NL-04-057, Annual Radiological Environmental Operating Report for 2003

Annual Radiological Environmental Operating Report for 2003

ML041340492
Person / Time
Site:	Indian Point
Issue date:	05/10/2004
From:	Conroy P Entergy Nuclear Northeast
To:	Document Control Desk, NRC/FSME
References
NL-04-057
Download: ML041340492 (133)

Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

Entergy Indian Point Energy Center 295 BroadNay, Suite 1 P.O. Box 249 Buchanan, NY 10511-0249 May 10, 2004 Docket Nos. 50-3, 50-247, 50-286 NL-04-057 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-Pl-17 Washington, DC 20555-0001

Subject:

Indian Point Nuclear Power Plants Units 1, 2 and 3 Indian Point's Annual Radiological Environmental Operating Report for 2003 Dear Sir; Enclosed plaase find one copy of the Indian Point Site Annual Radiological Environmental Operating Report for the period January 1, 2003 to December 31, 2003. This report is submitted as required by Technical Specifcation 5.6.2 in accordance with facility licenses DPR-5, DPR-26, and DPR-64 for Indian Point Unit Nos. 1,2 and 3 respectively.

Entergy Nuclear Operations, Inc. is making no new commitments in this letter.

Should you or your staff have any questions, please contact Mr. Chris Wend, Radiation Protection Manager, Indian Point Energy Center at (914) 736-8401.

Sincerel Patric onroy Manager, Licensing Entergy, Indian Point Energy Center Enclosure cc: See next page Adz

Docket Nos. 50-3, 50-247, 50-286 NL-04-057 Page 2 of 2 cc: Mr. Hubert J. Miller Regional Administrator - Region 1 U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Patrick D. Milano, Sr. Project Manager Project Directorate I Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mail Stop 0-8-C2 Washington, DC 20555-0001 U. S. Nuclear Regulatory Commission Senior Resident Inspector Indian Point Unit 2 P. 0. Box 59 Buchanan, NY 10511-0059 U. S. Nuclear Regulatory Commission Resident Inspector's Office Indian Point Unit 3 P. O. Box 337 Buchanan, NY 10511-0337 Mr. Michael K. Webb, Project Manager Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop o-7-D1 Washington, DC 20555-0001

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, 2003

TABLE OF CONTENTS Page 1.0 EXECUTIVE

SUMMARY

1-1

2.0 INTRODUCTION

2-1 2.1 Site Description 2-1 2.2 Program Background 2-1 2.3 Program Objectives 2-1 3.0 PROGRAM DESCRIPTION 3-1 3.1 Sample Collection 3-1 3.2 Sample Analysis 3-1 3.3 Sample Collection and Analysis Methodology 3-1 3.3.1 Direct Radiation 3-1 3.3.2 Airborne Particulates and Radioiodine 3-2 3.3.3 Hudson River Water 3-2 3.3.4 Drinking Water 3-2 3.3.5 Hudson River Shoreline Soil 3-2 3.3.6 Broad Leaf Vegetation 3-3 3.3.7 Fish and Invertebrates 3-3 3.3.8 Hudson River Aquatic Vegetation (Non-RETS) 3-3 3.3.9 Hudson River Bottom Sediment (Non-RETS) 3-3 3.3.10 Precipitation (Non-RETS) 3-3 3.3.11 Soil (Non-RETS) 3-3 3.3.12 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 3-5 3.4.3 Table Statistics 3-6 3.5 Program Units 3-7 i

TABLE OF CONTENTS (continued)

Pacie 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 Conclusion 4-7 5.0 BLIND TESTING 5-1

6.0 REFERENCES

6-1 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 RETS Sampling Locations (Within Two Miles) A-5 A-2 RETS Sampling Locations (Greater Than Two Miles) A-6 A-3 Non-RETS Sampling Locations A-7 C-1 Direct Radiation, 1993 to 2003 C-3 C-2 Radionuclides in Air - Gross Beta, 1993 to 2003 C-5 C-3 Hudson River Water-Tritium, 1993 to 2003 C-7 C-4 Drinking Water - Tritium, 1993 to 2003 C-9 C-5 Radionuclides in Shoreline Soil, 1993 to 2003 C-11 C-6 Broad Leaf Vegetation - Cs-137, 1993 to 2003 C-13 C-7 Fish and Invertebrates - Cs-1 37, 1993 to 2003 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, 2003 B-3 B-1 a 2003 Air Sampling Deviations B-4 B-1 b 2003 TLD Deviations B-4 B-1 c 2003 Other Media Deviations B-4 B-2 RETS Annual Summary, 2003 B-5 B-3 2003 Direct Radiation, Quarterly Data B-9 B-4 Direct Radiation, 1997 Through 2003 Data B-10 B-5 2003 Direct Radiation, Inner and Outer Rings B-1i1 B-6 Gross Beta Activity in Airborne Particulate Samples, 2003 B-12 B-7 Concentrations of Gamma Emitters in Quarterly Composites of Air Particulate Samples, 2003 B-1 6 B-8 1-131 Activity in Charcoal Cartridge Samples, 2003 B-21 B-9 Concentrations of Gamma Emitters in Hudson River Water Samples, 2003 B-23 B-10 Concentrations of Tritium in Hudson River Water Samples, 2003 B-25 B-1 1 Gross Beta Activity and Concentrations of Gamma Emitters in Drinking Water Samples, 2003 B-26 B-1 2 Concentrations of Tritium in Drinking Water Samples, 2003 B-28 B-13 Concentrations of Gamma Emitters in Shoreline Soil Samples, 2003 B-29 B-14 Concentrations of Gamma Emitters in Broad Leaf Vegetation, 2003 B-30 B-15 Concentrations of Gamma Emitters in Fish and Invertebrate Samples, 2003 B-36 B-16 Annual Summary, Non-RETS Sample Results, 2003 B-37 B-17 Milch Animal Census, 2003 B-38 B-18 Land Use Census, 2003 B-39 iv

LIST OF TABLES (Continued)

TABLE TITLE Page C-1 Direct Radiation Annual Summary, 1993 to 2003 C-2 C-2 Radionuclides in Air, 1993 to 2003 C-4 C-3 Radionuclides in Hudson River Water, 1993 to 2003 C-6 C-4 Radionuclides in Drinking Water, 1993 to 2003 C-8 C-5 Radionuclides in Shoreline Soil, 1993 to 2003 C-1 0 C-6 Radionuclides in Broad Leaf Vegetation, 1993 to 2003 C-12 C-7 Radionuclides in Fish and Invertebrates, 1993 to 2003 C-14 D-1 2003 QA Program Schedule D-2 D-2 Ratio of Agreement D-3 D-3 2003 Co-58 Results D-6 D-4 2003 Co-60 Results D-8 D-5 JAF (EML)Environmental Laboratory Summary D-9 D-6 Interlaboratory Comparison Program D-10 v

SECTION I EXECUTIVE

SUMMARY

1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report (AREOR) contains descriptions and results of the 2003 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 2003 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 were no increased levels of radioactivity attributable to 2003 Indian Point Station operation.

This report contains a description of the REMP and the conduct of that program as required by the IP2 Radiological Environmental Technical Specifications and IP3 Radiological Effluent Controls, herein referred to as RETS. IP2 implemented Improved Technical Specifications (ITS) in mid-December of 2003, at which time several of the required Radiological Controls were moved to the IP2 Off-site Dose Calculation Manual (ODCM). For the majority of the reporting year, the REMP was conducted under Technical Specifications for IP2. This 2003 AREOR also contains summaries and discussions of the results of the 2003 program, trend analyses, potential impact on the environment, land use census, and interlaboratory comparisons.

During 2003, a total of 1314 analyses were performed. Table B-1 presents a summary of the collected sample results. The actual sampling frequency in 2003 was higher than required, due to the inclusion of additional (non-RETS) sample locations and media.

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Insummary, the levels of radionuclides inthe environment surrounding Indian Point are significantly less than NRC limits as a result of Indian Point Station operations in 2003. The levels present in 2003 were within the historical ranges, i.e., previous levels resulting from natural and anthropogenic sources for the detected radionuclides. Consequently, Indian Point operations in 2003 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.

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SECTION 2 INTRODUCTION

2.0 INTRODUCTION

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

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

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

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

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

To identify changes inactivity, 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 2-1

generally be affected by plant discharges. The use of indicator and control locations enables the identification of potential sources of detected radioactivity, thus meeting one of the program objectives.

Verification of expected radionuclide concentrations resulting from effluent releases attributable to the site is another program objective. Verifying projected concentrations through the REMP is difficult since the environmental concentrations resulting from plant releases are consistently too small to be detected. Plant related radionuclides were detected in 2003, 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 Radiological Environmental Technical Specifications and Radiological Effluent Controls (RETS),

sampling and analysis of environmental media are performed as outlined in Table A-1 and described in section 3.3. The Indian Point REMP consists of samples that are required by RETS and additional samples, Non-RETS, that are not required by RETS.

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

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

3.2 Sample Analysis The analysis of Indian Point environmental samples is performed by the James A. Fitzpatrick Nuclear Power Plant (JAFNPP) Environmental Laboratory in Fulton, New York. The JAFNPP lab at Fulton currently analyzes all samples including tritium.

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

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

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

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3.3.2 Airborne Particulates and Radioiodine Air samples were taken at nine locations varying in distance from 0.28 to 20.7 miles (0.4 to 33 km) from the plant. These locations represent one control 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 RETS 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 (RETS designation Wal) and at a point exterior to the discharge canal where Hudson River water and water from the discharge canal mix (RETS 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 Drinking Water Samples of drinking water are collected monthly from the Camp Field Reservoir (3.4 miles NE, RETS designation Wb1) and New Croton Resevoir (6.3 Mi SE, RETs designation 8), see Figure A-2. Each monthly sample is approximately 4 liters and is analyzed for gamma-emitting radionuclides, gross beta, and 1-131. They are also composited quarterly and analyzed for tritium.

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

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3.3.6 Broad Leaf Vegetation Broad leaf vegetation samples are collected from three locations during the growing season. The designation for the two RETS indicator locations are Icl and Ic2, and the RETS 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 RETS designation for the upstream sample point is Ib2 and the downstream designation is Ibl, see Figures A-1 and A-2. These samples are collected in season or semiannually if they are not seasonal. The fish and invertebrates sampled are analyzed by gamma spectroscopy.

3.3.8 Hudson River Aquatic Vegetation (Non-RETS)

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-RETS)

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-RETS)

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-RETS)

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

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3.3.12 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.

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

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

3.4.1 Lower Limit of Detection (LLD) and Critical Level (L0)

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

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

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

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- Instrument characteristics (e.g., efficiency)

- Sample size

- Counting time

- Media density (self-absorption)

- Radioactive decay

- Chemical yield In the RETS 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 (La) 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) 0 5 in cpm where: ka = 1.645 (corresponds to a 95% confidence level)

Sb = standard deviation of the background count rate = (RWTb) 05 Rb = background count rate (cpm)

Tb = background count time (min)

T, = sample count time (min)

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

chance of false positive).

3.4.2 Determination of Mean and Propagated Error In accordance with program policy, recounts of positive samples are performed. When the initial count reveals the presence of radioactivity, which may be attributed to plant operations, at a value greater than the Lb, 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 intwo or 3-5

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

• xI X= 1 N

where: X= value of each individual observation N = number of observations

((ERRiI PE= .t 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 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.

Inthe 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 3-6

were performed on a sample and a radionuclide's values are "< L: " 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 1993 through 2002. The 2003 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:

Becquerel is a measure of radioactive material, abbreviated Bq, from the International System of Units (SI). A Becquerel isone 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.

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

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

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

The millirem is different from the milliroentgen in that the millirem is used for 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.

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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.

Picocuriespercubicmeter(pCVm3 ) is used to express concentration for all air samples.

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

Picocuriesperliter(pCUL) is used to express concentration for liquid samples such as, precipitation, drinking water, and river water samples.

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

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SECTION 4 RESULTS AND DISCUSSION

4.0 RESULTS AND DISCUSSION The 2003 Radiological Environmental Monitoring Program (REMP) was conducted in accordance with Indian Point's Radiological Environmental Technical Specifications and Radiological Effluent Controls, herein referred to as RETS. The RETS 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-RETS" because these samples are not required by the RETS.

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-RETS) bottom sediment (non-RETS)

Airborne Particulates and Radioiodine Precipitation (non-RETS)

Drinking Water Terrestrial Broad Leaf Vegetation Soil (non-RETS)

Direct Gamma Radiation 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 2003 and assessed the significance of the findings.

A summary of the results of the 2003 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 RETS indicator and control locations. Discussions of these results and their evaluations are provided below.

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

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

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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 invarious RETS and non-RETS 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 in2003 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 2003, the detected radionuclide(s) attributable to past atmospheric weapons testing also consisted of Cs-137 in some media. The levels detected were consistent with the historical levels of radionuclides resulting from weapons tests as measured in previous years.

The final group of radionuclides detected through the 2003 REMP comprises those that may be attributable to current plant operations. During 2003, Cs-1 37 was the only potentially plant-related radionuclide detected in some of the RETS and non-RETS samples.

H-3 may be present inthe local environment due to either natural occurrence, other man-made sources, or as a result of plant operations. There was not H-3 detected in 2003. 'Less than" values for H-3 are reported from the laboratory as less than the sample LLD, which are less than the RETS required LLD.

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-1 34 has a short half-life relative to Cs-1 37, Cs-1 34 from Chernobyl is not likely to be present in 2003. Only Cs-137 is currently found from Cherynobyl 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 the 1998, 2000, 4-2

2001, 2002 and 2003 AREOR.

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

They are produced by neutron activation in the reactor core. As Co-58 has a much shorter half-life, its absence "dates" the presence of Co-60 as residual from releases of both nuclides in the past. If Co-58 and Co-60 are concurrently detected in environmental samples, then the source of these nuclides is considered to be from recent releases. When significant concentrations of Co-60 are detected but no Co-58, there is an increased likelihood that the Co-60 is due to residual Co-60 from past operations. There was no Co-58 or Co-60 detected in the 2003 REMP, though they (Co-58 and Co-60) can be observed in historical tables.

Inthe following sections, a summary of the results of the 2003 REMP is presented by sample medium, and the significance of any positive findings discussed. Itshould 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 the JAFNPP Environmental Laboratory. The laboratory uses a Panasonic TLD system. In.2003, the TLD program produced a consistent picture of ambient background radiation levels in the vicinity of the Indian Point Station. A summary of the annual TLD data is provided in Table B-2 and all the TLD data are presented in Tables B-3, B-4 and B-5. TLD sample site DR-40 is the control site for the direct radiation (DR) series of measurements.

Table B-3 provides the quarterly and annual average reported doses in mR per standard quarter for each of the direct radiation sample points, DR-1 through DR-41. The table also provides the sector for each of the DR sample points. Table B4 provides the mean, standard deviation, minimum and maximum values in mR per standard quarter for the years 1997 through 2002. The 2003 means are also presented in Table B-4. Table B-5 presents the 2003 TLD data for the inner ring and outer ring of TLDs.

The 2003 mean value for the direct radiation sample points was 14.1 mR per standard quarter. In2002, the mean value was 14.3 mR and the mean value for the period 1997 through 2002 was 14.7 mR per standard quarter. At those locations where the 2003 mean value was higher, they are within historical bounds for the respective locations.

The DR sample locations are arranged so that there are two concentric rings of TLDs around the Indian Point site. The inner ring (DR-1 to DR-1 6) is close 4-3

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 14.3 mR per standard quarter while the average for the outer ring was 13.9 mR per standard quarter. The control location average for 2003 was 13.4 mR per standard quarter.

Table C-1 and Figure C-1 present the 10-year historical averages for the inner and outer rings of TLDS. The 2003 averages are consistent with the historical data. The 2003 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 2003 air particulate filter and charcoal cartridge analyses is presented inTable 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 0.014 pCVm 3 and the average for the control location was 0.014 pCVm3. 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 2003 gross beta concentration was consistent with historical levels. Cs-137 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 pCim 3) in the charcoal cartridge samples, which is consistent with historical trends.

From the data, it can be seen that no airborne radioactivity attributable to the 4-4

operation of Indian Point was detected in 2003.

4.3 Hudson River Water A summary of the radionuclides detected in the Hudson River water is contained in Table B-2. Data resulting from analysis of monthly Hudson River water samples for gamma emitters, and H-3 analysis of quarterly composites, are presented in Tables B-9 and B-1 0, respectively.

No radionuclides other than those that are naturally occurring 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. These historical tritium levels are well below the required LLD of 3000 pCVL. 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 2003 drinking water sample analysis results. Results of the gamma spectroscopy analyses of the monthly drinking water samples are in Table B-11; 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 inTable B-2. Table B-13 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 2003. Cs-137 was detected in three out of six samples from indicator locations. Cs-137 was detected at the control location intwo out of four samples. The average concentration for the indicator locations was 124 pCVkg-dry with a maximum concentration of 178 pCikg-dry. The control location had positive samples indicating an average of 73 pCVkg-dry and a maximum of 80 pCVkg-dry.

An historical look at Cs-1 37 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 inthis media, both at indicator and control locations, 4-5

at a consistent level over the past ten years.

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 2003 samples are presented in Table B-14. Analyses of broad leaf vegetation samples revealed naturally occurring nuclides, and Cs-1 37. Cs-1 37 was detected in one of the thirty-six samples from indicator locations at a concentration of 14.1 pCVkg-wet.

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-1 37 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 2003. 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 Sampling Although not required by the RETS, 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-16. As shown by these data, the radionuclides detected were consistent with their respective historical levels.

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

1-131 was detected in aquatic vegetation samples in one out of six indicator samples and one out of five control samples with an average concentration of 27.5 and 21.9 pCVkg-wet, respectively. The 1-131 detected was not due to station operations based on a review of plant discharge records during the sample months, but most likely due to medical administrations especially since the 1-131 was detected in both control and indicator locations. Cs-137 was detected in four out of six indicator samples and four out of five control samples at an average concentration of 7.2 pCikg-wet and 8.6 pCikg-wet, respectively.

4-6

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 Ouffall, Gypsum Plant Stream, Verplanck-5 t Street Well, and Trap Rock Quarry samples were analyzed for tritium and plant-related nuclides. The samples did not show any tritium or other plant-related nuclides. The non-RETS 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-RETS sampling show that the main detected anthropogenic activity is Cs-1 37, which is found at both indicator and control locations. 1-131 was detected in both indicator and control locations for aquatic vegetation and was likely attributed to sources other than plant operations, such as medical administrations. The non-RETS sample data corroborate the RETS sample data in determining that the operation of the Indian Point station in2003 had no detectable adverse radiological impact on the environment.

4.9 Land Use Census A census was performed in the vicinity of Indian Point in 2003. 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 2003 census were the same as the 2002 census results.

There were no animals producing milk for human consumption found within 5 miles (8 km) of the plant. The second part of this census revealed that the nearest residences are located 0.4 miles (0.64 km) ESE and 0.5 miles (0.75 km) E of the plant.

The Indian Point REMP does not include a garden census. RETS allows the sampling of broad leaf vegetation intwo 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 Conclusion The Radiological Environmental Monitoring Program is conducted each year to determine the radiological impact of Indian Point operations on the environment. The preceding discussions of the results of the 2003 REMP reveal that operations at the station did not result in an adverse impact on the environment.

4-7

The results of the 2003 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 2003 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.

4-8

SECTION 5 IPEC will no longer perform duplicate blind samples, refer to the Interlaboratory Comparison Study (Appendix D)

And Technical Information Document 2003-011 "Justification for the Removal of the Radiological Environmental Monitoring Blind Spike Program at IPEC" 5-1

SECTION 6 REFERENCES

6.0 REFERENCES

1. Radiological Environmental Technical Specifications, for Indian Point Nuclear Generating Stations 1, 2, and 3.

2. Entergy Nuclear Northeast, Nuclear Environmental Monitoring Procedures.

Radiological Support Procedures, Indian Point Station.

3. Environmental Analytical Procedures, Teledyne Isotopes, Inc., Westwood, NJ

- Knoxville, TN.

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

5. Eisenbud, M., Environmental Radioactivity, Academic Press, New York, 1987.

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

7. 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.

8. Cohen N., and Eisenbud M., Radiological Studies of the Hudson River.

Proaress Report Institute of Environmental Medicine, New York University Medical Center, December 1983.

9. 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.

10. 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.

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

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

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

6-1

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

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

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

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

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

19. 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.

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

21. Entergy Nuclear Northeast (1P3), Offsite Dose Calculation Manual - Part 1.

Radiological Effluent Controls - Part 2 Offsite Dose Calculation Manual, Revision 15, December 2001.

22. Entergy Nuclear Northeast (IP2), Offsite Dose Calculation Manual Rev. 6, October, 1999.

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

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

25. 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.

6-2

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

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

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

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

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

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

32. ENN-LI-1 02, Corrective Action Process

33. Improved Technical Specifications, ITS, Entergy Indian Point Unit 2, "Conversion of "CTS" to "ITS" based on NUREG-1431, Standard Technical Specifications" 11/3/03. Implemented at IPEC on 12/15/03.

34. Technical Information Document 2003-011 "Justification for the Removal of the Radiological Environmental Monitoring Blind Spike Program at IPEC" 6-3

APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS REQUIREMENTS

APPENDIX A Environmental media are sampled at the locations specified inTable A-1 and shown in Figures A-1, A-2, and A-3. The samples are analyzed according to criteria established in the Radiological Effluent Technical Specifications (RETS). These RETS 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, RETS designation and sample type. Non-RETS samples are also listed but have no RETS designation code. This table gives the complete listing of sample locations used in the 2002 REMP.

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

The RETS 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 invarious 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 RETS environmental surveillance requirement that an annual land use and milch animal census be performed. See Tables B-1 7 and B-1 8 for the milch animal and land use census.

A-1

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS DR8 4 Al Algonquin Gas Line Onsite - Air Particulate, Al AlgonquinGasLine_0.28 Mi (SW) at 2340 Radioiodine A4 Onie-Air Particulate, 5 A4 NYU Tower 0.88 Mi (SSW) at 208 Radioaodine,

______ DRi10.8 i(S) t28 Direct Gamma 7 Wbl Camp Field Reservoir 3.4 Mi (NE) at 51 Drinking Water 8 NR New Croton Reservoir 6.3 Mi (SE) at 1240 Drinking Water 9 Wal Plant Inlet (Hudson River Intake)* Onsite - HR Water

0. 16 Mi (W)at 2730HWae Wa2 Onsite - HR Water, 10 NR Discharge Canal (Mixing Zone) 0.3 Mi (WSW) at 2490 HR Bottom Sediment 14 DR7 Water Meter House Onsite - Direct Gamma

____________ ~0.3 Mi (SE) at 1330 Drc am NR HR Aquatic Vegetation.

17 NR Off Verplanck 1.5 Mi (SSW) at 202.50 HR Shoreline Soil, NR HR Bottom Sediment 20 DR38 (AKA Montrose Marina) 1.5 Mi (S) at 1800 Direct Gamma 22 NR Loveft Power Plant 1.6 Mi (WSW) at 2440 Air Particulate, NR Radioiodine NR Precipitation, A5 Air Particulate, A5 Radioiodine, 23 DR40 Roseton* 20.7 Mi (N) at 3570 Direct Gamma, Ic3 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 0690 Bottom Sediment, NR HR Aquatic Vegetation

'= Control location HR = Hudson River NR = non RETS RIS = Reuter Stokes A-2

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS 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 0530 Direct Gamma 34 DR9 South East Corner of site Onsite - Direct Gamma 35 DR5 Broadway & Bleakley Avenue 0.37 Mi (- at 0920 Direct Gamma 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 DR11 White Beach 0.92 Mi (SW) at 2260 HR Shoreline Soil, 56 DR37 Verplanck - Broadway & Sixth Street 1.25 Mi (SSW) at 2020 Direct Gamma 57 DR1 Roa Hook 2 Mi (N) at 0050 Direct Gamma 58 DR17 Route 9D - Garrison 5.41 Mi (N) at 3580 Direct Gamma 59 DR2 Old Pemart Avenue 1.8 Mi (NNE) at 0320 Direct Gamma 60 DR18 Gallows Hill Road & Sprout Brook 5.02 Mi (NNE) at 0290 Direct Gamma

_ _ __ __ _ _ _ _ _ _ _ _ _ _ _ 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) 64 DR20 Lincoln Road - Cort)andt 4.6 Mi (ENE) at 0670 Direct Gamma 66 DR21 Croton Avenue - Cortlandt 4.87 Mi (E) at 0830 Direct Gamma 67 DR22 Colabaugh Pond Road - Cortlandt 4.5 Mi (ESE) at 1140 Direct Gamma 69 DR23 Mt. Airy & Windsor Road 4.97 Mi (SE) at 1270 Direct Gamma 71 DR25 Warren Ave - Haverstraw 4.83 Mi (S) at 1880 Direct Gamma 72 DR26 Railroad Avenue & 9W - Haverstraw 4.53 Mi (SSW) at 2030 Direct Gamma 73 DR27 Willow Grove Road & Captain 4.97 Mi (SW) at 2260 Direct Gamma 74 DR12 West Shore Drive - South 1.59 Mi (WSW) at 2520 Direct Gamma

• = Control location HR = Hudson River NR = non RETS R/S = Reuter Stokes A-3

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS 75 DR28 Palisades Parkway 4.65 Mi (NW) at 3108 Direct Gamma 76 DR13 West Shore Drive - North 1.21 Mi (W) at 276° Direct Gamma 77 DR29 Palisades Parkway 4.15 Mi (W) at 272° Direct Gamma 78 DR14 Rt. 9W across from R/S #14 1.2 Mi (WNW) at 295° Direct Gamma 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 3170 Direct Gamma 81 DR31 Palisades Pkwy - Lake Welch Exit 4.96 Mi (WSW) at 2550 Direct Gamma 82 DR1 6 Ayers Road 1.01 Mi (NNW) at 3340 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 89____DR35___ (near rock cut) 2.89 Mi(NE)at02°_irctGam 90 DR3 Charles Point 0.88 Mi (NE) at 0470 Direct Gamma 92 DR24 Warren Road - Cortlandt 3.84 Ml (SSE) at 1490 Direct Gamma

_2 Air Particulate, 94 A2 IPEC Training Center Onsite- Radiolodine, Ic2 0.39 Mi (S) at 1930 Broadleaf Vegetation, NR Soil

• = Control location HR = Hudson River NR = non RETS RtS = Reuter Stokes A-4

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

Peekskill Westchester County Rockland County 1 Indian Point Ibl 7l 1 mile 1Hudson IC1'c2 River Ic2 El) Bud Verplanck Key: A - Waterborne: Surface (HR) Wa# Ic# - Broadleaf Vegetation o - Direct Radiation Sample Location DR# Ib1 - Fish and Invertebrates o - Air Particulate & Radiolodine A# (where available downstream)

O-- HR Shoreline Sediment Wc#

A-5

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

Roseton (20.7 mi. N): R5 ( Ic3 Upstream: lb2 Orange County Putnam County Bear Mountain Bridge (1

G)ndian Point HudSo RIver 1 s5miles Rockland County Westchester County Key: 0 - 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 NON-RETS 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

)

• 28: V 10: -

99: Sp /, .41 Han Point 17: vIt

-_1 03:sp 29: N I01 :sp Westchester County Rockland County 27: -

• 8: dw 5 miles Key: * - Air Particulate & Radiolodine Q>-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)

Gross 4 0.01 _ _ l _ll H-3 l 2000_(C) _ l_ ll1 Mn-54 1 _5 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1 (d) 0.07 1 60 X Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 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.

) 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 pCVL may be used.

A-8

TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES

=WIMI IW~AI RBORN EJ;I MAma Z42m Wfiata H-3 20000 (a)

Mn-54 1000 30000 Fe-59 400 10000 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 1 300 1 (a)For drinking water samples. This Isthe 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCVL may be used.

(b) If no drinking water pathway exists, a value of 20 pCVI- may be used.

A-9

3 DR8 Service Center Building Onsite - Direct Gamma 4Al ~~0 .35 Mi (SSE) at 1580 iet am 4 Al Algonquin Gas Line Onsite - Air Particulate, Al Algonquin Gas 0.28 Mi (SW) at 2340 Radioiodine A4 Air Particulate, 5 A4 NYU Tower Ons8 it (SW- t28 Radioiodine, DR10 0.88 Mi (SSW) at 208° Direct Gamma 7 Wbl Camp Field Reservoir 3.3 Mi (NE) at 450 Drinking Water 8 NR Croton Reservoir 6.3 Mi (SE) at 124° Drinking Water 9 Wal Plant Inlet (Hudson River Intake)* 0.16 Mi (W) at 273- HR Water 10W2 DicageCnl MxngZn) Onsite - HR Water, NR Discharge Canal (Mixing Zone) 0.3 Mi (WSW) at 2490 HR Bottom Sediment 14 DR7 Water Meter House Onsite - Direct Gamma

_______ __ ____ ______ _______ ______ 0.3 M i (SE) at 1330 Dr c a m NR HR Aquatic Vegetation, 17 NR Off Verplanck 1.5 Mi (SSW) at 202.50 HR Shoreline Soil, NR HR Bottom Sediment 20 DR38 (AKA Montrose Marina 1.5 Mi (S) at 1800 Direct Gamma 22 NR Lovett Power Plant 1.6 Mi (WSW) at 244° Air Particuiate, NR Precipitation, A5 Air Particulate, A5 Radioiodine, 23 DR40 Roseton* 20.7 Mi (N) at 357° Direct Gamma, Ic3 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 156° Radiolodine, DR41 Direct Gamma NR HR Shoreline Soil, 28 DNR4 Lent's Cove 0.45 Mi (ENE) at 069° Bottom Sedinment, 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 0530 Direct Gamma 34 DR9 South East Corner of site Onsite - Direct Gamma 35 DR5 Broadway & Bleakley Avenue 0.37 Mi (E) at 0920 Direct Gamma

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 052° Air Particulate, NR Radioiodine 50 Wc2 Manitou Inlet* 4.48 Mi (NNW) at 3470 HR Shoreline Soil 53DR11 White Beach 0.92 Mi (SW) at 2260 Direct Gamma 56 DR37 Verplanck - Broadway & Sixth 1.25 Mi (SSW) at 2020 Direct Gamma

________ ___ Street 57 DR1 Roa Hook 2 Mi (N) at 005° Direct Gamma 58 DR17 Route 9D - Garrison 5.41 Mi (N) at 358° Direct Gamma 59 DR2 Old Pemart Avenue 1.8 Mi (NNE) at 0320 Direct Gamma 60 DR18 Gallows Hill Road 8 Sprout Brook 5.02 Mi (NNE) at 0290 Direct Gamma 61 DR36 ower SouthS Frankin 1.3 Mi (NE) at 052° Direct Gamma 62 DR19 West rook Drive 5.03 Mi (NE) at 062° Direct Gamma 64 DR20 (School Parkina Lot) 4.6 Mi (ENE) at 0670 Direct Gamma 66 DR21 Croton Avenue - Cortlandt 4.87 Mi (E) at 0830 Direct Gamma 67 DR22 Colabaugh Pond Road - Cortlandt 4.5 Mi (ESE) at 1140 Direct Gamma 69 DR23 Mt. Airy & Windsor Road 4.97 Mi (SE) at 1270 Direct Gamma 71 DR25 Warren Aveu Haverstraw 4.83 Mi (S) at 1880 Direct Gamma 72 DR26 Railroad Avenue & 9W - 4.53 Mi (SSW) at 2030 Direct Gamma

____Haverstraw 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 DR31 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 79 DR30 Anthony Wayne Park 4.57 Mi (WNW) at 296° Direct Gamma 80 DR15 Route 9W South of Ayers Road 1.02 Mi (NW) at 3170 Direct Gamma 81 DR28 Palisades Pkwy - Lake Welch Exit 4.96 Mi (WSW) at 255° Direct Gamma 82 DR16 Ayers Road 1.01 Mi (NNW) at 3340 Direct Gamma 83 DR32 Route 9W - Fort Montgomery 4.82 Mi (NNW) at 3390 Direct Gamma NR HR Aquatic Vegetation, 84 NR Cold Spring 10.88 Mi (N) at 3560 HR Shoreline Soil, NR HR Bottom Sediment

NR f,4%, , ,,." . -  ; ~ Drinking Water QC 85' Amilcus Res ervoir¶" N./A':,; ',..W;, >Sarnpt~e';.. Z

.~ 1~ .. ~'

)*-I 1 .

88 DR6 R/S Pole #6 0.32 Mi (ESE) at 1180 Direct Gamma 89 DR35 Highland Ave & Sprout Brook 2.89 Mi (NNE) at 0250 Direct Gamma

__________ ~~R oad (near rock cut)__ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _

90 DR3 Charles Point 0.88 Mi (NE) at 047° Direct Gamma 92 DR24 Warren Road - Cortlandt 3.84 Mi (SSE) at 1490 Direct Gamma A2 Air Particulate, 94 A1c2 IPEC Training Center Onsite- Radioiodine, Ic20.39 Mi (S)at 19301 Broadleaf Vegetation, NR Soil A3 Air Particulate, A3 Meteorological Tower Onsite - Radioiodine, Ic1 0.46 Mi (SSW) at 208° Broadleaf Vegetation, NR Soil 99 NR Algonquin Outfall Onsite - Special Ouffall 0.34 Mi (SW) at 2370 Special Outfall 100 NR Gypsum Plant Stream Onsite -SpcaOufl

___ ____ ____ ___ 0.34 Mi (SW ) at 237 0 pca uf l 101 NR 5th Street Well - Verplanck 1 .3 Mi (5) at 2020 Special Groundwater 102 NR Trap Rock Quarry 0.7 Mi (SSW) at 208° Special Surface Water 103 NR IP3 Trailer Well Onsite - Special Groundwater

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS

SUMMARY

APPENDIX B B.1 2003 Annual Radiological Environmental Monitoring Program Summary The results of the 2003 radiological environmental sampling program are presented in Tables B-2 through B-16. Table B-2 is a summary of the RETS samples and Table B-16 is a summary of the non-RETS samples. The format of these summary tables conforms to the reporting requirements of the RETS, NRC Regulatory Guide 4.8 (Reference 4), and NRC Branch Technical Position to Regulatory Guide 4.8 (Reference 14). Inaddition, the data obtained from the analysis of all the individual RETS samples are provided in Tables B-3 through B-1 5.

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 RETS.

B.2 Land Use Census In accordance with Sections 4.11.8 of the IP2 RETS and Part I Section 2.8 of the IP3 RECS, 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 intwo sectors and at a designated control location (results are presented in Table B-14).

B.3 Sampling Deviations During 2003, environmental sampling was performed for six media types required by RETS, five other media types and direct radiation. A total of 1322 samples (1241 RETS and 81 non-RETS) were scheduled. Of the scheduled samples, 99% 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-1 a for air samples, B-1 b for TLDs, and B-1 c for other environmental media.

B.4 Analytical Deviations During 2003, two fish samples could not meet the LLD for Fe-59 due to sample receipt/shipment delays.

B-1

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

B-2

TABLE B-1

SUMMARY

OF SAMPLING DEVIATIONS 2003 RETS MEDIA PARTICULATES IN AIR 468 1 99.8 SEE TABLE B-i1a CHARCOAL FILTER 468 1 99.8 SEE TABLE B-1a TLD 164 2 98.8 SEE TABLb HUDSON RIVER WATER 32 0 100.0 DRINKING WATER 32 0 100.0 SHORELINE SOIL 10 0 100.0 BROAD LEAF 5 0.

VEGETATION 54 0 100.0 FISH & INVERTEBRATES 13 2 84.6 SEE TABLE B-ic SUBTOTALS 1241 6 99.5 NON-RETS MEDIA AQUATIC VEGETATION 10 0 100.0 HUDSON RIVER BOTTOM 0 100.0 SEDIMENT 8 SOIL 3 0 100.0 PRECIPITATION 8 0 100.0 SPECIAL WATER 52 2 962 SEE TABLE SAMPLES B-1 c SUBTOTALS 81 2 98 IOVERALL TOTALS 1322 l 8 99.4 TOTAL NUMBER OF ANALYSES REPORTED - 1314

• Samples not collected or unable to be analyzed.

B-3

TABLE B-i a I B-1 b/B-1 c TABLE B-1a 2003 Air Sampling Deviations 122ST~AT10N ft= 0=1144MWE PROBLEM'IACTIONS~TOPREVENThECURRENCE*UM

1. 44 Peekskill Gas Holder Sample was collected but has lower than normal volume. Pump Bldg 16 failure. Pump was replaced.

1. 44 Peekskill Gas Holder 25 No Sample. Ground Fault Circuit Interrupter tripped. OK after Bldg reset.

Sample was collected but has lower than normal volume.

1. 22 Lovett Power Plant 33 Voltage problem during 8/14/03 blackout resulted in high current surge which caused pump to bum out. Pump was replaced.

TABLE B-1b 2003 TLD Deviations r . .

16UflhiTAIA1ONNUI s _ w _

MUATHMWIRB&'ATO~a~'tVrtCUMCtM

_ sXs__ -~~__ ~ f~ r . _ _ _ ~ _ _ _

1. 59 (DR-02) Old Pemart 2nd QTR LDTLD was missing. / Replaced and relocated TLD. Continue to Ave. n OT ) trend missing TLDs for patterns.

1. 81 (DR 31)Palisades 2d QTR TLD) TLD was missing. / Replaced and relocated TLD. Continue to Pkwy - Lake Welch Exit 2n (TL) trend missing TLDs for patterns.

TABLE B-1c 2003 Other Media Deviations iA ISTATION -!lW "SAMPLE:SCHEDULELA PROBLEMU'ACTIONS7O PREVENT-RECURRENCE i l

1. 102 - Trap Rock Quarry Week # 4 (Non-rets Special Iced Over - no sample Water)

1. 103 - IP3 Trailer Well Week 6 (Non-rets Special Trailers have been vacated, pump Is mOS. Unable to collect Water) sample. Sample discontinued.

1. 23 Roselon Week 38 (Fish and Sample held too long prior to counting. Did not meet LLD for Fe

1. stnInvertebrates) 3R 59.

Week 38 (Fish and Sample held too long prior to counting. Did not meet LLD for Fe

1. 25 Downstream Invertebrates) 59.

B-4

TABLE B-2*

RETS ANNUAL

SUMMARY

- 2003 DIRECT RADIATION #78 West Shore Drive North TLD Reads (mR / standard quarter) N/A 14.1 (158/158) /9.6 - 19.9 1.21 Mi. (276°) DR13 14.7(4/4) 113.5 - 15.3 0 162 B-3 19.9 (4/4)116.2-19.9 AIR PARTICULATES #44 Peekskill Gas Holder Bldg AND RADIOIODINE GB (467) 0.01 0.015(415/415)/0.004-0.030 1.84 Mi. (52°) 0.0140(5252) 4 0.004 0 (pCifrr 3) B-6, B-7, B-8 _0. 016 (52(52) /0.008-0.023 0.024 1-131 (467) 0.07 <b <b < Le 0 GSA (36)

Cs-134 0.05 <Lc <LL <IL 0 Cs-137 0.06 <Ib <, <Ib 0 SURFACE HUDSON RIVER WATER (pCI/L) H-3 (8) 3000 <c <IL <Ic 0 B-9, B-10 GSA (241 Mn-54 15 <Ic <Ic <IL 0 Co-58 15 <Ic <L <Ic 0 Fe-59 30 <Ic <'bb <I 0 Co-60 15 <c <Ic 'b

< 0 Zn-65 30 < c <Ic <I 0 Zr/Nb.95 15 <Ic <Ic <I 0 1-131 15 <Ic <Ic < , 0 Cs-134 15 <Ic <L <'bb 0 Cs-137 18 <c <Ic <Ic 0 Ba/La-140 15 I I < 0 DRINKING WATER #8 New Croton Reservoir (pCVL) B-1 1, B-12 GB (24) 4 2.64(24/24)/1.89-3.84 6.3 Mi (11.24) N/A 0 2.69 (12/112 / 1.98-332 __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

H-3 (8) 2000 <IL <Ic N/A 0 GSA (24)

Mn-54 15 <Ic <c N/A 0 Co-58 15 <Ic <c N/A 0 Fe-59 30 <Cb <b N/A 0 Co-60 15 <C < N/A 0

_ Zn-65 30 <Ic <Ic N/A 0 B-5

TABLE B-2*

RETS ANNUAL

SUMMARY

- 2003 4NKINU Wf N/Am

&cb U (CON1) 1-131 1 <bo < I, N/A 0 Cs-134 15 < IC N/A 0 Cs-137 18 <IC <IL, N/A 0 Ba4a-140 15 < LC N/A 0 SHORELINE SOIL GSA(10 (pCIkg - dry) B-13 (1)

Cs-134 150 c LC c.bLc 0

1. 17 Off Verplanck Cs-137 180 124 (3/6)149.6 -178 1.5 Mi. (202.5°) 73 (2/4) 166-80 0 161 (212)/143-178 BROADLEAF VEGETATION GSA (54)

(pCIkg - wet) B-14 1-131 60 Cb~ Ole Icb 0 Co-60 N/A <Cb < Le Cb

< 0 Cs-134 60 <CbC < < L, 0

1. 95 Met Tower Cs-137 80 14.0(1136)/14.0-14.0 0.39 Mi. (202.5°) < 0 14.1(1/18)/14.1-14.1 FISH AND INVERTEBRATES GSA (11)

(pCi/kg -wet) B-15 Co-58 130 <I <I <b 0 Fe-59 260 < Lc <b <b 0 Co-60 130 <I. <b c< 0 Zn-65 260 < b, < <bcb 0 Cs-134 130 <Lcb <IL <CIb 0 Cs-137 150 <Ic <C <Ic 0 B-6

Table B-2 Notation 2003 RETS ANNUAL

SUMMARY

TABLE NOTES

• = Data for the Annual Summary Tables are based on RETS required samples, with the exception of Air Samples which include RETS and Non-RETS locations.

N/A = Not applicable.

(a) = (Detectable activity measurements) / (Total measurements.)

(b) = Location is distance in miles and direction in compass degrees.

(c) = RETS Required LLD, see Table A-2 (d) = RETS Required LLD > Critical Level (L).

GB = Gross Beta Analysis.

GSA = Gamma Spectroscopy Analysis.

The format of Table B-2, RETS Annual Summary, is dictated by regulations. To help understand this table, one section of Table B-2 is presented in narrative. The following explanation for the Shoreline Soil section of Table B-2 should help the reader understand all of the summaries in Table B-2.

1. The left-hand column reports the sample media, media reporting units, and the table containing the detailed sample results. For Shoreline Soil, the reporting units are pCVkg-dry and the detailed sample results are in Table B-13.

2. The second column tells how the samples are analyzed and how many samples were analyzed. In this case, the samples are analyzed by gamma spectroscopy analysis (GSA) for the nuclides Cs-134 and Cs-137 and there were a total of 10 samples.

B-7

Table B-2 Notation (Continued) 2002 RETS ANNUAL

SUMMARY

TABLE NOTES

3. The third column lists the RETS required lower limit of detection for the type of analysis performed. These values are also listed in Table A-2.

4. The column labeled Indicator Locations gives the results for all the indicator sites.

For shoreline soil, three out of six samples from indicator locations had Cs-137.

The mean of the Cs-137 from the three indicator location sample results that were >

Lc was 124 pCVkg-dry. The range of the samples results > Lc was 206 to 241 pCVkg-dry.

5. The location of the highest indicator is the next column. The indicator site with the highest mean is reported here. For shoreline soil samples, the highest indicator mean for Cs-137 is from sample location 17, Off Verplanck, 1.5 miles from Indian Point at compass direction 202.5 degrees.

6. The control location column is next. For shoreline soil in 2003, Cs-137 was detected in two one of the four samples averaging 73 pCVkg-dry, one sample was 66 and the other was 80 pCVkg-dry respectively.

7. The right hand column gives the number of non-routine reports that are required because of sample results at or above the reporting level. The reporting levels are given in Table A-3.

8. All the sample media reported in Table B-2 follow this general format.

B-8

TABLE B-3 2002 DIRECT RADIATION, QUARTERLY DATA (miRner STANDAR QUARTER)

DR-01 l_N l _15.3 _ _15.6 r _14.7_l 15 15.2 DR-02 NNE 15 14.8 14.7 14.8 DR-03 NE 11.4 12.3 14.1 12.3 12.5 DR-04 ENE 12.9 15.3 15.1 14.7 14.5 DR-05 ENE 11.4 13.5 15.3 13.8 13.5 DR-06 ESE 12.3 13.8 14.2 13.5 13.5 DR-07 SE 13.8 16.5 17.4 16.5 16.1 DR-08 SSE 12.3 13.5 14.1 13.5 13.4 DR-09 S 13.5 13.8 14.7 13.2 13.8 DR-10 SSW 13.2 15.1 14.8 15.3 14.6 DR-11 SW 10.2 12 11.4 12 11.4 DR-12 WSW 14.7 18.3 17.8 17.1 17.0 DR-13 WSW 16.2 18.9 19.9 19.8 18.7 DR-14 WNW 11.1 13.2 13.9 14.1 13.1 DR-15 NW 11.4 13.2 13.6 13.5 12.9 DR-16 NNW 11.4 14.4 15.2 14.4 13.9 DR-17 N 12.3 14.1 14.6 15.3 14.1 DR-18 NNE 10.8 14.1 14.4 14.4 13.4 DR-19 NE 12.3 13.2 14.6 15 13.8 DR-20 ENE 11.4 12.3 14 13.5 12.8 DR-21 E 11.7 13.2 14.1 13.8 13.2 DR-22 ESE 9.6 11.1 10.4 12.3 10.9 DR-23 SE 11.4 13.5 13.1 15 13.3 DR-24 SSE 11.7 13.5 15 15.6 14.0 DR-25 S 11.4 11.4 11.6 14.1 12.1 DR-26 SSW 12.6 12.9 13.9 15.6 13.8 DR-27 SW 13.8 13.2 14.2 15.3 14.1 DR-28 NW 13.5 15.9 17.1 18.6 16.3 DR-29 W 15 15 15.9 17.4 15.8 DR-30 SNS 13.8 15.3 15.7 16.2 15.3 DR-31 WSW 13.5 18.7 18.6 16.9 DR-32 NNW 12 13.2 12.6 13.2 12.8 DR-33 NE 12.9 12.3 15.6 13.5 13.6 DR-34 SE 12.3 12.9 13.5 14.7 13.4 DR-35 NNE 12.3 13.8 14.2 16.2 14.1 DR-36 NE 14.7 14.1 15.2 15.3 14.8 DR-37 SSW 13.8 12.3 12.6 15.62 13.6 DR-38 S 11.4 12 13.2 14.7 12.8 DR-39 SSW 16.8 14.7 15.8 15.9 15.8 DR-40' N 14.7 13.5 15.2 15.3 14.7 DR-41 SSE 14.4 12.6 12.7 13.8 13.4 AVERAGE 12.8 13.8 14.6 14.9 14.1 Data not available

• • Control Location B-9

TABLE B-4 DIRECT RADIATION, 1997 THROUGH 2003 DATA (mR per Standard Quarter) wMFAM Iea n9&i MdoEmnfnn'EiMuIn Tm afduaIfMiIrmbni it-iMI E -.

DR-01 16.1 1.3 14.1 20.7 15.2 DR-02 17.4 3.0 12.9 23.3 14.8 DR-03 12.2 0.9 10.5 14.4 12.5 DR-04 13.7 1.3 11.1 16.3 14.5 DR-05 13.9 0.9 12.3 15.6 13.5 DR_06 13.7 1.1 11.7 16.3 13.5 DR-07 16.4 1.7 14.0 21.7 16.1 DR-08 13.3 1.2 11.1 16.3 13.4 DR-09 13.4 1.2 10.8 16.7 13.8 DR-10 13.5 2.5 5.3 16.8 14.6 DR-11 11.6 1.2 9.5 15.6 11.4 DR-12 16.7 1.7 14.2 19.8 17.0 DR-13 19.4 1.7 16.4 24.6 18.7 DR-14 14.1 1.5 11.1 17.4 13.1 DR-15 14.3 1.6 12.1 19.0 12.9 DR-16 15.2 1.5 12.2 18.4 13.9 DR-17 15.2 1.4 13.1 18.0 14.1 DR-18 14.5 1.3 12.2 17.4 13.4 DR-19 15.4 1.4 12.3 18.2 13.8 DR-20 14.3 1.2 12.5 16.8 12.8 DR-21 14.2 1.2 12.3 18.0 13.2 DR-22 12.2 1.2 10.6 15.9 10.9 DR-23 14.4 1.1 12.6 17.1 13.3 DR-24 14.0 1.3 11.6 15.6 14.0 DR-25 12.8 0.9 11.7 14.9 12.1 DR-26 14.1 1.0 12.5 17.0 13.8 DR-27 14.3 1.0 12.3 16.8 14.1 DR-28 15.3 1.4 12.2 18.6 16.3 DR-29 18.2 1.7 13.9 21.9 15.8 DR-30 17.1 2.1 14.0 23.8 15.3 DR-31 19.1 2.1 14.6 24.6 16.9 DR-32 13.8 1.5 10.7 17.7 12.8 DR-33 9.6 1.5 7.2 12.6 13.6 DR-34 14.0 1.3 11.7 17.6 13.4 DR-35 14.9 1.4 11.9 18.0 14.1 DR-36 16.2 2.4 13.0 25.5 14.8 DR-37 14.3 1.3 12.2 18.0 13.6 DR-38 13.2 1.4 11.1 17.9 12.8 DR-39 16.3 1.3 13.2 19.4 15.8 DR.40 16.0 1.9 12.6 20.3 14.7 DR-41* 13.7 2.0 11.0 19.4 13.4 Average 14.7 1.5 12.0 18.4 14.1 B-10

TABLE B-5 2002 DIRECT RADIATION INNER AND OUTER RINGS (mR per Standard Quarter)

DR-01 DR-17 l_N l_15.2 _ _14.1_l DR-02 DR-18 NNE 14.8 13.4 DR-03 DR-19 NE 12.5 13.8 DR-04 DR-20 ENE 14.5 12.8 DR-05 DR-21 E 13.5 13.2 DR-06 DR-22 ESE 13.5 10.9 DR-07 DR-23 SE 16.1 13.3 DR-08 DR-24 SSE 13.4 14.0 DR-09 DR-25 S 13.8 12.1 DR-10 DR-26 SSW 14.6 13.8 DR-11 DR-27 SW 11.4 14.1 DR-12 DR-28 WSW 17.0 16.3 DR-13 DR-29 W 18.7 15.8 DR-14 DR-30 WNW 13.1 15.3 DR-15 DR-31 NW 12.9 16.9 DR-16 DR-32 NNW 13.9 12.8 Average 14.3 13.9 B-11

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2003 (pCVm 3 +/- 1 sigma)

STATION #

Wa0eWI# 4EndnPat0lr MSV WAMM __i____NS _B mWIWt27LRWJM W94:WM M 950Ml 1 1/7/2003 0.011 + 0.001 0.014 + 0.001 0.014+ lOi 0.012 + 0.001 0.011 + 0.001 2 1/14/2003 0.013 + 0.001 0.014 + 0.002 0.014 + 0.001 0.013 + 0.001 0.014 + 0.002 3 1/21/2003 0.017 + 0.001 0.018 + 0.002 0.018 + 0.002 0.019 + 0.002 0.018 + 0.002 4 1/28/2003 0.016 + 0.001 0.016 + 0.002 0.014 + 0.001 0.016 + 0.002 0.012 + 0.001 5 2/4/2003 0.020 + 0.001 0.016 + 0.002 0.021 + 0.002 0.018 + 0.002 0.018 + 0.001 6 2/11/2003 0.016 + 0.001 0.018 + 0.002 0.016 + 0.002 0.013 + 0.002 0.015 + 0.002 7 2/19/2003 0.018 + 0.001 0.015 + 0.001 0.015 + 0.001 0.014 + 0.001 0.014 + 0.001 8 2/25/2003 0.015 + 0.001 0.018 + 0.002 0.017 + 0.002 0.011 + 0.002 0.014 + 0.002 9 3/4/2003 0.018 + 0.001 0.021 + 0.002 0.021 + 0.002 0.021 + 0.002 0.018 + 0.002 10 3/11/2003 0.023 + 0.002 0.023 + 0.002 0.019 + 0.002 0.020 + 0.002 0.023 + 0.002 11 3/18/2003 0.019 + 0.001 0.021 + 0.002 0.017 + 0.001 0.018 + 0.002 0.019 + 0.002 12 3/25/2003 0.013 + 0.001 0.013 + 0.002 0.010 + 0.001 0.013 + 0.002 0.013 + 0.001 13 4/1/2003 0.011 + 0.001 0.011 + 0.001 0.013 + 0.001 0.010 + 0.001 0.012 + 0.001 14 4/8/2003 0.014 + 0.001 0.012 + 0.002 0.014 + 0.002 0.016 + 0.002 0.013 + 0.001 15 4/15/2003 0.014 _ 0.001 0.015 + 0.001 0.013 + 0.002 0.015 + 0.002 0.012 + 0.002 16 4/22/2003 0.019 + 0.001 0.015 + 0.002 0.018 + 0.002 0.019 + 0.002 0.019 + 0.002 17 4/29/2003 0.008 + 0.001 0.011 + 0.001 0.007 + 0.001 0.014 + 0.002 0.010 + 0.001 18 5/6/2003 0.014 + 0.001 0.012 + 0.001 0.011 + 0.001 0.016 + 0.002 0.014 + 0.002 19 5/13/2003 0.010 + 0.001 0.008 + 0.001 0.008 + 0.001 0.010 + 0.001 0.010 + 0.001 20 5/20/2003 0.010 + 0.001 0.011 + 0.001 0.009 + 0.001 0.010 + 0.002 0.006 + 0.001 21 5/27/2003 0.004 + 0.001 0.005 + 0.001 0.005 + 0.001 0.007 + 0.001 0.005 + 0.001 22 6/3/2003 0.010 + 0.001 0.008 + 0.001 0.011 + 0.001 0.011 + 0.001 0.009 + 0.001 23 6/10/2003 0.011 + 0.001 0.007 + 0.001 0.010 + 0.001 0.010 + 0.001 0.008 + 0.001 24 6/17/2003 0.009 + 0.001 0.009 + 0.001 0.010 + 0.001 0.010 + 0.001 0.010 + 0.001 25 6/24/2003 0.009 + 0.001 0.009 + 0.002 0.010 + 0.002 0.010 + 0.002 0.008 + 0.002 26 7/1/2003 0.021 + 0.002 0.024 + 0.002 0.022 + 0.002 0.023 + 0.002 0.020 + 0.002

• Sample deviation.

• • Control location. B-1 2

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2003 (pCVm3 +/- 1 sigma)

STATION #

,WaeK& UltndQfteJ ______ _ Af 27 7/8/2003 0.019 + 0.001 0.019 + 0.002 0.020 + 0.002 0.020 + 0.002 0.018 + 0.002 28 7/15/2003 0.017 + 0.001 0.016 + 0.002 0.015 + 0.002 0.016 + 0.002 0.015 + 0.002 29 7/22/2003 0.015 + 0.001 0.016 + 0.002 0.012 + 0.002 0.016 + 0.002 0.012 + 0.002 30 7/29/2003 0.014 + 0.001 0.012 + 0.002 0.019 + 0.002 0.014 + 0.002 0.016 + 0.002 31 8/5/2003 0.008 + 0.001 0.010 + 0.001 0.012 + 0.002 0.011 + 0.002 0.009 + 0.001 32 8/1212003 0.009 + 0.001 0.009 + 0.001 0.009 + 0.001 0.008 + 0.001 0.012 + 0.001 33 8/19/2003 0.014 + 0.001 0.016 + 0.002 0.019 + 0.002 0.016 + 0.002 0.013 + 0.001 34 8/26/2003 0.019 + 0.001 0.023 + 0.002 0.025 + 0.002 0.020 + 0.002 0.020 + 0.002 35 9/3/2003 0.015 + 0.001 0.008 + 0.002 0.015 + 0.001 0.016 + 0.002 0.015 + 0.001 36 9/8/2003 0.010 + 0.001 0.012 + 0.002 0.014 + 0.002 0.011 + 0.002 0.013 + 0.002 37 9/16/2003 0.013 + 0.001 0.014 + 0.001 0.013 + 0.001 0.013 + 0.001 0.013 + 0.001 38 9/23/2003 0.017 + 0.001 0.019 + 0.002 0.021 + 0.002 0.018 + 0.002 0.020 + 0.002 39 9/30/2003 0.019 + 0.001 0.017 + 0.002 0.017 + 0.002 0.017 + 0.002 0.019 + 0.002 40 10/6/2003 0.008 + 0.001 0.007 + 0.002 0.008 + 0.001 0.009 + 0.002 0.009 + 0.002 41 10/14/2003 0.029 + 0.002 0.034 + 0.002 0.032 + 0.002 0.029 + 0.002 0.029 + 0.002 42 10/21/2003 0.015 + 0.001 0.014 + 0.002 0.014 + 0.002 0.012 + 0.002 0.015 + 0.002 43 10/28/2003 0.012 + 0.001 0.009 + 0.001 0.012 + 0.001 0.012 + 0.001 0.012 + 0.001 44 11/4/2003 0.018 + 0.001 0.025 + 0.002 0.023 + 0.002 0.022 + 0.002 0.020 + 0.002 45 11/10/2003 0.012 + 0.001 0.012 + 0.001 0.012 + 0.001 0.013 + 0.001 0.011 + 0.001 46 11/18/2003 0.017 + 0.002 0.016 + 0.002 0.016 + 0.002 0.017 + 0.002 0.015 + 0.002 47 11/25/2003 0.022 + 0.002 0.020 + 0.002 0.021 + 0.002 0.024 + 0.002 0.018 + 0.002 48 12/212003 0.017 + 0.001 0.017 + 0.002 0.019 + 0.002 0.017 + 0.002 0.019 + 0.002 49 12/9/2003 0.010 + 0.001 0.011 + 0.001 0.015 _ 0.002 0.011 + 0.001 0.011 + 0.001 50 12116/2003 0.010 + 0.001 0.011 + 0.001 0.012 + 0.001 0.010 + 0.001 0.011 + 0.001 51 12/22/2003 0.017 + 0.001 O 0.014 + 0.002 0.015 + 0.002 0.014 + 0.002 0.017 + 0.002 52 12/30/2003 0.017 + 0.001 0.014 +/- 0.002 0.015 +/- 0.002 0.014 + 0.002 0.017 + 0.002

• Sample deviation.

• • Control location. B-13

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2003 (pG Vm 3 t 1sigma)

STATION #

Week,,# End Qqate0 _M_22________ ___ __ __ _______

1 1/6/2003 0.012 + 0.001 0.014 + 0.001 0.014 + 0.001 0.012 + 0.001 2 1/13/2003 0.012 + 0.001 0.014 + 0.001 0.013 + 0.001 0.012 + 0.001 3 1/2112003 0.016 + 0.001 0.017 + 0.001 0.017 + 0.001 0.019 + 0.002 4 1/27/2003 0.017 + 0.002 0.015 + 0.002 0.015 + 0.001 0.012 + 0.002 5 2/3/2003 0.018 + 0.001 0.016 + 0.002 0.018 + 0.001 0.025 + 0.002 6 2/10/2003 0.013 + 0.001 0.016 + 0.002 0.014 + 0.001 0.015 + 0.002 7 2/18/2003 0.015 + 0.001 0.017 + 0.001 0.015 + 0.001 0.017 + 0.001 8 2/24/2003 0.014 + 0.001 0.014 + 0.002 0.014 + 0.001 0.013 + 0.002 9 3/3/2003 0.022 + 0.002 0.021 + 0.002 0.021 + 0.001 0.023 + 0.002 10 3/10/2003 0.018 + 0.001 0.022 + 0.002 0.020 + 0.001 0.021 + 0.002 11 3117/2003 0.018 + 0.001 0.021 + 0.002 0.020 + 0.001 0.019 + 0.002 12 3/24/2003 0.011 + 0.001 0.013 + 0.001 0.012 + 0.001 0.013 + 0.002 13 3/31/2003 0.010 + 0.001 0.012 + 0.001 0.012 + 0.001 0.011 + 0.001 14 4/7/2003 0.012 + 0.001 0.013 + 0.001 0.014 + 0.001 0.014 + 0.002 15 4/14/2003 0.012 + 0.001 0.013 + 0.001 0.014 + 0.001 0.013 + 0.002 16 4/21/2003 0.021 + 0.002 0.020 + 0.002 0.019 + 0.001 0.019 + 0.002 17 4/28/2003 0.011 + 0.001 0.011 + 0.001 0.010 + 0.001 0.009 + 0.001 18 5/5/2003 0.013 + 0.001 0.012 + 0.001 0.012 + 0.001 0.017 + 0.002 19 5/12/2003 0.010 + 0.001 0.010 + 0.001 0.012

• 0.001 0.011 + 0.001 20 5/19/2003 0.008 + 0.001 0.005 + 0.001 0.005 + 0.001 0.004 + 0.001 21 5/27/2003 0.007 + 0.001 0.007 + 0.001 0.009 + 0.001 0.008 + 0.001 22 6/2/2003 0.009 + 0.001 0.009 + 0.001 0.008 + 0.001 0.009 + 0.001 23 6/9/2003 0.012 + 0.001 0.014 + 0.002 0.009 + 0.001 0.012 + 0.001 24 6/16/2003 0.010 + 0.001 0.012 + 0.001 0.009 + 0.001 0.009 + 0.001 25 6/23/2003 0.007 + 0.001 0.004 + 0.002 0.005 + 0.001 26 6/30/2003 0.018 + 0.001 O0.016 + 0.002 0.021 + 0.002 0.024 + 0.002

• Sample deviation.

• • Control location. B-14

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2003 (pCi/m3 +/- 1 sigma)

STATION #

WteeK#,W End Patea M1M922 M 94 9I2 27 717/2003 0.017 + 0.001 0.020 + 0.002 0.018 + 0.002 0.021 + 0.002 28 7/14/2003 0.012 + 0.001 0.014 + 0.002 0.014 + 0.001 0.010 + 0.002 29 7/21/2003 0.015 + 0.001 0.015 + 0.002 0.015 + 0.001 0.015 + 0.002 30 7/28/2003 0.013 + 0.001 0.016 + 0.002 0.014 + 0.001 0.017 + 0.002 31 8/4/2003 0.011 + 0.001 0.011 + 0.001 0.011 + 0.001 0.010 + 0.001 32 8/11/2003 0.010 + 0.001 0.010 + 0.001 0.009 + 0.001 0.011 + 0.001 33 8/18/2003 0.011 + 0.002 0.014 + 0.002 0.014 + 0.001 0.016 + 0.002 34 8/25/2003 0.020 + 0.002 0.018 + 0.002 0.019 + 0.001 0.017 + 0.002 35 912/2003 0.012 + 0.001 0.014 + 0.001 0.016 + 0.001 0.016 + 0.002 36 9/8/2003 0.011 + 0.001 0.012 + 0.002 0.012 + 0.001 0.012 + 0.002 37 9115/2003 0.013 + 0.002 0.012 + 0.001 0.012 + 0.001 0.016 + 0.002 38 9/22/2003 0.016 + 0.001 0.019 + 0.002 0.016 + 0.001 0.018 + 0.002 39 9/29/2003 0.016 + 0.001 0.014 + 0.001 0.022 + 0.002 0.020 + 0.002 40 10/7/2002 0.009 + 0.001 0.013 + 0.002 0.010 + 0.001 0.009 + 0.001 41 10/14/2003 0.027 + 0.002 0.024 + 0.002 0.025 + 0.002 0.028 + 0.002 42 10/20/2003 0.011 + 0.001 0.014 + 0.002 0.014 + 0.001 0.014 + 0.002 43 10/28/2003 0.013 + 0.001 0.010 + 0.001 0.013 + 0.001 0.015 + 0.002 44 11/3/2003 0.018 + 0.001 0.019 + 0.002 0.018 + 0.001 0.019 + 0.002 45 11/12/2003 0.014 + 0.001 0.014 + 0.002 0.014 + 0.001 0.015 + 0.002 46 11/17/2003 0.013 + 0.001 0.013 + 0.001 0.012 + 0.001 0.009 + 0.001 47 11/24/2003 0.022 + 0.002 0.023 + 0.002 0.025 + 0.002 0.030 + 0.002 48 12/1/2003 0.019 + 0.001 0.015 + 0.002 0.018 + 0.001 0.020 + 0.002 49 12/8/2003 0.011 + 0.001 0.012 + 0.001 0.010 + 0.001 0.010 + 0.001 50 12/16/2002 0.011 + 0.001 0.010 + 0.001 0.012 + 0.001 0.011 + 0.001 51 12/23/2003 0.016 + 0.001 0.011 + 0.001 0.015 + 0.001 0.017 + 0.002 52 12/29/2003 0.016 + 0.001 0.012 + 0.001 0.015 +/- 0.001 0.017 + 0.002

• Sample deviation.

• • Control location. B-15

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2003 (RESULTS IN UNITS OF 104 pCVm 3 +/-1 SIGMA)

1. 4 ALGONQUIN GAS LINE GJRADIONUCLIDES~t PMRSTQUARTER4 itSECONDQUARTERS OTHIRD QUARTERJA iFOURTH-QUARTER Be-7^ 102+/-9.71 88.23+/-7.46 107+/-7.51 83.4+/-10.67 K-40* <4.58 17.77+/-4.62 30.05+/-4.36 <4.1 Mn-54 <0.59 <0.22 <0.34 <0.6 Co-58 <0.47 <0.5 <0.48 <0.38 Fe-59 <2.19 <1.01 <1.67 <2.5 Co-60 <0.6 <0.21 <0.47 <0.41 Zn-65 <0.56 <0.96 <1 <2.05 Zr-95 <0.93 <0.62 <0.99 <1.16 Nb-95 <0.94 <0.9 <0.87 <1.23 Ru-103 <0.84 <0.48 <0.61 <1.09 Ru-106 <4.43 <3.71 <3.04 <5.64 1-131 <8.78 <5.21 <14.17 <6.96 Cs-134 <0.33 <0.38 <0.36 <0.5 Cs-137 <0.22 <0.22 <0.32 <0.4 Ba/La-1 40 <4.49 <2.41 <4.93 <3.97 Ce-141 <0.67 <0.66 <1.2 <1.21 Ce-144 <1.59 <1.2 <1.39 <2.26 Ra-226* <4.11 <4.31 <5.36 <7.13 Ac/Th-228* <0.868 <0.81 <0.9 <2.39 OTHERS <Lb <L, <LC

1. 5 NYU TOWER ORADIONUCUDESZ OI1lRST.OUARTE-Rw RSECOND-QUARTER1~, PTHIRD'QUARTERO, 4 FOURTh O)UARTERS Be-7* 99.8+/-9.24 79.96+/-7.2 99.29+/-10.11 96.17+/-10.79 K-40* 22.05+/-6.26 <1.87 3.39 <7.8 Mn-54 <0.54 <0.29 <0.38 <0.58 Co-58 <0.57 <0.42 <0.76 <1.08 Fe-59 <1.46 <2.15 <3.06 <1.7 Co-60 <0.49 <0.4 <0.54 <0.52 Zn-65 <1.12 <0.86 <1.11 <1.72 Zr-95 <0.93 <0.51 <1.23 <1.77 Nb-95 <1.05 <0.68 <1.36 <1.1 Ru-103 <0.71 <0.54 <0.95 <1.37 Ru-106 <3.39 <3.79 <3.66 <7.39 1-131 <8.77 <6.04 <17.93 <6.66 Cs-134 <0.44 <0.43 <0.45 <0.57 Cs-1 37 <0.27 <0.35 <0.3 <0.48 BalLa-140 <7.21 <2.77 6.52 <4.85 Ce-141 <1.06 <0.85 <1.17 <1.63 Ce-144 <1.72 <1.44 <1.49 <3.6 Ra-226* <4.76 <4.89 <6.74 <10.25 AcrTh-228* <1.34 <1.07 <1.12 <3.33 OTHERS <y Lc <b <

• Indicates naturally occurring.

• 'Less than' values expressed as Critical Level (U,) unless otherwise noted. B-16

• • • Reported as sample LLD.

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2003 (RESULTS IN UNITS OF 1O pCVm 3 +/- 1 SIGMA)

1. 27 CROTON POINT JiOUARTERF USECOND QUARTER'UIRD'QUARTER~ FURTH .aUARTERa1 Best7 Ins8.6i9.35 1M+7-82 1 1 1.8+/-8.88 93.37+/-f1 3.71 K-40* 18.57+/-4.79 21.46*4.44 21.63+/-4.66 <8.22 Mn-54 <0.3 <0.41 <0.43 <0.51 Co-58 <0.26 <0.4 <0.42 <1.02 Fe-59 <2.72 <1.31 <2.24 <5.95 Co-60 <0.4 <0.29 <0.48 <0.81 Zn-65 <0.71 <0.81 <0.79 <1.29 Zr-95 <1.19 <0.72 <0.97 <1.15 Nb-95 <0.83 <0.85 <1.04 <1.1 Ru-1 03 <0.76 <0.58 <0.75 <0.99 Ru-106 <4.44 <.c2s <3.17 <3.87 1-131 <9.55 <5.33 <10.38 <7.71 Cs-134 <0.49 <0.36 <0.5 <0.77 Cs-137 <0.38 <0.35 <0.15 <0.36 BalLa-140 <6.74 <2.67 <7.82 <8.94 Ce-141 <1.12 0.96 <1.02 <0.98 Ce-144 <1.67 <1.i3 <1.36 <2.49 Ra-226* <6.55 <4.06 <4.16 <9.03 AcrTh-228* <0.62 <0.92 <1.25 <2.02 OTHERS <L <1bc <I<c

1. 94 IP TRAINING CENTER XRADIONUCUDESW 2FIRST..QUARTER;t. USECOND.'QUARTERt PT.-HIRD QUARTER.Wl AFOURTH QUARTER4 Be-7* 98.71+/-9.81 92.01+/-7.55 139.2+/-9.47 85+/-11.71 K-40* <2.64 16.43+/-3.98 14.96+/-4.33 <5.78 Mn-54 <0.5 <0.32 <0.4 <0.31 Co-58 <0.57 <0.47 <0.65 <1.09 Fe-59 <1.94 0.960 <1.58 <4.87 Co-60 <0.286 <0.18 <0.56 <0.46 Zn-65 <0.67 <0.92 <0.94 <0.99 Zr-95 <1.61 <0.75 <0.97 <0.92 Nb-95 <0.89 <0.63 <0.74 <1.69 Ru-103 <0.8 <0.6 <0.59 <0.67 Ru-106 <2.56 <2.71 <2.92 <5.44 1-131 <7.68 <4.62 <14.71 <6.74 Cs-134 <0.52 <0.39 <0.48 <0.49 Cs-137 <0.41 <0.21 <0.38 <0.66 BalLa-140 <6.76 <3.6 <8.58 <6.25 Co-141 <1.12 <0.86 <1.08 <1.3 Ce-144 <1.21 <1.18 <1.34 <2.23 Ra-226* <5.75 <4.43 <4.12 <8.93 AcrTh-228* <0.83 <0.92 <0.94 <2.18 OTHERS <Lc <L0 <L 0 <Le

• Indicates naturally occurring.

- Less than values expressed as Critical Level (L.). unless otherwise noted. B-1 7 Reported as sample LLD.

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES' - 2003 (RESULTS IN UNITS OF 104 pCVm 3 +/- 1 SIGMA)

1. 95 METEOROLOGICAL TOWER IARTER1I¶ =ECOND QUARTERXITTHIRD QUARFTER I ~ FOURTH Q)UARTE-R=

Be 110.4+/-10.61 98.84+/-8.16 106.9+/-8.46 79.51+/-10.96 K-40* 31.09+/-6.67 32.3+/-5.87 25.3+/-4.82 <7.53 Mn-54 <0.42 <0.34 <0.23 <0.51 Co-58 <0.63 <0.52 <0.63 <0.93 Fe-59 <1.38 <1.76 <1.49 <3.21 Co-60 <0.38 <0.37 <0.45 <0.86 Zn-65 <1.35 <1.08 <0.95 <1.22 Zr-95 <1.13 <0.85 <1.07 <0.92 Nb-95 <1.07 <0.87 <1.05 <1.41 Ru-103 <0.78 <0.72 <0.69 <0.44 Ru-106 <4.56 <3.54 <2.95 <8.3 1-131 <6.92 <5.58 <10.66 <5.83 Cs-134 <0.54 <0.42 <0.4 <0.65 Cs-1i37 <0.42 <0.36 <0.28 <0.55 Ba/La-1 40 <4.13 <4.34 <8.03 <7.15 Ce-1 41 <1.23 <0.85 <1.06 <1.07 Ce-144 <1.92 <1.57 <1.45 <1.98 Ra-226* <6.36 <4.94 <4.86 <6.3 Aclrh-228* <1.81 <1.24 <1.31 <2.04 OTHERS <Lc <Lc <Lc <Lc

1. 22 LOVETT POWER PLANT YMRADlONUCUDESTI WFIRSMAGUARTERM NSECOND CIUARTER* tOTHIRD:QUARTERM ^FOURTHQUARTERM Be-7* 91.82+/-8.63 84.4+/-7.57 84.4+/-7.57 70.99+/-8.79 K-40* 20.85+/-4.55 22.78+/-4.97 22.78+/-4.97 <3.94 Mn-54 <0.3 <0.36 <0.36 <0.52 Co-58 <0.71 <0.33 <0.33 <0.64 Fe-59 <2.25 <2.41 <2.41 <2.39 Co-60 <0.43 <0.31 <0.31 <0.36 Zn-65 <0.76 <1.01 <1.01 <0.64 Zr-95 <0.505 <1.08 <1.08 <0.69 Nb-95 <0.94 <0.79 <0.79 <1.07 Ru-103 <0.74 <0.43 <0.43 <0.84 Ru-106 <4.48 <2.13 <2.13 .c3.5 1-131 <6.49 <4.63 <4.63 <4.61 Cs-134 <0.36 <0.4 <0.4 'o.57 Cs-1 37 <0.27 <0.2 <0.2 <0.27 Ba/La-1 40 <4.71 <4.64 <4.64 < i3.17 Ce-141 <0.99 <0.81 <0.81 <0.82 Ce-144 <1.61 <1.21 <1.21 <1.32 Ra-226* <5.25 <4.52 <4.52 <4.86 Ac/Th-228* <1.33 <1.21 <1.21 1.4 OTHERS <Lc <c <Lc <Lc

• Indicates naturally occurring.

• • 'Less than' values expressed as Critical Level (Lv), unless otherwise noted. B-1 8

• • • Reported as sample LLD.

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2003 (RESULTS IN UNITS OF 104 pCrmn3 +/-1 SIGMA)

1. 23 ROSETON

'WFHIRO QUARTER~t ISFOURTHQ UARTERN Be-7* 104+/-9.62 77.75+/-7.01 116.6+/-8.38 88.17+/-12.33 K <3.41 25.08+/-4.3 17.72+/-3.66 50.52+/-10.79 Mn-54 <0.45 <0.35 <0.33 <0.82 Co-58 <0.84 <0.39 <0.63 <1.26 Fe-59 <1.92 <1.79 <2.25 <3.86 Co-60 <0.32 <0.41 <0.3 <0.71 Zn-65 <0.49 <0.65 <0.44 <1.27 Zr-95 <1.45 <0.82 <0.8 <1.19 Nb-95 <1.05 <0.87 <0.75 <1.56 Ru-103 <0.97 <0.64 <0.8 <0.69 Ru-106 <4.11 <4.12 <3.37 <3.32 1-131 <9.91 <4.84 <12 <9.77 Cs-134 <0.51 <0.33 <0.33 <0.31 Cs-137 <0.25 <0.25 <0.18 <0.49 BalLa-140 <3.48 <4.25 <8.19 <5.12 Ce-141 <1.07 <0.7 <0.85 <1.39 Ce-144 <1.41 <1.4 <1.21 <2.32 Ra-226' <6.1 <3.66 7.21 +/-3.91 <7.04 Ac/rh-228* <0.87 <0.88 <0.77 <1.32 OTHERS <Lc <L 0 <L

1. 29 GRASSY POINT IRADIONUCLIUDESt,FIRSTQUARTER7 USECOND04UARTER" FTHIRD OUARTER.V IFOURTHWOUARTER Be-7* 112.4+/-8.53 95.53+/-6.43 111.1+/-7.69 79.71+/-9.15 K-40* <2.09 8.4+/-3.23 18.56+/-3.68 <4.03 Mn-54 <0.31 <0.29 <0.2 <0.63 Co-58 <0.36 <0.3 <0.48 <0.3 Fe-59 <1.44 <1.54 <1.49 <1.78 Co-60 <0.33 <0.3 <0.33 <0.27 Zn-65 <0.77 <0.8 <0.71 <1.03 Zr-95 <0.92 <0.61 <0.91 <1.64 Nb-95 <0.66 <0.52 <0.34 <1.08 Ru-103 <0.75 <0.52 <0.58 <0.77 Ru-106 <2.65 <3.03 <2.7 <4.84 1-131 <6.09 <4.17 <8.41 <5.88 Cs-134 <0.21 <0.31 <0.32 <0.59 Cs-137 <0.22 <0.14 <0.26 <0.5 Ba/La-1 40 <3.02 1.700 <6.44 <3.75 Ce-141 <0.76 <0.61 <0.89 <1.27 Ce-144 <0.99 <1.34 <1.17 <2.19 Ra-226* <4.03 <3.73 <3.85 <6.12 AcITh-228' <0.96 <0.75 <0.79 <1.09 OTHERS <Lc < 0 <L,

• Indicates naturally occurring.

• ^ *Less than' values expressed as Critical Level (I-U, unless otherwise noted. B-1 9

• • ' Reported as sample LLD.

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2003 (RESULTS IN UNITS OF 104 pCVm3 +/-1 SIGMA)

1. 44 PEEKSKILL GAS HOLDER BUILDING FRADIONUCUDES* #FFIRSTIQUARTER* AMSECOND QUARTERA ZTHIRDnUARTERX VFOURTHQUARTERNi Be-7' l 111+/-10.32 79.51+/-7.21 112.3+/-10.35 77.91+/-13.87 K-40* 35.89+/-6.45 18.66+/-4.56 <7.5 <8.43 Mn-54 <0.42 <0.42 <0.6 <0.56 Co-58 <0.7 <0.29 <0.48 <0.74 Fe-59 <2 <0.95 <3.55 <3.58 Co-60 <0.27 <0.28 0.330 <0.83 Zn-65 <1.28 <0.98 <1.54 <1.33 Zr-95 <1.05 <1.19 <1.35 <1.39 Nb-95 <0.93 <0.91 <1.37 <1.15 Ru-103 <1.18 <0.55 <0.8 <0.77 Ru-106 <3.49 <3.6 <4.82 <4.63 1-131 <11.3 <5.54 <10.89 <11.59 Cs-134 <0.59 <0.43 <0.38 <0.39 Cs-137 <0.48 <0.3 <0.41 <0.64 BalLa-140 <4.37 <2.01 <6.03 <7.98 Ce-141 <1.15 <0.89 <1.1 <1.11 Ce-144 <1.8 <1.4 <1.77 <2.78 Ra-226* <6.06 6.36+/-3.89 <4.45 <6.55 AclTh-228^ <1.2 <0.87 <1.35 <2.07 OTHERS <Lzb Cb <b

• Indicates naturally occurring.

• • 'Less than' values expressed as Critical Level (Lc) unless otherwise noted. B-20

• ^ Reported as sample LLD.

TABLE B-8 1-131 ACTIVITY IN CHARCOAL CARTRIDGE SAMPLES - 2003*

(pCVrm3 +/- 1 sigma) r%-.- --- -A

'I<<waolc.wra/sFnn-I- -, - - - C- -- _________

• 1 1/6/2003 1<0.01291 <0.01681 <.0165 l <0.023 1 <0.022 1 <0.017 1 <0-021 = <o-ni a <n-npa 2 1/13/2003 <0.022 <0.017 <0.019 <0.018 <0.016 <0.019 <0.022 <0.014 <0.021 3 1/21/2003 <0.020 <0.017 <0.011 <0.016 <0.019 <0.021 <0.016 <0.015 <0.014 4 1/27/2003 <0.013 <0.018 <0.012 <0.015 <0.015 <0.017 <0.020 <0.015 <0.018 S 2/3/2003 <0.017 <0.018 <0.008 <0.017 <0.016 <0.015 <0.015 <0.011 <0.022 6 2110/2003 <0.017 <0.019 <0.018 <0.022 <0.019 <0.016 <0.019 <0.017 <0.016 7 2/1 8/2003 <0.018 <0.015 <0.018 <0.019 <0.015 <0.024 <0.016 <0.015 <0.028 8 2/24/2003 <0.027 <0.019 <0.020 <0.027 <0.027 <0.032 <0.027 <0.022 <0.028 9 3/312003 <0.021 <0.023 <0.021 <0.020 <0.020 <0.019 <0.022 <0.016 <0.016 10 3/10/2003 <0.016 <0.022 <0.024 <0.019 <0.023 <0.015 <0.024 <0.017 <0.031 11 3/17/2003 <0.018 <0.018 <0.020 <0.021 <0.023 <0.019 <0.025 <0.016 <0.019 12 3/24/2003 <0.016 <0.019 <0.022 <0.019 <0.017 <0.023 <0.020 <0.020 <0.022 13 3/31/2003 <0.020 <0.022 <0.021 <0.031 <0.024 <0.025 <0.019 <0.023 <0.037 14 4/7/2003 <0.016 <0.029 <0.021 <0.014 <0.029 <0.024 <0.021 <0.016 <0.024 15 4/14/2003 <0.010 <0.019 <0.024 <0.025 <0.022 <0.021 <0.021 <0.020 <0.018 16 4/21/2003 <0.014 <0.014 <0.020 <0.023 <0.018 <0.019 <0.018 <0.018 <0.027 17 4/28/2003 <0.033 <0.021 <0.022 <0.030 <0.026 <0.032 <0.014 <0.009 <0.030 18 5/5/2003 <0.026 <0.013 <0.021 <0.023 <0.023 <0.024 <0.016 <0.021 <0.022 19 5/12/2003 <0.019 <0.019 <0.026 <0.027 <0.031 <0.017 <0.028 <0.017 <0.026 20 5119/2003 <0.024 <0.021 <0.027 <0.026 <0.020 <0.021 <0.021 <0.020 <0.024 21 5/27/2003 <0.018 <0.015 <0.020 <0.027 <0.026 <0.021 <0.017 <0.019 <0.020 22 6/2/2003 <0.026 <0.028 <0.049 <0.039 <0.033 <0.030 <0.037 <0.028 <0.041 23 6/9/2003 <0.023 <0.023 <0.023 <0.023 <0.021 <0.018 <0.022 <0.014 <0.024 24 6116/2003 <0.021 <0.022 <0.016 <0.024 <0.022 <0.022 <0.026 <0.015 <0.026 25 6/23/2003 <0.016 <0.020 <0.019 <0.025 <0.019 <0.029 <0.024 <0.019 ...

26 .1 6130/2003 1 <0.033 1<0.031 <0.019 <0.026 <0.031 A <0.022 1 <0.026 <0.020 1 <0.027

• 'Less than' values expressed as sample Critical Level (K) unless otherwise noted.

" Reported as sample LLD.

... Control location.

• • • • Sample deviation. B-21

TABLE B-8 1-131 ACTIVITY IN CHARCOAL CARTRIDGE SAMPLES - 2003*

(pCvm3 +/-t1 sigma)

W-ekU nd-Datelq O-W,41W, W5W =27M- M940P W52"**Jv

-- - _ 4 27 717/2003 <0.023 <0.023 <0.018 <0.027 <0.031 <0.018 <0.018 <0.019 <0.024 28 7/14/2003 <0.038 <0.029 <0.023 <0.033 <0.031 <0.031 <0.044 <0.020 <0.022 29 7/21/2003 <0.033 <0.025 <0.025 <0.017 <0.029 <0.024 <0.030 <0.024 <0.016 30 7/28/2003 <0.021 <0.020 <0.024 <0.023 <0.032 <0.024 <0.033 <0.029 <0.044 31 8/4/2003 <0.017 <0.019 <0.019 <0.025 <0.026 <0.021 <0.031 <0.021 <0.020 32 8/11/2003 <0.01 B <0.023 <0.021 <0.023 <0.026 <0.021 <0.026 <0.024 <0.025 33 8/18/2003 <0.034 <0.020 <0.024 <0.036 <0.036 <0.061 <0.043 <0.029 <0.044 34 8/25/2003 <0.018 <0.022 <0.019 <0.025 <0.026 <0.044 <0.031 <0.023 <0.029 35 9/2J2003 <0.022 <0.038 <0.028 <0.031 <0.032 <0.022 <0.032 <0.023 <0.037 36 9/8/2003 <0.023 <0.037 <0.027 <0.037 <0.023 <0.019 <0.021 <0.018 <0.029 37 9/15/2003 <0.033 <0.028 <0.032 <0.030 <0.031 <0.030 <0.021 <0.020 <0.038 38 9/22/2003 <0.012 <0.019 <0.024 <0.024 <0.026 <0.019 <0.030 <0.014 <0.023 39 9/29/2003 <0.030 <0.042 <0.037 <0.042 <0.050 <0.043 <0.024 <0.017 <0.037 40 101712002 <0.048 <0.048 <0.025 <0.027 <0.028 <0.020 <0.025 <0.024 <0.028 41 10/14/2003 <0.020 <0.030 <0.033 <0.026 <0.023 <0.203 <0.026 <0.024 <0.026 42 10/20/2003 <0.018 <0.022 <0.022 <0.023 <0.024 <0.004 <0.032 <0.025 <0.041 43 10/28/2003 <0.024 <0.021 <0.017 <0.015 <0.021 <0.017 <0.025 <0.025 <0.025 44 11/3/2003 <0.015 <0.016 <0.020 <0.021 <0.025 <0.016 <0.021 <0.019 <0.017 45 11/12/2003 <0.031 <0.031 <0.046 <0.025 <0.016 <0.026 <0.038 <0.025 <0.043 46 11/17/2003 <0.014 <0.031 <0.023 <0.032 <0.037 <0.014 <0.017 <0.014 <0.022 47 11/24/2003 <0.020 <0.032 <0.025 <0.039 <0.027 <0.032 <0.040 <0.020 <0.026 48 12/1/2003 <0.016 <0.021 <0.010 <0.014 <0.021 <0.017 <0.021 <0.013 <0.023 49 12/8/2003 <0.016 <0.027 <0.014 <0.023 <0.023 <0.022 <0.026 <0.023 <0.020 50 12/16/2002 <0.021 <0.027 <0.031 <0.024 <0.028 <0.013 <0.019 <0.019 <0.027 51 12/23/2003 <0.023 <0.038 <0.031 <0.038 <0.035 <0.028 <0.028 <0.027 <0.025 52 12/29/2003 <0.022 <0.018 <0.015 <0.020 <0.020 <0.027 <0.021 <0.014 <0.025

• "Less than' values expressed as sample Critical Level (Lj unless otherwise noted.

• Reported as sample LLD.

• • • Control location.

• • '* Sample deviation. B-22

TABLE B-9 CONCENTRATIONS OF GAMMA EMMITERS IN HUDSON RIVER WATER SAMPLES** - 2003 (pC/L t 1 SIGMA)

1. 9 PLANT INLET (HUDSON RIVER INTAKE)

WRadlonueIldeV AftJanuarVa SFbruar iMarchWA pr U.l avUM82*=n Be <9.6 <8.31 <11.14 <10.94 <7.03 <9.6 K-40* 198.2+/-12.8 214.5+/-10.56 168.1+/-15.75 244.8+/-13.27 262.5+/-7.22 186.2+/-13.01 Mn-54 <1.14 <0.83 <1.31 <1.03 <0.55 <1.06 Co-58 <1.28 <0.93 <1.44 <1.2 <0.67 <1.4 Fe-59 <3.8 <2.71 <3.62 <2.87 <2.07 <3.07 Co-60 <1.05 <0.81 <1.21 <1.11 <0.55 <1.08 Zn-65 <2.35 <1.73 <2.66 <1.49 <0.73 <1.99 Zr-95 <2.05 <1.66 <2.14 <2.01 <1.27 <1.89 Nb-95 <1.32 <1.11 <1.65 <1.31 <0.96 <1.37 Ru-103 <1.46 <1.17 <1.07 <1.63 <1.05 <1.31 Ru-106 <9.72 <9.13 <13.7 <10.52 <5.82 <10.67 1-131 <5.73 <3.54 <5.34 <4.42 <5.91 <5.11 Cs-134 <1.03 <0.89 <1.21 <0.71 <0.37 <1.05 Cs-137 <1.05 <0.81 <1.14 <1.02 <0.56 <1.02 Ba/La-140 <4.14 <2.51 <4.34 <2.78 <1.73 <4.03 Ce-141 <2.34 <1.92 <2.59 <2.55 <1.72 <1.6 Ce-144 <6.72 <5.75 <8.01 <8.06 <4.49 <6.82 Ra-226- 88.32+/-16.6 43.23+/-14.89 82.98+/-21.66 92+/-21.94 76.43+/-10.47 120+/-18.32 Ac/Th-228* 9.43+/-2.89 5.3+/-2.09 <4.51 12.46+/-2.74 13.85+/-1.56 6.85+/-2.85

1. 10 DISCHARGE CANAL (MIXING ZONE)

RmidIonucIIdCsi 2WJahU gi! bmIebruanr*l WMnrclAam ltA!rII: l +/-%Mavlma *'Ju une3 Be <8.67 <8.94 <9.65 <7.54 <8.95 <8.19 K-40* 193.5+/-10.43 160.9+/-9.71 181.4+/-11.9 145.5+/-8.62 187.7+/-10.36 165.1+/-9.92 Mn-54 <0.78 <0.86 <1.01 <0.75 <0.79 <0.81 Co-58 <0.87 <0.97 <1.02 <0.9 <0.93 <0.89 Fe-59 <3.07 <2.85 <2.86 <2.47 <3.35 <2.75 Co-60 <0.86 <0.86 <0.9 <0.69 <0.82 <0.83 Zn-65 <1.69 <1.97 <2.22 <1.81 <1.73 <1.62 Zr-95 <1.77 <1.64 <1.92 <1.48 <1.92 <1.68 Nb-95 <1.15 <1.14 <1.22 <1.01 <1.23 <1.09 Ru-103 <1.24 <1.21 <0.79 <1.12 <1.4 <1.15 Ru-106 <8.83 <9.19 <10.12 <7.9 <8.85 <8.99 1-131 <3.97 <3.91 <3.91 <3.59 <6.93 <3.56 Cs-134 <0.83 <0.58 <0.6 <0.5 <0.86 <0.84 Cs-137 <0.82 <0.81 <1.04 <0.77 <0.83 <0.78 Ba/La-140 <2.62 <2.66 <2.99 <2.19 <4.2 <2.69 C-141 <1.96 <2.07 <2.21 <1.94 <2.33 <1.92 Ce-144 <5.71 <6.64 <6.96 <6 <5.9 <5.72 Ra-226* 61.96+/-11.24 47.55+/-15.78 66.63+/-16.21 69.78+/-13.6 61.59+/-13.71 43.09+/-16.33 AcTh-2281 7.76+/-2.19 3.84+/-2.11 <3.42 3.35+/-1.89 4.48+/-2.14 3.8+/-2.04

• Indicates naturally occurring. B-23

• • "Less than' values expressed as Critical Level (I-).

TABLE B-9 CONCENTRATIONS OF GAMMA EMMITERS IN HUDSON RIVER WATER SAMPLES** - 2003 (pCItL +/-1 SIGMA)

1. 9 PLANT INLET (HUDSON RIVER INTAKE) t i~Radlontlelldoej h%"~e&-j=A9 = I *Doemn~bM RF-7* 8.c7R <10.71 <18.33 <8.57 <10.34 <9.59 K-40* 216.5+/-10.78 209.4+/-13.5 193.3+/-23.84 207.4+/-10.53 200.1+/-13.39 382.5+/-14.34 Mn-54 <0.82 <1.06 <1.85 <0.79 <1.04 <0.95 Co-58 <0.91 c1.25 <2.05 <0.87 <1.33 <1.13 Fe-59 <2.81 <3.83 <3.99 <2.61 <3.68 <3.29 Co-60 <0.9 <1.09 <1.58 <0.85 <1.17 <1.07 Zn-65 <1.75 <2.31 <4.13 <1.8 <2.13 <1.37 Zr-95 <1.63 <1.93 <4.1 <1.73 <1.82 <2.14 Nb-95 <1.17 <1.38 <2.68 <1.15 <1.33 <1.41 Ru-103 <1.22 <1.48 <2.36 <1.27 <1.4 <1.27 Ru-106 <9.43 <10.42 <18.24 <8.65 <11.02 <9.91 1-131 <4.05 <6.48 <6.94 <3.95 <4.69 <4.54 Cs-134 <0.85 <1.03 <1.99 <0.47 <1.02 <0.61 Cs-137 <0.83 <0.96 <1.51 <0.83 <1.05 <0.92 BatLa-140 <3.19 <3.93 <3.65 <2.6 <3.45 <3.44 Ce-141 <1.96 <1.68 <4.03 <1.98 <2.17 <2.17 Ce-144 <5.88 <6.91 <12.89 <5.74 <6.87 <6.62 Ra-226* 45.88+/-13.61 71.89+/-16.37 106.5+/-31.46 47.66+/-12.79 101.5+/-16.71 106.7+/-14.53 AcrTh-228* 8.68+/-2.44 8.94+/-3.25 <6.3 8.23+/-2.45 <3.93 9.85+/-2.51

1. 10 DISCHARGE CANAL (MIXING ZONE) tRadlonficIldes~ . JuIl7t Xl .AuqustilSeptembei . October- , .Novemberge lDecemberM Be <10.13 <12.17 <19.24 <9.7 <8.11 <6.79 K 347.5+/-13.9 124.9+/-13.05 362+28.88 373.4+/-14.02 192.4+/-10.11 264.7+/-8.6 Mn-54 <1.01 <1.23 <1.94 <0.95 <0.72 <0.7 Co-58 <1.17 <1.53 <2.63 <1.01 <0.87 <0.8 Fe-59 <3.3 <4 <6.68 <3.3 <2.92 <2.01 Co-60 <0.93 <1.12 <2.19 <1.02 <0.84 <0.63 Zn-65 <1.29 <2.68 <4.69 <1.39 <1.13 <0.84 Zr-95 <1.79 <2.51 <3.43 <1.89 <1.68 <1.34 Nb-95 <1.3 <1.69 <2.61 <1.38 <1.04 <0.89 Ru-103 <1.43 <1.8 <2.36 <1.38 <1.18 <1.01 Ru-106 <10.02 <12.82 <22.05 <9.82 <9.06 <7.33 1-131 <4.78 <7.12 <6.59 <4.97 <3.38 <3.47 Cs-134 <0.65 <1.31 <1.11 <0.61 <0.47 <0.43 Cs-137 <0.98 <1.19 <1.99 <0.93 <0.83 <0.66 BalLa-140 <3.66 <4.65 <6.11 <3.48 <2.35 <1.91 Ce-141 <1.46 <2.95 <4.44 <2.19 <1.84 <1.14 Ce-144 <6.71 <9.28 <13.9 <6.51 <5.78 <5.43 Ra-226- 132.8+/-17.74 <27.99 130.5+/-42.51 107.3+/-16.2 48.44+/-15.24 91.35+/-12.78 AcTh-228* 9.96+/-2.6 <3.75 <7.14 13.68+/-2.85 7.15+/-2.51 10.88+/-1.93

• Indicates naturally occurring. B-24

"'Less than values expressed as Critical Level (I.).

TABLE B-10 CONCENTRATION OF TRITIUM IN HUDSON RIVER WATER SAMPLES*- 2003 (QUARTERLY COMPOSITES)

(pCVIL +/-1 sigma)

1. 9 PLANT INLET (HUDSON RIVER INTAKE)

(Control Location) 5tsdoucid'llT Q~rtrNWtD o~IarerRD QCiarteraI$4TH QtzartWrS TRITIUM <434 <474 <498 1 <487 l

1. 10 DISCHARGE CANAL (MIXING ZONE)

ItRadlonuclldeslidSriQUariei ;2ND-QuarteV I3RD.40arterg I4TH~Qtiarto I TRITIUM l <434 1 <474 1 <498 1 <487 l

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

TABLE B-11 GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES** - 2003 (pCVL +/- 1 sigma)

1. 7 CAMP FIELD RESERVOIR SXadlonuclideol W1January, eFebnlaztMarch l UprI 3unh WmJay3w Gross Beta 1.89+/-0.61 1.89+/-0.54 2.12+/-0.42 2.78+/-0.52 2.41+/-0.49 3.61 +/- 0.49 Be-r7 <17 <14.89 <:21.06 <16.19 <22.81 <15.12 K-40* 177.8+/-27.93 232.7+/-28.89 170.7+/-32.98 139.1+/-23.52 142.1+/-29.03 173.8+/-26.78 Mn-54 <2.32 <1.7 <2.98 <1.89 <1.94 <1.99 Co-58 <2.35 <2.15 <2.78 <2.12 <2.96 <1.94 Fe-59 <5.72 <5.86 <6.14 <5.41 <7.29 <5.81 Co-60 <2.18 <2.06 <2.45 <2.08 <1.93 <1.86 Zn-65 <4.66 <4.68 <5.66 <3.54 <6.84 <3.81 Zr-95 <3.57 <3.35 <4.33 <2.5 <4.21 <3.51 Nb-95 <2.6 <1.82 <1.98 <2.09 <2.18 <2.27 Ru-1 03 <2.31 <2.34 <2.26 <2.48 <2.86 <1.9 Ru-106 <23.84 <19.43 <24.7 <20.99 <30.57 <20.86 1-131 <0.28 <0.22 <0.26 <0.36 <0.20 <0.23 Cs-134 <1.83 <2.66 <2.61 <1.9 <3.07 <1.67 Cs-137 <1.68 <2.37 <2.16 <1.86 <2.54 <2.1 BalLa-140 <2.83 <3.01 <4.36 <3.69 <3.49 <2.98 Ce-141 <2.38 <3.32 <3.89 <3.73 <4.7 <3.34 Ce-144 <12.52 <13.87 <17.07 <12.33 <20.17 <12.18 Ra-226* 148.8+/-37.19 <43.57 <51.67 81.68+/-31.7 <60.84 63.41+/-32.23 Ac[Th-228* <7.34 <8.41 <12.24 <7.5 <9.32 <7.47

1. 7 CAMP FIELD RESERVOIR MRadfohuclIldd ftLJWVyi4 U gtJstff *$eptember';- kOctober,, 'NoVember, %Decmben6 Gross Beta 2.28+/-0.35 2.76+/-0.48 3.84+/-0.53 3.06+/-0.43 1.92 +/- 0.32 2.65 +/- 0.46 Be-7* <17 <21.8 <26.43 <18.02 <17.55 <22.99 K-40* 177.8+/-27.93 316.2+/-35.63 190.3+/-37.66 190+/-29.68 209.8+/-31.43 189.7+/-30.73 Mn-54 <2.32 <2.43 <3.23 <2.68 <2.03 <2.48 Co-58 <2.35 <2.41 <3.23 <2.46 <2.86 <2.48 Fe-59 <5.72 <6 <5.53 <5.19 <7.34 <5.98 Co-60 <2.18 <2.51 <2.67 <1.94 <2.75 <2.96 Zn-65 <4.66 <5.57 <7.1 <5.7 <7.3 <5.32 Zr-95 <3.57 <3.9 <5.1 <3.19 <4.13 <4.43 Nb-95 <2.6 <2.71 <2.67 <3.07 <2.89 <2.42 Ru-103 <2.31 <2.64 <3.31 <2.54 <2.68 <2.59 Ru-106 <23.84 <30.3 <31.27 <20.53 <25.37 <30.94 1-131 <0.29 <0.28 <0.41 <0.41 <0.38 <0.198 Cs-134 <1.83 <2.61 <3.54 <2.12 <2.28 <2.74 Cs-137 <1.68 <2.39 <3.28 <2.85 <2.03 <2.54 Ba/La-140 <2.83 <4.03 <4.52 <3.05 <4.99 <3.92 Ce-141 <2.38 <4.1 <4.96 <3.95 <3.94 <4.24 Ce-144 <12.52 <16.73 <22.66 <17.81 <16.8 <17.54 Ra-226* 148.8+/-37.19 111.3+/-49.88 <70.26 <58.58 <54.3 <60.36 Ac/Th-228* <7.34 <7.63 <8.45 <8.27 <8.49 <10.34

• Indicates naturally occurring.

• • 'Less than' values expressed as Critical Level (Lb). B-26

TABLE B-11 GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES** - 2002 (pCVL +/- 1 sigma)

1. 8 NEW CROTON RESERVOIR itadronuclidetl gJanUaT MbIruebhzarY.1 MarchlU; illi ~Mu ay wflne.

Gross Beta 2.51*0.63 2.37+/-0.54 2.87*0.45 2.44*0.43 2.90+/-0.50 2.68 +/-0.45 Be-7* <16.93 <14.94 <17.21 <20.43 <23.41 <20.23 K-40* 165.9+/-26.95 170.8+/-25.31 188.5+/-26.71 171.1+/-26.19 153+/-31.11 323.2+/-33.43 Mn-54 <1.99 <2.43 <2.01 - <1.9 <2.13 <2.75 Co-58 <1.93 <1.92 <2.17 <2 <2.05 <2.88 Fe-59 <6.33 <5.14 <5.06 <5.11 <6.1 <6.52 Co-60 <1.31 <1.59 <2.17 <2.28 <2.97 <2.42 Zn-65 <3.34 <5.46 <5.04 <4.85 <5.71 <5.72 Zr-95 <2.88 <3.58 <3.7 <3.87 <4.13 <4.17 Nb-95 <2.04 <1.49 <2.15 <2.4 <2.44 <2.28 Ru-103 <2.14 <2.36 <2.13 <2.74 <2.65 <2.83 Ru-106 <21.2 <23.12 <23.96 <26.9 <27.93 <26.28 1-131 <0.27 <0.26 <0.21 <0.32 <0.20 <0.21 Cs-134 <2.27 <2.4 <2.13 <2.33 <2.51 <2.84 Cs-137 <1.68 <2.41 <2.54 <2.29 <2.58 <2.73 Ba/La-140 <2.62 <2.71 <2.43 <3.02 <4.8 <3.37 Ce-141 <2.22 <3.86 <3.2 <3.87 <4.34 <4.11 Ce-144 <12.74 <15.85 <14.64 <14.04 <17.7 <17.5 Ra-226* 102.9+/-38.43 <55.55 <44.32 <46.01 <54.23 90.03+/-42.71 AcTrh-228* <5.7 <6 <6.64 <7.1 <8.9 <8.02

1. 8 NEW CROTON RESERVOIR tRadlonucilde', OMMINM kAkgustTm 3September rOctobobri. tNldiiembea LDecemberl Gross Beta 1.98*0.34 2.64*0.48 3.18*0.50 3.32+/-0.44 2.76 +/- 0.45 2.61 +/- 0.46 Be-7* <19.98 <14.65 <28.84 <22.75 <17.89 <23.99 K-40* 140.7+/-23.99 156.5+/-27.19 298.7+/-49.54 117.4+/-27.94 100.8+/-23.33 120.9+/-28.17 Mn-54 <2.32 <1.7 <3.21 <1.79 <1.88 <2.73 Co-58 <2.49 <2.01 <3.34 <1.69 <2.32 <2.48 Fe-59 <3.87 <5.42 <10.33 <7.97 <4.63 <8.09 Co-60 <2.25 <3.02 <3.48 <1.71 <1.38 <3.1 Zn-65 <4.82 <4.4 <9.2 <6.15 <4.19 <6.11 Zr-95 <3.51 <3.64 <4.99 <4.67 <3.89 <5.01 Nb-95 <2.27 <1.91 <3.48 <2.83 <2.45 <3.41 Ru-i 03 <2.47 <2.38 <3.38 <2.49 <2.56 <2.95 Ru-106 <18.27 <20.23 <30.73 <29.07 <25.42 <27.03 1-131 <0.34 <0.27 <0.31 <0.31 <0.49 <0.200 Cs-134 <2.48 <2.25 <3.73 <2.46 <1.84 <1.93 Cs-137 <1.71 <2.1 <3.62 <2.17 <2.13 <2.52 Ba/La-140 <4.18 <3.42 <5.36 <3.69 <4.24 <1.94 Ce-141 <4.21 <3.5 <5.22 <4.77 <3.92 <4.68 Ce-144 <17.72 <12.65 <22.6 <16.01 <14.09 <19.24 Ra-226- <53.89 166.7+/-36.16 <78.58 <52.98 <51.45 127.5+/-47.04 AcrTh-228' <5.5 <7.01 <14.89 <7.45 <6.26 <10.69

• Indicates naturally occurring.

• • 'Less than values expressed as Critical Level (LC. B-27

TABLE B-12 CONCENTRATION OF TRITIUM IN DRINKING WATER SAMPLES*- 2003 (QUARTERLY COMPOSITES)

(pCV/L t 1 sigma)

1. 7 CAMP FIELD RESERVOIR I TRITIUM l <435 1 <465 1 <498 l <469

1. 8 NEW CROTON RESERVOIR ICRadI~oht irt I TRITIUM l <435 1 <465 1 <498 r <469

• "Less thanr values expressed as Critical Level (Lj. B-28

TABLE B-13 CONCENTRATION OF GAMMA EMITTERS IN SHORELINE SOIL SAMPLES**-2003 (pCi/Kg ,dry + 1 sigma)

1. 17 OFF VERPLANCK i

idlectibn Date iI aSLK4l0WIt4C6.60OWII .Cs.134JdiCsY137 6/10/2003- 16980+545 <18.69 <12.22 kRa-226*AzI hAct-1228n-1178.4+13.911179.45+232.41497.3+47.41I t t1er

<c 9/16P2003' 19063+402 <27.79 <24.06 142.8+14.0 1396.3+235 629.7+531 <LI

1. 28 LENTS COVE trColbect2on 1 KK0.4 6 I-3se Ce-134i 3Ca-137t 1Ra226!*v' iAcrh-228'4 =ithers-#

6/10/2003rn 13190+390.62 <27.4 <2567 49.58+14.47 2465.5+308.6 1126.5+69.7 <Lc 9/17I2003*- 16510_967.5 1 <41.26 <50.57 <50.09 3826+897 1204+170 <Lc

1. 50 MANITOU INLET (control location)

Collectlon'DateI l~fw ~ X0 ~WC. O 48Cs-134b s4 7 . 2 ~ I~ A I h2 V~ -.,Othem v 610/2003~ 12250+723 <32.06 <26.03 79.61+31.82 3873+693 1465+156 <Le 9t16/20O3" 111900+866.3 <58.34 <39.36 <46.83 3837+867 1608+189 <Lc

1. 53 WHITE BEACH e _ [W OthersU 6/10/2003- 9034+374 <15.3 <9.09 <15.42 932.6+216 95.77+37.9 <Lc 9/16t2003m 7079+589 <21.78 <21.09 <25.26 641.7+289 <108 <L,

1. 84 COLD SPRING

__ __ __ __ _ __ _ __ _ __ _ _ __ _ _ _ _ _(c on tro l locatio n)_ _ _ _ _ __ _ _ _ _ _

WColhectbn Date I UK a4 0 (*XAao60i WCs.37, mCs-134W! a-26V-1

- Ac/Th-228*,w.OtheM 6I10/2003-* 37235+539.4 j <28.06 j <23.25 165.97+12.571 1270.5+230.5 635.2+57.8 <Lc 9f117/2003 4 36720+1233 <41.26 <34.46 1 <34.46 1333+532 460.1+/-108 1 <L

• Indicates naturally occurring.

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

... Indicates the average of the positive sample results reported for samples with recounts performed. B-29

TABLE B-14 t

CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION' - 2003 (pCUKg, wet 1 sigma)

1. 23 Roseton**

May June Pe-7 230.9*37.92 452.1*37.96 443+/-39.01 Be-r 1618+/-66.11 1416+/-56.91 2404+/-49.03 K-0 7348+/-195 6934+/-156.6 5274+/-138.2 K-40 5154+/-164.3 8201+/-180.4 5812+/-11 1 Mn-54 <5.98 <5.2 <4.8 Mn-54 <5.95 <5.72 <3.67 Co-58 <6.45 <5.43 <4.53 Co-58 <6.15 <5.75 <3.64 Fe-S9 <19.31 <16.95 <14.58 Fe-59 <16.98 <17.43 <11.74 Co-60 <6.79 <6.03 <4.79 Co-60 <5.62 <6.36 <4.12 Zn-65 <17.27 <14.9 <12.81 Zn-65 <17.31 <14.69 <9.69 Zr-95 <10.87 <9.27 <9.54 Zr-95 <9.9 <11.46 <5.61 Nb-O <6.05 <5.32 <5.44 Nb-95 <5.86 <5.79 <.42 Ru-103 <5.46 <5.22 <4.89 Ru-103 <5.42 <5.15 <3.11 Ru-106 <59.66 <56.74 <48.14 Ru-106 <63.09 <62.55 <35.93 1-131 <7.48 <5.62 <5.46 1-131 <8.22 <7.17 <4.24 Cs-134 <6.25 <3.72 <5.75 Cs-134 <6.55 <6.34 <2.39 Cs-137 <6.41 <5.52 <5.3 Cs-137 <5.96 <5.9 <3.29 Ba/La-1 40 <7.97 <6.91 <6.37 Da/La-140 <10.62 <4.97 <4.51 Ce-141 <5.08 <6.77 <6.17 Ce-141 <7.01 <7.22 <5 Ce-14 <30.01 <30.4 <26.85 Ce-144 <29.74 <29.12 <21.58 Ra-226' 408.9+/-84.66 139.1+/-69.8 237.9I81.44 Ra-2261 189.3+/-B3.19 144.5+/-87.19 141.2+/-48.29 AcTrh-228' <24.95 <17.74 33.22+/-13.54 ActTh-228- <24 44.31+/-17.24 <13.29 July August "da$Qe Sb M De-7 205.6+/-43.53 531.1+/-75.08 538.3+/-55.77 Be-7 834.3+/-47.06 1413+/-64.98 1783+/-63.38 K 7892+/-197.5 10420t307.8 8371+/-t212.3 K 6447+/-163.2 8770+/-205 5159+/-149.3 Mn-54 <6.35 <10.66 <7.28 Mn-54 <5.39 <6.61 <5.92 CO_58 <6.36 <11.73 <8.04 Co-58 <5.82 <6.83 <5.79 Fe-59 <24.08 <32.9 <24.94 Fe-59 <16.89 <20.48 <18.03 Co-60 <8.97 <10.27 <8.91 Co-60 <6.59 <7.21 <6.05 Zn-65 <15.93 <28.49 <20.93 Zn-65 <13.81 <18.04 <16.01 Zr-95 <12.36 <18.51 <12.96 Zr-95 <10.97 <11 <9.56 Nb-95 <7.51 <10.36 <7.68 Nb-95 <5.54 <6.87 <5.63 Ru-1OS <6.35 <9.11 <6.98 Ru-103 <5.58 <6.22 <5.74 Ru-106 <75.1 <111.2 <82.8 Ru-106 <59.31 <66.35 <61.65 1-131 <8.21 <13.54 <9.73 1-131 <6.14 <8.48 <6.83 Cs-134 <8.13 <11.47 <5.51 Cs-134 1 <3.98 <7.45 <4.14 Cs-137 <6.71 <9.72 <8.28 Cs-137 <5.36 <6.19 <6.05 Ba/.a-140 <9.72 <10.4 <12.1 Ba/L-140 <7.49 <7.79 <7.86 Ce-141 <9.03 <12.42 <10.81 Ce-141 <7.41 <8.39 <7.75 Ce-144 <34.86 <49.88 <41.28 Ce-144 <30.39 <30.43 <34.7 Ra-226' 282*88 574.1+/-144.9 457.5+/-112.1 Rs-226- <100.5 612.2+/-92.44 287.7+/-80.53 Ac/Th-228- <24.55 <46.34 38.61+/-L20.69 ActTh-228- 29.38+/-15.08 <22.09 <21.11

• Indicates naturally occurring.

- Indicates control location.

""Less than values expressed as Critical Level (L.J. B-30

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION** - 2003 (pCi/Kg, wet +/-1 sigma)

1. 23 Roseton (continued)**

September October Be-r 1224+/-73.43 1105*60.24 1075+/-95.4 Be-7' 2213+/-60.32 4515+/-141 1551+/-80.42 K-4 7292+/-225.9 4882+/-157.3 7502+/-312.5 K 8649+/-140.9 13170+/-305.7 6557+/-202.7 Mn-54 <7.65 <6.08 <5.68 Mn-54 <5.75 <11.05 <7.6 CO-58 <8.74 <6.15 <9.69 Co-58 <5.5 0<1237 <8.32 Fe-59 <25.43 <16.92 <32.45 F"9 1 <17.45 <38.7 <21.96 Co-60 <8.59 <6.92 <11.21 Co-60 <5.16 <14.51 <9.42 Zn-65 <20.45 <15.13 <26.62 Zn-65 <8.44 <33.5 <20.57 Zr-g <14.79 < 1.75 <17.67 Zr-95 <10.61 <22.34 <12.92 Nb-95 <9.49 <7.25 <10.38 Nb-O95 <6.35 <14.06 <6.82 Ru-103 <7.94 <6.66 <9.2 Ru-103 <5.35 <12.81 <7.7 RU-106 <79.7 <63.62 <103.4 Ru-106 <55.35 <123.9 <74.91 1-131 <13.67 <10.06 <10.23 1-131 <14.58 <29.34 <18.51 Ca-134 <8.18 <7.59 <13.65 Cs-1 34 <3.82 <13.62 <7.84 Cs-137 <8.27 <6.58 <10.61 C.-137 <5.09 <11.47 <7.02 Ba/La-i 40 <12.07 <10.44 <9.8 Ba/La-140 <9.64 <25.95 <15.12 Ce-141 <10.62 <8.97 <12.34 Ce-141 <9.56 <17.16 <9.79 Cr-144 <38.04 <34.86 <51.24 Ce-44 <32.49 <59.12 <34.98 Ra-226- 246.8+/-106.6 320.7+/-109.2 <196.4 Ra-226- 394.7*81.62 932.2+/-175.4 510.4+/-106.7 AcITh-228- 37.73+/-22.93 <24.37 <36.32 AcITh-228 87.22+/-15.18 93.02+/-33.99 <26.31

• Indicates naturally occurring.

- Indicates control location.

- 'Less than' values expressed as Critical Level (L-J B-31

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2003 (pCVlKg, wet +/- 1 sigma)

1. 94 IPEC Training Center May June aNMI rswoot ME Be-r 132.1+/-30.78 79.91+/-26.18 162+/-37.19 Be-7 200+/-56.95 1534+/-39.51 3281+/-70.69 K 5513+/-138.6 4811+/-1 21.4 5385+/-153.2 K-40 9344+/-234.6 7874+/-110.6 7545+/-156.1 Mn-54 <4.68 <4.45 <5.98 Mn-54 <8.74 <3.67 <5.15 co-Ss <4.68 <4.48 <6.04 Co-s <8.75 <3.63 <5.16 Fe-59 <13.2 <13.63 <19.05 Fe-59 <28.86 <10.34 <16.5 Co-60 <4.95 <4.66 <7.39 Co-60 <10.22 <3.75 <5.22 Zn-65 <11.76 <10.4 <15.51 Zn-65 <23.31 <9.67 <12.86 Zr-95 <8.34 <7.76 <9.28 Zr-95 <15.26 <6.41 <8.54 Nb-95 <4.8 <4.11 <6.34 Nb-95 <8.59 <3.68 <4.78 Ru-103 <4.36 <4.19 <5.37 Ru-103 <8.24 <3.65 <4.18 Ru-106 <52.62 <43.19 <61.95 Ru-106 <92.14 <33.16 <43.87 1-131 <5.22 <5.12 <6.9 1-131 <9.8 <4.11 <6.29 Cs-134 <5.62 <4.77 <6.82 Cs-134 <10.21 <2.49 <5.3 Cs-137 <4.51 <4.19 <6.23 Cs-137 <8.76 <3.51 <4.6 Ba/L-ji140 <4.67 <5.24 <6.54 B/SLa-140 <10.28 <3.83 <5.22 Ce-141 <6.17 <5.5 <8.08 Ce-141 <10.73 <3.36 <6.52 Ce-144 <25.87 <19.84 <32.54 Ce-144 <43.01 <21.38 <22.65 Ra-226* 168.2+/-76.61 347+/-55.2 186.2+/-87.34 Ra-2261 502.9+/-134.7 257.4+/-51.56 402.6+/-69.68 AcTrh-228 <17.93 <16.52 45.96+/-18.02 Actrh-228- 115.9+/-28.18 42.33+/-10.51 40.17+/-14.85 July August on die, a aIPp d0loncUltde, MRagwed _____

Be-7' 629.1*48.19 532.3+/-49.72 1286+/-71.3 Be-7 1489+/-58.56 449.6+/-37.68 1805+/-49.25 K 9821+/-210.2 4481 +/-148.7 9370+/-247.3 K-40 9063+/-162.6 4342+/-122.6 7713+/-124.5 Mn-54 <7.06 <5.47 <7.51 Mn-s4 <5.88 <6.27 <4.42 Co-Ss <6.39 <5.72 <8.27 Co-58 <6.44 <6.67 <4.57 Fe-59 <20.34 <17.88 <24.01 Fe-59 <18.32 <16.08 <13.84 Co-60 <7.79 <6.96 <8.03 Ce-60 <6.97 <6.03 <4.8 Zn-65 <20.26 <14.74 <21.41 Zn-65 <9.09 <12.31 <6.59 Zr-95 <11.42 <11.96 <12.43 Zr-95 <10.25 <9.58 <7.46 Nb-95 <6.05 <5.97 <4.27 Nb-95 <6.32 <5.55 <4.61 Ru-103 <6.35 <5.59 <6.78 Ru-103 <6.71 <5.12 <4.58 Ru-106 <70.27 <70.64 <80.25 Ru-106 <59.5 <54.11 <42.79 1-131 <8.14 <7.81 ' <9.87 1-131 <7.46 <7.71 <6.81 Cs-134 <7.38 <7.67 <8.44 CS-134 <4.36 <3.66 <3.07 Cs-137 <6.51 <6.79 <7.94 Cs-137 <5.74 <4.99 <4.4 BAL-140 <8.74 <9.06 <10.15 Ba/La-1 40 <6.73 <8.83 <5.47 Ce-141 <9.19 <8.38 <9.2 Co-141 <8.23 <6.8 <6.56 Ce-144 <36.43 <34.37 <d6.12 Ce-144 <35.83 <26.82 <25.76 Ra-2261 369.6+/-94.71 342.7t97.23 508.6+/-110.8 Ra-226- 558.6+/-99.9 298.8+/-70.3 388.6+/-70.84 Ac/rh-228 <24.21 65.91+/-19.24 50.37+/-22.31 ArJrh-228- 86.95t20.09 43.64+/-15.74 85.48+/-14.33

• Indicates naturally occurring.

• ¢ Indicates control location.

• - Less than' values expressed as Critical Level (LC). B-32

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION' - 2003 (pCVKg, wet +/-1 sigma)

1. 94 IPEC Training Center (continued)

September October

,onadrwde l Ge Lmea N _____

_oklenr Radlo wxuciekS.11t9 d,. o I ___WP

,Od __Or Be.- 1023+/-93.75 733.4+/-105.9 2231+/-150.6 Be-7 1 4388+/-103.5 3356+/-94.46 2708+/-86.53 K-40 5673+/-238.9 7072+/-381.5 7734+/-380.2 K 7765+/-184.9 7295+/-183 4208+/-143.7 Mn-54 <10.93 <13.44 <14.43 Mn-54 <6.25 <7.14 <6.2 Co-5J <9.78 <12.76 <16.03 Co-58 <6.4 <7.26 <7.04 Fe-59 <27.16 <38.72 <53.18 Fe-59 <21.94 <24.94 <20.29 Co-60 <9.62 <16.16 <11.79 Co-60 <6.99 <7.49 <6.91 Zn-65 <28.83 <30.44 <41.26 Zn-65 <17.13 <17.41 <15.91 Zr-95 <17.54 <22.31 <22.96 Zr-95 <12.1 <14.47 <11.06 Nb-95 <11.89 <13.94 <14.42 Nb-95 <7.12 <8.4 <8.66 Ru-103 <11.78 <13.79 <12.17 Ru-103 <7.76 <7.63 <7.05 Ru-106 <103.2 <112.2 <157.4 Ru-106 <67.87 <69.59 <70.67 1-131 <13.09 <17.08 <18.05 1-131 <18.83 <19.21 <19.54 Cs-134 <7.49 <14.29 <14.67 Cs-134 <7.51 <7.04 <6.43 Cs-137 <10.76 <12.82 <14.98 Cs-137 <5.86 <6.65 <8.73 Ba/La-140 <12.86 <23.36 <12.07 Ba/La-140 <12.02 <11.79 <14.82 Ce-141 <14.48 <15.88 <19.38 Ce-141 <11.4 <10.3 <11.48 Ce-144 <62.09 <62Z64 <80.67 Ce-144 <34.68 <34.92 <34.17 Ra-226- 382.3168.2 <228 633+/-221.1 Ra-226' 297.8+/-97.68 670.9+/-106.4 325.1+/-98.1 Actrh-228' 50.77*29.33 <56.58 <51.9 Ac/Th-228- <24.16 <24.74 38.37+/-16.22

• Indicates naturally occurring.

• • Indicates control location.

• ' 'Less than' values expressed as Critical Level (I-j. B-33

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION**- 2003 (pCVKg, wet +/-1 sigma)

1. 95 Meteorological Tower May Juno Be-r 169.8+/-28.19 157.3+/-25.41 343.8*38.31 Be-7 656+/-42-57 2048+/-67.14 1347+/-54.26 K-40 5066+/-126.3 6717+/-107.6 6227+/-156.9 K 3608+/-116.5 7306+/-178.3 5587+/-143.3 Mn-54 <4.61 <3.85 <5.32 Mn-54 <5.11 <6.11 <5.43 Co-se <4.65 <3.92 <5.66 Co-58 <4.91 <5.84 <4.84 Fe-59 <13.88 <10.65 <14.76 Fe-59 <15.95 <16.91 <16.56 Co-60 <5.2 <4.52 <6.96 Co-60 <5.51 <5.95 <5.75 Zn-85 <12.4 <5.48 <12.77 Zn-65 <11.83 <15.81 <12.31 Zr-95 <7.56 <6.1 <9.02 Zr-95 <8.2 <9.44 <9.58 Nb-95 <4.15 <3.67 <5.85 Nb-95 <5.35 <5 <5.64 Ru-103 <4.29 <3.65 <4.5 Ru-103 <5.11 <5.11 <5.38 Ru-106 <49.52 <38.12 <55.95 Ru-106 <53.37 <57.15 <54.91 1-131 <4.67 <4 <5.87 1-131 <7.37 <8.55 <7.04 Cs-134 <3.36 <4.03 <5.89 Cs-134 <3.52 <5.75 <5.95 Cs-137 <4.82 <3.91 <5.47 Cs-137 <4.94 <5.08 <5.52 Ba/La-i40 <5.94 <3.85 <5.62 Ba/La-1 40 <8.26 <7.59 <7.52 Ce-141 <5.89 <4.9 <6.66 Ce-141 <7.3 <6.46 <6.92 Ce-U44 <23.69 <20.93 <24.65 Ce-144 <30.85 <28.04 <28.3 Ra-226 376.1+/-71.85 463.3t51.8 377.8+/-74.12 Ra-226- 395.4+/-75.56 237.8+/-81.27 276.3+/-81.1 Ac/Th-228' 23.82+/-12.32 49.73*10.97 <19.17 AcTh-228' <19.51 <21.83 29.8+/-13.8 July August Radleucil Ora ves YeW. Ralonucildn Uulb .. :Gnpe I

Be-7' 253.5+/-43.31 548.4+/-58.69 1739*73.57 De-7 1555*72.52 2481+/-54.5 552.9*42.57 K-401 4217+/-140.8 11180+/-257.6 10360+/-198.6 K-40 9139+/-220.4 7052+/-120.9 4553+/-139 Mn-54 <6.79 <9.14 <7.95 Mn-54 <8.84 <4.63 <6.19 Co-se c5.58 <9.48 <7.51 Co-58 <7.79 <4.24 <5.5 Fe-59 <17.86 <26.63 <21.24 Fe-59 <23.16 <12.66 <16.33 Co 60 <6.9 <9.33 <8.18 Co-60 <8.76 <4.75 <6.96 Zn-65 <14.2 <25.69 <11.55 Zn-65 <18.96 <6.75 <14.53 Zr-95 <9.65 <13.73 <13.21 Zr-95 <13.8 <7.66 <10.53 Nb-95 <6.33 <9.04 <8.12 Nb-95 <7.88 <4.35 <6.21 Ru-103 <5.59 <8.72 <7.72 Ru-103 <7.43 <4.42 <4.93 Ru-106 <56.09 <93.21 <74.29 Ru-106 <84.14 <42.64 <53.95 1-131 <7.55 <9.17 <9.47 1-131 <7.43 <4.85 <7.14 Cs-134 <6.87 <9.89 <5.52 Cs-134 <9.63 <3.14 <6.1 Cs-137 <6.02 <9.31 <8.46 Cs-137 <8.78 <4.66 <5.39 Ba-140 <8.77 <12.46 <8.89 BaLa-140 <10.43 <4.8 <6.93 Ce-141 <7.28 <11.24 <10.4 Ce-141 <6.41 <6.01 <7.25 Ce-144 <28.13 <44.72 <44.75 Ce-144 <40.06 <27.12 <26.06 Ra-2261 528.7+/-92.2 626+/-115.4 871.6+/-126.5 Ra-226- 347.4t124.7 413.9+/-73.75 425+/-75.31 Acrh-228' <21.15 60.36+/-27.94 85.89+/-24.92 Ac/Th-228' 64.25+/-24.66 61+/-13.05 25.96+/-15.66

• Indicates naturally occurring.

- Indicates control location.

"' Less than' values expressed as Critical Level (I. B-34

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2003 (pCiKg, wet +/-: 1 sigma)

1. 95 Meteorological Tower (continued)

September October O-7 1155*108.8 505.5+/-72.43 1742+/-105 seBr 3950+/-90.94 2634+/-49.85 3101*88.68 K-40 7249t382.1 3994+/-230.1 9249+/-293.3 K-40' 6631+/-161 7078+/-111.4 6908+/-176.2 Mn-54 <13.5 <6.89 <11.3 Mn-54 <5.22 <2.91 <6.08 Co-58 <15.33 <8.77 <11.76 Co-58 6.13 <3.08 <6.2 Fe-59 <42.02 <26.79 <26.47 Fe-59 <20.89 <12.08 <21.5 Co-60 <15.36 <10.41 <12.59 Co-60 <6.48 <3.71 <7.63 Zn-65 <32.33 <22.96 <17.81 Zn-65 <14.18 <7.69 <16.56 Zr-95 <22.26 <16.42 <19.02 Zr-95 <11.04 <5.62 <12.43 Nb-95 <15.19 <10.32 <10.73 Nb-95 <6.64 <3.77 <8.17 Ru-103 <12.13 <7.53 <12.15 Ru-103 <6.46 <3.48 <6.79 RU-106 <139.9 <83.27 <107.8 Ru-106 <61.31 <28.5 <69.87 1-131 <17.35 <10.9 <14.54 1-131 <13.27 <8.03 <15.47 Ca-134 <13.1 <10.76 <7 Cs-134 T35 d3.O4 <6.69 Cs-137 <13.2 <9.61 <10.21 Cs-137 <5.49 13.97+/-2.56 <7.07 Ba&Ls-140 <13.97 <8.15 <10.77 Ba/La-140 <10.6 <6.03 <11.8 Ce.141 <15.69 <11.48 <14.84 Ce-141 <9.08 <3.04 <10.65 Ce-144 <59.51 <41.52 <61.05 Ce-1 44 <30.53 <16.85 <31.66 Ra-226- 577.9+/-194.3 397.1+/-135.3 510.2+/-156.4 RJ-226- 170.7+/-95.99 173.3+/-42-66 <122.5 ActTh-228' <39.87 <23.46 75.18+/-30.76 Ac/Th-228- <22.11 20.71+/-k8.65 <22.02

• Indicates naturally occurring.

- Indicates control location.

"' Less than' values expressed as Critical Level (Lv). B-35

TABLE B-15 CONCENTRATIONS OF GAMMA EMITTERS IN FISH AND INVERTEBRATE SAMPLES - 2003 (pCVKg. wet

• 1 sigma)

1. 23 ROSETON (control)

Be-r <207.2 <302.7 <218.8 <202 <247.2 K-4r 9423+/-319 4700+/-438 5563+/-339.1 4576+/-328.3 4476+/-276.7 Mn-54 <19.47 <25.92 <14.03 <20.21 <19.76 CO-58 <23.48 <32.18 <25.64 <26.32 <29.48 Fe-59 <68.61 <116.8 <96.02 <95.66 <78.03 CO-60 <21.49 <24.06 <17.7 <15.49 <16.91 Znr65 <44.38 <49.88 <39.3 <42.82 <48.73 zr-95 <41.7 <62.27 <51.62 <40.93 <41.89 Nb-95 <32 <57.79 <38.56 <37.94 <41.09 Ru-1 03 <32.66 <46.85 <37.49 <29.25 <35.92 Ru-106 <213.3 <271.3 <183.1 <145.8 <195.2 1-131 <173.4 <875.9 <1152 <1051 <1238 Cs-134 <20.27 <27.76 <19.78 <16.02 <9.98 Cs-137 <19.81 <24.15 <15.52 <15.55 <17.26 Ba/La- 40 <82.84 <320.1 <287.9 <225.6 <207.2 Cea 41 <43.33 <67.43 <53.25 <46.19 <64.5 Ce-l <113.6 <123.3 <95.48 <74.86 <110.6 Rm-226- 1314+/-312.4 628.9+/-288.9 <284.8 454.9+/-200.5 455.6+/-234.1 AcTrh-228 241.9+/-56.46 <86.95 <52.52 <62.13 102.5+/-49.61

1. 25 DOWNSTREAM (HUDSON RIVER)

(indicator)

_____ 11-1_.1 Be-r <73.67 <128 <156.4 <323.8 <183.3 <164.5 K-40' 3812+/-159.6 5086+/-240 4566+/-302.4 8951+/-361.1 5122+/-283.2 4902+/-205.6 Mn-54 <8.47 <15.01 <12.99 <23.78 <13.74 <13.64 CO-58 <9.75 <16.5 <18.62 <34.12 <22.28 <18.75 Fe-59 <29.06 <47.99 <69.89 <112.8 <66.52 <56.45 Co-60 <9.48 <13.15 <17.42 <21.36 <13.78 <11.94 Zn-65 <20.09 <32.54 <35.18 <58.42 <44.35 <34.27 zr-95 <16.49 <27.54 <40.45 <62.38 <38.19 <31.72 Nb-95 <11.4 <18.27 <23.58 <60.41 <34.32 <27.66 Ru-103 <10.49 <17.71 <25.05 <53.2 <27.34 <25.67 Ru-106 <84.61 <156.8 <143.5 <249.3 <163.4 <141.1 1-131 <37.52 <75.37 <332.4 <2483 <474.2 <684.6 Cs-134 <9.22 <13.48 <15.36 <14.24 <8.97 <8.18 CS-137 <8.98 <14.41 <15.34 <20.23 <12.39 <12.79 Ba/-140 <28.71 <44.59 <115.3 <359.1 <185.6 <158.1 Ce-141 <15.06 <25.29 <35.36 <90.75 <37.69 <46.15 Ce-144 <42.91 <8.1 <79.19 <151.4 <77.5 <82.51 Ra-226- 376.9+/-114.3 542.7+/-2 15.1 <259.9 1312t351.1 420.2+/-t201.3 890.7+/-1 95.3 AcTrh-228 <29.73 <48.29 <50.77 234.5+/-63.52 <60.97 114.5+/-41.28

• Indicates naturally occuring. B-36

TABLE B-16 ANNUAL

SUMMARY

, NON-RETS SAMPLE RESULTS 2003 AQUATIC VEGETATION (pCVkg-WET) Co-60 NONE <L. <cL. < L. 0 6 < L. < L, c L. O 4,5 14. <

1-131 100 27.5 27.5 27.5 6 21.9 21.9 21.9 1 5 87 27.9 Cs-134 100 < L. < , <cL. 0 6 < L, <L. cL, 0 5 <L, cL, Cs.137 100 7.21 8.27 5.39 4 6 8.6 12.0 7.1 4 5 29.7 73.6 BOTTOM SEDIMENT (pCVkg - DRY) Co-60 NONE < LO ' 0 6 .L, < L, cL. 0 2 83.7 cL.

Cs-134 1S0 'L, ci.L, 0 6 cL. <L, L. 0 2 47.8 44.r-Cs-137 180 601 1746 287 6 6 299.4 299.4 299.4 1 2 598 86 SOIL (pCikg - DRY) Co-60 NONE < i, t' ci,, 0 2 'cL, ci. ci,, 0 1 ' LiL Cs-134 150 c L. 'L 0 2 cL. <L. 0 1 ci. ci Cs-137 180 i < L. <L. 0 2 108.6 108.6 108.6 1 1 159 75.7 PRECIPITATION (pCVL) H-3 2000 < L. < L. c. 0 4 < L. < L, < L. 0 4 261 341 Co-O0 15 'b" < L, -cL. 0 4 'c. <L < L. 0 4 <cL. L, Cs-134 15 <cL. < L. L. 0 4 <cL . <cL. 0 4 <c, c.

Cs-137 18 <cL. < L. L. 0 4 <cL. L. 'L. 0 4 <L. 'L.

SPECIAL WATER (p)CUL) H-3 2000 < bi <L L. 0 50 NA NA NA NA NA 167 NA Co-60 is 'b <L. Lc 0 50 NA NA NA NA NA 'L. <c.

Cs-134 15 <ci cL, L. 0 50 NA NA NA NA NA <cL, -ci.

Cs-137 18 <.'c ',L. 0 50 NA NA NA NA NA < L. 'L.

• Average of positive values for 1993 - 2002 Detected at control location 1999, AND 2001.

NA - Data not available.

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

B-37

TABLE B-17 MILCH ANIMAL CENSUS 2003 THERE ARE NO ANIMALS PRODUCING MILK FOR HUMAN CONSUMPTION WITHIN FIVE MILES OF INDIAN POINT.

B-38

TABLE B-18 LAND USE CENSUS 2003

-l I-1-N 1.14 Ayers Road, Jones Point 2- NNE 1.95 St. Mary's School, Peekskill 3-NE 1.21 South Street, Peekskill 4- ENE 1 South Street, Peekskill 5-E 0.47 Bleakley Avenue, Buchanan 6 - ESE 0.39 Broadway, Buchanan Westchester Avenue, 7 - SE 0.73 Buchanan Westchester Avenue, 8 - SSE 0.76 Buchanan 9-S 0.71 Broadway, Verplanck St. Partricks Rectory, 10 - SSW 0.97 Verplanck 11 - SW 1.8 Elm Avenue, Tomkins Cove West Shore Drive South, 12 - WSW 1.36 Tomkins Cove

. 1West Shore Drive North, 13-W 1.21 Tomkins Cove 14 - WNW 1.09 Route 9W, Tomrkins Cove 15 - NW 1.04 Route 9W, Tomkins Cove 16 - NNW 0.98 Jones Point B-37

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 2003 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 2003 are from a single sample of broadleaf vegetation that indicated Cs-1 37.

C-1

TABLE C-1 DIRECT RADIATION ANNUAL

SUMMARY

1993 to 2003 C-2

FIGURE C-1 DIRECT RADIATION 40 - 1993 to 2003 35 -

30 25 c-

&20 a:

E 15 10 0 -Y 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 C-3

TABLE C-2 RADIONUCLIDES IN AIR 1993 to 2003 (pCVm 3 )

1993 0.02 0.02 <Lc < Le 1994 0.02 0.01 <aLe <Lc 1995 0.01 0.01 < Lr 1996 0.01 0.01 <Lc 1997 0.01 0.01 <Lc 1998 0.02 0.01 < L, <Le 1999 0.02 0.01 <Lc <aLe 2000 0.01 0.01 <Lc < L, 2001 0.02 0.02 <Lc < L,,

2002 0.02 0.02 Le <aLc 2003 0.01 0.01 0.02 0.01 <Le <aLe Critical Level (La) is less than the RETS required LLD.

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

C-4

FIGURE C-2 RADIONUCLIDES IN AIR - GROSS BETA 1993 to 2003 0.05 0.04 0.03 E

0.

0.02 0.01 0.00 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003

• Includes RETS and non-RETS indicator locations.

Gross Beta RETS required LLD = 0.01 pCVm3 C-5

TABLE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 1993 to 2003 (pCUL) 1993 240 270 < L, ' L, 1994 230 280 < Le < Le 1995 370 270 < L, < L, 1996 < L, 280 < Lc ' Le 1997 ' L, 430 < Le < Le 1998 < Le 220 < Lr < Le 1999 191 318 ' Lc < L, 2000 190 267 < Lc ' L, 2001 < Le 323 ' Lc ' Le

<L < L, 2002 432 562 2003 < L, < L, < L, < L:

276 322 <L, < L, Critical Level (La) Is less than the RETS required LLD.

<Lc indicates no positive values above sample critical level.

C-6

FIGURE C-3 HUDSON RIVER WATER - TRITIUM 1993 to 2003 9n2n 1800 -

S Inlet (H-3) 0 Discharge (H-3) 1600 -

1400]

1200 -

0 1000-800-600 400 -

71]

200 - . ..

M-11 U 'p .a. aI 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 Tritium RETS required LLD = 3000 pCi/L C-7

TABLE C-4 RADIONUCLIDES IN DRINKING WATER 1993 to 2003 (pCVL)

-s.m.L9. ... I 1993 <e <L 1994 <L <L 1995 <L <L 1996 < '<

1997 <L' 1998 <LL0 1999 < <'L 2000 <L 'L 2001 < '<

2002 << Le 2003 <L, < L-

<'L, < Le Critical Level (La) is less than the RETS required LLD.

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

C-8

FIGURE C-4 DRINKING WATER - TRITIUM 1993 to 2003 2000 1800 1 Camp Field Reservior (H-3)

U New Croton Resevoir (H-3) 1600 1400 -

1200 -

d 1000 -

0.

NO IDENTIFIED TRITIUM IN PREVIOUS TEN YEAR HISTORY 800 -

600 -

400-200 0 -

1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 Tritium RETS required LLD = 2000 pCiVL C-9

TABLE C-5 RADIONUCLIDES IN SHORELINE SOIL 1993 - 2003 (pCiUKg, dry)

Critical Level (La) is less than the RETS required LLD.

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

C-10

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

0.

700 600 500 400 300 200 100 0

1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 Cs-134 RETS required LLD = 150 pCVKg, dry Cs-1 37 RETS required LLD = 175 pCi/Kg, dry C- 1

TABLE C-6 RADIONUCLIDES IN BROAD LEAF VEGETATION 1993 to 2003 (pCiVKg, wet) 1993 44 18 1994 22 < Lc 1995 28 <Lc 1996 17 <L 1997 <EL <Lc 1998 < Lc <Lc 1999 < Lc 27 2000 28 6Lc 2001 7 <Lc 2002 14 16 2003 14 <b 23 20 Critical Level (Lj is less than the RETS required LLD.

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

C-12

FIGURE C-6 BROAD LEAF VEGETATION - Cs-137 1993 to 2003 100 -

80 60 C,

40 20 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 RETS required LLD = 80 pCi/Kg, wet C-13

TABLE C-7 RADIONUCLIDES IN FISH AND INVERTEBRATES 1993 to 2003 (pCVKg, wet)

Critical Level (Lj)is less than the RETS required LLD.

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

C-14

FIGURE C-7 FISH AND INVERTEBRATES - Cs-137 1993 to 2003 200 -

180 - l Indicator (Cs-1 37) l Control (Cs-1 37) 160 140 120 100 C.,

80-60 40 20 0 1 1 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 Cs-137 RETS required LLD = 150 pCi/Kg, wet C-15

APPENDIX D INTERLABORATORY COMPARISON PROGRAM

APPENDIX D D.1 PROGRAM DESCRIPTION Radiological Effluent Technical Specification (RETS) and Radiological Effluent Controls (RECS) require that each 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 Technical Specification 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 inAtlanta, Georgia and the U.S. Department of Energy's Environmental Measurements Laboratory (EML) in New York City.

Analytics supplies requested 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 participated in the Environmental Measurements Laboratory (EML) Quality Assessment Program (QAP). EML supplies sample media as blind sample spikes to approximately 127 laboratories worldwide. These samples, containing a spiked amount of low level activity, are analyzed using standard laboratory procedures.

The results are submitted to the Environmental Measurements Laboratory for statistical evaluation. Reports are provided to each participating laboratory, which provide an evaluation of the laboratory's performance.

During 2003, tritium analyses for the JAF Environmental Laboratory were at JAF Environmental Laboratory, in the past they were performed by Framatome, ANP.

D-1

D.2 PROGRAM SCHEDULE TABLE D-1 2003 QA Program Schedule Water Gross Beta _ 2 2 Water Tritium 1 2 3 Water 1-131 2 0 2 Water Mixed Gamma 2 2 4 Air Gross Beta 2 2 4 Air 1-131 2 0 2 Air Mixed Gamma 2 2 4 Milk 1-131 2 0 2 Milk Mixed Gamma 2 0 2 Soil Mixed Gamma 1 0 1 VeMation Gamma 1 0 1 17 10 27 D.3 ACCEPTANCE CRITERIA Each sample result is evaluated to determine the accuracy and precision of the laboratory's analysis result. The evaluation method for the QA sample results is dependent on the supplier of the sample. The sample evaluation methods are discussed below.

D.3.1 ANALYTICS SAMPLE RESULTS Samples provided by Analytics 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).

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 D-2

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

TABLE D-2 Ratio of Agreement 8ER'WO'RIESVOLXTIO'N -wATIO1FGREEMENX

<3 0.4 to 2.5 3.1 to7.5 0.5to2.0 7.6 to 15.5 0.6 to 1.66 15.6 to 50.5 0.75 to 1.33 50.6 to 200 0.8 to 1.25

>200 0.85 to 1.18 Again, this acceptance test is generally referred to as the "NRC" method. The acceptance criteria is contained in JAFNPP 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 Inc. 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.3.2 ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

The laboratory's analytical performance is evaluated by EML based on the historical analytical capabilities for individual analyte/matrix pairs.

The statistical criteria for Acceptable Performance, "A", has been chosen by EML to be between the 15th and 85th percentile of the cumulative normalized distribution, which can be viewed as the middle 70% of all historic measurements. The Acceptable With Warning criteria, "W", is between the 5th and 15th percentile and between the 85th and 95th percentile. In other words, the middle 70% of all reported values are acceptable, while the other 5th-1 5th (10%) and 85th-95th percentiles (10%) are in the warning area. The Not Acceptable criteria, "N", is established at less than the 5th percentile D-3

and greater than the 95th percentile, that is, the outer 10% of the historical data. Using five years worth of historical analytical data, the EML, determined performance results using the percentile criteria summarized below:

Result Cumulative Normalized Distribution Acceptable ("A") 15% - 85%

Acceptable with Warning ("W") 5% - 15% or 85% - 95%

Not Acceptable ("N") <5% or >95%

D.4 PROGRAM RESULTS

SUMMARY

The Interlaboratory Comparison Program numerical results are provided on Table D-6.

D.4.1 ANALYTICS QA SAMPLES RESULTS Seventeen QA blind spike samples were analyzed as part of Analytics' 2003 Interlaboratory Comparison Program. The following sample media were evaluated as part of the comparison program.

• Air Charcoal Cartridge, 1-131

• Air Particulate Filter, Mixed Gamma Emitters/Gross Beta

• Water, 1-131/Mixed Gamma Emitters/Tritium

• Soil, Mixed Gamma Emitters

• Milk, 1-131 Mixed Gamma Emitters

• Vegetation, Mixed Gamma Emitters The JAF Environmental Laboratory performed 81 individual analysis on the seventeen QA samples. Of the 81 analysis performed, 79 were in agreement using the NRC acceptance criteria for a 97.5% agreement ratio.

Sample non-conformities are discussed in Section D.4.2.

D-4

D.4.2 ANALYTICS SAMPLE NONCONFORMITIES D.4.2.1.A Analytics Sample E-3687-05, Co-58 In Soil Nonconformity No. 2003-02 A spiked mixed gamma insoil sample supplied by Analytics, Inc., was analyzed in accordance with standard laboratory procedures. The sample contained a total of nine radionuclides for analysis. Nine of the nine radionuclides present were quantified. Eight of the nine radionuclides were quantified within the acceptable range. The mean result for Co-58 was determined to be outside the QA Acceptance Criteria resulting in a sample nonconformity. The soil sample was analyzed five times using three different detectors with the mean Co-58 result reported as 81 pCVkg. The known result for the sample was 102 pCi/kg as determined by the supplier. One of the five reported results was 92 pCi/kg and resulted inan agreement when compared to the known of 102 pCVkg with a ratio of 0.90. The remaining 4 individual results were outside the acceptance criteria and had ratios to the known that ranged from 0.75 to 0.79. All of the analysis had relatively high associated counting errors, which ranged from 9.8% to 22%.

An evaluation of the Co-58 result was performed. The spectrum and peak search results were examined with no abnormalities identified.

Co-58 decays by electron capture with a 70.9 day half-life and a gamma ray energy of 810 KeV with a yield of 99.5%. No significant secondary gamma energies are produced inthe Co-58 decay scheme.

The average net count rates of the five analyses were very low and ranged from a high of 0.94 counts per minute to a low of 0.66 counts per minute. The low activity in the sample resulted in high associated counting errors as noted above.

The combination of low sample activity, very low count rate and high background level in the spectrum, resulted in an inaccurate sample result. The wide range of the associated counting errors demonstrates the low confidence level in the reported results. The nonconforming analytical results for this sample is not routine and does not indicate a programmatic deficiency in the analysis of Co-58 in soil samples or other environmental media. Confidence in the accurate analysis of D-5

Co-58 can be demonstrated by other Co-58 analytical results, both in the overall results for the 2003 QA program and historical Co-58 QA program results. The Co-58 results for the other Quality Assurance samples analyzed as part of the 2003 Interlaboratory Comparison Program were all acceptable and are summarized below:

TABLE D-3 2003 Co-58 Results E-3610-05 WATER pCi/liter 43+2 42+/-1 1.02 E-3855-05 WATER pCi/liter 94+/-3 94+/-3 1.00 E-3611-05 FILTER pCi/filter 53+/-2 52+/-2 1.02 E-3856-05 FILTER pCi/filter 70+/-3 69+/-2 1.01 E-3686-05 SOIL pCVkg 89+/-5 93+/-3 0.96 E-3857-05 MILK pCiliter 99+/-3 98+/-3 1.00 E-3689-05 VEGETATION pCikg 149+/-8 138+/-5 1.08 Mean Ratio 1.01 A review of historical QA data for the period of 2002 through 1999 was performed. There were no nonconformities related to the analysis of Co-58 during this period. In 2002, six QA samples were analyzed which contained Co-58. The mean ratio for these samples relative to the known (reference) value was 1.02. The 2003 nonconformity is considered to be an isolated instance. The low concentration of Co-58 present in the sample is considered to be the major contributor to the nonconformity. This low activity resulted in a very low count rate and a low net count rate to background ratio as indicated by the high associated counting error. The historical Co-58 results and the 2003 program result demonstrate that there is no systematic error or persistent bias present inthe analysis of samples for Co-58 in soil of other environmental sample media. No corrective actions were implemented as a result of this nonconformity.

D-6

D1.4.2.11.B Analytics Sample E-3689-05, Co-60 in Vegetation Nonconformity No. 2003-01 A spiked mixed gamma inVegetation sample supplied by Analytics, Inc., was analyzed in accordance with standard laboratory procedures. The sample contained a total of nine radionuclides for analysis. Nine of the nine radionuclides present were quantified.

Eight of the nine radionuclides were quantified within the acceptable range. The results for Co-60 were determined to be outside the QA Acceptance Criteria resulting a sample nonconformity. The Vegetation sample was analyzed three times using three different detectors with the mean Co-60 result reported as 0.253 +/- 0.007 pCi/gram. The known result for the sample was 0.197 +/- 0.007 pCigram as determined by the supplier. The calculated ratio to the known was 1.28 or 28% greater than the known.

An evaluation of the Co-60 result was performed. The spectrum and peak search results were examined with no abnormalities identified. The precise cause of the nonconformity could not be explicitly determined. The difference inthe sample density and the density of vegetation geometry calibration source is considered to be a significant contributing cause. The vegetation calibration source is constructed using 720 grams of homogeneous organic material in a 1 liter Marinelli beaker. The analytics cross check sample contained 600 grams of the same material that was analyzed using the same counting geometry as the calibration source. In addition to the difference in sample density, the results were biased by settling of the sample in the Marinelli beaker, which because of the geometry, would place the material closer to the detector. With the material in the counting beaker being closer to the detector along with the overall difference in density, a positive bias would be introduced into the analysis. The presence of the high bias is confirmed by the results for the other radionuclides present in the sample. With the exception of Cr-51, the results for the other seven radionuclides resulted inhigh ratios (bias) relative to the known value and ranged from 1.05 to 1.22 (5%to 22% higher)

D-7

when compared to the reference results.

The nonconforming analytical results for this sample media is not routine and does not indicate a programmatic deficiency in the analysis of Co-60 in Vegetation samples or other environmental media. Confidence in the accurate analysis of Co-60 can be demonstrated by other Co-60 analytical results, both in the sample results for the 2003 QA program and historical Co-60 QA results.

The Co-60 results for the other Quality Assurance samples analyzed as part of the 2003 Interlaboratory Comparison Program were all acceptable and are summarized below:

TABLE D-4 2003 Co-60 Results E-3610-05 WATER pCi/liter 156+2 157+/-5 0.99 E-3855-05 WATER pCi/liter 122+/-2 117+/-4 1.04 E-3611-05 FILTER pCi/filter 175+2 179+/-6 0.98 E-3856-05 FILTER pCi/filter 90+/-2 87+/-3 1.03 E-3686-05 MILK pCiliter 132+/-4 132+/-4 1.00 E-3857-05 MILK pCiAiter 133+/-2 123+/-4 1.08 E-3687-05 SOIL pCi/kg 155+/-5 l 145+/-5 1.07 MI HI I 1 - 03 A review of historical QA data for the period of 2002 through 1999 was performed. There were no nonconformities related to the analysis of Co-60 during this period. In 2002, eight QA samples were analyzed which contained Co-60. The mean ratio for these samples relative to the known (reference) value was 0.99. The 2003 nonconformity is considered to be an isolated instance. The lower sample volume/density produced a high bias in the analytical results which is considered to be the major cause of the nonconformity. The historical Co-60 results and the 2003 program result demonstrate that there is no systematic error or persistent bias present in the analysis of samples for Co-60 in Vegetation or other environmental sample media. No corrective actions were D-8

implemented as a result of this nonconformity.

D.4.3 ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

In 2003, JAF Environmental Laboratory participated in both the EML Quality Assessment Programs, QAP-56 and QAP-57. Sample sets consisted of the following sample media:

• Water - Gross Beta/Mixed Gamma Emitters

• Water - Tritium

• Air Particulate Filter- Mixed Gamma Emitters/Gross Beta A total of 10 samples containing 18 individual radionuclides were evaluated for the samples included in QAP-56 and QAP-57. Using the EML acceptance criteria, 18 of 18 radionuclides analyses (100%) were evaluated to be acceptable. Results forthe EML Cross Check Program can be viewed on-line at www.eml.doe.cov. A summary of the JAF Environmental Laboratory results is as follows:

TABLE D-5 JAF (EML) Environmental Lab Summary Air 10 10 0 Water 8 8 1

__ to__ l__ I 18 18 0

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I 100.0% 0%

There were no sample nonconformities associated with the samples analyzed for the Environmental Measurements Laboratory program.

D-9

TABLE D-6 INTERLABORATORY COMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filters (pCi/filter) 6/12/03 E-3685-05 AIR GROSS BETA 76.8+/-1.2 81+/-3 0.94, A pC/filter 73.7+/-1.2 76.6+/-1.2 Mean = 75.7+/-0.7 12/11/03 E-3930-05 AIR GROSS BETA 56.6+/-0.85 57+/-2 1.00, A pCi/filter 58.6+/-0.87 54.9+/-0.84 Mean = 56.7+/-0.49 (1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

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

Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-10

TABLE D-6(Continued)

INTERLABORATORY COMPARISON PROGRAM Tritium Analysis of Water (pCilliter) lIi' 3/20/03 E-3609-05 WATER H-3 4538+/-183 4463+/-149 1.03, A pCiliter 4547+/-183 4729+/-185 Mean = 4605+/-106 (1) Results reported as activity +/- 1 sigma. Sample Analyzed by Framatome, ANP.

(2) Results reported as activity +/- 3 sigma.

(3) Ratio = ReportedcAnalytics (See Section D.3).

(*) Samples provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-11

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Iodine Analysis of Water, Air and Milk vvWla L1 I 72.6+f2.9 pCiliter 1-1 31 ** 70.2+/-4.3 68.7+/-2.6 Mean = 70.5+/-1.9 6/12/03 E-3688-05 AIR 1-131 73.8+/-9.3 62+/-2 1.18, A pCVcc 73.2+/-9.7 72.2+/-10.1 Mean = 73.1+/-5.6 6/12/03 E-3686-05 MILK 91.8+/-2.5 103+/-3 0.90, A pCi/liter 1-131* 94.7+/-2.5 91.6+/-2.0 Mean = 92.7+/-1.3 9/18/03 E-3858-05 AIR 1-131 79.3+/-9.2 82+/-3 1.02, A pCVcc 76.9+/-9.1 95.0+/-9.0 Mean = 83.7+/-5.3 9/18/03 E-3855-05 1-131 ** 77.0+/-1.7 76+/-3 1.00, A WATER 76.4+/-1.5 pCiliter 74.0+/-2.4 Mean = 75.8+/-1.1 9/18/03 E-3857-05 1-131 ** 68.2+/-2.9 74+/-2 0.95, A MILK 70.7+/-1.7 pCUliter 68.9+/-1.9 Mean = 69.3+/-1.3 (1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

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

(*) Samples provided by Analytics, Inc.

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

(A) Evaluation Results, Acceptable.

D-12

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Ana Is Water pCilliter 3/20/03 E-3610-05 Ce-141 167+/-9.9,165+/-8.3 168+/-6 0.99, A WATER 160+/-10.4,177+/-3.8 pCifliter 166+/-6.3 Mean = 167+/-3.6 Cr-51 339+/-44.8,192+/-41.7 238+/-8 1.08, A 241+/-55.0, 244+/-18.7 270+/-33.6 Mean = 257.2+/-18.2 Cs-134 76.7+/-5.2, 76.9+/-4.7 88+/-3 0.89, A 75.4+/-5.7, 83.9+/-1.7 78.1+/-3.0 Mean = 78.2+/-1.9 Cs-1 37 180+/-6.5,184+/-6.3 195+/-7 0.94, A 182+/-7.8,185+/-2.4 185+/-4.4 Mean = 183.2+/-2.6 Mn-54 68.0+/-4.7, 68.1+/-4.4 63+/-2 1.06, A 67.0+/-5.7, 65.9+/-1.7 66.0+/-3.1 Mean = 67.0+/-1.9 Fe-59 49.9+/-6.2, 53.4+/-6.8 46+/-2 1.09, A 47.5+/-7.7, 45.1+/-2.4 53.8+/-4.5 Mean = 49.9+/-2.6 Zn-65 92.8+/-9.2, 77.2+/-8.4 90+/-3 0.98, A 87.1+/-10.7, 95.1 +/-3.4 85.5+/-6.3 Mean = 87.5+/-3.6 Co-60 156+/-4.9,151+/-4.8 157+/-5 0.99, A 156+/-6.0,160+/-1.8 156+/-3.3 Mean = 155.8 +/-2.0 Co-58 44.9+/-4.7, 35.1+/-4.2 42+/-1 1.02, A 39.8+/-5.5, 47.4+/-1.6 45.6+/-3.2 Mean = 42.6+/-1.8 (1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

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

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-13

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Water (pCi/liter) 1110Nlff-JR110114:01310MI l1wip-m-6`-§Vs2 1Z)Rq;ww I www'wg" 9/18/03 E-3855-05 Ce-141 77.0+/-7.1 81+/-3 0.95, A pCiliter 81.5+/-6.3 73.1+/-6.7 Mean = 77.2+/-3.9 Cr-51 174.0+/-31.2 221+/-7 0.87, A 239.0+/-31.1 162.0+/-30.9 Mean = 191.7+/-17.9 Cs-1 34 102+/-4.5 113+/-4 0.93, A 108+/-3.8 104+/-8.6 Mean = 104.7+/-3.5 Cs-1 37 76.5+/-3.8 84+/-3 0.94, A 81.8+/-3.6 77.1+/-4.5 Mean = 78.5+/-2.3 Mn-54 84.3+/-4.4 88+/-3 1.08, A 102+/-3.9 98.4+/-5.0 Mean = 94.9+/-2.6 Fe-59 83.9+/-5.9 75+/-3 1.03, A 73.4+/-4.8 73.6+/-5.9 Mean = 77.0+/-3.2 Zn-65 158+/-9.4 166+/-6 1.04, A 178+/-8.2 184+/-10.5 Mean = 173.3+/-5.4 Co-60 125+/-3.7 117+/-4 1.04, A 120+/-3.2 121+/-4.2 Mean =1 22.0 +/- 2.1 Co-58 94.8+/-4.5 94+/-3 1.00, A 96.8+/-3.9 89.7+/-5.2 I I I Mean = 93.8+/-2.6 I (1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

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

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-14

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (pCVfilter)

I 911-9 111 3/20103 E-3611-05 1211 Ce-141 191:t6.5

.111" h2kV, 191:t6 1.00, A pC~ilter 191+/-2.7 191+/-6.7 Mean = 191+/-t3.2 Cr-51 271 +/-32.0 272+/-9 0.97, A 247+/-30.8 264*14.6 270+/-32.2 Mean = 263+/-14.2 Cs-1 34 90.6+/-5.1 100+/-3 0.92, A 91.3+/-1.6 93.0+/-4.9 Mean = 91.6+/-2.4 Cs-1 37 212+/-6.7 221+/-7 0.96, A 216+/-6.7 211+2.2 214+/-6.1 Mean = 213.3+/-2.9 Mn-54 81.9+/-5.0 71+/-2 1.14, A 79.8+/-1.6 80.8+/-4.4 Mean = 80.9+/-2.4 Fe-59 62.1+/-7.0 52+/-2 1.12, A 57.1+/-6.7 58.8+2.6 54.4+/-6.3 Mean = 58.1+/-3.0 Zn-65 120+/-10.4 103+/-3 1.06, A 98+/-10.5 115+/-3.4 102+/-9.5 Mean = 108.8+/-4.5 Co-60 176+/-5.6 179+/-6 0.98, A 176+/-5.7 174+/-1.7 176+/-5.0 Mean = 175.5+/-2.4 I Co-58 I 1 53.8+/-4.7 59.0+/-4.6I 52+/-2 11.02, A I I 49.6+/-1.5

_ __ __ _ __ __ _ _ _ ____ _ _ _ _ _ _ _ _ _ _ _M ean = 52.7+/-2.0 _ _ _ _ _ _ _ _ _ _ _

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

(2) Results reported as activity +/- 3 sigma.

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

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-15

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (pCitfilter)

IAI~ i ~[I 1 R EE %%TN VA LOUBV0 I 9/18103 I E-3856-05 ommIN 62.8i4.U, 64.6+/-b.1 A M1.U3, ue-141 b61+

pCi/filter 58.8+/-8.7, 66.9+/-1.6 Mean = 63.3+/-2.8 Cr-51 21 0+/-36.4 165+/-6 1.06, A 141+/-42.0 173+/-83.8 176+/-35.2 Mean = 175.0+/-27 Cs-134 85.5+/-4.9,81.2+/--4.8 85+/-3 0.99, A 83.7+/--4.7, 84.6+/-4.7 Mean = 83.8+/-2.4 Cs-1 37 59.7+/-4.0 63+/-2 0.98, A 59.9+/-3.6 61.1+/-3.7 66.1+/-4.0 Mean = 61.7+/-1.9 Mn-54 83.2+/-4.9, 79.2+/-4.4 66+/-2 1.17, A 70.2+/-4.8, 76.7+/-4.9 Mean = 77.3+/-2.4 Fe-59 78.5+/-7.6,45.1+/-6.6 56+/-2 1.16, A 76.7+/-11.8 58.6+/-7.9 Mean = 64.7+/--4.4 Zn-65 148+/-11.1 124+/-4 1.13, A 128+/-9.6 136+/-10.7 148+/-10.4 Mean = 140+/-5.2 Co-60 82.8+/-4.0, 86.9+/-3.6 87+/-3 1.03, A 93.5+/-4.0, 95.1+/-4.1 Mean =89.6+/-2.0 Co-58 69.3+/-5.4 69+/-2 1.01, A 67.7+/-5.1 69.9+/-6.7 73.2+/-5.4 Mean = 70.0+/-2.8 (1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

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

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

(D) Evaluation Results, Disagreement.

(NC) Nonconformity Report Number.

D-16

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Milk (pG Vliter)

• itBS" '"

6/12103 E-3686- MILK Ce-1 41 I 282+/-7.7,280+/-8.8 283+/-9 1.01, 05 pCi/liter 292+/-8.3, 290+/-9.2 A Mean = 286+/-8.5 Cr-51 248+/-34.7,203+/-34.5 239+/-8 1.03, 247+/-31.2, 291+/-34.8 A Mean = 247.3+/-33.8 Cs-134 94.3+/-3.8, 94.4+/-5.3 103+/-3 0.89, 85.0+/-4.0, 94.7+/-5.1 A Mean = 92.1+/-4.6 Cs-1 37 226+/-5.1,206+/-6.7 230+/-8 0.96, 229+/-5.4, 221+/-6.8 A Mean = 220.5+/-6.0 Mn-54 192+/-5.0,182+/-6.4 186+/-6 1.02, 191+/-5.1,195+/-6.5 A Mean = 190+/-5.8 Fe-59 101+/-5.6, 94.5+/-7.3 99+/-3 1.01, 100+/-5.3, 106+/-7.0 A Mean = 100.4+/-6.3 Zn-65 182+/-8.2, 196+/-11.5 181+/-6 1.07, 195+/-8.6,202+/-11.2 A Mean = 193.8+/-10.0 Co-60 137+/-t3.3, 132+/-4.5 132+/-4 1.00, 132+/-3.4, 128+/-4.3 A Mean 132.3=3.9 Co-58 83.5+/-3.9 93+/-3 0.96, 89.6+/-5.2 A 88.4+/-4.2 95.8+/-5.3

- I b Mean = 89.3+/-4.7 b (1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

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

Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-17

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Milk (pCilliter) rS A 9/18/03 E-3857-05 MILK pCi/liter Ce-141 81.9+/-f8.4 87.1+/-7.0 86+/-3 1.00, A 88.2+/-5.9 Mean = 85.7+/-4.2 Cr-51 218+/-39.1 233+/-8 0.96, A 245+/-34.8 208+/-32.7 Mean = 223.7+/-20.6 Cs-134 112+/-5.8 119+/-4 0.99, A 122+/-5.4 120+/-4.0 Mean = 1188+/-3.0 Cs-137 81.9+/-5.1 88+/-3 0.95, A 82.0+/-4.8 89.2+/-3.9 Mean = 84.4+/-2.7 Mn-54 98.8+/-5.6 93+/-3 1.09, A 103+/-5.3 102+/-4.3 Mean = 101.3+/-2.9 Fe-59 70.6+/-7.6 79+/-3 1.00, A 79.2+/-6.7 86.0+/-6.0 Mean = 78.6+/-3.9 Zn-65 172+/-12.1 176+/-6 1.03, A 184+/-11.0 191+/-6.5 Mean = 182.3+/-5.9 Co-60 132+/-4.8 123+/-4 1.08, A 132+/-4.5 134+/-3.7 Mean = 132.7i2.5I Co-58 93.2+/-5.9 99+/-3 1.00, A 103+/-5.7 99.5+/-4.7 I I Mean = 98.6+/-3.1 h I (1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

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

() Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

(D) Evaluation Results, Disagreement.

(NC) Nonconformity Report Number.

D-18

TABLE D-6(Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Soil (pCVgram) 6/12/03 E-3687-05 SOIL Ce- 0.375 +/- 0.035,0.315+/-0.0310 0.310+/-0.010 1.07, A pCi/gram 141 0.356+/-0.0318, 0.299+/-0.0146 0.312 +/- 0.020 Mean = 0.331+/-0.012 Cr- 0.370+/-0.137,0.311+/-0.094 0.262+/-0.009 1.16, A 51 0.228+/-0.082 Mean = 0.303+/-0.062 Cs- 0.119+/-0.019,0.134+/-0.018 0.113+/-0.004 1.19, A 134 0.1 60+/-0.018, 0.131i+/-O.012 0.131+/-0.008 Mean = 0.135+/-0.007 Cs- 0.355+/-0.024,0.372+/-0.024 0.359+/-0.012 1.02, A 137 0.362+/-0.022,0.377+/-0.010 0.367+/-0.014 Mean = 0.367+/-0.009 Mn- 0.221+/-0.022,0.235+/-0.021 0.204+/-0.007 1.08, A 54 0.213+/-0.019, 0.222+/-0.009 0.212+/-0.012 Mean = 0.220+/-0.008 Fe- 0.094+/-0.033,0.068+/-0.029 0.108+/-0.004 0.94, A 59 0.141+/-0.017 0.102+/-0.017 Mean = 0.1 01 +/-0.010 Zn- 0.220+/-0.030, 0.156+/-0.032 0.199+/-0.007 1.07, A 65 0.249+/-0.029, 0.208+/-0.014 0.234+/-0.019 Mean = 0.213+/-0.012 Co- 0.169+/-0.014,0.144+/-0.014 0.145+/-0.005 1.07, A 60 0.1 55+/-0.013, 0.159+/-0.006 0.150+/-0.008 Mean = 0.155+/-0.005 . -

Co- 0.077+/-0.017,0.092+/-0.018 0.102+/-0.003 0.79, D 58 0.077+/-0.017,0.081+/-0.008 NC #

0.079+/-0.011 2003-2

_________________Mean = 0.081+/-0.007 20-(1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity + 3 sigma.

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

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

(NC) Nonconformity Report Number D-19

TABLE D-6(Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Vegetation (pCilgram) 6/12/03 E-3689-05 I2 VEGETATION pCl/gram Ce-141 0.434+/-0.021 0.449+/-0.024 OA22+/-0.014 1.05, A 0.470+/-O.011 Mean = 0.442+/-0.011 Cr-51 0.205+/-0.074 0.356+/-0.012 0.83, A 0.269+/-0.102 0.410+/-0.057 Mean = 0.295+/-0.046 Cs-1 34 0.188+/-0.013 0.154+/-0.005 1.22, A 0.188+/-0.016 0.188+/-0.005 Mean = 0.188+/-0.007 Cs-137 0.378+/-0.018 0.343+/-0.011 1.13, A 0.373+/-0.021 0.414+/-0.007 Mean = 0.388+/-0.009 Mn-54 0.326+/-0.017 0.277+/-0.009 1.15, A 0.308+/-0.021 0.323+/-0.007 Mean = 0.319+/-0.009 Fe-59 0.173+/-0.021 0.148+/-0.005 1.07, A 0.144+/-0.026 0.160+/-0.010 Mean = 0.159+/-0.012 Zn-65 0.281+/-0.030 0.270+/-0.009 1.07, A 0.253+/-0.037 0.332+/-0.012 Mean = 0.289+/-0.016 Co-60 0.261+/-0.012 0.197+/-0.007 1.28, D 0.254+/-0.015 NC #

0.244+/-0.005 2003-1 Mean = 0.255+/-0.008 Co-58 0.130+/-0.014 0.138+/-0.005 1.08, A 0.152+/-0.017 0.166+/-0.006 U U Mean = 0.149+/-0.008 S U-(1) Results reported as activity +/- 1 sigma.

(2) Results reported as activity +/- 3 sigma.

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

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

(NC) Nonconformity Report Number D-20

TABLE D-6(Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Water (Bq/liter) 3/1/03 QAP-58 WATER Cs-1 34 29.2+1.8 30.5+/-1.09 0.934, A Bq/liter 29.8+/-1.8 29.9+/-1.0 26.4+/-1.3 27.4+/-1.6 Mean = 28.5+/-0.7 Cs-1 37 60.3+2.3 63.8+/-3.4 0.964, A 61.8+/-1.3 62.2+/-1.7 61.8+/-2.1 Mean =

61.5+/-0.94 Co-60 230.5+/-3.4 234.0+/-8.4 0.986, A 225.7+/-3.4 228.7+/-1.9 231.6+/-2.6 236.8+/-3.3 Mean =

230.7+/-1.3 (1) Results reported as activity +/- 1 sigma.

(2) Ratio = Reported/Environmental Measurements Lab (EML)(See Section D.3).

(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A) Evaluation Results, Acceptable.

(D) Evaluation Results, Disagreement.

D-21

TABLE D-6(Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Water (Bqlliter) 09/01/03 QAP-59 WATER Cs-1 34 63.6+/-2.5 63.0+/-2.0 1.054, A Bq/liter 65.1+/-2.5 67.7+/-3.3 69.2+/-2.3 Mean = 66.4+/-1.3 Cs-137 82.1 +2.7 80.3+/-4.1 1.032, A 84.7+/-2.7 83.6+/-4.0 81.0+/-2.6 Mean = 82.9+/-1.5 Co-60 525.4+/-4.8 513.0+/-18.0 1.026, A 525.4+/-4.8 518.0+/-6.9 536.5+/-4.7 Mean = 526.3+/-2.7 (1) Results reported as activity +/- 1 sigma.

(2) Ratio = Reported/EML(See Section D.3).

(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A) Evaluation Results, Acceptable.

D-22

TABLE D-6(Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Air Particulate Filters (Bqlfilter) 3/1/03 QAP-58 FILTER Co-60 33.9+/-0.5 33.5+/-0.87 0.994, A Bq/filter 32.5+/-0.5 33.7+/-0.4 33.3+/-0.2 Mean = 33.3+/-0.2 Mn-54 47.7+/-0.7 43.8+/-1.13 1.091, A 45.9+/-0.6 49.6+/-0.7 48.1+/-0.2 Mean = 47.8+/-0.3 Cs-137 104.3+/-0.9 99.7+/-2.3 1.023, A 98.3+/-0.9 103.6+/-0.9 104.0+/-0.3 Mean = 102.7+/-0.4 9/1/03 QAP-59 FILTER Mn-54 65.1+/-0.9 58.0+/-1.3 1.112, A Bq/filter 65.9+/-0.9 62.9+/-0.9 64.0+/-0.8 Mean =

64.47+/-0.43 Co-60 57.0+/-0.7 55.1+/-1.1 1.009, A 55.1+/-0.7 55.5+/-0.7 54.8+/-0.6 Mean =

55.59+/-0.33 Cs-1 37 58.8+/-0.8 54.8+/-1.1 1.057, A 59.6+/-0.8 56.6+/-0.8 56.6+/-0.7 Mean =

57.91+/-0.38 (1) Results reported as activity +/- 1 sigma.

(2) Ratio = Reported/EML (See Section D.3).

(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A) Evaluation Results, Acceptable.

D-23

TABLE D-6 Continued)

INTERLABORATORY COMPARISON PROGRAM Gross Beta Analysis of Water (BqIliter) 3/1/03 QAP-58 WATER GROSS 583+/-13 627.5+/-10.0 0.937, Bq/liter BETA 595+/-13 A 587+/-13 Mean = 588+/-7 9/1/03 QAP-59 WATER GROSS 1760+/-29 1948.0+/-195.0 0.922, Bq/liter BETA 1776+29 A 1853+29 Mean = 1796+/-17 (1) Results reported as activity +/- 1 sigma.

(2) Ratio = Reported/EML (See Section D.3).

(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A) Evaluation Results, Acceptable.

D-24

TABLE D-6(Continued)

INTERLABORATORY COMPARISON PROGRAM Tritium Analysis of Water (Bq/liter) 3/1/03 QAP-58 WATER H-3 419.3+/-8.8 390.0+/-3.4 1.067, A Bq/liter 415.8+/-8.8 413.0+/-8.8 Mean = 416+/-5.1 9/1/03 QAP-59 WATER H-3 470+/-10 446.3+/-2.2 1.058, A Bq/liter 469+/-10 477+/-10 Mean = 472+/-6 (1) Results reported as activity +/- 1 sigma.

(2) Ratio = Reported/EML (See Section D.3).

'2) Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A) Evaluation Results, Acceptable.

D-25

TABLE D-6(Continued)

INTERLABORATORY COMPARISON PROGRAM Gross Beta Analysis of Air (Bqtfilter) 3/1/03 QAP-58 AIR GROSS 1.52+/-0.03 1.5+/-0.15 0.987, A Bq/filter BETA 1.47+/-0.03 1.44+/-0.03 Mean = 1.48+/-0.02 9/1/03 QAP-59 AIR GROSS 3.82+/-0.04 3.89+/-0.39 0.979, A Bq/filter BETA 3.83+/-0.04 3.79+/-0.04 Mean = 3.81+/-0.02 (1) Results reported as activity +/- I sigma.

(2) Ratio = Reported/EML (See Section D.3).

(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A) Evaluation Results, Acceptable.

D-26