NL-11-0888, Annual Radiological Environmental Operating Reports for 2010

Annual Radiological Environmental Operating Reports for 2010

ML111330385
Person / Time
Site:	Hatch, Vogtle, Farley
Issue date:	05/12/2011
From:	Moorer T Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-11-0888
Download: ML111330385 (234)

Text

Southern Nuclear Operating Company, Illc.

! ,\1 SOUTHERN A COMPANY May 12, 2011 Docket Nos.: 50-321 50-348 50-424 NL-11-0888 50-366 50-364 50-425 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radiological Environmental Operating Reports for 2010 Ladies and Gentlemen:

In accordance with section 5.6.2 of the referenced plants' Technical Specifications, Southern Nuclear Operating Company hereby submits the Annual Radiological Environmental Operating Reports for 2010.

This letter contains no NRC commitments. If you have any questions, please advise.

Respectfully submitted, T.C. Moorer Environmental Affairs, Chemistry, and Radiological Services Manager TCM/LWWllac

Enclosures:

1. Hatch Annual Radiological Environmental Operating Report for 2010

2. Farley Annual Radiological Environmental Operating Report for 2010

3. Vogtle Annual Radiological Environmental Operating Report for 2010

U. S. Nuclear Regulatory Commission NL-11-0888 Page 2 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. L. M. Stinson, Vice President - Farley Mr. D. R. Madison, Vice President - Hatch Mr. T. E. Tynan, Vice President - Vogtle Ms. P. M. Marino, Vice President - Engineering RType: CFA04.054; CHA02.004; CVC7000 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley, Hatch and Vogtle Mr. P. G. Boyle, NRR Project Manager Mr. E. L. Crowe, Senior Resident Inspector - Farley Mr. E. D. Morris, Senior Resident Inspector - Hatch Mr. M. L. Cain, Senior Resident Inspector - Vogtle State of Alabama Mr. J. L. McNees, Department of Public Health, Division of Radiation Control State of Georgia Mr. Jim Hardeman, Department of Natural Resources Georgia Power Company Mr. Rickey E. Smith American Nuclear Insurers Mr. R. A. Oliveira

Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radiological Environmental Operating Reports for 2010 Enclosure 1 Hatch Annual Radiological Environmental Operating Report for 2010

VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2010

TABLE OF CONTENTS Section and/or Title Subsection Page List of Figures ii List of Tables iii List of Acronyms iv 1.0 Introduction 1-1 2.0 REMP Description 2-1 3.0 Results Summary 3-1 4.0 Discussion of Results 4-1 4.1 Land Use Census and River Survey 4-5 4.2 Airborne 4-7 4.3 Direct Radiation 4-11 4.4 Milk 4-17 4.5 Vegetation 4-19 4.6 River Water 4-22 4.7 Drinking Water 4-25 4.8 Fish 4-35 4.9 Sediment 4-38 4.10 Groundwater 4-47 5.0 Interlaboratory Comparison Program (ICP) 5-1 6.0 Conclusions 6-1 i

LIST OF FIGURES Figure Number Title Page Figure 2-1 REMP Stations in the Plant Vicinity 2-11 Figure 2-2 REMP Control Stations for the Plant 2-12 Figure 2-3 REMP Indicator Drinking Water Stations 2-13 Figure 2-4 Groundwater Monitoring Wells 2-14 Figure 4.2-1 Average Weekly Gross Beta Air Concentration 4-8 Figure 4.3-1 Average Quarterly Exposure from Direct Radiation 4-12 Figure 4.3-2 Average Quarterly Exposure from Direct Radiation at Special Interest Areas 4-14 Figure 4.4-1 Average Annual Cs-137 Concentration in Milk 4-17 Figure 4.5-1 Average Annual Cs-137 Concentration in Vegetation 4-20 Figure 4.6-1 Average Annual H-3 Concentration in River Water 4-23 Figure 4.7-1 Average Monthly Gross Beta Concentration in Raw Drinking Water 4-26 Figure 4.7-2 Average Monthly Gross Beta Concentration in Finished Drinking Water 4-28 Figure 4.7-3 Average Annual H-3 Concentration in Raw Drinking Water 4-31 Figure 4.7-4 Average Annual H-3 Concentration in Finished Drinking Water 4-33 Figure 4.8-1 Average Annual Cs-137 Concentration in Fish 4-36 Figure 4.9-1 Average Annual Be-7 Concentration in Sediment 4-39 Figure 4.9-2 Average Annual Co-58 Concentration in Sediment 4-41 Figure 4.9-3 Average Annual Co-60 Concentration in Sediment 4-43 Figure 4.9-4 Average Annual Cs-137 Concentration in Sediment 4-45 Figure 4.10-1 Ground Water H3 Concentration in Protected Area Water Table Wells 4-49 Figure 4.10-2 Ground Water H3 Concentration in Existing Water Table Wells 4-50 Figure 4.10-3 Ground Water H3 Concentration in New Water Table Wells 4-51 ii

LIST OF TABLES Table Number Title Page Table 2-1 Summary Description of Radiological Environmental Monitoring Program 2-2 Table 2-2 Radiological Environmental Sampling Locations 2-7 Table 2-3 Groundwater Monitoring Locations 2-10 Table 3-1 Radiological Environmental Monitoring Program Annual Summary 3-2 Table 4-1 Minimum Detectable Concentrations (MDC) 4-1 Table 4-2 Reporting Levels (RL) 4-2 Table 4-3 Deviations from Radiological Environmental Monitoring Program 4-4 Table 4.1-1 Land Use Census Results 4-5 Table 4.2-1 Average Weekly Gross Beta Air Concentration 4-9 Table 4.3-1 Average Quarterly Exposure from Direct Radiation 4-13 Table 4.3-2 Average Quarterly Exposure from Direct Radiation at Special Interest Areas 4-15 Table 4.4-1 Average Annual Cs-137 Concentration in Milk 4-18 Table 4.5-1 Average Annual Cs-137 Concentration in Vegetation 4-21 Table 4.6-1 Average Annual H-3 Concentration in River Water 4-24 Table 4.7-1 Average Monthly Gross Beta Concentration in Raw Drinking Water 4-27 Table 4.7-2 Average Monthly Gross Beta Concentration in Finished Drinking Water 4-29 Table 4.7-3 Average Annual H-3 Concentration in Raw Drinking Water 4-32 Table 4.7-4 Average Annual H-3 Concentration in Finished Drinking Water 4-34 Table 4.8-1 Average Annual Cs-137 Concentration in Fish 4-37 Table 4.9-1 Average Annual Be-7 Concentration in Sediment 4-40 Table 4.9-2 Average Annual Co-58 Concentration in Sediment 4-42 Table 4.9-3 Average Annual Co-60 Concentration in Sediment 4-44 Table 4.9-4 Average Annual Cs-137 Concentration in Sediment 4-46 Table 4.9-5 Additional Sediment Nuclide Concentrations 4-46 Table 5-1 Interlaboratory Comparison Program Results 5-3 iii

LIST OF ACRONYMS Acronyms presented in alphabetical order.

Acronym Definition ASTM American Society for Testing and Materials CL Confidence Level EL Georgia Power Company Environmental Laboratory EPA Environmental Protection Agency GPC Georgia Power Company ICP Interlaboratory Comparison Program MDC Minimum Detectable Concentration MDD Minimum Detectable Difference MWe MegaWatts Electric NA Not Applicable NDM No Detectable Measurement(s)

NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual Po Preoperation PWR Pressurized Water Reactor REMP Radiological Environmental Monitoring Program RL Reporting Level RM River Mile TLD Thermoluminescent Dosimeter TS Technical Specification VEGP Alvin W. Vogtle Electric Generating Plant iv

1.0 INTRODUCTION

The Radiological Environmental Monitoring Program (REMP) is conducted in accordance with Chapter 4 of the Offsite Dose Calculation Manual (ODCM). The REMP activities for 2010 are reported herein in accordance with Technical Specification (TS) 5.6.2 and ODCM 7.1.

The objectives of the REMP are to:

1) Determine the levels of radiation and the concentrations of radioactivity in the environs and;

2) Assess the radiological impact (if any) to the environment due to the operation of the Alvin W. Vogtle Electric Generating Plant (VEGP).

The assessments include comparisons between results of analyses of samples obtained at locations where radiological levels are not expected to be affected by plant operation (control stations) and at locations where radiological levels are more likely to be affected by plant operation (indicator stations), as well as comparisons between preoperational and operational sample results.

VEGP is owned by Georgia Power Company (GPC), Oglethorpe Power Corporation, the Municipal Electric Authority of Georgia, and the City of Dalton, Georgia. It is located on the southwest side of the Savannah River approximately 23 river miles upstream from the intersection of the Savannah River and U.S.

Highway 301. The site is in the eastern sector of Burke County, Georgia, and across the river from Barnwell County, South Carolina. The VEGP site is directly across the Savannah River from the Department of Energy Savannah River Site.

Unit 1, a Westinghouse Electric Corporation Pressurized Water Reactor (PWR),

with a licensed core thermal power of 3565 MegaWatts (MWt), received its operating license on January 16, 1987 and commercial operation started on May 31, 1987. Unit 2, also a Westinghouse PWR rated for 3565 MWt, received its operating license on February 9, 1989 and began commercial operation on May 19, 1989.

The pre-operational stage of the REMP began with initial sample collections in August of 1981. The transition from the pre-operational to the operational stage of the REMP occurred as Unit 1 reached initial criticality on March 9, 1987.

A description of the REMP is provided in Section 2 of this report. Maps showing the sampling stations are keyed to a table which indicates the direction and distance of each station from a point midway between the two reactors. Section 3 provides a summary of the results of the analyses of REMP samples for the year.

The results are discussed, including an assessment of any radiological impacts upon the environment and the results of the land use census and the river survey, in Section 4. The results of the Interlaboratory Comparison Program (ICP) are provided in Section 5. Conclusions are provided in Section 6.

1-1

2.0 REMP DESCRIPTION A summary description of the REMP is provided in Table 2-1. This table summarizes the program as it meets the requirements outlined in ODCM Table 4-

1. It details the sample types to be collected and the analyses to be performed in order to monitor the airborne, direct radiation, waterborne and ingestion pathways, and also delineates the collection and analysis frequencies. In addition, Table 2-1 references the locations of stations as described in ODCM Section 4.2 and in Table 2-2 of this report. The stations are also depicted on maps in Figures 2-1 through 2-3.

REMP samples are collected by Georgia Power Company's (GPC) Environmental Laboratory (EL) personnel. The same lab performs all the laboratory analyses at their headquarters in Smyrna, Georgia.

2-1

TABLE 2-1 (SHEET 1 of 5)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Collection Type and Frequency of and/or Sample Samples and Sample Frequency Analysis Locations

1. Direct Radiation Thirty nine routine monitoring Quarterly Gamma dose, quarterly stations with two or more dosimeters placed as follows:

An inner ring of stations, one in each compass sector in the general area of the site boundary; An outer ring of stations, one in each compass sector at approximately 5 miles from the site; and Special interest areas, such as 2-2 population centers, nearby recreation areas, and control stations.

2. Airborne Radioiodine Samples from seven locations: Continuous sampler operation Radioiodine canister: I-and Particulates with sample collection weekly, 131 analysis, weekly.

Five locations close to the site or more frequently if required by boundary in different sectors; dust loading. Particulate sampler:

Gross beta analysis1 A community having the following filter change highest calculated annual and gamma isotopic average ground level D/Q; analysis2 of composite (by location), quarterly.

A control location near a population center at a distance of about 14 miles.

TABLE 2-1 (SHEET 2 of 5)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Collection Type and Frequency of and/or Sample Samples and Sample Frequency Analysis Locations

3. Waterborne

a. Surface3 One sample upriver. Composite sample over one Gamma isotopic month period4. analysis2, monthly.

Two samples downriver. Composite for tritium analysis, quarterly.

b. Drinking Two samples at each of the Composite sample of river water I-131 analysis on each three nearest water treatment near the intake of each water sample when the dose plants that could be affected treatment plant over two week calculated for the by plant discharges. period4 when I-131 analysis is consumption of the required for each sample; water is greater than 1 Two samples at a control monthly composite otherwise; mrem per year5.

location. and grab sample of finished Composite for gross water at each water treatment beta and gamma plant every two weeks or isotopic analysis2 on 2-3 monthly, as appropriate. raw water, monthly.

Gross beta, gamma isotopic and I-131 analyses on grab sample of finished water, monthly. Composite for tritium analysis on raw and finished water, quarterly.

c. Groundwater See Table 2-3 and Figure 2-4 Quarterly sample; pump used to Tritium, gamma isotopic, for well locations. sample GW wells; grab sample and field parameters (pH, from yard drains and ponds temperature, conductivity, dissolved oxygen, oxidation/reduction potential, and turbidity) of each sample quarterly; Hard to detect radionuclides as necessary based on results of tritium and gamma

TABLE 2-1 (SHEET 3 of 5)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Collection Type and Frequency of and/or Sample Samples and Sample Frequency Analysis Locations

d. Sediment from Shoreline One sample from downriver Semiannually Gamma isotopic area with existing or potential analysis2, semiannually.

recreational value.

One sample from upriver area with existing or potential recreational value.

4. Ingestion

a. Milk Two samples from milking Biweekly Gamma isotopic animals6 at control locations analysis2,7, biweekly.

at a distance of about 10 miles or more.

b. Fish At least one sample of any Semiannually Gamma isotopic 2-4 commercially or analysis2 on edible recreationally important portions, semiannually.

species near the plant discharge.

At least one sample of any commercially or recreationally important species in an area not influenced by plant discharges.

At least one sample of any During the spring spawning Gamma isotopic anadromous species near the season. analysis2 on edible plant discharge. portions, annually.

TABLE 2-1 (SHEET 4 of 5)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Collection Type and Frequency of and/or Sample Samples and Sample Frequency Analysis Locations

c. Grass or Leafy One sample from two onsite Monthly during growing Gamma isotopic Vegetation locations near the site season. analysis2, 7, monthly.

boundary in different sectors.

One sample from a control location at a distance of about 17 miles.

2-5

TABLE 2-1 (SHEET 5 of 5)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Notes:

(1) 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. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

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

(3) Upriver sample is taken at a distance beyond significant influence of the discharge. Downriver samples are taken beyond but near the mixing zone.

(4) Composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) to assure obtaining a representative sample.

(5) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

2-6 (6) A milking animal is a cow or goat producing milk for human consumption.

(7) If the gamma isotopic analysis is not sensitive enough to meet the Minimum Detectable Concentration (MDC) for I-131, a separate analysis for I-131 may be performed.

TABLE 2-2 (SHEET 1 of 3)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Station Station Descriptive Direction1 Distance Sample Type Number Type Location (miles)1 1 Indicator River Bank N 1.1 Direct Rad.

2 Indicator River Bank NNE 0.8 Direct Rad.

3 Indicator Discharge Area NE 0.6 Airborne Rad.

3 Indicator River Bank NE 0.7 Direct Rad 4 Indicator River Bank ENE 0.8 Direct Rad.

5 Indicator River Bank E 1.0 Direct Rad.

6 Indicator Plant Wilson ESE 1.1 Direct Rad.

7 Indicator Simulator SE 1.7 Airborne Rad.

Building Direct Rad.

Vegetation 8 Indicator River Road SSE 1.1 Direct Rad.

9 Indicator River Road S 1.1 Direct Rad.

10 Indicator Met Tower SSW 0.9 Airborne Rad.

10 Indicator River Road SSW 1.1 Direct Rad.

11 Indicator River Road SW 1.2 Direct Rad.

12 Indicator River Road WSW 1.2 Airborne Rad.

Direct Rad.

13 Indicator River Road W 1.3 Direct Rad.

14 Indicator River Road WNW 1.8 Direct Rad.

15 Indicator Hancock NW 1.5 Direct Rad.

Landing Road Vegetation 16 Indicator Hancock NNW 1.4 Airborne Rad.

Landing Road Direct Rad.

17 Other Sav. River Site N 5.4 Direct Rad.

(SRS), River Road 18 Other SRS, D Area NNE 5.0 Direct Rad.

19 Other SRS, Road NE 4.6 Direct Rad.

A.13 20 Other SRS, Road ENE 4.8 Direct Rad.

A.13.1 21 Other SRS, Road E 5.3 Direct Rad.

A.17 22 Other River Bank ESE 5.2 Direct Rad.

23 Other River Road SE 4.6 Direct Rad.

24 Other Chance Road SSE 4.9 Direct Rad.

25 Other Chance Road S 5.2 Direct Rad.

near Highway 23 26 Other Highway 23 SSW 4.6 Direct Rad.

and Ebenezer Church Road 27 Other Highway 23 SW 4.7 Direct Rad.

opposite Boll Weevil Road 28 Other Thomas Road WSW 5.0 Direct Rad.

2-7

TABLE 2-2 (SHEET 2 of 3)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Station Station Descriptive Direction1 Distance Sample Type Number Type Location (miles)1 29 Other Claxton-Lively W 5.1 Direct Rad.

Road 30 Other Nathaniel WNW 5.0 Direct Rad.

Howard Road 31 Other River Road at NW 5.0 Direct Rad.

Allens Chapel Fork 32 Other River Bank NNW 4.7 Direct Rad.

35 Other Girard SSE 6.6 Airborne Rad.

Direct Rad.

36 Control GPC WSW 13.9 Airborne Rad.

Waynesboro Op. Direct Rad.

HQ 37 Control Substation WSW 16.7 Direct Rad Waynesboro, Vegetation GA 43 Other Employees Rec. SW 2.2 Direct Rad.

Center 47 Control Oak Grove SE 10.4 Direct Rad.

Church 48 Control McBean NW 10.2 Direct Rad.

Cemetery 51 Control SGA School S 11.0 Direct Rad.

Sardis, GA 52 Control Oglethorpe SW 10.7 Direct Rad.

Substation; Alexander, GA 80 Control Augusta Water NNW 29.0 Drinking Treatment Plant Water2 81 Control Sav River N 2.5 Fish3 Sediment4 82 Control Sav River (RM NNE 0.8 River Water 151.2) 83 Indicator Sav River (RM ENE 0.8 River Water 150.4) Sediment4 84 Other Sav River (RM ESE 1.6 River Water 149.5) 85 Indicator Sav River ESE 4.3 Fish3 87 Indicator Beaufort-Jasper SE 76 Drinking County Water Water5 Treatment Plant 88 Indicator Cherokee Hill SSE 72 Drinking Water Treatment Water6 Plant, Port Wentworth, Ga 2-8

TABLE 2-2 (SHEET 3 of 3)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS 89 Indicator Purrysburg SSE 76 Drinking Water Treatment Water7 Plant; Purrysburg, SC 98 Control W.C. Dixon SE 9.8 Milk8 Dairy 101 Indicator Girard Dairy S 5.5 Milk8 102 Control Seven Oaks W 7.5 Milk8 Dairy Notes:

(1) Direction and distance are determined from a point midway between the two reactors.

(2) The intake for the Augusta Water Treatment Plant is located on the Augusta Canal. The entrance to the canal is at River Mile (RM) 207 on the Savannah River. The canal effectively parallels the river. The intake to the pumping station is about 4 miles down the canal.

(3) A 5 mile stretch of the river is generally needed to obtain adequate fish samples.

Samples are normally gathered between RM 153 and 158 for upriver collections and between RM 144 and 149.4 for downriver collections.

(4) Sediment is collected at locations with existing or potential recreational value. Because high water, shifting of the river bottom, or other reasons could cause a suitable location for sediment collections to become unavailable or unsuitable, a stretch of the river between RM 148.5 and 150.5 was designated for downriver collections while a stretch between RM 153 and 154 was designated for upriver collections. In practice, collections are normally made at RM 150.2 for downriver collections and RM 153.3 for upriver collections.

(5) The intake for the Beaufort-Jasper County Water Treatment Plant is located at the end of canal that begins at RM 39.3 on the Savannah River. This intake is about 16 miles by line of sight down the canal from its beginning on the Savannah River.

(6) The intake for the Cherokee Hill Water Treatment Plant is located on Abercorn Creek which is about one and a quarter creek miles from its mouth on the Savannah River at RM 29.

(7) The intake for the Purrysburg Water Treatment Plant is located on the same canal as the Beaufort-Jasper Water Treatment Plant. The Purrysburg intake is nearer to the Savannah River at the beginning of the canal.

(8) Girard Dairy is considered an indicator station since it is the closest dairy to the plant

(@5.5 miles). Dixon Dairy went out of business in June 2009 and Seven Oaks Dairy

(@7.5 miles) was added as a replacement and is considered a control station even though a control station is typically 10 miles or greater.

2-9

Groundwater Monitoring Locations Table 2-3 WELL AQUIFER MONITORING PURPOSE LT-1B Water Table NSCW related tank LT-7A Water Table NSCW related tank LT-12 Water Table NSCW related tank LT-13 Water Table NSCW related tank 802A Water Table Southeastern potential leakage 803A Water Table Up gradient to rad waste building Down gradient from rad waste bldg and 805A Water Table NSCW related facilities 806B Water Table Dilution line 808 Water Table Up gradient; along Pen Branch Fault NSCW related tank; western potential R1 Water Table leakage R2 Water Table Southern potential leakage R3 Water Table Eastern potential leakage R4 Water Table Dilution line R5 Water Table Dilution line R6 Water Table Dilution line R7 Water Table Dilution line Water Table within R8 Dilution line Sav. River sediments 1013* Water Table Low level rad waste storage 1014 Tertiary Up gradient 1015 Water Table Vertically up gradient 1003* Tertiary Up gradient 1004* Water Table Vertically up gradient 27** Tertiary Down gradient tertiary 29** Tertiary Down gradient tertiary MU-1 Tertiary/Cretaceous Facility water supply River N/A Surface water NSCW - Nuclear service cooling water

• Wells abandoned in Feb. 2009 due to construction activities with proposed new units

• • Sampling discontinued in 2010 due to structural issues with the well 2-10

3.0 RESULTS

SUMMARY

In accordance with ODCM 7.1.2.1, the summarized and tabulated results for all of the regular samples collected for the year at the designated indicator and control stations are presented in Table 3-1. The format of Table 3-1 is similar to Table 3 of the Nuclear Regulatory Commission (NRC) Branch Technical Position, An Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. Results for samples collected at locations other than indicator or control stations are discussed in Section 4 under the particular sample type.

As indicated in ODCM 7.1.2.1, the results for naturally occurring radionuclides that are also found in plant effluents must be reported along with man-made radionuclides. The radionuclide Be-7, which occurs abundantly in nature, is often detected in REMP samples. It is occasionally detected in the plants liquid and gaseous effluents. When it is detected in effluents, it is also included in the REMP results. In 2010, Be-7 was not detected in Vogtles liquid or gaseous effluents.

3-1

TABLE 3-1 (SHEET 1 of 8)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Medium or Type and Minimum Indicator Location with the Highest Other Control Pathway Total Detectable Locations Annual Mean Stations (g) Locations Sampled Number of Concentration Mean (b), Mean (b), Mean (b),

(Unit of Analyses (MDC) (a) Range Name Distance Mean (b), Range Range Measurement) Performed (Fraction) & Direction Range (Fraction) (Fraction) (Fraction)

Airborne Gross Beta 10 25.8 Station 10 26.3 25.5 24.4 Particulates 363 8.7-59.1 Met Tower 10.4-59.1 11.7-49.2 7.2-47.2 (fCi/m3) (259/259) 0.9 miles SSW (52/52) (52/52) (52/52)

Gamma Isotopic 28 3-2 Cs-134 50 NDM (c) NDM NDM NDM Cs-137 60 NDM NDM NDM NDM Airborne I-131 70 NDM NDM NDM NDM Radioiodine 363 (fCi/m3)

Direct Gamma NA (d) 16.2 Station 29 20.2 16.6 16.7 Radiation Dose 10.6-25.5 Claxton-Lively 16.4-28.2 10.7-28.2 12.0-24.9 (mR/91 days) 159 (63/63) Road (4/4) (24/24)

(72/72) 5.1 miles W

TABLE 3-1 (SHEET 2 of 8)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Medium or Type and Minimum Indicator Location with the Highest Other Control Pathway Total Detectable Locations Annual Mean Stations (g) Locations Sampled Number of Concentration Mean (b), Mean (b),

(Unit of Analyses (MDC) (a) Range Name Distance Mean (b), Mean (b), Range Measurement) Performed (Fraction) & Direction Range (Fraction) Range (Fraction)

(Fraction)

Milk (pCi/l) Gamma Isotopic 52 Cs-134 15 NDM NDM NA NDM Cs-137 18 NDM NDM NA NDM Ba-140 60 NDM NDM NA NDM 3-3 La-140 15 NDM NDM NA NDM I-131 1 NDM NDM NA NDM 52 Vegetation Gamma (pCi/kg-wet) Isotopic 36 I-131 60 NDM NDM NA NDM Cs-134 60 NDM NDM NA NDM Cs-137 80 NDM NDM NA NDM

TABLE 3-1 (SHEET 3 of 8)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Medium or Type and Minimum Indicator Location with the Highest Other Control Pathway Total Number Detectable Locations Annual Mean Stations (g) Locations Sampled of Analyses Concentration Mean (b), Mean (b),

(Unit of Performed (MDC) (a) Range Name Distance Mean (b), Mean (b), Range Measurement) (Fraction) & Direction Range (Fraction) Range (Fraction)

(Fraction)

River Water Gamma (pCi/l) Isotopic 36 Be-7 124(e) NDM NDM NDM NDM Mn-54 15 NDM NDM NDM NDM Fe-59 30 NDM NDM NDM NDM 3-4 Co-58 15 NDM NDM NDM NDM Co-60 15 NDM NDM NDM NDM Zn-65 30 NDM NDM NDM NDM Zr-95 30 NDM NDM NDM NDM Nb-95 15 NDM NDM NDM NDM I-131 15 NDM NDM NDM NDM Cs-134 15 NDM NDM NDM NDM Cs-137 18 NDM NDM NDM NDM Ba-140 60 NDM NDM NDM NDM La-140 15 NDM NDM NDM NDM Tritium 2000 873 Station 83 873 591 264 12 456-1410 RM 150.4 456-1410 394-886 214-323 (4/4) 0.8 miles ENE (4/4) (4/4) (3/4)

TABLE 3-1 (SHEET 4 of 8)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Medium or Type and Total Minimum Indicator Location with the Highest Other Control Pathway Number of Detectable Locations Annual Mean Stations (g) Locations Sampled Analyses Concentration Mean (b), Mean (b),

(Unit of Performed (MDC) (a) Range Name Distance Mean (b), Mean (b), Range Measurement) (Fraction) & Direction Range (Fraction) Range (Fraction)

(Fraction)

Water Near Gross Beta 4 2.95 Station 87 3.79 NA 1.76 Intakes to 48 1.09-7.49 Beaufort-Jasper WTP 1.09-7.487 1.28-2.18 Water (36/36) 76 miles SE (12/12) (9/12)

Treatment Plants (pCi/l)

Gamma Isotopic 48 3-5 Be-7 124(e) NDM NDM NA NDM Mn-54 15 NDM NDM NA NDM Fe-59 30 NDM NDM NA NDM Co-58 15 NDM NDM NA NDM Co-60 15 NDM NDM NA NDM Zn-65 30 NDM NDM NA NDM Zr-95 30 NDM NDM NA NDM Nb-95 15 NDM NDM NA NDM I-131(f) 15 NDM NDM NA NDM Cs-134 15 NDM NDM NA NDM Cs-137 18 NDM NDM NA NDM Ba-140 60 NDM NDM NA NDM La-140 15 NDM NDM NA NDM Tritium 2000 343 Station 87 376 NA 244 16 229-539 Beaufort-Jasper WTP 285-465 239-248 (11/12) 76 miles SE (3/4) (2/4)

TABLE 3-1 (SHEET 5 of 8)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Medium or Type and Minimum Indicator Location with the Highest Other Control Pathway Total Detectable Locations Annual Mean Stations (g) Locations Sampled Number of Concentration Mean (b), Mean (b),

(Unit of Analyses (MDC) (a) Range Name Distance Mean (b), Mean (b), Range Measurement) Performed (Fraction) & Direction Range (Fraction) Range (Fraction)

(Fraction)

Finished Water Gross Beta 4 2.89 Station 88 NA at Water 48 1.32-6.33 Cherokee Hill WTP 1.39-3.92 1.20-3.83 Treatment (36/36) Port Wentworth (11/12) (11/12)

Plants (pCi/l) 72 miles SSE Gamma Isotopic 3-6 48 Be-7 124(e) NDM NDM NA NDM Mn-54 15 NDM NDM NA NDM Fe-59 30 NDM NDM NA NDM Co-58 15 NDM NDM NA NDM Co-60 15 NDM NDM NA NDM Zn-65 30 NDM NDM NA NDM Zr-95 30 NDM NDM NA NDM Nb-95 15 NDM NDM NA NDM I-131 1 NDM NDM NA NDM Cs-134 15 NDM NDM NA NDM Cs-137 18 NDM NDM NA NDM Ba-140 60 NDM NDM NA NDM La-140 15 NDM NDM NA NDM Tritium 2000 374 Station 89 463 NA 262 16 204-693 Purrysburg WTP 263-693 (1/4)

(8/12) 76 miles SSE (4/4)

TABLE 3-1 (SHEET 6 of 8)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Medium or Type and Minimum Indicator Location with the Highest Other Control Pathway Total Detectable Locations Annual Mean Stations (g) Locations Sampled Number of Concentration Mean (b), Mean (b),

(Unit of Analyses (MDC) (a) Range Name Distance Mean (b), Mean (b), Range Measurement) Performed (Fraction) & Direction Range (Fraction) Range (Fraction)

(Fraction)

Anadromous Gamma Fish Isotopic (pCi/kg-wet) 1 Be-7 655(e) NDM NDM NA NA Mn-54 130 NDM NDM NA NA Fe-59 260 NDM NDM NA NA Co-58 130 NDM NDM NA NA 3-7 Co-60 130 NDM NDM NA NA Zn-65 260 NDM NDM NA NA Cs-134 130 NDM NDM NA NA Cs-137 150 NDM NDM NA NA Fish Gamma (pCi/kg-wet) Isotopic 4

Be-7 655(e) NDM NDM NA NDM Mn-54 130 NDM NDM NA NDM Fe-59 260 NDM NDM NA NDM Co-58 130 NDM NDM NA NDM Co-60 130 NDM NDM NA NDM Zn-65 260 NDM NDM NA NDM Cs-134 130 NDM NDM NA NDM Cs-137 150 42.8 Station 81 74.4 NA 74.4 39.5-46.2 2.5 miles N 33.7-115.0 33.7-115.0 (2/2) (upstream) (2/2) (2/2)

TABLE 3-1 (SHEET 7 of 8)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Medium or Type and Minimum Indicator Location with the Highest Other Control Pathway Total Number Detectable Locations Annual Mean Stations (g) Locations Sampled of Analyses Concentration Mean (b), Mean (b),

(Unit of Performed (MDC) (a) Range Name Distance Mean (b), Mean (b), Range Measurement) (Fraction) & Direction Range Range (Fraction)

(Fraction) (Fraction)

Sediment Gamma (pCi/kg-dry) Isotopic 4

Be-7 655(e) 1217 Station 83 1217 NA 533 764-1670 0.8 miles ENE 764-1670 522-544 (2/2) (downstream) (2/2) (2/2)

Co-60 70(e) NDM NDM NA NDM 3-8 Cs-134 150 NDM NDM NA NDM Cs-137 180 164.6 Station 83 164.6 NA 64.1 139.3-189.8 0.8 miles ENE 139.3-189.8 54.0-74.3 (2/2) (downstream) (2/2) (2/2)

TABLE 3-1 (SHEET 8 of 8)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Notes:

a. The MDC is defined in ODCM 10.1. Except as noted otherwise, the values listed in this column are the detection capabilities required by ODCM Table 4-3. The values listed in this column are a priori (before the fact) MDCs. In practice, the a posteriori (after the fact) MDCs are generally lower than the values listed. Any a posteriori MDC greater than the value listed in this column is discussed in Section 4.

b. Mean and range are based upon detectable measurements only. The fraction of all measurements at a specified location that are detectable is placed in parenthesis.

c. No Detectable Measurement(s).

d. Not Applicable.

3-9

e. The EL has determined that this value may be routinely attained under normal conditions. No value is provided in ODCM Table 4-3.

f. Item 3 of ODCM Table 4-1 implies that an I-131 analysis is not required to be performed on water samples when the dose calculated from the consumption of water is less then 1 mrem per year. However, I-131 analyses have been performed on the finished drinking water samples.

g. Other stations, as identified in the Station Type column of Table 2-2, are Community and/or Special stations.

4.0 DISCUSSION OF RESULTS Included in this section are evaluations of the laboratory results for the various sample types. Comparisons were made between the difference in mean values for pairs of station groups (e.g., indicator and control stations) and the calculated Minimum Detectable Difference (MDD) between these pairs at the 99%

Confidence Level (CL). The MDD was determined using the standard Student's t-test. A difference in the mean values that was less than the MDD was considered to be statistically indiscernible.

The 2010 results were compared with past results, including those obtained during preoperation. As appropriate, results were compared with their Minimum Detectable Concentrations (MDC) and Reporting Levels (RL) which are listed in Tables 4-1 and 4-2 of this report, respectively. The required MDCs were achieved during laboratory sample analysis. Any anomalous results are explained within this report.

Results of interest are graphed to show historical trends. The data points are tabulated and included in this report. The points plotted and provided in the tables represent mean values of only detectable results. Periods for which no detectable measurements (NDM) were observed or periods for which values were not applicable (e.g., milk indicator, etc.) are listed as NDM and are plotted in the tables as 0s.

Table 4-1 Minimum Detectable Concentrations (MDC)

Analysis Water Airborne Fish Milk Grass or Sediment (pCi/l) Particulate (pCi/kg- (pCi/l) Leafy (pCi/kg) or Gases wet) Vegetation (fCi/m3) (pCi/kg-wet)

Gross Beta 4 10 H-3 2000 (a)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 1 (b) 70 1 60 Cs-134 15 50 130 15 60 150 Cs-137 18 60 150 18 80 180 Ba-140 60 60 La-140 15 15 (a) If no drinking water pathway exists, a value of 3000 pCi/l may be used.

(b) If no drinking water pathway exists, a value of 15 pCi/l may be used.

4-1

Table 4-2 Reporting Levels (RL)

Analysis Water Airborne Fish Milk (pCi/l) Grass or (pCi/l) Particulate (pCi/kg-wet) Leafy or Gases Vegetation (fCi/m3) (pCi/kg-wet)

H-3 20,000 (a)

Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-95 400 Nb-95 700 I-131 2 (b) 900 3 100 Cs-134 30 10,000 1000 60 1000 Cs-137 50 20,000 2000 70 2000 Ba-140 200 300 La-140 100 400 (a) This is the 40 CFR 141 value for drinking water samples. If no drinking water pathway exists, a value of 30,000 may be used.

(b) If no drinking water pathway exists, a value of 20 pCi/l may be used.

Atmospheric nuclear weapons tests from the mid 1940s through 1980 distributed man-made nuclides around the world. The most recent atmospheric tests in the 1970s and in 1980 had a significant impact upon the radiological concentrations found in the environment prior to and during preoperation, and the earlier years of operation. Some long lived radionuclides, such as Cs-137, continue to have some impact. A significant component of the Cs-137 which has often been found in various samples over the years (and continues to be found) is attributed to the nuclear weapons tests.

Data in this section has been modified to remove any obvious non-plant short term impacts. The specific short term impact data that has been removed includes: the nuclear atmospheric weapon test in the fall of 1980; abnormal releases from the Savannah River Site (SRS) during 1987 and 1991; and the Chernobyl incident in the spring of 1986.

In accordance with ODCM 4.1.1.2.1, deviations from the required sampling schedule are permitted, if samples are unobtainable due to hazardous conditions, unavailability, inclement weather, equipment malfunction or other just reasons.

Deviations from conducting the REMP as described in Table 2-1 are summarized in Table 4-3 along with their causes and resolutions.

4-2

All results were tested for conformance with Chauvenet's criterion (G. D. Chase and J. L. Rabinowitz, Principles of Radioisotope Methodology, Burgess Publishing Company, 1962, pages 87-90) to identify values which differed from the mean of a set by a statistically significant amount. Identified outliers were investigated to determine the reason(s) for the difference. If equipment malfunction or other valid physical reasons were identified as causing the variation, the anomalous result was excluded from the data set as non-representative. No data were excluded exclusively for failing Chauvenet's criterion. Data exclusions are discussed in this section under the appropriate sample type.

4-3

TABLE 4-3 DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM COLLECTION AFFECTED DEVIATION CAUSE RESOLUTION PERIOD SAMPLES 03/23/10-03/30/10 AF/AC Non-representative sample of Power interruption; lost 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of Station operation satisfactory after power CR2011100231 Simulator Bldg. airborne particulates sampling time restored 1.7 miles SE 2nd Quarter TLD #26 Non-representative direct radiation TLDs found on the ground during mid- Put back in place at mid-quarter CR2011100392 Hwy. 23 and Ebenezer data quarter check 4.6 miles SSW 2nd Quarter 2010 All Second Quarter TLD Direction radiation results higher Panasonic TLD reader problems caused OSL Inlight system put in service in Corp CR2011100346 Results than typical a three week delay in reading 2nd January 2011; Panasonic system retired quarter badges 07/20/10-07/27/10 AF/AC Non-representative sample of Controlled burn in area Noted to ensure data was satisfactory CR2011100396 River Road airborne particulates 1.2 miles WSW 08/10/10-08/17/10 AF/AC Non-representative sample of Fuse blown - likely cause was Station operation satisfactory after fuse CR2011100397 River Road airborne particulates inclement weather; short 41 hours4.74537e-4 days <br />0.0114 hours <br />6.779101e-5 weeks <br />1.56005e-5 months <br /> of replaced 1.2 miles WSW sampling time 09/14/10-09/21/10 AF/AC Non-representative sample of Four day power supply outage due to Station operation satisfactory after power 4-4 CR2011100398 Simulator Bldg. airborne particulates construction activities restored 1.7 miles SE 09/21/10-09/28/10 AF/AC Non-representative sample of No sample; at sample change out, quick Station operation satisfactory after fuse CR2011100399 Discharge Area airborne particulates connect left unattached causing fuse to replaced EXCLUDED 0.6 miles NE blow 3rd Quarter TLD #5 Non-representative direct radiation TLDs missing at end of quarter Replaced TLDs at beginning of 4th quarter CR2011100401 River Bank data EXCLUDED 1.0 mile E 3rd Quarter TLD #9A Non-representative direct radiation Moisture in TLD holding bag Replaced TLDs at beginning of 4th quarter CR2011100401 River Road data 1.1 mile S 3rd Quarter TLD #25 Non-representative direct radiation TLDs found on the ground during mid- Put back in place at mid-quarter CR2011100401 Chance Road data quarter check 5.2 miles S 3rd Quarter TLD #31 Non-representative direct radiation TLDs found on the ground during mid- Put back in place at mid-quarter CR2011100401 River Road data quarter check 5.0 miles NW 4th Quarter TLD #13 Non-representative direct radiation TLDs were missing at mid-quarter Replaced TLDs at beginning of 1st quarter CR2011106703 River Road data check 1.3 miles W

4.1 Land Use Census and River Survey In accordance with ODCM 4.1.2, a land use census was conducted on November 9, 2010 to determine the locations of the nearest permanent residence, milk animal, and garden of greater than 500 square feet producing broad leaf vegetation, in each of the 16 compass sectors within a distance of 5 miles; the locations of the nearest beef cattle in each sector were also determined. A milk animal is a cow or goat producing milk for human consumption. Land within SRS was excluded from the census. The census results are tabulated in Table 4.1-1.

Table 4.1-1 LAND USE CENSUS RESULTS Distance in Miles to the Nearest Location in Each Sector SECTOR RESIDENCE MILK BEEF GARDEN ANIMAL CATTLE N 1.4 None None None NNE None None None None NE None None None None ENE None None None None E None None None None ESE 4.2 None None None SE 4.4 None 5.0 None SSE 4.6 None 4.7 None S 4.4 None 4.3 None SSW 4.7 None 4.5 None SW 3.1 None 5.0 None WSW 2.6 None 2.7 None W 3.4 None 4.5 None WNW 1.9 None None None NW 1.6 None 1.6 None NNW 1.5 None None None ODCM 4.1.2.2.1 requires a new controlling receptor to be identified, if the land use census identifies a location that yields a calculated receptor dose greater than the one in current use. In 2008, the controlling receptor was moved to a more conservative location at 1.2 miles WSW. This property was acquired by Georgia Power in 2008. The residents were relocated but this property will potentially be used for contract labor in the future.

ODCM 4.1.2.2.2 requires that whenever the land use census identifies a location which yields a calculated dose (via the same ingestion pathway) 20% greater than 4-5

that of a current indicator station, the new location must become a REMP station (if samples are available). None of the identified locations yielded a calculated dose 20% greater than that for any of the current indicator stations. No milk animals were identified within five miles of the plant. A new dairy was started at Girard in 2008 and was added to the REMP. Since control stations are approximately 10 miles are greater, this dairy is considered an indicator station.

A survey of the Savannah River downstream of the plant for approximately 100 miles was conducted on September 21, 2010 to identify any withdrawal of water from the river for drinking, irrigation, or construction purposes. No such usage was identified. These results were corroborated by checking with the Georgia Department of Natural Resources on September 29 and 30, 2010; and the South Carolina Department of Health and Environmental Control on September 29, 2010. Each of these agencies confirmed that no water withdrawal permits for drinking, irrigation, or construction purposes had been issued for this stretch of the Savannah River. The three water treatment plants used as indicator stations for drinking water are located farther downriver.

4-6

4.2 Airborne As specified in Table 2-1 and shown in Figures 2-1 through 2-3, airborne particulate filters and charcoal canisters are collected weekly at 5 indicator stations (Stations 3, 7, 10, 12 and 16) which encircle the plant at the site periphery, at a nearby community station (Station 35) approximately 7 miles from the plant, and at a control station (Station 36) which is approximately 14 miles from the plant. At each location, air is continuously drawn through a glass fiber filter to retain airborne particulate and an activated charcoal canister is placed in series with the filter to adsorb radioiodine.

Each particulate filter is counted for gross beta activity. A quarterly gamma isotopic analysis is performed on a composite of the air particulate filters for each station. Each charcoal canister is analyzed for I-131.

As provided in Table 3-1, the 2010 annual average weekly gross beta activity was 25.8 fCi/m3 for the indicator stations. It was 1.4 fCi/m3 greater than the control station average of 24.4 fCi/m3 for the year. This difference is not statistically discernible, since it is less than the calculated MDD of 3.4 fCi/m3.

The 2010 annual average weekly gross beta activity at the Girard community station was 25.5 fCi/m3 which was 1.1 fCi/m3 greater than the control station average. This difference is not statistically discernible since it is less than the calculated MDD of 4.2 fCi/m3.

The historical trending of the average weekly gross beta air concentrations for each year of operation and the preoperational period (September, 1981 to January, 1987) at the indicator, control and community stations is plotted in Figure 4.2-1 and listed in Table 4.2-1. In general, there is close agreement between the results for the indicator, control and community stations. This close agreement supports the position that the plant is not contributing significantly to the gross beta concentrations in air.

4-7

Figure 4.2-1 Average Weekly Gross Beta Air Concentration 30 25 Concentration (fCi/m3) 20 15 10 5

0 Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Indicator Control Community MDC 4-8

Table 4.2-1 Average Weekly Gross Beta Air Concentration Period Indicator Control Community (fCi/m3) (fCi/m3) (fCi/m3)

Pre-op 22.9 22.1 21.9 1987 26.3 23.6 22.3 1988 24.7 23.7 22.8 1989 19.1 18.2 18.8 1990 19.6 19.4 18.8 1991 19.3 19.2 18.6 1992 18.7 19.3 18.0 1993 21.2 21.4 20.3 1994 20.1 20.3 19.8 1995 21.1 20.7 20.7 1996 23.3 21.0 20.0 1997 20.6 20.6 19.0 1998 22.7 22.4 20.9 1999 22.5 21.9 22.2 2000 24.5 21.5 21.1 2001 22.4 22.0 22.7 2002 19.9 18.9 18.6 2003 19.4 20.5 18.3 2004 21.6 22.8 21.4 2005 20.5 20.4 19.4 2006 25.5 24.6 24.3 2007 27.3 25.1 26.5 2008 24.0 23.2 23.7 2009 23.0 22.4 22.5 2010 25.8 24.4 25.5 4-9

During 2010, no man-made radionuclides were detected from the gamma isotopic analysis of the quarterly composites of the air particulate filters. In 1987, Cs-137 was found in one indicator composite at a concentration of 1.7 fCi/m3. During pre-operation, Cs-137 was found in approximately 12% of the indicator composites and 14% of the control composites with average concentrations of 1.7 and 1.0 fCi/m3, respectively. The MDC for airborne Cs-137 is 60 fCi/m3. Also, during pre-operation, Cs-134 was found in about 8% of the indicator composites at an average concentration of 1.2 fCi/m3. The MDC for Cs-134 is 50 fCi/m3.

The naturally occurring radionuclide Be-7 is typically detected in all indicator and control station gamma isotopic analyses of the quarterly composites of the air particulate filters. In 2010, Be-7 was not identified in plant gaseous effluents therefore it is not included in the 2010 REMP summary table for the airborne pathway samples. Be-7 has been detected in gaseous effluents in only eight of the years of plant operation. However, there was not a statistically discernible difference between the indicator and control station Be-7 concentrations in air samples in any of the years.

Airborne I-131 was not detected in any sample during 2010. During pre-operation, positive results were obtained only during the Chernobyl incident when concentrations as high as 182 fCi/m3 were observed. The MDC and RL for airborne I-131 are 70 and 900 fCi/m3, respectively.

Table 4-3 lists REMP deviations that occurred in 2010. There were five air monitoring deviations in 2010. Three deviations were due to power supply issues but the results passed Chauvenets Criterion and were retained in the data summary. A controlled burn was noted the week of July 20th near the River Road air station. The results passed Chauvenets Criterion and were retained in the data set. The other air monitoring deviation occurred due to personnel error. On 09/21/2010 after changing out the filter, the sample line was not properly reconnected and no sample was collected for the week. Personnel were reminded to double check connections after sample collection. These types of errors have been very infrequent over the years.

4-10

4.3 Direct Radiation Direct (external) radiation is measured with thermoluminescent dosimeters (TLDs). Two Panasonic UD-814 TLD badges are placed at each station. Each badge contains three phosphors composed of calcium sulfate crystals (with thulium impurity). The gamma dose at each station is based upon the average readings of the phosphors from the two badges. The badges for each station are placed in thin plastic bags for protection from moisture while in the field. The badges are nominally exposed for periods of a quarter of a year (91 days). An inspection is performed near mid-quarter to assure that all badges are on-station and to replace any missing or damaged badges.

Two TLD stations are established in each of the 16 compass sectors, to form 2 concentric rings. The inner ring (Stations 1 through 16) is located near the plant perimeter as shown in Figure 2-1 and the outer ring (Stations 17 through 32) is located at a distance of approximately 5 miles from the plant as shown in Figure 2-2. The 16 stations forming the inner ring are designated as the indicator stations. The two ring configuration of stations was established in accordance with NRC Branch Technical Position An Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. The 6 control stations (Stations 36, 37, 47, 48, 51 and 52) are located at distances greater than 10 miles from the plant as shown in Figure 2-2. Monitored special interest areas consist of the following: Station 35 at the town of Girard, and Station 43 at the employee recreational area. The TLD mean and range values presented in the Other column in Table 3-1 (page 1 of 8) includes the outer ring stations (stations 17 through 32) as well as stations 35 and 43.

As provided in Table 3-1 the average quarterly exposure measured at the indicator stations was 16.2 mR with a range of 10.6 to 25.5 mR. This average was 0.5 mR less than the average quarterly exposure measured at the control stations (16.7 mR). This difference is not statistically discernible since it is less than the MDD of 2.1 mR. Over the operational history of the site, the annual average quarterly exposures shows a variation of no more than 0.7 mR difference between the indicator and control stations. The overall average quarterly exposure for the control stations during preoperation was 1.2 mR greater than that for the indicator stations.

The quarterly exposures acquired at the outer ring stations during 2010 ranged from 10.7 to 28.2 mR with an average of 16.6 mR which was 0.1 mR less than that for the control stations. However, this difference is not discernible since it is less than the MDD of 2.3 mR. For the entire period of operation, the annual average quarterly exposures at the outer ring stations vary by no more than 1.2 mR from those at the control stations. The overall average quarterly exposure for the outer ring stations during preoperation was 1.8 mR less than that for the control stations.

The historical trending of the average quarterly exposures for the indicator inner ring, outer ring, and the control stations are plotted in Figure 4.3-1 and listed in Table 4.3-1. The decrease between 1991 and 1992 values is attributed to a change in TLDs from Teledyne to Panasonic. It should be noted however that the differences between indicator and control and outer ring values did not change.

The close agreement between the station groups supports the position that the plant is not contributing significantly to direct radiation in the environment.

4-11

Figure 4.3-1 Average Quarterly Exposure from Direct Radiation 20 18 16 14 Dose (mR) 12 10 8

6 4

2 0

Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Indicator Control Outer Ring 4-12

Table 4.3-1 Average Quarterly Exposure from Direct Radiation Period Indicator Control Outer Ring (mR) (mR) (mR)

Pre-op 15.3 16.5 14.7 1987 17.6 17.9 16.7 1988 16.8 16.1 16.0 1989 17.9 18.4 17.2 1990 16.9 16.6 16.3 1991 16.9 17.1 16.7 1992 12.3 12.5 12.1 1993 12.4 12.4 12.1 1994 12.3 12.1 11.9 1995 12.0 12.5 12.3 1996 12.3 12.2 12.3 1997 13.0 13.0 13.1 1998 12.3 12.7 12.4 1999 13.6 13.5 13.4 2000 13.5 13.6 13.5 2001 12.9 13.0 12.9 2002 12.8 12.9 12.6 2003 12.2 12.5 12.4 2004 12.4 12.2 12.3 2005 12.5 13.2 12.9 2006 13.1 12.9 13.0 2007 13.0 12.5 12.7 2008 13.3 13.0 13.1 2009 13.1 13.6 13.3 2010 16.2 16.7 16.6 4-13

The historical trending of the average quarterly exposures at the special interest areas for the same periods are provided in Figure 4.3-2 and listed in Table 4.3-2.

These exposures are within the range of those acquired at the other stations. They too, show that the plant is not contributing significantly to direct radiation at the special interest areas.

Figure 4.3-2 Average Quarterly Exposure from Direct Radiation at Special Interest Areas 25 20 Dose (mR) 15 10 5

0 Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Hunting Cabin (Sta 33) Girard (Sta 35) Rec Center (Sta 43) 4-14

Table 4.3-2 Average Quarterly Exposure from Direct Radiation at Special Interest Areas Period Station 33 Station 35 Station 43 (mR) (mR) (mR)

Pre-op 16.6 15.1 15.3 1987 21.3 18.5 15.2 1988 19.7 18.1 14.8 1989 21.2 18.7 17.4 1990 16.8 18.9 16.2 1991 17.3 19.6 17.0 1992 12.8 13.5 12.0 1993 12.9 13.3 12.1 1994 12.6 13.6 12.0 1995 13.3 13.5 12.3 1996 13.0 13.6 12.1 1997 13.8 14.4 12.7 1998 13.5 13.7 12.5 1999 NA 14.5 12.7 2000 NA 14.8 13.1 2001 NA 14.0 12.6 2002 NA 14.0 12.1 2003 NA 14.1 12.2 2004 NA 14.2 11.7 2005 NA 15.2 12.7 2006 NA 14.3 12.6 2007 NA 13.6 11.8 2008 NA 14.4 12.6 2009 NA 14.6 13.0 2010 NA 18.0 16.4 The hunting cabin activities at Station 33 have been discontinued and, consequently, this location is no longer considered as an area of special interest.

Monitoring at this location was discontinued at the end of 1998.

There were six deviations from the REMP pertaining to measuring quarterly gamma doses during 2010. In second quarter, the TLDs at Station 26 were found on the ground at mid quarter checks and were put back in place, and similarly in third quarter, the TLDs at Stations 25 and 31 were found on the ground at mid quarter. All of these results passed Chauvenets Criterion and were retained in the annual TLD data set. TLD 9A had moisture in the bag in third quarter, but the results passed Chauvenets Criterion. Also in third quarter, the TLDs from Station 5 were missing at collection time so there was no third quarter data for this station.

Most notable was in second quarter the TLD readings from Vogtle (and Hatch and Farley) were higher for the majority of the stations. This anomaly was attributed to significant problems with the Panasonic TLD reader (which was nearing obsolescence). Processing the second quarter badges was delayed about three weeks. The TLD data was kept for second quarter and the anomaly was noted.

The Panasonic system was retired at the end of 2010 and a new Inlight OSL system (which was in use for personnel monitoring in 2010), is now in use for environmental direct radiation measurements. A comparison study was done 4-15

during 2010 where the OSL badges were placed on station with the TLD badges.

The results of this study will be discussed in the 2011 REMP Report.

The standard deviation for the quarterly result for each badge was subjected to a self imposed limit of 1.4. This limit is based upon the standard deviations obtained with the Panasonic UD-814 badges during 1992 and is calculated using a method developed by the American Society of Testing and Materials (ASTM Special Technical Publication 15D, ASTM Manual on Presentation of Data and Control Chart Analysis, Fourth Revision, Philadelphia, PA, October 1976). The limit serves as a flag to initiate an investigation. To be conservative, readings with a standard deviation greater than 1.4 are excluded since the high standard deviation is interpreted as an indication of unacceptable variation in TLD response.

The readings for the following badges were deemed unacceptable since the standard deviation for each badge was greater than the self-imposed limit of 1.4:

First Quarter: V13B and V14A Second Quarter: V06A, V25A, V30B, V31B, and V32B Third Quarter: V30B Fourth Quarter: None However, for the cases when only one badge exceeded a standard deviation of 1.4, the companion badges were available and were used for determining the quarterly doses. The badges exceeding the self-imposed limit were visually inspected under a microscope and the glow curve and test results for the anneal data and the element correction factors were reviewed. No reason was evident for the high standard deviation.

4-16

4.4 Milk In accordance with Tables 2-1 and 2-2, milk samples are collected biweekly from two locations, the W. C. Dixon Dairy (Station 98) and the Girard Dairy (Station 101). Dixon Dairy was considered a control location and Girard was considered an indicator station. In June 2009, Dixon Dairy went out of business and was replaced with Seven Oaks Dairy (Station 102) as the new control location. As discussed in Section 4.1, no milk animal was found during the 2010 land use census. There were no milk sampling deviations in 2010.

Gamma isotopic and I-131 analyses are performed on each milk sample. No man-made radionuclides were identified by gamma isotopic analysis in 2010. The MDC and RL for Cs-137 in milk are 18 and 70 pCi/l, respectively. During preoperation and each year of operation through 1991, Cs-137 was found in 2 to 6% of the samples at concentrations ranging from 5 to 27 pCi/l. During preoperation, Cs-134 was detected in one sample and in the first year of operation, Zn-65 was detected in one sample. Figure 4.4-1 and Table 4.4-1 provide the historical trending of the Cs-137 concentration in milk.

Figure 4.4-1 Average Annual Cs-137 Concentration in Milk 20 18 16 Concentration (pCi/l) 14 12 10 8

6 4

2 0

Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Indicator Control MDC 4-17

Table 4.4-1 Average Annual Cs-137 Concentration in Milk Year Indicator Control (pCi/l) (pCi/l)

Pre-op 18.5 18 1987 NDM 10.4 1988 NDM 6.9 1989 NDM 7 1990 NDM 17 1991 NDM 14.2 1992 NDM NDM 1993 NDM NDM 1994 NDM NDM 1995 NDM NDM 1996 NDM NDM 1997 NDM NDM 1998 NDM NDM 1999 NDM NDM 2000 NDM NDM 2001 NDM NDM 2002 NDM NDM 2003 NDM NDM 2004 NDM NDM 2005 NDM NDM 2006 NDM NDM 2007 NDM NDM 2008 NDM NDM 2009 NDM NDM 2010 NDM NDM During 2010, I-131 was not detected in any of the milk samples. Since plant operations began in 1987, I-131 may have been detected in one sample in 1996 and two during 1990; however, its presence in these cases was questionable, due to large counting uncertainties. During preoperation, positive I-131 results were found only during the Chernobyl incident with concentrations ranging from 0.53 to 5.07 pCi/l. The MDC and RL for I-131 in milk are 1 and 3 pCi/l, respectively.

4-18

4.5 Vegetation In accordance with Tables 2-1 and 2-2, grass samples are collected monthly at two indicator locations onsite near the site boundary (Stations 7 and 15) and at one control station located about 17 miles WSW from the plant (Station 37). Gamma isotopic analyses are performed on the samples. During 2010, none of the 24 samples collected at the indicator stations were positive for the man-made radionuclide, Cs-137. Cesium-137 was not identified in the twelve control station samples. Cs-137 is often detected in environmental samples as a result of atmospheric weapons testing and the Chernobyl incident.

In 2006, one sample at the indicator station was positive for Cs-137 at a higher concentration, 491.8 pCi/kg-wet, than typically seen over the years in Vogtle vegetation samples. A duplicate sample (which is taken periodically) happened to be taken at the same collection time and also revealed a similar activity. The higher concentration more than likely resulted from plowing and seeding activities (to maintain the vegetation plot) which took place a couple of weeks prior to the sample collection.

The historical trending of the average concentration of Cs-137 at the indicator and control stations is provided in Figure 4.5-1 and listed in Table 4.5-1. No trend is recognized in this data. The MDC and RL for Cs-137 in vegetation samples are 80 and 2000 pCi/kg-wet, respectively. Cs-137 is the only man-made radionuclide that has been identified in vegetation samples during the operational history of the plant. During preoperation, Cs-137 was found in approximately 60% of the samples from indicator stations and in approximately 20% of the samples from the control station. These percentages have generally decreased during operation.

The naturally occurring radionuclide Be-7 is typically detected in indicator and control station vegetation samples. Be-7 was not detected in gaseous effluents in 2010, therefore it is not included in the REMP summary table for the airborne pathway samples. Be-7 has been detected in gaseous effluents eight of the twenty years of plant operation and is therefore of interest in the REMP program.

However, the levels of Be-7 found in the REMP make no significant contribution to dose.

In May and June of 1986 during preoperation, as a consequence of the Chernobyl incident, I-131 was found in nearly all the samples collected for a period of several weeks in the range of 200 to 500 pCi/kg-wet. The MDC and RL for I-131 in vegetation are 60 and 100 pCi/kg-wet, respectively. Also during this time period, Co-60 was found in one of the samples at a concentration of 62.5 pCi/kg-wet.

There is no specified MDC or RL for Co-60 in vegetation.

4-19

Figure 4.5-1 Average Annual Cs-137 Concentration in Vegetation 600 500 Concentration (pCi/kg-wet) 400 300 200 100 0

Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Indicator Control MDC 4-20

Table 4.5-1 Average Annual Cs-137 Concentration in Vegetation Year Indicator Control (pCi/kg-wet) (pCi/kg-wet)

Pre-op 54.6 43.7 1987 24.4 61.5 1988 38.7 NDM 1989 9.7 NDM 1990 30.0 102.0 1991 35.3 62.4 1992 38.1 144.0 1993 46.4 34.1 1994 20.7 57.4 1995 57.8 179.0 1996 NDM NDM 1997 NDM 32.6 1998 NDM 50.1 1999 37.2 NDM 2000 36.6 NDM 2001 NDM NDM 2002 NDM 98.3 2003 24.5 NDM 2004 36.8 19.7 2005 49.5 NDM 2006 23.9 491.8 2007 20.2 NDM 2008 24.6 62.1 2009 34.6 NDM 2010 NDM NDM 4-21

4.6 River Water Surface water from the Savannah River is obtained at three locations using automatic samplers. Small quantities are drawn at intervals not exceeding a few hours. The samples drawn are collected monthly; quarterly composites are produced from the monthly collections.

The collection points consist of a control location (Station 82) which is located about 0.4 miles upriver of the plant intake structure, an indicator location (Station

83) which is located about 0.4 miles downriver of the plant discharge structure, and a special location (Station 84) which is located approximately 1.3 miles downriver of the plant discharge structure. A statistically significant increase in the concentrations found in samples collected at the indicator station compared to those collected at the control station could be indicative of plant releases.

Concentrations found at the special station are more likely to represent the activity in the river as a whole, which might include plant releases combined with those from other sources along the river.

A gamma isotopic analysis is conducted on each monthly sample. As in all previous years, there were no gamma emitting radionuclides of interest detected in the 2010 river water samples.

Each quarterly composite is analyzed for tritium. As indicated in Table 3-1, the average concentration found at the indicator station was 814 pCi/l which was 579 pCi/l greater than the average at the control station (235 pCi/l). The difference between the indicator and the control station was less than the calculated MDD (2094 pCi/l). The MDD is influenced by the variability of concentrations at the indicator station from quarter to quarter. The low number of samples (four quarterly composite samples), the variability of the four sample values, and the high standard deviation contributed to the large MDD value. The MDC for tritium in river water used to supply drinking water is 2000 pCi/l and the RL is 20,000 pCi/l.

At the special river water sampling station, the results ranged from 394 pCi/l to 886 pCi/l with an average of 607 pCi/l. The difference between the average concentration at the control station and the average at the special station was less than the calculated MDD of 857 pCi/l. The decrease in tritium concentration between the indicator station and the special station is due to the additional dispersion over the 0.9 miles that separates the two stations. In the first two years of operation, the tritium concentration at the special station was somewhat greater than that at the indicator station. In recent years, the level at the special station has generally become less than the level at the indicator station.

The historical trending of the average tritium concentrations found at the special, indicator, and control stations along with the MDC for tritium is plotted on Figure 4.6-1. The data for the plot is listed in Table 4.6-1. Also included in the table are data from the calculated difference between the indicator and control stations; the MDD between the indicator and control stations; and the total curies of tritium released from the plant in liquid effluents.

4-22

The annual downriver survey of the Savannah River showed that river water is not being used for purposes of drinking or irrigation for at least 100 miles downriver (discussed in Section 4.1).

Figure 4.6-1 Average Annual H-3 Concentration in River Water 3000 2500 Concentration (pCi/l) 2000 1500 1000 500 0

Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Indicator Control Special MDC 4-23

Table 4.6-1 Average Annual H-3 Concentration in River Water Year Special Indicator Control Difference MDD Annual Site (pCi/l) (pCi/l) (pCi/l) Between (pCi/l) Tritium Indicator and Released Control (Ci)

(pCi/l)

Pre-op 1900 650 665 -15 145 NA 1987 1411 680 524 156 416 321 1988 1430 843 427 416 271 390 1989 1268 1293 538 755 518 918 1990 1081 1142 392 750 766 1172 1991 1298 1299 828 471 626 1094 1992 929 1064 371 693 714 1481 1993 616 712 238 474 1526 761 1994 774 1258 257 1001 2009 1052 1995 699 597 236 361 766 968 1996 719 1187 387 800 2147 1637 1997 686 1547 254 1293 1566 1449 1998 640 1226 196 1030 1313 1669 1999 859 2005 389 1616 1079 1674 2000 885 1564 496 1068 1786 869 2001 931 2101 743 1358 1696 1492 2002 1280 2628 437 2190 1211 1566 2003 800 1376 399 977 1706 1932 2004 743 1269 351 918 1061 1212 2005 713 800 458 342 1333 1860 2006 852 2307 384 1882 2688 2005 2007 489 879 344 535 1189 757 2008 1105 1874 832 1042 4838 1364 2009 614 1203 221 982 3551 1224 2010 607 814 235 579 2094 903 4-24

4.7 Drinking Water Samples are collected at a control location (Station 80 - the Augusta Water Treatment Plant in Augusta, Georgia located about 56 river miles upriver), and at three indicator locations (Station 87 - the Beaufort-Jasper County Water Treatment Plant near Beaufort, South Carolina, 112 river miles downriver; Station 88 - the Cherokee Hill Water Treatment Plant near Port Wentworth, Georgia, 122 river miles downriver; and Station 89 - the Purrysburg Water Treatment Plant near Purrysburg, South Carolina, located about 112 miles downriver. The Purrysburg Station was added to the REMP in January 2006.) Stations 87 and 89 are located on the same canal with the Purrysburg location at the beginning of the canal (nearer the Savannah River) and the Beaufort-Jasper location near the end of the canal. These upriver and downriver distances in river miles are the distances from the plant to the point on the river where water is diverted to the intake for each of these water treatment plants.

Water samples are taken near the intake of each water treatment plant (raw drinking water) using automatic samplers that take periodical small aliquots from the stream. These composite samples are collected monthly along with a grab sample of the processed water coming from the treatment plants (finished drinking water). Quarterly composites are made from these monthly collections for both raw and processed river water. Gross beta and gamma isotopic analyses are performed on each of the monthly samples while tritium analysis is conducted on the quarterly composites. An I-131 analysis is not required to be conducted on these samples, since the dose calculated from the consumption of water is less than 1 mrem per year (see ODCM Table 4-1). However, an I-131 analysis is conducted on each of the monthly finished water grab samples, since a drinking water pathway exists.

Provided in Figures 4.7-1 and 4.7-2 and Tables 4.7-1 and 4.7-2, are the historical trends of the average gross beta concentrations found in the monthly collections of raw and finished drinking water.

For 2010, the indicator station average gross beta concentration in the raw drinking water was 2.95 pCi/l which was 1.24 pCi/l greater than the average gross beta concentration at the control station (1.71 pCi/l). This difference is statistically discernible since it is greater than the calculated MDD of 0.57 pCi/l.

Through the years, there has been close agreement between the gross beta values at the indicator stations and the control station which supports that there is no significant gross beta contribution from the plant effluents. The required MDC for gross beta in water is 4.0 pCi/l. There is no RL for gross beta in water.

For 2010, the indicator station average gross beta concentration in the finished drinking water was 2.89 pCi/l which was 0.66 pCi/l more than the average gross beta concentration at the control station (2.23 pCi/l). This difference is not statistically discernible since it is less than the MDD of 0.73 pCi/l. The gross beta concentrations at the indicator stations ranged from 1.32 to 6.33 pCi/l while the concentrations at the control station ranged from 1.01 to 3.99 pCi/l. The required MDC for gross beta in water is 4.0 pCi/l. There is no RL for gross beta in water.

4-25

Figure 4.7-1 Average Monthly Gross Beta Concentration in Raw Drinking Water 8

7 Concentration (pCi/l) 6 5

4 3

2 1

0 Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Indicator Control MDC 4-26

Table 4.7-1 Average Monthly Gross Beta Concentration in Raw Drinking Water Period Indicator Control (pCi/l) (pCi/l)

Pre-op 2.70 1.90 1987 2.20 5.50 1988 2.67 3.04 1989 2.93 3.05 1990 2.53 2.55 1991 2.83 3.08 1992 2.73 2.70 1993 3.17 2.83 1994 3.51 3.47 1995 3.06 4.90 1996 5.83 3.02 1997 2.93 2.94 1998 3.31 2.58 1999 4.10 4.37 2000 4.52 3.59 2001 3.21 2.94 2002 3.09 2.61 2003 3.73 2.59 2004 4.06 2.39 2005 3.75 2.48 2006 3.85 2.93 2007 4.00 3.13 2008 3.46 2.37 2009 3.28 2.26 2010 2.95 1.71 4-27

Figure 4.7-2 Average Monthly Gross Beta Concentration in Finished Drinking Water 4.5 4

3.5 Concentration (pCi/l) 3 2.5 2

1.5 1

0.5 0

Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Indicator Control MDC 4-28

Table 4.7-2 Average Monthly Gross Beta Concentration in Finished Drinking Water Period Indicator Control (pCi/l) (pCi/l)

Pre-op 2.90 1.80 1987 2.10 1.80 1988 2.28 2.35 1989 2.36 2.38 1990 2.08 1.92 1991 1.90 1.53 1992 2.09 1.67 1993 2.23 2.30 1994 2.40 2.68 1995 2.74 2.32 1996 2.19 2.21 1997 2.38 1.77 1998 3.23 1.67 1999 3.23 3.21 2000 3.39 2.68 2001 2.67 2.00 2002 2.80 2.61 2003 2.51 2.34 2004 2.36 1.92 2005 2.61 2.00 2006 3.23 3.25 2007 3.19 3.36 2008 2.86 2.07 2009 2.53 2.13 2010 2.89 2.23 4-29

As provided in Table 3-1, there were no positive results during 2010 for the radionuclides of interest from the gamma isotopic analysis of the monthly collections for both raw and finished drinking water. Only one positive result has been found since operation began. Be-7 was found at a concentration of 68.2 pCi/l in the sample collected for September 1987 at Station 87. During preoperation Be-7 was found in about 5% of the samples at concentrations ranging from 50 to 80 pCi/l. The MDC assigned for Be-7 in water is 124 pCi/l. Also during preoperation, Cs-134 and Cs-137 were detected in about 7% of the samples at concentrations on the order of their MDCs which are 15 and 18 pCi/l, respectively.

I-131 was detected in finished drinking water in 1997 at levels near the MDC.

This was the first occurrence for detecting I-131 in finished drinking water since operation began. During preoperation, it was detected in only one of 73 samples at a concentration of 0.77 pCi/l at Port Wentworth. The MDC and RL for I-131 in drinking water are 1 and 2 pCi/l, respectively.

Figures 4.7-3 and 4.7-4 and Tables 4.7-3 and 4.7-4 provide historical trending for the average tritium concentrations found in the quarterly composites of raw and finished drinking water collected at the indicator and control stations. The tables also list the calculated differences between the indicator and control stations, and list the MDDs between these two station groups.

The graphs and tables show that the tritium concentrations in the drinking water samples, both raw and finished, have been gradually trending downward since 1988. The small increase in average concentrations at the indicator stations for 1991 and 1992 reflect the impact of the inadvertent release from SRS of 7,500 Ci of tritium to the Savannah River about 10 miles downriver of VEGP, in December 1991 (SRS release data was obtained from Release of 7,500 Curies of Tritium to the Savannah River from the Savannah River Site, Georgia Department of National Resources, Environmental Protection Division, Environmental Radiation Program, January 1992).

The 2010 raw drinking water indicator stations average tritium was 343 pCi/l which was 99 pCi/l greater than the average of the two positive concentrations found at the control station (244 pCi/l). The difference between the two averages was not statistically discernible since it was less than the MDD of 205 pCi/l. The MDC and RL for tritium in drinking water are 2000 pCi/l and 20,000 pCi/l, respectively.

The finished drinking water average tritium concentration at the indicator stations during 2010 was 374 pCi/l which was 112 pCi/l greater than the one positive concentration found at the control station (262 pCi/l). Application of the modified Students t-test shows that the difference between the average at the indicator stations and the single value at the control station is not statistically discernible.

The MDC and RL for tritium in drinking water are 2000 pCi/l and 20,000 pCi/l, respectively.

4-30

Figure 4.7-3 Average Annual H-3 Concentration in Raw Drinking Water 3000 2500 Concentration (pCi/l) 2000 1500 1000 500 0

Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Indicator Control MDC 4-31

Table 4.7-3 Average Annual H-3 Concentration in Raw Drinking Water Period Indicator Control Difference MDD (pCi/l) (pCi/l) Between Ind. & (pCi/l)

Control (pCi/l)

Pre-op 2300 400 1900 1987 2229 316 1913 793 1988 2630 240 2390 580 1989 2508 259 2249 1000 1990 1320 266 1054 572 1991 1626 165 1461 834 1992 1373 179 1194 353 1993 955 NDM 955 NA 1994 871 NDM 871 NA 1995 917 201 716 NA 1996 1014 207 807 151 1997 956 230 726 61 1998 791 160 631 NA 1999 908 NDM 908 NA 2000 1020 373 647 704 2001 889 525 364 NA 2002 938 304 634 284 2003 563 203 360 NA 2004 585 220 365 204 2005 463 393 70 301 2006 690 451 239 394 2007 462 357 105 NA 2008 726 386 340 269 2009 602 587 15 NA 2010 343 244 99 205 4-32

Figure 4.7-4 Average Annual H-3 Concentration in Finished Drinking Water 3500 3000 Concentration (pCi/l) 2500 2000 1500 1000 500 0

Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Indicator Control MDC 4-33

Table 4.7-4 Average Annual H-3 Concentration in Finished Drinking Water Period Indicator Control Difference MDD (pCi/l) (pCi/l) Between Ind. & (pCi/l)

Control (pCi/l)

Pre-op 2900 380 2520 1987 2406 305 2101 1007 1988 2900 270 2630 830 1989 2236 259 1977 627 1990 1299 404 895 1131 1991 1471 225 1246 647 1992 1195 211 984 427 1993 993 NDM 993 NA 1994 880 131 749 270 1995 847 279 568 NA 1996 884 168 716 NA 1997 887 221 666 383 1998 713 180 533 NA 1999 920 263 657 NA 2000 1043 251 792 833 2001 1037 516 521 NA 2002 1060 340 720 416 2003 473 196 277 NA 2004 531 255 276 314 2005 546 223 323 NA 2006 688 710 22 NA 2007 494 229 265 NA 2008 661 391 270 468 2009 579 667 88 NA 2010 374 262 112 NA 4-34

4.8 Fish Table 2-1 requires the collection of at least one sample of any anadromous species of fish in the vicinity of the plant discharge during the spring spawning season, and for the semi-annual collection of at least one sample of any commercially or recreationally important species in the vicinity of the plant discharge area and in an area not influenced by plant discharges. Table 2-1 specifies that a gamma isotopic analysis be performed on the edible portions of each sample collected.

As provided in Table 2-2, a 5-mile stretch of the river is generally needed to obtain adequate fish samples. For the semiannual collections, the control location (Station 81) extends from approximately 2 to 7 miles upriver of the plant intake structure, and the indicator location (Station 85) extends from about 1.4 to 7 miles downriver of the plant discharge structure. For anadromous species, all collection points can be considered as indicator stations.

Anadromous fish were collected during the spring spawning season and no man-made radioisotopes were identified in the sample. In all but three previous years of operation, no radionuclides were detected in anadromous fish samples. In 2005, Cs-137 was detected in the anadromous fish sample at a low level of 28.8 pCi/kg-wet. In 1987, as well as in 1991, Cs-137 was found in a single sample of American Shad at concentrations of 10 and 12 pCi/kg-wet, respectively.

The dates and compositions of the semi-annual catches at the indicator and control stations during 2010 are shown below.

Date Indicator Control April 13 Largemouth Bass Largemouth Bass November 23 Largemouth Bass Largemouth Bass As indicated in Table 3-1, Cs-137 was found in the semiannual collections of a commercially or recreationally important species of fish and in fish at the control station. It has been found in all but 5 samples collected during operation and in all but 5 of the 32 samples collected during preoperation. As provided in Table 3-1, 42.8 pCi/kg-wet was the average Cs-137 detected in the two samples from the indicator station, and 74.3 pCi/kg-wet was the average Cs-137 detected at the control station. The difference is not statistically significant since it is less than the MDD of 284 pCi/kg-wet. No discernible difference between the indicator and contorl stations has occurred for any year of operation or during pre-operation.

Figure 4.8-1 and Table 4.8-1 provide the historical trending of the average concentrations of Cs-137 in units of pCi/kg-wet found in fish samples at the indicator and control stations. The indicator station fish sample concentration of Cs-137 in 1999 was greatly influenced by a largemouth bass collected in October with a concentration of 2500 pCi/kg-wet. Other than the fact that largemouth bass are predators that concentrate Cs-137, no specific cause for the elevated concentration in this sample is known. No trend is recognized in this data. The MDC and RL for Cs-137 in fish are 150 and 2000 pCi/kg-wet, respectively.

4-35

Figure 4.8-1 Average Annual Cs-137 Concentration in Fish 900 800 Concentration (pCi/kg-wet) 700 600 500 400 300 200 100 0

Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Indicator Control MDC 4-36

Table 4.8-1 Average Annual Cs-137 Concentration in Fish Year Indicator Control (pCi/kg-wet) (pCi/kg-wet)

Pre-op 590 340 1987 337 119 1988 66 116 1989 117 125 1990 103 249 1991 105 211 1992 178 80 1993 360 84 1994 165 200 1995 125 96 1996 194 404 1997 93 139 1998 190 200 1999 848 221 2000 55 96 2001 48 39 2002 59 133 2003 62 21 2004 56.4 26.0 2005 39.3 40.2 2006 257 35.7 2007 58.7 37.7 2008 39.4 47.0 2009 NDM 30.4 2010 42.8 74.4 The only other radionuclide found in fish samples during operation is I-131. In 1989, it was found in one sample at the indicator station at a concentration of 18 pCi/kg-wet. In 1990, it was found in one sample at the indicator station and in one sample at the control station, at concentrations of 13 and 12 pCi/kg-wet, respectively. The MDC assigned to I-131 in fish is 53 pCi/kg-wet. In the November 2008 collection, the Largemouth Bass sample from the control location showed 90 pCi/kg-wet of I-131. The specific source of the I-131 is unknown but is likely due to medical waste.

During preoperation, Cs-134 was found in two of the 17 samples collected at the control station at concentrations of 23 and 190 pCi/kg-wet. The MDC and RL for Cs-134 are 130 and 1000 pCi/kg-wet, respectively. Nb-95 was also found in one of the control station samples at a concentration of 34 pCi/kg-wet. The assigned MDC and calculated RL for Nb-95 are 50 and 70,000 pCi/kg-wet, respectively.

4-37

4.9 Sediment Sediment was collected along the shoreline of the Savannah River on April 6 and October 5, 2010 at Stations 81 and 83. Station 81 is a control station located about 2.5 miles upriver of the plant intake structure while Station 83 is an indicator station located about 0.6 miles downriver of the plant discharge structure. A gamma isotopic analysis was performed on each sample. The radionuclides of interest identified in 2010 samples were Be-7 and Cs-137.

Be-7, which is abundant in nature, was not identified in plant liquid effluents during 2010. However, it continues to be trended in river sediment in the REMP report. In 2010, the average at the indicator station was 1217 pCi/kg-dry and at the control station the average concentration was 533 pCi/kg-dry. The difference (684 pCi/kg-dry) is not statistically discernible because it is less than the calculated MDD of 3156 pCi/kg-dry. Due to the low number of samples, the variability of Be-7 activity found in them, and the high standard deviation the MDD value is very high. Because Be-7 has not been identified in plant effluents for the past several years and because there continues to be no significant difference between the indicator and control station, the Be-7 found at the indicator station is not attributed to plant releases.

For Cs-137, the average concentration at the indicator station during 2010 was 164.6 pCi/kg-dry which was 100.5 pCi/kg-dry greater than that at the control station (64.1 pCi/kg-dry). The difference between the average value at the indicator station and the average value at the control station is not statistically discernible since it is less than the calculated MDD of 189 pCi/kg-dry. However, the concentration of Cs-137 found at the indicator station could be attributed to plant effluents or to other facilities that release radioactive effluents in the vicinity of the plant. The Cs-137 level at the indicator station has averaged nearly 100 pCi/kg-dry greater than that at the control station over the entire period of operation. During preoperation, the Cs-137 was 170 pCi/kg-dry greater at the indicator station than at the control station.

During 2010, Co-60 was not detected in any of the four sediment samples.

Cobalt-60 has been detected in sediment collected at the indicator station every year of plant operation but four. The concentrations of Co-60 often found at the indicator station could be attributed to plant releases or, potentially, to other facilities that release radioactive effluents in the vicinity of the plant.

The historical average concentrations of Be-7, Co-58, Co-60, and Cs-137 in sediment are plotted in Figures 4.9-1 through 4.9-4 along with listings of their concentrations in Tables 4.9-1 through 4.9-4. The concentrations of the solely man-made nuclides (Co-58, Co-60, & Cs-137) are consistent with past average concentrations. No pattern has been detected. Be-7, produced by man and nature, is also within the range that is typically seen.

4-38

During preoperation, Zr-95, Nb-95, Cs-134, and Ce-141 were detected in at least one of the control station samples and Nb-95 was detected in one of the indicator station samples. Be-7 and Cs-137 were found in several of the samples. The concentrations of these preoperational nuclides were on the order of their respective MDC values. The presence of these preoperational nuclides could be attributed to atmospheric weapons testing and the Chernobyl incident.

Mn-54 and I-131 were found sporadically over several years of operation. A summary of the positive results for these nuclides along with their applicable MDCs is provided in Table 4.9-5.

Figure 4.9-1 Average Annual Be-7 Concentration in Sediment 3500 3000 Concentration (pCi/kg-dry) 2500 2000 1500 1000 500 0

Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Indicator Control MDC 4-39

Table 4.9-1 Average Annual Be-7 Concentration in Sediment MDC=655 pCi/kg-dry Year Indicator Control (pCi/kg-dry) (pCi/kg-dry)

Pre-op 580 500 1987 987 543 1988 970 810 1989 1300 415 1990 465 545 1991 826 427 1992 2038 380 1993 711 902 1994 1203 964 1995 1865 1575 1996 1925 831 1997 1130 1028 1998 1396 1016 1999 662 769 2000 1526 3324 2001 1697 2614 2002 742 1254 2003 1150 903 2004 1309 905 2005 1931 1086 2006 1254 704 2007 1034 1274 2008 394 805 2009 2011 1131 2010 1217 533 4-40

Figure 4.9-2 Average Annual Co-58 Concentration in Sediment 300 250 Concentration (pCi/kg-dry) 200 150 100 50 0

Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Indicator Control MDC 4-41

Table 4.9-2 Average Annual Co-58 Concentration in Sediment MDC=43 pCi/kg-dry Year Indicator Control (pCi/kg-dry) (pCi/kg-dry)

Pre-op NDM NDM 1987 NDM NDM 1988 190 NDM 1989 135 NDM 1990 140 NDM 1991 NDM NDM 1992 124 NDM 1993 NDM NDM 1994 18.4 NDM 1995 42.4 NDM 1996 274 NDM 1997 NDM NDM 1998 NDM NDM 1999 NDM NDM 2000 NDM NDM 2001 NDM NDM 2002 NDM NDM 2003 NDM NDM 2004 NDM NDM 2005 NDM NDM 2006 NDM NDM 2007 NDM NDM 2008 NDM NDM 2009 NDM NDM 2010 NDM NDM 4-42

Figure 4.9-3 Average Annual Co-60 Concentration in Sediment 400 350 Concentration (pCi/kg-dry) 300 250 200 150 100 50 0

Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Indicator Control MDC 4-43

Table 4.9-3 Average Annual Co-60 Concentration in Sediment MDC=70 pCi/kg-dry Year Indicator Control (pCi/kg-dry) (pCi/kg-dry)

Pre-op NDM NDM 1987 NDM NDM 1988 62 NDM 1989 46 NDM 1990 46 NDM 1991 113 NDM 1992 59.5 NDM 1993 65.9 NDM 1994 85.2 NDM 1995 267 NDM 1996 344 NDM 1997 86 NDM 1998 263 NDM 1999 49.5 NDM 2000 131.3 NDM 2001 NDM NDM 2002 49.7 NDM 2003 146 NDM 2004 77 NDM 2005 146 NDM 2006 40 NDM 2007 NDM NDM 2008 61.9 NDM 2009 NDM NDM 2010 NDM NDM 4-44

Figure 4.9-4 Average Annual Cs-137 Concentration in Sediment 600 500 Concentration (pCi/kg-dry) 400 300 200 100 0

Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Indicator Control MDC 4-45

Table 4.9-4 Average Annual Cs-137 Concentration in Sediment MDC=180 pCi/kg Year Indicator Control (pCi/kg) (pCi/kg)

Pre-op 320 150 1987 209 111 1988 175 175 1989 230 125 1990 155 140 1991 246 100 1992 259 111 1993 345 115 1994 240 118 1995 357 123 1996 541 93 1997 184 98 1998 316 122 1999 197 97 2000 138 218 2001 252 118 2002 189 60 2003 171 90 2004 149 100 2005 263 89 2006 142 68 2007 125 83 2008 66.2 60.9 2009 127.7 103.2 2010 164.6 64.1 Table 4.9-5 Additional Sediment Nuclide Concentrations Nuclide YEAR Indicator Control MDC (pCi/kg-dry) (pCi/kg-dry) (pCi/kg-dry)

Mn-54 1988 22 NDM 1989 18 NDM 42 1994 32 NDM I-131 1992 194 20 53 1994 51 41 4-46

4.10 Groundwater As nuclear plants began to undergo decommissioning in the late 1990s to early 2000s, instances of subsurface and/or groundwater contamination were identified.

In addition, several operating facilities also identified groundwater contamination resulting from spills and leaks or equipment failure. In one instance, low levels of licensed material were detected in a private well located on property adjacent to a nuclear power plant.

In 2006, NEI (Nuclear Energy Institute) formed a task force to address monitoring onsite groundwater for radionuclides at nuclear facilities. A Groundwater Protection Initiative was developed which was adopted by all U.S. commercial operating nuclear plants.

The NRC also formed a task force to study the groundwater issues and released Information Notice 2006-13, Ground-water Contamination due to Undetected Leakage of Radioactive Water, which summarized its review of radioactive contamination of ground water at multiple facilities as a result of undetected leakage from structures, systems, and components that contain or transport radioactive fluids. Licensees were instructed to review the information for applicability and to consider appropriate actions to avoid similar problems.

The NEI task force felt it was prudent for the industry to update site hydrology information and to develop radiological groundwater monitoring plans at each site. These groundwater protection plans would ensure that underground leaks and spills would be addressed promptly. Additionally, the task force recommended developing a communications protocol to report radioactive leaks or spills that entered groundwater (or might eventually enter groundwater) to the NRC and State / Local government officials as needed. NEI-07-07, Industry Groundwater Protection Final Guidance Document, was developed by the task force to document the guidelines recommended for the industry.

To ensure compliance with NEI-07-07, Southern Nuclear developed the Nuclear Management Procedure, Radiological Groundwater Protection Program. The procedure contains detailed site-specific monitoring plans, program technical bases, and communications protocol (to ensure that radioactive leaks and spills are addressed and communicated appropriately). In an effort to prevent future leaks of radioactive material to groundwater, SNC plants have established detailed buried piping and tanks inspection programs.

In 2006, Vogtle sampled onsite drinking water deep wells and onsite makeup water deep wells for tritium and gamma isotopic activity. These wells did not contain detectable amounts of radioactivity. In 2007, Vogtle implemented a more extensive radiological groundwater monitoring program. A qualified hydrologist made recommendations for drilling additional onsite monitoring wells and updated the site hydrology information. Eight new wells and 17 existing wells comprise the current VEGP groundwater monitoring program (see Table 2-3).

These locations were sampled twice in the latter portion of 2007. Several wells were positive for tritium but no gamma emitters were detected. The highest activity sample showed approximately 900 pCi/l of tritium. This level of tritium is typical background for the area around Plant Vogtle based on historical information from Georgia Department of Natural Resources and Savannah River Site. Drinking water wells, sewage treatment plant effluent, and several surface 4-47

water locations supplement the monitoring program and were also sampled in 2007. None of these locations showed activity above typical environmental levels in this area. This is also true of the 2008 supplemental sampling.

The tritium levels in the water table since the radiological groundwater sampling program started in mid-2007 through 2010 are graphed in Figures 4.10-1, 4.10-2, and 4.10-3. The February 2008 sampling event appears to be an outlier, however, more data is needed to determine seasonal changes and typical fluctuations in tritium concentration due to rain washout and recharge of the aquifer. None of the tertiary aquifer wells have shown tritium concentrations above background.

In 2008, three of the monitoring wells (1013, 1003, and 1004) used for groundwater monitoring (but not newly drilled for the program) were retired due to preliminary construction activities of two potential new operating reactors.

These wells were not critical to the radiological groundwater monitoring program as they were upgradient and used primarily to obtain background data for site characterization.

In 2009, upgradient well 805-A had silted in and is now only being used for groundwater level data. In 2010, tertiary aquifer wells 27 and 29 were no longer sampled due to structural issues with the wells that made sampling extremely labor intensive. It was determined that enough background data had been gathered from these wells.

In 2010, tritium concentrations observed in the Vogtle groundwater monitoring wells fluctuated but did not exceed the newly established Administrative Control Limits (ACLs). The ACLs were derived based on previous years tritium results and total measurement uncertainty and are site specific by plant and aquifer.

There are no reporting requirements associated with exceeding an ACL but additional actions would be taken to verify no new sources of tritium were contributing to the increase. For the deeper aquifer sampled at Vogtle, the ACL is 1600 pCi/L and for the surficial aquifer, the ACL is 2100 pCi/L.

4-48

5.0 INTERLABORATORY COMPARISON PROGRAM In accordance with ODCM 4.1.3, the EL participates in an ICP that satisfies the requirements of Regulatory Guide 4.15, Revision 1, "Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment", February 1979. The guide indicates the ICP is to be conducted with the Environmental Protection Agency (EPA) Environmental Radioactivity Laboratory Intercomparison Studies (Cross-check) Program or an equivalent program, and the ICP should include all of the determinations (sample medium/radionuclide combinations) that are offered by the EPA and included in the REMP.

The ICP is conducted by Analytics, Inc. of Atlanta, Georgia. Analytics has a documented Quality Assurance (QA) program and the capability to prepare Quality Control (QC) materials traceable to the National Institute of Standards and Technology. The ICP is a third party blind testing program which provides a means to ensure independent checks are performed on the accuracy and precision of the measurements of radioactive materials in environmental sample matrices.

Analytics supplies the crosscheck samples to the EL which performs the laboratory analyses in a normal manner. Each of the specified analyses is performed three times. The results are then sent to Analytics who performs an evaluation which may be helpful to the EL in the identification of instrument or procedural problems.

The samples offered by Analytics and included in the EL analyses are gross beta and gamma isotopic analyses of an air filter; gamma isotopic analyses of milk samples; and gross beta, tritium and gamma isotopic analyses of water samples.

The accuracy of each result is measured by the normalized deviation, which is the ratio of the reported average less the known value to the total error. The total error is the square root of the sum of the squares of the uncertainties of the known value and of the reported average. The uncertainty of the known value includes all analytical uncertainties as reported by Analytics. The uncertainty of the reported average is the propagated error of the values in the reported average by the EL.

The precision of each result is measured by the coefficient of variation, which is defined as the standard deviation of the reported result divided by the reported average. An investigation is undertaken whenever the absolute value of the normalized deviation is greater than three or whenever the coefficient of variation is greater than 15% for all radionuclides other than Cr-51 and Fe-59. For Cr-51 and Fe-59, an investigation is undertaken when the coefficient of variation exceeds the values shown as follows:

Nuclide Concentration

• Total Sample Activity Percent Coefficient (pCi) of Variation Cr-51 <300 NA 25 Cr-51 NA >1000 25 Cr-51 >300 <1000 15 Fe-59 <80 NA 25 Fe-59 >80 NA 15

• For air filters, concentration units are pCi/filter. For all other media, concentration units are pCi/liter (pCi/l).

5-1

As required by ODCM 4.1.3.3 and 7.1.2.3, a summary of the results of the EL's participation in the ICP is provided in Table 5-1 for: the gross beta and gamma isotopic analyses of an air filter; gamma isotopic analyses of milk samples; and gross beta, tritium and gamma isotopic analyses of water samples. Delineated in this table for each of the media/analysis combinations, are: the specific radionuclides; Analytics preparation dates; the known values with their uncertainties supplied by Analytics; the reported averages with their standard deviations; and the resultant normalized deviations and coefficients of variation expressed as a percentage.

In 2010, the laboratory analyzed 9 samples for 35 parameters. The analyses included tritium, gross beta and gamma emitting radio-nuclides in different matrices. The attached results indicate two analyses outside the acceptance limits for accuracy. The activity recovery of Cr-51 and Fe-59 in air filters was above the upper acceptance limit for accuracy.

The analysis of Cr-51 and Fe-59 is performed by gamma spectroscopy, with the value determined by a weighted average of four germanium detectors. In a 2005 investigation a positive bias was determined to exist in the analysis based on summing of nuclides in the calibration standard. The detectors are calibrated on a three year geometry rotation. The air filter geometry calibration was scheduled and completed in 2010. The sample analysis results indicate further investigations should be performed into the biases associated with this matrix in 2011.

5-2

TABLE 5-1 (SHEET 1 of 3)

INTERLABORATORY COMPARISON PROGRAM RESULTS GROSS BETA ANALYSIS OF AN AIR FILTER (pCi/filter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Gross Beta 09/16/10 75.40 85.80 1.91 0.48 5.86 -2.36 GAMMA ISOTOPIC ANALYSIS OF AN AIR FILTER (pCi/filter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Ce-141 09/16/10 142.70 142.00 5.99 0.79 9.77 0.05 Co-58 09/16/10 91.40 80.30 4.3 0.45 7.89 1.54 Co-60 09/16/10 196.90 186.00 3.52 1.04 3.47 1.59 Cr-51 09/16/10 345.10 255.00 47.02 1.42 24.68 1.06 Cs-134 09/16/10 90.90 101.00 2.01 0.56 5.04 -2.19 Cs-137 09/16/10 115.10 103.00 4.28 0.57 4.79 2.19 5-3 Fe-59 09/16/10 128.70 99.40 27.63 0.55 20.97 1.08 Mn-54 09/16/10 150.90 130.00 2.21 0.73 5.10 2.72 Zn-65 09/16/10 263.40 222.00 16.73 1.24 7.13 2.20 GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (pCi/liter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Ce-141 06/17/10 108.60 110.00 3.43 0.61 7.06 -0.18 Co-58 06/17/10 101.10 101.00 7.89 0.56 9.22 0.01 Co-60 06/17/10 198.60 197.00 5.92 1.09 14.97 0.05 Cr-51 06/17/10 351.40 339.00 32.24 1.89 14.01 0.25 Cs-134 06/17/10 119.60 126.00 5.23 0.70 6.32 -0.85 Cs-137 06/17/10 159.80 150.00 5.87 0.84 20.46 0.30

TABLE 5-1 (SHEET 2 of 3)

INTERLABORATORY COMPARISON PROGRAM RESULTS GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (pCi/liter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Fe-59 06/17/10 141.00 119.00 1.16 0.66 8.17 1.91 I-131 06/17/10 105.80 96.90 1.29 0.54 6.58 1.28 Mn-54 06/17/10 180.20 169.00 5.45 0.94 5.09 1.22 Zn-65 06/17/10 223.40 206.00 4.52 1.15 7.65 1.02 GROSS BETA ANALYSIS OF WATER SAMPLE (pCi/liter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Gross Beta 03/18/10 270.90 293.00 15.73 1.63 7.72 -1.06 5-4 06/17/10 264.00 266.00 8.8 1.48 6.42 -0.12 GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (pCi/liter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Ce-141 03/18/10 273.20 263.00 1.31 1.47 4.16 0.89 Co-58 03/18/10 146.80 144.00 5.93 0.48 6.07 0.32 Co-60 03/18/10 185.80 185.00 7.46 1.03 5.20 0.09 Cr-51 03/18/10 389.00 364.00 45.91 2.03 13.51 0.48 Cs-134 03/18/10 167.80 179.00 4.46 1.00 4.66 -1.43 GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (pCi/liter)

TABLE 5-1 (SHEET 3 of 3)

INTERLABORATORY COMPARISON PROGRAM RESULTS Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Cs-137 03/18/10 166.40 159.00 10.97 0.89 7.23 0.62 Fe-59 03/18/10 154.80 138.00 18.72 0.77 11.00 0.99 I-131 03/18/10 71.70 72.70 1.4 0.40 8.44 -0.09 Mn-54 03/18/10 219.80 209.00 16.06 1.16 8.88 0.55 Zn-65 03/18/10 281.60 256.00 4.16 3 8.06 1.13 TRITIUM ANALYSIS OF WATER SAMPLES (pCi/liter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation H-3 03/18/10 10480.70 12000.00 980.83 67 9.67 -1.50 5-5 06/17/10 9595.20 9630.00 177.19 53.67 2.97 -0.12 I-131 ANALYSIS OF AN AIR CARTRIDGE (pCi/cartridge)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation I-131 06/17/10 75.50 79.80 1.36 3.10 4.10 -1.39

6.0 CONCLUSION

S This report confirms the licensee's conformance with the requirements of Chapter 4 of the ODCM. It provides a summary and discussion of the results of the laboratory analyses for each type of sample.

In 2010, there was one instance in which the indicator station readings were statistically discernible from the control station readings. This is discussed in detail below. No discernible radiological impact upon the environment or the public as a consequence of plant discharges to the atmosphere and to the river was established for any other REMP samples.

The indicator station average gross beta concentration in the raw drinking water was 2.95 pCi/l which was 1.24 pCi/l greater than the average gross beta concentration at the control station (1.71 pCi/l). This difference is statistically discernible since it is greater than the calculated MDD of 0.57 pCi/l. Gross beta is a screening analysis for beta activity. Through the years, there has been close agreement between the gross beta values at the indicator stations and the control station which supports that there is no significant gross beta contribution from the plant effluents. The required MDC for gross beta in water is 4.0 pCi/l. There is no RL for gross beta in water.

The radiological levels reported in 2010 were low. The REMP trends over the course of time from preoperation to the present are generally decreasing or have remained fairly constant. This supports the conclusion that there is no adverse radiological impact on the environment or to the public as a result of the operation of Plant Vogtle.

6-1

JOSEPH M. FARLEY NUCLEAR PLANT ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2010

TABLE OF CONTENTS Section and/or Title Subsection Page List of Figures ii List of Tables iii List of Acronyms iv 1.0 Introduction 1-1 2.0 REMP Description 2-1 3.0 Results Summary 3-1 4.0 Discussion of Results 4-1 4.1 Land Use Census 4-6 4.2 Airborne 4-7 4.3 Direct Radiation 4-13 4.4 Milk 4-17 4.5 Forage 4-21 4.6 Ground Water 4-27 4.7 Surface Water 4-32 4.8 Fish 4-35 4.9 Sediment 4-41 5.0 Interlaboratory Comparison Program 5-1 6.0 Conclusions 6-1 i

LIST OF FIGURES Figure Number Title Page Figure 2-1 REMP Stations Near the Plant Perimeter 2-10 Figure 2-2 REMP Stations 2 to 5 Miles from the Plant 2-11 Figure 2-3 REMP Stations Beyond 5 Miles from the Plant 2-12 Figure 2-4 Onsite Ground Water Monitoring Locations 2-13 Figure 4.2-1 Average Weekly Gross Beta Air Concentration 4-8 Figure 4.2-2 Average Annual Cs-137 Concentration in Air 4-10 Figure 4.3-1 Average Quarterly Exposure from Direct Radiation 4-14 Figure 4.4-1 Average Annual Cs-137 Concentration in Milk 4-17 Figure 4.4-2 Average Annual I-131 Concentration in Milk 4-19 Figure 4.5-1 Average Annual Cs-137 Concentration in Forage 4-22 Figure 4.5-2 Average Annual I-131 Concentration in Forage 4-24 Figure 4.6-1 Average Annual H-3 Concentration in Offsite Ground 4-28 Water Figure 4.6-2 H-3 Concentration in Onsite Ground Water Well R-3 4-31 Figure 4.7-1 Average Annual H-3 Concentration in Surface Water 4-33 Figure 4.8-1 Average Annual Cs-137 Concentration in Bottom Feeding Fish 4-36 Figure 4.8-2 Average Annual Cs-137 Concentration in Game Fish 4-38 Figure 4.9-1 Average Annual Cs-134 Concentration in Sediment 4-42 Figure 4.9-2 Average Annual Cs-137 Concentration in Sediment 4-43 ii

LIST OF TABLES Table Number Title Page Table 2-1 Summary Description of Radiological Environmental Monitoring Program 2-2 Table 2-2 Onsite Groundwater Monitoring Locations 2-9 Table 3-1 Radiological Environmental Monitoring Program Annual Summary 3-2 Table 4-1 Minimum Detectable Concentrations (MDC) 4-1 Table 4-2 Reporting Levels (RL) 4-2 Table 4-3 Deviations from Radiological Environmental Monitoring Program 4-4 Table 4.1-1 Land Use Census Results 4-6 Table 4.2-1 Average Weekly Gross Beta Air Concentration 4-9 Table 4.2-2 Average Annual Cs-137 Concentration in Air 4-11 Table 4.3-1 Average Quarterly Exposure from Direct Radiation 4-15 Table 4.4-1 Average Annual Cs-137 Concentration in Milk 4-18 Table 4.4-2 Average Annual I-131 Concentration in Milk 4-20 Table 4.5-1 Average Annual Cs-137 Concentration in Forage 4-23 Table 4.5-2 Average Annual I-131 Concentration in Forage 4-25 Table 4.6-1 Average Annual H-3 Concentration in Ground Water 4-29 Table 4.7-1 Average Annual H-3 Concentration in Surface Water 4-34 Table 4.8-1 Average Annual Cs-137 Concentration in Bottom Feeding Fish 4-37 Table 4.8-2 Average Annual Cs-137 Concentration in Game Fish 4-39 Table 4.9 Sediment Nuclide Concentrations 4-41 Table 5-1 Interlaboratory Comparison Program Results 5-3 iii

LIST OF ACRONYMS Acronyms presented in alphabetical order Acronym Definition APCo Alabama Power Company ASTM American Society for Testing and Materials CL Confidence Level EL Georgia Power Company Environmental Laboratory EPA Environmental Protection Agency FNP Joseph M. Farley Nuclear Plant ICP Interlaboratory Comparison Program MDC Minimum Detectable Concentration MDD Minimum Detectable Difference MWe MegaWatts Electric NA Not Applicable NDM No Detectable Measurement(s)

NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual Po Preoperation PWR Pressurized Water Reactor REMP Radiological Environmental Monitoring Program RL Reporting Level RM River Mile TLD Thermoluminescent Dosimeter TS Technical Specification iv

1.0 INTRODUCTION

The Radiological Environmental Monitoring Program (REMP) for 2010 was conducted in accordance with Chapter 4 of the Offsite Dose Calculation Manual (ODCM). The REMP activities for 2010 are reported herein in accordance with Technical Specification (TS) 5.6.2 and ODCM 7.1.

The objectives of the REMP are to:

1) Determine the levels of radiation and the concentrations of radioactivity in the environs and;

2) Assess the radiological impact (if any) to the environment due to the operation of the Joseph M. Farley Nuclear Plant (FNP).

The assessments include comparisons between results of analyses of samples obtained at locations where radiological levels are not expected to be affected by plant operation (control stations) and at locations where radiological levels are more likely to be affected by plant operation (indicator stations), as well as comparisons between preoperational and operational sample results.

FNP is owned by Alabama Power Company (APCo) and operated by Southern Nuclear Operating Company. It is located in Houston County, Alabama approximately fifteen miles east of Dothan, Alabama on the west bank of the Chattahoochee River. Unit 1, a Westinghouse Electric Corporation Pressurized Water Reactor (PWR) with a licensed core thermal power output of 2775 MegaWatts thermal (MWt), achieved initial criticality on August 9, 1977 and was declared "commercial" on December 1, 1977. Unit 2, also a 2775 MWt Westinghouse PWR, achieved initial criticality on May 8, 1981 and was declared "commercial" on July 30, 1981.

The preoperational stage of the REMP began with initial sample collections in January of 1975. The transition from the preoperational to the operational stage of the REMP was marked by Unit 1 initial criticality.

A description of the REMP is provided in Section 2 of this report. An annual summary of the results of the analyses of REMP samples is provided in Section 3.

A discussion of the results, including assessments of any radiological impacts upon the environment and the results of the land use census are provided in Section 4. The results of the Interlaboratory Comparison Program (ICP) are provided in Section 5. Conclusions are provided in Section 6.

1-1

2.0 REMP DESCRIPTION A summary description of the REMP is provided in Table 2-1. This table summarizes the program as it meets the requirements outlined in ODCM Table 4-1. It details the sample types to be collected and the analyses to be performed in order to monitor the airborne, direct radiation, waterborne and ingestion pathways, and also delineates the collection and analysis frequencies. In addition, Table 2-1 describes the locations of the indicator, community and control stations as described in ODCM Table 4-4 and the identification of each sample according to station location and analysis type. The stations are also depicted on maps in Figures 2-1 through 2-3.

The location of each REMP station for gaseous releases is described by its direction and distance from a point midway between the Unit 1 and Unit 2 plant vent stacks. The surrounding area is divided into 16 azimuthal sectors which are centered on the major compass points; each sector is numbered sequentially clockwise and oriented so that the centerline of sector 16 is due north. Each sampling station is identified by a four digit number. The first two digits indicate the sector number, and the last two digits indicate the distance from the origin to the nearest mile. For example, air monitoring station 0215 is located approximately 15 miles northeast of the origin. The locations for the sampling stations along the river are identified by the nearest River Mile (RM) which is the distance along the navigable portion of the Chattahoochee River upstream of the Jim Woodruff Dam near Chattahoochee, Florida. The approximate locations of the plant discharge and intake structures are at RM 43.5 and 43.8, respectively.

The samples are collected by the plant's technical staff, except for fish and river sediment samples which are collected by APCo Environmental Field Services personnel.

All laboratory analyses were performed by Georgia Power Company's Environmental Laboratory (EL) in Smyrna, Georgia.

2-1

TABLE 2-1 (SHEET 1 of 7)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sample Identification Sampling and Collection Frequency Type and Frequency of Analysis with Sample Types and Locations (sector-miles)

AIRBORNE Particulates Continuous sampler operation with sample Particulate sampler: Analyze for gross collection weekly. beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change. Perform gamma isotopic analysis on each sample when gross beta activity is > 10 times the yearly mean of control samples. Perform gamma isotopic analysis on composite sample (by location) quarterly.

Indicator Stations:

River Intake Structure PI-0501 (ESE-0.8)

South Perimeter PI-0701 2-2 (SSE-1.0)

Plant Entrance PI-1101 (WSW-0.9)

North Perimeter PI-1601 (N-0.8)

Control Stations:

Blakely GA (NE-15) PB-0215 Neals Landing, FL PB-0718 (spare (SSE-18) station, not in service)

Dothan, AL (W-18) PB-1218 Community Stations:

GA Pacific Paper Co. PC-0703 (SSE-3)

Ashford, AL PC-1108 (WSW-8)

Columbia, AL (N-5) PC-1605

TABLE 2-1 (SHEET 2 of 7)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sample Identification Sampling and Collection Frequency Type and Frequency of Analysis with Sample Types and Locations (sector-miles)

Iodine Continuous sampler operation with sample Radioiodine canister: Analyze each collection weekly sample for I-131 weekly.

Indicator Stations:

River Intake Structure II-0501 (ESE-0.8)

South Perimeter II-0701 (SSE-1.0)

Plant Entrance II-1101 (WSW-0.9)

North Perimeter II-1601 (N-0.8)

Control Station:

Blakely, GA (NE-15) IB-0215 Neals Landing, FL IB-0718 (spare station, 2-3 (SSE-18) not in service)

Dothan, AL (W-18) IB-1218 Community Station:

GA Pacific Paper Co. IC-0703 (SSE-3)

DIRECT RADIATION TLD Quarterly Gamma dose: Read each badge quarterly Indicator Stations:

Plant Perimeter (NNE-0.9) RI-0101 (NE-1.0) RI-0201 (ENE-0.9) RI-0301 (E-0.8) RI-0401 (ESE-0.8) RI-0501

TABLE 2-1 (SHEET 3 of 7)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sample Sampling and Collection Frequency Type and Frequency of Analysis with Sample Types Identification and Locations (sector-miles)

(SE-1.1) RI-0601 (SSE-1.0) RI-0701 (S-1.0) RI-0801 (SSW-1.0) RI-0901 (SW-0.9) RI-1001 (WSW-0.9) RI-1101 (W-0.8) RI-1201 (WNW-0.8) RI-1301 (NW-1.1) RI-1401 (NNW-0.9) RI-1501 (N-0.8) RI-1601 Control Stations:

Blakely, GA (NE-15) RB-0215 2-4 Neals Landing, FL RB-0718 (SSE-18)

Dothan, AL (W-15) RB-1215 Dothan, AL (W-18) RB-1218 Webb, AL RB-1311 (WNW-11)

Haleburg, AL (N-12) RB-1612 Community Station By sector (NNE-4) RC-0104 (NE-4) RC-0204 (ENE-4) RC-0304 (E-5) RC-0405 (ESE-5) RC-0505 (SE-5) RC-0605 (SSE-3) RC-0703

TABLE 2-1 (SHEET 4 of 7)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sample Sampling and Collection Frequency Type and Frequency of Analysis with Sample Types Identification and Locations (sector-miles)

(S-5) RC-0805 (SSW-4) RC-0904 (SW-5) RC-1005 (WSW-4) RC-1104 (W-4) RC-1204 (WNW-4) RC-1304 (NW-4) RC-1404 (NNW-4) RC-1504 (N-5) RC-1605 Of Special Interest:

Nearest Residence RC-1001 (SW-1.2)

City of Ashford, AL RC-1108 2-5 (WSW-8.0)

WATERBORNE Aliquots taken with proportional semi-Surface Water continuous sampler, having a minimum Gamma isotopic analysis of each 4 week sampling frequency not exceeding two composite sample. Tritium analysis for hours, collected weekly for 4 week each quarterly composite.

composites and quarterly composites Indicator Station:

Paper Mill, (~3 miles WRI downstream of plant discharge, RM 40)

Control Station:

Upstream of WRB Andrews Lock and dam (~3 miles upstream of the plant intake, RM 47)

TABLE 2-1 (SHEET 5 of 7)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sample Sampling and Collection Frequency Type and Frequency of Analysis with Sample Types Identification and Locations (sector-miles)

Offsite Ground Water Grab sample quarterly Gamma isotopic, I-131, and tritium analyses of each sample quarterly Indicator Station:

Paper Mill Well WGI-07 (SSE-4)

Control Station:

Whatley Residence WGB-10 Well (SW-1.2)

Onsite Ground Water See Table 2-2 Quarterly sample; pump used to sample GW Tritium, gamma isotopic, and field wells; grab sample from yard drains and parameters (pH, temperature, ponds conductivity, dissolved oxygen, oxidation/reduction potential, and 2-6 turbidity) of each sample quarterly; Hard to detect radionuclides as necessary based on results of tritium and gamma River Sediment Grab sample semiannually Gamma isotopic analysis of each sample semiannually Indicator Station:

Downstream of plant RSI discharge at Smiths Bend (RM 41)a Control Station:

Upstream of plant RSB discharge at Andrews Lock & Dam Reservoir (RM 48)a

TABLE 2-1 (SHEET 6 of 7)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sample Sampling and Collection Frequency Type and Frequency of Analysis with Sample Types Identification and Locations (sector-miles)

INGESTION Milk Grab sample biweekly Gamma isotopic and I-131 analyses of each sample biweekly Control Station:

Robert Weir Dairy MB-0714 NOTE: Samples were no longer available at Donaldsonville, GA this location in 2010. No replacement (SSE - 14) location was identified.

Fish Grab sample semiannually for Game Fish Gamma isotopic analysis on the edible and Bottom Feeding Fish portions of each sample semiannually Indicator Stations:

Downstream of plant FGI & FBI discharge in vicinity of Smiths Bend (RM 41)b 2-7 Control Station:

Upstream of plant FGB & FBB discharge in Andrews Lock &

Dam Reservoir (RM 48)b Forage Grab sample from forage every 4 weeks. Gamma isotopic analysis of each sample every 4 weeks.

Indicator Station:

South Southeast FI-0701 Perimeter (SSE-1.0)

North Perimeter FI-1601 (N-0.8)

Control Station:

Dothan, AL (W-18) FB-1218

TABLE 2-1 (SHEET 7 of 7)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NOTATIONS

a. These collections are normally made at river mile 41.3 for the indicator station and river mile 47.8 for the control station; however, due to river bottom sediment shifting caused by high flows, dredging, etc., collections may be made from river mile 40 to 42 for the indicator station and from river mile 47 to 49 for the control station.

b. Since a few miles of river water may be needed to obtain adequate fish samples, these river mile positions represent the approximate locations about which the catches are taken. Collections for the indicator station should be from river mile 37.5 to 42.5 and for the control station from river mile 47 to 52.

2-8

TABLE 2-2 Onsite Groundwater Monitoring Locations WELL ACQUIFER MONITORING PURPOSE R1 Major Shallow Dilution line aquifer R2 Major Shallow Dilution line aquifer R3 Major Shallow Unit 2 RWST aquifer R4 Major Shallow Unit 1 RWST aquifer R5 Major Shallow Dilution line aquifer R6 Major Shallow Dilution line aquifer R7 Major Shallow Dilution line aquifer R8 Major Shallow Dilution line aquifer R9 Major Shallow Dilution line aquifer R10 Major Shallow Dilution line aquifer R11 Major Shallow Background 1 aquifer R13 Major Shallow Dilution line aquifer R14 Major Shallow Background 2 aquifer PW#2 Drinking water Production Well #2 Supply PW#3 Drinking water Production Well #3 Supply CW West Drinking water Construction Well West Supply CW East Drinking water Construction Well East Supply FRW Drinking water Firing Range Well Supply SW-1 N/A Background 3 Service Water Pond East YD N/A Plant outfall East Yard Drain SE YD N/A Plant outfall Southeast Yard Drain 2-9

Figure 2-4 Onsite Groundwater Monitoring Location 2-13

3.0 RESULTS

SUMMARY

In accordance with ODCM 7.1.2.1, the summarized and tabulated results for all of the regular samples collected for the year at the designated indicator, community and control stations are presented in Table 3-1. The format of Table 3-1 is similar to Table 3 of the Nuclear Regulatory Commission (NRC) Branch Technical Position, An Acceptable Radiological Environmental Monitoring Program Revision 1, November 1979. Results for samples collected at locations other than those listed in Table 2-1 are discussed in Section 4 under the particular sample type.

As indicated in ODCM 7.1.2.1, the results for naturally-occurring radionuclides that are also found in plant effluents must be reported along with man-made radionuclides. The radionuclide Be-7, which occurs abundantly in nature, is often detected in REMP samples. It is occasionally detected in the plants liquid and gaseous effluents. When it is detected in effluents, it is also included in the REMP results. In 2010, Be-7 was detected in both liquid and gaseous effluents at Farley.

3-1

TABLE 3-1 (SHEET 1 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Medium or Type and Minimum Indicator Location with the Highest Community Control Pathway Total Detectable Locations Annual Mean Locations Locations Sampled Number of Concentration Mean (b), Mean (b), Mean(b),

(Unit of Analyses (MDC) (a) Range Name Distance Mean (b), Range Range Measurement) Performed (Fraction) & Direction Range (Fraction) (Fraction) (Fraction)

Airborne Gross 10 21.2 PI-0501 27.2 18.2 17.5 Particulates Beta 5.4-56.5 River Intake 8.2-56.5 3.0-41.9 2.6-36.8 (fCi/m3) 466 (205/206) 0.8 miles ESE (52/52) (153/156) (98/104)

Gamma Isotopic 36 Be-7 24 71.9 PC-0703 88.4 74.1 72.0 10.8-96.7 Ga. Pacific 72.0-106.9 47.2-106.9 30.6-123.4 (16/16) 3 miles SSE (4/4) (12/12) (8/8)

I-131 70 NDM(c) NA(d) NDM NDM (0/16) (0/12) (0/8) 3-2 Cs-134 50 NDM NA NDM NDM (0/16) (0/12) (0/8)

Cs-137 60 NDM NA NDM NDM (0/16) (0/12) (0/8)

Airborne I-131 70 NDM NA NDM NDM Radioiodine 362 (0/206) (0/52) (0/104)

(fCi/m3)

Direct Radiation Gamma NA 17.8 RI-0401 25.1 15.5 16.7 (mR/91 days) Dose 10.2-31.7 Plt. Perimeter 19.9-31.2 9.4-24.8 10.5-23.6 159 (64/64) 0.8 miles E (4/4) (71/72) (24/24)

Milk (pCi/l) Gamma Isotopic 0

Cs-134 15 NA NA NA NA Cs-137 18 NA NA NA NA Ba-140 60 NA NA NA NA La-140 15 NA NA NA NA I-131 1 NA NA NA NA

TABLE 3-1 (SHEET 2 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Medium or Type and Minimum Indicator Location with the Highest Community Control Pathway Total Detectable Locations Annual Mean Locations Locations Sampled Number of Concentration Mean (b), Mean (b), Mean(b),

(Unit of Analyses (MDC) (a) Range Name Distance Mean (b), Range Range Measurement) Performed (Fraction) & Direction Range (Fraction) (Fraction) (Fraction)

Forage Gamma (pCi/kg wet) Isotopic 39 Be-7 729 1870 FI-0701 1897 NA 1508 (166-6415) Firing Range (478-6071) (254-3224)

(26/26) 1.0 mile SSE (13/13) (13/13)

I-131 60 NDM NA NA NDM (0/26) (0/13)

Cs-134 60 NDM NA NA NDM (0/26) (0/13)

Cs-137 80 NDM NA NA NDM 3-3 (0/26) (0/13)

Offsite Ground H-3 2000 400 WGB-10 556 NA 556 Water (pCi/l) 8 (1/4) 1.2 miles SW (1/4) (1/4)

(g) I-131 1 NDM NA NA NDM 8 (0/4) (0/4)

Gamma Isotopic 8 Mn-54 15 NDM NA NA NDM (0/4) (0/4)

Fe-59 30 NDM NA NA NDM (0/4) (0/4)

Co-58 15 NDM NA NA NDM (0/4) (0/4)

Co-60 15 NDM NA NA NDM (0/4) (0/4)

Zn-65 30 NDM NA NA NDM (0/4) (0/4)

Zr-95 30 NDM NA NA NDM (0/4) (0/4)

TABLE 3-1 (SHEET 3 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Medium or Type and Minimum Indicator Location with the Highest Community Control Pathway Total Detectable Locations Annual Mean Locations Locations Sampled Number of Concentration Mean (b), Mean (b), Mean(b),

(Unit of Analyses (MDC) (a) Range Name Distance Mean (b), Range Range Measurement) Performed (Fraction) & Direction Range (Fraction) (Fraction) (Fraction)

Nb-95 15 NDM NA NA NDM (0/4) (0/4)

Cs-134 15 NDM NA NA NDM (0/4) (0/4)

Cs-137 18 NDM NA NA NDM (0/4) (0/4)

Ba-140 60 NDM NA NA NDM (0/4) (0/4)

La-140 15 NDM NA NA NDM (0/4) (0/4) 3-4 Surface Water H-3 3000 518 Ga Pacific 518 NA 446 (pCi/l) 8 300-735 Paper Mill 300-735 216-663 (2/4) RM 40 (2/4) (3/4)

Gamma Isotopic 26 Be-7 124 (e) NDM NA NA NDM (0/13) (0/13)

Mn-54 15 NDM NA NA NDM (0/13) (0/13)

Fe-59 30 NDM NA NA NDM (0/13) (0/13)

Co-58 15 NDM NA NA NDM (0/13) (0/13)

Co-60 15 NDM NA NA NDM (0/13) (0/13)

Zn-65 30 NDM NA NA NDM (0/13) (0/13)

Zr-95 30 NDM NA NA NDM (0/13) (0/13)

Nb-95 15 NDM NA NA NDM (0/13) (0/13)

TABLE 3-1 (SHEET 4 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Medium or Type and Minimum Indicator Location with the Highest Community Control Pathway Total Detectable Locations Annual Mean Locations Locations Sampled Number of Concentration Mean (b), Mean (b), Mean(b),

(Unit of Analyses (MDC) (a) Range Name Distance Mean (b), Range Range Measurement) Performed (Fraction) & Direction Range (Fraction) (Fraction) (Fraction)

I-131 15 (f) NDM NA NA NDM (0/13) (0/13)

Cs-134 15 NDM NA NA NDM (0/13) (0/13)

Cs-137 18 NDM NA NA NDM (0/13) (0/13)

Ba-140 60 NDM NA NA NDM (0/13) (0/13)

La-140 15 NDM NA NA NDM 3-5 (0/13) (0/13)

Bottom Gamma Feeding Fish Isotopic (pCi/kg wet) 4 Be-7 655 (e) NDM NA NA NDM (0/2) (0/2)

Mn-54 130 NDM NA NA NDM (0/2) (0/2)

Fe-59 260 NDM NA NA NDM (0/2) (0/2)

Co-58 130 NDM NA NA NDM (0/2) (0/2)

Co-60 130 NDM NA NA NDM (0/2) (0/2)

Zn-65 260 NDM NA NA NDM (0/2) (0/2)

Cs-134 130 NDM NA NA NDM (0/2) (0/2)

Cs-137 150 8.5 Downstream, 7.1 NA 7.1 5.7-11.4 near Smiths (1/2) (1/2)

(2/2) Bend (RM 41)

TABLE 3-1 (SHEET 5 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Medium or Type and Minimum Indicator Location with the Highest Community Control Pathway Total Detectable Locations Annual Mean Locations Locations Sampled Number of Concentration Mean (b), Mean (b), Mean(b),

(Unit of Analyses (MDC) (a) Range Name Distance Mean (b), Range Range Measurement) Performed (Fraction) & Direction Range (Fraction) (Fraction) (Fraction)

Game Fish Gamma (pCi/kg wet) Isotopic 4

Be-7 655 (e) NDM NA NA NDM (0/2) (0/2)

Mn-54 130 NDM NA NA NDM (0/2) (0/2)

Fe-59 260 NDM NA NA NDM (0/2) (0/2)

Co-58 130 NDM NA NA NDM 3-6 (0/2) (0/2)

Co-60 130 NDM NA NA NDM (0/2) (0/2)

Zn-65 260 NDM NA NA NDM (0/2) (0/2)

Cs-134 130 NDM NA NA NDM (0/2) (0/2)

Cs-137 150 7.6 Upstream, at 9.8 NA 9.8 6.4-8.8 Andrews Dam 8.5-11.1 8.5-11.1 (2/2) (RM 48) (2/2) (2/2)

River Shoreline Gamma Sediment Isotopic (pCi/kg dry) 4 Be-7 655 (e) NDM NA NA NDM (0/2) (0/2)

Cs-134 150 NDM NA NA NDM (0/2) (0/2)

Cs-137 180 NDM NA NA NDM (0/2) (0/2)

TABLE 3-1 (SHEET 6 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama NOTATIONS

a. The MDC is defined in ODCM 10.1. Except as noted otherwise, the values listed in this column are the detection capabilities required by ODCM Table 4-3 (Table 4-1 of this report). The values listed in this column are a priori (before the fact) MDCs. In practice, the a posteriori (after the fact) MDCs are generally lower than the values listed. Any a posteriori MDC greater than the value listed in this column is discussed in Section 4.

b. Mean and range are based upon detectable measurements only. The fraction of all measurements at a specified location that are detectable is placed in parentheses.

c. No Detectable Measurement(s).

d. Not Applicable.

e. The EL has determined that this value may be routinely attained under normal conditions. No value is provided in Table 4-1 of this 3-7 report.

f. If a drinking water pathway exists, a value of 1 pCi/l would be used. See note b of Table 4-1 of this report.

g. Onsite groundwater results are discussed in Section 4.6.

4.0 DISCUSSION OF RESULTS Included in this section are evaluations of the laboratory results for the various sample types. Comparisons were made between the difference in mean values for pairs of station groups (e.g., indicator and control stations, or, community and control stations) and the calculated Minimum Detectable Difference (MDD) between these pairs, at the 99% Confidence Level (CL). The MDD was determined using the standard Student's t-test. A difference in the mean values which was less than the MDD was considered to be statistically indiscernible.

The 2010 results were compared with past results, including those obtained during preoperation. As appropriate, results were compared with their Minimum Detectable Concentrations (MDC) and Reporting Levels (RL) which are listed in Tables 4-1 and 4-2 of this report, respectively. The required MDCs were achieved during laboratory sample analysis. Any anomalous results are explained within this report.

Results of interest are graphed to show historical trends. The data points are tabulated and included in this report. The points plotted and provided in the tables represent mean values of only detectable results. Periods for which no detectable measurements (NDM) were observed, or periods for which values were not applicable (e.g., milk indicator, etc.), are plotted as 0s and listed in the tables as NDM.

Table 4-1 Minimum Detectable Concentrations (MDC)

Analysis Water Airborne Fish Milk Grass or Sediment (pCi/l) Particulate (pCi/kg) (pCi/l) Leafy (pCi/kg) or Gases wet Vegetation dry (fCi/m3) (pCi/kg) wet Gross Beta 4 10 H-3 2000 (a)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 1 (b) 70 1 60 Cs-134 15 50 130 15 60 150 Cs-137 18 60 150 18 80 180 Ba-140 60 60 La-140 15 15 (a) If no drinking water pathway exists, a value of 3000 pCi/l may be used.

(b) If no drinking water pathway exists, a value of 15 pCi/l may be used.

4-1

Table 4-2 Reporting Levels (RL)

Analysis Water Airborne Fish Milk (pCi/l) Grass or (pCi/l) Particulate (pCi/kg) wet Leafy or Gases Vegetation (fCi/m3) (pCi/kg) wet H-3 20,000 (a)

Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-95 400 Nb-95 700 I-131 2 (b) 900 3 100 Cs-134 30 10,000 1000 60 1000 Cs-137 50 20,000 2000 70 2000 Ba-140 200 300 La-140 100 400 (a) This is the 40 CFR 141 value for drinking water samples. If no drinking water pathway exists, a value of 30,000 may be used.

(b) If no drinking water pathway exists, a value of 20 pCi/l may be used.

Atmospheric nuclear weapons tests from the mid 1940s through 1980 distributed man-made nuclides around the world. The most recent atmospheric tests in the 1970s and in 1980 had a significant impact upon the radiological concentrations found in the environment prior to and during preoperation, and the earlier years of operation. Some long-lived radionuclides, such as Cs-137, continue to have some impact.

Significant upward trends also followed the Chernobyl incident, which began on April 26, 1986.

In accordance with ODCM 4.1.1.2.1, deviations from the required sampling schedule are permitted if samples are unobtainable due to hazardous conditions, unavailability, inclement weather, equipment malfunction or other just reasons.

Deviations from conducting the REMP as described in Table 2-1 are summarized in Table 4-3 along with their causes and resolutions.

4-2

All results were tested for conformance with Chauvenet's criterion (G. D. Chase and J. L. Rabinowitz, Principles of Radioisotope Methodology, Burgess Publishing Company, 1962, pages 87-90) to identify values which differed from the mean of a set by a statistically significant amount. Identified outliers were investigated to determine the reason(s) for the variation. If equipment malfunction or other valid physical reasons were identified as causing the variation, the anomalous result was excluded from the data set as non-representative. No data were excluded exclusively for failing Chauvenet's criterion. Data exclusions are discussed in this section under the appropriate sample type.

4-3

TABLE 4-3 (SHEET 1 of 2)

DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM COLLECTION AFFECTED DEVIATION CAUSE RESOLUTION PERIOD SAMPLE(S) 1st Quarter 2010 TLD Station TLD rendered suspect by presence of Moisture / rain water entered Replaced TLDs at beginning of CR2010106168 RI-1101B water in bag holding bag quarter 0.9 miles WSW 1st Quarter 2010 TLD Station TLDs rendered suspect by presence Moisture / rain water entered Replaced TLDs at beginning of CR2010106168 RB-1215A&B of water in bag holding bag quarter 15 miles W 05/25/10 - 06/01/10 PI-1101/II-1101 Non-representative sample of Sample station lost power for Station operation satisfactory after CR2010107397 0.9 miles WSW airborne particulates approximately 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> while WO# power restored S092858801 was performed 06/15 07/13/10 WRB Non-representative monthly river ISCO sampler out of service for ISCO sampler operation CR2010108527 Andrews Dam water composite approximately 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> while satisfactory after maintenance

~3 miles upstream sample pump tubing was replaced performed 06/29/10-07/06/10 PI-0701/II-0701 Non-representative sample of Lost approximately 15.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of Station operation satisfactory after CR2010109019 1.0 mile SSE airborne particulates sample time; likely cause was power power restored 4-4 supply issue which also affected power at the firing range 08/03/10-08/10/10 PI-0701/II-0701 Non-representative sample of Lost approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of Station operation satisfactory at CR2010110579 1.0 mile SSE airborne particulates sample time; likely cause was sample collection inclement weather 08/03/10-08/10/10 PI-1101/II-1101 Non-representative sample of Sample station out of service for Station operation satisfactory on CR2010110614 0.9 miles WSW airborne particulates; inadequate approximately 93 hours0.00108 days <br />0.0258 hours <br />1.537698e-4 weeks <br />3.53865e-5 months <br /> during 08/11/10 after maintenance EXCLUDED sample volume collected (less than collection period to resolve several performed 250 m3) maintenance issues 08/10/10-08/17/10 PI-1101/II-1101 Non-representative sample of Sample station out of service for Station operation satisfactory on CR2010110614 0.9 miles WSW airborne particulates maintenance approximately 25.5 08/11/10 after maintenance hours during collection period performed

TABLE 4-3 (SHEET 2 of 2)

DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM COLLECTION AFFECTED DEVIATION CAUSE RESOLUTION PERIOD SAMPLE(S) 2nd Quarter 2010 All Second Quarter Direction radiation results higher Panasonic TLD reader problems OSL Inlight system put in service in Corp CR2011100346 TLD Results than typical caused a three week delay in January 2011; Panasonic system reading 2nd quarter badges retired 2nd Quarter 2010 TLD Station Non-representative direct radiation TLD was heat damaged and Data was used from companion CR2010112818 RB-1311B data couldnt be processed badge RB-1311A EXCLUDED 11 miles WNW 3rd Quarter 2010 TLD Station TLDs rendered suspect because Likely due to wildlife encounter Replaced TLDs at beginning of CR2010113678 RI-0101A&B found on ground at collection time (holding bag was torn off of quarter 0.9 miles NNE locking clip and the holding bags were tattered) 3rd Quarter 2010 TLD Station TLDs missing at collection time Likely cause was vandalism; metal Replaced TLDs at beginning of CR2010113678 RC-0204A&B hanger was badly twisted quarter EXCLUDED 4 miles NE 3rd Quarter 2010 TLD Station TLD rendered suspect by presence of Moisture / rain water entered Data was used from companion 4-5 CR2010117495 RI-0201A water in bag; badge had >1.4 holding bag badge RI-0201B; replaced TLDs at EXCLUDED 1.0 mile NE standard deviation after analysis beginning of quarter 10/12/10-10/19/10 PI-1101/II-1101 Non-representative sample of Sample station lost time while Station operation satisfactory after CR2010114774 0.9 miles WSW airborne particulates; inadequate operating on temporary power maintenance performed EXCLUDED sample volume collected (less than supply 250 m3) 10/12/10-10/19/10 PI-1101/II-1101 No flow measurement on totalizer Flow turbine not operating Flow verified adequate; 48 LPM (through end of year) 0.9 miles WSW display correctly WO#S103189801; no used as estimated sample flow for CR2010114777 flow indicated remaining collection weeks of 2010 10/26/10-11/02/10 PI-1601/II-1601 Non-representative sample of Circuit breaker tripped; likely due Station operation satisfactory after CR2010115941 0.8 miles N airborne particulates to inclement weather breaker reset 12/13/10-12/20/10 PI-0701/II-0701 No flow measurement on totalizer Flow turbine not operating Flow verified adequate; 48 LPM (through end of year) 1.0 mile SSE display correctly WO#S103568801; no used as estimated sample flow for CR2010118511 flow indicated remaining collection weeks of 2010

4.1 Land Use Census In accordance with ODCM 4.1.2, a land use census was conducted during the month of December 2010. The land use census is used to determine the locations of the nearest permanent residence and milk animal in each of the 16 compass sectors within a distance of 5 miles. A milk animal is a cow or goat producing milk for human consumption. The 2010 survey revealed no significant changes from the 2009 survey. No milk animals were found within a 5 mile distance. The census results are tabulated in Table 4.1-1.

Table 4.1-1 LAND USE CENSUS RESULTS Distance in Miles to the Nearest Location in Each Sector SECTOR RESIDENCE MILK ANIMAL N 2.6 none NNE 2.5 none NE 2.4 none ENE 2.4 none E 2.8 none ESE 3.0 none SE 3.4 none SSE >5 none S 4.3 none SSW 2.9 none SW 1.2 none WSW 2.4 none W 1.3 none WNW 2.1 none NW 1.5 none NNW 3.4 none The Houston County, Alabama and the Early County, Georgia Extension Agents were contacted for assistance in locating commercial dairy farms and privately owned milk animals within 5 miles of the plant. A list of commercial dairy farms in Houston County, AL and Seminole County, GA was provided; there are no commercial dairy farms in Early County. Neither agent knew of privately owned milk animals within 5 miles of FNP. In addition, field surveys were conducted in the plant vicinity along the state and county highways and the interconnecting secondary roads. No milk animals were found within 5 miles of the plant.

ODCM 4.1.2.2.1 requires a new controlling receptor to be determined, if the land use census identifies a location that yields a calculated receptor dose greater than the one in current use. Neither current sampling locations nor the controlling receptor were affected by the 2010 land use census results. The current controlling receptor as described in ODCM Table 3-7 remains a child in the SW Sector at 1.2 miles.

4-6

4.2 Airborne As specified in Table 2-1 and shown in Figures 4.2-1 and 4.2-2, airborne particulate filters and charcoal canisters are collected weekly at 4 indicator, 3 control and 3 community stations. Particulate filters are collected at all of the stations while the charcoal canisters are collected at all but 2 of the community stations. At each location, air is continuously drawn through a glass fiber filter to retain airborne particulates and, as appropriate, an activated charcoal canister is placed in series to adsorb radioiodine.

Each particulate filter is counted for gross beta activity. A quarterly gamma isotopic analysis is performed on a composite of the air particulate filters for each station. Each charcoal canister is analyzed for I-131.

As provided in Table 3-1, the 2010 annual average weekly gross beta activity was 21.2 fCi/m3 at the indicator stations and 17.5 fCi/m3 at the control stations. The difference of 3.7 fCi/m3 between the two averages is statistically discernible since it is greater that the MDD of 2.6 fCi/m3. The trend over the years has shown close agreement between the control, community, and indicator stations, and in most years (including pre-op), the indicator station gross beta average activity was lower than the control and community annual averages.

As shown in Table 3-1, the 2010 annual average weekly gross beta concentration was 18.2 fCi/m3 at community stations. The community stations average was 0.7 fCi/m3 greater than the average for the control stations. The difference is not statistically discernible since it is less than the MDD of 2.4 fCi/m3.

Due to the weapons tests during preoperation and the early years of operation, the average gross beta concentrations were 5 to 10 times greater than those currently being measured. By the mid 1980s, the readings had diminished to about half the current levels. These annual averages approximately doubled as a consequence of the Chernobyl incident in 1986; this impact faded away in approximately 2 years.

The installation of new air monitoring equipment in 1992 yielded an approximate factor of 2 increase in the readings. Since then, the levels have been fairly flat.

The historical trending of the average weekly gross beta air concentrations for each year of operation and the preoperational period at the indicator, control and community stations is plotted in Figure 4.2-1 and listed in Table 4.2-1. In general, there is close agreement between the results for the indicator, control and community stations. This close agreement supports the position that the plants contribution to gross beta concentration in air is insignificant.

4-7

Figure 4.2-1 4-8

Table 4.2-1 Average Weekly Gross Beta Air Concentration Period Indicator Control Community (fCi/m3) (fCi/m3) (fCi/m3)

Pre-op 90 92 91 1977 205 206 206 1978 125 115 115 1979 27.3 27.3 28.7 1980 29.7 28.1 29.2 1981 121 115 115 1982 20.0 20.4 21.0 1983 15.5 14.1 14.5 1984 10.2 12.6 10.5 1985 9.0 9.6 10.3 1986 10.5 15.8 12.5 1987 9.0 11.0 17.0 1988 8.0 8.0 10.0 1989 7.0 7.0 8.0 1990 10.0 10.0 10.0 1991 9.0 10.0 8.0 1992 15.0 17.9 18.5 1993 19.1 22.3 22.4 1994 19.0 20.0 19.0 1995 21.7 22.9 21.6 1996 20.3 22.3 23.5 1997 21.1 21.6 22.4 1998 20.6 19.3 22.0 1999 20.5 22.1 25.2 2000 20.9 20.8 23.6 2001 16.3 17.2 17.3 2002 16.8 18.0 16.8 2003 19.1 19.3 19.9 2004 22.0 21.3 22.4 2005 18.4 19.3 19.0 2006 16.1 17.5 16.8 2007 14.5 18.9 17.3 2008 16.7 20.6 18.0 2009 16.2 16.3 17.3 2010 21.2 17.5 18.2 4-9

During 2010, no radionuclides other than Be-7 were detected from the gamma isotopic analysis of the quarterly composites of the air particulate filters. This has generally been the case since the impact of the weapons tests and the Chernobyl incident have faded. The average Be-7 at the indicator stations was 71.9 fCi/m3 and the average at the control stations was 72.0 fCi/m3. The difference of 0.1 fCi/m3 is not statistically different since it is less than the MDD of 30.0 fCi/m3.

The average Be-7 at the community stations was 74.1 fCi/m3. The difference (2.1 fCi/m3) between the control and community stations is not statistically discernible since it is less than the MDD of 27.7 fCi/m3.

During preoperation and the early years of operation, a number of fission and activation products were detected. During preoperation, the average levels for Cs-134 and Cs-137 were 22 and 9 fCi/m3, respectively. In 1986, as a consequence of the Chernobyl incident, Cs-134 and Cs-137 levels of 3 to 4 fCi/m3 were found.

The MDC and RL for Cs-134 are 50 and 10,000 fCi/m3 and the MDC and RL for Cs-137 are 60 and 20,000 fCi/m3 respectively.

The historical trending of the annual detectable Cs-137 concentrations for the indicator, control and community stations is provided in Figure 4.2-2 and Table 4.2-2. The trend has been generally downward since preoperation and no positive results have been observed since 1988.

Figure 4.2-2 4-10

Table 4.2-2 Average Annual Cs-137 Concentration in Air Period Indicator Control Community (fCi/m3) (fCi/m3) (fCi/m3)

Pre-op 8 13 7 1977 3.0 3.0 3.0 1978 4.0 5.0 5.0 1979 2.0 NDM 2.0 1980 1.0 2.0 1.8 1981 2.8 3.2 2.6 1982 1.7 NDM 1.0 1983 1.0 NDM 1.0 1984 NDM 1.5 NDM 1985 1.0 1.0 1.0 1986 3.3 3.4 2.7 1987 NDM NDM NDM 1988 NDM NDM 1 1989 NDM NDM NDM 1990 NDM NDM NDM 1991 NDM NDM NDM 1992 NDM NDM NDM 1993 NDM NDM NDM 1994 NDM NDM NDM 1995 NDM NDM NDM 1996 NDM NDM NDM 1997 NDM NDM NDM 1998 NDM NDM NDM 1999 NDM NDM NDM 2000 NDM NDM NDM 2001 NDM NDM NDM 2002 NDM NDM NDM 2003 NDM NDM NDM 2004 NDM NDM NDM 2005 NDM NDM NDM 2006 NDM NDM NDM 2007 NDM NDM NDM 2008 NDM NDM NDM 2009 NDM NDM NDM 2010 NDM NDM NDM 4-11

Airborne I-131 was not detected in the charcoal canisters during 2010. In 1978, levels between 40 and 50 fCi/m3 were found in a few samples and attributed to the Chinese weapons tests; then after the Chernobyl incident, levels up to a few hundred fCi/m3 were found in some samples. At no other times has airborne I-131 been detected in the environmental samples. The MDC and RL for airborne I-131 are 70 and 900 fCi/m3 respectively.

Table 4-3 lists REMP deviations that occurred during 2010. There were nine air sampling deviations listed in Table 4-3, seven results passed Chauvenets Criterion and the data was retained in the calculation of the mean values. Two air sample results were excluded because they failed to meet the MDC. Low sample volumes were collected during those two weeks due to maintenance issues and equipment malfunctions.

4-12

4.3 Direct Radiation Direct (external) radiation is measured with thermoluminescent dosimeters (TLDs). Two Panasonic UD-814 TLD badges are placed at each station. Each badge contains three phosphors composed of calcium sulfate crystals (with thulium impurity). The gamma dose at each station is based upon the average readings of the phosphors from the two badges. The two badges for each station are placed in thin plastic bags for protection from moisture while in the field. The badges are nominally exposed for periods of a quarter of a year (91 days). An inspection is performed near mid-quarter for offsite badges to assure that the badges are on-station and to replace any missing or damaged badges.

Two TLD stations are established in each of the 16 sectors, to form 2 concentric rings. The inner ring stations are located near the plant perimeter, as shown in Figure 2-1, and the outer ring stations are located at distances of approximately 3 to 5 miles from the plant, as shown in Figure 2-2. The stations forming the inner ring are designated as the indicator stations. The 6 control stations are located at distances greater than 10 miles from the plant, as shown in Figure 2-3. Stations are also provided which monitor special interest areas: the nearest occupied residence (SW at 1.2 miles), as shown in Figure 2-1, and the city of Ashford (WSW at 8 miles), as shown in Figure 2-3. The 16 outer ring stations and the 2 special interest stations are designated as community stations.

As provided in Table 3-1, the average quarterly exposure measured at the indicator stations (inner ring) during 2010 was 17.8 mR which was 1.1 mR greater than the 16.7 mR which was acquired at the control stations. This difference is not statistically discernible since it is less than the MDD of 2.4 mR. The difference of 1.2 mR found between the control stations (16.7 mR) and community stations (15.5 mR) is not statistically discernible since the difference is less than the MDD of 2.0 mR. The difference between the indicator and control and between the control and community stations is consistent with what has been seen in previous years.

The historical trending of the average quarterly exposures in units of mR at the indicator, control, and community locations are plotted in Figure 4.3-1 and listed in Table 4.3-1. During preoperation the average exposure at the indicator stations was 1.2 mR greater than that for the control stations, but the average over the entire period of operation was only 1.1 mR greater. During preoperation, the average exposure at the control stations was 1.3 mR greater than that at the community stations and the average over the period of operation is 1.5 mR greater. This supports the position that the plant is not contributing significantly to direct radiation in the environment.

Table 4-3 lists the REMP program deviations that occurred in 2010. There were seven deviations involving TLD badges. In first quarter, RI-1101B and RB-1215A&B had moisture in the holding bags, but the results passed Chauvenets Criterion and were retained in the data set. In second quarter, RB-1311B was heat damaged and couldnt be processed; the results from the A badge were used. In third quarter, RI-0101A&B were found on the ground at collection time but the results passed Chauvenets Criterion. RC-0204A&B were missing at collection time so data was not available for the quarter. RI-0201A was wet in the holding bag and the result was >1.4 SD therefore it was excluded from the data set. Most notable was in second quarter the TLD readings from Farley (and Hatch and 4-13

Vogtle) were higher for the majority of the stations. This anomaly was attributed to significant problems with the Panasonic TLD reader (which was nearing obsolescence). Processing the second quarter badges was delayed about three weeks. The TLD data was kept for second quarter and the anomaly was noted.

The Panasonic system was retired at the end of 2010 and a new Inlight OSL system (which was in use for personnel monitoring in 2010), is now in use for environmental direct radiation measurements. A comparison study was done during 2010 where the OSL badges were placed on station with the TLD badges.

The results of this study will be discussed in the 2011 REMP Report.

Figure 4.3-1 Average Quarterly Exposure from Direct Radiation 30 25 20 Exposure (mR) 15 10 5

0 Po 78 80 82 84 86 88 90 92 94 96 98 00 02 04 06 08 10 Year Indicator Control Comm unity 4-14

Table 4.3-1 Average Quarterly Exposure from Direct Radiation Period Indicator (mR) Control (mR) Community (mR)

Pre-op 12.6 11.4 10.1 1977 10.6 12.2 10.6 1978 15.0 13.5 12.0 1979 20.3 18.7 15.2 1980 21.9 21.6 18.5 1981 16.5 14.9 14.5 1982 15.5 14.7 13.0 1983 20.2 20.2 17.4 1984 18.3 16.9 15.3 1985 21.9 22.0 18.0 1986 17.8 17.7 15.1 1987 20.8 20.0 18.0 1988 21.5 19.9 18.5 1989 18.0 16.2 15.3 1990 18.9 16.4 15.8 1991 18.4 16.1 16.1 1992 16.1 13.6 13.5 1993 17.4 15.9 15.6 1994 15.0 13.0 12.0 1995 14.0 12.5 11.8 1996 14.2 12.7 11.9 1997 15.3 13.9 11.9 1998 16.2 14.6 13.9 1999 14.7 13.4 12.6 2000 15.5 14.1 13.5 2001 14.9 13.4 12.7 2002 14.1 12.6 11.9 2003 15.2 13.6 12.9 2004 14.3 12.9 12.1 2005 14.7 13.4 12.5 2006 15.2 13.6 12.9 2007 14.6 13.3 12.5 2008 15.0 13.7 12.9 2009 15.2 13.6 12.8 2010 17.8 16.7 15.5 4-15

The standard deviation for the quarterly result for each badge was subjected to a self imposed limit of 1.4. This limit is calculated using a method developed by the American Society for Testing and Materials (ASTM) (ASTM Special Technical Publication 15D, ASTM Manual on Presentation of Data and Control Chart Analysis, Fourth Revision, Philadelphia, PA, October 1976). The calculation is based upon the standard deviations obtained by the EL with the Panasonic UD-814 badges during 1992. This limit serves as a flag to initiate an investigation. To be conservative, readings with a standard deviation greater than 1.4 are excluded since the high standard deviation is interpreted as an indication of unacceptable variation in TLD response.

The TLD results from the following stations were excluded from the data set because their standard deviations were greater than 1.4:

Quarter 1 - RI-0101B and RI-1101B Quarter 2 - RC-1304B Quarter 3 - RI-0201A and RI-1215A Quarter 4 - None For the TLD stations where these badges were located, only the reading of the companion badge was used to determine the quarterly exposure for the station.

The badges (with >1.4 SD) were visually inspected under a microscope and the glow curve and test results for the anneal data and the element correction factors were reviewed. No reason was found for the high standard deviations.

4-16

4.4 Milk Milk samples had been collected biweekly from a control location until the end of 2009 when the dairy would no longer provide samples. No indicator station (a location within five miles of the plant) has been available for milk sampling since 1987. As discussed in Section 4.0, no milk animals were found within five miles of the plant during the 2010 land use census therefore no milk sampling was performed during 2010.

Per Table 2.1, gamma isotopic analyses were performed on milk samples when they were collected in previous years. Cs-137 and I-131 are the only man-made radionuclides that have been identified over the history of milk sampling. The historical trending of the average annual detectable Cs-137 concentration in milk samples is shown in Figure 4.4-1 and Table 4.4-1. Cs-137 has not been detected in milk since 1986. Its presence at that time is attributed to the Chernobyl incident.

The earlier detectable results were attributed to weapons testing. The MDC and RL for Cs-137 in milk are 18 and 70 pCi/l, respectively.

Figure 4.4-1 Average Annual Cs-137 Concentration in Milk 45 40 35 Concentration (pCi/l) 30 25 20 15 10 5

0 Po 78 80 82 84 86 88 90 92 94 96 98 00 02 04 06 08 Year Indicator Control MDC 4-17

Table 4.4-1 Average Annual Cs-137 Concentration in Milk Period Indicator Control (pCi/l) (pCi/l)

Pre-op 32 18 1977 41 20 1978 15 17 1979 NDM NDM 1980 NDM NDM 1981 NDM 23.0 1982 NDM NDM 1983 NDM NDM 1984 NDM NDM 1985 NDM NDM 1986 NDM 16.5 1987 NDM NDM 1988 NDM NDM 1989 NDM NDM 1990 NDM NDM 1991 NDM NDM 1992 NDM NDM 1993 NDM NDM 1994 NDM NDM 1995 NDM NDM 1996 NDM NDM 1997 NDM NDM 1998 NDM NDM 1999 NDM NDM 2000 NDM NDM 2001 NDM NDM 2002 NDM NDM 2003 NDM NDM 2004 NDM NDM 2005 NDM NDM 2006 NDM NDM 2007 NDM NDM 2008 NDM NDM 2009 NDM NDM 2010 No sample No sample 4-18

As specified in Table 2-1, milk samples were also analyzed for I-131, which has not been detected in milk since 1986. The presence of I-131 at that time is attributed to the Chernobyl incident. The earlier detectable results were attributed to weapons testing. The MDC and RL for I-131 are 1 and 3 pCi/l, respectively.

Figure 4.4-2 and Table 4.4-2 show the historical trending of the average annual detectable I-131 concentration in milk samples.

Figure 4.4-2 4-19

Table 4.4-2 Average Annual I-131 Concentration in Milk Period Indicator Control (pCi/l) (pCi/l)

Pre-op 41 14 1977 20 2.6 1978 30 11 1979 NDM NDM 1980 NDM NDM 1981 NDM NDM 1982 NDM NDM 1983 NDM NDM 1984 NDM NDM 1985 NDM NDM 1986 NDM 5.0 1987 NDM NDM 1988 NDM NDM 1989 NDM NDM 1990 NDM NDM 1991 NDM NDM 1992 NDM NDM 1993 NDM NDM 1994 NDM NDM 1995 NDM NDM 1996 NDM NDM 1997 NDM NDM 1998 NDM NDM 1999 NDM NDM 2000 NDM NDM 2001 NDM NDM 2002 NDM NDM 2003 NDM NDM 2004 NDM NDM 2005 NDM NDM 2006 NDM NDM 2007 NDM NDM 2008 NDM NDM 2009 NDM NDM 2010 No sample No sample 4-20

4.5 Forage In accordance with Table 2-1, forage samples are collected every 4 weeks at two indicator stations on the plant perimeter, and at one control station located approximately 18 miles west of the plant, in Dothan. Gamma isotopic analyses are performed on each sample.

During preoperation and the years of operation through 1986 (the year of the Chernobyl incident), Cs-137 was typically found in about a third of the 35 to 40 forage samples collected per year. In 1987 and 1988 the number dropped to about a seventh of the total samples and from 1989 through 1994, it was only found in one or two samples every year. From 1994 to 2006, Cs-137 was detected in only a few samples, three indicator samples and three control samples.

In 2010, Cs-137 was not detected in any of the 13 control samples or in any of the 26 indicator samples. The occasional presence of Cs-137 in vegetation samples is attributed primarily to fallout from nuclear weapons tests and from the Chernobyl incident. The MDC and RL for Cs-137 in forage are 80 and 2000 pCi/kg wet, respectively. Table 4.5-1 presents the average detectable results of Cs-137 found in forage over the life of the plant and Figure 4.5-1 shows the historical trending of this data.

Be-7 is naturally occurring but was also detected in liquid and gaseous effluent samples in 2010 therefore it was reported when detected in REMP samples in 2010. All forage indicator and control samples were positive for Be-7. The average Be-7 at the indicator stations was 1870 pCi/kg wet and the average at the control station was 1508 pCi/kg wet. The difference of 362 pCi/kg wet is less than the MDD of 1105 and therefore is not statistically discernible. There is no Required MDC or Reporting Level for Be-7.

4-21

Figure 4.5-1 4-22

Table 4.5-1 Average Annual Cs-137 Concentration in Forage Period Indicator Control (pCi/kg) wet (pCi/kg) wet Pre-op 59.4 48.6 1977 25.0 NDM 1978 52.5 32.5 1979 37.2 32.8 1980 36.2 35.9 1981 32.1 43.1 1982 25.0 33.1 1983 16.8 23.6 1984 19.9 22.8 1985 22.2 9.5 1986 41.2 36.2 1987 46.8 NDM 1988 33.6 31.7 1989 35.7 NDM 1990 56.0 NDM 1991 NDM 12.9 1992 NDM 43.0 1993 NDM 24.0 1994 NDM 24 1995 NDM NDM 1996 NDM NDM 1997 52.6 NDM 1998 NDM 22.7 1999 NDM NDM 2000 NDM NDM 2001 NDM NDM 2002 NDM NDM 2003 24.1 25.2 2004 21.6 NDM 2005 NDM 23.1 2006 NDM NDM 2007 NDM NDM 2008 10.1 NDM 2009 NDM NDM 2010 NDM NDM 4-23

During preoperation and in the early years of operation, I-131 was found in 10%

to 25% of the forage samples at very high levels which ranged from around 100 to 1,000 pCi/kg wet. In 1986 (Chernobyl incident), I-131 reappeared after not having been detected for 3 years. The MDC and RL for I-131 are 60 and 100 pCi/kg wet, respectively. Table 4.5-2 lists the average detectable results of I-131 found in forage over the life of the plant and Figure 4.5-2 plots the historical trending of this data.

Figure 4.5-2 4-24

Table 4.5-2 Average Annual I-131 Concentration in Forage Period Indicator Control (pCi/kg) wet (pCi/kg) wet Pre-op 405 486 1977 971 654 1978 220 240 1979 NDM NDM 1980 NDM NDM 1981 21.4 NDM 1982 46.4 NDM 1983 NDM NDM 1984 NDM NDM 1985 NDM NDM 1986 184 NDM 1987 NDM NDM 1988 NDM NDM 1989 NDM NDM 1990 NDM NDM 1991 NDM NDM 1992 NDM NDM 1993 NDM NDM 1994 NDM NDM 1995 NDM NDM 1996 NDM NDM 1997 NDM NDM 1998 NDM NDM 1999 NDM NDM 2000 NDM NDM 2001 NDM NDM 2002 NDM NDM 2003 NDM NDM 2004 NDM NDM 2005 NDM NDM 2006 NDM NDM 2007 NDM NDM 2008 NDM NDM 2009 NDM NDM 2010 NDM NDM 4-25

These forage analyses results show the impact of the weapons tests during preoperation and the early years of operation and of the Chernobyl incident in 1986 and for a few years afterwards. The impact is reflected by the number of different radionuclides detected, the fraction of samples with detectable results, as well as the magnitude of the results. During preoperation and for the first few years of operation, 11 different radionuclides from fission and activation products were detected. By 1985, only 2 different radionuclides were detected and the fraction of samples with detectable results had diminished. In 1986, the same two nuclides as seen in 1985 appeared at a significantly higher magnitude and I-131 reappeared. In the years following 1986, only Cs-137 has been found in forage and it has been found in a decreasing fraction of the samples.

4-26

4.6 Ground Water In the FNP offsite environs, there are no true indicator sources of ground water. A well, located about four miles south-southeast of the plant on the east bank of the Chattahoochee River, serves Georgia Pacific Paper Company as a source of potable water and is designated as the indicator station. A deep well located about 1.2 miles southwest of the plant, which supplies water to the Whatley residence, is designated as the control station. Samples are collected quarterly and analyzed for gamma isotopic, I-131 and tritium as specified in Table 2-1. In 2010, one quarterly indicator sample and one quarterly control sample were positive for tritium. No other radionuclides were detected.

In 1983, 1985, and 1986, Cs-134 was detected in single samples at levels ranging from 3 to 13 pCi/l. The MDC and RL for Cs-134 in water are 15 and 30 pCi/l, respectively.

During preoperation, Cs-137 was detected in two of the samples at levels of 15 and 17 pCi/l. Then in 1984 and 1985, Cs-137 was again detected in a few samples with levels ranging from 4 to 5 pCi/l. The MDC and RL for Cs-137 in water are 18 and 50 pCi/l, respectively.

Iodine-131 has never been detected in ground water samples. From 1986-2003, no radionuclides were detected. In 2004, 2005, 2007, 2008, 2009, and 2010 tritium was detected at very low concentrations (near the instrument detection level) and close to environmental background concentration which is approximately 350 pCi/l (+/- 250 pCi/l) in the area around Farley. The positive results seen in these years were less than 3% of the reporting level for tritium. In 2010, both positive results were seen in the 4th quarter of 2010. The control sample was 556 pCi/L and the indicator sample was 400 pCi/L. Both results were very close to the environmental background level at Farley. The MDC and RL for tritium in drinking water are 2,000 and 20,000 pCi/l, respectively. Figure 4.6-1 and Table 4.6-1 show the historical trending of the average annual detectable tritium concentration in offsite ground water.

4-27

Figure 4.6-1 Average Annual H-3 Concentration in Offsite Ground Water 2500 2000 Concentration (pCi/l) 1500 1000 500 0

Po 78 80 82 84 86 88 90 92 94 96 98 00 02 04 06 08 10 Year Indicator Control MDC 4-28

Table 4.6-1 Average Annual H-3 Concentration in Offsite Ground Water Period Indicator Control (pCi/l) (pCi/l)

Pre-op 150 240 1977 NDM NDM 1978 NDM 240 1979 NDM NDM 1980 124 NDM 1981 264 NDM 1982 240 NDM 1983 360 341 1984 NDM NDM 1985 NDM NDM 1986 NDM NDM 1987 NDM NDM 1988 NDM NDM 1989 NDM NDM 1990 NDM NDM 1991 NDM NDM 1992 NDM NDM 1993 NDM NDM 1994 NDM NDM 1995 NDM NDM 1996 NDM NDM 1997 NDM NDM 1998 NDM NDM 1999 NDM NDM 2000 NDM NDM 2001 NDM NDM 2002 NDM NDM 2003 NDM NDM 2004 194 271 2005 264 360 2006 NDM NDM 2007 218 321 2008 196 237 2009 474 401 2010 400 556 4-29

As nuclear plants began to undergo decommissioning in the late 1990s to early 2000s, instances of subsurface and/or groundwater contamination were identified.

In addition, several operating facilities also identified groundwater contamination resulting from spills, leaks, and equipment failure. In one instance, low levels of licensed material were detected in a private well located on property adjacent to a nuclear power plant.

In 2006, NEI (Nuclear Energy Institute) formed a task force to address monitoring onsite groundwater for radionuclides at nuclear facilities. A Groundwater Protection Initiative was developed which was adopted by all U.S. commercial operating nuclear plants.

The NRC also formed a task force to study the groundwater issues and released Information Notice 2006-13, Ground-water Contamination due to Undetected Leakage of Radioactive Water, which summarized its review of radioactive contamination of ground water at multiple facilities as a result of undetected leakage from structures, systems, and components that contain or transport radioactive fluids. Licensees were instructed to review the information for applicability and to consider appropriate actions to avoid similar problems.

The NEI task force felt it was prudent for the industry to update site hydrology information and to develop radiological groundwater monitoring plans at each site. These groundwater protection plans would ensure that underground leaks and spills would be addressed promptly. Additionally, the task force recommended developing a communications protocol to report radioactive leaks or spills that entered groundwater (or might eventually enter groundwater) to the NRC and State / Local government officials as needed. NEI-07-07, Industry Groundwater Protection Final Guidance Document, was developed by the task force to document the guidelines recommended for the industry.

To ensure compliance with NEI-07-07, Southern Nuclear developed the Nuclear Management Procedure, Radiological Groundwater Protection Program. The procedure contains detailed site-specific monitoring plans, program technical bases, and communications protocol (to ensure that radioactive leaks and spills are addressed and communicated appropriately). In an effort to prevent future leaks of radioactive material to groundwater, SNC plants have established detailed buried piping and tanks inspection programs.

In 2006, Farley located several old onsite piezometer wells and sampled these and the onsite drinking water wells for tritium and gamma isotopic activity. None of these wells contained detectable amounts of radioactivity. In 2007, after the site hydrology was evaluated, Farley implemented a more extensive radiological groundwater monitoring program which included drilling twelve new onsite monitoring wells (see Table 2-2). The twelve new wells along with one of the existing piezometer wells, the onsite drinking water wells, and several surface water / discharge locations comprise the monitoring program. These locations were sampled twice in the latter portion of 2007 and sampled quarterly in 2008.

Of the numerous samples taken from 2007 through 2010 (from the locations described above), only one location (groundwater well R-3) has shown low levels of radiological contamination (see Figure 4.6-2). Tritium was the only nuclide identified. R-3 was also analyzed for gamma emitters (quarterly) and strontium (initially and after increase was noted) and these were not detected. This well is located near the Protected Area and in the vicinity of the site where the Unit-2 radioactive effluent discharge line ruptured in 2002.

4-30

In 2010, an Administrative Control Limit (ACL) was established for the area near R-3 where legacy material has been the source of tritium. The quarterly results for R-3 were all below the ACL of 6800 pCi/L of tritium. The ACL was derived based on previous years tritium results and total measurement uncertainty. There are no reporting requirements associated with exceeding an ACL but additional actions would be taken to verify no new sources of tritium if an ACL was exceeded. The only notable change in R-3 during 2010 was an increase of 1240 pCi/L of tritium in the second quarter. Heavy rainfall during the late winter and early spring timeframe would likely have caused more surface influence and more groundwater movement within the aquifer.

Figure 4.6-2 H-3 Concentration in Onsite Ground Water Well R-3 7000 6000 5000 Concentration (pCi/l) 4000 3000 2000 1000 0

Ja M 8p-No 7 v-n-

ar M 8 ay -00 07 0

Ju Se 8 No 8 Ja v-n--0 l -0 p- 08 08 M ar M 9 ay Ju Se -009

-0 l-0 p- 99 Se N 9 Ja M ov M 0n-ar ay Ju Se 0 p-No 0 v-

-0

-1

-1 l -1 0

1 9

10 0

10 R-3 Admin Control Limit 4-31

4.7 Surface Water As specified in Table 2-1 and shown in Figure 2-2, water samples are collected from the Chattahoochee River at a control station approximately 3 miles upstream of the intake structure and at an indicator station approximately 4 miles downstream of the discharge structure. Small quantities are collected during the week at periodic intervals using automatic samplers. For each station, one liter from each of four consecutive weekly samples is combined into a composite sample which is analyzed for gamma emitters. In addition, 0.075 liters is collected from 13 consecutive weekly samples for each station to form composite quarterly samples which are analyzed for tritium.

No detectable results have been found from these gamma isotopic analyses since 1988. During preoperation and in every year of operation through 1988 (except 1979 and 1980), a few samples showed at least one of nine different activation or fission products at levels less than or on the order of their MDCs. During preoperation, Cs-137 was found in about 3% of the samples. From 1981 through 1988, it was found in about 15% of the samples. Cs-134 was found in about 15%

of the samples from 1981 to 1986. All of these gamma emitters are attributed to the weapons tests and the Chernobyl incident.

In 2010, as shown in Table 3-1, tritium was detected in two of the 4 quarterly composites at the indicator station (average of 518 pCi/L) and in three of the 4 quarterly composite samples collected at the control station (average of 446 pCi/L). The difference (71 pCi/L) between the average of the detectable values at the indicator station and the average of the detectable values at the control station was not statistically discernible since it was less than the MDD of 1056 pCi/L.

Historical trending of the detectable concentrations of tritium in surface water is provided in Figure 4.7-1 and Table 4.7-1. The slightly elevated plot of the indicator stations is indicative of plant tritium contributions to surface water.

However, it is noteworthy that the annual average levels are less than 10% of the MDC and less than 1% of the RL. The MDC and RL for tritium in surface water are 3,000 and 30,000, respectively.

4-32

Figure 4.7-1 Average Annual H-3 Concentration in Surface Water 3500 3000 Concentration (pCi/l) 2500 2000 1500 1000 500 0

Po 78 80 82 84 86 88 90 92 94 96 98 00 02 04 06 08 10 Year Indicator Control MDC 4-33

Table 4.7-1 Average Annual H-3 Concentration in Surface Water Period Indicator Control (pCi/l) (pCi/l)

Pre-op 200 170 1977 300 160 1978 230 250 1979 169 135 1980 221 206 1981 294 162 1982 300 132 1983 434 111 1984 333 152 1985 351 105 1986 478 272 1987 291.8 116.5 1988 293.3 NDM 1989 253.8 NDM 1990 166 NDM 1991 122 NDM 1992 360.5 134 1993 388.8 NDM 1994 NDM NDM 1995 257 NDM 1996 386 NDM 1997 NDM NDM 1998 415 NDM 1999 314 NDM 2000 424 212 2001 252 NDM 2002 598 NDM 2003 296 NDM 2004 270 NDM 2005 215 173 2006 348 179 2007 321 NDM 2008 644 NDM 2009 343 NDM 2010 518 446 4-34

4.8 Fish Two types of fish (bottom feeding and game) are collected semiannually from the Chattahoochee River at a control station several miles upstream of the plant intake structure and at an indicator station a few miles downstream of the plant discharge structure. These locations are shown in Figure 2-2. Gamma isotopic analysis is performed on the edible portions of each sample as specified in Table 2-1.

As provided in Table 3-1, Cs-137 was the only radionuclide of interest that was found from the gamma isotopic analysis of fish samples in 2010. Cs-137 was detected in both the spring and fall collection of game fish samples at the indicator station (average of 7.6 pCi/kg wet). Cs-137 was detected in both game fish samples at the control station (average of 9.8 pCi/kg wet). The difference of 2.2 pCi/kg wet between the indicator and control station was not statistically discernible since it was less than the MDD of 12.2 pCi/kg wet. The MDC for Cs-137 in fish is 150 pCi/kg wet and the RL is 2000 pCi/kg wet.

Cesium-137 was detected in both bottom feeding fish samples at the indicator location (spring and fall collections) at an average of 8.5 pCi/kg wet, and one bottom feeding fish at the control station (spring collection) at 7.1 pCi/kg wet.

Using the modified Students t-test, the difference of 1.4 pCi/kg wet between the average values at the indicator station and the single positive value at the control station is not statistically discernible. The MDC for Cs-137 in fish is 150 pCi/kg wet and the RL is 2000 pCi/kg wet.

Historically, Cs-137 has been found in approximately 30% of the bottom feeding fish samples and in 80% of the game fish samples. Figures 4.8-1 and 4.8-2 and Tables 4.8-1 and 4.8-2 provide the historical trending of the average annual detectable concentrations of Cs-137 in pCi/kg wet in bottom feeding and game fish, respectively. Since the early 1980s, values have generally decreased for both indicator and control groups, with the exception of the bottom feeding fish collected at the indicator station in 1993. While some contribution from the plant cannot be ruled out, most of the Cs-137 in these samples may be attributed to the nuclear weapons tests and the Chernobyl incident, as evidenced by the normally close agreement between the control and indicator station results.

4-35

Figure 4.8-1 Average Annual Cs-137 Concentration in Bottom Feeding Fish 250 200 Concentration (pCi/kg) wet 150 100 50 0

Po 78 80 82 84 86 88 90 92 94 96 98 00 02 04 06 08 10 Year Indicator Control MDC 4-36

Table 4.8-1 Average Annual Cs-137 Concentration in Bottom Feeding Fish Period Indicator Control (pCi/kg) wet (pCi/kg) wet Pre-op 69 48 1977 NDM NDM 1978 NDM NDM 1979 38 30 1980 92 90 1981 96 106 1982 51.5 39.0 1983 NDM NDM 1984 NDM 19 1985 NDM NDM 1986 28 25 1987 25 19 1988 25.5 22.0 1989 NDM NDM 1990 NDM NDM 1991 NDM NDM 1992 NDM NDM 1993 208 NDM 1994 15.9 10.3 1995 NDM 14.2 1996 16.4 9.9 1997 10.9 7.7 1998 NDM NDM 1999 19.2 NDM 2000 NDM NDM 2001 9.8 NDM 2002 NDM NDM 2003 NDM 8.5 2004 8.1 NDM 2005 NDM 9.6 2006 9.7 NDM 2007 8.1 NDM 2008 11.4 7.7 2009 8.4 21.9 2010 8.5 7.1 4-37

Figure 4.8-2 Average Annual Cs-137 Concentration in Game Fish 350 300 Concentration (pCi/kg) wet 250 200 150 100 50 0

Po 78 80 82 84 86 88 90 92 94 96 98 00 02 04 06 08 10 Year Indicator Control MDC 4-38

Table 4.8-2 Average Annual Cs-137 Concentration in Game Fish Period Indicator Control (pCi/kg) wet (pCi/kg) wet Pre-op 84 60 1977 95 48 1978 NDM NDM 1979 111 83.5 1980 289 316 1981 189 126 1982 76 77 1983 57 56.5 1984 42 26 1985 84 44 1986 51 35 1987 83 46 1988 42 33 1989 38 29 1990 28 NDM 1991 36 24 1992 32.5 28 1993 34 NDM 1994 19 16 1995 17.9 18.2 1996 19.6 23.1 1997 25.9 NDM 1998 52 20 1999 36.9 15.9 2000 22.9 12.5 2001 22.4 12.3 2002 NDM 10.1 2003 19.3 12.0 2004 12.7 10.8 2005 15.7 NDM 2006 15.0 14.7 2007 15.4 6.5 2008 16.6 23.2 2009 24.9 12.5 2010 7.6 9.8 4-39

Radionuclides of interest other than Cs-137 have been found in only a few samples in the past. The following table provides a summary of the results in pCi/kg wet compared with the applicable MDCs.

YEAR Nuclide Fish Type Indicator Control MDC (pCi/kg) (pCi/kg) (pCi/kg) 1978 Ce-144 Bottom Feeding NDM 200 1981 Nb-95 Bottom Feeding 38 NDM 50 (a) 1982 Nb-95 Game 31 NDM 50 (a) 1986 Co-60 Game 25 NDM 130 (a) Determined by the EL. Not defined in ODCM Table 4-3 (Table 4-1 of this report) 4-40

4.9 Sediment River sediment samples are collected semiannually on the Chattahoochee River at a control station which is approximately 4 miles upstream of the intake structure and at an indicator station which is approximately 2 miles downstream of the discharge structure as shown in Figure 2-2. A gamma isotopic analysis is performed on each sample as specified in Table 2-1. During 2010, no man-made radioisotopes (nor Be-7) were identified in river sediment samples.

Historically, Be-7, Cs-134, Cs-137, and Nb-95 have been detected in some samples. These positive results were generally for samples collected at the control station. A summary of the positive historical results for these nuclides along with their applicable MDCs in units of pCi/kg dry is provided in Table 4.9. Cs-134 and Cs-137 data are plotted in Figures 4.9-1 and 4.9-2, respectively.

Table 4.9 Sediment Nuclide Concentrations Nuclide YEAR Indicator (pCi/kg) Control (pCi/kg) MDC (pCi/kg)

Be-7 1985 535 945 655 (a) 2003 199 NDM 2009 72.8 NDM Cs-134 1987 NDM 45 150 1989 NDM 48 1992 138 51 1993 94 105 Cs-137 1981 NDM 185 180 1985 NDM 97 1989 NDM 39 1994 29 11 1996 11.8 NDM 2005 14.5 NDM 2009 NDM 24.4 Nb-95 1981 52 113 50 (a)

(a) Determined by the EL. Not defined in ODCM Table 4-3 (Table 4-1 of this report).

4-41

Figure 4.9-1 Average Annual Cs-134 Concentration in Sediment 160 140 Concentration (pCi/kg) 120 100 80 60 40 20 0

o 78 80 82 84 86 88 90 92 94 96 98 00 02 04 06 08 10 P

Year Indicator Control MDC The positive results for Cs-134 appear mostly at the control station. Due to its relatively short half-life of approximately 2 years, the positive results may be attributed to the Chernobyl incident. The overall plotting of the positive results does not show any discernible trends.

4-42

Figure 4.9-2 Average Annual Cs-137 Concentration in Sediment 200 180 160 Concentration (pCi/kg) 140 120 100 80 60 40 20 0

Po 78 80 82 84 86 88 90 92 94 96 98 00 02 04 06 08 10 Year Indicator Control MDC Cs-137 appears to be trending down since the ceasing of above ground weapons testing and the majority of the positive results appear at the control stations.

Therefore in general, the positive results can be attributed to the weapons tests and the Chernobyl incident.

4-43

5.0 INTERLABORATORY COMPARISON PROGRAM In accordance with ODCM 4.1.3, the EL participates in an ICP that satisfies the requirements of Regulatory Guide 4.15, Revision 1, "Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment", February 1979. The guide indicates the ICP is to be conducted with the Environmental Protection Agency (EPA) Environmental Radioactivity Laboratory Intercomparison Studies (Cross-check) Program or an equivalent program, and the ICP should include all of the determinations (sample medium/radionuclide combinations) that are offered by the EPA and included in the REMP.

The ICP is conducted by Analytics, Inc. of Atlanta, Georgia. Analytics has a documented Quality Assurance (QA) program and the capability to prepare Quality Control (QC) materials traceable to the National Institute of Standards and Technology. The ICP is a third party blind testing program which provides a means to ensure independent checks are performed on the accuracy and precision of the measurements of radioactive materials in environmental sample matrices.

Analytics supplies the crosscheck samples to the EL which performs the laboratory analyses in a normal manner. Each of the specified analyses is performed three times. The results are then sent to Analytics who performs an evaluation which may be helpful to the EL in the identification of instrument or procedural problems.

The samples offered by Analytics and included in the EL analyses are gross beta and gamma isotopic analyses of an air filter; gamma isotopic analyses of milk samples; and gross beta, tritium and gamma isotopic analyses of water samples.

The accuracy of each result is measured by the normalized deviation, which is the ratio of the reported average less the known value to the total error. The total error is the square root of the sum of the squares of the uncertainties of the known value and of the reported average. The uncertainty of the known value includes all analytical uncertainties as reported by Analytics. The uncertainty of the reported average is the propagated error of the values in the reported average by the EL.

The precision of each result is measured by the coefficient of variation, which is defined as the standard deviation of the reported result divided by the reported average. An investigation is undertaken whenever the absolute value of the normalized deviation is greater than three or whenever the coefficient of variation is greater than 15% for all radionuclides other than Cr-51 and Fe-59. For Cr-51 and Fe-59, an investigation is undertaken when the coefficient of variation exceeds the values shown as follows:

Nuclide Concentration

• Total Sample Activity Percent Coefficient (pCi) of Variation Cr-51 <300 NA 25 Cr-51 NA >1000 25 Cr-51 >300 <1000 15 Fe-59 <80 NA 25 Fe-59 >80 NA 15

• For air filters, concentration units are pCi/filter. For all other media, concentration units are pCi/liter (pCi/l).

5-1

As required by ODCM 4.1.3.3 and 7.1.2.3, a summary of the results of the EL's participation in the ICP is provided in Table 5-1 for: the gross beta and gamma isotopic analyses of an air filter; gamma isotopic analyses of milk samples; and gross beta, tritium and gamma isotopic analyses of water samples. Delineated in this table for each of the media/analysis combinations, are: the specific radionuclides; Analytics preparation dates; the known values with their uncertainties supplied by Analytics; the reported averages with their standard deviations; and the resultant normalized deviations and coefficients of variation expressed as a percentage.

In 2010, the laboratory analyzed 9 samples for 35 parameters. The analyses included tritium, gross beta and gamma emitting radio-nuclides in different matrices. The attached results indicate two analyses outside the acceptance limits for accuracy. The activity recovery of Cr-51 and Fe-59 in air filters was above the upper acceptance limit for accuracy.

The analysis of Cr-51 and Fe-59 is performed by gamma spectroscopy, with the value determined by a weighted average of four germanium detectors. In a 2005 investigation a positive bias was determined to exist in the analysis based on summing of nuclides in the calibration standard. The detectors are calibrated on a three year geometry rotation. The air filter geometry calibration was scheduled and completed in 2010. The sample analysis results indicate further investigations should be performed into the biases associated with this matrix in 2011.

5-2

TABLE 5-1 (SHEET 1 of 3)

INTERLABORATORY COMPARISON PROGRAM RESULTS GROSS BETA ANALYSIS OF AN AIR FILTER (pCi/filter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Gross Beta 09/16/10 75.40 85.80 1.91 0.48 5.86 -2.36 GAMMA ISOTOPIC ANALYSIS OF AN AIR FILTER (pCi/filter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Ce-141 09/16/10 142.70 142.00 5.99 0.79 9.77 0.05 Co-58 09/16/10 91.40 80.30 4.3 0.45 7.89 1.54 Co-60 09/16/10 196.90 186.00 3.52 1.04 3.47 1.59 Cr-51 09/16/10 345.10 255.00 47.02 1.42 24.68 1.06 Cs-134 09/16/10 90.90 101.00 2.01 0.56 5.04 -2.19 5-3 Cs-137 09/16/10 115.10 103.00 4.28 0.57 4.79 2.19 Fe-59 09/16/10 128.70 99.40 27.63 0.55 20.97 1.08 Mn-54 09/16/10 150.90 130.00 2.21 0.73 5.10 2.72 Zn-65 09/16/10 263.40 222.00 16.73 1.24 7.13 2.20 GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (pCi/liter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Ce-141 06/17/10 108.60 110.00 3.43 0.61 7.06 -0.18 Co-58 06/17/10 101.10 101.00 7.89 0.56 9.22 0.01 Co-60 06/17/10 198.60 197.00 5.92 1.09 14.97 0.05 Cr-51 06/17/10 351.40 339.00 32.24 1.89 14.01 0.25 Cs-134 06/17/10 119.60 126.00 5.23 0.70 6.32 -0.85 Cs-137 06/17/10 159.80 150.00 5.87 0.84 20.46 0.30

TABLE 5-1 (SHEET 2 of 3)

INTERLABORATORY COMPARISON PROGRAM RESULTS GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (pCi/liter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Fe-59 06/17/10 141.00 119.00 1.16 0.66 8.17 1.91 I-131 06/17/10 105.80 96.90 1.29 0.54 6.58 1.28 Mn-54 06/17/10 180.20 169.00 5.45 0.94 5.09 1.22 Zn-65 06/17/10 223.40 206.00 4.52 1.15 7.65 1.02 GROSS BETA ANALYSIS OF WATER SAMPLE (pCi/liter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation 5-4 Gross Beta 03/18/10 270.90 293.00 15.73 1.63 7.72 -1.06 06/17/10 264.00 266.00 8.8 1.48 6.42 -0.12 GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (pCi/liter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Ce-141 03/18/10 273.20 263.00 1.31 1.47 4.16 0.89 Co-58 03/18/10 146.80 144.00 5.93 0.48 6.07 0.32 Co-60 03/18/10 185.80 185.00 7.46 1.03 5.20 0.09 Cr-51 03/18/10 389.00 364.00 45.91 2.03 13.51 0.48 Cs-134 03/18/10 167.80 179.00 4.46 1.00 4.66 -1.43

TABLE 5-1 (SHEET 3 of 3)

INTERLABORATORY COMPARISON PROGRAM RESULTS GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (pCi/liter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Cs-137 03/18/10 166.40 159.00 10.97 0.89 7.23 0.62 Fe-59 03/18/10 154.80 138.00 18.72 0.77 11.00 0.99 I-131 03/18/10 71.70 72.70 1.4 0.40 8.44 -0.09 Mn-54 03/18/10 219.80 209.00 16.06 1.16 8.88 0.55 Zn-65 03/18/10 281.60 256.00 4.16 3 8.06 1.13 TRITIUM ANALYSIS OF WATER SAMPLES (pCi/liter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation 5-5 H-3 03/18/10 10480.70 12000.00 980.83 67 9.67 -1.50 06/17/10 9595.20 9630.00 177.19 53.67 2.97 -0.12 I-131 ANALYSIS OF AN AIR CARTRIDGE (pCi/cartridge)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation I-131 06/17/10 75.50 79.80 1.36 3.10 4.10 -1.39

6.0 CONCLUSION

S This report confirms the licensee's conformance with the requirements of Chapter 4 of the ODCM. It provides a summary and discussion of the results of the laboratory analyses for each type of sample.

In 2010, there one instance where the indicator station results were statistically discernible from the control station results. The annual average weekly gross beta activity in air filters was 21.2 fCi/m3 at the indicator stations and 17.5 fCi/m3 at the control stations. Gross beta is a screening analysis for beta activity. The required MDC for gross beta in air filters is 10 fCi/m3; there is no Reporting Level for gross beta in air. In general, there is close agreement between the results for the indicator, control and community stations. This close agreement supports the position that the plants contribution to gross beta concentration in air is insignificant.

No discernible radiological impact upon the environment or the public as a consequence of plant discharges to the atmosphere and to the river was established for any other REMP samples.

The radiological levels reported in 2010 were low and are generally trending downward. The REMP trends over the course of time from preoperation to the present are generally decreasing or have remained fairly constant. This supports the conclusion that there is no adverse radiological impact on the environment or to the public as a result of the operation of Farley Nuclear Plant.

6-1

EDWIN I. HATCH NUCLEAR PLANT ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2010

TABLE OF CONTENTS Title and/or Section Subsection Page List of Figures ii List of Tables iii List of Acronyms iv 1.0 Introduction 1-1 2.0 REMP Description 2-1 3.0 Results Summary 3-1 4.0 Discussion of Results 4-1 4.1 Land Use Census and River Survey 4-5 4.2 Airborne 4-7 4.3 Direct Radiation 4-12 4.4 Milk 4-18 4.5 Vegetation 4-22 4.6 River Water 4-25 4.7 Fish 4-28 4.8 Sediment 4-32 4.9 Groundwater 4-38 5.0 Interlaboratory Comparison Program 5-1 6.0 Conclusions 6-1 i

LIST OF FIGURES Figure Number Title Page Figure 2-1 REMP Stations Near the Plant 2-8 Figure 2-2 REMP Stations Beyond Six Miles from the Plant 2-9 Figure 2-3 Groundwater Monitoring Locations 2-10 Figure 2-4 Deep Wells 2-11 Figure 4.2-1 Average Weekly Gross Beta Air Concentration 4-7 Figure 4.2-2 Average Annual Cs-137 Concentration in Air 4-9 Figure 4.3-1 Average Quarterly Exposure from Direct Radiation 4-13 Figure 4.3-2 Average Quarterly Exposure from Direct Radiation at Special Interest Areas 4-15 Figure 4.4-1 Average Annual Cs-137 Concentration in Milk 4-18 Figure 4.4-2 Average Annual I-131 Concentration in Milk 4-20 Figure 4.5-1 Average Annual Cs-137 Concentration in Vegetation 4-23 Figure 4.6-1 Average Annual H-3 Concentration in River Water 4-26 Figure 4.7-1 Average Annual Cs-137 Concentration in Fish 4-28 Figure 4.7-2 Average Annual Cs-134 Concentration in Fish 4-30 Figure 4.8-1 Average Annual Co-60 Concentration in Sediment 4-32 Figure 4.8-2 Average Annual Cs-137 Concentration in Sediment 4-34 Figure 4.8-3 Average Annual Indicator Station Concentrations of Select Nuclides in Sediment 4-36 Figure 4.9-1 Plant Hatch Unconfined Perched Aquifer 4-42 November 2010 ii

LIST OF TABLES Table Number Title Page Table 2-1 Summary Description of Radiological Environmental Monitoring Program 2-2 Table 2-2 Radiological Environmental Sampling Locations 2-5 Table 2-3 Groundwater Monitoring Locations 2-7 Table 3-1 Radiological Environmental Monitoring Program Annual Summary 3-2 Table 4-1 Minimum Detectable Concentrations (MDC) 4-1 Table 4-2 Reporting Levels (RL) 4-2 Table 4-3 Deviations from Radiological Environmental Monitoring Program 4-4 Table 4.1-1 Land Use Census Results 4-5 Table 4.2-1 Average Weekly Gross Beta Air Concentration 4-8 Table 4.2-2 Average Annual Cs-137 Concentration in Air 4-10 Table 4.3-1 Average Quarterly Exposure from Direct Radiation 4-14 Table 4.3-2 Average Quarterly Exposure from Direct Radiation at Special Interest Areas 4-16 Table 4.4-1 Average Annual Cs-137 Concentration in Milk 4-19 Table 4.4-2 Average Annual I-131 Concentration in Milk 4-21 Table 4.5-1 Average Annual Cs-137 Concentration in Vegetation 4-24 Table 4.6-1 Average Annual H-3 Concentration in River Water 4-27 Table 4.7-1 Average Annual Cs-137 Concentration in Fish 4-29 Table 4.7-2 Average Annual Cs-134 Concentration in Fish 4-31 Table 4.8-1 Average Annual Co-60 Concentration in Sediment 4-33 Table 4.8-2 Average Annual Cs-137 Concentration in Sediment 4-35 Table 4.8-3 Sediment Nuclide Concentrations Other Than Co-60 &

Cs-137 4-37 Table 5-1 Interlaboratory Comparison Results 5-3 iii

LIST OF ACRONYMS Acronyms presented in alphabetical order.

Acronym Definition ASTM American Society for Testing and Materials CL Confidence Level EL Georgia Power Company Environmental Laboratory EPA Environmental Protection Agency GPC Georgia Power Company HNP Edwin I. Hatch Nuclear Plant ICP Interlaboratory Comparison Program MDC Minimum Detectable Concentration MDD Minimum Detectable Difference NA Not Applicable NDM No Detectable Measurement(s)

NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual Po Preoperation REMP Radiological Environmental Monitoring Program RL Reporting Level TLD Thermoluminescent Dosimeter TS Technical Specification iv

1.0 INTRODUCTION

The Radiological Environmental Monitoring Program (REMP) is conducted in accordance with Chapter 4 of the Offsite Dose Calculation Manual (ODCM).

REMP activities for 2010 are reported herein in accordance with Technical Specification (TS) 5.6.2 and ODCM 7.1.

The objectives of the REMP are to:

1) Determine the levels of radiation and the concentrations of radioactivity in the environs and;

2) Assess the radiological impact (if any) to the environment due to the operation of the Edwin I. Hatch Nuclear Plant (HNP).

The assessments include comparisons between the results of analyses of samples obtained at locations where radiological levels are not expected to be affected by plant operation (control stations) and at locations where radiological levels are more likely to be affected by plant operation (indicator stations), as well as comparisons between preoperational and operational sample results.

The pre-operational stage of the REMP began with the establishment and activation of the environmental monitoring stations in January of 1972. The operational stage of the REMP began on September 12, 1974 with Unit 1 initial criticality.

A description of the REMP is provided in Section 2 of this report. An annual summary of the results of the analyses of REMP samples is provided in Section 3.

A discussion of the results, including assessments of any radiological impacts upon the environment, and the results of the land use census and the river survey, are provided in Section 4. The results of the Interlaboratory Comparison Program (ICP) are provided in Section 5. Conclusions are provided in Section 6.

1-1

2.0 REMP DESCRIPTION A summary description of the REMP is provided in Table 2-1. This table summarizes the program as it meets the requirements outlined in ODCM Table 4-1. It details the sample types to be collected and the analyses to be performed in order to monitor the airborne, direct radiation, waterborne and ingestion pathways, and also delineates the collection and analysis frequencies. The sampling locations (stations) specified by ODCM 4.2 are depicted on maps in Figures 2-1 and 2-2. These maps are keyed to Table 2-2 which delineates the direction and distance of each station from the main stack.

REMP samples are collected by Georgia Power Company's (GPC) Environmental Laboratory (EL) personnel. The same lab performs all the laboratory analyses at their headquarters in Smyrna, Georgia.

2-1

TABLE 2-1 (SHEET 1 of 3)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Approximate Sampling and Type of Analysis and Frequency and/or Sample Number of Sample Collection Frequency Locations

1. Airborne 6 Continuous operation Radioiodine canister: I-131 analysis, weekly.

Radioiodine and of the sampler with Particulates sample collection Particulate sampler: analyze for gross beta radioactivity not less weekly. than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change, weekly; perform gamma isotopic analysis on affected sample when gross beta activity is 10 times the yearly mean of control samples; and composite (by location) for gamma isotopic analysis, quarterly.

2. Direct Radiation 37 Quarterly Gamma dose, quarterly.

3. Ingestion 2-2 Milk (a) 1 Biweekly Gamma isotopic and I-131 analysis, biweekly.

Fish or Clams (b) 2 Semiannually Gamma isotopic analysis on edible portions, semiannually.

Grass or Leafy 3 Monthly during Gamma isotopic analysis, monthly. (c)

Vegetation growing season.

4. Waterborne Surface 2 Composite sample Gamma isotopic analysis, monthly. Composite (by location) for collected monthly. (d) tritium analysis, quarterly.

Sediment 2 Semiannually. Gamma isotopic analysis, semiannually.

TABLE 2-1 (SHEET 2 of 3)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Approximate Sampling and Type of Analysis and Frequency and/or Sample Number of Sample Collection Frequency Locations Drinking Water One sample of river River water collected I-131 analysis on each sample when biweekly collections are (e & f) water near the intake near the intake will be required. Gross beta and gamma isotopic analysis on each and one sample of a composite sample; sample; composite (by location) for tritium analysis, quarterly.

finished water from the finished water will each of one to three be a grab sample.

of the nearest water These samples will be supplies which could collected monthly be affected by HNP unless the calculated discharges. dose due to consumption of the water is greater than 1 2-3 mrem/year; then the collection will be biweekly. The collections may revert to monthly should the calculated doses become less than 1 mrem/year.

Groundwater See Table 2-3, Quarterly sample; Tritium, gamma isotopic, and field parameters (pH, Figure 2-3, and pump used to sample temperature, conductivity, dissolved oxygen, Figure 2-4 GW wells; grab oxidation/reduction potential, and turbidity) of each sample sample from yard quarterly; Hard to detect radionuclides as necessary based on drains and ponds results of tritium and gamma

TABLE 2-1 (SHEET 3 of 3)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Notes:

a. Up to three sampling locations within 5 miles and in different sectors will be used as available. In addition, one or more control locations beyond 10 miles will be used.

b. Commercially or recreationally important fish may be sampled. Clams may be sampled if difficulties are encountered in obtaining sufficient fish samples.

c. If gamma isotopic analysis is not sensitive enough to meet the Minimum Detectable Concentration (MDC), a separate analysis for I-131 may be performed.

d. The composite samples shall be composed of a series of aliquots collected at intervals not exceeding a few hours.

e. If it is found that river water downstream of the plant is used for drinking, drinking water samples will be collected and analyzed as specified herein.

f. A survey shall be conducted annually at least 50 river miles downstream of the plant to identify those who use water from the 2-4 Altamaha River for drinking.

TABLE 2-2 (SHEET 1 of 2)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Station Station Descriptive Location Direction Distance (a) Sample Type Number Type (a) (miles) 064 Other Roadside Park WNW 0.8 Direct Rad 101 Indicator Inner Ring N 1.9 Direct Rad 102 Indicator Inner Ring NNE 2.5 Direct Rad 103 Indicator Inner Ring NE 1.8 Airborne Rad Direct Rad 104 Indicator Inner Ring ENE 1.6 Direct Rad 105 Indicator Inner Ring E 3.7 Direct Rad 106 Indicator Inner Ring ESE 1.1 Direct Rad Vegetation 107 Indicator Inner Ring SE 1.2 Airborne Rad Direct Rad 108 Indicator Inner Ring SSE 1.6 Direct Rad 109 Indicator Inner Ring S 0.9 Direct Rad 110 Indicator Inner Ring SSW 1.0 Direct Rad 111 Indicator Inner Ring SW 0.9 Direct Rad 112 Indicator Inner Ring WSW 1.0 Airborne Rad Direct Rad Vegetation 113 Indicator Inner Ring W 1.1 Direct Rad 114 Indicator Inner Ring WNW 1.2 Direct Rad 115 Indicator Inner Ring NW 1.1 Direct Rad 116 Indicator Inner Ring NNW 1.6 Airborne Rad Direct Rad 170 Control Upstream WNW (c) River (b) 172 Indicator Downstream E (c) River (b) 201 Other Outer Ring N 5.0 Direct Rad 202 Other Outer Ring NNE 4.9 Direct Rad 203 Other Outer Ring NE 5.0 Direct Rad 204 Other Outer Ring ENE 5.0 Direct Rad 205 Other Outer Ring E 7.2 Direct Rad 206 Other Outer Ring ESE 4.8 Direct Rad 207 Other Outer Ring SE 4.3 Direct Rad 208 Other Outer Ring SSE 4.8 Direct Rad 209 Other Outer Ring S 4.4 Direct Rad 210 Other Outer Ring SSW 4.3 Direct Rad 211 Other Outer Ring SW 4.7 Direct Rad 212 Other Outer Ring WSW 4.4 Direct Rad 213 Other Outer Ring W 4.3 Direct Rad 214 Other Outer Ring WNW 5.4 Direct Rad 215 Other Outer Ring NW 4.4 Direct Rad 216 Other Outer Ring NNW 4.8 Direct Rad 301 Other Toombs Central School N 8.0 Direct Rad 304 Control State Prison ENE 11.2 Airborne Rad Direct Rad 304 Control State Prison ENE 10.3 Milk 309 Control Baxley S 10.0 Airborne Rad Substation Direct Rad 416 Control Emergency News NNW 21.0 Direct Rad Center Vegetation 2-5

TABLE 2-2 (SHEET 2 of 2)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Notes:

a. Direction and distance are determined from the main stack.

b. River (fish or clams, shoreline sediment, and surface water)

c. Station 170 is located approximately 0.6 river miles upstream of the intake structure for river water, 1.1 river miles for sediment and clams, and 1.5 river miles for fish.

Station 172 is located approximately 3.0 river miles downstream of the discharge structure for river water, sediment and clams, and 1.7 river miles for fish.

The locations from which river water and sediment may be taken can be sharply defined.

However, the sampling locations for clams often have to be extended over a wide area to obtain a sufficient quantity. High water adds to the difficulty in obtaining clam samples and may also make an otherwise suitable location for sediment sampling unavailable. A stretch of the river of a few miles or so is generally needed to obtain adequate fish samples. The mile locations given above represent approximations of the locations where samples are collected.

2-6

TABLE 2-3 GROUNDWATER MONITORING LOCATIONS WELL DEPTH (ft) MONITORING PURPOSE R1 82.9 Confined Aquifer Upgradient R2 82.7 Confined Aquifer Near Diesel Generator Bldg.

R3 89.2 Confined Aquifer Near CST-1 R4 41 Dilution Line Near River Water Discharge Structure R5 33.6 Between Subsurface Drain Lines Downgradient R6 38.2 Between Subsurface Drain Lines Downgradient NW2A 27 Water Table Near CST-2 Inside of Subsurface Drain NW2B 27 Water Table Outside of Subsurface Drain NW3A 26.5 Water Table Inside of Subsurface Drain NW3B 25.3 Water Table Outside of Subsurface Drain NW4A 27 Water Table Upgradient Inside of Subsurface Drain NW5A 26.7 Water Table Upgradient Inside of Subsurface Drain NW5B 26.3 Water Table Upgradient Outside of Subsurface Drain NW6 27 Water Table Near Diesel Generator Bldg.

NW8 23 Water Table Near Diesel Generator Bldg.

NW9 26.1 Water Table Downgradient Inside of Subsurface Drain NW10 26.2 Water Table Near CST-2 T3 18 Water Table Near Turbine Bldg.

T7 21.4 Water Table Near Diesel Generator Bldg.

T10 18.8 Water Table Near CST-1 T12 23.2 Water Table Near CST-1 T15 27.4 Water Table Near CST-1 P15A* 74.5 Confined Aquifer Near Turbine Bldg.

P15B 18 Water Table Near Turbine Bldg.

P17A* 77 Confined Aquifer Near Diesel Generator Bldg.

P17B 14.8 Water Table Near Diesel Generator Bldg.

Deep Well 1 680 Backup Supply for Potable Water (infrequently used)

Deep Well 2 711 Plant Potable Water Supply Deep Well 3 710 Potable Water Supply - Rec. Center, Firing Range, and Garage

• Used for water level only 2-7

3.0 RESULTS

SUMMARY

In accordance with ODCM 7.1.2.1, the summarized and tabulated results for all of the regular samples collected for the year at the designated indicator and control stations are presented in Table 3-1. The format of Table 3-1 is similar to Table 3 of the Nuclear Regulatory Commission (NRC) Branch Technical Position, An Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. Since no naturally occurring radionuclides were found in the plant's effluent releases, only man-made radionuclides are reported as permitted by ODCM 7.1.2.1. Results for samples collected at locations other than control or indicator stations are discussed in Section 4 under the particular sample type.

3-1

TABLE 3-1 (SHEET 1 of 4)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Edwin I. Hatch Nuclear Plant, Docket Nos. 50-321 and 50-366 Appling County, Georgia Medium or Type and Total Minimum Indicator Location with the Highest Other Control Pathway Number of Detectable Locations Annual Mean Stations(g) Locations Sampled Analyses Concentration Mean (b), Mean (b), Mean (b),

(Unit of Performed (MDC) (a) Range Name Distance Mean (b), Range Range Measurement) (Fraction) & Direction Range (Fraction) (Fraction)

(Fraction)

Airborne Gross Beta 10 23.1 No. 304 24.3 NA 24.0 Particulates 312 10.0-52.4 State Prison 10.2-51.8 10.2-51.8 (fCi/m3) (208/208) 11.2 miles ENE (52/52) (104/104)

Gamma Isotopic 24 Cs-134 50 NDM (c) NDM NDM Cs-137 60 NDM NDM NDM Airborne I-131 70 NDM NDM NA NDM Radioiodine 299 3-2 (fCi/m3)

Direct Radiation Gamma Dose NA (d) 15.8 No. 214 19.3 15.9 15.6 (mR/91 days) 146 9.7-24.6 Outer Ring 14.6-26.1 10.1-26.1 10.0-21.7 (64/64) 5.4 miles WNW (4/4) (72/72) (12/12)

Milk Gamma Isotopic NA (pCi/l) 26 Cs-134 15 NA NDM NDM Cs-137 18 NA NDM NDM Ba-140 60 NA NDM NDM La-140 15 NA NDM NDM I-131 1 NA NDM NDM 26

TABLE 3-1 (SHEET 2 of 4)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Edwin I. Hatch Nuclear Plant, Docket Nos. 50-321 and 50-366 Appling County, Georgia Medium or Type and Minimum Indicator Location with the Highest Control Pathway Total Number Detectable Locations Annual Mean Locations Sampled of Analyses Concentration Mean (b), Mean (b),

(Unit of Performed (MDC) (a) Range Name Distance Mean (b), Range Measurement) (Fraction) & Direction Range (Fraction) (Fraction)

Vegetation Gamma (pCi/kg-wet) Isotopic 36 I-131 60 NDM NDM NDM Cs-134 60 NDM NDM NDM Cs-137 80 31.4 Station 106 33.4 NDM 16.8-68.8 Inner Ring 16.8-68.8 (8/24) 1.1 miles ESE (7/12)

River Water Gamma (pCi/l) Isotopic 3-3 24 Mn-54 15 NDM NDM NDM Fe-59 30 NDM NDM NDM Co-58 15 NDM NDM NDM Co-60 15 NDM NDM NDM Zn-65 30 NDM NDM NDM Zr-95 30 NDM NDM NDM Nb-95 15 NDM NDM NDM I-131 15 (e) NDM NDM NDM Cs-134 15 NDM NDM NDM Cs-137 18 NDM NDM NDM Ba-140 60 NDM NDM NDM La-140 15 NDM NDM NDM Tritium 3000 (f) 403 No. 170 426 426 8 307-583 0.6 miles 262-589 262-589 (3/4) Upstream (2/4) (2/4)

TABLE 3-1 (SHEET 3 of 4)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Edwin I. Hatch Nuclear Plant, Docket Nos. 50-321 and 50-366 Appling County, Georgia Medium or Type and Minimum Indicator Location with the Highest Control Pathway Total Number Detectable Locations Annual Mean Locations Sampled of Analyses Concentration Mean (b), Mean (b),

(Unit of Performed (MDC) (a) Range Name Distance Mean (b), Range Measurement) (Fraction) & Direction Range (Fraction) (Fraction)

Fish Gamma (pCi/kg-wet) Isotopic 4

Mn-54 130 NDM NDM NDM Fe-59 260 NDM NDM NDM Co-58 130 NDM NDM NDM Co-60 130 NDM NDM NDM Zn-65 260 NDM NDM NDM Cs-134 130 NDM NDM NDM Cs-137 150 11.6 No. 172 11.6 8.6 3-4 10.6-12.6 3.0 miles 10.6-12.6 7.2-10.0 (2/2) Downstream (2/2) (2/2)

Sediment Gamma (pCi/kg-dry) Isotopic 4

Cs-134 150 NDM NDM NDM Cs-137 180 47.0 No. 172 47.0 39.5 21.4-72.7 3.0 miles 21.4-72.7 35.2-43.9 (2/2) Downstream (2/2) (2/2)

TABLE 3-1 (SHEET 4 of 4)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Edwin I. Hatch Nuclear Plant, Docket Nos. 50-321 and 50-366 Appling County, Georgia NOTATIONS

a. The MDC is defined in ODCM 10.1. Except as noted otherwise, the values listed in this column are the detection capabilities required by ODCM Table 4-3. The values listed in this column are a priori (before the fact) MDCs. In practice, the a posteriori (after the fact) MDCs are generally lower than the values listed. Any a posteriori MDC greater than the value listed in this column is discussed in Section 4.

b. Mean and range are based upon detectable measurements only. The fraction of all measurements at specified locations that are detectable is placed in parenthesis.

c. No Detectable Measurement(s).

d. Not Applicable.

3-5 e. If a drinking water pathway were to exist, a MDC of 1 pCi/l would have been used (see Table 4-1 of this report).

f. If a drinking water pathway were to exist, a MDC of 2000 pCi/l would have been used (see Table 4-1 of this report).

g. Other stations, identified in the station type column of Table 2-2, include community and special stations.

4.0 DISCUSSION OF RESULTS Included in this section are evaluations of the laboratory results for the various sample types. Comparisons were made between the difference in mean values for pairs of station groups (e.g., indicator and control stations) and the calculated Minimum Detectable Difference (MDD) between these pairs at the 99%

Confidence Level (CL). The MDD was determined using the standard Student's t-test. A difference in the mean values which was less than the MDD was considered to be statistically indiscernible.

The 2010 results were compared with past results, including those obtained during pre-operation. As appropriate, results were compared with their Minimum Detectable Concentrations (MDC) and Reporting Levels (RL) which are listed in Tables 4-1 and 4-2 of this report, respectively. The required MDCs were achieved during laboratory sample analyses. Any anomalous results are explained within this report.

Results of interest are graphed to show historical trends. The data points are tabulated and included in this report. The points plotted and provided in the tables represent mean values of only detectable results. Periods for which no detectable measurements (NDM) were observed or periods for which values were not applicable (e.g., milk indicator, etc.) are plotted as 0s and listed in the tables as NDM.

Table 4-1 Minimum Detectable Concentrations (MDC)

Analysis Water Airborne Fish Milk Grass or Sediment (pCi/l) Particulate (pCi/kg- (pCi/l) Leafy (pCi/kg-or Gases wet) Vegetation dry)

(fCi/m3) (pCi/kg-wet)

Gross Beta 4 10 H-3 2000 (a)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 1 (b) 70 1 60 Cs-134 15 50 130 15 60 150 Cs-137 18 60 150 18 80 180 Ba-140 60 60 La-140 15 15 (a) If no drinking water pathway exists, a value of 3000 pCi/l may be used.

(b) If no drinking water pathway exists, a value of 15 pCi/l may be used.

4-1

Table 4-2 Reporting Levels (RL)

Analysis Water Airborne Fish Milk (pCi/l) Grass or Leafy (pCi/l) Particulate (pCi/kg-wet) Vegetation or Gases (pCi/kg-wet)

(fCi/m3)

H-3 20,000 (a)

Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-95 400 Nb-95 700 I-131 2 (b) 900 3 100 Cs-134 30 10,000 1000 60 1000 Cs-137 50 20,000 2000 70 2000 Ba-140 200 300 La-140 100 400 (a) This is the 40 CFR 141 value for drinking water samples. If no drinking water pathway exists, a value of 30,000 may be used.

(b) If no drinking water pathway exists, a value of 20 pCi/l may be used.

4-2

Atmospheric nuclear weapons tests from the mid 1940s through 1980 distributed man-made nuclides around the world. The most recent atmospheric tests in the 1970s and in 1980 had a significant impact upon the radiological concentrations found in the environment prior to and during preoperation, and the earlier years of operation. Some long lived radionuclides, such as Cs-137, continue to be detectable.

Significant upward trends also followed the Chernobyl incident which began on April 26, 1986.

In accordance with ODCM 4.1.1.2.1, deviations from the required sampling schedule are permitted, if samples are unobtainable due to hazardous conditions, unavailability, inclement weather, equipment malfunction or other just reasons.

Deviations from conducting the REMP as described in Table 2-1 are summarized in Table 4-3 along with their causes and resolutions.

All results were tested for conformance to Chauvenet's criterion (G. D. Chase and J. L. Rabinowitz, Principles of Radioisotope Methodology, Burgess Publishing Company, 1962, pages 87-90) to identify values which differed from the mean of a set by a statistically significant amount. Identified outliers were investigated to determine the reason(s) for the difference. If equipment malfunction or other valid physical reasons were identified as causing the variation, the anomalous result was excluded from the data set as non-representative. No data were excluded exclusively for failing Chauvenet's criterion. Data exclusions are discussed in this section under the appropriate sample type.

4-3

TABLE 4-3 DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM COLLECTION AFFECTED DEVIATION CAUSE RESOLUTION PERIOD SAMPLES January - May 2010 RW Station 172 Non-representative river Monthly grab sample taken of river water Platform reconstructed and Monthly Composites Downstream 3 miles E sample January through May; ISCO sampler ISCO sampler replaced CR2011105991 destroyed by flooding when flood waters receded 2nd Quarter 2010 All Second Quarter TLD Direction radiation Panasonic TLD reader problems caused OSL Inlight system put in Corp CR2011100346 Results results higher than a three week delay in reading 2nd quarter service in January 2011; typical badges Panasonic system retired 2nd Quarter 2010 TLD Non-representative Badges were wet at collection time Replaced TLDs at CR2011105992 Station 201 direct radiation data beginning of quarter 5.0 miles N 2nd Quarter 2010 TLD Non-representative At collection time, pouch found opened Replaced TLDs at CR2011105992 Station 112A direct radiation data with slide partially exposed beginning of quarter 1.0 mile WSW 4th Quarter TLD Non-representative TLDs were missing at mid-quarter; Replaced TLDs at 4-4 CR2010105988 Station 210 direct radiation data replaced with blanks but data was not beginning of quarter EXCLUDED 4.3 miles SSE representative of collection period

4.1 Land Use Census and River Survey In accordance with ODCM 4.1.2, a land use census was conducted on November 8, 2010, to determine the locations of the nearest permanent residence and milk animal in each of the 16 compass sectors within a distance of 5 miles, and the locations of all milk animals within a distance of 3 miles. A milk animal is defined as a cow or goat producing milk for human consumption. The locations of beef cattle and of gardens greater than 500 square feet producing broad leaf vegetation were also included in the census. The census results are tabulated in the Table 4.1-1.

Table 4.1-1 LAND USE CENSUS RESULTS Distance in Miles to Nearest Location in Each Sector SECTOR RESIDENCE MILK ANIMAL BEEF CATTLE GARDEN N 2.8 None None 3.8 NNE 2.9 None None 4.7 NE 3.3 None 3.4 None ENE 4.2 None 4.1 None E 3.0 None None None ESE 3.8 None None None SE 1.8 None 2.4 4.4 SSE 2.0 None 3.6 2.1 S 1.1 None 2.5 2.2 SSW 1.3 None 2.0 None SW 1.1 None 2.3 1.6 WSW 1.0 None 3.6 3.0 W 1.1 None 2.7 None WNW 1.1 None None None NW 3.6 None 4.5 4.3 NNW 1.8 None 2.8 2.8 4-5

ODCM 4.1.2.2.1 requires a new controlling receptor to be identified if the land use census identifies a location that yields a calculated receptor dose greater than the one in current use. No change in the controlling receptor was required as a result of the 2010 land use census. The current controlling receptor as described in ODCM Table 3-7 is a child in the WSW Sector at 1.2 miles ODCM 4.1.2.2.2 requires that whenever the land use census identifies a location which would yield a calculated dose (via the same ingestion pathway) 20% greater than that of a current indicator station, the new location must become a REMP station (if samples are available). The 2010 land use census did not identify a garden which yielded a calculated dose 20% greater than that for any of the current indicator stations for vegetation. The results of the census were corroborated by inquiries to the county extension agents in the 5 counties in the vicinity of the plant.

As required by Note f of Table 2-1, the annual survey of the Altamaha River for 50 miles downstream of the plant was conducted on September 27, 2010 to identify any withdrawal of river water for drinking purposes. No sources of withdrawal for drinking water or agricultural purposes were identified. Information obtained from the Georgia Department of Natural Resources on September 29 and 30, 2010 indicated that no surface water withdrawal permits for agricultural or drinking purposes had been issued for this stretch of the Altamaha River between the 2009 survey and the 2010 survey. Should it be determined that river water downstream of the plant is being used for drinking, the sampling and analysis requirements for drinking water found in Table 2-1 would be implemented.

4-6

4.2 Airborne As indicated in Table 2-2 and Figures 2-1 and 2-2, airborne particulates and airborne radioiodine are collected at 4 indicator stations (Nos. 103, 107, 112 and 116) which encircle the plant near the site periphery and at 2 control stations (Nos.

304 and 309) which are located approximately 10 miles from the main stack. At each location, air is continuously drawn through a glass fiber filter and a charcoal canister placed in series to collect airborne particulates and radioiodine. The filters and canisters are collected weekly and analyzed for gross beta and I-131, respectively. A gamma isotopic analysis is performed quarterly on a composite of the filters for each station.

The 2010 annual average weekly gross beta concentration of 23.1 fCi/m3 for the indicator stations was 0.9 fCi/m3 less than that for the control stations (24.0 fCi/m3). This difference is not statistically discernible, since it is less than the calculated MDD of 2.3 fCi/m3. Figure 4.2-1 and Table 4.2-1 provide the historical trending of the average weekly gross beta concentrations in air. In general, there is close agreement between the results for the indicator and control stations. This close agreement supports the position that the plant is not contributing significantly to the gross beta concentration in air.

Figure 4.2-1 Average Weekly Gross Beta Air Concentration 300 250 Concentration (fCi/m3) 200 150 100 50 0

Po 75 77 79 81 83 85 87 89 91 93 95 97 99 01 03 05 07 09 Year MDC Indicator Control 4-7

Table 4.2-1 Average Weekly Gross Beta Air Concentration Year Indicator Control (fCi/m3) (fCi/m3)

Pre-op 140 140 1974 87 90 1975 85 90 1976 135 139 1977 239 247 1978 130 137 1979 38 39 1980 49 48 1981 191 203 1982 33 34 1983 31 30 1984 26 28 1985 22 21 1986 36 38 1987 23 22 1988 22.6 21.7 1989 18.4 17.8 1990 19.3 18.7 1991 18.1 18 1992 18.5 18.4 1993 20.4 20.7 1994 19.5 19.7 1995 21.7 21.7 1996 21.3 21.4 1997 20.3 20.7 1998 20.0 20.5 1999 21.3 21.3 2000 23.6 23.9 2001 21.5 21.0 2002 19.3 19.2 2003 18.8 18.2 2004 21.4 21.3 2005 19.7 19.4 2006 24.9 24.7 2007 24.4 24.3 2008 21.8 22.5 2009 21.2 21.4 2010 23.1 24.0 4-8

During 2010, no man-made radionuclides were detected from the gamma isotopic analysis of the quarterly composites of the particulate air filters. During preoperation and during operation through 1986, a number of fission products and activation products were detected.

These were generally attributed to the nuclear weapons tests and to the Chernobyl incident.

On only one occasion since 1986, has a man-made radionuclide been detected in a quarterly composite. A small amount of Cs-137 (1.7 fCi/m3) was identified in the first quarter of 1991 at Station 304. The MDC and RL for Cs-137 in air are 60 and 20,000 fCi/m3, respectively.

The historical trending of the average annual concentrations of detectable Cs-137 from quarterly air filter composites is provided in Figure 4.2-2 and Table 4.2-2.

Figure 4.2-2 Average Annual Cs-137 Concentration in Air 60 50 Concentration (fCi/m3) 40 30 20 10 0

Po 75 77 79 81 83 85 87 89 91 93 95 97 99 01 03 05 07 09 Year Indicator Control MDC 4-9

Table 4.2-2 Average Annual Cs-137 Concentration In Air Year Indicator Control (fCi/m3) (fCi/m3)

Pre-op NDM 2.0 1974 1.5 2.0 1975 1.4 1.4 1976 0.6 0.7 1977 1.5 1.4 1978 2.3 2.6 1979 0.8 0.8 1980 0.4 0.6 1981 1.8 1.7 1982 0.5 0.6 1983 0.7 NDM 1984 NDM NDM 1985 0.7 NDM 1986 8.1 9.6 1987 NDM NDM 1988 NDM NDM 1989 NDM NDM 1990 NDM NDM 1991 NDM 1.7 1992 NDM NDM 1993 NDM NDM 1994 NDM NDM 1995 NDM NDM 1996 NDM NDM 1997 NDM NDM 1998 NDM NDM 1999 NDM NDM 2000 NDM NDM 2001 NDM NDM 2002 NDM NDM 2003 NDM NDM 2004 NDM NDM 2005 NDM NDM 2006 NDM NDM 2007 NDM NDM 2008 NDM NDM 2009 NDM NDM 2010 NDM NDM 4-10

No airborne I-131 was detected in the charcoal canisters in 2010. During 1976, 1977, and 1978, positive levels of I-131 were found in nearly all of the samples collected for a period of a few weeks following atmospheric nuclear weapons tests.

Some of the concentrations were on the order of 70 fCi/m3. In 1986, the same phenomenon occurred following the Chernobyl incident. The highest airborne I-131 concentration found to date in an individual charcoal canister was 217 fCi/m3 in 1977. The MDC and RL for airborne I-131 are 70 fCi/m3 and 900 fCi/m3, respectively.

Table 4-3 lists REMP deviations that occurred in 2010. There were no air sampling deviations.

4-11

4.3 Direct Radiation Direct (external) radiation is measured with thermoluminescent dosimeters (TLDs). Two Panasonic UD-814 TLD badges are placed at each station. Each badge contains three phosphors composed of calcium sulfate crystals (with thulium impurity). The gamma dose at each station is based upon the average readings of the phosphors from the two badges. The badges for each station are placed in thin plastic bags for protection from moisture while in the field. The badges are nominally exposed for periods of a quarter of a year (91 days). An inspection is performed near mid-quarter to assure that all badges are on-station and to replace any missing or damaged badges.

Two TLD stations are established in each of the 16 compass sectors around the plant to form 2 concentric rings, as seen in Figures 2-1 and 2-2. The two ring configuration of stations was established in 1980, in accordance with NRC Branch Technical Position An Acceptable Radiological Environmental Monitoring Program, Revision 1, 1979. With the exception of the East sector, the inner ring stations (Nos. 101 through 116) are located near the site boundary and the outer ring stations (Nos. 201 through 216) are located at distances of 4 to 5 miles from the plant. The stations in the East sector are a few miles farther out than the other stations in their respective rings due to large swamps making normal access extremely difficult. The 16 stations forming the inner ring are designated as the indicator stations. The 3 control stations (Nos. 304, 309 and 416) are located 10 miles or more from the plant. Stations 064 and 301 monitor special interest areas.

Station 064 is located at the onsite roadside park, while Station 301 is located near the Toombs Central School. Station 210, in the outer ring, is located near the Altamaha School (the only other nearby school).

As provided in Table 3-1, the average quarterly exposure measured at the indicator stations (inner ring) during 2010 was 15.8 mR. At the control stations, the average quarterly exposure was 15.6 mR. This difference (0.2 mR) is not statistically discernible since it is less than the MDD of 2.8 mR.

The quarterly exposures acquired at the outer ring stations during 2010 ranged from 10.1 to 26.1 mR, with an average of 16.0 mR. The average for the outer ring stations was 0.4 mR more than the average for the control stations. Since the results for the outer ring stations and the control stations differ by less than the MDD of 3.0 mR, there is no discernible difference between outer ring and control station results for 2010.

The historical trending of the average quarterly exposures for the indicator inner ring, outer ring, and the control stations are plotted in Figure 4.3-1 and listed in Table 4.3-1. The decrease between 1991 and 1992 values is attributed to a change in TLDs from Teledyne to Panasonic. It should be noted however that the differences between indicator and control and outer ring values did not change.

The close agreement between the station groups supports the position that the plant is not contributing significantly to direct radiation in the environment.

4-12

Figure 4.3-1 Average Quarterly Exposure from Direct Radiation 30 25 20 Exposure (mR) 15 10 5

0 Po 75 77 79 81 83 85 87 89 91 93 95 97 99 01 03 05 07 09 Year Indicator Control Outer Ring 4-13

Table 4.3-1 Average Quarterly Exposure from Direct Radiation Year Indicator (mR) Control (mR) Outer Ring (mR)

Pre-op 22.3 23 NA 1974 23.2 25.6 NA 1975 10.0 10.5 NA 1976 8.18 6.9 NA 1977 7.31 6.52 NA 1978 6.67 6.01 NA 1979 5.16 6.77 NA 1980 4.44 5.04 4.42 1981 5.9 5.7 5.7 1982 12.3 12 11.3 1983 11.4 11.3 10.6 1984 13.3 12.9 11.9 1985 14.7 14.7 13.7 1986 15 14 14.5 1987 14.9 14.6 15.3 1988 15.0 14.7 15.2 1989 16.4 18.0 16.5 1990 14.9 13.9 14.7 1991 15.1 13.7 15.6 1992 11.9 10.9 12.3 1993 11.6 10.7 11.5 1994 11 10.7 11.2 1995 11.5 10.8 11.3 1996 11.6 11.3 11.6 1997 12.3 11.8 12.3 1998 12.1 12.3 12.3 1999 12.8 13.2 13.0 2000 13.6 13.3 13.3 2001 12.0 12.1 11.8 2002 11.7 11.7 11.5 2003 11.4 11.4 11.4 2004 12.2 12.4 12.2 2005 12.1 12.5 12.0 2006 12.4 11.9 11.8 2007 12.8 12.5 12.6 2008 13.0 12.3 12.4 2009 12.4 12.2 12.2 2010 15.8 15.6 16.0 4-14

The historical trending of the average quarterly exposures at the special interest areas for the past 23 years is provided in Figure 4.3-2 and listed in Table 4.3-2. These exposures are within the range of those acquired at the other stations. They too, show that the plant is not contributing significantly to direct radiation at the special interest areas.

Figure 4.3-2 Average Quarterly Exposure from Direct Radiation at Special Interest Areas 25 20 Dose (mR) 15 10 5

0 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 Year Roadside Park (Sta 064) Toombs Central School (Sta 301) 4-15

Table 4.3-2 Average Quarterly Exposure from Direct Radiation at Special Interest Areas Period Station 064 Station 301 (mR) (mR) 1986 14.6 15.1 1987 14.2 15.0 1988 14.9 15.3 1989 16.1 16.6 1990 15.1 14.4 1991 14.4 15.2 1992 11.1 11.5 1993 11.2 10.8 1994 10.4 10.7 1995 11.0 10.5 1996 11.7 11.0 1997 12.6 11.4 1998 12.4 11.8 1999 12.5 12.4 2000 13.3 12.6 2001 11.8 11.3 2002 11.4 11.4 2003 11.2 11.1 2004 11.9 12.3 2005 11.8 12.4 2006 11.9 11.6 2007 11.9 12.1 2008 12.3 12.2 2009 12.1 12.1 2010 15.7 15.5 In 2010, there were four deviations involving direct radiation measurements. Most notable was in second quarter the TLD readings from Hatch (and Farley and Vogtle) were higher for the majority of the stations. This anomaly was attributed to significant problems with the Panasonic TLD reader (which was nearing obsolescence). Processing the second quarter badges was delayed about three weeks. The TLD data was kept for second quarter and the anomaly was noted.

The Panasonic system was retired at the end of 2010 and a new Inlight OSL system (which was in use for personnel monitoring in 2010), is now in use for environmental direct radiation measurements. A comparison study was done 4-16

during 2010 where the OSL badges were placed on station with the TLD badges.

The results of this study will be discussed in the 2011 REMP Report. Also in second quarter, TLD 201A&B were wet at collection time and TLD 112A was found with the pouch open and the slide partially exposed. In fourth quarter, the TLDs at Station 210 were missing at midquarter and blanks were put in place to collect data for the remainder of the quarter. The results passed Chauvenets Criterion for the affected stations in second and fourth quarters and were retained in the data set.

The standard deviation for the quarterly result for each badge was subjected to a self-imposed limit of 1.4. This limit is based upon the standard deviations obtained with the Panasonic UD-814 badges during 1992 and is calculated using a method developed by the American Society of Testing and Materials (ASTM Special Technical Publication 15D, ASTM Manual on Presentation of Data and Control Chart Analysis, Fourth Revision, Philadelphia, PA, October 1976).

The limit serves as a flag to initiate an investigation. To be conservative, readings with a standard deviation greater than 1.4 are excluded from the data set since the high standard deviation is interpreted as an indication of unacceptable variation in TLD response. In 2010, the following TLD results were excluded from the data set because their standard deviations were greater than 1.4:

First Quarter None Second Quarter 214B Third Quarter 104B Fourth Quarter None If one badge at a station exhibited a standard deviation greater than 1.4, then the reading of the companion badge at each location would be used to determine the quarterly exposure. The badges exceeding the self-imposed limit would be visually inspected under a microscope and the glow curve and test results for the anneal data and the element correction factors would be reviewed.

4-17

4.4 Milk Milk samples are obtained biweekly from Station 304 (the state prison dairy) which is a control station located more than 10 miles from the plant. Gamma isotopic and I-131 analyses are performed on each sample as specified in Tables 2-1 and 2-2. Since 1989, efforts to locate a reliable milk sample source within 5 miles of the plant have been unsuccessful.

During 2010, no man-made radionuclides were detected from the gamma isotopic analysis of the milk samples. Cesium-137 was found in most of the samples each year from 1978 (when this analysis became a requirement) through 1989. No other man-made radionuclides have been detected by this analysis.

The MDC and RL for Cs-137 in milk are 18 and 70 pCi/l, respectively. The historical trending of the average annual detectable Cs-137 concentration in milk is provided in Figure 4.4-1 and Table 4.4-1.

Figure 4.4-1 Average Annual Cs-137 Concentration in Milk 25 20 Concentration (pCi/l) 15 10 5

0 Po 75 77 79 81 83 85 87 89 91 93 95 97 99 01 03 05 07 09 Year Indicator Control MDC 4-18

Table 4.4-1 Average Annual Cs-137 Concentration in Milk Year Indicator Control (pCi/l) (pCi/l)

Pre-op 19.9 19.4 1974 NDM NDM 1975 NDM NDM 1976 NDM NDM 1977 NDM NDM 1978 12.1 18.3 1979 16.1 13 1980 14.7 15.4 1981 12.57 10.2 1982 11.8 11 1983 12 7.2 1984 9.6 10.2 1985 9.14 5.35 1986 9.8 10 1987 NDM NDM 1988 10.9 NDM 1989 8.6 7.9 1990 NDM NDM 1991 NDM NDM 1992 NDM NDM 1993 NDM NDM 1994 NDM NDM 1995 NDM NDM 1996 NDM NDM 1997 NDM NDM 1998 NDM NDM 1999 NDM NDM 2000 NDM NDM 2001 NDM NDM 2002 NDM NDM 2003 NDM NDM 2004 NDM NDM 2005 NDM NDM 2006 NDM NDM 2007 NDM NDM 2008 NDM NDM 2009 NDM NDM 2010 NDM NDM 4-19

During 2010, I-131 was not detected in any of the milk samples. During preoperation, all readings were less than 2 pCi/l which was the allowed MDC at that time. Figure 4.4-2 and Table 4.4-2 provide the historical trending of the average annual detectable concentration of I-131 in milk. In 1988, a single reading of 0.32 pCi/l, which was believed to have resulted from a procedural deficiency, was reported. The MDC and RL for I-131 in milk are 1 and 3 pCi/l, respectively.

All the detectable results for Cs-137 and I-131 are attributed to fallout from the nuclear weapons tests and the Chernobyl incident.

Figure 4.4-2 Average Annual I-131 Concentration in Milk 16 14 12 Concentration (pCi/l) 10 8

6 4

2 0

Po 75 77 79 81 83 85 87 89 91 93 95 97 99 01 03 05 07 09 Year Indicator Control MDC RL 4-20

Table 4.4-2 Average Annual I-131 Concentration in Milk Year Indicator Control (pCi/l) (pCi/l)

Pre-op NDM NDM 1974 0.98 2.6 1975 0.3 NDM 1976 12.23 9.1 1977 14.61 4.08 1978 2.72 4.18 1979 NDM NDM 1980 1.26 0.69 1981 NDM NDM 1982 NDM NDM 1983 NDM NDM 1984 NDM NDM 1985 NDM NDM 1986 8.9 7.6 1987 NDM NDM 1988 NDM 0.32 1989 NDM NDM 1990 NDM NDM 1991 NDM NDM 1992 NDM NDM 1993 NDM NDM 1994 NDM NDM 1995 NDM NDM 1996 NDM NDM 1997 NDM NDM 1998 NDM NDM 1999 NDM NDM 2000 NDM NDM 2001 NDM NDM 2002 NDM NDM 2003 NDM NDM 2004 NDM NDM 2005 NDM NDM 2006 NDM NDM 2007 NDM NDM 2008 NDM NDM 2009 NDM NDM 2010 NDM NDM 4-21

4.5 Vegetation In accordance with Tables 2-1 and 2-2, grass samples are collected monthly from two indicator stations near the site boundary (Nos. 106 and 112) and at one control station located about 21 miles from the plant (No. 416). Gamma isotopic analyses are performed on each sample. Gamma isotopic analysis on vegetation samples began in 1978 when the analysis became a TS requirement.

The results presented in Table 3-1 show that Cs-137 was the only man-made radionuclide detected in vegetation samples during 2010. Cs-137 was detected in 8 samples of the 24 samples collected at the indicator stations at an average value of 31.4 pCi/kg-wet. No samples collected at the control station had detectable Cs-137. The Cs-137 seen at the indicator stations could potentially be attributed to plant effluents.

Since 1986, Cs-137 has been the only man-made radionuclide found in vegetation samples. The MDC and RL for Cs-137 in vegetation samples are 80 pCi/kg-wet and 2000 pCi/kg-wet, respectively. The occasional presence of Cs-137 in vegetation samples is attributed primarily to fallout from nuclear weapons tests and the Chernobyl incident.

Figure 4.5-1 and Table 4.5-1 provide the historical trending of the average annual detectable Cs-137 concentration found in vegetation. Since 1978, the Cs-137 concentration has been on a decline, and since about 1989, generally occurring below the required MDC.

4-22

Figure 4.5-1 Average Annual Cs-137 Concentration in Vegetation 1200 1000 Concentration (pCi/kg-wet) 800 600 400 200 0

Po 75 77 79 81 83 85 87 89 91 93 95 97 99 01 03 05 07 09 Year Indicator Control MDC 4-23

Table 4.5-1 Average Annual Cs-137 Concentration in Vegetation Year Indicator Control (pCi/kg-wet) (pCi/kg-wet)

Pre-op 55 30 1974 NDM NDM 1975 NDM NDM 1976 NDM NDM 1977 NDM NDM 1978 112 1089 1979 59 695 1980 208 916 1981 182 152 1982 65 99 1983 95 211 1984 149 388 1985 60.9 113.3 1986 80 215 1987 60 428 1988 40.1 228.8 1989 37 NDM 1990 66.7 34.5 1991 34.1 36.1 1992 35.2 41.3 1993 24.7 45.8 1994 32.2 46.6 1995 49.8 47.6 1996 47.2 41.1 1997 48.4 54.9 1998 81.4 44.1 1999 26.9 NDM 2000 NDM NDM 2001 NDM NDM 2002 33.7 41.1 2003 61.0 62.8 2004 41.6 43.5 2005 47.7 39.8 2006 66.8 29.6 2007 55.7 31.1 2008 41.8 38.1 2009 46.8 NDM 2010 31.4 NDM 4-24

4.6 River Water Surface water from the Altamaha River is obtained at an upstream location (Station 170) and at a downstream location (Station 172) using automatic samplers. Small quantities are drawn at intervals not exceeding a few hours. The samples drawn are collected monthly and quarterly composites are produced from the monthly collections.

As specified in Table 2-1, a gamma isotopic analysis is conducted on each monthly sample. No man-made gamma emitters were detected during 2010. The only man-made gamma emitters previously detected are presented in the table below.

Year Quarter Station Radionuclide Level (pCi/l) 1975 4th 172 Ce-141 78.2 1986 2nd 170 La-140 18.0 1986 2nd 172 Cs-137 12.0 1988 2nd 170 Cs-137 6.8 A tritium analysis is performed on the quarterly composite. Prior to 1986, positive results were usually found in each quarterly composite at levels generally ranging from 200 and 350 pCi/l which is approximately background environmental levels.

Subsequently, the number of positive results have diminished.

In 2010, tritium was detected in two of the four quarterly samples at the upstream (control) location for an average of 426 pCi/l, and in three of the four quarterly samples at the downstream (indicator) location for an average of 403 pCi/l. The difference between the average value at the control and indicator stations is not statistically discernible since it is less than the MDD of 765 pCi/l. The low levels detected at both the indicator and control stations are essentially environmental background levels (typically 350 pCi/L +/- 250 pCi/L). The MDC and RL for tritium in river water are 3000 and 30,000 pCi/l, respectively. Figure 4.6-1 and Table 4.6-1 provide the historical trending of the annual average detectable tritium concentration in river water.

The annual 50 mile downstream survey of the Altamaha River to determine if river water is being withdrawn for drinking purposes is discussed in Section 4.1.

4-25

Figure 4.6-1 Average Annual H-3 Concentration in River Water 3500 3000 Concentration (pCi/l) 2500 2000 1500 1000 500 0

Po 75 77 79 81 83 85 87 89 91 93 95 97 99 01 03 05 07 09 Year Indicator Control MDC 4-26

Table 4.6-1 Average Annual H-3 Concentration in River Water Year Indicator Control (pCi/l) (pCi/l)

Pre-op 210 191 1974 230 205 1975 205 238 1976 165 153 1977 189 170 1978 224 193 1979 210 180 1980 358 218 1981 220 135 1982 165 220 1983 265 328 1984 437 327 1985 288 220 1986 242 206 1987 241 204 1988 220 NDM 1989 NDM NDM 1990 139 NDM 1991 NDM NDM 1992 NDM NDM 1993 NDM NDM 1994 NDM NDM 1995 200 NDM 1996 144 147 1997 NDM NDM 1998 NDM NDM 1999 NDM NDM 2000 209 NDM 2001 NDM NDM 2002 NDM NDM 2003 NDM 261 2004 206 302 2005 245 NDM 2006 299 NDM 2007 235 338 2008 329 298 2009 242 343 2010 403 426 4-27

4.7 Fish Gamma isotopic analyses were performed on the edible portion of the fish samples collected at the river stations on April 12, 2010 and November 22, 2010. The control station (No. 170) is located upstream of the plant while the indicator station (No. 172) is located downstream.

As shown in Table 3-1, Cs-137 was the only man-made radionuclide detected in fish during 2010. Both of the samples taken at the indicator station and both of the samples taken at the control station were positive for Cs-137. The average concentration at the indicator station was 11.6 pCi/kg-wet, and the average at the control station was 8.6 pCi/kg-wet. The difference between the averages at the indicator and control stations (3.0 pCi/kg-wet) is not statistically discernible since it is less than the MDD of 12 pCi/kg-wet. Cs-137 in fish samples is attributed primarily to weapons testing and the Chernobyl incident. However, the Cs-137 seen in the fish samples at the indicator station could be attributed to plant effluents. The MDC and RL for Cs-137 in fish are 150 and 2000 pCi/kg-wet, respectively.

The historical trending of the average annual detectable Cs-137 concentration in fish is provided in Figure 4.7-1 and Table 4.7-1. Figure 4.7-1 indicates, in general, a decline in the Cs-137 levels after l983. (Note: From 1979 through 1982, clams were collected rather than fish.)

Figure 4.7-1 Average Annual Cs-137 Concentration in Fish 160 140 Concentration (pCi/kg-wet) 120 100 80 60 40 20 0

Po 75 77 79 81 83 85 87 89 91 93 95 97 99 01 03 05 07 09 Year Indicator Control MDC 4-28

Table 4.7-1 Average Annual Cs-137 Concentration in Fish Year Indicator Control (pCi/kg-wet) (pCi/kg-wet)

Pre-op 90 115 1974 134 61 1975 80.6 89.4 1976 73 88 1977 76 91 1978 88 47 1979 NDM NDM 1980 NDM NDM 1981 NDM NDM 1982 NDM NDM 1983 138.6 67.5 1984 84 53 1985 117 63.3 1986 79 44 1987 62 52 1988 77.8 33.3 1989 34.3 28.9 1990 26.7 24.2 1991 32.9 26.9 1992 41.6 28.8 1993 38.0 25.9 1994 23.8 20.7 1995 25.0 27.9 1996 20.4 18.0 1997 29.4 15.1 1998 26.1 17.7 1999 22.3 13.5 2000 17.9 25.3 2001 20.8 10.2 2002 18.2 13.0 2003 13.1 7.1 2004 11.6 18.8 2005 13.0 13.3 2006 10.4 13.5 2007 6.8 9.8 2008 19.9 8.4 2009 12.4 8.4 2010 11.6 8.6 4-29

In the past, the only other man-made radionuclides detected in fish samples were Co-60 and Cs-134. During preoperation, Co-60 was detected in one fish sample at a very low concentration. During the period of 1983 through 1988, Cs-134 was found in about half of the samples at concentrations of the same order of magnitude as those found for Cs-137.

The Co-60 and Cs-134 levels found in these samples are attributed to the nuclear weapons tests and the Chernobyl incident. Figure 4.7-2 and Table 4.7-2 show the historical trending of the annual average detectable concentration of Cs-134 in fish.

Figure 4.7-2 Average Annual Cs-134 Concentration in Fish 160 140 Concentration (pCi/kg-wet) 120 100 80 60 40 20 0

Po 75 77 79 81 83 85 87 89 91 93 95 97 99 01 03 05 07 09 Year Indicator Control MDC 4-30

Table 4.7-2 Average Annual Cs-134 Concentration in Fish Year Indicator Control (pCi/kg-wet) (pCi/kg-wet)

Pre-op NDM NDM 1974 NDM NDM 1975 NDM NDM 1976 NDM NDM 1977 NDM NDM 1978 NDM NDM 1979 NDM NDM 1980 NDM NDM 1981 NDM NDM 1982 NDM NDM 1983 101.8 NDM 1984 35.8 26.3 1985 46.7 21.1 1986 29 NDM 1987 69 15 1988 21.7 6.9 1989 NDM NDM 1990 NDM NDM 1991 NDM NDM 1992 NDM NDM 1993 NDM NDM 1994 NDM NDM 1995 NDM NDM 1996 NDM NDM 1997 NDM NDM 1998 NDM NDM 1999 NDM NDM 2000 NDM NDM 2001 NDM NDM 2002 NDM NDM 2003 NDM NDM 2004 NDM NDM 2005 NDM NDM 2006 NDM NDM 2007 NDM NDM 2008 NDM NDM 2009 NDM NDM 2010 NDM NDM 4-31

4.8 Sediment Sediment was collected along the shoreline of the Altamaha River on May 3 and November 1, 2010, at the upstream control station (No. 170) and the downstream indicator station (No. 172). A gamma isotopic analysis was performed on each sample.

Co-60 was not found in sediment samples in 2010. With the exception of a few years, Co-60 has been found at either the indicator or the control station every year since 1986. There is no RL or MDC assigned to Co-60 in sediment in ODCM Tables 4-2 and 4-3 (Tables 4-2 and 4-1 of this report). The MDC assigned by the EL for Co-60 in sediment is 70 pCi/kg-dry. The historical trending of the average annual detectable Co-60 concentration in sediment is provided in Figure 4.8-1 and Table 4.8-1.

Figure 4.8-1 Average Annual Co-60 Concentration in Sediment 250 200 Concentration (pCi/kg-dry) 150 100 50 0

Po 75 77 79 81 83 85 87 89 91 93 95 97 99 01 03 05 07 09 Year Indicator Control MDC 4-32

Table 4.8-1 Average Annual Co-60 Concentration in Sediment Year Indicator Control (pCi/kg-dry) (pCi/kg-dry)

Pre-op NDM NDM 1974 NDM NDM 1975 NDM NDM 1976 NDM NDM 1977 NDM NDM 1978 NDM NDM 1979 NDM NDM 1980 NDM NDM 1981 NDM NDM 1982 NDM NDM 1983 NDM NDM 1984 NDM NDM 1985 NDM NDM 1986 108 33 1987 NDM NDM 1988 67.8 NDM 1989 NDM 31 1990 33 19 1991 123.6 NDM 1992 81.4 NDM 1993 70.7 NDM 1994 218 NDM 1995 NDM NDM 1996 118.5 NDM 1997 NDM NDM 1998 79.4 NDM 1999 107.7 NDM 2000 70.0 NDM 2001 58.1 NDM 2002 NDM NDM 2003 NDM 31.5 2004 NDM NDM 2005 NDM NDM 2006 NDM NDM 2007 NDM NDM 2008 NDM NDM 2009 NDM NDM 2010 NDM NDM 4-33

Co-60 was not detected in sediment samples near the plant until 1986, the year of the Chernobyl incident. However, because Co-60 was detected in indicator station samples more often than in control station samples during the years 1986 through 2002, some contribution from plant effluents cannot be ruled out. Co-60 has not been detected in either control or indicator station samples since 2004.

In 2010, Cs-137 was detected in both indicator and control station sediment samples. It has been found in over 95% of all of the sediment samples collected back through preoperation, and is generally attributed to the atmospheric nuclear weapons tests or to the Chernobyl incident. As shown in Table 3-1, the average at the indicator station was 47.1 pCi/kg-dry and the average at the control station was 39.6 pCi/kg-dry. The difference between the indicator and control stations (7.5 pCi/kg-dry) is not statistically discernible since it is less than the MDD of 181 pCi/kg-dry. The MDC for Cs-137 in sediment is 180 pCi/kg-dry. The historical trending of the average annual detectable Cs-137 concentration in sediment is provided in Figure 4.8-2 and Table 4.8-2.

Figure 4.8-2 Average Annual Cs-137 Concentration in Sediment 1000 900 800 Concentration (pCi/kg-dry) 700 600 500 400 300 200 100 0

Po 75 77 79 81 83 85 87 89 91 93 95 97 99 01 03 05 07 09 Year Indicator Control MDC 4-34

Table 4.8-2 Average Annual Cs-137 Concentration in Sediment Year Indicator Control (pCi/kg-dry) (pCi/kg-dry)

Pre-op 170 270 1974 218 57 1975 330 615 1976 211 300 1977 364 200 1978 330 260 1979 NDM 310 1980 240 NDM 1981 590 110 1982 141 285 1983 384 365 1984 500 260 1985 76.5 269 1986 238 190 1987 59 39 1988 903 114 1989 56 62 1990 130.5 66 1991 43.1 54.5 1992 151 198.5 1993 113 115 1994 127 104 1995 52.3 80.6 1996 106 110 1997 186 137 1998 148.5 101.4 1999 92 111.8 2000 68.1 114.5 2001 68.7 69.6 2002 68.1 62.8 2003 57.3 106 2004 59.5 57.1 2005 57.2 30.3 2006 85.2 79.2 2007 82.1 71.6 2008 112.7 61.9 2009 74.9 60.5 2010 47.1 39.6 4-35

Other man-made nuclides, besides Co-60 and Cs-137, were occasionally found in past years. Their presence was generally attributed to the nuclear weapons tests or to the Chernobyl incident, although plant releases were not ruled out. Mn-54, Co-58, and Zn-65, which have relatively short half-lives, are most likely a result of plant releases and have been plotted in Figure 4.8-3 along with their MDCs. All the man-made nuclides detected in sediment except for Co-60 and Cs-137 have been listed in Table 4.8-3. The Cs-134 MDC (150 pCi/kg-dry) is defined in ODCM Table 4-3 (Table 4-1 of this report). The MDCs for Mn-54 (42 pCi/kg-dry) and Zn-65 (129 pCi/kg-dry) were determined by the EL since no values are provided in ODCM Table 4-3.

Figure 4.8-3 Average Annual Indicator Station Concentrations of Select Nuclides in Sediment 600 500 Concentration (pCi/kg-dry) 400 300 200 100 0

Po 75 77 79 81 83 85 87 89 91 93 95 97 99 01 03 05 07 09 Year Mn-54 Zn-65 Cs-134 Mn-MDC Zn-MDC Cs-MDC 4-36

Table 4.8-3 Sediment Nuclide Concentrations Other Than Co-60 & Cs-137 Nuclide YEAR Indicator Control (pCi/kg-dry) (pCi/kg-dry)

Ce-141 1976 340 254 1977 141 Ce-144 Preop 720 1974 363 1975 342 389 1978 700 1981 1290 Co-58 1994 22.2 Cs-134 Preop 40 1981 280 1984 130 40 1986 132 1988 505 1990 31 Mn-54 1975 36.1 1986 28 26 1991 57.2 1996 77.7 Ru-103 1974 81 1976 158 1977 195 1981 220 Zn-65 1986 175 1988 136 1991 250.5 1992 83 1993 39.9 1994 332 Zr-95 Preop 180 1974 138 1976 427 170 1977 349 294 1978 220 230 1981 860 280 4-37

4.9 Groundwater As nuclear plants began to undergo decommissioning in the late 1990s to early 2000s, instances of subsurface and/or groundwater contamination were identified.

In addition, several operating facilities also identified groundwater contamination resulting from spills and leaks or equipment failure. In one instance, low levels of licensed material were detected in a private well located on property adjacent to a nuclear power plant.

In 2006, NEI (Nuclear Energy Institute) formed a task force to address monitoring onsite groundwater for radionuclides at nuclear facilities. A Groundwater Protection Initiative was developed which was adopted by all U.S. commercial operating nuclear plants.

The NRC also formed a task force to study the groundwater issues and released Information Notice 2006-13, Ground-water Contamination due to Undetected Leakage of Radioactive Water, which summarized its review of radioactive contamination of ground water at multiple facilities as a result of undetected leakage from structures, systems, and components that contain or transport radioactive fluids. Licensees were instructed to review the information for applicability and to consider appropriate actions to avoid similar problems.

The NEI task force felt it was prudent for the industry to update site hydrology information and to develop radiological groundwater monitoring plans at each site.

These groundwater protection plans would ensure that underground leaks and spills would be addressed promptly. Additionally, the task force recommended developing a communications protocol to report radioactive leaks or spills that entered groundwater (or might eventually enter groundwater) to the NRC and State and Local government officials as needed. NEI-07-07, Industry Groundwater Protection Final Guidance Document, was developed by the task force to document the guidelines recommended for the industry.

To ensure compliance with NEI-07-07, Southern Nuclear developed the Nuclear Management Procedure, Radiological Groundwater Protection Program. The procedure contains detailed site-specific monitoring plans, program technical bases, and communications protocol (to ensure that radioactive leaks and spills are addressed and communicated appropriately). The guidance in this procedure is used to informally update both the NRC and the State of Georgia regarding the changes in Hatchs groundwater tritium concentrations. In an effort to prevent future leaks of radioactive material to groundwater, SNC plants have established detailed buried piping and tanks inspection programs.

Plant Hatch has monitored onsite groundwater since preoperation. Initially piezometers, which were installed prior to plant construction, were used to monitor groundwater. In the late 1970s to the early 1980s timeframe, a hydrological engineering consultant was hired to evaluate several areas where leaks had occurred and tritium had been detected in onsite wells. The consultant recommended drilling additional monitoring wells to study the groundwater movement, to determine the source of the leaks, and to track the tritium concentrations in groundwater.

In the late 1970s through the mid 1980s, Hatch reported groundwater results to the NRC. The reporting frequency was decreased for several reasons - the areas where the groundwater showed tritium were all onsite and the movement of 4-38

groundwater was extremely slow and in a direction (towards the river) that was not expected to impact the public. Although the reports are no longer made on a routine basis, Plant Hatch has continued to monitor onsite groundwater wells for tritium on a scheduled frequency.

In 2006 as the nuclear industry was moving towards establishing groundwater monitoring programs, Plant Hatch hired a hydrological engineering consultant to re-evaluate the groundwater study which had been done previously. The key purpose of the new study was to evaluate the adequacy of the current monitoring program and to diagram the existing groundwater tritium plume to ensure that the plume had not migrated offsite. The consultant concluded that tritium was not leaving the site through the groundwater. The consultant recommended installing additional monitoring wells to better characterize the groundwater plume in areas of the site where there were no existing wells.

During the course of Plant Hatchs groundwater evaluation in 2006, some leaks were discovered which explained why the levels of tritium around CST-1 (Unit 1 Condensate Storage Tank) were not decreasing. Underground piping which carried radioactive liquids was evaluated over the plant site and replaced in some areas around CST-1. Both CST tank/pump moats (Unit 1 and Unit 2) were coated and sealed to ensure that moats would not leak in the event of transfer pump or tank leaks.

In 2006, Plant Hatchs groundwater monitoring program included over 50 location points which were sampled on weekly, monthly, quarterly, or annual frequencies.

Included in these sample points were the onsite drinking water wells (which did not contain detectable amounts of radioactivity above background). Surface drains or outfalls were also included as sample points. Tritium was detected in two of the outfalls which discharged to the river. These outfalls were initially added to the Hatch ODCM as radiological effluent release points. Permitted release point Y22N008A (by design) discharges groundwater from the site subsurface drainage system which includes the tritiated groundwater around the CST-1. The other release point, Y22N003A, discharges runoff from the roof drains. The source of tritium in this outfall has been determined to be from rain washout of the gaseous plant effluents and is no longer a permitted release point. Plant Hatch sampled rainfall during two rain events in 2006 and found tritium levels as high as 4.58E5 pCi/l on the reactor building roof. Two other outfalls, Y22N024A and Y22N025A, which discharge into the onsite swamp show sporadic levels of tritium. The source of tritium in these outfalls is also believed to be from rain washout.

In 2007, Hatch continued to aggressively monitor the groundwater tritium plume especially in two areas of higher activity around CST-1 and CST-2. The amount of seasonal rainfall during 2007 seems to have had some correlation with the tritium concentrations in the T-12 well near CST-1. During early spring and late fall rainy seasons, the concentrations of tritium were at their highest levels, whereas, during the summer and early fall drought season the tritium concentrations decreased significantly. This is indicative of water table level fluctuations.

However, this same seasonal affect was not observed in the newer NW10 monitoring well installed in 2006 near CST-2. The tritium concentration in NW10 increased from February 2007 through September 2007 by a factor of 2.5. Events which could have contributed to the increase were a CST-2 transfer pump leak (in November 2006) which led to an accumulation of a couple feet of CST-2 water in the pump moat. Although the moat had been sealed earlier in 2006, there was a possibility that some of the contaminated water seeped through the concrete moat 4-39

and gradually seeped through the ground to NW10. In addition, there was a deep hole dug (in January 2007) near the CST-2 (and NW10) to replace some CST-2 piping. The hole may have altered groundwater flow toward NW10 from the CST-1 groundwater plume and resulted in higher concentrations of tritium being drawn to NW10.

In 2008, Hatch made further enhancements to the groundwater tritium monitoring program. Three additional shallow wells and three additional deep wells were installed (R series wells). One of the deep wells was a replacement well for the deep well N7A. The integrity of N7A was questioned due to the high level of tritium (~211,000 pCi/l) seen in this well which should have been protected from contamination by a confining layer. The well was retired and a new well (R-3) was placed in the same vicinity. The newer well showed much smaller amounts of tritium activity (average of 1257 pCi/l in 2010).

In addition, several other groups within Southern Company are now utilized to conduct an improved sampling program and to provide additional expertise in characterizing groundwater quality and flow. The sampling frequency for radiological groundwater monitoring was officially changed to quarterly starting in second quarter of 2008 with SCS Civil Field Services performing the sampling and Georgia Power Environmental Laboratory continuing to analyze the samples.

Over the past couple of years, SNC Corporate Engineering and Hatch Site Engineering have developed a Buried Piping and Tanks Inspection Program. This program should help to prevent releases of radioactive material to groundwater.

Underground piping and components are risked ranked using detailed procedures and EPRIs software, BPWorks, to ensure vulnerable areas are identified and repaired or replaced before problems occur.

In May of 2009, there was an increase in tritium concentration in well T-3 (located near the U-1 Turbine Building) from approximately 2600 pCi/l to approximately 37,000 pCi/l. Neighboring well N9B (not part of the formal GW sampling program) also showed an approximate 10X increase - going from 1300 pCi/l to over 10K pCi/l. Investigation found no process leaks and the non-rad constituents continued to match groundwater. The increase was attributed to migration of the plume. Increased rainfall and the fact that the wells are located near the subsurface drain could likely have facilitated the pathway of the plume towards the T3 well.

A courtesy notification was made to the State of Georgia Dept. of Natural Resources, and a 10CFR50.72 formal report was made to the NRC - although only courtesy notifications were required per procedure. The tritium concentration in T3 continues to decrease (average of 4990 pCi/l in 2010).

No tritium activity above background has been detected in the Deep Wells 2 and 3 which are used for drinking water at the plant. The plant staff continues to sample and monitor strategically located wells on a more frequent basis than quarterly to ensure that radiological leaks have not occurred. In addition, outfalls, pull boxes, manholes, and the sewage treatment plant effluent are sampled by the plant staff on a periodic basis.

The latest groundwater tritium plume map (generated from the 2010 SCS sampling data) is shown on the following page. It is a representation of the current groundwater conditions at Plant Hatch. The two wells of interest around the CSTs continued to show an overall decreasing trend. T-12, near CST-1, averaged approximately 275,750 pCi/l of tritium (down from an average of 295,000 pCi/l in 2009). In 2010, the range in values in T-12 was 203,000 pCi/l to 321,000 pCi/l.

NW10, near CST-2, averaged 41,850 pCi/l of tritium (down from an average of 4-40

75,400 pCi/l in 2009). The range at NW-10 was 23,700 pCi/l to 58,500 pCi/l of tritium. The subsurface drain system and rainfall continue to influence groundwater movement around the site and contribute to the wide range of tritium values seen in the groundwater monitoring wells.

Administrative Control Limits (ACL) were established near the end of 2010 for the surficial and deep aquifers and for specific wells based on the presence of legacy tritium, the previous well results, and total measurement uncertainty. There are no reporting requirements associated with exceeding an ACL but additional actions would be taken to verify no new sources of tritium if an ACL was exceeded. The ACL for T-12 is 900,000 pCi/l, and for NW-10 the ACL is 160,000 pCi/l. As noted above, the tritium levels seen in these wells was significantly less than the ACLs for the wells.

4-41

5.0 INTERLABORATORY COMPARISON PROGRAM In accordance with ODCM 4.1.3, the EL participates in an ICP that satisfies the requirements of Regulatory Guide 4.15, Revision 1, "Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment", February 1979. The guide indicates the ICP is to be conducted with the Environmental Protection Agency (EPA) Environmental Radioactivity Laboratory Intercomparison Studies (Cross-check) Program or an equivalent program, and the ICP should include all of the determinations (sample medium/radionuclide combinations) that are offered by the EPA and included in the REMP.

The ICP is conducted by Analytics, Inc. of Atlanta, Georgia. Analytics has a documented Quality Assurance (QA) program and the capability to prepare Quality Control (QC) materials traceable to the National Institute of Standards and Technology. The ICP is a third party blind testing program which provides a means to ensure independent checks are performed on the accuracy and precision of the measurements of radioactive materials in environmental sample matrices.

Analytics supplies the crosscheck samples to the EL which performs the laboratory analyses in a normal manner. Each of the specified analyses is performed three times. The results are then sent to Analytics who performs an evaluation which may be helpful to the EL in the identification of instrument or procedural problems.

The samples offered by Analytics and included in the EL analyses are gross beta and gamma isotopic analyses of an air filter; gamma isotopic analyses of milk samples; and gross beta, tritium and gamma isotopic analyses of water samples.

The accuracy of each result is measured by the normalized deviation, which is the ratio of the reported average less the known value to the total error. The total error is the square root of the sum of the squares of the uncertainties of the known value and of the reported average. The uncertainty of the known value includes all analytical uncertainties as reported by Analytics. The uncertainty of the reported average is the propagated error of the values in the reported average by the EL. The precision of each result is measured by the coefficient of variation, which is defined as the standard deviation of the reported result divided by the reported average. An investigation is undertaken whenever the absolute value of the normalized deviation is greater than three or whenever the coefficient of variation is greater than 15% for all radionuclides other than Cr-51 and Fe-59.

For Cr-51 and Fe-59, an investigation is undertaken when the coefficient of variation exceeds the values shown as follows:

Nuclide Concentration

• Total Sample Activity Percent Coefficient (pCi) of Variation Cr-51 <300 NA 25 Cr-51 NA >1000 25 Cr-51 >300 <1000 15 Fe-59 <80 NA 25 Fe-59 >80 NA 15

• For air filters, concentration units are pCi/filter. For all other media, concentration units are pCi/liter (pCi/l).

5-1

As required by ODCM 4.1.3.3 and 7.1.2.3, a summary of the results of the EL's participation in the ICP is provided in Table 5-1 for: the gross beta and gamma isotopic analyses of an air filter; gamma isotopic analyses of milk samples; and gross beta, tritium and gamma isotopic analyses of water samples. Delineated in this table for each of the media/analysis combinations, are: the specific radionuclides; Analytics preparation dates; the known values with their uncertainties supplied by Analytics; the reported averages with their standard deviations; and the resultant normalized deviations and coefficients of variation expressed as a percentage.

In 2010, the laboratory analyzed 9 samples for 35 parameters. The analyses included tritium, gross beta and gamma emitting radio-nuclides in different matrices. The attached results indicate two analyses outside the acceptance limits for accuracy. The activity recovery of Cr-51 and Fe-59 in air filters was above the upper acceptance limit for accuracy.

The analysis of Cr-51 and Fe-59 is performed by gamma spectroscopy, with the value determined by a weighted average of four germanium detectors. In a 2005 investigation a positive bias was determined to exist in the analysis based on summing of nuclides in the calibration standard. The detectors are calibrated on a three year geometry rotation. The air filter geometry calibration was scheduled and completed in 2010. The sample analysis results indicate further investigations should be performed into the biases associated with this matrix in 2011.

5-2

TABLE 5-1 (SHEET 1 of 3)

INTERLABORATORY COMPARISON PROGRAM RESULTS GROSS BETA ANALYSIS OF AN AIR FILTER (pCi/filter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Gross Beta 09/16/10 75.40 85.80 1.91 0.48 5.86 -2.36 GAMMA ISOTOPIC ANALYSIS OF AN AIR FILTER (pCi/filter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Ce-141 09/16/10 142.70 142.00 5.99 0.79 9.77 0.05 Co-58 09/16/10 91.40 80.30 4.3 0.45 7.89 1.54 Co-60 09/16/10 196.90 186.00 3.52 1.04 3.47 1.59 Cr-51 09/16/10 345.10 255.00 47.02 1.42 24.68 1.06 Cs-134 09/16/10 90.90 101.00 2.01 0.56 5.04 -2.19 Cs-137 09/16/10 115.10 103.00 4.28 0.57 4.79 2.19 5-3 Fe-59 09/16/10 128.70 99.40 27.63 0.55 20.97 1.08 Mn-54 09/16/10 150.90 130.00 2.21 0.73 5.10 2.72 Zn-65 09/16/10 263.40 222.00 16.73 1.24 7.13 2.20 GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (pCi/liter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Ce-141 06/17/10 108.60 110.00 3.43 0.61 7.06 -0.18 Co-58 06/17/10 101.10 101.00 7.89 0.56 9.22 0.01 Co-60 06/17/10 198.60 197.00 5.92 1.09 14.97 0.05 Cr-51 06/17/10 351.40 339.00 32.24 1.89 14.01 0.25 Cs-134 06/17/10 119.60 126.00 5.23 0.70 6.32 -0.85 Cs-137 06/17/10 159.80 150.00 5.87 0.84 20.46 0.30

TABLE 5-1 (SHEET 2 of 3)

INTERLABORATORY COMPARISON PROGRAM RESULTS GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (pCi/liter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Fe-59 06/17/10 141.00 119.00 1.16 0.66 8.17 1.91 I-131 06/17/10 105.80 96.90 1.29 0.54 6.58 1.28 Mn-54 06/17/10 180.20 169.00 5.45 0.94 5.09 1.22 Zn-65 06/17/10 223.40 206.00 4.52 1.15 7.65 1.02 GROSS BETA ANALYSIS OF WATER SAMPLE (pCi/liter) 5-4 Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Gross Beta 03/18/10 270.90 293.00 15.73 1.63 7.72 -1.06 06/17/10 264.00 266.00 8.8 1.48 6.42 -0.12 GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (pCi/liter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Ce-141 03/18/10 273.20 263.00 1.31 1.47 4.16 0.89 Co-58 03/18/10 146.80 144.00 5.93 0.48 6.07 0.32 Co-60 03/18/10 185.80 185.00 7.46 1.03 5.20 0.09 Cr-51 03/18/10 389.00 364.00 45.91 2.03 13.51 0.48 Cs-134 03/18/10 167.80 179.00 4.46 1.00 4.66 -1.43

TABLE 5-1 (SHEET 3 of 3)

INTERLABORATORY COMPARISON PROGRAM RESULTS GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (pCi/liter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Cs-137 03/18/10 166.40 159.00 10.97 0.89 7.23 0.62 Fe-59 03/18/10 154.80 138.00 18.72 0.77 11.00 0.99 I-131 03/18/10 71.70 72.70 1.4 0.40 8.44 -0.09 Mn-54 03/18/10 219.80 209.00 16.06 1.16 8.88 0.55 Zn-65 03/18/10 281.60 256.00 4.16 3 8.06 1.13 TRITIUM ANALYSIS OF WATER SAMPLES (pCi/liter) 5-5 Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation H-3 03/18/10 10480.70 12000.00 980.83 67 9.67 -1.50 06/17/10 9595.20 9630.00 177.19 53.67 2.97 -0.12 I-131 ANALYSIS OF AN AIR CARTRIDGE (pCi/cartridge)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation I-131 06/17/10 75.50 79.80 1.36 3.10 4.10 -1.39

6.0 CONCLUSION

S This report confirms the licensee's conformance with the requirements of Chapter 4 of the ODCM. It provides a summary and discussion of the results of the laboratory analyses for each type of sample.

In 2010, there was one instance where the indicator station results were statistically discernible from the control station results. This is discussed below.

No discernible radiological impact upon the environment or the public as a consequence of plant discharges to the atmosphere and to the river was established for any other REMP samples.

Cesium-137 was identified in 8 of 24 samples vegetation samples at the indicator stations and in none of the samples at the control station. The average of the positive samples at the indicator stations was 31.4 pCi/kg-wet. The potential dose to a member of the public due (an adult) who would receive the highest dose due to regular consumption of vegetation containing the above level of Cs-137 would be 0.87 mrem in a year. This dose is less than 6% of the regulatory limit of 15 mrem per year to any organ due to gaseous effluents.

Low levels of Cs-137 in the environment are attributed primarily to fallout from nuclear weapons testing and from the Chernobyl incident. However, the levels of Cs-137 seen at the indicator stations for vegetation and for fish could potentially be attributed to plant effluents.

The radiological levels reported in 2010 were low and are generally trending downward. The REMP trends over the course of time from preoperation to the present are decreasing or have remained fairly constant. This supports the conclusion that there is no adverse radiological impact on the environment or to the public as a result of the operation of Hatch Nuclear Plant.

6-1