Text

2014 Annual Radiological Environmental Operating Report
	ML15138A133
Person / Time
Site:	Nine Mile Point
Issue date:	05/13/2015
From:	Trafton W; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NMP1L 3024
	Download: ML15138A133 (164)
	v • d • e

'Exelon Generation.

Technical Specifications NMP1L 3024 May 13, 2015 U.S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 Docket Nos. 50-220 and 50-410

Subject:

2014 Annual Radiological Environmental Operating Report In accordance with the Technical Specifications for Nine Mile Point Nuclear Station, Units 1 and 2, attached is the 2014 Annual Radiological Environmental Operating Report for the period of January 1, 2014 through December 31, 2014.

This submittal does not contain any regulatory commitments.

Should you have questions regarding the information in this submittal, please contact Shane Howe, Site Chemistry Environmental & Radwaste Manager, at (315) 349-5210.

Sincerely, William J. TIfton Plant Manager - Nine Mile Point Nuclear Station Exelon Generation Company, LLC WJT/BTV

Enclosure:

Nine Mile Point Nuclear Station, LLC 2014 Annual Radiological Environmental Operating Report cc:

NRC Regional Administrator, Region I NRC Project Manager NRC Resident Inspector C. Graves, NRC T. Rice, NYSDEC C. Costello, NYSDOH T. Bennett, Oswego County Emergency Management

Enclosure Nine Mile Point Nuclear Station, LLC 2014 Annual Radiological Environmental Operating Report

An Exelon Generation.

NINE MILE POINT NUCLEAR STATION, LLC 2014 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

NINE MILE POINT NUCLEAR STATION, LLC ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January 1, 2014 - December 31, 2014 For NINE MILE POINT NUCLEAR STATION UNIT 1 Facility Operating License DPR-63 Docket No. 50-220 And NINE MILE POINT NUCLEAR STATION UNIT 2 Facility Operating License NPF-69 Docket No. 50-410

TABLE OF CONTENTS Page 1.0 EXECUTIVE

SUMMARY

1-1

2.0 INTRODUCTION

2-1 2.1 Program History 2-1 2.2 Site Description 2-1 2.3 Program Objectives 2-2 3.0 PROGRAM DESCRIPTION 3-1 3.1 Sample Collection Methodology 3-13 3.2 Analyses Performed 3-18 3.3 Sample Locations 3-18 3.4 Land Use Census 3-30 3.5 Changes to the REMP Program 3-30 3.6 Deviations and Exceptions to the Program 3-30 3.7 Statistical Methodology 3-31 3.8 Compliance with Required Lower Limits of Detection (LLD) 3-35 3.9 Regulatory Dose Limits 3-35 4.0 SAMPLE

SUMMARY

TABLES IN BRANCH TECHNICAL 4-1 POSITION FORMAT 5.0 DATA EVALUATION AND DISCUSSION 5-1 5.1 Aquatic Program 5-5 5.2 Terrestrial Program 5-16 5.3 Conclusion 5-34 5.4 References 5-36 6.0 REPORT PERIOD ANALYTICAL RESULTS TABLES 6-1 i

TABLE OF CONTENTS (Continued)

Page 7.0 HISTORICAL DATA TABLES 7-1 8.0 QUALITY ASSURANCE/QUALITY CONTROL PROGRAM 8-1 8.1 Program Description 8-1 8.2 Program Schedule 8-2 8.3 Acceptance Criteria 8-2 8.4 Program Results Summary 8-4 8.5 Teledyne Brown Engineering 8-10 8.6 References 8-15 ii

LIST OF TABLES Page Table 3.0-1 Radiological Environmental Monitoring Program Required Sample Collection and Analysis, Nine Mile Point Unit 1 3-2 Table 3.0-2 Radiological Environmental Monitoring Program Required Sample Collection and Analysis, Nine Mile Point Unit 2 3-6 Table 3.3-1 2014 Environmental Sample Locations 3-20 Table 3.7-1 Required Detection Capabilities for Environmental Sample Analysis, 3-35 Lower Limit of Detection (LLD)

Table 4.0-1 Radiological Environmental Monitoring Program Annual Summary, 4-2 January - December 2014 Table 6-1 Concentrations of Gamma Emitters in Shoreline Sediment Samples - 2014 6-2 Table 6-2 Concentrations of Gamma Emitters in Fish Samples -2014 6-3 Table 6-3 Concentrations of Tritium in Surface Water Samples - 2014 6-6 Table 6-4 Concentrations of Gamma Emitters in Surface Water Samples -2014 6-7 Table 6-5 Environmental Airborne Particulate Samples - Off-Site Sample 6-12 Locations -2014, Gross Beta Activity Table 6-6 Environmental Airborne Particulate Samples - On-Site Sample 6-14 Locations -2014, Gross Beta Activity Table 6-7 Environmental Charcoal Cartridge Samples - Off-Site Sample 6-16 Locations -2014, 1-131 Activity Table 6-8 Environmental Charcoal Cartridge Samples - On-Site Sample 6-18 Locations - 2014, 1-131 Activity Table 6-9 Concentrations of Gamma Emitters in Quarterly Composites 6-20 of JAFNPP/NMPNS Site Air Particulate Samples - 2014 Table 6-10 Direct Radiation Measurement Results -2014 6-24 Table 6-11 Concentrations of Iodine-131 and Gamma Emitters in Milk - 2014 6-26 Table 6-12 Concentrations of Gamma Emitters in Food Products - 2014 6-28 Table 6-13 Milk Animal Census - 2014 6-29 Table 6-14 Residence Census - 2014 6-30 iii

LIST OF TABLES (continued)

Page Table 7-1 Historical Environmental Sample Data, Shoreline Sediment (Control) 7-2 Table 7-2 Historical Environmental Sample Data, Shoreline Sediment (Indicator) 7-3 Table 7-3 Historical Environmental Sample Data, Fish (Control) 7-4 Table 7-4 Historical Environmental Sample Data, Fish (Indicator) 7-5 Table 7-5 Historical Environmental Sample Data, Surface Water (Control) 7-6 Table 7-6 Historical Environmental Sample Data, Surface Water (Indicator) 7-7 Table 7-7 Historical Environmental Sample Data, Surface Water Tritium (Control) 7-8 Table 7-8 Historical Environmental Sample Data, Surface Water Tritium (Indicator) 7-9 Table 7-9 Historical Environmental Sample Data, Groundwater Tritium (Control) 7-10 Table 7-10 Historical Environmental Sample Data, Groundwater Monitoring Wells Tritium (Indicator) 7-11 Table 7-1Oa Historical Environmental Sample Data, NMP2 Storm Drain Tritium (Indicator) 7-11 Table 7-11 Historical Environmental Sample Data, Air Particulate Gross Beta (Control) 7-12 Table 7-12 Historical Environmental Sample Data, Air Particulate Gross Beta (Indicator) 7-13 Table 7-13 Historical Environmental Sample Data, Air Particulates (Control) 7-14 Table 7-14 Historical Environmental Sample Data, Air Particulates (Indicator) 7-15 Table 7-15 Historical Environmental Sample Data, Air Radioiodine (Control) 7-16 Table 7-16 Historical Environmental Sample Data, Air Radioiodine (Indicator) 7-17 Table 7-17 Historical Environmental Sample Data, Environmental TLD (Control) 7-18 Table 7-18 Historical Environmental Sample Data, Environmental TLD (Site Boundary) 7-19 Table 7-19 Historical Environmental Sample Data, Environmental TLD (Off-site Sectors) 7-20 Table 7-20 Historical Environmental Sample Data, Environmental TLD (Special Interest) 7-21 iv

LIST OF TABLES (continued)

Page Table 7-21 Historical Environmental Sample Data, Environmental TLD 7-22 (On-Site Indicator)

Table 7-22 Historical Environmental Sample Data, Environmental TLD 7-23 (Off-Site Indicator)

Table 7-23 Historical Environmental Sample Data, Milk (Control) 7-24 Table 7-24 Historical Environmental Sample Data, Milk (Indicator) 7-25 Table 7-25 Historical Environmental Sample Data, Food Products (Control) 7-26 Table 7-26 Historical Environmental Sample Data, Food Products (Indicator) 7-27 Table 8-1 Quality Assurance Acceptance Criteria 8-3 Table 8-2 Interlaboratory Intercomparison Program 8-5 Table 8-3 Analytics Environmental Radioactivity Cross Check Program Teledyne 8-11 Brown Engineering Environmental Services v

LIST OF FIGURES Figure 3.3-1 Figure 3.3-2 Figure 3.3-3 Figure 3.3-4 Figure 3.3-5 Figure 3.3-6 New York State Map Off-Site Environmental Station and TLD Locations On-Site Environmental Station and TLD Locations Milk and Surface Water Sample Locations Nearest Residence, Food Product, Fish and Shoreline Sediment Sample Locations NMPNS On-Site Groundwater Monitoring Wells and Unit 2 Storm Drain Outfall Page 3-24 3-25 3-26 3-27 3-28 3-29 vi

1.0 EXECUTIVE

SUMMARY

The Annual Radiological Environmental Operating Report is published pursuant to Section 6.6.2 of the Nine Mile Point Unit 1 (NMP1) Technical Specifications and Section 5.6.2 of the Nine Mile Point Unit 2 (NMP2) Technical Specifications.

This report describes the Radiological Environmental Monitoring Program (REMP), the implementation of the program, and the results obtained as required by the Offsite Dose Calculation Manuals (ODCM). The report also contains the analytical results tables, data evaluation, dose assessment, and data trends for each environmental sample media. Also included are results of the land use census, historical data, and the Environmental Laboratory's performance in the Interlaboratory Comparison Quality Assurance Program (ICQAP) required by the NMPI and NMP2 ODCM.

The REMP is a comprehensive surveillance program, which is implemented to assess the impact of site operations on the environment and compliance with 10 CFR 20, 10 CFR 72 and 40 CFR 190. Samples are collected from the aquatic and terrestrial pathways applicable to the site. The aquatic pathways include Lake Ontario fish, surface waters, and lakeshore sediment.

The terrestrial pathways include airborne particulate and radioiodine, milk, food products, and direct radiation.

During 2014, there were 2064 analyses performed on environmental media collected as part of the REMP.

The results demonstrate that there was no significant or measurable radiological impact from the operation of either the NMPI or NMP2 facilities. The 2014 results for all pathways sampled were consistent with the previous five-year historical results and exhibited no adverse trends.

In summary, the analytical results from the 2014 REMP demonstrate that the routine operation of both facilities at the Nine Mile Point site had no significant or measurable radiological impact on the environment. The results of the REMP continue to demonstrate that the operation of the plants did not result in a significant measurable dose to a member of the general population, or adversely impact the environment as a result of radiological effluents. The program continues to demonstrate that the dose to a member of the public, as a result of the operation of NMPI1 and NMP2, remains significantly below the federally required dose limits specified in 10 CFR 20, 10 CFR 72 and 40 CFR 190.

1-1

2.0 INTRODUCTION

Nine Mile Point Units 1 and 2 are operated by Nine Mile Point Nuclear Station, LLC. This report is submitted in accordance with Appendix A (Technical Specifications) Section 6.6.2 to License DPR-63, Docket No. 50-220 for Nine Mile Point Nuclear Station, Unit 1, and Appendix A (Technical Specifications) Section 5.6.2 to License NPF-69, Docket No. 50-410 for Nine Mile Point Nuclear Station, Unit 2, for the calendar year 2014.

Nine Mile Point Unit 1 (NMPI) and Nine Mile Point Unit 2 (NMP2) Radiological Environmental Monitoring Program (REMP) requirements reside within the NMP1 Offsite Dose Calculation Manual (ODCM) and NMP2 ODCM, respectively. Throughout this report, references will be made to the ODCM.

This refers to both the NMP1 ODCM and the NMP2 ODCM.

2.1 PROGRAM HISTORY Environmental monitoring of the Nine Mile Point (NMP) site has been on-going since 1964. The program includes five years of pre-operational data which was conducted prior to any reactor operations. In 1968, the Niagara Mohawk Power Company began the required pre-operational environmental site testing program. This pre-operational data serves as a reference point to compare data obtained during reactor operation. In 1969, NMP1, a 1,850 Megawatt-Thermal (MWt) Boiling Water Reactor (BWR) began full power operation. In 1975, the James A. FitzPatrick Nuclear Power Plant (JAFNPP), a 2,536 MWt BWR, currently owned and operated by Entergy, began full power operation.

In 1988, NMP2, a 3,323 MWt BWR located between NMP1 and JAFNPP, began full power operation. In 1995, NMP2 was uprated to 3,467 MWt and in 2012, NMP2 was uprated to 3,988 MWt.

In 1985, the individual stations' Plant Effluent Technical Specifications were standardized to the generic Radiological Effluent Technical Specifications, much of which is common to both NMPI and JAFNPP, and subsequently to NMP2.

Subsequent Technical Specification amendments relocated the REMP requirements to the ODCM for all three plants. Data generated by the REMIP is shared between Nine Mile Point Nuclear Station (NMPNS) and JAFNPP, but each operating company reviews and publishes their own annual report.

In summary, the three BWRs, which together generate approximately 8,374 MWt, have operated collectively since 1988. A large database of environmental results for the exposure pathways has been collected and analyzed to determine the effect from reactor operations.

2.2 SITE DESCRIPTION The NMP site is located on the southeast shore of Lake Ontario in the town of Scriba, approximately 6.2 miles northeast of the city of Oswego. The nearest metropolitan area is located approximately 36 miles south southeast of the site. The reactors and support buildings occupy a small shoreline portion of the 900-acre site. The land, soil of glacier deposits, rises gently from the lake in all directions. Oswego County is a rural environment, with about 15% of the land devoted to agriculture.

2-1

2.3 PROGRAM OBJECTIVES The objectives of the REMP are to:

1. Measure and evaluate the effects of plant operation on the environs and to verify the effectiveness of the controls on radioactive material sources.

2.

Monitor natural radiation levels in the environs of the NMP site.

3. Demonstrate compliance with the requirements of applicable federal regulatory agencies, including Technical Specifications and the Offsite Dose Calculation Manuals.

2-2

3.0 PROGRAM DESCRIPTION To achieve the objectives listed in Section 2.3, an extensive sampling and analysis program is conducted every year.

The Nine Mile Point Nuclear Station (NMPNS) Radiological Environmental Monitoring Program (REMP) consists of sampling and analysis of various media that include:

Air Fish Food Products Milk Shoreline Sediment Surface Waters Groundwater In addition, direct radiation measurements are performed using thermoluminescent dosimeters (TLDs).

These sampling programs are outlined in Table 3.0-1 and Table 3.0-2. The NMPNS REMP sampling locations are selected and verified by an annual land use census. The accuracy and precision of the sample analysis program is assured by participation in an Interlaboratory Comparison Quality Assurance Program (ICQAP). In addition to the participation in the ICQAP, sample splits are provided to the New York State.

Department of Health for cross-checking purposes.

Sample collections for the radiological program are accomplished by a dedicated site environmental staff from both the NMPNS and James A. FitzPatrick Nuclear Power Plant (JAFNPP). The site staff is assisted by a contracted environmental engineering company, EA Engineering, Science and Technology, Inc. (EA).

3-1

TABLE 3.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 1 Exposure Pathway and/or Sample Number of Samples (a) and Locations Sampling and Collection Frequency (a)

Type of Analysis and Frequency AIRBORNE

a. Radioiodine and Particulates Samples from five locations:

1. Three samples from offsite locations in different sectors of the highest calculated site average D/Q (based on all site licensed reactors).

2. One sample from the vicinity of an established year round community having the highest calculated site average D/Q (based on all site licensed reactors).

3. One sample from a control location 10-17 miles distant and in a least prevalent wind direction (d).

32 stations with two or more dosimeters to be placed as follows: an inner ring of stations in the general area of the site boundary and an outer ring in the 4 to 5 mile range from the site with a station in each land based sector (*)- The balance of the stations should be placed in special interest areas such as population centers, nearby residences, schools and in 2 or 3 areas to serve as control stations.

Continuous sampler operation with sample collection weekly or as required by dust loading, whichever is more frequent.

Radioiodine Canisters -

Analyze once per week for 1-131.

Particulate Samplers - Gross beta radioactivity following filter change (").

Composite (by location) for gamma isotopic analysis (c) once per 3 months (as a minimum).

b. Direct Radiation (e)

Once per 3 months.

Gamma dose once per 3 months.

At this distance, 8 wind rose sectors, (W, WNW, NW, NNW, N, NNE, NE, and ENE) are over Lake Ontario.

3-2

TABLE 3.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 1 Exposure Pathway and/or Samole Number of Samples (a) and Locations Sampling and Collection Freauencv (a)

Type of Analysis and Freciuencv WATERBORNE

a. Surface M0

1. One sample upstream.

Composite sample over I month period (g).

2. One sample from the site's downstream cooling water intake.

One sample from a downstream area with existing or potential recreational value.

Gamma isotopic analysis (c) once per month. Composite for once per 3 months tritium analysis.

Gamma isotopic analysis(c).

b.

Sediment from Shoreline Twice per year.

INGESTION

a. Milk

1. Samples from milk sampling locations in three locations within 3.5 miles distance having the highest calculated site average D/Q. If there are none, then one sample from milking animals in each of 3 areas 3.5 - 5.0 miles distant having the highest calculated site average D/Q (based on all site licensed reactors).

2.

One sample from a milk sampling location at a control location (9-20 miles distant and in a least prevalent wind direction) 0d).

Twice per month, April -

December (samples will be collected in January - March if 1-131 is detected in November and December of the preceding year).

Gamma isotopic (c) and I-131 analysis twice per month when animals are on pasture (April - December); once per month at other times (January

- March) if required.

3-3

TABLE 3.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 1 Exposure Pathway and/or Sample Number of Samples (a) and Locations Sampling and Collection Frequency (a)

Type of Analysis and Frequency

b. Fish

1. One sample each of two commercially or recreationally important species in the vicinity of a plant discharge area (h).

2. One sample each of the same species from an area at least 5 miles distant from the site (d)

Twice per year.

Gamma isotopic analysis (C) on edible portions twice per year.

c. Food Products

1. Samples of three different kinds of broad leaf Once per year during harvest vegetation (such as vegetables) grown nearest to each season.

of two different off-site locations of highest calculated site average D/Q (based on all licensed site reactors).

2. One sample of each of the similar broad leaf vegetation grown at least 9.3 - 20 miles distant in a least prevalent wind direction.

Gamma isotopic (c) analysis of edible portions (Isotopic to include 1-131 or a separate I-131 analysis may be performed) once during the harvest season.

3-4

NOTES FOR TABLE 3.0-1 (a)

It is recognized that, at times, it may not be possible or practical to obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and may be substituted. Actual locations (distance and directions) from the site shall be provided in the Annual Radiological Environmental Operating Report. Highest D/Q locations are based on historical meteorological data for all site licensed reactors.

(b)

Particulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If the gross beta activity in air is greater than 10 times a historical yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(c)

Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

(d)

The purpose of these samples is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites, such as historical control locations which provide valid background data may be substituted.

(e)

One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously, may be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter may be considered to be one phosphor, and two or more phosphors in a packet may be considered as two or more dosimeters. Film badges shall not be used for measuring direct radiation.

(f)

The "upstream sample" should be taken at a distance beyond significant influence of the discharge. The "downstream sample" should be taken in an area beyond but near the mixing zone, if possible.

(g)

Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g. hourly) relative to the compositing period (e.g. monthly) in order to assure obtaining a representative sample.

(h)

In the event commercial or recreational important species are not available as a result of three attempts, then other species may be utilized as available.

3-5

TABLE 3.0-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway and/or Sample Number of Samples and Sample Locations (a)

Sampling and Collection Frequencv Type of Analysis and Frequency AIRBORNE

a. Direct Radiation 32 routine monitoring stations (b) either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

1. An inner ring of stations, one in each meteorological sector in the general area of the Site Boundary.

2.

An outer ring of stations, one in each land base meteorological sector in the 4 to 5 mile (c) range from the site.

3.

The balance of the stations should be placed in special interest areas such as population centers, nearby residences, schools, and in one of two areas to serve as control stations (d).

Once per 3 months.

Gamma dose once per 3 months.

3-6

TABLE 3.0-2 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway and/or Sample Number of Samples and Sample Locations (a)

Sampling and Collection Frequency Type of Analysis and Frequency

b. Airborne Radioiodine Samples from five locations:

and Particulates

1. Three samples from off-site locations close to the site boundary (within one mile) in different sectors of the highest calculated annual site average ground-level D/Q (based on all site licensed reactors)(').

Continuous sampler operation with sample collection weekly, or more frequently if required by dust loading.

2.

One sample from the vicinity of an established year-round community having the highest calculated annual site average ground-level D/Q (based on all site licensed reactors)(e).

3.

One sample from a control location at least 10 miles distant and in a least prevalent wind direction

.o)

Radioiodine Canister:

1-131 analysis weekly.

Particulate Sampler:

1. Gross beta radioactivity analysis > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change"),

2.

Gamma isotopic analysis on each sample where gross beta activity is >10 times the previous yearly mean of control samples, and

3. Gamma isotopic analysis (g) of composite sample (by location) once per 3 months.

WATERBORNE

a. Surface

1. One sample upstream (d)

(h)

2.

One sample from the site's downstream cooling water intake N.

Composite sample over 1-month period (0)

Gamma isotopic analysis Wg) once per month and tritium analysis once per 3 months.

3-7

TABLE 3.0-2 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway and/or Sample Number of Samples and Sample Locations (a)

Sampling and Collection Freauencv Type of Analysis and Freciuencv

b. Ground Samples from one or two sources if likely to be affected 0.

Grab sample once per 3 months.

c. Drinking

d.

Sediment from Shoreline One sample each of one to three of the nearest water supplies that could be affected by its discharge (k).

One sample from a downstream area with existing or potential recreational value.

When 1-131 analysis is performed, a composite sample over a 2-week period();

otherwise, a composite sample monthly.

Gamma isotopic (g) and tritium analysis once per 3 months.

1. 1-131 analysis on each composite when the dose calculated for the consumption of the water is greater than 1 mrem per year(t.

2.

Composite for gross beta and gamma isotopic analyses (g) monthly.

3.

Composite for tritium analysis once per 3 months.

Gamma isotopic analysis(g).

Twice per year.

3-8

TABLE 3.0-2 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway and/or Sample Number of Samples and Sample Locations (a)

Sampling and Collection Frequency Type of Analysis and FreQuency INGESTION

a.

Milk

1. Samples from Milk Sampling Locations in three locations within 3.5 miles(e) distance having the highest calculated annual site average D/Q (based on all licensed site reactors).

2. If there are none, then 1 sample from Milk Sampling Locations in each of three areas 3.5 - 5.0 miles(e) distant having the highest calculated annual site average D/Q (based on all licensed site reactors).

3.

One sample from a Milk Sample Location at a control location 9 - 20 miles distant and in a least prevalent wind direction (d).

1. One sample each of two commercially or recreationally important species in the vicinity of a plant discharge area (n.

2.

One sample of the same species in areas not influenced by station discharge {d Twice per month, April -

December (samples will be collected January - March if I-131 is detected in November and December of the preceding year)(m).

1. Gamma isotopic (g) and 1-131 analysis twice per month when animals are on pasture (April -

December);

2.

Gamma isotopic (g) and 1-131 analysis once per month at other times (January

- March, if required).

b.

Fish Twice per year.

Gamma isotopic analysis (g) on edible portions twice per year.

3-9

TABLE 3.0-2 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway and/or Sample Number of Samples and Sample Locations (a)

Sampling and Collection Frequency Type of Analysis and Frequency

c. Food Products

1. One sample of each principal class of food products from any area that is irrigated by water in which liquid plant wastes have been discharged (o).

2.

Samples of three different kinds of broad leaf vegetation (such as vegetables) grown nearest to each of two different off-site locations of highest calculated annual site average D/Q (based on all licensed site reactors)(e).

3. One sample of each of the similar broad leaf vegetation grown at least 9.3 miles distant in a least prevalent wind direction.

At time of harvest (P).

Gamma isotopic (g) and I-131 analysis of each sample of edible portions.

Once per year during the harvest season.

3-10

NOTES FOR TABLE 3.0-2 (a)

Specific parameters of distance and direction sector from the centerline of one reactor, and additional descriptions where pertinent, shall be provided for each and every sample location in Table 3.0-2. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"

October 1978, and to Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable because of such circumstances as hazardous conditions, seasonal unavailability (which includes theft and uncooperative residents), or malfunction of automatic sampling equipment.

(b)

One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously, may be used in place of, or in addition to, integrating dosimeters. Each of the 32 routine monitoring stations shall be equipped with 2 or more dosimeters or with 1 instrument for measuring and recording dose rate continuously. For the purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor, two or more phosphors in a packet are considered as two or more dosimeters.

Film badges shall not be used as dosimeters for measuring direct radiation.

(c)

At this distance, 8 wind rose sectors, (W, WNW, NW, NNW, N, NNE, NE, and ENE) are over Lake Ontario.

(d)

The purpose of these samples is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites, which provide valid background data, may be substituted.

(e)

Having the highest calculated annual site average ground-level D/Q based on all site licensed reactors.

(f)

Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay.

(g)

Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

(h)

The "upstream" sample shall be taken at a distance beyond significant influence of the discharge. The "downstream" sample shall be taken in an area beyond but near the mixing zone.

(i)

In this program, representative composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

(I)

Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

(k)

Drinking water samples shall be taken only when drinking water is a dose pathway.

(1)

Analysis for 1-131 may be accomplished by Ge-Li analysis, provided that the lower limit of detection (LLD) for 1-131 in water samples found on Table 3.7-1 can be met. Doses shall be calculated for the maximum organ and age group.

(in)

Samples will be collected January through March if 1-131 is detected in November and December of the proceeding year.

3-11

NOTES FOR TABLE 3.0-2 (continued)

(n)

In the event two commercially or recreationally important species are not available after three attempts of collection, then two samples of one species or other species not necessarily commercially or recreationally important may be utilized.

(o)

Applicable only to major irrigation projects within 9 miles of the site in the general down current direction.

(p)

If harvest occurs more than once/year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be taken monthly. Attention shall be paid to including samples of tuberous and root food products.

3-12

3.1 SAMPLE COLLECTION METHODOLOGY 3.1.1 SHORELINE SEDIMENTS Shoreline sediment is collected at one area of existing or potential recreational value. One sample is also collected from a location beyond the influence of the site. Samples are collected as surface scrapings to a depth of approximately one inch. The samples are placed in plastic bags, sealed and shipped to the lab for analysis. Sediment samples are analyzed for gamma-emitting radionuclides.

Shoreline sediment sample locations are shown in Section 3.3, Figure 3.3-5.

3.1.2 FISH Samples of available fish species that are commercially or recreationally important to Lake Ontario, such as lake trout, salmon, walleye, and smallmouth bass, are collected twice per year, once in the spring and again in the fall. Indicator samples are collected from a combination of the two on-site sample transects located offshore from the site. One set of control samples are collected at an off-site sample transect located offshore, 8 - 10 miles west of the site. Available species are selected using the following guidelines:

a.

A minimum of two species that are commercially or recreationally important are to be collected from each sample location. Samples selected are limited to edible and/or sport species when available.

b.

Samples are composed of the edible portion only.

Selected fish samples are frozen after collection and segregated by species and location. Samples are shipped frozen in insulated containers for analysis. Edible portions of each sample are analyzed for gamma-emitting radionuclides.

Fish collection locations are shown in Section 3.3, Figure 3.3-5.

3.1.3 SURFACE WATER Surface water samples are taken from the respective inlet canals of the JAFNPP and the NRG Oswego Generating Station. The JAFNPP facility draws water from Lake Ontario on a continuous basis. This is used for the "downstream" or indicator sampling point for the Nine Mile Point site. The Oswego Generating Station inlet canal removes water from Lake Ontario at a point approximately 7.6 miles west of the site. This "upstream" location is considered a control location because of the distance from the site as well as the result of the lake current patterns and current patterns from the Oswego River located nearby.

Samples from the JAFNPP facility are composited from automatic sampling equipment, which discharges into a compositing tank or bottles. Samples are collected monthly from the compositor and analyzed for gamma emitters. Samples from the Oswego Generating Station are also obtained using automatic sampling equipment and collected in a holding tank. Representative samples from this location are obtained weekly 3-13

and are composited to form a monthly composite sample. The monthly samples are analyzed for gamma emitting radionuclides.

A portion of the monthly sample from each of the locations is saved and composited to form quarterly composite samples which are analyzed for tritium.

In addition to the sample results for the JAFNPP and Oswego Generating Station collection sites, data is presented for the Nine Mile Point Unit 1 (NMPl) and Nine Mile Point Unit 2 (NMP2) facility inlet canal samples and from the City of Oswego drinking water supply. These three locations are not required by the ODCM. These locations are optional sample points which are collected and analyzed to enhance the surface water sampling program. Monthly composite samples from these three locations are analyzed for gamma emitting nuclides and quarterly composite samples are analyzed for tritium.

Sampling for groundwater and drinking water, as found in Section D 3.5.1 of the NMP2 ODCM, was not required during 2014. There was no groundwater source in 2014 that was tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties support contamination migration; therefore, drinking water was not a dose pathway during 2014.

Surface water sample locations are shown in Section 3.3, Figure 3.3-4.

3.1.4 GROUNDWATER MONITORING PROGRAM The Nuclear Energy Institute (NEI) Groundwater Protection Initiative was established to determine the potential impact nuclear power plants may have on the surrounding environment due to unplanned releases of radioactive liquids. Under the NEI 07-07 Groundwater Protection Initiative (GPI) - Final Guidance Document, August 2007, groundwater monitoring is accomplished through sampling of the water table around the plant and analyzing for tritium. In addition to the groundwater monitoring requirements specified in the NMP2 ODCM, NMPNS started monitoring groundwater wells in October 2005 and has been monitoring the plant dewatering systems as part of the response to Generic Letter 80-10 for several years.

Samples collected from these locations are analyzed for tritium, gamma emitters, and strontium.

During the operating year 2014, there were no unplanned releases or spills of radioactive liquids on the NMPNS site.

Groundwater samples are analyzed using liquid scintillation detection and gamma isotopic analysis.

Groundwater tritium results are documented in the 2014 Annual Radiological Effluent Release Report.

Historical groundwater data is presented in Section 7, Historical Data Tables.

Groundwater sample locations are shown in Section 3.3, Figure 3.3-6.

3-14

3.1.5 AIR PARTICULATE / IODINE The air sampling stations required by the ODCM are located in the general area of the site boundary. The sampling stations are sited within a distance of 0.2 miles of the site boundary in sectors with the highest calculated annual site average ground-level deposition factor (D/Q) based on historical meteorological data.

These stations (R-l, R-2, and R-3) are located in the E, ESE, and SE sectors as measured from the center of the NMP2 Reactor Building. The ODCM also requires that a fourth air sampling station be located in the vicinity of a year-round community. This station is located in the SE sector at a distance of 1.8 miles and is designated as Station R-4. A fifth station required by the ODCM is a control location designated as Station R-5. Station R-5 is located 16.2 miles from the site in the NE meteorological sector.

In addition to the five ODCM required locations, there are ten additional sampling stations. Six of these sampling stations are located within the site boundary and are designated as Onsite Stations D1, G, H, I, J, and K. These locations are within the site boundary of the NMPNS and JAFNPP. One air sampling station is located offsite in the SW sector in the vicinity of the City of Oswego and is designated as Offsite Station G. Three remaining air sampling stations are located in the ESE, SSE, and SSW sectors and range in distance from 7.1 to 9.0 miles. These are designated as Offsite Stations D2, E and F, respectively.

Each station collects airborne particulates using glass fiber filters (47 millimeter diameter) and radioiodine using charcoal sample cartridges (2 x 1 inches). The samplers run continuously and the charcoal cartridges and particulate filters are changed on a weekly basis. Sample volume is determined by use of calibrated gas flow meters located at the sample discharge. Gross beta analysis is performed on each particulate filter.

Charcoal cartridges are analyzed for radioiodine using gamma spectral analysis. The particulate filters are composited quarterly by location and analyzed for gamma-emitting radionuclides.

Air sampling station locations (Environmental Stations) are shown in Section 3.3, Figures 3.3-2 and 3.3-3.

3.1.6 THERMOLUMINESCENT DOSIMETERS (DIRECT RADIATION)

Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the environment. Environmental TLDs are supplied and processed quarterly by the Environmental Dosimetry Company. The laboratory utilizes a Panasonic based system using UD-814 dosimeters that are constructed of rectangular teflon wafers impregnated with 25% CaSO4:Dy phosphor. Each dosimeter contains three calcium sulfate elements and one lithium borate element.

1. Environmental TLDs Environmental TLDs are placed in five different geographical regions around the site to evaluate effects of direct radiation as a result of plant operations. The following is a description of the five TLD geographical categories used in the NMPNS and JAFNPP Environmental Monitoring Program and the TLDs that make up each region:

3-15

TLD Geographical Category Description Onsite Site Boundary Offsite TLDs placed at various locations within the Site Boundary are not required by the ODCM, with the exception of TLD # 7, 18 and 23. (TLD locations comprising this group are: 3, 4, 5, 6, 7*, 18*, 23*, 24, 25, 26, 27, 28, 29, 30, 31, 39, 47, 103, 106 and 107)

An inner ring of TLDs placed in the general area of the Site Boundary in each of the sixteen meteorological sectors. This category is required by the ODCM. (TLD locations comprising this group are: 7*, 18*, 23*, 75*, 76*,

77*, 78*, 79*, 80*, 81*, 82*, 83*, 84*, 85*, 86*, and 87*)

An outer ring of TLDs placed 4 to 5 miles from the site in each of the eight land-based meteorological sectors.

This category is required by the ODCM. (TLD locations comprising this group are 88*, 89*, 90*, 91*, 92*,

93*, 94*, and 95*)

TLDs placed in Special Interest areas of high population density and use.

These TLDs are located at or near large industrial sites, schools, or nearby towns or communities. This category is required by the ODCM. (TLD locations comprising this group are: 9, 10, 11, 12, 13, 15*, 19, 51, 52, 53, 54, 55, 56*, 58*, 96*, 97*, 98*, 99, 100, 101, 102, 108, and 109)

TLDs placed in areas beyond significant influence of the site and plant operations. These TLDs are located to the SW, S and NE of the site at distances of 12.6 to 24.7 miles. This category is also required by the ODCM. (TLD locations comprising this group are 8, 14*, 49*, 111, 113)

Special Interest Control TLD location required by ODCM The ODCM requires a total of 32 TLD stations. Environmental TLDs are also placed at additional locations not required by the ODCM, within the Onsite, Special Interest and Control TLD categories to supplement the ODCM required direct radiation data.

Two dosimeters are placed at each TLD monitoring location. The TLDs are sealed in polyethylene packages to ensure dosimeter integrity, placed in open webbed plastic holders, and attached to supporting structures, such as utility poles.

Environmental TLD locations are shown in Section 3.3, Figures 3.3-2 and 3.3-3.

3-16

2.

Independent Spent Fuel Storage Installation (ISFSI)

In order to provide adequate spent fuel storage capacity at NMP1 and NMP2, NMPNS constructed an ISFSI onsite west of NMP1. During 2012 the NMPNS ISFSI facility was placed into service.

TLDs are used to monitor direct radiation levels in the vicinity of the ISFSI facility. Sixteen (16) TLD locations were established around the site boundary. Background data has been collected from the initiation of the NMPNS REMP TLD program in 1985.

In addition, fourteen (14) Optically Stimulated Luminescence Dosimeters (OSDLs) are located around the ISFSI and in areas where personnel are assigned routine work activities. These locations are designated as optional locations. Background data was collected starting in June, 2011.

REMP TLD locations are shown in Section 3.3, Table 3.3. 1.

3.1.7 MILK Milk samples are routinely collected from farms during the sampling year. These farms include one indicator location and one control location. Samples are normally collected April through December of the sample year. If plant-related radionuclides are detected during November and December of the previous year, milk collections are continued into the following year, starting in January. If plant-related radionuclides are not detected in the November and December samples, then milk collections do not commence until April of the next sampling year. Milk samples were not collected in January through March of 2014, as there were no positive detections of plant related radionuclides in samples collected during November and December 2013.

The ODCM also requires that a sample be collected from a control location nine to twenty miles from the site and in a least prevalent wind direction. This location, No. 77, is in the south sector at a distance of 16 miles and serves as the control location.

Milk samples are collected in polyethylene bottles from a bulk storage tank at each sampled farm. Before the sample is drawn, the tank contents are agitated to assure a homogenous mixture of milk and butterfat.

Two gallons are collected from each indicator and control location during the first half and second half of each month. The samples are chilled, preserved and shipped fresh to the analytical laboratory within thirty-six hours of collection, in insulated shipping containers.

The milk sample locations are shown in Section 3.3, Figure 3.3-4.

3-17

3.1.8 FOOD PRODUCTS (VEGETATION)

Food products are collected once per year during the late summer harvest season. A minimum of three different kinds of broadleaf vegetation, edible or inedible, is collected from two different indicator garden locations. Sample locations are selected from gardens identified in the annual census that have the highest calculated annual site average D/Q values based on historical site meteorological data. Control samples are also collected from available locations greater than 9.3 miles distant from the site in a least prevalent wind direction. Control samples are of the same or similar type of vegetation when available.

Food product samples are analyzed for gamma emitters using gamma isotopic.

Food product locations are shown in Section 3.3, Figure 3.3-5.

3.2 ANALYSES PERFORMED The following environmental sample analyses are performed by the JAFNPP laboratory, the Nine Mile Point Nuclear Station Laboratory, or by a contract Laboratory:

Air Particulate Filter - Gross Beta Air Particulate Filter Composites - Gamma Spectral Analysis Airborne Radioiodine - Gamma Spectral Analysis Direct Radiation using Thermoluminescent Detectors (TLDs) - Analyses performed by a contractor laboratory - Environmental Dosimetry Company.

Fish - Gamma Spectral Analysis Food Products (Vegetation) - Gamma Spectral Analysis and 1-131 Milk - Gamma Spectral Analysis and 1-131 Shoreline Sediment - Gamma Spectral Analysis

" Special Samples (soil, food products, bottom sediment, etc.) - Gamma Spectral Analysis Surface Water Monthly Composites - Gamma Spectral Analysis and 1-131 Surface Water Quarterly Composites - Tritium Groundwater Quarterly Samples - Gamma Spectral Analysis and Tritium Groundwater Quarterly Samples - Strontium analysis performed by a contractor laboratory - GEL Laboratories, LLC 3.3 SAMPLE LOCATIONS Figures 3.3-1 through 3.3-6 provide maps illustrating sample locations. Sample locations referenced as letters and numbers on the report period data tables are consistent with designations plotted on the maps.

3-18

This section also contains an environmental sample location reference table (Table 3.3-1). This table contains the following information:

Sample medium Map designation, (this column contains the key for the sample location and is consistent with the designation on the sample location maps and on the sample results data tables)

Figure number

" Location description

" Degrees and distance of the sample location from the site 3-19

TABLE 3.3-1 2014 ENVIRONMENTAL SAMPLE LOCATIONS MAP DEGREES & DISTANCE SAMPLE MEDIUM DESIGNATION FIGURE NUMBER LOCATION DESCRIPTION (c & d)

(a & b)

Shoreline Sediment 5*

6 Fish Surface Water Air Radioiodine and Particulates 02*

03*

00*

03*

08*

09 10 11 R-l*

R-2*

R-3*

R-4*

R-5*

D1 G

H I

J K

G D2 E

F Figure 3.3-5 Figure 3.3-5 Figure 3.3-5 Figure 3.3-5 Figure 3.3-5 Figure 3.3-4 Figure 3.3-4 Figure 3.3-4 Figure 3.3-4 Figure 3.3-4 Figure 3.3-2 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-2 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Sunset Bay Langs Beach, Control Nine Mile Point Transect FitzPatrick Transect Oswego Transect - Control 2900 620 2370 at at at FitzPatrick Inlet Oswego Generating Station Inlet - Control NMP1 Inlet Oswego City Water NMP2 Inlet R-1 Station, Nine Mile Point Road R-2 Station, Lake Road R-3 Station, Co. Rt. 29 R-4 Station, Co. Rt. 29 R-5 Station, Montario Point - Control Dl On-Site Station G On-Site Station H On-Site Station I On-Site Station J On-Site Station K On-Site Station G Off-Site Station, Saint Paul Street D2 Off-Site Station, Rt. 64 E Off-Site Station, Rt. 4 F Off-site Station, Dutch Ridge Road 840 at 1.2 miles 2320 at 4.8 miles 710 at 2360 at 3190 at 2400 at 3360 at 3530 at 920 1060 1340 1450 420 730 2440 740 960 1100 1330 2260 1180 1620 1920 at at at at at at at at at at at at at at at 0.4 miles 0.8 miles 5.9 miles 0.5 miles 7.6 miles 0.3 miles 7.8 miles 0.3 miles 0.3 miles 1.8 miles 1.1 miles 1.4 miles 1.8 miles 16.2 miles 0.3 miles 0.7 miles 0.8 miles 0.8 miles 0.9 miles 0.5 miles 5.4 miles 9.0 miles 7.1 miles 7.6 miles 3 - 20

TABLE 3.3-1 (continued) 2014 ENVIRONMENTAL SAMPLE LOCATIONS MAP DEGREES & DISTANCE SAMPLE MEDIUM DESIGNATION FIGURE NUMBER LOCATION DESCRIPTION (c & d)

(a & b)

Thermoluminescent Dosimeters (TLD) 3 4

5 6

7*

8 9

10 11 12 13 14*

15*

18*

19 23*

24 25 26 27 28 29 30 31 39 47 49*

51 52 53 54 55 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-3 Figure 3.3-2 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 DI On-Site Station D2 On-Site Station E On-Site Station F On-Site Station G On-Site Station R-5 Off-Site Station - Control Dl Offsite - State Route 3 D2 Off-Site Station E Off-Site Station F Off-Site Station G Off-Site Station Southwest Oswego - Control West Site Boundary Energy Information Center East Site Boundary H On-Site Station I On-Site Station J On-Site Station K On-Site Station North Fence, JAFNPP North Fence, JAFNPP North Fence JAFNPP North Fence JAFNPP North Fence NMP 1 North Fence NMP 1 North Fence JAFNPP Phoenix, NY - Control Oswego Generating Station, East Fitzhugh Park Elementary School, East Fulton High School Mexico High School Pulaski Gas Substation, Rt. 5 730 1430 1500 2130 2440 420 800 1180 1620 1920 2260 2270 2390 2660 830 740 960 1100 1330 600 680 650 570 2780 2960 690 1680 2340 2270 1830 1150 750 0.3 miles 0.4 miles 0.4 miles 0.5 miles 0.7 miles 16.2 miles 11.4 miles 9.0 miles 7.1 miles 7.7 miles 5.4 miles 12.5 miles 0.9 miles 0.5 miles 1.4 miles 0.8 miles 0.8 miles 0.9 miles 0.5 miles 0.4 miles 0.5 miles 0.5 miles 0.4 miles 0.2 miles 0.2 miles 0.6 miles 19.7 miles 7.3 miles 5.9 miles 13.7 miles 9.4 miles 13.0 miles 3-21

TABLE 3.3-1 (continued) 2014 ENVIRONMENTAL SAMPLE LOCATIONS MAP DEGREES & DISTANCE SAMPLE MEDIUM DESIGNATION FIGURE NUMBER LOCATION DESCRIPTION (c & d)

(a & b)

Thermoluminescent Dosimeters (TLD)

(Continued) 56*

58*

75*

76*

77*

78*

79*

80*

81*

82*

83*

84*

85*

86*

87*

88*

89*

90*

91

92*

93*

94*

95*

96*

97*

98*

99 100 101 102 103 104 Figure 3.3-2 Figure 3.3-2 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-3 Figure 3.3-2 Figure 3.3-2 Figure 3.3-3 Figure 3.3-3 Figure 3.3-2 Figure 3.3-3 Figure 3.3-2 New Haven Elementary School County Route lA and Alcan North Fence, NMP2 North Fence, NMP2 North Fence, NMP2 East Boundary, JAFNPP County Route 29 County Route 29 Miner Road Miner Road Lakeview Road Lakeview Road North Fence, NMP 1 North Fence, NMP 1 North Fence, NMP2 Hickory Grove Road Leavitt Road Route 104 and Keefe Road County Route 51 A Maiden Lane Road County Route 53 County Route 1 and Kocher Road Lakeshore Camp Site Creamery Road County Route 29 Lake Road Nine Mile Point Road County Route 29 and Lake Road County Route 29 Oswego County Airport Energy Center, East Parkhurst Road 1240 2220 3540 270 370 860 1210 1360 1600 1800 2030 2250 2900 3100 3320 970 1120 1350 1570 1830 2060 2240 2390 1990 1450 1030 920 1060 1340 1750 2680 1020 5.2 miles 3.0 miles 0.1 miles 0.1 miles 0.2 miles 1.0 miles 1.2 miles 1.5 miles 1.7 miles 1.6 miles 1.2 miles 1.1 miles 0.2 miles 0.1 miles 0.1 miles 4.5 miles 4.3 miles 4.2 miles 4.9 miles 4.5 miles 4.4 miles 4.4 miles 3.7 miles 3.7 miles 1.8 miles 1.2 miles 1.8 miles 1.1 miles 1.4 miles 11.9 miles 0.4 miles 1.4 miles 3 - 22

TABLE 3.3-1 (continued) 2014 ENVIRONMENTAL SAMPLE LOCATIONS MAP DEGREES & DISTANCE SAMPLE MEDIUM DESIGNATION FIGURE NUMBER LOCATION DESCRIPTION (c & d)

(a & b)

Thermoluminescent 105 Figure 3.3-3 Lakeview Road 1990 at 1.4 miles Dosimeters (TLD) 106 Figure 3.3-3 Shoreline Cove, West of NMPI 2720 at 0.3 miles (Continued) 107 Figure 3.3-3 Shoreline Cove, West of NMP1 2710 at 0.3 miles 108 Figure 3.3-3 Lake Road 1050 at 1.1 miles 109 Figure 3.3-3 Lake Road 1040 at 1.1 miles 111 Figure 3.3-2 Sterling, NY-Control 214' at 21.8 miles 112 Figure 3.3-2 EOF/Env. Lab, Oswego County Airport 175' at 11.9 miles 113 Figure 3.3-2 Baldwinsville, NY - Control 1780 at 24.7 miles Cow Milk 55 Figure 3.3-4 Indicator Location 970 at 8.8 miles 77*

Figure 3.3-4 Control Location 1900 at 16.0 miles Food Products 133**

Figure 3.3-5 Indicator Location 840 at 1.6 miles 134**

Figure 3.3-5 Indicator Location 840 at 1.5 miles 144*

Figure 3.3-5 Indicator Location 1390 at 1.6 miles 145*

Figure 3.3-5 Control Location 2220 at 15.4 miles 484*

Figure 3.3-5 Indicator Location 1320 at 1.4 miles MW 1,2, 4-13, Groundwater**

15-21 Figure 3.3-6 Down Gradient Wells - Indicator 2580 to 78' at <0.3 miles GMX-MW-1 Figure 3.3-6 Upland Well - Control 1600 at 0.3 miles GMX-MW-2 Figure 3.3-6 Upland Well - Control 1980 at 0.3 miles MW-B 119 Figure 3.3-6 Upland Well - Control 1950 at 0.8 miles MW-14 Figure 3.3-6 Control 1870 at 0.2 miles Storm Drain Figure 3.3-6 NMP2 Dewatering System - Indicator 320 at <0.1 miles Table Notes:

(a) Sample Locations marked by an asterisk (*) are locations required by ODCM (b) Sample Locations marked by an double asterisk (**) are optional locations (c) Degrees and Distance based on Nine Mile Point Unit 2 Reactor Centerline (d) Degrees and Distances updated by Global Positioning System (GPS) 3 - 23

Figure 3.3-1 FIGURE 3.3-1 NEW YORK STATE MAP VERMONT NEW YORK /

LAKE

+

'/

BUFFALOCHI*R MASSACHIJSETTS PENmISYLVANA N*NINE MILE POINT SITE:

Nine Mile Point Nuclear Station Unit - 1 Nine Mile Point Nuclear Station Unit - 2 James A. FitzPatrickf.W JERSEY Nuclear Power Plant NW W cT 3 - 24

FIGURE 3.3-2 OFF-SITE ENVIRONMENTAL STATION AND TLD LOCATIONS KEY:

STLD LOCATION ENVIRONMENTAL STATION Montaro Lake Ontario Oswego County New York 78.750 SCALE IN MILES 0

1 2

3 4

5

.250 10 MI.

FSW 21 1,

S SW rS_-1 3SS-E2 3 -25

ISite Map 6.25' Lake Ontario ENE 348.75' 303.75' 0.5 Mile Radius 1 Mil Radius 101.25' WSW ESE 236.25"

.I SW 213.

SE 165.75' 146.25' FIGURE 3.3-3 ON-SITE ENVIRONMENTAL STATION AND TLD LOCATIONS KEY:

A ENVIRONMENTAL STATIONS O

TLD LOCATIONS SSE Scale

.1 (tenths) 0 (miles) 1

FIGURE 3.3-4 MILK AND SURFACE WATER SAMPLE LOCATIONS KEY:

SSURFACE WATER LOCATION MILK SAMPLE LOCATION Lake Ontario Oswego County New York SCALE IN MILES 0

1 2

3 4

5 E~E WSW 236.2!

FS7W Is swi FS-1 FS-SEI]

3 - 27

FIGURE 3.3-5 NEAREST RESIDENCE, FOOD PRODUCT FISH, AND SHORELINE SEDIMENT SAMPLE LOCATIONS

.78.750 250 mSI 3 - 28

FIGURE 3-3-6 NMPNS ON-SITE GROUNDWATER MONITORING WELLS AND UNIT 2 STORM DRAIN OUTFALL

- Monitoring Well Location

- Storm Drain Outfall 001 I

iv Unit 2 Storm 326.25 303.75 SSW Ur 168.75 IMW-B1 19 Ground Water Monitoring well is located south of Lake Road at a distance and direction of 1,355 yrds @ 195 degrees, (SSW). Based on NMP2 Rx Building.

SCALE (YARDS) 0 100 200 GMX-MW2 300 GMX-MWl 3 - 29

3.4 LAND USE CENSUS The ODCM requires that a milch animal census and a residence census be conducted annually out to a distance of five miles. Milch animals are defined as any animal that is routinely used to provide milk for human consumption.

The milch animal census is an estimation of the number of cows and goats within an approximate ten-mile radius of the Nine Mile Point site. This census is performed once per year in the summer by sending questionnaires to previous milch animal owners, and by road surveys to locate any possible new owners. In the event that questionnaires are not answered, the owners are contacted by telephone or in person. The Oswego County Cooperative Extension Service is also contacted to provide any additional information.

The residence census is conducted each year to identify the closest residence in each of the 22.5 degree meteorological sectors out to a distance of five miles. A residence, for the purposes of this census, is a residence that is occupied on a part-time basis (such as a summer camp), or on a full-time, year-round basis.

Several of the site meteorological sectors are located over Lake Ontario; therefore, there are only eight sectors over land where residences are located within five miles.

In addition to the milch animal and residence census, a garden census is performed. The census is conducted each year to identify the gardens near the site that are to be used for the collection of food product samples.

The results of the garden census are not provided in this report. The results are used only to identify appropriate sample locations. The garden census is not required by the ODCMs if broadleaf vegetation sampling and analysis is performed.

3.5 CHANGES TO THE REMP PROGRAM There were no changes to the 2014 REMP sampling program.

3.6 DEVIATIONS AND EXCEPTIONS TO THE PROGRAM The noted exceptions to the 2014 sample program address only those samples or monitoring requirements which are required by the ODCM. This section satisfies the reporting requirements of Section D 6.9.1.d of the NMP1 ODCM and Section D 4.1.2 of the NMP2 ODCM.

A.

ODCM PROGRAM DEVIATIONS The following are the deviations from the program specified by the NMP1 and NMP2 ODCM:

1.

The air station sample pumps at RI and R2 off-site environmental sampling stations were inoperable for approximately 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months during the sampling period of July 7, 2014 to July 15, 2014. The sample pump out-of-service time was determined based on the sample pump run 3 - 30

time integrator. The inoperability of the pumps was due to loss of power to the air station.

No corrective actions were required to restore power to the air stations.

B.

AIR SAMPLING STATION OPERABILITY ASSESSMENT The ODCM-required air sampling program consists of 5 individual sampling locations.

The collective operable time period for the air monitoring stations was 44,830 hours0.00961 days 0.231 hours 0.00137 weeks 3.15815e-4 months out of a possible 42,840 hours0.00972 days 0.233 hours 0.00139 weeks 3.1962e-4 months . The air sampling availability factor for the reporting period was 99.9%.

3.7 STATISTICAL METHODOLOGY There are a number of statistical calculation methodologies used in evaluating the data from the environmental monitoring program. These methodologies include determination of standard deviation, the mean and associated error for the mean and the lower limit of detection (LLD).

3.7.1 ESTIMATION OF THE MEAN AND STANDARD DEVIATION The mean, (X), and standard deviation, (s), were used in the reduction of the data generated by the sampling and analysis of the various media in the NMPNS REMP. The following equations were utilized to compute the mean (X) and the standard deviation (s):

n A.

Mean x

=-zxi i=1 N

Where, X

= estimate of the mean i

= individual sample, i N, n

= total number of samples with positive indications Xi

= value for sample i above the lower limit of detection B.

Standard Deviation S=

'X

--X)2

=i

Where, X = mean for the values of X s = standard deviation for the sample population 3-31

3.7.2 ESTIMATION OF THE MEAN AND THE ESTIMATED ERROR FOR THE MEAN In accordance with program policy, two recounts of samples are performed when the initial count indicates the presence of a plant-related radionuclide(s). When a radionuclide is positively identified in two or more counts, the analytical result for the radionuclide is reported as the mean of the positive detections and the associated propagated error for that mean. In cases where more than one positive sample result is available, the mean of the sample results and the estimated error for the mean are reported in the Annual Report.

The following equations were utilized to estimate the mean (X) and the associated propagated error.

A.

Mean xi i=l N

Where, X

= estimate of the mean i

= individual sample, i N, n

= total number of samples with positive indications Xi

= value for sample i above the lower limit of detection B.

Error of the Mean ERROR MEAN = I Y (ERRoR)'l i=1 N

Where, ERROR MEAN i

= propagated error

= individual sample ERROR

= I sigma* error of the individual analysis N, n

= number of samples with positive indications Sigma (a)

Sigma is the Greek letter used to represent the mathematical term Standard Deviation.

Standard Deviation is a measure of dispersion from the arithmetic mean of a set of numbers.

3 - 32

3.7.3 LOWER LIMIT OF DETECTION (LLD)

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

The LLDs are specified by the ODCM for radionuclides in specific media and are determined by taking into account the overall measurement methods. The equation used to calculate the LLD is:

4.66 Sb LLD =

(E) (V) (2.22) (Y) exp (-XAt)

Where:

LLD =

the a priori lower limit of detection, as defined above (in picocuries per unit mass or volume)

Sb the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (in counts per minute)

E

=

the counting efficiency (in counts per disintegration)

V

=

the sample size (in units of mass or volume) 2.22 =

the number of disintegrations per minute per picocurie Y

=

the fractional radiochemical yield (when applicable)

X

=

the radioactive decay constant for the particular radionuclide At

=

the elapsed time between sample collection (or end of the sample collection period) and time of counting The ODCM LLD formula assumes that:

The counting times for the sample and background are equal The count rate of the background is approximately equal to the count rate of the sample.

In the ODCM program, LLDs are used to ensure that minimum acceptable detection capabilities are met with specified statistical confidence levels (95% detection probability with 5% probability of a false negative). Table 3.7-1 lists the ODCM program required LLDs for specific media and radionuclides. The LLDs actually achieved are routinely lower than those specified by the ODCM.

3 - 33

TABLE 3.7-1 REQUIRED DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)

Analysis Water (pCi/l)

Airborne Particulate or Gases (pCi/m3)

Fish (pCi/kg, wet)

Milk (pCi/)

Food Products (pCi/kg, wet)

Sediment (pCi/kg, dry)

Gross Beta H-3 Mn-54 Fe-59 Co-58, Co-60 Zn-65 Zr-95, Nb-95 1-131 Cs-134 Cs-137 Ba/La-140 4

0.01 3000 (a) 15 30 15 30 15 130 260 130 260 15 (a) 15 18 0.07 0.05 0.06 130 150 1

15 18 15 60 60 80 150 180 15 (a)

No drinking water pathway exists at the Nine Mile Point Site under normal operating conditions due to the direction and distance of the nearest drinking water intake. Therefore, an LLD value of 3000 pCi/liter is used for H-3, and an LLD value of 15 pCi/liter is used for 1-131.

3 - 34

3.8 COMPLIANCE WITH REQUIRED LOWER LIMITS OF DETECTION (LLD)

Tables D 4.6.20-1 and D 3.5.1-3 of the NMP ODCM and NMP2 ODCM, respectively, specify the detection capabilities for environmental sample analysis (See Table 3.7-1). The reporting requirements of NMP I ODCM, Section D 6.9.1.d and NMP2 ODCM, Section D 4.1.2 require that a discussion of all analyses for which the LLDs required by Tables D 4.6.20-1 and D 3.5.1-3 were not achieved be included in the Annual Radiological Environmental Operating Report. This Section is provided pursuant to this requirement.

All sample analyses performed in 2014, as required by the ODCM, achieved the LLD specified by ODCM Tables D 4.6.20-1 and D 3.5.1-3.

3.9 REGULATORY DOSE LIMITS Two federal agencies, the Nuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA) have responsibility for regulations promulgated for protecting the public from radiation and radioactivity beyond the site boundary.

3.9.1 The Nuclear Regulatory Commission The NRC, in 10 CFR 20.1301, limits the levels of radiation in unrestricted areas resulting from the possession or use of radioactive materials such that they limit any individual to a dose of:

less than or equal to 100 mrem per year to the total body.

In addition to this dose limit, the NRC has established design objectives for nuclear plant licensees.

Conformance to these guidelines ensures that nuclear power reactor effluents are maintained as far below the legal limits as is reasonably achievable.

The NRC, in 10 CFR 50, Appendix I, establishes design objectives for the dose to a member of the general public from radioactive material in liquid effluents released to unrestricted areas to be limited to:

less than or equal to 3 mrem per year to the total body, or less than or equal to 10 mrem per year to any organ.

The air dose due to release of noble gases in gaseous effluents is restricted to:

less than or equal to 10 mrad per year for gamma radiation, or less than or equal to 20 mrad per year for beta radiation.

The dose to a member of the general public from iodine-131, tritium, and all particulate radionuclides with half-lives greater than eight days in gaseous effluents is limited to:

less than or equal to 15 mrem per year to any organ.

3 -35

The NRC, in 10 CFR 72.104(a), established criteria for radioactive materials in effluents and direct radiation from an ISFSI. During normal operations and anticipated occurrences, the annual dose equivalent to any real individual who is located beyond the owner controlled area must not exceed:

25 mrem per year to the total body, 75 mrem per year to the thyroid, and 25 mrem per year to any organ as a result of:

1.

Planned discharge of radioactive material, radon and its decay products excepted, to the environment,

2.

Direct radiation from ISFSI, and

3.

Any other radiation from fuel cycle operation in the region.

3.9.2 Environmental Protection Agency The EPA, in 40 CFR 190.10 Subpart B, sets forth the environmental standards for the uranium fuel cycle.

During normal operation, the annual dose to any member of the public from the entire uranium fuel cycle shall be limited to:

less than or equal to 25 mrem per year to the whole body, less than or equal to 75 mrem per year to the thyroid, and less than or equal to 25 mrem per year to any other organ.

3 - 36

4.0 SAMPLE

SUMMARY

TABLES IN BRANCH TECHNICAL POSITION FORMAT All sample data is summarized in table form. Table 4.0-1 is titled "Radiological Environmental Monitoring Program Annual Summary" and follows the specification outlined in the NRC Radiological Assessment Branch Technical Position (Rev. 1, November 1979), which is summarized below.

Column I.

2.

3.

4.

5.

6.

7.

NOTE:

Sample medium.

Type and number of analyses performed.

Required Lower Limits of Detection (LLD), see Section 3.7.3, Table 3.7-1. This wording indicates that inclusive data is based on 4.66 Sb (sigma) of background (See Section 3.7).

The mean and range of the positive measured values of the indicator locations.

The mean, range, and location of the highest indicator annual mean. Location designations are keyed to Table 3.3-1 in Section 3.3.

The mean and range of the positive measured values of the control locations.

The number of non-routine reports sent to the Nuclear Regulatory Commission.

Only positive measured values are used in statistical calculations.

4-I

TABLE 4.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2014*

TYPE AND)

INDICATOR LOCATION (c) OF HIGHEST CONTROL NUMBER OF MEDIUM NUMBERLOCATIONS:

ANNUAL MEAN:

LOCATION:

NONROUTINE (UNITS)

ANALYSES*

MEAN () /

LOCATION & MEAN (b) /

MEAN (b) / RANGE REPORTS RANGE RANGE Shoreline Gamma-Spectrum Sediment Analysis (GSA) (4):

(pCi/kg-dry)

Cs-134 150

<LLD

<LLD 0

Cs-137 180

<LLD

<LLD 0

Fish GSA (18)-

(pCi/kg-wet)

Mn-54 130

<LLD

<LLD 0

Fe-59 260

<LLD

<LLD 0

Co-58 130

<LLD

<LLD 0

Co-60 130

<LLD

<LLD 0

Zn-65 260

<LLD

<LLD 0

Cs-134 130

<LLD

<LLD 0

Cs-137 150

<LLD

<LLD 0

4-2

TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2014*

MEDIUM TYPE AND INDICATOR LOCATION (c) OF HIGHEST NUMBER OF LOCTINS:ANUALMEN:CONTROL NUBRO (UNIUM NUMBER OF LLD(a)

LOCATIONS:

ANNUAL MEAN:

LOCATION:

NONROUTINE ANALYSES*

MEAN (/

LOCATION & MEAN (b) /

MEAN (b) / RANGE REPORTS RANGE RANGE Surface Water (pCi/liter)

H-3 (8):

H-3 GSA (24):

Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba/La-140 3000(e) 15 30 15 15 30 15 15 15(c) 15 18 15

<LLD

<LLD i

hh i

b 4-3

TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2014*

MEDIIJ TYPE AND INDICATOR LOCATION c) OF HIGHEST NUMBEROF LOCTINS:ANAALMEN:CONTROLNUBRO MEDIUM NUMBER OF LLD(a)

LOCATIONS:

ANNUAL MEAN:

LOCATION:

NONROUTINE (UNITS)

ANALYSES*

MEAN

/

LOCATION & MEAN (b) /

MEAN (b) / RANGE REPORTS RANGE RANGE TLD (mrem per Gamma Dose (140)

M 4.5 (120/120) (g)

TLD #85 0h):

9.2 (4/4) 3.8 (20/20) 0 standard month) 2.9-9.0 0.2 miles at 2900 8.5 -9.9 3.1 -5.0 Air Particulates Gross Beta (260) 0.01 0.016 (208/208)

R-2 0.016 (52/52) 0.016 (52/52) 0 (pCi/m3) 1.1 miles at 1060 0.007 - 0.026 0.005 - 0.030 0.006 - 0.030 1-131(260):

0.07

<LLD

<LLD 0

GSA (20):

<LLD

<LLD 0

Cs-134 0.05

<LLD

<LLD 0

Cs-137 0.06 Milk GSA (36): (d)(i)

(pCi/liter)

Cs-134 15

<LLD

<LLD 0

Cs-I 37 18

<LLD

<LLD 0

Ba/La-140 15

<LLD

<LLD 0

1-131 (36):

1-131 1

<LLD

<LLD 0

4-4

TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2014*

MEDIUM TYPE AND INDICATOR LOCATION (c) OF HIGHEST CONTROL NUMBER OF MEDIUM NUMBER OF LLD(a)

LOCATIONS:

ANNUAL MEAN:

LOCATION:

NONROUTINE (UNITS)

NANALYSES*

MEAN N /

LOCATION & MEAN )/

MEAN

/ RANGE REPORTS RANGE RANGE Food Products GSA (18): (d)

(pCi/kg-wet) 1-131 60

<LLD

<LLD 0

Cs-134 60

<LLD

<LLD 0

Cs-137 80

<LLD

<LLD 0

4-5

TABLE NOTES:

Data for Table 4.0-1 is based on NMP1 and NMP2 ODCM required samples unless otherwise indicated.

(a)

LLD values as required by the ODCM. LLD units are specified in the medium column.

(b)

Fraction of number of detectable measurements to total number of measurements. Mean and range results are based on detectable measurements only.

(c)

Location is distance in miles and direction in compass degrees based on NMP2 reactor center-line. Units in this column are specified in medium column.

(d) Data includes results from optional samples in addition to samples required by the ODCM.

(e)

The ODCM specify an 1-131 and tritium LLD value for surface water analysis (non-drinking water) of 15 pCi/liter and 3000 pCi/liter respectively.

(f)

The ODCM do not specify a particular LLD value for environmental TLDs. The NMP 1 and NMP2 ODCM contain specifications for environmental TLD sensitivities.

(g)

Indicator TLD locations are: #7, 15, 18, 23, 56, 58, 75, 76, 77, 78, 79, 80, 81, 82, 83, 84, 85, 86, 87, 88, 89, 90, 91, 92, 93, 94, 95, 96, 97, and 98. Control TLDs are all TLDs located beyond the influence of the site (TLD #8, 14, 49, 111, and 113).

(h)

This dose is not representative of doses to a member of the public since this area is located near the north shoreline, which is in close proximity to the generating facility and is not accessible to members of the public (See Section 5.2.4, TLDs).

(i)

The ODCM criteria for indicator milk sample locations include locations within 5.0 miles of the site. There are no milk sample locations within 5.0 miles of the site. Therefore, the only sample location required by the ODCM is the control location. There was one optional location during 2012.

4-6

5.0 DATA EVALUATION AND DISCUSSION A.

Introduction Each year, the results of the Radiological Environmental Monitoring Program (REMP) are evaluated with consideration of plant operations at the site, the natural processes in the environment and the archive of historical enviromnental radiological data.

A number of factors are considered in the course of evaluating and interpreting the annual environmental radiological data. This interpretation can be made using several methods including trend analysis, population dose estimates, risk estimates to the general population based on significance of environmental concentrations, effectiveness of plant effluent controls, and specific research areas. This report not only presents the data collected during the 2014 sample program, but also assesses the significance of radionuclides detected in the environment.

It is important to note that detection of a radionuclide is not, of itself, an indication of environmental significance. Evaluation of the impact of the radionuclide in terms of potential increased dose to man, in relation to natural background, is necessary to determine the true significance of any radionuclide detection.

B.

Units of Measure Some of the units of measure used in this report are explained below.

Radioactivity is the number of atoms in a material that decay per unit of time. Each time an atom decays, radiation is emitted. The curie (Ci) is the unit used to describe the activity of a material and indicates the rate at which the atoms are decaying. One curie of activity indicates the decay of 37 billion atoms per second.

Smaller units of the curie are used in this report. Two common units are the microcurie (uCi),

which is one millionth (0.000001) of a curie, and the picocurie (pCi), which is one trillionth (0.000000000001) of a curie. The picocurie is the unit of radiation that is routinely used in this report. The mass, or weight, of radioactive material that would result in one curie of activity depends on the disintegration rate or half-life. For example, one gram of radium-226 contains one curie of activity, but it would require about 1.5 million grams of natural uranium to equal one curie.

Radium-226 is more radioactive than natural uranium on a weight or mass basis.

C.

Dose/Dose to Man The dose or dose equivalent, simply put, is the amount of ionizing energy deposited or absorbed in living tissue. The amount of energy deposited or ionization caused is dependent on the type of radiation. For example, alpha radiation can cause dense localized ionization that can be up to 20 times the amount of ionization for the same energy imparted from gamma or x-rays. Therefore, a quality factor must be applied to account for the different ionizing capabilities of various types of radiation. When the quality factor is multiplied by the absorbed dose, the result is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to any 5-1

type of ionizing radiation. The dose equivalent is measured in rem (roentgen equivalent man). In terms of environmental radiation, the rem is a large unit. Therefore, a smaller unit, the millirem (mrem) is often used. One millirem (mrem) is equal to 0.001 of a rem.

The term "dose to man" refers to the dose or dose equivalent that is received by members of the general public at or beyond the site boundary. The dose is calculated based on concentrations of radioactive material measured in the environment. The primary pathways that contribute to the dose to man are: the inhalation pathway, the ingestion pathway and direct radiation.

D.

Discussion In the United States, a person's average annual radiation dose is 620 mrem. About half that amount comes from naturally occurring radionuclides. Radon and thoron gases account for two-thirds of this exposure, while cosmic, terrestrial, and internal radiation account for the remainder.

The other half comes from manmade sources and is mostly from diagnostic medical procedures.

The pie chart below shows a breakdown of radiation sources that contribute to the average annual U.S. radiation dose of 620 mrem. Nearly three-fourths of this dose is split between radon/thoron gas (naturally occurring) and diagnostic medical procedures (manmade).

Sources of Radiation Exposure in the United States Source: NCRP Report No. 160 (2009)

Industrial &

Consumer Occupational \\

Products

<0.1%

2%

Terrestrial (soil) 3%

Cosmic (space) 5%

Internal 5%

Radon and Thoron 37%

Nuclear Medicine 12%

ID Natural Sources - 50%

-310 millirem (0.31 rem)

Medical Procedures 36%

3 Manmade Sources - 50%

-310 millirem (0.31 rem) 5-2

There are three separate groups of radionuclides that were measured in the environment and analyzed for the 2014 sampling program.

1. The first of these groups consists of the radionuclides that are naturally occurring.

The environment contains a significant inventory of naturally occurring radioactive elements. The components of natural or background radiation include the decay of radioactive elements in the earth's crust, a steady stream of high-energy particles from space called cosmic radiation and naturally-occurring radioactive isotopes in the human body like potassium-40.

A number of naturally occurring radionuclides are present in the environment.

These are expected to be present in many of the environmental samples collected in the vicinity of the Nine Mile Point Site. Some of the radionuclides normally present include:

Tritium (H-3), present as a result of the interaction of cosmic radiation with the upper atmosphere Beryllium-7 (Be-7), present as a result of the interaction of cosmic radiation with the upper atmosphere

Potassium-40 (K-40) and Radium-226, naturally occurring radionuclides found in the human body and throughout the environment Be-7 and K-40 are especially common in REMP samples. Since they are naturally occurring and are abundant, positive results for these radionuclides are reported in some cases in Section 6.0 of this report. Comparisons of program samples to naturally occurring radiation are made throughout this section to help put program results into perspective and to aid the reader in determining what, if any, significant impact is demonstrated by the REMP results.

2.

The second group consists of radionuclides that may be detected in the environment as a result of the detonation of thermonuclear devices in the earth's atmosphere. Atmospheric nuclear testing during the early 1950's produced a measurable inventory of radionuclides presently found in the lower atmosphere, as well as in ecological systems. In 1963, an Atmospheric Test Ban Treaty was signed. Since the treaty, the global inventory of manmade radioactivity in the environment has been greatly reduced through the decay of short lived radionuclides and the removal of radionuclides from the food chain by such natural processes as weathering and sedimentation. This process is referred to in this report as ecological cycling. Since 1963, several atmospheric weapons tests have been conducted by the People's Republic of China and underground weapons testing by India, Pakistan & North Korea. In some cases, the usual radionuclides associated with nuclear detonations were detected for several months following the test, and then after a peatk detection period, diminished to a point where most could not be detected. Although reduced in frequency, atmospheric testing continued into the 1980's. The resulting fallout or deposition from these most recent tests has influenced the background radiation in the vicinity of the site and was evident in many of the sample media analyzed over the years. Fallout radionuclides from nuclear weapons testing included Cesium-137 (Cs-137) and Strontium-90 (Sr-90). The highest weapons testing concentrations were noted in samples 5-3

collected for the 1981 REMP. Cs-137 was the major byproduct of this testing and is still occasionally detected in a few select number of environmental media.

3. The third group of radionuclides that may be detected in the environment are related to nuclear power technology.

These radionuclides are the byproduct of the operation of light water reactors.

These byproduct radionuclides are the same as those produced in atmospheric weapons testing and have been found in the Chemobyl and Fukushima Daiichi Nuclear Power Station fallout. This commonality makes a determination of the source of these radionuclides that may be detected in environmental samples difficult to determine.

A number of factors must be considered in performing radiological sample data evaluation and interpretation. An attempt has been made not only to report the data collected during 2014, but also to assess the significance of the radionuclides detected in the environment as compared to naturally occurring and manmade radiation sources.

It is important to note that detected concentrations of radionuclides in the local environment as a result of man's technology are very small and are of no or little significance from an environmental or dose-to-man perspective.

The 2009 per capita average dose was determined to be 620 mrem per year from all sources, as noted in National Council on Radiation Protection and Measurement (NCRP) Report No. 160.

This average dose includes such exposure sources as industrial & occupational, consumer products, terrestrial, cosmic, internal, nuclear medicine, medical procedures, radon and thoron. The 2009 per capita dose rate due to naturally occurring sources was 310 mrem per year. The per capita radiation dose from nuclear power production nationwide is less than one mrem per year.

The naturally occurring gamma radiation in the environs of the Nine Mile Point site, resulting from radionuclides in the atmosphere and in the ground, accounts for approximately 47 mrem per year.

This dose is a result of radionuclides of cosmic origin (for example, Be-7) and of primordial origin Ra-226, K-40, and Thorium-232 (Th-232). A dose of 47 mrem per year, as a background dose, is significantly greater than any possible dose as a result of routine operations at the site during 2014.

The results of each sample medium are discussed in detail in Sections 5.1 and 5.2. This includes a summary of the results, the estimated environmental impact, a detailed review of any relevant findings with a dose-to-man estimate where appropriate, and an analysis of possible long-term and short-term trends.

During routine implementation of the REMP, additional or optional environmental pathway media are sampled and analyzed. These samples are obtained to:

" Expand the area covered by the program beyond that required by the ODCM Provide more comprehensive monitoring than is currently required

" Monitor the secondary dose-to-man pathways 5-4

Maintain the analytical data base established when the plants began commercial operation The optional samples that are collected will vary from year to year. In addition to the optional sample media, additional locations are sampled and analyzed for those pathways required by the ODCM. These additional sample locations are obtained to ensure that a variety of environmental pathways are monitored in a comprehensive manner. Data from additional sample locations that are associated with the required ODCM sample media are included in the data presentation and evaluation. When additional locations are included, the use of this data is specifically noted in Sections 5.1 and 5.2.

Section 6.0 contains the analytical results for the sample media addressed in the report. Tables are provided for each required sample medium analyzed during the 2014 program.

Section 7.0, titled Historical Data, contains statistics from previous years' environmental sampling.

The process of determining the impact of plant operation on the environment includes the evaluation of past analytical data to determine if trends are changing or developing. As state-of-the-art detection capabilities improve, data comparison is difficult in some cases. For example, Lower Limits of Detections (LLDs) have improved significantly since 1969 due to technological advances in laboratory procedures and analytical equipment.

5.1 AQUATIC PROGRAM The aquatic program consists of samples collected from four environmental pathways. These pathways are:

Shoreline Sediment Fish Surface Waters Groundwater Section 6.0, Tables 6-1 through 6-4 present the analytical results for the aquatic samples collected for the 2014 sampling period.

Sampling for groundwater, as found in Section D 3.5.1 of the NMP2 ODCM, was not required during 2014. There was no groundwater source in 2014 that was tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties were suitable for contamination; therefore, groundwater was not a dose pathway during 2014.

5-5

5.1.1 SHORELINE SEDIMENT RESULTS A.

Results Summary Shoreline sediment samples were obtained in April and October of 2014 at one off-site control location (Lang's Beach located near Oswego Harbor) and at one indicator location (Sunset Bay),

which is an area east of the site considered to have recreational value.

A total of four sediment samples were collected for the 2014 sample program, two indicator and two control. These results continue to show a downward trend over the past 10 plus years. Cs-137 was not detected in samples collected from the control or indicator locations during 2014.

The following is a graph of the average Cs-137 concentration in shoreline sediment samples over the previous twenty years.

This graph illustrates a general downward trend in the Cs-137 concentrations since 1994.

Shoreline Sediment Cs-137 I

Control U Indicator 0.3 Note: Years with values of less than the lower limit of detection are presented as 0.25 zero in the graph.

0.2 S0.15 0.

0.1 0.05 0

O~O O

)0 0

0 0

0 Year B.

Data Evaluation and Discussion Shoreline sediment samples are routinely collected twice per year from the shoreline of Lake Ontario. Samples are collected from one indicator location (Sunset Bay) and one control location (Lang's Beach). Samples were collected from both the indicator and control locations in April and October 2014. The results of these sample collections are presented in Section 6.0, Table 6-1, Concentrations of Gamma Emitters in Shoreline Sediment Samples - 2014. K-40 was the only significant radionuclide detected in the sediment samples.

5-6

C.

Dose Evaluation The calculated potential whole body and skin dose which may result from the measured Cs-137 concentrations in previous years are extremely small and are insignificant when compared to natural background doses.

The radiological impact of Cs-137 measured in the shoreline sediment can be evaluated on the basis of dose to man. In the case of shoreline sediments, the critical pathway is direct radiation to the whole body and skin. Using the parameters provided in Regulatory Guide 1.109, the potential dose to man in mrem per year can be calculated. The following regulatory guide values and the maximum 2014 shoreline sediment indicator Cs-137 concentration were used in calculating the dose to man:

A teenager spends 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months per year at the beach area or on the shoreline, The sediment has a mass of 40 kg/m2 (dry) to a depth of 2.5 cm,

" The shoreline width factor is 0.3, and The maximum 2014 Cs-137 concentration of <0.084 pCi/g (dry) (<LLD).

Using these conservative parameters, the potential dose to the maximum exposed individual (teenager) would be 0.00028 mrem/year to the whole body and 0.00033 mrem/year to the skin.

This calculated dose is very small and is insignificant when compared to the natural background annual exposure of approximately 46 mrem as measured by control thermoluminescent dosimeters (TLDs) in the vicinity of the site.

D.

Data Trends Cs-137 was not detected at the indicator or the control samples locations in 2014. The average Cs-137 concentration (LLD) for the shoreline sediment indicator sample for 2014 was <0.063 pCi/g (dry). This is consistent with mean concentration measured at the indicator location over the past six years.

The previous five years of data show that Cs-137 was not detected in the control or indicator location.

The general absence of Cs-137 in the control and indicator samples can be attributed to changing lake level and shoreline erosion. Recent soil samples from locations beyond any expected influence from the site have contained levels of Cs-137 equal to or greater than the concentrations found in the historical shoreline sediment samples collected in the past. The Cs-137 is commonly found in soil samples and is attributed to weapons testing fallout. Shoreline samples containing soil or sediment are likely to contain Cs-137.

5-7

The previous ten year data trend for indicator shoreline samples showed an overall downward trend in concentration measured at the indicator sample locations.

Over the previous ten-year period of 2004 through 2013, mean concentrations at the indicator location ranged from a maximum of 0.08 pCi/g (dry) in 2005 to a minimum of 0.04 pCi/g (dry) measured in 2004 and again in 2007. Cs-137 was not detected at the indicator location for 2008 thru 2014. This continues to support the long-term decreasing trend in Cs-137 concentration in shoreline sediment samples.

Cesium-137 was not detected in the control samples collected over the previous ten years.

Shoreline sediment sampling at the indicator location commenced in 1985. Prior to 1985, no data was available for long-term trend analysis.

Section 7.0, Tables 7-1, Historical Environmental Sample Data, Shoreline Sediment (Control) and 7-2, Historical Environmental Sample Data, Shoreline Sediment (Indicator), illustrate historical environmental data for shoreline sediment samples.

5.1.2 FISH SAMPLE RESULTS A.

Results Summary A total of 18 fish samples were collected for the 2014 sample program. Species collected were:

Smallmouth Bass, Brown Trout, Lake Trout, Chinook Salmon and Walleye. The analytical results for the 2014 fish samples showed no detectable concentration of radionuclides that would be attributable to plant operations at the site or past atmospheric weapons testing. Since 2003, no Cs-137 has been measured in fish samples. Over the previous 20 years prior to 2003, Cs-I 37 has been detected at both the indicator and/or control locations (Refer to Tables 7-3 and 7-4). These low levels of Cs-137 represented no significant dose to man or impact on the environment.

The 2014 fish sample results demonstrate that plant operations at the Nine Mile Point site have no measurable radiological environmental impact on the upper levels of the Lake Ontario food chain.

The 2014 results are consistent with the previous years' results in that they continue to support the general long-term downward trend in fish Cs-137 concentrations over the last 37 years. Cs-137 was not detected in fish samples collected in 2003 to 2014 from indicator locations. The period of 2004 through 2014, as a group, are the lowest results measured since the beginning of the Site Environmental Monitoring Program in 1969.

B.

Data Evaluation and Discussion Fish collections were made utilizing gill nets at one location greater than five miles from the site (Oswego Harbor area) and at two locations in the vicinity of the lake discharges for the NMPNS and the JAFNPP facilities. The Oswego Harbor samples served as control samples, while the NMPNS and JAFNPP samples served as indicator samples.

All samples were analyzed for gamma-emitters. Section 6.0, Table 6-2, Concentration of Gamma Emitters in Fish Samples-2014, shows individual results for all the samples collected in 2014 in units of pCi/g (wet).

5-8

The spring fish collection was made up of 9 individual samples representing three separate species.

Walleye, Smallmouth Bass, and Brown Trout were collected.

The total fall fish collection was comprised of 9 individual samples representing three individual species. Chinook Salmon, Brown Trout, and Lake Trout were collected.

Cs-137 was not detected in any of the fish species collected for the 2014 sample program.

C.

Dose Evaluation Fish represent the highest level in the aquatic food chain and have the potential to be a contributor to the dose to man from the operations at the site. Some Lake Ontario fish species may be considered an important food source due to the local sport fishing industry.

Therefore, these fish are an integral part of the human food chain. The lack of detectable concentrations of plant-related radionuclides in the 2014 fish samples demonstrates that there is no attributable dose to man from operations at the site through the aquatic pathway.

D.

Data Trends The Cs-137 data for fish samples over the previous five years (2010 through 2014) show that the number of positive detections has decreased over this period relative to historical data. There were no positive detections of Cs-137 over the previous five-year period at the indicator locations. The graph below illustrates the mean control and indicator Cs-137 concentrations for 2014 and the previous twenty-one years.

5-9

Annual Mean Fish Cs-137 Concentrations 0.035 0.03 0.025 0.02 U

.h 0.015 0.01 0.005 0

I Control S Indicator I

Note: Years with values of less than the lower limit of detection are presented as zero in the graph.

-n 10 t-W a,

00 M~

-I e.1 rC l

W C

Year The ten-year data trend shows a consistent decrease in the level of Cs-137 measured in fish.

The 2004 through 2014 results, as a group, are the lowest Cs-137 concentrations measured over the existence of the sample program.

The general long-term decreasing trend for Cs-137, illustrated in the following graph, is most probably a result of the cesium becoming unavailable to the ecosystem due to ion exchange with soils and sediments and radiological decay. The concentrations of Cs-137 detected in fish since 1976 are considered to be the result of weapons testing fallout. The general downward trend in concentrations will continue as a function of additional ecological cycling and radiological decay.

5-10

Fish Cs-137 1.4 U Control U Indicator 1.2 Note: Years with values of less thain thelowr limit of I

detection are presented as zero in the graph.

g0.8 0o.6 0.4 0.2 C

Year Section 7.0, Tables 7-3, Historical Environmental Sample Data, Fish (Control) and 7-4, Historical Environmental Sample Data, Fish (Indicator), show the historical environmental sample data for fish.

5.1.3 SURFACE WATER (LAKE)

A.

Results Summary The ODCM requires that monthly surface water samples be taken from the respective inlet water supplies of the JAFNPP and NRG Energy's Oswego Generating Station. In conjunction with the required samples, three additional Lake Ontario surface water locations are sampled and analyzed.

These additional locations are the Oswego City Water Intake, the Nine Mile Point Unit 1 (NMP1)

Intake and the Nine Mile Point Unit 2 (NMP2) Intake. Gamma spectral analysis was performed on 24 monthly composite samples from the ODCM locations and on 36 monthly composite samples collected from the additional sample locations. The results of the gamma spectral analyses showed that only naturally-occurring radionuclides were detected in the 60 samples from the five locations collected for the 2014 Sampling Program. The two naturally-occurring radionuclides detected were K-40 and Ra-226 and were not related to plant operations. Monthly composite samples showed no presence of plant-related gamma-emitting isotopes in the waters of Lake Ontario as a result of plant operations.

The monthly surface water samples are composited on a quarterly basis and are analyzed for tritium.

A total of 20 samples were analyzed for tritium as part of the 2014 REMP program. The results for the 2014 samples showed no positive detection for tritium in samples taken during 2014.

5-11

B.

Data Evaluation and Discussion Gamma spectral analysis was performed on monthly composite samples from five Lake Ontario sampling locations. No plant-related radionuclides were detected in 2014 samples. This is consistent with historical data, which has not shown the presence of plant-related radionuclides in surface water samples.

Tritium samples are quarterly samples that are a composite of the applicable monthly samples for a given location.

Tritium samples analyzed for the 2014 sample program were analyzed to an instrument detection level of 500 pCi/1.

The ODCM required indicator location (JAFNPP inlet canal) showed no positive detections of tritium.

The 2014 results had LLD values that ranged from <360 pCi/1 to <402 pCi/l. The ODCM control location (Oswego Generating Station inlet canal) results showed no positive detections, and the sample results had LLD values in the range of<193 pCi/l to <431 pCi/l.

Tritium was not detected in any of the twelve optional Lake Ontario samples collected in the 2014 program.

The Oswego City Water inlet is sampled to monitor drinking water quality and is representative of a control location due to its distance from the site. The city water inlet is located 7.8 miles west of the site in an "up-stream" direction based on the current patterns in the lake.

The following table provides the specific results for the 2014 sample program:

Sample Tritium Concentration pCi/liter SampleMean Location Minimum Maximum (Annual)

JAFNPP Inlet (Indicator)*

<360

<402

<388 Oswego Generating Station Inlet (Control)*

<193

<434

<355 NMP1 Inlet

<191

<436

<355 NMP2 Inlet

<190

<423

<351 Oswego City Water Supply

<193

<431

<354

Sample location required by ODCM The LLD values are below the ODCM required LLD of 3000 pCi/1 for a non-dfinking water pathway.

Analytical results for surface water samples are found in Section 6.0, Table 6-3, Concentration of Tritium in Surface Water Samples - 2014 and Table 6-4, Concentration of Gamma Emitters in Surface Water Samples - 2014.

5-12

C.

Dose Evaluation The radiological impact to members of the public from low levels of tritium in water is insignificant.

This can be illustrated by calculating a dose to the whole body and maximum organ using the maximum LLD value and Regulatory Guide 1.109 methodology. Based on a water ingestion rate of 510 liters/yr and the maximum 2014 LLD concentration of <434 pCi/l, the calculated dose would be less than 0.045 mrem to the child whole body and less than 0.045 mrem to the child liver (critical age group/organ).

D.

Data Trends There are no data trends for gamma-emitters such as Cs-137 and Co-60, as historically these radionuclides have not been detected in lake water samples.

Tritium results for the 2014 lake water samples were consistent with results from the previous five-years for both the indicator and control locations. The mean measured tritium concentrations for the previous five-year period of 2009 to 2013 was <LLD pCi/l for the control and the indicator locations. The mean 2014 tritium concentrations were <355 pCi/1 for the control and between

<351 and <386 pCi/l for the indicator locations. The previous five-year data indicates no significant trends in either the indicator or the control mean concentrations. This previous five-year data set is consistent with long-term tritium results measured at the site. The indicator data from the previous ten-year period, 2004 through 2013, are representative of natural variations in environmental tritium concentrations with no significant levels of tritium measured.

The 1999 mean control value of 337 pCi/l is the highest concentration measured since 1989 and is within the variability of results measured over the life of the program. The ten-year historical results are consistent between the control and indicator locations with no large variation in the measured results.

The following graph illustrates the concentrations of tritium measured in Lake Ontario over the previous 38 years at both an indicator and control location. Prior to 1985, the Oswego City Water Supply results were used as control location data as this location closely approximates the Oswego Generating Station, the current control location.

5-13

Surface Water Tritium 700 600 500 It 400 300 200 100 0

a'I-P-9 a a' a' "1 a If, a' S; 0'a 'a'a

'5 550~

Year Section 7.0, Tables 7-5, Historical Environmental Sample Data Surface Water (Control) and 7-6, Historical Environmental Sample Data Surface Water (Indicator),

show the historical environmental sample data for surface water Co-60 and Cs-137. Tables 7-7, Historical Environmental Sample Data, Surface Water Tritium (Control) and 7-8, Historical Environmental Sample Data, Surface Water Tritium (Indicator) show historical the environmental sample data for surface water tritium.

5.1.4 GROUNDWATER A.

Results Summary A groundwater monitoring program is not required by the ODCM. The program is being implemented as the result of Nuclear Energy Institue (NEI) Ground Water Protection Initiative.

Groundwater samples were collected from a number of locations shown in Section 3.3, Figure 3.3-6 and listed in Table 3.3-1.

A total of 84 tritium samples were collected for the 2014 sample program using eighteen indicator locations and three control locations. All monitoriong well results were less than the LLD for tritium.

A total of 72 monitoring well samples were collected for plant-related gamma-emitters, and eighteen strontium-90 (Sr-90) samples were collected for the 2014 sample program using fifteen indicator locations and three control locations. All sample results for 2014 groundwater monitoring program were less than the LLD for plant-related gamma-emitters and Sr-90.

5-14

B.

Data Evaluation and Discussion Plant related gamma-emitters and strontium-90 analysis were performed on samples from the indicator and control locations. No plant-related radionuclides were detected in the 2014 samples. This is consistent with historical data, which has not shown the presence of plant-related radionuclides in groundwater samples.

Tritium samples analyzed for the 2014 sample program were analyzed to an LLD of 500 pCi/l. The tritium results for the control locations and indicator locations were less than the established LLD.

The NMP2 storm drain system indicator location results ranged from <368 to <488 pCi/l tritium.

C.

Dose Evaluation Sampling for groundwater, as found in Section D 3.5.1 of the NMP2 ODCM, was not required during 2014. There was no groundwater source in 2014 that was tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties support contaminant migration; therefore, drinking water was not a dose pathway during 2014.

To assess the dose associated with tritium, the highest LLD was used and assumed to be present:

Maximum tritium concentration 493 pCi/l (highest LLD)

510 liters of water consumed per year The theoretical dose to the whole body and maximum organ using the maximum value and Regulatory Guide 1.109 methodology were determined. The calculated dose would be 0.05 mrem to the child whole body and less than 0.05 mrem to the child liver (critical age group/organ), although the actual dose to an individual would be lower.

D.

Data Trends There are no data trends for gamma-emitters or Strontium-90 as these radionuclides have not been detected in groundwater samples.

Groundwater tritium results are documented in the Annual Radiological Effluent Release Report for 2014. Historical data for groundwater tritium is presented in Section 7.0, Tables 7-9, Historical Environmental Sample Data, Surface Water Tritium (Control) and 7-10, Historical Environmental Sample Data, Surface Water Tritium (Indicator).

5-15

5.2 TERRESTRIAL PROGRAM The terrestrial program consists of samples collected from four environmental pathways. These pathways are:

" Airborne Particulate and Radioiodine,

" Direct Radiation, Milk, and Food Products.

Section 6.0, Tables 6-5 through 6-12 present the analytical results for the terrestrial samples collected during the 2014 reporting period.

5.2.1 AIR PARTICULATE GROSS BETA A.

Results Summary Weekly air samples were collected and analyzed for particulate gross beta particulate activity.

For the 2014 program, a total of 52 samples were collected from control location R-5, and 208 samples were collected from indicator locations R-l, R-2, R-3, and R-4. These five locations are required by the ODCM.

Additional air sampling locations are maintained and are discussed in Section 5.2.1..B below. The mean gross beta concentration for samples collected from the control location (R-5) in 2014 was 0.016 pCi/m 3, the same as reported for 2013. The mean gross beta concentration for the samples collected from the indicator locations (R-1, R-2, R-3, and R-4) in 2014 was 0.016 pCi/m 3, the same as reported for 2013. The consistency between the indicator and control mean values demonstrates that there are no increased airborne radioactivity levels in the general vicinity of the site. The indicator results are consistent with concentrations measured over the last twenty years. This consistency demonstrates that the natural baseline gross beta activity has been reached. The man-made radionuclide contribution to the natural background from atmospheric weapons testing and Chernobyl can no longer be detected above the background concentrations of naturally occurring beta-emitting radionuclides.

B.

Data Evaluation and Discussion The air monitoring system consists of fifteen sample locations, six on-site and nine off-site. Each location is sampled weekly for particulate gross beta activity.

A total of 780 samples were collected and analyzed as part of the 2014 program. Five of the nine off-site locations are required by the ODCM. These locations are designated as R-1, R-2, R-3, R-4, and R-5. R-5 is a control location required by the ODCM and is located beyond any local influence from the site. In addition, optional off-site and on-site air sample locations are maintained from which weekly samples are collected. The optional off-site locations are designated as D-2, E, F and G. The optional on-site locations are designated as D-1, G, H, I, J and K.

5-16

Gross beta analysis requires that the samples be counted no sooner than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after collection.

This allows for the decay of short half-life naturally-occurring radionuclides, thereby increasing the sensitivity of the analysis for plant-related radionuclides.

Section 6.0, Tables 6-5, Environmental Airborne Particulate Samples - Offsite Sample Locations -

2014, and 6-6, Environmental Airborne Particulate Samples - Onsite Sample Locations - 2014, present the weekly gross beta activity results for samples collected from the off-site and on-site locations.

The mean annual gross beta indicator concentrations for the ODCM indicator stations (R-1, R-2, R-3 and R-4) was 0.016 pCi/m3. The off-site ODCM control station (R-5) annual mean gross beta concentration was 0.016 pCi/m3.

The minimum, maximum and average gross beta results for sample locations required by the ODCM were as follows:

Concentration pCi/mr Location Minimum Maximum Mean R-1 0.006 0.027 0.016 R-2 0.007 0.026 0.016 R-3 0.005 0.027 0.015 R-4 0.005 0.030 0.016 Summary (R1 - R4) 0.006 0.030 0.016 R-5 (Control) 0.006 0.030 0.016 The mean weekly gross beta concentrations measured in 2014 are illustrated in the following graphs:

5-17

Air Particular Filter - Gross Beta (2014) easm/

... 4,-- C~o2 c-a Week No.

The fluctuations observed in the gross beta activity over the year can be attributed to changes in the environment, especially seasonal changes. The concentrations of naturally-occurring radionuclides in the lower levels of the atmosphere directly above the land are affected by time-related processes such as wind direction, precipitation, snow cover, soil temperature and soil moisture content.

C.

Dose Evaluation Dose calculations are not performed based on gross beta concentrations. Dose to man as a result of radioactivity in air is calculated using the specific radionuclide and the associated dose factor. See Section 5.2.2.C for dose calculations from air concentrations. The dose received by man from air gross beta concentration is a component of the natural background.

D.

Data Trends With the exception of the 1986 sample data, which was affected by the Chernobyl accident, the general trend in air particulate gross beta activity has been one of decreasing activity since 1981, when the mean control value was 0.165 pCi/m3. The 1981 samples were affected by fallout from a Chinese atmospheric nuclear test which was carried out in 1980.

The mean gross beta concentrations measured in 1978 to 2014 are illustrated in the following graph:

5-18

Air Particulate Filter - Gross Beta 0.18 0 Control M Indicator 0.16 1980: Atmospheric 0.14 Nuclear Tests 0.12 M. 0.08 0.04 h1988 Chernobyl Accident 0.02 1

ll l

l,

1111111 lgl 11111111 l11111111 4

...1.--

Year The trend for the previous five years represents a base line concentration or natural background level for gross beta concentrations.

This trend is stable with minor fluctuations due to natural variations. The change in concentrations over the period of 2004 through 2014 is very small. This is illustrated by the following graph:

F 0.025 -

Air Particulate Filter - Gross Beta 0.02 0.015 0.01 0.005 0

WControl SlIndicator Year For the previous 10 years, the mean annual gross beta concentration at the control station (R-5) has remained steady with a narrow range of 0.014 pCi/m3 to 0.019 pCi/m3.

The mean annual concentrations for the indicator stations for this same time period were similar to the control and ranged from a minimum mean of 0.015 pCi/m3 to a maximum mean of 0.018 pCi/m3.

5-19

Historical data of air particulate gross beta activity are presented in Section 7.0, Tables 7-11, Historic Environmental Sample Data, Air Particulate Gross Beta (Control) and 7-12, Historic Environmental Sample Data, Air Particulate Gross Beta (Indicator).

5.2.2 AIRBORNE RADIOIODINE (1-131)

A.

Results Summary 1-131 was not detected in any of the 780 samples analyzed for the 2014 program.

B.

Data Evaluation and Discussion Airborne radioiodine (1-131) is monitored at the fifteen air sampling stations also used to collect air particulate samples. There are nine off-site locations, five of which are required by the ODCM.

The off-site locations required by the ODCM are designated as R-1, R-2, R-3, R-4 and R-5. R-5 is a control station located beyond any local influence from the plant. Ten air sampling locations are also maintained in addition to those required by the ODCM. Six of these stations D-1, G, H, I, J and K are located on-site. D-2, E, F and G are the optional stations located off-site. Samples are collected using activated charcoal cartridges and analyzed weekly for 1-131.

The analytical data for radioiodine are presented in Section 6.0, Tables 6-7, Environmental Charcoal Cartridge Samples - Offsite Sample Locations - 2014 and 6-8, Environmental Charcoal Cartridge Samples - Onsite Sample Locations - 2014.

C.

Dose Evaluation The calculated dose as a result of 1-131 was not detected during 2014. The 1-131 sampling program demonstrated no offsite dose to man from this pathway as a result of operation of the plants located at Nine Mile Point.

D.

Data Trends No radioiodine had been detected in samples collected from the air sampling locations required by the ODCM from 1987 to 2010 and 2012 to 2014. In 2011, 1-131 was detected at all 15 sampling locations over a three week period. The positive detections were the result of the trans-Pacific transport of airborne releases from Fukushima Daiichi Nuclear Power Station fallout following the Tohoku earthquake. During 2014, 1-131 was not detected in any of the samples collected for the sampling location required by the ODCM.

There has been no positive detection of 1-131 in air samples collected over the last ten years that could be attributed to the operation of the Nine Mile Point Site. This demonstrates that there is no measurable environmental impact or positive trend for iodine buildup due to plant operations during the period from 2003 through 2014.

1-131 has previously been detected in samples collected during the last twenty five year period in 1986, 1987 and 2011. The 1986 detection of I-5 - 20

131 was the result of the Chernobyl accident, the 1987 detection was the result of plant operations and the 2011 detection of 1-131 was the result of the Fukushima Daiichi Nuclear Power Station accident.

1-131 has been detected at the control location in the past. Control samples collected during 1976 had a mean 1-131 concentration of 0.60 pCi/m3. During 1977 the mean decreased to 0.32 pCi/m 3, and further decreased by a factor of ten to 0.03 pCi/m3 in 1978.

1-131 was not detected in samples collected from the control location during 1979 to 1981, 1983 to 1985, 1987 to 2010, and 2012 to 2014. 1-131 was detected at the control location during 1982 at a maximum concentration of 0.039 pCi/m 3, in 1986 at a maximum concentration of 0.151 pCi/m 3 and during 2011 at a maximum concentration of 0.093 pCi/m3.

1-131 has been detected in samples collected from the on-site indicator locations during 1976 to 1978, 1980 to 1983, 1986 to 1987 and 2011. The mean concentrations ranged from 0.013 pCi/m3 in 1980 to a maximum of 0.33 pCi/m3 in 1976. The maximum mean indicator 1-131 concentration of 0.33 pCi/m 3 was the result of the atmospheric nuclear testing. The Chernobyl accident resulted in 1-131 being detected in a total of 75 weekly samples collected during the 1986 sample program.

The 1986 measured concentrations ranged from a minimum of 0.023 pCi/m 3 to a maximum of 0.36 pCi/m 3. Each positive detection of 1-131 in samples collected in 1986 was the direct result of the Chernobyl Nuclear accident. The Fukushima Daiichi Nuclear Power Station accident resulted in I-131 being detected in a total of 3 weekly samples collected during the 2011 sample program. The 2011 measured concentrations ranged from a minimum of 0.021 pCi/m 3 to a maximum of 0.11 pCi/m 3. Each positive detection of 1-131 in samples collected in 2011 was the direct result of the Fukushima Daiichi Nuclear Power Station accident.

Historical data for 1-131 are presented in Section 7.0, Tables 7-15, Historic Environmental Sample Data, Air Radioiodine (Control) and 7-16, Historic Environmental Sample Data, Air Radioiodine (Indicator).

5.2.3 QUARTERLY PARTICULATE COMPOSITES (GAMMA-EMITTERS)

A.

Results Summary Fifteen air monitoring stations are maintained around the Nine Mile Point site. Five of the 15 air monitoring stations are required by the ODCM; four are located off-site near the site boundary, and one is located off-site as a control location.

Ten additional air sampling stations are also maintained as part of the sampling program. Together, these fifteen continuous air sampling stations make up a comprehensive environmental monitoring network for measuring radioactive air particulate concentrations in the environs of the site. Annually, the air monitoring stations provide 780 individual air particulate samples that are assembled by location into 60 quarterly composite samples. The quarterly composites are analyzed using gamma spectroscopy.

5-21

No plant-related gamma-emitting radionuclides were detected in any of the air particulate filter samples collected during 2014.

The gamma analysis results for the quarterly composite samples routinely showed positive detections of Be-7, K-40, and Ra-226. Each of these radionuclides is naturally occurring.

B.

Data Evaluation Discussion A total of fifteen air sampling stations are in continuous operation and located both on-site and in the off-site sectors surrounding the Nine Mile Point site. Five of the fifteen monitoring stations are required by the ODCM, and the remaining ten are optional to provide an effective monitoring network. Composite air filter samples are assembled for each of the fifteen sampling locations.

Each of the weekly air particulate filters collected for the quarter is assembled by location to form quarterly composite samples.

The quarterly composite samples required by the ODCM are composite samples assembled for R-1, R-2, R-3, R-4 and R-5. Other sample locations not required by the ODCM, for which analytical results have been provided, include six on-site locations and four off-site locations. The analytical results for the 60 air particulate filter composites in 2014 showed no detectable activity of plant related radionuclides.

The results of the quarterly composite samples are presented in Section 6.0, Table 6-9, Concentration of Gamma in Quarterly Composites of JAFNPP/NMPNS Site Air Particulate Samples - 2014 C.

Dose Evaluation The calculated dose as a result of plant effluents is not evaluated due to the fact that no plant related radionuclides were detected in 2014.

The monthly air particulate sampling program demonstrated no off-site dose to man from this pathway as a result of operation of the plants located at the Nine Mile Point site.

D.

Data Trends No plant-related radionuclides were detected during 2014 at the off-site air monitoring locations.

The ten-year database of air particulate composite analysis shows that there is no buildup or routine presence of plant related radionuclides in particulate form in the atmosphere around the site.

Historically Co-60 was detected in each of the years from 1977 through 1984 at both the indicator and control locations, with the exception of 1980 when Co-60 was not detected at the control location. The presence of Co-60 in the air samples collected during these years was the result of atmospheric weapons testing. Co-60 was again detected in an off-site 2000 indicator sample and was the only positive detection of Co-60 since 1984. The detection of Co-60 in the one 2000 sample was an isolated event associated with effluents from the NMP1 facility. There have been 5 - 22

no subsequent measurable concentrations of Co-60 in the environment surrounding the Nine Mile Point site.

Historical data shows that cesium-137 (Cs-137) is the fission product radionuclide most frequently detected in the air particulate filter composites. Cs-137 was detected in each of the years from 1977 through 1983 at both the control and indicator sampling locations. The presence of Cs-137 in the air samples collected during these years was the result of atmospheric weapons testing. Cs-137 was again detected in 1986 as a result of the Chernobyl accident. Since 1986 there have been no detections of Cs-137 in the environment surrounding the Nine Mile Point site.

After 1986, no plant-related or fallout radionuclides were detected in any of the off-site air particulate composite samples with the exception of the isolated detection of Co-60 in 2000 in a single sample. A review of the past five years' data for air particulate filter composites indicates no plant related radiological impact on the environment. All previous historical positive detections of fission product radionuclides were associated with atmospheric weapons testing or the Chernobyl accident, with the exception of the 2000 detection noted above.

Historical data for air particulate results are presented in Section 7.0, Tables 7-13, Historic Environmental Sample Data, Air Particulate (Control) and 7-14, Historic Environmental Sample Data, Air Particulate (Indicator).

5.2.4 DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS (TLD)

A.

Results Summary TLDs are used to measure direct radiation (gamma dose) in the environment. As part of the 2014 environmental monitoring program, TLDs were placed at a total of 72 different environmental TLD locations (32 required by the ODCM and 40 optional locations). These TLDs were placed, collected and read each quarter of 2014. As a result of placing two TLDs at each location, the results presented in this report are the average of two TLD readings obtained for a given location.

The TLDs were placed in the following five geographical locations around the site boundary:

On-site (areas within the site boundary: TLDs 3, 4, 5, 6, 7, 23, 24, 25, and 26; TLDs 18, 27, 28, 29, 30, 30, 31, 39, 47, 103, 106, and 107 are excluded)

" Site Boundary (area of the site boundary in each of the 16 meteorological sectors: Only includes TLD results that are not affected by radwaste direct shine, TLDs 7, 18, 78, 79, 80, 81, 82, 83, and 84; TLDs 23, 75, 76, 77, 85, 86, and 87 are excluded)

" Off-site Sector (area four to five miles from the site in each of the eight land-based meteorological sectors: TLDs 88, 89, 90, 91, 92, 93, 94, and 95) 5 - 23

Special Interest (areas of high population density and use: TLDs 15, 56, 58, 96, 97 and 98)

Control (areas beyond significant influence of the site: TLDs 14 and 49)

All geographical locations are required by the ODCM with the exception of the On-site area which was optional. Description of the five geograpical categories and the designation of specific TLD locations that make up each category is presented in Section 3.1.6, TLD (Direct Radiation) of this report.

A summary of the 2014 dose rates for each of the five geographical locations is as follows:

Dose in mrem per standard month Geographic Category Minimum Maximum Mean On-site (Optional) 3.3 12.9 4.9 Site Boundary (Inner Ring)

0) 3.3 4.6 3.9 Off-site Sectors (Outer Ring)

3.2 4.4 3.8 Special Interest * (2) 2.9 4.3 3.8 Control * (3) 3.3 4.1 3.8 Geographical locations required by the ODCM I

Only includes TLD results that are not affected by radwaste direct shine (TLDs. 7, 18, 78, 79, 80, 81, 82, 83, and 84) 2 Only includes TLD results required by the ODCM (TLDs 15, 56, 58, 96, 97, and 98) 3 Only includes TLD results required by the ODCM (TLDs 14 and 49)

Comparison of annual mean dose rates associated with each geographical location indicate that there is no statistical difference in annual dose as a function of distance from the site boundary. The measured annual dose rate at the nearest resident to the site was consistent with the dose rates measured at the site boundary and control locations. The results for the Site Boundary, Off-site Sectors and Special Interest (Off-site) were well within expected normal variation when compared to the Control TLD results.

The results for the 2014 environmental TLD monitoring program indicate that there was no significant increase in dose rates as a result of operations at the site. The Hydrogen Water Chemistry systems and the ISFSI used at NMPNS and JAFNPP did not measurably increase the ambient radiation exposure rate beyond the site boundary.

B.

Data Evaluation and Discussion Direct Radiation (Gamma Dose) measurements were taken at 72 different environmental locations during 2014, 32 of which are required by the ODCM. These locations are grouped into five geographical location categories for evaluation of results. The five categories include: On-site, Site Boundary, Offsite by Sector, Special Interest, and Control locations. All categories are required by the ODCM with the exception of the On-site TLDs. On-site TLDs are placed at various locations 5 -24

within the site boundary to provide additional information on direct radiation levels at and around the NMPI, NMP2 and JAFNPP facilities.

On-site TLDs are optional and are subdivided into three categories for which direct radiation results are evaluated. The 2014 direct radiation results for On-site TLD locations were as follows:

1.

Results for TLDs located near the NMPI, NMP2 and JAFNPP facilities and at previous or existing on-site air monitoring stations ranged from 2.9 to 9.9 mrem per standard month.

2.

Results for TLDs located near the north shoreline of NMP 1, NMP2 and JAFNPP in close proximity to the Radwaste and NMP1 Reactor Building ranged from 3.3 to 24.7 mrem per standard month.

3.

Results for TLDs located on-site near the Energy Information Center and its associated shoreline ranged from 3.9 to 5.3 mrem per standard month.

Site Boundary TLD results ranged from 3.3 to 9.9 mrem per standard month in 2014. This range included all TLDs placed in each of the 16 meteorological sectors in the general area of the site boundary. The highest dose rate measured at a location required by the ODCM was 9.9 mrem per standard month. This TLD, (TLD 85) represents the site boundary maximum dose and is located in the WNW sector along the lake shore in close proximity to the NMP 1 plant. The TLD locations along the lakeshore close to the plants (TLDs 75, 76, 77, 85, 86 and 87) are influenced by radwaste buildings and radwaste shipping activities. These locations are not accessible to members of the public, and the TLD results for these areas are not representative of dose rates measured at the remaining site boundary locations. The remaining Site Boundary TLD locations, which are located away from the plant ranged from 3.3 to 4.6 mrem per standard month resulting in an average dose rate of 3.9 mrem per standard month.

Off-site Sector TLDs, required by the ODCM, located 4 to 5 miles from the site in each of the 8 land based meteorological sectors ranged from 3.2 to 4.4 mrem per standard month with an average dose rate of 3.8 mrem per standard month.

Special Interest TLDs from all locations ranged from 2.9 to 4.3 mrem per standard month with an annual average dose rate of 3.8 mrem per standard month.

The Control TLD group required by the ODCM utilizes locations positioned well beyond the site. 2014 Control TLD results ranged from 3.1 to 5.0 mrem per standard month with an annual average dose rate of 3.8 mrem per standard month.

These results include both the ODCM required control TLDs (14 and 49) and the additional control TLDs (8, 111 and 113).

TLD analysis results are presented in Section 6.0, Table 6-10, Direct Radiation Measurement Results - 2014.

5-25

C.

Dose Evaluation 2014 annual mean dose rates for each geographic location required by the ODCM are as follows:

Site Boundary:

3.9 mrem per standard month Off-site Sectors:

3.8 mrem per standard month Special Interest:

3.8 mrem per standard month (TLDs: 78, 79, 80, 81, 82, 83, 84, 7 and 18)

(TLDs: 88, 89, 90, 91, 92, 93, 94 and 95)

(TLDs: 15, 56, 58, 96, 97 and 98)

(TLDs 14 and 49)

Control:

3.8 mrem per standard month The measured mean dose rate in the proximity of the closest resident was 4.0 mrem per standard month (TLD #s: 108, 109), which is consistent with the control measurements of 3.8 mrem per standard month.

The mean annual dose for each of the geographic location categories demonstrates that there is no statistical difference in the annual dose as a function of distance from the site. The TLD program verifies that operations at the site do not measurably contribute to the levels of direct radiation present in the off-site environment.

D.

Data Trends A comparison of historical TLD results can be made using the different geographical categories of measurement locations.

These include Site Boundary TLDs located in each of the 16 meteorological sectors, TLDs located off-site in each land based sector at a distance of 4 to 5 miles from the site, TLDs located at special interest areas and TLDs located at control locations. Site Boundary, Off-site Sector and Special Interest TLD locations became effective in 1985; therefore, trends for these results can only be evaluated from 1985 to the present.

The following graph illustrates TLD results for the Control, Site Boundary, Off-site Sectors and Special Interest groups from 2003 through 2014:

5 - 26

TLD Data 6

5 4

3-EL 2 0

C'4 Nq N

Nq C44 C4 N

ra Year TLDs located at the site boundary averaged 3.9 mrem per standard month during 2014 (Site Boundary average results do not include TLDs influenced by radwaste buildings and radwaste shipping activities). This result is consistent with the previous five year average of 4.0 mrem per standard month.

Off-site Sector TLDs averaged 3.8 mrem per standard month during 2014. This result is also consistent with the previous five-year average of 3.9 mrem per standard month for off-site sectors.

Special Interest TLD locations averaged 3.8 mrem per standard month during 2014 which is consistent with the previous five-year average of 3.9 mrem per standard month.

The last group of TLD locations required by the ODCM is the Control Group. This group utilized TLD locations positioned well beyond the site.

2014 control results from all Control TLDs averaged 3.8 mrem per standard month, consistent with the previous five-year average of 3.9 mrem per standard month. The 2014 TLD program results, when compared to the previous ten years, showed no significant trends relative to increased dose rates in the environment.

Section 7.0, Tables 7-17 through 7-22 show the historical environmental sample data for environmental TLDs.

5 - 27

5.2.5 MILK A.

Results Summary A total of 36 milk samples were collected during the 2014 program and analyzed for gamma emitting radionuclides using gamma spectroscopy. In addition, each sample undergoes an iodine extraction procedure to determine the presence of Iodine-131 (I-131).

1-13 1, a possible plant related radionuclide, is measured to evaluate the cow/milk dose pathway to man. 1-131 was not detected in any of the 36 milk samples collected in 2014 from the two milk sample locations.

Gamma spectral analyses of the milk samples showed only naturally occurring radionuclides, such as K-40, were detected in milk samples collected during 2014. K-40 was detected in all indicator and control samples.

K-40 is a naturally occurring radionuclide and is found in many environmental sample media.

The 2014 results demonstrate that routine operations of the Nine Mile Point site resulted in no measurable contribution to the dose to the public from the cow/milk pathway.

B.

Sampling Overview Milk samples were collected from one indicator location and one control location. The ODCM requires that three sample locations be within five miles of the site. Based on the milch animal census, there were no adequate milk sample locations within five miles of the site in 2014.

Samples were collected from two farms located beyond the five-mile requirement to ensure the continued monitoring of this important pathway. The indicator location is approximately 9 miles east from the site. The control samples were collected from a farm located 16.0 miles from the site and in a low frequency wind sector (upwind). The geographic location of each sample location is listed below:

Location No.

Direction From Site Distance (Miles) 55 E

8.8 77 (Control)

SSW 16.0 Samples were collected from Indicator location #55 and Control location #77 from April through December. Sampling occurs during the first and second half of each month. Samples were not required to be collected during January through March of 2014 as a result of 1-131 not having been detected in samples collected during November and December of 2013, as stipulated in the ODCM.

5-28

C.

Data Evaluation and Discussion Each milk sample is analyzed for gamma-emitters using gamma spectral analysis.

The 1-131 analysis is performed using resin extraction followed by spectral analysis for each sample. 1-131 and gamma analysis results for milk samples collected during 2014 are provided in Section 6.0, Table 6-11, Concentration of Iodine-131 and Gamma Emitters in Milk - 2014.

Iodine 131 was not detected in any indicator or control milk samples analyzed during 2014. All I-131 milk results were reported as Lower Limits of Detection (LLD).

No plant-related radionuclides were detected in any milk sample collected in 2014. K-40 was the most abundant radionuclide detected, and found in every indicator and control sample collected.

K-40 is a naturally-occurring radionuclide and is found in many of the environmental media samples. Cs-137 was not detected in any indicator or control milk sample collected in 2014.

The results of the milk samples are presented in Section 6.0, Table 6-11, Concentration of Iodine-131 and Gamma Emitters in Milk - 2014.

D.

Dose Evaluation The calculated dose as a result of plant effluents is not evaluated due to the fact that no plant-related radionuclides were detected.

The dose to man from naturally occurring concentrations of K-40 in milk and other environmental media can be calculated. This calculation illustrates that the dose received due to exposure from plant effluents is negligible compared to the dose received from naturally occurring radionuclides.

Significant levels of K-40 have been measured in environmental samples. A 70 kilogram (154 pound) adult contains approximately 0.1 microcuries of K-40 as a result of normal life functions (inhalation, consumption, etc.). The dose to bone tissue is about 20 mrem per year as a result of internal deposition of naturally-occurring K-40.

E.

Data Trends Man-made radionuclides are not routinely detected in milk samples. In the past twenty five years, Cs-137 was only detected in 1986, 1987, and 1988. The mean Cs-137 indicator activities for those years were 8.6, 6.8 and 10.0 pCi/liter, respectively. 1-131 was measured in two milk samples collected in 1997 from a single indicator sample location, having a mean concentration of 0.50 pCi/liter and was of undetermined origin.

The previous detection was in 1986 with a mean concentration of 13.6 pCi/liter in a control location. The 1986 - 1988 activity was a result of the Chernobyl accident.

The comparison of 2014 data to historical results over the operating life of the plants shows that Cs-137 and 1-131 levels in milk have decreased significantly since the 1980's.

5 - 29

Historical data of milk sample results for Cs-1 37 and 1-131 are presented in Section 7.0, Tables 7-23, Historical Environmental Sample Data, Milk (Control) and 7-24, Historical Environmental Sample Data, Milk (Indicator).

5.2.6 FOOD PRODUCTS (VEGETATION)

A.

Results Summary There were no plant-related radionuclides detected in the 18 food product samples collected and analyzed for the 2014 program.

Detectable levels of naturally occurring K-40 were measured in all control and indicator samples collected for the 2014 program. Be-7, a naturally-occurring radionuclide, was also detected in all samples collected in 2014. These results are consistent with the levels measured in previous years.

The results of the 2014 sampling program demonstrate that there is no measurable impact on the dose to the public from the garden pathway as a result of plant operations.

B.

Data Analysis and Discussion Food product samples were collected from five indicator locations and one control location. The indicator locations are represented by nearby gardens in areas of highest D/Q (deposition factor) values based on historical meteorology and an annual garden census. The control location was a garden 15 miles away in a predominately upwind direction.

Food product samples collected during 2014 included varieties considered to be edible broadleaf vegetables. The general lack of edible broadleaf vegetation samples was the result of grower preference and such varieties were not available in local gardens.

Where broadleaf vegetables were not available, non-edible broadleaf vegetation was collected. Vegetation samples consisting of tomatoes, cabbage, bean leaves, horseradish leaves, rhubarb leaves, kale leaves, grape leaves and squash leaves were collected for the 2014 program. The leaves of these plants were sampled as representative of broadleaf vegetation, which is a measurement of radionuclide deposition. Samples were collected during the late summer/fall harvest season. Each sample was analyzed for gamma-emitters using gamma spectroscopy.

The analysis of food product samples collected during 2014 did not detect any plant-related radionuclides. Results for the past five years also demonstrate that there is no buildup of plant-related radionuclides in the garden food products grown in areas close to the site.

Naturally-occurring Be-7 and K-40 were detected in food product samples. The results for naturally-occurring radionuclides are consistent with the data of prior years.

5-30

Analytical results for food products are found in Section 6.0, Table 6-12, Concentration of Gamma Emitters and C-14 in Food Products - 2014.

C.

Dose Evaluation The calculated dose as a result of plant effluents is not evaluated due to the fact that no plant-related radionuclides were detected.

The food product sampling program demonstrated no measurable off-site dose to man from this pathway as a result of operation of the plants located at the Nine Mile Point site.

D.

Data Trends Food product/vegetation sample results for the last five years demonstrate that there is no chronic deposition or buildup of plant-related radionuclides in the garden food products in the environs near the site.

The last positive indication was for Cs-137 which was detected at one indicator location in 1999 with a concentration of 0.008 pCi/g (wet).

Historically, Cs-137 had been detected in ten separate years since 1976 ranging from a maximum mean concentration of 0.047 pCi/g (wet) in 1985 to a minimum of 0.004 pCi/g (wet) in 1979. The trend for Cs-137 is a general reduction in concentration to non-detectable levels in samples collected during the 2003 through 2014 sample programs.

Historical data of food product results are presented in Section 7.0, Tables 7-25, Historical Environmental Sample Data, Food Products (Control) and 7-26, Historical Environmental Sample Data, Food Products (Indicator).

5.2.7 LAND USE CENSUS RESULTS A.

Results Summary The ODCM requires that an annual land use census be performed to identify potential new locations for milk sampling and for calculating the dose to man from plant effluents. In 2014, a milk animal census, a nearest resident census, and a garden census were performed.

The results of the closest residence census conducted in 2014 required no change to either the NMP1 or NMP2 ODCMs' closest resident location.

A garden census, not required by the ODCM, is performed to identify appropriate garden sampling locations and dose calculation receptors.

Garden samples were collected from a number of locations listed in Table 5-1 of the NMPI and NMP2 ODCMs and identified in the census as active for 2014. See Table 3.3-1 for 2014 sampling locations.

5-31

B.

Data Evaluation and Discussion A land use census is conducted each year to determine the utilization of land in the vicinity of the Nine Mile Point site. The land use census consists of two types of surveys. A milk animal census is conducted to identify all milk animals within a distance of 10 miles from the site. The census, covering areas out to a distance of 10 miles exceeds the 5 mile distance required by the ODCM. A resident census is conducted and is designed to identify the nearest resident in each meteorological sector out to a distance of 5 miles.

The milk animal census is an estimation of the number of cows and goats within an approximate 10 mile radius of the Nine Mile Point Site. The annual census is conducted during the first half of the grazing season by sending questionnaires to previous milk animal owners and also by road surveys to locate any possible new locations. In the event the questionnaires are not answered, the owners are contacted by telephone or in person. The local county agricultural extension service is also contacted as an additional source of information concerning new milk animal locations in the vicinity of the site.

The number of milk animals located within an approximate 10-mile radius of the site was estimated to be 238 cows and no goats based on the 2014 land use census. The number of cows has remained the same when compared to the 2013 census. The results of the milk animal census are found in Section 6.0, Table 6-13, Milk Animal Census - 2014.

The second type of census conducted is a residence census. The census is conducted in order to identify the closest residence within 5 miles in each of the 22.5 degree land-based meteorological sectors. There are only eight sectors over land where residences are located within 5 miles. The water sectors include: N, NNE, NE, ENE, W, WNW, NW and NNW. The results of the residence census, showing the applicable sectors and degrees and distance of each of the nearest residence, are found in Section 6.0, Table 6-14, Residence Census - 2014. There were no changes identified in the 2014 census for the closest resident in the land based meteorological sectors. The nearest resident locations are illustrated in Section 3.3, Figure 3.3-5.

5.2.8 DIRECT RADIATION, INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

A. Results Summary TLDs are used to measure direct radiation (gamma dose) at the site boundary and Optically Stimulated Luminescence Dosimeters (OSLDs) are used to measure direct radiation (gamma dose) in the localized environment of the ISFSI pad. Sixteen TLDs are located around the site, one in each of the sixteen compass sectors, and fourteen OSLDs are located around the perimeter of the ISFSI pad and specific areas of interest. OSLDs were placed at these locations prior to loading the first storage casks for baseline dose rate determination in the general area of the pad.

5-32

During 2014, four storage casks were moved to the storage facility. The total number of casks in storage is twenty.

The implementation and loading of the ISFSI project has resulted in no increase in dose at the site boundary or to the public. The analysis of offsite doses from direct radiation measurements, presented in Section 5.2.4 of this report, concludes that there is no significant difference in annual dose to the public at or beyond the site boundary. The measured annual dose rate at the nearest residence to the site was consistent with the dose rates measured at the site boundary and the offsite control locations. The results for the Site Boundary, Offsite Sectors, and Special Interest (offsite) were well within expected normal variation when compared to the Control TLD results. The results for the 2014 environmental TLD monitoring program indicate that there is no significant increase in dose rates as a result of operations at the site. The implementation of the ISFSI at the NMPNS plant did not measurably increase the ambient radiation exposure rate at or beyond the site boundary. The lack of a dose rate increase at or beyond the site boundary is consistent with design calculations performed to evaluate compliance with 10 CFR72.104(a).

The measured results of the 2014 TLD monitoring program demonstrate compliance with the offsite dose limits to members of the public specified in 40CFR190 and 10CFR72.104(a).

B. Program Design An array of ten OSLD locations was established around the perimeter of the ISFSI pad and four OSLD locations were placed in specific areas of interest twelve months prior to facility usage.

These pre-operational OSLDs were used for baseline dose rate determination. The OSLDs are placed, collected and read each quarter. Two dosimeters are placed at each location and the average of the two dosimeters is reported. The quarterly results are compared to baseline data to assess the contribution to ambient dose rates in the vicinity of the storage facility from casks as they are placed on the storage pad.

C. Dose Evaluation The pre-operation minimum and maximum dose rates were 2.9 and 6.3 mrem per standard month, respectively. During 2014, the maximum dose rate of 7.1 mrem per standard month was measured at OSLD location 241, north of the ISFSI. The lowest measured dose rate was 2.8 mrem per standard month was measured at OSLD location 237, southeast of the ISFSI.

The following table presents the pre-operation dose rate data and the operational dose rate data for 2014:

5 - 33

Pre-Operation 2014 OSLD Number Sector mrem per mrem per Standard Standard Month Month 233 WNW 3.5 3.7 234 WSW 2.9 3.4 235 S

4.2 3.6 236 SSE 3.8 3.5 237 SE 3.0 2.8 238 ESE 3.5 3.1 239 E

4.0 5.1 240 NE 3.6 6.3 241 N

5.1 7.1 242 NE 6.3 4.5 243 NNW 4.8 5.2 244 NE 4.6 5.4 245 NE 4.0 5.3 246 ENE 4.8 5.0 An evaluation of Site Boundary TLDs and Control TLDs dose rate results for 2014 shows that there is no increase in dose rate at or beyond the site boundary as result of the operation of NMPNS and JAFNPP. A detailed discussion of this evaluation is found in Section 5.2.4. The Environmental TLD results for this period show no significant difference in control and site boundary dose rates compared to preoperational data gathered in 2012.

5.3 CONCLUSION

The Radiological Environmental Monitoring Program (REMP) is an ongoing program implemented to measure and document the radiological impact of NMPNS operations on the local environment.

The program is designed to detect and evaluate small changes in the radiological environment surrounding the site. Environmental media representing food sources consumed at the higher levels of the food chain, such as fish, food products and milk, are part of a comprehensive sampling program. Results of all samples are reviewed closely to determine any possible impact to the environment or to man. In addition, program results are evaluated for possible short-and long-term historical trends.

The federal government has established dose limits to protect the public from radiation and radioactivity.

The Nuclear Regulatory Commission (NRC) specifies a whole body dose limit of 100 mrem/yr to be received by the maximum exposed member of the general public. This limit is set forth in Section 1301, Part 20, Title 10 of the U.S. Code of Federal Regulations (10 CFR 20). The Environmental Protection Agency (EPA) limits the annual whole body dose to 25 mrem/yr, which is specified in Section 10, Part 190, Title 40, of the Code of Federal Regulations (40 CFR 190). Radiation exposure to members of the public, calculated based on the results of the REMP, is extremely small. The dose to members of the public from 5 - 34

operations at the Nine Mile Point site, based on environmental measurement and calculations made from effluent releases, is determined to be a fraction of limits set forth by the NRC and EPA.

The results of the 2014 REMP continue to clearly demonstrate that there is no significant short-term or chronic long-term radiological impact on the environment in the vicinity of the Nine Mile Point site.

No unusual radiological characteristics were measured or observed in the local environment.

The REMP continues to demonstrate that the effluents from the site to the environment contribute no significant or even measurable radiation exposures to the general public as confirmed by the sampling and analysis of environmental media from recognized environmental pathways.

Based on TLD results, there was no measurable increase in radiation levels beyond the site boundary as a result of the hydrogen water chemistry programs or the operations of the ISFSI.

Environmental radiation levels measured at the nearest residence are at the background level based on control station TLD results.

The only measurable radiological impact on the environment continues to be the result of atmospheric weapons testing conducted in the early 1980s, the 1986 accident at the Chernobyl Nuclear Power Plant, and the March 11, 2011 accident at Fukushima Daiichi Nuclear Power Stations.

The results for the 2014 sample program demonstrate that the concentrations of man-made radionuclides continue to decline.

This reduction in environmental background concentrations will allow for the site environmental program to become more sensitive to the measurable impact of plant operations on the environment as time goes on.

The REMP did not detect any plant-related radionuclide in the sample media collected during 2014. Dose from man-made sources in the environment is very small when compared to the dose originating from naturally-occurring sources of radioactivity.

Radiation from naturally-occurring radionuclides such as K-40 and Ra-226 contributed the vast majority of the total annual dose to members of the general public. The dose to members of the public, resulting from plant operations, is extremely small in comparison to the dose contribution from natural background levels and sources other than the plants.

The whole body dose in Oswego County due to natural sources is approximately 46 mrem per individual per year as demonstrated by control environmental TLDs. The fraction of the annual dose to man, attributable to site operation, remains insignificant.

Based upon the overall results of the 2014 Radiological Environmental Monitoring Program, it can be concluded that the levels and variation of radioactivity in the environment samples were consistent with background levels that would be expected for the lakeshore environment of the site.

5-35

5.4 REFERENCES

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," March 1976.

2.

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," October 1977 (Revision 1).

3.

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

4.

U.S. Nuclear Regulatory Commission Branch Technical Position to Regulatory Guide 4.8, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.

5.

National Council on Radiation Protection and Measurements (NCRP), Environmental Radiation Measurements, NCRP Report No. 50, 1975.

6.

National Council on Radiation Protection and Measurements (NCRP), Natural Background Radiation in the United States, NCRP Report No. 45, 1975.

7.

National Council on Radiation Protection and Measurements (NCRP), Cesium-137 from the Environment to Man: Metabolism and Dose, NCRP Report No. 52, 1977.

8.

National Council on Radiation Protection and Measurements (NCRP), Radiation Exposure from Consumer Products and Miscellaneous Sources, NCRP Report No. 56, 1977.

9.

International Commission on Radiological Protection (ICRP), Radionuclide Release into the Environment: Assessment of Doses to Man, ICRP Publication 29, 1979.

10.

Glasstone, Samuel and Jordan, Walter H., Nuclear Power and Its Environmental Effects, First Edition, American Nuclear Society, La Grange Park, I11., 1980.

11.

Schleien, Bernard, The Health Physics and Radiological Health Handbook, Scinta, Inc., Silver Spring, Maryland, 1992.

12.

U.S. Department of Health and Human Services, Preparedness and Response in Radiation Accidents, National Center for Devices and Radiological Health, Rockville, Maryland 20857, August 1983.

13.

National Council on Radiation Protection and Measurements (NCRP), Ionizing Radiation Exposure of the Population of the United States, NCRP Report No. 93, 1987.

5-36

14.

National Council on Radiation Protection and Measurements (NCRP), Exposure of the Population in the United States and Canada from National Background Radiation, NCRP Report No. 94, 1987.

15.

National Council on Radiation Protection and Measurements (NCRP), Ionizing Radiation Exposure of the Population of the United States, NCRP Report No. 160, 2009.

16.

Institute of Nuclear Power Operations, Special Report on the Nuclear Accident at the Fukushima Daiichi Nuclear Power Station, INPO 11-005, November 2012.

5-37

6.0 REPORT PERIOD ANALYTICAL RESULTS TABLES Environmental sample data is summarized in table format. Tables are provided for select sample media and contain data based on actual values obtained over the year. These values are comprised of both positive values and LLD (Lower Limit of Detection) values where applicable.

The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability and with 5% probability of falsely concluding that a blank observation represents a "oreal" signal (see Section 3.7.3 for detailed explanation).

When the initial count of a sample indicates the presence of radioactivity, two recounts are normally performed. When a radionuclide is positively identified in two or more counts, the analytical results for that radionuclide are reported as the mean of the positive detections and the associated error for that mean (see Section 3.7.2 for methodology).

Many of the tables are footnoted with the term "Plant Related Radionuclides".

Plant Related Radionuclides are radionuclides that are produced in the reactor; as a result of plant operation, either through the activation or fission process.

6-1

TABLE 6-1 CONCENTRATIONS OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES - 2014 Results in Units of pCi/kg (dry) +/- 1 Sigma GAMMA EMITTERS Sample Location ***

Collection Date K-40 Co-60 Cs-134 Cs-137 Zn-65 Others t 04/22/14 18890

+

1067 100.4

< 65.5

< 83.9

< 286.5

<LLD Sunset Bay (05)

10/21/14 16700

+

1200 31.7

< 30.0

< 41.3

< 82.1

<LLD 04/22/14 12650

+

716 49.0

< 50.3

< 67.3 117.4

<LLD Lang's Beach (06, Control) 10/21/14 13700

+/-

1060

< 43.1

< 31.7

< 36.0

< 82.3

<LLD

Sample required by the ODCM Corresponds to sample location noted on Figure 3.3-5 t Plant related radionuclides 6-2

TABLE 6-2 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2014 Results in Units of pCi/kg (wet) + 1 Sigma FITZPATRICK * (03)***

GAMMA EMITTERS Date Description K-40 Mn-54 Co-58 Fe-59 Co-60 Cs-134 Cs-137 Zn-65 Others 5/7/2014 BROWN TROUT 3615 -

342

< 44

< 41

< 128

< 48

< 32

< 43

< 64

< LLD 5/7/2014 SMALLMOUTH 4002 + 394

< 39

< 52

< 151

< 64

< 27

< 43

< 110

<LLD BASS 5/7/2014 WALLEYE 4153 + 368

< 45

< 47

< 96

< 42

< 48

< 92

<LLD 9/16/2014 BROWN TROUT 3530 +/- 315

< 31

< 39

< 123

< 33

< 27

< 48

< 92

<LLD 9/16/2014 CHINOOK SALMON 4010 + 400

< 44

< 42

< 165

< 40

< 42

< 39

< 124

<LLD 9/16/2014 LAKETROUT 3450 + 305

< 37

< 135

< 31

< 29

< 44

< 109

<LLD

Sample required by the ODCM Corresponds to sample location noted on Figure 3.3-5 t Plant related radionuclides 6-3

TABLE 6-2 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2014 Results in Units of pCi/kg (wet) +/- 1 Sigma NINE MILE POINT * (02)***

GAMMA EMITERS Date Description K-40 Mn-54 Co-58 Fe-59 Co-60 Cs-134 Cs-137 Zn-65 Others t 5/7/2014 BROWN TROUT 3098 +/- 337

< 46

< 43

< 103

< 49

< 28

< 42

< 102

<LLD 5/7/014 SMALLMOUTH 5/7/2014 3408 +/- 402

< 43

< 53

< 173

< 63

< 44

< 105

<LLD BASS 5/7/2014 WALLEYE 4233 +/- 368

< 45

< 42

< 120

< 41

< 47

< 44

< 74

< LLD 9/16/2014 BROWN TROUT 3540 +/- 319

< 42

< 37

< 123

< 42

< 28

< 39

< 101

<LLD CHINOOK 9/16/2014 SALMON 3700 +/- 371

< 35

< 41

< 124

< 33

< 38

< 32

< 110

<LLD SALMON 9/16/2014 LAKETROUT 3430 +/- 308

< 27

< 34

< 122

< 40

< 30

< 87

<LLD

Sample required by the ODCM Corresponds to sample location noted on Figure 3.3-5 t Plant related radionuclides 6-4

TABLE 6-2 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2014 Results in Units of pCi/kg (wet) +/- 1 Sigma OSWEGO HARBOR (CONTROL) * (00)***

GAMMA EMITTERS Date Description K-40 Mn-54 Co-58 Fe-59 Co-60 Cs-134 Cs-137 Zn-65 Others 5/7/2014 BROWN TROUT 3959

+/- 367

< 49

< 55 143

< 48

< 38

< 55

< 66

<LLD 5/7/2014 SMALLMOUTH 3449 + 392

< 52

< 43 160 71

< 28

< 47 184

<LLD BASS 5/7/2014 WALLEYE 4854

+ 384

< 36

< 35 104

< 32

< 44

< 44 130

<LLD 9/16/2014 BROWNTROUT 3210 +/- 366

< 44 51 131

< 45

< 36

< 36 105

<LLD 9/16/2014 CHINOOK 4710 +/- 362

< 35

< 45 125

< 29

< 30

< 28 86

<LLD SALMON 9/16/2014 LAKETROUT 3100 +/- 294

< 33

< 43

< 124

< 30

< 51

< 38 107

<LLD

Sample required by the ODCM Corresponds to sample location noted on Figure 3.3-5 t Plant related radionuclides 6-5

TABLE 6-3 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES - 2014 (QUARTERLY COMPOSITE SAMPLES)

Results in Units of pCi/liter +/- 1 Sigma STATION CODE PERIOD DATE TRITIUM First Quarter 12/30/13 03/31/14

< 389 FITZPATRICK*

Second Quarter 03/28/14 06/30/14

< 401 (03, INLET)***

Third Quarter 06/30/14 09/30/14

< 402 Fourth Quarter 09/30/14 12/29/14

<360 First Quarter 01/03/14 03/28/14

< 389 OSWEGO STEAM STATION*

Second Quarter 03/28/14 06/27/14

< 402 (08, CONTROL)***

Third Quarter 06/27/14 09/26/14

< 193 Fourth Quarter 09/26/14 01/02/15

< 434 First Quarter 01/03/14 03/28/14

< 389 NINE MILE POINT UNIT I **

Second Quarter 03/28/14 06/27/14

< 402 (09, INLET)***

Third Quarter 06/27/14 09/26/14

< 191 Fourth Quarter 09/26/14 01/02/15

< 436 First Quarter 01/03/14 03/28/14

< 389 NINE MILE POINT UNIT 2**

Second Quarter 03/28/14 06/27/14

< 402 (11, INLET)***

Third Quarter 06/27/14 09/26/14

< 190 Fourth Quarter 09/26/14 01/02/15

< 423 First Quarter 01/03/14 03/28/14

< 389 OSWEGO CITY WATER**

Second Quarter 03/28/14 06/27/14

< 402 (10)***

Third Quarter 06/27/14 09/26/14

< 193 Fourth Quarter 09/26/14 01/02/15

< 431 Sample location required by ODCM Optional sample location Corresponds to sample location noted on Figure 3.3-4 6-6

TABLE 6-4 CONCENTRATIONS OF GAMMA EMITrERS IN SURFACE WATER SAMPLES - 2014 Results in Units of pCi/liter +/- 1 Sigma OSWEGO STEAM STATION * (08, CONTROL)***

Date 1/31/2014 2/28/2014 3/28/2014 5/2/2014 5/30/2014 6/27/2014 NUCLIDE 1-131

< 0.87

< 1.0

< 0.62

< 0.75

< 0.72

< 0.98 Cs-134

< 1.71

< 1.73

< 2.12

< 1.66

< 1.59

< 2.93 Cs-137

< 2.42

< 2.28

< 2.79

< 2.24

< 2.05

< 2.41 Zr-95

< 5.00

< 4.73

< 5.02

< 4.52

< 4.37

< 4.79 Nb-95

< 3.28

< 2.95

< 3.44

< 3.27

< 2.86

< 3.17 Co-58

< 2.97

< 2.34

< 2.91

< 2.21

< 2.22

< 2.97 Mn-54

< 2.53

< 1.99

< 3.06

< 2.36

< 2.20

< 2.47 Fe-59

< 9.90

< 6.72

< 8.86

< 6.87

< 6.77

< 7.85 Zn-65

< 6.55

< 4.99

< 6.55

< 2.95

< 4.35

< 2.36 Co-60

< 3.15

< 2.13

< 2.28

< 1.97

< 2.33

< 8.50 Ba/La-140

< 10.5

< 7.26

< 7.96

< 7.12

< 6.02

< 6.54 Date 8/1/2014 8/29/2014 9/26/2014 10/31/2014 11/26/2014 1/2/2015 NUCLIDE 1-131

< 0.59

< 0.96

<0.82

< 0.38

< 0.42

< 0.73 Cs-134

< 1.72

< 1.88

< 0.94

< 0.57

< 0.64

< 0.83 Cs-137

< 2.04

< 2.36

< 0.94

< 0.62

< 0.81

< 0.86 Zr-95

< 3.79

< 4.66

< 2.23

< 1.26

< 1.43

< 2.17 Nb-95

< 2.69

< 3.23

< 1.09

< 0.85

< 0.81

< 1.39 Co-58

< 2.30

< 2.56

< 1.18

< 0.74

< 0.82

< 1.19 Mn-54

< 1.93

< 2.36

< 1.07

< 0.66

< 0.78

< 0.88 Fe-59

< 6.73

< 7.59

< 3.18

< 1.95

< 1.65

< 2.89 Zn-65

< 2.62

< 3.01

< 2.12

< 1.3

< 1.23

< 2.16 Co-60

< 2.18

< 2.40

< 1.27

< 0.80

< 0.72

< 1.00 Ba/La-140

< 6.54

< 7.16

< 6.58

< 3.7

< 2.27

< 8.51

Sample location required by ODCM Corresponds to sample location noted on Figure 3.3-4 6-7

TABLE 6-4 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2014 Results in Units of pCi/liter +/- 1 Sigma OSWEGO CITY WATER* (10)***

Date 1/31/2014 2/28/2014 3/28/2014 5/2/2014 5/30/2014 6/27/2014 NUCLIDE 1-131

< 14.4

< 14.0

< 10.5

< 13.9

< 11.0

< 11.3 Cs-134

< 1.88

< 1.69

< 3.95

< 1.84

< 2.23

< 1.09 Cs-137

< 2.36

< 2.52

< 2.99

< 2.90

< 1.36 Zr-95

< 4.71

< 5.05

< 6.17

< 5.51

< 6.42

< 3.05 Nb-95

< 3.47

< 3.30

< 4.16

< 3.59

< 3.88

< 2.19 Co-58

< 2.86

< 2.76

< 3.26

< 2.79

< 3.49

< 1.69 Mn-54

< 2.43

< 2.26

< 3.02

< 2.83

< 2.98

< 1.42 Fe-59

< 8.34

< 11.3

< 8.61

< 10.8

< 4.23 Zn-65

< 5.72

< 5.05

< 6.84

< 3.39

< 7.62

< 1.76 Co-60

< 2.30

< 2.58

< 3.89

< 2.84

< 3.81

< 1.41 Ba/La-140

< 8.79

< 10.2

< 8.30

< 8.92

< 11.3

< 6.19 Date 8/1/2014 8/29/2014 9/26/2014 10/31/2014 11/26/2014 1/2/2015 NUCLIDE 1-131

< 12.5

< 13.9

< 12.4

< 10.6

< 1.80 Cs-134

< 2.01

< 2.26

< 0.78

< 0.84

< 0.91

< 0.80 Cs-137

< 2.57

< 3.08

< 0.84

< 1.00

< 0.89

< 0.84 Zr-95

< 4.65

< 6.90

< 1.80

< 2.27

< 2.04

< 2.13 Nb-95

< 3.50

< 4.36

< 1.02

< 1.22

< 1.17

< 1.25 Co-58

< 2.69

< 3.65

< 0.92

< 1.16

< 0.99

< 1.10 Mn-54

< 2.53

< 3.07

< 0.74

< 1.02

< 0.84

< 0.88 Fe-59

< 8.87

< 10.2

< 2.18

< 2.91

< 2.48

< 2.62 Zn-65

< 5.94

< 4.57

< 1.61

< 2.00

< 1.67

< 1.76 Co-60

< 2.34

< 3.81

< 0.71

< 0.78

< 0.84

< 0.82 Ba/La-140

< 7.26

< 12.5

< 4.39

< 4.43

< 3.78

< 7.07

Sample location required by ODCM Corresponds to sample location noted on Figure 3.3-4 6-8

TABLE 6-4 (Continued)

CONCENTRATIONS OF GAMMA EMITEERS IN SURFACE WATER SAMPLES - 2014 Results in Units of pCi/liter + 1 Sigma FITZPATRICK * (03, INLET)***

Date 1/30/2014 2/27/2014 3/31/2014 4/29/2014 5/28/2014 6/30/2014 NUCLIDE 1-131

< 0.43

< 0.49

< 0.58

< 0.45

< 0.44

< 0.51 Cs-134

< 2.19

< 2.06

< 1.90

< 2.03

< 1.96

< 1.81 Cs-137

< 2.70

< 3.20

< 2.45

< 2.89

< 2.53 Zr-95

< 6.22

< 5.45

< 4.61

< 4.28

< 5.49

< 4.96 Nb-95

< 3.35

< 3.36

< 3.15

< 2.82

< 2.46

< 2.81 Co-58

< 2.93

< 3.07

< 2.69

< 2.56

< 2.84

< 2.45 Mn-54

< 2.86

< 3.03

< 2.31

< 2.45

< 2.72

< 2.22 Fe-59

< 7.20

< 7.78

< 7.05

< 6.36

< 7.95

< 7.68 Zn-65

< 6.17

< 6.67

< 2.97

< 4.96

< 3.23

< 5.65 Co-60

< 2.97

< 2.52

< 2.74

< 2.33

< 2.74

< 2.54 Ba/La-140

< 8.28

< 6.64

< 5.44

< 5.46

< 6.50

< 6.39 Date 7/30/2014 8/28/2014 9/30/2014 10/29/2014 12/1/2014 12/29/2014 NUCLIDE 1-131

< 0.74

< 0.50

< 0.43

< 0.62

< 0.20

< 0.74 Cs-134

< 2.03

< 2.18

< 2.22

< 1.10

< 0.83

< 1.15 Cs-137

< 2.20

< 2.71

< 2.94

< 1.14

< 0.91

< 1.35 Zr-95

< 4.34

< 4.89

< 2.18

< 1.77

< 2.59 Nb-95

< 2.90

< 3.31

< 3.28

< 1.31

< 1.02

< 1.45 Co-58

< 2.37

< 3.29

< 2.77

< 1.25

< 0.77

< 1.35 Mn-54

< 2.13

< 2.83

< 3.08

< 1.13

< 0.67

< 1.11 Fe-59

< 7.34

< 7.98

< 7.57

< 2.94

< 2.13

< 3.14 Zn-65

< 5.05

< 7.14

< 6.76

< 2.31

< 1.49

< 2.30 Co-60

< 2.66

< 2.75

< 3.00

< 1.14

< 0.79

< 1.13 Ba/La-140

< 5.78

< 5.04

< 6.35

< 4.43

< 3.74

< 4.85

Sample location required by ODCM Corresponds to sample location noted on Figure 3.3-4 6-9

TABLE 6-4 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2014 Results in Units of pCi/liter +/- 1 Sigma NINE MILE POINT UNIT 1 ** (09, INLET)***

Date 1/31/2014 2/28/2014 3/28/2014 5/2/2014 5/30/2014 6/27/2014 NUCLIDE 1-131

< 12.9

< 9.74

< 8.67

< 12.9

< 8.73

< 13.6 Cs-134

< 1.63

< 2.11

< 1.87

< 2.00

< 1.96

< 1.57 Cs-137

< 2.36

< 2.52

< 2.07

< 2.33

< 2.54

< 2.13 Zr-95

< 4.27

< 5.91

< 4.25

< 4.89

< 5.57

< 4.17 Nb-95

< 2.73

< 4.04

< 3.04

< 3.52

< 3.75

< 3.05 Co-58

< 2.51

< 3.18

< 2.78

< 2.60

< 2.98

< 2.29 Mn-54

< 1.92

< 2.99

< 2.54

< 2.33

< 2.59

< 1.95 Fe-59

< 7.55

< 12.4

< 7.07

< 7.95

< 10.5

< 7.32 Zn-65

< 4.70

< 6.98

< 5.81

< 6.05

< 6.07

< 4.53 Co-60

< 2.00

< 4.05

< 2.42

< 2.55

< 3.31

< 2.08 Ba/La-140

< 8.32

< 11.4

< 5.77

< 7.04

< 10.1

< 8.64 Date 8/1/2014 8/29/2014 9/26/2014 10/31/2014 11/26/2014 1/2/2015 NUCLIDE 1-131

< 12.5

< 13.1

< 14.20

< 9.06

< 11.1

< 1.87 Cs-134

< 1.90

< 2.06

< 0.76

< 0.60

< 0.84

< 0.68 Cs-137

< 2.53

< 3.11

< 0.85

< 0.63

< 0.98

< 0.78 Zr-95

< 4.74

< 6.48

< 1.90

< 1.28

< 2.12

< 1.70 Nb-95

< 3.10

< 4.43

< 1.15

< 0.81

< 1.14

< 1.15 Co-58

< 2.72

< 3.48

< 0.97

< 0.78

< 1.13

< 0.94 Mn-54

< 2.53

< 3.35

< 0.83

< 0.64

< 0.79

< 0.79 Fe-59

< 7.25

< 10.2

< 2.37

< 1.57

< 2.25

< 2.10 Zn-65

< 3.06

< 9.01

< 1.61

< 1.49

< 1.74

< 1.79 Co-60

< 2.58

< 3.73

< 0.87

< 0.61

< 0.95

< 0.80 Ba/La-140

< 7.23

< 13.1

< 5.02

< 3.12

< 3.93

< 6.85

- Optional sample location Corresponds to sample location noted on Figure 3.3-4 6-10

TABLE 6-4 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2014 Results in Units of pCi/liter +/- 1 Sigma NINE MILE POINT UNIT 2 ** (11, INLET)***

Date 1/31/2014 2/28/2014 3/28/2014 5/2/2014 5/30/2014 6/27/2014 NUCLIDE 1-131

< 14.4

< 12.8

< 8.99

< 13.0

< 9.48

< 13.7 Cs-134

< 3.35

< 3.23

< 2.00

< 2.10

< 1.95

< 1.32 Cs-137

< 2.38

< 2.58

< 2.89

< 2.76

< 2.84

< 1.87 Zr-95

< 5.36

< 5.73

< 5.72

< 5.16

< 4.42

< 3.93 Nb-95

< 3.68

< 3.50

< 3.51

< 3.20

< 3.01 Co-58

< 2.68

< 3.52

< 2.84

< 2.82

< 2.79

< 2.41 Mn-54

< 2.54

< 2.44

< 3.18

< 2.44

< 2.74

< 2.09 Fe-59

< 10.4

< 7.13

< 7.74

< 8.15

< 7.40

< 7.54 Zn-65

< 5.55

< 7.04

< 6.64

< 5.98

< 6.01

< 4.66 Co-60

< 3.11

< 2.76

< 2.80

< 2.46

< 2.62

< 3.32 Ba/La-140

< 10.3

< 7.57

< 7.18

< 7.02

< 6.68

< 9.66 Date 8/1/2014 8/29/2014 9/26/2014 10/31/2014 11/26/2014 1/2/2015 NUCLIDE 1-131

< 14.3

< 13.9

< 10.5

< 12.4

< 9.85

< 1.83 Cs-134

< 2.18

< 2.41

< 0.64

< 0.92

< 1.03

< 0.60 Cs-137

< 2.81

< 0.66

< 1.03

< 1.05

< 0.63 Zr-95

< 6.01

< 4.81

< 1.40

< 2.73

< 2.27

< 1.38 Nb-95

< 4.06

< 3.52

< 0.97

< 1.18

< 1.19

< 0.85 Co-58

< 3.31

< 3.11

< 0.80

< 1.22

< 1.25

< 0.84 Mn-54

< 2.96

< 2.71

< 0.61

< 1.19

< 1.13

< 0.60 Fe-59

< 9.08

< 7.67

< 1.71

< 3.32

< 2.54

< 1.90 Zn-65

< 3.53

< 6.92

< 1.30

< 2.25

< 1.81

< 1.33 Co-60

< 2.54

< 2.63

< 0.60

< 1.20

< 1.19

< 0.60 Ba/La-140

< 9.38

< 8.42

< 4.05

< 4.49

< 3.37

< 4.82

- Optional sample location

- - Corresponds to sample location noted on Figure 3.3-4 6-11

TABLE 6-5 ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFFSITE SAMPLE LOCATIONS - 2014 GROSS BETA ACTIVITY pCi/ mn3 +/-

1 Sigma Week End R-1*

R-2*

R-3*

R-4*

R-5 D-2 E*

F*

G**

01/07/14 0.018 +/- 0.001 0.015 +/- 0.001 0.018 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.013 +/- 0.001 0.020 +/- 0.001 0.018 +/- 0.001 0.018 +/- 0.001 01/14/14 0.019 +/- 0.001 0.020 +/- 0.001 0.019 +/- 0.001 0.018 +/- 0.001 0.020 +/- 0.002 0.015 +/- 0.001 0.020 +/- 0.001 0.016 +/- 0.001 0.019 +/- 0.001 01/21/14 0.019 +/- 0.001 0.022 +/- 0.002 0.019 +/- 0.001 0.024 +/- 0.002 0.019 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.020 +/- 0.001 0.020 +/- 0.001 01/28/14 10.013 +/- 0.001 0.013 +/- 0.001 0.020 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 02/04/14 0.019 +/- 0.001 0.020 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.022 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.021 +/- 0.001 0.021 +/- 0.001 02/11/14 0.021 +/- 0.001 0.021 +/- 0.001 0.020 +/- 0.001 0.018 +/- 0.001 0.019 +/- 0.001 0.020 +/- 0.001 0.019 +/- 0.001 0.019 +/- 0.001 0.019 +/- 0.001 02/18/14 0.021 +/- 0.001 0.019 +/- 0.001 0.022 +/- 0.002 0.023 +/- 0.002 0.023 +/- 0.002 0.023 +/- 0.002 0.021 +/- 0.001 0.021 +/- 0.001 0.024 +/- 0.002 02/25/14 0.016 +/- 0.001 0.017 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.015 +/- 0.001 0.018 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001 03/04/14 0.027 +/- 0.002 0.026 +/- 0.002 0.027 +/- 0.002 0.030 +/- 0.002 0.030 +/- 0.002 0.027 +/- 0.002 0.029 +/- 0.002 0.032 +/- 0.002 0.026 +/- 0.002 03/11/14 0.020 +/- 0.001 0.018 +/- 0.001 0.021 +/- 0.001 0.020 +/- 0.001 0.019 +/- 0.001 0.022 +/- 0.001 0.019 +/- 0.001 0.022 +/- 0.001 0.022 +/- 0.001 03/18/14 0.017 +/- 0.001 0.017 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.018 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 03/25/14 0.014 +/- 0.001 0.014 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 04/01/14 0.016 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.020 +/- 0.001 0.018 +/- 0.001 04/08/14 0.013 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.012 +/- 0.001 0.016 +/- 0.001 04/15/14 0.019 +/- 0.001 0.020 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 0.018 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 04/22/14 0.019 +/- 0.001 0.019 +/- 0.001 0.022 +/- 0.002 0.017 +/- 0.001 0.020 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.020 +/- 0.001 0.020 +/- 0.001 04/29/14.0.018 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.018 +/- 0.001 0.019 +/- 0.001 0.013 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 05/06/14 0.006 +/- 0.001 0.007 +/- 0.001 0.005 +/- 0.001 0.008 +/- 0.001 0.006 +/- 0.001 0.006 +/- 0.001 0.008 +/- 0.001 0.006 +/- 0.001 0.006 +/- 0.001 05/13/14 0.018 +/- 0.001 0.017 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.012 +/- 0.001 0.015 +/- 0.001 0.019 +/- 0.001 0.019 +/- 0.001 05/20/14 0.015 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 05/28/14 0.018 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.019 +/- 0.001 06/03/14 0.011 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.009 +/- 0.001 0.011 +/- 0.001 0.008 +/- 0.001 0.013 +/- 0.001 06/10/14 0.012 +/- 0.001 0.012 +/- 0.001 0.008 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.007 +/- 0.001 0.008 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 06/17/14.0.007 +/- 0.001 0.007 +/- 0.001 0.008 +/- 0.001 0.005 +/- 0.001 0.007 +/- 0.001 0.006 +/- 0.001 0.007 +/- 0.00110.006 +/- 0.00110.008 +/- 0.001 06/24/14 0.010 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 07/01/14 10.016 +/- 0.00110.015 +/- 0.00110.013 +/- 0.00110.017 +/- 0.00110.019 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.00110.017 +/- 0.001 0.013 +/- 0.001

Sample location required by ODCM

- Optional sample location 6 -12

TABLE 6-5 (Continued)

ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFFSITE SAMPLE LOCATIONS - 2014 GROSS BETA ACTIVITY pCi/ m,3 + 1 Sigma Week End R-1 R-2*

R-3*

R-4*

R-5 D-2*

E*

F G

Date 07/08/14 0.016 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 07/15/14 0.014 +/- 0.001 0.017 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.018 +/- 0.001 07/22/14 0.015 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 07/29/14 0.015 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 08/05/14 0.018 +/- 0.001 0.020 +/- 0.001 0.018 +/- 0.001 0.018 +/- 0.001 0.017 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001 08/12/14 10.015 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.011 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 08/19/14 0.010 +/- 0.001 0.008 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.013 +/- 0.001 0.008 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 08/26/14 0.015 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.018 +/- 0.001 0.017 +/- 0.001 0.009 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 09/03/14 0.018 +/- 0.001 0.014 +/- 0.001 0.017 +/- 0.001 0.016 +-0.001 0.015 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.017 +/- 0.001 09/09/14 0.016 +/- 0.001 0.021 +/- 0.002 0.017 +/- 0.002 0.021 +/- 0.002 0.016 +/- 0.001 0.015 +/- 0.001 0. 018 +/- 0.002 0,019 +/- 0. 001 0.021 +/- 0.002 09/16/14 0.009 +/- 0.001 0.009 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 0.011 +/- 0.001 0.008 +/- 0.001 0.010 +/- 0.001 0.008 +/- 0.001 0.011 +/- 0.001 09/23/14 0.018 +/- 0.001 0.018 +/- 0.001 0.015 +/- 0.002 0.017 +/- 0.002 0.017 +/- 0.001 0.017 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.019 +/- 0.001 09/30/14 0.022 +/- 0.001 0.021 +/- 0.001 0.020 +/- 0.001 0.018 +/- 0.001 0.021 +/- 0.001 0.020 +/- 0.001 0.020 +/- 0.001 0.020 +/- 0.001 0.023 +/- 0.001 10/07/14 0.017 +/- 0.003 0.015 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.017 +/- 0.003 0.099 +/- 0.010 0.019 +/- 0.003 10/14/14 0.014 +/- 0.002 0.016 +/- 0.002 0.015 +/- 0.003 0.016 +/- 0.003 0.014 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.003 0.015 +/- 0.003 0.016 +/- 0.002 10/21/14 0.023 +/- 0.003 0.026 +/- 0.003 0.025 +/- 0.003 0.024 +/- 0.003 0.022 +/- 0.003 0.024 +/- 0.003 0.028 +/- 0.003 0.028 +/- 0.003 0.026 +/- 0.003 10/28/14 0.011 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.003 0.015 +/- 0.002 11/04/14 0.015 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.003 0.015 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.015 + 0.002 0.015 +/- 0.002 11/12/14 0.016 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.002 0.016 +/- 0.002 0.018 +/- 0.002 11/18/14 0.014 +/- 0.003 0.016 +/- 0.003 0.012 +/- 0.003 0.011 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.003 0.014 +/- 0.003 0.016 +/- 0.003 0.014 +/- 0.003 11/25/14 0.018 +/- 0.003 0.018 +/- 0.003 0.018 +/- 0.003 0.014 +/- 0.002 0.015 +/- 0.003 0.022 +/- 0.003 0.019 +/- 0.003 0.018 +/- 0.003 0.017 +/- 0.002 12/02/14 0.016 +/- 0.003 0.014 +/- 0.002 0.013 +/- 0.002 0.017 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.015 +/- 0.002 12/09/14 0.022 +/- 0.003 0.020 +/- 0.003 0.018 +/- 0.003 0.018 +/- 0.003 0.018 +/- 0.002 0.018 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.003 12/16/14 0.012 +/- 0.002 0.014 +/- 0.002 0.010 +/- 0.002 0.015 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 12/23/14 0.012 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 12/30/14 0.013 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.017 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002

Sample location required by ODCM

- Optional sample location 6-13

TABLE 6-6 ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ONSITE SAMPLE LOCATIONS - 2014

_____GROSS BETA ACTIVITY pCi/ m 3 +/- 1 Sigma Week End D-1 GH**

Date 01/06/14 0.019 +/-

0.001 0.018 +/-

0.001 0.019 +/-

0.001 0.012 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 01/13/14 0.018 +/- 0.001 0.020 +/-

0.001 0.022 +/-

0.001 0.015 +/- 0.001 0.020 +/- 0.001 0.021 +/-

0.001 01/20/14 0.019 +/- 0.001 0.018 +/-

0.001 0.022 +/-

0.002 0.017 +/-

0.001 0.021 +/- 0.001 0.024 +/- 0.002 01/27/14 0.016 +/- 0.001 0.021 +/- 0.001 0.021 +/- 0.001 0.014 +/-

0.001 0.017 +/-

0.001 0.020 +/- 0.001 02/03/14 0.015 +/- 0.001 0.018 +/- 0.001 0.019 +/- 0.001 0.011 +/- 0.001 0.018 + 0.001 0.018 +/- 0.001 02/10/14 0.019 +/- 0.001 0.018 +/- 0.001 0.020 +/- 0.002 0.010 +/- 0.001 0.019 +/- 0.001 0.021 +/- 0.001 02/17/14 0.025 +/- 0.002 0.025 +/- 0.002 0.026 +/- 0.002 0.013 +/- 0.001 0.021 +/- 0.001 0.027 +/-

0.002 02/24/14 0.016 +/-

0.001 0.015 +/- 0.001 0.015 +/-

0.001 0.013 +/-

0.001 0.016 + 0.002 0.016 +/-

0.001 03/03/14 0.028 +/-

0.002 0.026 +/- 0.002 0.027 +/-

0.002 0.016 +/-

0.001 0.025 + 0.002 0.025 +/-

0.002 03/10/14 0.024 +/-

0.002 0.022 +/-

0.002 0.024 +/-

0.002 0.016 +/-

0.001 0.020 + 0.001 0.022 +/-

0.001 03/17/14 0.022 +/-

0.001 0.017 +/-

0.001 0.018 +/-

0.001 0.015 +/-

0.001 0.017 + 0.001 0.017 +/-

0.001 03/24/14 0.013 +/-

0.001 0.012 +/-

0.001 0.013 +/- 0.001 0.010 +/- 0.001 0.014 + 0.001 0.011 +/-

0.001 03/31/14 0.019 +/- 0.001 0.022 +/-

0.002 0.022 +/- 0.002 0.013 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 04/07/14 0.016 +/-

0.001 0.011 +/-

0.001 0.015 +/- 0.001 0.012 +/-

0.001 0.016 +/- 0.001 0.015 +/-

0.001 04/14/14 0.017 +/-

0.001 0.016 +/-

0.001 0.019 +/- 0.002 0.018 +/-

0.001 0.017 + 0.001 0.019 +/-

0.001 04/21/14 0.018 +/-

0.001 0.018 +/- 0.001 0.022 +/-

0.002 0.014 +/-

0.001 0.018 + 0.001 0.019 +/-

0.001 04/28/14 0.016 +/-

0.001 0.019 +/-

0.001 0.018 +/-

0.001 0.019 +/-

0.001 0.019 +/- 0.001 0.020 +/-

0.001 05/05/14 0.008

+/-

0.001 0.006

+/-

0.001 0.008 +/-

0.001 0.007 +/-

0.001 0.006

+/-

0.001 0.006 +/-

0.001 05/12/14 0.014 +/- 0.001 0.014 +/-

0.001 0.014 +/-

0.001 0.017 +/-

0.001 0.014

+/-

0.001 0.015 +/-

0.001 05/19/14 0.013

+/- 0.001 0.011

+/-

0.001 0.010 +/-

0.001 0.013 +/-

0.001 0.012

+/- 0.001 0.012 +/-

0.001 05/27/14 0.016

+/- 0.001 0.013

+/-

0.001 0.017 +/-

0.001 0.019 +/-

0.001 0.017 +/-

0.001 0.015

+/-

0.001 06/02/14 0.009

+/- 0.001 0.008

+/-

0.001 0.010 +/-

0.001 0.008

+/-

0.001 0.009

+/- 0.001 0.009

+/-

0.001 06/09/14 0.008 +/-

0.001 0.012

+/-

0.001 0.010 +/-

0.001 0.010

+/- 0.001 0.011

+/-

0.001 06/16/14 0.007

+/- 0.001 0.009

+/-

0.001 0.008 +/-

0.001 0.007

+/-

0.001 0.008

+/- 0.001 0.008

+/- 0.001 06/23/14 0.010 +/-

0.001 0.010

+/-

0.001 0.012 +/-

0.001 0.009

+/-

0.001 0.001

+/- 0.001 0.009 +/- 0.001 06/30/14 0.014 +/-

0.001 0.013 +/-

0.001 0.016 +/-

0.001 0.015 +/-

0.001 013+/- 0.001

- Optional sample location 6 -14

TABLE 6-6 (Continued)

ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ONSITE SAMPLE LOCATIONS - 2014 GROSS BETA ACTIVITY pCi/mn3 + 1 Sigma Week End D-1 G*

Date 07/07/14 0.016

+/-

0.001 0.015 0.001 0.015

+/- 0.001 0.015

+/- 0.001 0.016

+/-

0.001 0.014

+/- 0.001 07/14/14 0.015 0.001 0.014

+/-

0.001 0.016 +/-

0.001 0.015

+/-

0.001 0.018

+/-

0.001 0.014

+/-

0.001 07/21/14 0.015

+/-

0.001 0.013 0.001 0.015

+/-

0.001 0.014 +/-

0.001 0.013

+/-

0.001 0.011

+/-

0.001 07/28/14 0.019

+/-

0.001 0.016

+/-

0.001 0.018 -

0.001 0.016 +/-

0.001 0.021

+/- 0.002 0.016 0.001 08/04/14 0.014

+/-

0.001 0.016 + 0.001 0.013 0.001 0.013

+/- 0.001 0.012 +/- 0.001 0.013 0.001 08/11/14 0.015 0.001 0.016 0.001 0.013 0.001 0.015

+/- 0.001 0.015

+/- 0.001 0.015 0.001 08/18/14 0.011

+/- 0.001 0.013 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.013 0.001 0.011

+/-

0.001 08/25/14 0.014

+/- 0.001 0.014

+/- 0.001 0.014 -

0.001 0.012

+/- 0.001 0.015

+/-

0.001 0.013 0.001 09/02/14 0.014 +/-

0.001 0.017 0.001 0.016 +/-

0.001 0.016

+/- 0.001 0.016

+/-

0.001 0.014 +/- 0.001 09/08/14 0.020 +/-

0.002 0.017 -

0.001 0.018

+/- 0.001 0.017 0.001 0.019 0.002 0.019

+/-

0.002 09/15/14 0.010 +/- 0.001 0.009 +/-

0.001 0.008

+/-

0.001 0.009

+/-

0.001 0.009

+/-

0.001 0.009

+/-

0.001 09/22/14 0.018 +/-

0.001 0.020 +/-

0.001 0.018

+/-

0.001 0.016

+/-

0.001 0.020

+/-

0.001 0.017

+/-

0.001 09/29/14 0.018 -

0.001 0.017 +/- 0.001 0.019

+/-

0.001 0.019

+/-

0.001 0.018

+/-

0.001 0.017

+/-

0.001 10/06/14 0.017 +/- 0.003 0.018 -

0.003 0.016

+/-

0.003 0.019 +/- 0.003 0.017

+/- 0.003 0.016 +/- 0.003 10/13/14 0.016

+/-

0.003 0.015

+/- 0.002 0.012

+/- 0.002 0.016

+/-

0.002 0.014

+/-

0.002 0.012 +/-

0.002 10/20/14 0.014

+/-

0.002 0.012 -

0.002 0.014

+/-

0.002 0.011 0.002 0.012

+/-

0.002 0.013 0.002 10/27/14 0.013

+/- 0.002 0.014 +/-

0.002 0.013

+/-

0.002 0.012 0.002 0.015

+/-

0.002 0.013

+/-

0.002 11/03/14 0.013

+/-

0.002 0.016 -

0.003 0.015

+/- 0.002 0.015

+/-

0.002 0.014 +/-

0.002 0.014 -

0.002 11/10/14 0.018

+/-

0.003 0.014

+/-

0.002 0.015

+/-

0.002 0.018 0.003 0.016 +/-

0.002 0.018 0.002 11/17/14 0.016 +/-

0.003 0.015

+/-

0.002 0.015 0.002 0.014 0.002 0.018

+/-

0.003 0.015 0.002 11/24/14 0.022

+/-

0.003 0.020

+/-

0.003 0.019 0.003 0.019 0.003 0.016

+/-

0.002 0.018

+/-

0.003 12/01/14 0.014 0.002 0.014

+/-

0.002 0.014

+/-

0.002 0.015 0.002 0.014

+/-

0.002 0.014

+/-

0.002 12/08/14 0.019

+/-

0.003 0.021 0.003 0.019

+/-

0.003 0.020 0.003 0.021

+/-

0.003 0.018

+/-

0.003 12/15/14 0.017 0.003 0.013

+/-

0.002 0.015 0.002 0.018 0.003 0.013

+/- 0.002 0.015 0.003 12/22/14 0.016 0.002 0.012

+/-

0.002 0.014

+/-

0.002 0.016 +/-

0.002 0.014 +/-

0.002 0.012 0.002 12/29/14 0.011

+/-

0.002 0.015

+/-

0.002 0.012

+

0.002 0.012 +/-

0.002 0.012

+/-

0.002 0.010

+/-

0.002

- Optional sample location 6-15

TABLE 6-7 ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFFSITE SAMPLE LOCATIONS - 2014 1-131 ACTIVITY DCi/ m3 -- 1 Sigma Week End R-1

R-2

R-3 I R-4*

R-5

D-2**

E **

F**

G**

Date I

01/07/14 01/14/14 01/21/14 01/28/14 02/04/14 02/11/14 02/18/14 02/25/14 03/04/14 03/11/14 03/18/14 03/25/14 04/01/14 04/08/14 04/15/14 04/22/14 04/29/14 05/06/14 05/13/14 05/20/14 05/28/14 06/03/14 06/10/14 06/17/14 06/24/14 07/01/14 0.018 0.012 0.023 0.017 0.019 0.020 0.011 0.022 0.021 0.018 0.017 0.022 0.021 0.024 0.020 0.017 0.023 0.024 0.022 0.021 0.018 0.027 0.019 0.024 0.017 0.012

< 0.017

< 0.016

< 0.015

< 0.017

< 0.015

< 0.017

< 0.015

< 0.021

< 0.025

< 0.012

< 0.018

< 0.022

< 0.016

< 0.003

< 0.018

< 0.016

< 0.015

< 0.019

< 0.014

< 0.019

< 0.018

< 0.015

< 0.016

< 0.017

< 0.019 0.018 0.008 0.014 0.021 0.016 0.014 0.014 0.019 0.020 0.014 0.014 0.019 0.017 0.017 0.027 0.022 0.019 0.020 0.017 0.016 0.010 0.021 0.015 0.009 0.022 0.013 0.024 0.018 0.022 0.021 0.019 0.018 0.015 0.021 0.021 0.021 0.019 0.021 0.021 0.019 0.020 0.021 0.025 0.016 0.021 0.016 0.017 0.020 0.022 0.018 0.020 0.014 0.014 0.021 0.018 0.013 0.014 0.015 0.023 0.017 0.020 0.017 0.020 0.018 0.014 0.018 0.020 0.017 0.028 0.018 0.014 0.014 0.014 0.017 0.014 0.018 0.013 0.020 0.017 0.017 0.017 0.017 0.020 0.017 0.022 0.018 0.017 0.020 0.017 0.021 0.013 0.016 0.012 0.021 0.026 0.013 0.020 0.019 0.021 0.024 0.017 0.017 0.015 0.018 0.016 0.022 0.027 0.019 0.019 0.022 0.020 0.023 0.021 0.022 0.017 0.013 0.015 0.015 0.020 0.019 0.024 0.022 0.019 0.024 0.016 0.021 0.019 0.021 0.023 0.020 0.021 0.012 0.017 0.022 0.012 0.017 0.015 0.012 0.013 0.022 0.017 0.020 0.014 0.012 0.023 0.018 0.019 0.014 0.015 0.019 0.016 0.014 0.014 0.017 0.012 0.026 0.016 0.017 0.019 0.016 0.016 0.020 0.010 0.018 0.021 0.018 0.015 0.031 0.019 0.019 0.022 0.017 0.018 0.020 0.016 0.017 0.016 0.016 0.013 0.018 0.023 0.019

Sample location required by ODCM

- Optional sample location 6-16

TABLE 6-7 (Continued)

ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFFSITE SAMPLE LOCATIONS - 2014 1-131 ACTIVITY DCi/ m3 +/- 1 Sigma Week End R1 R2*

R R-3

R-4

R-5*

D-2**

E**

F **I G**

Date I

I 07/08/14 07/15/14 07/22/14 07/29/14 08/05/14 08/12/14 08/19/14 08/26/14 09/03/14 09/09/14 09/16/14 09/23/14 09/30/14 10/07/14 10/14/14 10/21/14 10/28/14 11/04/14 11/12/14 11/18/14 11/25/14 12/02/14 12/09/14 12/16/14 12/23/14 12/30/14 0.016 0.023 0.021 0.017 0.020 0.020 0.019 0.015 0.019 0.021 0.020 0.021 0.014 0.009 0.030 0.021 0.026 0.017 0.022 0.050 0.024 0.035 0.052 0.030 0.054 0.035 0.017 0.022 0.014 0.023 0.013 0.009 0.023 0.016 0.013 0.018 0.010 0.020 0.022 0.022 0.032 0.022 0.026 0.017 0.022 0.049 0.024 0.034 0.050 0.030 0.052 0.034 0.020 0.018 0.014 0.016 0.021 0.022 0.018 0.010 0.016 0.024 0.024 0.014 0.018 0.022 0.032 0.022 0.026 0.018 0.023 0.052 0.024 0.034 0.055 0.027 0.058 0.032 0.018 0.015 0.016 0.026 0.016 0.019 0.023 0.014 0.024 0.019 0.013 0.016 0.020 0.021 0.010 0.008 0.011 0.007 0.022 0.022 0.012 0.013 0.012 0.017 0.022 0.019 0.024 0.022 0.018 0.014 0.017 0.019 0.012 0.017 0.018 0.017 0.024 0.021 0.023 0.021 0.026 0.019 0.025 0.016 0.037 0.041 0.031 0.032 0.030 0.032 0.044 0.035 0.018 0.016 0.003 0.016 0.022 0.018 0.014 0.019 0.029 0.020 0.024 0.014 0.015 0.022 0.024 0.018 0.026 0.015 0.036 0.041 0.030 0.031 0.031 0.029 0.043 0.036 0.022 0.011 0.021 0.021 0.016 0.015 0.019 0.018 0.020 0.024 0.017 0.026 0.020 0.020 0.026 0.020 0.025 0.016 0.037 0.041 0.030 0.034 0.031 0.033 0.045 0.035 0.023 0.016 0.012 0.016 0.013 0.018 0.016 0.016 0.013 0.018 0.020 0.009 0.015 0.063 0.027 0.017 0.028 0.014 0.037 0.040 0.028 0.032 0.030 0.031 0.042 0.036 0.020 0.021 0.020 0.022 0.018 0.019 0.016 0.020 0.020 0.020 0.024 0.019 0.015 0.022 0.031 0.024 0.027 0.017 0.022 0.052 0.024 0.033 0.049 0.030 0.054 0.035

Sample location required by ODCM

- Optional sample location 6-17

TABLE 6-8 ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ONSITE SAMPLE LOCATIONS - 2014 1-131 ACTIVITY pCi/ n3 +/- 1 Sigma Week End Dae DE1n**

D G**

H**

I **

JI**

K**

Date II 01/06/14

< 0.019

< 0.018

< 0.019

< 0.018

< 0.015 01/13/14

< 0.018

< 0.025

< 0.022

< 0.018

< 0.024

< 0.017 01/20/14

< 0.021

< 0.022

< 0.023

< 0.032

< 0.021

< 0.021 01/27/14

< 0.021

< 0.017

< 0.014

< 0.021

< 0.011

< 0.016 02/03/14

< 0.018

< 0.014

< 0.022

< 0.017

< 0.021 02/10/14

< 0.019

< 0.022

< 0.014

< 0.018

< 0.019

< 0.019 02/17/14

< 0.020

< 0.019

< 0.023

< 0.017

< 0.023 02/24/14

< 0.022

< 0.017

< 0.025

< 0.020

< 0.029

< 0.024 03/03/14

< 0.021

< 0.016

< 0.020

< 0.015

< 0.009

< 0.011 03/10/14

< 0.019

< 0.021

< 0.016

< 0.020

< 0.017

< 0.017 03/17/14

< 0.029

< 0.015

< 0.023

< 0.021

< 0.011

< 0.024 03/24/14

< 0.012

< 0.011

< 0.023

< 0.018

< 0.015

< 0.026 03/31/14

< 0.024

< 0.015

< 0.018

< 0.022

< 0.016

< 0.017 04/07/14

< 0.018

< 0.012

< 0.014

< 0.016

< 0.018 04/14/14

< 0.021

< 0.012

< 0.018

< 0.021

< 0.019 04/21/14

< 0.023

< 0.017

< 0.018

< 0.019

< 0.017

< 0.023 04/28/14

< 0.024

< 0.015

< 0.020

< 0.015

< 0.018

< 0.020 05/05/14

< 0.020

< 0.024

< 0.021

< 0.013

< 0.018 05/12/14

< 0.018

< 0.015

< 0.023

< 0.010

< 0.017 05/19/14

< 0.017

< 0.016

< 0.017

< 0.016

< 0.015

< 0.013 05/27/14

< 0.017

< 0.022

< 0.017

< 0.015

< 0.014 06/02/14

< 0.020

< 0.014

< 0.024

< 0.021

< 0.018

< 0.021 06/09/14

< 0.016

< 0.014

< 0.021

< 0.013

< 0.012 06/16/14

< 0.019

< 0.020

< 0.021

< 0.018

< 0.021 06/23/14

< 0.020

< 0.021

< 0.019

< 0.021

< 0.018

< 0.017 06/30/14

< 0.018

< 0.010

< 0.013

< 0.016

< 0.014

< 0.018

- Optional sample location 6-18

TABLE 6-8 (Continued)

ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ONSITE SAMPLE LOCATIONS - 2014 1-131 ACTIVITY pCi/m 3.- 1 Sigma Week End K

Date D-1 *G**

H**

I**

J **

K-**

07/07/14 07/14/14 07/21/14 07/28/14 08/04/14 08/11/14 08/18/14 08/25/14 09/02/14 09/08/14 09/15/14 09/22/14 09/29/14 10/06/14 10/13/14 10/20/14 10/27/14 11/03/14 11/10/14 11/17/14 11/24/14 12/01/14 12/08/14 12/15/14 12/22/14 12/29/14

< 0.017

< 0.019

< 0.017

< 0.020

< 0.013

< 0.017

< 0.022

< 0.021

< 0.010

< 0.020

< 0.012

< 0.017

< 0.024

< 0.033

< 0.024

< 0.027

< 0.015

< 0.036

< 0.032

< 0.026

< 0.032

< 0.020

< 0.031

< 0.040

< 0.024

< 0.018

< 0.014

< 0.020

< 0.018

< 0.020

< 0.024

< 0.018

< 0.010

< 0.012

< 0.016

< 0.012

< 0.020

< 0.014

< 0.016

< 0.012

< 0.021

< 0.011

< 0.016

< 0.024

< 0.018

< 0.020

< 0.016 0.026 0.018 0.020 0.016 0.019 0.020 0.013 0.011 0.020 0.018 0.020 0.023 0.017 0.029 0.013 0.009 0.026 0.006 0.014 0.012 0.010 0.014 0.007 0.017 0.017 0.009

< 0.015

< 0.018

< 0.022

< 0.024

< 0.026

< 0.022

< 0.026

< 0.021

< 0.015

< 0.022

< 0.021

< 0.012

< 0.024

< 0.031

< 0.032

< 0.024

< 0.026

< 0.015

< 0.036

< 0.033

< 0.026

< 0.035

< 0.019

< 0.031

< 0.039

< 0.023

< 0.017

< 0.020

< 0.016

< 0.020

< 0.024

< 0.015

< 0.017

< 0.020

< 0.017

< 0.015

< 0.016

< 0.030

< 0.034

< 0.023

< 0.026

< 0.015

< 0.036

< 0.032

< 0.026

< 0.035

< 0.019

< 0.032

< 0.039

< 0.023

< 0.019

< 0.022

< 0.015

< 0.019

< 0.018

< 0.020

< 0.021

< 0.015

< 0.018

< 0.015

< 0.017

< 0.024

< 0.018

< 0.029

< 0.034

< 0.024

< 0.027

< 0.014

< 0.033

< 0.030

< 0.027

< 0.033

< 0.018

< 0.032

< 0.042

< 0.022

Optional sample location 6-19

TABLE 6-9 CONCENTRATIONS OF GAMMA EMITITERS IN QUARTERLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2014 Results in Units of 1OE-3 pCi/m 3?-

1 Sigma OFFSITE SAMPLE LOCATIONS - 1ST QTR 2014 Nuclide R-1*

R-2*

R-3

R-4

R-5

D-2 **

E*

F G**

Be-7 92.3 +/- 10.8 89.4 +/- 11.2 109.0 +/- 13.0 84.7 +/- 11.1 91.1 +/- 11.3 89.7 + 12.0 92.3 + 11.2 98.4 - 12.3 106.0 +/- 12.2 Cs-134

< 1.1

< 2.0

< 1.8

< 1.5

< 1.6

< 2.0

< 1.6

< 1.9

< 1.6 Cs-137

< 1.3

< 1.0

< 0.9

< 1.2

< 1.3

< 1.2

< 1.4 Zr-95

< 3.4

< 3.3

< 3.4

< 2.6

< 2.8

< 3.1

< 3.8

< 3.4 Nb-95

< 2.6

< 3.0

< 2.9

< 2.5

< 2.7

< 1.9

< 0.7

< 2.7

< 3.6 Co-58

< 1.6

< 2.3

< 2.0

< 1.9

< 2.0

< 1.6

< 1.9

< 2.1 Mn-54

< 1.1

< 1.4

< 1.0

< 1.1

< 1.4

< 1.2

< 1.3

< 1.4

< 1.4 Zn-65

< 4.1

< 4.4

< 3.7

< 2.4

< 3.5

< 2.8

< 3.2

< 4.1

< 3.1 Co-60

< 0.5

< 1.2

< 1.7

< 1.9

< 2.0

< 1.2

< 0.5

< 0.5 K-40

< 15.7

< 19.3

< 16.9

< 15.6

< 5.3

< 19.7

< 12.5

< 20.5

< 12.5 OFFSITE SAMPLE LOCATIONS - 2ND QTR 2014 Nuclide R-1*

R-2*

R-3

R-4

R-5

D-2 **

E*

F*

G_**

Be-7 126.0 +/- 13.4 106.0 +/- 12.2 93.7 +/- 11.3 93.8 +/- 11.7 122.0 +/- 13.7 98.8 +/- 11.8 85.6 +/- 11.4 95.5 + 11.5 118.0 +/- 11.8 Cs-134

< 2.5

< 1.9

< 1.6

< 2.4

< 0.9

< 1.8

< 2.0

< 2.2

< 2.1 Cs-137

< 1.1

< 1.0

< 1.5

< 1.1

< 1.5

< 1.2

< 1.3

< 1.6 Zr-95

< 2.9

< 2.6

< 2.2

< 3.4

< 2.6

< 3.5

< 4.2

< 3.3

< 3.5 Nb-95

< 3.5

< 4.3

< 2.7

< 2.8

< 2.2

< 3.0

< 3.8

< 3.3

< 3.4 Co-58

< 1.7

< 1.4

< 1.9

< 2.1

< 2.0

< 2.5

< 1.5

< 1.4

< 2.1 Mn-54

< 1.2

< 1.1

< 1.4

< 0.9

< 1.5

< 1.6

< 0.4

< 1.7 Zn-65

< 3.7

< 4.6

< 3.2

< 3.6

< 0.1

< 4.1

< 3.3

< 3.5

< 4.5 Co-60

< 2.2

< 2.7

< 1.2

< 2.2

< 2.7

< 1.2

< 1.8

< 1.6

< 1.7 K-40

< 15.2

< 16.1

< 4.6

< 4.2

< 26.7

< 15.9

< 12.1

< 16.0

< 15.6

ODCM required sample location

- Optional sample location 6 - 20

TABLE 6-9 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2014 Results in Units of 10E-3 pCi/ n3 +/- 1 Sigma OFFSITE SAMPLE LOCATIONS - 3RD QTR 2014 Nuclide R-1*

R-2*

R-3

R-4

R-5

D-2 **

E*

F*

G_**

Be-7 96.7 +/- 12.0 129.0 +/- 13.1 119.0 +/- 12.2 107.0 + 12.4 103.0 +/- 12.1 89.6 +/- 11.3 112.0 + 11.6 75.6 +/- 10.6 124.0 + 13.0 Cs-134

< 1.1

< 1.3

< 2.7

< 1.4

< 2.5

< 2.0

< 1.6

< 2.6

< 1.3 Cs-137

< 1.0

< 0.8

< 0.7

< 1.3

< 0.9

< 0.3

< 0.7

< 1.4

< 1.5 Zr-95

< 4.5

< 3.1

< 2.2

< 4.5

< 3.6

< 3.7

< 3.9

< 3.1

< 3.2 Nb-95

< 2.3

< 3.0

< 2.9

< 0.7

< 3.9

< 2.6

< 2.4

< 2.3

< 2.1 Co-58

< 2.3

< 2.1

< 2.0

< 2.3

< 2.1

< 1.7

< 1.8

< 2.0

< 1.9 Mn-54

< 1.5

< 1.2

< 1.3

< 1.2

< 1.7

< 1.2

< 1.3

< 1.7

< 0.9 Zn-65

< 3.6

< 3.5

< 2.8

< 3.5

< 3.9

< 2.8

< 3.6

< 2.7

< 3.5 Co-60

< 1.2

< 1.6

< 1.2

< 2.4

< 1.5

< 1.6

< 1.2

< 0.4

< 2.1 K-40

< 11.9

< 15.9

< 15.2

< 16.1

< 12.0

< 27.1

< 22.3

< 19.2

< 27.1 OFFSITE SAMPLE LOCATIONS - 4TH QTR 2014 Nuclide R-1*

R-2*

R-3

R-4

R-5

D-2 **

E_

F*

FG**

Be-7 97.2 + 10.5 58.3 +/- 9.5 79.5 +/- 11.2 85.4 +/- 9.6 52.2 - 10.6 68.7 +/- 10.5 74.2 + 9.9 65.8 + 9.4 60.7 +/- 9.4 Cs-134

< 1.5

< 1.4

< 1.8

< 2.1

< 1.8

< 1.6 Cs-137

< 1.4

< 1.3

< 1.2

< 1.4

< 1.6

< 2.0

< 1.6

< 1.3 Zr-95

< 4.0

< 4.1

< 5.2

< 3.4

< 4.1

< 4.8

< 5.9

< 5.0

< 3.2 Nb-95

< 1.6

< 2.4

< 1.8

< 1.9

< 2.3

< 3.4

< 3.5

< 2.5

< 1.7 Co-58

< 2.2

< 1.9

< 2.3

< 2.4

< 3.2

< 2.1 Mn-54

< 1.5

< 1.8

< 1.2

< 1.5

< 1.6

< 1.8

< 1.4

< 1.5 Zn-65

< 3.2

< 4.3

< 2.7

< 4.2

< 4.0

< 4.3

< 4.9

< 3.7

< 3.4 Co-60

< 1.8

< 1.7

< 1.4

< 1.6

< 1.8

< 2.0

< 2.1

< 1.2

< 1.1 K-40

< 17.1

< 5.7

< 27.4 17.7 + 5.2

< 31.8

< 32.1

< 33.2

< 28.0

< 23.7

ODCM required sample location

Optional sample location 6-21

TABLE 6-9 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2014 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma ONSITE SAMPLE LOCATIONS - 1ST QTR 2014 Nuclide D-1**

G**

H **

I_**

J_**

K**

Be-7 81.2 + 10.5 96.0 + 11.5 85.8 +/- 12.0 70.1 + 10.0 104.0 +/- 12.2 77.0 + 11.1 Cs-134

< 1.6

< 1.3

< 2.1

< 2.0

< 1.6 Cs-137

< 1.0

< 1.1

< 0.8

< 1.2

< 1.3

< 1.1 Zr-95

< 2.6

< 2.7

< 3.5

< 4.1

< 0.8

< 0.9 Nb-95

< 2.1

< 3.3

< 4.6

< 3.7

< 2.5

< 2.2 Co-58

< 2.5

< 2.3

< 1.8

< 2.1

< 2.3

< 2.6 Mn-54

< 2.1

< 0.9

< 2.0

< 1.4

< 1.8

< 1.5 Zn-65

< 2.8

< 3.2

< 4.3

< 3.3

< 3.4

< 5.8 Co-60

< 1.6

< 2.0

< 1.7

< 1.8

< 0.4

< 2.1 K-40

< 24.1

< 12.6

< 5.6

< 15.2

< 15.7

< 5.3 ONSITE SAMPLE LOCATIONS - 2ND QTR 2014 Nuclide D-1**

G**

H**

I_**

J_**

K_**

Be-7 116.0 +/- 12.3 130.0 + 14.1 90.9 + 11.8 91.6 + 11.6 94.6 + 11.5 103.0 + 11.9 Cs-134

< 2.2

< 2.1

< 1.6

< 1.2

< 1.5

< 2.0 Cs-137

< 1.0

< 1.4

< 1.1

< 1.3

< 1.0

< 1.2 Zr-95

< 4.5

< 2.7

< 2.2

< 3.8

< 4.0

< 3.2 Nb-95

< 2.9

< 0.8

< 2.7

< 3.5

< 2.9

< 3.3 Co-58

< 2.4

< 1.8

< 2.3

< 1.4

< 2.3 Mn-54

< 1.0

< 1.4

< 1.3

< 1.2

< 1.0

< 1.3 Zn-65

< 4.0

< 3.6

< 3.2

< 5.1

< 3.6

< 4.1 Co-60

< 1.2

< 0.5

< 1.8

< 1.5

< 2.4

< 1.7 K-40

< 15.1

< 16.3

< 15.9

< 19.7

< 5.4

< 12.4

- Optional sample location 6 - 22

TABLE 6-9 (Continued)

CONCENTRATIONS OF GAMMA EMIITERS IN QUARTERLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2014 Results in Units of 10E-3 pCi/m 3 4-1 Sigma ONSITE SAMPLE LOCATIONS - 3RD QTR 2014 Nuclide D-1**

G**

H_**

I_**

J_**

K_**

Be-7 103.0 +/- 12.1 84.3 +/- 11.5 98.6 +/- 11.1 118.0 +/- 12.4 107.0 +/- 12.0 85.4 -

11.9 Cs-134

< 1.9

< 2.1

< 1.9

< 2.3

< 1.1

< 1.7 Cs-137

< 1.5

< 1.4

< 0.8

< 1.5

< 1.2

< 1.5 Zr-95

< 0.9

< 4.6

< 3.2

< 3.3

< 3.7

< 3.2 Nb-95

< 2.0

< 4.0

< 3.4

< 3.2

< 2.8

< 3.0 Co-58

< 1.6

< 1.9

< 1.6

< 1.7

< 2.2

< 2.3 Mn-54

< 0.9

< 1.7

< 1.9

< 1.3

< 1.4

< 1.5 Zn-65

< 4.5

< 4.2

< 3.5

< 5.3

< 4.1

< 0.1 Co-60

< 2.0

< 0.4

< 1.6

< 1.2

< 2.0

< 1.6 K-40

< 5.2

< 12.0

< 5.2

< 17.9

< 4.6

< 5.3 ONSITE SAMPLE LOCATIONS - 4TH QTR 2014 Nuclide D-1 **

G_**

H[**

I_**

J_**

K_**

Be-7 72.9 +/- 13.7 81.4 +/- 10.0 72.6 +/- 8.0 79.0 +/- 8.8 101.0 +/- 10.3 69.3 - 7.8 Cs-134

< 1.9

< 2.3

< 1.3

< 1.2

< 1.6

< 1.2 Cs-137

< 2.3

< 2.0

< 1.2

< 1.4

< 0.9

< 1.1 Zr-95

< 6.1

< 4.9

< 3.5

< 3.4

< 5.0

< 2.4 Nb-95

< 3.3

< 2.9

< 2.3

< 2.1

< 2.4

< 2.2 Co-58

< 2.9

< 3.4

< 1.5

< 1.8

< 2.1

< 1.6 Mn-54

< 2.3

< 1.7

< 1.2

< 1.4

< 1.5

< 1.1 Zn-65

< 5.1

< 4.5

< 3.1

< 3.2

< 3.3

< 3.6 Co-60

< 1.4

< 2.2

< 1.6

< 1.3

< 1.1

< 1.2 K-40

< 38.3 22.6 +/- 7.2 13.9 +/- 6.0

< 25.4

< 22.7

< 14.5

- Optional sample location 6 - 23

TABLE 6-10 DIRECT RADIATION MEASUREMENT RESULTS - 2014 Results in Units of mrem/std. Month +/- 1 Sigma LOCATION DESCRIPTION FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER DEGREES & DISTANCE")

NUMBER 3

D1 Onsite 11.46

+1-0.69 11.73

+1-0.56 6.99

+/-

0.30 12.87

+1-0.83 690 at 0.2 miles 4

D2 Onsite 4.14

+/-

0.30 4.58

+1-0.23 4.13

+1-0.20 4.54

+1-0.29 1400 at 0.4 miles S

EOnsite 3.92

+/-

0.20 4.51

+/-

0.17 4.20

+/-

0.21 4.59

+1.

0.22 176 at 0.4 miles 6

FOnsite 3.28

+/-

0.20 4.01

+1-0.27 3.74

+/-

0.18 3.94

+1-0.16 2100 at 0.5 miles 7*

G Onsite 3.37

+/-

0.19 3.77

+/-

0.21 3.58

+/-

0.22 3.92

+1-0.16 244' at 0.7 miles 8*

R-5 Offs ite Control 4.20

+1-0.23 4.79

+/-

0.26 4.71

+/*

0.23 4.95

+1-0.26 420 at 16.4 miles 9

D1 Offsite 3.45

+/-

0.27 3.95

+1-0.17 3.82

+1-0.19 4.22

+/-

0.20 800 at 11.4 miles 10 D2 Offsite 3.30

+1-0.17 3.91

+1-0.20 3.73

+1-0.23 3.88

+/-

0.21 11? at 9.0 miles 11 E Offsite 3.41

+1-0.20 3.77

+1-0.19 3.78

+1-0.21 3.93

+/-

0.17 1600 at 7.2 miles 12 F Offsite 3.48

+1-0.22 3.92

+1-0.21 3.84

+1-0.27 4.03

+1-0.16 190( at 7.7 miles 13 G Offsite 3.84

+1-0.22 3.96

+1-0.21 3.75

+1-0.17 4.08

+/-

0.19 2250 at 5.3 miles 14*

DeMass Rd SW Oswego -Control 3.80

+1-0.21 4.09

+1-0.19 3.92

+1-0.20 4.08

+1-0.21 2270 at 12.5 miles i5*

Pole 66 W Boundary -Bible Camp 3.26

+/-

0.21 3.77

+1-0.17 3.53

+/-

0.16 3.88

+1-0.15 239 at 0.9 miles 18*

Energy Info Center - Lamp Post SW 3.92

+/-

0.20 4.33

+/-

0.27 4.21

+1-0.30 4.60

+1-0.19 2660 at 0.5 miles 19 East Boundary-JAF Pole 9 3.88

+/-

0.19 4.21

+1-0.20 4.18

+/-

0.22 4.75

+/-

0.46 810 at 1.3 miles 23*

H Onsite 4.38

+/-

0.24 4.76

+1-0.26 4.51

+./-

0.20 5.19

+/-

0.20 740 at 0.8 miles 24 I Onsite 3.81

+/-

0.23 4.12

+/-

0.18 3.95

+/-

0.16 4.40

+1-0.19 980 at 0.8 miles 25 J Onsite 3.67

+/-

0.20 4.52

+/-

0.56 3.97

+/-

0.20 4.28

+/-

0.22 11(Y at 0.9 miles 26 K Onsite 3.62

+/*

0.17 4.18

+1-0.19 3.94

+1-0.20 4.39

+/-

0.36 132* at 0.5 miles 27 N Fence N of Switchya rd JAF 20.72

+/-

1.25 19.49

+/-

0.99 10.66

+/-

0.48 21.91

+/-

1.21 600 at 0.4 miles 28 N Light Pole N ofScreenhouse JAF 21.44

+/-

2.09 22.94

+/.

2.20 11.98

+/-

0.70 22.90

+1-1.37 680 at 0.5 miles 29 N Fence N of W Side 24.73

+/-

1.77 23.52

+/-

1.74 11.24 4/-

0.56 23.01

+/-

1.09 650 at 0.5 miles 30 N Fence (NW)JAF 11.29

+/-

0.66 11.01

+/-

0.81 6.54

+/-

0.34 12.33

+/-

0.87 57' at 0.4 miles 31 N Fence (NW) NMP-1 6.19

÷/o 0.29 6.85

÷/-

0.51 6.79

+/-

0.31 7.13

+1-0.34 2760 at 0.2 miles 39 N Fence Rad Waste-NMP-1 9.16

+/-

0.46 9.66

+1-0.55 9.03

+1-0.56 10.52

+/-

0.44 292 'at 0.2 miles 47 N Fence (NE) JAF 6.05

+/-

0.30 6.52

+/-

0.37 4.77

+/-

0.32 6.73

+/-

0.42 690 at 0.6 miles 49*

Phoenix NY-Control 3.33 e/-

0.23 3.67

+/-

0.25 3.54

+/-

0.23 3.70

+/-

0.18 1680 at 19.7 miles 51 Liberty & Bronson Sts E ofOSS 3.89

+/-

0.23 4.08

+/-

0.22 3.78 4/-

0.24 4.06

+/-

0.20 2330 at 7.4 miles 52 E 12th & Cayuga Sts Oswego School 3.53

+1-0.19 3.87

+/-

0.26 3.76 4/-

0.18 3.84

+/-

0.17 2270 at 5.8 miles 53 Broadwell & Chestnut Sts Fulton HS 3.71

+/-

0.18 4.26

+/-

0.21 4.07

+/.

0.17 4.22

+1-0.21 1830 at 13.7 miles 54 Liberty St & Co Rt 16 Mexico HS 3.38

+/-

0.17 3.64

+1-0.20 3.66

+/-

0.15 3.79

+/-

0.20 113 at 9.3 miles 55 Gas Substation Co Rt 5-Pulaski 3.28

+1-0.27 3.87

+/-

0.17 3.94 4/-

0.20 3.93

+/-

0.19 75' at 13.0 miles 56*

Rt 104-New Haven Sch (SE Corner) 2.90

+/-

0.18 3.80

+1-0.16 3.81

+/-

0.15 3.60

+1-0.16 1240 at 5.2 miles 58*

Co Rt 1A-Alcan (EofE Entrance Rd) 3.74 4/-

0.20 4.34

+1-0.17 4.15 4/*

0.22 4.12

+/-

0.17 220 0 at3.0 miles 75*

Unit 2 N Fence N of Reactor Bldg 6.64

+1-0.38 7.34

+/-

0.34 6.76

+/-

0.52 7.34

/-

0.40 3540 at 0.1 miles 76*

Unit 2 N Fence N of Change House 5.04

1-0.27 5.58 4/-

0.30 5.16

+/-

0.20 5.74

+/-

0.28 278atO.1 miles 77*

Unit 2 N Fence N of Pipe Bldg 5.75

+/-

0.31 6.09

+/-

0.27 5.57

+1-0.26 6.72

+/-

0.29 37r at 0.2 miles (1) Degrees and distance based on NMP-2 reactor centerline.

TLD required by ODCM 6 -24

TABLE 6-10 (Continued)

DIRECT RADIATION MEASUREMENT RESULTS - 2014 Results in Units of mrem/std. Month +/- 1 Sigma LOCATION DESCRIPTION FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER DEGREES & DISTANCE(')

NUMBER 78*

JAF E of Old Lay Down Area 3.90

+1-0.22 4.30

+1-0.21 4.30

+/-

0.18 4.39

+/-

0.21 860 at 1.0 miles 79*

Co Rt 29 Pole #63 0.2 mi S of Lake Rd 3.37

+/o 0.20 3.91

+1o 0.16 3.74

+/-

0.24 3.91

+/-

0.17 12f at 1.2 miles 80*

Co Rt 29 Pole #54 0.7 mi S of Lake Rd 3.36

+/-

0.17 4.06

+/-

0.17 3.85

+/-

0.19 4.00

+/-

0.18 136` at 1.5 miles 81*

Miner Rd Pole #16 0.5 mi W ofRt 29 3.36

+1-0.23 3.97

+/-

0.21 3.67

+1-0.17 3.87

+I-0.16 160C at 1.7 miles 82*

Miner Rd Pole #1-1/2 11 mi W of Rt 29 3.34 4/-

0.18 4.01

+/-

0.17 3.66

+/-

0.28 3.95

+/-

0.16 1800 at 1.6 miles 83*

Lakeview Rd Tree 0.45 mi N of Miner Rd 3.44

+1-0.22 3.84

+/-

0.18 3.68

+/-

0.18 3.81

+/-

0.19 203' at 1.2 miles 84*

Lakeview Rd N Pole #6117 200ft N of Lake R(

3.55 4/-

0.19 4.09

+/-

0.27 3.87

+1-0.24 4.14

+/-

0.20 225° at 1.1 miles 85*

Unit 1 N Fence N ofW Side of Screen House 9.00

+/-

0.43 9.44 4/-

0.47 8.50

+1-0.49 9.95

+/-

0.56 2900 at 0.2 miles 86*

Unit 2 N Fence N ofW Side of Screen House 7.12

+/-

0.40 7.79

+1-0.49 7.50

+1-0.47 8.12

+1-0.42 3100 at 0.1 miles 87*

Unit 2 N Fence N ofE Side of Screen House 7.13

+/-

0.38 8.04

+/-

0.48 7.37

+/-

0.50 8.15

+/-

0.27 3320 at 0.1 miles 88*

Hickory Grove Rd Pole #2 0.6 mi N ofRt 1 3.40 4/-

0.16 4.00 4/-

0.17 3.73 4/-

0.28 4.17

+/-

0.20 970 at 4.5 miles 89*

Leavitt Rd Pole #16 0.4 mi S of Rt 1 3.63

+/-

0.20 4.35

+1-0.22 4.07

+/-

0.22 4.25

+1-0.20 112 at 4.3 miles 90*

Rt 104 Pole #300 150ft E of Keefe Rd 3.15

+/-

0.20 4.00

+1-0.20 3.73 4/-

0.16 4.03

+1-0.21 139 at 4.2 miles 91*

Rt 51A Pole #59 0.8 mi W of Rt 51 3.22

+/-

0.22 3.83

+/-

0.20 3.62

+1-0.23 3.88

+/-

0.17 151 at 4.9 miles 92*

Maiden Lane Rd Power Pole 0.6 mi S of Rt 1(

3.37

+/-

0.20 4.38

+/-

0.23 4.43

/-

0.45 4.26

+/-

0.18 183' at 4.5 miles 93*

Rt 53 Pole 1-1 12Oft SofRt 104 3.64

+/-

0.19 3.99

+/-

0.16 3.70

+/-

0.18 4.11 4/-

0.32 206 0 at4.4 miles 94*

Rt I Pole #82 25Oft E of Kocher Rd (Co Rt 63) 3.17

+/-

0.17 3.63

+1-0.26 3.48

+/-

0.14 3.69

+1-0.19 224° at 4.4 miles 95*

Alcan W Access Rd Joe Fultz Blvd Pole #21 3.16

+/-

0.18 3.47 0.16 3.19

+/-

0.19 3.55

+/-

0.20 2390 at 3.7 miles 96*

Creamery Rd 0.3 mi S of Middle Rd Pole 1-1/

3.35

+/-

0.20 3.95 4/-

0.18 3.60

+/-

0.23 3.82

+1-0.18 1990 at 3.7 miles 97*

Rt 29 Pole #50 200ft N of Miner Rd 3.26

+/-

0.22 3.93

+1.

0.25 3.82

+1-0.22 3.90

+/-

0.16 146 at 1.8 miles 98 Lake Rd Pole #145 0.15 mi E of Rt 29 3.51

+1-0.18 4.07

+/-

0.21 3.87

+/-

0.20 4.21

+/-

0.22 1030 at 1.2 miles 99 NMP Rd.04 mi N of La ke Rd Env Station R1 3.56

+1-0.18 4.41

+/-

0.21 4.25

+/-

0.26 4.23

+/-

0.17 880 at 1.8 miles 100 Rt 29 & Lake Rd Env Station R2 3.61

+1-0.21 4.23 41-0.23 3.96

+/-

0.17 4.19

+/-

0.24 1040 at 1.1 miles 101 Rt 29 0.7 mi S of Lake Rd Env Station R3 3.12

+/-

0.19 3.54 4/-

0.24 3.65

+/-

0.21 3.79 4/-

0.17 132at 1.5 miles 102 EOF/Env Lab Rt 176 E Driveway Lamp Post 3.42

+/-

0.21 3.74

+/-

0.15 3.63

+/-

0.21 3.68

+/-

0.17 176 at 11.9 miles 103 EIC East Garage Rd Lamp Post 4.05

+1-0.23 4.47

+/-

0.20 4.31

+/-

0.19 4.63

+/-

0.18 2670 at 0.4 miles 104 Parkhurst Rd Pole #23 0.1 mi S of Lake Rd 3.49

+/-

0.21 3.96

+/-

0.17 3.93

+1-0.21 3.87

+/-

0.15 1020 at 1.4 miles 105 La keview Rd Pole #36 0.5 mi S of Lake Rd 3.55

+1-0.20 4.10

+/-

0.17 3.83

+/-

0.17 3.89

+/-

0.21 1980 at 1.4 miles 106 Shoreline Cove W of NMP-1 Tree on W Edge 4.41

+/-

0.22 5.07

+/-

0.27 4.88

+/-

0.24 5.33 4/-

0.26 2740 at 0.3 miles 107 Shoreline Cove W of NMP-1 30ft SSW of#10(

4.24

+1-0.23 4.98

+/-

0.25 4.70

+/-

0.26 5.17

+1-0.24 2720 at 0.3 miles 108 Lake Rd Pole #142 300ft E of Rt 29 5 3.56

+/-

0.21 4.23

+/-

0.21 3.92

+/-

0.19 4.06 4/-

0.18 1040 at 1.1 miles 109 Tree North of Lake Rd 300ft E of Rt 29 N 3.62

+/-

0.18 4.07

+/-

0.22 3.96

+/-

0.17 4.30

+1-0.39 1030 at 1.1 miles 111 State Route 38 Sterling NY-Control 3.12

+/-

0.23 3.72

+/-

0.21 3.47

+/-

0.17 3.60

+1-0.16 166' at 26.4 miles 112 EOF/Env Lab Oswego County Airport 3.62

+/-

0.23 3.69

+1-0.17 3.64

+/-

0.19 0.00

+/-

0.00 176 at 11.9 miles 113 Baldwinsville NY-Control 3.27

+/-

0.18 3.76

+/-

0.21 3.42

+/-

0.17 3.75

+/-

0.20 214' at 21.8 miles (1) Degrees and distance based on NMP-2 reactor centerline.

TLD required by ODCM 6-25

TABLE 6-11 CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2014 Results in Units of pCi/kg (wet) +/- 1 Sigma Sampple Location ** No. 55 ***

Date 1-131 Cs-134 Cs-137 K-40 Ba/La-140 Otherst 04/07/14

< 0.48

< 8.10

< 6.86 1536 +/- 81.0

< 7.07

<LLD 04/21/14

< 0.60

< 3.85

< 5.22 1439 +/- 58.0

< 5.16

<LLD 05/05/14

< 0.44

< 4.28

< 6.07 1413 +/- 79.0

< 10.42

< LLD 05/19/14

< 0.54

< 3.58

< 4.54 1510 +/- 59.0

< 5.35

<LLD 06/09/14

< 0.41

< 3.62

< 4.82 1420 +/- 57.0

< 4.68

< LLD 06/23/14

< 0.40

< 7.34

< 6.44 1560 +/- 72.0

< 5.32

< LLD 07/07/14

< 0.46

< 7.17

< 6.64 1490 +/- 71.0

< 5.32

<LLD 07/28/14

< 0.45

< 4.50

< 6.61 1460 +/- 81.0

< 11.30

<LLD 08/04/14

< 0.64

< 4.49

< 7.93 1360 +/- 89.0

< 13.20

< LLD 08/18/14

< 0.52

< 7.03

< 5.78 1450 +/- 80.0

< 9.95

<LLD 09/08/14

< 0.42

< 7.79

< 6.35 1390 +/- 77.0

< 9.45

< LLD 09/22/14

< 0.52

< 8.58

< 6.48 1430 +/- 81.0

< 8.39

< LLD 10/06/14

< 0.32

< 8.37

< 7.76 1290 +/- 94.5

< 8.65

< LLD 10/20/14

< 0.68

< 3.67

< 4.04 1390 +/- 68.5

< 11.80

< LLD 11/03/14

< 0.86

< 5.01

< 6.65 1220 +/- 70.5

< 9.33

< LLD 11/17/14

< 0.86

< 8.65

< 11.50 1300 +/- 148.5

< 11.80

<LLD 12/01/14

< 0.26

< 5.10

< 6.85 1490 +/- 80.0

< 13.10

< LLD 12/15/14

< 0.36

< 2.07

< 2.42 1410 +/- 29.1

< 2.60

<LLD

Sample location is required by the ODCM

- Sample location is optional Corresponds to sample location noted on Figure 3.3-4 t Plant related radionuclides 6 - 26

TABLE 6-11 (Continued)

CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2014

.Results in Units of pCi/kg (wet) +/- 1 Sigma Sample Location

No. 77 (Control) ***

Date 1-131 Cs-134 Cs-137 K-40 Ba/La-140 Others t 04/07/14

< 0.41

< 5.66

< 5.33 1690 +/- 74.0

< 4.94

<LLD 04/21/14

< 0.45

< 6.32

< 6.54 1604 +/- 74.0

< 8.18

<LLD 05/05/14

< 0.54

< 4.10

< 4.68 1457 +/- 60.0

< 5.76

<LLD 05/19/14

< 0.43

< 3.58

< 5.46 1520 +/- 60.0

< 4.67

< LLD 06/09/14

< 0.52

< 7.58

< 5.78 1460 +/- 80.0

< 8.91

<LLD 06/23/14

< 0.49

< 7.34

< 5.33 1530 +/- 71.0

< 4.95

< LLD 07/07/14

< 0.54

< 3.46

< 5.34 1490 +/- 59.0

< 3.84

< LLD 07/28/14

< 0.56

< 3.85

< 5.34 1560 +/- 61.0

< 5.35

<LLD 08/04/14

< 0.81

< 5.09

< 6.20 1620 +/- 68.0

< 6.50

< LLD 08/18/14

< 0.60

< 3.38

< 5.87 1480 +/- 59.0

< 4.36

<LLD 09/08/14

< 0.51

< 3.85

< 4.31 1530 +/- 59.0

< 4.91

< LLD 09/22/14

< 0.44

< 6.61

< 5.69 1470 +/- 69.0

< 4.06

< LLD 10/06/14

< 0.26

< 7.44

< 8.59 1470 +/- 96.5

< 13.50

< LLD 10/20/14

< 0.62

< 4.87

< 5.34 1210 +/- 63.0

< 13.40

< LLD 11/03/14

< 0.91

< 8.93

< 8.34 1500 +/- 68.0

< 12.10

<LLD 11/17/14

< 0.47

< 9.70

< 8.42 1220 +/- 115.0

< 14.40

<LLD 12/01/14

< 0.31

< 4.29

< 5.48 1290 +/- 60.5

< 12.00

<LLD 12/15/14

< 0.24

< 2.65

< 3.18 1480 +/- 39.3

< 4.00

<LLD

Sample location is required by the ODCM

Sample location is optional Corresponds to sample location noted on Figure 3.3-4

" Plant related radionuclides 6 - 27

TABLE 6-12 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCTS - 2014 Results in Units of pCi/kg (wet)+ I sigma Location***

Date Description Be-7 K-40 1-131 Cs-134 Cs-137 Zn-65 C-14 Others f C2*

09/08/14 HORSERADISH LEAVES 762 + 65.5 3080 +

161

< 19.0

< 11.3

< 14.3

< 45.5 tt

< LLD Flack 09/08/14 SQUASH LEAVES 1280 + 47.2 3690 +/- 105

< 10.9

< 6.4

< 7.5

< 19.1 jt

< LLD 09/08/14 TOMATOES

< 41.7 2390 +/- 78

< 6.9

< 5.4

< 6.6

< 16.7 tt

< LLD 09/08/14 RHUBARB LEAVES 203 + 31.5 3620 +/- 129

< 13.9

< 7.6

< 9.8

< 32.2 tt

< LLD Location**

Date Description Be-7 K-40 1-131 Cs-134 Cs-137 Zn-65 C-14 Others t 133*

09/09/14 RHUBARB LEAVES 252 + 35.0 2200 + 98

< 9.2

< 12.4

< 8.8

< 26.7 tt

< LLD Culeton 09/09/14 KALE LEAVES

< 140.0 5360 +/- 194

< 16.9

< 14.9

< 16.5

< 24.4 tt

<LLD 09/09/14 BEAN LEAVES 1380 a: 56.3 3810 + 126

< 12.8

< 9.5

< 10.0

< 26.9 tt

<LLD 09/09/14 TOMATOES

< 74.5 3320 + 138

< 8.8

< 7.2

< 9.4

< 27.2 tt

<LLD Location**

Date Description Be-7 K-40 1-131 Cs-134 Cs-137 Zn-65 C-14 Others t 144" 09/08/14 HORSERADISH LEAVES 900

+/- 64.9 3620 + 153

< 17.2

< 14.2

< 17.1

< 24.7 tt

<LLD 09/08/14 CABBAGE 985 +/- 57.7 3100 + 141

<11.2

<9.5

<10.8

<34.3 tt

<LLD 09/08/14 SQUASH LEAVES 1170 +/- 72.3 3020 + 153

< 16.1

< 13.5

< 17.0

< 45.6 tt

<LLD 09/08/14 TOMATOES

< 49.5 2080 + 82.0

< 6.8

< 5.8

< 7.1

< 18.7 tt

<LLD Location***

Date Description j

Be-7 K-40 1-131 Cs-134 Cs-137 Zn-65 C-14 Otherst 48**

09/09/14 GRAPE LEAVES 1300 + 83.5 2420

+ 166

< 15.2

< 20.8

< 14.5

< 50.1 tt

<LLD Kronenbitter 09/09/14 BEAN LEAVES 1310 +/- 63.5 2760 + 125

< 11.9

< 10.1

< 11.5

< 19.1 tt

<LLD Location**

Date Description Be-7 K-40 1-131 Cs-134 Cs-137 Zn-65 C-14 Others t 484**

09/08/14 HORSERADISH LEAVES 484

- 37.5 2540 + 104

< 10.8

< 7.9

< 10.8

<25.8 it

<LLD O'Connor 09/08/14 GRAPE LEAVES 1530

= 72.3 3330 + 148

< 15.1

< 17.8

< 15.8

< 36.5 t"

<LLD 09/08/14 RHUBARB LEAVES 117 + 31.4 4490 + 164

< 10.7

< 15.1

< 11.3

< 32.6 tt

<LLD 09/08/14 TOMATOES

< 48.1 2260 +/- 76.4

< 6.4

< 5.7

< 6.6

< 18.0 tt

< LLD

Sample location required by the ODCM

- Sample location is optional

- - Corresponds to sample location noted on Figure 3.3-5 t Plant related radionuclides tt C-I14 analysis not perfoned on this sample 6-28

TABLE 6-13 MILK ANIMAL CENSUS 2014 Number of Town or Location DistanceM 2 )

Milk Animals Area(a)

Designation(')

Degrees(2 )

(Miles)

(Cows)

New Haven 64 1080 7.8 40 14 1250 9.1 50 Mexico 55*

970 8.8 63 72 1000 9.6 30 Granby 77**

190° 16.0 55 (Control)

MILKING ANIMAL TOTALS:

238 (including control locations)

MILKING ANIMAL TOTALS:

183 (excluding control locations)

NOTES:

Milk sample location

- Milk sample control location (1) Reference Figure 3.3-4 (2) Degrees and distance are based on NMP-2 Reactor Building centerline (a) Census performed out to a distance of approximately 10 miles 6-29

TABLE 6-14 RESIDENCE CENSUS 2014 Meteorological Map Sector Location Location0')

Direction(2)

Distance(2)

N NNE NE ENE E

116 Lake Road A

1000 1.3 miles ESE 161 Lake Road B

1040 1.1 miles SE 1216 County Route 29 C

1250 1.4 miles SSE 268 Miner Road D

1580 1.7 miles S

356 Miner Road E

1710 1.6 miles SSW 281 Lakeview Road F

2080 1.2 miles SW 319 Lakeview Road G

2170 1.1 miles WSW Bayshore Drive H

2370 1.4 miles W

WNW NW NNW NOTES:

This meteorological sector is over Lake Ontario. There is no residence within five miles (1) Corresponds to Figure 3.3-6 (2)

Direction and distance are based on NMPNS Reactor Building centerline 6-30

7.0 HISTORICAL DATA TABLES Sample Statistics from Previous Environmental Sampling The mean, minimum value and maximum value were calculated for selected sample mediums and isotopes.

Special Considerations:

1. Sample data listed as 1969 was taken from the NINE MILE POINT, PREOPERATION SURVEY, 1969 and ENVIRONMENTAL MONITORING REPORT FOR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION, NOVEMBER, 1970.

2. Sample results listed as 1974 and 1975 were taken from the respective Annual Radiological Environmental Operating Reports for Nine Mile Point Unit 1 Nuclear Station. Sample results listed as 1986 through the current year were taken from the respective Nine Mile Point Nuclear Power Station Annual Radiological Environmental Operating Reports.

3. Only measured values were used for statistical calculations.

7-1

TABLE 7-1 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT (CONTROL) (a)

Cs-137 (pCi/g (dry))

J Co-60 (pCi/g (dry))

YEAR MIN.

MAX.

MEAN MIN.

MAX.

MEAN 1979(b) 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 0.22 0.07 LLD 0.05 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.03 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.22 0.09 LLD 0.05 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.03 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.22 0.08 LLD 0.05 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.03 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (a) Control location was at an area beyond the influence of the site (westerly direction).

(b) Sampling was initiated in 1979. Sampling was not required prior to 1979.

7-2

TABLE 7-2 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT (INDICATOR) (')

Cs-137 (pCi/g (dry))

I Co-60 (pCi/g (dry))

YEAR MIN.

I MAX.

MEAN MIN.

I MAX.

I MEAN 1985(b) 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 LLD LLD LLD LLD 0.25 0.28 0.11 0.10 0.17 0.08 0.16 0.13 0.13 0.07 0.06 0.06 0.06 0.05 0.04 0.04 0.06 0.06 0.04 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.34 0.28 0.16 0.16 0.49 0.39 0.17 0.18 0.18 0.07 0.09 0.08 0.07 0.05 0.05 0.04 0.09 0.06 0.04 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.30 0.28 0.14 0.13 0.33 0.24 0.16 0.16 0.16 0.07 0.08 0.07 0.07 0.05 0.05 0.04 0.08 0.06 0.04 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (a) Location was offsite at Sunset Beach (closest location with recreational value).

(b) Sampling initiated in 1985 as required by Technical Specifications requirements.

7-3

TABLE 7-3 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH (CONTROL) (a)

Cs-137 (vCi/g (wet))

YEAR MIN.

MAX.

MEAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 1.2 0.13 0.04 0.03 0.03 0.028 0.027 0.041 0.015 0.026 0.021 0.017 0.023 0.020 0.025 0.016 0.019 0.023 0.012 0.014 0.014 0.019 0.013 LLD 0.021 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 1.2 0.13 0.20 0.06 0.11 0.062 0.055 0.057 0.038 0.047 0.032 0.040 0.053 0.033 0.079 0.045 0.024 0.041 0.035 0.020 0.018 0.043 0.013 LLD 0.021 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 1.2 0.13 0.09 0.04 0.06 0.043 0.046 0.049 0.032 0.034 0.025 0.031 0.033 0.029 0.043 0.030 0.022 0.032 0.024 0.016 0.016 0.031 0.013 LLD 0.021 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (a) Control location was at an area beyond the influence of the site (westerly direction).

7-4

TABLE 7-4 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH (INDICATOR) (a)

Cs-137 (pCi/g (wet))

YEAR MIN.

MAX.

MEAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 0.5 0.13 0.03 0.02 0.03 0.03 0.034 0.033 0.033 0.018 0.009 0.024 0.020 0.020 0.024 0.021 0.013 0.021 0.011 0.016 0.014 0.015 0.021 0.016 LLD LLD 0.016 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 3.9 0.79 0.10 0.55 0.10 0.10 0.064 0.056 0.061 0.044 0.051 0.063 0.074 0.043 0.115 0.035 0.034 0.038 0.028 0.019 0.016 0.017 0.021 0.018 LLD LLD 0.016 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 1.4 0.29 0.08 0.10 0.06 0.06 0.048 0.045 0.043 0.030 0.028 0.033 0.034 0.035 0.044 0.027 0.026 0.030 0.020 0.018 0.015 0.016 0.021 0.017 LLD LLD 0.016 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (a) Indicator locations are in the general area of the NMP 1 and J. A. FitzPatrick cooling water discharge structures.

7-5

TABLE 7-5 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER (CONTROL) (")

Cs-137 (pCi/liter)

Co-60 (pCi/liter)

YEAR MIN.

MAX.

I MEAN MIN.

MAX.

MEAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 (b)

(c)

LLD 2.5 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (b)

(c)

LLD 2.5 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (b)

(c)

LLD 2.5 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (b)

(c)

LLD LLD 1.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (b)

(c)

LLD LLD 1.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (b)

(c)

LLD LLD 1.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (a)

Location was the City of Oswego Water Supply for 1976 - 1984, and the Oswego Steam Station inlet canal for 1985 - 2014.

(b)

No gamma analyses performed (not required).

(c)

Data showed instrument background results.

7-6

TABLE 7-6 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER (INDICATOR) (a)

Cs-137 (pCi/liter)

Co-60 (pCi/liter)

YEAR MIN.

I MAX.

I MEAN MIN.

I MAX.

MEAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 (b)

(c)

LLD LLD LLD LLD 0.43 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (b)

(c)

LLD LLD LLD LLD 0.43 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (b)

(c)

LLD LLD LLD LLD 0.43 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (b)

(c)

LLD LLD LLD 1.6 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (b)

(c)

LLD LLD LLD 2.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (b)

(c)

LLD LLD LLD 1.9 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (a)

Location was the J. A. FitzPatrick inlet canal.

(b)

No gamma analyses performed (not required).

(c)

Data showed instrument background results.

7-7

TABLE 7-7 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM (CONTROL) (')

TRITIUM (pCi/liter)

YEAR MIN.

1 MAX.

MEAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 440 300 215 174 211 211 112 230 190 230 250 140 240 180 260 180 190 160 250 230 LLD LLD 190 220 196 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 929 530 490 308 290 328 307 280 220 370 550 270 460 660 320 200 310 230 250 230 LLD LLD 190 510 237 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 652 408 304 259 257 276 165 250 205 278 373 210 320 373 290 190 242 188 250 230 LLD LLD 190 337 212 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (a)

Control location is the City of Oswego drinking water for 1976 - 1984, and the Oswego Steam Station inlet canal for 1985 - 2014.

7-8

TABLE 7-8 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM (INDICATOR) ()

TRITIUM (pCi/liter)

YEAR MIN.

I MAX.

MEAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 365 380 377 176 150 212 194 249 110 250 260 160 430 210 220 250 240 200 180 320 LLD 160 190 180 161 LLD 297 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 889 530 560 276 306 388 311 560 370 1200 (b) 500 410 480 350 290 390 300 280 260 320 LLD 160 190 270 198 LLD 297 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 627 455 476 228 227 285 266 347 280 530 380 322 460 280 250 310 273 242 220 320 LLD 160 190 233 185 LLD 297 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (a) Indicator location is the FitzPatrick inlet canal.

(b) Suspect sample contamination. Recollected samples showed normal levels of tritium.

7-9

TABLE 7-9 HISTORICAL ENVIRONMENTAL SAMPLE DATA GROUNDWATER TRITIUM (CONTROL) (a)

TRITIUM (pCi/liter)

YEAR MIN.

MAX.

MEAN 2005

<854

<854 2006(b)

<447

<825

<636 2007

<442

<445

<444 2008

<427

<439

<431 2009

<411

<418

<415 2010

<172

<410

<341 2011

<408

<424

<415 2012

<363

<499

<420 2013

<365

<381

<374 2014

<404

<493

<433 (a)

Control well locations (2) are upland wells located south of protected area.

(b)

Required LLD changed to 500 pCi/l from 1000 pCi/l 7-10

TABLE 7-10 HISTORICAL ENVIRONMENTAL SAMPLE DATA GROUNDWATER MONITORING WELLS TRITIUM (INDICATOR) (a TRITIUM (DCi/liter)

YEAR MIN.

MAX.

MEAN 2005

<854

<871

<863 2 0 0 6(b)

<462

<933

<823 2007

<440

<461

<445 2008

<427

<439

<433 2009

<406

<424

<413 2010

<287 611

<384 2011

<407

<428

<414 2012

<314

<499

<395 2013

<365 820'c)

<382 2014

<376

<493

<436 (a) Indicator locations are down gradient wells located in the owner control area.

(b) Required LLD changed to 500 pCi/l from 1000 pCi/I (c) Re-sample tritium concentration = <459 pCi/1 TABLE 7-10a HISTORICAL ENVIRONMENTAL SAMPLE DATA NMP2 STORM DRAIN TRITIUM (INDICATOR) (a)

TRITIUM (pCi/liter)

YEAR MIN.

MAX.

MEAN 2005

<854

<871

<863 2006(')

<667

<933

<850 2007

<440

<461

<447 2008

<415

<446

<432 2009

<406

<424

<413 2010

<289 446

<408 2011

<407

<428

<414 2012

<298 908

<417 2013

<366 403(c)

<385 2014

<368

<488

<401 (a) NMP2 depression cone system.

(b) Required LLD changed to 500 pCi/l from 1000 pCi/l (c) Re-sample tritium concentration = <393 pCi/l 7-11

TABLE 7-11 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA (CONTROL) (a)

GROSS BETA (pCi/m3)

YEAR MIN.

I MAX.

MEAN 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 0.001 0.01 0.010 0.009 0.016 0.011 0.007 0.013 0.013 0.008 0.009 0.008 0.007 0.003 0.006 0.006 0.007 0.008 0.006 0.008 0.006 0.004 0.010 0.006 0.006 0.008 0.004 0.008 0.008 0.007 0.008 0.007 0.006 0.004 0.008 0.005 0.006 0.006 0.484 0.66 0.703 0.291 0.549 0.078 0.085 0.051 0.043 0.272 0.037 0.039 0.039 0.027 0.028 0.020 0.022 0.025 0.023 0.023 0.025 0.034 0.032 0.027 0.034 0.027 0.032 0.032 0.034 0.033 0.028 0.031 0.032 0.026 0.034 0.025 0.031 0.030 0.125 0.16 0.077 0.056 0.165 0.033 0.024 0.026 0.024 0.039 0.021 0.018 0.017 0.013 0.014 0.012 0.013 0.015 0.014 0.014 0.013 0.014 0.017 0.015 0.016 0.016 0.015 0.016 0.019 0.016 0.016 0.015 0.016 0.014 0.018 0.016 0.016 0.016 I

J. _________________

(a) Locations used for 1977 - 1984 were C off-site, D1 off-site, D2 off-site, E off-site, F off-site, and G off-site. Control location R-5 off-site was used for 1985 - 2014 (formerly C offsite location).

7-12

TABLE 7-12 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA (INDICATOR) (a)

GROSS BETA (pCi/m 3)

YEAR MIN.

MAX.

I MEAN 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 0.002 0.01 0.001 0.002 0.004 0.001 0.002 0.002 0.010 0.007 0.009 0.007 0.007 0.005 0.007 0.005 0.005 0.006 0.004 0.006 0.001 0.002 0.009 0.005 0.004 0.006 0.005 0.003 0.007 0.005 0.007 0.004 0.006 0.005 0.007 0.004 0.006 0.005 0.326 0.34 0.271 0.207 0.528 0.113 0.062 0.058 0.044 0.289 0.040 0.040 0.041 0.023 0.033 0.024 0.025 0.025 0.031 0.025 0.018 0.040 0.039 0.033 0.037 0.026 0.035 0.037 0.040 0.035 0.028 0.030 0.032 0.030 0.034 0.031 0.032 0.030 0.106 0.11 0.058 0.044 0.151 0.031 0.023 0.025 0.023 0.039 0.021 0.018 0.017 0.014 0.015 0.013 0.014 0.015 0.014 0.013 0.010 0.015 0.017 0.015 0.016 0.016 0.015 0.016 0.018 0.015 0.016 0.016 0.016 0.016 0.018 0.016 0.016 0.016 (a) Locations used for 1977 - 1984 were D1 onsite, D2 onsite, E onsite, F onsite, G onsite, H onsite, I onsite, J onsite, and K onsite as applicable. 1985 - 2013 locations were R-1 offsite, R-2 offsite, R-3 offsite, and R-4 offsite.

7-13

TABLE 7-13 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES (CONTROL) 0)

Cs-137 (pCi/m3)

Co-60 (pCi/m 3)

YEAR MIN.

MAX.

MEAN MIN.

MAX.

MEAN 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 0.0002 0.0008 0.0008 0.0015 0.0003 0.0002 0.0002 LLD LLD 0.0075 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0112 0.0042 0.0047 0.0018 0.0042 0.0009 0.0002 LLD LLD 0.0311 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0034 0.0018 0.0016 0.0016 0.0017 0.0004 0.0002 LLD LLD 0.0193 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0034 0.0003 0.0005 LLD 0.0003 0.0004 0.0007 0.0004 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0347 0.0056 0.0014 LLD 0.0012 0.0007 0.0007 0.0012 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0172 0.0020 0.0009 LLD 0.0008 0.0006 0.0007 0.0008 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (a) Locations included composites of C, DI, E, F, and G offsite air monitoring locations for 1977 - 1984.

Sample location included only R-5 air monitoring location for 1985 - 2013.

7-14

TABLE 7-14 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES (INDICATOR) (a)

Cs-137 (pCi/m3)

Co-60 (pCi/m3)

YEAR MIN.

MAX.

MEAN MIN.

MAX.

MEAN 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 0.0001 0.0003 0.0003 0.0005 0.0002 0.0001 0.0002 LLD LLD 0.0069 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0105 0.0026 0.0020 0.0019 0.0045 0.0006 0.0003 LLD LLD 0.0364 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0043 0.0016 0.0010 0.0011 0.0014 0.0004 0.0002 LLD LLD 0.0183 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0003 0.0003 0.0003 0.0016 0.0002 0.0003 0.0003 0.0007 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0048 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0711 0.0153 0.0007 0.0016 0.0017 0.0010 0.0017 0.0017 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0048 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0179 0.0023 0.0005 0.0016 0.0006 0.0005 0.0007 0.0012 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0048 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (a)

Locations included composites of D1, D2, E, F, G, H, I, J, and K onsite air monitoring locations for 1977 - 1984. Locations included R-1 through R-4 air monitoring locations for 1985 - 2013.

7-15

TABLE 7-15 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE (CONTROL) (a)

IODINE-131 (pCi/m3)

YEAR MIN.

I MAX.

I MEAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 0.01 0.02 0.03 LLD LLD LLD 0.039 LLD LLD LLD 0.041 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.034(b)

LLD LLD LLD 5.88 0.82 0.04 LLD LLD LLD 0.039 LLD LLD LLD 0.332 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0 9 3(b)

LLD LLD LLD 0.60 0.32 0.03 LLD LLD LLD 0.039 LLD LLD LLD 0.151 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.055b)

LLD LLD LLD (a)

Locations Dl off-site, D2 off-site, E off-site, F off-site, and G off-site used for 1976 - 1984.

Location R-5 off-site used for 1985 - 2013.

(b) 1-131 concentration attributed to fallout from the Fukushima Daiichi Nuclear Station accident.

7-16

TABLE 7-16 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE (INDICATOR) (a)

IODINE-131 (pCi/m3)

YEAR MIN.

MAX.

MEAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 0.01 0.02 0.02 LLD 0.013 0.016 0.002 0.022 LLD LLD 0.023 0.011 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.021(b)

LLD LLD LLD 2.09 0.73 0.07 LLD 0.013 0.042 0.042 0.035 LLD LLD 0.360 0.018 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.11 )

LLD LLD LLD 0.33 0.31 0.04 LLD 0.013 0.029 0.016 0.028 LLD LLD 0.119 0.014 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.055b LLD LLD LLD (a)

Locations used for 1976 - 1984 were DI on-site, D2 on-site, E on-site, F on-site, G on-site, H on-site, I on-site, J on-site, and K on-site, as applicable. Locations used for 1985 - 2013 were R1 off-site, R-2 off-site, R-3 off-site, and R-4 off-site.

(b) 1-131 concentration attributed to fallout from the Fukushima Daiichi Nuclear Station accident.

7-17

TABLE 7-17 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (CONTROL) (a)

DOSE (mrem per standard month)

YEAR MIN.

MAX.

MEAN 1969 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 (b) 6.0 2.0 2.2 2.2 2.7 4.8 3.2 4.0 3.3 3.3 3.8 3.5 3.8 4.9 4.7 4.5 (4.4)*

5.3 (5.5)*

4.6 (4.6)*

4.4 (4.8)*

2.9 (2.9)*

3.7 (3.7)*

3.8 (3.8)*

2.6 (2.6)*

3.4 (3.4)*

3.1 (3.1)*

3.4 (3.4)*

3.7 (3.9)*

3.7 (3.7)*

3.6 (3.7)*

3.7 (3.7)*

3.6 (3.9)*

3.4 (3.4)*

3.3 (3.3)*

3.3 (3.4)*

3.3 (3.3)*

3.2 (3.2)*

3.3(3.3)*

3.2(3.2)*

2.7(2.7)*

2.6(2.6)*

3.6(3.6)*

3.2(3.2)*

3.1(3.3)*

(b) 7.3 6.7 6.2 6.9 8.9 6.0 7.2 8.0 4.7 5.7 5.8 5.9 6.1 7.2 8.2 7.6 (6.8)*

7.5 (7.2)*

6.6 (5.8)*

6.8 (6.8)*

6.4 (5.6)*

6.0 (5.9)*

5.4 (5.3)*

5.0 (4.7)*

5.6 (5.2)*

5.0 (4.6)*

5.7 (4.9)*

5.6 (5.6)*

6.2 (5.2)*

5.6 (4.8)*

7.1 (4.7)*

7.3 (5.5)*

5.4 (5.0)*

5.5 (5.2)*

5.5 (4.8)*

5.9 (5.9)*

5.1 (4.5)*

5.3 (4.4)*

5.8 (5.3)*

5.1(4.8)*

4.8(4.2)*

4.6(4.1)*

5.5(4.7)*

5.0(4.3)*

4.9(4.4)*

5.0(4.1 )*

(b) 6.7 4.3 4.4 4.7 5.6 5.5 5.4 5.3 4.3 4.7 4.9 4.8 5.1 5.8 6.2 5.6 (5.4)*

6.3 (6.3)*

5.4 (5.2)*

5.6 (5.4)*

4.7 (4.6)*

4.8 (4.6)*

4.5 (4.3)*

4.1 (3.9)*

4.4 (4.3)*

4.1 (3.9)*

4.4 (4.2)*

4.3 (4.2)*

4.7 (4.6)*

4.4 (4.2)*

4.6 (4.4)*

4.7 (4.3)*

4.4 (4.4)*

4.3 (4.1)*

4.2 (4.2)*

4.3 (4.5)*

4.1 (4.0)*

4.4 (4.3)*

4.1(4.0)*

3.9(3.7)*

3.9(3.6)*

4.0(3.8)*

4.0(3.9)*

3.9(3.9)*

3.8(3.8)*

(a)

TLD #8, 14,49, 111 and 113 where applicable.

(b)

Data not available.

(*) TLD result based on the ODCM required locations (TLD #14 and 49).

7-18

TABLE 7-18 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (SITE BOUNDARY) (")

DOSE (mrem per standard month)

YEAR MIN.

MAX.

MEAN 1985()

1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 4.1 4.4 4.4 3.4 2.8 3.6 3.2 3.2 3.3 2.8 3.5 3.2 3.5 3.7 3.3 3.6 3.6 3.5 3.2 3.3 3.4 3.5 3.2 3.2 3.1 3.3 3.1 3.6 3.5 3.3 12.6 18.7 14.3 17.9 15.4 14.8 16.7 10.4 11.6 12.4 9.6 9.1 10.2 9.4 12.3 10.0 10.3 9.4 8.9 10.8 9.2 9.2 9.0 8.8 11.7 12.1 11.6 10.6 10.4 9.9 6.2 7.0 6.1 6.4 5.9 5.8 5.7 4.8 5.3 5.2 5.4 5.2 5.9 5.4 5.8 5.5 5.7 5.4 5.4 5.6 5.5 5.4 5.6 5.2 5.4 5.4 5.5 5.5 5.4 5.2 (a) TLD locations initiated in 1985 as required by the new Technical Specifications. Includes TLD numbers 7, 18, 23, 75, 76, 77, 78, 79, 80, 81, 82, 83, 84, 85, 86, and 87.

(b) Not required prior to 1985.

7-19

TABLE 7-19 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (OFF-SITE SECTORS) (a)

DOSE (mrem per standard month)

YEAR MIN.

MAX.

I MEAN 1985b) 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 4.0 4.6 4.3 3.8 2.5 3.6 3.6 2.9 3.4 3.0 3.2 3.2 3.5 3.5 3.6 3.4 3.6 3.1 3.4 3.2 3.2 3.3 3.1 3.2 3.3 3.0 3.0 3.5 3.2 3.2 7.1 8.6 6.0 7.0 6.8 6.3 5.6 5.0 6.3 5.1 5.2 5.3 5.8 5.0 5.6 6.6 5.4 5.3 4.8 6.7 4.7 4.4 5.1 4.5 4.5 4.4 5.2 4.6 4.5 4.4 5.0 6.0 5.2 5.3 4.9 4.7 4.5 4.1 4.5 4.0 4.2 4.2 4.5 4.2 4.4 4.5 4.4 4.2 4.1 4.4 4.0 4.0 4.2 3.8 3.9 3.9 4.0 4.0 3.8 3.8 (a)

TLD locations initiated in 1985 as required by the new Technical Specifications. Includes TLD numbers 88, 89, 90, 91, 92, 93, 94, and 95.

(b)

Not required prior to 1985.

7 - 20

TABLE 7-20 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (SPECIAL INTEREST) (.) (b)

DOSE (mrem per standard month)

YEAR MIN.

MAX.

I MEAN 1985(c) 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 3.9 4.8 3.5 3.9 2.1 3.2 2.9 3.0 3.2 2.9 3.4 3.2 3.5 3.7 3.6 3.6 3.8 3.5 3.4 3.0 3.4 3.5 3.0 3.1 3.1 3.2 2.9 3.4 3.2 2.9 6.8 8.2 6.0 6.6 7.0 6.3 5.6 4.8 5.8 4.8 4.9 5.3 5.4 4.9 5.5 6.3 5.0 4.7 5.0 5.9 4.7 4.6 5.1 4.6 4.5 4.7 4.9 4.7 4.5 4.3 5.3 6.1 5.1 5.3 4.8 4.7 4.4 4.1 4.5 4.0 4.3 4.2 4.5 4.3 4.4 4.5 4.3 4.1 4.2 4.2 3.9 4.0 4.2 3.9 3.8 3.8 4.0 4.0 3.8 3.8 (a)

TLD locations initiated in 1985 as required by the new Technical Specifications. TLD's included are numbers 15, 56, 58, 96, 97 and 98.

(b)

TLD locations include critical residences and populated areas near the site.

(c)

Not required prior to 1985.

7-21

TABLE 7-21 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (ON-SITE INDICATOR) (a)

DOSE (mrem per standard month)

YEAR MIN.

MAX.

MEAN 1969 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 (b) 4.7 1.5 2.3 3.0 3.1 4.6 3.7 3.0 3.0 2.7 3.9 4.1 3.9 5.0 4.6 4.7 4.7 4.0 4.4 2.7 3.6 3.2 3.2 3.1 2.8 3.5 3.1 3.5 3.6 3.3 3.7 3.8 3.5 3.2 3.3 3.4 3.5 3.2 3.2 3.1 3.3 3.1 3.5 3.3 3.3 (b) 9.0 7.7 8.2 24.4 10.6 16.0 18.8 15.3 9.0 8.3 12.0 11.8 13.0 16.5 13.2 15.9 16.1 11.4 11.9 14.5 12.9 11.6 5.6 13.6 14.3 28.6 32.6 28.8 28.8 28.4 16.5 14.5 13.6 12.9 13.2 14.1 14.4 14.8 13.8 13.6 13.3 13.0 11.8 12.2 12.9 (b) 6.0 4.7 4.9 6.6 5.7 7.3 6.9 5.7 4.3 4.3 5.3 5.8 6.3 6.9 7.0 6.3 7.0 5.8 6.0 6.0 5.5 5.1 4.3 5.2 5.1 6.2 6.4 7.7 6.2 6.6 5.6 5.6 5.3 5.3 5.4 5.4 5.3 5.6 5.2 4.9 4.8 5.1 4.9 5.0 4.9 (a)

Includes TLD numbers 3, 4, 5, 6, and 7 (1970 - 1973). Includes TLD numbers 3, 4, 5, 6, 7, 23, 24, 25, and 26 (1974 - 2011). Locations are existing or previous on-site environmental air monitoring locations.

(b)

No data available.

7 - 22

TABLE 7-22 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (OFF-SITE INDICATOR) (a)

DOSE (mrem per standard month)

YEAR MIN.

I VMAX.

MEAN 1969 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 (b) 5.0 1.1 1.8 2.2 2.4 4.5 3.4 3.7 2.7 3.0 3.1 3.6 4.0 4.6 4.6 4.6 5.0 4.4 4.2 2.8 3.8 3.4 3.1 3.2 3.0 3.9 3.3 3.7 3.9 3.8 3.8 3.7 3.6 3.1 3.2 3.6 3.9 3.4 3.3 3.3 3.5 3.2 3.6 3.5 3.3 (b) 8.0 7.7 6.6 6.9 8.9 7.1 7.2 8.0 4.7 5.7 5.8 5.9 6.2 7.2 8.2 7.7 7.6 6.6 6.6 6.4 6.0 5.4 5.2 5.6 5.0 5.7 5.5 6.2 5.6 7.1 7.3 5.9 5.5 5.5 6.5 5.1 5.3 5.8 5.1 4.8 4.6 5.5 5.0 4.9 5.0 (b) 6.7 4.5 4.4 4.1 5.3 5.5 5.2 5.3 3.7 4.0 4.6 4.7 5.2 5.6 6.1 5.5 6.1 5.2 5.4 4.6 4.8 4.3 4.1 4.3 4.1 4.4 4.1 4.7 4.4 4.6 4.6 4.5 4.4 4.4 4.5 4.2 4.2 4.5 4.1 3.9 3.8 4.1 4.1 4.0 3.9 (a)

Includes TLD numbers 8, 9, 10, 11, 12, and 13 (off-site environmental air monitoring locations).

(b)

No data available.

7-23

TABLE 7-23 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK (CONTROL) (a)

Cs-137 (pCi/liter) 1 1-131 (pCi/liter)

YEAR MIN.

MAX.

MEAN MIN.

I MAX.

MEAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 (b)

(b) 2.4 LLD 3.6 3.9 LLD LLD LLD LLD 5.3 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (b)

(b) 7.8 LLD 5.6 3.9 LLD LLD LLD LLD 12.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (b)

(b) 5.8 LLD 4.5 3.9 LLD LLD LLD LLD 8.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (b)

(b)

LLD LLD 1.4 LLD LLD LLD LLD LLD 0.8 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (b)

(b)

LLD LLD 1.4 LLD LLD LLD LLD LLD 29.0 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (b)

(b)

LLD LLD 1.4 LLD LLD LLD LLD LLD 13.6 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (a)

Location used was an available milk sample location in a least prevalent wind direction greater than ten miles from the site.

(b)

No data available (samples not required).

7 - 24

TABLE 7-24 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK (INDICATOR) (a)

Cs-137 (pCi/liter) 1-131 (pCi/liter)

YEAR MIN.

MAX.

MEAN MIN.

I MAX.

MEAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 4.0 11.0 3.4 3.2 3.2 3.5 3.5 3.3 LLD LLD 6.1 5.5 10.0 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 15.0 22.0 33.0 53.0 21.0 29.0 14.0 10.9 LLD LLD 11.1 8.1 10.0 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 9.3 17.1 9.9 9.4 8.1 8.6 5.7 7.2 LLD LLD 8.6 6.8 10.0 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.02 0.01 0.19 LLD 0.3 LLD LLD LLD LLD LLD 0.3 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.50 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 45.00 49.00 0.19 LLD 8.8 LLD LLD LLD LLD LLD 30.0 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.50 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 3.20 6.88 0.19 LLD 3.8 LLD LLD LLD LLD LLD 5.2 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.50 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (a) Locations sampled were available downwind locations within ten miles with high radionuclide deposition potential.

7-25

TABLE 7-25 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS (CONTROL) (')

Cs-137 (pCi/g (wet))

YEAR_()_

MIN.

I MAX.

MEAN 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 0.02 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.007 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.02 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.007 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.02 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.007 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (a)

Location was an available food product sample location in a least prevalent wind direction greater than ten miles from the site.

(b)

Data comprised of broadleaf and non-broadleaf vegetation (1980 - 1984, 2007 - 2009, 2011,2012 &

2014).

(c)

Data comprised of broadleaf vegetation only (1985 - 2006, 2010 & 2013).

7-26

TABLE 7-26 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS (INDICATOR) (a)

Cs-137 (pCi/g (wet))

YEARo,)(c)

MIN.

MAX.

J MEAN 1976-1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 LLD 0.004 0.004 LLD LLD LLD LLD 0.047 LLD LLD 0.008 0.009 LLD 0.040 LLD LLD 0.004 0.010 LLD 0.012 LLD 0.008 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.004 0.060 LLD LLD LLD LLD 0.047 LLD LLD 0.008 0.009 LLD 0.040 LLD LLD 0.011 0.012 LLD 0.012 LLD 0.008 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.004 0.036 LLD LLD LLD LLD 0.047 LLD LLD 0.008 0.009 LLD 0.040 LLD LLD 0.008 0.011 LLD 0.012 LLD 0.008 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (a)

Indicator locations were available downwind locations within ten miles of the site and with high radionuclide deposition potential.

(b)

Data comprised of broadleaf and non-broadleaf vegetation (1976 - 1984, 2007 - 2009, 2011, 2012

&2014).

(c)

Data comprised of broadleaf vegetation only (1985 - 2006, 2010 & 2013).

7-27

8.0 QUALITY ASSURANCE / QUALITY CONTROL PROGRAM There was a change of laboratories that analyzed the samples taken for the REMP, the quality assurance results from both programs are detailed below.

The JAFNPP Environmental Laboratory ceased operation on October 1, 2014. Samples subsequent to the October 1, 2014 date were shipped to and analyzed by Teledyne Brown Engineering. Teledyne Brown Engineering maintains and operates its own Quality Assurance Program, including an Interlaboratory Comparison Program.

8.1 PROGRAM DESCRIPTION The Offsite Dose Calculation Manual (ODCM), for Nine Mile Point Unit 1 (NMPI) and Nine Mile Point Unit 2 (NMP2), Part II, Section 4.0 requires that the licensee participate in an Interlaboratory Comparison Program. The Interlaboratory Comparison Program shall include sample media for which samples are routinely collected and for which comparison samples are commercially available. Participation in an Interlaboratory Comparison Program ensures that independent checks on the precision and accuracy of the measurement of radioactive material in the environmental samples are performed as part of the Quality Assurance Program for environmental monitoring.

To fulfill the requirement for an Interlaboratory Comparison Program, the James A. FitzPatrick Nuclear Power Plant (JAFNPP) Environmental Laboratory and Teledyne Brown Engineering has engaged the services of Eckert & Ziegler Analytics, Incorporated in Atlanta, Georgia.

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

These samples are prepared and analyzed by the JAFNPP Environmental Laboratory using standard laboratory procedures. Eckert

& Ziegler Analytics issues a statistical summary report of the results. The JAFNPP Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratory's performance.

The JAFNPP Environmental Laboratory and TBE 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.

8-1

8.2 JAFNPP's PROGRAM SCHEDULE SAMPLE PROVIDER SAMPLE LABORATORY ECKERT & ZIEGLER MEDIA ANALYSIS ANALYTICS Water 1-131 1

Water Mixed Gamma 1

Air Gross Beta 1

Air 1-131 2

Milk 1-131 1

Milk Mixed Gamma I

Vegetation Mixed Gamma 1

TOTAL SAMPLE INVENTORY 8

8.3 JAFNPP's 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.

8.3.1 SAMPLE RESULTS EVALUATION Samples provided by Eckert & Ziegler 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).

8-2

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

The value for the error resolution is calculated.

The error resolution =

Reference Result Reference Results Error (1 sigma)

Using the appropriate row under the Error Resolution column in Table 8-1 below, a corresponding Ratio of Agreement interval is given.

The value for the ratio is then calculated.

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

TABLE 8-1 ERROR RESOLUTION RATIO OF AGREEMENT

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

>200 0.85 to 1.18 This acceptance test is generally referred to as the "NRC" method. The acceptance criteria are contained in Procedure CY-AA-130-201-F-08, NRC Radiochemical Acceptance Criteria for Split Samples. 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.

8-3

8.4 PROGRAM RESULTS

SUMMARY

The Interlaboratory Comparison Program numerical results are provided on Table 8-3.

8.4.1 ECKERT & ZIEGLER ANALYTICS QA SAMPLES RESULTS Eleven QA blind spike samples were analyzed as part of Eckert & Ziegler Analytics 2014 Interlaboratory Comparison Program. The following sample media were evaluated as part of the comparison program.

Air Charcoal Cartridge: 1-131

Air Particulate Filter: Gross Beta Water: 1-131, Mixed Gamma Emitters Milk: 1-131, Mixed Gamma Emitters Vegetation: Mixed Gamma Emitters The JAFNPP Environmental Laboratory performed 33 individual analyses on the 8 QA samples. Of the 33 analyses performed, 33 were in agreement using the NRC acceptance criteria for a 100 % agreement ratio.

8-4

TABLE 8-2 INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filter REFERENCE SAMPLE JAF ELAB RESULTS LAB*

RATIO DATE ID NO.

MEDIUM ANALYSIS pCi+/-1 sigma pCi I sigma (1) 06/12/2014 E10907 Filter 92

+

1.0 GROSS 92.5

+/-

1.0 89.6 1.50 1.02 A

BETA 90.7

+/-

1.0 Mean=

91.7

+/-

0.6 (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable INTERLABORATORY INTERCOMPARISON PROGRAM 1-131 Gamma Analysis of Air Charcoal DATE SAMPLE JAF ELAB RESULTS REFERENCE LAB*

RATIO (1)

ID NO.

MEDIUM ANALYSIS pCi '1 sigma pCi 1 sigma RATIO (1) 3/20/2014 E10813 Air 72.0

+/-

3.0 1-131 715 2.9 74.9

+/-

1.25 0.97 A

72.8

+

3.1 Mean=

72.4

+ 1.5 9/11/2014 E10985 Air 91.4

+/-

3.83 1-131 91.2 3.78 90.2

=4 1.51 1.01 A

89.9

4-3.86 Mean=

90.8 4

2.2 (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable 8-5

TABLE 8-2 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water DATE SAMPLE M

I I

JAF ELAB RESULTS REFERENCE LAB*

R (1)

ID NO.

MEDIUM ANALYSIS pCi/liter+/-1 sigma pCi/liter +/-1 sigma RATI_(1 6/12/2014 1 E10906 Water Ce-141 143 152 148 Mean=

148 6.62 6.80 6.58 3.9 143

+/-

2.4 1.03 A

326. +/-

30.2 Cr-51 252

+/-

30.2 294

+/-

4.91 0.97 A

279

+

27.7 Mean=

286

+/-

17.0 175

+/-

9.08 Cs-134 179

+/-

9 188

+/-

3.14 0.95 A

181

+

8.72 Mean =

178

+/-

5.3 138

+

4.61 Cs-137 129

+/-

4.82 139

+/-

2.32 0.99 A

144

+/-

4.23 Mean=

137

+/-

2.6 139

+/-

4.63 Co-58 133

+/-

4.96 130

+/-

2.17 1.03 A

129

+/-

4.4 Mean =

134

+/-

2.7 186

+/-

5.14 Mn-54 186

+/-

5.55 180

+/-

3.01 1.03 A

184

+/-

4.88 Mean=

185

+

3.0 127

+/-

5.39 Fe-59 124 6.02 119

+

1.98 1.03 A

119

+/-

5.18 Mean =

123

+/-

3.2 297

+/-

10.1 Zn-65 297

+/-

11.3 293

+

4.89 1.03 A

311

+/-

9.61 Mean =

302

+/-

6.0 270

+/-

4.54 Co-60 261

+/-

4.92 260

+

4.34 1.02 A

263

+/-

4.26 Mean =

265

+/-

2.7 1-131**

102 97.6 95.5 Mean =

98.4 4-

+

+/-

2.96 3.39 3.30 1.9 98.3

+/-

1.64 1.00 A

(1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable 8-6

TABLE 8-2 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk DATE SAMPLE I

A rJAF ELAB RESULTS REFERENCE LAB*

RATIO (1)

I ID NO.

MEDIUM ANALYSIS pCi/liter 41 sigma I

pCi/liter +/- 1 sigma RAIO (1) 3/20/2014 E10812 MILK Ce-141 127 119 94.5 110 Mean=

113 4-4-

4-7.7 9.9 10.6 9.7 4.8 119 1.98 0.95 AI 450 41.4 445 52.6 Cr-51 423 60.4 491

+/-

8.20 0.92 A

484 52.9 Mean=

451 26.1 176 11.6 186 16.8 Cs-134 183 4

19.0 210

+/-

3.51 0.86 A

179

+

16.4 Mean=

181 8.1 236 7.1 249 9.7 Cs-137 226 10.8 253 4.22 0.94 A

243 9.8 Mean =

239 4.7 262

+/-

7.5 266

+/-

10.4 Co-58 259 4

11.0 268 4.47 0.99 A

274

+

10.4 Mean=

265 5.0 312

+/-

7.8 323

+/-

10.9 Mn-54 300

+/-

12.0 297 4

4.96 1.04 A

304

+/-

10.8 Mean=

310 1

5.2 Fe-59 226 216 208 213 Mean=

216

+/-

8.7 11.5 13.4 11.9 5.7 219

+/-

3.65 0.99 A

(Continued) 8-7

TABLE 8-2 (Continued) 1NTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk DATE SAMPLE MEDIUM ANALYSIS JAF ELAB RESULTS REFERENCE LAB*

RATIO (I)

ID NO.

pCi/liter +/- 1 sigma pCi/liter +1 sigma 3/20/2014 E10812 MILK 341 13.6 (Continued) 320 19.2 ZN-65 337 22.0 323

+/- 5.93 1.00 A

298 18.5 Mean=

324 12.4 322 6.1 331

+

8.7 Co-60 326

+/-

9.9 337

+

5.63 0.96 A

321

+/-

8.6 Mean=

325 4.2 87.1

+

8.4 93.6

+

10.0 1-131 102

+

11.3 98.5

+/-

1.65 0.94 A

87.7

+

10.0 Mean =

93

+

5.0 95.0

+

2.8 1-131**

93.1 3.4 98.5

+/-

1.65 0.97 A

97.1

+

3.6 Mean =

95.1

+ 1.9 (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable 8-8

TABLE 8-2 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation DATE SAMPLE M

J JAF ELAB RESULTS REFERENCE LAB*

RATIO (1)

DATE_

ID NO.

MEDIUM ANALYSIS pCi/g -+ sigma pCi/g +I sigma RATIO (1) 9/11/2014 E10986 VEG Ce-141 0.186 0.202 0.213 Mean =

0.200 0.010 0.010 0.010 0.006 0.192

+/-

0.003 1.04 A

0.444

+/-

0.051 0.459

+/-

0.046 Cr-51 0.51

+

0.050 0.439

+/-

0.007 1.08 A

0.516

+/-

0.050 Mean =

0.473

+/-

0.027 0.242

+/-

0.020 0.255

+/-

0.018 Cs-134 0.240

+/-

0.016 0.240

+/-

0.004 1.03 A

0.240

+/-

0.016 Mean =

0.246

+/-

0.010 0.288

+/-

0.011 Cs-137 0.309

+/-

0.010 0.294

+/-

0.005 1.21 A

0.303

+/-

0.010 Mean =

0.300

+/-

0.006 0.240

+/-

0.011 Co-58 0.236

+

0.009 0.218

+/-

0.004 1.02 A

0.240

+/-

0.008 Mean =

0.239

+/-

0.006 0.244

+/-

0.011 0.254

+/-

0.010 Mn-54 0.259 1

0.00 0.216

+ 0.004 1.17 A

0.259

+/-

0.009 Mean =

0.252

+/-

0.006 0.270

+/-

0.015 0.255

+/-

0.013 Fe-59 0.272

+/-

0.012 0.240

+

0.004 1.11 A

0.272

+/-

0.012 Mean =

0.266

+/-

0.008 0.099

+/-

0.019 Zn-65 0.120 0.016 0.111

+/-

0.002 1.05 A

0.128

+/-

0.012 Mean=

0.116

+/-

0.009 Co-60 0.489 0.512 0.497 Mean =

0.499

+

+/-

0.011 0.011 0.009 0.007 0.453

+/-

0.008 1.10 A

(1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable 8-9

8.5 TELEDYNE BROWN ENGINEERING Eckert & Ziegler Analytics supplies sample media as blind sample spikes, which contain certified levels of radioactivity unknown to the analysis laboratory. These samples are prepared and analyzed by the TBE laboratory using standard laboratory procedures. Eckert & Ziegler Analytics issues a statistical summary report of the results. TBE uses predetermined acceptance criteria methodology for evaluating the laboratory's performance.

For the TBE laboratory, 163 out of 169 analyses performed met the specified acceptance criteria. Six analyses (Ni-63, K-40 and 1-131 in water, two Sr 90s and one Gross Alpha in Air Particulate samples) did not meet the specified acceptance criteria for the following reasons:

1.

Teledyne Brown Engineering's MAPEP March 2014 Ni-63 in water result of 32.7 +/- 1.69 Bq/L was overlooked when reporting the data but would have passed the acceptance range of 23.9 - 44.2 Bq/L.

2.

Teledyne Brown Engineering's MAPEP March 2014 K-40 in water result of 1.63 +/- 2.49 Bq/L was overlooked when reporting the data but would have passed the false positive test.

NCR 14-04

3.

Teledyne Brown Engineering's ERA November 2014 1-131 in water result of 15.8 pCi/L was lower than the known value of 20.3 pCi/L, failing below the lower acceptance limit of 16.8. The result was evaluated as failed with a found to known ratio of 0.778. No cause could be found for the slightly low result. All ERA 1-131 evaluations since 2004 have been acceptable. NCR 14-08

4.

Teledyne Brown Engineering's MAPEP March 2014 Sr-90 in AP result of 0.822 Bq/sample was lower than the known value of 1.18 Bq/sample, failing below the lower acceptance limit of 0.83 Bq/sample. The rerun result was still low, but fell within the lower acceptance range of 0.836. The rerun result was statistically the same number as the original result. No cause could be found for the slightly low results. NCR 14-04

5.

Teledyne Brown Engineering's MAPEP September 2014 Sr-90 in AP result of 0.310 Bq/sample was lower than the known value of 0.703 Bq/sample. The gravimetric yield of 117% was very high (we normally see yields of 60% to 70 %) and could account for the low activity. NCR 14-09

6.

Teledyne Brown Engineering's MAPEP September 2014 Gr-Alpha in AP result of 0.153 Bq/sample was lower than the known value of 0.53 Bq/sample. The AP sample was counted on the wrong side. The AP was flipped over and recounted with acceptable results. NCR 14-09 8-10

TABLE 8-3 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported Known Ratio (c)

Value Month/Year Number Matrix Nuclide Units Value (a)

(b)

TBE/Analytics Evaluation (2d March 2014 E10854 Milk E10855 Milk E10857 AP E10856 Charcoal E10858 Water E10913 Milk E10914 Milk Sr-89 pCi/L Sr-90 pCi/L 95.1 91.7 10.9 15.1 1-131 pCi/L 96.6 98.5 Ce-141 pCi/L 112 119 Cr-51 pCi/L 449 491 Cs-134 pCi/L 186 210 Cs-137 pCi/L 250 253 Co-58 pCi/L 248 268 Mn-54 pCi/L 292 297 Fe-59 pCi/L 230 219 Zn-65 pCi/L 312 323 Co-60 pCi/L 321 337 Ce-141 pCi 53.0 53.9 Cr-51 pCi 232 223 Cs-i 34 pCi 100 95.3 Cs-137 pCi 122 115 Co-58 pCi 122 121 Mn-54 pCi 135 135 Fe-59 pCi 111 99.3 Zn-65 pCi 140 147 Co-60 pCi 187 153 1-131 pCi 74.1 76.4 1.04 0.72 0.98 0.94 0.91 0.89 0.99 0.93 0.98 1.05 0.97 0.95 0.98 1.04 1.05 1.06 1.01 1.00 1.12 0.95 1.22 0.97 1.19 0.94 0.95 0.95 0.90 1.01 0.91 1.03 0.94 0.99 1.04 1.00 0.97 A

W A

A A

A W

A A

June 2014 Fe-55 pCi/L Sr-89 pCi/L Sr-90 pCi/L 1-131 pCi/L Ce-141 pCi/L Cr-51 pCi/L Cs-i 34 pCi/L Cs-137 pCi/L Co-58 pCi/L Mn-54 pCi/L Fe-59 pCi/L Zn-65 pCi/L Co-60 pCi/L 2090 1760 85.9 91.3 13.8 14.5 86.5 111 255 147 123 105 155 106 251 218 90.9 124 253 162 120 112 156 102 252 224 8-11

TABLE 8-3 (Continued)

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Month/Year Identification Number Matrix E10916 AP Reported Known Value Nuclide Units Value (a)

(b)

Ce-141 pCi 95.1 92.6 Cr-51 pCi 215 190 Cs-134 pCi 122 122 Cs-137 pCi 95.1 89.8 Co-58 pCi 88.7 84.1 Mn-54 pCi 115 116 Fe-59 pCi 72.6 76.7 Zn-65 pCi 193 189 Co-60 pCi 179 168 Ratio (c)

TBE/Analytics Evaluation (d) 1.03 A

1.13 A

1.00 A

1.06 A

1.05 A

0.99 A

0.95 A

1.02 A

1.07 A

E10915 Charcoal E10917 Water 1-131 pCi 85.6 85.2 June 2014 September 2014 E10946 Milk E10947 Milk E10949 AP E10948 Charcoal E10950 Water Fe-55 pCi/L 1680 1810 Sr-89 pCi/L 90.7 96.9 Sr-90 pCi/L 14.0 16.4 1-131 pCi/L 92.0 97.6 Ce-141 pCi/L 117 126 Cr-51 pCi/L 281 288 Cs-134 pCi/L 141 158 Cs-137 pCi/L 186 193 Co-58 pCi/L 137 143 Mn-54 pCi/L 138 142 Fe-59 pCi/L 162 158 Zn-65 pCi/L 75.2 73.0 Co-60 pCi/L 286 297 Ce-141 pCi 97.8 82.1 Cr-51 pCi 212 188 Cs-134 pCi 106 103 Cs-137 pCi 131 126 Co-58 pCi 85.7 93.0 Mn-54 pCi 92.8 92.3 Fe-59 pCi 113 103 Zn-65 pCi 53.2 47.5 Co-60 pCi 202 193 1.00 0.93 0.94 0.85 0.94 0.93 0.98 0.89 0.96 0.96 0.97 1.03 1.03 0.96 1.19 1.13 1.03 1.04 0.92 1.01 1.10 1.12 1.05 0.93 1.17 1-131 pCi 83.9 89.8 Fe-55 pCi/L 2010 1720 8-12

TABLE 8-3 (Continued)

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Month/Year Identification Number Matrix E10951 Soil Reported Nuclide Units Value (a)

Ce-141 pCi/g 0.208 Cr-51 pCi/g 0.398 Cs-134 pCi/g 0.216 Cs-137 pCi/g 0.398 Co-58 pCi/g 0.197 Mn-54 pCi/g 0.242 Fe-59 pCi/g 0.238 Zn-65 pCi/g 0.117 Co-60 pCi/g 0.447 Known Value (b) 0.186 0.425 0.233 0.365 0.211 0.209 0.233 0.108 0.438 Ratio (c)

TBE/Analytics Evaluation (d 1.12 A

0.94 A

0.93 A

1.09 A

0.93 A

1.16 A

1.02 A

1.08 A

1.02 A

December 2014 E11078 Milk Sr-89 pCi/L 85.7 Sr-90 pCi/L 12.9 E11079 Milk 1-131 pCi/L 85.9 Ce-141 pCi/L 205 Cr-51 pCi/L 402 Cs-134 pCi/L 156 Cs-137 pCi/L 194 Co-58 pCi/L 122 Mn-54 pCi/L 220 Fe-59 pCi/L 183 Zn-65 pCi/L 287 Co-60 pCi/L 224 December 2014 E11081 AP Ce-141 pCi 96.4 Cr-51 pCi 171 Cs-134 pCi 73.1 Cs-1 37 pCi 99.0 Co-58 pCi 57.5 Mn-54 pCi 107 Fe-59 pCi 74.2 Zn-65 pCi 144 Co-60 pCi 114 E11080 Charcoal 1-131 pCi 93.5 95.7 15.6 95.1 219 406 164 198 130 225 175 297 235 102 190 76.9 92.6 60.8 105 81.6 139 110 98.2 0.90 0.83 0.90 0.94 0.99 0.95 0.98 0.94 0.98 1.05 0.97 0.95 0.95 0.90 0.95 1.07 0.95 1.02 0.91 1.04 1.04 0.95 E11082 Water Fe-55 pCi/L 1760 1970 0.89 A

(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 standard preparation.

(c) Ratio of Teledyne Brown Engineering to 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.

8-13

TABLE 8-3 (Continued)

ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Number Reported Known Acceptance Month/Year Media Nuclide Units Value (a)

Value (bh Limits Evaluation (c)

Month/Year May 2014 RAD-97 Water Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 MRAD-20 Filter Gr-A pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 38.25 24.65 89.1 45.55 91.15 65.10 244 45.65 27.95 23.75 9.61 8435 36.7 26.5 87.9 44.3 89.1 64.2 235 61.0 33.0 25.7 10.2 8770 27.5 - 43.6 19.2 - 30.9 74.0 - 96.7 35.5 - 48.7 80.2-101 57.8 - 73.1 212-275 31.9-75.8 21.4 -40.7 21.3-30.3 7.95-11.8 7610- 9650 A

A A

pCi/filter 28.0 46.0 15.4-71.4 November 2014 RAD-99 Water Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 30.4 18.6 46.8 88.0 99.0 92.5 325 29.9 27.5 15.8 5.74 6255 31.4 21.8 49.1 89.8 98.8 92.1 310 37.6 27.4 20.3 5.80 6880 22.8 - 38.1 15.6-25.7 40.3 - 54.5 73.7 - 98.8 88.9-111 82.9-104 279 - 362 19.4-48.1 17.3 - 35.3 16.8-24.4 4.34 - 6.96 5940 - 7570 A

A A

N (1)

A A

MRAD-21 Filter Gr-A pCi/filter 27.3 36.9 12.4 - 57.3 A

(1) The Iodine-131 was evaluated as failed with a ratio of 0. 778. No cause could be found for the slighty low activity. TBE would evaluate this as acceptable with warning. A rerun was not possible due to 1-131 decay. All ERA Iodine-131 evaluations since 2004 have been acceptable. NCR 14-08 (a) Teledyne Brown Engineering reported result.

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

(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.

8-14

8.6 REFERENCES

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

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

8-15

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Enclosure:

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