ML12144A413

Transmittal of 2011 Annual Radiological Environmental Operating Report

ML12144A413
Person / Time
Site:	Nine Mile Point
Issue date:	05/15/2012
From:	Dosa J EDF Development, Nine Mile Point, Constellation Energy Nuclear Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12144A413 (168)

Text

P.O. Box 63 C EN G SM Lycoming, NY 13093 a joint venture of Constellation neg NINE MILE POINT NUCLEAR STATION May 15, 2012 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

Nine Mile Point Nuclear Station Unit Nos. 1 & 2; Docket Nos. 50-220 & 50-410 2011 Annual Radiological Environmental Operating Report In accordance with the Technical Specifications for Nine Mile Point Nuclear Station, Units 1 and 2, enclosed is the 2011 Annual Radiological Environmental Operating Report for the period January 1, 2011 through December 31, 2011.

This submittal does not contain any new regulatory commitments.

Should you have questions regarding the information in this submittal, please contact me at (315) 349-5219.

Very truly yours, John J. Dosa Director Licensing JJD/KES

Enclosure:

Nine Mile Point Nuclear Station, LLC, 2011 Annual Radiological Environmental Operating Report cc: Regional Administrator, Region I, NRC Project Manager, NRC Resident Inspector, NRC B. Dionne, NRC T. Rice, NYS DEC C. Costello, NYS DOH P. Egan, Oswego County Emergency Management M/ut

ENCLOSURE NINE MILE POINT NUCLEAR STATION, LLC 2011 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Nine Mile Point Nuclear Station, LLC May 15, 2012

CENG.

a joint venture of EnergyeD NINE MILE POINT NUCLEAR STATION NINE MILE POINT NUCLEAR STATION, LLC 2011 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

NINE MILE POINT NUCLEAR STATION, LLC ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January 1, 2011 - December 31, 2011 For NINE MILE POINT NUCLEAR STATION UNIT 1 Facility Operating License DPR-63 Docket No. 50-220 And NINE MILE POINT NUCLEAR STATION UNIT 2 Facility Operating License NPF-69 Docket No. 50-410

TABLE OF CONTENTS Page 1.0 EXECUTIVE

SUMMARY

1-1

2.0 INTRODUCTION

2-1 2.1 Program History 2-1 2.2 Site Description 2-1 2.3 Program Objectives 2-2 3.0 PROGRAM DESCRIPTION 3-1 3.1 Sample Collection Methodology 3-13 3.2 Analyses Performed 3-17 3.3 Sample Locations 3-18 3.4 Land Use Census 3-29 3.5 Changes to the REMP Program 3-29 3.6 Deviation and Exceptions to the Program 3-29 3.7 Statistical Methodology 3-30 3.8 Compliance with Required Lower Limits of Detection (LLD) 3-35 3.9 Regulatory Dose Limits 3-35 4.0 SAMPLE

SUMMARY

TABLES IN BRANCH TECHNICAL 4-1 POSITION FORMAT 5.0 DATA EVALUATION AND DISCUSSION 5-1 5.1 Aquatic Program 5-5 5.2 Terrestrial Program 5-15 5.3 Conclusion 5-31 5.4 References 5-33 6.0 REPORT PERIOD ANALYTICAL RESULTS TABLES 6-1 i

TABLE OF CONTENTS (Continued)

Page 7.0 HISTORICAL DATA TABLES 7-1 8.0 QUALITY ASSURANCE/QUALITY CONTROL PROGRAM 8-1 8.1 Program Description 8-1 8.2 Program Schedule 8-2 8.3 Acceptance Criteria 8-2 8.4 Program Results Summary 8-4 8.5 References 8-21 ii

LIST OF TABLES Page Table 3.0-1 Required Sample Collection and Analysis, Nine Mile Point Unit 1 3-2 Table 3.0-2 Required Sample Collection and Analysis, Nine Mile Point Unit 2 3-6 Table 3.3-1 2011 Environmental Sample Locations 3-19 Table 3.7-1 Required Detection Capabilities for Environmental Sample Analysis, 3-34 Lower Limit of Detection (LLD)

Table 4.0-1 Radiological Environmental Monitoring Program Annual Summary, 4-2 January - December 2011 Table 6-1 Concentrations of Gamma Emitters in Shoreline Sediment Samples - 2011 6-2 Table 6-2 Concentrations of Gamma Emitters in Fish Samples - 2011 6-3 Table 6-3 Concentrations of Tritium in Surface Water Samples - 2011 6-6 Table 6-4 Concentrations of Gamma Emitters in Surface Water Samples - 2011 6-7 Table 6-5 Environmental Airborne Particulate Samples - Off-Site Sample 6-12 Locations, Gross Beta Activity - 2011 Table 6-6 Environmental Airborne Particulate Samples - On-Site Sample 6-14 Locations, Gross Beta Activity - 2011 Table 6-7 Environmental Charcoal Cartridge Samples - Off-Site Sample 6-16 Locations, 1-131 Activity -2011 Table 6-8 Environmental Charcoal Cartridge Samples - On-Site Sample 6-18 Locations, 1-131 Activity - 2011 Table 6-9 Concentrations of Gamma Emitters in Quarterly Composites 6-20 JAFNPP/NMPNS Site Air Particulate Samples - 2011 Table 6-10 Direct Radiation Measurement Results - 2011 6-24 Table 6-11 Concentrations of Iodine-131 and Gamma Emitters in Milk - 2011 6-26 Table 6-12 Concentrations of Gamma Emitters in Food Products - 2011 6-28 Table 6-13 Milk Animal Census - 2011 6-29 Table 6-14 Residence Census - 2011 6-30 iii

LIST OF TABLES (continued)

Page Table 7-1 Historical Environmental Sample Data, Shoreline Sediment (Control) 7-2 Table 7-2 Historical Environmental Sample Data, Shoreline Sediment (Indicator) 7-3 Table 7-3 Historical Environmental Sample Data, Fish (Control) 7-4 Table 7-4 Historical Environmental Sample Data, Fish (Indicator) 7-5 Table 7-5 Historical Environmental Sample Data, Surface Water (Control) 7-6 Table 7-6 Historical Environmental Sample Data, Surface Water (Indicator) 7-7 Table 7-7 Historical Environmental Sample Data, Surface Water Tritium (Control) 7-8 Table 7-8 Historical Environmental Sample Data, Surface Water Tritium (Indicator) 7-9 Table 7-9 Historical Environmental Sample Data, Groundwater Tritium (Control) 7-10 Table 7-10 Historical Environmental Sample Data, Groundwater Tritium (Indicator) 7-11 Table 7-11 Historical Environmental Sample Data, Air Particulate Gross Beta (Control) 7-12 Table 7-12 Historical Environmental Sample Data, Air Particulate Gross Beta (Indicator) 7-13 Table 7-13 Historical Environmental Sample Data, Air Particulates (Control) 7-14 Table 7-14 Historical Environmental Sample Data, Air Particulates (Indicator) 7-15 Table 7-15 Historical Environmental Sample Data, Air Radioiodine (Control) 7-16 Table 7-16 Historical Environmental Sample Data, Air Radioiodine (Indicator) 7-17 Table 7-17 Historical Environmental Sample Data, Environmental TLD (Control) 7-18 Table 7-18 Historical Environmental Sample Data, Environmental TLD (Site Boundary) 7-19 Table 7-19 Historical Environmental Sample Data, Environmental TLD (Off-site Sectors) 7-20 Table 7-20 Historical Environmental Sample Data, Environmental TLD (Special Interest) 7-21 Table 7-21 Historical Environmental Sample Data, Environmental TLD 7-22 (On-Site Indicator)

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

LIST OF TABLES (continued)

Page Table 7-23 Historical Environmental Sample Data, Milk (Control) 7-24 Table 7-24 Historical Environmental Sample Data, Milk (Indicator) 7-25 Table 7-25 Historical Environmental Sample Data, Food Products (Control) 7-26 Table 7-26 Historical Environmental Sample Data, Food Products (Indicator) 7-27 Table 8-1 Interlaboratory Intercomparison Program 8-5 V

LIST OF FIGURES Page Figure 3.3-1 New York State Map 3-23 Figure 3.3-2 Off-Site Environmental Station and TLD Locations 3-24 Figure 3.3-3 On-Site Environmental Station and TLD Locations 3-25 Figure 3.3-4 Milk and Surface Water Sample Locations 3-26 Figure 3.3-5 Nearest Residence, Food Product, Fish and Shoreline Sediment 3-27 Sample Locations Figure 3.3-6 NMPNS On-Site Groundwater Monitoring Wells and Unit 2 Storm 3-28 Drain Outfall vi

1.0 EXECUTIVE

SUMMARY

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

This report describes the Radiological Environmental Monitoring Program (REMP), the implementation of the program, and the results obtained as required by the Offsite Dose Calculation Manuals (ODCM). The report also contains the analytical results tables, data evaluation, dose assessment, and data trends for each environmental sample media. Also included are results of the land use census, historical data, and the Environmental Laboratory's performance in the Interlaboratory Comparison Quality Assurance Program (ICQAP) required by the NMP 1 and NMP2 ODCM.

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

During 2011, there were 2,430 analyses performed on environmental media collected as part of the REMP.

The results demonstrate that there was no significant or measurable radiological impact from the operation of either the NMUP1 or NMP2 facilities. The 2011 results for all pathways sampled were consistent with the previous five-year historical results and exhibited no adverse trends.

On March 11, 2011 at 1446, a magnitude 9.0 earthquake struck off the east coast of Japan. The Fukushima Daiichi Nuclear Power Station, operated by Tokyo Electric Power Co., withstood the earthquake but lost all offsite electrical power sources to the site. Forty-one minutes later however, the plant was hit with a series of tsunamis and all AC power was lost and the facility went into a state of emergency. The Nuclear Safety Commission of Japan estimated approximately 17 million curies of iodine-131 (1-131) equivalent radioactive material was released into the air and 0.127 million curies into the sea between March 11 and April 5. 1-131 was detected at the Nine Mile Point Nuclear Station site from the Fukushima Daiichi Nuclear Power Station event in both the indicator and control air sampling locations from March 22 through April 12, 2011.

In summary, the analytical results from the 2011 REMP demonstrate that the routine operation of both facilities at the Nine Mile Point site had no significant or measurable radiological impact on the environment. The results of the REMP continue to demonstrate that the operation of the plants did not result in a significant measurable dose to a member of the general population, or adversely impact the environment as a result of radiological effluents. The program continues to demonstrate that the dose to a member of the public, as a result of the operation of NMP 1 and NMP2, remains significantly below the federally required dose limits specified in 10 CFR 20 and 40 CFR 190.

1-1

2.0 INTRODUCTION

Nine Mile Point Units 1 and 2 are operated by Nine Mile Point Nuclear Station, LLC. This report is submitted in accordance with Appendix A (Technical Specifications) Section 6.6.2 to License DPR-63, Docket No. 50-220 for Nine Mile Point Nuclear Station, Unit 1, and Appendix A (Technical Specifications) Section 5.6.2 to License NPF-69, Docket No. 50-410 for Nine Mile Point Nuclear Station, Unit 2, for the calendar year 2011.

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

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

2.1 PROGRAM HISTORY Environmental monitoring of the Nine Mile Point (NMP) site has been on-going since 1964. The program includes five years of pre-operational data which was conducted prior to any reactor operations. In 1968, the Niagara Mohawk Power Company began the required pre-operational environmental site testing program. This pre-operational data serves as a reference point to compare data obtained during reactor operation. In 1969, NMP1, a 1,850 Megawatt-Thermal (MWt) Boiling Water Reactor (BWR) began full power operation. In 1975, the James A. FitzPatrick Nuclear Power Plant (JAFNPP), a 2,536 MWt BWR, currently owned and operated by Entergy, began full power operation. In 1988, NMP2, a 3,323 MWt BWR located between NMP1 and JAFNPP, began full power operation. In 1995, NMP2 was uprated to 3,467 MWt.

In 1985, the individual station's Plant Effluent Technical Specifications were standardized to the generic Radiological Effluent Technical Specifications, much of which is common to both NMP1 and JAFNPP, and subsequently to NMP2. Subsequent Technical Specification amendments relocated the REMP requirements to the ODCM for all three plants. Data generated by the REMP is shared between Nine Mile Point Nuclear Station (NMPNS) and JAFNPP, but each operating company reviews and publishes their own annual report.

In summary, the three BWRs, which together generate approximately 7,853 MWt, have operated collectively since 1988. A large database of environmental results for the exposure pathways has been collected and analyzed to determine the effect from reactor operations.

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

2-1

2.3 PROGRAM OBJECTIVES The objectives of the REMP are to:

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

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

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

2-2

3.0 PROGRAM DESCRIPTION To achieve the objectives listed in Section 2.3, an extensive sampling and analysis program is conducted every year. The Nine Mile Point Nuclear Station (NMPNS) Radiological Environmental Monitoring Program (REMP) consists of sampling and analysis of various media that include:

o Air o Fish

• Food Products o Milk

• Shoreline Sediment

" Surface Waters

" Groundwater In addition, direct radiation measurements are performed using thermoluminescent dosimeters (TLDs).

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

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

3-1

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

Sample Frequency Frequency AIRBORNE

a. Radioiodine and Samples from five locations: Continuous sampler operation Radioiodine Canisters -

Particulates with sample collection weekly or analyze once per week for

1. Three samples from offsite locations in different sectors as required by dust loading, 1-131.

of the highest calculated site average D/Q (based on all whichever is more frequent.

site licensed reactors). Particulate Samplers - Gross beta radioactivity following

2. One samplefrom the vicinity of an established year filter change (b) round community having the highest calculated site Composite (by location) for average D/Q (based on all site licensed reactors). gamma isotopic analysis (c) once per 3 months (as a

3. One sample from a control location 10-17 miles distant minimum).

and in a least prevalent wind direction (d)

b. Direct Radiation (e) 32 stations with two or more dosimeters to be placed as Once per 3 months. Gamma dose once per 3 follows: an inner ring of stations in the general area of the months.

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

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

3-2

m - *mm m m m m m m m mm m m m m m TABLE 3.0-1 (Continued)

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

Sample Frequency Frequency WATERBORNE

a. Surface M 1. One sample upstream. Composite sample over I month Gamma isotopic analysis (0) period (g) once per month. Composite

2. One sample from the site's downstream cooling for once per 3 months tritium water intake. analysis.

b. Sediment from One sample from a downstream area with existing or Twice per year. Gamma isotopic analysis(c).

Shoreline potential recreational value.

INGESTION

a. Milk 1. Samples from milk sampling locations in three Twice per month, April - Gamma isotopic (c)and I-locations within 3.5 miles distance having the highest December (samples will be 131 analysis twice per month calculated site average D/Q. If there are none, then collected in January - March if when animals are on pasture one sample from milking animals in each of 3 areas 1-131 is detected in November (April - December); once per 3.5 - 5.0 miles distant having the highest calculated and December of the preceding month at other times (January site average D/Q (based on all site licensed reactors). year). - March) if required.

2. One sample from a milk sampling location at a control location (9-20 miles distant and in a least prevalent wind direction) (d) 3-3

TABLE 3.0-1 (Continued)

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

b. Fish 1. One sample each of two commercially or Twice per year. Gamma isotopic analysis (W) recreationally important species in the vicinity of a on edible portions twice per plant discharge area (h) year.

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

c. Food Products 1. Samples of three different kinds of broad leaf Once per year during harvest Gamma isotopic (c)analysis of vegetation (such as vegetables) grown nearest to each season. edible portions (Isotopic to of two different off-site locations of highest include 1-13 1 or a separate I-calculated site average D/Q (based on all licensed 131 analysis maybe site reactors). performed) once during the harvest season.

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

3-4

- m- m m m mM -M M Mm m M M mM

NOTES FOR TABLE 3.0-1 (a) It is recognized that, at times, it may not be possible or practical to obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and may be substituted. Actual locations (distance and directions) from the site shall be provided in the Annual Radiological Environmental Operating Report.

Highest D/Q locations are based on historical meteorological data for all site licensed reactors.

(b) Particulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days <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 the gross beta activity in air is greater than 10 times a historical yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

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

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

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

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

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

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

3-5

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

Sample Frequency . r Frequency AIRBORNE

a. Direct Radiation 32 routine monitoring stations (b) either with two or more Once per 3 months. Gamma dose once per 3 dosimeters or with one instrument for measuring and months.

recording dose rate continuously, placed as follows:

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

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

3. The balance of the stations shouldbe placed in special interest areas such as population centers, nearby residences, schools, and in one of two areas to serve as control stations (d) 3-6 mnmmummmmmmmmm mmmmm m m m

mm m mm m. m m m -m - m m mm m m m m m TABLE 3.0-2 (Continued)

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

Sample Frequency Frequency

b. Airborne Radioiodine Samples from five locations: Radioiodine Canister:

and Particulates 1-131 analysis weekly.

1. Three samples from off-site locations close to the site Continuous sampler operation boundary (within one mile) in different sectors of the with sample collection weekly, Particulate Sampler:

highest calculated annual site average ground-level or more frequently if required by 1. Gross beta radioactivity D/Q (based on all site licensed reactors)(e). dust loading. analysis >_ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change(0,

2. One sample from the vicinity of an established year- 2. Gamma isotopic analysis round community having the highest calculated on each sample where annual site average ground-level D/Q (based on all gross beta activity is >10 site licensed reactors)(e). times the previous yearly mean of control samples,

3. One sample from a control location at least 10 miles and distant and in a least prevalent wind direction (. 3. Gamma isotopic analysis of composite sample (9g)

(by location) once per 3 months.

WATERBORNE

a. Surface 1. One sample upstream (d) (h) Composite sample over 1-month Gamma isotopic analysis (g) period (i). once per month and tritium

2. One sample from the site's downstream cooling analysis once per 3 months.

water intake (h) 3-7

TABLE 3.0-2 (Continued)

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

Sample Frequency Frequency

b. Ground Samples from one or two sources if likely to be Grab sample once per 3 months. Gamma isotopic (g)and affected 0). tritium analysis once per 3 months.

c. Drinking One sample each of one to three of the nearest water supplies When 1-131 analysis is 1. 1-131 analysis on that could be affected by its discharge (k) performed, a composite sample each composite when over a 2-week periodi); the dose calculated otherwise, a composite sample for the consumption monthly. of the water is greater than 1 mrem per year(').

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

3. Composite for tritium analysis once per 3 months.

d. Sediment from One sample from a downstream area with existing or Twice per year. Gamma isotopic analysis(g).

Shoreline potential recreational value.

3-8

m m m m M m m m m m m m m m m m m m M TABLE 3.0-2 (Continued)

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

Sample Frequency Frequency INGESTION

a. Milk I. Samples from Milk Sampling Locations in three Twice per month, April - 1. Gamma isotopic (g) locations within 3.5 miles(c) distance having the December (samples will be and 1-131 analysis highest calculated annual site average D/Q (based on collected January - March if I- twice per month all licensed site reactors). 131 is detected in November and when animals are on December of the preceding pasture (April -

2. If there are none, then 1 sample from Milk Sampling year)(m). December);

Locations in each of three areas 3.5 - 5.0 miles(c) 2. Gamma isotopic (g) distant having the highest calculated annual site and 1-131 analysis average D/Q (based on all licensed site reactors). once per month at other times (January

3. One sample from a Milk Sample Location at a ' March, if required).

control location 9 - 20 miles distant and in a least prevalent wind direction (d)

b. Fish 1. One sample each of two commercially or Twice per year. Gamma isotopic analysis (g) recreationally important species in the vicinity of a on edible portions twice per plant discharge area (n). year.

2. One sample of the same species in areas not influenced by station discharge (d) 3-9

TABLE 3.0-2 (Continued)

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

Frequency Sample Frequency

c. Food Products 1. One sample of each principal class of food products At time of harvest (p). Gamma isotopic (g)and I-from any area that is irrigated by water in which 131 analysis of each sample liquid plant wastes have been discharged (o). of edible portions.

2. Samples of three different kinds of broad leaf vegetation (such as vegetables) grown nearest to each Once per year during the harvest of two different off-site locations of highest season.

calculated annual site average D/Q (based on all licensed site reactors)(e).

3. One sample of each of the similar broad leaf vegetation grown at least 9.3 miles distant in a least Once per year during the harvest prevalent wind direction. season.

3-10 m m m m M m m M m M m m m m m m m m m

NOTES FOR TABLE 3.0-2 (a) Specific parameters of distance and direction sector from the centerline of one reactor, and additional descriptions where pertinent, shall be provided for each and every sample location in Table 3.0-2. Refer to NUREG-0 133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"

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

(b) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously, may be used in place of, or in addition to, integrating dosimeters. Each of the 32 routine monitoring stations shall be equipped with 2 or more dosimeters or with 1 instrument for measuring and recording dose rate continuously. For the purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor, two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

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

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

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

(f) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <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.

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

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

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

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

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

(1) Analysis for 1-131 may be accomplished by Ge-Li analysis, provided that the lower limit of detection (LLD) for 1-131 in water samples found on Table 3.8-1 can be met. Doses shall be calculated for the maximum organ and age group.

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

3-11

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

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

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

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

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

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

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

b. Samples are composed of the edible portion only.

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

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

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

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

I 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. i A portion of the monthly sample from each of the locations is saved and composited to form quarterly composite samples, that are analyzed for tritium. i In addition to the sample results for the JAFNPP and Oswego Generating Station collection sites, data is presented for the Nine Mile Point Unit 1 (NMP1) and Nine Mile Point Unit 2 (NMP2) facility inlet canal samples and from the City of Oswego drinking water supply. These three locations are not required by the ODCM. These locations are optional sample points which are collected and analyzed to enhance the surface water sampling program. Monthly composite samples from these three locations are analyzed for gamma emitting nuclides, and quarterly composite samples are analyzed for tritium.

Sampling for groundwater and drinking water, as found in Section D 3.5.1 of the NMP2 ODCM, was not required during 2011. There was no groundwater source in 2011 that was tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties support contamination migration; therefore, drinking water was not a dose pathway during 2011.

I Surface water sample locations are shown in Section 3.3, Figure 3.3-4. i 3.1.4 GROUNDWATER MONITORING PROGRAM The Nuclear Energy Institute (NEI) Groundwater Protection Initiative was established to determine the potential impact nuclear power plants may have on the surrounding environment due to unplanned releases of radioactive liquids. Under the NEI 07-07 Groundwater Protection Initiative (GPI) 7 Final Guidance Document, August 2007, groundwater monitoring is accomplished through sampling of the water table around the plant and analyzing for tritium. In addition to the groundwater monitoring requirements specified in the NMP2 ODCM, NMPNS started monitoring groundwater wells in October 2005 and has I

been monitoring the plant dewatering systems as part of the response to Generic Letter 80-10 for several years. Samples collected from these locations are analyzed for tritium, gamma emitters, and strontium.

During the operating year 2011, there were no unplanned releases or spills of radioactive liquids on the NMPNS site.

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

Groundwater tritium results are documented in the 2011 Annual Radiological Effluent Release Report.

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

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

3-14

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

These stations (R-1, R-2, and R-3) are located in the E, ESE, and SE sectors as measured from the center of the NMP2 Reactor Building. The ODCM also requires that a fourth air sampling station be located in the vicinity of a year-round community. This station is located in the SE sector at a distance of 1.8 miles and is designated as Station R-4. A fifth station required by the ODCM is a control location designated as Station R-5. Station R-5 is located 16.4 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 D 1, G, H, I, J, and K. These locations are within the site boundary of the NMPNS and JAFNPP. One air sampling station is located offsite in the SW sector in the vicinity of the City of Oswego and is designated as Offsite Station G. Three remaining air sampling stations are located in the ESE, SSE, and SSW sectors and range in distance from 7.2 to 9.0 miles. These are designated as Offsite Stations D2, E and F, respectively.

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

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

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

3.1.6 THERMOLUMMINESCENT DOSIMETERS (DIRECT RADIATION)

Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the environment. Environmental TLDs are supplied and processed quarterly by the AREVA NP Environmental Laboratory. The laboratory utilizes a Panasonic based system using UD-814 dosimeters that are constructed of rectangular .teflon wafers impregnated with 25% CaSO 4:Dy phosphor. Each dosimeter contains three calcium sulfate elements and one lithium borate element.

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

3- 15

I TLD Geographical Category Description I

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

I 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 I

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*) I Offsite An outer ring of TLDs placed -4 to 5 miles from the site in each of the eight land-based meteorological sectors. This category is required by the I ODCM. (TLD locations comprising this group are 88*, 89*, 90*, 91*,

92*, 93*, 94*, and 95*)

I 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.

I (TLD locations comprising this groupare: 9, 10, 11, 12, 13, .15*, 19, 51, 52, 53, 54, 55, 56*, 58*, 96*, 97*, 98*, 99, 100, 101, 102, 108, and 109) I 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 I

ODCM. (TLD locations comprising this group are 8, 1'4*, 49*, 111, 113)

I

• TLD location required by ODCM The ODCM requires a total of 32 TLD stations. Environmental TLDs are also placed at additional locations I

not required by the ODCM, within the Onsite, Special Interest and Control TLD categories to supplement the ODCM required direct radiation data. I Two dosimeters are placed at each TLD monitoring location. The TLDs are sealed in polyethylene packages to ensure dosimeter integrity, placed in open webbed plastic holders, and attached to supporting structures, such as utility poles.

I Environmental TLD locations are shown in Section 3.3, Figures 3.3-2 and 3.3-3. I 3- 16

3.1.7 MILK Milk samples are routinely collected from farms during the sampling year. These farms include one indicator location and one control location. Samples are normally collected April through December of the sample year. If plant-related radionuclides are detected during November and December of the previous year, milk collections are continued into the following year, starting in January. If plant-related radionuclides are not detected in the November and December samples, then milk collections do not commence until April of the next sampling year. Milk samples were not collected in January through March of 2011, as there were no positive detections of plant related radionuclides in Samples collected during November and December 2010.

The ODCM also requires that a sample be collected from a control location nine to twenty miles from the site and in a least prevalent wind direction. This location is in the south sector at a distance of 16 miles and serves as the control location.

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

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

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

3.1.8 FOOD PRODUCTS (VEGETATION)

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

Food product samples are analyzed for gamma emitters using gamma isotopic analysis and for carbon-14 (C-14) using liquid scintillation detection.

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

3.2 ANALYSES PERFORMED The following environmental sample analyses are performed by the JAFNPP Environmental Laboratory:

• Air Particulate Filter - Gross Beta

• Air Particulate Filter Composites - Gamma Spectral Analysis 3- 17

I

• Airborne Radioiodine - Gamma Spectral Analysis

• Fish - Gamma Spectral Analysis Food Products (Vegetation) - Gamma Spectral Analysis, 1-131 and C-14 Milk - Gamma Spectral Analysis and 1-131 I

• Shoreline Sediment - Gamma Spectral Analysis

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

• Surface Water Monthly Composites - Gamma Spectral Analysis and 1-131

• Surface Water Quarterly Composites - Tritium

• Groundwater Quarterly Samples - Gamma Spectral Analysis, Strontium and Tritium The analyses of Direct Radiation using Thermoluminescent (TLDs) are performed by a contractor n laboratory - Areva NP Environmental Laboratory.

The strontium and C-14 analyses are performed by a contractor laboratory - GEL Laboratories, LLC. m 3.3 SAMPLE LOCATIONS 3 Figures 3.3-1 through 3.3-6 provide maps.-illustrating sample locations. Sample locations referenced as letters and numbers on the report period data tables are consistent with designations plotted on the maps. i This section also contains an environmental sample -location reference table (Table 3.3-1). This table contains the following information:

• Sample medium

• Map designation, (this column contains the key for the sample location and is consistent with the designation on the sample location maps and on thesample results datatables)

" Figure number

• Location description

• Degrees and distance of the sample location from the site 3-18

m M M mm M m m m m m m m m m Mm m m TABLE 3.3-1 2011 ENVIRONMENTAL SAMPLE LOCATIONS MAP DE VES & DISTANCE

'SAMPLE MEDIUM DESIGNATION FIGURE NUMBER: "LOCATION DESCRIPTIONE (C&pd)

(a &b)

Shoreline Sediment 5* Figure 3.3-5 Sunset Bay 840 at 1.2 miles 6 Figure 3.3-5 Langs Beach, Control 2320 at 4.8 miles Fish 02* Figure 3.3-5 Nine Mile Point Transect 2900 at 0.4 miles 03* Figure 3.3-5 FitzPatrick Transect 620 at 0.8 miles 00* Figure 3.3-5 Oswego Transect - Control 2370 at 5.9 miles Surface Water 03* Figure 3.3-4 FitzPatrick Inlet 710 at 0.5 miles 08* Figure 3.3-4 Oswego Generating Station Inlet - Control 2360 at 7.6 miles 09 Figure 3.3-4 NMP1 Inlet 3190 at 0.3 miles 10 Figure 3.3 Oswego City Water 2400 at 7.8 miles 11 Figure 3.3-4 NMP2 Inlet 3360 at 0.3 miles 3530 at 0.3 miles Air Radioiodine and R-l* Figure 3.3-2 R-1 Station, Nine Mile Point Road 920 at 1.8 miles Particulates R-2* Figure 3.3-3 R-2 Station, Lake Road 1060 at 1.1 miles R-3* Figure 3.3-3 R-3 Station, Co. Rt. 29 134' at 1.4 miles R-4* Figure 3.3-3 R-4 Station, Co. Rt. 29 1450 at 1.8 miles R-5* Figure 3.3-2 R-5 Station, Montario Point - Control 420 at 16.2 miles Dl Figure 3.3-3 Dl On-Site Station 730 at 0.3 miles G Figure 3.3-3 G On-Site Station 2440 at 0.7 miles H Figure 3.3-3 H On-Site Station 740 at 0.8 miles I Figure 3.3-3 I On-Site Station 960 at 0.8 miles J Figure 3.3-3 J On-Site Station 1100 at 0.9 miles K Figure 3.3-3 K On-Site Station 1330 at 0.5 miles G Figure 3.3-2 G Off-Site Station, Saint Paul Street 2260 at 5.4 miles D2 Figure 3.3-2 D2 Off-Site Station, Rt. 64 1180 at 9.0 miles E Figure 3.3-2 E Off-Site Station, Rt. 4 1620 at 7.1 miles F Figure 3.3-2 F Off-site Station, Dutch Ridge Road 1920 at 7.6 miles 3-19

TABLE 3.3-1 (Continued) 2011 ENVIRONMENTAL SAMPLE LOCATIONS IvIA1~DEGREES & DISTANCE' SAMPLE MEDIUM DESIGNATION FIGURE NUMBER LOCATION DESCRIPTION (c &d)

(a & b)

Thermoluminescent 3 Figure 3.3-3 D1 On-Site Station 730 at 0.3 miles Dosimeters (TLD) 4 Figure 3.3-3 D2 On-Site Station 1430 at 0.4 miles 5 Figure 3.3-3 E On-Site Station 1500 at 0.4 miles 6 Figure 3.3-3 F On-Site Station 213' at 0.5 miles 7* Figure 3.3-3 G*On-Site Station 2440 at 0.7 miles 8 Figure 3.3-2 R-5 Off-Site Station - Control 420 at 16.2 miles 9 Figure 3.3-2 State Route 3 80' at 11.4 miles 10 Figure 3.3-2 D2 Off-Site Station 1180 at 9.0 miles 11 Figure 3.3-2 E Off-Site Station 1620 at 7.1 miles 12 Figure 3.3-2 F Off-Site Station 1920 at 7.7 miles 13 Figure 3.3-2 G Off-Site Station 2260 at 5.4 miles 14* Figure 3.3-2 Southwest Oswego - Control 2270 at 12.5 miles 15* Figure 3.3-2 West Site Boundary 2390 at 0.9 miles 18* Figure 3.3-3 henrgy Information Center 2660 at 0.5 miles 19 Figure 3.3-2 East Site Boundary 830 at 1.4 miles 23* Figure 3.3-3 H On-Site Station 740 at 0.8 miles 24 Figure 3.3-3 I On-Site Station 960 at 0.8 miles 25 Figure 3.3-3 J On-Site Station 1100 at 0.9 miles 26 Figure 3.3-3 K On-Site Station 1330 at 0.5 miles 27 Figure 3.3-3 North Fence, JAFNPP 600 at 0.4 miles 28 Figure 3.3-3 North Fence, JAFNPP 680 at 0.5 miles 29 Figure 3.3-3 North Fence'JAFNPP 650 at 0.5 miles 30 Figure 3.3-3 North Fefice JAFNPP 570 at 0.4 miles 31 Figure 3.3-3 North Fence NMP1 2780 at 0.2 miles 39 Figure 3.3-3 NorthFence NMP1 2960 at 0.2 miles 47 Figure 3.3-3 North Fence JAFNPP' 690 at 0.6 miles 49* Figure 3.3-2 Phoenix, NY- Control 1680 at 19.7 miles 51 Figure 3.3-2 Oswego Generating Station, East 2340 at 7.3 miles 52 Figure 3.3-2 Fitzhugh Park Elementary School, East 2270 at 5.9 miles 53 Figure 3.3-2 Fulton High School 1830 at 13.7 miles 54 Figure 3.3-2 Mexico High School 1150 at 9.4 miles 55 Figure 3.3-2 Pulaski Gas Substation, Rt. 5 750 at 13.0 miles 3 - 20

- m -m u- m- - - m m

M -M m m m m mM M m m mM TABLE 3.3-1 (Continued) 2011 ENVIRONMENTAL SAMPLE LOCATIONS

.MAP DEGREES &,DISTANCE SAMPLE MEDIUM DESIGNATION FIGURE NUMBER LOCATION"DESCRIPfION (c.d)

(& b)

Thermoluminescent 56* Figure 3.3-2 New Haven Elementary School 1240 at 5.2 miles Dosimeters (TLD) 58* Figure 3.3-2 County Route IA and Alcan 222' at 3.0 miles (Continued) 75* Figure 3.3-3 North Fence, NMP2 3540 at 0.1 miles 76* Figure 3.3-3 North Fence, NMP2 270. at 0.1 miles 77* Figure 3.3-3 North Fence, NMP2 370 at 0.2 miles 78* Figure 3.3-3 East Boundary, JAFNPP 860 at 1.0 miles 79* Figure 3.3-3 County Route 29 121' at 1.2 miles 80* Figure&3.3-3 County Route 29 1360 at 1.5 miles 81' Figure 3.3-3 Miner Road 1600 at 1.7 miles 82* Figure 3.3-3 Miner Road 1800 at 1.6 miles 83* Figure 3.3-3 Lakeview Road 2030 at 1.2 miles 84* Figure 3.3-3 Lakeview Road 2250 at 1.1 miles 85* Figure 3.3-3 North Fence, NMP1 2900 at 0.2 miles 86* Figure 3.3-3 North Fence, NMP! 3100 at 0.1 miles 87* Figure 3.3-3 North Fence, NMP2 3320 at 0.1 miles 88* Figure 3.3-2 Hickory Grove Road 970 at 4.5 miles 89* Figure 3.3-2 Leavitt Road 1120 at 4.3 miles 90* Figure 3.3-2 Route 104 and Keefe Road 1350 at 4.2 miles 91* Figure 3.3-2 County Route 51A 1570 at 4.9 miles 92* Figure 3.3-2 Maiden Lane Road 1830 at 4.5 miles 93* Figure 3.3-2 County Route 53 2060 at 4.4 miles 94* Figure 3.3-2 Country Route 1 and Kocher Road 2240 at 4.4 miles 95* Figure 3.3-2 Lakeshore Camp Site 2390 at 3.7 miles 96* Figure 3.3-2 Creamery Road 1990 at 3.7 miles 97* Figure 3.3-3 County Route 29 1450 at 1.8 miles 98* Figure 3.3-2 Lake Road 1030 at 1.2 miles 99 Figure 3.3-2 Nine Mile Point Road 920 at 1.8 miles 100 Figure 3.3-3 Country Route 29 and Lake Road 1060 at 1.1 miles 101 Figure 3.3-3 County Route 29 1340 at 1.4 miles 102 Figure 3.3-2 Oswego County Airport 1750 at 11.9 miles 103 Figure 3.3-3 Energy Center, East 2680 at 0.4 miles 104 Figure 3.3-2 Parkhurst Road 1020 at 1.4 miles 3 -21

TABLE 3.3-1 (Continued) 2011 ENVIRONMENTAL SAMPLE LOCATIONS MAI~DEGREES -&'DISTANCE SAMPLE.MEDIUM .-DESIGNATION FIG R NUMBER LOCATION DESCRIPTION & D)

(a & b)

Thermoluminescent 105 Figure 3.3-3 Lakeview Road 1990 at 1.4 miles Dosimeters (TLD) 106 Figure 3.3-3 Shoreline Cove, West of NMP1 272' at 0.3 miles (Continued) 107 Figure 3.3-3 Shoreline Cove, West of NMP1 271' at 0.3 miles 108 Figure 3.3-3 Lake Road 105' at 1.1 miles 109 Figure 3.3-3 Lake Road 1040 at 1.1 miles 111 Figure 3.3-2 Sterling, NY- Control 2140 at 21.8 miles 112 Figure 3.3-2 EOF/Env. Lab, Oswego County Airport 1750 at 11.9 miles 113 Figure 3.3-2 Baldwinsville, NY - Control 1780 at 24.7 miles Cows Milk 55 Figure 3.3-4 Indicator Location 970 at 8.8 miles 77* Figure 3.3-4 Control Location 190' at 16.0 miles Food Products 133** Figure 3.3-5 Indicator Location 840 at 1.6 miles 134** Figure 3.3-5 Indicator Location 84' at 1.5 miles 144* Figure 3.3-5 Indicator Location 1390 at 1.6 miles 145* Figure 3.3-5 Control Location 2220 at 15.4 miles 484* Figure 3.3-5. Indicator Location 1320 at 1.4 miles Groundwater** MW 1-13 Figure 3.3-6 Down Gradient Wells - Indicator 2580 to 780 at <0.3 miles GMX-MW-1 Figure 3.116 Upland Well - Control 1600 at 0.1 miles GMX-MW-2 Figure 3.3-6 Upland Well - Control 1980 at 0.1 miles MW-B119 Figure 3.3-6 Upland Well - Control 195' at 0.3 miles Storm Drain Figure 3.3-6. NMP2 Dewatering System - Indicator 32' at <0.1 miles Table Notes:

(a) Sample marked by an asterisk (*) are location required by ODCM (b) Sample marked by an double asterisk (**) are optional locations (c) Degrees and distance based on Nine Mile Point Unit 2 Reactor Centerline (d) Degrees and Distances updated by Global Positioning System (GPS) 3 - 22

m m m M m m m m m m m m m m m m m m m FIGURE 3.3-1 NEW YORK STATE MAP NQY/ YORK<

K 0 0 n /VO' I)

I

-AMI fRME lMmULVAM C -~en NINE MILE POINT SITE:

Nine Mile Point Nuclear Station Unit - 1 Nine Mile Point Nuclear Station Unit- 2 James A. FitzPatrick Nuclear Power Plant 3 - 23

I FIGURE 3.3-2 OFF-SITE ENVIRONMENTAL STATION AND TLD LOCATIONS L

v I Montarlo I

I 2TLD KEY:

I LOCATION ENVIRONMENTAL STATION Lake Oswego County Ontario I New York I

SCALE IN MILES 0 1 2 3 4 5 I

I I

I I

I I

I I

1 I

I 3 - 24 I

Sit MaM3.WLaeOnai 112o* ENEs WI W 2812302 30

.1 (tenths)

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

SSURFACE WATER LOCATION MILK SAMPLE LOCATION Lake Oswego County Ontario New York SCALE IN MILES 0 1 2 3 4 5 5MI.

10 MI.

1, 3 - 26

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

C FISH A FOOD PRODUCT D SHORELINE ONEAREST RESIDENCE (Based on NMP-U nit 2 Centerline)

SEDIMENT Lake

.Oswego County Ontario New York 78.750 SCALE IN MILES 0 1 2 3 4 5 25*EFE 258.

0 FSE 21

,4 allI FS S-WI rF-] SEKE 3 - 27

FIGURE 3.3-6 NMPNS ON-SITE GROUNDWATER MONITORING WELLS AND UNIT 2

'4 Unit 2 Storm LAKE ONTAJPJO STORM DRAIN OUTFALL

- Monitoring Well Location

/AA - Storm Drain Outfall 001 11.25 ENE 200 W 1 Ground Water Monitoring well is located south of Lake Road at a distance and direction of FGMX-MW1 1,355 yrds @ 195 degrees, (SSW). Based on NMP2 Rx Building. ,

3 - 28

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

The milch animal census is an estimation of the number of cows and goats within an approximate ten-mile radius of the Nine Mile Point site: This census is performed once per year in the summer by sending questionnaires to previous milch animal owners, and by road surveys to locate any possible new owners. In the event that questionnaires are not answered, the owners are contacted by telephone or in person. The Oswego County Cooperative Extension Service 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. Several of the site meteorological sectors are located over Lake Ontario; therefore, there are only eight sectors over land where residences are located within five miles.

In addition to the milch animal and residence census, a garden census is performed. The census is conducted each year to identify the gardens near the site that are to be used for the collection of food product samples. The results of the garden census are not provided in this report. The results are used only to identify appropriate sample locations. The garden census is not required by the ODCMs if broadleaf vegetation sampling and analysis is performed.

3.5 CHANGES TO THE REMP PROGRAM There were no changes to the 2011 REMP sampling program.

3.6 DEVIATION AND EXCEPTIONS TO THE PROGRAM The noted exceptions to the 2011 sample program address only those samples or monitoring requirements which are required by the ODCM. This section satisfies the reporting requirements of Section D 6.9.1 .d of the NMP1 ODCM and Section D 4.1.2 of the NMP2 ODCM.

A. ODCM PROGRAM DEVIATIONS The following are the deviations from the program specified by the NMP 1 and NMP2 ODCM:

1. The air station sample pumps at RI and R2 off-site environmental sampling stations were inoperable for approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> each during the sampling period of February 1, 2011 to February 8, 2011. The sample pump out-of-service time was determined based on the sample pump run time integrator. The inoperability of the pump was due to loss of power to the air station. No corrective actions were required to restore power to the air stations.

3 - 29

I

2. The air station sample pumps at R3 and R4 off-site environmental sampling stations were inoperable for approximately 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> each during the sampling period of March 8, 2011 to March 15, 2011. The sample pump out-of-service time was determined based on the i

sample pump run time integrator. The inoperability of the pump was due to loss of power to the air station. No corrective actions were required to restore power to the air stations.

3. The air station sample pumps at R3 and R4 off-site environmental sampling stations were inoperable for approximately 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> each during the sampling period of May 10, 2011 to May 17, 2011. The sample pump out-of-service time was determined based on the sample pump run time integrator. The inoperability of the pump was due to loss of power to the air station. No corrective actions were required to restore power to the air stations.

4. The air station sample pump at R5 off-site environmental sampling station was inoperable for approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> during the sampling period of June 7, 2011 to June 14, 2011.

5 The sample pump out of service time was determined based on the sample pump run time integrator. The inoperability of the pump was due to loss of power to the air station. No corrective actions were required to restore power to the air station.

1

5. The air station sample pump at R3 off-site environmental sampling station was inoperable i for approximately 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> during the sampling period of July 12, 2011 to July 19, 2011.

The sample pump out of service time was determined based on the isample pump run time integrator. The inoperability of the pump was due to equipment failure, i.e., the cabinet blower fan. The cabinet blower fan was replaced and the air station was returned to service.

6. The Oswego Steam Station Inlet Canal surface water sampler was discovered inoperable i on July 22, 2011. The sampler was out of service for 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> due to equipment failure, an electrical breaker trip. The electrical breaker was reset.

B. AIR SAMPLING STATION OPERABILITY ASSESSMENT 3 The ODCM required air sampling program consists of 5 individual sampling locations. The collective operable time period for the air monitoring stations was 43,621 hours0.00719 days <br />0.173 hours <br />0.00103 weeks <br />2.362905e-4 months <br /> out of a possible 43,800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />. The air sampling availability factor for the reporting period was 99.59%.

3.7 STATISTICAL METHODOLOGY 3 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 I

3 -301

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

n Xi A. Mean N

Where, X = estimate of the mean i = individual sample, i N, n = total number of samples, with positive indications Xi = value for sample i above the lower limit of detection B. Standard Deviation 1/2 n

S-.

(N-i)-

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

3 -31

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

A. Mean

-I I i=1 xi I

N Where, 3 X = estimate of the mean i

N, n Xi

= individual sample, i

= total number of samples with positive indications

= value for sample i above the lower limit of detection 3

I B. Error of the Mean n ( 1/2 ERROR MEAN = (ERROR)2 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 (a)

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

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

3.7.3 LOWER LIMIT OF DETECTION (LLD)

The LLD is the predetermined concentration or activity level used to establish a detection limit for the I 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:

3-32

4.66 Sb LLD =

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

Where:

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

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

E = the counting efficiency (in counts per disintegration)

V = the sample size (in units of mass or volume) 2.22 = the number of disintegrations per minute per picocurie Y - the fractional radiochemical yield (when applicable)

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

• The counting times for the sample and background are equal

" The count rate of the background is approximately equal to the count rate of the sample.

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

Table 3.7-1 lists the ODCM program required LLDs for specific media and radionuclides. The LLDs actually achieved are routinely lower than those specified by the ODCM.

3-33

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

Analysis Water Airborne Particulate or Gases Fish Milk Food Products Sediment (pCi/1) (pCi/m3 ) (pCi/kg, wet) (pCi/1) (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 1-131 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, an LLD value of 3000 pCi/liter is used for H-3, and an LLD value of 15 pCi/liter is used for 1-131.

3 - 34

- mmmmmm - m m m m m -m m-m m m -

3.8 COMPLIANCE WITH REQUIRED LOWER LIMITS OF DETECTION (LLD)

Tables D 4.6.20-1 and D 3.5.1-3 of the NMPI ODCM and NMP2 ODCM, respectively, specify the detection capabilities for environmental sample analysis (See Table 3.7-1). The reporting requirements of NMIP1 ODCM, Section D 6.9.1.d and NMP2 ODCM, Section D 4.1.2 require that a discussion of all analyses for which the LLDs required by Tables D 4.6.20-1 and D 3.5.1-3 were not achieved be included in the Annual Radiological Environmental Operating Report. This Section is provided pursuant to this requirement.

All sample analyses performed in 2011, as required by the ODCM, achieved the LLD specified by ODCM Tables D 4.6.20-1 and D 3.5.1-3.

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

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

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

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

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

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

• less than or equal to 3 mrem per year to the total body, or

• less than or equal to 10 mrem per year to any organ.

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

• less than or equal to 10 mrad per year for gamma radiation, or

• less than or equal to 20 mrad per year for beta radiation.

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

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

3 - 35

I I

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

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

• less than or equal to 25 mrem per year to the whole body,

• less than or equal to 75 mrem per year to the thyroid, and

• less than or equal to 25 mrem per year to any other organ.

I I

I I

I I

I I

I I

I I

3 -36 i

4.0 SAMPLE

SUMMARY

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

Column

1. Sample medium.

2. Type and number of analyses performed.

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

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 2011*

NUMBER OF~

~LOCATION~

NOREPRI; MEAN~ /~RA~NGE R Shoreline Gamma-Spectrum Sediment Analysis (GSA) (4):

(pCi/kg-dry) Cs-134 150 <LLD <LLD <LLD 0 Cs-137 180 <LLD <LLD <LLD 0 Fish GSA ( 1 8 )(d):

(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 I I h 4-2 m - l M M M M M M M M Mm M M M M ý M

- - m m m m m - - m m m m m m m TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2011*

Surtace Water H-3 (8):

(pCi/liter)

H-3 3000(e) <LLD <LLD <LLD 0 GSA (24):

Mn-54 15 <LLD <LLD <LLD Fe-59 30 <LLD <LLD <LLD Co-58 15 <LLD. <LLD <LLD Co-60 15 <LLD <LLD <LLD Zn-65. 30 <LLD <LLD <LLD Zr-95 15 <LLD <LLD <LLD Nb-95 15 <LLD <LLD <LLD 1-131 15(e) <LLD <LLD <LLD Cs-134 15 <LLD <LLD <LLD Cs-137 18 <LLD <LLD <LLD Ba/La-140 15 <LLD <LLD <LLD I I~h I I 4-3

TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2011*

NUMBER~

~R.~TS TLD (mrem per Gamma Dose (140) 4.8 (120/120) (g) TLD #85 (h): 10.6 (4/4) 4.0 (20/20) 0 standard month) 2.9-11.6 0.2 miles at 290' 9.5-11.6 2.6-5.5 Air Particulates Gross Beta (260): 0.01 0.018 (208/208) R-1 0.018 (52/52) 0.018 (52/52) 0 (pCi/m3) 0.007 - 0.034 1.8 miles at 920 0.007 - 0.033 0.008 - 0.034 1-131 (260): 0.07 0.055 (12/208) R-1 0:059 (3/52) 0.055 (3/52) 0 0.021 -0.11 1.8 miles at 920 0.034 - 0.100 0.034 -.093 GSA (20):

Cs-134 0.05 <LLD <LLD <LLD 0 Cs-137 0.06 <LLD <LLD <LLD 0 Milk GSA (36): (d)(i)

(pCi/liter) Cs-134 15 <LLD <LLD <LLD 0 Cs-137 18. <LLD <LLD <LLD 0 Ba/La-140 15 <LLD <LLD <LLD 0 1-131 (36):

1-131 1 <LLD <LLD <LLD 0 4-4

- - - M M M M M -

M M - M M M M M M

m m m m m m m m m m m m m m m m m m m TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2011*

~N L BA (14): (d)

Food Products GS (pCi/kg-wet) 1-131 60 <LLD <LLD <LLD 0 Cs-134 60 <LLD <LLD <LLD 0 Cs-137 80 <LLD <LLD <LLD 0 i I~ I 4-5

TABLE NOTES:

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

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

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

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

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

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

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

(g) Indicator TLD locations are: #7, 15, 18,23, 56, 58, 75, 76, 77, 78, 79, 80, 81, 82, 83, 84, 85, 86, 87, 88, 89, 90, 91, 92, 93, 94, 95, 96, 97, and 98. Control TLDs are all TLDs located beyond the influence of the site (TLD #8, 14, 49, 11 1,,and 113).

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

(i) The ODCM criteria for indicator milk sample locations include locations within 5.0 miles of the site. There are no milk sample locations within 5.0 miles of the site. Therefore, the only sample location required by the ODCM is the control location. There was one optional location during 2011.

4-6 M l-i m M M M M m MM m M MM

5.0 DATA EVALUATION AND DISCUSSION A. Introduction Each year, the results of the Radiological Environmental Monitoring Program (REMP) are evaluated with consideration of plant operations at the site, the natural processes in the environment and the archive of historical 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. This report not only presents the data collected during the 2011 sample program, but also assesses the significance of radionuclides detected in the environment. It is important to note that detection of a radionuclide is not, of itself, an indication of environmental significance. Evaluation of the impact of the radionuclide in terms of potential increased dose to man, in relation to natural background, is necessary to determine the true significance of any radionuclide detection.

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

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

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

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

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

C. Dose/Dose to Man The dose or dose equivalent, simply put, is the amount of ionizing energy deposited or absorbed in living tissue. The amount of energy deposited or ionization caused is dependent on the type of radiation. For example, alpha radiation can cause dense localized ionization that can be up to 20 times the amount of ionization for the same energy imparted 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 5-1

U type of ionizing radiation. The dose equivalent is measured in rem (roentgen equivalent man). In I

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. I 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 I

D.

dose to man are: the inhalation pathway, the ingestion pathway and direct radiation.

Discussion I

In the United States, a person's average annual radiation dose is 620 mrem. About half that I 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.

I 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 I

gas (naturally occurring) and diagnostic medical procedures (manmade).

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

I Consumer Products Terrestrial (soil) 3%

I Cosmic (space)

~-5%

5%

Internal I

Radon and Thoron 37%

Nuclear Medicine 12%

I I

I D -310 millirem (0.31 rem)

Natural Sources - 50%

r Medical Procedures 36% * -310 Manmade millirem (0.31 -rem)

Sources 50% I II 5-2 II I

There are three separate groups of radionuclides that were measured in the environment and analyzed for the 2011 sampling program.

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

• A number of naturally occurring radionuclides are present in the environment. These are expected to be present in many of the environmental samples collected in the vicinity of the Nine Mile Point Site. Some of the radionuclides normally present include:*

• Tritium (H-3), present as a result of the interaction of cosmic radiation with the upper atmosphere.

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

2. The second group consists of radionuclides that may be detected in the environment as a result of the detonation of thermonuclear devices in the earth's atmosphere. Atmospheric nuclear testing during the early 1950's produced a measurable inventory of radionuclides presently found in the lower atmosphere, as well as in ecological systems. In 1963, an Atmospheric Test Ban. Treaty wds signed. Since the treaty, the global inventory of manmade radioactivity in the environmenit 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 wyeapons:tests have been conducted by the People's Republic of China and underground Weapons testing'b.ij 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 (Cs-137) and Strontium-90 (Sr-90). The highest weapons testing concentrations were noted in samples 5-3

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

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

During 2011, 1-131 was detected in REMP samples and has been attributed to the trans-Pacific transport of airborne releases from Fukushima Daiichi Nuclear Power Stations fallout following the Tohoku earthquake and is not related to the operations of NMP1 or NMP2. There were no other plant-related radionuclides detected in the REMP samples collected during 2011. 5 A number of factors must be considered in performing radiological sample data evaluation and interpretation. An attempt has been made not only to report the data collected during 2011, but n also to assess the significance of the radionuclides detected in the environment as compared to naturally occurring and manmade radiation sources. It is important to note that detected concentrations of radionuclides in the local environment as a result of man's technology are i very small and are of no or little, significance from an environmental or dose to man perspective. 3 The 2009 per capita average dose was determined to be 620 mrem per year from all sources, as noted in National Council on Radiation Protection and Measurement (NCRP) Report No. 160.

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

The naturally occurring gamma radiation in the environs of the Nine Mile Point site, resulting from 3 radionuclides in the atmosphere and in the ground, accounts for approximately 60-65 mrem per year. This dose is a result of radionuclides of cosmic origin (for example, Be-7) and of primordial origin Ra-226, K-40, and Thorium-232 (Th-232). A dose of 60 mrem per year, as a background I dose, is significantly greater than any possible doses as a result of routine operations at the site during 2011. 5 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 3

short-term trends.

5-4

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

o 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 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 2011 program.

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

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

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

• Shoreline Sediment

• Fish

• Surface Waters

• Groundwater Section 6.0, Tables 6-1 through 6-4 present the analytical results for the aquatic samples collected for the 2011 sampling period.

Sampling for groundwater, as found in Section D 3.5.1 of the NMP2 ODCM, was not required during 2011. There was no groundwater source in 2011 that was tapped for drinking or irrigation purposes in 5-5

I areas where the hydraulic gradient or recharge properties were suitable for contamination; therefore, groundwater was not a dose pathway during 2011.

5.1.1 SHORELINE SEDIMENT RESULTS A. Results Summary I Shoreline sediment samples were obtained in April and October of 2011 at one off-site control location (Lang's Beach located near Oswego Harbor) and at one indicator location (Sunset Bay),

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

A total of four sediment samples were collected for the 2011 sample program, two indicator and two control. These results continue to show a downward trend over the past 10 plus years. Cs-137 was not detected in samples collected from the control or indicator locations during 2011. I Historical mean concentrations measured at the Sunset Bay indicator location ranged from a maximum of 0.33 pCi/g in 1993 to a minimum of less than lower limit of detection (<LLD) in 2011. The results I for the 2011 control location were less than the detection limit. The one naturally-occurring radionuclide detected was K-40, which was not related to plant operations. No other plant-related radionuclides were detected in the 2011 shoreline sediment samples.

The following is a graph of the average Cs-137 concentration in shoreline sediment samples over the previous ten years. This graph illustrates a general downward trend in the Cs-137 concentrations since 2001.

Shoreline Sediment Cs-I137 1. I U.U0 I MCCntrol N Indicator 0.08 Note: Years with values of less than the lower 0.07 limit of detection are presented as zero In the graph.

0.06 0,05 0,04 0.03 0.02 0.01 0

2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Year 5-6 I I

B. Data Evaluation and Discussion Shoreline sediment samples are routinely collected twice per year from the shoreline of Lake Ontario. Samples are collected from one indicator location (Sunset Bay) and one control location (Lang's Beach). Samples were collected from both the indicator and control locations in April and October 2011. The results of these sample collections are presented in Section 6.0, Table 6-1, Concentrations of Gamma Emitters in Shoreline Sediment Samples - 2011. K-40 was the only significant radionuclide detected in the sediment samples.

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

The radiological impact of Cs-137 measured in the shoreline sediment can be evaluated on the basis of dose to man. In the case of shoreline sediments, the critical pathway is direct radiation to the whole body and skin. Using the parameters provided in Regulatory Guide 1.109, the potential dose to man in mrem per ytear can be calculated. The following regulatory guide values and the maximum 2011 shoreline sediment indicator Cs-137 concentration 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/m 2 (dry) to a depth of 2.5 cm;'

• The shoreline width factor is 0.3, and

• The maximum 2011 Cs-137 concentration of <0.106,pCi/g (dry) (<LLD).

Using these conservative parameters, the potential dose to the maximum exposed individual (teenager) would be 0.00036 mrem/year to the whole body and 0.00042 mrem/year to the skin.

This calculated dose is very small and is insignificant when compared to the natural background annual exposure of approximately 48 mrem as measured by control TLDs in the vicinity of the site.

D. Data Trends Cs-137 was not detected at the indicator or the control samples locations in 2011. The average Cs-137 concentration (LLD) for the Shoreline sediment indicator sample for 2011 was <0.091 pCi/g (dry). This is consistent with mean concchtratioh-measured at the indicator location over the past ten years.

The previous five years of data show a general dedreasing~mean concentration values measured at the indicator locations. Over the five year period, mean concentrations ranged from a high of 0.08 pCi/g (dry) in 2005 to a low value of 0.04 pCi/g (dry) measured in 2007. Cesium-137 was not detected in the control location samples over this same five-year period.

5-7

I The general absence of Cs-137 in the control samples is attributed to the differences in the sediment types between the two sample locations. Few shoreline regions west of the site contain l fine sediment and/or sand that are characteristic of the indicator location. It is difficult to obtain control samples that are comparable in physical and chemical characteristics to the indicator samples. Other factors, which include changing lake level and shoreline erosion, further I complicate attempts at consistency in shoreline sediment sampling. Recent soil samples from locations beyond any expected influence from the site have contained levels of Cs-137 equal to or greater than the concentrations found in the shoreline sediment samples collected in the past. The Cs-137 is commonly found in soil samples and is attributed to weapons testing fallout. Shoreline samples containing soil or sediment are likely to contain Cs-137. 3 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 i period of 2001 through 2010, mean concentrations at the indicator location ranged from a maximum of 0.08 pCi/g (dry) in 2005 to a minimum of 0.04 pCi/g (dry) measured in 2004 and again in 2007. Cs-137 was not detected at the indicator location for 2008 thru 2011. This continues to support the long-term decreasing trend in Cs-137 concentration in shoreline sediment samples.

I Cesium- 137 was not detected in the control samples collected over the previous ten years. i Shoreline sediment sampling at the indicator location commenced in 1985. Prior to 1985, no data was available for long-term trend analysis. . I Section 7.0, Tables 7-1, Historical Environmental Sample Data, Shoreline Sediment (Control) and 7-2, Historical Environmental Sample Data, Shoreline Sediment (Indicator), illustrate historical environmental data for shoreline sediment samples.

5.1.2 FISH SAMPLE RESULTS A. Results Summary 3 A total of 18 fish samples were collected for the 2011 sample program. Species collected were:

smallmouth bass, brown trout, chinook salmon and walleye. The analytical results for the 2011 fish samples showed no detectable concentration of radionuclides that would be attributable to plant operations at the site or past atmospheric weapons testing. Since 2003, no Cs-137 has been measured in fish samples. Over the previous 20 years prior to 2003; Cs-137 has been detected at both the indicator and/or control locations (Refer to Tables 7-3 and 7-4). These low levels of Cs-137 represented no significant dose to man or impact on the environment.

The 2011 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 2011 results are consistent with the previous years' results in that they continue to support the general long-term downward trend in fish Cs-137 concentrations over the last 34 years. Cs-137 I

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was not detected in fish samples collected in 2003 to 2011 from indicator locations. The period of 2001 through 2011 as a group are the lowest results measured since the beginning of the Site Environmental Monitoring Program in 1969.

B. Data Evaluation and Discussion Fish collections were made utilizing gill nets at one 'location greater than five miles from the site (Oswego Harbor area) and at two locations in the vicinity of'the lake discharges for the NMPNS and the JAFNPP facilities. The Oswego Harbor samples served as control samples, while the NMPNS and JAFNPP samples served as indicator samples. , All samples were analyzed for gamma-emitters. Section 6.0, Table 6-2, Concentration of Gamma Emitters in Fish Samples- 2011, shows individual results for all the samples collected in 2011 in units of pCi/g (wet).

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

Walleye, smallmouth bass and brown trout were collected.

The total fall fish collection was comprised of 9 individual samples representing three individual species. Chinook salmon, smallmouth bass and brown trout were collected.

Cs-137 was not detected in any of the fish species collected for the 2011 sample program.

C. Dose Evaluation Fish represent the highest level in the aquatic food chain and have the potential to be a contributor to the dose to man from the operations at the site. Some Lake Ontario. fish species may be considered an important food source due to the local sport fishing industry. Therefore, these fish are an integral part of the human food chain. The lack of detectable concentrations of plant-related radionuclides in the 2011 fish samples demonstrates that there is no attributable dose to man from operations at the site through the aquatic pathway.

D. Data Trends The Cs-137 data for fish samples over the previous five years (2006 through 2010) show that the number of positive detections has decreased over this period relative to historical data. There were no positive detections of Cs-137 over the previous five-year period at the indicator locations. The graph below illustrates the mean control and indicator Cs-137 concentrations for 2011 and the previous ten years.

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I 0,018 Annual Mean FIsh Cs-137 Concentrations I 0.016 0.014 F mControl aIndcator Note: Years with values of less than the I

0.012 lower limit of detection are presented as 0.01 IL 0.008 zero in the graph.

I 0.006 0.004 i

0,002 0

I Y80ar I

The ten-year data trend shows a consistent decrease in the level of Cs-137 measured in fish between 2001 and 2011. The 2001 through 2011 results, as a group, are the lowest Cs-137 concentrations measured over the existence of the sample program. I The general long-term decreasing trend for Cs-137, illustrated in the following graph, is most probably a result of the cesium becoming unavailable to the ecosystem due to ion exchange with I

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.

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

I Fish Cs-137 i

1.4 1.2 EControl Mludicator I

I Note: Years with values of less than the lower limit of detection are presented as zero in the graph. I 0.8 0.6 I

J 0.4 0.2 I Year I 5-10 I

5.1.3 SURFACE WATER.(LAKE)

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

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

Intake and the Nine Mile Point Unit 2 (NMP2) Intake. Gamma spectral analysis was performed on 24 monthly composite samples from the ODCM locations and on 36 monthly composite samples collected from the additional sample locations. The results of the gamma spectral analyses showed that only naturally-occurring radionuclides were detected in the 60 samples from the five locations collected for the 2011 Sampling Program. The two nattirally-occurring radionuclide detected were K-40 and Ra-226 and were not related to plant operations. Monthly composite samples showed no presence of plant-related gamma-emitting isotopes in the waters of Lake Ontario as a result of plant operations.

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

A total of 20 samples were analyzed for tritium as part of the 2011 REMP program. The results for the 2011 samples showed no positive detection for tritium in samples taken during 2011.

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 2011 samples. This is consistent with historical data, which has not shown the presence of plant-related radionuclides in surface water samples.

Tritium samples are quarterly samples that are a composite of the applicable monthly samples for a given location. Tritium samples' analyzed for the 2011 sample program were analyzed to an instrument detection level of 500 pCi/l.

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

The 2011 results had LLD values that ranged from <410 pCi/l to <432 pCi/l. The ODCM control location (Oswego Generating Station inlet canal) results showed no positive' detections, and the sample results had LLD values in the range of <412 pCi/l to <432 pCi/l.

Tritium was not detected in any of the twelve optional Lake Ontario samples collected in the 2011 program.

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

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I The following table provides the specific results for the 2011 sample program:

I Sample Tritium Concentration pCi/liter I Location Minimum Maximum Mean JAFNPP Inlet (Indicator)* <410 <432 (Annual)

• <419.

I Oswego Generating Station Inlet <412 <432 " <419 (Control)* (oto)

NMP1 Inlet <417 <432 <419 I

NMP2 Inlet <412 <432 <419 Oswego City Water Supply Sample location required by ODCM

<412 <450 <428 I The LLD values are below the ODCM required LLD of 3000 pCi/1 for a non-drinking water pathway. I Analytical results for surface water samples are found in Section 6.0, Table, 6-3,. Concentration of Tritium in Surface Water, Samples - 2011 and Table 6-4, Concentration of Gamma Emitters in I Surface Water Samples -20111.

C. Dose Evaluation ."

I The radiological impact to members: 6fithe 0ublc from low levels of tritium in water is insignificant.

This-can .be illustrated by calculatifig., dose to- the -whole botay-and maximum organ using the I

maximum LLD value and Regulatory Guidel. 109 methodology. Based on a water ingestion rate of 510 liters/yr and the maximum 2011 LLD concentration of <450 pCi/l, the calculated dose would be less than 0.045 mrem to the child whole body and less than 0.045 mrem to the child liver (critical age I

group/organ).

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

Tritium results for the 2011 lake water samples were consistent with results from the previous five-I years for both the indicator and control locations. The mean measured tritium concentrations for the previous five-year period of 2006 to 2010 was <LLD pCi/l for the control and the indicator location.

The mean 2011 tritium concentrations were <419 pCi/l for the control and <419 pCi/l for the indicator I

locations. The previous five-year data indicates no significant trends in either the indicator or the control mean concentrations. This previous five-year data set is consistent with long-term tritium results measured at the site. The indicator data from the previous ten-year period, 2001 through 2010, I

are representative of natural variations in environmental tritium concentrations with no significant levels of tritium measured. The 1999 mean control value of 337 pCi/I is the highest concentration I 5-12

measured since 1989 and is within the variability of results measured over the life of the program. The ten-year historical results are consistent between the control and indicator locations with no large variation in the measured results.

The following graph illustrates the concentrations of tritium measured in Lake Ontario over the previous 21 years at both an indicator and control location. Prior to 1985, the Oswego City Water Supply results were used as control location data as this location closely approximates the Oswego Generating Station, the current control location.

Surface Water Tritium 500 450 Note: Years with vw 400 detection are prese 350 300 250 200 150 100 50 0

a, a, ON 0, 0% 0% a, 0 0 0 0 0 10 0 0

'ear N 0% 0 Year Section 7.0, Tables 7-5, Historical Environmental Sample Data Surface Water (Control) and 7-6, Historical Environmental Sample data Surface Water (Indicator), show the historical environmental sample data for surface water Co-60 and Cs-137. Tables 7-7, Historical Environmental Sample Data, Surface Water Tritium (Control) and 7-8, Historical Environmental Sample Data, Surface Water Tritium (Indicator) show historical the environmental sample data for surface water tritium.

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

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

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U A total of 44 tritium samples were collected for the 2011 sample program using ten indicator locations and three control locations. All samples results for 2011 groundwater monitoring program were less than the LLD for tritium. i A total of 86 samples were collected for plant-related gamma-emitters, and thirteen strontium-90 (Sr-90) samples were collected for the 2011 sample program using ten indicator locations and three i control locations. All samples results for 2011 groundwater monitoring program were less than the LLD for plant-related gamma-emitters and Sr-90.

B. Data Evaluation and Discussion Plant related gamma-emitters and strontium-90 analysis were performed on samples from the indicator i and control locations. No plant-related radionuclides were detected in the 2011 samples. This is consistent with historical data, which has not shown the presence of plant-related radionuclides in groundwater samples.

Tritium samples analyzed for the 2011 sample program were analysed to a lower limit of detection i of 500 pCi/l. The tritium results for the control locations had LLD values that ranged from <386 pCi/I to <424 pCi/l. The indicator locations results ranged from <407 pCi/1 to <430 pCi/l.

C. Dose Evaluation Sampling for groundwater, as found in Section D 3.5.1 of the NMP20DCM, was not required during 2011. There was no groundwater source in 2011 that was tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties support contaminant migration; therefore, drinking water was not a dose pathway during 2011.

D. Data Trends There are no data trends for gamma-emitters or Strontium-90 as these radionuclides have not been detected in groundwater samples. l Groundwater tritium results are documented in the Annual Radiological Effluent Release Report for 2011. Historical data for groundwater tritium is presented in Section 7.0, Tables 7-9, Historical Environmental Sample Data, Surface Water Tritium (Control) and 7-10, Historical Environmental Sample Data, Surface Water Tritium (Indicator).

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

• Airborne Particulate and Radioiodine,

• Direct Radiation,

• Milk, and

• Food Products.

Section 6.0, Tables 6-5 through 6-12 present the analytical results for the terrestrial samples collected for the 2011 reporting period.

5.2.1 AIR PARTICULATE GROSS BETA A. Results Summary Weekly air samples were collected and analyzed for particulate gross beta particulate activity. For the 2011 program, a total of 52 samples were collected from control location R-5, and 208, samples were collected from indicator locations R-1, R-2, R-3, and R-4. These five locations are required by the ODCM. Additional air sampling locations are maintained and are discussed in Section 5.2.1.B below. The mean gross beta concentration for samples collected from the control location (R-5) in 201 1 was 0.0 18 pCi/m 3. The mean gross beta concentration for the samples collected from the indicator locations (k-I, R-2, R-3, and R-4) in 2011 was 0.018 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. The indicator results are consistent. with concentrations measured over the last twenty years. This consistency demonstrates that the natural baseline gross beta activity has been reached. The man-made radionuclide contribution to the natural background from atmospheric weapons testing and Chernobyl can no longer be detected above the background concentrations of naturally occurring beta-emitting radionuclides.

B. Data Evaluation and Discussion The air monitoring system consists of fifteen sample locations, six on-site and nine off-site. Each location is sampled weekly for particulate gross beta activity. A total of 780 samples were collected and analyzed as part of the 2011 program. Five of the nine off-site locations are required by the ODCM. These locations are designated as R-1, R-2, R-3, R-4, and R-5. R-5 is a control location required by the ODCM and is located beyond any local influence from the site. In addition, optional off-site and on-site air sample locations are maintained from which weekly samples are collected. The optional off-site locations are designated as D-2, E, F and G. The optional on-site locations are designated as D-l, G, H, I, J and K.

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I I

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.

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

2011, and 6-6, Environmental Airborne Particulate Samples - Onsite Sample Locations - 2011, present the weekly gross beta activity results for samples collected from the off-site and on-site I

locations. I The mean annual gross beta indicator concentrations for the ODCM indicator stations (R-1, R-2, R-3 and R-4) was 0.018 pCi/m 3. The off-site ODCM control station (R-5) annual mean gross beta I concentration was 0.018 pCi/m 3. The minimum, maximum and average gross beta results for sample locations required by the ODCM were as follows:

I Concentration pCi/m3 Location Minimum Maximum Mean I R-1 0.007 0.033 0.018 R-2 R-3 0.007 0.008 0.032 0.034 0.017 0.018 I

R-4 Summary (RI - R4) 0.008 0.007 0.033 0.034 0.018 0.018 I R-5 (Control) 0.008 0.034 0.018 The mean weekly gross beta concentrations measured in 2011 are illustrated in the following I

graphs:

I Air Particular Filter - Gross Beta (2011)

A ..-....-- Indicator --4--Control I

00200 I

I oaloo*,

I 00 2 3 4 5 6 7 06 9 10 11 12 Week No.

13t 14 15 16 17 18 19 20 21 *22 23 24 5 26 I

5-16 I

I

Ahi Particulate Filter - Gross Beta (2011)

Indicator ~ -Control Week No.

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

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

D. Data Trends With the exception of the 1986 sample data, which was affected by the Chernobyl accident, the general trend in air particulate gross beta activity has been one of decreasing activity since 1981, when the mean control value was 0.165 pCi/m 3. The 1981 samples were affected by fallout from a Chinese atmospheric nuclear test which was carried out in 1980.

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I The mean gross beta concentrations measured in 1977 to 2011 are illustrated in the following graph:

I Air Particulate Filter - Gross Beta 0.18 0.16

• Control KIndicator I 0.14 0.12 1980AtmosphRbc Nuclear Tests I 0.1 0.08 1986 Chernobyl I

0.06 0.04 0.02 I

0 Yea" I The trend for the previous five years represents a base line concentration or natural background I

level for gross beta concentrations. This trend is stable with minor fluctuations due to natural variations. The change in concentrations over the period of 2001 through 2011 is very small. This is illustrated by the following graph:

I Air Particulate Filter - Gross Beta I 002I EControl *Indicator 1

0.018 0.016 0.014 I M Mýu 0 0 MIN MM 0 I

1 I

M N N I S0.012 0.01 I I

0.006 0.004 0 N N M I 0.002 0 0 0 0 N M M N I Year I For the previous 10 years, the mean annual gross beta concentration at the control station (R-5) has remained steady with a narrow range of 0.014 pCi/m 3 to 0.019 pCi/m3 . The mean annual I

concentrations for the indicator stations for this same time period were similar to the control and ranged from a minimum mean of 0.015 pCi/m3 to a maximum mean of 0.018 pCi/m3 . I 5-18 I

I

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

5.2.2 AIRBORNE RADIOIODINE(I-131)'

A. Results Summary From 1987 through 2010, no radioiodine (1-131) has been measured offsite at any of the air monitoring stations.

During the 2011 air sampling program, airborne radioiodine wasAdetected, in 15 of the 260 weekly samples collected at the five sampling stations required by the ODCM.'7 1-131 was detected at both the indicator and control stations during the weeks of March 29; April 5, and April 12. The measurable 6oncentrations of I-.1,31 are attributed to fallout from the Fukushima Daiichi Nuclear Power Station event that occufred on March 11, 2011 and not operations at the site. Observed detectable concentrations of 1-131 ranged from 0.031 to 0.11 pCi/m3 for the indicator stations, and 0.034 to 0.093 pCi/m 3 for the control station.

1-131 was also detected in 30 of the 515 weekly samples collected from the ten optional sampling stations. The positive detections of 1-131 were observed during the same weeks of March and April as noted above for the ODCM required stations. These measurable concentrations of 1-131 are also attributed to fallout from the Fukushima Daiichi Nuclear Power Station event. Observed detectable concentrations of 1-131 ranged from 0.025 to 0.111 pCi/m 3 for the ten optional onsite and offsite stations.

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

The off-site locations required by the ODCM are designated as R-1, R-2, R-3, R-4 and R-5. R-5 is a control station located beyond any local influence from the plant: Ten air sampling locations are also maintained in addition to those required by the ODCM. Six of these stations D-1, G, H, I, J and K are located on-site. D-2, E, F and G are the optional stations located off-site. Samples are collected using activated charcoal cartridges and analyzed weekly for 1-131. 1-131 was detected in 45 of the 780 samplescollected during 2011.

The analytical data for radioiodine are presented in Section 6.0, Tables 6-7, Environmental Charcoal Cartridge Samples - Offsite Sample Locations - 2011 and 6-8, Environmental Charcoal Cartridge Samples -- Onsite Sample Locations - 2011.

C. Dose Evaluation The 1-131 sampling program demonstrated no offsite dose to man from this pathway as a result of operation of the plants located at Nine Mile Point.

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I I

The impact of 1-131 concentrations as a result of the Fukushima Daiichi Nuclear Power Station fallout can be assessed by projecting a maximum organ dose (thyroid) and whole body dose to the critical individual. The critical individual, in this case, would be a child. Using standard Regulatory Guide 1.109 methodology and an inhalation rate of 3700 m3 per year, the thyroid and whole body doses were I

calculated.

The calculated doses due to the average 1-131 concentration from the indicator stations (0.055 pCi/m 3) were 0.05 mrern/yr to the thyroid and 8.6 E-05 mrem/yr to the whole body of the above mentioned critical individual. 3The calculated doses due to the average 1-131 concentration from the control station (0.055 pCi/m ) were 0.05 mrem/yr to the thyroid and 8.6 E-05 mrem/yr to the whole body. The calculated doses from the indicator stations and control station were identical.

I The calculated dose is very small when compared to the natural background annual exposure of approximately 50 mrem as measured by control TLDs in the vicinity of the site.

3 D. Data Trends In 2011, 1-131 was detected at all 15 sampling locations over a three week period. The positive detections were the result of the trans-Pacific transport of airborne releases from Fukushima Daiichi Nuclear Power Station fallout following the Tohoku earthquake.

I No radioiodine had been detected in samples collected from the air sampling locations required by the ODCM since 1987 until 2011.

3 There has been no positive detection of 1-131 in air samples collected over the last ten years that could be attributed to the operation of the Nine Mile Point Site. This demonstrates that there is no measurable environmental impact Or positive trend for iodine buildup due to plant operations during the period from 2001 through 2011. 1-131 has previously been detected in samples collected during the last twenty five year period in 1986 and 1987. The 1986 detection of 1-131 I

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

1-131 has been detected in the past at control locations. Control samples collected during 1976 had a mean 1-131 concentration of 0.60 pCi/m 3. During 1977 this mean decreased to 0.32 pCi/mr3, and further decreased by a factor of ten to 0.03 pCi/m3 in 1978. 1-131 was not detected in samples n collected from the control location during 1979 - 1981 and 1983 to 1985. 1-131 was detected once at the control location during 1982 at a concentration of 0.039 pCi/m3 .

1-131 has been detected in samples collected from the on-site indicator locations during 1976 to 3

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

The 1986 measured concentrations ranged from a minimum of 0.023 pCi/m3 to a maximum of 0.36 pCi/m 3. Each positive detection of 1-131 in samples collected in 1986 was the direct result of the 5-20 I

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

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

5.2.3 QUARTERLY PARTICULATE COMPOSITES (GAMMA-EMITTERS)

A. Results Summary Fifteen air monitoring stations are maintained around the Nine Mile Point site. Five of the 15 air monitoring stations are required by the ODCM; four are located off-site near the site boundary, and one is located off-site as a control location. Ten additional air sampling stations are also maintained as part of the sampling program. Together, these fifteen continuous air sampling stations make up a comprehensive environmental monitoring network for measuring radioactive air particulate concentrations in the environs of the site. Annually, the air monitoring stations provide 780 individual air particulate samples that are assembled by location into 60 monthly composite samples. The quarterly composites are analyzed using gamma spectroscopy.

No plant-related gamma-emitting radionuclides were detected in any of the air particulate filter samples collected during 2011.

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

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

Each of the weekly air particulate filters collected for the quarter is assembled by location to form quarterly composite samples. The quarterly composite samples required by the ODCM are composite samples assembled for R-1, R-2, R-3, R-4 and R-5. Other sample locations not required by the ODCM, for which analytical results have been provided, include six on-site locations and four off-site locations. The analytical results for the 60 air particulate filter composites in 2011 showed no detectable activity,of plant related radionuclides.

5 -21

The results of the quarterly composite samples are presented in -Section 6.0, Table 6-9, Concentration of Gamma in Quarterly Composites of JAFNPP/NMPNS Site Air Particulate Samples - 2011.

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 2011. The monthly air particulate sampling program demonstrated .no off-site dose to man from this pathway as a result of operations of the plants located at the Nine Mile Point site.

D. Data Trends i No plant-related radionuclides were detected during 2011 at the off-site air monitoring locations. 3 The ten-year database of air particulate composite analysis shows that there is no buildup or routine presence of plant related radionuclides in. particulate form in the atmosphere around the site.

Historically Co-60 was detected in each of the years from 1977 through 1984 at both the indicator and control locations, with the exception of 1980 when Co-60 was not detected at the control location. The presence of Co-60 in the air samples collected during these years was the result of atmospheric weapons testing. Co-60, was again detected in an off-site 2000 indicator sample and was the only positive detection of Co-60 since 1984. The detection of Co-60 in the one 2000 sample was an isolated event associated with effluents from the NMP1 facility. There have been no subsequent measurable concentrations of Co-60 in the environment surrounding the Nine Mile Point site. 3 Historical data shows that cesium-137 (Cs-137) is the fission product radionuclide most frequently detected in the air particulate filter composites. Cs-137 was detected in each of the years from 1977 through 1983 at both the control and indicator sampling locations. The presence of Cs-137 in the air samples collected during these years was the result of atmospheric, weapons testing. Cs-137 was again detected in 1986 as a result of the Chernobyl accident. Since 1986 there have been no 3

detections of Cs-137 in the environment surrounding the Nine Mile Point site.

After 1986, no plant-related or fallout radionuclides were detected in any of the off-site air I particulate composite samples with the exception of the isolated detection of Co-60 in 2000 in a single sample. A review of the past five years' data for air particulate filter composites indicates i no plant related radiological impact on the environment. All previous historical positive detections of fission product radionuclides were associated with atmospheric weapons testing or the Chernobyl accident, with the exception of the 2000 detection noted above. i Historical data for air particulate results are presented in Section 7.0, Tables 7-13, Historic Environmental Sample Data, Air Particulate (Control) and 7-14, Historic Environmental Sample Data Air, Particulate (Indicator).

I 5-22 I

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 2011 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 2011. As a result of placing two TLDs at each location, the results presented in this report are the average of two TLD readings obtained for a given location.

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

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

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

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

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

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

All geographical locations are required by the ODCM with the exception of the On-site area which was optional. Description of the five geograpical categories and the designation of specific TLD locations that make up each category is presented in Section 3.1.6, TLD (Direct Radiation) of this report. A summary of the 2011 dose rates for each of the five geographical locations is as follows:

Dose inmrem per standard month Geographic Category Minimum Maximum Mean On-site (Optional) 3.1 13.0 5.1 Site Boundary (Inner Ring) * () 3.1 5.3 4.1 Off-site Sectors (Outer Ring)

• 3.0 5.3 4.0 Special Interest * (2) 2.9 4.9 4.0 Control*( 3) 2.6 4.7 3.8

• Geographical locations required by the ODCM 1 Only includes TLD results that are not affected by radwaste direct shine (TLDs. 7, 18, 78, 79, 80, 81, 82, 83, and 84) 2 Only includes TLD results required by the ODCM (TLDs 15, 56, 58, 96, 97, and 98) 3 Only includes TLD results required by the ODCM (TLDs 14 and 49) 5-23

I Comparison of annual mean dose rates associated with each geographical location indicate that there is no statistical difference in annual dose as a function of distance from the site boundary. The measured annual dose rate at the nearest resident to the site was consistent with the dose rates measured at the site boundary and control locations. The results for the Site Boundary, Off-site I

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

The results for the 2011 environmental TLD monitoring program indicate that there was no significant increase in dose rates as a result of operations at the site., The Hydrogen Water Chemistry systems used at 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 2011, 32 of which are required by the ODCM. These locations are grouped into five geographical location categories for evaluation of results. The five categories include: On-site, Site I Boundary, Offsite by Sector, Special Interest, and Control locations. All categories are required by the ODCM with the exception of the On-site TLDs. On-site TLDs are placed at various locations within the site boundary to provide additional information on direct radiation levels at and around the NMP1, NMP2 and JAFNPP facilities.

On-site TLDs are optional and are subdivided into three categories for which direct radiation results are evaluated. The 2011 direct radiation results for On-site TLD locations were as follows:

1. Results for TLDs located near the NMP1, NMP2 and JAFNPP facilities and at previous or existing on-site air monitoring stations ranged from 3.1 to 13.0 mrem per standard month.

2. Results for TLDs located near the north shoreline of NMP1, NMP2 and JAFNPP in close proximity to the Radwaste and NMP1 Reactor Building ranged from 2.6 to 28.8 mrem per standard month.

3. Results for TLDs located on-site near the Energy Information Center and its associated shoreline ranged from 3.9 to 6.0 mrem per standard month.

Site Boundary TLD results ranged from 3.3 to 11.6 mrem per standard month in 2011. This range included all TLDs placed in each of the 16 meteorological sectors in the general area of the site boundary. The highest dose rate measured at a location required by the ODCM was 11.6 mrem per standard month. This TLD, (TLD 85) represents the site boundary maximum dose and is located in the WNW sector along the lake shore in close proximity to the NMP 1 plant. The TLD locations i

along the lakeshore close to the plants (TLDs 75, 76, 77, 85, 86 and 87) are influenced by radwaste buildings and radwaste shipping activities. These locations are not accessible to members of the public, and the TLD results for these areas are not representative of dose rates measured at the I

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remaining site boundary locations. The remaining Site Boundary TLD locations, which are located away from the plant ranged from 3.1 to 5.3 mrem per standard month resulting in an average dose

• rate of 4.1 mrem per standard month.

• Off-site Sector TLDs, required by the ODCM, located 4 to 5 miles from the site in each of the 8 land based meteorological sectors ranged from 3.0 to 5.3 mrem per standard month with an average dose rate of 4.0 mrem per standard month.

Special Interest TLDs from all locations ranged from 2.9 to 4.9 mrem per standard month with an annual average dose rate of 4.0 mrem per standard month.

The Control TLD group required by the ODCM utilizes locations positioned well beyond the site.

2011 Control TLD results ranged from 2.6 to 5.5 mrem per standard month with an annual average dose rate of 4.0 mrem per standard month. These results include both the ODCM required control TLDs (14 and 49) and the additional controlTLDs (8, 111 and 113).

TLD analysis results are presented in Section 6.0, Table 6-10, Direct Radiation Measurement Results - 2011.

C. Dose Evaluation 2011 annual mean dose rates for each geographic location required by the ODCM are as follows:

Site Boundary: 4.1 mrem per standard month (TLDs: 78, 79, 80, 81, 82, 83, 84, 7 and 18)

Off-site Sectors: 4.0 mrem per standard month (TLDs: 88, 89, 90, 91, 92, 93, 94 and 95)

Special Interest: 4.0 mrem per standard month (TLDs: 15, 56, 58, 96, 97 and 98)

Control: 3.8 mrem per standard month (TLDs 14 and 49)

The measured mean dose rate in the proximity of the closest resident was 4.2 mrem per standard month (TLD #s: 108, 109), which is consistent with the control measurements of 3.8 mrem per standard month.

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

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I D. Data Trends I 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 I meteorological sectors, TLDs located off-site in each land based sector at a distance of 4 to 5 miles from the site, TLDs located at special interest areas and TLDs located at control locations. Site Boundary, Off-site Sector and Special Interest TLD locations became effective in 1985; therefore, I

trends for these results can only be evaluated from 1985 to the present.

The following graph illustrates TLD results for the Control, Site Boundary, Off-site Sectors and I

Special Interest groups from 2002 through 2011:

I TLD Data I

5 4

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I 0

Year I

TLDs located at the site boundary averaged 4.1 mrem per standard month during 2011 (Site I Boundary average results do not include TLDs influenced by radwaste buildings and radwaste shipping activities). This result is consistent with the previous five year average of 4.1 mrem per standard month.

I Off-site Sector TLDs averaged 4.0 mrem per standard month during 2011. This result is also consistent with the previous five-year average of 4.0 mrem per standard month for off-site sectors.

I Special Interest TLD locations averaged 4.0 mrem per standard month during 2011 which is consistent with the previous five-year average of 4.0 mrem per standard month.

I The last group of TLD locations required by the ODCM is the Control Group. This group utilized TLD locations positioned well beyond the site. 2011 control results from all Control TLDs I

averaged 3.8 mrem per standard month, consistent with the previous five-year average of 4.1 mrem I

5 - 26 I

per standard month. The 2011 TLD program results, when compared to the previous ten years, showed no significant trends relative to increased dose rates in the environment.

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

5.2.5 MILK A. Results Summary A total of 36 milk samples were collected during the 2011 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 (1-131).

1-131, a possible plant related radionuclide, is measured to evaluate the cow/milk dose pathway to man. 1-131 was not detected in any of the 36 milk samples collected in 2011 from the two milk sample locations.

Gamma spectral analyses of the milk samplesshowed, nly naturally occurring radionuclides, such as K-40,, were detected in milk samples collected during 2011L K-40 was ,detected in all indicator arid contl samples.. K 0 is anatural1yy ,occurring .radionuclide 'and is found in many environirintal samnible media. .' ".

The 2011 :results' demonstrate'thaf routine operations':,of the Nine Mile point site resulted in no measurable contribution to the dose to the public from the cow/milk pathway.

B. Sampling Overview Milk samples were collected from one indicator. location and. one control location. The ODCM requires that three sample locations be within five miles of the site.. Based on the milch animal census, there were no adequate .milk sample locations within five. miles of the site in 2011.

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

Location No. Direction From Site Distance (Miles) 55 E 8.8 77 (Control) SSW 16.0 5 -27'

Samples were collected from Indicator location #55 and Control location #77 from April through December. Sampling occurs during the first and second half of each month. Samples were not required to be collected during January through March of 2011 as a result of 1-131 not having been detected in samples collected during November and December of 2010, as stipulated in the ODCM.

C. Data Evaluation and Discussion Each milk sample is analyzed for gamma-emitters using gamma spectral analysis. The 1-131 analysis is performed using resin extraction followed by spectral analysis for each sample. 1-131 and gamma analysis results for milk samples collected during 2011 are provided in Section 6.0, Table 6-11, Concentration of Iodine-131 and Gamma Emitters in Milk- 2011.

Iodine 131 was not detected in any indicator or control milk samples analyzed during 2011. 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 2011. 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 2011.

The results of the milk samples are presented in Section 6.0, Table 6-11, Concentration of Iodine-131 and Gamma Emitters in Milk 2011.

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

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

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

E. Data Trends Man-made radionuclides are not routinely detected in milk samples. In the past twenty five years, Cs-137 was only detected in 1986, 1987, and 1988. The mean Cs-137 indicator activities for those years were 8.6, 6.8 and 10.0,pCi/liter, respectively. 1-131 was measured in two milk samples collected in 1997 from a single indicator sample location, having a mean concentration of 0.50 pCi/liter and was of undetermined origin. The previous detection was in 1986 with a mean 5-28

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

The comparison of 2011 data to historical results over the operating life of the plants shows that Cs-137 and 1-131 levels in milk have decreased significantly since the 1980's.

Historical data of milk sample results for Cs-137 and 1-131 are presented in Section 7.0, Tables 7-23, Historical Environmental Sample Data, Milk (Control) and 7-24, Historical Environmental Sample Data, Milk (Indicator).

5.2.6 FOOD PRODUCTS (VEGETATION)

A. Results Summary There were no plant-related radionuclides detected in the 14 food product samples collected and analyzed for the 2011 program.

Detectable levels of naturally occurring K-40 were measured in all control and most of the indicator samples collected for the 2011 program. Be-7 a naturally-occurring radionuclide, was also detected intermittently in samples collected in 2011. These results are consistent with the levels measured in previous years.

The results of the 2011 sampling program demonstrate that there is no measurable impact on the dose to the public from the garden pathway as a result of plant operations.

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

Food product samples collected during 2011 did not include any varieties considered to be edible broadleaf vegetables. The general lack of edible broadleaf vegetation samples was the result of grower preference and such varieties were not available in local gardens. Where broadleaf vegetables were not available, non-edible broadleaf vegetation was collected. Non-edible vegetation consisting of brussel sprout leaves, corn leaves, horseradish leaves, rhubarb leaves, tomatoes leaves, cabbage leaves, grape leaves and squash leaves were collected for the 2011 program. The leaves of these plants were sampled as representative of broadleaf vegetation, which is a measurement of radionuclide deposition.. Samples were collected during the late summer/fall harvest season. Each sample was analyzed for gamma-emitters using gamma spectroscopy. At least one sample from each garden location was analyzed for Carbon-14.

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The analysis of food product samples collected during 2011 did not detect any plant-related radionuclides. Results for the past five years also demonstrate that there is no buildup of plant-related radionuclides in the garden food products grown in areas close to the site.

Naturally-occurring Be-7 and K-40 were detected in food product samples. The results for naturally-occurring radionuclides are consistent with the data of prior years. I Analytical results for food products are found in Section 6.0, Table 6-12, Concentration of Gamma Emitters and C-14 in Food Products - 2011. I C. Dose Evaluation 3 The calculated dose as a result of plant effluents is not evaluated due-to the fact that no plant-related radionuclides were detected. The food product sampling program demonstrated no measurable off-site dose to man from this pathway as a result of operations of the plants located at I

the Nine Mile Point site.

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

The last positive indication was for Cs-137 which was detected at one indicator location in 1999 with a concentration of 0.008 pCi/g (wet). i Historically, Cs-137had been.detected in ten separate years since 1976. ranging from a maximum mean concentration of 0.047 pCi/g (wet) in 1985 to a minimum of 0.004 pCi/g (wet) in 1979. The trend for Cs-137 is a general reduction in concentration to non-detectable levels in samples collected during the 2001 through 2011 sample programs.

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

5.2.7 LAND USE CENSUS RESULTS A. Results Summary 3 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 2011, a milk animal census, a nearest resident census, and a garden census were performed.

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The results of the closest residence census conducted in 2011 required no change to either the

• NMP I or NMP2 ODCMs' closest resident location.

A garden census, not required by the ODCM, is performed to identify appropriate garden sampling locations and dose calculation receptors. Garden samples were collected from a number of locations listed in Table 5-1 of the NMP1 and NMP2 ODCMs and identified in the census as active for 2011. See Table 3.3-1 for 2011 sampling locations.

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

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

The number of milk animals located within an approximate 10-mile radius of the site was estimated to be 352 cows and no goats based on the 2011 land use census. The number of cows has decreased by 57, when compared to the 2010 census. The results of the milk animal census are found in Section 6.0, Table 6-13, Milk Animal Census - 2011.

The second type of census conducted is a residence census. The census is conducted in order to identify the closest residence within 5 miles in each of the 22.5 degree land-based meteorological

.sectors. There are only eight sectors over land where residences are located within 5 miles. The water sectors include: N, NNE, NE, ENE, W, WNW, NW and NNW. The results of the residence census, showing the applicable sectors and degrees and distance of each of the nearest residence, are found in Section 6.0, Table 6-14, Residence Census - 2011. There Were no changes identified in the 2011 census for the closest resident in the land based meteorological sectors. The nearest resident locations are illustrated in Section 3.3, Figure 3.3-5.

5.3 CONCLUSION

The Radiological Environmental Monitoring Program (REMP) is an ongoing program implemented to measure and document the radiological impact of NMPNS operations on the local environment. The 5-31

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

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

The Nuclear Regulatory Commission (NRC) specifies a whole body dose limit of 100 mrem/yr to be received by the maximum exposed member of the general public. This limit is set forth in Section 1301, Part 20, Title 10 of the U.S. Code of Federal Regulations (10 CFR 20). The Environmental Protection Agency (EPA) limits the annual whole bodydose 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 results of the 2011 REMP continue to clearly demonstrate that there is no significant short-term or chronic long-term radiological impact on the environment in the vicinity of the Nine Mile Point site. No unusual radiological characteristics were measured or observed in the local environment. The REMP continues to demonstrate that the effluents from the site to the environment contribute no significant or I even measurable radiation exposures to the general public as confirmed by the sampling and analysis of environmental media from recognized environmental pathways. Based on TLD results, there was no measurable increase in radiation levels beyond the site boundary as a result of the hydrogen water chemistry programs. Environmental radiation levels, measured at the. nearest residence are at the background level based on control station TLD results.,. The only measurable radiological impact on the environment continues to be the result of atmospheric weapons testing conducted in the early 1980s, the

• 1986 accident at the Chernobyl Nuclear Power Plant, and the March 11, 2011 accident at Fukushima Daiichi Nuclear Power Stations. "

The results for the 2011 sample program demonstrate that the concentrations of man-made radionuclides continue to decline. This reduction in environmental background concentrations will allow for the site environmental program to become more sensitive to the measurable impact of plant operations on the environment as time goes on.

The REMP did not detect any plant-related radionuclide in the sample media collected during 2011. 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 I 5-32

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 2011 Radiological Environmental Monitoring Program, it can be concluded that the levels and variation of radioactivity in the environment samples were consistent with background levels that would be expected for the lakeshore environment of the site.

5.4 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 Measurments (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.

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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 Measurments (NCRP), Ionizing Radiation Exposure I 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 I in the United States and Canada from National Background Radiation, NCRP Report No. 94, 1987.

15. National Council on Radiation Protection and Measurement (NCRP), Ionizing Radiation Exposure I 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.

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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 - 2011 Results in Units of pCi/kg (dry) +/- 1 Sigma Sample Location *** Collection Date GAMMA EMITTERS K-40 Co-60 Cs-134 Cs-137 Zn-65 Others t 04/25/it 22240 +/- 1124 < 106.6 < 76.0 < 75.7 < 251.5 <LLD Sunset Bay (05)

• 10/24/11 21330 +/- 1267 < 74.5 < 62.2 < 106.0 < 329.6 <LLD

- 04/25/11 12500 +/- 905 < 106.0 < 92.6 < 68.1 < 183.9 <LLD Lang's Beach (06, Control) 10/24/11 10820 +/- 722 < 48.2 < 48.7 < 49.8 < 146.9 < LLD

• Sample Location required by the ODCM Corresponds to Sample Location noted on Figure 3.3-5 t Plant related radionuclides 6-2 I I- M M M M I M M M M I

mmmmm - m m m m m m m m m m m m m TABLE 6-2 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2011 Results in Units of pCi/kg (wet) + 1 Sigma FITZPATRICK * (03)***

GAMMA EMITTERS Date Description K-40 Mn-54 Co-58 Fe-59 Co-60 Cs-134 Cs-137 Zn-65 Others t 5/10/2011 BROWNTROUT 4611 + 388 < 51 < 48 < 125 < 51 < 61 < 50 < 110 <LLD 5/10/2011 LAKETROUT 4392 +/- 379 < 41 < 46 < 85 < 42 < 40 < 41 < 112 <LLD 5/10/2011 WALLEYE 3645 +/- 406 < 42 < 42 < 147 < 62 < 43 < 54 < 113 <LLD 9/22/2011 BROWN TROUT 3032 +/- 330 < 35 < 41 < 112 < 24 < 42 < 38 < 78 <LLD 9/22/2011 SMALLMOUTH 4782 +/- 383 < 41 < 43 < 122 < 45 < 42 < 45 < 95 <LLD BASS 9/22/2011 CHINOOK SALMON 5132 +/- 458 < 54 < 44 < 121 < 53 < 47 < 33 < 108 <LLD

• Sample Location required by the ODCM

• Corresponds to Sample Location noted on Figure 3.3-5 t Plant related radionuclides 6-3

TABLE 6-2 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2011 Results in Units of pCi/kg (wet) +/- 1 Sigma NINE MILE POINT * (02)***

GAMMA EMITTERS Date Description K-40 Mn-54 Co-58 Fe-59 Co-60 Cs-134 Cs-137 Zn-65 Others t 5/10/2011 BROWNTROUT 4511 +/- 413 < 40 < 50 < 135 < 53 < 42 < 43 < 117 <LLD 5/10/2011 LAKE TROUT 3708 +/- 358 < 56 < 43 < 78 < 39 < 37 < 48 < 132 <LLD 5/10/2011 WALLEYE 5921 +/- 525 < 67 < 71 < 200 < 75 < 67 < 61 < 215 <LLD 9/22/2011 BROWNTROUT 4150 +/- 341 < 40 < 34 < 94 < 45 < 42 < 47 < 101 <LLD 9/22/2011 SMALLMOUTS BASS 4084 + 348 < 36 < 41 < 81 < 42 < 35 < 40 < 86 <LLD 9/22/2011 CHINOOK SALMON 3664 +/- 317 < 28 < 33 < 93 < 36 < 43 < 41 < 100 <LLD

• Sample Location required by the ODCM -

• ** Corresponds to Sample Location noted on Figure 3.3-5 t Plant related radionuclides 6-4

m m m - m- - m m m m - m m m TABLE 6-2 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2011 Results in Units of pCi/kg (wet) +/- 1 Sigma OSWEGO HARBOR (CONTROL) * (00)***

GAMMA EMITTERS Date Description K-40 Mn-54 Co-58 Fe-59 Co-60 Cs-134 Cs-137 Zn-65 Others t 5/10/2011 BROWN TROUT 5066 + 489 < 56 < 68 < 196 < 57 < 66 < 45 < 162 <LLD 5/10/2011 LAKETROUT 4910 +/- 454 < 59 < 43 < 140 < 52 < 43 < 51 < 129 <LLD 5/10/2011 WALLEYE 6392 +/- 463 < 50 < 46 < 111 < 54 < 50 < 47 < 123 <LLD 9/22/2011 BROWN TROUT 4242 + 369 < 30 < 40 < 80 < 41 < 42 < 37 < 107 <LLD 9/22/2011 SMALLMOUTH 5344+/- 445 < 43 < 57 < 131 < 62 < 53 < 59 < 153 <LLD BASS 9/22/2011 CHINOOK 4162 + 336 < 43 < 32 < 98 < 34 < 33 < 42 < 78 < LLD SALMON

• Sample Location required by the ODCM

• Corresponds to Sample Location noted on Figure 3.3-5 t Plant related radionuclides 6-5

TABLE 6-3 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES - 2011 (QUARTERLY COMPOSITE SAMPLES)

Results in Units of pCi/l +/- 1 Sigma STATION CODE PERIOD DATE TRITIUM First Quarter 12/28/10 04/01/11 < 410 FITZPATRICK* Second Quarter 04/01/11 06/28/11 < 432 (03, INLET)*** Third Quarter 06/28/11 09/26/11 < 420 Fourth Quarter 09/26/11 12/28/11 < 413 First Quarter 12/27/10 04/01/11 < 417 OSWEGO STEAM STATION* Second Quarter 04/01/11 07/01/11 < 432 (08, CONTROL)*** Third Quarter 07/01/11 .09/29/11 < 412 Fourth Quarter 09/29/11 12/30/11 < 413 First Quarter 12/27/10 04/01/11 < 417 NINE MILE POINT UNIT 1* Second Quarter. 04/01/li 07/01/11 . < 432 (09, INLET)*** Third Quarter 07/01/11 09/29/11 < 412 Fourth Quarter 09/29/11 12/30/11 < 413 First Quarter 12/27/10 04/01/11 < 417 NINE MILE POINT UNIT 2** Second Quarter 04/01/11 07/01/11 < 432 (11, INLET)*** Third Quarter 07/01/11 09/29/11 < 412 Fourth Quarter 09/29/11 12/30/11 < 413 First Quarter 12/27/10 04/01/11 < 417 OSWEGO CITY WATER** Second Quarter 04/01/11 07/01/11 < 432 (10)*** Third Quarter 07/01/11 09/29/11 < 412 Fourth Quarter 09/29/11 12/30/11 < 450.

• Sample Location required by ODCM

• • Optional Sample Location

• • • Corresponds to Sample Location noted on Figure 3.3-4 6-6 m M Mm M M - M M M m M M M M M

m - m m mI m m m - m m m - m M M M TABLE 6-4 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2011 Results in Units of pCi/liter +/- 1 Sigma OSWEGO STEAM STATION * (08, CONTROL)***

Date 1/28/2011 2/25/2011 4/1/2011 4/29/2011 6/3/2011 7/1/2011 NUCLIDE 1-131 < 0.91 < 0.97 < 0.66 < 0.80 < 0.60 < 0.71 Cs-134 < 2.46 < 3.33 < 1.71 < -3.02 < 2.52 < 2.93 Cs-137 < 3.12 < 3.29 < 2.73 < 2.83 < 2.54 < 2.82 Zr-95 < 6.75 < 5.51 < 5.49 < 6.07 < 4.78 < 4.93 Nb-95 < 4.53 < 4.08 < 3.93 < 3.47 < 3.47 < 3.58 Co-58 < 3.28 < 3.22 < 2.68 < 3.64 < 3.09 < 2.83 Mn-54 < 2.99 < 2.74 < '2.53 < 3.09 < 2.43 < 2.54 Fe-59 < 10.45 < 11.95 < 10.21 < 9.18 < 9.61 < 9.65 Zn-65 < 7.73 < 8.52 < 3.38 < 6.99 < 2.98 < 7.11 Co-60 < 3.06 < 3.50 < 2.84 < 3.19 < 2.70 < 2.35 K-40 25.24 +/- 11.80 176 +/- 18.11 242.1. +/- 15.91 225.1 +/- 18.66 161.9 :E 14.59 82.86 +/- 11.82 Ba/La-140 < 11.49 < 9.46 < 8.82 < 9.90 < 7.35 < 8.62 Date 7/28/2011 9/2/2011 9/29/2011 10/28/2011 12/2/2011 12/30/2011 NUCLIDE 1-131 < 0.75 < 0.63 < 0.46 < 0.91 < 0.81 < 0.88 Cs-134 < 1.81 < 2.62 < 2.50 < 2.19 < 2.13 < 1.72 Cs-137 < 2.64 < 2.21 < 2.63 < 3.31 < 2.99 < 2.74 Zr-95 < 5.11 < 4.37 < 4.98 < 6.97 < 5.24 < 5.73 Nb-95 < 4.03 < 2.88 < 3.41 < 4.26 < 3.47 < 3.90 Co-58 < 3.03 < 2.50 < 2.47 < 3.79 < 3.39 < 3.22 Mn-54 < 2.43 < 2.42 < 2.38 < 3.48 < 2.98 < 2.93 Fe-59 < 8.52 < 8.60 < 8.00 < 10.49 < 7.74 < 8.05 Zn-65 < 3.34 < 5.17 < 6.27 < 5.24 < 6.02 < 6.42 Co-60 < 2.54 < 2.55 < 2.84 < 4.18 <.2.58 < 2.73 K-40 179.5 + 15.22 81.52 + 11.04 174.4 + 14.70 226.3 +/- 21.32 166.5 +/- 15.69 193.9 +/- 14.88 Ba/La-140 < 7.15 < 7.17 < 7.06 < 10.70 < 8.26 < 7.19

• Sample Location required by ODCM Corresponds to Sample Location noted on Figure 3.3-4 6-7

TABLE 6-4 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2011 Results in Units of pCi/liter + 1 Sigma OSWEGO CITY WATER** (10)***

Date 1/28/2011 2/25/2011 4/1/2011 4/29/2011 6/3/2011 7/1/2011 NUCLIDE 1-131 < 12.29 < 12.67 < 10.13 < 12.18 < 9.35 < 12.97 Cs-134 < 2.06 < 2.65 < 2.96 < 2.34 < 1.39 < 2.33 Cs-137 < 2.45 < 2.82 < 2.78 < 3.31 < 2.09 < 3.23 Zr-95 < 5.60 < 5.49 < 5.44 < 6.18 < 3.94 < 5.30 Nb-95 < 3.54 < 3.72 < 3.95 < 4.20 < 2.78 < 3.63 Co-58 < 2.80 < 2.68 < 2.92 < 4.33 < 2.18 < 3.56 Mn-54 < 2.70 < 2.89 < 2.77 < 3.28 < 1.85 < 2.71 Fe-59 < 8.67 < 8.88 < 7.28 < 12.13 < 5.80 < 9.36 Zn-65 < 7.10 < 6.76 < 6.59 < 4.84 < 4.49 < 7.21 Co-60 < 2.35 < 3.02 < 2.91 < 3.55 < 1.80 < 3.08 K-40 107.9 +/- 13.19 51.5 +/- 11.52 195.2 +/- 15.15 254.3 +/- 20.86 17.71 +/- 7.39 32.32 +/-11.70 Ba/La-140 < 8.29 < 7.06 < 7.73 < 9.86 < 6.10 < 9.97 Date 7/28/2011 9/2/201.1 9/29/2011 10/28/2011 12/2/2011 12/30/2011 NUCLIDE 1-131 < 10.73 < 10.92 < 9.82 < 10.02 < 13.73 < 13.91 Cs-134 < 1.69 < 2.02 < 3.59 < 1.90 < 2.41 < 2.35 Cs-137 < 2.38 < 2.32 < 3.01 < 2.70 < 3.50 < 3.74 Zr-95 < 3.97 < 4.62 < 5.15 < 5.37 < 6.98 < 7.41 Nb-95 < 3.29 < 3.44 < 3.80 < 3.41 < 4.85 < 5.32 Co-58 < 2.71 < 2.82 < 2.82 < 3.35 < 4.09 < 4.77 Mn-54 < 2.26 < 2.54 < 3.06 < 3.01 < 3.82 < 3.50 Fe-59 < 8.28 < 8.05 < 7.80 < 8.45 < 12.94 < 14.47 Zn-65 < 5.10 < 5.6.1 < 6.68 < 6.78 < 8.43 < 9.10 Co-60 < 2.23 < 2.47 < 3.36 < 2.68 < 4.18 < 4.45 K-40 46.14 +/- 7.85 40.27 +/- 11.22 50.08 +/- 11.24 182.7 + 14.64 236.8 +/- 21.38 287.9 +/- 22.99 Ba/La-140 < 7.24 < 9.81 < 9.14 < 7.19 < 12.29 < 12.62

• • Optional Sample Location -

• • • Corresponds to Sample Location noted on Figure 3.3-4 6-8 m- M M - M m m M m M Mm m m - m M m

TABLE 6-4 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2011 Results in Units of pCi/liter +/- 1 Sigma FITZPATRICK* (03, INLET)***

Date 1/31/2011 3/1/2011 4/1/2011 5/2/2011 6/1/2011 6/28/2011 NUCLIDE 1-131 < 0.42 < 0.55 < 0.46 < 0.46 < 0.60 < 0.62 Cs-134 < 2.42 < 1.81, < 2.56 < 1.60 < 3.94 < 2.78 Cs-137 < 2.80 < 2.53 < 3.80 < 2.10 < 3.45 < 2.12 Zr-95 < 5.95 < 4.33 < 7.82 < 3.72 < 6.88 < 4.59 Nb-95 < 4.47 < 3.45 < 4.74 < 2.70 < 4.86 < 3.03, Co-58 < 3.47 < 2.80 < 4.52 < 2.38 < 3.89 < 2.56 Mn-54 < 3.11 < 2.64 < 3.83 < 2.61 < 4.09 < 2.39 Fe-59 < 10.18 < 7.86 < 13.08 < 5.81 < 12.68 < 7.34 Zn-65 < 8.33 < 6.75 < 6.40 < 4.91 < 9.57 < 5.97 Co-60 < 3.06 < 2.75 < 3.72 < 1.91 < 3.72 < 2.89 K-40 110.9 +/- 16.82 < 27.16 < 43.43 < 24.52 < 44.75 47.1 +/- 12.27 Ba/La-140 < 8.01 < 6.66 < 11.18 < 6.06 < 6.33 < 5.31 Date 8/1/2011 8/30/2011 9/26/2011 , 10/31/2011 12/1/2011 12/28/2011 NUCLIDE 1-131 < 0.45 < 0.53 < 0.55 < 0.67 < 0.47 < 0.62 Cs-134 < 6.19 < 2.61 < 5.18 < 2.17 < 2.01 < 4.38 Cs-137 < 4.89 < 4.47 < 4.66 < 2.90 < 2.75 < 3.61 Zr-95 < 10.08 < 7.37 < 8.54 < 5 53 < 5.29 < 6.13 Nb-95 < 5.94 < 4.58 < 6.73 < 4.05. < 3.23 < 4.68 Co-58 < 5.77 < 4.11 < 4.40 < 2.62 < 3.14 < 4.71 Mn-54 < 5.28 < 3.46 < 5.20 < 2.89 < 2.84 < 3.90 Fe-59 < 19.62 < 10.83 < 17A48 < 7.77 < 8.02 < 11.01 Zn-65 < 12.26 < 9.94 < 11.73 < 3.19 < 6.23 < 9.78 Co-60 < 5.49 < 4.25 < 5.82 < 3.14 < 2.97 < 4.64 K-40 332.1 -+/- 31.69 < 43.41 174 +/- -24.52 26.96 .- 8.45 37.76 +/- 11.05 < 49.65 Ba/La-140 < 14.42 < 11.69 < 11.42 < 7.07 < 7.41 < 8.10

• Sample Location required by ODCM

• Corresponds to Sample Location noted on Figure 3.3-4.

6-9

TABLE 6-4 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2011 Results in Units of pCi/liter +/- 1 Sigma NINE MILE POINT UNIT 1 ** (09, INLET)***

Date 1/28/2011 2/25/2011 4/1/2011 4/29/2011 6/3/2011 7/1/2011 NUCLIDE 1-131 < 13.57 < 12.91 < 11.75 < 7.32 < 11.13 < 13.10 Cs-134 < 1.96 < 4.43 < .3.28 < 1.45 < 3.25 < 1.97 Cs-137 < 2.67 < 3.06 < 3.19 < 1.83 < 3.05 < 2.83 Zr-95 < 5.99 < 6.96 < 6.58 < 3.85 < 5.32 < 5.93 Nb-95 < 4.27 < 4.63 < 4.13 < 2.51 < 3.47 < 4.13 Co-58 < 2.77 < 4.48 < 3.30 < 1.92 < 3.53 < 3.61 Mn-54 < 2.69 < 3.78 < 3.19 < 2.03 < 2.97 < 3.06 Fe-59 < 9.48 < 11.00 < 8.93 < 5.41 < 10.47 < 10.30 Zn-65 < 6.89 < 8.38 < 6.61 < 4.50 < 7.10 < 7.13 Co-60 < 2.81 < 4.00 < 3.36 < 1.90 < 2.67 < 2.79 K-40 45.94 + 10.77 < 39.11 68.96 +/- 14.11 39.86 +/- 7.82 47.79 +/- 14.77 2086 +/- 17.21 Ba/La-140 < 8.71 < 12.67 < 11.71 < 5.60 < 10.75 < 10.60 Date 7/28/2011 9/2/2011, 9/29/2011 10/28/2011 12/2/2011 12/30/2011 NUCLIDE 1-131 < 12.48 < 8.98 < 9:73 < 10.48 < 11.37 < 10.30 Cs-134 < 1.97 < :1.35 < .3.12 < 2.22 < 2.53 < 2.05 Cs-137 < 2.81 < 1.98 < 2.63 < 2.71 < 2.57 < 2.57 Zr-95 < 6.43 < 3.49 < 5.47 < 5.16 < 7.53 < 5.20 Nb-95 < 4.04 < 2.75 < 3.38 < 3.44 < 4.63 < 3.62 Co-58 < 2.80 < 2.33 < 1305 < 3.51 < 3.70 < 2.62 Mn-54 < 3.22 11.91 < 2.87 < 2.84 < 2.46 < 2.41 Fe-59 < 9.46 , 5.91 < 8.55 < 10.75 < 10.18 < 7.62 Zn-65 < 6.98 < 4.32 < 6:07 < 7.59 < 7.06 < 6.53 Co-60 < 2.49 < 1.87 < 2.23 < 2.93 < 3.40 < 2.95 K-40 121.2 +/- 15.04 < 20.07 160.6 : 15.57 36.35 +/- 13.29 34.35 +/- 13.07 130.1 +/- 14.19 Ba/La-140 < 10.17 < 6.39 < 7.90 < 7.33 < 11.05 < 7.28

• • Optional Sample Location Corresponds to Sample Location noted on Figure 3.3-4 6-10

- mýM -, m -, -ý -m mm m m MM-

=1 M =1 M M M M M M M M M M M M M TABLE 6-4 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2011 Results in Units of pCi/liter + 1 Sigma NINE MILE POINT UNIT 2 ** (11, INLET)***

Date 1/28/2011 2/25/2011 4/1/2011 4/29/2011 6/3/2011 7/1/2011 NUCLIDE 1-131 < 12.51 < 11.01 < 14.65 < 9.31 < 13.73 < 10.17 Cs-134 < 1.55 < 3.38 < 2.22 < 2.84 < 2.35 < 1.66 Cs-137 < 2.27 < 3.35 < 3.02. < 2.44 < 3.46 < 2,23 Zr-95 < 4.34 < 7.03 < 5.69 < 5.04 < 6.80 < 4.65 Nb-95 < 3.20 < 3.98 < 3.93 < 3.29 < 4.65 < 2.77 Co-58 < 2.51. < 3.15 < 3.68 < 2.75 < 4.51 < 1.97 Mn-54 < 2.15 < 3.68 < 3.11 < 2.34 < 3.53 < 2.17 Fe-59 ,< 6.81 < 8.89 < 10.96 < 6.94 < 12.30 < 7.34 Zn-65 < 5.02 < 8.12 < 6.89 < 5.09 < 8.65 < 4.74 Co-60 < 2.35 < 3.30 < 3.11 < 2.53 < 3.09 < 2.61 K-40 46.5 +/- 8.13 67.7 +/- 15.68 261.7 +/- 19.50 < 21.59 200.1 +/- 20.78 36.3 + 8.68 Ba/La-140 < 8.37 < 9.76 < 9.27 < 6.75 < 11.10 < 7.39 Date 7/28/201.1 9/2/2011 9/29/2011 10/28/2011 12/2/2011 12/30/2011 NUCLIDE 1-131 < 14.-78 < 8.00 < 11.78 < 13.44 < 9.56 < 14.51 Cs-134 < 2.41 < 2.41 < 3.53 < 2.48 < 1.65 < 4.12 Cs-137 < 2.03 < 2'02 < 3.59 < 3.48 < 2.10 < 3.34 Zr-95 < 4.65 < 4.54 < 6.24 < 8.24 < 4.44 < 6.82 Nb-95 < 2.90 < 3.29 < 4.52 < 4.82 < 3.29 < 4.90 Co-58 < 2.45 <. 2.53 < 3.48 < 4.32 < 2.60 < 4.25 Mn-54 < 2.08 < 2.16 < 3.36 < 3.50 < 2.48 < 4.08 Fe-59 < 8.04 < 8.02 < 12.75 < 14.70 < 7.43 < 11.86 Zn-65 < 5.41 < 4.84 < 8.11 < 8.90 < 4.88 < 8.91 Co-60 < 2.21 < 2.41 < 3.97 < 4.31 < 2.50 < 3.90 K-40 46.47 +/- 9.01 174.4 +/- 12.88 206.8 +/- 21.13 225.2 +/- 20.99 30.56 +/- 9.21 204.2 +/- 20.16 Ba/La-140 < 9.83 < 5.66 < 10.32 < 11.94 < 6.91 < 10.83

• • Optional Sample Location Corresponds to Sample Location noted on Figure 3.3-4 6-11

TABLE 6-5 ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFF-SITE SAMPLE LOCATIONS - 2011 GROSS BETA ACTIVITY pCi/ m3 . 1 Sigma.

WeekEnd R-1

• R-2

• R-3

• R-4-* R-5

• D-2 ** E** F **G Date 01/04/11 0.027 +/- 0.002 0.022 +/- 0.001 0.023 +/- 0.002 0.023 +/- 0.002 0.024 +/- 0.002 0.025 +/- 0.002 0.025 +/- 0.002 0.023 + 0.002 0.022 0.002 01/11/11 0.021 - 0.001 0.021+ 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.022 0.001 0.022 + 0.001 0.018 4 0.001 0.017 +/- 0.001 0.017 4 0.001 01/18/11 0.014 +/- 0.001 0.012 +/- 0.001 0.011 - 0.001 0.012 +/- 0.001 0.012 0.001 0.009 +/- 0.001 0.013 + 0.001 0.011 + 0.001 0.013 +/- 0.001 01/25/11 0.021 +/- 0.001 0.019 +/- 0.001 0.02 1 0.001 0.018 +/- 0.001 0.019 +/- 0.001 0.020 +/- 0.001 0U022 +/- 0.002 0.017 + 0.001 0.022 +/- 0.002 02/01/11 0.023 +/- 0.002 0.023 +/- 0.002. 0.021 + 0.002 0.021 *+/- 0.002 0.020 + 0.001 0.023 +/- 0.002 0.020 +/- 0.002 0.023 +/- 0.002 0.023 +/- 0.002 02/08/11 0.021 +/- 0.001 0.018 + 0.001 0.018 +/- 0.001 .0.021 +/- 0.001 0.023 +/- 0.001 0.019 +/- 0.001 0.025 + 0.002 0.019 +/- 0.001 .0.021 + 0.001 02/15/11 0.022 +/- 0.002 .0.017 + 0.001 0.018 *+/- 0.001 0.019 +/- 0.001 0.021 +/- 0.001 0.021 +/- 0.001 0.021 +/- 0.001 0.018 +/- 0.001 0.018 - 0.001 02/22/11 0.023 +/- 0.002 0.020 +/- 0.001 0.021 +/- 0.001 0.020 +/- 0.001 0.019 +/- 0.001 0.017 +/- 0.001 0.021 ,- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 03/01/11 0.019 +/- 0.001 0.019 +/- 0.001 0.019 +/- 0.001. 0.018 + 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.020 - 0.001 0.020 +/- 0.001 0.018 - 0.001 03/08/11 0.019 +/- 0.001 0.017 +/- 0.001 0.018 - 0.001 0.015 +/- 0.001 0.017 +/- 0.001 0.021 +/- 0.001 0.018 - 0.001 0.021 +/- 0.001 0.019 - 0.001 03/15/11 0.014 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001, 0.016 +/- 0.001 0.014 +/- 0.001 0.018 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001. 0.014 - 0.001 03/22/11 0.024 +/- 0.002 0.021 +/- 0.001 0.015 - 0.001 0.017 +/- 0.001 0.020 - 0.001 0.019 .+/- 0.001- 0.020 - .0.001 0.018 +/- 0.001. 0.017 +/- .0.001 03/29/11 0.030 +/- 0.002 0.028 +/- 0.002 0.027 +/- 0.002 0.028 +/- 0.002 0.029 +/- 0.002 0.030 +/- 0.002 0.028 +/- 0.002 0.030 +/- 0.002 0.030 - 0.002 04/05/11 0.033 +/- 0.002 0.032 +/- 0.002 0.034 +/- 0.002 0.033 +/- 0.002 0.030 +/- 0.002 0.035 +/- 0.002 0.030 +/- 0.002 -0.030 +/- 0.002 0.039 - 0.002 04/12/11 0.023 +/- 0.002 0.020 +/- 0.001 0.023 +/- 0.002 0.024 +/- 0.002 0.023 + 0.002 0.025 +/- 0.002 0.024 +/- 0.002 0.022 +/- 0.002 0.022 +/- 0.002 04/19/11 0.022 +/- 0.001 0.025 +/- 0.002 0.022 +/- 0.002, 0.024 +/- 0.002 0.019 +/- 0.001 .0.023 +/- 0.002 0.022 +/- 0.002 0.021 +/- 0.001 0.020 - 0.001 04/26/11 0.015 +/- 0.001 0.013 - 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.014 +/- .0.001 0.011 +/- 0.001 0.013 - 0.001 05/03/11 0.011 +/- 0.001 0.011 + 0.001 0.008 +/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.055 +/- 0.002 0.012 - 0.001ý 05/10/11 0.014 +/- 0.001 0.015 +/- 0.001 0.010 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.008 +/- 0.001 0.012 - 0.001 05/17/11 0.007 +/- 0.001 0.007 + 0.001 0.008 +/- 0.001 0.008 +/- 0.001 0.008 4 0.001 0.007 +/- 0.001 0.007 4 0.001 0.008 +/- 0.001 0.006 09.001 05/24/11 0.009 +/- 0.001 0.007 +/- 0.001 0.009 A0.001 0.009 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.010 + 0.001 0.011 +/- 0.001 0.008 - 0.001 06/01/11 0.011 +/- 0.001 0.010 +/- .0.001 0.013  : 0.001 0.014 +0.001 0.0147+ 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.015 +/- 0.001 06/07/11 0.019 +/- 0.001 0.018 + 0.001 0.021 - 0.002. 0.020 - 0.002 0.018 - 0.001 -0.019 +/- 0.002 0.022 +/- 0.002 0.016 +/- 0.001 0.021 +/- 0.002 06/14/11 0.017 +/- 0.001 0.015 +/- 0.001 0.015 - 0.001 0.016 -4.0.001 0.010 +-0.001 0.016 +/-- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.017 +- 0.001 06/21/11 0.011 +/- 0.001 0.012 +/- 0.001 0.013 + 0.001 0.014 - 0.001 0.015 - 0.002 0.014 +/- 0.001 0.012 +/- 0.001 0.011 - 0.001 0.015 - 0.001 06/28/11 0.009 +/- 0.001 0.010 + 0.001 0.008 +/- 0.001 0.009 - 0.001 0.008 - 0.001 0.009 +/- 0.001 0.011 - 0.001 0.010 +/- 0.001 0.008 - 0.001

• Sample Location required by ODCM

• • Optional Sample Location 6-12

- l- - - - - M M M M M M M M M M M M

m---- -mm m-- mm m --m --- - m -

TABLE 6-5 (Continued)

ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFF-SITE SAMPLE LOCATIONS - 2011 GROSS BETA ACTIVITY pCi/ m3 +/- 1 Sigma WeekEnd R-* R-2* R-3* R-4* R-5* D-2** E** F** G**

Date 07/06/11 0.013 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.014 +/- 0.001 0.014 + 0.001 0.013 +/- 0.001 07/12/11 0.019 +/- 0.002 0.020 +/- 0.002 0.017 +/- 0.001 0.015 1 0.001 0.015 +/- 0.001 0.018 +/- 0.001 0.017 +/- 0.001 0.018 +/- 0.001 0.020 +/- 0.002 07/19/11 0.018 - 0.001 0.017 - 0.001 0.021 - 0.002 0.015. +/-- 0.001 0.016 +/- 0.001 .0.016 0.001 0.016 - 0.001 0.016 - 0.001 0.018 - 0.001 07/26/11 0.019 +/- 0.001 0.018 +/- 0.001 0.017 - 0.001 0;019 +/- 0.001 0.019 +/- 0.001 0.018 +/-:0.001 0.019. +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 08/02/11 0.015 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.014 - 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.019 +/- 0.001 08/09/11 0.013 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.013 +/--0.001 0.017 - 0.001 0.014 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 08/16/11 0.013 +/- 0.001 0.016 +/- 0.001 0.016 - 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.014 - 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.014 +/- 0.001 08/23/11 0.024 +/- 0.002 0.023 +/- 0.001 0.022 + 0.001 0.023 +/-' 0.001 0.022 +/- 0.001 0.019 - 0.001 0.019 +/- 0.001 0.022 +/- 0.001 0.019 +/- 0.001 08/30/11 0.012 +/- 0.001 0.011 +/- 0.001 0.014 - 0.001 0.012 - 0.001 0.013 +/- 0.001 0.013 - 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.015 + 0.001 09/07/11 0.026 +/- 0.001 0.024 +/- 0.001 0.025 - 0.001 0.024 4 0.001 0.025 +/- 0.001 0.025 +/--0.001 0.024 +/- 0.001 0.024 +/- 0.001 0.025 - 0.001 09/13/11 0.015 +/- 0.001 0.012 +/- 0.001 0.016 +/- 0.001 0.015 - 0.001 0.017. +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001. 0.018 +/- 0.001 0.018 +/- 0.001 09/20/11 0.011 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.012 - 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.012 +/-- 0.001 0.009 +/- 0.001 0.013 +/- 0.001 09/27/11 0.020 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001. 0.020 - 0.001 0.017 +/- 0.001 0.015 +/- 0.001 .0.017 +/- 0.001 0.019 +/- 0.001 0.022 +/- 0.002 10/04/11 0.014 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001' 0.009. +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.009- +/- 0.001 0.011 +/- 0.001.

10/11/11 0.030 +/- 0.002 0.032 +/- 0.002 0.032 +/-- 0.002 0.028 +/- 0.002 0.034 +/- 0.002 0.030 +/- 0+/-002 0.030 +/- 0.002 0.028 :L 0.002 0.030 +/- 0.002 10/18/11 0.015 +/- 0.001 0.016 +/- 0.00.1 0.014 *- 0.001 0.017 +/- 0.001 0.018 - 0.002 0.017 +/- 0.001 0.020 +/- 0.001 0.015. +/- 0.001 0.022 +/- 0.001 10/25/11 0.014 +/- 0.001 0.011 +/- 0.001 0.011 -. 0.001 0.012 +/- 0.001 0.012 - 0.001 0.012 +/- 0.001 0.011 +/-- 0.00.1 0.012 +/- 0.001 0.013 +/- 0.001 11/01/11 0.014 +/- 0.001 0.012 1: 0.001 0.016 - 0.001 0.013 +/- 0.001 0.016 + 0.001 .0.014 +/- 0.001 0.013 +/- 0.001 0.012 +/--0.001 0.016 +/- 0.001 11/08/11 0.019 +/- 0. 001 0.021 +/- 0.001 0.022 - 0.001 0.021 +/- 0.001 0.024 +/- 0.002 0.021 +/- 0.001 0.021 +/- 0.001 0.022 +/-- 0.002 0.024 +/- 0.002 11/15/11 0.026 +/- 0.002 0.026 +/- 0.002 0.027 +/- 0.002 0.026 +/- 0.002 0.029 - 0.002 0.024 +/- 0.002 0.027 +/- 0.002 0.027 +/- 0.002 0.028 +/- 0.002 11/22/11 0.018 +/- 0.001 0.01.9 +/- 0.001 0.020 +/- 0.001 '0.019 +/- 0.001 0.024'+/- 0.002 0.020 +/- 0.001 0.019 +/- 0.001 0.019 +/- 0.001 0.021 +/- 0.002 11/30/11 0.016 +/- 0.001 0.018 +/- 0.001 0.019 +/- 0.001 0.019 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001.

12/06/11 0.018 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001 0.016 +/- 0.001. 0.017 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.017 +/- 0.001 12/13/11 0.023 +/- 0.002 0.021 +/- 0.001 0.022 +/- 0.002 .0.021 +/- 0.001 0.024 -. 0.002 -0.020 +/- 0.001 0.020 +/- 0.001 0.021. +/- 0.001 0.025 +/- 0.002 12/20/11 0.028 +/- 0.002 0.027 +/- 0.002 0.027 +/- 0.002 0.025 +/- 0.002 0.031 - 0.002 0.027 +/- 0.002 0.028 +/- 0.002 0.028 +/- 0.002 0.032 +/- 0.002 12/28/11 0.017 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.015 - 0.001 0.015 - 0.001 0.014 +/- 0.001 0.018 +/- 0.001 0.014 +/- 0.001

• Sample Location required by ODCM

• • Optional Sample Location 6-13

TABLE 6-6 ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ON-SITE SAMPLE LOCATIONS - 2011 GROSS BETA ACTIVITY pCi/ m 3 1 1 Sigma WeekEnd D-1** G ** H** *J** K**

Date 01/03/11 0.022 +/- 0.001 0.018 - 0.001. 0.023 4 0.001 0.019 - 0.001 0.022 +/- 0.002 0.019 +- 0.001 01/10/11 0.023 +/- 0.001 0.022. 0.001 0.019 +/- 0.001 0.019  :. 0.001 0.019 +/- 0.001 0.022 +/- 0.001 01/17/11 0.013 +/- 0.001 0.012 - 0.001 0.013 - 0.001 0.012 - 0.001 0.008 +/-. 0.001 0.013 - 0.001 01/24/11 0.017 - 0.001 0.017 +/- 0.001 '0.018 +/- 0.001 0.019 +/- 0.001 0.018 - 0.001 0.020 +/- 0.001 01/31/11 0.021 - 0.001 0.021 - 0.001 0:023 - 0.002 0.025 - 0.002 0.020 - 0.001 0.020 +/- 0.001 02/07/11 0.022 - 0.001 .0.019 +/- 0.001 0.021 - 0.001 0.021 +/- 0.001 0.018 '0.001 0.020 - 0.001 02/14/11 0.020 +-, 0.001 0.021 +/- 0.001 0"019 +/- 0.001 0.019 +/- 0.001 0.021 +- 0.001 0.019 +- 0.001 02/21/11 0.020 +/- 0.001 0.016 '0.001 0.019 - 0.001 0.017 +/- 0.001 0.018 4- 0.001 0.017 +/- 0.001 02/28/11 0.017 - 01001 0.017 +/- 0.001 0.018 +/- 0.001 0.020 +/- 0.001 0.020 - 0.001 0.018 4 0.001 03/07/11 0.020 +/- 0.001 0.016 +/- 0.001 0.020 +/- 0.001 0.018. +/- 0.001 0.016 0.001 6 0.017 - 0.001 03/14/11 0.015..4- 0.001 0.014 +/- 0.001 (3.0.14 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.011 - 0.,001 03/21/11 0.020 - 0.001 0.019 +/- 0.001 01020 +/- 0.00.1 0.020 +/- 0.001 0.021 0.002 W 0.020 +. 0.001 03/28/11 0.027 - 01002 0.023 - 0.002 P.025 +/- 0.002 0..024 +/- 0.002 0.026 +- 0.002 0.025 - 0.002 04/04/11 0.036. 0.002 0:041 - 0.002. 0.032 +/- !0.002 0.038 .+ 0.002 0.035 +/- 0.002 0.033 - 0.002 04/11/11 0.021  : 0.001 0.024 - 0.002 0.024 +/- 0.002 0.022 - 0.002 0.023 +/- 0.002 0.021 - 0.001 04/18/11 0.021 - 0.001 0.019 +/- 0.001 0.021 - 0.002 0.021 +/- 0.002 0.019 - 0.001 0.018 - 0.001 04/25/11 0.013 - 0.001 0.014 - 0.001. 0.014 - 0.001 0.017 - 0.001 0.015 - 0.001 0.016 - 0.001 05/02/11 0.010 - 0.001 0.011! - 0.001 0.010 +/- .0.001 0.012 +/- 0.001 0.010 - 0.001 0.009 - 0.001 05/09/11 0.013 + 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.010 +/- 0.001 0.011 - 0.001 0.014 +/- 0.001 05/16/11 0.009 - 0.001 0.011 .+ 0.001 0.008 +/- .0.001 0.008 +/- 0.001 0.009 +/- 0.001 0.007 +/- 0.001 05/23/11 0.006  :- 0.001 0.008 +/- 0.001 0.006 - 0.001 0.008 - 0.001 0.007 - 0.001 0.007 +/- 0.001 05/31/11 0.009 +/- 0.001 0.012 - 0.001 .0.010. +/- 0.001 0.008 +/-- 0.001 01010 - 0.001 0.009 +/- 0.001 06/06/11 0.020 + 0.001 0.021 +/- 0.002 0.016 +/- 0.001 0.021 +/- 0.002 0.021 +/- 0.002 0.021 + 0.002 06/13/11 0.021 +/- 0.001 0.015 - 0.001 0.021 - 0.001 0.019 +/- 0.001 0.018 +/- 0.001 0.017 - 0.001 06/20/11 0.013 +/- 0.001 0.011 - 0.001 0.013 - 0.001 0.013 - 0.001 0.014 +/- 0.001 0.012 - 0.001 06/27/11 0.007 +/- 0.001 0.009 +/- 0.001 0.010 - 0.001 0.010 - 0.001 0.010 - 0.001 0.009 +/- 0.001

• • Optional Sample Location 6-14 1 i a m m M M M m M M mM l M M M M M

m mm mm Immm/mmmmmm m m TABLE 6-6 (Continued)

ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ON-SITE SAMPLE LOCATIONS - 2011 GROSS BETA ACTIVITY pCi/m 3 +/- 1 Sigma WeekEnd D-1** G** H** J** K**

Date*

07/05/11 0.015 +/- 0.001 0.011 .- 0.001 0.013 - 0.001- 0.013 - 0.001 0.015 - 0.001 0.013 z- 0.001 07/11/11 0.017 +/- 0.001 0.012 +/- 0.001 0.018 + 0.001 0.015 0.001 6 0.013 +/- 0.001 0.018 +/- 0.001 07/18/11 0.019 +/- 0.001 0.017 +/- 0.001 0.020 - 0.001 0.018 +/- 0.001 0.018 +/- 0.001 0.019 +/- 0.001 07/25/11 0.021 +/- 0.002 0.019 +/- 0.001 0.021 - 0.001 0.01.8 0.001 0.022 +/- 0.002 0.018 +/- 0.001 08/01/11 0.013 +/- 0.001 0.014 +/- 0.001 0.016 - 0.001 0.017 +- 0.001 0.015 - 0.001 0.016 +/- 0.001 08/08/11 0.017 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.015 + 0.001 0.018 +/- 0.001 08/15/11 0.019 +/-- 0.001 0.0.16 +/- 0.001 0.018 -: 0.001 0.015 +- .0.001 0.014 +/- 0.001 0.015 +/- 0.001 08/22/11 0.020 +/- 0.001 0.023 +/- 0.002 0.023 - 0.001 0.021 +/- 0.001 0.021 +/- 0.001 0.023 - 0.002 08/28/11 0.013 - 0.001 0.012 + 0.001 0'016 +/- 0.001 0.015 - 0.001 0.012 +/- 0.001 0.014 +/- 0.001 09/06/11 0.026 +/- 0.001 0.025 - 0.001 0.026 - 0.001 0.023 - 0.001 0.024 - 0.001 0.021 - 0.001 09/12/11 0.010 +/- 0.001 0.014 - 0.001 0.011 - 0.001 0.011 +- 0.001 0.011 +/-- 0.001 0.010 - 0.001 09/19/11 0.013 +/- 0.001 0.016 - 0.001 0.015 - 0.001 0.015 +/- 0.001 0.014 +/-- 0001 0.012 - 0.001 09/26/11 0.017 - 0.001 0.019 + 0.001 0.017 +/- 0.001 0.017 +- 0.001 0.016 - 0.001 0.017 +/- 0.001 10/03/11 01015 +/- 0.001 0.014 - 0.001 0.013' +/- 0.001 0.016 - 0.001,. 0.015 +/- 0.001 0.015 +/- 0.001 10/10/11 0.022 +/- 0.001 0.021 - 0.001 0.024 - 0.002 0.026 - 0.002 0.024 - 0.002 0.025 - 0.002 10/17/11 0.024 +/- 0.002 0.019 + 0.001 0.023 +/- 0.002 0.025 - 0.002 0.024 - 0.002 0.020 +/- 0.001 10/24/11 0.015 +/- 0.001 0.014 - 0.001 0.008 -- 00 1L 0.008 0.001 0.007 - 0.001 0.0122 0.001 10/31/11 0.011 - 0.001 0.013  :- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.016 +/- 0.001 11/07/11 0.022 - 0.001 0.018 - 0.001' 0.020 +/- 0.001 0.019 - 0.001 0.019 - 0.001 0.020 - 0.001 11/14/11 0.026 - 0.002 0.031 - 0.002 0.029 - 0.002 0.023 LL 0.002 0.027 - 0.002 0.027 +/- 0.002 11/21/11 0.022 +/- 0.001 0.023 - 0.002.. 0.023 - 0.002 0.022 +/- 0.001 0.022 - 0.001 0.023 - 0.002 11/28/11 0.019 +/- 0.001 0.019 L 0.001. 0.018 - 0.001 0.017 +/- 0.001 m0.020 - 0.001 0.018 +- 0.001 12/05/11 0.016 +/- 0.001 0.017 - 0.001 0.016 +/- 0.001 0.017 - 0.001 0.014 - 0.001 0.013 - 0.001 12/12/11 0.021 +/- 0.001 0.019 - 0.001 0.021 - 0.001 0.022 +/- 0.002 0.020 +/- 0.001 0.023 - 0.002 12/19/11 0.028 +/- 0.002 0.029 - 0.002 0.028 +/- 0.002 0.028 - 0.002 0.027 - 0.002 0.024 +/- 0.002 12/27/11 0.021 - 0.001 0.019 - 0.001 0.019 - 0.001 0.020 - 0.001 0.018 - 0.001 0.021 +/-- 0.001

• • Optional Sample Location 6-15

TABLE 6-7 ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFF-SITE SAMPLE LOCATIONS - 2011 1-131 ACTIVITY nCi/ m3 + 1 Skima ____ ___

Week End R-1

• R-2* R-3* R-4* R-5* D-2** E** F **G Date 01/04/11 < 0.018 < 0.019 < 0.019 < 0.019 < 0.020 < 0.017 < 0.019 < 0.024 < 0.026 01/11/11 < 0.019 < 0.013 < 0.019 < 0.020 < 0.022 < 0.019 < 0.019 < 0.017 < 0.017 01/18/11 < 0.019 < 0.013 < 0.018 < 0.021 < 0.021 < 0.014 < 0.015 < 0.019 < 0.025 01/25/11 < 0.026 < 0.016 < 0.025 < 0.019 < 0.016 < 0.027 < 0.022 < 0.009 < 0.015 02/01/11 < 0.021 < 0.015 < 0.018 < 0.022 < 0.021 < 0.017 < 0.020 < 0.017 < 0.021 02/08/11 < 0.020 < 0.014 < 0.014 < 0.020 < 0.024 < 0.017 < 0.009 < 0.021 < 0.018 02/15/11 < 0.019 < 0.021 < 0.016 < 0.015 < 0.016 < 0.019 < 0.020 < 0.019 < 0.021 02/22/11 < 0.016 < 0.021 < 0.017 < 0.019 < 0.017 < 0.016 < 0.013 < 0.022 < 0.024 03/01/11 < 0.016 < 0.020 < 0.021. < 0.016 < 0.019 < 0.016 < 0.014 < 0.025 < 0.016 03/08/11 < 0.014 < 0.012 < 0.012 < 0.025 < 0.019 < 0.016 < 0.014 < 0.029 < 0.023 03/15/11 < 0.016 < 0.027 < 0.017 < 0.024 < 0.019 < 0.023 < 0.023 < 0.027 < 0.017 03/22/11 < 0.016 < 0.017 < 0.016 < 0.017 < 0.023 < 0.010 < 0.015 < 0.014 <.0.013 03/29/11 3.415E-02 +/- .007 3.230E-02 +/- .006 3.130E-02 +/- .006 4.185E-02 +/- .006 3.440E-02 +/- .006 2.625E-02 +/- .006 2.770E-02 .007 4.150E-02 +/- .007 3.230E-02 +/- .006 04/05/11 9.950E-02 +/- .009 1.095E-01 +/- .010 8.810E-02 +/- .009 9.765E-02 +/-.009 9.330E-02 +/- .009 7.825E-02 +/- .008 1.025E-01 +/- .009 8.070E-02 +/- .008 1.105E-01 +/- .011 04/12/11 4.360E-02 +/- .007 3.265E-02 +/- .006 2.070E-02 +/- .007 3.440E-02 +/- .006 3.875E-02 +/- .007 3.780E-02 +/- .006 2.895E-02 +/- .006 2.990E-02 +/- .006 4.350E-02 +/- .007 04/19/11 < 0.023 < 0.016 < 0.015 < 0.020 < 0.019 < 0.014 < 0.021 < 0.016 < 0.014 04/26/11 < 0.018 < 0.022 < 0.016 < 0.015 < 0.024 < 0.018 < 0.016 < 0.017 < 0.015 05/03/11 < 0.019 < 0.01.8 < 0.013 < 0.016 < 0.028 < 0.023 < 0.023 < 0.148 < 0.022 05/10/11 < 0.019 < 0.014 < 0.016 < 0.014 < 0.024 < 0.019 < 0.021 < 0.020 < 0.016 05/17/11 < 0.022 < 0.017 < 0.018 .< 0.016 < 0.027 < 0.020 < 0.021 < 0.018 < 0.013 05/24/11 < 0.023 < 0.018 < 0.018 < 0.019 < 0.021 < 0.010 < 0.021 < 0.020 < 0.016 06/01/11 < 0.016 < 0.013 < 0.013 < 0.017 <-0.019 < 0.018 < 0.018 < 0.018 < 0.018 06/07/11 < 0.028 < 0.025 < 0.019 < 0.017 < 0.021 < 0.023 < 0.022 < 0.021 < 0.018 06/14/11 < 0.020 < 0.015 < 0.010 < 0.016 < 0.019 < 0.016 < 0.016. < 0.014 < 0.015 06/21/11 < 0.023 < 0.019 < 0.014 < 0.018 < 0.025 < 0.016 < 0.020 < 0.020 < 0.018 06/28/11 < 0.024 < 0.019 < 0.020 < 0.016 < 0.020 < 0.022 < 0.020 < 0.018 < 0.015

• ODCM Required Sample Location ** Optional Sample Location 6-16 M M m 1 - mM -M M mM M - M - M

mmm m m m m m m m m m m m m m m - m TABLE 6-7 (Continued)

ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFF-SITE SAMPLE LOCATIONS - 2011 1-131 ACTIVITY pCi/m 3 +/- 1 Sigma Week End R-1

• R-2

• R-3

• R-4

• R-5

• D-2 **F G **

Date 07/06/11 < 0.013 < 0.015 < 0.016 < 0.014 < 0.017 < 0.014 < 0.012 < 0.015 < 0.009 07/12/11 < 0.022 < 0.019 < 0.016 < 0.018 < 0.025 < 0.016 < 0.021 < 0.021 < 0.019 07/19/11 < 0.016 < 0.015 < .0.014 < 0.016 < 0.022

• 0.019 < 0.019 < 0.014 < 0.021 07/26/11 < 0.022 < 0.016 < 0.018 < 0.014 < 0.027 < 0.018 < 0.015 < 0.016 < 0.015.

08/02/11 < 0.021 < 0.012 < 0.016 < 0.018 <: 0.020 < 0.018 < 0.017 < 0.017 < 0.018 08/09/11 < 0.024 < 0.016 < 0.014 < 0.017 < 0.024 < 0.029 < 0.021 < 0.016 < 0.015 08/l6/-/-1 - O-.009- O-<-0:02 1---<-0:02 1- -<-0.020- -- 0_018- <-ori7 < 0:021 < 0_020 < 0.0-17 08/23/11 < 0.019 < 0.013 < .0.014 < 0.016 < 0.022 < 0.019 < 0.017 < 0.022 < 0.015 08/30/11 < 0.018 < 0.018 < 0.023 < 0.020 < 0.015 < 0.016 < 0.011 < 0.022 < 0.021 09/07/11 < 0.020 < 0.023 < 0.016 < 0.015 < 0.017 < 0.022 < 0.014 < 0.012 < 0.019 09/13/11 < 0.016 < 0.018 < 0.024 < 0.024 < 0.015 < 0.01.7 < 0.016 < 0.014 < 0.021 09/20/11 < 0.017 < 0.012 < 0.011 < 0.020 < 0.016

• 0.014 < 0.011 < 0.010 < 0.013 09/27/11 < 0.018 < 0.014 < 0.012 < 0.016 < 0.013 < 0.019 < 0.011 < 0.022 < 0.021 10/04/11 < 0.023 < 0.021 < 0.014 < 0.016 < 0.018 < 0.016 < 0.016 < 0.015 < 0.022 10/11/11 < 0.013 < 0.016 < 0.019 < 0.025 < 0.020 < 0.012 < 0.017 < 0.018 < 0.023 10/18/11 < 0.022 < 0.020 < .0.013 < 0.021 < 0.020 < 0.015 < 0.018 < 0.018 < 0.023 10/25/11 < 0.024 < 0.012 < 0.014 < 0.023 < 0.030 < 0.019 < 0.0i1 < 0.019 < 0.016 11/01/11 < 0.019 < 0.014 < 0.019 < 0.020 < 0.018 < 0.019 < 0.011 < 0.014 < 0.014-11/08/11 < 0.015 < 0.024 < 0.016 < 0.,020 < 0.019 <'0.018 < 0.015 < 0.026 < 0.019 11/15/11 < 0.014 < 0.020 < 0.017 < 0.023 < 0.017 < 0.016 < 0.018 < 0.017 < 0.021 11/22/11 < 0.020 < 0.019 < 0.017 < 0.016 < 0.021 < 0.022 < 0.019 < 0.013 < 0.020 11/30/11 < 0.016 < 0.015 < 0.009 < 0.014 < 0.022 < 0.024 < 0.016 < 0.018 < 0.014 12/06/11 < 0.016 < 0.013 < 0.018 < 0.016 < 0.019 < 0.024 < 0.022 < 0.020 < 0.019 12/13/11 < 0.023 < 0.020 < 0.012 < 0.018 < 0.018 < 0.019 < 0.020 < 0.023 < 0.021 12/20/11 < 0.016 < 0.017 < 0.016 < 0.020 < 0.019 < 0.0.17 < 0.024 < 0.016 < 0.012 12/28/11 < 0.013 < 0.015 < 0.019 < 0.012 < 0.020 < 0.019 < 0.019 < 0.016 < 0.016

• ODCM Required Sample Location

• • Optional Sample Location 6-17

TABLE 6-8 ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ON-SITE SAMPLE LOCATIONS - 2011 1-131 ACTIVITY pCi/ m 3 1 Sigma WeekEnd D-1**

• H*** I ** J** K**

Date 01/03/11 < 0.017 < 0.015 < 0.018 < 0.022 < 0.024 < 0.021 01/10/11 < 0.022 < 0.022 < 0.014 < 0.027 < 0.027 < 0.024 01/17/11 < 0.017 < 0.017 < 0.019 < 0.017 < 0.020 < 0.034 01/24/11 < 0.022 < 0.021 < 0.017 < 0.025 < 0.019 < 0.021 01/31/11 < 0.020 < 0.019 < 0.012 < 0.025 < 0.022 < 0.020 02/07/11 < 0.023 < 0.016 < 0.013 < 0.021 < 0.023 < 0.020 02/14/11 < 0.020 < 0.018 < 0.019 < 0.020 < 0.023 < 0.017 02/21/11 < 0.019 < 0.015 < 0.018 < 0.026 < 0.019 < 0.021 02/28/11 < 0.016 < 0.020 < 0.019 < 0.016 < 0.013 < 0.019 03/07/11 < 0.014 < 0.022 < 0.018 < 0.020 < 0.012 < 0.023 03/14/11 < 0.021 < 0.012 < 0.016 < 0.018 < 0.022 < 0.023 03/21/11 < 0.019 < 0.016 < 0.016 < 0.018 < 0.023 < 0.017 03/28/11 2.506E-02 +/- .009 3.856E-02 +/- .009 3.962E-02 +/- .009 4.573E .011 3.904E-02 + .010 3.283E-02 +/-'.009 04/04/11 9.465E-02 +/- .009 1.002E-01 +/- .009 7.805E-02 +/- .009 9.710E-02 + .009 8.790E-02 +/- .009 8.675E-02 + .009 04/11/11 3.565E-02 +/- .007 3.340E-02 +/- .006 3.905E-02 +/- .007 5.130E-02 +/- .006 4.615E-02 +/- .008 4.635E-02 + .007 04/18/11 < 0.023 < 0.012 < 0.016 < 0.009 < 0.022 < 0.018 04/25/11 < 0.018 < 0.012 < 0.010 < 0.029 < 0.013 < 0.017.

05/02/11 < 0.016 < 0.016 < 0.021 < 0.022 < 0.024 < 0.016 05/09/11 < 0.018 < 0.018 < 0.026 < 0.017 < 0.016 < 0.021 05/16/11 < 0.023 < 0.023 < 0.012 < 0.013 < 0.020 < 0.023 05/23/11 < 0.013 < 0.017 < 0.017 < 0.013 < 0.015 < 0.022 05/31/11 < 0.016 < 0.019 < 0.011 < 0.023 < 0.017 < 0.015 06/06/11 < 0.020 < 0.022 < 0.021 < 0.017 < 0.019 < 0.019 06/13/11 < 0.010 < 0.015 < 0.015 < 0.016 < 0.020 < 0.016 06/20/11 < 0.020 < 0.018 < 0.017 < 0.013 < 0.024 < 0.021 06/27/11 < 0.013 < 0.021 < 0.015 < 0.028 <, 0.021 < 0.022

• • Optional Sample Location 6-18 m M mM mMMm m M M m M M M m

TABLE 6-8 (Continued)

ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ON-SITE SAMPLE LOCATIONS - 2011 1-131 ACTIVITY pCi/ m 3 1 Sigma WeekEndD-1 G** H** I J** K**

Date 07/05/11 < 0.021 < 0.017 < 0.014 < 0.017 < 0.015 < 0.019 07/11/11 < 0.024 < 0.020 < 0.017, < 0.013 < 0.028 < 0.018 07/18/11 < 0.017 < 0.016 < 0.010 < 0.017 < 0.015 < 0.016 07/25/11 < 0.019 < 0.014 < 0.012. < 0.022 < 0.021 < 0.019 08/01/11 < 0.019 < 0.015 < 0.016 < 0.020 < 0.018 < 0.018 08/08/11 < 0.016 < 0.020 < 0.012 < 0.020 < 0.021 < 0.014 08/15/11 < 0.025 < 0.016 < 0.016 < 0.021 < 0.025 < 0.016 08/22/11 < 0.019 < 0.017 < 0.021 < 0.018 < 0.021 < 0.018 08/29/11 < 0.014 < 0.018 < 0.009 < 0.018 < 0.027 < 0.018 09/06/11 < 0.016 < 0.016 <.0.014 < 0.011 < 0.015- < 0.021 09/12/11 < 0.022 < 0.019 < 0.019 < 0.022 < 0.028 < 0.020 09/19/11 < 0.016 < 0.015 < 0.026 < 0.021 < 0.015 < 0.011 09/26/11 < 0.016 < 0.015 < 0.014 < 0.018 < 0.026 < 0.023 10/03/11 < 0.019 < 0.01.5 < 0.018 < 0.012 < 0.028 < 0.023 10/10/11 < 0.018 < 0.020 < 0.028 < 0.034 < 0.020 < 0.017 10/17/11 < 0.018 < 0.016 < 0.014 < 0.017 < 0.013 < 0.015 10/24/11 < 0.022 < 0.019 < 0.016 < 0.017 < 0.024 < 0.021 10/31/11 < 0.018 < 0.016 < 0.019 < 0.017 < 0.019 < 0.019 11/07/11 < 0.018 < 0.020 < 0.017 < 0.012 < 0.019 < 0.021 11/14/11 < 0.022 < 0.022 < 0.017 < 0.014 < 0.020 < 0.018 11/21/11 < 0.012 < 0.017 < 0.014 < 0.016 < 0.019 < 0.018 11/28/11 < 0.017 < 0.013 < 0.014 < 0.018 < 0.023 < 0.013 12/05/11 < 0.012 < 0.013 < 0.016 < 0.020 < 0.018 < 0.021 12/12/11 < 0.015 < 0.014 < 0.017 < 0.020 < 0.021 < 0.024 12/19/11 < 0.027 < 0.020 < 0.023 < 0.020 < 0.010 < 0.014 12/27/11 < 0.018 < 0.020 < 0.018 < 0.018 < 0.015 < 0.019

• • Optional Sample Location 6-19

TABLE 6-9 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF JAFNPP/NMPNS SITE AIR PARTICULATE SAMPLES - 2011 Results in Units of 1OE-3 pCi/ m3 +/- 1 Sigma OFFSITE SAMPLE LOCATIONS - 1ST QTR 2011 Nuclide R-1

• R-2 R-3

• R-4

• R-5

• D-2 ** E** F** G**

Be-7 103.6 + 12.0 112.4 +/- 12.1 92.8 + 10.8 113.0 +/- 13.2 119.5 +/- 12.6 98.9 +/- 11.8 96.9 + 11.8 99.5 +/- 11.4 103.6 +/- 12.4 Cs-134 < 1'3 < 2.0 < 17 < 1.7 < 1.5 < 1.9 < 2.2 < 1.7 < 2.0 Cs-137 < 1.2 < 1.3 < 1.1 < 0.3 < 1.2 < 1.3 < 1.2 < 1.2 < 1.7 Zr-95 < 3.6 < 2.8 < 3.4 < 3.1 < 3.0 < 4.9 < 3.5 < 2.7 < 3.2 Nb-95 < 2.7 < 2.7 < 3.7 < 2.6 < 2.5 < 2.1 < 3.9 < 2.5 < 3.0 Co-58 < 1.6 < 1.2 < 1.7 < 1.8 < 2.5 < 0.5 < 2.2 < 1.7 < 2.4 Mn-54 < 1.1 < 1.5 < 1.6 < 1.0 < 1.0 < 2.0 < 1.5 < 1.2 < 1.3 Zn-65 < 4.0 < 2.2 < 4.4 < 2.8 < 3.7 < 3.3 < 4.8 < 4.0. < 3.8 Co-60 < 1.7 < 1.5 <1.2 < 1.8 <2.1 < 1.9 < 1.3 < 1.0 < 2.2 K-40 < 20.0 < 14.7 < 4.5 < 18.7 < 5.3 < 5.4 < 19.9 23.5 +/- 6.2 < 11.6 OFFSITE SAMPLE LOCATIONS - 2ND QTR 2011 Nuclide R-1* R-2* R-3* R-4* R-5* D-2** E** F **G**

Be-7 81.8 +/- 11.4 72.6 +/- 10.8 92.4 +/- 12.4 87.1 +/- 11.9 82.6 +/- 12.1 75.2 +/- 11.2 91.6 +/- 13.0 93.3 +/- 12.6 99.3 +/- 12.2 Cs-134 < 1.4 < 1.8 < 2.0 < 1.7 < 1.8 < 1.8 < 1.5 < 2.0 < 1.7 Cs-137 < 1.0 < 1.3 < 1.4 < 1.2 < 1.5 < 1.0 < 1.8 < 1.9 < 0.8 Zr-95 < 3.7 < 3.8 < 4.6 <4.8 < 3.3 < 3.4 < 4.9 < 2.7 < 3.2 Nb-95 < 3.6 < 2.5 < 2.2 < 4.1 < 3.7 < 2.0 < 3.2 < 0.8 < 2.8 Co-58. < 2.1 < 1.7 < 2.5 < 2.0 < 1.5 < 1.9 < 2.5 < 2.5 < 2.4 Mn-54 < 1.6 < 1.6 < 1.5 <1.6 < 1.5 < 1.3 < 1.0 < 2.0 < 1.0 Zn-65 < 3.5 < 3.7 < 3.0 < 4.1 < 3.7 < 3.7 < 5.5 < 3.7 < 1.0 Co-60 < 1.4 < 0.5 < 2.1 < 1.9 < 2.1 < 0.5 < 1.7 < 1.6 < 2.1 K-40 < 5.2 < 18.1 < 17.2 < 4.4 < 19.3 < 20.1 < 22.0 31.3 +/- 8.4 < 14.7

• ODCM Required Sample Loction

• Optional Sample Location 6 - 20 Mm M M M-- M M ----- M -

ml m m[ m m mk m m m m m '! m m mI m ml m TABLE 6-9 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF JAFNPP/NMPNS SITE AIR PARTICULATE SAMPLES - 2011 Results in Units of 10E-3 pCi/ m 3 1 Sigma OFFSITE SAMPLE LOCATIONS - 3RD QTR 2011 Nuclide R-1

• R-2* R-3* R-4* R-5* D-2** E** F** G**

Be-7 98.4 + 12.4 101.9 +/- 12.7 94.4 +/- 12.4 83.5 +/- 10.3 94.4 +/- 12.0 .73.8 +/- 11.9 108.7 +/- 11.8 100.8 +/- 12.1 95.6 +/- 11.2 Cs-134 < 2.3 < 1.9 < 2.1 < 1.4 < 2.1 < 1.3 < 1.7 < 1.8 < 1.3 Cs-137 < 1.2 < 1.0, < 1.3 < 0.9 < 0.8 < 1.3 < 1.0 < 1.1 < 1.1 Zr-95 < 3.1 < 4.2 < 3.5 < 3.1 < 4.0 < 4.8 < 2.7 < 3.2 < 3.0 Nb-95 < 0.8 <4.5 < 2.6 < 2.6 < 2.6. < 3.2 < 3.2 < 2.6 < 2.8 Co-58 < 2.3 < 1.7 < 2.2 < 2.2 < 1.8 < 1.9 < 1.2 < 1.5 < 1.9 Mn-54 < 1.7 < 1.4 < 1.3 < 1.6 < 1.8 < 1.4 < 1.1 < 1.7 < 1.3 Zn-65 < 4.4 < 4.1 < 3.2. < 3.5 < 4.5 < 3.7 < 3.1 < 3.5 < 3.1 Co-60 < 1.6 < 1.3 < 0.5 < 1.7 < 2.5 < 1.6 < 1.2 < 1.9 < 1.2 K-40 42.1 +/- 10.7 < 4.5 < 4.7 < 4.4 < 5.5 < 15.1 < 4.2 < 4.2 < 12.3 OFFSITE SAMPLE LOCATIONS - 4TH QTR 2011 Nuclide R-1

• R-2

• R-3*. R-4* R-5* D-2** E** F** G**

Be-7 104.5 +/- 12.1 96.3 +/- 11.4 78.3 +/- 9.7 75.8 +/- 10.5 85.7 + 11.2 100.0 +/- 12.9 91.7 +/- 12.1 78.9 +/- 10.6 104.6 +/- 11.7 Cs-134 < 2.0 < 2.1 < 1.5 < 1.4 < 1.6 < 1.7 < 2.1 < 2.0 < 2.0 Cs-137 < 1.2 < 1.0 < 1.2 < 1.0 < 0.9 < 1.3 < 1.3 < 0.9 < 1.2 Zr-95 < 4.0 < 2.8 < 3.6 < 0.9 < 4.1 < 3.9 < 5.4 < 3.7 < 3.6 Nb-95 < 3.0 < 2.3 < 3.0 < 3.2 < 2.4 < 3.2 < 3.3 < 3.5 < 1.8 Co-58 < 3.0 < 2.0 < 1.4 < 2.0 < 2.0 < 2.2 < 2.3 < 2.4 < 1.8 Mn-54 < 1.9 < 1.7 < 1.6 < 1.4 < 1.4 < 1.9 < 1.3 < 0.9 < 2.1 Zn-65 < 3.7 < 2.7 < 2.3 < 1.0 < 2.4 < 3.6 < 3.3 < 3.3 .< 2.7 Co-60 < 1.8 < 1.7 < 1.4 < 1.4 < 1.5 < 0.5 < 1.4 < 1.8 < 1.2 K-40 < 15.5 < 14.7 < 14.7 < 18.3 < 4.5 < 16.5 < 14.6 < 15.4 < 11.6

• ODCM Required Sample Loction

• • Optional Sample Location 6-21

TABLE 6-9 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF JAFNPP/NMPNS SITE AIR PARTICULATE SAMPLES - 2011 Results in Units of 10E-3 pCi/ I +/- 1 Sigma ONSITE SAMPLE LOCATIONS - 1ST QTR 2011 Nuclide D-1** G** H** I** J** K**

Be-7 103.4 +/- 12.6 103.3 +/- 12.5 99.8 +/- 13.0 121.0 +/- 12.8 115.7 +/- 12.3 107.2 + 13.0 Cs-134 < 1.9 < 2.1 < 1.9 < 1.8 < 0.3 < 2.2 Cs-137 < 1.7 < 1.4 < 1.0 < 0.9 < 1.2 < 1.9 Zr-95 < 3.6 < 4.6 < 3.6 < 4.0 < 3.1 < 3.2 Nb-95 < 3.0 < 3.6 < 3.3 < 1.8 < 3.4 < 2.7 Co-58 < 2.4 < 2.2 < 2.4 < 1.2 < 2.1 < 1.5 Mn-54 < 2.2 < 1.7 < 1.5 < 1.4 < 1.6 < 2.0 Zn-65 < 3.8 < 3.9 < 3.1 < 3.1 < 4.6 < 3.9 Co-60 < 0.5 < 0.5 < 1.2 < 1.5 < 1.4 < 2.5 K-40 < 5.4 < 5.4 < 18.9 < 20.1 < 5.2 53.0 + 10.4 ONSITE SAMPLE LOCATIONS - 2ND QTR 2011 Nuclide D-1 G** H** J** K**

Be-7 107.1 +/- 12.7 88.8 +/- 12.4 86.2 +/- 11.8 94.1 +/- 13.0 98.3 +/- 12.0 94.7 + 11.3 Cs-134 < 2.1 < 1.8 < 1.7 < 1.4 < 1.9 < 1.9 Cs-137 < 1.3 < 1.3 < 1.2 < 1.1 < 0.7 < 1.2 Zr-95 < 4.1 < 3,9 < 3.3 < 3.8 < 4.8 < 4.1 Nb-95 < 3.5 < 3.1 < 2.9 , < 5.0 < 3.9 < 3.0.

Co-58 < 1.6 < 2.5 < 2.2 < 1.5 < 2.3 < 0.5 Mn-54 < 2.1 < 1.7 < 1.8 < 1.3 < 1.8 < 1.6 Zn-65 < 3.8 < 2.5 < 1.0 < 3.8 < 3.4 < 3.1 Co-60 < 1.9 < 0.5 < 0.5 < 0.5 < 1.2 < 0.4 K-40 < 11.4 < 15.4 < 14.8 < 17.1 < 15.2 < 17.8

• • Optional Sample Location 6 - 22

- 1 mm M-- MM

m - m M M M M m m M m m M- m m M m TABLE 6-9 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF JAFNPP/NMPNS SITE AIR PARTICULATE SAMPLES - 2011 Results in Units of 10E-3 pCi/rm 3 +/- 1 Sigma ONSITE SAMPLE LOCATIONS - 3RD QTR 2011 Nuclide D-1** G** H** J** K**

Be-7 77.4 +/- 10.6 108.1 +/- 12.9 83.1 +/- 11.8 102.3 +/- 11.8 104.4 +/- 12.0 85.0 +/- 11.0 Cs-134 < 1.5 < 1.8 < 1.9 < 1.3 < 1.6 < 1.8 Cs-137 < 1.1 < 1.2 < 0.8 < 1.2 < 1.5 < 1.1 Zr-95 < 3.0 < 0.8 < 3.5 < 3.9 < 3.7 < 4.7 Nb-95 < 3.5 < 3.6 < 2.9 < 3.3 < 2.2 < 2.7 Co-58 < 1.9 < 1.3 < 2.1 < 2.0 < 1.2 < 1.6 Mn-54 < 1.3 < 1.1 <1.9 < 1.3 < 1.3 < 1.7 Zn-65 < 3.6 < 4.1 < 3.7 < 2.9 < 3.1 < 3.1 Co-60 < 1.5 < 1.5 < 1.6 < 1.3 < 1.5 < 1.2 K-40 < 12.2 < 15.7 < 21.5 29.6 +/- 7.0 < 15.3 < 15.3 ONSITE SAMPLE LOCATIONS - 4TH QTR 2011 Nuclide D-1** G** H** I** J** K**

Be-7 86.3 +/- 10.5 84.7 +/- 11.0 72.9 + 10.5 94.8 +/- 10.7 89.5 +/- 12.3 110.4 +/- 12.8 Cs-134 < 1.9 < 1.4 < 1.5 < 1.7 < 1.9 < 2.0 Cs-137 < 1.0 < 1.2 < 0.9 < 1.1 < 1.2 < 1.1 Zr-95 < 3.6 < 4.3 < 3.0 < 2.1 < 4.4 < 3.1 Nb-95 < 3.5 < 3.8 < 2.5 < 2.2 < 3.6 < 3.3 Co-58 < 1.2 < 1.4 < 1.3 < 1.6 < 0.5 < 1.8 Mn-54 < 1.8 < 1.0 < 1.2 < 1.3 < 1.7 < 1.5 Zn-65 < 4.1 < 2.3 < 2.6 < 3.1 < 5.1 < 4.2 Co-60 < 1.5 < 1.1 < 1.4 < 1.5 < 0.5 < 0.5.

K-40 < 20.9 < 11.6 < 18.0 < 12.2 < 16.2 < 23.3

• • Optional Sample Location 6 - 23

TABLE 6-10 DIRECT RADIATION MEASUREMENT RESULTS - 2011 Results in Units of mrem/std. Month +/- 1 Sigma LOCATION FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER DEGREES & DISTANCE (1)

NUMBER ____________________ _________________

3 Dl Onsite 10.98 , 0.46 12.98 .4 0.44 12.45 +/- 0.57 10.35 +/- 0.31 690 at 0.2 miles 4 D2 Onsite 3.83 4 0.18 5.14 4 0.23 4.04 +/- 0.25 4.07 + 0.19 140' at 0.4 miles 5 E Onsite 3.88 +/- 0.18 5.09 + 0.20 4.61 +/- 0.22 4.12 +/- 0.16 175' at 0.4 miles 6 F Onsite *3.25 - 0.18 4.41 4 0.28 3.97 +/- 0.28 3.52 + 0.13 210' at 0.5 miles 7* G Onsite 3.13 +/- 0.18 4.47 + 0.23 4.01 + 0.17 3.52 +/- 0.20 2500 at 0.7 miles 8* R-5 Offsite Control 4.08 4 0.22 5.45 - 0.27 5.10 +/- 0.30 4.49 + 0.14 42' at 16.4 miles 9 DI Offsite 3.50 +/- 0.21 4.61 +/- 0.25 4.23 +/- 0.28 3.85 +/- 0.21 800 at 11.4 miles 10 D2Offsite 3.31 +/- 0.24 4.16 + 0.20 4.50 + 0.25 3.72 +/- 0.20 1170 at 9.0 miles 11 EOffsite . 3.32 +/- 0.19 4.60 - 0.28 3.99 +/- 0.20 3.73 + 0.12 1600 at 7.2 miles

.12 F-Offsite 3.18 +/- 0.18 4.67 + 0.22 4.18 +/- 0.28 3.81 + 0.14 1900 at 7.7 miles 13 GOffsite 3.40 +/- 0.20 4.80 - 0.30 4.14 +/- 0.24 3.92 +/- 0.24 2250 at 5.3 miles 14* DeMass Rd SW Oswego - Control 3.22 +/- .0.18 4.67 +/- 0.23 4.27 +/- 0.23 3.78 +/- 0.17 2260 at 12.6 miles 15* Pole 66 W Boundary - Bible Camp 3.26 +/- 0.19 4.36 4 0.22 3.70 +/- 0.17 3.51 +/- 0.11 2370 at 0.9miles 18* Energy lnfo Center- Lamp Post SW 4.13 +/- 0.22 4.55 +/- 0.17 5.29 +/- 0.28 4.27 +/- 0.16 265' at 0.4 miles 19 East Boundary - JAF Pole 9 4.01 +/- 0.20 4.99 +/- 0.21 4.64 -+ 0.20 4.28 +/- 0.17 810 at 1.3 miles 23* H Onsite 4.48 +/- 0.20 5:92 +/- 0.32- 5.18 +/- 0.25 4.79 +/- 0.25 700 at 0.8 miles 24 IOnsite 3.83 +/- 0.25 4.67 +/- 0.22 4.54 +/- 0.26 3.96 +/- 0.12 980 at 0.8 miles 25 J Onsite 3.75 +/- 0.21 4.83 +/- 0.24 4.45 +/- 0.22 4.66 +/- 0.17 1100 at 0.9 miles 26 K Onsite. 3.57 +/- 0.23 4.79 + 0.23 4.28 +/- 0.21 3.76 .+/- 0.15 132' at 0.5 miles 27 NFenceNofSwitchyardJAF 18.50 +/- 1.11 21.52 +/- 1.35 20.45 +/- 1.24 18.29 +/- 0.88 600. at 0.4miles 28 NLightPoleNofScreenhouse JAF 22.24 +/- ,1.31 28.82 +/- 1.42 .27.76 +/- 1.29 23.72 +/- 0.88 680 at 0.5 miles 29 NFenceNofWSide 20.87 + 1.25 26.30 +/- 1.47 21.89 +/- 0.91 23.61 + 1.42 650 at 0.5 miles 30 N Fence (NW) JAF 10.11 +/- 0.57 11.77 +/- 0.82 11.16 +/- 0.70 11.38 +/- 0.95 570 at 0.4 miles 31 N Fence (NW) NMP-1 6.42 +/- 0.32 8.03 +/- 0.34 7.19 +/- 0.31 7.29 +/- 0.33 2760 at 0.2 miles 39 NFenceRadWaste-NMP-1 " 10.17 +/- 0.44 12.26 +/- 0.45 11.15 +/- 0.56 10.68 +/- 0.36 2920 at 0.2 miles 47 N Fence (NE) JAF 6.02 +/- 0.25 7.33 +/- 0.33 6.74 +/- 0.38 6.95 +/- 0.39 690 at 0.6 miles 49* PhoenixNY-Control 2.61 +/- .0.12 4.22 +/- 0.22 3.38 +/- 0.17 3.89 + 0.23 1630 at 19.8miles 51 Liberty & Bronson Sts E of OSS 3.3.3 + 0.20 5.08 +/- 0.43 4.07 +/- 0.20 4.07 + 0.15 2330 at 7.4 miles 52 E 12th&CayugaStsOswegoSchool 3.22 + 0.16 4.52 +/- 0.20 3.99 +/- 0.21 3.89 +/- 0.13 2270 at 5.8 miles 53 Broadwell & Chestnut Sts Fulton HS 3.29 +/- 0.16 . 5.10 +/- 0.31 4.30 +/- 0.25 4.27 +/- 0.16 1830 at 13.7 miles 54 Liberty St&CoRt 16MexicoHS 3.30 + 0.22 4.14 +/- 0.22 4.38 +/- "0.31 3.92 +/- 0.20 1150 at 9.3 miles 55 Gas Substation Co Rt 5-Pulaski 3.21 +/- 0.21 4.74 +/- 0.21 4.03 +/- 0.22 4.07 +/- 0.14 750 at 13.0 miles 56* Rt 104-New Haven Sch (SE Comer) 2.87 1 0.18 4.06 +/- 0.21 4.35 +/- 0.22 3.81 +/- 0.15 1230 at 5.3 miles 58* Co Rt IA-Alcan (E ofE Entrance Rd) 3.55 1- 0.21 4.91 +/- 0.24 4.43 +/- 0.26 4.24 +/- 0.21 2200 at 3.1 miles 75* Unit 2NFenceNofReactorBldg 6.78 +/- 0.43 8.23 +/- 0.28 7.55 +/- 0.41 7.39 +/- -0.33 50 at 0.1 miles 76* Unit2NFenceNofChangeHouse 5.19 +/- 0.26 6.54 +/- 0.25 5.78 +/- 0.32 5.44 +/- 0.22 250 at 0.1 miles 77* Unit 2 N Fence N of Pipe Bldg 5.96 +/- 0.32. 7.30 +/- 0.29 6.55 +/- 0.45 6.66 +/- 0.22 450 at 0.2 miles (1) Direction and distance based on NMP-2 reactor centerline.

• TLD required by ODCM 6 - 24 m rlnrn llm mm Blmmml

m m m m mmmmmmmm m mm m m TABLE 6-10 (Continued)

DIRECT RADIATION MEASUREMENT RESULTS - 2011 Results in Units of mrem/std. Month :E 1 Sigma LOCATION FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER DEGREES & DISTANCE (1)

NUMBER 78* JAF E ofE Old Lay Down Area 3.76 +/- 0.20 5.07 +/- 0.21 4.52 +/- 0.26 4.41 +/- 0.15 900 at 1.0miles 79* Co Rt 29 Pole #63 02 mi S of Lake Rd 3.44 +/-4 0.21 4.56 +/- 0.21 4.17 +/- 0.18 3.90 +/-- 0.20 115' at 1.1 miles 80* Co Rt 29 Pole #54 07mi S of Lake Rd 3.33 +/- 0.15 4.74 +/- 0.24 4.31 +/- 0.26 3.99 +/- 0.25 1330 at 1.4miles 81* MinerRdPole#16,05miWofRt29 3.38 +/- 0.15 4.55 +/- 0.24 4.11 +/- 0.20 3.81 +/- 0.14 1590 at 1.6 miles 82* MinerRdPole# 1-1/211 miWofRt29 3.31 +/- 0.17 4.72 +/- 0.23 4.02 +/- 0.19 3.79 +/- 0.18 1810 at 1.6miles 83* Lakeview Rd Tree 045 mi N of Miner Rd 3.33 +/- 0.15 3.99 +/- 0.18 4.44 + 0.20 3.74 +/- 0.14 2000 at 1.2 miles 84* LakeviewRdNPole#6117 200ftNofLakeRd 3.59 +/- 0.21 4.59 +/- 0.25 4.15 +/- 0.21 4.13 +/- 0.15 2250- at 1.1 miles 85* Unit 1 NFenceNofWSide ofScreen House 9:46 +/- 0.37 11.58 +/- 0.45 10.91 +/- 0.57 10.58 +/- 0.50 2940 at 0.2 miles 86* Unit 2 N Fence N of W Side of Screen House 7.30 +/- 0.50 8.74 + 0.41 8.27 +/- 0.46 8.24 +/-z 0.33 3150 at 0.1 miles 87* Unit 2 N Fence N ofE Side ofScreen House 7.48 +/- 0.38 8.92 Az 0.34 8.11 +/- 0.48 8.01 +/- 0.26 341' at 0.1 miles 88* Hickory Grove Rd Pole #2 06 mi N ofRt 1 3.39 4+/- 0.21 4.55 4+/- 0.22 4.12 +/- 0.19 3.91 +/-z 0.23 970 at 4.5 miles 89* LeavittRdPole#1604miSofRtl 3.67 +/- 0.18 5.02 +z 0.23 4.46 +/- 0.23 4.22 +/- 0.21 1110 at 4.1 miles 90* IRtl04Pole#300 150ftEofKeefeRd 3.42 +/- 0.17 4.51 +/- 0.18 4.59 +/- 0.24 3.88' +/- 0.17 1350 at 4.2miles 91* Rt 51A Pole #5908 mi W ofRt 51 3.00 +/-- 0.18 4.58 4. 0.22. 3.80 +/-z 0.20 .3.77 +/-- 0.18 1560 . at 4.8 miles 92* Maiden Lane Rd Power Pole'06 mi S of Rt 104 3.42 +/- 0.19 5.25 4+/- 0.23 4.31 ,+/- 0.21 4.31 +/- 0.22 1830 at 4.4 miles 93* Rt53 Pole 1- 120 ftSofRt 104 - 3.27 +/- 0.14 4.67 +/-- 0.24 4.00. +/- 0.21 3.91 .+/-A 0.20 2050 at 4.4miles 94* RtI Pole#82250ftEofKocherRd(CoRt63) 3.10 4. 0.15 4.42 +/- 0.23 . 3.71 Az 0.18 3.62 +/-z 0.27 2230 at 4.7-miles 95* Alcan W access Rd Joe Fultz Blvd Pole #21 3.10 +/- 0.15 4.22 Az 0.19 3.46 Az 0.18 3.61 +/- 0.27 2370 at 4.1 miles 96* Creamery Rd 03 mi S of Middle Rd Pole 1-1/2 3.12 +/- 0.17 4.46 +/- 0.23 4.00 +/- 0.19 3.83 +/- 0.16 1990 at 3.6 miles 97* Rt 29 Pole #50 200ftNofMinerRd 3.30 +/- 0.19 4.71 A+/- 0.24 3.92 Az 0.21 3.97 +/- 0.24 1430 at 1.8 miles 98 Lake Rd Pole #145 015 mi E ofRt 29 3.41 +/- 0.16 4.66 +/- 0.22 4.26 Az 0.27 4.19 +/- 0.24 1010 at 1.2 miles 99 NMP Rd 04 mi N ofLake Rd Env Station R1 3.51 +/- 0.19 4.92 +/- 0.24 4.25 +/-- 0.22 4.22 +/- 0.15 880 at 1.8 miles 100 Rt 29 & Lake Rd Env Station R2 3.45 Az 0.15 4.65 : 0.22 4.06 +/- 0.19 4.08 A+/- 0.14 1040 at 1.1 miles 101 Rt2907miSofLakeRdEnvStationR3 3.21 A+/- 0.20 4.31 A 0.21 3.97, +/- 0.31 3.68 +/- 0.13 1320 at 1.5 miles 102 EOF/EnvLab Rt 176 E Driveway Lamp Post 3.15 +/- 0.16 4.57 Az 0.32 3.86 +/-- 0.21 4.00 +/- 0.14 1750 at 11.9 miles 103 EIC East Garage Rd Lamp Post 3.89. +/- 0.21 4.57 A 0.19 4.80 +/- 0.25 4.53 +/- 0.18 2670 at 0.4 miles' 104 ParkhurstRdPole#23 01 mi S of Lakerd 3.40 +/- 0.20 4.48 Az 0.20 4.18. +/- 0.21 4.13 +/- 0.17 1020 at 1.4 miles 105 Lake viewRdPole#3605miSofLakeRd 3.44 +/- 0.23 4.19 +/- 0.23 4.68 +/- 0.33 4.14 +/- 0.21 1980 at 1.4 miles 106 Shoreline Cove W ofNMP-1 Tree on W Edge 4.19 +/- 0.21 5.13 +/- 0.24 6.03 +/- 0.31 5.54 Az 0.21 2740 at 0.3 miles 107 ShorelineCoveWofNMP-1 30ftSSWof#106 4.07 +/- 0.20 5.04 +/- 0.22 5.48 +/-z 0.27 5.17 +/- 0.20 2720 at 0.3 miles 108 LakeRdPole#142300ftEofRt29S 3.56 +/- 0.17 4.77 +/- 0.21 4.20 +/- 0.17 4.15 Az 0.16 1040 at 1.1 miles 109 TreeNorthofLakeRd300ftEofRt29N 3.39 +/-A 0.15 4.70 +/- 0.26 4.29 Az 0.28 4.25 +/- 0.25 1030 at 1.1 miles 111 State Route 38 Sterling NY-Control 3.03 +/- 0.20 4.50 +/- 0.22 3.87 +/-z 0.18 3.84 Az 0.14 1660 at 26.4.miles 112 EOF/Env Lab Oswego County Airport 3.52 +/- 0.16 4.76 +/- - 0.21 3.87 +/- 0.27 4.13 +/-z 0.18 1750 at 11.9miles 113 BaldwinsvilleNY- Control 2.98 :E 0.16 4.34 J- 0.20 3.57 +/- 0.18 3.87 +/- 0.16 2140 at 21.8 miles (1) Direction and distance based on NMP-2 reactor centerline. .* TLD required by ODCM 6 - 25

TABLE 6-11 CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK- 2011 Results in Units of pCi/liter + 1 Sigma Sample Location ** No. 55 Date 1-131 Cs-134 Cs-137 K-40 Ba/La-140 Others t 04/11/11 < 0.588 < 5.54 < 5.24 1686 +/- 66.6 < 5.17 <LLD 04/25/11 < 0.528 < 4.00 < 5.61 1571 +/- 71.4 < 5.48 <LLD 05/09/11 < 0.472 < 8.12 < 6.01 1349 +/- 77.3 < 4.71 <LLD 05/23/11 < 0.634 < 7.52 < 5.23 1335 +/- 62.1 < 3.22 <LLD 06/06/11 < 0.480 < 7.57 < 6.37 1419 +/- 81.3 < 8.07 <LLD 06/20/11 < 0.595 < 6.25 < 5.79 1643 +/- 77.6 < 7.15 <LLD 07/11/11 < 0.580 < 3.40 < 4.97 1565 +/- 70.6 < 5.83 <LLD 07/27/11 < 0.506 < 12.81 < 10.41 1820 +/- 107.8 < 12.30 <LLD 08/08/11 < 0.621 < 12.94 < 10.79 1755 + 109.4 < 12.34 <LLD 08/22/11 < 0.423 < 7.66 < 8.19 1692 +/- 104.5 < 10.43 <LLD 09/06/11 < 0.597 < 3.64 < 4.82 1530 +/- 60.5 < 4.69 <LLD 09/19/11 < 0.530 < 8.12 < 7.78 1587 +/- 84.6 < 3.73 <LLD 10/03/11 < 0.656 < 4.49 < 6.88 1564.+/- 82.6 < 4.72 <LLD 10/17/11 < 0.651 < 6.04 < 10.19 1657 +/- 100.4 < 6.78 <LLD 11/07/11 < 0.627 < 4.39 < 7.55 1594 +/- 76.6 < 8.67 <LLD 11/21/11 < 0.700 < 8.01 < 6.32 1544 +/- 81.4 < 6.96 <LLD 12/06/11 < 0.705 < 12.39 < 9.35 1631 +/- 103.5 < 9.01 <LLD 12/19/11 < 0.616 < 7.67 < 6.98 1307 +/- 74.4 < 7.43 <LLD

• • Sample Location is Optional

• • • Corresponds to Sample Location noted on Figure 3.3-4 t Plant related radionuclides 6 - 26 M ----

M M M M M M M M

m- - m m m - m m m - m m m TABLE 6-11(Continued)

CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2011 Results in Units of pCi/liter +/- 1 Sigma Sample Location

• No.77 (Control)

Date 1-131 Cs-134 Cs-137 K-40 Ba/La- 140 Others t 04/11/11 < 0.470 < 6.96. < 7.73 1540 +/- 83.2 < 7.87 <LLD 04/25/11 < 0.519 < 4.9.1 < 5.71 1567 +/- 84.0. < 7.36 <LLD 05/09/11 < 0.430 < 7.53 < 4.61 1458 + 67.4 < 6.76 <LLD 05/23/11 < 0.540 < 8.19 < 7.37 1340 + 73.9 < 7.22 <LLD 06/06/11 < 0.642 < 8.09 < 5.71 1385 +/- 68.1 < 4.65 <LLD 06/20/11 < 0.629 < 5.66 < 8.34 1762. +/- 103.9 < 8.96 <LLD 07/11/11 < 0.729 < 8.87 < 6.20 1588. +/- 84.3 < 8.03 <LLD 07/27/11 < 0.522 < 9.08 < 6.46 1540 +/- 84.8 < 7.88 <LLD 08/08/11 < 0.801 < 10.59 < 11.09 1543. +/- 100.5 < 6.92 <LLD 08/22/11 < 0.412 < 4.67 < 6.87 1506 +/- 84.7 < 6.89 <LLD 09/06/11 < 0.415 < 8.94- < 7.90 1815 + 93.0 < 8.20 <LLD 09/19/11 < 0.638 < 4.27 < 5.41 1545 +/- 71.0 < 6.15 <LLD 10/03/11 < 0.584 < 3.95 < 6.36 1413 +/- 68.1 < 6.47 <LLD 10/17/11 < 0.562 < 4.33 < 6.33 1651 +/- 79.7 < 5.62 <LLD 11/07/11 < 0.712 < 9.05 < 7.47 1603 +/- 87.3 < 8.72 <LLD 11/21/11 < 0.575 < 4.25 < 5.86 1391 +/- 66.8 < 6.34 <LLD 12/06/11 < 0.699 < 11.37 < 10.03 1662 +/- 101.0 < 10.35 <LLD 12/19/11 < 0.814 < 4.30 <.5.05 1392 +/- 68.4 < 4.08 <LLD

• Sample Location is required by the ODCM

• • • Corresponds to Sample Location noted on Figure 3.3-4 t Plant related radionuclides 6 - 27

'TABLE 6-12 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCTS - 2011 Results in Units of pCi/kg (wet) + 1 sigma Location *** Date Description Be-7 K-40 1-131 Cs-134 Cs-137 Zn-65 C-14 Otherst 9/7/2011 Horseradish Leaves 1834 +/- 84 3905 + 161 < 18.4 < 12 < 15.2 < 34 < 3060 <LLD 145* 9/7/2011 SquashLeaves 2482 +/- 69 2523 +/- 96 < 12.7 < 10.1 < 7.9 < 24.3 - <LLD Control 9/7/2011 Tomatoes . < 46 1884 +/- 83 < 8.8 < 5.1 < 6.2 < 20.1 < 2770 <LLD 9/7/2011 Rhubarb Leaves 303 < 49 3929 +/- 163 < 18.9 < 10.6 < 13.3 < 39.5 - <LLD Location *** Date Description Be-7 K-40 1-131 Cs-134 Cs-137 Zn-65 C-14 Otherst 133* 9/6/2011 Rhubarb Leaves 266 +/- 32 3280 +/- 109 < 13.6 < 12.3 < 8.9 < 23.3 - <LLD 9/6/2011 Tomatoes 7 _ - - - < 1950 <LLD Location *** Date Description Be-7 K-40 1-131 Cs-134 Cs-137 Zn-65 C-14 Otherst 3323 + 129 .4246 + 210 < 30.8 < 16.2 < 20.5 < 54.3 <LLD 144* 9/6/2011 Com Leaves 9/6/2011 Horseradish Leaves 1656 +/- 77 < 183 < 22.4 < 11.6 < 15.1 < 40.2 <LLD 9/6/2011 Tomatoes < 54 2307 +/- 77 < 8 < 6.2 < 5.8 < 16.4 < 2910 <LLD Location *** Date Description Be-7 K-40 1-131 Cs-134 Cs-137 Zn-65 C-14 Otherst 9/6/2011 Tomatoes < 88 2309 + 114 < 17.6 < 8.4 < 10.6 < 32.6 - <LLD 484* 9/6/2011 Squash Leaves 2557 + 87 4640 +/- 162 < 20.6 < 10.1 < 12.3 < 36.6 < 2740 <LLD 9/6/2011 Brussel Sprouts 291 +/- 62 2442 + 161 < 26.6 < 13.7 < 18.5 < 44.8 - <LLD 9/6/2011 Cabbage 274 +/- 57 :2672 +/- 164 < 34.7 < 16 < 19.3 < 54.7 <LLD Date Description Be-7 [ K-40 [ 1-131 Cs-134 I Cs-137 I Zn-65 C-14 I Otherst 9/6/2011 Tomatoes < 67 2297 +97 < 10.9 < 5.2 < 7.2 < 19.2 - <LLD 9/6/2011 Grape Leaves 2016 -+/- 87 3551 + 161 < 21.4 < 13.6 < 16.4 < 38.2 < 3000 <LLD

• Sample Location Required by the ODCM

• • Sample Location is Optional

• • • Corresponds to Sample Location noted on Figure 3.3-5 t Plant Related Radionuclides 6 - 28 M M m - m m M m m M- M M m M MM

M MmmmmmmmMM MM TABLE 6-13 MILK ANIMAL CENSUS - 2011 Town or Location Distance(2) Number of Area(a) DesignationO') Degrees(2) (Miles) Milk Animals Scriba 62 1840 6.6 0 9 98 4.8 40C New Haven 64 108 7.8 26C 78 128° 8.0 19C 14 125 9.1 55C 60 91 .9.5 0 55* 97 8.8 54C Mexico0 21 112' 10.4 61C 72 1000 9.6 34C 50 93 8.7 0 Granby 77"* 1900 16.0 63C (Control)

MILKING ANIMAL TOTALS: 352 Cows (including control locations) 0 Goats MILKING ANIMAL TOTALS: 289 Cows (excluding control locations) 0 Goats NOTES:

C Cows G Milking Goats

• Milk sample location

• Milk sample control location (1) Reference Figure 3.3-4 -

(2) Degrees and distance are based on NMP-2 Reactor Building centerline (a) Census performed out to a distance of approximately 10 miles 6 - 29

TABLE 6-14 RESIDENCE CENSUS - 2011 Meteorological Map Sector Location Location(a) Degrees~b Distance~b N

• NNE

• NE

• ENE *-

E West Sunset Bay /Lake Road A 1000 1.3 miles ESE Lake Road B 1040 1.1 miles SE County Route 29 C 1250 1.4 miles SSE County Route 29 / Miner Road D 1580 1.7 miles S Miner Road E 1710 1.6 miles SSW Lakeview Road F 2080 1.2 miles SW Lakeview Road G 2170 1.1 miles WSW Bayshore Drive H 2370 1.4 miles W

• WNW

• NW

• NNW

• NOTES:

• This meteorological sector is over Lake Ontario. There is no residence within five miles (a) Corresponds to Figure 3.3-5 (b) Degrees and distance are based on NMP-2 Reactor Building centerline 6 -30 M - m M - - - - M - M M MMMMMMM

7.0 HISTORICAL DATA TABLES Sample Statistics from Previous Environmental Sampling The mean, minimum value and maximum value were calculated for selected sample mediums and isotopes.

Special Considerations-

1. Sample data listed as 1969 was taken from the NINE MILE POINT, PREOPERATION SURVEY, 1969 and ENVIRONMENTAL MONITORING REPORT FOR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION, NOVEMBER, 1970.

2. Sample results listed as 1974 and 1975 were taken from the respective Annual Radiological Environmental Operating Reports for Nine Mile Point Unit 1 Nuclear Station. Sample results listed as 1986 through the current year were taken from the respective Nine Mile point Nuclear Power Station Annual Radiological Environmental Operating Reports.

3. Only measured values were used for statistical calculations.

7-1

I I

TABLE 7-1 I

HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT (CONTROL) ('A I I

MIN.

Co-60 (pCi/g (dry))

MAX.

I--

MEAN I

I P 1979@)

1980 0.22 0,07 0.22 0.09 0.22 0.08 LLD LLD LLD LLD LLD LLD I

1981 LLD LLD LLD LLD LLD LLD 1982 1983 1984 0.05 LLD LLD 0.05 LLD LLD 0.05 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1985 1986 1987 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1988 LLD LLD LLD LLD LLD LLD 1989 1990 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1991 LLD LLD LLD LLD LLD LLD 1992 1993 1994 LLD 0.03 LLD LLD 0.03 LLD LLD 0.03 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1995 1996 1997 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1998 LLD LLD LLD LLD LLD LLD 1999 2000 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2001 LLD LLD LLD LLD LLD LLD 2002 2003 2004 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2005 2006 2007 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2008 LLD LLD LLD LLD LLD LLD 2009 2010 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2011 LLD LLD LLD LLD LLD LLD a J. I I (a) Control location was at an area beyond the influence of the site (westerly direction).

I I

(b) Sampling was initiated in 1979. Sampling was not required prior to 1979.

I I

7-2 1

TABLE 7-2 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT (INDICATOR) (a)

Cs-137 (pCi/g(drv) Co-60 (pCi/g ( .

YEAR MIN. MAX. MEEAN N4N. MAX. MEAN 1985(b) LLD LLD LLD LLD LLD LLD 1986 LLD LLD LLD LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD 1989 0.25 0.34 0.30 LLD LLD LLD 1990 0.28 0.28 0.28 LLD LLD LLD 1991 0.11 0.16 0.14 LLD LLD LLD 1992 0.10 0.16 0.13 LLD LLD LLD 1993 0.17 0.49 0.33 LLD LLD LLD 1994 0.08 0.39 0.24 LLD LLD LLD 1995 0.16 0.17 0.16 LLD LLD LLD 1996 0.13 0.18 0.16 LLD LLD LLD 1997 0.13 0.18 0.16 LLD LLD LLD 1998 0.07 0.07 0.07 LLD LLD LLD 1999 0.06 0.09 0.08 LLD LLD LLD 2000 0.06 0.08 0.07 LLD LLD LLD 2001 0.06 0.07 0.07 LLD LLD LLD 2002 0.05 0.05 0.05 LLD LLD LLD 2003 0.04 0.05 0.05 LLD LLD LLD 2004 0.04 0.04 0.04 LLD LLD LLD 2005 0.06 0.09 0.08 LLD LLD LLD 2006 0.06 0.06 0.06 LLD LLD LLD 2007 0.04 0.04 0.04 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 (a) Location was offsite at Sunset Beach (closest location with recreational value).

(b) Sampling initiated in 1985 as required by Technical Specifications requirements.

7-3

I TABLE 7-3 I HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH (CONTROL) (a) I I

V MEAN I

1976 1977 1.2 0.13 1.2 0.13 1.2 0.13 I

1978 0.04 0.20 0.09 1979 1980 1981 0.03 0.03 0.028 0.06 0.11 0.062 0.04 0.06 0.043 I

1982 0.027 1983 1984 0.041 0.015 0.055 0.057 0.038 0.046 0.049 0.032 I

1985 0.026 0.047 0.034 1986 1987 0.021 0.017 0.032 0.040 0.025 0.031 I

1988 0.023 0.053 0.033 1989 1990 1991 0.020 0.025 0.016 0.033 0.079 0.045 0.029 0.043 0.030 I

1992 1993 1994 0.019 0.023 0.012 0.024 0.041 0.035 0.022 0.032 0.024 I

1995 0.014 0.020 0.016 1996 1997 0.014 0.019 0.018 0.043 0.016 0.031 I

1998 0.013 0.013 0.013 1999 2000 2001 LLD 0.021 LLD LLD 0.021 LLD LLD 0.021 LLD I

2002 LLD LLD LLD 2003 2004 LLD LLD LLD LLD LLD LLD I

2005 LLD LLD LLD 2006 2007 LLD LLD LLD LLD LLD LLD I

2008 LLD LLD LLD 2009 2010 2011 LLD LLD LLD LLD LLD LLD LLD LLD LLD I

(a) Control location was at an area beyond the influence of the site (westerly direction).

I I

7-4

TABLE 7-4 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH (INDICATOR) (')

Cs-137_(pCi/g (wet))

YEAR MIN. MAX. MEAN 1976 0.5 3.9 1.4 1977 0.13 0.79 0.29 1978 0.03 0.10 0.08 1979 0.02 0.55 0.10 1980 0.03 0.10 0.06 1981 0.03 0.10 0.06 1982 0.034 0.064 0.048 1983 0.033 0.056 0.045 1984 0.033 0.061 0.043 1985 0.018 0.044 0.030 1986 0.009 0.051 0.028 1987 0.024 0.063 0.033 1988 0.020 0.074 0.034 1989 0.020 0.043 0.035 1990 0.024 0.115 0.044 1991 0.021 0.035 0.027 1992 0.013 0.034 0.026 1993 0.021 0.038 0.030 1994 0.011 0.028 0.020 1995 0.016 0.019 0.018 1996 0.014 0.016 0.015 1997 0.015 0.017 0.016 1998 0.021 0.021 0.021 1999 0.016 0.018 0.017 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 (a) Indicator locations are in the general area of the NMP1 and J. A. FitzPatrick cooling water discharge structures.

7-5

I I

TABLE 7-5 I HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER (CONTROL) (a)

I f(¶ 1 '217 i-l I r..L Uo- O I

V (.IiIZI MAY MPAVA

-~ -- i---. ~

1976 (b) (b) (b) (b) (b) (b) 1977 (c) 1978 LLD (c)

LLD (c)

LLD (c)

(c)

(c)

(c)

(c)

(c)

I 1979 2.5 2.5 2.5 LLD LLD LLD 1980 LLD LLD LLD LLD LLD LLD 1981 LLD LLD LLD 1.4 1.4 1.4 I 1982 LLD LLD LLD LLD LLD LLD 1983 1984 1985 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD i

1986 LLD LLD LLD LLD LLD LLD 1987 1988 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1989 LLD LLD LLD LLD LLD LLD 1990 1991 1992 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1993 1994 1995 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

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 2005 2006 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2007 2008 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2009 LLD LLD LLD LLD LLD LLD 2010 2011 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD i (a) Location was the City of Oswego Water Supply for 1976 - 1984, and the Oswego Steam Station (b) inlet canal for 1985 - 2011.

No gamma analyses performed (not required). I (c) Data showed instrument background results.

I 7-6 I

TABLE 7-6 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER (INDICATOR) (a)

Cs-137 (pCi/liter) Co-60 (pCi/liter)

YEAR N [* MI MI. I I MAX. MEAN 1976 (b) (b) (b) (b) (b) (b) 1977 (c) (c) (c) (c) (c) (c) 1978 LLD LLD LLD (c) (c) (c) 1979 LLD LLD LLD LLD LLD LLD 1980 LLD LLD LLD LLD LLD LLD 1981 LLD LLD LLD LLD LLD LLD 1982 0.43 0.43 0.43 1.6 2.4 1.9 1983 LLD LLD LLD LLD LLD LLD 1984 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 LLD LLD LLD LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD 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 (a) Location was the J. A. FitzPatrick inlet canal.

(b) No gamma analyses performed (not required).

(c) Data showed instrument background results.

7-7

I I

TABLE 7-7 I

HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM (CONTROL) (')

I I (pCi/liter)

MAX. 4.

MEAN I 1976 440 929 652 1977 1978 300 215 530 490 408 304 I

1979 174 308 259 1980 1981 1982 211 211 112 290 328 307 257 276 165 I

1983 230 280 250 1984 1985 190 230 220 370 205 278 I

1986 250 550 373 1987 1988 140 240 270 460 210 320 I

1989 180 660 373 1990 1991 1992 260 180 190 320 200 310 290 190 242 I

1993 160 230 188 1994 1995 250 230 250 230 250 230 I

1996 LLD LLD LLD 1997 1998 LLD 190 LLD 190 LLD 190 I

1999 220 510 337 2000 2001 2002 196 LLD LLD 237 LLD LLD 212 LLD LLD i

2003 LLD LLD LLD 2004 LLD LLD LLD 2005 LLD LLD LLD 2006 LLD LLD LLD 2007 2008 LLD LLD LLD LLD LLD LLD I

2009 LLD LLD LLD 2010 2011 LLD LLD 1 LLD LLD 4 LLD LLD I (a) Control location is the City of Oswego drinking water for 1976 - 1984, and the Oswego Steam Station inlet canal for 1985 - 2011.

I 7-8

TABLE 7-8 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM (INDICATOR) (")

TRITIUM (pCi/hter)

YEAR M.MAX. MAN 1976 365 889 627 1977 380 530 455 1978 377 560 476 1979 176 276 228 1980 150 306 227 1981 212 388 285 1982 194 311 266 1983 249 560 347 1984 110 370 280 1985 250 1200 (b) 530 1986 260 500 380 1987 160 410 322 1988 430 480 460 1989 210 350 280 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 (a) Indicator location is the FitzPatrick inlet canal.

(b) Suspect sample contamination. Recollected samples showed normal levels of tritium.

7-9

I I

TABLE 7-9 I HISTORICAL ENVIRONMENTAL SAMPLE DATA GROUNDWATER TRITIUM (CONTROL) (s) I

'YEAR MIN.

TRITIUM MAX.

Ci/liter)

MEAN I

2005 <854 <854 <854 2006(b) 2007

<447

<442

<825

<445

<636

<444 I

2008 <427 <439 <431 2009 2010

<411

<172

<418

<410

<415

<341 I

2011 <408 <424 <415 (a)

(b)

Control well locations (2) are upland wells located south of protected area.

Required LLD changed to 500 pCi/1 from 1000 pCi/l I

I I

I I

I I

I I

I 7-10 I

I

TABLE 7-10 HISTORICAL ENVIRONMENTAL SAMPLE DATA GROUNDWATER TRITIUM (INDICATOR) (a)

TRITIUM (pCi/liter)

YEAR MIN. MAX.. NEAN 2005 <854 <871 <863 20061b) <462 <933 <823 2007 <440 <461 <445 2008 <427 <439 <433 2009 <406 <424 <413 2010 <287 61l(c) <384 2011 <407 <428 <414 (a) Indicator locations are down gradient wells located in the owner control area and samples collected from the NMP2 depression cone system.

(b) Required LLD changed to 500 pCi/l from 1000 pCi/l (c) Re-sample tritium concentration = <268 pCi/l 7-11

I I

TABLE 7-11 I HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA (CONTROL) (') I I GROSS BETA (pCi/m3)

MAX.

Y MEAN I

~-1* 1~

1977 1978 0.001 0.01 0.484 0.66 0.125 0.16 I

1979 0.010 0.703 0.077 1980 1981 1982 0.009 0.016 0.011 0.291 0.549 0.078 0.056 0.165 0.033 I

1983 0.007 0.085 0.024 1984 1985 0.013 0.013 0.051 0.043 0.026 0.024 I

1986 0.008 0.272 0.039 1987 1988 0.009 0.008 0.037 0.039 0.021 0.018 I 1989 0.007 0.039 0.017 1990 1991 1992 0.003 0.006 0.006 0.027 0.028 0.020 0.013 0.014 0.012 I

1993 0.007 0.022 0.013 1994 1995 0.008 0.006 0.025 0.023 0.015 0.014 I

1996 0.008 0.023 0.014 1997 1998 0.006 0.004 0.025 0.034 0.013 0.014 I 1999 0.010 0.032 0.017 2000 2001 2002 0.006 0.006 0.008 0.027 0.034 0.027 0.015 0.016 0.016 I

2003 0.004 0.032 0.015 2004 2005 0.008 0.008 0.032 0.034 0.016 0.019 I

2006 0.007 0.033 0.016 2007 2008 0.008 0.007 0.028 0.031 0.016 0.015 I 2009 0.006 0.032 0.016 2010 2011 I 0.004 0.008 I 0.026 0.034 1 0.014 0.018 I (a) Locations used for 1977 - 1984 were C off-site, D1 off-site, D2 off-site, E off-site, F off-site, and G off-site. Control location R-5 off-site was used for 1985 - 2010 (formerly C offsite location). I I

7- 12 I

TABLE 7-12 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA (INDICATOR) (a)

GROSS BETA (pCi/m3)

.YEAR I ý IN.. .... I . IMEA 1977 0.002 0.326 0.106 1978 0.01 0.34 0.11 1979 0.001 0.271 0.058 1980 0.002 0.207 0.044 1981 0.004 0.528 0.151 1982 0.001 0.113 0.031 1983 0.002 0.062 0.023 1984 0.002 0.058 0.025 1985 0.010 0.044 0.023 1986 0.007 0.289 0.039 1987 0.009 0.040 0.021 1988 0.007 0.040 0.018 1989 0.007 0.041 0.017 1990 0.005 0.023 0.014 1991 0.007 0.033 0.015 1992 0.005 0.024 0.013 1993 0.005 0.025 0.014 1994 0.006 0.025 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 0.037 0.016 2005 0.007 0.040 0.018 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 0.016 2011 0.007 0.034 0.018 (a) Locations used for 1977 - 1984 were DI onsite, D2 onsite, E onsite, F onsite, G onsite, H onsite, I onsite, J onsite, and K onsite as applicable. 1985 - 2010 locations were R-1 offsite, R-2 offsite, R-3 offsite, and R-4 offsite.

7-13

I i

TABLE 7-13 HISTORICAL ENVIRONMENTAL SAMPLE DATA I

AIR PARTICULATES (CONTROL) (a)

Cs-137 (tCi/m3) Co-60 (DCi/m 3 )

I 1977 1978 0.0002 0.0008 0.0112 0.0042 0.0034 0.0018 0.0034 0.0003 0.0347 0.0056 0.0172 0.0020 I

1979 0.0008 0.0047 0.0016 0.0005 0.0014 0.0009 1980 0.0015 0.0018 0.0016 LLD LLD LLD 1981 0.0003 0.0042 0.0017 0.0003 0.0012 0.0008 1982 1983 0.0002 0.0002 0.0009 0.0002 0.0004 0.0002 0.0004 0.0007 0.0007 0.0007 0.0006 0.0007 I

1984 LLD LLD LLD 0.0004 0.0012 0.0008 1985 1986 1987 LLD 0.0075 LLD LLD 0.0311 LLD LLD 0.0193 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1988 LLD LLD LLD LLD LLD LLD 1989 1990 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1991 LLD LLD LLD LLD LLD LLD 1992 1993 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1994 LLD LLD LLD LLD LLD LLD 1995 1996 1997 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1998 LLD LLD LLD LLD LLD 1999 2000 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2001 LLD LLD LLD LLD LLD LLD 2002 2003 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD i

2004 LLD LLD LLD LLD LLD LLD 2005 2006 2007 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2008 LLD LLD LLD LLD LLD LLD 2009 2010 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2011 LLD LLD LLD LLD LLD LLD (a) Locations included composites of C, D1, E, F, and G offsite air monitoring locations for 1977 - 1984.

Sample location included only R-5 air monitoring location for 1985 - 2011.

I 7- 14

TABLE 7-14 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES (INDICATOR) (a)

SICs-137 (pCi/m3 ) j o6 (pCi/rn)__ _ _

1977 0.0001 0.0105 0.0043 0.0003 0.0711 0.0179 1978 0.0003 0.0026 0.0016 0.0003 0.0153 0.0023 1979 0.0003 0.0020 0.0010 0.0003 0.0007 0.0005 1980 0.0005 0.0019 0.0011 0.0016 0.0016 0.0016 1981 0.0002 0.0045 0.0014 0.0002 0.0017 0.0006 1982 0.0001 0.0006 0.0004 0.0003 0.0010 0.0005 1983 0.0002 0.0003 0.0002 0.0003 0.0017 0.0007 1984 LLD LLD LLD 0.0007 0.0017 0.0012 1985 LLD LLD LLD LLD LLD LLD 1986 0.0069 0.0364 0.0183 LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD 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 (a) Locations included composites of D1, D2, E, F, G, H, I, J, and K onsite air monitoring locations for 1977 - 1984. Locations included R-1 through R-4 air monitoring locations for 1985 - 2011.

7-15

I I

TABLE 7-15 HISTORICAL ENVIRONMENTAL SAMPLE DATA I

AIR RADIOIODINE (CONTROL) (i)

I E-131 (pCi/m3)

I I

1976 0.01 MAX.

5.88 MEAN 0.60 I

1977 1978 1979 0.02 0.03 LLD 0.82 0.04 LLD 0.32 0.03 LLD I

1980 LLD LLD LLD 1981 1982 LLD 0.039 LLD 0.039 LLD 0.039 I

1983 LLD LLD LLD 1984 1985 1986 LLD LLD 0.041 LLD LLD 0.332 LLD LLD 0.151 I

1987 LLD 1988 1989 LLD LLD LLD LLD LLD LLD LLD LLD I

1990 LLD LLD LLD 1991 1992 LLD LLD LLD LLD LLD LLD I

1993 LLD LLD LLD 1994 1995 1996 LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1997 1998 1999 LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2000 LLD LLD LLD 2001 2002 LLD LLD LLD LLD LLD LLD I

2003 LLD LLD LLD 2004 2005 2006 LLD LLD LLD LLD LLD LLD LLD LLD LLD i

2007 2008 2009 LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2010 LLD LLD LLD 2011 0.034(b) 0.093P")

0.055(b)

I (a) Locations D1 off-site, D2 off-site, E off-site, F off-site, and G off-site used for 1976 - 1984.

(b)

Location R-5 off-site used for 1985 - 2011.

1-131 concentration attributed to fallout from the Fukushima Daiichi Nuclear Station accident. I 7-16 I

TABLE 7-16 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE (INDICATOR) (a)

IOflTNP-1 ~ 1 (nCi/m3 ~

YEAR NUN. MAX. MEAN 1976 0.01 2.09 0.33 1977 0.02 0.73 0.31 1978 0.02 0.07 0.04 1979 LLD LLD LLD 1980 0.013 0.013 0.013 1981 0.016 0.042 0.029 1982 0.002 0.042 0.016 1983 0.022 0.035 0.028 1984 LLD LLD LLD 1985 LLD LLD LLD 1986 0.023 0.360 0.119 1987 0.011 0.018 0.014 1988 LLD LLD LLD 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 0.0210") 0.11(b) 0.055_b)

(a) Locations used for 1976 - 1984 were DI on-site, D2 on-site, E on-site, F on-site, G on-site, H on-site, I on-site, J on-site, and K on-site, as applicable. Locations used for 1985 - 2011 were R1 off-site, R-2 off-site, R-3 off-site, and R-4 off-site.

(b) 1-131 concentration attributed to fallout from the Fukushima Daiichi Nuclear Station accident.

7-17

TABLE 7-17 I HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (CONTROL) (a) I 1969 (b) (b)

MEAN (b)

I 1970 1971 1972 1973 6.0 2.0 2.2 2.2 7.3 6.7 6.2 6.9 6.7 4.3 4.4 4.7 I

1974 1975 1976 1977 2.7 4.8 3.2 4.0 8.9 6.0 7.2 5.6 5.5 5.4 5.3 I

8.0 1978 1979 1980 3.3 3.3 3.8 4.7 5.7 5.8 4.3 4.7 4.9 I

1981 3.5 5.9 4.8 1982 1983 1984 1985 3.8 4.9 4.7 4.5 (4.4)*

6.1 7.2 8.2 7.6 (6.8)*

5.1 5.8 6.2 5.6 (5.4)*

I 1986 1987 1988 5.3 (5.5)*

4.6 (4.6)*

4.4 (4.8)*

7.5 (7.2)*

6.6 (5.8)*

6.8 (6.8)*

6.3 (6.3)*

5.4 (5.2)*

5.6 (5.4)*

I 1989 2.9 (2..9)* 6.4 (5.6)* 4.7 (4.6)*

1990 1991 1992 3.7 (3.7)*

3.8 (3.8)*

2.6 (2.6)*

6.0 (5.9)*

5.4 (5.3)*

5.0 (4.7)*

4.8 (4.6)*

4.5 (4.3)*

4.1 (3.9)*

I 1993 3.4 (3.4)* 5.6 (5.2)* 4.4 (4.3)*

1994 1995 1996 3.1 (3.1)*

3.4 (3.4)*

3.4 (3.4)*

5.0 (4.6)*

5.7 (4.9)*

5.6 (5.6)*

4.1 (3.9)*

4.4 (4.2)*

4.3 (4.2)*

I 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 (4.4)* 4.1 (4.0)*

2007 3.2 (3.2)* 5.8 (5.3)* 4.4 (4.3)*

2008 3.3(3.3)* 5.1(4.8)* 4.1(4.0)*

2009 3.2(3.2)* 4.8(4.2)* 3.9(3.7)*

2010 2.7(2.7)* 4.6(4.1)* 3.9(3.6)*

2011 2.6(2.6)*

(a) TLD #8, 14, 49, 111 and 113 where applicable.

5.5(4.7)* 4.0(3.8)*

I (b) Data not available.

(*) TLD result based on the ODCM required locations (TLD #14 and 49).

I 7-18 I

I

TABLE 7-18 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (SITE BOUNDARY) (')

DOSE (mrem ner standard month)

YEAR MIN. MAX MAN 1985(b) 4.1 12.6 6.2 1986 4.4 18.7 7.0 1987 4.4 14.3 6.1 1988 3.4 17.9 6.4 1989 2.8 15.4 5.9 1990 3.6 14.8 5.8 1991 3.2 16.7 5.7 1992 3.2 10.4 4.8 1993 3.3 11.6 5.3 1994 2.8 12.4 5.2 1995 3.5 9.6 5.4 1996 3.2 9.1 5.2 1997 3.5 10.2 5.9 1998 3.7 9.4 5.4 1999 3.3 12.3 5.8 2000 3.6 10.0 5.5 2001 3.6 10.3 5.7 2002 3.5 9.4 5.4 2003 3.2 8.9 5.4 2004 3.3 10.8 5.6 2005 3.4 9.2 5.5 2006 3.5 9.2 5.4 2007 3.2 9.0 5.6 2008 3.2 8.8 5.2 2009 3.1 11.7 5.4 2010 3.3 12.1 5.4 2011 3.1 11.6 5.5 (a) TLD locations initiated in 1985 as required by the new Technical Specifications. Includes TLD numbers 7, 18, 23, 75, 76, 77, 78, 79, 80, 81, 82, 83, 84, 85, 86, and 87.

Q2) Not required prior to 1985.

7- 19

a TABLE 7-19 I

HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (OFF-SITE SECTORS) (') I I month)

MEAN U

4 1985(') 4.0 7.1 5.0 1986 4.6 8.6 6.0 1987 1988 4.3 3.8 6.0 7.0 5.2 5.3 I

1989 2.5 6.8 4.9 1990 1991 1992 3.6 3.6 6.3 5.6 4.7 4.5 I 2.9 5.0 4.1 1993 1994 1995 3.4 3.0 3.2 6.3 5.1 5.2 4.5 4.0 4.2 a

1996 1997 1998 3.2 3.5 3.5 5.3 5.8 5.0 4.2 4.5 4.2 I

1999 3.6 5.6 4.4 2000 2001 2002 3.4 3.6 3.1 6.6 5.4 5.3 4.5 4.4 4.2 I

2003 2004 2005 3.4 3.2 3.2 4.8 6.7 4.7 4.1 4.4 4.0 I

2006 2007 2008 3.3 3.1 3.2 4.4 5.1 4.5 4.0 4.2 3.8 I

2009 3.3 4.5 3.9 2010 3.0 4.4 3.9 2011 3.0 5.2 4.0 (a) TLD locations initiated in 1985 as required by the new Technical Specifications. Includes TLD numbers 88, 89, 90, 91, 92, 93, 94, and 95.

(b) Not required prior to 1985.

I I

7 - 20 I

I

TABLE 7-20 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (SPECIAL INTEREST) ( 'b)

DOSE (mrem per standard month)

YEAR MIN MAX. MEAN 1985(c) 3.9 6.8 5.3 1986 4.8 8.2 6.1 1987 3.5 6.0 5.1 1988 3.9 6.6 5.3 1989 2.1 7.0 4.8 1990 3.2 6.3 4.7 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 4.0 1995 3.4 4.9 4.3 1996 3.2 5.3 4.2 1997 3.5 5.4 4.5 1998 3.7 4.9 4.3 1999 3.6 5.5 4.4 2000 3.6 6.3 4.5 2001 3.8 5.0 4.3 2002 3.5 4.7 4.1 2003 3.4 5.0 4.2 2004 3.0 5.9 4.2 2005 3.4 4.7 3.9 2006 3.5 4.6 4.0 2007 3.0 5.1 4.2 2008 3.1 4.6 3.9 2009 3.1 4.5 3.8 2010 3.2 4.7 3.8 2011 2.9 4.9 4.0 (a) TLD locations initiated in 1985 as required by the new Technical Specifications. TLD's included are numbers 15, 56, 58, 96, 97 and 98.

(b) TLD locations include critical residences and populated areas near the site.

(c) Not required prior to 1985.

7-21

I I

TABLE 7-21 I HISTORICALENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (ON-SITE INDICATOR) (a)

I.

DOSE (mrem per standard month)

I

~YEAR 1969

-MIN.

(b)

MAK (b)

MIEAN (b)

I 1970 1971 1972 1973 4.7 1.5 2.3 3.0 9.0 7.7 8.2 24.4 6.0 4.7 4.9 I

6.6 1974 1975 1976 3.1 4.6 3.7 10.6 16.0 18.8 5.7 7.3 6.9 I

1977 3.0 15.3 5.7 1978 1979 1980 3.0 2.7 3.9 9.0 8.3 12.0 4.3 4.3 5.3 I

1981 4.1 11.8 5.8 1982 1983 1984 3.9 5.0 4.6 13.0 16.5 13.2 6.3 6.9 7.0 I

1985 4.7 15.9 6.3 1986 1987 1988 4.7 4.0 4.4 16.1 11.4 11.9 7.0 5.8 6.0 I

1989 2.7 14.5 6.0 1990 1991 1992 3.6 3.2 3.2 12.9 11.6 5.6 5.5 5.1 4.3 I

1993 3.1 13.6 5.2 1994 1995 1996 2.8 3.5 3.1 14.3 28.6 32.6 5.1 6.2 6.4 I

1997 3.5 1

28.8 7.7 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 2003 2004 3.5 3.2 3.3 13.6 12.9 13.2 5.3 5.3 5.4 I

2005 3.4 14.1 2006 2007 2008 3.5 3.2 3.2 14.4 14.8 13.8 5.4 5.3 5.6 5.2 I

2009 2010 2011

• 3.1 3.3 3.1 .L 13.6 13.3 13.0 4.9 4.8 5.1 I

(a) Includes TLD numbers 3, 4, 5, 6, and 7 (1970 - 1973). Includes TLD numbers 3, 4, 5, 6, 7, 23, 24, 25, and 26 (1974 - 2011). Locations are existing or previous on-site environmental air monitoring (b) locations.

No data available. I 7 - 22 I

I

TABLE 7-22 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (OFF-SITE INDICATOR) (a)

DOSE (mrem per standard month)

YEAR N11N .[M 4AX. NIk 1969 (b) (b) (b) 1970 5.0 8.0 6.7 1971 1.1 7.7 4.5 1972 1.8 6.6 4.4 1973 2.2 6.9 4.1 1974 2.4 8.9 5.3 1975 4.5 7.1 5.5 1976 3.4 7.2 5.2 1977 3.7 8.0 5.3 1978 2.7 4.7 3.7 1979 3.0 5.7 4.0 1980 3.1 5.8 4.6 1981 3.6 5.9 4.7 1982 4.0 6.2 5.2 1983 4.6 7.2 5.6 1984 4.6 8.2 6.1 1985 4.6 7.7 5.5 1986 5.0 7.6 6.1 1987 4.4 6.6 5.2 1988 4.2 6.6 5.4 1989 2.8 6.4 4.6 1990 3.8 6.0 4.8 1991 3.4 5.4 4.3 1992 3.1 5.2 4.1 1993 3.2 5.6 4.3 1994 3.0 5.0 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 4.4 1999 3.8 7.1 4.6 2000 3.8 7.3 4.6 2001 3.7 5.9 4.5 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 5.8 4.5 2008 3.3 5.1 4.1 2009 3.3 4.8 3.9 2010 3.5 4.6 3.8 2011 3.2 5.5 4.1 (a) Includes TLD numbers 8, 9, 10, 11, 12, and 13 (off-site environmental air monitoring locations).

(b) No data available.

7 - 23

I TABLE 7-23 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK (CONTROL) i Cs-137 (pCi/liter) 1-131 (Ci/literI YEA1 MIN. MAX. MEAN M(N. MAX (EAN 1976 (b) (b) (b) (b) (b) (b) 1977 (b) (b) (b) (b) (b) (b) 1978 2.4 7.8 5.8 LLD LLD LLD 1979 LLD LLD LLD LLD LLD LLD 1980 3.6 5.6 4.5 1.4 1.4 1.4 1981 1982 3.9 LLD 3.9 LLD 3.9 LLD LLD LLD LLD LLD LLD LLD I

1983 1984 1985 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1986 5.3 12.4 8.4 0.8 29.0 13.6 1987 LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD 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 LLD LLD LLD LLD LLD I

2004 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 (a) Location used was an available milk sample location in a least prevalent wind direction greater than (b) ten miles from the site.

No data available (samples not required).

I 7 -24 I

I

TABLE 7-24 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK (INDICATOR) (a)

Cs-137 (pCi/liter 1-131 (pCi/liter) . . ...

-YEAR MIN. MAX MEAN. MIN. MIAX. MIEAN 1976 4.0 15.0 9.3 0.02 45.00 3.20 1977 11.0 22.0 17.1 0.01 49.00 6.88 1978 3.4 33.0 9.9 0.19 0.19 0.19 1979 3.2 53.0 9.4 LLD LLD LLD 1980 3.2 21.0 8.1 0.3 8.8 3.8 1981 3.5 29.0 8.6 LLD LLD LLD 1982 3.5 14.0 5.7 LLD LLD LLD 1983 3.3 10.9 7.2 LLD LLD LLD 1984 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 6.1 11.1 8.6 0.3 30.0 5.2 1987 5.5 8.1 6.8 LLD LLD LLD 1988 10.0 10.0 10.0 LLD LLD LLD 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 0.50 0.50 0.50 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 (a) Locations sampled were available downwind locations within ten miles with high radionuclide deposition potential.

7 - 25

I TABLE 7-25 I HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS (CONTROL) (a) I I

,MEAN i

-I 1980 1981 0.02 LLD 0.02 LLD 0.02 LLD I 1982 LLD LLD LLD 1983 1984 1985 LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1986 1987 1988 LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1989 LLD LLD LLD 1990 1991 LLD LLD LLD LLD LLD LLD I 1992 LLD LLD LLD 1993 1994 1995 0.007 LLD LLD 0.007 LLD LLD 0.007 LLD LLD I

1996 LLD 1997 1998 LLD LLD LLD LLD LLD LLD LLD LLD I

1999 LLD LLD LLD 2000 2001 LLD LLD LLD LLD LLD LLD I

2002 LLD LLD LLD 2003 2004 2005 LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2006 2007 2008 LLD LLD LLD LLD LLD LLD LLD LLD LLD 3

2009 LLD LLD LLD 2010 2011 LLD LLD LLD LLD LLD LLD I

(a)

(b)

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

Data comprised of broadleaf and non-broadleaf vegetation (1980 - 1984, 2007 - 2009, & 2011).

I (c) Data comprised of broadleaf vegetation only (1985 - 2006 & 2010).

I I

7 -26

TABLE 7-26 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS (INDICATOR) (')

Cs-137 (pCi/g (wet))

YEpileXc) I MIN.. _1 I, ME-AAN 1976 LLD LLD LLD 1977 LLD LLD LLD 1978 LLD LLD LLD 1979 0.004 0.004 0.004 1980 0.004 0.060 0.036 1981 LLD LLD LLD 1982 LLD LLD LLD 1983 LLD LLD LLD 1984 LLD LLD LLD 1985 0.047 0.047 0.047 1986 LLD LLD LLD 1987 LLD LLD LLD 1988 0.008 0.008 0.008 1989 0.009 0.009 0.009 1990 LLD LLD LLD 1991 0.040 0.040 0.040 1992 LLD LLD LLD 1993 LLD LLD LLD 1994 0.004 0.011 0.008 1995 0.010 0.012 0.011 1996 LLD LLD LLD 1997 0.012 0.012 0.012 1998 LLD LLD LLD 1999 0.008 0.008 0.008 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 (a) Indicator locations were available downwind locations within ten miles of the site and with high radionuclide deposition potential.

(b) Data comprised of broadleaf and non-broadleaf vegetation (1976 - 1984, 2007 - 2009, & 2011).

(c) Data comprised of broadleaf vegetation only (1985 - 2006 & 2010).

7 -27

I 8.0 QUALITY ASSURANCE / QUALITY CONTROL PROGRAM 8.1 PROGRAM DESCRIPTION The Offsite Dose Calculation Manuals (ODCM), for Nine Mile Point Unit 1 (NMP 1) and Nine Mile Point Unit 2 (NMP2), Part II, Section 4.0 requires that the licensee participate in an Interlaboratory Comparison Program.

The Interlaboratory Comparison Program shall include sample media for which samples are routinely collected and for which comparison samples are commercially available. Participation in an Interlaboratory Comparison Program ensures that independent checks on the precision and accuracy of the measurement of radioactive material in the environmental samples are performed as part of the Quality Assurance Program for environmental monitoring. To fulfill the requirement for an Interlaboratory Comparison Program, the James A. FitzPatrick Nuclear Power Plant (JAFNPP) Environmental Laboratory has engaged the services of Eckert & Ziegler Analytics, Incorporated in Atlanta, Georgia (Analytics).

Analytics supplies sample media as blind sample spikes, which contain certified levels of radioactivity unknown to the analysis laboratory. These samples are prepared and analyzed by the JAFNPP Environmental Laboratory using standard laboratory procedures. Analytics issues a statistical summary report of the results.

The JAFNPP Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratory's performance.

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

8-1

I I

8.2 PROGRAM SCHEDULE SAMPLE PROVIDER ECKERT&IEER I

SAMPLE LABORATORY MEDI ANAYSISECKERT & ZIEGLER MEDIA Water ANALYSISANLTC Gross Beta ANALYTICS I 3

Water Tritium, 5 I Water 1-131 4 Water Mixed Gamma 4 I Air Gross Beta 3 Air 1-131 4 I Air Mixed Gamma 2 Milk 1-131 3 I Milk Mixed Gamma 3 Soil Mixed Gamma 1 I Vegetation Mixed Gamma 2 TOTAL SAMPLE INVENTORY 34 I

I 8.3 ACCEPTANCE CRITERIA Each sample result is evaluated to determine the accuracy and precision of the laboratory's analysis result. The I sample evaluation method is discussed below.

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

I 8-2

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

The value for the error resolution is calculated.

The error resolution = Reference Result Reference Results Error (1 sigma)

Using the appropriate row under the Error Resolution column below, a corresponding Ratio of Agreement interval is given.

The value for the ratio is then calculated.

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

ERROR RESOLUTION RATIO OF AGREEMENT

<4 No Comparison 4 to 7 0.5 to 2.0 8 to 15 0.6 to 1.66' 16 to 50 0.75 to 1.33 51 to200 0.8 to 1.25

>200 0.85 to 1.18 This acceptance test is generally referred to as the "NRC" method. The acceptance criteria is contained in Procedure EN-CY-102 (JAFNPP). The NRC method generally results in an acceptance range of approximately

+/- 25% of the Known value when applied to sample results from the Eckert & ZieglerAnalytics Interlaboratory Comparison Program. This method is used as the procedurally required assessment method and requires the generation of a deviation from QA/QC program report when results are unacceptable.

8-3

I 8.4 PROGRAM RESULTS

SUMMARY

The Interlaboratory Comparison Program numerical results are provided on Table 8-1. I 8.4.1 ECKERT & ZIEGLER ANALYTICS QA SAMPLES RESULTS Thirty-four QA blind spike samples were analyzed as part of Analytics 2010 Interlaboratory Comparison Program. The following sample media were evaluated as part of the comparison program.

• Air Charcoal Cartridge: 1-131

• Air Particulate Filter: Mixed Gamma Emitters, Gross Beta Water: 1-131, Mixed Gamma Emitters, Tritium, Gross Beta Soil: Mixed Gamma Emitters 3

• Milk: 1-131, Mixed Gamma Emitters

• Vegetation: Mixed Gamma Emitters 3 The JAF Environmental Laboratory performed 133 individual analyses on the 34 QA samples. Of the 133 analyses performed, 133 were in agreement using the NRC acceptance criteria for a 100% agreement ratio. i There were no nonconformities in the 2011 program.

I I

, . . , ,I 8-4

8.4.2 NUMERICAL RESULTS TABLES TABLE 8-1 INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM ANALYSIS pCi +1 sigma pCi 1 sigma RATIO (1) 06/16/2011 E7633-05 Filter 93.2 + 1.4 GROSS BETA 91.1 +/- 1.3 91.1 1.4 85.5 + 1.43 1.08 A BETA 91.7 1: 1.4 Mean= 92.0 +/- 0.8 06/16/2011 E7618-09 Filter 76.1 +/- 1.2 GROSS 79.3 +/- 1.3 72.9 1.22 1.06 A BETA 76.4 +/- 1.2 Mean = 77.3 + 0.7 12/08/2011 E8254-05 Filter 101.2 +/- 2.7 99.6 +/- 2.7 100:8 +/- 2.7 99.8 +/- 2.7 98.9 + 2.7 GROSS 97.9 +/- 2.7 105.4 +/- 2.8 89.6 +/- 1.5 1.11 A 108.3 +/- 2.8 99.7 +/- 2.7 91.4 +/- 2.7 91.4 +/- 2.7 98.1 +/- 2.8 Mean = 99.4 +/- 0.8 J kI ) Kano = KeportecLAnalytlcs. A=Acceptaole

• Sample provided by Analytics, Inc. U=Unacceptable 8-5

I TABLE 8-1 (Continued)

I INTERLABORATORY INTERCOMPARISON PROGRAM

..... _Tritium Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM ANALYSIS pCi/liter 1 sigma pCi/liter ,1 sigma RATIO (1) 3/17/2011 E7476-05 Water H-3 4314 + 163 4673 - 166

4650 .- 166 4530 - 75.7 1.00 A Mean= 4546 +/- 95 6/16/2011 E7632-05 Water H-3 833 134, 923 -- 135 905 + 15.1 0.98 A 908 135 1

Mean= 888 + 78 9/15/2011 E8121-05 Water H-3 915 , 131 1002 - 132 792 132 1.21 A 957 - 132 Mean=. 958 +/- 76 12/8/2011 E8181-09 Water H-3 10617' 209 10199 208 10900 , 182 0.94 A 10082 - 211 Mean= 10299 - 121 12/8/2011 E8182-09 Water H-3 10339 - 206 10320 208 10900 + 182 0.94 A 10090 - 210 Mean= 10250 - 120 (1) Ratio = Reported/Analytics. A=Acceptable

• Sample provided by Analytics, Inc. U=Unacceptable I

I I

I I

I I

8-6 I

I

TABLE 8-1 (Continued)

'INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-1 sigma RATIO (1)

E7479-05 Water 250.6 +/- 2.50 -.

03/17/2011 GROSS 252.2  :- 2.50 253.6 - 2.50 247 4.13 1.02 A BETA 255.2 - 2.50

.... ... ..... M ean 252.9 " 1.30 06/16/2011 E7638-05 Water 233.0 +/- 2.40

• ,GROSS 232.0 +/- 2.40 BETA 234.0 +/- 2.40

......... _ _Mean= 233.0 +/- 1.39 I 09/15/2011 E8126-05 Water GROSS BETA 253.8 256.9 250.4

+/-

+/-

+/-

3.30 3.30 3.30 249 4.16 1.02 A I 1.) Katlo = Keported/Analytics.

Mean= 253.7 - 1.90 A=Acceptafle

• Sample provided by Analytics, Inc. U=Unacceptable 8-7

I i

'TABLE 8-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM 1-131 Gamma Analysis of Air Charcoal I

SAMPLE JAFELAB RESULTS REFERENCE LAB*

DATE 3/17/2011 ID NO.

E7437-09 MEDIUM Air ANALYSIS 1-131 pCi +/-1 sigma 96.3 9

+/- 3.3 1.5 pCi 1 sigma 96.2 +/- 1.61 RATIO (1) 1.01 A I

6/16/2011 E7636-05 Air Mean=

98 97.2 95.3

+

+/-

3.2 1.57 2.7 I

1-131 100 + 2.7 86.7 + 1.45 1.08 A 9/15/2011 E8125-05 Air Mean =

86.1 93.8 80.5

+

+

2.8 1.57 3

I 1-131 Mean 83.2 84.0 82.6

+/-,

+/-

+/-

3.2 3.1 1.80 80.5 + 1.34 1.03 A I

9/15/2011 E8127-09 Air 72.3 - 4.3 1-131 I Mean =

72.1 80.6 75.0 +/-

+/-

- 4.6 2.60 80.5 + 1.34 0.93 A I

(I1) Katio = Keported/Analytlcs. A=Acceptable

• Sample provided by Analytics, Inc. U=Unacceptable 8-8

TABLE 8-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE I JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIURM ANALYSISI pCi/liter +/-1 sigma .pCi/liter +/-1 sigma RATIO (1) 3/17/2011 1 E7477-05 I Water 186 +/- 18.5 205 +/- 10 Cr-51 196.0 +/- 3.27 1.04 A 222 +/- 25.7 Mean= 204 +/- 11.1 94 +/- 3.32 Cs-134. 92 +/- 2.32 856 1.43 1.08 A 91 +/- 5.06 Mean= 92.2 +/- 2.2 143 +/- 3.86 Cs-137 142 2.49 135.0 2'.25 1.04 A 134 +/- 5.55 Mean= 140 +/- 2.4 81 +/- 2.96 Co-58 ..... 77 +/- 1.97 +/- 1.24 1.04 A 74 +/- 4.54 Mean= 77.2 +/- 1.9 187 +/- 4.33 Mn-54 183 -+/- 2.82 +/- 2.92 1.06 A 189 +/- 6.38 175.0 Mean= 186 +/- 2.7 121 +/- 4.09 128 +/- 2.83 Fe-59 115 115 +/- 6.22 6.221 115.0 +/- 1.91 1.05 A Mean = 121.0 +/- 2.7 198 +/- 7.05 Zn-65 191 +/- 4.62 172.0 +/- 2.87 1.12 A 187 +/- 10.3 Mean = 192 +/- 4.4 117 +/- 2.65 Co-60 115 1.8 113.0 +/- 1.88 1.03 A 116 +/- 3.97 Mean = 116 +/- 1.7 92.6 +/- 325 1-131 95.9 2.12 94.0 +/- 1.57 1.01 A 95.3 +/- 4.53 Mean = 94.6 +/- 1.99 90 +/- 0.95 84.1 +/- 2.19 1-131** 94.0 +/- 1.57 0.94 A 90.9 +/- 2.14 Mean= 88.3 +/- 1.1 (1) Ratio = Reported/Analytics. A=Acceptable (1) Ratio = Reported/Analytlcs.

• Sample provided by Analytics, Inc. U=Unacceptable

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

8-9

I

.... TABLE 8-1 (Continued) I INTERLABORATORY INTERCOMPARISON PROGRAM DATE SAMPLE jID NO. MEDIUM I

[ANAJAF Gamma Analvsis of Water

_ANALYSIS I ELAB RESULTS pCi/liter +/--1 sigma REFERENCE LAB*

pCi/liter +/-1 sigma I RATIO (1)

I 6/16/2011 1 E7617-09 Water " 92 . 7.08 Ce-141 92 88 87

+/-

+/-

+/-

7.37 7.26 7.68 94 +/- 1.56 0.95 A I Mean 89.6 +/- 4.26 Cr-51

.1 . . .. 197 183 267

+/-

+/-

+/-

31.8 36.8 32.1 241 +/- '4.03 0.96 A I

277 + 45.4 Mean= 231 211 222

.+/-

+/-

+/-

22.2 11:8 11.6 I

Cs-134 208 +/- 10.6 222 +/- 3.71 0.98 A Mean=

225 217 168

+/-

+/-

+/-

13.9 7.2 5.77 I

156 +/- 5.73 Cs-137 Mean=

164 156 161 190

+/-

+/-

+/-

+/-

5.25 6.66 3.5 6.17 161 +/- 2.7 1.00 A I

Co-58 Mean=

175 188 183 184

+/-

+/-

+/-

+/-

5.95 5.93 7.07 3.7 177 +/- 2.96 1.04 A I

Mn-54 165 183 169 174

+/-

+/-

+/-

+/-

5.71 6.12 5.41 7.25 161 +/- 2.69 1.07 A I

I Mean 173 +/- 3.7 157 +/- 6.81 145 +/- 6.86 Fe-59 173 +/- 8.93 144 +/- 2.41 1.10 A I

155 + 6.68 Mean 158 : 4.4 316 +/- 12.4 298 +/- 12.1 I

Zn-65 323 +/- 12.0 305 +/- 5.09 1.03 A 316 +/- 15.3 Mean= 313 "+/- 7.7' 226 +/- 5.07 I

232 +/- 5.17 Co-60 243 +/- 4.79 228 +/- 3.8 1.02 A 225 +/- 6.21 Mean = 232 +/- 3.2 110 7.24 I

+/-

101 +/- 7.44 1-131 106 + 7.37 101 4 1.68 1.07 A 115 +/- 9.22 Mean 108 +/- 3.9 1-131*

97.3 97.8 94.3 4-

+/-

+/--

1.33 1.52 1.47 101 +/- 1.68 0.96 A I

+/-

Mean= 96.5 0.8 (1) Ratio = Reported/Analytics.

J J.

(1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

.1.

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

L A=Acceptable U=Unacceptable L

I 8-10 I

TABLE 8-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM

- .Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM ANALYSIS pCi/liter 11 sigma pCi/liter +/-1 sigma RATIO (1) 9/15/2011 E8122-05 Water 47.5 +/- 4.7 52.8 - 4.9 Ce-141 53.2 +/- 0.'89 1.00 A 59.9 + 4.2 Mean= 53.4 2.7 165.0 +/- 23.9 Cr-51 175.0 23.5 180.0 +/- 3.01 0.97 A 184.0 +/- 19.8 Mean= 175.0 +/- 13.0 98.6 +/- 7.0 Cs-134 88.6 97.5 +

+/- 7.8 6.7 102.0 +/- 1.71 0.93 A Mean= 94.9 +/- 4.1.

91.0 +/- 3.7 Cs-137 94.1 4 90.7 + 1.51 1.00 A 88.0 +/- 3.5 Mean= 91.0 +/- 4.1 75.9 +/- 3.6 Co-58 83.7 4.4 77.7 +/- 1.30 1.05 A 84.3 +/- 3.4 Mean= 81.3 +/- 2.2 117.0 +/- 4.3 118.0 +/- 4.9 Mn-54 128.0 +/- 120.0 +/- 2.01 1.01 A Mean= 121.0 +/- 2.5 51.7 +/- 3Y8 44.4 4 4.3 Fe-59 47.3 .3 43.7 +/- 0.73 1.09 A Mean 47.8 4 2.3 149.0 +/- 7.9 Zn-65 . 143.0 + 8.9 144.0 +/- 2.40 1.02 A 148.0 +/- 7.0 Mean= 147.0 +/- 4.6 124.0' 3.3 Co-60 122.0 - 3.8 125.0 +/- 2.09 0.98 A 123.0 +/- .3.0 Mean = 123.0 +/- 1.9 85.9 .+ 4.5 1-131 82.0 5.2 79.9 +/- 1.33 1.03 A 79.1 +/- 4.1 Mean = 82.3 +/- 2.7 79.3 1.0 76.1 1.3 1-131** 79.9 +/- 1.33 0.97 A 76.3 1.3 Mean= 77.2 0.7 (1) Ratio = ReportedlAnalytics.

A. J. A. A. A. A.

(1) Ratio = Reported/Analytics. A=Acceptable

• Sample provided by Analytics, Inc. U=Unacceptable

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

8-11

I TABLE 8-1 (Continued)

I INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water I DATE ISAMPLE ID NO. MEDIUM ANALYSIS - JAF ELAB +/-z pCi/liter RESULTS 1 sigma REFERENCE LAB*

p.Ci/liter +/-1 sigma RATIO.(1) 12/8/2011 1 E8183-09 I Water Cr-51

.501.

,612 566

• 589

+/-

+-

40.8 38.1 36.1 34.9 566 +/- 9.45 0.99 ' A I

Mean=

546 563 S159 1'68

+/-

+/-

+

37.7 25.5 13.4 11.7 I

Cs-134 ,170 +/- 9.3 Mean=

178 174 169.8

+/-

+/-

+/-

10.8 10.7 7.6 171 +/- 2.86 0.99 A I

216 +/-- 7.5 Cs-137 213 209 212 228 :+/-

+

+/-

6.7 5.7 6

6.5 210 3.5 1.03 A I

Mean= 215.6 +/- 4.4 Co-58 229 236 224

+/-

4 7.8 5

7' 221 +/- 3.69 1.04 A I

221 +/- 6.3 Mean =

237 229.4 249 264 4

+/-

4 A

6.5 4.5 8.1 7.2 I

I Mn-54 269 A 6.2 261 A 6.6 241 A 4.02 1.08 A 262 +/- 6.9 Mean= 261 +/- 4.8 214 +/- 8.5 Fe-59

• 203..

203 204 188 4

4

+/-

.7.7.3 6.4 7

7.3 183 3.06 1.11 A I Zn-65 Mean = 202.4 320 . +

311 330

+/-

+/-

+/-

4.9

.14.4 12.7 10.3 I

306 - 11.3 291 - 4.87 1.08 A Mean 307 314.8 286 A

+/-

+/-

12.2 8.3 6.5 I

287 +/- 5.7 Co-60 Mean=

282 288 287 286

+/-

+/-

-A A

4.8 5.2 5.5 3.8 270 A 4.51 1.06 A I

I 92.5 Az 5.5 100.0 +/- 5.3 111.99.6 . +/- 5.5 1-13. * ,84.9 8.9 55.4 88.7 +/- 1.48 1.05 A Mean =

86.6 92.7 107 116

+/-

+/-

+

5.6 3.6 1.9 2.1 I

1-131**

I 108 +/- 2.8 88.7 +/- 1.48 1.25 A 111 0 2.5 Mean = 110.5 +/-z 1.3 (1) Ratio = Reported/Analytics. A=Acceptable U=Unacceptable

• Sample provided by Analytics, Inc. ** Result determined by Resin Extraction/Gamma Spectral Analysis.

8-12 I

I

. .ý I i I TABLE 8-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM.

Gamma Analysis of Milk.

SAMPLE jJAFELAB RESULTS REFERENCE LAB*

DATE j ID NO. I MEDIUM 1ANALYSIS I pCi/liter +/-l sigma pCi/liter +/-1 sigma RATIO (1 3/17/2011 1 E7438-09 I MILK 264.0 +/- 41.3 312.0 +/- 23.2 Cr-51 298 +/- 4.98 0.97 A 295.0 A 55.9 Mean = 290.3 + 16.0

• 135.0 +/- 7.5 133.0 +/-z 4.7 Cs-134 130 + 2.18 1.04 A 136.0 +/- 9.8 Mean = 134.7 +/- 3.1 206.0 +/- 8.8 Cs-137 208.0 5.0 205 +/- 3.43 1.03 A 219.0 +/- 10.6 Mean 211.0 A 3.5 126.0 + .7.2 Co-58 122.0 +/- 4.0 113 1.89 1.07 A 1 16.0 +/- 9.3 Mean = 121.3 +/- 2.9 S282.0 +/- 10.0 Mn-54 ..- 275.0. +/- 5.6 266 4.45 1.05 A 279.0 +/- 12.0 Mean 278.7 +/- , 5.5 174.0 +/- 10.7 184.0 +/- 6.0 Fe-59 .... 198.0 +/- 14.0 175 + 2.91 1.06 A Mean = 185.3 A 6.2 275.0 +/- 17.1 Zn-65 287.0 +/- 9.6 261 A 4.36 1.13 A 324.0 +/- 21.3 Mean= . 295.3- +/- 9.6 184.0 +/- 6.6 Co-60 169.0 3.6 172 A 2.87 1.00 A 161.0 A 7.8 Mean= . 171.3 A 3.6 108.0 A 8.4 1-131 104.0 +/- 4.5 97 A 1.62 1.07 A 97.5 +/- 9.5 Mean = 103.2 +/- 4.5 95.4 +/- 6.5 103.0 +/- 2.6 1-131** 97 A 1.62 1.00 A 91.8 +/- 3.6 Mean= 96.7 1 2.6 (1) Ratio = Reported/Analytics. A=Acceptable

• Sample provided by Analytics, Inc. U=Unacceptable

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

8-13

I TABLE 8-1 (Continued)

I SAMPLE INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk JAF ELAB RESULTS REFERENCE LAB*

I I

DATE ID NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-1 sigma RATIO (1) 6/16/2011 E7634-05 MILK 86.1 +/- 5.9 85.7 +/-. 8.0 Ce-141 80 +/- 1.33 1.07 A 84.7 +/- 7.2 Mean= 85.5 209.0

+/-

4.1 26.4 I Cr-51 221.0 +/- 42.4 206 3.44 1.08 A Mean 238.0 222.7 181.0

+/-

+/-

37.0 20.7 9.4 I

Cs-134 179.0190 1 3.17 0.91 A Mean=

159.0 173.0

+

+/-

13.1 6.8 I 135.0.. +/- 4.7 Cs-137 Mean=,

145.0 136.0 138.7

+/-'

+.

+/-

6.5 6.4 3.4 138 +/- 2.3 1.00 A I

I 158.0 +/- 4.9 Co-58 153.0 153.0 +/-

+/- 6.6 7.0 152.0 + 2.53 1.02 A Mean = 154.7 +/- 3.6 Mn154 M-4141.0 136.0 1138.0

-4

+/-

- 4.8 6.8 6.5 6.5 138 +/- 2.3 1.00 A I

Fe-59 Mean = 138.3 133.0 145.0

+

+/-

+/-

3.5 5.6',

8.6 123 +/- 2.06 1.10 A I

127.0 +/- 7.7 Zn-6 Mean 135.0 266.0

+/-

+/-

4.3 10.0 I 262.0 +/- 14.4 261 +/- 4.35 1.01 A Zn-65261.0 Mean= 263.0 196.0

+/-

+/-

+/-

13.8 7.4 4.1 I

196.0 I

Co-60 5.9 195 +/- 3.25 1.02 A 205.0 +/- 5.7 Mean= 199.0 +/-. 3.1 112.0 - 5.24 1-131 13192.3 Mean=

9 101.0 101.8 +/-

+

7.65 8.95 8.95 4.3 __

103 +/- 1.72 0.99 A I 1-131**

92.3 89.8 92.5

+/-

+/-

+/- 112 1.7 1.3 103 +/- 1.72 0.89 A I Mean= 91.5. +/- 0.8 (1) Ratio (1)

= Reported/Analytics.

Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable I

8-14 I

I TABLE 8-1 (Continued)

INTERLABORATORY.INTERCOMPARISON PROGRAM Gamma Analvsis of Milk SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. I MEDIUM IANALYSIS pCi/liter +/-1 sigma pCi/liter *1 sigma RATIO (1) 9/15/2011 1 E8124-05 I MILK 79.2 +/- 7.5 64.7 +/- 5.2 Ce-141 67 + 1.11 1.07 A 69.8 +/- 6.4 Mean= 71.2 +/- 3.7 187.0 + 35.5 Cr-5I 243.0 - 25.8 226 +/- 3.78 0.96 A 224.0 +/- 29.3 Mean= 218.0 + 17.6.

112.0 +/- 11.7 Cs-134 124.0 +/- 8.5 128 + 2.14 0.92 A 116.0 +/- 9.5 Mean= 117.3 +/- 5.8 111.0 +/- 6.0 Cs'-137 111.0 4.5- 114 +/- 1.9 0.99 A 115.0 +/- 4.9 Mean= 112.3 +/- 3.0 104.0 +/- 5.8 Co-58 107.0 4 98 +/- 1.63 1.04 A 93.1 +/- 4.5 Mean = 101.4 +/- 2.9 168.0 +/- 6.9 157.0  :+/- 5.1 Mn-54 154.0 154.0 +/- 5.6 5.6 151 +/- 2.52 1.06 A Mean= 159.7 +/- 3.4 61.9 +/- 7.0 65.8 +/- 4.9 Fe-59 55 +/- 0.915 1.11 A 55.2 +/- 5.4 Mean = 61.0 +/- 3.4 194.0 +/-. 13.6 Zn-65 191.0 199.0 +/-

+/- 9.4 10.6 180 +/- 3.01 1.08 A Mean= 194.7 +/-. 6.5 159.0 +/- 5.3 Co-60 165.0 4.1 157 +/- 2.62 1.02 A 155.0 +/- 4.4 Mean,= 159.7 ' 2.7 86.9 +/- 6.6

"-3 97.9 +/- 5.3

-.131 9 5. 89.2 1.49 1.06 A 97.7 +/- 5.8 Mean = 94.2 *+ 3.4 79.8 +/- 1.1 79.5 +/- 1.0 1-131** 89.2 1.49 0.89 A 78.5 +/- 1.6 Mean = 79.3 +/- 0.7 (1) Ratio = Reported/Analytics. A=Acceptable

• Sample provided by Analytics, Inc. U=Unacceptable

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

8-15

I I

TABLE 8-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM I

_ _Gamma Analysis of Air Particulate Filter.

DATE SAMPLE ID NO.

MEDIUM ANALYSIS JAF ELAB RESULTS pCi+/- 1 sigma REFERENCE LAB*

pCi +/-1 sigma RATIO (1)

I 3/17/2011 E7478-05 FILTER Cr-51 221.0 +

224.0 233.0 -

15.9 18.0 13.7 230 +/- 3.84 0.98 A I I

Mean = 226.0 - 9.2 117.0 +/- 4.5 Cs-134: 111.0 4.9 101 +/- 1.68 1.13 A 115.-0 + 3.8 Mean= 114.0 169.0

+

+

2.6 4.5 I

Cs-137 . 159.0 +/- 4.8 158 +/- 2.64 1.04 A

_Mean=

165.0 164.0

+/-

+/-

3.8 2.5 I

90.0 4 3.5 Co-58 *84.0 Mean=

90.0 88.1

+/-

+/-

+/-

4.1 3.2 2.1 87.3 +/- 1.46 1.01 A I

Mn-54 211.0 221.0 218.0

+/-

+/-

i:

5.2 5.8 4.5 205 +/- 3.43 1.06 A I

Fe-59 Mean= 217.0 144.0 138.0

+/-

+/-

+/-

3.0 5.2 6.1 134 +/- 2.24 1.09 A I

Mean=

156.0 146.0 226.0

+/-

+/-

4.6 3.1 8.8 I

Zn-65 Mean=

212.0 208.0 215.0

+/-

+/-

9.8 7.6 5.0 201 +/- 3.36 1.07 A I

127.0. +/- 3.4 Co-60 Mean=

132.0 130.0 130.0

+/-

+/-

+/-

3.8 2.9 1.9 132 +/- 2.21 0.98 A I

(1) Ratio = Reported/Analytics.

• Sample provided by Analytics, Inc.

A=Acceptabie.

U=Unacceptable I I

I 8-16 I

I

TABLE 8-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM

...._ Gamma Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM ANALYSIS pCi+/- 1 sigma pCi +/-1 sigma RATIO (1) 9/15/2011 E8123-05 FILTER 6.84E+01 +/- 2.80E+00 Ce-141 7.11E+01 +/- 2.70E+00 6.96E+01 +/- 1.16E+00 1.02 A 7.35E+01 +/-- 2.80E+00 Mean= 7.10E+01 +/- 1.60E+00 2.17E+02 +/- 1.84E+01 Cr-51 2.32E+02 +/- 1.79E+01 2.36E+02 +/- 3.94E+00 0.96 A 2.28E+02 +/- 1.80E+01 Mean= 2.26E+02 +/- 1.05E+01 1.15E+02 +/- 8.70E+00 Cs-134- 1.15E+02 +/- 8.50E+00 1.34E+02 +/- 2.23E+00 0.85 A 1.11E+02 +/- 8.20E+00 Mean= 1.14E+02 +/- 4.89E+00 1.24E+02 +/- 4.30E+00 Cs-137 1.14E+02 +/- 4.20E+00 1.19E+02 +/- 1.98E+00 0.99 A 1.15E+02 +/- 4.OOE+00 Mean= 1.18E+02 +/- 2.41E+00 1.04E+02 +/- 4.1OE+00 1.08E+02 +/- 4.iOE+00 Co-58 1.08E+02 +/- 4.00E+00 1.02E+02 - 1.70E+00 1.05 A Mean= 1.07E+02 +/- 2.35E+00 1.75E+02 +/- 5.20E+00 Mn-54 1.67E+02 +/- 5'1OE+00 1.57E+02 +/- 2.63E+00 .1.11 A 1.79E+02 +/- 4.80E+00 Mean= 1.74E+02 +/- 2.91E+00 6.17E+01 -+/- 4.90E+00 6.86E+01 +/- 4.80E+00 Fe-59 5.72E+01 + 9.55E-01 1.13 A 6.35E+01 +/- 4.30E+00

_ _ Mean 6.46E+01 +/- 2.70E+00 1.97E+02 +/- 1.01E+01 Zn-65 2.18E+02 +/- 9.80E+00 1.88E+02 + 3.14E+00 1.13 A 2.25E+02 +/- 9.OOE+00 Mean= 2.13E÷02 +/- 5.57E+00 1.61E+02 +/- 4.20E+00 Co-60 1.59E+02 +/- 4.10E+00 1.64E+02 - 2.74E+00 0.98 A 1.64E+02 +/- 3.90E+00 Mean= 1.61E+02 +/- 2.35E+00 t1I)Katio = KeportecliAnalytics. A=Acceptaole 8-17

I TABLE 8-1 (Continued)

I INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Soil I SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE 6/16/2011 ID NO. I MEDIUM IANALYSISI E7635-05 SOIL Ce-141 pCi/g +/-1 sigma .

0.189 0.189

+/-

+/-

0.022 0.020 pCi/g +/-1 sigma 0.154 +/- 0.003 RATIO (1) 1.24 A I

0.193 0.021 I

+/-

Mean .0.190 + 0.012 0.316 +/- 0.010 Cr-51 0.365 0.009 0.397 0.007 0.86 A I

+/-

0.342 +/- 0.009 Mean = 0.341 +/-. 0.005 0.358 +/- 0.003 Cs-134 Mean =

0.363 0.349 0.357 4

4-

+

0.003 0.004 0.002 0.366 - 0.006 0.97 A N

0.308 + 0.019 Cs-137 Mean =

0.354 0.347 0.336

+/-

+/-

0.019 0.021 0.011 0.355 +/- 0.006 0.95 A I

CoL58 0.292 0.295 0.290

+

+/-

0.018 0.017.

0.020 0.292 +/- 0.005 1.00 A I

,_ Mean= 0.292 4 0.011 I

0.304 + 0.017 Mn-54 0.281 0.285 +/- 0.017 0.017 0.266 ,+/- 0.004 1.07 A 0.285 +/- 0.020 Fe-59 Mean= 0.285 0.233 0.253

+/-

+/-

0.010 0.020 0.021 0.238 +/- 0.004 1.03 A I

Mean=

0.248 0.245 0.522 0.557

• +/-

+/-

+/-

+/-

0.023 0.012 0.033 0.034 I

Zn-65 0.502 +/- 0.008 1.08 A Mean =

0.553 0.544

.0.402

+/-

+/-

0.039 0.020 0.015 I

Co-60 Mean 0.386.

0.369 0.386

+/-

0.015 0.017 0.009 0.375. +/- 0.006 1.03 A I

(1) Ratio = Reported/Analytics. A=Acceptable

• Sample provided by Analytics, Inc. U=Unacceptable I

I I

8-18 I

I

TABLE 8-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation ....... _..

SAMPLE . JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM ANALYSIS. pCi/g+/-l sigma pCi/g+/-1 sigma RATIO (1) 6/16/2011 E7637-05 VEG 0.274 + 0.013 Ce-141 0.270 + 0.015 0.307 0.005 0.92 A 0.304 +/- 0.014 Mean = 0.283 + 0.008 0.739 +/- 0.073 Cr-50.767 +/- 0.088 0.792 + 0.013 1.00 A 0.863 + 0.071 Mean = 0.790 +/- 0.045 0.664 + 0.035 Cs-134 0.660 0.004 0.729 + 0.012 0.89 A 0.629 +/- 0.003 Mean= 0.651 + 0.012 0.494 +/- 0.016 Cs-137 0.506 +/- 0.019 0.530 0.009 0.95 A 0.511 +/- 0.015 Mean 0.504 + 0.010 0.579 + 0.017.

0.556 + 0.019 0.583 0.010 0.99 A Co-58 " 0.595 + 0.015 Mean= 0.577 +/- 0.010 0.520 + 0.017 0.512 + 0.019 Mn-54 0.530 0.009 0.96 A 0.487 + 0.015 Mean= 0.506 +/- 0.010 0.487  : 0.019 Fe-59 0.514 0.023 0.474 0.008 1.03 A 0.470 +/- 0.017 Mean= 0.490 + 0.011 1.100 +/- 0.037 Zn-65 0.941 0.043 1.000 +/- 0.017 1.01 A 0.983 +/- 0.031 Mean= .1.008 + 0.022 0.718 + 0.015

._ 0.7*16 Co-60 + 0.017 0.748 + 0.013 0.94 A 0.680 - 0.013 Mean= 0.705 + 0.009 (1) Ratio = Reported/Analytics. A=Acceptable

• Sample provided by Analytics, Inc. U=Unacceptable 8-19

I I

TABLE 8-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM I Gamma Analvsis of Vegetation.

DATE SAMPLE.

ID NO. MEDIUM ANALYSIS  :

JAF ELAB RESULTS pCi/g +/-1 sigma REFERENCE LAB*

pCi/g +/-1 sigma RATIO (1)

I I

9/15/2011 E8128-09 VEG 0.151 -4 0.013 0.167 +/- 0.017 Ce-141 +/--

0.169 +/- 0.003 0.95 A 0.163 0.015

+

Mean= 0.160 0.009 Cr-51 0.632 0.553

- 0.082 0.114 0.573 +/- 0.010 1.07 A I

0.662 - 0.009 Mean = 0.616 0.332

+/-

+

0.047 0.029 I Cs-134 0.343 0.032 0.325 +/- 0.005 0.97 A Mean =

0.271 0.315 0.299

+/-

+/-

+/-

0.033 0.018 0.014 I

Cs-137 Mean =

0.256 0.281 0.279

+

+

0.016 0.016 0.009 0.288 +/- 0.005 0.97 A I

Co-58 0.273 0.256 0.258

+

+/-

+/-

0.014 0.016 0.016 0.247 +/- 0.004 1.06 A I Mean = 0.262 0.009 I

+/-

0.400 + 0.016 Mn-54 0.430 0.020 0.382 +/- 0.006 1.04 A 0.366 +/- 0.019 Mean = 0.399 0.158

+/-

+/-

0.011 0.016 I

Fe-59 Mean =

0.155 0.109 0.141 0.419

+/-

+/-

+

0.021 0.019 0.011 0.029 0.139 +/- 0.002 1.01 A I

Zn-65 Mean =

0.493 0.477 0.463 +/-

0.039

+0.036 0.020 0.457 +/- 0.008 1.01 A I

Co-60 0.388 0.366 0.395 0.013 0.015 0.015 0.397 +/- 0.007 0.96 A I I

Mean= 0.383 0.008 (1) Ratio = Reported/Analytics. A=Acceptable

• Sample provided by Analytics, Inc. U=Unacceptable I

8-20 I

I

8.5 REFERENCES

8.5.1 Radioactivity andRadiochemistry, The Counting Room: Special Edition, 1994 Caretaker Publications, Atlanta, Georgia.

8.5.2 Data Reduction and Error Analysis for the Physical Sciences, Bevington P.R., McGraw Hill, New York (1969).

8-21