View source for NL-16-0741, Annual Radiological Environmental Operating Report for 2015 - Page 1 of 2

{{Adams
| number = ML16145A377
| issue date = 05/16/2016
| title = Annual Radiological Environmental Operating Report for 2015 - Page 1 of 2
| author name = Pierce C
| author affiliation = Southern Nuclear Operating Co, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000321, 05000348, 05000364, 05000366, 05000424, 05000425
| license number = 
| contact person = 
| case reference number = NL-16-0741
| document type = Environmental Monitoring Report, Letter type:NL
| page count = 86
}}

=Text=
{{#Wiki_filter:Charles R. Pierce                Southern Nuclear Regulatory Affairs Director      Operating Company, Inc.
40*1nverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992 .7872                      SOUTHERN ._\
Fax 205 .992.7601 NUCLEAR A SOUTHERN COMPANY MAY 1 6 2016 Docket Nos .:       50-321     50-348      50-424                          NL-16-0741 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 2015 Lad ies 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 2015.
This letter contains no NRC commitments . If you have any questions, please contact Ken McElroy at (205) 992-7369 .
C. R. Pierce Regulatory Affairs Director CRP/RMJ

U. S. Nuclear Regulatory Commission NL-16-0741 Page 2

==Enclosures:==
: 1. Hatch Annual Radiological Environmental Operating Report for 2015
: 2. Farley Annual Radiological Environmental Operating Report for 2015
: 3. Vogtle Annual Radiological Environmental Operating Report for 2015 cc:   Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, 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 Ms. C. Haney, Regional Administrator Mr. S. A. Williams, NRR Project Manager - Farley Mr. D. H. Hardage, Senior Resident Inspector - Hatch Mr. W. D. Deschaine, Senior Resident Inspector - Vogtle 1 & 2 Mr. P. K. Niebaum, Senior Resident Inspector - Farley Mr. R. E. Martin, NRR Project Manager - Vogtle 1 & 2 Mr. A. M. Alen, Resident Inspector - Vogtle 1 & 2 Mr. M. D. Orenak, NRR Project Manager - Hatch 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 2015 Enclosure 1 Hatch Annual Radiological Environmental Operating Reports for 2015

EDWIN le. HATCH NUCLEAR PLANT 2015 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SOUTHERN << \
NUCLEAR A SOUTHERN COMPANY

LANT      A   H                                                                                                            NNUAL                  ADIOLOGICAL RT EDWIN I. HATCH NUCLEAR PLANT 2015 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE OF CONTENTS 1       lntroduction .. ... ........... .......... ....................................... ...................... .......... . 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      lnterlaboratory Comparison Program ..... ... .......................................................... 23 3.7      Groundwater .. .... .. ... .. .. .... .. ......... .. ........... .......... ........ ............................................ 27 4       Survey Summaries ..... .. ............................................................................... 30 4.1      Land Use Census ... .. .... ... .......... ... ........... ........ .. .................. .. ... ......... ... ...... .... .. ...... 30 4 .2     Altamaha River Survey ........... ................. .............. .... ..... .. ........ ....... .. ............ .... .... 30 5       Conclusions ............. .................................................................................... 32 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. lnterlaboratory Comparison Limits ........ ... .. ........ .. ......................................................... ...... .. ... 24 2015 HNP !A.nnual Radiological Environmental Operating Report                                                                        I i lP age

PLANT            c                                                                                             NNU L ADIOLOGICAL Table  3-7. lnterlaboratory Comparison Summary .. ........ ....... ..... .. ...... .. ... ... ............ ................. ..... ... .......... 25 Table  3-8 . Groundwater Monitoring Locations .. ... ...... .. .......... .... .. ....... .... .. ................ .... .. .......... ...... ... .. .... 27 Table  3-9 . Groundwater Monitoring Results ....... .. ...... .... .... ................. .. ........... ... ..... ....... ... .. .. .... ... ....... .... 28 Table  4-1. Land Use Census Results ... .......... ... ............................................ .. ....... ........... .. ........ ................. 30 Table  4-2 . Special Sample Results (Peanuts) ........................................... ......... .. .. .............. .. .. .......... .......... 31 Figures Figure 3-1. Average Weekly Gross Beta Air Concentration ... ....... ..... .. ........ ....... .. ..... .. ........ .. ............. .... .. .. 16 Figure 3-2 . Average Quarterly Exposure from Direct Radiation ................. .. .. ...... ........ .. .. ..... .... ........... ... ... 19 Figure 3-3. 2015 Average Exposure from Direct Radiation ....................... .................................. ........... ... . 20 Figure 3-4 . 2015 Biological Media Average Concentrations .................. .. ............. ........ .... .... .. ........ ........ .... 22 Figure 3-5. Average Annual Tritium Concentrations in River Water ......... ..... ... ... ....... .... .. ......... .. ..... .. .... ... 23 Appendix A - Maps A REMP Stations in Plant Vicinity A REMP Stations within 5 Miles A Facility Groundwater Wells Appendix B - Errata Groundwater Protection Results from 2014 Report 2015 HNP Annual Radiological Environmental Operating Report                                        1 ii I P age

PL   NTH TC                                                       ANNUAL    ADIOLOGICAL PERATING    E ORT 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 GA EPD     State of Georgia Environmental Protection Division GPC        Georgia Power Company GPCEL      Georgia Power Company Environmental Laboratory HNP        Edwin I. Hatch Nuclear Plant ICP        lnterlaboratory Comparison Program MDC        Minimum Detectable Concentration MOD        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 2015 HNP Annual Radiological Environmental Operatihg Report       iii IPage I

PLANT      ATCH                                                         ANNUAL RADIOLOGICAL ENVI                   PERATING      EPORT 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 2015 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 preope rat ional 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 as well as the results from the interlaboratory comparison
* A summary of the land use census and the river survey are included in Section 4
* Conclusions are included in Section 5 2015 HNP Annual Radiological Environmental Operating Report           ll P age

L NT        c                                                           NNUAL ADIOLOGICAL 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 Appendix A of this report .
Georgia Power Company's Environmental Laboratory (GPCEL), located in Smyrna, Georgia collects and analyzes REMP samples .
~'
2015 HNP Annual Radiological Environmental Operating Report      2 1P age I

PLANT      ATCH                                                                        NNUAL RADI LOGIC l                 NVIRONMENT l 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     Qua rterly                                         Gamma dose, quarterly stations Airborne Radioiodine Samples from six          Continuous sampler operation with sample           Radioiodine canister: 1-131 analysis, weekly and Particulates     locations :               collection weekly Particulate sampler : analyze for gross beta radioactivity not less than 24 hours following filter change, weekly; perform gamma isotopic analysis on affected samp le when gross beta activity is 10 times the yearly mean of control samples; and compo site (by locati on) 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       Rive r water collected near the intake will be a   1-131 analysis on each sample when biweekly water near the intake and composite sample; the finished water will be a     coll ect ion s are required . Gross beta and gamma one sample of finished    grab sample . These samples will be collected      isotopic analysis on each sa mple; 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 rT"he collections may revert to monthly should the discharges.               calculated doses become less than 1 mrem/year.
2015 HNP Annual Radiological Environmental Operating Report                                              3 I Page

LANT       A C                                                                        NNU l          ADI l Gtc              NVIR N ENT l 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- Quarte rly 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 rad ionuclides as necessary based on results of tritium and gamma .
2 Shoreline Sediment           Two                      Semiannually                                           Gamma isotopic analysis    , semiannually Ingestion 5                                                                                                                             27 M ilk                       On e                      Bimonthly                                             Gamma isotopic analysis    ' , bimonthly 0                                                                                                                   2 Fish or Clams               Two                      Semiannually                                           Gamma isotopic analysis on edible portion s, semian nually 27 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 facility.
3 1f it is found that river water downstream of the plant is used for drinking, drinking water sam ples will be collected and analyzed as specified herein .
14 A survey shall be conducted annually at least 50 river mile s downstream of the plant to identify those who use water from the Altamaha River for drinking.
15 up to three sampling locations within five miles and in different sectors will be used as available. In addition, one or more con t rol locations beyond 10 miles will be used .
16commercially or recreationally important fish may be sampled . Clams may be sa mpled if diffi culties are encountered in obtaining su fficient fish samples.
7 1f the gamma isotopic analysis is not se nsitive enough to meet the Minimum Detectabl e Concentrati on (MDC) for 1-131, a separate analysis for 1-131 may be performed.
2015 HNP Annual Radiological Environmental Operating Report                                             4 1P age

PLANT HATC                                   NNUAL RA IOLOGIC . l ENVI *ONME T l Table 2-2. Radiological Environmental Sampling Locations 1
Station  Station  Descriptive Location Direction    Distance        Radiation Sample Type 1
Number    Type                                      (miles) 064      Othe r     Roadside Park       WNW           0.8                    Direct 101   Indicator      Inner Ring            N         1.9                    Direct 102   Indicator      Inner Ring         NNE          2.5                    Di rect 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, Dire ct 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      Inn er Ring          w          1.1                    Direct 114   Indicator      Inner Ring        WNW           1.2                    Direct 115   Indicator      Inn er Ring         NW          1.1                    Direct 116   Indicator      Inn er 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     Oth er      Outer Ring          NNW          4.8                    Direct 2015 HNP Annual Radiological Environmental Operating Report                SI P age

LANT          CH                              ANNUAL RADIOLOGlC L ENVIRONM                          TAL T
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 Pri son           ENE          10.3                        Milk Ba xley 309       Control Substation s           10.0                 Airborne, Direct 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 approximate ly 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 .
::>tation 172 is located approximately 3.0 river miles downstream of the discharge structure for river water, sed iment and clams, and 1.7 river miles for fish .
The location s from which river water and sedim ent may be taken can be sharply defined. However, the sam pling locations for clams often have to be extended over a wide area to obta in a sufficient quantity. High water adds to the difficulty in obtaining clam sa mples 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 approxi mations of the location s where
,,amples are collected.
3 River (fish or clams, shoreline sediment, and surface water) 2015 HNP Annual Radiological Environmental Operating Report                          6I P age

PLA T        A CH                          ANNUAL      ADIOLOGIC L NVI ONMENTAL OPE                 RT 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, 885 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 plant's liquid and gaseous effluents . When it is detected in effluents and REMP samples, it is also included in the REMP results . In 2015, 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 (MOD), and Chauvenet's 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.
2015 HNP Annual Radiological Environmental Operating Report I         71 Page I

LA T      A CH                            NNUAL   R     IOLOGI       L NVIRONMENTAL Minimum Detectable Difference The Minimum Detectable Difference {MOD) 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 MOD was considered to be statistically indiscernible.
ChauvenersCriterion All results were tested for conformance with Chauvenet 's criterion {G . D. Chase and J. L.
Rabinowitz, Principles of Radioisotope Methodology, Burgess Publ ishing 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 2015 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 Chauvenet's criterion .
2015 HNP Annual Radiological Environmental Operati rlg Report         S f Page

LANT HATCH                                                                                                       NUAL      ADIOLQGtCAL 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       19.l              State Pri son       20                                 19.6 Particulates      312                                   4-40.4            ENE 11.2 Mi les     2.3-35 .9                          2.3-35 .9 (fCi/m3)                                                (208/208)                             (52/52)                            (104/104)
Gamma Isotopic 24 1-131                 70              NDM(c)                                NDM                                NDM Cs-134                so              NDM                                   NDM                                NDM Cs-137                60              NDM                                   NDM                                NDM Airborne          1-131                 70              NDM                                   NDM             NDM                NDM Radioiod ine      312 (fCi/m3)
Direct Radiati on Gamma Dose                            12.l              Outer Ring          16.4            12.1               11.7 (mR/91 days)      148                                   9.4-17.4          WNW 5.4 mi.         14.3-16.2       8.6-16.9          9.8-14.2 (64/64)                               (4/4)           (72/72)            (12/12)
Milk (pCi/I)      Gamma Isotopic 24 1-131                 1                                                     NDM                                NDM Cs-134                15                                                    NDM                                NDM Cs-137                18                                State Prison        0.78-0.78                         0.78-0.78 ENE 10.3 Miles      (1/24)                             (1/24)
Ba-140                60                                                    NDM                                NDM La-140                15                                                    NDM                                NDM Vegetation        Gamma Isotopic (pCi/kg-wet)      36 1-131                 60              NDM                                                                      NDM 2015 HNP Annual Radiological Environmental Operating Report                                       9 1P age

PLANT HATCH                                                                                                    NUAL       ADtQLOGlCAl PE RATING
                                . ..       *
* I e I :                         :
* I : "
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                                                                   NDM Cs-137                 80                135.2           Inn er Ring    ESE  149.7                             NDM 16.2-376.2      1.1 mi.             16.2-376.2 (9/24)                              (8/12)
Riv er Water  Gamma Isotopic (pCi/I)       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 1-131                  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)          200             Downstream E        200                               17.5 8                                        200-200         3.0 RM from         200-200                           17.5-17.5 (1/4)           intake              (1/4)                             (1/4)
Fish          Gamma Isotopic (pCi/kg-wet)  4 2015 HNP Annual Radiological Environmental Operating Report                                     10 IP age

PLA T ATCH                                                                                                                            NU L ADtOL GlCAL ENVIRONME                  PE RATING
                                            . ..         .. .. I :                                :
* I :
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               NDM                                                                               NDM Sediment              Gamma Isotopic (pCi/kg-dry)          4 Cs-134                     150               NDM                                                                               NDM Cs-137                     180               40.5                 Upstream WNW          84.0                                   84.0 28.9-52 .0           1.1 RM from           79 .6-88 .5                            79 .6-88.5 (2/2)                inta ke               (2/2)                                  (2/2)
Notes:
(a)The MDC is defined in ODCM 10.1. Except as noted otherwise, the value s listed in this column are the detection capabil ities required by ODCM Table 4-3.
The values listed in this co lumn are a priori (before the fact) MDCs. In practice, the a posteriori (after the fact) MDCs are generally lower than the value s 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 lpCi/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 re qu ired )
-- ~                                           2015 HNP Annual Radiological Environmental Operating Report                                                    ll lP age

LANT HATCH                                              NNUAL RADIOLOGICAL               NVIRONME TAL OPERATING Table 3-2. Reporting Levels (RL)
Analysis      Water (pCi/I)  Airborne Particulate   Fish (pCi/kg-wet)       Milk          Grass or Leafy or Gases (fCi/m3)                            (pCi/I)    Vegetation (pCi/kg-wet)
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 1-131            2b                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
* 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/I 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.
2015 HNP Annual Radiological Environmental Operating Report                          12 1P age

PLANT HATCH                                                                                                                     NUAL      ADIOLOGICAL ENVIRON       E TAL     0   ERATING Table 3-3. Anomalies and Deviations from Radiological Environmental Monitoring Program Collection Period          Affected Samples           Anolmaly (A)* or Deviation                    Cause                            Resolution (D)**
No program deviations were identified in the Hatch Radiological Environmental Monitoring Program during 2015.
* An anomaly is considered a non-standard sample that stil l meets sampl ing criteria outlined in SNC and Georgia Powe r 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 2015 HNP Annual Radiological Environmental Operating Report                               13j Page

PLANT      A CH                                                      ANNUAL RADIOL GI AL NVIRONMEN AL                             RT 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 sampling locations containing a filter and cartridge series, 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 2015 annual average weekly gross beta activity was 19.l fCi/m3 for the indicator stations . It was 0.5 fCi/m3 less than the control station average of 19.6 fCi/m3 for the year. This difference is not statistically discernible, since it is less than the calculated MOD of 4.1 fCi/m3.
Avera ge 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 2015 HNP Annual Radiological Environmental Operating Report                   14 I Page

PLANT A CH                                                     NNUAL      RA     IOLOGICAL ERA.TING 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 2015                          19 .1                                19 .6 2015 HNP Annual Radiological Environmental Operating Report 1               15 I Page

LANT    A CH                                                    ANNUAL     A IOLOGICAL Figure 3-1. Average Weekly Gross Beta Air Concentration 3.1.2 Gamma Particulates During 2015, 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 2015, 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.
I Page A '. I 2015 HNP Annual Radiological Environmental Operati ng Report           16

LANT HA CH                                                         NNUAL     ~ADIOLOGICAL NMENTAL      PERATING       EPORT 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 Appendix A 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 Appendix A. 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 2015 average quarterly exposure at the indicator stations (inner ring) was 12.1 mR with a range of 9.4-17.4 mR. The indicator station average was 0.4 mR more than the control station average (11.7 mR) . This difference is not considered statistically discernible since it is less than the MOD of 1.1 mR.
The quarterly exposures acquired at the community/other (outer ring) stations during 2015 ranged from 8.6 to 16.2 mR with an average of 12.1 mR which was 0.4 mR more than that for the control stations. However, this difference is not discernible since it is less than the MOD 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 1979                    5.16                  6.77                   NA 2015 HNP Annual Radiological Environmental Operating Report               171 Page

LA THATCH                                                      NNUAL ENVIRONMENTAL Table 3-5. Average Quarterly Exposure from Direct Radiation Period               Indicator              Control               Outer Ring (mR)                   (mR)                  (mR) 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 2015                  12 .1                  11.7                  12 .1 2015 HNP Annual Radiological Environmental Operating Report                18 I Page

LANT        TCH                                                   ANNUAL RADIOLOGI        l ENVIRONMENT l Figure 3-2. Average Quarterly Exposure from Direct Radiation ifoomos Central Scliool (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 2015 values. The values for the special interest areas detailed below, indicate that Plant Hatch did not significantly contribute to direct radiation at those areas.
2015 HNP Annual Radiological Environmental Operating Report           19 I Page

LANT     ATCH                                                    ANNUAL    ADIOLOGICAL NVIRONMENTAL Figure 3-3. 2015 Average Exposure from Direct Radiation 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 2015 land census did not identify a milk animal within five miles of the plant.
2015 HNP Annual Radiological Environmental Operating Report          20 I Page

LANT HATCH                                                       ANNUAL ADIOLOGICAL NVIRONMENT l Gamma isotopic (including 1-131 and Cs-137) analyses were performed on each collected milk sample and there were no detectable results for gamma isotopes, with the exception of a single detection of Cs-137 (0.78 pCi/L) in November 2015. Figure 3-4 provides the 2015 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 nine of the 24 samples collected at the indicator stations. The average of the samples was 135.2 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 1-131 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 below the MDC and the RL for Cs-137 {80 and 2000 pCi/kg-wet, respectively).
During 2015, no other man-made gamma isotopes were detected in any Hatch 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 not 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 2015 biological media samples when compared to historical data . Figure 3-4 below, details the 2015 Cs-137 concentration compared to the Reportable Limits.
2015 HNP Annual Radiological Environmental Operating Report            21 I Page

LANT     ATCH                                                       NNUAL      ADIOLOGICAL NVIRONMENT L Figure 3-4. 2015 Biological Media Average Cs-137 Concentrations
* Indicator
* Control
* MDC 1000 1Reportable Limit 500 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 Appendix A} . 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 2015 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 200 pCi/I which was 182.5 pCi/I more than the average at the control station (17 .5 pCi/I}. No MDD was calculated because only one of the four samples for both the indicator and control stations indicated any concentration. Historically, the relationship between the indicator and control stations has remained consistent. Figure 3-5 below details the 2015 historical average tritium concentrations in river water.
2015 HNP Annual Radiological Environmental Operating Report              22 I Page

LANT       TCH                                                     ANNUAL       ADIOLOGICAL ERATING Figure 3-5. Average Annual Tritium Concentrations in River Water 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 (slightly above 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     lnterlaboratory Comparison Program In accordance with ODCM 4.1.3, GPCEL participates in an lnterlaboratory 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.
2015 HNP Annual Radiological Environmental Operating Report               23 I Page

LA T       TC                                                                        A   NUAL        ADIOLOGICAL 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. lnterlaboratory 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/I) .
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 2015 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).
2015 HNP Annual Radiological Environmental Operating Report                                      24  I Page

PLANT HATCH                                                                                              NNUAL RADIOL GIC l Table 3-7. lnterlaboratory Comparison Summary Analysis or Date Prepared  Reported         Known Value        Standard         Uncertainty    Percent Coef of Normalized Radionuclide                 Average                           Deviation EL      Analytics (3S)    Variation     Deviation 1-131 ANALYSIS OF AN AIR CARTRIDGE (pCl/cartridge) 1-131      9/10/2015       85.4               82.0             1.37               1.37            5.79          0.69 GAMMA ISOTOPIC ANALYSIS OF AN AIR FILTER (pCi/filter)
Ce-141      9/10/2015       92 .7              85.5             4.36               1.43             7.5           1.03 Co-58      9/10/2015        114               106              5.28               1.76             5.6           0.9 Co-60      9/10/2015        139               132              5.38               2.21              5            0.37 Cr-51      9/10/2015        226               216             16.66               3.61             9.6           0.45 Cs-134      9/10/2015       85.3               84.9             3.37               1.42             5.4           0.08 Cs-137      9/10/2015        111               102                 5               1.71             6.5            1.2 Fe-59      9/10/2015       96.7               90.5              5.5               1.51             6.2           0.91 Mn-54      9/10/2015        133               116               5.82              1.94              6            2.09 Zn-65      9/10/2015        164               142              8.46               2.37             7.3           1.85 GROSS BETA ANALYSIS OF AN AIR FILTER (PCl/FILTER)
Gross Beta   9/10/2015        103               96 .3             3.66              1.61             5.9           1.44 GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE PCl/LITER)
Co-58      6/11/2015       77.7               68.4              5.92              1.14           10.92            1.1 Co-60      6/11/2015        203               193               8.29              1.06            4.52           1.12 Cr-51      6/11/2015        295               276              33.19              4.61            12.3           0.53 Cs-134     6/11/2015        184               163               6.93              2.72            5.02           2.28 Cs-137     6/11/2015        144               125               7.77              2.09            7.38           1.75 Fe-59      6/11/2015        163               151              10.07              2.53            6.94           1.03 1-131     6/11/2015        105               95.9              6.91               1.6              8            1.04 Mn-54      6/11/2015        115               101                6.9              1.68            7.31           1.62 Zn-65      6/11/2015        282               248              15.62              4.15             7.3           1.64 2015 HNP Annual Radiological Environmental Operating Report                           25  I Page

LANT       ATCH                                                                                     A    NUAL ADIOLOGIC l ENVIRONMENTAL OPERATING REPO T Table 3-7. lnterlaboratory Comparison Summary Analysis or     Date Prepared  Reported        Known Value        Standard      Uncertainty    Percent Coef of Normalized Radionuclide                    Average                          Deviation EL   Analytics (3S)    Variation     Deviation GROSS BETA ANALYSIS OF WATER SAMPLE (PCl/LITER) 3/19/2015        319              281              10.5            4.69            4.56           2.59 Gross Beta 6/11/2015        290              248              10.2            4.15            4.68            3.1 GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (PCl/LITER)
Ce-141         3/19/2015       135.7            139.2             8.44            2.32            7.97           -0.3 Co-58          3/19/2015        183              180              9.32              3             6.76           0.24 Co-60          3/19/2015       325.3             328             12.73            5.48            5.61          -0.15 Cr-51         3/19/2015       399.1             366             38.04            6.11           17.12           0.48 Cs-134         3/19/2015       131.1             126              5.81             2.1            9.49           0.41 Cs-137         3/19/2015        175              167                9             2.78            7.49            0.6 Fe-59         3/19/2015        203              195             11.63            3.25            7.01           0.56 1-131         3/19/2015       100.5             96.7             7.16            1.61            9.24           0.41 Mn-54          3/19/2015        170              159              8.97            2.65            7.78            0.8 Zn-65          3/19/2015        328              299             17.26            4.99            7.61           1.15 TRITIUM ANALYSIS OF WATER SAMPLES (PCl/LITER) 3/19/2015      12104             12600              140            210             3.14          -1.31 H-3 6/11/2015      12700             13000              148            217             2.11          -0.95 2015 HNP Annual Radiological Environmental Operating Report                       26  I Page

LANT      TCH                                                             NNUAL    ADIOLOGIC L EPORT 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 woundwater, SNC plants have established robust buried piping and tanks inspection programs. No changes were made to the Groundwater Protection Program in 2015.
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 2015 were all within regulatory limits specified within this report. Table3-9 contains the results of the Groundwater Protection Program tritium results (in pCi/L). See Map A-4 in Appendix A for well locations.
Rl           82 .9      Confined Aquifer Upgrad ient R2          82 .7       Confined Aquifer Near Diesel Generato r Bldg.
R3          89.2        Confined Aquifer Near CST-1 R4            41        Dilution Line Near River Water Discharge Structure RS          33 .6       Between Subsurface Drain Lines Downgrad ient R6          38 .2       Between Subsurface Drai n Lines Downgrad ient NW2A            27          ater Table Near CST-2 In side of Subsurface Dra in NW2B            27          ater Table Outs ide of Subsurface Dra in NW3A          26.5          ater Table Inside of Subsurface Drain NW3B          25 .3         ater Table Outside of Subsurface Drain NW4A            27          ater Table Upgradient Inside of Subsurface Drain NWSA          26 .7         ater Table Upgradient Inside of Subsu rface Drain NWSB          26.3          ater Table Upgradient Outside of Subsurface Drain NW6             27          ater Table Near Diesel Generator Bldg.
NW8             23          ater Table Near Diesel Generator Bldg.
NW9           26.1          ater Table Downgradient Inside of Subsurface Drain NWlO          26 .2         ater Table Near CST-2 T3             18          ater Table Near Turbine Bldg.
T7           21.4          ater Table Near Diesel Generator Bldg.
TlO          18.8          ater Table Near CST-1 2015 HNP Annual Radiological Environmental Operating Report                  27 I Page

LANT     ATCH                                                             ANNUAL RADIOLOGICAL EPORT ater Table Near CST-1 PlSA           74.5 PlSB           18              ater Tab le Near Turbine Bldg.
P17A*           77             onfined Aquifer Near Diesel Generator Bldg.
P17B           14.8             ater 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 Table 3-9. Groundwater Protection Pro ram Tritium Results               . L
:*1*r:****               i****r.:***"'         ,.*aur:1*1*         '**a**Jn:1*1'"'
Rl                 12.6                     NDM                     220                     286 R2               NDM                       NDM8                     66 .1                   370 R3               1040                         961                  1320                    1430 R4               NDM                          120                   12.3                  NDM RS               17400                     18600                  12600                   8400 R6                88.5                        324                   161                    326 NW2A                 153                       491                    500                    272 NW2B                 154                        199                  NDM                    NDM NW3A                17.4                      NDM                    NDM                     52 .7 NW3B                 105                       327                   NDM                     101 NW4A                 111                       135                   41.3                    325 NWSA                 159                       218                   83.1                    288 NWSB                 125                       89.1                  75 .8                  NDM NW6                  100                       297                    285                    184 NW8                   NS                        NS                     NS                    298 NW9                 57 .5                      484                    477                   NDM NWlO               9540                       8620                 10000                    6140 T3               7260                       3200                   1370                   1720 T7                 19.9                       235                    224                    273 TlO              14100                      18600                 23300                   19900 T12              18300                      18300                  7290                    8190 TlS                 911                      2810                    941                   1910 Pl SA              NDM                         91.6                  45.2                    195 2015 HNP Annual Radiological Environmental Operating Report                         28   I Page

LANT       TCH                                                      NNUAL RADIOLOGICAL NS - Not enough P15B                                    2440                3270                1900 water to sample P17A                135                  106                NDM                 NDM P17B                132                  173                 545                423 Deep Well 1     NS - Out of Service NS - Out of Service NS - Out of Service NS - Out of Service Deep Well 2           NDM                  NDM                 NDM                 NDM Deep Well 3            81.2                NDM                 NDM                 113 Plant Hatch has had historic tritium leaks into the perched aquifer from around the Unit 1 Condensate Storage Tank (CST), documented on 10 CFR 50.75(g) records. The tritium values in the wells that were found to be elevated above MDC were from previous CST and related piping leaks and are not considered present issues. Historic leaks and spills are reported in accordance with NEI 07-07.
2015 HNP Annual Radiological Environmental Operating Report             29 I Page

PLANT HATCH                                                           NNUAL     ADIOLOGICAL ENVIRONMENTAL                           T 4 SURVEY SUMMARIES 4.1      Land Use Census In accordance with ODCM 4.1.2, a land use census was conducted on November 9, 2015 to verify the locations of the nearest radiological receptor within five miles. The census results, shown in Table 4-1, indicated no major changes from 2014; therefore, no changes to the ODCM are required . Residents were located in each sector as identified below; no resident was identified closer than the current closest resident.
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           2.0             None              None               4.2            3.8 NNE           2.9             None              None               4.7           None NE           3.3             None              None             None            None ENE         4.2              None               4.1             None            None E         3.0              None              None             None            None ESE         3.8              None              None             None            None SE         1.8              None               2.4             None             2.4 SSE         2.0              None               3.6             None             2.2 s         1.0              None               2.5             None             1.0 SSW          1.1              None               2.8               1.4            2.5 SW          1.1              None               4.0               1.6            1.6 WSW           1.0              None               3.6               1.5            2.0 w          1.1              None               2.7               2.8           None 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 September 21, 2015 to identify any new withdrawal of water from the river for drinking, irrigation, or construction purposes.
2015 HNP Annual Radiological Environmental Operating Report         30 I Page

PLANT HATCH                                                           NNUAL ADIOL GICAL EPORT Irrigation equipment was identified at Clarke's Farm about% mile downstream of Station #172 river water sampling station. The equipment is potentially used to irrigate crops. Mr. Clarke was contacted on September 3, 2015, and he stated that he had used river water to irrigate peanuts this year. A sample of peanuts was collected and analyzed for gamma isotopes. The data is indicated in Table 4-2 below.
Correspondence from the Georgia Environmental Protection Division (EPD) on September 29, 2015, and November 12, 2015, indicated that no new agricultural or drinking water withdrawal permits had been issued at those respective times.
Table 4-2. Special Sample Results (Peanuts)
Nuclide         Sample              Units             Activity             MDA Cs-134         Peanuts             pCi/Kg       NDM                      8.07E+01 Cs-137         Peanuts             pCi/Kg       NDM                      7.56E+OO 1-131         Peanuts             pCi/Kg       NDM                      1.11E+01 NDM - No Detectable Measurement 2015 HNP Annual Radiological Environmental Operating Report          31 I Page

PLANT       TC NVIRONME 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 2015 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 2015 HNP Annual Radiological Environmental Operating Report          32 I Page

PLANT HATCH                                                      NUAL ADIOLOGICAL T
APPENDIX A Maps 2015 HNP Annual Radiological Environmental Operating Report     Appendix A

Appendix A MapA-1 Indicator Stations _
                     .--1---__J Control Stations _     April 30, 2016 Other Stations _

Legend :
Indicator Stations -
Control Stations -
Other Stations -
Edwin I. Hatch Nuclear Plant 2015 Annual Rad iological Environmental Report REMP Stations within 10 miles
                                                                     .r' t--D-r-aw
_ n_b_y_
C_. G April 30, 2016
_ r_o_c_
e _ ... ::p*:~~x A

z Drawn by:  C. Groce Appendix A Legend:                            Edwin I. Hatch Nuclear Plant Map A-3 Upper Perched Aquifer -
* 2015 Annual Radiological Environmental Report Minor Confined Aquifer -
* Facility Groundwater Wells April 30, 2016

PLANTHATC                                                    ANNUAL ADIOL GICAL APPENDIX B Errata 2015 HNP Annual Radiological Environmental Operating Report    Appendix B

PLANT      ATCH 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, Rad iological 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 . No changes were made to the Groundwater Protection Program in 2014.
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 resu lts for 2014 were all within regulatory limits specified within this report. Table3-9 contains the results of the Groundwater Protection Program results. See Map A-4 in appendix for well locations.
Rl           82 .9      Confined Aquifer Upgradient R2           82 .7      Confined Aqu ifer Near Diesel Generator Bldg.
R3           89 .2      Confined Aqu ifer Near CST-1 R4            41        Dilution Line Near River Water Discharge Structu re RS           33 .6      Between Subsurface Dra in Lines Downgradient R6           38 .2      Between Subsurface Dra in Lines Downgradient NW2A            27          ater Table Near CST-2 Inside of Subsu rface Drain NW2B            27          ater Table Outside of Subsurface Drain NW3A           26 .5        ater Table Inside of Subsurface Drain NW3B           25 .3        ater Table Outside of Subsurface Drain NW4A            27          ater Table Upgrad ient Inside of Subsurface Dra in NWSA          26 .7         ater Table Upgradient Inside of Subsurface Dra in NWSB          26.3          ater Table Upgradient Outside of Subsurface Dra in NW6             27          ater Table Near Diesel Generator Bldg.
NW8             23          ater Table Near Diesel Generato r Bldg.
NW9           26 .1         ater Table Downgradient Inside of Subsurface Drain NWlO          26 .2         ater Table Near CST-2 T3            18          ater Table Near Turbine Bldg.
T7          21.4          ater Table Near Diesel Generator Bldg.
TlO          18.8          ater Table Near CST-1 T12          23.2          ater Table Near CST-1 TlS          27 .4         ater Table Near CST-1 A               2015 HNP Annual Radiological Environmental Operating Report            Appendix B

PLANTHATC                                                                           NNUAL     ADIOLOGICAL NVIRONMENT L Pl SB                          ater Table Near Turbine Bldg.
P17A
* 77          onfined Aquifer Near Diesel Generator Bldg.
P17B            14.8           ater 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 Table 3-9. Groundwater Protection Pro ram Tritium Results                 Ci l
       .                 ,.                    ***  1--:1a'"             *** 1r:* .. *'"        "~ill     .
Rl                  259                    NDM                       NDM                       NDM R2                 NDM                      130                       173                      NDM R3                  941                     792                      1040                       887 R4                  295                    NDM                       NDM                       NDM RS                12500                   22500                     30300                     24200 R6                  194                    NDM                        195                      NDM NW2A                   440                    1420                       829                       188 NW2B                  NDM                     NDM                      NDM                        NDM NW3A                   208                    NDM                        185                      NDM NW3B                  NDM                     NDM                        303                       197 NW4A                  NDM                     NDM                      NDM                       NDM NWSA                  NDM                      160                     NDM                       NDM NWSB                   966                   NDM                       NDM                       NDM NW6                  1050                   NDM                       NDM                       NDM NW8                   215                   NDM              NS - insufficient water NS - insufficient water NW9                  NDM                    NDM                         162                       161 NW10                 15500                   11800                     9920                      10800 T3                 2290                    1970                      1240                     3440 T7                 NDM                    NDM                       NDM                       NDM no                 11100                   38500                     55900                     16500 T12                10500                  59700                     43400                      17600 TlS                 NDM                    4190                      4130                       1520 Pl SA         NS - not assigned       NS - not assigned               NDM                       NDM Pl SB                6007                   4300                      2180            NS - insufficient water P17A                 NDM                    NDM                       NDM                       NDM P17B                  519                    474                       547                       361 2015 HNP Annual Radiological Environmental Operating Report                           Append ix B

PLANT      A CH                                                    A    NUAL RADIOLOGICAL T
Deep Well 1      NS - not assigned  NS - not assigned          143          NS - not assigned Deep Well 2            NDM                NDM           NS - not assigned         208 Deep Well 3            NDM                NDM                 NDM                 NDM NDM - No Detectable Measurement NS - Not Sampled Plant Hatch has had historic tritium leaks into the perched aquifer from around the Unit 1 Condensate Storage Tank (CST), documented on 10 CFR 50.75(g) records. The tritium values in the wells that were found to be elevated above MDC were from previous CST and related piping leaks and are not considered present issues. Historic leaks and spills are reported in accordance with NEI 07-07.
2015 HNP Annual Radiological Environmental Operating Report          Appendix B

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 2015 Enclosure 2 Farley Annual Radiological Environmental Operating Reports for 2015

JOSEPH M. FARLEY NUCLEAR PLANT 2015 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SOUTHERN << \
NUCLEAR A SOUTHERN COMPANY

LANT FA LE ENVIRONMENTAL JOSEPH M. FARLEY NUCLEAR PLANT 2015 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE OF CONTENTS 1       Introduction ................................. .......... .... ................ ..... ....... ... .. ........... ....... 1 2        REMP Description ..... ... ................................................................................. 2 3       Results Summary ............................................. .... ... ..... ........ ... .......... ..... .. ..... 8 3.1      Airborne Particulates .... .. ...... .. ..... ... .. ............. ................................ .. .. ...... ... ..... ..... 17 3.1.1 Gross Beta ...................................... ......... .................... ......................................... 17 3.1. 2 Gamma Particulates ............... ............. ................................ .............. .. ................. 19 3.2      Direct Radiation ....... ..... ...... .... ................................................................ ... ....... .... 19 3.3      Biological Media .... ............ ........ .......................................................... .... ....... .... ... 23 3.3.1    Milk ......................................................... ............... .............................................. 23 3.3.2 Vegetation ...................... ............. .. .. .. ...................... ..................... .. ... .. ... ... .. ......... 24 3.3.3    Fish ......................... ........................ ...................................................................... 24 3.3.3.1 Bottom Feeding Species ...................................................................................... 24 3.3.3.2 Game Species ....................... ............. ........................ .. ........ ................... .............. 24 3.3 .4 Biological Media Summary .................................................................................. 24 3.4      Off-site Groundwater .......................................... .... .............................................. 25 3.5      River Water .. ..... ... ... ............. ..................................... .................... ........ .......... ...... 25 3.6      Sediment .... .. .. ... ... .. ...... .............. ..... ..................... ... ... ................................... .. ...... 26 3.7      lnterlaboratory Comparison Program ........................ .. ........................ ................ 26 3.8      Groundwater .............................................. .. ........ .......... ....................... ................ 30 4       Survey Summaries ...................................................................................... 32 4.1      Land Use Census .... ... ............................... ................................ .... ............ ........ ..... 32 4.2      Chattahoochee River Survey ................................................................................. 33 5       Conclusions .............. ... ........................ .... .. ....... ....... .... .. .......... ..... ............... 34 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 2015 FNP Annual Radiological Environmental Operating Report                                                               i l Page

PLANT     f    RLEY                                                                                                 NNUAL             ADIOLOGtCAL ENVI ONMENTAL Table   3-4. Average Weekly Gross Beta Air Concentration .. ... ..................... ................................... ............ 17 Table  3-5 . Average Quarterly Exposure from Direct Rad iation .. .... .. ... ............. ................ ...... .............. .. .. . 20 Table  3-6. lnterlaboratory Comparison Limits ................. .. ................ .... .. .. ................................... .... .... ... .. 27 Table  3-7. lnterlaboratory Comparison Summary ................................................................... ......... ......... 28 Table  3-8. Groundwater Protection Program Locations .. ....... .. ... ... ..... .. .. ... ............. ......... .... ..... ... ..... ... .. ... 30 Table  3-9. Groundwater Protection Program Results ........ ..... .. .................................... .... ... ..... ................. 31 Table  4-1. Land Use Census Results ....... .. ........ ... .. ... ... .. ........................ .. ................................. ........ .. ........ 32 Figures Figure  3-1. Average Weekly Gross Beta Air Concentration .. .... .............. .. ... ..... ............ .... ... ............... .. ...... 19 Figure  3-2. Average Quarterly Exposure from Direct Radiation .............. ......... ... ........................ .. .... ......... 22 Figure   3-3. 2015 Average Exposure from Direct Radiation .. .... .. ................. ............................ ...... .. .. ... ...... 23 Figure   3-4. 2015 Average Tritium Concentrations in River and Off-site Groundwater .. ............ ....... ... .. .... 26 Appendix A - Maps A REMP Stations in Plant Vicinity A REMP Stations within 5 Miles A Extended REMP Stations A Facility Groundwater Wells Appendix B - Errata Groundwater Protection Results from 2014 Report 2015 FNP Annual Rad iologi cal Environmental Operating Report                                                            ii l Page

LANT FARLE                                                        ANNU L ADIOLOGtCAL LIST OF ACRONYMS ADEM        Alabama Department of Environmental Management APC         Alabama Power Company ARE OR      Annual Radiological Environmental Operating Report ASTM        American Society for Testing and Materials CL          Confidence Level EPA         Environmental Protection Agency GA EPD      State of Georgia Environmental Protection Division FNP         Joseph M . Farley Nuclear Plant GPCEL       Georgia Power Company Environmental Laboratory ICP         lnterlaboratory 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 TLD         Thermoluminescent Dosimeter TS          Technical Specification 2015 FNP Annual Rad iological Environmental Operating Report   iii IPage

LANT F Rl                                                                  N U l   ADIOLOGICAL EPORT 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 2015 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 as well as the results from the lnterlaboratory Comparison
* A summary of the land use census and the river survey are included in Section 4
* Conclusions are included in Section 5 2015 FNP Annual Radiological Environmental Operating Report        l l Page

LANT ARLE                                                              NNUAL ADIOLOGICAL ONMENTAL                  EPORT 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 A of this report.
Plant personnel collect some samples, while others are collected by Georgia Power Company's Environmental Laboratory (GPCEL), located in Smyrna, Georgia. The lab analyzes all REMP samples.
2015 FNP Annual Radiological Environmental Operating Report      2 1Page

LANT FA LEY                                                                        ANNUAL RADIOLOGICAL ENVIRONME T L OPERATING           EPORT 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 isector in the general area of the site boundary;
                 !An outer ring of stations, one in each compass isector at approximately 5 miles from the site; and
::ipecial interest areas, such as population centers, nearby recreation areas, and control stations Airborne                                                                Continuous sampler operation    Particulate sampler: Analyze for gross beta
:.amples from nine locations :
Radioiodine and                                                         with sample collection weekly   radioactivity~ 24 hours following filter Particulates                                                                                            change. Perform gamma isotopic analysis on Four locations close to the site boundary in                                          ~ach sample when gross beta activity is > 10 different sectors;
                                                                                                        ~imes the yearly mean of control samples.
Perform gamma isotopic analysis on Three community stations; within 8 miles
                                                                                                        ~omposite sample (by location) quarterly.
Two control locations near population centers, Radioiodine canister: 1-131 analysis, weekly approximately 15 and 18 miles away (One community station)
Waterborne 2
Surface"          One sample upriver                                    Composite sample over one       Gamma isotopic analysis , monthly 4
One sample downriver                                  month period                    :=omposite for tritium analysis, quarterly 2015 FNP Annual Radiological Environmental Operating Report                                 3I Page

PLANT FARLEY                                                                  ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING             EPORT 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 Groundwater     ~ee Table 3-8 and Map A-4 in Appendix A for well   Quarterly sample; pump used to  rTritium, gamma isotopic, and field location s                                         sample GW wells; grab sample    parameters (pH, temperature, conductivity, Off-site monitoring includes one indicator station ~ram yard drains and ponds      k!issolved oxygen, oxidation/reduction and one control station                                                            potential, and turbidity) of each sample 1<1uarterly; Hard t o detect radionuclides as necessary based on results of tritium and jgamma (Off-site wells are analyzed only for Gamma Isotopic, 1-131, & tritium 2
:::ihoreline 7
* One sample from downriver area with existing ~emiannually                     Gamma isotopic analysis , semiannually
:::iediment          or potential recreational value
* One sample from upriver area with existing or potential r ecreational value Ingestion 5                                                                          26 Milk            rrwo samples from milking animals at control       Bimonthly                       Gamma isotopic analysis       ' , bimonthly locations at a distance of about 10 miles or more 8                                                                                                                         2 Fish
* One bottom feeding fish and one game fish     ~emiannually                    Gamma isotopic analysis on edible portions, both upstream and downstream                                                  :.emiannually During spring spawning season 2
Gamma isotopic analysis on edible portions, annually.
Gra ss 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 2015 FNP Annual Radiological Environmental Operating Report                                   4 I Page

LANT FARLEY                                                                              NNUAL RADIOLOGICAL ENVIRONME                              L OPERATING REPO T Table 2-1. Summary Description of Radiological Environmental Monitoring Program Exposure         Number of Representative Samples and Sample                   .           .                                                      .
                                                 .                            Samphng/Collect1on Frequency                 Type/Frequency of Analysis Path way an d/ or                          Locations Notes:
Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron aughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis hall 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 he facility.
Upriver samp le 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 ssure obtaining a representative sample.
A milking animal is a cow or goat producing milk for human consumption, no milk animals were found within five miles of the plant.
-If the gamma isotopic analysis is not sensitive enough to meet the Minimum Detectable Concentration (MDC) for 1-131, a separate analysis for 1-131 may be performed .
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 ediment 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 o 49 for the control station .
Since several miles of river water may be needed to obtain adequate fish samples, these river mile positions represent the approximate locations from hich 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.
2015 FNP Annual Radiological Environmental Operating Report                                           SI Page

NT                                         NNUAL RADIOLOGI                NVIRONME T l PERATING              RT 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 3
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, Direct 1108    Community              Ashford, AL             WSW         8                Airborne 1605    Community             Columbia, Al                N        5            Airborne, Direct 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     Ind icator          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       Contro l             Dothan, Al               w        15                 Direct 1311       Contro l             Webb, Al                 w        11                 Direct 1612       Control             Haleburg, Al            WNW        12                 Direct 1001   Community           Whatley Residence            SW        12                 Direct 1108   Community               Ashford, Al             WSW        8.0                Direct Downstream of plant discharge, WRI      Indicator approximately RM 40 s       3.0             River Water Upstream of plant intake, WRB        Control                                      NNE       3.0             River Water approximately RM 47 WGl-07    Ind icato r         Paper M ill Well           SSE       4.0            Groundwater 2015 FNP Annual Radiological Environmental Operating Report               6 1Page

LANT ARLE                                     A    NUAL RADIOL GIC l              NVIRONMENT l PERATING          E ORT 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 at Smith' s Bend (RM 41) s         4.0               Sediment 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                  Mi lk Donaldsonville, GA FGI &                Downstream of plant discharge FGB Indicator at Smith's Bend (RM 41) s         4.0                  Fish FGB &                   Upstream of plant intake at Control                                            N         4.0                  Fish FBB                 Andrews Lock and Dam (RM 48) 0104   Community              Early Co., GA                NNE         4.0                 Direct 0204   Community              Early Co ., GA                NE         4.0                 Direct 0304   Community              Early Co., GA                ENE         4.0                 Direct 0405   Community              Early Co ., GA                 E         5.0                 Direct 0505   Community              Early Co ., GA               ESE         5.0                 Direct 0605   Community              Early Co., GA                 SE         5.0                 Direct 0805   Community            Houston Co ., AL               SSE         5.0                 Direct 0904   Community            Houston Co., AL                SSW         4.0                 Direct 1005   Community            Houston Co ., AL               SW          5.0                 Direct 1104   Commun ity           Houston Co ., AL              WSW          4.0                 Direct 1204   Community            Houston Co ., AL                w          4.0                 Direct 1304   Community            Houston Co., AL               WNW          4.0                 Direct 1404   Community            Houston Co ., AL               NW          4.0                 Direct 1504   Community            Houston Co ., AL              NNW          4.0                 Direct Notes:
1 Direction and distance are determined as the mid-point between the Unit 1 and Unit 2 vent stacks .
12 No milk animals were found w ithin five miles of the plant, control sample not collected since 2009.
~ Spare, per the ODCM 2015 FNP Annual Radiological Environmental Operating Report                        7 1Page

LA T F      LE                             NUAL RADIOLOGICAL          NVIRONMENTAL PERA ING    EPOR 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, 1,120 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 sign ificant 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 radiologica l 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 ind icated 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 plant's liquid and gaseous effluents. When it is detected in effluents and REMP samples, it is also included in the REMP results. In 2015, 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 Detect able Difference (MOD}, and Chauvenet' s 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.
2015 FNP Annual Radiological Environmental Operating Report          S IPage

LANT F       LE                              NUAL RADIOLOGIC L NVIRO PERATING    e -ORT 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.
Chauvenet's 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 2015 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 Chauvenet's criterion.
2015 FNP Annual Radiological Environmental Operating Report          9I Page

LANT FARLEY                                                                                       ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING Airborne            Gross Beta             10        13.4              Columbia , AL      21.5       16.8       15.9 Particulates        466                              0.8-35 .6         NS mi.             2.6-42.2   1.1-42 .2  2.3-33 .6 (fCi/m3)                                             (206/207)         Community          (52/52)    (155/155)  (104/104)
Gamma Isotopic 36 1-131            70              NDM(c)                               NDM        NDM        NDM Cs-134           so              NDM                                  NDM        NDM        NDM Cs-137           60              NDM                                  NDM        NDM        NDM Airborne            1-131            70              NDM                                  NDM        NDM        NDM Radioiodine(fCi/m3) 363 Direct Radiation    Gamma      Dose                  17.1                                 25 .4      14.4        15.6 Plant Perimeter, E (mR/91 days)        157                              11.4-27.7                            23 .7-26.1 10.9-18.3   12.3-19 0.8 (63/63)                              (4/4)      (70/70)    (24/24)
Indicator Milk (pCi/I)        Gamma Isotopic 0
1-131            1 Cs-134           15 Cs-137           18 Ba-140           60 La-140           15 Vegetation (pCi/kg- Gamma Isotopic wet)                36 1-131            60              NDM                                                         NDM Cs-134           60              NDM                                                         NDM 2015 FNP Annual Radiological Environmental Operating Report                       tOI P age

LANT FARLEY                                                                                               ANNUAL RADIOLOGIC L ENVIRONMENTAL OPERATING Table 3-1. Radiological Environmental Monitoring Program Annual Summary Indicator Medium or Pathway Type and Total        Minimum             Locations        Location with the Highest      Other Stations      Control Sampled        Number of          Detectable         Mean (b),                Annual Mean              (f) Mean (b), Locations Mean (Unit of        Analyses       Concentration          Range     Name Distance and    Mean (b), Range      Range         (b), Range Measurement)       Performed           (MDC) (a)         (Fraction)       Direction            (Fraction)    (Fraction)      (Fraction)
Cs-137             80                7.9             Dothan, AL            12.3                          12.3 4.5-11.3        W18mi.                (12 .3-12.3)                  (12 .3-12 .3)
(2/12)          Control               (1/12)                        (1/12)
River Water       Gamma Isotopic (pCi/I)           26 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 1-131              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              203 .3          Paper Mill (RM 40)    203 .3                        NDM 8                                    156-248         Indicator             156-248 (3/4)                                 (3/4)
Off-site          Gamma Isotopic Groundwater       8 Mn-54              15                NDM                                   NDM                           NDM Fe-59              30                NDM                                   NDM                           NDM Co-58              15                NDM                                   NDM                           NDM 2015 FNP Annual Radiological Environmental Operating Report                                  ll l P age

PLANT FARLEY                                                                                                  NNUAL      AOIOLOGICAL ENVIRONMENTAL OPERATING               EPORT Table 3-1. Radiological Environmental Monitoring Program Annual Summary Indicator Medium or Pathway Type and Total         Minimum           Locations        Location with the Highest      Other Stations        Control Sampled         Number of          Detectable        Mean (b),                Annual Mean              (f) Mean (b),    Locations Mean (Unit of         Analyses        Concentration        Range      Name Distance and   Mean (b), Range      Range          (b), Range Measurement)      Performed           (MDC) (a)        (Fraction)       Direction           (Fraction)     (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 1-131              15                NDM                                  NDM                              NDM 8
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              NDM                                  NDM                              NDM 8
Bottom Feeding    Gamma Isotopic Fish              4 (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 Fe-59               260               NDM                                 NDM                              NDM 2015 FNP Annual Radiological Environmental Operating Report                                   12 IPage

PLANT FARLEY                                                                                                                   ANNUAL RADIOL GtCAL ENVIRONMENTAL OPERATING 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                13.5                 Downstream       of  13.5                                   NDM (13 .1-14.0)         plant discharge in   (13.1-14.0)
(2/2)                vicinity of Smith' s (2/2)
Bend (RM 41)
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.l. 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 1-131 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, 1-131 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) 2015 FNP Annual Radiological Environmental Operating Report                                               13 IPage

LANT FARLE                                             A    NUAL      ADIOLOGICAL ENVIRONMENTAL OPERATING            EPORT Table 3-2. Reporting Levels (RL)
Analysis      Water (pCi/I)  Airborne Particulate   Fish (pCi/kg-wet)      M ilk         Grass or Leafy or Gases (fCi/m3)                           (pCi/I)    Vegetation (pCi/kg-wet)
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 1-131             2b                900                                     3                  100 Cs-134             30              10,000                 1000              60                 1000 Cs-137             so              20,000                 2000              70                 2000 Ba-140            200                                                      300 La-140            100                                                      400
* Th is 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/I 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.
2015 FNP Annual Radiological Environmental Operating Report                         141 Page

LANT     F  RLEY                                                                                                   ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING                    EPO T Table 3-3. Anomalies and Deviations from Radiological Environmental Monitoring Program Collection Period       Affected Samples        Anomaly (A)* or Deviation                      Cause                           Resolution (D)**
04/07/15 - 04/14/15   Pl-1101/11-1101             Non-representative sample       Lost 102 hours of sample time when   Station operation satisfactory CR10053095            0.9 mile - WSW              of airborne particulates.       portable generator used to supply    after normal power restored .
power during outage tripped off.
2nd Quarter 2015      OSLO Station                Non -representative      direct In-service OSLO badge set missing    Spare      OSLO     badge    set 04/07 /15 to 04/28/15 Rl -0701A&B                 radiation data                  and presumed lost following severe   installed at station during CR 10062765                                                                                                                                 nd 1.0 mile - SSE                                              weather event in area.               remainder of 2           Quarter period .
04/21/15 - 04/28/15   Pl-1601/11-1601             Non-representative sample       Lost 6.25 hours of sample time due   Station operation satisfactory CR 10062765           0.8 mile - North            of airborne particulates        to power interruption during severe  after normal power restored .
weather event in area.
05/12/15 - 05/19/15   Pl-0701/11-0701             Non-representative sample       Lost 3.5 hours of sample time due to Station operation satisfactory CR 10069726           1.0 mile - SSE              of airborne particulates        unexpected loss of the 12KV South    after normal power restored .
Feeder power supply.
2nd Quarter 2015      OSLO Station                OSLO missing from station       In-service OSLO badge set missing    New OSLO badge set installed 04/08/15 - 07 /10/15  RC-0204A&B                                                  and presumed lost following severe   at start of 3'd Quarter period.
CR 10095289           (4 miles - NE)                                              weather event in area .
09/29/15 - 10/06/15   PC-0703/IC-0703             Non-representative sample       Lost 171 hours of sample time after  Station operation satisfactory CR 10131957           3 miles - SSE               of    airborne    particulates. local breaker on sampler tripped off after normal power restored .
Inadequate sample volume        during electrical storm.
3 collected (less than 250 m )
12/24/15 - EOY        WRB                         Non-representative monthly      Water sampler out of service for 7.5 Station               operability CR 10162085           (Andrews Dam)               and quarterly river water       days due to high river levels and    satisfactory after access to
                      -3 miles - upstream         composites                      resulting flood conditions           facility restored and sampling equipment        returned      to service.
12/21/15 - EOY        Pl-0701/11-0701             Air samples not obtained        In-service air samples and sampling  Station operation satisfactory CR 10162781           1.0 mile - SSE                                              equipment ruined during river        following power restoration flooding event.                      and replacement of sampling equipment.
2015 FNP Annual Radiological Environmental Operating Report                                 15 I Page

PLANT FARLEY                                                                                                              ANNUAL RADIOLOGIC L ENVIRONMENTAL OPERATING                   EPORT 4th Quarter 2015          OSLO Station                  OSLO collection delayed        OSLO station is inaccessible due to   4th Quarter OSLO badge set 10/08/15 - EOY            RC-0405A &B                                                  closed roads in surrounding area . will be changed-out when CR 10167965               5 miles - East                                                                                     normal access is restored.
1 1' through 3'd Quarter    Groundwater Sample Point      Samples not obtained for       PW#3 pump was Danger-Tagged           PW#3 pump was untagged 2015                      PW#3 (onsite Production       tritium and gamma isotopic     'off' for an underground piping leak  and samples collected during TE 921084                 Well #3 supply)               analyses                       (1-DT-14-Y36-00041).                  4th Quarter 2015.
3'd Quarter 2015          Groundwater Sample Point Samples not obtained for CW#2                  pump    was    inoperable CW#2 pump was repaired TE 921084                 CW#2 (onsite Construction tritium and gamma isotopic (SNC677410)                                   and samples collected during 1
East Well supply)              analyses                                                            4 h 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 2015 FNP Annual Radiological Environmental Operating Report                               16  I Page

LANT         LE                                                    ANNUAL      ADIOLOGICAL 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 commun ity station (0703, 1108, and 1605) approximately three to eight miles from the plant, and at three control stations (0215 and 1218) which 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. An activated cha rcoal canister is also placed in series with the particulate filter to adsorb radioiodine at each indicator and control station and at community station 0703 in Cedar Springs, GA for comparison purposes with GA EPD .
3.1.1 Gross Beta As provided in Table 3-1, the 2015 annual average weekly gross beta activity was 13.4 fCi/m3 for the indicator stations. It was 2.5 fCi/m3 less than the control station average of 15.9 fCi/m3 for the year. The MOD is not applicable as the ind icator stations produced a lower average than the control stations .
The 2015 annual average weekly gross beta activity at the community stations was 16.8 fCi/m3 which was 0.9 fCi/m3 more than the control station average . This difference is not statistically discernible since it is less than the calculated MOD of 3.0 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 2015 FNP Annual Radiological Environmental Operating Report                 17 I Page

LANT FARLEY                                                    NNUAL RADIOLOGICAL NVIRONMENTAL OPERATING REPORT Table 3-4. Average Weekly Gross Beta Air Concentration 1986                   10.5                  15.8              12 .5 1987                    9.0                  11.0              17.0 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.l 2014                  17.7                   19.l              18.5 2015                  13.4                   15 .9             16.8 I Page A        2015 FNP Annual Radiological Environmental Operating Report           18

LANT   FA   LE                                                   ANNUAL    ADIOLOGICAL ENVIRON Figure 3-1. Average Weekly Gross Beta Air Concentration 3.1.2 Gamma Particulates During 2015, 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 2015, 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.
2015 FNP Annual Radiological Environmental Operating Report          19  I Page

LANT       LE                                                     NNUAl      ADIOLOGI        l NVIRONMENT l 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 Appendix A and the outer ring (Stations 0104 through 1605) is located at a distance of approximately 5 miles from the plant as shown in Map A-2 in Appendix A. 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 Appendix A.
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 0104 through 1605) as well as stations 1001 and 1108.
As provided in Table 3-1, the 2015 average quarterly exposure at the indicator stations (inner ring) was 17.1 mR with a range of 11.4 to 27.7 mR. The indicator station average was 1.5 mR more than the control station average (15 .6 mR). This difference is considered statistically discernible since it is more than the MOD of 1.1 mR. However, the average is consistent with historical readings and is only slightly above the control value and therefore no environmental concerns were identified.
The quarterly exposures acquired at the community/other {outer ring) stations during 2015 ranged from 10.9 to 18.3 mR with an average of 14.4 mR which was 1.2 mR less than that of 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 2015 FNP Annual Radiological Environmental Operating Report                20 I Page

LANT FARLEY                                                   ANNUAL RADIOLOGICAL NVIRONMENTAL -                     -
Table 3-5. Average Quarterly Exposure from Direct Radiation 1985                  21.9                    22                   18 1986                  17.8                   17.7                 15 .1 1987                  20.8                   20 .0                18 .0 1988                  21 .5                  19.9                 18.5 1989                  18.0                   16.2                 15.3 1990                  18.9                   16.4                 15.8 1991                  18.4                   16.1                 16.1 1992                  16.1                   13 .6                13.5 1993                  17.4                   15.9                 15 .6 1994                  15.0                   13.0                 12.0 1995                  14.0                   12.5                 11.8 1996                  14.2                   12.7                 11.9 1997                  15 .3                  13 .9                11.9 1998                  16.2                   14.6                 13.9 1999                  14.7                   13.4                 12 .6 2000                  15.5                   14.1                 13 .5 2001                  14.9                   13.4                 12 .7 2002                  14.1                   12.6                 11.9 2003                  15.2                   13.6                 12 .9 2004                  14.3                   12 .9                12.1 2005                  14.7                   13.4                 12 .5 2006                  15.2                   13 .6                12 .9 2007                  14.6                   13.3                 12.5 2008                  15.0                   13 .7                12.9 2009                  15.2                   13 .6                12.8 2010                  17.8                   16.7                 15.S 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 2015                   17 .1                  15 .6                14.4 I Page
.\       2015 FNP Annual Radiological Environmental Operating Report              21

LANT A LE                                                            NNUAL RADIOLOGICAL NVIRONMENT L Figure 3-2. Average Quarterly Exposure from Direct Radiation 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 2015 values. The values for the special interest areas detailed below indicate that Plant Farley did not significantly contribute to direct radiation at those areas.
2015 FNP Annual Radiological Environmental Operating Report          22  I Page

LANT        LEY                                                  ANNUAL NVIRONMENT L Figure 3-3. 2015 Average Exposure from Direct Radiation 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 2015 land use census and therefore no milk sampling was performed during the reporting year.
2015 FNP Annual Radiological Environmental Operating Report          23  I Page

LANT A LEY                                                        ANNUAL     ADIOLOGICAL 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 2015, one gamma isotope (Cs-137) was identified twice at Station 1601 (Plant Perimeter) and once at a control station (Dothan, Alabama). The average for the indicator station (7.9 pCi/L) was below the average for the control station (12.3 pCi/L). No environmental concerns are noted as these values are below the MDC and RL.
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 Append ix A.
3.3.3.1      Bottom Feeding Species For bottom-feeding species, all fish sampled are considered indicator stations. No radionuclides were detected in the 2015 analyses, which is consistent with historical data .
3.3.3.2      Game Species For game species, all fish sampled are considered indicator stations. One sample location identified Cs-137 on two occasions with an average value of 13.5 pCi/kg. While the control samples did not contain Cs-137, the indicator value is below the MDC (SO pCi/kg) and the RL (2,000 pCi/kg) and this value is not considered attributable to Plant activity.
3.3.4 Biological Media Summary There were no statistical differences, trends, or anomalies associated with the 2015 biological media samples when compared to historical data. As shown in Table 3-1, Cs-137 was identified in vegetation and game species fish ; no other radionuclides were found from the gamma isotopic analysis of biological media samples in 2015.
2015 FNP Annual Rad iological Environmental Operating Report           24 I Page

LANT      LE                                                      NNU L ADIOLOGICAL NVIRONMENT L 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, 1-131 and tritium as specified in Table 2-1.
In 2015, 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 2015, tritium was not detected. Typically the positive results are at concentrations well below the MDC and RL for tritium (2,000 and 20,000 pCi/I, 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 2015 from the gamma isotopic analysis of the river water samples. Also indicated in Table 3-1, the average tritium concentration (three samples) found at the indicator station was 203 .3 pCi/I, the control station did not indicate any positive concentrations (four samples) . The MDC for tritium in river water used to supply drinking water is 2000 pCi/I and the RL is 20000 pCi/I.
Figure 3-4 below details the 2015 average tritium concentrations across both water mediums.
2015 FNP Annual Radiological Environmental Operating Report             25 I Page

LANT        LE                                                      NNUAL       ADIOLOGICAL ENVIRONMENT l Figure 3-4. 2015 Average Tritium Concentrations in River and Off-site Groundwater 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 2015.
3.7     lnterlaboratory Comparison Program In accordance with ODCM 4.1.3, GPCEL participates in an lnterlaboratory 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 thi rd 2015 FNP Annual Radiological Environmental Operating Report               26 I Page

LANT   FA     LE                                                                      ANNUAL          ADIOL GICAL ENVI 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. lnterlaboratory 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/I) .
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 2015 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 2015 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.
2015 FNP Annual Radiological Environmental Operating Report                                      27  I Page

LANT FARLEY                                                                                        ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPO T Table 3-7. lnterlaboratory Comparison Summary Analysis or  Date Prepared Reported        Known Value        Standard          Uncertainty   Percent Coef of Normalized Radionuclide                Average                          Deviation EL      Analytics (35)    Variation     Deviation 1-131 ANALYSIS OF AN AIR CARTRIDGE (pCi/cartridge) 1-131      9/10/2015      85.4              82.0             1.37               1.37            5.79          0.69 GAMMA ISOTOPIC ANALYSIS OF AN AIR FILTER (pCi/filter)
Ce-141      9/10/2015      92.7              85.5             4.36               1.43            7.5            1.03 Co-58       9/10/2015       114              106              5.28               1.76            5.6            0.9 Co-60       9/10/2015       139              132              5.38               2.21              5           0.37 Cr-51      9/10/2015       226              216             16.66               3.61            9.6           0.45 Cs-134      9/10/2015      85.3              84.9             3.37               1.42            5.4           0.08 Cs-137      9/10/2015       111              102                 5               1.71            6.5             1.2 Fe-59      9/10/2015      96.7              90.5              5.5               1.51             6.2          0.91 Mn-54       9/10/2015       133              116              5.82               1.94              6            2.09 Zn-65      9/10/2015       164              142              8.46               2.37             7.3           1.85 GROSS BETA ANALYSIS OF AN AIR FILTER (PCl/FILTER)
Gross Beta    9/10/2015       103              96.3             3.66               1.61             5.9           1.44 GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE Pel/LITER)
Co-58      6/11/2015      77.7              68.4             5.92               1.14           10.92            1.1 Co-60      6/11/2015       203              193              8.29               1.06            4.52           1.12 Cr-51      6/11/2015       295              276              33.19              4.61            12.3           0.53 Cs-134      6/11/2015       184              163               6.93              2.72            5.02           2.28 Cs-137      6/11/2015       144              125               7.77              2.09            7.38           1.75 Fe-59      6/11/2015       163              151              10.07              2.53            6.94           1.03 1-131     6/11/2015       105              95.9              6.91               1.6              8            1.04 Mn-54       6/11/2015       115              101                6.9              1.68            7.31           1.62 Zn-65      6/11/2015       282              248              15.62              4.15             7.3           1.64 2015 FNP Annual Radiological Environmental Operating Report                         28  I Page

LANT FARLEY                                                                                     ANNUAL    ADIOL GtCAL ENVIRONMENTAL OPERATING REPO T Table 3-7. lnterlaboratory Comparison Summary Analysis or  Date Prepared Reported        Known Value        Standard       Uncertainty   Percent Coef of Normalized Radionuclide                Average                          Deviation EL   Analytics (35)    Variation     Deviation GROSS BETA ANALYSIS OF WATER SAMPLE (Pel/LITER) 3/19/2015       319              281              10.5            4.69            4.56           2.59 Gross Beta 6/11/2015       290              248              10.2            4.15            4.68            3.1 GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (PCl/LITER)
Ce-141      3/19/2015      135.7            139.2             8.44            2.32            7.97           -0.3 Co-58       3/19/2015       183              180              9.32              3             6.76          0.24 Co-60       3/19/2015      325.3             328             12.73            5.48            5.61          -0.15 Cr-51      3/19/2015      399.1             366             38.04            6.11           17.12           0.48 Cs-134      3/19/2015      131.1             126              5.81             2.1            9.49          0.41 Cs-137      3/19/2015       175              167                9             2.78            7.49            0.6 Fe-59      3/19/2015       203              195             11.63            3.25            7.01           0.56 1-131      3/19/2015      100.5             96.7             7.16            1.61            9.24           0.41 Mn-54       3/19/2015       170              159              8.97            2.65            7.78            0.8 Zn-65      3/19/2015       328              299              17.26           4.99            7.61           1.15 TRITIUM ANALYSIS OF WATER SAMPLES (PCl/LITER) 3/19/2015      12104            12600              140            210             3.14          -1.31 H-3 6/11/2015      12700            13000              148            217             2.11          -0.95 2015 FNP Annual Radiological Environmental Operating Report                      29  I Page

LANT A LEY                                                           ANNUAL RADIOLOGICAL EPORT 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 bu ried piping and tanks inspection programs-. No changes were made to the Groundwater Protection Program in 2015 .
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 2015 were all within regulatory limits specified within this report. Table 3-9 contains the results of the Groundwater Protection Program results for tritium (in pCi/L) .
Rl           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 RS           Major Shallow aqu ifer        Dilution line R6           Major Shallow aquifer         Dilution line R7           Major Shallow aquifer         Dilution line R8           Maj or Shallow aqu ifer       Dilution line R9           Major Shallow aquifer         Dilution line RlO           Major Shallow aquifer         Dilution line Rll           Major Shallow aquifer         Background 1 R13           Major Shallow aquifer         Dilution line Rl4           Major Shallow aquifer         Background 2 PW#2               Drinking water            Production Well #2 Supply PW#3               Drinking water            Produ ction Well #3 Supply PW#4               Drink ing 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 2015 FNP Annual Radiological Environmental Operating Report             30 I Page

LA T         LE                                                        NUAL ADIOL GICAL ENVIRONMENT                        EPORT Rl                27 .6               NDM                   NDM                87 .2 R2                45 .1                53.7                 6.87               96.9 R3               1690                  1870                 1660              1650 R4               NDM                   145                  NDM               NDM RS                45.4                NDM                    143              NDM R6                182                 NDM                   78.4              NDM R7                90 .5                16.3                  123              NDM R8                50.6                 57 .9                NDM                28.9 R9                60 .3               NDM                   76 .1             NDM RlO                60.5                NDM                   41.6              NDM Rll               NDM                   9.33                  110              NDM R13               NDM                  NDM                   27.1              NDM R14                131                 NDM                   NDM               NDM PW#2                173                 NDM                   NDM               NDM PW#3         NS - Out of Service NS - Out of Service   NS - Out of Service       173 PW#4               NDM                  NDM                   NDM                209 CW West              NDM                  NDM                   NDM               NDM CW East             NDM                   74 .5         NS - Out of Service       179 FRW               NDM                  NDM                   NDM                248 SW-1               NDM                   53 .6                NDM               NDM NDM - No Detectable Measurements NS - Not Samp led 2015 FNP Annual Radiological Environmental Operating Report          31   I Page

LANT fARLE                                                                   NNUAL      ADIOLOGICAL NVIRONMENT l                   TING REPO 4 SURVEY SUMMARIES 4.1     Land Use Census In accordance with ODCM 4.1.2, a land use census was conducted on November 25, 2015 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.
The census results are tabulated in Table 4.1-1. The 2015 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 2014 census, nor were any milk animals located within a five-mile radius .
In accordance with ODCM 4.1.2, a land use census was conducted on November 25, 2015 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 0.2 miles). This location was evaluated under CAR 249563 in accordance with ODCM 4.1.2.2.1. There were no significant differences in X/Q or D/Q values or radiological doses between the new location and the previous location.
Table 4-1. Land Use Census Results Sector                          Residence                       Milk Animal Distance in M iles 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 2015 FNP Annual Radiological Environmental Operating Report                   32 I Page

LA Tf                                                              NNUAL     ADI LOGICAL NVIRONMENT L 4.2      Chattahoochee River Survey A previous river survey performed for Plant Farley 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.
In June 2015, a survey was sent to the Alabama Department of Environmental Management (ADEM) and Alabama Department of Economic and Community Affairs (ADECA) to request any information about river use permits that had been issued in the area near the plant. No additional withdrawal permits or intake locations had been added at the time of the survey.
2015 FNP Annual Radiological Environmental Operating Report         33 I Page

LA T A LE                                                         NNUAL      ADIOLOGICAL T
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 2015 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 2015 FNP Annual Radiological Environmental Operating Report          34 I Page

Charles R. Pierce                Southern Nuclear Regulatory Affairs Director      Operating Company, Inc.
40*1nverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992 .7872                      SOUTHERN ._\
Fax 205 .992.7601 NUCLEAR A SOUTHERN COMPANY MAY 1 6 2016 Docket Nos .:       50-321     50-348      50-424                          NL-16-0741 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 2015 Lad ies 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 2015.
This letter contains no NRC commitments . If you have any questions, please contact Ken McElroy at (205) 992-7369 .
C. R. Pierce Regulatory Affairs Director CRP/RMJ

U. S. Nuclear Regulatory Commission NL-16-0741 Page 2

==Enclosures:==
: 1. Hatch Annual Radiological Environmental Operating Report for 2015
: 2. Farley Annual Radiological Environmental Operating Report for 2015
: 3. Vogtle Annual Radiological Environmental Operating Report for 2015 cc:   Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, 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 Ms. C. Haney, Regional Administrator Mr. S. A. Williams, NRR Project Manager - Farley Mr. D. H. Hardage, Senior Resident Inspector - Hatch Mr. W. D. Deschaine, Senior Resident Inspector - Vogtle 1 & 2 Mr. P. K. Niebaum, Senior Resident Inspector - Farley Mr. R. E. Martin, NRR Project Manager - Vogtle 1 & 2 Mr. A. M. Alen, Resident Inspector - Vogtle 1 & 2 Mr. M. D. Orenak, NRR Project Manager - Hatch 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 2015 Enclosure 1 Hatch Annual Radiological Environmental Operating Reports for 2015

EDWIN le. HATCH NUCLEAR PLANT 2015 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SOUTHERN << \
NUCLEAR A SOUTHERN COMPANY

LANT      A   H                                                                                                            NNUAL                  ADIOLOGICAL RT EDWIN I. HATCH NUCLEAR PLANT 2015 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE OF CONTENTS 1       lntroduction .. ... ........... .......... ....................................... ...................... .......... . 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      lnterlaboratory Comparison Program ..... ... .......................................................... 23 3.7      Groundwater .. .... .. ... .. .. .... .. ......... .. ........... .......... ........ ............................................ 27 4       Survey Summaries ..... .. ............................................................................... 30 4.1      Land Use Census ... .. .... ... .......... ... ........... ........ .. .................. .. ... ......... ... ...... .... .. ...... 30 4 .2     Altamaha River Survey ........... ................. .............. .... ..... .. ........ ....... .. ............ .... .... 30 5       Conclusions ............. .................................................................................... 32 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. lnterlaboratory Comparison Limits ........ ... .. ........ .. ......................................................... ...... .. ... 24 2015 HNP !A.nnual Radiological Environmental Operating Report                                                                        I i lP age

PLANT            c                                                                                             NNU L ADIOLOGICAL Table  3-7. lnterlaboratory Comparison Summary .. ........ ....... ..... .. ...... .. ... ... ............ ................. ..... ... .......... 25 Table  3-8 . Groundwater Monitoring Locations .. ... ...... .. .......... .... .. ....... .... .. ................ .... .. .......... ...... ... .. .... 27 Table  3-9 . Groundwater Monitoring Results ....... .. ...... .... .... ................. .. ........... ... ..... ....... ... .. .. .... ... ....... .... 28 Table  4-1. Land Use Census Results ... .......... ... ............................................ .. ....... ........... .. ........ ................. 30 Table  4-2 . Special Sample Results (Peanuts) ........................................... ......... .. .. .............. .. .. .......... .......... 31 Figures Figure 3-1. Average Weekly Gross Beta Air Concentration ... ....... ..... .. ........ ....... .. ..... .. ........ .. ............. .... .. .. 16 Figure 3-2 . Average Quarterly Exposure from Direct Radiation ................. .. .. ...... ........ .. .. ..... .... ........... ... ... 19 Figure 3-3. 2015 Average Exposure from Direct Radiation ....................... .................................. ........... ... . 20 Figure 3-4 . 2015 Biological Media Average Concentrations .................. .. ............. ........ .... .... .. ........ ........ .... 22 Figure 3-5. Average Annual Tritium Concentrations in River Water ......... ..... ... ... ....... .... .. ......... .. ..... .. .... ... 23 Appendix A - Maps A REMP Stations in Plant Vicinity A REMP Stations within 5 Miles A Facility Groundwater Wells Appendix B - Errata Groundwater Protection Results from 2014 Report 2015 HNP Annual Radiological Environmental Operating Report                                        1 ii I P age

PL   NTH TC                                                       ANNUAL    ADIOLOGICAL PERATING    E ORT 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 GA EPD     State of Georgia Environmental Protection Division GPC        Georgia Power Company GPCEL      Georgia Power Company Environmental Laboratory HNP        Edwin I. Hatch Nuclear Plant ICP        lnterlaboratory Comparison Program MDC        Minimum Detectable Concentration MOD        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 2015 HNP Annual Radiological Environmental Operatihg Report       iii IPage I

PLANT      ATCH                                                         ANNUAL RADIOLOGICAL ENVI                   PERATING      EPORT 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 2015 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 preope rat ional 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 as well as the results from the interlaboratory comparison
* A summary of the land use census and the river survey are included in Section 4
* Conclusions are included in Section 5 2015 HNP Annual Radiological Environmental Operating Report           ll P age

L NT        c                                                           NNUAL ADIOLOGICAL 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 Appendix A of this report .
Georgia Power Company's Environmental Laboratory (GPCEL), located in Smyrna, Georgia collects and analyzes REMP samples .
~'
2015 HNP Annual Radiological Environmental Operating Report      2 1P age I

PLANT      ATCH                                                                        NNUAL RADI LOGIC l                 NVIRONMENT l 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     Qua rterly                                         Gamma dose, quarterly stations Airborne Radioiodine Samples from six          Continuous sampler operation with sample           Radioiodine canister: 1-131 analysis, weekly and Particulates     locations :               collection weekly Particulate sampler : analyze for gross beta radioactivity not less than 24 hours following filter change, weekly; perform gamma isotopic analysis on affected samp le when gross beta activity is 10 times the yearly mean of control samples; and compo site (by locati on) 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       Rive r water collected near the intake will be a   1-131 analysis on each sample when biweekly water near the intake and composite sample; the finished water will be a     coll ect ion s are required . Gross beta and gamma one sample of finished    grab sample . These samples will be collected      isotopic analysis on each sa mple; 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 rT"he collections may revert to monthly should the discharges.               calculated doses become less than 1 mrem/year.
2015 HNP Annual Radiological Environmental Operating Report                                              3 I Page

LANT       A C                                                                        NNU l          ADI l Gtc              NVIR N ENT l 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- Quarte rly 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 rad ionuclides as necessary based on results of tritium and gamma .
2 Shoreline Sediment           Two                      Semiannually                                           Gamma isotopic analysis    , semiannually Ingestion 5                                                                                                                             27 M ilk                       On e                      Bimonthly                                             Gamma isotopic analysis    ' , bimonthly 0                                                                                                                   2 Fish or Clams               Two                      Semiannually                                           Gamma isotopic analysis on edible portion s, semian nually 27 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 facility.
3 1f it is found that river water downstream of the plant is used for drinking, drinking water sam ples will be collected and analyzed as specified herein .
14 A survey shall be conducted annually at least 50 river mile s downstream of the plant to identify those who use water from the Altamaha River for drinking.
15 up to three sampling locations within five miles and in different sectors will be used as available. In addition, one or more con t rol locations beyond 10 miles will be used .
16commercially or recreationally important fish may be sampled . Clams may be sa mpled if diffi culties are encountered in obtaining su fficient fish samples.
7 1f the gamma isotopic analysis is not se nsitive enough to meet the Minimum Detectabl e Concentrati on (MDC) for 1-131, a separate analysis for 1-131 may be performed.
2015 HNP Annual Radiological Environmental Operating Report                                             4 1P age

PLANT HATC                                   NNUAL RA IOLOGIC . l ENVI *ONME T l Table 2-2. Radiological Environmental Sampling Locations 1
Station  Station  Descriptive Location Direction    Distance        Radiation Sample Type 1
Number    Type                                      (miles) 064      Othe r     Roadside Park       WNW           0.8                    Direct 101   Indicator      Inner Ring            N         1.9                    Direct 102   Indicator      Inner Ring         NNE          2.5                    Di rect 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, Dire ct 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      Inn er Ring          w          1.1                    Direct 114   Indicator      Inner Ring        WNW           1.2                    Direct 115   Indicator      Inn er Ring         NW          1.1                    Direct 116   Indicator      Inn er 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     Oth er      Outer Ring          NNW          4.8                    Direct 2015 HNP Annual Radiological Environmental Operating Report                SI P age

LANT          CH                              ANNUAL RADIOLOGlC L ENVIRONM                          TAL T
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 Pri son           ENE          10.3                        Milk Ba xley 309       Control Substation s           10.0                 Airborne, Direct 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 approximate ly 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 .
::>tation 172 is located approximately 3.0 river miles downstream of the discharge structure for river water, sed iment and clams, and 1.7 river miles for fish .
The location s from which river water and sedim ent may be taken can be sharply defined. However, the sam pling locations for clams often have to be extended over a wide area to obta in a sufficient quantity. High water adds to the difficulty in obtaining clam sa mples 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 approxi mations of the location s where
,,amples are collected.
3 River (fish or clams, shoreline sediment, and surface water) 2015 HNP Annual Radiological Environmental Operating Report                          6I P age

PLA T        A CH                          ANNUAL      ADIOLOGIC L NVI ONMENTAL OPE                 RT 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, 885 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 plant's liquid and gaseous effluents . When it is detected in effluents and REMP samples, it is also included in the REMP results . In 2015, 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 (MOD), and Chauvenet's 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.
2015 HNP Annual Radiological Environmental Operating Report I         71 Page I

LA T      A CH                            NNUAL   R     IOLOGI       L NVIRONMENTAL Minimum Detectable Difference The Minimum Detectable Difference {MOD) 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 MOD was considered to be statistically indiscernible.
ChauvenersCriterion All results were tested for conformance with Chauvenet 's criterion {G . D. Chase and J. L.
Rabinowitz, Principles of Radioisotope Methodology, Burgess Publ ishing 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 2015 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 Chauvenet's criterion .
2015 HNP Annual Radiological Environmental Operati rlg Report         S f Page

LANT HATCH                                                                                                       NUAL      ADIOLQGtCAL 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       19.l              State Pri son       20                                 19.6 Particulates      312                                   4-40.4            ENE 11.2 Mi les     2.3-35 .9                          2.3-35 .9 (fCi/m3)                                                (208/208)                             (52/52)                            (104/104)
Gamma Isotopic 24 1-131                 70              NDM(c)                                NDM                                NDM Cs-134                so              NDM                                   NDM                                NDM Cs-137                60              NDM                                   NDM                                NDM Airborne          1-131                 70              NDM                                   NDM             NDM                NDM Radioiod ine      312 (fCi/m3)
Direct Radiati on Gamma Dose                            12.l              Outer Ring          16.4            12.1               11.7 (mR/91 days)      148                                   9.4-17.4          WNW 5.4 mi.         14.3-16.2       8.6-16.9          9.8-14.2 (64/64)                               (4/4)           (72/72)            (12/12)
Milk (pCi/I)      Gamma Isotopic 24 1-131                 1                                                     NDM                                NDM Cs-134                15                                                    NDM                                NDM Cs-137                18                                State Prison        0.78-0.78                         0.78-0.78 ENE 10.3 Miles      (1/24)                             (1/24)
Ba-140                60                                                    NDM                                NDM La-140                15                                                    NDM                                NDM Vegetation        Gamma Isotopic (pCi/kg-wet)      36 1-131                 60              NDM                                                                      NDM 2015 HNP Annual Radiological Environmental Operating Report                                       9 1P age

PLANT HATCH                                                                                                    NUAL       ADtQLOGlCAl PE RATING
                                . ..       *
* I e I :                         :
* I : "
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                                                                   NDM Cs-137                 80                135.2           Inn er Ring    ESE  149.7                             NDM 16.2-376.2      1.1 mi.             16.2-376.2 (9/24)                              (8/12)
Riv er Water  Gamma Isotopic (pCi/I)       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 1-131                  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)          200             Downstream E        200                               17.5 8                                        200-200         3.0 RM from         200-200                           17.5-17.5 (1/4)           intake              (1/4)                             (1/4)
Fish          Gamma Isotopic (pCi/kg-wet)  4 2015 HNP Annual Radiological Environmental Operating Report                                     10 IP age

PLA T ATCH                                                                                                                            NU L ADtOL GlCAL ENVIRONME                  PE RATING
                                            . ..         .. .. I :                                :
* I :
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               NDM                                                                               NDM Sediment              Gamma Isotopic (pCi/kg-dry)          4 Cs-134                     150               NDM                                                                               NDM Cs-137                     180               40.5                 Upstream WNW          84.0                                   84.0 28.9-52 .0           1.1 RM from           79 .6-88 .5                            79 .6-88.5 (2/2)                inta ke               (2/2)                                  (2/2)
Notes:
(a)The MDC is defined in ODCM 10.1. Except as noted otherwise, the value s listed in this column are the detection capabil ities required by ODCM Table 4-3.
The values listed in this co lumn are a priori (before the fact) MDCs. In practice, the a posteriori (after the fact) MDCs are generally lower than the value s 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 lpCi/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 re qu ired )
-- ~                                           2015 HNP Annual Radiological Environmental Operating Report                                                    ll lP age

LANT HATCH                                              NNUAL RADIOLOGICAL               NVIRONME TAL OPERATING Table 3-2. Reporting Levels (RL)
Analysis      Water (pCi/I)  Airborne Particulate   Fish (pCi/kg-wet)       Milk          Grass or Leafy or Gases (fCi/m3)                            (pCi/I)    Vegetation (pCi/kg-wet)
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 1-131            2b                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
* 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/I 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.
2015 HNP Annual Radiological Environmental Operating Report                          12 1P age

PLANT HATCH                                                                                                                     NUAL      ADIOLOGICAL ENVIRON       E TAL     0   ERATING Table 3-3. Anomalies and Deviations from Radiological Environmental Monitoring Program Collection Period          Affected Samples           Anolmaly (A)* or Deviation                    Cause                            Resolution (D)**
No program deviations were identified in the Hatch Radiological Environmental Monitoring Program during 2015.
* An anomaly is considered a non-standard sample that stil l meets sampl ing criteria outlined in SNC and Georgia Powe r 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 2015 HNP Annual Radiological Environmental Operating Report                               13j Page

PLANT      A CH                                                      ANNUAL RADIOL GI AL NVIRONMEN AL                             RT 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 sampling locations containing a filter and cartridge series, 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 2015 annual average weekly gross beta activity was 19.l fCi/m3 for the indicator stations . It was 0.5 fCi/m3 less than the control station average of 19.6 fCi/m3 for the year. This difference is not statistically discernible, since it is less than the calculated MOD of 4.1 fCi/m3.
Avera ge 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 2015 HNP Annual Radiological Environmental Operating Report                   14 I Page

PLANT A CH                                                     NNUAL      RA     IOLOGICAL ERA.TING 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 2015                          19 .1                                19 .6 2015 HNP Annual Radiological Environmental Operating Report 1               15 I Page

LANT    A CH                                                    ANNUAL     A IOLOGICAL Figure 3-1. Average Weekly Gross Beta Air Concentration 3.1.2 Gamma Particulates During 2015, 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 2015, 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.
I Page A '. I 2015 HNP Annual Radiological Environmental Operati ng Report           16

LANT HA CH                                                         NNUAL     ~ADIOLOGICAL NMENTAL      PERATING       EPORT 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 Appendix A 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 Appendix A. 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 2015 average quarterly exposure at the indicator stations (inner ring) was 12.1 mR with a range of 9.4-17.4 mR. The indicator station average was 0.4 mR more than the control station average (11.7 mR) . This difference is not considered statistically discernible since it is less than the MOD of 1.1 mR.
The quarterly exposures acquired at the community/other (outer ring) stations during 2015 ranged from 8.6 to 16.2 mR with an average of 12.1 mR which was 0.4 mR more than that for the control stations. However, this difference is not discernible since it is less than the MOD 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 1979                    5.16                  6.77                   NA 2015 HNP Annual Radiological Environmental Operating Report               171 Page

LA THATCH                                                      NNUAL ENVIRONMENTAL Table 3-5. Average Quarterly Exposure from Direct Radiation Period               Indicator              Control               Outer Ring (mR)                   (mR)                  (mR) 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 2015                  12 .1                  11.7                  12 .1 2015 HNP Annual Radiological Environmental Operating Report                18 I Page

LANT        TCH                                                   ANNUAL RADIOLOGI        l ENVIRONMENT l Figure 3-2. Average Quarterly Exposure from Direct Radiation ifoomos Central Scliool (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 2015 values. The values for the special interest areas detailed below, indicate that Plant Hatch did not significantly contribute to direct radiation at those areas.
2015 HNP Annual Radiological Environmental Operating Report           19 I Page

LANT     ATCH                                                    ANNUAL    ADIOLOGICAL NVIRONMENTAL Figure 3-3. 2015 Average Exposure from Direct Radiation 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 2015 land census did not identify a milk animal within five miles of the plant.
2015 HNP Annual Radiological Environmental Operating Report          20 I Page

LANT HATCH                                                       ANNUAL ADIOLOGICAL NVIRONMENT l Gamma isotopic (including 1-131 and Cs-137) analyses were performed on each collected milk sample and there were no detectable results for gamma isotopes, with the exception of a single detection of Cs-137 (0.78 pCi/L) in November 2015. Figure 3-4 provides the 2015 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 nine of the 24 samples collected at the indicator stations. The average of the samples was 135.2 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 1-131 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 below the MDC and the RL for Cs-137 {80 and 2000 pCi/kg-wet, respectively).
During 2015, no other man-made gamma isotopes were detected in any Hatch 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 not 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 2015 biological media samples when compared to historical data . Figure 3-4 below, details the 2015 Cs-137 concentration compared to the Reportable Limits.
2015 HNP Annual Radiological Environmental Operating Report            21 I Page

LANT     ATCH                                                       NNUAL      ADIOLOGICAL NVIRONMENT L Figure 3-4. 2015 Biological Media Average Cs-137 Concentrations
* Indicator
* Control
* MDC 1000 1Reportable Limit 500 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 Appendix A} . 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 2015 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 200 pCi/I which was 182.5 pCi/I more than the average at the control station (17 .5 pCi/I}. No MDD was calculated because only one of the four samples for both the indicator and control stations indicated any concentration. Historically, the relationship between the indicator and control stations has remained consistent. Figure 3-5 below details the 2015 historical average tritium concentrations in river water.
2015 HNP Annual Radiological Environmental Operating Report              22 I Page

LANT       TCH                                                     ANNUAL       ADIOLOGICAL ERATING Figure 3-5. Average Annual Tritium Concentrations in River Water 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 (slightly above 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     lnterlaboratory Comparison Program In accordance with ODCM 4.1.3, GPCEL participates in an lnterlaboratory 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.
2015 HNP Annual Radiological Environmental Operating Report               23 I Page

LA T       TC                                                                        A   NUAL        ADIOLOGICAL 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. lnterlaboratory 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/I) .
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 2015 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).
2015 HNP Annual Radiological Environmental Operating Report                                      24  I Page

PLANT HATCH                                                                                              NNUAL RADIOL GIC l Table 3-7. lnterlaboratory Comparison Summary Analysis or Date Prepared  Reported         Known Value        Standard         Uncertainty    Percent Coef of Normalized Radionuclide                 Average                           Deviation EL      Analytics (3S)    Variation     Deviation 1-131 ANALYSIS OF AN AIR CARTRIDGE (pCl/cartridge) 1-131      9/10/2015       85.4               82.0             1.37               1.37            5.79          0.69 GAMMA ISOTOPIC ANALYSIS OF AN AIR FILTER (pCi/filter)
Ce-141      9/10/2015       92 .7              85.5             4.36               1.43             7.5           1.03 Co-58      9/10/2015        114               106              5.28               1.76             5.6           0.9 Co-60      9/10/2015        139               132              5.38               2.21              5            0.37 Cr-51      9/10/2015        226               216             16.66               3.61             9.6           0.45 Cs-134      9/10/2015       85.3               84.9             3.37               1.42             5.4           0.08 Cs-137      9/10/2015        111               102                 5               1.71             6.5            1.2 Fe-59      9/10/2015       96.7               90.5              5.5               1.51             6.2           0.91 Mn-54      9/10/2015        133               116               5.82              1.94              6            2.09 Zn-65      9/10/2015        164               142              8.46               2.37             7.3           1.85 GROSS BETA ANALYSIS OF AN AIR FILTER (PCl/FILTER)
Gross Beta   9/10/2015        103               96 .3             3.66              1.61             5.9           1.44 GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE PCl/LITER)
Co-58      6/11/2015       77.7               68.4              5.92              1.14           10.92            1.1 Co-60      6/11/2015        203               193               8.29              1.06            4.52           1.12 Cr-51      6/11/2015        295               276              33.19              4.61            12.3           0.53 Cs-134     6/11/2015        184               163               6.93              2.72            5.02           2.28 Cs-137     6/11/2015        144               125               7.77              2.09            7.38           1.75 Fe-59      6/11/2015        163               151              10.07              2.53            6.94           1.03 1-131     6/11/2015        105               95.9              6.91               1.6              8            1.04 Mn-54      6/11/2015        115               101                6.9              1.68            7.31           1.62 Zn-65      6/11/2015        282               248              15.62              4.15             7.3           1.64 2015 HNP Annual Radiological Environmental Operating Report                           25  I Page

LANT       ATCH                                                                                     A    NUAL ADIOLOGIC l ENVIRONMENTAL OPERATING REPO T Table 3-7. lnterlaboratory Comparison Summary Analysis or     Date Prepared  Reported        Known Value        Standard      Uncertainty    Percent Coef of Normalized Radionuclide                    Average                          Deviation EL   Analytics (3S)    Variation     Deviation GROSS BETA ANALYSIS OF WATER SAMPLE (PCl/LITER) 3/19/2015        319              281              10.5            4.69            4.56           2.59 Gross Beta 6/11/2015        290              248              10.2            4.15            4.68            3.1 GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (PCl/LITER)
Ce-141         3/19/2015       135.7            139.2             8.44            2.32            7.97           -0.3 Co-58          3/19/2015        183              180              9.32              3             6.76           0.24 Co-60          3/19/2015       325.3             328             12.73            5.48            5.61          -0.15 Cr-51         3/19/2015       399.1             366             38.04            6.11           17.12           0.48 Cs-134         3/19/2015       131.1             126              5.81             2.1            9.49           0.41 Cs-137         3/19/2015        175              167                9             2.78            7.49            0.6 Fe-59         3/19/2015        203              195             11.63            3.25            7.01           0.56 1-131         3/19/2015       100.5             96.7             7.16            1.61            9.24           0.41 Mn-54          3/19/2015        170              159              8.97            2.65            7.78            0.8 Zn-65          3/19/2015        328              299             17.26            4.99            7.61           1.15 TRITIUM ANALYSIS OF WATER SAMPLES (PCl/LITER) 3/19/2015      12104             12600              140            210             3.14          -1.31 H-3 6/11/2015      12700             13000              148            217             2.11          -0.95 2015 HNP Annual Radiological Environmental Operating Report                       26  I Page

LANT      TCH                                                             NNUAL    ADIOLOGIC L EPORT 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 woundwater, SNC plants have established robust buried piping and tanks inspection programs. No changes were made to the Groundwater Protection Program in 2015.
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 2015 were all within regulatory limits specified within this report. Table3-9 contains the results of the Groundwater Protection Program tritium results (in pCi/L). See Map A-4 in Appendix A for well locations.
Rl           82 .9      Confined Aquifer Upgrad ient R2          82 .7       Confined Aquifer Near Diesel Generato r Bldg.
R3          89.2        Confined Aquifer Near CST-1 R4            41        Dilution Line Near River Water Discharge Structure RS          33 .6       Between Subsurface Drain Lines Downgrad ient R6          38 .2       Between Subsurface Drai n Lines Downgrad ient NW2A            27          ater Table Near CST-2 In side of Subsurface Dra in NW2B            27          ater Table Outs ide of Subsurface Dra in NW3A          26.5          ater Table Inside of Subsurface Drain NW3B          25 .3         ater Table Outside of Subsurface Drain NW4A            27          ater Table Upgradient Inside of Subsurface Drain NWSA          26 .7         ater Table Upgradient Inside of Subsu rface Drain NWSB          26.3          ater Table Upgradient Outside of Subsurface Drain NW6             27          ater Table Near Diesel Generator Bldg.
NW8             23          ater Table Near Diesel Generator Bldg.
NW9           26.1          ater Table Downgradient Inside of Subsurface Drain NWlO          26 .2         ater Table Near CST-2 T3             18          ater Table Near Turbine Bldg.
T7           21.4          ater Table Near Diesel Generator Bldg.
TlO          18.8          ater Table Near CST-1 2015 HNP Annual Radiological Environmental Operating Report                  27 I Page

LANT     ATCH                                                             ANNUAL RADIOLOGICAL EPORT ater Table Near CST-1 PlSA           74.5 PlSB           18              ater Tab le Near Turbine Bldg.
P17A*           77             onfined Aquifer Near Diesel Generator Bldg.
P17B           14.8             ater 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 Table 3-9. Groundwater Protection Pro ram Tritium Results               . L
:*1*r:****               i****r.:***"'         ,.*aur:1*1*         '**a**Jn:1*1'"'
Rl                 12.6                     NDM                     220                     286 R2               NDM                       NDM8                     66 .1                   370 R3               1040                         961                  1320                    1430 R4               NDM                          120                   12.3                  NDM RS               17400                     18600                  12600                   8400 R6                88.5                        324                   161                    326 NW2A                 153                       491                    500                    272 NW2B                 154                        199                  NDM                    NDM NW3A                17.4                      NDM                    NDM                     52 .7 NW3B                 105                       327                   NDM                     101 NW4A                 111                       135                   41.3                    325 NWSA                 159                       218                   83.1                    288 NWSB                 125                       89.1                  75 .8                  NDM NW6                  100                       297                    285                    184 NW8                   NS                        NS                     NS                    298 NW9                 57 .5                      484                    477                   NDM NWlO               9540                       8620                 10000                    6140 T3               7260                       3200                   1370                   1720 T7                 19.9                       235                    224                    273 TlO              14100                      18600                 23300                   19900 T12              18300                      18300                  7290                    8190 TlS                 911                      2810                    941                   1910 Pl SA              NDM                         91.6                  45.2                    195 2015 HNP Annual Radiological Environmental Operating Report                         28   I Page

LANT       TCH                                                      NNUAL RADIOLOGICAL NS - Not enough P15B                                    2440                3270                1900 water to sample P17A                135                  106                NDM                 NDM P17B                132                  173                 545                423 Deep Well 1     NS - Out of Service NS - Out of Service NS - Out of Service NS - Out of Service Deep Well 2           NDM                  NDM                 NDM                 NDM Deep Well 3            81.2                NDM                 NDM                 113 Plant Hatch has had historic tritium leaks into the perched aquifer from around the Unit 1 Condensate Storage Tank (CST), documented on 10 CFR 50.75(g) records. The tritium values in the wells that were found to be elevated above MDC were from previous CST and related piping leaks and are not considered present issues. Historic leaks and spills are reported in accordance with NEI 07-07.
2015 HNP Annual Radiological Environmental Operating Report             29 I Page

PLANT HATCH                                                           NNUAL     ADIOLOGICAL ENVIRONMENTAL                           T 4 SURVEY SUMMARIES 4.1      Land Use Census In accordance with ODCM 4.1.2, a land use census was conducted on November 9, 2015 to verify the locations of the nearest radiological receptor within five miles. The census results, shown in Table 4-1, indicated no major changes from 2014; therefore, no changes to the ODCM are required . Residents were located in each sector as identified below; no resident was identified closer than the current closest resident.
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           2.0             None              None               4.2            3.8 NNE           2.9             None              None               4.7           None NE           3.3             None              None             None            None ENE         4.2              None               4.1             None            None E         3.0              None              None             None            None ESE         3.8              None              None             None            None SE         1.8              None               2.4             None             2.4 SSE         2.0              None               3.6             None             2.2 s         1.0              None               2.5             None             1.0 SSW          1.1              None               2.8               1.4            2.5 SW          1.1              None               4.0               1.6            1.6 WSW           1.0              None               3.6               1.5            2.0 w          1.1              None               2.7               2.8           None 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 September 21, 2015 to identify any new withdrawal of water from the river for drinking, irrigation, or construction purposes.
2015 HNP Annual Radiological Environmental Operating Report         30 I Page

PLANT HATCH                                                           NNUAL ADIOL GICAL EPORT Irrigation equipment was identified at Clarke's Farm about% mile downstream of Station #172 river water sampling station. The equipment is potentially used to irrigate crops. Mr. Clarke was contacted on September 3, 2015, and he stated that he had used river water to irrigate peanuts this year. A sample of peanuts was collected and analyzed for gamma isotopes. The data is indicated in Table 4-2 below.
Correspondence from the Georgia Environmental Protection Division (EPD) on September 29, 2015, and November 12, 2015, indicated that no new agricultural or drinking water withdrawal permits had been issued at those respective times.
Table 4-2. Special Sample Results (Peanuts)
Nuclide         Sample              Units             Activity             MDA Cs-134         Peanuts             pCi/Kg       NDM                      8.07E+01 Cs-137         Peanuts             pCi/Kg       NDM                      7.56E+OO 1-131         Peanuts             pCi/Kg       NDM                      1.11E+01 NDM - No Detectable Measurement 2015 HNP Annual Radiological Environmental Operating Report          31 I Page

PLANT       TC NVIRONME 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 2015 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 2015 HNP Annual Radiological Environmental Operating Report          32 I Page

PLANT HATCH                                                      NUAL ADIOLOGICAL T
APPENDIX A Maps 2015 HNP Annual Radiological Environmental Operating Report     Appendix A

Appendix A MapA-1 Indicator Stations _
                     .--1---__J Control Stations _     April 30, 2016 Other Stations _

Legend :
Indicator Stations -
Control Stations -
Other Stations -
Edwin I. Hatch Nuclear Plant 2015 Annual Rad iological Environmental Report REMP Stations within 10 miles
                                                                     .r' t--D-r-aw
_ n_b_y_
C_. G April 30, 2016
_ r_o_c_
e _ ... ::p*:~~x A

z Drawn by:  C. Groce Appendix A Legend:                            Edwin I. Hatch Nuclear Plant Map A-3 Upper Perched Aquifer -
* 2015 Annual Radiological Environmental Report Minor Confined Aquifer -
* Facility Groundwater Wells April 30, 2016

PLANTHATC                                                    ANNUAL ADIOL GICAL APPENDIX B Errata 2015 HNP Annual Radiological Environmental Operating Report    Appendix B

PLANT      ATCH 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, Rad iological 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 . No changes were made to the Groundwater Protection Program in 2014.
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 resu lts for 2014 were all within regulatory limits specified within this report. Table3-9 contains the results of the Groundwater Protection Program results. See Map A-4 in appendix for well locations.
Rl           82 .9      Confined Aquifer Upgradient R2           82 .7      Confined Aqu ifer Near Diesel Generator Bldg.
R3           89 .2      Confined Aqu ifer Near CST-1 R4            41        Dilution Line Near River Water Discharge Structu re RS           33 .6      Between Subsurface Dra in Lines Downgradient R6           38 .2      Between Subsurface Dra in Lines Downgradient NW2A            27          ater Table Near CST-2 Inside of Subsu rface Drain NW2B            27          ater Table Outside of Subsurface Drain NW3A           26 .5        ater Table Inside of Subsurface Drain NW3B           25 .3        ater Table Outside of Subsurface Drain NW4A            27          ater Table Upgrad ient Inside of Subsurface Dra in NWSA          26 .7         ater Table Upgradient Inside of Subsurface Dra in NWSB          26.3          ater Table Upgradient Outside of Subsurface Dra in NW6             27          ater Table Near Diesel Generator Bldg.
NW8             23          ater Table Near Diesel Generato r Bldg.
NW9           26 .1         ater Table Downgradient Inside of Subsurface Drain NWlO          26 .2         ater Table Near CST-2 T3            18          ater Table Near Turbine Bldg.
T7          21.4          ater Table Near Diesel Generator Bldg.
TlO          18.8          ater Table Near CST-1 T12          23.2          ater Table Near CST-1 TlS          27 .4         ater Table Near CST-1 A               2015 HNP Annual Radiological Environmental Operating Report            Appendix B

PLANTHATC                                                                           NNUAL     ADIOLOGICAL NVIRONMENT L Pl SB                          ater Table Near Turbine Bldg.
P17A
* 77          onfined Aquifer Near Diesel Generator Bldg.
P17B            14.8           ater 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 Table 3-9. Groundwater Protection Pro ram Tritium Results                 Ci l
       .                 ,.                    ***  1--:1a'"             *** 1r:* .. *'"        "~ill     .
Rl                  259                    NDM                       NDM                       NDM R2                 NDM                      130                       173                      NDM R3                  941                     792                      1040                       887 R4                  295                    NDM                       NDM                       NDM RS                12500                   22500                     30300                     24200 R6                  194                    NDM                        195                      NDM NW2A                   440                    1420                       829                       188 NW2B                  NDM                     NDM                      NDM                        NDM NW3A                   208                    NDM                        185                      NDM NW3B                  NDM                     NDM                        303                       197 NW4A                  NDM                     NDM                      NDM                       NDM NWSA                  NDM                      160                     NDM                       NDM NWSB                   966                   NDM                       NDM                       NDM NW6                  1050                   NDM                       NDM                       NDM NW8                   215                   NDM              NS - insufficient water NS - insufficient water NW9                  NDM                    NDM                         162                       161 NW10                 15500                   11800                     9920                      10800 T3                 2290                    1970                      1240                     3440 T7                 NDM                    NDM                       NDM                       NDM no                 11100                   38500                     55900                     16500 T12                10500                  59700                     43400                      17600 TlS                 NDM                    4190                      4130                       1520 Pl SA         NS - not assigned       NS - not assigned               NDM                       NDM Pl SB                6007                   4300                      2180            NS - insufficient water P17A                 NDM                    NDM                       NDM                       NDM P17B                  519                    474                       547                       361 2015 HNP Annual Radiological Environmental Operating Report                           Append ix B

PLANT      A CH                                                    A    NUAL RADIOLOGICAL T
Deep Well 1      NS - not assigned  NS - not assigned          143          NS - not assigned Deep Well 2            NDM                NDM           NS - not assigned         208 Deep Well 3            NDM                NDM                 NDM                 NDM NDM - No Detectable Measurement NS - Not Sampled Plant Hatch has had historic tritium leaks into the perched aquifer from around the Unit 1 Condensate Storage Tank (CST), documented on 10 CFR 50.75(g) records. The tritium values in the wells that were found to be elevated above MDC were from previous CST and related piping leaks and are not considered present issues. Historic leaks and spills are reported in accordance with NEI 07-07.
2015 HNP Annual Radiological Environmental Operating Report          Appendix B

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 2015 Enclosure 2 Farley Annual Radiological Environmental Operating Reports for 2015

JOSEPH M. FARLEY NUCLEAR PLANT 2015 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SOUTHERN << \
NUCLEAR A SOUTHERN COMPANY

LANT FA LE ENVIRONMENTAL JOSEPH M. FARLEY NUCLEAR PLANT 2015 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE OF CONTENTS 1       Introduction ................................. .......... .... ................ ..... ....... ... .. ........... ....... 1 2        REMP Description ..... ... ................................................................................. 2 3       Results Summary ............................................. .... ... ..... ........ ... .......... ..... .. ..... 8 3.1      Airborne Particulates .... .. ...... .. ..... ... .. ............. ................................ .. .. ...... ... ..... ..... 17 3.1.1 Gross Beta ...................................... ......... .................... ......................................... 17 3.1. 2 Gamma Particulates ............... ............. ................................ .............. .. ................. 19 3.2      Direct Radiation ....... ..... ...... .... ................................................................ ... ....... .... 19 3.3      Biological Media .... ............ ........ .......................................................... .... ....... .... ... 23 3.3.1    Milk ......................................................... ............... .............................................. 23 3.3.2 Vegetation ...................... ............. .. .. .. ...................... ..................... .. ... .. ... ... .. ......... 24 3.3.3    Fish ......................... ........................ ...................................................................... 24 3.3.3.1 Bottom Feeding Species ...................................................................................... 24 3.3.3.2 Game Species ....................... ............. ........................ .. ........ ................... .............. 24 3.3 .4 Biological Media Summary .................................................................................. 24 3.4      Off-site Groundwater .......................................... .... .............................................. 25 3.5      River Water .. ..... ... ... ............. ..................................... .................... ........ .......... ...... 25 3.6      Sediment .... .. .. ... ... .. ...... .............. ..... ..................... ... ... ................................... .. ...... 26 3.7      lnterlaboratory Comparison Program ........................ .. ........................ ................ 26 3.8      Groundwater .............................................. .. ........ .......... ....................... ................ 30 4       Survey Summaries ...................................................................................... 32 4.1      Land Use Census .... ... ............................... ................................ .... ............ ........ ..... 32 4.2      Chattahoochee River Survey ................................................................................. 33 5       Conclusions .............. ... ........................ .... .. ....... ....... .... .. .......... ..... ............... 34 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 2015 FNP Annual Radiological Environmental Operating Report                                                               i l Page

PLANT     f    RLEY                                                                                                 NNUAL             ADIOLOGtCAL ENVI ONMENTAL Table   3-4. Average Weekly Gross Beta Air Concentration .. ... ..................... ................................... ............ 17 Table  3-5 . Average Quarterly Exposure from Direct Rad iation .. .... .. ... ............. ................ ...... .............. .. .. . 20 Table  3-6. lnterlaboratory Comparison Limits ................. .. ................ .... .. .. ................................... .... .... ... .. 27 Table  3-7. lnterlaboratory Comparison Summary ................................................................... ......... ......... 28 Table  3-8. Groundwater Protection Program Locations .. ....... .. ... ... ..... .. .. ... ............. ......... .... ..... ... ..... ... .. ... 30 Table  3-9. Groundwater Protection Program Results ........ ..... .. .................................... .... ... ..... ................. 31 Table  4-1. Land Use Census Results ....... .. ........ ... .. ... ... .. ........................ .. ................................. ........ .. ........ 32 Figures Figure  3-1. Average Weekly Gross Beta Air Concentration .. .... .............. .. ... ..... ............ .... ... ............... .. ...... 19 Figure  3-2. Average Quarterly Exposure from Direct Radiation .............. ......... ... ........................ .. .... ......... 22 Figure   3-3. 2015 Average Exposure from Direct Radiation .. .... .. ................. ............................ ...... .. .. ... ...... 23 Figure   3-4. 2015 Average Tritium Concentrations in River and Off-site Groundwater .. ............ ....... ... .. .... 26 Appendix A - Maps A REMP Stations in Plant Vicinity A REMP Stations within 5 Miles A Extended REMP Stations A Facility Groundwater Wells Appendix B - Errata Groundwater Protection Results from 2014 Report 2015 FNP Annual Rad iologi cal Environmental Operating Report                                                            ii l Page

LANT FARLE                                                        ANNU L ADIOLOGtCAL LIST OF ACRONYMS ADEM        Alabama Department of Environmental Management APC         Alabama Power Company ARE OR      Annual Radiological Environmental Operating Report ASTM        American Society for Testing and Materials CL          Confidence Level EPA         Environmental Protection Agency GA EPD      State of Georgia Environmental Protection Division FNP         Joseph M . Farley Nuclear Plant GPCEL       Georgia Power Company Environmental Laboratory ICP         lnterlaboratory 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 TLD         Thermoluminescent Dosimeter TS          Technical Specification 2015 FNP Annual Rad iological Environmental Operating Report   iii IPage

LANT F Rl                                                                  N U l   ADIOLOGICAL EPORT 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 2015 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 as well as the results from the lnterlaboratory Comparison
* A summary of the land use census and the river survey are included in Section 4
* Conclusions are included in Section 5 2015 FNP Annual Radiological Environmental Operating Report        l l Page

LANT ARLE                                                              NNUAL ADIOLOGICAL ONMENTAL                  EPORT 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 A of this report.
Plant personnel collect some samples, while others are collected by Georgia Power Company's Environmental Laboratory (GPCEL), located in Smyrna, Georgia. The lab analyzes all REMP samples.
2015 FNP Annual Radiological Environmental Operating Report      2 1Page

LANT FA LEY                                                                        ANNUAL RADIOLOGICAL ENVIRONME T L OPERATING           EPORT 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 isector in the general area of the site boundary;
                 !An outer ring of stations, one in each compass isector at approximately 5 miles from the site; and
::ipecial interest areas, such as population centers, nearby recreation areas, and control stations Airborne                                                                Continuous sampler operation    Particulate sampler: Analyze for gross beta
:.amples from nine locations :
Radioiodine and                                                         with sample collection weekly   radioactivity~ 24 hours following filter Particulates                                                                                            change. Perform gamma isotopic analysis on Four locations close to the site boundary in                                          ~ach sample when gross beta activity is > 10 different sectors;
                                                                                                        ~imes the yearly mean of control samples.
Perform gamma isotopic analysis on Three community stations; within 8 miles
                                                                                                        ~omposite sample (by location) quarterly.
Two control locations near population centers, Radioiodine canister: 1-131 analysis, weekly approximately 15 and 18 miles away (One community station)
Waterborne 2
Surface"          One sample upriver                                    Composite sample over one       Gamma isotopic analysis , monthly 4
One sample downriver                                  month period                    :=omposite for tritium analysis, quarterly 2015 FNP Annual Radiological Environmental Operating Report                                 3I Page

PLANT FARLEY                                                                  ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING             EPORT 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 Groundwater     ~ee Table 3-8 and Map A-4 in Appendix A for well   Quarterly sample; pump used to  rTritium, gamma isotopic, and field location s                                         sample GW wells; grab sample    parameters (pH, temperature, conductivity, Off-site monitoring includes one indicator station ~ram yard drains and ponds      k!issolved oxygen, oxidation/reduction and one control station                                                            potential, and turbidity) of each sample 1<1uarterly; Hard t o detect radionuclides as necessary based on results of tritium and jgamma (Off-site wells are analyzed only for Gamma Isotopic, 1-131, & tritium 2
:::ihoreline 7
* One sample from downriver area with existing ~emiannually                     Gamma isotopic analysis , semiannually
:::iediment          or potential recreational value
* One sample from upriver area with existing or potential r ecreational value Ingestion 5                                                                          26 Milk            rrwo samples from milking animals at control       Bimonthly                       Gamma isotopic analysis       ' , bimonthly locations at a distance of about 10 miles or more 8                                                                                                                         2 Fish
* One bottom feeding fish and one game fish     ~emiannually                    Gamma isotopic analysis on edible portions, both upstream and downstream                                                  :.emiannually During spring spawning season 2
Gamma isotopic analysis on edible portions, annually.
Gra ss 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 2015 FNP Annual Radiological Environmental Operating Report                                   4 I Page

LANT FARLEY                                                                              NNUAL RADIOLOGICAL ENVIRONME                              L OPERATING REPO T Table 2-1. Summary Description of Radiological Environmental Monitoring Program Exposure         Number of Representative Samples and Sample                   .           .                                                      .
                                                 .                            Samphng/Collect1on Frequency                 Type/Frequency of Analysis Path way an d/ or                          Locations Notes:
Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron aughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis hall 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 he facility.
Upriver samp le 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 ssure obtaining a representative sample.
A milking animal is a cow or goat producing milk for human consumption, no milk animals were found within five miles of the plant.
-If the gamma isotopic analysis is not sensitive enough to meet the Minimum Detectable Concentration (MDC) for 1-131, a separate analysis for 1-131 may be performed .
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 ediment 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 o 49 for the control station .
Since several miles of river water may be needed to obtain adequate fish samples, these river mile positions represent the approximate locations from hich 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.
2015 FNP Annual Radiological Environmental Operating Report                                           SI Page

NT                                         NNUAL RADIOLOGI                NVIRONME T l PERATING              RT 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 3
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, Direct 1108    Community              Ashford, AL             WSW         8                Airborne 1605    Community             Columbia, Al                N        5            Airborne, Direct 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     Ind icator          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       Contro l             Dothan, Al               w        15                 Direct 1311       Contro l             Webb, Al                 w        11                 Direct 1612       Control             Haleburg, Al            WNW        12                 Direct 1001   Community           Whatley Residence            SW        12                 Direct 1108   Community               Ashford, Al             WSW        8.0                Direct Downstream of plant discharge, WRI      Indicator approximately RM 40 s       3.0             River Water Upstream of plant intake, WRB        Control                                      NNE       3.0             River Water approximately RM 47 WGl-07    Ind icato r         Paper M ill Well           SSE       4.0            Groundwater 2015 FNP Annual Radiological Environmental Operating Report               6 1Page

LANT ARLE                                     A    NUAL RADIOL GIC l              NVIRONMENT l PERATING          E ORT 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 at Smith' s Bend (RM 41) s         4.0               Sediment 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                  Mi lk Donaldsonville, GA FGI &                Downstream of plant discharge FGB Indicator at Smith's Bend (RM 41) s         4.0                  Fish FGB &                   Upstream of plant intake at Control                                            N         4.0                  Fish FBB                 Andrews Lock and Dam (RM 48) 0104   Community              Early Co., GA                NNE         4.0                 Direct 0204   Community              Early Co ., GA                NE         4.0                 Direct 0304   Community              Early Co., GA                ENE         4.0                 Direct 0405   Community              Early Co ., GA                 E         5.0                 Direct 0505   Community              Early Co ., GA               ESE         5.0                 Direct 0605   Community              Early Co., GA                 SE         5.0                 Direct 0805   Community            Houston Co ., AL               SSE         5.0                 Direct 0904   Community            Houston Co., AL                SSW         4.0                 Direct 1005   Community            Houston Co ., AL               SW          5.0                 Direct 1104   Commun ity           Houston Co ., AL              WSW          4.0                 Direct 1204   Community            Houston Co ., AL                w          4.0                 Direct 1304   Community            Houston Co., AL               WNW          4.0                 Direct 1404   Community            Houston Co ., AL               NW          4.0                 Direct 1504   Community            Houston Co ., AL              NNW          4.0                 Direct Notes:
1 Direction and distance are determined as the mid-point between the Unit 1 and Unit 2 vent stacks .
12 No milk animals were found w ithin five miles of the plant, control sample not collected since 2009.
~ Spare, per the ODCM 2015 FNP Annual Radiological Environmental Operating Report                        7 1Page

LA T F      LE                             NUAL RADIOLOGICAL          NVIRONMENTAL PERA ING    EPOR 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, 1,120 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 sign ificant 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 radiologica l 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 ind icated 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 plant's liquid and gaseous effluents. When it is detected in effluents and REMP samples, it is also included in the REMP results. In 2015, 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 Detect able Difference (MOD}, and Chauvenet' s 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.
2015 FNP Annual Radiological Environmental Operating Report          S IPage

LANT F       LE                              NUAL RADIOLOGIC L NVIRO PERATING    e -ORT 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.
Chauvenet's 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 2015 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 Chauvenet's criterion.
2015 FNP Annual Radiological Environmental Operating Report          9I Page

LANT FARLEY                                                                                       ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING Airborne            Gross Beta             10        13.4              Columbia , AL      21.5       16.8       15.9 Particulates        466                              0.8-35 .6         NS mi.             2.6-42.2   1.1-42 .2  2.3-33 .6 (fCi/m3)                                             (206/207)         Community          (52/52)    (155/155)  (104/104)
Gamma Isotopic 36 1-131            70              NDM(c)                               NDM        NDM        NDM Cs-134           so              NDM                                  NDM        NDM        NDM Cs-137           60              NDM                                  NDM        NDM        NDM Airborne            1-131            70              NDM                                  NDM        NDM        NDM Radioiodine(fCi/m3) 363 Direct Radiation    Gamma      Dose                  17.1                                 25 .4      14.4        15.6 Plant Perimeter, E (mR/91 days)        157                              11.4-27.7                            23 .7-26.1 10.9-18.3   12.3-19 0.8 (63/63)                              (4/4)      (70/70)    (24/24)
Indicator Milk (pCi/I)        Gamma Isotopic 0
1-131            1 Cs-134           15 Cs-137           18 Ba-140           60 La-140           15 Vegetation (pCi/kg- Gamma Isotopic wet)                36 1-131            60              NDM                                                         NDM Cs-134           60              NDM                                                         NDM 2015 FNP Annual Radiological Environmental Operating Report                       tOI P age

LANT FARLEY                                                                                               ANNUAL RADIOLOGIC L ENVIRONMENTAL OPERATING Table 3-1. Radiological Environmental Monitoring Program Annual Summary Indicator Medium or Pathway Type and Total        Minimum             Locations        Location with the Highest      Other Stations      Control Sampled        Number of          Detectable         Mean (b),                Annual Mean              (f) Mean (b), Locations Mean (Unit of        Analyses       Concentration          Range     Name Distance and    Mean (b), Range      Range         (b), Range Measurement)       Performed           (MDC) (a)         (Fraction)       Direction            (Fraction)    (Fraction)      (Fraction)
Cs-137             80                7.9             Dothan, AL            12.3                          12.3 4.5-11.3        W18mi.                (12 .3-12.3)                  (12 .3-12 .3)
(2/12)          Control               (1/12)                        (1/12)
River Water       Gamma Isotopic (pCi/I)           26 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 1-131              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              203 .3          Paper Mill (RM 40)    203 .3                        NDM 8                                    156-248         Indicator             156-248 (3/4)                                 (3/4)
Off-site          Gamma Isotopic Groundwater       8 Mn-54              15                NDM                                   NDM                           NDM Fe-59              30                NDM                                   NDM                           NDM Co-58              15                NDM                                   NDM                           NDM 2015 FNP Annual Radiological Environmental Operating Report                                  ll l P age

PLANT FARLEY                                                                                                  NNUAL      AOIOLOGICAL ENVIRONMENTAL OPERATING               EPORT Table 3-1. Radiological Environmental Monitoring Program Annual Summary Indicator Medium or Pathway Type and Total         Minimum           Locations        Location with the Highest      Other Stations        Control Sampled         Number of          Detectable        Mean (b),                Annual Mean              (f) Mean (b),    Locations Mean (Unit of         Analyses        Concentration        Range      Name Distance and   Mean (b), Range      Range          (b), Range Measurement)      Performed           (MDC) (a)        (Fraction)       Direction           (Fraction)     (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 1-131              15                NDM                                  NDM                              NDM 8
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              NDM                                  NDM                              NDM 8
Bottom Feeding    Gamma Isotopic Fish              4 (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 Fe-59               260               NDM                                 NDM                              NDM 2015 FNP Annual Radiological Environmental Operating Report                                   12 IPage

PLANT FARLEY                                                                                                                   ANNUAL RADIOL GtCAL ENVIRONMENTAL OPERATING 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                13.5                 Downstream       of  13.5                                   NDM (13 .1-14.0)         plant discharge in   (13.1-14.0)
(2/2)                vicinity of Smith' s (2/2)
Bend (RM 41)
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.l. 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 1-131 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, 1-131 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) 2015 FNP Annual Radiological Environmental Operating Report                                               13 IPage

LANT FARLE                                             A    NUAL      ADIOLOGICAL ENVIRONMENTAL OPERATING            EPORT Table 3-2. Reporting Levels (RL)
Analysis      Water (pCi/I)  Airborne Particulate   Fish (pCi/kg-wet)      M ilk         Grass or Leafy or Gases (fCi/m3)                           (pCi/I)    Vegetation (pCi/kg-wet)
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 1-131             2b                900                                     3                  100 Cs-134             30              10,000                 1000              60                 1000 Cs-137             so              20,000                 2000              70                 2000 Ba-140            200                                                      300 La-140            100                                                      400
* Th is 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/I 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.
2015 FNP Annual Radiological Environmental Operating Report                         141 Page

LANT     F  RLEY                                                                                                   ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING                    EPO T Table 3-3. Anomalies and Deviations from Radiological Environmental Monitoring Program Collection Period       Affected Samples        Anomaly (A)* or Deviation                      Cause                           Resolution (D)**
04/07/15 - 04/14/15   Pl-1101/11-1101             Non-representative sample       Lost 102 hours of sample time when   Station operation satisfactory CR10053095            0.9 mile - WSW              of airborne particulates.       portable generator used to supply    after normal power restored .
power during outage tripped off.
2nd Quarter 2015      OSLO Station                Non -representative      direct In-service OSLO badge set missing    Spare      OSLO     badge    set 04/07 /15 to 04/28/15 Rl -0701A&B                 radiation data                  and presumed lost following severe   installed at station during CR 10062765                                                                                                                                 nd 1.0 mile - SSE                                              weather event in area.               remainder of 2           Quarter period .
04/21/15 - 04/28/15   Pl-1601/11-1601             Non-representative sample       Lost 6.25 hours of sample time due   Station operation satisfactory CR 10062765           0.8 mile - North            of airborne particulates        to power interruption during severe  after normal power restored .
weather event in area.
05/12/15 - 05/19/15   Pl-0701/11-0701             Non-representative sample       Lost 3.5 hours of sample time due to Station operation satisfactory CR 10069726           1.0 mile - SSE              of airborne particulates        unexpected loss of the 12KV South    after normal power restored .
Feeder power supply.
2nd Quarter 2015      OSLO Station                OSLO missing from station       In-service OSLO badge set missing    New OSLO badge set installed 04/08/15 - 07 /10/15  RC-0204A&B                                                  and presumed lost following severe   at start of 3'd Quarter period.
CR 10095289           (4 miles - NE)                                              weather event in area .
09/29/15 - 10/06/15   PC-0703/IC-0703             Non-representative sample       Lost 171 hours of sample time after  Station operation satisfactory CR 10131957           3 miles - SSE               of    airborne    particulates. local breaker on sampler tripped off after normal power restored .
Inadequate sample volume        during electrical storm.
3 collected (less than 250 m )
12/24/15 - EOY        WRB                         Non-representative monthly      Water sampler out of service for 7.5 Station               operability CR 10162085           (Andrews Dam)               and quarterly river water       days due to high river levels and    satisfactory after access to
                      -3 miles - upstream         composites                      resulting flood conditions           facility restored and sampling equipment        returned      to service.
12/21/15 - EOY        Pl-0701/11-0701             Air samples not obtained        In-service air samples and sampling  Station operation satisfactory CR 10162781           1.0 mile - SSE                                              equipment ruined during river        following power restoration flooding event.                      and replacement of sampling equipment.
2015 FNP Annual Radiological Environmental Operating Report                                 15 I Page

PLANT FARLEY                                                                                                              ANNUAL RADIOLOGIC L ENVIRONMENTAL OPERATING                   EPORT 4th Quarter 2015          OSLO Station                  OSLO collection delayed        OSLO station is inaccessible due to   4th Quarter OSLO badge set 10/08/15 - EOY            RC-0405A &B                                                  closed roads in surrounding area . will be changed-out when CR 10167965               5 miles - East                                                                                     normal access is restored.
1 1' through 3'd Quarter    Groundwater Sample Point      Samples not obtained for       PW#3 pump was Danger-Tagged           PW#3 pump was untagged 2015                      PW#3 (onsite Production       tritium and gamma isotopic     'off' for an underground piping leak  and samples collected during TE 921084                 Well #3 supply)               analyses                       (1-DT-14-Y36-00041).                  4th Quarter 2015.
3'd Quarter 2015          Groundwater Sample Point Samples not obtained for CW#2                  pump    was    inoperable CW#2 pump was repaired TE 921084                 CW#2 (onsite Construction tritium and gamma isotopic (SNC677410)                                   and samples collected during 1
East Well supply)              analyses                                                            4 h 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 2015 FNP Annual Radiological Environmental Operating Report                               16  I Page

LANT         LE                                                    ANNUAL      ADIOLOGICAL 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 commun ity station (0703, 1108, and 1605) approximately three to eight miles from the plant, and at three control stations (0215 and 1218) which 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. An activated cha rcoal canister is also placed in series with the particulate filter to adsorb radioiodine at each indicator and control station and at community station 0703 in Cedar Springs, GA for comparison purposes with GA EPD .
3.1.1 Gross Beta As provided in Table 3-1, the 2015 annual average weekly gross beta activity was 13.4 fCi/m3 for the indicator stations. It was 2.5 fCi/m3 less than the control station average of 15.9 fCi/m3 for the year. The MOD is not applicable as the ind icator stations produced a lower average than the control stations .
The 2015 annual average weekly gross beta activity at the community stations was 16.8 fCi/m3 which was 0.9 fCi/m3 more than the control station average . This difference is not statistically discernible since it is less than the calculated MOD of 3.0 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 2015 FNP Annual Radiological Environmental Operating Report                 17 I Page

LANT FARLEY                                                    NNUAL RADIOLOGICAL NVIRONMENTAL OPERATING REPORT Table 3-4. Average Weekly Gross Beta Air Concentration 1986                   10.5                  15.8              12 .5 1987                    9.0                  11.0              17.0 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.l 2014                  17.7                   19.l              18.5 2015                  13.4                   15 .9             16.8 I Page A        2015 FNP Annual Radiological Environmental Operating Report           18

LANT   FA   LE                                                   ANNUAL    ADIOLOGICAL ENVIRON Figure 3-1. Average Weekly Gross Beta Air Concentration 3.1.2 Gamma Particulates During 2015, 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 2015, 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.
2015 FNP Annual Radiological Environmental Operating Report          19  I Page

LANT       LE                                                     NNUAl      ADIOLOGI        l NVIRONMENT l 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 Appendix A and the outer ring (Stations 0104 through 1605) is located at a distance of approximately 5 miles from the plant as shown in Map A-2 in Appendix A. 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 Appendix A.
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 0104 through 1605) as well as stations 1001 and 1108.
As provided in Table 3-1, the 2015 average quarterly exposure at the indicator stations (inner ring) was 17.1 mR with a range of 11.4 to 27.7 mR. The indicator station average was 1.5 mR more than the control station average (15 .6 mR). This difference is considered statistically discernible since it is more than the MOD of 1.1 mR. However, the average is consistent with historical readings and is only slightly above the control value and therefore no environmental concerns were identified.
The quarterly exposures acquired at the community/other {outer ring) stations during 2015 ranged from 10.9 to 18.3 mR with an average of 14.4 mR which was 1.2 mR less than that of 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 2015 FNP Annual Radiological Environmental Operating Report                20 I Page

LANT FARLEY                                                   ANNUAL RADIOLOGICAL NVIRONMENTAL -                     -
Table 3-5. Average Quarterly Exposure from Direct Radiation 1985                  21.9                    22                   18 1986                  17.8                   17.7                 15 .1 1987                  20.8                   20 .0                18 .0 1988                  21 .5                  19.9                 18.5 1989                  18.0                   16.2                 15.3 1990                  18.9                   16.4                 15.8 1991                  18.4                   16.1                 16.1 1992                  16.1                   13 .6                13.5 1993                  17.4                   15.9                 15 .6 1994                  15.0                   13.0                 12.0 1995                  14.0                   12.5                 11.8 1996                  14.2                   12.7                 11.9 1997                  15 .3                  13 .9                11.9 1998                  16.2                   14.6                 13.9 1999                  14.7                   13.4                 12 .6 2000                  15.5                   14.1                 13 .5 2001                  14.9                   13.4                 12 .7 2002                  14.1                   12.6                 11.9 2003                  15.2                   13.6                 12 .9 2004                  14.3                   12 .9                12.1 2005                  14.7                   13.4                 12 .5 2006                  15.2                   13 .6                12 .9 2007                  14.6                   13.3                 12.5 2008                  15.0                   13 .7                12.9 2009                  15.2                   13 .6                12.8 2010                  17.8                   16.7                 15.S 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 2015                   17 .1                  15 .6                14.4 I Page
.\       2015 FNP Annual Radiological Environmental Operating Report              21

LANT A LE                                                            NNUAL RADIOLOGICAL NVIRONMENT L Figure 3-2. Average Quarterly Exposure from Direct Radiation 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 2015 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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LANT        LEY                                                  ANNUAL NVIRONMENT L Figure 3-3. 2015 Average Exposure from Direct Radiation 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 2015 land use census and therefore no milk sampling was performed during the reporting year.
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LANT A LEY                                                        ANNUAL     ADIOLOGICAL 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 2015, one gamma isotope (Cs-137) was identified twice at Station 1601 (Plant Perimeter) and once at a control station (Dothan, Alabama). The average for the indicator station (7.9 pCi/L) was below the average for the control station (12.3 pCi/L). No environmental concerns are noted as these values are below the MDC and RL.
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 Append ix A.
3.3.3.1      Bottom Feeding Species For bottom-feeding species, all fish sampled are considered indicator stations. No radionuclides were detected in the 2015 analyses, which is consistent with historical data .
3.3.3.2      Game Species For game species, all fish sampled are considered indicator stations. One sample location identified Cs-137 on two occasions with an average value of 13.5 pCi/kg. While the control samples did not contain Cs-137, the indicator value is below the MDC (SO pCi/kg) and the RL (2,000 pCi/kg) and this value is not considered attributable to Plant activity.
3.3.4 Biological Media Summary There were no statistical differences, trends, or anomalies associated with the 2015 biological media samples when compared to historical data. As shown in Table 3-1, Cs-137 was identified in vegetation and game species fish ; no other radionuclides were found from the gamma isotopic analysis of biological media samples in 2015.
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LANT      LE                                                      NNU L ADIOLOGICAL NVIRONMENT L 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, 1-131 and tritium as specified in Table 2-1.
In 2015, 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 2015, tritium was not detected. Typically the positive results are at concentrations well below the MDC and RL for tritium (2,000 and 20,000 pCi/I, 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 2015 from the gamma isotopic analysis of the river water samples. Also indicated in Table 3-1, the average tritium concentration (three samples) found at the indicator station was 203 .3 pCi/I, the control station did not indicate any positive concentrations (four samples) . The MDC for tritium in river water used to supply drinking water is 2000 pCi/I and the RL is 20000 pCi/I.
Figure 3-4 below details the 2015 average tritium concentrations across both water mediums.
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LANT        LE                                                      NNUAL       ADIOLOGICAL ENVIRONMENT l Figure 3-4. 2015 Average Tritium Concentrations in River and Off-site Groundwater 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 2015.
3.7     lnterlaboratory Comparison Program In accordance with ODCM 4.1.3, GPCEL participates in an lnterlaboratory 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 thi rd 2015 FNP Annual Radiological Environmental Operating Report               26 I Page

LANT   FA     LE                                                                      ANNUAL          ADIOL GICAL ENVI 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. lnterlaboratory 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/I) .
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 2015 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 2015 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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LANT FARLEY                                                                                        ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPO T Table 3-7. lnterlaboratory Comparison Summary Analysis or  Date Prepared Reported        Known Value        Standard          Uncertainty   Percent Coef of Normalized Radionuclide                Average                          Deviation EL      Analytics (35)    Variation     Deviation 1-131 ANALYSIS OF AN AIR CARTRIDGE (pCi/cartridge) 1-131      9/10/2015      85.4              82.0             1.37               1.37            5.79          0.69 GAMMA ISOTOPIC ANALYSIS OF AN AIR FILTER (pCi/filter)
Ce-141      9/10/2015      92.7              85.5             4.36               1.43            7.5            1.03 Co-58       9/10/2015       114              106              5.28               1.76            5.6            0.9 Co-60       9/10/2015       139              132              5.38               2.21              5           0.37 Cr-51      9/10/2015       226              216             16.66               3.61            9.6           0.45 Cs-134      9/10/2015      85.3              84.9             3.37               1.42            5.4           0.08 Cs-137      9/10/2015       111              102                 5               1.71            6.5             1.2 Fe-59      9/10/2015      96.7              90.5              5.5               1.51             6.2          0.91 Mn-54       9/10/2015       133              116              5.82               1.94              6            2.09 Zn-65      9/10/2015       164              142              8.46               2.37             7.3           1.85 GROSS BETA ANALYSIS OF AN AIR FILTER (PCl/FILTER)
Gross Beta    9/10/2015       103              96.3             3.66               1.61             5.9           1.44 GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE Pel/LITER)
Co-58      6/11/2015      77.7              68.4             5.92               1.14           10.92            1.1 Co-60      6/11/2015       203              193              8.29               1.06            4.52           1.12 Cr-51      6/11/2015       295              276              33.19              4.61            12.3           0.53 Cs-134      6/11/2015       184              163               6.93              2.72            5.02           2.28 Cs-137      6/11/2015       144              125               7.77              2.09            7.38           1.75 Fe-59      6/11/2015       163              151              10.07              2.53            6.94           1.03 1-131     6/11/2015       105              95.9              6.91               1.6              8            1.04 Mn-54       6/11/2015       115              101                6.9              1.68            7.31           1.62 Zn-65      6/11/2015       282              248              15.62              4.15             7.3           1.64 2015 FNP Annual Radiological Environmental Operating Report                         28  I Page

LANT FARLEY                                                                                     ANNUAL    ADIOL GtCAL ENVIRONMENTAL OPERATING REPO T Table 3-7. lnterlaboratory Comparison Summary Analysis or  Date Prepared Reported        Known Value        Standard       Uncertainty   Percent Coef of Normalized Radionuclide                Average                          Deviation EL   Analytics (35)    Variation     Deviation GROSS BETA ANALYSIS OF WATER SAMPLE (Pel/LITER) 3/19/2015       319              281              10.5            4.69            4.56           2.59 Gross Beta 6/11/2015       290              248              10.2            4.15            4.68            3.1 GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (PCl/LITER)
Ce-141      3/19/2015      135.7            139.2             8.44            2.32            7.97           -0.3 Co-58       3/19/2015       183              180              9.32              3             6.76          0.24 Co-60       3/19/2015      325.3             328             12.73            5.48            5.61          -0.15 Cr-51      3/19/2015      399.1             366             38.04            6.11           17.12           0.48 Cs-134      3/19/2015      131.1             126              5.81             2.1            9.49          0.41 Cs-137      3/19/2015       175              167                9             2.78            7.49            0.6 Fe-59      3/19/2015       203              195             11.63            3.25            7.01           0.56 1-131      3/19/2015      100.5             96.7             7.16            1.61            9.24           0.41 Mn-54       3/19/2015       170              159              8.97            2.65            7.78            0.8 Zn-65      3/19/2015       328              299              17.26           4.99            7.61           1.15 TRITIUM ANALYSIS OF WATER SAMPLES (PCl/LITER) 3/19/2015      12104            12600              140            210             3.14          -1.31 H-3 6/11/2015      12700            13000              148            217             2.11          -0.95 2015 FNP Annual Radiological Environmental Operating Report                      29  I Page

LANT A LEY                                                           ANNUAL RADIOLOGICAL EPORT 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 bu ried piping and tanks inspection programs-. No changes were made to the Groundwater Protection Program in 2015 .
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 2015 were all within regulatory limits specified within this report. Table 3-9 contains the results of the Groundwater Protection Program results for tritium (in pCi/L) .
Rl           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 RS           Major Shallow aqu ifer        Dilution line R6           Major Shallow aquifer         Dilution line R7           Major Shallow aquifer         Dilution line R8           Maj or Shallow aqu ifer       Dilution line R9           Major Shallow aquifer         Dilution line RlO           Major Shallow aquifer         Dilution line Rll           Major Shallow aquifer         Background 1 R13           Major Shallow aquifer         Dilution line Rl4           Major Shallow aquifer         Background 2 PW#2               Drinking water            Production Well #2 Supply PW#3               Drinking water            Produ ction Well #3 Supply PW#4               Drink ing 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 2015 FNP Annual Radiological Environmental Operating Report             30 I Page

LA T         LE                                                        NUAL ADIOL GICAL ENVIRONMENT                        EPORT Rl                27 .6               NDM                   NDM                87 .2 R2                45 .1                53.7                 6.87               96.9 R3               1690                  1870                 1660              1650 R4               NDM                   145                  NDM               NDM RS                45.4                NDM                    143              NDM R6                182                 NDM                   78.4              NDM R7                90 .5                16.3                  123              NDM R8                50.6                 57 .9                NDM                28.9 R9                60 .3               NDM                   76 .1             NDM RlO                60.5                NDM                   41.6              NDM Rll               NDM                   9.33                  110              NDM R13               NDM                  NDM                   27.1              NDM R14                131                 NDM                   NDM               NDM PW#2                173                 NDM                   NDM               NDM PW#3         NS - Out of Service NS - Out of Service   NS - Out of Service       173 PW#4               NDM                  NDM                   NDM                209 CW West              NDM                  NDM                   NDM               NDM CW East             NDM                   74 .5         NS - Out of Service       179 FRW               NDM                  NDM                   NDM                248 SW-1               NDM                   53 .6                NDM               NDM NDM - No Detectable Measurements NS - Not Samp led 2015 FNP Annual Radiological Environmental Operating Report          31   I Page

LANT fARLE                                                                   NNUAL      ADIOLOGICAL NVIRONMENT l                   TING REPO 4 SURVEY SUMMARIES 4.1     Land Use Census In accordance with ODCM 4.1.2, a land use census was conducted on November 25, 2015 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.
The census results are tabulated in Table 4.1-1. The 2015 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 2014 census, nor were any milk animals located within a five-mile radius .
In accordance with ODCM 4.1.2, a land use census was conducted on November 25, 2015 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 0.2 miles). This location was evaluated under CAR 249563 in accordance with ODCM 4.1.2.2.1. There were no significant differences in X/Q or D/Q values or radiological doses between the new location and the previous location.
Table 4-1. Land Use Census Results Sector                          Residence                       Milk Animal Distance in M iles 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 2015 FNP Annual Radiological Environmental Operating Report                   32 I Page

LA Tf                                                              NNUAL     ADI LOGICAL NVIRONMENT L 4.2      Chattahoochee River Survey A previous river survey performed for Plant Farley 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.
In June 2015, a survey was sent to the Alabama Department of Environmental Management (ADEM) and Alabama Department of Economic and Community Affairs (ADECA) to request any information about river use permits that had been issued in the area near the plant. No additional withdrawal permits or intake locations had been added at the time of the survey.
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LA T A LE                                                         NNUAL      ADIOLOGICAL T
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 2015 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 2015 FNP Annual Radiological Environmental Operating Report          34 I Page}}