NL-06-053, Annual Radiological Environmental Operating Report for 2005

Annual Radiological Environmental Operating Report for 2005

ML061290085
Person / Time
Site:	Indian Point
Issue date:	04/30/2006
From:	Conroy P Entergy Nuclear Indian Point 2, Entergy Nuclear Operations
To:	Document Control Desk, NRC/FSME
References
NL-06-053
Download: ML061290085 (133)

Text

Indian Point Energy Center 450 Broadway, GSB

- Entergy P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 734-6700 Patric W. Conroy Manager, Licensing IPEC April 30, 2006 Re: Indian Point Units 1, 2 & 3 Docket Nos. 50-3, 50-247, 50-286 NL-06-053 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Indian Point Nuclear Power Plants Units 1, 2 and 3 Annual Radiological Environmental Operating Report for 2005

Dear Sir:

Enclosed please find one copy of the Indian Point Site Annual Radiological Environmental Operating Report for the period January 1, 2005 to December 31, 2005.

No commitments are being made by this report.

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

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

Sincerel Patric W. Conroy Manager, Licensing Entergy, Indian Point Energy Center Enclosure cc: See next page j---- s

NL-06-053 Docket Nos. 50-3, 50-247, 50-286 Page 2 of 2 cc:

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

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

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

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

January 1 - December 31, 2005

TABLE OF CONTENTS Paoe 1.0 EXECUTIVE

SUMMARY

1-1

2.0 INTRODUCTION

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

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 Additional Media Sampling 4-6 4.9 Land Use Census 4-7 4.10 Augmented Groundwater Sampling Results. 4-8 4.11 Conclusion 4-8

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 Sampling Locations (Non-RECS Sample Locations) A-7 C-1 Direct Radiation, 1995 to 2005 C-3 C-2 Radionuclides in Air - Gross Beta, 1995 to 2005 C-5 C-3 Hudson River Water-Tritium, 1995 to 2005 C-7 CA4 Drinking Water - Tritium, 1995 to 2005 C-9 C-5 Radionuclides in Shoreline Soil, 1995 to 2005 C-11 C-6 Broad Leaf Vegetation - Cs-1 37, 1995 to 2005 C-1 3 C-7 Fish and Invertebrates - Cs-137, 1995 to 2005 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, 2005 B-2 B-1 a 2005 Air Sampling Deviations B-3 B-1 b 2005 TLD Deviations B-4 B-1c 2005 Other Media Deviations B-4 B-2 Annual Summary, 2005 B-5 B-3 2005 Direct Radiation, Quarterly Data B-7 B-4 Direct Radiation, 1999 Through 2005 Data B-8 B-5 2005 Direct Radiation, Inner and Outer Rings B-9 B-6 Gross Beta Activity in Airborne Particulate Samples, 2005 B-1 0 B-7 Concentrations of Gamma Emitters in Quarterly Composites of Air Particulate Samples, 2005 B-16 B-8 1-131 Activity in Charcoal Cartridge Samples, 2005 B-22 B-9 Concentrations of Gamma Emitters in Hudson River Water Samples, 2005 B-23 B-1 0 Concentrations of Tritium in Hudson River Water Samples, 2005 B-25 B-11 Gross Beta Activity and Concentrations of Gamma Emitters in Drinking Water Samples, 2005 B-26 B-12 Concentrations of Tritium in Drinking Water Samples, 2005 B-38 B-13 Concentrations of Gamma Emitters in Shoreline Soil Samples, 2005 B-39 B-14 Concentrations of Gamma Emitters in Broad Leaf Vegetation, 2005 B-40 B-15 Concentrations of Gamma Emitters in Fish and Invertebrate Samples, 2005 B-46 B-16 Annual Summary, Non-RECS Sample Results, 2005 B-48 B-17 Milch Animal Census, 2005 B-49 B-18 Land Use Census, 2005 B-50 iv

LIST OF TABLES (Continued)

TABLE TITLE Paae C-1 Direct Radiation Annual Summary, 1995 to 2005 C-2 C-2 Radionuclides in Air, 1995 to 2005 C-4 C-3 Radionuclides in Hudson River Water, 1995 to 2005 C-6 C-4 Radionuclides in Drinking Water, 1995 to 2005 C-8 C-5 Radionuclides in Shoreline Soil, 1995 to 2005 C-10 C-6 Radionuclides in Broad Leaf Vegetation, 1995 to 2005 C-12 C-7 Radionuclides in Fish and Invertebrates, 1995 to 2005 C-14 D-1 2005 QA Program Schedule D-2 D-2 Ratio of Agreement D-3 D-3 2005 Gross Beta Results (inter lab comparison) D-5 D-4 2005 Tritium (inter lab comparison) D-6 D-5 Interlaboratory Comparison Program D-9 v

SECTION 1 EXECUTIVE

SUMMARY

1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report (AREOR) contains descriptions and results of the 2005 Radiological Environmental Monitoring Program (REMP) for the Indian Point site. The Indian Point site consists of Units 1, 2 and 3.

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

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

The airborne pathway includes measurements of air, precipitation, drinking water, and broad leaf vegetation samples. The airborne pathway measurements indicated that there was no increased radioactivity attributable to 2005 Indian Point Station operation.

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

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

The OCM designates samples required by Radiological Effluents Controls (RECS) as well as additional samples not required by RECS. This 2005 AREOR also contains summaries and discussions of the results of the 2005 program, trend analyses, potential impact on the environment, land use census, and interlaboratory comparis ns.

During 2 05, a total of 1347 analyses were performed. Table B-1 presents a summary of the collected sample results. The actual sampling frequency in 2005 was high r than required, due to the inclusion of additional (Non-RECS) sample locations nd media.

During the latter part of 2005(Sept-Dec 2005), IPEC identified an onsite Tritium ground w ter contamination issue in the Unit 2 transformer yard. The exact source is currently nknown and under investigation but may be associated with a small hairline c ack discovered on the Unit 2 spent fuel pool shield wall (southern pool wall). As such IPEC has implemented an aggressive onsite and offsite ground water 1-1

monitoring program to fully characterized the onsite contamination, to quantify and determine its onsite and offsite radiological impact to the workers, public and surrounding environment, and to aid in identification and ultimate repair of any leaking systems, structures or components affected. To this end, interim changes have been made to the REMP program in the areas of offsite drinking water sampling, special ground and surface water sampling. Section 3 further discusses these augmented programs and there descriptions In summary, the levels of radionuclides in the environment surrounding Indian Point are significantly less than NRC limits as a result of Indian Point Station operations in 2005. The levels present in the REMP Program for 2005 were within the historical ranges, i.e., previous levels resulting from natural and anthropogenic sources for the detected radionuclides. Further, Indian Point operations in 2005 did not result in approaching any environmental regulatory limits posed by the NRC, or result in any 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 Northeast.

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

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

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

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

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

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

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 2005, however, residual radioactivity from atmospheric bomb tests and naturally occurring radioactivity were the predominant sources of radioactivity in the samples collected. Nonetheless, analysis of the data verified that plant effluents were far below regulatory limits at environmental levels.

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SECTION 3 PROGRAM DESCRIPTION

3.0 PROGRAM DESCRIPTION To achieve the objectives of the REMP and ensure compliance with the ODCM, sampling and analysis of environmental media are performed as outlined in Table A-l and described in section 3.3. The Indian Point REMP consists of samples that are required by ODCM and additional samples, Non-RECS, that are not required by ODCM.

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

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

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

3.3 Samgle 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 I mile (1.6 km). The outer ring is located at approximately 5 miles (8 km) from the site (6.7- 8.0 km), see Figures A-1 and A-2.

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

Intotal, 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.

3-1

3.3.2 Airborne Particulates and Radioiodine Air samples were taken at nine locations varying indistance from 0.28 to 20.7 miles (0.4 to 33 km) from the plant. These locations represent one control and eight indicator locations. 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. The five required ODCM air sample locations are designated by the codes A-1 through A-5, see Figures A-1 and A-2.

3.3.3 Hudson River Water Hudson River water sampling is performed continuously at the intake structure (ODCM designation Wal) and at a point exterior to the discharge canal where Hudson River water and water from the discharge canal mix (ODCM designation Wa2), see Figure A-1. An automatic sampling apparatus is used to take representative samples. On a weekly basis, accumulated samples are taken from both sample points. These weekly river water samples are composited for monthly gamma spectroscopy analysis, and quarterly for tritium analysis.

3.3.4 Drinkina Water Samples of drinking water are collected monthly from the Camp Field Reservoir (3.4 miles NE, ODCM designation Wb1) and New Croton Reservoir (6.3 Mi SE, Non-RECS designation 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. In addition, due to the onsite tritium groundwater contamination issue, augmented sampling of this pathway was performed (see 3.3.12.) Sample point AMICUS is a quality control split of a drinking water sample point.

3.3.5 Hudson River Shoreline Soil Shoreline soil samples are collected at three indicator and two control locations along the Hudson River. The designation for the ODCM indicator location is Wc1 and the ODCM control location is designated Wc2, see Figures A-1 and A-2. The remaining two indicator and one control locations are Non-RECS. 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.

3-2

3.3.6 Broad Leaf Vegetation Broad leaf vegetation samples are collected from three locations during the growing season. The designation for the two ODCM indicator locations are Icl and Ic2, and the ODCM control location is designated Wc3, see Figures A-1 and A-2. The samples are collected monthly, when available, and analyzed by gamma spectroscopy. These samples consist of at least 1 kg of leafy vegetation and are used in the assessment of the food product and milk ingestion pathways.

3.3.7 Fish and Invertebrates Fish and invertebrate samples are obtained from the Hudson River at locations upstream and downstream of the plant discharge. The ODCM designation for the upstream sample point is Ib2 and the downstream designation is Ibl, see Figures A-I 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.

3.3.8 Hudson River Aquatic Vegetation (Non-RECS)

During the spring and summer, aquatic vegetation samples are collected from the Hudson River at two indicator locations and one control location, see Figure A-3. Samples of aquatic vegetation are obtained depending on sample availability. These samples are analyzed by gamma spectroscopy.

3.3.9 Hudson River Bottom Sediment (Non-RECS)

Bottom sediment and benthos are sampled at four locations, three indicator and one control, 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 (Non-RECS)

Precipitation samples are continuously collected at one indicator and one control location, 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 (Non-RECS)

Soil samples are collected from one control and two indicator locations, see Figure A-3. They are approximately 2 kg in size and consist of about twenty 3-3

2-inch deep cores. The soil samples are analyzed by gamma spectroscopy.

3.3.12 Auamented Groundwater Sampling Due to the onsite discovery of tritium and strontium-90 ground water contamination, augmented sampling of (in addition to the REMP) existing drinking water sources and special water sources (non-drinking water sources) was implemented for the latter part of 2005. For drinking water sources, both the Camp Field and Croton Reservoirs were sampled monthly for tritium. Further, near site special waters were sampled monthly for tritium at the Algonquin and Gypsum Ouffalls, Rock Quarry and a private abandoned well. In addition, regulatory agencies together with IPEC conducted "split samples" of all of these offsite locations as an independent quality check.

Section 4.10 discusses the results for 2005. Additionally more changes will be implemented in 2006 in accordance with NL-06-033-NRC Commitments.

Those commitments include routine sampling of new site perimeter well and special strontium sampling of fish and invertebrates and shoreline sediment.

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

The milch animal census is used to identify animals producing milk for human consumption within 5 miles (8 km) of Indian Point. The census consists of visual field surveys of the areas where a high probability of milch animals exists and confirmation through personnel such as feed suppliers who deal with farm animals and dairy associations (See Table B-17). 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-18.

ODCM allow sampling of vegetation in two sectors near the site boundary in lieu of a garden census.

3.4 Statistical Methodoloay 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 (L.), and estimation of 3-4

the mean and associated propagated error.

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

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

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

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

- Instrument characteristics (e.g., efficiency)

- Sample size

- Counting time

- Media density (self-absorption)

- Radioactive decay

- Chemical yield In the ODCM program, LLDs are used to ensure that minimum acceptable detection capabilities for the counting system are met with specified statistical confidence levels (95% detection probability with 5% probability of a false negative). The LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement process and not as an "a posteriori" (after the fact) limit for a particular measurement. Table A-2 presents the RETS required LLDs for specific media and radionuclides as specified by the NRC. The LLDs actually achieved are usually much lower since the RETS required LLDs represent the maximum allowed.

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

Lc ka Sb (1 + Tb'TS)) 05 in cpm where: ka = 1.645 (corresponds to a 95% confidence level)

Sb = standard deviation of the background count rate = (Rb/Tb) 0 5 Rb = background count rate (cpm)

Tb = background count time (min)

Ts = sample count time (min)

For the REMP, net sample results which are less than the Lc value are considered not detected, and the Lc value is reported as the "less than" 3-5

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 Propaaated Error In accordance with program policy, recounts of positive samples are performed. When the initial count reveals the presence of radioactivity, which may be attributed to plant operations, at a value greater than the Lc, 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 EX,

=_ 1=1 N

where: X= value of each individual observation N = number of observations Z (ERRi)2 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 NRC's 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 3 -6

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

In the data tables B-6 through B-15, values shown are based on the Lc 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 Lc values for that sample, unless otherwise noted. If multiple counts were performed on a sample and a radionuclide's values are "< Lc " each time, the largest critical level is reported in the data table.

The historical data tables contain the annual averages of the positive values for each year. The historical averages are calculated using only the positive values presented for 1995 through 2004. The 2005 average values are included in these historic tables for purposes of comparison.

3.5 Program Units The Radiological Environmental Monitoring Program uses standard radiological units to express program results. The units and their description are as follows: r Becquerel is a measure of radioactive material, abbreviated Bq, from the International System of Units (SI). A Becquerel is one atom disintegration per second. A Becquerel will normally be used with a volume or mass to express the radioactive concentration of some sample material.

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

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

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

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

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

Millirem is a measure of radiation dose to humans, abbreviated mrem; it is 1/1 000 of a rem. Millirem expressed for some period of time is the dose rate.

The millirem is different from the milliroentgen in that the millirem is used for 3-7

reporting radiation dose to humans and the milliroentgen is a measure of radiation in the environment or in air. Normal background radiation dose is approximately 300 mrem per year.

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

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

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

Picocuries per cubic meter (pCi/M3) is used to express concentration for all air samples.

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

Picocuries perliter (pCill) is used to express concentration for liquid samples such as, precipitation, drinking water, and river water samples.

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

3-8

SECTION 4 RESULTS AND DISCUSSION

SECTION 4 RESULTS AND DISCUSSION 4.0 RESULTS AND DISCUSSION The 2005 Radiological Environmental Monitoring Program (REMP) was conducted in accordance with Indian Point's Offsite Dose Calculation Manuals ODCM. The ODCM contain 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. Additional sampling conducted for the REMP is designated "Non-RECS" because these samples are not required by the ODCM.

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 (Non-RECS)

Bottom sediment (Non-RECS)

Airborne Particulates and Radioiodine Precipitation (Non-RECS)

Drinking Water Terrestrial Broad Leaf Vegetation Direct Gamma Radiation Soil (Non-RECS)

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 2005 and assessed the significance of the findings.

A summary of the results of the 2005 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.

4-1

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.

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.

In addition to the naturally occurring radionuclides discussed above, Cs-137 was detected above background levels in various ODCM and Non-RECS sample media in the vicinity of Indian Point. The sources and significance of the presence of this radionuclide is described in later sections.

The second group of radionuclides detected in 2005 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), remains detectable.

In 2005, the detected radionuclide(s) attributable to past atmospheric weapons testing also consisted of Cs-1 37 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 2005 REMP comprises those that may be attributable to current plant operations. During 2005, Cs-137 and H-3 were the only potentially plant-related radionuclide detected in some of the 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. Trace amounts of H-3 were detected in one of four quarterly composite samples from the discharge mixing zone.

The levels detected were consistent with historical levels.

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 4-2

not likely to be present in 2005. Only Cs-1 37 is currently found from Chernobyl and also found in weapons test debris.

1-131 is also produced in fission reactors, but can result from non-plant related anthropogenic sources, e.g., medical administrations, such as in four of the last five annual reports.

In the following sections, a summary of the results of the 2005 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. The laboratory uses a Panasonic TLD system. In 2005, 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-I through DR-41. The table also provides the sector for each of the DR sample points. Table B4 provides the mean, standard deviation, minimum and maximum values in mR per standard quarterfor the years 1999 through 2004.

The 2005 means are also presented in Table B-4. Table B-5 presents the 2005 TLD data for the inner ring and outer ring of TLDs.

The 2005 mean value for the direct radiation sample points was 14.1 mR per standard quarter. The mean value for the period 1999 through 2004 was 14.2 mR per standard quarter. At those locations where the 2005 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- 6) is close to the site boundary. The outer ring (DR-17 to DR-32) has a radius of approximately 5 miles from the three Indian Point units. The results for these two rings of TLDs are provided in Table B-5. The annual average for the inner ring was 14.1 mR per standard quarter and also average for the outer ring was 14.1 mR per standard quarter. The control location average for 2005 was 15.9 mR per standard quarter.

4-3

Table C-1 and Figure C-1 present the 10-year historical averages for the inner and outer rings of TLDS. The 2005 averages are consistent with the historical data. The 2005 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 2005 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 0.015 pCi/M 3 and the average for the control location was 0.016 pCi/M 3. The activities detected were consistent for all locations, with no significant differences in gross beta activity in any sample due to location. Gamma spectroscopy analyses of the quarterly composite air samples showed that no reactor-related nuclides were detected and that only naturally-occurring radionuclides were present at detectable levels.

The mean annual gross beta concentrations and Cs-1 37 concentrations in air for the past 10 years are presented in Table C-2. From this table and Figure C-2, it can be seen that the average 2005 gross beta concentration was consistent with historical levels. Cs-1 37 has not been detected since 1987. This is consistent with the trend of decreasing ambient Cs-137 concentrations in recent years.

The charcoal cartridge analytical results are presented in Table B-8. "Less than" values are presented as sample critical level (Lc). There was no 1-131 detected (LLD = 0.07 pCi/mi3 ) 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 2005.

4.3 Hudson River Water 4-4

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-1 0, respectively.

No radionuclides other than those that are naturally occurring and tritium were detected in the Hudson River Water samples. Tritium, whose presence may or may not be attributable to plant operations, has been detected in the past as depicted in Table C-3, and was detected in one of four samples from the discharge canal at 618 + 130 pCi/I, slightly above Lc (413 pCi/I). These tritium levels are well below the required LLD of 3000 pCi/L. Additionally, table C-3 indicates the absence of Cs-1 37 which is consistent with historical data 4.4 Drinking Water The annual program summary table (Table B-2) contains a summary of the 2005 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-1 3 contains all the results of the gamma spectroscopic analyses of the shoreline soil samples.

In addition to the naturally occurring nuclides, Cs-137 was identified in the Hudson River shoreline soil samples in 2005. Cs-1 37 was detected in four out of ten samples from indicator locations. Cs-137 was detected at the control locations in two out of four samples. The average concentration for the indicator locations was 15$ pCi/kg-dry with a maximum concentration of 173 pCi/kg-dry. The control locations had positive samples indicating an average of 104 pCi/kg-dry and a maximum of 173 pCi/kg-dry.

An historical look at Cs-137 detected in shoreline soil at indicator and control locations can be viewed in Table and Figure C-5. Cs-137 has been and continues to be present in this media, both at indicator and control locations, 4-5

at a consistent level over the past ten years, and is likely due to legacy contamination from weapons fallout.

4.6 Broad Leaf Vegetation Table B-2 contains a summary of the broad leaf vegetation sample analysis results. All the data from analysis of the 2005 samples are presented in Table B-14. Analyses of broad leaf vegetation samples revealed only naturally occurring nuclides. Historically, Cs-1 37 has been detected in both control and indicator broad leaf vegetation.

Table C-6 contains a summary and Figure C-6 an illustration, of the broad leaf vegetation analysis results for the past 10 years. The detection of low levels of Cs-137 is consistent with the sporadic detection at both indicator and control locations of relatively low concentrations for the past ten years.

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 all fish and invertebrate samples for 2005. None of the indicator samples revealed radionuclide concentrations greater than Lc values. Only naturally occurring nuclides were detected. 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 Additional Media SamDling Although not required by the RECS, analyses were performed on aquatic vegetation, Hudson River bottom sediment, soil, precipitation samples, and various other special water samples. A summary of the analytical results obtained is presented in Table B-1 6. As shown by these data, the radionuclides detected were consistent with their respective historical levels.

Since these samples were not required by the ODCM, individual tables and graphs are not presented for the data.

Cs-1 37 was detected in one of five indicator samples in aquatic vegetation and zero of five control location samples.

Precipitation samples were analyzed for H-3 (tritium) and plant-related nuclides at two locations. No tritium or other plant related nuclides were detected at either location. Historically, tritium has been detected in precipitation at both indicator and control locations.

The Algonquin Outfall, Gypsum Plant Stream, Verplanck-5' Street Well, and 4-6

Trap Rock Quarry samples were analyzed for tritium and plant-related nuclides. The samples did not show any tritium or other plant-related nuclides.

SThe Non-RECS sample location of Algonquin Outfall was designated in 1996 and the other special water samples were designated late in 2003 The results from the Non-RECS sampling show that the main detected anthropogenic activity is Cs-1 37, which is found at both indicator and control locations. The Non-RECS sample data corroborate the ODCM sample data in determining that the operation of the Indian Point station in 2005 had no detectable adverse radiological impact on the environment.

4.9 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 2005 Spring, Summer and Fall months in accordance with the ODCM Section D 3.5 Radiological 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 and summer and fall.

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

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

Results:

A census was performed in the vicinity of Indian Point in 2005. This census consisted of a milch animal and a residence census. Results of this census are presented in Tables B-17 and B-18.

The results of the 2005 census were generally same as the 2004 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 nearest residences are located 0.44 miles (0.71 km) ESE and 0.73 miles (1.13 km) S of the plant.

The 2005 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.

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.

4.10 Tritium Investigation Results.

All water samples associated with the augmented offsite sampling showed no detectable levels of tritium, strontium-90 or other isotopes that were distinguishable from natural background levels related to nuclear power plant operations. Samples were counted at the JAF offsite environmental laboratory and some samples cross-checked with a third party independent laboratory.

Further, regulatory agencies' sample results, which conducted split samples offsite, also showed no detection of plant related isotopes which were distinguishable from natural background levels for tritium or strontium-90.

Accordingly, for this public dose pathway or offsite environmental impact assessment, all samples continue to show radioactivity levels that were indistinguishable from background radiation levels from natural occurring radionuclide's or legacy environmental contamination from weapons fallout.

4.11 Conclusion The Radiological Environmental Monitoring Program is conducted each year to determine the radiological impact of Indian Point operations on the 4-8

environment. The preceding discussions of the results of the 2005 REMP reveal that operations at the station did not result in an adverse impact on the environment.

The results of the 2005 REMP also revealed that the impact on the environment of fallout from previous atmospheric weapons testing and Chernobyl continues to represent the greatest long-term radiological environmental impact from anthropogenic sources. The 2005 REMP results demonstrate the relative contributions of different radionuclide sources, both natural and anthropogenic, to the environmental concentrations. Overall, doses to humans are much more significant from non-plant related sources than those associated with plant operations.

4-9

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.

5-1

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

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

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

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-1 37 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 Throuah 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. McFarland, R.C., et al., The Counting Room: Special Edition, Radioactivity and Radiochemistry, Caretaker Publications, Atlanta, Georgia, 1994.

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

28. EN-LI-1 02, Corrective Action Process 29.Technical Information Document 2003-011 "Justification for the Removal of the Radiological Environmental Monitoring Blind Spike Program at IPEC" 5-3

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-1, 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, ODCM designation and sample type. Non-RECS samples are also listed but have no ODCM designation code. This table gives the complete listing of sample locations used in the 2005 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. Figure A-2 shows the sampling locations within ten miles of Indian Point. Figure A-3 shows the Non-RECS sample locations within ten miles of Indian Point.

The ODCM required lower limits of detection 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-1, there is the environmental surveillance requirement that an annual land use and milch animal census be performed. See Tables B-17 and B-18 for the milch animal and land use census.

A-1

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS 3 DR8 Service Center Building Direct Gamma 0.35 Mi (SSE) at 1580 Al . . Onsite - Air Particulate, Al Algonquin Gas Line 0.28 Mi (SW) at 234° Radioiodine A4 . Air Particulate, 5 A4 NYU Tower Onsite - Radioiodine, DR1008 i(SW t28 Direct Gamma 7 Wbl Camp Field Reservoir 3.4 Mi (NE) at 510 Drinking Water 8 NR New Croton Reservoir 6.3 Mi (SE) at 124° Drinking Water 9 Wal Plant Inlet (Hudson River Intake)* Onsite - HR Water 0.16 Mi (W)at 2730 RWae 10 Wa2 Discharge Canal (Mixing Zone) Onsite - HR Water,

__ _ __ _NR __ _ _ _ _ _ _ _ _ _ _ _ _ _0.3 Mi (WSW) at 2490 HR Bottom Sediment 14 DR7 Water Meter House Onsite - 0.3 Direct Gamma

_____ ____Mi (SE) at 1330 NR HR Aquatic Vegetation, 17 NR Off Verplanck 1.5 Mi (SSW) at 202.50 HR Shoreline Soil, NR HR Bottom Sediment 20 DR38 Cortlandt Yacht Club 1.5 Mi (S) at 180° Direct Gamma

__________ ~~(AKA Montrose Marina)1. Mi( ) a 18 0D rc Gm a 22 NR Lovett Power Plant 1.6 Mi (WSW) at 2440 Radioodine NR Precipitation, A5 Air Particulate, A5 Radioiodine, 23 DR40 Roseton* 20.7 Mi (N) at 3570 Direct Gamma, lc3 Broad Leaf Vegetation, NR Soil, Ib2 Fish & Invertebrates 25 Ib1 Downstream Downstream Fish & Invertebrate NR Air Particulate, 27 NR Croton Point 6.36 Mi (SSE) at 1560 Radioiodine, DR41 Direct Gamma NR HR Shoreline Soil, 28 DR4 Lent's Cove 0.45 Mi (ENE) at 069° Direct Gamma, HR NR Bottom Sediment, NR HR Aquatic Vegetation NR Air Particulate, 29 NR Grassy Point 3.37 Mi (SSW) at 1960 Radioiodine, DR39 Direct Gamma 33 DR33 Hamilton Street (Substation) 2.88 Mi (NE) at 053° Direct Gamma I = Control location HR = Hudson River NR = non ODCM R/S = Reuter Stokes A-2

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS 34 DR9 South East Comer of site W5JI0IR - at Direct Gamma 35 DR5 Broadway & Bleakley Avenue nsite - Direct Gamma DR5 _______

____ _______ _______ 0.37 M i (F) at 092 0 i et a m 38 DR34 Furnace Dock (Substation) 3.43 Mi (SE) at 1410 Direct Gamma NR Precipitation, 44 NR Peekskill Gas Holder Bldg 1.84 Mi (NE) at 0520 Air Particulate, NR Radioiodine 50 Wc2 Manitou Inlet* 4.48 Mi (NNW) at 3470 HR Shoreline Soil 53 Wc1 White Beach 0.92 Mi (SW) at 226 Direct Gammia 56 DR37 Verplanck - Broadway & Sixth Street 1.25 Mi (SSW) at 2020 Direct Gamma 57 DR1 Roa Hook 2 Mi (N) at 005' Direct Gamma 58 DR17 Route 9D - Garrison 5.41 Mi (N) at 3580 Direct Gamma 59 DR2 Old Pemart Avenue 1.8 Mi (NNE) at 0320 Direct Gamma 60 DR18 Gallows Hill Road & Sprout Brook 5.02 Mi (NNE) at 0290 Direct Gamma

_ __ _ __ _ __ _ _ _ _ _ _ _ _ _ R oad_ _ _ _ _ _ _ _ _

61 DR36 Lower South Street & Franklin Street 1.3 Mi (NE) at 0520 Direct Gamma 62 DR19 Westbrook Drive 5.03 Ml (NE) at 062° Direct Gamma (near the Community Center) 5 64 DR20 Lincoln Road - Cortlandt 4.6 Mi (ENE) at 0670 Direct Gamma 66 DR21 Croton Avenue - Cortlandt 4.87 Mi (E) at 0830 Direct Gamma 67 DR22 Colabaugh Pond Road - Cortlandt 4.5 Mi (ESE) at 1140 Direct Gamma 69 DR23 Mt. Airy & Windsor Road 4.97 Mi (SE) at 127° Direct Gamma 71 DR25 Warren Ave - Haverstraw 4.83 Mi (S) at 1880 Direct Gamma 72 DR26 Railroad Avenue & 9W - Haverstraw 4.53 Mi (SSW) at 2030 Direct Gamma 73 DR27 Willow Grove Road & Captain 4.97 Mi (SW) at 2260 Direct Gamma Faldermeyer Drive 74 DR12 West Shore Drive - South 1.59 Mi (WSW) at 2520 Direct Gamma 75 DR28 Palisades Parkway 4.65 Mi (NW) at 3100 Direct Gamma 76 DR13 West Shore Drive - North 1.21 Mi (W) at 2760 Direct Gamma 77 DR29 Palisades Parkway 4.15 Mi (W) at 2720 Direct Gamma 78 DR14 Rt. 9W across from R/S #14 1.2 Mi (WNW) at 2950 Direct Gamma

• =Control location HR = Hudson River NR = non ODCM RIS = Reuter Stokes A-3

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS 79 DR30 Anthony Wayne Park 4.57 Mi (WNW) at 2960 Direct Gamma 80 DR15 Route 9W South of Ayers Road 1.02 Mi (NW) at 317° Direct Gamma 81 DR31 Palisades Pkwy - Lake Welch Exit 4.96 Mi (WSW) at 255° Direct Gamma 82 DR16 Ayers Road 1.01 Mi (NNW) at 334° Direct Gamma 83 DR32 Route 9W - Fort Montgomery 4.82 Mi (NNW) at 3390 Direct Gamma NR HR Aquatic Vegetation, 84 NR Cold Spring

• 10.88 Mi (N)at 3560 HR Shoreline Soil, NR HR Bottom Sediment 88 DR6 R/S Pole #6 0.32 Mi (ESE) at 1180 Direct Gamma 89 DR35 Highland Ave & Sprout Brook Road 2.89 Mi (NNE) at 0250 Direct Gamma

___ ____ ____ (near rock cut) 90 DR3 Charles Point 0.88 Mi (NE) at 0470 Direct Gamma 92 DR24 Warren Road - Cortlandt 3.84 Mi (SSE) at 1490 Direct Gamma A2 Air Particulate, 94 A2 IPEC Training Center Onsite- Radioiodine, 1c2 0.39 Mi (S) at 193° Broadleaf Vegetation, NR Soil A3 Air Particulate, 95 A3 Meteorological Tower Onsite - Radioiodine, Id Mtorlgca oe 0.46 Mi (SSW) at 2080 Broadleaf Vegetation, NR Soil 99 NR Algonquin Outfall Onsite - 0.34 Special Water

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ M i (S W ) at 237 0 _ _ _ _ _ _ _ _

100 NR Gypsum Plant Outfall Onsite - 0.34 Special Water

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ M i (S W ) at 237 0 _ _ _ __ _ _ _ _

101 NR 5th Street Well - Verplanck 1 .3 Mi (S) at 2020 Special Water 102 NR Trap Rock Quarry 0.7 Mi (SSW) at 2080 Special Water

• = Control location HR = Hudson River NR = non ODCM R/S = Reuter Stokes A-4

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

LIl Peekskill Westchester County Rockland County Indian PoinK-Ib1 li I I mile Hudson Ilc1' River Ic2 Buct Verplanck Key: A - Waterborne: Surface (HR) Wa# Ic# - Broadleaf Vegetation o - Direct Radiation Sample Location DR# IbI - Fish and Invertebrates (where available downstream) o - Air Particulate & Radioiodine A#

O - HR Shoreline Sediment Wc#

A-5

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

Roseton (20.7 mi. N): E5 © Ic3 Upstream: Ib2 Orange County Putnam County Bear Mountain Bridge Cl 5) ndian Point Hudso River 1 5 miles Rockland County Westchester County Key: o - Direct Radiation Sample Location DR# Ic3 - Broadleaf Vegetation O - Air Particulate & Radioiodine A# Ib2 - Fish and Invertebrates

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

A-6

FIGURE A-3 SAMPLING LOCATIONS Non-RECS Sampling Locations N

Roseton (20.7 mi. N): 23: p

• Orange County Putnam County Cold Spring (10.88 mi. N): 84 :V Bear Mountain Bridge 10:

• 99: sp 17: V 29: U

-101:sp Westchester County Rockland County

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

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

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

- -1M

-AA I H-3 I 2000'X' I l ll_ I Mn-54 15 l 130 l l T 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-1 40 15 15 (a) This list does not mean that only these nuclides are to be considered. Other identifiable peaks 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.

A-8

TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES I I t Mn-54 1000 30000 Fe-59 400 l 10000 7 _

Co-58 1000 30000 Co-60 300 10000 Zn-65 300 20000 Zr-Nb-95 400 1-131 2 (b) 0.9 3 100 Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La-140 200 300 (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 2005 Annual Radiological Environmental Monitoring Program Summary The results of the 2005 radiological environmental sampling program are presented in Tables B-2 through B-16. Table B-2 is a summary of the ODCM samples and Table B-1 6 is a summary of the Non-RECS samples. The format of these summary tables 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 all the individual ODCM samples are provided in Tables B-3 through B-15.

REMP samples were analyzed by various counting methods as appropriate. The methods are; gross beta, gamma spectroscopy analysis, liquid scintillation, 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 (1-131) and tritium analyses were performed for specific media and locations as required in the ODCM.

B.2 Land Use Census Inaccordance with Sections 4.11.B of the ODCM, a land use census was conducted to identify the nearest milch animal and the nearest residence. The results of the milch animal and land use censuses are presented in Tables B-17 and B-18, respectively. In lieu of identifying and sampling the nearest garden of greater than 50m 2 , 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 Samoling Deviations During 2005, environmental sampling was performed for six media types required by ODCM, five other media types and direct radiation. A total of 1347 were obtained.

Of the scheduled samples, 97.9% were collected and analyzed for the program.

Sampling deviations are summarized in Table B-1; discussions of the reasons for the deviations are provided in Table B-1a for air samples, B-1b for TLDs, and B-1c for other environmental media.

B.4 Analytical Deviations There were no analytical deviations for 2005.

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

B-1

TABLE B-1

SUMMARY

OF SAMPLING DEVIATIONS 2005 MEDIA PARTICULATES IN AIR 477 12 97.5 See Table Ba CHARCOAL FILTER 477 12 97.5 See Table B1 la TLD 164 0 100.0 HUDSON RIVER WATER 32 2 93.8 See Table ic B-DRINKING WATER 48 1 97.9 See Table B-SHORELINE SOIL 10 0 100.0 BROAD LEAF VEGETATIO 54 0 100.0 FISH & INVERTEBRATES 14 0 100.0 SUBTOTALS 1276 27 97.9 NON.ODCM MEDIA AQUATIC VEGETATION 10 1 90.0 See Table B-IC HUDSON RIVER BOTTOM SEDIMENT 10 0 100.0 SOIL 3 0 100.0 PRECIPITATION 8 0 100.0 SPECIAL WATER 4 975 See Table B3-SAMPLES 40 1 97.5 S c SUBTOTALS 71 2 97.2 See Table I

OVERALL TOTALS 1347 J 29 J 97.8 l TOTAL NUMBER OF ANALYSES REPORTED = 1318

• Samples not collected or unable to be analyzed.

B-2

TABLE B-1a / B-1bIB-1c TABLE B-1a 2005 Air Sampling Deviations FI$:)N' li J K3/40WEEK P lMACTONS$TOPREVE4T MENE lovett power plant week 4 The volume on the sample was low due to power outage at the site The time meter indicates 2 and 1/2 days.

CR-IP2-2005-00358 GRASSY POINT Week 11 The air sampler was not running on Monday. The breaker was Tripped some time early Saturday morning. We lost 51 hours5.902778e-4 days <br />0.0142 hours <br />8.43254e-5 weeks <br />1.94055e-5 months <br /> of Sample this week. The power was restored at 0900 Monday Algonquin Week 14 We found that the power too the air sampler was out and by the hour meter itwas off from 0630 on 41215. There was a black out test that morning and the breaker did not reset. The power was restored and the sampler started at 1300 on 4/7/5.CR 2005-0136 Met tower Week 18 The air sampler had lost power some Ume during the week for 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> The flow was good and the power was normal when we changed out the sample. CR 2005-01681 Algonquin Week 20 The GFI was tripped and by the hour meter It had tripped at 1430 on Friday 5/13/5 I reset the GFI and It started up.CR 2005 1915 Algonquin Week 26 We found the door on Algonquin air sample station open and the pump was not running. Attemps to restart the pump tripped the GFI. The pump ran for 107.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> out of 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br />. We replaced the pump and wrote CR 2005-02660 Algonquin Week 28 The air sample at Algonquin was found not running with the GFI tripped. The sample ran for 82 hours9.490741e-4 days <br />0.0228 hours <br />1.35582e-4 weeks <br />3.1201e-5 months <br /> from 8:40 AM Tuesday 7/5/5 until Friday at 6:40 PM. We reset the GFI and the air sample was left running. Wrote CR-1P2-2005-02892 Algonquin Week 37 The air sample at Algonquin was found not running with the GFI tripped. The sample ran for 82.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> from 8:45 AM Tuesday 9/6/5 until Friday at 7:15 PM. We reset the GFI and the air sample was left running.On 9/1415 NEM replaced the GFI with a new one a Lovett week 45 The air sample at Lovett Power Plant was not running. There was no power to the air sample. We lost 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of sample. I got the operator to reset the breaker. The plant Is in an outage. Wrote C.R.-IP2-2005-04537 Roseton Week 45 The air sample at Roseton was not running. The power was out at the locatlon.We had about 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of sample. Power was not restored to that location so we had to move the air sample to a different location on the Roseton site.

Lovett Week 46 The air sample lost 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> some time during the week. It was running when NEM collected the sample.

NYU week 50 The air sample was not running. The pump was seized and we also had a problem with the power. We replaced the pump and rebuilt the Air sample station.wo 1P2-05-112035 B-3

TABLE B-1a / B-1b/B-1c TABLE B-1b 2005 TLD Deviations NM0T,1- 01l10iNO--0 None NONE NONE TABLE B-1c 2005 Other Media Deviations I*iTATIONo"g lSAPL ECHDUE ROBEMICTINSTOPRVEN RECUREC Hudson River Intake Week 1 There was no water In the sample collection bucket.CR- P2-2005-00084 NEM took a grab sample on 1/7/5 Replaced sampler on 1/12/5 Hudson River Intake Week 3 There was no water In the sample collection container. The sample tube was frozen.

NEM took a grab sample and relocated the heat trace tube.

All this week the weather was well below freezing.

CR-1P2-2005-00308 DRINKING WATERS week 6 The drinking waters was not counted for 1-131. The submittal forms did not request It to be counted for 1-131 The lab tried to count for 1-131 and they counted for 55 hrs but could not get LLD Verplank/Cold Spring week 24 Unable two get aquatic vegetation It Is not growing yet. CR 2005 2456 5 th street well Week 37 We were uable to get a sample from the well. It has been a very dry summer an the well seems to be dry.CR 1P3-2005-04400 Hudson River Discharge Week 43 The composite water sample hose for the site discharge canal was found to be located Inside the canal structure Instead of the Hudson River-canal mixng zone as stated in the REMP program description. Sample hose was relocated back to Its previous location IAW REMP technical bases. CR-1P2-2005-4319 B-4

TABLE B-2*

ODCM ANNUAL

SUMMARY

- 2005 DIRECT RADIATION r6 West Shore Drive North TLD Reads 14.0 (160/160)1 0 (mR / standard quarter) NIA 1.21 Mi. (2760) DR13 1 15.9 (4/4)113.2 - 20.3 1 164 9.6 - 22.5 B-3 18.9 (4/4)117.2 - 20.2 AIR PARTICULATES #4 Algonquin Gas Line (Onsite)

AND RADIOIODINE GB (477) 0.015(424/424)/0.003 - 0.033 0.28 Mi. (2340) 0.016 (53153) 0.003- 0 (pCUm 3) B-6, B-7, B-8 0.016 (53/53) / 0.004-0.029 0.029 1-131 (467) 0.07 <Lc <Lc <Lc 0 GSA (36)

Cs-1 34 0.05 <Lc <Lc <Lc 0 Cs-137 0.06 <Lc <Lc <Lc 0 SURFACE HUDSON RIVER WATER (pCi/L) H-3 (8) 3000 <Lc <Lc <Lc 0 B-9, B-10 GSA (241 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 <c 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 DRINKING WATER 2.39(12/12) / Camp Field Resevoir (pCVL) B-11, B-12 GB (12) 1.11- 3.54 3.4 Mi (0512 ) N/A 0

___________2.39 (12/12Y 1. I1 - 3.54 H-3 (4) 2000 <Lc <Lc N/A 0 GSA 1IN/

Mn-54 15 <Lc <Ic N/A 0 Co-58 15 <Lc <Lc N/A 0 Fe-59 30 <Lc <Lc N/A 0 Co-60 15 <Lc <Lc N/A 0 Zn-65 30 <Ic <Lc N/A 0 B-5

TABLE B.2*

ODCM ANNUAL

SUMMARY

- 2005 JKING WP <Lc <Lc N/A (CONT) 1-131 15 <Lo 0

<Lc N/A Cs-134 15 <Lc 0

<Lc N/A Cs-1 37 18 <Le 0

<Lc N/A 0

Ba/La-140 15 <Lr~ <Lc N/A SHORELINE SOIL G (pCVkg - dry) B-13 SA (43 Cs-134 150 <Lc <Lc Lc 0

1. 50 Manitou Inlet Cs-1 37 180 <Lo 4.48 Mi. (347.5-) 174 -(174) 0 18174

-s13 (112)1/174 - 174 1 BROADLEAF VEGETATION GSA (541 (pCi/kg - wet) B-14 1-131 60 cLc <Lc <Lc 0 Co-60 N/A <Lc <Lc <Lc 0 Cs-134 60 <Lc <Lc <Lc 0 Cs-137 80 <Lc <Lc <Lc 0 FISH AND INVERTEBRATES GSA (14)

(pCikg - 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 <Ic 0 Zn-65 260 <Lc <Lc <Lc 0 Cs-134 130 <Lc <Lc <Lc 0 Cs-137 150 <Lc <Lc <Lc 0 B-6

TABLE B-3 2005 DIRECT RADIATION, QUARTERLY DATA (mR per STANDARD QUARTER) t 0.8 I t .Q z t u.o DR-02 NNE 14.2 i 0.9 12.6 +/- 0.8 14.4 +/- 0.8 16.0 +/- 1.1 14.3 57 DR-03 NE 12.4 +/- 0.6 10.4 +/- 0.8 12.6 +/- 0.8 13.3 +/- 1.0 12.2 49 DR-04 ENE 13.2 +/- 0.8 11.6 +/- 1.0 14.5 +/- 1.1 14.4 +/- 0.6 13.4 54 DR-05 ENE 13.0 +/- 0.9 11.5 +/- 0.8 14.5 +/- 0.7 15.6 +/- 0.9 13.6 55 DR-06 ESE 12.8 +/- 1.0 11.8 +/- 0.9 14.1 +/- 0.7 15.0 +/- 0.7 13.5 54 DR-07 SE 14.5 i 0.7 13.9 +/- 1.0 16.9 +/- 0.9 17.1 +/- 0.9 15.6 62 DR-08 SSE 11.7 +/- 0.7 11.1 +/- 0.8 13.9 +/- 0.8 13.8 +/- 0.6 12.6 51 DR-09 S 12.3 +/- 1.0 12.0 +/- 1.3 14.3 +/- 0.9 15.1 +/- 1.1 13.4 54 DR-10 SSW 13.7 +/- 1.2 12.9 +/- 0.8 15.9 +/- 1.0 16.1 +/- 0.8 14.6 59 DR-11 SW 10.3 +/- 0.6 9.6 +/- 0.8 11.5 +/- 0.7 13.2 +/- 0.7 11.2 45 DR-12 WSW 16.0 +/- 0.8 15.2 +/- 1.3 18.3 +/- 0.8 17.3 +/- 0.9 16.7 67 DR-13 WSW 18.5 +/- 1.6 17.2 t 1.0 20.2 +/- 1.1 20.0 +/- 0.8 18.9 76 DR-14 WNW 12.2 +/- 0.8 11.6 +/- 0.8 14.3 +/- 0.9 13.6 +/- 0.8 12.9 52 DR-15 NW 11.9 +/- 0.8 11.6 +/- 0.8 14.3 +/- 0.7 13.9 +/- 0.5 12.9 52 DR-16 NNW 13.1 +/- 0.7 12.9 i 0.9 16.6 +/- 1.1 15.3 +/- 0.8 14.5 58 DR-17 N 13.8 +/- 1.0 13.6 +/- 0.9 16.4 +/- 0.8 15.5 +/- 0.6 14.8 59 DR-18 NNE 13.7 +/- 0.9 12.2 +/- 0.9 15.6 +/- 0.7 16.0 +/- 0.6 14.4 57 DR-19 NE 14.8 +/- 0.8 12.9 +/- 1.2 16.2 +/- 0.9 16.2 i 0.8 15.0 60 DR-20 ENE 13.2 +/- 0.8 11.4 +/- 0.8 14.4 +/- 0.9 14.6 +/- 0.8 13.4 54 DR-21 E 12.2 +/- 0.8 12.0 +/- 0.9 14.5 +/- 0.7 15.6 +/- 0.7 13.6 54 DR-22 ESE 10.4 +/- 0.6 9.6 +/- 0.9 12.1 +/- 0.7 12.8 +/- 0.7 11.2 45 DR-23 SE 12.2 +/- 0.7 11.7 +/- 1.3 14.6 +/- 0.7 16.0 +/- 1.5 13.6 55 DR-24 SSE 12.8 +/- 0.8 12.6 +/- 1.0 16.0 +/- 0.9 16.2 +/- 0.7 14.4 58 DR-25 S 11.4 +/- 0.8 10.6 +/- 0.9 13.8 +/- 0.6 13.0 +/- 0.5 12.2 49 DR-26 SSW 12.4 +/- 0.7 12.2 +/- 1.0 14.4 +/- 0.8 13.9 +/- 0.6 13.2 53 DR-27 SW 12.2 +/- 0.7 12.2 +/- 0.9 14.8 +/- 0.8 13.9 +/- 0.8 13.3 53 DR-28 NW 15.2 +/- 1.0 15.5 +/- 1.0 22.5 +/- 1.7 19.3 +/- 0.9 18.1 73 DR-29 W 12.5 +/- 0.8 12.5 +/- 0.9 16.3 +/- 0.9 14.5 +/- 0.6 14.0 56 DR-30 SNS 13.0 +/- 0.8 13.9 +/- 1.1 16.4 +/- 0.7 14.5 +/- 0.6 14.5 58 DR-31 WSW 15.6 +/- 0.8 16.0 +/- 1.1 20.6 +/- 1.1 17.8 +/- 1.1 17.5 70 DR-32 NNW 12.2 +/- 0.8 11.2 +/- 0.8 14.5 +/- 0.8 13.1 +/- 0.6 12.7 51 DR-33 NE 13.8 +/- 0.7 11.8 +/- 0.8 14.7 +/- 1.0 14.9 +/- 0.7 13.8 55 DR-34 SE 11.8 +/- 0.7 11.3 +/- 0.9 13.6 +/- 0.7 13.8 +/- 0.8 12.6 50 DR-35 NNE 13.2 +/- 0.7 12.1 +/- 0.9 15.1 +/- 0.7 15.9 +/- 0.9 14.1 56 DR-36 NE 15.0 +/- 0.7 12.6 +/- 0.9 15.2 +/- 0.7 15.6 +/- 0.8 14.6 58 DR-37 SSW 12.3 +/- 0.9 11.9 +/- 0.8 14.2 +/- 0.7 14.1 +/- 0.6 13.1 53 DR-38 S 12.3 +/- 0.9 11.9 +/- 0.9 13.9 +/- 0.7 14.4 +/- 0.8 13.1 52 DR-39 SSW 13.4 +/- 1.0 13.9 +/- 1.0 15.6 +/- 0.7 14.5 +/- 0.7 14.4 58 DR-41 SSE 12.4 +/- 0.9 11.3 +/- 0.8 14.2 +/- 0.6 14.4 +/- 0.6 13.1 52 AVERAGE 13.1I +/- 0.8 12.51 +/- 0.9 15.5T +/- 0.8 15.21+/-1 0.8 14.1 56.2

• Data not available MM' to _at B-7

TABLE B-4 DIRECT RADIATION, 1999 THROUGH 2005 DATA (mR per Standard Quarter)

DR-02 15.5 2.8 12.3 23.3 14.3 DR-03 12.0 1.2 9.3 14.4 12.2 DR-04 13.5 1.5 11.1 16.3 13.4 DR-05 13.5 1.2 11.4 15.6 13.6 DR-06 13.3 1.3 10.8 16.3 13.5 DR-07 16.0 1.9 13.2 21.7 15.6 DR-08 13.0 1.3 11.1 16.3 12.6 DR-09 12.9 2.8 0.1 16.7 13.4 DR-i09 DR-10 13.7 2.4 5.3 16.8 14.6 DR-11 11.3 1.1 9.5 14.2 11.2 DR-12 16.8 1.5 14.5 19.8 16.7 DR-13 18.7 1.4 16.2 20.9 18.9 DR-14 13.2 1.2 11.1 15.9 12.9 DR-15 13.5 1.6 11.4 19.0 12.9 DR-16 14.7 1.6 11.4 18.4 14.5 I 4. I 4. 4.

DR-17 15.0 1.3 12.3 17.7 14.8 DR-18 14.0 1.4 10.8 16.0 14.4 DR-19 14.8 1.5 12.3 18.2 15.0 DR-20 13.6 1.4 11.4 16.1 13.4 DR-21 13.6 1.2 11.7 16.0 13.6 DR-22 11.4 1.2 9.6 14.1 11.2 DR-23 13.9 1.5 11.4 17.1 13.6 DR-24 14.0 1.5 10.8 16.2 14.4 DR-25 12.3 1.1 9.9 14.9 12.2 DR-26 13.6 1.2 11.7 17.0 13.2 DR-27 13.6 1.2 10.2 15.6 13.3 DR-28 15.6 2.1 12.2 22.5 18.1 DR-29 16.5 2.6 9.0 21.9 14.0 DR-30 15.8 2.5 9.9 23.8 14.5 DR-31 17.9 2.6 12.3 24.6 17.5 DR-32 13.1 1.7 9.9 17.7 12.7 DR-33 10.7 2.5 7.2 15.6 13.8 DR-34 13.3 1.7 9.9 17.6 12.6 DR-35 14.2 1.7 11.1 18.0 14.1 DR-36 15.4 2.5 12.3 25.5 14.6 DR-37 13.7 1.3 11.7 16.2 13.1 DR-38 13.0 1.4 11.1 17.9 13.1 DR-39 15.6 1.5 12.9 19.4 14.4 DR-41 13.2 1.8 10.8 19.4 13.1 Average 14.2 14.1

• Data not available we.-mnrd oclor B-8

TABLE B-5 2005 DIRECT RADIATION INNER AND OUTER RINGS (mR per Standard Quarter)

DR-02 -1 .4 DR-03 DR-19 12.2 15.0 DR-04 DR-20 I 13.4 13.4 DR-05 DR-21 13.6 13.6 DR-06 DR-22 I 13.5 11.2 DR-07 DR-23 = 15.6 13.6 DR-08 DR-24 I 12.6 14.4 DR-09 DR-25 _ 13.4 12.2 DR-10 DR-26 c 14.6 13.2 DR-1I DR-27 = Al 11.2 13.3 DR-12 DR-28 V F 16.7 18.1 DR-13 DR-29 18.9 14.0 DR-14 DR-30 V _ 12.9 14.5 DR-15 DR-31 . I 12.9 17.5 DR-16 DR-32 r I

/ 14.5 12.7 Average- I 1 14.1 14.1 B-9

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2005 (pCi/m 3 +/- 1 sigma)

STATION #

Week 2ndat4 Jr0.02 94+/- 0.002 Jr 1 95 0.02 0.002 t 23S 0.021 +/- 0.002 1 1/4/2005 0.027 +/- 0.002 0 .002 +/-

2 1/11/2005 0.013 +/- 0.001 0.01 +/- 0.001 0.01 0.001 0.011 o0.001 0.015 '0.002 3 1/18/2005 0.016 +/- 0.002 0.014 i 0.002 0.018 i 0.002 0.014 +/- 0.001 0.013 0.001 4 1/25/2005 0.014 +/- 0.002 0.018 0.002 0.0162 0.002 0.018 0.002 0.02 +/- 0.002 5 2/1/2005 0.014 +/- 0.002 0.012+/-0.002 0.014 0.001 0.015 +/- 0.002 0.015 0.001 6 2/8/2005 0.027 +/- 0.002 0.021 +/- 0.002 0.023 +/- 0.002 0.024 +/- 0.002 0.023 +/- 0.002 7 2/15/2005 0.019 +/- 0.002 0.019 0.002 0.016 0.002 0.018 0.002 0.019 +/- 0.002 8 2/22/2005 0.015 0.002 0.013 0.002 0.014 +/- 0.001 0.013 0.002 0.011 o0.001 9 2/28/2005 0.015 0.002 0.017 0.002 0.012 0.002 0.014 0.002 0.012 0.002 10 3/8/2005 0.016 i0.001 0.014 +/-0.001 0.017 0.001 0.01370.001 0.014 +/- 0.001 11 3/14/2005 0.014 0.002 0.013 0.002 0.011 +/-0.001 0.012 0.002 0.015 0.001 12 3/22/2005 0.018 0.002 0.015 +/-0.002 0.014 0.001 0.013 0.001 0.014 0.002 13 3/29/2005 0.01 +/-0.001 0.01 +/-0.001 0.009 0.001 0.011 0.001 0.01 0.001 14 4/5/2005 0.005 0.001 0.005 0.001 0.005 +/- 0.001 0.005 0.001 0.004 +/- 0.001 15 4/12/2005 0.012 0.002 0.014 +/- 0.001 0.013 0.001 0.011 +/- 0.001 0.016 0.001 16 4/19/2005 0.024 0.002 0.022 0.002 0.028 0.002 0.023 0.002 0.013 0.001 17 4/26/2005 0.018 0.002 0.015 +/- 0.001 0.014 0.001 0.011 +/- 0.001 0.013 0.001 18 5/3/2005 0.012 +/- 0.001 0.013 0.001 0.012 0.001 0.014 +/- 0.001 0.008 +/- 0.001 19 5/10/2005 0.017 +/- 0.001 0.011 0.001 0.009 0.001 0.008 0.001 0.012 0.001 20 5/17/2005 0.014 0.002 0.015 0.001 0.015 +/- 0.001 0.017 +/- 0.001 0.015 +/- 0.001 21 5/24/2005 0.013 +/- 0.001 0.011 0.001 0.012 0.001 0.01 0.001 0.015 0.001 22 5/31/2005 0.009 +/- 0.001 0.01 i 0.001 0.009 0.001 0.009 +/- 0.001 0.009 0.001 23 6/7/2005 0.024 0.002 0.024 0.002 0.026 0.002 0.022 0.002 0.02 0.002 24 6/14/2005 0.024 .024 '0.002 0.025 0.002 0.022 0.002 0.02 0.002 25 6/21/2005 0.012 +/- 0.001 0.012 0.001 0.01 0.001 0.008 '0.001 0.011 0.001 26 6/27/2005 0.017 +/- 0.002 0.021 70.002 0.021 +/- 0.002 0.02 i0.002 0.023 +/- 0.002

• Sample deviation.

• • Control location. B-10

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2005 (pCi/m 3 +/- 1 sigma)

STATION #

Wek#Enlate _ 4 . , 0fg 5 _ _3 _

27 7/5/2005 0.019 +/- 0.001 0.018 +/- 0.001 0.017 +/- 0.001 0.014 +/- 0.001 0.018 + 0.001 28 7/12/2005 0.016 +/- 0.002 0.025+/-0.002 0.01970.001 0.019+0.002 0.016 7 0.002 29 7/19/2005 0.016 +/- 0.001 0.009 0.001 0.011 +/-0.001 0.012 0.001 0.017 + 0.002 30 7/26/2005 0.017+/-0.001 0.017 0.001 0.017 0.001 0.017 0.001 0.021 +/- 0.002 31 8/2/2005 0.021 70.002 0.0270.002 0.018 i 0.001 0.019 0.002 0.019 T 0.002 32 8/9/2005 0.027 7 0.002 0.028 7 0.002 0.025 +/- 0.002 0.026 +/- 0.002 0.029 +/- 0.002 33 8/16/2005 0.023 +/- 0.002 0.023 +/- 0.002 0.02170.002 0.02 0.002 0.024 +/- 0.002 34 8/23/2005 0.014 0.001 0.017 0.002 0.018 0.001 0.015i0.001 0.016 7 0.002 35 8/30/2005 0.01470.001 0.007 0.001 0.011 +/-0.001 0.012 0.001 0.014 7 0.001 36 9/6/2005 0.014 0.001 0.012 0.001 0.015 0.001 0.014 0.001 0.016 7 0.001 37 l9/13/2005 0.021 0.002 0.023 0.002 0.023 0.002 0.022 0.002 0.027 0.002 38 9/20/2005 0.021 : 0.002 0.022 0.002 0.021 0.002 0.017 0.001 0.027 + 0.002 39 9/27/2005 0.02470.002 0.023 _0.002 0.02 0.002 0.024 0.002 0.028 _ 0.002 40 10/4/2005 0.01870.002 0.015 0.001 0.018 0.001 0.016 0.001 0.02 +/- 0.002 41 10/11/2005 0.01370.001 0.013 0.001 0.009 0.001 0.011 +/-0.001 0.013 _ 0.001 42 10/18/2005 0.00470.001 0.005 0.001 0.005 0.001 0.004 0.001 0.003 7 0.001 43 10/25/2005 0.008 0.001 0.01 i 0.001 0.009 0.001 0.009 0.001 0.012 _ 0.001 44 11/1/2005 0.012 +/- 0.001 0.012 0.001 0.01 i 0.001 0.012 +/- 0.001 0.008 +/- 0.001 45 11/8/2005 0.02 +/- 0.002 0.02 0.002 0.019 i 0.002 0.021 +/- 0.002 0.024 +/- 0.002 46 11/15/2005 0.01570.001 0.012 0.001 0.016 +/- 0.001 0.013 0.001 0.019 +/- 0.002 47 11/21/2005 0.014 +/- 0.001 0.014 +/- 0.001 0.014 0.001 0.014 0.001 0.015 7 0.001 48 11/29/2005 0.012 0.001 0.012 0.001 0.013 0.001 0.01 +/-0.001 0.013 7 0.001 49 12/5/2005 0.012 0.001 0.009 70.001 0.009 +/- 0.001 0.009 +/- 0.001 0.012 7 0.001 50 12/13/2005 0.02270.001 0.018 0.003 0.0270.001 0.022T0.001 0.024 7 0.002 51 12/20/2005 0.015 7 0.001 0.015 7 0.003 0.01370.001 0.014 0.001 0.016 +/- 0.001 52 12/27/2005 0.029 +/- 0.002 0.033 +/- 0.002 0.028 0.002 0.027 +/- 0.002 0.029 +/- 0.002 53 1/4/2006 0.012 +-0.001 0.012 +-0.001 0.013 +-0.001 0.008 + 0.001 0.011 +- 0.001

• Sample deviation.

• • Control location. B-11

=

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2005 (pCi/m 3 t 1 sigma)

STATION #

wXl . ae[ 22 _ 4 7 1/3/2005 0.019 i 0.001 0.024 +/- 0.002 0.021 i 0.001 0.U25 i 0.U02 1/10/2005 0.013 i 0.001 0.012i0.001 0.012 i 0.001 0.012 i 0.001 1/18/2005 0.013 i 0.001 0.016"70.002 0.015 i 0.001 0.015 i 0.001 1/24/2005 0.02 _ 0.002 0.016 +/- 0.002 0.019 i 0.001 0.018 +/- 0.002 2/1/2005 0.013 i 0.001 0.014 i0.002 0.014 i 0.001 0.015 0.001 2/7/2005 0.02 i 0.002 0.021 i 0.002 0.019 i 0.002 0.022 i 0.002 2/14/2005 0.016 i 0.001 0.015 7 0.002 0.017 0.001 0.017 i 0.002 2/22/2005 0.012 0.001 i 0.001 i 0.001 0.015 i 0.001 0.01 0.013 0.001 0.014 2/28/2005 0.015 i 0.002 0.015 0.002 0.013 i 0.001 0.014 i 0.002 3/7/2005 0.016 i 0.001 0.015 0.001 0.014 i 0.001 0.013 i 0.001 3/14/2005 0.014 i 0.001 0.013 0.002 0.015 i 0.002 0.016 i 0.002 3/21/2005 0.017 i 0.001 0.012 i0.001 0.014 i 0.001 0.012 i 0.001 3/28/2005 0.011 7 0.001 0.009 i 0.001 0.009 i 0.001 0.012 i 0.001 4/4/2005 0.006 i 0.001 0.006 0.001 0.004 i 0.001 0.004 i 0.001 4/11/2005 0.011 i 0.001 0.012 0.001 0.011 i 0.001 0.01 i 0.001 4/18/2005 0.014 i 0.001 0.021 i 0.002 0.013 i 0.001 0.013 i 0.001 4/25/2005 0.013 i 0.001 0.012 i 0.001 0.01 i 0.001 0.01 i 0.001 5/2/2005 0.008 i 0.001 0.011 0.001 0.007 i 0.001 0.006 i 0.001 5/9/2005 0.009 i 0.001 0.011 i 0.001 0.005 i 0.001 0.007 i 0.001 5/16/2005 0.014 i 0.001 0.016 0.001 0.013 i 0.001 0.012 i 0.001 5/23/2005 0.014 i 0.001 0.011 +/-0.001 0.011 i 0.001 0.01 i 0.001 5/31/2005 0.009 i 0.001 0.006 i 0.001 0.008 i 0.001 0.008 i 0.001 6/6/2005 0.02 i 0.001 0.0247 0.002 0.019 0.001 0.018 i 0.001 6/13/2005 0.02 i 0.001 0.025 7 0.002 0.019 i 0.001 0.018 i 0.001 6/20/2005 0.007 i 0.001 0.009 i 0.001 0.007 i 0.001 0.006 +/- 0.001 6/27/2005 0.018 i 0.001 0.022 0.002 0.02 i 0.001 0.016 i 0.001

• Sample deviation.

• • Control location. B-12

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2005 (pCi/m 3 +/- 1 sigma)

STATION #

Wek EnDat 22iL 27i9 44 W 7/5/200r 0.013 +/- 0.001 0.014 +/- 0.001 0.015 i 0.001 0.012 i 0.001 7/11/2005 0.011 i 0.001 0.022 i 0.002 0.011 i 0.001 0.013 i 0.001 7/18/2005 0.013 i 0.001 0.013 i 0.001 0.015 0.001 0.015 7 0.001 7/25/2005 0.017 i 0.001 0.019 0.002 0.017 i 0.001 0.012 7 0.001 8/1/2005 0.015 i 0.001 0.01870.001 0.016 i 0.001 0.018 i 0.001 8/8/2005 0.026 i 0.002 0.027 i 0.002 0.023 i0.001 0.025 7 0.002 8/15/2005 0.023 +/- 0.002 0.021 7 0.002 0.021 i0.001 0.025 7 0.002 8/23/2005 0.017 i 0.001 0.02 +/-0.002 0.019 i 0.001 0.015 7 0.001 8/29/2005 0.012 i 0.001 0.011 0.001 0.011 i 0.001 0.011 i 0.001

=

9/6/2005 0.012 i 0.001 0.014 i 0.001 0.014 7 0.001 9/12/2005 0.018 i 0.001 0.023 0.002 0.021 i 0.001 0.019 7 0.002 9/19/2005 0.025 i 0.001 0.019 0.001 0.019 i 0.001 0.022 i 0.002 9/26/2005 0.024 i 0.001 0.02370.002 0.025 i 0.001 0.024 i 0.002 10/3/2005 0.016 i 0.001 0.017i0.001 0.013 7 0.001 0.015 i 0.001 10/11/2005 0.009 i 0.001 0.012i0.001 0.01 7 0.001 0.012 +/- 0.001 10/17/2005 0.004 i 0.001 0.004 i 0.001 0.005 7 0.001 0.003 i 0.001 10/24/2005 0.01 i 0.001 0.012 +/-0.001 0.01 7 0.001 0.009 7 0.001 10/31/2005 0.008 i 0.001 0.01 i 0.001 0.008 i 0.001 0.006 7 0.001 11/7/2005 0.017 i 0.002 0.021 i 0.002 0.021 i 0.001 0.023 0.002 11/15/2005 0.014 7 0.001 0.015 +/- 0.001 0.013 i 0.001 0.017 i 0.001 11/21/2005 0.014 i 0.001 0.016 +/- 0.002 0.014 0.001 0.005 i 0.001 11/28/2005 0.011 i 0.001 0.01270.001 0.01 i 0.001 0.012 i 0.001 12/6/2005 0.011 i 0.001 0.011 i 0.001 0.012 i0.001 0.011 i 0.001 12/12/2005 0.021 i 0.001 0.023i0.001 0.021 i 0.001 0.023 7 0.002 12/19/2005 0.015 7 0.001 0.012 0.001 0.012 i 0.001 0.013 =7 0.001 12/26/2005 0.024 i 0.001 0.0275 0.002 0.024 7 0.001 0.027 i 0.002 1/3/200f 0.01 +- 0.001 0.0122 +-0.001 0.011 0.001 0.012 +- 0.001

- a - - U U

• Sample deviation.

• • Control location. B-1 3

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2004 (RESULTS IN UNITS OF 1 0-3 pCi/m3 +/- 1 SIGMA) 1ST QUARTER 2005

[. ISOTOE REQS ALGONU..N.U.T STA ....... .MIN ST WR CROTON PT J TRINING aLDbe]TWE STA-9 STA-9 t-00-;ISO -:0l0::200C*'::-0 TOPE.i,.0i.:.00 0:~:::, i:: :::.:lE :iEE ........

Be.7 128.6+/-17.35 11413.67 11 9.813.15 100.2+/-12.9 126.8.13.51 K-40 <7.82 <5.01 <5.88 41.36+/-9.76 <9.2 Mn-54 <0.57 <0.66 <0.45 <0.57 <0.42 Co-58 <1.25 <6.01 <0.51 <0.85 <0.62 Fe-59 c4.26 <2.73 <2.45 <4.1 <2.51 Co-60 <0.84 <0.76 <0.39 <1.04 <0.49 Zn-65 <1.77 <1.34 <0.79 <0.96 <0.87 Zr-95 <2.55 <1.42 c0.90 <1.8 <0.92 Nb-95 <1.57 <1.23 <1.95 <0.99 <1.13 Ru-103 __ __ <1.64 <1.21 <0.93 <1.28 <0.99 Ru- 106 _ <6.98 <5.08 <2.5 <7.54 <6.59 1-131 ______ <12.73 <10.77 <11.8 <10.78 <11.15 Cs-I 34 (25.0)* <0.78 <0.95 <0.54 <0.57 <0.84 Cs-I 37 (30.0)* <0.75 <0.54 <0.4 <0.57 <0.38 BaLa-140 <12.5 <9.14 <6.19 <6.94 <6.90 Ce-141 <1.72 <1.35 <1.04 <1.64 <1.16 TICe-144 <2.48 <2.09 <1.34 <3.09 <2.19 Ra-226 <8.81 <8.12 <7.41 <9.51 <6.25 AcTh-228 (2.09 <2.36 <2.4 <1.71 <2.03 BOLD PRINT INDICATES REPORTED LLD VALUES

• Indicates naturally occurring.

• • 'Less than' values expressed as Critical Level (Lc), unless otherwise noted.

• • • Reported as sample LLD. B-14

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2004 (RESULTS IN UNITS OF 1 0-3 pCi/m3 +/- 1 SIGMA) 1ST QUARTER 2005 l :., .ISOTOPE I

MIN. gRSQ.;0R OEFROSETON STA-2 -2 GRASSY PT 1STAQ

~~~PEEKSKILL..

STA-44 Be-7 103.3+/-13.94 107.8+/-12.92 117.3+/-11.42 110+/-14.09 K-40 <6.2 <4.68 <4.39 <8.9 Mn-54 <0.45 <0.62 <0.24 <0.49 Co-58 <1 <0.57 <0.36 <0.52 Fe-59 <3.43 <2.59 <1.72 <3.54 Co-60 <0.67 <0.71 <0.41 <0.69 Zn-65 <1.41 <1.26 <0.6 <2 Zr-95 <2.04 <1.34 <0.64 <1.2 Nb-95 <1.27 <1.17 <0.56 <1.05 Ru-103 <1.33 <1.15 <0.71 <1.47 Ru-106 <5.55 <4.75 <2.65 <6.43 1-131 <11 <10.95 <8.36 <11.48 Cs-134 (25.or <0.62 . <0.88 <0.4 <0.85 Cs-137 (30.or <0.59 <0.51 <0.24 <0.42 BaLa-140 <10.46 <9 (4.90 <7.65 Ce-141 <1.39 <1.29 <1.04 <1.81 TICe-144 <1.97 <1.95 <1.26 <3.23 Ra-226 <6.98 <7.58 <3.92 <6.8 AcTh-228 <1.66 <2.21 <0.8 <2.82 a ______________ a _________________ .& ____________________ I ____________________ ____________________

BOLD PRINT INDICATES REPORTED LLD VALUES

• Indicates naturally occurring.

• • 'Less than" values expressed as Critical Level (Lc), unless otherwise noted.

• • • Reported as sample LLD. B-1 5

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2004 (RESULTS IN UNITS OF 1 0-3 pCi/m3 +/- 1 SIGMA) 2ND QUARTER 2005 IASOTPET f MIN. REQ.

... ALGONQUIN.

.4 NYU TOWER-STA-5 X.~..~CROTON PT... ..

STA-2 .

U3TRNBLOG:

TA-

.. MET TOWER STA-95 Be-7 77.88+/-14.17 102.6+/-12.99 111.7+/-13.43 107.8+/-15.57 76.22+/-1 1.2 K-40 _______<9.82 <4.64 51.25+/-10.46 c9.37 <5.27 Mn-54 _______ <0.83 <0.71 <0.7 <0.48 <0.35 Co5 <1.96 <0.71 <0.49 <0.86 <1.1 Fe-59__________ <4.19 <2.53 <2.3 <3.44 a.44 Co-60 _______<1.13 <0.43 <0.99 <0.79 <0.53 Zn65____ <1.91 <1.75 <1.42 <1.70 <1.48 Zr-95 <2.43 <0.89 <2.13 <1.50 <0.87 Nb-95 <1.51 <0.73 <1.15 <1.23 <1.43 Ru-103 <9.88 <0.81 <0.87 <1.56 <0.79 Ru16<5.21 <3.91 <4.6 <7.39 <3.14

-1:131 <8.5 <2.81 <6.94 <6.98 <6.15 Cs13 (25.0)* <0.74 <0.95 <0.7 <0.78 <0.51 Cs-37 (30.0)* <0.98 <0.52 <0.52 <0.69 <0.29 BaLa-140 <9.82 . <5.02 <5.37 <8.83 <4.49 Ce-141 <1.26 <0.97 <1.43 <1.35 <0.85 Kl4014 <2.86 <1.68 <2.91 <1.35 <1.81 Ra-226 <9.97 <7.02 <12.58 <10.02 <5.31 AcTh-228 _ _ _ <2.3796 <.00139 <1.28 <2.26 <1.17

__ __ __ _ _ _ _ __ __ _ _ __ _ __-_ _ I__ _ __ __ _ __ _ __ __ _ __ __ _ . _ _ __ __ _ __ __.. __ _ ___-_

50U0PLU mii DIA ES RPOuI EDu LLD VALUES

)

• Indicates naturally occurring.

• • 'Less than' values expressed as Critical Level (Lc), unless otherwise noted.

• • • Reported as sample LLD. B-1 6

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2004 (RESULTS IN UNITS OF 1 0-3 pCi/m3 +/- 1 SIGMA) 2ND QUARTER 2005 I...OP FI ... RE.I...... .. LOVETT~

S7777ST-2 ROSETON IEEK2~SKALL4 GRASSYP EKKL 1~i e

Be 7 J CL

• 111.8+/-12.77 101.6+/-16.52 118+/-10.78 89.49+/-12.25 K-40 <5.96 <8.56 <3.72 <5.77 Mn-54 <0.48 <0.51 <0.42 <0.7 Co-58 <0.56 <1.22 <0.6 <1.21 Fe-59 <1.85 <3.67 <1.6 <4.63 Co-60 <0.56 <0.84 <0.42 <0.58 Zn-65 <1.14 <2.36 <1.04 . <1.01 Zr-95 <0.91 <1.5 <1.06 <1.81 Nb-95 i <1.2 <1.32 <0.72 <1.77 Ru- 103 <0.7 <1.49 <0.56 <0.87 Ru-106 <3.68 <4.54 <4.26 <6.5i 1-131 <3.97 <11.47 <4.39 <4.97 Cs-134 (25.0)* <0.69 <0.64 <0.51 <0.61 Cs-137 (30.0)* <0.42 <0.43 <0.18 <0.52 BaLa-140 c4.34 <9.49 <4.52 <5.25 Ce-141 <1.28 <1.03 <0.83 <1.39 TlCe-144 <2.18 <1.30 <1.09 <2.73 Ra-226 <7.63 <6.14 <3.42 <8.89 AcTh-228 <1.78 <2.92 <0.82 <1.49 BOLD PRINT INDIICATES REPORTED LLD VALUES

• Indicates naturally occurring.

• • 'Less than' values expressed as Critical Level (Lc), unless otherwise noted.

• • • Reported as sample LLD. B-1 7

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2004 (RESULTS IN UNITS OF 1 0-3 pCi/m3 +/- 1 SIGMA)

QTR. NEAR 3rd 2005 I ALGONQUIN NYU TOWER CROTON:PT: f U3:N:: MET TOWER lSOT0PI MIN. REQ.  ::;:: i 0STA4 S.... .. ..-.. STA-27 ....... . ....-......

Be-7 125.2+/-11.7 112.9$13.16 107.5+/-9.71 98+/-9.85 115.8+/-12.2 K-40 <5.07 <6.62 <3.34 30.47+/-7.54 36.06+/-8.5 Mn-54 <0.24 <0.43 <0.28 <0.71 <0.69 Co-58 <0.91 <0.97 <0.49 <0.8 <0.49 Fe-59 <2.17 <3.64 <1.86 <3.67 <2.47 Co-60 <0.62 <1.12 <0.4 <0.65 <0.54 Zn-65 <1.6 <1.57 <1.29 <1.29 <1.00 Zr-95 <1.13 <1 <1.13 <0.92 <0.78 Nb-95 <1.22 <0.87 <0.85 <0.75 <0.64 Ru-103 <1.03 <1.11 <0.86 <0.98 <0.79 Ru-106 <5.53 <6.09 <3.74 <5.53 <5.89 1-131 <5.9 <5.34 <3.44 <4.22 <5.86 Cs-134 (25.0)* <0.6 <0.35 <0.64 <0.57 <0.7 Cs-137 (30.0)* <0.37 <0.62 <0.3 <0.34 <0.49 BaLa-140 <3.2 <5.44 <3.83 <3.19 <4.85 Ce-141 <1.25 <0.83 <0.69 <1.04 <1.06 TiCe-144 <2.12 <2.05 <1.33 <1.97 <2.25 Ra-226 <7.5 <4.12 <4.81 <7.82 <9.71 AcTh-228 _ __<2.03 <2.39 <0.74 <2.07 <2.55 BOLD PRINT INDICATES REPORTED LLD VALUES

• Indicates naturally occurring.

• • "Less than" values expressed as Critical Level (Lc), unless otherwise noted.

• • • Reported as sample LLD. B-18

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2004 (RESULTS IN UNITS OF 1 0-3 pCi/m3 +/- 1 SIGMA)

QTR. /YEAR 3rd 2005

....... .... ROSETON -11.. GRASSY PT. ...... IL ISO OPE. MIN...EQ.. S 2. I.. S. . I. S-TA-2 .... . S.

Be-7 82.158.66 113.310.92 101.1+/-1 103.39.86 K-40 C3.05 <5.9 <5.65 <3.1 Mn-54 <0.31 <0.52 <0.34 <0.35 Co-58 <0.34 <0.81 <0.34 <0.5 Fe-59 <1.97 <2.55 <1.83 <1.35 Co-60 <0.24 <0.34 <0.68 <0.5 Zn-65 <1.49 <1.36 <1.1 <1.02 Zr-95 <0.73 <1.07 <0.75 <0.47 Nb-95 <1.04 <0.96 <0.82 <0.78 Ru-103 <0.69 <0.47 <0.61 <0.88 Ru- 106 <2.39 <3.03 <3.03 <4.67 1-131 <3.95 <5.79 <4.96 <4.95 Cs-134 (25.0)* <0.58 <0.77 <0.43 <0.68 Cs- 137 (30.0)* <0.31 <0.28 <0.31 <0.4 BaLa-140 <4.89 <4.49 <5.65 <2.88 Ce-141 <0.93 <1.13 <0.63 <1.06 TICe-144 <1.37 <2.34 <1.05 <1.47 Ra-226 _<4.96 <7.33 <4.8 <6.16 AcTh-228 <1.16 <0.86 <1.37 <1.68 BOLD PRINT INIICATES REPORTED LLD VALUES

• Indicates naturally occurring.

• • 'Less than' values expressed as Critical Level (Lc), unless otherwise noted.

• • • Reported as sample LLD. B-19

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2004 (RESULTS IN UNITS OF 1 0-3 pCi/m3 +/- 1 SIGMA)

REPORTING UNITS IN: DCi/m3(x O-3) 4TH QTR 2005 ISOTOPE WOREQ.~

MIN.

CL*

ALGONQUIN STA4 NY TOWER3 STA-5 I1. CR SA2STA-VA T US.RN 3LDG 4STA-........

MET T R Be7_ 85.46+/-13.12 55.5+/-10.25 68.25+/-10.23 53.49+/-9.52 60.47i8.54 K-40 <6.91 <5.95 <7.03 <5.01 <4.57 Mn-54 <0.48 <0.33 <0.49 <0.62 <0.28 Co-58 <1.19 <0.82 <1 <0.58 <0.52 Fe-59 <4.31 <2.83 <3.14 <3.13 <2.65 Co-60 <0.74 <0.83 <0.57 <0.46 <0.39 Zn-65 <1.40 <2.08 <0.82 <1.31 <1.13 Zr-95 <1.11 <1.72 <1.15 <0.90 <0.65 Nb-95 <1.3 <0.83 <0.84 <1.2 <0.68 Ru-103 <0.98 <1.04 <0.58 <0.50 <0.58 Ru-106 <5.18 <7.4 <5.84 <6.21 <5.17 1-131 <5 <8.01 <4.7 <5.3 <5.4 Cs 134 (25.0)* <0.39 <0.46 <0.49 <0.55 <0.62 Cs 37 (30.0)* <0.59 <0.53 <0.34 <0.52 <0.24 BaLa-140 . <7.15 <4.87 <5.47 <4.81 <4.35 Ce-141 <1.33 <1.43 <1.21 <0.98 <1.13 TICe-144 _ <2.37 <2.13 <1.77 <1.66 <1.57 Ra-226 <6 <7.46 <9.21 <4.52 <5.39 AcTh-228 I <1.88 <2.27 <1.8 <1.15 <2.28 BOLD PRINT INDICATES REPORTED LLD VALUES

• Indicates naturally occurring.

• • "Less than" values expressed as Critical Level (Lc), unless otherwise noted.

• • • Reported as sample LLD. B-20

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2004 (RESULTS IN UNITS OF 1 0-3 pCi/m3 +/- 1 SIGMA) 4TH QTR 2005 LOVETT:! RSTNGRASSY. PT EKKL ISOTO- MIN~

.. ~  : ~II. I~.ST4

-STA--3 .......... TA.44 Be-7 7 .41 55.16+/-11.82 59.09+/-6.52 55.6+/-9.7 K-40 31.63+/-7.53 <10.1 <2.36 <5.74 Mn-54 <0.65 <0.49 <0.3 <0.4 Co-58 <0.8 <1.23 <0.31 <0.57 Fe-59 <2.55 <3.65 <1.2 <2.24 Co-60 <0.85 <0.77 <0.31 <0.47 Zn-65 <1.17 <2.77 <0.83 <1.42 Zr-95 <0.63 <1.62 <0.64 <1.15 Nb-95 <0.91 <1.34 <0.53 <0.59 Ru-103 <0.88 <0.82 <0.58 <0.82 Ru-106 <5.51 <8.46 <4.02 <6.92 1-131 <4.91 <4.84 <2.77 <5.58 Cs-134 (25.0)* <0.52 <0.71 <0.34 <0.75 Cs-137 (30.0)* <0.39 <0.5 <0.35 <0.34 BaLa-140 <3.7 <8.15 <3.07 <4.35 Ce-141 _ <1.36 <1.11 <0.6 <0.99 TiCe-144 <2.24 <2.34 <1.49 <1.98 Ra-226 _ <6.43 <6.21 <4.85 <4.72 AcTh-228 <2.2 <2.58 <1.6 <2.08 BULU PKINT INDICAiTEb REPORTUKE LLU VALUES

• Indicates naturally occurring.

• • 'Less than' values expressed as Critical Level (Lc), unless otherwise noted.

Reported as sample LLD. B-21

TABLE B-8 1-131 ACTIVITY IN CHARCOAL CARTRIDGE SAMPLES - 2005*

(pCi/m3

• 1 sigma)

F[)at~a~lSWER4E~iRD-q1m W1 510 1/4/2005 0.016 < 0.022 < 0.011 < 0.022 < 0.019 < 0.021 (0.017 < 0.017 < 0.022 2 1/11/2005 0.02 < 0.017 <0.02 < 0.028 < 0.021 < 0.019 (0.023 < 0.015 ( 0.016 3 1/18/2005 0.021 < 0.011 < 0.022 < 0.021 < 0.016 < 0.015 (0.013. < 0.013 ' 0.02 4 1/26/2005 (0.016 < 0.022 < 0.022 < 0.017 < 0.023 < 0.041 (0.022 < 0.017 < 0.031 5 2/1/2005 (0.018 < 0.022 < 0.023 < 0.018 <0.02 < 0.014 (0.016 < 0.015 ( 0.018 6 2V8/2005 (0.018 < 0.023 < 0.024 < 0.024 < 0.029 < 0.02 (0.022 < 0.017 ( 0.028 7 2115/2005 (0.022 < 0.031 < 0.014 < 0.023 < 0.022 < 0.021 (0.024 < 0.027 ( 0.035 8 2/22/2005 (0.022 < 0.019 <0.02 < 0.021 <0.021 < 0.014 (0.018 < 0.014 ( 0.023 9 2/28/2005 0.026 < 0.021 < 0.024 < 0.025 <0.022 < 0.021 (0.025 < 0.017 < 0.025 10 3/8/2005 0.035 < 0.021 < 0.018 < 0.014 < 0.026 < 0.019 (0.015 < 0.023 ( 0.024 11 3/14/2005 0.026 < 0.023 < 0.028 < 0.021 <0.022 < 0.013 (0.02 < 0.029 < 0.021 12 3/22/2005 (0.03 < 0.036 < 0.037 < 0.032 < 0.029 < 0.037 (0.018 < 0.006 < 0.032 13 3/29/2005 (0.048 < 0.023 < 0.016 < 0.038 <0.038 < 0.035 (0.032 < 0.026 < 0.032 14 4/5/2005 (0.04 < 0.009 < 0.026 < 0.029 < 0.029 < 0.021 (0.03 < 0.019 < 0.027 15 4/12V2005 (0.041 < 0.021 < 0.007 < 0.022 < 0.034 < 0.017 (0.035 < 0.023 < 0.024 16 4/19/2005 0.034 < 0.026 < 0.035 < 0.027 < 0.026 < 0.026 (0.022 < 0.022 < 0.024 17 4/26/2005 0.029 <0.018 < 0.026 < 0.018 < 0.026 < 0.017 (0.014 < 0.012 < 0.024 18 5/3/2005 0.023 < 0.021 < 0.012 < 0.032 < 0.023 < 0.025 (0.038 < 0.014 ' 0.019 19 5/10/2005 0.025 < 0.024 < 0.027 < 0.022 < 0.01 < 0.022 (0.026 < 0.019 ( 0.034 20 5/17/2005 0.033 < 0.032 < 0.028 < 0.021 < 0.008 < 0.011 (0.026 < 0.013 < 0.024 21 5/24/2005 0.029 < 0.023 < 0.024 < 0.021 < 0.045 <0.02 (0.028 < 0.022 < 0.028 22 5/31/2005 (0.029 < 0.032 < 0.008 < 0.024 < 0.029 <0.022 (0.029 < 0.015 < 0.028 23 6/6/2005 (0.022 < 0.025 < 0.022 < 0.024 < 0.031 < 0.0168 (0.0162 < 0.0127 < 0.0229 24 6/14/2005 (0.034 < 0.029 < 0.031 < 0.034 < 0.031 < 0.021 0.022 < 0.025 ( 0.009 25 6/21/2005 (0.029 < 0.042 < 0.019 < 0.009 < 0.031 < 0.021 <0.033 < 0.018 < 0.031 26 6/27/2005 (0.036 < 0.03 < 0.035 < 0.035 < 0.025 < 0.028 0.01 < 0.016 < 0.036 27 7/5/2005 (0.032 < 0.025 < 0.029 < 0.019 < 0.022 < 0.022 0.027 < 0.026 < 0.021 28 7/1212005 (0.029 < 0.032 < 0.025 < 0.026 < 0.028 < 0.031 0.036 < 0.021 ' 0.027 29 7/19/2005 (0.034 < 0.027 < 0.025 < 0.028 < 0.039 < 0.027 0.025 < 0.031 ( 0.025 30 7/26/2005 (0.017 < 0.03 < 0.006 < 0.026 <0.03 < 0.028 <0.043

• 0.022 e 0.031 31 8/2/2005 (0.017 < 0.025 < 0.022 < 0.032 < 0.025 < 0.028 <0.022 < 0.018 < 0.053 32 8/9/2005 (0.026 < 0.024 < 0.028 < 0.019 <0.03 < 0.02 <0.018 < 0.024 ( 0.025 33 8/16/2005 0.029 < 0.02 <0.02 < 0.006 < 0.032 < 0.003 <0.021 < 0.017 < 0.019 34 8/23/2005 0.028 < 0.02 < 0.021 < 0.024 < 0.022 < 0.021 <0.025 < 0.025 < 0.018 35 8/30/2005 0.014 < 0.02 < 0.018 < 0.025 < 0.025 < 0.014 <0.021 < 0.017 ' 0.029 36 9/6/2005 0.02 < 0.016 < 0.021 < 0.018 < 0.024 < 0.013 <0.015 < 0.014 c 0.02 37 9/13/2005 0.043 < 0.024 < 0.005 < 0.026 < 0.049 < 0.039 <0.037 < 0.021 c 0.031 38 9/20/2005 0.034 < 0.009 < 0.027 < 0.047 < 0.034 < 0.014 <0.022 < 0.022 < 0.024 39 9/27/2005 0.026 < 0.024 < 0.031 <0.021 <0.044 < 0.025 0.027 < 0.016 < 0.027 40 10/4/2005 0.04 < 0.025 < 0.027 < 0.042 < 0.029 < 0.018 <0.028 < 0.018 ( 0.033 41 10/11/2005 0.027 < 0.023 < 0.017 <0.04 <0.024 < 0.022 <0.024 < 0.019 < 0.029 42 10/18/2005 0.024 < 0.024 < 0.024 <0.04 < 0.027 < 0.023 <0.031 < 0.02 < 0.039 43 10/25/2005 (0.024 < 0.016 < 0.013 < 0.034 < 0.026 < 0.023 <0.043 < 0.034 ( 0.025 44 11/1/2005 (0.033 < 0.023 <0.021 < 0.043 < 0.022 < 0.015 <0.005 < 0.022 < 0.022 45 11/8/2005 (0.028 < 0.023 < 0.019 < 0.027 <0.035 < 0.052 <0.03 < 0.019 < 0.033 46 11/15/2005 (0.03 < 0.022 < 0.008 < 0.022 <0.03 < 0.034 <0.024 < 0.015 < 0.027 47 11/21/2005 (0.027 < 0.028 < 0.021 < 0.032 < 0.023 < 0.025 <0.033 < 0.019 < 0.034 48 11/29/2005 0.007 < 0.023 < 0.021 < 0.012 < 0.034 < 0.023 <0.021 < 0.026 < 0.026 49 12/5/2005 0.023 < 0.033 < 0.022 < 0.037 < 0.026 < 0.024 <0.036 <0.015 < 0.018 50 12/13/2005 0.025 (0.07 < 0.019 < 0.035 < 0.047 < 0.018 <0.018 < 0.035 < 0.024 51 12/20/2005 0.045 < 0.059 < 0.013 < 0.033 < 0.026 < 0.041 <0.025 < 0.031 < 0.03 52 12/27/2005 0.031 < 0.034 < 0.035 <0.04 < 0.028 < 0.02 <0.021 < 0.016 < 0.028 53 1/4/2006 (0.021 < 0.0446 < 0.0423 < 0.0311 < 0.0224 < 0.0217 <0.0325 < 0.0066 < 0.03

^ Less than' values expressed as sample Critical Level (Lj)unless otherwise noted.

B-22

TABLE B-9 CONCENTRATIONS OF GAMMA EMMITERS IN HUDSON RIVER WATER SAMPLES** - 2005 (pCi/L

• 1 SIGMA)

1. 9 PLANT INLET (HUDSON RIVER INTAKE) 4adlnucide d anu

• Marc A ni - Jne Be-7* <11.49 <16.18 <15.47 <12.36 <13.08 K.40* 199.5+/-13.48 210.9+/-17.03 172+/-21.99 400+/-22.24 375.9+/-17.82 167.4+/-15.4 Mn-54 <1.09 <1.31 <1.56 <1.55 <1.25 <1.28 Co-58 <1.24 <1.57 <2.2 <1.72 <1.36 <1.6 Fe-59 <3.61 <4.71 <5.68 <4.88 <3.87 <4.61 Co-60 <1.09 <1.55 <2 <1.59 <1.14 <1.38 Zn-65 <2.44 <3.21 <4.17 <2.48 <1.84 <2.89 Zr-95 <2.26 <2.84 <3.83 <2.73 <2.43 <2.92 Nb-95 <1.53 <1.85 <2.06 <1.87 <1.66 <1.94 Ru-103 <1.6 <0.99 <2.47 <2.21 <1.67 <1.92 Ru-106 <9.9 <13.31 <16.06 <17.85 <13.57 <16.21 1-131 <6.35 <5.57 <6.45 <7.01 <4.81 <5.47 Cs-134 <1.02 <1.24 <1.42 <1.73 <1.31 <1.5 Cs-137 <0.95 <1.22 <1.73 <1.56 <1.28 <1.2 Ba/La-140 <3.93 <4.68 <6.53 <6.35 <3.62 <4.12 Ce-141 <2.66 <2.4 <3.14 <3.56 <2.8 <2.85 Ce-144 <7.38 <6.97 <10.1 <11 <8.41 <9.15 Ra-226* 71.56+/-20.36 193.8+/-20.99 144.5+/-28.04 102.3+/-27.89 94.14+/-21.15 44.03+/-22.35 Ac/Th-228* <3.31 6.97+/-3.24 <6.78 <5.18 9.79+/-3.09 <4.43

1. 10 DISCHARGE CANAL (MIXING ZONE)

~aincide l ana Fena March 0 A il -gMa 'June Be-7* <12.23 <6.78 <14.44 <14.87 <9.04 <11.1 K-40* 387.3+/-18.61 287.7+/-8.93 192.6+/-17.87 206.3+/-23.86 286.8+/-11.57 124.1+/-14.01 Mn-54 <1.21 <0.73 <1.45 <1.53 <0.9 <1.05 Co-58 <1.39 <0.81 <1.54 <1.98 <1.09 <1.48 Fe-9 <4.17 <2.17 <4.15 <4.99 <2.87 <3.55 Co-60 <1.34 <0.66 <1.3 <2 <0.89 <1.24 Zn-65 <1.9 <0.91 <2.82 <4.48 <1.09 <2.69 Zr-95 <2.29 <1.42 <2.62 <3.68 <1.95 <2.03 Nb-95 <1.7 <0.99 <2.02 <2.96 <1.3 <1.77 Ru-103 <1.01 <1.03 <1.98 <2.5 <1.35 <1.82 Ru-106 <12.85 <7.38 <12.42 <17.3 <9.6 <13.24 1-131 <6.96 <3.31 <6.08 <7.85 <4.11 <5.38 Cs-134 <0.88 <0.48 <1.43 <1.57 <0.61 <0.8 Cs-137 <1.25 <0.66 <1.36 <1.7 <0.91 <1.09 Ba/La-140 <5.42 <1.93 <5.22 <7.16 <2.69 <4.29 Ce-141 <3.02 <1.82 <3.24 <3.26 <2.38 <2.33 Ce-144 <8.40 <5.86 <10.4 <7.68 <7.6 <7.15 Ra.226* 85.02+/-22.28 86.43+/-12.8 75.17+/-27.49 188.7+/-27.37 74.66+/-15.88 122.8+/-19.28 AclTh-228* 10.16+/-3.36 11.62+/-1.85 <4.41 9.25+/-4.38 15.81+/-2.65 <4.21

• Indicates naturally occurring. B-23

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

TABLE B-9 CONCENTRATIONS OF GAMMA EMMITERS IN HUDSON RIVER WATER SAMPLES** - 2005 (pCi/L +/- 1 SIGMA)

1. 9 PLANT INLET (HUDSON RIVER INTAKE)

= _,_,.j N ovmbe Decembe

- ,_2,^_

S eMbr Ob 7,. . O.!.m..,6...,iX ii ..ga, E

<.8...7....

_.....z.

A _ s

. -W.../

Be-7* <12.75 <13.74 1 <14.19 <14.64 1 <11.-49 K-40* 390.6+/-18.6 171.2+/-16.08 234.1+/-19.65 162.7+/-16.18 135.7+/-15.56 361.5+/-14.63 Mn-54 <1.36 <1.34 <1.49 <1.4 <1.4 <1.14 Co-58 <1.44 <1.45 <1.55 <1.64 <1.79 <1.21 Fe-59 <4.52 <4.15 <5.42 <4.5 <4.37 <3.48 Co-60 <1.36 <1.36 <1.64 <1.49 <1.41 <1.04 Zn-65 <3.05 <3.01 <3.5 <1.82 <3.43 <2.75 Zr-95 <2.37 <2.45 <2.82 <2.52 <2.49 <2.26 Nb-95 <1.59 <1.81 <2.17 <1.82 <2.08 <1.5 Ru-103 <1.93 <2.06 <2.04 <2.04 <1.99 <1.69 Ru-106 <13.46 <14.17 <15.3 <15.54 <15.95 <10.12 1-131 <6 <5.74 <7.08 <6.14 <6.95 <5.52 Cs-134 <0.92 <1.63 <1.49 <1.66 <1.51 <0.71 Cs-137 <1.22 <1.3 <1.31 <1.49 <1.51 <0.99 Ba/La-140 <4.3 <4.37 <5.78 <4.56 <5.87 <3.95 Ce-141 <2.88 <2.88 <3.06 <3.57 <2.49 <2.65 Ce-144 <8.67 <9.21 <92.1 <11.2 <10.9 <7.68 Ra-226* 102+/-21.26 77.01+/-21.87 81.91+/-22.64 41.53+/-24.28 61.56+/-22.49 114.5+/-16.9 Ac/Th-228* 16.59+/-3.57 <5.1 8.31+/-3.78 15.65+/-4.23 <5.16 10.13+/-3.01

1. 10 DISCHARGE CANAL (MIXING ZONE)

Radionuclide Jl August ut Se tmer.8 -. October November Decembef r Be-^7 <14.6 <8.94 <14.63 <12.48 <12.43 <10.67 K.40* 252.4+/-20.37 122.8+/-11.26 230.7+/-18.67 197.7+/-17.12 105.1+/-14.03 149+/-10.99 Mn-54 <1.48 <0.95 <1.54 <1.33 <1.08 <0.97 Co-58 <1.83 <1.17 <1.36 <1.39 <1.47 <1.27 Fe-59 <5.97 <3.24 <4.8 <4.08 <4.12 <3.03 Co-60 <1.86 <1.05 <1.46 <1.34 <1.17 <0.98 Zn-65 <2.35 <2.18 <3.34 <1.88 <3.09 <2.58 Zr-95 <3.21 <2.19 <2.93 <2.66 <2.46 <1.87 Nb-95 <2.35 <1.45 <1.85 <2.04 <1.67 <1.57 Ru-103 <2.07 <1.59 <2.16 <1.98 <1.69 <1.52 Ru-106 <13.83 <10.18 <16.38 <12.26 <13.93 <10.43 1-131 <7.11 <6.41 <6.31 <5.63 <5.72 <5.13 Cs-134 <1.33 <0.89 <1.8 <1.38 <1.27 <0.77 Cs-137 <1.37 <0.82 <1.27 <1.18 <1.24 <0.98 Ba/La-140 <5.58 <3.6 <4.57 <3.59 <4.55 <3.87 Ce-141 <2.92 <2.05 <3.61 <3.17 <2.86 <2.64 Ce-144 <8.69 <5.82 <10.8 <9.38 <7.69 <7.73 Ra-226* 130.1+/-22.7 124+/-16.84 83.18+/-25.47 <33.15 126.6+/-24.65 _- 66.94+/-16.1 AcITh 228* I 10.17+/-4.11 <3.47 j <4.49 [ <4.25 _ _

a 5.4Ri2.47

• Indicates naturally occurring. B-24

'Less than' values expressed as Critical Level (L.

TABLE B-10 CONCENTRATION OF TRITIUM IN HUDSON RIVER WATER SAMPLES*- 2005 (QUARTERLY COMPOSITES)

(pCi/L i 1 sigma)

1. 9 PLANT INLET (HUDSON RIVER INTAKE)

(Control Location)

I Rdioudlde STQuer N1Qart iterLR1VatrIT Quatr I TRITIUM 2004 l <413 <c424 l <421 <471

1. 10 DISCHARGE CANAL (MIXING ZONE)

TRITIUM 2004 l 618 +/- 130 l <424 I <421 c471

• "Less than" values expressed as Critical Level (L). B-25

TABLE B-1 I GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2005 INDIAN POINT

SUMMARY

SHEET SAMPLE TYPE: Drinking Water REPORTING UNITS IN: pCIIL +/- 1 sigma MONTH I YEAR: JANUARY 2005

. -. CAM..P FIE.LD. NEW CROTN M £US-

.. 5TH STREET.

ISOTOPE  ; M;N E; ;E;lES J E.WL Gross BetaH LLD = 4.0 l2.452 +/-f0.449 l 3.306 +/- 0.47 6.5 ;.8 .1 .0 Be-7 ll <28.52 l <14.2 7 <28.33 l <26.83 K-40 ll216.1+/-40.33 l 142.8+/-f25.94 7160.8+/-29.99 l412.4+/-46.1 Mn-54 l (7.5*) <3.27 l <1.87 T <2.94 <3.68 7 Co-58B (7.5*) <3 <2.05 <3.33 <3.84 Fe-59 l (15*) l <6.3 l <6.08 l <7.17 l <9.97 7 Co-60 T (7.5*) <3.43 T <2.29 T <2.73 <2.92 1 Zn-65 T (15*) <7.76 T <5.35 T <3.88 <6.54 7 Zr-95 T (7.5*) <5.46 T <4.71 T <5.59 <6.47 7 Nb-95 (7-5*) <2.78 l <2.43 T <2.38 l <2.47 7 Ru-I103 T1 <2.43 l <2.86 T <3.38 l <3.7 1 RU-106 T1 <34.48 l <24.74 T <30.55 l <40.39 1 1-131 (0.5*) <0.19 <.183 <.212 <.262 Cs-I134 (7.5*) <3.35 <2.61 <3.63 <2.7 Cs-137 (9.0*) <3.14 <2.11 <2.07 <4.08 Ba/La-140 (7.5*) <2.17 <4.01 <4.1 <4.41 Ce-I141 <4.38 <3.62 <6.01 <6.43 Ce-144 <19.2 <15.9 <26.5 <27.2 l Ra-226 175.1 *51.58 <47.48 <92.14 <78.06 Ac-228 _______ <9.93 <8.82 <13.09 <12.05 Results reported as < are CL values JAF Environmental Laboratory B-26 4/13/2006

TABLE B-1I GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2005 INDIAN POINT

SUMMARY

SHEET SAMPLE TYPE: Drinking Water REPORTING UNITS IN: pCilL +/- 1 sigma FEBRUARY 2005 J E iELDWNEWC N TH S

_________I_ _____;: :g0 CAMPQ

________I- CL*

I'.'SOTOPE;; MI.RQ E.RES. RES. WL Gross Beta LLD = 4.0 2.71 +/- 0.48 3.09 i 0.49 2.23 +/- 0.46 7.88 +/- 0.63 Be-7 <26.66 <19.47 <17.29 <19.77 K-40 193+/-36.6 183.3+/-31.4 154+/-26.98 <25.28 Mn-54 (7.5*) <2.75 <2.5 <2.17 <2.62 Co-58 (7.5*) <2.98 <2.7 <2.28 <2.5 Fe-59 (15*) <8.9 <5.46 <3.83 <6.31 Co-60 (7.5*) <3.83 <1.66 <2.02 <3.05 Zn-65 (15*) <8.13 <3.52 <4.39 <2.43 Zr-95 (7.5*) <3.98 <3.76 <4.6 <4.16 Nb-95 (7.5*) <2.66 <2.29 <2.68 <2 Ru-103 <3.1 <2.62 <2.6 <2.64 Ru-106 <27.13 <18.51 <27.08 <21.07 1-131 (0.5*) <0.76 <0.71 <0.64 <0.77 Cs-134 (7.5*) <3.19 <2.37 <2.48 <2.62 Cs-137 (9.0*) <2.64 <2.06 <2.32 <2.77 BalLa-140 (7.5*) <2.65 <2.73 <2.04 <3.42 Ce-141 <4.98 <3.66 <3.69 <4.23 Ce-144 <16.90 <15.90 <16.80 <18.20 Ra-226 129.6+/-54.52 <53.83 125.8+/-45.72 <62.35 Ac-228 <11.64 <6.66 <10.56 <10.04 H-3 R Results reported as care CIL values ill

,- Thrift 10"

.,., t1d"

" 1 -

't6:;' - v Om me,i - -, " N-MKRMI 0 18 JM rf

,I tl p

0 W,

g:

Allow

"" " IWO: As w7M JAF Environmental Laboratory B-27 4/13/2006

TABLE B-11 GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2005 INDIAN POINT

SUMMARY

SHEET SAMPLE TYPE: Drinking Water REPORTING UNITS IN: PCI/L +/- 1 sigma March-05 ISOT

....... ': RE~

CAP FIED

........ ES jRES J NW Ei-.-.,.............

RT N 1

........ EE ACUS

RES .............

CE f.5TH STREETS'

'0WW- ' WLL

... , -gg0----

............. iE.-

l-

. ]

Gross Beta LLD = 4.0 1.18 i 0.40 . 2.62 0.51 2.40i 0.49 4.69 i 0.55 Be-7 _______ <30.24 <22.62 <32.58 <31.04 K-40 _______ <39.41 <39.08 414.5+/-56.59 260.2+/-41.09 Mn-54 (7.5*) <2.69 <3.79 <3.88 <3.69 Co-58 (7.5*) <2.82 <1.89 <4.33 <4.46 Fe-59 (15*) <8.05 <4.37 <10.66 <9.65 Co-60 (7.5*) <3.15 <1.64 <2.8 <3.84 Zn-65 (15*) <8.16 <5.22 <11.17 <4.17 Zr-95 (7.5*) <6.2 <3.24 <5.58 <6.64 Nb-95 (7.5*) <3.25 <3.45 <4.02 <3.33 Ru-103 <3.15 <4.42 <3.99 <4.05 Ru-106 <37.08 <27.65 <37.12 <40.3 1-131 (0.5*) <0.30 <0.30 <0.31 <0.36 Cs-134 (7.5*) <3.92 <3.19 <2.41 <2.93 Cs-137 (9.0*) <3.62 <1.61 <4.52 <3.46 Ba/La-140 (7.5*) <3.05 <6.11 <6.02 <2.59 Ce-141 <5.3 <4.33 <6.17 _7 <7.89C Ce-144 <19.10 <19.10 <28.80 <33.40 Ra-226 <76.37 105.5B60.65 <82.43 <101.7 Ac-228 <9.37

<10.5 <1.54 <4.34 <12.75 Results reported as < are CL values JAF Environmental Laboratory B-28 4/13/2006

TABLE B-1 GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2005 INDIAN POINT

SUMMARY

SHEET SAMPLE TYPE: Drinking Water REPORTING UNITS IN: pCiIL +/- 1 sigma Apr-05

. CA.P FIELD -NEW CROTN - -AM£US 5TH STREE

- I-SOOPE N. REQ. RES" - RES. - RE WELL Gross Beta LLD = 4.0 1.11 i 0.50 2.51 i 0.57 5.61 i 0.63 5.83 i 0.62 Be-7 _______ <30.35 <25.7 <33.6 <34.52 K-40 _______ 311.6i41.67 <34.83 163*39.31 486.4i57.53 Mn-54 (7.5*) <3.15 <3.53 <3.72 <4.75 l Co-58 (7.5*) <3.15 <2.98 <3.94 <4.89 l Fe-59 (15*) <8.26 <4.36 <8.62 <11.98 Co-60 (7.5*) <3.37 <3.26 <4.27 <5.14 l Zn-65 (15*) <8.43 <5.2 <4.37 <5.95 l Zr-95 (7.5*) <4.69 <3.95 <6.2 <5.77 l Nb-95 (7.5*) <3.36 <3.67 <2.09 <3.77 l Ru-103 <3.27 <3.82 <3.84 <4.82 Ru-106 <32.43 <29.78 <31.41 <39.36 1-131 (0.5*) <0.28 <0.22 <0.22 <0.20 Cs-134 (7.5*) <2.28 <3.73 <4.99 <3.18 Cs-I137 (9.0*) <2.5 <2.27 <4.08 <4.15 Ba/La-140 (7.5*) <2.98 <2.48 <4.86 <5.81 Ce-I141 <5.67 <5.38 <7.09 <7.3 Ce-I144 <26.20 <22.00 <29.30 <33.20 Ra-226 c80.2 <76.46 <116.6 159.7+/-81.12 Ac-228 <9.97 <16.29 <14.87 <16.21 H-3_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Results reported as < are CL values JAF Environmental Laboratory B-29 4/13/2006

TABLE B-1I GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2005 INDIAN POINT

SUMMARY

SHEET SAMPLE TYPE: Drinking Water REPORTING UNITS IN: PCI/L +/-t1 sigma May-05

. -NEW l P FIELD CRO N AMICUS 5T STREET w,:ISOTOPE.R.:: . RE:. RE. WLL Gross Beta LLD = 4.0 2.55 i 0.46 2.80 i 0.44 2.49 i 0.45 7.70 i 0.58 Be-7 <24.62 <20.89 <24.07 <30.27 K-40 _______ 264.4i39.15 222.9i29.82 347.2i57.4 189.9+/-36.57 Mn-54 (7.5*) <3.24 <2.39 <4.25 <3.16 Co-58 (7.5*) <3.43 <2.05 <3.79 <3.58 Fe-59 (15*) <7.04 <5.2 <7.81 <10.3 Co-60 (7.5*) <3.2 <2.35 <4.33 <3.95 Zn-65 (15*) <7.45 <6.59 <12.9 <3.51 Zr-95 (7.5*) <5.58 <4.72 <5.59 <6.49 Nb-95 (7.5*) <3.53 <2.94 <3.99 <2.45 Ru-I103 _______ <3.49 <2.43 <3.69 <3.45 Ru-106 _______ <30.13 <28.06 <32.86 <39.01 1-131 (0.5*) <0.28 <0.21 <0.23 <0.20 Cs-134 (7.5*) <2.51 <3.3 <5.18 <3.49 Cs-I137 (9.0*) <2.94 <3.09 <4.88 <3.93 BatLa-140 (7.5*) <4.93 <3.6 <3.03 <3.71 Ce-I141 _______ <5.62 <4.77 <6.88 <6.29 Ce-144=______ <26.30 <20.80 <29.00 <26.60 Ra-226 ______ 132.3i54.67 193.2i51.22 <87.28 <101.1 Ac-228 <10.84 <6.94 <13.71 <11.39 Results reported as care CL values. Bold numbers are LLD values.

JAF Environmental Laboratory B-30 4/13/2006

TABLE B-11 GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2005 INDIAN POINT

SUMMARY

SHEET SAMPLE TYPE: Drinkinq Water REPORTING UNITS IN: oCIIL +/- 1 sigma Jun-05 ISOTOPE MIN.

J CAMP FIELD RES I

NEW CRTNAICS RES J RES.

5HSTREE W..E lGross Beta LLD =4.0 2.8+/-04 .9+/-05 .7+/-04 .5+/-06 r Be-7 <27.67 l <19.11 l <23.61 l <29.96

<34.85 416.9i45.92

.K-40 262.7i39.8 257.7.38.23 Mn-54 (7.5') <4.66 <3.23 <3.46 <3.33 Co-58 (7.5') <3.28 <2.52 <3.17 <4.59 Fe-59 (15*) <8.52 <8.17 <7.01 <7.46 Co..60 (7.5') <3.26 <2.75 <2.82 <3.52 Zn-65 (15*) <8.51 <9.32 <5.9 <3.87 l Zr-95 (7.5') <5.11 <5.51 <5.48 <5.57 l l Nb-95 (7.5*) <3.68 <2.9 <3.91 <2.58 l l Ru-I103 <4.07 <2.84 <3.75 <3.49 l Ru-I106 <29.82 <37.43 <27.87 <33.78 1-131 (0.5') <0.50 <0.46 <0.40 <0.45 Cs-I134 (7.5') <3.56 <3.48 <1.99 <2.35 Cs-I137 (9.0*) <2.54 <3.39 <2.5 <3.38 lBa/La-140 (7.5*) <4.99 <2.96 <4.9 <4.23 l Ce-141 _______ <4.83 <4.83 <6.34 <7.31 l Ce-144 .. <20.60 <19.80 <24.00 <31.10..

l Ra-226 _______ <84.06 134.4i51.28 <82.87 <95.72 Ac-228 _______ <15.61 <10.71 <10.01 <13.41 Results reported as < are CL values JAF Environmental Laboratory B-31 4/13/2006

TABLE B-11 GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2005 INDIAN POINT

SUMMARY

SHEET SAMPLE TYPE: Drinking Water REPORTING UNITS IN: pCUIL i 1 sigma Jul-05 J...........1--.-

C..P FIELDI  :::NEW: CROTON AICUS f 5TH STREET

-: ISOTOPE MIN.REQ. RES.,... - RES. WELL

X' ....... .......................

Gross Beta LLD = 4.0 2.57 +/- 0.54 2.53 i 0.52 7.10 i 0.65 6.99 +/- 0.64 Be-7 <26.14 <20.66 <28.47 <22.63 K-40 181.9+/-44.43 137.3+/-28.96 191.3+/-33.97 155.3+/-31.99 Mn-54 (7.5*) <3.73 <2.74 <2.98 <3.16 Co-58 (7.5') <1.99 <2.12 <3.04 <2.84 Fe-59 (15*) <8.95 <6.56 <6.51 <9.02 Co-60 (7.5') <2.91 <2.82 <4.07 <3.28 Zn-65 (15*) <5.63 <4.79 <4.35 <3.7 Zr-95 (7.5*) <4.78 <5.39 <4.66 <4.58 Nb-95 (7.5*) <1.93 <2.75 <1.84 <2.29 Ru-103 <3.61 <2.93 <3.53 <2.71 Ru-106 <37.23 <24.48 <31.18 <23.31 1-131 (0.5*) <0.67 <0.60 <0.41 <0.36 Cs-I34 (7.5*) <2.7 <3.02 <3.55 <2.99 Cs-1 37 (9.0*) <2.74 <2.87 <3.34 <3.27 Ba/La-140 (7.5*) <3.68 <3.29 <3.01 <3.73 Ce-141 <5.45 <4.2 <5.63 <4.8 Ce-144 <20.90 <17.80 <23.40 <21.90 Ra-226 110.6+/-62.23 93.67+/-46.92 <94.11 <71.86 Ac-228 <11.14 <8.31 <11.92 <13.57 Results reported as < are CL values JAF Environmental Laboratory B-32 4/13/2006

TABLE B-11 GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2005 INDIAN POINT

SUMMARY

SHEET SAMPLE TYPE: Drinkinq Water REPORTING UNITS IN: PCiIL +/- 1 sigma Aug-05

......-..... . i -CAMP FIELD: --:-:NEW CRO.TON:- - AMICUS -. :--5TH.:STREET ISOTOPE N Q. RE . . .RES.

Gross Beta LLD = 4.0 2.99 +/- 0.53 1.58+/-i 0.47 2.42 i 0.50 7.34 i 0.64 Be-7 <18.02 <18.58 <17.17 <25.95 K-40 140.6+/-27.63 262.5+/-35.81 <19.58 386.9+/-46.51 Mn-54 (7.5*) <2.24 <2.15 <2.32 <3.56 Co-58 (7.5*) <2.55 <2.73 <1.34 <3.22 Fe-59 (15*) <6.97 <3.99 <7.26 <9.04 Co-6O (7.5*) <2.44 <2.79 <3.06 <3.88 Zn-65 (15*) <5.05 <5.26 <4.77 <5.17 Zr-95 (7.5*) <4.35 <5.78 <4.13 <5.9 Nb-95 (7.5*) <2.75 <2.66 <2.16 <4.09 Ru-I103 _______ <2.54 <2.5 <2.67 <3.25 Ru-106 <26.55 <27.58 <18.75 <30.06 1-131 (0.5*) <0.232 <0.227 <0.214 <0.205 Cs-134 (7.5*) <1.78 <2.11 <2.39 <2.43 Cs-137 (9.0*) <2.61 <2.93 <2.21 <4.01 Ba/La-140 (7.5*) <3.74 <3.89 <3.52 <4.88 Ce-141 _______ <3.71 <3.9 <3.15 <5.87 Ce-144 _ <1.08 c____ <0.962 <0.872 <0.684 Ra-226 _______ <59.75 <57.5 151+/-i40.92 <83.73 Ac-228 <7.29 <10.24 <8.52 <11.9 Results reported as < are CL values JAF Environmental Laboratory B-33 4/13/2006

TABLE B-1I GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2005 INDIAN POINT

SUMMARY

SHEET 1S SAMPLE TYPE: Drinking Water REPORTING UNITS IN: g)Ci/L i: I sigma Sep-05

[. 1

[... CA...PFIELD -EW CROTON

-1l AMICUS 5THSTREET-S MiN REQ. RES RES:. RES WE Gross Beta LLD = 4.0 3.06 i 0.45 2.40 i 0.44 3.97 +/- 0.48 Sample not Be-7 <32.19 <19.26 <29.02 available. See 3eviation d Table B-K-40 145.1+/-50.42 <38.46 365+/-56.38 Ic Mn-54 (7.5*) <3.39 <3.36 <3.74 Co-58 (7.5*) <3.38 <2.79 <3.61 Fe-59 (15*) <8.14 <6.08 <6.28 Co-60 (7.5*) <3.5 <1.97 <4.26 Zn-65 (15*) <7.83 <6.63 <9.32 Zr-95 (7.5*) <4.7 <5.51 <6.07 Nb-95 (7.5*) <4.02 <3.62 <3.24 Ru-103 <4.04 <3.3 <3.4 Ru-106 <30.72 <27.21 <41.75 1-131 (0.5*) <0.19 <0.20 <0.19 Cs-134 (7.5*) <4.08 <2.35 <2.27 Cs-137 (9.0*) <4.2 <2.5 <3.65 BaILa-140 (7.5*) <3.62 <4.23 <5.4 Ce-141 <6.25 <4.08 <5.83 Ce-144 <23.20 <16.50 <23.90 Ra-226 <90.05 112.8+/-48.97 <76.57 Ac-228 <15.48 <6.56 <11.4 l rH-3 Results reported as < are CL values JAF Environmental Laboratory B-34 4/13/2006

TABLE B-11 GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES -- 2005 INDIAN POINT

SUMMARY

SHEET SAMPLE TYPE: Drinking Water REPORTING UNITS IN: pCIIL +/-1 sigma Oct-05 0 - CAM P FIELD N CROTN AMICUS 5T STREET

..isoOPE M-.E...E. .S W Gross Beta LLD = 4.0 3.54 i 0.48 2.18 i 0.42 9.94 i 0.66 8.78 i 0.66 Be-7 _______ <22.36 <22.01 <31.19 <37.63 K-40 _______ 196.7i45.27 189.7+/-32.09 115.8i32.55 128.9+/-36.69 Mn-54 (7.5*) <3.53 <2.67 <3.72 <3.27 l Co-58 (7.5*) <4.17 <2.6 <4.11 <3.53 l Fe-59 (15*) <9.17 <6.96 <8.9 <8.03 Co-60 (7.5*) <4.24 <2.86 <3.62 <3.45 Zn-65 (15*) <8.06 <5.67 <5.71 <5.51 Zr-95 (7.5*) <3.88 <4.18 <5.6 <6.6 Nb-95 (7.5*) <4.07 c2.66 <2.54 <2.37 Ru-103 _______ <3.55 <3.17 <3.68 <3.6 Ru-106 _______ <34.65 <28.39 <31.84 <37.4 1-131 (0.5*) <0.31 <0.29 <0.29 <0.31 Cs-I134 (7.5*) <4.33 <3.2 <2.37 <2.97 Cs-I137 (9.0*) <3.24 <2.37 <3.78 <4.4 BalLa-140 (7.5*) <4.02 <2.76 <3.75 <4.07 Ce-I141 _______ <5.76 <4.57 <7.31 <6.44 Ce-144 _______ <18.90 <16.50 <30.80 <26.00 Ra-226 _______ <76.38 <54.17 <102.5 <89.44 Ac-228 ___ ___ <12.95 <9.96 <12.41 <11.94 H-3 ______NA NA NA <431 Results reported as < are CL values JAF Environmental Laboratory B-35 4/13/2006

TABLE B-1I GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2005 INDIAN POINT

SUMMARY

SHEET SAMPLE TYPE: Drinking Water REPORTING UNITS IN: pCI/L +/- 1 sigma MONTH I YEAR: NOV 2005 fiSOTOPE NRERRSE 1.........

CAP:ED NWCOO MCS 5HSTREET.::

WELL Gross Beta LLD = 4.0 2.37 i 0.45 2.36 i 0.44 2.97 i 0.46 9.81 i 0.66 Be-7 <26.18 <19.87 <19.69 <22.3 K-40 182.6+/-34.16 146.4+/-30.21 128.6+/-26.46 93+/-25.12 Mn-54 (7.5*) <3.22 <2.19 <2.58 <2.8 Co-58 (7.5*) <2.83 <2.28 <2.31 <2.66 Fe-59 (15*) <6.39 <7.79 <5.89 <5.36 Co-60 (7.5*) <2.93 <3.04 <3.35 <3.19 Zn-65 (15*) <8.1 <4.92 <5.74 <3.24 Zr-95 (7.5*) <3.43 <4.76 <3.69 <4.53 Nb-95 (7.5*) <2.5 <2.42 <2.18 <1.73 Ru-103 <3.63 <3.31 <3.02 <2.83 Ru-106 <29.36 <29.65 <28.14 <27.03 1-131 (0.5*) <0.25 <0.22 <0.24 <0.23 Cs-134 (7.5*) <2.34 <2.42 <2.37 <1.73 Cs-137 (9.0*) <2.96 <2.91 <3.04 <3.01 Ba/La-140 (7.5*) <3.92 <3.08 <3.12 <4.08 Ce-141 <5.3 <4.47 <3.43 <5.64 Ce-144 <21.5 <18.3 <15.8 <23.2 Ra-226 <58.73 <63.96 147+/-45.26 <65.43 Ac-228 <10.89 <9.14 <9.02 <9.82 H-3 NA NA NA <476 Results reported as < are CL values JAF Environmental Laboratory B-36 4/13/2006

TABLE B-1I GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2005 INDIAN POINT

SUMMARY

SHEET SAMPLE TYPE: Drinking Water REPORTING UNITS IN: PCI/L +/- 1 sigma Dec-05

.. PFIELD CAM............ AM 5THTREET SNEWCROTN ISOTOPE -- MIN. REQ.-:E R .. WELL Gross Beta LLD = 4.0 2.09 i 0.51 3.25 +/- 0.55 2.17 i 0.52 8.29 i 0.72 Be-7 _______ <21.23 <21.47 <18.35 <26.04 K-40 _______ 153i30.32 130.9+/-27.35 <22.59 128.6i29.43 Mn-54 (7.5*) <3.23 <2.09 <1.59 <2.87 l Co-58 (7.5*) <2.28 <2.57 <2.41 <2.61 Fe-59 (15*) <5.01 <6.87 <6.61 <8.71 l Co-60 (7.5*) <3.86 <2.96 <2.99 <2.53 Zn-65 (15*) <7.58 <7.59 <6.18 <3.55 Zr-95 (7.5*) <3.75 <4.69 <3.85 <5.18 Nb-95 (7.5*) <3.07 <2.84 <2.8 <2.57 Ru-I103 _______ <3.01 <2.64 <2.95 <2.94 Ru-106 _______ <24.84 <31.19 <27.68 <30.23 1-131 (0.5*) <0.20 <0.21 <0.26 <0.19 Cs-134 (7.5*) <2.16 <4.3 <2.66 <2.76 Cs-I137 (9.0*) <2.67 <2.76 <3.01 <3.23 1 Ba/La-I140 (7.5*) <3.07 <3.94 <4.09 <2.99 Ce-I141 <4.54 <4.38 <4.22 7 <5.51 lCe-144 _______ <19.60 <19.00 <16.90 <22.40 r Ac-228 Ra-226 90.8i44.14

<9.81

<58.05

<8.41

<58.91

<8.98

<68.39

<9.03 l

l H-3 NA NA NA NA Results reported as < are CL values JAF Environmental Laboratory B-37 4/13/2006

TABLE B-12 CONCENTRATION OF TRITIUM IN DRINKING WATER SAMPLES*- 2005 (QUARTERLY COMPOSITES)

(pCi/L i I sigma)

• Nu TRITIUM <421 <409 <406 <464 VWM4 2D %~fer RDQItrF7iS~~rer ofutot TRITIUM <421 <409 <406 l <464 TRITIUM [ ^42 . 2ND409 409 <464

[TRITIUM l <421 <409 <409 <464 l

• "Less than" values expressed as Critical Level (La). B-38

TABLE B-13 SHORELINE SOIL SAMPLES**-2005 (pCVKg ,dry +/- I sigma)

Jun-05 OFF LENTS I ANITOU [ WHITE COLD ISOTOPE MIN. REq. VERPLANK l COVE INLET r BEACH = SPRING

_ _ 5CL* IP-05-295 5 IP-05-297 IP-05-298 ' IP-05-296 IP-05-299; Be-7 <196.7 2613 +/- 508.3 <315.5 <204.1 <204.1 K-40 16110 +/- 781.7 8313 +/- 860.1 14800 +/- 863.7 10410 +/- 608.1 10410 +/- 608.1 Mn-54 <29.41 <46.07 <30.8 <18.73 <18.73 Co-58 <28.12 <57.66 <35.45 <25.84 <25.84 Fe-59 <107.3 <134.8 <76.79 <87.91 <87.91 Co-60 <35.01 <62.66 <25.85 <24.54 <24.54 Zn-65 <72.12 <103.6 <49.07 <69.98 <69.98 Zr-95 <59.27 <105.7 <57.08 <40.03 <40.03 Nb-95 <29.9 <57.7 <34.29 <24.74 <24.74 Ru-103 <25.64 <70.71 <32.41 <21.8 <21.8 Ru-106 <204.5 <680 <281 <226.8 <226.8 1-131 <62.22 <152.3 <74.22 <42.37 <42.37 Cs-134 (75S) <30.85 <67.54 <30.27 <13.66 <13.66 Cs-137 (90*) 149.5 +/- 23.1 ** <59.53 173.5 +/- 26.1 <20.58 <20.58 BaLa-140 <53 <158.4 <66.2 <50.93 <50.93 Ce-141 <39.12 <98.11 <58.07 <35.84 <35.84 Ce-144 <143.00 <306.00 <176.00 <124.00 <164.00 Ra-226 1166 +/- 394.6 4374 +/- 865.3 2398 +/- 629.8 638.4 +/- 348.6 638.4 +/- 348.6 AcTh-228 513.6 +/- 94.51 994.2 +/- 232.3 679.6 +/- 128.3 <71.64 <71.64 September-05 1 1 OFF LENTS MANITOU  : WHITE COLD ISOTOPE MIN. REQ. l VERPLANK COVE l INLET 5 BEACH SPRING

= l __CL* l IP-05-569 l IP-05.572 l IP-05-568 IP-05-571 l IP-05-570 Be-7 <191.1 <384.5 727.7 f 478.7 <122.2 <194.00 K-40 16000+/-725.3 12370+/-1183 13140+/-1248 9015+/-446.7 38700+/-936 Mn-54 <25.26 <30.19 <69.71 <15.19 <26.80 Co-58 <24.05 <39.63 <75.04 <16.65 <28.30 Fe-59 <77.7 <199.1 <197.2 <53.73 <94.30.

Co-60 <23.76 <60.29 <68.06 <13.85 <64.60 Zn-65 <34.53 <170.2 <216.6 <44.81 <47.80 Zr-95 <38.48 <103.3 <150.2 <26.39 <49.30 Nb-95 <31.58 <49.88 <89.46 <18.31 <31.30 Ru-103 <21.71 <52.65 <95.7 <15.5 <25.00 Ru-106 <157 <428.5 <692.4 <187.2 <274.00 1-131 <37.99 <103.9 <195.6 <26.3 <43.00 Cs-134 (75*) 1 <22.87 <50.4 <54.55 <19.67 <27.60 Cs-137 1(90*) 143.8 +/- 24.69 <34.96 <77.33 <13.85 36.3 +/- 17A BaLa-140 <39.45 <106.7 <219.4 <20.62 <59.80 Ce-141 <32.99 <62.03 <125.7 <27.64 1 <39.00 Ce-144 <127.00 <183.00 <407.00 <90.50 <145.00 Ra-226 640.1 +/-348.4 <716.7 5381+/- 1199 797.4 +/- 261 1180 +/- 386 AcTh-228l 614 +/- 80.01 730.8 +/- 171.6 1569 +/- 274.6 <52.15 427 87.1 Results reported as < are CL values

• Posted CL's correspond to LLD's listed In TS-5.104 (Rev.5)

• • Cs-137 Value represent average of two counts.

• Indicates naturally occurring.

'- Less than' values expressed as Critical Level (I.J Indicates the average of the positive sample results reported for samples with recounts performed. B-39

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2005 (pCi/Kg, wet +/- 1 sigma)

May June BO-7* 584.9i143.9 438.3i131.2 53i13 KZr- 71172480.5 47052460.6 8619+/-563.9 Mn-54 <17.45 <16.23 <16.32 Co-58 <12.37 <21.04 <17.12 Fe-59 <60.09 <50.63 <52.51 Co-60 <23.46 <16.61 <28.41 Zn-65 <46.87 c<43.12 <51.78 Zr4-5 <29.65 <22.65 <32.99 Nb495 <18.24 <22.55 <22.15 Ru-103 <13.82 <17.18 <14.53 Ru-106 <109.1 <204.1 <203.1 1-131 <15.8 <23.71 <18.59 Cs-134 <23.09 <21.55 <22.98 Cs-137 - <19.61 c 17.43 -CM 9 BalLa-140 <28.85 <25.6 < 19.41 Ce-141 <21.45 <22.1 <23.29 Ce-144 <78.8 &987 90.6 Ra-226* <282.9 <312.8 <300 Acrh-228* <68.75 <53.12 <77.03 July Aug Mado0esuMUL 0 CATAL  : a. x .:r§s<A s x 150~t4S*Ifm Al u A ;?

Be-7' 1189i157.8 747.2i89.32 506.1i81.53 7 _ RfI RiR .7 fl

_a I - _ . _ _

K.40* 7234i521.2 4945+/-292.6 3744+/-249.6 K 40' 6857i204.1 5816+/-200.2 3182+/-112.1 Mn-54 <12.17 <9.23 <9.61 Mn-54 <6.59 <6.1 <4.49 Co-58 <12.2 <11.18 <8.44 Co-58 <6.2 <6.5 <4.06 Fe-59 <19.45 <28.56 <21.03 Fe-59 <22.29 <20.44 <13.01 Co40 <18.44 <8.06 <6.89 Co-OD <6.81 <7.04 <4.93 Zn-65 <42.74 <26.4 <26.1 Zn-65 <17.78 <21.05 <10.29 Zr-95 '33.34 <15.78 <14.9 Zr45 <12.81 <9.9 <7.52 Nb-95 <18.44 <10.6 <11.5 Nb-95 <6.85 <6.32 <4.7 Ru-103 <16.79 <8.26 <8.43 Ru-103 <7.17 <5.32 <3.8 Ru-106 <173.4 <76 <86.02 Ru-106 <69.73 <44.17 <40.46 1-131 <18.97 <10.53 <11.13 1-131 <8.16 <7.16 <5.29 Cs-134 <20.2 <11.77 <9.81 Cs-134 <8.46 <4.88 <5.36 Cs-137 <16.17 <9.54 <8.32 Cs-137 <6.38 <5.37 <3.58 Ba/La-140 <11.25 <10.79 <7.53 BaLa-140 <8.55 <8.18 <4.86 Ce-141 <21.24 <11.39 <11.29 Ce-f41 <8.18 <5.83 <3.72 Ce-144 <77.3 <53.7 <46.7 Ce-14 <33.4 <26.1 <19.1 Ra-22t <329.9 <177.9 350.1+/-148.6 Ra-226' 333.5*100.7 322.7*75.45 349.7*65.13 AcrTh-228* <65.47 <34.08 <35.14 Ac/Th-228' 62+/-22.8 <26.86 <16.36

• Indicates naturally occurring.

• • Indicates control location.

'Less than' values expressed as Critical Level (I. B-40

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION** - 2005 (pCi/Kg, wet +/- I sigma)

September October

"D*'WI^^.vAtZ

_AU- X C E ROD n~rwwUnuqt~ 77+/-13 ?.7 15R/4GW+/-E1Q11 31u.IX4T Be- V979.4+/-125.6 3.4*71.37 789.7+/-147.9 Be-7 Be-T 27713' 2.7 _ 1504f171.1 391.3+/-94.11 K-40* 8960+/-447.9 7392+/-329.2 9684+/-595.8 K-40^ 8046f441 . 7100+/-527.3 6441+/-389.9 Mn-54 <17.81 '10.95 <19.53 Mn-54 <13.94 <14.25 <12.18 Co-58 <15.93 '11.82 <20 .39 Co-58 < 1.99 '18.08

< <12.65 Fe-59 <51.09 <28.78 <46.19 Fe-59 <42.22 <41.61 <34.59 Co-60 <15.44 <12.02 <20.9 Co-60 <13.98 <26.81 <11.95 Zn465 <37.14 <27.66 <44.59 Zn_65 <43.44 <51.66 <43.72 Zr-45 '22.17 <22.32 <32.2 Zr4_5 <22.05 <32.87 <24.22 Nb-45 <18.54 <11.77 <16.38 Nb495 <12.77 < 18.04 <1 1.96 Ru-103 <14.66 <10.55 <14.3 Ru-103 <13.91 <1 2.09 <10.3 Ru-106 <126.4 <114.7 <201 Ru-106 <146.3 <163.1 <133.7 1-131 <18.41 <13.07 <23.24 1-131 <16.67 <21.25 <15.64 Cs-134 <15.75 <9.9 <15.13 Cs-134 <16.94 <21.84 <9.85 Cs-137 <15.14 <8.74 <18.08 Cs-137 <15.2 <16.53 <15.2 BalLa-140 <20.93 <16.13 <31.81 Ba/La-140 <15.2 <20.83 <15.02 Ce-141 <15.2 <12.36 <23.62 Ce-141 <20.82 <21.36 <15.55 Ce-144 <62.40 <50.80 <84.70 Ce-144 <79.6 <91.3 <62.1 Ra-226* 388.8+/-176.8 296+/-147.2 <343.1 Ra-226' <274.7 <339 <240.4 Acrh-228' <57.18 <44.99 '85.91 AcTrh.228* <50.19 <70.11 <52.77

• Indicates naturally occurring.

• • Indicates control location.

• • • Less than values expressed as Critical Level (LC). B41

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2005 (pCi/Kg, wet +/- I sigma)

May June Be-7^ <67.19 886.8+/-113.6 526 +/- 88.5 .1 <1.4 K40* 5733+/-258.8 5583+/-348.1 9054+/-421.8 K-40* 5389+/-373.4 9602+/-351 Mn-54 <10.1 <10.68 <11.64 Mn-54 <12.39 <13.07 Co-58 <10.81 <14.19 0<11.93 Co-58 <15.12 - <10.29 Fe-59 <28.63 <37.97 <45.06 Fe-59 [ <34.69 '32.42 Co60 <9.91 <13.66 <14.09 Co-60 <12.92 <13.91 Zn-65 <22.74 <40.09 <29.81 Zn-65 Zr4a5 r.

<19.99 t < .

<24.42

<34.14

<18.69 Zr-45 <16.92 <17.06 <22.01 Nb-95 <10.85 <14.99 <12.15 Nb-95 <14.34 <11.95 <10.23 Ru-103 <9.55 <8.74 <10.81 Ru-103 <11.62 <14.11 <10.55 Ru-106 1 <103.9 <97.24 <130.9 Ru-106 <128.9 <136.3 <122 1-131 <11.53 <13.74 <13.35 1-131 <11.3 <14.44 <13.08 Cs-134 <7.26 <13.64 <17.28 Cs-134 <14.79 <17.26 <7.83 Cs-137 <8.55 <9.84 <13.24 Cs-137 <9.85 <11.82 <13.61 Ba/La-140 <11.05 <11.33 <11.89 Ba/La-140 <17.41 <13.96 <11.42 Ce-141 <12.57 <13.85 <14.26 Ce-141 <12.47 <17.05 <16.76 Ce-144 <59 <66 <70 Ce-144 <48.2 <65 <68.9 Ra-226 276.9+/-138.2 <192 <252 Ra-226 545.3+/-169.7 482.1+/-226.2 <222.7 AcwTh-228* <41.02 <40.4 <50.11 AcITh-228* <43.44 <53.66 <44.56 July Aug Be-7' 280.3+/-124.5 278.9+/-75.85 534+/-109.1 Be-7 1087+/-75.54 1344+/-61.27 1320+/-74.02 K.40* 7706+/-570.8 3279+/-239.2 4600+/-334.6 K-40 8356+/-245 3154+/-122.9 8202+/-250.8 Mn-54 <14.6 <8.57 <15.41 Mn454 <6.42 0 <.45 <7.1 9 Co-58 <18.33 <9.45 <12.71 Co-58 <10.01 <4.96 <8.7 Fe-59 <70.15 <25.38 <50.04 Fe-59 <26.43 <14.82 <28.82 Co-60 <24.68 <10.16 <14.75 Co-60 <9.96 <5.22 _<8.92 Zn-65 <70.91 <12.03 <28.65 Zn-65 <23.25 l <12.13 l <24.85 Zr-95 <28.9 <19.99 <24.15 Zr495 <15.25 l <8.92 <13.01 Nb-95 <10.8 <13.54 <15.8 Nb-95 <8.76 <6.04 <8.98 Ru-103 <16.21 <9.98 <13.96 Ru-103 <8.48 <5.13 <6.23 Ru-106 <137.1 <91.42 <125.5 Ru-106 <76.46 <50.87 <71.89 1-131 <16.6 <10.49 <9.43 1-131 <11.27 <8.97 <10.76 Cs4134 <14.14 <10.03 <15.73 Cs-134 <9.57 <6.78 '5.79 Cs-137 <15.86 <9.84 <14.52 Cs-137 <7.79 <4.9 <6.25 BaILa-140 <30.79 <13.58 <17.87 Ba/La-140 <10.9 <7.2 '<11.4 Ce-141 <18.61 <11.12 <16.87 Ce-141 '11.44 <7.35 <7.37 Ce-144 <61 <40.9 <72.8 Ce-144 <41.3 <26.9 <29.4 Ra-226* <308.8 300.3+/-121.3 <260.6 Ra-226* <146 179+/-73.65 292.4+/-82.38 Ac/Th-228 <66.13 <36.46 <56.48 Ac/Th-228* <28.03 <19.9 <32.56

• Indicates naturally occurring.

• - Indicates control location.

Less than' values expressed as Critical Level (L.). B-42

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION* - 2005 (pCi/Kg, wet +/- 1 sigma)

September October 4chi4~OW ~IIWAGM, _

Be-7* 1147+/-134 1463+/-152 247.8+/-64.54 BeG-7 1489+/-172.5 969.6+/-127.3 <106.3 K40- 6686+/-407.4 5813+/-392.8 4734+/-280.7 K.40 7786+/-487.5 3873+/-344.3 6275+/-494.3 Mn-54 <12.49 <14.01 <8.55 Mn-54 <17.59 <13 <13.17 Co-58 <17.08 <15.71 <10.1 Co-58 <17.41 <14.06 <16.28 Fe-59 <38.03 <36.5 <19.42 Fe-59 <65.24 <41.45 <50.84 Co-60 <18.05 <16.57 <12.49 Co-60 <21.84 <16.19 <14.58 Zn-65 <39.55 <52.64 <33.64 Zn-65 <62.51 <38.57 <60.2 Zr-45 <21.32 <29.29 <11.27 Zr-95 <37.68 <18.04 <35.24 Nb-95 <15 <20.98 <7.35 Nb-95 <22.09 <11.4 <15.64 Ru-103 <12.38 <15.36 <8.15 Ru-103 <17.96 <13.59 <13.9 Ru-106 <163.1 <156.2 <77.67 Ru-1O6 <155.4 <151 <140.4 1-131 <15.14 <18.56 <9.04 1-131 <18.55 <10.29 <12.82 Cs-134 <16.55 <20.64 <6.47 Cs-134 <23.09 <19.3 <11.44 Cs-137 <16.48 <16.14 <7.91 Cs-137 <16.56 <14.18 <16.53 Ba/La-140 <16.89 <23.27 <13.65 Ba/La-140 <21.08 <13.67 <23.59 Ce-141 <19.16 <19.72 <9.23 Ce-141 <25.14 <15.47 <17.57 Ce-144 <85.20 <82.50 <33.40 Ce-144 <88.1 <85 <67 Ra-226' <330.2 <317.7 <134.6 Ra-226^ <314.7 <276.8 <244.9 AcIrh-228* <44.19 <45.87 <36.16 AcrTh-228* <79.94 <47.88 <55.84 I Indicates naturally occurring.

Indicates control location.

• • • 'Less than' values expressed as Critical Level (LC). B-43

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2005 (pCVKg, wet : 1 sigma)

May June Be-7* <111.4 318.5+/-74.71 344 +/- 178 Be-7* 354.3+/-116.1 277.4+/-84.05 242.4+/-90.25 K 4O* 4064+/-438.6 6831+/-335.1 5556+/-317.1 K-40t 7670+/-525.4 4424+/-325.9 4013+/-308.3 Mn-54 <13.99 <10.29 '10.52 Mn-44 <18.72 l 9.15 <13.69 1 Co-58 <9.48 <9.78 <11.13 Co-58 <17.14 <12.9 <13.27 Fe-59 <46.86 <30.83 <32.54 Fe-59 1 <66.03 l _<30.87 l <34 Co-60 <19.31 <10.27 <11.64 Co-60 <23.66 c16.25 <13.53 Zn45 <45.76 <26.45 <36.24 Zn4_5 _ <42.58 '33.26

< <32.79 Zr-95 <25.28 <14.59 <21.02 Zr-95 <31.54 <17.9 <25.88 Nb-45 c17.07 <10.52 <9.4 Nb-5O <14.97 <16.54 <12.78 Ru-103 <11.86 '7.99 <8.88 Ru-103 '<15.78 <9.17 <11.81 Ru-1O6 <193.4 <77.87 <100.3 Ru-106 <145.2 <115.1 <124 1-131 <14.52 <10.16 <9.88 1-131 <15.37 <14.15 <'15.71 Cs-134 <12.25 '<11.03 <7.85 Cs-134 <20.35 <13.49 <15.55 Cs-137 <12.23 <9.37 '11.72 Cs-137 <13.19 <10.32 <12.5 Ba/La-140 <20.15 <9.12 <16.78 BatLa-140 <17.63 <15.35 <12.12 Ce-141 '13.75 <9.5 '14.36 Ce-141 <19.87 <15.7 <15.66 Ce-144 64.2 <45 <61.7 Ce-144 <82.1 <71.5 <64.6 Ra-226' <236 <174.6 344.1+/-178.3 Ra-226' <278.7 <230.4 338.4+/-178.1 AcfTh-228* <41.91 <37.3 <43.25 AcrTh-228* <49.46 <50.46 <40.55 July Aug Be-7* 344.1+/-115.5 <100.2 <167.3 Se-7* 832.3+/-67.02 1306+/-83.37 282.6+/-43.47 K-401 7572+/-501.9 4734+/-350.5 5074+/-495.9 K-40* 5613+/-198.6 9779+/-278.6 3397+/-146.5 Mn-54 <19.21 <13.25 '18.35 Mn-S4 <7.75 <9.68 <4.78 Co-58 <17.13 <15.63 <15.43 Co-58 <8.23 <9.87 <4.57 Fe-59 <66.22 <44.68 <48.9 Fe-59 <23.86 <29.38 <19.05 Co4o <19.46 <10.53 <25.81 Cg460 <8.3 <11.49 <4.8 Zn-65 <48.1 <28.91 <36.71 Zn4S5 <18.8 <21.82 <13.65 Zr-95 <24.35 <20.08 <23.36 Zr495 k13.62 <17.67 <8.27 Nb-95 <12.98 <16.68 <25.8 Nb-45 <8.64 <9.88 <6.71 Ru-103 <16.12 <14.23 <18.47 Ru-103 <6.28 <8.41 <5.57 Ru-106 <194.3 <142.3 <193.9 Ru-106 <70.23 <77.58 <43.76 1-131 <18.43 <14.83 '18.67 1-431 <11.13 <12.85 <8.46 Cs-134 <13.5 <15.6 <21.92 Cs-134 <8.74 <10.48 <5.94 Cs-137 <13.9 <12.6 <17.62 Cs-137 <6.74 <8.54 0.63 BaILa-140 <13.14 <20.32 <23.49 Ba/La-140 <11.54 <12.51 <8.17 Ce-141 <20.62 <14.5 <23.79 Ce-141 <10.13 <9.78 <7.54 Ce-144 <87.9 <68.4 <79.6 Ce-144 <39.4 <36.8 <28.2 Ra-226* <323.5 <220.2 <321.1 Ra-226' 263.5+/-102.8 779.5+/-117.2 215.8+/-70.61 Acrrh-228' <71.99 <45.55 <78.18 AciTh-228* <24.46 1 <36.34 <21.7

• Indicates naturally occurring.

• t Indicates control location.

"*t

'Less than' values expressed as Critical Level (I. B-44

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION* - 2005 (pCUiKg, wet +/- I sigma)

Sept October Of Be-7*

Žiffii4 454.2+/-106.8 516.8+/-111.5 1244il46.2 Be.7*

_M 1216+/-156.2 489.5+/-113.1 492.8+/-125.6 K-40* 4451+/-380.6 6472+/-408.9 8363+/-480.9 KA40 9400+/-567.5 3810+/-351.1 3127+/-374.2 Mn-54 <15.08 '17.21 <19.26 Mn_54 <17.13 <16.64 <25.35 Co-58 <15.69 <15.02 <20.87 Co-58 <18.31 <14.26 <23.43 Fe-59 <48.17 <37.31 <43.13 Fe-59 <57.86 <51.01 <49.33 Co-60 <13.81 <19.15 <11.58 Co-60 <14.58 <19.39 <23.18 Zn65 '37.3 <41.85 <49.84 Zn-65 <39.99 <27.05 <27.22 Zr-95 <27.64 <27.43 <28.43 Zr-95 <31.69 <24.19 <30.63 Nb-95 <10.72 <13.4 <15.93 Nb-95 <16.82 <18.94 <24.49 Ru-103 <13.29 <16.23 <15.72 Ru-103 <16.49 <14.23 <14.53 Ru-106 <133.4 '157.6 '189.5 Ru-106 <195.1 <153.5 <177.8 1-131 <11.52 <21.59 <18.6 1-131 <14.28 <15.98 <17.8 Cs-134 <14.91 <23.24 <15.38 Cs-134 '7.8 <24.67 <25.77 Cs-137 <14.73 <15.95 <17.92 Cs-137 <17.83 '14.41 <18.83 BaILa-140 <21.93 <23.11 <22.69 Ba6La-140 <17.28 <11.17 <21.51 Ce-141 <18.36 <19.23 <21.82 Ce-141 <20.31 <21.34 <24.05 Ce-14 '76.20 <82.90 <102.00 Ce-144 <87.7 <99.8 <111 Ra-226* 287.2 <288.5 529.1 286.8 Ra-226* 573.2+/-252.7 <319 <387.9 AcrTh-228* <58.12 <62.7 <83.35 AcrTh-228* <60.63 <60.35 <74.15

• Indicates naturally occurring.

- Indicates control location.

• • • Less than' values expressed as Critical Level (L.). B-45

2005 TABLE B-15 CONCENTRATIONS OF GAMMA EMITTERS IN FISH AND INVERTEBRATE SAMPLES (pCi/Kg, wet i 1 sigma)

(control)

Radionuclide I" Fi 1:1 ITE PERCH Be-7 <212.8 <249.6 <240.1 K-40 4825i550.4 5672W417.3 4448+/-449.3 Mn-54 <24.22 <21.5 <20.59 Co-58 <10.06 <29.67 <25.57 Fe-59 <76.39 <103 <77.5 Co-60 <19.1 <22.82 <23.1 Zn-65 <72.21 <48.55 <31.15 Zr-95 <57.26 <50.92 <41.82 Nb-95 <33.18 <37.28 <25.24 Ru-103 <26.81 <33.72 <26.39 Ru-106 <268.2 <181.8 <174.9 1-131 <90.23 <423.6 <74.65 Cs-134 <27.97 <20.58 <22.62 Cs-137 <27.77 <16.72 <19.58 Ba/La-140 <60.64 < 189.6 <37.21 Ce-141 <45.13 <46.57 <35.58 Ce-144 <120 <116 <133 Ra-226 <428.2 <340.1 <455.7 Ac-228 <93.91 <71.44 <72.36 DATE 15-Jun-05 24-May-05 15-Jun-05 Radionuclide eERAE E BLCRAEL Be-7 <281 <173.2 <206.8 <202.4 K-40 4724+/-470.8 3666+/-298.6 3428+/-303 3025+/-411.4 Mn-54 <22.17 <16.45 <14.55 <19.86 Co-58 <27.61 <16.06 <23.58 <29.04 Fe-59 <92.64 <46.01 <67.94 <64.14 Co-60 <23.15 <15.41 <13.4 <24.23 Zn-65 <62.46 <34.63 <36.04 <67.2 Zr-95 <53.18 <26.79 <32.46 <65.63 Nb-95 <36.21 <21.94 <33.25 <49.88 Ru-103 <40.57 <22.16 <28.06 <38.45 Ru-106 <219.3 <146.9 <190.3 <210.6 1-131 <479.5 <155.5 <379.5 <427.4 Cs-134 <19.33 <13.02 <14.09 <19.49 Cs-137 <16.72 <18.18 <14.56 <13.66 Ba/La-140 <167.9 <55.31 <127.9 <201.5 Ce-141 <55.89 <33.85 <38.8 <36.99 Ce-144 <117 <79.6 <84.5 <82.2 Ra-226 645.5+/-321 <248.9 466.8+/-194.1 786.1+/-264.1 Ac-228 <101.9 <37.92 <68.96 <50.88 DATE 2-Aug-05 12-Aug-05 2-Aug-05 2-Aug-05

• Indicates naturally occurring. B46

2005 TABLE B-15 CONCENTRATIONS OF GAMMA EMITTERS IN FISH AND INVERTEBRATE SAMPLES (pCi/Kg, wet +/- I sigma)

(indicator)

Radionuclide C I AM Be-7 <204.1 <170.4 <147.4 K-40 3851+/-520.1 5303+/-473.8 3624+/-370.9 Mn-54 <22.52 <28.01 <22.6 Co-58 <21.95 <28.89 <19.32 Fe-59 <101.5 <64.12 <56.01 Co-60 <25.78 <24.93 <13.32 Zn-65 <47.87 <70.44 <40.87 Zr-95 <46.11 <40.83 <31.15 _

Nb-95 <26.72 <24.81 <27.7 Ru-103 <25.14 <24.54 <20.1 Ru-106 <295.1 <180.3 <227.4 1-131 <61.32 <63.8 <50.86 Cs-134 <23.87 <24.7 <19.5 Cs-137 <30.62 <32.08 <20.66 Ba/La-140 <51.6 <54.54 <30.21 Ce-141 <34.8 <32.37 <28.33 Ce-144 <123 <114 <88.3 Ra-226 <422.3 <422.2 808+/-281.7 Ac-228 <59.72 <61.8 <76.08 DATE 16-Jun-05 17-Jun-05 17-Jun-05 Radionuclide C . W T PRC .M ER Be-7 <136 <200.3 <195.7 <206.7 K-40 3397+/-273.6 6130+/-404.2 5005+/-467.1 3917i371.6 Mn-54 <11.98 <20.86 <19.66 <20.4 Co-58 <22.92 <25.79 <30.99 <22.98 Fe-59 <65.66 <86.85 <65.85 <63.58 Co-60 <13.31 <20.79 <29.79 <19.88 Zn-65 <33 <25.67 <56.69 <48.82 Zr-95 <29.88 <40.14 <52.15 <38.43 Nb-95 <21.04 <33.11 <28.61 <29.53 Ru-103 <21.54 <28.89 <35.68 <28.07 Ru-106 <161.9 <226.6 <276.3 <250.2 1-131 <242.5 <330 <222.2 <138.3 Cs-134 <15.24 <21.32 <16.46 <19.84 Cs-137 <15.65 <15.96 <20.84 <19.05 Ba/La-140 <119.2 <94.55 <186.6 <71.64 Ce-141 <32 <45.77 <53.36 <38.66 Ce-144 <40.6 <87.8 <117 <103 Ra-226 399.5+/-186.3 500.2+/-244.1 435.5+/-280.9 710.8+/-319.1 Ac-228 <42.62 <83.5 <93.48 <62.65 DATE 4-Aug-05 4-Aug-05 11 -Aug-05 17-Aug-05

• Indicates naturally occurring. B47

TABLE B-16 ANNUAL

SUMMARY

, NON-RECS SAMPLE RESULTS 2005 W~jM eMVX AQUATIC VEGETATION (pCikg - WET) Co-s0 NONE <La <La <La 0 5 <La <La <Lea <La 5 22.8 1-131 100 <La <La <ILa 0 5Is <Le <La <La <La 5 92 24.2 Cs-134 100 <La <La <La 10 5 <La <La <La <La 5 r.13l7 inn 17 17 17 ~1

~ 1 CI..

A~ 727 BU1 IUTM StUIMt:N I .,w ... ,,,Wa_ ,gc~s (pCigk - DRY) Co-60 NONE <La <LaC <La 0 6 <Lc <La <La <Lc 2 82 < L, Cs-134 150 <La Lac <La 0 6 <L <La <Lc <La 2 48.4 44.7 SOIL Cs-137 180 426 737 278 6 6 <La <La <La <La 2 489.4 107.9 (pCitkg - DRY) Co-60 NONE <La <La <La 0 2 Lac <La <La <La I < L. < L.

Cs-134 150 <La <La <La 0 2 <La <La <La <La I L. ' L, Cs-137 180 15 15 15 1 2 <Lc <La <La <L 1 129 88.6 PRECIPITATION (pCVL) H-3 2000 <La <La <La 0 3 <La <La <La 0 3 261 411 Co-80 15 <LC <L <La 0 4 <La <L <La 0 4 < L, Cs-134 15 LaC <La <C 0 4 <La <La <La 0 4 < L.

Cs-137 18 <La <La <La 0 4 <Lc <La <L 0 4 < L, < L.

SPECIAL WATER (pCVL) H-3 2000 <Le <La <La 0 i5 NA NA NA NA NA 213 NA Co-60 15 <Lc <La <La 0 37 NA NA NA NA NA <L, <L.

Cs-134 15 <La <La <La 0 37 NA NA NA NA NA < L, < L, Cs-137 18 <La <La <La 0 37 NA NA NA NA NA ' L, < L, Sr-90 NONE <La <La <La 0 4 NA NA NA NA NA NA NA

• Average of positive values for 1995 - 2004 Detected at conrol localion 1999, AND 2001.

NA . Data not available.

Lc - Crilcal Level, which is less than the required Lower Limit of Detection (LLD), unless otherwise noted.

B48

TABLE B-17 MILCH ANIMAL CENSUS 2004 THERE ARE NO ANIMALS PRODUCING MILK FOR HUMAN CONSUMPTION WITHIN FIVE MILES OF INDIAN POINT.

B-49

TABLE B-18 Table B-18 Land Use Census 2005 A comprehensive survey of the of the 5 mile (8 kilometer) area surrounding the Indian Point Site was conducted during the 2005 Spring, Summer and Fall months in accordance with the Indian ODCM 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 and summer and fall.

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

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

Results:

The 2005 land use census indicated there were new residences that were closer in proximity to IPEC.

NEM performed a complete nearest residence survey with updated distances. The new survey information is being updated in the ODCM. and is attached to this document.

No milch animals were observed during this reporting period within the 5-mile zone or listed in the New Vnrk Ainrit- llhiro Arnf C:"ictir. RCamroi B-50

TABLE B-18 INDIAN POINT ENERGY CENTER UNRESTRICTED AREA BOUNDARY AND NEAREST RESIDENCES 2005

- I. Y --- - F -- - U I - - -- --

sector, Compass Point Distance to site Distance to site Distance to Address of nearest resident, Dec Boundary from ; Boundary from nearest resident, 2004 Census Unit 2 Plant Vent Unit 3 Plant Vent from Unit I (In meters) ,(in meters) superheater in meters N RIVER RIVER 1788.1 41 River Road Tomkins Cove NNE RIVER RIVER 3111.3 Chateau Rive Apts. John St. Peekskill NE 550 636 1907.3 122 Lower South St. Peekskill ENE 600 775 1478.2 1018 Lower South St. Peekskill E 662 785 1370.9 1103 Lower South St. Peekskill ESE 569 622 715.2 461 Broadway Buchanan SE 553 564 1168.2 223 First St. Buchanan SSE 569 551 1239.7 5 Pheasants Run Buchanan S 700 566 1132.5 320 Broadway Verplanck SSW 755 480 1573.5 240 Eleventh St. Verplanck SW 544 350 3015.9 29 Church St. Tomkins Cove WSW RIVER RIVER 2169.6 9 West Shore Dr. Tomkins Cove W RIVER RIVER 1918.7 712 Rt. 9W Tomkins Cove WNW RIVER RIVER 1752.4 770 Rt. 9W Tomkins Cove NW RIVER RIVER 1692.7 807 Rt. 9W Tomkins Cove NNW RIVER RIVER 1609.3 4 River Rd. Tomkins Cove B-51

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 2005 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.

This bias can be seen in Table and Figure C-6 where the values reflected for 2004 are from a single sample of broadleaf vegetation that indicated Cs-1 37. Also in Table and Figure C-7 where the values reflected for the historical average are base upon the one positive sample of Cs-137 in fish and invertebrates in 1995.

C-1

TABLE C-1 DIRECT RADIATION ANNUAL

SUMMARY

N 1995 - 2005 1995 15.0 15.0 17.0 1996 14.0 14.0 16.0 1997 15.0 15.0 18.0 1998 14.0 15.0 16.0 1999 15.0 15.0 16.0 2000 14.0 15.0 16.0 2001 15.0 15.0 17.0 2002 15.0 15.0 14.0 2003 14.3 13.9 14.7 2004 13.0 13.0 14.0 2005 14.1 14.1 15.9 l 14.4 14.6 15.9 C-2

FIGURE C-1 DIRECT RADIATION 40.0 35.0 30.0 I-

• 25.0 a

E 20.0 E

E 15.0 10.0 5.0 0.0 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 C-3

TABLE C-2 RADIONUCLIDES IN AIR 1995 - 2005 (nCi/m 3 }

1995 0.01 0.01 < LK < LK 1996 0.01 0.01 < LK

<K 1997 0.01 0.01

<K <K 1998 0.02 0.01

<K 1999 0.02 0.01 <K

< Lc <K 2000 0.01 0.01 <L 2001 0.02 0.02 <E 2002 0.02 0.02 <

< L0 Lc < LC 2003 0.01 0.01 < L, < Lc 2004 0.01 0.01 < L, 2005 0.02 0.02 < Lc < Le 0.01 0.01 < Lc < Kl Critical Level (K) is less than the ODCM required LLD.

<c indicates no positive values above sample critical level.

C4

FIGURE C-2 RADIONUCLIDES IN AIR - GROSS BETA 1995 to 2005 0.05 MAII ODCM Indicator Locations El Control Location 0.04 0.03 0,

E 5

m.

0.02 0.01 I FvT

.n 0 - U -. U S I .1 * & .-.. a a a - - a .... ,.... a a a a aa a a 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005

• 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 1995 - 2005 (DCI/L) 1995 370 270 < Lc < Lc 1996 < L. 280 < Lc < Lc 1997 < Lc 430 ' Lc < Lc 1998 c Le 220 <k < Lc 1999 191 318 < Lc < Lc 2000 190 267 < Lc < Lc 2001 323 < Lc

< L4 < LC 2002 432 562 < Lc < Le 2003 < L, < L, < Lc < Le 2004 < L, 553 < Lc < Le 2005205< Le 618 < Le L.

5 296 i358 < Lc < Le Critical Level (Lj)is less than the ODCM required LLD.

<Lc indicates no positive values above sample critical level.

C-6

FIGURE C-3 HUDSON RIVER WATER - TRITIUM 1995 to 2005 2000 1800 1600 1400 1200

-E Z3 1000 800 600 400 200 0 .

1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 Tritium ODCM required LLD = 3000 pCi/L C-7

TABLE C-4 RADIONUCLIDES IN DRINKING WATER 1995 -2005 (pCilL) 1995 < Le < Le 1996 < Lc < LC 1997 < Lr < L, 1998 < Le <L 1999 < L, <L 2000 < L, <L 2001 < Lc <L 2002 < Lc <L 2003 < Le < Le 2004 < L'. < L" 2005 c L,

' Lc < L1 Critical Level (L,) is less than the ODCM required LLD.

<Lr indicates no positive values above sample critical level.

C-8

FIGURE C-4 DRINKING WATER - TRITIUM 1995 to 2005 2000 1800 - l Camp Field Reservior (H-3)

[3 New Croton Resevoir (H-3) 1600 -

1400 -

1200 -

-1 C. 1000 -

0.

NO IDENTIFIED TRITIUM IN PREVIOUS TEN YEAR HISTORY 800 -

600 -

400 -

200 -

0-1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 Tritium ODCM required LLD = 2000 pCi/L C-9

TABLE C-5 RADIONUCLIDES IN SHORELINE SOIL 1995 -2005 (pCi/Kg, dry) 1995 176 335 1996 173 453 1997 < Lc 203 340

' Lc 1998 143 1999 46 200 238 2000 58 179 231

' LC 2001 45 230 427 2002 ' Lc 221 238 2003 124 73 2004 104 138 2005 < L. 174 50 ' Lc 175 275 Critical Level (Lj)is less than the RETS required LLD.

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

C-10

FIGURE C-5 RADIONUCLIDES IN SHORELINE SOIL 1500 1400 1300 1200 1100 1000 900 M 800

- 700 600 500 400 300 200 100 0

1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 Cs-134 ODCM required LLD = 150 pCi/Kg, dry Cs-137 ODCM required LLD = 175 pCi/Kg, dry C-11

TABLE C-6 RADIONUCLIDES IN BROAD LEAF VEGETATION 1995 - 2005 (pCi/Kg, wet) 1995 28 < Lc 1996 17 < L, 1997 < Le < L, 1998 < Lc < Lc 1999 < Le 27 2000 28 < Lc 2001 7 < L1 2002 14 16 2003 14 < Lc 2004 10 < L, 2005 C L0 17 22 J Critical Level (Lj)is less than the ODCM required LLD.

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

C-12

FIGURE C-6 BROAD LEAF VEGETATION - Cs-137 1995 to 2005 100 l Indicator (Cs-1 37) 0 Control (Cs-1 37) 80 60 en 0.

40 20 I h

0 . . ..... ..... .

1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 ODCM required LLD = 80 pCi/Kg, wet C-13

TABLE C-7 RADIONUCLIDES IN FISH AND INVERTEBRATES 1995 16 < LC 1996 < Lc < LC 1997 < Lc < LC 1998 < Lc < LC 1999 < LC < LC 2000 <k < LC 2001 < LC < LC 2002 < Lc < Lc 2003 < L. < L, 2004 < Le < L, 2005 ' Le ( L.

16 L.

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

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

C-14

FIGURE C-7 FISH AND INVERTEBRATES - Cs-137 1995 to 2005 200 180 -

l Indicator (Cs-1 37) 0 Control (Cs-1 37) 160 -

140 -

120 -

4-a, 6 100 -

80 -

60 -

40 -

20 -

0 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 Cs-137 ODCM required LLD = 150 pCi/Kg, wet C-15

APPENDIX D INTERLABORATORY COMPARISON PROGRAM

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

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

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

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

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

The samples are prepared by NIST to present specific challenges to participating laboratories. For 2005, the two mixed gamma samples analyzed tested the ability of the JAF Environmental Laboratory to accurately account for coincidence summing from Cs-134. NIST supplies sample media as blind sample spikes. These samples are prepared and analyzed by the JAF Environmental Laboratory and the results are submitted to the Entergy Nuclear Northeast representative, who uses predetermined acceptance criteria methodology for evaluating the laboratory's performance. The performance results along with the NIST Report of Test (Certifies what activities are present in the sample) are forwarded to the laboratory.

D-1

D.2. PROGRAM SCHEDULE Table D-1 Water Gross Beta 1 Water Tritium 1 Water I-131 2 Water Mixed Gamma 3 Air Gross Beta 2 Air 1-131 2 Air Mixed Gamma 3 Milk I-131 2 Milk Mixed Gamma 2 Soil Mixed Gamma 1 Vegetation Mixed Gamma 1 TOTAL SAMPLE INVENTORY 20 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.

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 Using the appropriate row under the Error Resolution column in Table D-2 below, a corresponding Ratio of Agreement interval is given.

The value for the ratio is then calculated.

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

TARTU J)-7

<3 0.4-2.5 3.1 to 7.5 0.5-2.0 7.6 to 15.5 0.6-1.66 15.6 to 50.5 0.75-1.33 50.6 to 200 0.8-1.25

>200 0.85-1.18 This acceptance test is generally referred to as the "NRC" method. The acceptance criteria is contained in Procedure DVP-04.01 and was taken from the Criteria of Comparing Analytical Results (USNRC) and Bevington, P.R., Data Reduction and Error Analysis for the Physical Sciences, McGraw-Hill, New York, (1969). 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 nonconformity report when results are unacceptable.

D-3

D.3. PROGRAM RESULTS

SUMMARY

The Interlaboratory Comparison Program numerical results are provided on Table D-3,4 and 5.

ANALYTICS QA SAMPLES RESULTS Eighteen QA blind spike samples were analyzed as part ofAnalytics 2005 Interlaboratory Comparison Program. The following sample media were evaluated as part of the comparison program.

Air Charcoal Cartridge: I-131 Air Particulate Filter: Mixed Gamma Emitters, Gross Beta Water: I-13 1, 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 79 individual analyses on the eighteen QA samples. Of the 79 analyses performed, 79 were in agreement using the NRC acceptance criteria for a 100% agreement ratio.

There were no non-conformities in the 2005 program.

NIST QA SAMPLES RESULTS In 2005, 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 ofthe comparison program.

Air Particulate Filter: Mixed Gamma Emitters Water: Mixed Gamma Emitters The JAF Environmental Laboratory performed 10 individual analyses on the two QA samples. Of the 10 analyses performed, 10 were in agreement using the NRC acceptance criteria for a 100% agreement ratio.

There were no non-conformities in the 2005 program.

D-4

Table D-3 NUMERICAL RESULTS TABLES TABLE D-3 INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filters (pCfilter E-4583-05 AIR 142.4 + 1.8 pCi/filter GROSS 146.6 + 1.8 13E W. I 2.3 1.05 A BETA 145.2 + 1.8 Mean= 144.7 + 1.0 12/8/05 E-4824-05 AIR 202.8 +/- 3.0 pCi/filter GROSS 204.7 + 3.0 186.0 + 3.1 1.10 A nBETA 206.5 + 3.0

___I IJ Mean = 204.7 :: 1.71 (1) Results reported as activity 41 sigma.

(2) Results reported as activity 41 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

TABLE D4 INTERLABORATORY INTERCOMPARISON PROGRAM (1) Results reported as activity +1 sigma. Sample analyzed by JAF Environmental Laboratory (2) Results reported as activity +1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-5

TABLE D-5 INTERLABORATORY INTERCOMPARISON PROGRAM 3/17/05 E-4488-05 WATER 59.4 + 1.8 pCi/liter 63.3 + 2.4 I-131** 65.9 +/- 1.1 0.95 A 64.6 + 1.8 Mean= 62.4 + 1.1 6/9/05 E-4586-05 AIR 102.0 + 5.6 pCi/cc I-131 98.7 +/- 4.8 92.5 + 1.5 1.04 A Mean = 96.3 +/- 2.9 6/9/05 E-4584-05 MILK 80.4 + 2.2 pCi/liter 81.9 + 2.4 1-131** 813 + 2.7 86.9 + 1.5 0.93 A Mean= 81.2 + 1.4 9/15/05 E-4716-05 AIR 65.2 + 4.0 pCi/cc I-131 58.6 4.7 63.4 1.1 1.00 A 66.7 + 3.6 Mean= 63.5 + 2.4 9/15/05 E-4713-05 WATER 77.0 + 1.6 pCi/liter I-131** 78.0 + 2.0 78.2 +/- 1.3 0.98 A Mean = 76.9 +/- 1.1 9/15/05 E-4715-05 MILK 86.4 +/- 1.7 pCi/liter 90.6 1.9 I-131** 90.6 1.9 943 1.6 0.92 A

_ _ _ __ __ __ _ _ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ M ean =~ 87 .2 1 .0 _ _ _ _ _ _ _ _ _ _ _ _

(1) Results reported as activity =1 sigma.

(2) Results reported as activity 41 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(**) Result determined by Resin Extraction/Gamma Spectral Analysis.

(A) Evaluation Results, Acceptable.

D-6

TABLE D-5 (cont)

INTERLABORATORY INTERCOMPARISON PROGRAM w tt II = 11.14 pCi/liter 248.0 + 11.8 Ce-141 221 4 3.7 1.06 A 236.0 +/- 9.4 Mean= 235.3 + 6.3 278.0 + 53.9 Cr-51 295.0 X 48.7 322 + 5.4 0.86 A 262.0 38.5 Mean= 278.3 + 27.4 128.0 + 9.6 Cs-134 113.0 14.6 134 + 2.2 0.94 A 138.0 6.8 Mean = 126.3 + 6.2 112.0 b 8.0 Cs-137 121.0 7.9 125 + 2.1 0.97 A 130.0 6.3 Mean= 121.0 + 4.3 157.0 + 9.2 Mn-54 162.0 9.0 154 d 2.6 1.05 A 164.0 7.0 Mean= 161.0 + 4.9 106.0 + 10.0 Fe-59 114.0 + 9.6 107 4 1.8 1.07 A 122.0 7.1 Mean = 114.0 + 5.2 184.0 + 16.4 Zn-65 203.0 + 16.4 191 + 3.2 0.99 A 179.0 11.5 Mean= 188.7 + 8.6 136.0 + 6.6 Co-60 131.0 A 6.3 139 1 2.3 0.99 A 144.0 4 4.9

_____ ____ Mean= 137.0 +/- 3.5 _ _ _ _ _ _ _

117.0 + 8.2 120.0 + 8.0 Co-58 111 I 1.9 1.05 A 112.0 +/- 5.8 Mean= 116.3 +/- 4.3 (1) Results reported as activity +1 sigma.

(2) Results reported as activity <<lsigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-7

TABLE D-5 (cont)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analvriq Water (nCilliter) 292.0 4.4 pCi/liter 284.0 9.0 Ce-141 282 + 4.7 1.03 A 296.0 4.1 Mean= 290.7 3.6 395.0 + 18.2 Cr-51 3 4110 3816 408 4 6.8 0.98 A 397.0 16.2 Mean= 401.0 + 15.1 152.0 + 3.3 Cs-134 152.0 6.3 148 + 2.5 1.03 A 153.0 2.9 Mean = 152.3 + 2.6 234.0 3 3.7 Cs-137 235.0 7.2 235 + 3.9 0.99 A 231.0 3.5 Mean = 233.3 + 2.9 119.0 + 2.8 Mn-54 118.0 5.5 111 1.9 1.07 A 118.0 + 2.7 Mean= 118.3 + 2.3 74.7 + 3.1

( Fe-59 77.0 6.2 74 I 1.2 1.05 A 81.6 + 3.0 Mean= 77.8 + 2.5 158.0 + 5.3 160.0 11.0 Zn-65 149 fi- 2.5 1.08 A 163.0 +/- 5.2 Mean = 160.3 f 4.4 201.0 + 2.7 Co-60 202.0 +/- 2 202 4 3.4 0.99 A 198.0 :03 2.6

_____ _____ M ean = 200.3 +/- 2.2 _ _ _ _ _ _ _ _ _ _ _

71.6 2.5 81.0 4.6 Co-58 77 + 1.3 1.00 A 79.2 2.5

_________ I Mean = 77.3 1.9 (1) Results reported as activity d1 sigma.

(2) Results reported as activity +1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-8

TABLE D-5 (coat)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (nCi/filter)

FILTER 160.0 6.0 pCi/filter 151.0 5.4 Ce-141 155 + 2.6 1.01 A 160.0 4.8 Mean= 157.0 3.1 268.0 + 30.8 Cr-51 259.0 + 29.6 226 +/- 3.8 1.22 A 302.0 +/- 23.5 Mean = 276.3 +/- 16.3 107.0 +/- 7.0 Cs-134 94.5 + 7.1 93.9 + 1.6 1.08 A 102.0 + 5.4 Mean= 101.2 + 3.8 91.1 + 5.6 Cs-137 88.2 + 5.9 87.6 +/- 1.5 1.05 A 96.5 + 4.5 Mean= 91.9 + 3.1 115.0 +/- 6.6 Mn-54 116.0 +/- 7.1 108 +/- 1.8 1.10 A 126.0 + 5.5 Mean = 119.0 + 3.7 79.8 + 7.9 Fe-59 89.0 +/- 9.1 75.0 A 1.3 1.17 A 94.2 +/- 6.8 Mean = 87.7 + 4.6 150.0 + 12.5 Zn-65 162.0 + 14.1 134 + 2.2 1.15 A 151.0 + 10.0 Mean= 154.3 + 7.1 95.2 + 5.0 Co-60 106.0 + 5.6 97.1 + 1.6 1.02 A 96.6 + 4.0

_____ _____ M ean = 99.3 +/- 2.8 _ _ _ _ _ _ _ _ _ _ _

73.2 5.8 82.6 6.6 Co-58 77.8 i 1.3 1.01 A 80.1 4.9

a. a. I A Mean = 78.6 3.4 A (1) Results reported as activity +1 sigma.

(2) Results reported as activity +1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-9

TABLE D-5 (cont)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (nC1/literl FILTER 174.0 4.8 pCi/liter 173.0 4.8 Ce-141 187.0 5.8 165 +/- 2.8 1.07 A 170.0 4.4 Mean = 176.0 2.5 239.0 + 22.1 246.0 + 22.3 Cr-51 230.0 + 24.5 239 +/- 4.0 0.99 A 232.0 + 20.7 Mean = 236.8 + 11.2 90.4 + 5.2 93.2 + 5.2 Cs-134 110.0 +/- 6.6 86.3 + 1.4 1.10 A 84.7  : 4.9 Mean = 94.6 A 2.8 143.0 + 5.7 144.0 + 5.5 Cs-137 139.0 + 6.6 138 +/- 2.3 1.04 A 150.0 + 5.3 Mean = 144.0  : 2.9 75.0 +/- 4.4 65.4 +/- 4.4 Mn-54 82.9 + 5.6 65.0 + 1.1 1.19 A 84.9 + 4.5 Mean = 77.1 2.4 50.6 +/- 5.2 45.2 +/- 4.9 Fe-59 53.4 + 5.8 43.0 +/- 0.7 1.17 A 51.2 + 4.9 Mean = 50.1 + 2.6 93.6 + 9.3 110.0 +/- 9.0 Zn-65 118.0 + 10.8 87.2 +/- 1.5 1.19 A 93.3 + 8.5 Mean= 103.7 +/- 4.7 119.0 +/- 4.5 113.0 + 4.5 Co-60 133.0 + 5.8 118 + 2.0 1.01 A 114.0 + 4.3 Mean = 119.8 i 2.4

- 47.8 3.9 44.3 3.9 Co-58 39.1 *: 4.5 44.7 +/- 0.8 1.00 A 47.3 3.8 Mean= 44.6 2.0 (1) Results reported as activity i1 sigma.

(2) Results reported as activity +/-1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable D-10

TABLE D-5 (cont)

INTERLABORATORY INTERCOMPARISON PROGRAM CGmma Analvaia Milk tnCiflitprI IVI1L1 85.9 8.64 pCi/liter 112.0 10.6 Ce-141 92.4 A 1.5 1.09 A 105.0 7.9 Mean= 101.0 5.3 224.0 I 48.4 Cr-51 298.0 + 61.1 303 + 5.1 0.96 A 350.0 +/- 45.5 Mean = 290.7 L 30.1 83.0 + 6.9 Cs-134 91.5 i 9.8 95 + 1.6 0.95 A 97.5 +/- 7.3 Mean = 90.7 +/- 4.7 174.0 +/- 9.8 Cs-137 178.0 + 10.9 189 + 3.2 0.93 A 175.0 +/- 8.5 Mean = 175.7 +/- 5.7 128.0 + 8.5 Mn-54 101.0 +/- 9.8 125 + 2.1 0.94 A 124.0 +/- 7.8 Mean = 117.7 +/- 5.0 49.5 +/- 10.1 Fe-59 71.3 +/- 11.9 63.9 + 1.1 0.96 A 63.5 +/- 8.3 Mean= 61.4 +/- 5.9 121.0 +/- 16.6 Zn-65 170.0 +/- 20.7 155 + 2.6 1.01 A 179.0 + 15.6 Mean= 156.7 +/- 10.3 142.0 + 7.0 Co-60 128.0 +/- 8.3 145 +/- 2.4 0.92 A 130.0 +/- 6.4 Mean= 133.3 + 4.2 (1) Results reported as activity +1 sigma.

(2) Results reported as activity :l sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc (A) Evaluation Results, Acceptable D-11

TABLE D-5 (cont)

INTERLABORATORY INTERCOMPARISON PROGRAM 9/1' 232.0 4.9 pCi/liter 241.0 8.1 Ce-141 233 4 3.9 1.02 A 237.0 7.6 Mean = 236.7 4.1 326.0 +/- 21.0 Cr-51 344.0 i 35.9 338 :i 5.7 0.97 A 314.0 + 31.4 Mean= 328.0 +/- 17.4 130.0 + 3.7 Cs-134 126.0 + 5.7 122 + 2.0 1.03 A 120.0 + 5.6 Mean= 125.3 +/- 2.9 187.0 + 4.0 Cs-137 198.0 +/- 7.0 195 + 3.2 0.99 A 194.0 + 6.3 Mean= 193.0 + 3.4 97.2 + 3.3 Mn-54 102.0 + 5.6 92.0 + 1.5 1.09 A 102.0 5.1 Mean= 100.4 + 2.8 65.0 + 3.7 Fe-59 49.9 i 6.3 61.0 +/- 1.0 1.00 A 68.4 6.0 Mean= 61.1 + 3.1 124.0 + 6.3 Zn-65 147.0 12.3 123 + 2.1 1.07 A 121.0 9.6 Mean= 130.7 X 5.6 159.0 4 3.2 Co-60 163.0 55 167 + 2.8 0.98 A 169.0 + 5.0

__________ M ean = 163.7 2.6 _ _ _ _ _ _ _ _ _ _ _

55.2 2.8 62.6 5.0 Co-58 63.4 +/- 1.1 0.94 A 61.8 4.5 Mean = 59.9 2.4 (1) Results reported as activity d1 sigma.

(2) Results reported as activity +/-1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-12

TABLE D-5 (cont)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analvqia onil (nCiluram) aJIL, 0.022 pCi/gram 0.157 0.022 Ce-141 0.190 0.024 0.182 + 0.003 0.95 A 0.171 0.037 Mean = 0.173 0.017 0.356 + 0.101 0.593 + 0.122 Cr-51 0.697 d 0.135 0.596 + 0.010 1.08 A 0.640 d 0.198 Mean = 0.643 + 0.090 0.160 + 0.015 0.204 + 0.016 Cs-134 0.193 +/- 0.018 0.187 + 0.003 1.03 A 0.182 +/- 0.008 Mean= 0.193 +/- 0.009 0.449 + 0.021 0.480 + 0.023 Cs-137 0.479 +/- 0.027 0.474 + 0.008 1.01 A 0.473 +/- 0.010 Mean= 0.477

• 0.012 0.256

• 0.018 0.255 4 0.018 Mn-54 0.223 +/- 0.021 0.246 +/- 0.004 0.98 A 0.244 +/- 0.009 Mean= 0.241 +/- 0.010 0.109 4 0.025 0.104 +/- 0.029 Fe-59 0.132 t 0.032 0.126 + 0.002 1.01 A 0.157 0.033 Mean= 0.127 + 0.013 0.320 + 0.034 0.360 4 0.033 Zn-65 0.374 4 0.040 0.305

• 0.005 1.15 A 0.320

• 0.017 Mean= 0.351

• 0.018 0.277 0.014 0.266 0.015 Co-60 0.279 0.017 0.285 + 0.005 0.96 A 0.274 0.007 I I .1.

Mean = 0.273 0.008 I 1 (I) Results reported as activity +I sigma.

(2) Results reported as activity +/-1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-13

TABLE D-5 (cont)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Vegetation (pCI/gram)

V hLIT, IAlI WIN 0.179 J_ 0.012 pCi/gram 0.160 0.012 Ce-141 0.193 0.012 0.174 +/- 0.003 l 1.02 A 0.180 0.015 Mean = 0.178 0.009 0.600 A 0.087 0.464 + 0.075 Cr-51 0.470 + 0.059 0.569 + 0.010 0.95 A 0.638 + 0.118 Mean= 0.543 + 0.058 0.232 . 0.013 0.213 + 0.013 Cs-134 0.197 + 0.010 0.179 + 0.003 1.17 A 0.195 + 0.006 Mean = 0.209  : 0.007 0.370 + 0.015 0.340 + 0.015 Cs-137 0.341 + 0.012 0.355 + 0.006 0.97 A 0.326 + 0.007 Mean = 0.344 + 0.008 0.243 + 0.014 0.227 + 0.014 Mn-54 0.238 + 0.011 0.235 & 0.004 1.00 A 0.235 + 0.006 Mean= 0.236  : 0.008 0.123 + 0.015 0.112 0.016 Fe-59 0.139 + 0.012 0.120 4 0.002 1.04 A 0.123 + 0.014 Mean= 0.124 + 0.009 0.275 + 0.023 0.280 + 0.029 Zn-65 0.301 + 0.019 0.292 + 0.005 1.00 A 0.317 + 0.013 Mean = 0.293 + 0.014 0.273 0.011 0.252 0.011 Co-60 0.267 0.009 0.272 + 0.005 I 0.98 A 0.271 0.005 Mean= 0.266 0.006 I L I (1) Results reported as activity 41 sigma.

(2) Results reported as activity +/-1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-14

TABLE D-5 (cont)

INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Water (pCi/mi) 11/11/05 A19773-05 WATER GROSS 1908 +/- 2 pCi/ml BETA 1687 + 2 1908 + 2 1830 + 46 0.98 A 1706 + 2 Mean= 1802 +/- 2 (1) Results reported as activity =1 sigma.

(2) Results reported as activity =1 sigma.

(3) Ratio = Reported/lcnown

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-15

TABLE D-5 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of NIST Filter and water samples HLTER 1.86E5 + 791 pCi/filter 1.85E5 + 887 1.96E5 +/- 2176 0.96 A 1.96E5 + 785 Mean = 1.89E5 + 475 Ba-133 5.25E4 4 277 5.36E4 +/- 300 5.95E4 +/- 619 0.89 A 5.21E4 + 262 Mean = 5.27E4 +/- 162 Cs-134 2.90E4 +/- 230 2.30E4 +/- 226 2.79E4 +/- 254 0.97 A 2.95E4 + 224 Mean = 2.72E4 4 131 Fe-59 1.99E5 4 1140 1.94E5 4 1460 1.87E5 +/- 1982 1.06 A 2.03E5 + 1110 Mean = I.99E5 + 720 Zn-65 9.59E4 686 9.30E4 878 9.02E4 +/- 1344 1.06 A 9.76E4 664 Mean= 9.55E4 432 I I* 1 I 8/2005 1800-10 WATER Ce-141 1A8E5 752 pCi/g 1.46E5 686 1.48E5 +/- 1125 0.99 A 1.47E5 845 Mean = 1.47E5 441 Ba-133 4.17E4 + 193 4.22E4 : 188 4.41E4 +/- 291 0.96 A 4.27E4 + 237 Mean= 4.22E4 + 120 Cs-134 2.69E4 + 170 2.69E4 + 166 2.62E4 + 115 1.03 A 2.74E4 +/- 208 Mean 2.71E4 +/- 105 Fe-59 1.21E5 + 685 1.22E5 +/- 687 1.18E5 + 814 1.03 A 1.22E5 +/- 871 Mean = 1.22E5 +/- 435 Zn-65 6.16E4 426 6.12E4 423 5.91E4 I 745 1.04 A 6.13E4 535 Mean = 6.14E4 268 (1) Results reported as activity +/-1 sigma.

(1) Results reported as activity 12 sigma (total propagated uncertainty).

(3) Ratio = Reported/NIST (see Section 8.3).

(*) Sample provided by NIST.

(A) Evaluation Results, Acceptable.

D-16

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

Data Reduction and Error Analysis for the Physical Sciences, Bevington P.R., McGraw Hill, New York (1969).3 D-17