Text

Annual Radiological Environmental Operating Report
	ML051220210
Person / Time
Site:	Indian Point
Issue date:	04/28/2005
From:	Conroy P; Entergy Nuclear Northeast
To:	; Document Control Desk, NRC/FSME
References
	NL-05-0051
	Download: ML051220210 (134)
	v • d • e

Entegy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

Indian Point Energy Center 450 Broadway, Suite 1 R0. Box 249 Buchanan, NY 10511-0249 April 28, 2005 Re: Indian Point Units No 1, 2, 3 Docket Nos. 50-3, 50-247, 50-286 NL-05-051 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001

Subject:

2004 Annual Radiological Environmental Operating Report Dear Sir; Enclosed please find the 2004 Annual Radiological Environmental Operating Report for Indian Point Unit Nos. 1, 2, and 3 during the period of January 1, 2004 to December 31, 2004. Entergy Nuclear Operation, Inc. (Entergy) is submitting this report as required by Technical Specifications 5.6.2 in accordance with facility licenses DPR-5, DPR-26 and DPR-64 for Indian Point Unit Nos. 1, 2 and 3 respectively.

Entergy Nuclear Operations, Inc. is making no new commitments in this letter. Should you have any questions regarding this matter, please contact Mr. Patric W. Conroy, Licensing Manager at (914) 734-6668.

Very truly you Patric W. Conroy Manager Licensing Indian Point Energy Center

Enclosure:

2004 Annual Radiological Environmental Operating Report Cc: next page

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Docket Nos. 50-3, 50-247, 50-286 NL-05-050 Page 2 of 2 cc:

Mr. Samuel J. Collins Regional Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Patrick D. Milano, Senior Project Manager Division of Reactor Projects I/li U.S. Nuclear Regulatory Commission Mail Stop O-8-C2 Washington, D.C. 20555-0001 Resident Inspector's Office U.S. Nuclear Regulatory Commission Indian Point 2 P.O. Box 38 Buchanan, NY 10511-0038 Resident Inspector's Office U.S. Nuclear Regulatory Commission Indian Point 3 P.O. Box 337 Buchanan, NY 10511-0337 Attn. Chief, Compliance Section New York State DEC Division of Water 50 Wolf Road Albany, NY 12233 Attn. Regional Water Engineer New York State DEC 200 White Plains Road White Plains, NY 10601 Mr. Paul Eddy NYS Department of Public Service 3 Empire Plaza Albany, NY 12223 Mr. Robert Oliveira American Nuclear Insurers 95 Glastonbury Blvd Glastonbury, Conn 06033

ENCLOSURE TO NL-05-051 Indian Point Energy Center 2004 Annual Radiological Environmental Operating Report

( 131 Pages)

ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT UNIT 1, 2, and 3 NUCLEAR POWER PLANTS DOCKET Nos. 50-03, 50-247, and 50-286

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

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

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

January 1 - December 31, 2004

TABLE OF CONTENTS Paqe 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-ODCM)3-3 3.3.9 Hudson River Bottom Sediment (Non-ODCM) 3-3 3.3.10 Precipitation (Non-ODCM) 3-3 3.3.11 Soil (Non-ODCM) 3-3 3.3.12 Land Use Census 3-4 3.4 Statistical Methodology 3-4 3.4.1 Lower Limit of Detection and Critical Level 3-4 3.4.2 Determination of Mean and Propagated Error 3-5 3.4.3 Table Statistics 3-6 3.5 Program Units 3-7 i

TABLE OF CONTENTS (continued)

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

6.0 REFERENCES

6-1 APPENDICES:

A.

ENVIRONMENTAL SAMPLING AND ANALYSIS REQUIREMENTS A-1 B.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM B-1 RESULTS

SUMMARY

C.

HISTORICAL TRENDS C-1 D.

INTERLABORATORY COMPARISON PROGRAM D-1 ii

LIST OF FIGURES FIGURE TITLE Page A-1 Sampling Locations (Within Two Miles)

A-5 A-2 Sampling Locations (Greater Than Two Miles)

A-6 A-3 Non-ODCM Sampling Locations A-7 C-1 Direct Radiation, 1994 to 2004 C-3 C-2 Radionuclides in Air - Gross Beta, 1994 to 2004 C-5 C-3 Hudson River Water-Tritium, 1994 to 2004 C-7 C-4 Drinking Water - Tritium, 1994 to 2004 C-9 C-5 Radionuclides in Shoreline Soil, 1994 to 2004 C-11 C-6 Broad Leaf Vegetation - Cs-1 37, 1994 to 2004 C-13 C-7 Fish and Invertebrates - Cs-137, 1994 to 2004 C-15 iii

LIST OF TABLES TABLE TITLE Page A-1 Indian Point REMP Sampling Station Locations A-2 A-2 Lower Limit of Detection Requirements for Environmental Sample Analysis A-8 A-3 Reporting Levels for Radioactivity Concentrations in Environmental Samples A-9 B-1 Summary of Sampling Deviations, 2004 B-3 B-1 a 2004 Air Sampling Deviations B4 B-1b 2004 TLD Deviations B-4 B-1c 2004 Other Media Deviations B4 B-2 Annual Summary, 2004 B-5 B-3 2004 Direct Radiation, Quarterly Data B-9 B4 Direct Radiation, 1998 Through 2004 Data B-10 B-5 2004 Direct Radiation, Inner and Outer Rings B-1I1 B-6 Gross Beta Activity in Airborne Particulate Samples, 2004 B-12 B-7 Concentrations of Gamma Emitters in Quarterly Composites of Air Particulate Samples, 2004 B-16 B-8 1-131 Activity in Charcoal Cartridge Samples, 2004 B-21 B-9 Concentrations of Gamma Emitters in Hudson River Water Samples, 2004 B-23 B-10 Concentrations of Tritium in Hudson River Water Samples, 2004 B-25 B-11 Gross Beta Activity and Concentrations of Gamma Emitters in Drinking Water Samples, 2004 B-26 B-12 Concentrations of Tritium in Drinking Water Samples, 2004 B-28 B-13 Concentrations of Gamma Emitters in Shoreline Soil Samples, 2004 B-29 B-14 Concentrations of Gamma Emitters in Broad Leaf Vegetation, 2004 B-30 B-1 5 Concentrations of Gamma Emitters in Fish and Invertebrate Samples, 2004 B-37 B-16 Annual Summary, Non-ODCM Sample Results, 2004 B42 B-17 Milch Animal Census, 2004 B42 B-18 Land Use Census, 2004 B44 iv

LIST OF TABLES (Continued)

TABLE TITLE Page C-1 Direct Radiation Annual Summary, 1994 to 2004 C-2 C-2 Radionuclides in Air, 1994 to 2004 C-4 C-3 Radionuclides in Hudson River Water, 1994 to 2004 C-6 C-4 Radionuclides in Drinking Water, 1994 to 2004 C-8 C-5 Radionuclides in Shoreline Soil, 1994 to 2004 C-10 C-6 Radionuclides in Broad Leaf Vegetation, 1994 to 2004 C-12 C-7 Radionuclides in Fish and Invertebrates, 1994 to 2004 C-14 D-1 2004 QA Program Schedule D-2 D-2 Ratio of Agreement D-3 D-3 2004 Co-58 Results D-6 D-4 2004 Co-60 Results D-8 D-5 JAF (EML)Environmental Laboratory Summary D-9 D-6 Interlaboratory Comparison Program D-10 v

SECTION I EXECUTIVE

SUMMARY

1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report (AREOR) contains descriptions and results of the 2004 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 2004 Indian Point Station operation.

The waterborne pathway consists of Hudson River water, fish and invertebrates, aquatic vegetation, bottom sediment, and shoreline soil. Measurements of the media comprising the waterborne pathway indicated that there were no increased levels of radioactivity attributable to 2004 Indian Point Station operation.

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

This 2004 AREOR also contains summaries and discussions of the results of the 2004 program, trend analyses, potential impact on the environment, land use census, and interlaboratory comparisons.

During 2004, a total of 1338 analyses were performed. Table B-1 presents a summary of the collected sample results. The actual sampling frequency in 2004 was higher than required, due to the inclusion of additional (non-ODCM) sample locations and media.

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 2004. The levels present in 2004 were within the historical ranges, i.e., previous levels resulting from natural and anthropogenic sources for the detected radionuclides. Consequently, Indian Point operations in 2004 did not result in 1-1

approaching any environmental regulatory limits posed by the NRC, or result in any exposure to the public greater than environmental background levels.

1-2

SECTION 2 INTRODUCTION

2.0 INTRODUCTION

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

2.2 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 resulting from plant releases are consistently too small to be detected. Plant related radionuclides were detected in 2004, however, residual radioactivity from atmospheric bomb tests and naturally occurring radioactivity were the predominant sources of radioactivity in the samples collected.

Nonetheless, analysis of the data verified that plant effluents were far below regulatory limits at environmental levels.

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SECTION 3 PROGRAM DESCRIPTION

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

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

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

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

3.3 Sample Collection and Analysis Methodologv 3.3.1 Direct Radiation Direct gamma radiation is measured using integrating calcium sulfate thermoluminescent dosimeters (TLDs),

which provide cumulative measurements of radiation exposure (i.e., total integrated exposures in milliroentgen, mR) for a given period. The area surrounding the Indian Point site is divided into 16 compass sectors. Each sector has two TLD sample locations. The inner ring is located near the site boundary at approximately 1 mile (1.6 km). The outer ring is located at approximately 5 miles (8 km) from the site (6.7-8.0 km), see Figures A-1 and A-2.

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

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

3-1

3.3.2 Airborne Particulates and Radioiodine Air samples were taken at nine locations varying in distance from 0.28 to 20.7 miles (0.4 to 33 km) from the plant. These locations represent one control and eight indicator locations. The air samples are collected continuously by means of fixed air particulate filters followed by in-line charcoal cartridges.

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

The five required ODCM air sample locations are designated by the codes A-1 through A-5, see Figures A-1 and A-2.

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

3.3.4 Drinkinq Water Samples of drinking water are collected monthly from the Camp Field Reservoir (3.4 miles NE, Non-ODCM designation Wb1) and New Croton Reservoir (6.3 Mi SE, ODCM designation 8), see Figure A-3. Each monthly sample is approximately 4 liters and is analyzed for gamma-emitting radionuclides, gross beta, and 1-131. They are also composited quarterly and analyzed for tritium.

3.3.5 Hudson River Shoreline Soil Shoreline soil samples are collected at three indicator and two control locations along the Hudson River. The designation for the ODCM indicator location is Wc1 and the ODCM control location is designated Wc2, see Figures A-1 and A-2. The remaining two indicator and one control locations are non-ODCM. The samples are gathered at a level above low tide and below high tide and are approximately 2-kg grab samples. These samples are collected at greater than 90 days apart and are analyzed by gamma spectroscopy.

3-2

3.3.6 Broad Leaf Vegetation Broad leaf vegetation samples are collected from three locations during the growing season. The designation for the two ODCM indicator locations are Icl and Ic2, and the ODCM control location is designated 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 ODCM designation for the upstream sample point is lb2 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-ODCM)

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-ODCM)

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-ODCM)

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-ODCM)

Soil samples are collected from one control and two indicator locations, see Figure A-3. They are approximately 2 kg in size and consist of about twenty 2-inch deep cores. The soil samples are analyzed by gamma spectroscopy.

3-3

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

The milch animal census is used to identify animals producing milk for human consumption within 5 miles (8 km) of Indian Point. The census consists of visual field surveys of the areas where a high probability of milch animals exists and confirmation through personnel such as feed suppliers who deal with farm animals and dairy associations (See Table B-17). Although there are presently no animals producing milk for human consumption within 5 miles (8 km) of the site, the census is performed to determine if a milk-sampling program needs to be conducted.

A residence census is also performed to identify the nearest residence(s) to the site in each of the 16 sectors surrounding Indian Point. See Table B-18.

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

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

3.4.1 Lower Limit of Detection (LLD) and Critical Level (LA The LLD is a predetermined concentration or activity level used to establish a detection limit for the analytical procedures.

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

The equation used to calculate the LLD is:

LLD = 4.66 K Sb, where:

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

3-4

- Instrument characteristics (e.g., efficiency)

- Sample size

- Counting time

- Media density (self-absorption)

- Radioactive decay

- Chemical yield In the ODCM program, LLDs are used to ensure that minimum acceptable detection capabilities for the counting system are met with specified statistical confidence levels (95% detection probability with 5% probability of a false negative).

The LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement process and not as an "a posteriori' (after the fact) limit for a particular measurement. Table A-2 presents the RETS required LLDs for specific media and radionuclides as specified by the NRC. The LLDs actually achieved are usually much lower since the RETS required LLDs represent the maximum allowed.

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

Lc = k Sb (1 + TbI/TS) 0 5 in cpm where:

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

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

Tb = background count time (min)

T, = sample count time (min)

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

chance of false positive).

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

counts, the analytical result for the radionuclide is reported as the mean of the positive detections and the associated propagated error for that mean. In cases where more than one sample result is available, the mean of the sample results and the estimated error for the mean are reported in the Annual Report.

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

N EX, N

where:

X= value of each individual observation N = number of observations X (ERRid2 PE-N where:

ERR, = 1 sigma error of the individual analysis N = number of observations 3.4.3 Table Statistics The averages shown in the summary table (Table B-2) are the averages of the positive values in accordance with the NRC's Branch Technical Position (BTP) to Regulatory Guide 4.8 (Reference 14). Samples with "<"values are not included in the averages.

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

In the data tables B-6 through B-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 Lc values for that sample, unless otherwise noted. If multiple counts 3-6

were performed on a sample and a radionuclide's values are "< La " each time, the largest critical level is reported in the data table.

The historical data tables contain the annual averages of the positive values for each year. The historical averages are calculated using only the positive values presented for 1993 through 2002. The 2003 average values are included in these historic tables for purposes of comparison.

3.5 Program Units The Radiological Environmental Monitoring Program uses standard radiological units to express program results. The units and their description are as follows:

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

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

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

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

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

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

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

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

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

3-7

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 concentration for all air samples.

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

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

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

3-8

SECTION 4 RESULTS AND DISCUSSION

4.0 RESULTS AND DISCUSSION The 2004 Radiological Environmental Monitoring Program (REMP) was conducted in accordance with Indian Point's Offsite Dose Calculation Manuals ODCM. The ODCM contain requirements for the number and distribution of sampling locations, the types of samples to be collected, and the types of analyses to be performed for measurement of radioactivity. Additional sampling conducted for the REMP is designated "non-ODCM" because these samples are not required by the ODCM.

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

Hudson River-water Shoreline soil Fish and invertebrates Aquatic vegetation (non-ODCM)

Bottom sediment (non-ODCM)

Airborne Particulates and Radioiodine Precipitation (non-ODCM)

Drinking Water Terrestrial Broad Leaf Vegetation Direct Gamma Radiation Soil (non-ODCM)

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 2004 and assessed the significance of the findings.

A summary of the results of the 2004 REMP is presented in Table B-2. This table lists the mean and range of all positive results obtained for each of the media sampled at ODCM indicator and control locations. Discussions of these results and their evaluations are provided below.

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

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

The environment contains a broad inventory of naturally occurring radionuclides 4-1

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

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

The second group of radionuclides detected in 2004 consists of those resulting from past weapons testing in the earth's atmosphere. Such testing in the 1950's and 1960's resulted in a significant atmospheric radionuclide inventory, which, in turn, contributed to the concentrations in the lower atmosphere and ecological systems.

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

through radioactive decay), remains detectable.

In 2004, the detected radionuclide(s) attributable to past atmospheric weapons testing also consisted of Cs-1 37 in some media. The levels detected were consistent with the historical levels of radionuclides resulting from weapons tests as measured in previous years.

The final group of radionuclides detected through the 2004 REMP comprises those that may be attributable to current plant operations. During 2004, Cs-137 and H-3 were the only potentially plant-related radionuclide detected in some of the samples.

H-3 may be present in the local environment due to either natural occurrence, other man-made sources, or as a result of plant operations. Trace amounts of H-3 were detected in two of four quarterly composite samples from the discharge mixing zone (553pCi/l average, LLD 440 pCi/I "Less than" values for H-3 are reported from the laboratory as less than the sample LLD, which are less than the RETS required LLD.

Cs-137 and Cs-134 are both produced in and released from fission reactors and were introduced into the environment from the accident at Chernobyl in 1986.

Because Cs-134 has a short half-life relative to Cs-137, Cs-134 from Chernobyl is not likely to be present in 2004. Only Cs-1 37 is currently found from Cherynobyl and also found in weapons test debris.

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

4-2

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 2004 REMP, though they (Co-58 and Co-60) can be observed in historical tables.

In the following sections, a summary of the results of the 2004 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 2004, 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 quarterforthe years 1998 through 2003.

The 2004 means are also presented in Table B-4. Table B-5 presents the 2004 TLD data for the inner ring and outer ring of TLDs.

The 2004 mean value for the direct radiation sample points was 12.7 mR per standard quarter. In 2004, the mean value was 12.7 mR and the mean value for the period 1998 through 2004 was 14.2 mR per standard quarter. At those locations where the 2004 mean value was higher, they are within historical bounds for the respective locations.

The DR sample locations are arranged so that there are two concentric rings of TLDs around the Indian Point site. The inner ring (DR-1 to DR-16) is close to the site boundary. The outer ring (DR-17 to DR-32) has a radius of 4-3

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 12.9 mR per standard quarter while the average for the outer ring was 12.8 mR per standard quarter. The control location average for 2004 was 11.1 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 2004 averages are consistent with the historical data. The 2004 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 2004 air particulate filter and charcoal cartridge analyses is presented in Table B-2. As shown, there were no radionuclides detected in the air attributable to plant operations.

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

Gross beta activity was found in air particulate samples throughout the year at all indicator and control locations. The average gross beta activity for the eight indicator air sample locations was 0.015 pCi/M3 and the average for the control location was 0.014 pCi/M3. The activities detected were consistent for all locations, with no significant differences in gross beta activity in any sample due to location. Gamma spectroscopy analyses of the quarterly composite air samples showed that no reactor-related nuclides were detected and that only naturally-occurring radionuclides were present at detectable levels.

The mean annual gross beta concentrations and Cs-1 37 concentrations in air for the past 10 years are presented in Table C-2.

From this table and Figure C-2, it can be seen that the average 2004 gross beta concentration was consistent with historical levels. Cs-137 has not been detected since 1987. This is consistent with the trend of decreasing ambient Cs-137 concentrations in recent years.

The charcoal cartridge analytical results are presented in Table B-8. "Less than" values are presented as sample critical level (Lc). There was no 1-131 detected (LLD = 0.07 pCi/mr3) in the charcoal cartridge samples, which is consistent with historical trends.

From the data, it can be seen that no airborne radioactivity attributable to the operation of Indian Point was detected in 2004.

4-4

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

No radionuclides other than those that are naturally occurring and tritium were detected in the Hudson River Water samples. Tritium, whose presence may or may not be attributable to plant operations, has been detected in the past as depicted in Table C-3, and was detected in two of four samples from the discharge canal at levels slightly above LLD (553 pCi/I). These historical tritium levels are well below the required LLD of 3000 pCi/L. Additionally, table C-3 indicates the absence of Cs-1 37 which is consistent with historical data 4.4 Drinking Water The annual program summary table (Table B-2) contains a summary of the 2004 drinking water sample analysis results.

Results of the gamma spectroscopy analyses of the monthly drinking water samples are in Table B-11 and results of tritium analysis of quarterly composites are in Table B-1 2.

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

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

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

In addition to the naturally occurring nuclides, Cs-137 was identified in the Hudson River shoreline soil samples in 2004. Cs-137 was detected in five out of six samples from indicator locations. Cs-137 was detected at the control location in three out of four samples. The average concentration for the indicator locations was 104 pCi/kg-dry with a maximum concentration of 203 pCi/kg-dry. The control location had positive samples indicating an average of 138 pCi/kg-dry and a maximum of 172 pCi/kg-dry.

An historical look at Cs-1 37 detected in shoreline soil at indicator and control locations can be viewed in Table and Figure C-5. Cs-137 has been and 4-5

continues to be present in this media, both at indicator and control locations, at a consistent level over the past ten years.

4.6 Broad Leaf Vegetation Table B-2 contains a summary of the broad leaf vegetation sample analysis results. All the data from analysis of the 2004 samples are presented in Table B-14. Analyses of broad leaf vegetation samples revealed naturally occurring nuclides, and Cs-1 37. Cs-1 37 was detected in one of the thirty-six samples from indicator locations at a concentration of 10.0 pCikg-wet.

Historically, Cs-1 37 has been detected in both control and indicator broad leaf vegetation.

Table C-6 contains a summary and Figure C-6 an illustration, of the broad leaf vegetation analysis results for the past 10 years. The detection of low levels of Cs-1 37 is consistent with the sporadic detection at both indicator and control locations of relatively low concentrations for the past ten years.

4.7 Fish and Invertebrates A summary of the fish and invertebrate sample analysis results is presented in Table B-2. Table B-15 contains the results of the analysis of all fish and invertebrate samples for 2004. None of the indicator samples revealed radionuclide concentrations greater than Lc values. Only naturally occurring nuclides were detected. A summary of historical fish and invertebrate analytical data is presented in Table C-7 and illustrated in Figure C-7. Data are consistent with historical trends.

4.8 Additional Media Sampling Although not required by the ODCMS, analyses were performed on aquatic vegetation, Hudson River bottom sediment, soil, precipitation samples, and various other special water samples. A summary of the analytical results obtained is presented in Table B-16. As shown by these data, the radionuclides detected were consistent with their respective historical levels.

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

1-131 was not detected in indicator aquatic vegetation samples and was detected in one out of two control samples with an average concentration of 16.0 pCVkg-wet. 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 only detected in control locations. Cs-1 37 was detected in two of five indicator samples and one of two control samples.

4-6

nuclides at two locations. No tritium or other plant related nuclides were detected at either location.

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

The Algonquin Outfall, Gypsum Plant Stream, Verplanck-5th Street Well, and Trap Rock Quarry samples were analyzed for tritium and plant-related nuclides. The samples did not show any tritium or other plant-related nuclides.

The non-ODCM sample location of Algonquin Outfall was designated in 1996 and the other special water samples were designated late in 2003.

In addition, a comparison of gross beta analysis to radioactive liquid effluents for special water samples was done for 2005 to determine any potential environmental impact from low level Sr-90 releases during early 2004. There was no statistical variation in gross beta results and as such no measurable environmental impact from plant operations.

The results from the non-ODCM 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 control locations only for aquatic vegetation and was likely attributed to sources other than plant operations, such as medical administrations. The non-ODCM sample data corroborate the ODCM sample data in determining that the operation of the Indian Point station in 2004 had no detectable adverse radiological impact on the environment.

4.9 Land Use Census A census was performed in the vicinity of Indian Point in 2004. 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 2004 census were generally same as the 2003 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 0.44 miles (0.71 km) ESE and 0.73 miles (1.13 km) S of the plant.

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

4.10 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 2004 REMP reveal that operations at the station did not result in an adverse impact on the 4-7

I environment.

The results of the 2004 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 2004 REMP results demonstrate the relative contributions of different radionuclide sources, both natural and anthropogenic, to the environmental concentrations. Overall, doses to humans are much more significant from non-plant related sources than those associated with plant operations.

4-8

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

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

SECTION 6 REFERENCES

6.0 REFERENCES

1.

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

2.

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

- Knoxville, TN.

3.

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

4.

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

5.

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

6.

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.

7.

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

8.

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.

9.

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.

10.

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

11.

Andrews, Howard L.

and Lapp, Ralph E. Nuclear Radiation

Physics, Prentice-Hall, Inc., Englewood Cliffs, New Jersey, 1972.

12.

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

13.

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

6-1

14.

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

15.

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

16.

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

17.

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

18.

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.

19.

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

20.

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

21.

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.

22.

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

23.

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

24.

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

25.

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

26.

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

6-2

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

28.

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

29.

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

30.

ENN-LI-1 02, Corrective Action Process

31.

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

APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS REQUIREMENTS

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

Table A-1 provides the sampling station number, location, sector, distance from Indian Point, ODCM designation and sample type. Non-ODCM samples are also listed but have no ODCM designation code. This table gives the complete listing of sample locations used in the 2004 REMP.

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

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

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

In addition to the sampling outlined in Table A-1, there is the environmental surveillance requirement that an annual land use and milch animal census be performed. See Tables B-17 and B-18 for the milch animal and land use census.

A-1

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS RETSIRECS

.SM`SAMPLE-I

-OCATION

-:iDISTANCE

` -'-.-SAMPLE TYPES, j

'STATION SAPL I

' D ESIG N A TIO N

_ _ _ _ _ _ _-l 3

DR8 Service Center Building Onsite -

Direct Gamma 0.35 M i (SSE) at 1580 ie t a m AlOst Air Particulate, 4Al Algonquin Gas Line Onsite -

ArPriuae 4 A1Al_______

Gas 0.28 Mi (SW) at 2340 Radioiodine A4 Air Particulate, 5

A4 NYU Tower Onsite -

Radioiodine, DR1008 i(SW t28 Direct Gamma 7

Wb1 Camp Field Reservoir 3.4 Mi (NE at 51 0 Drinking Water 8

NR New Croton Reservoir 6.3 Mi (SE) at 124° Drinking Water 9

Wal Plant Inlet (Hudson River Intake)*

Onsit -

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

Onsite -

HR Water, 10NR DshreCnl(iigZe) 0.3 Mi (WSW) at 2490 HR Bottom Sediment 14 DR7 Water Meter House Onsite -

Direct Gamma 0.3 M i (S E ) at 1330 i e t a m NR HR Aquatic Vegetation, 17 NR Off Verplanck 1.5 Mi (SSW) at 202.5° HR Shoreline Soil, NR HR Bottom Sediment 20 DR38 Cortlandt Yacht Club 1.5 Mi (S) at 180° Direct Gamma (AKA Montrose Marina) 22 NR Lovett Power Plant 1.6 Mi (WSW) at 2440 Air Particulate, NR Radioiodine NR Precipitation, A5 Air Particulate, A5 Radioiodine, 23 DR40 Roseton*

20.7 Mi (N) at 3570 Direct Gamma, lc3 Broad Leaf Vegetation, NR

Soil, 1b2 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, 28 DNR4 Lent's Cove 0.45 Mi (ENE) at 0690 Bottom Sediment, NR HR Aquatic Vegetation

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

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING. RETSIRECS

'SAiN ',AML'OAINDISTANCE1f--

.SAMVPLE TYPES~

DESIGNATION NR Air Particulate, 29 NR Grassy Point 3.37 Mi (SSW) at 1960 Radioiodine, DR39 Direct Gamma 33 DR33 Hamilton Street (Substation) 2.88 Mi (NE) at 053° Direct Gamma 34 DR9 South East Corner of site Onsite -

Direct Gamma

__________________________0.52-Mi(S) at 1790 iet am 35 DR5 Broadway & Bleakley Avenue Onsite -

Direct Gamma DR5 Broadwy

& Bleakey Avenue0.37 Mi (E) at 0920 38 DR34 Furnace Dock (Substation) 3.43 Mi (SE) at 1410 Direct Gamma NR Precipitation, 44 NR Peekskill Gas Holder Bldg 1.84 Mi (NE) at 052° Air Particulate, NR Radioiodine 50 Wc2 Manitou Inlet*

4.48 Mi (NNW) at 3470 HR Shoreline Soil 53 Wc1 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 202° Direct Gamma 57 DR1 Roa Hook 2 Mi (N) at 005° Direct Gamma 58 DR17 Route 9D - Garrison 5.41 Mi (N) at 3580 Direct Gamma 59 DR2 Old Pemart Avenue 1.8 Mi (NNE) at 0320 Direct Gamma 60 DR18 Gallows Hill Road & Sprout Brook 5.02 Mi (NNE) at 0290 Direct Gamma

~R oad_

61 DR36 Lower South Street & Franklin Street 1.3 Mi (NE) at 052° Direct Gamma 62 DR19 Wesrook Drive 5.03 Mi (NE) at 0620 Direct Gamma

~~(near the Community Center) 50 i(E t02 64 DR20 (School Parking Lot) 4.6 Mi (ENE) at 067° Direct Gamma 66 DR21 Croton Avenue - Cortlandt 4.87 Mi (E) at 0830 Direct Gamma 67 DR22 Colabaugh Pond Road - Cortlandt 4.5 Mi (ESE) at 1140 Direct Gamma 69 DR23 Mt. Airy & Windsor Road 4.97 Mi (SE) at 1270 Direct Gamma 71 DR25 Warren Ave - Haverstraw 4.83 Mi (S) at 1880 Direct Gamma 72 DR26 Railroad Avenue & 9W - Haverstraw 4.53 Mi (SSW) at 2030 Direct Gamma 73 DR27 Willow Grove Road & Captain 4.97 Mi (SW) at 226° Direct Gamma Faldermeyer Drive 74 DR12 West Shore Drive - South 1.59 Mi (WSW) at 2520 Direct Gamma

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

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS S

lING RETS/RECS.

STTO

-SAMPLE;-..

LOCATION DISTANCE SAMPLE TYPES'."

-STATION -.--...;-.- -b-.^-.<---..

----u---',-;

I.-v

DESIGNATION i

-1' I

75 DR28 Palisades Parkway 4.65 Mi (NW) at 3100 Direct Gamma 76 DR1 3 West Shore Drive - North 1.21 Mi (W) at 276° Direct Gamma 77 DR29 Palisades Parkway 4.15 Mi (W) at 2720 Direct Gamma 78 DR14 Rt. 9W across from R/S #14 1.2 Mi (WNW) at 2950 Direct Gamma 79 DR30 Anthony Wayne Park 4.57 Mi (WNW) at 2960 Direct Gamma 80 DR15 Route 9W South of Ayers Road 1.02 Mi (NW) at 317

° Direct Gamma 81 DR31 Palisades Pkwy - Lake Welch Exit 4.96 Mi (WSW) at 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 2.89 Mi (NNE) at 0250 Direct Gamma (near rock cut) 90 DR3 Charles Point 0.88 Mi (NE) at 0470 Direct Gamma 92 DR24 Warren Road - Cortlandt 3.84 Mi (SSE) at 149° Direct Gamma A2 Air Particulate, 94 c2 IPEC Training Center Onsite-Radioiodine, 0.39 Mi(S) at 1930 Broadleaf Vegetation, NR Soil

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

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

Peekskill Westchester County Rockland County I

1 mile I

Key:

A - Waterbome: Surface (HR) Wa#

o - Direct Radiation Sample Location DR#

El - Air Particulate & Radioiodine A#

O - HR Shoreline Sediment Wc#

Ic# - Broadleaf Vegetation Ibl - Fish and Invertebrates (where available downstream)

A-5

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

Roseton (20.7 mi. N): [i i) lc3 Upstream:

lb2 Orange County Bear Mountain Bridge 0

JO Putnam County 0

(D 0

1 5 miles I

Rockland County Key:

Q - Direct Radiation Sample Location DR#

a

- Air Particulate & Radioiodine A#

<>- HR Shoreline Sediment Wc#

O - Waterbome: Drinking Wb#

Westchester County lc3 - Broadleaf Vegetation Ib2 - Fish and Invertebrates (where available upstream)

A-6

FIGURE A-3 SAMPLING LOCATIONS NL' Roseton (20.7 mi. N): 23: p

dounty Putnam County Cold Spring (10.88 mi. N) : 84 :V Orange C Bear Mountain Bridge 10: *,

99: sp

p U 17:

v 29: v 101 :sp Rockland County K

y:

- Air Particulate & Radioiodine v - Aquatic Vegetation

_ - HR Bottom Sediment p - Precipitation Westchester County

8:dw 27: E l

l Ke) 5 miles

<>- HR Shoreline Sediment

- Soil sp - Special Water dw - Drinking Water A-7

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

(b)

.-~

---AIRBORNE FOO SEDIM, NT ANALYSIS WATER PARTICULATES FISH (pC: kg, MILK PO T

(SEDIMENTgw pC/)

OR GASES f.We)

JpCI/I)i (pCI/kg, wet)

Gross 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

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 27).

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

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

A-8

TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES AIRBORNE; ANAYSS iWATER PARTICULAE IH g

MILK I

O (pCAILYwe)S(pIIL)

PRODUCTS~

( CI~m

)

-(PpCIIkg, w et)

H-3 20000 (a)

Mn-54 1000 30000 Fe-59 400 10000 Co-58 1000 30000 Co-60 300 10000 Zn-65 300 20000 Zr-Nb-95 400 1-131 2 (b) 0.9 3

100 Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La-140 200 300 (a) For drinking water samples. This Is the 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCIVL may be used.

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

A-9

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS

SUMMARY

APPENDIX B B.1 2004 Annual Radiological Environmental Monitorin-Program Summary The results of the 2004 radiological environmental sampling program are presented in Tables B-2 through B-16. Table B-2 is a summary of the ODCM samples and Table B-16 is a summary of the non-ODCM samples. The format of these summary tables conforms to the reporting requirements of the ODCM, NRC Regulatory Guide 4.8 (Reference 4), and NRC Branch Technical Position to Regulatory Guide 4.8 (Reference 14). In addition, the data obtained from the analysis of all the individual ODCM samples are provided in Tables B-3 through B-15.

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

B.2 Land Use Census In accordance with Sections 4.11.B of the ODCM, a land use census was conducted to identify the nearest milch animal and the nearest residence. The results of the milch animal and land use censuses are presented in Tables B-17 and B-18, respectively. In lieu of identifying and sampling the nearest garden of greater than 50m2, at least three kinds of broad leaf vegetation were sampled near the site boundary in two sectors and at a designated control location (results are presented in Table B-14).

B.3 Sampling Deviations During 2004, environmental sampling was performed for six media types required by ODCM, five other media types and direct radiation. A total of 1338 were obtained.

Of the scheduled samples, 99% were collected and analyzed for the program.

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

BA4 Analytical Deviations There were no analytical deviations for 2004.

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

B-1

THIS PAGE LEFT INTENTIONALLY BLANK B-2

TABLE B-1

SUMMARY

OF SAMPLING DEVIATIONS 2004 VTOTAL>*

SAMPUING TREASON E'MEDA SCHETOULE.NUMBER OF

,EDij, SCHEAULNSD EFFICIENCY.

' FOR

-dSAMPLES,

~DEVIATION MEDIA PARTICULATES IN AIR 467 3

98.1 SEE TABLE B-la CHARCOAL FILTER 467 3

99.8 SEE TABLE TLD 163 1

98.8 SEEB-LE HUDSON RIVER WATER 32 0

100.0 DRINKING WATER 36 0

100.0 SHORELINE SOIL 10 0

100.0 BROAD LEAF 62 1

100.0 SEE TABLE VEGETATION B-1c FISH & INVERTEBRATES 21 1

84.6 SEE TABLE SUBTOTALS 1254 9

98.9 NON-ODCM MEDIA AQUATIC VEGETATION 12 2

100.0 HUDSON RIVER BOTTOM 100.0 SEDIMENT SOIL 4

0 100.0 PRECIPITATION 8

0 100.0 SPECIAL WATER 52 1

96.2 SAMPLES SUBTOTALS 84 3

98 SEE TABLE B-1c SEE TABLE B-1c IOVERALLTOTALS 1

1338 J

12 l

99.0 1

TOTAL NUMBER OF ANALYSES REPORTED =

1326

' Samples not collected or unable to be analyzed.

B-3

TABLE B-la / B-1b/B-1c TABLE B-1a 2004 Air Sampling Deviations

- STATION WEEK '"

PROBLEM I ACTIONS TO PREVENT RECURRENCE The gated area was broken into and the bird house was tipped

05 NYU Tower I

~

over. The plug was unpluged and the electric cut out was opened.The air sample was off from Friday afternoon until Tuesday. We reinstated the sample and put on a new lock.

When we got to the Met tower, the air sample pump was not running. By the hour meter it was off for about 21.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months . That

95 Met Tower 18 puts it off at 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months on Monday When we came back at 1230 hours0.0142 days 0.342 hours 0.00203 weeks 4.68015e-4 months to check the unit, the power was returned to service IIhe asl bdiIIpit pullip Wda IIUi lUlMlilily. IL Idl 101 OIUy "* IIUUlb

23 Roston 25 until Thurday. We contacted Dynegy and they had the outlet replaced because it was damaged. We restarted the air sample Sk-A G.

4-.,

TABLE B-1b 2003 TLD Deviations STATION QUART 7

PROBLEM i ACTIONSTO PREVENT RECURRENCE -

DR-28 fourth TTLD was sent for evaluation but there were no results TABLE B-1c 2004 Other Media Deviations

-.'.-i:-STATION,. t SAMPLE SCHEDULE."-. PROBLEM I ACTIONS TO PREVENT RECURRENCE

102 Trap Rock Quarry 4

Trap Rock Quarry was frozen over no sample.

We only got two of the three broad leaf vegetations and the two

23 Roseton 17 that we got were lite (less then 1000 grams). That was all we could get this early in the spring.

17 Off Verplanck 24 Unable to get aquatic vegetation in this area because it is not

17 Of Ve~lank 24growing yet.

84 Cold Spring 24 Unable to get aquatic vegetation in this area because it is not growing yet.

We only got one sample of inverterbrates at one location this yea M25 Down Stream of plant 37 and the procedure requires two samples at two locations.

B-4

TABLE B-2*

ODCM ANNUAL

SUMMARY

- 2004 t

LOCATION(b) OF HIGHEST',

TYPE AND TOTAL

-NUMBER OF MEDIUM (UNITS),.

NUMBER OF-J' LOCATIONS AND

._CONTROL LOCATION:,_

NONROUTINE

,;.-SEE TABLE_

ANALYSIS (c;

INCAOR DESIGNATION ORTS PERFORMED-'.

RANGE

' RANGE-RANGE,______AG__

DIRECT RADIATION

76 West Shore Drive North (mR / standard quarter)

T Ra N/A 12.7(163/163)/10.8 -17.0 1.21 Mi. (2760) DR13 11.1 (4/4)110.8-11.4 0

B-3 163 17.0 (2/4)116.2-17.0 AIR PARTICULATES

95 Met Tower 1.84 Mi.

AND RADIOIODINE GB (467) 0.01 0.015 (467/467) /0.001-0.023 (520) 0.014 (52/52) /

0.005 o

(pCVm 3) B-6, B-7, B-8 0.016(52/52)/0.008-0.023 0.021 1-131 (467) 0.07

< Le

< L__

< Lc 0

GSA (36)

Cs-134 0.05

< Le

< L 0

Cs-137 0.06

< L

<ILc 0

SURFACE HUDSON RIVER WATER (pCUL)

H-3 (8) 3000

< Lc

< Lc 0

B-9, B-10 GSA (24)

Mn-54 15

< L

< Lc 0

Co-58 15

<Le

< L

< L 0

Fe-59 30

< Le

< Lc

< L 0

Co-60 15

< Le

< k

< L0 o

Zn-65 30

< Lc

< Le

< L 0

Zr/Nb-95 15

< Lc

< Le

< Le 0

1-131 15

<Le

< Le Le 0

Cs-134 15

< Lc

<Ic L<c 0

Cs-137 18

< L

<Ic

<Le 0

Ba/La-140 15

< Lc

<Lc

<Lc 0

5Th Street Well 6.3 Mi (pCi/L) B-11, B-12 GB (36) 4 2.74 (36/36) / 1.38-3.02 (124.

6 N/A 0

6.72 (12112) / 4.84-8.60 H-3 (8) 2000

< Lc

< Lc N/A 0

GSA (241 Mn-54 15

< L

< Lc N/A 0

Co-58 15

< Lc

< Lc N/A 0

Fe-59 30

< Lc

< Lc N/A 0

Co-60 15

< Lc

< Lc N/A 0

Zn-65 30

< Lc

< Lc N/A 0

B-5

TABLE B-2*

ODCM ANNUAL

SUMMARY

- 2004 MEDIUM '(UNITS)

SEE TABLE,.

=

r TYPE-AND TOTAL NUMBER OF.

t.-'ANALYSIS;':;.-.,

PERFORMED.

'..' t.^;'. '{-

t_

s s S-:

t

.:.':h a,..,':

,. t 4 LLD (cd).'

W.t ;....;

s f..;..

x, 4.-o

-'INDICATOR LOCATIONS:'

,,;: i"MEAN (a)>u^

D;-

"'r AM

. ' 'I *,,,

LOCATION (b).OF HIGHESTj

ANNUAL MEAN-:--,

t LOCATIONS AND',

DESIGNATION MEAN/):

A MVf.c CONTROL LOCATION:,:'

D.

A MDAf W

NUMBER OF NON ROUTINEk'

' REPORTS.

0 0

0 DRINKING WATER ZriNs95 15

<L, N/A (CONT) 1-131 1

< Le

< k N/A Cs-134 15

< Lc N/A Cs-137 18

< Lc

< Le N/A Ba/La-140 15

<L 0

<ILc N/A SHORELINE SOIL (pCi/kg - dry) B-13 GSA (10)

Cs-134 Cs-137 150

+

0 0

180 104 (5/6) / 14 -203

17 Off Verplanck 1.5 Mi. (202.50) 203 (1/2) / 173-203 138 (3/4) / 18-172 BROADLEAF VEGETATION GSA (62)

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

<Le

<L

< LC 0

Co-60 N/A

< Le

< Lc

< L, 0

Cs-134 60

< L,

< Lc

< Le 0

94 IPEC Training Center Cs-1 37 80 10.14(1/62) / 10.14-10.14 0.39 Mi. (202.50)

< Lc 0

10.14 (1/62)1 10.14 FISH AND INVERTEBRATES GSA (21)

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

<L

< L

< Lc 0

Co-58 130

< Lc

< Lc 0

Fe-59 260

< Lc

< L.

< Lc 0

Co-60 130

< Lc

< Lc 0

Zn-65 260

< Lc

< b-

< Lc 0

Cs-134 130

< Lc

< Le

< Lc 0

Cs-137 150

<Lc

< Lc

<ILc 0

B-6

Table B-2 Notation 2004 ANNUAL

SUMMARY

TABLE NOTES

=

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

N/A

=

Not applicable.

(a)

=

(Detectable activity measurements) / (Total measurements.)

(b)

=

Location is distance in miles and direction in compass degrees.

(c)

=

Required LLD, see Table A-2 (d)

=

Required LLD > Critical Level (Lc).

GB

=

Gross Beta Analysis.

GSA

=

Gamma Spectroscopy Analysis.

The format of Table B-2, ODCM 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-1 34 and Cs-1 37 B-7

Table B-2 Notation (Continued) 2004 ANNUAL

SUMMARY

TABLE NOTES

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

4. The column labeled Indicator locations gives the results for all the indicator sites. For shoreline soil, two out of six samples from indicator locations had Cs-1 37, but no Cs-134. The mean of the Cs-137 from the two indicator location sample results that were > Lc was 183 pCi/kg-dry. The range of the samples results > Lc was 183 to 256 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, Off Verplanck, 1.5 miles from Indian Point at compass direction 202.5 degrees.

6. The control location column is next. For shoreline soil in 2004,1-131 was detected in 2 of 3 samples and is not attributed to plant operations but likely from sewage effluent discharges from nearby communities.

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 2004 DIRECT RADIATION, QUARTERLY DATA (mR per STANDARD QUARTER)

SttionD Sector 1ST Quarter 2ND Quaiter 3RD Quart

-4 u

A Y

DR-01 N

14.1

+/- 0.6 14.4

+/- 0.6 13.2 +/- 0.6 16.5 +/- 1.2 14.6 58 DR-02 NNE 13.5

+/- 0.6 12.9 +/- 0.9 12.3 +/- 0.9 15.0 +/- 1.2 13.4 54 DR-03 NE 11.1 +/- 0.6 12.3

+/- 0.9 9.3 +/- 0.9 11.1

+/- 0.6 11.0 44 DR-04 ENE 12.0

+/- 0.6 11.4

+/- 0.9 11.7 +/- 1.2 11.7 +/- 0.9 11.7 47 DR-05 ENE 12.3

+/- 0.9 12.3

+/- 0.9 11.4 +/- 0.3 12.3

+/- 1.2 12.1 48 DR-06 ESE 12.3 +/- 0.9 11.4

+/- 0.3 10.8 +/- 0.9 11.7 +/- 0.3 11.6 46 DR-07 SE 14.1

+/- 1.5 13.2

+/- 0.6 14.1

+/- 1.2 14.2 +/- 0.6 13.9 56 DR-08 SSE 11.7 +/- 0.6 12.3

+/- 1.5 12.0 +/- 1.2 11.1

+/- 0.9 11.8 47 DR-09 S

12.0

+/- 0.6 10.8 +/- 0.6 12.3 +/- 1.2 12.0 +/- 0.6 11.8 47 DR-10 SSW 13.2

+/- 0.6 12.3 +/- 0.6 13.2

+/- 0.6 15.0 +/- 0.9 13.4 54 DR-11 SW 10.5

+/- 0.9 9.6 +/- 0.9 10.2 +/- 0.6 10.5 +/- 1.2 10.2 41 DR-12 WSW 16.2 +/- 1.8 15.6 +/- 2.1 15.6 +/- 1.5 15.0 +/- 0.9 15.6 62 DR-13 WSW 17.7

+/- 1.2 16.8

+/- 0.9 17.1

+/- 0.9 16.2 +/- 0.6 17.0 68 DR-14 WNW 12.3

+/- 0.9 12.0

+/- 1.2 12.6 +/- 0.9 12.9 +/- 0.9 12.5 50 DR-15 NW 11.7

+/- 0.6 11.4 +/- 0.9 11.4 +/- 0.9 12.0

+/- 0.6 11.6 47 DR-16 NNW 13.2

+/- 0.9 12.9

+/- 1.5 15.3 +/- 1.2 13.8 +/- 1.2 13.8 55 DR-17 N

14.7 +/- 0.9 13.5

+/- 0.9 13.5 +/- 0.9 15.0 +/- 0.6 14.2 57 DR-18 NNE 12.3 +/- 0.3 13.5

+/- 1.2 12.6 +/- 0.9 13.8

+/- 0.9 13.1 52 DR-19 NE 13.5 +/- 0.9 13.8

+/- 1.5 14.1

+/- 0.9 14.1

+/- 1.5 13.9 56 DR-20 ENE 12.0

+/- 0.9 11.4

+/- 1.2 12.0 +/- 0.9 12.0 +/- 0.6 11.9 47 DR-21 E

12.6

+/- 1.5 12.0

+/- 0.3 12.6 +/- 0.3 12.6 +/- 0.9 12.5 50 DR-22 ESE 10.5

+/- 0.6 9.6

+/- 1.2 9.9

+/- 0.9 10.2 +/- 0.6 10.1 40 DR-23 SE 12.3

+/- 0.6 13.2

+/- 1.2 12.0

+/- 0.6 12.0 +/- 0.6 12.4 50 DR-24 SSE 12.6 +/- 0.6 13.5 +/- 1.2 12.3

+/- 0.6 10.8 +/- 0.9 12.3 49 DR-25 S

12.6 +/- 1.5 11.4 +/- 2.1 10.8 +/- 0.3 9.9 +/- 0.9 11.2 45 DR-26 SSW 12.6

+/- 0.9 12.0

+/- 1.2 14.1

+/- 4.2 11.7

+/- 2.7 12.6 50 DR-27 SW 13.2

+/- 1.2 11.4 +/- 0.9 12.0 +/- 0.9 10.2 +/- 0.9 11.7 47 DR-28 NW 16.2

+/- 1.2 16.5 +/- 0.6 15.3 +/- 0.6 No Data 16.0 64 DR-29 W

15.0

+/- 0.6 14.7

+/- 0.9 15.9 +/- 0.6 9.0 f 1.2 13.7 55 DR-30 SNS 14.7

+/- 1.2 12.9 +/- 1.2 14.7 +/- 0.6 9.9 +/- 0.9 13.1 52 DR-31 WSW 17.7

+/- 1.2 15.0 +/- 0.9 17.1

+/- 0.9 12.3 +/- 0.3 15.5 62 DR-32 NNW 13.5

+/- 0.9 11.7 +/- 1.2 10.8

+/- 0.3 9.9 +/- 0.9 11.5 46 DR-33 NE 14.4

+/- 1.2 12.3 +/- 0.9 12.0 +/- 0.3 10.5 +/- 0.9 12.3 49 DR-34 SE 11.7 +/- 0.6 11.1

+/- 0.6 10.5 +/- 0.9 9.9 +/- 1.2 10.8 43 DR-35 NNE 12.0

+/- 0.3 12.6 +/- 1.5 12.9 +/- 0.6 11.1

+/- 0.6 12.2 49 DR-36 NE 13.8 +/- 1.5 12.9

+/- 1.5 13.5 +/- 0.6 12.3 +/- 0.9 13.1 53 DR-37 SSW 12.6

+/- 0.9 11.7

+/- 0.9 12.0 +/- 0.6 12.6 +/- 0.9 12.2 49 DR-38 S

12.3 +/- 0.6 11.7

+/- 0.6 12.0 +/- 1.2 12.6 +/- 0.6 12.2 49 DR-39 SSW 14.1 t 0.6 13.5 +/- 0.9 12.9 +/- 0.6 14.7 +/- 2.7 13.8 55 DR N

13.2 +/- 0.6 13.2 +/- 0.6 13.8 +/- 0.6 14.4 +/- 0.9 13.7 55 DR-41 SSE 11.4

+/- 1.2 10.8 +/- 0.6 10.8 +/- 0.6 11.4 +/- 0.6 11.1 44 AVERAGE 13.2 +/-0.9 12.6l I 1.0 12.71 +/- 0.9 12.31 +/- 0.9 12.7 1 51.0 Data not available

- Control Location B-9

TABLE B-4 DIRECT RADIATION, 1998 THROUGH 2004 DATA (mR per Standard Quarter)

Stanidard Mean i-Dvi Minimum Value mMimu Vlue.

Station ID (1998-2004)

.:' (1995-2004)92004) : -

(1998-2004): -rK 2004Average DR-01 15.8 0.8 14.6 17.0 14.6 DR-02 16.2 2.4 13.4 19.8 13.4 DR-03 12.0 0.5 11.0 12.5 11.0 DR-04 13.4 1.1 11.7 14.7 11.7 DR-05 13.5 0.7 12.1 14.3 12.1 DR-06 13.3 0.9 11.6 14.1 11.6 DR-07 16.0 1.0 13.9 17.2 13.9 DR-08 13.1 0.8 11.8 14.1 11.8 DR-09 12.7 1.0 11.0 13.8 11.8 DR-10 13.5 1.7 9.8 15.0 13.4 DR-11 11.4 0.6 10.2 12.1 10.2 DR-12 16.8 1.1 15.6 19.0 15.6 DR-13 18.9 1.1 17.0 20.3 17.0 DR-14 13.6 0.9 12.5 15.1 12.5 DR-15 13.7 1.1 11.6 15.0 11.6 DR-16 14.9 0.9 13.8 15.9 13.8 DR-17 15.1 0.9 14.1 16.7 14.2 DR-18 14.1 0.8 13.1 15.2 13.1 DR-19 14.9 0.8 13.8 15.7 13.9 DR-20 13.8 1.1 11.9 14.8 11.9 DR-21 13.8 1.0 12.5 15.2 12.5 DR-22 11.7 1.0 10.1 13.0 10.1 DR-23 14.0 0.9 12.4 14.7 12.4 DR-24 13.9 0.8 12.3 14.9 12.3 DR-25 12.3 0.6 11.2 13.2 11.2 DR-26 13.8 0.7 12.6 14.7 12.6 DR-27 13.9 1.2 11.7 15.4 11.7 DR-28 15.6 1.1 14.3 17.3 16.0 DR-29 17.2 2.0 13.7 19.3 13.7 DR-30 16.3 1.7 13.1 17.8 13.1 DR-31 18.3 1.7 15.5 20.1 15.5 DR-32 13.3 1.0 11.5 14.3 11.5 DR-33 10.4 2.0 8.5 13.6 12.3 DR-34 13.5 1.3 10.8 15.2 10.8 DR-35 14.4 1.1 12.2 15.3 12.2 DR-36 15.6 1.4 13.1 17.6 13.1 DR-37 13.8 0.8 12.2 14.7 12.2 DR-38 13.1 0.9 12.2 14.6 12.2 DR-39 15.9 1.0 13.8 16.7 13.8 DR-40 15.2 1.1 13.7 16.5 13.7 DR-41*

11.3 5.1 0.0 14.5 11.1 Average 14.2 12.7 B-1 0

TABLE B-5 2004 DIRECT RADIATION INNER AND OUTER RINGS (mR per Standard Quarter)

Inner Ring Outer.Ring c

.nner Ring

.Outr Ring

-D ID

.Annual Average Annual Average DR-01 DR-17 N

14.6 14.2 DR-02 DR-18 NNE 13.4 13.1 DR-03 DR-19 NE 11.0 13.9 DR-04 DR-20 ENE 11.7 11.9 DR-05 DR-21 E

12.1 12.5 DR-06 DR-22 ESE 11.6 10.1 DR-07 DR-23 SE 13.9 12.4 DR-08 DR-24 SSE 11.8 12.3 DR-09 DR-25 S

11.8 11.2 DR-10 DR-26 SSW 13.4 12.6 DR-11 DR-27 SW 10.2 11.7 DR-12 DR-28 WSW 15.6 16.0 DR-13 DR-29 W

17.0 13.7 DR-14 DR-30 WNW 12.5 13.1 DR-15 DR-31 NW 11.6 15.5 DR-16 DR-32 NNW 13.8 11.5 Average 12.9 12.8 B-11

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2004 (pCim 3+/- I sigma)

STATION #

Week#I End Date 4- 4--

5-27

-- - 94 i

95 1

116/2004 0.021 +/- 0.001 0.015 +/- 0.003 0.017 +/- 0.002 0.021 i 0.002 0.019 +/- 0.002 2

1/13/2004 0.02 +/- 0.001 0.021 +/- 0.002 0.018 +/- 0.002 0.023 i 0.002 0.021 +/- 0.002 3

1/21/2004 0.01 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 4

1/27/2004 0.017 +/- 0.001 0.017 +/- 0.002 0.016 +/- 0.002 0.013 +/- 0.002 0.018 +/- 0.002 5

2/3/2004 0.015 +/- 0.001 0.015 +/- 0.002 0.015 +/- 0.001 0.018 +/- 0.002 0.014 +/- 0.001 6

2/10/2004 0.012 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.015 i 0.002 0.014 +/- 0.002 7

2/17/2004 0.023 +/- 0.002 0.017 +/- 0.002 0.021 +/- 0.002 0.022 +/- 0.002 0.023 +/- 0.002 8

2/24/2004 0.02 +/- 0.001 0.018 +/- 0.002 0.017 +/- 0.002 0.02 +/- 0.002 0.018 +/- 0.002 9

3/2/2004 0.02 +/- 0.001 0.019 +/- 0.002 0.021 +/- 0.002 0.021 +/- 0.002 0.02 +/- 0.002 10 3/8/2004 0.014 +/- 0.001 0.016 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.016 +/- 0.002 11 3/16/2004 0.013 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 12 3/23/2004 0.011 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.002 0.012 +/- 0.001 13 3/30/2004 0.016 +/- 0.002 0.016 +/- 0.002 0.018 +/- 0.002 0.018 +/- 0.002 0.015 +/- 0.002 14 4/6/2004 0.006 +/- 0.001 0.006 +/- 0.001 0.006 +/- 0.001 0.006 +/- 0.001 0.007 +/- 0.001 15 4/13/2004 0.015 +/- 0.002 0.013 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.002 0.016 +/- 0.002 16 4/20/2004 0.018 +/- 0.002 0.013 +/- 0.002 no sample 0.016 +/- 0.002 0.01 +/- 0.001 17 4/27/2004 0.011 +/- 0.001 0.007 +/- 0.001 0.01

+/- 0.001 0.012 +/- 0.001 0.009 +/- 0.001 18 5/4/2004 0.018 +/- 0.002 0.011 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.002 19 5/11/2004 0.017 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.018 +/- 0.002 0.015 +/- 0.002 20 5/18/2004 0.016 +/- 0.002 0.008 +/- 0.002 0.017 +/- 0.002 0.014 +/- 0.002 0.016 +/- 0.002 21 5/25/2004 0.017 +/- 0.002 0.015 +/- 0.002 0.017 +/- 0.002 0.013 +/- 0.001 0.014 +/- 0.002 22 6/1/2004 0.011 +/- 0.001 0.014 +/- 0.002 0.011 +/- 0.001 0.01 +/- 0.001 0.013 +/- 0.002 23 6/8/2004 0.011 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.014 +/- 0.002 0.011 +/- 0.001 24 6/15/2004 0.016 +/- 0.002 0.012 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.002 25 6/21/2004 0.014 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 26 6/29/2004 0.016 +/- 0.002 1 0.012 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.002 1 0.016 +/- 0.002

Sample deviation.

- Control location.

B-12

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2004 (pCi/m3 +/- 1 sigma)

STATION #

Week#

EndDate:;

4 5-

27.

94 95 3/4 27 7/6/2004 0.018 +/- 0.002 0.014 +/- 0.002 0.016 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 28 7/13/2004 0.007 +/- 0.001 0.007 +/- 0.001 0.005 +/- 0.001 0.008 +/- 0.001 0.007 +/- 0.001 29 7/20/2004 0.012 +/- 0.002 0.014 +/- 0.002 0.008 +/- 0.002 0.016 +/- 0.002 0.012 +/- 0.002 30 7/27/2004 0.021 +/- 0.002 0.017 +/- 0.002 0.016 +/- 0.002 0.02 +/- 0.002 0.017 +/- 0.002 31 8/3/2004 0.016 +/- 0.002 0.009 +/- 0.002 0.013 +/- 0.001 0.017 +/- 0.002 0.016 +/- 0.002 32 8/10/2004 0.013 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.001 0.015 +/- 0.002 0.014 +/- 0.002 33 8/17/2004 0.016 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.001 0.014 +/- 0.002 0.014 +/- 0.002 34 8/24/2004 0.02 +/- 0.002 0.016 +/- 0.002 0.018 +/- 0.002 0.018 +/- 0.002 0.018 +/- 0.002 35 8/31/2004 0.013 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.014 i 0.002 36 917/2004 0.014 +/- 0.002 0.012 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.002 0.013 i 0.001 37 9/14/2004 0.012 +/- 0.002 0.011 +/- 0.002 0.01

+/- 0.002 0.011 +/- 0.001 0.01 i 0.001 38 9/21/2004 0.01 +/- 0.001 0.007 +/- 0.001 0.006 +/- 0.001 0.009 +/- 0.001 0.007 i 0.001 39 9/28/2004 0.024 +/- 0.002 0.017 +/- 0.002 0.02

+/- 0.002 0.021 +/- 0.002 0.018 i 0.002 40 10/4/2004 0.016 +/- 0.002 0.009 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.002 0.012 +/- 0.002 41 10/12/2004 0.017 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.001 0.018 +/- 0.002 0.016 +/- 0.002 42 10/19/2004 0.016 +/- 0.002 0.012 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.002 0.017 +/- 0.002 43 10/26/2004 0.009 +/- 0.001 0.007 +/- 0.001 0.007 +/- 0.001 0.007 +/- 0.001 0.006 +/- 0.001 44 11/2/2004 0.013 +/- 0.002 0.011 +/- 0.002 0.014 +/- 0.001 0.015 +/- 0.002 0.013 +/- 0.002 45 11/9/2004 0.012 +/- 0.001 0.009 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.002 0.014 +/- 0.002 46 11/16/2004 0.017 +/- 0.002 0.014 +/- 0.002 0.016 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 47 11/23/2004 0.021 +/- 0.002 0.02 +/- 0.002 0.017 +/- 0.002 0.021 +/- 0.002 0.018 +/- 0.002 48 11/30/2004 0.012 +/- 0.001 0.013 +/- 0.002 0.013 +/- 0.001 0.013 +/- 0.001 0.011 i 0.001 49 12/7/2004 0.019 +/- 0.002 0.017 +/- 0.002 0.018 +/- 0.002 0.017 +/- 0.002 0.017 i 0.002 50 12/14/2004 0.007 +/- 0.001 0.007 +/- 0.001 0.009 +/- 0.001 0.005 +/- 0.001 0.007 i 0.001 51 12/21/2004 0.019 +/- 0.002 0.018 +/- 0.002 0.017 +/- 0.002 0.016 +/- 0.002 0.018 i 0.002 52 12/28/200411 0.014 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.015 +/- 0.002 0.014 i 0.002

Sample deviation.

- Control location.

B-13

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2004 (pCilm3 t 1 sigma)

STATION #

Week#

End Date 22 t23*

29%

44 1

1/6/2004 0.021 i 0.002 0.021 +/- 0.002 0.022 +/- 0.002 0.02 +/- 0.002 2

1/13/2004 0.016 i 0.001 0.018 +/- 0.002 0.017 +/- 0.001 0.016 +/- 0.002 3

1/21/2004 0.013 i 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 4

1/27/2004 0.013 i 0.001 0.012 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.002 5

2/3/2004 0.016 i 0.001 0.019 +/- 0.002 0.019 +/- 0.001 0.018 +/- 0.002 6

2/1012004 0.014 i 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.002 7

2117/2004 0.02 i 0.001 0.02 +/- 0.002 0.02 +/- 0.001 0.025 +/- 0.002 8

2/24/2004 0.019 +/- 0.002 0.02 +/- 0.002 0.02 +/- 0.002 0.016 +/- 0.002 9

3/2/2004 0.018 +/- 0.001 0.02 +/- 0.002 0.02

+/- 0.001 0.02 +/- 0.002 10 3/8/2004 0.015 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.002 11 3116/2004 0.014 +/- 0.001 0.014 +/- 0.002 0.012 +/- 0.001 0.011 +/- 0.001 12 3/23/2004 0.014 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 13 3/30/2004 0.015 +/- 0.001 0.015 +/- 0.002 0.016 +/- 0.001 0.014 +/- 0.002 14 4/6/2004 0.009 +/- 0.001 0.006 +/- 0.001 0.007 +/- 0.001 0.006 +/- 0.001 15 4/13/2004 0.014 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.015 +/- 0.002 16 4/20/2004 0.014 +/- 0.001 0.014 +/- 0.002 0.012 +/- 0.001 0.014 +/- 0.002 17 4/27/2004 0.013 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 18 5/4/2004 0.014 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.012 +/- 0.001 19 5/11/2004 0.014 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.002 20 5118/2004 0.019 +/- 0.001 0.017 +/- 0.002 0.016 +/- 0.001 0.018 +/- 0.002 21 5/25/2004 0.01

+/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.002 22 6/1/2004 0.009 +/- 0.001 0.012 +/- 0.001 0.009 +/- 0.001 0.012 +/- 0.001 23 61812004 0.012 +/- 0.001 0.013 +/- 0.002 0.011 +/- 0.001 0.011 +/- 0.002 24 6/15/2004 0.014 +/- 0.001 0.017 +/- 0.002 0.015 +/- 0.001 0.018 +/- 0.002 25 6/21/2004 0.013 +/- 0.001 0.019 +/- 0.003 0.015 +/- 0.001 0.013 +/- 0.001 26 6/29/2004 0.015 +/- 0.002 0.013 +/- 0.002 0.018 +/- 0.002 0.018 +/- 0.002

Sample deviation.

- Control location.

B-14

TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES-2004 (pCi/m3 i I sigma)

STATION #

Week#

End Date 22 23**

-29 44 27 7/6/2004 0.015 +/- 0.001 0.017 +/- 0.002 0.014 +/- 0.001 0.015 +/- 0.002 28 7/13/2004 0.009 +/- 0.001 0.01 +/- 0.002 0.009 +/- 0.001 0.01 +/- 0.002 29 7/20/2004 0.01 +/- 0.001 0.01 +/- 0.001 0.01 +/- 0.001 0.01 +/- 0.001 30 7/27/2004 0.015 +/- 0.001 0.015 +/- 0.002 0.015 +/- 0.001 0.018 +/- 0.002 31 8/3/2004 0.011 +/- 0.001 0.008 +/- 0.001 0.011 +/- 0.001 0.01 +/- 0.001 32 8/10/2004 0.013 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.002 33 8/17/2004 0.011 +/- 0.001 0.014 +/- 0.002 0.014 +/- 0.001 0.014 +/- 0.002 34 8/24/2004 0.016 +/- 0.001 0.016 +/- 0.002 0.016 +/- 0.001 0.014 +/- 0.002 35 8/31/2004 0.017 +/- 0.001 0.018 +/- 0.002 0.016 +/- 0.001 0.016 +/- 0.002 36 9/7/2004 0.016 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 37 9/14/2004 0.011 +/- 0.001 0.01 +/- 0.002 0.009 +/- 0.001 0.008 +/- 0.002 38 9/21/2004 0.009 +/- 0.001 0.008 +/- 0.001 0.011 +/- 0.001 0.01 +/- 0.001 39 9/28/2004 0.018 +/- 0.001 0.018 +/- 0.002 0.018 +/- 0.001 0.017 +/- 0.002 40 10/4/2004 0.015 +/- 0.001 0.016 +/- 0.002 0.015 +/- 0.001 0.015 +/- 0.002 41 10/12/2004 0.015 +/- 0.001 0.017 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 42 10/19/2004 0.014 +/- 0.001 0.013 +/- 0.002 0.016 +/- 0.001 0.015 +/- 0.002 43 10/26/2004 0.007 +/- 0.001 0.005 +/- 0.001 0.005 +/- 0.001 0.006 +/- 0.001 44 11/2/2004 0.015 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.002 45 11/9/2004 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.015 +/- 0.002 46 11/16/2004 0.011 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.002 47 11/23/2004 0.019 +/- 0.002 0.020 +/- 0.002 0.019 +/- 0.001 0.022 +/- 0.002 48 11/30/2004 0.011 +/- 0.001 0.016 +/- 0.002 0.01 +/- 0.001 0.013 +/- 0.002 49 12/7/2004 0.017 +/- 0.001 0.016 +/- 0.002 0.015 +/- 0.001 0.017 +/- 0.002 50 12/14/2004 0.008 +/- 0.001 0.01 +/- 0.001 0.007 +/- 0.001 0.009 +/- 0.001 51 12/21/2004 0.016 +/- 0.001 0.016 +/- 0.002 0.016 +/- 0.001 0.022 +/- 0.002 521 12/28/2004 0.017 +/- 0.002 0.016 +/- 0.002 0.015 +/- 0.001 0.015 +/- 0.002

Sample deviation.

- Control location.

B-15

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AiR PARTICULATE SAMPLES** - 2004 (RESULTS IN UNITS OF 103 pCilm3 +/- 1 SIGMA)

4 ALGONQUIN GAS LINE

-.RADIONUCLIDES FIRST QUARTER-- lSECOND QUARTERl -THIRD QUARTER lFOURTH QUARTERl Be-7' 89.15+/-7.85 111.2+/-10.2 107.4+/-12.06 80i12.27 K-40'

<2.94

<3.55 34.19+/-7.46

<4.95 Mn-54

<0.24

<0.42

<0.59

<0.45 Co-58

<0.51

<1.03

<0.66 Fe-59

<2.43

<1.44

<4.28

<2.32 Co-60

<0.21

<0.57

<0.54

<0.574 Zn-65

<0.78

<1.34

<2.41

<2.47 Zr-95

<0.37

<1.3

<1.38

<1.39 Nb-95

<0.91

<0.92

<1.49

<1.2 Ru-103

<0.69

<0.64

<1.36

<0.91 Ru-106

<1.89

<2.71

<8.7

<7.09 1-131

<4.89

<6.15

<4.54

<8.71 Cs-134

<0.42

<0.41

<0.87

<0.44 Cs-137

<0.22

<0.74

<0.72 BatLa-140

<3.32

<5.73

<7.04

<6.09 Ce-141

<0.55

<0.76

<1.71

<1.37 Ce-144

<1.2

<1.75

<2.79

<2.16 Ra-226^

<4.33

<5.98

<9.17

<6.29 Ac/Th-228*

<1.15

<1.67

<2.43

<2.19 OTHERS

<Lc

<LC

<Lc

5 NYU TOWER RADIONUCLIDES l:FIRST QUARTER SECOND QUARTER -

THIRD QUARTER

.,-FOURTH QUARTER:

Be-7^

125.2+/-10.52 105.7+/-12.34 106.9+/-14.69 111.6+/-13.1 K.40*

<3.95 27.2+/-9.69 50.51+/-11.61

<5.34 Mn-54

<0.51

<0.53

<0.76

<0.36 Co-58

<0.53

<0.77

<0.93

<0.52 Fe-59

<2.16

<2.42

<4.96

<2.68 Co-60

<0.26

<0.48

<0.630

<0.61 Zn-65

<0.99

<1.7

<1.91

<1.76 Zr-95

<1.58

<1.57

<2.5

<1.32 Nb-95

<0.84

<1.36

<2.04

<0.8 Ru-103

<0.8

<1.47

<1.08

<0.65 Ru-106

<3.27

<4.72

<7.09

<3.22 1-131

<7.58

<10.19

<6.9

<7.44 Cs-1 34

<0.48

<0.66

<0.54

<0.52 Cs-137

<0.4

<0.44

<0.81

<0.62 Ba/La-140

<5.13

<9.12

<5.37

<5.64 Ce-141

<1.11

<1.17

<1.6

<0.9 Ce-144

<1.69

<1.66

<3.07

<1.77 Ra-226*

<5.32

<5.87

<13.19

<3.8 Ac/Th-228*

<1.23

<1.71

<1.98

<1.91 OTHERS

<Lc

<Lc Lc Lc

Indicates naturally occurring.

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

` Reported as sample LLD.

B-1 6

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2004 (RESULTS IN UNITS OF 104 pCi/m3 +/- 1 SIGMA)

27 CROTON POINT RADIONUCLIDES FIRST QUARTER

'-'SECOND QUARTER THIRD QUARTER FOURTH QUARTER Be-7*

98.47+/-9.27 106.8+/-10 94.47+/-12.05 77.77+/-13.04 K-40*

<2.26 17.45+/-4.97

<5.09

<10.37 Mn-54

<0.22

<0.52

<0.58

<0.5 Co-58

<0.61

<0.88

<0.81

<11.04 Fe-59

<2.63

<2.77

<3.04

<3.94 Co-60

<0.52

<0.55

<0.58

<0.786 Zn-65

<0.65

<0.85

<0.82

<1.27 Zr-95

<0.84

<1.47

<0.882

<1.19 Nb-95

<0.84

<1

<0.96

<1.45 Ru-103

<0.64

<0.81

<0.68

<1.23 Ru-106

<3.16

<3.78

<5.21

<3.78 1-131

<7.09

<8.38

<5.91

<7.92 Cs-134

<0.42

<0.37

<0.49

<0.472 Cs-137

<0.43

<0.28

<0.42

<0.5 BaJLa-140

<4.43

<5.48

<4.48

<7.93 Ce-141

<0.91

<0.99

<1.31 Ce-144

<0.94

<1.13

<1.29

<2.08 Ra-226*

<5.53 12.2+/-4.28

<5.53

<6.16 AcITh-228*

<1.07

<1.84

<1.47

<1.85 OTHERS

<Lc

<F

<1-c

<Lc

94 IP TRAINING CENTER RADIONUCLIDES l,FIRST QUARTER

-SECOND QUARTER THIRD QUARTER lFOURTH QUARTER l

Be-7*

92.92+/-10.52 149.6+/-11.98 105+/-13.04 65.26+/-11.38 K.40*

<7.44 36.52+/-7.74

<5.91

<6.77 Mn-54

<0.29

<0.68

<0.46

<0.43 Co-58

<0.87

<1.05

<0.45

<0.45 Fe-59

<2.02

<2.8

<2.17

<3.18 Co-60

<0.74

<0.56

<0.47

<0.45 Zn-65

<1.67

<1.58

<1.10

<1.05 Zr-95

<0.99

<1.47

<1.88

<0.95 Nb-95

<0.95

<0.63

<0.77

<1.42 Ru-103

<0.97

<0.82

<1.28

<0.88 Ru-106

<5.43

<4.87

<5.09

<2.8 1-131

<7.14

<10.28

<4.82

<11.46 Cs-134

<0.62

<0.51

<0.370

<0.52 Cs-1 37

<0.46

<0.42

<0.52

<0.57 BalLa-140

<4.9

<5.46

<4.49

<10.23 Ce-141

<1.26

<1.09

<1.33

<1.48 Ce-144

<2.02

<1.89

<2.19

<2.18 Ra-226*

<6.84

<7.57

<6.04

<8.61 AcITh-228*

<1.08

<1.25

<1.29

<1.73 OTHERS

<LC

<LC Lc

Indicates naturally occurring.

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

^^ Reported as sample LLD.

B-1 7

TABLE B-7 CONCENTRATIONS OF GAMMA EMI1TERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2004 (RESULTS IN UNITS OF 103 pCi/m3 +/-1 SIGMA)

95 METEOROLOGICAL TOWER RADIONUCLIDES' FIRST QUARTER :',SECOND QUARTER THIRD QUARTER -FOURTH QUARTER Be-7*

84.25+/-9.29 102.1+/-9.64 87.38+/-13.32 80.58+/-11.23 K.40*

<4.65 43.94+/-6.52

<8.71

<6.17 Mn-54

<0.35

<0.5

<0.54

<0.67 Co-58

<0.63

<0.82

<1.08

<0.86 Fe-59

<2.08

<2.62

<4.79

<2.36 Co-S0

<0.43

<0.47

<0.863

<0.71 Zn-65

<0.55

<0.58

<1.37

<1.18 Zr-95

<1.32

<1.48

<2.99

<1.77 Nb-95

<1.15

<1.23

<1

<0.76 Ru-103

<1.16

<0.9

<1.6

<0.62 Ru-106

<4.16

<4.29

<4.11

<2.63 1-131

<8.18

<10.57

<5.12

<4.24 Cs-134

<0.35

<0.72

<0.77

<0.4 Cs-1137

<0.32

<0.35

<0.38

<0.64 Ba/La-140

<4.95

<4.74

<8.83

<6.24 Ce-141

<1.14

<1.27

<1.19

<0.86 Ce-144

<1.7

<2.59

<1.95

<1.51 Ra-226*

<4.98

<6.23

<7.42

<5.11 AclTh-228*

<0.97

<1.36

<3.49

<1.05 OTHERS

<Lc

<L

<Lc

22 LOVETT POWER PLANT RADIONUCLIDES

'FIRST QUARTER -

SECOND QUARTER

-THIRD QUARTER

-FOURTH QUARTER Be-7*

92.51+/-8.53 95.45+/-10.5 110.6+/-11.23 91.25+/-13.16 K-40*

18.25+/-4.48

<3.74

<3.55

<6.71 Mn-54

<0.58

<0.47

<0.48

<0.73 Co-58

<0.69

<0.35

<0.96

<0.63 Fe-59

<1.25

<2.67

<1.88

<2.91 Co-60

<0.26

<0.37

<0.4

<6.65 Zn-65

<1.29

<0.92

<1

<2.41 Zr-95

<1.02

<1.49

<1

<1.01 Nb-95

<0.7

<1.19

<1.17

<1.03 Ru-103

<0.79

<0.77

<0.74

<1.18 Ru-106

<3.97

<4.18

<4.91

<4.53 1-131

<6.13

<6.51

<4.65

<12.66 Cs-134

<0.45

<0.41

<0.53

<0.34 Cs-137

<0.27

<0.34

<0.22

<0.59 Ba/La-140

<3.1

<5.40

<3.53

<8.80 Ce-141

<0.93

<1.00

<0.93

<1.2 Ce-144

<0.93

<1.47

<1.54 1.970 Ra-226*

<5.9

<4.68

<7.27

<8.4 Ac/Th-228

<1.41

<1.85

<1.36

<2.71 OTHERS

<Lc

Indicates naturally occurring.

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

- - Reported as sample LLD.

B-1 8

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES** - 2004 (RESULTS IN UNITS OF 104 pCi/m3 +1 SIGMA)

23 ROSETON RADIONUCLIDES FIRST QUARTER SECOND QUARTER, THIRD QUARTER FOURTH QUARTER, Be-7*

100.1+/-9.44 130.6i10.49 98.73+/-12.2 75.23+/-10.7 K-40*

<4.21 21.18+/-5.01 40.44+/-8.28

<4.67 Mn-54

<0.39

<0.38

<0.28

<0.43 Co-58

<0.58

<0.57

<0.68

<0.45 Fe-59

<3.07

<3.6

<1.65

<3.15 Co-60

<0.42

<0.53

<0.94

<0.62 Zn-65

<0.75

<0.67

<1.36

<1.65 Zr-95

<0.93

<0.88

<1.95

<1.32 Nb-95

<0.41

<1.25

<0.93

<1.41 Ru-103

<0.73

<0.83

<1.01

<1.01 Ru-106

<3.59

<2.98

<5.03

<2.74 1-131

<7.51

<9.19

<8.65

<11.64 Cs-134

<0.42

<0.36

<1.06

<0.78 Cs-137

<0.31

<0.51

<0.87 Ba/La-140

<4.35

<6.45

<3.46

<6.09 Ce-141

<0.65

<0.77

<1.6

<1.32 Ce-144

<1.32

<1.42

<2.88

<1.63 Ra-226*

<5.04

<4.58

<10.46

<5.56 Ac/Th-228*

<0.93

<1.03

<1.76

<1.19 OTHERS

<Lc

29 GRASSY POINT RADIONUCLIDES' FIRST QUARTER SECOND QUARTER THIRD QUARTER -

FOURTH QUARTERl Be-7*

98.87+/-8.53 133.3+/-10.03 122.4+/-12.37 86.47+/-9.65 K-40*

30.72+/-5.66 26.46+/-5.11

<4.05

<3.94 Mn-54

<0.31

<0.15

<0.6

<0.274 Co-58

<0.67

<0.62

<0.76

<0.32 Fe-59

<2.29

<2.12

<2.06

<2.01 Co-60

<0.47

<0.29

<0.38

<.0393 Zn-65

<1.12

<1.24

<1.35

<0.64 Zr-95

<0.75

<0.96

<0.95

<1.18 Nb-95

<0.81

<0.76

<1.36

<0.84 Ru-103

<0.72

<0.66

<0.67

<0.37 Ru-106

<2.62

<2.38

<5

<3.98 1-131

<6.7

<6.52

<3.75

<7.57 Cs-1 34

<0.43

<0.49

<0.66

<0.48 Cs-137

<0.48

<0.33

<0.46

<0.28 Ba/La-140

<5.26

<4.3

<5.64

<7.65 Ce-141

<0.84

<1.06

<1.47

<0.95 Ce-144

<1.61

<1.63

<1.58

<1.14 Ra-226*

<3.79

<5.25

<5.68

<4.26 AclTh-228*

<1.36

<1.32

<0.99

<1.93 OTHERS

<Lc

<Lc 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** - 2004 (RESULTS IN UNITS OF 104 pCi/m3 +/- 1SIGMA)

44 PEEKSKILL GAS HOLDER BUILDING RADIONUCLIDES liFIRST QUARTER; [ '-SECOND QUARTER THIRD QUARTER FOURTH QUARTER'-

Be-7*

92.88+/-9.27 122.8+/-10.45 126.4+/-13.22 73.5+/-9.44 K.40*

34.87+/-6.25 32.64+/-6.33

<5.23

<5.89 Mn-54

<0.57

<0.55

<0.77

<0.23 Co-58

<0.59

<0.89

<1.09

<0.68 Fe-59

<3.76

<2.39

<2.43

<1.61 Co-60

<0.4

<0.51

<0.42

<0.342 Zn-65

<1.36

<1.46

<1.69

<0.8 Zr-95

<1.19

<1.41

<0.86

<1.2 Nb-95

<1.35

<1.23

<1.01

<0.74 Ru-103

<0.83

<0.93

<0.71

<0.383 Ru-106

<4.65

<5.16

<4.65

<4.69 1-131

<11.06

<8.96

<4.7

<6.03 Cs-134

<0.7

<0.67

<0.65

<0.6 Cs-I37

<0.49

<0.42

<0.43

<0.4 BaILa-140

<6.44

<5.69

<4.19

<4.44 Ce-141

<1.3

<1.37

<0.95

<0.8 Ce-144

<2.42

<2.39

<1.88

<1.65 Ra-226*

<7.01

<7.17

<8.6

<5.62 AcITh-228*

<1.41

<1.34

<1.52

<0.7 OTHERS

<Lc

<L

<Lc

Indicates naturally occurring.

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

- - Reported as sample LLD.

B-20

TABLE B-8 1-131 ACTIVITY IN CHARCOAL CARTRIDGE SAMPLES - 2004*

(pCi/M 3 i 1 sigma)

Week#

EndDate 4

l

5.

27 94

95.

22 23*

l 29

.l 44 1

1/5/2004

<0.023

<0.034

<0.027

<0.024

<0.018

<0.028

<0.017

<0.037 2

1/12/2004

<0.021

<0.014

<0.019

<0.026

<0.019

<0.014

<0.024 3

1/20/2004

<0.014

<0.012

<0.031

<0.027

<0.018

<0.046

<0.021

<0.018

<0.005 4

1/26/2004

<0.018

<0.041

<0.032

<0.035

<0.026

<0.032

<0.028

<0.033 5

2/2/2004

<0.035

<0.022

<0.024

<0.030

<0.025

<0.040

<0.033

<0.025

<0.029 6

2/9/2004

<0.032

<0.015

<0.016

<0.033

<0.029

<0.025

<0.028

<0.019

<0.023 7

2117/2004

<0.020

<0.012

<0.020

<0.018

<0.021

<0.015

<0.019

<0.013

<0.014 8

2/23/2004

<0.014

<0.016

<0.022

<0.024

<0.019

<0.012

<0.021

<0.030 9

3/1/2004

<0.014

<0.018

<0.013

<0.019

<0.018

<0.021

<0.019

<0.015

<0.014 10 3/8/2004

<0.020

<0.029

<0.013

<0.025

<0.041

<0.018

<0.021

<0.016

<0.034 11 3/1512004

<0.014

<0.018

<0.021

<0.013

<0.021

<0.020

<0.023

<0.014

<0.020 12 3/22/2004

<0.020

<0.023

<0.020

<0.015

<0.018

<0.016

<0.034

<0.015

<0.024 13 3/29/2004

<0.018

<0.022

<0.019

<0.014

<0.027

<0.021

<0.013

<0.022 14 4/5/2004

<0.026

<0.031

<0.024

<0.031

<0.025

<0.023

<0.022

<0.021

<0.025 15 4/12/2004

<0.020

<0.023

<0.018

<0.024

<0.023

<0.017

<0.019

<0.015

<0.026 16 4/19/2004

<0.018

<0.023 4o Sampl <0.020

<0.038

<0.017

<0.028

<0.014

<0.026 17 4/26/2004

<0.020

<0.013

<0.010

<0.017

<0.015

<0.014

<0.016

<0.014

<0.020 18 5/3/2004

<0.024

<0.013

<0.017

<0.020

<0.028

<0.022

<0.021

<0.010

<0.023 19 5/10/2004

<0.022

<0.017

<0.019

<0.017

<0.018

<0.025

<0.015

<0.018 20 5/17/2004

<0.028

<0.027

<0.017

<0.022

<0.027

<0.019

<0.028

<0.017

<0.017 21 5/24/2004

<0.011

<0.021

<0.028

<0.021

<0.020

<0.028

<0.020

<0.028 22 6/1/2004

<0.024

<0.017

<0.025

<0.020

<0.015

<0.017

<0.014

<0.016 23 6/7/2004

<0.015

<0.025

<0.019

<0.028

<0.015

<0.029

<0.021

<0.025

<0.030 24 6/14/2004

<0.030

<0.019

<0.024

<0.028

<0.025

<0.018

<0.015

<0.019

<0.036 25 6/22/2004

<0.034

<0.013

<0.019

<0.032

<0.020

<0.013

<0.062

<0.014

<0.018 26 6/28/2004

<0.026

<0.029

<0.018

<0.015

<0.016

<0.020

<0.032

<0.026

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

- Reported as sample LLD.

^ Control location.

^ Sample deviation.

B-21

TABLE B-8 1-131 ACTIVITY IN CHARCOAL CARTRIDGE SAMPLES - 2004*

(pCVM3 +/- I sigma)

Week#

End Date 4

5 27 l

-94 95l

-.22

-23*." --

44 -

27 716/2004

<0.017

<0.014

<0.029

<0.026

<0.030

<0.015

<0.018

<0.013

<0.017 28 7/1212004

<0.031

<0.018

<0.022

<0.025

<0.022

<0.017

<0.022

<0.024 29 7/19/2004

<0.037

<0.018

<0.026

<0.021

<0.023

<0.021

<0.015

<0.019

<0.023 30 7/26/2004

<0.020

<0.021

<0.020

<0.021

<0.015

<0.017

<0.023

<0.021

<0.030 31 8/2/2004

<0.023

<0.028

<0.022

<0.024

<0.017

<0.012

<0.024

<0.019

<0.016 32 8/9/2004

<0.016

<0.026

<0.018

<0.027

<0.022

<0.021

<0.027

<0.016

<0.026 33 8/16/2004

<0.017

<0.019

<0.018

<0.033

<0.020

<0.012

<0.021

<0.016 34 8/23/2004

<0.027

<0.028

<0.026

<0.025

<0.010

<0.013

<0.018

<0.024 35 8/30/2004

<0.025

<0.029

<0.038

<0.046

<0.036

<0.035

<0.037

<0.010 36 9/7/2004

<0.006

<0.021

<0.016

<0.026

<0.022

<0.020

<0.028

<0.014

<0.025 37 911312004

<0.006

<0.018

<0.019

<0.017

<0.027

<0.026

<0.021

<0.013

<0.025 38 9120/2004

<0.025

<0.017

<0.024

<0.021

<0.016

<0.017

<0.023

<0.017

<0.026 39 9/27/2004

<0.021

<0.026

<0.034

<0.020

<0.024

<0.013

<0.019

<0.018 40 10/3/2004

<0.033

<0.011

<0.019

<0.021

<0.018

<0.024

<0.017

<0.021

<0.030 41 10/12/2004

<0.017

<0.019

<0.016

<0.027

<0.009

<0.022

<0.018

<0.018 42 10/18/2004

<0.020

<0.021

<0.031

<0.018

<0.019

<0.028

<0.027

<0.018

<0.019 43 10/25/2004

<0.022

<0.034

<0.020

<0.018

<0.031

<0.021

<0.029

<0.023

<0.019 44 11/1/2004

<0.015

<0.029

<0.017

<0.024

<0.020

<0.017

<0.027

<0.016

<0.020 45 11/8/2004

<0.027

<0.029

<0.042

<0.052

<0.025

<0.029

<0.020

<0.042 46 11/15/2004

<0.015

<0.011

<0.022

<0.013

<0.021

<0.018

<0.021

<0.017

<0.024 47 11/22/2004

<0.043

<0.032

<0.025

<0.022

<0.029

<0.028

<0.031

<0.020

<0.028 48 11/29/2004

<0.018

<0.021

<0.030

<0.019

<0.021

<0.031

<0.021

<0.023 49 12/6/2004

<0.020

<0.030

<0.016

<0.025

<0.018

<0.016

<0.019

<0.020

<0.021 50 12/13/2004

<0.018

<0.022

<0.019

<0.023

<0.022

<0.016

<0.019

<0.016

<0.022 51 12/20/2004

<0.026

<0.031

<0.023

<0.018

<0.024

<0.027

<0.031

<0.028

<0.030 52 12/27/2004

<0.027

<0.019

<0.020

<0.026

<0.017

<0.022

<0.012

<0.020

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

- Reported as sample LLD.

- Control location.

... Sample deviation.

B-22

TABLE B-9 CONCENTRATIONS OF GAMMA EMMITERS IN HUDSON RIVER WATER SAMPLES** - 2004 (pCi/L +/- 1 SIGMA)

9 PLANT INLET (HUDSON RIVER INTAKE)

-Radlonuclide January Februarv March May

-l June Be

<9.49

<10.45

<10.82

<10.32

<8.23

<15.78 K.40*

175.8+/-10.18 183.4+/-15.8 215.8+/-14.07 224.6+/-14.17 184.1+/-10.96 156.2+/-21.78 Mn-54

<0.77

<1.37

<1.04

<1.06

<0.94

<1.76 Co-58

<0.98

<1.31

<1.32

<1.36

<1.06

<2.23 Fe-59

<2.9

<4.57

<3.51

<3.72

<3.09

<6.25 Co-60

<0.74

<1.32

<1.17

<1.18

<0.8

<1.69 Zn-65

<2.01

<2.61

<2.4

<2.29

<1.86

<3.79 Zr-95

<1.81

<2.49

<2.01

<2.14

<1.86

<3.25 Nb-95

<1.35

<1.79

<1.52

<1.72

<1.22

<2.52 Ru-103

<1.42

<1.65

<1.41

<1.51

<1.21

<2.38 Ru-106

<8.87

<13.15

<10.74

<11.33

<8.92

<18.92 1-131

<6.26

<5.32

<4.79

<5.98

<3.91

<7.86 Cs-134

<0.78

<1.15

<1

<1.18

<0.81

<1.88 Cs-137

<0.82

<1.15

<0.98

<1.01

<0.88

<1.48 BalLa-140

<4.23

<3.71

<3.31

<3.99

<2.74

<5.95 Ce-141

<2.21

<2.49

<2.23

<2.35

<1.26

<3.78 Ce-144

<5.86

<7.59

<6.95

<7.2

<5.33

<11.51 Ra-226*

40.69+/-15.29 156.2+/-21.95 92.86+/-18.45 91.25+/-16.62 125.8+/-15.68 108.9+/-30.39 Ac/Th-228*

6.52+/-2.17 9.45+/-3.34 10.41+/-3.62 10.89+/-3.04 5.58+/-2.37

<6.64

10 DISCHARGE CANAL (MIXING ZONE)

Radlonuclide

--J February J

-a March -

May

'June Be-7*

<9.26

<11.36

<8.84

<8.58

<10.46

<14.83 K.40*

115.8+/-8.69 353.2+/-16.82 148+/-9.48 176.7+/-10.5 356.9+/-15.69 251.3i19.01 Mn-54

<0.79

<1.21

<0.79

<0.8

<1.07

<1.62 Co-58

<0.96

<1.44

<0.97

<0.9

<1.25

<1.66 Fe-59

<3.33

<4.32

<2.56

<2.95

<3.5

<4.16 Co-60

<0.9

<1.27

<0.9

<0.82

<1.19

<1.37 Zn-65

<1.76

<2.64

<1.6

<2.21

<2.26

<1.82 Zr-95

<1.59

<2.5

<1.55

<1.92

<1.98

<3 Nb-95

<1.25

<1.87

<1.07

<1.26

<1.45

<2.07 Ru-103

<1.31

<1.82

<1.13

<1.29

<1.42

<2.11 Ru-106

<8.36

<12.73

<7.91

<7.9

<11.4

<16.16 1-131

<6.2

<7.17

<3.29

<3.92

<4.06

<6.93 Cs-134

<0.78

<0.69

<0.82

<0.81

<1.16

<0.94 Cs-137

<0.83

<1.08

<0.92

<0.82

<1.07

<1.43 BalLa-140

<3.63

<4.79

<2.52

<2.94

<3.25

<3.81 Ce-141

<2.36

<2.81

<1.83

<2.04

<2.38

<4.09 Ce-144

<5.9

<8.09

<5.82

<5.77

<7.45

<12.24 Ra-226*

71.57+/-14.88 106.4+/-20.44 75.19+/-15.12 89.86+/-16.28 90.29+/-19.71 93.73+/-27.58 AclTh-228*

<3.02 12.24+/-3.03

<2.87 7.72+/-2.54 9.12+/-2.81 11+/-4.62

Indicates naturally occurring.

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

B-23

TABLE B-9 CONCENTRATIONS OF GAMMA EMMITERS IN HUDSON RIVER WATER SAMPLES** - 2004 (pCVL +/- 1 SIGMA)

9 PLANT INLET (HUDSON RIVER INTAKE)

Radlonuclide Jul

-August.

September

',October

---November; December.

Be-7*

<13.93

<9.17

<17.57

<10.18

<7.54

<11.22 K-40*

189.7+/-16.47 202.7+/-12.22 223.4+/-22.76 367.7+/-14.03 112.4+/-9.37 167.5+/-13.25 Mn-54

<1.26

<1.01

<1.7

<1.03

<0.77

<1.04 Co-58

<1.44

<1.19

<1.83

<1.13

<0.93

<1.25 Fe-59

<4.1

<3.23

<5.55

<3.63

<2.98

<3.45 Co-60

<1.37

<0.93

<2.01

<1.06

<0.83

<0.95 Zn-65

<2.78

<2.14

<3.93

<2.4

<1.86

<2.29 Zr-95

<2.99

<1.72

<2.81

<2.2

<1.79

<2.3 Nb-95

<2.01

<1.27

<2.12

<1.52

<1.22

<1.59 Ru-103

<1.9

<0.81

<2.42

<0.9

<1.1

<1.64 Ru-106

<11.15

<9.63

<17.79

<10.97

<8.8

<10.25 1-131

<6.73

<3.82

<7.22

<5.65

<3.31

<6.97 Cs-134

<1.22

<0.96

<1.77

<1.08

<0.92

<1.09 Cs-137

<1.38

<0.9

<1.46

<0.98

<0.79

<1.01 BalLa-140

<4.8

<3.11

<5.91

<3.81

<2.61

<4.51 Ce-141

<3.23

<1.38

<3.56

<2.48

<1.14

<2.63 Ce-144

<8.95

<7.59

<10.8

<6.85

<5.02

<7.37 Ra.226-

<27.66 79.35+/-15.22 66.88+/-26.99 103.8+/-17.87 126+/-14.95 69.28+/-19.31 AclTh-228^

<4.59

<3.49

<6.52 12.22+/-2.94

<2.78 10.49+/-2.8

10 DISCHARGE CANAL (MIXING ZONE)

Radlonuclide July -

August lSeptember

--October

-- November l

December Be-7*

<11.53

<12.78

<13.79

<7.62

<10.23

<11.28 K-40*

133.3+/-13.46 201.7+/-16.83 221.7+/-20.31 288.8+/-8.92 391.7+/-16.46 123.7+/-11.74 Mn-54

<1.28

<1.19

<1.38

<0.78

<1.13

<1.02 Co-58

<1.35

<1.3

<1.53

<0.89

<1.3

<1.35 Fe-59

<4.15

<3.47

<4.46

<2.25

<3.75

<3.76 Co-60

<1.23

<1.52

<1.3

<0.62

<1.13

<1.13 Zn-65

<2.63

<2.89

<2.92

<0.92

<2.53

<2.28 Zr-95

<2.82

<2.73

<2.54

<1.37

<2.17

<2.02 Nb-95

<1.7

<1.83

<1.99

<1.05

<1.55

<1.61 Ru-103

<1.71

<1.81

<2.28

<0.68

<0.85

<1.8 Ru-106

<12.5

<11.68

<15.34

<7.54

<10.85

<9.73 1-131

<5.92

<4.91

<6.07

<4.83

<3.75

<6.33 Cs-134

<1.11

<1.27

<1.64

<0.49

<0.78

<1.08 Cs-137

<1.07

<1.18

<1.42

<0.71

<1.07

<1.07 BalLa-140

<4.51

<3.88

<4.06

<2.53

<3.17

<4.35 Ce-141

<2.54

<2.96

<3.39

<2.04

<2.39

<2.66 Ce-144

<7.09

<8.09

<10.3

<5.89

<7.33

<7.64 Ra-226*

96.4+/-19.46 38.78+/-22.21 84.01+/-26.74 83.01+/-12.94 100.4+/-16.88 102.2+/-19.05 AcITh-228*

<4.25 6+/-2.59

<5.58 I

1 6.71+/-2.73 A

Indicates naturally occurring.

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

B-24

TABLE B-10 CONCENTRATION OF TRITIUM IN HUDSON RIVER WATER SAMPLES*- 2004 (QUARTERLY COMPOSITES)

(pCi/L i 1 sigma)

9 PLANT INLET (HUDSON RIVER INTAKE)

(Control Location) l: 'Radlonuclide

1ST Quarter. -i 2ND Quarter l 3RD Quarter.. I..4TH Quarter,:

TRITIUM

<432 l

<442 l

<435 l

<409

10 DISCHARGE CANAL (MIXING ZONE)

. Radlonuclide 1.-1ST Quarter - 2ND Quarter l; 3RD Quarter *. 4TH Quarter.l TRITIUM

<432 1

<442 585+/-136 l

521+/-128

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

B-25

TABLE B-11 GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES** - 2004 (pCUL i 1 sigma)

7 CAMP FIELD RESERVOIR

-Radlonucilde

- January: lFebruary ; -.-:March. -:+

---April-May- -.-

June- -.l Gross Beta 1.38 +/- 0.44 1.63+/-0.36 2.14+/-0.46 2.29+/-0.45 1.94 +/- 0.49 2.07 +/- 0.485 Be-7*

<21.16

<15.82

<19.74

<18.79

<25.97

<15.18 K-40*

391.1+/-35.64 148+/-22.46 160.3+/-30.48 280.4+/-27.61 175.1+/-31.82 186.9+/-25.76 Mn-54

<2.26

<2.15

<1.78

<2.66

<3.16

<1.75 Co-58

<2.83

<2.11

<2.94

<1.93

<2.67

<2.4 Fe-59

<7.28

<5.79

<6.59

<4.35

<6.51

<5.99 Co-60

<2.49

<2.85

<2.67

<2.16

<3.12

<1.6 Zn-65

<5.74

<5.06

<5.87

<4.62

<5.72

<4.47 Zr-95

<3.9

<3.33

<4.46

<3.77

<3.81

<3.12 Nb-95

<2.55

<2.18

<2.45

<2.32

<3.43

<2.17 Ru-103

<2.46

<2.17

<2.63

<2.36

<2.94

<2.22 Ru-106

<26.6

<18.96

<26.05

<23.96

<24.52

<16.77 1-131

<0.353

<0.211

<0.21

<0.249

<0.23 Cs-134

<2.37

<1.97

<2.78

<2.05

<3.01

<1.93 Cs-137

<2.29

<1.91

<2.8

<2.02

<2.78

<1.86 Ba/La-140

<4.21

<2.58

<2.04

<2.87

<4.1

<2.96 Ce-141

<3.94

<3.31

<3.6

<3.65

<4.84

<2.9 Ce-144

<16.2

<13.58

<14.8

<17.5

<19.2

<13.4 Ra-226*

<59.63

<42.74 118.9+/-45.96 93.34+/-34.79

<73.67 174.3+/-37.03 AcJTh-228*

<9.13

<5.5

<6.2

<5.6

<10.24

<6.82

7 CAMP FIELD RESERVOIR Radionuclide l -- July-i2.

.August; l September. l-October November December Gross Beta 2.66+/-0.44 2.99+/-0.49 3.33+/-0.51 2.63 +/- 0.47 2.45 +/-.49 2.36 +/- 0.498 Be-7*

<21.47

<24.12

<23.96

<30.45

<11.7

<23.88 K-40*

161+/-31.11 362+/-41.93 158.6+/-34.75 298.3+/-45.19 180.2+/-11.9 103.9+/-26.98 Mn-54

<1.89

<3.36

<2.86

<3.44

<0.98

<1.98 Co-58

<2.31

<3.29

<3.23

<2.87

<1.37

<2.86 Fe-59

<6.96

<8.15

<5

<10.14

<3.93

<6.51 Co-60

<1.74

<3.07

<2.43

<3.56

<0.82

<3.12 Zn-65

<6.42

<7.66

<5.52

<7.46

<2.08

<6.55 Zr-95

<4.18

<4.58

<4.59

<4.78

<2.23

<2.95 Nb-95

<2.91

<2.84

<2.71

<3.05

<1.66

<3.36 Ru-103

<2.97

<3.58

<2.63

<3.53

<1.66

<2.55 Ru-106

<24.48

<35.56

<23.64

<36.12

<10.46

<24.52 1-131

<0.221

<0.263

<0.261

<0.211

<0.498

<0.314 Cs-134

<2.57

<3.04

<2.87

<3.48

<0.99

<2.59 Cs-137

<3

<3.39

<2.54

<3.54

<0.86

<3.07 BalLa-140

<3.93

<4.15

<4.49

<5.2

<6.67

<3.02 Ce-141

<4.39

<4.92

<4.18

<4.52

<2.74

<4.13 Ce-144

<18.8

<19.96

<15.3

<20.27

<6.46

<18.3 Ra-226*

<55.32

<66.05 154.6+/-46.16

<78.81 90.34+/-16.7 81.53+/-48.65 AclTh-228*

<9.66

<11.32 17.32+/-7.4

<12.63 7.11+/-2.89

<8.61

Indicates naturally occurring.

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

B-26

TABLE B-11 GROSS BETA ACTIVITY AND CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES** - 2004 (pCi/L +/- I sigma)

8 NEW CROTON RESERVOIR

'RadIonucIlde

-January- -- %February. %; March,--

April; r,-

.-May

--^June -i-Gross Beta 2.53 +/- 0.46 2.65+/-0.44 3.02+/-0.50 2.13+/-0.44 1.67 +/- 0.50 2.088 +/- 0.48 Be-7*

<18.75

<19.21

<16.06

<23.36

<18.92

<16.86 K-40*

359.7+/-34.95 327.2+/-36.38 266.1+/-26.51 188.8+/-29.57 194.4+/-26.02 108.3+/-24.93 Mn-54

<2.34

<2.39

<2.42

<2.7

<2.07

<2.07 Co-58

<2.76

<2.31

<1.76

<1.91

<2.45

<1.9 Fe-59

<7.03

<6.17

<5.57

<7.61

<5.06

<5.31 Co-60

<2.27

<3.36

<1.72

<2.83

<2.05

<2.74 Zn-65

<6.86

<5.92

<5.09

<6.06

<5.30

<4.27 Zr-95 4.36

<5.08

<3.27

<5.4

<3.21

<3.45 Nb-95

<2.44

<2.49

<2.02

<2.46

<2.23

<2.44 Ru-1 03

<2.83

<2.48

<2.04

<2.39

<2.31

<2.46 Ru-106

<28.4

<22.91

<21.32

<27.85

<23.45

<18.47 1-131

<0.193

<0.242

<0.272

<0.197

<0.209

<0.229 Cs-134

<1.56

<1.61

<2.42

<2.41

<2.5

<2.12 Cs-137

<2.18

<2.46

<2.32

<1.81

<1.96

<2.61 BalLa-140

<3.4

<3.23

<1.84

<1.67

<2.79

<2.59 Ce-141

<4.12

<3.97

<3.9

<3.58

<3.78

<3.16 Ce-144

<17.09

<17.52

<17.3

<13.9

<17.4

<13.7 Ra-226*

<57.59

<60.62 138+/-43.25 132.2+/-41.17 84.4+/-45.56

<45.56 Ac/Th-228*

<8.88

<8.45 13.4+/-5.46

<6.58 11.97+/-5.28

<7.72

8 NEW CROTON RESERVOIR

.Radionuclide-

-,:July August :.September -orOctober Novemberc

December, Gross Beta 2.48+/-0.47 2.92+/-0.47 3.06+/-0.48 3.28 +/- 0.50 2.93 +/- 0.50 2.30 +/- 0.496 Be-7*

<19.03

<17.45

<14.23

<20.24

<19.2

<16.83 K-40*

151.7+/-29.72 263.5+/-25.07 242.3+/-21.07 224.7+/-36.65 141.6+/-23.7 156.3+/-29.72 Mn-54

<2.67

<2.18

<1.78

<1.98

<2.18

<2.16 Co-58

<2.38

<2.45

<1.72

<2.67

<2.22

<2.89 Fe-59

<5.63

<4.92

<4.02

<6.07

<6.22

<6.18 Co-60

<2.79

<2.22

<1.58

<2.46

<1.94

<1.07 Zn-65

<5.94

<5.65

<1.95

<6.42

<5.12

<6.16 Zr-95

<3.19

<3.77

<2.95

<3.81

<4.14

<3.85 Nb-95

<2.74

<1.82

<1.88

<2.83

<2.62

<2.21 Ru-103

<2.8

<2.23

<1.83

<3.02

<2.58

<3.17 Ru-106

<25.23

<21.87

<20.95

<26.55

<19.55

<27.94 1-131

<0.188

<0.219

<0.217

<0.200

<0.382

<0.216 Cs-134

<2.52

<1.43

<1.12

<2.65

<1.22

<2.66 Cs-137

<2.45

<2.02

<1.36

<2.17

<1.93

<2.54 BalLa-140

<2.75

<2.5

<2.61

<4.12

<4.17

<3.18 Ce-141

<4.58

<3.93

<2.35

<4.18

<3.55

<3.98 Ce 144

<18.4

<16.97

<13.7

<18.71

<15.09

<17.5 Ra-226*

<65.13 82.42+/-39.52 55.85+/-33.71

<57.38 65.01+/-33.72

<59.63 Ac/Th-228*

<8.96 16.99+/-6.25

<5.52

<8.64

<7.36

<6.58

Indicates naturally occurring.

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

B-27

TABLE B-1 I 5th Street Well Radionuclide January February March April May June Gross Beta 5.00 +/- 0.53 5.61+/-0.53 5.73+/-0.56 5.65+/-0.55 5.42 +/- 0.60 5.06 +/- 0.57 Be-7*

<18.52

<21.24

<23.76

<28.67

<25.73

<21.34 K-40*

253.2+/-23.98 149.5+/-26.54 191.9+/-33.19 194.6+/-33.19 158.6+/-32.09 180.5+/-29.35 Mn-54

<2.13

<2.92

<2.9

<2.74

<3.37

<2.53 Co-58

<1.27

<2.85

<2.81

<3.16

<3.37

<2.71 Fe-59

<4.63

<7.32

<8.37

<8.05

<7.29

<6.11 Co-60

<2.15

<2.85

<2.6

<3.58

<3.53

<2.77 Zn-65

<2.75

<3.59

<4.21

<4.43

<3.59

<3.36 Zr-95

<3.63

<5.48

<5.02

<6.04

<4.61

<4.14 Nb-95

<1.45

<2.06

<2.01

<2.06

<2.22

<3.18 Ru-1 03

<2.31

<3.08

<3.28

<3.74

<2.99

<2.68 Ru-106

<23.03

<24.65

<28.47

<29.69

<27.85

<21.85 1-131

<0.392

<0.235

<0.216

<0.245

<0.210

<0.279 Cs-134

<1.49

<2.65

<2.86

<3.29

<2.97

<2.5 Cs-137

<1.39

<1.76

<2.73

<2.7

<2.86

<2.73 BalLa-140

<2.56

<2.95

<3.71

<3.76

<4.56

<2.4 Ce-141

<4.8

<5.28

<5.58

<5.43

<4.98

<4.53 Ce-144

<20.89

<20.87

<23.0

<24.4

<20.8

<19.2 Ra-226*

<65.67 126.5+/-51.97 93.11+/-56.47

<79.99

<73.61 96.21+/-54.48 AclTh-228*

<7.84

<9.87

<9.03

<11.15

<10.52

<9.65 H-3

<486 1

5th Street Well Radionuclide July August

?ptemberMar October November December Gross Beta 4.84+/-0.50 8.06+/-0.64 6.41+/-0.79 7.51 +/- 0.64 8.47 +/- 0.69 8.60 +/- 0.691 Be-7*

<19.04

<20.65

<20.23

<27.75

<18.82

<24.85 K-40*

265.7+/-29.04 238.1+/-28.74 362.4+/-35.75 93.8+/-27.74 242.7+/-22.33 88.42+/-32.39 Mn-54

<2.66

<2.85

<2.36

<3.42

<2.08

<3.15 Co-58

<2.63

<3.04

<2.87

<3.15

<2.14

<3.31 Fe-59

<5.05

<5.19

<6.03

<7.59

<5.7

<7.69 Co-60

<2.53

<2.22

<2.24

<2.72

<2.13

<3.28 Zn-65

<2.92

<3.42

<3.86

<3.7

<2.49

<3.93 Zr-95

<4.21

<5.03

<5.05

<6.38

<3.38

<6.23 Nb-95

<1.67

<1.91

<3.14

<2.66

<1.35

<1.73 Ru-103

<2.65

<2.59

<2.73

<2.84

<2.01

<3.06 Ru-106

<27.66

<27.01

<25.33

<28.84

<19.98

<26.57 1-131

<0.282

<0.278

<0. 198

<0.258

<.337

<0.303 Cs-134

<1.8

<1.48

<2.88

<2.99

<1.39

<3.04 Cs-137

<2.68

<2.85

<3.09

<3.69

<1.92

<3.6 BalLa-140

<3.1

<3.11

<5.39

<4.84

<3.15

<3.9 Ce-141

<5.38

<6.09

<4.48

<5.5

<4.42

<5.04 Ce-144

<23.2

<24.08

<18.5

<22.62

<17.37

<21.2 Ra-226*

<70.52

<79.22 34.99+/-22.68

<81.75 98.26+/-41.65

<72.76 AclTh-228*

22.14+/-7.02

<9.92

<9.05

<9.01

<7.38

<9.28

Indicates naturally occurring.

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

B-28

TABLE B-12 CONCENTRATION OF TRITIUM IN DRINKING WATER SAMPLES*- 2004 (QUARTERLY COMPOSITES)

(pCUL i I sigma)

7 CAMP FIELD RESERVOIR l- - Radlonuclide -.-.

1ST Quarter I.: 2ND Quarter l

-3RD Quarter:-- I. 4TH Quarter. -l I

TRITIUM l

<432 l

<442 l

<418 1

<431

8 NEW CROTON RESERVOIR

- Radionuclide. I.1STQuarter.I.2ND Quarter --

.3RD Quarter

- 4TH Quarteri I I

TRITIUM

<432

<442

<418

<431

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

B-29

TABLE B-13 CONCENTRATION OF GAMMA EMITTERS IN SHORELINE SOIL SAMPLES**-2004 (pCi/Kg,dry +/- 1 sigma)

17 OFF VERPLANCK Collection Date K.40 -

Co-60

-Cs.134-Cs-137 I lRa-226^--, ::Ac/Th-228-Others --

6110/2004^^

17483+291

<20.79

<17.33 173+10 1075+184 587+36

<Le 9/2004-16470+450

<16.13

<12.21 203+18.0 12453+345 585+60 L

]

28 LENT'S COVE Collection Date K.40 Co l Cs-134

-:Cs-137 l

Ra-226 I -AclTh-228';

Others -

6/1012004*'^

14873+320

<29.6

<24.43 44.7+10.7 3145+234 1426+60

<Le 912004^^^

13860+565

<26.43

<23.34 71.5+20.1 1841+402 1104+101

<L J

50 MANITOU INLET (control location)

Collection Date K-40 i, Co r Cs-134 :.,

Cs-137t.[

Ra-226--.- ( AclTh-228 [ Others 611712004*^

J 15393+335

<26.36

<27.1 94.9+13.7 3309+290 1424+62

<L, 912004 17070+589

<19.66

<20.52 148+21 1997+363 794+84

<Lc

53 WHITE BEACH

-Collectlon Date l

K140.

Co

,.Cs-134 -:1 Cs-137 - I<

Ra-226^--.r. IAc/T h-228t.1--Others 1l 6/1012004 1 9633+374

<13.3

<11.09 28.6+8.8 l 814.63+125 112.45+22 l L

l 912004-^

10430+433

<14.7

<18.8

<13.99 7227+228 130.4+47.8

<Ic

84 COLD SPRING (control location)

Collection Date l

- K-40; Co.60 l-Cs-134

-lCs-37 l

.Ra-226',,7 Ae/Th-228^l Others 611012004*^^

17483.33+291

<18.07

<11.17 172.66+17.01074.97+183.65 586.87+36.46

<Lc 912004^

35410+674.

<19.83

<13.55

<18.44 860.9+337.5 664.6+72

<L,

Indicates naturally occurring.

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

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

B-30

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION'** - 2004 (pCUKg, wet i 1 sigma)

23 Roseton**

April Radlonuclide Ragweed Motherwort-Common MulleIn Be 405.9+/-24.94 76.83+/-29.73 1463+/-72.15 K

4742+/-83.18 5300+/-139.6 4149+/-173.9 Mn-54

<3

<4.72

<8.44 Co-58

<3.13

<4.83

<8.41 Fe-59

<8.55

<14.19

<19.71 Co-60

<3.18

<5.74

<8.53 Zn-65

<4.14

<13.33

<19.78 Zr-95

<5.56

<9.12

<11.7 Nb-95

<3.36

<5.38

<8.91 Ru-103

<3.04

<4.75

<7.24 Ru-106

<29.29

<49.92

<73.44 1-131

<5.31

<5.84

<9.31 Cs-134

<2.01

<5.52

<7.96 Cs-137

<2.99

<5.41

<7.08 Ba/La-140

<4.52

<6

<11.29 Ce-141

<4.78

<3.76

<8.87 Ce-144

<19.1

<25.8

<36.6 Ra-226-150.2t49.98 173.8+/-73.38 459.9+/-111.9 Ac/Th-228-41.44+/-8.42

<19.86 70.35+/-20.12 June Radlonucilde Grape Leaves Ragweed Common Multein Be 354.6+/-69.94 869.6t88.25 674.2+/-91.52 K

4046+/-227.8 10770+/-351.2 6559+/-303.5 Mn-54

<11.31

<10.45

<11.08 Co-58

<10.83

<12.44

<11.86 Fe-59

<42.66

<31.15

<33.46 Co-60

<13.6

<11.8

<11.14 Zn-65

<32.46

<33.74

<35.7 Zr-95

<18.28

<18.68

<20.41 Nb-95

<10.95

<12.61

<12.47 Ru-103

<10.75

<11.47

<11.64 Ru-106

<103.5

<127.6

<111.1 1-131

<10.4

<13.19

<14.15 Cs-134

<12.18

<13.65

<13.61 Cs-137

<12.19

<11.98

<10.15 Ba/La-140

<15.62

<16.63

<12.2 Ce-141

<11.81

<13.56

<14.72

__Ce-144

<44.3

<54.0

<62.7 Ra-226-771.9+/-142.7

<202.3

<218.6 AcTrh-228' 81.12+/-33.18

<48.43

<38.69 May Radlonuclide ;,Common Mullein' Rag-weed Burdock Be-r7 610.3+/-69.34 354.7+/-51.05 620.5+/-63.98 K

5400+/-217.5 9478+/-253.2 5681+/-219.6 Mn-54

<9.02

<7.07

<7.89 Co-58

<9.91

<7.52

<9 Fe-59

<26.28

<23.46

<22.13 Co-60

<10.14

<8.65

<8.06 Zn-65

<22.84

<18.21

<21.73 Zr-95

<14.87

<13.14

<15.17 Nb-95

<9.72

<8.71

<8.27 Ru-103

<7.45

<7.2

<7.04 Ru-106

<91.62

<79.3

<81.1 1-131

<11.2

<7.72

<9.44 Cs-134

<10.47

<7.39

<8.58 Cs-1 37

<8.05

<7.98

<8.37 Ba/La-140

<11.21

<8.79

<13.08 Ce-141

<7.15

<9.31

<9.11 Ce-144

<40.8

<38.3

<36.3 Ra-226-457.3+/-131.6 307.7+/-120.9 392.2+/-107.5 AcJrh-228-47.09+/-23.25

<28.01 105.6t25.23 July Radionuclide l:-.

Buroci Common Mullion Ragweed.

Be 1451+/-114.8 1921+/-113.7 1296+/-103.6 K

7402+/-343.4 5761+/-268.1 8481+/-322.1 Mn-54

<13.53

<10.35

<11.12 Co-58

<13.56

<9.42

<10.12 Fe-59

<30.72

<26.81

<31.8 Co-60

<12.42

<11.61

<12.49 Zn-65

<27.61

<28.27

<28.83 Zr-95

<21.02

<18.05

<21.47 Nb-95

<15.73

<12.03

<11.89 Ru-103

<10.97

<11.19

<10.72 Ru-106

<118.4

<100.8

<115.6 1-131

<13.26

<11.54

<11.87 Cs-134

<14.13

<11.49

<12.09 Cs-137 1

<1.83

<11.69

<1 1.27 Ba/La-140

<17.08

<12.57

<12.78 Ce-141

<12.59

<13.83

<13.32 Ce-144

<62.23

<53.48

<58.21 Ra-226-529.4+/-170.2

<195.6 388.6+/-152.2 AcJrh-228' 1

<54.43

<38.64

<39.69

Indicates naturally occurring.

Indicates control location.

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

B-31

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2004 (pCi/Kg, wet +/- I sigma)

23 Roseton (continued)**

September October Radlonucide Golden Rod Apulonla Common Mullion Be-7' 4349+/-229.1 815.5+/-97.62 3406+/-220 K-40' 9056+/-478.3 3997+/-226.6 9389+/-489.7 Mn-54

<18.65

<10.21

<21.2 Co-58

<20.54

<13.24

<19.19 Fe-59

<37.58

<28.27

<67.54 Co-60

<17.36

<12.43

<20.62 Zn-65

<35.78

<29.6

<45.42 Zr-95

<26.72

<19.26

<39.27 Nb-95

<20.96

<11.75

<24.37 Ru-103

<12.24

<10.88

<20.62 Ru-106

<142

<140.5

<201 1-131

<20.06

<15.18

<21.82 Cs-134

<17.29

<9.12

<26.31 Cs-137

<11.53

<10.75

<22.18 Ba/La-140

<13.94

<12.98

<21.17 Ce-141

<17.35

<18.7

<25.8 Ce-144

<58.5

<72.5

<114 Ra-226-1041+/-240.9 894+/-205.7 666.8+/-282.1 AcfTh-228'

<38.56 125.1+/-37.68

<74.33 Radionucilde Common Mullion

- Apulonia

.1urrdock~

Be 1290+/-113 2716+/-152.5 2322+/-96.55 K-40, 6931+/-306 2540+/-224.5 10470+/-260.8 Mn-54

<11.81

<12.79

<9.65 Co-58

<10.75

<12.91

<10.28 Fe-59

<40.75

<27.69

<27.65 Co-60

<12.81

<12.22

<8.64 Zn-65

<28.46

<32.05

<25.92 Zr-95

<21.65

<18.02

<16.88 Nb-95

<11.39

<11.62

<9.77 Ru-103

<11.25

<11.83

<9.04 Ru-106

<112.3

<125.6

<93.74 1-131

<12.93

<17.24

<13.03 Cs-134

<13.33

<16.89

<7.14 Cs-137

<11.75

<13.31

<8.86 Ba/La-140

<16.29

<19.12

<10.63 Ce-141

<15.15

<13.75

<14.66 Ce-144

<59.14

<60.05

<57.85 Ra-226-399.7+/-221.7

<248.1 396.2+/-146.7 Ac/Th-228

<40.3

<53.14 64.75+/-32.66

23 Roseton Continued August Radionuclide Ipanese Knotweo Apulonla Golden Rod Be 246.3+/-62.78 1134+/-131.4 2765+/-132.5 K

5268+/-219.2 6005+/-356 8397+/-302.7 Mn-54

<10.68

<17.98

<12.42 Co-58

<9.52

<14.24

<12.64 Fe-59

<20.28

<47.1

<29.23 Co-60

<8.58

<18.5

<13.23 Zn-65

<26.6

<42.97

<34.53 Zr-95

<16.18

<25.77

<16.7 Nb-95

<9.38

<16.44

<11.57 Ru-103

<8.65

<15.59

<12.01 Ru-106

<88.63

<179.4

<120.9 1-131

<11.77

<16.53

<15.97 Cs-134

<7.44

<20.66

<15.33 Cs-137

<8.73

<14.7

<12.54 BalLa-140

<12.79

<18.57

<14.24 Ce-141

<14.1

<18.58

<17.74 Ce.144

<61.5

<76.1

<73.6 Ra-226-520.1+/-155.4 946+/-258.9 366.6+/-181.1 Acrrh-228-64.19+/-26.46

<66.73 104.3+/-39.22

Indicates naturally occurring.

Indicates control location.

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

B-32

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2004 (pCI/Kg, wet +/- I sigma)

94 IPEC Training Center May April Radlonuclide l-Burdock -

Motherwort Ragweed a-Be-7' 735.5+/-45.3 132.3+/-21.39 474.6+/-53.09 K

7786+/-1 67.9 5985+/-94.16 8460+/-215.1 Mn-54

<6.18

<3.22

<6.63 Co-58

<5.96

<3.34

<6.87 Fe-59

<18.72

<9.7

<22.26 Co-60

<7.29

<3.82

<7.59 Zn-65

<15.04

<5.33

<19.62 Zr-95

<10.21

<5.66

<12.16 Nb-95

<6.08

'3.16

<8.26 Ru-103

<5.6

'3.12

<7.35 Ru-106

<60.36

<33.68

<65.79 1-131

<5.42

<3.93

<9.86 Cs-134

<4.21

<2.31

<7.95 Cs-137

<5.97

<3.28

<7.44 BalLa-140

<6.77

<3.48

<10.17 Ce-141

<7.12

<4.81

<8.95 Ce-144

<29.1

<20.9

<36.3 Ra-226' 430.2+/-80.91 251.8+/-58.37 341.5t102.2 AcrTh-2285 57.33+/-16.59 53.89+/-11.27

<27.08 June Radlonuclide l Pokeweed

,-Burdock Ragweed Be 829+/-52.1 560.1+/-32.66 904.4+/-59.41 K-40' 6046+/-165.5 6583+/-130.8 8982+/-213.4 Mn-54

<5.87

<4.13

<7.35 Co-58

'5.8

<4.17

<7.4 Fe-59

'18

<12.33

<21.91 Co-60

<6.79

<5.1

<8.02 Zn-65

<15.81

<10.94

<18.77 Zr-95

<11.2

<7.1

<12.18 Nb-95

<5.92

<4.54

<8.01 Ru-103

<5.71

<3.52

<6.84 Ru-106

<60.83

<40.86

<69.06 1-131

<6.07

<4.45

<6.66 Cs-t34

<6.72

<2.55

<4.7 Cs-137

<6.5 10.14+/-3.14

<7.26 BalLa-140

<6.31

<3.79

<8.15 Ce-141

<7.72

<4.24

<8.66 Ce-144

<32.2

<18.0

<35.6 Ra-226-270.1+/-95.39 432.4+/-49.23 306.4+/-97.17 Acrrh-228-

<23.52

<15.75

'28.21 Radlonuclide i Pokeweed Burdock Burdock Be

<56.08 1197+/-60.76 344.4+/-56.75 K-40t 5207+/-197 6346+/-180.1 7219+/-222.3 Mn-54

<7.99

<6.09

<7.28 Co-58

<7.15

<6.56

<7.9 Fe-59

<24.49

<18.57

<21.25 Co-60

<10.79

<7.69

<7.77 Zn-65

<21.42

<16.19

<18.21 Zr-95

<14.8

<10.98

<12.41 Nb-95

<8.2

<5.24

<8.15 Ru-103

<6.8

<5.32

<7.48 Ru-106

<81.21

<57.08

<78.95 14131

<6.77

<6.85

<7.77 Cs-134

<7.86

<6.47

<8.72 Cs-137

<7.73

<5.81

<7.91 BalLa-140

<1 1.46

<8.04

<8.03 Ce-141

<7.88

<6.74

<9.08 Ce-144

<32.5

<26.4

<39.7 Ra-2261 538.9t94.16 447.1+/-88.99 258+/-104.6 AclTh-228-

<33.37

<20.1

<28.88 July Radionucide Ragweed GrapeLeaves. -,

Burdock Be 1679+/-123 275.9+/-68.16 918.2+/-88.6 K-40' 8471t366.8 4218+/-248.6 7035+/-285.7 Mn-54

<13.94

<10.6

'9.67 Co-58

<12.77

<11.45

<9.84 Fe-59

<36.66

<31.21

<36.7 Co-60

<16.81

<10.71

<12.32 Zn-65

<33.54

<30.53

<27.35 Zr-95

<21.75

'19.69

<19.52 Nb-95

<14.13

<11.24

<11.36 Ru-103

<11.04

<9.63

<9.29 Ru-106

<133.1

<110.3

<106.6 1-131

<13.5

<10.22

'11.04 Cs-134

<14.82

<12.17

<6.71 Cs-137

<11.83

<10.92

<9.51 BalLa-140

<16.78

<13.01

<13.13 Ce-141

<13.77

<13.81

<12.82 Ce-144

<54.46

<56.9

<51.85 Ra-226-752.3+/-183.4

<215.7 405+/-151.4 Ac/Th-228-

<44.84

<36

<36.94

Indicates naturally occurring.

- Indicates control location.

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

B-33

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2004 (pCI/Kg, wet +/- I sigma)

94 IPEC Training Center (continued)

September August Radlonuclide Jewetweed Burdock -- :

Grape Leaves..

Be-r 445.8+/-39.49 300.7+/-38.64 961.9+/-58.15 K

3995+/-132.9 6086+/-156.3 3639+/-134.7 Mn-54

<4.98

<5.14

<6.01 Co-58

<5.07

<5.3

<6.38 Fe-59

<13.02

<15.56

<18.15 Co-60

<5.42

<5.96

<5.27 Zn-65

<7.3

<13.72

<15.4 Zr-95

<8.31

<11.19

<11.38 Nb-95

<5.21

<6.29

<6.13 Ru-103

<4.63

<5.71

<6.49 Ru-106

<51.57

<53.01

<57.86 1-131

<8.4

<8.48

<9.22 Cs-134

<5.04

<3.82

<7.45 Cs-137

<4.75

<5.63

<6.07 Ba/La-140

<6.64

<6.24

<9.57 Ce-141

<6.16

<7.71

<7.92 Ce-144

<23.0

<28.5

<32.8 Ra-226-267.7+/-69.5 279.8+/-87.92 230.5+/-104.2 AcIrh-228

<18.77 27.85+/-15.51

<21.59 October Radionuclide Pokeweed Burdock Common Mulilen Be-r 711.7172.16 2472+/-108.5 65351249.6 K-40' 5791+/-t242.2 6595+/-243.7 11070+/-465.7 Mn-54

<8.1

<8.19

<17.81 Co-58

<9.02

<8.61

<17.49 Fe-59

<25.97

<20.61

<56.33 Co-60

<9.59

<7.16

<18.91 Zn-65

<22.3

<21.6

<46.14 Zr-95

<16.13

<13.31

<31.67 Nb-95

<9.93

<7.78

<19.01 Ru-103

<8.23

<6.81

<15.87 Ru-106

<78.9

<80.62

<181.3 1-131

<10.27

<9.77

<20.36 Cs-134

<10.43

<10.14

<23.81 Cs-137

<9.66

<7.76

<17.57 Ba/La-140

<14.95

<8.43

<21.28 Ce.141

<11.67

<9.03

<22.13 Ce-144

<46.27

<36.12

<93.86 Ra-226-345.7+/-124.5 569.6+/-135.2

<365.9 Acrrh-228

<36.26

<26.35

<67.39 Radionucilde Ragweed Goldenrod Burdock Be 4048+/-256.7 3405+/-214.2 1291+/-120.1 K

12320+/-619.8 8683+/-476.2 6023+/-318.4 Mn-54

<22.09

<19.11

<12.68 Co-58

<25.37

<15.41

<12.11 Fe-59

<69.94

<51.03

<43.24 Co-60

<25.38

<20.16

<10.68 Zn-65

<65.17

<54.87

<29.09 Zr-95

<40.2

<28.31

<20.04 Nb-95

<21.77

<16.84

<15.83 Ru-103

<19.87

'<16.3

<8.54 Ru-106

<239.9

<182.7

<104.8 1-131

<21.29

<19.26

<10.68 Cs-134

<18.59

<17.22

<13.82 Cs-137

<18.88

<16.47

<9.16 Ba/La-140

<34.85

<22.05

<12.29 Ce-141

<25.38

<23.78

<12.33 Ce-144

<101

<97.0

<47.6 Ra-226-844.7+/-330.5

<303.4 385.9+/-167.2 AcrTh-228

<69.04

<52.34

<46.36

Indicates naturally occurring.

- Indicates control location.

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

B-34

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*'

-2004 (pCi/Kg, wet

1 sigma)

95 Meteorological Tower May April

.. Common -

w-Radlonuclide j

Mullen -'

Motherwort; Be-7^

1821+/-72.97 176.2+/-29.34 K40^

5979+/-175.3 5340+/-133 Mn-54

<6.76

<4.9 Co-58

<6.49

<4.8 Fe-59

<19.17

<13.7 Co-60

<8.22

<5.38 Zn-65

<18.82

<12.15 Zr-95

<11.81

<8.91 Nb-95

<6.69

<5.25 Ru.103

<6.73

<4.12 Ru-106

<64.83

<47.57 1-131

<6.72

<5.13 Cs-134

<7.39

<3.03 Cs-137

<7.17

<4.66 Ba/La-140

<8.44

<4.9 Ce-141

<8.27

<5.44 Ce-144

<36.9

<21.2 Ra-226^

275.1+/-98.96 442.7+/-65.32 AclTh-228^

<27.08 18.04+/-10.61 June Radionuclide common Mullie Rag Weed

-BurDdock Be-7^

1579+/-58.1 925.5+/-57.13 454+/-58.89 K.40' 7935+/-152 11300+/-229 8889+/-262.2 Mn-54

<5.94

<7.96

<9.86 Co-58

<6.67

<7.95

<8.61 Fe-59

<16.16

<23.85

<27.14 Co-60

<6.82

<7.92

<10.17 Zn-65

<8.37

<20.66

<22.92 Zr-95

<9.95

<13.67

<16.49 Nb-95

<6.11

<8.06

<8.87 Ru-103

<5.86

<7.02

<7.58 Ru-106

<67.39

<81.3

<94.5 1-131

<7.66

<7.09

<9.69 Cs-134

<4.45

<5.43

<9.35 Cs.137

<6.15

<7.5

<8.1 BalLa-140

<6.54

<9.61

<10.32 Ce-141

<9.09

<8.82

<6.99 Ce-144

<37.0

<38.3

<40.5 Ra-226^

441.1+/-105.3 355.5+/-112.6 361.4+/-112.3 ActTh-228^

123.3t19.49 68.09+/-21.17 65.43+/-27.63 Radlonuclide

Common Mullin

Grape Leaves

. Burdock Be-7^

704+/-73.55 318.5+/-39.8 397.1+/-34.42 K-40^

5652+/-216.2 5128+/-141.1 7097+/-138.4 Mn-54

<9.02

<6.3

<4.83 Co-58

<9.51

<5.59

<4.59 Fe-59

<25.62

<16.89

<13.04 Co-60

<10.79

<6.33

<4.99 Zn-65

<22.12

<15.33

<12.97 Zr-95

<16.87

<10.94

<7.16 Nb-95

<8.66

<6.11

<4.47 Ru-103

<8.47

<5.95

<4.41 Ru-106

<102.5

<69.44

<48.14 1-131

<8.6

<7.76

<5.22 Cs-134

<11.07

<4.18

<3.22 Cs-137

<8.52

<5.85

<4.84 BalLa-140

<9.89

<7.32

<4.9 Ce-141

<10.88

<8.69

<7 Ce-144

<44.2

<37.0

<28.4 Ra-226^

518.4t132.1 298.8+/-101.9 246.7+/-73.32 AclTh-228^

75.22+/-26.25 60.1+/-18.39 85.89+/-16.44 July Radlonuclide Common Mullien

, Ragweed,

-l Burdock --

Be-7 1497+/-105.1 1866+/-126.8 1773+/-121.9 K-40' 6359+/-283.9 8406+/-351.8 8603+/-383.7 Mn-54

<11.1

<15.13

<12.25 Co-58

<12.31

<14.53

<14.09 Fe-59

<36.72

<39.42

<47.31 Co-60

<9.7

<16.07

<16.45 Zn-65

<31.17

<39.12

<33.7 Zr-95

<18.22

<25.68

<15.43 Nb-95

<11.95

<14.24 c15.87 Ru-103

<9.09

<11.96

<12.45 Ru-106

<111.1

<141.9

<118.4 1-131

<12.82

<14.4

<13.72 Cs-134

<12.29

<15.94

<14.57 Cs-137

<9.88

<14.21

<13.17 Ba/La-140

<9.85

<15.53

<12.77 Ce-141

<11.37

<16.44

<13.84 Ce-144

<46.49

<64.67

<53.71 Ra-226^

624.1+/-134 538.6+/-208.8 391.2+/-166.8 AcrTh-228'

<34.48

<44.42

<46.56

Indicates naturally occurring.

Indicates control location.

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

B-35

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION*** - 2004 (pCi/Kg, wet +/- I sigma)

95 Meteorological Tower (continued)

September August Radlonucilde Ragweed Grape Leaves Crown Vetch Be 2168+/-147.6 955.5+/-97.63 228+/-49.51 K

5840+/-340 4700+/-276.4 6256+/-264.9 Mn-54

<9.72

<12.38

<8.45 Co-58

<11.58

<13.9

<7.95 Fe-59

<37.28

<37.13

<27.93 Co-60

<13.46

<13.4

<11.68 Zn-65

<33.94

<25.31

<21.69 Zr-95

<22.7

<19.23

<15.36 Nb-95

<13.28

<11.27

<8.62 Ru-103

<11.93

<10.74

<7.56 Ru-106

<129

<116.6

<92.01 1-131

<12.33

<11.74

<7.99 Cs-134

<14.41

<11.34

<9.93 Cs-137

<11.54

<13.13

<9.86 BatLa-140

<14.97

<12.99

<9.74 Ce-141

<14.95

<12.88

<9.33 Ce-144

<71.6

<56.6

<43.5 Ra-226-

<212.2 372.6+/-149.7

<141.3 AclTh-228-

<43.53

<40.17

<30.88 October Radionucilde Apulonla Ragweed Bittersweet Be-P 1500+/-130.5 6201+/-193.5 540.9+/-76.9 K

3805+/-281.3 9365+/-316.4 4066+/-220.4 Mn-54

<13.6

<15.85

<9.96 Co-58

<11.91

<16.28

<9.5 Fe-59

<38.84

<39.22

<28.89 Co-40

<15.94

<14.61

<10.25 Zn-65

<33.36

<36.11

<27.64 Zr-95

<22.14

<23.97

<16.56 Nb-95

<13.81

<15.54

<11.45 Ru-103

<11.7

<14.2

<9.49 Ru-106

<147.9

<144.1

<95.8 1-131

<15.6

<19.01

<11.24 Cs-134

<16.8

<10.38

<10.36 Cs-137

<13.76

<15.11

<11.24 BalLa-140

<13.77

<17.26

<11.99 Ce-141

<14.97

<21.25

<12.68 Ce-144

<64.63

<97.41

<56.05 Ra-226-600.5+/-201.5 610+/-270.7

<183.1 Acfrh-228'

<46.21 123.8+/-48

<40.65 Radlonuclide

- Grape Leaves Ragweed Goldenrod Be 1088+/-122.2 3714+/-209.7 2997+/-195.6 K

7370+/-341.7 7249+/-418.2 8048+/-452.8 Mn-54

<14.48

<17.32

<13.64 Co-58

<18.64

<15.07

<14.91 Fe-59

<34.84

<49.43

<57.73 Co-60

<16.27

<12.5

<20.01 Zn-65

<21.5

<39.77

<38.91 Zr-95

<25.46

<27.29

<29.04 Nb-95

<14.83

<17.45

<14.03 Ru-103

<13.94

<14.51

<15.73 Ru-106

<156.1

<153

<159.4 1-131

<17.45

<16.33

<16.42 Cs-134

<12.54

<20.38

<20.4 Cs-137

<13.91

<19.29

<12.37 BalLa-140

<14.71

<12.95

<17.69 Ce-141

<21.77

<20.78

<16.06 Ce-144

<99.8

<80.0

<65.3 Ra-226-499.5+/-236.7 976.3+/-291.3 981.5t220.9 ActTh-228-

<55.58

<56.46

<46.6

Indicates naturally occurring.

Indicates control location.

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

B-36

2004 TABLE B-15 CONCENTRATIONS OF GAMMA EMITTERS IN FISH AND INVERTEBRATE SAMPLES (pCi/Kg, weti 1 sigma)

23 Roeston (control)

Radionuclide CATFISH :

STR. BASS

--- WH.- PERCH

- -AMER.-EEL Be-7

<212.5

<163.6

<223.5

<235.4 K-40 4717+/-358.5 4211+/-266.6 5987+/-262.6 5196+/-324.7 Mn-54

<20.24

<13.96

<16.44

<20 Co-58

<23.2

<16.57

<24.62

<25.51 Fe-59

<77.25

<65.66

<69.16

<103 Co-60

<20.17

<12.9

<13.42

<20.49 Zn-65

<25.89

<35.02

<41.26

<36.48 Zr-95

<48.42

<30.98

<39.06

<57.65 Nb-95

<38.93

<28.58

<36.55

<43.66 Ru-1 03

<32.72

<24.56

<33.66

<34.84 Ru-106

<187

<121.6

<183.8

<212.4 1-131

<687.4

<415.8

<981.7

<544.2 Cs-134

<17.63

<12.87

<9.98

<16.02 Cs-137

<14.9

<13.45

<15.71

<16.68 Ba/La-140

<147.1

<141.4

<205.3

<174.4 Ce-141

<43.08

<35.59

<55.24

<54.25 Ce-144

<92.0

<64.3

<98.4

<99.2 Ra-226

<319.4 240.9+/-149.3 654.8+/-255.2 1023+/-280.1 Ac-228

<65.4 95.71+/-34.18 95.05+/-49.06

<65.31 DATE 11-May-04 11-May-04 5-May-04 11-May-04 Radionuclide

-,AMER.;EEL RO-AMER. EEL R1.- :AMER. EEL R2l ---SUNFISH :..-

Be-7

<130.8

<289.6

<220.3

<122.7 K-40 5816+/-280.5 6629+/-535.5 10070+/-486.7 3995+/-320 Mn-54

<15.57

<34.41

<25.37

<15.16 Co-58

<16.3

<38.91

<28.38

<16.52 Fe-59

<49.5

<100.4

<83.07

<59.94 Co-60

<14.46

<34.92

<26.65

<13.24 Zn-65

<29.68

<80.01

<65.23

<45.65 Zr-95

<32.09

<64.82

<51.74

<29.24 Nb-95

<21.04

<37.91

<33.59

<16.91 Ru-103

<17.87

<29.03

<31.37

<17.01 Ru-106

<158.8

<351.2

<285.9

<191.3 1-131

<42.6

<76.19

<70.66

<25.37 Cs-134

< 15.61

<31.63

<26.35

<14.28 Cs-137

<16.73

<31.67

<25.06

<16.47 Ba/La-140

<28.6

<107.6

<73.82

<39.88 Ce-141

<21.68

<39.68

<38.75

<18.52 Ce-144

<76.0

<135

<121

<68.2 Ra-226 543.3+/-210.8 1625+/-390.6 995.8+/-358.2 435.7+/-210.9 Ac-228

<57.86

<108.5

<95.88

<49.8 DATE 9-Jun-04 9-Jun-04 9-Jun-04 16-Jun-04

Indicates naturally occurring.

B37

2004 TABLE B-15 CONCENTRATIONS OF GAMMA EMITTERS IN FISH AND INVERTEBRATE SAMPLES (pCi/Kg, wet +/- I sigma)

23 Roeston (control)

Radionuclide WHITEPERCH All AMER. EEL.-

,;,.AMER;EEL ?l' Be-7

<292.8

<262.8

<124.4 K-40 6448+/-337 5694+/-361.9 3289+/-262.4 Mn-54

<20.54

<19.13

<15.68 Co-58

<31.95

<28.26

<17.33 Fe-59

<113.1

<105.3

<63.39 Co-60

<19.68

<19.85

<13.54 Zn-65

<55.56

<51.52

<31.67 Zr-95

<53.78

<52.36

<33.82 Nb-95

<51.45

<49.81

<23.47 Ru-103

<49.11

<46.12

<18.96 Ru-106

<227.2

<229.1

<141.1 1-131

<1692

<1353

<292.8 Cs-134

<13.03

<20.36

<10.22 Cs-137

<18.48

<23.71

<12.16 Ba/La-140

<304.2

<384.7

<106 Ce-141

<83.6

<64.36

<31.26 Ce-144

<134

<107

<49.4 Ra-226 810+/-330.4 725.8+/-289.6 346.5+/-158.5 Ac-228 217.9+/-65.57

<68.84

<37.95 DATE 4-Aug-04 4-Aug-04 17-Aug-04

Indicates naturally occurring.

B38

2004 TABLE B-15 CONCENTRATIONS OF GAMMA EMITTERS IN FISH AND INVERTEBRATE SAMPLES (pCi/Kg, wet i 1 sigma)

25 Downstream (Hudson River)

(indicator)

Radionuclide AMER. EEL:

CATFISH CATFISH BLUE CRAB Be-7

<108.1

<184.7

<152.3

<217.9 K-40 4722+/-247.6 8590+/-487.3 6317+/-303.8 3879+/-334.1 Mn-54

<11.52

<22.37

<19.66

<17.52 Co-58

<11.62

<22.34

<21.59

<24.22 Fe-59

<36.09

<66.89

<42.98

<98.72 Co-60

<15.52

<27.26

<15.67

<18.15 Zn-65

<29.99

<57.39

<41.97

<43.88 Zr-95

<22.78

<43.95

<29.21

<53.25 Nb-95

<14.03

<29.59

<21.19

<33.31 Ru-103

<13.05

<21.27

<19.57

<36.83 Ru-106

<133.3

<281.3

<209.9

<189.4 1-131

<17.4

<45.21

<31.27

<1199 Cs-134

<7.98

<24.27

<18.59

<15.62 Cs-137

<13.22

<23.17

<18.67

<15 Ba/La-140

<22.28

<36.54

<24.6

<231 Ce-141

<15.69

<28.93

<30.63

<52.65 Ce-144

<59.2

<108

<109

<75.3 Ra-226 436.9+/-135.3 1972+/-351.9 861.7+/-280.5

<282.6 Ac-228

<48.37

<83.89 245.2+/-59.89

<49.05 DATE 17-Jun-04 17-Jun-04 17-Jun-04 5-Aug-04 Radionuclide WHITE PERCH.

-AMER. EEL WH. PERCH;-

-,AMER.-EEL Be-7

<252.5

<130.2

<339.1

<183.8 K40 4233+/-274.5 6190+/-279.4 9192+/-300.7 3977+/-320.9 Mn-54

<18.36

<16.52

<23.21

<16.81 Co-58

<21.83

<16.24

<34.2

<21.67 Fe-59

<112.7

<49.59

<122.9

<63.1 Co-60

<15.67

<17.39

<17.85

<22.6 Zn-65

<47.78

<38.93

<29.87

<43.14 Zr-95

<48.82

<27.48

<60.03

<49.64 Nb-95

<51.57

<18.88

<62.42

<33.19 Ru-103

<36.3

<15.55

<52.7

<27.39 Ru-106

<149.3

<173.4

<240.3

<206.6 1-131

<5096

<42.94

<4484

<423.3 Cs-134

<15.21

<9.35

<12.81

<19.42 Cs-137

<14.96

<14.93

<18.68

<19.02 Ba/La-140

<680.2

<30.62

<597.3

<76.94 Ce-141

<63.23

<14.91

<99.36

<41.76 Ce-144

<65.0

<71.0

<132

<82.5 Ra-226 942.7+/-216.5 1712+/-227.2 1697+/-322.4 609.6+/-248.1 Ac-228

<54.49 85.89+/-40.15 194.7+/-59.62

<62.25 DATE 15-Apr-04 10-Jun-04 20-Apr-04 17-Aug-04

Indicates naturally occurring.

B39

2004 TABLE B-15 CONCENTRATIONS OF GAMMA EMITTERS IN FISH AND INVERTEBRATE SAMPLES (pCi/Kg, wet +/- 1 sigma)

25 Downstream (Hudson River)

(indicator)

Radionuclide

-- CATFISH,.l;,'SUNFISH Be-7

<166

<220.5 K-40 4701+/-314.4 4465+/-336.1 Mn-54

<19.61

<17.74 Co-58

<20.82

<30.12 Fe-59

<76.26

<100.6 Co-60

<20.09

<18.19 Zn-65

<33.65

<47.54 Zr-95

<32.95

<49.04 Nb-95

<31.6

<42.37 Ru-103

<22.86

<34.79 Ru-106

<166.6

<189.3 1-131

<153.8

<1663 Cs-134

<18.57

<17.61 Cs-137

<16.27

<15.79 Ba/La-140

<46.58

<346.7 Ce-141

<33.21

<51.49 Ce-144

<77.9

<83.2 Ra-226

<256.3 876.5+/-229 Ac-228

<55.2

<47.52 DATE 25-Aug-04 1-Aug-04

Indicates naturally occurring.

B40

TABLE B.16 ANNUAL

SUMMARY

, NON-ODCM SAMPLE RESULTS 2004 SAMPLE MEDIUM NUCUDE (UNITS) -

DETECTED LLD INDICATOR LOCATIONS AVG. OF HIGHEST;J LOWEST:'.NO. OFp' TOTAL POSmVE POSITIVE. POSTITIVE. POSITIVE:NO. OF" SAMPLES: SAMPLE SAMPLE SAMPLES SAMPLES

-CONTROL LOCATIONS AVG.

F,.HIGHEST LOWEST.

NO. OF.`. TOTAL' POSITIVE POSITIVE POSITIVE*= POSITIVE NO. OF, SAMPLES SAMPLE SAMPLE -'SAMPLES-SAMPLES HISTORICAL AVG VALUE^

INDICATOR -'CONTROL?

AQUATIC VEGETATION (pCIkg - WET)

Co-60 NONE 1-131 100 Cs-134 100 Cs-137 100

-<ILe

< Ic

< IC

< Ic

< I

<C 21 211

< Ic in 0

5 0

5 2

5

<Lc

< Lc

< c 15.6 18.4 12.7

<Lc

<c

<L c 6.7 A67

<5.5 0

2 1

2 0

2 1

2 14.8 87

<Lc 29.7

< c 27.9

<Lc 73 A BOTTOM SEDIMENT (pCikg - DRY)

Co-60 NONE

<ILe

< L,

< L 0

6

< L.

< Lc 0

2 83.7

<Lc Cs-134 150

'ILe

' L

< Lc 0

6

<ILe

< Ic

< L, 0

2 47.8 44.7" Cs-137 180 567 1020 274 6

6

<~

<L.

< L.

0 2

598 86 SOIL (pCIkg - DRY)

Co-60 NONE

< L.

< Le.

< L 0

3

< L

< L.

< L, 0

1

< L

< I-Cs-134 150

<Ic L

<L

<Lc 0

3

<L.

< L,

<L, 0

1

<Ic,<c Cs-137 180 183 256 110 2

3

< Lc

< L 0

1 159 75.7 PRECIPITATION (pCUL)

H-3 2000

< L

< L,

< L 0

4

< L

< Lc

< L, 0

4 261 341 Co-60 15

< L

< Lc 0

4

<c

< Lc

< Lc 0

4

< Lc

< Lc Cs-134 15

< Lc

< Lc 0

4

<Ic

< Lc

< Lc 0

4

<IL

< Lc Cs-137 18

<Lc

< Lc

< Lc 0

4

< L.

< Lc

< Lc 0

4

<L.

< L SPECIAL WATER (PCi/L)

H-3 2000

<Lc

< Lc

< Ic 0

35 NA NA NA NA NA 167 NA Co-60 15

< Lc

< Lc 0

35 NA NA NA NA NA

< Lc

< Lc Cs-134 15

< Lc

< Lc 0

35 NA NA NA NA NA

< Lc

< Lc Cs-137 18

< Lc

< Lc 0

35 NA NA NA NA NA

< Lc

Average of positive values for 1993 - 2002

Detected at control location 1999. AND 2001.

NA - Data not available.

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

B-41

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

B-42

TABLE B-18 Table B-18 Land Use Census 2004 A comprehensive survey of the of the 5 mile (8 kilometer) area surrounding the Indian Point Site was conducted during the 2004 Spring, Summer and Fall months in accordance with the Indian ODCM Methodology:

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

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

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

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

Orange County was surveyed during through the summer and fall.

Rockland County was surveyed during summer and fall.

Putnam County was surveyed during the and summer and fall.

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

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

Results:

The 2004 land use census indicated there were new residences that were closer in proximity to IPEC.

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

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

B43

TABLE B-18 INDIAN POINT ENERGY CENTER UNRESTRICTED AREA BOUNDARY AND NEAREST RESIDENCES 2004 sector Compass Point Distance to site Distance to site Distance to Address of nearest resident, Dec Boundary from Boundary from nearest resident, 2004 Census Unit 2 Plant Vent Unit 3 Plant Vent from Unit I (in meters)

(in meters) superheater In meters I

N RIVER RIVER 1788.1 41 River Road Tomkins Cove 2

NNE RIVER RIVER 3111.3 Chateau Rive Apts. John St. Peekskill 3

NE 550 636 1907.3 122 Lower South St. Peekskill 4

ENE 600 775 1478.2 1018 Lower South St. Peekskill 5

B 662 785 1370.9 1103 Lower South St. Peekskill 6

ESE 569 622 715.2 461 Broadway Buchanan 7.

SE 553 564 1168.2 223 First St. Buchanan

8 SSE 569 551 1239.7 5 Pheasant's Run Buchanan

__-9:_,:

S 700 566 1132.5 320 Broadway Verplanck 10 SSW 755 480 1573.5 240 Eleventh St. Verplanck 11 SW 544 350 3015.9 29 Church St. Tomkins Cove E*12 WSW RIVER RIVER 2169.6 9 West Shore Dr. Tomkins Cove

'13 W

RIVER RIVER 1918.7 712 Rt. 9WTomkins Cove

'14 WNW RIVER RIVER 1752.4 770 Rt. 9W Tomkins Cove C:155 NW RIVER RIVER 1692.7 807 Rt. 9W Tomkins Cove 16 NNW RIVER RIVER 1609.3 4 River Rd. Tomkins Cove B44

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 2004 data with historical values. Although other samples were taken and analyzed, values were only tabulated and plotted where positive indications were present.

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

This bias can be seen in Table and Figure C-6 where the values reflected for 2004 are from a single sample of broadleaf vegetation that indicated Cs-1 37.

C-1

TABLE C-1 DIRECT RADIATION ANNUAL

SUMMARY

1994 - 2004 Ar Quarterly-.!

Dose (mQur)

-a-7 Yearn nnr i uter Rin-g Rzn7 Location-1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 14 15 14 15 14 15 14 15 15 14 14 15 14 15 15 15 15 16 17 16 18 16 16 16 15 17 15 14 14 15 2004 13 13 14 Historia4l Average l

1 15 16

-.,-1994-2004 t C-2

FIGURE C-1 DIRECT RADIATION 40 1994 to 2004 1 Inner Ring 35 El Outer Ring El Control Location 30 25 -

a 20 E

15 N

N 10 N'

5 1

0 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 C-3

TABLE C-2 RADIONUCLIDES IN AIR 1994 - 2004 (pCilm3) i

i

+

-. ;All ODCM All ODCM-

---. Year ;-

Indicator i; Cntrl C

odiatol Locations.

L ocation di-1-6 7

Loation 1-1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 0.02 0.01 0.01 0.01 0.02 0.02 0.01 0.02 0.02 0.01 0.01 0.01

<fi 0.01 0.01 0.01 0.01 0.01 0.02 0.02 0.01 2004 0.01 0.01

< L,

< LC H r Average 0.02 0.01

< LC

< KC 1994-2004 Critical Level (K) is less than the ODCM required LLD.

<Lc indicates no positive values above sample critical level.

C-4

FIGURE C-2 RADIONUCLIDES IN AIR - GROSS BETA 1994 to 2004 0.05 0.04 0.03 0

0.02 0.01 0.00 1994 1995 1996

Includes ODCM and non-ODCM indicator locations.

Gross Beta ODCM required LLD = 0.01 pCi/m3 1997 1998 1999 2000 2001 2002 2003 2004 C-5

TABLE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 1994 - 2004 (pCi/L)

',i;

,'Tritium" (H-3)-

C:s 37;

.-iYear Inl Discharge Inlet Discharge"<

1994 1995 230 370 280 270 1996 280

< Lc 1997 430 1998 220 1999 2000 191 190 318 267 323 562 2001 2002 432 2003 2004

< L, 553

< L,

< L, s

a 276 358

< LC L,

1994-2004 2638 K<

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

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

C-6

FIGURE C-3 HUDSON RIVER WATER - TRITIUM 1994 to 2004 2000 1800 1600 1400 -

1200 -

5 1000 800 600 400 200 0

1994 1995 Tritium ODCM required LLD = 3000 pCi/L 1996 1997 1998 1999 2000 2001 2002 2003 2004 C-7

TABLE C-4 RADIONUCLIDES IN DRINKING WATER 1994 -2004 (pCiIL)

Year

~~Tritkium(H-3) sI3 1994

< L

< K 1995

< K

<KL 1 996

< L,

<KL 1997

< L,

<KL 1998

< -C

< -C 1999

< -c

< K 2000

< K

<KL 2001

<KL

< L 2002

<KL

< K 2003

< LC

<KL 2004

<1L Historica! Av'erage

<K

<K 1 994-2004"'

Critical Level (K) is less than the 00CM required LLD.

<Kc indicates no positive values above sample critical level.

C-8

FIGURE C-4 DRINKING WATER - TRITIUM 1994 to 2004 2000 1800 1600 1400 -

1200

-J c

1000

£:L 800 600 -

400 -

200 0

as Camp Field Reservior (H-3)l U

M New Croton Resevoir (3)

NO IDENTIFIED TRITIUM IN PREVIOUS TEN YEAR HISTORY 1994 1995 Tritium ODCM required LLD = 2000 pCi/L 1996 1997 1998 1999 2000 2001 2002 2003 2004 C-9

TABLE C-5 RADIONUCLIDES IN SHORELINE SOIL 1994 - 2004 (pCi/Kg, dry)

CsA134 Cs-13

-Year K

Indicator

-Control Indicator Control 1994 485 1995 176 516 335 453 340 1996 173 1997

< Lc 203 1998 143 1999 2000 2001 2002 46 200 58 179 45 230 238 231 427 238 73

< Lc 221 2003 124 2004 Lc

< Lc 104 138 orical Average2 1920450

< -C 201 297 Critical Level (Lv) is less than the RETS required LLD.

<Lc indicates no positive values above sample critical level.

C-10

FIGURE C-5 RADIONUCLIDES IN SHORELINE SOIL 400A En 'nnA 1500 1400 E Indicator (Cs-1 34) 1300 El Control (Cs-1 34) 1200 E2 Indicator (Cs-1 37) 1100 El Control (Cs-1 37).

1000 900 o 800

,in

~

700 0.

600 500 400[

300 200-100-0 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 Cs-134 ODCM required LLD = 150 pCi/Kg, dry Cs-137 ODCM required LLD = 175 pCi/Kg, dry C-11

TABLE C-6 RADIONUCLIDES IN BROAD LEAF VEGETATION 1994 - 2004 (pCi/Kg, wet) yea Indictot oto 1994 22

< Lc 1995 28 1996 17 1997 1998 1999

' Lc 27 2000 28 2001 7

2002 14 16 2003 14 2004 10

< L, F Historical Average4i

.194-00 16 22

',.;1994-2004..;,i.i Critical Level (Lj) is less than the ODCM required LLD.

<Lc indicates no positive values above sample critical level.

C-12

FIGURE C-6 BROAD LEAF VEGETATION - Cs-137 1994 to 2004 100 -

0 Indicator (Cs-1 37)

El Control (Cs-1 37) 80 60 3

C-,a._

40 20 0 -

_ V 194 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 ODCM required LLD = 80 pCi/Kg, wet C-1 3

TABLE C-7 RADIONUCLIDES IN FISH AND INVERTEBRATES 1994 - 2004 i-.Cs-1';

.-- --. Year.--:.i.aI or C

ontrol 1 9' 4*i 1994'L:'c 1995 16 1996 1997 1998 1999 2000 2001 2002

< Lc

< Lc 2003

< L:

< LC 2004

< Lc

< LC Historical Average

'192004 1

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

<Lc indicates no positive values above sample critical level.

C-14

FIGURE C-7 FISH AND INVERTEBRATES - Cs-137 1994 to 2004 200 -

Ei Indicator (Cs-137)

El Control (Cs-1 37) 160 -

140 120 100 a-80 60 40 20 0

1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 Cs-137 ODCM required LLD = 150 pCi/Kg, wet C-1 5

APPENDIX D INTERLABORATORY COMPARISON PROGRAM

D.O QA/QC PROGRAM D.1 PROGRAM DESCRIPTION The Offsite Dose Calculation Manual (ODCM) requires that the licensee participate in an Interlaboratory Comparison Program.

The Interlaboratory Comparison Program shall include sample media for which samples are routinely collected and for which comparison samples are commercially available.

Participation in an Interlaboratory Comparison Program ensures that independent checks on the precision and accuracy of the measurement of radioactive material in the environmental samples are performed as part of the Quality Assurance Program for environmental monitoring.

To fulfill the requirement for an Interlaboratory Comparison Program, the JAF Environmental Laboratory has engaged the services of two independent laboratories to provide quality assurance comparison samples.

The two laboratories are Analytics, Incorporated in Atlanta, Georgia and the U.S.

Department of Energy's Environmental Measurements Laboratory (EML) in New York City.

Analytics supplies sample media as blind sample spikes, which contain certified levels of radioactivity unknown to the analysis laboratory.

These samples are prepared and analyzed using standard laboratory procedures. The results are submitted to Analytics, which issues a statistical summary report. The JAFNPP Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratory's performance for Analytic's sample results.

In addition to the Analytics Program, the JAF Environmental Laboratory 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.

In 2004, the program provided by Environmental Measurements Laboratory was scaled back as a result of the laboratory being reorganized under the Federal Department of Homeland Security as part of the Science and Technology directorate. Under the reorganization, the laboratory no longer provided spiked cross check samples to commercial laboratories. The JAF Environmental lab was eligible to participate in the first of two annual quality assessment programs (QAP-60) in 2004 before the program was restructured.

D-1

D.2 PROGRAM SCHEDULE SAMPLE LABORATOR SAPLE

-v.

MDIA PROVIDER:.

.EML, A

N ALYSIS ACS TOA.

Water Gross Beta 0

1 1

Water Tritium 1

1 2

Water 1-131 2

0 2

Water Mixed Gamma 2

1 3

Air Gross Beta 2

1 3

Air 1-131 2

0 2

Air Mixed Gamma 2

1 3

Milk I-131 2

0 2

Milk Mixed Gamma 2

0 2

Soil Mixed Gamma 1

0 1

Vegetation Mixed Gamma 1

0 1

TOTAL SAMPLE INVENTORY 17 5

22 D.3 ACCEPTANCE CRITERIA Each sample result is evaluated to determine the accuracy and precision of the laboratory's analysis result. The evaluation method for the QA sample results is dependent on the supplier of the sample. The sample evaluation methods are discussed below.

D.3.1 ANALYTICS SAMPLE RESULTS Samples provided by Analytics are evaluated using what is specified as the NRC method. This method is based on the calculation of the ratio of results reported by the participating laboratory (QC result) to the Vendor Laboratory Known value (reference result).

D-2

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

The value for the error resolution is calculated.

The error resolution =

Reference Result Reference Results Error Using the appropriate row under the Error Resolution column in Table D.3.1 below, a corresponding Ratio of Agreement interval is given.

The value for the ratio is then calculated.

Ratio of Agreement

=

OC Result Reference Result If the value falls within the agreement interval, the result is acceptable.

TABLE D.3.1

-- ERROR RESOLUTION - - +'-^ ¢ - RATIO OF AGREEME

<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

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 Warnin 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-lSth (10%) and 85th-95th percentiles (10%) are in the warning area. The Not Acceptable criteria, "N", is established at less than the 5th percentile and greater than the 95th percentile, that is, the outer 10% of the historical data. Using five years of historical analytical data, the EML, determined performance results using the percentile criteria summarized below:

Result Cumulative Normalized Distribution Acceptable ("A")

15% - 85%

Acceptable with Warning ("W")

5% - 15% or 85% - 95%

Not Acceptable ("N")

<5% or >95%

D.4 PROGRAM RESULTS

SUMMARY

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

D.4.1 ANALYTICS QA SAMPLES RESULTS Seventeen QA blind spike samples were analyzed as part of Analytics 2004 Interlaboratory Comparison Program. The following sample media were evaluated as part of the comparison program.

Air Charcoal Cartridge: 1-131 Air Particulate Filter: Mixed Gamma Emitters, Gross Beta Water: I-131, Mixed Gamma Emitters, Tritium Soil: Mixed Gamma Emitters Milk: I-131, Mixed Gamma Emitters Vegetation: Mixed Gamma Emitters The JAF Environmental Laboratory performed 81 individual analyses on the seventeen QA samples. Of the 81 analyses performed, 80 were in agreement using the NRC acceptance criteria for a 98.8% agreement ratio.

Sample non-conformities are discussed in Section D.4.l.1.

D4

DA.1.1 ANALYTICS SAMPLE NONCONFORMITIES Analytics Sample E4166-05, ZN-65 in Soil Nonconformity No. 2004-01 A spiked mixed gamma in soil sample supplied by Analytics, Inc., was analyzed in accordance with standard laboratory procedures. The sample contained a total of nine radionuclides for analysis. Nine of the nine radionuclides present were quantified. Eight of the nine radionuclides were quantified within the acceptable range. The mean result for Zn-65 was determined to be outside the QA Acceptance Criteria resulting in a sample nonconformity. The soil sample was analyzed five times using four different detectors with the mean Zn-65 result reported as 334 pCi/kg. The known result for the sample was 262 pCi/kg as determined by the supplier. One of the five reported results was 292 pCi/kg and resulted in an agreement when compared to the known of 262 pCi/kg with a ratio of 1.11. The remaining 4 individual results were outside the acceptance criteria and had ratios to the known value that ranged from 1.29 to 1.34. All of the analysis had relatively high associated counting errors, which ranged from 8.3% to 18.3%.

An evaluation of the Zn-65 result was performed. The spectrum and peak search results were examined with no anomalies identified. Zn-65 decays by electron capture with a 244 day half-life and a gamma ray energy of 1115 KeV with a yield of 50.75%. No significant secondary gamma energies are produced in the Zn-65 decay scheme. The average net count rates of the five analyses were low and ranged from a high of 1.50 counts per minute to a low of 0.93 counts per minute. The low activity in the sample resulted in high associated counting errors as noted above.

In soil samples, Ra-226 is a naturally occurring radionuclide, which produces a secondary peak at 1120 KeV. The presence of Ra-226 (1120 KeV) and Zn-65 (1115 KeV) in the sample resulted in a doublet peak formation in this region of the spectrum. In most cases, the computer algorithm can differentiate the two adjacent peaks and correct for interferences from overlapping (doublet) peaks.

In these sample spectrums, there was a low number of total counts in the 1110 to 1130 KeV area. The low count rate and subsequent poor peak shape made it difficult for the algorithm to select an exact background for determining the total counts in the peak. In addition, low count rate made it difficult to define the two peaks contained in the doublet.

In addition to the complicated nature of the spectrum, the settling of the soil media in the counting geometry may have effected the homogeneity of the sample and produced a positive bias in the collective sample results. 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 2004, eleven spiked samples were analyzed which contained certified concentrations of Zn-65 and other radionuclides.

This sample set included four additional soil samples.

D-5

The results are as follows:

2004 Zn-65 Results Sample D i

aF Muppl.ie I.

E-4053-05 Water pCi/liter 146+6 143+5 1.03 E-4319-05 Water pCi/liter 165+6 178+6 0.93 E-4054-05 Filter pCilfifter 98+/-5 95+3 1.03 E-4320-05 Filter pCi/filter 141+/-6 120+/-4 1.18 E-4321-05 Milk pCi/liter 155+7 167+6 0.93 E-4165-05 Milk pCi/liter 94+5 99+/-3 0.94 E-4168-05 Vegetation pCi/kg 260+/-17 232+/-8 1.12 E4154-09t Soil pCi/kg 289+20 26215 1.10 E-4051-09*

Soil pCi/kg 289+/-17 252+6 1.15 E-4253-09*

Soil pCi/kg 239+12 248+6 0.96 E-4373-09*

Soil pCi/kg 336+22 329+6 1.02 Mean Ratio 1.04 Provided by laboratory client, NOT reported in Annual Report t

Duplicate sample of E-4165-05 provided by laboratory client, NOT reported in Annual Report A duplicate sample of this sample (E-4166-05) was submitted to the laboratory as a blind spike (E-4154-09). This sample was made from the exact supplier stock as the non-conformity sample. The Zn-65 result for this duplicate sample was in full agreement with the known value on all five of the analysis performed. The mean Zn-65 result for the duplicate sample was 289+20 pCi/Kg for a ratio to the known value of 1.10 (See results in the table above). The mean ratio for all eleven Zn-65 results was 1.04. The mean ratio for the four soil sample Zn-65 results was 1.06.

The mean ratio value for the eleven samples noted above and each individual ratio values for each of Zn-65 results are excellent indicators that the routine measurement of Zn-65 in environmental media is 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-6

8.4.2 ENVIRONMENTAL MEASUREMENTS LABORATORY (ENIL)

In 2004, JAF Environmental Laboratory participated in both the EML Quality Assessment Programs, QAP-60. Sample sets consisted of the following sample media:

Water: Gross Beta, Mixed Gamma Emitters Water: Tritium Air Particulate Filter: Mixed Gamma Emitters/Gross Beta A total of 5 samples containing 8 individual radionuclides were evaluated for the samples included in QAP-58 and QAP-59. Using the EML acceptance criteria, 8 of 8 radionuclides analyses (100%) were evaluated to be acceptable. Results for the EML cross Check Program are contained in Table D-1 and results for all participants can be viewed on-line at www.eml.doe.gov. A summary of the JAF Environmental Laboratory results is as follows:

iMatrix ATotalAnalyses Acceptable:

0 c

Air 4

4 0

Water 4

4 0

Total 8

8 0

Percentage 100%

0.0%

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

D-7

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

.- AF NV RFERENCE'-

DATE

'ID NO.'.

'MEDIUM A

L SR UT LA RATIO (3) 6/17/2004 E-4164-05 AIR 159.8 i

3.1 pCi/filter GROSS 158.5 i

166.0 3

5.5 0.95 A

BETA 155.7

+/-

3.1 Mean=

158.0 +/-

1.8 12/9/2004 E-4376-05 AIR 223.2

+

2.1 pCi/filter GROSS 219.7

+/- 2.1 225.0 4

7.5 0.99 A

BETA 222.4

+/-

2.1 Mean = 221.8

+/-

1.2 (1) Results reported as activity +1 sigma.

(2) Results reported as activity +2 sigma.

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

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-8

TABLE D-1 INTERLABORATORY INTERCOMPARISON PROGRAM Tritium Analysis Water (pCi/liter)

FENV

.:-.FERE

-DATE-

-~

IDNO.¢ v

MEDIUM:

ANALYSIS JAF RESULT(I)

LAB* (2)

RATIO(3) 3/25/2004 E-4052-05 WATER 4681

+/-

171 pCi/liter 4699 i

170 H-3 4769

+/-

171 4700 300 1.00 A

M ean =

4699

+/-

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

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

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

e analyzed by JAF Environmental Laboratory D-9

TABLE D-I (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Iodine Analysis of Water, Air nnd Milk JAFENV REFERENCE DATE ID NO.:

MEDIUM

-ANALYSIS JAF RESULT(1 )

LAB*

')

RATIO (3).>

3/25/2004 E-4053-05 WATER 92.9 +/-

1.9 pCilitcr 1-131**

907 +/-

1.7 90.2

+

3.0 1.03 A

90.7

+/-

1.8 Mean=

92.6

+/-

1.0 6/17/2004 E-4167-05 AIR 83.8

+

5.6 pCi/cc 1-131 78.3

+/-

5.8 83.1 i

2.8 0.97 A

80.4

+/- 4.9 Mean=

80.8

+/-

3.1 6/17/2004 E-4165-05 MILK 53.0

+/-

1.7 pCi/liter 1-131**

55.4 9

2.2 58.2

+

1.9 0.95 A

56.9

+/-

2.0 Mean =

55.1

+/-

0.8 9/16/2004 E-4322-05 AIR 72.4

+/-

5.2 pCi/cc 1-131 75.0

+ 4.8 76.7

+

2.6 0.96 A

73.5 4.9 Mean =

73.6 +/- 2.9 9/16/2004 E-4319-05 WATER 69.7

+

1.1 pCi/liter 1-131**

67.2 1.2 70.8 1

2.4 0.98 A

71.7 1.0 Mean =

69.5

+ 0.6 9/16/2004 E-4321-05 MILK 74.1

+

1.2 pCi/liter 1-131**

72.7 4

1.1 83.5

+/-

2.8 0.89 A

75.1

+/-

1.3 Mean =

74.0

+/-

0.7 (1) Results reported as activity N sigma.

(2) Results reported as activity +2 sigma.

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

(*) Sample provided by Analytics, Inc.

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

(A) Evaluation Results, Acceptable.

D-10

TABLE D-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Water (pCi/liter)

'JAFENi 1

7 REFEEN DATE-IDNO.

MEDIUM ANALYSIS -

JAF RESULT(I)

LAB* (2).

RATIO (3) 3/25/2004 I E4053-05 WATER pCi/litcr Ce-141 81.5 86.2 89.0 80.4 Mean =

84.3

+

10.4

+

1.1 I

9.4

+

7.8

+

4.0 85.0

+

2.8 0.99 A

362.0

+

48.1 325.0

+

6.6 Cr-51 431.0

+

47.7 326.0

+

10.9 1.09 A

305.0

+

35.8 Mean = 355.8

+

19.2 83.3

+

1.4 Cs-134 85.9 4

7.0 89.7

+

3.0 0.94 A

84.5

+

5.7 Mean =

84.6 +

3.1 174.0

+

9.3 Cs-137 178.0

+

1.1 185.0

+

6.2 0.95 A

174.0

+

9.0 Mean = 175.3

+

4.3 116.0

+

7.9 116.0

+

1.0 Mn-54 116.0

+

7.8 114.0

+

3.8 1.02 A

115.0

+

5.9 Mean=

115.8

+

3.1 66.3

+/-

8.8 59.5

+

1.1 Fe-59 64.4

+

8.1 56.7

+

1.9 1.15 A

70.9

+

5.7 Mean=

65.3

+

3.3 161.0

+

15.2 149.0 +/-

1.7 Zn-65 124.0

+

14.5 143.0

+

4.8 1.03 A

151.0

+

10.8 Mean= 146.3

+

5.9 143.0

+

6.8 153.0

+

0.8 Co-60 145.0

+

6.6 153.0

+

5.1 0.97 A

153.0

+

5.0 Mean= 148.5

+

2.7 Co-58 Mean =

114.0 116.0 118.0 112.0 115.0

+

8.3

+

1.0

+

7.8

+

5.9

+

3.2 112.0

+

3.7 1.03 A

(1) Results reported as activity +1 sigma.

(2) Results reported as activity 42 sigma.

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

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-1l

TABLE D-1 (Continued)

INTERLABORATORY INTERCONIPARISON PROGRAM Gamma Analysis Water (pCi/liter)

D lEERENCEDl DAE'IN

______ANALYSIS' JAI ESL L`,AB* -(2)

RATI()

D AAEE' IIJAFRESULT l) 9/16/2004 l E-4319-05 WATER pCi/litcr Ce-141 251.0 257.0 255.0 Mean= 254.3 9.1 8.6 7.8 4.9 250.0

+/-

8.3 1.02 A

163.0

+

30.9 Cr-2090 31.8 223.0

+/-

7.5 0.81 A

Cr51173.0 30.4 Mean = 181.7 d

17.9 91.6

+

5.8 Cs-134 97 9.2 96.4

+/-

3.2 0.97 A

97.9

+/-

5.4 Mean =

93.2

+/-

4.1 217.0

+/-

7.2 Cs-137 206.0 +/-

6.8 215.0 +/-

7.2 0.98 A

206.0

+/-

6.6 Mean= 209.7

+/-

4.0 182.0

+/-

6.9 Mn-54 169.0

+/-

6.4 181.0 +/-

6.1 0.97 A

175.0

+/-

6.3 Mean = 175.3

+/-

3.8.

83.6

+

6.6 Fe-59 99.6

+/-

6.4 91.6

+/-

3.1 1.02 A

96.7

+/-

6.1 Mean=

93.3

+/-

3.7 178.0

+/-

11.4 Zn-65 1610

+/-

10.2 178.0 +/-

5.9 0.93 A

161.0

+/-

10.1 Mean = 165.0 +/-

6.1 117.0 +/-

4.4 Co-60 132.0 +/-

4.5 125.0

+/-

4.2 0.98 A

119.0

+/-

4.1 Mean =

122.7

+/-

2.5 Co-58 100.0 89.4 90.2 Mean =

93.2 5.6 5.2 5.0 3.1 94.6

+/-

3.2 0.99 A

(1) Results reported as activity l sigma.

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

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

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-12

TABLE D-1 (Continued)

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

I I -

T REFERENCE AFNANLSSj JAF RESULT (1).

LAB*

2 RATIO (3)'

3/25/2004 E-4054-05 FILTER pCi/filter Ce-141 51.1 52.8 57.2 Mean =

53.7

+/- 2.9

+/-

3.6

+

2.9

+/-

1.8 56.6

+

1.9 0.95 A

192.0

+

21.1 Cr-512140 25.4 217.0

+/- 7.2 0.92 A

194.0

+/-19.7 Mean = 200.0

+

12.8 55.0

+

4.1 Cs-134 52.4 5.0 59.7 4

2.0 0.88 A

50.3 4.0 Mean =

52.6

+

2.5 116.0

+/- 5.0 Cs-137 131.0 b 6.4 123.0 +/-

4.1 0.98 A

116.0 4.9 Mean = 121.0

+/- 3.1 79.2

+/- 4.6 Mn-54 77.4 0 5.5 75.8

+/-

2.5 1.02 A

76.0

+/- 4.3 Mean =

77.5

+/- 2.8 33.7

+/- 4.7 Fe-59 37.1

+/- 57 37.8

+/-

1.3 0.98 A

40.2

4.7 Mean =

37.0

2.9 87.7 i

8.6 Zn-65 109.0 7

.1 95.1

+/-

3.2 1.03 A

97.7

+/-8.3 Mean =

98.1

5.4 105.0 4.3 Co-60 95.7 5.0 102.0

+

3.4 0.96 A

91.3 4.0 M ean =

97.3 2.6 Co-58 78.3 71.6 71.9 Mean =

73.9

+/- 4.6

+/- 5.5

+/- 4.4

+/- 2.8 74.6

+

2.5 0.99 A

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

(2) Results reported as activity +2 sigma.

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

(*)

Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-13

TABLE D-l (Continued)

INTERLABORATORY INTERCOINPARISON PROGRAM Gamma Analysis of Air Particulate Filters (pCiffilter)

-JAFENV l

D N J

MREFERENCEJ

-!DATE ID NO."

MfEDIU M

.'ANALYSIS:-A RESULT (1).

jLAB~*.- (2)'-

-RATIO (3) 9/16/2004 l E-4320-05 FILTER pCi/filter Ce-141 183.0 195.0 173.0 Mean = 183.7 4

5.0

+

5.7

+/- 5.1

+/- 3.0 168.0

+

5.6 1.09 A

132.0

+

20.9 Cr-51 128.0 4

21.5 150.0

+ 5.0 0.89 A

142.0 21.7 Mean = 134.0

+ 12.3 60.4

+

8.4 Cs-134 74.8 5.3 64.9

+

2.2 1.08 A

76.0 4-4.8 Mean =

70.4

+ 3.7 148.0

+

5.7 Cs-137 155.0 6.2 145.0

+

4.8 1.04 A

149.0 5.3 Mean = 150.7

+ 3.3 154.0

+

6.0 Mn-54 143.0

+

6.0 122.0

+

4.1 1.18 A

135.0

+/-

5.3 Mean= 144.0

+/-

3.3 78.7 4

6.1 Fe-59 78.7

+

6.3 61.6

+

2.1 1.25 A

73.3

+

5.4 Mean =

76.9

+/-

3.4 144.0

+/-

10.4 Zn-65 145.0 9 1 120.0

+

4.0 1.18 A

135.0

+

9.1 Mean= 141.3

+/-

5.8 87.0

+

3.8 Co-60 73.7

+

3.9 84.3

+

2.8 0.96 A

82.3

+/-

3.5

_______Mean

=

81.0

+/-

2.1 Co-58 77.0 69.2 64.2 Mean =

70.1 I

4.8 I

4.9

+

4.2

+

2.7 63.7

+

2.1 1.10 A

(1) Results reported as activity PI sigma.

(2) Results reported as activity +2 sigma.

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

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-14

TABLE D-l (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Milk (pCi/liter)

D JAFENV J

I RERERNCE DATE ID NO.,

MEDM NALYSIS

_JAFRESULT (1)'

LRATIO

_3)_

6/17/2004 1 E-4165-05 MILK pCi/liter Ce-141 161.0 157.0 153.0 155.0 141.0 166.0 Mean=

155.5

+/-

6.1

+/-

11.1 7.6 i

10.9

+

6.4

+/-

8.2 3.5 157.0

+/-

5.2 0.99 A

274.0 30.6 143.0 47.8 239.0 31.3 Cr-51 228.0 44.0 228.0

+/-

7.6 0.95 A

225.0 28.6 195.0 37.9 Mean=

217.3 15.3 96.6 4.6 96.6 7.6 92.5 4.2 Cs-134 97.9

+/-

7.2 101.0

+

3.4 0.96 A

104.0

+/-

4.6 93.6 5.8 Mean =

96.9 4

2.4 147.0

+/-

5.5 134.0

+

8.8 147.0

+/-

5.5 Cs-137 141.0

+/-

8.3 156.0

+

5.2 0.92 A

151.0

+/-

5.4 139.0 4

6.4 Mean=

143.2 2.8 68.9 4.2 64.4 7.4 65.9 4.6 Mn-54 62.4 6.3 70.5 4

2.4 0.97 A

71.7 4.2 76.9

+/-

5.2 Mean 68.4

+/-

2.2 37.5

+/-

5.1 45.3 9.1 53.6 6.3 Fe-59 50.3 7.9 44.5 4

1.5 1.12 A

60.3

+/-

5.4 51.8 5.8 Mean =

49.8 2.8 113.0 8.9 76.5 14.0 95.4 9.4 Zn-65 88.2 13.5 99.3 4

3.3 0.94 A

90.6 8.5 99.2 10.3 Mean=

93.8 4

4.5 172.0 4.7 172.0

+/-

7.7 180.0

+/-

4.9 Co-60 160.0 4

7.1 172.0 +/-

5.7 1.00 A

175.0

+/-

4.7 175.0

+/-

5.3 Mean=

172.3 I

2.4 Co-58 45.2 38.4 40.7 45.3 40.9 49.8 Mean=

43.4 3.8 4

6.3

+

3.7 5.9 3.7

+/-

4.6

+

1.9 46.2 J

1.5 0.94 A

(1) Results reported as activity *I sigma.

(2) Results reported as activity +2 sigma.

(3) Ratio Reported'Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-15

TABLE D-I (Continued)

INTERLABORATORY INTERCOM PARISON PROGRAM Gamma Analysis Milk (pCilliter) 1 AfENV 1REFERENC DAE D N'j MEDIUM JANALYI j

JAF RESULT ()

.LAB*t (2)'RAI(3 9/16/2004 I E-4321-05 MILK pCi/liter Ce-141 226.0 220.0 230.0 Mean = 225.3

+/-8.5

+/- 9.1

+/-

8.6

+/- 5.0 235.0

+

7.8 0.96 A

256.0

+

35.5 Cr-51212i0

+ 37 210.0 4

7.0 0.97 A

145.0

+

37.0 Mean = 204.3

+/-

20.3 84.0

+

9.5 Cs-134 81.4

+

9.6 90.6 4

3.0 0.89 A

75.7

+/-

11.2 Mean =

80.4

+/-

5.9 193.0

+/-

6.6 Cs-137 188.0

+/-

6.8 202.0

+/-

6.7 0.92 A

179.0 +/-

7.9 Mean= 186.7 +/-

4.1 180.0

+/-

6.5 Mn-54 185.0 +/- 6.9 171.0

+/- 5.7 1.04 A

169.0

+/- 7.9 Mean= 178.0

+/- 4.1 90.6 4

6.4 Fc-59 92.6

+/-

7.2 86.1

+/-

2.9 1.09 A

97.5

+/-

8.6 Mean =

93.6 +/- 4.3 173.0

+/-

11.4 Zn-65 150.0

+/-

11.4 167.0 +/- 5.6 0.93 A

143.0

i 13.3 Mean = 155.3

+/-

7.0 108.0

+/- 4.2 Co-60 116.0

+

4.5 118.0

+

3.9 0.98 A

122.0

+

5.5 Mean =

115.3

+/-

2.8 Co-58 83.7 88.4 81.5 Mean =

84.5

+/-

5.2

+/-

5.7

+

6.3

+/-

3.3 89.0

+/- 3.0 0.95 A

(1) Results reported as activity*ll sigma.

(2) Results reported as activity *2 sigma.

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

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-16

TABLE D-l (Continued)

INTERLABORATORY INTERCONIPARISON PROGRAM Gamma Analysis Soil (pCi/gram)

_.-JAFENV -

A RF

-DATE-ID NO.-;

MEDIUM

M ANALYSIS JAF RESULT (I)

LAB*

RATIO (3)'

6/17/2004 l E-4166-05 SOIL pCi/gram Ce-141 0.378 0.493 0.503 0.467 0.414 Mean =

0.451 0.034 0.025

+/-

0.043

+/-

0.022

+/-

0.032 i

0.015 0.413

+/-

0.014 1.09 A

0.502 0.162 0.617 4

0.110 Cr-51 0.825

+/-

0.110 0.601 b 0.020 1.20 A

0.932

+/-

0.183 Mean =

0.719 +/-

0.054 0.302 +/-

0.028 0.244 +/-

0.032 Cs-134 0.370 +/-

0.033 0.267 +/- 0.009 1.11 A

0.279 0.262 Mean=

0.296

0.012 0.568 0.034 0.525 0.022 Cs-137 0.534

+/-

0.020 0.516

+/- 0.017 1.02 A 0.518 +/-

0.032 Mean=

0.525 +/-

0.012 0.227 +/-

0.025 0.215 +/-

0.016 Mn-54 0.178 +/-

0.032 0.186 4

0.006 1.08 A 0.183

+/-

0.024 Mean=

0.201

+/-

0.011 0.149

+/-

0.049 0.129 +/-

0.031 Fe-59 0.120 +/-

0.026 0.117

+ 0.004 1.08 A

0.101

+/-

0.037 Mean=

0.126 +/-

0.013 0.342 +/-

0.044 0.292 +/-

0.029 Zn-65 0.338 +/-

0.062 0.262

+ 0.009 1.27 D

0.348

+/-

0.029 0.352 +/-

0.046 NC #2004-Mean=

0.334

0.019 1

0.539 +/-

0.026 0.461 a

0.017 Co-60 0.466 A 0.031 0.453

+

0.015 1.08 A

0.500 +/-

0.025 Mean 0.488 X 0.011 Co-58 0.127 +/-

0.140 +/-

0.112

+/-

0.112

+/-

0.079 +/-

Mean=

0.114 +/-

0.022 0.016 0.028 0.014 0.022 0.009 0.122

+ 0.004 0.93 A

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

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

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

(*)

Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

(D) Evaluation Results, Not Acceptable (NC) Non Conformity number D-17

TABLE D-l (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Vegetation (pCi/gram)

JAFENV l JI.EFEENCE C-DATE

- ID NO.

MEDIUM -

ANALYSIS JAF RESULT (I)

LAB* (2)

R (3) 6/17/2004 I E-4168-05 VEGETATION pCi/gram Cc-141 0.371 L

0.370 +/-

0.346 +

0.330 :

Mean=

0.354 +

0.010 0.022 0.025 0.020 0.010 0.365

+

0.012 0.97 A

0.478 +

0.054 0.511 +

0.011 Cr-51 0.670 +

0.013 0.531

+

0.018 1.07 A

0.617 +

0.010 Mean =

0.569 +/-

0.051 0.234 -

0.007 0.256 h

0.020 Cs-134 0.278 +

0.025 0.235

+

0.008 1.07 A

0.238 +

0.019 Mean 0.252 X

0.010 0.353 +

0.008 0.381 f

0.022 Cs-137 0.340 A 0.025 0.363

+

0.012 1.01 A

0.388 X 0.021 Mean=

0.366 +

0.010 0.179 +

0.006 0.200 +

0.018 Mn-54 0.154 4 0.023 0.164 i

0.005 1.07 A

0.170 X 0.017 Mean=

0.176 +

0.009 0.085 0.010 0.108 +

0.025 Fe-59 0.140 +

0.028 0.104

+/- 0.003 1.06 A

0.107 +

0.022 Mean 0.110 +

0.011 0.251 +

0.014 0.300 +

0.039 Zn-65 0.240 +

0.047 0.232

+

0.008 1.12 A

0.249 +

0.031 Mean=

0.260 A 0.017 0.405 +/-

0.007 0.390 +/-

0.019 Co-60 0.409 +/-

0.025 0.400

+/- 0.013 1.01 A

0.412 +/-

0.019 Mean =

0.404 +/-

0.010 Co-58 0.106 +

0.114 +/-

0.121 b

0.101 +/-

Mean=

0.111 +/-

0.006 0.016 0.022 0.016 0.008 0.108

+

0.004 1 1.03 A

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

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

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

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

D-18

TABLE D-l (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Water (Bq/liter)

JAFENV'

REFERENCE:

DATE

-AID NO.-

- MEDIUM

ANALYSIS, JAF RESULT (I)

-LAB*

RATIO (3);

3/1/2004 QAP-60 WATER 52.5

+

2.9 Bq/liter 47.4

+ 2.7 Cs-137 50.0 2 2.8 52.0

+

2.7 0.972 A 52.2

+/- 3.4 50.7

+

2.6 Mean=

50.5

+

1.3 156.1 4

3.7 161.3 4

3.9 Co-60 159.5

+/- 3.8 163.2

+

5.9 0.975 A

159.5

+/- 4.7 159.5

+/- 3.7 Mean= 159.2

+/-

1.8 (1) Results reported as activity 1 sigma.

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

(3) Ratio = Reported/EML(Sec Section 8.3).

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

(A) Evaluation Results, Acceptable.

D-19

TABLE D-I (Continued)

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

JAF ENV.'

REFERENCE.

-DATE

-ID NO.'

MEDIUM ANALYSIS JAF RESULT (1) -

LAB*

(2)

'RATIO (3)M 3/1/2004 QAP-60 FILTER 35.0

+/- 0.5 Bq/filtcr Co-60 36.1

+/-

0.5 35.4

+/- 0.85 1.006 A

35.6

+/-

0.4 Mean =

35.6 +/-

0.3 19.4 I

0.4 Cs-134 20.8

+/- 0.4 18.2 +/-

0.40 1.104 W

20.2

+/-

0.4 Mean =

20.1 E 0.2 27.9 +/- 0.5 Cs-137 28.0 i 035 26.4

+/- 0.86 1.057 A

27.8

+/-

0.4

____M ean =

27.9

+/-

0.3 (1) Results reported as activityid sigma.

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

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

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

(A) Evaluation Results, Acceptable.

(W) Acceptable with Warning.

D-20

TABLE D-l (Continued)

INTERLABORATORY INTERCOMNPARISON PROGRAM Gross Beta Analysis of Water (Bqlliter)

AF EN i

7

.REFERENC

'l' DATE ID NO.'

MEDIUM

-"'ANALYSIS

'JAF RESULT (-)

LAB*

(2)

RATIO (3) 3/1/2004 QAP-60 WATER GROSS 1109

+

30 Bq/liter BETA 1115

+ 30 1170

+

117 0.944 A

1090 +/- 30 Mean=

1105

+/-

17 (1) Results reported as activity PI sigma.

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

(3) Ratio = Rcported/EML (See Section 8.3).

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

(A) Evaluation Results, Acceptable.

D-21

TABLE D-I (Continued)

INTERLABORATORY INTERCONIPARISON PROGRAM Tritium Analysis Water (Bq/liter)

JAFEN REFERENCE DATE ID NO MEDIUM :-

ANALYSIS JAF RESULT (1)

, LAB* (2)

RATIO (3) 3/1/2004 QAP-60 WATER H-3 233.4

+ 7.8 Bq/liter 224.9

+

7.8 238.3

+

8.0 186.6

+

3.3 1.25 A

232.0

+

7.9 235.3

+/- 8.0 Mean = 232.8

+/- 3.5 (1) Results reported as activity +/-I sigma.

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

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

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

(A) Evaluation Results, Acceptable.

D-22

TABLE D-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air (Bq/filter)

JAF ENV REFERENCE,

DATE.

ID NO.'.

MEDIUM ANALYSIS JAF RESULT (1)

LAB* (2)

RATIO (3) 3/1/2004 QAP-60 AIR GROSS 2.8 +/- 0.08 Bq/filter BETA 2.6 7 0.08 2.7 +/- 0.08 2.6

+/- 0.08 2.85 i

0.28 0.94 A

2.6 +/- 0.08 2.7 +/-

0.08

______M ean'=

2.7

+/-

0.05 (1) Results reported as activity l sigma.

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

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

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

(A) Evaluation Results, Acceptable.

D-23

D.5 REFERENCES D.5.1 Semi-Annual Report of the Department of Energy, Office of Environmental Management, Quality Assessment Program, EML 621, June 2004.

D.5.2 Radioactivity and Radiochemistry, The Counting Room: Special Edition, 1994 Caretaker Publications, Atlanta, Georgia.

D.5.3 Data Reduction and Error Analysis for the Physical Sciences, Bevington P.R., McGraw Hill, New York (1969).3 D-24

NL-05-0051, Annual Radiological Environmental Operating Report

Contents

Text

Subject:

Enclosure:

SUMMARY

2.0 INTRODUCTION

6.0 REFERENCES

SUMMARY

SUMMARY

SUMMARY

2.0 INTRODUCTION

6.0 REFERENCES

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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NL-05-0051, Annual Radiological Environmental Operating Report

Text

Subject:

Enclosure:

SUMMARY

2.0 INTRODUCTION

6.0 REFERENCES

SUMMARY

SUMMARY

SUMMARY

2.0 INTRODUCTION

6.0 REFERENCES

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

REFERENCE:

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