NL-08-081, Annual Radiological Environmental Operating Report for 2007

Annual Radiological Environmental Operating Report for 2007

ML081420476
Person / Time
Site:	Indian Point
Issue date:	05/15/2008
From:	Robert Walpole Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-08-081
Download: ML081420476 (151)

Text

Indian Point Energy Center 450 Broadway, GSB P.O. Box 249

.lt&W Buchanan, N.Y. 10511-0249 Tel (914) 734-6710 Robert Walpole Manager, Licensing May 15, 2008 Re:

Indian Point Units 1, 2 & 3 Docket Nos.50-003, 50-247, 50-286 NL-08-081 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001

Subject:

Indian Point Nuclear Power Plants Units 1, 2 and 3 Annual Radiological Environmental Operating Report for 2007 Dear Sir or Madam; Enclosed please find one copy of the Entergy Nuclear Operations, Inc. (Entergy) Indian Point Energy Center (IPEC) site Annual Radiological Environmental Operating Report for the period January 1, 2007 to December 31, 2007.

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. No commitments are being made by this report.

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

Sincerely yours, Lobert Walpo e Manager, Licensing Indian Point Energy Center Enclosure cc: w/o enclosure Mr. John P. Boska, Senior Project Manager, NRC NRR DORL Mr. Samuel J. Collins, Regional Administrator, NRC Region 1 NRC Resident Inspector's Office Indian Point Mr. Paul Eddy, New York State Department of Public Service Mr. Paul D. Tonko, President NYSERDA Mr. Tim Rice, New York State DEC

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ENTERGY NUCLEAR 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, 2007

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 3-3 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 3-4 3.3.10 Precipitation 3-4 3.3.11 Soil 3-4 3.3.12 Groundwater Samples 3-4 3.3.13 Land Use Census 3-4 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

TABLE OF CONTENTS (continued)

Page 4.0 RESULTS AND DISCUSSION 4-1 4.1 Direct Radiation 4-3 4.2 Airborne Particulates and Radioiodine 4-4 4.3 Hudson River Water 4-5 4.4 Drinking Water 4-5 4.5 Hudson River Shoreline Soil 4-5 4.6 Broad Leaf Vegetation 4-6 4.7 Fish and Invertebrates 4-6 4.8 Aquatic Vegetation 4-7 4.9 Hudson River Bottom Sediment 4-7 4.10 Precipitation 4-7 4.11 Soil 4-8 4.12 Groundwater 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, 1997 to 2007 0-3 C-2 Radionuclides in Air - Gross Beta, 1997 to 2007 C-5 C-3 Hudson River Water-Tritium, 1997 to 2007 0-7 C-4 Drinking Water - Tritium, 1997 to 2007 0-9 C-5 Radionuclides in Shoreline Soil, 1997 to 2007 C-1l1 C-6 Broad Leaf Vegetation - Cs-1 37, 1997 to 2007 C-13 C-7 Fish and Invertebrates - Cs-1 37, 1997 to 2007 C-15 iii

LIST OF TABLES TABLE TITLE Page 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, 2007 B-2 B-la 2007 Air Sampling Deviations B-3 B-lb 2007 TLD Deviations B-3 B-Ic 2007 Other Media Deviations B-3 B-2 ODCM Annual Summary, 2007 B-4 B-3 2007 Direct Radiation, Quarterly Data B-9 B-4 Direct Radiation, 1997 through 2007 Data B-10 B-5 2007 Direct Radiation, Inner and Outer Rings B-11 B-6 Environmental Airborne Particulate Samples - 2007 Gross Beta Activity B-12 B-7 Concentrations of Gamma Emitters in Quarterly Composites of Air Particulate Samples, 2007 B-14 B-8 Environmental Charcoal Cartridge Samples - 2007 1-131 Activity B-16 B-9 Concentrations of Gamma Emitters in Surface Water Samples, 2007 B-18 B-10 Concentrations of Tritium in Surface Water Samples, 2007 B-20 B-11 Concentrations of Gamma Emitters in Drinking Water Samples, 2007 B-21 B-12 Concentrations of Tritium in Drinking Water Samples, 2007 B-23 B-13 Concentrations of Radionuclides in Shoreline Soil Samples, 2007 B-24 B-14 Concentrations of Gamma Emitters in Broad Leaf Vegetation Samples, 2007 B-26 iv

LIST OF TABLES (Continued)

TABLE TITLE Page B-15 Concentrations of Radionuclides in Fish Samples, 2007 B-35 B-16 Concentrations of Gamma Emitters in Aquatic Vegetation Samples, 2007 B-40 B-1 7 Concentrations of Gamma Emitters in Bottom Sediment Samples, 2007 B-41 B-18 Concentrations of Radionuclides in Rainwater Samples, 2007 B-43 B-19 Concentrations of Gamma Emitters in Soil Samples, 2007 B-45 B-20 Concentrations of Gamma Emitters in Surface Water Samples, 2007 B-46 B-21 Concentrations of Radionuclides in Monitoring Well Samples, 2007 B-49 B-22 Milch Animal Census, 2007 B-62 B-23 Land Use Census, 2007 B-64 C-1 Direct Radiation Annual Summary, 1997 to 2007 C-2 C-2 Radionuclides in Air, 1997 to 2007 C-4 C-3 Radionuclides in Hudson River Water, 1997 to 2007 C-6 C-4 Radionuclides in Drinking Water, 1997 to 2007 C-8 C-5 Radionuclides in Shoreline Soil, 1997 to 2007 C-10 C-6 Radionuclides in Broad Leaf Vegetation, 1997 to 2007 C-12 C-7 Radionuclides in Fish and Invertebrates, 1997 to 2007 C-14 D-1 QA Program Schedule D-2 D-2 Ratio of Agreement D-3 D-3 Interlaboratory Comparison Program D-5 V

SECTION I EXECUTIVE

SUMMARY

1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report (AREOR) contains descriptions and results of the 2007 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 and operated by Entergy Nuclear Operations, Inc. 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 adverse radiological impact to the surrounding environment attributed to Indian Point Station operations.

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 Manual, herein referred to as ODCM. This 2007 AREOR also contains summaries and discussions of the results of the 2007 program, trend analyses, potential impact on the environment, land use census, and interlaboratory comparisons.

During 2007, a total of 1312 analyses were performed. Table B-1 presents a summary of the collected sample analyses results.

An investigation of groundwater contamination with tritium and other radionuclides has been ongoing since 2005 and continued throughout 2007. 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.

Specifically, two new groundwater wells (non-drinking water) were 1-1

designated as "boundary wells" and were sampled as groundwater samples for tritium and strontium-90, as well as gamma spectroscopy analysis. These wells (MW-40 and MW-51) were designated as REMP sample stations 104 and 105. In addition, a change was made to the existing fish and invertebrate samples and shoreline soil samples.

The locations and frequency remained the same; however, strontium-90 was added to the required analyses. These additions were committed to in 2006 with the sampling and analyses conducted in 2007. These changes are captured in the ODCM. Groundwater sample results for 2007 are summarized in Table 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 2007 did not result in exposure to the public greater than environmental background levels.

1-2

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.

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 2-1

into indicator and control locations. Indicator locations are established near the site, where the 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 2007; however, residual radioactivity from atmospheric weapons tests and naturally occurring radioactivity were the predominant sources of radioactivity in the samples collected. Analysis of the 2007 REMP sample results supports the premise that radiological effluents were well below regulatory limits. -

2-2

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, with the exception of groundwater and fish/invertebrate samples.

The groundwater (monitoring well) samples are collected by a contracted environmental vendor, GZA Geo Environmental, Inc.

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 nearly all samples, except for groundwater samples and some tritium and strontium analyses on other media. These samples were analyzed at other New York State Department of Health Environmental Laboratory Approval Program (ELAP) certified laboratories.

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.

3-1

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.

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 composite sampler 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.

3.3.4 Drinkinq 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.

3-2

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.

3.3.6 Broad Leaf Veaetation 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 (Ic3).

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.

In 2007, additional sampling of fish was performed further upstream in the Hudson River, to confirm the acceptability of Roseton as the control location. Samples from all three locations were split with the US NRC and the New York State Department of Environmental Conservation.

The results of this effort are described in Section 4.0 of this report 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

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.

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.

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 Groundwater Samples Based on recent site hydrology evaluations and the addition of a number of groundwater sampling wells, two new monitoring wells were installed in 2006 and designated as REMP sample stations 104 (MW-

40) and 105 (MW-51). These wells have sample points at six different elevations which were specifically designed to be representative of groundwater moving towards the site boundary.

The locations of the groundwater samples are shown in Figure A-3.

Groundwater samples from these wells were obtained quarterly and analyzed for tritium, strontium-90 and by gamma spectroscopy.

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.

3-4

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 exists and confirmation through personnel such as feed suppliers who deal with farm animals and dairy associations (See Tables B-21 and B-22). 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-22.

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 (L)

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, 3-5

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 posteriori" (after the fact) limit for a particular measurement. Table A-2 presents the ODCM required LLDs for specific media and radionuclides as specified by the NRC. The LLDs actually achieved are usually much lower since the ODCM 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 + Tb/TI) 0°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 L, 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 Propaqated Error In accordance with program policy, recounts of positive samples are performed. When the initial count reveals the presence of radioactivity, 3-6

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:

N

>zxi N

where:

Xi value of each individual observation N.= number of observations PE= -=

N where:

ERR, = 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 NRCs. Branch Technical Position (BTP) to Regulatory Guide 4.8 (Reference, 14).

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 3-7

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 Lc 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 L. 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 1997 through 2006.

The 2007 average values are included in these historic tables for purposes of comparison.

3-8

SECTION 4 RESULTS AND DISCUSSION

4.0 RESULTS AND DISCUSSION The 2007 Radiological Environmental Monitoring Program (REMP) was conducted in accordance with Indian Point's Offsite Dose Calculation Manual 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 Groundwater 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 2007 and assessed the significance of the findings.

A summary of the results of the 2007 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.

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.

4-1

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.

The second group of radionuclides detected in 2007 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.

In 2007, the detected radionuclide that may be attributable to past atmospheric weapons testing consisted of Cs-137 in some media.

The levels detected were consistent with the historical levels of radionuclides resulting from weapons tests as measured in previous years.

The final group of radionuclides detected through the 2007 REMP comprises those that may be attributable to current plant operations.

During 2007, 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 groundwater boundary wells in 5 of 45 samples at levels which were much lower than the required Lower Limit of Detection (3000 pCi/Liter); however, they were detectable.

Cs-137 and Cs-134 are both produced in and released from fission reactors and were introduced into the environment from the accident at Chernobyl in 1986. Because Cs-134 has a short half-life relative to Cs-137, Cs-134 from Chernobyl is not likely to be present in 2007. Cs-137 is ubiquitous in the environment from atmospheric testing debris and a lesser amount from the Chernobyl accident. Strontium-90 (Sr-90) is also present in the environment from atmospheric testing debris. In 2007, there were several detections of Cs-137 in shoreline soil (2 indicator samples and one control sample),

aquatic vegetation (1 indicator station sample), bottom sediment (6 indicator and one control sample), soil (1 indicator location) and 5 groundwater samples. The fact that there was no Cs-134 present (recent plant releases 4-2

would contain Cs-134) and that there were detections also at control locations indicates that the activity was likely due to atmospheric weapons testing, with some contribution from plant releases from several years past.

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 2007.

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 radionuclides in the past. If Co-58 and Co-60 are concurrently detected in environmental samples, then the source of these radionuclides is considered to be from recent releases.

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 2007 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 2007 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.

4.1 Direct Radiation The environmental TLDs used to measure the direct radiation were TLDs supplied and processed by Framatome via the JAF Laboratory.

In 2007, 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 1997 through 2006.

The 2007 means are also presented in Table B-4. Table B-5 presents the 2007 TLD data for the inner ring and outer ring of TLDs.

The 2007 mean value for the direct radiation sample points was 14.3 mR per standard quarter. The mean value for the period 2000 through 2006 was 14.3 mR per standard quarter. At those locations where the 4-3

2007 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-

16) 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 14.4 mR per standard quarter and also average for the outer ring was 14.6 mR per standard quarter.

The control location average for 2007 was 18.8 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 2007 averages are consistent with the historical data. The 2007 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 2007 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.

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/m3 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 radionuclides 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 2007 gross beta concentration was consistent with historical levels.

Cs-1 37 has not 4-4

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 2007.

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 were detected in the Hudson River Water samples. Additionally, Table C-3 indicates the absence of Cs-1 37 which is consistent with historical data.

4.4 Drinking Water The annual program summary table (Table B-2) contains a summary of the 2007 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-12. 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 radionuclides, Cs-137 was identified in the Hudson River shoreline soil samples in 2007. 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 4-5

indicator locations. Cs-137 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-137 was 106 pCi/kg-dry with a maximum concentration of 149 pCi/kg-dry. The control location with one positive sample indicated 357 pCi/kg-dry.

An historical look at Cs-137 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-134 and Cs-137 are both discharged from the plant in similar quantities. The lack of Cs-134 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 Veqetation Table B-2 contains a summary of the broad leaf vegetation sample analysis results. Data from analysis of the 2007 samples are presented in Table B-14. Analyses of broad leaf vegetation samples revealed only naturally occurring radionuclides.

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-137 was not detected in 2007.

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 2007. There were no plant related radionuclides detected as a result of the GSA.

Strontium-90 was added to the analyte list in 2007. An intensive one-time sampling and analysis program was undertaken in the Spring to confirm the use of Roseton as a control location. Seven fish samples were taken from the indicator location and 5 from the control location.

An additional 5 samples were taken further upstream near Catskill, NY.

There were no plant related radionuclides or Strontium-90 detected in the samples above background. The US NRC and NYSDEC obtained splits of samples from all three locations and also analyzed them for strontium-90.

Their results were consistent with those obtained by Entergy.'

4-6

This intensive one time sampling and analysis program shows that there is no measurable impact on fish and invertebrates from Indian Point releases and that Roseton is a satisfactory control location. 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-16 contains the results of the analysis of aquatic vegetation samples for 2007.

Cs-137 was detected at one of one indicator station samples, and neither of the two control station samples. The concentration of Cs-137 in the indicator sample was 31 pCi/kg. Cs-134 was not detected in any aquatic vegetation samples.

While it is possible that the Cs-137 is from plant origin, the lack of Cs-134 suggests that the primary source of the Cs-137 is residual weapons test fallout.

This detection of Cs-137 in aquatic vegetation at the indicator location at such a low concentration 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 2007. Cs-137 was detected at 6 of 6 indicator station samples, and at one of 2 control station samples.

Cs-134 was not detected in any bottom sediment samples. The lack of Cs-134 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.

This detection of Cs-137 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 2007 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 2007. Other than naturally occurring radionuclides, no radionuclides were detected in precipitation samples.

4-7

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 2007. Other than naturally occurring radionuclides, only Cs-137 was detected in any of the soil samples. It was detected in one of two indicator samples at 136.5 pCi/kg, and not in the control sample. No Cs-134 was detected in any soil samples. The lack of Cs-134 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: This is also consistent with historical results over the last 10 years.

4.12 Groundwater A summary of the groundwater samples for 2007 is contained in Table B-2.

Data resulting from analysis of the groundwater samples for gamma emitters, tritium analysis, and Sr-90 are presented in Table B-21.

Tritium was detected at very low concentrations in 5 of the 45 groundwater samples analyzed. The amount detected ranged from 176

- 223 pCi/L and averaged 194 pCi/L which was well below the required LLD of 3000 pCi/L.

Other than tritium, Cs-137 and Ru-106 were the only other potentially plant-related radionuclides detected in the groundwater samples.

Cesium-137 was present in 5 of the 45 samples taken at an average concentration of 11.5 pCi/L.

The 5 positive Cs-137 sample results were all from MW-51 all on the same sample date. This data was investigated by Entergy and the offsite laboratory. No apparent reason for these positive results could be determined.

Follow-up samples collected a month later were all non-detect. Therefore these data are considered anomalous.

There was only one positive Ru-106 sample result out of the 45 samples taken. Since no other positive radionuclides were present in the sample, this result is also considered anomalous.

Sporadic detection of H-3, Sr-90 and Cs-137 is expected as these radionuclides are normally present in the environment as "background 4-8

radioactivity" as a consequence of both natural radioactivity and man-made activities un-related to the plant operations. The concentrations detected by this monitoring program are in the expected range of normal background and based on site hydrogeology are not likely a result of plant activities. Additionally, these detected concentrations well below any applicable or relevant regulatory standards.

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 2007 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, summer and fall.

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

4-9

Results:

A census was performed in the vicinity of Indian Point in 2007. 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 2007 census were generally same as the 2006 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 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 2007 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 2007 REMP reveal that operations at the station did not result in an adverse impact on the environment.

The 2007 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-137 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., Environmental Radioactivity, Academic Press, New York, 1987.

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-137 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.

5-1

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

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. U.S 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 theDepartment 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 Environmental Monitoring Blind Spike Program at IPEC" 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 2007 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 0DCM 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 3

DR8 Service Center Building Onsite -

0.35 Mi (SSE) at 1580 Direct Gamma Al Onsite - 0.28 Mi (SW) at Air Particulate 4_____

Al Algonquin Gas Line 24 aiidn Al 234' Radioiodine A4 Air Particulate 5

A4 NYU Tower Onsite - 0.88 Mi (SSW)

Radioiodine at 2080 DR10 Direct Gamma 7

Wbl Camp Field Reservoir 3.4 Mi (NE) at 51' Drinking Water 8

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 2730 RWae Wa2 Onsite -

HR Water 10 Discharge Canal (Mixing Zone)

Ost 0

D0.3 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 Marina) 1.5 Mi (5) at 1800 Air Particulate 22 Lovett Power Plant 1.6 Mi (WSW) at 2440 radiculdie 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 IbIl Downstream Downstream Fish & Invertebrates Air Particulate 27 Croton Point 6.36 Mi (SSE) at 1560 Radioiodine DR41 Direct Gamma HR Shoreline Soil 28 DR4 Lent's Cove 0.45 Mi (ENE) at 069' Direct Gamma 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 RJS = 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 179D 35 DR5 Broadway & Bleakley Avenue Onsite -

Direct Gamma 0.37 Mi (E) at 092D 38 DR34 Furnace Dock (Substation) 3.43 Mi (SE) at 1410 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 & 6th 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 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 62 DRI 9 Westbrook5.03 Mi (NE) at 062 Direct Gamma (near the Community Center)

Lincoln Road - Cortlandt 64 DR20 4.6 Mi (ENE) at 0670 Direct Gamma (School Parking Lot) 66 DR21 Croton Avenue - Cortlandt 4.87 Mi (E) at 083' 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 188° 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 226*

Direct Gamma Faldermeyer Drive 74 DR12 West Shore Drive - South 1.59 Mi (WSW) at 2520 Direct Gamma 75 DR31 Palisades Parkway 4.65 Mi (NW) at 225' Direct Gamma 76 DR1 3 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 79 DR30 Anthony Wayne Park 4.57 Mi (WNW) at 2960 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 80 DR15 Route 9W South of Ayers Road 11.02 Mi (NW) at 317° Direct Gamma 81 DR28 Palisades Pkwy - Lake Welch Exit 4.96 Mi (WSW) at 310' 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 339' 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 1185 Direct Gamma 89 DR35 Highland Ave & Sprout Brook Road 2.89 Mi (NNE) at 025' Direct Gamma (near rock cut) 90 DR3 Charles Point 0.88 Mi (NE) at 047° Direct Gamma 92 DR24 Warren Road - Cortlandt 3.84 Mi (SSE) at 1490 Direct Gamma A2 Air Particulate A2 IPEC Onsite- 0.39 Mi (S) at Radioiodine lc2 193° Broad Leaf Vegetation Soil A3 Air Particulate A3 Meteorological Tower Onsite -

Radioiodine Icl 0.46 Mi (SSW) at 208' Broad Leaf Vegetation Soil 104 MW-40 Boundary Well, lower parking Onsite - 0.21 mi (SW)

Groundwater lot 105 MW-51 Boundary Well, middle Onsite- 0.18 mi (SSW)

Groundwater parking lot

= 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 Rockland County G

Indian (3

© Point.

1 Hudson c1 1m]

River 1

lc2I Bucl Verplanck 38 Key:

A - Waterborne: Surface (HR) Wa#

0

- Direct Radiation Sample Location DR#

0l - Air Particulate & Radioiodine A#

"c> - HR Shoreline Sediment Wc#

Westchester County 1 mile Ic# - Broadleaf Vegetation Ibl - Fish and Invertebrates (where available downstream)

A-5

FIGURE A-2 SAMPLING LOCATIONS Greater Than 2 Miles From Indian Point N

Roseton (20.7 mi. N):

Ic3 Upstream:

Ib2 Orange County Bear Mountain Bridge 0

Putnam County 0

5 miles Rockland County Westchester County Key:

O

- Direct Radiation Sample Location DR#

[l

- Air Particulate & Radioiodine A#

<> - HR Shoreline Sediment Wc#

) - Waterborne: Drinking Wb#

Ic3 - Broadleaf Vegetation Ib2 - Fish and Invertebrates (where available upstream)

A-6

FIGURE A-3 SAMPLING LOCATIONS Additional Sampling Locations N

Roseton (20.7 mi: N)- 23: p.

Orange County Bear Mountain Bridge Putnam County Cold Spring (10.88 mi. N) 84 Y 17: V 104/105 :gw 29: U Rockland County 27: U v

Westchester County o 8: dw 5 miles Key:

N - Air Particulate & Radioiodine V - Aquatic Vegetation

,0* - HR Bottom Sediment p - Precipitation dw - Drinking Water HR Shoreline Sediment

• .- Soil

,gw - Ground Water Boundary Monitoring (see detailed site map)

A-7

TABLE A-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLE ANALYSIS (a) (b)

Gross p3 4

u.ul 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.

(e)

I

_1_5 1

1 1

5,000 (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 Sr-90 water LLD is only for groundwater samples locations 104 and 105 (see Table A-i)

A-8

TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES H-3 20,000(a)

I

]

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-1 37 50 20 2,000 70 2,000 Ba-La-140 200 300

'Sr-90 8

40 (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.

A-9

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS

SUMMARY

APPENDIX B B.1 2007 Annual Radiological Environmental Monitoring Pro-gram Summary The results of the 2007 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 2007.

The format of this summary table conforms to the reporting requirements of the ODCM, NRC Regulatory Guide 4.8 (Reference 4),

and NRC Branch Technical Position to Regulatory Guide 4.8 (Reference 14). 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 census are presented in Tables B-22 and B-23, respectively.

In lieu of identifying and sampling the nearest garden of greater than 50 M2, 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 2007, environmental sampling was performed for 12 media types addressed in the ODCM and direct radiation.

A total of 1322 samples/measurements were obtained. Of the scheduled samples, 99.3% 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-Ia for air samples, B-1 b for TLDs and B-Ic for other environmental media.

B.4 Analytical Deviations There were no analytical deviations for 2007.

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

B-1

TABLE B-1

SUMMARY

OF SAMPLING DEVIATIONS 2007 MEDIA PARTICULATES IN AIR CHARCOAL FILTER TLD HUDSON RIVER WATER DRINKING WATER SHORELINE SOIL BROAD LEAF VEGETATIOI\\

FISH & INVERTEBRATES AQUATIC VEGETATION HUDSON RIVER BOTTOM SEDIMENT SOIL PRECIPITATION GROUNDWATER SAMPLES 468 466 164 32 24 20 54 27 3

8 3

8 45 99.8%

99.6%

99%

100%

100%

80%

100%

100%

100%

100%

100%

100%

100%

See Table B-la See Table B-la See Table B-lb N/A N/A See Table B-ic N/A N/A N/A N/A N/A N/A N/A TOTALS 1322 I

9

_99.3%_

TOTAL NUMBER OF ANALYSES REPORTED

• Samples not collected or unable to be analyzed.

1313 B-2

TABLE B-la / B-lb/B-lc TABLE B-la 2007 Air Sampling Deviations STATION WEEK PROBL~EM ACTIONS TO PREVENJT RECURRENCE LOVETT 01/16/2007 We lost about 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> of sample this past week. The pump had failed.

The Lovett air sample lost 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of sample time last week. It was running when we left it last week and it was running when we changed it this week.

LOVETT 04/16/2007 The Lovett air sample lost 105 hours0.00122 days <br />0.0292 hours <br />1.736111e-4 weeks <br />3.99525e-5 months <br /> of sample time last week. It was running when we left it last week and it was running when we changed it this week.

The Lovett air sample was not running when we went to change it out on LOVETT 04/23/2007 4/23/2007. According to the hour meter it stopped running 30 minutes after we left on 4/16/2007. We have no air 'sample for the past week. Power was restored to the station.

The Lovett air sample lost 118.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of sample time last week. It was LOVETT 05/21/2007 running when we left it last week and it was running when we changed it this week.

The Training Bldg air sample pump failed this past week and we lost 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> of sample. We replaced the pump.

PEEKSKILL GAS HOLDER 07/30/2007 The Peekskill Gas Holder air sample was not running when we went to change E0 it out. The pump had failed and we lost 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> of sample this past week.

The Training Bldg air sampler lost 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> of sample time last week, It was TRAINING BLDG 11/13/2007 running when left the week berofre and it was running when changed out again.

The Grassy Point air sample lost 47 hours5.439815e-4 days <br />0.0131 hours <br />7.771164e-5 weeks <br />1.78835e-5 months <br /> of sample last week. It was running when we left it last week and it was running when we changed it this week.

TABLE B-lb 2007 TLD Deviations T

STATION QUARTER 2

PROBLEM / ACTIONS TO PREVENT R~ECURRENCE IL 20 & 21"01820 Two of the 10 CFR20 / 40CFRI90 TILD locations on site had the TLD's TLD 200 & 212 10/18/2007 missing.

TABLE B-Ic 2007 Other Media Deviations STATION SAMPLE SCHEDULE PROBLEME

/ACTIONS TO PREVENT RECURRENGE-.

The dock was snow covered and ice covered and unsafe to go out and get the HIUDSON RIVER INLET 02/16/2007sape sample.

HUDSON RIVER OUTLET 02/16/2007 The hose was frozen and there was no sample for the week.

LENT'S COVE 06/06/2007 Shoreline soil sample not analyzed for Sr-90 WHITE BEACH 06/07/2007 Shoreline soil sample not analyzed for Sr-90 MANITOU INLET 06/06/2007 Shoreline soil sample not analyzed for Sr-90 COLD SPRING 06/06/2007 Shoreline soil sample not analyzed for Sr-90 LENTS COVE 09/06/2007 No aquatic vegetation was found in this area iVERPLANCK AREA 09/06/2007 No aquatic vegetation was found in this area B-3

TABLE B-2 ODCM ANNUAL

SUMMARY

- 2007 DIRECT RADIATION (mR / standard quarter)

B-3 TLD Reads 164 NIA 14.3 (160/160) /

9.5-22.2 West Shore Drive - North 1.21 Mi (W) at 276' DR13 20.0 (4/4) / 18.3 - 21.6 18.8 (4/4) /

17.4-21.5 0

AIR PARTICULATES

1. 22 Lovett Power Plant 0

(

AND RADIOIODINE GB (467) 0.0131.6 Mi (WSW) at 244(52/52)

/

(pCi/m 3) B-6, B-7, B-8 0.003 - 0.026 0.014 (51/52) / 0.003-0.023 0.003-0,023 1-131 (466) 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 RIVER WATER (pCi/L)

H-3 (8) 3000 (c)

<Lc

<Lc

<Lc 0

B-9, B-10 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,; Groundwater above MDC (b) Required a priori 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

- 2007 DRINKING WATER (pCi/L) B-11, B-12 GB (24) 4 H-3(8) 1 2000

<,c I

<Lc I

N/A

[

0 GSA (24)

Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr/Nb-95 1-131 Cs-1 34 Cs-137 Ba/La-i140 15 15 30 15 30 15-15 15 18 i5

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0

0 0

0 0

0 0

0 0

0 SHORELINE SOIL GSA (10)

(pCi/kg - dry) B-13 Cs-134 150

<Lc

<Lc

<Lc 0

106(216)1

1. 17 Off Verplanck

1. 50 Manitow Inlet Cs-137 180 6 (2/6 1.5 Mi (SSW) at 202.50 357(1/4) /

0 106 (2/2) / 63.3 - 149 357-357 Sr-90 (6) 5000

<Lc

<Lc

<Lc 0

(a) Positive values above L,; Grouridwater above MDC (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

- 2007 BROADLEAF VEGETATION (pCi/kg - wet) B-14 GSA (54) 1-131 Co-60 Cs-1 34 Cs-1 37 60 N/A 60 80

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc

<Lc 0

0 0

0 FISH AND INVERTEBRATES GSA (27)

(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

Sr-90 (27) 5

<Lc

<Lc

<Lc 0

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

1. 17 Off Verplanck

1. 17 Off Verplanck Cs-1 37 100 1.5 Mi (SSW) at 202.50 1.5 Mi (SSW) at 202.5'

<Lc 0

31.0 (1/1) / 31.0 - 31.0 31.0 (1/1) / 31.0 - 31.0 (a) Positive values above L,; Groundwater above MDC (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

- 2007 TTIM SJEDIME (pCi/kg - DRY)

GSA(8)

Co-60 Cs-134 NONE 150

<Lc

<Lc

<Lc

<Lc

1. 28 Lents Cove 0.45 Mi (ENE) at 069' 291.5 (2/2) /

373.7 - 209.2

<Lc

<Lc

1. 84 Cold Spring 20.7 Mi (N) at 356° 254.8 (1/2) /

254.8-254.8 0

0 0

Cs-137 180 221 (6/6)1 95.0-373.7 SOIL (pCi/kg - DRY)

GSA(3)

Co-60 NONE

<Lc

<Lc

<Lc 0

Cs-134 150

<Lc

<Lc

<Lc 0

1. 94 Training Center

1. 94 Training Center Cs-137 180 0.45 Mi (SSW) at 2080 0.45 Mi (SSW) at 2080

<Lc 0

136.5 (1/2) /

136.5 (1/1) /

136.5 - 136.5 136.5 - 136.5 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

(a) Positive values above Lc; Groundwater above MDC (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-2 ODCM ANNUAL

SUMMARY

- 2007 UNDWA (pCi/L)

GSA(45)

H-3 (45)

Co-60 (45)

Cs-134 (45)

Cs-137 (45)

Sr-90 (41) 3000 (c) 15 15 18 1

194 (5/45)/

176 - 223

<Lc

<Lc 11.5 (5/45)!

5.15-21.6

<Lc

1. 105 MW-51 0.18 mi - SSW 203 (3/26)/

187-223

<Lc

<Lc

1. 105 MW-51 0.18 mi - SSW 11.5 (5/26)/

5.15-21.6

<Lc N/A N/A N/A N/A N/A 0

0 0

0 0

(a) Positive values above L.; Groundwater above MDC (b) Required a priori LLD; see Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCi/L B-8

TABLE B-3 2007 DIRECT RADIATION, QUARTERLY DATA (mR per STANDARD QUARTER)

DR-02 DR-03 DR-04 DR-05 DR-06 DR-07 DR-08 DR-09 DR-10 DR-11 DR-12 DR-13 DR-14 DR-15 DR-16 NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 14.00 11.91 13.03 13.29 13.99 15.44 11.70 12.81 13.28 10.35 16.39 18.34 12.51 12.95 13.82

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

0.55 0.77 0.65 0.75 0.53 0.73 0.55 0.71 0.62 0.57 0.77 0.78 0.69 0.66 0.61 15.4 12.9 15.0 15.2 15.7 18.5 13.6 14.3 15.2 12.3 19.5 21.6 15.5 15.4 16.9

+ 1.3

+ 0.7

+ 0.8

+/- 0.7

+/- 0.7

+/- 0.7

+/- 0.7

+ 0.8

+/- 1.1

+ 0.8

+ 0.9

+/- 1.1

+/- 1.2

+/- 0.6

+ 0.6 13.24 10.47 12.57 13.24 12.79 14.73 11.38 12.46 13.64 9.96 16.86 19.49 13.39 12.59 14.78

+/- 0.7

+/- 0.7

+/- 0.7

+/- 0.8

+/- 0.7

+/- 0.8

+/- 0.8

+/- 0.9

+ 0.9

0.6

+ 0.9

+/- 1.5

+/- 1.1

+ 0.7

+ 0.7 14.54 11.75 13.63 14.20 14.41 15.96 12.04 13.43 14.53 10.63 15.52 20.74 12.86 13.88 15.08

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

0.69 0.82 0.70 0.82 0.63 0.79 0.55 0.82 0.78 0.69 0.79 1.07 0.99 0.86 0.82 14.3 11.8 13.6 14.0 14.2 16.2 12.2 13.3 14.2 10.8 17.1 20.0 13.6 13.7 15.2 57 47 54 56 57 65 49 53 57 43 68 80 54 55 61

-I

4.

4.

4 4

DR-17 DR-18 DR-19 DR-20 DR-21 DR-22 DR-23 DR-24 DR-25 DR-26 DR-27 DR-28 DR-29 DR-30 DR-31 DR-32 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 14.27 13.53 14.89 12.58 13.27 11.42 13.28 13.87 12.17 13.58 13.01 18.05 13.12 13.55 15.57 12.97

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

0.78 0.66 1.28 0.58 0.71 0.65, 0.47 0.85 0.56 0.61 0.91 0.66 0.68 0.58 0.67 0.50 17.3 16.2 16.7 14.6 15.5 13.1 16.3 16.4 15.5 16.9 17.3 22.2 17.9 18.8 19.8 16.1

+/- 1.0

+/- 0.9

+/- 0.9

+/- 0.7

+/- 0.6

+/- 0.9

+/- 1.0

+/- 0.8

+/- 1.0

+/- 0.7

+/- 2.2

+/- 0.9

+/- 1.3

+/- 1.0

+/- 0.9

+/- 0.9 14.49 12.85 13.47 12.37 12.09 9.52 12.54 13.68 11.51 13.70 12.61 18.57 13.43 14.42 15.46 12.31

+/- 0.8

+/- 0.7

+/- 1.0

+/- 0.8

+/- 0.8

+/- 0.6

+/- 0.7

+/- 0.7

+/- 0.8

+/- 1.2

+ 0.8

+ 0.9

+ 0.7

+/- 0.7

+/- 1.1

+ 0.7 15.34 14.50 15.17 13.71 13.94 11.63 13.97 14.93 13.42 14.73 13.65 20.06 14.27 14.56 16.59 13.33

+/-

+/-

+/-

+/-

+/-

+

+/-

+

+/-

+/-

+/-

+/-

+/-

+

+/-

+

1.35 0.93 0.85 0.87 0.76 0.70 1.20 0.73 0.91 1.18 0.84 1.19 0.88 0.63 0.89 0.68 15.3 14.3 15.0 13.3 13.7 11.4 14.0 14.7 13.1 14.7 14.1 19.7 14.7 15.3 16.9 13.7 61 57 60 53 55 46 56 59 53 59 57 79 59 61 67 55 DR-33 NE 13.12

+/-

0.88 15.8

+/- 0.7 12.28

+/- 0.7 13.50

+/- 0.68 13.7 55 DR-34 SE 12.24

+/-

0.50 15.5

+/- 0.9 11.28

+/- 0.6 12.21

+/- 0.59 12.8 51 DR-35 NNE 12.95

+/-

0.62 15.4

+/- 0.8 11.63

+/- 0.6 13.01

+/- 0.95 13.2 53 DR-36 NE 14.28

+/-

0.76 17.6

+/- 2.3 13.07

+/- 0.8 14.91

+/-

1.34 15.0 60 DR-37 SSW 12.75

+/-

0.61 15.4

+/- 0.6 12.17

+/- 1.6 14.60

+/- -0.86 13.7 55 DR-38 S

11.71

+/-

0.58 14.5

+/- 0.7 11.60

+/- 0.7 13.59

+/- 0.66 12.8 51 DR-39 SSW 14.46

+/-

0.70 18.1

+/- 2.2 13.79

+/- 0.7 14.94

+/- 0.75 15.3 61 DR4*

1.2+/-099

2.

+/- 0.9~ 17.3+/-0.9 1i88u

+/- 0.90 18.8 7

DR-41 SSE 12.41

+/-

0.81 14.8

+/- 0.8 11.64

+/- 0.8 12.04

+/- 0.69 12.7 51 AVERAGE 13.6 16.3 13.2 14.3 14.3 57

• Data not available

• • Control Loc~ation~

B-9

TABLE B-4 DIRECT RADIATION, 1997 THROUGH 2007 DATA (mR per Standard Quarter)

JIX-U I DR-02 DR-03 DR-04 DR-05 DR-06 DR-07 DR-08 DR-09 DR-10 DR-11 DR-12 DR-13 DR-14 DR-15 DR-16 Um.o 64.4 48.2 53.9 54.5 53.8 63.7 52.1 51.6 55.3 45.3 67.0 76.2 54.4 54.5 59.4

ý..v 9.9 2.1 3.7 2.6 3.1 3.7 2.6 3.6 6.0 2.2 3.7 4.0 3.5 4.1 2.8 Iu.-

53.7 43.8 46.8 48.3 46.2 55.6 47.1 44.1 39.2 40.8 62.4 67.8 49.8 46.5 55.2 79.0 50.4 58.6 58.0 57.6 68.6 56.3 55.2 59.8 48.5 76.0 81.3 60.4 59.8 63.6 57.1 47.0 54.3 55.9 56.9 64.6 48.7 53.0 56.7 43.3 68.3 80.2 54.3 54.9 60.6

4.

4.

I I

DR-1 7 DR-1 8 DR-19 DR-20 DR-21 DR-22 DR-23 DR-24 DR-25 DR-26 DR-27 DR-28 DR-29 DR-30 DR-31 DR-32 59.8 57.0 60.0 54.8 55.2 46.8 56.1 55.7 49.7 55.2 55.3 64.8 66.8 63.9 72.7 53.1 3.2 2.6 2.8 3.7 3.2 3.6 2.9 2.9 2.5 2.5 3.9 6.5 8.7 6.3 5.8 3.4 56.0 52.2 55.1 47.4 49.8 40.2 49.5 49.2 44.7 50.4 46.8 57.2 54.6 52.2 62.1 45.9 66.8 60.7 63.6 59.2 60.6 51.9 58.9 59.8 53.2 58.9 61.5 77.1 77.3 71.1 80.4 57.2 61.4 57.1 60.2 53.3 54.8 45.7 56.1 58.9 52.6 58.9 56.6 78.9 58.8 61.3 67.4 54.7 DR-33 44.7 8.6 34.0 55.0 54.7 DR-34 53.5 4.7 43.2 60.7 51.2 DR-35 57.4 4.1 48.6 61.2 52.9 DR-36 61.8 5.0 52.5 70.5 59.9 DR-37 55.2 3.3 48.9 60.0 54.9 DR-38 52.2 2.8 48.6 58.4 51.4 DR-39 62.8 4.0 55.2 66.8 61.3 DR-41 52.5 4.0 44.4 57.9 50.9 Average 57.2 50.0 62.9 57.8 Data not available

• • CwntrpLotcation.

B-10

TABLE B-5 2007 DIRECT RADIATION INNER AND OUTER RINGS (mR per Standard Quarter)

DR-05 DR-21 E

55.9 54.8 DR-06 DR-22 ESE 56.9 45.7 DR-07 DR-23 SE 64.6 56.1 DR-08 DR-24 SSE 48.7 58.9 DR-09 DR-25 I S 53.0 52.6 DR-10 DR-26 SSW 56.7 58.9 DR-11 DR-27 SW 43.3 56.6 DR-12 DR-28 WSW 68.3 78.9 DR-13 DR-29 W

80.2 58.8 DR-14 DR-30 WNW 54.3 61.3 DR-15 DR-31 NW 54.9 67.4 DR-16 DR-32 NNW 60.6 54.7 Average 57.4 58.5 B-11

TABLE B-6 IPEC ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - 2007 GROSS BETA ACTIVITY pCi/rm 3 +/- 1 Sigma SAMPLE STATION #

Number' Date' I

Ib 1

01/02/2007 0.012 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.010 -

0.001 0.014 +/- 0.001 1

0.016 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.012 +/- 0.001 2

01/09/2007 0.013 +/- 0.001 0.012 0.001 0.010 +/- 0.001 0,011 0.001 0.010 +/- 0.001 2

0.013 :L 0.002 0.012 -

0.001 0.011

+/- 0.001 0.015 +/- 0.002 3

01/16/2007 0.011 -

0.001 0.011

- 0.001 0.010 +/- 0.001 0.012 +/- 0.001 0,011 +/- 0,001 3

0,012 +/- 0.002 0,013 +/-0L001 0,010 +/- 0,001 0.012 +/- 0.001 4

01/23/2007 0.017 0.001 0.013 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0,001 4

0.018 +/- 0.002 0.016 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 5

01/30/2007 0.015 +/- 0.001 0.017 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 5

0.017 +/- 0.002 0.017 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 6

02/06/2007 0.020 +/- 0.002 0.018 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 6

0.020 +/- 0.002 0.019 +/- 0.001 0.020 -

0.001 '0.023 +/- 0.002 7

02/13/2007 0.015

= 0,001 0.011

- 0.001 0.017 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 7

0.013 +/- 0.001 0.014 -

0.001 0.011

+/- 0.001 0.014 +/- 0.001 8

02/20/2007 0.017 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0,015 +/- 0.001 0.009 +/- 0.001 8

0.016 +/- 0.001 0.014 +/- 0.001 0.015 -

0.001 0.016 +/- 0.001 9

02/27/2007 0.010 +/- 0.001 0.008

= 0.001 0.010 = 0.001 0.010 +/- 0.001 0.012 +/- 0.001 9

0.012

- 0.001 0.010 +/- 0.001 0.013 +/- 0.001 0.010 +/- 0.001 10 03/06/2007 0.011 +/- 0.001 0.008

= 0.001 0.007 +/- 0.001 0.009 +/- 0.001 0.008 +/- 0.001 10 0.008 -

0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.009 +/- 0.001 11 03/13/2007 0.018 +/- 0.001 0.018 +/- 0.001 0.019 +/- 0.001 0.017 -

0.001 0.021

+/- 0.001 11 0.022 +/- 0.002 0.016 +/- 0.001 0.020 +/- 0.001 0.018 +/- 0.001 12 03/20/2007

.0.015

+/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.016 -

0.001 0.014

= 0.001 12 0.015 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 13 03/27/2007 0.010 +/- 0.001 0.012 0.001 0.012 = 0.001 0.013 +/- 0.001 0.011

+/- 0.001 13 0.015 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 14 04/03/2007 0.011

+/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.011

+/- 0.001 0.011 +/- 0.001 14 0.012 +/- 0.001 0.008 +/- 0.001 0.011

- 0.001 0.012 f 0.001 15 04/10/2007 0.004 +/- 0.001 0.004 +/- 0.001 0.004 +/- 0.001 0.005 -

0.001 0.003

+/- 0.001 15 0.003 +/- 0.001 0.003 "+/- 0.001 0.004 +/- 0.001 0.004 +/- 0.001 16 04/17/2007 0.004 +/- 0.001 0.005 +/- 0.001 0.005 +/- 0.001 0.007 +/- 0.001 0.005 0.001 16 0.008 +/- 0.002 0.006 +/- 0.001 0.005 +/- 0.001 0.009 +/- 0.001 17 04/24/2007 0.011 +/- 0.001 0.008 +/- 0.001 0.010 +/- 0.001 0.009 =L 0.001 0.010 +/- 0.001 17 See Deviation Report 0.010 +/- 0.001 0.012 +/- 0.001 0.006 +/- 0.001 18 05/01/2007 0.008 +/- 0.001 0.007 : 0.001 0.007 0.001 0.007 +/- 0.001 0.007 +/- 0.001 18 0.005 +/- 0,001 0.006 +/- 0.001 0.007 +/- 0.001 0.008 +/- 0.001 19 05/08/2007 0.008 +/- 0.001 0.008 +/- 0.001 0.008 +/- 0.001 0.008 +/- 0.001 0.007 +/- 0.001 19 0.009 +/- 0.001 0.009 +/- 0.001 0,008 +/- 0.001 0.008 0.001 20 05/15/2007 0.009

= 0.001 0.007 +/- 0.001 0.006 +/- 0.001 0.006 =L 0.001 0.007 +/- 0.001 20 0,006 +/- 0.001 0.009 +/- 0.001 0.006 +/- 0.001 0.009 +/- 0,001 21 05/22/2007 0.009 +/- 0.001 0.007 +/- 0.001 0.012 0.001 6.011 =- 0.001 0.009 +/- 0.001 21 0.021 "

0.003 0.012 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 22 05/29/2007 0.015 +/- 0.001 0.016 +/- 0.001 0.020 +/- 0.002 0.014 -

0.001 0.018 +/- 0.001 22 0.017 +/- 0.001 0.019 = 0.001 0,015 0.001 0.020 +/- 0.001 23 06/05/2007 0.012 +/- 0.001 0.013

+/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.017 +/- 0.002 23 0.015 +/- 0.002 0.011 +/- 0.001 0.015 +/- 0.001 0.013 0.001 24 06/12/2007 0.009 0.001 0.012 +/- 0.001 0.010 =- 0.002 0.013 +/-- 0.001 0.010 +/- 0.001 24 0.008 +/- 0.001 0.011 +/- 0.001 0.008 +/- 0.001 0.010 +/- 0.001 25 06/19/2007 0.009 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 25 0.009 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 26 06/26/2007 0.013 +/- 0.001 0.011 0,001 0.010 +/- 0.004 0.011 +/- 0.001 0.009 +/- 0.001 26 0.010 -

0.001 0.011 0.001 0.011 +/- 0.001 0,013

+/- 0.001

• • Control sample location B-12

TABLE B-6 ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - 2007 GROSS BETA ACTIVITY pC+/-/ m3 1 Sigma SAMPLE STATION #

Week.

Week End 5.

94 95 23**

2 27 I

29

[Number Date._____

Number______I 27 07/02/2007 0.010 +/- 0.001 0.009 +/- 0.001 0.013 +/- 0.001 0.013 =L 0.001 0.016 +/- 0.001 27 0.016 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.017 +/- 0.001 28 07/10/2007 0.016 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.012 +/- 0.001 28 0.012 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 29 07/17/2007 0.016 +/- 0.001 0.010 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 29 0.018 +/- 0.002 0.010

+/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 30 07/24/2007 0.010 +/- 0.001 0.011

+/- 0.001 0.009 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 30 0.012 -L 0.001 0.012 +/- 0.001 0.009 +/- 0.001 0.016 +/- 0.001 31 07/31/2007 0.015 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.011

+/- 0.001 31 0.011

+/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.002 32 08/07/2007 0.021

+/- 0.002 0.017 +/- 0.001 0.018 +/- 0.001 0.019 +/- 0.002 0.018 +/- 0.001 32 0.018 +/- 0.002 0.020 +/- 0.002 0.017 +/- 0.001 0.018 +/- 0.002 33 08/14/2007 0.017 +/- 0.001 0.013 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.002 0.015 +/- 0.001 33 0.018 +/- 0.002 0.014 +/- 0.001 0.018 +/- 0.001 0.015 +/- 0.001 34 08/21/2007 0.013 +/- 0.001 0.011 4 0.001 0.015 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 34 0.016 +/- 0.002 0.012 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 35 08/28/2007 0.011

+/- 0.001 0.007 +/- 0.001 0.009 +/- 0.001 0.007 +/- 0.001 0.012 +/- 0.001 35 0.007 +/- 0.001 0.012 + 0.001 0.010 +/- 0.001 0.009 +/- 0.001 36 09/04/2007 0.016 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.002 0.016 +/- 0.001 36 0.017 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001 0.015 +/- 0.001 37 09/11/2007 0.018 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 0.018 +/-L 0.002 0.019 +/- 0.002 37 0.020 +/- 0.002 0.018 +/- 0.001 0.017 +/- 0.001 0.020 +/- 0.002 38 09/18/2007 0.010 +/- 0.001 0.010 +/- 0.001 0.007 +/- 0.001 0.009 +/- 0.001 0.007 +/- 0.001 38 0.007 +/- 0.001 0.006 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 39 09/25/2007 0.020 +/- 0.002 0.016 +/- 0.001 0.021 +/- 0.002 0.021

+/- 0.002 0.012 +/- 0.001 39 0.012 :L 0.001 0.018 +/- 0.001 0.017 +/- 0.001 0.021 +/- 0.002 40 10/02/2007 0.017 +/- 0.001 0.021 +/- 0.002 0.022 +/- 0.002 0.021 4 0.002 0.019 +/- 0.002 40 0.023 +/- 0.002 0.017 +/- 0.001 0.021 +/- 0.001 0.018

+/- 0.002 41 10/09/2007 0.015 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.017 +/- 0.002 0.017 +/- 0.001 41 0.014 +/- 0.001 0.011

+/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 42 10/16/2007 0.005

+/- 0.001 0.007 +/- 0.001 0.005 +/- 0.001 0.008 +/- 0.001 0.005 +/- 0.001 42 0.006 +/- 0.001 0.007 +/- 0.001 0.007 +/- 0.001 0.004 +/- 0.001 43 10/23/2007 0.024 +/- 0.002 0.022 +/- 0.002 0.026 +/- 0.002 0.025 +/- 0.002 0.023 +/- 0.002 43 0.020 +/- 0.002 0.020 +/- 0.002 0.020 +/- 0.001 0.021

+/- 0.002 44 10/30/2007 0.011

+/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.015 +/- 0.001 44 0.012 +/- 0.001 0.010 +/- 0.001 0.011

+/- 0.001 0.022

+/- 0.002 45 11/06/2007 0.019 +/- 0.002 0.019 +/- 0.001 0.019 +/- 0.001 0.020 +/- 0.002 0.020 +/- 0.001 45 0.017 +/- 0.001 0.019 +/- 0.001 0.019 +/- 0.001 0.017 +/- 0.002 46 11/13/2007 0.011 +/- 0.001 0.011

- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 46 0.017 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 47 11/19/2007 0.016 +/- 0.002 0.014 +/- 0.001 0.018 +/- 0.002 0.018 +/- 0.002 0.013

+/- 0.001 47 0.017 +/- 0.002 0.015 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.002 48 11/27/2007 0.011 +/- 0.001 0.011

+/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.012 + 0.001 48 0.016 +/- 0.001 0.011 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 49 12/04/2007 0.014 +/- 0.001 0.013

+/- 0.001 0.015 +/- 0.001 0.018 +/- 0.001 0.017 +/- 0.001 49 0.017 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 50 12/11/2007 0.013 +/- 0.001 0.015

+/- 0.001 0.015 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 50 0.013 +/- 0.001 0.017 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 51 12/18/2007 0.016 +/- 0.001 0.018 +/- 0.001 0.021 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 51 0.020 +/- 0.002 0.017 +/- 0.001 0.019 +/- 0.001 0.019 +/- 0.002 52 12/24/2007 0.018 dz 0.002 0.018 +/- 0.002 0.018 +/- 0.002 0.019 +/- 0.002 0.018 +/- 0.001 52 0.019

+/- 0.002 0.017 +/- 0.001 0.020 +/- 0.001 0.019 +/- 0.002

• • Control sample location B-13

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF SITE AIR PARTICULATE SAMPLES - 2007 Results in Units of 10E-3 pCi/ m +/- 1 Sigma SAMPLE LOCATIONS - 1ST QTR 2007

Nuclide, Algonquin Sta #4 NYU Tower #5 Croton Point #27 TrainingBidg,#94 Met Tower #95.

Lovett.#22 **

Roseton #23 Grassy Point #29

'Peekskill #44 Be-7 57.5 +/-

20.2 84.2 +/-

20.5 122.4 +/-

29.3 115.3 +/-

23.7 95.7 +/-

24.3 108.5 +/-

25.5 112.2 +/-

21.2 91.4 +/-

17.8

< 26.8 Cs-134

< 1.5

< 1.6

< 1.5

< 1.1

< 1.9

< 1.5

< 1.4

< 0.9

< 1.6 Cs-137

< 0.8

< 0.7

< 1.3

< 1.0

< 0.8

< 1.1

< 1.6

< 0.5

< 1.2 Zr-95

< 2.6

< 3.0

< 3.5

< 2.8

< 3.0

< 5.3

< 2.5

< 1.9

< 3.8 Nb-95

< 2.5

< 2.7

< 2.9

< 2.5

< 2.5

< 2.7

< 2.4

< 2.0

< 3.1 Co-58

< 2.2

< 1.4

< 2.3

< 1.7

< 1.6

< 2.5

< 1.5

< 1.1

< 2.5 Mn-54

< 1.2

< 1.0

< 1.5

< 1.2

< 1.2

< 1.2

< 1.5

< 0.8

< 1.7 Zn-65

<3.0

< 3.8

< 4.5

< 2.8

< 3.3

< 3.0

< 3.2

< 3.0

< 4.9 Co-60

< 1.7

< 1.2

< 2.2

< 1.6

< 1.7

< 1.7

< 1.7

< 1.0

< 2.6 K-40

< 18.7

< 13.4

< 24.2

< 14.1

< 17.6

< 18.6

< 17.1

< 10.3

< 24.4

• • Control Sample Location SAMPLE LOCATIONS - 2ND QTR 2007 Nuclide Algonquin Sta #4 NYU.Tower #5 Croton Point #27-Training Bldg.#94 Met Tower #95.

Lovett.#22 **

Roseton #23 Grassy Point #29 4Peekskill#44 Be-7 131.5 +/-

17.0 103.3 +/-

12.7 110.1 +/-

14.6 125.5 +/-

14.6 136.0 +/-

14.1 107.1 +/-

15.0 137.1 +/-

17.2 131.3 +/-

12.3 109.5 +/-

15.1 Cs-134

< 0.7

< 0.6

< 0.4

< 0.9

< 0.7

< 0.9

< 0.5

< 0.3

< 0.6 Cs-137

< 0.5

< 0.3

< 0.4

< 0.6

< 0.3

< 0.6

< 0.4

< 0.6

< 0.6 Zr-95

< 1.6

< 1.8

< 1.6

< 1.4

< 0.9

< 2.4

< 2.0

< 1.2

< 1.2 Nb-95

< 1.5

< 0.6

< 1.1

< 0.8

< 1.5

< 0.9

< 1.4

< 1.0

< 1.4 Co-58

< 0.7

< 0.7

< 0.7

< 0.7

< 0.7

< 0.6

< 0.9

< 0.4

< 0.7 Mn-54

< 0.8

< 0.6

< 0.9

< 0.8

< 0.5

< 0.6

< 0.5

< 0.6

< 0.7 Zn-65

< 2.9

< 1.6

< 1.2

< 1.4

< 1.3

< 2.0

< 2.2

< 1.2

< 1.5 Co-60

<1.0

< 0.5

< 0.8

< 0.8

< 0.5

< 0.6

< 0.9

< 0.8

< 0.8 K-40

< 8.5

< 5.7

< 7.2

< 7.5

< 6.8

< 7.1

< 9.4

< 4.1

< 7.5

• • Control Sample Location B-14

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF SITE AIR PARTICULATE SAMPLES - 2007 Results in Units of 10E-3 pCi/ m I Sigma SAMPLE LOCATIONS - 3RD QTR 2007 Nuclide Algonquin Sta #4 NYU Tower #5 Croton Point #2T Training Bldg #94 Met Tower #95 Lovett#22:**:

Roseton #23 Grassy YPoiht #29 Peekskll #44 Be-7 132.7 +/-

13.6 130.1 +/-

13.2 116.9 +/-

13.6 104.3 +/-

15.0 112.5 +/-

13.9 143.8 +/-

14.9 130.6 +/-

13.2 136.5 +1-15.1 112.5 +/-

13.5 Cs-134

< 0.6

< 0.8

< 0.5

< 0.8

< 0.3

< 0.9

< 0.6

< 0.5

< 0.8 Cs-137

< 0.5

< 0.3

< 0.5

< 0.5

< 0.3

< 0.6

< 0.4

< 0.4

< 0.3 Zr-95

< 1.4

< 0.9

< 1.9

< 1.6

< 1.9

< 1.4

< 1.7

< 1.2

< 1.5 Nb-95

< 1.1

< 1.6

< 0.9

< 1.6

< 1.6

< 1.4

< 1.7

< 1.0

< 0.7 Co-58

"< 0.4

< 0.5

< 0.7

< 1.0

< 0.7

< 0.5 1.1

< 0.8

< 1.0 Mn-54

< 0.3

< 0.7

< 0.5

< 0.7

< 0.3

< 0.4

< 0.3

< 0.5

< 0.6 Zn-65

< 1.3

< 1.0

< 1.5

< 1.2

< 1.6

< 0.9

< 1.6

< 1.3

< 2.2 Co-60

< 0.5

< 0.5

< 0.5

< 0.8

< 0.8

< 0.5

< 0.5

< 0.6

< 1.1 K-40

< 6.5

< 5.1

< 9.6

< 7.2

< 5.9

< 5.0 39.4+/-

8.9

< 7.5

< 10.5

• • Control Sample Location SAMPLE LOCATIONS - 4TH QTR 2007 Nuclide Algonquin Sta #4 NYU Tower #5 Croton Point'#27 Training Bldg #94 Met Tower #95 Lovett #22 *.

Roseton #23 GrasSyPoint #29.

Peekskill #44 Be-7 109.9

+/-

11.9 105.0 +/-

15.2 89.4

+/-

12.1 119.6 +/-

14.9 102.8

+/-

13.4 99.4 +/-

13.0 109.2 +

1-12.4 96.1 +/-

13.5 102.2

+/-

12.9 Cs-134

< 0.7

< 0.7

< 0.3

< 0.4

< 0.4

< 0.6

< 0.5

< 0.6

< 1.0 Cs-137

< 0.4

< 0.7

< 0.2

< 0.5

< 0.6

< 0.6

< 0.5

< 0.4

< 0.4 Zr-95

< 1.4

< 1.6

< 0.8

< 1.8

< 1.2

< 1.7

< 1.7

< 1.0

< 1.5 Nb-95

< 1.1

< 1.0

< 1.3

< 2.0

< 1.4

< 1.6

< 0.9

< 1.6

< 1.7 Co-58

< 0.5

< 1.3

< 0.8

< 1.0

< 1.0

< 1.0

< 0.9

< 1.1

< 1.0 Mn-54

< 0.7

< 0.9

< 0.5

< 0.5

< 0.7

< 0.8

< 0.4

< 0.4

< 0.7 Zn-65

< 1.9

< 2.3

< 0.8

< 2.5

< 2.1

< 1.7

< 1.5

< 1.3

< 1.8 Co-60

< 0.8

< 0.9

< 0.8

< 0.8

< 0.6

< 0.6

< 0.7

< 0.7

< 0.5 K-40 45.2 +/-

8.9

< 8.2

< 5.2

< 10.2

< 6.0

< 6.9 27.8 +/-

7.6

< 7.6

< 5.5

• • Control Sample Location B-15

TABLE B-8 IPEC ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2007 1-131 ACTIVITY pCi/ m3 I Sigma SAMPLE STATION #

'Week, Week End94923'2279 Number Date:-

1 01/02/07

< 0.025

< 0.023

< 0.022

< 0.018

< 0.028

< 0.022

< 0.022

< 0.020

< 0.021 2

01/09/07

< 0.029

< 0.019

< 0.024

< 0.031

< 0.036

< 0.067

< 0.020

< 0.020

< 0.034 3

01/16/07

< 0.033

< 0.032

< 0.035

< 0.039

< 0.023

< 0.041

< 0.023

< 0.022

< 0.025 4

01/23/07

< 0.022

< 0.020

< 0.023

< 0.029

< 0.034

< 0.046

< 0.022

< 0.013

< 0.007 5

01/30/07

< 0.014

< 0.025

< 0.027

< 0.033

< 0.030

< 0.031

< 0.019

< 0.019

< 0.033 6

02/06/07

< 0.026

< 0.017

< 0.022

< 0.023

< 0.026

< 0.034

< 0.014

< 0.026

< 0.023 7

02/13/07

< 0.056

< 0.024

< 0.027

< 0.047

< 0.039

< 0.058

< 0.035

< 0.030

< 0.045 8

02/20/07

< 0.023

< 0.025

< 0.032

< 0.040

< 0.017

< 0.027

< 0.019

< 0.020

< 0.029 9

02/27/07

< 0.051

< 0.036

< 0.030

< 0.042

< 0.029

< 0.046

< 0.035

< 0.033

< 0.011 10 03/06/07

< 0.023

< 0.016

< 0.024

< 0.023

< 0.039

< 0.032

< 0.027

< 0.013

< 0.019 11 03/13/07

< 0.022

< 0.036

< 0.024

< 0.015

< 0.032

< 0.038

< 0.026

< 0.018

< 0.023 12 03/20/07

< 0.033

< 0.028

< 0.031

< 0.021

< 0.036

< 0.044

< 0.027

< 0.017

< 0.025 13 03/27/07

< 0.017

< 0.021

< 0.024

< 0.030

< 0.028

< 0.020

< 0.022

< 0.022

< 0.027 14 04/03/07

< 0.044

< 0.023

< 0.035

< 0.031

< 0.028

< 0.028

< 0.030

< 0.022

< 0.017 15 04/10/07

< 0.029

< 0.031

< 0.024

< 0.019

< 0.022

< 0.027

< 0.013

< 0.021

< 0.032 16 04/17/07

< 0.038

< 0.027

< 0.032

< 0.026

< 0.036

< 0.068

< 0.025

< 0.017

< 0.029 17 04/24/07

< 0.021

< 0.030

< 0.026

< 0.023

< 0.026 D.cv~i..

oRcpwr

< 0.026

<1 0.013

< 0.017 18 05/01/07

< 0.023

< 0.016

< 0.023

< 0.038

< 0.023

< 0.028

< 0.026

< 0.023

< 0.032 19 05/08/07

< 0.030

< 0.038

< 0.030

< 0.031

< 0.034

< 0.041

ý< 0.029

< 0.017

< 0.020 20 05/15/07

< 0.042

< 0.041

< 0.014

< 0.031

< 0.039

< 0.033

< 0.027

< 0.032

< 0.019 21 05/22/07

< 0.028

< 0.009

< 0.027

< 0.030

< 0.031

< 0.049

< 0.017

< 0.028

< 0.020 22 05/29/07

< 0.036

< 0.024

< 0.031

< 0.039

< 0.016

< 0.018

< 0.022

< 0.031

< 0.039 23 06/05/07

< 0.024

< 0.021

< 0.019

< 0.022

< 0.036

< 0.035

< 0.017

< 0.031

< 0.023 24 06/12/07

< 0.030

< 0.024

< 0.044

< 0.035

< 0.037

< 0.033

< 0.026

< 0.027

< 0.028 25 06/19/07

< 0.035

< 0.021

< 0.026

< 0.030

< 0,033

< 0.029

< 0.022

< 0.029

< 0.032 26 06/26/07

< 0.024

< 0.024

< 0.055

< 0.025

< 0.027

< 0.052

< 0.022

< 0.017

< 0.024

• • Control sample location B-1 6

TABLE B-8 IPEC ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2007 1-131 ACTIVITY pCi/ m3+/- I Sigma SAMPLE STATION #

Week Week End

9.

27 29 44 94 22 4

Number Date 27 07/02/07

< 0.030

< 0.031

< 0.024

< 0.028

< 0.030

< 0.036

< 0.025

< 0.016

< 0.024 28 07/10/07

< 0.027

< 0.030

< 0.029

< 0.022

< 0.024

< 0.037

< 0.018

< 0.018

< 0.022 29 07/17/07

< 0.032

< 0.005

< 0.020

< 0.032

< 0.025

< 0.035

< 0.009

< 0.023

< 0.010 30 07/24/07

< 0.022

< 0.023

< 0.020

< 0.037

< 0.024

< 0.021

< 0.021

< 0.018

< 0.016 31 07/31/07

< 0.021

< 0.023

< 0.028

< 0.020

< 0.006

< 0.031

< 0.016

< 0.036

< 0.011 32 08/07/07

< 0.034

< 0.029

< 0.030

< 0.033

< 0.027

< 0.030

< 0.036

< 0.024

< 0.018 33 08/14/07

< 0.035

< 0.025

< 0.028

< 0.022

< 0.027

< 0.053

< 0.021

< 0.025

< 0.009 34 08/21/07

< 0.029

< 0.016

< 0.020

< 0.028

< 0.028

< 0.042

< 0.031

< 0.022

< 0.034 35 08/28/07

< 0.027

< 0.032

< 0.021

< 0.034

< 0.010

< 0.037

< 0.022

< 0.021

< 0.029 36 09/04/07

< 0.032

< 0.006

< 0.032

< 0.021

< 0.029

< 0.028

< 0.026

< 0.025

< 0.021 37 09/11/07

< 0.035

< 0.028

< 0.021

< 0.033

< 0.033

< 0.022

< 0.027

< 0.016

< 0.031 38 09/18/07

< 0.022

< 0.033

< 0.027

< 0.029

< 0.033

< 0.031

< 0.019

< 0.037

< 0.023 39 09/25/07

< 0.034

< 0.021

< 0.028

< 0.021

< 0.029

< 0.027

< 0.031

< 0.027

< 0.027 40 10/02/07

< 0.028

< 0.016

< 0.030

< 0.036

< 0.035

< 0.031

< 0.025

< 0.028

< 0.027 41 10/09/07

< 0.029

< 0.029

<.0.037

< 0.007

< 0.036

< 0.034

< 0.027

< 0.014

< 0.027 42 10/16/07

< 0.029

< 0.033

<.0.030

< 0.032

< 0.045

< 0.036

< 0.031

< 0.023

< 0.039 43 10/23/07

< 0.027

< 0.034

< 0.027

< 0.036

< 0.030

< 0.031

< 0.019

< 0.021

< 0.022 44 10/30/07

< 0.028.

< 0.029

< 0.031

< 0.028

< 0.025

< 0.029

< 0.020

< 0.024

< 0.038 45 11/06/07

< 0.037

< 0.025

< 0.030

< 0.022

< 0.033

< 0.025

< 0.024

< 0.022

< 0.028 46 11/13/07

< 0.026

< 0.029

< 0.040

< 0.030

< 0.024

< 0.026

< 0.033

< 0.031

< 0.023 47 11/19/07

< 0.010

< 0.028

< 0.025

< 0.040

< 0.046

< 0.029

< 0.040

< 0.020

< 0.030 48 11/27/07

< 0.008

< 0.030

< 0.023

< 0.023

< 0.038

< 0.036

< 0.021

< 0.022

< 0.035 49 12/04/07

< 0.030

< 0.024

< 0.007

< 0.022

< 0.023

< 0.044

< 0.032

< 0.026

< 0.028 50 12/11/07

< 0.007

< 0.033

< 0.028

< 0.028

< 0.032

< 0.031

< 0.034

< 0.023

< 0.044 51 12/18/07

< 0.032

< 0.028

< 0.024

< 0.025

< 0.026

< 0.025

< 0.020

< 0.022

< 0.030 52 12/24/07

< 0.039

< 0.042

< 0.037

< 0.046

< 0.028

< 0.037

< 0.024

< 0.027

< 0.035 53 12/31/07

< 0.035

< 0.022

< 0.031

< 0.048

< 0.026

< 0.034

< 0.033 Dcviatio

< 0.034

• • Control sample location B-17

TABLE B-9 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCi/liter +/- I Sigma

1. 9 PLANT INLET (HUDSON RIVER INTAKE)

Date' 01/26/2007

-' 02/23/2007

-03/30/2007:

04/27/2007 0525207-::.

06/29/2007

.NUCLIDE.

1-131

< 6.03

< 4.09

< 5.78

< 7.03

< 6.91

< 5.70 Cs-134

< 0.75

< 1.01

< 0.75

< 1.78

< 1.27

< 1.10 Cs-137

< 0.94

< 0.79

< 1.00

< 1.35

< 1.22

< 0.63 Zr-95

< 2.09

< 1.84

< 1.94

< 3.43

< 2.64

< 2.19 Nb-95

< 1.42

< 1.29

< 1.51

< 2.16

< 1.72

< 1.08 Co-58

< 1.07

< 1.00

< 1.30

< 1.59

< 1.24

< 1.29 Mn-54

< 0.90

< 0,89

< 1.12

< 1.71

< 1.14

< 1.10 Fe-59

< 2.97

< 2.99

< 3.36

< 5.19

< 4.03

< 3.47 Zn-65

< 2.12

< 1.06

< 2.55

< 2.01

< 2.95

< 1.38 Co-60

< 0.76

< 0.90

< 1.01

< 1.47

< 1.25

< 0.99 K-40 106.5 +/- 9.51 321.7 +/-

12.43 157.9 +/- 11.24 349.6 +/- 21.96 127.3 +/- 12.77 326.4 +/- 13.70 Ba/La-140

< 3.13

< 2.48

< 3.11

< 3.82

< 4.20

< 3.65 Date j

07/27/2007.

[

. 08/31/2007. :

.09/28/2007 10/26/2007:4..: 11/30/2007 7

-12/31/2007 1-131

< 5.34

< 7.00

< 6.87

< 6.72

< 6.89

< 6.75 Cs-134

< 1.41

< 1.37

< 1.45

< 1.09

< 1.14

< 1.98 Cs-137

< 1.18

< 1.14

< 1.84

< 1.54

< 1.05

< 1.88 Zr-95

< 2.65

< 2.70

< 4.08

< 2.94

< 2.23

< 3.06 Nb-95

< 1.70

< 2,12

< 2.65

< 1,40

< 1.47

< 2.30 Co-58

< 1.40

< 1.56

< 1.95

< 1.77

< 1.14

< 2.19 Mn-54

< 1.34

< 1.25

< 2.05

< 1.41

< 0.96

< 1.63 Fe-59

< 4.27

< 4.49

< 5.08

< 4.31

< 3.94

< 5.69 Zn-65

< 1.69

< 1.57

< 4.72

< 1.91

< 1.41

< 4.72 Co-60

< 1.44

< 1.24

< 2.11

< 1.33

< 1.12

< 1.96 K-40 361.6 +/-

18.82 348.3 +/- 17.84 365.1 +/- 27.71 190.2 +/- 14.55 337.6 +/- 14.56 163.9 +/- 20.54 Ba/La-140

< 4.15

< 4.10

< 5.35

< 3.73

< 3.89

< 4.09 B-18

TABLE B-9 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCi/liter +/- 1 Sigma

1. 10 DISCHARGE CANAL (MIXING ZONE)

Date

[

01/26/2007

' 02/23/2007:

03/30/2007.:

04/27/2007 1 05/25/2007 06/29/2007 NUCLIDE..

1-131

< 6.91

< 4.02

< 6.75

< 6.57

< 6.42

< 6.95 Cs-134

< 1.22

< 0.68

< 0.87

< 0.81

< 1.32

< 1,50 Cs-137

< 1.45

< 1.09

< 1.30

< 1.24

< 1.29

< 1.36 Zr-95

< 3.33

< 2.02

< 2.81

< 2.44

< 2.30

< 3.21 Nb-95

< 2.04

< 1.40

< 2.07

< 1.94

< 1.90

< 2.17 Co-58

< 1.86

< 1,23

< 1.61

< 1.41

< 1.49

< 1.87 Mn-54

< 1.75

< 1.06

< 1.21

< 1.43

< 1.29

< 1.55 Fe-59

< 4.00

< 3.51

< 5.05

< 4.47

< 4.21

< 4.85 Zn-65

< 3.89

< 2.56

< 3.44

< 1.79

< 3.04

< 1.80 Co-60

< 1.40

< 1.27

< 1.58

< 1.24

< 1.23

< 1.34 K-40 128 +/- 14.77 271.2 +/- 14.85 162.4 +/- 15.84 122 +/- 13.66 293.2 +/- 17.84 277.1 +/- 19.80 Ba/La-140

< 3.55

< 4.01

< 5.30

< 3.96

< 3.82

< 4.13 Date 07/27/2007 08/31/2007,

09/28/2007..I 10/26/2007 11/30/2007...

12/31/2007 1-131

< 5.19

< 6.15

< 5.74

< 6.41

< 6.59

< 5.42 Cs-134

< 0.72

< 0.79

< 1.70

< 1.84

< 1.45

< 1.03 Cs-137

< 1.08

< 0.69

< 1.56

< 1.81

< 1.33

< 1.21 Zr-95

< 2.09

< 1.65

< 2.99

< 4.03

< 2.43

< 2.75 Nb-95

< 1.56

< 1.20

< 2.24

< 2.73

< 1.75

< 1.86 Co-58

< 1.14

< 0.93

< 1.81

< 1.89

< 1.77

< 1.55 Mn-54

< 1.07

< 0.75

< 1.58

< 1.58

< 1.36

< 1.48 Fe-59

< 3.05

< 2.70

< 4.17

< 4.95

< 4.53

< 4.58 Zn-65

< 1.35

< 0.95

< 3.49

< 3.31

< 3.06

< 3.34 Co-60

< 0.94

< 0.72

< 1.47

< 1.63

< 1.26

< 1.41 K-40 171.5 +/- 11.44 322.5 +/-

10.33 203.9 +/- 20.17 385.3 +/- 24.76 163.2 +/- 15.73 136.5 +/- 15.47 Ba/La-140

< 3,15

< 3.26

< 4.16

< 5.77

< 4.53

< 4,37 B-19

TABLE B-10 CONCENTRATIONS OF TRITIUM IN-SURFACE WATER SAMPLES -2007 (QUARTERLY COMPOSITE SAMPLES)

Results in Units of pCi/I +/- 1 Sigma STATION CODE PERIOD DATE TRITIUMLI First Quarter 12/29/06 03/30/07

<476 PLANT INTAKE (HUDSON RIVER)

Second Quarter 03/30/07 06/29/07

< 443 (09, INLET) **

Third Quarter 06/29/07 09/28/07

< 449 Fourth Quarter 09/28/07 12/31/07

< 439 First Quarter 12/29/06 03/30/07

<476 DISCHARGE CANAL Second Quarter 03/30/07 06/29/07

< 443 (10, MIXING ZONE)

Third Quarter 06/29/07 09/28/07

< 449 Fourth Quarter 09/28/07 12/31/07

<439

• • Control Sample location B-20

TABLE B-1i CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES-2007 Results in Units of pCi/liter +/- 1 Sigma CAMP FIELD RESERVOIR Date 01/09/2007 02/06/2007 03/06/2007 04/03/2007, 05/08/2007 06/12/2007."

N(JCLIDE:.......

1-131

< 0.25

< 0.26

< 0.37

< 0.35

< 0.27

< 0.41 Cs-134

< 2.23

< 3.52

< 3.96

< 4.42

< 3.57

< 2.52 Cs-137

< 2.73

< 3.68

< 2.95

< 2.50

< 3.18

< 2.45 Zr-95

< 3.24

< 5.06

< 6.19

< 5.39

< 5.92

< 4.18 Nb-95

< 2.78

< 3.97

< 4.24

< 4.49

< 3.37

< 2.83 Co-58

< 2.13

< 3.51

< 3.98

< 4.44

< 3.60

< 2.31 Mn-54

< 2.16

< 2.97

< 2.97

< 4.11

< 4.00

< 2.24 Fe-59

< 5.15

< 9.96

< 10.92

< 8.47

< 12.62

< 5.16 Zn-65

< 5.21

< 6.54

< 8.03

< 9.12

< 7.78

< 4.50 Co-60

< 1.74

< 5.52

< 5.04

< 2.30

< 4.42

< 2.21 K-40 321.2 +/- 35.25 231.5 +/- 45.77

< 42.91 275.6 +/- 48.57 89.5 +/- 31.21 99.1 +/- 26.92 Ba/La-140

< 2.90

< 4.96

< 4.80

< 5.31

< 4.94

< 2.14 Date 07/10/2007/

.. 08/07/2007.

09/11/2007:,. [

10/09/2007::.

11/19/2007 1 12/218/2007:

1-131

< 0.33

< 0.31

< 0.38

< 0.32 Cs-134

< 2.59

< 2.84

< 1.94

< 2.51

< 1.63

< 1.93 Cs-137

< 2.62

< 2.12

< 3.58

< 3.15

< 2.38

< 2.77 Zr-95

< 4.35

< 4.60

< 5.99

< 4.86

< 3.65

< 3.94 Nb-95

< 2.91

< 2.71

< 4.46

< 3.16

< 2.16

< 2.32 Co-58

< 2.23

< 2.49

< 4.50

< 3.36

< 2.16

< 2.88

'Mn-54

< 2.80

< 1.90

< 4.28

< 3.49

< 1.94

< 2.41 Fe-59

< 6.52

< 7.41

< 9.80

< 8.79

< 3.99

< 8.78 Zn-65

< 6.36

< 6.05

< 13.23

< 6.39

< 6.45

< 9.14 Co-60

< 2.42

< 2.84

< 3.90

< 3.97

< 2.25

< 2.58 K-40 197.3 +/- 31.68 133.6 +/- 30.08 326,8 +/- 47.02 85.98 +/- 32.57 131 +/- 22,62 215 +/- 32.21 Ba/La-140

< 3.49

< 3.06

< 2.35

< 3.13

. < 3.23

< 3.44 B-21

TABLE B-I1 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2007 Results in Units of pCi/liter +/- I Sigma NEW CROTON RESERVOIR Date NUCLIDE 1-131

< 0.26

< 0.23

< 0.34

< 0.32

< 0.34

< 0.30 Cs-134

< 3.65

< 3.50

< 2.84

< 3.64

< 2.81

< 3.26 Cs-137

. < 3.17

< 3.53

< 2.90

< 3.89

< 2.88

< 2.52 Zr-95

< 5.16

< 6.50

< 6.03

< 5.77

< 5.99

< 4.92 Nb-95

< 3.60

< 4.16

< 2.68

< 3.53

< 3.65

< 3.05 Co-58

< 2.62

< 3.71

< 2.24

< 3.49

< 3.90

< 2.88 Mn-54

< 2.70

< 3.22

< 2.49

< 3.19

< 4.28

< 2.97 Fe-59

< 7.57

< 6.41

< 5.37

< 12.84

< 9.82

< 9.08 Zn-65

< 9.13

< 3.31

< 6.83

< 8.86

< 11.53

< 7.41 Co-60

< 3.08

< 3.60

< 2.31

< 4.21

< 4.21

< 2.66 K-40 221.9 +/- 38.95

< 40.52 177 +/- 32.14 243.1 +/- 47.97 347.2 +/- 53.88 137.6 +/- 27.55 Ba/La-140

< 4.62

< 4.21

< 2.23

< 6.23

< 5.28

< 3.96 Date.

07/10/2007, 08/07/2007-

. 09/11/2007

[

10/09/2007_j 11/19/2007:.:

12/18/2007.1.

1-131

< 0.29

< 0.25

< 0.31

< 0.30 Cs-134

< 2.35

< 2.38

< 3.40

< 2.51

< 1.78

< 2.89 Cs-137

< 2.45

< 2.19

< 3.29

< 2.29

< 1.96

< 2.39 Zr-95

< 4.43

< 3.78

< 3.75

< 5.18

< 4.34

< 5.13 Nb-95

< 2.62

< 2.89

< 3.69

< 2.78

< 3.00

< 3.19 Co-58

< 2.59

< 2.61

< 2.49

< 3.11

< 2.52

< 3.00 Mn-54

< 2.88

< 2.85

< 3.62

< 3.42

< 2.30

< 2.54 Fe-59

< 8.76

< 6.30

< 7.84

< 7.54

< 6.24

< 7.14 Zn-65

< 5.36

< 5.36

< 7.96

< 5.91

< 3.12

< 7.29 Co-60

< 3.02

< 2.47

< 2.38

< 2.76

< 2.32

< 2.06 K-40 139.6 +/- 29.84 315.7 +/- 35.43 201 +/- 42.41 277.3 +/- 41.09 146.9 +/- 27.10 142.8 +/- 29.31 Ba/La-140

< 4.33

< 3.04

< 3.82

< 3.81

< 3.35

< 3.46 B-22

TABLE B-12 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES - 2007 (QUARTERLY COMPOSITE SAMPLES)

Results in Units of pCi/l +/- 1 Sigma STATION CODE PERIOD DATE j...TRITIUM First Quarter 12/12/06.

03/06/07

< 461.00 CAMP FIELD RESERVOIR Second Quarter 03/06/07 06/12/07

< 436.00 Third Quarter 06/12/07 09/11/07

< 448 Fourth Quarter 09/11/07 12/18/07

< 433 First Quarter 12/12/06 03/06/07

< 461.00 NEW CROTON RESEVOIR Second Quarter 03/06/07 06/12/07

< 436.00 Third Quarter 06/12/07 09/11/07

< 448 Fourth Quarter 09/11/07 12/18/07

< 433 B-23

TABLE B-13 CONCENTRATIONS OF RADIONUCLIDES IN SHORELINE SOIL SAMPLES - 2007 Results in Units of pCi/kg +/- I Sigma Sample COLD SPRING LENTS COVE' ANITOU VERLANCK WI BEACH

'Location SHORELINE SHORELINE SHORELINE SHORELINE SHORELINE Date

06/06/2007 06/06/2007.:

06/06/2007 06/0/2007 6/07/2007 Client ID ISS842307 ISS282307 ISS502307 ISS172307 ISS532307 Radionuclide I Req. CL F Be-7 234.9 319.8 448.6 165.3 176.4 1-131 44.2 80.7 118.3 39.9 30.3 Cs-134 75 31.4 46.2 36.2 11.3 11.2 Cs-137 90 26.0 54.7 357.0

+/-

33.4 63.3

+/-

18.1 19.6 Zr-95 46.6 82.9 62.3 41.3 35.7 Nb-95 34.6 68.6 55.3 30.0 26.3 Co-58 30.3 39.5 47.8 22.2 18.6 Mn-54 28.7 49.1 46.4 15.1 20.0 Zn-65 92.4 52.5 115.3 54.8 61.3 Fe-59 95.9 143.4 125.4 53.6 60.2 Co-60 37.9 41.0 49.4 22.1 15.5 Ba/La-140 40.3-96.6 59.0 45.4 30.9 Ru-103 20.6 44.6 51.2 20.4 22.2 Ru-106 298.9 381.1 555.5 264.8 202.5 Ce-141 45.9 63.6 86.0 39.8 30.7 Ce-144 164.1 259.6 341.1 150.2 104.7 AcTh-228 468.4

+/-

98.0 1052.0

+/-

187.2 806.3

+/-

154.1 194.3

+/-

64.0 61.5 Ra-226 593.0 2250.0

+/-

702.7 2006.0

+/-

737.3 1194.0

+/-

388.5 979.4

+/-

314.7 K-40 36000.0

+/-

1070.0 15770.0

+1-1077.0 24470.0

+1-1177.0 5423.0

+1-411.2 9411.0

+/-

598.1 Sr-90 5000 140 B-24

TABLE B-13 CONCENTRATIONS OF RADIONUCLIDES IN SHORELINE SOIL SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma Sample LocanCOLD SPRING LENTS COVE MANITOU-:

VERPLANCK WHITE BEACH Sample Location

'l s

RENE"I SHORELINE SHORELINE SHORELINE SHORELINE.

SHORELINE.,.

Date 09/06/2007 09/06/2007 09/06/2007 09/07/2007 09/07/2007 Client ID 1SS843607 ISS283607 ISS503607 ISS173607R1 1SS533607 Radionuclide Req. CL Be-7 312.9 332.2 615.1 175.9 167.6 1-131 46.4 57.6 86.9 30.9 26.5 Cs-134 75 24.2 39.9 58.2 23.4 18.5 Cs-137 90 38.3 37.3 67.0 149.0

+/-

22.6 19.2 Zr-95 70.0 59.9 107.1 36.7 30.8 Nb-95 38.2 52.4 78.1 20.1 27.2 Co-58 37.7 43.3 32.7 18.6 20.7 Mn-54 33.6 37.3 48.7 24.7 20.3 Zn-65 68.5 46.1 198.1 58.9 66.3 Fe-59 147.0 107.0 98.2 57.7 51.6 Co-60 50.9 39.5 39.9 21.2 28.4 Ba/La-140 57.0 55.1 114.6 22.2 24.2 Ru-103 32.3 39.7 52.4 24.4 18.8 Ru-106 268.8 309.3 383.3 163.2 191.8 Ce-141 51.7 58.8 80.1 31.8 23.7 Ce-144 167.4 235.8 324.0 123.3 112.0 AcTh-228 691.6

+1-138.8 992.0

+/-

151.6 1380.0

+/-

284.0 141.9

+/-

71.2 77.8 Ra-226 1508.0

+/

492.5 3924.0

+/-

683.2 2561.0

+/-

1041.0 748.8

+/-

371.0 397.7 K-40 1

31600.0

+/-

1200.0 14540.0

+/-

894.9 10230.0

+/-

1239.0 8613.0

+/-

624.5 8537.0

+/-

586.1 Sr-90 5000 300 350 370 270 1200 B-25

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units of pCi/kg +/- I Sigma

1. 95 Meteorological Tower Sampe J-,

.MET TOWER VMET TOWER MET TOWER MET TOWER MET.TOWER IMET TOWER

,Date

__,l 05/24/2007 05/24/2007 05/25/2007 06/26/2007 06/26/2007 j 06/26/2007 Client ID 1BV952107S3 1BV952107S2 IBV952107S1 IBV952607S1 IBV952607S2 1BV952607S3 MULLEN RAG WEED MOTHERS WORT GRAPE LEAVES RAGWEED MULLEN Radionuclide Req. CL Be-7 73.05 441.1

+/-

81.2 357.1

+/-

73.5 394.1

+/-

53.9 681.3

+/-

84.9 422.9

+/-

82.2 1-131 so 18.99 16.52 27.21 7.27 10.59 13.44 Cs-134 50 11.49 13.43 11.74 8.34 13.63 14.78 Cs-137 50 9.71 9.92 8.97 6.35 10.15 11.96 Zr-95 14.46 14.50 15.75 11.71 19.55 19.25 Nb-95 9.44 11.31 13.31 7.76 12.38 10.99 Co-58 11.60 9.71 13.34 7.53 13.16 11.02 Mn-54 10.51 11.30 10.59 7.54 11.54 11.06 Zn-65 29.73 28.85 31.51 19.45 29.27 29.20 Fe-59 30.05

< 46.86 48.51 19.06 42.10 32.25 Co-60 8.62 12.01 8.51 6.92 16.93 16.49 Ba/La-140 13.10 18.44 28.56 6.74 13.62 11.06 Ru-103 9.16 9.82 12.63 6.23 10.93 10.39 Ru-106 91.08 93.88

< 120.90 74.87 94.36 120.80 Ce-141 12.72 12.38 16.66 9.80 11.93 14.98 Ce-144 48.86

< 42.50 58.89 41.41 47.90 58.53 AcTh-228 34.94 37.75 46.54 25.89 48.41 53.57 Ra-226 146.30

< 150.70 312.4

+/-

131.1 218.8

+1-121.9 280.2

+/-

138.6 210.50 K-40 5208.0

+/-

275.0 6498.0

+/-

300.7 4962.0

+/-

320.2 4307.0

+/-

203.4 10580.0

+/-

386.5 7602.0

+/-

395.4 B-26

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma

1. 95 Meteorological Tower Sample MET TOWER MET TOWER MET TOWER METTOWER MET-TOWER.

METTOWER

.Date 07/24/2007 07/24/2007 e

07/24/2007 08/14/2007, 08/14/2007 08/14/2007 Client ID IBV953007SI IBV953007S2 fBV953007S3 IBV953307S1 1BV953307S2 IBV953307S3 GRAPE LEAVES RAGWEED MULLEN GRAPE LEAVE RAGWEED CATALPA Radionuclide Req. CL Be-7 491.8

+/-

77.3 1007.0

+1-99.2 1258.0

+/-

131.6 746.5

+/-

73.1 2332.0

+/-

121.1 1047.0

+/-

95.8 1-131 50 12.16 17.77 18.01 16.82 16.43 18.17 Cs-134 50 9.64 8.67 7.73 8.73 11.80 12.56 Cs-137 50 9.37 9.48 12.30 6.74 9.00 10.80 Zr-95 20.83 22.03 17.45 13.15 16.85 19.57 Nb-95 10.04 13.02 13.63 9.27 12.70 12.71 Co-58 9.49 11.87 12.23 7.84 9.80 11.56 Mn-54 10.05 13.38 11.92 7.96 9.31 12.17 Zn-65 32.62 31.94 36.43 18.90 30.37 36.59 Fe-59 33.42 35.49 41.73 25.76 32.09 37.74 Co-60 9.03 11.71 13.49 9.40 9.52 16.51 Ba/La-140 18.70 16.44 11.31 11.85 17.74 23.26 Ru-103 11.85 10.24 11.49 7.43 9.68 10.86 Ru-106 96.38

< 109.60 111.90 89.75 93.88 95.17 Ce-141 11.69 17.94 13.90 1-1.84 12.37 15.04 Ce-144 43.14 69.45 55.13 44.93 42.83 46.99 AcTh-228 40.90

< 40.06 44.84 25,64 34.75

<..43.88 Ra-226 175.60

< 225.80

< 212.60

< 139.50 340.6

+1-97.3 366.8

+/-

133.1 K-40 13716.0

+/-

264.0 8313.0

+/-

343.1 6807.0

+/-

380.4 4246.0

+/-

205.8 7933.0

+/-

300.7 6510.0

+/-

288.6 B-27

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma

1. 95 Meteorological Tower Sample Location METTOWER MET TOWER MET TOWER

..:,,,MET.TOWER NMET TOWER

.MET TOWER Date'

-can.

09/18/2007 09/18I2007, 09/18/20107 I

10/16/2007 10/16/2007 10/16/2007 Client ID IBV953807S1 IBV953807S2 1BV953807S3 IBV954207S]

IBV954207S2 1BV954207S3 GRAPE LEAVES RAGWEED MULLEIN GRAPE LEAVES RAGWEED MULLEIN Radionuclide Req. CL Be-7 929.3

+/-

94.6 1715.0

+/-

118.3 362.2

+/-

85.9 1214.0

+/-

96.9 2203.0

+/-

157.3 755.2

+/-

94.1 1-131 50 9.79 12.14 13.83 12.85 14.82 11.32 Cs-134 50 13.59 13.33 9.17 8.50 18.55 12.13 Cs-137 50 7.73 9.84 14.32 6.62 13.55 9.82 Zr-95 14.96 18.34 23.08 14.97 23.41 16.86 Nb-95 10.44 10.14 16.12 10.20 13.46 12.26 Co-58 11.80 12.51 15.19 8.45 17.00 8.66 Mn-54 10.44 11.69 15.53 8.22 13.48 10.57 Zn-65 23.10 27.20 44.00 21.80 32.83 26.33 Fe-59 23.00 28.69 48.12 20.26 40.10 35.01 Co-60 "

12.11 9.10 21.25 12.40 20.87 12.86 BalLa-140 11.41 9.33 16.40 6.78 17.40 12.12 Ru-103 8.41 8.92 10.75 8.10 12.76 8.35 Ru-106 103.00 99.95 117.90 75.51 133.60 108.80 Ce-141 13.27 13.78 15.38 12.01 17.88 11.26 Ce-144 56.27 64.28 57.44 53.08 82.95 49.55 AcTh-228 34.20 46.23 56.26 31.59 54.58 35.01 Ra-226 299.2

+/-

179.2 200.70 250.10 174.80 510.8

+/-

216.9 190.40 K-40 3719.0

+/-

249.0 7667.0

+/-

347.4 7117.0

+/-

373.7 4006.0

+/-

228.4 8246.0

+/-

454.5 6177.0

,+/-

• 309.9 B-28

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma

1. 23 Roseton **

Sample ROSETON ROSETON ROSETON.:.

ROSETON ROSETON ROsETON Date 05/24/2007 05/24/2007

.05/24/2007 06/25/2007, 06/25/2007 i06/25/2007 Client ID IBv232107SI IBV232107S2 IBv232107S3 1BV232607SI lBV232607S2 IBV232607S3 RAGWEED BURDOCK MULLEN RAGWEED BURDOCK MULLEN Radionuclide Req. CL Be-7 406.5

+1-95.8 389.9

+1-59.2 165.9

+1-64.9 1084.0

+1-105.7 1352.0

+/-

83.5 1130.0

+1-135.4 1-131 50 27.19 16.65 23.51 12.27 8.19 17.41 Cs-134 50 12.10 9.90 12.94 13.35 10.85 17.92 Cs-137 50 10.85 6.89 9.67 11.65 8.25 15.90 Zr-95 21.42 17.45 16.28 18.80 14.73 24.09 Nb-95 14.49 9.31 11.56 12.70 7.45 15.30 Co-58 12.42 7.19 11.21 12.95 8.47 9.28 Mn-54 13.49 9.65 9.25 10.63 8.71 19.39 Zn-65 31.73 30.83 22.32 29.58 23.68 46.40 Fe-59 57.99 24.10 33.86 41.95 26.95 44.85 Co-60 13.58.

9.40 9.70 15.35 8.44 16.27 Ba/La-140 9.90 15.22 19.09 11.92 12.88 16.78 Ru-103 10.99 6.78 12.63 10.31 7.76 11.72 Ru-106 99.86 62.41 110.00 126.00 82.92 138.00 Ce-141 17.01 9.87 12.25 12.39 9.39 17.78 Ce-144 66.45 33.14 46.19 59.93 32.27 74.82 AcTh-228 1

37.64 29.74 34.95 47.51 28.42 53.33 Ra-226

< 208.30

< 115.40 155.70 208.70 130.50 385.0

+/-

213.4 K-40 18773.0

+/-

406.3 5144.0

+/-

249.1 3757.0

+/-

252.3 10020.0

+/-

412.2 6088.0

+/-

248.3 5830.0

+/-

402.7 Control Sample Location B-29

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units of pCi/kg + 1 Sigma

1. 23 Roseton **

ROSETON ROSETON rOSETON

-ROSETON ROSETON ROSETON:'

.. Date 07/23/2007 07/23/2007 07/23/2007 08/13/2007 08/13/2007 08/13/2007,,

Client ID 1BV233007S 1 IBV233007S2 IBV233007S3 1BV233307S1 1BV233307S2 IBV233307S3 Req. CL CATALPA BURDOCK MULLEN GRAPE LEAVES RAGWEED MULLEN Radionuclide (pCi)

Be-7 141.5

+/-

71.0 1411.0

+/-

107.5 504.4

+/-

82.2 541.5

+/-

88.5 1990.0

+/-

144.4 2027.0

+/-

139.7 1-131 50 13.77 14.60 18.33 23.19 26.68 25.24 Cs-134 50 11.49 9.97 11.34 13.95 17.31 13.58 Cs-137 50 9.32 6.86 11.06 12.91 11.74 10.15 Zr-95 11.35 11.77 18.85 19.02 24.50 11.85 Nb-95 8.55 6.61 8.87 12.49 15.12 17.40 Co-58 11.24 7.95 11.34 12.11 16.73 8.45 Mn-54 8.06 9.92 9.94 8.51 14.63 9.53 Zn-65 17.59 23.96 29.01 33.00 46.81 15.40 Fe-59 32.87 23.90 33.82 22.92 52.13 37.44 Co-60 9.29 11.90 15.87 15.42 21.23 10.64 Ba/La-140

.6.85 10.46 8.64 17.60 24.23 24.24 Ru-103 11.55 8.32 9.01 11.06 13.27 12.54 Ru-106 66.64 85.69 96.44 85.24 124.30 110.80 Ce-141 10.71 12.36 13.70 12.54 17.30 16.31 Ce-144 39.73 42.25 61.21 42.12 53.71 59.70 AcTh-228 22.66 30.64 42.01 40.03 48.92 36.33 Ra-226

< 157.10

< 155.70

< 192.40

< 181.20 220.00 183.90 K-40 2478.0

+/-

211.3 6527.0

+/-

298.3 4840.0

+/-

277.8 3640.0

+/-

246.0 7920.0

+/-

358.9 3590.0

+/-

243.8 Control Sample Location B-30

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units of pCi/kg +/- I Sigma

1. 23 Roseton **

Sample LocationROSETON R.OSETON ROSETON ROSFTON ROSETON ROSETONTl

Location Date 09/17/2007 09/17/2007 09/17/2007 10/15/2007 10/15/2007 10/15/2007 Client ID IBV233807S1 IBV233807S2 IBV233807S3 1BV234207S1 IBV234207S2 IBV234207S3 MULLEIN RAGWEED CATALPA MULLEN RAGWEED CATALPA Radionuclide Req. CL Be-7 1589.0

+/-

142.8 994.1

+1-114.0 693.1

+/-

87.2 1679.0

+/-

185.7 1961.0

+/-

140.4 1771.0

+/-

94.1 1-131 50 17.12 11.84 10.81 21.35 15.31 11.14 Cs-134 50 16.78 12.18 12.76 21.33 12.20 8.23 Cs-137 50 14.27 12.29 8.32 17.33 12.82 7.78 Zr-95 23.44 22.37 18.96 19.63 23.40 12.55 Nb-95 16.53 11.41 7.72 21.11 13.88 7.76 Co-58 14.47 11.52 11.48 16.56 12.36 5.86 Mn-54 15.07 11.84 8.76 18.93 12.90 7.08 Zn-65 44.37 26.80

< 27.74 56.50 16.03 17.21 Fe-59 49.21 39.91 26.74 54.21 36.91 21.02 Co-60 17.12 11.39 12.00 25.33 14.26 6.57 Ba/La-140 21.48 13.69 5.36 20.04 14.25 9.19 Ru-103 9.53 10.93 9.59 12.89 10.09 6.94 Ru-106 145.10 111.30 88.46 175.50 106.50 88.35 Ce-141 20.31 13.53 14.15 22.65 15.18 11.39 Ce-144 68.00 56.57 51.31 100.40 47.94 48.36 AcTh-228 58.61 44.71 30.05 126.5

+/-

59.9 42.54 30.34 Ra-226 226.20 226.70 151.90 334.90

< 241.70 146.90 K-40 4950.0

+1-363.5 6742.0

+/-

380.3 3412.0

+/-

245.5 8119.0

+/-

494.8 7434.0

+/-

366.0 3715.0

+/-

188.1 Control Sample Location B-31

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units of pCi/kg + I Sigma

1. 94 IPEC Training Center S am ple.

Samp TRAINING BLDG TRAINING.BLDG.

TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING.BLDG Location Date 05/24/2007 05/24/2007

'05/24/2007 06/26/2007:,

06/26/2007 06/26/2097 Client ID IBV942107S1 IBV942107S2 1BV942107S3 IBV942607S1 IBV942607S2 IBV942607S3 BURDOCK MULLEN RAGWEED GRAPE LE MULLEN RAGWEED Radionuclide Req. CL Be-7 613.8

+/-

84.1 235.4

+/-

90.5 293.2

+/-

67.0 560.2

+/-

63.8 538.7

+1-80.2 997.7

+/-

108.9 1-131 50 24.59 21.68 20.77 7.01 8.50 13.35 Cs-134 50 9.18 15.91 9.46 8.56 14.08 15.96 Cs-137 50 9.04 11.65 7.21 7.01 9.97 12.42 Zr-95 16.48 21.08 20.03 11.11 18.57 23.32 Nb-95 11.32 15.40 13.04 8.35 12.47 14.33 Co-58 9.56 12.65 10.68 7.62 10.30 15.06 Mn-54 9.27 11.05 10.46 7.48 11.54 10.40 Zn-65 29.95 34.24 23.90 20.38 34.46 36.27 Fe-59 31.31 45.19 29.75 20.44 36.16 47.44 Co-60 10.02 15.16 5.96 7.36 15.97 15.50 Ba/La-140 5.54 21.45 16.18 7.10 11.37 13.31 Ru-103 7.76 12.27 8.52 6.14 10.25 9.42 Ru-106 77.09

< 104.90 79.41 72.78 91.08 112.30 Ce-141 11.10 16.79 14.55.

9.68 12.53 14.83 Ce-144 47.63 61.57 53.33 40.26 46.90 66.81 AcTh-228 32.40 43.30 30.89 28.87 44.82 44.78 Ra-226 148.50

< 209.90

< 139.00 260.3

+/-

108.4 179.00 227.20 K-40 7976.0

+/-

291.2 6472.0

+/-

333.8 7224.0

+/-

281.2 4342.0

+1-197.8 7540.0

+/-

331.3 10130.0

+/-

467.0 B-32

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units of pCi/kg + 1 Sigma

1. 94 IPEC Training Center SampleJ Lamloc atio I oIn TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAININGBBLDG:

TRAINING BLDG Date I

07/24/2007 07/24/2007 07/2412007 08/14/2007 08/14/2007 08/14/2007 Client ID IBV943007S1 IBV943007S2 IBV943007S3 IBV943307S1 IBV943307S2

]BV943307S3 GRAPE LEAVES MULLEN RAG WEED GRAPE LE BURDOCK RAGWEED Radionuclide Req. CL Be-7 831.5

+/-

118.6 1097.0

+/-

104.5 916.9

+-/-

125.3 1585.0

+/-

105.1 346.4

+/-

92.5 1492.0

+/-

134.5 1-131 50 14.37 16.38 19.93 18&16 20.72 26.73 Cs-134 50 12.89 10.47 19.76 9.82 15.78 13.85 Cs-137 50 9.26 10.50 16.32 8.77 12.85 12.31 Zr-95 15.66

< 21.68 23.25 16.52 25.16 23.18 Nb-95 14.83 15.56 14.67 10.05 15.95 14.79 Co-58 10.96 9.88 12.37 10.39 10.47 15.48 Mn-54 14.32 13.09 17.46 10.83 10.73 14.65 Zn-65 25.76 16.40 43.55 25.86 27.85 25.77 Fe-59 33.86 33.51 57.00 31.31 52.61 55.43 Co-60 14.54 10.25 13.80 10.48 10.08 14.28 Ba/La-140 20.05 13.78 30.32 18.13 26.26 18.79 Ru-103 9.86 10.29 13.65 8.90 12.52 13.34 Ru-106 92.23 90.79

< 150.10 85.99 149.40 108.50 Ce-141 12.52 16.13 18.07 14.03 16.79 17.93 Ce-144 58.37 65.13 55.64 49.71 52.33 69.60 AcTh-228 31.12

< 45.20

< 46.22 30.53-58.82 50.57 Ra-226 166.60 362.0

+/-

175.2

< 230.70 256.0

+/-

129.6 253.5

+/-

145.7 234.60 K-40 4100.0

+/-

293.0 7202.0

+/-

328.7 9241.0

+/-

482.9 4136.0

+/-

231.0 5268.0

+/-

396.7 8102.0

+/-

404.9 B-33

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma

1. 94 IPEC Training Center Sample Locat.on TRAINING BLDG TRAINING BLDG.

TRAINING BLDG TRAINING BLDG.

TRAINING BLDG.

TRAINING BLDG Date' 09/18/2007 09/18/2007 09/18/2007:.

10/6/2007 10/16/2007, 10/16/2007 Client ID IBV943807SI IBV943807S2 IBV943807S3 IBV944207SI IBV944207S2 IBV944207S3 GRAPELEAVES MULLEIN RAGWEED GRAPE LE MULLEN RAGWEED Radionuclide Req. CL GRELAE Be-7 1345.0

+/-

105.7 539.2

+/-

83.5 1440.0

+/-

146.5 2445.0

+/-

164.7 314.8

+/-

54.4 2255.0

+/-

147.3 1-131 50 12.91 26.90 14.73 12.31 7.31 12.15 Cs-134 50 11.06 12.41 10.65 12.05 8.90 14.17 Cs-137 50 9.24 8.45 13.38 13.34 6.91 11.70 Zr-95 17.68 19.26 30.52 22.31 13.52 23.37 Nb-95 11.46 12.49 20.10 13.74 8.15 13.93 Co-58 9.74 10.82 16.24 12.24 6.64 13.63 Mn-54 10.97 10.12 18.94 13.22 8.48 12.65 Zn-65 29.70 30.89 58.15 30.11 21.11 30.71 Fe-59 25.02 35.04 56.13 34.50 28.90 42.12 Co-60 12.39 10.57 21.37 9.60 7.22 18.43 Ba/La-140 15.63 18.94 25.72 8.65 8.32 10.32 Ru-103 9.51 10.06 15.31 13.29 8.36 12.73 Ru-106 115.00 92.89

.161.70 145.50 91.07 136.70 Ce-141 14.60 15.71 18.53 15.71 8.63 15.01 Ce-144 63.04 57.79 70.35 58.49 40.61 56.59 AcTh-228 32.22 52.2

+/-

27.3 59.71 36.52 24.55 54.05 Ra-226 203.30 180.00 269.20 204.60 213.7

+/-

106.8

< 223.10 K-40 6580.0

+/-

309.2 7892.0

+/-

291.2 7873.0

+/-

455.9 3811.0

+/-

327.3 4757.0

+/-

228.5 6010.0

+/-

337.7 B-34

TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma

1. 25 Downstream (Hudson River)

'Sample Location VOP FISH VOP FISH VOP FISH

-VPFS O

iHVPFS

Date, 06/06/2007 06/06/2007 06/07/2007

/08/2007.

0r6/08/2007 06/11/2007 Client ID IFH252407S6 IFH252407S4 1FH252407S2 IFH252407S5 1FH252407S3 IFH252507S7 CRABS WHITE PERCH STRIPED BASS CARP CATFISH SUNFISH Radionuclide Req. CL Be-7 289.1 322.6 214.0 255.9 269.8 373.3 1-131

< 1042.0 1360.0 972.2 971.1 857.3 1023.0 Cs-134 65 23.1 23.5 20.5 17.9 17.8 24.6 Cs-137 75 18.9 17.6 15.7 15.7 17.5 22.6 Zr-95 59.6 54.7 41.9 44.7 48.1 73.4 Nb-95 50.1 50.4 39.9 38.5 39.6 56.8 Co-58 65 38.1 26.5 26.0 29.5 26.0 29.9 Mn-54 65 20.4 25.0 16.6 19.5 19.2 28.8 Zn-65 130 50.3 59.7 41.1 46.4 49.7 64.7 Fe-59 130 90.9 99.1 83.5 95.5 69.9 107.5 Co-60 65 23.9 29.7 17.8 23.5 17.9 22.9 Ba/La-140 442.3 254.7 268.1 252.2 193.5 360.2 Ru-103 49.2 49.8 35.1 32.1 37.6 54.5 Ru-106 217.1 250.7 186.4 212.9 173.1 274.8 Ce-141 75.9 77.0 46.5 56.0 50.9 73.5 Ce-144 115.8 135.6 102.1 103.8 88.6 134.4 AcTh-228 62.9 74.8 66.3 50.5 52.7 97.6 Ra-226 361.6 429.1 295.3 723.7

+/-

245.7 286.8 1001.0

+/-

376.6 K-40 3784.0

+/-

373.4 4656.0

+/-

484.3 3680.0

+/-

333.1 4399.0

+1-331.8 3913.0

+/-

343.2 7191.0

+1-.

468.2 Sr-90 5

7.1 8.6 6

6.8 7.7 14 B-35

TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2007 Results in Units of pCi/kg +/- I Sigma

1. 25 Downstream (Hudson River)

"Sample, Loain

.VOP FISH VOP FISH VOP FISH.

.VOP FISH VOP FISH VOP FISH, D ~cate~n

.r06/13/2007 08/16/2007"

ý28/16/2007 08/20/2007.

08/24/200I7 l

08/29/2007 Client ID IFH252507S1 IFH254407S1 IFH254407S5 IFH254407S4

[FH254407S3 IFH254407S2 AMERICAN EEL BLUE CRAB WHITE PERCH AMERICAN EEL CATFISH SUN FISH Radionuclide Req. CL 1

1 1

Be-7 306.7 203.3 309.0 223.4 213.8 267.5 1-131 658.1 5898.0 10980.0

< 5610.0 4142.0 3583.0 Cs-134 65 22.8 8.9 10.6 10.9 7.1 10.0 Cs-137 75 25.8 9.6 14.0 12.3 10.9 15.2 Zr-95 67.6 28.7 53.1 38.8 34.2 44.4 Nb-95 42.7 35.5 56.7 52.9 45.4 50.8 Co-58 65 21.6 17.4 29.3 23.9 20.7 26.2 Mn-54 65 22.6 9.9 17.4 13.6 13.5 18.0 Zn-65 130 60.1 25.2 24.3 18.3 20.2 23.0 Fe-59 130 86.5 80.7 114.6 90.4 88.3 90.7 Co-6O 65 28.8 9.8 14.7 12.6 12.4 15.7 Ba/La-140 267.7 583.5 774.0 645.4 479.7 395.1 Ru-103 39.7 34.9 53.9 38.8 38.5 41.2 Ru-106 232.3 104.3 160.5 132.0 143.1 172.6 Ce-141 66.4 58.1 98.2 70.2 62.5 75.8 Ce-144 103.0 57.8 100.6 71.4 73.3 98.9 AcTh-228 93.5 95.8

+/-

29.2 219.5

+/-

41.4 99.4

+1-33.0 48.6

+/-

29.9 55.0 Ra-226 401.0 707.8

+/-

155.2 580.8

+/-

209.5 521.0

+/-

187.4 456.1

+/-

158.1 968.4

+/-

215.9 K-40 3629.0

+/-

422.8 4690.0

+/-

183.9 4539.0

+/-

206.2 5245.0

+/-

222.3 4154.0

+/-

219.7 4196.0

+/-

196.3 Sr-90 5

6.6 7.1 6.5 6.3 6.8 5.2 B-36

TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES-2007 Results in Units of pCi/kg +/- 1 Sigma

1. 23 Roseton (Control)

Sample..

ROSETON FISH

.!ROSETONFISH ROSETON FIFISROSETON FISH ROSETON FISH Location Date 06/07/2007 06/07/2007.......

06/07/2007.,

06/07/20*706/13/2007 08/14/2007, Client ID IFH232407S]

1FH232407S3 IFH232407S4 1FH232407S5 IFH232507S2 IFH234407S4 AMERICAN EEL CARP CATFISH WHITE PERCH SUNFISH WHITE PERCH Radionuclide Req. CL Be-7 194.6 210.0 190.2 238.9 169.6 359,8 1-131 744.3 896.0 855.9 999.5 476.2 14910.0 Cs-134 65 16.2 20.0 14.0 15.5 16.5 17.6 Cs-137 75

.17.2 18.0 12.5 15.0 15.2 15.9 Zr-95 43.1 46.9 33.4 41.6 38.5 63.5 Nb-95 36.6 41.9 35.0 43.8 29.0 79.6 Co-58 65 21.7 25.1 23.0 22.0 21.3 39.0 Mn-54 65 15.3 22.3 15.0 11.9 16.6 17.3 Zn-65 130 35.8 48.9 32.5 41.5 34.2 28.5 Fe-59 130 86.7 106.4 68.7 71.9 53.3 107.8 Co-60 65 18.2 21.3 14.6 16.3 20.8 19.8 Ba/La-140 197.4 329.7 158.8 235.4 140.9 1306.0 Ru-103 33.1 42.3 27.1 26.7 23.0 63.8 Ru-106 156.4 162.9 132.6 151.1 173.2 200.2 Ce-141

<_ 43.0 47.0 44.2 41.1 23.1 98.6 Ce-144 77.4 72.8 79.0 78.0 73.0 92.3 AcTh-228 52.4 66.3 41.2 59.0 44.6 66.5 Ra-226 251.6 833.9

+/-

240.7 232.9 267.7 667.5

+/-

178.4 617.1

+/-

268.4 K-40 3849.0

+/-

276.6 4407.0

+1-342.6 5490.0

+/-

266.8 3751.0

+/-

280.4 3405.0

+/-

303.4 5439.0

+/-

308.5 Sr-90 5

7.2 9.5 5.2 8.3 7.2 6.8 B-37

TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2007 Results in Units of pCi/kg +/- I Sigma

1. 23 Roseton (Control)

Sample ROSETON FISH ROSETON FISH ROSETON FISH ROSETON FISH

Location, Date

08/15/20070.8:::

/24 08/24/2007 08/31/2007...

Client ID IFH234407S3 IFH234407S2 IFH234407S5 IFH234407S1 BLUE CRAB AMERICAN EEL SUNFISH CAT FISH Radionuclide Req. CL Be-7 228.9 252.5 215.3 216.4 1-131 7870.0 4760.0 4582.0 2880.0 Cs-134 65 13.2 14.7 8.0 14.9 Cs-137 75 11.0 16.1 12.5 15.5 Zr-95 38.4 51.0 45.1 47.3 Nb-95 48.1 51.5 45.8 52.1 Co-58 65 23.4 26.9 25.9 26.6 Mn-54 65 11.9 18.4 16.2 19.4 Zn-65 130 30.0 38.8 38.8 38.7 Fe-59 130 92.3 96.9 104.3 99.7 Co-60 65 12.3 13.6 16.5 20.7 Ba/La-140 709.6 590.6 875.6 490.9 Ru-103 45.7 44.6 42.2 35.9 Ru-106 119.0 151.9 140.7 184.0 Ce-141 66.5 71.3 60.5 67.0 Ce-144 63.4 86.0 75.5 77.8 AcTh-228 35.5 61.0 127.1

+1-46.5 64.2 Ra-226 419.9

+/-

130.3 511.5

+/-

182.0 599.8

+/-

185.3 796.7

+/-

210.3 K-40 4044.0

+/-

209.8 5483.0

+/-

285.2 5276.0

+/-

264.1 5481.0

+/-

310.0 Sr-90 5

6.9 6.5 6.7 7.6 B-38

TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma Catskill SapeCATSKILL FISH!

CATSKILL FISH CATSKILL FISH~ CATSKILL FISH CATSKILL FISH Location Date

6/0712007 06/07/2007:

06/07/2007 06/07/2007 06/19/2007 Client ID IFHCAT2407S5 IFHCAT2407S2 IFHCAT2407S3 IFHCAT2407S4 IFHCAT2607S I CARP AMERICAN EEL WHITE PERCH CATFISH SUNFISH Radionuclide Req. CL Be-7 199.4 254.2 182.8 207.1 201.6 1-131 849.4 971.4 999.4 999.6 421.5 Cs-134 65 16.4 13.8 14.3 9.4 18.7 Cs-137 75 15.0 18.1 13.1 15.0 14.9 Zr-95 36.6 46.7 37.8 44.0 37.0 Nb-95 33.1 47.2 32.1 37.1 31.2 Co-58 65 24.5 26.1 19.6 19.3 22.3 Mn-54 65 18.0 19.9 13.4 15.0 18.6 Zn-65 130 45.1 48.1 37.5 20.2 40.6 Fe-59 130 98.9 83.9 80.4 74.5 61.3 Co-60 65 16.7 16.3 16.1 13.7 16.5 Ba/La-140 249.5 340.8 224.0 203.0 129.5 Ru-103 30.4 37.3 27.8 32.1 31.2 Ru-106 170.2 157.9 139.2 164.2 177.9 Ce-141 44.0 60.2 46.1 54.6 44.8 Ce-144 62.5 91.1 77.1 82.8 107.1 AcTh-228 46.9 54.1 47.8 48.7 133.0

+/-

42.9 Ra-226 504.3

+/-

180.1 702.6

+/-

266.5 427.1

+/-

167.9 831.8

+/-

254.8 580.1

+/-

250.4 K-40 14487.0

+/-

293.7 3331.0

+/-

320.6 5681.0

+/-

273.5 4671.0

+/-

234.7 3946.0

+/-

258.2 Sr-90 5

6.1 6.8 7.9 7.8 6.6 B-39

TABLE B-16 CONCENTRATIONS OF GAMMA EMITTERS IN AQUATIC VEGETATION SAMPLES -

2007 Results in Units of pCi/kg 1 Sigma Sam lpe Location COLD SPRING COLD SPRING VERPLANCK Date 06/06/2007

.09,/06/2007:

06/07/2007 Client ID IAV842307 1AV843607 IAV172307 Aquatic WATERMILFOIL Aquatic Radionuclide Req. CL Be-7 230.2

+/-

46.4 90.5 445.3

+/-

75.0 1-131 30 10.9 14.0 17.1 Cs-134 30 4.9 6.6 11.7 Cs-137 40 6.2 12.6 31.0

+/-

6.4 Zr-95 9.1 18.9 16.5 Nb-95 6.3 15.4 11.9 Co-58 8.7 12.0 11.0 Mn-54 7.7 13.1 11.2 Zn-65 19.3 33.8 29.9 Fe-59 23.5 35.6 35.5 Co-60 8.8 8.7 9.8 Ba/La-140 16.2 9.7 18.7 Ru-103 6.9 11.0 9.1 Ru-106 66.7 115.1 100.6 Ce-141 8.7 13.0 15.3 Ce-144 30.2 50.3 56.1 AcTh-228 21.3 89.3

+/-

32.7 190.1

+/-

36.0 Ra-226 317.2

+/-

84.1 435.0

+/-

170.1 210.0 K-40 12500.0

+/-

157.2 1749.0

+/-

212.7 4320.0

+/-

279.3 B-40

TABLE B-17 CONCENTRATIONS OF GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2007 Results in Units of pCi/kg +/- I Sigma Saople COLD SPRING COLD SPRING LENTS COVE LENTS COVE VERPLANCK VERPLANCK Location.-

Date..I

._06/06/2007:

09/06/2007 06o06/2007 09/06/2007 06/07/20,07 09/07/1007..

Client ID IBS842307 1BS843607 JBS282307 1BS283607 IBS1 72307

]BS173607 Radionuclide Req. CL Be-7 423.0 234.0 399.4 339.4 417.3 309.8 1-131 108.6 48.9 112.3 54.1 86.0 55.5 Cs-134 75 31.3 38.3 32.9 54.1 48.5 39.4 Cs-137 90 254.8

+/-

44.1 34.9 373.7

+/-

58.4 209.2

+/-

41.1 252.7

+/-

49.6 217.1

+/-

41.0 Zr-95 68.5 56.1 121.4 77.0 100.1 70.3 Nb-95 64.8 25.4 83.2 47.0 44.8 51.5 Co-58 43.6 36.4 54.1 45.0 56.7 27.2 Mn-54 50.9 40.7 62.4 42.1 45.1 42.8 Zn-65 133.6 93.9 167.7 149.8 131.5 100.4 Fe-59 133.0 114.8 171.8 143.4 175.8 130.9 Co-60 47.3 26.1 56.1 77.3 46.6 40.6 BalLa-140 101.9 57.5 151.2 101.2 36.0 47.6 Ru-103 47.5 35.0 54.3 36.7 43.8 42.9 Ru-106 I

393.5 399.4 599.5 379.5 463.1 392.2 Ce-141 84.9 45.3 79.7 58.0 72.1 56.5 Ce-144 322.1 183.0 268.5 231.0 260.2 211.0 AcTh-228 1045.0

+/-

170.7 960.5

+/-

141.8 1214.0

+/-

237.0 658.1

+/-

152.0 1143.0

+/-

176.9 728.1

+/-

134.6 Ra-226 3153.0

+1-869.8 2009.0

+/-

581.3 2263.0

+1-908.4 1630.0

+/-

603.7 2008.0

+/-

792.1 1796.0

+/-

668.7 K-40 20630.0

+/-

1052.0 33510.0

+/-

1219.0 20430.0

+/-

1464.0 14160.0

+/-

1041.0 19610.0

+/-

1193.0 16900.0

+/-

1017.0 B-41

TABLE B-17 CONCENTRATIONS OF GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES -

2007 Results in Units of pCi/kg + 1 Sigma

.Sample IDISCHARGE CANAL DISCHARGE.CANAL Location Date 06/07/2007..

09/07/2007 Client ID IBS102307 IBS103607 Radionuclide Req. CL, Be-7 208.8 233.1 1-131 43.8 55.6 Cs-134 75 15.0 41.1 Cs-137 90 177.3

+/-

31.3 95.0

+/-

34.9 Zr-95 49.1 49.7 Nb-95 31.6 37.6 Co-58 25.6 26.1 Mn-54 34.0 38.4 Zn-65 94.1 94.1 Fe-59 95.3 140.5 Co-60 22.6 26.5 Ba/La-140 60.6 83.9 Ru-103 30.8 34.9 Ru-106 401.0 404.4 Ce-141 35.1 46.3 Ce-144 138.8 183.6 AcTh-228 176.0

+/-

104.1 148.6 Ra-226 1248.0

+/-

425.1 659.0 K-40 15430.0

+/-

912.1 14730.0

+/-

1065.0 B-42

TABLE B-18 CONCENTRATIONS OF RADIONUCLIDES IN RAINWATER SAMPLES - 2007 Results in Units of pCi/L +/- I Sigma

.Sample Location ROSETON ROSETON ROSETON ROSETON RAINWATER RA INWA" kTE R RA INWNAT ER -

RAINWATER>

Date*

03/26/2007 06/28/2007 10/01/2007 t2/31/2007 Client ID IRF23Q107 tRF23Q207 IRF23Q307 IRF23Q407 Radionuclide Reg. CL H-3 474.0 443.0 448.0 439.0 Be-7 39.4 49.5 62.2 34.4 1-131 28.1 28.3 35.9 24.4 Cs-134 7.5 1.9 3.1 3.4 3.2 Cs-137 9

2.5 2.3 4.5 2.8 Zr-95 6.0 7.3 11.9 7.1 Nb-95 5.4 6.7 10.0 5.3 Co-58 3.9 5.1 6.4 4.1 Mn-54 2.9 3.0 5.8 2.0 Zn-65 3.3 7.7 17.5 7.2 Fe-59 8.3 14.0 13.4 16.1 Co-60 7.5 2.6 2.3 6.0 3.1 Ba/La-140 21.9 21.4 37.4 12.4 Ru-103 5.5 6.4 8.3 5.2 Ru-106 29.0 26.7 39.3 30.1 Ce-141 12.2 10.8 13.7 1.0 Ce-144 25.1 23.3 26.9 21.0 AcTh-228 11.2 10.7 15.0 10.4 Ra-226 128.0

+1-55.4 59.9 86.0 58.6 K-40 126.6

+/-

25.9 98.7

+/-

27.7 55.4 277.6

+/-

34.2 B-43

TABLE B-18 CONCENTRATIONS OF RADIONUCLIDES IN RAINWATER SAMPLES - 2007 Results in Units of pCi/L +/- 1 Sigma

ýýSample PEEKSKILL PEEKSKILLý PEEKSKILL PEEKSKILL Location RAINWATER RAINWATER RAINWATER RAINWATER Date

.03/26/2007..

06/28/2007 i:10/01/2007 12/31/2007 Client ID IRF44Q107 IRF44Q207 IRF44Q307 IRF44Q407 Radionuclide Req. CL H-3 474.0 443.0 448.0 443.0 Be-7 43.3 48.0 44.9 40.2 1-131 39.0 35.1 34.9 39.5 Cs-1 34 7.5 3.3 2.0 4.3 2.4 Cs-137 9

3.5 3.9 4.5 3.2 Zr-95 11.3 8.7 9.3 4.1 Nb-95 8.6 7.7 8.7 7.9 Co-58 4.9 4.9 4.9 6.1 Mn-54 3.4 3.2 4.3 4.6 Zn-65 7.1 5.0 7.4 3.3 Fe-59 12.1 17.7 21.6 21.6 Co-60 7.5 4.0 3.1 5.8 4.3 Ba/La-140 15.4 35.6 36.4 32.4 Ru-103 6.0 6.8 8.6 8.8 Ru-106 25.5 27.5 37.0 42.6 Ce-141 9.4 11.3 14.1 11.2 Ce-144 21.5 21.1 26.6 22.8 AcTh-228 10.9 10.3 12.8 16.9 Ra-226 70.2 70.4 77.1 81.1

+/-

51.3 K-40 194.6

+/-

39.3 198.5

+/-

38.0 182.2

+/-

46.7 42.7 B-44

TABLE B-19 CONCENTRATIONS OF GAMMA EMITTERS IN SOIL SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma.

Sapl ROSETONý,...

MET TOWER:

TRAININGBLDG Location

... Dater 10/01/2007 10/02/2007 10/02/2007:'

Client ID IS0234007 IS0954007 IS0944007 Radionuclide Req. CL Be-7 876.0

+/-

195.2 1596.0

+/-

252.1 1458.0

+/-

206.2 1-131 31.7 31.0 33.1 Cs-134 75 33.2 33.4 32.9 Cs-137 90 27.3 27.4 136.5

+/-

22.5 Zr-95 49.5 54.2 52.8 Nb-95 36.0 33.4 38.9 Co-58 32.8 30.8 31.8 Mn-54 28.9 31.0 26.6 Zn-65 37.9 94.0 42.4 Fe-59 70.3 117.6 84.3 Co-60 21.8 42.1 37.0 Ba/La-140 36.4 40.9 25.4 Ru-103 28.2 24.5 24.4 Ru-106 279.4 316.8 261.0 Ce-141 39.2 38.4 43.2 Ce-144 169.6 185.4 187.0 AcTh-228 829.1

+/-

117.3 694.9

+1-126.3 1037.0

+/-

128.4, Ra-226 1965.0

+/-

526.2 2193.0

+/-

490.7 2293.0

+/-

505.4 K-40 13870.0

+/-

701.3 16750.0

+/-

938.9 23110.0

+/-

854.3 B-45

TABLE B-20 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCi/liter +/- 1 Sigma ALGONQUIN OUTFALL Date j1/23/2007

02/13/2007 f-03/20/2007<:"

04/16/2007 05115/2007 06/19/2007

~NUCLIDE 1-131

< 3.73

< 5.28

< 2.82

< 3.31

< 4.09

< 3.67 Cs-134

< 4.28

< 3.22

< 2.58

< 1.57

< 3.70

< 2.66 Cs-137

< 3.79

< 3.05

< 2.32

< 2.77

< 3.78

< 3.08 Zr-95

< 6.07

< 6.10

< 4.02

< 3.78

< 5.08

< 4.19 Nb-95

< 2.66

< 3.47

< 2.48

< 1.81

< 4.44

< 3.23 Co-58

< 3.63

< 3.15

< 2.52

< 2.61

< 2.85

< 3.16 Mn-54

< 2.76

< 3.33

< 2.39

< 2.50

< 3.54

< 3.22 Fe-59

< 7.14

< 6.88

< 6.20

< 5.73

< 7.99

< 4.62 Zn-65

< 4.68

< 4.26

< 4.81

< 2.75

< 3.87

< 4.02 Co-60

< 3.06

< 2.73

< 2.66

< 2.35

< 3.42

< 2.97 K-40 389.6 +/- 45.28 259.7 +/- 38.73 183.9 +/- 26.41 109.4 +/- 22.55 253.6 +/- 39.58 170.5 +/- 30.22 Ba/La-140

< 4.81

< 5.81

< 2.85

< 2.66

< 3.54

< 2.15 Date 07/17/2007 08/21/2007

[

09/25/2007-1-131

< 3.60

< 3.27

< 3.82 Cs-134

< 3.21

< 3.05

< 3.15 Cs-137

< 2.93

< 3.15

< 4.10 Zr-95

< 5.07

< 4.47

< 6.16 Nb-95

< 3.96

< 3.23

< 2.20 Co-58

< 3.14

< 2.67

< 3.73 Mn-54

< 3.14

< 2.60

< 2.74 Fe-59

< 6.63

< 7.10

< 8.63 Zn-65

< 3.84

< 8.31

< 2.92 Co-60

< 3.48

< 2.27

< 3.28 K-40 126.2 +/- 30.28 191.2 +/- 33.92 115 +/- 30.54 Ba/La-140

< 3.97

< 2.54

< 3.03 B-46

TABLE B-20 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCi/liter +/- 1 Sigma GYPSUM PLANT Date 01/23/2007 02/13/2007 03/20/2007 04/16/2007 05/15/2007 06/19/2007 NUCLIDE J

1-131

< 5.06

< 5.75

< 4.01

< 3.29

< 3.11

< 2.91 Cs-134

< 3.90

< 3.93

< 3.44

< 2.86

< 2.92

< 2.57 Cs-137

< 2.38

< 4.38

< 1.54

< 2.61

< 3.50

< 2.94 Zr-95

< 6.75

< 6.64

< 6.22

< 4.11

< 5.91

< 4.76 Nb-95

< 2.75

< 2.63

< 2.73

< 2.60

< 3.07

< 3.15 Co-58

< 4.81

< 3.78

< 4.21

< 2.48

< 2.64

< 2.81 Mn-54

< 3.78

< 3.29

< 3.97

< 2.77

< 3.46

< 2.99 Fe-59

< 9.55

< 11.75

< 7.81

< 6.81

< 6.51

< 9.63 Zn-65

< 5.26

< 4.39

< 4.86

< 3.76

< 6.35

< 9.20 Co-60

< 4.99

< 3.65

< 3.63

< 1.94

< 2.42

< 3.44 K-40 244.5 +/- 46.13 130.7 +/- 35.72 149.7 +/- 31.47 300 +/- 35.31 129.6 +/- 37.81 266.3 +/- 42.45 Ba/La-140

< 4.75

< 5.39

< 4.44

< 3.20

< 3.01

< 4.17 Date 07/17/2007.[

08/21M2007

] 1,09/25/2007

.J......I NUCLIDE 1-131

< 2.49

< 3.43

< 2.81 Cs-134

< 2.12

< 3.39

< 2.35 Cs-137

< 2.24

< 1.70

< 2.67 Zr-95

< 4.03

< 5.22

< 5.07 Nb-95

< 2.16

< 2.65

< 3.43 Co-58

< 2.06

< 1.88

< 2.04 Mn-54

< 2.42

< 3.14

< 2.69 Fe-59

< 6.56

< 7.04

< 8.12 Zn-65

< 6.06

< 4.02

< 6.05 Co-60

< 3.02

< 3.73

< 2.84 K-40 402.3 +/- 38.66 169.5 +/- 27.58 197.4 +/- 32.26 Ba/La-140

< 2.89

< 3.02

< 4.35 B-47

TABLE B-20 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCi/liter +/- I Sigma TRAP ROCK QUARRY Date.

01/23/2007,1

.02/1372007 j

03/20/2007:I 04/16/2007 05/15/2007:1 06/19/2007 NU.CLIDE

p.

1-131

< 3.12

< 4.34

< 2.56

< 3.64

< 3.95

< 3.87 Cs-134

< 1.78

< 3.27

< 1.91

< 2.24

< 3.30

< 4.33 Cs-137

< 2.67

< 2.90

< 2.28

< 2.35

< 3.97

< 3.63 Zr-95

< 4.02

< 5.16

< 3.90

< 4.58

< 5.03

< 4.59 Nb-95

< 1.98

< 3.00

< 2.04

< 3.37

< 4.16

< 3.13 Co-58

< 2.72

< 3.15

< 2.20

< 1.81

< 2.94

< 4.60 Mn-54

< 2.50

< 3,04

< 2.06

< 3.59

< 3.22

< 2.74 Fe-59

< 5.85

< 9.25

< 5.05

< 7.48

< 4.53

< 4.91 Zn-65

< 5.31

< 8.64

< 4.96

< 6.74

< 9.37

< 7.21 Co-60

< 1.51

< 4.38

< 1.95

< 2.74

< 2.38

< 4.24 K-40 122.5 +/- 26.20 267.9 +/- 38.23 277.1 +/- 29.28 103.8 +/- 30.27 134.9 +/- 37.84 127.7 +/- 36.36 Ba La-140

< 2.57

< 6,51

< 2.68

< 3.29

< 4.53

< 4.53 I -Date I

07/17/2007T 4 08/21/2007

_09/25/2007 I

J. I NUCLIDE 1-131

< 3.12

< 3125

< 3.40 Cs-134

< 3.89

< 2.07

< 3.03 Cs-137

< 2.65

< 3.07

< 3.65 Zr-95

< 5.28

< 5.03

< 4.89 Nb-95

< 3.15

< 2.79

< 3.01 Co-58

< 2.90

< 3.63

< 3.08 Mn-54

< 3.25

< 2.81

< 2.72 Fe-59

< 8.01

< 9.26

< 6.54 Zn-65

< 7.91

< 4.08

< 11.33 Co-60

< 3.24

< 3.03

< 3.97 K-40 234.6 +/- 39.31 218.6 +/- 43.43 241.2 +/- 45.51 Ba/La-140

< 5.37

< 6.14

< 4.80 B-48

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- 1 Sigma Monitoring Well:.

MWm'51 zýMW-40,:.

MW-51 MW-40 Sample Name:'.

MW-51-012.I.:

MW-40-011, :'.

MW-51-,012 MW40-011 Sample Date:

02/21/2007 :':

02/21/2007 06/26/2007 06/26/2007 Client ID IMW510707 IMW400707 IMW512607 IMW402607 Radionuclide Req. MDC Result Result Result Result H-3 467.00 467.00 444.00 444.00 Be-7 24.13 32.89 22.14 21.13 K-40 197.3

+/-

26.5 191.8

+/-

35.5 115.8

+/-

31.4 173.7

+/-

33.9 Mn-54 1.76 3.52 2.83 2.48 Co-58 1.68 2.29 2.66 2.39 Fe-59 7.45 8.61 10.66 9.38 Co-60 2.98 4.07 4.72 4.19 Zn-65 3.37 4.46 5.19 4.95 Sr-90 1

1.5 1.5 Nb-95 1.83 2.84 3.71 2.59 Zr-95 4.83 6.57 7.10 7.04 Ru-103 2.70 3.94 4.25 4.00 Ru-106 25.65 33.20 39.68 34.76 1-131 5.52 7.04 4.85 5.13 Cs-134 15 3.05 3.52 4.46 3.93 Cs-137 18 1.37 1.99 2.28 2.41 Ba/La-140 4.69 6.69 5.59 5.05 Ce-141 5.88 6.78 9.16 7.58 Ce-144 22.65 26.74 39.34 31.12 Ra-226 104.9

+1-63.3 99.42 122.10 118.50 AcTh-228 10.07 13.36 14.74 19.4

+/-

11.5 Note 1: Less than values "<" are the Critical Level values Note 2: A sample is positive if the result is greater than the critical level B-49

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- 1 Sigma Monitoring Well:

MW40:

MW-40 Sample Name:

MW-40-27-(001),

MW-40-27-(002),

Sample Date:r,:

_ 06/05/2007:

07/23/20071 Radionuclide Req. MDC Result Result H-3

< 163

< 169 Be-7

< 64.4

< 37.7 K-40

< 37.8

< 56.4 Mn-54

< 3.09

< 3.71 Co-58

< 5.51

< 4.05 Fe-59

< 17.4

< 9.58 Co-60

< 3.17

< 3.83 Zn-65

< 6.93

< 8.51 Sr-90 1

< 0.85

< 0.662 Nb-95

< 10.8

< 4.68 Zr-95

< 10

< 6.03 Ru-1 06

< 30.1

< 32.1 Cs-134 15

< 3.66

< 4.36 Cs-137 18

< 3.39

< 3.88 Ba-140

< 346

< 33.1 La-140

< 117

< 11.1 Ce-141

< 18.3

< 8.84 Ce-144

< 24.4

< 26.7 Ac-228

< 13.6

< 14.9 Note 1: Less than values "<" are the MDC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MDC.

B-50

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- 1 Sigma Monitoring Well:

_ MW-40 MW-40 :..

MW-40 Sample Name:

MW-40-46-(001):

MW-40-46-(002)

MW-40-46-*003)

Sample Date:,

06/05/2007, 07/23/2007T, 10/12/2007 Radionuclide Req. MDC Result Result Result H-3

< 166

< 171

< 174 Be-7

< 60.6

< 40.4

< 40.1 K-40

< 40.8

< 47

< 37.4 Mn-54

< 3.59

< 3.43

< 4.09 Co-58

< 4.95

< 5.22

< 4.31 Fe-59

< 15.7

< 8.52

< 10.1 Co-60

< 2.27

< 2.9

< 4.26 Zn-65

< 7.33

< 7.05

< 8.08 Sr-90 1

< 0.888

< 0.628

< 0.685 Nb-95

< 10.8

< 6.17

< 7.06 Zr-95

< 8.89

< 7.9

< 7.58 Ru-106

< 27.3

< 35.2

< 33.5 Cs-1 34 15

< 3.95

< 3.94

< 4.46 Cs-1 37 18

< 3.39

< 4.09

< 3.59 Ba-140

< 324

< 30.7

< 37.5 La-140

< 118

< 12

< 15.2 Ce-141

< 19.2

< 9.35

< 9.68 Ce-144

< 23.6

< 29.4

< 28.7 Ac-228

< 12.3

< 17

< 16.1 Note 1: Less than values "<" are the MDC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MDC.

B-51

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- 1 Sigma Monitoring Well:_.______ MW-40 q: MW-40ý'ý MW-40, Sample Name:.

MW-40-81-(001)

MW-40-81-(002).'ý MW-40-81,-(003)

Sample Date:!

06/05/2007 07/23/2007.',,

10/12/2007 Radionuclide Reg. MDC Result Result Result H-3

< 163

< 172

< 173 Be-7

< 56.4

< 42.3

< 44.2 K-40

< 38.1

< 69.8

< 48.7 Mn-54

< 3.35

< 3.69

< 3.89 Co-58

< 5.01

< 5.22

< 3.58 Fe-59

< 15.2

< 10.8

< 8.81 Co-60

< 3.62

< 4.95

< 4.64 Zn-65

< 7.49

< 8.1

< 10.5 Sr-90 1<

0.911

< 0.694

< 0.71 Nb-95

< 11

< 6.65

< 7.32 Zr-95

< 11.7

< 8.64

< 8.14 Ru-106

< 30.2

< 37.6

< 35.2 Cs-134 15

< 3.88

< 4.47

< 4.12 Cs-137 18

< 3.22

< 5.2

< 4.48 Ba-140

< 330

< 39

< 37.5 La-140

< 150

< 11.1

< 12.4 Ce-141

< 21.2

< 11.2

< 10.2 Ce-144

< 27.5

< 35.8

< 30.7 Ac-228

< 12.1

< 18.4

< 16.3 Note 1: Less than values "<" are the MDC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MDC.

B-52

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- 1 Sigma M6nitoringWell:

MW-40 MW-40 MW-40 SamplewName:

MW440*1100-(001)

MW-40-100-(002)

MW-40-1100-(003)

Sample Datd:

06/05/2007007 10/12/2007 Radionuclide Req. MDC Result Result Result H-3 176 +/- 53.5

< 175

< 173 Be-7

< 64.6

< 20.4

< 40.3 K-40

< 49.7

< 25

< 39.3 Mn-54,

< 3.55

< 2.16

< 3.78 Co-58

< 6.59

< 2.11

< 4.02 Fe-59

< 19.1

< 5.09

< 8.19 C0-60

< 3.59

< 2.2

< 3.61 Zn-65

< 7.93

< 4.47

< 8.16 Sr-90 1

< 0.694

< 0.696

< 0.769 Nb-95

< 11.9

< 2.92

< 6.55 Zr-95

< 12.4

< 4.15

< 7.79 Ru-106

< 35.3

< 18.2

< 34.4 Cs-134 15

< 4.19

< 2.34

< 4.06 Cs-1 37 18

< 3.04

< 2.1

< 3.87 Ba-140

< 377

< 17.9

< 35.6 La-140

< 115

< 6.81

< 14.1 Ce-141

< 16.8

< 4.92

< 10.2 Ce-144

< 24.1

< 15.1

< 30.1 Ac-228

< 15.1

< 8.97

< 12.7 Note 1: Less than values "<" are the MDC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MDC.

B-53

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- I Sigma Monitoring Well:

MW-40 MW-40 MW-40.

Sample Name:

MW-40-127-(001)

MW-40-127-(002) MW-40-127-(003).

Sample Date::

06/05/2007:

07/23/2007 10/12/2007 Radionuclide Reg. MDC Result Result Result H-3 187 +/- 54

< 168

< 164 Be-7

< 57.7

< 17.1

< 35.9 K-40

< 41.2

< 17.7

< 44.4 Mn-54

< 3.59

< 1.67

< 4.19 Co-58

< 6.06

< 1.74

< 4.49 Fe-59

< 17.7

< 4.06

< 9.26 Co-60

< 3.26

< 1.77

< 3.79 Zn-65

< 7.83

< 3.57

< 8.23 Sr-90

< 0.571

< 0.573

< 0.624 Nb-95

< 11.3

< 2.41

< 5.09 Zr-95

< 10.8

< 3.5

< 7.84

_Ru-106

< 31.8

< 16.3

< 38 Cs-1_34 15

< 3.98

< 2.01

< 5.04 Cs-1_37 18

< 3.41

< 1.76

< 4.06 Ba-140

< 359

< 15.5

< 40 La-140

< 118

< 5.48

< 13.9 Ce-141

< 20.8

< 4.03

< 10.1

(

_e-144

< 27.6

< 13.1

< 30.7 Ac-228

< 16.4 30.3 +/- 3.71 30 +/- 8.75 Note 1: Less than values "<" are the MDC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MDC.

B-54

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- I Sigma Monitoring Well:

MW-40 MW-40.

MW740::,

Sample Name:*.

MW-40-162-(001)

MW-40-162-(002)

MW-40-162-(003)ýý.

Sarmple Date*:

06/05/2007-07/23/2007 10/12/2007T.-I Radionuclide Req. MDC Result Result Result H-3

< 164

< 173

< 169 Be-7

< 76

< 16.6

< 36.1 K-40

< 37.1

< 22.5

< 33.1 Mn-54

< 5.44

< 1.65

< 3.57 Co-58

< 8.48

< 1.74

< 3.71 Fe-59

< 21.9

< 3.88

< 8.41 Co-60

< 4.53

< 1.69

< 3.47 Zn-65

< 10.2

< 3.4

< 9 Sr-90 1

< 0.504

< 0.507

< 0.819 Nb-95

< 17

< 2.43

< 5.24 Zr-95

< 14.4

< 3.43

< 7.49 Ru-106

-< 45.6

< 14.7

< 30.3 Cs-134 15

< 5.48

< 1.99

< 4.47 Cs-1 37 18

< 4.95

< 1.75

< 4.05 Ba-140

< 433

< 14.8

< 30.7 La-140

< 172

< 4.85

< 12.4 Ce-141

< 17.5

< 3.92

< 9.42 Ce-144

< 25.8

< 12.1

< 27 Ac-228

< 15.2 33.1 +/- 4.42 35.5 +/- 6.5 Note 1: Less than values "<" are the MDC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MDC.

B-55

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- I Sigma Monitoring Well:

MW-51:

MW-51 MW-51:i

-: !i,

MW-51:'

Sample Name:

1 MW-51-40-(00,1)

MW-51-40-(002)

MW-51-40-(003)

MW7-5140-(004)'..

Sample Date:

05/30/2007:

07/24/2007 10/02/2007 11/09/2007 Radionuclide Req. MDC Result Result Result Result H-3 198 +/- 55 223 +/- 53

< 196

< 170 Be-7

< 37.7

< 36.8

< 29.1

< 33 K-40

< 46.7

< 35.3

< 37.3

< 50.5 Mn-54

< 3.14

< 3.71

< 2.68

< 2.95 Co-58

< 3.51

< 3.54

< 2.43

< 3.39 Fe-59

< 8.68

< 8.97

< 7.36

< 7.2 Co-60

< 3.77

< 4.13

<-2.55

< 3.49 Zn-65

< 7.33

< 7.48

< 5.37

< 7.15 Sr-90 1

< 0.982

< 0.538

< 0.373

< 0.452 Nb-95

< 5.39

< 6.14

< 3.44

< 4.88 Zr-95

< 6.6

< 7.41

< 4.98

< 6.97 Ru-106

< 32.4

< 30.1

< 21.3 24.2 +/- 6.35 Cs-134 15

< 3.49

< 3.97

< 2.63

< 3.68 Cs-137 18

< 3.77

< 3.85 5.15 +/- 1.35

< 3.52 Ba-140

< 28.6

< 33.5

< 27.2

< 33.7 La-140

< 11.1

< 11

< 7.96

< 15.1 Ce-141

< 8.24

< 7.66

< 7.13

< 8.15 Ce-144

< 26.1

< 26.4

< 21.5

< 21.4 Ac-228

< 13.7

< 15.6

< 10.6

< 12.7 Note 1: Less than values "<" are the MDC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MDC.

B-56

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- 1 Sigma Mbnitoring Well:

t MW-5.1,'ý :.,

MW-51

.=.,

MW-51 II MW-51... :

Sample Name:

MW-51-79-(001)ý MW-5179-(002)

MW-51-79-(003)

VMW-5.1-79-(004)2 Sample Date:

05/30/2007T 07/24/2007 10/02/2007 11/09/2007,':

Radionuclide Reg. MDC Result Result Result Result H-3

< 172

< 167

< 194

< 171 Be-7

< 34.3

< 41.6

< 36.8

< 45.4 K-40

< 32.5

< 65.4

< 28.7

< 50 Mn-54

< 3.06

< 4.51

< 3.35

< 4.22 Co-58

< 4.45

< 4.15

< 3.61

< 4.66 Fe-59

< 7.97

< 10.7

< 7.74

< 9.73 Co-60

< 3.76

< 4.93

< 3.27

< 4.45 Zn-65

< 7.16

< 9.78

< 6.51

< 7.85 Sr-90 1

< 0.956

< 0.615

.< 0.327

< 0.352 Nb-95

< 4.58

< 4.87

< 5.49

< 6.5 Zr-95

< 7.26

< 6.89

< 6.48

< 7.83 Ru-106

< 31.4

< 33.4

< 29.5

< 34 Cs-1 34 15

< 4.15

< 4.49

< 3.92

< 4.21 Cs-137 18

< 3.9

< 4.21 5.37 +/- 1.69

< 3.56 Ba-140

< 33.3

< 34.1

< 36.2

< 52.3 La-140

< 10.9

< 13.6

< 10.7

< 17.8 Ce-141

< 7.46

< 10.9

< 8.04

< 11 Ce-144

< 22

< 32.1

< 23.5

< 28.1 Ac-228

< 13.6

< 18.5

< 10.9

< 16.3 Note 1: Less than values "<" are the MDC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MDC.

B-57

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- I Sigma Monitoring Well:

MW-51::

MW-51..

MW-51 MW-51i Sample Name::

MW-51-104-(001)! MW-51 -104-(002) MW-51-104-(003) MW-51-104-(004)

Sample Date:

05/30/2007 07/24/2007, 10/02/2007'.*

11/09/2007 Radionuclide Req. MDC Result Result Result Result H-3

< 171

< 164

< 194

< 170 Be-7

< 31.2

< 49.4

< 41.7

< 28 K-40

< 40.1

< 41.2

< 55.9

< 40.8 Mn-54

< 3.15

< 4.33

< 4.42

< 2.77 Co-58

< 3.21

< 5.71

< 4.55

< 2.97 Fe-59

< 7.38

< 10.8

< 9.58

< 7.36 Co-60

< 3.62

< 5.33

< 3.68

< 3.18 Zn-65

< 6.8

< 10.7

< 9.79

< 7.06 Sr-90 1<

0.99

< 0.541

< 0.508

< 0.386 Nb-95

< 4.48

< 5.92

< 7.41

< 4.72 Zr-95

< 5.79

< 9.53

< 8.29

< 5.02 Ru-106

< 29.7

< 44.8

< 34.6

< 25.9 Cs-134 15

< 3.24

< 6.04

< 4.9

< 3.3 Cs-137 18

< 3.35

< 3.92

< 4.25

< 2.92 Ba-140

< 29.3

< 37

< 39.1

< 34.7 La-140

< 11.2

< 14.2

< 15.3

< 12.1 Ce-141

< 7.93

< 10.9

< 10.1

< 7.33 Ce-144

< 24.1

< 36.1

< 30.7

< 18.6 Ac-228

< 15.3

< 22.8

< 13.7 17.6 +/- 4.72 Note 1: Less than values "<" are the MDC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MDC.

B-58

CONCENTRATIONS TABLE B-21 OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- I Sigma Monitoring Well MW-51 MW-Si MW-5l1 MW-51.

Sample Name:

MW-51-135-(001)" MW-517-135-(002)

MW-51-135-(003)

MW-51i-135-(004)

Sampl0 Datd:*

05/30/2007 07/24/2007 10/02/2007 11/09/2007 Radionuclide Req. MDC Result Result Result Result H-3

< 170

< 159

< 196

<172 Be-7

< 42

< 39.7

< 27.3

< 37.8 K-40

<52

<33

<25.7'

<51.8 Mn-54

< 3.94

< 4.4

< 2.69

< 3.79 Co-58

< 4.27

< 5.18

< 3.22

< 3.96 Fe-59

< 10.2

< 8.49

< 6.97

< 7.85 Co-60

< 4.48

< 3.84

< 2.92

< 3.66 Zn-65

< 6.69

< 11.1

< 6.38

< 6.88 Sr-90 1

< 0.84

< 0.576

< 0.549

< 0.318 Nb-95

< 6.3

< 5.32

< 3.22

< 5.59 Zr-95

< 7.32

< 8.52

< 5.35

< 7.11 Ru-106

< 28.6

< 40

< 23.7

< 34.5 Cs-134 15

< 4.37

< 5.09

< 3.05

< 4.13 Cs-137 18

< 4.03

< 4.36 21.6 +/- 1.92

< 3.7 Ba-140

< 36.3

< 34.7

< 27.6

< 40.2 La-140

< 14.2

< 14.9

< 9.69

< 16.1 Ce-141

< 9.95

< 10.1

< 5.45

< 9.56 Ce-144

< 29.1

< 30.1

< 15.9

< 29.4 Ac-228

< 19.4

< 14.1 18 +/- 4.89 22.6 +/- 6.95 Note 1: Less than values "<" are the MDC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MDC.

B-59

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCiIL +/- 1 Sigma Monitoring Well:

MW-51 MW-51i..

MW-51 MW-51.

Sample Name:

MW-51-163-m(001)

MW-51-163-(002)

MW-51-163-(003)

MW-51-163a-(004)

Sample Date:

___1_-.,

_ 05/30/2007,.

07/2412007 10/02/2007:.','ý 11/09/2007 Radionuclide Req. MDC Result Result Result Result H-3

< 169

< 166

< 196

< 171 Be-7

< 32.2

< 42

< 44.4

< 33.3 K-40

< 33.3

< 45.8

< 51.4

< 50.5 Mn-54

< 2.92

< 4.04

< 4.94

< 3.41 Co-58

< 3.83

< 4.01

< 5.49

< 3.91 Fe-59

< 9.68

< 8.47

< 11.4

< 8.56 Co-60

< 3.2

< 3.63

< 4.89

< 3.11 Zn-65

< 7.44

< 9.18

< 7.87

< 6.11 Sr-90 1<

1.36

< 0.521

< 0.364

< 0.312 Nb-95

< 5.71

< 5.38

< 6.74

< 5.5 Zr-95

< 6.32

< 7.51

< 9.42

< 7.59 Ru-106

< 32.9

< 40.5

< 41.6

< 31.8 Cs-134 15

< 3.89

< 3.82

< 5.88

< 4.27 Cs-137 18

< 3.45

< 3.78 11.6 +/- 2.4

< 3.51 Ba-140

< 33.2

< 33.6

< 47.2

< 39.2 La-140

< 12.5

< 10.2

< 13.9

< 14.3 Ce-141

< 7.26

< 9.32

< 7.63

< 8.57 Ce-144

< 24.8

< 29.3

< 22.8

< 23.5 Ac-228

< 15.1

< 20.1 24.4 +/- 7.8 23.7 +/- 6.1 Note 1: Less than values "<" are the MDC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MDC.

B-60

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- I Sigma Monitoring Well.:

MW-51 MW-51 MW-5I MW-51i Sample, Name:.......I:i..<::.,j..

MW-51-189-(001)

MW-51m89-(002)

MW751-189-(003) MW-51-189-(004)

SampleDate:,

05/30/2007.

07/24/2007

10/02/2007, 1,1/09/2007' Radionuclide Req. MDC Result Result Result Result H-3 187 +/- 55.5

< 163

< 196

< 171 Be-7

< 44.4

< 38.2

< 31.8

< 44.9 K-40

< 57

< 45.4

< 37

< 50.9 Mn-54

< 4.26

< 3.93

< 3.21

< 4.38 Co-58

< 4.25

< 4.08

< 3.6

< 4.56 Fe-59

< 10.9

< 8.91

< 8.28

< 10.4 Co-60 4.63

< 4.31

< 3.04

< 4.05 Zn-65

< 10.3

< 6.95

< 5.9

< 8.58 Sr-90 1

< 1.11

< 0.448

< 0.258

< 0.408 Nb-95

< 6.32

< 4.62 5 5.27

< 6.12 Zr-95

< 8.85

< 7.7

< 5.88

< 7.78 Ru-106

< 39.7

< 30.3

< 30.6

< 29.7 Cs-134 15

< 4.86

< 4.07

< 3.3

< 4.8 Cs-137 18

< 3.82

< 3.58 13.8 +/- 1.81

< 4.07 Ba-140

< 38.1

< 26.5

< 34.8

< 50.2 La-140

< 15.5

< 9.8

< 12.9

< 16.3 Ce-141

< 9.6

< 7.8

< 8.07

< 10.4 Ce-144

< 29.1

< 26

< 23.1

< 28.1 Ac-228

< 18.6

< 15.6

< 15.1

< 17.7 Note 1: Less than values "<" are the MDC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MDC.

B-61

TABLE B-22 MILCH ANIMAL CENSUS 2007 THERE ARE NO ANIMALS PRODUCING MILK FOR HUMAN CONSUMPTION WITHIN FIVE MILES OF INDIAN POINT.

B-62

LAND USE CENSUS DESCRIPTION 2007 A comprehensive survey of the of the 5 mile (8 kilometer) area surrounding the Indian Point Site was conducted during the 2007 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.

" Putnam County was surveyed during the summer and fall.

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

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

Results:

The 2007 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-63

TABLE B-23 LAND USE CENCUS 2007 INDIAN POINT ENERGY CENTER UNRESTRICTED AREA BOUNDARY AND NEAREST RESIDENCES 2007 Distance to Distance to site Distance to site nearest resident, Boundary from Boundary from from Unit 1 Unit 2 Plant Vent Unit 3 Plant Vent superheater Address of nearest resident, Dec Sector Compass Point (meters)

(meters)

(meters) 2004 Census N

RIVER RIVER 1788A1 41 River Road Tomkins Cove 2

NNE RIVER RIVER 3111.3 Chateau Rive Apts. John St. Peekskill

__________NE 550 636 1907.3 122 Lower South St. Peekskill 4

ENE 600 775 1478.2 1018 Lower South St. Peekskill 5

E 662 785 1370.9 1103 Lower South St. Peekskill 6

ESE 569 622 71512 461 Broadway Buchanan 7_____,_

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 1_____0_

SSW 755 480 1573.5 240 Eleventh St. Verplanck 11_SW 544 350 3015.9 29 Church St. Tomkins Cove 12 WSW RIVER RIVER 2169.6 9 West Shore Dr. Tomkins Cove W

RIVER RIVER 1918.7 712 Rt. 9W Tomkins Cove 14 WNW RIVER RIVER 1752.4 770 Rt. 9W Tomkins Cove 15 NW RIVER RIVER 1692.7 807 Rt. 9W Tomkins Cove 16 NNW RIVER RIVER 1609.3 4 River Rd. Tomkins Cove B-64

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 2007 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

1997 -2007 Average Quarterly Dose (mR/Quart~er)

Ye~~ar Inner Ring Outer Ring Cocntion 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 16.0 200.1 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 2007 14.4 14.6 18.8 Historical Average 1.

1997-2006 14.3 14.5 16.2 C-2

FIGURE C-I DIRECT RADIATION 40.0 35.0 30.0 S25.0 CY S20.0 E

~-15.0 10.0 5.0 0.0 MInner Ring

=]IOuter Ring Control Location 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 C-3

TABLE C-2 RADIONUCLIDES IN AIR 1997 to 2007 (nr i/m 3 1 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 0.01 0.02 0.02 0.01 0.02 0.02 0.01 0.01 0.02 0.01 0.01 0.01 0.01 0.01 0.01 0.02 0.02 0.01 0.01 0.02 0.01 0.01

< Lc 0.01 0.01

< Lc

< Lc 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 1997 to 2007 0.05 M All ODCM Indicator Locations

-- Control Location 0.04 0.03-0.0 0.01 0.00 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007

• Includes ODCM and non-ODCM indicator locations.

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

TABLE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 1997 to 2007 (PCi/L) 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007

" Lc

" Lc 191 190

< Lc 432

< Lc

" Lc

" Lc

" Lc

" Lc 430 220 318 267 323 562

< Lc 553 618 386

< Lc

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

,< Lc

< Lc

< Lc

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc Historical Average 271 409

< Lc

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

<L, indicates no positive values above sample critical level.

C-6

FIGURE C-3 HUDSON RIVER WATER - TRITIUM 1997 to 2007 2000 1800 1600 1400 1200 1000 800 600 400 200 0

d 1997 1998 Tritium ODCM required LLD = 3000 pCi/L 1999 2000 2001 2002 2003 2004 2005 2006 2007 C-7

TABLE C-4 RADIONUCLIDES IN DRINKING WATER 1997 to 2007 (pCi/L) 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

< Lc

< L,

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

" Lc

< L,:

< Lc

~Historical Average>L 997 06<

Lc

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

<L, indicates no positive values above sample critical level.

C-8

FIGURE C-4 DRINKING WATER - TRITIUM 1997 to 2007 CL 2000 1800-1600 -

1400 1200 1000 800 600-400 -

200 0

NO IDENTIFIED TRITIUM IN PREVIOUS TEN YEAR 1997 1998 Tritium ODCM required LLD = 2000 pCi/L 1999 2000 2001 2002 2003 2004 2005 2006 2007 C-9

TABLE C-5 RADIONUCLIDES IN SHORELINE SOIL 1997 to 2007 (pCi/Kg, dry) 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007

" Lc 46 58 45

" Lc

< Lc

" Lc

" Lc

< Lc

< Lc 203 143 200 179 230 221 124 104

< Lc 120 156 340

< Lc 238 231

.427 238 73 138 174

< Lc

< Lc

< Lc

" Lc

" Lc

" Lc Historical Average51 1 *197-92006 50

<Lc 168 Critical Level (L,) is less than the RETS required LLD.

<L, indicates no positive values above sample critical level.

C-10

FIGURE C-5 RADIONUCLIDES IN SHORELINE SOIL 1997 to 2007 750 650 550 450 350 250 150 50 1997 1998 1999

-50 "Cs-134 ODCM required LLD = 150 pCi/Kg, dry Cs-137 ODCM required LLD = 175 pCi/Kg, dry

=Indicator (Cs-1 34)

=ZControl (Cs-134)

=Indicator (Cs-137)

-Control (Cs-137) 2000 2001 2002 2003 2004 2005 C-11

TABLE C-6 RADIONUCLIDES IN BROAD LEAF VEGETATION 1997 to 2007 (pCi/Kg, wet) 1997

< L,

< Lc 1998

< Lc

< L, 1999

< L, 27 2000 28

< Lc 2001 7

< Lc 2002 14 16 2003 14

< Lc 2004 10

< Lc 2005

< L,

< L, 2006

< Lc

< Lc 2007

< Lc

< Lc

.Historicl Average 15 22 997-2006 Critical Level (Lc) 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 1997 to 2007 100 80 60 C.,

40.

40 20 1997 1998 1999 2000 2001 2002 2003

. 2004 2005 2006 2007 ODCM required LLD = 80 pCi/Kg, wet C-13

TABLE C-7 RADIONUCLIDES IN FISH AND INVERTEBRATES 4 007 o% 3nnll7 Critical Level (Lc) is less than the ODCM required LLD.

<Lc indicates no positive values above sample critical level.

C-14

FIGURE C-7 FISH AND INVERTEBRATES - Cs-137 1997 to 2007 200 180 -

160-140 -

120 100 L) 0.

80 60 40-20 0*

Ms Indicator (Cs-137) 0 Control (Cs-137)

NO IDENTIFIED Cs-137 IN PREVIOUS TEN YEAR HISTORY 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 Cs-137 ODCM required LLD = 150 pCi/Kg, wet C-1 5

APPENDIX D INTERLABORATORY COMPARISON PROGRAM

APPENDIX D D.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 by the JAF Environmental Laboratory using standard laboratory procedures.

Analytics issues a statistical summary report of the results.

The JAF Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratory's performance.

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.

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 representative 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.

The JAF Environmental Laboratory also analyzes laboratory blanks.

The analysis of laboratory blanks provides a means to detect and measure radioactive contamination of analytical samples. The analysis of analytical blanks also provides information on the adequacy of background subtraction.

D-1

Laboratory blank results are analyzed using control charts.

D.2 PROGRAM SCHEDULE TABLE D-1 QA PROGRAM SCHEDULE Water Gross Beta 1

Water Tritium 3

Water 1-131 4

Water Mixed Gamma 4

1 Air Gross Beta 3

Air 1-131 4

Air Mixed Gamma 2

1 Milk 1-131 3

Milk Mixed Gamma 3

Soil Mixed Gamma 1

Vegetation Mixed Gamma 2

TOTAL SAMPLE INVENTORY 30 2

D.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.

D.3.1 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 D.3.1 below, a corresponding Ratio of Agreement interval is given.

The value for the ratio is then calculated.

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

TABLE D-2 RATIO OF AGREEMENT ERROR RESOLUTION RATIO 0.F AG. REEMENT.

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

>200 0.85 to 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

D.4 PROGRAM RESULTS

SUMMARY

The Interlaboratory Comparison Program numerical results are provided on Table D-3.

D.4.1 ANALYTICS QA SAMPLES RESULTS Thirty QA blind spike samples were analyzed as part of Analytics 2007 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 126 individual analyses on the 30 QA samples. Of the 126 analyses performed, 126 were in agreement using the NRC acceptance criteria for a 100% agreement ratio.

There were no non-conformities in the 2007 program.

D.4.2 NIST QA SAMPLES RESULTS In 2007, JAF Environmental Laboratory participated in the NEI/NIST 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: Mixed Gamma Emitters The JAF Environmental Laboratory performed 8 individual analyses on the two QA samples. Of the 8 analyses performed, 8 were in agreement using the NRC acceptance criteria for a 100% agreement ratio.

There were no non-conformities in the 2007 program.

D-4

D.4.3 NUMERICAL RESULTS TABLES TABLE D-3 INTERLABORATORY COMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*

RATIO DATE ID NO.

MEDIUM ANALYSIS pCi +/-1 sigma pCi +/-2 sigma (1) 06/14/2007 E5352-05 Filter 78.3

+

2.2 GROSS 79.6 2.3 72.8

+/-

2.43 1.07 A

BETA 76.6

+

2.2 Mean =

78.2

+

1.3 06/14/2007 E5346-09 Filter 78.0

+

2.2 GROSS 82.0

+

2.3 75.0

+/-

3 1.07 A

BETA 80.0

+/-

2.3 Mean =

80.0

+

1.3 12/06/2007 E5767-05 Filter 76.6

+

2.2 GROSS 82.2 2.3 73.8

+/-

2.46 1.06 A

BETA 76.8

+/-

2.2 Mean =

78.5

+/-

1.3 (1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D-5

TABLE D-3 (Continued)

Tritium Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB* RATIO DATE ID NO.

MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-2 sigma (1) 3/22/2007 E5331-05 Water H-3 5510 177 5584 179 5010

+/-

167 1.10 A

5490 178 Mean =

5528

+

103 12/6/2007 E5542-09 Water H-3 9671 208 9901

+

210 9000

+/-

300 1.09 A

Mean =

9786

+/-

148 12/6/2007 E5543-09 Water H-3 9684

+/-

209 9843

+/-

210 9000

+/-

300 1.08 A

Mean =

9764

+/-

148 (1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D-6

TABLE D-3 (Continued)

Gross Beta Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

RATIO DATE ID NO.

MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-2 sigma (1) 11/09/2007 A21998-05 Water 9.11E+05

+/- 1.50E+04 GROSS 8.95E+05

+/- 1.49E+04 9.30E+05 +/-

0.97 A BETA 8.91E+05

+/- 1.48E+04 5.58E+04 Mean = 8.99E+05

+/- 8.60E+03, (1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D-7

TABLE D-3 (Continued) 1-131 Gamma Analysis of Air Charcoal SAMPLE.

JAF ELAB RESULTS REFERENCE LAB*

RATIO DATE ID NO.

MEDIUM ANALYSIS pCi +1 sigma pCi +/-2 sigma (1)

E5315-09 3/22/2007 Air 66.8

+

4.46 69.8

+/-

4.55 1-131 61.7

+/-

3.99 70.0

+

2.3 0.97 A 72.7

+

5.2 Mean =

67.8

+

2.29 E5355-05 6/14/2007 Air 72.7

+/-

4.22 1-131 79.7 5.09

.79.0

+

2.63 0.99 A

83.0

+/-

4.16 Mean =

78.5

+

2.60 E5466-05 9/13/2007 Air 74.4

+/-

3.46 1-131 65.7

+/-

3.92 69.6 2.32 0.98 A 64.5

+/-

3.13 Mean =

68.2

+/-

2.03 E5446-09 9/13/2007 Air 67.8

+/-

3.34 1-131 61.8 3.27 70.0

+/-

2 0.93 A 66.3

+/-

3.18 Mean =

65.3

+/-

1.88 (1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D-8

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*1 RATIO DATE ID NO.

MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-2 sigma (1) 4/18/2007 E5332-05 Water Ce-141 153

+

7.98 151

+

2.4 148

+

3.63 Mean=

151

+/-

3.0 140

+/-

4.65 11.08 A

115

+

12.1 Cr-51 139

+/-

15.4 104 3.47 1.22 A

Mean =

127

+

9.8 83.0

+/-

6.11 Cs-134 94.3 2.03 91.2

+/-

3.04 1.02 A 102

+/-

2.43 Mean =

93.1

+/-

2.3 201

+/-

7.53 Cs-137 195 2.41 196

+/-

6.53 1.01 A

197

+/-

3.08 Mean =

198

+/-

2.8 65.6

+/-

6.04 Co-58 67.0 1.71 63.5

+/-

2.12 1.01 A

59.8

+/-

2.27 Mean =

64.1

+/-

2.2 168

+/-

7.48 Mn-54 146 2.36 144

+/-

4.79 1.08 A 154

+

2.89 Mean =

156

+/-

2.8 63.1

+/-

6.4 Fe-59 58.1 2.26 58.0

+/-

1.93 1.03 A

58.6

+

2.5 Mean =

59.9

+/-

2.4 830

+

23 Zn-65 817 7.46 776

+/-

25.9 1.06 A 825

+/-

9.26 Mean =

824

+

8.6 123

+/-

4.79 128

+

1.6 Co-60 129 1.9 126

+/-

4.2 1.01 A

129

+/-

1.95 Mean =

127 1.!8 1-131**

100 99.4 90.9 104 Mean =

98.6

+/-

4.75

+/-

4.9

+/-

4.32

+/-

4.32

+/-

2.3 89.8

+/-

2.99 11.10 A

(1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D-9

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB* RATIO DATE ID NO.

MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-2 sigma (1) 6/14/2007 1 E5345-09 I Water Ce-141 158 181 169 Mean=

169

+/-

+/-

+/-

+/-

3.78 3.47 9.27 3.5 160

+/-

5 1.06 A

428

+/-

20.1 Cr-51 420

+/-

16.3 411

+/-

14 1.06 A

461

+/-

52.3 Mean =

436

+/-

19.5 208

+/-

3.6 Cs-134 204 2.73 194

+/-

6 1.05 A

202

+/-

10.3 Mean =

205

+/-

3.7 "132

+/-

2.99 Cs-137 141 2.34 135

+/-

5 1.01 A

140

+/-

8.12 Mean =

138

+/-

3.0 164

+/-

3.3 Co-58 166 2.49 159

+/-

5 1.05 A

170

+/-

8.93 Mean =

167

+/-

3.3 147

+/-

3.32 Mn-54 154 2.41 133

+/-

4 1.15 A 159

+/-

8.67 Mean =

153

+/-

3.2 141

+/-

4.05 Fe-59 145 2.81 134

+/-

4 1.03 A 130

+/-

10.4 Mean =

139

+/-

3.8 277

+/-

7.04 Zn-65 293 5.05 268

+/-

9 1.08 A 300

+/-

18.7 Mean =

290

+/-

6.9 192

+/-

2.79 Co-60 195 2

191

+/-

6 1.01 A

189

+/-

7.36 Mean =

192

+/-

2.7 1-131**

Mean =

108 102 103 104

+/-

+/-

+/-

+/-

8.97 2.13 2.37 3.2 102

+/-

3, 1.02 A (1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D-10

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Water SAMPLE

. JAF ELAB RESULTS TREFERENCE LAB*- RATIO DATE ID NO. [ MEDIUM ANALYSIS I pCi/liter'+/-l sigma pCi/liter +/-2 sigma (1) 9/13/2007 E5463-05 Water Ce-141 198 179 188 Mean=

188

+

+/-

+/-

+

9.06 9.53 10.8 5.7 182

+/-

6.05 1.03 A

253

+/-

37.5.

Cr-51 245 41.3 249

+/-

8.29 0.93 A 200

+/-

42.5 Mean =

233

+/-

23.4 134

+/-

8.9 Cs-134 134 9.08 127

+/-

4.22 1.10 A

150

+/-

8.93 Mean =

139

+/-

5.2 105

+/-

6.75 Cs-137 107 7.68 112

+/-

3.74 0.96 A 109

+/-

7.87 Mean =

107

+/-

4.3 103

+/-

6.62 Co-58 103 7.11 98.1

+/-

3.27 0.99 A 86.5

+/-

7.35 Mean =

97.5

+/-

4.1 173

+/-

8.22 Mn-54 161 8.73 144

+/-

4.8 1.14 A 158

+/-

8.93 Mean =

164

+/-

5.0 105

+/-

7,93 Fe-59 106 8.51 95.1

+/-

3.17 1.15 A

117

+/-

9.07 Mean =

109

+/-

4.9 204

+/-

13.8 Zn-65 212 15.9 174

+/-

5.8 1.20 A 208

+/-

16.3 Mean =

208

+/-

8.9 121

+/-

5.3 Co-60 128 6.28 127

+/-

4.24 1.03 A 144

+/-

6.72 Mean =

131

+/-

3.5 1-131**

83.5 80.3 86.1 Mean =

83.3

+/-

+/-

+/-

+/-

1.77 2.51 2.38 1.3 80.1

+/-

2.67 1.04 A

(1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D-11

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*I RATIO DATE ID NO.

MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-2 sigma (1) 12/6/2007 1 E5544-09 I Water Ce-141 156 155 153 Mean=

155

+/-

10.7

+/-

8.47

+/-

11.5

+/-

5.9 157

+/-

5 0.99 A

657

+/-

52 Cr-51 557 40.6 572

+/-

19 1.06 A

611

+

58.7 Mean =

608

+

29.4 168

+/-

8.91 155

+/-

7.61 Cs-134 1

9.7 153

+/-

5 1.05 A

161

+/-

9.97 Mean =

161

+/-

5.1 191

+

8.36 Cs-137 177 7.05 185

+/-

6 0.97 A

172

+/-

9.27 Mean =

180

+/-

4.8 214

+/-

8.97 Co-58 223 7.81 194

+/-

6 1.10 A

202

+

10.1 Mean =

213

+

5.2 240

+

9.27 Mn-54 228 7.81 212

+/-

7 1.10 A

231

+/-

10.9 Mean =

233

+/-

5.4 177

+/-

9.99 Fe-59 182 8.84 166

+/-

6 1.06 A

169

.11.6 Mean =

176

+/-

5.9 296

+/-

16.6 Zn-65 287 14.3 261

+/-

9 1.10 A

278

+/-

19.3 Mean =

287

+/-

9.7 229

+/-

6.95 Co-60 228 6.05 236

+/-

8 0.98 A

237

+/-

8.36 Mean =

231

+/-

4.1 1-131**

73.7 74.5 76.3 Mean =

74.8

+/-

+/-

+/-

+/-

3.53 1.97 3.37 1.8 72.0

+/-

2 1.04 A (1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D-1 2

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Milk SAMPLE JAF ELAB RESULTS iREFERENCE LAB*

RATIO DATE ID NO.

MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-2 sigma (1) 3/22/2007 E5316-09 MILK Ce-141 304 304 293 Mean =

300

+

+/-

+/-

4.2 5.4 5.5 2.9 297

+/-

9.9 1.01 A

227

+/-

16.6 Cr-51 204

+/-

22.1 245

+

8.2 0.90 A 227

+/-

22.9 Mean=

219

+/-

12.0 110

+/-

2.8 Cs-134 111

+

3.2 112

+/-

3.7 0.98 A 107

+/-

3.5 Mean 109

+

1.8 227

+

3.5 Cs-137 232 4.1 234

+/-

7.8 0.98 A 232

+/-

4.7 Mean =

230

+

2.4 95.6

+/-

3.1 Co-58 101 3.3 99.0

+/-

3.3 0.99 A 98.0

+/-

3.8 Mean =

98.2

+

2.0 189

+/-

3.6 Mn-54 189

3.

182

+/-

6.1 1.04 A 189

+

4.5 Mean =

189

+/-

2.3 114

+/-

3.8 Fe-59 127

+

4.1 106 3.5 1.12 A

114

+

4.6 Mean =

118

+/-

2.4 1040

+

11.6 Zn-65 1090 12.9 1000

+

33.3 1.06 A

1050

+/-

14.7 Mean =

1060

+/-

7.6 144

+/-

2.4 Co-60 146 2.6 152

+/-

5.1 0.95 A

144

+/-

3.0 Mean 145

+/-

1.5 1-131**

97 91.2 95.5 Mean =

94.6

+/-

+/-

+/-

+/-

3.9 4.1 5.3 2.6 85.0

+/-

2.8 1.11 A

(1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D-1 3

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Milk SAMPLE JAF ELAB RESULTS REFERENCE LAB*]

RATIO DATE ID NO.

MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-2 sigma (1) 6/14/2007 1 E5353-05 I MILK Ce-141 209 205 192 Mean =

202

+/-

4.33

+/-

5.94

+

4.16

+/-

2.82 200.

+/-

6.66 1.01 A

519

+/-

22.1 Cr-51 575 26.9 512

+/-

17.1 1.07 A 543

+/-

19.2 Mean =

546

+/-

13.3 249

+/-

4.19 Cs-1 34 257 4.55 242

+/-

8.06 1.06 A 260

+/-

3.47 Mean =

255

+/-

2.36 162

+/-

3.45 Cs-137 169 3.86 169

+/-

5.63 0.99 A

170

+/-

3.06 Mean =

167

+/-

2.00 198

+/-

3.81 Co-58 211 4.14 198

+/-

6.61 1.04 A

208

+/-

3.30 Mean =

206

+/-

2.17 177

+/-

3.55 Mn-54 185 3.94 166

+/-

5.53 1.10 A 185

+/-

3.19 Mean =

182

+/-

2.06 184

+/-

4.42 Fe-59 182 4.75 167

+/-

5.56 1.09 A

181

+/-

3.78 Mean =

182

+/-

2.50 352

+/-

7.63 Zn-65 379 10.6 334

+/-

11.1 1.08 A

354

+/-

6.73 Mean =

362

+/-

4.90 237

+/-

3.02 Co-60 242 3.27 238

+/-

7.93 1.01 A

240

+/-

2.62 Mean =

240

+/-

1.72 1-131**

65.4 65.9 65.9 Mean =

65.7

+/-

2.07

+/-

2.29

+/-

1.87

+/-

1.20 70.1

+/-

2.34 0.94 A (1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D-14

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Milk SAMPLE JAF ELAB RESULTS REFERENCE LAB*I RATIO DATE ID NO.

MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-2 sigma (1) 9/13/2007 E5465-05 MILK Ce-141 188 239 198 Mean =

208

+

10.8

+

10.5

+

9.94

+

6.02 211

+/-

7.04 10.99 A

200

+

42.5 Cr-51 250 41.4 289

+

9.65 0.89 A

320 42.1 Mean =

257

+

24.3 150 8.93 Cs-134 156 8.74 147

+/-

4.91 1.03 A

149

+

8.69 Mean =

152

+

5.07 109

+

7.87 Cs-137 144 8.32 131

+/-

4.35 0.96 A 126 7.38 Mean =

126

+

4.54 86.5

+

7.35 Co-58 127

+/-

8.17 114

+/-

3.80 0.95 A 111 7.19 Mean =

108

+/-

4.38 158 8.93 Mn-54 176 9.18 168

+/-

5.59 1.03 A

184

+/-

8.60 Mean =

173 5.14 117

+/-

9.07 Fe-59 113 9.94 111 3.69 1.04 A

117

+/-

8.44 Mean =

116

+/-

5.29 208 16.3 Zn-65 226 17.5 202

+/-

6.74 1.10 A

232 15.7 Mean =

222

+/-

9.54 144

+/-

6.72 Co-60 151 6.83 148

+/-

4.94 0.98 A 139

+

5.89 Mean =

145

+/-

3.75 1-131**

77.6 76.4 72.7 Mean =

75.6

_+

_+

_+

+

2.52 2.34 3.10 1.54 85.2

+/-

2.84 10.89 A

(1) Ratio = Reported/Analytics.

(1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D-1 5

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*T RATIO DATE J ID NO.

MEDIUM ANALYSIS pCi +/-1 sigma pCi +/-2 sigma (1) 3/22/2007 1 E5333-05,1 FILTER Ce-141 234 230 246 Mean =

237

+

3.01

+/-

2.54

+/-

8.32

+

3.07 233

+/-

7.78 1.02 A

206

+/-

15.8 Cr-51 197 15.6 192

+/-

6.41 1.10 A 230

+/-

40.0 Mean =

211

+/-

15.3 95.8

+/-

1.99 Cs-134 76.8 3.02 87.9

+/-

2.93 1.02 A 95.6

+/-

5.43 Mean =

89.4

+/-

2.17 188

+

2.43 Cs-137 179 2.04 185

+/-

6.15 1.00 A

186

+

6.48 Mean =

184

+/-

2.41 76.9

+/-

2.18 Co-58 77 2.09 77.7

+/-

2.59 0.99 A 76.4

+/-

6.07 Mean =

76.8

+/-

2.26 160

+/-

2.62 Mn-54 150

+/-

2.17 144

+/-

4.78 1.08 A 157

+/-

6.71 Mean =

156

+

2.51 93.1

+

3.46 Fe-59 84.2 2.94 83.1

+/-

2.77 1.08 A 93.1

+/-

8.98 Mean =

90.1

+/-

3.35 870

+/-

8.82 Zn-65 852 7.55 787

+/-

26.2 1.09 A 856

+/-

23.5 Mean =

859

+/-

8.74 Co-60 114 118 111 Mean=

114

+/-

1.69

+/-

1.46

+/-

4.42

+/-

1.65 120

+

3.99 0.95 A

(1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D-1 6

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*1 RATIO DATE ID NO.

MEDIUM ANALYSIS pCi +/-1 sigma pCi +/-2 sigma (1) 9/13/2007 1 E5464-05 I FILTER Ce-141 195 194 209 Mean=

199

+/-

+/-

5.84 5.05 6.01 3.3 207

+/-

6.90 10.96 A

238

+/-

27.9 Cr-51 256 23 284

+/-

9.46 0.94 A 307

+/-

33.5 Mean =

267

+/-

16.4 163

+/-

8.66 Cs-134 151 6.52 145

+/-

4.82 1.13 A

177

+

10.2 Mean =

164

+/-

5.0 117

+/-

6.54 Cs-137 123 5.42 128

+/-

4.27 0.94 A 120

+/-

7.64 Mean =

120

+/-

3.8 109

+

7 Co-58 112 544 112

+/-

3.73 0.99 A 113

+/-

7.41 Mean =

111

+/-

3.9 179

+/-

8.69 Mn-54 166 6.59 164

+/-

5.48 1.04 A 168

+/-

9.02 Mean =

171

+/-

4.7 117

+/-

8.96 Fe-59 130 7.02 108

+/-

3.61 1.10 A

110

+/-

9.8 Mean =

119

+/-

5.0 211

+/-

15.1 Zn-65 239 12.6 198

+/-

6.61 1.16 A

237

+/-

18.5 Mean =

229

+/-

9.0 Co-60 141 140 135 Mean=

139

+/-

+/-

+

+/-

6.38 4.88 7

3.6 145

+/-

4.84 10.96 A

(1) Ratio = Reported/Analytics.

(1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D-1 7

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Soil SAMPLE JAF ELAB RESULTS JREFERENCE LAB* RATIO DATE ID NO.

MEDIUM ANALYSIS pCi/g +/-1 sigma pCi/g +/-2 sigma (1) 6/14/2005 E5354-05 SOIL Ce-141 0.164 0.144 0.190 Mean 0.166

+

+/-

+

+/-

0.007 0.014 0.012 0.007 0.178

+/-

0.006 0.93 A

0.413

+

0.041 0.401

+

0.071 Cr-51 0.401

+

0.07 0.456

+/-

0.015 0.88 A 0.387

+/-

0.057 Mean =

0.400

+/-

0.033 0.218

+/-

0.007 Cs-134 0.218 0.013 0.215

+/-

0.007 1.02 A

0.220

+/-

0.009 Mean =

0.219

+/-

0.006 0.242

+

0.007 Cs-137 0.249 0.013 0.248

+/-

0.008 1.00 A

0.251

+/-

0.008 Mean =

0.247

+/-

0.006 0.166

+/-

0.006 Co-58 0.154 0.012 0.176

+

0.006 0.93 A

0.169

+

0.007 Mean =

0.163

+

0.005 0.137

+/-

0.006 0.161

+/-

0.011 Mn-54 0.16

+/-

0.011 0.148

+/-

0.005 1.01 A

0.1S2

+/-

0.007 Mean =

0.150 0.005 0.141

+

0.009 Fe-59 0.147 0.016 0.148

+/-

0.005 0.97 A 0.144

+/-

0.009 Mean =

0.144

+/-

0.007 0.315

+/-

0.013 Zn-65 0.30S 0.023 0.297

+/-

0.010 1.04 A

0.306

+/-

0.014 Mean =

0.309

+/-

0.010 Co-60 0.201 0.192 0.196 Mean 0.196

+

+/-

+/-

0.005 0.010 0.005 0.004 0.212

+/-

0.007 0.93 A (1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D-1 8

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Vegetation SAMPLE JAF ELAB RESULTS REFERENCE LAB*T RATIO DATE ID NO.

MEDIUM ANALYSIS pCi/g +/-1 sigma pCi/g +/-2 sigma (1) 6/14/2007 1 E5356-05 VEG Ce-141 0.158 0.145 0.154 Mean=

0.152

+

+

+/--

0.010 0.005 0.007 0.004 0.161

+/-

0.005 10.95 A

0.404

+/-

0.050 Cr-Si 0.349

+/-

0.028 0.413 0.014 0.92 A

0.388

+/-

0.043 Mean =

0.380

+/-

0.024 0.210

+

0.010 Cs-134 0.215 0.006 0.195

+

0.007 1.11 A

0.222

+/-

0.009 Mean =

0.216

+

0.005 0.132

+/-

0.008 Cs-137 0.134 0.005 0.136

+/-

0.005 0.96 A 0.126

+/-

0.008 Mean =

0.131

+/-

0.004 0.145

+/-

0.010 Co-58 0.151 0.005 0.160

+/-

0.005 0.98 A 0.173

+

0.008 Mean =

0.156

+/-

0.005 0.144

+/-

0.009 Mn-54 0.137 0.005 0.133

+/-

0.004 1.05 A 0.138

+/-

0.008 Mean=

0.140

+/-

0.004 0.122

+/-

0.013 Fe-59 0.141 0.007 0.135

+/-

0.005 1.00 A

0.143

+/-

0.011 Mean =

0.135

+/-

0.006 0.241

+/-

0.021 Zn-65 0.275 0.011 0.270

+

0.009 0.98 A

0.279

+/-

0.018 Mean =

0.265

+/-

0.010 Co-60 0.188 0.182 0.193 Mean=

0.188

+

+/-

+/-

0.008 0.004 0.007 0.004 0.192

+/-

0.006 10.98 A

(1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D-19,

]

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Vegetation SAMPLE JAF ELAB RESULTS REFERENCE LAB*T RATIO DATE ID NO.

MEDIUM ] ANALYSIS pCi/g +/-1 sigma pCi/g +/-2 sigma (1) 9/13/2007 E5447-09 VEG Ce-141 0.342 0.298 0.312 Mean=

0.317

+

+

+

-+/-

0.016 0.015 0.014 0.009 0.333 -+/-

0.011 0.95 A

0.409

+/-

0.070 Cr-51 0.392

+/-

0.068 0.457

+

0.015 0.90 A

0.433

+/-

0.063 Mean =

0.411

+/-

0.039 0.269

+/-

0.026 Cs-134 0.221 0.018 0.233

+/-

0.008 1.05 A

0.243

+/-

0.016 Mean =

0.244

+/-

0.012 0.224

+/-

0.015 Cs-137 0.206 0.014 0.206 0.007 1.05 A

0.220

+/-

0.014 Mean =

0.217

+/-

0.008 0.161

+/-

0.013 Co-58 0.166 0.014 0.180

+/-

0.006 0.94 A 0.179

+/-

0.013 Mean =

0.169

+/-

0.008 0.282

+/-

0.016 Mn-54 0.275 0.016 0.265

+/-

0.009 1.00 A

0.240

+

0.014 Mean =

0.266

+/-

0.009 0.178

+/-

0.017 0.169

+

0.019 Fe-59 0.165 0.019 0.175

+/-

0.006 1.01 A

0.185

+

0.017 Mean=

0.177

+/-

0.010 0.346

+/-

0.032 Zn-65 0.392 0.031 0.319 +/-

0.001 1.17 A 0.379

+

0.029 Mean =

0.372

+/-

0.018 Co-60 0.244 0.235 0.235 Mean =

0.238

+/-

+

+/-

0.012 0.012 0.012 0.005 0.234

+/-

0.008 1.02 A

(1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D-20

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of NIST Water SAMPLE JAF ELAB RESULTS REFERENCE LAB* RATIO DATE ID NO.

MEDIUM ANALYSIS Bq/g +/-1 sigma Bq/g +/-2 sigma (1) 4/23/2007 1911-4 Water 300.8

+/-

2.09 Co-57 299.7

+/-

2.09 310.7

+/-

2.05 0.97 A

303.4

+/-

2.10 Mean =

301.3

+

1.21 306.4

+/-

2.38 Ba-133 312.7 2.35 326.7

+/-

3.1 0.95 A 312.3

+

2.27 Mean =

310.4

+/-

1.35 283.8

+/-

2.32 Cs-137 290.1 2.31 308.4

+/-

2.31 0.94 A 291.9

+/-

2.22 Mean =

288.6

+

1.32 190.6

+/-

1.69 Co-60 196.5 1.69 202.4

+/-

1.01 0.96 A 193.9

+/-

1.57 Mean =

193.6

+/-

0.95 (1) Ratio = Reported/Analytics.

• Sample provided by NIST A=Acceptable U=Unacceptable D-21

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of NIST Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*

RATIO DATE ID NO.

MEDIUM ANALYSIS Bq/filter +1 sigma Bq/filter +/-2 sigma (1) 4/23/2007 1912-11 Filter 1077

+

4.0 Co-57 1073 4.6 1089

+

10.9 1.01 A

1143

+

4.8 Mean=

1098

+/-

2.6 1006

+/-

5.2 Ba-133 1003 6.0 1048

+/-

10.5 0.96 A

1006

+

5.4 Mean =

1005

+/-

3.2 743.7

+/-

4.9 Cs-137 725.2 5.7 766.1

+/-

7.7 0.98 A

777.0

+/-

5.0 Mean =

748.6

+/-

3.0 969.4

+/-

5.2 Co-60 962.0 6.1 987.0

+/-

9.9 0.98 A

976.8

+/-

4.9 Mean =

969.4

+/-

3.1 (1) Ratio = Reported/Analytics.

• Sample provided by NIST A=Acceptable U=Unacceptable D-22

D.5 REFERENCES D.5.1 Radioactivity and Radiochemistry, The Counting Room: Special Edition, 1994 Caretaker Publications, Atlanta, Georgia.

D.5.2 Data Reduction and Error Analysis for the Physical Sciences, Bevington P.R.,

McGraw Hill, New York (1969).

D-23