View source for NL-09-0775, Annual Radiological Environmental Operating Reports for 2008

{{Adams
| number = ML091390815
| issue date = 05/14/2009
| title = Annual Radiological Environmental Operating Reports for 2008
| author name = Caston M
| 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-09-0775
| document type = Annual Operating Report, Environmental Monitoring Report, Letter type:NL
| page count = 235
}}

=Text=
{{#Wiki_filter:Moanica M. Caston           Southern Nuclear Vice President,             Operating Company, Inc.
General Counsel and         40 Inverness Center Parkway Corporate Secretary         Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5316 SOUTHERNSLra COMPANY May 14, 2009                                                         Energy to Serve Your Worlde Docket Nos.: 50-321            50-348        50-424                    NL-09-0775 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 Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radioloqical Environmental Operatinq Reports for 2008 Ladies and Gentlemen:
In accordance with section 5.6.2 of the referenced plants' Technical Specifications, Southern Nuclear Operating Company hereby submits the Annual Radiological Environmental Operating Reports for 2008.
This letter contains no NRC commitments. If you have any questions, please advise.
Sincerely, M. Caston Vice President, External Affairs and General Counsel MC/TWS/daj

==Enclosures:==
: 1. Hatch Annual Radiological Environmental Operating Report for 2008
: 2. Farley Annual Radiological Environmental Operating Report for 2008
: 3. Vogtle Annual Radiological Environmental Operating Report for 2008

U. S. Nuclear Regulatory Commission NL-09-0775 Page 2 cc:   Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Mr. D. R. Madison, Vice President - Hatch Mr. T. E. Tynan, Vice President - Vogtle Ms. P. M. Marino, Vice President - Engineering RType: CFA04.054; CHA02.004; CVC7000 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley Ms. D. N. Wright, NRR Project Manager - Hatch Ms. D. N. Wright, NRR Project Manager - Vogtle Mr. E. L. Crowe, Senior Resident Inspector - Farley Mr. J. A. Hickey, Senior Resident Inspector - Hatch Mr. M. Cain, Senior Resident Inspector - Vogtle State of Alabama Mr. K. E. Whatley, Department of Public Health, Division of Radiation Control State of Georgia Mr. T. V. Jackson, Department of Natural Resources Georgia Power Company Ms. M. A. Heilbron American Nuclear Insurers Mr. R. A. Oliveira

Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radiological Environmental Operating Reports for 2008 Enclosure 1 Hatch Annual Radiological Environmental Operating Report for 2008

EDWIN I. HATCH NUCLEAR PLANT ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2008 SOUTHERN NA COMPANY Energy to Serve Your World"

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

LIST OF FIGURES Figure Number Title                                                 Page Figure 2-1    REMP Stations Near the Plant                          2-8 Figure 2-2    REMP Stations Beyond Six Miles from the Plant         2-9 Figure 2-3    Groundwater Monitoring Locations                      2-10 Figure 2-4    Deep Wells                                            2-11 Figure 4.2-1  Average Weekly Gross Beta Air Concentration           4-7 Figure 4.2-2  Average Annual Cs-137 Concentration in Air            4-9 Figure 4.3-1  Average Quarterly Exposure from Direct Radiation      4-13 Figure 4.3-2  Average Quarterly Exposure from Direct Radiation at Special Interest Areas                                4-15 Figure 4.4-1  Average Annual Cs-137 Concentration in Milk           4-18 Figure 4.4-2  Average Annual 1-131 Concentration in Milk            4-20 Figure 4.5-1  Average Annual Cs-137 Concentration in Vegetation     4-23 Figure 4.6-1  Average Annual H-3 Concentration in River Water       4-26 Figure 4.7-1  Average Annual Cs-137 Concentration in Fish           4-28 Figure 4.7-2  Average Annual Cs-134 Concentration in Fish           4-30 Figure 4.8-1  Average Annual Co-60 Concentration in Sediment        4-32 Figure 4.8-2  Average Annual Cs-137 Concentration in Sediment       4-34 Figure 4.8-3  Average Annual Indicator Station Concentrations of Select Nuclides in Sediment                        4-36 Figure 4.9-1  Plant Hatch Tritium Concentration Levels October 2008 4-41 ii

LIST OF TABLES Table Number Title                                               Page Table 2-1    Summary Description of Radiological Environmental Monitoring Program                                  2-2 Table 2-2    Radiological Environmental Sampling Locations       2-5 Table 2-3    Groundwater Sampling Locations                      2-7 Table 3-1    Radiological Environmental Monitoring Program Annual Summary                                      3-2 Table 4-1    Minimum Detectable Concentrations (MDC)             4-1 Table 4-2    Reporting Levels (RL)                               4-2 Table 4-3   Deviations from Radiological Environmental Monitoring Program                                  4-4 Table 4.1-1 Land Use Census Results                             4-5 Table 4.2-1 Average Weekly Gross Beta Air Concentration         4-8 Table 4.2-2 Average Annual Cs-137 Concentration in Air          4-10 Table 4.3-1 Average Quarterly Exposure from Direct Radiation    4-14 Table 4.3-2 Average Quarterly Exposure from Direct Radiation at Special Interest Areas                              4-16 Table 4.4-1 Average Annual Cs-137 Concentration in Milk         4-19 Table 4.4-2 Average Annual 1-131 Concentration in Milk          4-21 Table 4.5-1 Average Annual Cs-137 Concentration in Vegetation   4-24 Table 4.6-1 Average Annual H-3 Concentration in River Water     4-27 Table 4.7-1 Average Annual Cs-137 Concentration in Fish         4-29 Table 4.7-2 Average Annual Cs-134 Concentration in Fish         4-31 Table 4.8-1 Average Annual Co-60 Concentration in Sediment      4-33 Table 4.8-2 Average Annual Cs-137 Concentration in Sediment     4-35 Table 4.8-3 Sediment Nuclide Concentrations Other Than Co-60 &
Cs-137                                              4-37 Table 5-1   Interlaboratory Comparison Results                  5-3 iii

LIST OF ACRONYMS Acronyms presented in alphabetical order.
Acronym   Definition ASTM      American Society for Testing and Materials CL         Confidence Level EL         Georgia Power Company Environmental Laboratory EPA       Environmental Protection Agency GPC        Georgia Power Company HNP        Edwin I. Hatch Nuclear Plant ICP        Interlaboratory Comparison Program MDC        Minimum Detectable Concentration MDD        Minimum Detectable Difference NA         Not Applicable NDM        No Detectable Measurement(s)
NRC        Nuclear Regulatory Commission ODCM       Offsite Dose Calculation Manual Po         Preoperation REMP       Radiological Environmental Monitoring Program RL         Reporting Level TLD        Thermoluminescent Dosimeter TS         Technical Specification iv

==1.0 INTRODUCTION==

The Radiological Environmental Monitoring Program (REMP) is conducted in accordance with Chapter 4 of the Offsite Dose Calculation Manual (ODCM).
REMP activities for 2008 are reported herein in accordance with Technical Specification (TS) 5.6.2 and ODCM 7.1.
The objectives of the REMP are to:
: 1) Determine the levels of radiation and the concentrations of radioactivity in the environs and;
: 2) Assess the radiological impact (if any) to the environment due to the operation of the Edwin I. Hatch Nuclear Plant (HNP).
The assessments include comparisons between the results of analyses of samples obtained at locations where radiological levels are not expected to be affected by plant operation (control stations) and at locations where radiological levels are more likely to be affected by plant operation (indicator stations), as well as comparisons between preoperational and operational sample results.
The pre-operational stage of the REMP began with the establishment and activation of the environmental monitoring stations in January of 1972. The operational stage of the REMP began on September 12, 1974 with Unit 1 initial criticality.
A description of the REMP is provided in Section 2 of this report. An annual summary of the results of the analyses of REMP samples is provided in Section 3.
A discussion of the results, including assessments of any radiological impacts upon the environment, and the results of the land use census and the river survey, are provided in Section 4. The results of the Interlaboratory Comparison Program (ICP) are provided in Section 5. Conclusions are provided in Section 6.
1-I

2.0 REMP DESCRIPTION A summary description of the REMP is provided in Table 2-1. This table summarizes the program as it meets the requirements outlined in ODCM Table 4-1. It details the sample types to be collected and the analyses to be performed in order to monitor the airborne, direct radiation, waterborne and ingestion pathways, and also delineates the collection and analysis frequencies. The sampling locations (stations) specified by ODCM 4.2 are depicted on maps in Figures 2-1 and 2-2.
These maps are keyed to Table 2-2 which delineates the direction and distance of each station from the main stack.
REMP samples are collected by Georgia Power Company's (GPC) Environmental Laboratory (EL) personnel. The same lab performs all the laboratory analyses at their headquarters in Smyrna, Georgia.
2-1

TABLE 2-1 (SHEET 1 of 3)

==SUMMARY==
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway                         Approximate                             Sampling and                                 Type of Analysis and Frequency and/or Sample                            Number of Sample                        Collection Frequency Locations
: 1. Airborne                             6                                       Continuous operation                        Radioiodine canister: 1-131 analysis, weekly.
Radioiodine and                                                                  of the sampler with Particulates                                                                     sample collection                           Particulate sampler: analyze for gross beta radioactivity not less weekly.                                     than 24 hours following filter change, weekly; perform gamma isotopic analysis on affected sample when gross beta activity is 10 times the yearly mean of control samples; and composite (by location) for gamma isotopic analysis, quarterly.
: 2. Direct Radiation                       37                                     Quarterly                                    Gamma dose, quarterly.
             . .3.                                     ....................................................
i.........................................................................n...gIi......o......
Milk (a)                      1                                      Biweekly                                     Gamma isotopic and 1-131 analysis, biweekly.
Fish or Clams (b)                     2                                      Semiannually                                 Gamma isotopic analysis on edible portions, semiannually.
Grass or Leafy                      3                                      Monthly during                               Gamma isotopic analysis, monthly. (c)
Vegetation                                                             growing season.
: 4. Waterbome Surface                      2                                      Composite sample                             Gamma isotopic analysis, monthly. Composite (by location) for collected monthly. (d)                      tritium analysis, quarterly.
.................     .........................................                                                                G               ...... c       ....        s i................l.......................................................
Sediment                       2                                      Semiannually.                                Gamma isotopic analysis, semiannually.

TABLE 2-1 (SHEET 2 of 3)

==SUMMARY==
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway   Approximate             Sampling and                  Type of Analysis and Frequency and/or Sample      Number of Sample        Collection Frequency Locations Drinking Water     One sample of river     River water collected         1-131 analysis on each sample when biweekly collections are (e&f)              water near the intake   near the intake will be       required. Gross beta and gamma isotopic analysis on each and one sample of       a composite sample;           sample; composite (by location) for tritium analysis, quarterly.
finished water from     the finished water will each of one to three    be a grab sample.
of the nearest water    These samples will be supplies which could    collected monthly be affected by HNP      unless the calculated discharges.             dose due to consumption of the water is greater than 1 mrem/year; then the collection will be biweekly. The collections may revert to monthly should the calculated doses become less than 1 I.........................
I...................
mremlyear.               ....
Groundwater        See Table 2-3, Figure Quarterly sample;               Tritium, gamma isotopic, and field parameters (pH, 2-3, and Figure 2-4     pump used to sample           temperature, conductivity, dissolved oxygen, GW wells; grab                oxidation/reduction potential, and turbidity) of each sample sample from yard              quarterly; Hard to detect radionuclides as necessary based on drains and ponds              results of tritium and gamma i
* a

TABLE 2-1 (SHEET 3 of 3)

==SUMMARY==
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Notes:
: a. Up to three sampling locations within 5 miles and in different sectors will be used as available. In addition, one or more control locations beyond 10 miles will be used.
: b. Commercially or recreationally important fish may be sampled. Clams may be sampled if difficulties are encountered in obtaining sufficient fish samples.
: c. If gamma isotopic analysis is not sensitive enough to meet the Minimum Detectable Concentration (MDC), a separate analysis for 1-131 may be performed.
: d. The composite samples shall be composed of a series of aliquots collected at intervals not exceeding a few hours.
: e. If it is found that river water downstream of the plant is used for drinking, drinking water samples will be collected and analyzed as specified herein.
: f. A survey shall be conducted annually at least 50 river miles downstream of the plant to identify those who use water from the 4)
Altamaha River for drinking.

TABLE 2-2 (SHEET 1 of 2)
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Station  Station   Descriptive Location      Direction Distance (a) Sample Type Number   Type                                (a)           (miles) 064     Other     Roadside Park             WNW       0.8                 Direct Rad 101    Indicator Inner Ring                N         1.9                 Direct Rad 102    Indicator Inner Ring                NNE       2.5                 Direct Rad 103    Indicator Inner Ring                NE        1.8                 Airborne Rad Direct Rad 104    Indicator Inner Ring                ENE       1.6                 Direct Rad 105    Indicator Inner Ring                E         3.7                 Direct Rad 106    Indicator Inner Ring                ESE       1.1                 Direct Rad Vegetation 107    Indicator Inner Ring                SE        1.2                 Airborne Rad Direct Rad 108    Indicator Inner Ring                SSE       1.6                 Direct Rad 109    Indicator Inner Ring                S         0.9                 Direct Rad 110    Indicator Inner Ring                SSW       1.0                 Direct Rad 111    Indicator Inner Ring                SW        0.9                 Direct Rad 112    Indicator Inner Ring                WSW       1.0                 Airborne Rad Direct Rad Vegetation 113    Indicator Inner Ring                W         1.1                 Direct Rad 114    Indicator Inner Ring                WNW       1.2                 Direct Rad 115    Indicator Inner Ring                NW        1.1                 Direct Rad 116    Indicator Inner Ring                NNW       1.6                 Airborne Rad I_                                                                 Direct Rad 170    Control   Upstream                  WNW       (c)                 River (b) 172    Indicator Downstream                E         (c)                 River (b) 201    Other     Outer Ring                N         5.0                 Direct Rad 202    Other     Outer Ring                NNE       4.9                 Direct Rad 203    Other     Outer Ring                NE        5.0                 Direct Rad 204    Other     Outer Ring                ENE       5.0                 Direct Rad 205    Other     Outer Ring                E         7.2                 Direct Rad 206    Other     Outer Ring                ESE       4.8                 Direct Rad 207    Other     Outer Ring                SE        4.3                 Direct Rad 208    Other     Outer Ring                SSE       4.8                 Direct Rad 209    Other     Outer Ring                S         4.4                 Direct Rad 210    Other     Outer Ring                SSW       4.3                 Direct Rad 211    Other     Outer Ring                SW        4.7                 Direct Rad 212    Other     Outer Ring                WSW       4.4                 Direct Rad 213    Other     Outer Ring                W         4.3                 Direct Rad 214    Other     Outer Ring                WNW       5.4                 Direct Rad 215    Other     Outer Ring                NW        4.4                 Direct Rad 216    Other     Outer Ring                NNW       4.8                 Direct Rad 301    Other     Toombs Central School     N         8.0                 Direct Rad 304    Control   State Prison              ENE       11.2                Airborne Rad Direct Rad 304    Control   State Prison              ENE       10.3                Milk 309    Control   Baxley                    S         10.0                Airborne Rad Substation                                              Direct Rad 416    Control   Emergency News            NNW       21.0                Direct Rad I_         Center                   II                  ___Vegetation 2-5

TABLE 2-2 (SHEET 2 of 2)
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Notes:
: a. Direction and distance are determined from the main stack.
: b. River (fish or clams, shoreline sediment, and surface water)
: c. Station 170 is located approximately 0.6 river miles upstream of the intake structure for river water, 1.1 river miles for sediment and clams, and 1.5 river miles for fish.
Station 172 is located approximately 3.0 river miles downstream of the discharge structure for river water, sediment and clams, and 1.7 river miles for fish.
The locations from which river water and sediment may be taken can be sharply defined.
However, the sampling locations for clams often have to be extended over a wide area to obtain a sufficient quantity. High water adds to the difficulty in obtaining clam samples and may also make an otherwise suitable location for sediment sampling unavailable. A stretch of the river of a few miles or so is generally needed to obtain adequate fish samples. The mile locations given above represent approximations of the locations where samples are collected.
2-6

Table 2-3 Groundwater Monitoring Locations WELL       DEPTH (ft)                  MONITORING PURPOSE R1          82.9         Confined Aquifer Upgradient R2          82.7         Confined Aquifer Near Diesel Generator Bldg.
R3          89.2         Confined Aquifer Near CST-1 R4          41           Dilution Line Near River Water Discharge Structure R5          33.6         Between Subsurface Drain Lines Downgradient R6          38.2         Between Subsurface Drain Lines Downgradient NW2A        27           Water Table Near CST-2 Inside of Subsurface Drain NW2B        27           Water Table Outside of Subsurface Drain NW3A        26.5         Water Table Inside of Subsurface Drain NW3B        25.3         Water Table Outside of Subsurface Drain NW4A        27           Water Table Upgradient Inside of Subsurface Drain NW5A        26.7         Water Table Upgradient Inside of Subsurface Drain NW5B        26.3         Water Table Upgradient Outside of Subsurface Drain NW6         27           Water Table Near Diesel Generator Bldg.
NW8         23           Water Table Near Diesel Generator Bldg.
NW9         26.1         Water Table Downgradient Inside of Subsurface Drain NW10        26.2         Water Table Near CST-2 T2          21.9         Water Table Near Recombiner Bldg.
T3          18           Water Table Near Turbine Bldg.
T7          21.4         Water Table Near Diesel Generator Bldg.
T10         18.8         Water Table Near CST-1 T12         23.2         Water Table Near CST-1 T15         27.4         Water Table Near CST-1 P15A        74.5         Confined Aquifer Near Turbine Bldg.
P15B        18           Water Table Near Turbine Bldg.
P17A        77           Confined Aquifer Near Diesel Generator Bldg.
P1 7B       14.8         Water Table Near Diesel Generator Bldg.
Deep Well 1 680          Backup Supply for Potable Water (infrequently used)
Deep Well 2 711          Plant Potable Water Supply Deep Well 3 710          Potable Water Supply - Rec. Center, Firing Range, and Garage 2-7

N Radiological Environmental Sampling Locations       REMP Stations Near Indicator Control Additional TLD             A       A         A              the Plant Other                   0        0 TLD & Other                                       Figure 2-1 2-8

205 Radiological Environmental Sampling Locations       REMP Stations Beyond Indicator Control Additional TLD             A       A         A          Five Miles from the Plant Other          *
* 0 TLD & Other                                           Figure 2-2 2-9

Lii Figure 2-3 Groundwater Monitoring Locations 2-10

Figure 2-4 Deep Wells ED-
                                            -I-AREA WATER BLDG DEEP WELL22 D
DEEP WELL 3 2-11

3.0 RESULTS 

==SUMMARY==

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

TABLE 3-1 (SHEET 1 of 4)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Edwin I. Hatch Nuclear Plant, Docket Nos. 50-321 and 50-366 Appling County, Georgia Medium or        Type and Total   Minimum          Indicator          Location with the Highest  Other       Control Pathway          Number of        Detectable       Locations                Annual Mean          Stations(g) Locations Sampled          Analyses         Concentration    Mean (b),                                     Mean (b),   Mean (b),
(Unit of         Performed        (MDC) (a)        Range           Name Distance Mean (b),       Range       Range Measurement)                                       (Fraction)      & Direction       Range       (Fraction)  (Fraction)
(Fraction)
Airborne         Gross Beta       10               21.8            No. 309             22.5      NA          22.5 Particulates     311                               7.6-39.1        Baxley              11.8-40.8             8.3-40.8 (fCi/m3)                                           (208/208)       Substation          (52/52)               (103/103) 10.0 miles, S Gamma   Isotopic 24 Cs-134           50               NDM (c)                             NDM                   NDM Cs-137           60               NDM                                 NDM                   NDM Airborne         1-131            70               NDM                                 NDM       NA          NDM N., Radioiodine      311 (fCi/m3)
Direct Radiation Gamma Dose       NA (d)           13.0            No. 104             16.5       12.4       12.3 (mR/91 days)     147                               10.0-19.3       Inner Ring          14.7-18.6 9.3-18.3    10.1-14.8 (63/63)          1.6 miles, ENE     (3/3)     (72/72)     (12/12)
Milk             Gamma Isotopic                                                                  NA (pCi/l)          26 Cs-134           15               NA                                  NDM                   NDM Cs-137           18               NA                                  NDM                   NDM Ba-140           60               NA                                  NDM                   NDM La- 140          15               NA                                  NDM                   NDM I-1311                            NA                                  NDM                   NDM 26

TABLE 3-1 (SHEET 2 of 4)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Edwin I. Hatch Nuclear Plant, Docket Nos. 50-321 and 50-366 Appling County, Georgia Medium or     Type and     Minimum           Indicator                 Location with the Highest       Control Pathway       Total Number Detectable        Locations                        Annual Mean              Locations Sampled       of Analyses  Concentration     Mean (b),                                                 Mean (b),
(Unit of      Performed    (MDC) (a)         Range             Name Distance          Mean (b),        Range Measurement)                                 (Fraction)        & Direction            Range (Fraction) (Fraction)
Vegetation    Gamma (pCi/kg-wet)  Isotopic 36 1-131        60                NDM                                       NDM             NDM Cs-134       60                NDM                                       NDM             NDM Cs-137       80                41.8              Station 106             48.2            38.1 15.9-85.4         Inner Ring              15.9-85.4       (1/12)
(7/24)            1.1 miles; ESE          (5/12)
River Water   Gamma (pCi/l)       Isotopic 24 Mn-54        15                NDM                                       NDM             NDM Fe-59        30                NDM                                       NDM             NDM Co-58        15                NDM                                       NDM             NDM Co-60        15                NDM                                       NDM             NDM Zn-65        30                NDM                                       NDM             NDM Zr-95        30                NDM                                       NDM             NDM Nb-95        15                NDM                                       NDM             NDM 1-131        15 (e)            NDM                                       NDM             NDM Cs-134       15                NDM                                       NDM             NDM Cs-137       18                NDM                                       NDM             NDM Ba-140       60                NDM                                       NDM             NDM La- 140      15                NDM                                       NDM             NDM Tritium      3000 (f)          329               No. 170                 329             298 8                              284-373           0.6 miles               284-373         (1/4)
(2/4)             Upstream                (2/4)

TABLE 3-1 (SHEET 3 of 4)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Edwin I. Hatch Nuclear Plant, Docket Nos. 50-321 and 50-366 Appling County, Georgia Medium or     Type and     Minimum           Indicator                 Location with the Highest   Control Pathway       Total Number Detectable        Locations                         Annual Mean         Locations Sampled       of Analyses  Concentration     Mean (b),                                             Mean (b),
(Unit of      Performed    (MDC) (a)         Range             Name Distance Mean (b),             Range Measurement)                                 (Fraction)        & Direction        Range (Fraction) (Fraction)
Fish          Gamma (pCi/kg-wet)  Isotopic 6
Mn-54        130               NDM                                       NDM         NDM Fe-59        260               NDM                                       NDM         NDM Co-58        130               NDM                                       NDM         NDM Co-60        130               NDM                                       NDM         NDM Zn-65        260               NDM                                       NDM         NDM Cs- 134      130               NDM                                       NDM         NDM Cs-137       150               19.9              No. 172                 19.9        8.4 18.5-21.2         3.0 miles               18.5-21.2   7.5-9.3 (3/3)             Downstream              (3/3)       (2/3)
Sediment      Gamma (pCi/kg-dry)  Isotopic 4
Cs-134       150               NDM                                       NDM         NDM Cs-137       180               112.7             No. 172                 112.7       61.9 103.9-121.4       3.0 miles               103.9-121.4 (1/2)
(2/2)             Downstream              (2/2)

TABLE 3-1 (SHEET 4 of 4)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Edwin I. Hatch Nuclear Plant, Docket Nos. 50-321 and 50-366 Appling County, Georgia NOTATIONS
: a. The MDC is defined in ODCM 10.1. Except as noted otherwise, the values listed in this column are the detection capabilities required by ODCM Table 4-3. The values listed in this column are a priori (before the fact) MDCs. In practice, the a posteriori (after the fact) MDCs are generally lower than the values listed. Any a posteriori MDC greater than the value listed in this column is discussed in Section 4.
: b. Mean and range are based upon detectable measurements only. The fraction of all measurements at specified locations that are detectable is placed in parenthesis.
: c. No Detectable Measurement(s).
: d. Not Applicable.
: e. If a drinking water pathway were to exist, a MDC of 1 pCi/l would have been used (see Table 4-1 of this report).
: f. If a drinking water pathway were to exist, a MDC of 2000 pCi/l would have been used (see Table 4-1 of this report).
: g. "Other" stations, identified in the "station type" column of Table 2-2, include community and special stations.

4.0        DISCUSSION OF RESULTS Included in this section are evaluations of the laboratory results for the various sample types. Comparisons were made between the difference in mean values for pairs of station groups (e.g., indicator and control stations) and the calculated Minimum Detectable Difference (MDD) between these pairs at the 99%
Confidence Level (CL). The MDD was determined using the standard Student's t-test. A difference in the mean values which was less than the MDD was considered to be statistically indiscernible.
The 2008 results were compared with past results, including those obtained during pre-operation. As appropriate, results were compared with their Minimum Detectable Concentrations (MDC) and Reporting Levels (RL) which are listed in Tables 4-1 and 4-2 of this report, respectively. The required MDCs were achieved during laboratory sample analyses. Any anomalous results are explained within this report.
Results of interest are graphed to show historical trends. The data points are tabulated and included in this report. The points plotted and provided in the tables represent mean values of only detectable results. Periods for which no detectable measurements (NDM) were observed or periods for which values were not applicable (e.g., milk indicator, etc.) are plotted as O's and listed in the tables as NDM.
Table 4-1 Minimum Detectable Concentrations (MDC)
Analysis         Water        Airborne          Fish          Milk        Grass or       Sediment (pCi/_)     Particulate      (pCi/kg-       (pCi/))        Leafy         (pCi/kg-or Gases          wet)                     Vegetation         dry)
(fCi/m3)                                  (pCi/kg-wet)
Gross Beta           4             10 H-3         2000 (a)
Mn-54            15                            130 Fe-59            30                           260 Co-58            15                            130 Co-60            15                            130 Zn-65            30                           260 Zr-95            30 Nb-95            15 1-131             1 (b)        70                            1             60 Cs-134            15             50             130           15             60             150 Cs-137            18             60             150           18             80             180 Ba-140            60                                          60 La-140            15                                          15 (a) If no drinking water pathway exists, a value of 3000 pCi/l may be used.
(b) If no drinking water pathway exists, a value of 15 pCi/l may be used.
4-1

Table 4-2 Reporting Levels (RL)
Analysis          Water        Airborne            Fish       Milk (pCi/l) Grass or Leafy (pCi/l)     Particulate      (pCi/kg-wet)                  Vegetation or Gases                                    (pCi/kg-wet)
(fCi/m3)
H-3          20,000 (a)
Mn-54             1000                           30,000 Fe-59              400                           10,000 Co-58             1000                           30,000 Co-60              300                           10,000 Zn-65              300                           20,000 Zr-95             400 Nb-95              700 1-131               2 (b)        900                              3            100 Cs- 134             30           10,000           1000            60           1000 Cs-137              50          20,000            2000            70          2000 Ba-140             200                                           300 La-140             100                                           400 (a) This is the 40 CFR 141 value for drinking water samples. If no drinking water pathway exists, a value of 30,000 may be used.                                                  K (b) If no drinking water pathway exists, a value of 20 pCi/1 may be used.
4-2

Atmospheric nuclear weapons tests from the mid 1940s through 1980 distributed man-made nuclides around the world. The most recent atmospheric tests in the 1970s and in 1980 had a significant impact upon the radiological concentrations found in the environment prior to and during preoperation, and the earlier years of operation. Some long lived radionuclides, such as Cs-137, continue to be detectable.
Significant upward trends also followed the Chernobyl incident which began on April 26, 1986.
In accordance with ODCM 4.1.1.2.1, deviations from the required sampling schedule are permitted, if samples are unobtainable due to hazardous conditions, unavailability, inclement weather, equipment malfunction or other just reasons.
Deviations from conducting the REMP as described in Table 2-1 are summarized in Table 4-3 along with their causes and resolutions.
All results were tested for conformance to Chauvenet's criterion (G. D. Chase and J. L. Rabinowitz, Principles of Radioisotope Methodology, Burgess Publishing Company, 1962, pages 87-90) to identify values which differed from the mean of a set by a statistically significant amount. Identified outliers were investigated to determine the reason(s) for the difference. If equipment malfunction or other valid physical reasons were identified as causing the variation, the anomalous result was excluded from the data set as non-representative.          No data were excluded exclusively for failing Chauvenet's  criterion. Data exclusions are discussed in this section under the appropriate sample type.
4-3

TABLE 4-3 DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM COLLECTION         AFFECTED       DEVIATION                        CAUSE                                  RESOLUTION PERIOD             SAMPLES 01/28/08-02/04/08  AF/AC          Non-representative sample of     Power loss during rewiring work in Station operated satisfactorily CR2008111149       Station 309    airborne particulates.           area; lost -100 hours sample time. after power restored.
10.0 miles S 1s Quarter         TLD            Non-representative direct        TLDs destroyed in a fire.              Replaced TLDs at beginning CR2008111151       Station 110    radiation data.                                                         of quarter.
1.0 mile SSW 06/23/08-06/30/08  AF/AC          Non-representative sample of     Breaker on power pole tripped;         GPC trouble man contacted.
CR2008111152       Station 304    airborne particulates.           lost -116.4 hours of sample time.      Sample station operated EXCLUDED           11.2 miles ENE                                                                         satisfactorily after power restored.
07/28/08-08/04/08  AF/AC          Non-representative sample of     Fuse on power pole tripped; lost       Station operated satisfactorily CR2008111153       Station 304    airborne particulates.           -69.2 hours of sample time.            after power restored.
11.2 miles ENE 3 rd Quarter       TLD            No direct radiation data         TLDs missing at mid-quarter            Replaced TLDs at beginning CR2009104826       Station 104    available,                       checks.                                of quarter.
EXCLUDED           1.6 miles ENE Second Semi-       Fish           Fall fish collection postponed. Unable to do electrofishing due to Fish was collected on Annual Collection                                                  low river water level during the fall. 01/06/09.
Period CR2009101127

4.1    Land Use Census and River Survey In accordance with ODCM 4.1.2, a land use census was conducted on November 10, 2008, to determine the locations of the nearest permanent residence and milk animal in each of the 16 compass sectors within a distance of 5 miles, and the locations of all milk animals within a distance of 3 miles. A milk animal is defined as a cow or goat producing milk for human consumption. The locations of beef cattle and of gardens greater than 500 square feet producing broad leaf vegetation were also included in the census. The census results are tabulated in the Table 4.1-1.
Table 4.1-1 LAND USE CENSUS RESULTS Distance in Miles to Nearest Location in Each Sector SECTOR        RESIDENCE         MILK ANIMAL         BEEF CATTLE        [      GARDEN N               2.1               None                None                  None NNE               2.9               None                None                  None NE               3.3               None                 3.5                    3.5 ENE               4.2               None                 4.1                  None E               3.0               None                None                  None ESE              3.8               None                None                  None SE              1.8               None                 2.3                    4.4 SSE              2.0               None                 3.6                    4.5 S              1.1               None                 2.3                    2.3 SSW               1.5               None                 2.0                  None SW               1.1               None                 2.3                    1.6 WSW               1.0               None                 4.8                    1.6 W               1.1               None                 2.8                  None WNW               1.1               None                None                  None NW               3.6               None                  3.2                 None NNW               1.9               None                 2.8                    2.8 4-5

ODCM 4.1.2.2.1 requires a new controlling receptor to be identified if the land use census identifies a location that yields a calculated receptor dose greater than the one in current use. No change in the controlling receptor was required as a result of the 2008 land use census. The current controlling receptor as described in ODCM Table 3-7 is a child in the WSW Sector at 1.2 miles ODCM 4.1.2.2.2 requires that whenever the land use census identifies a location which would yield a calculated dose (via the same ingestion pathway) 20% greater than that of a current indicator station, the new location must become a REMP station (if samples are available). The 2008 land use census did not identify a garden which yielded a calculated dose 20% greater than that for any of the current indicator stations for vegetation. The results of the census were corroborated by inquiries to the county extension agents in the 5 counties in the vicinity of the plant.
As required by Note f of Table 2-1, the annual survey of the Altamaha River for 50 miles downstream of the plant was conducted on September 22, 2008 to identify any withdrawal of river water for drinking purposes. No sources of withdrawal for drinking water purposes were identified. One irrigation source was noted about 3/4 miles downriver from river water Station #172 belonging to Clarke Farms who informed GPC that peanuts were being irrigated. Information obtained from the Georgia Department of Natural Resources on October 2, 2008 indicated that no surface water withdrawal permits for agricultural or drinking purposes had been issued for this stretch of the Altamaha River between the 2007 survey and the 2008 survey. Should it be determined that river water downstream of the plant is being used for drinking, the sampling and analysis requirements for drinking water found in Table 2-1 would be implemented.
4-6

4.2       Airborne As indicated in Table 2-2 and Figures 2-1 and 2-2, airborne particulates and airborne radioiodine are collected at 4 indicator stations (Nos. 103, 107, 112 and 116) which encircle the plant near the site periphery and at 2 control stations (Nos.
304 and 309) which are located approximately 10 miles from the main stack. At each location, air is continuously drawn through a glass fiber filter and a charcoal canister placed in series to collect airborne particulates and radioiodine. The filters and canisters are collected weekly and analyzed for gross beta and 1-131, respectively. A gamma isotopic analysis is performed quarterly on a composite of the filters for each station.
The 2008 annual average weekly gross beta concentration of 21.8 fCi/m 3 for the indicator stations was 0.7 fCi/m- less than that for the control stations (22.5 fCi/m 3). This difference is not statistically discernible, since it is less than the calculated MDD of 1.8 fCi/m 3 . Figure 4.2-1 and Table 4.2-1 provide the historical trending of the average weekly gross beta concentrations in air. In general, there is close agreement between the results for the indicator and control stations. This close agreement supports the position that the plant is not contributing significantly to the gross beta concentration in air.
Figure 4.2-1 Average Weekly Gross Beta Air Concentration 300 250 520O 0
150-C 0.~
q0 Ab AA-nio                       C       ]
Year I-MDC   MIndicator   A&- Control 4-7

Table 4.2-1 Average Weekly Gross Beta Air Concentration Year                 Indicator               Control (fCi/m3)               (fCi/m3)
Pre-op                   140                    140 1974                     87                    90 1975                     85                    90 1976                    135                    139 1977                    239                   247 1978                    130                    137 1979                     38                    39 1980                     49                    48 1981                    191                   203 1982                     33                    34 1983                     31                    30 1984                     26                    28 1985                     22                    21 1986                     36                     38 1987                     23                    22 1988                   22.6                   21.7 1989                   18.4                   17.8 1990                    19.3                  18.7 1991                    18.1                    18 1992                    18.5                  18.4 1993                   20.4                   20.7 1994                    19.5                  19.7 1995                   21.7                   21.7 1996                   21.3                   21.4 1997                   20.3                   20.7 1998                   20.0                   20.5 1999                   21.3                   21.3 2000                   23.6                   23.9 2001                   21.5                   21.0 2002                    19.3                  19.2 2003                    18.8                  18.2 2004                   21.4                   21.3 2005                    19.7                  19.4 2006                   24.9                   24.7 2007                   24.4                   24.3 2008                   21.8                   22.5 4-8

During 2008, no man-made radionuclides were detected from the gamma isotopic analysis of the quarterly composites of the particulate air filters. During preoperation and during operation through 1986, a number of fission products and activation products were detected. These were generally attributed to the nuclear weapons tests and to the Chernobyl incident. On only one occasion since 1986, has a man-made radionuclide been detected in a quarterly composite. A small amount of Cs-137 (1.7 fCi/m3) was identified in the first quarter of 1991 at Station 304. The MDC and RL for Cs-137 in air are 60 and 20,000 fCi/m3, respectively.
The historical trending of the average annual concentrations of detectable Cs-137 from quarterly air filter composites is provided in Figure 4.2-2 and Table 4.2-2.
Figure 4.2-2 Average Annual Cs-137 Concentration in Air 60 50 4
E-O 30 ro 20 10 Qo Year Indicator--Cotl             MD 4-9

Table 4.2-2 Average Annual Cs-137 Concentration In Air Year                 Indicator               Control (fCi/m3)               (fCi/m3)
Pre-op                  NDM                     2.0 1974                     1.5                   2.0 1975                     1.4                   1.4 1976                     0.6                   0.7 1977                     1.5                   1.4 1978                     2.3                   2.6 1979                     0.8                   0.8 1980                     0.4                   0.6 1981                     1.8                   1.7 1982                     0.5                   0.6 1983                     0.7                  NDM 1984                   NDM                    NDM 1985                     0.7                  NDM 1986                     8.1                   9.6 1987                   NDM                    NDM 1988                   NDM                    NDM 1989                   NDM                    NDM 1990                   NDM                    NDM 1991                   NDM                     1.7 1992                   NDM                    NDM 1993                   NDM                    NDM 1994                   NDM                    NDM 1995                   NDM                    NDM 1996                   NDM                    NDM 1997                   NDM                    NDM 1998                   NDM                    NDM 1999                   NDM                    NDM 2000                   NDM                    NDM 2001                   NDM                    NDM 2002                   NDM                    NDM 2003                   NDM                    NDM 2004                   NDM                    NDM 2005                   NDM                    NDM 2006                   NDM                    NDM 2007                   NDM                    NDM 2008                   NDM                    NDM 4-10

No airborne 1-131 was detected in the charcoal canisters in 2008. During 1976, 1977, and 1978, positive levels of 1-131 were found in nearly all of the samples collected for a period of a few weeks following atmospheric nuclear weapons tests.
Some of the concentrations were on the order of 70 fCi/m 3 . In 1986, the same phenomenon occurred following the Chernobyl incident. The highest airborne 1-131 concentration found to date in an individual charcoal canister was 217 fCi/m 3 in 1977. The MDC and RL for airborne 1-131 are 70 fCi/m 3 and 900 fCi/m 3 , respectively.
Table 4-3 lists REMP deviations that occurred in 2008. Three deviations involved air sampling; one at Station #309 and two at Station #304. All three were related to power interruptions. Only one resulted in data exclusion. The results from the other two passed Chauvenet's Criterion and were included in the data set.
4-11

4.3 Direct Radiation Direct (external) radiation is measured with thermoluminescent dosimeters (TLDs). Two Panasonic UD-814 TLD badges are placed at each station. Each badge contains three phosphors composed of calcium sulfate crystals (with thulium impurity). The gamma dose at each station is based upon the average readings of the phosphors from the two badges. The badges for each station are placed in thin plastic bags for protection from moisture while in the field. The badges are nominally exposed for periods of a quarter of a year (91 days). An inspection is performed near mid-quarter to assure that all badges are on-station and to replace any missing or damaged badges.
Two TLD stations are established in each of the 16 compass sectors around the plant to form 2 concentric rings, as seen in Figures 2-1 and 2-2. The two ring configuration of stations was established in 1980, in accordance with NRC Branch Technical Position "An Acceptable Radiological Environmental Monitoring Program", Revision 1, 1979. With the exception of the East sector, the inner ring stations (Nos. 101 through 116) are located near the site boundary and the outer ring stations (Nos. 201 through 216) are located at distances of 4 to 5 miles from the plant. The stations in the East sector are a few miles farther out than the other stations in their respective rings due to large swamps making normal access extremely difficult. The 16 stations forming the inner ring are designated as the indicator stations. The 3 control stations (Nos. 304, 309 and 416) are located 10 miles or more from the plant. Stations 064 and 301 monitor special interest areas.
Station 064 is located at the onsite roadside park, while Station 301 is located near the Toombs Central School. Station 210, in the outer ring, is located near the Altamaha School (the only other nearby school).
As provided in Table 3-1, the average quarterly exposure measured at the indicator stations (inner ring) during 2008 was 13.0 mR. At the control stations, the average quarterly exposure was 12.3 mR. This difference (0.7 mR) is not statistically discernible since it is less than the MDD of 1.5 mR.
The quarterly exposures acquired at the outer ring stations during 2008 ranged from 9.3 to 18.3 mR, with an average of 12.4 mR. The average for the outer ring stations was 0.1 mR more than the average for the control stations. Since the results for the outer ring stations and the control stations differ by less than the MDD of 1.5 mR, there is no discernible difference between outer ring and control station results for 2008.
The historical trending of the average quarterly exposures for the indicator inner ring, outer ring, and the control stations are plotted in Figure 4.3-1 and listed in Table 4.3-1. The decrease between 1991 and 1992 values is attributed to a change in TLDs from Teledyne to Panasonic. It should be noted however that the differences between indicator and control and outer ring values did not change.
The close agreement between the station groups supports the position that the plant is not contributing significantly to direct radiation in the environment.
4-12

Figure 4.3-1 Average Quarterly Exposure from Direct Radiation E
1...
0 a.
Year I Indicator --U--Control -&-- Outer Ring I 4-13

Table 4.3-1 Average Quarterly Exposure from Direct Radiation Year          Indicator (mR)   I  Control (mR)    Outer Ring (mR)
Pre-op              22.3                23               NA 1974               23.2               25.6              NA 1975                10.0              10.5              NA 1976               8.18                6.9              NA 1977               7.31               6.52              NA 1978               6.67               6.01              NA 1979               5.16               6.77              NA 1980               4.44               5.04              4.42 1981                5.9                5.7               5.7 1982                12.3                12              11.3 1983                11.4              11.3              10.6 1984                13.3              12.9              11.9 1985                14.7              14.7              13.7 1986                 15                 14              14.5 1987                14.9              14.6              15.3 1988                15.0              14.7              15.2 1989                16.4              18.0              16.5 1990                14.9              13.9              14.7 1991                15.1              13.7              15.6 1992                11.9              10.9              12.3 1993                11.6              10.7              11.5 1994                 11               10.7              11.2 1995                11.5              10.8              11.3 1996                11.6              11.3              11.6 1997                12.3              11.8              12.3 1998                12.1              12.3              12.3 1999                12.8              13.2              13.0 2000                13.6              13.3              13.3 2001                12.0              12.1              11.8 2002                11.7              11.7              11.5 2003                11.4              11.4              11.4 2004                12.2              12.4              12.2 2005                12.1              12.5              12.0 2006                12.4              11.9              11.8 2007                12.8              12.5              12.6 2008                13.0              12.3              12.4 4-14

The historical trending of the average quarterly exposures at the special interest areas for the past 19 years is provided in Figure 4.3-2 and listed in Table 4.3-2. These exposures are within the range of those acquired at the other stations. They too, show that the plant is not contributing significantly to direct radiation at the special interest areas.
Figure 4.3-2 Average Quarterly Exposure from Direct Radiation at Special Interest Areas 25-20-I 0
a 5
0  t 86 87  88  89  90   91  92   93   94    95   96 97 98   99   00   01   02  03 04 05 06 07 08 Year 1--   Roadside Park (Sta 064) ---*-Toombs Central School (Sta 301) 1 4-15

Table 4.3-2 Average Quarterly Exposure from Direct Radiation at Special Interest Areas Period        Station 064    Station 301 (mR)          (mR) 1986              14.6          15.1 1987              14.2          15.0 1988              14.9          15.3 1989              16.1          16.6 1990              15.1          14.4 1991              14.4          15.2 1992              11.1          11.5 1993              11.2          10.8 1994              10.4          10.7 1995              11.0          10.5 1996              11.7          11.0 1997              12.6          11.4 1998              12.4          11.8 1999              12.5          12.4 2000              13.3          12.6 2001              11.8          11.3 2002              11.4          11.4 2003              11.2          11.1 2004              11.9          12.3 2005              11.8          12.4 2006              11.9          11.6 2007              11.9          12.1 2008              12.3          12.2 In 2008, there were two deviations involving direct radiation measurements. In the first quarter, the TLDs at Station 110 were destroyed in a fire. In the third quarter, the TLDs at Station 104 were missing at mid-quarter. Blanks were put in place at mid-quarter for both of these stations. The results passed Chauvenet's Criterion at Station 110 and were retained in the data set. The results failed Chauvenet's Criterion at Station 104 and were excluded from the data set.
The standard deviation for the quarterly result for each badge was subjected to a self-imposed limit of 1.4. This limit is based upon the standard deviations obtained with the Panasonic UD-814 badges during 1992 and is calculated using a method developed by the American Society of Testing and Materials (ASTM 4-16

Special Technical Publication 15D, ASTM Manual on Presentation of Data and Control Chart Analysis, Fourth Revision, Philadelphia, PA, October 1976).
The limit serves as a flag to initiate an investigation. To be conservative, readings with a standard deviation greater than 1.4 are excluded from the data set since the high standard deviation is interpreted as an indication of unacceptable variation in TLD response. In 2008, the following TLD results were excluded from the data set because their standard deviations were greater than 1.4:
First Quarter          113B Second Quarter         None Third Quarter          416A Fourth Quarter         114A For the stations listed above, where one badge at a station exhibited a standard deviation greater than 1.4, the reading of the companion badge at each location was used to determine the quarterly exposure. A deviation occurred in the first quarter that involved a large number of TLD results which had high standard deviations.
To minimize data loss, only the results from elements 3 and 4 were used to determine dose. The badges exceeding the self-imposed limit were visually inspected under a microscope and the glow curve and test results for the anneal data and the element correction factors were reviewed. No reason was evident for the high standard deviation.
4-17

4.4      Milk Milk samples are obtained biweekly from Station 304 (the state prison dairy) which is a control station located more than 10 miles from the plant. Gamma isotopic and I-131 analyses are performed on each sample as specified in Tables 2-1 and 2-2. Since 1989, efforts to locate a reliable milk sample source within 5 miles of the plant have been unsuccessful.
During 2008, no man-made radionuclides were detected from the gamma isotopic analysis of the milk samples. Cesium-137 was found in most of the samples each year from 1978 (when this analysis became a requirement) through 1989. No other man-made radionuclides have been detected by this analysis.
The MDC and RL for Cs-137 in milk are 18 and 70 pCi/l, respectively. The historical trending of the average annual detectable Cs-137 concentration in milk is provided in Figure 4.4-1 and Table 4.4-1.
Figure 4.4-1 Average Annual Cs-137 Concentration in Milk 25 20 15 0
U 5
0
     .Qo Year indicator -UW-Control       D 4-18

Table 4.4-1 Average Annual Cs-137 Concentration in Milk Year               Indicator            Control (pCi/l)            (pCi/l)
Pre-op                   19.9               19.4 1974                   NDM               NDM 1975                   NDM               NDM 1976                   NDM               NDM 1977                   NDM               NDM 1978                    12.1               18.3 1979                    16.1                13 1980                    14.7               15.4 1981                   12.57               10.2 1982                    11.8                11 1983                     12                7.2 1984                    9.6                10.2 1985                   9.14               5.35 1986                    9.8                 10 1987                   NDM                NDM 1988                    10.9             NDM 1989                    8.6                7.9 1990                   NDM                NDM 1991                   NDM                NDM 1992                   NDM                NDM 1993                   NDM                NDM 1994                   NDM                NDM 1995                   NDM                NDM 1996                   NDM                NDM 1997                   NDM                NDM 1998                   NDM                NDM 1999                   NDM                NDM 2000                   NDM                NDM 2001                   NDM                NDM 2002                   NDM                NDM 2003                   NDM                NDM 2004                   NDM                NDM 2005                   NDM                NDM 2006                   NDM                NDM 2007                   NDM                NDM 2008                   NDM                NDM 4-19

During 2008, 1-131 was not detected in any of the milk samples. During preoperation, all readings were less than 2 pCi/1 which was the allowed MDC at that time. Figure 4.4-2 and Table 4.4-2 provide the historical trending of the average annual detectable concentration of 1-131 in milk. In 1988, a single reading of 0.32 pCi/l, which was believed to have resulted from a procedural deficiency, was reported. The MDC and RL for 1-131 in milk are 1 and 3 pCi/l, respectively.
All the detectable results for Cs-137 and 1-131 are attributed to fallout from the nuclear weapons tests and the Chernobyl incident.
Figure 4.4-2 Average Annual 1-131 Concentration in Milk 16 14 i                i
__12 C.,
10 CL 10
          ~   /                 iii         -      -   -  -   -    -    -     -    -   -
2 0
q0 All 10   10   lt Year 1 0  Indicator -U-  Control   -MDC     -RLI 4-20

Table 4.4-2 Average Annual 1-131 Concentration in Milk Year                 Indicator            Control (pCi/l)             (pCi/l)
Pre-op                   NDM                 NDM 1974                    0.98                 2.6 1975                     0.3                NDM 1976                    12.23                9.1 1977                    14.61               4.08 1978                    2.72                4.18 1979                    NDM                 NDM 1980                     1.26               0.69 1981                    NDM                 NDM 1982                    NDM                 NDM 1983                    NDM                 NDM 1984                    NDM                 NDM 1985                    NDM                 NDM 1986                     8.9                 7.6 1987                    NDM                 NDM 1988                    NDM                 0.32 1989                    NDM                 NDM 1990                    NDM                 NDM 1991                    NDM                 NDM 1992                    NDM                 NDM 1993                    NDM                 NDM 1994                    NDM                 NDM 1995                    NDM                 NDM 1996                    NDM                 NDM 1997                    NDM                 NDM 1998                    NDM                 NDM 1999                    NDM                 NDM 2000                    NDM                 NDM 2001                    NDM                 NDM 2002                    NDM                 NDM 2003                    NDM                 NDM 2004                    NDM                 NDM 2005                    NDM                 NDM 2006                    NDM                 NDM-2007                    NDM                 NDM 2008                    NDM                 NDM 4-21

4.5 Vegetation In accordance with Tables 2-1 and 2-2, grass samples are collected monthly from two indicator stations near the site boundary (Nos. 106 and 112) and at one control station located about 21 miles from the plant (No. 416). Gamma isotopic analyses are performed on each sample. Gamma isotopic analysis on vegetation samples began in 1978 when the analysis became a TS requirement.
The results presented in Table 3-1 show that Cs-137 was the only man-made radionuclide detected in vegetation samples during 2008. Cs-137 was detected in seven samples collected at the indicator stations at an average value of 41.8 pCi/kg-wet. One samples collected at the control station had detectable Cs-137 at 38.1 pCi/kg-wet. Application of the modified Student's t-test shows that the difference of 3.7 pCi/kg-wet between the control and the indicator stations is not statistically discernible. The Cs-137 seen at the indicator stations could potentially be attributed to plant effluents.
Since 1986, Cs-137 has been the only man-made radionuclide found in vegetation samples. The MDC and RL for Cs-137 in vegetation samples are 80 pCi/kg-wet and 2000 pCi/kg-wet, respectively. The occasional presence of Cs-137 in vegetation samples is attributed primarily to fallout from nuclear weapons tests and the Chernobyl incident.
Figure 4.5-1 and Table 4.5-1 provide the historical trending of the average annual detectable Cs-137 concentration found in vegetation. Since 1978, the Cs-137 concentration has been on a decline, and since about 1989, generally occurring below the required MDC.
4-22

Figure 4.5-1 Average Annual Cs-137 Concentration in Vegetation 1200 1000 800 600
.2 S400 0
200 0
qo All 4%      191,0     4)                 0    4A qq -S, (P 41    t3A Year I--*-Indicator -U-Control -MDCI 4-23

Table 4.5-1 Average Annual Cs-137 Concentration in Vegetation Year                 Indicator            Control (pCi/kg-wet)         (pCi/kg-wet)
Pre-op                    55                  30 1974                   NDM                NDM 1975                   NDM                NDM 1976                   NDM                NDM 1977                   NDM                NDM 1978                    112                1089 1979                     59                 695 1980                    208                 916 1981                    182                 152 1982                     65                  99 1983                     95                 211 1984                    149                 388 1985                   60.9                113.3 1986                     80                 215 1987                     60                 428 1988                   40.1               228.8 1989                     37               NDM 1990                   66.7                34.5 1991                   34.1                36.1 1992                   35.2                41.3 1993                   24.7                45.8 1994                   32.2                46.6 1995                   49.8                47.6 1996                   47.2                41.1 1997                   48.4                54.9 1998                   81.4                44.1 1999                   26.9.              NDM 2000                   NDM                NDM 2001                   NDM                NDM 2002                   33.7                41.1 2003                   61.0                62.8 2004                   41.6                43.5 2005                   47.7                 39.8 2006                   66.8                29.6 2007                   55.7                 31.1 2008                   41.8                 38.1 4-24

4.6       River Water Surface water from the Altamaha River is obtained at an upstream location (Station 170) and at a downstream location (Station 172) using automatic samplers. Small quantities are drawn at intervals not exceeding a few hours. The samples drawn are collected monthly and quarterly composites are produced from the monthly collections.
As specified in Table 2-1, a gamma isotopic analysis is conducted on each monthly sample. No man-made gamma emitters were detected during 2008. The only man-made gamma emitters previously detected are presented in the table below.
Year            Quarter         Station       Radionuclide        Level I     _(pCi/I) 1975             4th             172            Ce-141            78.2 1986             2nd             170            La- 140           18.0 1986             2nd             172            Cs-137            12.0 1988             2nd             170            Cs-137             6.8 A tritium analysis is performed on the quarterly composite. Prior to 1986, positive results were usually found in each quarterly composite at levels generally ranging from 200 and 350 pCi/l which is approximately background environmental levels.
Subsequently, the number of positive results have diminished.
In 2008, tritium was detected in one of the four quarterly samples at the upstream (control) location and in two of the four quarterly samples at the downstream (indicator) location. The average of the two indicator samples was 329 pCi/l (the range was 284-373 pCi/1). The single positive value at the control station was 298 pCi/l. Application of the modified Student's t-test shows that the difference between the two stations is not statistically discernible. These low levels are essentially background environmental levels. The MDC and RL for tritium in river water are 3000 and 30,000 pCi/l, respectively. Figure 4.6-1 and Table 4.6-1 provide the historical trending of the annual average detectable tritium concentration in river water.
The annual 50 mile downstream survey of the Altamaha River to determine if river water is being withdrawn for drinking purposes is discussed in Section 4.1.
4-25

Figure 4.6-1 Average Annual H-3 Concentration in River Water 35000 3000
* 2500 a.
C 2000---------        ---     --         -      -      -   - -- --  - - --- ---
L010000 500 0
Year Indicator   -    -Control      MDC 4-26

Table 4.6-1 Average Annual H-3 Concentration in River Water Year                Indicator              Control (pCi/l)               (pCi/1)
Pre-op                   210                   191 1974                    230                   205 1975                    205                   238 1976                    165                   153 1977                    189                   170 1978                    224                   193 1979                    210                   180 1980                    358                   218 1981                    220                   135 1982                    165                   220 1983                    265                   328 1984                    437                   327 1985                    288                   220 1986                    242                   206 1987                    241                   204 1988                    220                  NDM 1989                   NDM                   NDM 1990                    139                  NDM 1991                   NDM                   NDM 1992                   NDM                   NDM 1993                   NDM                   NDM 1994                   NDM                   NDM 1995                    200                  NDM 1996                    144                   147 1997                   NDM                   NDM 1998                   NDM                   NDM 1999                   NDM                   NDM 2000                    209                  NDM 2001                   NDM                   NDM 2002                   NDM                   NDM 2003                   NDM                    261 2004                    206                   302 2005                    245                  NDM 2006                    299                  NDM 2007                    235                   338 2008                    329&#xfd;
* 298 4-27

4.7          Fish Gamma isotopic analyses were performed on the edible portion of the fish samples collected at the river stations on April 14, 2008 and January 6, 2009 (the fall collection was delayed due to low river water level). The control station (No. 170) is located upstream of the plant while the indicator station (No. 172) is located downstream.
As shown in Table 3-1, Cs-137 was the only man-made radionuclide detected in fish during 2008. The average concentration of 19.9 pCi/kg-wet at the indicator station was 11.5 pCi/kg-wet more than the average concentration found at the control station (8.4 pCi/kg-wet). This difference is statistically discernible since it is more than the calculated MDD of 5.4 pCi/kg-wet. Cs-137 in fish samples is attributed primarily to weapons testing and the Chernobyl incident. However, the Cs- 137 seen in the fish samples at the indicator station could be attributed to plant effluents. The MDC and RL for Cs-137 in fish are 150 and 2000 pCi/kg-wet, respectively.
The historical trending of the average annual detectable Cs-137 concentration in fish is provided in Figure 4.7-1 and Table 4.7-1. Figure 4.7-1 indicates, in general, a decline in the Cs-137 levels after 1983. (Note: From 1979 through 1982, clams were collected rather than fish.)
Figure 4.7-1 Average Annual Cs-137 Concentration in Fish 6W - -      I*                      -                           I I I---------------------
1 40                                                       --
00--                                                  -      -    -      -        -        -   - -  - -
S.2 80                           ---
0 U. 60-.-                                                    -      -   -         -    -       -   -  - - -
4            00-------------                               -
0-IQ&deg; 0 A     AA          ,    ,   b"     tb    tA    tbYa c&#xfd;  o-                    SA,     04q Year 1  -Indicator     -U-Control -            MDC I 4-28

Table 4.7-1 Average Annual Cs-137 Concentration in Fish Year                  Indicator             Control (pCi/kg-wet)         (pCi/kg-wet)
Pre-op                     90                 115 1974                     134                  61 1975                    80.6                89.4 1976                      73                  88 1977                      76                  91 1978                      88                  47 1979                    NDM                 NDM 1980                    NDM                 NDM 1981                    NDM                 NDM 1982                    NDM                 NDM 1983                    138.6               67.5 1984                      84                  53 1985                     117                63.3 1986                      79                  44 1987                      62                  52 1988                    77.8                 33.3 1989                    34.3                 28.9 1990                    26.7                 24.2 1991                    32.9                 26.9 1992                    41.6                 28.8 1993                    38.0                 25.9 1994                    23.8                 20.7 1995                    25.0                 27.9 1996                    20.4                 18.0 1997                    29.4                 15.1 1998                    26.1                 17.7 1999                    22.3                 13.5 2000                     17.9                25.3 2001                    20.8                 10.2 2002                     18.2                13.0 2003                     13.1                 7.1 2004                     11.6                18.8 2005                     13.0                13.3 2006                     10.4                13.5 2007                     6.8                  9.8 2008                     19.9                 8.4 4-29

In the past, the only other man-made radionuclides detected in fish samples were Co-60 and Cs-134. During preoperation, Co-60 was detected in one fish sample at a very low concentration. During the period of 1983 through 1988, Cs-134 was found in about half of the samples at concentrations of the same order of magnitude as those found for Cs-137. The Co-60 and Cs-134 levels found in these samples are attributed to the nuclear weapons tests and the Chernobyl incident. Figure 4.7-2 and Table 4.7-2 show the historical trending of the annual average detectable concentration of Cs- 134 in fish.
Figure 4.7-2 Average Annual Cs-134 Concentration in Fish 160-140-S120-100 S80-0.
40-Indicator   --  -Control    MDC 4-30

Table 4.7-2 Average Annual Cs-134 Concentration in Fish Year                 Indicator               Control (pCi/kg-wet)            (pCi/kg-wet)
Pre-op                  NDM                    NDM 1974                   NDM                    NDM 1975                   NDM                    NDM 1976                   NDM                    NDM 1977                   NDM                    NDM 1978                   NDM                    NDM 1979                   NDM                    NDM 1980                   NDM                    NDM 1981                   NDM                    NDM 1982                   NDM                    NDM 1983                   101.8                  NDM 1984                    35.8                   26.3 1985                   46.7                    21.1 1986                     29                   NDM 1987                     69                     15 1988                    21.7                    6.9 1989                   NDM                    NDM 1990                   NDM                    NDM 1991                   NDM                    NDM 1992                   NDM                    NDM 1993                   NDM                    NDM 1994                   NDM                    NDM 1995                   NDM                    NDM 1996                   NDM                    NDM 1997                   NDM                    NDM 1998                   NDM                    NDM 1999                   NDM                    NDM 2000                   NDM                    NDM 2001                   NDM                    NDM 2002                   NDM                    NDM 2003                   NDM                    NDM 2004                   NDM                    NDM 2005                   NDM                    NDM 2006                   NDM                    NDM 2007                   NDM                    NDM 2008                   NDM                    NDM 4-31

4.8    Sediment Sediment was collected along the shoreline of the Altamaha River on May 5 and November 3, 2008, at the upstream control station (No. 170) and the downstream indicator station (No. 172). A gamma isotopic analysis was performed on each sample.
Co-60 was not found in sediment samples in 2008. With the exception of a few years, Co-60 has been found at either the indicator or the control station every year since 1986. There is no RL or MDC assigned to Co-60 in sediment in ODCM Tables 4-2 and 4-3 (Tables 4-2 and 4-1 of this report). The MDC assigned by the EL for Co-60 in sediment is 70 pCi/kg-dry. The historical trending of the average annual detectable Co-60 concentration in sediment is provided in Figure 4.8-1 and Table 4.8-1.
Figure 4.8-1 Average Annual Co-60 Concentration in Sediment 250 200 150 Year 9I-i-ndicator -U- -Control   -MDCI 4-32

Table 4.8-1 Average Annual Co-60 Concentration in Sediment Year                   Indicator               Control (pCi/kg-dry)            (pCi/kg-dry)
Pre-op                   NDM                    NDM 1974                    NDM                    NDM 1975                    NDM                    NDM 1976                    NDM                    NDM 1977                    NDM                    NDM 1978                    NDM                    NDM 1979                    NDM                    NDM 1980                    NDM                    NDM 1981                    NDM                    NDM 1982                    NDM                    NDM 1983                    NDM                    NDM 1984                    NDM                    NDM 1985                    NDM                    NDM 1986                      108                    33 1987                    NDM                    NDM 1988                     67.8                  NDM 1989                    NDM                      31 1990                      33                     19 1991                    123.6                  NDM 1992                     81.4                  NDM 1993                     70.7                  NDM 1994                     218                   NDM 1995                    NDM                    NDM 1996                    118.5                  NDM 1997                    NDM                    NDM 1998                     79.4                  NDM 1999                    107.7                  NDM 2000                     70.0                  NDM 2001                     58.1                  NDM 2002                    NDM                    NDM 2003                    NDM                     31.5 2004                    NDM                    NDM 2005                    NDM                    NDM 2006                    NDM                    NDM 2007                    NDM                    NDM 2008                    NDM                    NDM 4-33

Co-60 was not detected in sediment samples near the plant until 1986, the year of the Chernobyl incident. However, because Co-60 was detected in indicator station samples more often than in control station samples during the years 1986 through 2002, some contribution from plant effluents cannot be ruled out. Co-60 has not been detected in either control or indicator station samples since 2004.
In 2008, Cs-137 was detected in both indicator and control station sediment samples. It has been found in over 95% of all of the sediment samples collected back through preoperation, and is generally attributed to the atmospheric nuclear weapons tests or to the Chernobyl incident. As shown in Table 3-1, the average at the indicator station was 112.7 pCi/kg-dry and at the control station the single positive value was 61.9 pCi/kg-dry. Application of the modified Student's t-test shows that the difference (50.8 pCi/kg-dry) between the stations is not statistically discernible. The MDC for Cs-137 in sediment is 180 pCi/kg-dry. The historical trending of the average annual detectable Cs-137 concentration in sediment is provided in Figure 4.8-2 and Table 4.8-2.
Figure 4.8-2 Average Annual Cs-137 Concentration in Sediment 1000-800 ---
'? 7   00- -               -            -                               -
 .X 400-0 r-   500 -;,                                .. ,
0 Y200e j
100                                         --
Year 1  -6Indicator     --U-  Control -  MDC I 4-34

Table 4.8-2 Average Annual Cs-137 Concentration in Sediment Year                 Indicator               Control (pCi/kg-dry)            (pCi/kg-dry)
Pre-op                    170                   270 1974                     218                     57 1975                     330                   615 1976                     211                   300 1977                     364                   200 1978                     330                   260 1979                   NDM                      310 1980                     240                  NDM 1981                     590                    110 1982                     141                   285 1983                     384                    365 1984                     500                    260 1985                    76.5                    269 1986                     238                    190 1987                      59                     39 1988                     903                    114 1989                      56                     62 1990                   130.5                     66 1991                    43.1                   54.5 1992                     151                  198.5 1993                     113                    115 1994                     127                    104 1995                    52.3                   80.6 1996                     106                    110 1997                     186                    137 1998                   148.5                   101.4 1999                      92                   111.8 2000                    68.1                   114.5 2001                    68.7                   69.6 2002                    68.1                   62.8 2003                    57.3                    106 2004                    59.5                   57.1 2005                    57.2                   30.3 2006                    85.2                   79.2 2007                    82.1                   71.6 2008                   112.7                   61.9 4-35

Other man-made nuclides, besides Co-60 and Cs-137, were occasionally found in past years. Their presence was generally attributed to the nuclear weapons tests or to the Chernobyl incident, although plant releases were not ruled out. Mn-54, Co-58, and Zn-65, which have relatively short half-lives, are most likely a result of plant releases and have been plotted in Figure 4.8-3 along with their MDCs. All the man-made nuclides detected in sediment except for Co-60 and Cs-137 have been listed in Table 4.8-3. The Cs-134 MDC (150 pCi/kg-dry) is defined in ODCM Table 4-3 (Table 4-1 of this report). The MDCs for Mn-54 (42 pCi/kg-dry) and Zn-65 (129 pCi/kg-dry) were determined by the EL since no values are provided in ODCM Table 4-3.
Figure 4.8-3 Average Annual Indicator Station Concentrations of Select Nuclides in Sediment 600
,   500 "0) 400 0.
. 300 0
200
                             /4                 d~ /R /            I 100                              II        ol      I= 111 0
0 q
Year
                        -*- Mn-54        -- U-- Zn-65     -- A-Cs-134
                       -Mn-MDC           -Zn-MDC          -Cs-MDC 4-36

Table 4.8-3 Sediment Nuclide Concentrations Other Than Co-60 & Cs-137 Nuclide      YEAR            Indicator           Control (pCi/kg-dry)        (pCi/kg-dry)
Ce-141        1976               340               254 1977               141 Ce- 144      Preop                                 720 1974               363 1975               342               389 1978               700 1981               1290 Co-58        1994               22.2 Cs-134       Preop                                  40 1981               280 1984               130                40 1986               132 1988               505 1990                31 Mn-54         1975               36.1 1986                28                26 1991               57.2 1996               77.7 Ru-103        1974                81 1976               158 1977                195 1981               220 Zn-65        1986                175 1988                136 1991              250.5 1992                83 1993               39.9 1994               332 Zr-95       Preop                                  180 1974                138 1976               427                170 1977               349               294 1978               220               230 1981               860               280 4-37

4.9 Groundwater As nuclear plants began to undergo decommissioning in the late 1990's to early 2000s, instances of subsurface and/or groundwater contamination were identified.
In addition, several operating facilities also identified groundwater contamination resulting from spills and leaks or equipment failure. In one instance, low levels of licensed material were detected in a private well located on property adjacent to a nuclear power plant.
In 2006, NEI (Nuclear Energy Institute) formed a task force to address monitoring onsite groundwater for radionuclides at nuclear facilities.          A Groundwater Protection Initiative was developed which was adopted by all U.S. commercial operating nuclear plants.
The NRC also formed a task .force to study the groundwater issues and released Information Notice 2006-13 "Ground-water Contamination due to Undetected Leakage of Radioactive Water" which summarized its review of radioactive contamination of ground water at multiple facilities as a result of undetected leakage from structures, systems, or components that contain or transport radioactive fluids. Licensees were instructed to review the information for applicability and to consider appropriate actions to avoid similar problems.
The NEI task force felt it was prudent for the industry to update site hydrology information and to develop radiological groundwater monitoring plans at each site.
These groundwater protection plans would ensure that underground leaks and spills would be addressed promptly. Additionally, the task force recommended developing a communications protocol to report radioactive leaks or spills that entered groundwater (or might eventually enter groundwater) to the NRC and State and Local government officials as needed.
Southern Nuclear developed a company-wide communications protocol which is contained in the Nuclear Management Procedure, Actions for Potential Groundwater Contamination Events, to ensure radioactive leaks and spills would be addressed and communicated appropriately. The guidance in this procedure is used to informally update both the NRC and the State of Georgia regarding the changes in Hatch's groundwater tritium concentrations.
Plant Hatch has monitored onsite groundwater since preoperation. Initially piezometers, which were installed prior to plant construction, were used to monitor groundwater. In the late 1970s to the early 1980s timeframe, a hydrological engineering consultant was hired to evaluate several areas where leaks had occurred and tritium had been detected in onsite wells.              The consultant recommended drilling additional monitoring wells to study the groundwater movement, to determine the source of the leaks, and to track the tritium concentrations in groundwater.
In the late 1970s through the mid 1980s, Hatch reported groundwater results to the NRC. The reporting frequency was decreased for several reasons - the areas where the groundwater showed tritium were all onsite and the movement of groundwater was extremely slow and in a direction (towards the river) that was not expected to impact the public. Although the reports are no longer made on a routine basis, Plant Hatch has continued to monitor onsite groundwater wells for tritium on a scheduled frequency.
4-38

In 2006 as the nuclear industry was moving towards establishing groundwater monitoring programs, Plant Hatch hired a hydrological engineering consultant to re-evaluate the groundwater study which had been done previously. The key purpose of the new study was to evaluate the adequacy of the current monitoring program and to diagram the existing groundwater tritium plume to ensure that the plume had not migrated offsite. The consultant concluded that tritium was not leaving the site through the groundwater. The consultant recommended installing additional monitoring wells to better characterize the groundwater plume in areas of the site where there were no existing wells.
During the course of Plant Hatch's groundwater evaluation in 2006, some leaks were discovered which explained why the levels of tritium around CST-1 (Unit 1 Condensate Storage Tank) were not decreasing. Underground piping which carried radioactive liquids was evaluated over the plant site and replaced in some areas around CST-1. Both CST tank/pump moats (Unit 1 and Unit 2) were coated and sealed to ensure that moats would not leak in the event of transfer pump or tank leaks.
In 2006, Plant Hatch's groundwater monitoring program included over 50 location points which were sampled on weekly, monthly, quarterly, or annual frequencies (see maps at the end of this section). Included in these sample points were the onsite drinking water wells.        They did not contain detectable amounts of radioactivity. Surface drains or outfalls were also included as sample points.
Tritium was detected in two of the outfalls which discharged to the river. These outfalls were added to the Hatch ODCM as radiological effluent release points.
Permitted release point Y22N008A (by design) discharges groundwater from the site subsurface drainage system which includes the tritiated groundwater around the CST-1. The other permitted release point, Y22N003A, discharges runoff from the roof drains. The source of tritium in this outfall is believed to be from rain washout of the gaseous plant effluents. Plant Hatch sampled rainfall during two rain events in 2006 and found tritium levels as high as 4.58E5 pCi/l on the reactor building roof. Two other outfalls, Y22N024A and Y22N025A, which discharge into the onsite'swamp show sporadic levels of tritium. The source of tritium in these outfalls is also believed to be from rain washout.
In 2007, Hatch continued to aggressively monitor the groundwater tritium plume especially in two areas of higher activity around CST- 1 and CST-2. The amount of seasonal rainfall during 2007 seems to have had some correlation with the tritium concentrations in the T-12 well near CST-1. During early spring and late fall rainy seasons, the concentrations of tritium were at their highest levels, whereas, during the summer and early fall drought season the tritium concentrations decreased significantly. This is indicative of water table level fluctuations.
However, this same seasonal affect was not observed in the newer NW1O monitoring well installed in 2006 near CST-2. The tritium concentration in NW10 increased from February 2007 through September 2007 by a factor of 2.5. Events which could have contributed to the increase were a CST-2 transfer pump leak (in November 2006) which led to an accumulation of a couple feet of CST-2 water in the pump moat. Although the moat had been sealed earlier in 2006, there was a possibility that some of the contaminated water seeped through the concrete moat and gradually seeped through the ground to NW1O. In addition, there was a deep hole dug (in January 2007) near the CST-2 (and NW10) to replace some CST-2 piping. The hole may have altered groundwater flow toward NW1O from the CST-1 groundwater plume and resulted in higher concentrations of tritium being drawn to NW1O.
4-39

In 2008, Hatch made further enhancements to the groundwater tritium monitoring program. Three additional shallow wells and three additional deep wells were installed ("R" series wells). One of the deep wells was a replacement well for the deep well N7A. The integrity of N7A was questioned due to the high level of tritium (-211,000 pCi/1) seen in this well which should have been protected from contamination by a confining layer. The well was retired and a new well (R-3) was placed in the same vicinity. The newer well showed much smaller amounts of tritium activity (average of 2180 pCi/1 for the last three quarters of 2008).
In addition, two other groups within Southern Company are now utilized to conduct an improved sampling program and to provide additional expertise in characterizing groundwater quality and flow.            The sampling frequency for radiological groundwater monitoring was officially changed to quarterly starting in second quarter of 2008 with SCS Civil Field Services performing the sampling and Georgia Power Environmental Laboratory continuing to analyze the samples. The latest groundwater tritium plume map (generated from the 2008 SCS sampling data) is shown on the following page. It is a representation of the current groundwater conditions at Plant Hatch. The wells of interest around the CSTs had the following average tritium concentrations from the 3 quarters of sampling: T-12, near CST-1, averaged approximately 650,000 pCi/l of tritium and NW10, near CST-2, averaged 116,000 pCi/1 of tritium. No tritium activity was seen in the Deep Wells 2 and 3 which are used for drinking water at the plant. The plant staff continues to sample and monitor strategically located wells on a more frequent basis than quarterly to ensure that radiological leaks have not occurred. In addition, outfalls, pull boxes, manholes, and the sewage treatment plant effluent are sampled by the plant staff on a periodic basis.
4-40

CONCENT"RATION DATA PCi/L 1.+
                                                        ]DO     06 5.00E + 05 - 1.00E + 06 1.00E + 05 - 5.0013+ 05 5.OOE+ 04 - 1 00E + 05 2.00E + 04 - 5.00E + 04 1.00E + 04 - 2.00E + 04 1 00E + 03 - 1.00E + 04 3.00E + 02 - 1.00E + 03 LEGEND-NW9 0         Unconfined Perched Aquifer Tritium Source Detection Monitoring Welt N8          Tritium Attenuation Monitoring Weills (not part of groundwater source detection program)
                                                   --
* Approximately Located French Drain & Flow Direction
                                              < MIDA       Less Than Minimum Detectable Activity
           *,* *-*-*-e* *-  - - *--Southern                       Company Genration
         ,2*,*,*,.:,*    .*     *Engineering                     and Construction Services PLANT     RATC                                  Southern Nuclear FIGURE 4.9-1                                                                11IIAI0 ANSI    B, 17xll    Acod2GOO 4-41

5.0 INTERLABORATORY COMPARISON PROGRAM In accordance with ODCM 4.1.3, the EL participates in an ICP that satisfies the requirements of Regulatory Guide 4.15, Revision 1, "Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment", February 1979. The guide indicates the ICP is to be conducted with the Environmental Protection Agency (EPA) Environmental Radioactivity Laboratory Intercomparison Studies (Cross-check) Program or an equivalent program, and the ICP should include all of the determinations (sample medium/radionuclide combinations) that are offered by the EPA and included in the REMP.
The ICP is conducted by Analytics, Inc. of Atlanta, Georgia. Analytics has a documented Quality Assurance (QA) program and the capability to prepare Quality Control (QC) materials traceable to the National Institute of Standards and Technology. The ICP is a third party blind testing program which provides a means to ensure independent checks are performed on the accuracy and precision of the measurements of radioactive materials in environmental sample matrices.
Analytics supplies the crosscheck samples to the EL which performs the laboratory analyses in a normal manner. Each of the specified analyses is performed three times. The results are then sent to Analytics who performs an evaluation which may be helpful to the EL in the identification of instrument or procedural problems.
The samples offered by Analytics and included in the EL analyses are gross beta and gamma isotopic analyses of an air filter; gamma isotopic analyses of milk samples; and gross beta, tritium and gamma isotopic analyses of water samples.
The accuracy of each result is measured by the normalized deviation, which is the ratio of the reported average less the known value to the total error. The total error is the square root of the sum of the squares of the uncertainties of the known value and of the reported average. The uncertainty of the known value includes all analytical uncertainties as reported by Analytics. The uncertainty of the reported average is the propagated error of the values in the reported average by the EL.
The precision of each result is measured by the coefficient of variation, which is defined as the standard deviation of the reported result divided by the reported average. An investigation is undertaken whenever the absolute value of the normalized deviation is greater than three or whenever the coefficient of variation is greater than 15% for all radionuclides other than Cr-51 and Fe-59. For Cr-51 and Fe-59, an investigation is undertaken when the coefficient of variation exceeds the values shown as follows:
Nuclide      Concentration
* Total Sample Activity     Percent Coefficient (pCi)                     of Variation Cr-51        <300                 NA                        25 Cr-51        NA                   >1000                     25 Cr-51        >300                 <1000                     15 Fe-59        <80                  NA                        25 Fe-59        >80                  NA                        15
* For air filters, concentration units are pCi/filter.      For all other media, concentration units are pCi/liter (pCi/1).
5-1

As required by ODCM 4.1.3.3 and 7.1.2.3, a summary of the results of the EL's participation in the ICP is provided in Table 5-1 for: the gross beta and gamma isotopic analyses of an air filter; gamma isotopic analyses of milk samples; and gross beta, tritium and gamma isotopic analyses of water samples. Delineated in this table for each of the media/analysis combinations, are: the specific radionuclides; Analytics' preparation dates; the known values with their uncertainties supplied by Analytics; the reported averages with their standard deviations; and the resultant normalized deviations and coefficients of variation expressed as a percentage.
The GPC EL analyzed 13 samples for 43 parameters in 2008. The analyses included tritium, gross beta, Fe-55, Sr-89/90 and gamma emitting radio-nuclides in milk, water, air cartridge and air filter matrices. The attached results indicate three analyses outside the three sigma control limits. They were the following:
: 1) Mn-54 in air filter (Environmental Program) for accuracy.
: 2) Co-58 in water (Environmental Program) for precision
: 3) Gross alpha in water (Effluent Program) for accuracy.
The first quarter effluent water sample analyzed for gross alpha had a low activity recovery. The gross alpha in water self absorption curve was evaluated and updated. The second quarter alpha sample was in control for both accuracy and precision. A known alpha activity sample will be processed with the blind samples in the future to assure accurate results.
The third quarter environmental air filter sample was analyzed by gamma spectroscopy and had a high activity recovery for Mn-54. The sample was analyzed by three detectors and a weighted average reported. A small range from the three detectors produced an elevated normalized deviation result. The value was above the three sigma control limit, however the recovery of the Mn-54 activity is 114% and is acceptable.
The precision failure was in the first quarter water sample analyzed by gamma spectroscopy. The %CV for Co-58 was above the control limit. The sample was analyzed on three detectors with an error weighted average reported. An elevated range of values in the analysis is due to one of the detectors measuring a higher activity. No inconsistencies were found in the detector shaping or analysis of the 810 kev gamma peak. No further investigation will be performed.
In 2009 the Environmental Laboratory will adopt the NRC Inspection Procedure's guidance for acceptance criteria in performance sample testing. The adoption of the NRC Inspection Procedure 84750 will keep the lab consistent with the nuclear industry.
5-2

TABLE 5-1 (SHEET I of 3)
INTERLABORATORY COMPARISON PROGRAM RESULTS GROSS BETA ANALYSIS OF AN AIR FILTER (pCi/filter)
Analysis or    Date         Reported        Known          Standard       Uncertainty      Percent Coef Normalized Radionuclide I Prepared     Average       I Value        I Deviation EL I Analytics (3S)   of Variation     Deviation Gross Beta   ] 09/18/08   1       128.00          121.001           4.82 1           2.03            5.43 1           1.01 GAMMA ISOTOPIC ANALYSIS OF AN AIR FILTER (pCi/filter)
Analysis or    Date         Reported        Known          Standard        Uncertainty     Percent Coef     Normalized Radionuclide   Prepared     Average         Value          Deviation EL    Analytics (3S)  of Variation     Deviation Ce-141         09/18/08           134.00          132.00            6.74             0.74            5.81             0.25 Co-58          09/18/08           149.70          146.00             6.7             0.81            3.84             0.61 Co-60          09/18/08           197.10          192.00            7.81              1.07           3.22             0.74 Cr-51          09/18/08           390.10          345.00           14.59              1.92           6.74             1.69 Cs-134         09/18/08           186.90          190.00            6.88              1.06           4.54            -0.35 Cs-137         09/18/08           143.20          133.00            5.23             0.74            4.92             1.40 Fe-59          09/18/08           140.60          118.00            2.99             0.66            4.58             3.40 Mn-54          09/18/08           154.60          136.00            1.14             0.76            3.42             3.30 Zn-65          09/18/08           295.40          262.00           13.08              1.46           5.70             1.93 GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (pCi/liter)
Analysis or    Date         Reported        Known          Standard        Uncertainty     Percent Coef     Normalized Radionuclide   Prepared     Average         Value        I Deviation EL    Analytics (3S)  of Variation     Deviation Ce- 141        06/19/08           180.10          174.00           13.17             0.97            8.56             0.39 Co-58          06/19/08             68.90          61.90            4.77             0.34            0.65             0.96 Co-60          06/19/08           112.60          104.00            5.69             0.58            6.87             1.10 Cr-51          06/19/08           146.70          138.00           23.39             0.77          25.12              0.24 Cs-134         06/19/08             74.70          76.70            2.67             0.43            7.18            -0.36 Cs-137         06/19/08           118.20          116.00            5.44             0.65            7.27             0.25

TABLE 5-1 (SHEET 2 of 3)
INTERLABORATORY COMPARISON PROGRAM RESULTS GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (pCi/liter)
Analysis or    Date                       Known mReportedStandard       Uncertainty     Percent Coef Normalized Radionuclide I Prepared    Average        Value         I Deviation EL Analytics (3S) of Variation     Deviation Fe-59          06/19/08           109.40          91.70           13.67           0.51           14.96           1.08 1-131          06/19/08            88.90          71.40             9.9           0.40           12.83           1.53 Mn-54          06/19/08           152.00         135.00            4.56           0.75            5.68           1.92 Zn-65          06/19/08           135.40.        127.00            8.19           0.71           10.23           0.60 GROSS BETA ANALYSIS OF WATER SAMPLE (pCi/liter)
GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (pCi/liter)
Analysis or    Date        Reported       Known             -Standard   Uncertainty     Percent Coef   Normalized Radionuclide [Prepared     Average        Value           Deviation EL  Analytics (3S)  of Variation   Deviation Ce-141         03/20/08          204.60          198.00            8.08           2.21            5.87           0.55 Co-58          03/20/08            58.50          56.40            9.22           0.63           15.77           0.23 Co-60          03/20/08           188.90         189.00            9.74           2.09            6.57           0.06 Cr-51          03/20/08          356.30          286.00           21.56           2.85           12.23           1.61 Cs- 134        03/20/08            99.90          99.70            2.29            1.11           5.91           0.03

TABLE 5-1 (SHEET 3 of 3)
INTERLABORATORY COMPARISON PROGRAM RESULTS GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (pCi/liter)
Analysis or    Date        Reported      Known        Standard      Uncertainty     Percent Coef   Normalized Radionuclide I Prepared    Average       Value        Deviation EL  Analytics (3S)  of Variation   Deviation Cs-137         03/20/08           121.50       116.00          9.85            1.29          10.22           0.45 Fe-59          03/20/08            92.60        81.40          7.75           0.91           12.21           0.99 1-131          03/20/08            68.90        70.40          0.98           0.79            8.64          -0.25 Mn-54          03/20/08            83.20        75.00          4.32           0.83            8.84           1.11 Zn-65          03/20/08           119.90       109.00          6.41            1.21          11.03           0.83 TRITIUM ANALYSIS OF WATER SAMPLES (pCi/liter) 1-131 ANALYSIS OF AN AIR CARTRIDGE (pCi/cartridge)
Analysis or    Date        Reported      Known        Standard      Uncertainty     Percent Coef Normalized Radionuclide   Prepared    Average       Value        Deviation EL Analytics (3S)   of Variation   Deviation 1-131          12/11/08            51.30        54.80          0.22           0.31            3.83          -1.75

==6.0 CONCLUSION==
S This report confirms the licensee's conformance with the requirements of Chapter 4 of the ODCM. It provides a summary and discussion of the results of the laboratory analyses for each type of sample.
In 2008, there was one instance where the indicator station results were statistically discernible from the control station results. This is discussed below.
No discernible radiological impact upon the environment or the public as a consequence of plant discharges to the atmosphere and to the river was established for any other REMP samples.
Cesium-137 was identified in both of the fish collections (spring and winter) at the indicator station and at the control station. The average of the samples at the indicator station was 19.9 pCi/kg-wet and the average at the control station was 8.4 pCi/kg-wet. The potential dose to a member of the public who would receive the highest dose (an adult) due to regular consumption of fish containing Cs-137 would be 1.72E-2 mrem in a year. This dose is approximately 0.6% of the regulatory limit of 3 mrem per year due to liquid effluents. Low levels of Cs-137 in the environment are attributed primarily to fallout from nuclear weapons testing and from the Chernobyl incident. However, the level of Cs-137 seen at the indicator station could potentially be attributed to plant effluents.
The radiological levels reported in 2008 were low and are generally trending downward. The REMP trends over the course of time from preoperation to the present are decreasing or have remained fairly constant. This supports the conclusion that there is no adverse radiological impact on the environment or to the public as a result of the operation of Hatch Nuclear Plant.
6-1

Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radiological Environmental Operating Reports for 2008 Enclosure 2 Farley Annual Radiological Environmental Operating Report for 2008

JOSEPH M. FARLEY NUCLEAR PLANT ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2008 oaftiofo SOUTHERN Nk COMPANY Energy to Serve Your World" A

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

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

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

LIST OF ACRONYMS Acronyms presented in alphabetical order Acronym    Definition APCo       Alabama Power Company ASTM       American Society for Testing and Materials CL         Confidence Level EL         Georgia Power Company Environmental Laboratory EPA        Environmental Protection Agency FNP        Joseph M. Farley Nuclear Plant ICP        Interlaboratory Comparison Program MDC        Minimum Detectable Concentration MDD        Minimum Detectable Difference MWe        MegaWatts Electric NA         Not Applicable NDM        No Detectable Measurement(s)
NRC        Nuclear Regulatory Commission ODCM       Offsite Dose Calculation Manual Po         Preoperation PWR        Pressurized Water Reactor REMP       Radiological Environmental Monitoring Program RL         Reporting Level RM         River Mile TLD        Thermoluminescent Dosimeter TS         Technical Specification iv

==1.0 INTRODUCTION==

The Radiological Environmental Monitoring Program (REMP) for 2008 was conducted in accordance with Chapter 4 of the Offsite Dose Calculation Manual (ODCM). The REMP activities for 2008 are reported herein in accordance with Technical Specification (TS) 5.6.2 and ODCM 7.1.
The objectives of the REMP are to:
: 1) Determine the levels of radiation and the concentrations of radioactivity in the environs and;
: 2) Assess the radiological impact (if any) to the environment due to the operation of the Joseph M. Farley Nuclear Plant (FNP).
The assessments include comparisons between results of analyses of samples obtained at locations where radiological levels are not expected to be affected by plant operation (control stations) and at locations where radiological levels are more likely to be affected by plant operation (indicator stations), as well as comparisons between preoperational and operational sample results.
FNP is owned by Alabama Power Company (APCo) and operated by Southern Nuclear Operating Company. It is located in Houston County, Alabama approximately fifteen miles east of Dothan, Alabama on the west bank of the Chattahoochee River. Unit 1, a Westinghouse Electric Corporation Pressurized Water Reactor (PWR) with a licensed core thermal power output of 2775 MegaWatts thermal (MWt), achieved initial criticality on August 9, 1977 and was declared "commercial" on December 1, 1977. Unit 2, also a 2775 MWt Westinghouse PWR, achieved initial criticality on May 8, 1981 and was declared "commercial" on July 30, 1981.
The preoperational stage of the REMP began with initial sample collections in January of 1975. The transition from the preoperational to the operational stage of the REMP was marked by Unit 1 initial criticality.
A description of the REMP is provided in Section 2 of this report. An annual summary of the results of the analyses of REMP samples is provided in Section 3.
A discussion of the results, including assessments of any radiological impacts upon the environment and the results of the land use census are provided in Section 4. The results of the Interlaboratory Comparison Program (ICP) are provided in Section 5. Conclusions are provided in Section 6.
1-1

2.0 REMP DESCRIPTION A summary description of the REMP is provided in Table 2-1. This table summarizes the program as it meets the requirements outlined in ODCM Table 4-1. It details the sample types to be collected and the analyses to be performed in order to monitor the airborne, direct radiation, waterborne and ingestion pathways, and also delineates the collection and analysis frequencies. In addition, Table 2-1 describes the locations of the indicator, community and control stations as described in ODCM Table 4-4 and the identification of each sample according to station location and analysis type. The stations 'are also depicted on maps in Figures 2-1 through 2-3.
The location of each REMP station for gaseous releases is described by its direction and distance from a point midway between the Unit 1 and Unit 2 plant vent stacks. The surrounding area is divided into 16 azimuthal sectors which are centered on the major compass points; each sector is numbered sequentially clockwise and oriented so that the centerline of sector 16 is due north. Each sampling station is identified by a four digit number. The first two digits indicate the sector number, and the last two digits indicate the distance from the origin to the nearest mile.       For example, air monitoring station 0215 is located approximately 15 miles northeast of the origin. The locations for the sampling stations along the river are identified by the nearest River Mile (RM) which is the distance along the navigable portion of the Chattahoochee River upstream of the Jim Woodruff Dam near Chattahoochee, Florida. The approximate locations of the plant discharge and intake structures are at RM 43.5 and 43.8, respectively.
The samples are collected by the plant's technical staff, except for fish and river sediment samples which are collected by APCo Environmental Field Services personnel.
All laboratory analyses were performed by Georgia                Power    Company's Environmental Laboratory (EL) in Smyrna, Georgia.
2-1

TABLE 2-1 (SHEET 1 of 7)

==SUMMARY==
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway                 Sample Identification                                  Sampling and Collection Frequency          Type and Frequency of Analysis with Sample Types and Locations (sector-miles)
AIRBORNE Particulates                                                                            Continuous sampler operation with sample   Particulate sampler: Analyze for gross collection weekly.                         beta radioactivity > 24 hours following filter change. Perform gamma isotopic analysis on each sample when gross beta activity is > 10 times the yearly mean of control samples. Perform gamma isotopic analysis on composite sample (by location) quarterl.. .........
Indicator Stations:
River Intake Structure           PI-0501 (ESE-0.8)
South Perimeter                  PI-0701 (SSE-1.0)
Plant Entrance                   PI-1101 (WSW-0.9)
North Perimeter                  PI-1601 (N-0.8)
Control Stations:
Blakely GA (NE-15)               PB-0215 Neals Landing, FL                PB-0718 (spare (SSE- 18)                        station, not in service)
D....o..
th.an,. AL.
            . (W - 1..          PB..-.1 21...........................................
8)................. 1.8..........................-
Community Stations:
GA Pacific Paper Co.             PC-0703 (SSE-3)
Ashford, AL                     PC-1108 (WSW-8)
Columbia, AL (N-5)              PC- 1605 i                                                       i                                          I

TABLE 2-1 (SHEET 2 of 7)

==SUMMARY==
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway                                                  Sample Identification                                                 Sampling and Collection Frequency                                                                          Type and Frequency. of Analysis with Sample Types and Locations (sector-miles)
Iodine                                                                                                                                  Continuous sampler operation with sample Radioiodine canister: Analyze each
.-I jc.l.n                                                             ....................
                                                                                                                                                      .......  ... w......................................................................e...................................
week....       ...........  ........................................................................................................... ...........................................
Indicator Stations:
River Intake Structure                                            11-0501 (ESE-0.8)
South Perimeter                                                   11-0701 (SSE-1.0)
Plant Entrance                                                    11-1101 (WSW-0.9)
North Perimeter                                                   11-1601 Control Station:
Blakely, GA (NE-15)                                               IB-0215 Neals Landing, FL                                                 IB-0718 (spare station, (SSE-18)                                                          not in service)
Dothan, AL (W-18)                                                 IB-1218 Community Station:
GA Pacific Paper Co.                                              IC-0703 (SSE-3)
DIRECT RADIATION TLD                                                                                                                                     Quarterly                                                                                                  Gamma dose: Read each badge Indicator Stations:
Plant Perimeter (NNE-0.9)                                                         RI-0101 (NE-1.0)                                                          RI-0201 (ENE-0.9)                                                         RI-0301 (E-0.8)                                                           RI-0401 (ESE-0.8)                                                         RI-0501

TABLE 2-1 (SHEET 3 of 7)

==SUMMARY==
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway      Sample         Sampling and Collection Frequency   Type and Frequency of Analysis with Sample Types     Identification and Locations (sector-miles)
(SE-1.1)              RI-0601 (SSE-1.0)             RI-0701 (S-1.0)               RI-0801 (SSW-1.0)             RI-0901 (SW-0.9)              RI-1001 (WSW-0.9)             RI-1101 (W-0.8)               RI-1201 (WNW-0.8)             RI-1301 (NW-1.1)              RI-1401 (NNW-0.9)             RI-1501 (N-0.8)               RI-1601 Control Stations:
Blakely, GA (NE-15)   RB-0215 Neals Landing, FL     RB-0718 (SSE-18)
Dothan, AL (W-15)     RB-1215 Dothan, AL (W-18)     RB-1218 Webb, AL              RB-1311 (WNW- 11)
Haleburg, AL (N-12)   RB-1612 Community Station By sector (NNE-4)               RC-0104 (NE-4)                RC-0204 (ENE-4)               RC-0304 (E-5)                 RC-0405 (ESE-5)               RC-0505 (SE-5)                RC-0605 (SSE-3)             I RC-0703                                          I

TABLE 2-1 (SHEET 4 of 7)

==SUMMARY==
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway                        Sample         Sampling and Collection Frequency         Type and Frequency of Analysis with Sample Types                       Identification and Locations (sector-miles)
(S-5)                                   RC-0805 (SSW-4)                                 RC-0904 (SW-5)                                  RC-1005 (WSW-4)                                 RC- 1104 (W-4)                                   RC-1204 (WNW-4)                                 RC-1304 (NW-4)                                  RC-1404 (NNW-4)                                 RC-1504 (N-5)                                   RC-1605 Of Special Interest:
Nearest Residence                       RC-1001 (SW-1.2)
City of Ashford, AL                     RC- 1108 (WSW-8.0)
WATERBORNE                                             Aliquots taken with proportional semi-Surface Water                                          continuous sampler, having a minimum      Gamma isotopic analysis of each 4 week sampling frequency not exceeding two      composite sample. Tritium analysis for hours, collected weekly for 4 week        each quarterly composite.
er.....o I..........................................
                                                                                               .t Indicator Station:
Paper Mill, (-3 miles                   WRI downstream of plant discharge, RM 40)
Control Station:
Upstream of                             WRB Andrews Lock and dam (-3 miles upstream of the plant intake, RM 47)

TABLE 2-1 (SHEET 5 of 7)

==SUMMARY==
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway                Sample                                   Sampling and Collection Frequency                                                                                               Type and Frequency of Analysis with Sample Types               Identification and Locations (sector-miles)
Offsite Ground Water                                                     Grab sample quarterly                                                                                                           Gamma isotopic, 1-131, and tritium
                                              .........                                                                                                                                                                 s f ac...
       ..............................................................................................................                                                                                                                            am    . .....
aer Indicator Station:
Paper Mill Well                 WGI-07 (SSE-4)
Control Station:
Whatley Residence               WGB-10 Well (SW-1.2)
Onsite Ground Water             See Table 2-2                            Quarterly sample; pump used to sample GW                                                                                        Tritium, gamma isotopic, and field wells; grab sample from yard drains and                                                                                         parameters (pH, temperature, ponds                                                                                                                           conductivity, dissolved oxygen, oxidation/reduction potential, and turbidity) of each sample quarterly; Hard to detect radionuclides as necessary based on results of tritium and gamma River Sediment                                                           Grab sample semiannually                                                                                                        Gamma isotopic analysis of each sample semiannually Indicator Station:..
Downstream of plant             RSI discharge at Smith's Bend (RM 41)a Control Station:
Upstream of plant               RSB discharge at Andrews Lock & Dam Reservoir (RM 48)a

TABLE 2-1 (SHEET 6 of 7)

==SUMMARY==
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway                          Sample                                    Sampling and Collection Frequency                                                    Type and Frequency of Analysis with Sample Types                         Identification and Locations (sector-miles)
INGESTION Milk                                                                                Grab sample biweekly                                                                 Gamma isotopic and 1-131 analyses of e........s                     e.........k...............l y....................................
Control Station:
Robert Weir Dairy                         MB-0714 Donaldsonville, GA (SSE - 14)
Fish                                                                                Grab sample semiannually for Game Fish                                               Gamma isotopic analysis on the edible Bo.....Fee.................................................................................................ion...............se.ia and Bottom Feeding Fish                                            ..................portions of each samp le semiannually..........
Indicator Stations:
Downstream of plant                       FGI & FBI discharge in vicinity of Smith's Bend
.(RM41) b Control Station:
Upstream of plant                         FGB & FBB discharge in Andrews Lock &
Dam Reservoir (RM 4 8 )b Forage                                                                              Grab sample from forage every 4 weeks.                                               Gamma isotopic analysis of each sample
                                                                                                                                                                      -  every 4 weeks.
Indicator Station:
South Southeast                           FI-0701 Perimeter (SSE- 1.0)
North Perimeter                           FI- 1601
(...
N- .. .......................................
I..
Control Station:
Dothan, AL (W-18)                         FB-1218

TABLE 2-1 (SHEET 7 of 7)

==SUMMARY==
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NOTATIONS
: a. These collections are normally made at river mile 41.3 for the indicator station and river mile 47.8 for the control station; however, due to river bottom sediment shifting caused by high flows, dredging, etc., collections may be made from river mile 40 to 42 for the indicator station and from river mile 47 to 49 for the control station.
: b. Since a few miles of river water may be needed to obtain adequate fish samples, these river mile positions represent the approximate locations about which the catches are taken. Collections for the indicator station should be from river mile 37.5 to 42.5 and for the control station from river mile 47 to 52.
I'Q 00

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

E Radiological Environmental Sampling Locations Indicator Control  Community        REMP Stations Near the TLD            A         A         A               Plant Perimeter Other          S         S                    _
TED & Other    (0             Q                       Figure 2-1 2-10

Radiological Environmental Sampling Locations Indicator Control  Community      REMP Stations 2 to 5 TLD            A         A         A          Miles From the Plant Other          0         0          0 TLD &Other                                          Figure 2-2 2-11

Radiological Environmental Sampling Locations Indicator Control  Community         REMP Stations Beyond TLD                      A A         A             5 Miles From the Plant Other           S        S                     _
TLD & Other                                             Figure 2-3 2-12

Figure 2-40nsite Groundwater Monitoring Location 2-13

3.0       RESULTS 

==SUMMARY==

In accordance with ODCM 7.1.2.1, the summarized and tabulated results for all of the regular samples collected for the year at the designated indicator, community and control stations are presented in Table 3-1. The format of Table 3-1 is similar to Table 3 of the Nuclear Regulatory Commission (NRC) Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program" Revision 1, November 1979. Results for samples collected at locations other than those listed in Table 2-1 are discussed in Section 4 under the particular sample type.
As indicated in ODCM 7.1.2.1, the results for naturally-occurring radionuclides that are also found in plant effluents must be reported along with man-made radionuclides. The radionuclide Be-7, which occurs abundantly in nature, is often detected in REMP samples. It is occasionally detected in the plant's liquid and gaseous effluents. When it is detected in effluents, it is also included in the REMP results. In 2008, Be-7 was detected in Farley's liquid effluents but not in the gaseous effluents.
3-1

TABLE 3-1 (SHEET 1 of 6)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Medium or      Type and                            Minimum                            Indicator                                    Location with the Highest                   Community           Control Pathway        Total                               Detectable                         Locations                                            Annual Mean                         Locations           Locations Sampled        Number of                           Concentration                      Mean (b),                                                                                Mean (b),           Mean(b),
(Unit of       Analyses                            (MDC) (a)                          Range                            Name Distance Mean (b),                                 Range               Range Measurement)   Performed                                                              (Fraction)                       & Direction                  Range (Fraction)           (Fraction)          (Fraction)
Airborne       Gross Beta 10                                                          16.7                             PB-0215                      21.1                       18.0                20.6 Particulates   476                                                                    2.7-33.8                         Blakely, GA                  7.8-39.6                   4.4-36.1            5.6-39.6 (fC i m 3)      ........
(212/212 )                       15 miles,.N .                 ( 53/5 )                  (158/15 9)           1.06/10 6..)............................
Gamma Isotopic 36 1-131                               70                                 NDM(c)                           NA(d)                                                   NDM                 NDM (0/16)                                                                                   (0/12)              (0/8)
Cs- 134                             50                                 NDM                              NA                                                      NDM                 NDM (0/16)                                                                                   (0/12)              (0/8)
Cs- 137                             60                                 NDM                              NA                                                      NDM                 NDM (0/16)                                                                                   (0/12)              (0/8)
Airborne       1-131                               70                                 NDM                              NA                                                      NDM                 NDM Radioiodine    371                                                                    (0/212)                                                                                  (0/53)              (0/106)
(fCi/m3)
Direct         Gamma                               NA                                 15.0                             RI-0401                       22.2                      12.9                13.7 Radiation      Dose                                                                   11.0-22.6                        Plt. Perimeter                21.7-22.6                 10.4-16.1           10.9-17.5 (mR/91 days)    158                                                                   (63/63)                          0.8 miles, E                  (4/4)                     (71/71)             (24/24)
Milk (pCi/1)   Gamma Isotopic 27 Cs-134                              15                                 NA                               NA                                                      NA                  NDM (0/27)
Cs-137                              18                                 NA                               NA                                                      NA                  NDM (0/27)
B a- 140                            60                                 NA                               NA                                                      NA                  NDM (0/27)
La-140                              15                                 NA                               NA                                                      NA                  NDM f....
r.O. . . . . . . . . . ......                                                                       ............... ......
                                                                                                                                    ..........................                                         27 I-131                               1                                  NA                                NNA                                                                        NDM 27                                                                                                                                                                                  (0/27)

TABLE 3-1 (SHEET 2 of 6)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Medium or        Type and                  Minimum                       Indicator                          Location with the Highest                               Community                   Control Pathway          Total                     Detectable                    Locations                                    Annual Mean                                   Locations                  Locations Sampled          Number of                 Concentration                 Mean (b),                                                                                  Mean (b),                  Mean(b),
(Unit of         Analyses                  (MDC) (a)                     Range                      Name Distance Mean (b),                                         Range                      Range Measurement)     Performed                                               (Fraction)                 & Direction              Range (Fraction)                       (Fraction)                  (Fraction)
Forage           Gamma (pCi/kg wet)     Isotopic 39 1-131                     60                            NDM                        NA                                                              NA                          NvM (0/26)                                                                                                                 (0/13)
Cs-134                    60                            NDM                        NA                                                              NA                          NDM (0/26)                                                                                                                 (0/13)
Cs-137                    80                            10.1                       FI-0701                    10.1                                 NA                          NDM (1/26)                     Plt. Perimeter            (1/26)                                                            (0/13)
                                                                                                   -1.0 mile, SSE Offsite Ground   H-3                       2000                          196                        WGB-10                    237                                   NA                          237 Water (g)        8                                                       (1/4)                      Whatley Res.              234-240                                                           234-240 (p C i/ )         .........      ...............
                                       .........                                                    1... m.le s ,. S ................
(............
(2 / 4).............................................
I-131                      1                            NDM                        NA                                                              NA                          NDM 8                                                       (/4. )                                                                                                                 (0/4)
Gamma Isotopic 8
Mn-54                      15                           NDM                        NA                                                              NA                          NDM (0/4)                                                                                                                  (0/4)
Fe-59                     30                            NDM                        NA                                                              NA                          NDM (0/4)                                                                                                                  (0/4)
Co-58                      15                           NDM                        NA                                                              NA                          NDM (0/4)                                                                                                                  (0/4)
Co-60                      15                           NDM                        NA                                                              NA                          NDM (0/4)                                                                                                                  (0/4)
Zn-65                     30                            NDM                        NA                                                              NA                          NDM (0/4)                                                                                                                  (0/4)
Zr-95                     30                            NDM                        NA                                                                 NA                       NDM (0/4)                                                                                                                  (0/4)
Nb-95                      15                           NDM                        NA                                                                 NA                       NDM 1(0/4)                                                                                                                 1(0/4)

TABLE 3-1 (SHEET 3 of 6)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Medium or       Type and          Minimum                   Indicator                      Location with the Highest                                    Community                            Control Pathway         Total             Detectable                Locations                              Annual Mean                                          Locations                            Locations Sampled         Number of         Concentration             Mean (b),                                                                                   Mean (b),                            Mean(b),
(Unit of        Analyses          (MDC) (a)                 Range                    Name Distance Mean (b),                                            Range                                Range Measurement)    Performed                                   (Fraction)               & Direction            Range (Fraction)                            (Fraction)                            (Fraction)
Cs-134             15                       NDM                      NA                                                                 NA                                    NDM (0/4)                                                                                                                             (0/4)
Cs-137             18                       NDM                      NA                                                                 NA                                    NDM (0/4)                                                                                                                             (0/4)
B a- 140          60                        NDM                      NA                                                                 NA                                    NDM (0/4)                                                                                                                             (0/4)
La- 140            15                       NDM                      NA                                                                 NA                                    NDM (0/4)                                                                                                                             (0/4)
Surface Water   H-3               3000                      644                      Ga Pacific              644                                        NA                                    NDM (pCi/1)          8                                          412-875                  Paper Mill              412-875                                                                          (0/4)
I.........................................
Gamma Isotopic 28 Be-7               124 (e)                  NDM                      NA                                                                 NA                                    NDM (0/14)                                                                                                                            (0/14)
Mn-54              15                       NDM                      NA                                                                 NA                                    NDM (0/14)                                                                                                                            (0/14)
Fe-59             30                        NDM                      NA                                                                 NA                                    NDM (0/14)                                                                                                                            (0/14)
Co-58              15                       NDM                      NA                                                                 NA                                    NDM (0/14)                                                                                                                            (0/14)
Co-60              15                       NDM                      NA                                                                 NA                                    NDM (0/14)                                                                                                                            (0/14)
Zn-65             30                        NDM                      NA                                                                 NA                                    NDM (0/14)                                                                                                                            (0/14)
Zr-95             30                        NDM                      NA                                                                 NA                                    NDM (0/14)                                                                                                                            (0/14)
Nb-95              15                       NDM                      NA                                                                 NA                                    NDM (0/14)                                                                                                                            (0/14)

TABLE 3-1 (SHEET 4 of 6)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Medium or      Type and  Minimum          Indicator            Location with the Highest      Community  Control Pathway        Total     Detectable       Locations                   Annual Mean             Locations  Locations Sampled        Number of Concentration    Mean (b),                                           Mean (b),  Mean(b),
(Unit of       Analyses  (MDC) (a)        Range           Name Distance Mean (b),             Range      Range Measurement)   Performed                  (Fraction)      & Direction        Range (Fraction) (Fraction) (Fraction) 1-131     15 (f)           NDM             NA                                  NA         NDM (0/14)                                                         (0/14)
Cs-134    15               NDM             NA                                  NA         NDM (0/14)                                                         (0/14)
Cs-137    18               NDM             NA                                  NA         NDM (0/14)                                                         (0/14)
Ba-140    60               NDM             NA                                  NA         NDM (0/14)                                                         (0/14)
La- 140   15               NDM             NA                                  NA         NDM (0/14)                                                         (0/14)
Bottom         Gamma Feeding Fish   Isotopic (pCi/kg wet)   4 Be-7      655 (e)          NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Mn-54     130              NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Fe-59     260              NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Co-58     130              NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Co-60     130              NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Zn-65     260              NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Cs-134    130              NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Cs-137    150              11.4            Downstream,         11.4            NA         7.7 9.8-13.0        near Smith's       9.8-13.0                    (1/2)
(2/2)           Bend (RM 41)       (2/2)

TABLE 3-1 (SHEET 5 of 6)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Medium or        Type and    Minimum          Indicator            Location with the Highest      Community  Control Pathway          Total       Detectable       Locations                   Annual Mean             Locations  Locations Sampled          Number of   Concentration    Mean (b),                                           Mean (b),  Mean(b),
(Unit of         Analyses    (MDC) (a)        Range           Name Distance Mean (b),             Range      Range Measurement)     Performed                    (Fraction)      & Direction        Range (Fraction) (Fraction) (Fraction)
Game Fish        Gamma (pCi/kg wet)     Isotopic 4
Be-7        655 (e)          NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Mn-54       130              NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Fe-59       260              NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Co-58        130             NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Co-60        130             NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Zn-65       260              NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Cs-134      130              NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Cs-137      150              16.6            Upstream, at       23.2             NA         23.2 15.5-17.7       Andrews Dam        (1/2)                       (1/2)
(2/2)           (RM 48)
River Shoreline  Gamma Sediment         Isotopic (pCi/kg dry)     4 Be-7        655 (e)          NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Cs-134      150              NDM             NA                                  NA         NDM (0/2)                                                          (0/2)
Cs-137      180              NDM             NA                                  NA         NDM 1                 1(0/2)                                                          (0/2)

TABLE 3-1 (SHEET 6 of 6)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama NOTATIONS
: a. The MDC is defined in ODCM 10.1.            Except as noted otherwise, the values listed in this column are the detection capabilities required by ODCM Table 4-3 (Table 4-1 of this report). The values listed in this column are a priori (before the fact) MDCs. In practice, the a posteriori (after the fact) MDCs are generally lower than the values listed. Any a posteriori MDC greater than the value listed in this column is discussed in Section 4.
: b. Mean and range are based upon detectable measurements only. The fraction of all measurements at a specified location that are detectable is placed in parentheses.
: c. No Detectable Measurement(s).
: d. Not Applicable.
: e. The EL has determined that this value may be routinely attained under normal conditions. No value is provided in Table 4-1 of this report.
: f. If a drinking water pathway exists, a value of 1 pCi/l would be used. See note b of Table 4-1 of this report.
: g. Onsite groundwater results are discussed in Section 4.6.

4.0        DISCUSSION OF RESULTS Included in this section are evaluations of the laboratory results for the various sample types. Comparisons were made between the difference in mean values for pairs of station groups (e.g., indicator and control stations, or, community and control stations) and the calculated Minimum Detectable Difference (MDD) between these pairs, at the 99% Confidence Level (CL). The MDD was determined using the standard Student's t-test. A difference in the mean values which was less than the MDD was considered to be statistically indiscernible.
The 2008 results were compared with past results, including those obtained during preoperation. As appropriate, results were compared with their Minimum Detectable Concentrations (MDC) and Reporting Levels (RL) which are listed in Tables 4-1. and 4-2 of this report, respectively. The required MDCs were achieved during laboratory sample analysis. Any anomalous results are explained within this report.
Results of interest are graphed to' show historical trends. The data points are tabulated and included in this report. The points plotted and provided in the tables represent mean values of only detectable results. Periods for which no detectable measurements (NDM) were observed, or periods for which values were not applicable (e.g., milk indicator, etc.), are plotted as O's and listed in the tables as NDM.
Table 4-1 Minimum Detectable Concentrations (MDC)
Analysis         Water        Airborne          Fish          Milk       Grass or       Sediment (pCi/l)     Particulate     (pCi/kg)        (pCi/l)       Leafy        (pCi/kg) or Gases          wet                     Vegetation         dry (fCi/m3)                                   (pCi/kg) wet Gross Beta          4             10 H-3         2000 (a)
Mn-54            15                           130 Fe-59            30                           260 Co-58            15                           130 Co-60            15                           130 Zn-65            30                           260 Zr-95           30 Nb-95            15 1-131          1 (b)           70                            1            60 Cs-134           15             50             130           15            60            150 Cs-137           18             60            150            18            80            180 Ba-140           60                                          60 La-140           15                                          15 (a) If no drinking water pathway exists, a value of 3000 pCi/l may be used.
(b) If no drinking water pathway exists, a value of 15 pCi/l may be used.
4-1

Table 4-2 Reporting Levels (RL)
Analysis          Water         Airborne            Fish      Milk (pCi/l)     Grass or (pCi/i)      Particulate      (pCi/kg) wet                     Leafy or Gases                                     Vegetation (fCi/m3)                                    (pCi/kg) wet H-3          20,000 (a)
Mn-54             1000                            30,000 Fe-59             400                            10,000 Co-58             1000                            30,000 Co-60              300                            10,000 Zn-65              300                            20,000 Zr-95             400 Nb-95              700 1-131            2 (b)           900                              3              100 Cs-134              30          10,000             1000           60             1000 Cs-137              50          20,000             2000           70            2000 Ba-140             200                                           300 La-140             100                                           400 (a) This is the 40 CFR 141 value for drinking water samples. If no drinking water pathway exists, a value of 30,000 may be used.
(b) If no drinking water pathway exists, a value of 20 pCi/l may be used.
Atmospheric nuclear weapons tests from the mid 1940's through 1980 distributed man-made nuclides around the world. The most recent atmospheric tests in the 1970's and in 1980 had a significant impact upon the radiological concentrations found in the environment prior to and during preoperation, and the earlier years of operation. Some long-lived radionuclides, such as Cs-137, continue to have some impact.
Significant upward trends also followed the Chernobyl incident, which began on April 26, 1986.
In accordance with ODCM 4.1.1.2.1, deviations from the required sampling schedule are permitted if samples are unobtainable due to hazardous conditions, unavailability, inclement weather, equipment malfunction or other just reasons.
Deviations from conducting the REMP as described in Table 2-1 are summarized in Table 4-3 along with their causes and resolutions.
4-2

All results were tested for conformance with Chauvenet's criterion (G. D. Chase and J. L. Rabinowitz, Principles of Radioisotope Methodology,' Burgess Publishing Company, 1962, pages 87-90) to identify values which differed from the mean of a set by a statistically significant amount. Identified outliers were investigated to determine the reason(s) for the variation. If equipment malfunction or other valid physical reasons were identified as causing the variation, the anomalous result was excluded from the data set as non-representative. No data were excluded exclusively for failing Chauvenet's criterion. Data exclusions are discussed in this section under the appropriate sample type.
4-3

TABLE 4-3 (SHEET 1 of 2)
DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM COLLECTION          AFFECTED         DEVIATION                            CAUSE                            RESOLUTION PERIOD              SAMPLE(S) 04/01/08-04/08/08   PB-0215/IB-0215  Non-representative sample of         Sample time short about 1 hour. Station operation satisfactory after CR2008103522        Blakely, GA'     airborne particulates.               Possible power loss due to       sample change out.
inclement weather.
04/22/08-04/29/08   PI-1601/11-1601  Non-representative sample of         Sample time short about 2 hours. Station operation satisfactory after CR2008104250        North Perimeter  airborne particulates.               Reason unknown.                  sample  change out.
04/22/08-04/29/08   PC- 1605         Non-representative sample of         Sample time short about 2 hours. Station operation satisfactory after CR2008104250        Columbia         airborne particulates.               Reason unknown.                  sample  change out.
04/22/08-04/29/08   PC- 1108         Non-representative sample of         Sample time short about 1.25     Station operation satisfactory after CR2008104250        Ashford          airborne particulates.               hours. Reason unknown.           sample  change out.
05/13/08-05/20/08   PC-0703/IC-0703  Non-representative sample of         Sample time short about I hour. Station operation satisfactory after CR2008105037        GA Pacific       airborne particulates.               Possible power loss due to       sample  change out.
inclement weather.
04/22/08-05/20/08   WRI              Non-representative sample of surface Sample supply valve found        Temporary signage added to alert CR2008104736        Paper Mill       water.                               isolated during 3 rd week        paper mill employees not to operate collection. Reason unknown,      valve without notifying Farley Enough sample in collection      personnel.
container to use for weekly portion of monthly composite.
05/27/08-06/03/08   PI- 1601/II-1601 Non-representative sample of         Sample time short about 23       Station operation satisfactory after CR2008105635        North Perimeter  airborne particulates.               hours.                           sample change out.
Reason unknown.
06/03/08-06/10/08   PC-0703/IC-0703  Non-representative sample of         Sample time short about 2 hours. Station operation satisfactory after CR2008105891        GA Pacific       airborne particulates.               Possible power loss due to       sample change out.
inclement weather.
05/20/08-06/17/08   WRI              Non-representative sample of surface Cold shutdown at paper mill for  Autosampler put back in operation CR2008106134        Paper Mill       water,                               maintenance. No flow available   when sample flow resumed.
for river water autosampler on 06/13/08-06/24/08.
06/24/08-07/01/08   PI-0701/II-0701  Non-representative sample of         Sample time short about 2 hours. Station operation satisfactory after CR2008106602        South Perimeter  airborne particulates.               Possible power loss due to       sample change out.
inclement weather.

TABLE 4-3 (SHEET 2 of 2)
DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM COLLECTION          AFFECTED        DEVIATION                             CAUSE                             RESOLUTION PERIOD              SAMPLE(S) 06/17/08-07/15/08   WRI             Non-representative sample of surface  Cold shutdown at paper mill for   Autosampler put back in operation CR2008106134        Paper Mill      water,                                maintenance. No flow available    when sample flow resumed.
for river water autosampler from 06/13/08-06/24/08.
06/17/08-07/15/08   WRI             Non-representative sample of surface  Sample supply valve found         Permanent signage purchased and CR2008106857        Paper Mill      water,                                isolated during 3rd week          added to alert paper mill employees collection. Reason unknown.       not to operate valve without notifying Enough sample in collection       Farley personnel.
container to use for weekly
                                                                         -portion of monthly composite.
2nd Quarter         TLD Station     No direct radiation data available. TLD badges missing at end of      Replaced TLDs at beginning of CR2008106842        RC-1 104 A & B                                        quarter collection.               quarter.
EXCLUDED            WSW @ 4 miles 2 nd Quarter        TLD Station     TLD rendered suspect by presence of   Moisture / rain water entered     Replaced TLDs at beginning of CR2008106842        RI-0201B        water in bag.                         holding bag.                      quarter.
EXCLUDED            NE @ 1.0 mile 07/22/08-07/29/08   PI-1601/II-1601 Non-representative sample of          Sample pump circuit breaker       Station operation satisfactory after CR2008107578        North Perimeter airborne particulates.                tripped. Probable cause was       sample change out.
inclement weather. Sample time short about 16 hours.
08/19/08-08/26/08   PC-1605         Non-representative sample of          Sample lost - possibly            Horizon labels are now affixed to each CR2008108902        Columbia        airborne particulates.                inadvertently discarded. Visual   AF and AC upon receipt by the lab EXCLUDED                                                                  confirmation not performed        requiring the receiver to visually when samples received by lab. confirm that each sample has arrived and been accounted for.
06/17/08-09/09/08   WRI             3 rd Quarter river water tritium      No limits were exceeded, but an   The quarterly sample was reanalyzed CR2008111287        Paper Mill      composite sample higher than usual    investigation revealed that       (confirmed 875 pCi/L). The monthly (923 pCi/1).                          radiological liquid releases made river water gamma samples were also in the 3 rd quarter were higher   analyzed for tritium (6/17-7/15 was activity and river water levels   <MDA, 7/15-8/12 was 99i pCi/L, and were low due to drought           8/12-9/9 was 731 pCi/L) which further conditions (therefore less        confirmed the results. 9/9-10/7 results dilution).                        were -500 pCi/L which was a more typical result for river water tritium.

4.1 Land Use Census In accordance with ODCM 4.1.2, a land use census was conducted during the month of November 2008. The land use census is used to determine the locations of the nearest permanent residence and milk animal in each of the 16 compass sectors within a distance of 5 miles. A milk animal is a cow or goat producing milk for human consumption. The 2008 survey revealed no significant changes from the 2007 survey. No milk animals were found within a 5 mile distance. The census results are tabulated in Table 4.1-1.
Table 4.1-1 LAND USE CENSUS RESULTS Distance in Miles to the Nearest Location in Each Sector SECTOR                RESIDENCE              MILK ANIMAL N                       2.6                     none NNE                       2.5                     none NE                      2.4                     none ENE                      2.4                     none E                       2.8                     none ESE                      3.0                     none SE                      3.4                     none SSE                     none                     none S                      4.3                     none SSW                      2.9                     none SW                       1.2                     none WSW                       2.4                     none W                       1.3                     none WNW                       2.1                     none NW                       1.5                     none NNW                       3.4                     none The Houston County, Alabama and the Early County, Georgia Extension Agents were contacted for assistance in locating commercial dairy farms and privately owned milk animals within 5 miles of the plant. A list of commercial dairy farms in Houston County, AL and Seminole County, GA was provided; there are no commercial dairy farms in Early County. Neither agent knew of privately owned milk animals within 5 miles of FNP. In addition, field surveys were conducted in the plant vicinity along the state and county highways and the interconnecting secondary roads. No milk animals were found within 5 miles of the plant.
ODCM 4.1.2.2.1 requires a new controlling receptor to be determined, if the land use census identifies a location that yields a calculated receptor dose greater than the one in current use. Neither current sampling locations nor the controlling receptor were affected by the 2008 land use census results. The current controlling receptor as described in ODCM Table 3-7 remains a child in the SW Sector at 1.2 miles.
4-6

4.2 Airborne As specified in Table 2-1 and shown in Figures 4.2-1 and 4.2-2, airborne particulate filters and charcoal canisters are collected weekly at 4 indicator, 3 control and 3 community stations. Particulate filters are collected at all of the stations while the charcoal canisters are collected at all but 2 of the community stations. At each location, air is continuously drawn through a glass fiber filter to retain airborne particulates and, as appropriate, an activated charcoal canister is placed in series to adsorb radioiodine.
Each particulate filter is counted for gross beta activity. A quarterly gamma isotopic analysis is performed on a composite of the air particulate filters for each station. Each charcoal canister is analyzed for 1-131.
As provided in Table 3-1, the 2008 annual average weekly gross beta activity was 16.7 fCi/m 3 at the indicator stations and 20.6 fCi/m 3 at the control stations. The difference of 3.9 fCi/m 3 between the two averages is statistically discernible since the MDD for these two average values is 1.8 fCi/m3 . However, the trend over the years has shown close agreement between the control, community, and indicator stations, and in most years (including pre-op), the indicator station gross beta average activity was lower than the control and community annual averages.
As shown in Table 3-1, the 2008 annual average weekly gross beta concentration was 18.0 fCi/m 3 at community stations. The community stations average was 2.6 fCi/m 3 less than the average for the control stations. The difference is not statistically discernible since it is less than the MDD of 1.9 fCi/m 3 between the two averages.
Due to the weapons tests during preoperation and the early years of operation, the average gross beta concentrations were 5 to 10 times greater than those currently being measured. By the mid 1980s, the readings had diminished to about half the current levels. These annual averages approximately doubled as a consequence of the Chernobyl incident in 1986; this impact faded away in approximately 2 years.
The installation of new air monitoring equipment in 1992 yielded an approximate factor of 2 increase in the readings. Since then, the levels have been fairly flat.
The historical trending of the average weekly gross beta air concentrations for each year of operation and the preoperational period at the indicator, control and community stations is plotted in Figure 4.2-1 and listed in Table 4.2-1. In general, there is close agreement between the results for the indicator, control and community stations. This close agreement supports the position that the plant's contribution to gross beta concentration in air is insignificant.
4-7

Figure 4.2-1 Average Weekly Gross Beta Air Concentration 1000 E
0*   100 10 00) 11 1                                                                      -
qO~ &#xfd;b    b'V  q&#xfd;  tpo                qoI        0&sect;    oqb p    b    b'   k d   1 Year I   -  MDC ---  Indicator     -&--Control    -X    Community  I 4-8

Table 4.2-1 Average Weekly Gross Beta Air Concentration Period         Indicator        Control        Community (fCi/m3)        (fCi/m3)        (fCi/m3)
Pre-op             90               92              91 1977             205              206             206 1978              125             115             115 1979             27.3            27.3            28.7 1980             29.7            28.1            29.2 1981              121             115             115 1982             20.0            20.4            21.0 1983             15.5            14.1            14.5 1984             10.2            12.6            10.5 1985              9.0             9.6            10.3 1986             10.5            15.8            12.5 1987              9.0            11.0            17.0 1988              8.0             8.0            10.0 1989              7.0             7.0             8.0 1990             10.0            10.0            10.0 1991              9.0            10.0             8.0 1992             15.0            17.9            18.5 1993             19.1            22.3            22.4 1994             19.0            20.0            19.0 1995             21.7            22.9            21.6 1996             20.3            22.3            23.5 1997             21.1            21.6            22.4 1998             20.6            19.3            22.0 1999             20.5            22.1            25.2 2000             20.9            20.8            23.6 2001             16.3            17.2            17.3 2002             16.8            18.0            16.8 2003             19.1            19.3            19.9 2004             22.0            21.3            22.4 2005             18.4            19.3            19.0 2006             16.1            17.5            16.8 2007             14.5            18.9            17.3 200         16.7            20.6            18.0 4-9

During 2008, no man-made radionuclides were detected from the gamma isotopic analysis of the quarterly composites of the air particulate filters. This has generally been the case since the impact of the weapons tests and the Chernobyl incident have faded. During preoperation and the early years of operation, a number of fission and activation products were detected. Durin~g preoperation, the average levels for Cs-134 and Cs-137 were 22 and 9 fCi/m , respectively. In 1986, as a consequence of the Chernobyl incident, Cs-134 and Cs-137 levels of 33 to 4 fCi/m3 were found. The MDC and RL for Cs-134 are 50 and 10,000 fCi/m and the MDC and RL for Cs-137 are 60 and 20,000 fCi/m 3 respectively.
The historical trending of the annual detectable Cs-137 concentrations for the indicator, control and community stations is provided in Figure 4.2-2 and Table 4.2-2. The trend has been generally downward since preoperation and no positive results have been observed since 1988.
Figure 4.2-2 Average Annual Cs-137 Concentration in Air 20
 ~15-E t0 S10-05 0-qo Year Indicator    -U-*Control --k- CommunityI 4-10

Table 4.2-2 Average Annual Cs-137 Concentration in Air Period          Indicator         Control      Community (fCi/m3)        (fCi/m3)        (fCi/m3)
Pre-op               8                13             7 1977               3.0              3.0            3.0 1978               4.0              5.0            5.0 1979               2.0             NDM             2.0 1980               1.0              2.0            1.8 1981               2.8              3.2            2.6 1982               1.7             NDM             1.0 1983               1.0             NDM             1.0 1984              NDM               1.5           NDM 1985               1.0              1.0            1.0 1986               3.3              3.4            2.7 1987              NDM              NDM            NDM 1988              NDM              NDM               1 1989              NDM              NDM            NDM 1990              NDM              NDM            NDM 1991              NDM              NDM            NDM 1992              NDM              NDM            NDM 1993              NDM              NDM            NDM 1994              NDM              NDM            NDM 1995              NDM              NDM            NDM 1996              NDM              NDM            NDM 1997              NDM              NDM            NDM 1998              NDM              NDM            NDM 1999              NDM              NDM            NDM 2000              NDM              NDM            NDM 2001              NDM              NDM            NDM 2002              NDM              NDM            NDM 2003              NDM              NDM            NDM 2004              NDM              NDM            NDM 2005              NDM              NDM            NDM 2006              NDM              NDM            NDM 2007              NDM              NDM            NDM 2008              NDM          ...'NDM            NDM 4-11

Airborne 1-131 was not detected in the charcoal canisters during 2008. In 1978, levels between 40 and 50 fCi/m 3 were found in a few samples and attributed to the Chinese weapons tests; then after the Chernobyl, incident, levels up to a few hundred fCi/m3 were found in some samples. At no other times has airborne 1-131 been detected in the environmental samples. The MDC and RL for airborne 1-131 are 70 and 900 fCi/m3 respectively.
Table 4-3 lists REMP deviations that occurred during 2008. Although there were 10 air sampling deviations listed in Table 4-3, nine results passed Chauvenet's Criterion and the data was retained in the calculation of the mean values. The one excluded air sample was because the particulate filter was inadvertently discarded prior to analysis. Seven of the 10 were minor deviations where less than 2 hours of sampling time was lost for the week due to power interruptions.
4-12

4.3 Direct Radiation Direct (external) radiation is measured with thermoluminescent dosimeters (TLDs). Two Panasonic UD-814 TLD badges are placed at each station. Each badge contains three phosphors composed of calcium sulfate crystals (with thulium impurity). The gamma dose at each station is based upon the average readings of the phosphors from the two badges. The two badges for each station are placed in thin plastic bags for protection from moisture while in the field. The badges are nominally exposed for periods of a quarter of a year (91 days). An inspection is performed near mid-quarter to assure that all badges are on-station and to replace any missing or damaged badges.
Two TLD stations are established in each of the 16 sectors, to form 2 concentric rings. The inner ring stations are located near the plant perimeter, as shown in Figure 2-1, and the outer ring stations are located at distances of approximately 3 to 5 miles from the plant, as shown in Figure 2-2. The stations forming the inner ring are designated as the indicator stations. The 6 control stations are located at distances greater than 10 miles from the plant, as shown in Figure 2-3. Stations are also provided which monitor special interest areas: the nearest occupied residence (SW at 1.2 miles), as shown in Figure 2-1, and the city of Ashford (WSW at 8 miles), as shown in Figure 2-3. The 16 outer ring stations and the 2 special interest stations are designated as community stations.
As provided in Table 3-1, the average quarterly exposure measured at the indicator stations (inner ring) during 2008 was 15.0 mR which was 1.3 mR greater than the 13.7 mR which was acquired at the control stations. This difference is not statistically discernible since it is less than the MDD of 1.4 mR. The difference of 0.78 mR found between the control stations (13.7 mR) and community stations (12.9 mR) is not statistically discernible since the difference is less than the MDD of 0.84 mR. The difference between the indicator and control and between the control and community stations is consistent with what has been seen in previous years.
The historical trending of the average quarterly exposures in units of mR at the indicator, control, and community locations are plotted in Figure 4.3-1 and listed in Table 4.3-1. During preoperation the average exposure at the indicator stations was 1.2 mR greater than that for the control stations, but the average over the entire period of operation was only 1.1 mR greater. During preoperation, the average exposure at the control stations was 1.3 mR greater than that at the community stations and the average over the period of operation is 1.5 mR greater. This supports the position that the plant is not contributing significantly to direct radiation in the environment.
Table 4-3 lists the REMP program deviations that occurred in 2008. There were two deviations (both in second quarter) involving TLD badges. RI-0201B had moisture in the TLD holding bag. The results from the "B" badge failed Chauvenet's Criterion and were excluded while the "A" badge results were retained in the data set. The badges at RC- 1104 were missing at the end of the second quarter therefore no data was available from the station for that quarter.
4-13

Figure 4.3-1 Average Quarterly Exposure from Direct Radiation 30O 25-E 0
15 0.
X 01 q    Albb                                      4   o0            'Z% QP Year I --- Indicator    --     Control   -    -Community 4-14

Table 4.3-1 Average Quarterly Exposure from Direct Radiation Period     Indicator (mR)      Control (mR)  Community (mR)
Pre-op           12.6              11.4          10.1 1977            10.6              12.2          10.6 1978            15.0              13.5          12.0 1979           20.3               18.7          15.2 1980           21.9               21.6          18.5 1981            16.5              14.9          14.5 1982            15.5              14.7          13.0 1983           20.2               20.2          17.4 1984            18.3              16.9          15.3 1985           21.9               22.0          18.0 1986            17.8              17.7          15.1 1987           20.8               20.0          18.0 1988           21.5               19.9          18.5 1989            18.0              16.2          15.3 1990            18.9              16.4          15.8 1991            18.4              16.1          16.1 1992            16.1              13.6          13.5 1993           .17.4              15.9          15.6 1994            15.0              13.0          12.0 1995            14.0              12.5          11.8 1996            14.2              12.7          11.9 1997            15.3              13.9          11.9 1998            16.2              14.6          13.9 1999            14.7              13.4          12.6 2000            15.5              14.1          13.5 2001            14.9              13.4          12.7 2002            14.1              12.6          11.9 2003            15.2              13.6          12.9 2004            14.3              12.9          12.1 2005            14.7              13.4          12.5 2006            15.2              13.6          12.9 2007            14.6              13.3          12.5 4-15

The standard deviation for the quarterly result for each badge was subjected to a self imposed limit of 1.4. This limit is calculated using a method developed by the American Society for Testing and Materials (ASTM) (ASTM Special Technical Publication 15D, ASTM Manual on Presentation of Data and Control Chart Analysis, Fourth Revision, Philadelphia, PA, October 1976).                 The calculation is based upon the standard deviations obtained by the EL with the Panasonic UD-814 badges during 1992. This limit serves as a flag to initiate an investigation. To be conservative, readings with a standard deviation greater than 1.4 are excluded since the high standard deviation is interpreted as an indication of unacceptable variation in TLD response.
The TLD results from the following stations were excluded from the data set because their standard deviations were greater than 1.4:
Quarter   1 - RI-1401A, RI-1501A Quarter   2 - RC-0304B, RC-1504B, RI- 1101B Quarter   3 - RC-0104B, RC-1404B, RI-0201A, RI-0201B, RI-0901B, RI-1301B Quarter   4 - None For the TLD stations where these badges were located, only the reading of the companion badge was used to determine the quarterly exposure for the station with the exception of 3 rd Qtr RI-0201. Both badges were greater than 1.4 standard deviation so the 3 rd Qtr results from RI-0201 were excluded.
The affected badges were visually inspected under a microscope and the glow curve and test results for the anneal data and the element correction factors were reviewed. No reason was found for the high standard deviations.
4-16

4.4       Milk In accordance with Table 2-1, milk samples are collected biweekly from a control location. 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 2008 land use census.
Gamma isotopic analyses were performed on each sample as specified in Table 2-1. No man-made radionuclides were identified from the gamma isotopic analysis of the milk samples during 2008. The MDC and RL for Cs-137 in milk are 18 and 70 pCi/l, respectively. The historical trending of the average annual detectable Cs-137 concentration in milk samples is shown in Figure 4.4-1 and Table 4.4-1. Cs-137 has not been detected in milk since 1986. Its presence at that time is attributed to the Chemobyl incident. The earlier detectable results were attributed to the weapons tests.
Figure 4.4-1 Average Annual Cs-137 Concentration in Milk 45 40-     1 3-(AI III 35
   .2 0C 25-20-0 5-                                                11111 0--            - --                   -           -
Year Indicator    --*-Control    _MDC 4-17

Table 4.4-1 Average Annual Cs-137 Concentration in Milk Period              Indicator             Control (pCi/i)              (pCi/i)
Pre-op                   32                   18 1977                    41                   20 1978                    15                   17 1979                  NDM                  NDM 1980                  NDM                  NDM 1981                  NDM                  23.0 1982                  NDM                  NDM 1983                  NDM                  NDM 1984                  NDM                  NDM 1985                  NDM                  NDM 1986                  NDM                   16.5 1987                  NDM                  NDM 1988                  NDM                  NDM 1989                  NDM                  NDM 1990                  NDM                  NDM 1991                  NDM                  NDM 1992                  NDM                  NDM 1993                  NDM                  NDM 1994                   NDM                 NDM 1995                  NDM                  NDM 1996                  NDM                  NDM 1997                  NDM                  NDM 1998                  NDM                  NDM 1999                  NDM                  NDM 2000                  NDM                  NDM 2001                  NDM                  NDM 2002                   NDM                 NDM 2003                  NDM                  NDM 2004                   NDM                 NDM 2005                   NDM                 NDM 2006                   NDM                 NDM 2007                   NDM                 NDM 2008                   NDM                 NDM 4-18

As specified in Table 2-1, each sample was analyzed for 1-131, which has not been detected in milk since 1986. The presence of 1-131 at that time is attributed to the Chernobyl incident. The earlier detectable results were attributed to the weapons tests. The MDC and RL for 1-131 are 1 and 3 pCi/l, respectively. Figure 4.4-2 and Table 4.4-2 show the historical trending of the average annual detectable 1-131 concentration in milk samples.
Figure 4.4-2 Average Annual 1-131 Concentration in Milk 50-40     -
: 0. 30-
'4 0
20-0 10, 0 -                        /   \
q0     Xb  q         ~q~bsqcg&#xfd;                C!? o0   4b    VP    &#xfd;9   CvY S Year 1      Indicator     -U-Control  -   MDC     -     RL  I 4-19

Table 4.4-2 Average Annual 1-131 Concentration in Milk Period              Indicator              Control (pCi/i)              (pCi/i)
Pre-op                  41                    14 1977                   20                   2.6 1978                   30                    11 1979                  NDM                  NDM 1980                  NDM                  NDM 1981                  NDM                  NDM 1982                  NDM                  NDM 1983                  NDM                  NDM 1984                  NDM                  NDM 1985                  NDM                  NDM 1986                  NDM                   5.0 1987                  NDM                  NDM 1988                  NDM                  NDM 1989                  NDM                  NDM 1990                  NDM                  NDM 1991                  NDM                  NDM 1992                  NDM                  NDM 1993                  NDM                  NDM 1994                  NDM                  NDM 1995                  NDM                  NDM 1996                  NDM                  NDM 1997                  NDM                  NDM 1998                  NDM                  NDM 1999                  NDM                  NDM 2000                  NDM                  NDM 2001                  NDM                  NDM 2002                  NDM                  NDM 2003                  NDM                  NDM 2004                  NDM                  NDM 2005                  NDM                  NDM 2006                  NDM                  NDM 2007                  NDM                  NDM
` `20089"               7 NDM"                 NDM 4-20

4.5 Forage In accordance with Table 2-1, forage samples are collected every 4 weeks at two indicator stations on the plant perimeter, and at one control station located approximately 18 miles west of the plant, in Dothan. Gamma isotopic analyses are performed on each sample.
During preoperation and the years of operation through 1986 (the year of the Chernobyl incident), Cs-137 was typically found in about a third of the 35 to 40 forage samples collected per year. In 1987 and 1988 the number dropped to about a seventh of the total samples and from 1989 through 1994, it was only found in one or two samples every year. From 1994 to 2006, Cs-137 was detected in only a few samples, three indicator samples and three control samples.
In 2008, Cs-137 was not detected in any of the 13 control samples and detected in only one of the 26 indicator samples at 10.1 pCi/kg wet at FI-0701, 1.0 mile SSE Perimeter. The occasional presence of Cs-137 in vegetation samples is attributed primarily to fallout from nuclear weapons tests and from the Chernobyl incident.
The MDC and RL for Cs-137 in forage are 80 and 2000 pCi/kg wet, respectively.
Table 4.5-1 presents the average detectable results of Cs-137 found in forage over the life of the plant and Figure 4.5-1 shows the historical trending of this data.
4-21

Figure 4.5-1 Average Annual Cs-137 Concentration in Forage 90 80 70 CL 60 0,
50 40 0  30                                  AI I I 20 10 0
qo ,Q Ab 41  tl Year
                    -- Indicator -Control - MDC 4-22

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

During preoperation and in the early years of operation, 1-131 was found in 10%
to 25% of the forage samples at very high levels which ranged from around 100 to 1,000 pCi/kg wet. In 1986 (Chernobyl incident), 1-131 reappeared after not having been detected for 3 years. The MDC and RL for 1-131 are 60 and 100 pCi/kg wet, respectively. Table 4.5-2 lists the average detectable results of 1-131 found in forage over the life of the plant and Figure 4.5-2 plots the historical trending of this data.
1-131 has not been detected in forage samples since the 1986 Chernobyl accident.
Figure 4.5-2 Average Annual 1-131 Concentration in Forage 1000-900 -
15   800-700 O    600 0.
C   500-cc  400-8C  300-0,0  200 0--                                -     -           -                   -
Year
                         --    Indicator    ----  Control -   MDC - RL 4-24

Table 4.5-2 Average Annual 1-131 Concentration in Forage Period              Indicator             Control (pCi/kg) wet          (pCi/kg) wet Pre-op                  405                 486 1977                   971                 654 1978                   220                 240 1979                  NDM                 NDM 1980                  NDM                 NDM 1981                  21.4                NDM 1982                  46.4                NDM 1983                  NDM                 NDM 1984                  NDM                 NDM 1985                  NDM                 NDM 1986                   184                NDM 1987                  NDM                 NDM 1988                  NDM                 NDM 1989                  NDM                 NDM 1990                  NDM                 NDM 1991                  NDM                 NDM 1992                  NDM                 NDM 1993                  NDM                 NDM 1994                  NDM                 NDM 1995                  NDM                 NDM 1996                  NDM                 NDM 1997                  NDM                 NDM 1998                  NDM                 NDM 1999                  NDM                 NDM 2000                  NDM                 NDM 2001                  NDM                 NDM 2002                  NDM                 NDM 2003                  NDM                 NDM 2004                  NDM                 NDM 2005                  NDM                 NDM 2006                  NDM                 NDM 2007                  NDM                 NDM 2008',.               NDM ..  *   ,       NDM 4-25

These forage analyses results show the impact of the weapons tests during preoperation and the early years of operation and of the Chernobyl incident in 1986 and for a few years afterwards. The impact is reflected by the number of different radionuclides detected, the fraction of samples with detectable results, as well as the magnitude of the results. During preoperation and for the first few years of operation, 11 different radionuclides from fission and activation products were detected. By 1985, only 2 different radionuclides were detected and the fraction of samples with detectable results had diminished. In 1986, the same two nuclides as seen in 1985 appeared at a significantly higher magnitude and 1-131 reappeared. In the years following 1986, only Cs-137 has been found in forage and it has been found in a decreasing fraction of the samples.
4-26

4.6 Ground Water In the FNP offsite environs, there are no true indicator sources of ground water. A well, located about four miles south-southeast of the plant on the east bank of the Chattahoochee River, serves Georgia Pacific Paper Company as a source of potable water and is designated as the indicator station. A deep well located about 1.2 miles southwest of the plant, which supplies water to the Whatley residence, is designated as the control station. Samples are collected quarterly and analyzed for gamma isotopic, 1-131 and tritium as specified in Table 2-1. In 2008, one indicator sample and two control samples were positive for tritium. No other radionuclides were detected.
In 1983, 1985, and 1986, Cs-134 was detected in single samples at levels ranging from 3 to 13 pCi/l. The MDC and RL for Cs-134 in water are 15 and 30 pCi/l, respectively.
During preoperation, Cs-137 was detected in two of the samples at levels of 15 and 17 pCi/l. Then in 1984 and 1985, Cs-137 was again detected in a few samples with levels ranging from 4 to 5 pCi/l. The MDC and RL for Cs-137 in water are 18 and 50 pCi/l, respectively.
Iodine-131 has never been detected in ground water samples. From 1986-2003, no radionuclides were detected. In 2004, 2005, 2007, and 2008, tritium was detected at very low concentrations (near the instrument detection level) and close to environmental background concentration which is approximately 350 pCi/l (+/-
150 pCi/1) in the area around Farley. The positive results seen in these years were less than 2% of the reporting level for tritium. In 2008, the difference between the single positive value (196 pCi/L) seen at the indicator station and the average of the 2 positive values (237 pCi/L) seen at the control station was not statistically discernible (using the modified Student's t-test). The MDC and RL for tritium in drinking water are 2,000 and 20,000 pCi/l, respectively. Figure 4.6-1 and Table 4.6-1 show the historical trending of the average annual detectable tritium concentration in ground water.
4-27

Figure 4.6-1 Average Annual H-3 Concentration in Offsite Ground Water 2500 2000 C.2e- 1500 O1000 0
500 0
0-   --          -           ..        ..    .--.-..-.. . . . J -*
Year 0                            -Indicator   -- l--Control  -MDC 4-28

Table 4.6-1 Average Annual H-3 Concentration in Offsite Ground Water Period             Indicator              Control
(_C__   _(pCi/l)      (pCi/i)
Pre-op                  150                  240 1977                 NDM                   NDM 1978                 NDM                    240 1979                 NDM                   NDM 1980                   124                 NDM 1981                  264                  NDM 1982                  240                  NDM 1983                  360                   341 1984                 NDM                   NDM 1985                 NDM                   NDM 1986                 NDM                   NDM 1987                 NDM                   NDM 1988                 NDM                   NDM 1989                 NDM                   NDM 1990                 NDM                   NDM 1991                 NDM                   NDM 1992                 NDM                   NDM 1993                 NDM                   NDM 1994                 NDM                   NDM 1995                 NDM                   NDM 1996                 NDM                   NDM 1997                 NDM                   NDM 1998                 NDM                   NDM 1999                 NDM                   NDM 2000                 NDM                   NDM 2001                 NDM                   NDM 2002                 NDM                   NDM 2003                 NDM                   NDM 2004                   194                  271 2005                  264                   360 2006                 NDM                   NDM 2007                  218                   321 2008                 *196                   237 4-29

As nuclear plants began to undergo decommissioning in the late 1990's to early 2000s, instances of subsurface and/or groundwater contamination were identified.
In addition, several operating facilities also identified groundwater contamination resulting from spills and leaks or equipment failure. In one instance, low levels of licensed material were detected in a private well located on property adjacent to a nuclear power plant.
In 2006, NEI (Nuclear Energy Institute) formed a task force to address monitoring onsite groundwater for radionuclides at nuclear facilities. A Groundwater Protection Initiative was developed which was adopted by all U.S. commercial operating nuclear plants.
The NRC also formed a task force to study the groundwater issues and released Information Notice 2006-13 "Ground-water Contamination due to Undetected Leakage of Radioactive Water" which summarized its review of radioactive contamination of ground water at multiple facilities as a result of undetected leakage from structures, systems, or components that contain or transport radioactive fluids. Licensees were instructed to review the information for applicability and to consider appropriate actions to avoid similar problems.
The NEI task force felt it was prudent for the industry to update site hydrology information and to develop radiological groundwater monitoring plans at each site. These groundwater protection plans would ensure that underground leaks and spills would be addressed promptly.                Additionally, the task force recommended developing a communications protocol to report radioactive leaks or spills that entered groundwater (or might eventually enter groundwater) to the NRC and State and Local government officials as needed.
In 2006, Farley located several old onsite piezometer wells and sampled these and the onsite drinking water wells for tritium and gamma isotopic activity. None of these wells contained detectable amounts of radioactivity. In 2007, after the site hydrology was evaluated, Farley implemented a more extensive radiological groundwater monitoring program which included drilling twelve new onsite monitoring wells (see Table 2-2). The twelve new wells along with one of the existing piezometer wells, the onsite drinking water wells, and several surface water / discharge locations comprise the monitoring program. These locations were sampled twice in the latter portion of 2007 and sampled quarterly in 2008.
Of the numerous samples taken during 2007 and 2008 (from the locations described above), only one location (groundwater well R-3) showed low levels of radiological contamination (see Figure 4.6-2). Tritium was the only nuclide identified. R-3 was also analyzed for gamma emitters (quarterly) and strontium (initially and after increase was noted) and these were not detected. This well is located near the Protected Area and in the vicinity of the site where the Unit-2 radioactive effluent discharge line ruptured several years ago. For guidance regarding monitoring wells with unexpected results, Southern Nuclear developed a company-wide communications protocol which is contained in the Nuclear Management Procedure, Actions for Potential Groundwater Contamination Events, to ensure radioactive leaks and spills are addressed and communicated appropriately.
4-30

Figure 4.6-2 H-3 Concentration in Onsite Ground Water Well R-3 6000-5000       -
: 0. 4000 --                                    ,___
"u 3000                                   ___
2000 1000-   -
0 0                   11i 4-31

4.7           Surface Water As specified in Table 2-1 and shown in Figure 2-2, water samples are collected from the Chattahoochee River at a control station approximately 3 miles upstream of the intake structure and at an indicator station approximately 4 miles downstream of the discharge structure. Small quantities are collected during the week at periodic intervals using automatic samplers. For each station, one liter from each of four consecutive weekly samples is combined into a composite sample which is analyzed for gamma emitters. In addition, 0.075 liters is collected from 13 consecutive weekly samples for each station to form composite quarterly samples which are analyzed for tritium.
No detectable results have been found from these gamma isotopic analyses since 1988. During preoperation and in every year of operation through 1988 (except 1979 and 1980), a few samples showed at least one of nine different activation or fission products at levels less than or on the order of their MDCs. During preoperation, Cs-137 was found in about 3% of the samples. From 1981 through 1988, it was found in about 15% of the samples. Cs-134 was found in about 15%
of the samples from 1981 to 1986. All of these gamma emitters are attributed to the weapons tests and the Chernobyl incident.
In 2008, as shown in Table 3-1, tritium was detected in the 2 nd quarter (412 pCi/L) and 3 rd quarter (875 pCi/L) composite samples collected at the indicator station and in none of the 4 quarterly composite samples collected at the control station.
The annual average concentration at the indicator station was 644 pCi/l. The initial result of the 3rd Qtr indicator composite was 923 pCi/L of tritium.
Although no limits were exceeded, Condition Report 2008111287 was written to investigate the higher than typical quarterly result. The sample was reanalyzed at 875 pCi/L and this value was used in the annual average. The reason for the atypical quarterly result was due to higher activity liquid releases during the summer in combination with lower river flow due to drought conditions.
Historical trending of the detectable concentrations of tritium in surface water is provided in Figure 4.7-1 and Table 4.7-1. The slightly elevated plot of the indicator stations is indicative of plant tritium contributions to surface water.
However, it is noteworthy that the annual average levels are less than 10% of the MDC and less than 1% of the RL. The MDC and RL for tritium in surface water are 3,000 and 30,000, respectively.
4-32

Figure 4.7-1 Average Annual H-3 Concentration in Surface Water 3500 3000
  .2500 2000 0 1500--
0   1000-500 0
Year
                   -- e Indicator  --   Control - MDC 4-33

Table 4.7-1 Average Annual H-3 Concentration in Surface Water Period              Indicator              Control (pCi/l)              (pCi/i)
Pre-op                  200                 170 1977                   300                 160 1978                   230                 250 1979                   169                 135 1980                   221                 206 1981                   294                 162 1982                   300                 132 1983                   434                 111 1984                   333                 152 1985                   351                 105 1986                   478                 272 1987                  291.8               116.5 1988                  293.3               NDM 1989                  253.8               NDM 1990                   166                NDM 1991                   122                NDM 1992                  360.5                134 1993                  388.8               NDM 1994                  NDM                 NDM 1995                   257                NDM 1996                   386                NDM 1997                  NDM                 NDM 1998                   415                NDM 1999                   314                NDM 2000                   424                 212 2001                   252                NDM 2002                   598                NDM 2003                   296                NDM 2004                   270                NDM 2005                   215                 173 2006                   348                 179 2007                   321                NDM 2008                  -:644              "NDM 4-34

4.8 Fish Two types of fish (bottom feeding and game) are collected semiannually from the Chattahoochee River at a control station several miles upstream of the plant intake structure and at an indicator station a few miles downstream of the plant discharge structure. These locations are shown in Figure 2-2. Gamma isotopic analysis is performed on the edible portions of each sample as specified in Table 2-1.
As provided in Table 3-1, Cs-137 was the only radionuclide of interest that was found from the gamma isotopic analysis of fish samples in 2008. Cs-137 was detected in both the fall and spring collection of game fish samples at the indicator station. The average was 16.6 pCi/kg wet. Cs-137 was detected in one game fish sample at the control station (23.2 pCi/kg-wet). Using the modified Student's t-test, the difference between the indicator and control station was not statistically discernible. The average of the samples at the indicator station was less than 1%
of the reporting level. The MDC for Cs-137 in fish is 150 pCi/kg wet and the RL is 2000 pCi/kg wet.
Cesium-137 was detected in both the fall and spring collection of bottom feeding fish samples at the indicator location. The average of the two samples was 11.4 pCi/kg wet. Cs-137 was detected in one (7.7 pCi/kg wet) of the two bottom feeding fish samples collected at the control station. Using the modified Student's t-test, the difference between the indicator and control station was not statistically discernible. The average of the samples at the indicator station was less than 1%
of the reporting level. The MDC for Cs-137 in fish is 150 pCi/kg wet and the RL is 2000 pCi/kg wet.
Historically, Cs-137 has been found in approximately 30% of the bottom feeding fish samples and in 80% of the game fish samples. Figures 4.8-1 and 4.8-2 and Tables 4.8-1 and 4.8-2 provide the historical trending of the average annual detectable concentrations of Cs-137 in pCi/kg wet in bottom feeding and game fish, respectively. Since the early 1980s, values have generally decreased for both indicator and control groups, with the exception of the bottom feeding fish collected at the indicator station in 1993. While some contribution from the plant cannot be ruled out, most of the Cs-137 in these samples may be attributed to the nuclear weapons tests and the Chernobyl incident, as evidenced by the normally close agreement between the control and indicator station results.
4-35

Figure 4.8-1 Average Annual Cs-137 Concentration in Bottom Feeding Fish 250 S200 L     150 0.
2-. 100 0
LU     50 I
0NI&#xfd;-4-D  1-.1   &#xfd;    I -    I~ -I-lKt
                                         -4          h .1-- 4 T   E .r E I Year 1  ---
4-Indicator    Control  -   MDC I 4-36

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

Figure 4.8-2 Average Annual Cs-137 Concentration in Game Fish 350 300
  ~250
: c. 200 S150 0
Year Indicator -m-  Control MDC 4-38

Table 4.8-2 Average Annual Cs-137 Concentration in Game Fish Period               Indicator            Control Pre-op 7       (pCi/kg) wet 84 (pCi/kg) wet 60 1977                    95                  48 1978                  NDM                 NDM 1979                   111                 83.5 1980                   289                316 1981                   189                126 1982                     76                 77 1983                     57                 56.5 1984                    42                  26 1985                     84                 44 1986                     51                 35 1987                     83                 46 1988                    42                  33 1989                     38                 29 1990                     28               NDM 1991                     36                 24 1992                    32.5                28 1993                     34               NDM 1994                     19                 16 1995                    17.9                18.2 1996                    19.6                23.1 1997                    25.9              NDM 1998                    52                  20 1999                    36.9                 15.9 2000                   22.9                12.5 2001                   22.4                12.3 2002                  NDM                  10.1 2003                   19.3                12.0 2004                   12.7                10.8 2005                   15.7               NDM 2006                   15.0                14.7 2007                   15.4                 6.5 2008                   16.6                23.2 4-39

Radionuclides of interest other than Cs-137 have been found in only a few samples in the past. The following table provides a summary of the results in pCi/kg wet compared with the applicable MDCs.
YEAR          Nuclide         Fish Type      Indicator     Control       MDC (pCi/kg)    (pCi/kg)     (pCi/kg) 1978          Ce- 144     Bottom Feeding      NDM           200 1981          Nb-95       Bottom Feeding        38         NDM          50 (a) 1982          Nb-95            Game             31         NDM          50 (a) 1986          Co-60            Game             25         NDM            130 (a) Determined by the EL. Not defined in ODCM Table 4-3 (Table 4-1 of this report) 4-40

4.9      Sediment River sediment samples are collected semiannually on the Chattahoochee River at a control station which is approximately 4 miles upstream of the intake structure and at an indicator station which is approximately 2 miles downstream of the discharge structure as shown in Figure 2-2. A gamma isotopic analysis is performed on each sample as specified in Table 2-1. During 2008, no nuclides of interest were detected in river sediment.
Historically, Be-7, Cs-134, Cs-137, and Nb-95 have been detected in some samples. These positive results were generally for samples collected at the control station. A summary of the positive historical results for these nuclides along with their applicable MDCs in units of pCi/kg dry is provided in Table 4.9. Cs-134 and Cs-137 data are plotted in Figures 4.9-1 and 4.9-2, respectively.
Table 4.9 Sediment Nuclide Concentrations Nuclide      YEAR       Indicator (pCi/kg)    Control (pCi/kg)       MDC (pCi/kg)
Be-7         1985               535                 945                  655 (a) 2003               199                NDM Cs-134        1987              NDM                   45                    150 1989              NDM                   48 1992               138                   51 1993                 94                105 Cs-137        1981              NDM                  185                    180 1985              NDM                   97 1989              NDM                   39 1994                29                  11 1996                11.8              NDM 2005                14.5              NDM Nb-95        1981                 52                113                   50 (a)
(a) Determined by the EL. Not defined in ODCM Table 4-3 (Table 4-1 of this report).
4-41

Figure 4.9-1 Average Annual Cs-134 Concentration in Sediment 160         -  1-1--          1-            - -  - -  - -   -  - -    - - -
140 -
120 ----
1
-. 08o---
0
     ,0                                                                4z%  c.?/
Year I-4-Indicator -U---Control   -- MDC  I The positive results for Cs-134 appear mostly at the control station. Due to its relatively short half-life of approximately 2 years, the positive results may be attributed to the Chemobyl incident. The overall plotting of the positive results does not show any discernible trends.
4-42

Figure 4.9-2 Average Annual Cs-1 37 Concentration in Sediment 200-180   --     -    -  -     -    -    -     -     -     -      -   -    -   - -   -       -
10)
   ~140--
,. 120       --
C) 0 0
40------------
60                          /         -     -     -     --     -    -   --    -   -   -
40--
20             /
Year
                               -*lndicator        --  Control    -    MDC Cs-137 appears to be trending down since the ceasing of above ground weapons testing and the majority of the positive results appear at the control stations.
Therefore in general, the positive results can be attributed to the weapons tests and the Chernobyl incident.
4-43

5.0 INTERLABORATORY COMPARISON PROGRAM In accordance with ODCM 4.1.3, the EL participates in an ICP that satisfies the requirements of Regulatory Guide 4.15, Revision 1, "Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment", February 1979. The guide indicates the ICP is to be conducted with the Environmental Protection Agency (EPA) Environmental Radioactivity Laboratory Intercomparison Studies (Cross-check) Program or an equivalent program, and the ICP should include all of the determinations (sample medium/radionuclide combinations) that are offered by the EPA and included in the REMP.
The ICP is conducted by Analytics, Inc. of Atlanta, Georgia. Analytics has a documented Quality Assurance (QA) program and the capability to prepare Quality Control (QC) materials traceable to the National Institute of Standards and Technology. The ICP is a third party blind testing program which provides a means to ensure independent checks are performed on the accuracy and precision of the measurements of radioactive materials in environmental sample matrices.
Analytics supplies the crosscheck samples to the EL which performs the laboratory analyses in a normal manner. Each of the specified analyses is performed three times. The results are then sent to Analytics who performs an evaluation which may be helpful to the EL in the identification of instrument or procedural problems.
The samples offered by Analytics and included in the EL analyses are gross beta and gamma isotopic analyses of an air filter; gamma isotopic analyses of milk samples; and gross beta, tritium and gamma isotopic analyses of water samples.
The accuracy of each result is measured by the normalized deviation, which is the ratio of the reported average less the known value to the total error. The total error is the square root of the sum of the squares of the uncertainties of the known value and of the reported average. The uncertainty of the known value includes all analytical uncertainties as reported by Analytics. The uncertainty of the reported average is the propagated error of the values in the reported average by the EL.
The precision of each result is measured by the coefficient of variation, which is defined as the standard deviation of the reported result divided by the reported average. An investigation is undertaken whenever the absolute value of the normalized deviation is greater than three or whenever the coefficient of variation is greater than 15% for all radionuclides other than Cr-51 and Fe-59. For Cr-51 and Fe-59, an investigation is undertaken when the coefficient of variation exceeds the values shown as follows:
Nuclide       Concentration
* Total Sample Activity     Percent Coefficient (pCi)                     of Variation Cr-51       <300                  NA                        25 Cr-51       NA                    >1000                     25 Cr-51       >300                  <1000                     15 Fe-59       <80                   NA                        25 Fe-59       >80                   NA                        15
* For air filters,    concentration units are pCi/filter. For all other media, concentration units are pCi/liter (pCi/1).
5-1

As required by ODCM 4.1.3.3 and 7.1.2.3, a summary of the results of the EL's participation in the ICP is provided in Table 5-1 for: the gross beta and gamma isotopic analyses of an air filter; gamma isotopic analyses of milk samples; and gross beta, tritium and gamma isotopic analyses of water samples. Delineated in this table for each of the media/analysis combinations, are: the specific radionuclides; Analytics' preparation dates; the known values with their uncertainties supplied by Analytics; the reported averages with their standard deviations; and the resultant normalized deviations and coefficients of variation expressed as a percentage.
The GPC EL analyzed 13 samples for 43 parameters in 2008. The analyses included tritium, gross beta, Fe-55, Sr-89/90 and gamma emitting radio-nuclides in milk, water, air cartridge and air filter matrices. The attached results indicate three analyses outside the three sigma control limits. They were the following:
: 1) Mn-54 in air filter (Environmental Program) for accuracy.
: 2) Co-58 in water (Environmental Program) for precision
: 3) Gross alpha in water (Effluent Program) for accuracy.
The first quarter effluent water sample analyzed for gross alpha had a low activity recovery. The gross alpha in water self absorption curve was evaluated and updated. The second quarter alpha sample was in control for both accuracy and precision. A known alpha activity sample will be processed with the blind samples in the future to assure accurate results.
The third quarter environmental air filter sample was analyzed by gamma spectroscopy and had a high activity recovery for Mn-54. The sample was analyzed by three detectors and a weighted average reported. A small range from the three detectors produced an elevated normalized deviation result. The value was above the three sigma control limit, however the recovery of the Mn-54 activity is 114% and is acceptable.
The precision failure was in the first quarter water sample analyzed by gamma spectroscopy. The %CV for Co-58 was above the control limit. The sample was analyzed on three detectors with an error weighted average reported. An elevated range of values in the analysis is due to one of the detectors measuring a higher activity. No inconsistencies were found in the detector shaping or analysis of the 810 kev gamma peak. No further investigation will be performed.
In 2009 the Environmental Laboratory will adopt the NRC Inspection Procedure's guidance for acceptance criteria in performance sample testing. The adoption of the NRC Inspection Procedure 84750 will keep the lab consistent with the nuclear industry.
5-2

TABLE 5-1 (SHEET 1 of 3)
INTERLABORATORY COMPARISON PROGRAM RESULTS GROSS BETA ANALYSIS OF AN AIR FILTER (pCi/filter)
Analysis or  Date        Reported      Known          Standard          Uncertainty      Percent Coef Normalized Radionuclide Prepared    Average       Value        I Deviation  EL   I Analytics (3S) I of Variation   Deviation Gross Beta   09/18/08          128.00[       121.00[            4.82]             2.03             5.43           1.01 GAMMA ISOTOPIC ANALYSIS OF AN AIR FILTER (pCi/filter)
Analysis or  Date        Reported      Known          Standard          Uncertainty      Percent Coef   Normalized Radionuclide Prepared    Average       Value          Deviation EL      Analytics (3S)   of Variation   Deviation Ce- 141      09/18/08          134.00        132.00             6.74              0.74             5.81          0.25 Co-58        09/18/08          149.70        146.00               6.7             0.81             3.84          0.61 Co-60        09/18/08          197.10        192.00             7.81              1.07             3.22          0.74 Cr-51        09/18/08          390.10        345.00           14.59               1.92             6.74           1.69 Cs-134       09/18/08          186.90        190.00             6.88              1.06             4.54         -0.35 Cs-137       09/18/08          143.20        133.00             5.23              0.74             4.92           1.40 Fe-59        09/18/08          140.60        118.00             2.99              0.66             4.58           3.40 Mn-54        09/18/08          154.60        136.00             1.14              0.76             3.42           3.30 Zn-65        09/18/08          295.40        262.00           13.08               1.46             5.70           1.93 GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (pCi/liter)
Analysis or  Date        Reported      Known          Standard          Uncertainty      Percent Coef   Normalized Radionuclide Prepared    Average       Value          Deviation EL      Analytics (3S)   of Variation   Deviation Ce- 141      06/19/08          180.10        174.00           13.17               0.97             8.56          0.39 Co-58        06/19/08            68.90        61.90             4.77              0.34             0.65          0.96 Co-60        06/19/08          112.60        104.00             5.69              0.58             6.87           1.10 Cr-51        06/19/08          146.70        138.00           23.39               0.77           25.12           0.24 Cs- 134      06/19/08            74.70        76.70             2.67              0.43             7.18         -0.36 Cs-137       06/19/08          118.20        116.00             5.44              0.65             7.27          0.25

TABLE 5-1 (SHEET 2 of 3)
INTERLABORATORY COMPARISON PROGRAM RESULTS GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (pCi/liter)
Analysis or    Date        Reported        Known          Standard      Uncertainty    Percent Coef Normalized Radionuclide I Prepared    Average       I Value        I Deviation EL Analytics (3S)  of Variation I Deviation Fe-59          06/19/08          109.40           91.70           13.67           0.51          14.96           1.08 1-131          06/19/08            88.90          71.40             9.9           0.40          12.83           1.53 Mn-54          06/19/08          152.00          135.00            4.56           0.75           5.68           1.92 Zn-65        106/19/08    1      135.40          127.00            8.19           0.71          10.23           0.60 GROSS BETA ANALYSIS OF WATER SAMPLE (pCi/liter)
GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (pCi/liter)
Analysis or    Date        Reported        Known          Standard      Uncertainty    Percent Coef   Normalized Radionuclide   Prepared    Average         Value          Deviation EL  Analytics (3S) of Variation   Deviation Ce-141         03/20/08          204.60          198.00            8.08           2.21           5.87           0.55 Co-58          03/20/08            58.50          56.40            9.22           0.63          15.77           0.23 Co-60          03/20/08          188.90          189.00            9.74           2.09           6.57           0.06 Cr-51          03/20/08          356.30          286.00           21.56           2.85          12.23           1.61 Cs-134         03/20/08            99.90          99.70            2.29           1.11           5.91           0.03

TABLE 5-1 (SHEET 3 of 3)
INTERLABORATORY COMPARISON PROGRAM RESULTS GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (pCi/liter)
Analysis or     Date         Reported       Known           Standard        Uncertainty       Percent Coef Normalized Radionuclide    Prepared     Average        Value           Deviation EL    Analytics (3S) of Variation       Deviation Cs-137          03/20/08            121.50         116.00            9.85              1.29           10.22             0.45 Fe-59          03/20/08              92.60          81.40            7.75             0.91            12.21             0.99 1-131          03/20/08              68.90          70.40            0.98             0.79             8.64            -0.25 Mn-54          03/20/08              83.20          75.00            4.32             0.83             8.84             1.11 Zn-65          03/20/08             119.90         109.00            6.41              1.21           11.03             0.83 TRITIUM ANALYSIS OF WATER SAMPLES (pCi/liter)
Analysis or     Date         Reported       Known           Standard       1Uncertainty       Percent Coef Normalized Radionuclide    Prepared     Average        Value          IDeviation EL I Analytics (3S) of Variation        Deviation H-3             03/20/08          3988.70[        4010.00           87.41 1          22.33             4.28 [          -0.13 106/19/08    1     12,900.00[     13,000.00 [         44.32]           72.33 1           2.16 [          -0.48 1-131 ANALYSIS OF AN AIR CARTRIDGE (pCi/cartridge)
~Analysis or    Date         Reported      [Known           Standard        Uncertainty       Percent Coef    Normalized Radionuclide Prepared       Average        Value           Deviation EL Analytics (3S) of Variation          Deviation 1-131         112/11/08   151.301                  54.801           0.22 1o.31             1          3.83-F-1.75

==6.0 CONCLUSION==
S This report confirms the licensee's conformance with the requirements of Chapter 4 of the ODCM. It provides a summary and discussion of the results of the laboratory analyses for each type of sample.
In 2008, there were two instances where the indicator station results were statistically discernible from the control station results - tritium in surface water and Cs-137 in forage. These are discussed below. No discernible radiological impact upon the environment or the public as a consequence of plant discharges to the atmosphere and to the river was established for any other REMP samples.
Tritium was detected at the indicator station in two of the four quarterly surface water sample collections. No tritium was detected at the control station.
Although no drinking water pathway via surface water exists in the plant vicinity, a potential dose was calculated assuming a person regularly consumed drinking water from the river. The potential dose of 0.049 mrem in a year is less than 2%
of the annual dose limit for the total body due to liquid effluents (3 mrem).
Another pathway to obtain dose from tritium in the river is through consumption of fish. The potential total body dose for an adult who consumed fish regularly from the river would be about 1.3E-03 mrem in a year which is approximately 0.04% of the annual limit for the total body (3 mrem) due to liquid effluents.
Cesium-137 was detected in forage in one of 26 samples at the indicator station, FI-0701 Plant Perimeter 1.0 mile SSE, (at 10.1 pCi/kg wet) and in none of the 13 samples at the control station. The potential dose to an adult (member of the public who would receive the highest dose) due to regular consumption of leafy vegetation containing Cs-137 at this low level would be 0.016 mrem in a year.
This dose is approximately 0.1% of the regulatory limit of 15 mrem per year to any organ due to gaseous effluents. Low levels of Cs-137 in the environment are attributed primarily to fallout from nuclear weapons testing and from the Chernobyl incident. However, the level of Cs-137 seen at FI-0701 could potentially be attributed to plant effluents.
The radiological levels reported in 2008 were low and are generally trending downward. The REMP trends over the course of time from preoperation to the present are generally decreasing or have remained fairly constant. This supports the conclusion that there is no adverse radiological impact on the environment or to the public as a result of the operation of Farley Nuclear Plant.
6-1

Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radiological Environmental Operating Reports for 2008 Enclosure 3 Vogtle Annual Radiological Environmental Operating Report for 2008

VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2008 SOUTHERN LAk COMPANY Energy to Serve Your World"

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

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

LIST OF TABLES Table Number Title                                                 Page Table 2-1    Summary Description of Radiological Environmental Monitoring Program                                        2-2 Table 2-2    Radiological Environmental Sampling Locations             2-7 Table 2-3    Groundwater Monitoring Locations                         2-10 Table 3-1    Radiological Environmental Monitoring Program Annual Summary                                                   3-2 Table 4-1    Minimum Detectable Concentrations (MDC)                   4-1 Table 4-2    Reporting Levels (RL)                                     4-2 Table 4-3    Deviations from Radiological Environmental Monitoring Program                                                   4-4 Table 4.1-1  Land Use Census Results                                   4-5 Table 4.2-1  Average Weekly Gross Beta Air Concentration               4-9 Table 4.3-1  Average Quarterly Exposure from Direct Radiation         4-13 Table 4.3-2  Average Quarterly Exposure from Direct Radiation at Special Interest Areas                                   4-15 Table 4.4-1  Average Annual Cs-137 Concentration in Milk              4-18 Table 4.5-1  Average Annual Cs-137 Concentration in Vegetation        4-21 Table 4.6-1  Average Annual H-3 Concentration in River Water          4-24 Table 4.7-1  Average Monthly Gross Beta Concentration in Raw Drinking Water                                           4-27 Table 4.7-2  Average Monthly Gross Beta' Concentration in Finished Drinking Water                                           4-29 Table 4.7-3  Average Annual H-3 Concentration in Raw Drinking Water                                                    4-32 Table 4.7-4  Average Annual H-3 Concentration in Finished Drinking Water                                                    4-34 Table 4.8-1  Average Annual Cs-137 Concentration in Fish              4-37 Table 4.9-1  Average Annual Be-7 Concentration in Sediment            4-40 Table 4.9-2  Average Annual Co-58 Concentration in Sediment           4-42 Table 4.9-3  Average Annual Co-60 Concentration in Sediment           4-44 Table 4.9-4  Average Annual Cs-137 Concentration in Sediment          4-46 Table 4.9-5  Additional Sediment Nuclide Concentrations               4-46 Table 5-1    Interlaboratory Comparison Program Results                5-3 111

LIST OF ACRONYMS.
Acronyms presented in alphabetical order.
Acronym    Definition ASTM       American Society for Testing and Materials CL         Confidence Level EL         Georgia Power Company Environmental Laboratory EPA        Environmental Protection Agency GPC        Georgia Power Company ICP        Interlaboratory Comparison Program MDC        Minimum Detectable Concentration MDD        Minimum Detectable Difference MWe        MegaWatts Electric NA         Not Applicable NDM        No Detectable Measurement(s)
NRC        Nuclear Regulatory Commission ODCM       Offsite Dose Calculation Manual Po         Preoperation PWR        Pressurized Water Reactor REMP       Radiological Environmental Monitoring Program RL         Reporting Level RM         River Mile TLD        Thermoluminescent Dosimeter TS         Technical Specification VEGP       Alvin W. Vogtle Electric Generating Plant iv

==1.0 INTRODUCTION==

The Radiological Environmental Monitoring Program (REMP) is conducted in accordance with Chapter 4 of the Offsite Dose Calculation Manual (ODCM). The REMP activities for 2008 are reported herein in accordance with Technical Specification (TS) 5.6.2 and ODCM 7.1.
The objectives of the REMP are to:
: 1) Determine the levels of radiation and the concentrations of radioactivity in the environs and;
: 2) Assess the radiological impact (if any) to the environment due to the operation of the Alvin W. Vogtle Electric Generating Plant (VEGP).
The assessments include comparisons between results of analyses of samples obtained at locations where radiological levels are not expected to be affected by plant operation (control stations) and at locations where radiological levels are more likely to be affected by plant operation (indicator stations), as well as comparisons between preoperational and operational sample results.
VEGP is owned by Georgia Power Company (GPC), Oglethorpe Power Corporation, the Municipal Electric Authority of Georgia, and the City of Dalton, Georgia. It is located on the southwest side of the Savannah River approximately 23 river miles upstream from the intersection of the Savannah River and U.S.
Highway 301. The site is in the eastern sector of Burke County, Georgia, and across the river from Barnwell County, South Carolina. The VEGP site is directly across the Savannah River from the Department of Energy Savannah River Site.
Unit 1, a Westinghouse Electric Corporation Pressurized Water Reactor (PWR),
with a licensed core thermal power of 3565 MegaWatts (MWt), received its operating license on January 16, 1987 and commercial operation started on May 31, 1987. Unit 2, also a Westinghouse PWR rated for 3565 MWt, received its operating license on February 9, 1989 and began commercial operation on May 19, 1989.
The pre-operational stage of the REMP began with initial sample collections in August of 1981. The transition from the pre-operational to the operational stage of the REMP occurred as Unit 1 reached initial criticality on March 9, 1987.
A description of the REMP is provided in Section 2 of this report. Maps showing the sampling stations are keyed to a table which indicates the direction and distance of each station from a point midway between the two reactors. Section 3 provides a summary of the results of the analyses of REMP samples for the year.
The results are discussed, including an assessment of any radiological impacts upon the environment and the results of the land use census and the river survey, in Section 4. The results of the Interlaboratory Comparison Program (ICP) are provided in Section 5. Conclusions are provided in Section 6.
1-1

2.0 REMP DESCRIPTION A summary description of the REMP is provided in Table 2-1. This table summarizes the program as it meets the requirements outlined in ODCM Table 4-
: 1. It details the sample types to be collected and the analyses to be performed in order to monitor the airborne, direct radiation, waterborne and ingestion pathways, and also delineates the collection and analysis frequencies. In addition, Table 2-1 references the locations of stations as described in ODCM Section 4.2 and in Table 2-2 of this report. The stations are also depicted on maps in Figures 2-1 through 2-3.
REMP samples are collected by Georgia Power Company's (GPC) Environmental Laboratory (EL) personnel. The same lab performs all the laboratory analyses at their headquarters in Smyrna, Georgia.
2-1

TABLE 2-1 (SHEET 1 of 5)

==SUMMARY==
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway        Number of Representative          Sampling and Collection            Type and Frequency of and/or Sample           Samples and Sample                Frequency                          Analysis Locations
: 1. Direct Radiation      Thirty nine routine monitoring    Quarterly                          Gamma dose, quarterly stations with two or more dosimeters placed as follows:
An inner ring of stations, one in each compass sector in the general area of the site boundary; An outer ring of stations, one in each compass sector at approximately 5 miles from the site; and Special interest areas, such as population centers, nearby recreation areas, and control stations.
: 2. Airborne Radioiodine  Samples from seven locations:     Continuous sampler operation       Radioiodine canister: I-and Particulates                                           with sample collection weekly,     131 analysis, weekly.
Five locations close to the site  or more frequently if required by boundary in different sectors;    dust loading.                      Particulate sampler:
Gross beta analysis' A community having the                                               following filter change highest calculated annual                                            and gamma isotopic average ground level D/Q;                                            analysis2 of composite (by location), quarterly.
A control location near a population center at a distance of about 14 miles.

TABLE 2-1 (SHEET 2 of 5)

==SUMMARY==
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway     Number of Representative         Sampling and Collection           Type and Frequency of and/or Sample        Samples and Sample               Frequency                         Analysis Locations
: 3. Waterbome
: a. Surface 3
One sample upriver.              Composite sample over one       ...........................................
so..o.;...........................
Gamma 2isotopic   c month period4 .                    analysis2 , monthly.
Two samples downriver.                                              Composite for tritium analysis, quarterly.
: b. Drinking           Two samples at each of the       Composite sample of river water    1-131 analysis on each three nearest water treatment    near the intake of each water      sample when the dose plants that could be affected    treatment plant over two week      calculated for the by plant discharges.             period 4 when 1-131 analysis is    consumption of the required for each sample;          water is greater than 1 Two samples at a control         monthly composite otherwise;       mrem per year5.
location.                        and grab sample of finished        Composite for gross water at each water treatment      beta and gamma plant every two weeks or           isotopic analysis2 on monthly, as appropriate.           raw water, monthly.
Gross beta, gamma isotopic and 1-131 analyses on grab sample of finished water, monthly. Composite for tritium analysis on raw and finished water, quarterly.
: c. Groundwater        See Table 2-3 and Figure 2-4    Quarterly sample; pump used to    Tritium, gamma isotopic, for well locations.             sample GW wells; grab sample      and field parameters (pH, from yard drains and ponds        temperature, conductivity, dissolved oxygen, oxidation/reduction potential, and turbidity) of each sample quarterly; Hard to detect radionuclides as necessary based on results of tritium
                   &                                d and gamma m

TABLE 2-1 (SHEET 3 of 5)

==SUMMARY==
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway                          Number of Representative                       Sampling and Collection                                    Type and Frequency of and/or Sample                             Samples and Sample                             Frequency                                                  Analysis Locations
: d. Sediment from Shoreline                   One sample from downriver                     Semiannually                                               Gamma isotopic area with existing or potential                                                                          analysis2 , semiannually.
recreational value.
One sample from upriver area with existing or potential recreational value.
4....
I.n.g.s.i..
    ...t.i0....... .......
                     .I................
                                                                                                        . . . .n............................................
: a. Milk                                      Two samples from milking                    Biweekly                                                      Gamma isotopic animals6 at control locations                                                                             analysis2, biweekly.
at a distance of about 10 miles or more.
: b. Fish                                      At least one sample of any                     Semiannually                                               Gamma isotopic commercially or                                                                                           analysis on edible recreationally important                                                                                  portions, semiannually.
species near the plant discharge.
At least one sample of any commercially or recreationally important species in an area not influenced by plant discharges.
At least one sample of any                     During the spring spawning                                 Gamma isotopic anadromous species near the                    season.                                                    analysis2 on edible plant discharge.                                                                                          portions, annually.

TABLE 2-1 (SHEET 4 of 5)

==SUMMARY==
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway    Number of Representative         Sampling and Collection Type and Frequency of and/or Sample       Samples and Sample               Frequency               Analysis Locations
: c. Grass or Leafy    One sample from two onsite       Monthly during growing  Gamma isotopic Vegetation           locations near the site          season.                 analysis 2' , monthly.
boundary in different sectors.
One sample from a control location at a distance of about 17 miles.

TABLE 2-1 (SHEET 5 of 5)

==SUMMARY==
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Notes:
(1)    Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. -If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
(2)    Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
(3)    Upriver sample is taken at a distance beyond significant influence of the discharge. Downriver samples are taken beyond but near the mixing zone.
(4)    Composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) to assure obtaining a representative sample.
(5)    The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.
(6)    A milking animal is a cow or goat producing milk for human consumption.
(7)    If the gamma isotopic analysis is not sensitive enough to meet the Minimum Detectable Concentration (MDC) for 1-131, a separate analysis for 1-131 may be performed.

TABLE 2-2 (SHEET 1 of 3)
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Station   Station   Descriptive     Direction 1    Distance Sample Type Number     Type      Location                       (miles)1 1          Indicator River Bank      N              1.1      Direct Rad.
2          Indicator River Bank      NNE            0.8      Direct Rad.
3          Indicator Discharge Area  NE             0.6      Airborne Rad.
3          Indicator River Bank      NE             0.7      Direct Rad 4          Indicator River Bank      ENE            0.8      Direct Rad.
5          Indicator River Bank      E              1.0      Direct Rad.
6          Indicator Plant Wilson    ESE            1.1      Direct Rad.
7          Indicator Simulator       SE             1.7      Airborne Rad.
Building                                Direct Rad.
Vegetation 8          Indicator River Road      SSE            1.1      Direct Rad.
9          Indicator River Road      S              1.1      Direct Rad.
10         Indicator Met Tower       SSW            0.9      Airborne Rad.
10         Indicator River Road      SSW            1.1      Direct Rad.
11         Indicator River Road      SW             1.2      Direct Rad.
12         Indicator River Road      WSW            1.2      Airborne Rad.
Direct Rad.
13         Indicator River Road      W              1.3      Direct Rad.
14         Indicator River Road      WNW            1.8      Direct Rad.
15         Indicator Hancock         NW             1.5      Direct Rad.
Landing Road                            Vegetation 16         Indicator Hancock         NNW            1.4      Airborne Rad.
Landing Road                            Direct Rad.
17         Other     Sav. River Site N              5.4      Direct Rad.
(SRS), River Road 18         Other     SRS, D Area     NNE            5.0      Direct Rad.
19         Other     SRS, Road       NE             4.6      Direct Rad.
A.13 20         Other     SRS, Road       ENE            4.8      Direct Rad.
A. 13.1 21         Other     SRS, Road       E              5.3      Direct Rad.
A.17 22         Other     River Bank      ESE            5.2      Direct Rad.
23         Other     River Road      SE             4.6      Direct Rad.
24         Other     Chance Road     SSE            4.9      Direct Rad.
25         Other     Chance Road     S              5.2      Direct Rad.
near Highway 23 26         Other     Highway 23      SSW            4.6      Direct Rad.
and Ebenezer Church Road 27         Other     Highway 23      SW             4.7      Direct Rad.
opposite Boll Weevil Road 28         Other     Thomas Road     WSW            5.0      Direct Rad.
2-7

TABLE 2-2 (SHEET 2 of 3)
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Station   Station   Descriptive     Direction'      Distance Sample Type Number     Type      Location                        (miles)'
29         Other     Claxton-Lively  W               5.1      Direct Rad.
Road 30         Other     Nathaniel       WNW             5.0      Direct Rad.
Howard Road 31         Other     River Road at   NW              5.0      Direct Rad.
Allen's Chapel Fork 32         Other     River Bank      NNW             4.7      Direct Rad.
35         Other     Girard          SSE             6.6      Airborne Rad.
Direct Rad.
36         Control   GPC             WSW              13.9    Airborne Rad.
Waynesboro Op.                           Direct Rad.
HQ 37         Control   Substation      WSW              16.7    Direct Rad Waynesboro,                              Vegetation GA 43         Other     Employee's Rec. SW              2.2      Direct Rad.
Center 47         Control   Oak Grove       SE               10.4    Direct Rad.
Church                                   _
48         Control   McBean          NW               10.2    Direct Rad.
Cemetery 51         Control   SGA School      S                11.0    Direct Rad.
Sardis, GA 52         Control   Oglethorpe      SW               10.7    Direct Rad.
Substation; Alexander, GA 80         Control   Augusta Water   NNW             29.0     Drinking 2
Treatment Plant                          Water 81         Control   Sav River       N               2.5      Fish 3 Sediment 4 82         Control   Sav River (RM   NNE             0.8      River Water 151.2) 83         Indicator Sav River (RM   ENE             0.8      River Water 4
150.4)                                   Sediment 84         Other     Sav River (RM   ESE              1.6     River Water 149.5) 85         Indicator Sav River       ESE             4.3      Fish 3 87         Indicator Beaufort-Jasper SE              76       Drinking County Water                             Water 5 Treatment Plant 88         Indicator Cherokee Hill   SSE             72       Drinking Water Treatment                          Water 6 Plant, Port Wentworth, Ga 2-8

TABLE 2-2 (SHEET 3 of 3)
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS 89             Indicator    Purrysburg        SSE               76                Drinking Water Treatment                                       Water7 Plant; Purrysburg, SC 98             Control      W.C. Dixon        SE                9.8               Milk Dairy 100T           Control      Coble Dairy       WSW               23.8              Milk 101            Indicator    Girard Dairy      S                 5.5               Milk Notes:
(1)     Direction and distance are determined from a point midway between the two reactors.
(2)     The intake for the Augusta Water Treatment Plant is located on the Augusta Canal. The entrance to the canal is at River Mile (RM) 207 on the Savannah River. The canal effectively parallels the river. The intake to the pumping station is about 4 miles down the canal.
(3)     A 5 mile stretch of the river is generally needed to obtain adequate fish samples.
Samples are normally gathered between RM 153 and 158 for upriver collections and between RM 144 and 149.4 for downriver collections.
(4)     Sediment is collected at locations with existing or potential recreational value. Because high water, shifting of the river bottom, or other reasons could cause a suitable location for sediment collections to become unavailable or unsuitable, a stretch of the river between RM 148.5 and 150.5 was designated for downriver collections while a stretch between RM 153 and 154 was designated for upriver collections. In practice, collections are normally made at RM 150.2 for downriver collections and RM 153.3 for upriver collections.
(5)     The intake for the Beaufort-Jasper County Water Treatment Plant is located at the end of canal that begins at RM 39.3 on the Savannah River. This intake is about 16 miles by line of sight down the canal from its beginning on the Savannah River.
(6)     The intake for the Cherokee Hill Water Treatment Plant is located on Abercom Creek which is about one and a quarter creek miles from its mouth on the Savannah River at RM 29.
(7)     The intake for the Purrysburg Water Treatment Plant is located on the same canal as the Beaufort-Jasper Water Treatment Plant. The Purrysburg intake is nearer to the Savannah River at the beginning of the canal.
(8)     Milk sampling was discontinued at Coble Dairy in April 2008 when Girard Dairy was added. Girard Dairy was much closer to the plant (@ 5.5 miles) and would be considered an indicator station since a control station is usually 10 miles or greater.
2-9

Groundwater Monitoring Locations Table 2-3 WELL              AQUIFER                    MONITORING PURPOSE LT-1B          Water Table                NSCW related tank LT-7A          Water Table                NSCW related tank LT- 12         Water Table                NSCW related tank LT-13          Water Table                NSCW related tank 802A           Water Table                Southeastern potential leakage 803A           Water Table                Up gradient to rad waste building Down gradient from rad waste bldg and NSCW related facilities 806B           Water Table                Dilution line 808            Water Table                Up gradient; along Pen Branch Fault NSCW related tank; western potential Ri1            Water Tablelekg            leakage R2             Water Table                Southern potential leakage R3             Water Table                Eastern potential leakage
*R4            Water Table                Dilution line R5             Water Table                Dilution line R6             Water Table                Dilution line R7             Water Table                Dilution line Water Table within R8             Savy. River sediments      Dilution line 1013*         Water Table                Low level rad waste storage 1014          Tertiary                   Up gradient 1015          Water Table                Vertically up gradient 1003*         Tertiary                   Up gradient 1004*         Water Table                Vertically up gradient 27             Tertiary                   Down gradient tertiary 29             Tertiary                   Down gradient tertiary MU-I           Tertiary/Cretaceous        Facility water supply River          N/A                        Surface water NSCW - Nuclear service cooling water
* Wells abandoned in Feb. 2009 due to construction activities with proposed new units 2-10

N Radiological Environmental Sampling Locations          REMP Stations Indicator Control Additional TLD            A       A         A           in the Plant Vicinity Other          0       0
* TLD &Other                                         Figure 2-1 2-11

les Radiological Environmental Sampling Locations        REMP Control Stations Indicator Control Additional TLD                     ,         A               for the Plant Other          0        0
* TLD & Other                                         Figure 2-2 2-12

10 Miles
                                                 ,%Ii 88 4D Radiological Environmental Sampling Locations               REMP Indicator Drinking Indicator Control Additional TLD                 A       A         A,                 Water Stations Other              0        0
* TLD & Other                 -                               Figure 2-3 2-13

                                                                                    *,lk!Wk   850A
                                                                                                      ~-<"NEW               BARGE FACIU1YOPTION I
                                                                                                                 ~nttekl           NEW 011SCHARGIEINIE SST, DEBRIS BASIN DAM DU,
                                                                                          '1 29M~
ace Dcuvi)NA%
179 pl 00                0-1051A00 OW-1005        BI 27L "4
OW-1001IA
                      -002 J
OW- 1007
          'I' R
1-2
                                                                              =
0 OW-1009 1"iS S 04 0
OW-1010                                                                                                            552 500W EXw~nma                 -- inI &#xa3;,-Ia*
0-      plant-5
                                                         -..-          .0-1014-LEGEOLIO OW- 101         2'W-1012 2A,      Lower Terio     coquifer Monif-,rig  Well woter Tobte Monitoring Well WoC5A mIJ-2 0       Weter Supply Well in Lower Tertiory      -nd Cretoceous oquifer.
C)      Other WeIIS not   Potl  of Tritimt  *tjdy FIGURE 2-4                Groundwater Monitoring Wells 2-14

3.0 RESULTS 

==SUMMARY==

In accordance with ODCM 7.1.2.1, the summarized and tabulated results for all of the regular samples collected for the year at the designated indicator and control stations are presented in Table 3-1. The format of Table 3-1 is similar to Table 3 of the Nuclear Regulatory Commission (NRC) Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program", Revision 1, November 1979. Results for samples collected at locations other than indicator or control stations are discussed in Section 4 under the particular sample type.
As indicated in ODCM 7.1.2.1, the results for naturally occurring radionuclides that are also found in plant effluents must be reported along with man-made radionuclides. The radionuclide Be-7, which occurs abundantly in nature, is often detected in REMP samples. It is occasionally detected in the plant's liquid and gaseous effluents. When it is detected in effluents, it is also included in the REMP results. In 2008, Be-7 was not detected in Vogtle's liquid or gaseous effluents.
3-1

TABLE 3-1 (SHEET 1 of 8)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Medium or    Type and   Minimum           Indicator            Location with the Highest       Other        Control Pathway      Total      Detectable        Locations                   Annual Mean              Stations (g) Locations Sampled      Number of  Concentration     Mean (b),                                            Mean (b),    Mean (b),
(Unit of     Analyses   (MDC) (a)         Range          Name Distance         Mean (b),       Range        Range Measurement) Performed                     (Fraction)    & Direction          Range (Fraction) (Fraction)   (Fraction)
Airborne     Gross Beta 10                24.0           Station 3             25.3            23.7         23.2 Particulates 364                          6.5-48.0       Discharge Area        14.5-44.5       12.0-40.4    9.3-42.7 (fCi/m3)                                  (260/260)      0.6 miles NE          (52/52)         (52/52)      (52/52)
Gamma Isotopic 28 Cs- 134    50                NDM (c)                              NDM             NDM          NDM Cs-137     60                NDM                                  NDM             NDM          NDM Airborne     1-131      70                NDM                                  NDM             NDM          NDM Radioiodine  364 (fCi/m3)
Direct       Gamma      NA (d)             13.3          Station 20            17.0            13.1         13.0 Radiation    Dose                         9.9-18.7       SRS Road              15.7-18.9       9.1-19.0     10.6-17.2 (mR/91 days) 157                          (62/62)       A.13.1                 (3/3)           (71/71)      (24/24) 4.8 miles ENE

TABLE 3-1 (SHEET 2 of 8)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Medium or    Type and   Minimum            Indicator            Location with the Highest       Other        Control Pathway      Total      Detectable        Locations                    Annual Mean              Stations (g) Locations Sampled      Number of  Concentration      Mean (b),                                            Mean (b),    Mean (b),
(Unit of     Analyses   (MDC) (a)          Range         Name Distance         Mean (b),                     Range Measurement) Performed                     (Fraction)     & Direction          Range (Fraction) Range        (Fraction)
(Fraction)
Milk (pCi/1)  Gamma Isotopic 54 Cs- 134    15                NA                                   NDM             NA           NDM Cs-137     18                NA                                   NDM             NA           NDM Ba-140    60                 NA                                   NDM             NA           NDM La- 140    15                NA                                   NDM             NA           NDM I-131      1                 NA                                   NDM             NA           NDM 53 Vegetation   Gamma (pCi/kg-wet) Isotopic 36 1-131      60                 NDM                                  NDM             NA           NDM Cs-134     60                 NDM                                  NDM             NA           NDM Cs-137    80                  24.6           Station 37            62.2            NA           62.2 20.6-29.2      Waynesboro            41.9-82.3                    41.9-82.3 (3/24)         Substation            (2/12)                       (2/12) 16.7 miles WSW

TABLE 3-1 (SHEET 3 of 8)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Medium or    Type and     Minimum              Indicator           Location with the Highest        Other        Control Pathway      Total Number Detectable           Locations                  Annual Mean               Stations (g) Locations Sampled      of Analyses  Concentration        Mean (b),                                            Mean (b),    Mean (b),
(Unit of     Performed    (MDC) (a)            Range        Name Distance           Mean (b),       Man          Range Measurement)                                   (Fraction) & Direction              Range (Fraction) Range        (Fraction)
(Fraction)
River Water  Gamma (pCi/1)      Isotopic 36 Be-7          124(e)              NDM                                  NDM             NDM          NDM Mn-54         15                  NDM                                  NDM             NDM          NDM Fe-59        30                   NDM                                  NDM             NDM          NDM Co-58         15                  NDM                                  NDM             NDM          NDM Co-60         15                  NDM                                  NDM             NDM          NDM Zn-65        30                   NDM                                  NDM             NDM          NDM Zr-95        30                   NDM                                  NDM             NDM          NDM Nb-95         15                  NDM                                  NDM             NDM          NDM 1-131         15                  NDM                                  NDM             NDM          NDM Cs- 134       15                  NDM                                  NDM             NDM          NDM Cs-137        18                  NDM                                  NDM             NDM          NDM Ba-140       60                   NDM                                  NDM             NDM          NDM La- 140       15                  NDM                                  NDM             NDM          NDM Tritium      2000                 1873          Station 83             1873            1105         832 12                               289-3870      RM 150.4               289-3870        630-2030     664-1000 (4/4)         0.8 miles ENE          (3/4)           (4/4)        (2/4)

TABLE 3-1 (SHEET 4 of 8)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Medium or      Type and Total Minimum                 Indicator             Location with the Highest        Other          Control Pathway        Number of       Detectable             Locations                   Annual Mean                Stations (g)   Locations Sampled        Analyses        Concentration          Mean (b),                                              Mean (h),      Mean (b),
(Unit of       Performed       (MDC) (a)              Range            Name Distance Mean (b),               Man            Range Measurement)                                          (Fraction)       & Direction        Range (Fraction)   Range (Fraction)     (Fraction)
Water Near     Gross Beta       4                     3.46             Station 87                5.32        NA             2.37 Intakes to     48                                     1.17-11.4        Beaufort-Jasper WTP       3.58-11.4                  1.01-3.61 Water                                                 (36/36)          76 miles SE               (12/12)                    (12/12)
Treatment Plants (pCi/1)
Gamma Isotopic 48 tJ, Be-7             124(e)                NDM                                        NDM         NA             NDM Mn-54            15                    NDM                                        NDM         NA             NDM Fe-59            30                    NDM                                        NDM         NA             NDM Co-58            15                    NDM                                        NDM         NA             NDM Co-60            15                    NDM                                        NDM         NA             NDM Zn-65            30                    NDM                                        NDM         NA             NDM Zr-95            30                    NDM                                        NDM         NA             NDM Nb-95            15                    NDM                                        NDM         NA             NDM 1-131(f)         15                    NDM                                        NDM         NA             NDM Cs-134           15                    NDM                                        NDM         NA             NDM Cs-137           18                    NDM                                        NDM         NA             NDM B a- 140         60                    NDM                                        NDM         NA             NDM La- 140          15                    NDM                                        NDM         NA             NDM Tritium          2000                  726              Station 89                855         NA             386 16                                     303-1370         Purrysburg WTP            387-1370                   367-404 (12/12)          76 miles SSE              (4/4)                      (2/4) i                      I                                          I           I              I

TABLE 3-1 (SHEET 5 of 8)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Medium or      Type and   Minimum             Indicator           Location with the Highest        Other          Control Pathway        Total      Detectable          Locations                 Annual Mean                Stations (g)   Locations Sampled        Number of  Concentration       Mean (b),                                            Mean (b),      Mean (b),
(Unit of       Analyses   (MDC) (a)           Range          Name Distance      Mean (b),                         Range Measurement)   Performed                      (Fraction)     & Direction       Range (Fraction)    Range          (Fraction)
(Fraction)
Finished Water Gross Beta 4                   2.86           Station 88                3.07        NA             2.07 at Water       48                             1.25-4.37      Cherokee Hill WTP         2.26-4.30                  1.05-3.50 Treatment                                     (35/36)        Port Wentworth            (11/12)                    (12/12)
Plants (pCi/1)                                               72 miles SSE 4             .~                        1-                          t Gamma Isotopic 48 Be-7       124(e)              NDM                                      NDM         NA             NDM Mn-54      15                  NDM                                      NDM         NA             NDM Fe-59      30                  NDM                                      NDM         NA             NDM Co-58      15                  NDM                                      NDM         NA             NDM Co-60      15                  NDM                                      NDM         NA             NDM Zn-65      30                  NDM                                      NDM         NA             NDM Zr-95      30                  NDM                                      NDM         NA             NDM Nb-95      15                  NDM                                      NDM         NA             NDM 1-131      1                   NDM                                      NDM         NA             NDM Cs- 134    15                  NDM                                      NDM         NA             NDM Cs-137     18                  NDM                                      NDM         NA             NDM Ba- 140    60                  NDM                                      NDM         NA             NDM La- 140    15                  NDM                                      NDM         NA             NDM Tritium    2000                661            Station 89                669         NA             391 16                             332-992        Purrysburg WTP            534-824                    286-495 (12/12)        Purrysburg, SC            (4/4)                      (2/4) 76 miles SSE i                                                    i              i

TABLE 3-1 (SHEET 6 of 8)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Medium or    Type and   Minimum             Indicator          Location with the Highest        Other        Control Pathway      Total      Detectable          Locations                 Annual Mean               Stations (g) Locations Sampled      Number of  Concentration       Mean (b),                                           Mean (b),    Mean (b),
(Unit of     Analyses   (MDC) (a)           Range         Name Distance        Mean (b),                     Range Measurement) Performed                      (Fraction)    & Direction          Range (Fraction) Range        (Fraction)
(Fraction)
Anadromous   Gamma Fish         Isotopic (pCi/kg-wet)  1 Be-7       655(e)              NDM                               NDM               NA           NA Mn-54      130                 NDM                               NDM               NA           NA Fe-59      260                 NDM                               NDM               NA           NA Co-58      130                 NDM                               NDM               NA           NA Co-60      130                 NDM                               NDM               NA           NA Zn-65      260                 NDM                               NDM               NA           NA Cs- 134    130                 NDM                               NDM               NA           NA Cs-137     150                 NDM                               NDM               NA           NA Fish        Gamma (pCi/kg-wet) Isotopic 6
Be-7       655(e)              NDM                               NDM               NA           NDM Mn-54      130                 NDM                               NDM               NA           NDM Fe-59      260                 NDM                               NDM               NA           NDM Co-58      130                 NDM                               NDM               NA           NDM Co-60      130                 NDM                               NDM               NA           NDM Zn-65      260                 NDM                               NDM               NA           NDM Cs- 134    130                 NDM                               NDM               NA           NDM Cs-137     150                 39.4          Station 81          47.0              NA           47.0 16.4-64.2     2.5 miles N         19.9-90.2                      19.9-90.2 (3/3)         (upstream)          (3/3)                          (3/3)

TABLE 3-1 (SHEET 7 of 8)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Medium or      Type and                   Minimum                            Indicator                  Location with the Highest                    Other                        Control Pathway        Total Number               Detectable                         Locations                        Annual Mean                            Stations (g)                 Locations Sampled        of Analyses                 Concentration                     Mean (b),                                                               Mean (b),                    Mean (b),
(Unit of       Performed                  (MDC) (a)                          Range             Name Distance Mean (b),                                                            Range Measurement)                                                                 (Fraction) & Direction                     Range (Fraction)             Range                        (Fraction)
(Fraction)
Sediment       Gamma (pCi/kg-dry)   Isotopic 4.
Be-7                       655(e)                             394               Station 81               1274                         NA                           805 (1/2)             2.5 miles N              (1/2)                                                     (1/2) t...               .....
                                                                                                                                                                                                      ..t......................
Co-60                      70(e)                              61.9              Station 83               61.9                         NA                           NDM
.,oc Or*                                                                               (1/2)             0.8 miles ENE            (1/2)
(downstream) s-134                    150                              NDM                                         NDM                          NA                           NDM Cs- 137                     180                              66.2               Station 83               66.2                         NA                           60.9 48.5-83.9          0.8 miles ENE            48.5-83.9                                                 33.4-88.4 (2/2)             (downstream)             (2/2)                                                     (2/2)

TABLE 3-1 (SHEET 8 of 8)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL 

==SUMMARY==

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Notes:
: a. The MDC is defined in ODCM 10.1. Except as noted otherwise, the values listed in this column are the detection capabilities required by ODCM Table 4-3. The values listed in this column are a priori (before the fact) MDCs. In practice, the a posteriori (after the fact) MDCs are generally lower than the values listed. Any a posteriori MDC greater than the value listed in this column is discussed in Section 4.
: b. Mean and range are based upon detectable measurements only. The fraction of all measurements at a specified location that are detectable is placed in parenthesis.
: c. No Detectable Measurement(s).
: d. Not Applicable.
: e. The EL has determined that this value may be routinely attained under normal conditions. No value is provided in ODCM Table 4-3.
: f. Item 3 of ODCM Table 4-1 implies that an 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.
: g. "Other" stations, as identified in the "Station Type" column of Table 2-2, are "Community" and/or "Special" stations.
1&#xfd;

4.0        DISCUSSION OF RESULTS Included in this section are evaluations of the laboratory results for the various sample types. Comparisons were made between the difference in mean values for pairs of station groups (e.g., indicator and control stations) and the calculated Minimum Detectable Difference (MDD) between these pairs at the 99%
Confidence Level (CL). The MDD was determined using the standard Student's t-test. A difference in the mean values that was less than the MDD was considered to be statistically indiscernible.
The 2008 results were compared with past results, including those obtained during preoperation.      As appropriate, results were compared with their Minimum Detectable Concentrations (MDC) and Reporting Levels (RL) which are listed in Tables 4-1 and 4-2 of this report, respectively. The required MDCs were achieved during laboratory sample analysis. Any anomalous results are explained within this report.
Results of interest are graphed to show historical trends. The data points are tabulated and included in this report. The points plotted and provided in the tables represent mean values of only detectable results. Periods for which no detectable measurements (NDM) were observed or periods for which values were not applicable (e.g., milk indicator, etc.) are listed as NDM and are plotted in the tables as 0's.
Table 4-1 Minimum Detectable Concentrations (MDC)
Analysis          Water         Airborne        Fish           Milk     Grass or       Sediment (pCi/I)     Particulate     (pCi/kg-        (pCi/I)     Leafy        (pCi/kg) or Gases        wet)                   Vegetation (fCi/m3)                                (pCi/kg-wet)
Gross Beta            4              10 H-3           2000 (a)
Mn-54              15                           130 Fe-59              30                          260 Co-58              15                           130 Co-60              15                           130 Zn-65              30                          260 Zr-95              30 Nb-95              15 1-131              1 (b)         70                             1         60 Cs-134             15             50            130             15         60            150 Cs-137             18             60            150             18         80            180 Ba-140              60                                          60 La-140             15                                           15 (a) If no drinking water pathway exists, a value of 3000 pCi/1 may be used.
(b) If no drinking water pathway exists, a value of 15 pCi/l may be used.
4-1

Table 4-2 Reporting Levels (RL)
Analysis          Water         Airborne            Fish       Milk (pCi/1)    Grass or (pCi/l)      Particulate      (pCi/kg-wet)                     Leafy or Gases                                     Vegetation (fCi/m3)                                    (pCi/kg-wet)
H-3            20,000 (a)
Mn-54             1000                            30,000 Fe-59              400                            10,000 Co-58             1000                            30,000 Co-60              300                            10,000 Zn-65              300                            20,000 Zr-95              400 Nb-95              700 1-131                2 (b)         900                              3             100 Cs-134               30           10,000            1000            60            1000 Cs-137               50           20,000            2000            70           2000 Ba-140              200                                            300 La- 140             100                                            400 (a) This is the 40 CFR 141 value for drinking water samples. If no drinking water pathway exists, a value of 30,000 may be used.
(b) If no drinking water pathway exists, a value of 20 pCi/1 may be used.
Atmospheric nuclear weapons tests from the mid 1940s through 1980 distributed man-made nuclides around the world. The most recent atmospheric tests in the 1970s and in 1980 had a significant impact upon the radiological concentrations found in the environment prior to and during preoperation, and the earlier years of operation. Some long lived radionuclides, such as Cs-137, continue to have some impact. A significant component of the Cs-137 which has often been found in various samples over the years (and continues to be found) is attributed to the nuclear weapons tests.
Data in this section has been modified to remove any obvious non-plant short term impacts. The specific short term impact data that has been removed includes: the nuclear atmospheric weapon test in the fall of 1980; abnormal releases from the Savannah River Site (SRS) during 1987 and 1991; and the Chernobyl incident in the spring of 1986.
In accordance with ODCM 4.1.1.2.1, deviations from the required sampling schedule are permitted, if samples are unobtainable due to hazardous conditions, unavailability, inclement weather, equipment malfunction or other just reasons.
Deviations from conducting the REMP as described in Table 2-1 are summarized in Table 4-3 along with their causes and resolutions.
4-2

All results were tested for conformance with Chauvenet's criterion (G. D. Chase and J. L. Rabinowitz, Principles of Radioisotope Methodology, Burgess Publishing Company, 1962, pages 87-90) to identify values which differed from the mean of a set by a statistically significant amount. Identified outliers were investigated to determine the reason(s) for the difference.         If equipment malfunction or other valid physical reasons were identified as causing the variation, the anomalous result was excluded from the data set as non-representative. No data were excluded exclusively for failing Chauvenet's criterion. Data exclusions are discussed in this section under the appropriate sample type.
4-3

TABLE 4-3 DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM COLLECTION        AFFECTED                DEVIATION                   CAUSE                         RESOLUTION PERIOD            SAMPLES 01/30/08-02/12/08 Coble Dairy             No milk sample available    Dairy operator not able to    Sample available at next CR2009101392                                                          provide sample                collection period 1st Quarter       River Bank TLD 23B      TLD rendered suspect by     Moisture / rain water entered Replaced TLDs at beginning of CR2008113434      SE @ 4.6 miles          presence of water in bag    holding bag                   quarter April 2008        Girard Dairy replaced   None                        NA                            New dairy at Girard much closer CR2008113435      Coble Dairy                                                                       to VEGP than Coble Dairy 2 dQuarter        River Road TLDs 10      TLDs missing at collection  TLDs destroyed during         TLDs replaced at beginning of CR2009100123      and 12 @ 1.1 mile       time                        transmission line relocation  quarter SSW and 1.2 miles WSW, respectively 09/03/08          Station 83              Non-representative river    Weak battery on autosampler;  Replaced battery on autosampler CR2009103649      River Water             water sample                had to pull a grab sample to RM 150.4                                            complete monthly gamma composite sample 10/22/08-11/04/08 Girard Dairy            Milk sample had high fat    Alternate sampling method     Gamma analysis resulted in 2.7 CR2008113436                              content and would not pass  had to be utilized; normal    pCi/L MDC through resin column used   milk sample not available for low level iodine analysis; could not meet 1 I pCi/L MDC

4.1   Land Use Census and River Survey In accordance with ODCM 4.1.2, a land use census was conducted on November 11, 2008 to determine the locations of the nearest permanent residence, milk animal, and garden of greater than 500 square feet producing broad leaf vegetation, in each of the 16 compass sectors within a distance of 5 miles; the locations of the nearest beef cattle in each sector were also determined. A milk animal is a cow or goat producing milk for human consumption. Land within SRS was excluded from the census. The census results are tabulated in Table 4.1-1.
Table 4.1-1 LAND USE CENSUS RESULTS Distance in Miles to the Nearest Location in Each Sector SECTOR          RESIDENCE              MILK              BEEF          GARDEN ANIMAL            CATTLE N                 1.4                None             None            None NNE                None                None             None            None NE                None                None             None            None ENE                None                None             None            None E                None                None             None            None ESE                 4.2                None             None            None SE                 4.4                None              5.0             4.5 SSE                4.6                None              4.7            None S                 4.4                None             None            None SSW                 4.7                None              4.5            None SW                 2.7                None              4.9            None WSW                  2.6                None              2.7            None W                 3.4                None              4.5            None WNW                  1.9                None             None            None NW                 1.6                None              1.6            None NNW                  1.5                None             None            None ODCM 4.1.2.2.1 requires a new controlling receptor to be identified, if the land use census identifies a location that yields a calculated receptor dose greater than the one in current use. In 2008, the controlling receptor was moved to a more conservative location at 1.2 miles WSW. This property was acquired by Georgia Power in 2008. The residents were relocated but this property will potentially be used for contract labor in the near future.
ODCM 4.1.2.2.2 requires that whenever the land use census identifies a location which yields a calculated dose (via the same ingestion pathway) 20% greater than 4-5

that of a current indicator station, the new location must become a REMP station (if samples are available). None of the identified locations yielded a calculated dose 20% greater than that for any of the current indicator stations. No milk animals were identified within five miles of the plant. A new dairy was started at Girard in 2008 and was added to the REMP.                Since control stations are approximately 10 miles are greater, this dairy is considered an indicator station.
A survey of the Savannah River downstream of the plant for approximately 100 miles was conducted on September 30, 2008 to identify any withdrawal of water from the river for drinking or irrigation purposes. No such usage was identified.
These results were corroborated by checking with the Georgia Department of Natural Resources on October 2, 2008 and the South Carolina Department of Health and Environmental Control on October 2, 2008. Each of these agencies confirmed that no water withdrawal permits for drinking or irrigation purposes had been issued for this stretch of the Savannah River. The three water treatment plants used as indicator stations for drinking water are located farther downriver.
4-6

4.2 Airborne As specified in Table 2-1 and shown in Figures 2-1 through 2-3, airborne particulate filters and charcoal canisters are collected weekly at 5 indicator stations (Stations 3, 7, 10, 12 and 16) which encircle the plant at the site periphery, at a nearby community station (Station 35) approximately 7 miles from the plant, and at a control station (Station 36) which is approximately 14 miles from the plant. At each location, air is continuously drawn through a glass fiber filter to retain airborne particulate and an activated charcoal canister is placed in series with the filter to adsorb radioiodine.
Each particulate filter is counted for gross beta activity. A quarterly gamma isotopic analysis is performed on a composite of the air particulate filters for each station. Each charcoal canister is analyzed for 1-131.
As provided in Table 3-1, the 2008 annual average weekly gross beta activity was 24.0 fCi/m 3 for the indicator stations. It was 0.8 fCi/m 3 greater than the control station average of 23.2 fCi/m 3 for the year. This difference is not statistically discernible, since it is less than the calculated MDD of 2.24 fCi/m3 .
The 2008 annual average weekly  3        gross beta 3 activity at the Girard community 3
station was 23.7 fCi/m which was 0.5 fCi/m less than the control station average.
This difference is not statistically discernible since it is less than the calculated MDD of 2.83 fCi/m3 .
The historical trending of the average weekly gross beta air concentrations for each year of operation and the preoperational period (September, 1981 to January, 1987) at the indicator, control and community stations is plotted in Figure 4.2-1 and listed in Table 4.2-1. In general, there is close agreement between the results for the indicator, control and community stations. This close agreement supports the position that the plant is not contributing significantly to the gross beta concentrations in air.
4-7

Figure 4.2-1 Average Weekly Gross Beta Air Concentration 30 25
             .2            15        -     -
Po 87 88 89   90    91   92   93    94  95  96  97   98 99  00 01 02  03 04 05 06 07 08 Year
                    -- 0-- Indicator ---- Control     - Community    MDC 4-8

Table 4.2-1 Average Weekly Gross Beta Air Concentration Period      Indicator (fCi/m3)     Control      Community (fCi/m3)      (fCi/m3)
Pre-op             22.9              22.1          21.9 1987              26.3              23.6          22.3 1988              24.7              23.7          22.8 1989               19.1             18.2          18.8 1990               19.6             19.4          18.8 1991               19.3             19.2          18.6 1992               18.7             19.3          18.0 1993              21.2              21.4          20.3 1994              20.1              20.3           19.8 1995              21.1              20.7          20.7 1996              23.3              21.0          20.0 1997              20.6              20.6           19.0 1998              22.7              22.4          20.9 1999              22.5              21.9          22.2 2000              24.5              21.5          21.1 2001              22.4              22.0          22.7 2002               19.9             18.9           18.6 2003               19.4             20.5           18.3 2004              21.6              22.8          21.4 2005              20.5              20.4           19.4 2006              25.5              24.6          24.3 2007              27.3              25.1          26.5 2008            '.24.0              23.2          23.7 4-9

During 2008, no man-made radionuclides were detected from the gamma isotopic analysis of the quarterly composites of the air particulate filters. In 1987, Cs-137 was found in one indicator composite at a concentration of 1.7 fCi/m3 . During pre-operation, Cs-137 was found in approximately 12% of the indicator composites and 14% of the control composites with average concentrations of 1.7 and 1.0 fCi/m 3 , respectively. The MDC for airborne Cs-137 is 60 fCi/m3 . Also, during pre-operation, Cs-134 was found in about 8% of the indicator composites at an average concentration of 1.2 fCi/m3. The MDC for Cs-134 is 50 fCi/m3.
The naturally occurring radionuclide Be-7 is typically detected in all indicator and control station gamma isotopic analyses of the quarterly composites of the air particulate filters. In 2008, Be-7 was not identified in plant gaseous effluents therefore it is not included in the 2008 REMP summary table for the airborne pathway samples. Be-7 has been detected in gaseous effluents in only eight of the years of plant operation. However, there was not a statistically discernible difference between the indicator and control station Be-7 concentrations in air samples in any of the years.
Airborne 1-131 was not detected in any sample during 2008. During pre-operation, positive results were obtained only during the Chernobyl incident when concentrations as high as 182 fCi/m 3 were observed. The MDC and RL for airborne 1-131 are 70 and 900 fCi/m3 , respectively.
Table 4-3 lists REMP deviations that occurred in 2008.            There were no air monitoring deviations in 2008.
4-10

4.3 Direct Radiation Direct (external) radiation is measured with thermoluminescent dosimeters (TLDs). Two Panasonic UD-814 TLD badges are placed at each station. Each badge contains three phosphors composed of calcium sulfate crystals (with thulium impurity). The gamma dose at each station is based upon the average readings of the phosphors from the two badges. The badges for each station are placed in thin plastic bags for protection from moisture while in the field. The badges are nominally exposed for periods of a quarter of a year (91 days). An inspection is performed near mid-quarter to assure that all badges are on-station and to replace any missing or damaged badges.
Two TLD stations are established in each of the 16 compass sectors, to form 2 concentric rings. The inner ring (Stations 1 through 16) is located near the plant perimeter as shown in Figure 2-1 and the outer ring (Stations 17 through 32) is located at a distance of approximately 5 miles from the plant as shown in Figure 2-2. The 16 stations forming the inner ring are designated as the indicator stations. The two ring configuration of stations was established in accordance with NRC Branch Technical Position "An Acceptable Radiological Environmental Monitoring Program", Revision 1, November 1979. The 6 control stations (Stations 36, 37, 47, 48, 51 and 52) are located at distances greater than 10 miles from the plant as shown in Figure 2-2. Monitored special interest areas consist of the following: Station 35 at the town of Girard, and Station 43 at the employee recreational area. The TLD mean and range values presented in the "Other" column in Table 3-1 (page 1 of 8) includes the outer ring stations (stations 17 through 32) as well as stations 35 and 43.
As provided in Table 3-1 the average quarterly exposure measured at the indicator stations was 13.3 mR with a range of 9.9 to 18.7 mR. This average was 0.3 mR greater than the average quarterly exposure measured at the control stations (13.0 mR). This difference is not statistically discernible since it is less than the MDD of 1.15 mR. Over the operational history of the site, the annual average quarterly exposures shows a variation of no more than 0.7 mR difference between the indicator and control stations. The overall average quarterly exposure for the control stations during preoperation was 1.2 mR greater than that for the indicator stations.
The quarterly exposures acquired at the outer ring stations during 2008 ranged from 9.1 to 19.0 mR with an average of 13.1 mR which was 0.1 mR greater than that for the control stations. However, this difference is not discernible since it is less than the MDD of 1.3 mR. For the entire period of operation, the annual average quarterly exposures at the outer ring stations vary by no more than 1.2 mR from those at the control stations. The overall average quarterly exposure for the outer ring stations during preoperation was 1.8 mR less than that for the control stations.
The historical trending of the average quarterly exposures for the indicator inner ring, outer ring, and the control stations are plotted in Figure 4.3-1 and listed in Table 4.3-1. The decrease between 1991 and 1992 values is attributed to a change in TLDs from Teledyne to Panasonic. It should be noted however that the differences between indicator and control and outer ring values did not change.
The close agreement between the station groups supports the position that the plant is not contributing significantly to direct radiation in the environment.
4-11

Figure 4.3-1 Average Quarterly Exposure from Direct Radiation 20 18 16 S8 6
Po 87 88 89 90 91   92   93  94  95    96 97 98 99   00 01  02 03 04 05 06 07 08 Year I -- *-Indicator    -U-Control   -*--OuterRing I 4-12

Table 4.3-1 Average Quarterly Exposure from Direct Radiation Period          Indicator          Control       Outer Ring (mR)              (mR)             (mR)
Pre-op             15.3              16.5             14.7 1987              17.6              17.9             16.7 1988              16.8              16.1             16.0 1989              17.9              18.4             17.2 1990              16.9              16.6             16.3 1991              16.9              17.1             16.7 1992              12.3              12.5             12.1 1993              12.4              12.4             12.1 1994              12.3              12.1             11.9 1995              12.0              12.5             12.3 1996              12.3              12.2             12.3 1997              13.0              13.0             13.1 1998              12.3              12.7             12.4 1999              13.6              13.5             13.4 2000              13.5              13.6             13.5 2001              12.9              13.0             12.9 2002              12.8              12.9             12.6 2003              12.2              12.5             12.4 2004              12.4              12.2             12.3 2005              12.5              13.2             12.9 2006              13.1              12.9             13.0 2007              13.0              12.5             12.7 2008              13.3              13.0             13.1 4-13

The historical trending of the average quarterly exposures at the special interest areas for the same periods are provided in Figure 4.3-2 and listed in Table 4.3-2.
These exposures are within the range of those acquired at the other stations. They too, show that the plant is not contributing significantly to direct radiation at the special interest areas.
Figure 4.3-2 Average Quarterly Exposure from Direct Radiation at Special Interest Areas 25 20 0
 ~10    -    -     -       -    --                     -     -     -    -        -
Po   87   88    89 90   91    92  93   94    95     96 97   98  99   00  01   02   03  04 05 06 07 08 Year
                  -- " Hunting Cabin (Sta 33)    Girard (Sta 35)    - Rec Center (Sta 4 4-14

Table 4.3-2 Average Quarterly Exposure from Direct Radiation at Special Interest Areas Period               Station 33           Station 35         Station 43 (mR)                  (mR)              (mR)
Pre-op                 16.6                  15.1              15.3 1987                  21.3                  18.5              15.2 1988                  19.7                  18.1              14.8 1989                  21.2                  18.7              17.4 1990                  16.8                  18.9              16.2 1991                  17.3                  19.6              17.0 1992                  12.8                  13.5              12.0 1993                  12.9                  13.3              12.1 1994                  12.6                  13.6              12.0 1995                  13.3                  13.5              12.3 1996                  13.0                  13.6              12.1 1997                  13.8                  14.4              12.7 1998                  13.5                  13.7              12.5 1999                  NA                    14.5              12.7 2000                  NA                    14.8              13.1 2001                  NA                    14.0               12.6 2002                  NA                    14.0              12.1 2003                  NA                    14.1               12.2 2004                  NA                    14.2               11.7 2005                  NA                    15.2               12.7 2006                  NA                    14.3               12.6 2007                  NA                    13.6               11.8 2008                  NA                    14.4              12.6J4 The hunting cabin activities at Station 33 have been discontinued and, consequently, this location is no longer considered as an area of special interest.
Monitoring at this location was discontinued at the end of 1998.
There were three deviations from the REMP pertaining to measuring quarterly gamma doses during 2008. In first quarter, moisture was found in the TLD holding bag at River Road location 23B. The result from this deviation passed Chauvenet's Criterion and was included in the data set. In the second quarter, River Road locations 10 and 12 were destroyed during transmission line relocation. These TLDs were missing at the end of the quarter therefore no data was available from these two stations for the second quarter.
The standard deviation for the quarterly result for each badge was subjected to a self imposed limit of 1.4. This limit is based upon the standard deviations obtained with the Panasonic UD-814 badges during 1992 and is calculated using a method developed by the American Society of Testing and Materials (ASTM Special Technical Publication 15D, ASTM Manual on Presentation of Data and Control Chart Analysis, Fourth Revision, Philadelphia, PA, October 1976). The limit serves as a flag to initiate an investigation. To be conservative, readings with a standard deviation greater than 1.4 are excluded since the high standard deviation is interpreted as an indication of unacceptable variation in TLD response.
4-15

The readings for the following badges were deemed unacceptable since the standard deviation for each badge was greater than the self-imposed limit of 1.4:
First Quarter:      VIOB, V24B, V52B Second Quarter:     None Third Quarter:      V20A, V20B, V32A Fourth Quarter:     None However, for the cases when only one badge exceeded a standard deviation of 1.4, the companion badges were available and were used for determining the quarterly doses. The badges exceeding the self-imposed limit were visually inspected under a microscope and the glow curve and test results for the anneal data and the element correction factors were reviewed. No reason was evident for the high standard deviation.
4-16

4.4        Milk In accordance with Tables 2-1 and 2-2, milk samples are collected biweekly from two locations, the W. C. Dixon Dairy (Station 98) and the Coble Dairy (Station 100). Both are control locations. A new dairy was added to the REMP in April 2008. Since it was much closer to the plant, Coble Dairy was dropped as a sampling location. Since control stations are approximately 10 miles or more, the Girard Station was considered an indicator station. As discussed in Section 4.1, no milk animal was found during the 2008 land use census. There was one collection period in 2008 where milk samples were not available from Coble Dairy (01/30/08-02/12/08). In November 2008, one of the Girard samples had an extremely high fat content and would not pass through the resin used in the low level iodine analysis. The required MDC of 1 pCi/L for 1-131 could not be met.
However, an MDC of 2.7 pCi/L was met by gamma spectroscopy of the liquid sample which is less than the Reporting Level of 3 pCi/L for 1-131.
Gamma isotopic and 1-131 analyses are performed on each milk sample. No man-made radionuclides were identified by gamma isotopic analysis in 2008. The MDC and RL for Cs-137 in milk are 18 and 70 pCi/l, respectively. During preoperation and each year of operation through 1991, Cs-137 was found in 2 to 6% of the samples at concentrations ranging from 5 to 27 pCi/l. During preoperation, Cs-134 was detected in one sample and in the first year of operation, Zn-65 was detected in one sample. Figure 4.4-1 and Table 4.4-1 provide the historical trending of the Cs- 137 concentration in milk.
Figure 4.4-1 Average Annual Cs-1 37 Concentration in Milk 20 18 16 14 2
0 F.
C 0 6 0
4 2
a                                         95    96  97 98 99 93   94 DoF 87   88  89  90  91   92                              00   01 02 03 04 05  06 07   08 Year 1*   Indicator    -U-Control       MVDCI 4-17

Table 4.4-1 Average Annual Cs-137 Concentration in Milk Year                     Indicator                   Control (pcR)           I         (pCi/i)
Pre-op                       18.5                       18 1987                      NDM                         10.4 1988                      NDM                         6.9 1989                      NDM                           7 1990                      NDM                          17 1991                      NDM                         14.2 1992                      NDM                        NDM 1993                      NDM                        NDM 1994                      NDM                        NDM 1995                      NDM                        NDM 1996                      NDM                        NDM 1997                      NDM                        NDM 1998                      NDM                        NDM 1999                      NDM                        NDM 2000                      NDM                        NDM 2001                      NDM                        NDM 2002                      NDM                        NDM 2003                      NDM                        NDM 2004                      NDM                        NDM 2005                      NDM                        NDM 2006                      NDM                        NDM 2007                      NDM                        NDM 2008                  .NDM                           NDM.
During 2008, 1-131 was not detected in any of the milk samples. Since plant operations began in 1987, 1-131 may have been detected in one sample in 1996 and two during 1990; however, its presence in these cases was questionable, due to large counting uncertainties. During preoperation, positive 1-131 results were found only during the Chernobyl incident with concentrations ranging from 0.53 to 5.07 pCi/l. The MDC and RL for 1-131 in milk are 1 and 3 pCi/l, respectively.
4-18

4.5 Vegetation In accordance with Tables 2-1 and 2-2, grass samples are collected monthly at two indicator locations onsite near the site boundary (Stations 7 and 15) and at one control station located about 17 miles WSW from the plant (Station 37). Gamma isotopic analyses are performed on the samples. During 2008, three samples out of the 24 samples collected at the indicator stations were positive for the man-made radionuclide, Cs-137. The average of the three positive indicator samples was 24.6 pCi/kg-wet. The two positive values for Cs-137 at the control station were 41.9 pCi/kg-wet and 82.3 pCi/kg-wet and were higher than any of the three values seen at the indicator stations. However, Cs-137 is often detected in environmental samples as a result of atmospheric weapons testing and the Chernobyl incident.
In 2006, one sample at the control station was positive for Cs-137 at a higher concentration, 491.8 pCi/kg-wet, than typically seen over the years in Vogtle vegetation samples. A duplicate sample (which is taken periodically) happened to be taken at the same collection time and also revealed a similar activity. The higher concentration more than likely resulted from plowing and seeding activities (to maintain the vegetation plot) which took place a couple of weeks prior to the sample collection.
The historical trending of the average concentration of Cs-137 at the indicator and control stations is provided in Figure 4.5-1 and listed in Table 4.5-1. No trend is recognized in this data. The MDC and RL for Cs-137 in vegetation samples are 80 and 2000 pCi/kg-wet, respectively. Cs-137 is the only man-made radionuclide that has been identified in vegetation samples during the operational history of the plant. During preoperation, Cs-137 was found in approximately 60% of the samples from indicator stations and in approximately 20% of the samples from the control station. These percentages have generally decreased during operation.
The naturally occurring radionuclide Be-7 is typically detected in indicator and control station vegetation samples. Be-7 was not detected in gaseous effluents in 2008, therefore it is not included in the REMP summary table for the airborne pathway samples. Be-7 has been detected in gaseous effluents eight of the twenty years of plant operation and is therefore of interest in the REMP program.
However, the levels of Be-7 found in the REMP make no significant contribution to dose.
In May and June of 1986 during preoperation, as a consequence of the Chernobyl incident, 1-131 was found in nearly all the samples collected for a period of several weeks in the range of 200 to 500 pCi/kg-wet. The MDC and RL for 1-131 in vegetation are 60 and 100 pCi/kg-wet, respectively. Also during this time period, Co-60 was found in one of the samples at a concentration of 62.5 pCi/kg-wet.
There is no specified MDC or RL for Co-60 in vegetation.
4-19

Figure 4.5-1 Average Annual Cs-137 Concentration in Vegetation 600 500
,*400 CL 0.
r- 300
.2 E200 0
Q 100 0
Po 87 88  89 90 91   92 93  94  95   96   97 98  99   00 01  02  03 04 05 06 07 08 Year I-4-Indicator      --U-Control    -    MDC   I 4-20

Table 4.5-1 Average Annual Cs-137 Concentration in Vegetation Year               Indicator            Control (pCi/kg-wet)         (pCi/kg-wet)
Pre-op                  54.6               43.7 1987                   24.4                61.5 1988                   38.7              NDM 1989                   9.7               NDM 1990                   30.0               102.0 1991                   35.3                62.4 1992                   38.1               144.0 1993                  46.4                 34.1 1994                   20.7                57.4 1995                   57.8               179.0 1996                 NDM                 NDM 1997                 NDM                   32.6 1998                 NDM                   50.1 1999                   37.2               NDM 2000                   36.6               NDM 2001                 NDM                  NDM 2002                 NDM                   98.3 2003                   24.5               NDM 2004                   36.8                19.7 2005                   49.5               NDM 2006                   23.9               491.8 2007                   20.2               NDM 2008                   24.6                62.1 4-21

4.6 River Water Surface water from the Savannah River is obtained at three locations using automatic samplers. Small quantities are drawn at intervals not exceeding a few hours. The samples drawn are collected monthly; quarterly composites are produced from the monthly collections.
The collection points consist of a control location (Station 82) which is located about 0.4 miles upriver of the plant intake structure, an indicator location (Station
: 83) which is located about 0.4 miles downriver of the plant discharge structure, and a special location (Station 84) which is located approximately 1.3 miles downriver of the plant discharge structure. A statistically significant increase in the concentrations found in samples collected at the indicator station compared to those collected at the control station could be indicative of plant releases.
Concentrations found at the special station are more likely to represent the activity in the river as a whole, which might include plant releases combined with those from other sources along the river.
There was one river water sampling deviation that occurred in 2008. The autosampler at the indicator station (150.4) had a week battery and the monthly composite collected on 9/03/08 had to be supplemented with a grab sample.
A gamma isotopic analysis is conducted on each monthly sample. As in all previous years, there were no gamma emitting radionuclides of interest detected in the 2008 river water samples.
Each quarterly composite is analyzed for tritium. As indicated in Table 3-1, the average concentration found at the indicator station, was 1874 pCi/1 which was 1042 pCi/l greater than the average at the control station (832 pCi/1). The difference between the indicator and the control station was less than the calculated MDD (4838 pCi/1). The MDD is influenced by the variability of concentrations at the indicator station from quarter to quarter. The low number of samples (four quarterly composite samples), the variability of the four sample values, and the high standard deviation contributed to the large MDD value. The MDC for tritium in river water used to supply drinking water is 2000 pCi/l and the RL is 20,000 pCi/l.
At the special river water sampling station, the results ranged from 630 pCi/l to 2030 pCi/l with an average of 1105 pCi/I. The difference between the average concentration at the control station and the average at the special station was less than the calculated MDD of 1843 pCi/l. The decrease in tritium concentration between the indicator station and the special station is due to the additional dispersion over the 0.9 miles that separates the two stations. In the first two years of operation, the tritium concentration at the special station was somewhat greater than that at the indicator station. In recent years, the level at the special station has generally become less than the level at the indicator station.
4-22

The historical trending of the average tritium concentrations found at the special, indicator, and control stations along with the MDC for tritium is plotted on Figure 4.6-1. The data for the plot is listed in Table 4.6-1. Also included in the table are data from the calculated difference between the indicator and control stations; the MDD between the indicator and control stations; and the total curies of tritium released from the plant in liquid effluents.
The annual downriver survey of the Savannah River showed that river water is not being used for purposes of drinking or irrigation for at least 100 miles downriver (discussed in Section 4.1).
Figure 4.6-1 Average Annual H-3 Concentration in River Water 3000 2500 C.) 2000 j   1500 Q.
0 C   1000 0
50 0
Po  87  88  89  90   91  92  93 94  95   96  97  98  99  00 01  02 03 04  05  06  07   08 Year 1-0-Indicator Control    -&-Special    -MDCI 4-23

Table 4.6-1 Average Annual H-3 Concentration in River Water Year  Special   Indicator Control     Difference   MDD      Annual Site (pCi/l)     (pCi/l)  (pCi/l)     Between    (pCi/l)    Tritium Indicator and            Released Control                 (Ci)
(pCi/I)
Pre-op  1900         650      665          -15       145         NA 1987   1411         680      524          156       416         321 1988   1430         843      427          416       271         390 1989   1268        1293      538          755       518         918 1990   1081        1142      392          750       766        1172 1991   1298        1299      828          471       626        1094 1992    929        1064      371          693       714        1481 1993    616         712      238          474      1526         761 1994    774        1258      257         1001      2009        1052 1995    699         597      236          361       766         968 1996    719        1187      387          800      2147        1637 1997    686        1547      254         1293      1566        1449 1998    640        1226      196         1030      1313        1669 1999    859        2005      389         1616      1079        1674 2000    885        1564      496         1068      1786         869 2001    931        2101      743         1358      1696        1492 2002   1280        2628      437         2190      1211        1566 2003    800        1376      399          977      1706        1932 2004    743        1269      351          918      1061        1212 2005    713         800      458          342      1333        1860 2006    852        2307      384         1882      2688        2005 2007   489          879      344          535      1189         757 2008   1105        1874      832         1042      4838        1364 4-24

4.7 Drinking Water Samples are collected at a control location (Station 80 - the Augusta Water Treatment Plant in Augusta, Georgia located about 56 river miles upriver), and at three indicator locations (Station 87 - the Beaufort-Jasper County Water Treatment Plant near Beaufort, South Carolina, 112 river miles downriver; Station 88 - the Cherokee Hill Water Treatment Plant near Port Wentworth, Georgia, 122 river miles downriver; and Station 89 - the Purrysburg Water Treatment Plant near Purrysburg, South Carolina, located about 112 miles downriver. The Purrysburg Station was added to the REMP in January 2006.) Stations 87 and 89 are located on the same canal with the Purrysburg location at the beginning of the canal (nearer the Savannah River) and the Beaufort-Jasper location near the end of the canal. These upriver and downriver distances in river miles are the distances from the plant to the point on the river where water is diverted to the intake for each of these water treatment plants.
Water samples are taken near the intake of each water treatment plant (raw drinking water) using automatic samplers that take periodical small aliquots from the stream. These composite samples are collected monthly along with a grab sample of the processed water coming from the treatment plants (finished drinking water). Quarterly composites are made from these monthly collections for both raw and processed river water. Gross beta and gamma isotopic analyses are performed on each of the monthly samples while tritium analysis is conducted on the quarterly composites. An 1-131 analysis is not required to be conducted on these samples, since the dose calculated from the consumption of water is less than 1 mrem per year (see ODCM Table 4-1). However, an 1-131 analysis is conducted on each of the monthly finished water grab samples, since a drinking water pathway exists.
Provided in Figures 4.7-1 and 4.7-2 and Tables 4.7-1 and 4.7-2, are the historical trends of the average gross beta concentrations found in the monthly collections of raw and finished drinking water.
For 2008, the indicator station average gross beta concentration in the raw drinking water was 3.46 .pCi/1 which was 1.09 pCi/l greater than the average gross beta concentration at the control station (2.37 pCi/1).            This difference is statistically discernible, since it is greater than the calculated MDD of 0.95 pCi/l.
The required MDC for gross beta in water is 4.0 pCi/l. There is no RL for gross beta in water.
For 2008, the indicator station average gross beta concentration in the finished drinking water was 2.86 pCi/l which was 0.79 pCi/l more than the average gross beta concentration at the control station (2.07 pCi/1). This difference is more than the MDD of 0.57 pCi/l. The gross beta concentrations at the indicator stations ranged from 1.24 to 4.37 pCi/l while the concentrations at the control station ranged from 1.05 to 2.07 pCi/l. The required MDC for gross beta in water is 4.0 pCi/l. There is no RL for gross beta in water.
4-25

Figure 4.7-1 Average Monthly Gross Beta Concentration in Raw Drinking Water 8-7
.- 2 1
02 Po 87 88 89 90 91  92 93   94   95    96  97  98 99 00   01 02 03 04 05 06 07 08 Year Indicator    ---   Control      M-MDC 4-26

Table 4.7-1 Average Monthly Gross Beta Concentration in Raw Drinking Water Period             Indicator            Control (pCi/)             (pCi/l)
Pre-op                 2.70               1.90 1987                  2.20              5.50 1988                  2.67              3.04 1989                  2.93              3.05 1990                  2.53              2.55 1991                  2.83              3.08 1992                  2.73              2.70 1993                  3.17              2.83 1994                  3.51              3.47 1995                  3.06              4.90 1996                  5.83              3.02 1997                  2.93              2.94 1998                  3.31              2.58 1999                  4.10              4.37 2000                  4.52              3.59 2001                  3.21              2.94 2002                  3.09              2.61 2003                  3.73              2.59 2004                  4.06              2.39 2005                  3.75              2.48 2006                  3.85              2.93 2007                  4.00              3.13 2008                  3.46              2.37 4-27

Figure 4.7-2 Average Monthly Gross Beta Concentration in Finished Drinking Water 4.5-4---
C.)
0.5 0
0.5--
Po 87 88 89 90 91    92  93  94   95   96  97  98 99 00 01 02 03 04 05 06 07 08 Year
                           ----  Indicator    --*-Control  -   MDC 4-28

Table 4.7-2 Average Monthly Gross Beta Concentration in Finished Drinking Water Period           Indicator            Control (pCi/l)            (pCi/l)
Pre-op              2.90                1.80 1987               2.10                1.80 1988               2.28               2.35 1989               2.36               2.38 1990               2.08                1.92 1991               1.90                1.53 1992               2.09                1.67 1993               2.23               2.30 1994               2.40               2.68 1995               2.74               2.32 1996               2.19               2.21 1997               2.38                1.77 1998               3.23                1.67 1999               3.23                3.21 2000               3.39                2.68 2001               2.67                2.00 2002               2.80               2.61 2003               2.51                2.34 2004               2.36                1.92 2005               2.61                2.00 2006               3.23                3.25 2007               3.19                3.36 2008               2.86                2.07 4-29

As provided in Table 3-1, there were no positive results during 2008 for the radionuclides of interest from the gamma isotopic analysis of the monthly collections for both raw and finished drinking water. Only one positive result has been found since operation began. Be-7 was found at a concentration of 68.2 pCi/l in the sample collected for September 1987 at Station 87.                During preoperation Be-7 was found in about 5% of the samples at concentrations ranging from 50 to 80 pCi/1. The MDC assigned for Be-7 in water is 124 pCi/l. Also during preoperation, Cs-134 and Cs-137 were detected in about 7% of the samples at concentrations on the order of their MDCs which are 15 and 18 pCi/l, respectively.
1-131 was detected in finished drinking water in 1997 at levels near the MDC.
This was the first occurrence for detecting 1-131 in finished drinking water since operation began. During preoperation, it was detected in only one of 73 samples at a concentration of 0.77 pCi/l at Port Wentworth. The MDC and RL for 1-131 in drinking water are 1 and 2 pCi/l, respectively.
Figures 4.7-3 and 4.7-4 and Tables 4.7-3 and 4.7-4 provide historical trending for the average tritium concentrations found in the quarterly composites of raw and finished drinking water collected at the indicator and control stations. The tables also list the calculated differences between the indicator and control stations, and list the MDDs between these two station groups.
The graphs and tables show that the tritium concentrations in the drinking water samples, both raw and finished, have been gradually trending downward since 1988. The small increase in average concentrations at the indicator stations for 1991 and 1992 reflect the impact of the inadvertent release from SRS of 7,500 Ci of tritium to the Savannah River about 10 miles downriver of VEGP, in December 1991 (SRS release data was obtained from "Release of 7,500 Curies of Tritium to the Savannah River from the Savannah River Site", Georgia Department of National Resources, Environmental Protection Division, Environmental Radiation Program, January 1992).
The 2008 raw drinking water indicator stations average tritium was 726 pCi/l which was 340 pCi/1 greater than the average of the two positive concentrations found at the control station (386 pCi/1). The difference between the average at the indicator stations and the average at the control station is statistically discernible since it is greater than the calculated MDD of 269 pCi/l. The MDC and RL for tritium in drinking water are 2000 pCi/I and 20,000 pCi/1, respectively.
The finished drinking water average tritium concentration at the indicator stations during 2008 was 661 pCi/l which was 270 pCi/i more than that the average of the two positive concentrations found at the control station (391 pCi/l). The difference between the average at the indicator stations and the average at the control station is not statistically discernible since it is less than the calculated MDD of 486 pCi/l. The MDC and RL for tritium in drinking water are 2000 pCi/I and 20,000 pCi/l, respectively.
4-30

Figure 4.7-3 Average Annual H-3 Concentration in Raw Drinking Water 3000 2500-------------------------------------
4j 2000 0
1500 C  1000   --               -           --                                    -
0 0
Po     87     88     89     90    91 92    93   94   95   96  97  98   99  00 01 02 03 04 05 06 07 Year Indicator -U-iiControl        MDC 4-31

Table 4.7-3 Average Annual H-3 Concentration in Raw Drinking Water Period  Indicator     Control   Difference     MDD (pCi/i)     (pCi/i) Between Ind. &   (pCi/l)
Control (pCi/l)
Pre-op     2300          400        1900 1987      2229          316        1913         793 1988      2630          240       2390          580 1989      2508          259       2249         1000 1990      1320          266        1054         572 1991      1626          165        1461         834 1992      1373          179        1194         353 1993       955        NDM          955          NA 1994       871        NDM           871         NA 1995       917          201        716          NA 1996      1014          207         807         151 1997       956          230        726           61 1998       791          160        631          NA 1999       908        NDM          908          NA 2000      1020          373        647          704 2001       889          525         364         NA 2002       938          304        634          284 2003       563          203         360         NA 2004       585          220         365         204 2005       463          393         70          301-2006       690          451         239         394 2007       462          357         105         NA 2008       726          386         340         269 4-32

Figure 4.7-4 Average Annual H-3 Concentration in Finished Drinking Water 3500 3000 2500 e   2000
.2
*1500 a-0.)
1000 500 0
Po 87 88 89 90 91  92  93   94  95    96  97   98 99 00 01  02 03 04 05 06 07 08 Year S  Indicator    --    Control  -   MDC I 4-33

Table 4.7-4 Average Annual H-3 Concentration in Finished Drinking Water Period   Indicator       Control   Difference    MDD (pCi/l)       (pCi/l) Between Ind. &  (pCi/l)
Control (pCi/i)
Pre-op     2900            380       2520 1987      2406            305       2101        1007 1988      2900           270        2630         830 1989      2236           259        1977        627 1990      1299           404         895        1131 1991      1471           225        1246        647 1992      1195           211        984         427 1993       993          NDM         993          NA 1994       880            131       749          270 1995       847           279         568         NA 1996       884            168        716         NA 1997       887           221         666         383 1998       713            180        533         NA 1999       920            263        657         NA 2000      1043            251        792         833 2001      1037            516        521         NA 2002      1060            340        720         416 2003       473            196        277         NA 2004       531            255        276         314 2005       546            223        323         NA 2006       688            710         22         NA 2007       494            229        265         NA 2008       661            391        270         468 4-34

4.8 Fish Table 2-1 requires the collection of at least one sample of any anadromous species of fish in the vicinity of the plant discharge during the spring spawning season, and for the semi-annual collection of at least one sample of any commercially or recreationally important species in the vicinity of the plant discharge area and in an area not influenced by plant discharges. Table 2-1 specifies that a gamma isotopic analysis be performed on the edible portions of each sample collected.
As provided in Table 2-2, a 5-mile stretch of the river is generally needed to obtain adequate fish samples. For the semiannual collections, the control location (Station 81) extends from approximately 2 to 7 miles upriver of the plant intake structure, and the indicator location (Station 85) extends from about 1.4 to 7 miles downriver of the plant discharge structure. For anadromous species, all collection points can be considered as indicator stations.
The anadromous fish (American Shad) sample was collected on April 15, 2008 during the spring spawning season. No man-made radionuclides were detected in the 2008 sample. In all but three previous years of operation, no radionuclides were detected. In 2005, Cs-137 was detected in the anadromous fish sample at a low level of 28.8 pCi/kg-wet. In 1987, as well as in 1991, Cs-137 was found in a single sample of American Shad at concentrations of 10 and 12 pCi/kg-wet, respectively.
The dates and compositions of the semi-annual catches at the indicator and control stations during 2008 are shown below.
Date                          Indicator                    Control April 15                      Largemouth Bass              Largemouth Bass November 20                   Largemouth Bass              Largemouth Bass Channel Catfish              Mullet As indicated in Table 3-1, Cs-137 was found in the semiannual collections of a commercially or recreationally important species of fish. It has been found in all but 4 of the 135 samples collected during operation and in all but 5 of the 32 samples collected during preoperation. As provided in Table 3-1, the average concentration at the indicator station was 39.4 pCi/kg-wet which was 7.6 pCi/kg-wet less than that at the control station (47.0 pCi/kg-wet). The difference between the average at the indicator station and the average at the control station is less than the calculated MDD of 97 pCi/kg-wet and therefore is not statistically discernible. No discernible difference has occurred for any year of operation or during pre-operation.
Figure 4.8-1 and Table 4.8-1 provide the historical trending of the average concentrations of Cs-137 in units of pCi/kg-wet found in fish samples at the indicator and control stations. The indicator station fish sample concentration of Cs-137 in 1999 was greatly influenced by a largemouth bass collected in October with a concentration of 2500 pCi/kg-wet. Other than the fact that largemouth bass are predators that concentrate Cs-137, no specific cause for the elevated concentration in this sample is known. No trend is recognized in this data. The MDC and RL for Cs-137 in fish are 150 and 2000 pCi/kg-wet, respectively.
4-35

Figure 4.8-1 Average Annual Cs-1 37 Concentration in Fish 900        -      -   -      -       -      -        -     -      -      -      -      -     -       -       -   -    -         -
800          -     -   -     -       -       -       -     -      -       -     -      -      -      -       -    -       -     -
C, 7500            -      - -      -        -      -      -     -        -       -
                                                                                       /
 ~400                 -   -     -       -       -       -     -      -      -                              - -      -     -          -
D5-300---    I\ .       .'                                                    * .   "       1             - -      -     -          -
0200-                                 -             --
100-0--
Po     87    88   89    90     91    92     93   94  9      fr97        98    99  00    01     02    03 04  05    06   07   08 1-*-Indicator         -- W-Control         -MDCI 4-36

Table 4.8-1 Average Annual Cs-137 Concentration in Fish Year                       Indicator                     Control (pCi/kg-wet)                 (pCi/kg-wet)
Pre-op                        590                          340 1987                         337                          119 1988                          66                          116 1989                          117                         125 1990                          103                         249 1991                          105                         211 1992                          178                          80 1993                         360                           84 1994                          165                         200 1995                          125                          96 1996                          194                         404 1997                          93                          139 1998                          190                         200 1999                          848                         221 2000                           55                          96 2001                          48                           39 2002                           59                         133 2003                          62                           21 2004                         56.4                        26.0 2005                         39.3                        40.2 2006                         257                         35.7 2007                         58.7                        37.7 2008                         39.4,                       47.0 The only other radionuclide found in fish samples during operation is 1-131. In 1989, it was found in one sample at the indicator station at a concentration of 18 pCi/kg-wet. In 1990, it was found in one sample at the indicator station and in one sample at the control station, at concentrations of 13 and 12 pCi/kg-wet, respectively. The MDC assigned to 1-131 in fish is 53 pCi/kg-wet. In the November 2008 collection, the Largemouth Bass sample from the control location showed 90 pCi/kg-wet of 1-131. The specific source of the 1-131 is unknown but is likely due to medical waste.
During preoperation, Cs-134 was found in two of the 17 samples collected at the control station at concentrations of 23 and 190 pCi/kg-wet. The MDC and RL for Cs-134 are 130 and 1000 pCi/kg-wet, respectively. Nb-95 was also found in one of the control station samples at a concentration of 34 pCi/kg-wet. The assigned MDC and calculated RL for Nb-95 are 50 and 70,000 pCi/kg-wet, respectively.
4-37

4.9 Sediment Sediment was collected along the shoreline of the Savannah River on April 22 and October 7, 2008 at Stations 81 and 83. Station 81 is a control station located about 2.5 miles upriver of the plant intake structure while Station 83 is an indicator station located about 0.6 miles downriver of the plant discharge structure. A gamma isotopic analysis was performed on each sample. The radionuclides of interest identified in 2008 samples were Be-7, Co-60, and Cs-137.
Be-7, which is abundant in nature, was not identified in plant liquid effluents during 2008. However, it continues to be trended in river sediment in the REMP report. In 2008, the single positive value at the indicator station was 394 pCi/kg-dry and at the control station the single positive value was 805 pCi/kg-dry.
Because there continues to be no significant difference between the indicator and control station, the Be-7 found at the indicator station is not attributed to plant releases.
For Cs-137, the average concentration at the indicator station during 2008 was 66.2 pCi/kg-dry which was 5.3 pCi/kg-dry greater than that at the control station (60.9 pCi/kg-dry). The difference between the average value at the indicator station and the average value at the control station is not statistically discernible since it is less than the calculated MDD of 228 pCi/kg-dry. However, the concentration of Cs-137 found at the indicator station could be attributed to plant effluents or to other facilities that release radioactive effluents in the vicinity of the plant. The Cs-137 level at the indicator station has averaged nearly 100 pCi/kg-dry greater than that at the control station over the entire period of operation. During preoperation, the Cs-137 was 170 pCi/kg-dry greater at the indicator station than at the control station.
During 2008, Co-60 was detected in one sediment sample at the indicator station at 61.9 pCi/kg-dry and in no samples at the control station. Cobalt-60 has been detected in sediment collected at the indicator station every year of plant operation but three. The concentrations of Co-60 often found at the indicator station could be attributed to plant releases or, potentially, to other facilities that release radioactive effluents in the vicinity of the plant.
The historical average concentrations of Be-7, Co-58, Co-60, and Cs-137 in sediment are plotted in Figures 4.9-1 through 4.9-4 along with listings of their concentrations in Tables 4.9-1 through 4.9-4. The concentrations of the solely man-made nuclides (Co-58, Co-60, & Cs-137) are consistent with past average concentrations. No pattern has been detected. Be-7, produced by man and nature, is also within the range that is typically seen.
During preoperation, Zr-95, Nb-95, Cs-134, and Ce-141 were detected in at least one of the control station samples and Nb-95 was detected in one of the indicator station samples. Be-7 and Cs-137 were found in several of the samples. The concentrations of these preoperational nuclides were on the order of their respective MDC values. The presence of these preoperational nuclides could be attributed to atmospheric weapons testing and the Chernobyl incident.
Mn-54 and 1-131 were found sporadically over several years of operation. A summary of the positive results for these nuclides along with their applicable MDCs is provided in Table 4.9-5.
4-38

Figure 4.9-1 Average Annual Be-7 Concentration in Sediment 3500 3000 S2500
?L 2000 C
0 1500 1000 C
0 U. 500 0
Po 87 88  89 90 91  92  93  94 95  96  97 98 99 00  01 02 03 04 05 06 07 08 Year S-4--Indicator   -U-Control  -    MDC I 4-39

Table 4.9-1 Average Annual Be-7 Concentration in Sediment MDC=655 pCi/kg-dry Year                     Indicator              Control (pCi/kg-dry)           (pCi/kg-dry)
Pre-op                       580                   500 1987                       987                   543 1988                       970                    810 1989                      1300                   415 1990                       465                   545 1991                       826                   427 1992                      2038                    380 1993                       711                   902 1994                      1203                   964 1995                      1865                   1575 1996                      1925                    831 1997                      1130                   1028 1998                      1396                   1016 1999                       662                    769 2000                        1526                  3324 2001                        1697                  2614 2002                        742                   1254 2003                       1150                    903 2004                        1309                   905 2005                        1931                  1086 2006                        1254                   704 2007                        1034                  1274
___ __ __  __  __1            94                    805__
4-40

Figure 4.9-2 Average Annual Co-58 Concentration in Sediment 300 250 200 C.)
.C
: 0. 15 E100 0                  T1- ,-                                                       --
o    50 0
Po 87 88  89 90 91   92  93   94  95  96   97 98 99  00 01 02 03 04 05 06 07 08 Year I-4--Indicator   -UControl        -MDCI 4-41

Table 4.9-2 Average Annual Co-58 Concentration in Sediment
_MDC=43   pCi/kg-dry Year                    Indicator               Control (pCi/kg-dry)            (pCi/kg-dry)
Pre-op                    NDM                    NDM 1987                     NDM                    NDM 1988                      190                   NDM 1989                      135                   NDM 1990                      140                   NDM 1991                     NDM                    NDM 1992                      124                   NDM 1993                     NDM                    NDM 1994                      18.4                  NDM 1995                      42.4                  NDM 1996                      274                   NDM 1997                     NDM                    NDM 1998                     NDM                    NDM 1999                     NDM                    NDM 2000                     NDM                    NDM 2001                     NDM                    NDM 2002                     NDM                    NDM 2003                     NDM                    NDM 2004                     NDM                    NDM 2005                     NDM                    NDM 2006                     NDM                    NDM 2007                     NDM                    NDM 20Q8,.                   NDM                    NDM, 4-42

Figure 4.9-3 Average Annual Co-60 Concentration in Sediment 400 350       --
300       ----
C>   250---
0
                                    -------     -b-150-        ----               ----------      MDC--
E 100    -        -     -      -
0
: 50)   --             -    --                        -     -       -      -        -       -      -       -
0 1 -        -4                                                      -                                               -
Po      87    88   89      90     91   92   93    94 95    96   97     98     99    00    01   02 03   04 05 06 07   08 Year
                                               --indicator     -- W-Control               -MDC 4-43

Table 4.9-3 Average Annual Co-60 Concentration in Sediment MIDC=70 pCilkg-dry Year                   Indicator              Control (pCi/kg-dry)           (pCi/kg-dry)
Pre-op                   NDM                   NDM 1987                    NDM                   NDM 1988                       62                 NDM 1989                       46                 NDM 1990                       46                 NDM 1991                      113                 NDM 1992                     59.5                 NDM 1993                     65.9                 NDM 1994                      85.2                NDM 1995                      267                 NDM 1996                      344                 NDM 1997                       86                 NDM 1998                      263                 NDM 1999                     49.5                 NDM 2000                     131.3                NDM 2001                    NDM                   NDM 2002                     49.7                 NDM 2003                      146                 NDM 2004                       77                 NDM 2005                      146                 NDM 2006                       40                 NDM 2007                    NDM                   NDM 2008                     61.9                 NDM 4-44

Figure 4.9-4 Average Annual Cs-1 37 Concentration in Sediment 600 500-400 0
100 0
Po 87 88  89 90 91 92 93  94  95  96  97   98  99 00  01 02 03 04 05 06 07 08 Year Indicator   --    Control  --   MDC 4-45

Table 4.9-4 Average Annual Cs-137 Concentration in Sediment MDC=180 pCi/kg Year                   Indicator                Control (pCiLkg)           I   (pCi/kg)
Pre-op                      320                   150 1987                       209                   111 1988                       175                   175 1989                       230                   125 1990                       155                   140 1991                       246                   100 1992                       259                   111 1993                       345                   115 1994                       240                   118 1995                       357                   123 1996                       541                    93 1997                       184                    98 1998                       316                   122 1999                       197                    97 2000                       138                   218 2001                       252                   118 2002                       189                    60 2003                       171                    90 2004                       149                   100 2005                       263                    89 2006                       142                    68 2007                       125                    83 2008                      66.2                   60.9 Table 4.9-5 Additional Sediment Nuclide Concentrations Nuclide      YEAR       Indicator            Control         MDC
____        (pCi/kg-dry)       j(pCi/kg-dry)   (pCi/kg-dry)
Mn-54         1988         22                 NDM 1989          18                NDM             42 1994         32                 NDM 1-131        1992         194                  20            53 1994         51                   41 4-46

4.10 Groundwater As nuclear plants began to undergo decommissioning in the late 1990's to early 2000s, instances of subsurface and/or groundwater contamination were identified.
In addition, several operating facilities also identified groundwater contamination resulting from spills and leaks or equipment failure. In one instance, low levels of licensed material were detected in a private well located on property adjacent to a nuclear power plant.
In 2006, NEI (Nuclear Energy Institute) formed a task force to address monitoring onsite groundwater for radionuclides at nuclear facilities. A Groundwater Protection Initiative was developed which was adopted by all U.S. commercial operating nuclear plants.
The NRC also formed a task force to study the groundwater issues and released Information Notice 2006-13 "Ground-water Contamination due to Undetected Leakage of Radioactive Water" which summarized its review of radioactive contamination of ground water at multiple facilities as a result of undetected leakage from structures, systems, or components that contain or transport radioactive fluids. Licensees were instructed to review the information for applicability and to consider appropriate actions to avoid similar problems.
The NEI task force felt it was prudent for the industry to update site hydrology information and to develop radiological groundwater monitoring plans at each site. These groundwater protection plans would ensure that underground leaks and spills would be addressed promptly.               Additionally, the task force recommended developing a communications protocol to report radioactive leaks or spills that entered groundwater (or might eventually enter groundwater) to the NRC and State and Local government officials as needed.
For guidance regarding monitoring wells with unexpected results, Southern Nuclear has developed a company-wide communications protocol which is contained in the Nuclear Management Procedure, Actions for Potential Groundwater ContaminationEvents, to ensure radioactive leaks and spills would be addressed and communicated appropriately.
In 2006, Vogtle sampled onsite drinking water deep wells and onsite makeup water deep wells for tritium and gamma isotopic activity. These wells did not contain detectable amounts of radioactivity. In 2007, Vogtle implemented a more extensive radiological groundwater monitoring program. A qualified hydrologist made recommendations for drilling additional onsite monitoring wells and updated the site hydrology information. Eight new wells and 17 existing wells comprise the current VEGP groundwater monitoring program (see Table 2-3).
These locations were sampled twice in the latter portion of 2007. Several wells were positive for tritium but no gamma emitters were detected. The highest activity sample showed approximately 900 pCi/l of tritium. This level of tritium is typical background for the area around Plant Vogtle based on historical information from Georgia Department of Natural Resources and Savannah River Site. Drinking water wells, sewage treatment plant effluent, and several surface water locations supplement the monitoring program and were also sampled in 2007. None of these locations showed activity above typical environmental levels in this area. This is also true of the 2008 supplemental sampling.
4-47

The tritium levels in the water table since the radiological groundwater sampling program started in mid-2007 through 2008 are graphed in Figures 4.10-1, 4.10-2, and 4.10-3. The February 2008 sampling event appears to be an outlier, however, more data is needed to determine seasonal changes and typical fluctuations in tritium concentration due to rain washout and recharge of the aquifer. None of the tertiary aquifer wells have shown tritium concentrations above background.
In 2008, three of the monitoring wells (1013, 1003, and 1004) used for groundwater monitoring (but not newly drilled for the program) were retired due to preliminary construction activities of two potential new operating reactors.
These wells were not critical to the radiological groundwater monitoring program as they were upgradient and used primarily to obtain background data for site characterization.
4-48

RGULIE4.10-1 VEGP GW Wells inPA 1200 1000 800
                                                                                         - LT-1B
                                                                                        -  LT-7A 600 LT-12
                                                                                            -LT-13 400 200 0 -
Aug-07 Sep-07 Nov-07 Jan-08 Feb-08    Apr-08       Jun-08 Jul-08 Sep-08 Oct-08 Dec-08 4-49

RGUR    4.102 Existing Water Table Wells (Zeroes are below MDA) 1200 1000
                                                                                              +802A 800                                                                                        -- 803A 80--
805A
* 806B
-600
                                                                                             -OW-1013' 400                                                                                        -i OW-1015 OW.1004 200-0 Aug-07 Sep-07 NKv-07 Jan-08 Feb-08       Apr-08        Jun-08 Jul-08 Sep-08 Oct-08 Dec-08 4-50

RGUFE 4.10.3 New Water Table Wells (Zeroes are below MDA) 1200 1000
                                                                                            -*R-2, R-i 800                                .
R-3 R-4 600                                                                                        ___
                                                                                               --*R-6, 400
                                                                                                -- 7-R-7
                                                                                              ,--R-8.
2OOO 0
Aug-07 Sep-07   Nov-07 Jan-08 Feb-08       Apr-08       Jun-08 Jul-08 Sep-08 Oct-08 Dc-08 4-51

5.0 INTERLABORATORY COMPARISON PROGRAM In accordance with ODCM 4.1.3, the EL participates in an ICP that satisfies the requirements of Regulatory Guide 4.15, Revision 1, "Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment", February 1979. The guide indicates the ICP is to be conducted with the Environmental Protection Agency (EPA) Environmental Radioactivity Laboratory Intercomparison Studies (Cross-check) Program or an equivalent program, and the ICP should include all of the determinations (sample medium/radionuclide combinations) that are offered by the EPA and included in the REMP.
The ICP is conducted by Analytics, Inc. of Atlanta, Georgia. Analytics has a documented Quality Assurance (QA) program and the capability to prepare Quality Control (QC) materials traceable to the National Institute of Standards and Technology. The ICP is a third party blind testing program which provides a means to ensure independent checks are performed on the accuracy and precision of the measurements of radioactive materials in environmental sample matrices.
Analytics supplies the crosscheck samples to the EL which performs the laboratory analyses in a normal manner. Each of the specified analyses is performed three times. The results are then sent to Analytics who performs an evaluation which may be helpful to the EL in the identification of instrument or procedural problems.
The samples offered by Analytics and included in the EL analyses are gross beta and gamma isotopic analyses of an air filter; gamma isotopic analyses of milk samples; and gross beta, tritium and gamma isotopic analyses of water samples.
The accuracy of each result is measured by the normalized deviation, which is the ratio of the reported average less the known value to the total error. The total error is the square root of the sum of the squares of the uncertainties of the known value and of the reported average. The uncertainty of the known value includes all analytical uncertainties as reported by Analytics. The uncertainty of the reported average is the propagated error of the values in the reported average by the EL.
The precision of each result is measured by the coefficient of variation, which is defined as the standard deviation of the reported result divided by the reported average. An investigation is undertaken whenever the absolute value of the normalized deviation is greater than three or whenever the coefficient of variation is greater than 15% for all radionuclides other than Cr-51 and Fe-59. For Cr-51 and Fe-59, an investigation is undertaken when the coefficient of variation exceeds the values shown as follows:
Nuclide      Concentration
* Total Sample Activity     Percent Coefficient (pCi)                     of Variation Cr-51        <300                 NA                        25 Cr-51        NA                   >1000                     25 Cr-51        >300                 <1000                     15 Fe-59        <80                  NA                        25 Fe-59        >80                  NA                        15
* For air filters, concentration units are pCi/filter.      For all other media, concentration units are pCi/liter (pCi/1).
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As required by ODCM 4.1.3.3 and 7.1.2.3, a summary of the results of the EL's participation in the ICP is provided in Table 5-1 for: the gross beta and gamma isotopic analyses of an air filter; gamma isotopic analyses of milk samples; and gross beta, tritium and gamma isotopic analyses of water samples. Delineated in this table for each of the media/analysis combinations, are: the specific radionuclides; Analytics' preparation dates; the known values with their uncertainties supplied by Analytics; the reported averages with their standard deviations; and the resultant normalized deviations and coefficients of variation expressed as a percentage.
The GPC EL analyzed 13 samples for 43 parameters in 2008. The analyses included tritium, gross beta, Fe-55, Sr-89/90 and gamma emitting radio-nuclides in milk, water, air cartridge and air filter matrices. The attached results indicate three analyses outside the three sigma control limits. They were the following:
: 1) Mn-54 in air filter (Environmental Program) for accuracy.
: 2) Co-58 in water (Environmental Program) for precision
: 3) Gross alpha in water (Effluent Program) for accuracy.
The first quarter effluent water sample analyzed for gross alpha had a low activity recovery. The gross alpha in water self absorption curve was evaluated and updated. The second quarter alpha sample was in control for both accuracy and precision. A known alpha activity sample will be processed with the blind samples in the future to assure accurate results.
The third quarter environmental air filter sample was analyzed by gamma spectroscopy and had a high activity recovery for Mn-54. The sample was analyzed by three detectors and a weighted average reported. A small range from the three detectors produced an elevated normalized deviation result. The value was above the three sigma control limit, however the recovery of the Mn-54 activity is 114% and is acceptable.
The precision failure was in the first quarter water sample analyzed by gamma spectroscopy. The %CV for Co-58 was above the control limit. The sample was analyzed on three detectors with an error weighted average reported. An elevated range of values in the analysis is due to one of the detectors measuring a higher activity. No inconsistencies were found in the detector shaping or analysis of the 810 kev gamma peak. No further investigation will be performed.
In 2009 the Environmental Laboratory will adopt the NRC Inspection Procedure's guidance for acceptance criteria in performance sample testing. The adoption of the NRC Inspection Procedure 84750 will keep the lab consistent with the nuclear industry.
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TABLE 5-1 (SHEET 1 of 3)
INTERLABORATORY COMPARISON PROGRAM RESULTS GROSS BETA ANALYSIS OF AN AIR FILTER (pCi/filter)
Analysis or  Date        Reported        Known          Standard      Uncertainty     Percent Coef   Normalized Radionuclide Prepared    Average       I Value        [Deviation EL I Analytics (3S)  of Variation   Deviation Gross Beta   09/18/08          128.00 1        121.00[           4.82           2.03            5.43           1.01 GAMMA ISOTOPIC ANALYSIS OF AN AIR FILTER (pCi/filter)
Analysis or  Date        Reported        Known          Standard      Uncertainty     Percent Coef   Normalized Radionuclide Prepared    Average         Value          Deviation EL  Analytics (3S)  of Variation   Deviation Ce-141       09/18/08          134.00          132.00            6.74           0.74            5.81           0.25 Co-58        09/18/08          149.70          146.00             6.7           0.81            3.84           0.61 Co-60        09/18/08          197.10          192.00            7.81            1.07           3.22           0.74 Cr-51        09/18/08          390.10          345.00           14.59            1.92           6.74           1.69 Cs- 134      09/18/08          186.90          190.00            6.88            1.06           4.54         -0.35 Cs-137       09/18/08          143.20          133.00            5.23           0.74            4.92           1.40 Fe-59        09/18/08          140.60          118.00            2.99           0.66            4.58           3.40 Mn-54        09/18/08          154.60          136.00            1.14           0.76            3.42           3.30 Zn-65        09/18/08          295.40          262.00           13.08            1.46           5.70           1.93 GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (pCi/liter)
Analysis or  Date        Reported        Known          Standard      Uncertainty     Percent Coef   Normalized Radionuclide Prepared    Average         Value        I Deviation EL  Analytics (3S)  of Variation   Deviation Ce-141       06/19/08          180.10          174.00           13.17           0.97            8.56           0.39 Co-58        06/19/08            68.90          61.90            4.77           0.34            0.65           0.96 Co-60        06/19/08          112.60          104.00            5.69           0.58            6.87           1.10 Cr-51        06/19/08          146.70          138.00           23.39           0.77          25.12            0.24 Cs- 134      06/19/08            74.70          76.70            2.67           0.43            7.18          -0.36 Cs-137       06/19/08          118.20          116.00            5.44           0.65            7.27           0.25

TABLE 5-1 (SHEET 2 of 3)
INTERLABORATORY COMPARISON PROGRAM RESULTS GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (pCi/liter)
Analysis or   Date        Reported      Known          Standard      Uncertainty     Percent Coef Normalized Radionuclide  Prepared    Average       Value          Deviation EL  Analytics (3S)  of Variation I Deviation Fe-59         06/19/08          109.40         91.70           13.67           0.51          14.96            1.08
 -131         06/19/08            88.90        71.40             9.9           0.40          12.83            1.53 Mn-54         06/19/08          152.00        135.00            4.56           0.75            5.68           1.92 Zn-65        106/19/08          135.40        127.00 1          8.19           0.71           10.23           0.60 GROSS BETA ANALYSIS OF WATER SAMPLE (pCi/liter)
GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (pCi/liter)
Analysis or   Date        Reported      Known          Standard      Uncertainty     Percent Coef   Normalized Radionuclide  Prepared    Average       Value          Deviation EL  Analytics (3S)  of Variation   Deviation Ce- 141       03/20/08          204.60        198.00            8.08           2.21            5.87           0.55 Co-58         03/20/08            58.50        56.40            9.22           0.63           15.77           0.23 Co-60         03/20/08          188.90        189.00            9.74           2.09            6.57           0.06 Cr-51         03/20/08          356.30        286.00           21.56           2.85           12.23           1.61 Cs- 134       03/20/08            99.90        99.70            2.29            1.11           5.91           0.03

TABLE 5-1 (SHEET 3 of 3)
INTERLABORATORY COMPARISON PROGRAM RESULTS GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (pCi/liter)
Analysis or    Date         Reported         Known           Standard      Uncertainty    Percent Coef Normalized Radionuclide   Prepared     Average          Value           Deviation EL Analytics (3S)  of Variation   Deviation Cs-137         03/20/08            121.50           116.00            9.85           1.29          10.22           0.45 Fe-59          03/20/08             92.60            81.40            7.75           0.91         12.21            0.99 1-131          03/20/08             68.90            70.40            0.98           0.79           8.64         -0.25 Mn-54          03/20/08             83.20            75.00            4.32           0.83           8.84           1.11 Zn-65          03/20/08            119.90           109.00            6.41           1.21         11.03            0.83 TRITIUM ANALYSIS OF WATER SAMPLES (pCi/liter)
Analysis or   Date          Reported         Known           Standard      Uncertainty    Percent Coef Normalized Radionuclide  Prepared      Average        I Value         I Deviation EL Analytics (3S) of Variation    Deviation H-3            03/20/08          3988.70 1         4010.00           87.41         22.33 1          4.28         -0.13 1 06/19/08   1     12,900.00]       13,000.00 1         44.32         72.33]           2.16         -0.48 1-131 ANALYSIS OF AN AIR CARTRIDGE (pCi/cartridge)
Analysis or   Date          Reported         Known           Standard      Uncertainty    Percent Coef   Normalized Radionuclide  Prepared      Average          Value           Deviation EL Analytics (3S) of Variation    Deviation 1-131          12/11/08             51.30            54.80            0.22           0.31           3.83         -1.75

==6.0 CONCLUSION==
S This report confirms the licensee's conformance with the requirements of Chapter 4 of the ODCM. It provides a summary and discussion of the results of the laboratory analyses for each type of sample.
In 2008, there were four instances in which the indicator station readings were statistically discernible from the control station readings. This is discussed in detail below. No discernible radiological impact upon the environment or the public as a consequence of plant discharges to the atmosphere and to the river was established for any other REMP samples.
Gross beta results in raw and finished drinking water were statistically higher at the indicator stations than at the control station. For raw drinking water the average results at the indicator stations were 3.46 pCi/1 and the average at the control station was 2.37 pCi/l. For finished drinking water the average results at the indicator stations were 2.86 pCi/1 and the average at the control station was 2.07 pCi/l. All average results were below the required MDC for gross beta in water which is 4 pCi/l. There is no reporting level for gross beta in water. Gross beta is a screening analysis for beta activity. No gamma emitters were detected in raw or finished drinking water samples. The low level of beta activity seen is likely due to naturally-occurring radionuclides but could be attributed to plant effluents.
Tritium in raw drinking water was statistically higher at the indicator stations than at the control station. The average tritium at the indicator stations was 726 pCi/1 and the average at the control station was 386 pCi/l. The concentration seen at the indicator station could be attributed to plant effluents. The MDC and RL for tritium in drinking water are 2000 pCi/1 and 20,000 pCi/l, respectively. Although raw water in not intended for human consumption, a potential dose from tritium in the drinking water pathway was calculated assuming that a person regularly consumed untreated water taken from the river near the intake to the water treatment plants. Under these assumed circumstances, the potential dose to such an individual would be approximately 0.026 mrem in a year. This dose is approximately 1% of the annual dose limit from liquid effluents which is 3 mrem.
One of the two sediment samples at the indicator station was positive for Co-60 at 61.9 pCi/kg-dry. Neither of the two samples at the control station was positive.
There has not been a positive sample at the control station from pre-op to present.
The results seen at the indicator station over the years could be attributed to plant effluents. The potential dose to the maximally exposed individual from the Co-60 concentration seen at the indicator station in 2008 would be approximately 2.82E-3 mrem in a year which is only 0.1% of the annual dose limit from liquid effluents.
The radiological levels reported in 2008 were low. The REMP trends over the course of time from preoperation to the present are generally decreasing or have remained fairly constant. This supports the conclusion that there is no adverse radiological impact on the environment or to the public as a result of the operation of Plant Vogtle.
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