Text

Submittal of Annual Radiological Environmental Operating Reports for 2014
	ML15175A475
Person / Time
Site:	Hatch, Vogtle, Farley
Issue date:	05/15/2015
From:	Pierce C; Southern Co, Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-15-0877
	Download: ML15175A475 (135)
	v • d • e

Charles R. Pierce Sout hern Nuclear Regulatory Affairs Director Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 SOUTHERN~

Birmingham, AL 35242 Tel 205.992 7872 Fax 205.992 7601 COMPANY MAY 1 5 2015 Docket Nos.: 50-321 50-348 50-424 NL-15-0877 50-366 50-364 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant- Units 1 & 2 Joseph M. Farley Nuclear Plant- Units 1 & 2 Vogtle Electric Generating Plant- Units 1 & 2 Annual Radiological Environmental Operating Reports for 2014 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 2014.

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.

Respectfully submitted ,

etf~

C. R. Pierce Regulatory Affairs Director CRP/RMJ

U. S. Nuclear Regulatory Commission NL-15-0877 Page2

Enclosures:

1. Hatch Annual Radiological Environmental Operating Report for 2014

2. Farley Annual Radiological Environmental Operating Report for 2014

3. Vogtle Annual Radiological Environmental Operating Report for2014 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President - Farley Mr. D. R. Vineyard, Vice President- Hatch Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. K. Taber, Vice President- Vogtle 1 & 2 Mr. M.D. Meier, Vice President- Regulatory Affairs Mr. B. J. Adams, Vice President- Engineering Ms. B. L. Taylor, Regulatory Affairs Manager - Farley Mr. G. L. Johnson, Regulatory Affairs Manager- Hatch Mr. G . W. Gunn, Regulatory Affairs Manager - Vogtle 1 & 2 RType: Farley=CFA04.054; Hatch=CHA02.004; Vogtle=CVC7000 U. S. Nuclear Regulatory Commission Mr. V . M. McCree, Regional Administrator Mr. S. A. Williams, NRR Project Manager - Farley Mr. D. H. Hardage, Senior Resident Inspector- Hatch Mr. L. M. Cain, Senior Resident Inspector - Vogtle 1 & 2 Mr. P. K. Niebaum, Senior Resident Inspector - Farley Mr. R.E. Martin, NRR Project Manager- Hatch, Vogtle 1 & 2 State of Alabama Mr. D. K. Walter, Department of Public Health, Office of Radiation Control State of Georgia Mr. M. Williams, Department of Natural Resources American Nuclear Insurers Mr. R. A. Oliveira

Edwin I. Hatch Nuclear Plant - Units 1 & 2 Joseph M. Farley Nuclear Plant- Units 1 & 2 Vogtle Electric Generating Plant- Units 1 & 2 Annual Radiological Environmental Operating Reports for 2014 Enclosure 1 Hatch Annual Radiological Environmental Operating Report for 2014

EDWIN I. HATCH NUCLEAR PLANT 2014 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

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PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT EDWIN I. HATCH NUCLEAR PLANT 2014 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE OF CONTENTS 1 Introduction .................................................................................................. 1 2 REMP Description ......................................................................................... 2 3 Results Summary .......................................................................................... 7 3.1 Airborne Particulates ............................................................................................ 14 3.1.1 Gross Beta ............................................................................................................ 14 3.1.2 Gamma Particulates............................................................................................. 16 3.2 Direct Radiation .................................................................................................... 16 3.3 Biological Media .................................................................................................... 20 3.3.1 Milk ...................................................................................................................... 20 3.3.2 Vegetation............................................................................................................ 21 3.3.3 Fish ....................................................................................................................... 21 3.3.4 Biological Media Summary .................................................................................. 21 3.4 Surface Water ....................................................................................................... 22 3.5 Sediment ............................................................................................................... 23 3.6 Interlaboratory Comparison Program .................................................................. 23 3.7 Groundwater ......................................................................................................... 27 4 Survey Summaries ...................................................................................... 29 4.1 Land Use Census ................................................................................................... 29 4.2 Altamaha River Survey .......................................................................................... 29 5 Conclusions ................................................................................................. 31 Tables Table 2-1. Summary Description of Radiological Environmental Monitoring Program............................... 3 Table 2-2. Radiological Environmental Sampling Locations ........................................................................ 5 Table 3-1. Radiological Environmental Monitoring Program Annual Summary .......................................... 9 Table 3-2. Reporting Levels (RL) ................................................................................................................. 12 Table 3-3. Anomalies and Deviations from Radiological Environmental Monitoring Program ................. 13 Table 3-4. Average Weekly Gross Beta Air Concentration ......................................................................... 14 Table 3-5. Average Quarterly Exposure from Direct Radiation ................................................................. 17 Table 3-6. Interlaboratory Comparison Limits ........................................................................................... 24 2014 HNP Annual Radiological Environmental Operating Report ilPage

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-7. Interlaboratory Comparison Summary ..................................................................................... 25 Table 3-8. Groundwater Monitoring Locations ......................................................................................... 27 Table 4-1. Land Use Census Results ........................................................................................................... 29 Figures Figure 3-1. Average Weekly Gross Beta Air Concentration ........................................................................ 16 Figure 3-2. Average Quarterly Exposure from Direct Radiation ................................................................. 19 Figure 3-3. 2014 Average Exposure from Direct Radiation ........................................................................ 20 Figure 3-4. 2014 Biological Media Average Concentrations ....................................................................... 22 Figure 3-5. Average Annual Tritium Concentrations in River Water .......................................................... 23 Appendix - Maps A REMP Stations in Plant Vicinity A REMP Stations within 5 Miles A Facility Groundwater Wells 2014 HNP Annual Radiological Environmental Operating Report ii l P a g e

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF ACRONYMS AREOR Annual Radiological Environmental Operating Report ASTM American Society for Testing and Materials BWR Boiling Water Reactor CL Confidence Level EPA Environmental Protection Agency GPC Georgia Power Company GPCEL Georgia Power Company Environmental Laboratory HNP Edwin I. Hatch 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)

NEI Nuclear Energy Institute NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual OSL Optically Stimulated Luminescence Po Preoperation REMP Radiological Environmental Monitoring Program RL Reporting Level RM River Mile SNC Southern Nuclear Operating Company TLD Thermoluminescent Dosimeter TS Technical Specification 2014 HNP Annual Radiological Environmental Operating Report iii l P a g e

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1 INTRODUCTION The Radiological Environmental Monitoring Program (REMP) is conducted in accordance with Chapter 4 of the Offsite Dose Calculation Manual (ODCM). REMP activities for 2014 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), areas of higher population (community 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

Section 3 provides a summary of the results and an assessment of any radiological impacts to the environment

A summary of the land use census and the river survey are included in Section 4

Conclusions are included in Section 5 2014 HNP Annual Radiological Environmental Operating Report 1lPage

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2 REMP DESCRIPTION The following section provides a description of the sampling and laboratory protocols associated with the REMP. Table 2-1 provides a summary of 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 summarizes the collection and analysis frequencies (in accordance with ODCM Section 4.2). Table 2-2 provides specific information regarding the station locations, their proximity to the plant, and exposure pathways.

Additionally, the locations of the sampling stations are depicted on Maps A-1 through A-3 of the georeferenced data included in the appendix of this report.

Georgia Power Company's Environmental Laboratory (GPCEL), located in Smyrna, Georgia collects and analyzes REMP samples.

2014 HNP Annual Radiological Environmental Operating Report 2lPage

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 2-1. Summary Description of Radiological Environmental Monitoring Program Exposure Pathway Approximate Number of Sampling/Collection Frequency Type/Frequency of Analysis and/or Sample Sample Locations Direct Radiation 37 routine monitoring Quarterly Gamma dose, quarterly stations Airborne Radioiodine Samples from six Continuous sampler operation with sample Radioiodine canister: I-131 analysis, weekly and Particulates locations: collection weekly Particulate sampler: analyze for gross beta radioactivity not less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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.

Waterborne 1 2 Surface One sample upriver Composite sample over one month period Gamma isotopic analysis , monthly One sample downriver Composite for tritium analysis, quarterly 3,4 Drinking One sample of river River water collected near the intake will be a I-131 analysis on each sample when biweekly water near the intake and composite sample; the finished water will be a collections are required. Gross beta and gamma one sample of finished grab sample. These samples will be collected isotopic analysis on each sample; composite (by water from each of one monthly unless the calculated dose due to location) for tritium analysis, quarterly.

to three of the nearest consumption of the water is greater than 1 water supplies which mrem/year; then the collection will be biweekly.

could be affected by HNP The collections may revert to monthly should the discharges. calculated doses become less than 1 mrem/year.

2014 HNP Annual Radiological Environmental Operating Report 3lPage

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 2-1. Summary Description of Radiological Environmental Monitoring Program Exposure Pathway Approximate Number of Sampling/Collection Frequency Type/Frequency of Analysis and/or Sample Sample Locations Groundwater See Table 3-8 and Map A- Quarterly sample; pump used to sample GW wells; Tritium, gamma isotopic, and field parameters 3 for well locations grab sample from yard drains and ponds (pH, 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.

2 Shoreline Sediment Two Semiannually Gamma isotopic analysis , semiannually Ingestion 5 2,7 Milk One Bimonthly Gamma isotopic analysis , bimonthly 6 2 Fish or Clams Two Semiannually Gamma isotopic analysis on edible portions, semiannually 2,7 Grass or Leafy Three Monthly during growing season Gamma isotopic analysis , monthly Vegetation Notes:

1 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.

2 Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the 3

facility.

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.

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

5 Up to three sampling locations within five miles and in different sectors will be used as available. In addition, one or more control locations beyond 10 miles 6

will be used.

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

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.

2014 HNP Annual Radiological Environmental Operating Report 4lPage

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 2-2. Radiological Environmental Sampling Locations 1

Station Station Descriptive Location Direction Distance Radiation Sample Type 1

Number Type (miles) 064 Other Roadside Park WNW 0.8 Direct 101 Indicator Inner Ring N 1.9 Direct 102 Indicator Inner Ring NNE 2.5 Direct 103 Indicator Inner Ring NE 1.8 Airborne, Direct 104 Indicator Inner Ring ENE 1.6 Direct 105 Indicator Inner Ring E 3.7 Direct 106 Indicator Inner Ring ESE 1.1 Direct, Vegetation 107 Indicator Inner Ring SE 1.2 Airborne, Direct 108 Indicator Inner Ring SSE 1.6 Direct 109 Indicator Inner Ring S 0.9 Direct 110 Indicator Inner Ring SSW 1.0 Direct 111 Indicator Inner Ring SW 0.9 Direct 112 Indicator Inner Ring WSW 1.0 Airborne, Direct, Vegetation 113 Indicator Inner Ring W 1.1 Direct 114 Indicator Inner Ring WNW 1.2 Direct 115 Indicator Inner Ring NW 1.1 Direct 116 Indicator Inner Ring NNW 1.6 Airborne, Direct 2 3 170 Control Upstream WNW River 2 3 172 Indicator Downstream E River 201 Other Outer Ring N 5.0 Direct 202 Other Outer Ring NNE 4.9 Direct 203 Other Outer Ring NE 5.0 Direct 204 Other Outer Ring ENE 5.0 Direct 205 Other Outer Ring E 7.2 Direct 206 Other Outer Ring ESE 4.8 Direct 207 Other Outer Ring SE 4.3 Direct 208 Other Outer Ring SSE 4.8 Direct 209 Other Outer Ring S 4.4 Direct 210 Other Outer Ring SSW 4.3 Direct 211 Other Outer Ring SW 4.7 Direct 212 Other Outer Ring WSW 4.4 Direct 213 Other Outer Ring W 4.3 Direct 214 Other Outer Ring WNW 5.4 Direct 215 Other Outer Ring NW 4.4 Direct 216 Other Outer Ring NNW 4.8 Direct 2014 HNP Annual Radiological Environmental Operating Report 5lPage

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 2-2. Radiological Environmental Sampling Locations 1

Station Station Descriptive Location Direction Distance Radiation Sample Type 1

Number Type (miles)

Toombs Central 301 Other N 8.0 Direct School 304 Control State Prison ENE 11.2 Airborne, Direct 304 Control State Prison ENE 10.3 Milk Baxley 309 Control S 10.0 Airborne, Direct Substation Emergency News 416 Control NNW 21.0 Direct, Vegetation Center Notes:

1 Direction and distance are determined from the main stack.

2 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.

3 River (fish or clams, shoreline sediment, and surface water) 2014 HNP Annual Radiological Environmental Operating Report 6lPage

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 3 RESULTS

SUMMARY

Included in this section are statistical evaluations of the laboratory results, comparison of the results by media, and a summary of the anomalies and deviations. Overall, 855 analyses were performed across nine exposure pathways. Tables and figures are provided throughout this section to provide an enhanced presentation of the information.

In recent history, man-made nuclides have been released into the environment and have resulted in wide spread distribution of radionuclides across the globe. For example, 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 pre-operation, and through early operation. Some long-lived radionuclides, such as Cs-137, continue to be detected and a portion of these detections are believed to be attributed to the nuclear weapons tests.

Additionally, data associated with certain radiological effects created by off-site events have been removed from the historical evaluation, this includes: the nuclear atmospheric weapon test in the fall of 1980 and the Chernobyl incident in the spring of 1986.

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. Historically, the radionuclide Be-7, which occurs abundantly in nature, is often detected in REMP samples, and occasionally detected in the plants liquid and gaseous effluents. When it is detected in effluents and REMP samples, it is also included in the REMP results. In 2014, Be-7 was not detected in any plant effluents and is therefore not included in this report. The Be-7 detected in select REMP samples likely represents naturally occurring and/or background conditions.

As part of the data evaluation process, SNC considered the impact of the non-plant associated nuclides along with a statistical evaluation of the REMP data. The statistical evaluations included within this report include the Minimum Detectable Concentration (MDC), the Minimum Detectable Difference (MDD), and Chauvenets Criterion as described below.

Minimum Detectable Concentration The minimum detectable concentration is defined as an estimate of the true concentration of an analyte required to give a specified high probability that the measured response will be greater than the critical value.

2014 HNP Annual Radiological Environmental Operating Report 7lPage

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Minimum Detectable Difference The Minimum Detectable Difference (MDD) compares the lowest significant difference (between the means) of a control station, versus an indicator station or a community station, that can be determined statistically at the 99% Confidence Level (CL). A difference in mean values which was less than the MDD was considered to be statistically indiscernible.

Chauvenets Criterion 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.

The 2014 results were compared with past results, including those obtained during pre-operation. As appropriate, results were compared with their MDC (listed in Table 3-1) and RL which is listed in Table 3-2. The required MDCs were achieved during laboratory sample analysis. No data points were excluded for violating Chauvenets criterion.

2014 HNP Annual Radiological Environmental Operating Report 8lPage

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-1. Radiological Environmental Monitoring Program Annual Summary Medium or Indicator Pathway Minimum Locations Location with the Highest Control Sampled Type and Total Detectable Mean (b), Annual Mean Other Stations Locations Mean (Unit of Number of Analyses Concentration Range Name Distance Mean (b), Range (f) Mean (b), (b), Range Measurement) Performed (MDC) (a) (Fraction) and Direction (Fraction) Range (Fraction) (Fraction)

Airborne Gross Beta 10 22 Baxley 22.7 22.3 Particulates 310 6.2-38.3 Substation, S, 10 6.6-38.2 9.5-36.6 (fCi/m3) (207/207) mi. (52/52) (103/103)

Gamma Isotopic 24 I-131 70 NDM(c) NDM NDM Cs-134 50 NDM NDM NDM Cs-137 60 NDM NDM NDM Airborne I-131 70 NDM NDM NDM NDM Radioiodine 306 (fCi/m3)

Direct Radiation Gamma Dose 12.0 Inner Ring 16.4 11.8 11.7 (mR/91 days) 148 8.8-18.4 NW 1.1 mi. 13.5-18.4 8.1-16.6 10.5-13.2 (64/64) (4/4) (72/72) (12/12)

Milk (pCi/l) Gamma Isotopic 24 I-131 1 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 Vegetation Gamma Isotopic (pCi/kg-wet) 36 I-131 60 NDM 2014 HNP Annual Radiological Environmental Operating Report 9lPage

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-1. Radiological Environmental Monitoring Program Annual Summary Medium or Indicator Pathway Minimum Locations Location with the Highest Control Sampled Type and Total Detectable Mean (b), Annual Mean Other Stations Locations Mean (Unit of Number of Analyses Concentration Range Name Distance Mean (b), Range (f) Mean (b), (b), Range Measurement) Performed (MDC) (a) (Fraction) and Direction (Fraction) Range (Fraction) (Fraction)

Cs-134 60 NDM Cs-137 80 69.8 Inner Ring ESE 123.0 0-508.5 1.1 mi. 0-508.5 (7/24) (7/12)

River Water Gamma Isotopic (pCi/l) 13 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(d) 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 (e) 141.9 Upstream WNW 250.5 250.5 8 2.4-370 0.6 RM from 139-362 139-362 (3/3) intake (2/2) (2/2)

Fish Gamma Isotopic (pCi/kg-wet) 4 2014 HNP Annual Radiological Environmental Operating Report 10 l P a g e

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-1. Radiological Environmental Monitoring Program Annual Summary Medium or Indicator Pathway Minimum Locations Location with the Highest Control Sampled Type and Total Detectable Mean (b), Annual Mean Other Stations Locations Mean (Unit of Number of Analyses Concentration Range Name Distance Mean (b), Range (f) Mean (b), (b), Range Measurement) Performed (MDC) (a) (Fraction) and Direction (Fraction) Range (Fraction) (Fraction)

Be-7 655(d) NDM NDM Mn-54 130 NDM NDM Fe-59 260 NDM NDM Co-58 130 NDM NDM Co-60 130 NDM NDM Zn-65 260 NDM NDM Cs-134 130 NDM NDM Cs-137 150 12.8 Downstream E 12.8 NDM 0-12.8 ~3.0 RM from 0-12.8 NDM (1/2) intake (1/2) (0/2)

Sediment Gamma Isotopic (pCi/kg-dry) 8 Cs-134 150 NDM NDM Cs-137 180 14.4 Upstream WNW 19.8 19.8 0-57.6 1.1 RM from 0-79.2 0-79.2 (1/4) intake (1/4) (1/4)

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.

(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) (NDM).

(d) If a drinking water pathway were to exist, a MDC of 1pCi/L would have been used.

(e) If a drinking water pathway were to exist, a MDC of 2000pCi/L would have been used.

Not Applicable (sample not required) 2014 HNP Annual Radiological Environmental Operating Report 11 l P a g e

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-2. Reporting Levels (RL)

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

I-131 2 900 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.

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 sampling (as described in Table 2-1) are summarized in Table 3-3 along with their causes and resolution.

2014 HNP Annual Radiological Environmental Operating Report 12 l P a g e

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-3. Anomalies and Deviations from Radiological Environmental Monitoring Program Collection Period Affected Samples Anolmaly (A)* or Deviation Cause Resolution (D)**

12/30/14-01/06/14 River Water Gamma (A) Grab sample obtained Grab sample was obtained instead GPCEL sampling procedure Station 170 rather than composite of a composite, which was updated to reflect this previously allowed per procedure. requirement. Sample was analyzed as usual.

12/30/13-01/06/14 Air I, Air Part. (D) Sample not obtained Sampler found damaged during No sample obtained.

CR 753916 Station #116 weekly change-out.

01/06/14-01/13/14 Air I, Air Part. (A) Low sample volume Sampler found damaged during Sample volume was low, but CR 753916 Station #116 weekly change-out. still acceptable per GPCEL sampling procedure.

05/12/14-05/19/14 Air I, Air Part. (D) Sample not obtained Sample motor was not started after Discussed expectations with Station #309 changing filter. GPCEL personnel.

An anomaly is considered a non-standard sample that still meets sampling criteria outlined in SNC and Georgia Power Lab procedures.

- A deviation is a sample result that is not recorded due to not meeting scheduling and/or procedural requirements as outlined by SNC and Georgia Power Lab 2014 HNP Annual Radiological Environmental Operating Report 13 l P a g e

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 3.1 Airborne Particulates As specified in Table 2-1, airborne particulate filters and charcoal canisters are collected weekly at four indicator stations (Stations 103, 107, 112 and 116) which encircle the plant at the site periphery, and at two control stations (Station 304 and 309) which is approximately 10 miles from the main stack. 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.

3.1.1 Gross Beta As provided in Table 3-1, the 2014 annual average weekly gross beta activity was 22 fCi/m3 for the indicator stations. It was 0.3 fCi/m3 less than the control station average of 22.3 fCi/m3 for the year. This difference is not statistically discernible, since it is less than the calculated MDD of 4.6 fCi/m3.

Average Air Gross Beta historical data (Table 3-4) is graphed to show trends associated with a prevalent exposure pathway (Figure 3-1). 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.

Table 3-4. Average Weekly Gross Beta Air Concentration Period Indicator (fCi/m3) Control (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 2014 HNP Annual Radiological Environmental Operating Report 14 l P a g e

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-4. Average Weekly Gross Beta Air Concentration Period Indicator (fCi/m3) Control (fCi/m3) 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 2011 23.5 25.1 2012 23.7 22.7 2013 21.3 20.3 2014 22.0 22.3 2014 HNP Annual Radiological Environmental Operating Report 15 l P a g e

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Figure 3-1. 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 11 13 Year Indicator Control MDC 3.1.2 Gamma Particulates During 2014, no man-made radionuclides were detected from the gamma isotopic analysis of the quarterly composites of the air particulate filters.

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.

3.2 Direct Radiation In 2014, direct (external) radiation was measured with Optically Stimulated Luminescent (OSL) dosimeters by placing two OSL badges at each station. The gamma dose at each station is reported as the average reading of the two badges. The badges are analyzed on a quarterly basis. 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.

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PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Two direct radiation stations are established in each of the 16 compass sectors, to form two concentric rings. The inner ring stations (Nos. 101 through 116) are located near the plant perimeter as shown in Map A-1 in the appendix and the outer ring stations (Nos. 201 through 216) are located at distances of four to five miles from the plant as shown in Map A-2 in the appendix. The stations in the East sector are a few additional miles away with regard to 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 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 three control stations (Nos. 304, 309 and 416) are located at distances greater than 10 miles from the plant as shown in Map A-2. The mean and range values presented in the Other column in Table 3-1 includes the outer ring stations (stations 201 through 216) as well as stations 064 and 301, which 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 2014 average quarterly exposure at the indicator stations (inner ring) was 12.0 mR with a range of 8.8-18.4 mR. The indicator station average was 0.3 mR more than the control station average (11.7 mR). This difference is not considered statistically discernible since it is less than the MDD of 1.3 mR.

The quarterly exposures acquired at the community/other (outer ring) stations during 2014 ranged from 8.1 to 16.6 mR with an average of 11.8 mR which was 0.1 mR more than that for the control stations. However, this difference is not discernible since it is less than the MDD of 0.6 mR.

Average Direct Radiation historical data (Table 3-5) is graphed to show trends associated with a prevalent exposure pathway (Figure 3-2). 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.

Table 3-5. Average Quarterly Exposure from Direct Radiation Period Indicator Control Outer Ring (mR) (mR) (mR)

Pre-op 22.3 23.0 NA 1974 23.2 25.6 NA 1975 10.0 10.5 NA 1976 8.18 6.90 NA 1977 7.31 6.52 NA 1978 6.67 6.01 NA 2014 HNP Annual Radiological Environmental Operating Report 17 l P a g e

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-5. Average Quarterly Exposure from Direct Radiation Period Indicator Control Outer Ring (mR) (mR) (mR) 1979 5.16 6.77 NA 1980 4.44 5.04 4.42 1981 5.90 5.70 5.70 1982 12.3 12.0 11.3 1983 11.4 11.3 10.6 1984 13.3 12.9 11.9 1985 14.7 14.7 13.7 1986 15.0 14.0 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 11.0 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 2011 19.7 19.1 19.2 2012 14.4 13.6 14.1 2013 12.7 10.2 12.4 2014 12.0 11.7 11.8 2014 HNP Annual Radiological Environmental Operating Report 18 l P a g e

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Figure 3-2. Average Quarterly Exposure from Direct Radiation 30 25 20 15 10 5

0 Po 75 77 79 81 83 85 87 89 91 93 95 97 99 01 03 05 07 09 11 13 Indicator Control Outer Ring Roadside Park (Station 064)

Toombs Central School (Station 301)

The increase shown in 2010 reflects issues with the aging Panasonic TLD reader. The close agreement between the station groups supports the position that the plant is not contributing significantly to direct radiation in the environment. Figure 3-3 below provides a more detailed view of the 2014 values. The values for the special interest areas detailed below, indicate that Plant Hatch did not significantly contribute to direct radiation at those areas.

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PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Figure 3-3. 2014 Average Exposure from Direct Radiation 12 11.9 11.8 Concentration (mR) 11.7 11.6 11.5 11.4 11.3 11.2 11.1 3.3 Biological Media Cs-137 was the only radionuclide analyzed across all three biological mediums. As indicated in Figure 3-4, the Cs-137 activity levels are below the respective MDCs and well below that of the respective RLs for each sample media for both the indicator and control stations.

3.3.1 Milk In accordance with Tables 2-1 and 2-2, milk samples are collected bimonthly from Station 304 (the state prison dairy) which is a control station located more than 10 miles from the plant.

Since 1989, efforts to locate a reliable milk sample source within five miles of the plant have been unsuccessful and the 2014 land census did not identify a milk animal within five miles of the plant.

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PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Gamma isotopic (including I-131 and Cs-137) analyses were performed on each collected milk sample and there were no detectable results for gamma isotopes. Figure 3-4 provides the 2014 Cs-137 concentration in milk.

3.3.2 Vegetation In accordance with Tables 2-1 and 2-2, vegetation samples are collected monthly for gamma isotopic analyses at two indicator locations near the site boundary (Stations 106 and 112) and at one control station located about 21 miles from the plant (Station 416). Cesium-137 was detected in seven samples (Station 106 and Station 112 did not return any activity) of the 24 samples collected at the indicator stations. The average of the samples was 69.8 pCi/kg-wet.

Cesium-137 was not detected in any control station samples. Due to the low number of samples, MDD was not able to be used to evaluate the data. The man-made radionuclide Cs-137 is periodically identified in vegetation samples, and is generally attributed to offsite sources (such as weapons testing, Chernobyl, and Fukushima).

While Cs-137 and I-131 were periodically found in vegetation samples during pre-operation, the historical trends and the relationship between the indicator and control stations demonstrate that plant operations are having no adverse impact to the environment. The sample results have consistently been well below the MDC and the RL for Cs-137 (80 and 2000 pCi/kg-wet, respectively).

During 2014, no other gamma isotopes were detected in any Vogtle REMP vegetation samples.

3.3.3 Fish Fish samples were collected in accordance with the ODCM (as indicated in Table 2-1). For the semiannual collections, the control location (Station 170) is located upriver of the plant intake structure, and the indicator location (Station 172) is located downriver of the plant discharge structure.

Cs-137 was detected in the indicator and control locations, which is consistent with historical results.

3.3.4 Biological Media Summary There were no statistical differences, trends, or anomalies associated with the 2014 biological media samples when compared to historical data. Figure 3-4 below, details the 2014 Cs-137 concentration compared to the Reportable Limits.

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PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Figure 3-4. 2014 Biological Media Average Concentrations 2000 Indicator 1500 Control MDC Concentration (pCi/kg) 1000 Reportable Limit 500 0

Milk Vegetation Fish Sediment 3.4 Surface Water Composite river water samples are collected monthly at an upstream control location and at a downstream indicator location (shown on Map A-3 in the appendix). The details of the sampling protocols are outlined in Tables 2-1 and Table 2-2. A gamma isotopic analysis is conducted on each monthly sample and the monthly aliquots are combined to form quarterly composite samples, which are analyzed for tritium.

As provided in Table 3-1, there were no positive results during 2014 from the gamma isotopic analysis of the river water samples. Also indicated in Table 3-1, the average tritium concentration found at the indicator station was 141.9 pCi/l which was 108.6 pCi/l less than the average at the control station (250.5 pCi/l). No MDD was calculated because the indicator station average was below the control station. Historically, the relationship between the indicator and control stations has remained consistent. Figure 3-5 below details the 2014 historical average tritium concentrations in river water.

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PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Figure 3-5. Average Annual Tritium Concentrations in River Water 3500 3000 2500 Concentration (pCi/l) 2000 1500 1000 500 0

Po 75 77 79 81 83 85 87 89 91 93 95 97 99 01 03 05 07 09 11 13 Indicator Control MDC 3.5 Sediment Sediment was collected along the shoreline of the Altamaha River in the spring and fall, at the upstream control station (No. 170) and the downstream indicator station (No. 172). A gamma isotopic analysis was performed on each sample. There were no man-made radionuclides detected in sediment samples, with the exception of Cs-137 (below the control average), which is previously plotted along with biological media (Cs-137 across all detected mediums) in Section 3.3.4, and Figure 3-4.

3.6 Interlaboratory Comparison Program In accordance with ODCM 4.1.3, GPCEL participates in an Interlaboratory Comparison Program (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 ICP includes the required determinations (sample medium/radionuclide combinations) included in the REMP.

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PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT The ICP was conducted by Eckert & Ziegler Analytics, Inc. (EZA) of Atlanta, Georgia. EZA 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. EZA supplies the crosscheck samples to GPCEL which performs routine laboratory analyses. Each of the specified analyses is performed three times.

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. 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 on Table 3-6 below:

Table 3-6. Interlaboratory Comparison Limits Nuclide Concentration

Total Sample Activity Percent Coefficient of (pCi) Variation

<300 NA 25 Cr-51 NA >1000 25

>300 <1000 15

<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).

As required by ODCM 4.1.3.3 and 7.1.2.3, a summary of the results of the GPCEL's participation in the ICP is provided in Table 3-7 for:

gross beta and gamma isotopic analyses of an air filter

gamma isotopic analyses of milk samples

gross beta, tritium and gamma isotopic analyses of water samples The 2014 analyses included tritium, gross beta and gamma emitting radio-nuclides in different matrices. The attached results for all analyses were within acceptable limits for accuracy (less than 15% coefficient of variation and less than 3.0 normalized deviations, except for Cr-51 and Fe-59, which are outlined in Table 3-6).

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PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-7. Interlaboratory Comparison Summary Analysis or Date Prepared Reported Known Value Standard Uncertainty Percent Coef of Normalized Radionuclide Average Deviation EL Analytics (3S) Variation Deviation I-131 ANALYSIS OF AN AIR CARTRIDGE (pCi/cartridge)

I-131 12/4/2014 102.5 98.4 1.8 1.64 5.05 0.8 GAMMA ISOTOPIC ANALYSIS OF AN AIR FILTER (pCi/filter)

Ce-141 12/4/2014 108 103 9 1.73 9.61 0.5 Co-58 12/4/2014 66 61.4 4.76 1.02 9 0.77 Co-60 12/4/2014 113 111 5.96 1.85 6.82 0.25 Cr-51 12/4/2014 200 192 9.22 3.2 8.42 0.48 Cs-134 12/4/2014 74.5 77.6 4.51 1.3 7.46 -0.55 Cs-137 12/4/2014 97.4 93.5 10.7 1.56 12.04 0.33 Fe-59 12/4/2014 83.3 82.4 8.01 1.38 11.41 0.09 Mn-54 12/4/2014 114 106 7.97 1.78 8.5 0.82 Zn-65 12/4/2014 153 140 18.4 2.34 13.25 0.62 GROSS BETA ANALYSIS OF AN AIR FILTER (PCI/FILTER)

Gross Beta 09/12/13 58.30 58.70 0.79 0.98 5.08 -0.14 GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (PCI/LITER)

Ce-141 6/12/2014 132 124 3.53 2.07 6.43 0.93 Co-58 6/12/2014 120 112 6.8 1.88 8.11 0.84 Co-60 6/12/2014 240 224 2.91 3.74 4.32 1.53 Cr-51 6/12/2014 269 253 13.3 4.23 12.91 0.47 Cs-134 6/12/2014 181 162 9.8 2.71 6.74 1.52 Cs-137 6/12/2014 130 120 4.6 2 7.09 1.06 Fe-59 6/12/2014 108 102 5.79 1.71 9.4 0.56 I-131 6/12/2014 99.2 90.9 4.25 1.52 7.58 1.1 Mn-54 6/12/2014 175 156 4.41 2.6 5.7 1.9 2014 HNP Annual Radiological Environmental Operating Report 25 l P a g e

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-7. Interlaboratory Comparison Summary Analysis or Date Prepared Reported Known Value Standard Uncertainty Percent Coef of Normalized Radionuclide Average Deviation EL Analytics (3S) Variation Deviation Zn-65 6/12/2014 299 252 14.8 4.22 7.56 2.09 GROSS BETA ANALYSIS OF WATER SAMPLE (PCI/LITER) 3/20/2014 309 279 12.35 1.79 6.32 1.54 Gross Beta 12/4/2014 339 299 11.94 4.99 5.42 2.2 GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (PCI/LITER)

Ce-141 3/20/2014 74.9 77.1 6.05 1.29 11.96 -0.24 Co-58 3/20/2014 173 174 7.87 2.9 7.03 -0.12 Co-60 3/20/2014 221 219 6.12 3.65 5.22 0.15 Cr-51 3/20/2014 334 319 17.7 5.32 12.47 0.36 Cs-134 3/20/2014 142 136 5.6 2.28 6 0.7 Cs-137 3/20/2014 169 164 11.1 2.74 8.52 0.35 Fe-59 3/20/2014 142 142 7.55 2.37 8.64 -0.02 I-131 3/20/2014 91.8 89.9 3.86 1.5 8.34 0.25 Mn-54 3/20/2014 202 193 11.7 3.22 7.61 0.56 Zn-65 3/20/2014 221 210 10.1 3.5 8.06 0.61 TRITIUM ANALYSIS OF WATER SAMPLES (PCI/LITER) 3/20/2014 9820 10000 157.6 167 2.71 -0.69 H-3 12/4/2014 14800 14900 127.53 249 2.18 -0.46 2014 HNP Annual Radiological Environmental Operating Report 26 l P a g e

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 3.7 Groundwater To ensure compliance with NEI 07-07 (Industry Ground Water Protection Initiative - Final Guidance Document), 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 robust buried piping and tanks inspection programs.

Plant Hatch maintains the following wells (Table 3-8), which are sampled at a frequency that satisfies the requirements of NEI 07-07. The analytical results for 2014 were all within regulatory limits specified within this report. See Map A-4 in the appendix for well locations.

Table 3-8. Groundwater Monitoring Locations Well Depth (Feet) 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 2014 HNP Annual Radiological Environmental Operating Report 27 l P a g e

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-8. Groundwater Monitoring Locations Well Depth (Feet) Monitoring Purpose 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

Water Level Only 2014 HNP Annual Radiological Environmental Operating Report 28 l P a g e

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 4 SURVEY SUMMARIES 4.1 Land Use Census In accordance with ODCM 4.1.2, a land use census was conducted on November 24, 2014 to verify the locations of the nearest radiological receptor within five miles. The census results, shown in Table 4-1, indicated no changes from 2013; therefore, no changes to the ODCM are required.

Table 4-1. Land Use Census Results Sector Residence Milk Animal Beef Cattle Fruit/Nut Tree Garden Distance in Miles to the Nearest Location in Each Sector N 2.8 None None 4.2 3.8 NNE 2.9 None None 4.7 None NE 3.3 None 4.1 None None ENE 4.2 None None None None E 3.0 None None None None ESE 3.8 None None None None SE 1.8 None 2.4 None None SSE 2.0 None 3.6 None 4.5 S 1.1 None 2.5 None 1.0 SSW 1.3 None 2.8 1.4 3.0 SW 1.1 None 4.7 1.6 1.6 WSW 1.0 None 3.6 1.5 None W 1.1 None None 2.8 2.0 WNW 1.1 None None None None NW 3.6 None 4.5 None None NNW 1.8 None 2.8 None 2.9 4.2 Altamaha River Survey A survey of the Altamaha River downstream of the plant for approximately 50 miles (approximately river miles 66.5 to 117.0) was conducted on October 21, 2014 to identify any new withdrawal of water from the river for drinking, irrigation, or construction purposes.

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PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Irrigation equipment was identified at Clarkes Farm about 3/4 mile downstream of Station #172 river water sampling station. The equipment is potentially used to irrigate crops. Mr. Clarke was contacted on October 22, 2014 and he stated that he had used river water to irrigate corn in 2014. SNC will implement steps to insure that this vegetation is collected in 2015 and included in that AREOR.

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PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 5 CONCLUSIONS This report confirms SNCs conformance with the requirements of Chapter 4 of the ODCM and the objectives were 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 HNP.

Based on the 2014 activities associated with the REMP, SNC offers the following conclusions:

Samples were collected and there were no deviations or anomalies that negatively affected the quality of the REMP

Land use census and river survey did not reveal any changes

Analytical results were below reporting levels

These values are consistent with historical results, indicating no adverse radiological environmental impacts associated with the operation of HNP 2014 HNP Annual Radiological Environmental Operating Report 31 l P a g e

PLANT HATCH ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT APPENDIX Maps 2014 HNP Annual Radiological Environmental Operating Report Appendix

W SW NW N

S 5 Miles NE SE E

Legend: Drawn by: C. Groce Appendix A Edwin I. Hatch Nuclear Plant Map A1 Indicator Sta ons 2014 Annual Radiological Environmental Report Control Sta ons REMP Sta ons in Plant Vicinity April 30, 2015 Other Sta ons

Legend: Drawn by: C. Groce Appendix A Edwin I. Hatch Nuclear Plant Map A2 Indicator Sta ons 2014 Annual Radiological Environmental Report Control Sta ons REMP Sta ons within 10 miles April 30, 2015 Other Sta ons

Legend: Drawn by: C. Groce Appendix A Edwin I. Hatch Nuclear Plant Map A3 Upper Perched Aquifer 2014 Annual Radiological Environmental Report Minor Confined Aquifer Facility Groundwater Wells April 30, 2015

Edwin I. Hatch Nuclear Plant - Units 1 & 2 Joseph M. Farley Nuclear Plant- Units 1 & 2 Vogtle Electric Generating Plant- Units 1 & 2 Annual Radiological Environmental Operating Reports for 2014 Enclosure 2 Farley Annual Radiological Environmental Operating Report for 2014

JOSEPH M. FARLEY NUCLEAR PLANT 2014 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

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PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JOSEPH M. FARLEY NUCLEAR PLANT 2014 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE OF CONTENTS 1 Introduction .................................................................................................. 1 2 REMP Description ......................................................................................... 2 3 Results Summary .......................................................................................... 8 3.1 Airborne Particulates ............................................................................................ 16 3.1.1 Gross Beta ............................................................................................................ 16 3.1.2 Gamma Particulates............................................................................................. 18 3.2 Direct Radiation .................................................................................................... 18 3.3 Biological Media .................................................................................................... 22 3.3.1 Milk ...................................................................................................................... 22 3.3.2 Vegetation............................................................................................................ 23 3.3.3 Fish ....................................................................................................................... 23 3.3.3.1 Bottom Feeding Species ...................................................................................... 23 3.3.3.2 Game Species ....................................................................................................... 23 3.3.4 Biological Media Summary .................................................................................. 23 3.4 Off-site Groundwater............................................................................................ 23 3.5 River Water ........................................................................................................... 24 3.6 Sediment ............................................................................................................... 25 3.7 Interlaboratory Comparison Program .................................................................. 25 3.8 Groundwater ......................................................................................................... 29 4 Survey Summaries ...................................................................................... 30 4.1 Land Use Census ................................................................................................... 30 4.2 Chattahoochee River Survey................................................................................. 31 5 Conclusions ................................................................................................. 32 Tables Table 2-1. Summary Description of Radiological Environmental Monitoring Program............................... 3 Table 2-2. Radiological Environmental Sampling Locations ........................................................................ 6 Table 3-1. Radiological Environmental Monitoring Program Annual Summary ........................................ 10 Table 3-2. Reporting Levels (RL) ................................................................................................................. 14 Table 3-3. Anomalies and Deviations from Radiological Environmental Monitoring Program ................. 15 2014 FNP Annual Radiological Environmental Operating Report ilPage

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-4. Average Weekly Gross Beta Air Concentration......................................................................... 16 Table 3-5. Average Quarterly Exposure from Direct Radiation ................................................................. 19 Table 3-6. Interlaboratory Comparison Limits ........................................................................................... 26 Table 3-7. Interlaboratory Comparison Summary ..................................................................................... 27 Table 3-8. Groundwater Monitoring Locations ......................................................................................... 29 Table 4-1. Land Use Census Results ........................................................................................................... 30 Figures Figure 3-1. Average Weekly Gross Beta Air Concentration ........................................................................ 18 Figure 3-2. Average Quarterly Exposure from Direct Radiation ................................................................. 21 Figure 3-3. 2014 Average Exposure from Direct Radiation ........................................................................ 22 Figure 3-4. 2014 Average Tritium Concentrations in River and Off-site Groundwater .............................. 25 Appendix - Maps A REMP Stations in Plant Vicinity A REMP Stations within 5 Miles A Extended REMP Stations A Facility Groundwater Wells 2014 FNP Annual Radiological Environmental Operating Report ii l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF ACRONYMS APC Alabama Power Company AREOR Annual Radiological Environmental Operating Report ASTM American Society for Testing and Materials CL Confidence Level EPA Environmental Protection Agency FNP Joseph M. Farley Nuclear Plant GPCEL Georgia Power Company Environmental Laboratory ICP Interlaboratory Comparison Program MDC Minimum Detectable Concentration MDD Minimum Detectable Difference MWe MegaWatts Electric NA Not Applicable NDM No Detectable Measurement(s)

NEI Nuclear Energy Institute NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual OSL Optically Stimulated Luminescence Po Preoperation PWR Pressurized Water Reactor REMP Radiological Environmental Monitoring Program RL Reporting Level RM River Mile SNC Southern Nuclear Operating Company SRS ChattahoocheeRiver Site TLD Thermoluminescent Dosimeter TS Technical Specification 2014 FNP Annual Radiological Environmental Operating Report iii l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1 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 2014 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), areas of higher population (community 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 (APC) and operated by Southern Nuclear Operating Company (SNOC). 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

Section 3 provides a summary of the results and an assessment of any radiological impacts to the environment

A summary of the land use census and the river survey are included in Section 4

Conclusions are included in Section 5 2014 FNP Annual Radiological Environmental Operating Report 1lPage

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2 REMP DESCRIPTION The following section provides a description of the sampling and laboratory protocols associated with the REMP. Table 2-1 provides a summary of 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 summarizes the collection and analysis frequencies (in accordance with ODCM Section 4.2). Table 2-2 provides specific information regarding the station locations, their proximity to the plant, and exposure pathways.

Additionally, the locations of the sampling stations are depicted on Maps A-1 through A-3 of the station locations included in the appendix of this report.

Georgia Power Company's Environmental Laboratory (GPCEL), located in Smyrna, Georgia collects and analyzes REMP samples.

2014 FNP Annual Radiological Environmental Operating Report 2lPage

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 2-1. Summary Description of Radiological Environmental Monitoring Program Exposure Number of Representative Samples and Sample Sampling/Collection Frequency Type/Frequency of Analysis Pathway and/or Locations Direct Radiation Forty routine monitoring stations with two or more Quarterly Gamma dose, quarterly 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 population centers, nearby recreation areas, and control stations Airborne Continuous sampler operation Particulate sampler: Analyze for gross beta Radioiodine and Samples from nine locations: with sample collection weekly radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter Particulates change. Perform gamma isotopic analysis on Four locations close to the site boundary in each sample when gross beta activity is > 10 different sectors; times the yearly mean of control samples.

Perform gamma isotopic analysis on Three community stations; within 8 miles composite sample (by location) quarterly.

Two control locations near population centers, Radioiodine canister: I-131 analysis, weekly approximately 15 and 18 miles away (One community station)

Waterborne 3 2 Surface One sample upriver Composite sample over one Gamma isotopic analysis , monthly 4

One sample downriver month period Composite for tritium analysis, quarterly 2014 FNP Annual Radiological Environmental Operating Report 3lPage

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 2-1. Summary Description of Radiological Environmental Monitoring Program Exposure Number of Representative Samples and Sample Sampling/Collection Frequency Type/Frequency of Analysis Pathway and/or Locations Drinking Two samples at each of the three nearest water Composite sample of river water I-131 analysis on each sample when the dose treatment plants that could be affected by plant near the intake of each water calculated for the consumption of the water is 5

discharges treatment plant over two week greater than 1 mrem per year . Composite 4 2 period when I-131 analysis is for gross beta and gamma isotopic analysis Two samples at a control location required for each sample; monthly on raw water, monthly. Gross beta, gamma composite otherwise; and grab isotopic and I-131 analyses on grab sample of sample of finished water at each finished water, monthly. Composite for water treatment plant every two tritium analysis on raw and finished water, weeks or monthly, as appropriate quarterly Groundwater See Table 3-8 and Map A-4 in the appendix for well Quarterly sample; pump used to Tritium, gamma isotopic, and field locations sample GW wells; grab sample parameters (pH, temperature, conductivity, Off-site monitoring includes one indicator station from yard drains and ponds dissolved oxygen, oxidation/reduction and one control station potential, and turbidity) of each sample quarterly; Hard to detect radionuclides as necessary based on results of tritium and gamma (Off-site wells are analyzed only for Gamma Isotopic, I-131, & tritium 2

Shoreline

One sample from downriver area with existing Semiannually Gamma isotopic analysis , semiannually 8

Sediment or potential recreational value

One sample from upriver area with existing or potential recreational value Ingestion 6 2,7 Milk Two samples from milking animals at control Bimonthly Gamma isotopic analysis , bimonthly locations at a distance of about 10 miles or more 2014 FNP Annual Radiological Environmental Operating Report 4lPage

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 2-1. Summary Description of Radiological Environmental Monitoring Program Exposure Number of Representative Samples and Sample Sampling/Collection Frequency Type/Frequency of Analysis Pathway and/or Locations 9 2 Fish

One bottom feeding fish and one game fish Semiannually Gamma isotopic analysis on edible portions, both upstream and downstream semiannually During spring spawning season 2

Gamma isotopic analysis on edible portions, annually.

2,7 Grass or Leafy

One sample from two onsite locations near the Monthly during growing season Gamma isotopic analysis , monthly Vegetation site boundary in different sectors

One sample from a control location at a distance of about 18 miles Notes:

1 Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall 2

be performed on the individual samples.

Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the 3

facility.

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

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 5

obtaining a representative sample.

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

A milking animal is a cow or goat producing milk for human consumption, no milk animals were found within five miles of the plant.

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.

8 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.

9 Since several miles of river water may be needed to obtain adequate fish samples, these river mile positions represent the approximate locations from which the fish 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.

2014 FNP Annual Radiological Environmental Operating Report 5lPage

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 2-2. Radiological Environmental Sampling Locations 1

Station Station Descriptive Location Direction Distance Radiation Sample Type 1

Number Type (miles) 0501 Indicator River Intake Structure ESE 0.8 Airborne 0701 Indicator South Perimeter SSE 1.0 Airborne 1101 Indicator Plant Entrance WSW 0.9 Airborne 1601 Indicator North Perimeter N 0.8 Airborne 0215 Control Blakely GA NE 15 Airborne, Direct 0718 Control Neals Landing, FL SSE 18 Airborne, Direct 1218 Control Dothan, AL W 18 Airborne, Direct, Vegetation 0703 Community GA Pacific Paper Co. SSE 3 Airborne 1108 Community Ashford, AL WSW 8 Airborne 1605 Community Columbia, AL N 5 Airborne 0101 Indicator Plant Perimeter NNE 0.9 Direct 0201 Indicator Plant Perimeter NE 1.0 Direct 0301 Indicator Plant Perimeter ENE 0.9 Direct 0401 Indicator Plant Perimeter E 0.8 Direct 0501 Indicator Plant Perimeter ESE 0.8 Direct 0601 Indicator Plant Perimeter SE 1.1 Direct 0701 Indicator Plant Perimeter SSE 1.0 Direct, Vegetation 0801 Indicator Plant Perimeter S 1.0 Direct 0901 Indicator Plant Perimeter SSW 1.0 Direct 1001 Indicator Plant Perimeter SW 0.9 Direct 1101 Indicator Plant Perimeter WSW 0.9 Direct 1201 Indicator Plant Perimeter W 0.8 Direct 1301 Indicator Plant Perimeter WNW 0.8 Direct 1401 Indicator Plant Perimeter NW 1.1 Direct 1501 Indicator Plant Perimeter NNW 0.9 Direct 1601 Indicator Plant Perimeter N 0.8 Direct, Vegetation 1215 Control Dothan, AL W 15 Direct 1311 Control Webb, AL W 11 Direct 1612 Control Haleburg, AL WNW 12 Direct 1001 Community Nearest Residence SW 12 Direct 1108 Community Ashford, AL WSW 8.0 Direct Downstream of plant discharge, WRI Indicator S 3.0 River Water approximately RM 40 Upstream of plant intake, WRB Control NNE 3.0 River Water approximately RM 47 WGI-07 Indicator Paper Mill Well SSE 4.0 Groundwater 2014 FNP Annual Radiological Environmental Operating Report 6lPage

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 2-2. Radiological Environmental Sampling Locations 1

Station Station Descriptive Location Direction Distance Radiation Sample Type 1

Number Type (miles)

WGB-10 Control Whatley Residence SW 1.2 Groundwater Downstream of plant discharge RSI Indicator S 4.0 Sediment at Smiths Bend (RM 41)

Upstream of plant intake at RSB Control N 4.0 Sediment Andrews Lock and Dam (RM 48) 2 Robert Weir Dairy, MB-0714 Control SSE 14 Milk Donaldsonville, GA FGI & Downstream of plant discharge Indicator S 4.0 Fish FGB at Smiths Bend (RM 41)

FGB & Upstream of plant intake at Control N 4.0 Fish FBB Andrews Lock and Dam (RM 48)

Notes:

1 2

Direction and distance are determined from the main stack.

No milk animals were found within five miles of the plant, control sample not collected since 2009.

2014 FNP Annual Radiological Environmental Operating Report 7lPage

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 3 RESULTS

SUMMARY

Included in this section are statistical evaluations of the laboratory results, comparison of the results by media, and a summary of the anomalies and deviations. Overall, 1,102 analyses were performed across nine exposure pathways. Tables and figures are provided throughout this section to provide an enhanced presentation of the information.

In recent history, man-made nuclides have been released into the environment and have resulted in wide spread distribution of radionuclides across the globe. For example, 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 pre-operation, and through early operation. Some long-lived radionuclides, such as Cs-137, continue to be detected and a portion of these detections are believed to be attributed to the nuclear weapons tests.

Additionally, data associated with certain radiological effects created by off-site events have been removed from the historical evaluation, this includes: the nuclear atmospheric weapon test in the fall of 1980 and the Chernobyl incident in the spring of 1986.

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. Historically, the radionuclide Be-7, which occurs abundantly in nature, is often detected in REMP samples, and occasionally detected in the plants liquid and gaseous effluents. When it is detected in effluents and REMP samples, it is also included in the REMP results. In 2014, Be-7 was not detected in any plant effluents and therefore is not included in this report. The Be-7 detected in select REMP samples likely represents naturally occurring and/or background conditions.

As part of the data evaluation process, SNC considered the impact of the non-plant associated nuclides along with a statistical evaluation of the REMP data. The statistical evaluations included within this report include the Minimum Detectable Concentration (MDC), the Minimum Detectable Difference (MDD), and Chauvenets Criterion as described below.

Minimum Detectable Concentration The minimum detectable concentration is defined as an estimate of the true concentration of an analyte required to give a specified high probability that the measured response will be greater than the critical value.

2014 FNP Annual Radiological Environmental Operating Report 8lPage

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Minimum Detectable Difference The Minimum Detectable Difference (MDD) compares the lowest significant difference (between the means) of a control station, versus an indicator station or a community station, that can be determined statistically at the 99% Confidence Level (CL). A difference in mean values which was less than the MDD was considered to be statistically indiscernible.

Chauvenets Criterion 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.

The 2014 results were compared with past results, including those obtained during pre-operation. As appropriate, results were compared with their MDC (listed in Table 3-1) and RL which is listed in Table 3-2. The required MDCs were achieved during laboratory sample analysis. No data points were excluded for violating Chauvenets criterion.

2014 FNP Annual Radiological Environmental Operating Report 9lPage

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-1. Radiological Environmental Monitoring Program Annual Summary Medium or Indicator Pathway Type and Total Minimum Locations Location with the Highest Control Sampled Number of Detectable Mean (b), Annual Mean Other Stations Locations Mean (Unit of Analyses Concentration Range Name Distance and Mean (b), Range (f) Mean (b), (b), Range Measurement) Performed (MDC) (a) (Fraction) Direction (Fraction) Range (Fraction) (Fraction)

Airborne Gross Beta 10 17.7 Plant Entrance, 24.6 18.5 19.1 Particulates 413 1.8-51.7 WSW 0.9 mi. 3.4-51.7 3.8-50 4.1-37..1 (fCi/m3) (189/189) (52/52) (120/120) (104/104)

Gamma Isotopic 36 I-131 70 NDM(c) NDM NDM NDM Cs-134 50 NDM NDM NDM NDM Cs-137 60 NDM NDM NDM NDM Airborne I-131 70 NDM NDM NDM NDM Radioiodine 352 (fCi/m3)

Direct Radiation Gamma Dose 16.7 25.2 14.1 15.7 (mR/91 days) 159 11.4-26.2 Plant Perimeter, E 23.7-26.2 11.5-17.1 12.7-19.2 (63/63) 0.8 (4/4) (72/72) (24/24)

Milk (pCi/l) Gamma Isotopic 0

I-131 1 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Vegetation Gamma Isotopic (pCi/kg-wet) 36 2014 FNP Annual Radiological Environmental Operating Report 10 l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-1. Radiological Environmental Monitoring Program Annual Summary Medium or Indicator Pathway Type and Total Minimum Locations Location with the Highest Control Sampled Number of Detectable Mean (b), Annual Mean Other Stations Locations Mean (Unit of Analyses Concentration Range Name Distance and Mean (b), Range (f) Mean (b), (b), Range Measurement) Performed (MDC) (a) (Fraction) Direction (Fraction) Range (Fraction) (Fraction)

I-131 60 NDM NDM Cs-134 60 NDM NDM Cs-137 80 NDM NDM River Water Gamma Isotopic (pCi/l) 22 Mn-54 15 NDM NDM NDM NDM Fe-59 30 NDM NDM NDM NDM 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 Ba-140 60 NDM NDM La-140 15 NDM NDM Tritium 3000 69 Upstream of plant 96.3 96.3 3 29.7-109 discharge (RM 48) 96.3 96.3 (2/2) (1/1) (1/1)

Off-site Gamma Isotopic Groundwater 6 Mn-54 15 NDM NDM NDM Fe-59 30 NDM NDM NDM Co-58 15 NDM NDM NDM 2014 FNP Annual Radiological Environmental Operating Report 11 l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-1. Radiological Environmental Monitoring Program Annual Summary Medium or Indicator Pathway Type and Total Minimum Locations Location with the Highest Control Sampled Number of Detectable Mean (b), Annual Mean Other Stations Locations Mean (Unit of Analyses Concentration Range Name Distance and Mean (b), Range (f) Mean (b), (b), Range Measurement) Performed (MDC) (a) (Fraction) Direction (Fraction) Range (Fraction) (Fraction)

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 NDM NDM NDM 6

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 2000 30.8 Whatley Residence 37.3 37.3 3 17.3-44.2 Well, SW, 1.2 mi. 37.3 37.3 (2/2) (1/1) (1/1)

Bottom Feeding Gamma Isotopic Fish 2 (pCi/kg-wet) Mn-54 130 NDM NDM Fe-59 260 NDM NDM Co-58 130 NDM NDM Co-60 130 NDM NDM Zn-65 260 NDM NDM Cs-134 130 NDM NDM Cs-137 150 NDM NDM Game Fish Gamma Isotopic (pCi/kg-wet) 4 Mn-54 130 NDM NDM NDM 2014 FNP Annual Radiological Environmental Operating Report 12 l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-1. Radiological Environmental Monitoring Program Annual Summary Medium or Indicator Pathway Type and Total Minimum Locations Location with the Highest Control Sampled Number of Detectable Mean (b), Annual Mean Other Stations Locations Mean (Unit of Analyses Concentration Range Name Distance and Mean (b), Range (f) Mean (b), (b), Range Measurement) Performed (MDC) (a) (Fraction) Direction (Fraction) Range (Fraction) (Fraction)

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 NDM NDM NDM Sediment Gamma Isotopic (pCi/kg-dry) 4 Co-60 70(e) NDM NDM NDM Cs-134 150 NDM NDM NDM Cs-137 180 NDM NDM NDM 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.

(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) (NDM).

(d) The Georgia Power Company Environmental Laboratory has determined that this value may be routinely attained under normal conditions. No value is provided in ODCM Table 4-3.

(e) 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.

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

Not Applicable (sample not required) 2014 FNP Annual Radiological Environmental Operating Report 13 l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-2. Reporting Levels (RL)

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

I-131 2 900 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.

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 sampling (as described in Table 2-1) are summarized in Table 3-3 along with their causes and resolution.

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PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-3. Anomalies and Deviations from Radiological Environmental Monitoring Program Collection Period Affected Samples Anomaly (A)* or Deviation Cause Resolution (D)**

01/21/14-01/28/14 Air I, Air Part. (A) Low sample volume Loss of power for approximately 72 Power restored to cabinet.

CR 760966 N Perimeter Cabinet hours.

First quarter 2014 Groundwater Tritium (D) Samples not obtained PW#3 pump was danger tagged out; Samples were not obtained.

CR 773511 PW#3, CW#1 CW#1 pump was inoperable 04/29/14-05/06/14 Air I, Air Part. (A) Low sample volume Loss of power for approximately 6 Power restored to cabinet.

CR 809561 GP Paper Mill Sampler days, due to electrical storm.

Second quarter 2014 Groundwater Tritium (D) Samples not obtained PW#3 pump was danger tagged out; Samples were not obtained.

CR 811754 PW#3, CW#1 CW#1 pump was inoperable 08/19/14-08/26/14 Air I, Air Part. (A) Low sample volume Loss of power for approximately 5 Power restored to cabinet.

CR 857395 N Perimeter Cabinet days, due to storm.

08/19/14-08/26/14 Air I, Ari Part. (A) Low sample volume Loss of power for approximately Equipment repaired and CR 857681 SSE Perimeter Station 15.5 hrs, due to birds contacting power restored to cabinet.

12KV power lines.

09/02/14-09/09/14 Air I, Ari Part. (A) Low sample volume Loss of power for approximately 65 Power restored to cabinet.

CR 863951 SSE Perimeter Station hrs, due to electrical storm Third quarter 2014 Gamma (D) OSLD missing from Cause attributed to wildlife activity. New OSLD placed at station CR 875393 OSLD Station 0501 station to replace old dosimeter.

12/22/14-12/29/14 Air I, Ari Part. (A) Low sample volume Loss of power for approximately Power restored to cabinet.

CR 10005467 SSE Perimeter Station 10.25 hrs, due to electrical storm Third and Fourth Groundwater Tritium (D)Samples not obtained PW#3 pump was danger tagged out; Samples were not obtained.

quarter 2014 PW#3, CW#1 CW#1 pump was inoperable CW#1 pump operability CR 811754 restored and sampled in First quarter 2015.

An anomaly is considered a non-standard sample that still meets sampling criteria outlined in SNC and Georgia Power Labs procedures.

- A deviation is a sample result that is not recorded due to not meeting scheduling and/or procedural requirements as outlined by SNC and Georgia Power Labs 2014 FNP Annual Radiological Environmental Operating Report 15 l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 3.1 Airborne Particulates As specified in Table 2-1, airborne particulate filters and charcoal canisters are collected weekly at four indicator stations (Stations 0501, 0701, 1101, and 1601) which encircle the plant at the site periphery, at three community station (0703, 1108, and 1605) approximately three to eight miles from the plant, and at three control stations (0215, 0718, and 1218) which are range from approximately 15 to 18 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.

3.1.1 Gross Beta As provided in Table 3-1, the 2014 annual average weekly gross beta activity was 17.7 fCi/m3 for the indicator stations. It was 1.4 fCi/m3 less than the control station average of 19.1 fCi/m3 for the year. This difference is not statistically discernible, since it is less than the calculated MDD of 3.0 fCi/m3.

The 2014 annual average weekly gross beta activity at the community stations was 18.5 fCi/m3 which was 0.6 fCi/m3 less than the control station average. This difference is not statistically discernible since it is less than the calculated MDD of 2.9 fCi/m3.

Average Air Gross Beta historical data (Table 3-4) is graphed to show trends associated with a prevalent exposure pathway (Figure 3-1). 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.

Table 3-4. 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 2014 FNP Annual Radiological Environmental Operating Report 16 l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-4. Average Weekly Gross Beta Air Concentration Period Indicator Control Community (fCi/m3)

(fCi/m3) (fCi/m3) 1988 8 8 10 1989 7 7 8 1990 10 10 10 1991 9 10 8 1992 15 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 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 2011 20.9 14.5 18.2 2012 18.0 17.3 18.9 2013 16.7 18.7 16.1 2014 17.7 19.1 18.5 2014 FNP Annual Radiological Environmental Operating Report 17 l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Figure 3-1. Average Weekly Gross Beta Air Concentration 250 200 Concentration (fCi/m3) 150 100 50 0

Po 78 80 82 84 86 88 90 92 94 96 98 00 02 04 06 08 10 12 14 Year MDC Indicator Control Community 3.1.2 Gamma Particulates During 2014, no man-made radionuclides were detected from the gamma isotopic analysis of the quarterly composites of the air particulate filters.

Historically, gamma isotopes have been detected as a result of offsite events. During pre-operation Cs-137 was occasionally detected.

3.2 Direct Radiation In 2014, direct (external) radiation was measured with Optically Stimulated Luminescent (OSL) dosimeters by placing two OSL badges at each station. The gamma dose at each station is reported as the average reading of the two badges. The badges are analyzed on a quarterly basis. 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.

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PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Two direct radiation stations are established in each of the 16 compass sectors, to form two concentric rings. The inner ring (Stations 0101 through 1601) is located near the plant perimeter as shown in Map A-1 in the appendix and the outer ring (Stations 1701 through 3201) is located at a distance of approximately 5 miles from the plant as shown in Map A-2 in the appendix. 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 six control stations (Stations 0215, 0718, 1215, 1218, 1311 and 1612) are located at distances greater than 10 miles from the plant as shown in Map A-3 in the appendix.

Monitored special interest areas consist of the following: Station 1001 which is the nearest residence to the plant, and Station 1108 in the town of Ashford, Alabama. The mean and range values presented in the Other column in Table 3-1 includes the outer ring stations (stations 1701 through 3201) as well as stations 1101 and 1108.

As provided in Table 3-1, the 2014 average quarterly exposure at the indicator stations (inner ring) was 16.7 mR with a range of 11.4 to 26.2 mR. The indicator station average was 1.0 mR more than the control station average (15.7 mR). This difference is not statistically discernible since it is less than the MDD of 1.4 mR.

The quarterly exposures acquired at the community/other (outer ring) stations during 2014 ranged from 11.5 to 17.1 mR with an average of 14.1 mR which was 1.6 mR less than that for the control stations.

Average Direct Radiation historical data (Table 3-5) is graphed to show trends associated with a prevalent exposure pathway (Figure 3-2). 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.

Table 3-5. Average Quarterly Exposure from Direct Radiation Period Indicator Control Outer Ring (mR) (mR) (mR)

Pre-op 12.6 11.4 10.1 1977 10.6 12.2 10.6 1978 15 13.5 12 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 1983 20.2 20.2 17.4 1984 18.3 16.9 15.3 1985 21.9 22 18 1986 17.8 17.7 15.1 2014 FNP Annual Radiological Environmental Operating Report 19 l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-5. Average Quarterly Exposure from Direct Radiation Period Indicator Control Outer Ring (mR) (mR) (mR) 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 2011 21.0 19.9 18.4 2012 17.4 15.8 14.7 2013 16.5 15.1 13.8 2014 16.7 15.7 14.1 2014 FNP Annual Radiological Environmental Operating Report 20 l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Figure 3-2. Average Quarterly Exposure from Direct Radiation 25 20 Exposure (mR) 15 Indicator 10 Control Community 5

0 Po 78 80 82 84 86 88 90 92 94 96 98 00 02 04 06 08 10 12 14 Year The increase shown in 2010 reflects issues with the aging Panasonic TLD reader. The close agreement between the station groups supports the position that the plant is not contributing significantly to direct radiation in the environment. Figure 3-3 provides a more detailed view of the 2014 values. The values for the special interest areas detailed below indicate that Plant Farley did not significantly contribute to direct radiation at those areas.

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PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Figure 3-3. 2014 Average Exposure from Direct Radiation 20 18 16 14 Concentration (mR) 12 10 8

6 4

2 0

3.3 Biological Media Cs-137 was the only radionuclide detected in two of the three biological media. As indicated in Figure 3-4, the Cs-137 activity levels are below the respective MDCs and well below that of the respective RLs for each sample media for both the indicator and control stations.

3.3.1 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 2014 land use census therefore no milk sampling was performed during the reporting year.

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PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 3.3.2 Vegetation In accordance with Table 2-1 and 2-2, forage samples are collected every four weeks at two indicator stations on the plant perimeter, and at one control station located approximately 18 miles west of the plant, in Dothan. The man-made radionuclide Cs-137 is periodically identified in vegetation samples, and is generally attributed to offsite sources (such as weapons testing, Chernobyl, and Fukushima).

During 2014, no gamma isotopes were detected in any Farley REMP vegetation samples.

3.3.3 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 Map A-3 in appendix.

3.3.3.1 Bottom Feeding Species For bottom-feeding species, all fish sampled are considered indicator stations. No radionuclides were detected in the 2014 analyses, which is consistent with historical data.

3.3.3.2 Game Species For game species, all fish sampled are considered indicator stations. No radionuclides were detected in the 2014 analyses, which is consistent with historical data.

3.3.4 Biological Media Summary There were no statistical differences, trends, or anomalies associated with the 2014 biological media samples when compared to historical data. As shown in Table 3-1, no radionuclides were found from the gamma isotopic analysis of biological media samples in 2014.

3.4 Off-site Groundwater There are no true indicator sources of ground water offsite of Plant Farley. A well, located approximately 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.

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PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT In 2014, there were no radionuclides detected in any of the ground water samples from either sample station, with the exception of tritium.

Since 2004, tritium has been detected at very low concentrations (near the instrument detection level) and close to environmental background levels in off-site groundwater. In 2014, tritium was detected with an average of 30.8 pCi/l at the indicator station, and 37.3 pCi/l at the control station (one sample). Typically the positive results are at concentrations well below the MDC and RL for tritium (2,000 and 20,000 pCi/l, respectively).

3.5 River Water Composite river water samples are collected monthly at an upstream control location and at two downstream indicator locations (shown on Figure 2). The details of the sampling protocols are outlined in Tables 2-1 and Table 2-2. A gamma isotopic analysis is conducted on each monthly sample and the monthly aliquots are combined to form quarterly composite samples, which are analyzed for tritium.

As provided in Table 3-1, there were no positive results during 2014 from the gamma isotopic analysis of the river water samples. Also indicated in Table 3-1, the average tritium concentration found at the indicator station was 69.0 pCi/l which was 27.3 pCi/l less than the average (one sample) at the control station (96.3 pCi/l). The MDC for tritium in river water used to supply drinking water is 2000 pCi/l and the RL is 20000 pCi/l.

Figure 3-4 below details the 2014 average tritium concentrations across both water mediums.

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PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Figure 3-4. 2014 Average Tritium Concentrations in River and Off-site Groundwater 500 400 Concentration (pCi/l) 300 200 100 0

River Water Off-site Groundwater Indicator Control 3.6 Sediment Sediment was collected along the shoreline of the Chattahoochee River in the spring and fall at a control station which is approximately four miles upstream of the intake structure and at an indicator station which is approximately two miles downstream of the discharge structure as shown in Map A-3. A gamma isotopic analysis was performed on each sample. There were no radionuclides detected in sediment samples in 2014.

3.7 Interlaboratory Comparison Program In accordance with ODCM 4.1.3, GPCEL participates in an Interlaboratory Comparison Program (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 ICP includes the required determinations (sample medium/radionuclide combinations) included in the REMP.

The ICP was conducted by Eckert & Ziegler Analytics, Inc. (EZA) of Atlanta, Georgia. EZA 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 2014 FNP Annual Radiological Environmental Operating Report 25 l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 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. EZA supplies the crosscheck samples to GPCEL which performs routine laboratory analyses. Each of the specified analyses is performed three times.

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. 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 on Table 3-6 below:

Table 3-6. Interlaboratory Comparison Limits Nuclide Concentration

Total Sample Activity Percent Coefficient of (pCi) Variation

<300 NA 25 Cr-51 NA >1000 25

>300 <1000 15

<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).

As required by ODCM 4.1.3.3 and 7.1.2.3, a summary of the results of the GPCEL's participation in the ICP is provided in Table 3-7 for:

gross beta and gamma isotopic analyses of an air filter

gamma isotopic analyses of milk samples

gross beta, tritium and gamma isotopic analyses of water samples The 2014 analyses included tritium, gross beta and gamma emitting radio-nuclides in different matrices. The attached results for all analyses were within acceptable limits for accuracy (less than 15% coefficient of variation and less than 3.0 normalized deviations, except for Cr-51 and Fe-59, which are outlined in Table 3-6).

The 2014 analyses included tritium, gross beta and gamma emitting radio-nuclides in different matrices. The attached results for all analyses were within acceptable limits for accuracy.

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PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-7. Interlaboratory Comparison Summary Analysis or Date Prepared Reported Known Value Standard Uncertainty Percent Coef of Normalized Radionuclide Average Deviation EL Analytics (3S) Variation Deviation I-131 ANALYSIS OF AN AIR CARTRIDGE (pCi/cartridge)

I-131 12/4/2014 102.5 98.4 1.8 1.64 5.05 0.8 GAMMA ISOTOPIC ANALYSIS OF AN AIR FILTER (pCi/filter)

Ce-141 12/4/2014 108 103 9 1.73 9.61 0.5 Co-58 12/4/2014 66 61.4 4.76 1.02 9 0.77 Co-60 12/4/2014 113 111 5.96 1.85 6.82 0.25 Cr-51 12/4/2014 200 192 9.22 3.2 8.42 0.48 Cs-134 12/4/2014 74.5 77.6 4.51 1.3 7.46 -0.55 Cs-137 12/4/2014 97.4 93.5 10.7 1.56 12.04 0.33 Fe-59 12/4/2014 83.3 82.4 8.01 1.38 11.41 0.09 Mn-54 12/4/2014 114 106 7.97 1.78 8.5 0.82 Zn-65 12/4/2014 153 140 18.4 2.34 13.25 0.62 GROSS BETA ANALYSIS OF AN AIR FILTER (PCI/FILTER)

Gross Beta 09/12/13 58.30 58.70 0.79 0.98 5.08 -0.14 GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (PCI/LITER)

Ce-141 6/12/2014 132 124 3.53 2.07 6.43 0.93 Co-58 6/12/2014 120 112 6.8 1.88 8.11 0.84 Co-60 6/12/2014 240 224 2.91 3.74 4.32 1.53 Cr-51 6/12/2014 269 253 13.3 4.23 12.91 0.47 Cs-134 6/12/2014 181 162 9.8 2.71 6.74 1.52 Cs-137 6/12/2014 130 120 4.6 2 7.09 1.06 Fe-59 6/12/2014 108 102 5.79 1.71 9.4 0.56 I-131 6/12/2014 99.2 90.9 4.25 1.52 7.58 1.1 Mn-54 6/12/2014 175 156 4.41 2.6 5.7 1.9 2014 FNP Annual Radiological Environmental Operating Report 27 l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-7. Interlaboratory Comparison Summary Analysis or Date Prepared Reported Known Value Standard Uncertainty Percent Coef of Normalized Radionuclide Average Deviation EL Analytics (3S) Variation Deviation Zn-65 6/12/2014 299 252 14.8 4.22 7.56 2.09 GROSS BETA ANALYSIS OF WATER SAMPLE (PCI/LITER) 3/20/2014 309 279 12.35 1.79 6.32 1.54 Gross Beta 12/4/2014 339 299 11.94 4.99 5.42 2.2 GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (PCI/LITER)

Ce-141 3/20/2014 74.9 77.1 6.05 1.29 11.96 -0.24 Co-58 3/20/2014 173 174 7.87 2.9 7.03 -0.12 Co-60 3/20/2014 221 219 6.12 3.65 5.22 0.15 Cr-51 3/20/2014 334 319 17.7 5.32 12.47 0.36 Cs-134 3/20/2014 142 136 5.6 2.28 6 0.7 Cs-137 3/20/2014 169 164 11.1 2.74 8.52 0.35 Fe-59 3/20/2014 142 142 7.55 2.37 8.64 -0.02 I-131 3/20/2014 91.8 89.9 3.86 1.5 8.34 0.25 Mn-54 3/20/2014 202 193 11.7 3.22 7.61 0.56 Zn-65 3/20/2014 221 210 10.1 3.5 8.06 0.61 TRITIUM ANALYSIS OF WATER SAMPLES (PCI/LITER) 3/20/2014 9820 10000 157.6 167 2.71 -0.69 H-3 12/4/2014 14800 14900 127.53 249 2.18 -0.46 2014 FNP Annual Radiological Environmental Operating Report 28 l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 3.8 Groundwater 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 robust buried piping and tanks inspection programs.

Plant Farley maintains the following wells (Table 3-8), which are sampled at a frequency that satisfies the requirements of NEI 07-07. The analytical results for 2014 were all within regulatory limits specified within this report.

Table 3-8. Groundwater Monitoring Locations Well Aquifer Monitoring Purpose R1 Major Shallow aquifer Dilution line R2 Major Shallow aquifer Dilution line R3 Major Shallow aquifer Unit 2 RWST R4 Major Shallow aquifer Unit 1 RWST R5 Major Shallow aquifer Dilution line R6 Major Shallow aquifer Dilution line R7 Major Shallow aquifer Dilution line R8 Major Shallow aquifer Dilution line R9 Major Shallow aquifer Dilution line R10 Major Shallow aquifer Dilution line R11 Major Shallow aquifer Background 1 R13 Major Shallow aquifer Dilution line R14 Major Shallow aquifer Background 2 PW#2 Drinking water Production Well #2 Supply PW#3 Drinking water Production Well #3 Supply PW#4 Drinking water Production Well #4 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 2014 FNP Annual Radiological Environmental Operating Report 29 l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 4 SURVEY SUMMARIES 4.1 Land Use Census In accordance with ODCM 4.1.2, a land use census was conducted on November 25, 2014 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 five 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.

The 2014 census indicated that there were no changes to the nearest location for any of the categories in any of the sectors when compared to the 2013 census.

In accordance with ODCM 4.1.2, a land use census was conducted on November 25, 2014 to verify the locations of the nearest radiological receptor within five miles. The census results, shown in Table 4-1 indicated one change from 2013; a new permanent resident was identified in the western sector (12); now located 1.0 mile from the plant (a change of 0.3 miles). This location will be evaluated within the 2015 AREOR in accordance with ODCM 4.1.2.2.1.

Table 4-1. Land Use Census Results Sector Residence Milk Animal Distance in Miles to the Nearest Location in Each Sector 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 None None S 4.3 None SSW 2.9 None SW 1.2 None WSW 2.4 None W 1.0 None WNW 2.1 None NW 1.5 None NNW 3.4 None 2014 FNP Annual Radiological Environmental Operating Report 30 l P a g e

PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 4.2 Chattahoochee River Survey A river survey performed for Plant Farley in early 2014 identified a potential use of water from the Chattahoochee River, downstream of the plant discharge at a distance of approximately 2 miles. In July 2013, the Georgia Department of Natural Resources issued a farm use permit to withdraw from the Chattahoochee River to the Nature Conservancy of Georgia. The Nature Conservancy of Georgia leases property along the river for agricultural and grazing purposes to a private farm family, and water from the river could potentially be used for crop irrigation.

It is not known, at the time of this report, if the property lessee (farmer) has exercised permit rights to withdraw from the river. Plant Farley is pursuing this information from the farmer and will request future crop samples from the farmer if, and when, water is withdrawn from the river for irrigation of crops.

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PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 5 CONCLUSIONS This report confirms SNCs conformance with the requirements of Chapter 4 of the ODCM and the objectives were 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 FNP.

Based on the 2014 activities associated with the REMP, SNC offers the following conclusions:

Samples were collected and there were no deviations or anomalies that negatively affected the quality of the REMP

Land use census and river survey did not reveal any changes

Analytical results were below reporting levels

These values are consistent with historical results, indicating no adverse radiological environmental impacts associated with the operation of FNP 2014 FNP Annual Radiological Environmental Operating Report 32 l P a g e

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PLANT FARLEY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT APPENDIX Maps 2014 FNP Annual Radiological Environmental Operating Report Appendix

W SW NW S N 5 Miles SE NE E

Legend: Drawn by: C. Groce Appendix A Joseph M. Farley Nuclear Plant Map A1 Indicator Sta ons 2014 Annual Radiological Environmental Report REMP Sta ons in Plant Vicinity April 30, 2015

10 Miles Legend: Drawn by: C. Groce Appendix A Joseph M. Farley Nuclear Plant Map A2 Indicator Sta ons 2014 Annual Radiological Environmental Report Control Sta ons REMP Sta ons within 10 miles April 30, 2015

10 Miles Drawn by: C. Groce Appendix A Legend: Joseph M. Farley Nuclear Plant Map A3 Control Sta ons 2014 Annual Radiological Environmental Report Extended REMP Sta ons April 30, 2015

Legend: Drawn by: C. Groce Appendix A Joseph M. Farley Nuclear Plant Map A4 Groundwater Wells 2014 Annual Radiological Environmental Report Facility Groundwater Wells April 30, 2015

Edwin I. Hatch Nuclear Plant - Units 1 & 2 Joseph M. Farley Nuclear Plant- Units 1 & 2 Vogtle Electric Generating Plant- Units 1 & 2 Annual Radiological Environmental Operating Reports for 2014 Enclosure 3 Vogtle Annual Radiological Environmental Operating Report for 2014

VOGTLE ELECTRIC GENERATING PLANT 2014 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT VOGTLE ELECTRIC GENERATING PLANT 2014 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE OF CONTENTS 1 Introduction .................................................................................................. 1 2 REMP Description ......................................................................................... 2 3 Results Summary .......................................................................................... 9 3.1 Airborne Particulates ............................................................................................ 19 3.1.1 Gross Beta ............................................................................................................ 19 3.1.2 Gamma Particulates............................................................................................. 21 3.2 Direct Radiation .................................................................................................... 21 3.3 Biological Media .................................................................................................... 24 3.3.1 Milk ...................................................................................................................... 24 3.3.2 Vegetation............................................................................................................ 25 3.3.3 Fish ....................................................................................................................... 25 3.3.3.1 Anadromous Species............................................................................................ 25 3.3.3.2 Commercially or Recreationally Important Species ............................................ 25 3.3.4 Biological Media Summary .................................................................................. 26 3.4 Drinking Water ...................................................................................................... 26 3.5 River Water ........................................................................................................... 28 3.6 Sediment ............................................................................................................... 29 3.7 Interlaboratory Comparison Program .................................................................. 30 3.8 Groundwater ......................................................................................................... 34 4 Survey Summaries ...................................................................................... 36 4.1 Land Use Census ................................................................................................... 36 4.2 Savannah River Survey .......................................................................................... 36 5 Conclusions ................................................................................................. 38 Tables Table 2-1. Summary Description of Radiological Environmental Monitoring Program............................... 3 Table 2-2. Radiological Environmental Sampling Locations ........................................................................ 6 Table 3-1. Radiological Environmental Monitoring Program Annual Summary ........................................ 11 Table 3-2. Reporting Levels (RL) ................................................................................................................. 17 Table 3-3. Anomalies and Deviations from Radiological Environmental Monitoring Program ................. 18 2014 VEGP Annual Radiological Environmental Operating Report ilPage

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-4. Average Weekly Gross Beta Air Concentration......................................................................... 19 Table 3-5. Average Quarterly Exposure from Direct Radiation ................................................................. 22 Table 3-6. Interlaboratory Comparison Limits ........................................................................................... 31 Table 3-7. Interlaboratory Comparison Summary ..................................................................................... 32 Table 3-8. Groundwater Monitoring Locations ......................................................................................... 34 Table 4-1. Land Use Census Results ........................................................................................................... 36 Figures Figure 3-1. Average Weekly Gross Beta Air Concentration ........................................................................ 20 Figure 3-2. Average Quarterly Exposure from Direct Radiation ................................................................. 23 Figure 3-3. 2014 Average Exposure from Direct Radiation ........................................................................ 24 Figure 3-4. 2014 Biological Media Average Concentrations ....................................................................... 26 Figure 3-5. 2014 Average Gross Beta Concentration in Raw and Finished Drinking Water ....................... 28 Figure 3-6. 2014 Average Tritium Concentrations in River, Raw Drinking, and Finished Drinking Water.. 29 Appendix - Maps A REMP Stations in Plant Vicinity A REMP Stations within 5 Miles A Extended REMP Stations A Facility Groundwater Wells 2014 VEGP Annual Radiological Environmental Operating Report ii l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF ACRONYMS AREOR Annual Radiological Environmental Operating Report ASTM American Society for Testing and Materials CL Confidence Level EPA Environmental Protection Agency GPC Georgia Power Company GPCEL Georgia Power Company Environmental Laboratory ICP Interlaboratory Comparison Program MDC Minimum Detectable Concentration MDD Minimum Detectable Difference MWe MegaWatts Electric NA Not Applicable NDM No Detectable Measurement(s)

NEI Nuclear Energy Institute NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual OSL Optically Stimulated Luminescence Po Preoperation PWR Pressurized Water Reactor REMP Radiological Environmental Monitoring Program RL Reporting Level RM River Mile SNC Southern Nuclear Operating Company SRS Savannah River Site TLD Thermoluminescent Dosimeter TS Technical Specification VEGP Alvin W. Vogtle Electric Generating Plant 2014 VEGP Annual Radiological Environmental Operating Report iii l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1 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 2014 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), areas of higher population (community 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 (SRS). Unit 1, a Westinghouse Electric Corporation Pressurized Water Reactor (PWR), with a licensed core thermal power of 3626 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 3626 MWt, received its operating license on February 9, 1989 and began commercial operation on May 19, 1989. Both units were relicensed on June 3, 2009.

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

Section 3 provides a summary of the results and an assessment of any radiological impacts to the environment

A summary of the land use census and the river survey are included in Section 4

Conclusions are included in Section 5 2014 VEGP Annual Radiological Environmental Operating Report 1lPage

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2 REMP DESCRIPTION The following section provides a description of the sampling and laboratory protocols associated with the REMP. Table 2-1 provides a summary of 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 summarizes the collection and analysis frequencies (in accordance with ODCM Section 4.2). Table 2-2 provides specific information regarding the station locations, their proximity to the plant, and exposure pathways.

Additionally, the locations of the sampling stations are depicted on Maps A-1 through A-4 of the station locations included in the appendix of this report.

Georgia Power Company's Environmental Laboratory (GPCEL), located in Smyrna, Georgia collects and analyzes REMP samples.

2014 VEGP Annual Radiological Environmental Operating Report 2lPage

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 2-1. Summary Description of Radiological Environmental Monitoring Program Exposure Number of Representative Samples and Sample Sampling/Collection Frequency Type/Frequency of Analysis Pathway and/or Locations Direct Radiation 40 routine monitoring stations with two or more Quarterly Gamma dose, quarterly 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 five miles from the site; and Special interest areas, such as population centers, nearby recreation areas, and control stations Airborne Samples from seven locations: Continuous sampler operation Radioiodine canister: I-131 analysis, weekly Radioiodine and with sample collection weekly, or 1

Particulates Five locations close to the site boundary in different more frequently if required by Particulate sampler: Gross beta analysis sectors; dust loading following filter change and gamma isotopic 2

analysis of composite (by location),

A community having the highest calculated annual quarterly average ground level D/Q; A control location near a population center at a distance of about 14 miles Waterborne 3 2 Surface One sample upriver Composite sample over one Gamma isotopic analysis , monthly 4

Two samples downriver month period Composite for tritium analysis, quarterly 2014 VEGP Annual Radiological Environmental Operating Report 3lPage

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 2-1. Summary Description of Radiological Environmental Monitoring Program Exposure Number of Representative Samples and Sample Sampling/Collection Frequency Type/Frequency of Analysis Pathway and/or Locations Drinking Two samples at each of the three nearest water Composite sample of river water I-131 analysis on each sample when the dose treatment plants that could be affected by plant near the intake of each water calculated for the consumption of the water is 5

discharges treatment plant over two week greater than 1 mrem per year . Composite 4 2 period when I-131 analysis is for gross beta and gamma isotopic analysis Two samples at a control location required for each sample; monthly on raw water, monthly. Gross beta, gamma composite otherwise; and grab isotopic and I-131 analyses on grab sample of sample of finished water at each finished water, monthly. Composite for water treatment plant every two tritium analysis on raw and finished water, weeks or monthly, as appropriate quarterly Groundwater See Table 3-8 and Map A-4 for well locations See Table 3-8 and Map A-4 for Tritium, gamma isotopic, and field well locations. Quarterly sample; parameters (pH, temperature, conductivity, pump used to sample GW wells; dissolved oxygen, oxidation/reduction grab sample from yard drains and potential, and turbidity) of each sample ponds quarterly; Hard to detect radionuclides as necessary based on results of tritium and gamma 2

Shoreline

One sample from downriver area with existing Semiannually Gamma isotopic analysis , semiannually Sediment or potential recreational value

One sample from upriver area with existing or potential recreational value Ingestion 6 2,7 Milk Two samples from milking animals at control Bimonthly Gamma isotopic analysis , bimonthly locations at a distance of about 10 miles or more 2014 VEGP Annual Radiological Environmental Operating Report 4lPage

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 2-1. Summary Description of Radiological Environmental Monitoring Program Exposure Number of Representative Samples and Sample Sampling/Collection Frequency Type/Frequency of Analysis Pathway and/or Locations 2

Fish

At least one sample of any commercially or Semiannually Gamma isotopic analysis on edible portions, recreationally important species near the plant semiannually discharge During spring spawning season 2

At least one sample of any commercially or Gamma isotopic analysis on edible portions, recreationally important species in an area not annually.

influenced by plant discharges

At least one sample of any anadromous species near the plant discharge 2,7 Grass or Leafy

One sample from two onsite locations near the Monthly during growing season Gamma isotopic analysis , monthly Vegetation site boundary in different sectors

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

1 Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall 2

be performed on the individual samples.

Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the 3

facility.

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

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 5

obtaining a representative sample.

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

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.

2014 VEGP Annual Radiological Environmental Operating Report 5lPage

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 2-2. Radiological Environmental Sampling Locations 1

Station Station Type Descriptive Location Direction Distance Radiation Sample Type 1

Number (miles) 1 Indicator River Bank N 1.1 Direct 2 Indicator River Bank NNE 0.8 Direct 3 Indicator Discharge Area NE 0.6 Airborne 3 Indicator River Bank NE 0.7 Direct 4 Indicator River Bank ENE 0.8 Direct 5 Indicator River Bank E 1.0 Direct 6 Indicator Plant Wilson ESE 1.1 Direct 7 Indicator Simulator Building SE 1.7 Airborne, Direct, Vegetation 8 Indicator River Road SSE 1.1 Direct 9 Indicator River Road S 1.1 Direct 10 Indicator Met Tower SSW 0.9 Airborne 10 Indicator River Road SSW 1.1 Direct 11 Indicator River Road SW 1.2 Direct 12 Indicator River Road WSW 1.2 Airborne, Direct 13 Indicator River Road W 1.3 Direct 14 Indicator River Road WNW 1.8 Direct 15 Indicator Hancock Landing Road NW 1.5 Direct, Vegetation 16 Indicator Hancock Landing Road NNW 1.4 Airborne, Direct 17 Other Sav. River Site (SRS), River Road N 5.4 Direct 18 Other SRS, D Area NNE 5.0 Direct 19 Other SRS, Road A.13 NE 4.6 Direct 20 Other SRS, Road A.13.1 ENE 4.8 Direct 21 Other SRS, Road A.17 E 5.3 Direct 2014 VEGP Annual Radiological Environmental Operating Report 6lPage

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 2-2. Radiological Environmental Sampling Locations 1

Station Station Type Descriptive Location Direction Distance Radiation Sample Type 1

Number (miles) 22 Other River Bank ESE 5.2 Direct 23 Other River Road SE 4.6 Direct 24 Other Chance Road SSE 4.9 Direct 25 Other Chance Road near Highway 23 S 5.2 Direct 26 Other Highway 23 and Ebenezer Church Road SSW 4.6 Direct 27 Other Highway 23 opposite Boll Weevil Road SW 4.7 Direct 28 Other Thomas Road WSW 5.0 Direct 29 Other Claxton-Lively Road W 5.1 Direct 30 Other Nathaniel Howard Road WNW 5.0 Direct 31 Other River Road at Allens Chapel Fork NW 5.0 Direct 32 Other River Bank NNW 4.7 Direct 35 Other Girard SSE 6.6 Airborne, Direct 36 Control GPC Waynesboro Op. HQ WSW 13.9 Airborne, Direct 37 Control Substation, Waynesboro, GA WSW 16.7 Direct, Vegetation 43 Other Employees Rec. Center SW 2.2 Direct 47 Control Oak Grove Church SE 10.4 Direct 48 Control McBean Cemetery NW 10.2 Direct 51 Control SGA School, Sardis, GA S 11.0 Direct 52 Control Oglethorpe Substation; Alexander, GA SW 10.7 Direct 2

80 Control Augusta Water Treatment Plant NNW 29.0 Drinking Water 3 4 81 Control Sav. River N 2.5 Fish Sediment 82 Control Sav. River (RM 151.2) NNE 0.8 River Water 4

83 Indicator Sav. River (RM 150.4) ENE 0.8 River Water Sediment 2014 VEGP Annual Radiological Environmental Operating Report 7lPage

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 2-2. Radiological Environmental Sampling Locations 1

Station Station Type Descriptive Location Direction Distance Radiation Sample Type 1

Number (miles) 84 Other Sav. River (RM 149.5) ESE 1.6 River Water 3

85 Indicator Sav. River ESE 4.3 Fish 5

87 Indicator Beaufort-Jasper County Water Treatment Plant SE 76 Drinking Water 6

88 Indicator Cherokee Hill Water Treatment Plant, Port Wentworth, GA SSE 72 Drinking Water 7

89 Indicator Purrysburg Water Treatment Plant; Purrysburg, SC SSE 76 Drinking Water 8

98 Control W.C. Dixon Dairy SE 9.8 Milk 8

101 Indicator Girard Dairy S 5.5 Milk 8

102 Control Seven Oaks Dairy W 7.5 Milk 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 closer 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.

2014 VEGP Annual Radiological Environmental Operating Report 8lPage

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 3 RESULTS

SUMMARY

Included in this section are statistical evaluations of the laboratory results, comparison of the results by media, and a summary of the anomalies and deviations. Overall, 964 analyses were performed across nine exposure pathways. Tables and figures are provided throughout this section to provide an enhanced presentation of the information.

In recent history, man-made nuclides have been released into the environment and have resulted in wide spread distribution of radionuclides across the globe. For example, 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 pre-operation, and through early operation. Some long lived radionuclides, such as Cs-137, continue to be detected and a portion of these detections are believed to be attributed to the nuclear weapons tests.

Additionally, data associated with certain radiological effects created by off-site events have been removed from the historical evaluation, this includes: the nuclear atmospheric weapon test in the fall of 1980; the Chernobyl incident in the spring of 1986; and abnormal releases from the Savannah River Site (SRS) during 1987 and 1991.

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. Historically, the radionuclide Be-7, which occurs abundantly in nature, is often detected in REMP samples, and occasionally detected in the plants liquid and gaseous effluents. When it is detected in effluents and REMP samples, it is also included in the REMP results. In 2014, Be-7 was not detected in any plant effluents and therefore is not included in this report. The Be-7 detected in select REMP samples likely represents naturally occurring and/or background conditions.

As part of the data evaluation process, SNC considered the impact of the non-plant associated nuclides along with a statistical evaluation of the REMP data. The statistical evaluations included within this report include the Minimum Detectable Concentration (MDC), the Minimum Detectable Difference (MDD), and Chauvenets Criterion as described below.

Minimum Detectable Concentration The minimum detectable concentration is defined as an estimate of the true concentration of an analyte required to give a specified high probability that the measured response will be greater than the critical value.

2014 VEGP Annual Radiological Environmental Operating Report 9lPage

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Minimum Detectable Difference The Minimum Detectable Difference (MDD) compares the lowest significant difference (between the means) of a control station, versus an indicator station or a community station, that can be determined statistically at the 99% Confidence Level (CL). A difference in mean values which was less than the MDD was considered to be statistically indiscernible.

Chauvenets Criterion 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.

The 2014 results were compared with past results, including those obtained during pre-operation. As appropriate, results were compared with their MDC (listed in Table 3-1) and RL which is listed in Table 3-2. The required MDCs were achieved during laboratory sample analysis. No data points were excluded for violating Chauvenets criterion.

2014 VEGP Annual Radiological Environmental Operating Report 10 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-1. Radiological Environmental Monitoring Program Annual Summary Medium or Indicator Pathway Type and Total Minimum Locations Location with the Highest Sampled Number of Detectable Mean (b), Annual Mean Other Stations (f) Control Locations (Unit of Analyses Concentration Range Name Distance Mean (b), Range Mean (b), Range Mean (b), Range Measurement) Performed (MDC) (a) (Fraction) and Direction (Fraction) (Fraction) (Fraction)

Airborne Gross Beta 10 24.1 Hancock Landing 25.3 23.5 23.4 Particulates 356 4.2-42.9 Road NNW 1.4 7.0-42.9 7.3-39.9 12.4-39 (fCi/m3) (254/254) mi. (51/51) (51/51) (51/51)

Gamma Isotopic 28 I-131 70 NDM(c) NDM NDM NDM Cs-134 50 NDM NDM NDM NDM Cs-137 60 NDM NDM NDM NDM Airborne I-131 70 NDM NDM NDM NDM Radioiodine 98 (fCi/m3)

Direct Radiation Gamma Dose 13.1 17.3 13.6 13.2 (mR/91 days) 160 8.1-18 SRS, Road A.13.1 16.3-19.6 10.8-16.8 8.4-19.6 (64/64) ENE 4.8 mi. (4/4) (72/72) (24/24)

Milk (pCi/l) Gamma Isotopic 14 I-131 1 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 Vegetation Gamma Isotopic (pCi/kg-wet) 37 2014 VEGP Annual Radiological Environmental Operating Report 11 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-1. Radiological Environmental Monitoring Program Annual Summary Medium or Indicator Pathway Type and Total Minimum Locations Location with the Highest Sampled Number of Detectable Mean (b), Annual Mean Other Stations (f) Control Locations (Unit of Analyses Concentration Range Name Distance Mean (b), Range Mean (b), Range Mean (b), Range Measurement) Performed (MDC) (a) (Fraction) and Direction (Fraction) (Fraction) (Fraction)

I-131 60 NDM NDM Cs-134 60 NDM NDM Cs-137 80 0-14.9 Simulator 0-14.9 NDM (1/24) Building SE, 1.7 (1/24) miles River Water Gamma Isotopic (pCi/l) 36 Be-7 124(d) NDM NDM NDM NDM Mn-54 15 NDM NDM NDM NDM Fe-59 30 NDM NDM NDM NDM 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 Ba-140 60 NDM NDM La-140 15 NDM NDM Tritium 2000 1399 Savannah River 1399 606 152 12 790-2700 (RM 150.4) 790-2700 377-940 80.7-286 (4/4) (4/4) (4/4) (3/4) 2014 VEGP Annual Radiological Environmental Operating Report 12 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-1. Radiological Environmental Monitoring Program Annual Summary Medium or Indicator Pathway Type and Total Minimum Locations Location with the Highest Sampled Number of Detectable Mean (b), Annual Mean Other Stations (f) Control Locations (Unit of Analyses Concentration Range Name Distance Mean (b), Range Mean (b), Range Mean (b), Range Measurement) Performed (MDC) (a) (Fraction) and Direction (Fraction) (Fraction) (Fraction)

Water Near Gross Beta 4 2.8 Purrysburg 3.8 1.9 Intakes to Water 43 0-7.9 Water Treatment 0-7.9 0-3.7 Treatment Plants (33/36) Plant, (11/12) (10/12)

(pCi/l) Purrysburg, SC, SSE, 76 miles Gamma Isotopic 48 Be-7 124(d) NDM NDM NDM 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 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 2000 370.8 Purrysburg 396.8 137 16 170-520 Water Treatment 245-520 78.9-174 (12/12) Plant, (4/4) (4/4)

Purrysburg, SC, SSE, 76 miles 2014 VEGP Annual Radiological Environmental Operating Report 13 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-1. Radiological Environmental Monitoring Program Annual Summary Medium or Indicator Pathway Type and Total Minimum Locations Location with the Highest Sampled Number of Detectable Mean (b), Annual Mean Other Stations (f) Control Locations (Unit of Analyses Concentration Range Name Distance Mean (b), Range Mean (b), Range Mean (b), Range Measurement) Performed (MDC) (a) (Fraction) and Direction (Fraction) (Fraction) (Fraction)

Finished Water Gross Beta 4 2.2 Augusta Water 5.7 5.7 at Water 48 0-5.3 Treatment Plant, 0-9.6 0-9.6 Treatment Plants (33/36) NNW, 29 mi. (11/12) (11/12)

(pCi/l)

Gamma Isotopic 48 Be-7 124(d) NDM NDM NDM 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 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 2000 380.1 Beaufort-Jasper 444.5 136.1 16 192-701 County Water 212-530 51.4-190 (12/12) Treatment Plant, (4/4) (3/4)

SE, 76 miles Anadromous Fish Gamma Isotopic (pCi/kg-wet) 1 Be-7 655(d) NDM NDM 2014 VEGP Annual Radiological Environmental Operating Report 14 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-1. Radiological Environmental Monitoring Program Annual Summary Medium or Indicator Pathway Type and Total Minimum Locations Location with the Highest Sampled Number of Detectable Mean (b), Annual Mean Other Stations (f) Control Locations (Unit of Analyses Concentration Range Name Distance Mean (b), Range Mean (b), Range Mean (b), Range Measurement) Performed (MDC) (a) (Fraction) and Direction (Fraction) (Fraction) (Fraction)

Mn-54 130 NDM NDM Fe-59 260 NDM NDM Co-58 130 NDM NDM Co-60 130 NDM NDM Zn-65 260 NDM NDM Cs-134 130 NDM NDM Cs-137 150 NDM NDM Fish Gamma Isotopic (pCi/kg-wet) 4 Be-7 655(d) NDM NDM Mn-54 130 NDM NDM Fe-59 260 NDM NDM Co-58 130 NDM NDM Co-60 130 NDM NDM Zn-65 260 NDM NDM Cs-134 130 NDM NDM Cs-137 150 32.7 Savannah River, 13.9 13.9 27.8-37.7 N, 2.5 Miles 0-41.6 0-41.6 (2/3) (1/3) (1/3)

Sediment Gamma Isotopic (pCi/kg-dry) 4 Co-60 70(e) NDM NDM Cs-134 150 NDM NDM 2014 VEGP Annual Radiological Environmental Operating Report 15 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-1. Radiological Environmental Monitoring Program Annual Summary Medium or Indicator Pathway Type and Total Minimum Locations Location with the Highest Sampled Number of Detectable Mean (b), Annual Mean Other Stations (f) Control Locations (Unit of Analyses Concentration Range Name Distance Mean (b), Range Mean (b), Range Mean (b), Range Measurement) Performed (MDC) (a) (Fraction) and Direction (Fraction) (Fraction) (Fraction)

Cs-137 180 114.6 Savannah River 114.6 77.1 86.8-154.5 (RM 150.4), ENE, 86.8-154.5 65.9-88.3 (3/3) 0.8 miles (3/3) (2/2)

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.

(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) (NDM).

(d) The Georgia Power Company Environmental Laboratory has determined that this value may be routinely attained under normal conditions. No value is provided in ODCM Table 4-3.

(e) 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.

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

Not Applicable (sample not required) 2014 VEGP Annual Radiological Environmental Operating Report 16 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-2. Reporting Levels (RL)

Analysis Water (pCi/l) Airborne Particulate Fish (pCi/kg-wet) Milk Grass or Leafy or Gases (fCi/m3) (pCi/l) Vegetation (pCi/kg-wet) a H-3 20000 Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 Zn-65 300 20000 Zr-95 400 Nb-95 700 b

I-131 2 900 3 100 Cs-134 30 10,000 1000 60 1000 Cs-137 50 20000 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.

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 sampling (as described in Table 2-1) are summarized in Table 3-3 along with their causes and resolution.

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PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-3. Anomalies and Deviations from Radiological Environmental Monitoring Program Collection Period Affected Samples Anolmaly (A)* or Deviation Cause Resolution (D)**

01/14/14-01/28/14 Milk (D) Milk sample failed to Ice storm caused GPC lab to close Milk was resampled on CR 768165 Station 102 (Seven Oaks) meet MDC for several days. Milk sample hold 02/04/14 from Seven Oaks to time is typically <2 days. replace sample.

02/11/14-02/18/14 Air I, Air Part. (A) Low sample volume Loss of power to entire area due to Power restored to all CR 775962 Stations 3 (Discharge), 7 ice storm. stations. Sample volumes (Simulator), 12 (River were low but acceptable per Road), 35 (Girard), 36 GPCEL sampling procedure.

(Waynesboro) 02/11/14-02/18/14 Air I, Air Part. (D) No sample obtained Loss of power to entire area due to Power was not restored to CR 775962 Stations 16 (Hancock) ice storm. this station by the end of the sampling period. No sample obtained.

First half of 2014 Sediment (A) Unexpected isotope No apparent cause to presence of Very low levels; future CR 826087 River Station 1502 present in sample Co-58 in sediment. samples observed closely for presence of this isotope.

07/29/14-08/12/14 Milk (D) No samples obtained Milk trucks had completely drained No milk samples were Station 101 (Girard), 102 the milk tanks prior to arrival to obtained for this sampling (Seven Oaks) collect the samples. period.

An anomaly is considered a non-standard sample that still meets sampling criteria outlined in SNC and Georgia Power Labs procedures.

- A deviation is a sample result that is not recorded due to not meeting scheduling and/or procedural requirements as outlined by SNC and Georgia Power Labs 2014 VEGP Annual Radiological Environmental Operating Report 18 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 3.1 Airborne Particulates As specified in Table 2-1, airborne particulate filters and charcoal canisters are collected weekly at five 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 seven 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.

3.1.1 Gross Beta As provided in Table 3-1, the 2014 annual average weekly gross beta activity was 24.1 fCi/m3 for the indicator stations. It was 0.7 fCi/m3 more than the control station average of 23.4 fCi/m3 for the year. This difference is not statistically discernible, since it is less than the calculated MDD of 3.6 fCi/m3.

The 2014 annual average weekly gross beta activity at the Girard community station was 23.5 fCi/m3 which was 0.1 fCi/m3 more than the control station average. This difference is not statistically discernible since it is less than the calculated MDD of 8.7 fCi/m3.

Average Air Gross Beta historical data (Table 3-4) is graphed to show trends associated with a prevalent exposure pathway (Figure 3-1). 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.

Table 3-4. 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 2014 VEGP Annual Radiological Environmental Operating Report 19 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-4. Average Weekly Gross Beta Air Concentration Period Indicator Control Community (fCi/m3)

(fCi/m3) (fCi/m3) 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 2011 25.8 25.1 24.6 2012 25.9 25.2 26.1 2013 22.9 23.9 22.2 2014 24.1 23.4 23.5 Figure 3-1. Average Weekly Gross Beta Air Concentration 30 25 Concentration (fCi/l) 20 15 10 MD C

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 11 12 13 14 Year Indicator Community 2014 VEGP Annual Radiological Environmental Operating Report 20 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 3.1.2 Gamma Particulates During 2014, no man-made radionuclides were detected from the gamma isotopic analysis of the quarterly composites of the air particulate filters.

Historically, gamma isotopes have been detected as a result of offsite events. During pre-operation, Cs-134, Cs-137 and I-131 were occasionally detected. In 1987, Cs-137 was found in one indicator composite at a concentration of 1.7 fCi/m3. Additionally, I-131 was also detected after the Fukushima incident in 2011, the highest I-131 result in 2011 was 93.8 fCi/m3, which is approximately 10% of the RL.

3.2 Direct Radiation In 2014, direct (external) radiation was measured with Optically Stimulated Luminescent (OSL) dosimeters by placing two OSL badges at each station. The gamma dose at each station is reported as the average reading of the two badges. The badges are analyzed on a quarterly basis. 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 direct radiation stations are established in each of the 16 compass sectors, to form two concentric rings. The inner ring (Stations 1 through 16) is located near the plant perimeter as shown in Map A-1 in the appendix and the outer ring (Stations 17 through 32) is located at a distance of approximately five miles from the plant as shown in Map A-2 in the appendix. 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 six control stations (Stations 36, 37, 47, 48, 51 and 52) are located at distances greater than 10 miles from the plant as shown in Map A-3 in the appendix. Monitored special interest areas include Station 35 at the town of Girard and Station 43 at the employee recreational area. The mean and range values presented in the Other column in Table 3-1 includes the outer ring stations (stations 17 through 32) as well as stations 35 and 43.

As provided in Table 3-1, the 2014 average quarterly exposure at the indicator stations (inner ring) was 11.6 mR with a range of 5.6 to 17.7 mR. The indicator station average was 0.7 mR less than the control station average (12.3 mR). This difference is not statistically discernible since it is less than the MDD of 1.3 mR. Over the operational history, the annual average quarterly exposures shows a variation of no more than 0.7 mR between the indicator and control stations.

The quarterly exposures acquired at the community/other (outer ring) stations during 2014 ranged from 8.5 to 17.3 mR with an average of 12.0 mR which was 0.3 mR less than that for the 2014 VEGP Annual Radiological Environmental Operating Report 21 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT control stations. However, this difference is not discernible since it is less than the MDD of 1.1 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.

Average Direct Radiation historical data (Table 3-5) is graphed to show trends associated with a prevalent exposure pathway (Figure 3-2). 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.

Table 3-5. 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 2011 13.9 13.9 14.0 2012 14.4 14.3 14.2 2013 13.1 13.2 13.6 2014 11.6 12.3 12.0 2014 VEGP Annual Radiological Environmental Operating Report 22 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Figure 3-2. Average Quarterly Exposure from Direct Radiation 25 20 Indicator 15 Control Dose (mR)

Outer Ring 10 Hunting Cabin (Station 33)

Girard (Station 35) 5 Rec Center (Station 43) 0 Po 88 90 92 94 96 98 00 02 04 06 08 10 12 14 Year The increase shown in 2010 reflects issues with the aging Panasonic TLD reader. The close agreement between the station groups supports the position that the plant is not contributing significantly to direct radiation in the environment. Figure 3-3 provides a more detailed view of the 2014 values. The values for the special interest areas detailed below indicate that Plant Vogtle did not significantly contribute to direct radiation at those areas.

2014 VEGP Annual Radiological Environmental Operating Report 23 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Figure 3-3. 2014 Average Exposure from Direct Radiation 14.2 14 13.8 Concentration (mR) 13.6 13.4 13.2 13 12.8 12.6 12.4 12.2 3.3 Biological Media Cs-137 was the only radionuclide detected in two of the three biological media. As indicated in Figure 3-4, the Cs-137 activity levels are below the respective MDCs and well below that of the respective RLs for each sample media for both the indicator and control stations.

3.3.1 Milk In accordance with Tables 2-1 and 2-2, milk samples are collected bimonthly from two locations, the Girard Dairy (Station 101) which is considered an indicator station because it is approximately 5.5 miles from Vogtle (ideally a milk indicator station is less than 5 miles from the plant), and the Seven Oaks Dairy (Station 102) at 7.5 miles from Vogtle is the control location (ideally control locations are greater than 10 miles from the plant). SNC identified Milky Way Dairy as a replacement control location. The ODCM is in the process of being revised 2014 VEGP Annual Radiological Environmental Operating Report 24 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT to include the Milky Way Dairy for sampling. No milk animal was found within five miles of Plant Vogtle during the 2014 land use census.

Gamma isotopic (including I-131 and Cs-137) analyses were performed on each collected milk sample and there were no detectable results for gamma isotopes. Figure 3-4 provides the 2014 Cs-137 concentration in milk.

3.3.2 Vegetation In accordance with Tables 2-1 and 2-2, vegetation samples are collected monthly for gamma isotopic analyses at two indicator locations near the site boundary (Stations 7 and 15) and at one control station located about 17 miles WSW from the plant (Station 37). Cs-137 was detected (14.8 pCi/kg-wet) in a sample collected from the Simulator Building (Station 7). The man-made radionuclide Cs-137 is periodically identified in vegetation samples, and is generally attributed to offsite sources (such as weapons testing, Chernobyl, and Fukushima).

While Cs-137 and I-131 were periodically found and Co-60 was discovered once in vegetation samples during pre-operation, the historical trends and the relationship between the indicator and control stations demonstrate that plant operations are having no adverse impact to the environment. The sample results have consistently been well below the MDC and the RL for Cs-137 (80 and 2000 pCi/kg-wet, respectively).

During 2014, no other gamma isotopes were detected in any Vogtle REMP vegetation samples.

3.3.3 Fish Fish samples were collected in accordance with the ODCM (as indicated in Table 2-1). For the semiannual collections, the control location (Station 81) extends from approximately two to seven miles upriver of the plant intake structure, and the indicator location (Station 85) extends from about 1.4 to seven miles downriver of the plant discharge structure.

3.3.3.1 Anadromous Species For anadromous species, all fish sampled are considered indicator stations. Anadromous fish were sampled twice during 2014, on May 22 and December 5. No radionuclides were detected in the 2014 analyses, which is consistent with historical data.

3.3.3.2 Commercially or Recreationally Important Species For this year, as provided in Table 3-1, Cs-137 was found in the semiannual collections of commercially or recreationally important species of fish (indicator and control). The indicator station averaged a Cs-137 concentration of 32.7 pCi/kg-wet, and 13.9 pCi/kg-wet was the 2014 VEGP Annual Radiological Environmental Operating Report 25 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT average Cs-137 detected at the control station. The difference of 18.8 pCi/kg-wet between the indicator and control stations is not statistically significant since it is less than the MDD of 41.1 pCi/kg-wet. No discernible difference between the indicator and control stations has occurred for any year of operation or during pre-operation. No other gamma nuclides were discovered in 2014.

3.3.4 Biological Media Summary There were no statistical differences, trends, or anomalies associated with the 2014 biological media samples when compared to historical data. Figure 3-4 below, details the 2014 Cs-137 concentration compared to the Reportable Limits.

Figure 3-4. 2014 Biological Media Average Concentrations 2000 Indicator 1500 Control Concentration (pCi/kg) 1000 MDC Reportable Limit 500 0

Milk Vegetation Fish 3.4 Drinking Water Samples are collected at an upstream control location and at three downstream indicator locations (shown on Map A-3) and further described in Table 2-2.

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PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Water samples are taken near the intake of each water treatment plant (raw drinking water) using automatic composite samplers, which are collected monthly. Additionally, monthly grab samples of the processed water effluent from the treatment plants (finished drinking water) are collected. Monthly aliquots from the raw and processed drinking water are analyzed for gross beta and gamma isotopic activity. The monthly aliquots are also combined to form quarterly composites, which are analyzed for tritium.

For 2014, the indicator station average gross beta concentration in the raw drinking water was 2.77 pCi/l which was 0.87 pCi/l greater than the average gross beta concentration at the control station (1.90 pCi/l). This difference is not statistically discernible since it is less than the calculated MDD of 1.09 pCi/l. Historically, 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 2014, the indicator station average gross beta concentration in the finished drinking water was 2.21 pCi/l which was 1.09 pCi/l less than the average gross beta concentration at the control station (3.30 pCi/l). The MDD was not calculated because the control station was higher than the indicator station. Figure 3-5 show the relationship between the average indicator station and average control station for 2014 and the comparison to the MDC.

As provided in Table 3-1, there were no positive results during 2014 from the gamma isotopic analysis of the raw and finished drinking water samples. The 2014 raw drinking water indicator stations average tritium concentration was 371 pCi/l which was 234 pCi/l greater than the average concentration found at the control station (137 pCi/l). The difference between the station averages was greater than the MDD (156 pCi/l), which indicates a statistically discernible difference. However, given the small difference, historical trends, and the concentrations being less than the MDC and RL (2000 pCi/l and 20000 pCi/l, respectively), no adverse environmental impact is evident.

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.

The finished drinking water average tritium concentration at the indicator stations during 2014 was 381 pCi/l which was 245 pCi/l greater than the average concentration found at the control station (136 pCi/l). MDD was calculated as 229 pCi/l between the indicator and control stations, indicating a statistically significant difference. However the small difference and historical trends do not indicate environmental impact.

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PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Figure 3-5. 2014 Average Gross Beta Concentration in Raw and Finished Drinking Water 5

4.5 4

Concentration (pCi/l) 3.5 3

2.5 2

1.5 1

0.5 0

Raw Drinking Water Finished Drinking Water Indicator Control 3.5 River Water Composite river water samples are collected monthly at an upstream control location and at two downstream indicator locations (shown on Map A-3). The details of the sampling protocols are outlined in Tables 2-1 and Table 2-2. A gamma isotopic analysis is conducted on each monthly sample and the monthly aliquots are combined to form quarterly composite samples, which are analyzed for tritium.

As provided in Table 3-1, there were no positive results during 2014 from the gamma isotopic analysis of the river water samples. Also indicated in Table 3-1, the average tritium concentration found at the indicator station was 1399 pCi/l which was 1247 pCi/l greater than the average at the control station (152 pCi/l). The River Water tritium MDD was calculated to be 1195 pCi/l, which would indicate a value that is statistically discernible. Since the value is slightly above the MDD and below the MDC and the RL, no adverse environmental impact 2014 VEGP Annual Radiological Environmental Operating Report 28 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT exists. The MDC for tritium in river water used to supply drinking water is 2000 pCi/l and the RL is 20000 pCi/l.

At the Other river water sampling station (Station 84), the results ranged from 377 pCi/l to 940 pCi/l with an average of 607 pCi/l. The difference between the Station 84 and the control station was 521 pCi/l. The MDD was calculated to be 361 pCi/l, which would indicate a value that is statistically discernible. Since the value is slightly above the MDD and below the MDC and the RL, no adverse environmental impact exists. Historically, the relationship between the indicator and control stations, and Station 84 has remained consistent. Figure 3-6 below details the 2014 average tritium concentrations across the three water mediums.

Figure 3-6. 2014 Average Tritium Concentrations in River, Raw Drinking, and Finished Drinking Water 20000 Concentration (pCi/l) 15000 10000 5000 0

River Water Raw Drinking Special Indicator Control Water Finished Drinking Water 3.6 Sediment Sediment was collected along the shoreline of the Savannah River in the spring and fall 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 detected in 2014 samples were Be-7 and Cs-137. Even though Be-7 was detected in sediment, it has not been discussed within this report, because it was not detected in any plant effluents and likely represents naturally occurring and/or background conditions.

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PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT For Cs-137, the average concentration at the indicator station during 2014 was 114.6 pCi/kg-dry which was 37.5 pCi/kg-dry greater than that at the control station (77.1 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 66.6 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.

Co-58 was detected at a very low level (46.3 pCi/kg) in a sediment sample collected in May, 2014, from station 83 (approximately 0.8 miles downstream of the plant discharge) and will be monitored in the future. A review of plant effluents indicates that Co-58 is regularly released at very low levels. Co-58 is currently measured in both water and fish samples; however, if this isotope is consistently observed in subsequent sediment samples, it will be added to the Vogtle ODCM for future inclusion on the REMP. There are no reporting levels for sediment results.

3.7 Interlaboratory Comparison Program In accordance with ODCM 4.1.3, GPCEL participates in an Interlaboratory Comparison Program (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 ICP includes the required determinations (sample medium/radionuclide combinations) included in the REMP.

The ICP was conducted by Eckert & Ziegler Analytics, Inc. (EZA) of Atlanta, Georgia. EZA 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. EZA supplies the crosscheck samples to GPCEL which performs routine laboratory analyses. Each of the specified analyses is performed three times.

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. 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 on Table 3-6 below:

2014 VEGP Annual Radiological Environmental Operating Report 30 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-6. Interlaboratory Comparison Limits Nuclide Concentration

Total Sample Activity Percent Coefficient of (pCi) Variation

<300 NA 25 Cr-51 NA >1000 25

>300 <1000 15

<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).

As required by ODCM 4.1.3.3 and 7.1.2.3, a summary of the results of the GPCEL's participation in the ICP is provided in Table 3-7 for:

gross beta and gamma isotopic analyses of an air filter

gamma isotopic analyses of milk samples

gross beta, tritium and gamma isotopic analyses of water samples The 2014 analyses included tritium, gross beta and gamma emitting radio-nuclides in different matrices. The attached results for all analyses were within acceptable limits for accuracy (less than 15% coefficient of variation and less than 3.0 normalized deviations, except for Cr-51 and Fe-59, which are outlined in Table 3-6).

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PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-7. Interlaboratory Comparison Summary Analysis or Date Prepared Reported Known Value Standard Uncertainty Percent Coef of Normalized Radionuclide Average Deviation EL Analytics (3S) Variation Deviation I-131 ANALYSIS OF AN AIR CARTRIDGE (pCi/cartridge)

I-131 12/4/2014 102.5 98.4 1.8 1.64 5.05 0.8 GAMMA ISOTOPIC ANALYSIS OF AN AIR FILTER (pCi/filter)

Ce-141 12/4/2014 108 103 9 1.73 9.61 0.5 Co-58 12/4/2014 66 61.4 4.76 1.02 9.00 0.77 Co-60 12/4/2014 113 111 5.96 1.85 6.82 0.25 Cr-51 12/4/2014 200 192 9.22 3.2 8.42 0.48 Cs-134 12/4/2014 74.5 77.6 4.51 1.3 7.46 -0.55 Cs-137 12/4/2014 97.4 93.5 10.7 1.56 12.04 0.33 Fe-59 12/4/2014 83.3 82.4 8.01 1.38 11.41 0.09 Mn-54 12/4/2014 114 106 7.97 1.78 8.5 0.82 Zn-65 12/4/2014 153 140 18.4 2.34 13.25 0.62 GROSS BETA ANALYSIS OF AN AIR FILTER (PCI/FILTER)

Gross Beta 09/12/13 58.30 58.70 0.79 0.98 5.08 -0.14 GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (PCI/LITER)

Ce-141 6/12/2014 132 124 3.53 2.07 6.43 0.93 Co-58 6/12/2014 120 112 6.8 1.88 8.11 0.84 Co-60 6/12/2014 240 224 2.91 3.74 4.32 1.53 Cr-51 6/12/2014 269 253 13.3 4.23 12.91 0.47 Cs-134 6/12/2014 181 162 9.8 2.71 6.74 1.52 Cs-137 6/12/2014 130 120 4.6 2.00 7.09 1.06 Fe-59 6/12/2014 108 102 5.79 1.71 9.4 0.56 I-131 6/12/2014 99.2 90.9 4.25 1.52 7.58 1.10 Mn-54 6/12/2014 175 156 4.41 2.60 5.70 1.90 2014 VEGP Annual Radiological Environmental Operating Report 32 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-7. Interlaboratory Comparison Summary Analysis or Date Prepared Reported Known Value Standard Uncertainty Percent Coef of Normalized Radionuclide Average Deviation EL Analytics (3S) Variation Deviation Zn-65 6/12/2014 299 252 14.8 4.22 7.56 2.09 GROSS BETA ANALYSIS OF WATER SAMPLE (PCI/LITER) 3/20/2014 309 279 12.35 1.79 6.32 1.54 Gross Beta 12/4/2014 339 299 11.94 4.99 5.42 2.20 GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (PCI/LITER)

Ce-141 3/20/2014 74.9 77.1 6.05 1.29 11.96 -0.24 Co-58 3/20/2014 173 174 7.87 2.9 7.03 -0.12 Co-60 3/20/2014 221 219 6.12 3.65 5.22 0.15 Cr-51 3/20/2014 334 319 17.7 5.32 12.47 0.36 Cs-134 3/20/2014 142 136 5.6 2.28 6.00 0.70 Cs-137 3/20/2014 169 164 11.1 2.74 8.52 0.35 Fe-59 3/20/2014 142 142 7.55 2.37 8.64 -0.02 I-131 3/20/2014 91.8 89.9 3.86 1.5 8.34 0.25 Mn-54 3/20/2014 202 193 11.7 3.22 7.61 0.56 Zn-65 3/20/2014 221 210 10.1 3.5 8.06 0.61 TRITIUM ANALYSIS OF WATER SAMPLES (PCI/LITER) 3/20/2014 9820 10000 157.6 167 2.71 -0.69 H-3 12/4/2014 14800 14900 127.53 249 2.18 -0.46 2014 VEGP Annual Radiological Environmental Operating Report 33 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 3.8 Groundwater To ensure compliance with NEI 07-07 (Industry Ground Water Protection Initiative - Final Guidance Document), 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 robust buried piping and tanks inspection programs.

Plant Vogtle maintains the following wells (Table 3-8), which are sampled at a frequency that satisfies the requirements of NEI 07-07. The analytical results for 2014 were all within regulatory limits specified within this report.

Table 3-8. Groundwater Monitoring Locations 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 building and NSCW 805A** Water Table related facilities 806B Water Table Dilution line 808 Water Table Up gradient; along Pen Branch Fault R1 Water Table NSCW related tank; western potential 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 R8 Water Table within Sav. River sediments Dilution line 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 2014 VEGP Annual Radiological Environmental Operating Report 34 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Table 3-8. Groundwater Monitoring Locations Well Aquifer Monitoring Purpose 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

Well abandoned due to construction activities with Vogtle Units 3&4

- Well no longer sampled due to structural issues 2014 VEGP Annual Radiological Environmental Operating Report 35 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 4 SURVEY SUMMARIES 4.1 Land Use Census In accordance with ODCM 4.1.2, a land use census was conducted on November 25, 2014 to verify the locations of the nearest radiological receptor within five miles. The census results, shown in Table 4-1, indicated no changes from 2013; therefore, no changes to the ODCM are required.

Table 4-1. Land Use Census Results Sector Residence Milk Animal* Beef Cattle Garden**

Distance in Miles to the Nearest Location in Each Sector 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 4.3 None 4.9 None SSE 4.7 None 4.7 None S 4.4 None 4.3 None SSW 4.7 None 4.6 None SW 3.1 None None None WSW 2.6 None 2.7 None W 3.4 None 4.4 None WNW 1.9 None None None NW 1.5 None None None NNW 1.5 None None None

A milk animal is a cow or goat producing milk for human consumption.

- A garden of greater than 500 square feet producing broad leaf vegetation.

Note: Land within SRS was excluded from the census.

4.2 Savannah River Survey A survey of the Savannah River downstream of the plant for approximately 100 miles (approximately river miles 44.7 to 151.2) was conducted on September 16, 2014 to identify any new withdrawal of water from the river for drinking, irrigation, or construction purposes. No 2014 VEGP Annual Radiological Environmental Operating Report 36 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT new usage was visually identified. These results were verified with the South Carolina Department of Health and Environmental Control on October 2, 2014, and the Georgia Department of Natural Resources on October 6, 2014. 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. It should be noted that Vogtle Units 3 and 4 received a surface water withdrawal permit in December of 2014.

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PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 5 CONCLUSIONS This report confirms SNCs conformance with the requirements of Chapter 4 of the ODCM and the objectives were 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 VEGP.

Based on the 2014 activities associated with the REMP, SNC offers the following conclusions:

Samples were collected and there were no deviations or anomalies that negatively affected the quality of the REMP

Land use census and river survey did not reveal any changes

Analytical results were below reporting levels

These values are consistent with historical results, indicating no adverse radiological environmental impacts associated with the operation of VEGP 2014 VEGP Annual Radiological Environmental Operating Report 38 l P a g e

PLANT VOGTLE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT APPENDIX Maps 2014 VEGP Annual Radiological Environmental Operating Report Appendix

W SW NW S N 5 Miles SE NE E

Legend: Drawn by: C. Groce Appendix A Vogtle Electric Genera ng Plant Map A1 Indicator Sta ons 2014 Annual Radiological Environmental Report Control Sta ons REMP Sta ons in Plant Vicinity April 30, 2015 Other Sta ons

N 5 Miles 10 Miles Legend: Drawn by: C. Groce Appendix A Vogtle Electric Genera ng Plant Map A2 Indicator Sta ons 2014 Annual Radiological Environmental Report Control Sta ons REMP Sta ons within 10 miles April 30, 2015 Other Sta ons

10 Miles Legend: Drawn by: C. Groce Appendix A Vogtle Electric Genera ng Plant Map A3 Indicator Sta ons 2014 Annual Radiological Environmental Report Control Sta ons Extended REMP Sta ons April 30, 2015 Other Sta ons

Legend: Drawn by: C. Groce Appendix A Vogtle Electric Genera ng Plant Map A4 Surficial Aquifer 2014 Annual Radiological Environmental Report Ter ary Aquifer Facility Groundwater Wells April 30, 2015

NL-15-0877, Submittal of Annual Radiological Environmental Operating Reports for 2014

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