ML13142A527

LLC 2012 Annual Radiological Environmental Operating Report, Enclosure

ML13142A527
Person / Time
Site:	Nine Mile Point
Issue date:	05/15/2013
From:	Constellation Energy Group, EDF Group, Nine Mile Point
To:	Office of Nuclear Reactor Regulation
References
Download: ML13142A527 (55)

Text

ENCLOSURE NINE MILE POINT NUCLEAR STATION, LLC 2012 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Nine Mile Point Nuclear Station, LLC May 15,2013

CENG.

a joint venture of Contelastion 61 O Energy .. D NINE MILE POINT NUCLEAR STATION NINE MILE POINT NUCLEAR STATION, LLC 2012 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

NINE MILE POINT NUCLEAR STATION, LLC ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January 1, 2012 - December 31, 2012 For NINE MILE POINT NUCLEAR STATION UNIT 1 Facility Operating License DPR-63 Docket No. 50-220 And NINE MILE POINT NUCLEAR STATION UNIT 2 Facility Operating License NPF-69 Docket No. 50-410

TABLE OF CONTENTS Page 1.0 EXECUTIVE

SUMMARY

1-1

2.0 INTRODUCTION

2-1 2.1 Program History 2-1 2.2 Site Description 2-1 2.3 Program Objectives 2-2 3.0 PROGRAM DESCRIPTION 3-1 3.1 Sample Collection Methodology 3-13 3.2 Analyses Performed 3-18 3.3 Sample Locations 3-18 3.4 Land Use Census 3-30 3.5 Changes to the REMP Program 3-30 3.6 Deviations and Exceptions to the Program 3-30 3.7 Statistical Methodology 3-31 3.8 Compliance with Required Lower Limits of Detection (LLD) 3-36 3.9 Regulatory Dose Limits 3-36 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 5-33 5.4 References 5-34 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 8-22 ii

LIST OF TABLES Page Table 3.0-1 Radiological Environmental Monitoring Program Required Sample Collection and Analysis, Nine Mile Point Unit 1 3-2 Table 3.0-2 Radiological Environmental Monitoring Program Required Sample Collection and Analysis, Nine Mile Point Unit 2 3-6 Table 3.3-1 2012 Environmental Sample Locations 3-20 Table 3.7-1 Required Detection Capabilities for Environmental Sample Analysis, 3-35 Lower Limit of Detection (LLD)

Table 4.0-1 Radiological Environmental Monitoring Program Annual Summary, 4-2 January - December 2012 Table 6-1 Concentrations of Gamma Emitters in Shoreline Sediment Samples - 2012 6-2 Table 6-2 Concentrations of Gamma Emitters in Fish Samples - 2012 6-3 Table 6-3 Concentrations of Tritium in Surface Water Samples - 2012 6-6 Table 6-4 Concentrations of Gamma Emitters in Surface Water Samples - 2012 6-7 Table 6-5 Environmental Airborne Particulate Samples - Off-Site Sample 6-12 Locations, Gross Beta Activity - 2012 Table 6-6 Environmental Airborne Particulate Samples - On-Site Sample 6-14 Locations, Gross Beta Activity - 2012 Table 6-7 Environmental Charcoal Cartridge Samples - Off-Site Sample 6-16 Locations, 1-131 Activity -2012 Table 6-8 Environmental Charcoal Cartridge Samples - On-Site Sample 6-18 Locations, 1-131 Activity - 2012 Table 6-9 Concentrations of Gamma Emitters in Quarterly Composites 6-20 of JAFNPP/NMPNS Site Air Particulate Samples - 2012 Table 6-10 Direct Radiation Measurement Results - 2012 6-24 Table 6-11 Concentrations of Iodine- 131 and Gamma Emitters in Milk - 2012 6-26 Table 6-12 Concentrations of Gamma Emitters in Food Products - 2012 6-28 Table 6-13 Milk Animal Census - 2012 6-29 Table 6-14 Residence Census - 2012 6-30 iii

LIST OF TABLES (continued)

Page Table 7-1 Historical Environmental Sample Data, Shoreline Sediment (Control) 7-2 Table 7-2 Historical Environmental Sample Data, Shoreline Sediment (Indicator) 7-3 Table 7-3 Historical Environmental Sample Data, Fish (Control) 7-4 Table 7-4 Historical Environmental Sample Data, Fish (Indicator) 7-5 Table 7-5 Historical Environmental Sample Data, Surface Water (Control) 7-6 Table 7-6 Historical Environmental Sample Data, Surface Water (Indicator) 7-7 Table 7-7 Historical Environmental Sample Data, Surface Water Tritium (Control) 7-8 Table 7-8 Historical Environmental Sample Data, Surface Water Tritium (Indicator) 7-9 Table 7-9 Historical Environmental Sample Data, Groundwater Tritium (Control) 7-10 Table 7-10 Historical Environmental Sample Data, Groundwater Monitoring Wells Tritium (Indicator) 7-11 Table 7-1 Oa Historical Environmental Sample Data, NMP2 Storm Drain Tritium (Indicator) 7-11 Table 7-11 Historical Environmental Sample Data, Air Particulate Gross Beta (Control) 7-12 Table 7-12 Historical Environmental Sample Data, Air Particulate Gross Beta (Indicator) 7-13 Table 7-13 Historical Environmental Sample Data, Air Particulates (Control) 7-14 Table 7-14 Historical Environmental Sample Data, Air Particulates (Indicator) 7-15 Table 7-15 Historical Environmental Sample Data, Air Radioiodine (Control) 7-16 Table 7-16 Historical Environmental Sample Data, Air Radioiodine (Indicator) 7-17 Table 7-17 Historical Environmental Sample Data, Environmental TLD (Control) 7-18 Table 7-18 Historical Environmental Sample Data, Environmental TLD (Site Boundary) 7-19 Table 7-19 Historical Environmental Sample Data, Environmental TLD (Off-site Sectors) 7-20 Table 7-20 Historical Environmental Sample Data, Environmental TLD (Special Interest) 7-21 Table 7-21 Historical Environmental Sample Data, Environmental TLD 7-22 (On-Site Indicator) iv

LIST OF TABLES (continued)

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

Table 7-23 Historical Environmental Sample Data, Milk (Control) 7-24 Table 7-24 Historical Environmental Sample Data, Milk (Indicator) 7-25 Table 7-25 Historical Environmental Sample Data, Food Products (Control) 7-26 Table 7-26 Historical Environmental Sample Data, Food Products (Indicator) 7-27 Table 8-1 Interlaboratory Intercomparison Program 8-6 V

LIST OF FIGURES Page Figure 3.3-1 New York State Map 3-24 Figure 3.3-2 Off-Site Environmental Station and TLD Locations 3-25 Figure 3.3-3 On-Site Environmental Station and TLD Locations 3-26 Figure 3.3-4 Milk and Surface Water Sample Locations 3-27 Figure 3.3-5 Nearest Residence, Food Product, Fish and Shoreline Sediment 3-28 Sample Locations Figure 3.3-6 NMPNS On-Site Groundwater Monitoring Wells and Unit 2 Storm 3-29 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 (NMPl) 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 2012, there were 1887 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 NMP I or NMP2 facilities. The 2012 results for all pathways sampled were consistent with the previous five-year historical results and exhibited no adverse trends.

In summary, the analytical results from the 2012 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 NMPI and NMP2, remains significantly below the federally required dose limits specified in 10 CFR 20, 10 CFR 72 and 40 CFR 190.

1-1

2.0 INTRODUCTION

Nine Mile Point Units 1 and 2 are operated by Nine Mile Point Nuclear Station, LLC. This report is submitted in accordance with Appendix A (Technical Specifications) Section 6.6.2 to License DPR-63, Docket No. 50-220 for Nine Mile Point Nuclear Station, Unit 1, and Appendix A (Technical Specifications) Section 5.6.2 to License NPF-69, Docket No. 50-410 for Nine Mile Point Nuclear Station, Unit 2, for the calendar year 2012.

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

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

2.1 PROGRAM HISTORY Environmental monitoring of the Nine Mile Point (NMP) site has been on-going since 1964. The program includes five years of pre-operational data which was conducted prior to any reactor operations. In 1968, the Niagara Mohawk Power Company began the required pre-operational environmental site testing program. This pre-operational data serves as a reference point to compare data obtained during reactor operation. In 1969, NMP1, a 1,850 Megawatt-Thermal (MWt) Boiling Water Reactor (BWR) began full power operation. In 1975, the James A. FitzPatrick Nuclear Power Plant (JAFNPP), a 2,536 MWt BWR, currently owned and operated by Entergy, began full power operation. In 1988, NMP2, a 3,323 MWt BWR located between NMP1 and JAFNPP, began full power operation. In 1995, NMP2 was uprated to 3,467 MWt and in 2012, NMP2 was uprated to 3988 MWt.

In 1985, the individual stations' Plant Effluent Technical Specifications were standardized to the generic Radiological Effluent Technical Specifications, much of which is common to both 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 8,374 MWt, have operated collectively since 1988. A large database of environmental results for the exposure pathways has been collected and analyzed to determine the effect from reactor operations.

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

2-1

2.3 PROGRAM OBJECTIVES The objectives of the REMP are to:

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

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

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

2-2

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

• Air

• Fish

• Food Products

" Milk

• Shoreline Sediment

" Surface Waters

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

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

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

3-1

TABLE 3.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 1 Exposure Pathway and/or Sampling and Collection Type of Analysis and Number of Samples (a) and Locations Sample Frequency (a) 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 sample from the vicinity of an established year filter change .

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

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 WATERBORNE

a. Surface (0 1. One sample upstream. Composite sample over 1 month Gamma isotopic analysis (c) 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 Freauencv (a) Freouencv

b. Fish 1. One sample each of two commercially or Twice per year. Gamma isotopic analysis (c) recreationally important species in the vicinity of a on edible portions twice per plant discharge area 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 1-131 or a separate I-calculated site average D/Q (based on all licensed 131 analysis may be 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

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 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 should be placed in special interest areas such as population centers, nearby residences, schools, and in one of two areas to serve as control stations (d) 3-6

TABLE 3.0-2 (continued)

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

Sample Freauencv Freauencv

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

and Particulates I- 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 changef),

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 .d). 3. Gamma isotopic analysis of composite sample (9g)

(by location) once per 3 months.

WATERBORNE

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

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

water intake ).

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 ( 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 *. performed, a composite sample each composite when over a 2-week period'); 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(9).

Shoreline potential recreational value.

3-8

TABLE 3.0-2 (continued)

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

Sample Frequency Frequency INGESTION

a. Milk 1. Samples from Milk Sampling Locations in three Twice per month, April - 1. Gamma isotopic (9) locations within 3.5 miles(e) 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~e) 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)

Sample Frequency Frequency

c. Food Products 1. One sample of each principal class of food products At time of harvest P). Gamma isotopic (9)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

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

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

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

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

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

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

(f) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <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 3.7-1 can be met. Doses shall be calculated for the maximum organ and age group.

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

3-11

NOTES FOR TABLE 3.0-2 (continued)

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

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

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

3- 12

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

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

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

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

b. Samples are composed of the edible portion only.

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

equipment and collected in a holding tank. Representative samples from this location are obtained weekly and are composited to form a monthly composite sample. The monthly samples are analyzed for gamma emitting radionuclides.

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

In addition to the sample results for the JAFNPP and Oswego Generating Station collection sites, data is presented for the Nine Mile Point Unit 1 (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 2012. There was no groundwater source in 2012 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 2012.

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

3.1.4 GROUNDWATER MONITORING PROGRAM The Nuclear Energy Institute (NEI) Groundwater Protection Initiative was established to determine the potential impact nuclear power plants may have on the surrounding environment due to unplanned releases of radioactive liquids. Under the NEI 07-07 Groundwater Protection Initiative (GPI) - Final Guidance Document, August 2007, groundwater monitoring is accomplished through sampling of the water table around the plant and analyzing for tritium. In addition to the groundwater monitoring requirements specified in the NMP2 ODCM, NMPNS started monitoring groundwater wells in October 2005 and has been monitoring the plant dewatering systems as part of the response to Generic Letter 80-10 for several years. During 2012, eight (8) new wells were installed. Samples collected from these locations are analyzed for tritium, gamma emitters, and strontium.

During the operating year 2012, 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 2012 Annual Radiological Effluent Release Report.

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

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

3- 14

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

These stations (R-l, R-2, and R-3) are located in the E, ESE, and SE sectors as measured from the center of the NMP2 Reactor Building. The ODCM also requires that a fourth air sampling station be located in the vicinity of a year-round community. This station is located in the SE sector at a distance of 1.8 miles and is designated as Station R-4. A fifth station required by the ODCM is a control location designated as Station R-5. Station R-5 is located 16.4 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 l, 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 Environmental Dosimetry Company. 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.

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

3-15

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

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

76*, 77*, 78*, 79*, 80*, 81*, 82*, 83*, 84*, 85*, 86*, and 87*)

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

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

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

These TLDs are located at or near large industrial sites, schools, or nearby towns or communities. This category is required by the ODCM.

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

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

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

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

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

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2. Independent Spent Fuel Storage Installation (ISFSI)

In order to provide adequate spent fuel storage capacity at NMP1 and NMP2, NMPNS constructed an ISFSI onsite west ofNMP1. During 2012 the NMPNS ISFSI facility was placed into service.

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

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

REMP TLD locations are shown in Section 3.3, Table 3.3.1.

3.1.7 MILK Milk samples are routinely collected from farms during the sampling year. These farms include one indicator location and one control location. Samples are normally collected April through December of the sample year. If plant-related radionuclides are detected during November and December of the previous year, milk collections are continued into the following year, starting in January. If plant-related radionuclides are not detected in the November and December samples, then milk collections do not commence until April of the next sampling year. Milk samples were not collected in January through March of 2012, 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, No. 77, is in the south sector at a distance of 16 miles and serves as the control location.

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

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

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

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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

" Airborne Radioiodine - Gamma Spectral Analysis

• Fish - Gamma Spectral Analysis

• Food Products (Vegetation) - Gamma Spectral Analysis, and 1-131

" Milk - Gamma Spectral Analysis and 1-131

• Shoreline Sediment - Gamma Spectral Analysis

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

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

• Surface Water Quarterly Composites - Tritium

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

The strontium and C-14 analyses are performed by a contractor laboratory - GEL Laboratories, LLC.

3.3 SAMPLE LOCATIONS Figures 3.3-1 through 3.3-6 provide maps illustrating sample locations. Sample locations referenced as letters and numbers on the report period data tables are consistent with designations plotted on the maps.

3-18

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

" Sample medium

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

" Figure number

• Location description

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

TABLE 3.3-1 2012 ENVIRONMENTAL SAMPLE LOCATIONS DEGREES & DISTANCE SAMPLE MEDIUM DESIGNATION FIGURE NUMBER LOCATION DESCRIPTION (c &d)

(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 62' 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 236' at 7.6 miles 09 Figure 3.3-4 NMP1 Inlet 319' at 0.3 miles 10 Figure 3.3-4 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. 29 145' at 1.8 miles R-5* Figure 3.3-2 R-5 Station, Montario Point - Control 420 at 16.2 miles DI Figure 3.3-3 D1 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 96' 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 - 20

TABLE 3.3-1 (continued) 2012 ENVIRONMENTAL SAMPLE LOCATIONS MAP DEGREES & DISTANCE SAMPLE MEDIUM DESIGNATION FIGURE NUMBER LOCATION DESCRIPTION (c& d)

(a& b)

Thermoluminescent 3 Figure 3.3-3 Dl 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 3 800 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 Energy 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 1 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 60' at 0.4 miles 28 Figure 3.3-3 North Fence, JAFNPP 68' at 0.5 miles 29 Figure 3.3-3 North Fence JAFNPP 650 at 0.5 miles 30 Figure 3.3-3 North Fence JAFNPP 570 at 0.4 miles 31 Figure 3.3-3 North Fence NMP1 2780 at 0.2 miles 39 Figure 3.3-3 North Fence NM[P1 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 3-21

TABLE 3.3-1 (continued) 2012 ENVIRONMENTAL SAMPLE LOCATIONS MAP DEGREES & DISTANCE SAMPLE MEDIUM DESIGNATION FIGURE NUMBER LOCATION DESCRIPTION (c&d)

(a & b)

Thermoluminescent 56* Figure 3.3-2 New Haven Elementary School 1240 5.2 miles Dosimeters (TLD) 58* Figure 3.3-2 County Route 1A and Alcan 2220 3.0 miles 3540 (Continued) 75* Figure 3.3-3 North Fence, NMP2 0.1 miles 76* Figure 3.3-3 North Fence, NMP2 270 0.1 miles Figure 3.3-3 North Fence, NMP2 370 0.2 miles 77*

78* Figure 3.3-3 East Boundary, JAFNPP 860 1.0 miles 79* Figure 3.3-3 County Route 29 1210 1.2 miles 80* Figure 3.3-3 County Route 29 1360 1.5 miles 81* Figure 3.3-3 Miner Road 1600 1.7 miles 82* Figure 3.3-3 Miner Road 1800 1.6 miles 83* Figure 3.3-3 Lakeview Road 2030 1.2 miles 84* Figure 3.3-3 Lakeview Road 2250 1.1 miles 85* Figure 3.3-3 North Fence, NMP I 2900 0.2 miles 86* Figure 3.3-3 North Fence, NMP 1 3100 0.1 miles 87* Figure 3.3-3 North Fence, NMP2 3320 0.1 miles 88* Figure 3.3-2 Hickory Grove Road 970 4.5 miles 89* Figure 3.3-2 Leavitt Road 1120 4.3 miles 90* Figure 3.3-2 Route 104 and Keefe Road 1350 4.2 miles 91* Figure 3.3-2 County Route 51A 1570 4.9 miles 92* Figure 3.3-2 Maiden Lane Road 1830 4.5 miles 93* Figure 3.3-2 County Route 53 2060 4.4 miles 94* Figure 3.3-2 County Route 1 and Kocher Road 2240 4.4 miles 95* Figure 3.3-2 Lakeshore Camp Site 2390 3.7 miles 96* Figure 3.3-2 Creamery Road 1990 3.7 miles 97* Figure 3.3-3 County Route 29 1450 1.8 miles 98* Figure 3.3-2 Lake Road 1030 1.2 miles 99 Figure 3.3-2 Nine Mile Point Road 920 1.8 miles 100 Figure 3.3-3 County Route 29 and Lake Road 1060 1.1 miles 101 Figure 3.3-3 County Route 29 1340 1.4 miles 102 Figure 3.3-2 Oswego County Airport 1750 11.9 miles 103 Figure 3.3-3 Energy Center, East 2680 0.4 miles 104 Figure 3.3-2 Parkhurst Road 1020 1.4 miles 3 - 22

TABLE 3.3-1 (continued) 2012 ENVIRONMENTAL SAMPLE LOCATIONS MAP DEGREES & DISTANCE SAMPLE MEDIUM DESIGNATION FIGURE NUMBER LOCATION DESCRIPTION (c& d)

(a & b)

Thermoluminescent 105 Figure 3.3-3 Lakeview Road 1990 at 1.4 miles Dosimeters (TLD) 106 Figure 3.3-3 Shoreline Cove, West of NMP1 2720 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 104' 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 Cow Milk 55 Figure 3.3-4 Indicator Location 970 at 8.8 miles 77* Figure 3.3-4 Control Location 1900 at 16.0 miles Food Products 133** Figure 3.3-5 Indicator Location 840 at 1.6 miles 134** Figure 3.3-5 Indicator Location 840 at 1.5 miles 144* Figure 3.3-5 Indicator Location 1390 at 1.6 miles 145* Figure 3.3-5 Control Location 222' at 15.4 miles 484* Figure 3.3-5 Indicator Location 1320 at 1.4 miles MW 1,2,4-13, Groundwater** 15-21 Figure 3.3-6 Down Gradient Wells - Indicator 2580 to 780 at <0.3 miles GMX-MW-1 Figure 3.3-6 Upland Well - Control 1600 at 0.3 miles GMX-MW-2 Figure 3.3-6 Upland Well - Control 198' at 0.3 miles MW-B119 Figure 3.3-6 Upland Well - Control 1950 at 0.8 miles MW-14 Figure 3.3-6 Control 1870 at 0.2 miles Storm Drain Figure 3.3-6 NMP2 Dewatering System - Indicator 320 at <0.1 miles Table Notes:

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

FIGURE 3.3-1 NEW YORK STATE MAP I

NQ\V/YorI<

0 UICA /V00 IUAL

( "ALBA*

'('N POOMUUVAJ 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 - 24

FIGURE 3.3-2 OFF-SITE ENVIRONMENTAL STATION AND TLD LOCATIONS KE'Y: P 56.250 TLD LOCATION ENVIRONMENTAL STATION Lake Oswego County Ontario New York Co. Rt.C 5 SCALE IN MILES Nine Mile Point 0 1 2 3 4 5 01W~

ec SEM

.750 3 - 25

t'J 0I

FIGURE 3.3-4 x MILK AND SURFACE WATER SAMPLE LOCATIONS 2SURFACE KEY:

WATER LOCATION MILK SAMPLE LOCATION Lake Oswego County Ontario New York SCALE IN MILES 0 1 2 3 4 5 E--]

5Mi.

.250 10 MI.

258.75' WSW FSW--

146.250 191.250 155S WI- FS SEI 3 - 27

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

Q FISH A FOOD PRODUCT NEAREST RESIDENCE SHORELINE SEDIMENT (Based an NMP-UnIt 2 Centerline)

EJ Lake Oswego County Ontario New York .78.750 SCALE IN MILES 0 1 2 3 4 5 5 MI.

10 MI.

258.'

lwS 191.250 I FS-SW-I F!-] Fs-sEIf 3 - 28

FIGURE 3.3-6 NMPNS ON-SITE GROUNDWATER MONITORING WELLS AND UNIT 2 STORM DRAIN OUTFALL I

() - Monitoring Well Location

- Storm Drain Outfall 001 SSW 168.75 14625

)l MW-B1 19 Ground Water Monitoring well is located SCALE (YARDS) south of Lake Road at a distance and direction of 0 100 200 300 1,355 yrds @ 195 degrees, IGXMWl (SSW). Based on NMP2 Rx Building.

3 - 29

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

The milch animal census is an estimation of the number of cows and goats within an approximate ten-mile radius of the Nine Mile Point site. This census is performed once per year in the summer by sending questionnaires to previous milch animal owners, and by road surveys to locate any possible new owners. In the event that questionnaires are not answered, the owners are contacted by telephone or in person. The Oswego County Cooperative Extension Service 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 2012 REMP sampling program.

3.6 DEVIATIONS AND EXCEPTIONS TO THE PROGRAM The noted exceptions to the 2012 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 NMPI 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 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> each during the sampling period of March 27, 2012 to April 3, 2012. The sample pump out-of-service time was determined based on the sample pump run time integrator. The inoperability of the pumps were due to loss of power to the air station. No corrective actions were required to restore power to the air stations.

3 - 30

2. The air station sample pump at R5 off-site environmental sampling station was inoperable for approximately 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> during the sampling period of July 3, 2012 to July 10, 2012.

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.

3. The air station sample pump at R5 off-site environmental sampling station was inoperable for approximately 5.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> during the sampling period of July 31, 2012 to August 7, 2012.

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.

4. The air station sample pump at R5 off-site environmental sampling station was inoperable for approximately 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the sampling period of August 14, 2012 to August 21, 2012. 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.

5. The air station sample pumps at RI, R2, R3 and R4 off-site environmental sampling stations were inoperable for approximately 30.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> each during the sampling period of October 23, 2012 to October 30, 2012. The sample pump out-of-service time was determined based on the sample pump run time integrator. The inoperability of the pumps was due to loss of power to the air stations. No corrective actions were required to restore owner to the air stations.

B. AIR SAMPLING STATION OPERABILITY ASSESSMENT The ODCM required air sampling program consists of 5 individual sampling locations. The collective operable time period for the air monitoring stations was 43,876 hours0.0101 days <br />0.243 hours <br />0.00145 weeks <br />3.33318e-4 months <br /> out of a possible 43,920 hours0.0106 days <br />0.256 hours <br />0.00152 weeks <br />3.5006e-4 months <br />. The air sampling availability factor for the reporting period was 99.9%.

3.7 STATISTICAL METHODOLOGY There is 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).

3-31

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 X= xi A. Mean i =1 N

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

'~1/2 n

X)2 S= X(X i=l L (N -1) j 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 - 32

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

A. Mean xi i=1 N

Where, X = estimate of the mean i = individual sample, i N, n = total number of samples with positive indications Xi = value for sample i above the lower limit of detection B. Error of the Mean ERROR MEAN = [ (ERROR)21 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 (o)

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 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 - 33

4.66 Sb LLD =

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

Where:

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

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

E = the counting efficiency (in counts per disintegration)

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

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

• The counting times for the sample and background are equal

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

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

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

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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/l) (pCi/n 3) (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.

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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 NMiP2 ODCM, respectively, specify the detection capabilities for environmental sample analysis (See Table 3.7-1). The reporting requirements of NMP1 ODCM, Section D 6.9. l.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 2012, 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.

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

• 25 mrem per year to the total body,

• 75 mrem per year to the thyroid, or

• 25 mrem per year to any organ as a result of:

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

2. Direct radiation from ISFSI, and

3. Any other radiation from fuel cycle operation in the region.

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

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

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

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

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

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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.

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TABLE 4.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2012*

TYPE AND INDICATOR LOCATION (c)OF HIGHEST CONTROL NUMBEROF MEDI NUMBER OF LLD(a) LOCATIONS: ANNUAL MEAN: LOCATION: NONROUTINE (UNITS) ANALYSES* MEAN 0) / LOCATION & MEAN MEAN (b)/ RANGE REPORTS RANGE RANGE 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 (18)

(pCi/kg-wet) Mn-54 130 <LLD <LLD <LLD 0 Fe-59 260 <LLD <LLD <LLD 0 Co-58 130 <LLD <LLD <LLD 0 Co-60 130 <LLD <LLD <LLD 0 Zn-65 260 <LLD <LLD <LLD 0 Cs-134 130 <LLD <LLD <LLD 0 Cs-137 150 <LLD <LLD <LLD 0 4-2

TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2012*

TYPE AND DIUM INDICATOR LOCATION (c)OF HIGHEST CONTROL NUMBEROF NUMBER OF LLD() LOCATIONS. A MEAN: LOCATION: NONROUTINE (UNITS) ANALYSES* MEAN o/ LOCATION & MEAN o, MEAN b)/ RANGE REPORTS RANGE RANGE Surface Water H-3 (8):

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

Mn-54 15 <LLD <LLD <LLD 0 Fe-59 30 <LLD <LLD <LLD 0 Co-58 15 <LLD <LLD <LLD 0 Co-60 15 <LLD <LLD <LLD 0 Zn-65 30 <LLD <LLD <LLD 0 Zr-95 15 <LLD <LLD <LLD 0 Nb-95 15 <LLD <LLD <LLD 0 1-131 15 (e) <LLD <LLD <LLD 0 Cs-134 15 <LLD <LLD <LLD 0 Cs-137 18 <LLD <LLD <LLD 0 Ba/La-140 15 <LLD <LLD <LLD 0 4-3

TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2012*

MEDIU TYPE AND (a) LOCNTROLS INDICATOR ANNUAL LOCATION MEAN (c)OF HIGHEST CONTROL NUMBEROF NUMBER OF LLD(b) LOCATIONS LOCATION: NONROUTINE (UNITS) ANALYSES* MEAN ) / LOCATION & MEAN () MEAN () / RANGE REPORTS RANGE RANGE TLD (mrem per Gamma Dose (140) 4.8 (120/120) g TLD #85 0h). 10.2 (4/4) 4.0 (20/20) 0 standard month) 3.4- 10.6 0.2 miles at 290' 9.8 - 10.6 3.6-5.0 Air Particulates Gross Beta (260): 0.01 0.016 (208/208) R-3 0.016 (52/52) 0.016 (52/52) 0 (pCi/m 3) 0.004 - 0.031 1.4 miles at133° 0.004 - 0.029 0.005 - 0.025 1-131 (260): 0.07 <LLD <LLD <LLD 0 GSA (20): <LLD <LLD <LLD Cs-134 0.05 0

<LLD <LLD <LLD Cs-137 0.06 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

TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2012*

TYPE AND MERMLD,) INDICATOR LOCATION INOCATRRAOMEN:NUMBER LOCATIONS: (c)OF HIGHEST ANNUALNMEAN: CONTROL OF (UIS (UNITS) NUMBER OF LLD(a) LA MAN ) LOCATION &MEAN ) LOCATION: NONROUTINE ANALYSES* L ANME MEAN (b) RANGE REPORTS RANGE RANGE Food Products GSA (16): (d)

(pCi/kg-wet) 1-131 60 <LLD <LLD <LLD 0 Cs-134 60 <LLD <LLD <LLD 0 Cs-137 80 <LLD <LLD <LLD 0 4-5

TABLE NOTES:

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

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

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

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

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

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

(f) The ODCM do not specify a particular LLD value for environmental TLDs. The NMP1 and NMP2 ODCM contain specifications for environmental TLD sensitivities.

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

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

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

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