NL-02-067, Indian Points Annual Radiological Environmental Operating Report for 2001

Indian Points Annual Radiological Environmental Operating Report for 2001

ML021280605
Person / Time
Site:	Indian Point
Issue date:	04/29/2002
From:	Herron J Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	Document Control Desk, NRC/FSME
References
IPN-02-035, NL-02-067
Download: ML021280605 (131)

Text

Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

Indian Point 3 NPP PO. Box 308 Buchanan. NY 1

051I Te: 91Z 736 8000 April 29, 2002 IPN-02-035 NL-02-067 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001

SUBJECT:

Indian Point Nuclear Generating Unit No. I Docket No.50-003 Indian Point Nuclear Generating Unit No. 2 Docket No. 50-247 Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 Indian Point's Annual Radiological Environmental Operatina Report for 2001

Dear Sir:

Enclosed please find one copy of the Indian Point Site Annual Radiological Environmental Operating Report for the period January 1, 2001 to December 31, 2001. No commitments are being made by this report.

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

Should you or your staff have any questions, please contact Mr. Robert Deschamps of the Indian Point Energy Center staff at (914) 736-8401.

Very truly yours,

)JJoh T. Herron

.Seni r Vice President Enclosure cc: next page

Docket Nos.50-003, 50-247, 50-286 Indian Point Nos. 1,2, 3 License Nos. DPR-5, DPR-26, DPR-64 I PN-02-035 NL-02-067 Page 2 of 2 Cc:

Mr. Hubert J. Miller Regional Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Patrick D. Milano, Project Manager Project Directorate I, Division of Reactor Physics 1/11 U.S. Nuclear Regulatory Commission Mail Stop 0-8-C2 Washington, DC 20555 Resident Inspectors' Office Indian Point Unit 2 U.S. Nuclear Regulatory Commission P.O. Box 38 Buchanan, NY 10511 Resident Inspectors' Office Indian Point Unit 3 U.S. Nuclear Regulatory Commission P.O. Box 337 Buchanan, NY 10511 Mr. William M. Flynn New York State Energy, Research and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Mr. Paul Eddy New York State Dept. of Public Service 3 Empire Plaza Albany, NY 12223 Mr. James C. Baranski Center for Environmental Health Flanigan Square, Room 530 547 River Street Troy, New York 12180

2001 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT INDIAN POINT NUCLEAR POWER PLANTS January 1 through December 31, 2001 0

© ENTERGY NUCLEAR NORTHEAST

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT ENERGY CENTER 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 (1P3)

January 1 - December 31, 2001

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 (LLD) and Critical Level (Lc) 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 3.6 Program Changes in 2001 3-8

TABLE OF CONTENTS (continued)

Page 4.0 RESULTS AND DISCUSSION 4-1 4.1 Direct Radiation 4-3 4.2 Airborne Particulates and Radioiodine 4-4 4.3 Hudson River Water 4-5 4.4 Drinking Water 4-5 4.5 Hudson River Shoreline Soil 4-6 4.6 Broad Leaf Vegetation 4-6 4.7 Fish and Invertebrates 4-7 4.8 Additional Media Sampling 4-7 4.9 Land Use Census 4-8 4.10 Conclusion 4-8 5.0 QUALITY ASSURANCE 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 of Indian Point)

A-5 A-2 RETS Sampling Locations (Within 10 Miles of Indian Point)

A-6 A-3 Non-RETS Sampling Locations A-7 C-1 Direct Radiation, 1991 to 2001 C-3 C-2 Radionuclides in Air - Gross Beta, 1991 to 2001 C-5 C-3 Hudson River Water-Tritium, 1991 to 2001 C-7 C-4 Drinking Water - Tritium, 1991 to 2001 C-9 C-5 Radionuclides in Shoreline Soil, 1991 to 2001 C-11 C-6 Broad Leaf Vegetation - Cs-1 37, 1991 to 2001 C-13 C-7 Fish and Invertebrates - Cs-137, 1991 to 2001 C-15 iii

LIST OF TABLES TABLE TITLE Paae A-1 Indian Point REMP Sampling Station Locations A-2 A-2 Lower Limit of Detection (LLD) 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, 2001 B-3 B-i a 2001 Air Sampling Deviations B-4 B-i b 2001 TLD Deviations B-4 B-ic 2001 Other Media Deviations B-4 B-2 RETS Annual Summary - 2001 B-5 B-3 2001 Direct Radiation, Quarterly Data B-9 B-4 Direct Radiation, 1996 Through 2001 Data B-1 0 B-5 2001 Direct Radiation, Inner and Outer Rings B-i 1 B-6 Gross Beta Activity in Airborne Particulate Samples - 2001 B-1 2 B-7 Concentrations of Gamma Emitters in Quarterly Composites of Air Particulate Samples - 2001 B-1 6 B-8 1-131 Activity in Charcoal Cartridge Samples - 2001 B-21 B-9 Concentrations of Gamma Emitters in Hudson River Water Samples - 2001 B-23 B-10 Concentrations of Tritium in Hudson River Water Samples - 2001 B-25 B-1 1 Gross Beta Activity and Concentrations of Gamma Emitters In Drinking Water Samples - 2001 B-26 B-12 Concentrations of Tritium in Drinking Water Samples - 2001 B-27 B-13 Concentrations of Gamma Emitters in Shoreline Soil Samples - 2001 B-28 B-1 4 Concentrations of Gamma Emitters in Broad Leaf Vegetation - 2001 B-29 B-15 Concentrations of Gamma Emitters in Fish and Invertebrate Samples - 2001 B-35 B-1 6 Annual Summary, Non-RETS Sample Results, 2001 B-36 B-17 Milch Animal Census - 2001 B-37 B-1 8 Land Use Census - 2001 B-38 iv

LIST OF TABLES (Continued)

TABLE TITLE Page C-1 Direct Radiation Annual Summary, 1991 to 2001 C-2 C-2 Radionuclides in Air, 1991 to 2001 C-4 C-3 Radionuclides in Hudson River Water, 1991 to 2001 C-6 C-4 Radionuclides in Drinking Water, 1991 to 2001 C-8 C-5 Radionuclides in Shoreline Soil, 1991 to 2001 C-10 C-6 Radionuclides in Broad Leaf Vegetation, 1991 to 2001 C-12 C-7 Radionuclides in Fish and Invertebrates, 1991 to 2001 C-14 D-1 2001 QA Program Schedule D-2 D-2 Ratio of Agreement D-3 D-3 2001 Cr-51 Results D-6 D-4 2001 Zn-65 Results D-8 D-5 JAF 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 contains descriptions and results of the 2001 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 2001 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 significantly increased levels of radioactivity attributable to 2001 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. This 2001 AREOR also contains summaries and discussions of the results of the 2001 program, trend analyses, potential impact on the environment, land use census, and interlaboratory comparisons.

During 2001, a total of 1262 analyses were performed on samples taken at RETS and non-RETS locations. Table B-1 contains a list of the quantity of samples collected, sample discrepancies, and sample efficiencies.

In summary, the levels of radionuclides in the environment surrounding Indian Point are significantly less than NRC limits as a result of Indian Point Station operations in 2001. The levels present in 2001 were within the historical ranges, i.e., previous levels resulting from natural and anthropogenic sources for the detected radionuclides. Consequently, Indian Point operations in 2001 did not result in approaching any environmental regulatory limits required by the NRC.

1-1

SECTION 2 INTRODUCTION

2.0 INTRODUCTION

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

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

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

1.

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

2.

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

To identify changes in activity, the environmental sampling schedule requires that analyses be conducted for specific environmental media on a regular basis.

The radioactivity profile of the environment is established and monitored through routine evaluation of the analytical results obtained.

The REMP designates sampling locations for the collection of environmental media for analysis. These sample locations are divided into indicator and control locations. Indicator locations are established near the site, where the 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 projected from plant releases are consistently too small to be detected. Plant related radionuclides were detected in 2001; however, residual radioactivity from atmospheric bomb tests and naturally occurring radioactivity were the predominant sources of radioactivity in the samples collected. An 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 (IP2) Nuclear Environmental Monitoring personnel perform collection of environmental samples for the entire Indian Point site.

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

3.2 Sample Analysis The analysis of Indian Point environmental samples is performed by three laboratories:

James A.

Fitzpatrick Nuclear Power Plant (JAFNPP)

Environmental Laboratory in Fulton, New York; and two commercial analytical laboratories: Environmental Inc. Midwest Laboratories, Illinois, and Duke Engineering and Services, Environmental Laboratory, Massachusetts. The JAFNPP lab at Fulton analyzes all samples except tritium samples, which were processed by Environmental Inc. Midwest Laboratories during the first quarter of 2001 and Duke Engineering and Services, Environmental Laboratory during the second, third and fourth quarters of 2001.

3.3 Sample Collection and Analysis Methodoloav 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 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 3-1

two TLDs at each site. TLDs are collected and processed on a quarterly basis. The results are reported as mR per standard quarter (91 days). The mR reported is the average of the two TLDs from each sample site.

3.3.2 Airborne Particulates and Radioiodine Air samples were taken at nine locations varying in distance from 0.28 to 20 miles (0.45 to 32 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-I. An automatic sampling apparatus is used to take representative samples. On a weekly basis, accumulated samples are taken from both sample points. These weekly river water samples are composited for monthly gamma spectroscopy analysis and quarterly for tritium analysis.

3.3.4 Drinking Water Samples of drinking water are collected monthly from the Camp Field Reservoir (3.3 miles NE, RETS designation Wbl). 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 Wcl 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.

3-2

3.3.6 Broad Leaf Vegetation Broad leaf vegetation samples are collected from three locations during the growing season. The designation for the two RETS indicator locations are Icl and Ic2, and the RETS control location is designated Ic3. See Figures A-1 and A-2. The samples are collected monthly, when available, and analyzed by gamma spectroscopy. These samples consist of at least 1 kg of leafy vegetation and are used in the assessment of the food product and milk ingestion pathways.

3.3.7 Fish and Invertebrates Fish and invertebrate samples are obtained from the Hudson River at locations upstream and downstream of the plant discharge. The 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 3-3

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

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 Indian Point. 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 within 5 miles (8 km) of Indian Point producing milk for human consumption. 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 Figure 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 Figure B-1 8.

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

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

3.4.1 Lower Limit of Detection (LLD) and Critical Level (L,)

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

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

The equation used to calculate the LLD is:

3-4

LLD = 4.66 K Sb, where:

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

- Instrument characteristics (e.g., efficiency)

- Sample size

- Counting time

- Media density (self-absorption)

- Radioactive decay

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

Lc = ka Sb (1 + TbI/Ts)'5 in cpm where:

ka = 1.645 (corresponds to a 95% confidence level)

Sb = standard deviation of the background count rate = (RTb)

Rb = background count rate (cpm)

Tb = background count time (min)

Ts = sample count time (min)

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

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

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

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

N N

where:

X= value of each individual observation N = number of observations E (ERRif PE =

'=' N where:

ERR, = 1 sigma error of the individual analysis N = number of observations 3.4.3 Table Statistics The averages shown in the summary table (Table B-2) are the averages of the positive values in accordance with the NRC's Branch Technical Position (BTP) to Regulatory Guide 4.8 (Reference 15). 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 above L,.

The REMP data show few values >L,; thus the 3-6

corresponding means are biased high. Exceptions to this include direct radiation measured by TLDs and gross beta radioactivity in air, which show monitoring results > Lc throughout the year.

In the data tables B-6 through B-1 5, 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 L. values for that sample. If multiple counts were performed on a sample and a radionuclide's values are "< 1.c" each time, the largest critical level is reported in the data table.

The historical data tables contain the annual averages of the values > L, for each year. The historical averages are calculated using only the positive values presented for 1991 through 2000. The 2001 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 is one atom disintegration per second. A Becquerel will normally be used with a volume or mass to express the radioactive concentration of some sample material.

Cubic meter is a metric volume slightly larger than a cubic yard.

It is abbreviated m3 and is used in this report as the unit for the volume of air.

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

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

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.

3-7

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.

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

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

Picocuries per cubic meter (pCi/m 3) is used to express concentrationfor all air samples.

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

Picocuries per liter (pCi/L) 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.

3.6 Proqram Changes in 2001 Indian Point Unit 1 and 2 submitted license amendments (No. 50 and 220, respectively) transferring its operating licenses (DPR-5 and 26, respectively) from Consolidated Edison to Entergy Nuclear Northeast Operations, Inc. effective September 6, 2001.

3-8

SECTION 4 RESULTS AND DISCUSSION

4.0 RESULTS AND DISCUSSION The 2001 Radiological Environmental Monitoring Program (REMP) was conducted in accordance with Indian Point's Radiological Environmental Technical Specifications and Radiological Effluent Controls (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 2001 and assessed the significance of the findings.

A summary of the results of the 2001 REMP is presented in Table B-2. This table lists the mean and range of all results > L. 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.

4-1

The environment contains a broad inventory of naturally occurring radionuclides which can be classified as cosmic ray induced (e.g., Be-7) 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 comparable 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, H-3 (which results from human activity as well as from natural occurrence), 1-131, Cs-1 34, and Cs-137 were detected above background levels in various RETS and non-RETS sample media in the vicinity of Indian Point.

The sources and significance of the presence of these radionuclides are described in later sections.

H-3 may be present in the local environment due to either natural occurrence, other man-made sources, or as a result of plant operations. The H-3 detected in 2001 resulted from a combination of sources. There was no H-3 detected at concentrations above the RETS required LLD. "Less than" values for H-3 are reported from the laboratory as less than sample LLD, which are less than the RETS required LLD.

The second group of radionuclides detected in 2001 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.

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. Only Cs-1 37 is found in weapons test debris. In 2001, the detected radionuclide(s) in some media attributable in part to past atmospheric weapons testing consisted of Cs-1 37. 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 2001 REMP comprises those that may be attributable to current plant operations. During 2001, H-3, 1-131, Cs 134, and Cs-137 were the only potentially plant-related radionuclides detected in some of the RETS and non-RETS samples.

4-2

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, and 2001 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 2001 REMP, though they (Co-58 and Co-60) have been historically observed.

In the following sections, a summary of the results of the 2001 REMP is presented by sample medium, and the significance of any positive findings discussed. It should be noted that naturally occurring radionuclides are omitted from the summary table (Table B-2) and further discussion.

4.1 Direct Radiation The environmental TLDs used to measure the direct radiation were TLDs supplied and processed by the JAFNPP Environmental Laboratory. The laboratory uses a Panasonic TLD system.

In 2001, the TLD program produced a consistent picture of ambient background radiation levels in the vicinity of the Indian Point Station. A summary of the annual TLD data is provided in Table B-2 and all the TLD data are presented in Tables B-3, B-4 and B-5. TLD sample site DR-40 is the control site for the direct radiation (DR) series of measurements.

Table B-3 provides the quarterly and annual average reported doses in mR per standard quarter for each of the direct radiation sample points, DR-1 through DR-41. The table also provides the sector for each of the DR sample points.

Table B-4 provides the mean, standard deviation, minimum and maximum values in mR per standard quarter for the years 1996 through 2000. The 2001 means are also presented in Table B-4. Table B-5 presents the 2001 TLD data for the inner ring and outer ring of TLDs.

The 2001 mean value for the direct radiation sample points was 14.7 mR per standard quarter. In 2000, the mean value was 14.5 mR and the mean value for the period 1996 through 2000 was 14.6 mR per standard quarter. At those locations where the 2001 mean value was higher, they are within historical bounds for the respective locations.

4-3

The DR sample locations are arranged so that there are two concentric rings of TLDs around the Indian Point site. The inner ring (DR-1 to DR-1 6) is close to the site boundary. The outer ring (DR-17 to DR-32) has a radius of approximately 5 miles from the three Indian Point units. The results for these two rings of TLDs are provided in Table B-5. The annual average for the inner ring was 14.5 mR per standard quarter while the average for the outer ring was 14.9 mR per standard quarter. The control location average for 2001 was 16.5 mR per standard quarter.

Table C-1 and Figure C-1 present the 10-year historical averages for the inner and outer rings of TLDS. The 2001 averages are consistent with the historical data. The 2001 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 2001 air particulate filter and charcoal cartridge analyses is presented in Table B-2. As shown, there were no radionuclides detected in the air attributable to plant operations.

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

Gross beta activity was found in air particulate samples throughout the year at all indicator and control locations. The average gross beta activity for the eight indicator air sample locations was 0.016 pCi/m3 and the average for the control location was 0.016 pCi/m 3. The activities detected were consistent for all locations, with no significant differences in gross beta activity in any sample.

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 2001 gross beta concentration was consistent with historical levels. Cs-137 has not been detected since 1987.

The charcoal cartridge analytical results are presented in Table B-8. "Less than" values are reported from the laboratory and presented in the table as sample LLD, which is < RETS required LLD. 1-131 was not detected (RETS Required LLD = 0.07 pCi/m 3) in the charcoal cartridge samples, which is consistent with historical trends.

4-4

From the data, it can be seen that no airborne radioactivity attributable to the operation of Indian Point was detected in 2001.

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.

In addition to naturally occurring radionuclides, tritium was the only radionuclide detected in the Hudson River water in 2001.

Tritium was detected in the discharge canal mixing zone at a maximum concentration of 323 pCi/L in 2001. The detected H-3 concentration was far below the RETS required LLD of 3000 pCiIL.

The relative insignificance of the H-3 concentration of 323 pCi/L can be seen by calculating the potential dose from the H-3. Using the guidelines set forth in the Offsite Dose Calculation Manual (Reference 24), it was conservatively calculated that the "maximum exposed individual" is an adult who would receive a dose of 0.0008 mrem/year.

The insignificance of this dose becomes readily apparent when it is compared to the annual average dose of 300 mrem from background (Reference 22).

Dose calculation assumptions, which continue to provide conservative estimates of dose, still yield an insignificant dose result.

The major assumptions are: all fish and invertebrates eaten in 2001 came from waters with 323 pCi/L H-3; the maximum exposed individual is an adult who consumed 21 kg of fish and 5 kg of invertebrates; and generic bioaccumulation factors for fish are representative. The potential dosimetric impact of 0.0008 mrem/year is insignificant.

Data on the radionuclides H-3 and Cs-1 37 detected in Hudson River water over the past ten years, are summarized in Table C-3. From this table and Figure C-3, it can be seen that the H-3 detected in the discharge canal, as well as the absence of detectable Cs-1 37, were consistent with the historical data trends.

4.4 Drinking Water The annual program summary table (Table B-2) contains a summary of the 2001 drinking water sample analysis results.

Results of the gamma spectroscopy analyses of the monthly drinking water samples are in Table B-1 1; 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.

4-5

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

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

In addition to the naturally occurring nuclides, Cs-134 and Cs-137 were identified in the Hudson River shoreline soil samples in 2001. Cs-137 was detected in four out of six samples from indicator locations. Cs-137 was detected at the control location in one out of four samples. The average concentration for the indicator locations was 203 pCi/kg-dry Cs-137 with a maximum concentration of 270 pCi/kg-dry Cs-1 37. The control location had a positive sample indicating 427 pCi/kg-dry Cs-1 37.

Cs-1 34 was detected with the Cs-1 37 in one of the six indicator samples with a concentration of 45 pCi/kg-dry. Cs-1 37 with the accompanying presence of Cs-134 would tend to date the radioactivity as resulting from recent plant operations. Cs-137 and Cs-134 have been detected in shoreline soil at indicator and control locations within 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 2001 samples are presented in Table B-1 4. Analyses of broad leaf vegetation samples revealed naturally occurring nuclides, and Cs-137 was detected in one of forty-seven samples from indicator locations at a concentration of 6.95 pCi/kg-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 ten 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 2001. None of the indicator samples revealed radionuclide concentrations greater than Lc values. Only naturally occurring 4-6

nuclides were detected. No Cs-134, Cs-137, Co-58, or Co-60 was 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, and precipitation 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 two indicator samples and two out of four control samples with an average concentration of 44.5 and 50.6 pCi/kg-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-1 37 was detected in four out of four control samples at an average concentration of 15.9 pCi/kg-wet. Cs-137 was not found in indicator samples. Data are consistent with historical trends.

Soil samples were obtained at two indicator locations and one control location. Cs-1 37 was detected in one indicator sample at a concentration of 109 pCi/kg-dry. Historically, Cs-1 37 is detectable in numerous environmental media because of previous atmospheric weapons testing.

Precipitation samples were analyzed for H-3 (tritium) and plant-related nuclides at two locations. No tritium or other plant related nuclides were detected at either location.

Historically, tritium has been detected in precipitation at both indicator and control locations.

The Algonquin Outfall samples were analyzed for tritium and plant-related nuclides. The samples did not show any tritium or other plant-related nuclides.

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 in 2001 had no detectable adverse radiological impact on the environment.

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4.9 Land Use Census A census was performed in the vicinity of Indian Point in 2001. 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 2001 census were the same as the 2000 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 in two sectors at the site boundary in lieu of performing a garden census. Analysis results are discussed in section 4.6 and presented in Table B-14, Table C-6 and Figure C-6.

4.10 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 2001 REMP reveal that operations at the station did not result in an adverse impact on the environment.

The results of the 2001 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 2001 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 QUALITY ASSURANCE

5.0 QUALITY ASSURANCE The Indian Point Radiological Environmental Monitoring Program (REMP) includes a quality assurance (QA) program. The QA program ensures that the REMP fulfills its intended function and that results of the REMP are reliable. The QA program of the REMP consists of operational (i.e., day-to-day) activities as well as routine inspections and audits.

The operational quality assurance activities are:

"* Submission for analysis of duplicate (split) samples to the radioanalytical laboratory to verify reproducibility (precision) of results, and

"* Submission for analysis of environmental samples, spiked with known levels of radioactivity, to the radioanalytical laboratory to verify accuracy of results.

During 2001, 57 samples involving 90 individual analyses were requested of the JAFNPP Environmental Laboratory that processes the Indian Point REMP samples.

Spiked air, water, soil, and vegetation samples were submitted for analysis. The spiked samples were obtained from a commercial vendor laboratory and sent to the JAFNPP Environmental Laboratory to be analyzed as regular environmental samples.

The supply vendor certified the activity levels of the spikes at the time of preparation.

Of the 57 samples, two gross beta air particulate filters were discounted from the sample load due to human factor errors. These filters were compromised in an attempt to disguise their spiked sample status prior to shipment to JAFNPP Environmental Lab.

After the Environmental Laboratory analyzed the spike samples, statistical tests were performed using both the spike vendor's and the Laboratory's data. In summary, of the 83 identified and analyzed isotopes, 80 met the Indian Point acceptance criteria, which yields an overall performance rating of 96.4%.

A summary of the identified nonconforming samples:

All mixed gamma samples for water, vegetation and soil did not detect Cr-51 (4 samples.) One mixed gamma sample for water did not detect 1-131.

All other analysis for the mixed gamma samples fell within the acceptance criteria. These types of nonconformities and their associated corrective actions are discussed in detail in section D.4.2.

" One gross beta air particulate filter did not meet the criteria (-17%.) With the exception of this filter, the remaining 24 samples of this type were within the acceptance range.

5-1

"* One water sample analyzed for H-3 failed the prescribed statistical criteria.

Additionally, a separate water sample for gross beta failed to meet the criteria.

The Environmental Laboratory's performance in other comparable areas, notably the Interlaboratory Comparison Program, remains good. We conclude that results from the JAFNPP Environmental Laboratory are expected to remain reliable.

Reviews and audits of the Radiological Environmental Monitoring Program are conducted by Entergy Nuclear Northeast personnel and include:

"* Audits of Indian Point and radioanalytical contractor procedures related to the Radiological Environmental Monitoring Program by Entergy Nuclear Northeast Quality Assurance (QA) personnel.

"* Assessment of the radioanalytical contractor's performance in the Analytics Environmental Cross Check Program and the Environmental Measurements Laboratory Quality Assurance Program (see Appendix D).

"* Audits of Indian Point sample collection and radioanalytical laboratory processes by QA personnel and program personnel.

Conduct of the quality assurance program in 2001 ensured that sampling and analysis of environmental media at Indian Point were conducted in accordance with quality assurance requirements specified in Regulatory Guide 4.15 (Reference 11) and internal procedures (Reference 2). Performance of routine audits demonstrates this compliance.

The quality assurance programs of Entergy Nuclear Northeast's Environmental Laboratory demonstrate that all requirements specified in 10 CFR Part 50 Appendix B and applicable sections of Regulatory Guide 4.15 are achieved. In addition, the JAFNPP Laboratory's performance in the Analytics Environmental Cross Check Program and the Environmental Measurements Laboratory Quality Assurance Program was satisfactory (see Appendix D).

In summary, the quality assurance program conducted in conjunction with the Indian Point Radiological Environmental Monitoring Program included audits and evaluations of in-house and contractor procedures, work functions, and quality assurance programs. Review of the 2001 quality assurance program indicated that the Radiological Environmental Monitoring Program was performed in accordance with the RETS.

5-2

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

9.

Entergy Nuclear Northeast, Quality Control Program for Environmental Monitoring Rev. 5 (RS - 8.500)

10.

Quality Assurance Manual Environmental Analysis Department Teledyne Isotopes, Westwood, NJ - Knoxville, TN.

11.

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.

12.

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.

13.

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

6-1

14.

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

15.

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

16.

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

17.

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

18.

Entergy Nuclear Northeast, James A. FitzPatrick Nuclear Power

Plant, Radiological and Environmental Services Department Environmental Surveillance Procedures.

19.

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

20.

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

21.

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.

22.

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

23.

Entergy Nuclear Northeast (IP3), Offsite Dose Calculation Manual - Part 1, Radiological Effluent Controls-Part 2 Offsite Dose Calculation Manual, Revision 15, December 2001.

24.

Entergy Nuclear Northeast (1P2), Offsite Dose Calculation Manual Rev. 6, October, 1999.

25.

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.

26.

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

6-2

27.

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.

28.

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

29.

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

30.

Office of Environmental Management, Semi-Annual Report of the Department of Energy, Quality Assessment Program. EML 613, June 2001.

31.

Office of Environmental Management, Semi-Annual Report of the Department of Energy, Quality Assessment Program, EML 615, December 2001.

32.

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

6-3

APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS REQUIREMENTS

APPENDIX A Environmental media are sampled at the locations specified in Table A-1 and shown in Figures A-i, 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 (NR) samples are also listed but have no RETS designation code. This table gives the complete listing of sample locations used in the 2001 REMP. GPS coordinates of the sample points were used to calculate the distances from the 10 mile Emergency Planning Zone center and sectors used by the New York State Emergency Management Office.

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 in various media. Sample results that exceed these levels and are due to plant operations require that a special report be submitted to the NRC.

In addition to the sampling outlined in Table A-i, there is 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

%JI IILU 0.35 Mi (SSE) at 1580 Al Onsite -

Air Particulate, Al 0.28 Mi (SW) at 2340 Radioiodine A4 Onsite -

Air Particulate, 5

A4 NYU Tower 0.88 Mi (SSW) at 2080 Radioiodine, DR10 Direct Gamma 7

Wbl Camp Field Reservoir 3.3 Mi (NE) at 450 Drinking Water 9

Wal Plant Inlet (Hudson River Intake)*

Onsite -

FIR Water 0.16 Mi (W) at 2730HR Water 10 Wa2 Discharge Canal (Mixing Zone)

Onsite -

HR Water, NR 0.3 Mi (WSW) at 2490 HR Bottom Sediment 14 DR7 Water Meter House OnsiteDirect Gamma 0.3 Mi (SE) at 1330 NR HR Aquatic Vegetation, 17 NR Off Verplanck 1.5 Mi (SSW) at 202.50 HR Shoreline Soil, NR HR Bottom Sediment Cortlandt Yacht Club 20 DR38 Aontrose Marna 1.5 Mi (S) at 1800 Direct Gamma (AKA Montrose Marina)

NR Lovett Power Plant 1.6 Mi (WSW) at 244' Air Particulate, 22 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 Ibl 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, DR4 Direct Gamma, HR 28 NR Lent's Cove 0.45 Mi (ENE) at 0690 Bottom Sediment, NR HR Aquatic Vegetation NR Air Particulate, 29 NR Grassy Point 3.37 Mi (SSW) at 1960 Radioiodine, DR39 Direct Gamma

• = Control location HR = Hudson River NR = non RETS R/S = Reuter Stokes A-2

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS Hamilton Street (Substation) 2.88 Mi (NE) at 0530 Direct Gamma Onsite -

Drc am 34 DR9 South East Corner of site 1752 0

Direct Gamma 35 DR5 Broadway & Bleakley Avenue 0nite -

DEc Gamma

.37 Mi (E) at 0920 iet a

m 38 DR34 Furnace Dock (Substation) 3.43 Mi (SE) at 141 0 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 Wcl White Beach 0.92 Mi (SW) at 226-HR Shoreline Soil, DR1 1 Direct Gamma 56 DR37 Verplanck - Broadway & Sixth Street 1.25 Mi (SSW) at 2020 Direct Gamma 57 DR1 Roa Hook 2 Mi (N) at 0050 Direct Gamma 58 DR17 Route 9D - Garrison 5.41 Mi (N) at 3580 Direct Gamma 59 DR2 Old Pemart Avenue 1.8 Mi (NNE) at 0320 Direct Gamma 60 DR18 Gallows Hill Road & Sprout Brook 5.02 Mi (NNE) at 0290 Direct Gamma Road 61 DR36 Lower South Street & Franklin Street 1.3 Mi (NE) at 0520 Direct Gamma 62 DR19 Westbrook Drive 62_________

DR19________ (near the Community Center) 5.03 Mi (NE) at 0620 Direct Gamma 64 DR20 Lincoln Road - Cortlandt 4.6 Mi (ENE) at 0670 Direct Gamma 64________

DR20__________ (School Parkinq Lot) 4.6_Mi_(ENE)_at_067_

DirectGamma 66 DR21 Croton Avenue - Cortlandt 4.87 Mi (E) at 0830 Direct Gamma 67 DR22 Colabaugh Pond Road - Cortlandt 4.5 Mi (ESE) at 1140 Direct Gamma 69 DR23 Mt. Airy & Windsor Road 4.97 Mi (SE) at 1270 Direct Gamma 71 DR25 Warren Ave - Haverstraw 4.83 Mi (S) at 1880 Direct Gamma 72 DR26 Railroad Avenue & 9W - Haverstraw 4.53 Mi (SSW) at 2030 Direct Gamma 73 DR27 Willow Grove Road & Captain 4.97 Mi (SW) at 2260 Direct Gamma Faldermeyer Drive 74 DR12 West Shore Drive - South 1.59 Mi (WSW) at 2520 Direct Gamma 75 DR28 Palisades Parkway 4.65 Mi (NW) at 3100 Direct Gamma 76 DR13 West Shore Drive - North 1.21 Mi (W) at 2760 Direct Gamma

• = Control location HR = Hudson River NR = non RETS RIS = Reuter Stokes A-3 33 DR33

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING

.OAI~

. SAPLELOCAIONDISTANCE S

~AMPL ~TYPES STATION SMP.

_______DESIGNATIONS

~

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 2950 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 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 88 DR6 R/S Pole #6 0.32 Mi (ESE) at 1180 Direct Gamma 89 DR35 Highland Ave & Sprout Brook Road 89_________

DR35__________ (near rock cut) 2.89 Mi (NNE) at 0250 Direct Gamma 90 DR3 Charles Point 0.88 Mi (NE) at 047' Direct Gamma 92 DR24 Warren Road - Cortlandt 3.84 Mi (SSE) at 1490 Direct Gamma A2 Air Particulate, A2 nst-Radioiodine, 94 IP Training Center Onsite Ic2 0.39 Mi (S) at 1930 Broadleaf Vegetation, NR Soil A3 Air Particulate, A3 Meteorological Tower Onsite -

Radioiodine, Icl 0.46 Mi (SSW) at 2080 Broadleaf Vegetation, NR Soil 99 NR Algonquin Outffall Onsite 10.34 Mi (SW) at 2370 Special Outfall

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

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

Peekskill Rockland County G

Indian Point 04 Ibi 6]

12Hudson lc1

]2

'c River I

Buck Verplanok 0//

38 Key:

A - Waterborne: Surface (HR) Wa#

O - Direct Radiation Sample Location DR#

El - Air Particulate & Radioiodine A#

-<= - HR Shoreline Sediment Wc#

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

A-5

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

Roseton (20 mi. N):

[5 Ic3 Upstream:

Ib2 Orange County Bear Mountain Bridge 0

Rockland County 10 O - Direct Radiation Sample Location DR#

M - Air Particulate & Radioiodine A#

<>- HR Shoreline Sediment Wc#

O

- Waterborne: Drinking Wb#

Putnam County 5 miles Westchester County Ic3 - Broadleaf Vegetation Ib2 - Fish and Invertebrates (where available upstream)

A-6 Key:

FIGURE A-3 NON-RETS SAMPLING LOCATIONS N

Orange County Bear Mountain Bridge 10: 4 V

99: sp 17:

V 29: U Rockland County 0 - Air Particulate & Radioiodine V - Aquatic Vegetation S-HR Bottom Sediment p - Precipitation Roseton (20 mi. N): 23: p

• Putnam County Cold Spring (10.8 mi. N) : 84: V

-28:

V lian

)int 4

W5 *

)5:

on 5 miles r

27: E

/

Westchester County S-HR Shoreline Sediment

• - Soil sp - Special Outfall A-7 Key:

P

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

AIRBORNE~K oo ANLYIS WATER PARTICULATES

ýFISH MILK PRDOS EDIMEN (pCV/L).

OR GASES, (pCi/kg, wet)

_(pCi/L).

(pCUkgwet)

_____ (p~m3 (pC/kgwt Gross 0 4

0.01 H-3 2000 (c)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1 (d) 0.07 1

1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 (a) This list does not mean that only these nuclides are to be considered. Other identifiable peaks shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

(b) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13 (Reference 29).

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

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

A-8

TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES A-9 H-3 20000___

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

1 1

300 (a) For drinking water samples. This is the 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/L may be used.

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

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS

SUMMARY

APPENDIX B B.1 2001 Annual Radiological Environmental Monitoring Program Summary The results of the 2001 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-1 6 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 15). In addition, the data obtained from the analysis of all the individual RETS samples are provided in Tables B-3 through B-15.

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

B.2 Land Use Census In accordance with Sections 4.11.B 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 census are presented in Tables B-1 7 and B-1 8, resp ectively. In lieu of identifying and sampling the nearest garden of greater than 50m, at least three kinds of broad leaf vegetation were sampled near the site boundary in two sectors and at a designated control location (results are presented in Table B-14).

B.3 Sampling Deviations During 2001, environmental sampling was performed for six media types required by RETS, five other media types and direct radiation. A total of 1278 samples (1246 RETS and 32 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-i a for air samples, B-i b for TLDs, and B-ic for other environmental media.

B-1

B.4 Analytical Deviations No analytical deviations were identified during the 2001 sampling period.

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

B-2

TABLE B-1

SUMMARY

OF SAMPLING DEVIATIONS 2001 I TOTAL NUMBER OF SAMPLING IREASON.

MDASCHEDULED A

EFFICIENCY~.'

FOR" MEDIASAMPLES DEVIATIONS ATO RETS MEDIA PARTICULATES IN AIR 468 5

99 SEE TABLE B-la SEE TABLE CHARCOAL FILTER 468 5

99BL B-1la SEE TABLE TLD*

166 3

98 Bl B-lb HUDSON RIVER WATER 32 0

100 DRINKING WATER 16 0

100 SHORELINE SOIL 10 0

100 BROAD LEAF SEE TABLE VEGETATION B-1 c FISH & INVERTEBRATES 14 0

100 SUBTOTALS 1246 14 99 NON-RETS MEDIA AQUATIC VEGETATION 8

2 75 HUDSON RIVER BOTTOM SEDIMENT SOIL 3

0 100 PRECIPITATION 8

0 100 OUTFALL 5

0 100 S U BTOTALS j

32 2

94 SEE TABLE B-ic O VERA*LTOTALS 1278 16 99 TOTAL NUMBER OF ANALYSES REPORTED =

1262

• Two out of the three TLD sample deviations where identified before the end of the sample period and two replacement TLDs were issued for these locations. However, since the sample results are not for a full period, they are not considered to be representative samples.

B-3

TABLE B-ia / B-i b / B-ic TABLE B-la 2001 Air Sampling Deviations STATION WEEK' PROBLEM /ACTIONS TO PREVENT RECURRENCE

• z

1. 94 IP Training Center 1

Low volume due to power outage./ No actions can be taken to (Air Particulate & Charcoal) prevent a future power outage.

1. 5 NYU Tower 30 Low volume due to pump failure./Replaced pump.

(Air Particulate & Charcoal) w33 Low volume due to pump being turned off and the sample site

1. 5 NYU Tower unlocked. Technicians are verifying the sample site locked prior (Air Particulate & Charcoal) to leaving the site.

1. 22 Lovett Power Plant 33 Low volume due to faulty outlet,/Plant maintenance repaired the (Air Particulate & Charcoal) outlet.

1. 22 Lovett Power Plant 36 Low volume due to faulty outlet./A new permanent A.C. power (Air Particulate & Charcoal) feed has been installed to correct the loss of power problems.

TABLE B-1 b 2001 TLD Deviations STATION--

QUARTER PROBLEM! ACTIONS TO PREVENT RECURRENCE*,

1. 35 Broadway &

2nd QTR (TLD)

TLD missing / Replaced TLD and continued to trend missing Bleakley Avenue TLDs for patterns.

1. 5 NYU Tower 3rd QTR (TLD)

Sample site vandalized and TLD missing / Replaced TLD and continued to trend missing TLDs for patterns.

Sample site vandalized and TLD missing. / Replaced TLD and

1. 5 NYU Tower 4th QTR (TLD) moved theTLD storage location away from the sample site fence.

TABLE B-lc 2001 Other Media Deviations STATION SAMPLE SCHEDULE PROBLEM IACTIONS TO PREVENT RECURRENCE April samples were available for only Sweet Cicely and Sorrel at

1. 95 Meteorological Tower April (Broad Leaf Vegetation) this location. / Sampled three types of broad leaf vegetation at this location in May.

No spring sample available. / Attempted to obtain samples at the Grassy Point and Lent's Cove locations along with the Off

1. 17 Off Verplanck Spring (Aquatic Vegetation)

Verplanck location during weeks 19, 23, and 24. No vegetation was present for sampling. Sampled aquatic vegetation in summer.

No spring sample available. / Attempted to obtain samples at the

1. 28 Lent's Cove Spring (Aquatic Vegetation)

Grassy Point and Off Verplanck locations along with the Lent's Cove location during weeks 19, 23, and 24. No vegetation was present for sampling. Sampled aquatic vegetation in summer.

B-4

TABLE B-2*

RETS ANNUAL

SUMMARY

- 2001 DIRECT RADIATION (mR / standard quarter)

R-3 TLD Reads 163 N/A 14.5 (163/163) / 7.2 -21.7

1. 14 Water Meter House 0.3 Mi. (1330) DR7 17.2 (4/4) / 14.3 -21.7 16.5 (4/4) / 13.2 -20.3 0

AIR PARTICULATES

1. 94 IP Training Center 0.016 (52152) 0 AND RADIOIODINE GB (463) 0.01 0.016 (463/463)/0.004-0.036 0.39 Mi. (1930) 0.007-0.028 (pCi/rn3) B-6, B-7, B-8 0.017 (51/51)/0.007-0.036 1-131(463) 0.07

< LLD

< LLD

< LLD 0

GSA (36)

Cs-134 0.05

< LK:

<L

<L0 0

Cs-137 0.06

< LK

< L

< L 0

SURFACE HUDSON

1. 10 Discharge Canal Mixing RIVER WATER (pCi/L)

H-3 (8) 3000 323 (1/4)1323-323 Zone - 0.3 Mi (2490)

< LLD 0

B-9, B-10 323 (1/4)1323-323 GSA (24)

Mn-54 15

<L

<K

<L 0

Co-58 15

< L,

< LK

< Lc 0

Fe-59 30

< L,

< LK

< Kc 0

Co-60 15

<L

< Le

< L 0

Zn-65 30

<K

< LK

< L 0

Zr/Nb-95 15

<K

< L

< LK 0

1-131 15

<K

< LK

< K-;

0 Cs-134 15

<L

< L

< LK 0

Cs-137 18

<K

< Lc

< K-;

0 Ba/La-140 15

< LK

< Lc

< L, 0

1. 7 Camp Field Reservoir DRINKING WATER GB (12) 4 2.05(12/12) /0.71-3.19 3.3 Mi (450)

N/A 0

(pCi/L) B-1 1, B-12 2.05 (12212) / 0.71-3.19 H-3 (4) 2000

< LLD

< LLD N/A 0

GSA (12)

Mn-54 15

< L0

< Lc N/A 0

Co-58 15

< LK

< L, N/A 0

Fe-59 30

< Lc

< Lc N/A 0

Co-60 15

< LK

< Lc N/A 0

Zn-65 30

< Lc

< K N/A 0

B-5

TABLE B-2*

RETS ANNUAL

SUMMARY

- 2001 CN'TU vv (CON-T)

L./IIIUvuJ 1-131 Cs-1 34 Cs-1 37 Rn/I *-14A3 1

15 18

<K

<K

<K

<KL

<K

<Kc N/A N/A N/A N/A U

0 0

0 0

SHORELINE SOIL (pCi/kg - dry) B-13

1. 17 Off Verplanck 1.5 Mi.

Cs-1 34 150 44.9 (1/6)144.9-44.9 (202.5°)

< L0 44.9 (1/2)144.9-44.9

1. 17 Off Verplanck 1.5 Mi.

Cs-1 37 180 203 (4/6) / 100-270 (202.50) 427(1/4) /427-427 0

222 (2/2)1 190-254 BROADLEAF VEGETATION GSA (70)

(pCi/kg - wet) B-14 1-131 60

< L,

< L,

< L0 0

Co-60 N/A

< Lc

< L,

< L, 0

Cs-134 60

< -c

< LK

< LK 0

1. 94 IP Training Center Cs-137 80 6.95 (1/47)16.95-6.95 0.39 Mi. (1930)

< L 0

6.95 (1/24) /6.95-6.95 FISH AND INVERTEBRATES GSA (14)

(pCi/kg - wet) B-15 Mn-54 130

<KI

<KL

<KL 0

Co-58 130

< L,

< LK

< LK 0

Fe-59 260

< LK

< LK

< LK 0

Co-60 130

< Lc

< LK

<K, 0

Zn-65 260

< L,

< LK

< K, 0

Cs-134 130

< Lo

< L-;

< K, 0

Cs-137 150

< LK

< LK

< K 0

B-6 NOTE: The location designation of the highest annual mean for direct radiation in the 2000 AREOR was incorrectly reported as UH-13.

The correct designation for the Pailsades Pkwy South location is DR-31.

Table B-2 Notation 2001 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 (Lc).

(e)

=

"Less than" results for tritium and airborne radioiodine are reported as

<sample LLD, which is less than the RETS Required LLD.

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 pCi/kg-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) 2001 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.

Four out of six samples from indicator locations had Cs-137 and one out of six samples from indicator locations had Cs-134. The mean of the Cs-1 37 from the four indicator location sample results that were > L. was 203 pCi/kg-dry. The range of the samples results > L, was 100 to 270 pCi/kg-dry. Since there was only one indicator location sample result > L. for Cs-1 34, the mean and range of the Cs-1 34 is listed as 44.9 pCi/kg-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, Verplanck, 1.5 miles from Indian Point at compass direction 202.5 degrees. The mean for this indicator sample site is 222 pCi/kg-dry Cs-137, two samples were taken and both sample results were > Lc. The range of the samples results that were > L, was 190 to 254 pCi/kg-dry.

The highest indicator mean for Cs-134 is from sample location 17, Verplanck, 1.5 miles from Indian Point at compass direction 202.5 degrees. Since there was only one indicator location sample result > Lc for Cs-134, the mean and range of the sample result indicating Cs-134 are listed as 44.9 pCi/kg-dry. Two samples were taken and one was > Lc.

6. The control location column is next. For 2001, no Cs-134 was detected at the control location. Cs-1 37 was detected in one of the four samples at 427 pCi/kg-dry.

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 2001 DIRECT RADIATION, QUARTERLY DATA

- ~

A f Er.

Anr-.

i* a nr'-rnr"l 4

1 1

NNE 12.9 15.4 13.6 L1.5 1I.u 17.5 14.9 DR-03 NE 11.8 10.6 13.0 14.4 12.5 DR-04 ENE 12.7 15.2 14.8 15.9 14.7 DR-05 ENE 13.5 13.3 13.2 13.3 DR-06 ESE 12.1 12.6 13.9 13.8 13.1 DR-07 SE 14.3 15.8 16.8 21.7 17.2 DR-08 SSE 12.2 14.3 13.5 16.3 14.1 DR-09 S

13.3 13.9 15.1 15.6 14.5 DR-l0 SSW 13.2 13.3 5.3**

7.4**

13.3 DR-11 SW 9.5 11.2 12.1 14.2 11.8 DR-12 WSW 14.7 16.2 16.4 18.4 16.4 DR-13 WSW 16.4 19.2 17.0 20.3 18.2 DR-14 WNW 11.1 13.4 12.6 14.1 12.8 DR-15 NW 12.5 16.3 14.2 14.4 14.4 DR-16 NNW 12.2 15.4 15.8 15.3 14.7 DR-17 N

15.5 17.6 16.0 17.7 16.7 DR-18 NNE 12.5 14.6 15.4 16.0 14,6 DR-19 NE 13.5 18.2 13.8 15.8 15.3 DR-20 ENE 12.5 14.7 15.3 16.1 14.7 DR-21 E

12.7 14.3 12.3 13.1 13.1 DR-22 ESE 11.2 13.9 11.7 14.1 12.7 DR-23 SE 12.6 15.7 14.6 16.0 14.7 DR-24 SSE 12.6 15.0 15.4 14.4 14.4 DR-25 S

13.2 11.7 12.1 11.9 12.2 DR-26 SSW 12.9 13.0 14.5 17.0 14.4 DR-27 SW 12.3 14.5 13.7 14.1 13.7 DR-28 NW 12.2 14,7 15.3 16.1 14.6 DR-29 W

13.9 19.4 17.9 16.1 16.8 DR-30 SNS 14.6 19.9 14.7 18.7 17.0 DR-31 WSW 15.3 17.5 19.0 22.4 18.6 DR-32 NNW 12.3 14.2 13.0 17.7 14.3 DR-33 NE 8.9 8.8 9.1 9.2 9.0 DR-34 SE 12.0 17.6 15.7 15.4 15.2 DR-35 NNE 13.7 17.9 14.0 15.3 15.2 DR-36 NE 13.0 17.5 16.1 19.1 16.4 DR-37 SSW 13.1 15.4 13.0 14.1 13.9 DR-38 S

13.1 17.9 13.0 14.4 14.6 DR-39 SSW 14.5 15.9 18.0 17.5 16.5 DR-40 CONTROL 13.2 16.1 16.3 20.3 16.5 DR-41 SSE 12.2 13.8 14.5 14.8 13.8 AV iiE 12.9 15.2 14.6 16.1 14,7 B-9 DR-02 Data not available

• • TLD result is not representative of the sample period due to being installed in the middle of the sampling period to replace a missing TLD. This sample result was not used in the calculation of the average.

TABLE B-4 DIRECT RADIATION, 1996 THROUGH 2001 DATA (mR per Standard Quarter) 16.2 I0.1 I.U 19.8 14.9 B-10 DR-02 18.5 1.5 DR-03 12.1 0.4 11.6 12.6 12.5 DR-04 13.2 0.6 12.8 14.1 14.7 DR-05 13.9 0.5 13.3 14.5 13.3 DR-06 13.9 0.4 13.3 14.4 13.1 DR-07 15.9 0.7 15.0 16.7 17.2 DR-08 12.8 0.6 12.1 13.3 14.1 DR-09 13.0 0.6 12.5 13.8 14.5 DR-10 13.9 0.6 12.9 14.6 13.3 DR-11 11.5 0.4 10.9 12.1 11.8 DR-12 16.1 0.9 14.7 17.0 16.4 DR-13 19.5 1.1 17.7 20.3 18.2 DR-14 14.2 0.8 13.3 15.1 12.8 DR-15 14.1 0.9 12.6 15.0 14.4 DR-16 15.0 0.9 13.6 15.9 14.7 DR-17 14.5 0.9 13.0 15.3 16.7 DR-18 14.6 0.4 14.2 15.2 14.6 DR-19 15.4 0.5 14.7 15.9 15.3 DR-20 14.1 0.7 12.9 14.8 14.7 DR-21 14.3 0.7 13.3 15.2 13.1 DR-22 12.1 0.6 11.6 13.0 12.7 DR-23 14.4 0.3 14.0 14.7 14.7 DR-24 14.5 0.6 14.0 14.9 14.4 DR-25 12.6 0.6 11.8 13.3 12.2 DR-26 14.0 0.6 13.2 14.7 14.4 DR-27 14.0 1.0 12.7 15.4 13.7 DR-28 15.6 1.0 14.8 17.3 14.6 DR-29 18.2 0.9 16.9 19.3 16.8 DR-30 17.1 0.7 16.0 17.8 17.0 DR-31 19.2 0.8 18.0 20.1 18.6 DR-32 13.6 0.6 12.7 14.0 14.3 DR-33 10.7 1.6 8.5 12.2 9.0 DR-34 13.7 0.5 12.9 14.2 15.2 DR-35 14.9 0.6 13.9 15.3 15.2 DR-36 16.1 1.0 14.9 17.6 16.4 DR-37 14.2 0.7 13.1 15.0 13.9 DR-38 12.8 0.9 11.5 13.7 14.6 DR-39 16.0 1.0 14.3 16.7 16.5 DR-40 16.2 0.8 15.5 17.6 16.5 DR-41 13.6 0.6 12.8 14.5 13.8 Averagebi 14.6 0.7 13.6 15.4 14.7

TABLE B-5 2001 DIRECT RADIATION INNER AND OUTER RINGS (mR per Standard Quarter) nnerRig Outer Ring IDke RIn Annr~ig

~e~o' ual Ave~rage AnnuaIl~verage DR-01 DR-17 N

17.0 16.7 DR-02 DR-18 NNE 14.9 14.6 DR-03 DR-19 NE 12.5 15.3 DR-04 DR-20 ENE 14.7 14.7 DR-05 DR-21 E

13.3 13.1 DR-06 DR-22 ESE 13.1 12.7 DR-07 DR-23 SE 17.2 14.7 DR-08 DR-24 SSE 14.1 14.4 DR-09 DR-25 S

14.5 12.2 DR-10 DR-26 SSW 13.3 14.4 DR-11 DR-27 SW 11.8 13.7 DR-12 DR-31 WSW 16.4 14.6 DR-13 DR-29 W

18.2 16.8 DR-14 DR-30 WNW 12.8 17.0 DR-15 DR-28 NW 14.4 18.6 DR-16 DR-32 NNW 14.7 14.3 Average*

14.5 14.9 B-11

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2001 (pCi/m 3 +/- 1 sigma)

STATION #

Week #

End Date 45____

27 94 9

1 01/09/01 0.019 + 0.001 0.019 + 0.001 0.019 + 0.002 0.019 + 0.002 2

01/16/01 0.019 + 0.001 0.017 + 0.001 0.016 + 0.002 0.016 + 0.002 0.017 + 0.002 3

01/23/01 0.016 + 0,001 0.015 + 0.001 0.017 + 0.002 0.017 + 0.002 0.013 + 0.001 4

01/30/01 0.021 + 0.001 0.018 + 0.001 0.021 + 0.002 0.022 + 0.002 0.021 + 0.002 5

02/06/01 0.016 + 0.001 0.013 + 0.001 0.015 + 0.002 0.016 + 0.002 0.016 + 0.002 6

02/13/01 0.015 + 0.001 0.014 + 0.001 0.016 + 0.001 0.013 + 0.001 0.016 + 0.002 7

02/20/01 0.019 + 0.001 0.021 + 0.001 0.018 + 0.002 0.021 + 0.002 0.020 + 0.002 8

02/27/01 0.013 + 0.001 0.016 + 0.001 0.017 + 0.001 0.017 + 0.002 0.020 + 0.002 9

03/05/01 0.019 + 0.001 0.017 + 0.001 0.018 + 0.002 0.019 + 0.002 0.021 + 0.002 10 03/12/01 0.009 + 0.001 0.008 + 0.001 0.009 + 0.001 0.010 + 0.001 0.008 + 0.001 11 03/20/01 0.009 + 0.001 0.011 + 0.001 0.013 + 0.001 0.012 + 0.001 0.009 + 0.001 12 03/27/01 0.010 + 0.001 0.008 + 0.001 0.012 + 0.001 0.009 + 0.001 0.011 + 0.001 13 04/03/01 0.006 + 0.001 0.006 + 0.001 0.008 + 0.001 0.007 + 0.001 0.006 + 0.001 14 04/10/01 0.011 + 0.001 0.012 + 0.001 0.013 + 0.001 0.014 + 0.002 0.015 + 0.002 15 04/16/01 0.011 + 0.001 0.009 + 0.001 0.011

+ 0.001 0.011 + 0.001 0.011 + 0.001 16 04/24/01 0.020 + 0.001 0.022 + 0.001 0.020 + 0.002 0.022 + 0.002 0.018 + 0.002 17 04/30/01 0.019 + 0.001 0.020 + 0.001 0.021

+ 0.002 0.022 + 0.002 0.021 + 0.002 18 05/08/01 0.021 + 0.001 0.018 + 0.001 0.023 + 0.002 0.019 + 0.002 0.023 + 0.002 19 05/15/01 0.016 + 0.001 0.016 + 0.001 0.018 + 0.002 0.017 + 0.002 0.016 + 0.002 20 05/22/01 0.010 + 0.001 0.011 + 0.001 0.010 + 0.001 0.009 + 0.001 0.010 + 0.001 21 05/29/01 0.005 + 0.001 0.005 + 0.001 0.007 + 0.001 0.005 + 0.001 0.006 + 0.001 22 06/05/01 0.007 + 0.001 0.007 + 0.001 0.008 + 0.001 0.010 + 0.001 0.008 + 0.001 23 06/12/01 0.014 + 0.001 0.013 + 0.001 0.012 + 0.001 0.017 + 0.002 0.012 + 0.002 24 06/18/01 0.019 + 0.002 0.016 + 0.001 0.017 + 0.002 0.011 + 0.002 0.017 + 0.002 25 06/26/01 0.013 + 0.001 0.013 + 0.001 0.014 + 0.001 0.014 + 0.001 0.012 + 0.001 26 07/03/01 0.017 + 0.001 0.017 + 0.001 0.017 + 0.002 0.016 + 0.002 0.015 + 0.002

• Sample deviation.

• • Control location.

B-1 2

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2001 (pCi/m 3 +/- 1 sigma)

STATION #

WEEK # End0Date 4

5 0

27

+0

+

27 07/10/01 0.012 + 0.001 0.011 + 0.001 0.012 + 0.001 0.013 + 0.001 0.012 + 0.001 28 07/17/01 0.011 + 0.001 0.010 + 0.001 0.009 + 0.001 0.010 + 0.001 0.009 + 0.001 29 07/24/01 0.017 + 0.001 0.014 + 0.001 0.016 + 0.002 0.015 + 0.002 0.013 + 0.002 30 07/31/01 0.013 + 0.001 020.014

+ 0.001 0.016 + 0.002 0.016 + 0.002 31 08/08/01 0.026 + 0.002 0.027 + 0.002 0.024 + 0.002 0.029 + 0.002 0.025 + 0.002 32 08/14/01 0.021 + 0.002 0.021 + 0.002 0.024 + 0.002 0.022 + 0.002 0.022 + 0.002 33 08/21/01 0.023 + 0.002 020.019

+ 0.002 0.025 + 0.002 0.022 + 0.002 34 08/28/01 0.017 + 0.001 0.016 + 0.002 0.017 + 0.002 0.017 + 0.002 0.018 + 0.002 35 09/04/01 0.015 + 0.001 0.013 + 0.001 0.014 + 0.001 0.016 + 0.002 0.016 + 0.002 36 09/11/01 0.017 + 0.001 0.016 + 0.002 0.016 + 0.002 0.016 + 0.002 0.016 + 0.002 37 09/17/01 0.016 + 0.002 0.013 + 0.002 0.016 + 0.002 0.012 + 0.002 0.017 + 0.002 38 09/25/01 0.019 + 0.001 0.022 + 0.002 0.020 + 0.002 0.024 + 0.002 0.020 + 0.002 39 10/02/01 0,012 + 0.001 0.011

+ 0.001 0.011 + 0.001 0.010 + 0.001 0.012 + 0.001 40 10/09/01 0.024 + 0.002 0.023 + 0.002 0.027 + 0.002 0.024 + 0.002 0.028 + 0.002 41 10/16/01 0.016 + 0.001 0.013 + 0.002 0.013 + 0.002 0.014 + 0.002 0.014 + 0.002 42 10/23/01 0.019 + 0.002 0.018 + 0.002 0.017 + 0.002 0.020 + 0.002 0.014 + 0.002 43 10/30/01 0.012 + 0.001 0.012 + 0.001 0.011 + 0.001 0.010 + 0.001 0.014 + 0.002 44 11/06/01 0.014 + 0.001 0.016 + 0.002 0.016 + 0.002 0.016 + 0.002 0.018 + 0.002 45 11/13/01 0.018 + 0.001 0.016 + 0.002 0.016 + 0.002 0.017 + 0.002 0.014 + 0.002 46 11/19/01 0.028 + 0.002 0.029 + 0.002 0.026 + 0.002 0.036 + 0.002 0.032 + 0.002 47 11/27/01 0.016 + 0.001 0.016 + 0.001 0.015 + 0.001 0.015 + 0.001 0.016 + 0.002 48 12/04/01 0.022 + 0.002 0.018 + 0.002 0.017 + 0.002 0.022 + 0.002 0.018 + 0.002 49 12/11/01 0.024 + 0.002 0.020 + 0.002 0.023 + 0.002 0.025 + 0.002 0.024 + 0.002 50 12/18/01 0.021 + 0.002 0.015 + 0.002 0.021 + 0.002 0.021 + 0.002 0.019 + 0.002 51 12/25/010 0,012 + 0.001 0.010 + 0.002 0.014 + 0.002 0.014 + 0.002 0.017 + 0.002 52 01/01/02 10.025 + 0.0021 0.017 + 0.0021 0.020 + 0.0021 0.021

+0.020.021

+ 0.00

• Sample deviation.

• • Control location.

B-13

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2001 (pCi/m 3 +/- 1 sigma)

STATION #

Week#

End Date 22 2329 1

01/08/01 0.016 + 0.001 0.022 + 0.002 0.016 + 0.001 0.016 + 0.002 2

01/15/01 0.017 + 0.001 0.017 + 0.002 0.017 + 0.001 0.020 + 0.002 3

01/22/01 0.014 + 0.001 0.017 + 0.001 0.015 + 0.001 0.019 + 0.002 4

01/29/01 0.020 + 0.001 0.019 + 0.002 0.018 + 0.001 0.021 + 0.002 5

02/05/01 0.014 + 0.001 0.015 + 0.002 0.016 + 0.001 0.015 + 0.002 6

02/12/01 0.017 + 0.001 0.015 + 0.001 0.018 + 0.001 0.016 + 0.002 7

02/19/01 0.016 + 0.001 0.016 + 0.001 0.016 + 0.001 0.019 + 0.002 8

02/26/01 0.020 + 0.001 0.015 + 0.001 0.018 + 0.001 0.018 + 0.002 9

03/05/01 0.020 + 0.001 0.018 + 0.002 0.016 + 0.001 0.020 + 0.002 10 03/12/01 0.013 + 0.001 0.008 + 0.001 0.010 + 0.001 0.011 + 0.001 11 03/19/01 0.012 + 0.001 0.013 + 0.001 0.011 + 0.001 0.014 + 0.001 12 03/26/01 0.010 + 0.001 0.010 + 0.001 0.009 + 0.001 0.009 + 0.001 13 04/02/01 0.006 + 0.001 0.008 + 0.001 0.007 + 0.001 0.009 + 0.001 14 04/09/01 0.014 + 0.001 0.013 + 0.001 0.014 + 0.001 0.017 + 0.002 15 04/16/01 0.011 + 0.001 0.012 + 0.001 0.009 + 0.001 0.012 + 0.001 16 04/23/01 0.020 + 0.001 0.018 + 0.002 0.022 + 0.001 0.022 + 0.002 17 05/01/01 0.018 + 0.001 0.019 + 0.002 0.015 + 0.001 0.021 + 0.002 18 05/07/01 0.019 + 0.001 0.026 + 0.002 0.021 + 0.001 0.023 + 0.002 19 05/14/01 0.012 + 0.001 0.015 + 0.001 0.022 + 0.002 0.017 + 0.002 20 05/21/01 0.012 + 0.001 0.009 + 0.001 0.009 + 0.001 0.011 + 0.001 21 05/28/01 0.005 + 0.001 0.007 + 0.001 0.006 + 0.001 0.004 + 0.001 22 06/04/01 0.009 + 0.001 0.009 + 0.001 0.007 + 0.001 0.006 + 0.001 23 06/11/01 0.012 + 0.001 0.009 + 0.001 0.010 + 0.001 0.009 + 0.001 24 06/18/01 0.017 + 0.001 0.018 + 0.002 0.017 + 0.001 0.018 + 0.002 25 06/25/01 0.016 + 0.001 0.013 + 0.001 0.011 + 0.001 0.011 + 0.001 26 07/02/01 0.017 + 0.001 0.016 + 0.002 0.014 + 0.001 0.016 + 0.002

• Sample deviation.

• • Control location.

B-1 4

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2001 (pCi/m 3 +/- 1 sigma)

STATION #

WEEK#

EndDate

-22" 23*

• 29' 4_*_-__

27 07/09/01 0.010 + 0.001 0.011 + 0.001 0.009 + 0.001 0.012 + 0.001 28 07/16/01 0.011 + 0.001 0.010 + 0.001 0.009 + 0.001 0.010 + 0.001 29 07/23/01 0.015 + 0.001 0.015 + 0.002 0.013 + 0.001 0.014 + 0.002 30 07/30/01 0.013 + 0.001 0.013 + 0.001 0.013 + 0.001 0.014 + 0.001 31 08/06/01 0.013 + 0.001 0.020 + 0.002 0.017 + 0.001 0.015 + 0.002 32 08/13/01 0.025 + 0.002 0.025 + 0.002 0.024 + 0.002 0.027 + 0.002 33 08/20/01 0.020 + 0.002 0.019 + 0.001 0.015 + 0.002 34 08/27/01 0.017 + 0.002 0.016 + 0.002 0.019 + 0.001 0.015 + 0.002 35 09/04/01 0.018 + 0.002 0.016 + 0.001 0.016 + 0.001 0.016 + 0.001 36 09/10/01 0.017 + 0.002 0.015 + 0.001 0.015 + 0.002 37 09/17/01 0.016 + 0.002 0.014 + 0.002 0.013 + 0.001 0.016 + 0.002 38 09/24/01 0.018 + 0.002 0.022 + 0.002 0.020 + 0.002 0.022 + 0.002 39 10/01/01 0.011 + 0.001 0.013 + 0.001 0.015 + 0.001 0.011 + 0.001 40 10/09/01 0.023 + 0.002 0.019 + 0.002 0.028 + 0.002 0.027 + 0.002 41 10/15/01 0.015 + 0.002 0.012 + 0.002 0.013 + 0.001 0.013 + 0.002 42 10/23/01 0.015 + 0.001 0.016 + 0.002 0.015 + 0.001 0.018 + 0.002 43 10/29/01 0.011 + 0.001 0.013 + 0.001 0.011 + 0.001 0.016 + 0.002 44 11/05/01 0.018 + 0.002 0.018 + 0.002 0.014 + 0.001 0.018 + 0.002 45 11/12/01 0.016 + 0.001 0.014 + 0.002 0.013 + 0.001 0.014 + 0.002 46 11/19/01 0.025 + 0.002 0.028 + 0.002 0.027 + 0.002 0.026 + 0.002 47 11/26/01 0.013 + 0.001 0.017 + 0.002 0.015 + 0.001 0.017 + 0.002 48 12/03/01 0.019 + 0.001 0.016 + 0.002 0.015 + 0.001 0.015 + 0.002 49 12/10/01 0.023 + 0.002 0.024 + 0.002 0.025 + 0.002 0.028 + 0.002 50 12/17/01 0.017 + 0.001 0.020 + 0.002 0.018 + 0.001 0.019 + 0.002 51 12/24/01 0.015 + 0.001 0.014 + 0.002 0.015 + 0.001 0.013 + 0.002 52 12/31/01 0.018 + 0.001 0.021

+ 0.002 0.020 + 0.001 0.022 + 0.002

• Sample deviation.

• • Control location.

B-15

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2001 (RESULTS IN UNITS OF 10-3 pCi/m 3 +/- 1 SIGMA)

1. 4 ALGONQUIN GAS LINE RADIONUCLIDES FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER.;

Be-7*

63.45+/-11.68 99.38+/-0.01 124.94+/-0.01 96.23+13.3 K-40*

<8.55

<2.76

<16.94

<6.87***

Mn-54

<0.85

<0.52

<10.67

<0.45 Co-58

<1.21

<0.46

<10.75

<1.11 Fe-59

<2.53***

<1.07

<11.86

<3.22***

Co-60

<0.83***

<0.39

<10.63

<0.89 Zn-65

<2.61

<0.79***

<11.1

<1.11 Zr-95

<3.25

<0.95

<11.05

<1.13 Nb-95

<2.7

<0.94

<10.66

<1.88 Ru-103

<0.75

<0.59

<10.95

<1.03 Ru-106

<7.13

<5.14

<14.02

<4.95 1-131

<6.77

<3.54

<16.54

<5.44 Cs-1 34

<1

<0.46

<10.65

<0.35 Cs-1 37

<0.66

<0.37

<10.46

<0.46 Ba/La-1 40

<8.19***

<4.36

<4.24***

<6.73***

Ce-141

<1.59

<1.21

<11.3

<1.21 Ce-144

<3.53

<1.54

<12.46

<2.45 Ra-226*

<9.91

<4.95

<14.96

<7.96 AcFrh-228*

<3.33

<2.07

<11.14

<1.40 OTHERS

<L0

<Lc

<Lo

<Lo

1. 5 NYU TOWER RADIONUCLIDES FIRST QUARTER SECOND QUARTER THIRDQUARTER.

FOURTHQUARTER*

Be-7*

68.95+/-8.63 105+/-0.01 104.94+/-0.01 82.77+11.3 K-40*

24.76+/-6.35

<5.15

<5.8**-

24.78+7.21 Mn-54

<0.36

<0.34

<10.7

<0.56 Co-58

<0.42

<0.58

<10.8

<0.70 Fe-59

<1.46

<1.1

<13.95

<3.13 Co-60

<0.38

<0.48

<10.6

<0.75 Zn-65

<0.52

<0.6

<11.86

<1.81 Zr-95

<1.3

<0.84

<10.91

<2.03 Nb-95

<1.25

<0.48

<11.27

<1.04 Ru-103

<0.83

<0.82

<10.6

<1.07 Ru-106

<7.17

<3.75

<15.67

<8.52 1-131

<4.9

<3.75

<16.54

<8.79 Cs-134

<0.5

<0.46

<10.88

<1.01 Cs-1 37

<0.44

<0.27

<10.4

<0.50 Ba/La-1 40

<3.94

<3.52***

<5.77***

<9.06 Ce-141

<1.12

<0.88

<11.28

<2.03 Ce-144

<1.87

<1.13

<12.2

<3.27 Ra-226*

<8.43

<4.79

<19.02

<10.12 Ac/Th-228*

<1.88

<1.52

<12.32

<1.54 OTHERS

<L0

<Lc

<L

< L

• Indicates naturally occurring.

Less than" values expressed as Critical Level (LU, unless otherwise noted.

Reported as sample LLD.

B-16

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2001 (RESULTS IN UNITS OF 10-3 pCi/m 3 +/- 1 SIGMA)

1. 27 CROTON POINT RADIONUCLIDES FIRST QUARTER SECOND QUARTER THIRD QUARTER; FOURTH QUARTER Be-7*

71+/-10.15 106.9+/-0.01 128.67+/-0.01 65.67+11.28 K-40*

<6.77

<5.26***

<19.62

<5.39***

Mn-54

<0.56

<0.57

<10.76

<0.32 Co-58

<0.79

<0.8

<10.76

<0.60 Fe-59

<1.54

<3.79

<12.2

<4,10 Co-60

<0.67

<0.68

<0.55***

<0.54...

Zn-65

<1.65

<1.19

<11.45

<1.74 Zr-95

<1.61

<1.67

<11.75

<1.06 Nb-95

<1.64

<1.81

<11.29

<0.89 Ru-103

<0.45

<0.61

<11.36

<0.66 Ru-106

<5.09

<4.03

<15.82

<5.89 1-131

<5.63

<4.75

<16.15

<10.18 Cs-134

<0.77

<0.56

<10.62

<0.65 Cs-137

<0.46

<0.38

<10.68

<0.39 Ba/La-1 40

<5.45***

<4.01

<5.46***

<8.32 Ce-141

<1.42

<1.22

<11.61

<1.07 Ce-144

<2.33

<2.34

< 12.42

<2.02 Ra-226*

<5.81

<6.54

< 17.24

<5.35 Ac/Th-228*

<2.67

<2.29

<12.8

<1.18 OTHERS

<L

<LG

<L;

<Lc

1. 94 IP TRAINING CENTER RADIONUCLIDES FIRST QUARTER SECONDQUARTER THIRD QUARTER FOURTHQUARTER; Be-7*

52.59+/-10.57 112.2+/-0.01 142.81+/-0.01 69.53+10.37 K-40*

<8

<8.48

<15.17 28.72+8.6 Mn-54

<0.7

<0.77

<10.46

<0.79 Co-58

<0.77

<0.69

<11.13

<0.54***

Fe-59

<2.47

<1.58***

<12.48

<2.37 Co-60

<0.57***

<0.528***

<10.6

<0.86 Zn-65

<0.92

<0.98

<1.02***

<0.87 Zr-95

<1.31

<1.92

<11.38

<0.90 Nb-95

<0.77

<0.7

<11.41

<1.07 Ru-103

<0.48

<1

<11.06

<0.67 Ru-106

<3.11

<3.82

<15.68

<5.50 1-131

<6.06

<3.55

<18.32

<11.38 Cs-134

<0.69

<0.54

<10.49

<0.47 Cs-137

<0.41

<0.36

<10.62

<0.51 Ba/La-1 40

<4.8

<4.32

<5.37***

<6.77 Ce-141

<0.73

<1.22

<11.14

<1.42 Ce-144

<1.87

<1.97

<11.94

<2.23 Ra-226"

<8.72

<5.74

<17.54

<7.97 Ac/Th-228*

<1.76

<1.08

<12.03

<1.10 OTHERS

<Lr

<L0

<Lo

<Lo

• Indicates naturally occurring.

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

Reported as sample LLD.

B-1 7

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2001 (RESULTS IN UNITS OF 10-3 pCi/m 3 +/- 1 SIGMA)

1. 95 METEOROLOGICAL TOWER RADIONUCLIDES FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER Be-7*

61.44+/-10.12 101.6+/-0.01 119.89+/-0.01 65.13+11.72 K-40*

<5.08***

36.47+/-0.01

<19.57 38.33+10.35 Mn-54

<0.75

<0.82

<10.72

<0.85 Co-58

<0.48

<0.92

<11.45 -_-_<0.58***

Fe-59

<1.89

<1.62

<3.25***

<5.35 Co-60

<5.07***

<0.38

<0.59"**

<0.58***

Zn-65

<1.64

<1.43

<11.91

<2.32 Zr-95

<1.45

<1.78

<11.65

<1.25 Nb-95

<0.99

<1.45

<11.77

<1.05 Ru-103

<0.99

<0.97

<11.72

<1.24 Ru-106

<5.81

<7.03

<19.95

<7.20 1-131

<7.48

<7.93

<18.93

<8.18 Cs-134

<0.57

<0.96

<10.83

<0.71 Cs-137

<0.34

<0.69

<10.36

<0.76 Ba/La-140

<6.46

<4.98

<18.23

<6.07"**

Ce-141

<1.26

<1.65

<11.67

<1.56 Ce-144

<2.08

<2.97

<13.26

<3.04 Ra-226*

<7.21

<9.18

<20.03

<9.37 Ac/Th-228*

<1.8

<2.14

<11.41

<3.38 OTHERS

<LQ

<Lc

<Lc

<LG

1. 22 LOVETT POWER PLANT RADIONUCLIDES FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER:

Be-7*

72.75+/-9.9 94.67+/-0.01 81.93+/-0.01 53.68+9.22 K-40*

33.17+/-8.55

<4.33***

42.99+/-0.02

<4.38***

Mn-54

<0.52

<0.33

<10.75

<0.26 Co-58

<0.91

<0.58

<10.81

<0.49 Fe-59

<1.76

<1.94

<14.21

<3.35 Co-60

<0.43

<0.46

<10.76

<0.44***

Zn-65

<1.39

<1.2

<11.8

<1.41 Zr-95

<1.47

<0.74***

<11.36

<0.86 Nb-95

<1,23

<0.57

<11.16

<0.73 Ru-103

<1.07

<0.72

<11.26

<0.54 Ru-106

<3,79

<2.35

<16.66

<4.79 1-131

<6.79

<5.05

<10.8

<8.37 Cs-134

<0.72

<0.47

<11.1

<0.53 Cs-1 37

<0,58

<0.38

<10,7

<0.31 Ba/La-140

<4.68

<3.49

<15.99

<6.83 Ce-141

<1.45

<1.06

<11.84

<0.87 Ce-144

<2.27

<1.58

<14.24

<1.64 Ra-226*

<7.43

<7.12

<18.97

<4.35 Ac/Th-228*

<2,89

<1.63

<12.46

<0.96 OTHERS

<Lo

<Lo

<Lo

<LC

• Indicates naturally occurring.

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

Reported as sample LLD.

B-1 8

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2001 (RESULTS IN UNITS OF 103 pCi/m 3 +/- 1 SIGMA)

1. 23 ROSETON RADIONUCLIDES FIRST-QUARTER

- SECONDQUARTER THIRD QUARTER FOURTH QUARTER:

Be-7*

63.67+/-10.1 99.59+/-0.01 86.69+/-0.01 64.97+9.69 K-40*

38.64+/-8.67

<4.63

<16.94 26.69+7.99 Mn-54

<0.84

<0.8

<10.87

<0.74 Co-58

<0.94

<0.81

-<0.53***

<0,51**

Fe-59

<2.65

<2.26

<2.51

<2.22 Co-60

<0.97

<0.61

<10.78

<0.80 Zn-65

<1.47

<1.62

<0.98***

<0.81 Zr-95

<1.52

<1.16

<11.87

<0.84 Nb-95

<1.27

<0.68

<10.85

<1.00 Ru-103

<1.25

<0.61

<11.05

<0.63 Ru-106

<6.42

<5.11

<14.74

<5.12 1-131

<9.2

<5.19

<19.32

<10.70 Cs-134

<0.9

<0.67

<10.56

<0.44 Cs-137

<0.69

<0.53

<10.53

<0.47 Ba/La-140

<4.07***

<4.67***

<5.68***

<6.36 Ce-141

<1.87

<1.18

<11.13

<1.33 Ce-144

<2.96

<1.77

<12.44

<2.07 Ra-226*

<8.97

<5.8

<17.53

<7.41 AcITh-228*

<2.17

<2.29

<12.49

<1.02 OTHERS

<Lc

<L0

<Lc

<Lc

1. 29 GRASSY POINT RADIONUCLIDES FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER Be-7*

53.91+/-8 91.76+/-0.01 112.31 +/-0.01 48.02+8.64 K-40*

<3.56

<4.29***

<15.82 28.11+7.59 Mn-54

<0.48

<0.43

<10.47

<0.63 Co-58

<0.69

<0.62

<10.76

<0.43***

Fe-59

<2.33

<2.03

<2.13**

<3.95 Co-60

<0.61

<0.71

<0.437***

<0.43***

Zn-65

<1.42

<1.54

<11.26

<1.70 Zr-95

<1.21

<1.53

<11.27

<0.92 Nb-95

<0.72

<1.26

<11.25

<0.77 Ru-103

<0.48

<1.13

<10.88

<0.92 Ru-1 06

<3.78

<3.64

<14.98

<5.29 1-131

<4.57

<5.6

<17.76

<6.07 Cs-134

<0.37

<0.51

<10.74

<0.52 Cs-137

<0.17

<0.48

<10.61

<0.56 Ba/La-140

<3.91

<4.03***

<4.82***

<4.5***

Ce-141

<0.72

<1.11

<11.31

<1.15 Ce-144

<2.15

<2.46

<11.95

<2.23 Ra-226*

<5.71

<7.36

<17.96

<6.87 Ac/Th-228*

<1.54

<2.2

<11.07

<2.48 OTHERS

<Lc

<Lc

<L0

<Lc

• Indicates naturally occurring.

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

Reported as sample LLD.

B-19

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2001 (RESULTS IN UNITS OF 10-3 pCVm 3 + 1 SIGMA)

1. 44 PEEKSKILL GAS HOLDER BUILDING RADIONUCLIDES FIRST QUARTER SECOND QUARTER THIRD QUARTER, FOURTH QUARTER*

Be-7*

68.68+/-10.99 124.8+/-0.01 115.14+/-0.01

<6.66 K-40*

<4.22

<5.21**

<5.37***

39.03+9.15 Mn-54

<0.359***

<0.76

<10.72

<0.58 Co-58

<0.58

<0.77

<11.14

<1.25 Fe-59

<1.39

<1.46

<13.55

<2.64 Co-60

<0.83

<0.63

<10.6

<0.55 Zn-65

<0.84

<1.37

<10.98

<1.41 Zr-95

<1.48

<1.36

<0.967***

<1.82 Nb-95

<0.763***

<1.83

<11.45

<1.87 Ru-103

<1.1

<0.69

<10.79

<1.32 Ru-106

<4.03

<4.26

<14.91

<6.63 1-131

<7.16

<5.37

<13.72

<9.79 Cs-134

<0.4

<0.64

<10.37

<0.84 Cs-137

<0.37

<0.55

<10.55

<0.52 Ba/La-140

<4.64

<4.46

<5.9***

<8.44 Ce-141

<1.28

<0.93

<11.47

<1.57 Ce-144

<1.82

<1.48

<12.44

<3.68 Ra-226*

<6.5

<6.26

<16.4

<10.14 Ac/Th-228*

<1.61

<2.57

<11.21

<2.42 OTHERS

<LC

<Lc

<L;

<Lc

• Indicates naturally occurring.

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

Reported as sample LLD.

B-20

TABLE B-8 1-131 ACTIVITY IN CHARCOAL CARTRIDGE SAMPLES - 2001**

(pCi/m 3 +/- 1 sigma)

Week#

End Date, -:

5 27-27 4

95 22-:

ý23,ý 29 44 1

01/09/01

<0.013

<0.010

<0-015

<0016

<0.011

<0,017

<0.010

<0.024 2

01/16/01

<0.009

<0.010

<0.013

<0.018

<0.015

<0.012

<0.015

<0.016

<0.014 3

01/23/01

<0.010

<0.010

<0.014

<0.013

<0.016

<0.011

<0.016

<0.013

<0.015 4

01/30/01

<0.010

<0.007

<0.013

<0.015

<0.015

<0.011

<0.017

<0.011

<0.016 5

02/06/01

<0.011

<0.008

<0.016

<0.017

<0.017

<0.015

<0.015

<0.011

<0.018 6

02/13/01

<0.010

<0.011

<0.010

<0.019

<0.015

<0.012

<0.020

<0.010

<0.018 7

02/20/01

<0.009

<0.010

<0.014

<0.016

<0.012

<0.011

<0.017

<0.011

<0.016 8

02/27/01

<0,009

<0.008

<0.015

<0.013

<0.013

<0.014

<0.015

<0.009

<0,015 9

01/00/00

<0.015

<0.015

<0.022

<0.019

<0.018

<0.018

<0.014

<0.015

<0.014 10 03/12/01

<0.014

<0.016

<0.017

<0.018

<0.017

<0.014

<0.012

<0.014

<0,023 11 03/20/01

<0.010

<0.009

<0.016

<0.013

<0.012

<0.015

<0.019

<0.014

<0.016 12 03/27/01

<0.012

<0.013

<0.013

<0.020

<0.019

<0.016

<0.021

<0.014

<0.019 13 04/03/01

<0.016

<0.015

<0.014

<0,016

<0.013

<0,017

<0.018

<0.009

<0.021 14 04/10/01

<0,013

<0.016

<0.018

<0,016

<0.021

<0,015

<0.016

<0.016

<0.024 15 04/16/01

<0.009

<0.013

<0.012

<0.022

<0.020

<0.014

<0.016

<0.013

<0.018 16 04/24/01

<0.017

<0.016

<0.014

<0.033

<0.026

<0.021

<0.025

<0.018

<0.025 17 04/30/01

<0,019

<0.015

<0.024

<0.021

<0.022

<0.014

<0.033

<0.014

<0.031 18 05/08/01

<0.012

<0.018

<0.033

<0.034

<0.041

<0.027

<0.043

<0.029

<0.034 19 05/15/01

<0.012

<0.019

<0.026

<0.024

<0.035

<0.013

<0,029

<0,029

<0.038 20 05/22/01

<0,012

<0.021

<0.029

<0.029

<0.030

<0.016

<0.026

<0.019

<0.025 21 05/29/01

<0.019

<0.019

<0.024

<0.027

<0.028

<0.021

<0.028

<0.019

<0.032 22 06/05/01

<0.021

<0.019

<0.030

<0.031

<0.023

<0.030

<0.032

<0.024

<0.035 23 06/12/01

<0.022

<0.023

<0.022

<0.026

<0.035

<0.037

<0.034

<0.018

<0.034 24 06/18/01

<0.033

<0.022

<0.028

<0.038

<0.021

<0.029

<0.047

<0.014

<0.046 25 06/26/01

<0.016

<0.019

<0.031

<0.015

<0.022

<0.015

<0.023

<0.027

<0.043 26 07/03/01

<0.031

<0.027

<0.017

<0.022

<0.037

<0.024

<0.030

<0.023

<0.029

• Sample deviation.

"Less than" values expressed as sample LLD.

Control location.

B-21

TABLE B-8 1-131 ACTIVITY IN CHARCOAL CARTRIDGE SAMPLES - 2001**

(pCi/m 3 +/- 1 sigma)

Week #

End Date 4-5 27.ý 54 -

95 22 23ý4 429 4

27 07/10/01

<0.021

<0.031

<0.017

<0.034

<0.034

<0.028

<0.040

<0.027

<0.039 28 07/17/01

<0.021

<0.023

<0.024

<0.024

<0.038

<0.022

<0.025

<0.016

<0.035 29 07/24/01

<0.021

<0.020

<0.025

<0.022

<0.022

<0.019

<0.025

<0.023

<0.022 30 07/31/01

<0.019

<0.020

<0.024

<0.028

<0.027

<0.037

<0.027

<0.022 31 08/08/01

<0.016

<0.027

<0.020

<0.017

<0.030

<0.018

<0.042

<0.034

<0.040 32 08/14/01

<0.014

<0.037

<0.031

<0.037

<0.023

<0.005

<0.028

<0.018

<0.029 33 08/21/01

<0.021

<0.015

<0.019

<0.022

<0.023

<0.016

<0.023 34 08/28/01

<0.027

<0.022

<0.019

<0.024

<0.031

<0.039

<0.025

<0.013

<0.028 35 09/04/01

<0.027

<0.041

<0.031

<0.026

<0.024

<0.040

<0.015

<0.019

<0.032 36 09/11/01

<0.030

<0.022

<0.025

<0.019

<0.034

<0.053

<0.040

<0.051 37 09/17/01

<0.023

<0.025

<0.036

<0.037

<0.029

<0.046

<0.023

<0.022

<0.035 38 09/25/01

<0.015

<0.022

<0.023

<0.031

<0.034

<0.014

<0.029

<0.029

<0.039 39 10/02/01

<0.013

<0.025

<0.017

<0.032

<0.021

<0.003

<0.033

<0.021

<0.031 40 10/09/01

<0.016

<0.023

<0.022

<0,019

<0.021

<0.014

<0.025

<0,020

<0.016 41 10/16/01

<0.005

<0.021

<0.022

<0.026

<0.040

<0.023

<0.033

<0.034

<0.038 42 10/23/01

<0.023

<0.031

<0.031

<0.037

<0.022

<0.020

<0.036

<0.022

<0.028 43 10/30/01

<0.022

<0.022

<0.027

<0.034

<0.018

<0.015

<0.032

<0.022

<0.045 44 11/06/01

<0.017

<0.029

<0.028

<0.032

<0.023

<0.015

<0.039

<0.024

<0.036 45 11/13/01

<0.016

<0.028

<0.026

<0.026

<0.023

<0.024

<0.030

<0.020

<0.027 46 11/19/01

<0.018

<0.024

<0.021

<0.029

<0.018

<0.019

<0.010

<0.013

<0.021 47 11/27/01

<0.014

<0.026

<0.022

<0.031

<0.019

<0.022

<0.033

<0.005

<0.028 48 12/04/01

<0.022

<0.006

<0.032

<0.029

<0.027

<0.018

<0.034

<0.025

<0.028 49 12/11/01

<0.016

<0.025

<0.027

<0.031

<0.024

<0.020

<0.021

<0.016

<0.018 50 12/18/01

<0,018

<0.024

<0.020

<0.017

<0.021

<0.026

<0.031

<0.013

<0.032 51 12/24/01

<0.019

<0.030

<0.030

<0.026

<0.032

<0.014

<0.024

<0.020

<0.018 52 12/31/01

<0.023

<0.036

<0.056

<0.042

<0.047

<0.043

<0.048

<0.031

<0.037

• Sample deviation.

"". Less than" values expressed as sample LLD.

Control location.

B-22

<8.26

<8.41 TABLE B-9 CONCENTRATIONS OF GAMMA EMMITERS IN HUDSON RIVER WATER SAMPLES** - 2001 (pCi/L +/- 1 SIGMA)

1. 9 PLANT INLET (HUDSON RIVER INTAKE)

January February

[

March IMapril_1_MayJun Be-7*

K-40*

162.6+/-10.01 185.9+/-5.15 153.1+/-9.49 100.5+/-14.83 366.3+/-14.88 113+/-13.76 Mn-54

<0.81

<0.84

<0.74

<1.32

<1.06

<1.19 Co-58

<0.98

<1.00

<0.97

<1.18

<1.18

<1.51 Fe-59

<2

<2.26

<2

<3.24

<2.7

<3.45 Co-60

<0.87

<0.95

<0.85

<1.05

<1.17

<1.22 Zn-65

<1.77

<1.83

<1.83

<1.64

<2.8

<3.00 Zr-95

<1.75

<1.71

<1.72

<2.62

<2.25

<2.69 Nb-95

<1.1

<1.22

<1.14

<2.06

<1.48

<1.96 Ru-103

<1.29

<1.25

<0.64

<2.07

<1.57

<1.75 Ru-106

<9.15

<9.08

<9.46

<13.54

<11.29

<12.60 1-131

<4.1

<5.95

<3.75

<4.65

<4.92

<6.00 Cs-134

<0.56

<0.70

<0.56

<1.31

<0.64

<1.18 Cs-137

<0.86

<0.84

<0.85

<1.25

<1.02

<1.15 BaILa-140

<2.88

<3.14

<2.64

<3.09

<3.33

<3.92 Ce-141

<2.16

<2.12

<1.89

<2.89

<2.57

<2.94 Ce-144

<6.13

<6.10

<5.9

<9.41

<8.34

<8.40 Ra-226*

68.59+/-15.05 82.3+/-7.8 67.93+/-13.67 68.34+/-20.86 121.5+/-19.32

<25.81 AcITh-228*

4.05+_2.3 10.1+1.46 4.39+/-2

<4.59 6.74+/-2.5

<4.39

1. 10 DISCHARGE CANAL (MIXING ZONE)

Radionuclide MJanuary Faarch AprIIF-:-

M M

..une Be-7*

<8.4

<7.84

<8.33

<14.18

<7.37

<13.18 K-40*

188.8+/-10.2 294.4+/-9.25 178.8+/-10.12 194.5+/-20.54 290.3+/-9.36 204.3+/-13.99 Mn-54

<0.76

<0.74

<0.76

<1.62

<0.72

<1.04 Co-58

<0.99

<0.85

<0.97

<1.78

<0.85

<1.27 Fe-59

<2.23

<1.08

<1.83

<4.02

<1.58

<3.01 Co-60

<0.77

<0.72

<0.83

<1.8

<0.73

<1.08 Zn-65

<1.65

<0.92

<1.65

<3.63

<0.87

<2.33 Zr-95

<1.64

<1,42

<1.72

<3.39

<1.48

<2.31 Nb-95

<1.15

<1.02

<1.1

<2,41

<0.65

<1.66 Ru-103

<1.19

<1.08

<1.1

<2.22

<0.62

<1.73 Ru-106

<8

<7.37

<8.05

<15.94

<7.77

<12.32 1-131

<3.72

<3.76

<3.47

<6.39

<3.52

<6.42 Cs-134

<0.8

<0.43

<0.86

<1.59

<0.43

<1.23 Cs-137

<0.74

<0.71

<0.72

<1.52

<0.71

<1.10 BaILa-140

<2.49

<1.97

<2.55

<5.49

<1.9

<3.77 Ce-141

<1.88

<1.94

<1.17

<3.51

<1.85

<2.71 Ce-144

<5.61

<5.94

<5.31

<11.33

<5.99

<7.94 Ra-226*

93.92+/-14.28 70.59+/-12.32 114.7+/-13.83

<32.61 104.8+/-13.43 43.54+/-20.01 AcJTh-228*

7.2+/-2.09 13.47+1.96 4.26+/-1.99

<5.32 16.75+/-2.12

<4.27

• Indicates naturally occurring.

. Less than" values expressed as Critical Level (LU.

B-23

< 13.55

<1 1.55

< 14.47

<8.41

TABLE B-9 CONCENTRATIONS OF GAMMA EMMITERS IN HUDSON RIVER WATER SAMPLES** - 2001 (pCi/L +/- 1 SIGMA)

1. 9 PLANT INLET (HUDSON RIVER INTAKE)

Radfonuclide July August:

Septemberr

" October, Novemberher,

,Decem r

Be-7*

<16.81

<9.06

<15.34

<7.87

<11.35

<8.01 K-40*

205.1+19.29 209.1+/-10.68 277.4+20.93 258+/-11.59 148.1+13.5 229+/-11.05 Mn-54

<1.36

<0.79

<1.57

<0.84

<1.13

<0.78 Co-58

<1.63

<0.95

<1.62

<0.97

<1.38

<0.98 Fe-59

<3.87

<2.79

<4.39

<2.79

<3.91

<2.94 Co-60

<1.54

<0.91

<1.77

<0.92

<1.3

<0.82 Zn-65

<3.26

<2.09

<3.62

<2.03

<2.93

<1.73 Zr-95

<2.99

<1.76

<2.61

<1.51

<2.1

<1.58 Nb-95

<2.35

<1.21

<1.71

<1.13

<1.63

<1.18 Ru-103

<1.7

<1.35

<2.07

<1.22

<1.74

<0.70 Ru-106

<13.42

<9.34

<15.78

<9.33

<11.82

<8.27 1-131

<5.95

<4.99

<7.2

<3.86

<5.58

<3.96 Cs-134

<1.53

<0.59

<1.46

<0.88

<0.73

<0.75 Cs-137

<1.53

<0.86

<1.38

<0.78

<1.05

<0.70 Ba/La-140

<4.77

<2.99

<5.54

<2.72

<4.3

<2.61 Ce-141

<3.44

<2.23

<3.58

<1.94

<2.76

<1.90 Ce-144

<10.38

<6.3

<10.32

<5.81

<7.49

<5.72 Ra-226*

137.9+28.02 100.3+/-16.73 64.9+31.15 58.7+/-15.11 65.38+18.37 107.3+12.76 Ac/Th-228*

<4.61 6.79+/-2.61

<4.62 3.79+/-2.05

<4.19 8.16+2.06

1. 10 DISCHARGE CANAL (MIXING ZONE)

Radionucllideo JuIy August Se.teb.*er

'October

'Nov mberk!

D6cmberA Be-7*

<10.13

<9.53

<15.45

<10.12

<14.25

<9.04 K-40*

112.4+10.56 208.5+/-10.83 228.7+20.21 247.4+/-11.26 188.4+16.62 431.2+/-14.94 Mn-54

<0.96

<0.84

<1.71

<0.9

<1.37

<0.93 Co-58

<1.12

<0.96

<1.6

<0.93

<1.64

<1.14 Fe-59

<2.45

<3.14

<5.13

<2.6

<4.17

<3.15 Co-60

<1.05

<0.93

<1.42

<0.85

<1.11

<0.97 Zn-65

<1.94

<1.91

<3.35

<1.89

<3.11

<2.23 Zr-95

<1.85

<1.86

<3.15

<1.83

<2.88

<2.06 Nb-95

<1.27

<1.44

<2.35

<1.29

<2.05

<1.32 Ru-103

<1.43

<1.37

<2.38

<0.86

<2.22

<1.36 Ru-106

<8.59

<9.34

<16.38

<8.87

<12.26

<10.37 1-131

<4.3

<6.46

<7.13

<4.08

<6.91

<4.62 Cs-134

<1.04

<0.89

<1.49

<0.9

<1.36

<0.62 Cs-137

<0.95

<0.88

<1.46

<0.84

<1.28

<0.87 Ba/La-140

<3.43

<4.16

<4.81

<3.13

<4.63

<3.07 Ce-1 41

<2.09

<2.29

<3.68

<2.08

<3.26

<2.53 Ce-144

<6.59

<6.16

<12.2

<6.89

<10.81

<6.79 Ra-226*

64.06+15.15 43.9+/-13.99 75.71+28.05 62.27+/-14.45 65.11+30.62 91.07+/-16.46 Ac/Th-228*

<3.95 4.29+/-2.4

<5.35 5.81:f_2.59

<4.36 7.96+2.6

• Indicates naturally occurring.

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

B-24

TABLE B-10 CONCENTRATIONS OF TRITIUM IN HUDSON RIVER WATER SAMPLES*- 2001 (QUARTERLY COMPOSITES)

(pCi/L +/- 1 sigma)

1. 9 PLANT INLET (HUDSON RIVER INTAKE)

(Control Location)

..Rad..

clide I ST Quarter

.2ND Qua.ter

.3R.

i i.

4TH Quart....

TRITIUM

<153

<240

<280

<260

1. 10 DISCHARGE CANAL (MIXING ZONE)

I Radionuclid.e I. 1STQua.er.,*..21NDQuarter1 3RD.Quarter-.....TH Quart Jr TRITIUM 1

323+/-94 1

<240 1

<280

<250

• "Less than" values expressed as sample LLD.

B-25

TABLE B-11 GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES** - 2001 (pCi/L +/- 1 sigma)

1. 7 CAMP FIELD RESERVOIR Raidtionuclide January February' M6 rch<

Aprili Mah y

'Jun~e' Gross Beta 2.66+/-0.48 1.71+/-0.5 2.04+/-0.48 1.52+/-0.44 3.1+/-0.42 1.44+/-0.44 Be-7*

<21.23

<12.59

<16.14

<28.7

<16.68

<20.05 K-40*

<29.76 80.41+/-19.59 256.5+/-22.42 322.6+/-46.16 161.1+/-26.94 166.7+/-38.71 Mn-54

<2.11

<1.12

<1.82

<2.29

<2.02

<3.23 Co-58

<2.1

<1.65

<1.74

<2.92

<1.93

<3.61 Fe-59

<5.64

<2.92

<3.42

<7.85

<4.11

<3.33 Co-60

<1.82

<1.67

<1.92

<5.09

<2.64

<2.6 Zn-65

<5.54

<3.52

<4.72

<7.03

<5.04

<7.74 Zr-95

<4.93

<3.28

<3.31

<6.3

<3.98

<3.9 Nb-95

<2.29

<1,47

<2.14

<2.9

<1.87

<1.92 Ru-103

<2.74

<2.09

<1.77

<3.86

<2.15

<3.02 Ru-106

<23.01

<17,77

<19.61

<36.92

<20.43

<34.58 1-131

<0.28

<0.35

<0.28

<0.204

<0.31

<0.28 Cs-1 34

<2.77

<2.02

<1.21

<2.43

<2.35

<3.31 Cs-137

<2.69

<1.97

<1.84

<3.15

<2.44

<3.21 Ba/La-140

<3.94

<2.12

<2.23

<2.35

<1.96

<4.33 Ce-141

<4.49

<2.4

<3.5

<5.91

<3.53

<5.54 Ce-144

<16.54

<11.11

<14.68

<24.56

<14.40

<21.39 Ra-226*

<48.25

<31.86 115.1+/-36.56 98.16+/-61.77

<52.35

<73.42 AcITh-228*

<8.14

<6.08 11.48+/-4.7

<12.5

<8.43

<10.53

1. 7 CAMP FIELD RESERVOIR Radinuclide**--July August

'September October NoVemberf December{j Gross Beta 2.08+0.47 2.21+/-0.42 2.20+/-0.49 1.80+/-0.43 0,708+/-0.48 3.19+/-0.58 Be-7*

<21.02

<17.94

<16.13

<19.73

<23.41

<24.04 K-40*

149.6+/-33.02

<21.31

<25.48 258.6+26.75 209.3+/-32.07 367.7+/-45.5 Mn-54

<2.74

<1.52

<2.17

<1.95

<2.48

<3.41 Co-58

<2.26

<1.7

<2.16

<2,24

<2.21

<3.20 Fe-59

<4.63

<6.36

<4.21

<4.77

<7.25

<5.95 Co-60

<3.25

<2.15

<2.84

<2.47

<2.76

<3.48 Zn-65

<5.13

<4.08

<4.82

<5.29

<5.11

<10.19 Zr-95

<4.78

<3.55

<3.18

<3.54

<4.16

<4.70 Nb-95

<2.86

<1.81

<2.47

<2.02

<2.69

<3.11 Ru-1 03

<2.57

<2.57

<2.72

<2.4

<2.75

<3.61 Ru-106

<25.73

<18.98

<20.22

<19.1

<33.29

<29.12 1-131

<0.29

<0.29

<0.45

<0.22

<0.28

<0.27 Cs-134

<2.91

<2.29

<1.81

<2.24

<2.90

<1.80 Cs-137

<2.25

<1.5

<2.35

<2.3

<2,58

<3,17 Ba/La-1 40

<2.48

<3.85

<3.77

<2.55

<3.22

<4.41 Ce-141

<4.23

<3.14

<3.38

<4.33

<4.17

<5.77 Ce-144

<16.38

<13.59

<13.94

<18.49

<16,75

<22,77 Ra-226*

104.1+/-44.92

<44.82 92.46+/-42.85

<60.18

<68.48 133.7+63.22 Ac/Th-228*

<8.95

<7.44

<6.22

<7.95

<9.56

<8.94

• Indicates naturally occurring.

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

B-26

TABLE B-12 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES*- 2001 (QUARTERLY COMPOSITES)

(pCi/L +/- 1 sigma)

1. 7 CAMP FIELD RESERVOIR Radionu.lide T

1ST Quarte1 jI 2ND QuarterI 3RD a00rtef j

4THI uarte I

TRITIUM

-<1 84

<240

<200

<250

• "Less than" values expressed as sample LLD.

B-27

TABLE B-13 CONCENTRATIONS OF GAMMA EMITTERS IN SHORELINE SOIL SAMPLES**-2001 (pCi/Kg,dry +/- 1 sigma)

1. 17 OFF VERPLANCK Collection Date 6/8/2001 ***

9/25/2001 ***t CO-60

<30.54

<32.68 1CS-134 I-Cs--137ý,',

Raý-226*ý,..-

ACtTh-228-UOtnerS.

44.86+26 P90.33+15.41 951.8+225.17 484.87+52.61

<L0

<33.53 1253.97+18.9 1156+385.9 436.3+55.79

<L;

1. 28 LENT'S COVE C611ection Date 6/19/2001 ***

9/24/2001 *** "1-Co-60

<34.4

<39.02 Cs-134 Cs-137<

Ra-226ý Ac/Th"228*

<32.5 P69.67+17.8 1884.33+261.08 610.77+59.4

<43.68 99.8+17.78 3788.33+426.58 340.67+94.54 Collection Date 5/10/2001 ***

9/24/2001 t Co-60

<51.57

<51.79 4

• Cs*

<4z

<44

1. 50 MANITOU INLET (control location) 134 Cs-137

] ý Ra.226*ý 9.65 427.2+/-51.44 2565+/-758.3 4.89

<60.03 1703+892.9 Ac/Th-28*ý -`ýOthdrs:Y,.

1001+/-+180

<Lc 1122+238.9

<Lo

1. 53 WHITE BEACH Collection Date Co-60 Cs-134 Cs-137

ý- Ra-226*

AcITh-228*

Others 6/8/2001

<17.68

<16.91

<18.71 810.1+338 213.4+60.34

<L0 9/24/2001

<23.55

<18.64

<18.45 728.3+320.4

<71.14

<L:

1. 84 COLD SPRING (control location)

Collection Date Co-60

Cs-134 Cs-137 Ra-226*1 AcITh-22..

Others3 5/10/2001

<24.72

<23.37

<19.8 784.3+/-325.5 538.7+/-74.89

<L0 9/24/2001

<34.43

<37.49

<33.12 1558+487.9 438.8+94.49

<Lo

• Indicates naturally occurring.

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

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

B-28 I

SOthers

<Lc:

I ----

I I

I

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2001 (pCi/Kg, wet +/- 1 sigma)

1. 23 Roseton**

Apr-01

-ýRadlonuclide

-:So-.

Sorr RagWee4:

Motherwort.

Be-7*

175+/-49.02 208+/-45.71

<34.49 K-40*

5450+/-1 83.9 13520+/-225.6 5206+/-1 36.8 Mn-54

<7.84

<7.34

<4.92 Co-58

<7.06

<7.73

<4.45 Fe-59

<17.78

<18.03

<10.31 Co-60

<8.85

<7.93

<4.79 Zn-65

<20.21

<10.98

<10.59 Zr-95

<11.71

<12.74

<7.86 Nb-95

<7.51

<7.64

<4.6 Ru-103

<7.39

<7.08

<4.07 Ru-106

<69.18

<74.76

<39.98 1-131

<6.87

<8.86

<4.83 Cs-134

<8.12

<5.02

<4.55 Cs-137

<6.95

<6.9

<4.26 Ba/La-140

<10.66

<7.79

<5.24 Ce-141

<7.82

<9.62

<5.12 Ce-144

<32.06

<42.17

<20.9 Ra-226*

276.1+/-88.71 552.8+/-112.1 304.8+/-62.03 Ac/rh-228*

38.36+/-19.88 72.99+/-18.71

<15.61 Jun-01 Radlonuclide CIover Motherort Soirrell Be-7*

123.8:.27.64 277.9+/-58.12 139.5+/-38.31 K-40*

5846+/-141 9543+/-226.4 4605+/-124.4 Mn-54

<4.78

<7.96

<6.66 Co-58

<4.92

<8.44

<6.27 Fe-59

<10.05

<20.75

<13.42 Co-60

<4.62

<9.93

<5.91 Zn-65

<11.35

<25.17

<8.03 Zr-95

<9.35

<14.28

<10.8 Nb-95

<5.42

<8.74

<6.53 Ru-103

<4.44

<8.4

<6.07 Ru-106

<45.61

<86.57

<67.74 1-131

<5.52

<9.95

<7.61 Cs-134

<4.93

<5.56

<4.43 Cs-137

<4.42

<8.15

<6 Ba/La-140

<5.6

<11.64

<7.68 Ce-141

<5.44

<14.26

<8.75 Ce-144

<22.61

<53.67

<37.43 Ra-226*

477.5+/-64.35

<243.5 677+/-95.92 Ac/'h-228*

25.78+/-13.06

<33.52 117+/-18.73 May-01 Rafdfornucllde'-

'Sorriil Clover3 Motherwort*ý Be-7*

97.97+/-48

<65.56 104.9+/-44.52 K-40*

6137+/-213.5 8059+/-209.4 10210+/-201.5 Mn-54

<9.06

<7.72

<7.88 Co-58

<8.4

<6.91

<8.04 Fe-59

<17.67

<17.41

<15.7 Co-60

<9.31

<9.47

<7.67 Zn-65

<22.15

<12.49

<19.77 Zr-95

<14.52

<13.47

<12.55 Nb-95

<7.97

<7.62

<7.85 Ru-103

<8.54

<7.35

<7.5 Ru-1 06

<87.44

<77.39

<79.03 1-131

<9.77

<8.59

<8.54 Cs-134

<9.09

<9.48

<7.9 Cs-137

<7.4

<7.62

<7.02 BaILa-140

<9.36

<8.05

<7.13 Ce-141

<10.12

<9.7

<10.53 Ce-144

<40.96

<39.49

<43.16 Ra-226" 812.3+/-120.6 544.5+/-112.6 515.7+/-97.47 Ac/'rh-228 78.68+/-24.9

<31 114.5+/-22.71 Jul-01 Radionuf~lbde Ciov'eirý Ragweed Grape Leaves/

Be-7*

405.8+/-53.96 770.1+/-62.9 534.2+/-95.92 K-40*

7443+/-209.6 10510+/-242.8 8885+/-292.4 Mn-54

<6.98

<7.8

<14.31 Co-58

<7.92

<8.73

<14.16 Fe-59

<18.57

<19.75

<31.66 Co-60

<9.17

<8.51

<16.3 Zn-65

<21.05

<20.45

<40.39 Zr-95

<14.7

<15.23

<25.74 Nb-95

<8.45

<7.9

<15.71 Ru-103

<7.49

<7.28

<13.37 Ru-106

<86.92

<78.28

<152 1-131

<10.43

<10.73

<17.71 Cs-134

<9.7

<8.66

<10.29 Cs-137

<8.67

<7.98

<13.94 Ba/La-1 40

<11.49

<10.6

<20.64 Ce-141

<8.46

<8.84

<18.41 Ce-144

<39.05

<37.89

<77.22 Ra-226" 494.3+/-101.6 837+/-109.2 921.1+/-191.9 AcIrh-228*

<30.16

<26.74 117.9+/-39.97

• Indicates naturally occurring.

• • Indicates control location.

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

B-29

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2001 (pCi/Kg, wet + 1 sigma)

1. 23 Roseton (continued)**

Sep-01 Radionuclide Grape Leaves '.

Ragweed Golden Rod*

Be-7*

770.3+60.62 816.2+64.64 630.6+57.96 K-40*

5150+181.3 9230+229.4 7178+204.7 Mn-54

<7.70

<8.25

<7.11 Co-58

<9.01

<8.34

<7.82 Fe-59

<25.80

<26.01

<23.17 Co-60

<9.16

<8.04

<9.40 Zn-65

<18.15

<21.86

<21.08 Zr-95

<14.95

<14.54

<14.14 Nb-95

<8.87

<8.13

<9.37 Ru-103

<7.45

<7.86

<8.06 Ru-106

<84.03

<77.79

<86.28 1-131

<12.44

<11.60

<13.30 Cs-134

<9.37

<9.30

<9.63 Cs-137

<7.57

<8.10

<7.63 Ba/La-140

<11.07

<14.14

<11.03 Ce-141

<10.00

<8.59

<9.94 Ce-144

<38.21

<34.33

<36.49 Ra-226*

780.3+103.3 348.4+101.3 433+134.8 AclTh-228*

70.63+22.09

<28.02 41.47+17.88 Oct-01 RadIcnuclide; Ragweed Go0denrod Sorrel Be-7*

1276+/-76.47 2204+/-117.2 433.6+/-71.36 K-40*

8806+/-248.3 8897+/-315.3 6105+/-241.8 Mn-54

<8.59

<11.01

<10.09 Co-58

<8.61

<12

<9.1 Fe-59

<24.85

<34.59

<27.47 Co-60

<8.9

<12.51

<9.98 Zn-65

<23.47

<36.5

<21.27 Zr-95

<13.54

<18.3

<16.97 Nb-95

<8.39

<11.02

<10.86 Ru-103

<7.39

<10.99

<9.22 Ru-106

<81.66

<126.4

<95.12 1-131

<8.33

<12.99

<11.53 Cs-134

<4.76

< 13.55

<10.04 Cs-137

<6.66

<11.55

<8.45 Ba/La-140

<8.94

<18.98

<10.97 Ce-141

<9.68

<12.67

<10.96 Ce-144

<38.19

<50.62

<41.59 Ra-226" 311.6+/-101 480+/-173.9 731+/-134.7 Ac/Th-228*

<28.46

<39.23

<35.07 Ralndle Ragweed Grp.

ae

. ~SWO r Be-7*

648.1+/-83.88 348.5+/-88.96 1125+/-110.9 K-40*

7492+/-336.3 5528+/-267.5 9045+/-295.8 Mn-54

<11.1

<12.36

<13.04 Co-58

<10.07

<14.16

<13.93 Fe-59

<28.58

<33.91

<30.71 Co-60

<12.13

<11

<13.01 Zn-65

<34.01

<40.38

<37.63 Zr-95

<20.53

<22.29

<23.58 Nb-95

<12.47

<13.54

<15.15 Ru-103

<10.26

<13.55

<14.36 Ru-106

<99.92

<136.2

<111.6 1-131

<12.74

<17.39

<17.34 Cs-134

<12.52

<15.62

<15.18 Cs-137

<12.92

<12.23

< 13.25 Ba/La-140

<10.53

<18.1

<20.12 Ce-141

<14.15

<10.58

< 16.37 Ce-144

<52.25

<67.46

<69.45 Ra-226" 499.9+/-142.3 414+/-178.8 877.2+/-191.6 Ac/Th-228*

<41.14

<48.44

<47.43 Nov-01 Radlonuclide.

Sorrekl Peppermint FalseVolet-I Be-7*

527.8+/-70.88 578.1+/-34.55 417.9+/-52.96 K-40*

9431+/-219.5 5691+/-106.4 8554+/-230.3 Mn-54

<8.57

<3.9

<8.85 Co-58

<10.86

<4.48

<8.77 Fe-59

<28.24

<12.81

<25.7 Co-60

<10.25

<4.35

<8.58 Zn-65

<14.95

<5.97

<25.55 Zr-95

<18.99

<7.66

<13.34 Nb-95

<10.8

<4.85

<8.28 Ru-103

<11.2

<4.46

<7.67 Ru-106

<114.4

<41.96

<81.07 1-131

<17.44

<7.38

<13.96 Cs-134

<7.11

<2.91

<5.99 Cs-1 37

<9.86

<4.42

<8.37 BaILa-140

<13.51

<6.92

<13.04 Ce-141

<15.99

<6.8

<9.75 Ce-144

<61.91

<26.1

<37.99 Ra-226" 635.5+/-156.5 441.7+/-67.18 244.8+/-100.8 Ac/Th-228 129.6+/-26.03 85.5+/-12.64 46.48+/-23.56

• Indicates naturally occurring.

• • Indicates control location.

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

Aug-01 B-30

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2001 (pCi/Kg, wet +/- 1 sigma)

1. 94 IP Training Center May-01

ýRadlonucllde sweet Cicely soie PokeWeed,.

Be-7*

460.3+/-64.22 1382+/-100.3 493.8+/-54.87 K-40*

8272+/-253.1 6624+/-277 7351+/-187.9 Mn-54

<8.42

<10

<7.57 Co-58

<9.35

<11.86

<7.32 Fe-59

<22.28

<23.28

<16.62 Co-60

<12.83

<11.94

<6.79 Zn-65

<24.71

<29.4

<10.39 Zr-95

<14.67

<19.95

<13.02 Nb-95

<8.7

<12.99

<7.53 Ru-1 03

<8.37

<10.07

<7.42 Ru-106

<91.01

<122.1

<70.59 1-131

<9.05

<11.2

<8.36 Cs-1 34

<6.57

<8.98

<5.11 Cs-1 37

<8.75

<12.06

<7.12 Ba/La-140

<9.86

<12.3

<7.88 Ce-141

<11.18

<12.92

<9.99 Ce-144

<46.79

<52.76

<44.61 Ra-226" 349.1+/-144.3 568+/-157.6 343.1+/-109.1 Ac[Th-228*

<35.4

<43.98 88.34+/-24.68 Jun-01 Radironuclide Motherwoirt

Clo r'

Bittersweet Be-7*

553.7+/-39.04 131.7+/-38.36 278.5+/-49.81 K-40*

6568+/-154.9 6537+/-160.1 6509+/-165.7 Mn-54

<5.68

<6.71

<8.56 Co-58

<4.99

<6.25

<7.88 Fe-59

<12.2

<14.99

<17.73 Co-60

<5.06

<7.53

<8.17 Zn-65

<13.04

<18.43

<12.02 Zr-95

<8.53

<11.1

<14.73 Nb-95

<5.87

<6.92

<8.9 Ru-1 03

<4.73

<6.58

<8.43 Ru-106

<49.79

<67.67

<86.13 1-131

<5.9

<7.07

<10.04 Cs-1 34

<5.28

<7.94

<6.08 Cs-1 37

<4.58

<5.97

<7.96 BaILa-140

<6.23

<8.17

<9.79 Ce-141

<6.02

<7.87

<11.57 Ce-144

<23.1

<33.38

<49.05 Ra-226" 525.1+/-69.29 463+/-93.5 791+/-123.6 AciTh-228*

<18.47 53.89+/-18.06 145.4+/-26.92 Radlonuclide iSoirnel

~Clover.~

Motherwort-(

Be-7*

379.9+/-59.29 184.8+/-39.28 289+/-54.88 K-40*

5156+/-201.6 7201+/-187.7 7336+/-228.1 Mn-54

<7.59

<6.47

<7.6 Co-58

<8.72

<6.38

<8.77 Fe-59

<16.77

<12.23

<17.2 Co-60

<9.8

<6.66

<9.69 Zn-65

<22.96

<15.03

<21.72 Zr-95

<14.35

<10.78

<13.27 Nb-95

<9.72

<6.21

<8.99 Ru-103

<7.59

<5.57

<8.5 Ru-106

<79.44

<59.3

<89.82 1-131

<7.63

<5.64

<9 Cs-134

<9.71

<6.86

<10.38 Cs-137

<9.19

<5.75

<9.44 Ba/La-140

<11.75

<6.35

<11.1 Ce-141

<9.16

<6.23

<9.5 Ce-144

<35.92

<26.7

<37.81 Ra-226*

354.7+/-108.5 221.3+/-77.72 590.2+/-125.3 Acflh-228"

<30.91

<21.39

<30.15 Jul-01 Radionuclide' Reed R

Grape I*avei RA-e Be-7*

278+/-94.59 355.4+/-92.53 945.4+36.1 K-40*

6731+/-329.7 6409+/-268.3 7819+131.4 Mn-54

<16.05

< 13.04

<8.19 Co-58

<15.81

<14.26

<7.2 Fe-59

<29.41

<29.7

<18.23 Co-60

<14.31

<15.8

<8.58 Zn-65

<36.67

<31.28

<21.1 Zr-95

<25.87

<23.12

<13.47 Nb-95

<17.45

<14.84

<7.4 Ru-103

<14.42

<13.72

<7.84 Ru-106

<125.5

<123.4

<66.69 1-131

<23.41

<23.19

<12.56 Cs-134

<16.31

<9.24

<7.18 Cs-137

<14.66

<12.31 6.95+4.38 Ba/La-140

<22.86

<25.31

<11.5 Ce-141

<18.66

<17.88

<8.23 Ce-144

<64.91

<68.52

<29.2 Ra-226*

814.3+/-177.6 582.9+/-170.1

<122.5 AcJTh-228*

66.87+/-37.49

<52.83

<24.03

• Indicates naturally occurring.

• • Indicates control location.

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

Apr-01 B-31

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2001 (pCi/Kg, wet +/- 1 sigma)

1. 94 IP Training Center (continued)

Sep-01 Radionucilde Ragweedi Grape Leaves Reeds 'ý Be-7*

444.2+46.42 415.8+62.39 236.3+46.28 K-40*

9310+195.6 5886+204 6004+180.7 Mn-54

<6.34

<8.53

<7.46 Co-58

<6.04

<9.42

<6.81 Fe-59

<20.48

<28.43

<19.87 Co-60

<8.16

<11.25

<8.44 Zn-65

<16.77

<21.53

<15.86 Zr-95

<10.85

<16.47

<12.16 Nb-95

<6.74

<9.82

<8.08 Ru-103

<5.77

<9.15

<7.80 Ru-106

<58.12

<96.62

<74.48 1-131

<7.71

<14.44

<10.25 Cs-134

<6.11

<10.75

<7.72 Cs-1 37

<5.62

<10.21

<6.96 Ba/La-140

<8.42

<12.88

<11.26 Ce-141

<6.49

<10.93

<8.52 Ce-144

<26.15

<42.98

<33.56 Ra-226" 446.8+79.5 388.9+121.6 659.8+97.65 Ac/'h-228*

<24.91

<35.91

<22.22 Oct-01 Radionuclide.,Goldenf Rod.. Grape Leaves ThJsjIl>

Be-7*

3202+/-128.1 1734+/-93.99 407.9+/-61.76 K-40*

8271+/-291.6 4465+/-194.7 7153+/-246.5 Mn-54

<11.9

<8.16

<10.16 Co-58

<8.51

<9.02

<9.2 Fe-59

<33.11

<25.93

<29.84 Co-60

<12.63

<8.92

<9.97 Zn-65

<29.89

<20.51

<22.42 Zr-95

<16.52

<16.03

<16.16 Nb-95

<11.27

<8.22

<9.41 Ru-103

<9.05

<9.27

<8.57 Ru-106

<101.3

<90.53

<100.3 1-131

<15.47

<12.36

<12.45 Cs-134

<7.78

<9.01

<6.28 Cs-137

<10.81

<8.79

<7.92 BaILa-140

<15.89

<12.05

<18.04 Ce-141

<12.49

<10.58

<12.68 Ce-144

<51.01

<38.88

<46 Ra-226"

<192.7 504.2+/-118.6 281.4+/-140.2 AcfTh-228*

<40.64

<32.13 72.31+/-26.71

ýRadlonucllde

-~ Reeds Ra&,eed ~Gradpe LwWaWe Be-7*

466.1+/-81.03 1403+/-81.04 753.7+/-99.72 K-40*

5640+/-267.9 6669+/-227.4 5089+/-254.9 Mn-54

<12.09

<8.68

<1 1.27 Co-58

<12.07

<9.43

<12.86 Fe-59

<43.09

<26.78

<34.01 Co-60

<12.93

<8.83

<12.17 Zn-65

<29.52

<20.51

<31.69 Zr-95

<19.65

<15.47

<21.25 Nb-95

<11.87

<9.32

<13.33 Ru-103

<12.18

<8.08

<14.53 Ru-106

<137.2

<73.93

<131.6 1-131

<17.93

<12.27

<21.13 Cs-134

<16.53

<9.2

<14.83 Cs-1 37

<12.63

<8.38

<10.25 Ba/La-140

<19.73

<12.87

<19.33 Ce-141

<14.93

<10.16

<15.76 Ce-144

<58.23

<39.63

<63.42 Ra-226*

675.6+/-163.9 510+/-109.9 561.3+/-154.2 Ac/rh-228*

<44.89

<26.33

<42.54 Nov-01

'Radfonucilde Sorrel Rushes,%

Brti Be-7*

580.9+/-82.96 630.7+/-93.55 610.6+/-42.28 K-40*

9074+/-304 9239+/-303.2 7116+/-159.3 Mn-54

<10.73

<13.23

<5.9 Co-58

<13.53

<15.13

<5.88 Fe-59

<36.8

<37.65

<17.03 Co-60

<15.63

<15.34

<6.33 Zn-65

<36.13

<36.8

<16.24 Zr-95

<21.02

<23.98

<9.72 Nb-95

<11.98

<15.11

<5.64 Ru-103

<13.05

<14.04

<4.76 Ru-106

<132.2

<133.1

<54.73 1-131

<19.32

<22.21

<7.83 Cs-134

<9.49

<14.65

<3.68 Cs-137

<11.9

<12.21

<5.27 Ba/La-140

<19.25

<26.57

<8.87 Ce-141

<14.77

<19.54

<6.57 Ce-144

<60.02

<65.71

<23.82 Ra-226" 599.7+/-176.2 1025+/-F206.9 219.1:1-62.11 Ac/Th-228*

<47.17 102.2+/-39.08

<21.61

• Indicates naturally occurring.

• • Indicates control location.

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

Aug-01 B-32

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2001 (pC[/Kg, wet +/- 1 sigma)

1. 95 Meteorological Tower May-01 RadI0nullde S*Aelt.Clceyy Sorrel-..

Be-7*

356.4+/-53.46 856.1+/-80.24 K-40*

7544+/-236.6 5722+255.5 Mn-54

<8.4

<9.28 Co-58

<7.31

<12.26 Fe-59

<21.19

<19.36 Co-60

<7.9

<12.58 Zn-65

<21.57

<28.12 Zr-95

<14.34

<20.36 Nb-95

<8.43

<10.23 Ru-103

<6.93

<10.95 Ru-106

<74.83

<101.1 1-131

<8.13

<11.3 Cs-134

<5.84

<11.62 Cs-137

<7.42

<11.46 Ba/La-140

<11.12

<11.64 Ce-1 41

<8.25

<12.5 Ce-144

<35.39

<47 Ra-226"

<124 673+/-150.8 Ac/Th-228 48.47+/-25.15

<37.19 Jun-01 Radionuclide6 Motherwo* t Sorrel e Clover Be-7*

408.6+/-45.51 135.8+/-34.71 139.7+/-30.35 K-40*

8239+/-198.5 3461+/-127.5 5567+/-141.3 Mn-54

<6.6

<5.57

<5.08 Co-58

<7.06

<6.11

<5.03 Fe-59

<17.01

<14.47

<11.3 Co-60

<7.79

<6.47

<4.72 Zn-65

<15.7

<14.13

<12.76 Zr-95

<10.11

<9.47

<9.14 Nb-95

<6.28

<5.46

<5.24 Ru-103

<6.06

<5.63

<4.93 Ru-106

<66.61

<55.43

<52.14 1-131

<6.54

<5.99

<6.25 Cs-134

<6.96

<4.37

<5.73 Cs-1 37

<6.42

<5.28

<5.59 BaILa-140

<7.4

<6.93

<6.64 Ce-141

<7

<6.12

<5.78 Ce-144

<30.07

<26.52

<23.81 Ra-226" 215.2+/-85.91 346.5+/-78.98 154+/-69.8 AcITh-228*

<23.75

<22.7

<17.83 Rad1ionuclide~

Sorrel Clover.--.

Mothdjetýor_

Be-7*

97.97+/-46

<65.56 104.9+/-44.52 K-40*

6137+/-213.5 8059+/-209.4 10210+/-201.5 Mn-54

<9.06

<7.72

<7.88 Co-58

<8.4

<6.91

<8.04 Fe-59

<17.67

<17.41

<15.7 Co-60

<9.31

<9.47

<7.67 Zn-65

<22.15

<12.49

<19.77 Zr-95

<14.52

<13.47

<12.55 Nb-95

<7.97

<7.62

<7.85 Ru-103

<8.54

<7.35

<7.5 Ru-106

<87.44

<77.39

<79.03 1-131

<9.77

<8.59

<8.54 Cs-134

<9.09

<9.48

<7.9 Cs-137

<7.4

<7.62

<7.02 Ba/La-140

<9.36

<8.05

<7.13 Ce-141

<10.12

<9.7

<10.53 Ce-144

<40.96

<39.49

<43.16 Ra-226" 812.3+/-120.6 544.5+/-112.6 515.7+/-97.47 Ac/Th-228*

78.68+/-24.9

<31 114.5+/-22.71 Jul-01 Radionuclide Sorrel.

Ragweed Grape Leaves Be-7*

1572+/-63.08 837.6+/-66.17 178.2+/--h65.73 K-40*

6825+/-156.9 7987+/-239.3 4852+/-243.3 Mn-54

<7.38

<7.47

<9.09 Co-58

<7.04

<8.49

<8.48 Fe-59

<14.05

<19.15

<20.94 Co-60

<7.02

<9.04

<9.02 Zn-65

<19.26

<22.73

<24.46 Zr-95

<13.11

<12.22

<16.22 Nb-95

<8.1

<7.6

<11.55 Ru-103

<6.95

<7.35

<8.51 Ru-1 06

<73.72

<65.65

<94.11 1-131

<8.88

<11.38

<18.5 Cs-134

<5.21

<6.81

<10.61 Cs-137

<7.31

<6.5

<8.84 Ba/La-140

<8.09

<11.65

<22.62 Ce-141

<10.5

<7.72

<11.36 Ce-144

<41.63

<31.28

<42.84 Ra-226" 670.1+/-109.3 272.1+/-94.36 223.5+/-137.6 Acfrh-228*

137.4+/-22.07

<27.17

<31.57

• Indicates naturally occurring.

• • Indicates control location.

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

Apr-01 B-33

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2001 (pCi/Kg, wet +/- 1 sigma)

1. 95 Meteorological Tower (continued)

Sep-01 Radionuclide Ragweed Grape LeaVes Bitters.W...

Be-7*

555.5+66.26 172.8+68.01 675+85.41 K-40*

8541+278.4 4388+222.2 4736+242.6 Mn-54

<9.06

<9.96

<12.44 Co-58

<8.69

<10.74

<11.62 Fe-59

<31.18

<34.10

<32.77 Co-60

<10.68

<11.01

<1 1.59 Zn-65

<23.68

<26.00

<25.27 Zr-95

<17.16

<16.42

<19.77 Nb-95

<9.76

<11.20

<13.43 Ru-103

<9.23

<10.57

<11.96 Ru-106

<83.42

<114.10

<108.10 1-131

<11.83

<15.18

<13.67 Cs-134

<6.13

<12.32

<12.84 Cs-137

<9.46

<11.08

<11.79 Ba/La-140

<16.36

<11.25

<19.37 Ce-141

<10.67

<12.67

<13.63 Ce-144

<43.22

<47.06

<53.89 Ra-226" 312.9+116.1 487.1+143.7 900.8+153.8 Ac/Th-228*

<34.63

<42.15 55+33.65 Oct-01 Radionuclide Crown Vetchi Goldenrod Ragweed.

Be'7*

589+/-78.39 885.1+/-63.15 2510+/-91.53 K-40*

8658+/-296 7533+/-199.6 8623+/-218 Mn-54

<11.33

<7.75

<8.13 Co-58

<11.36

<8.38

<8.93 Fe-59

<27.3

<20.7

<27.73 Co-60

<13.25

<9.22

<9.42 Zn-65

<30.71

<11.78

<12.67 Zr-95

<20.24

<15.89

<15.67 Nb-95

<11.08

<8.26

<9.58 Ru-103

<10.33

<7.74

<8.79 Ru-106

<105.6

<96.67

<90.8 1-131

<11.9

<9.94

<13.7 Cs-134

<13.09

<5.73

<6.03 Cs-137

<10.89

<7.59

<9.07 Ba/La-140

<16.61

<10.4

<10.58 Ce-141

<14.81

<11.91

<13.82 Ce-144

<54.06

<49.21

<55.78 Ra-226*

654.5+/-174.3 476.2+/-115.2 624.6+/-132.6 Ac!Th-228*

<39.48 106.6+/-24.27 87.49+/-23.17 Racioneclde ReedsY Ragweed-1 Grape'Leaves~

Be-7*

584.4t62.79 1016+/-69.37 607+/-75.16 K-40*

6780+/-216.5 7930+/-227.4 6596+/--226.6 Mn-54

<8.92

<8.7

<10.82 Co-58

<8.56

<8.78

<10.11 Fe-59

<26.19

<23.51

<31.18 Co-60

<10.26

<9.74

<12.36 Zn-65

<22.72

<21.75

<14.56 Zr-95

<15.03

<12.52

<18.02 Nb-95

<10.38

<7.45

<11.12 Ru-103

<8.57

<7.57

<10.62 Ru-106

<88.98

<89.06

<110.1 1-131

<11.73

<10.83

<13.62 Cs-134

<10.05

<6.33

<6.8 Cs-1 37

<8.26

<8.54

<9.9 BalLa-140

<15.79

<13.49

<14.27 Ce-141

<10.56

<9.85

<12.78 Ce-144

<41.73

<37.59

<52 Ra-226" 839,2+/-117

<154.3 891.6+/-137.9 AcITh-228*

<29.67

<30.86

<38.74 Nov-01 R a d l o n u c li d e s o r re...

.R u se.

Be-7*

1209+/-85.15 1366+/-121.1 1580+/-91.51 K-40*

7888+/-243.2 10030A351 8653+/-257.7 Mn-54

<10.02

<15.39

<10.79 Co-58

<10.62

<15.58

<10.47 Fe-59

<32.8

<47.84

<32.23 Co-60

<12.02

<15.94

<11.68 Zn-65

<27.61

<40.01

<26.31 Zr-95

<18.06

<30.26

<20.31 Nb-95

<11.73

<16.88

<14.15 Ru-103

<9.89

<16.53

<10.07 Ru-106

<108.5

<158.1

<102.1 1-131

<16.29

<27.35

<17.35 Cs-134

<6.94

<17.78

<10.67 Cs-137

<10

<14.41

<9.23 BaILa-140

< 17.68

<21.83

<14.61 Ce-141

< 12.46

<19.8

<13.02 Ce-144

<46.35

<72.18

<50 Ra-226" 513.1+/-139.7 1496+/-204.8 720.9+/-133.3 Ac/Th-228 76.08+/-30.61 150.4+/-46.65 57.97+/-27.11

• Indicates naturally occurring.

• • Indicates control location.

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

Aug-01 B-34

TABLE B-15 CONCENTRATIONS OF GAMMA EMITTERS IN FISH AND INVERTEBRATE SAMPLES - 2001 (pCi/Kg, wet +/- 1 sigma)

1. 23 ROSETON (control)

Radionuclide White Catfish Strip~ed Bass W"1itrPe~rch American Eel WhileCatish lu Crab S

5122J01 I~

5/22V01 -

522(01 9/10101 Vi9O~i 9t10/01(

Be

<285.6

<378.3

<180.7

<133

<125.1

<175.6 K-40*

7346+/-534.4 8525+/-647.9 5858+/-377.6 4749+/-403.8 4509+/-372.2 6173+/-421.9 Mn-54

<29.39

<38.64

<18.87

<22.73

<20.88

<20.28 Co-58

<32.51

<50.96

<19.75

<24.99

<19.28

<18.47 Fe-59

<90.47

<93.53

<51.01

<65.47

<50.31

<52.96 Co-60

<28.13

<41.34

<18.02

<21.33

<22.88

<28.97 Zn-65

<63.45

<94.58

<55.96

<42.97

<44.15

<63.17 Zr-95

<55.03

<81.96

<38.29

<29.66

<32.15

<41.33 Nb-95

<43.01

<51.93

<25.72

<20.83

<19.34

<22.48 Ru-103

<43.33

<52.25

<25.96

<20.17

<21.61

<22.68 Ru-106

<352.5

<405.9

<189

<227.3

<176.5

<284.8 1-131

<181.2

<242.7

<100.5

<32.45

<32.95

<40.18 Cs-1 34

<25.85

<39.75

<11.4

<25.1

<20.85

<22.78 Cs-137

<28.37

<42.26

<15.72

<22.22

<13.55

<25.55 Ba/La-140

<104.3

<135.4

<51.77

<34.59

<31.14

<39.49 Ce-1 41

<50.94

<69.52

<23.96

<24.99

<24.5

<30.43 Ce-144

<146.6

<179.4

<102.9

<104.1

<90.2

<125.3 Ra-226" 2004+/-442.4 3168+/-622.9

<369.9

<315.9

<363 875.8+/-400 Ac/Th-228*

<89.56

<121.8

<62.27

<61.58

<69.02

<69.75

1. 25 DOWNSTREAM (HUDSON RIVER)

_________(indicator)

Radionucide.Striped Pass. White Perch White Catfish American Eel WhiteO Parchr Bliue Crab White Catfifsh America o

S5122J0l 5/22/01 5122/01-5/22oi0

-.9/10/o1>

qgiiojofý 69*/

.~9101ol 91o Be-7*

<118.2

<405.4

<456.3

<237.8

<149.1

<396.6

< 143.7

<135 K-40*

4205+/-270.6 9500+/-601 11640+/-688.5 4401+/-375.7 3566+/-332.4 9001+/-711.9 5087+/-320.9 3589+/-301.5 Mn-54

<11.76

<42.83

<41.15

<21.95

<14.09

<44.36

<18.7

<15.19 Co-58

<15.02

<48.35

<47.18

<25.45

<19.45

<37.56

<16.39

<18.66 Fe-59

<34.19

<92.74

<117.6

<56.82

<61.92

<101.6

<55.23

<49.5 Co-60

<15

<36.01

<46.39

<16.26

<14.74

<42.36

<18.25

<7.92 Zn-65

<34.17

<91.05

<115

<49.9

<42.76

<103.8

<39.65

<30.68 Zr-95

<25.58

<97.69

<98.98

<52.22

<32.46

<79.26

<32.49

<21.3 Nb-95

<16.19

<62.73

<73.18

<34.13

<21.84

<43.45

<17.22

<18.12 Ru-103

<22.07

<62.51

<63.46

<35.66

<18.5

<50.78

<18.13

<13.17 Ru-106

<139.6

<410.4

<511.3

<236.6

<159.7

<465.7

<189.9

<177.1 I-131

<65.39

<261.3

<302

<144.5

<29.87

<86.34

<29.7

<26.78 Cs-134

<11.07

<23.99

<47.49

<23.99

<15.37

<50.32

<16.68

<11.59 Cs-137

<13.89

<36.12

<45.14

<23.54

<16.9

<47.05

<16.87

<15.53 Ba/La-140

<41.6

<107.8

<141.5

<85.26

<33.66

<77.82

<21.56

<27.78 Ce-141

<19.31

<82.48

<78.16

<37.16

<27.05

<62.94

<21.95

<22.65 Ce-1 44

<55.73

<228.4

<240.3

<104.3

<107.2

<219.3

<84.47

<81.26 Ra-226"

<213.6 966.4+/-573.6 2631 +/-638.3

<448.7

<307.6 975.3+/-562 677.7+/-246 757.7.t232 Acl'rh-228*

<50.78 237+/-106.5

<151.1

<78.3

<73.39

<141.3

<47.1

<49.38

• Indicates naturally occurring.

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

B-35

TABLE B-16 ANNUAL

SUMMARY

, NON-RETS SAMPLE RESULTS 2001 NIE~J05J 9O.O TOTAL AVG F HIHS LWET N.F.

OA' AVG.

1`1-ýH GHEST LOWESTSI

,AMPLEQ MEI~

NUoLIEuv;`

POITV tLPST OST1TTI POSITIV NtQ.OF ~1 POSITVE POSITIVEPSITIVE, POSITIVE NO.,F

ýUI5 :ýiý%ETEQTED LLD (d)

SAMPLESsý4,SAM P

L

$ML SMI-1PSE&

AMP1LES I SAMPLES SAMPLE SAMPLE~ 5AMPLE$ SAMPL.ES tNPICATOR C0ONTRQLý AQUATIC VEGETATION (pCi/kg - WET)

Co-60 NONE

<K

<L,,

< L 0

2

<I..

<L,

<L0 0

4 19.8

<L.

1-131 100 44.5 44.5 44.5 1

2 50.6 52 49.2 2

4 148 15.5 Cs-134 100

<1L

<Lc

<L, 0

2

<1L,

<L,

<L, 0

4

<L0 Cs-137 100

< L0

< LK

< L, 0

2 15.9 31.8 9.3 4

4 29.2 76.4 BOTTOM SEDIMENT (pci/kg - DRY)

Co-60 NONE

< LK

< LK

< LK 0

6

< LK

< K

< LK 0

2 131.2

<L Cs-134 150 48.5 48.5 48.5 1

6 35.4 35.4 35.4 1

2 51.1 42 (b)

Cs-1 37 180 330 628 253 6

6 56.3 75.9 36.8 2

2 766 139 SOIL (pCi/kg - DRY)

Cs-137 180 109 109

< LK 1

2

< LK

< LK

< K 0

1 146 75.7 PRECIPITATION (pCi/._)

H-3 (c) 2000

<LLD

<LLD

< LLD 0

4

< LLD

< LLD

< LLD 0

4 254 341 ALGONQUIN OUTFALL (pCi/L)

H-3 (c) 2000

< LLD

<LLD

< LLD 0

5 NA NA NA NA NA 167 NA (a) - Average of positive values for 1991 - 2000 (b) - Detected at control location, 1992 AND 1999.

(c) - H-3 results reported by the laboratory as < sample LLD, which is less than the RETS required LLD.

(d) - RETS Required LLD.

NA - Data not available.

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

B-36

TABLE B-17 MILCH ANIMAL CENSUS 2001 THERE ARE NO ANIMALS PRODUCING MILK FOR HUMAN CONSUMPTION WITHIN FIVE MILES OF INDIAN POINT.

B-37

TABLE B-18 LAND USE CENSUS 2001 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 Bcaa Buchanan Westchester Avenue, 8 - SSE 0.73 Bcaa Buchanan 9 - S 0.71 Broadway, Verplanck St. Partricks Rectory, 10 - SSW 0.97 epnc Verplanck 11 - SW 1.8 Elm Avenue, Tomkins Cove West Shore Drive South, 12 - WSW 1.36TokisCv West Shore Drive North, 13 - W 1.21 TmisCv Tomkins Cove 14 - WNW 1.09 Route 9W, Tomkins Cove 15 - NW 1.04 Route 9W, Tomkins Cove 16 - NNW 0.98 Jones Point B-38

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 2001 data with historical values. Although other samples were taken and analyzed, values were only tabulated and plotted where positive indications were present. The RETS required LLD is posted at the bottom of the figures for comparison purposes.

C-1

TABLE C-1 DIRECT RADIATION ANNUAL

SUMMARY

1991 to 2001 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 12 13 14 14 15 14 15 14 15 14 13 13 14 14 15 14 15 15 15 15 14 13 15 16 17 16 18 16 16 16 2001 15 15 17 Hi

• toricaI Average 14 14 16 1991-2000 14141 C-2

FIGURE C-1 DIRECT RADIATION 40 1991 to 2001 El Inner Ring 35-i Outer Ring El Control Location 30 25 S20 E

15 10 5-N 015 N I'

~i::.

1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 C-3

TABLE C-2 RADIONUCLIDES IN AIR 1991 to 2001 (pCi/m 3) 0.02 0.02 0.02 0.02 0.01 0.01 0.01 0.02 0.02 0.01 0.02 0.02 0.02 0.02 0.01 0.01 0.01 0.01 0.01 0.01 0.01

< Lo

< LC

< L,

"< Le

"< Lc

< L

"< Lc

"< Lc

"< Lc

"< L

< L;

"< L0

"< Lc

"< Lc

"< Lc

"< L0

"< Lc

"< Lc 0.02 0.02 0.01

< Lc

< L0 Critical Level (L,) is less than the RETS required LLD.

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

C-4 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001

FIGURE C-2 RADIONUCLIDES IN AIR - GROSS BETA 1991 to 2001 N All RETS Indicator Locations El Control Location 1\\ŽLŽ:JINŽŽui1XNŽJ-,--1XN r1

..

i.i i'.--

1992 1993 1994 1995

• Includes RETS and non-RETS indicator locations.

Gross Beta RETS required LLD = 0.01 pCi/m 3 0.05 0.04 0.03 C) 0.02 0.01 0.00 1991 "7

1996 1997 1998 1999 C-5 2000 2001

TABLE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 1991 to 2001 (pCVL) 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 439 170 240 230 370

"< Lc

"< Lc

"< Lc 191 190 656 437 270 280 270 280 430 220 318 267

<L0

<Lc

< Lc

< L/

"< Lo

"< Lc

"< Lc

"< Lc

"< Lc

"< Lc 2001

< Lc 323

< Le

< L; Historical Average2634

~2 1991-2000 Critical Level (L,) is less than the RETS required LLD.

<Lo indicates no positive values above sample critical level.

C-6

<L0

<L0

< Lc

< LC

< L°ý

< Lý

< Lc

< L,:

"< LC

"< Lv

FIGURE C-3 HUDSON RIVER WATER - TRITIUM 1991 to 2001 1992 1993 1994 1995 1996 1997 1998 1999 2000 Tritium RETS required LLD = 3000 pCi/L C-7

-J C.,

2000 1800 1600 1400 1200 1000 800 600 400 200 0

1991 2001

TABLE C-4 RADIONUCLIDES IN DRINKING WATER 1991 to 2001 (pCVL) 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000

"< Lc

"< Lc

"< Lc

"< LC

"< Lc

"< Lo

< L

"< Lc

"< Lc

"< LC 2001

< LC

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

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

C-8

< Lý

"< Lo

"< Lc

"< LC

< Lc:

"< Lc

"< Lc

"< Lc

< Loý

< LC

FIGURE C-4 DRINKING WATER - TRITIUM 1991 to 2001 N Camp Field Reservior (H-3) 2000 1800 1600 1400 1200 1000 800 600 400 200 0-1991 1992 Tritium RETS required LLD = 2000 pCi/L 1993 1994 1995 1996 C-9 CJ (3

£0.

NO IDENTIFIED TRITIUM IN PREVIOUS TEN YEAR HISTORY 1997 1998 1999 2000 2001

TABLE C-5 RADIONUCLIDES IN SHORELINE SOIL 1991 -2001 (pCi/Kg, dry) 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 48 56 46

"< Lc

"< Lc

"< Lo

"< Lr

"< LC 46 58

"< L

"< Lc

"< Lc

"< L

"< Lc

"< Lc

"< Le

"< Le

"< Lc

"< Lv 202 207 137 485 176 173 203 143 200 179 313 433 135 516 335 453 340

< Lcý 238 231 2001 45

< LC 230 427 Hi,storical Average 51

<L,211 345 1991-2000~§ Critical Level (L,) is less than the RETS required LLD.

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

C-10

FIGURE C-5 RADIONUCLIDES IN SHORELINE SOIL 1991 to 2001 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0

1991 1992 1993 1994 1995 Cs-1 34 RETS required LLD = 150 pCi/Kg, dry Cs-137 RETS required LLD = 175 pCi/Kg, dry 1996 1997 1998 1999 2000 2001 C-11

0)

C.,

(.

I 1994

TABLE C-6 RADIONUCLIDES IN BROAD LEAF VEGETATION 1991 to 2001 (pCi/Kg, wet) 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 26 28 44 22 28 17

<L0

<L0

<2 28 21

< Loý 18

< Lc

< L0

"< Lc "2 L

"< Lc 27

< Lc 2001 7

< Lc Historica 28 22

~1991 -2000 C-12 Critical Level (Lc) is less than the RETS required LLD.

<L0 indicates no positive values above sample critical level.

FIGURE C-6 BROAD LEAF VEGETATION - Cs-137 1991 to 2001 100 0 Indicator (Cs-1 37)

El Control (Cs-1 37) 80 60 CL 40 20 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 RETS required LLD = 80 pCi/Kg, wet C-13

TABLE C-7 RADIONUCLIDES IN FISH AND INVERTEBRATES 1991 to 2001 (pCi/Kg, wet) 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000

"< L

"< Lc 23

< Lc 16

< L

"< Lc

"< Lc

< L/:

2001

< Le

< Lr Histo, 06.6iAverage 2

C-14 Critical Level (Lj) is less than the RETS required LLD.

<LC indicates no positive values above sample critical level.

< L

< L

< L-c

< Lo;

"< Lc

"< L-c

"< LC

< L,ý

"< Lv

"< L-c

FIGURE C-7 FISH AND INVERTEBRATES - Cs-137 1991 to 2001 200 180 160 140 120 d100 C.)

a.

80 60 40 20 0

1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 Cs-1 37 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) requires that each licensee participate in an Interlaboratory Comparison Program. The I nterlaboratory Comparison Program shall include sample media for which samples are routinely collected and for which cross check 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 cross-check samples.

The two laboratories are Analytics, Incorporated in Atlanta, 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 2001, the tritium analysis for the JAF Environmental Laboratory was performed by Environmental Inc., Midwest Laboratory for samples collected during the first quarter of the year. Tritium analysis for samples collected during the second, third and fourth quarter of 2001 was performed by Duke Engineering and Services, Environmental Laboratory.

D-1

D.2 PROGRAM SCHEDULE Table D-1 Water Gross Beta 0

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

Veaetation Mixed Gamma 1

0 1

17 Ti 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 cross-check 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 ERROR RESOLUTION RATIO OF AGREEMEN 1

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

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

25% of the Known Value when applied to sample results from the Analytics 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 Warningq 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 Cross-Check 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' 2001 Interlaboratory Comparison Program. The following sample media were evaluated as part of the Cross-Check 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 Analytics Sample E-2677-05 Nonconformity No. 2001-08, Cr-51 in Soil Nonconformity No. 2001-09, Zn-65 in Soil A spiked mixed gamma in soil sample was received from Analytics, Inc. and 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. Seven of the nine radionuclides were quantified within the acceptable range. The results for Cr-51 and Zn-65 were determined to be outside the QA Acceptance Criteria.

The soil sample was analyzed on six different detectors with the following reported results for Cr-51 and Zn

65.

Mean Known Activity pCi/g Activity pCi/cl Ratio Cr-51 0.626_+0.012 0.455-+0.008 1.38 Zn-65 0.270_-0.032 0.368_+0.018 0.73 An evaluation of the Cr-51 result was performed.

The spectrum and peak search results were examined with no abnormalities identified. Cr-51 decays by electron capture with a 27.7 day half-life and a gamma ray energy of 320 KeV with a yield of 9.8%. No secondary gamma energies are produced in the Cr-51 decay scheme. This low gamma energy yield and short half-life will result in very low net counts for samples containing environmental levels of Cr-51.

The average net count rate of the six analyses was less than one count per minute. The counting error for the six analyses was high and ranged from 26% to 62%. The sample matrix of soil has a relatively high density, which would have a high self-absorption factor for the low energy gamma associated with Cr-51.

The combination of the following; low sample activity and resulting very small net count rate, short half-life, low gamma energy, small gamma yield and high sample density, resulted in an inaccurate sample result. The wide range of the associated counting errors demonstrates the low confidence level in the reported results. The poor analytical results for this sample is not routine and does not indicate a programmatic deficiency in the analysis of Cr-51 in soil samples or other environmental media. Confidence in the accurate analysis of Cr-51 can be D-5

easily demonstrated by other Cr-51 analytical results both in the aggregate sample results for the 2001 QA program and historical QA results. There was a second nonconformity associated with Cr-51 in soil for a sample submitted by a laboratory client in 2001. Physical parameters and conditions that affected this sample are the same that were identified in this nonconformity. The Cr-51 results for other Quality Assurance samples analyzed as part of the 2001 program were all acceptable, with the exception of E-2694-09, and are summarized below:

Table D-3 2001 Cr-51 Results SampleID,.*

Medjui.

4*F;

• --Lab--

Ratio E-2601-5 WATER pCi/liter 224+/-28 242+/-4 0.93 E-2812-05 WATER pCi/liter 261+/-23 265+/-4 0.98 E-2602-05 FILTER pCi/filter 190+/-17 201+/-3 0.95 E-2813-05 FILTER pCi/filter 214+/-31 266+/-4 0.8 E-2676-05 MILK pCi/liter 179+/-27 224+/-4 0.8 E-2814-05 MILK pCi/liter 348+/-25 366+/-6 0.95 E-2679-05 VEGETATION pCi/kg 318+/-73 373+/-6 0.85 E-2853-09*

SOIL* pCi/kg 469+/-130 404+/-20 1.16 E-2542-09*

SOIL* pCi/kg 530+/-102 479+/-8 1.11 E-2694-09*

SOIL* pCi/kg 585+/-79 455+/-8 1.29**

E-2951-09*

SOIL* pCi/kg 624+/-70 631+/-11 0.99 Mean Ratio 0.983

• Provided by lab client - NOT reported in Annual Report.

• • Nonconformity Result.

A review of historical QA data for 2000 was also performed to determine if this is a recurring systematic error or bias. In 2000, six QA samples were analyzed which contained Cr-51.

The mean ratio for these samples relative to the Known (reference)

Value is 0.95.

There were no Cr-51 nonconformities in the 2000 Crosscheck Program.

The current and historical data demonstrate that there is no systematic error or significant bias for the analysis of Cr-51 in environmental samples.

In summary, 2001 QA sample E-2677-05 had a very low net count rate, which resulted in a poorly defined spectrum peak.

The low Cr-51 activity in a high-density sample matrix resulted in an inaccuracy in the measured results. This nonconformity does not represent a systematic error or programmatic deficiency in the laboratory analysis program.

D-6

The Zn-65 results for sample E-2677-05 were also evaluated to be outside the Acceptance Criteria with a ratio of 0.73. The reported Zn-65 results were 0.363+/--0.068, 0.0285-+0.055 and 0.162+/-+0.066 pCi/kg. The individual results ratios relative to the known were 0.99, 0.77 and 0.44 respectively. The ratios for the 0.363 pCi/kg and 0.285 pCi/kg were within the Acceptance Criteria.

The ratio for the 0.162 pCi/kg result of 44 is significantly outside the acceptance range.

Based on the known results, the 0.162 pCi/kg result is considered an outlier.

A review of the peak search and raw spectrum shows that there was a possible interference peak with a centroid of 1120 KeV.

In soil samples, Ra-226 is a naturally occurring radionuclide, which produces a secondary peak at 1120 KeV. When the 1115 KeV (Zn-65) peak is manually defined and the interfering 1120 KeV was eliminated, the calculated result for Zn-65 is 0.358--0.078 pCi/kg, which has an acceptable reference ratio of 0.97. In most cases, the computer algorithm can differentiate the two adjacent peaks and correct for interferences from overlapping (doublet) peaks.

In this particular sample spectrum, there were a low number of total counts in the 1110 to 1130 KeV area of the spectrum. The computer did not identify the counts in the 1120 KeV area as a second peak due to the low activity and subsequent poor peak shape. By not identifying the peak at 1120 KeV the software did not resolve this section of the spectrum as a double peak.

To determine if this was a programmatic or systematic error inherent to the software/analysis system, an extent of condition was performed using another spiked sample result for any similar nonconformities. In 2001, eleven spiked samples were analyzed which contained certified concentrations of Zn-65 and other radionuclides. This sample set included four additional samples. The results are as follows:

D-7

Table D-4 2001 Zn-65 Results E-2601 -05 WATER DCi/liter 201 +/-9 186+/-9 1.08 E-2812-05 WATER pCi/liter 187+/-6 184+/-3 1.02 E-2602-05 FILTER pCi/filter 170+/-9 155+/-3 1.1 E-2813-05 FILTER pCi/filter 192+/-7 185+/-3 1.04 E-2676-05 MILK pCi/liter 182+/-9 182+/-3 1.01 E-2814-05 MILK pCi/liter 261+/-8 254+/-4 1.03 E-2679-05 VEGETATION pCi/kg 284+/-24 302+/-5 0.94 E-2853-09*

SOIL* pCi/kg 255+/-20 281+/-5 0.91 E-2542-09*

SOIL* pCi/kg 354+/-27 369+/-6 0.96 E-2694-09*

SOIL* pCi/kg 414+/-25 368+/-6 1.13 E-2951-09*

SOIL* pCi/kg 255+/-17 262+/-4 0.97

-- ~

1.02 Mean Ratio

• Provided by Lab client-NOT reported in Annual Report The mean ratio for all eleven Zn-65 results was 1.02 and the ratio for the four soil samples was 0.99. Both of these mean ratio values and the eleven individual ratio values for Zn-65 are excellent indicators that the routine measurement of Zn-65 in environmental media is very accurate.

These results demonstrate that there is no systematic error or bias for the analysis of Zn-65 in soil or other environmental sample media.

No corrective action was implemented as a result of this non conformity.

D.4.3 ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

In 2001, JAF Environmental Laboratory participated in both the EML Quality Assessment Programs, QAP-54 and QAP-55. Sample sets consisted of the following sample media:

"* Water - Gross Beta/Mixed Gamma Emitters

"* Water - Tritium

"* Air Particulate Filter - Mixed Gamma Emitters/Gross Beta D-8

A total of 18 radionuclides were evaluated for the samples included in QAP-54 and QAP-55. Using the EML acceptance criteria, 17 of 18 radionuclides analyses (94.4%) were evaluated to be acceptable.

Results for the EML cross Check Program can be viewed on-line at www.eml.doe.qov. A summary of the JAF Environmental Laboratory results is as follows:

Table D-5 JAF Environmental Laboratory Summary Matrix Analyses Total Acceptable' N't Acceptable Air 10 10 0

Water 8

7 1

Total Evaluation, 18 17 1

Percentage

-94.4%

5.6%

D.4.3.1 EML Sample QAP-54, Gross Beta in Water Nonconformity No. 2001-04 The JAF Environmental Laboratory reported results of 1.22

+/-0.02 Bq/ml. The EML activity was 1297 +/- 100 Bq/L. The cause of this error was technician error in reporting the data to the EML website. The JAF appropriate result was 1220 +/- 18.5Bq/L. The ratio of the JAF/EML results was 0.94. This ratio is consistent with other gross beta in water results.

D-9

TABLE D-6 INTERLABORATORY COMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filters (pCi/filter)

JAE NUMBER MEDIUM ANALYSIS JAF RESULTO()

LABORATORY*.

()

06/14/01 E-2675-05 AIR GROSS BETA 73.8+2.9 76+/-1.3 0.98, A pCi/filter 76.2+_2.9 74.2+2.9 Mean = 74.7+/-1.7 12/06/01 E-2907A-05 AIR GROSS BETA 75.0+2.3 67+/-3 1.12, A pCi/filter 76.7+/-+2.4 73.8+/-+2.3 Mean = 75.1+/-1.4 (1)

(2)

(*)

(A)

Results reported as activity +/- 1 sigma.

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

Sample provided by Analytics, Inc.

Evaluation Results, Acceptable.

D-10

TABLE D-6(Continued)

INTERLABORATORY COMPARISON PROGRAM Tritium Analysis of Water (pCi/liter)

(1)

Results reported as activity +/- 1 sigma. Sample Analyzed by Environmental Inc.,

Midwest Laboratory (2)

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

(*)

Samples provided by Analytics, Inc.

(A)

Evaluation Results, Acceptable.

D-11 IJAKý R-EFEREN4CE JAEN

~RESULT, L.ABORATORY*-~ RATIO.

DATE ID NUMBER MEDIUM ANALYSIS

()()

2 03/22/01 E-2600-05 WATER H-3 3108+/-173 3114+/-52 1.03, A pCi/liter 3382+/-179 3090+/-173 Mean = 3193+/-1 01

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Iodine Analysis of Water, Air and Milk

~~JAF

', 3/4 REFERENC JAFENV' t DATE:

I MEDIUM

'ANALYSIS

RESULT, LABORATORY*

\\RATIO.,

_____NUMBER 0_____

(1y 03/22/01 E-2601-05 WATER 1-131**

85.4+/-2.0 90+/-2 0.94, A pCi/liter 83.7+2.1 85.5+2.4 Mean = 84.9+/-1.3 06/14/01 E-2678A-AIR 1-131 70.9_+6.1 82+/-1 0.94, A 05 pci/cc 73.0+/-5.8 86.4+/--6.4 Mean = 76.8+/-3.5 06/14/01 E-2676-05 MILK 60.5+/-+2.7 69.0+/-1 0.93, A pCi/liter I-131**

67.7+2.9 65.0+/-3.9 Mean = 64.4+/-1.9 09/20/01 E-2814-05 MILK 1-131 85.4+/-5.1 91.0+/-2 0.91, A pCi/liter 83.2+/-+2.0 78.8+/-1.9 Mean = 82.5+/-1.9 09/20/01 E-2815-05 AIR 1-131 65.2_-6.9 68.0+/-1 0.99, A pci/cc 64.2+/-5.2 72.4+/-4.7 Mean = 67.3+/-3.3 09/20/01 E-2812-05 WATER 1-131*

60.3+/-1.1 60.0+/-1 0.93, A pCi/liter 49.3+/-1.4 57.2+/-1.3 Mean = 55.6+/-+0.7 (1)

(2)

(*)

(**)

(A)

Results reported as activity +/- 1 sigma.

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

Samples provided by Analytics, Inc.

Result determined by Resin Extraction/Gamma Spectral Analysis.

Evaluation Results, Acceptable.

D-12

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Water (pCi/liter)

JAF ENV ID R<:;

FEEC ATIO DATE NUMBER ANALYSIS JA EUT()

AOAOY NUM BER

<1......*.....

Ce-141 89.8+/-8.9 89.7+/-8.4 112.0+/-11.0 Mean = 97.2+/-5.5 94+/-2 1.03, A Cr-51 215.0+/-44.5 242+/-4 0.93, A 268.0+/-39.6 190.0+/-58.2 Mean = 224.3+/-+27.8 Cs-134 119.0+/-12.1 129+/-2 0.91, A 122.0+/--6.3 112.0+/-8.5 Mean = 11 7.7+/-5.4 Cs-1 37 91.9_-6.3 102+/-2 0.93, A 98.5+/-5.7 94.1+/-8.1 Mean = 94.8+/-3.9 Mn-54 108.0_+6.9 101+/-2 1.09, A 114.0+/--6.2 107.0+/-8.5 Mean = 109.7+/-4.2 Fe-59 85.2+/-11.2 84+/-1 1.07, A 106.0+/-9.4 77.8+/-14.4 Mean = 89.7-+6.8 Zn-65 195.0+/-14.7 186+/-9 1.08, A 201.0+/-12.7 208.0+/-17.6 Mean = 201.3+/-8.7 Co-60 149.0-+6.0 147+/-2 1.01, A 154.0+/-5.2 143.0+/-7.0 Mean = 148.7+/-3.5 Co-58 47.6+/-5.1 44.3+/-4.7 49.0+/--6.5 Mean = 47.0+/-3.2 J

a a

Results reported as activity + 1 sigma.

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

Sample provided by Analytics, Inc.

Evaluation Results, Acceptable.

48+/-1 0.98, A D-13 E-2601-05 WATER pCi/liter 03/22/01 (1)

(2)

(*)

(A)

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Water (pCi/liter)

I JA EN It)r fREFE1RENCE.

R.

DAEMEDIUM ANALYSIS JAF RESUL~T (1)-:

LABORATORY*.

AT9 DAE NUMBER (2)__Ib~L iK~

Ce-141 81.3+/-7.7 88.7+/-7.5 89.1 +/-6.8 Mean = 86.4+/-4.2 88+/-1 0.98, A Cr-51 232.0+/-42.3 265+/-4 0.98, A 240.0+/-36.6 312.0_-40.7 Mean = 261.3+23.1 Cs-134 116.0+/-5.7 116+/-2 0.97, A 109.0+/-5.2 110.0+/-5.3 Mean = 111.7+/-3.1 Cs-137 228.0+/-7.2 232+/-4 0.97, A 226.0_+6.5 220.0_+6.8 Mean = 224.7+/-3.9 Mn-54 142.0+-6.3 149+/-2 0.97, A 149.0+/-5.6 141.0-+6.1 Mean = 144.0+/-3.5 Fe-59 66.7+/--6.2 62+/-1 1.08, A 68.7+/-5.9 64.2-+6.2 Mean = 66.5+/-3.5 Zn-65 184.0+/-11.7 184+/-3 1.02, A 199.0+/-10.5 179.0+/-10.5 Mean = 187.3_+6.3 Co-60 204.0+/-5.5 193+/-3 1.03, A 197.0+/-4.9 194.0+/-5.2 Mean = 198.3+/-3.0 Co-58 132.0+/-+6.2 134.0+/-5.5 125.0+/-+6.1 Mean = 130.3+/-3.4 128+/-2 1.02, A Results reported as activity +/- 1 sigma.

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

Sample provided by Analytics, Inc.

Evaluation Results, Acceptable.

D-14 09/20/01 E-2812-05 WATER pCi/liter h

i (1)

(2)

(*)

(A)

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (pCi/filter)

JAF ENV 7

jREFERENCE-RAI DATE ID MEDIUM ALYS JAF RESULWT{

LABORATORYL L,_

____NUMBER A(LYI I)

~

Ce-141 74.8+/-5.3 69.5+/-4.8 67.2+/-5.1 Mean = 70.5+/-2.9 78+/-1 0.91, A Cr-51 184.0+/-29.4 201 t3 0.95, A 180.0+/-28.2 206.0+/-30.4 Mean = 190.0t16.9 Cs-1 34 95.8+/-7.7 107t2 0.91, A 93.9_+11.9 101.0+/-7.0 Mean = 96.9t5.3 Cs-1 37 69.0+/-6.0 84+/-1 0.87, A 79.7+/-5.9 71.0+/-5.8 Mean = 73.2+/-3.4 Mn-54 93.8+/-7.7 84+/-1 1.06, A 81.5+/-6.7 90.8+/-6.7 Mean = 88.7+/-4.1 Fe-59 70.8+/-12.0 70+/-1 1.00, A 65.1 +/-11.1 73.3+/-10.4 Mean = 69.7+/-6.5 Zn-65 176.0+/-16.1 155+/-3 1.10, A 177.0+/-14.6 158.0+/-14.3 Mean = 170.3+/-8.7 Co-60 103.0+/-+6.4 122+/-2 0.97, A 118.0_+6.3 133.0_+6.1 Mean = 118.0+/-3.6 Co-58 35.3+/-5.8 41.5+/-4.6 41.3+/-5.2 Mean = 39.4+/-3.0 40.-1 Results reported as activity +/- 1 sigma.

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

Sample provided by Analytics, Inc.

Evaluation Results, Acceptable.

D-15 E-2602-05 FILTER pCi/filter 03/22/01

______I (1)

(2)

(*)

(A) 0.98, A

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (pCi/filter)

Results reported as activity +/- 1 sigma.

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

Sample provided by Analytics, Inc.

Evaluation Results, Acceptable.

D-16

.~~>

R~EFERENCE

~

AI DATE EN MEDIUM AALYSIS JAF RESULT (11 L

ATORY NUMBER (2)____

09/20/01 E-2813-05 FILTER Ce-141 81.3+/-7.5 88+/-1 0.98, A pCi/filter 92.3+/-6.9 83.5+/-6.7 Mean = 85.7+/-4.1 Cr-51 213.0+/-55.5 266+/-4 0.80, A 214.0+/-52.8 215.0+/-52.1 Mean = 214.0+/-30.9 Cs-1 34 98.5+/-5.3 116+/-2 0.91, A 106.0+/-5.5 112.0+/-5.4 Mean = 105.5+/-3.1 Cs-1 37 218.0-+6.1 232+/-4 0.96, A 223.0+/-6.7 224.0_+6.7 Mean = 221.7+/-3.8 Mn-54 154.0+/-5.9 149+2 1.03, A 153.0+/-+6.5 153.0-+6.6 Mean = 153.3+/-3.7 Fe-59 58.9+/-8.6 62+/-1 1.00, A 57.3+/-8.6 70.0_+/-9.2 Mean = 62.1+/-5.1 Zn-65 180.0+/-11.3 185+/-3 1.04, A 208.0+/-12.1 188.0+/-12.9 Mean_= 192.0+/-7.0 (1)

(2)

(*)

(A)

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (pCi/filter)

Results reported as activity +/- 1 sigma.

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

Sample provided by Analytics, Inc.

Evaluation Results, Acceptable.

D-17 DAE JAF ENV ID REENE RATIO NUMBE MEDIUM ANALYSIS JiAF RESULT (1)

LAB'(2):;ý

NUMBER!

E 09/20/01 E-2813-05 FILTER Co-60 186.0+/-4.9 194+/-3 0.95, A (Cont) pCi/filter 186.0+/-5.5 182.0+/-5.5 Mean = 184.7+/-3.1 Co-58 117.0+/--6.8 129+2 0.96, A 133.0+/-7.1 123.0+/-7.2 Mean = 124.3+/-4.1 (1)

(2)

(*)

(A)

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Milk (pCi/liter)

S JAF ENVI D

RAEFR, DATE

MEDIUM, ANALYSIS JAF RESULT,(1).

i LABORATORY,

+,-'

1 NUMBER U(2)

Ce-141 166.0+/-10.9 152.0+/-13.1 172.0+/-11.1 Mean = 163.3_+6.4 163+/-3 1.00, A Cr-51 217.0+/-51.1 224+/-4 0.80, A 152.0+/-+62.1 168.0+/-42.8 Mean = 179.0+/-+27.3 Cs-1 34 122.0+/-7.7 134+/-2 0.92, A 123.0+/-8.1 124.0+/-7.2 Mean = 123.0+/-4.4 Cs-137 115.0+/-7.9 121+/-2 1.02, A 127.0+/-8.7 131.0+/-7.0 Mean = 124.3+/-4.3 Mn-54 164.0+/-9.7 150+/-3 1.03, A 151.0+/-9.9 151.0+/-8.1 Mean = 155.3+/-5.2 Fe-59 110.0+/-13.8 88+/-1 1.10, A 95.5+/-15.9 86.4+/-11.7 Mean = 97.3+/-7.4 Zn-65 187.0+/-17.5 182+/-3 1.01, A 168.0+/-18.9 193.0+/-14.9 Mean = 182.7+/-9.3 Co-60 148.0+/-7.0 135+/-2 1.04, A 132.0+/-7.1 144.0_+6.0 Mean = 141.3+/-3.8 Co-58 94.0+/-8.0 96.5+8.4 98.0-+6.6 Mean = 96.2+/-4.3 J

I I

I 96+/-2 1.00, A Results reported as activity +/- 1 sigma.

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

Sample provided by Analytics, Inc.

Evaluation Results, Acceptable.

D-18 06/14/01 E-2676-05 MILK pCi/liter (1)

(2)

(*)

(A)

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Milk (pCi/liter)

JAF ENV LREFERENCE, RATIO DATE ID IMEDIUM ANALYSIS JAF RESULT, (1)"

LABORATORY,;

__jNUMBER

_ ji~.

(2)

Ce-141 116.0+/-9.1 118.0+/-8.1 111.0+/-9.1 Mean = 115.0+/-5.1 121+/-2 0.95, A Cr-51 360.0+/-44.1 366+/-6 0.95, A 350.0+/-40.6 333.0+/-45.1 Mean = 347.7+/-+25.0 Cs-134 157.0_+6.7 160+/-3 0.95, A 152.0+/-5.4 147.0+/--6.2 Mean = 152.0+3.5 Cs-137 301.0+/-8.0 319+/-5 0.96, A 317.0+/-7.4 303.0+/-8.1 Mean = 307.0+4.5 Mn-54 209.0+/-7.2 205+/-3 1.03, A 208.0--6.5 217.0+/-7.4 Mean = 211.3+/-4.0 Fe-59 81.8+/-7.2 86+/-1 1.05, A 93.6_+6.8 94.6+/-7.4 Mean = 90.0+/-4.1 Zn-65 265.0+/-13.5 254+/-4 1.03, A 256.0+/-12.2 262.0+/-13.2 Mean = 261.0+7.5 Co-60 268.0+/-+6.3 266+/-4 0.99, A 263.0+/-5.6 261.0+/-+6.2 Mean = 264.0+3.5 Co-58 178.0+/-7.1 173.0+/-6.1 189.0+/-7.1 Mean = 180.0+3.9 177+/-3 1.02, A Results reported as activity +/- 1 sigma.

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

Sample provided by Analytics, Inc.

Evaluation Results, Acceptable.

D-19 E-2814-05 MILK pCi/liter 09/20/01 (1)

(2)

(*)

(A)

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Soil (pCi/liter)

DAE JAF ENV ID RFECEIRATIO,

.AEMEDIUM ANLSS JAF RESULT (1)

LABORATORY*,

(2 Ce-1 41 0.371_-0.037 0.340-_0.038 0.371_-0.041 Mean = 0.361-+0.021 0.330_+0.006 Cr-51 0.415_+0.178 0.455_+0.008 1.38, N 0.771+/-0.205 0.693_+0.220 Mean = 0.626+/-+0.116 Cs-1 34 0.276_+0.031 0.272+/-+0.005 0.96, A 0.254_+0.028 0.252+-0.034 Mean = 0.261_-0.017 Cs-1 37 0.330-+0.029 0.373_+0.006 0.94, A 0.338_+0.027 0.383_+0.033 Mean = 0.350+/-+0.016 Mn-54 0.366-+0.031 0.305_+0.005 1.19, A 0.347_+0.027 0.375_+0.032 Mean = 0.363--0.017 Fe-59 0.229_-0.047 0.178_+0.003 0.96, A 0.105_+0.041 0.178-+0.052 Mean = 0.171 ++/-0.026 Zn-65 0.363+/-+0.068 0.368--0.018 0.73, N 0.285--0.055 0.162-+0.066 Mean = 0.270_-0.032 Co-60 0.273-+0.022 0.274+/-+0.005 1.06, A 0.289+/--0.020 0.310+/-+0.023 Mean = 0.291+-0.012 Co-58 0.173+/--0.026 0.179--0.025 0.220+/-+0.029 Mean = 0.1 91_+/-0.015 0.196+/-+0.003 b

h Results reported as activity +/- 1 sigma.

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

Sample provided by Analytics, Inc.

Evaluation Results, Acceptable.

Evaluation Results, Not Acceptable.

D-20 06/14/01 E-2677-05 SOIL pCi/gram 1.09, A (1)

(2)

(*)

(A)

(N) 0.97, A

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Ve¢ etation (pCi/gram

• JAF ENV ID Bv-RT 0 EEEC DATE MEDIUM ANALYSIS JAF RESULT (1) jLA ORATORY*

AI NUMBER(2 VEGETATION pCi/gram Ce-141 0.274+/-0.022 0.304+/-0.023 0.288+/-0.022 Mean = 0.289+/-0.014 0.271+/-0.005 Cr-51 0.283+/-0.119 0.373+/-0.006 0.85, A 0.344+/-0.123 0.327+/-0.104 Mean = 0.3188+/-0.073 Cs-1 34 0.176+/-0.021 0.224+/-0.004 1.01, A 0.241+/-0.020 0.264+/-0.017 Mean = 0.227+/-0.012 Cs-137 0.202+/-0.020 0.202+/-0.003 1.03, A 0.197+/-0.019 0.225+/-0.017 Mean = 0.208+/-0.011 Mn-54 0.276+0.021 0.250+/-0.004 1.08, A 0.269+/-0.022 0.266+/-0.019 Mean = 0.270+/-0.013 Fe-59 0.174+/-0.037 0.146+/-0.003 1.16, A 0.153+/-0.038 0.180+/-0.030 Mean = 0.169+/-0.021 Zn-65 0.305+/-0.040 0.302+/-0.005 0.94, A 0.219+/-0.042 0.327+/-0.035 Mean = 0.284+/-0.024 Co-60 0.231+/-0.016 0.225+/-0.004 1.09, A 0.262+/-0.017 0.244+/-0.013 Mean = 0.246+/-0.009 Co-58 0.184+/-0.019 0.177+/-0.019 0.157+/-0.016 Mean = 0.173+/-0.011 0.160+/-0.003 J

d i

Results reported as activity +/- 1 sigma.

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

Sample provided by Analytics, Inc.

Evaluation Results, Acceptable.

D-21 06/14/01 E-2679-05 1.07, A (1)

(2)

(*)

(A) 1.08, A

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Water (Bq/liter)

Results reported as activity +/- 1 sigma.

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

Sample provided by EML.

Evaluation Results, Acceptable.

D-22 JAF ENV KA REFERENCE~.

DATE ID MEDIUM~ ANALYSIS JAF RESULT-1 LABORATORY*

TI

_____NUMBER LX A

03/01/01 QAP-54 WATER Cs-1 37 69.2+/-2.6 73+/-3.7 0.98, A Bq/Iiter 76.2+/-3.1 69.2+/-2.2 Mean = 71.5+/-1.5 Co-60 98.4+/-2.5 98.2+/-3.6 1.04, A 105.5+/-3.0 103.6+/-2.1 Mean = 102.5+/-1.5 09/01/01 QAP-55 WATER Cs-1 37 49.6+/-2.1 45.1+/-2.5 1.03, A Bq/liter 43.3+/-2.4 46.3+/-2.5 Mean = 46.4+/-1.3 Co-60 219.4+/-3.1 209.0+/-7.6 1.01, A 211.6+/-3.7 205.4+/-3.9 Mean = 212.1+/-2.1 (1)

(2)

(*)

(A)

TABLE D-6 (Continued)

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

Results reported as activity +/- 1 sigma.

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

Sample provided by EML, Inc.

Evaluation Results, Acceptable.

D-23 JAFENV REFERENCE RAO DATE

.ID MEDIUM

ANALYSIS, JAF RESULT (1)

LABORATORY-2

_NUMBER 03/01/01 QAP-54 FILTER Cs-1 34 2.2+/-0.3 2.83+/-0.16 0.85, A Bq/filter 2.3+/-0.4 2.6+/-0.2 Mean = 2.4+/-0.2 Co-60 17.9+/-0.3 19.44+/-0.5 0.94, A 18.1+/-0.3 18.8+/-0.3 Mean = 18.3+/-0.2 Mn-54 6.5+/-0.3 6.52+/-0.28 1.03, A 6.4+/-0.3 7.0+/-0.3 Mean = 6.7+/-0.2 Cs-137 8.8+/-0.3 8.76+/-0.34 0.96, A 8.0+/-0.3 8.5+/-0.3 Mean = 8.4+0.2 09/01/01 QAP-55 FILTER Mn-54 82.5+/-0.8 81.15+/-4.76 1.04, A Bq/filter 84.7+/-0.8 86.2+/-0.8 Mean = 84.5+/-0.5 Co-60 16.6+/-0.3 17.5+/-0.47 0.95, A 16.4+/-0.3 16.7+/-0.3 Mean = 16.6+/-0.2 Cs-134 13.2+/-0.4 12.95+/-0.36 1.03, A 13.2+/-0.4 13.3+/-0.4 Mean = 13.3+/-0.2 Cs-1 37 16.5+/-0.4 17.1+/-0.58 0.97, A 16.0+/-0.3 17.4+/-0.4 Mean = 16.6+/-0.2 (1)

(2)

(*)

(A)

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gross Beta Analysis of Water (Bq/liter)

Results reported as activity +/- 1 sigma.

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

Sample provided by EML.

Evaluation Results, Acceptable.

Evaluation Results, Not Acceptable.

D-24 JAFNVI A'REFERENCE RATIJO DATE NUMBEu MEDIUM ANALYSIS JAF RESULT (1)

LABORATORY*

03/01/01 QAP-54 WATER GROSS BETA 1.28+/-0.03 1297+/-100 0.00, N Bq/liter 1.14+/-0.03 1.24+/-0.03 Mean = 1.22+/-0.02 09/01/01 QAP-55 WATER GROSS BETA 7189+/-32.62 7970+/-800 0.90, A Bq/liter 7091+/-32.40 7327+/-32.92 Mean = 7202+/-18.85 (1)

(2)

(*)

(A)

(N)

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Tritium Analysis of Water (Bq/liter)

Results reported as activity +/- 1 sigma.

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

Sample provided by EML.

Evaluation Results, Acceptable.

Analysis performed by vendor laboratory: Environmental Inc. Midwest Laboratory Analysis performed by vendor laboratory: Duke Engineering and Services, Environmental Laboratory, Marlborough MA.

D-25

• ~

JAF ENV ID REUT()

REFERENCE RATIO.

DATE NUMBER MEDIUM ANALYSIS JAF RESI LABORATORY-(2)i*

03/01/01 QAP-54 WATER H-3 87.0+/-6.1 79.3+/-2.0 1.11, A Bq/liter 88.6+/-3.8(B) 88.9+/-6.1 Mean = 88.2+/-3.1 09/01/01 QAP-55 WATER H-3 231.3+/-3.6 207+/-2.69 1.13, A Bq/liter 237.3+/-3.6(C) 234.5+/-3.6 Mean = 234.4+/-2.1 (1)

(2)

(*)

(A)

(B)

(c)

TABLE D-6 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gross Beta Analysis of Air (Bqlfilter)

Results reported as activity +/- 1 sigma.

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

Sample provided by EML.

Evaluation Results, Acceptable.

D-26

.JAF ENV, -

REFERENCE DATE ID MEDIUM ANALYSIS JAF RESUL~TQ)

LABORATORY",

____NUMBER.

~

iA L111 03/01/01 QAP-54 AIR GROSS BETA 2.69+/-0.08 2.58+/-0.15 1.02, A Bq/filter 2.57+/-+0.08 2.67+/-0.08 Mean = 2.64+/-0.05 09/01/01 QAP-55 AIR GROSS BETA 11.52+/-0.10 12.77+/-1.28 0.90, A Bq/filter 11.48+/-0.10 11.48+/-0.10 Mean = 11.49+/-0.06 (1)

(2)

(*)

(A)