16 <6.2 <6.47 Co-60 <3.61 <2.48 <3.8 <2.28 <1.42 <3.2 Zn-65 <5.75 <3.93 <6.54 <5.03 <6.05 <4.02 Zr.95 <5.05 <4.58 <5.31 <4.18 <5.5 <5.21 Nb-95 <3.64 <3.91 <3.8 <2.57 <3.05 <3.33 Ru-103 <3.59 <2.96 <3.85 <2.95 <3.15 <3.48 Ru-106 <34.09 <36.61 <35.48 <23.07 <25.71 <28.66 1-131 <0.314 <0.312 <0.395 <0.377 <0.382 <0.389 Cs-134 <2.82 <2.39 <2.67 <2.66 <1.78 <2.35 Cs-137 <3.55 <3.01 <3.16 <2.37 <2.84 <3.1 Ba/La-140 <5.86 <3.54 <5.92 <3.26 <2.51 <4.17 Ce,141 <5.55 <4.84 <4.91 <4.29 <4.27 <6.88 Ce,144 <19.5 <18.3 <20.6 <18.0 <18.2 <26.9 Ra-226* 186.5+/-60.74 177.8+/-46.95 <73.51 <54.61 <67.83 <85.84 Ac-228" <11.24 <12.52 <9.57 <8.62 <10.13 <9.43

Indicates naturally occurring. B-27 5/14/2007

TABLE B-11 RADIOACTIVITY CONCENTRATIONS IN DRINKING WATER SAMPLES - 2006 (pCiIL +/- la)

New Croton Reservoir ISOTOPE January February March April May June Gross Beta 2.98 +/- 0.53 2.15 +/- 0.47 2.39 +/- 0.46 2.7 +/- 0.5 3.0 +/- 0.5 2.1 +/- 0.5 Be-7* <23.85 <19.28 <26.39 <25.46 <25.28 <15.78 K-40* 194.6+/-38.28 137+/-28.9 205.1+/-41.99 <39.48 162.7+/-34.53 <17.94 Mn-54 <2.8 <3 <3.91 <3.88 <2.6 <2.67 Co-58 <2.36 <2.31 <3.46 <3.55 <2.28 <2.08 Fe-59 <5 <5.11 <9.47 <4.97 <5.81 <3.13 Co-60 <3.05 <2.83 <3.75 <4.53 <1.93 <2.69 Zn-65 <6.76 <7.6 <7.96 <11.43 <7.46 <5.03 Zr-95 <4.77 <4.19 <5.72 <4.95 <6.35 <4.87 Nb-95 <3.75 <2.45 <3.07 <3.89 <3.61 <2.03 Ru-103 <2.77 <2.71 <3.32 <3.37 <3.38 <3.28 Ru-106 <32.57 <25.94 <33.43 <34.71 <24.88 <27.17 1-131 <0.205 <0.491 <0.232 <0.241 <0.325 <0.276 Cs-134 <3.06 <1.41 <3.52 <2.77 <2.48 <2.76 Cs-137 <2.96 <2.54 <3.48 <3.38 <2.29 <1.53 Ba/La-140 <4.09 <3.61 <3.29 <5.17 <3.89 <4.72 Ce-141 <4.75 <3.98 <4.29 <6.21 <4.17 <4.32 Ce-144 <19.7 <17.1 <17.6 <23.6 <17.4 <15 Ra-226" <82.04 128.1+/-46.81 187.1+/-48.24 <74.38 138.6+/-45.51 <54.98 Ac-228* <11.22 <9.94 <10.94 <10.58 <8.51 <7.65 New Croton Reservoir ISOTOPE July August September October November December Gross Beta 3.0 +/- 0.5 2.5 +/- 0.5 2.0 +/- 0.5 3.7 +/- 0.6 2.2 +/- 0.5 4.1 +/- 0.5 Be-7* <20.82 <30.02 <31.2 <23.95 <20.12 <25.26 K-40* 131.1+/-28.22 <36.75 138.7+/-32.04 <28.11 280.3+/-31.52 265.9+/-49.51 Mn-54 <2.2 <3.27 <3.2 <2.93 <2.36 <3.65 Co-58 <1.96 <2.8 <2.58 <1.94 <2.36 <3.65 Fe-59 <9.6 <5.63 <10.54 <7.53 <6.81 <7.46 Co-60 <3.97 <3.94 <3.9 <3.02 <2.21 <5.55 Zn-65 <4.94 <8.09 <7.88 <5.62 <5.51 <10.07 Zr-95 <5.03 <4.51 <5.76 <4.31 <4.48 <5.09 Nb-95 <3.82 <3.07 <3.31 <2.18 <2.61 <3.4 Ru-103 <2.98 <4.04 <3.92 <3.06 <2.51 <3.88 Ru-106 <27.42 <37.96 <29.49 <26.6 <24.84 <29.96 1-131 <0.302 <0.303 <0.35 <0.377 <0.342 <0.377 Cs-134 <2.33 <2.47 <3.8 <3.69 <2.58 <3.81 Cs-137 <2.23 <4.25 <3.62 <2.99 <2.62 <3.5 BaILa-140 <2.97 <3.01 <2.61 <3.74 <2.73 <5.08 Ce-141 <4.21 <4.88 <5.06 <4.21 <4.35 <4.74 Ce-144 <21.3 <24.7 <24.3 <17.4 <17.4 <25.7 Ra-226" <68.87 <76.54 <68.7 <62.35 <65.36 154.2+/-79.36 Ac-228" <9.14 <8.61 <11.79 <9.14 <9.37 <11.55

Indicates naturally occurring. B-28 5/14/2007

TABLE B-12 CONCENTRATION OF TRITIUM IN DRINKING WATER SAMPLES*- 2006 (QUARTERLY COMPOSITES)

(pCi/L +/- 1a)

'<,RAdIonucItIe> i V-940,e~ 2NDC QuirW jRDQuiArter 4TH quart I TRITIUM < 466 <499 < 451 <456 CRi1OTON REýSERVOIfR q'>'EWV

~Raiowkpi~de '1STQuarter, 2NDP Quarter 3RD

- Q4arter 4T ure TRITIUM I < 466 I < 499 I < 451 <456

"Less than" values expressed as Critical Level (Lc). B-29

TABLE B-13 SHORELINE SOIL SAMPLES** 2006 (pCi/Kg dry +/- lo)

April 2006 OFF LENTS MANITOU WHITE COLD ISOTOPE VERPLANK COVE INLET BEACH SPRING Be-7* <128.20 <209.30 <211.90 <89.22 <162.50 K-40* 15820 +/- 529.4 17140 +/- 632.3 14440 1 585.3 8410 +/- 361.1 36580 +/- 985.6 Mn-54 <15.06 <24.09 <25.61 <10.34 <25.09 Co-58 < 18.12 <27.83 <27.97 <10.80 <22.79 Fe-59 <58.11 <76.34 <72.46 <42.61 <85.47 Co-60 <16.85 <30.87 <23.48 < 13.70 <33.89 Zn-65 <25.23 <32.98 <38.42 <40.78 <83.67 Zr-95 <30.63 <46.52 <49.28 <20.88 <39.80 Nb-95 <18.68 <21.45 <20.33 <14.85 <25.29 Ru-103 < 15.99 <27.23 <28.83 <11.55 < 19.52 Ru-106 <181.20 <282.10 <278.20 <106.50 <295.80 1-131 <21.26 <35.71 <35.74 <14.50 <31.65 Cs-134 <17.43 <32.05 <29.11 <13.75 <26.12 Cs-137 135.9 +/- 18.05 <25.95 <28.14 <12.53 <23.74 BaLa-140 <28.60 <36.49 <46.94 <16.39 <24.93 Ce-141 <26.08 <41.92 <39.57 <18.77 <33.86 Ce-144 <107.00 <168.00 <158.00 <59.00 <121.00 Ra-226" 912.2 1 304.9 3584 +/- 465.9 3456 +/- 471.5 898.8 +186.9 823.6 +/- 341.8 Ac/Th-228* 553.3 +/- 63.46 1534 +/- 118.9 1359 +/- 107.4 111.1 +/- 42.99 471.6 +/- 92.48 August 2006 OFF LENTS MANITOU WHITE COLD ISOTOPE VERPLANK COVE INLET BEACH SPRING Be-7* <372.1 <734.4 <252.6 < 124.2 <275 K-40* 25200+/-1203 20700+/-1522 19670+/-802.3 14490+/-560.7 46540+/-1046 Mn-54 <34.48 <61.09 <38.83 <14.66 <36.88 Co-58 <39.52 <85.76 <36.74 <16.84 <34.22 Fe-59 <128.2 <176.8 <96.59 <64.34 < 107.1 Co-60 <52.81 <64.82 <34.59 <21.09 <39.62 Zn-65 < 107.8 <120.3 <53.08 <31.39 <55.58 Zr-95 <78.17 <172.2 <51.57 <28.63 <60.32 Nb-95 <52.85 <108.1 <23.95 <22.82 <41.76 Ru-103 <38.78 <74.45 <31 <16.11 <40.31 Ru-106 <435.5 <699.1 <331.3 <141.1 <376.4 1-131 <68.66 < 148.5 <51.5 <27.23 <53.16 Cs-134 <44.88 <53.96 <26.05 <19.17 <25.94 Cs-137 158 +/- 23.6 <75.86 64.9 +/- 19.5 <14.11 <35.46 BaLa-140 <71.37 <68.76 <50.78 <28.74 <45.02 Ce-141 <59.17 <171.5 <48.1 <24.1 <64.89 Ce-144 <240.00 <668.00 <200.00 <99.70 <273.00 Ra-226* 2136+/-604.2 6453+/-1779 3544+/-615.2 1335+/-255.7 2429+/-576.6 Acrrh-228* 905.8+/-139.6 1433+/-296.6 1180+/-136.7 117+/-52 974.2+/-118.2 Sr-89 <3.60 <3.20 <5.00 <1.20 <2.50 Sr-90 <0.16 <0.15 <0.24 <0.24 <0.23 BOLD PRINT INDICATES REPORTED LLD VALUES Indicates naturally occurring.

"Less than" values expressed as Critical Level (Lc).

Indicates the average of the positive sample results reported for samples with recounts performed. B-30

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2006 (pCi/Kg, wet +/- ia) may June

................T......................... * ................. .... T ....................... .. ...........

COMMON x gRadioiiucidl, Be-'7*

NCABBAGE>

295.9+/-57.43 MULLEN I> MOiHERWORT *~*.*+/-~

Radlouuchd-Be K-4*

~

686.9+/-120.4 7115+/-473.9 ý .11,11, 365.7+/-120.3 4582+/-402

ý i111.11,11, 1081+/-92.42 5985+/-281.1 K-40* 3021+/-214.4 Mn-54 <6.16 <8.58 <7.63 Mn-54 <19.82 <17.81 <9.51 Co-58 <7.16 <6.63 Co-58 <18.15 <17.86 <11.24 Fe-59 <3 <27.02 <18.44 Fe-S9 <45.74 <47.44 <33.84 Co-60 <6.09 <11.42 <9.43 Co-60 <19.65 <22.95 <13.72 Zn-65 <22.94 <27.71 <17.29 Zn-65 <36.25 <31.84 <14.39 Zr-95 <17.94 <11.24 Zr-95 <20.55 <30.96 <22.09 Nb-95 <11.19 <7.5 Nb-95 <20.06 <17.81 <11.45 Ru-103 1 <7.69 <8.31 <6.53 Ru-1O3 <13.85 <16.56 <9.26

<108.2 <72.18 Ru-106 <146.4 <195.2 <117.4

<11.33 <7.21 1-131 <17.59 <20.09 <11.34 Cs-134 1 <8.94 <6.7 <4.53 Cs-134 <19.39 <20.35 <7.96 Cs-137 <9.4 <8.7 <6.18 Cs-137 <13.82 <21.52 <9.53 BalLa-140 <9.61 <6.56 Ba/La-140 <13.29 <25.27 <9.96 Ce-141 <12.14 <10.05 Ce-141 <19.4 <23.34 <12.18 Ce-144 <49.80 <48.70 <43.30 Ce-144 <77.10 <81.30 <52.00 Ra-226" 448.6+/-182.8 365.2+/-221.6 <196.2 AcJTh-228* <60.26 <69.3 <34.72 July Aug PAC4WErL-D MillIFNcSIc4 BURDOCK 4 tRadlonucllde CATASA cRAG WEED BU;RDOCK Be-7' 621.4+/-101.2 705.1+/-163.1 2329+/-119.9 K-40* 3120+/-294.9 8606+/-619.7 7714+/-292.6 Mn-54 1 <12.08 <15.92 <11.6 Mn-54 <11.77 <25.09 <10.48 Co-58 <16.88 <8.49 Co-58 <14.37 <25.99 <10.16 Fe-59 <47.09 <27.36 Fe-59 <33.3 <57.13 <30.76 Co-60 I <15.98 <12.59 <12.48 Co-60 <15.47 <24.14 <11.09

<2 <42.77 <29.27 Zn-65 <36.29 <61.08 <33.64

<24.1 <21.38 Zr-95 <17.84 <27.35 <16.56 Nb-95 <15.18 <13.55 Nb-95 <12.96 <21.12 <8.93 Ru-103 <12.63 <15.68 <13.65 Ru-1B3 <13.18 <16.87 <9.84 Ru-106 <172.8 <148.1 <103.8 Ru-106 <137 <227.1 <96.4 1-131 <15.62 <17.61 <12.83 1-131 <14.44 <20.2 <10.77 Cs-134 <21.86 <17.69 <12.55 Cs-134 <18.82 <19.26 <7.61 Cs-137 <13.64 <15.79 <9.66 Cs-137 <12.14 <23.07 <9.81 aelLa-140 <17.45 <9.73 <10.88 BaeLa-140 <14.6 <23.93 <7.62 Ce-141 <18.83 <24.73 <16.96 Ce-141 <13.82 <25.89 <15.65 Ce-144 <74.70 <94.70 <62.30 Ce-144 <65.40 <110.00 <73.60 Ra-226" <308.5 386.6+/-156.4 Ra-226" 725.2+/-199 511.6+/-298.2 <194.1 AclTh-228* <56.41 <43.88 AclTh-228* <63.94 <74.64 <36.53

Indicates naturally occurring.

Indicates control location.

"Less than" values expressed as Critical Level (L). B-31

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2006 (pCi/Kg, wet l1a)

S23 October September October

~R~danucta , rA-GWEED ý CATA1LBA LAVtO IRadLon"cllde Be-7*

RAG.WEEDzI 4049+/-266.3 QiATALBA 1894+/-167.1 MULLLN 1211+/-107.1 Be-7* 1746+/-139.1 1 705.8+/-129.5 701.6+/-92.5 K-40O 7337+/-557 3064+/-292.6 5748+/-264.5 Mn-54 <15.75 <10.3 '12 Co-58 1 '13.48 <13.78 Co-58 <14.42 <9.68 <10.06

<46.36 Fe-59 <72.71 <46.79 <32.64

<19.34 <9.94 Co-60 <23.43 '14.46 <11.84 Zn-65 1 <30.94 <29.28 <16.56 Zn-65 <47.59 <24.34 <29.95

<28.83 <22.1 Zr-95 <26.45 <26.51 '17.87

<18.43 <12.43 Nb-95 <20.75 '13.38 <10.27

<12.35 '12.85 <9.06 Ru-103 <20.33 <12.33 <11.22 Ru-106 <123.1 '161 <102.7 Ru-106 <226.8 <127.4 <119.5 1-131 <26.01 <26.09 <21.79 1-131 <22 <15.01 <12.78 Cs-134 <17.45 <15.05 <8.02 Cs-134 1 <26.08 <17.31 <17.46 Cs-137 <14.68 <17.17 <10.47 Ba/La-I 40 <; <27.74 Ce-141 <21.11 <19t11 <17.47 Ce-144 <69.60 <75.10 Ce-144 <100.00 <73.80 Ra-226* <360.6 <____ <224.8 AC/Th-228* <66.18 1 <40.36 <41.71 Indicates naturally occurring.

Indicates control location.

"Less than" values expressed as Critical Level (L,). B-32

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2006 (pCiIKg, wet +/- la) a #IeEeCTRa e x>

J#4 COMMENt .,

Radlionuolide, MULtEN RAGWEED ~MOTFIERWORT _R1j0U1d BQi' C MýWj4LL4 .' RAGWEED Be-7* 1183+/-157.8 180+/-57.3 <65.19 Be-7* 1180+/-86.52 1381+/-136.3 738.2+/-93.05 K-40* 5363+/-470.2 6236+/-310.1 5052+/-240 K-40* 7516+/-268.4 4873+/-347.3 7813+/-348.3 Mn-54 <16.69 <10.07 <11.02 Mn-54 <10.5 <12.46 <10.95 Co-58 <20.36 <8.57 <8.27 Co-58 <10.99 <15.03 <12.48 Fe-59 <53.13 <25.53 <25.84 Fe-59 <27.61 <42.74 <30.79 Co-60 <21.27 <9.57 <9.5 Co-60 <9.97 <15.29 <14.69 Zn-65 <47.43 <25.99 <21.16 Zn-65 <13.54 <35.1 <24.03 Zr-95 <38.69 <17.77 < 12.81 Zr-95 <16.52 <21.35 <20.64 Nb-95 <20.14 <10.13 <7.71 Nb-9S <9.17 <14.67 <11.73 Ru-1E3 <16.22 <7.69 <6.89 Ru-1E3 <9.09 <13.66 <10.35 Ru-106 <166.7 <81.34 <82.67 Ru-16 <96.88 <146.5 <127.5 1-131 <23 <6.47 <9.52 1-131 <10.69 <15.03 <11.73 Cs-134 <23.93 <8.62 <6.11 Cs-134 <6.98 < 16.42 <8.02 Cs-137 <17.6 <7.7 <8.13 Cs-137 <9.64 <14.26 <11.11 Ba/La-140 <19.19 <9.25 <10.19 Ba/La-140 <12.43 <15.71 <12.27 Ce-141 <25.23 <11.29 <12.44 Ce-141 <14.66 <17.39 <12.96 Ce-144 <80.80 <45.80 <51.90 Ce-144 <59.60 <80.20 <52.00 Ra-226 561,4+/-261.1 <155.7 <172.9 Ra-226" <203.8 <284.5 <221.9 Ac h-228* <68.77 <35.94 <30.82 AcITh-228* <34.67 <52.26 <44.97 July Aug Redlonucflidf RAGWEED MSMULLEN fr BURDOCK Ralnuld R WE uRDOCK GRAPE LEAVESi Be-7* 881.2+/-99.99 1511t209.9 1233+/-142.8 Be-7* 2137+/-180 1261+/-129.9 457.9+/-121.2 K-40* 8159+/-372.7 6582+/-552.6 6866+/-437.9 K-40" 10080+/-568.6 7051+/-369.5 2935+/-314.3 Mn-54 <11.35 <27.64 <7.86 Mn-54 <20.63 <15.28 <13.04 Co-58 <11.33 <29.56 <13.1 Co-58 <17.98 <17.09 <14.72 Fe-59 <42.27 <60.49 <41.7 Fe-59 <61.86 <46.24 <45.23 Co-6E <11.02 <36.13 <15.63 Co-6E <24.08 <17.98 <18.59 Zn-65 <33.26 <56.7 <44.21 Zn-65 <52.09 <47.3 <31.81 Zr-95 <25.42 <31.27 <24.89 Zr-95 <31.55 <23.86 <29.57 Nb-95 <11.36 <25.23 <15.55 Nb-95 <18.33 <14.36 <17.34 Ru-103 <12.01 <20.81 <12.69 Ru-193 <16.61 <13.7 <13.23 Ru-106 <112 <205.8 <152.6 Ru-106 <142 <181.7 <133.5 1-131 <11.13 <20.72 <11.95 1-131 <15.19 <15.35 <13.7 Cs-134 <14.2 <25.42 <17.74 C9-134 <25.16 <15.28 <10.48 Cs-137 <11.12 <23.58 <15.81 Cs-137 <20.43 <16.18 <14.13 BaLa-140 <16.54 <25.37 <17.23 Ba/La-140 <19.76 <18.14 <22.11 Ce-141 <15.68 <27.71 <16.11 Ce-141 <23.1 <23.85 <15.05 Ce-144 <74.70 <90.10 <67.60 Ce-l4 <84.50 <105.00 <74.80 Ra-226" <224.5 <394.9 <234.4 Ra-226" <350.7 411.3+/-242.4 556.5+/-207.3 Ac/Th-228* <51.72 <99.02 <54.68 Ac/TS-22B* <75.64 <51.55 <73.37

§4 i iter(continu #.)

OctobCeran September October RadlonuoIIcetIARAGWaEEDIýG.RAPE LEAVES1 MIL WLE ,tfla 4! elIde, -IRAswEEn~ I G APF LEAVE,, JEWEL' WEED RacýonýQlid. ý RAGWEX-D Be-7' 1335+/-103.4 K-40* 4932+/-267.3 Mn-54 1 <15.08 <15.13 <8.92

<8.44

<25.32 Co-6E 1 <17.94 <18.08 <13.01 Co-60 <14.14 <17.53 <9 Zn-65 <38.88 <30.79 Zr-95 <22.21 <16.48 Nb-95 <10,77 <14.65 <9.4 Ru-103 < 11. 21 <6.66 Ru-1E3 1 <17.61 <13.37 <14.45 Ru-196 <134.1 <88.76 1-131 < 13.84 <8 Cs-134 <12.3 <19.83 <17.59 Cs-134 <7.67 <15.92 <11.43

<20.26 Ce-141 <15.62 1 <20.07 <10.97

Indicates naturally occurring.

Indicates control location.

"Less than" values expressed as Critical Level (L.). B-33

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2006 (pCi/Kg, wet 1 ao)

May June

~MOTHER- ,

~Rýdlonu~de WORT B.KURDOCK RAW D Radlo.uAide POKE WAEED RA.WLEED MAULLEN Be-7* 139.2+/-69.03 557.8+/-67.3 423.6+/-80.95 Be-7* <78.04 1218+/-116.8 924.5+/-162.1 K-40* 4338+/-236.4 4597+/-250.7 6084+/-341.7 K-40* 6183+/-317.3 8653+/-376.4 5771+/-464.5 Mn-54 <12.29 <6.76 <9.99 Mn-54 <9.81 <14.56 <17.19 Co-58 '8.83 <8.26 <10.81 Co-58 '9.79 <1 5.32 <18.65 Fe-59 <32.19 <26.8 <27.1 Fe-59 <32.27 <44.57 <50.56 Co-60 <12.21 <8.49 <14.02 Co-60 '13.84 <13.98 <28.04 Zn-65 <28.72 <24.96 <28.82 Zn-65 <22.12 <20.98 <48.75 Zr-95 <15.74 <10.88 <16.12 Zr-95 '14.36 <21.47 <29.41 Nb-95 <9.6 <8.77 <7.5 Nb-95 <10.57 <14.55 <18.76 Ru-103 <9.86 <7.32 <8.28 Ru-103 <9.13 <11.43 <17.43 Ru-166 '103 <68.49 <104.2 Ru-106 <112.5 <150.1 <199.4 1-131 <10.75 <8.43 <11.04 1-131 '10.43 <15.57 '16.64 Cs-134 <8.59 <8.07 <10.08 Cs-134 '10.62 <10.6 <26.43 Cs-137 <9.98 <8.96 <9.32 Cs-137 <12.42 <12.63 <18.55 BaILa-140 '10.77 <9.51 <11.28 Ba/La-140 <8.72 <13.59 <19.48 Ce-141 <16.96 <9.42 '12.87 Ce-141 '14.06 1 <20.6 i <23.74 Ce-144 '64.70 <41.60 <47.30 Ra-226" < 186.9 <153.7 < 172.8 AcITh-228* <34.92 <25.09 <33.1 July Aug SRadlondhcde RAGWEED BURDOCK MULLEN :

Be-7* 925.5+/-136.9 744.8+/-88.23 976.2+/-121.9 K-40* 7941+/-509.5 7422+/-348.8 6505+/-406.5 K-40* 8845+/-499.5 6533t411.9 8710+/-489.4 Mn-54 <11.42 <9.44 <11.52 Mn-54 <17.43 <15.82 <19.6 Co-58 <16.86 <9.73 <14.52 Co-58 '14.44 <15.67 <17.51 Fe-59 <43.51 <25.96 <28.98 Fe-59 <47.25 <37.1 <62.36 Co-60 <13.19 <10.89 '15.26 Co-60 <20.62 <19.32 <21.4 Zn-65 <44.7 <24.99 <34.25 Zn-65 <44.02 '50.6 <52.84 Zr-95 <22.27 <15.88 <12.65 Zr-95 <30.02 '30.73 <35.3 Nb-95 <13.47 <11.09 <14.42 Nb-95 <17.52 <17.35 <19.95 Ru-103 <14.21 <10.27 <11.44 Ru-163 <16.13 <16.22 <18.85 Ru-106 <124.1 <111.2 <150.4 Ru-106 <156,9 <179.1 <203.2 1-131 <11.62 <7.84 <15.11 1-131 <16.76 <16.22 <18.27 Cs-134 <18.66 <11.43 <22.54 Cs-134 <20.88 <23.62 <25.75 Cs-137 <13.28 <10.73 <18.43 Cs-137 <15.9 <18.15 <18 BaLa-140 '21.77 <13.25 <17.61 Ba/La-140 <20.85 <20.59 <28.19 Ce-141 <18.06 <11.24 <16.85 Ce-141 <18.06 <21.88 <22.54 Ce-144 '68.40 '51.20 <66.90 Ce-144 <70.70 <75.10 <93.20 Ra-226 '284.2 251.4+/-130 <276.2 Ra-226B 356.6+/-:214.5 <365.7 510 .4+/-295 Ac/Th-228* <59.68 <33.28 <55 Acfrh-228* <69.37 <72.75 '106.7 Sept October Radionuecide Be-7*

LEAVES 505.6+/-129.2 RAGWEED 2113+/-147.4

+COTTONYWOOD 2116+/-175.7 Radwno~iulide I.RAGWEED BITTERSVEET~ I MULLEN~

Be-7*

K-40* 3569+/-317.1 7448+/-372.2 8903+/-477.3 K-40' Mn-54 <14.96 '15.48 <12.27 Mn-54 1 <13.38 <11 <11.89 Co-58 <17.13 '16.28 <15.13 Fe-59 <54.09 <42.77 <58.83 Co-B6 <18.89 <17.55 <14.92 Co-6O I <'16.19 1 12.52 <15.04 Zn-65 <19.5 <39.69 '36.27 Zn-65 1 '33.17 Zr-95 <28.59 <25.16 '30.54 Nb-95 <19.69 <16.84 '13.97 Ru-103 1 <15.68 <12.31 <16.58 Ru-103 <13.26 '9.44 <10.89 Cs-134 1 <23.17 <21.73 '18.35 Cs-134 1 <22.13 <16.86 <12.73 Ce-144 1 '77.30 1 <64.00 <71.80 Ce-14 1 <78.10 '71.10 1 '62.50 Indicates naturally occurring.

Indicates control location.

"Less than" values expressed as Critical Level (L,). B-34

2006 TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH AND INVERTEBRATE SAMPLES (pCi/Kg, wet +/- 1o)

(contr1)

Radionuclide WVHITE, PERCH SUNFISH ~.~CATFISH<

Be-7* <220.8 <125.2 <187.8 K-40* 3914+/-357 2036+/-197.6 4030+/-316.5 Mn-54 <17.05 <12.37 <12.93 Co-58 <23.02 <14.81 <17.64 Fe-59 <76.52 <58.84 <54.47 Co-60 < 12.64 <11.69 <16.54 Zn-65 <45.05 <28.37 <39.61 Zr-95 <35.93 <23.25 <41.65 Nb-95 <31.22 <21.24 <23.36 Ru-1 03 <29.41 <16.3 <27.25 Ru-106 <183 <109.5 <162.8 1-131 <301.5 <155.2 <244 Cs-134 <19.76 <10.05 <12.26 Cs-137 <18.52 <11.42 <14.74 Ba/La-140 <119.1 <64.55 <94.41 Ce-141 <46.72 <21.81 <33.91 Ce-144 <97.80 <53.00 <80.60 Ra-226* <313.9 <235.5 <284.6 Ac-228* <66.06 <36 <58.11 Sr-89 <4100 <3800 <4400 Sr-90 <230 <260 <240 Sr-89 (reanalysis) <1700 <5800 <2200 Sr-90 (reanalysis) <12.0 <19.0 <9.1 DATE April 2006 April 2006 April 2006 Radionuclide WHITEPERCH * *:SUNFISHB *CATFISH Be-7* <269 <323.1 <308.6 K-40* 4128+/-353 4235+/-356.9 4752+/-474.3 Mn-54 <21.2 <19.59 <29.67 Co-58 <32.79 <21.77 <37.92 Fe-59 <104 <102.9 <96.49 Co-60 <24.21 <21.24 <26.06 Zn-65 <53.36 <47.01 <65.62 Zr-95 <46.67 <51.54 <67.29 Nb-95 <54.03 <38.59 <49.4 Ru-103 <32.31 <40.56 <57.15 Ru-106 <234.2 <203.5 <270.4 1-131 <1126 <1293 <1577 Cs-134 <16.93 <20.19 <25.78 Cs-137 <17.11 <21.9 <19.61 Ba/La-140 <356.1 <296.00 <419.2 Ce-141 <39.2 <57.00 <87.2 Ce-144 <96.20 <104.00 <120.00 Ra-226* 720.9+/-264.2 430 +/- 272 <426.6 Ac-228* <77.66 <84.50 <82.06 Sr-89 <1900 <1900 <1100 Sr-90 24.5 +/- 2.9 17.1 +/- 3.1 <7.6 DATE September 2006 September 2006 September 2006 BOLD PRINT INDICATES REPORTED LLD VALUES

Indicates naturally occurring. B35

2006 TABLE B-1 5 CONCENTRATIONS OF RADIONUCLIDES IN FISH AND INVERTEBRATE SAMPLES (pCi/Kg, wet +/- 1a)

(control)

Radionuclide -STRIPED BASS AMERICAN EEL BLUE CRAB*

Be-7* <243.3 <262 <326.6 K-40* 4379+/-347.9 3466+/-299 4366+/-251.5 Mn-54 <18.45 <19.7 <24.02 Co-58 <20.28 <27.51 <30.02 Fe-59 <100.6 <107 <99.26 Co-60 <17.05 < 16.43 <19.84 Zn-65 <43.91 <44.02 <29.83 Zr-95 <40.99 <45.91 <59.3 Nb-95 <28 <38.17 <48.06 Ru-103 <41.9 <39.71 <45.64 Ru-106 <220.8 <214.5 <220.7 1-131 <1151 <1138 <1483 Cs-134 <16.96 <15.74 <15.13 Cs-137 < 16.57 <15.82 <19.3 Ba/La-140 <340.5 <287.2 <301 Ce-141 <54.19 <54.92 <77.75 Ce-144 <104 <89.9 <137 Ra-226* <317.2 622.8+/-229.5 1607+/-288.7 Ac-228* <66.63 <55.74 186.5+/-58.9 Sr-89 <1000 <930 <2200 Sr-90 <5.0 <5.0 13.6 +/- 3.6 DATE September 2006 September 2006 September 2006 BOLD PRINT INDICATES REPORTED LLD VALUES

Indicates naturally occurring. B36

2006 TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH AND INVERTEBRATE SAMPLES (pCi/Kg, wet +/- 1a)

j5 Downstream (Kudson ivei 7 _ 2 __

(indicator)_

Radionuclide WHITEJIPERC**CAT FISH S TSAMERICAN EEL Be-7* <248.8 <210.2 <214.8 <242.3 K-40* 5599+/-419.7 4319+/-313 4135+/-379.6 4713+/-447.8 Mn-54 < 19.44 <22.33 < 19.92 <24.42 Co-58 <32.97 <24.28 <19.84 <28.99 Fe-59 <86.15 <66.88 <72.53 <101 Co-60 <18.74 <19.55 <21.09 <21.89 Zn-65 <56.75 <42.74 <49.41 <60.86 Zr-95 <51.49 <43.19 <43.25 <49.07 Nb-95 <34.68 <31.31 <36.62 <33.62 Ru-103 <38.01 <31.9 <33.91 <26.03 Ru-106 <265.3 <202.4 <236.4 <253.7 1-131 <393.4 <338.5 <303.7 <255.4 Cs-134 <26.23 <23.84 <22.24 <20.62 Cs-137 <21 <19.68 <20.2 <22.67 Ba/La-140 <147.9 <109.3 <91.38 <136 Ce-141 <45.45 <50.84 <41.79 <51.02 Ce-144 <106.00 <117.00 <101.00 <118.00 Ra-226* <440.8 676.3+/-302.1 <343.9 607.3+/-289.8 Ac-228* <84.54 <61.42 <63.41 <86.21 Sr-89 <4000 <3700 <3900 <4100 Sr-90 <270 <270 <270 <240 Sr-89 reanalysis) <1800 <2200 <1500 <1500 Sr-90 (reanalysis) <8.8 <10.0 <11.0 <12.0 DATE April 2006 April 2006 April 2006 April 2006 Radionuclide MSUNFI.SH ~WHITE PERCH ~SUNF(Sk[H i CATFISH~.

Be-7* <256.2 <364.9 <247.4 <331.00 K-40* 6454+/-537.8 5203+/-437.8 6833+/-394.7 4450 +/- 278 Mn-54 <24.27 <26.87 <21.18 <19.90 Co-58 <39.14 <29.18 <30.92 <26.20 Fe-59 <95.85 <105.8 <112.4 <116.00 Co-60 <31.67 <17.13 <16.82 <17.60 Zn-65 <54.66 <72.99 <55.65 <47.20 Zr-95 <61.03 <69.84 <54.74 <51.90 Nb-95 <57.87 <61.65 <52.84 <57.20 Ru-103 <40.5 <44.46 <43.07 <47.00 Ru-106 <305.6 <240.5 <238.6 <248.00 1-131 <324.8 <1022 <989.6 <3240.00 Cs-134 <25.79 <15.29 <19.42 <12.60 Cs-137 <27.4 <22.26 <22.69 <17.30 Ba/La-140 <149.8 <390.4 <280 <484.00 Ce-141 <55.24 <71.93 <63.44 <89.10 Ce-144 <129.00 <71.90 <108.00 <132.00 Ra-226" 1062+/-394.1 <432.9 695.3+/-312.8 906 +/- 279 Ac-228" <107.4 <94.52 141.6+/-50.75 <69.30 Sr-89 <4100 <2000 <4100 <1100 Sr-90 <210 18.8 +/- 2.9 <15.1 <6.4 Sr-89 (reanalysis) <1800 NA NA NA Sr-90 (reanalysis) <9.2 NA NA NA DATE April 2006 Sept 2006 Sept 2006 Sept 2006 BOLD PRINT INDICATES REPORTED LLD VALUES

Indicates naturally occurring. B37

2006 TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH AND INVERTEBRATE SAMPLES (pCi/Kg, wet +/- 1a)

25 Downstream (H~udson FRiver)

(indicator)

Radionuclide !STRIPED* BASS AMERICAN EEL BLUE CRAB Be-7* <285.5 <333.5 <237.9 K-40* 5573+/-440.2 3657+/-319.7 2735+/-309.2 Mn-54 <22.91 <24.63 <18.11 Co-58 <25.12 <33.19 <28.92 Fe-59 <102 <104.7 <99.31 Co-60 <20.65 <23.31 <23.22 Zn-65 <44.8 <55.94 <54.6 Zr-95 <53.04 <56.03 <52.16 Nb-95 <54.47 <58.7 <49.71 Ru-103 <52.81 <52.31 <34.65 Ru-106 <234.2 <281.1 <206.1 1-131 <1045 <1048 <781.1 Cs-134 <23.01 <17.61 <20.57 Cs-137 <20.63 <21.9 <20.65 Ba/La-140 <236.7 <273.4 <367.4 Ce- 141 <55.09 <84.61 <57.22 Ce-144 <124.00 <156.00 <85.10 Ra-226* <388.5 1044+/-339.8 <299.3 Ac-228* <79.88 102.1+/-65.99 <51.58 Sr-89 NA <1100 <1200 Sr-90 NA <721 <5.7 DATE Sept 2006 Sept 2006 Sept 2006 BOLD PRINT INDICATES REPORTED LLD VALUES

Indicates naturally occurring. B38

2006 TABLE B-16 CONCENTRATIONS OF GAMMA EMITTERS IN AQUATIC VEGETATION (pCi/Kg, wet +/- 1 sigma)

June 2006 1 260221 ý,53 1

~I ý24L-,+/-,1

.15 <7 <5.69 <4.65 Co-58 <6.05 <8.09 <5.86 <6.3

<21.3 <26.3 <18.5 <17 Co-60 <9.45 <6.75 <6.54 <6.66

<21.3 <21.9 <18.1 <18.1 Zr-95 <13.5 <13.1 <10.9 <8.88 Nb-95 <7.66 <9.18 <6.00 <7.64 Ru-103 <6.51 <6.86 <6.20 <5.71 Ru-106 <79.40 <66.70 <68.00 <54.40 1-131 <9.72 <10.40 <9.89 <8.22 Cs-134 <5.00 <6.62 <4.45 <6.23 Cs-137 28.2 +/- 4.10 <9.26 24.6 +/- 3.98 <5.55 Ba/La-140 <25.80 <9.05 <8.47 <7.29 Ce-141 <10.60 <10.90 <9.62 <7.93 Ce-144 <5.72 <39.30 <39.50 <29.90 Ra-226* 411 +/- 110 <134.00 260 +/- 125 371 +/- 87.4 Ac-228* 98.9 +/- 26.0 <23.80 149 +/- 23.9 <20.30 September 2006 Co-58 <12.69 <13.33 <12.21 Fe-59 <38.64 <32.45 <28.56 Co-60 <10.43 <19.20 <12.00 Zn-65 <39.80 <45.04 <13.44 Zr-95 <26.50 <23.71 <20.60 Nb-95 <13.41 <15.18 <11.46 Ru-103 <11.41 <13.16 <12.85 Ru-106 <78.78 <115.50 <106.80 1-131 <15.47 <21.48 <16.38 Cs-134 <13.61 <10.39 <9.44 Cs-137 <11.19 <10.73 <10.45 Ba/La-140 <24.65 <21.79 <10.10 Ce-141 <18.56 <16.17 <19.89 Ce-144 <61.30 <70.10 <77.40 Ra-226* < 174.70 <290.30 388 +/- 188.3 Ac-228* <49.61 118.9 +/- 41.89 159.4 +/- 34.29

Indicates naturally occurring.

- Indicates control location.

" Less than" values expressed as Critical Level (Lc). B-39

2006 TABLE B-17 CONCENTRATIONS OF RADIONUCLIDES IN BOTTOM SEDIMENT (pCi/Kg, +/- 1 sigma)

April 2006 Rdi6@R R. flode,< 'OFF.VERPLANCK *OEFVERPLANCK Z$*/LENT7S COVE LENT!S=COVE DISCHARGECANAL Be-7* <223.4 <128.2 <309 <209.3 <199.8 K-40* 20130+/-681.7 15820 t 529.4 18790+/-920.5 17140 +/- 632.3 18420t819.4 Mn-54 <28.13 <15.06 <39.16 <24.09 <26.52 Co-58 <31.21 <18.12 <33.09 <27.83 <24.81 Fe-59 <74.05 <58.11 <110.4 <76.34 <83.12 Co-60 <23.75 <16.85 <37.21 <30.87 <30.81 Zn-65 <42.75 <25.23 <92.31 <32.98 <83.63 Zr-95 <47.28 <30.63 <75.35 <46.52 <43.19 Nb-95 <27.93 <18.68 <50.96 <21.45 <29.96 Ru-103 <27.94 <15.99 <29.49 <27.23 <22.07 Ru-106 <284 <181.2 <374.4 <282.1 <185.7 1-131 <48.23 <21.26 <46.06 <35.71 <36.34 Cs-134 <21.29 <17.43 <32.22 <32.05 <32.6 Cs-137 327.7t29.09 135.9 +/- 18.05 258.6+/-40.95 <25.95 165+/-28 BaLa-140 <39.35 <28.6 <44.88 <36.49 <35.4 Ce-141 <47.05 <26.08 <50.99 <41.92 <34.45 Ce-144 <195 <107 <201 <168 <130 Ra-226* 1753+/-542.9 912.2 +/- 304.9 1752+/-589.4 3584 t 465.9 1168+/-360.2 AcTh-228* 924.3+/-114.4 553.3 +/- 63.46 725.2+/-130.8 1534 +/- 118.9 334.5+/-82.02 Aori12006

RlionuicIdd COLDOSPRING' COLD*SPRING, . A1ANITOU INLET4r

< , A Be-7* <222 <162.5

4---

K-40* 34900 +/- 938 36580 +/- 985.6 8410 +/- 361.1 14440 +/- 585.3 Mn-54 <26.60 <25.09 <10.34 <25.61 Co-58 <26.10 <22.79 <10.80 <27.97 Fe-59 <83.30 <85.47 <42.61 <72.46 Co-60 <29.00 <33.89 <13.70 <23.48 Zn-65 <73.80 <83.67 <40.78 <38.42 Zr-95 <44.40 <39.80 <20.88 <49.28 Nb-95 <30.30 <25.29 <14.85 <20.33 Ru-103 <24.10 < 19.52 <11.55 <28.83 Ru-106 <280.00 <295.80 <106.50 <278.20 1-131 <37.30 <31.65 <14.50 <35.74 Cs-134 <33.40 <26.12 <13.75 <29.11 Cs-137 65.7 +/- 20.4 <23.74 <12.53 <28.14 BaLa-140 <33.60 <24.93 <16.39 <46.94 Ce-141 <36.20 <33.86 <18.77 <39.57 Ce-14 <149.00 <121.00 <59.00 <158.00 Ra-226" 2200 +/- 446 823.6 +/- 341.8 898.8 +/- 186.9 3456 +/- 471.5 AcTh-228* 633 +/- 101 471.6 +/- 92.48 111.1 +/- 42.99 1359+/- 107.4 August 2006 RadlonUc~lde .1OFF VERPLANCK> DISCHARGEZCANAL LEN1IS COVE' COLDISPRING>

Be-7* <502.8 <247.2 <515 <362.00 K-40* 30680+/-1825 18390+/-1034 18910+/-1394 34400+/- 1410 Mn-54 <59.61 <25.31 <55.66 <34.10 Co-58 <81.95 <39.6 <63.82 <46.70 Fe-59 <226.3 <100.3 <169.1 <161.00 Co-60 <58.01 <29.89 <44.08 <51.70 Zn-65 <173 <68.61 <138.3 <156.00 Zr-95 <113.3 <45.3 <122.1 <87.00 Nb-95 <77.89 <50.24 <94.26 <50.70 Ru-103 <77.24 <37.51 <73.29 <40.40 Ru-106 <566.5 <309.5 <468.9 <460.00 1-131 <137.6 <63.21 <127.6 <80.40 Cs-134 <64.86 <33.54 <59.23 <30.90 Cs-137 449 +/-44.0 261 +/- 24.0 375 +/- 41.4 <30.40 BaLa-140 <160.3 <42.73 <143.5 <71.90 Ce-141 <105.3 <52.76 <86.68 <58.90 Ce-144 <290.00 <197.00 <289.00 <210.00 Ra-226" 1902+/-903.1 <599.3 3585+/-910 1540 +/- 624 AcTh-228* 1329+/-273.1 330.9+/-116.9 1238+/-217 709 +/- 180 Sr-89 <2.50 <4.70 <2.00 <1.80 Sr-90 <0.22 <0.22 <0.20 <0.17 BOLD PRINT INDICATES REPORTED LLD VALUES

Indicates naturally occurring. **Indicates control location "Less than" values expressed as Critical Level (L.). B-40

2006 - TABLE B-18 CONCENTRATIONS OF RADIONUCLIDES IN PRECIPITATION - 2006 (pCi/I, +/- I sigma) 1ST QTR 2006 2nd QTR 2006 3rd QTR 2006 4th QTR 2006

~Radionuiclide ~ ROSETION~<< ~ ROSETON ROSETON ~ ROdSETON Be-7* <31.24 <60.65 <194.4 <49.53 K-40* 144.5+/-28.91 238.5+/-63.28 <42.87 290.3+/-60.11 Mn-54 <2.93 <5.06 <8.17 <4.17 Co-58 <3.4 <7.56 <24.02 <5.7 Fe-59 <11.79 <19.27 <48.79 <13.91 Co-60 <3.4 <5.43 <3.37 <3.48 Zn-65 <7.05 <8.4 < 16.72 <10.72 Zr-95 <7.38 <12.28 <30.89 <10.94 Nb-95 <6.32 <8.25 <41.52 <9.71 Ru-103 <4.56 <9.04 <34.24 <8.26 Ru-106 <28.71 <50.57 <52.3 <45.7 1-131 <19.21 <44.1 <199.2 <47.01 Cs-134 <2.74 <5.08 <5.02 <6.34 Cs-1 37 <2.25 <3.83 <4.8 <4.91 BaLa-140 <16.22 <41.49 <115.7 <34.11 Ce-141 <9.14 <16.68 <64.73 <17.88 Ce-144 <18.9 <30.2 <45.4 <32.9 Ra-226* 107.7+/-36.23 <90.02 <91.65 <97.02 AcTh-228* <9.76 <16.86 <12.88 <13.65 H-3 <467 <459 <456 <448 1ST QTR 2006 2nd QTR 2006 3rd QTR 2006 4th QTR 2006 Radionuclide PEEKSKILL GAS): PEEKSKILLGAS ! PEEKSKILLG GAS PEEKSKILL P GAS H~OLDER ~<HOLDER >>' HOLDER HOLDER Be-7* <43.93 <50.38 <65.58 <41.45 K-40* 330+/-42.47 200.7+/-47.14 <75.09 150.2+/-40.18 Mn-54 <3.81 <4.19 <4.45 <2.72 Co-58 <4.81 <4.35 <6.12 <4.46 Fe-59 <18.58 <12.56 <23.69 <13.47 Co-60 <3.61 <3.04 <3.39 <3.34 Zn-65 <9.27 <8.89 < 19.09 <9.32 Zr-95 <7.73 <10.26 <9.93 <9.37 Nb-95 <6.72 <11.52 <11.07 <8.98 Ru-103 <6.21 <8.09 <9.23 <5.89 Ru-106 <33.05 <36.8 <55.6 <31.9 1-131 <31.1 <30.7 <48.14 <22.55 Cs-1 34 <2.35 <4.3 <5.3 <3.61 Cs-137 <2.72 <2.94 <5.17 <3.54 BaLa-140 <26.2 <19.28 <43.88 <21.51 Ce-141 <10.78 <13.67 <18.8 <12.14 Ce-144 <23.4 <30.4 <35.3 <26.5 Ra-226* <72.35 <70.17 <118.1 <65.09 AcTh-228* <12.06 <11.67 <13.3 <9.06 H-3 <467 <459 <456 <448

Indicates naturally occurring.

- Indicates control location.

"Less than" values expressed as Critical Level (Lc). B-41

2006 - TABLE B-19 CONCENTRATIONS OF GAMMA EMITTERS IN SOIL - 2006 (pCi/Kg, +/- 1 sigma)

Radionuclide R:

.ROSETN *MET TOWER TFRAING BLDG*

Be-7* 831+/-212.3 <158.9 1136+/-190.2 K-40* 12710+/-704.7 7365+/-413.7 14550+/-807.7 Mn-54 <27.87 <22.2 <21.55 Co-58 <28.06 <18.02 <24.03 Fe-59 <66.3 <49.25 <94.95 Co-60 <36.18 <18.85 <25.81 Zn-65 <34.56 <53.18 <76.91 Zr-95 <43.38 <30.31 <45.06 Nb-95 <35.23 <17.23 <31.03 Ru-103 <25.81 <20.4 <23.03 Ru-106 <272.8 <186.8 <211.2 1-131 <34.72 <21.36 <31.13 Cs-134 <26.23 <17.11 <15.94 Cs-137 <26.51 <22.1 <33.74 Ba/La-140 <27.36 <15.18 <35.06 Ce-141 <43.15 <31.68 <37.85 Ce-144 <176 <143 <136 Ra-226* 1329+/-596.6 <406.4 <571.3 Ac-228* 826.9+/-110.5 260.8+/-56.06 360+/-105.7

Indicates naturally occurring.

- Indicates control location.

"Less than" values expressed as Critical Level (Lc). B-42

2006 TABLE B-20 RADIOACTIVITY CONCENTRATIONS IN SPECIAL WATER - EXISTING ODCM LOCATIONS (pCi/L +/- I a)

Jan 2006 ALGONQUIN GYPSUM PLANT TRAP ROCK 5TH STREET ISOTOPE OUTFALL STREAM QUARRY WELL GROSS BETA 10.59 +/- 0.84 9.10 +/- 1.30 3.72 +/- 0.60 5.96 +/- 0.62 Be-7* <26.16 <36.63 <17.27 <29.95 K-40* 177.9+/-46.27 287.7+/-50.55 146.9+/-29.52 218.5+/-45.36 Mn-54 <4.75 <4.79 <2.08 <3.77 Co-58 <4.9 <4.15 <2.41 <4.18 Fe-59 <7.03 <8.12 <5.6 <10.84 Co-60 <3.2 <4.27 <2.37 <3.94 Zn-65 <9.56 <5.9 <5.76 <4.92 Zr-95 <5.54 <5.39 <3.6 <6.12 Nb-95 <4.82 <2.6 <2.22 <2.71 Ru-103 <3.53 <4.01 <2.66 <3.94 Ru-106 <35.93 <40.37 <19.93 <35.6 1-131 <5.09 <6.7 <2.55 <0.27 Cs-134 <3.69 <5.5 <2.63 <3.57 Cs-137 <4.19 <4.32 <2.54 <4.91 Ba/La-140 <4.44 <5.53 <2.33 <5.56 Ce-141 <5.79 <7.82 <3.93 <6.28 Ce-144 <22.80 <30.60 <16.00 <23.40 Ra-226* <73.02 <109.4 16.9 214.2+/-66.45 Ac-228" <11.43 <12.44 <8.7 <16.64 H-3 <469 <469 <469 NA Feb 2006 ALGONQUIN GYPSUM PLANT TRAP ROCK WATER METER 5TH STREET ISOTOPE OUTFALL STREAM QUARRY WELL GSA GROSS BETA 6.23 +/- 0.71 10.60 +/- 0.76 3.02 +/- 0.59 0.97 +/- 0.41 3.66 +/- 0.54 Be-7* <25.42 <36 <18.38 <18.66 <23.65 K-40* 115+/-26.56 421.7+/-42.62 201.3+/-34.58 177.3+/-40.03 142.2+/-32.89 Mn-54 <2.79 <4.44 <2.46 <3.35 <3.01 Co-58 <2.86 <2.08 <2.13 <3.56 <2.68 Fe-59 <7.4 <9.65 <8.8 <7.53 <8 Co-60 <2.53 <4.3 <2.11 <3.53 <3.12 Zn-65 <4.13 <5.58 <6.6 <8.21 <5.33 Zr-95 <4.98 <6.98 <4.47 <4.52 <4.49 Nb-95 <2.1 <3.09 <2.52 <2.91 <2.01 Ru-103 <2.67 <4.37 <3.12 <2.97 <3.19 Ru-106 <32.64 <34.53 <22.52 <35.3 <40.36 1-131 <2.65 <4.5 <2.73 <4.12 0.55 Cs-134 <2.63 <2.78 <1.46 <3.07 <3.15 Cs-137 <3.35 <2.32 <3.15 <3.31 <2.93 Ba/La-140 <4.02 <4.9 <3.1 <4.73 <4.07 Ce-141 <4.78 <8.72 <4.18 <4.87 <5.5 Ce-144 <20.70 <36.60 <16.50 <17.50 <22.00 Ra-226" <73.25 272.4+/-93.91 <64.25 138.9+/-56.48 <79.63 Ac-228* <9.01 <15.72 <9.95 <9.51 <10.59 H-3 <469 <469 <469 <469 <460

Indicates naturally occurring.

"Lessthan" values expressed as Critical Level (L.).

- - Indicates the average of the positive sample results reported for samples with recounts performed. B-43

2006 TABLE B-20 RADIOACTIVITY CONCENTRATIONS IN SPECIAL WATER - EXISTING ODCM LOCATIONS (pCi/L +/- 1a)

Feb (2) 2006 ALGONQUIN GYPSUM PLANT TRAP ROCK ISOTOPE OUTFALL STREAM QUARRY GROSS BETA 6.84 +/-1.16 12.17 +/-1.43 10.36 +/- 0.77 Be-7* <24.62 <31.96 <31.38 K-40* 185.7+/-31.84 <39.73 422.3+/-45.98 Mn-54 <2.93 <3.69 <3.17 Co-58 <3.63 <2.02 <3.02 Fe-59 <8.93 <10.13 <10.69 Co-60 <3.23 <3.95 <3.84 Zn-65 <4.27 <5.49 <8.49 Zr-95 <5.12 <6.58 <4.75 Nb-95 <2.45 <3.84 <3.28 Ru-103 <3.5 <3.53 <3.46 Ru-106 <24.37 <40.28 <31.44 1-131 <3.3 <4.33 <3.4 Cs-134 <3.66 <3.83 <3.14 Cs-137 <3.21 <2.21 <3.07 Ba/La-140 <4.09 <5.42 <4.61 Ce-141 <6.19 <7.71 <5.79 Ce-144 <25.80 <32.80 <22.30 Ra-226* <86.48 <95.77 146.7+/-67.26 Ac-228* <12.2 <13.92 <9.69 H-3 <454 <454 <454 Mar 2006 ALGONQUIN GYPSUM PLANT TRAP ROCK 5TH STREET ISOTOPE OUTFALL STREAM QUARRY WELL GSA GROSS BETA 2.57 +/- 1.07 5.73 +/- 1.25 6.77 +/- 0.69 6.54 +/- 0.60 Be-7* <17.99 <12.9 <20.24 <31.72 K-40* 365.3+/-33.68 171.1+/-20.21 135.8+/-26.66 410.5+/-47.62 Mn-54 <2.51 <1.43 <2.22 <4.54 Co-58 <2.62 <1.45 <2.29 <3.95 Fe-59 <6.56 <5.78 <5.94 <8.85 Co-60 <2.9 <2.02 <2.9 <3.93 Zn-65 <3.1 <2.84 <3.57 <5.43 Zr-95 <4.04 <3.72 <5.57 <5.81 Nb-95 <1.67 <1.99 <3.19 <2.48 Ru-103 <2.53 <2.35 <2.34 <4.06 Ru-106 <26.73 <22.09 <27.7 <32.57 1-131 <2.85 <2.94 <2.86 <0.28 Cs-134 <2.47 <1.55 <2.28 <2.57 Cs-137 <2.6 <1.3 <2.49 <4.9 Ba/La-140 <3.36 <2.77 <3.46 <3.83 Ce-141 <4.02 <5.58 <3.81 <7.51 Ce-144 <17.30 <24.30 <16.70 <30.50 Ra-226* <67.35 <73.36 <57.69 <96.99 Ac-228* <9.17 <8.38 <8.71 <13.81 H-3 <463 <463 <463 <466

Indicates naturally occurring.

".Less than" values expressed as Critical Level (Lj).

Indicates the average of the positive sample results reported for samples with recounts performed. B-44

2006 TABLE B-20 RADIOACTIVITY CONCENTRATIONS IN SPECIAL WATER - EXISTING ODCM LOCATIONS (pCi/L +/- 1a)

Apr2006 ALGONQUIN GYPSUM PLANT TRAP ROCK 5TH STREET ISOTOPE OUTFALL STREAM QUARRY WELL MONTHLY GROSS BETA 4.9 +/- 1.0 7.1 +/- 1.2 8.0 +/- 0.7 8.3 +/- 0.7 Be-7* <32.3 <36.01 <17.17 <24.46 K-40* 141.8+/-42.38 177+/-35.41 153.2+/-24.91 350.5+/-41.36 Mn-54 <3.48 <3.37 <2.41 <3.29 Co-58 <3.35 <2.62 <1.8 <3.59 Fe-59 <10.81 <11.28 <4.6 <9.25 Co-60 <3.27 <3.88 <2.36 <3.53 Zn-65 <5.04 <5.17 <6.18 <4.26 Zr-95 <6.3 <6.42 <4.24 <5.74 Nb-95 <4.59 <3.05 <2.35 <2.13 Ru-103 <3.82 <3.81 <2.45 <3.28 Ru-106 <32.74 <38.64 <24.92 <32.55 1-131 <3.86 <5.17 <2.34 <0.29 Cs-134 <4.07 <2.91 <1.85 <1.95 Cs-137 <3.98 <2.54 <2.46 <3.2 Ba/La-140 <5.04 <4.41 <2.61 <3.6 Ce-141 <6.42 <8.02 <3.58 <5.82 Ce-144 <21.50 <35.00 <16.20 <23.00 Ra-226* <81.46 <123.8 132.6+/-38.88 <75.65 Ac-228" <14.83 <16.61 <8.52 <12.56 H-3 <451 <451 <451 <461 May 2006 ALGONQUIN GYPSUM PLANT TRAP ROCK 5TH STREET ISOTOPE OUTFALL STREAM QUARRY WELL GSA GROSS BETA 6.6 +/- 1.1 6.3 +/- 1.2 8.7 +/- 0.7 7.8 +/- 0.7 Be-7* <20.91 <33.46 <14.92 <35.1 K-40* 150.4+/-31.57 252.8+/-40.87 107.9+/-19.98 <40.62 Mn-54 <2.52 <4.16 <2.06 <4.45 Co-58 <2.77 <4.47 <2.06 <4.46 Fe-59 <7.22 <9.91 <5.35 <7.05 Co-60 <2.97 <3.87 <2.46 <3.37 Zn-65 <2.83 <5.08 <5.68 <3.97 Zr-95 <5.22 <6.75 <3.66 <5.72 Nb-95 <3.88 <3.11 <2.08 <2.53 Ru-103 <2.8 <4.11 <2.02 <3.68 Ru-106 <29.32 <39.06 <23.6 <38.52 1-131 <3.31 <4.44 <2.69 <0.41 Cs-134 <2.87 <2.72 <1.48 <2.32 Cs-1 37 <2.01 <3.85 <2.2 <3.86 Ba/La-140 <3.62 <6.05 <2.16 <5.38 Ce-141 <4.85 <7.16 <3.91 <8.36 Ce-144 <21.00 <30.30 < 16.70 <36.90 Ra-226* <69.34 <110.3 <55.11 <116.2 Ac-228" <10.5 <16.52 14.17+/-5.81 <15.4 H-3 <446 <446 <446 <466

Indicates naturally occurring.

".Less than" values expressed as Critical Level (Lj).

Indicates the average of the positive sample results reported for samples with recounts performed. B-45

2006 TABLE B-20 RADIOACTIVITY CONCENTRATIONS IN SPECIAL WATER - EXISTING ODCM LOCATIONS (pCi/L +/- Ia)

Jun 2006 ALGONQUIN GYPSUM PLANT TRAP ROCK 5TH STREET ISOTOPE OUTFALL STREAM QUARRY WELL GSA GROSS BETA 5.3 +/- 1.1 17.2 +/- 1.5 7.9 +/- 0.7 7.6 +/- 0.7 Be-7* <22.37 <21.92 <18.8 <19.95 K-40* 305.6+/-36.61 165.1+/-32.1 <34.77 161.5+/-27.97 Mn-54 <2.73 <2.59 <2.53 <2.32 Co-58 <2.58 <2.53 <2.26 <2.45 Fe-59 <6.12 <8.24 <6.69 <7 Co-60 <2.34 <3.02 <2.53 <1.82 Zn-65 <3.47 <5.13 <3.22 <5.54 Zr-95 <4.19 <5.12 <3.54 <3.91 Nb-95 <2.78 <2.26 <2.54 <4.24 Ru-103 <2.77 <3.15 <2.99 <3.26 Ru-106 <28.04 <27.42 <25.79 <25.33 1-131 <3.43 <3.42 <3.12 <0.33 Cs-1 34 <2.53 <2.89 <2.3 <2.72 Cs-1 37 <3.43 <2.5 <2.59 <2.83 Ba/La-140 <3.8 <3.49 <3.56 <3.94 Ce-141 <4.68 <3.97 <4.42 <4.53 Ce-144 <21.80 <17.40 <17.50 <1 8.60 Ra-226" <75.78 95.41+/-49.95 158.1+/-44.89 <55.92 Ac-228* <8.48 <9.49 <9.03 <8.34 H-3 <459 <459 <459 NA Jul 2006 ALGONQUIN GYPSUM PLANT TRAP ROCK 5TH STREET ISOTOPE OUTFALL STREAM QUARRY WELL GSA GROSS BETA 6.1 +/- 1.2 5.4 +/- 0.7 6.0 +/- 0.7 8.8 +/- 0.7 Be-7* <19.46 <19.48 <13.85 <34.04 K-40* 281.9+/-28.04 350+/-35.55 129.3+/-22.08 378.1+/-43.99 Mn-54 <2.44 <2.85 <1.61 <4 Co-58 <2.48 <1.88 <2.16 <4.29 Fe-59 <5.21 <6.21 <5.42 <9.06 Co-60 <2.23 <3.34 <2.24 <4.56 Zn-65 <3.09 <6.84 <5.28 <5.47 Zr-95 <4.6 <3.92 <3.34 <6.82 Nb-95 <1.73 <3.06 <2.06 <2.5 Ru-103 <2.79 <3.01 <2.35 <3.84 Ru-106 <21.92 <30.91 <22.96 <35.21 1-131 <2.67 <3.03 <2.2 <0.32 Cs-134 <2.46 <1.81 <2.29 <2.33 Cs-137 <2.63 <2.34 <2.01 <2.32 Ba/La-140 <2.99 <3.92 <2.94 <4.78 Ce-141 <4.68 <4.24 <3.3 <6.71 Ce-144 <19.50 <19.00 <15.10 <28.80 Ra-226* 67.68+/-40.21 132.7+/-55.11 98.04+/-36.67 <102.4 Ac-228* <8.55 <9.71 <7.67 <15.67 H-3 <458 <458 <458 NA

Indicates naturally occurring.

".Less than" values expressed as Critical Level (L.).

Indicates the average of the positive sample results reported for samples with recounts performed. B-46

2006 TABLE B-20 RADIOACTIVITY CONCENTRATIONS IN SPECIAL WATER - EXISTING ODCM LOCATIONS (pCi/L +/- Ia)

Aug 2006 ALGONQUIN GYPSUM PLANT TRAP ROCK 5TH STREET ISOTOPE OUTFALL STREAM QUARRY WELL GSA GROSS BETA 8.3 +/- 0.7 Be-7* <24.75 <30.89 <25.46 <30.48 K-40* 296.4+/-45.24 62.95+/-35.97 342.2+/-40.29 178.9+/-41.26 Mn-54 <3.48 <3.66 <2.25 <2.91 Co-58 <3.86 <3.74 <2.41 <4.63 Fe-59 <8.95 <9.78 <7.18 <7.96 Co-60 <3.84 <3.8 <3.77 <2.78 Zn-65 <4.22 <4.27 <6.31 <5.42 Zr-95 <5.93 <6.6 <5.03 <6.56 Nb-95 <3.48 <2.94 <2.86 <2.23 Ru-1 03 <3.38 <3.93 <3.4 <3.67 Ru-106 <35.95 <41.09 <25.78 <44.73 1-131 <3.98 <5.02 <3.23 <0.38 Cs-1 34 <2.06 <3.89 <3.04 <4.24 Cs-137 <3.82 <2.13 <3.13 <4.14 Ba/La-140 <3.64 <5.26 <4.5 <4.63 Ce-141 <5.58 <7.5 <5.02 <7.95 Ce-144 <22.30 <31.50 <19.40 <28.90 Ra-226* <81.68 149.4+/-80.59 <75.9 <105.5 Ac-228" <15.62 <14.66 <10.27 <14.01 H-3 <445 <445 <445 NA Sep 2006 ALGONQUIN GYPSUM PLANT TRAP ROCK 5TH STREET ISOTOPE OUTFALL STREAM QUARRY WELL GSA GROSS BETA 5.3 +/- 1.2 6.2 +/- 1.3 3.5 +/- 0.5 7.6 +/- 0.7 Be-7* <24.75 <30.89 <25.46 <30.26 K-40* 296.4+/-45.24 62.95+/-35.97 342.2+/-40.29 294.6+/-46.97 Mn-54 <3.48 <3.66 <2.25 <3.72 Co-58 <3.86 <3.74 <2.41 <3.33 Fe-59 <8.95 <9.78 <7.18 <8.19 Co-60 <3.84 <3.8 <3.77 <3.63 Zn-65 <4.22 <4.27 <6.31 <5.11 Zr-95 <5.93 <6.6 <5.03 <6.71 Nb-95 <3.48 <2.94 <2.86 <3.23 Ru-103 <3.38 <3.93 <3.4 <3.97 Ru-106 <35.95 <41.09 <25.78 <40.41 1-131 <3.98 <5.02 <3.23 <0.38 Cs-134 <2.06 <3.89 <3.04 <3.02 Cs-137 <3.82 <2.13 <3.13 <3.49 BalLa-140 <3.64 <5.26 <4.5 <3.82 Ce-141 <5.58 <7.5 <5.02 <6.27 Ce-144 <22.30 <31.50 <19.40 <27.30 Ra-226* <81.68 149.4+/-80.59 <75.9 <105 Ac-228" <15.62 <14.66 <10.27 <12.44 H-3 <445 <445 <445 NA

Indicates naturally occurring.

".Less than" values expressed as Critical Level (L,).

Indicates the average of the positive sample results reported for samples with recounts performed. B-47

2006 TABLE B-20 RADIOACTIVITY CONCENTRATIONS IN SPECIAL WATER - EXISTING ODCM LOCATIONS (pCi/L t Io)

Oct 2006 ALGONQUIN GYPSUM PLANT TRAP ROCK IP 5TH STREET ISOTOPE OUTFALL STREAM QUARRY WELL GSA GROSS BETA 15.5 +/-1.5 5.8 +/-1.2 3.0 +/- 0.5 7.5 +/- 0.7 Be-7* <23.03 <30.14 <27.61 <27.22 K-40* 257.2+/-43.05 185.4+/-40.17 202.9+/-43.66 137+/-25.91 Mn-54 <3.44 <4.29 <2.8 <2.82 Co-58 <3.27 <2.49 <3.37 <3.06 Fe-59 <11.56 <9.39 <8.6 <6.33 Co-60 <3.6 <4.51 <3.12 <2.83 Zn-65 <3.76 <5.47 <7.44 <3.83 Zr-95 <5.43 <6.62 <5.65 <5.07 Nb-95 <4.37 <3.11 <3.76 <2.29 Ru-1 03 <3.4 <4.01 <3.9 <2.85 Ru-106 <35.35 <39.27 <26.05 <28.43 1-131 <3.9 <4.63 <3.27 <0.40 Cs-134 <2.59 <3.7 <4.5 <2.18 Cs-137 <3.52 <3.73 <3.21 <1.8 Ba/La-140 <5.11 <3.71 <3.88 <2.66 Ce-141 <5.49 <7.8 <5.25 <6.27 Ce-144 <21.90 <33.30 <19.60 <28.00 Ra-226* <91.8 <105.2 <70.63 <84.19 Ac-228" <12.03 <13.85 <9.94 <10.84 H-3 <456 <456 <456 NA Nov 2006 ALGONQUIN GYPSUM PLANT TRAP ROCK IP 5TH STREET ISOTOPE OUTFALL STREAM QUARRY WELL GSA GROSS BETA 3.9 +/- 1.1 12.7 +/- 1.4 7.3 +/- 0.7 8.7 +/- 0.7 Be-7* <27.91 <22.86 <18.89 <23.12 K-40* 106.8+/-29.75 159.8+/-35.08 295.5+/-34.84 115.3+/-22.3 Mn-54 <2.99 <2.86 <2.68 <2.58 Co-58 <2.67 <2.02 <2.41 <2.58 Fe-59 <8.31 <7.03 <5.46 <5.97 Co-60 <3.56 <2.66 <2.59 <2.61 Zn-65 <3.37 <6.26 <3 <3.4 Zr-95 <5.26 <3.89 <4.37 <4.35 Nb-95 <1.95 <3.21 <3.05 <2.03 Ru-103 <3.08 <2.66 <3.05 <2.96 Ru-106 <25.27 <31.14 <27.56 <28.89 1-131 <3.4 <2.83 <2.7 <0.35 Cs-134 <2.97 <1.78 <2.58 <1.94 Cs-137 <2.54 <3.14 <2.78 <2.76 Ba/La-140 <3.26 <2.8 <2.72 <3.13 Ce-141 <5.17 <3.66 <4.65 <6.12 Ce-144 <20.90 <17.00 <20.40 <27.00 Ra-226* <76.61 <65.4 <68.2 <73.76 Ac-228" <9.31 <7.17 <9.37 <8.96 H-3 <449 <449 <449 NA

Indicates naturally occurring.

".Less than" values expressed as Critical Level (Lc).

Indicates the average of the positive sample results reported for samples with recounts performed. B-48

2006 TABLE B-20 RADIOACTIVITY CONCENTRATIONS IN SPECIAL WATER - EXISTING ODCM LOCATIONS (pCi/L +/- 1a)

Dec 2006 ALGONQUIN GYPSUM PLANT TRAP ROCK IP 5TH STREET ISOTOPE OUTFALL STREAM QUARRY WELL GSA GROSS BETA 6.5 +/- 1.2 10.0 +/- 1.3 9.2 +/- 0.7 8.0 +/- 0.7 Be-7* <24.09 <33.63 <21.89 <29.62 K-40* 180.8+/-28.14 305.4+/-48.22 182.4+/-38.94 138.3+/-37.12 Mn-54 <3.04 <2.83 <1.99 <3.64 Co-58 <2.82 <3.75 <3.14 <4.34 Fe-59 <6.61 <10 <6.98 <9.12 Co-60 <2.62 <3.97 <2.68 <4.05 Zn-65 <4.8 <7.43 <6.81 <4.12 Zr-95 <5.17 <4.54 <5.18 <6.52 Nb-95 <3.43 <4.32 <3.23 <2.73 Ru-1 03 <3.26 <4.01 <3.68 <3.32 Ru-106 <28.62 <37.89 <29.32 <41.99 1-131 <3.37 <3.67 <4.24 <0.39 Cs-134 <1.91 <2.23 <2.23 <4.87 Cs-137 <2.86 <3.52 <2.82 <3.74 Ba/La-140 <3.33 <3.46 <3.33 <3.91 Ce-141 <4.07 <7.05 <5 <7 Ce-144 <27.10 <27.90 <25.10 <31.10 Ra-226" <79.98 <102.3 <77.29 <107.5 Ac-228" <9.76 <13.13 <10.67 <12.07 H-3 <449 <449 <449 NA Dec (2) 2006 ALGONQUIN GYPSUM PLANT TRAP ROCK ISOTOPE OUTFALL STREAM QUARRY GROSS BETA 7.7 +/- 1.2 13.5 +/- 1.3 9.3 +/- 0.7 Be-7* <25.98 <23.72 <29.34 K-40* 160.2+/-37.61 159.2+/-26.75 255.7+/-39.96 Mn-54 <3.11 <1.98 <3.41 Co-58 <4.03 <2.51 <3.22 Fe-59 <5.39 <6.69 <10.06 Co-60 <3.05 <3.01 <2.9 Zn-65 <7.54 <8.11 <6.32 Zr-95 <4.77 <5.06 <5.15 Nb-95 <4.92 <3.06 <4.15 Ru-103 <3.09 <2.85 <3.37 Ru-106 <33.58 <28.49 <34.44 1-131 <5.1 <3.75 <3.42 Cs-134 <3.25 <2.1 <3.8 Cs-137 <3.07 <3.05 <2.36 BalLa-140 <4.5 <4.18 <4.27 Ce-141 <5.6 <5.51 <6.25 Ce-144 <20.80 <23.90 <25.10 Ra-226* <71.88 <68.8 <87.41 Ac-228* <10.36 <7.92 <12.45 H-3 <449 <448 <449

Indicates naturally occurring.

".Less than" values expressed as Critical Level (Lc).

Indicates the average of the positive sample results reported for samples with recounts performed. B-49

2006 TABLE B-21 RADIOACTIVITY CONCENTRATIONS IN SPECIAL WATER - NEW ODCM LOCATIONS (pCi/L +/- la)

Monitoring Well #40 (MW-40)

ISOTOPE 2/9/06 4/11106 5122106 6/20/06 7/5/06 Be-7 <38.02 <25.84 <24.37 <23.86 <41.21 K-40 159.8+/-34.43 132 +/- 34.5 145.2+/-23.42 213.1+/-37.41 112.2+/-33.1 Mn-54 <2.41 <2.78 <2.53 <2.95 <2.33 Co-58 <3.53 <2.75 <2.34 <2.89 <2.11 Fe-59 <8.71 <9.6 <6.89 <10.76 <10.93 Co-60 <4.03 <4.12 <2.46 <4.92 <3.65 Zn-65 <6.02 <5.3 <3.09 <5.15 <5.83 Zr-95 <6.47 <7.12 <4.58 <6.83 <6.77 Nb-95 <4.18 <2.59 <2.13 <2.55 <4.09 Ru-103 <4.38 <4.33 <2.9 <3.9 <4.86 Ru-106 <35.83 <41.9 <24.66 <40.52 <42.21 1-131 <6.56 <5.84 <4.77 <5.57 <7.05 Cs-134 <4.22 <3.01 <1.92 <4.58 <3.01 Cs-137 <2.22 <2.56 <1.54 <2.46 <2.48 Ba/La-140 <6.03 <5.26 <4.11 <5.72 <5.69 Ce-141 <8.87 <11.7 <5.29 <9.25 <11.52 Ce-144 <33.90 <49.2 <21.00 <33.50 <43.70 Ra-226 <109.4 <151.6 <71.64 <125.4 <133.3 Ac-228 <14.47 <16.25 <8.98 <17.51 <13.66 H-3 <473 <452 <446 <499 <452 Sr-89 NA <62 <14 <180 <24 Sr-90 NA 0.49 +/- 0.13 0.65 +/- 0.12 <4.1 <0.89 Monitoring Well #40 (MW-40)

ISOTOPE 7111/06 8/9/06 9/12/06 11/21/06 12/6/06 Be-7 <21.57 <25.21 <20.37 <18.92 <41.95 K-40 308.5+/-40.51 139.7+/-31.81 92.2 +/- 29.4 148 +/- 24.5 <42.42 Mn-54 <2.52 <2.48 <2.19 <2.94 <2.50 Co-58 <2.44 <2.39 <2.36 <1.68 <2.52 Fe-59 <10.9 <10.33 <9.70 <8.02 <10.72 Co-60 <4.73 <4.01 <3.71 <2.49 <3.86 Zn-65 <5.78 <5.94 <4.84 <4.09 <5.63 Zr-95 <7.09 <6.69 <6.74 <5.33 <7.03 Nb-95 <2.54 <2.5 <2.98 <2.79 <3.15 Ru-103 <4.12 <4.69 <3.97 <3.24 <4.40 Ru-106 <39.08 <40.1 <32.80 <28.94 <37.52 1-131 <5.38 <6.86 <6.10 <6.82 <6.20 Cs-134 <3.16 <2.93 <3.91 <2.11 <3.93 Cs-137 <2.58 <2.47 <2.18 <1.72 <2.58 Ba/La-140 <5.86 <5.47 <5.92 <5.12 <5.68 Ce-141 <8.64 <11.31 <8.25 <7.98 <9.72 Ce-144 <36.30 <45.40 <32.40 <29.60 <38.00 Ra-226 <133.6 <129 <103.30 <84.88 <137.80 Ac-228 <16.18 <14.46 <14.69 <9.46 <16.00 H-3 <452 <447 <452 <450 <460 Sr-89 NA <27 <53 NA NA Sr-90 0.68 +/- 0.11 <0.73 <0.75 <0.78 1.26 +/- 0.26 BOLD PRINT INDICATES REPORTED LLD VALUES

Indicates naturally occurring.

".Less than" values expressed as Critical Level (Lc).

Avg of positive results for recounts B-50

2006 TABLE B-21 RADIOACTIVITY CONCENTRATIONS IN SPECIAL WATER - NEW ODCM LOCATIONS (pCi/L +/- 1a)

Monitoring Well #51 (MW-51)

ISOTOPE 4/11106 5/30/06 6/20/06 7/5/06 7/10/06 Be-7 <32.64 <26.28 <22.49 <18.9 <39.39 K-40 153.1 +/- 26.9 73.76+/-33.3 132.6+/-32.39 292.3+/-36.79 178.2+/-41.87 Mn-54 <2.15 <2.74 <2.57 <3.89 <2.89 Co-58 <2.37 <2.95 <2.74 <2.08 <2.9 Fe-59 <8.76 <10.18 <10.47 <9.85 <11.51 Co-60 <3.4 <4.38 <4.31 <4.11 <4.94 Zn-65 <4.54 <5.42 <5.03 <4.68 <6.74 Zr-95 <6.23 <7.27 <7.16 <6.85 <5.16 Nb-95 <3.02 <2.76 <3.08 <2.79 <3.29 Ru-103 <3.84 <4.46 <4.32 <3.8 <4.87 Ru-106 <34.18 <44.28 <37.97 <34.6 <43.15 1-131 <6.57 <6.29 <4.94 <6.59 <6.7 Cs-1 34 <2.45 <3.1 <4.26 <2.61 <4.78 Cs-137 <1.96 <2.56 <2.61 <2.01 <2.57 Ba/La-140 <5.55 <5.69 <5.83 <6.63 <6.61 Ce-141 <9.51 <12.14 <9.06 <7.87 <10.83 Ce-144 <38.4 <51.30 <38.30 <30.00 <43.60 Ra-226 <113.9 <159.6 <121.9 <107.4 <142.4 Ac-228 <13.04 <17.49 <16.95 <13.55 <17.77 H-3 <452 <446 <499 <452 <452 Sr-89 <39 <26 <32 <31 NA Sr-90 <0.45 <0.43 <0.71 <0.89 <1.5 Monitoring Well #51 (MW-51)

ISOTOPE 8/10/06 9/12/06 11/21/06 12/6/06 Be-7 <21.58 <21.93 <18.31 <23.14 K-40 185+/-34.09 189 +/- 38.8 129 +/- 27.1 <49.48 Mn-54 <2.48 <2.70 <2.69 <2.21 Co-58 <2.36 <2.58 <2.17 <2.32 Fe-59 <10.54 <10.66 <8.15 <9.30 Co-60 <4.79 <4.41 <3.14 <3.64 Zn-65 <5.88 <5.16 <4.16 <5.24 Zr-95 <7.13 <6.92 <5.91 <6.37 Nb-95 <2.52 <2.67 <2.69 <2.15 Ru-103 <4.1 <3.89 <3.64 <4.39 Ru-106 <39.35 <39.10 <28.27 <35.88 1-131 <6.06 <7.24 <6.95 <7.04 Cs-134 <3.1 <3.90 <3.22 <2.91 Cs-137 <2.3 <2.11 <1.95 <2.53 Ba/La-140 <6.21 <6.69 <6.12 <5.35 Ce-141 <8.83 <9.11 <7.37 <11.19 Ce-144 <35.80 <31.60 <26.30 <44.70 Ra-226 <129 <114.50 <84.05 <123.20 Ac-228 <16.4 <15.81 <11.33 <15.90 H-3 <447 <452 <450 <460 Sr-89 <26 <53 NA NA Sr-90 <0.72 <0.78 <0.75 0.84 +/- 0.26 BOLD PRINT INDICATES REPORTED LLD VALUES

Indicates naturally occurring.

".Less than" values expressed as Critical Level (La).

Avg of positive results for recounts B-51

TABLE B-22 MILCH ANIMAL CENSUS 2006 THERE ARE NO ANIMALS PRODUCING MILK FOR HUMAN CONSUMPTION WITHIN FIVE MILES OF INDIAN POINT.

B-52

TABLE B-23 LAND USE CENSUS 2006 A comprehensive survey of the of the 5 mile (8 kilometer) area surrounding the Indian Point Site was conducted during the 2006 Spring, Summer and Fall months in accordance with the ODCM Section D 3.5 Radiological Environmental Monitoring Land Use Census Methodology:

Visual inspections were made of the 5-mile area around the Indian Point Site during routine sample collections and emergency plan equipment inspections in the area throughout the year.

Obtained information from the New York Agricultural Statistic Service on milching animals within the 5-mile area surrounding Indian Point Energy Center.

An extensive land survey was conducted of the 5-mile area in an attempt to identify new residential areas, commercial developments and to identify milch animals in pasture. Previous locations were visited and verified by dispatching Nuclear Environmental Technicians to the various locations.

Note: This was done while performing quarterly environmental badge change out and field inspections through out the 4 surrounding counties.

" Orange County was surveyed during through the summer and fall.

" Rockland County was surveyed during summer and fall with approx.

" Putnam County was surveyed during the summer and fall.

" Westchester County was surveyed during the summer and summer and fall.

Note: An aerial survey was not conducted of the 5-mile area this year.

Results:

The 2006 land use census indicated there were no new residences that were closer in proximity to IPEC.

NEM performed a complete nearest residence survey with updated distances.

No milch animals were observed during this reporting period within the 5-mile zone or listed in the New York Agricultural Statistic Service.

B-53

TABLE B-23 LAND USE CENSUS 2006 INDIAN POINT ENERGY CENTER UNRESTRICTED AREA BOUNDARY AND NEAREST RESIDENCES 2006 Distance to Distance to site Distance to site nearest resident, Boundary from Boundary from from Unit I Unit 2 Plant Vent Unit 3 Plant Vent superheater Address of nearest resident, Dec 2004 Sector Compass Point (meters) (meters) (meters) Census N RIVER RIVER 1788.1 41 River Road Tomkins Cove NNE RIVER RIVER 3111.3 Chateau Rive Apts. John St. Peekskill NE 550 636 1907.3 122 Lower South St. Peekskill ENE 600 775 1478.2 1018 Lower South St. Peekskill E 662 785 1370.9 1103 Lower South St. Peekskill ESE 569 622 715.2 461 Broadway Buchanan SE 553 564 1168.2 223 First St. Buchanan SSE 569 551 1239.7 5 Pheasant's Run Buchanan S 700 566 1132.5 320 Broadway Verplanck SSW 755 480 1573.5 240 Eleventh St. Verplanck SW 544 350 3015.9 29 Church St. Tomkins Cove WSW RIVER RIVER 2169.6 9 West Shore Dr. Tomkins Cove W RIVER RIVER 1918.7 712 Rt. 9W Tomkins Cove WNW RIVER RIVER 1752.4 770 Rt. 9W Tomkins Cove NW RIVER RIVER 1692.7 807 Rt. 9W Tomkins Cove NNW RIVER RIVER 1609.3 4 River Rd. Tomkins Cove B-54

APPENDIX C HISTORICAL TRENDS

APPENDIX C The past ten years of historical data for various radionuclides and media are presented both in tabular form and in graphical form to facilitate the comparison of 2006 data with historical values. Although other samples were taken and analyzed, values were only tabulated and plotted where positive indications were present.

Averaging only the positive values in these tables can result in a biased high value, especially, when the radionuclide is detected in only one or two quarters for the year.

C-1

TABLE C-1 DIRECT RADIATION ANNUAL

SUMMARY

1996-2006 Average Quarterly Dose (mR/Quarter)

YerInner Ring Outer Rin Contrc

............. Locatic 1996 14.0 14.0 16.0 1997 15.0 15.0 18.0 1998 14.0 15.0 16.0 1999 15.0 15.0 16.0 2000 14.0 15.0 16.0 2001 15.0 15.0 17.0 2002 15.0 15.0 14.0 2003 14.3 13.9 14.7 2004 13.0 13.0 14.0 2005 14.1 14.1 15.9 2006 13.9 14.3 17.5 Historical Average 14.3 14.5 15.9 1996-2005 C-2

FIGURE C-1 DIRECT RADIATION 40.0 MInner Ring 35.0 EOuter Ring

- Control Location 30.0

, 25.0 I-0 20.0 E

cc 1E 15.0 10.0 5.0 0.0 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 C-3

TABLE C-2 RADIONUCLIDES IN AIR 1996 to 2006 (OCi/m 3) 1996 0.01 0.01 <Lc 1997 0.01 0.01 <Lc <"Le 1998 0.02 0.01 1999 0.02 0.01 2000 0.01 0.01 2001 0.02 0.02 2002 0.02 0.02 2003 0.01 0.01 2004 0.01 0.01 2005 0.02 0.02 2006 0.01 0.01 < Lc < Lc istorical Average 0.02 0.01 <L Critical Level (L) is less than the ODCM required LLD.

<lc indicates no positive values above sample critical level.

C-4

FIGURE C-2 RADIONUCLIDES IN AIR - GROSS BETA 1996 to 2006 0.05 BAll ODCM Indicator Locations

-Control Location 0.04-0.03 -

aE 0.02 i/ 05y, 0.01 0.00 1996 1997 KAMM 1998 i04i NAAA, 1999 2000 2001 2002 2003 2004 a

.w.4r.,idm.

2005 no 2006

Includes ODCM and non-ODCM indicator locations.

3 Gross Beta ODCM required LLD = 0.01 pCi/m C-5

TABLE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 1996 to 2006 (pCi/L) 1996 < C 280 < Lc <KL 1997 430 <L,

<K 1998 220 <K <K

<Lc

<K <K 1999 191 318 2000 190 267 <K

<L " Lc

<"L

<K <K 2001 < L4 323

" Lc 2002 432 562 <K 2003 " Lc < Lc

" Lc

" Lc <Lc 2004 553 2005 " Le <Lc 618 2006 < Lc 386 < Lc < Lc 19205 1< Lc < Lc Critical Level (LK)is less than the ODCM required LLD.

<lK indicates no positive values above sample critical level.

C-6

FIGURE C-3 HUDSON RIVER WATER - TRITIUM 1996 to 2006 2000 1800-Inlet (H-3) 1800 0 Discharge (H-3) 1600 1400 1200 G 1000 a.

800 600 400 200 0 F I.. .

1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Tritium ODCM required LLD = 3000 pCi/L C-7

TABLE C-4 RADIONUCLIDES IN DRINKING WATER 1996 to 2006 f(Ci/L) 1996 " Lc <Lc 1997 " LC <K 1998 " Lc <L, 1999 " Lc <Lc 2000 " LC <K 2001 " Le <Lc 2002 " Lc <Lc 2003 < L, <K 2004 " Le <"

<KL 2005 " Lc 2006 < Lc < Lc

<L <Lc Critical Level (L) is less than the ODCM required LLD.

<lc indicates no positive values above sample critical level.

C-8

FIGURE C-4 DRINKING WATER - TRITIUM 1996 to 2006 2000 1800 1600 1400 1200 C.1 1000 0.

NO IDENTIFIED TRITIUM IN PREVIOUS TEN YEAR HISTORY 800 600 400 200 0

1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Tritium ODCM required LLD = 2000 pCi/L C-9

TABLE C-5 RADIONUCLIDES IN SHORELINE SOIL 1996 to 2006 (pCi/Kg, dry) 1996 <" <L 173 453 1997 <" <Lc 203 340 1998 <L, 143 <K 1999 46 200 238 2000 58 179 231 2001 45 230 427 2002 <Lc 221 238 2003 124 73 2004 104 138 2005 < Lc < Lr 174 2006 < Lc < Lc 119.6 < Lc Historical Average< Lc 175 257 1996-'gO Critical Level (L) is less than the RETS required LLD.

<Lc indicates no positive values above sample critical level.

C-10

FIGURE C-5 RADIONUCLIDES IN SHORELINE SOIL 1500 1400 MIndicator (Cs-1 34) 1300 E] Control (Cs-134) 1200 FIndicator (Cs-137) 1100

-Control (Cs-137) 1000 900 800 I..

700 600 500 400 300 200 100 0

1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Cs-1 34 ODCM required LLD = 150 pCi/Kg, dry Cs-1 37 ODCM required LLD = 175 pCi/Kg, dry C-11

TABLE C-6 RADIONUCLIDES IN BROAD LEAF VEGETATION 1996 to 2006 (pCi/Kg, wet) 1996 17 1997 1998 1999 27 2000 28 2001 7 2002 14 16 2003 14 2004 10 2005 2006 < Lc < Lc 15 22 Critical Level (I) is less than the ODCM required LLD.

<Lc indicates no positive values above sample critical level.

C-12

FIGURE C-6 BROAD LEAF VEGETATION - Cs-137 1996 to 2006 100 80 60 C.

40 20:

01___ :J2222X7 __

0:-!!:

1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 ODCM required LLD = 80 pCi/Kg, wet C-1 3

TABLE C-7 RADIONUCLIDES IN FISH AND INVERTEBRATES 1996 to 2006 1996 " Le

<L

" Lc 1997

< L,;

1998

" Lc 1999

" Lc 2000

" Lc 2001

"<Lc

" Lc 2002

"<L 2003 "<L 2004 "<L 2005 "<1/4 2006 < Lc < Lc

< Lc < Lc Critical Level (L.) is less than the ODCM required LLD.

<1K indicates no positive values above sample critical level.

C-14

FIGURE C-7 FISH AND INVERTEBRATES - Cs-137 1995 to 2005 200 ED Indicator (Cs-137) 180 El Control (Cs-1 37) 160 140 120 I00 CB 100-0.

80-60 -

40 20 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Cs-137 ODCM required LLD = 150 pCi/Kg, wet C-1 5

APPENDIX D RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM QUALITY ASSURANCE - QUALITY CONTROL PROGRAM

D) QA/QC PROGRAM

1) PROGRAM DESCRIPTION The Offsite Dose Calculation Manual (ODCM), Part 1, Section 5.3 requires that the licensee participate in an Interlaboratory Comparison Program. The Interlaboratory Comparison Program shall include sample media for Which samples are routinely collected and for which comparison samples are commercially available. Participation in an Interlaboratory Comparison Program ensures that independent checks on the precision and accuracy of the measurement of radioactive material in the environmental samples are performed as part of the Quality Assurance Program for environmental monitoring. To fulfill the requirement for an Interlaboratory Comparison Program, the JAF Environmental Laboratory has engaged the services of two independent laboratories to provide quality assurance comparison samples. The two laboratories are Analytics, Incorporated in Atlanta, Georgia and the U.S.

Department of Commerce's National Institute of Standards and Technology (NIST) in Gaithersburg, Maryland.

Analytics supplies sample media as blind sample spikes, which contain certified levels of radioactivity unknown to the analysis laboratory. These samples are prepared and analyzed using standard laboratory procedures. The results are submitted to Analytics, which issues a statistical summary report. The JAFNPP Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratory's performance for Analytic's sample results.

In addition to the Analytics Program, the JAF Environmental Laboratory participates in the NEI/NIST Measurement Assurance Program. In 1987, the nuclear industry established a Measurement Assurance Program at the National Bureau of Standards (now the National Institute of Standards and Technology) to provide sponsoring nuclear utilities an independent verification, traceable to NIST, of their capability to make accurate measurements of radioactivity, as described in NRC Regulatory Guide 4.15.

The program includes distribution to sponsoring utilities, approximately six times a year.

The samples are prepared by NIST to present specific challenges to participating laboratories. NIST supplies sample media as blind sample spikes. These samples are prepared and analyzed by the JAF Environmental Laboratory and the results are submitted to the Entergy Nuclear Northeast representative, who uses predetermined acceptance criteria methodology for evaluating the laboratory's performance. The performance results along with the NIST Report of Test (Certifies what activities are present in the sample) are forwarded to the laboratory.

D-1

2) PROGRAM SCHEDULE Water Gross Beta 1 Water Tritium 4 Water 1-131 2 Water Mixed Gamma 2 Air Gross Beta 2 Air 1-131 2 Air Mixed Gamma 3 Milk 1-131 2 Milk Mixed Gamma 2 Soil Mixed Gamma 1 Vegetation Mixed Gamma 1 TOTAL SAMPLE INVENTORY 22

3) ACCEPTANCE CRITERIA Each sample result is evaluated to determine the accuracy and precision of the laboratory's analysis result. The sample evaluation method is discussed below.

a) SAMPLE RESULTS EVALUATION Samples provided by Analytics and NIST are evaluated using what is specified as the NRC method. This method is based on the calculation of the ratio of results reported by the participating laboratory (QC result) to the Vendor Laboratory Known value (reference result).

D-2

An Environmental Laboratory analytical result is evaluated using the following calculation:

The value for the error resolution is calculated.

The error resolution = Reference Result Reference Results Error (1 sigma)

Using the appropriate row under the Error Resolution column in Table 8.3.1 below, a corresponding Ratio of Agreement interval is given.

The value for the ratio is then calculated.

Ratio = QC Result of Agreement Reference Result If the value falls within the agreement interval, the result is acceptable.

TABLE 8.3.1

<4 No Comparison 4 to 7 0.5-2.0 8 to 15 0.6-1.66 16 to 50 0.75-1.33 51 to 200 0.8-1.25

>200 0.85-1.18 This acceptance test is generally referred to as the "NRC" method. The acceptance criteria is contained in Procedure EN-CY-102. The NRC method generally results in an acceptance range of approximately +/- 25% of the Known value when applied to sample results from the Analytics and NIST Interlaboratory Comparison Program.

This method is used as the procedurally required assessment method and requires the generation of a deviation from QA/QC program report when results are unacceptable.

D-3

4) PROGRAM RESULTS

SUMMARY

The Interlaboratory Comparison Program numerical results are provided on Table 8-1.

a) ANALYTICS QA SAMPLES RESULTS Twenty QA blind spike samples were analyzed as part of Analytics 2006 Interlaboratory Comparison Program. The following sample media were evaluated as part of the comparison program.

Air Charcoal Cartridge: 1-131

Air Particulate Filter: Mixed Gamma Emitters, Gross Beta

" Water: 1-131, Mixed Gamma Emitters, Tritium, Gross Beta

" Soil: Mixed Gamma Emitters

Milk: 1-131, Mixed Gamma Emitters

Vegetation: Mixed Gamma Emitters The JAF Environmental Laboratory performed 84 individual analyses on the 20 QA samples. Of the 84 analyses performed, 82 were in agreement using the NRC acceptance criteria for a 97.6% agreement ratio.

There were two non-conformities in the 2006 program.

(i) ANALYTICS SAMPLE NONCONFORMITIES Analytics Sample E4882-05, Ce-141 in Water Nonconformity No. 2006-01 A spiked mixed gamma in water sample supplied by Analytics, Inc., was analyzed in accordance with standard laboratory procedures. The sample contained a total of ten radionuclides for analysis. Ten of the ten radionuclides present were quantified. Nine of the ten radionuclides were quantified within the acceptable range. The mean result for Ce-141 was determined to be outside the QA Acceptance Criteria resulting in a sample nonconformity. The water sample was analyzed three times using three different detectors. An average Ce-141 value of 64.8 pCiIL was reported.

The known result for the sample was 86.8 pCi/L as determined by the supplier. One of the three reported results was 72 pCi/L and resulted in an agreement when compared to the known of 86.8 pCi/L with a ratio of 0.83. The remaining 2 individual results were outside the acceptance criteria and had ratios to the known that ranged from 0.67 and 0.74. All of the analysis had relatively low count rate, which ranged from 3.9 counts per minute to 4.9 counts per minute.

An evaluation of the Ce- 141 result was performed. The detector calibrations were reviewed to determine if the efficiency determination in the lower end (<500 KeV) of the calibration curve exhibited any D-4

anomalies. The efficiency curve evaluation showed that shape of the curve and the corresponding efficiency coefficients were within the normal range and compared favorably with the previous calibration. The spectrum and peak search results were examined with no abnormalities identified. Ce-141 decays by beta minus with a 32.5 day half-life and a gamma ray energy of 145 KeV with a yield of 48%. No significant secondary gamma energies are produced in the Ce-141 decay scheme.

The combination of low sample activity and low net counts most likely resulted in an inaccurate sample result. The nonconforming analytical results for this sample media and radionuclide are not routine and does not indicate a programmatic deficiency in the analysis of Ce-141 in water samples or other environmental media. Confidence in the accurate analysis of Ce-141 can be demonstrated by other Ce-141 analytical results. The Ce- 141 results for the other Quality Assurance samples analyzed as part of the 2006 Interlaboratory Comparison Program were all acceptable and are summarized below. These results demonstrate that at the time of sample analysis the gamma spectral analysis system was performing properly and was in control.

2006 Ce-141 Results SapeIi5 _ Mediuiiii~ JAF Reeec ~Ratio.

E4883-05 Filter pCi/filter 58.6 +/- 1.6 61.4 +/- 1 0.95 E5002-05 Milk pCi/liter 185.7 + 4.0 184 +/- 3.1 1.01 E5003-05 Soil pCi/g 0.241 + 0.008 0.214 +/- 0.004 1.13 E5005-05 Vegetation pCi/g 0.209 + 0.007 0.223 +/- 0.004 0.94 E5076-05 Water pCi/liter 94.2 + 2.61 88.0 +/- 1.47 1.07 E5077-05 Filter pCi/filter 80.3 + 1.41 78.6 +/- 1.13 1.02 E5078-05 Milk pCi/liter 86.7 + 2.76 86.0 +/- 1.44 1.01 E4963-09

Milk pCi/liter 98.4 +/- 3.95 104 +/- 1.5 0.94 E4997-09

Water pCi/liter 160 + 19 149 +/- 2.5 1.07 E5073-09

Vegetation pCi/g 0.162 + 0.003 0.153 +/- 0.002 1.06 E5170-09

Water pCilliter 284.3 + 5.6 286 +/- 5.0 0.99 Mean Ratio = 1.02

Provided by laboratory client, NOT reported in Annual Report These results demonstrate that at the time of sample analysis the gamma spectral analysis system was performing properly and was in control.

Historical results from the 2005 Interlaboratory Comparison program demonstrated the laboratory's ability to analyze Ce-141 accurate in low level environmental sample media. These results are summarized below:

D-5

2005 Ce-141 Results

.Sample ID M...d.ium. JI Reference Ratio E-4488-05 Water pCi/liter 235+/-6 221-4 1.06 E-4713-05 Water pCi/liter 291+/-4 282+/-5 1.03 E-4489-05 Filter pCi/filter 157+/-3 155+/-3 1.01 E-4714-05 Filter pCi/filter 176+/-3 165+/-3 1.07 E-4585 Soil pCi/kg 173+/-2 182+/-3 0.95 E-4584-05 Milk pCi/liter 101+/-5 92+/-2 1.09 E-4715-05 Milk pCi/liter 237+/-4 233+/-4 1.02 E-4587 Vegetation pCi/kg 178+/-9 174+/-3 1.02 NIST 1801-20 Filter pCi/filter 1.89E5+/-475 1.96E5+/-2176 0.96 NIST-1800-10 Water pCi/G 1.47E5+/-441 1.48E5+/-1125 0.99 Mean Ratio = 1.02 The mean ratio for these samples relative to the known (reference) value was 1.02. The 2006 nonconformity is considered to be an isolated instance. The Ce-141 results for 2005 and 2006 program demonstrate that there is no systematic error or persistent low bias present in the analysis of samples for Ce- 141 in water or other environmental sample media. No corrective actions were implemented as a result of this nonconformity.

Analytics Sample E5221-05, Gross Beta in Water Nonconformity No. 2006-02 A water sample, spiked with Cs-137, supplied by Analytics was analyzed for gross beta activity in accordance with standard laboratory procedures.

Half of the 1 liter sample provided was evaporated such that any remaining residue would remain in a 2 inch stainless steel planchet. The planchet was then counted 3 times on a low background counter (LBC).

An average Gross Beta value of 173 pCi/L was determined and reported for the sample. The known value for the sample was 249 pCi/L as determined by Analytics. The acceptable ratio of agreement for this sample was determined to be 0.8 to 1.25. The calculated ratio of sample results divided by the known value was 0.69, which fell outside the QA Acceptance Criteria. An investigation into the QA nonconformity was initiated.

A thorough review of all raw data and calculations used to determine the reported gross beta value was conducted with no errors noted. The original stainless steel planchet was then reanalyzed on a different LBC with no appreciable difference in the resulting gross beta value.

D-6

The remaining 500ml of E5221-05 was then analyzed by gamma spectroscopy, which confirmed Analytics known Cs- 137 activity.

Following the confirmation of the samples Cs-137 concentration, a duplicate gross beta analysis was performed on the remaining sample in accordance with standard laboratory procedures. A value of 245 pCi/L was obtained on the backup gross beta analysis, equivalent to 98%

recovery of the known value.

Based on the difference between the initial and backup results, it is believed that some of the sample residue was removed from the original stainless steel planchet prior to counting. The missing material equates to 26cpm or 68dpm. All equipment used to process the original sample was checked for loose radioactive material, none was detected. The following procedure revision has been submitted to address this nonconformity:

Add "Use caution when evaporating samples. Boiling or spattering may cause substantial sample losses and cross-contamination."

Historical Water Gross Beta Results Sam~ple ifr I Mdiuml LAI?

J F Reference Ratio QAP-58 (2003) Water Bq/liter 588+/-7 627+/-10 0.937 QAP-59 (2003) Water Bq/liter 1796+/-17 1948+/-195 0.922 QAP-0403 (2004) Water Bq/liter 1105+/-17 1170+/-117 0.944 A19773-05 (2005) Water pCi/ml 1802+/-2 1830+/-46 0.985 E4458-80 (2005) Water pCi/L 260+/-_1.4 268+/-8.9 0.970 Mean Ratio = 0.95 The mean ratio for these samples relative to the known (reference) value was 0.95. The 2006 nonconformity is considered to be an isolated instance. The results for 2003 through 2005 demonstrate that there is no systematic error present in the analysis of samples for gross beta in water.

b) NIST QA SAMPLES RESULTS In 2006, JAF Environmental Laboratory participated in the NETNIST Measurement Assurance Program. Two QA blind spike samples were analyzed. The following sample media were evaluated as part of the comparison program.

Air Particulate Filter: Mixed Gamma Emitters

Water: 1-131, Tritium The JAF Environmental Laboratory performed 7 individual analyses on the two QA samples. Of the 7 analyses performed, 7 were in agreement using the NRC acceptance criteria for a 100% agreement ratio.

There were no non-conformities in the 2006 program.

D-7

c) NUMERICAL RESULTS TABLES TABLE D- 1 INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filter REFERENCE SAMPLE JAF LAB LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi/filter +/-1 sigma pCi/filter +/-2 sigma (1) EVALUATION 6/8/2006 E5001-05 Filter Gross Beta 64.8 +/- 1.20 60.0 +/- 2.00 1.08 Acceptable 12/7/2006 E5171-05 Filter Gross Beta 99.5 +/- 1.45 86.0 +/- 2.87 1.16 Acceptable (1) Ratio = Reported/Analytics (See Section 8.3).

Sample provided by Analytics, Inc.

Tritium Analysis of Water REFERENCE SAMPLE JAF LAB LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +2 sigma (1) EVALUATION 3/23/2006 E4881-05 Water H-3 4530 _ 107 4210 +/- 140 1.08 Acceptable 7/14/2006 E5059-05 Water H-3 933 - 84 750 +/- 25 1.24 Acceptable 9/14/2006 E5080-05 Water H-3 832 - 82 903 +/- 30 0.92 Acceptable (1) Ratio = Reported/Analytics (See Section 8.3).

Sample provided by Analytics, Inc.

Gross Beta Analysis of Water REFERENCE SAMPLE JAF LAB LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-2 sigma (1) EVALUATION 12/7/2006 E5221-05 Water Gross Beta 173.0 +/- 2.18 249 _ 8.29 0.69 Not Acceptable (1) Ratio = Reported/Analytics (See Section 8.3).

Sample provided by Analytics, Inc.

1-131 Gamma Analysis of Air Charcoal REFERENCE SAMPLE JAF LAB LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi +/-1 sigma pCi +/-2 sigma (1) EVALUATION 6/8/2006 E5004-05 Air 1-131 63.3 +/- 2.42 66.0 +/- 2.20 0.96 Acceptable 9/14/2006 E5079-05 Air 1-131 97.2 +/- 2.5 91.9 +/- 3.06 1.06 Acceptable (1) Ratio = Reported/Analytics (See Section 8.3).

Sample provided by Analytics, Inc.

D-8

TABLE D-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water REFERENCE SAMPLE JAF LAB LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-2 sigma (1) EVALUATION 3/23/2006 E4882-05 Water Ce-141 64.8 +/- 3.7 86.8 _ 2.9 0.75 Not Acceptable Cr-51 263.0 +/- 17.8 234.0 _ 7.8 1.12 Acceptable Cs-134 107.0 +/- 3.4 101.0 _ 3.4 1.06 Acceptable Cs-137 71.8 +/- 2.9 74.3 _ 2.5 0.97 Acceptable Co-58 79.0 +/- 3.1 87.5 +/- 2.9 0.90 Acceptable Mn-54 85.1 +/- 3.1 78.1 _ 2.6 1.09 Acceptable Fe-59 79.5 +/- 3.6 72.4 _ 2.4 1.10 Acceptable Zn-65 156.0 +/- 6.3 148.0 _ 4.9 1.05 Acceptable Co-60 104.0 +/- 2.5 107.0 _ 3.6 0.97 Acceptable 1-131** 71.9 +/- 0.9 67.4 _ 2.3 1.07 Acceptable 9/14/2006 E5076-05 Water Ce-141 94.2 +/- 2.6 88.0 - 2.9 1.07 Acceptable Cr-51 288.7 +/- 13.1 288.0 _ 9.6 1.00 Acceptable Cs-134 94.1 _ 1.9 87.0 _ 2.9 1.08 Acceptable Cs-137 173.0 +/- 2.4 179.0 _ 6.0 0.97 Acceptable Co-58 115.0 +/- 2.1 112.0 _ 3.7 1.03 Acceptable Mn-54 124.3 +/- 2.1 115.0 _ 3.8 1.08 Acceptable Fe-59 47.9 + 1.9 44.7 _ 1.5 1.07 Acceptable Zn-65 148.0 +/- 3.9 148.0 _ 4.9 1.00 Acceptable Co-60 139.0 +/- 1.7 137.0 _ 4.6 1.01 Acceptable I-131** 86.1 _ 1.2 79.9 - 2.66 1.08 Acceptable (1) Ratio = Reported/Analytics (See Section 8.3).

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

D-9

TABLE D-I (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Milk REFERENCE SAMPLE JAF LAB LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +2 sigma (1) EVALUATION 6/8/2006 E5002-05 Milk Ce-141 185.7 +/- 4.0 184.0 _ 6.1 1.01 Acceptable Cr-51 257.7 +/- 16.9 259.0 _ 8.6 0.99 Acceptable Cs-134 128.0 +/- 3.0 127.0 + 4.2 1.01 Acceptable Cs-137 112.7 +/- 2.8 117.0 _ 3.9 0.96 Acceptable Co-58 98.8 +/- 2.6 100.0 _ 3.3 0.99 Acceptable Mn-54 153.3 +/- 3.2 146.0 +/- 4.9 1.05 Acceptable Fe-59 94.8 +/- 3.4 93.6 +/- 3.1 1.01 Acceptable Zn-65 191.0 +/- 6.0 185.0 - 6.2 1.03 Acceptable Co-60 127.3 +/- 2.3 129.0 _ 4.3 0.99 Acceptable 1-131** 61.9 +/- 0.9 63.2 _ 2.1 0.98 Acceptable 9/14/2006 E5078-05 Milk Ce-141 86.7 +/- 2.8 86.0 _ 2.9 1.01 Acceptable Cr-51 285.3 +/- 14.2 282.0 + 9.4 1.01 Acceptable Cs-134 89.5 +/- 2.2 85.0 _ 2.8 1.05 Acceptable Cs-137 170.0 +/- 2.4 175.0 +/- 5.8 0.97 Acceptable Co-58 105.0 +/- 2.3 109.0 _ 3.7 0.96 Acceptable Mn-54 117.7 +/- 2.2 113.0 +/- 3.8 1.04 Acceptable Fe-59 47.5 +/- 2.4 43.7 +/- 1.5 1.09 Acceptable Zn-65 147.7 +/- 4.2 145.0 +/- 4.8 1.02 Acceptable Co-60 129.3 +/- 1.8 134.0 _ 4.5 0.97 Acceptable I-131** 72.7 +/- 1.3 73.8 +/- 2.46 0.99 Acceptable (1) Ratio = Reported/Analytics (See Section 8.3).

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

D-10

TABLE D-l (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filters REFERENCE SAMPLE JAF LAB LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi/filter+/-l sigma pCi/filter +/-2 sigma (1) EVALUATION 3/23/2006 E4883-05 Filter Ce-141 58.6 _ 1.60 61.4 - 2.05 0.95 Acceptable Cr-51 169.0 - 10.3 166.0 - 5.52 1.02 Acceptable Cs-134 74.0 +/- 3.90 71.5 - 2.38 1.03 Acceptable Cs-137 51.8 - 2.10 52.5 - 1.75 0.99 Acceptable Co-58 60.5 - 2.40 61.9 +/- 2.06 0.98 Acceptable Mn-54 61.5 - 2.40 55.3 - 1.84 1.11 Acceptable Fe-59 55.6 - 2.90 51.3 - 1.71 1.08 Acceptable Zn-65 115.0 - 5.50 104.0 - 3.48 1.11 Acceptable Co-60 72.5 - 2.10 75.6 +/- 2.52 0.96 Acceptable 9/14/2006 E5077-05 Filter Ce-141 80.3 - 1.41 78.6 - 2.62 1.02 Acceptable Cr-51 266.3 - 9.88 257.0 - 8.57 1.04 Acceptable Cs-134 84.1 - 2.03 77.7 - 2.59 1.08 Acceptable Cs-137 159.7 - 2.24 160.0 - 5.33 1.00 Acceptable Co-58 101.3 - 2.03 99.8 - 3.33 1.01 Acceptable Mn-54 112.0 - 2.01 103.0 - 3.42 1.09 Acceptable Fe-59 46.1 - 1.98 39.9 - 1.33 1.15 Acceptable Zn-65 147.7 - 4.09 132.0 - 4.41 1.12 Acceptable Co-60 119.7 - 1.71 122.0 - 4.07 0.98 Acceptable (1) Ratio = Reported/Analytics (See Section 8.3).

Sample provided by Analytics, Inc.

Gamma Analysis of Soil REFERENCE SAMPLE JAF LAB LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi/gram 1+sigma pCi/gram +/-2 sigma (1) EVALUATION 6/8/2006 E5003-05 Soil Ce-141 0.241 +/- 0.008 0.214 +/- 0.007 1.13 Acceptable Cr-51 0.349 +/- 0.036 0.302 +/- 0.010 1.16 Acceptable Cs-134 0.162 +/- 0.006 0.147 +/- 0.005 1.10 Acceptable Cs- 137 0.249 +/- 0.007 0.237 +/- 0.008 1.05 Acceptable Co-58 0.114 +/- 0.004 0.117 +/- 0.004 0.97 Acceptable Mn-54 0.185 +/- 0.006 0.170 +/- 0.006 1.09 Acceptable Fe-59 0.120 +/- 0.007 0.109 +/- 0.004 1.10 Acceptable Zn-65 0.236 +/- 0.010 0.216 +/- 0.007 1.09 Acceptable Co-60 0.155 +/- 0.004 0.150 +/- 0.005 1.04 Acceptable (1) Ratio = Reported/Analytics (See Section 8.3).

Sample provided by Analytics, Inc.

D-11

TABLE D- 1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation REFERENCE SAMPLE JAF LAB LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi/gram +1 sigma pCi/gram +/-2 sigma (1) EVALUATION 6/8/2006 E5005-05 Vegetation Ce-141 0.209 +/- 0.007 0.223 +/- 0.007 0.94 Acceptable Cr-51 0.293 +/- 0.034 0.315 +/- 0.011 0.93 Acceptable Cs-134 0.159 +/- 0.007 0.154 +/- 0.005 1.03 Acceptable Cs-137 0.127 +/- 0.006 0.143 +/- 0.005 0.89 Acceptable Co-58 0.109 +/- 0.006 0.122 +/- 0.004 0.90 Acceptable Mn-54 0.160 +/- 0.006 0.178 +/- 0.006 0.90 Acceptable Fe-59 0.105 +/- 0.008 0.114 +/- 0.004 0.92 Acceptable Zn-65 0.207 +/- 0.013 0.225 +/- 0.008 0.92 Acceptable Co-60 0.140 +/- 0.005 0.156 +/- 0.005 0.90 Acceptable (1) Ratio = Reported/Analytics (See Section 8.3).

Sample provided by Analytics, Inc.

D-12

TABLE D-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Analysis of water SAMPLE JAF LAB REFERENCE LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi/gram +/-1 sigma pCi/gram +2 sigma (1) EVALUATION 2/15/2006 1831-3 Water 1-131 2.06E+06 +/- 2.77E+04 2.09E+06 +/- 1.47E+04 0.99 Acceptable H-3 1.12E+06 +/- 3.11E+03 1.11E+06 +/- 8.86E+03 1.01 Acceptable (1) Ratio = Reported/NIST (See Section 8.3).

Sample provided by NIST Gamma Analysis of Filter SAMPLE JAF LAB REFERENCE LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi/filter +1 sigma pCi/filter +2 sigma (1) EVALUATION 6/8/2006 1851-16 Filter Mn-54 3.08E+04 +/- 158 2.80E+04 +/- 280 1.10 Acceptable Co-57 3.74E+04 +/- 94 3.36E+04 +/- 336 1.11 Acceptable Fe-59 1.01E+05 +/- 1418 8.91E+04 +/- 891 1.13 Acceptable Se-75 5.24E+04 +/- 508 5.61E+04 +/- 561 0.93 Acceptable Cs-134 3.OOE+04 +/- 143 2.76E+04 +/- 276 1.09 Acceptable (I) Ratio = Reported/NIST (See Section 8.3).

Sample provided by NIST D-13

REFERENCES Radioactivity and Radiochemistry, The Counting Room: Special Edition, 1994 Caretaker Publications, Atlanta, Georgia.

Data Reduction and Error Analysis for the Physical Sciences, Bevington P.R., McGraw Hill, New York (1969).3 D-14

NL-07-064, Annual Radiological Environmental Operating Report for the Period January 1, 2006 Through December 31, 2006

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NL-07-064, Annual Radiological Environmental Operating Report for the Period January 1, 2006 Through December 31, 2006

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Subject:

SUMMARY

2.0 INTRODUCTION

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