JAFP-17-0046, 2016 Annual Radiological Environmental Operating Report

2016 Annual Radiological Environmental Operating Report

ML17131A248
Person / Time
Site:	FitzPatrick
Issue date:	05/11/2017
From:	Drews W Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-17-0046
Download: ML17131A248 (162)

Text

Exelon Generation ., Exelon Generation Co., LLC James A. FitzPatrick NPP P.O. Box 110 Lycoming , NY 13093 Tel 315-342-3840 William C. Drews Regulatory Assurance Manager JAFP-17-0046 May 11, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

2016 Annual Radiological Environmental Operating Report James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59

Dear Sir or Madam:

This letter transmits the James A. FitzPatrick Nuclear Power Plant's (JAF) Annual Radiological Environmental Operating Report, for the period of January 1, 2016, through December 31, 2016. This document is submitted in accordance with the Reporting Requirements of the Technical Specifications Section 5.6.2, and Appendix H of the Technical Requirements Manual "Offsite Dose Calculation Manual (ODCM)", Part 1, Section 6.1 Annual Radiological Environmental Operating Report.

There are no new regulatory commitments contained in this letter.

If you have any questions concerning the enclosed report, please contact Jeff Gerber, Chemistry Manager, at (315) 349-6635.

Sincerely, William C. Drews Regulatory Assurance Manager WO/JG/de

Enclosure:

2016 Annual Radiological Environmental Operating Report cc: Next Page

JAFP-17-0046 Page 2 of 2 cc:

NRC Regional Administrator, Region I NRC Resident Inspector NRC Project Manager Supervisor, Town of Scriba Route 8, Box 382 Oswego, NY 13126

JAFP-17-0046 Enclosure 2016 Annual Radiological Environmental Operating Report

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January 1, 2016 - December 31, 2016 for JAMES A. FITZPATRICK NUCLEAR POWER PLANT Exelon Generation Company, LLC Facility Operating License No. DPR-59 Docket No. 50-333

TABLE OF CONTENTS Page 1.0 PURPOSE ..............................................................................................................................1-1

2.0 INTRODUCTION

.................................................................................................................2-1 2.1 Program History ........................................................................................................2-1 2.2 Site Description .........................................................................................................2-2 2.3 Program Objectives ...................................................................................................2-2 3.0 PROGRAM DESCRIPTION ................................................................................................3-1 3.1 Sample Collection Methodology................................................................................3-6 3.2 Analyses Performed..................................................................................................3-12 3.3 Sample Locations......................................................................................................3-13 3.4 Land Use Census ......................................................................................................3-27 3.5 Changes to the REMP Program................................................................................3-28 3.6 Deviation and Exceptions to the Program ................................................................3-28 3.7 Statistical Methodology ............................................................................................3-30 3.8 Compliance with Required Lower Limits of Detection (LLD) ...............................3-33 3.9 Regulatory Limits .....................................................................................................3-35 4.0 SA MPLE

SUMMARY

TABLES IN BRANCH TECHNICAL POSITION FORMAT....4-1 5.0 DA TA EVALUATION AND DISCUSSION .......................................................................5-1 5.1 Aquatic Program .........................................................................................................5-6 5.2 Terrestrial Program ...................................................................................................5-14 5.3 Conclusion ................................................................................................................5-33 5.4 References.................................................................................................................5-34 6.0 REPORT PERIOD ANALYTICAL RESULTS TABLES ..................................................6-1 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 9.0 ENVIRONMENTAL DOSIMETRY COMPANY ANNUAL QUALITY ASSURANCE STATUS REPORT.......................................................................................9-1 i

LIST OF TABLES Page Table 3.0-1 Required Sample Collection and Analysis................................................................3-2 Table 3.3-1 Environmental Sample Locations ...........................................................................3-14 Table 3.8-1 Required Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) ...........................................................................3-34 Table 4.0-1 Radiological Environmental Monitoring Program Annual Summary......................4-2 Table 6-1 Concentrations of Gamma Emitters in Shoreline Sediment Samples ...................6-2 Table 6-2 Concentrations of Gamma Emitters in Fish Samples FitzPatrick............................................................................................................6-3 Nine Mile Point ...................................................................................................6-3 Oswego Harbor ...................................................................................................6-3 Table 6-3 Concentrations of Tritium in Surface Water Samples Samples .....................................................................................................................6-4 Table 6-4 Concentrations of Gamma Emitters in Surface Water Samples FitzPatrick............................................................................................................6-5 Oswego Steam Station ........................................................................................6-5 Nine Mile Point Unit 1 ........................................................................................6-6 Oswego City Water .............................................................................................6-6 Nine Mile Point Unit 2 ........................................................................................6-7 Table 6-5 Environmental Airborne Particulate Samples-Offsite Sample Locations Gross Beta Activity (Jan-Jun) ..................................................................6-8 (Jul-Dec) ..................................................................6-9 Table 6-6 Environmental Airborne Particulate Samples-Onsite Sample Locations Gross Beta Activity (Jan-Jun) ................................................................6-10 (Jul-Dec) ................................................................6-11 Table 6-7 Environmental Charcoal Cartridge Samples-Offsite Sample Locations I-131 Activity (Jan-Jun) ................................................................6-12 (Jul-Dec) ................................................................6-13 Table 6-8 Environmental Charcoal Cartridge Samples-Onsite Sample Locations I-131 Activity (Jan-Jun) ................................................................6-14 (Jul-Dec) ................................................................6-15 ii

LIST OF TABLES (Continued)

Page Table 6-9 Concentrations of Gamma Emitters in Quarterly Composites of JAF/NMPNS Site Air Particulate Samples Offsite Sample Locations - 1st, 2nd, 3rd,4th Qtrs ...............................................6-16 Onsite Sample Locations - 1st, 2nd, 3rd, 4th Qtrs ...............................................6-18 Table 6-10 Direct Radiation Measurement Results...................................................................6-19 Table 6-11 Concentrations of Iodine-131 and Gamma Emitters in Milk Sample Location No. 55 ...................................................................................6-21 Sample Location No. 77 (Control) ...................................................................6-22 Table 6-12 Concentrations of Gamma Emitters in Food Products ....................................... 6-23 Table 6-13 Milk Animal Census 2016 .................................................................................. 6-24 Table 6-14 Residence Census 2016.......................................................................................6-25 Historical Environmental Sample Data Table 7-1 Shoreline Sediment Control ..................................................................... 7-2 Table 7-2 Indicator ................................................................... 7-3 Table 7-3 Fish Control ..................................................................... 7-4 Table 7-4 Indicator ................................................................... 7-5 Table 7-5 Surface Water Control ..................................................................... 7-6 Table 7-6 Indicator ................................................................... 7-7 Table 7-7 Surface Water Tritium Control ..................................................................... 7-8 Table 7-8 Indicator ................................................................... 7-9 Table 7-9 Air Particulate Gross Beta Control ................................................................... 7-10 Table 7-10 Indicator ................................................................. 7-11 Table 7-11 Air Particulates Control ................................................................... 7-12 Table 7-12 Indicator ................................................................. 7-13 iii

LIST OF TABLES (Continued)

Page Historical Environmental Sample Data (Continued)

Table 7-13 Air Radioiodine Control .................................................................. 7-14 Table 7-14 Indicator ................................................................ 7-15 Table 7-15 Environmental TLD Control .................................................................. 7-16 Table 7-16 Site Boundary........................................................ 7-17 Table 7-17 Offsite Sectors....................................................... 7-18 Table 7-18 Special Interest...................................................... 7-19 Table 7-19 Onsite Indicator..................................................... 7-20 Table 7-20 Offsite Indicator .................................................... 7-21 Table 7-21 Milk Control .................................................................. 7-22 Table 7-22 Indicator ................................................................ 7-23 Table 7-23 Food Products Control .................................................................. 7-24 Table 7-24 Indicator ................................................................ 7-25 Quality Assurance / Quality Control Program Interlaboratory Intercomparison Program Table 8-1 Eckert & Ziegler Analytics................................................................................ 8-6 Table 8-2 DOEs Mixed Analyte Performance Evaluation Program (MAPEP) .............. 8-9 Table 8-3 ERA Environmental Radioactivity Cross Check Program................................8-10 iv

LIST OF FIGURES Page Figure 3.3-1 New York State Map ..............................................................................................3-20 Figure 3.3-2 Off-Site Environmental Station and TLD Locations Map......................................3-21 Figure 3.3-3 Onsite Environmental Station and TLD Locations Map ........................................3-22 Figure 3.3-4 Milk and Surface Water Sample Locations Map ....................................................3-23 Figure 3.3-5 Nearest Residence, Food Product, Fish and Shoreline Sediment Sample Locations Map ...........................................................................................3-24 Figure 3.3-6 Nearest Residence-JAF Locations Map ..................................................................3-25 Figure 3.3-7 JAF On-Site Ground Water Monitoring Wells Map ..............................................3-26 v

1.0 PURPOSE The Annual Radiological Environmental Operating Report is published in accordance with the James A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part I, Section 6.1.

The ODCM requires that the results from the annual Radiological Environmental Monitoring Program (REMP) be provided to the Nuclear Regulatory Commission by May 15th of each year.

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 Manual (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 Laboratorys performance in the Quality Assurance Intercomparison.

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, 40 CFR 190 and 10 CFR 72.

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 2016 there were 2,181 analyses performed on environmental media collected as part of the REMP. These results demonstrated that there is no significant or measurable radiological impact from the operation of the James A. FitzPatrick Nuclear Power Plant. The 2016 results for all pathways sampled are consistent with the previous five-year historical results and exhibited no adverse trends.

In summary, the analytical results from the 2016 Radiological Environmental Monitoring Program demonstrate that the routine operation at the James A. FitzPatrick site had no significant or measurable radiological impact on the environment. The program continues to demonstrate that the dose to a member of the public, as a result of the operation of the James A. FitzPatrick Nuclear Power Plant, remains significantly below the federally required dose limits specified in 10 CFR 20, 40 CFR 190 and 10 CFR 72.

1-1

2.0 INTRODUCTION

The James A. FitzPatrick Nuclear Power Plant is owned and operated by Exelon Generation Company, LLC. This report is submitted in accordance with Offsite Dose Calculation Manual, Part 1, Section 6.1. This report covers the calendar year 2016.

2.1 PROGRAM HISTORY Environmental monitoring at the Nine Mile Point site has been ongoing 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 later data obtained during reactor operation. In 1969, the Nine Mile Point Unit 1 reactor, a 628 megawatt electric (MWe) Boiling Water Reactor (BWR) began full power operation. In 1975, the James A.

FitzPatrick Nuclear Power Plant, owned and operated at that time by the New York Power Authority, began full power operation. The FitzPatrick plant, an 892 MWe (rated) BWR, occupies the east sector of the Nine Mile Point site, approximately 0.57 miles east of Nine Mile Point Unit 1. In 1988, the Nine Mile Point Unit 2 reactor also owned and operated by Nine Mile Point Nuclear Station, LLC, began full power operation. This 1363 MWe BWR is located between the Nine Mile Point Unit 1 and FitzPatrick sites.

In 1985, the individual Plant Effluent Technical Specifications were standardized to the generic Radiological Effluent Technical Specifications, much of which was common to the two reactors, and subsequently Nine Mile Point Unit 2. Subsequent Technical Specification amendments relocated the REMP requirements to the ODCM for all three plants. Data generated by the Radiological Environmental Monitoring Program (REMP) is shared, but each utility reviews and publishes their own annual report. On November 21, 2000 the ownership and operation of the James A. FitzPatrick Nuclear Power Plant was transferred from the New York Power Authority to Entergy Nuclear FitzPatrick, LLC and Entergy Nuclear Operations, Inc. The Facility Operating License No. DPR-59 and Docket No. 50-333 remained the same in March 2017, ownership and operation of the James A. FitzPatrick Nuclear Power Plant was transferred to Exelon Generation Company, LLC.

On November 7, 2001, the ownership of the Nine Mile Point Unit I and II facilities was transferred to Constellation Energy Nuclear Group. These two facilities are operated by Nine Mile Point Nuclear Station, LLC. Exelon Generation Company, LLC took over ownership and operation of the Nine Mile Point Unit I and II facilities in 2014.

In summary, three Boiling Water Reactors, which together generate 2883 MWe, have operated collectively at the Nine Mile Point site since 1988. A large database of environmental results from the exposure pathways have been collected and analyzed to evaluate the potential impact from reactor operations.

2-1

2.2 SITE DESCRIPTION The Nine Mile Point 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 southeast of the site. The James A. FitzPatrick Nuclear Power Plant and support buildings occupy a small shoreline portion of the 702 acre Nine Mile Point site, which is partially wooded. 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.

2.3 PROGRAM OBJECTIVES The objectives of the Radiological Environmental Monitoring Program (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 James A. FitzPatrick Nuclear Power Plant site.

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

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 James A. FitzPatrick Nuclear Power Plant (JAFNPP) Radiological Environmental Monitoring Program (REMP) consists of sampling and analysis of various media that include:

• Air

• Fish

• Food Products

• Milk

• Shoreline Sediment

• Surface Waters In addition, direct radiation measurements are performed using thermoluminescent dosimeters (TLDs). These sampling programs are outlined in Table 3.0-1. The JAF REMP sampling locations are selected and verified by an annual Land Use Census. The accuracy and precision of the program is assured by participation in an Interlaboratory Comparison Quality Assurance Program (ICQAP).

Sample collections for the radiological program are accomplished by a dedicated site environmental staff from both the Nine Mile Point Nuclear Stations (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 REQUIRED SAMPLE COLLECTION AND ANALYSIS Exposure Pathway Sampling and Type and Frequency and/or Sample Number of Samples (a) and Locations Collection Frequency (a) of Analysis AIRBORNE Radioiodine Samples from 5 locations: Continuous sample Radioiodine Canisters:

and Particulates operation with sample Analyze weekly for

a. 3 Samples from offsite locations in different sectors of the collection weekly or as I-131 highest calculated site average D/Q (based on all licensed site required by dust reactors) loading, whichever is Particulate Samples: Gross more frequent beta radioactivity following

b. 1 sample from the vicinity of a community having the highest filter change (b), composite calculated site average D/Q (based on all licensed site reactors) (by location) for gamma isotopic(c) quarterly (as a

c. 1 sample from a control location 9 to 20 miles distant and in the minimum) least prevalent wind direction(d)

DIRECT RADIATION(e) 32 stations with two or more dosimeters placed as follows: Quarterly Gamma dose monthly or quarterly

a. An inner ring of stations in the general area of the Site Boundary

b. An outer ring in the 4 to 5 mile range from the site with a station in each of the land based sectors. There are 16 land based sectors in the inner ring, and 8 land based sectors in the outer ring

c. The balance of the stations (8) are placed in special interest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations 3-2

TABLE 3.0-1 (Continued)

REQUIRED SAMPLE COLLECTION AND ANALYSIS Exposure Pathway Sampling and Type and Frequency and/or Sample Number of Samples (a) and Locations Collection Frequency (a) of Analysis INGESTION Milk a. Samples from milch animals in 3 locations within 3.5 miles Twice per month, April Gamma isotopic and I-131 distant having the highest calculated site average D/Q. If there through December analysis twice per month are none, then 1 sample from milch animals in each of the 3 (samples will be when milch animals are on areas 3.5 to 5.0 miles distant having the highest calculated site collected in January pasture (April through average D/Q (based on all licensed site reactors)(h) through March if I-131 December); monthly (January is detected in November through March), if required(c)

b. 1 sample from milch animals at a control location (9 to 20 miles and December of the distant and in a less prevalent wind direction)(d) preceding year)

Fish a. 1 sample of each of 2 commercially or recreationally important Twice per year Gamma isotopic(c) analysis of species in the vicinity of a site discharge point edible portions.

b. 1 sample of each of 2 species (same as in a. above or of a species with similar feeding habits) from an area at least 5 miles distant from the site(d)

Food Products a. In lieu of the garden census as specified in Part 1, Section 5.2, Once during harvest Gamma isotopic(c) analysis of samples of at least 3 different kinds of broad leaf vegetation season edible portions. (Isotopic to (such as vegetables) grown nearest each of two different offsite include I-131) locations of highest predicted site average D/Q (based on all licensed site Reactors)

b. One (1) sample of each of the similar broad leaf vegetation grown at least 9.3 miles distant in a least prevalent wind direction sector(d) 3-3

TABLE 3.0-1 (Continued)

REQUIRED SAMPLE COLLECTION AND ANALYSIS Exposure Pathway Sampling and Type and Frequency (a) and/or Sample Number of Samples and Locations Collection Frequency (a) of Analysis WATERBORNE Surface(f) a. 1 sample upstream(d) Composite sample over a Gamma isotopic

b. 1 sample from the sites most downstream cooling water one month period(g) analysis monthly.

intake Composite for Tritium analysis quarterly(c)

Sediment from 1 sample from a downstream area with existing or potential Twice per year Gamma isotopic Shoreline recreational value analysis semi-annually(c) 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. Actual locations (distance and directions) from the site shall be provided in the Annual Radiological Environmental Operating Report. Calculated site averaged D/Q values and meteorological parameters are based on historical data (specified in the ODCM) for all licensed site reactors.

(b) Particulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples 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 plant.

(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) 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" 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, if practical.

(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 ensure that a representative sample is obtained.

(h) A milk sampling location, as required in Table 5.1-1 of the ODCM, is defined as a location having at least 10 milking cows present at a designated milk sample location. It has been found from past experience, and as a result of conferring with local farmers, that a minimum of 10 milking cows is necessary to guarantee an adequate supply of milk twice per month for analytical purposes. Locations with less than 10 milking cows are usually utilized for breeding purposes which eliminates a stable supply of milk for samples as a result of suckling calves and periods when the adult animals are dry.

In the event that 3 milk sample locations cannot meet the requirement for 10 milking cows, then a sample location having less than 10 milking cows can be used if an adequate supply of milk can reasonably and reliably be obtained based on communications with the farmer.

3-5

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 listed in Section 3.3, Table 3.3-1 and shown in Figure 3.3-5 3.1.2 FISH Samples of available fish species that are commercially or recreationally important to Lake Ontario; such as Brown Trout, Chinook Salmon, Smallmouth Bass, and Walleye, are collected twice per year, once in the spring and again in the fall. Indicator samples are collected from a combination of the two onsite sample transects located offshore from the site. One set of control samples are collected at an offsite sample transect located offshore 8-10 miles west of the site. Available species are selected using the following guidelines:

1. 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.

2. Samples are composed of the edible portion only.

Selected fish samples are frozen immediately 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 sample locations are listed in Section 3.3, Table 3.3-1 and shown in Figure 3.3-5.

3-6

3.1.3 SURFACE WATER Surface water samples are taken from the respective inlet canals of the James A.

FitzPatrick Nuclear Power Plant (JAFNPP) and NRCs Oswego Steam 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 Steam 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 Steam Station are also obtained using automatic sampling equipment and collected in a holding tank. Representative samples from this location are obtained weekly 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 Steam Station collection sites, data is presented for the Nine Mile Point Unit 1 and Unit 2 facility inlet canal samples and from the City of Oswego drinking water supply. The latter 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.

Surface water sample locations are listed in Section 3.3, Table 3.3-1 and shown on Figure 3.3-4.

3-7

3.1.4 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 deposition factor (D/Q) based on historical meteorological data. These stations (R1, R2, R3 and R4) are located in the E, ESE, and SE sectors as measured from the center of the Nine Mile Point Nuclear Station Unit 2 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 R4. A fifth station required by the ODCM is a control location designated as Station R5. Station R5 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 southwest sector in the vicinity of the City of Oswego and is designated as Station G Offsite. 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 cartridges (2x1 inch). 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 are listed in Section 3.3, Table 3.3-1 and shown on Figures 3.3-2 and 3.3-3.

3-8

3.1.5 TLD (DIRECT RADIATION)

Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the environment. Environmental TLDs are supplied and processed quarterly by Stanford Dosimetry. The vendor utilizes a Panasonic based system using UD-814 dosimeters, which contain three CaSO4 phosphor elements under 1000mg of lead and one lithium borate element.

1. Environmental TLDs Environmental TLDs are placed in five different geographical regions around 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:

TLD Geographical Category Description Onsite TLDs placed at various locations within the site boundary, with three exceptions, are not required by the ODCM. (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)

Site Boundary 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*)

Offsite An outer ring of TLDs placed 4 to 5 miles from the site in each of the 8 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*)

Special Interest 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)

Control 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)

• TLD location required by the ODCM 3-9

Although 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 readings.

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

Environmental TLD locations are listed in Section 3.3, Table 3.3-1 and show on Figures 3.3-2 and 3.3-3.

2. Independent Spent Fuel Storage Installation (ISFSI)

In order to provide adequate spent fuel storage capacity at the FitzPatrick plant, Entergy constructed an Independent Spent Fuel Storage Installation (ISFSI) onsite. On April 25, 2002, the ISFSI facility was placed in service.

TLDs are used to monitor direct radiation levels in the vicinity of the ISFSI facility.

Twelve TLD locations were established around the ISFSI pad on the perimeter fence. Six additional TLD locations are located at varying distances from the pad to determine dose rates at points of interest relative to the storage area and are designated as optional locations. Background data was collected starting in October, 2000 at eight of the TLD locations on the perimeter fence. The remaining locations were established in October 2001.

Two dosimeters are placed at each TLD monitoring location. The TLDs are sealed in polyethylene packages to ensure dosimeter integrity and placed in the field using a supporting structure such as a fence or other immovable object.

ISFSI TLD locations are listed in Section 3.3, Table 3.3-1.

3 - 10

3.1.6 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 in samples in 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 following sampling year. Milk samples were not collected in January through March of 2016 as there were no positive detections of plant related radionuclides in samples collected during November and December of 2015.

The ODCM also requires that a sample be collected from a control location nine to twenty miles from the site and in a less prevalent wind direction. This location 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 butter fat. 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 listed in Section 3.3, Table 3.3-1 and shown on Figure 3.3-4.

3.1.7 FOOD PRODUCTS (VEGETATION)

Food products are collected once per year during the late summer harvest season. A minimum of three different kinds of broad leaf vegetation (edible or inedible) are collected from two different indicator garden locations. Sample locations are selected from available gardens identified in the annual census that have the highest estimated deposition values (D/Q) based on historical site meteorological data. Control samples are also collected from available locations greater than 9.3 miles distance from the site in a less 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 analysis.

Food product locations are listed in Section 3.3, Table 3.3-1 and shown on Figure 3.3-5.

3 - 11

3.1.8 GROUND WATER MONITORING PROGRAM The Nuclear Energy Institute (NEI) Ground Water 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 NEI 07-07, Industry Ground Water Protection Initiative Final Guidance Document, August 2007, ground water monitoring is accomplished through sampling of the water table around the plant and analyzing it for gamma emitters and tritium. In November of 2007, JAF drilled 5 ground water wells along the north edge of the property next to the lake. Starting in March 2010, 16 additional monitoring wells were drilled in the area of the reactor building and nearby SSCs (see Section 3.3, Figure 3.3-7). In August 2013, 3 additional monitoring wells and 2 piezometers were installed on site.

Samples obtained from these wells are analyzed on a quarterly basis to determine gamma emitters and tritium concentrations. Ground water samples are analyzed for gamma emitters using gamma isotopic analysis and tritium using liquid scintillation detector.

Ground water results are documented in the Annual Radiological Effluent Release Report.

3.2 ANALYSES PERFORMED Environmental sample analyses are performed at the James A. FitzPatrick Nuclear Power Plant (JAFNPP) Chemistry Laboratory or by a contract laboratory. The following analyses were performed:

1. Air Particulate Filter - Gross Beta

2. Air Particulate Filter Composites - Gamma Spectral Analysis

3. Airborne Radioiodine - Gamma Spectral Analysis

4. Direct Radiation using Thermoluminescent Dosimeters (TLDs)

5. Fish - Gamma Spectral Analysis

6. Food Products (vegetation) - Gamma Spectral Analysis

7. Milk - Gamma Spectral Analysis and I-131

8. Shoreline Sediment - Gamma Spectral Analysis

9. Special Samples (soil, food, bottom sediment, etc.) - Gamma Spectral Analysis

10. Surface Water Monthly Composites - Gamma Spectral Analysis, I-131

11. Surface Water Quarterly Composite - Tritium

12. Ground Water Quarterly Samples - Tritium 3 - 12

3.3 SAMPLE LOCATIONS This section provides 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.

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

1. Sample Medium

2. 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)

3. Location Description

4. Degrees and Distance of the sample location from the site 3.3.1 LIST OF FIGURES Figure 3.3-1 New York State Map Figure 3.3-2 Off-Site Environmental Station and TLD Locations Map Figure 3.3-3 Onsite Environmental Station and TLD Locations Map Figure 3.3-4 Milk and Surface Water Sample Locations Map Figure 3.3-5 Nearest Residence, Food Product, Fish and Shoreline Sediment Sample Locations Map Figure 3.3-6 Nearest Residence-JAF Locations Map Figure 3.3-7 JAF On-Site Ground Water Monitoring Wells Map 3 - 13

TABLE 3.3-1 ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MAP FIGURE DEGREES & DISTANCE MEDIUM DESIGNATION NUMBER LOCATION DESCRIPTION (1) & (2)

Shoreline Sediment 05* Figure 3.3-5 Sunset Bay 84º at 1.2 miles 06 Figure 3.3-5 Langs Beach, Control 232° at 4.8 miles Fish 02* Figure 3.3-5 Nine Mile Point Transect 290° at 0.4 miles 03* Figure 3.3-5 FitzPatrick Transect 62° at 0.8 miles 00* Figure 3.3-5 Oswego Transect 237° at 5.9 miles Surface Water 03* Figure 3.3-4 FitzPatrick Inlet 53° at 0.6 miles 08* Figure 3.3-4 Oswego Steam Station Inlet (Control) 237° at 7.6 miles 09 Figure 3.3-4 NMP Unit 1 Inlet 319° at 0.3 miles 10 Figure 3.3-4 Oswego City Water 240° at 7.8 miles 11 Figure 3.3-4 NMP Unit 2 Inlet (Split intake with two locations) 336° at 0.3 miles 353° at 0.3 miles Air Radioiodine and R1* Figure 3.3-2 R1 Station, Nine Mile Point Road 92° at 1.8 miles Particulates R2* Figure 3.3-3 R2 Station, Lake Road 107° at 1.1 miles R3* Figure 3.3-3 R3 Station, Co. Rt. 29 133° at 1.4 miles R4* Figure 3.3-3 R4 Station, Village of Lycoming, Co. Rt. 29 145° at 1.8 miles R5* Figure 3.3-2 R5 Station, Montario Point Rd. (Control) 42° at 16.2 miles D1 Figure 3.3-3 D1 Onsite Station 71° at 0.3 miles G Figure 3.3-3 G Onsite Station 245° at 0.7 miles H Figure 3.3-3 H Onsite Station 73° at 0.8 miles I Figure 3.3-3 I Onsite Station 95° at 0.8 miles J Figure 3.3-3 J Onsite Station 109° at 0.9 miles K Figure 3.3-3 K Onsite Station 132° at 0.5 miles G Figure 3.3-2 G Offsite Station, Saint Paul Street 226° at 5.4 miles D2 Figure 3.3-2 D2 Offsite Station, Rt. 64 118° at 9.0 miles E Figure 3.3-2 E Offsite Station, Rt. 4 162° at 7.1 miles F Figure 3.3-2 F Offsite Station, Dutch Ridge Road 192° at 7.6 miles (1) Degrees and distance based on Nine Mile Point Unit 2 Reactor Centerline rounded to the nearest 1/10 of a mile.

(2) Degrees and Distances updated by Global Positioning System (GPS) in 2006.

• Sample location required by ODCM 3 - 14

TABLE 3.3-1 (Continued)

ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MAP FIGURE DEGREES & DISTANCE MEDIUM DESIGNATION NUMBER LOCATION DESCRIPTION (1) & (2)

Thermoluminescent 3 Figure 3.3-3 D1 Onsite 71° at 0.3 miles Dosimeters (TLD) 4 Figure 3.3-3 D2 Onsite 143° at 0.4 miles 5 Figure 3.3-3 E Onsite 180° at 0.3 miles 6 Figure 3.3-3 F Onsite 213° at 0.5 miles 7* Figure 3.3-3 G Onsite 245° at 0.7 miles 8* Figure 3.3-2 R5 Offsite Control 42° at 16.2 miles 9 Figure 3.3-2 State Route 3 80° at 11.4 miles 10 Figure 3.3-2 D2 Offsite 118° at 9.0 miles 11 Figure 3.3-2 E Offsite 162° at 7.1 miles 12 Figure 3.3-2 F Offsite 192° at 7.6 miles 13 Figure 3.3-2 G Offsite 226° at 5.4 miles 14* Figure 3.3-2 DeMass Rd., SW Oswego - Control 227° at 12.5 miles 15* Figure 3.3-2 Pole 66, W. Boundary - Bible Camp 240° at 0.9 miles 18* Figure 3.3-3 Energy Info. Center - Lamp Post, SW 268° at 0.4 miles 19 Figure 3.3-2 East Boundary - JAF, Pole 9 83° at 1.4 miles 23* Figure 3.3-3 H Onsite 73° at 0.8 miles 24 Figure 3.3-3 I Onsite 95° at 0.8 miles 25 Figure 3.3-3 J Onsite 109° at 0.9 miles 26 Figure 3.3-3 K Onsite 132° at 0.5 miles 27 Figure 3.3-3 N. Fence, N. of Switchyard, JAF 60° at 0.4 miles 28 Figure 3.3-3 N. Light Pole,N. of Screenhouse, JAF 68° at 0.5 miles 29 Figure 3.3-3 N. Fence, N. of W. Side 65° at 0.5 miles 30 Figure 3.3-3 N. Fence, (NW) JAF 57° at 0.4 miles 31 Figure 3.3-3 N. Fence, (NW) NMP-1 279° at 0.2 miles 39 Figure 3.3-3 N. Fence, Rad. Waste-NMP-1 298° at 0.2 miles 47 Figure 3.3-3 N. Fence, (NE) JAF 69° at 0.6 miles 49* Figure 3.3-2 Phoenix, NY-Control 168° at 19.7 miles 51 Figure 3.3-2 Liberty & Bronson Sts., E of OSS 234° at 7.3 miles 52 Figure 3.3-2 E. 12th & Cayuga Sts., Oswego School 227° at 5.9 miles 53 Figure 3.3-2 Broadwell & Chestnut Sts. Fulton H.S. 183° at 13.7 miles (1) Degrees and distance based on Nine Mile Point Unit 2 Reactor Centerline rounded to the nearest 1/10 of a mile.

(2) Degrees and Distances updated by Global Positioning System (GPS) in 2006.

• Sample location required by ODCM 3 - 15

TABLE 3.3-1 (Continued)

ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MAP FIGURE DEGREES & DISTANCE MEDIUM DESIGNATION NUMBER LOCATION DESCRIPTION (1) & (2)

Thermoluminescent 54 Figure 3.3-2 Mexico High School 115° at 9.4 miles Dosimeters (TLD) 55 Figure 3.3-2 Gas Substation Co. Rt. 5-Pulaski 75° at 13.0 miles (Continued) 56* Figure 3.3-2 Rt. 104-New Haven Sch. (SE Corner) 124° at 5.2 miles 58* Figure 3.3-2 Co Rt. 1A-Novelis (E. of E. Entrance Rd.) 222° at 3.0 miles 75* Figure 3.3-3 Unit 2, N. Fence, N. of Reactor Bldg. 354° at 0.1 miles 76* Figure 3.3-3 Unit 2, N. Fence, N. of Change House 25° at 0.1 miles 77* Figure 3.3-3 Unit 2, N. Fence, N. of Pipe Bldg. 36° at 0.2 miles 78* Figure 3.3-3 JAF. E. of E. Old Lay Down Area 85° at 1.0 miles 79* Figure 3.3-3 Co. Rt. 29, Pole #63, 0.2 mi. S. of Lake Rd. 120° at 1.2 miles 80* Figure 3.3-3 Co. Rt. 29, Pole #54, 0.7 mi. S. of Lake Rd. 136° at 1.5 miles 81* Figure 3.3-3 Miner Rd., Pole #16, 0.5 mi. W. of Rt. 29 159° at 1.6 miles 82* Figure 3.3-3 Miner Rd., Pole # 1-1/2, 1.1 mi. W. of Rt. 29 180° at 1.6 miles 83* Figure 3.3-3 Lakeview Rd., Tree 0.45 mi. N. of Miner Rd. 203° at 1.2 miles 84* Figure 3.3-3 Lakeview Rd., N., Pole #6117, 200ft. N. of Lake Rd. 226° at 1.1 miles 85* Figure 3.3-3 Unit 1, N. Fence, N. of W. Side of Screen House 292° at 0.2 miles 86* Figure 3.3-3 Unit 2, N. Fence, N of W. Side of Screen House 311° at 0.1 miles 87* Figure 3.3-3 Unit 2, N. Fence, N. of E. Side of Screen House 333° at 0.1 miles 88* Figure 3.3-2 Hickory Grove Rd., Pole #2, 0.6 mi. N. of Rt. 1 97° at 4.5 miles 89* Figure 3.3-2 Leavitt Rd., Pole #16, 0.4 mi. S. of Rt.1 112° at 4.3 miles 90* Figure 3.3-2 Rt. 104, Pole #300, 150 ft. E. of Keefe Rd. 135° at 4.2 miles 91* Figure 3.3-2 Rt 51A, Pole #59, 0.8 mi. W. of Rt. 51 157° at 4.9 miles 92* Figure 3.3-2 Maiden Lane Rd., Power Pole, 0.6 mi. S. of Rt. 104 183° at 4.4 miles 93* Figure 3.3-2 Rt. 53 Pole 1-1, 120 ft. S. of Rt. 104 206° at 4.4 miles 94* Figure 3.3-2 Rt. 1, Pole #82, 250 ft. E. of Kocher Rd. (Co. Rt. 63) 224° at 4.4 miles 95* Figure 3.3-2 Novelis W access Rd., Joe Fultz Blvd, Pole #21 239° at 3.7 miles 96* Figure 3.3-2 Creamery Rd., 0.3 mi. S. of Middle Rd., Pole 1-1/2 199° at 3.6 miles 97* Figure 3.3-3 Rt. 29, Pole #50, 200ft. N. of Miner Rd. 145° at 1.8 miles 98 Figure 3.3-2 Lake Rd., Pole #145, 0.15 mi. E. of Rt 29 102° at 1.2 miles (1) Degrees and distance based on Nine Mile Point Unit 2 Reactor Centerline rounded to the nearest 1/10 of a mile.

(2) Degrees and Distances updated by Global Positioning System (GPS) in 2006.

• Sample location required by ODCM 3 - 16

TABLE 3.3-1 (Continued)

ENVIRONMENTAL SAMPLE LOCATIONS MAP FIGURE DEGREES & DISTANCE SAMPLE MEDIUM DESIGNATION NUMBER LOCATION DESCRIPTION (1) & (2)

Thermoluminescent 99 Figure 3.3-2 NMP Rd., 0.4 mi. N. of Lake Rd., Env. Station R1 92° at 1.8 miles Dosimeters (TLD) 100 Figure 3.3-3 Rt. 29 & Lake Rd., Env. Station R2 107° at 1.1 miles (Continued) 101 Figure 3.3-3 Rt. 29, 0.7 mi. S. of Lake Rd., Env. Station R3 133° at 1.4 miles 102 Figure 3.3-2 EOF/Env. Lab, Rt 176, E. Driveway, Lamp Post 175° at 11.9 miles 103 Figure 3.3-3 EIC, East Garage Rd., Lamp Post 268° at 0.4 miles 104 Figure 3.3-2 Parkhurst Rd., Pole #23, 0.1 mi. S. of Lake Rd. 102° at 1.4 miles 105 Figure 3.3-3 Lakeview Rd. Pole #36, 0.5 mi. S. of Lake Rd. 199° at 1.4 miles 106 Figure 3.3-3 Shoreline Cove, W. of NMP-1, Tree on W. Edge 274° at 0.3 miles 107 Figure 3.3-3 Shoreline Cove, W. of NMP-1, 30 ft SSW of #106 273° at 0.3 miles 108 Figure 3.3-3 Lake Rd., Pole #142, 300 ft E. of Rt. 29 S. 105° at 1.1 miles 109 Figure 3.3-3 Tree North of Lake Rd., 300 ft E. of Rt. 29 N 104° at 1.1 miles 111 Figure 3.3-2 Control, State Route 38, Sterling NY 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 Control, Baldwinsville, NY 178° at 24.7 miles Cows Milk 55** Figure 3.3-4 Indicator Location 97° at 8.7 miles 77* Figure 3.3-4 Control Location 190° at 16.0 miles Food Products 144* Figure 3.3-5 Indicator Location - Whaley 139° at 1.6 miles 484* Figure 3.3-5 Indicator Location - OConnor 132° at 1.4 miles C2* Figure 3.3-5 Control Location - Flack 222° at 15.4 miles Nearest Residence (NMP) Based on NMP Unit 2 Centerline - Refer to Figure 3.3-5 Nearest Residence (JAF) Based on JAF Centerline - Refer to Figure 3.3-6 (1) Degrees and distance based on Nine Mile Point Unit 2 Reactor Centerline (2) Degrees and Distances updated by Global Positioning System (GPS) in 2006.

• Sample location required by ODCM

• • Optional sample 3 - 17

TABLE 3.3-1 (Continued)

ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE LOCATION MEDIUM DESIGNATION FIGURE NUMBER LOCATION DESCRIPTION I-1* ISFSI West Fence, South End of Storage Pad Thermoluminescent I-2* ISFSI West Fence, Center of Storage Pad Dosimeters (TLD)

I-3* ISFSI West Fence, North End of Storage Pad I-4* ISFSI North Fence, West End of Storage Pad I-5* ISFSI North Fence, Center of Storage Pad I-6* ISFSI North Fence, East End of Storage Pad I-7* ISFSI East Fence, North End of Storage Pad I-8* ISFSI East Fence, Center of Storage Pad I-9* ISFSI East Fence, South End of Storage Pad I-10* ISFSI South Fence, East End of Storage Pad I-11* ISFSI South Fence, Center of Storage Pad I-12* ISFSI South Fence, West End of Storage Pad I-13** ISFSI Building and Grounds Garage, East of Pad I-14** ISFSI Tree ~100 yards South of Pad I-15** ISFSI Transmission Line Tower South of Pad at East /West Access Road I-16** ISFSI Perimeter Fence ~100 yards West of Pad on Pad Centerline I-17** ISFSI North Fence of Main Switch Yard on Pad Centerline I-18** ISFSI North Inner Perimeter Fence at Lake Shore on Pad Centerline

• Sample location required by ODCM

• • Indicates Optional TLD location 3 - 18

TABLE 3.3-1 (Continued)

ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE LOCATION MEDIUM DESIGNATION FIGURE NUMBER LOCATION DESCRIPTION MW-1A Figure 3.3-7 Southwest of Reactor Building Ground Water MW-1B Figure 3.3-7 Southwest of Reactor Building Monitoring Wells MW-2A Figure 3.3-7 Northwest of Reactor Building MW-2B Figure 3.3-7 Northwest of Reactor Building MW-3A Figure 3.3-7 Northwest of Reactor Building MW-3B Figure 3.3-7 Northwest of Reactor Building MW-4A Figure 3.3-7 Northeast of Reactor Building MW-4B Figure 3.3-7 Northeast of Reactor Building MW-5 Figure 3.3-7 Northwest edge of property MW-6 Figure 3.3-7 North / Northwest edge of property MW-7 Figure 3.3-7 North edge of property MW-8 Figure 3.3-7 North / Northeast edge of property MW-9 Figure 3.3-7 Northeast edge of property MW-10A Figure 3.3-7 Southeast of Reactor Building MW-10B Figure 3.3-7 Southeast of Reactor Building MW-13 Figure 3.3-7 West of Reactor Building MW-14 Figure 3.3-7 East of Reactor Building MW-15 Figure 3.3-7 South of Reactor Building MW-16 Figure 3.3-7 Northwest of Reactor Building PZ-17 Figure 3.3-7 North / Northeast of Reactor Building PZ-18 Figure 3.3-7 North of Reactor Building MW-19 Figure 3.3-7 Northwest Edge of Property MW-20 Figure 3.3-7 Southwest Edge of Property MW-21 Figure 3.3-7 South of Reactor Building (Outside protected area)

MW-CST(A) Figure 3.3-7 West of Reactor Building MW-CST(B) Figure 3.3-7 West of Reactor Building 3 - 19

FIGURE 3.3-1 NEW YORK STATE MAP CANADA NINE MILE POINT SITE: VERMONT Nine Mile Point Nuclear Station Unit - 1 Nine Mile Point Nuclear Station Unit - 2 James A. FitzPatrick Nuclear Power Plant LAKE ONTARIO 38 M I.

MI. ROCHESTER UTICA 135 SYRACUSE BUFFALO ALBANY I.

23 0M MASSACHUSETTS NEW YORK PENNSYLVANIA CONNECTICUT NEW JERSEY NEW YORK CITY 3 - 20

3 - 21 3 - 22 3 - 23

$

3 - 24

La ke vie wR oad James A. FitzPatrick 3.3-6 3 - 25

3 - 26 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. The census is done once per year in the summer. It is conducted 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 was 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. Eight of the site meteorological sectors are 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 was performed for the 2016 growing season. The census is conducted each year to identify the gardens nearest the site, within a 5 mile radius, that are to be used for the collection of food product samples.

3 - 27

3.5 CHANGES TO THE REMP PROGRAM Based upon the results of the 2016 Land Use Census, there were no changes to the 2016 sampling program.

3.6 DEVIATION AND EXCEPTIONS TO THE PROGRAM The noted exceptions to the 2016 sample program address only those samples or monitoring requirements which are required by the ODCM, Part I, Table 5.1-1. This section satisfies the reporting requirements of ODCM, Part I, Section 5.1.1.c.1.

3.6.1 ODCM Program Deviations The following are deviations from the program specified by the ODCM:

03/24/16 - 03/29/16 Air Station R2 Offsite sample pump was inoperable for approximately 126 hours0.00146 days <br />0.035 hours <br />2.083333e-4 weeks <br />4.7943e-5 months <br />. Out of service time was determined based upon sample pump run time integrator. The inoperability was due to loss of power to the sample station. No corrective actions were required to restore power to the station. (AR 02647640 stated alternate power supply was used to provide power and follow up requested on breaker and switch) 07/18/16 - 07/26/16 Air Stations R1, R2, R3, R4 and R5 Offsite samples were not shipped in a timely manner. The I-131 concentration was not determined within the one week requirement. Vendor Laboratory received samples on 08/03/16 and all samples met the required Lower Limit of Detection (LLD) for I-131.

10/29/16 - 11/01/16 Air Station R1 Offsite sample pump was inoperable for approximately 61 hours7.060185e-4 days <br />0.0169 hours <br />1.008598e-4 weeks <br />2.32105e-5 months <br />. Out of service time was determined based upon sample pump run time integrator. The inoperability was due to sample pump overheating when installed cabinet cooling fan failed. Sample pump and the cooling fan were replaced.

10/25/16 - 11/01/16 Air Station R4 Offsite particulate filter was found misaligned in filter housing resulting in partial sample collection for approximately 168 hrs. Technician installing particulate filter validated position as procedure requires. Cabinet cooling fan was not operating during the 10/25/16 particulate filter change. Maintenance replaced the cabinet cooling fan later that day. Turning the sample pump on and off, to support fan replacement, may have disturbed the particulate filter positioning.

3 - 28

3.6.2 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 43,733 hours0.00848 days <br />0.204 hours <br />0.00121 weeks <br />2.789065e-4 months <br /> out of a possible 43,920 hours0.0106 days <br />0.256 hours <br />0.00152 weeks <br />3.5006e-4 months <br />. The air sampling availability factor for the report period was 99.6%.

Air sampling equipment found inoperable was returned to service. Identification of locations for obtaining replacement samples was not required.

3 - 29

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 JAFNPP Radiological Environmental Monitoring Program (REMP). The following equations were utilized to compute the mean (X) and the standard deviation(s):

1. Mean n

X Xi i 1 N

Where, X = estimate of the mean i = individual sample N, n = total number of samples with positive indications Xi = value for sample i above the lower limit of detection.

2. Standard Deviation 1/ 2 2

n s ( Xi X )

i 1 (N 1)

Where, X = mean for the values of X s = standard deviation for the sample population 3 - 30

3.7.2 ESTIMATION OF THE MEAN & THE ESTIMATED ERROR FOR THE MEAN In accordance with program policy, when the initial count indicates the presence of a plant related radionuclide(s) in a sample, two recounts of the sample may be required. 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 exists, 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.

1. Mean n

X Xi i 1 N

Where, X = estimate of the mean i = individual sample N,n = total number of samples with positive indications Xi = value for sample i above the lower limit of detection

2. Error of the Mean 1/ 2 n

2 ERROR MEAN ( ERROR )

i 1 N

Where, ERROR MEAN = propagated error i = individual sample ERROR = 1 sigma* error of the individual analysis N, n = number of samples with positive indications

• Sigma ()

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 - 31

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 S b LLD (E) (V ) (2.22) (Y ) exp (t )

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)

= the radioactive decay constant for the particular radionuclide t = the elapsed time between sample collection (or end of the sample collection period) and time of counting The ODCM LLD formula assumes that:

1. The counting times for the sample and background are equal

2. 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 3.8-1 lists the ODCM program required LLDs for specific media and radionuclides as specified by the NRC. The LLDs actually achieved are routinely lower than those specified by the ODCM.

3 - 32

3.8 COMPLIANCE WITH REQUIRED LOWER LIMITS OF DETECTION (LLD)

ODCM, Part 1, Table 5.1-3 specifies the detection capabilities for environmental sample analysis (see report Table 3.8-1). ODCM, Part 1, Section 6.1 requires that a discussion of all analyses for which the required LLDs specified were not routinely achieved be included in the Annual Radiological Environmental Operating Report. Section 3.8 is provided pursuant to this requirement.

3.8.1 All sample analyses performed in 2016 as required by the ODCM, achieved the Lower Limit of Detection (LLD) as specified by ODCM, Part 1, Table 5.1-3. See Table 3.8-1 for required LLD values.

3 - 33

TABLE 3.8-1 REQUIRED DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)

Airborne Particulate Food Water or Gases Fish Milk Products Sediment 3

Analysis (pCi/l) (pCi/m ) (pCi/kg, wet) (pCi/l) (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 H-3 3000 (a)

Mn-54 15 130 Fe-59 30 260 Co-58, Co-60 15 130 Zn-65 30 260 Zr-95, Nb-95 15 I-131 15 (a) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba/La-140 15 15 (a) 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, the LLD value of 3,000 pCi/liter is used for H-3 and the LLD value of 15 pCi/liter is used for I-131.

3 - 34

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

3.9.1 The Nuclear Regulatory Commission (NRC):

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 8 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), establishes criteria for radioactive materials in effluents and direct radiation from an Independent Spent Fuel Storage Installation (ISFSI).

During normal operations and anticipated occurrences, the annual dose equivalent to any real individual who is located beyond the 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 other organ as a result of :

1. Planned discharges of radioactive material, radon and its decay products excepted, to the environment

2. Direct radiation from ISFSI

3. Any other radiation from uranium fuel cycle operations in the region 3.9.2 Environmental Protection Agency (EPA)

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 total 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. The tables are titled Radiological Environmental Monitoring Program Annual Summary and use the following format as specified in the NRC Branch Technical Position:

Column

1. Sample Medium

2. Type and Number of Analyses Performed

3. Required Lower Limits of Detection (LLD), see Section 3.8, Table 3.8-1. This wording indicates that inclusive data is based on 4.66 Sb (sigma) of background (See Section 3.7).

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

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

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

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

NOTE: Only positive measured values are used in statistical calculations.

4-1

TABLE 4.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2016*

INDICATOR LOCATION (b) OF HIGHEST NUMBER OF TYPE AND NUMBER LOCATIONS: MEAN ANNUAL MEAN; LOCATION & CONTROL LOCATION: NONROUTINE MEDIUM (UNITS) OF ANALYSES* LLD(a) (f)/RANGE MEAN (f)/RANGE MEAN (f)/RANGE REPORTS Shoreline Sediment GSA (4):

(pCi/kg-dry) (Gamma-Spectrum Analysis)

Cs-134 150 <LLD <LLD <LLD 0 Cs-137 180 <LLD <LLD <LLD 0 Fish GSA (18):

(pCi/kg-wet)

Mn-54 130 <LLD <LLD <LLD 0 Fe-59 260 <LLD <LLD <LLD 0 Co-58 130 <LLD <LLD <LLD 0 Co-60 130 <LLD <LLD <LLD 0 Zn-65 260 <LLD <LLD <LLD 0 Cs-134 130 <LLD <LLD <LLD 0 Cs-137 150 <LLD <LLD <LLD 0 4-2

TABLE 4.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2016*

INDICATOR LOCATION (b) OF HIGHEST NUMBER OF TYPE AND NUMBER LOCATIONS: MEAN ANNUAL MEAN; LOCATION & CONTROL LOCATION: NONROUTINE MEDIUM (UNITS) OF ANALYSES* LLD(a) (f)/RANGE MEAN (f)/RANGE MEAN (f)/RANGE REPORTS Surface Water H-3 (8): 3000(c) <LLD <LLD <LLD 0 (pCi/liter)

GSA (24):

Mn-54 15 <LLD <LLD <LLD 0 Fe-59 30 <LLD <LLD <LLD 0 Co-58 15 <LLD <LLD <LLD 0 Co-60 15 <LLD <LLD <LLD 0 Zn-65 30 <LLD <LLD <LLD 0 Zr-95 15 <LLD <LLD <LLD 0 Nb-95 15 <LLD <LLD <LLD 0 I-131 15(c) <LLD <LLD <LLD 0 Cs-134 15 <LLD <LLD <LLD 0 Cs-137 18 <LLD <LLD <LLD 0 Ba/La-140 15 <LLD <LLD <LLD 0 TLD (mrem per Gamma Dose (128) (i) (d) 4.6 (116/116) TLD #87 (g) 7.8 (4/4) 4.2 (12/12) 0 standard month) 3.3-8.2 0.1 miles at 333º 7.3-8.2 3.6-5.2 4-3

TABLE 4.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2016*

INDICATOR LOCATION (b) OF HIGHEST NUMBER OF TYPE AND NUMBER LOCATIONS: MEAN ANNUAL MEAN; LOCATION & CONTROL LOCATION: NONROUTINE MEDIUM (UNITS) OF ANALYSES* LLD(a) (f)/RANGE MEAN (f)/RANGE MEAN (f)/RANGE REPORTS Air Particulates Gross Beta (265): 10 15.0 (212/212) R-4 15.3 (53/53) 14.4 (53/53) 0 (10E-3 pCi/m3) 7.6-25.4 1.8 miles at 145º 8.0-25.4 8.3-22.5 I-131 (265): 70 <LLD <LLD <LLD 0 GSA (20):

Cs-134 50 <LLD <LLD <LLD 0 Cs-137 60 <LLD <LLD <LLD 0 Milk GSA (36): (e) (h)

(pCi/liter)

Cs-134 15 <LLD <LLD <LLD 0 Cs-137 18 <LLD <LLD <LLD 0 Ba/La140 15 <LLD <LLD <LLD 0 I-131 (36):

I-131 1 <LLD <LLD <LLD 0 Food Products GSA (9):

(pCi/kg-wet)

I-131 60 <LLD <LLD <LLD 0 Cs-134 60 <LLD <LLD <LLD 0 Cs-137 80 <LLD <LLD <LLD 0 4-4

TABLE NOTES:

• = Data for Table 4.0-1 is based on ODCM required samples only.

(a) = LLD values as required by the ODCM. LLD units are specified in the medium column.

(b) = Location is distance in miles and direction in compass degrees based on NMP-2 reactor center-line rounded to the nearest 1/10 mile. Units in this column are specified in medium column.

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

(d) = The ODCM does not specify a particular LLD value to environmental TLDs.

(e) = 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 for 2016. The data is being included in the summary.

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

(g) = 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).

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

(i) = 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 and 97. Control TLDs are TLDs located beyond the influence of the site (TLD #: 8, 14 and 49).

4-5

5.0 DATA EVALUATION AND DISCUSSION Introduction Each year the results of the annual Radiological Environmental Monitoring Program (REMP) are evaluated considering plant operations at the site, the natural processes in the environment, and the archive of historical environmental 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. The report not only presents the data collected during the 2016 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 detection.

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.

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.

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

which is one millionth (0.000001) of a curie, and the picocurie (pCi), which is one trillionth (0.000000000001) of a curie. The picocurie (pCi) is the unit of radiation that is routinely used in this report.

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 as 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 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.

5-1

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.

Discussion In the United States, a persons 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).

5-2

There are three separate groups of radionuclides that were measured and analyzed for in the 2016 environmental 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 earths 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:

• Beryllium-7, present as a result of the interaction of cosmic radiation with the upper atmosphere

• Potassium-40 and Radium-226, naturally occurring radionuclides found in the human body and throughout the environment Beryllium-7 and Potassium-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 earths atmosphere. Atmospheric nuclear testing during the early 1950s 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 Peoples 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 peak 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 and Strontium-90. The highest weapons testing concentrations were noted in samples 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.

5-3

3. The third group consists 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, the same as those produced in atmospheric weapons testing, are found in the Chernobyl and Fukushima Daiichi Nuclear Power Station fallout. This commonality makes a determination of the source of these radionuclides, which may be detected in environmental samples, difficult. During 2016, there were no plant-related radionuclides detected in the REMP sampling.

A number of factors must be considered in performing radiological sample data evaluation and interpretation. The evaluation is made using several approaches including trend analysis and dose to man. An attempt has been made not only to report the data collected during 2016, 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 mans 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 1 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 50 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 Th-232). A dose of 50 mrem per year, as a background dose, is significantly greater than any possible doses as a result of routine operations at the site during 2016.

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

• Maintain the analytical data base established when the plants began commercial operation 5-4

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 2016 program.

Section 7.0, titled Historical Data Tables, 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.

5-5

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

• Shoreline Sediment

• Fish

• Surface Waters Section 6.0, Tables 6-1 through 6-4 present the analytical results for the aquatic samples collected for the 2016 sampling period.

5.1.1 SHORELINE SEDIMENT RESULTS A. Results Summary Shoreline sediment samples were obtained in April and October of 2016 at one offsite control location (Langs 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 2016 sample program, two indicator and two control. Cs-137 was not detected in samples collected from the Sunset Bay indicator location or the Langs Beach control location during 2016. No plant-related radionuclides were detected in the 2016 shoreline sediment samples.

The following is a graph of the average Cs-137 concentration in shoreline sediment samples over 20 years. This graph illustrates a general downward trend in the Cs-137 concentrations since 1995. No Cs-137 has been detected in shoreline sediment samples since 2007.

5-6

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 (Langs Beach). Samples were collected from both the indicator and control locations in April and October 2016. The results of these sample collections are presented in Section 6.0, Table 6-1, Concentrations of Gamma Emitters in Shoreline Sediment Samples - 2016. Potassium-40 (K-40) and Radium-226 (Ra-226), Thorium-228 (Th-228) and Thorium-232 (Th-232) all naturally-occurring isotopes, were the only radionuclides detected in the sediment samples.

C. Dose Evaluation The calculated potential whole body and skin doses 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 were used in calculating the dose to man:

• A teenager spends 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> 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 2016 LLD concentration of <0.084 pCi/g (dry).

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 50 (this was different in previous years) mrem as measured by control TLDs in the vicinity of the site.

5-7

D. Data Trends Cs-137 was not detected at the indicator and control sample locations from 2008 through 2016.

The general absence of Cs-137 in the indicator and control samples can be attributed to changing lake levels 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 shoreline samples collected in the past.

Cs-137 is commonly found in soil samples and is attributed to weapons testing fallout.

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 maximum concentration at the indicator locations was 0.04 pCi/g (dry) in 2007. Cs-137 was not detected at the indicator location for 2008 through 2016. This continues to support the long term decreasing trend in Cs-137 concentration in shoreline sediment samples. Cs-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 and 7-2 illustrate historical environmental data for shoreline sediment samples.

5-8

5.1.2 FISH SAMPLE RESULTS A. Results Summary A total of 18 fish samples were collected for the 2016 sample program. The analytical results for the 2016 fish samples showed no detectable concentration of radionuclide that would be attributable to plant operations at the site or past atmospheric weapons testing. Since 2002, no Cs-137 has been measured in fish samples. Over the previous 20 years prior to 2003, Cs-137 has been detected at a combination of 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 2016 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 2016 results are consistent with previous years results in that they continue to support the general long-term downward trend in fish Cs-137 concentrations over the last 25 years. Cs-137 was not detected in fish samples collected from 2003 to 2016 at indicator locations.

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 shows individual results for all the samples collected in 2016 in units of pCi/g (wet).

The spring fish collection was made up of 9 individual samples representing three separate species. Brown Trout, Smallmouth Bass, and Walleye were collected.

The fall fish collection was comprised of 9 individual samples representing three individual species. Chinook Salmon, Smallmouth Bass and Walleye were collected.

Due to the inability to gill net walleye a second independent sample of Chinook Salmon was used. Results recorded in Table 6-2 labeled sample results as Chinook Salmon1 and Chinook Salmon2.

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. The lack of detectable concentrations of plant-related radionuclides in the 2016 fish samples demonstrates that there is no dose to man attributable from operations at the site through the aquatic pathway. 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.

5-9

D. Data Trends The positive detection of Cs-137 in fish samples ceased in 2003. The graph below illustrates the mean control and indicator Cs-137 concentrations for 2016 and the previous fourteen years.

The general long-term decreasing trend for Cs-137, illustrated in the graph below, 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.

The data trend shows a consistent level of Cs-137 measured in fish between 1997 and 1998. After 1998, the number of positive detections drops off as noted in the five year trend. The 1995 through 2016 results, as a group, are the lowest Cs-137 concentrations measured over the existence of the sample program.

5 - 10

Section 7.0, Tables 7-3 and 7-4 show 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 Steam 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 NMP1 Intake and the 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 2016 Sampling Program. 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 2016 REMP program. The results for the 2016 samples showed no positive detection of tritium above 500 pCi/L.

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 2016 samples. This is consistent with historical data, which has not shown the presence of plant-related radionuclides in surface water samples.

The tritium results for the JAFNPP inlet canal samples contained no positive detections.

The 2016 results had LLD values that ranged from <336 pCi/l to <477 pCi/l. The ODCM Control location (Oswego Steam Station inlet canal) results showed no positive detections and the sample results had LLD values in the range of <191 pCi/l to <473 pCi/l.

Tritium was not detected in any of the twelve optional Lake Ontario samples collected in the 2016 program.

The Oswego City Water Supply 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 upstream direction based on the current patterns in the lake.

The following is a summary of LLD results for the 2016 sample program:

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

JAF Inlet (Indicator)* <336 <477 <399 Oswego Steam Inlet (Control)* <191 <473 <363 NMP #1 Inlet <190 <474 <360 NMP #2 Inlet <188 <464 <359 Oswego City Water Supply <186 <471 <358

• Sample location required by ODCM The above LLD values are below the ODCM required LLD value of 3000 pCi/l.

Analytical results for surface water samples are found in Section 6.0, Tables 6-3 through 6-4.

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 a maximum LLD concentration of <477 pCi/l, the calculated dose would be less than 0.049 mrem per year to the child whole body and less than 0.049 mrem per year to the child liver (critical age group/organ).

5 - 12

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 2016 lake water samples were consistent with results from the previous five years for both the indicator and control locations. The mean 2016 tritium concentrations were <363 pCi/l for the control and <399 pCi/l for the indicator location.

For the previous five years, there were no positive detections for the indicator and control locations. 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, 2007 through 2016, tritium concentrations show no detectable levels of tritium measured. The 1999 mean control value of 365 pCi/l is the highest concentration measured since 1987 and is within the variability of results measured over the life of the program.

The following graph illustrates the concentrations of tritium measured in Lake Ontario over the previous 20 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 Steam Station, the current control location. There is no existing preoperational data for comparison to recent data.

Historical data for Surface Water Tritium is presented in Section 7.0, Tables 7-7 and 7-8 5 - 13

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

• Food Products Section 6.0, Tables 6-5 through 6-12 present the analytical results for the terrestrial samples collected for the 2016 reporting period.

5.2.1 AIR PARTICULATE GROSS BETA A. Results Summary Weekly air samples were collected and analyzed for particulate gross beta activity. For the 2016 program, a total of 53 samples were collected from control location R5 and 212 samples were collected from indicator locations R1, R2, R3, and R4. 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 (R5) in 2016 was 0.014 pCi/m3. The mean gross beta concentration for the samples collected from the indicator locations (R1, R2, R3, and R4) in 2016 was 0.015 pCi/m3. 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 from plant effluents.

B. Data Evaluation and Discussion The air monitoring system consists of fifteen sample locations, six onsite and nine offsite.

Each location is sampled weekly for particulate gross beta activity. A total of 795 samples were collected and analyzed as part of the 2016 program. In addition, optional offsite and onsite air sample locations are maintained from which weekly samples are collected. The optional offsite locations are designated as D2, E, F and G.

The optional onsite locations are designated as D1, G, H, I, J and K.

5 - 14

Gross beta analysis requires that the samples be counted no sooner than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 and 6-6 present the weekly gross beta activity results for samples collected from the offsite and onsite locations.

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

Concentration pCi/m3 Location Minimum Maximum Mean R1 0.008 0.023 0.015 R2 0.008 0.024 0.015 R3 0.009 0.022 0.015 R4 0.008 0.025 0.015 R5 (control) 0.008 0.022 0.014 5 - 15

The mean weekly gross beta concentrations measured in 2016 are illustrated in the following graphs:

5 - 16

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 concentration measured in 1969 to 2016 are illustrated in the following graph:

5 - 17

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 2007 through 2016 is very small. This is illustrated by the following graph.

Air Particulate Filter - Gross Beta 0.030 0.025 INDICATOR CONTROL 0.020 pCi/m3 0.015 0.010 0.005 0.000 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 The mean annual gross beta concentration at the control station (R5) has remained steady with a narrow range of 0.014 pCi/m3 to 0.018 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 of 0.015 pCi/m3 to a maximum mean of 0.018 pCi/m3 in 2011.

Historical data of air particulate gross beta activity are presented in Section 7.0, Tables 7-9 and 7-10.

5.2.2 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 and are located offsite near the site boundary and offsite 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 fifteen air monitoring stations maintained around the Nine Mile Point Site provide 795 individual air particulate samples which are assembled by location into 60 quarterly composite samples. The quarterly composites are analyzed using gamma spectroscopy.

5 - 18

No plant-related gamma emitting radionuclides were detected in any of the air particulate filter samples collected during 2016.

The gamma analysis results for the quarterly composite samples routinely showed positive detections of Be-7 and K-40. Both of these radionuclides are naturally occurring.

B. Data Evaluation Discussion A total of fifteen air sampling stations are in continuous operation and located both onsite and in the offsite sectors surrounding the Nine Mile Point Site. 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 R1, R2, R3, R4 and R5. Other sample locations not required by the ODCM, for which analytical results have been provided, include six onsite locations and four offsite locations. The analytical results for the 60 air particulate filter composites in 2016 showed no detectable activity of plant related radionuclides.

The results of the quarterly composite samples are presented in Section 6.0, Table 6-9.

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 2016. The monthly air particulate sampling program demonstrated no offsite dose to man from this pathway as a result of operations of the plants located at the Nine Mile Point Site (NMP).

D. Data Trends No plant related radionuclides were detected during 2016 at the offsite 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 offsite 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 no subsequent measurable concentrations of Co-60 in the environment surrounding the NMP site.

5 - 19

Historical data shows that 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 NMP site.

Historical data for air particulate results are presented in Section 7.0, Tables 7-11 and 7-12.

5.2.3 AIRBORNE RADIOIODINE (I-131)

A. Results Summary Iodine-131 was not detected in any of the 795 samples analyzed for the 2016 program.

B. Data Evaluation and Discussion Airborne radioiodine (I-131) is monitored at the fifteen air sampling stations also used to collect air particulate samples. There are five offsite locations, required by the ODCM. Ten air sampling locations are also maintained in addition to those required by the ODCM. Six of these stations D1, G, H, I, J and K are located onsite. D2, E, F and G are the optional stations located offsite. Samples are collected using activated charcoal cartridges. They are analyzed weekly for I-131.

The analytical data for radioiodine are presented in Section 6.0, Tables 6-7 and 6-8.

C. Dose Evaluation The calculated dose as a result of I-131 in plant effluents is not evaluated due to the fact that no I-131 was detected in 2016. The I-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.

5 - 20

D. Data Trends There was no I-131 detected in any of the samples, collected from the 15 sample stations, for 2012 through 2016.

In 2011, I-131 was detected at all 15 sampling locations over a three week period. The positive detections were the result of the Fukushima event. Prior to then, there had been no positive detection of I-131 in air samples collected from 2002 to 2010.

I-131 has previously been detected in samples collected in 1986 and 1987. The 1986 detection of I-131 was the result of the Chernobyl accident and the 1987 detection was the result of plant operations.

I-131 has been detected in the past at control locations. Control samples collected during 1976 had a mean I-131 concentration of 0.60 pCi/m3. During 1977 this mean decreased to 0.32 pCi/m3, and further decreased by a factor of ten to 0.03 pCi/m3 in 1978. I-131 was not detected in samples collected from the control location during 1979 - 1981 and 1983 to 1985. I-131 was detected once at the control location during 1982 at a concentration of 0.039 pCi/m3.

Historical data for I-131 are presented in Section 7.0, Tables 7-13 and 7-14.

5 - 21

5.2.4 DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS (TLD)

A. Results Summary Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the environment. As part of the 2016 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 2016. 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:

• Onsite (areas within the site boundary, includes TLD #s 3, 4, 5, 6, 7, 23, 24, 25, 26; TLD #s 18, 27, 28, 29, 30, 31, 39, 47, 103, 106, 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 building direct shine, includes TLD #s 7, 18, 78, 79, 80, 81, 82, 83, 84; TLD #s: 23, 75, 76, 77, 85, 86, 87 are excluded)

• Offsite Sector (area four to five miles from the site in each of the eight land based meteorological sectors, includes TLD #s: 88, 89, 90, 91, 92, 93, 94, 95)

• Special Interest (areas of high population density, includes TLD #s 15, 56, 58, 96, 97)

• Control (areas beyond significant influence of the site, includes TLD #s 8, 14, 49)

All geographical locations are required by the ODCM with the exception of the Onsite area which was optional. Description of the five geographical categories and the designation of specific TLD locations that make up each category is presented in Section 3.1.5, TLD (Direct Radiation) of this report.

A summary of the 2016 dose rates for each of the five geographical locations is as follows:

Dose in mrem per standard month Geographic Category Min Max Mean Onsite (Optional) 3.5 11.3 4.8 Site Boundary (Inner Ring)

• 3.5 4.8 4.0 Offsite Sectors (Outer Ring)

• 3.3 4.6 3.9 Special Interest

• 3.5 4.4 3.9 Control

• 3.6 5.2 4.2

• Geographical locations required by the ODCM 5 - 22

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, Offsite Sectors and Special Interest (Offsite) were well within expected normal variation when compared to the Control TLD results.

The results for the 2016 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 system and the Independent Spent Fuel Storage Installation (ISFSI) in use at the FitzPatrick plant and NMPNS 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 2016, 32 of which are required by ODCM. These locations are grouped into five geographical location categories for evaluation of results. The five categories include: Onsite, Site Boundary, Offsite Sector, Special Interest and Control locations. All categories are required by the ODCM with the exception of the Onsite TLDs. Onsite TLDs are placed at various locations within the site boundary to provide additional information on direct radiation levels at and around the NMP1, NMP2 and JAFNPP facilities.

Onsite TLD result results ranged from 3.5 to 11.3 mrem per standard month resulting in an average dose rate of 4.8 mrem per standard month in 2016.

The highest dose rate measured at a location required by the ODCM was 8.2 mrem per standard month. This TLD, (TLD 87) represents the site boundary maximum dose and is located in the NNW sector along the lakeshore close to the plants (TLD #s: 23, 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.

Offsite 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 3.3 to 4.6 mrem per standard month with an average dosed rate of 3.9 mrem per standard month.

Special Interest TLDs from all locations ranged from 3.5 to 4.4 mrem per standard month with an average dose rate of 3.9 mrem per standard month.

5 - 23

The Control TLD group required by the ODCM utilized locations positioned well beyond the site. 2016 Control TLD results ranged from 3.6 to 5.2 mrem per standard month with an annual average dose rate of 4.2 mrem standard month.

TLD analysis results are presented in Section 6.0, Table 6-10.

C. Dose Evaluation 2016 annual mean dose rates for each geographic location required by the ODCM (excluding TLD #s: 23, 75, 76, 77, 85, 86, 87) are as follows:

Site Boundary: 4.0 mrem per standard month (TLD #s: 7,18, 78, 79, 80, 81, 82, 83, 84)

Offsite Sectors: 3.9 mrem per standard month (TLD #s: 88, 89, 90, 91, 92, 93, 94, 95)

Special Interest: 3.9 mrem per standard month (TLD #s: 15, 56, 58, 96, 97)

Control: 4.2 mrem per standard month (TLD #s: 8, 14, 49)

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 4.2 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 offsite 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 offsite 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, Offsite Sector and Special Interest TLD locations became effective in 1985; therefore, trends for these results can only be evaluated from 1985 to the present.

5 - 24

The following graph illustrates TLD results for the Control, Site Boundary, Offsite Sectors and Special Interest groups from 2000 through 2016:

The 2016 TLD program results, when compared to the previous ten years, showed no significant trends relative to increased dose rates in the environment.

Historical data for the various TLD groupings are presented in Section 7.0, Tables 7-15 through 7-20.

5 - 25

5.2.5 MILK A. Results Summary A total of 36 milk samples were collected during the 2016 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).

I-131, a possible plant related radionuclide, is measured to evaluate the cow milk dose pathway to man. I-131 was not detected in any of the 36 milk samples collected in 2016 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 2016.

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 2016 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 milk animal census, there were no adequate milk sample locations within five miles of the site in 2016. Samples were collected from two farms located beyond the five-mile requirement to ensure the continued monitoring of this important pathway. The indicator location was located 8.7 miles 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 8.7 77 (Control) S 16.0 Indicator location #55 and Control location #77 were sampled 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 2016 due to I-131 not having been detected in samples collected during November and December of 2015, as stipulated in the ODCM.

5 - 26

C. Data Evaluation and Discussion Each milk sample is analyzed for gamma emitters using gamma spectral analysis. The I-131 analysis is performed using resin extraction followed by spectral analysis for each sample. I-131 and gamma analysis results for milk samples collected during 2016 are provided in Section 6.0, Table 6-11.

Iodine-131 was not detected in any indicator or control milk samples analyzed during 2016. 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 2016. 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 2016.

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 thirty years, Cs-137 was only detected in 1986, 1987, and 1988. The mean Cs-137 indicator activities for those years were 8.6, 7.4 and 10.0 pCi/liter, respectively. I-131 was measured in two milk samples collected in 1997 from a single sample location, having a mean concentration of 0.35 pCi/liter and was of undetermined origin. The previous detection was in 1986 with a mean concentration of 13.6 pCi/liter. The 1986 activity was a result of the Chernobyl accident.

The comparison of 2016 data to historical results over the operating life of the plants shows that Cs-137 and I-131 levels in milk dropped to less than the lower limit of detection since 1988.

Historical data of milk sample results for Cs-137 and I-131 are presented in Section 7.0, Tables 7-21 and 7-22.

5 - 27

5.2.6 FOOD PRODUCTS (VEGETATION)

A. Results Summary There were no plant-related radionuclides detected in the nine food product samples collected and analyzed for the 2016 program.

Detectable levels of naturally occurring K-40 were measured in all of the indicator and control samples collected for the 2016 program. Be-7 and Th-228 both naturally-occurring radionuclides, were also detected intermittently in samples collected in 2016.

These results are consistent with the levels measured in 2015 and previous years.

The results of the 2016 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 two 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 15.4 miles away in a predominately upwind direction.

Food product samples collected during 2016 included both edible and nonedible vegetation. Nonedible samples include: grape leaves, horseradish leaves, rhubarb leaves, squash leaves and pumpkin leaves. The edible vegetation used in this years sampling was cabbage. 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 2016 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, K-40 and Th-228 were detected in food product samples.

The results for naturally-occurring radionuclides are consistent with the data of prior years.

Analytical results for food products are found in Section 6.0, Table 6-12.

5 - 28

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 offsite dose to man from this pathway as a result of operations of the plants located at Nine Mile Point.

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 0.007 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 1980. The trend for Cs-137 is a general reduction in concentration to non detectable levels in samples collected during the 2000 through 2016 sample programs.

Historical data of food product results are presented in Section 7.0, Tables 7-23 and 7-24.

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 2016 a milk animal census, a nearest resident census, and a garden census were performed.

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. This census, covering areas out to a distance of 10 miles exceeds the 5 mile distance required by the ODCM.

A total of 225 milk cows and 167 heifers were observed. Additionally approximately 30 goats were counted at one location during the survey. Attempts to contact the land owner were made by phone, post card and visitation but no response was received. The milking/non-milking status of these approximately 30 goats is currently unknown. There are no farms with milking animals with the 5 mile radius of the site.

5 - 29

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 survey for 2016 found new construction located in the South Sector at 294 Miner Road, Lycoming, New York. The location was determined to be 1.57 miles away from the center of the JAF Reactor Building at the 179 degree line. The new location is closer than the previously used 268 Miner Road address, which was 1.59 miles away at the 173 degree line. The results of the nearest residence census, showing the applicable sectors and direction and distance of each of the nearest residence, are found in Section 6.0, Table 6-14. There was 1 change identified in the 2016 census.

A new residence was found in the S meteorological sector and it has been added to the residence census table. The nearest resident locations are illustrated in Section 3.3, Figure 3.3-5.

The results of the nearest residence census conducted in 2016 required no change to FitzPatrick ODCMs closest resident location.

A garden census, not required by the ODCM, is performed to identify appropriate garden sampling locations and dose calculation receptors. The 2016 garden census identified a total of 63 gardens for consideration for the sampling program. Garden samples were collected from two locations (144 and 484) as well as a control location (C2) identified in census as active for 2016. See Table 3.3-1 for 2016 sampling locations.

5 - 30

5.2.8 DIRECT RADIATION, THERMOLUMINESCENT DOSIMETERS (TLD)

Independent Spent Fuel Storage Installation (ISFSI)

A. Results Summary Thermoluminescent Dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the localized environment of the ISFSI pad. Eighteen TLD locations are in place around the perimeter of the ISFSI pad. TLDs were placed at these locations prior to loading the first storage casks for baseline dose rate determination in the general area of the pad.

As of the last ISFSI Campaign which ended in the fourth quarter of 2013 there are a total of 21 cask stored at the facility.

The increase in dose rate is limited to the general area of the storage facility. 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 2016 environmental TLD monitoring program indicate that there is no significant increase in dose rates as a result of operations at the site. The use of hydrogen injection and the implementation of the Independent Spent Fuel Storage Installation (ISFSI) at the FitzPatrick 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 CFR 72.104(a).

The measured results of the 2016 TLD monitoring program demonstrate compliance with the offsite dose limits to members of the public specified in 40 CFR 190 and 10 CFR 72.104(a).

5 - 31

B. Program Design An array of eight TLD locations was established around the perimeter of the ISFSI pad 18 months prior to facility usage. Six months prior to the facility becoming operational, an additional 10 TLD locations were established at areas of interest on the facility perimeter. These preoperational TLDs were used for baseline dose rate determination.

The TLDs 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 A maximum dose rate of 50.7 mrem per standard month above the baseline dose rate was measured at the north perimeter fence. The lowest measured dose rate of 2016 was 12.2 mrem per standard month above the baseline dose rate and was measured at the east perimeter fence.

An evaluation of Site Boundary TLDs and Control TLDs results for 2016 shows that there is no increase in dose rate at or beyond the site boundary. 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 2015.

2016 DOSE IN MREM PER STANDARD MONTH Minimum Maximum Mean Site Boundary 3.5 4.8 4.0 Control 3.6 5.2 4.2 5 - 32

5.3 CONCLUSION

The Radiological Environmental Monitoring Program (REMP) is an ongoing program implemented to measure and document the radiological impact of JAFNPP 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-term 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 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 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 and ISFSI programs. 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 the Fukushima Daiichi Nuclear Power Station.

The REMP did not detect any plant-related radionuclide in the sample media collected during 2016. 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 50 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 2016 Radiological Environmental Monitoring Program, it can be concluded that the levels and variation of radioactivity in the environment samples were consistent with background levels. Effluents from the site to the environment contribute no significant or even measurable radiation exposures to the general public.

5 - 33

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, Ill., 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.

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 2011.

5 - 34

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 "real" 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 - 2016 Results in Units of pCi/kg (dry) +/- 1 Sigma SAMPLE COLLECTION K-40 Co-60 Zn-65 Cs-134 Cs-137 Others LOCATION*** DATE Sunset Bay (05)

• 04/18/16 18390 +/- 992 < 66 < 155 < 70 < 84 <LLD 10/14/16 17460 +/- 778 < 56 < 157 < 64 < 74 <LLD MEAN 17925 +/- 658 Lang's Beach (06 Control) 04/18/16 10250 +/- 645 < 66 < 135 < 62 < 64 <LLD 10/14/16 9007 +/- 470 < 35 < 88 < 35 < 36 <LLD MEAN 9629 +/- 879

• Sample required by the ODCM

• • • Corresponds to sample location noted on Figure 3.3-5 Plant related radionuclides 6-2

TABLE 6-2 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2016 Results in Units of pCi/kg (wet) +/- 1 Sigma SAMPLE COLLECTION DESCRIPTION K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Others LOCATION*** DATE FITZPATRICK * (03)***

05/11/16 Walleye 2996 +/- 177 < 17 < 18 < 37 < 19 < 40 < 16 < 20 <LLD 05/11/16 Brown Trout 3291 +/- 241 < 40 < 38 < 79 < 41 < 95 < 46 < 42 <LLD 05/11/16 Smallmouth Bass 3534 +/- 170 < 18 < 18 < 32 < 18 < 40 < 18 < 18 <LLD 09/13/16 Walleye 3398 +/- 506 < 54 < 63 < 151 < 60 < 151 < 56 < 67 <LLD 09/13/16 Chinook Salmon 3434 +/- 427 < 41 < 53 < 112 < 36 < 117 < 50 < 44 <LLD 09/20/16 Smallmouth Bass 4029 +/- 349 < 35 < 38 < 95 < 27 < 77 < 36 < 36 <LLD NINE MILE POINT * (02)***

05/11/16 Walleye 3566 +/- 247 < 31 < 27 < 66 < 30 < 62 < 27 < 35 <LLD 05/11/16 Brown Trout 3963 +/- 189 < 22 < 23 < 46 < 22 < 53 < 23 < 24 <LLD 05/11/16 Smallmouth Bass 4118 +/- 225 < 24 < 26 < 47 < 20 < 49 < 23 < 25 <LLD 09/13/16 Walleye 2973 +/- 317 < 31 < 37 < 81 < 28 < 67 < 29 < 41 <LLD 09/13/16 Chinook Salmon 3791 +/- 528 < 61 < 51 < 126 < 68 < 149 < 51 < 55 <LLD 09/13/16 Smallmouth Bass 3813 +/- 562 < 63 < 77 < 104 < 70 < 154 < 68 < 78 <LLD OSWEGO HARBOR (CONTROL) * (00)***

05/11/16 Walleye 4048 +/- 209 < 22 < 20 < 43 < 23 < 37 < 19 < 21 <LLD 05/11/16 Brown Trout 4021 +/- 165 < 18 < 16 < 35 < 17 < 38 < 17 < 20 <LLD 05/12/16 Smallmouth Bass 2913 +/- 225 < 33 < 32 < 63 < 32 < 72 < 32 < 34 <LLD 09/13/16 Chinook Salmon¹ 3547 +/- 337 < 41 < 37 < 84 < 43 < 100 < 35 < 52 <LLD 09/13/16 Chinook Salmon² 3545 +/- 583 < 73 < 84 < 170 < 85 < 155 < 62 < 81 <LLD 09/13/16 Smallmouth Bass 2332 +/- 376 < 46 < 43 < 96 < 51 < 93 < 42 < 51 <LLD

• Sample required by the ODCM

• • • Corresponds to sample location noted on Figure 3.3-5 Plant related radionuclides 6-3

TABLE 6-3 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES - 2016 Results in Units of pCi/liter +/- 1 Sigma SAMPLE COLLECTION DESCRIPTION H-3 LOCATION*** DATE FITZPATRICK * (03, INLET) 12/29/15 - 03/29/16 First Quarter < 336 03/29/16 - 06/30/16 Second Quarter < 344 06/30/16 - 09/29/16 Third Quarter < 477 09/29/16 - 01/03/17 Fourth Quarter < 438 OSWEGO STEAM STATION* (08, CONTROL) 12/31/15 - 04/01/16 First Quarter < 382 04/01/16 - 07/01/16 Second Quarter < 191 07/01/16 - 09/30/16 Third Quarter < 473 09/30/16 - 12/30/16 Fourth Quarter < 404 NINE MILE POINT UNIT 1** (09, INLET) 12/31/15 - 04/01/16 First Quarter < 380 04/01/16 - 07/01/16 Second Quarter < 190 07/01/16 - 09/30/16 Third Quarter < 474 09/30/16 - 12/30/16 Fourth Quarter < 396 OSWEGO CITY WATER** (10) 12/31/15 - 04/01/16 First Quarter < 382 04/01/16 - 07/01/16 Second Quarter < 186 07/01/16 - 09/30/16 Third Quarter < 471 09/30/16 - 12/30/16 Fourth Quarter < 394 NINE MILE POINT UNIT 2** (11, INLET) 12/31/15 - 04/01/16 First Quarter < 386 04/01/16 - 07/01/16 Second Quarter < 188 07/01/16 - 09/30/16 Third Quarter < 464 09/30/16 - 12/30/16 Fourth Quarter < 397

• Sample required by the ODCM

• • Optional sample location

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

TABLE 6-4 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2016 Results in Units of pCi/liter +/- 1 Sigma SAMPLE COLLECTION I-131 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-La-140 LOCATION DATE FITZPATRICK* (03, INLET)***

01/28/16 < 0.9 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 6 02/26/16 < 0.5 < 2 < 2 < 4 < 1 < 3 < 2 < 3 < 2 < 2 < 5 03/29/16 < 0.9 < 1 < 2 < 4 < 1 < 3 < 2 < 3 < 1 < 1 < 6 04/27/16 < 0.5 < 4 < 4 < 9 < 4 < 8 < 4 < 6 < 3 < 3 < 9 05/31/16 < 0.1 < 1 < 2 < 4 < 1 < 3 < 2 < 3 < 1 < 1 < 6 06/30/16 < 0.6 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 1 < 2 < 6 07/28/16 < 0.5 < 1 < 2 < 4 < 1 < 3 < 2 < 3 < 1 < 1 < 5 08/29/16 < 0.7 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 5 09/29/16 < 0.7 < 1 < 2 < 4 < 1 < 3 < 2 < 3 < 1 < 1 < 5 10/26/16 < 0.8 < 2 < 3 < 6 < 2 < 5 < 3 < 5 < 2 < 3 < 8 11/28/16 < 0.2 < 3 < 3 < 7 < 3 < 6 < 3 < 5 < 2 < 3 < 9 01/03/17 < 0.4 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 7 OSWEGO STEAM STATION* (08 CONTROL)***

01/29/16 < 0.8 < 2 < 2 < 4 < 2 < 3 < 2 < 4 < 2 < 2 < 7 02/26/16 < 0.5 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 5 04/01/16 < 0.5 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 5 04/29/16 < 0.7 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 1 < 2 < 7 06/03/16 < 0.5 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 6 07/01/16 < 0.4 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 7 07/29/16 < 0.7 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 6 09/02/16 < 0.6 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 5 09/30/16 < 0.6 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 1 < 2 < 6 10/28/16 < 0.6 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 6 12/02/16 < 1.0 < 2 < 2 < 4 < 2 < 3 < 2 < 4 < 2 < 2 < 6 12/30/16 < 0.5 < 1 < 2 < 4 < 1 < 3 < 2 < 3 < 1 < 1 < 4

• Sample required by the ODCM

• • • Corresponds to sample location noted on Figure 3.3-4 6-5

TABLE 6-4 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2016 Results in Units of pCi/liter +/- 1 Sigma SAMPLE COLLECTION I-131 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-La-140 LOCATION DATE NINE MILE POINT UNIT 1 (09, INLET)***

01/29/16 < 10 < 1 < 2 < 4 < 1 < 3 < 2 < 3 < 1 < 1 < 6 02/26/16 < 12 < 1 < 2 < 3 < 1 < 3 < 2 < 3 < 1 < 1 < 6 04/01/16 < 7 < 1 < 1 < 2 < 1 < 1 < 1 < 1 < 1 < 1 < 3 04/29/16 < 14 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 7 06/03/16 < 15 < 2 < 3 < 7 < 3 < 5 < 3 < 5 < 2 < 2 < 10 07/01/16 < 11 < 1 < 2 < 4 < 1 < 3 < 2 < 3 < 1 < 1 < 6 07/29/16 < 13 < 2 < 2 < 6 < 2 < 5 < 3 < 5 < 2 < 2 < 8 09/02/16 < 13 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 5 09/30/16 < 13 < 1 < 2 < 4 < 2 < 3 < 2 < 3 < 1 < 1 < 6 10/28/16 < 12 < 2 < 3 < 6 < 2 < 5 < 3 < 5 < 2 < 2 < 7 12/02/16 < 10 < 1 < 1 < 3 < 1 < 2 < 2 < 3 < 1 < 1 < 5 12/30/16 < 11 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 6 OSWEGO CITY WATER (10)***

01/29/16 < 12 < 1 < 2 < 4 < 2 < 3 < 2 < 3 < 1 < 2 < 6 02/26/16 < 10 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 4 04/01/16 < 10 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 4 04/29/16 < 14 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 6 06/03/16 < 13 < 2 < 2 < 4 < 1 < 3 < 2 < 4 < 2 < 2 < 5 07/01/16 < 14 < 2 < 2 < 6 < 2 < 4 < 2 < 4 < 2 < 2 < 7 07/29/16 < 9 < 2 < 2 < 4 < 2 < 4 < 2 < 4 < 2 < 2 < 5 09/02/16 < 14 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 6 09/30/16 < 14 < 1 < 2 < 4 < 2 < 3 < 2 < 3 < 1 < 2 < 7 10/28/16 < 9 < 1 < 2 < 4 < 2 < 3 < 2 < 3 < 1 < 2 < 5 12/02/16 < 14 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 8 12/30/16 < 10 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 6

• Sample required by the ODCM

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

TABLE 6-4 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2016 Results in Units of pCi/liter +/- 1 Sigma SAMPLE COLLECTION I-131 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-La-140 LOCATION DATE NINE MILE POINT UNIT 2* (11, INLET)***

01/29/16 < 13 < 2 < 2 < 4 < 1 < 3 < 2 < 3 < 1 < 2 < 6 02/26/16 < 11 < 1 < 2 < 3 < 1 < 3 < 2 < 2 < 1 < 1 < 5 04/01/16 < 12 < 1 < 1 < 2 < 1 < 2 < 1 < 2 < 1 < 1 < 4 04/29/16 < 13 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 7 06/03/16 < 13 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 7 07/01/16 < 15 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 1 < 2 < 6 07/29/16 < 12 < 2 < 3 < 7 < 2 < 5 < 3 < 5 < 2 < 2 < 8 09/02/16 < 15 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 5 09/30/16 < 15 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 7 10/28/16 < 12 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 7 12/02/16 < 14 < 2 < 2 < 4 < 2 < 4 < 2 < 4 < 2 < 2 < 6 12/30/16 < 8 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 5

• Sample required by the ODCM

• • • Corresponds to sample location noted on Figure 3.3-4 6-7

TABLE 6-5 ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFFSITE SAMPLE LOCATIONS - 2016 GROSS BETA ACTIVITY 10E-3 pCi/m3 +/- 1 Sigma COLLECTION DATE R1* R2* R3* R4* R5* D2** E** F** G**

12/29/15 - 01/05/16 18 +/- 1 20 +/- 1 21 +/- 1 22 +/- 1 21 +/- 1 19 +/- 1 19 +/- 1 17 +/- 1 21 +/- 1 01/05/16 - 01/12/16 15 +/- 1 16 +/- 1 16 +/- 1 16 +/- 1 17 +/- 1 20 +/- 1 17 +/- 1 17 +/- 1 17 +/- 1 01/12/16 - 01/19/16 22 +/- 1 23 +/- 1 17 +/- 1 20 +/- 1 17 +/- 1 15 +/- 1 18 +/- 1 17 +/- 1 19 +/- 1 01/19/16 - 01/26/16 13 +/- 1 13 +/- 1 12 +/- 1 12 +/- 1 11 +/- 1 10 +/- 1 14 +/- 1 15 +/- 1 12 +/- 1 01/26/16 - 02/02/16 17 +/- 1 19 +/- 1 16 +/- 1 20 +/- 1 19 +/- 1 15 +/- 1 19 +/- 1 19 +/- 1 19 +/- 1 02/02/16 - 02/09/16 15 +/- 1 13 +/- 1 14 +/- 1 14 +/- 1 15 +/- 1 15 +/- 1 15 +/- 1 16 +/- 1 15 +/- 1 02/09/16 - 02/17/16 14 +/- 1 11 +/- 1 12 +/- 1 11 +/- 1 13 +/- 1 12 +/- 1 15 +/- 1 13 +/- 1 12 +/- 1 02/17/16 - 02/23/16 14 +/- 1 14 +/- 1 15 +/- 1 15 +/- 1 12 +/- 1 14 +/- 1 14 +/- 1 16 +/- 1 16 +/- 1 02/23/16 - 03/01/16 15 +/- 1 16 +/- 1 15 +/- 1 13 +/- 1 13 +/- 1 13 +/- 1 16 +/- 1 16 +/- 2 13 +/- 1 03/01/16 - 03/08/16 14 +/- 1 15 +/- 1 12 +/- 1 16 +/- 1 12 +/- 1 12 +/- 1 13 +/- 1 9 +/- 1 13 +/- 1 03/08/16 - 03/15/16 13 +/- 1 13 +/- 1 12 +/- 1 13 +/- 1 12 +/- 1 13 +/- 1 13 +/- 1 6 +/- 1 14 +/- 1 03/15/16 - 03/22/16 10 +/- 1 11 +/- 1 9 +/- 1 10 +/- 1 8 +/- 1 10 +/- 1 10 +/- 1 10 +/- 1 10 +/- 1 03/22/16 - 03/29/16 16 +/- 1 (1) 15 +/- 1 14 +/- 1 14 +/- 1 16 +/- 1 16 +/- 1 18 +/- 1 17 +/- 1 03/29/16 - 04/05/16 17 +/- 1 17 +/- 1 14 +/- 1 17 +/- 1 17 +/- 1 20 +/- 1 17 +/- 1 16 +/- 1 14 +/- 1 04/05/16 - 04/12/16 17 +/- 1 17 +/- 1 18 +/- 1 18 +/- 1 19 +/- 1 15 +/- 1 19 +/- 1 19 +/- 1 17 +/- 1 04/12/16 - 04/19/16 19 +/- 1 18 +/- 1 20 +/- 1 22 +/- 1 17 +/- 1 17 +/- 1 20 +/- 1 18 +/- 1 21 +/- 1 04/19/16 - 04/26/16 19 +/- 1 17 +/- 1 18 +/- 1 18 +/- 1 16 +/- 1 18 +/- 1 18 +/- 1 20 +/- 1 19 +/- 1 04/26/16 - 05/03/16 12 +/- 1 12 +/- 1 12 +/- 1 12 +/- 1 11 +/- 1 11 +/- 1 12 +/- 1 13 +/- 1 12 +/- 1 05/03/16 - 05/10/16 8 +/- 1 8 +/- 1 9 +/- 1 8 +/- 1 10 +/- 1 11 +/- 1 9 +/- 1 10 +/- 1 8 +/- 1 05/10/16 - 05/17/16 11 +/- 1 13 +/- 1 16 +/- 1 13 +/- 1 10 +/- 1 12 +/- 1 11 +/- 1 12 +/- 1 13 +/- 1 05/17/16 - 05/24/16 12 +/- 1 15 +/- 1 13 +/- 1 25 +/- 2 15 +/- 1 17 +/- 1 15 +/- 1 16 +/- 1 17 +/- 1 05/24/16 - 06/01/16 23 +/- 1 23 +/- 1 22 +/- 1 21 +/- 1 20 +/- 1 19 +/- 1 20 +/- 1 22 +/- 1 23 +/- 1 06/01/16 - 06/07/16 13 +/- 1 12 +/- 1 9 +/- 1 17 +/- 1 14 +/- 1 11 +/- 1 15 +/- 1 13 +/- 1 13 +/- 1 06/07/16 - 06/14/16 11 +/- 1 9 +/- 1 9 +/- 1 11 +/- 1 11 +/- 1 10 +/- 1 9 +/- 1 11 +/- 1 10 +/- 1 06/14/16 - 06/21/16 10 +/- 1 13 +/- 1 12 +/- 1 12 +/- 1 12 +/- 1 11 +/- 1 13 +/- 1 13 +/- 1 14 +/- 1 06/21/16 - 06/28/16 16 +/- 1 13 +/- 1 13 +/- 1 16 +/- 1 16 +/- 1 17 +/- 1 17 +/- 1 15 +/- 1 16 +/- 1

• Sample required by the ODCM

• • Optional sample location (1)-Sample lost due to equipment failure 6-8

TABLE 6-5 (continued)

ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFFSITE SAMPLE LOCATIONS - 2016 GROSS BETA ACTIVITY 10E-3 pCi/m3 +/- 1 Sigma COLLECTION DATE R1* R2* R3* R4* R5* D2** E** F** G**

06/28/16 - 07/06/16 17 +/- 1 16 +/- 1 14 +/- 1 19 +/- 1 23 +/- 1 17 +/- 1 14 +/- 1 15 +/- 1 13 +/- 1 07/06/16 - 07/12/16 23 +/- 1 24 +/- 2 21 +/- 1 20 +/- 1 19 +/- 1 19 +/- 1 19 +/- 1 18 +/- 1 23 +/- 1 07/12/16 - 07/19/16 16 +/- 1 16 +/- 1 15 +/- 1 14 +/- 1 15 +/- 1 15 +/- 1 16 +/- 1 15 +/- 1 17 +/- 1 07/19/16 - 07/26/16 17 +/- 1 18 +/- 1 17 +/- 1 16 +/- 1 18 +/- 1 14 +/- 1 17 +/- 1 19 +/- 1 17 +/- 1 07/26/16 - 08/02/16 12 +/- 1 13 +/- 1 11 +/- 1 12 +/- 1 12 +/- 1 12 +/- 1 12 +/- 1 12 +/- 1 11 +/- 1 08/02/16 - 08/09/16 13 +/- 1 12 +/- 1 14 +/- 1 13 +/- 1 11 +/- 1 13 +/- 1 11 +/- 1 13 +/- 1 12 +/- 1 08/09/16 - 08/16/16 16 +/- 1 18 +/- 1 16 +/- 1 19 +/- 1 17 +/- 1 20 +/- 1 18 +/- 1 16 +/- 1 17 +/- 1 08/16/16 - 08/23/16 17 +/- 1 17 +/- 1 15 +/- 1 14 +/- 1 12 +/- 1 11 +/- 1 15 +/- 1 14 +/- 1 15 +/- 1 08/23/16 - 08/30/16 15 +/- 1 17 +/- 1 19 +/- 1 18 +/- 1 17 +/- 1 18 +/- 1 15 +/- 1 17 +/- 1 13 +/- 1 08/30/16 - 09/07/16 19 +/- 1 18 +/- 1 14 +/- 1 20 +/- 1 17 +/- 1 17 +/- 1 17 +/- 1 17 +/- 1 18 +/- 1 09/07/16 - 09/13/16 15 +/- 1 16 +/- 1 16 +/- 1 16 +/- 1 14 +/- 1 13 +/- 1 15 +/- 1 16 +/- 1 14 +/- 1 09/13/16 - 09/20/16 17 +/- 1 16 +/- 1 18 +/- 1 15 +/- 1 16 +/- 1 14 +/- 1 14 +/- 1 13 +/- 1 15 +/- 1 09/20/16 - 09/27/16 14 +/- 1 15 +/- 1 14 +/- 1 16 +/- 1 15 +/- 1 14 +/- 1 16 +/- 1 15 +/- 1 13 +/- 1 09/27/16 - 10/04/16 13 +/- 1 11 +/- 1 13 +/- 1 12 +/- 1 11 +/- 1 10 +/- 1 9 +/- 1 11 +/- 1 10 +/- 1 10/04/16 - 10/11/16 16 +/- 1 14 +/- 1 15 +/- 1 16 +/- 1 18 +/- 1 16 +/- 1 18 +/- 1 16 +/- 1 15 +/- 1 10/11/16 - 10/18/16 14 +/- 1 17 +/- 1 16 +/- 1 16 +/- 1 15 +/- 1 15 +/- 1 16 +/- 1 16 +/- 1 19 +/- 2 10/18/16 - 10/25/16 9 +/- 1 10 +/- 1 11 +/- 1 9 +/- 1 11 +/- 1 11 +/- 1 11 +/- 1 12 +/- 1 11 +/- 1 10/25/16 - 11/01/16 14 +/- 2 10 +/- 1 9 +/- 1 13 +/- 1 10 +/- 1 8 +/- 1 7 +/- 1 10 +/- 1 12 +/- 1 11/01/16 - 11/08/16 15 +/- 1 16 +/- 1 16 +/- 1 15 +/- 1 16 +/- 1 16 +/- 1 16 +/- 1 18 +/- 1 16 +/- 1 11/08/16 - 11/15/16 15 +/- 1 13 +/- 1 16 +/- 1 16 +/- 1 14 +/- 1 13 +/- 1 15 +/- 1 16 +/- 1 16 +/- 1 11/15/16 - 11/22/16 20 +/- 1 19 +/- 1 22 +/- 1 22 +/- 1 20 +/- 1 21 +/- 1 21 +/- 1 22 +/- 1 19 +/- 1 11/22/16 - 11/29/16 12 +/- 1 11 +/- 1 10 +/- 1 8 +/- 1 11 +/- 1 9 +/- 1 10 +/- 1 7 +/- 1 11 +/- 1 11/29/16 - 12/06/16 10 +/- 1 8 +/- 1 11 +/- 1 12 +/- 1 10 +/- 1 12 +/- 1 8 +/- 1 11 +/- 1 12 +/- 1 12/06/16 - 12/13/16 14 +/- 1 12 +/- 1 12 +/- 1 11 +/- 1 11 +/- 1 15 +/- 1 11 +/- 1 12 +/- 1 13 +/- 1 12/13/16 - 12/20/16 17 +/- 1 15 +/- 1 19 +/- 1 15 +/- 1 15 +/- 1 14 +/- 1 16 +/- 1 12 +/- 1 19 +/- 1 12/20/16 - 12/28/16 17 +/- 1 17 +/- 1 17 +/- 1 16 +/- 1 16 +/- 1 15 +/- 1 17 +/- 1 15 +/- 1 18 +/- 1 12/28/16 - 01/04/17 12 +/- 1 13 +/- 1 12 +/- 1 13 +/- 1 12 +/- 1 11 +/- 1 11 +/- 1 11 +/- 1 11 +/- 1

• Sample required by the ODCM

• • Optional sample location 6-9

TABLE 6-6 ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ONSITE SAMPLE LOCATIONS - 2016 GROSS BETA ACTIVITY 10E-3 pCi/m3 +/- 1 Sigma COLLECTION DATE D1** G** H** I** J** K**

12/28/15 - 01/04/16 18 +/- 1 22 +/- 1 17 +/- 1 20 +/- 1 19 +/- 1 19 +/- 1 01/04/16 - 01/11/16 14 +/- 1 19 +/- 1 17 +/- 1 18 +/- 1 15 +/- 1 17 +/- 1 01/11/16 - 01/18/16 18 +/- 1 21 +/- 1 18 +/- 1 22 +/- 1 18 +/- 1 19 +/- 1 01/18/16 - 01/25/16 10 +/- 1 11 +/- 1 9 +/- 1 10 +/- 1 13 +/- 1 12 +/- 1 01/25/16 - 02/01/16 18 +/- 1 19 +/- 1 17 +/- 1 19 +/- 1 18 +/- 1 18 +/- 1 02/01/16 - 02/08/16 14 +/- 1 12 +/- 1 15 +/- 1 15 +/- 1 14 +/- 1 17 +/- 1 02/08/16 - 02/15/16 13 +/- 1 14 +/- 1 15 +/- 1 15 +/- 1 15 +/- 1 13 +/- 1 02/15/16 - 02/22/16 15 +/- 1 13 +/- 1 15 +/- 1 15 +/- 1 14 +/- 1 14 +/- 1 02/22/16 - 02/29/16 14 +/- 1 15 +/- 1 12 +/- 1 13 +/- 1 12 +/- 1 10 +/- 1 02/29/16 - 03/07/16 15 +/- 1 16 +/- 1 14 +/- 1 13 +/- 1 13 +/- 1 13 +/- 1 03/07/16 - 03/14/16 17 +/- 1 13 +/- 1 13 +/- 1 14 +/- 1 15 +/- 1 15 +/- 1 03/14/16 - 03/21/16 9 +/- 1 10 +/- 1 10 +/- 1 9 +/- 1 11 +/- 1 13 +/- 1 03/21/16 - 03/28/16 16 +/- 1 17 +/- 1 15 +/- 1 14 +/- 1 17 +/- 1 15 +/- 1 03/28/16 - 04/04/16 16 +/- 1 17 +/- 1 15 +/- 1 15 +/- 1 18 +/- 1 15 +/- 1 04/04/16 - 04/11/16 19 +/- 1 19 +/- 1 18 +/- 1 20 +/- 1 17 +/- 1 19 +/- 1 04/11/16 - 04/18/16 20 +/- 1 21 +/- 1 19 +/- 1 17 +/- 1 20 +/- 1 20 +/- 1 04/18/16 - 04/25/16 19 +/- 1 21 +/- 1 17 +/- 1 19 +/- 1 19 +/- 1 18 +/- 1 04/25/16 - 05/02/16 14 +/- 1 13 +/- 1 13 +/- 1 10 +/- 1 12 +/- 1 13 +/- 1 05/02/16 - 05/09/16 7 +/- 1 8 +/- 1 9 +/- 1 8 +/- 1 8 +/- 1 7 +/- 1 05/09/16 - 05/16/16 14 +/- 1 12 +/- 1 12 +/- 1 13 +/- 1 12 +/- 1 13 +/- 1 05/16/16 - 05/23/16 14 +/- 1 16 +/- 1 23 +/- 1 14 +/- 1 16 +/- 1 14 +/- 1 05/23/16 - 05/31/16 23 +/- 1 26 +/- 1 26 +/- 1 20 +/- 1 23 +/- 1 21 +/- 1 05/31/16 - 06/06/16 13 +/- 1 11 +/- 1 14 +/- 1 14 +/- 1 14 +/- 1 13 +/- 1 06/06/16 - 06/13/16 10 +/- 1 12 +/- 1 10 +/- 1 11 +/- 1 11 +/- 1 10 +/- 1 06/13/16 - 06/20/16 10 +/- 1 13 +/- 1 13 +/- 1 12 +/- 1 12 +/- 1 13 +/- 1 06/20/16 - 06/27/16 17 +/- 1 18 +/- 1 14 +/- 1 16 +/- 1 17 +/- 1 17 +/- 1

• • Optional sample location 6 - 10

TABLE 6-6 (continued)

ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ONSITE SAMPLE LOCATIONS - 2016 GROSS BETA ACTIVITY 10E-3 pCi/m3 +/- 1 Sigma COLLECTION DATE D1** G** H** I** J** K**

06/27/16 - 07/05/16 16 +/- 1 15 +/- 1 14 +/- 1 14 +/- 1 15 +/- 1 14 +/- 1 07/05/16 - 07/11/16 21 +/- 2 21 +/- 1 22 +/- 2 20 +/- 1 20 +/- 2 22 +/- 2 07/11/16 - 07/18/16 15 +/- 1 16 +/- 1 14 +/- 1 18 +/- 1 14 +/- 1 15 +/- 1 07/18/16 - 07/25/16 17 +/- 1 16 +/- 1 18 +/- 1 16 +/- 1 16 +/- 1 16 +/- 1 07/25/16 - 08/01/16 13 +/- 1 15 +/- 1 12 +/- 1 14 +/- 1 14 +/- 1 13 +/- 1 08/01/16 - 08/08/16 14 +/- 1 13 +/- 1 16 +/- 1 14 +/- 1 14 +/- 1 14 +/- 1 08/08/16 - 08/15/16 18 +/- 1 14 +/- 1 18 +/- 1 16 +/- 1 17 +/- 1 17 +/- 1 08/15/16 - 08/22/16 15 +/- 1 16 +/- 1 13 +/- 1 16 +/- 1 16 +/- 1 16 +/- 1 08/22/16 - 08/29/16 17 +/- 1 17 +/- 1 16 +/- 1 16 +/- 1 19 +/- 1 18 +/- 1 08/29/16 - 09/06/16 18 +/- 1 16 +/- 1 16 +/- 1 16 +/- 1 16 +/- 1 14 +/- 1 09/06/16 - 09/12/16 19 +/- 1 18 +/- 1 20 +/- 1 21 +/- 1 17 +/- 1 18 +/- 1 09/12/16 - 09/19/16 13 +/- 1 13 +/- 1 13 +/- 1 12 +/- 1 14 +/- 1 12 +/- 1 09/19/16 - 09/26/16 17 +/- 1 16 +/- 1 19 +/- 1 16 +/- 1 17 +/- 1 18 +/- 1 09/26/16 - 10/03/16 14 +/- 1 13 +/- 1 12 +/- 1 13 +/- 1 13 +/- 1 15 +/- 1 10/03/16 - 10/10/16 19 +/- 1 17 +/- 1 18 +/- 1 16 +/- 1 17 +/- 1 15 +/- 1 10/10/16 - 10/17/16 16 +/- 1 12 +/- 1 14 +/- 1 13 +/- 1 13 +/- 1 13 +/- 1 10/17/16 - 10/24/16 13 +/- 1 13 +/- 1 14 +/- 1 12 +/- 1 14 +/- 1 15 +/- 1 10/24/16 - 10/31/16 16 +/- 1 11 +/- 1 19 +/- 1 10 +/- 1 11 +/- 1 11 +/- 1 10/31/16 - 11/07/16 16 +/- 1 17 +/- 1 18 +/- 1 16 +/- 1 15 +/- 1 18 +/- 1 11/07/16 - 11/14/16 17 +/- 1 13 +/- 1 13 +/- 1 13 +/- 1 13 +/- 1 14 +/- 1 11/14/16 - 11/21/16 22 +/- 1 24 +/- 1 27 +/- 1 25 +/- 1 28 +/- 2 27 +/- 2 11/21/16 - 11/28/16 9 +/- 1 7 +/- 1 6 +/- 1 8 +/- 1 7 +/- 1 8 +/- 1 11/28/16 - 12/05/16 14 +/- 1 12 +/- 1 12 +/- 1 16 +/- 1 13 +/- 1 15 +/- 1 12/05/16 - 12/12/16 13 +/- 1 12 +/- 1 14 +/- 1 12 +/- 1 12 +/- 1 10 +/- 1 12/12/16 - 12/19/16 17 +/- 1 19 +/- 1 18 +/- 1 16 +/- 1 19 +/- 1 18 +/- 1 12/19/16 - 12/27/16 19 +/- 1 16 +/- 1 17 +/- 1 17 +/- 1 17 +/- 1 19 +/- 1 12/27/16 - 01/03/17 13 +/- 1 14 +/- 1 12 +/- 1 14 +/- 1 14 +/- 1 14 +/- 1

• • Optional sample location 6 - 11

TABLE 6-7 ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFFSITE SAMPLE LOCATIONS - 2016 I-131 ACTIVITY 10E-3 pCi/m3 +/- 1 Sigma COLLECTION DATE R1* R2* R3* R4* R5* D2** E** F** G**

12/29/15 - 01/05/16 < 11 < 26 < 26 < 24 < 13 < 23 < 23 < 23 < 26 01/05/16 - 01/12/16 < 39 < 40 < 37 < 43 < 45 < 14 < 42 < 46 < 38 01/12/16 - 01/19/16 < 31 < 31 < 12 < 25 < 25 < 24 < 13 < 26 < 31 01/19/16 - 01/26/16 < 30 < 29 < 16 < 24 < 23 < 10 < 23 < 24 < 31 01/26/16 - 02/02/16 < 34 < 34 < 12 < 41 < 40 < 21 < 42 < 37 < 35 02/02/16 - 02/09/16 < 61 < 23 < 61 < 47 < 45 < 46 < 46 < 18 < 60 02/09/16 - 02/17/16 < 36 < 37 < 36 < 15 < 28 < 28 < 28 < 28 < 36 02/17/16 - 02/23/16 < 21 < 21 < 21 < 20 < 20 < 20 < 11 < 21 < 21 02/23/16 - 03/01/16 < 20 < 9 < 21 < 18 < 6 < 19 < 18 < 39 < 20 03/01/16 - 03/08/16 < 11 < 11 < 11 < 29 < 29 < 11 < 28 < 28 < 11 03/08/16 - 03/15/16 < 33 < 33 < 32 < 19 < 36 < 37 < 36 < 33 < 33 03/15/16 - 03/22/16 < 24 < 24 < 23 < 9 < 21 < 21 < 21 < 20 < 24 03/22/16 - 03/29/16 < 14 < 58 < 14 < 15 < 27 < 27 < 28 < 28 < 14 03/29/16 - 04/05/16 < 34 < 16 < 35 < 13 < 36 < 35 < 35 < 36 < 35 04/05/16 - 04/12/16 < 43 < 43 < 44 < 42 < 22 < 41 < 41 < 43 < 44 04/12/16 - 04/19/16 < 32 < 17 < 32 < 14 < 33 < 32 < 32 < 31 < 32 04/19/16 - 04/26/16 < 12 < 27 < 28 < 20 < 35 < 36 < 36 < 35 < 28 04/26/16 - 05/03/16 < 25 < 25 < 25 < 36 < 36 < 36 < 15 < 36 < 25 05/03/16 - 05/10/16 < 22 < 21 < 21 < 12 < 29 < 30 < 29 < 29 < 22 05/10/16 - 05/17/16 < 32 < 32 < 13 < 42 < 41 < 20 < 41 < 41 < 32 05/17/16 - 05/24/16 < 35 < 35 < 35 < 35 < 15 < 35 < 34 < 33 < 35 05/24/16 - 06/01/16 < 24 < 24 < 24 < 8 < 19 < 19 < 19 < 19 < 24 06/01/16 - 06/07/16 < 11 < 27 < 27 < 28 < 27 < 14 < 27 < 28 < 26 06/07/16 - 06/14/16 < 31 < 31 < 31 < 27 < 27 < 10 < 27 < 27 < 31 06/14/16 - 06/21/16 < 13 < 31 < 31 < 14 < 34 < 34 < 34 < 35 < 32 06/21/16 - 06/28/16 < 50 < 50 < 50 < 22 < 41 < 42 < 40 < 41 < 50

• Sample required by the ODCM

• • Optional sample location 6 - 12

TABLE 6-7 (continued)

ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFFSITE SAMPLE LOCATIONS - 2016 I-131 ACTIVITY 10E-3 pCi/m3 +/- 1 Sigma COLLECTION DATE R1* R2* R3* R4* R5* D2** E** F** G**

06/28/16 - 07/06/16 < 44 < 44 < 45 < 33 < 32 < 13 < 32 < 32 < 19 07/06/16 - 07/12/16 < 31 < 32 < 32 < 26 < 59 < 63 < 60 < 60 < 31 07/12/16 - 07/19/16 < 42 < 43 < 18 < 29 < 30 < 27 < 30 < 30 < 42 07/19/16 - 07/26/16 < 65 < 64 < 25 < 53 < 53 < 53 < 21 < 55 < 65 07/26/16 - 08/02/16 < 39 < 39 < 16 < 14 < 36 < 36 < 36 < 38 < 39 08/02/16 - 08/09/16 < 39 < 16 < 38 < 31 < 31 < 32 < 31 < 11 < 38 08/09/16 - 08/16/16 < 11 < 20 < 20 < 29 < 28 < 28 < 15 < 29 < 20 08/16/16 - 08/23/16 < 27 < 27 < 28 < 7 < 17 < 18 < 18 < 18 < 27 08/23/16 - 08/30/16 < 41 < 41 < 40 < 23 < 23 < 9 < 22 < 23 < 41 08/30/16 - 09/07/16 < 17 < 17 < 6 < 22 < 22 < 21 < 22 < 8 < 17 09/07/16 - 09/13/16 < 32 < 32 < 35 < 14 < 30 < 32 < 31 < 31 < 33 09/13/16 - 09/20/16 < 13 < 25 < 25 < 8 < 20 < 20 < 21 < 21 < 32 09/20/16 - 09/27/16 < 29 < 29 < 29 < 14 < 26 < 26 < 27 < 26 < 29 09/27/16 - 10/04/16 < 33 < 33 < 14 < 15 < 38 < 37 < 36 < 37 < 33 10/04/16 - 10/11/16 < 35 < 34 < 34 < 26 < 26 < 11 < 26 < 26 < 35 10/11/16 - 10/18/16 < 24 < 24 < 23 < 10 < 29 < 29 < 28 < 28 < 24 10/18/16 - 10/25/16 < 30 < 30 < 12 < 38 < 35 < 36 < 19 < 35 < 30 10/25/16 - 11/01/16 < 53 < 33 < 13 < 38 < 38 < 37 < 36 < 15 < 33 11/01/16 - 11/08/16 < 35 < 28 < 34 < 16 < 29 < 29 < 16 < 28 < 34 11/08/16 - 11/15/16 < 21 < 21 < 22 < 10 < 23 < 23 < 24 < 23 < 22 11/15/16 - 11/22/16 < 29 < 29 < 30 < 16 < 38 < 39 < 37 < 38 < 30 11/22/16 - 11/29/16 < 22 < 22 < 8 < 20 < 20 < 19 < 20 < 10 < 23 11/29/16 - 12/06/16 < 28 < 12 < 27 < 27 < 27 < 11 < 26 < 26 < 26 12/06/16 - 12/13/16 < 23 < 23 < 23 < 26 < 14 < 26 < 26 < 27 < 22 12/13/16 - 12/20/16 < 23 < 13 < 23 < 29 < 28 < 29 < 29 < 10 < 23 12/20/16 - 12/28/16 < 26 < 26 < 10 < 30 < 30 < 29 < 31 < 12 < 26 12/28/16 - 01/04/17 < 22 < 12 < 22 < 23 < 23 < 23 < 23 < 8 < 22

• Sample required by the ODCM

• • Optional sample location 6 - 13

TABLE 6-8 ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ONSITE SAMPLE LOCATIONS - 2016 I-131 ACTIVITY 10E-3 pCi/m3 +/- 1 Sigma COLLECTION DATE D1** G** H** I** J** K**

12/28/15 - 01/04/16 < 10 < 28 < 26 < 26 < 27 < 27 01/04/16 - 01/11/16 < 35 < 21 < 15 < 35 < 36 < 36 01/11/16 - 01/18/16 < 47 < 33 < 18 < 48 < 49 < 49 01/18/16 - 01/25/16 < 20 < 33 < 8 < 20 < 20 < 20 01/25/16 - 02/01/16 < 21 < 38 < 47 < 46 < 49 < 48 02/01/16 - 02/08/16 < 52 < 65 < 51 < 28 < 52 < 51 02/08/16 - 02/15/16 < 31 < 20 < 12 < 31 < 32 < 31 02/15/16 - 02/22/16 < 16 < 9 < 6 < 16 < 16 < 16 02/22/16 - 02/29/16 < 17 < 23 < 18 < 10 < 18 < 18 02/29/16 - 03/07/16 < 26 < 7 < 10 < 27 < 26 < 26 03/07/16 - 03/14/16 < 40 < 13 < 35 < 17 < 39 < 37 03/14/16 - 03/21/16 < 24 < 11 < 8 < 23 < 23 < 22 03/21/16 - 03/28/16 < 11 < 6 < 30 < 28 < 30 < 29 03/28/16 - 04/04/16 < 32 < 36 < 14 < 31 < 33 < 33 04/04/16 - 04/11/16 < 41 < 19 < 41 < 41 < 17 < 42 04/11/16 - 04/18/16 < 33 < 35 < 35 < 13 < 32 < 35 04/18/16 - 04/25/16 < 28 < 30 < 11 < 29 < 29 < 30 04/25/16 - 05/02/16 < 32 < 10 < 33 < 33 < 14 < 34 05/02/16 - 05/09/16 < 21 < 10 < 8 < 21 < 21 < 20 05/09/16 - 05/16/16 < 27 < 35 < 10 < 26 < 25 < 27 05/16/16 - 05/23/16 < 28 < 20 < 27 < 10 < 29 < 29 05/23/16 - 05/31/16 < 24 < 11 < 9 < 25 < 24 < 23 05/31/16 - 06/06/16 < 20 < 30 < 20 < 8 < 20 < 19 06/06/16 - 06/13/16 < 26 < 15 < 10 < 25 < 25 < 25 06/13/16 - 06/20/16 < 24 < 34 < 9 < 23 < 23 < 22 06/20/16 - 06/27/16 < 47 < 23 < 19 < 50 < 49 < 48

• • Optional sample location 6 - 14

TABLE 6-8 (continued)

ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ONSITE SAMPLE LOCATIONS - 2016 I-131 ACTIVITY 10E-3 pCi/m3 +/- 1 Sigma COLLECTION DATE D1** G** H** I** J** K**

07/05/16 - 07/11/16 < 54 < 14 < 22 < 53 < 53 < 53 07/11/16 - 07/18/16 < 38 < 48 < 20 < 37 < 36 < 37 07/18/16 - 07/25/16 < 61 < 69 < 61 < 25 < 62 < 62 07/25/16 - 08/01/16 < 41 < 42 < 13 < 34 < 34 < 35 08/01/16 - 08/08/16 < 12 < 42 < 32 < 31 < 32 < 32 08/08/16 - 08/15/16 < 31 < 22 < 32 < 31 < 31 < 14 08/15/16 - 08/22/16 < 22 < 10 < 13 < 23 < 23 < 22 08/22/16 - 08/29/16 < 19 < 17 < 7 < 18 < 17 < 18 08/29/16 - 09/06/16 < 18 < 24 < 10 < 24 < 25 < 25 09/06/16 - 09/12/16 < 13 < 37 < 37 < 36 < 20 < 37 09/12/16 - 09/19/16 < 35 < 34 < 28 < 27 < 35 < 12 09/19/16 - 09/26/16 < 12 < 40 < 17 < 39 < 40 < 39 09/26/16 - 10/03/16 < 36 < 13 < 34 < 34 < 34 < 33 10/03/16 - 10/10/16 < 14 < 29 < 12 < 29 < 29 < 28 10/10/16 - 10/17/16 < 14 < 29 < 12 < 29 < 29 < 29 10/17/16 - 10/24/16 < 33 < 33 < 33 < 14 < 33 < 32 10/24/16 - 10/31/16 < 39 < 18 < 43 < 44 < 43 < 45 10/31/16 - 11/07/16 < 40 < 39 < 39 < 40 < 40 < 41 11/07/16 - 11/14/16 < 9 < 29 < 12 < 30 < 29 < 28 11/14/16 - 11/21/16 < 12 < 41 < 17 < 41 < 40 < 43 11/21/16 - 11/28/16 < 24 < 28 < 11 < 29 < 28 < 28 11/28/16 - 12/05/16 < 30 < 23 < 9 < 23 < 23 < 24 12/05/16 - 12/12/16 < 27 < 10 < 11 < 27 < 27 < 28 12/12/16 - 12/19/16 < 33 < 25 < 14 < 32 < 32 < 32 12/19/16 - 12/27/16 < 43 < 28 < 17 < 43 < 45 < 43 12/27/16 - 01/03/17 < 29 < 24 < 30 < 29 < 30 < 12

• • Optional sample location 6 - 15

TABLE 6-9 CONCENTRATION OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2016 Results in Units of 10E-3 pCi/m3 +/- 1 Sigma OFFSITE SAMPLE LOCATIONS SAMPLE COLLECTION Be-7 K-40 Mn-54 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 LOCATION DATE R1*

12/29/15 - 03/29/16 95 +/- 11 < 9 < 1 < 2 < 1 < 3 < 3 < 5 < 1 < 1 03/29/16 - 06/28/16 121 +/- 11 < 21 < 1 < 1 < 1 < 2 < 1 < 3 < 1 < 1 06/28/16 - 09/27/16 122 +/- 14 < 29 < 2 < 2 < 2 < 4 < 2 < 5 < 2 < 2 09/27/16 - 01/04/17 92 +/- 10 < 20 < 1 < 2 < 1 < 2 < 1 < 3 < 1 < 1 R2*

12/29/15 - 03/29/16 85 +/- 11 < 18 < 1 < 2 < 1 < 3 < 2 < 3 < 1 < 1 03/29/16 - 06/28/16 123 +/- 18 < 29 < 2 < 2 < 1 < 3 < 3 < 5 < 2 < 2 06/28/16 - 09/27/16 110 +/- 11 < 13 < 1 < 2 < 1 < 3 < 2 < 3 < 1 < 1 09/27/16 - 01/04/17 69 +/- 10 < 12 < 1 < 1 < 1 < 3 < 2 < 4 < 1 < 1 R3*

12/29/15 - 03/29/16 89 +/- 12 < 15 < 1 < 2 < 1 < 2 < 2 < 3 < 1 < 1 03/29/16 - 06/28/16 155 +/- 13 < 17 < 1 < 2 < 1 < 1 < 1 < 3 < 1 < 1 06/28/16 - 09/27/16 141 +/- 13 < 23 < 2 < 2 < 2 < 4 < 1 < 5 < 1 < 1 09/27/16 - 01/04/17 76 +/- 12 < 26 < 1 < 3 < 1 < 4 < 3 < 5 < 2 < 1 R4*

12/29/15 - 03/29/16 87 +/- 13 < 31 < 2 < 2 < 1 < 3 < 2 < 4 < 1 < 1 03/29/16 - 06/28/16 135 +/- 11 < 27 < 1 < 2 < 1 < 3 < 2 < 3 < 1 < 1 06/28/16 - 09/27/16 142 +/- 10 18 +/- 5 < 2 < 3 < 2 < 4 < 3 < 5 < 1 < 1 09/27/16 - 01/04/17 67 +/- 6 < 11 < 1 < 2 < 1 < 3 < 2 < 3 < 1 < 1 R5*

12/29/15 - 03/29/16 90 +/- 10 < 13 < 1 < 2 < 1 < 5 < 2 < 4 < 2 < 1 03/29/16 - 06/28/16 123 +/- 13 < 30 < 1 < 2 < 1 < 3 < 2 < 4 < 1 < 1 06/28/16 - 09/27/16 118 +/- 11 < 18 < 1 < 2 < 1 < 4 < 3 < 4 < 1 < 1 09/27/16 - 01/04/17 84 +/- 8 < 18 < 1 < 1 < 1 < 3 < 1 < 3 < 1 < 1

• Sample required by the ODCM 6 - 16

TABLE 6-9 (continued)

CONCENTRATION OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2016 Results in Units of 10E-3 pCi/m3 +/- 1 Sigma OFFSITE SAMPLE LOCATIONS SAMPLE COLLECTION Be-7 K-40 Mn-54 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 LOCATION DATE D2**

12/29/15 - 03/29/16 87 +/- 14 < 21 < 2 < 4 < 2 < 6 < 4 < 8 < 2 < 2 03/29/16 - 06/28/16 111 +/- 13 < 24 < 1 < 2 < 1 < 2 < 2 < 4 < 1 < 1 06/28/16 - 09/27/16 113 +/- 12 20 +/- 7 < 1 < 2 < 1 < 4 < 2 < 3 < 1 < 1 09/27/16 - 01/04/17 71 +/- 8 17 +/- 6 < 1 < 2 < 1 < 2 < 2 < 3 < 1 < 1 E**

12/29/15 - 03/29/16 138 +/- 13 < 28 < 1 < 2 < 2 < 3 < 2 < 4 < 1 < 2 03/29/16 - 06/28/16 119 +/- 13 19 +/- 6 < 1 < 1 < 1 < 2 < 2 < 3 < 1 < 1 06/28/16 - 09/27/16 99 +/- 9 < 17 < 1 < 1 < 1 < 3 < 2 < 3 < 1 < 1 09/27/16 - 01/04/17 72 +/- 13 < 26 < 2 < 2 < 1 < 3 < 2 < 4 < 2 < 1 F**

12/29/15 - 03/29/16 86 +/- 13 < 33 < 2 < 4 < 2 < 5 < 4 < 6 < 2 < 2 03/29/16 - 06/28/16 117 +/- 10 < 16 < 1 < 1 < 1 < 1 < 1 < 2 < 1 < 1 06/28/16 - 09/27/16 166 +/- 12 < 22 < 2 < 2 < 1 < 4 < 2 < 3 < 1 < 1 09/27/16 - 01/04/17 78 +/- 9 < 20 < 1 < 2 < 1 < 2 < 2 < 4 < 1 < 1 G**

12/29/15 - 03/29/16 76 +/- 14 < 28 < 2 < 4 < 2 < 4 < 4 < 7 < 2 < 2 03/29/16 - 06/28/16 158 +/- 15 < 10 < 1 < 2 < 1 < 2 < 1 < 4 < 1 < 1 06/28/16 - 09/27/16 133 +/- 12 < 18 < 1 < 2 < 1 < 3 < 2 < 3 < 1 < 1 09/27/16 - 01/04/17 66 +/- 7 < 19 < 1 < 1 < 1 < 3 < 2 < 3 < 1 < 1

• • Optional sample location 6 - 17

TABLE 6-9 (continued)

CONCENTRATION OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2016 Results in Units of 10E-3 pCi/m3 +/- 1 Sigma ONSITE SAMPLE LOCATIONS SAMPLE COLLECTION Be-7 K-40 Mn-54 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 LOCATION DATE D1**

12/28/15 - 03/28/16 120 +/- 14 < 27 < 1 < 3 < 2 < 4 < 3 < 6 < 1 < 1 03/28/16 - 06/27/16 121 +/- 11 < 28 < 1 < 2 < 1 < 3 < 2 < 3 < 1 < 1 06/27/16 - 10/03/16 124 +/- 20 < 23 < 1 < 2 < 1 < 4 < 3 < 5 < 1 < 1 10/03/16 - 01/03/17 83 +/- 10 < 30 < 2 < 2 < 2 < 4 < 2 < 5 < 2 < 2 G**

12/28/15 - 03/28/16 96 +/- 12 < 9 < 1 < 1 < 1 < 2 < 1 < 3 < 1 < 1 03/28/16 - 06/27/16 161 +/- 13 < 18 < 1 < 1 < 1 < 2 < 1 < 2 < 1 < 1 06/27/16 - 10/03/16 82 +/- 21 < 23 < 2 < 4 < 1 < 4 < 5 < 7 < 2 < 2 10/03/16 - 01/03/17 61 +/- 8 < 25 < 1 < 2 < 1 < 3 < 2 < 4 < 1 < 1 H**

12/28/15 - 03/28/16 73 +/- 9 < 19 < 1 < 1 < 1 < 3 < 2 < 4 < 1 < 1 03/28/16 - 06/27/16 117 +/- 12 < 25 < 1 < 1 < 1 < 2 < 2 < 4 < 1 < 1 06/27/16 - 10/03/16 117 +/- 12 < 13 < 1 < 2 < 2 < 4 < 2 < 4 < 1 < 1 10/03/16 - 01/03/17 72 +/- 7 < 12 < 1 < 2 < 1 < 2 < 2 < 3 < 1 < 1 I**

12/28/15 - 03/28/16 105 +/- 11 < 21 < 1 < 2 < 1 < 3 < 2 < 3 < 1 < 1 03/28/16 - 06/27/16 117 +/- 16 < 36 < 2 < 2 < 1 < 3 < 2 < 5 < 1 < 1 06/27/16 - 10/03/16 94 +/- 10 < 10 < 1 < 2 < 1 < 3 < 2 < 4 < 1 < 1 10/03/16 - 01/03/17 83 +/- 13 < 19 < 2 < 3 < 2 < 4 < 2 < 4 < 1 < 2 J**

12/28/15 - 03/28/16 85 +/- 14 < 37 < 2 < 4 < 2 < 7 < 5 < 7 < 2 < 2 03/28/16 - 06/27/16 127 +/- 11 < 20 < 1 < 1 < 1 < 2 < 2 < 3 < 1 < 1 06/27/16 - 10/03/16 111 +/- 8 < 19 < 1 < 1 < 1 < 3 < 1 < 3 < 1 < 1 10/03/16 - 01/03/17 72 +/- 10 < 15 < 1 < 1 < 1 < 2 < 2 < 3 < 1 < 1 K**

12/28/15 - 03/28/16 72 +/- 12 < 14 < 2 < 2 < 2 < 4 < 3 < 4 < 2 < 1 03/28/16 - 06/27/16 116 +/- 11 < 26 < 1 < 1 < 1 < 3 < 2 < 3 < 1 < 1 06/27/16 - 10/03/16 100 +/- 11 < 22 < 1 < 2 < 2 < 4 < 2 < 4 < 1 < 1 10/03/16 - 01/03/17 86 +/- 9 < 15 < 1 < 2 < 2 < 3 < 2 < 4 < 1 < 1

• • Optional sample location 6 - 18

TABLE 6-10 DIRECT RADIATION MEASUREMENT RESULTS - 2016 Results in mrem/std. Month +/- 1 Sigma LOCATION JAN - MAR APR - JUN JUL - SEP OCT - DEC DEGREES & DISTANCE NO. DESCRIPTION (1) & (2) 3 D1 Onsite 11.0 +/- 0.5 11.3 +/- 0.5 8.6 +/- 0.4 7.6 +/- 0.3 71º at 0.3 miles 4 D2 Onsite 4.3 +/- 0.3 4.5 +/- 0.2 4.2 +/- 0.2 4.4 +/- 0.3 143º at 0.4 miles 5 E Onsite 4.0 +/- 0.2 4.7 +/- 0.2 4.4 +/- 0.2 4.5 +/- 0.2 180º at 0.3 miles 6 F Onsite 3.5 +/- 0.2 3.9 +/- 0.2 3.8 +/- 0.2 4.0 +/- 0.2 213º at 0.5 miles 7* G Onsite 3.5 +/- 0.2 3.9 +/- 0.2 3.6 +/- 0.2 4.0 +/- 0.2 245º at 0.7 miles 8* R5 Offsite Control 4.5 +/- 0.2 5.1 +/- 0.2 4.8 +/- 0.2 5.2 +/- 0.2 42º at 16.2 miles 9 D1 Offsite - State Route 3 3.9 +/- 0.3 4.2 +/- 0.2 3.9 +/- 0.2 4.5 +/- 0.2 80º at 11.4 miles 10 D2 Offsite 3.8 +/- 0.2 4.1 +/- 0.2 3.7 +/- 0.2 4.2 +/- 0.2 118º at 9.0 miles 11 E Offsite 3.7 +/- 0.3 4.0 +/- 0.2 3.9 +/- 0.2 4.1 +/- 0.2 162º at 7.1 miles 12 F Offsite 3.7 +/- 0.2 4.1 +/- 0.2 3.9 +/- 0.2 4.4 +/- 0.2 192º at 7.6 miles 13 G Offsite 3.8 +/- 0.2 4.2 +/- 0.2 3.9 +/- 0.2 4.4 +/- 0.2 226º at 5.4 miles 14* DeMass Rd., SW Oswego - Control 3.8 +/- 0.2 4.2 +/- 0.2 4.1 +/- 0.2 4.3 +/- 0.3 227º at 12.5 miles 15* Pole 66, W. Boundary - Bible Camp 3.5 +/- 0.2 3.7 +/- 0.1 3.6 +/- 0.2 4.1 +/- 0.2 240º at 0.9 miles 18* Energy Info. Center - Lamp Post, SW 4.4 +/- 0.2 4.7 +/- 0.2 4.4 +/- 0.2 4.8 +/- 0.3 268º at 0.4 miles 19 East Boundary - JAF, Pole 9 4.1 +/- 0.2 4.6 +/- 0.2 4.3 +/- 0.3 4.7 +/- 0.2 83º at 1.4 miles 23* H Onsite 4.6 +/- 0.2 5.0 +/- 0.2 4.6 +/- 0.3 5.0 +/- 0.3 73º at 0.8 miles 24 I Onsite 4.1 +/- 0.2 4.4 +/- 0.2 4.1 +/- 0.2 4.4 +/- 0.2 95º at 0.8 miles 25 J Onsite 3.9 +/- 0.2 4.3 +/- 0.2 3.9 +/- 0.2 4.4 +/- 0.2 109º at 0.9 miles 26 K Onsite 3.8 +/- 0.2 4.2 +/- 0.2 4.0 +/- 0.3 4.4 +/- 0.2 132º at 0.5 miles 27 N. Fence, N. of Switchyard, JAF 19.0 +/- 1.2 18.6 +/- 1.1 14.5 +/- 0.8 11.0 +/- 0.6 60º at 0.4 miles 28 N. Light Pole, N. of Screenhouse, JAF 23.9 +/- 1.6 23.3 +/- 1.0 13.8 +/- 0.7 14.5 +/- 0.6 68º at 0.5 miles 29 N. Fence, N. of W. Side 21.0 +/- 1.4 19.4 +/- 1.4 15.5 +/- 1.3 11.9 +/- 0.5 65º at 0.5 miles 30 N. Fence, (NW) JAF 9.9 +/- 0.7 10.3 +/- 0.8 8.2 +/- 0.6 6.8 +/- 0.5 57º at 0.4 miles 31 N. Fence, (NW) NMP-1 6.4 +/- 0.3 6.7 +/- 0.3 6.7 +/- 0.3 6.4 +/- 0.3 279º at 0.2 miles 39 N. Fence, Rad Waste-NMP-1 9.0 +/- 0.4 10.6 +/- 0.5 10.9 +/- 0.6 10.2 +/- 0.4 298º at 0.2 miles 47 N. Fence, (NE) JAF 6.0 +/- 0.4 6.1 +/- 0.2 5.4 +/- 0.3 4.9 +/- 0.3 69º at 0.6 miles 49* Phoenix, NY - Control 3.6 +/- 0.2 3.8 +/- 0.1 3.7 +/- 0.2 3.8 +/- 0.2 168º at 19.7 miles 51 Liberty & Bronson Sts., E. of OSS 4.0 +/- 0.2 4.2 +/- 0.2 3.9 +/- 0.2 4.2 +/- 0.2 234º at 7.3 miles 52 E. 12th & Cayuga Sts., Oswego School 3.7 +/- 0.2 4.0 +/- 0.2 3.8 +/- 0.2 4.1 +/- 0.2 227º at 5.9 miles 53 Broadwell & Chestnut Sts., Fulton H.S. 3.8 +/- 0.2 4.4 +/- 0.2 4.3 +/- 0.2 4.4 +/- 0.2 183º at 13.7 miles 54 Mexico High School 3.6 +/- 0.2 4.0 +/- 0.1 3.8 +/- 0.2 4.0 +/- 0.2 115º at 9.4 miles 55 Gas Substation Co. Rt. 5 - Pulaski 3.8 +/- 0.2 4.0 +/- 0.2 3.8 +/- 0.2 4.1 +/- 0.2 75º at 13.0 miles 56* Rt. 104 - New Haven Sch. (SE Corner) 3.5 +/- 0.2 3.9 +/- 0.2 3.8 +/- 0.2 3.9 +/- 0.3 124º at 5.2 miles 58* Co. Rt. 1A - Novelis (E. of E. Entrance Rd.) 4.0 +/- 0.2 4.4 +/- 0.2 4.3 +/- 0.2 4.2 +/- 0.2 222º at 3.0 miles 75* Unit 2, N. Fence, N. of Reactor Bldg. 7.2 +/- 0.3 7.4 +/- 0.3 6.8 +/- 0.3 6.7 +/- 0.4 354º at 0.1 miles 76* Unit 2, N. Fence, N. of Change House 5.6 +/- 0.3 5.6 +/- 0.2 5.1 +/- 0.2 5.4 +/- 0.3 25º at 0.1 miles (1) Direction and distance based on NMP-2 reactor centerline (2) Degrees and distances updated by Global PositioningSystem (GPS) in 2006.

• TLD required by ODCM 6 - 19

TABLE 6-10 (continued)

DIRECT RADIATION MEASUREMENT RESULTS - 2016 Results in mrem/std. Month +/- 1 Sigma LOCATION JAN - MAR APR - JUN JUL - SEP OCT - DEC DEGREES & DISTANCE NO. DESCRIPTION (1) & (2) 77* Unit 2, N. Fence, N. of Pipe Bldg. 6.1 +/- 0.3 6.3 +/- 0.2 5.8 +/- 0.3 5.8 +/- 0.3 36º at 0.2 miles 78* JAF E. of E. Old Lay Down Area 4.0 +/- 0.2 4.3 +/- 0.2 4.2 +/- 0.3 4.5 +/- 0.2 85º at 1.0 miles 79* Co. Rt. 29, Pole #63, 0.2 mi. S. of Lake Rd. 3.7 +/- 0.2 4.0 +/- 0.2 3.7 +/- 0.3 3.9 +/- 0.2 120º at 1.2 miles 80* Co. Rt. 29, Pole #54, 0.7 mi. S. of Lake Rd. 3.8 +/- 0.2 4.1 +/- 0.2 3.9 +/- 0.2 4.3 +/- 0.3 136º at 1.5 miles 81* Miner Rd., Pole # 16, 0.5 mi. W. of Rt. 29 3.7 +/- 0.2 3.9 +/- 0.2 3.8 +/- 0.2 4.0 +/- 0.2 159º at 1.6 miles 82* Miner Rd., Pole # 1-1/2, 11 mi. W. of Rt. 29 3.8 +/- 0.2 4.0 +/- 0.1 3.7 +/- 0.2 4.1 +/- 0.2 180º at 1.6 miles 83* Lakeview Rd., Tree 0.45 mi. N. of Miner Rd. 3.6 +/- 0.2 3.8 +/- 0.1 3.8 +/- 0.2 4.1 +/- 0.1 203º at 1.2 miles 84* Lakeview Rd., N., Pole #6117, 200ft. N. of Lake Rd. 3.9 +/- 0.2 4.1 +/- 0.2 4.0 +/- 0.2 4.3 +/- 0.2 226º at 1.1 miles 85* Unit 1, N. Fence, N. of W. Side of Screen House 7.6 +/- 0.5 8.0 +/- 0.6 7.8 +/- 0.4 7.6 +/- 0.6 292º at 0.2 miles 86* Unit 2, N. Fence, N. of W. Side of Screen House 7.8 +/- 0.3 7.8 +/- 0.4 7.6 +/- 0.5 7.8 +/- 0.4 311º at 0.1 miles 87* Unit 2, N. Fence, N. of E. Side of Screen House 8.2 +/- 0.5 8.1 +/- 0.4 7.3 +/- 0.3 7.6 +/- 0.4 333º at 0.1 miles 88* Hickory Grove Rd., Pole #2, 0.6 mi. N. of Rt. 1 3.8 +/- 0.2 3.9 +/- 0.2 3.8 +/- 0.2 4.2 +/- 0.2 97º at 4.5 miles 89* Leavitt Rd., Pole # 16, 0.4 mi. S. of Rt. 1 3.9 +/- 0.2 4.3 +/- 0.2 4.1 +/- 0.2 4.5 +/- 0.3 112º at 4.3 miles 90* Rt. 104, Pole #300, 150ft. E. of Keefe Rd. 3.8 +/- 0.2 4.1 +/- 0.2 3.9 +/- 0.2 4.2 +/- 0.2 135º at 4.2 miles 91* Rt. 51A, Pole #59, 0.8 mi. W. of Rt. 51 3.7 +/- 0.2 3.9 +/- 0.2 3.7 +/- 0.1 4.1 +/- 0.3 157º at 4.9 miles 92* Maiden Lane Rd., Power Pole, 0.6 mi. S. of Rt. 104 4.1 +/- 0.2 4.5 +/- 0.1 4.2 +/- 0.2 4.6 +/- 0.2 183º at 4.4 miles 93* Rt. 53, Pole 1-1, 120ft. S. of Rt. 104 3.7 +/- 0.3 4.0 +/- 0.1 3.7 +/- 0.2 4.2 +/- 0.2 206º at 4.4 miles 94* Rt. 1, Pole #82, 250ft. E. of Kocher Rd. (Co. Rt. 63) 3.5 +/- 0.2 3.9 +/- 0.1 3.7 +/- 0.2 4.0 +/- 0.2 224º at 4.4 miles 95* Novelis W. Access Rd., Joe Fultz Blvd., Pole #21 3.4 +/- 0.2 3.6 +/- 0.1 3.3 +/- 0.2 3.7 +/- 0.2 239º at 3.7 miles 96* Creamery Rd., 0.3 mi. S. of Middle Rd., Pole 1-1/2 3.6 +/- 0.2 3.9 +/- 0.2 3.7 +/- 0.2 4.0 +/- 0.2 199º at 3.6 miles 97* Rt. 29, Pole # 50, 200ft. N. of Miner Rd. 3.6 +/- 0.2 4.0 +/- 0.2 3.9 +/- 0.2 4.1 +/- 0.2 145º at 1.8 miles 98 Lake Rd., Pole #145, 0.15 mi. E. of Rt. 29 4.0 +/- 0.3 4.2 +/- 0.2 3.9 +/- 0.2 4.2 +/- 0.2 102º at 1.2 miles 99 NMP Rd., 0.4 mi. N. of Lake Rd., Env. Station R1 4.0 +/- 0.2 4.3 +/- 0.2 4.0 +/- 0.2 4.3 +/- 0.2 92º at 1.8 miles 100 Rt. 29 & Lale Rd. Env. Station R2 3.9 +/- 0.2 4.2 +/- 0.2 3.9 +/- 0.2 4.3 +/- 0.2 106º at 1.1 miles 101 Rt. 29, 0.7 mi. S. of Lake Rd. Env. Station R3 3.4 +/- 0.3 3.6 +/- 0.2 3.5 +/- 0.2 3.9 +/- 0.2 133º at 1.4 miles 102 EOF/Env. Lab, Rt. 176, E. Driveway, Lamp Post 3.7 +/- 0.3 3.9 +/- 0.1 3.5 +/- 0.2 4.0 +/- 0.3 175º at 11.9 miles 103 EIC, East Garage Rd., Lamp Post 4.4 +/- 0.2 4.7 +/- 0.2 4.4 +/- 0.2 4.8 +/- 0.2 268º at 0.4 miles 104 Parkhurst Rd., Pole #23, 0.1 mi. S. of Lake Rd. 3.6 +/- 0.2 4.0 +/- 0.2 3.7 +/- 0.2 4.1 +/- 0.2 102º at 1.4 miles 105 Lakeview Rd., Pole #36, 0.5 mi. S. of Lake Rd. 3.8 +/- 0.2 4.1 +/- 0.2 3.8 +/- 0.2 4.1 +/- 0.2 199º at 1.4 miles 106 Shoreline Cove, W. of NMP-1, Tree on W. Edge 4.7 +/- 0.2 5.0 +/- 0.2 4.9 +/- 0.3 5.0 +/- 0.3 274º at 0.3 miles 107 Shoreline Cove, W. of NMP-1, 30ft. SSW of #106 4.6 +/- 0.2 4.9 +/- 0.3 4.9 +/- 0.2 4.9 +/- 0.2 273º at 0.3 miles 108 Lake Rd., Pole #142, 300ft. E. of Rt. 29 S. 3.9 +/- 0.2 4.1 +/- 0.2 3.8 +/- 0.2 4.1 +/- 0.2 105º at 1.1 miles 109 Tree North of Lake Rd., 300ft. E. of Rt. 29 N. 3.9 +/- 0.2 4.1 +/- 0.2 3.9 +/- 0.2 4.3 +/- 0.2 104º at 1.1 miles 111 Control, State Route 38, Sterling, NY 3.3 +/- 0.2 3.8 +/- 0.2 3.4 +/- 0.2 3.8 +/- 0.2 214º at 21.8 miles 112 EOF/Env. Lab, Oswego County Airport 3.6 +/- 0.2 3.7 +/- 0.1 3.3 +/- 0.2 3.9 +/- 0.3 175º at 11.9 miles 113 Control, Baldwinsville, NY 3.4 +/- 0.2 3.7 +/- 0.2 3.4 +/- 0.2 3.9 +/- 0.3 178º at 24.7 miles (1) Direction and distance based on NMP-2 reactor centerline (2) Degrees and distances updated by Global PositioningSystem (GPS) in 2006.

• TLD required by ODCM 6 - 20

TABLE 6-11 CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2016 Results in Units of pCi/liter +/- 1 Sigma SAMPLE COLLECTION I-131 K-40 Cs-134 Cs-137 Ba-La-140 Others LOCATION DATE Sample Location** 55***

04/04/16 < 0.6 1274 +/- 113 < 6 < 8 < 13 <LLD 04/18/16 < 0.6 1351 +/- 71 < 5 < 5 < 8 <LLD 05/09/16 < 1.0 1406 +/- 79 < 5 < 6 < 5 <LLD 05/23/16 < 0.7 1247 +/- 82 < 6 < 7 < 11 <LLD 06/06/16 < 0.3 1416 +/- 70 < 6 < 6 < 7 <LLD 06/20/16 < 0.6 1189 +/- 150 < 13 < 14 < 3 <LLD 07/05/16 < 0.6 1289 +/- 124 < 9 < 9 < 10 <LLD 07/18/16 < 0.2 1276 +/- 97 < 8 < 6 < 10 <LLD 08/08/16 < 0.7 1184 +/- 89 < 7 < 7 < 6 <LLD 08/22/16 < 0.5 1427 +/- 84 < 9 < 10 < 7 <LLD 09/06/16 < 0.4 1467 +/- 113 < 9 < 11 < 12 <LLD 09/19/16 < 0.8 1193 +/- 93 < 8 < 9 < 11 <LLD 10/03/16 < 0.7 1228 +/- 91 < 6 < 9 < 8 <LLD 10/18/16 < 0.6 1275 +/- 53 < 3 < 4 < 4 <LLD 11/07/16 < 0.6 1291 +/- 112 < 9 < 11 < 10 <LLD 11/21/16 < 0.6 1312 +/- 58 < 4 < 5 < 7 <LLD 12/05/16 < 0.5 1194 +/- 94 < 7 < 9 < 9 <LLD 12/19/16 < 0.6 1289 +/- 68 < 6 < 6 < 9 <LLD

• Sample required by the ODCM

• • Optional sample location

• • • Corresponds to sample location noted on Figure 3.3-4 Plant related radionuclides 6 - 21

TABLE 6-11 (continued)

CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2016 Results in Units of pCi/liter +/- 1 Sigma SAMPLE COLLECTION I-131 K-40 Cs-134 Cs-137 Ba-La-140 Others LOCATION DATE Sample Location* 77(Control)***

04/04/16 < 0.6 1329 +/- 105 < 7 < 8 < 11 <LLD 04/18/16 < 0.6 1426 +/- 73 < 6 < 6 < 6 <LLD 05/09/16 < 0.8 1245 +/- 84 < 7 < 6 < 9 <LLD 05/23/16 < 0.9 1448 +/- 87 < 6 < 7 < 10 <LLD 06/06/16 < 0.5 1349 +/- 65 < 4 < 5 < 9 <LLD 06/20/16 < 0.8 1029 +/- 133 < 9 < 15 < 13 <LLD 07/05/16 < 0.5 1006 +/- 101 < 7 < 12 < 14 <LLD 07/18/16 < 0.2 1160 +/- 123 < 9 < 9 < 11 <LLD 08/08/16 < 0.5 1543 +/- 123 < 7 < 10 < 13 <LLD 08/22/16 < 0.4 1239 +/- 73 < 5 < 6 < 8 <LLD 09/06/16 < 0.7 1452 +/- 118 < 9 < 10 < 6 <LLD 09/19/16 < 0.5 1307 +/- 77 < 6 < 7 < 6 <LLD 10/03/16 < 0.8 1482 +/- 104 < 7 < 8 < 13 <LLD 10/18/16 < 0.8 1235 +/- 42 < 3 < 3 < 4 <LLD 11/07/16 < 0.6 1446 +/- 82 < 7 < 7 < 7 <LLD 11/21/16 < 0.7 1372 +/- 57 < 4 < 5 < 6 <LLD 12/05/16 < 0.6 1269 +/- 77 < 8 < 8 < 9 <LLD 12/19/16 < 0.4 1405 +/- 63 < 4 < 6 < 5 <LLD

• Sample required by the ODCM

• • Optional sample location

• • • Corresponds to sample location noted on Figure 3.3-4 Plant related radionuclides 6 - 22

TABLE 6-12 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCTS - 2016 Results in Units of pCi/kg (wet) +/- 1 Sigma SAMPLE COLLECTION Be-7 K-40 Zn-65 I-131 Cs-134 Cs-137 Others LOCATION*** DATE FLACK (C2*)

09/06/16 HORSERADISH LEAVES 410 +/- 97 3510 +/- 265 < 46 < 37 < 23 < 22 <LLD 09/06/16 PUMPKIN LEAVES 1716 +/- 142 4614 +/- 251 < 44 < 36 < 23 < 22 <LLD 09/06/16 RHUBARB LEAVES < 265 3758 +/- 240 < 68 < 55 < 31 < 32 <LLD WHALEY (144*)

09/07/16 CABBAGE 366 +/- 94 3269 +/- 247 < 56 < 39 < 27 < 27 <LLD 09/07/16 HORSERADISH LEAVES < 319 4525 +/- 329 < 50 < 59 < 23 < 34 <LLD 09/07/16 SQUASH LEAVES 416 +/- 199 2536 +/- 323 < 43 < 52 < 33 < 36 <LLD O'CONNOR (484*)

09/07/16 HORSERADISH LEAVES 436 +/- 146 2458 +/- 241 < 53 < 42 < 26 < 26 <LLD 09/07/16 RHUBARB LEAVES < 256 4177 +/- 252 < 50 < 35 < 21 < 28 <LLD 09/07/16 GRAPE LEAVES 924 +/- 130 2631 +/- 246 < 37 < 46 < 24 < 29 <LLD

• Sample required by the ODCM

• • Optional sample location

• • • Corresponds to sample location noted on Figure 3.3-5 Plant related radionuclides 6 - 23

TABLE 6-13 MILK ANIMAL CENSUS 2016 Number of (2)

Town or Location Distance Milk Animals Area(a) Designation(1) Degrees(2) (Miles) (Cows)

Richland 80 89° 9.7 25 14 125° 9.1 52 Mexico 55* 97° 8.8 60 72 100° 9.6 38 Granby 77** 190° 16.0 50 (Control)

MILKING ANIMAL TOTALS: 225 (including control locations)

MILKING ANIMAL TOTALS: 167 (excluding control locations)

NOTES:

• Milk sample location

• • Milk sample control location (1) Reference Figure 3.3-4 for locations 55 and 77 (2) Degrees and distance are based on NMP-2 Reactor Building centerline (a) Census performed out to a distance of approximately 10 miles 6 - 24

TABLE 6-14 RESIDENCE CENSUS 2016 Meteorological Map Sector Location Location(1) Direction(2) Distance(2)

N * - - -

NNE * - - -

NE * - - -

ENE * - - -

E 80 Sunset Bay Road A 83° 1.04 miles ESE 161 Lake Road B 116° 0.7 miles SE 1216 County Route 29 C 143° 1.07 miles SSE 1146 County Route 29 D 152° 1.29 miles S 294 Miner Road E 179° 1.57 miles SSW 210 Lakeview Road F 213° 1.65 miles SW 319 Lakeview Road G 230° 1.45 miles WSW Bayshore Drive H 242° 1.81 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 JAFNPP Reactor Building centerline 6 - 25

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 James A. FitzPatrick Nuclear Power Plant Annual Radiological Environmental Operating Reports.

3. Only measured values were used for statistical calculations.

4. The term MDL was used prior to 1979 to represent the concept of Lower Limit of Detection (LLD). MDL = Minimum Detectable Level.

7-1

TABLE 7-1 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Results in pCi/g (dry)

LOCATION: CONTROL

• Isotope Cs-134 Cs-137 Co-60 Year Min. Max. Mean Min. Max. Mean Min. Max. Mean 1969 ** ** ** ** ** ** ** ** **

1974 ** ** ** ** ** ** ** ** **

1975 ** ** ** ** ** ** ** ** **

1989 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD 0.027 0.027 0.027 <LLD <LLD <LLD 1994 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1995 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1996 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1997 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1998 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1999 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2000 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2001 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2002 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2003 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2004 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2005 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2006 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2007 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2008 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2009 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2010 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2011 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2012 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2013 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2014 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2015 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2016 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD

• Langs Beach - beyond influence of the site in a westerly direction.

• • No data. Sample not required until new technical specifications implemented in 1985.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-2

TABLE 7-2 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Results in pCi/g (dry)

LOCATION: INDICATOR

• Isotope Cs-134 Cs-137 Co-60 Year Min. Max. Mean Min. Max. Mean Min. Max. Mean 1969 ** ** ** ** ** ** ** ** **

1974 ** ** ** ** ** ** ** ** **

1975 ** ** ** ** ** ** ** ** **

1989 <LLD <LLD <LLD 0.25 0.32 0.29 <LLD <LLD <LLD 1990 <LLD <LLD <LLD 0.28 0.30 0.29 <LLD <LLD <LLD 1991 <LLD <LLD <LLD 0.12 0.14 0.13 <LLD <LLD <LLD 1992 <LLD <LLD <LLD 0.12 0.14 0.13 <LLD <LLD <LLD 1993 <LLD <LLD <LLD 0.18 0.46 0.32 <LLD <LLD <LLD 1994 <LLD <LLD <LLD 0.06 0.37 0.22 <LLD <LLD <LLD 1995 <LLD <LLD <LLD 0.14 0.15 0.15 <LLD <LLD <LLD 1996 <LLD <LLD <LLD 0.15 0.17 0.16 <LLD <LLD <LLD 1997 <LLD <LLD <LLD 0.11 0.17 0.14 <LLD <LLD <LLD 1998 <LLD <LLD <LLD 0.06 0.06 0.06 <LLD <LLD <LLD 1999 <LLD <LLD <LLD 0.06 0.10 0.08 <LLD <LLD <LLD 2000 <LLD <LLD <LLD 0.06 0.07 0.06 <LLD <LLD <LLD 2001 <LLD <LLD <LLD 0.06 0.07 0.07 <LLD <LLD <LLD 2002 <LLD <LLD <LLD 0.05 0.05 0.05 <LLD <LLD <LLD 2003 <LLD <LLD <LLD 0.04 0.05 0.05 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 0.04 0.04 0.04 <LLD <LLD <LLD 2005 <LLD <LLD <LLD 0.06 0.09 0.08 <LLD <LLD <LLD 2006 <LLD <LLD <LLD 0.06 0.06 0.06 <LLD <LLD <LLD 2007 <LLD <LLD <LLD 0.04 0.04 0.04 <LLD <LLD <LLD 2008 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2009 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2010 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2011 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2012 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2013 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2014 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2015 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2016 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD

• Sunset Beach - closest offsite location with recreational value.

• • No data. Sample not required until new technical specifications implemented in 1985.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-3

TABLE 7-3 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Results in pCi/g (wet)

LOCATION: CONTROL

• Isotope Cs-137 Year Min. Max. Mean 1969 No Data No Data No Data 1974 0.94 0.94 0.94 1975 <MDL <MDL <MDL 1989 0.028 0.043 0.034 1990 0.033 0.079 0.045 1991 0.021 0.034 0.029 1992 0.019 0.026 0.022 1993 0.030 0.036 0.033 1994 0.014 0.031 0.022 1995 0.017 0.023 0.019 1996 0.018 0.022 0.020 1997 0.012 0.030 0.021 1998 0.013 0.013 0.013 1999 <LLD <LLD <LLD 2000 0.021 0.021 0.021 2001 <LLD <LLD <LLD 2002 <LLD <LLD <LLD 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD 2006 <LLD <LLD <LLD 2007 <LLD <LLD <LLD 2008 <LLD <LLD <LLD 2009 <LLD <LLD <LLD 2010 <LLD <LLD <LLD 2011 <LLD <LLD <LLD 2012 <LLD <LLD <LLD 2013 <LLD <LLD <LLD 2014 <LLD <LLD <LLD 2015 <LLD <LLD <LLD 2016 <LLD <LLD <LLD

• Control location is at an area beyond the influence of the site (westerly direction).

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-4

TABLE 7-4 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Results in pCi/g (wet)

LOCATION: INDICATOR * (NMP/JAF)

Isotope Cs-137 Year Min. Max. Mean 1969 0.01 0.13 0.06 1974 0.08 4.40 0.57 1975 1.10 1.70 1.38 1989 0.020 0.044 0.034 1990 0.027 0.093 0.040 1991 0.018 0.045 0.029 1992 0.014 0.030 0.024 1993 0.018 0.035 0.028 1994 0.015 0.023 0.019 1995 0.016 0.022 0.019 1996 0.016 0.025 0.020 1997 0.014 0.023 0.018 1998 0.021 0.021 0.021 1999 0.018 0.021 0.020 2000 <LLD <LLD <LLD 2001 <LLD <LLD <LLD 2002 0.016 0.016 0.016 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD 2006 <LLD <LLD <LLD 2007 <LLD <LLD <LLD 2008 <LLD <LLD <LLD 2009 <LLD <LLD <LLD 2010 <LLD <LLD <LLD 2011 <LLD <LLD <LLD 2012 <LLD <LLD <LLD 2013 <LLD <LLD <LLD 2014 <LLD <LLD <LLD 2015 <LLD <LLD <LLD 2016 <LLD <LLD <LLD

• Indicator locations are in the general area of the NMP-1 and J.A. FitzPatrick cooling water discharge structures.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-5

TABLE 7-5 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER Results in pCi/liter LOCATION: CONTROL Isotope Cs-137 Co-60 Year Min. Max. Mean Min. Max. Mean 1969 * * * * *

• 1974 * * * * *

• 1975 * * * * *

• 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD <LLD <LLD <LLD 1994 <LLD <LLD <LLD <LLD <LLD <LLD 1995 <LLD <LLD <LLD <LLD <LLD <LLD 1996 <LLD <LLD <LLD <LLD <LLD <LLD 1997 <LLD <LLD <LLD <LLD <LLD <LLD 1998 <LLD <LLD <LLD <LLD <LLD <LLD 1999 <LLD <LLD <LLD <LLD <LLD <LLD 2000 <LLD <LLD <LLD <LLD <LLD <LLD 2001 <LLD <LLD <LLD <LLD <LLD <LLD 2002 <LLD <LLD <LLD <LLD <LLD <LLD 2003 <LLD <LLD <LLD <LLD <LLD <LLD 2004 <LLD <LLD <LLD <LLD <LLD <LLD 2005 <LLD <LLD <LLD <LLD <LLD <LLD 2006 <LLD <LLD <LLD <LLD <LLD <LLD 2007 <LLD <LLD <LLD <LLD <LLD <LLD 2008 <LLD <LLD <LLD <LLD <LLD <LLD 2009 <LLD <LLD <LLD <LLD <LLD <LLD 2010 <LLD <LLD <LLD <LLD <LLD <LLD 2011 <LLD <LLD <LLD <LLD <LLD <LLD 2012 <LLD <LLD <LLD <LLD <LLD <LLD 2013 <LLD <LLD <LLD <LLD <LLD <LLD 2014 <LLD <LLD <LLD <LLD <LLD <LLD 2015 <LLD <LLD <LLD <LLD <LLD <LLD 2016 <LLD <LLD <LLD <LLD <LLD <LLD

• No gamma analysis performed (not required).

Location was the City of Oswego Water Supply for 1969-1984 and the Oswego Steam Station inlet canal for 1985-Present.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-6

TABLE 7-6 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER Results in pCi/liter LOCATION: INDICATOR Isotope Cs-137 Co-60 Year Min. Max. Mean Min. Max. Mean 1969 * * * * *

• 1974 * * * * *

• 1975 * * * * *

• 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD <LLD <LLD <LLD 1994 <LLD <LLD <LLD <LLD <LLD <LLD 1995 <LLD <LLD <LLD <LLD <LLD <LLD 1996 <LLD <LLD <LLD <LLD <LLD <LLD 1997 <LLD <LLD <LLD <LLD <LLD <LLD 1998 <LLD <LLD <LLD <LLD <LLD <LLD 1999 <LLD <LLD <LLD <LLD <LLD <LLD 2000 <LLD <LLD <LLD <LLD <LLD <LLD 2001 <LLD <LLD <LLD <LLD <LLD <LLD 2002 <LLD <LLD <LLD <LLD <LLD <LLD 2003 <LLD <LLD <LLD <LLD <LLD <LLD 2004 <LLD <LLD <LLD <LLD <LLD <LLD 2005 <LLD <LLD <LLD <LLD <LLD <LLD 2006 <LLD <LLD <LLD <LLD <LLD <LLD 2007 <LLD <LLD <LLD <LLD <LLD <LLD 2008 <LLD <LLD <LLD <LLD <LLD <LLD 2009 <LLD <LLD <LLD <LLD <LLD <LLD 2010 <LLD <LLD <LLD <LLD <LLD <LLD 2011 <LLD <LLD <LLD <LLD <LLD <LLD 2012 <LLD <LLD <LLD <LLD <LLD <LLD 2013 <LLD <LLD <LLD <LLD <LLD <LLD 2014 <LLD <LLD <LLD <LLD <LLD <LLD 2015 <LLD <LLD <LLD <LLD <LLD <LLD 2016 <LLD <LLD <LLD <LLD <LLD <LLD

• No gamma analysis performed (not required).

Indicator location was the NMP 1 Inlet Canal for the period 1969-1973, and the JAF Inlet Canal for 1974-Present.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-7

TABLE 7-7 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM Results in pCi/liter LOCATION: CONTROL

• Isotope Tritium Year Min. Max. Mean 1969 No Data No Data No Data 1974 <MDL <MDL <MDL 1975 311 414 362 1989 143 217 186 1990 260 320 290 1991 180 200 190 1992 190 310 243 1993 160 230 188 1994 250 250 250 1995 230 230 230 1996 <LLD <LLD <LLD 1997 <LLD <LLD <LLD 1998 190 190 190 1999 220 510 365 2000 196 237 212 2001 <LLD <LLD <LLD 2002 <LLD <LLD <LLD 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD 2006 <LLD <LLD <LLD 2007 <LLD <LLD <LLD 2008 <LLD <LLD <LLD 2009 <LLD <LLD <LLD 2010 <LLD <LLD <LLD 2011 <LLD <LLD <LLD 2012 <LLD <LLD <LLD 2013 <LLD <LLD <LLD 2014 <LLD <LLD <LLD 2015 <LLD <LLD <LLD 2016 <LLD <LLD <LLD

• Control location is the City of Oswego, drinking water for 1969-1984 and the Oswego Steam Station inlet canal for 1985-Present.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-8

TABLE 7-8 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM Results in pCi/liter LOCATION: INDICATOR

• Isotope Tritium Year Min. Max. Mean 1969 No Data No Data No Data 1974 380 500 440 1975 124 482 335 1989 135 288 225 1990 220 290 250 1991 250 390 310 1992 240 300 273 1993 200 280 242 1994 180 260 220 1995 320 320 320 1996 <LLD <LLD <LLD 1997 160 160 160 1998 190 190 190 1999 180 270 233 2000 161 198 185 2001 <LLD <LLD <LLD 2002 297 297 297 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD 2006 <LLD <LLD <LLD 2007 <LLD <LLD <LLD 2008 <LLD <LLD <LLD 2009 <LLD <LLD <LLD 2010 <LLD <LLD <LLD 2011 <LLD <LLD <LLD 2012 <LLD <LLD <LLD 2013 <LLD <LLD <LLD 2014 <LLD <LLD <LLD 2015 <LLD <LLD <LLD 2016 <LLD <LLD <LLD

• Indicator location was the NMP-1 Inlet Canal during the period 1969-1973, and the JAF Inlet Canal for 1974-Present.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-9

TABLE 7-9 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA Results in pCi/m3 LOCATION: CONTROL

• Isotope Gross Beta Year Min. Max. Mean 1969 0.130 0.540 0.334 1974 0.001 0.808 0.121 1975 0.008 0.294 0.085 1989 0.007 0.039 0.017 1990 0.003 0.027 0.013 1991 0.007 0.028 0.014 1992 0.006 0.020 0.012 1993 0.007 0.022 0.013 1994 0.008 0.025 0.015 1995 0.006 0.023 0.014 1996 0.008 0.023 0.014 1997 0.006 0.025 0.013 1998 0.004 0.034 0.014 1999 0.010 0.032 0.017 2000 0.006 0.027 0.015 2001 0.006 0.034 0.016 2002 0.008 0.027 0.016 2003 0.004 0.032 0.015 2004 0.008 0.032 0.016 2005 0.008 0.034 0.019 2006 0.007 0.033 0.016 2007 0.008 0.028 0.016 2008 0.007 0.031 0.015 2009 0.007 0.030 0.016 2010 0.004 0.026 0.014 2011 0.008 0.034 0.018 2012 0.005 0.025 0.016 2013 0.006 0.031 0.016 2014 0.006 0.030 0.016 2015 0.008 0.038 0.016 2016 0.008 0.023 0.014

• Locations used for 1977-1984 were C offsite, D1 offsite, D2 offsite, E offsite, F offsite, and G offsite. Control location R5 offsite was used for 1986-Present (formerly C offsite location).

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 10

TABLE 7-10 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA Results in pCi/m3 LOCATION: INDICATOR

• Isotope Gross Beta Year Min. Max. Mean 1969 0.130 0.520 0.320 1974 0.003 0.885 0.058 1975 0.001 0.456 0.067 1989 0.007 0.041 0.017 1990 0.006 0.023 0.014 1991 0.006 0.033 0.015 1992 0.005 0.024 0.013 1993 0.005 0.023 0.014 1994 0.006 0.024 0.015 1995 0.004 0.031 0.014 1996 0.006 0.025 0.013 1997 0.001 0.018 0.010 1998 0.002 0.040 0.015 1999 0.009 0.039 0.017 2000 0.005 0.033 0.015 2001 0.004 0.037 0.016 2002 0.006 0.026 0.016 2003 0.005 0.035 0.015 2004 0.003 0.036 0.016 2005 0.007 0.041 0.019 2006 0.005 0.035 0.015 2007 0.007 0.028 0.016 2008 0.004 0.030 0.016 2009 0.006 0.032 0.016 2010 0.005 0.030 0.015 2011 0.007 0.034 0.018 2012 0.004 0.031 0.016 2013 0.007 0.032 0.016 2014 0.007 0.028 0.016 2015 0.007 0.041 0.016 2016 0.008 0.025 0.015

• Locations used for 1969-1973 were D1 onsite, D2 onsite, E onsite, F onsite and G onsite. Locations used for 1974-1984 were D1 onsite, D2 onsite, E onsite, F onsite, G onsite, H onsite, I onsite, J onsite and K onsite, as applicable. 1986 - Present: locations were R1 offsite, R2 offsite, R3 offsite, and R4 offsite.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 11

TABLE 7-11 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES Results in pCi/m3 LOCATION: CONTROL **

Isotope Cs-137 Co-60 Year Min. Max. Mean Min. Max. Mean 1969 * * * * *

• 1974 * * * * *

• 1975 * * * * *

• 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD <LLD <LLD <LLD 1994 <LLD <LLD <LLD <LLD <LLD <LLD 1995 <LLD <LLD <LLD <LLD <LLD <LLD 1996 <LLD <LLD <LLD <LLD <LLD <LLD 1997 <LLD <LLD <LLD <LLD <LLD <LLD 1998 <LLD <LLD <LLD <LLD <LLD <LLD 1999 <LLD <LLD <LLD <LLD <LLD <LLD 2000 <LLD <LLD <LLD <LLD <LLD <LLD 2001 <LLD <LLD <LLD <LLD <LLD <LLD 2002 <LLD <LLD <LLD <LLD <LLD <LLD 2003 <LLD <LLD <LLD <LLD <LLD <LLD 2004 <LLD <LLD <LLD <LLD <LLD <LLD 2005 <LLD <LLD <LLD <LLD <LLD <LLD 2006 <LLD <LLD <LLD <LLD <LLD <LLD 2007 <LLD <LLD <LLD <LLD <LLD <LLD 2008 <LLD <LLD <LLD <LLD <LLD <LLD 2009 <LLD <LLD <LLD <LLD <LLD <LLD 2010 <LLD <LLD <LLD <LLD <LLD <LLD 2011 <LLD <LLD <LLD <LLD <LLD <LLD 2012 <LLD <LLD <LLD <LLD <LLD <LLD 2013 <LLD <LLD <LLD <LLD <LLD <LLD 2014 <LLD <LLD <LLD <LLD <LLD <LLD 2015 <LLD <LLD <LLD <LLD <LLD <LLD 2016 <LLD <LLD <LLD <LLD <LLD <LLD

• No data available (not required prior to 1977).

• • Locations included composites of offsite air monitoring locations for 1977-1984. Sample location included only R5 air monitoring location for 1985-Present.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 12

TABLE 7-12 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES Results in pCi/m3 LOCATION: INDICATOR **

Isotope Cs-137 Co-60 Year Min. Max. Mean Min. Max. Mean 1969 * * * * *

• 1974 * * * * *

• 1975 * * * * *

• 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD <LLD <LLD <LLD 1994 <LLD <LLD <LLD <LLD <LLD <LLD 1995 <LLD <LLD <LLD <LLD <LLD <LLD 1996 <LLD <LLD <LLD <LLD <LLD <LLD 1997 <LLD <LLD <LLD <LLD <LLD <LLD 1998 <LLD <LLD <LLD <LLD <LLD <LLD 1999 <LLD <LLD <LLD <LLD <LLD <LLD 2000 <LLD <LLD <LLD 0.0048 0.0048 0.0048 2001 <LLD <LLD <LLD <LLD <LLD <LLD 2002 <LLD <LLD <LLD <LLD <LLD <LLD 2003 <LLD <LLD <LLD <LLD <LLD <LLD 2004 <LLD <LLD <LLD <LLD <LLD <LLD 2005 <LLD <LLD <LLD <LLD <LLD <LLD 2006 <LLD <LLD <LLD <LLD <LLD <LLD 2007 <LLD <LLD <LLD <LLD <LLD <LLD 2008 <LLD <LLD <LLD <LLD <LLD <LLD 2009 <LLD <LLD <LLD <LLD <LLD <LLD 2010 <LLD <LLD <LLD <LLD <LLD <LLD 2011 <LLD <LLD <LLD <LLD <LLD <LLD 2012 <LLD <LLD <LLD <LLD <LLD <LLD 2013 <LLD <LLD <LLD <LLD <LLD <LLD 2014 <LLD <LLD <LLD <LLD <LLD <LLD 2015 <LLD <LLD <LLD <LLD <LLD <LLD 2016 < LLD <LLD <LLD <LLD <LLD <LLD

• No data available (not required prior to 1977).

• • Locations included composites of onsite air monitoring locations for 1977-1984. Sample locations included R1 through R4 air monitoring locations for 1985-Present.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 13

TABLE 7-13 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE Results in pCi/m3 LOCATION: CONTROL

• Isotope Iodine-131 Year Min. Max. Mean 1969 ** ** **

1974 ** ** **

1975 <MDL <MDL <MDL 1989 <LLD <LLD <LLD 1990 <LLD <LLD <LLD 1991 <LLD <LLD <LLD 1992 <LLD <LLD <LLD 1993 <LLD <LLD <LLD 1994 <LLD <LLD <LLD 1995 <LLD <LLD <LLD 1996 <LLD <LLD <LLD 1997 <LLD <LLD <LLD 1998 <LLD <LLD <LLD 1999 <LLD <LLD <LLD 2000 <LLD <LLD <LLD 2001 <LLD <LLD <LLD 2002 <LLD <LLD <LLD 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD 2006 <LLD <LLD <LLD 2007 <LLD <LLD <LLD 2008 <LLD <LLD <LLD 2009 <LLD <LLD <LLD 2010 <LLD <LLD <LLD 2011 0.034 0.093 0.055 2012 <LLD <LLD <LLD 2013 <LLD <LLD <LLD 2014 <LLD <LLD <LLD 2015 <LLD <LLD <LLD 2016 <LLD <LLD <LLD

• Locations D1 offsite, D2 offsite, E offsite, F offsite and G offsite used for 1976-1984. Location R5 offsite used for 1985-Present.

• • No results - I-131 analysis not required.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

Iodine concentrations attributed to fallout from Fukushima accident.

7 - 14

TABLE 7-14 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE Results in pCi/m3 LOCATION: INDICATOR

• Isotope Iodine-131 Year Min. Max. Mean 1969 ** ** **

1974 ** ** **

1975 0.25 0.30 0.28 1989 <LLD <LLD <LLD 1990 <LLD <LLD <LLD 1991 <LLD <LLD <LLD 1992 <LLD <LLD <LLD 1993 <LLD <LLD <LLD 1994 <LLD <LLD <LLD 1995 <LLD <LLD <LLD 1996 <LLD <LLD <LLD 1997 <LLD <LLD <LLD 1998 <LLD <LLD <LLD 1999 <LLD <LLD <LLD 2000 <LLD <LLD <LLD 2001 <LLD <LLD <LLD 2002 <LLD <LLD <LLD 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD 2006 <LLD <LLD <LLD 2007 <LLD <LLD <LLD 2008 <LLD <LLD <LLD 2009 <LLD <LLD <LLD 2010 <LLD <LLD <LLD 2011 0.021 0.11 0.055 2012 <LLD <LLD <LLD 2013 <LLD <LLD <LLD 2014 <LLD <LLD <LLD 2015 <LLD <LLD <LLD 2016 <LLD <LLD <LLD

• Locations used for 1985 - Present, were R1 offsite, R2 offsite, R3 offsite, and R4 offsite.

• • No results. I-131 analysis not required.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

Iodine concentrations attributed to fallout from Fukushima accident.

7 - 15

TABLE 7-15 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem/standard month LOCATION: CONTROL * (2)

Year Min. Max. Mean Preop (Note 1) (Note 1) (Note 1) 1974 2.7 8.9 5.6 1975 4.8 6.0 5.5 1989 (2.9) 2.9 (6.4) 5.6 (4.7) 4.6 1990 (3.7) 3.7 (6.0) 5.9 (4.8) 4.6 1991 (3.8) 3.8 (5.4) 5.3 (4.5) 4.3 1992 (2.6) 2.6 (5.0) 4.7 (4.1) 3.9 1993 (3.4) 3.4 (5.6) 5.2 (4.4) 4.3 1994 (3.1) 3.1 (5.0) 4.6 (4.1) 3.9 1995 (3.4) 3.4 (5.7) 4.9 (4.4) 4.2 1996 (3.4) 3.4 (5.6) 5.6 (4.3) 4.2 1997 (3.7) 3.9 (6.2) 5.2 (4.7) 4.6 1998 (3.7) 3.7 (5.6) 4.8 (4.4) 4.2 1999 (3.6) 3.7 (7.1) 4.7 (4.6) 4.4 2000 (3.7) 3.7 (7.3) 5.5 (4.7) 4.3 2001 (3.6) 3.9 (5.4) 5.0 (4.4) 4.4 2002 (3.4) 3.4 (5.5) 5.2 (4.3) 4.1 2003 (3.4) 3.4 (5.5) 4.8 (4.2) 4.2 2004 (3.3) 3.3 (5.9) 5.9 (4.3) 4.5 2005 (3.3) 3.4 (5.1) 4.5 (4.1) 4.0 2006 (3.3) 3.3 (5.3) 5.3 (4.1) 4.3 2007 (3.2) 3.2 (5.8) 5.8 (4.4) 4.6 2008 (3.3) 3.3 (5.1) 5.1 (4.1) 4.3 2009 (3.2) 3.2 (4.8) 4.8 (3.9) 4.0 2010 (2.8) 2.8 (4.6) 4.6 (3.9) 3.9 2011 (2.6) 2.6 (5.5) 5.5 (4.0) 4.1 2012 (3.6) 3.6 (5.0) 5.0 (4.0) 4.2 2013 (3.2) 3.2 (4.9) 4.9 (3.9) 4.0 2014 (3) 3.3 5.0 4.1 2015 3.0 5.4 4.1 2016 3.6 5.2 4.2

• TLD #8 and 14 established 1974, TLD #49 established 1980, TLD #111 established 1988, TLD #113 established 1991.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for JAFNPP.

(1) Data not available.

(2) Data in parentheses is control data determined using TLDs #8, 14, 49, 111 and 113.

(3) Starting in 2014, only data from locations 8, 14, and 49 are reported.

7 - 16

TABLE 7-16 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION: SITE BOUNDARY **

Year Min. Max. Mean Preop * *

• 1974 * *

• 1975 * *

• 1989 4.5 5.2 4.8 1990 4.5 5.4 4.8 1991 4.3 5.5 4.8 1992 3.7 4.6 4.2 1993 3.8 4.8 4.3 1994 2.8 4.9 4.0 1995 3.5 5.1 4.4 1996 3.2 5.3 4.1 1997 3.5 5.9 4.6 1998 3.7 5.1 4.4 1999 3.3 7.5 4.7 2000 3.6 6.8 4.5 2001 3.6 5.3 4.5 2002 3.5 5.1 4.3 2003 3.2 4.9 4.3 2004 3.3 6.4 4.4 2005 3.4 4.8 4.2 2006 3.5 4.7 4.1 2007 3.2 5.4 4.3 2008 3.2 4.8 4.0 2009 3.1 4.5 3.9 2010 3.3 4.3 3.9 2011 3.1 5.3 4.1 2012 3.6 4.8 4.1 2013 3.5 4.7 3.9 2014 3.3 4.6 3.9 2015 2.9 5.1 4.0 2016 3.5 4.8 4.0

• Data not available (not required prior to 1985).

TLD #23, 75, 76, 77, 85, 86 and 87 are in close proximity to operational buildings along the north boundary. This boundary is the lakeshore and is considered to be generally not accessible to the public. These locations are not used in the site boundary dose determination.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

• • TLDs used for statistics: 7, 18, 78, 79, 80, 81, 82, 83 & 84.

7 - 17

TABLE 7-17 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION: OFFSITE SECTORS **

Year Min. Max. Mean Preop * *

• 1974 * *

• 1975 * *

• 1989 2.5 6.8 4.9 1990 3.6 6.3 4.7 1991 3.6 5.8 4.7 1992 2.9 5.0 4.1 1993 3.4 6.3 4.5 1994 3.0 5.1 4.0 1995 3.2 5.2 4.3 1996 3.2 5.3 4.2 1997 3.5 5.8 4.4 1998 3.5 5.0 4.2 1999 3.6 5.6 4.4 2000 3.4 6.6 4.5 2001 3.6 5.4 4.4 2002 3.1 5.3 4.2 2003 3.4 4.8 4.1 2004 3.2 6.7 4.4 2005 3.2 4.7 4.0 2006 3.3 4.4 4.0 2007 3.1 5.1 4.2 2008 3.2 4.5 3.8 2009 3.3 4.5 3.9 2010 3.0 4.4 3.9 2011 3.0 5.3 4.0 2012 3.5 4.6 4.0 2013 3.2 4.5 3.8 2014 3.2 4.4 3.8 2015 2.9 4.8 3.9 2016 3.3 4.6 3.9

• Data not available (not required prior to 1985).

• • Includes TLD numbers 88, 89, 90, 91, 92, 93, 94 and 95.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 18

TABLE 7-18 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION: SPECIAL INTEREST **

Year Min. Max. Mean Preop * *

• 1974 * *

• 1975 * *

• 1989 2.1 6.4 4.9 1990 3.2 6.3 4.8 1991 2.9 5.6 4.4 1992 3.0 4.8 4.1 1993 3.2 5.8 4.5 1994 2.9 4.8 4.1 1995 3.6 4.8 4.2 1996 3.2 5.1 4.2 1997 3.5 6.2 4.6 1998 3.7 5.6 4.4 1999 3.6 7.1 4.6 2000 3.6 7.3 4.7 2001 3.8 5.4 4.4 2002 3.5 5.5 4.2 2003 3.4 5.5 4.3 2004 3.0 5.9 4.2 2005 3.4 5.1 4.1 2006 3.5 5.3 4.1 2007 3.0 5.8 4.3 2008 3.1 5.1 4.0 2009 3.1 4.5 3.8 2010 3.2 4.7 3.9 2011 2.9 4.9 4.0 2012 3.4 4.7 4.0 2013 3.2 4.5 3.8 2014 2.9 4.3 3.8 2015 2.5 4.6 3.9 2016 3.5 4.4 3.9

• Data not available (not required prior to 1985).

• • Includes TLD numbers 15, 56, 58, 96, 97 and 98.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 19

TABLE 7-19 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION: ONSITE INDICATOR **

Year Min. Max. Mean Preop * *

• 1974 3.1 10.6 5.7 1975 4.6 16.0 7.3 1989 2.7 13.1 6.0 1990 3.6 12.9 5.5 1991 3.2 11.6 5.4 1992 3.2 5.6 4.3 1993 3.1 13.6 5.2 1994 2.8 14.3 5.1 1995 3.5 28.6 6.2 1996 3.1 32.6 6.4 1997 3.5 28.8 8.1 1998 3.6 28.8 6.2 1999 3.3 28.4 6.6 2000 3.7 16.5 5.6 2001 3.8 14.5 5.6 2002 3.5 13.6 5.3 2003 3.2 12.9 5.3 2004 3.3 13.2 5.4 2005 3.4 14.1 5.4 2006 3.5 14.4 5.3 2007 3.2 14.8 5.6 2008 3.2 13.8 5.2 2009 3.1 13.6 4.9 2010 3.3 13.3 4.8 2011 3.1 13.0 5.1 2012 3.5 11.8 4.9 2013 3.3 12.2 5.0 2014 3.3 12.9 4.9 2015 2.8 13.2 5.1 2016 3.5 11.3 4.8

• No data available.

• • 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 - Present).

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 20

TABLE 7-20 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION: OFFSITE INDICATOR **

Year Min. Max. Mean Preop * *

• 1974 2.4 8.9 5.3 1975 4.5 7.1 5.5 1989 2.8 6.4 4.6 1990 3.8 6.1 4.8 1991 3.4 5.8 4.5 1992 3.1 5.2 4.1 1993 3.2 5.7 5.0 1994 3.0 5.1 4.1 1995 3.9 5.7 4.4 1996 3.3 5.5 4.1 1997 3.7 6.2 4.7 1998 3.9 5.6 4.5 1999 3.8 7.1 4.6 2000 3.8 7.3 4.6 2001 3.7 5.9 4.6 2002 3.6 5.5 4.4 2003 3.1 5.5 4.4 2004 3.2 6.5 4.5 2005 3.6 5.1 4.2 2006 3.9 5.3 4.2 2007 3.4 4.9 4.3 2008 3.3 4.5 4.0 2009 3.3 4.1 3.8 2010 3.5 4.0 3.7 2011 3.2 4.8 4.0 2012 3.6 4.3 4.0 2013 3.5 4.3 3.9 2014 3.3 4.2 3.8 2015 3.0 4.5 3.9 2016 3.7 4.5 4.0

• No data available.

• • Includes TLD numbers 9, 10, 11, 12 and 13.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 21

TABLE 7-21 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Results in pCi/liter LOCATION: CONTROL **

Isotope Cs-137 I-131 Year Min. Max. Mean Min. Max. Mean 1969 * * * * *

• 1974 * * * * *

• 1975 * * * * *

• 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD <LLD <LLD <LLD 1994 <LLD <LLD <LLD <LLD <LLD <LLD 1995 <LLD <LLD <LLD <LLD <LLD <LLD 1996 <LLD <LLD <LLD <LLD <LLD <LLD 1997 <LLD <LLD <LLD <LLD <LLD <LLD 1998 <LLD <LLD <LLD <LLD <LLD <LLD 1999 <LLD <LLD <LLD <LLD <LLD <LLD 2000 <LLD <LLD <LLD <LLD <LLD <LLD 2001 <LLD <LLD <LLD <LLD <LLD <LLD 2002 <LLD <LLD <LLD <LLD <LLD <LLD 2003 <LLD <LLD <LLD <LLD <LLD <LLD 2004 <LLD <LLD <LLD <LLD <LLD <LLD 2005 <LLD <LLD <LLD <LLD <LLD <LLD 2006 <LLD <LLD <LLD <LLD <LLD <LLD 2007 <LLD <LLD <LLD <LLD <LLD <LLD 2008 <LLD <LLD <LLD <LLD <LLD <LLD 2009 <LLD <LLD <LLD <LLD <LLD <LLD 2010 <LLD <LLD <LLD <LLD <LLD <LLD 2011 <LLD <LLD <LLD <LLD <LLD <LLD 2012 <LLD <LLD <LLD <LLD <LLD <LLD 2013 <LLD <LLD <LLD <LLD <LLD <LLD 2014 <LLD <LLD <LLD <LLD <LLD <LLD 2015 <LLD <LLD <LLD <LLD <LLD <LLD 2016 <LLD <LLD <LLD <LLD <LLD <LLD

• No data available (sample not required).

• • Location used was an available milk sample location in a least prevalent wind direction greater than ten miles from the site.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 22

TABLE 7-22 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Results in pCi/liter LOCATION: INDICATOR Isotope Cs-137 I-131 Year Min. Max. Mean Min. Max. Mean 1969 * * * * *

• 1974 1.6 39 10.5 0.70 2.00 1.23 1975 6.0 22 16 0.01 2.99 0.37 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD <LLD <LLD <LLD 1994 <LLD <LLD <LLD <LLD <LLD <LLD 1995 <LLD <LLD <LLD <LLD <LLD <LLD 1996 <LLD <LLD <LLD <LLD <LLD <LLD 1997 <LLD <LLD <LLD 0.25 0.44 0.35 1998 <LLD <LLD <LLD <LLD <LLD <LLD 1999 <LLD <LLD <LLD <LLD <LLD <LLD 2000 <LLD <LLD <LLD <LLD <LLD <LLD 2001 <LLD <LLD <LLD <LLD <LLD <LLD 2002 <LLD <LLD <LLD <LLD <LLD <LLD 2003 <LLD <LLD <LLD <LLD <LLD <LLD 2004 <LLD <LLD <LLD <LLD <LLD <LLD 2005 <LLD <LLD <LLD <LLD <LLD <LLD 2006 <LLD <LLD <LLD <LLD <LLD <LLD 2007 <LLD <LLD <LLD <LLD <LLD <LLD 2008 <LLD <LLD <LLD <LLD <LLD <LLD 2009 <LLD <LLD <LLD <LLD <LLD <LLD 2010 <LLD <LLD <LLD <LLD <LLD <LLD 2011 <LLD <LLD <LLD <LLD <LLD <LLD 2012 <LLD <LLD <LLD <LLD <LLD <LLD 2013 <LLD <LLD <LLD <LLD <LLD <LLD 2014 <LLD <LLD <LLD <LLD <LLD <LLD 2015 <LLD <LLD <LLD <LLD <LLD <LLD 2016 <LLD <LLD <LLD <LLD <LLD <LLD

• No data available (sample not required).

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 23

TABLE 7-23 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS Results in pCi/g (wet)

LOCATION: CONTROL

• Isotope Cs-137 Year Min. Max. Mean 1969 ** ** **

1974 ** ** **

1975 ** ** **

1989 <LLD <LLD <LLD 1990 <LLD <LLD <LLD 1991 <LLD <LLD <LLD 1992 <LLD <LLD <LLD 1993 0.008 0.008 0.008 1994 <LLD <LLD <LLD 1995 <LLD <LLD <LLD 1996 <LLD <LLD <LLD 1997 <LLD <LLD <LLD 1998 <LLD <LLD <LLD 1999 <LLD <LLD <LLD 2000 <LLD <LLD <LLD 2001 <LLD <LLD <LLD 2002 <LLD <LLD <LLD 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD 2006 <LLD <LLD <LLD 2007 <LLD <LLD <LLD 2008 <LLD <LLD <LLD 2009 <LLD <LLD <LLD 2010 <LLD <LLD <LLD 2011 <LLD <LLD <LLD 2012 <LLD <LLD <LLD 2013 <LLD <LLD <LLD 2014 <LLD <LLD <LLD 2015 <LLD <LLD <LLD 2016 <LLD <LLD <LLD

• Locations was an available food product sample location in a least prevalent wind direction greater than ten miles from the site.

• • No data available (control samples not required).

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 24

TABLE 7-24 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS Results in pCi/g (wet)

LOCATION: INDICATOR

• Isotope Cs-137 Year Min. Max. Mean 1969 ** ** **

1974 0.04 0.34 0.142 1975 <MDL <MDL <MDL 1989 0.011 0.011 0.011 1990 <LLD <LLD <LLD 1991 0.039 0.039 0.039 1992 <LLD <LLD <LLD 1993 <LLD <LLD <LLD 1994 0.006 0.012 0.010 1995 0.011 0.012 0.012 1996 <LLD <LLD <LLD 1997 0.013 0.013 0.013 1998 <LLD <LLD <LLD 1999 0.007 0.007 0.007 2000 <LLD <LLD <LLD 2001 <LLD <LLD <LLD 2002 <LLD <LLD <LLD 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD 2006 <LLD <LLD <LLD 2007 <LLD <LLD <LLD 2008 <LLD <LLD <LLD 2009 <LLD <LLD <LLD 2010 <LLD <LLD <LLD 2011 <LLD <LLD <LLD 2012 <LLD <LLD <LLD 2013 <LLD <LLD <LLD 2014 <LLD <LLD <LLD 2015 <LLD <LLD <LLD 2016 <LLD <LLD <LLD

• Indicator locations were available downwind locations within ten miles of the site and with high deposition potential.

• • No data available (control samples not required).

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 25

8.0 QUALITY ASSURANCE / QUALITY CONTROL PROGRAM 8.1 PROGRAM DESCRIPTION The Offsite Dose Calculation Manual (ODCM), Part 1, Section 5.3 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 Teledyne Brown Engineering (TBE) Environmental Services laboratory has engaged the services of Eckert &

Ziegler Analytics, Incorporated in Atlanta, Georgia, The Department of Energys (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) located in Idaho Falls, Idaho, and Environmental Resource Associates (ERA) in Golden, Co.

The Interlaboratory Comparison providers supply 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 Teledyne Brown Engineering Environmental Services laboratory using standard laboratory procedures.

8-1

8.2 PROGRAM SCHEDULE SAMPLE PROVIDER SAMPLE LABORATORY ECKERT & ZIEGLER MEDIA ANALYSIS ANALYTICS Milk I-131 4 Milk Mixed Gamma 4 Air I-131 4 Air Mixed Gamma 4 Soil Mixed Gamma 2 SAMPLE LABORATORY SAMPLE PROVIDER MEDIA ANALYSIS DOE MAPEP Air Gr-Beta 2 Vegetation Mixed Gamma 2 SAMPLE LABORATORY SAMPLE PROVIDER MEDIA ANALYSIS ERA Water I-131 2 Water Mixed Gamma 2 Water H-3 2 TOTAL SAMPLE INVENTORY 28 8.3 ACCEPTANCE CRITERIA Each sample result is evaluated to determine the accuracy and precision of the laboratorys analysis result. The sample evaluation method is discussed below.

8.3.1 SAMPLE RESULTS EVALUATION Analytics:

Analytics evaluation report provides a ratio of TBEs result and Analytics known value.

8-2

Since flag values are not assigned, TBE evaluates the reported ratios based on internal QC requirements, which are based on the DOE/MAPEP criteria. The ratio of 0.80 to 1.20 is evaluated as acceptable. The ratios of 0.70 to 0.79 and 1.21 to 1.30 are evaluated as acceptable with warning.

DOE Evaluation Criteria (Handbook for the Department of Energys Mixed Analyte Performance Evaluation Program (MAPEP), Revision 13 (June 2012), pp 37-38, retrieved from http://www.id.energy.gov/resl/mapep/handbookv13.pdf )

MAPEP:

MAPEPs evaluation report provides an acceptance range with associated flag values.

The MAPEP defines three levels of performance: Acceptable (flag = A), Acceptable with Warning (flag = W), and Not Acceptable (flag = N). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value.

Performance is acceptable with warning when a mean result falls in the range from +/-20%

to +/-30% of the reference value (i.e., 20% < bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable.

False positive/negative testing and sensitivity evaluations are used in radiological performance evaluations. The specific analytes used for testing vary among performance evaluation test sessions.

The MAPEP program uses false positive testing to identify laboratory results that indicate the presence of a particular radionuclide in a MAPEP sample when, in fact, the actual activity of the radionuclide is far below the detection limit of the measurement. Not acceptable (N) performance, and hence a false positive result, is indicated when the range encompassing the result, plus or minus the total uncertainty at three standard deviations, does not include zero (e.g. 2.5 +/- 0.2; range of 1.9 - 3.1). Statistically, the probability that a result can exceed the absolute value of its total uncertainty at three standard deviations by chance alone is less than 1%. The MAPEP uses a three standard deviation criterion for the false positive test to ensure confidence about issuing a false positive performance evaluation. A result that is greater than three times the total uncertainty of the measurement represents a statistically positive detection with over 99% confidence.

Sensitivity evaluations are routinely performed to complement the false positive tests. In a sensitivity evaluation the radionuclide is present at or near the detection limit, and the difference between the report result and the MAPEP reference value is compared to the 8-3

propagated combined total uncertainties. The results are evaluated at three standard deviations. If the observed difference is greater than three time the combined total uncertainty, the sensitivity evaluation in Not Acceptable. The probability that such a difference can occur by chance alone is less than 1%. If the participant did not report a statistically positive result, a Not Detected is noted in the text field of the MAPEP performance report. A non-detect is potentially a false negative result, dependent upon the laboratorys detection limit for the radionuclide.

False negative tests are also performed in combination with the sensitivity evaluations. In this scenario, the sensitivity of the reported measurement indicates that the known specific activity of the targeted radionuclide in the performance evaluation sample should have been detected, but was not, and a Not Acceptable performance evaluation is issued.

The uncertainty of the MAPEP reference value and of the reported result at three standard deviations is used for the false negative test.

The false positive/negative and sensitivity evaluation tests are conducted in a manner that assists the participants with their measurement uncertainty estimates and helps ensure they are not under estimating or over inflating their total uncertainties. If the total uncertainty is over inflated to try to pass a false positive test, it will result in a Not Detected if the test is actually a sensitivity evaluation, and vice versa for a false positive test. False negatives and failed sensitivity evaluations can also result from under estimating the total uncertainty. An accurate estimate of measurement uncertainty is required for consistent performance at the acceptable level.

ERA:

The ERAs evaluation report provides an acceptance range for control and warning limits with associated flag values. The ERAs acceptance limits are established per the USEPA, NELAC, state specific performance testing program requirements or ERAs SOP for the Generation of Performance Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.

8.4 PROGRAM RESULTS

SUMMARY

The Interlaboratory Comparison Program numerical results for the TBE Environmental Services laboratory are provided on Table 8-3.

8-4

8.4.1 ECKERT & ZIEGLER ANALYTICS, DOE MAPEP, and ERA QA SAMPLES RESULTS For the TBE laboratory, 156 out of 160 analyses performed met the specified acceptance criteria, for a 97.5 agreement ratio. Four analyses (Milk - Sr-90, Vegetation - Sr-90, and Water - H-3 samples) did not meet the specified acceptance criteria for the following reasons and were addressed through the TBE Corrective Action Program.

Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained at commercial nuclear power facilities.

1. Teledyne Brown Engineerings MAPEP March 2016 air particulate cross check sample is now being provided to TBE by Analytics. MAPEPs policy is to evaluate as failed non-reported nuclides that were reported in the previous study. NRC 16-14 a-Since the Sr-90 was reported in the previous MAPEP study but not in this study, MAPEP evaluated the Sr-90 for Soil as failed. NCR 16-14 b-The MAPEP March 2016 Sr-90 in vegetation was evaluated as failing a false positive test. In reviewing the data that was reported vs the data in LIMS, it was found that the error was incorrectly reported as 0.023 rather than the correct value of 0.230. If the value had been reported with the activity and correct uncertainty of 0.301 +/- 0.230, MAPEP would have evaluated the result as acceptable. NCR 16-14

2. Teledyne Brown Engineerings Analytics March 2016 milk Sr-90 result of 15 +/- .125 pCi/L was higher than the known value of 11.4 pCi/L with a ratio of 1.32. The upper ratio of 1.30 (acceptable with warning) was exceeded. After an extensive review of the data it is believed the technician did not rinse the filtering apparatus properly and some cross contamination from one of the internal laboratory spike samples may have been transferred to the analytics sample. We feel the issue is specific to the March 2016 Analytics sample. NCR 16-26

3. Teledyne Brown Engineerings ERA November 2016 sample for H-3 in water was evaluated as failing. A result of 918 pCi/L was reported incorrectly due to a data entry issue. If the correct value of 9180 had been reported, ERA would have evaluated the result as acceptable. NCR 16-34

4. Teledyne Brown Engineerings Analytics December 2016 milk Sr-90 sample result of 14.7

+/- .26 pCi/L was higher than the known value of 10 pCi/L with a ratio of 1.47. The upper ratio of 1.30 (acceptable with warning) was exceeded. The technician entered the wrong aliquot into the LIMS system. To achieve a lower error term TBE uses a larger aliquot of 1.2L (Normally we use .6L for client samples). If the technion had entered an aliquot of 1.2L into the LIMS system, the result would have been 12.2 pCi/L, which would have been considered acceptable. NCR 16-35 8-5

Table 8-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

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

March 2016 E11476 Milk Sr-89 pCi/L 97 86.7 1.12 A Sr-90 pCi/L 15 11.4 1.32 N(2)

E11477 Milk I-131 pCi/L 85.9 82.2 1.05 A Ce-141 pCi/L 106 98.4 1.08 A Cr-51 pCi/L 255 243 1.05 A Cs-134 pCi/L 134 130 1.03 A Cs-137 pCi/L 174 161 1.08 A Co-58 pCi/L 123 117 1.05 A Mn-54 pCi/L 141 117 1.21 W Fe-59 pCi/L 152 131 1.16 A Zn-65 pCi/L 193 179 1.08 A Co-60 pCi/L 259 244 1.06 A E11479 AP Ce-141 pCi 69 81.1 0.85 A Cr-51 pCi 242 201 1.20 W Cs-134 pCi 98.1 107.0 0.92 A Cs-137 pCi 136 133 1.02 A Co-58 pCi 91.9 97 0.95 A Mn-54 pCi 98.6 96.2 1.02 A Fe-59 pCi 98.8 108 0.91 A Zn-65 pCi 131 147 0.89 A Co-60 pCi 209 201 1.04 A E11478 Charcoal I-131 pCi 85.3 88.3 0.97 A E11480 Water Fe-55 pCi/L 1800 1666 1.08 A June 2016 E11537 Milk Sr-89 pCi/L 94.4 94.4 1.00 A Sr-90 pCi/L 13.4 15.4 0.87 A E11538 Milk I-131 pCi/L 96.8 94.5 1.02 A Ce-141 pCi/L 129 139 0.93 A Cr-51 pCi/L 240 276 0.87 A Cs-134 pCi/L 157 174 0.90 A Cs-137 pCi/L 117 120 0.98 A Co-58 pCi/L 131 142 0.92 A Mn-54 pCi/L 128 125 1.02 A Fe-59 pCi/L 132 122 1.08 A Zn-65 pCi/L 235 235 1.00 A Co-60 pCi/L 169 173 0.98 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.

(2) NCR 16-26 was initiated 8-6

Table 8-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

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

June 2016 E11539 Charcoal I-131 pCi 86.1 89.4 0.96 A E11540 AP Ce-141 pCi 105 99.8 1.05 A Cr-51 pCi 216 198.0 1.09 A Cs-134 pCi 113 125 0.90 A Cs-137 pCi 94.5 86.6 1.09 A Co-58 pCi 101 102 0.99 A Mn-54 pCi 88.8 90.2 0.98 A Fe-59 pCi 82 87.5 0.94 A Zn-65 pCi 174 169 1.03 A Co-60 pCi 143 124 1.15 A E11541 Water Fe-55 pCi/L 164 186 0.88 A September 2016 E11609 Milk Sr-89 pCi/L 90 90.9 0.99 A Sr-90 pCi/L 13.3 13.7 0.97 A E11610 Milk I-131 pCi/L 80.4 71.9 1.12 A Ce-141 pCi/L 81.3 93 0.87 A Cr-51 pCi/L 198 236 0.84 A Cs-134 pCi/L 122 136 0.90 A Cs-137 pCi/L 119 119 1.00 A Co-58 pCi/L 92.2 97.4 0.95 A Mn-54 pCi/L 156 152 1.03 A Fe-59 pCi/L 97.5 90.6 1.08 A Zn-65 pCi/L 189 179 1.06 A Co-60 pCi/L 131 135 0.97 A E11611 Charcoal I-131 pCi 52.4 59.9 0.87 A E11612 AP Ce-141 pCi 67.5 63.6 1.06 A Cr-51 pCi 192 161.0 1.19 A Cs-134 pCi 91.4 92.6 0.99 A Cs-137 pCi 93.9 80.8 1.16 A Co-58 pCi 66 66.4 0.99 A Mn-54 pCi 104 104 1.00 A Fe-59 pCi 60.5 61.8 0.98 A Zn-65 pCi 140 122 1.15 A Co-60 pCi 119 91.9 1.29 W (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.

8-7

Table 8-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

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

September 2016 E11613 Water Fe-55 pCi/L 1990 1670 1.19 A E11614 Soil Ce-141 pCi/g 0.153 0.175 0.87 A Cr-51 pCi/g 0.482 0.441 1.09 A Cs-134 pCi/g 0.270 0.254 1.06 A Cs-137 pCi/g 0.313 0.299 1.05 A Co-58 pCi/g 0.177 0.182 0.97 A Mn-54 pCi/g 0.340 0.285 1.19 A Fe-59 pCi/g 0.206 0.17 1.21 W Zn-65 pCi/g 0.388 0.335 1.16 A Co-60 pCi/g 0.284 0.252 1.13 A December 2016 E11699 Milk Sr-89 pCi/L 95 74.2 1.28 W Sr-90 pCi/L 14.7 10 1.47 N(3)

E11700 Milk I-131 pCi/L 97.5 97.4 1.00 A Ce-141 pCi/L 136 143 0.95 A Cr-51 pCi/L 247 280 0.88 A Cs-134 pCi/L 164 178 0.92 A Cs-137 pCi/L 120 126 0.95 A Co-58 pCi/L 139 146 0.95 A Mn-54 pCi/L 126 129 0.98 A Fe-59 pCi/L 114 125 0.91 A Zn-65 pCi/L 237 244 0.97 A Co-60 pCi/L 168 178 0.94 A E11701 Charcoal I-131 pCi 95.6 98 0.98 A E11702 AP Ce-141 pCi 91.7 97.7 0.94 A Cr-51 pCi 210 192.0 1.09 A Cs-134 pCi 122 122 1.00 A Cs-137 pCi 93.9 86.4 1.09 A Co-58 pCi 92 100 0.92 A Mn-54 pCi 93.7 88.5 1.06 A Fe-59 pCi 84.9 85.4 0.99 A Zn-65 pCi 176 167 1.05 A Co-60 pCi 151 122 1.24 W E11730 AP Sr-89 pCi 79.7 92 0.87 A Sr-90 pCi 10 12.5 0.80 A E11703 Water Fe-55 pCi/L 2180 1800 1.21 W (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.

(3) NCR 16-35 was initiated 8-8

Table 8-2 DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)

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

March 2016 16-MaW34 Water Am-241 Bq/L 0.008 (1) A Ni-63 Bq/L 12.4 12.3 8.6-16.0 A Pu-238 Bq/L 1.4900 1.2440 0.871-1.617 A Pu-239/240 Bq/L 0.729 0.641 0.449-0.833 A 16-MaS34 Soil Ni-63 Bq/kg 1140 1250.0 875-1625 A Sr-90 Bq/kg 8.15 (1) A 16-RdF34 AP U-234/233 Bq/sample 0.1620 0.1650 0.116-0.215 A U-238 Bq/sample 0.163 0.172 0.120-0.224 A 16-GrF34 AP Gr-A Bq/sample 0.608 1.20 0.36-2.04 A Gr-B Bq/sample 0.8060 0.79 0.40-1.19 A 16-RdV34 Vegetation Cs-134 Bq/sample 10.10 10.62 7.43-13.81 A Cs-137 Bq/sample 6.0 5.62 3.93-7.31 A Co-57 Bq/sample 13.3000 11.8 8.3-15.3 A Co-60 Bq/sample 0.013 (1) A Mn-54 Bq/sample 0.0150 (1) A Sr-90 Bq/sample 0.301 (1) N(4)

Zn-65 Bq/sample 10.500 9.6 6.7-12.5 A September 2016 16-MaW35 Water Am-241 Bq/L 0.626 0.814 .570-1058 W Ni-63 Bq/L 12.4 17.2 12.0-22.4 A Pu-238 Bq/L 1.23 1.13 0.79-1.47 W Pu-239/240 Bq/L 0.0318 0.013 (1) A 16-MaS35 Soil Ni-63 Bq/kg 724 990 693-1287 A Sr-90 Bq/kg 747 894 626-1162 A 16-RdF35 AP U-234/233 Bq/sample 0.160 0.15 0.105-0.195 A U-238 Bq/sample 0.157 0.156 0.109-0.203 A 16-RdV35 Vegetation Cs-134 Bq/sample -0.103 (1) A Cs-137 Bq/sample 5.64 5.54 3.88-7.20 A Co-57 Bq/sample 7.38 6.81 4.77-8.85 A Co-60 Bq/sample 4.81 4.86 3.40-6.32 A Mn-54 Bq/sample 7.4 7.27 5.09-9.45 A Sr-90 Bq/sample 0.774 0.80 0.56-1.04 A Zn-65 Bq/sample 5.46 5.4 3.78-7.02 A (1) False positive test.

(a) Teledyne Brown Engineering reported result.

(b) The MAPEP 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) DOE/MAPEP evaluation: A=acceptable, W=acceptable with warning, N=not acceptable.

(4) NCR 16-14 was initiated 8-9

Table 8-3 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)

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

May 2016 RAD-105 Water Sr-89 pCi/L 48.9 48.2 37.8 - 55.6 A Sr-90 pCi/L 25.0 28.5 20.7 - 33.1 A Ba-133 pCi/L 53.1 58.8 48.7 - 64.9 A Cs-134 pCi/L 40.9 43.3 34.6 - 47.6 A Cs-137 pCi/L 84.8 78.4 70.6 - 88.9 A Co-60 pCi/L 108 102 91.8 - 114 A Zn-65 pCi/L 226 214 193 - 251 A Gr-A pCi/L 38.9 62.7 32.9 - 77.8 A Gr-B pCi/L 41.9 39.2 26.0 - 46.7 A I-131 pCi/L 24.1 26.6 22.1 - 31.3 A U-Nat pCi/L 4.68 4.64 3.39 - 5.68 A H-3 pCi/L 7720 7840 6790 - 8620 A November 2016 RAD-107 Water Sr-89 pCi/L 43.0 43.3 33.4-50.5 A Sr-90 pCi/L 30.0 33.6 24.6-38.8 A Ba-133 pCi/L 47.8 54.9 45.4-60.7 A Cs-134 pCi/L 72.9 81.8 67.0-90.0 A Cs-137 pCi/L 189 210 189-233 A Co-60 pCi/L 58.4 64.5 58.0-73.4 A Zn-65 pCi/L 243 245 220-287 A Gr-A pCi/L 37.2 68.4 35.9-84.5 A Gr-B pCi/L 35.1 33.9 22.1-41.6 A I-131 pCi/L 23.5 26.3 21.9-31.0 A U-Nat pCi/L 49.2 51.2 41.6-56.9 A H-3 pCi/L 918 9820 8540-10800 N(5)

MRAD-25 AP Gr-A pCi/Filter 56.8 71.2 23.9-111 A (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. N=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.

(5) NCR 16-34 was initiated 8 - 10

9.0 9-1

TABLE OF CONTENTS Page LIST OF TABLES ....................................................................................................................... iii EXECUTIVE

SUMMARY

............................................................................................................ iv I. INTRODUCTION ......................................................................................................... 9-2 A. QC Program..................................................................................................... 9-2 B. QA Program ......................................................................................................9-2 II. PERFORMANCE EVALUATION CRITERIA .................................................................9-2 A. Acceptance Criteria for Internal Evaluations......................................................9-2 B. QC Investigation Criteria and Result Reporting .................................................9-4 C. Reporting of Environmental Dosimetry Results to EDC Customers ...................9-4 III. DATA

SUMMARY

FOR ISSUANCE PERIOD JANUARY-DECEMBER 2016 ...............9-4 A. General Discussion ...........................................................................................9-4 B. Result Trending ................................................................................................9-5 IV. STATUS OF EDC CONDITION REPORTS (CR) .........................................................9-5 V. STATUS OF AUDITS/ASSESSMENTS ........................................................................9-5 A. Internal..............................................................................................................9-5 B. External ............................................................................................................9-5 VI. PROCEDURES AND MANUALS REVISED DURING JANUARY-DECEMBER 2016 ...9-5 VII. CONCLUSION AND RECOMMENDATIONS ...............................................................9-5 VIII. REFERENCES .............................................................................................................9-5 APPENDIX A DOSIMETRY QUALITY CONTROL TRENDING GRAPHS .............................9-7

- ii -

LIST OF TABLES Page

1. Percentage of Individual Analyses Which Passed EDC Internal Criteria, January - December 2016 5

2. Mean Dosimeter Analyses (n=6), January - December 2016 5

3. Summary of Independent QC Results for 2016 5

- iii -

EXECUTIVE

SUMMARY

Routine quality control (QC) testing was performed for dosimeters issued by the Environmental Dosimetry Company (EDC) .

During this annual period, 100% (72/72) of the individual dosimeters, evaluated against the EDC internal performance acceptance criteria (high-energy photons only), met the criterion for accuracy and 100% (72/72) met the criterion for precision (Table 1). In addition, 100% (12/12) of the dosimeter sets evaluated against the internal tolerance limits met EDC acceptance criteria (Table 2) and 100% (6/6) of independent testing passed the performance criteria (Table 3). Trending graphs, which evaluate performance statistic for high-energy photon irradiations and co-located stations are given in Appendix A.

One internal assessment was performed in 2016. There were no findings.

- iv-

I. INTRODUCTION The TLD systems at the Environmental Dosimetry Company (EDC) are calibrated and operated to ensure consistent and accurate evaluation of TLDs. The quality of the dosimetric results reported to EDC clients is ensured by in-house performance testing and independent performance testing by EDC clients, and both internal and client directed program assessments.

The purpose of the dosimetry quality assurance program is to provide performance documentation of the routine processing of EDC dosimeters. Performance testing provides a statistical measure of the bias and precision of dosimetry processing against a reliable standard, which in turn points out any trends or performance changes. Two programs are used:

A. QC Program Dosimetry quality control tests are performed on EDC Panasonic 814 Environmental dosimeters. These tests include: (1) the in-house testing program coordinated by the EDC QA Officer and (2) independent test perform by EDC clients. In-house test are performed using six pairs of 814 dosimeters, a pair is reported as an individual result and six pairs are reported as the mean result.

Results of these tests are described in this report.

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

B. QA Program An internal assessment of dosimetry activities is conducted annually by the Quality Assurance Officer (Reference 1). The purpose of the assessment is to review procedures, results, materials or components to identify opportunities to improve or enhance processes and/or services.

II. PERFORMANCE EVALUATION CRITERIA A. Acceptance Criteria for Internal Evaluations

1. Bias For each dosimeter tested, the measure of bias is the percent deviation of the reported result relative to the delivered exposure. The percent deviation relative to the delivered exposure is calculated as follows:

Hi Hi 100 Hi where:

Hi = the corresponding reported exposure for the ith dosimeter (i.e., the reported exposure)

Hi = the exposure delivered to the ith irradiated dosimeter (i.e., the delivered exposure) 9-2

2. Mean Bias For each group of test dosimeters, the mean bias is the average percent deviation of the reported result relative to the delivered exposure. The mean percent deviation relative to the delivered exposure is calculated as follows:

Hi Hi 1 100 n

Hi where:

Hi = the corresponding reported exposure for the ith dosimeter (i.e., the reported exposure)

Hi = the exposure delivered to the ith irradiated test dosimeter (i.e., the delivered exposure) n = the number of dosimeters in the test group

3. Precision For a group of test dosimeters irradiated to a given exposure, the measure of precision is the percent deviation of individual results relative to the mean reported exposure. At least two values are required for the determination of precision. The measure of precision for the ith dosimeter is:

Hi H 100 H

where:

Hi = the reported exposure for the ith dosimeter (i.e., the reported exposure) 1 H = the mean reported exposure; i.e., H Hi n

n = the number of dosimeters in the test group

4. EDC Internal Tolerance Limits All evaluation criteria are taken from the EDC Quality System Manual, (Reference 2). These criteria are only applied to individual test dosimeters irradiated with high-energy photons (Cs-137) and are as follows for Panasonic Environmental dosimeters: +/- 15% for bias and +/-

12.8% for precision.

9-3

B. QC Investigation Criteria and Result Reporting EDC Quality System Manual (Reference 2) specifies when an investigation is required due to a QC analysis that has failed the EDC bias criteria. The criteria are as follows:

1. No investigation is necessary when an individual QC result falls outside the QC performance criteria for accuracy.

2. Investigations are initiated when the mean of a QC processing batch is outside the performance criterion for bias.

C. Reporting of Environmental Dosimetry Results to EDC Customers

1. All results are to be reported in a timely fashion.

2. If the QA Officer determines that an investigation is required for a process, the results shall be issued as normal. If the QC results, prompting the investigation, have a mean bias from the known of greater than +/-20%, the results shall be issued with a note indicating that they may be updated in the future, pending resolution of a QA issue.

3. Environmental dosimetry results do not require updating if the investigation has shown that the mean bias between the original results and the corrected results, based on applicable correction factors from the investigation, does not exceed +/-20%.

III. DATA

SUMMARY

FOR ISSUANCE PERIOD JANUARY-DECEMBER 2016 A. General Discussion Results of performance tests conducted are summarized and discussed in the following sections. Summaries of the performance tests for the reporting period are given in Tables 1 through 3 and Figures 1 through 4.

Table 1 provides a summary of individual dosimeter results evaluated against the EDC internal acceptance criteria for high-energy photons only. During this period, 100% (72/72) of the individual dosimeters, evaluated against these criteria met the tolerance limits for accuracy and 100% (72/72) met the criterion for precision.

A graphical interpretation is provided in Figures 1 and 2.

Table 2 provides the Bias + Standard deviation results for each group (N=6) of dosimeters evaluated against the internal tolerance criteria. Overall,100%

(12/12) of the dosimeter sets evaluated against the internal tolerance performance criteria met these criteria. A graphical interpretation is provided in Figure 3.

Table 3 presents the independent blind spike results for dosimeters processed during this annual period. All results passed the performance acceptance criterion. Figure 4 is a graphical interpretation of Seabrook Station blind co-located station results.

9-4

B. Result Trending One of the main benefits of performing quality control tests on a routine basis is to identify trends or performance changes. The results of the Panasonic environmental dosimeter performance tests are presented in Appendix A. The results are evaluated against each of the performance criteria listed in Section II, namely: individual dosimeter accuracy, individual dosimeter precision, and mean bias.

All of the results presented in Appendix A are plotted sequentially by processing date.

IV. STATUS OF EDC CONDITION REPORTS (CR)

No condition reports were issued during this annual period.

V. STATUS OF AUDITS/ASSESSMENTS A. Internal EDC Internal Quality Assurance Assessment was conducted during the fourth quarter 2016. There were no findings identified.

B. External None.

VI. PROCEDURES AND MANUALS REVISED DURING JANUARY - DECEMBER 2016 Several procedures were reissued with no changes as part of the 5 year review cycle.

VII. CONCLUSION AND RECOMMENDATIONS The quality control evaluations continue to indicate the dosimetry processing programs at the EDC satisfy the criteria specified in the Quality System Manual. The EDC demonstrated the ability to meet all applicable acceptance criteria.

VIII. REFERENCES

1. EDC Quality Control and Audit Assessment Schedule, 2016.

2. EDC Manual 1, Quality System Manual, Rev. 3, August 1, 2012.

9-5

TABLE 1 PERCENTAGE OF INDIVIDUAL DOSIMETERS THAT PASSED EDC INTERNAL CRITERIA JANUARY - DECEMBER 2016(1), (2)

Number  % Passed Precision Dosimeter Type  % Passed Bias Criteria Tested Criteria Panasonic Environmental 72 100 100 (1)

This table summarizes results of tests conducted by EDC.

(2)

Environmental dosimeter results are free in air.

TABLE 2 MEAN DOSIMETER ANALYSES (N=6)

(1), (2)

JANUARY - DECEMBER 2016 Standard Tolerance Process Date Exposure Level Mean Bias % Deviation Limit +/-

% 15%

4/22/2016 40 3.5 0.7 Pass 4/29/2016 80 1.8 0.7 Pass 5/10/2016 70 1.8 1.8 Pass 7/25/2016 33 2.4 1.5 Pass 8/2/2016 56 2.4 1.6 Pass 8/2/2016 123 0.7 1.4 Pass 10/25/2016 28 2.9 1.0 Pass 10/29/2016 93 3.2 1.8 Pass 11/6/2016 61 0.0 1.6 Pass 1/30/2017 39 1.4 2.5 Pass 1/31/2017 76 2.2 1.3 Pass 1/31/2017 101 -1.7 1.5 Pass (1)

This table summarizes results of tests conducted by EDC for TLDs issued in 2016.

(2)

Environmental dosimeter results are free in air.

TABLE 3

SUMMARY

OF INDEPENDENT DOSIMETER TESTING JANUARY - DECEMBER 2016(1), (2)

Standard Pass / Fail Issuance Period Client Mean Bias %

Deviation %

1st Qtr. 2016 Millstone -0.2 1.0 Pass 2nd Qtr.2016 Millstone -3.4 3.0 Pass 2nd Qtr.2016 Seabrook 1.8 0.8 Pass 3rd Qtr. 2016 Millstone 3.0 2.4 Pass 4th Qtr.2016 Millstone .0.9 3.9 Pass 4th Qtr.2016 Seabrook -0.2 0.7 Pass (1)

Performance criteria are +/- 30%.

(2)

Blind spike irradiations using Cs-137 9-6

APPENDIX A DOSIMETRY QUALITY CONTROL TRENDING GRAPHS ISSUE PERIOD JANUARY - DECEMBER 2016 9-7

9-8 9-9 9 - 10 9 - 11