NL-14-068, 2013 Annual Radiological Environmental Operating Report

2013 Annual Radiological Environmental Operating Report

ML14142A031
Person / Time
Site:	Indian Point
Issue date:	05/09/2014
From:	Robert Walpole Entergy Nuclear Northeast
To:	Document Control Desk, NRC/FSME, Office of Nuclear Reactor Regulation
References
NL-14-068
Download: ML14142A031 (133)

Text

Enteray Nuclear Northeast Indian Point Energy Center

ý-Entergy 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 254-6710 Robert Walpole Licensing Manager NL-14-068 May 9, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852

SUBJECT:

2013 Annual Radiological Environmental Operating Report Indian Point Unit Nos. 1, 2 and 3 Docket Nos. 50-03, 50-247, 50-286 License Nos. DPR-5, DPR-26, DPR-64

Dear Sir or Madam:

Enclosed please find one copy of the Entergy Nuclear Operations, Inc. (Entergy) Indian Point Energy Center (IPEC) Annual Radiological Environmental Operating Report for the period January 1, 2013 to December 31, 2013.

This report is submitted in accordance with facility Technical Specification Appendix A section 6 of the provisional operating license for DPR-5 and section 5.6.2 for DPR-26, and DPR-64, Indian Point Unit Nos. 1, 2 and 3 respectively. There are no commitments being made by this report.

Should you or your staff have any questions, please contact Mr. Frank Mitchell, Radiation Protection Manager at 914-254-5236.

Sincerely, RW/ai cc: next page 7:jz:ýd'5 , I-V 0

1ý3pt-.'C7 -

NL-14-068 Docket Nos. 50-03, 50-247, 50-286 Page 2 of 2

Enclosure:

1. 2013 Annual Radiological Environmental Operating Report cc: Mr. William Dean, Regional Administrator, NRC Region 1 Mr. Douglas Pickett, Senior Project Manager, NRC NRR DORL IPEC NRC Resident Inspector's Office Mr. Stephen Giebel, IPEC NRC Unit 1 Project Manager Mr. John B. Rhodes, President and CEO, NYSERDA Ms. Bridget Frymire, New York State Department of Public Service Mr. Timothy Rice, Bureau of Hazardous Waste & Radiation Mgmt, NYSDEC

ENCLOSURE 1 TO NL-14-068 2013 Annual Radiological Environmental Operating Report 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 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, 2013

TABLE OF CONTENTS Page EXECUTIVE

SUMMARY

vii

1.0 INTRODUCTION

1-1 1.1 Overview 1-1

2.0 BACKGROUND

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 3-1 3.3.3 Precipitation 3-2 3.3.4 Drinking Water 3-2 3.3.5 Ground Water 3-2 3.3.6 Soil 3-2 3.3.7 Broad Leaf Vegetation 3-2 3.3.8 Hudson River Water 3-2 3.3.9 Hudson River Bottom Sediment 3-3 3.3.10 Hudson River Shoreline Soil 3-3 3.3.11 Hudson River Aquatic Vegetation 3-3 3.3.12 Fish and Invertebrates 3-3 3.3.13 Land Use Census 3-3 3.4 Statistical Methodology 3-4 3.4.1 Lower Limit of Detection and MDC 3-4 3.4.2 Table Statistics 3-5

TABLE OF CONTENTS (continued)

Page 4.0 RESULTS AND DISCUSSION 4-1 4.1 Direct Radiation 4-3 4.2 Airborne Particulates and Radioiodine 4-4 4.3 Precipitation 4-4 4.4 Drinking Water 4-4 4.5 Ground Water 4-5 4.6 Soil 4-5 4.7 Broad Leaf Vegetation 4-5 4.8 Hudson River Water 4-5 4.9 Hudson River Bottom Sediment 4-5 4.10 Hudson River Shoreline Soil 4-6 4.11 Hudson River Aquatic Vegetation 4-6 4.12 Fish and Invertebrates 4-6 4.13 Land Use Census 4-7 4.14 Conclusion 4-7

5.0 REFERENCES

and BIBLIOGRAPHY 5-1 APPENDICES:

A. ENVIRONMENTAL SAMPLING AND ANALYSIS REQUIREMENTS A-1 B. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM B-1 RESULTS

SUMMARY

C. HISTORICAL TRENDS C-1 D. INTERLABORATORY COMPARISON PROGRAM D-1

" Teledyne Environmental Laboratory

• TLD Dosimeter Testing ii

LIST OF FIGURES FIGURE TITLE Page A-1 Sampling Locations (Within Two Miles) A-5 A-2 Sampling Locations (Greater Than Two Miles) A-6 A-3 Additional Sampling Locations A-7 C-1 Direct Radiation, Annual Summary, 2003 to 2013 C-3 C-2 Radionuclides in Air - Gross Beta, 2003 to 2013 C-5 C-3 Radionuclides in Hudson River Water, Inlet & Discharge C-7 2003 to 2013 C-4 Radionuclides in Drinking Water, Tritium & Cs-1 37 C-9 2003 to 2013 C-5 Radionuclides in Shoreline Soil, 2003 to 2013 C-1i1 C-6 Broad Leaf Vegetation - Cs-137, 2003 to 2013 C-13 C-7 Radionuclides in Fish & Invertebrates, Cs-137, C-15 2003 to 2013 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-10 B-1 Sampling Summary, 2013 B-2 B-1 a 2013 Air Sampling Deviations B-3 B-lb 2013 Other Media Deviations B-3 B-Ic Analysis Deviations B-3 B-2 Radiological Environmental Monitoring Program Summary Indian Point Energy Center - 2013 B-4 B-3 Direct Radiation, Quarterly Data - 2013 B-13 B-4 Direct Radiation, 2003 through 2013 Data B-15 B-5 Direct Radiation, Inner and Outer Rings - 2013 B-17 B-6 Gross Beta Activity in Airborne Particulate Samples-2013 B-18 B-7 Iodine-1 31 in Airborne Charcoal Samples - 2013 B-20 B-8 Gamma Emitters in Airborne Particulate Samples- 2013 B-22 B-9 Radionuclides in Rain Water Samples - 2013 B-26 B-10 Radionuclides in Drinking Water Samples - 2013 B-27 B-11 Radionuclides in Ground Water Samples - 2013 B-31 B-12 Gamma Emitters in Soil Samples - 2013 B-32 B-13 Gamma Emitters in Broad Leaf Vegetation Samples - 2013 B-33 B-14 Radionuclides in River Water Samples - 2013 B-42 B-15 Gamma Emitters in Bottom Sediment Samples - 2013 B-46 B-16 Radionuclides in Shoreline Soil Samples- 2013 B-47 B-17 Gamma Emitters in Aquatic Vegetation Samples - 2013 B-49 B-18 Radionuclides in Fish / Invertebrates - 2013 B-50 B-19 Land Use Census, Residence & Milch Animal Results 2013 B-54 B-20 Land Use Census - 2013 - Unrestricted Area Boundary and Nearest Residences B-55 iv

LIST OF TABLES (Continued)

TABLE TITLE Page C-1 Direct Radiation Annual Summary, 2003 - 2013 C-2 C-2 Radionuclides in Air, 2003 - 2013 0-4 C-3 Radionuclides in Hudson River Water, Inlet & Discharge 0-6 2003 to 2013 0-4 Radionuclides in Drinking Water, Tritium & Cs-137 C-8 2003 to 2013 C-5 Radionuclides in Shoreline Soil, 2003 to 2013 0-10 C-6 Broad Leaf Vegetation - Cs-1 37, 2003 to 2013 C-12 C-7 Radionuclides in Fish & Invertebrates, Cs-137, 0-14 2003 to 2013 C-8 River Water Discharge Area Tritium, REMP vs Effluent 0-16 D-2.1 Ratio of Agreement D-2 D-3.1 Analytics Interlaboratory Comparison Program D-3 and Ratio of Agreement D-3.2 DOE Interlaboratory Comparison Program D-6 and Ratio of Agreement D-3.3 ERA Interlaboratory Comparison Program D-8 and Ratio of Agreement D-4.1 Percent of Individual Dosimeters That Passed EDO D-9 Internal Criteria, 2013 D-4.2 Mean Dosimeter Analysis (N=6), 2013 D-10 D-4.3 Summary of Independent Dosimeter Testing, 2013 D-10 v

EXECUTIVE

SUMMARY

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EXECUTIVE

SUMMARY

INTRODUCTION This report summarizes the results of the Radiological Environmental Monitoring Program (REMP) conducted in the vicinity of Indian Point Energy Center (IPEC) during the period from January 1 to December 31, 2013. The Indian Point site consists of Units 1, 2 and 3, which are operated by Entergy Nuclear Operations Inc. Unit 1 was retired as a generating facility in 1974, and its reactor is no longer operated.

The REMP has been established to monitor/measure the radiation and radioactivity detectable in the environment that may be attributable to the operation of IPEC. This program, initiated in 1958, includes the collection, analysis, and evaluation of radiological data in order to assess the impact of IPEC on the environment.

SAMPLING AND ANALYSIS The environmental sampling media collected in the vicinity of IPEC and at distant locations included air particulate filters and charcoal cartridges, soil, drinking water, ground water, broadleaf vegetation, river water, precipitation, shoreline sediment, bottom sediment, aquatic vegetation, fish, and invertebrates.

During 2013, there were 1015 samples collected from the atmospheric, aquatic, and terrestrial environments. In addition, 164 exposure measurements were obtained using environmental thermoluminescent dosimeters (TLDs).

A small number of inadvertent issues were encountered in 2013 in the collection of environmental samples in accordance with the IPEC Offsite Dose Calculation Manual (ODCM). Equipment failures and electrical outages resulted in a small number of instances in which lower than normal sampling volumes were collected at the airborne monitoring stations. A full description of all discrepancies encountered with the environmental monitoring program is presented in the Table B-1 of this report.

There were 1444 analyses performed on the environmental media samples. The analysis of the 2013 Indian Point environmental samples was performed by several laboratories.

General Engineering Labs (GEL) of Charlestown, SC, performed the ground water analyses.

Thermoluminescent dosimeters were analyzed by Environmental Dosimetry Company (formerly Stanford Associates) of Sterling, MA. Teledyne Brown Engineering, Inc. of Knoxville, TN performed all the remaining analyses for 2013. Samples were analyzed as required by the IPEC ODCM.

LAND USE CENSUS The annual land use census in the vicinity of IPEC was conducted as required by the IPEC ODCM in May through October. No dairy animals within 5 miles of the Station were located during the census. Due to the difficulty of locating individual gardens and determining those having an area greater than 500 square feet, broadleaf sampling was performed. As allowed for in the ODCM, monthly broad leaf sampling may be used in lieu of a garden census.

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SUMMARY

OF RESULTS Most samples collected as part of the IPEC REMP continued to contain detectable amounts of naturally-occurring and man-made radioactive materials. There was no plant related activity detected in any of the terrestrial samples. Offsite ambient radiation measurements using environmental TLDs beyond the site boundary ranged between 42 and 64 milli-Roentgens (mR) per year. The range of ambient radiation levels observed with the TLDs is consistent with natural background radiation levels for New York.

Monitoring of the aquatic environment in the area of the discharge indicated the presence of the following station related radionuclides: Tritium, Cs-137, and Sr-90. These station related nuclide were only found downstream from and in the mixing zone of the discharge at levels that were expected from routine plant operation. No other plant related activity was detected in any offsite samples. The predominant radioactivity for all samples was from non-plant related sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides.

CONCLUSIONS The 2013 Radiological Environmental Monitoring Program for IPEC resulted in the collection and analysis of over a thousand environmental samples and measurements. The data obtained were used to determine the impact of IPEC's operation on the environment and on the general public.

An evaluation of direct radiation measurements, environmental sample analyses, and dose calculations demonstrates that all applicable federal criteria were met. Furthermore, radiation levels and resulting doses from station operation were a small fraction of those attributed to natural and man-made background radiation.

In summary, the levels of radionuclides in the environment surrounding Indian Point were within the historical ranges, i.e., previous levels resulting from natural and anthropogenic sources for the detected radionuclides. Further, IPEC operations in 2013 did not result in exposure to the public greater than environmental background levels.

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SECTION

1.0 INTRODUCTION

1.1 Overview The Radiological Environmental Monitoring Program (REMP) for 2013 performed by Entergy for the Indian Point Energy Center (IPEC) is discussed in this report. Since the operation of a nuclear power plant results in the release of small amounts of radioactivity and low levels of radiation, the Nuclear Regulatory Commission (NRC) requires a program to be established to monitor radiation and radioactivity in the environment (Reference 1). This report, which is submitted to the NRC annually per Indian Point Technical Specifications, summarizes the results of measurements of radiation and radioactivity in the environment in the vicinity of the IPEC and at distant locations during the period January 1 to December 31, 2013.

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 and liquid material that might be released from the plant, cosmic radiation, and the naturally occurring radioactive materials in the ground. Analysis of thermoluminescent dosimeters (TLDs), used to measure direct radiation, indicated that there were no increased radiation levels attributable to plant operations.

The airborne pathway includes measurements of air, precipitation, drinking water, and broad leaf vegetation samples. The airborne pathway measurements indicated that there was no adverse radiological impact to the surrounding environment attributed to Indian Point Station operations.

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

The ground water table is listed after the rain water and drinking water tables for ease of data comparison. However, ground water is not a dose pathway since it is not a drinking water pathway at IPEC.

These results are reviewed by IPEC's staff and have been reported semiannually or annually to the Nuclear Regulatory Commission and others for over 30 years.

This report contains a description of the REMP for IPEC and the conduct of that program in 2013 as required by the IPEC ODCM. Also included are summaries and discussions of the results of the 2013 program, trend analyses (where appropriate), comparison to historical results and trend analyses (where appropriate) and evaluation of any potential impact on the environment. Results of the annual land use census, as well as the inter-laboratory comparison program are included, per the ODAs requirements.

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SECTION 2 BACKGROUND

2.0 BACKGROUND

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 began operation in 1962 and was retired as a generating facility in 1974. Units 2 and 3 began operation 1974 and 1978. Indian Point Units 1 and 2 are owned by Entergy Nuclear Indian Point 2, LLC and Unit 3 is owned by Entergy Nuclear Indian Point 3 LLC. All three units are operated by Entergy Nuclear, although only Units 2 and 3 continue to operate.

2.2 Program Background Environmental monitoring and surveillance have been conducted at Indian Point since 1958, 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 atmospheric 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.

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

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

The REMP designates sampling locations for the collection of environmental media for analysis. These sample locations are divided into indicator and control locations.

Indicator locations are established near the site, where the presence of environmental radioactivity of plant origin is most likely to be detected. Control locations are established farther away (and upwind/upstream, where applicable) from the site, where the level would not generally be affected by plant discharges. The use of indicator and control 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 objective of the REMP, which is met by meeting the two primary program objective described above. Verifying projected concentrations through the REMP is difficult since the environmental concentrations resulting from plant releases are typically too small to be detected. Plant related radionuclides were detected in 2013 in very low levels; however, residual radioactivity from atmospheric weapons tests and naturally occurring radioactivity were the predominant sources of radioactivity in the samples collected. Analysis of the 2013 REMP sample results confirms that radiological effluents were well below regulatory limits.

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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-1 and described in section 3.3.

3.1 Sample Collection Entergy personnel perform collection of environmental samples for the Indian Point site, with the exception of groundwater and fish/invertebrate samples. The groundwater samples are collected by a contracted environmental vendor, GZA Geo Environmental, Inc. Collection of fish and invertebrate samples is performed by a contracted environmental vendor -

Normandeau Associates, Inc.

3.2 Sample Analysis The analysis of the 2013 Indian Point environmental samples was performed by several laboratories. General Engineering Labs (GEL) of Charlestown, SC, performed the ground water analyses. Thermoluminescent dosimeters were analyzed by Environmental Dosimetry Company (formerly Stanford Associates) of Sterling, MA. Teledyne Brown Engineering, Inc. of Knoxville, TN performed all the remaining analyses.

3.3 Sample Collection and Analysis Methodology 3.3.1 Direct Radiation Direct gamma radiation is measured using integrating calcium sulfate thermoluminescent dosimeters (TLDs), which provide cumulative measurements of radiation exposure (i.e., total integrated exposures in milli-roentgen, 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. Additional TLD locations include a control location at Roseton (20.7 miles north) and eight locations of special interest. In total, there are 41 TLD sample sites, designated DR-1 through DR-41, with two TLDs placed at each site. TLDs are collected and processed on a quarterly basis. The results are reported as mR per standard quarter (91 days). The data reported is the average of the two TLDs from each sample site.

3.3.2 Airborne Particulates and Radioiodine Air samples were taken at eight locations varying in distance from 0.28 to 20.7 miles (0.4 to 33 km) from the plant. These locations represent one control at sampling station 23 (A5) and seven indicator locations. These indicator locations are at sampling stations 4 (Al), 5 (A4), 27, 29, 44, 94 (A2), and 95 (A3). The locations are shown on Figures A-i, A-2, and A-

3. The air samples are collected continuously by means of fixed air particulate filters followed by in-line charcoal cartridges. Both filters and cartridges are changed on a weekly basis. The filters are analyzed for gross beta and the cartridge samples for radioiodine. In addition, gamma spectroscopy analysis (GSA) is performed on quarterly composites of the air particulate filters.

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3.3.3 Precipitation Precipitation samples are continuously collected at one indicator location (sampling station

44) and one control location (23); see Figure A-3. They are collected in sample bottles designed to hinder evaporation. They are composited quarterly and analyzed by gamma spectroscopy and for tritium.

3.3.4 Drinking Water Samples of drinking water are collected monthly from the Camp Field Reservoir (3.4 miles NE, sample station 7, sample designation Wbl) and New Croton Reservoir (6.3 miles SE, sample station 8); see Figure A-3. Each monthly sample is approximately 4 liters and is analyzed for gross beta and gamma-emitting radionuclides. Monthly samples are composited quarterly and analyzed for tritium.

3.3.5 Groundwater Water Groundwater samples are obtained semi-annually at Lafarge (106.) Samples are analyzed for tritium, strontium-90, and nickel-63 and by gamma spectroscopy.

3.3.6 Soil Soil samples are collected from two indicator locations (sampling stations 94 and 95), and one control location (23) on an annual basis; see Figure A-3. They are approximately 2 kg in size and consist of.about twenty 2-inch deep cores. The soil samples are analyzed by gamma spectroscopy.

3.3.7 Broad Leaf Vegetation Broad leaf vegetation samples are collected from three locations during the growing season.

The indicator locations are sampling stations 94 (Ic2) and 95 (Icl), and the control location is at sampling station 23 (Ic3). See Figures A-1 and A-2. The samples are collected monthly, when available, and analyzed by gamma spectroscopy. These samples consist of at least 1 kg of leafy vegetation and are used in the assessment of the food product and milk ingestion pathways.

3.3.8 Hudson River Water Hudson River water sampling is performed continuously at the intake structure (sampling station 9, Wal) and at a point exterior to the discharge canal where Hudson River water and water from the discharge canal mix (sampling station 10, Wa2); see Figure A-1. An automatic composite sampler is used to take representative samples. On a weekly basis, accumulated samples are taken from both sample points. These weekly river water samples are composited for monthly gamma spectroscopy analysis and quarterly for tritium analysis.

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3.3.9 Hudson River Bottom Sediment Bottom sediment and benthos are sampled at four locations: three indicator locations (sampling stations 10, 17, and 28) and one control location (84), along the Hudson River, once each spring and summer; see Figure A-3. These samples are obtained using a Peterson grab sampler or similar instrument. The bottom sediment samples are analyzed by gamma spectroscopy.

3.3.10 Hudson River Shoreline Soil Shoreline soil samples are collected at three indicator and two control locations along the Hudson River. The indicator locations are at sampling stations 53 (Wcl), 28, and 17. The control locations are at sampling stations 50 (Wc2) and 84. Figures A-i, A-2, and A-3 show these locations. The samples are gathered at a level above low tide and below high tide and are approximately 2-kg grab samples. These samples are collected at greater than 90 days apart and are analyzed by gamma spectroscopy and for strontium-90.

3.3.11 Hudson River Aquatic Veqetation During the spring and summer, aquatic vegetation samples are collected from the Hudson River at two indicator locations (sampling stations 17 and 28) and one control location (84);

see Figure A-3. Samples of aquatic vegetation are obtained depending on sample availability. These samples are analyzed by gamma spectroscopy.

3.3.12 Fish and Invertebrates Fish and invertebrate samples are obtained from the Hudson River at locations upstream and downstream of the plant discharge. The indicator location (downstream sample point) is designated as sampling station 25 (Ibl), and a second sampling point is located further downstream. The control location (upstream) is at sampling station 23 (Ib2). See Figures A-1 and A-2. These samples are collected in season or semiannually ifthey are not seasonal.

The fish and invertebrates sampled are analyzed by gamma spectroscopy as well as for strontium-90 and for nickel-63.

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

For example, the milch animal census is used to identify animals producing milk for human consumption within 5 miles (8 km) of Indian Point. This census consists of visual field surveys of the areas where a high probability of milch animals exists and confirmation through New York State records or with personnel such as feed suppliers who deal with farm animals and dairy associations (See Tables B-21 and B-22).

Visual inspections are 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. An extensive land survey is conducted of the 5-mile area in an attempt to identify new residential areas, commercial developments and to identify milch animals in pasture.

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Although there are presently no animals producing milk for human consumption within 5 miles (8 km) of the site, the census is performed to determine if a milk-sampling program needs to be conducted.

A residence census is also performed to identify the nearest residence(s) to the site in each of the 16 sectors surrounding Indian Point. See Table B-22.

A garden census was not performed, since the ODCM allows sampling of vegetation in two sectors near the site boundary in lieu of a garden census. The sectors are chosen to be in the pre-dominant wind directions with the highest predicted deposition rates.

3.4 Statistical Methodology There are several statistical calculation methodologies used in evaluating the data from the Indian Point REMP. These methods include determination of Lower Limits of Detection (LLD) and the Minimum Detectable Concentration (MDC), and estimation of the mean and associated propagated error.

3.4.1 LOWER LIMIT OF DETECTION (LLD)

The LLD is the smallest concentration of radioactive material in a sample that will yield a net count above system background, and be detected with 95% probability, with a 5%

probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

2. 71 +/-+3.29sh* ]+(T6-)

LLD= T-,

E

• V

• k

• Y*e-Where:

LLD = The lower limit of detection as defined above (as picocurie per unit mass or volume)

Ts = The sample counting time in minutes Sb = The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

Tb = The background count time in minutes E= The counting efficiency (as counts per transformation)

V= The sample size (in units of mass or volume) k = A constant for the number of transformations per minute per unit of activity (normally, 2.22E+6 dpm per uCi)

Y= The fractional radiochemical yield (when applicable)

A= The radioactive decay constant for the particular radionuclide t= The elapsed time between midpoint of sample collection and time of counting 3-4

Note: The above LLD formula accounts for differing background and sample count times.

The Radiological Environmental Monitoring Program, REMP, may use an LLD formula that assumes equal background and sample count times, when appropriate.

The constants 2.71 and 3.29 and the general LLD equation were derived from References 2 and 3.

The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.

In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and t shall be used in the calculation. The background count rate is calculated from the background counts that are determined by a separate background count or in the case of gamma ray spectroscopy, from adjacent channels of the energy band of the gamma ray peak used for the quantitative analysis for that radionuclide.

It should be recognized that 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. To document the post priori (after the fact) measurement statistics, the MDC is calculated after the measurement using the same equation as above.

To handle the a posteriori problem, a decision level must be defined. To minimize the number of false positives, a value is not considered positive unless it is greater than the MDC or 3 times the total standard deviation of the post priori measurement, where MDC is the post priori (after the fact) measurement statistic calculated similar to the LLD equation listed above (for Tb = T,, the term 3.29 O'b [(1 + ( Tb /Tr ))112] = 4.66 Ob).

3.4.2 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 4). 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.

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 2003 through 2013. The 2013 average values are included in these historic tables for purposes of comparison.

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SECTION 4 RESULTS AND DISCUSSION

4.0 RESULTS AND DISCUSSION The 2013 Radiological Environmental Monitoring Program (REMP) was conducted in accordance with Indian Point's Offsite Dose Calculation Manual ODCM. The ODCM contains requirements for the number and distribution of sampling locations, the types of samples to be collected, and the types of analyses to be performed for measurement of radioactivity.

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

Direct Gamma Radiation Airborne Particulates and Radioiodine Precipitation Drinking Water Groundwater Soil Broad Leaf Vegetation Hudson River Water Bottom Sediment Shoreline Soil Aquatic Vegetation Fish and Invertebrates 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 2013 and assessed the significance of the findings.

A summary of the results of the 2013 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 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, and 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.

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The second group of radionuclides detected in 2013 consists of those resulting from past weapons testing in the earth's atmosphere. The more recent contamination events resulting from the Chernobyl and Fukushima accidents only indicated detectable activity shortly after their occurrences (Reference 5). However, weapons testing in the 1950's and 1960's resulted in a significant atmospheric radionuclide inventory, which, in turn, still contributes to the concentrations in the ecological systems. Although reduced in frequency, atmospheric weapons testing continued into the 1980's. The resultant radionuclide inventory of some radionuclides, although diminishing with time (e.g., through radioactive decay and natural dispersion processes), remains detectable.

In 2013, the detected radionuclide that may be attributable to past atmospheric weapons testing consisted of Cs-137 in several 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 by the 2013 REMP comprises those that may be attributable to current plant operations. During 2013, Cs-137, H-3 (Tritium), and Sr-90 were the only potentially plant-related radionuclides detected in any environmental samples.

H-3 may be present in the local environment due to either natural occurrence, other man-made sources, or as a result of plant operations. Natural occurrence is very low (on the order of approximately 5 pCi/liter - well below typical detectable levels). The major source of H-3 is typically from above ground nuclear weapons testing, in the range of 50 to 150 pCi/liter). Other sources include weapons production and industrial uses where levels are highly dependent on the release rates and distance from the source term. One such industrial source is nuclear power plant operation.

Cs-137 is ubiquitous in the environment from atmospheric testing debris and a lesser amount from the Chernobyl accident. In 2013, there were two detections of Cs-137 in shoreline soil (2 indicator samples). In bottom sediment there were five positive detections of Cs-137 (all at indicator stations or near the plant). The two discharge canal samples are consistent with historical values.

Shoreline sediment and bottom sediment samples showed detectable levels of Cs-137 somewhat higher at the indicator locations than at the control location at Cold Spring (distant location). The fact that there was no Cs-1 34 present (recent plant releases would contain Cs-134) and that there was detection also at a distant location indicates that the activity may be due to atmospheric weapons testing, with some contribution from plant releases from the past several years. None of the fish samples indicated any detectable levels of these isotopes.

Strontium-90 (Sr-90) may also be present in the environment from atmospheric testing debris. None of the fish samples, or any other media (except for blue crab) where Sr-90 was tested, indicated any detectable levels of this isotope. However, very low levels of Sr-90 were detected in one indicator and one control location sample of blue crab.

1-131 is also produced in fission reactors, but can result from non-plant related anthropogenic sources, e.g., medical administrations, such as in previous years. 1-131 was not detected in 2013 in aquatic or terrestrial vegetation indicator and control locations.

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. Co-58 has a much shorter half-life than Co-60. If Co-58 and Co-60 are concurrently detected in environmental samples, then the source of these radionuclides is more likely the result of 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 2013 REMP, although they were observed in historical data.

In the following sections, a summary of the results of the 2012 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 Environmental Dosimetry Company. In 2013, the TLD program produced a consistent picture of ambient background radiation levels in the vicinity of the Indian Point Station. A summary of the annual TLD data is provided in Table B-2 and all the TLD data are presented in Tables B-3, B-4 and B-5. TLD sample site DR-40 is the control site for the direct radiation (DR) series of measurements.

Table B-3 provides the quarterly and annual average reported doses in mR per standard quarter for each of the direct radiation sample points, DR-1 through DR-41. The table also provides the sector for each of the DR sample points. Table B-4 provides the mean, standard deviation, minimum and maximum values in mR per standard quarter for the years 2003 through 2013. The 2013 means are also presented in Table B-4. Table B-5 presents the 2013 TLD data for the inner ring and outer ring of TLDs.

The 2013 mean value for the indicator direct radiation sample points was 13.7 mR per standard quarter - which is consistent with historical values. At those locations where the 2013 mean value was higher than historical means, they are within historical bounds for the respective locations.

The DR sample locations are arranged so that there are two concentric rings of TLDs around the Indian Point site. The inner ring (DR-1 to DR-16) is close to the site boundary.

The outer ring (DR-17 to DR-32) has a radius of approximately 5 miles from the three Indian Point units. The results for these two rings of TLDs are provided in Table B-5. The annual average for the inner ring was 13.2 mR per standard quarter and also average for the outer ring was 14.1 mR per standard quarter. The control location average for 2013 was 12.5 mR per standard quarter.

Table C-1 and Figure C-1 present the 10-year historical averages for the inner and outer rings of TLDs. The 2013 averages are consistent with the historical data. The 2013 and previous years' data show that there is no measurable direct radiation in the environment due to the operation of the Indian Point site.

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4.2 Airborne Particulates and Radioiodine An annual summary of the results of the 2012 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 weekly charcoal cartridge analytical results are presented in Table B-7.

Gross beta activity was found in air particulate samples throughout the year at all indicator and control locations. The average gross beta activity for the eight indicator air sample locations was 0.014 pCi/m 3 and the average for the control location was 0.014 pCi/m 3. The activities detected were consistent for all locations, with no significant differences in gross beta activity in any sample due to location. All the charcoal cartridge results were less than MDC, consistent with historical trends when there were no episodes of fresh fallout from Weapons Testing or accidents.

The results of the GSA of the quarterly composites of these samples are in Table B-8.

These quarterly composite air samples showed that no reactor-related radionuclides were detected and that only naturally-occurring radionuclides were present at detectable levels.

The mean annual gross beta concentrations and Cs-137 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 2013 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.

From the data, it can be seen that no airborne radioactivity attributable to the operation of Indian Point was detected in 2013.

4.3 Precipitation A summary of the precipitation sample analysis results is presented in Table B-2. Table B-9 contains the results of the precipitation samples for 2013. Only naturally occurring radionuclides were detected in the precipitation samples.

A review of historical data over the last 10 years indicates tritium had been detected in one indicator precipitation sample in 2010 and both indicator and control locations in 2010; however, there have been no instances of positive values in 2013.

4.4 Drinking Water The annual program summary table (Table B-2) contains a summary of the 2013 drinking water sample analysis results. Results of the tritium and gamma spectroscopy analyses of the monthly drinking water samples are in Table B-10. Other than naturally occurring radionuclides, no radioactivity was detected in drinking water samples. This has historically been the case for the radionuclide results for this media. Operation of the Indian Point units had no detectable radiological impact on drinking water.

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4.5 Ground Water A summary of the groundwater samples for 2013 is contained in Table B-2. Data resulting from analysis of the groundwater samples for gamma emitters, tritium analysis, Ni-63 and Sr-90 are given in Table B-1 1. No plant related nuclides were noted in these samples.

4.6 Soil A summary of the soil sample analysis results is presented in Table B-2. Table B-12 contains the results of the soil samples for 2013. Other than naturally occurring radionuclides, no activity was detected in any of the soil samples.

4.7 Broad Leaf Vegetation Table B-2 contains a summary of the broad leaf vegetation sample analysis results. Data from analysis of the 2013 samples are presented in Table B-13.

Table C-3 contains an historical summary and Figure C-3 is an illustration of the broad leaf vegetation analysis results. There were no plant related nuclides detected in the 2013 samples. The detection of low levels of Cs-137 has occurred sporadically at both indicator and control locations at relatively low concentrations for the past ten years, most likely the result of previous atmospheric weapons testing.

4.8 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 quarterly composites of H-3 are presented in Tables B-14.

The only plant related activity detected was H-3, and it was detected at low levels in indicator and control samples. The levels are consistent with occasional historical detection of H-3. Table C-3 shows historical H-3 concentrations at the plant inlet and discharge points. Table C-8 contains a comparison of H-3 detected at the plant discharge (Hudson River Water mixing point) versus quarterly average effluents concentrations. Table C-8 provides assurance that the REMP is indeed providing verification of the calculation of radionuclide concentrations resulting from effluent releases attributable to the site.

4.9 Hudson River Bottom Sediment A summary of the Hudson River bottom sediment analysis results is included in Table B-2.

Table B-15 contains the results of the analysis of bottom sediment samples for 2013. Cs-137 was detected in all 10 indicator station samples, and 2 of 3 control location samples.

Detection of positive levels of Cs-137 in river bottom sediment is not unusual. Cs-134 was not detected in any bottom sediment samples. The lack of Cs-134 points to the primary source of the Cs-137 in bottom sediment as being from prior historical plant releases over the years and from residual weapons test fallout.

The discharge canal bottom sediment sample results were higher than the levels seen in recent years. The average concentration was 2738 pCi/kg, and the range was 153-13870 pCi/kg.

The levels observed during 2013 sampling are within the range of levels identified in historical samples. Given the significant movement of silt and sediment observed in the river during the 2013 hurricane season it is likely that deeper sediment material 4-5

was redistributed and re-deposited during the storm events. The elevated sediment concentrations are most likely the result of the observed higher sediment in the river.

Additionally the effluents from Indian Point in particular for Cs-137 continue to remain at very low concentrations in particular when compared to historical effluent releases where river sediment concentrations were at the higher end of the historical range.

4.10 Hudson River Shoreline Soil A summary of the radionuclide concentrations detected in the shoreline soil samples is contained in Table B-2. Table B-16 contains the results of the gamma spectroscopic and strontium-90 analyses of the shoreline soil samples.

In addition to the naturally occurring radionuclides, Cs-137 was identified in the Hudson River shoreline soil samples in 2013. Cs-137 was detected at the Verplank location in both samples from that location, for a total of two positive values out of eight samples from indicator locations. Cs-137 was not detected at the control location (Manitou Inlet). The average concentration for the indicator locations that had positive indication of Cs-137 was 133 pCi/kg (dry) with a maximum concentration of 158 pCi/kg (dry).

An historical look at Cs-137 detected in shoreline soil at indicator and control locations can be viewed in Table C-6 and Figure C-6. Cs-137 has been and continues to be present in this media, both at indicator and occasionally at the control location, at a consistent level over the past ten years. Cs-134 and Cs-137 are both discharged from the plant in similar quantities. The lack of Cs-134 activity is an indication that the primary source of the Cs-137 in the shoreline soil is legacy contamination from weapons fallout.

No Sr-90 was detected in any collected shoreline soil samples.

4.11 Aquatic Vegetation A summary of the aquatic sample analysis results is presented in Table B-2. Table B-17 contains the results of the analysis of aquatic vegetation samples for 2013. No plant related radionuclides were detected.

4.12 Fish and Invertebrates A summary of the fish and invertebrate sample analysis results is presented in Table B-2.

Table B-18 contains the results of the analysis of fish and invertebrate samples for 2013 The only plant related nuclide detected was Sr-90, which was detected at very low levels in one sample each of blue crab from both the control (4.1 pCi/kg) and indicator locations (6.1 pCi/kg). This was attributed to the presence of notable amounts of shell pieces in those samples. In addition, these values are well within the range of those identified by NYSDEC in their study of Sr-90 in fish and invertebrate in the lower Hudson River, reported in 2009.

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4.13 Land Use Census A census was performed in the vicinity of Indian Point in 2013. This census consisted of a milch animal and a residence census. Results of this census are presented in Tables B-21 and B-22.

The results of the 2013 census were generally same as the 2012 census results, with one exception. In August 2013, the presence of goats was noted on a property located 3.5 - 4 miles NNE of IPEC. However, discussions with the owner confirmed that the goats were all male and therefore not milch animals.

The second part of this census revealed that the two nearest residences in different sectors are located 0.44 miles (0.71 km) ESE and 0.73 miles (1.13 km) S of the plant. The 2013 land use census indicated there were no new residences that were closer in proximity to IPEC.

The ODCM allows the sampling of broad leaf vegetation in two sectors at the site boundary in lieu of performing a garden census. Analysis results for these two sectors are discussed in Section 4.6 and presented in Table B-14, Table C-6 and Figure C-6.

4.14 Conclusion The Radiological Environmental Monitoring Program is conducted each year to determine the radiological impact of Indian Point operations on the environment. The preceding discussions of the results of the 2013 REMP reveal that operations at the station did not result in an impact on the environment.

The 2013 REMP results demonstrate the relative contributions of different radionuclide sources, both natural and anthropogenic, to the environmental concentrations. The results indicate that the fallout from previous atmospheric weapons testing continues to contribute to detection of Cs-137 in some environmental samples. There are infrequent detections of plant related radionuclides in the environs; however, the radiological levels are very low and are significantly less than those from natural background and other anthropogenic sources.

4-7

SECTION 5 REFERENCES AND BIBLIOGRAPHY

5.1 REFERENCES

1. United States of America, Code of Federal Regulations, Title 10, Part 50, Appendix A Criteria 64.

2. Currie, L.A., "Limits for Qualitative Detection of Quantitative Determination",

Analytical Chemistry, 40:586-593, 1968.

3. Mayer, Dauer, "Application of Systematic Error Bounds to Detection Limits for Practical Counting"., Health Physics Journal, 65(1): 89-91, 1993.

4. U.S. Nuclear Regulatory Commission, Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.

5. Wetherbee, Gregory A., et.al., Wet Deposition of Fission-Product Isotopes to North America from the Fukushima Dai-ichi Incident, March 2012, Environmental Science and Technology.

5.2 BIBLIOGRAPHY

1. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977.

2. IPEC Offsite Dose Calculation Manual, Units 1, 2 and 3.

3. United States of America, Code of Federal Regulations, Title 10, Part 20.1301.

4. United States of America, Code of Federal Regulations, Title 10, Part 50, Appendix I.

5. United States of America, Code of Federal Regulations, Title 40, Part 190.

6. U.S. Nuclear Regulatory Commission, Regulatory Guide 4.1, "Program for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975.

7. International Commission of Radiological Protection, Publication No. 43, "Principles of Monitoring for the Radiation Protection of the Population," May 1984.

8. U.S. Nuclear Regulatory Commission, Regulatory Guide 4.1, Radiological Environmental Monitoring for Nuclear Power Plants, Revision 2, June 2009.

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

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

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

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

5-1

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

14.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.

15.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.

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

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

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

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

20. Kelly, J. J. (Ed.), Effluent and Environmental Radiation Surveillance, ASTM STP

1. 698, Philadelphia, PA, 1978.

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

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

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

1969.

24. 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.

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

26. Kuhn, W.,et al., The Influence of Soil Parameters on Cs-1 37 Uptake by Plants from Long-Term Fallout on Forest Clearings and Grasslands, Health Physics Journal, 46(5), p. 1083, May 1984.

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

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

5-2

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

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

31I.Office of Environmental Management, Semi-Annual Report of the Department of Energy, Quality Assessment Program, EML 617, June 2003.

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

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

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

35. ENN-LI-102, Corrective Action Process 36.Technical Information Document 2003-011 "Justification for the Removal of the Radiological Environmental Monitoring Blind Spike Program at IPEC"

37. National Council on Radiation Protection and Measurements, Report No. 169, "Design of Effective Radiological Effluent Monitoring and Environmental Surveillance Programs", December 2010.

38. Donald T. Oakley, "Natural Radiation Exposure in the United States." U. S.

Environmental Protection Agency, ORP/SID 72-1, June 1972.

39.National Council on Radiation Protection and Measurements, Report No. 160, "Ionizing Radiation Exposures of the Population of the United States," March 2009.

40.National Council on Radiation Protection and Measurements, Report No. 94, "Exposure of the Population of the United States and Canada from Natural Background Radiation," December 1987.

41.U.S. Nuclear Regulatory Commission, Regulatory Guide 8.29, "Instructions Concerning Risks from Occupational Radiation Exposure," Revision 0, July 1981.

42.U.S. Nuclear Regulatory Commission, NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors," April 1991.

43.NYS Department of Environmental Conservation, "Measurement of Strontium and Other Radionuclides in Edible Tissue and Bone/carapace of Fish and Blue Crabs from the Lower Hudson River, New York", November 2009.

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APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS REQUIREMENTS

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

Table A-1 provides the sampling station number, location, sector, and distance from Indian Point, sample designation code, and sample type. This table gives the complete listing of sample locations used in the 2013 REMP.

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

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

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

In addition to the sampling outlined in Table A-i, there is an environmental surveillance requirement that an annual land use and milch animal census be performed. See Tables B-19 and B-20 for the milch animal and land use census.

A-1

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING SATIN SAMPLE SATION LOCATION DISTANCE SAMPLE TYPES STATION DESIGNATION 3 DR8 Service Center Building Onsite - Direct Gamma 0.35 Mi (SSE) at 1580 Al Algonquin Gas Line Onsite - 0.28 Mi (SW) at Air Particulate Al 2340 Radioiodine A4 Air Particulate 5 A4 NYU Tower Onsite - 0.88 Mi (SSW) Radioiodine at 208' DR10 Direct Gamma 7 Wbl Camp Field Reservoir 3.4 Mi (NE) at 510 Drinking Water 8 Croton Reservoir 6.3 Mi (SE) at 1240 Drinking Water 9 ~~~Onsite - H ae Wal Plant Inlet (Hudson River Intake)* 0.16 Mi (W) at 273Water Wa2 Onsite - HR Water 10 W2 Discharge Canal (Mixing Zone) nie-HWar

• • 0.3 Mi (WSW) at 2490 HR Bottom Sediment 14 DR7 Water Meter House OnsiteDirect Gamma 0.3 Mi (SE) at 1330

• • HR Aquatic Vegetation 17 ** Off Verplanck 1.5 Mi (SSW) at 202.50 HR Shoreline Soil

• • HR Bottom Sediment Cortlandt Yacht Club 20 DR38 (AKA Montrose Marina) 1.5 Mi (5) at 1800 Direct Gamma

• • Precipitation A5 Air Particulate, A5 Radioiodine 23 DR40 Roseton* 20.7 Mi (N) at 3570 Direct Gamma Ic3 Broad Leaf Vegetation

• • Soil Ib2 Fish & Invertebrates 25 Ibl Downstream Downstream Fish & Invertebrates

• • Air Particulate 27 ** Croton Point 6.36 Mi (SSE) at 1560 Radioiodine DR41 Direct Gamma

• • HR Shoreline Soil DR4 Direct Gamma 28 Lent's Cove 0.45 Mi (ENE) at 0690

• • HR Bottom Sediment

• • HR Aquatic Vegetation

• • Air Particulate 29 ** Grassy Point 3.37 Mi (SSW) at 1960 Radioiodine DR39 Direct Gamma

• = Control location

• • = Locations listed do not have sample designation locations specified in the ODCM HR = Hudson River R/S = Reuter Stokes A-2

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING SATIN SAMPLE SATION LOCATION DISTANCE SAMPLE TYPES STATION DESIGNATION 33 DR33 Hamilton Street (Substation) 2.88 Mi (NE) at 053* Direct Gamma 34 DR9 South East Corner of Site OnsiteDirect Gamma 0.52 Mi (S) at 179D 35 DR5 Broadway & Bleakley Avenue Onsite - Direct Gamma 0.37 Mi (E) at 0920 iet am 38 DR34 Furnace Dock (Substation) 3.43 Mi (SE) at 141 Direct Gamma

• • Precipitation 44 ** Peekskill Gas Holder Bldg 1.84 Mi (NE) at 0520 Air Particulate

• • Radioiodine 50 Wc2 Manitou Inlet* 4.48 Mi (NNW) at 3470 HR Shoreline Soil Wcl HR Shoreline Soil 53 White Beach 0.92 Mi (SW) at 2260 DR11 Direct Gamma 56 DR37 Verplanck - Broadway & 6th 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 Road 61 DR36 Lower South Street & Franklin Street 1.3 Mi (NE) at 052' Direct Gamma 62 DR19 Westbrook Drive 62____DR19___ (near the Community Center) 5.03 Mi (NE) at 0620 Direct Gamma 64 DR20 Lincoln Road - Cortlandt 4.6 Mi (ENE) at 0670 Direct Gamma (School Parking Lot) 66 DR21 Croton Avenue - Cortlandt 4.87 Mi (E) at 0830 Direct Gamma 67 DR22 Colabaugh Pond Road - Cortlandt 4.5 Mi (ESE) at 114' Direct Gamma 69 DR23 Mt. Airy & Windsor Road 4.97 Mi (SE) at 127' Direct Gamma 71 DR25 Warren Ave - Haverstraw 4.83 Mi (S) at 1880 Direct Gamma 72 DR26 Railroad Avenue & 9W - Haverstraw 4.53 Mi (SSW) at 2030 Direct Gamma 73 DR27 Willow Grove Road & Captain 4.97 Mi (SW) at 2260 Direct Gamma Faldermeyer Drive 74 DR12 West Shore Drive - South 1.59 Mi (WSW) at 2520 Direct Gamma 75 DR31 Palisades Parkway 4.65 Mi (NW) at 2250 Direct Gamma 76 DR13 West Shore Drive - North 1.21 Mi (W) at 2760 Direct Gamma 77 DR29 Palisades Parkway 4.15 Mi (W) at 2720 Direct Gamma 78 DR14 Rt. 9W across from R/S #14 1.2 Mi (WNW) at 2950 Direct Gamma 79 DR30 Anthony Wayne Park 4.57 Mi (WNW) at 296' Direct Gamma

• = Control location

• • = Locations listed do not have sample designation locations specified in the ODCM HR = Hudson River R/S = Reuter Stokes A-3

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING SATIN SAMPLE SATION LOCATION DISTANCE SAMPLE TYPES STATION DESIGNATION 80 DR15 Route 9W South of Ayers Road 1.02 Mi (NW) at 3170 Direct Gamma 81 Palisades Pkwy - Lake Welch Exit 4.96 Mi (WSW) at 310° Direct Gamma 82 DR16 Ayers Road 1.01 Mi (NNW) at 3340 Direct Gamma 83 DR32 Route 9W - Fort Montgomery 4.82 Mi (NNW) at 3390 Direct Gamma

• • HR Aquatic Vegetation 84 Cold Spring

• 10.88 Mi (N) at 3560 HR Shoreline Soil

• • HR Bottom Sediment 88 DR6 Reuter Stokes 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

__9___DR______ (near rock cut) 2_89_Mi_(NNE)_at_025° Direct__amma 90 DR3 Charles Point 0.88 Mi (NE) at 0470 Direct Gamma 92 DR24 Warren Road - Cortlandt 3.84 Mi (SSE) at 1490 Direct Gamma A2 Air Particulate A2 IPEC Training Center Onsite- 0.39 Mi (S) at Radioiodine 94 Ic2 1930 Broad Leaf Vegetation

• • Soil A3 Air Particulate A3 Meteorological Tower Onsite - Radioiodine Icl 0.46 Mi (SSW) at 2080 Broad Leaf Vegetation

• • Soil 106 Lafarge Monitoring Well 0.63 mi SW Groundwater 107 Vicinity of Haverstraw Bay 2.5(dowSSW Fish & Invertebrates

_________ __________________________(downstream)

__________ Fs netbae 0 = Control location

• • = Locations listed do not have sample designation locations specified in the ODCM HR = Hudson River R/S = Reuter Stokes A-4

FIGURE A-1 SAMPLING LOCATIONS Within Two Miles of Indian Point I mile I I Fish am-]vertebrates I #(whereavd be) downstrim Hudson River F Aiborne

]# Ioditne/Par~t SAmple Location

,Oirect Radiation, Sam~ple Location~ DkI#

A-5

FIGURE A-2 SAMPLING LOCATIONS Greater than Two Miles from Indian Point Lake v t OKOt 4 Yo&Wn F3e ~M ir W Artiaw 1iocklatid Wc*

w e r) 9',ia *,

COUPoin f *P9f Mo trose f

'Broadleaf Vegetation Sample stor~y Locati n 6

• Direct Radiation cfolon (7r 'dscr Sample Location hdV&~5 W Westchester

- - #107 Coonty 5 miles I I Soil Fish and hivert (where availablehoiikw

5 51r,

ý()9 ~~happ.

r,,,*tNm UlaRon Ri er A-6 j

FIGURE A-3 SAMPLING LOCATIONS Additional Sampling Locations fI* _

I--84 "/,'ý <4 m. f I a-Cold Sprinf, 10.9 miles north I P utn am.;

Counti ke Valley, htr

'eek P!eek J1r i Yorktown aw,,

Corilandt uidian Manor

>oint106: GW 5 Mile, itro7e 95: I ~

Rockland 8:

'Count),try o~~

Story POla-t SPHreirpian PPreciptatioW(

Grolon-Qn Hki'ison I- _j'Le., ý,#3ý$ý Westchoster County 27:

G1l* Monitoring Well, GW SW of Site Boundary Soil IV Aquatic Vegetation Ossining

.~idiudson$ivor Ch ~pp, lw Bottomi S~diment rQZ~

fjk A-7

TABLE A-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLES FOOD SOIL or RADIONUCLIDE WATER AIRBORNE FISH MILK PRODUCTS SEDIMENT ANALYSIS (pCI/L) PARTIUCLATE 9R (pCi/kg, (pCiIL) (pCIlkg, wet) (pCUkg, dry)

GASES (pCI/m) wet)

Gross Beta 4 0.01 H-3 2,000 (d)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Ni-63 (f) 30 100 Zn-65 30 260 Sr-90 (f) 1 5 5000 Zr-95 30 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-140 60 60 La-140 15 15 A-8

TABLE A-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLES Table Notation (a) This list does not mean that only these nuclides are to be considered.

Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to the ODCM.

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

(c) The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to the ODCM.

(d) These LLDs are for drinking water samples. If no drinking water pathway exists, the LLDs may be increased to 3,000 for H-3 and 15 for 1-131.

(e) These required lower limits of detection are associated only with the REMP requirements. The Radiological Ground Water Monitoring Program may involve unique reporting level criteria, independent of the REMP, and defined in station procedures.

(f) Sr-90 and Ni-63 are included in this table due to their historical presence in ground water and possible migration to the environment.

A-9

TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES RADIONUCLIDE WATER AIRBORNE FISH MILK FOOD PARTIUCLATE 9R (pCi/kg, wet) (pCi/L) PRODUCTS ANALYSIS (pCiIL) GASES (pCilm) (pCikg, wet)

H-3 20,000*

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Ni-63 *** 300 1,000 Zn-65 300 20,000 Sr-90 *** 8* 40 Zr-95 400 Nb-95 400 1-131 2* 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-140 200 300 La-140 200 300 Values provided are for drinking water pathways. If no drinking water pathway exists, higher values are allowed, as follows:

H-3 30,000 pCi/L (This is a 40 CFR 141 value)

Sr-90 12 pCi/L 1-131 20 pCi/L These reporting levels are associated only with the REMP requirements. The Radiological Ground Water Monitoring Program may involve unique reporting level criteria, independent of the REMP, and defined in station procedures.

Sr-90 and Ni-63 are included in this table due to their historical presence in ground water and possible migration to the environment.

A-10

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS

SUMMARY

APPENDIX B B.1 2013 Annual Radiological Environmental Monitoring Program Summary The results of the 2013 radiological environmental sampling program are presented in Tables B-2 through B-18. Table B-2 is a summary table of the sample results for 2013. The format of this summary table conforms to the reporting requirements of the ODCM, NRC Regulatory Guide 4.8, and NRC Branch Technical Position to Regulatory Guide 4.8 (Reference 4). In addition, the data obtained from the analysis of samples are provided in Tables B-3 through B-18.

REMP samples were analyzed by various counting methods as appropriate.

The methods are; gross beta, gamma spectroscopy analysis, liquid scintillation, radiochemical analysis, and TLD processing. Gamma spectroscopy analysis was performed for the following radionuclides; Be-7, K-40, Mn-54, Co-58, Co-60, Fe-59, Zn-65, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Cs-134, Cs-137, Ba/La-140, Ce-141, Ce-144, Ra-226 and Ac/Th-228. Radiochemical analyses were performed for H-3, Ni-63, Sr-90 and 1-131 for specific media and locations as required in the ODCM.

B.2 Land Use Census In accordance with Sections IP2-D3.5.2 and IP3-2.8 of the ODCM, a land use census was conducted to identify the nearest milch animal and the nearest residence. The results of the milch animal and land use census are presented in Tables B-19 and B-20, respectively. In lieu of identifying and sampling the nearest garden of greater than 50 M2 , at least three kinds of broad leaf vegetation were sampled near the site boundary in two sectors and at a designated control location (results are presented in Table B-13).

B.3 Sampling Deviations During 2013, environmental sampling was performed for 12 unique media types addressed in the ODCM and for direct radiation. A total of 1178 samples of 1182 scheduled were obtained. Of the scheduled samples, 99.8% were collected and analyzed for the program. Sampling deviations are summarized in Table B-I. Discussions of the reasons for the deviations are provided in Table B-i a for the air samples and Table B-1 b for other media.

B.4 Analytical Deviations One precipitation sample could not be analyzed by gamma spectroscopy due to insufficient sample size being obtained.

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

B-1

TABLE B-1 Summary of Sampling Deviations - 2013 TOTAL NUMBER OF SAMPLING NUMBER OF REASON FOR MEDIA SCHEDULED DEVIATIONS* EFFICIENCY % ANALYSES* DEVIATION SAMPLES MEDIA TLD 164 100% 328 N/A PARTICULATES IN AIR 416 100% 415 See Table B-la CHARCOAL FILTER 416 100% 416 See Table B-la PRECIPITATION 8 100% 14 See Table B-ic DRINKING WATER 24 100% 48 N/A GROUNDWATER 2 100% 8 N/A SAMPLES SOIL 3 100% 3 N/A BROAD LEAF 61 100% 67 N/A VEGETATION HUDSON RIVER WATER 24 100% 40 N/A SHORELINE SOIL 10 100% 20 N/A HUDSON RIVER BOTTOM 13 100% 13 N/A SEDIMENT AQUATIC VEGETATION 6 67% 4 See Table B-lb FISH & INVERTEBRATES 34 100% 68 N/A TOTALS 1181 2 99.8% 1444 TOTAL NUMBER OF SAMPLES COLLECTED = 1179

• Samples not collected or unable to be analyzed.

• • Several sample types require more than one analysis B-2

TABLES B-la I B-lb / B-Ic TABLE B-la 2013 Air Sampling Deviations LOCATION WEEK PROBLEM I ACTIONS TO PREVENT RECURRENCE 121.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> lost (power outage). Breaker reset and work order issued fix a circuit Training Bldg. 5 ise issue.

NYU tower 21 106.8 hrs of sample time loss due to GFCI trip; probable cause was insect infestation. Breaker was reset.

Roseton 34 Hour-meter malfunction*; sample volume appeared to be routine amount.

Grassy Point 39 Hour-meter malfunction*; sample volume appeared to be routine amount.

Algonquin 41 Hour-meter malfunction*; sample volume appeared to be routine amount.

NYU tower 44 16.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> lost (short power outage, no repairs necessary).

Training Bldg. 45 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> lost; sample pump's carbon vanes were broken. New pump installed.

Training Bldg. 47 Approximately 57 hours6.597222e-4 days <br />0.0158 hours <br />9.424603e-5 weeks <br />2.16885e-5 months <br /> lost; pump seized. New pump installed.

Note: All air particulate filters and charcoal cartridges were analyzed.

• Not actual deviations, listed for information only. All hour meters have since been replaced with new hour-meters.

TABLE B-lb 2013 Other Media Deviations LOCATION Week PROBLEM I ACTIONS TO PREVENT RECURRENCE Loss of AC power at this location; power tagged out for excavation in the area. Grab HudsnDschage Rier S sample taken at time of routine composite sample collection.

HudsonLoss of AC power at this location; power tagged out for excavation in the area. Grab sample taken at time of routine composite sample collection.

Loss of AC power at this location; power tagged out for excavation in the area. Grab sample taken at time of routine composite sample collection.

Loss of AC power at this location; power tagged out for excavation in the area. Grab sample taken at time of routine composite sample collection.

Hudson River Discharge 98 oe etoe n34 Loss of AC power at this location; power tagged out for excavation in the area.

Power restored on 3/4.

h13 GFCI found tripped. Loss of autimatic sampling for 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br />. Sufficient sample found for weekly sample.

Lents Cove 22 &37 Aquatic vegetation not available at this location.

Less than expected amount of rain noted in collection device. Since less than 1 Gas Holder 39 gallon was samples, not sufficient valume for gamma analysis - only H-3 analysis was requested.

Note: Only samples not obtained were Week 22 &37 aquatic vegetation samples and sufficient volume for the Week 39 rain sample.

TABLE B-Ic 2013 Analysis Deviations LOCATION Media PROBLEM I ACTIONS TO PREVENT RECURRENCE Rain Gas Holder Water Insufficient volume for gamma analysis (see above)

B-3

TABLE B-2 RADIOLOGICIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2013 Dockets 50-03, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD* Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean Location Distance Mean Mean Reported (Units) (Range) Number Direction (Range) (Range) Measurements Direct Radiation TId-Quarterly 164 NA 13 7 (160/160) DR-28 4 96 Mi 194 (4/4) 14.2 14/4) lmR/Standard Quarter) (9.5/20.7) WSW (17 8/20 7) (12.2/15 4)

Air Particulate Gr-B 416 001 0.014 (363/364) 44 I 84 Mi. 0.014 151/52) 0.014 (52/52)

(pCi/mr) (0 004/0 0301 NE (0 006/0.030) (0.005/0 030)

Air Iodine GAMMA 416 (pCi/mI) 1-131 007 <LLD <LLD Air Particulate GAMMA 32 (I (I* pCi/mr) Be-7 NA 107 (28/28) 028 Mi 120 (4/4) 95 3 (4/4)

(74.7/152) SW (109/1301 (678/136)

K-40 NA 22.0 (1/28) 0 88 Mi. 220(1/4) <LLD SSW Cs-134 0.05 <LLD <LLD Cs-137 006 <LLD <LLD Th-228 NA <LLD <LLD Rainwater H-3 3000 <LLD <LLD (pCi/liter)

GAMMA 6 Co-60 15 <LLD <LLD Cs- 134 15 <LLD <LLD B-4

TABLE B-2 RADIOLOGICIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2013 Dockets 50-03, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD* Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean Location Distance Mean Mean Reported (Units) (Range) Number Direction (Range) (Range) Measurements Rainwater (cont'd) Cs-137 18 <LLD <LLD (pCi/liter)

Drinking Water H-3 2000 <LLD NA (pCi/liter)

Gr-B 24 3.02 (15/24) 08 6.3 Mi 3.02 18/12) NA (2.15/4.14) SE (2.47/4.14)

GAMMA 24 Mn-54 Is <LLD NA Co-58 I5 <LLD NA Fe-59 30 <LLD NA co-60 15 <LLD NA Zn-65 30 <LLD NA Nb-95 15 KLLD NA Zr-95 is <LLD NA 1-131 15 <LLD NA Cs-134 Is <LLD NA B-5

TABLE B-2 RADIOLOGICIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2013 Dockets 50-03, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD* Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean Location Distance Mean Mean Reported (Units) (Range) Number Direction (Range) (Range) Measurements Drinking Water lcont'd) Cs- 137 18 <LLD NA tpCi/liter)

Ba-140 60 <LLD NA La- 140 15 <LLD NA Groundwater 2000 <LLD NA (pCi/liter)

NA <LLD NA Sr-90 NA <LLD NA GAMMA Mn-54 15 <LLD NA 0 Co-58 15 <LLD NA 30 <LLD NA Co-60 I5 <LLD NA Zn-65 30 <LLD NA Nb-95 15 <LLD NA B-6

TABLE B-2 RADIOLOGICIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2013 Dockets 50-03, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD* Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean Location Distance Mean Mean Reported (Units) (Range) Number Direction (Range) (Range) Measurements Groundwater (cont'd) Zr-95 15 <LLD NA 0 (pCi/liter) 1-131 I5 <LLD NA 0 Cs- 134 I5 <LLD NA 0 Cs-137 18 <LLD NA 0 Ba-140 60 <LLD NA 0 La-140 15 <LLD NA 0 Soil GAMMA (pCi/kg dry) Be-7 NA 411t1/2) 94 0.39 Mi. 411 (1/2) <LLD S

K-40 NA 9339(2/2) 23 20.7 Mi. 19780(1/1/ 19780(1/1/

(6758/11920) N Co-60 NA <LLD - -LLD Cs- 134 150 ,LLD -<LLD Cs-137 180 <LLD - <LLD Ra-226 NA <LLD 23 20.7 Mi. 135001/1l 1350(1/1/

N B-7

TABLE B-2 RADIOLOGICIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2013 Dockets 50-03, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD* Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean ** Location Distance Mean Mean Reported (Units) (Range) Number Direction (Range) (Range) Measurements Soil I(co 'd) Th-228 NA 201 (2/2) 23 20.7 Mi. 1135 (1/1) 1135 (1/I)

(pCi/kg dry) 4178/224) N Broadleaf Vegetation 1-131 60 <LLD <LLD (pCi/kg wet)

GAMMA 61 BE-7 NA 1223 (41/42) 23 20.7 Mi. 1576 (19/19) 1576 (19/19)

Q256/2867) N (369/2854) (369/2854)

K-40 NA 4793 (42/42) 95 0 46 Mi 4977 (21/21) 478Q (19/19)

(1869/10160) SSW (2385/10160) (2099/8351)

Co-60 NA <LLD <LLD 1-131 60 <LLD <LLD Cs-134 60 <LLD <LLD Cs-I137 80 <LLD <LLD Th-228 NA 360(2/42) 23 20 7 Mi. 40.511/19) 405 (1/19)

(35.2/368) N River Water H-3 20 3000 410(3/10) 10 0.3 Mi. 410 (3/10) 241 (2/10)

(pCiiter) (306/566) WSW (306/566) (216/266)

GAMMA 24 Mn-54 15 <LLD <LLD B-8

TABLE B-2 RADIOLOGICIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2013 Dockets 50-03, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD* Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean Location Distance Mean Mean Reported (Units) (Range) Number Direction (Range) (Range) Measurements River Water (con'd) Co-58 I5 <LLD <LLD (pCi/liter) 30 <LLD <LLD Co-60 IS <LLD <LLD Zn-65 30 <LLD <LLD Nb-Q5 IS <LLD <LLD IS <LLD <LLD 1-131 IS <LLD <LLD Cs-I134 15 <LLD <LLD Cs-137 18 <LLD <LLD Ba-140 15 <LLD <LLD La-140 15 <LLD <LLD Bottom Sediment GAMMA 13 (pCi/kg dr,) K-40 NA 19900(10/10) 84 1088 Mi. 23157(3/3) 23157(3/3)

(14550/26550) N (21,00/26470) (21300/26470)

B-9 0

TABLE B-2 RADIOLOGICIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2013 Dockets 50-03, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD* Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean Location Distance Mean Mean Reported (Units) (Range) Number Direction (Range) (Range) Measurements Bottom Sediment (consd) Co-b0 NA <LLD <LLD 0 (pCi/&g drv)

Cs-I134 150 <LLD <LLD 0 Cs-137 180 2738 (10/10) 10 0.3 Mi. 6451 (4/4) 263 (2/3) 0 (153/1 38701 WSW (153/13870) (179/348)

Ra-226 NA 3254 (4/10) 10 0.3 Mi. 3691)(2/4) 27570(/3)

(2128/4051) WSW (3328/4051)

Th-228 NA I156 (10/10) 84 10 88 Mi. 1505 (3/3) 1505 (3/3) 0 (808/1491) N (121511779) (1215/1779)

Shoreline Soil Sr-90 10 5000 < LLD <LLD 0 (pCi/kg dry)

GAMMA 10 K-40 NA 14343 (8/8) 84 10 88 Mi 29220 (2/2) 2922012/2) 0 t10900!18580) N (18110/40330) 118110/40330)

Cs-134 150 <LLD <LLD 0 Cs-137 180 133(2/8) 17 I 5sMi 133 (2/2) <LLD (108/158) SSW 1108/158)

Ra-226 NA 3551 (4/8) 50 4.48 Mi 3928 (2/2) 1229(1/2) 11696/6160) NNW (1696/6160)

Th-228 NA 733 (8/8) 28 0.45 Mi 1365 (2/2) 442(2/2) 0 (93.2/1558) ENE (1171/1558) (324/560)

B-10

TABLE B-2 RADIOLOGICIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2013 Dockets 50-03, 50-247 & 50-286 Medium Medium oror Indicator Control Pathway Pathway Analysis Total LLD* Locations Location with Highest Mean Locations Non-Routine Sampled Sampled Type Number Mean ** Location Distance Mean Mean Reported (Units)

(Units) (Range) Number Direction (Range) (Range) Measurements Aquatic Vegetation GAMMA 4 7

(pCi/g wet) Be- NA 299(2/2) 17 1.5 Mi 299 (2/2) 183 (2/2) 0 (190/408) SSW (190/408) (180/18b)

K-40 NA 2409(.2/2) 17 I 5 Mi 2409 (2/2) 1868 (2/2) 0 (2243/2574) SSW (2243/2574) (I1 12/2224)

Co-60 NA <LLD <LLD 0 1-131 NA <LLD <LLD 0 Cs-134 NA <LLD <LLD 0 Cs-137 NA <LLD <LLD 0 Ra-226 NA <LLD 355 (1/2) 0 Ac-228 NA <LLD 84 1088 Mi 71 6(1/2) 71.6(1/2) 0 N

Th-228 NA 60.4 (2/2) 17 I 5 Mi. 60.4 (2/2) 42.o (1/2) 0 (59.2/61.6) SSW (59.2/61.6) (24.7/0o.4)

Ftsh Ni-63 34 100 <LLD ,LLD 0 (pCi/kg went Sr-90 34 5 6.1 (1/23) 25 Downstream 6.1 (1/12) 4 1 (1/11) 0 B-11

TABLE B-2 RADIOLOGICIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

INDIAN POINT ENERGY CENTER - 2013 Dockets 50-03, 50-247 & 50-286 Medium or Indicator Control Pathway Analysis Total LLD* Locations Location with Highest Mean Locations Non-Routine Sampled Type Number Mean ** Location Distance Mean Mean Reported (Units) (Range) Number Direction (Range) (Range) Measurements Fish (coa'd) G.AMMA 34 (pCi/kg wet) K-40 NA 2907 (23/231 25 Downvstream 3005 (12/12) 2702 (11/ll)

(1917/3881) t203,/3881) (1304/4391)

Mn-54 130 <LLD <LLD Co-58 130 <LLD <LLD Fe-59 260 <LLD <LLD Co-60 130 <LLD <LLD Zn-6S 260 <LLD <LLD Cs-134 130 <LLD <LLD Cs-137 150 <LLD <LLD Th-228 NA <LLD <LLD LLD IS THE LOWER LIMIT OF DETECTION THE MEAN VALUES ARE CALCULATED USING THE POSITIVE VALUES

• • • MDC IS THE MIMINUMNDETECTABLE CONCENTRATION B-12

INDIAN POINT ENERGY CENTER TABLE B-3 DIRECT RADIATION, QUARTERLY DATA - 2013 mR/Quarter + 1 sigma Sample Station First Quarter Second Quarter Third Quarter Fourth Quarter Annual Annual Nuclide Number 01/01-03/31 04/01-06/30 07/01-09/30 10/01-01/01 Average Total TLD DR-01 13.4 +/- 0.6 14.0 +/- 0.6 15.7 +/- 0.8 16.5 +/- 0.8 14.9 59.7 DR-02 12.5 +/- 0.7 13.5 +/- 0.5 15.0 +/- 0.6 15.4 +/- 0.5 14.1 56.4 DR-03 9.7 +/- 0.5 11.3 +/- 0.5 12.0 +/- 0.6 12.7 +/- 0.7 11.4 45.7 DR-04 11.1 +/- 0.6 12.8 +/- 0.6 14.0 +/- 0.5 14.6 +/- 1.3 13.1 52.5 DR-05 11.4 +/- 0.6 13.0 +/- 0.6 14.2 +/- 0.6 14.7 +/- 0.8 13.3 53.3 DR-06 11.7 +/- 0.5 13.9 +/- 0.7 14.3 +/- 0.7 15.0 +/- 0.7 13.7 54.9 DR-07 14.0 +/- 0.6 15.3 +/- 0.6 16.4 +/- 0.7 16.4 +/- 0.7 15.5 62.1 DR-08 10.0 +/- 0.4 11.6 +/- 0.8 11.9 +/- 0.6 12.4 +/- 0.5 11.5 46.0 DR-09 11.3 +/- 0.6 12.6 +/- 0.7 13.1 +/- 0.5 13.7 +/- 0.6 12.7 50.7 DR-10 12.1 +/- 0.7 13.5 +/- 0.7 14.3 +/- 0.7 14.8 +/- 0.6 13.6 54.6 DR-11 9.5 +/- 0.5 10.6 +/- 0.4 11.1 +/- 0.7 11.1 +/- 0.6 10.6 42.2 DR-12 15.0 +/- 0.8 14.9 +/- 0.8 16.2 +/- 1.1 16.2 +/- 0.6 15.6 62.2 DR-13 15.1 +/- 0.6 15.3 +/- 0.6 16.8 +/- 1.0 17.1 +/- 0.7 16.1 64.3 DR-14 12.7 +/- 0.5 12.6 +/- 0.6 14.1 +/- 0.7 13.9 +/- 1.0 13.3 53.3 DR-15 12.7 +/- 0.6 12.7 +/- 0.6 13.4 +/- 0.5 14.2 +/- 0.6 13.3 53.0 DR-16 13.7 +/- 0.6 13.9 +/- 0.8 15.0 +/- 0.8 15.5 +/- 0.6 14.5 58.1 DR-17 13.9 +/- 0.8 13.8 +/- 0.7 15.6 +/- 0.8 15.3 +/- 0.9 14.6 58.6 DR-18 12.4 +/- 0.5 13.7 +/- 0.8 15.1 +/- 0.7 14.5 +/- 0.6 13.9 55.6 DR-19 13.1 +/- 0.8 14.4 +/- 0.8 15.3 +/- 0.6 15.9 +/- 0.6 14.6 58.6 DR-20 12.2 +/- 0.5 13.4 +/- 0.6 15.1 +/- 0.6 14.5 +/- 0.9 13.8 55.3 DR-21 12.1 +/- 0.5 12.9 +/- 1.0 13.9 +/- 0.9 14.2 +/- 0.6 13.3 53.1 DR-22 9.8 +/- 0.4 10.4 +/- 0.7 11.4 +/- 0.6 11.7 +/- 0.5 10.8 43.4 DR-23 12.4 +/- 0.6 13.3 +/- 0.8 14.7 +/- 0.9 14.4 +/- 0.8 13.7 54.8 DR-24 12.7 +/- 0.7 14.4 +/- 0.6 15.3 +/- 0.6 14.8 +/- 0.5 14.3 57.2 DR-25 11.5 +/- 0.7 11.7 +/- 0.6 12.4 +/- 0.7 12.7 +/- 0.7 12.1 48.3 B-13

INDIAN POINT ENERGY CENTER TABLE B-3 DIRECT RADIATION, QUARTERLY DATA - 2013 mR/Quarter 1 sigma Sample Station First Quarter Second Quarter Third Quarter Fourth Quarter Annual Annual Nuclide Number 01/01-03/31 04/01-06/30 07/01-09/30 10/01-01/01 Average Total TLD DR-26 13.2 +/- 0.8 13.6 +/- 0.6 14.0 +/- 0.7 14.5 +/- 1.1 13.8 55.2 DR-27 12.9 +/- 0.7 13.1 +/- 0.5 13.9 +/- 0.7 14.3 +/- 0.7 13.5 54.2 DR-28 17.8 +/- 0.7 18.7 +/- 1.0 20.7 +/- 1.1 20.3 +/- 0.8 19.4 77.1 DR-29 12.8 +/- 0.7 13.4 +/- 0.6 15.3 +/- 0.9 15.0 +/- 0.5 14.1 56.6 DR-30 13.4 +/- 0.7 13.8 +/- 0.5 15.5 +/- 0.8 15.3 +/- 0.6 14.5 58.0 DR-31 14.7 +/- 0.6 15.7 +/- 0.7 17.5 +/- 0.7 17.2 +/- 0.8 16.3 65.1 DR-32 12.2 +/- 0.6 12.6 +/- 0.5 13.8 +/- 0.8 13.4 +/- 0.8 13.0 52.0 DR-33 11.4 +/- 0.5 13.4 +/- 0.5 14.1 +/- 0.5 14.0 +/- 0.5 13.2 52.9 DR-34 11.0 +/- 0.5 12.9 +/- 0.5 13.3 +/- 0.6 13.4 +/- 0.6 12.7 50.6 DR-35 11.4 +/- 0.6 12.6 +/- 0.7 12.9 +/- 0.8 13.1 +/- 0.9 12.5 49.9 DR-36 12.9 +/- 0.6 13.7 +/- 0.6 15.3 +/- 0.7 14.8 +/- 0.6 14.2 56.6 DR-37 11.7 +/- 0.5 13.4 +/- 0.7 14.4 +/- 0.5 14.4 +/- 0.8 13.5 53.9 DR-38 10.3 +/- 0.5 11.7 +/- 0.7 12.5 +/- 0.8 13.1 +/- 0.7 11.9 47.6 DR-39 13.0 +/- 0.7 13.7 +/- 0.8 14.8 +/- 0.6 15.1 +/- 0.6 14.2 56.6 DR-40* 12.2 +/- 0.7 14.3 +/- 0.7 15.1 +/- 0.6 15.4 +/- 0.6 14.2 57.0 DR-41 11.2 +/- 0.5 12.3 +/- 0.7 13.3 +/- 0.7 13.3 +/- 0.6 12.5 50.1 AVERAGE (Indicator 12.4 13.4 14.4 14.6 13.7 54.7 Locations)

Control location (a) TLD missing, the annual total is based on using the 3 quarters average for the first quarter.

B-14

INDIAN POINT ENERGY CENTER TABLE B-4 DIRECT RADIATION, 2003 THROUGH 2013 DATA mR per Year Station Mean Standard Deviation Minimum Value Maximum Value 2013 Mean Number (2003-2013) (2003-2013) (2003-2013) (2003-2013)

DR-01 66.2 2.2 55.6 63.6 59.7 DR-02 63.0 1.8 53.6 60.0 56.4 DR-03 51.5 1.9 44.0 50.0 45.7 DR-04 58.5 2.7 46.8 58.0 52.5 DR-05 59.5 2.2 48.4 56.8 53.3 DR-06 60.2 3.1 46.4 57.6 54.9 DR-07 68.9 2.9 55.6 66.4 62.1 DR-08 53.5 2.5 45.2 53.6 46.0 DR-09 57.4 2.3 47*2 55.2 50.7 DR-10 62.2 1.7 53.6 58.8 54.6 DR-11 47.6 1.6 40.8 45.6 42.2 DR-12 70.2 3.3 59.6 68.4 62.2 DR-13 79.9 6.8 62.4 82.0 64.3 DR-14 57.9 1.7 50.0 55.2 53.3 DR-15 57.1 2.2 46.4 54.8 53.0 DR-16 63.3 1.8 55.2 60.8 58.1 DR-17 64.0 1.9 55.6 61.2 58.6 DR-18 62.1 2.0 52.4 59.1 55.6 DR-19 64.4 2.0 55.2 60.8 58.6 DR-20 58.2 2.2 47.6 55.3 55.3 DR-21 59.7 2.2 50.0 57.6 53.1 DR-22 48.7 1.8 40.4 46.4 43.4 DR-23 60.3 2.2 49.6 58.0 54.8 DR-24 62.5 2.7 49.2 58.8 57.2 DR-25 53.6 2.1 44.8 52.4 48.3 DR-26 60.4 2.3 50.4 58.8 55.2 DR-27 58.8 2.6 46.8 56.4 54.2 DR-28 82.6 5.5 64.0 79.1 77.1 DR-29 62.9 2.3 54.8 63.2 56.6 DR-30 63.9 2.8 52.4 61.9 58.0 DR-31 72.6 2.6 61.5 70.0 65.1 DR-32 56.4 2.3 46.0 54.8 52.0 B-15

INDIAN POINT ENERGY CENTER TABLE B4 DIRECT RADIATION, 2003 THROUGH 2013 DATA mR per Year Station Mean Standard Deviation Minimum Value Maximum Value 2013 Mean Number (2003-2013) (2003-2013) (2003-2013) (2003-2013)

DR-33 59.2 1.7 49.2 55.2 52.9 DR-34 55.4 2.6 43.2 53.6 50.6 DR-35 58.0 2.5 48.8 56.4 49.9 DR-36 64.0 2.3 52.4 60.2 56.6 DR-37 59.4 2.5 48.8 58.0 53.9 DR-38 55.3 2.7 46.7 56.0 47.6 DR-39 65.2 2.8 54.8 63.2 56.6 DR-40* 66.4 8.3 49.3 75.2 57.0 DR-41 55.6 2.4 44.4 53.6 50.1 AVERAGE (Indicator 61.0 54.7 Locations)

• Control location B-16

INDIAN POINT ENERGY CENTER TABLE B-5 DIRECT RADIATION, INNER AND OUTER RINGS - 2013 (mR per Year)

Inner Ring Outer Ring Sector Inner Ring Outer Ring ID ID Annual Average Annual Average DR-01 DR-17 N 59.7 58.6 DR-02 DR-18 NNE 56.4 55.6 DR-03 DR-19 NE 45.7 58.6 DR-04 DR-20 ENE 52.5 55.3 DR-05 DR-21 ENE 53.3 53.1 DR-06 DR-22 ESE 54.9 43.4 DR-07 DR-23 SE 62.1 54.8 DR-08 DR-24 SSE 46.0 57.2 DR-09 DR-25 S 50.7 48.3 DR-10 DR-26 SSW 54.6 55.2 DR-11 DR-27 SW 42.2 54.2 DR-12 DR-28 WSW 62.2 77.6 DR-13 DR-29 WSW 64.3 56.6 DR-14 DR-30 WNW 53.3 58.0 DR-15 DR-31 NW 53.0 65.1 DR-16 DR-32 NNW 58.1 52.0 Average I 1 54.3 56.5 B-17

INDIAN POINT ENERGY CENTER TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES - 2013 3

pCi/rn +/- 2 Sigma PERIOD Algonquin NYU Tower Roseton Croton Point Grassy Point Peekskill Training Building Met Tower ENDING 4 5 23* 27 29 44 94 95 01/08/13 0.020 +/- 0.003 0.020 +/- 0.003 0.030 +/- 0.004 0.020 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 01/15/13 0.020 +/- 0.000 0.020 +/- 0.000 0.020 +/- 0.000 0.020 +/- 0.000 0.020 +/- 0.000 0.020 +/- 0.000 0.020 +/- 0.000 0.017 +/- 0.002 01/22/13 0.014 +/- 0.002 0.015 +/- 0.003 0.013 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.012 +/- 0.002 0.016 +/- 0.003 0.015 +/- 0.002 01/28/13 0.014 +/- 0.003 0.012 +/- 0.002 0.012 +/- 0.002 0.015 +/- 0.003 0.013 +/- 0.002 0.018 +/- 0.003 0.012 +/- 0.002 0.013 +/- 0.002 02/04/13 0.017 +/- 0.003 0.018 +/- 0.003 0.017 +/- 0.003 0.018 +/- 0.003 0.019 +/- 0.002 0.017 +/- 0.002 0.023 +/- 0.006 0.018 +/- 0.002 02/11/13 0.019 +/- 0.003 0.020 +/- 0.003 0.015 +/- 0.002 0.018 +/- 0.003 0.017 +/- 0.002 0.019 +/- 0.003 0.019 +/- 0.003 0.019 +/- 0.003 02/19/13 0.011 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.010 +/- 0.002 0.015 +/- 0.002 0.013 +/- 0.002 02/25/13 0.009 +/- 0.002 0.008 +/- 0.002 0.008 +/- 0.002 0.010 +/- 0.003 0.008 +/- 0.002 0.009 +/- 0.002 0.007 +/- 0.002 0.009 +/- 0.002 03/04/13 0.011 +/- 0.002 0.008 +/- 0.002 0.008 +/- 0.002 0.009 +/- 0.002 0.006 +/- 0.002 0.007 +/- 0.002 0.009 +/- 0.002 0.007 +/- 0.002 03/11/13 0.006 +/- 0.002 0.008 +/- 0.002 0.009 +/- 0.002 0.007 +/- 0.002 0.005 +/- 0.002 0.006 +/- 0.002 0.006 +/- 0.002 0.006 +/- 0.002 03/18/13 0.015 +/- 0.003 0.014 +/- 0.003 0.015 +/- 0.003 0.014 +/- 0.003 0.014 +/- 0.002 0.011 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 03/25/13 0.012 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.012 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 04/01/13 0.008 +/- 0.002 0.006 +/- 0.002 0.007 +/- 0.002 0.007 +/- 0.002 0.007 +/- 0.002 0.007 +/- 0.002 0.006 +/- 0.002 0.006 +/- 0.002 04/08/13 0.014 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 04/15/13 0.010 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 04/22/13 0.008 +/- 0.002 0.010 +/- 0.002 0.008 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.011 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 04/29/13 0.014 +/- 0.002 0.015 +/- 0.002 0.017 +/- 0.003 0.014 +/- 0.002 0.015 +/- 0.003 0.018 +/- 0.002 0.016 +/- 0.002 0.012 +/- 0.002 05/06/13 0.013 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.002 0.014 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 05/13/13 0.007 +/- 0.002 0.006 +/- 0.002 0.007 +/- 0.002 0.006 +/- 0.002 0.008 +/- 0.002 0.007 +/- 0.002 0.008 +/- 0.002 0.008 +/- 0.002 05/20/13 0.011 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.012 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 05/28/13 0.010 +/- 0.002 0.016 +/- 0.004 0.011 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 06/03/13 0.018 +/- 0.003 0.014 +/- 0.003 0.019 +/- 0.003 0.017 +/- 0.003 0.016 +/- 0.003 0.018 +/- 0.003 0.018 +/- 0.003 0.019 +/- 0.003 06/10/13 0.008 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.008 +/- 0.002 0.008 +/- 0.002 0.009 +/- 0.002 0.008 +/- 0.002 0.007 +/- 0.002 06/17/13 0.010 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 06/24/13 0.010 +/- 0.002 0.013 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.009 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 07/01/13 0.017 +/- 0.003 0.017 +/- 0.002 0.018 +/- 0.002 0.015 +/- 0.002 0.017 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.002

• Control location B-i18

INDIAN POINT ENERGY CENTER TABLE B-6 GROSS BETA ACTIVITY IN AIRBORNE PARTICULATE SAMPLES - 2013 3

pCi/rn +/- 2 Sigma PERIOD Algonquin NYU Tower Roseton Croton Point Grassy Point Peekskill Training Building Met Tower ENDING 4 5 23* 27 29 44 94 95 07/08/13 0.008 +/-0.002 0.008 +/- 0.002 0.008 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.006 +/- 0.002 07/15/13 0.013 +/-0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.011 +/- 0.002 0.012 +/- 0.002 07/22/13 0.016 +/-0.002 0.018 +/- 0.002 0.017 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.002 0.016 +/- 0.002 07/29/13 0.011 +/-0.002 0.008 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 08/05/13 0.013 +/-0.002 0.014 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 08/12/13 0.011 +/-0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.011 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.002 08/19/13 0.015 +/-0.002 0.011 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 08/26/13 0.017 +/-0.003 0.017 +/- 0.003 0.019 +/- 0.003 0.017 +/- 0.002 0.020 +/- 0.003 0.019 +/- 0.003 0.019 +/- 0.003 0.017 +/- 0.002 09/03/13 0.020 +/-0.003 0.019 +/- 0.002 0.019 +/- 0.002 0.019 +/- 0.002 0.022 +/- 0.003 0.020 +/- 0.002 0.020 +/- 0.002 0.018 +/- 0.002 09/09/13 0.012 +/-0.003 0.012 +/- 0.003 0.008 +/- 0.002 0.009 +/- 0.002 0.012 +/- 0.003 0.013 +/- 0.003 0.009 +/- 0.002 0.014 +/- 0.003 09/16/13 0.021 +/-0.003 0.022 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.018 +/- 0.003 0.018 +/- 0.003 09/23/13 0.010 +/-0.002 0.013 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 09/30/13 0.005 +/-0.002 0.005 +/- 0.002 0.005 +/- 0.002 0.004 +/- 0.002 0.004 +/- 0.002 < 0.003 0.005 +/- 0.002 0.004 +/- 0.002 10/07/13 0.027 +/-0.003 0.026 +/- 0.003 0.023 +/- 0.003 0.028 +/- 0.003 0.029 +/- 0.003 0.030 +/- 0.003 0.025 +/- 0.003 0.027 +/- 0.003 10/15/13 0.015 +/-0.002 0.015 +/- 0.002 0.014 +/- 0.002 0.015 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 10/21/13 0.020 +/-0.003 0.018 +/- 0.003 0.023 +/- 0.003 0.018 +/- 0.003 0.018 +/- 0.003 0.020 +/- 0.003 0.018 +/- 0.003 0.017 +/- 0.003 10/28/13 0.012 +/-0.002 0.013 +/- 0.002 0.010 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.011 +/- 0.002 11/04/13 0.019 +/-0.003 0.017 +/- 0.003 0.018 +/- 0.002 0.019 +/- 0.003 0.018 +/- 0.003 0.018 +/- 0.003 0.017 +/- 0.002 0.017 +/- 0.002 11/12/13 0.012 +/-0.002 0.012 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.009 +/- 0.002 0.011 +/- 0.002 11/18/13 0.014 +/- 0.003 0.013 +/- 0.003 0.011 +/- 0.002 0.013 +/- 0.003 0.014 +/- 0.003 0.015 +/- 0.003 0.013 +/- 0.003 0.014 +/- 0.003 11/25/13 0.009 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.008 +/- 0.002 0.007 +/- 0.002 0.010 +/- 0.003 0.011 +/- 0.002 12/02/13 0.013 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.003 0.013 +/- 0.002 12/09/13 0.028 +/- 0.003 0.025 +/- 0.003 0.024 +/- 0.003 0.023 +/- 0.003 0.028 +/- 0.003 0.028 +/- 0.003 0.026 +/- 0.003 0.027 +/- 0.003 12/16/13 0.020 +/- 0.003 0.018 +/- 0.002 0.018 +/- 0.002 0.019 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.021 +/- 0.003 0.021 +/- 0.003 12/23/13 0.017 +/- 0.003 0.018 +/- 0.003 0.017 +/- 0.002 0.018 +/- 0.003 0.017 +/- 0.002 0.020 +/- 0.003 0.021 +/- 0.003 0.016 +/- 0.002 12/30/13 0.018 +/- 0.003 0.016 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.017 +/- 0.002 0.015 +/- 0.002 0.018 +/- 0.003

• Control location B-i 9

INDIAN POINT ENERGY CENTER TABLE B-7 IODINE-1 31 ACTIVITY IN AIRBORNE CHARCOAL SAMPLES - 2013 pCi/ms +/- 2 Sigma PERIOD Algonquin NYU Tower Roseton Croton Point Grassy Point Peekskill Training Building Met Tower ENDING 4 5 23* 27 29 44 94 95 01/08/13 < 0.0331 < 0.0330 < 0.0272 < 0.0324 < 0.0211 < 0.0244 < 0.0316 < 0.0260 01/15/13 < 0.0202 < 0.0203 < 0.0357 < 0.0198 < 0.0278 < 0.0324 < 0.0191 < 0.0335 01/22/13 < 0.01 57 < 0.0157 < 0.0183 < 0.01 52 < 0.0139 < 0.0164 < 0.0149 < 0.0167 01/28/13 < 0.0242 < 0.0243 < 0.0300 < 0.0239 < 0.0223 < 0.0266 < 0.0232 < 0.0282 02/04/13 < 0.0187 < 0.0186 < 0.0183 < 0.0182 < 0.0142 < 0.0167 < 0.0623 < 0.0171 02/11/13 < 0.0486 < 0.0486 < 0.0333 < 0.0476 < 0.0257 < 0.0300 < 0.0474 < 0.0308 02/19/13 < 0.0190 < 0.0188 < 0.0169 < 0.0185 < 0.0127 < 0.0153 < 0.0180 < 0.0154 02/25/13 < 0.0346 < 0.0349 < 0.0433 < 0.0346 < 0.0338 < 0.0390 < 0.0332 < 0.0402 03/04/13 < 0.0206 < 0.0204 < 0.0207 < 0.0217 < 0.0160 < 0.0189 < 0.0196 < 0.0191 03/11/13 < 0.0092 < 0.0092 < 0.0147 < 0.0091 < 0.0114 < 0.0134 < 0.0088 < 0.0136 03/18/13 < 0.0250 <0.0250 < 0.0208 < 0.0244 < 0.0160 < 0.0190 < 0.0238 < 0.0192 03/25/13 < 0.0166 < 0.0168 < 0.0143 < 0.0163 < 0.0111 < 0.0131 < 0.0158 < 0.0132 04/01/13 < 0.0179 < 0.0179 < 0.0180 < 0.0175 < 0.0139 < 0.0160 < 0.0169 < 0.0165 04/08/13 < 0.0247 < 0.0246 < 0.0206 < 0.0240 < 0.0159 < 0.0189 < 0.0235 < 0.0187 04/15/13 < 0.0218 < 0.0216 < 0.0220 < 0.0210 < 0.0171 < 0.0201 < 0.0205 < 0.0198 04/22/13 < 0.0388 < 0.0383 < 0.0334 < 0.0370 < 0.0259 < 0.0299 < 0.0362 < 0.0297 04/29/13 < 0.0384 < 0.0380 < 0.0260 < 0.0366 < 0.0268 < 0.0227 < 0.0357 < 0.0234 05/06/13 < 0.0215 < 0.0213 < 0.0186 < 0.0205 < 0.0178 < 0.0150 < 0.0201 < 0.0166 05/13/13 < 0.0249 < 0.0243 < 0.0416 < 0.0233 < 0.0436 < 0.0416 < 0.0231 < 0.0408 05/20/13 < 0.0237 < 0.0234 < 0.0250 < 0.0227 < 0.0266 < 0.0264 < 0.0221 < 0.0250 05/28/13 < 0.0318 < 0.0681 < 0.0236 < 0.0298 < 0.0244 < 0.0241 < 0.0297 < 0.0233 06/03/13 < 0.0507 < 0.0500 < 0.0324 < 0.0484 < 0.0336 < 0.0331 < 0.0469 < 0.0329 06/10/13 < 0.0347 < 0.0337 < 0.0446 < 0.0328 < 0.0458 < 0.0450 < 0.0323 < 0.0436 06/17/13 < 0.0142 < 0.0140 < 0.0205 < 0.0134 < 0.0213 < 0.0211 < 0.0134 < 0.0207 06/24/13 < 0.0233 < 0:0228 < 0.0296 < 0.0221 < 0.0303 < 0.0299 < 0.0217 < 0.0295 07/01/13 < 0.0448 < 0.0440 < 0.0469 < 0.0422 < 0.0484 < 0.0473 < 0.0417 < 0.0462

• Control location B-20

INDIAN POINT ENERGY CENTER TABLE B-7 IODINE-131 ACTIVITY IN AIRBORNE CHARCOAL SAMPLES - 2013 pCi/m* + 2 Sigma PERIOD Algonquin NYU Tower Roseton Croton Point Grassy Point Peekskill Training Building Met Tower ENDING 4 5 23* 27 29 44 94 95 07/08/13 < 0.0142 <0.0139 < 0.0136 <0.0133 < 0.0139 < 0.0136 < 0.0133 < 0.0136 07/15/13 < 0.0193 <0.0188 <0.0219 <0.0181 <0.0226 <0.0221 <0.0181 <0.0217 07/22/13 < 0.0328 < 0.0321 < 0.0279 < 0.0309 < 0.0286 < 0.0278 < 0.0306 < 0.0279 07/29/13 < 0.0276 < 0.0270 < 0.0328 < 0.0262 < 0.0341 < 0.0328 < 0.0261 < 0.0326 08/05/13 < 0.0360 < 0.0352 < 0.0318 < 0.0337 < 0.0329 < 0.0320 < 0.0341 < 0.0320 08/12/13 < 0.0296 < 0.0293 < 0.0241 < 0.0287 < 0.0251 < 0.0242 < 0.0277 < 0.0232 08/19/13 < 0.0302 < 0.0294 < 0.0352 < 0.0283 < 0.0359 < 0.0351 < 0.0286 < 0.0359 08/26/13 < 0.0431 < 0.0421 < 0.0236 < 0.0404 < 0.0239 < 0.0237 < 0.0407 < 0.0240 09/03/13 < 0.0325 < 0.0317 < 0.0371 < 0.0307 < 0.0384 < 0.0374 < 0.0305 < 0.0365 09/09/13 < 0.0496 < 0.0493 < 0.0463 < 0.0479 < 0.0472 < 0.0476 < 0.0473 < 0.0463 09/16/13 < 0.0117 <0.0114 <0.0148 <0.0109 <0.0155 <0.0150 <0.0111 <0.0155 09/23/13 < 0.0388 < 0.0378 < 0.0258 < 0.0364 < 0.0272 < 0.0268 < 0.0370 < 0.0270 09/30/13 < 0.0340 < 0.0334 < 0.0408 < 0.0322 < 0.0422 < 0.0427 < 0.0326 < 0.0424 10/07/13 < 0.0692 < 0.0678 < 0.0590 < 0.0671 < 0.0614 < 0.0612 < 0.0647 < 0.0595 10/15/13 < 0.0300 < 0.0286 < 0.0267 < 0.0281 < 0.0276 < 0.0282 < 0.0281 < 0.0280 10/21/13 < 0.0390 < 0.0375 < 0.0338 < 0.0372 < 0.0358 < 0.0359 < 0.0370 < 0.0351 10/28/13 < 0.0227 < 0.0216 < 0.0228 < 0.0212 < 0.0229 < 0.0236 < 0.0212 < 0.0232 11/04/13 < 0.0399 < 0.0386 < 0.0333 < 0.0381 < 0.0360 < 0.0360 < 0.0377 < 0.0349 11/12/13 < 0.0429 < 0.0409 < 0.0296 < 0.0405 < 0.0310 < 0.0316 < 0.0440 < 0.0305 11/18/13 < 0.0325 < 0.0307 < 0.0261 < 0.0307 < 0.0269 < 0.0280 < 0.0343 < 0.0275 11/25/13 < 0.0370 < 0.0361 < 0.0309 < 0.0352 < 0.0327 < 0.0329 < 0.0536 < 0.0309 12/02/13 < 0.0120 <0.0115 <0.0116 <0.0115 <0.0124 <0.0123 <0.0135 <0.0118 12/09/13 < 0.0290 < 0.0280 < 0.0274 < 0.0274 < 0.0286 < 0.0285 < 0.0290 < 0.0293 12/16/13 < 0.0317 < 0.0306 < 0.0330 < 0.0299 < 0.0349 < 0.0349 < 0.0324 < 0.0342 12/23/13 < 0.0534 < 0.0515 < 0.0356 < 0.0506 < 0.0375 < 0.0374 < 0.0529 < 0.0368 12/30/13 < 0.0437 < 0.0408 < 0.0424 < 0.0422 < 0.0451 < 0.0448 < 0.0425 < 0.0447

• Control location B-21

INDIAN POINT ENERGY CENTER TABLE B-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES - 2013 3 3 10- pCi/m +/- 2 Sigma Algonquin NYU Tower 4 5 DATE 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Be-7 130 +/- 34 109 +/- 22 127 +/- 30 114 +/- 24 80 +/- 36 152 +/- 27 99 +/- 24 97 +/- 32 K-40 < 12 < 20 < 12 < 26 <31 < 14 22 +/-11 < 24 Mn-54 <2 <1 <2 <2 <2 <2 <1 <2 Co-58 <3 <2 <3 <3 <3 <2 <2 <4 Fe-59 <9 <6 < 13 <9 <13 <8 <7 < 12 Co-60 <1 <1 <2 <1 <2 <2 <1 <2 Zn-65 <4 <3 <7 <4 <5 <3 <5 <7 Nb-95 <3 <2 <4 <3 <5 <3 <3 <4 Zr-95 <5 <4 <6 <5 <8 <5 <5 <7 Ru-103 <5 <3 <6 <3 <5 <5 <4 <6 Ru-106 <15 <9 < 17 < 11 < 20 <10 < 14 < 16 1-131 < 993 < 506 < 1013 < 866 < 1055 < 537 < 771 < 1070 Cs-134 <2 <1 <2 <2 <2 <2 <2 <2 Cs-137 <1 <1 <2 <1 <2 <1 <1 <2 Ba-140 < 296 < 173 < 383 < 234 < 333 < 230 < 246 < 405 La-140 < 116 < 60 < 72 < 98 < 179 < 149 < 74 < 189 Ce-141 <8 <6 <8 <8 <7 <6 < 13 <8 Ce-144 <9 <5 <7 <8 <8 <7 < 14 <8 Ra-226 < 26 < 18 < 29 < 24 < 26 < 23 < 35 < 31 Ac-228 <6 <4 <7 <5 <6 <6 <6 <8 Th-228 <3 <2 <2 <2 <3 <2 <3 <3 B-22

INDIAN POINT ENERGY CENTER TABLE B-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES - 2013 3

10-1 pCi/m +/- 2 Sigma Roseton Croton Point 23* 27 DATE 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Be-7 68 +/- 27 136 +/- 37 96 +/- 34 82 +/- 34 109 +/- 32 113 +/- 26 112 +/- 31 90 +/- 23 K-40 < 21 < 34 < 15 < 32 < 26 < 21 < 37 <18 Mn-54 <1 <2 <2 <2 <1 <1 <2 <1 Co-58 <2 <4 <3 <3 <3 <2 <3 <2 Fe-59 <7 < 10 < 10 < 14 <5 <8 < 13 <6 Co-60 <1 <2 <2 <2 <2 <1 <2 <2 Zn-65 <3 <5 <4 <6 <4 <3 <6 <4 Nb-95 <2 <4 <4 <4 <3 <3 <4 <2 Zr-95 <4 <8 <6 <6 <5 <5 <7 <4 Ru-103 <3 <7 <6 <6 <5 <5 <5 <4 Ru-106 <9 *18 < 16

• 18 *17 *12 <15 <11 1-131 < 590 < 1136

• 887

• 971 < 733 < 815 < 918 < 737 Cs-134 <1 <3 <2 <2 <2 <1 <2 <2 Cs-137 <1 <2 <1 <2 <1 <1 <2 <1 Ba-140 < 183 < 379 < 331

• 298 < 230 < 225 < 324 < 227 La-140 < 104 < 185 < 104 < 113 < 100 < 55 < 130 < 66 Ce-141 <4 <8 <9 <7 <7 <8 <7 <7 Ce-144 <5 <7 < 10 <8 <6 <9 <8 <8 Ra-226 <18 < 24 < 29 < 24 < 23 < 25 < 23 < 20 Ac-228 <4 <9 <6 <7 <5 <4 <7 <4 Th-228 <2 <3 <3 <2 <2 <2 <2 <2

• Control location B-23

INDIAN POINT ENERGY CENTER TABLE B-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES - 2013 3

10-3 pCi/m +/- 2 Sigma Grassy Point Peekskill 29 44 DATE 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Be-7 86 +/- 18 128 +/- 31 116 +/- 24 100 +/- 31 75 +/- 22 114 +/- 28 107 +/- 22 112 +/- 29 K-40 < 15 < 13 < 17 < 36 < 13 < 23 < 15 < 39 Mn-54 <1 <1 <1 <2 <1 <2 <1 <2 Co-58 <2 <2 <2 <4 <2 <2 <2 <4 Fe-59 <6 <7 <7 < 13 <4 <8 <7 < 10 Co-60 <1 <1 <1 <2 <1 <1 <1 <2 Zn-65 <3 <4 <3 <6 <3 <4 <2 <5 Nb-95 <2 <2 <3 <4 <2 <3 <2 <4 Zr-95 <3 <4 <3 <7 <3 <6 <4 <6 Ru-103 <3 <4 <3 <6 <3 <4 <3 <7 Ru-106 <6 < 12 < 10 < 20 < 10 <11 <8 < 18 1-131 < 480

• 741 < 533 < 1036 < 517 < 754 < 519 < 959 Cs-134 <1 <2 <2 <2 <1 <1 <1 <2 Cs-137 <1 <1 <1 <2 <1 <1 <1 <2 Ba-140 < 131

• 225 < 156 < 405 < 173 < 302 < 177 < 384 La-140 < 71 < 72 < 80 < 187 < 46 < 37 < 76 < 169 Ce-141 <5 <5 <5 <8 <5 <7 <4 <8 Ce-144 <5 <7 <5 <8 <5 <7 <5 <7 Ra-226 < 16 < 19 < 18 < 28 <17 < 24 < 16 < 27 Ac-228 <4 <5 <5 <8 <3 <4 <5 <9 Th-228 <1 <2 <2 <3 <2 <2 <1 <2 B-24

INDIAN POINT ENERGY CENTER TABLE B-8 GAMMA EMITTERS IN AIRBORNE PARTICULATE SAMPLES - 2013 3 3 10i pCi/m + 2 Sigma Training Building Met Tower 94 95 DATE 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Be-7 99 +/- 25 117 +/- 24 113 +/- 26 109 +/- 33 80 +/- 27 113 +/- 30 94 +/- 23 93 +/- 26 K-40 < 14 < 12 < 16 < 23 < 14 < 10 <13 < 20 Mn-54 <2 <1 <2 <3 <2 <2 <1 <1 Co-58 <3 <1 <2 <4 <2 <2 <2 <2 Fe-59 <9 <6 <5 < 14 <9 <6 <5 <6 Co-60 <2 <1 <1 <2 <2 <2 <1 <1 Zn-65 <4 <3 <3 <5 <4 <4 <3 <3 Nb-95 <3 <2 <2 <4 <3 <3 <2 <2 Zr-95 <5 <4 <4 <8 <7 <5 <3 <4 Ru-103 <5 <4 <4 <7 <5 <3 <3 <4 Ru-106 <17 <11

• 14

• 22 <15

• 12 <11

• 12 1-131

• 895 < 701

• 618 < 1348

• 849

• 780 < 653

• 684 Cs-134 <2 <1 <2 <2 <2 <1 <1 <2 Cs-137 <1 <1 <1 <2 <2 <1 <1 <1 Ba-140

• 305

• 180

• 209

• 482

• 314

• 205

• 202

• 228 La-140 <71 < 66

• 58

• 180 < 116

• 120 < 99 < 84 Ce-141 <8 <5 <6 <9 <9 <6 <6 <7 Ce-144 <10 <5 <7 <8 <9 <6 <6 <7 Ra-226

• 32 < 17 < 20 < 33 < 26 < 20 <21 < 23 Ac-228 <6 <4 <5 <7 <6 <5 <4 <2 Th-228 <3 <2 <2 <3 <3 <2 <2 <2 B-25

INDIAN POINT ENERGY CENTER TABLE B-9 RADIONUCLIDES IN RAINWATER SAMPLES- 2013 pCi/mL +/- 2 Sigma Roseton Peekskill 23* 44 DATE 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter RADIOCHEMICAL H-3 < 163 < 184 < 184 < 176 < 190 < 185 < 184 < 175 GAMMA Be-7 < 19 <11 < 18 44 +/- 25 39 +/- 24 <9 (a) (a)

K-40 < 12 30 +/- 15 <7 < 21 <8 38 +/- 19 Mn-54 <1 <1 <1 <1 <1 <1 Co-58 <2 <1 <1 <1 <1 <1 Fe-59 <6 <2 <5 <3 <3 <2 Co-60 <1 <1 <1 <1 <1 <0 Zn-65 <3 <1 <2 <2 <2 <1 Nb-95 <2 <1 <2 <1 <1 <1 Zr-95 <4 <2 <4 <2 <2 <2 Ru-103 <3 <2 <2 <2 <2 <1 Ru-106 < 12 <6 <9 <7 <8 <6 1-131 < 77 < 73 < 439 < 85 < 51 < 64 Cs-134 <1 <1 <1 <1 <1 <1 Cs-137 <1 <1 <1 <1 <1 <1 Ba-140 < 61 < 43

• 165 < 50 < 37 < 39 La-140 < 19 <11 < 44 *13 <11 <11 Ce-141 <4 <3 <6 <4 <3 <3 Ce-144 <8 <6 <6 <6 <6 <5 Ra-226 < 23 < 14 < 17 <17 < 17 < 17 Ac-228 <5 <3 <4 <4 <4 <3 Th-228 <2 <2 <1 <2 <1 <1

• Control location (a) Gamma not ordered B-26

INDIAN POINT ENERGY CENTER TABLE B-10 RADIONUCLIDES IN DRINKING WATER SAMPLES - 2013 pCi/liter +/- 2 Sigma Camp Field 7

DATE 1/15/2013 2/11/2013 3/11/2013 4/8/2013 5/13/2013 6/10/2013 RADIOCHEMICAL Gr-B

• 2.5 < 3.2 2.2 +/- 1.4 2.9 +/- 1.2 2.28 +/- 1.38 3.87 +/- 1.41 H-3 (a) < 186 < 166 GAMMA Be-7 < 37 < 44 <31 < 25 < 38.2 < 38.3 K-40

• 36 < 79 < 27 < 22 < 38.7 < 72.4 Mn-54 <3 <4 <4 <3 < 5.0 < 4.3 Co-58 <3 <5 <3 <3 < 4.4 < 4.7 Fe-59 <8 < 11 <7 <6 < 8.4 < 9.7 Co-60 <3 <5 <4 <3 < 4.2 < 4.2 Zn-65 <7 < 10 <6 <5 < 7.7 < 9.7 Nb-95 <4 <5 <4 <3 < 4.0 < 5.3 Zr-95 <6 <9 <6 <5 < 8.7 < 7.7 Ru-103 <4 <5 <4 <3 < 5.2 < 4.7 Ru-106 < 37 < 43 < 35 < 26 < 42.9 < 37.5 1-131 <7 <9 <6 <5 < 9.2 < 8.1 Cs-134 <4 <4 <3 <3 <4.1 < 4.8 Cs-137 <4 <5 <4 <3 < 5.0 < 4.6 Ba-140 <19 < 28 <18 < 14 < 24.3 < 21.9 La-140 <4 <8 <5 <5 < 7.4 < 7.9 Ce-141 <8 <9 <7 <6 < 9.5 < 8.7 Ce-144 < 31 < 33 < 27 < 23 < 34.1 < 35.5 Ra-226 < 103 < 125 < 94 < 82 < 107.4 < 107.6 Ac-228 <18

• 20 < 13 < 12 29.18 +/- 10.44 < 17.9 Th-228 <7 *10 <8 <5 < 8.8 < 9.7 (a) Quarterly composite B-27

INDIAN POINT ENERGY CENTER TABLE B-10 RADIONUCLIDES IN DRINKING WATER SAMPLES - 2013 pCi/liter +/- 2 Sigma Camp Field 7

DATE 7/9/2013 8/19/2013 9/16/2013 10/21/13 11/18/13 12/09/13 RADIOCHEMICAL Gr-B 3.12 +/- 1.14 3.40 +/- 1.60 3.40 +/- 1.53 < 2.9 <3.7 <2.3 H-3 (a) < 170

• 196 GAMMA Be-7 < 34.1 < 36.5 < 54.5 < 21.5

• 34.8 < 45.9 K-40 < 61.9 < 59.0 < 101.5 < 47.4 < 27.6 < 36.6 Mn-54 < 2.8 < 4.3 < 6.3 < 2.5 < 3.3 <4.5 Co-58 < 3.6 < 3.4 < 5.2 < 2.8 <3.6 < 4.5 Fe-59

• 9.0 < 8.9 < 12.8 < 6.0 <7.0

• 10.1 Co-60 < 3.1 < 3.8 <6.1 < 2.8 <3.0 < 4.5 Zn-65 < 6.3 < 8.4 < 12.9 < 5.0 < 6.7 <8.9 Nb-95 < 3.9 < 4.9 <7.1 < 2.9 <3.8 < 5.4 Zr-95 < 5.7 < 7.5 < 10.5 < 4.6 <6.1 <8.7 Ru-103 < 3.8 < 4.6 < 6.8 < 2.9 < 4.4 < 5.3 Ru-106 < 38.6 < 36.8 < 37.8 < 21.6 < 30.7 < 48.3 1-131 < 5.8 < 8.5 < 10.2 < 7.8 < 13.3 < 13.5 Cs- 134 < 3.5 < 3.8 < 5.3 < 2.3 < 3.2 <4.7 Cs-137 < 3.3 <4.1 < 5.4 < 2.7 <3.5 <4.9 Ba-140 < 18.1 < 21.7 < 30.2 < 18.0 < 26.5 < 27.1 La-140

• 6.2 < 7.4 < 11.6 < 6.0 < 7.8 <8.7 Ce-141

• 7.8 < 9.0 < 11.1 < 4.0 < 9.0 < 11.0 Ce-144 < 29.4 < 35.4 < 41.0 < 14.2 < 29.3 < 38.7 Ra-226 < 81.5 < 94.8

• 142.2 < 45.0 < 86.6 < 137.4 Ac-228 < 15.4 < 14.8 < 23.2 < 9.7 < 13.2 < 19.1 Th-228

• 6.7 < 7.0

• 9.0 < 3.9 < 6.6 < 10.7 (a) Quarterly composite B-28

INDIAN POINT ENERGY CENTER TABLE B-10 RADIONUCLIDES IN DRINKING WATER SAMPLES - 2013 pCi/liter +/- 2 Sigma Croton 8

DATE 1/15/2013 2/11/2013 3/11/2013 4/8/2013 5/13/2013 6/10/2013 RADIOCHEMICAL Gr-B 3.15 + 2.0 3.1 +/- 2.0 < 2.1 4.14 +/- 1.5 2.6 +/- 1.4 2.7 +/- 1.3 H-3 (a) < 182.0 < 170.0 GAMMA Be-7 < 37.4 < 40.2 < 42.5 < 27.7 < 49.1 < 36.3 K-40 < 38.3 < 38.8 < 55.4 58.1 +/- 36.1 < 97.1 < 48.8 Mn-54 < 4.3 < 4.0 < 5.5 < 3.0 < 6.5 < 5.1 Co-58 < 4.1 < 4.2 < 5.6 < 3.1 < 6.9 <4.5 Fe-59 < 9.1 < 8.1 < 12.2 < 6.7 < 14.8 < 9.3 Co-60 < 4.0 <4.1 < 5.5 < 2.8 < 6.1 < 4.4 Zn-65 < 9.3 < 6.4 < 9.1 < 5.8 < 13.4 <9.5 Nb-95 < 4.9 < 4.8 < 5.8 < 3.3 < 7.5 < 4.8 Zr-95 < 7.3 < 7.2 < 9.2 < 5.2 < 9.6 < 7.9 Ru-103 < 4.6 < 4.3 < 5.6 < 3.1 < 6.2 <5.1 Ru-106 < 41.9 < 43.2 < 52.1 < 27.6 < 50.4 < 39.3 1-131 < 7.0 < 9.8 < 8.7 < 5.7 < 10.1 <7.7 Cs- 134 < 4.2 < 3.7 < 5.0 < 2.6 < 6.4 < 4.5 Cs-137 < 4.0 < 4.8 < 5.4 < 2.9 < 6.0 < 4.8 Ba-140 < 19.7 < 23.2 < 27.8 < 13.9 < 31.1 < 20.3 La-140 < 6.1 < 7.5 < 8.4 < 5.1 < 8.9 < 7.4 Ce-141 < 8.4 < 9.9 < 7.2 < 5.5 < 11.4 <7.9 Ce-144 < 34.5 < 38.8

• 28.7 < 22.1 < 42.3 < 31.5 Ra-226 < 99.7 < 113.1 < 99.5 < 70.0 < 163.2 < 107.4 Ac-228 < 17.6 < 20.3 < 20.1 < 12.2 < 21.5 < 15.0 Th-228 < 8.1 < 8.7 < 8.8 < 6.5 < 10.8 < 6.7 (a) Quarterly composite B-29

INDIAN POINT ENERGY CENTER TABLE B-10 RADIONUCLIDES IN DRINKING WATER SAMPLES - 2013 pCi/liter +/- 2 Sigma Croton 8

DATE 7/9/2013 8/19/2013 9/16/2013 10/21/13 11/18/13 12/09/13 RADIOCHEMICAL Gr-B 2.9 +/- 1.1 2.5 +/- 1.1 3.1 +/- 1.5

• 2.8 < 2.9

• 2.4 H-3 (a) < 172.0 < 183.0 GAMMA Be-7 < 39.1 < 47.6 < 54.5 < 17.8 < 32.7 < 58.2 K-40 < 55.6 < 50.3 < 108.5 < 37.6 < 22.8 < 58.7 Mn-54 < 4.9 < 4.5 < 5.6 < 1.8

• 3.2

• 7.8 Co-58

• 4.6 < 5.7 < 4.8 <2.1 < 3.5 *6.5 Fe-59 < 11.0 < 11.9 < 9.6 < 4.2 < 7.5 < 16.6 Co-60

• 5.0 <7.1 < 5.9

• 2.0

• 3.0

• 8.3 Zn-65

• 9.6 < 9.5 < 10.4 < 3.9

• 5.8 < 13.5 Nb-95 < 4.5 < 6.3 <6.1 *2.1

• 3.8

• 7.8 Zr-95 <8.1 < 9.6 < 9.0 < 3.7

• 6.7 < 14.8 Ru-103

• 5.2 < 5.5 <6.1

• 2.5 < 4.4 < 7.7 Ru-106 < 34.9 < 45.0 < 51.9 < 17.9 < 31.0 < 60.6 1-131 < 7.7 < 10.2 < 10.3

• 6.6 < 13.7 < 14.2 Cs- 134 < 4.2 < 4.0 < 6.4

• 1.8 < 3.3

• 6.2 Cs-137 <5.1 <5.1 < 6.6

• 1.9

• 3.6 < 6.2 Ba-140 < 20.7 < 24.7 < 28.4 < 14.1 < 27.9 < 39.9 La-140 < 5.5 < 7.2 < 6.3 < 4.9

• 8.0 < 12.0 Ce-141

• 8.3 < 8.8 < 12.6 < 4.4 <9.1 < 10.7 Ce-144 < 30.9 < 36.0 < 51.4 < 14.8 < 31.4 < 34.6 Ra-226 < 113.9 < 120.4 < 169.5 < 51.8 < 91.9 < 135.8 Ac-228 < 17.5 < 21.7 < 20.1 < 7.4 < 13.1 < 28.8 Th-228 < 9.5 < 9.4 < 12.8

• 4.0

• 7.6 < 11.0 (a) Quarterly composite B-30

INDIAN POINT ENERGY CENTER TABLE B-11 RADIONUCLIDES IN GROUNDWATER SAMPLES - 2013 pCi/liter +/- 2 Sigma Lafarge Monitoring Well 106 DATE 5/24/2013 11/26/2013 RADIOCHEMICAL H-3 < 383 < 392 Ni-63 < 17.5 < 16.3 Sr-90 < 1.89 < 1.88 GAMMA Be-7

• 121 < 75 K-40

• 101 < 128 Mn-54 <11 < 10 Co-58

• 14 <9 Fe-59 < 27 < 26 Co-60 <10 <10 Zn-65

• 20

• 24 Nb-95 *13 <11 Zr-95

• 23

• 18 Ru-106

• 92 < 73 Cs-134 <12 < 10 Cs-137 <11 <9 Ba-140

• 64 (a) < 41 La-140

• 64 (a) < 41 (a)

Ce-141

• 27 < 20 Ce-144

• 58 < 46 Ac-228 < 39 < 31 (a) LLD not met due to age of sample B-31

INDIAN POINT ENERGY CENTER TABLE B-12 GAMMA EMITTERS IN SOIL SAMPLES, 2013 pCi/kg dry +/- 2 Sigma Roseton Training Building Met Tower 23* 94 95 DATE 9/23/2013 9/23/2013 9/23/2013 Be-7 < 517 411 +/- 248 < 426 K-40 19780 +/- 1180 6758 +/- 607 11920 +/- 1034 Mn-54 < 45 < 26 < 36 Co-58 < 52 < 35 < 44 Fe-59 < 129 < 80 < 114 Co-60 < 58 < 36 < 42 Zn-65 < 102 < 73 < 103 Nb-95 < 62 < 39 < 54 Zr-95 < 95 < 61 < 80 Ru-103 < 58 < 39 < 48 Ru-1 06 < 411 < 251 < 342 1-131 < 335 < 243 < 296 Cs- 134 < 43 < 26 < 34 Cs-1 37 < 46 < 29 < 41 Ba-140 < 545 < 333 < 495 La-140 < 155 < 116 < 78 Ce-141 < 112 < 68 < 89 Ce-144 < 295 < 179 < 237 Ra-226 1350 +/- 897 < 649 < 766 Th-228 1135 +/- 75 178 +/- 40 224 +/- 47

• Control location B-32

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2013 pCi/kg wet +/- 2 Sigma Roseton 23*

DATE 04/29/13 05/20/13 05/20/13 05/20/13 06/17/13 06/17/13 07/15/13 RADIOCHEMICAL 1-131 (a) < 27 GAMMA Be-7 685 +/- 209 476 +/- 163 369 +/- 156 576 +/- 203 1966 +/- 185 991 +/- 237 1877 +/- 227 K-40 4104 +/- 436 3269 +/- 326 5780 +/- 506 5515 +/- 547 7447 +/- 458 3920 +/- 487 4674 +/- 444 Mn-54 < 16 <11 <19 < 26 <15 <21 <21 Co-58 <19

• 14 < 22 < 26 < 13 < 22 <19 Fe-59 <51

• 28 < 46 <51 < 35 < 58 < 49 Co-60 <21

• 19 < 26 < 30 < 18 < 27 < 23 Zn-65 < 42 < 33 < 44 < 51 < 40 < 39 < 50 Nb-95 <18 < 15 < 20 < 24 < 15 < 25 < 22 Zr-95 < 32 < 23 < 35 < 38 < 29 < 39 < 32 Ru-103 <15 < 14 < 19 < 26 < 16 < 25 < 20 Ru-106 < 137 < 116 < 163 < 198 < 134 < 192 < 203 1-131 < 36 < 28 < 39 < 50 < 32 < 47 < 37 Cs-134 <16 < 13 < 16 <21 < 12 < 20 < 22 Cs-137 <18 < 13 < 18 < 27 <14 < 22 < 23 Ba-140 < 89 < 77 < 106 < 141 < 77 <91 < 109 La-140 < 23 < 19 < 33 < 30 < 20 < 30 < 29 Ce-141 < 25 < 24 < 28 < 43 < 30 < 41 < 33 Ce-144 < 98 < 88 < 101 < 174 < 103 < 155 < 127 Ra-226 < 407

• 341 < 396 < 549 < 333 < 537 < 460 Th-228 < 29

• 22 < 32 < 43 < 30 < 44 < 42

• Control location (a) Iodine-131 by low level analysis B-33

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2013 pCi/kg wet +/- 2 Sigma Roseton 23*

DATE 07/15/13 07/15/13 07/15/13 08/12/13 08/12/13 08/12/13 09/09/13 RADIOCHEMICAL 1-131 (a)

GAMMA Be-7 918 +/- 187 1441 +/- 194 637 +/- 205 1508 +/- 233 2497 +/- 264 2813 +/- 259 2804 +/- 222 K-40 2099 +/- 330 8351 +/- 542 3124 +/- 434 5846 +/- 474 4791 +/- 477 4984 +/- 393 6112 +/- 394 Mn-54 <17 <18 <17 <15 < 22 < 17 < 16 Co-58 < 14 <21 <19 <15 < 20 < 16 < 16 Fe-59 < 26 < 42 < 49 < 41 < 54 < 37 < 40 Co-60 <18 < 24 < 24 < 22 < 25 < 19 < 18 Zn-65 < 39 < 46 < 43 < 38 < 49 < 36 < 36 Nb-95 <17 < 19 <21 <15 < 23 < 18 < 16 Zr-95 < 32 < 32 < 38 < 25 < 39 < 31 < 30 Ru-103 < 20 < 18 <19 <16 < 22 < 16 < 18 Ru-106 < 127 < 170 < 170 < 132 < 157 < 144 < 156 1-131 < 32 < 38 < 48 < 37 < 47 < 41 < 39 Cs-134 <16 < 17 < 19 <15 < 20 < 14 < 17 Cs-137 <18 <19 <21 <17 < 18 < 16 < 15 Ba-140 < 93 < 86 < 111 < 96 < 117 < 94 < 99 La-140 < 24 < 27

• 36 < 24 < 29 < 27 < 21 Ce-141 < 30 < 33

• 36 < 25 < 29 < 30 < 34 Ce-144 < 112 < 109

• 137 < 94 < 98 < 109 < 130 Ra-226 < 381 < 389

• 486 < 317 < 411 < 368 < 421 Th-228 < 29 < 37

• 36 < 28 < 32 < 29 < 30

• Control location (a) Iodine-131 by low level analysis B-34

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2013 pCi/kg wet +/- 2 Sigma Roseton 23*

DATE 09/09/13 09/09/13 10/07/13 10/07/13 10/07/13 RADIOCHEMICAL 1-131 (a)

GAMMA Be-7 2052 +/- 138 2854 +/- 230 2851 +/- 238 1768 +/- 144 863 +/- 140 K-40 2472 +/- 199 4260 +/- 342 6335 +/- 365 4236 +/- 249 3680 +/- 231 Mn-54 <10 < 14 < 13 < 11 < 10 Co-58 <11 < 16 < 15

• 12 <11 Fe-59 < 20 < 33 < 34

• 30 < 26 Co-60 <11 < 21 < 15

• 14 <11 Zn-65 <21 < 37 < 28

• 26 <21 Nb-95 <11 < 17 < 15

• 13 *12 Zr-95 *18 < 29 < 27

• 21 <21 Ru-103 *13 < 17 < 18

• 13 <13 Ru-106

• 100 < 133 < 109 < 94

• 88 1-131

• 28 < 37 < 58 < 59

• 58 Cs-134 *10 < 14 < 12 < 10 <9 Cs-137 <11 < 18 < 14 < 10 <11 Ba-140

• 65 < 87 < 116 < 105 < 106 La-140 *15 < 21 < 31 < 27 < 25 Ce-141

• 24 < 25 < 28 < 25 < 21 Ce-144 *91 < 99 < 86 < 72 < 66 Ra-226 <311 < 347 < 288 < 270 < 236 Th-228 *21 < 26 < 23 < 21 41 +/- 18

• Control location (a) Iodine-131 by low level analysis B-35

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2013 pCi/kg wet +/- 2 Sigma Training Center 94 DATE 04/29/13 04/29/13 04/29/13 05/20/13 05/20/13 05/20/13 06/17/13 RADIOCHEMICAL 1-131 (a) < 37 < 44 < 37 GAMMA Be-7 746 +/- 220 377 +/- 198 256 +/- 134 1214 +/- 252 502 +/- 147 1350 +/- 208 844 +/- 174 K-40 3743 +/- 512 5528 +/- 548 3802 +/- 434 3106 +/- 469 4577 +/- 388 5971 +/- 622 4472 +/- 410 Mn-54 < 23 < 24 <18 < 22 < 17 < 27 <17 Co-58 < 23 < 24 <17 < 20 < 16 < 26 < 17 Fe-59 < 54 < 63 < 43 < 43 < 40 < 66 < 37 Co-60 <31 < 30 *21 < 24 <21 < 29 < 23 Z-n-65 < 50 < 54

• 46 < 49 < 34 < 65 < 39 Nb-95 < 27 < 24 <21 < 20 <17 < 30 <19 Zr-95 < 38 < 45 < 37 < 36 < 32 < 47 < 30 Ru-103 < 28 < 28

• 20 < 22 <18 < 25 <18 Ru-106 < 182 < 195

• 180 < 189 < 150 < 237 < 158 1-131 < 58 < 50

• 40 < 44 < 36 < 56 < 34 Cs-134 < 24 < 21

• 16 < 20 < 14 < 22 < 16 Cs-137 < 27 < 25

• 19 < 20 <18 < 26 < 20 Ba-140 < 130 < 122 < 109 < 109 <91 < 131 < 92 La-140 < 47 < 42

• 25 < 34 < 26 < 43 < 29 Ce-141 < 50 < 34

• 27 < 36 < 32 < 33 < 25 Ce-144 < 172 < 117

• 100 < 132 < 113 < 125 < 88 Ra-226 < 597 < 486

• 415 < 438 < 408 < 505 < 300 Th-228 < 40 < 38 < 33 < 33 < 34 <41 < 29 (a) Iodine-131 by low level analysis B-36

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2013 pCi/kg wet +/- 2 Sigma Training Center 94 DATE 06/17/13 06/17/13 07/15/13 07/15/13 07/15/13 07/15/13 08/12/13 RADIOCHEMICAL 1-131 (a)

GAMMA Be-7 844 +/- 174 2123 + 233 1638 +/- 279 1223 +/- 255 765 + 182 440 +/- 250 2567 +/- 205 K-40 4472 +/- 410 6208 +/- 451 4427 +/- 509 8275 +/- 678 3515 + 386 6297 +/- 678 7170 +/- 442 Mn-54 <17 <17 <21 < 24 < 17 < 27 < 15 Co-58 <17 < 17 < 23 < 24 < 17 < 27 < 16 Fe-59 < 37

• 41 < 54 < 61 < 37 < 66 < 38 Co-60 < 23 <21 < 29 < 30 < 25 < 34 <19 Zn-65 < 39

• 40 < 46 < 55 < 38 < 69 < 36 Nb-95 < 19 < 17 < 19 < 23 < 17 < 29 <15 Zr-95 < 30 < 33 < 40 < 44 < 35 < 52 < 29 Ru-103 < 18 <19 < 25 < 27 < 20 < 29 < 18 Ru-106 < 158

• 129 < 211 < 192 < 163 < 229 < 139 1-131 < 34

• 38 < 49 < 51 < 37 < 56 < 40 Cs-134 < 16

• 15 < 21 < 22 <15 < 23 < 14 Cs-137 < 20

• 17 < 21 < 22 <19 < 24 < 18 Ba-140 < 92

• 98 < 129 < 128

• 96 < 168 < 85 La-140 < 29

• 22 < 36 < 25 <31 < 45 < 21 Ce-141 < 25 < 33 < 34 < 43

• 31 < 39 < 35 Ce-144 < 88 < 124 < 131 < 166

• 110 < 148 < 132 Ra-226 < 300 < 415 < 468 < 550

• 403 < 600 < 386 Th-228 < 29 < 33 < 41 < 43 < 33 < 45 < 29 (a) Iodine-131 by low level analysis B-37

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2013 pCi/kg wet +/- 2 Sigma Training Center 94 DATE 08/12/13 08/13/13 09/10/13 09/10/13 09/10/13 10/07/13 10/07/13 RADIOCHEMICAL 1-131 (a)

GAMMA Be-7 1619 +/- 266 1110 +/- 232 1944 +/- 246 2397 +/- 179 1093 +/- 263 940 +/- 128 959 +/- 146 K-40 3463 +/- 445 1869 +/- 329 6442 +/- 473 2196 +/- 270 3886 +/- 535 4251 +/- 271 4771 +/- 331 Mn-54 < 22 < 15 < 17 <17 < 26 < 10 < 15 Co-58 < 22 <16 <16 < 16 < 24 < 12 < 16 Fe-59 < 48 < 38 < 39 < 34 < 47 < 28 < 35 Co-60 < 26 < 20 < 24 <18 < 24 < 14 < 15 Zn-65 < 52 < 36 < 40 < 34 < 55 < 26 < 30 Nb-95 < 24 <21 < 17 < 17 < 25 < 13 < 15 Zr-95 < 45 < 27 <31 < 28 < 41 < 22 < 23 Ru-103 < 22 < 19 < 20 < 17 < 28 < 13 < 16 Ru-106 < 211 < 174 < 143 < 141 < 222 < 100 < 113 1-131 < 51 < 43 < 38 < 35 < 58 < 59 < 57 Cs-134 < 20 < 16 <17 <15 < 21 < 10 < 12 Cs-137 < 24 < 17 < 16 < 16 < 25 < 10 < 13 Ba-140 < 98 < 100 < 107 < 90 < 147 < 110 < 111 La-140 < 32 < 25 <21 < 27 < 32 < 31 < 30 Ce-141 < 39 < 36 < 34 < 25 < 51 < 23 < 30 Ce-144 < 132 < 132 < 121 < 95 < 186 < 69 < 92 Ra-226 < 458 < 404 < 480 < 380 < 662 < 259 < 334 Th-228 < 32 < 34 < 31 < 25 < 50 < 22 < 27 (a) lodine-131 by low level analysis B-38

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2013 pCi/kg wet +/- 2 Sigma Met Tower 95 DATE 4/29/2013 4/29/2013 4/29/2013 5/20/2013 5/20/2013 5/20/2013 6/17/2013 RADIOCHEMICAL 1-131 (a) < 28 < 36 < 41 GAMMA Be-7 454 +/- 226 < 175 617 +/- 182 1267 +/- 227 494 +/- 193 804 +/- 245 589 +/- 182 K-40 6589 +/- 550 5624 +/- 381 3750 +/- 435 6888 +/- 574 3920 + 412 3180 +/- 435 4299 +/- 386 Mn-54 < 24 <17 <21 < 22 *16 < 19 < 17 Co-58 < 25 < 17 < 20 <21 *19

• 24 < 18 Fe-59 < 56 < 40 < 46 < 44 < 39 < 49 < 39 Co-60 < 30 < 20 < 24 < 25

• 20

• 27 <21 Zn-65 < 50 < 37 < 56 < 43 < 42

• 48 < 41 Nb-95 < 30 < 19 < 24 < 24 *18

• 22 < 17 Zr-95 < 45 < 32 < 40 < 38 < 35 < 43 < 34 Ru-103 < 27 < 19 < 26 <19 *21

• 23 < 17 Ru-106 < 213 < 161 < 226 < 142

• 155

• 199 < 174 1-131 < 59 < 41 < 56 < 42 < 34 < 55 < 35 Cs-134 < 24 < 18 < 20 <18

• 17

• 25 <17 Cs-137 < 25 <18 < 26 <17 *19

• 23 < 19 Ba-140 < 142 < 99 < 113 < 117

• 114

• 129 < 98 La-140 < 37 < 24 < 26 <17

• 31

• 26 < 22 Ce-141 < 52 < 34 < 41 < 35

• 31 < 46 < 30 Ce-144 < 181 < 128 < 152 < 131 < 111

• 167 < 115 Ra-226 < 617 < 390 < 531 < 453

• 438

• 561 < 440 Th-228 < 49 < 34 < 37 < 32

• 28 <41 < 29 (a) Iodine-131 by low level analysis B-39

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2013 pCi/kg wet +/- 2 Sigma Met Tower 95 DATE 6/17/2013 6/17/2013 7/15/2013 7/15/2013 7/15/2013 8/12/2013 8/12/2013 RADIOCHEMICAL 1-131 (a)

GAMMA Be-7 1013 +/- 237 2362 +/- 227 1316 +/- 318 650 +/- 169 995 +/- 203 2867 +/- 299 2416 +/- 222 K-40 3859 +/- 428 8023 +/- 483 7074 +/- 632 3409 +/- 384 4587 +/- 475 6469 +/- 496 10160 +/- 494 Mn-54

• 18

• 15 < 29 < 20

• 20 < 20

• 18 Co-58

• 21

• 15 < 26 < 19

• 24 < 18

• 18 Fe-59 < 39

• 41 < 70 < 41

• 46 < 47 < 43 Co-60 < 20

• 20 < 33 < 21

• 26 < 27 < 25 Zn-65 < 45

• 36 < 67 < 45 < 52 < 45

• 41 Nb-95

• 19

• 18 < 29 < 20

• 22

• 19

• 17 Zr-95 < 40

• 25 < 44 < 32

• 41

• 32 < 34 Ru-103 < 23

• 16 < 26 < 21

• 25

• 19

• 19 Ru-106

• 201

• 138 < 202 < 152

• 210

• 163

• 164 1-131

• 48 < 34 < 46 < 42

• 48

• 48 < 44 Cs-134

• 21 < 16 < 23 < 18

• 19

• 17

• 16 Cs-137

• 22

• 13 < 24 < 18

• 23

• 18

• 17 Ba-140

• 123

• 88 < 124 < 108

• 131

• 112

• 104 La-140

• 25

• 12 < 44 < 21

• 22

• 27 < 25 Ce-141 < 45

• 29 < 31 < 30

• 40 < 37 < 33 Ce-144

• 166

• 101 < 119 < 113

• 149

• 131 < 123 Ra-226

• 578 < 411 < 411 < 412 < 554

• 438 < 434 Th-228 < 47

• 32 < 39 < 36 < 37 < 33 < 31 (a) lodine-131 by low level analysis B-40

INDIAN POINT ENERGY CENTER TABLE B-13 GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2013 pCi/kg wet +/- 2 Sigma Met Tower 95 DATE 8/12/2013 8/12/2013 9/10/2013 9/10/2013 9/10/2013 10/9/2012 10/9/2012 RADIOCHEMICAL 1-131 (a)

GAMMA Be-7 2867 +/- 299 2416 +/- 222 1354 +/- 259 1684 +/- 216 930 +/- 127 1471 +/- 350 2295 +/- 174 K-40 6469 +/- 496 10160 +/- 494 3384 +/- 436 5181 +/- 480 5503 +/- 300 5022 +/- 755 2688 +/- 278 Mn-54 < 20 <18 <17 < 18 <12 < 28 <13 Co-58 <18 <18 < 22 < 20 <12 < 30 < 14 Fe-59 < 47 < 43 < 44 < 48 < 26 < 73 < 30 Co-60 < 27 < 25 < 25 < 27 <12 < 33 < 15 Zn-65 < 45 < 41 < 50 < 45 < 24 < 77 < 28 Nb-95 <19 <17 < 24 < 20 <12 < 25 < 15 Zr-95 < 32 < 34 < 37 < 35 < 22 < 59 < 25 Ru-103 <19 <19 < 24 < 20 <11 < 30 < 15 Ru-106 < 163 < 164 < 177 < 174 < 99 < 241 < 132 1-131 < 48 < 44 < 52 < 41 < 23 < 59 < 31 Cs-134 <17 < 16 < 19 <19 < 11 < 25 < 14 Cs-137 <18 <17 <21 < 20 < 12 < 27 < 14 Ba-140 < 112 < 104 < 122 < 116 < 62 < 162 < 78 La-140 < 27 < 25 < 29 < 27 *19 < 53 < 23 Ce-141 < 37 < 33 < 39 < 32 *15 < 45 < 25 Ce-144 < 131 < 123 < 137 < 114 < 54 < 170 < 91 Ra-226 < 438 < 434 < 564 < 450 < 195 < 664 < 352 Th-228 < 33 <31 < 37 < 32 < 20 37 +/- 48 35 +/- 19 (a) lodine-131 by low level analysis B-41

INDIAN POINT ENERGY CENTER TABLE B-14 RADIONUCLIDES IN RIVER WATER SAMPLES - 2013 pCi/liter +/- 2 Sigma Plant Inlet Hudson River Intake 9*

DATE 1/28/2013 2/25/2013 3/25/2013 4/29/2013 5/28/2013 6/24/2013 RADIOCHEMICAL H-3 (a)

• 176

• 171 216 +/- 126 < 168 < 174

• 185 H-3, Quarterly 266 +/- 119

• 171 GAMMA K-40

• 29 <18 < 16 < 12 < 14 < 12 Mn-54 <4 <2 <2 <1 <2 <1 Co-58 <5 <2 <2 <2 <2 <1 Fe-59 < 10 <6 <4 <3 <4 <3 Co-60 <4 <2 <2 <1 <2 <2 Zn-65 <9 <4 <3 <3 <3 <3 Nb-95 <5 <2 <2 <2 <2 <2 Zr-95 <8 <4 <3 <3 <3 <3 Ru-103 <6 <3 <2 <2 <2 <2 Ru-106 < 37 < 18 *15 < 12 < 15 <12 1-131 < 45 < 13 <10 <12 < 12 <9 Cs- 134 <4 <2 <1 <1 <1 <1 Cs-137 <4 <2 <2 <1 <2 <1 Ba-140 < 55 < 22 <19 < 18 < 19 < 15 La-140 < 23 <7 <6 <6 <6 <5 Ce-141 *13 <5 <4 <4 <5 <3 Ce-144 < 35 < 16

• 12 < 11 < 14 <9 Ra-226

• 120 < 52

• 40 < 30 < 41 57 +/- 31 Ac-228 <17 <6 <7 <5 <6 <5 Th-228 <7 7+/-4 <3 4+/-2 <3 <2

• Control location (a) Quarterly composite B-42

INDIAN POINT ENERGY CENTER TABLE B-14 RADIONUCLIDES IN RIVER WATER SAMPLES - 2013 pCi/liter +/- 2 Sigma Plant Inlet Hudson River Intake 9,

DATE 7/29/2013 8/27/2013 10/1/2013 10/29/2013 12/2/2013 12/30/2013 RADIOCHEMICAL H-3 (a)

H-3, Quarterly < 186 < 192 GAMMA K-40 < 13 < 15 55 < 25 57 +/- 29 48 +/- 31 <31 Mn-54 <1 <2 <2 <2 <1 <2 Co-58 <2 <2 <2 <2 <1 <2 Fe-59 <4 <4 <5 <5 <3 <4 Co-60 <1 <2 <2 <2 <1 <2 Zn-65 <3 <3 <4 <4 <2 <3 Nb-95 <2 <2 <2 <2 <2 <2 Zr-95 <3 <4 <4 <4 <3 <4 Ru-103 <2 <3 <3 <3 <2 <3 Ru-106 < 13 < 16 < 16 < 17 < 10 <17 1-131 < 11 < 14 < 15 < 12 < 12 < 14 Cs- 134 <1 <2 <2 <2 <1 <2 Cs-137 <1 <2 <2 <2 <1 <2 Ba-140 < 18 < 21 < 22 < 21 < 19 < 22 La-140 <6 <7 <7 <7 <5 <6 Ce-141 <4 <5 <4 <5 <4 <6 Ce-144

• 10

• 15 <12

• 16 < 10 < 17 Ra-226 < 31 < 45 < 38 < 46 < 35 < 48 Ac-228 <4 <7 <7 <8 <7 <7 Th-228 <3 4+/-3 <3 <4 <3 <4

• Control location (a) Quarterly composite B-43

INDIAN POINT ENERGY CENTER TABLE B-14 RADIONUCLIDES IN RIVER WATER SAMPLES - 2013 pCi/liter +/- 2 Sigma Discharge Canal 10 DATE 1/2812013 2/25/2013 3/25/2013 4/29/2013 5/28/2013 6/24/2013 RADIOCHEMICAL H-3 (a) < 178

• 183 566 +/- 142 < 171 < 177 < 183 H-3, Quarterly 357 +/- 126 < 170 GAMMA K-40 < 32

• 16 44 +/- 21 101 +/- 30 *14 < 17 Mn-54 <4 <2 <1 <2 <1 <2 Co-58 <6 <2 <2 <2 <2 <2 Fe-59 < 12 <5 <4 <4 <4 <5 Co-60 <5 <2 <2 <2 <2 <2 Zn-65 <9 <4 <3 <3 <3 <4 Nb-95 <5 <2 <2 <2 <2 <2 Zr-95 <8 <4 <3 <3 <3 <4 Ru-103 <7 <3 <2 <2 <2 <3 Ru-106 < 38 < 18 < 14 *14 < 13 *17 1-131 < 42 < 14 <8 *15

• 10 *12 Cs-134 <4 <2 <1 <1 <1 <2 Cs-137 <4 <2 <2 <2 <2 <2 Ba-140 < 67 < 22 < 14 <21 < 17 < 21 La-140 < 20 <7 <4 <6 <5 <6 Ce-141 <12 <5 <4 <6 <4 <4 Ce-144 < 35 < 17 <12 <17 <10 < 11 Ra-226

• 110 < 46

• 36

• 48 < 33 < 38 Ac-228

• 15 <8 <6 <7 <7 10 t 6 Th-228 <8 <4 <3 <3 <3 <3 (a) Quarterly composite B-44

INDIAN POINT ENERGY CENTER TABLE B-14 RADIONUCLIDES IN RIVER WATER SAMPLES - 2013 pCi/liter +/- 2 Sigma Discharge Canal 10 DATE 7/29/2013 8/27/2013 10/1/2013 10/29/2013 12/2/2013 12/30/2013 RADIOCHEMICAL H-3 (a)

H-3, Quarterly < 186 306 t 137 GAMMA K-40 < 14 < 33 65 +/- 28 <16 < 35 < 33 Mn-54 <2 <2 <1 <2 <1 <2 Co-58 <2 <2 <2 <2 <2 <2 Fe-59 <5 <4 <4 <4 <3 <4 Co-60 <2 <2 <1 <2 <1 <2 Zn-65 <3 <3 <3 <4 <2 <3 Nb-95 <2 <2 <2 <2 <2 <2 Zr-95 <4 <3 <3 <3 <3 <3 Ru-103 <3 <2 <2 <2 <2 <2 Ru-106 < 16 < 16 < 14 < 16 < 12 < 15 1-131 < 15 < 13 < 14 < 11 < 11 < 13 Cs-134 <2 <2 <1 <2 <1 <2 Cs-1 37 <2 <2 <2 <2 <1 <2 Ba-140 < 23 < 22 < 20 < 18 < 15 < 21 La-140 <7 <7 <6 <6 <4 <7 Ce-141 <5 <5 <4 <4 <4 <5 Ce-144 < 14 < 13 < 11 < 14 <9 < 13 Ra-226 < 40 < 46 < 34 < 46 < 34 < 37 Ac-228 <7 <6 <7 <6 <5 <7 Th-228 <3 <4 <3 <4 <3 <3 (a) Quarterly composite B-45

INDIAN POINT ENERGY CENTER TABLE B-15 GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2013 pCi/kg dry +/- 2 Sigma Discharge Canal Off Verplanck 10 17 DATE 6/19/2013 9/10/2013 9/10/2013 10/9/2013 6/19/2013 9/10/2013 10/9/2013 Be-7 < 713 < 1157 < 1351 < 1194 < 814 < 623 < 565 K-40 15370 +/- 1260 26550 +/- 2319 20610 +/- 2405 24030 +/- 1765 20790 +/- 1837 22730 +/- 1874 14550 +/- 1814 Mn-54 < 83 < 85 < 98 < 76 < 83 < 75 < 61 Co-58 < 90 < 92 < 79 < 72 < 83 < 73 < 32 Fe-59 < 208 < 225 < 212 < 196 < 223 < 155 < 121 Co-60 < 103 < 109 < 113 < 103 < 90 < 87 < 65 Zn-65 < 232 < 199 < 263 < 182 < 187 < 157 < 130 Nb-95 < 95 < 102 < 111 < 89 < 93 < 89 < 59 Zr-95 < 168 < 181 < 191 < 145 < 173 < 116 < 134 Ru-103 < 100 < 124 < 134 < 138 < 102 < 72 < 71 Ru-106 < 698 < 757 < 893 < 774 < 639 < 559 < 478 1-131 < 418 < 427 < 411 < 411 < 438 < 213 < 265 Cs-134 < 100 < 87 < 93 < 83 < 72 < 56 e 60 Cs-137 153 +/- 47 6171 +/- 270 5609 +/- 315 13870 +/- 340 326 +/- 84 272 +/- 77 156 +/- 67 Ba-140 < 790 < 794 < 766 < 769 < 766 < 384 < 476 Ce-141 < 148 < 184 < 201 < 153 < 165 < 120 < 119 Ce-144 < 449 < 578 < 680 < 514 < 498 < 407 < 368 Ra-226 < 1657 3328 +/- 1642 < 2932 4051 +/- 1393 3510 < 1660 2128 +/- 1210 < 1268 Th-228 1038 +/- 89 1491 +/- 168 988 +/- 299 1355 +/- 128 1382 +/- 127 1275 +/- 119 808 +/- 128 B-46

INDIAN POINT ENERGY CENTER TABLE B-15 GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2013 pCi/kg dry +/- 2 Sigma Lent's Cove Cold Sprng 28 84*

DATE 6/12/2013 9/9/2013 10/9/2013 6/12/2013 9/9/2013 10/9/2013 Be-7 < 1063 < 819 < 992 < 996 < 992 < 545 K-40 18550 +/- 1641 18420 +/- 1930 17400 +/- 2214 21300 +/- 2138 26470 +/- 2214 21700 +/- 1573 Mn-54 < 99 < 85 < 107 < 104 < 107 < 54 Co-58 < 95 < 78 < 94 < 123 < 94 < 57 Fe-59 < 229 < 170 < 278 < 341 < 278 < 170 Co-60 < 95 < 83 < 113 < 121 <113 < 73 Zn-65 < 182 < 197 < 241 < 215 < 241 < 129 Nb-95 < 120 < 101 < 144 < 136 < 144 < 67 Zr-95 < 201 < 157 < 218 < 242 < 218 < 111 Ru-103 < 123 < 91 < 126 < 140 < 126 <71 Ru-106 < 804 < 595 < 863 < 955 < 863 < 476 1-131 < 957 < 264 < 400 < 1425 < 400 < 302 Cs-134 < 87 < 73 < 92 < 84 < 92 < 51 Cs-1 37 232 < 69 273 +/- 84 321 +/- 124 348 < 82 +/- 124 179 +/- 59 Ba-140 < 1365 < 684 < 898 < 1635

• 898 < 592 Ce-141 < 235 < 166 < 226 < 207

• 226 < 121 Ce-144 < 627 < 557 < 761 < 484

• 761 < 355 Ra-226 < 1918 < 2083 < 2270 < 1558 < 2270 2757 +/- 886 Th-228 939 +/- 138 1146 +/- 124 1134 +/- 173 1215 +/- 132 1779 +/- 173 1521 +/- 125

• Control location B-46 0-

INDIAN POINT ENERGY CENTER TABLE B-16 RADIONUCLIDES IN SHORELINE SEDIMENT SAMPLES - 2013 pCi/kg dry +/- 2 Sigma Off Verplanck Lent's Cove Manitou Inlet 17 28 50 DATE 6/19/2013 9/10/2013 6/12/2013 9/9/2013 6/12/2013 9/9/2013 RADIOCHEMICAL Sr-90 < 35 < 46 < 43 < 48 < 27 < 41 GAMMA Be-7 < 486 < 496 < 786 < 654 < 954 < 525 K-40 18010 +/- 1307 18580 +/- 1388 13660 +/- 1350 14340 +/- 1415 14600 +/- 1398 13300 +/- 1188 Mn-54 < 48 < 59 <71 < 78 < 98 < 56 Co-58 < 53 < 58 < 70 < 73 < 114 < 69 Fe-59 < 136 < 129 < 214 < 153 < 281 < 145 Co-60 < 60 < 62 < 90 < 73 < 105 < 67 Zn-65 < 119 < 118 < 137 < 151 < 300 < 134 Nb-95 < 59 < 66 < 101 < 93 < 117 < 94 Zr-95 < 99 < 107 < 149 < 139 < 191 < 113 Ru-103 < 55 < 64 < 87 < 85 < 125 < 63 Ru-106 < 440 < 504 < 517 < 608 < 753 < 467 1-131 < 243 < 175 < 575 < 271 < 803 < 194 Cs-134 <41 < 50 < 59 < 69 < 138 < 59 Cs-137 108 +/- 53 158 +/- 55 < 74 < 84 < 101 < 61 Ba-140 < 418 < 395 < 881 < 545 < 1245 < 463 La-140 < 144 < 95 < 276 < 140 < 381 < 152 Ce-141 < 99 < 110 < 143 < 156 < 199 < 117 Ce-144 < 287 < 368 < 388 < 545 < 521 < 374 Ra-226 < 892 < 1161 3503 +/- 1406 2845 < 1385 1696 +/- 1017 6160 +/- 1320 Ac-228 < 317 < 338 < 249 < 455 < 469 < 208 Th-228 798 +/- 72 696 +/- 85 1558 +/- 117 1171 +/- 117 806 +/- 90 628 +/- 79 B-47

INDIAN POINT ENERGY CENTER TABLE B-16 RADIONUCLIDES IN SHORELINE SEDIMENT SAMPLES - 2013 pCi/kg dry +/- 2 Sigma White Beach Cold Spring 53 84*

DATE 6/19/2013 9/10/2013 6/12/2013 9/10/2013 RADIOCHEMICAL Sr-90 < 33 < 43 < 28 < 50 GAMMA Be-7 < 296 < 327 < 390 < 285 K-40 11350 +/- 967 10900+/- 1009 40330 +/- 1539 18110 +/- 1340 Mn-54 <31 < 34 < 45 < 35 Co-58 < 29 < 40 < 47 < 33 Fe-59 < 66

• 101 < 139 < 102 Co-60 < 40 < 47 < 59 < 46 Zn-65 < 74 <91 < 120 < 98 Nb-95 < 32

• 38 < 53 < 34 Zr-95 < 59 < 77 < 93 < 69 Ru-103 < 38 < 40 < 56 < 31 Ru-106 < 226 < 340 < 357 < 247 1-131 < 155 < 95 < 370 < 105 Cs-134 < 25 *31 < 36 < 27 Cs-137 < 31

• 40 < 45 < 37 Ba-140 < 281 < 210 < 568 < 185 La-140 < 65

• 62 < 115 < 56 Ce-141 < 65

• 69 < 84 < 56 Ce-144 < 192 228 < 221 < 193 Ra-226 < 770 + 683 1229 +/- 747 < 711 Ac-228 < 105 < 182 < 240 < 222 Th-228 110 +/- 46 93 +/- 48 560 +/- 54 324 +/- 70

• Control location B-48

INDIAN POINT ENERGY CENTER TABLE B-17 GAMMA EMITTERS IN AQUATIC VEGETATION SAMPLES - 2013 pCi/kg wet +/- 2 Sigma Off Verplanck Cold Spring 17 84*

DATE 6/19/2013 9/10/2013 6/12/2013 9/9/2013 Myrophyllium Myrophyllium Myrophyllium Myrophyllium Be-7 408 +/- 63 190 +/- 74 186 +/- 51 180 +/- 83 K-40 2574 +/- 127 2243 +/- 170 1512 +/- 98 2224 +/- 170 Mn-54 < 7 < 7 < 5 < 9 Co-58 <7 < 8 <6 < 11 Fe-59 < 15 < 18 < 15 < 23 Co-60 <7 < 9 <6 < 11 Zn-65 < 13 < 17 < 11 < 19 Nb-95 <8 < 8 <7 < 11 Zr-95 < 12 < 14 < 10 < 18 Ru-103 < 9 < 9 < 7 < 12 Ru-106 < 57 < 65 < 47 < 87 1-131 < 43 < 25 < 57 < 37

.Cs-134 < 6 < 7 < 5 < 10 Cs-137 < 7 < 9 < 6 < 12 Ba-140 < 69 < 51 < 78 < 74 La-140 < 19 < 16 < 24 < 19 Ce-141 < 15 < 15 < 13 < 22 Ce-144 < 47 < 49 < 34 < 72 Ra-226 < 145 < 156 < 100 +/- 209 Ac-228 < 29 < 27 < 25 72 < 32 Th-228 59 +/- 9 62 +/- 14 25 +/- 6 60 < 19 Control location B-49

INDIAN POINT ENERGY CENTER TABLE B-18 RADIONUCLIDES IN FISH / INVERTEBRATES - 2013 pCi/kg wet + 2 Sigma Roseton 23*

DATE 5/10/2013 05/10/13 5/14/2013 6/12/2013 6/19/2013 8/8/2013 Catfish White Perch American Eel Sunfish Striped Bass White Perch RADIOCHEMICAL Ni-63 < 40 < 39 < 41 < 41 < 33 < 46 Sr-90 < 3 < 3 <4 <4 < 3 < 3 GAMMA Be-7 < 475 < 814 < 470 < 455 < 423 < 692 K-40 2687 +/- 563 2693 +/- 820 1665 +/- 533 2971 +/- 652 4169 +/- 789 1875 +/- 297 Mn-54 < 32 < 55 < 35 < 45 < 42 < 26 Co-58 < 46 < 82 < 53 < 43 < 45 < 49 Fe-59 < 151 < 248 < 136 < 113 < 97 < 167 Co-60 < 39 < 64 < 42 < 46 < 41 < 20 Zn-65 < 74 < 128 < 97 < 90 < 81 < 45 Nb-95 < 58 < 99 < 59 < 53 < 43 < 56 Zr-95 < 82 < 175 < 88 < 89 < 91 < 106 Ru-103 < 60 < 117 < 77 < 59 < 46 < 133 Ru-106 < 298 < 514 < 349 < 410 < 411 < 240 1-131 < 2552 < 4952 < 2461 < 251 < 133 < 216300 Cs-134 < 36 < 46 < 37 < 46 < 44 < 21 Cs-137 < 34 < 66 < 38 < 45 < 42 < 23 Ba-140 < 1982 < 3195 < 1563 < 417 < 319 < 22570 La-140 < 502 < 1004 < 476 < 128 < 99 < 4875 Ce-141 < 103 < 187 < 140 < 97 < 78 < 494 Ce-144 < 151 < 287 < 238 < 279 < 286 < 304 Ra-226 < 619 < 1065 < 732 < 998 < 1018 < 751 Th-228 < 46 < 88 < 63 < 91 < 87 < 65 B-50

INDIAN POINT ENERGY CENTER TABLE B-18 RADIONUCLIDES IN FISH / INVERTEBRATES - 2013 pCi/kg wet + 2 Sigma Roseton 23*

DATE 8/8/2013 8/22/2013 8/28/2013 9/5/2013 9/5/2013 Striped Bass White Perch Blue Crab Sunfish Eel RADIOCHEMICAL Ni-63 < 39 < 37 < 55.8 < 47 < 46 Sr-90 < 4 <4 4.1 +/- 2.5 < 3 <4 GAMMA Be-7 < 397 < 536 < 171.1 < 228 < 482 K-40 4391 +/- 352 3069 +/- 307 2326 +/- 243.2 1304 +/- 255 2577 +/- 322 Mn-54 < 20 < 24 < 13.34 < 14 < 21 Co-58 < 38 < 45 < 16.59 < 22 < 40 Fe-59 < 126 < 147 < 42.34 < 67 < 129 Co-60 < 20 < 21 < 12.09 < 13 < 20 Zn-65 < 48 < 50 < 27.28 < 32 < 47 Nb-95 < 41 < 53 < 18.37 < 25 < 47 Zr-95 < 75 < 87 < 30.33 < 39 < 80 Ru-103 < 71 < 101 < 23.92 < 38 < 83 Ru-106 < 183 < 217 < 120.5 < 116 < 203 1-131 < 21910 < 82370 < 352.8 < 6208 < 37410 Cs-134 < 18 < 21 < 12.99 < 10 < 20 Cs-137 < 19 < 21 < 13.13 < 13 < 20 Ba-140 < 5653 < 12960 < 359.7 < 1875 < 7375 La-140 < 1874 < 3516 < 100.1 < 735 < 1931 Ce-141 < 127 < 217 < 37.25 < 85 < 180 Ce-144 < 118 < 146 < 80.92 < 94 < 146 Ra-226 < 386 < 389 < 245.8 < 264 < 400 Th-228 < 34 < 34 < 24.74 < 21 < 35 B-51

INDIAN POINT ENERGY CENTER TABLE B-18 RADIONUCLIDES IN FISH /INVERTEBRATES -2013 pci/kg wet +/-2 Sigma Downstream 25 DATE 5/8/2013 5/8/2013 5/9/2013 5/9/2013 5/13/2013 6/10/2013 American Eel Striped Bass Whiter Perch Catfish Sunfish Blue Crab RADIOCHEMICAL Ni-63 < 40 < 37 < 45 < 33 < 40 < 51 Sr-90 <3 <3 <3 <3 <4 6.1 < 2.7 GAMMA Be-7 < 647 < 675 < 1035 < 515 < 547 < 515 K-40 3548 +/- 721 3881 +/- 699 2036 +/- 794 2691 +/- 625 3099 +/- 604 2159 +/- 689 Mn-54 < 50 < 45 < 70 < 41 < 36 < 47 Co-58 < 61 < 64 < 91 < 55 < 55 < 52 Fe-59 < 188 < 154 < 215 < 162 < 141 < 127 Co-60 < 48 < 48 < 60 < 42 < 35 < 56 Zn-65 < 98 < 83 < 133 < 70 < 85 < 91 Nb-95 < 75 < 69 < 102 < 70 < 65 < 54 Zr-95 < 141 < 106 < 179 < 93 < 102 < 119 Ru-103 < 103 < 95 < 149 < 80 < 78 < 69 Ru-106 < 482 < 378 < 677 < 329 < 363 < 435 1-131 < 4002 < 4311 < 5721 < 3054 < 2465 < 278 Cs-134 < 44 < 38 < 61 < 39 < 36 < 49 Cs-137 < 46 < 44 < 66 < 34 < 34 < 44 Ba-140 < 2809 < 2613 < 4430 < 2282 < 1729 < 487 La-140 < 835 < 1019 < 1368 < 450 < 583 < 126 Ce-141 < 181 < 145 < 278 < 121 < 148 < 100 Ce-144 < 265 < 229 < 390 < 159 < 238 < 306 Ra-226 < 920 < 822 < 1177 < 717 < 908 < 922 Th-228 < 85 < 71 < 116 < 63 < 64 < 86 B-52

INDIAN POINT ENERGY CENTER TABLE B-18 RADIONUCLIDES IN FISH IINVERTEBRATES - 2013 pCi/kg wet +/-2 Sigma Downstream 25 DATE 8/22/2013 8/22/2013 8/29/2013 9/4/2013 9/5/2013 9/6/2013 Catfish White Perch Eel Striped Bass Sunfish Blue Crab RADIOCHEMICAL Ni-63 < 39 < 45 < 46 < 41 < 35 < 51 Sr-90 <3 <3 <3 <3 <3 <4 GAMMA Be-7 < 651 < 538 < 733 < 980 < 514 < 238 K-40 3583 +/- 413 2970 +/- 334 3382 +/- 481 3676 +/- 551 2831 +/- 425 2200 +/- 258 Mn-54 < 30 < 24 < 34 < 44 < 24 < 14 Co-58 < 56 < 44 < 64 < 76 < 48 < 26 Fe-59 < 190 < 159 < 219 < 256 < 139 < 70 Co-60 < 26 <21 < 34 < 38 < 23 <16 Zn-65 < 62 < 53 < 77 < 93 < 57 < 36 Nb-95 < 59 < 59 < 79 < 94 < 51 < 28 Zr-95 < 102 < 88 < 132 < 162 < 82 < 42 Ru-103 < 114 < 98 < 136 < 166 < 90 < 39 Ru-106 < 259 < 203 < 334 < 403 < 232 < 127 1-131 < 67380 < 56360 < 62070 < 69310 < 28420 < 4372 Cs-134 < 26 <21 < 33 < 40 < 22 < 13 Cs-137 < 24 <21 < 34 < 41 < 20 < 14 Ba-140 < 12850 < 10060 < 12620 < 14400 < 6738 < 1750 La-140 < 3293 < 2942 < 3723 < 3728 < 2028 < 527 Ce-141 < 229 < 187 < 256 < 363 < 157 < 66 Ce-144 < 175 < 140 < 210 < 316 < 144 < 77 Ra-226 < 477 < 395 < 570 < 835 < 467 < 261 Th-228 < 50 < 34 < 52 < 73 < 40 < 25 B-53

INDIAN POINT ENERGY CENTER TABLE B-18 RADIONUCLIDES IN FISH /INVERTEBRATES - 2013 pci/kg wet +/-2 Sigma Downstream 107 DATE 5/8/2013 5/9/2013 5/9/2013 5/10/2013 6/3/2013 6/10/2013 Eel White Perch Catfish Striped Bass Sunfish Blue Crab RADIOCHEMICAL ANALYSIS:

Ni-63 < 42 < 36 < 39 < 35 < 37.1

• 61 Sr-90 <3 <3 <3 <3 <3 < 3.9 GAMMA SPECTRUM ANALYSIS:

Be-7 < 434 < 718 < 609 < 945 < 654 < 406 K-40 1917 +/- 453 2520 +/- 925 3125 +/- 691 3073 +/- 811 2658 +/- 977 2136 +/- 650 Mn-54 < 38 < 50 < 40 < 64 <61 < 43 Co-58 < 46 < 71 < 66 < 99 < 54 < 42 Fe-59 < 116 < 247 < 168 < 259 < 151 < 124 Co-60 < 40 < 63 < 50 < 54 < 72 < 46 Zn-65 < 73 < 132 < 83 < 146 < 66 < 111 Nb-95 < 49 < 87 < 66 < 106 < 75

• 52 Zr-95 < 86 < 100 < 106 < 155 < 112

• 84 Ru-103 < 72 < 126 < 79 < 125 < 75

• 58 Ru-106 < 276 < 434 < 381 < 539 < 605 < 445 1-131 < 3226 < 4512 < 3283 < 5391 < 533 < 285 Cs-134 <31 < 46 < 39 < 53 < 63 < 46 Cs-137 < 30 < 53 < 43 < 62 < 63 < 40 Ba-140 < 1736 < 3537 < 2531 < 3452 < 897 < 423 La-140 < 607 < 619 < 672 < 1066 < 173 < 176 Ce-141 < 131 < 216 < 147 < 231 < 118 < 80 Ce-144 < 186 < 348 < 225 < 387 < 278 < 258 Ra-226 < 711 < 1228 < 891 < 1308 < 1144 < 973 Th-228 < 49 < 106 < 59 < 113 < 92 < 83 B-54

INDIAN POINT ENERGY CENTER TABLE B-18 RADIONUCLIDES IN FISH /INVERTEBRATES - 2013 pci/kg wet +/-2 Sigma Downstream 107 DATE COLLI 6/10/2013 8/22/2013 8/29/2013 8/30/2013 9/5/2013 Blue Crab Sunfish Eel Catfish White Perch RADIOCHEMICAL ANALYSIS:

Ni-63 < 60 < 31 < 41 < 35 < 40 Sr-90 <4 <4 <3 <3 <3 GAMMA SPECTRUM ANALYSIS:

Be-7 < 377 < 412 < 445 < 355 < 406 K-40 3474 +/- 307 3586 +/- 335 2769 +/- 325 3433 +/- 271 3474 +/- 298 Mn-54 < 20 < 21 < 22 <17 < 20 Co-58 < 32 < 38 < 39 < 33 < 38 Fe-59 < 99 < 118 < 135 < 120 < 137 Co-60 < 20 < 19 <18 < 17 < 21 Zn-65 < 47 < 45 < 48 < 42 < 46 Nb-95 < 36 < 41 < 44 < 37 < 42 Zr-95 < 66 < 76 < 78 < 63 < 75 Ru-103 < 61 < 75 < 83 < 65 < 73 Ru-106 < 189 < 189 < 185 < 145 < 180 1-131 < 9206 < 26180 < 56220 < 36900 < 37480 Cs- 134 < 19 < 19 < 18 < 15 <18 Cs-137 <19 <19 < 17 <15 < 18 Ba-140 < 3174 < 6175 < 9905 < 7090 < 7320 La-140 < 921 < 1462 < 2988 < 2380 < 2384 Ce-141 < 108 < 151 < 185 < 109 < 129 Ce-144 < 124 < 133 < 130 < 87 < 101 Ra-226 < 339 < 411 < 366 < 289 < 287 Th-228 < 30 < 34 < 37 < 26 < 26 B-55

Table B-19 LAND USE CENSUS - RESIDENCE and MILCH ANIMAL RESULTS 2013 The 2013 land use census indicated there were no new residences that were closer in proximity to IPEC. IPEC maintains a complete nearest residence survey with updated distances.

No milch animals were observed during this reporting period within the 5-mile zone.

There are no animals producing milk for human consumption within five miles of Indian Point.

B-56

TABLE B-20 LAND USE CENSUS 2013 INDIAN POINT ENERGY CENTER UNRESTRICTED AREA BOUNDARY AND NEAREST RESIDENCES Distance to Distance to site Distance to site nearest resident, Boundary from Boundary from from Unit I Unit 2 Plant Vent Unit 3 Plant Vent superheater Address of nearest resident, Last Sector Compass Point (meters) (meters) (meters) Census N RIVER RIVER 1788 41 River Road Tomkins Cove 2 NNE RIVER RIVER 3111 Chateau Rive Apts. John St. Peekskill 3 NE 550 636 1907 211 Viewpoint Terrace, Peekskill ENE 600 775 1478 1018 Lower South St. Peekskill E 662 785 1371 1103 Lower South St. Peekskill ESE 569 622 715 461 Broadway Buchanan 7 SE 553 564 1168 223 First St. Buchanan SSE 569 551 1240 5 Pheasant's Run Buchanan S 700 566 1133 320 Broadway Verplanck

• • SSW 755 480 1574 240 Eleventh St. Verplanck SW 544 350 3016 8 Spring St. Tomkins Cove 12 WSW RIVER RIVER 2170 9 West Shore Dr. Tomkins Cove 13 W RIVER RIVER 1919 712 Rt. 9W Tomkins Cove 14 WNW RIVER RIVER 1752 770 Rt. 9W Tomkins Cove 1 NW RIVER RIVER 1693 807 Rt. 9W Tomkins Cove NNW RIVER RIVER 1609 4 River Rd. Tomkins Cove B-57

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 graphical form to facilitate the comparison of 2013 data with historical values. Although other samples were taken and analyzed, values were only tabulated and plotted where positive indications were present.

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

C-1

TABLE C-1 DIRECT RADIATION ANNUAL

SUMMARY

2003-2013 Average Quarterly Dose (mR/Quarter)

Control Year Inner Ring Outer Ring Location 2003 14.3 13.9 14.7 2004 13.0 13.0 14.0 2005 14.1 14.1 15.9 2006 13.9 14.3 17.5 2007 14.4 14.6 18.8 2008 14.5 14.2 17.3 2009 14.5 14.2 17.3 2010 14.0 14.3 13.0 2011 13.6 14.4 13.4 2012 13.2 13.5 12.5 2013 13.4 13.8 14.2 Historical Average 2003-2012 14.0

1. 14.1 411, 15.4 C-2

FIGURE C-1 TLD DIRECT RADIATION, ANNUAL

SUMMARY

2003 to 2013 40.0

- Inner Ring 35.0 Outer Ring

-Control Location 30.0 25.0 a

, 20.0 E

s 15.0 10.0 5.0 0.0 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 C-3

TABLE C-2 RADIONUCLIDES IN AIR 2003 to 2013 (pCi/m 3 )

Gross Beta Cs-1 37 All Indicator Control All Indicator Control Locations Location Locations Location 2003 0.01 0.01 < Lc < Lc 2004 0.01 0.01 < Lc < Lc 2005 0.02 0.02 < Lc < Lc 2006 0.01 0.01 < Lc < Lc 2007 0.01 0.01 < Lc < Lc 2008 0.01 0.01 < Lc < Lc 2009 0.01 0.01 < Lc < Lc 2010 0.01 0.01 < Lc < Lc 2011 0.014 0.014 < Lc < Lc 2012 0.014 0.014 <Lc <Lc 2013 0.014 0.014 Historical Average 0.01 0.01 < Lc < Lc 2003-2012 Critical Level (L,) is less than the ODCM required LLD.

<Lc indicates no positive values above sample critical level.

C-4

FIGURE C-2 AP Beta RADIONUCLIDES IN AIR - GROSS BETA 2003 to 2013 0.05 EZMAII Indicator L 0.04 0.03 0.02 0.01 0.00 10 J I w W A gIJ,0A I I W, A ,I A 11,0 M I. W,, F. Dj Zg 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 Includes ODCM and non-ODCM indicator locations.

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

TABLE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 2003 to 2013 (pCi/L)

Tritium (H-3) Cs-1 37 Year Inlet Discharge Inlet Discharge 2003 < Lc < Lc < Lc < Lc 2004 < Lc 553 < Lc < Lc 2005 < Lc 618 < Lc < Lc 2006 < Lc 386 < Lc < Lc 2007 < Lc < Lc < Lc < Lc 2008 < Lc < Lc < Lc < Lc 2009 < Lc < Lc < Lc < Lc 2010 428 < Lc < Lc < Lc 2011 < Lc 661 < Lc < Lc 2012 < Lc 539 < Lc < Lc 2013 241 462 Historical Average 428 551 < Lc < Lc 2003-2012 Critical Level (Lj)is less than the ODCM required LLD.

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

C-6

FIGURE C-3 WR H-3 RADIONUCLIDES IN HUDSON RIVER WATER - TRITIUM 2003 to 2013 2000 1800 UInlet (H-3) *Discharge (H-3) 1600 1400 1200 U 1000 0.

800 600 Z0 I

400 200 2003 2004 Tritium ODCM required LLD = 3000 pCi/L 2005 2006 2007 C-7 2008 2009 I2010 2011 2012 I2013

TABLE C-4 RADIONUCLIDES IN DRINKING WATER 2003 to 2013 (pCi/L)

Year Tritium (H-3) Cs-1 37 2003 < Lc < Lc 2004 < Lc < Lc 2005 < Lc < Lc 2006 < Lc < Lc 2007 < Lc < Lc 2008 < Lc < Lc 2009 < Lc < Lc 2010 < Lc < Lc 2011 < Lc < Lc 2012 < Lc < Lc 2013 203< LLc < Lc Historical Average <L 2003-2012 Critical Level (Lc) is less than the ODCM required LLD.

<Lc indicates no positive values above sample critical level.

C-8

FIGURE C-4 WD H-3 RADIONUCLIDES IN DRINKING WATER - TRITIUM 2003 to 2013 2000 1800 1600 1400 1200

-j 1000 L) NO IDENTIFIED NUCLIDES IN PREVIOUS TEN YEARS HISTORY 800 600 400 200 0

2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 Tritium ODCM required LLD = 2000 pCi/L C-9

TABLE C-5 RADIONUCLIDES IN SHORELINE SOIL 2003 to 2013 (pCi/Kg, dry)

Cs-134 Cs-1 37 Year Indicator Control Indicator Control 2003 < Lc < Lc 124 73 2004 < Lc < Lc 104 138 2005 < Lc < Lc 156 36 2006 < Lc < Lc 120 < Lc 2007 < Lc < Lc 190 < Lc 2008 < Lc < Lc 187 < Lc 2009 < Lc < Lc 149 < Lc 2010 < Lc < Lc 154 63 2011 < Lc < Lc 108 < Lc 2012 < Lc < Lc 141 < Lc 2013 < Lc < Lc 133 < Lc Historical Average <Lc <Lc 143 78 2003-2012 Critical Level (L,) is less than the RETS required LLD.

<Lc indicates no positive values above sample critical level.

C-10

FIGURE C-5 SS Cs134 137 RADIONUCLIDES INSHORELINE SOIL - CESIUM-134 AND CESIUM-137 2003 to 2013 750

-Indicator (Cs-134)

Control (Cs-134) 650 Indicator (Cs-i137) 550 -Control (Cs-i 37) 450

• dI 350 a.

250 150 50 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013

-50 LD.Crequired _ __ 150 p . _K., dry Cs-134 ODCM required LLD = 150 pCi/Kg, dry Cs-137 ODCM required LLD = 175 pCi/Kg, dry C-1 1

TABLE C-6 BROAD LEAF VEGETATION - Cs-1 37 2003 to 2013 (pCi/Kg, wet)

Cs-137 Year Indicator Control 2003 14 < Lc 2004 10 < Lc 2005 < Lc < Lc 2006 < Lc < Lc 2007 < Lc < Lc 2008 < Lc < Lc 2009 < Lc < Lc 2010 31 < Lc 2011 < Lc < Lc 2012 44 < Lc 2013 < Lc < Lc Historical Average 18 < Lc 2003-2012 Critical Level (Lc) is less than the ODCM required LLD.

<Lc indicates no positive values above sample critical level.

C-12

FIGURE C-6 Veg Cs137 BROAD LEAF VEGETATION - CESIUM-137 2003 to 2013 100 80 60 L)

C.,

40 20 0

2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 ODCM required LLD = 80 pCi/Kg, wet C-1 3

TABLE C-7 FISH AND INVERTEBRATES - Cs-137 2003 to 2013 (pCi/Kg, dry)

Cs-1 37 Year Indicator Control 2003 < Lc < Lc 2004 < Lc < Lc 2005 < Lc < Lc 2006 < Lc < Lc 2007 < Lc < Lc 2008 < Lc < Lc 2009 < Lc < Lc 2010 < Lc < Lc 2011 < Lc < Lc 2012 < Lc < Lc 2013 < Lc < Lc Historical Average <Lc 2003-2012 Critical Level (L,) is less than the ODCM required LLD.

<Lc indicates no positive values above sample critical level.

C-14

FIGURE C-7 Fish Cs137 FISH AND INVERTEBRATES - CESIUM-137 2003 to 2013 200 180 I I Indicator (Cs-1 37) o Control (Cs-1 37) 160 4 140 120 100 r.

80 NO IDENTIFIED Cs-137 IN PREVIOUS TEN YEARS HISTORY 60 40 20 0

2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 Cs-137 ODCM required LLD = 150 pCi/Kg, wet C-1 5

TABLE C-8 RIVER WATER - Discharge Area - Tritium REMP vs. EFFLUENT (pCi/liter)

Year REMP* EFFLUENT **

1Q 2010 < 403 959 2Q 2010 < 397 239 3Q 2010 < 409 261 4Q 2010 < 408 796 1Q 2011 661 2192 2Q 2011 < 424 400 3Q 2011 < 412 493 4Q 2011 < 182 389 1Q 2102 617 2186 2Q 2012 < 178 394 3Q 2012 < 193 489 4Q 2012 460 860 1Q 2103 357 1813 2Q 2013 < 170 223 3Q 2013 < 186 428 4Q 2013 306 896 Four Year Average, by 480 814 Quarter, 2010 - 2013

• Sample from mixing zone, expected to be less than average activity in the discharge canal.

• • Based upon Effluent Report data, average activity in the discharge canal calculated from the total H-3 discharged divided by the total dilution volume for the quarter.

C-16

APPENDIX D INTERLABORATORY COMPARISON PROGRAM

APPENDIX D INTERLABORATORY COMPARISON PROGRAM This section presents the results of the interlaboratory comparison program for the Teledyne Brown Engineering Environmental Services and Environmental Dosimetry Company. Since General Engineering Labs only analyzed 2 samples, their interlaboratory data is not presented.

However, their results can be provided upon request.

D. 1 Program Description - Teledyne Brown Engineering Environmental Services Comparison Programs The Teledyne Brown Engineering Environmental Services participates in several interlaboratory comparison programs. These programs include sample media for which samples are routinely collected and for which comparison samples are commercially available. Participation in these interlaboratory comparison programs ensure 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, Teledyne Brown Engineering Environmental Services has engaged the following programs:

• Eckert & Ziegler Analytics Environmental Radioactivity Cross Check Program

• Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP)

• Environmental Resource Associates (ERA) Cross Check Program These programs supply sample media as blind samples (typically spikes), which contain certified levels of radioactivity unknown to the analysis laboratory. These samples are prepared and analyzed by the Teledyne Brown Engineering Environmental Services using standard laboratory procedures. Each program issues a statistical summary report of the results. Teledyne Brown Engineering Environmental Services uses predetermined acceptance criteria methodology for evaluating its laboratory performance.

Teledyne Brown Engineering Environmental Services also analyzes laboratory blanks. The analysis of laboratory blanks provides a means to detect and measure radioactive contamination of analytical samples. The analysis of analytical blanks also provides information on the adequacy of background subtraction. Laboratory blank results are analyzed using control charts.

D.2 Acceptance Criteria Each sample result is evaluated to determine the accuracy and precision of the laboratory's analysis result. The sample evaluation method is discussed below.

D-1

D.2.1 Analytics Sample Results Evaluation Samples provided by Analytics are evaluated using what is specified as the NRC method.

This method is based on the calculation of the ratio of results reported by the participating laboratory (QC result) to the Vendor Laboratory Known value (reference result).

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

The value for the error resolution is calculated.

Error Resolution = Reference Result Reference Results Error (1 sigma)

Using the appropriate row under the Error Resolution column in Tables D-3.1, D-3.2, and D-3.3, a corresponding Ratio of Agreement interval is given.

The value for the ratio is then calculated.

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

TABLE D-2.1 Ratio of Agreement ERROR RESOLUTION RATIO OF AGREEMENT

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

>200 0.85-1.18 This acceptance test is generally referred to as the "NRC" method. The acceptance criteria are contained in Procedure EN-CY-102. The NRC method generally results in an acceptance range of approximately +/- 25% of the Known value when applied to sample results from the Eckert & Ziegler Analytics Interlaboratory Comparison Program. This method is used as the procedurally required assessment method and requires the generation of a deviation from QA/QC program report when results are unacceptable.

D.2.2 ERA and MAPEP Sample Result Evaluation Both these programs supply an acceptance range for evaluating the results.

D.3 Program Results Summary The Interlaboratory Comparison Program numerical results are summarized in the following tables.

D-2

TABLE D-3.1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

March 2013 E10477 Milk Sr-89 pCi/L 120 99.7 1.20 Sr-90 pCi/L 9.21 11.0 0.84 E10478 Milk 1-131 pCi/L 87.1 100 0.87 Ce-141 pCi/L 186 187 0.99 Cr-51 pCi/L 463 472 0.98 Cs-134 pCi/L 201 214 0.94 Cs-137 pCi/L 262 266 0.98 Co-58 pCi/L 200 208 0.96 Mn-54 pCi/L 215 208 1.03 Fe-59 pCi/L 266 252 1.06 Zn-65 pCi/L 311 301 1.03 Co-60 pCi/L 384 400 0.96 E10480 AP Ce-141 pCi 95.3 95.6 1.00 Cr-51 pCi 264 241 1.10 Cs-1 34 pCi 123 109 1.13 Cs-1 37 pCi 142 136 1.04 Co-58 pCi 112 106 1.06 Mn-54 pCi 115 106 1.08 Fe-59 pCi 139 129 1.08 Zn-65 pCi 163 153 1.07 Co-60 pCi 212 204 1.04 E10479 Charcoal 1-131 pCi 90.1 92.6 0.97 E10481 Water Fe-55 pCi/L 1840 1890 0.97 A June 2013 E10564 Milk Sr-89 pCi/L 110 95.0 1.16 A Sr-90 pCi/L 15.8 17.0 0.93 A E10545 Milk 1-131 pCi/L 92.6 95.5 0.97 A Ce-141 pCi/L 83.1 90.4 0.92 A Cr-51 pCi/L 253 250 1.01 A Cs-1 34 pCi/L 118 125 0.94 A Cs-137 pCi/L 143 151 0.95 A Co-58 pCi/L 87.1 94.0 0.93 A Mn-54 pCi/L 171 172 0.99 A Fe-59 pCi/L 125 120 1.04 A Zn-65 pCi/L 220 217 1.01 A Co-60 pCi/L 169 175 0.97 A E10547 AP Ce-141 pCi 56.8 56.7 1.00 A Cr-51 pCi 168 157 1.07 A Cs-1 34 pCi 85.2 78.4 1.09 A Cs-137 pCi 101 94.6 1.07 A Co-58 pCi 62.7 58.9 1.06 A Mn-54 pCi 125 108 1.16 A Fe-59 pCi 85.7 75.0 1.14 A Zn-65 pCi 169 136 1.24 W Co-60 pCi 116 110 1.05 A E10546 Charcoal 1-131 pCi 86.5 89.7 0.96 A D-3

TABLE D-3.1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

June 2013 E10549 Water Fe-55 pCi/L 1610 1610 1.00 A September2013 E10646 Milk Sr-89 pCi/L 63.9 96.0 0.67 N (1)

Sr-90 pCi/L 8.88 13.2 0.67 N (1)

E10647 Milk 1-131 pCi/L 93.9 98.3 0.96 A Ce-141 pCi/L NA (2)

Cr-51 pCi/L 272 277 0.98 A Cs-134 pCi/L 150 172 0.87 A Cs-137 pCi/L 125 131 0.95 A Co-58 pCi/L 105 108 0.97 A Mn-54 pCi/L 138 139 0.99 A Fe-59 pCi/L 125 130 0.96 A Zn-65 pCi/L 264 266 0.99 A Co-60 pCi/L 187 196 0.95 A E10672 AP Ce-141 pCi NA (2)

Cr-51 pCi 208 223 0.93 A Cs-134 pCi 143 139 1.03 A Cs-137 pCi 106 105 1.01 A Co-58 pCi 97.0 86.5 1.12 A Mn-54 pCi 116 112 1.04 A Fe-59 pCi 98.6 105 0.94 A Zn-65 pCi 219 214 1.02 A Co-60 pCi 166 158 1.05 A E10648 Charcoal 1-131 pCi 76.3 71.7 1.06 A E10673 Water Fe-55 pCi/L 1790 1690 1.06 A December2013 E10774 Milk Sr-89 pCi/L 97.3 93.8 1.04 Sr-90 pCi/L 13.3 12.9 1.03 E10775 Milk 1-131 pCi/L 89.7 96.1 0.93 Ce-141 pCi/L 99.8 110 0.91 Cr-51 pCi/L 297 297 1.00 Cs-1 34 pCi/L 129 142 0.91 Cs-1 37 pCi/L 126 126 1.00 Co-58 pCi/L 116 112 1.04 Mn-54 pCi/L 167 168 0.99 Fe-59 pCi/L 117 110 1.06 Zn-65 pCi/L 757 741 1.02 Co-60 pCi/L 141 147 0.96 E10777 AP Ce-141 pCi 85.1 88.0 0.97 Cr-51 pCi 278 238 1.17 Cs-1 34 pCi 123 114 1.08 Cs-1 37 pCi 102 101 1.01 Co-58 pCi 84.4 89.9 0.94 Mn-54 pCi 132 135 0.98 Fe-59 pCi 101 88.3 1.14 Zn-65 pCi 506 595 0.85 Co-60 pCi 118 118 1.00 D-4

TABLE D-3.1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

December 2013 E10776 Charcoal 1-131 pCi 84.7 80.5 1.05 A E10778 Water Fe-55 pCi/L 2010 1910 1.05 A (1) Milk, Sr-89/90 - The failure was due to analyst error. No client samples were affected by this failure. NCR 13-15 (2) The sample was not spiked with Ce-141.

(a) Teledyne Brown Engineering reported result.

(b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standardpreparation.

(c) Ratio of Teledyne Brown Engineeringto Analytics results.

(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0.80-1.20.

W-Acceptable with warning, reported result falls within 0. 70-0.80 or 1.20-1.30. N = Not Acceptable, reported result falls outside the ratio limits of < 0.70 and > 1.30.

D-5

TABLE D-3.2 DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)

March 2013 13-MaW28 Water Cs-134 Bq/L 21.0 24.4 17.1 -31.7 A Cs-137 Bq/L 0.0446 (1) A Co-57 Bq/L 28.3 30.9 21.6-40.2 A Co-60 Bq/L 18.2 19.56 13.69 - 25.43 A H-3 Bq/L 506 507 355 - 659 A Mn-54 Bq/L 25.7 27.4 19.2- 35.6 A K-40 Bq/L 2.09 (1) A Sr-90 Bq/L 10.5 10.5 7.4-13.7 A Zn-65 Bq/L 29.2 30.4 21.3 - 39.5 A 13-GrW28 Water Gr-A Bq/L 2.74 2.31 0.69 - 3.93 A Gr-B Bq/L 15.6 13.0 6.5- 19.5 A 13-MaS28 Soil Cs-134 Bq/kg 859 887 621-1153 A Cs-137 Bq/kg 633 587 411 -763 A Co-57 Bq/kg 0.256 (1) A Co-60 Bq/kg 738 691 484-898 A Mn-54 Bq/kg 0.671 (1) A K-40 Bq/kg 714 625.3 437.7 - 812.9 A Sr-90 Bq/kg 442 628 440-816 W Zn-65 Bq/kg 1057 995 697-1294 A 13-RdF28 AP Cs-134 Bq/sample 1.73 1.78 1.25-2.31 A Cs-137 Bq/sample 2.73 2.60 1.82 - 3.38 A Co-57 Bq/sample 2.38 2.36 1.65-3.07 A Co-60 Bq/sample 0.0302 (1) A Mn-54 Bq/sample 4.36 4.26 2.98 - 5.54 A Sr-90 Bq/sample 1.43 1.49 1.04- 1.94 A Zn-65 Bq/sample 3.14 3.13 2.19-4.07 A 13-GrF28 AP Gr-A Bq/sample 0.767 1.20 0.36 - 2.04 A Gr-B Bq/sample 0.871 0.85 0.43- 1.28 A 13-RdV28 Vegetation Cs-134 Bq/sample -0.197 (1) A Cs-137 Bq/sample 7.39 6.87 4.81 - 8.93 A Co-57 Bq/sample 9.87 8.68 6.08 - 11.28 A Co-60 Bq/sample 6.08 5.85 4.10-7.61 A Mn-54 Bq/sample -0.0104 (1) A Sr-90 Bq/sample 1.28 1.64 1.15-2.13 W Zn-65 Bq/sample 6.84 6.25 4.38- 8.13 A September 2013 13-MaW29 Water Cs-134 Bq/L 29.1 30.0 21.0-39.0 A Cs-137 Bq/L 34.5 31.6 22.1-41.1 A Co-57 Bq/L 0.0358 (1) A Co-60 Bq/L 24.6 23.58 16.51 - 30.65 A H-3 Bq/L 2.45 (1) A Mn-54 Bq/L 0.0337 (1) A K-40 Bq/L 0.193 (1) A Sr-90 Bq/L 9.12 7.22 5.05- 9.39 W Zn-65 Bq/L 38.1 34.6 24.2 -45.0 A 13-GrW29 Water Gr-A Bq/L 1.13 0.701 0.210- 1.192 A Gr-B Bq/L 7.61 5.94 2.97 - 8.91 A D-6

TABLE D-3.2 DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)

September 2013 13-MaS29 Soil Cs-1 34 Bq/kg 1150 1172 820-1524 A Cs-1 37 Bq/kg 1100 977 684-1270 A Co-57 Bq/kg 670 (1) N (2)

Co-60 Bq/kg 502 451 316-586 A Mn-54 Bq/kg 758 674 472 - 876 A K-40 Bq/kg 796 633 443 - 823 W Sr-90 Bq/kg 664 460 322 - 598 N (2)

Zn-65 Bq/kg 210 (1) N (2) 13-RdF29 AP Cs-134 Bq/sample -0.570 (1) N (2)

Cs-137 Bq/sample 2.85 2.7 1.9-3.5 A Co-57 Bq/sample 3.30 3.4 2.4 - 4.4 A Co-60 Bq/sample 2.41 2.3 1.6-3.0 A Mn-54 Bq/sample 3.65 3.5 2.5-4.6 A Sr-90 Bq/sample 1.40 1.81 1.27-2.35 W Zn-65 Bq/sample 2.90 2.7 1.9-3.5 A 13-GrF29 AP Gr-A Bq/sample 0.872 0.9 0.3- 1.5 A Gr-B Bq/sample 1.57 1.63 0.82-2.45 A 13-RdV29 Vegetation Cs-134 Bq/sample 5.29 5.20 3.64 - 6.76 A Cs-137 Bq/sample 7.48 6.60 4.62 - 8.58 A Co-57 Bq/sample 0.0129 (1) A Co-60 Bq/sample 0.0523 (1) A Mn-54 Bq/sample 8.78 7.88 5.52 - 10.24 A Sr-90 Bq/sample 1.63 2.32 1.62-3.02 W (2)

Zn-65 Bq/sample 3.18 2.63 1.84 - 3.42 W (1) Falsepositive test (2) Soil. Co-57 & Zn-65 identified by gamma software as not detected. MAPEP evaluated as failing the false positive test. A large concentration of Eu-152 was spiked into the sample, causing interference in the analysis. Gamma software recognized the interference and identified them as not detected. MAPEP does not allow clients to enter non-detect designation.NCR 13-04 Soil, Sr incorrectresults were submitted to MAPEP. Should have been 332 bq/kg, which would have passed. NCR 13-04 AP. Cs-134 - MAPEP evaluated the -0.570 as a failed false positive test. No client samples were affected by these failures. NCR 13-04 Vegetation, Sr it appearsthat the carrierwas double spiked into the sample, resulting in the low activity for this sample. NCR 13-04 (a) Teledyne Brown Engineering reported result.

(b) The MAPEP known value is equal to 100% of the parameterpresent in the standardas determined by gravimetricand/or volumetric measurements made during standardpreparation.

(c) DOEIMAPEP evaluation: A=acceptable, W=acceptable with warning, N=not acceptable.

D-7

TABLE D-3.3 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Limits Evaluation (c)

May 2013 RAD-93 Water Sr-89 pCi/L 48.3 41.3 31.6 - 48.4 A Sr-90 pCi/L 19.3 23.9 17.2 -28.0 A Ba-1 33 pCi/L 81.9 82.1 69.0 - 90.3 A Cs-1 34 pCi/L 40.9 42.8 34.2-47.1 A Cs-137 pCi/L 44.0 41.7 37.0-48.8 A Co-60 pCi/L 61.9 65.9 59.3 - 75.0 A Zn-65 pCi/L 202 189 170-222 A Gr-A pCi/L 34.2 40.8 21.1 -51.9 A Gr-B pCi/L 18.0 21.6 13.0-29.7 A 1-131 pCi/L 23.8 23.8 19.7 -28.3 A U-Nat pCi/L 60.4 61.2 49.8 - 67.9 A H-3 pCi/L 3970 4050 3450 - 4460 A MRAD-18 Filter Gr-A pCi/filter Lost during processing November 2013 RAD-95 Water Sr-89 pCi/L 25.5 21.9 14.4 - 28.2 A Sr-90 pCi/L 14.3 18.1 12.8-21.5 A Ba-133 pCi/L 57.2 54.2 44.7 - 59.9 A Cs-134 pCi/L 83.3 86.7 71.1 -95.4 A Cs-1 37 pCi/L 201 206 185-228 A Co-60 pCi/L 104 102 91.8-114 A Zn-65 pCi/L 361 333 300 - 389 A Gr-A pCi/L 29.5 42.8 22.2 - 54.3 A Gr-B pCi/L 30.1 32.2 20.8 - 39.9 A 1-131 pCi/L 23.1 23.6 19.6-28.0 A U-Nat pCi/L 5.53 6.24 4.70 - 7.44 A H-3 pCi/L 17650 17700 15500 - 19500 A MRAD-19 Filter Gr-A pCi/filter 33.0 83.0 27.8 - 129 A (a) Teledyne Brown Engineeringreported result.

(b) The ERA known value is equal to 100% of the parameterpresent in the standardas determined by gravimetricand/or volumetric measurements made during standardpreparation.

(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.

D-8

D.4 Environmental TLD Quality Assurance Environmental dosimetry services for the reporting period of January - December, 2013 were provided by the Environmental Dosimetry Company (EDC), Sterling, Massachusetts.

The TLD systems at the Environmental Dosimetry Company (EDC) are calibrated and operated to ensure consistent and accurate evaluation of TLDs. The quality of the dosimetric results reported to EDC clients is ensured by in house performance testing and independent performance testing by EDC clients.

The purpose of the dosimetry quality assurance program is to provide performance documentation of the routine processing of EDC dosimeters. Performance testing provides a statistical measure of the bias and precision of dosimetry processing against a reliable standard, which in turn points out any trends or performance changes. Dosimetry quality control tests are performed on EDC Panasonic 814 Environmental dosimeters. These tests include: (1) the in house testing program conducted by the EDC QA Officer and (2) independent test perform by EDC clients.

Excluded from this report are instrumentation checks. Although instrumentation checks represent an important aspect of the quality assurance program, they are not included as process checks in this report. Instrumentation checks represent between 5-10% of the TLDs processed.

Table D-4.1 provides a summary of individual dosimeter results evaluated against the EDC internal acceptance criteria for high-energy photons (Cs-137) only. The internal acceptance (tolerance) criteria for the Panasonic Environmental dosimeters are: +/- 15% for bias and +/-

12.8% for precision. During this period, 100% (72/72) of the individual dosimeters, evaluated against these criteria met the tolerance limits for accuracy and 100% (72/72) met the criterion for precision.

Table D-4.2 provides the Bias + Standard deviation results for each group (N=6) of dosimeters evaluated against the internal tolerance criteria. Overall, 100% (12/12) of the dosimeter sets evaluated against the internal tolerance performance criteria met these criteria.

Table D-4.3 presents the independent blind spike results for irradiated dosimeters provided by client utilities during this annual period. All results passed the performance acceptance criterion.

TABLE D-4.1 PERCENTAGE OF INDIVIDUAL DOSIMETERS THAT PASSED EDC INTERNAL CRITERIA JANUARY - DECEMBER 2013 (1), (2)

Number  % Passed Precision Dosimeter Type Tested %Passed Bias Criteria Criteria Panasonic Environmental 72 100 100 (M)This table summarizes results of tests conducted by EDC.

(2)Environmental dosimeter results are free in air.

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TABLE D-4.2 MEAN DOSIMETER ANALYSES (N=6)

JANUARY - DECEMBER 2013 (1), (2)

Standard Tolerance Mean Bias % Dation Tolimtnce Process Date Deviation % Limit +/-15%

4/22/2013 4.1 1.9 Pass 4/24/2013 4.5 1.2 Pass 5/23/2013 -1.1 1.9 Pass 7/24/2013 0.8 1.0 Pass 8/4/2013 -1.1 1.6 Pass 8/6/2013 0.1 2.3 Pass 10/31/2013 1.5 1.2 Pass 11/10/2013 0.1 1.7 Pass 11/15/2013 -1.8 1.0 Pass 1/27/2014 3.7 2.3 Pass 1/31/2014 2.6 0.9 Pass 2/5/2014 0.7 0.6 Pass

(')This table summarizes results of tests conducted by EDC for TLDs issued in 2013.

(2)Environmental dosimeter results are free in air.

TABLE D-4.3

SUMMARY

OF INDEPENDENT DOSIMETER TESTING JANUARY - DECEMBER 2013 (1), (2)

Standard

• Pass P / Fail Issuance Period Client Mean Bias % Dvan Deviation %

2 nd Qtr.2013 Millstone 0.7 1.5 Pass 2 nd Qtr.2013 Seabrook -2.3 2.7 Pass 3rd Qtr. 2013 Millstone -4.7 4.0 Pass 4" Qtr.2013 Seabrook -0.9 0.9 Pass

(')Performance criteria are +/- 30%.

(2)Blind spike irradiations using Cs-137 D-10