Text

Enclosure 3 - Vogtle, Units 1 and 2, Annual Radiological Environmental Operating Report for 2009
	ML101390536
Person / Time
Site:	Vogtle
Issue date:	05/14/2010
From:	; Southern Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
References
	NL-10-0905
	Download: ML101390536 (87)
	v • d • e

Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radiological Environmental Operating Reports for 2009 Enclosure 3 Vogtle Annual Radiological Environmental Operating Report for 2009

VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2009 SOUTHERNA 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 (ICP) 5-1 6.0 Conclusions 6-1 i

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

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

LIST OF ACRONYMS Acronyms presented in alphabetical order.

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

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

1.0 INTRODUCTION

The Radiological Environmental Monitoring Program (REMP) is conducted in accordance with Chapter 4 of the Offsite Dose Calculation Manual (ODCM). The REMP activities for 2009 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 analysisI A community having the following filter change highest calculated annual and gamma isotopic average ground level D/Q; analysis2 of composite (by location), quarterly.

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

TABLE 2-1 (SHEET 2 of 5)

SUMMARY

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

3. Waterborne

a. Surface 3 One sample .......

upriver. ........

om. . . i. . .o. . ie ;sample I...........

Composite m.....ie.....v

............................................... over er...o.....e.......................................................

one. m a2isotopic

~ io~ c................................

Gamma 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 2 N) plant every two weeks or isotopic analysis 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 and gamma

TABLE 2-1 (SHEET 3 of 5)

SUMMARY

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

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

recreational value.

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

4..In g s tio n . ...................

.. ..................................................... .I.s.

a. Milk Two samples from milking Biweekly Gamma isotopic animals6 at control locations analysis 27, biweekly.

at a distance of about 10 miles or more.

. ........................................... ........................... o............t......................................

Fish At least one sample of any emiannually Gamma l 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. analysis 2 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, 7, 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall 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' Distance Sample Type Number Type Location (miles)'

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 Say. 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 1 Distance Sample Type Number Type Location (miles)1 29 Other Claxton-Lively W 5.1 Direct Rad.

Road 30 Other Nathaniel WNW 5.0 Direct Rad.

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

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 Treatment Plant Water 2 81 Control Say 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 Say River ESE 4.3 Fish3 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 Water 7 Plant; Purrysburg, SC 98 Control W.C. Dixon SE 9.8 Milk' Dairy 101 Indicator Girard Dairy S 5.5 Milk8 102 Control Seven Oaks W 7.5 Milk' I I Dairy Notes:

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

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

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

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

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

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

(6) The intake for the Cherokee Hill Water Treatment Plant is located on 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) Girard Dairy is considered an indicator station since it is the closest dairy to the plant

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

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

2-9

Groundwater Monitoring Locations Table 2-3 WELL AQUIFER MONITORING PURPOSE LT-1B Water Table NSCW related tank LT-7A Water Table NSCW related tank LT-12 Water Table NSCW related tank LT-13 Water Table NSCW related tank 802A Water Table Southeastern potential leakage 803A Water Table Up gradient to rad waste building 805A Water Table 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 Table leakage R2 Water Table Southern potential leakage R3 Water Table Eastern potential leakage R4 Water Table Dilution line R5 Water Table Dilution line R6 Water Table Dilution line R7 Water Table Dilution line R8 Water Table within Dilution line Sav. River sediments 1013* Water Table Low level rad waste storage 1014 Tertiary Up gradient 1015 Water Table Vertically up gradient 1003* Tertiary Up gradient 1004* Water Table Vertically up gradient 27 Tertiary Down gradient tertiary 29 Tertiary Down gradient tertiary MU-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

TLD & Other Figure 2-1 2-11

'S'.

0 Aiken

/ Barnwell Radiological Environmental Sampling Locations REMP Control Stations Indicator Control Additional TLD A ,

A for the Plant Other *

0 TLD & Other Figure 2-2 2-12

10 Miles Radiological Environmental Sampling Locations Indicator Control Additional TLD A A A Water Stations Other 0 0 0 TLD & Other @ Figure 2-3 2-13

4 .p aSoA t'3 NEW BARGE FADiLITYOPTION 1 vnprtk NE fDSCHAGE LINE

-)(ST. DEBRIS BASIN DAM 29 179 0 51 0 OWS005 A 2L weB 0

OW-1009 *8O6 0 04 LI 0

OW-1010 &52 ol~n

..EW AISIOo.

A LEGEND:

2!6 o.,,, Tonli., ~ioMnto Well W5,oretToble lmooirrinq well mu'Wolor'Sepply Well in Lo- r T,'tlor .nd 0 Otler' welts not Port of Tritlumr Sturdy 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 2009, 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 23.0 Station 16 24.0 22.5 22.4 Particulates 363 5-4-41.0 Hancock 8.7-35.4 8.5-35.3 9.3-35.8 (fCi/m3) (259/259) Landing Rd. (52/52) (52/52) (52/52) 1.4 miles NNW 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) 13.1 Station 20 16.8 13.4 13.6 Radiation Dose 10.4-16.5 SRS Road 15.4-17.8 9.4-17.8 11.2-17.2 (mR/91 days) 160 (64/64) A. 13.1 (4/4) (72/72) (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/l) Gamma Isotopic 52 Cs-134 15 NDM NDM NA NDM Cs-137 18 NDM NDM NA NDM Ba- 140 60 NDM NDM NA NDM La-140

.. ..................................... 15

........................................ NDM

. .....ý ..... .............................

÷ ............... NDM................

. NA

..... NDM I-131 1 NDM NDM NA NDM 52 Vegetation Gamma (pCi/kg-wet) Isotopic 36 1-131 60 NDM NDM NA NDM Cs-134 60 NDM NDM NA NDM Cs-137 80 34.6 Station 7 34.6 NA NDM (1/24) Simulator Bldg. (1/12) 1 1.7 miles SE I I I

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), 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 Titium 0 01 2000 ............

12033 .. Tr tu2Station o 8. 83 ..............

12030.... .....................................

.tt

.2

. 614 221 12 218-2990 RM 150.4 218-2990 -352-1080 198-243 (4/4) 0.8 miles ENE (4/4) (3/4) (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 (b), 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 3.28 Station 87 4.58 NA 2.26 Intakes to 48 1.17-8.56 Beaufort-Jasper WTP 2.26-8.56 1.28-3.08 Water (34/36) 76 miles SE (11/12) (8/12)

Treatment Plants (pCi/1)

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 (f) 15 NDM NDM NA NDM Cs- 134 15 NDM NDM NA NDM Cs-137 18 NDM NDM NA NDM Ba-140 60 NDM NDM NA NDM La- 140 15 NDM NDM NA NDM Tritium 2000 602 Station 89 698 NA 587 16 258-1380 Purrysburg WTP 323-1380 (1/4)

(10/12) 76 miles SSE (3/4)

TABLE 3-1 (SHEET 5 of 8)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Medium or Type and Minimum Indicator Location with the Highest Other Control Pathway Total Detectable Locations Annual Mean Stations (g) Locations Sampled Number of Concentration Mean (b), Mean (b), 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 2.53 Station 88 2.64 NA 2.13 at Water 48 1.28-4.79 Cherokee Hill WTP 1.39-3.92 1.20-3.83 Treatment (31/36) Port Wentworth (11/12) (11/12)

Plants (pCi/1) 72 miles SSE I I I. 4 4 I 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 579 Station 88 720 NA 667 16 282-1180 Cherokee Hill WTP 339-1100 (1/4)

(9/12) Port Wentworth, GA (2/4) 72 miles SSE

& i I 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) 0 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 2

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 50 NDM81 30.4 NA 30.4 2.5 miles N (1/1) (1/1)

(upstream)

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) 2011 Station 83 2011 NA 1131 284-3737 0.8 miles ENE 284-3737 232-2030 (2/2 ) ....................

_ . (2 ....

2)................................. ...................

(2 /2)

Co-60 70(e) NDM NDM NA NDM

.....C-Cs-1343 I ......................

1150 I.............I........

0N...............................

NDM M............................

...... .. N.........................

NMNDM.........................

I.............

D ......

Cs-137 180 127.7 Station 83 127.7 NA 103.2 43.7-211.8 0.8 miles ENE 43.7-211.8 65.9-140.5 (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.

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 2009 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 O's.

Table 4-1 Minimum Detectable Concentrations (MDC)

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

Gross Beta 4 10 H-3 2000 (a)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 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/1 may be used.

4-1

Table 4-2 Reporting Levels (RL)

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

H-3 20,000 (a)

Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-95 400 Nb-95 700 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/I 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 02/17/09-02/24/09 AF/AC Non-representative sample Power cut off by Planters Power restored after billing CR2009106190 Hancock Landing Rd. of airborne particulates Electric due to overdue bill; issues resolved 1.4 miles NNW lost - 17.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of sampling time Late Winter / Early Anadromous Fish Unable to collect River level too high to collect NA Spring anadromous fish fish during the anadromous CR2009106339 collection period 2nd Quarter TLD #17 Non-representative direct TLDs found on ground at TLDs replaced at beginning of CR2010106101 SRS radiation data collection time quarter 5.4 miles N March, April, and Raw Drinking Water Non-representative raw Canal dry while construction Grab samples taken while canal May 2009 Augusta WTP drinking water samples performed; unable to use construction in progress CR2010106098 RM 207 autosampler 06/16/09 Seven Oaks Dairy Change in milk sampling Dixon Dairy went out of Seven Oaks Dairy added as CR2009106195 replaced Dixon Dairy location business replacement milk sampling CR2009204359 station 07/28/09-08/04/09 AF Non-representative sample Gross beta MDC not met on Filter replaced at beginning of CR2010106099 Met Tower of airborne particulates air filter; no activity next collection period EXCLUDED 0.9 miles SSW identified on filter; cause unknown Second Semi- Fish Unable to collect fish in the River level too high to collect NA Annual Period fall fish during the fall and early CR2009112683 winter

4.1 Land Use Census and River Survey In accordance with ODCM 4.1.2, a land use census was conducted on November 10, 2009 to. determine the locations of the nearest permanent residence, milk animal, and garden of greater than 500 square feet producing broad leaf vegetation, in each of the 16 compass sectors within a distance of 5 miles; the locations of the nearest beef cattle in each sector were also determined. A milk animal is a cow or goat producing milk for human consumption. Land within SRS was excluded from the census. The census results are tabulated in Table 4.1-1.

Table 4.1-1 LAND USE CENSUS RESULTS Distance in Miles to the Nearest Location in Each Sector SECTOR RESIDENCE MILK BEEF GARDEN ANIMAL CATTLE N 1.4 None None None NNE None None None None NE None None None None ENE None None None None E None None None None ESE 4.2 None None None SE 4.4 None 5.0 None SSE 4.6 None 4.7 None S 4.4 None 4.3 None SSW 4.7 None 4.5 None SW 3.1 None None 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 29, 2009 to identify any withdrawal of water from the river for drinking, irrigation, or construction purposes. No such usage was identified. These results were corroborated by checking with the Georgia Department of Natural Resources on October 7, 2009 and October 2, 2009; and the South Carolina Department of Health and Environmental Control on October 5, 2009 and October 2, 2009. Each of these agencies confirmed that no water withdrawal permits for drinking, irrigation, or construction purposes had been issued for this stretch of the Savannah River. The three water treatment plants used as indicator stations for drinking water are located farther downriver.

4-6

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

Each particulate filter is counted for gross beta activity. A quarterly gamma isotopic analysis is performed on a composite of the air particulate filters for each station. Each charcoal canister is analyzed for 1-131.

As provided in Table 3-1, the 2009 annual average weekly gross beta activity was 23.0 fCi/m3 for the indicator stations. It was 0.6 fCi/m3 greater than the control station average of 22.4 fCi/m 3 for the year. This difference is not statistically discernible, since it is less than the calculated MDD of 2.4 fCi/m 3 .

The 2009 annual averafe weekly gross beta activity at the Girard community station was 22.5 fCi/m- which was 0.1 fCi/m 3 greater than the control station average. This difference is not statistically discernible since it is less than the calculated MDD of 3.1 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 ES20 C.

S15 10 0

0 Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 Year

Indicator Control

Community -MDC I 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 2009 23.0 22.4 22.5 4-9

During 2009, no man-made radionuclides were detected from the gamma isotopic analysis of the quarterly composites of the air particulate filters. In 1987, Cs-137 was found in one indicator composite at a concentration of 1.7 fCi/m3 . During pre-operation, Cs-137 was found in approximately 12% of the indicator composites and 14% of the control composites with average concentrations of 1.7 and 1.0 fCi/m3 , respectively. The MDC for airborne Cs-137 is 60 fCi/m 3 . 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 2009, Be-7 was not identified in plant gaseous effluents therefore it is not included in the 2009 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 2009. 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/m 3 , respectively.

Table 4-3 lists REMP deviations that occurred in 2009. There were two air monitoring deviations in 2009. One deviation involved the air station at Hancock Landing Road which lost about 17.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of sampling time during the third week of February. Power to the station was cut off because of a billing issue with Planters Electric. Power was restored when the billing issue was resolved. The results were compared with other air station results from the same collection period. The Hancock Landing results passed Chauvenet's Criterion and were retained in the data summary. The other air monitoring deviation involved a filter from the end of July (at the Met Tower Station) which did not meet the gross beta MDC (and showed no activity). There were no issues noted with the collection or analysis of the filter. The filter was verified not to be the blank. No issues were noted with the gamma isotopic results for the quarter. No other similar occurrences have been noted over the years. This appears to be an isolated anomaly.

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 13.1 mR with a range of 10.4 to 16.5 mR. This average was 0.5 mR less than the average quarterly exposure measured at the control stations (13.6 mR). This difference is not statistically discernible since it is less than the MDD of 0.9 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 2009 ranged from 9.4 to 17.8 mR with an average of 13.3 mR which was 0.3 mR less than that for the control stations. However, this difference is not discernible since it is less than the MDD of 1.1 mR. For the entire period of operation, the annual average quarterly exposures at the outer ring stations vary by no more than 1.2 mR from those at the control stations. The overall average quarterly exposure for the outer ring stations during preoperation was 1.8 mR less than that for the control stations.

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

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

4-11

Figure 4.3-1 Average Quarterly Exposure from Direct Radiation 20 18 16 14 812 0

08 6

4 2

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

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

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

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 25 20

£15 C-010 5

0 Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 Year

-Hunting Cabin (Sta 33) -- Girard (Sta 35)

Rec Center (Sta 43) 1 4-14

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

Pre-op 16.6 15.1 15.3 1987 21.3 18.5 15.2 1988 19.7 18.1 14.8 1989 21.2 18.7 17.4 1990 16.8 18.9 16.2 1991 17.3 19.6 17.0 1992 12.8 13.5 12.0 1993 12.9 13.3 12.1 1994 12.6 13.6 12.0 1995 13.3 13.5 12.3 1996 13.0 13.6 12.1 1997 13.8 14.4 12.7 1998 13.5 13.7 12.5 1999 NA 14.5 12.7 2000 NA 14.8 13.1 2001 NA 14.0 12.6 2002 NA 14.0 12.1 2003 NA 14.1 12.2 2004 NA 14.2 11.7 2005 NA 15.2 12.7 2006 NA 14.3 12.6 2007 NA 13.6 11.8 2008 NA 14.4 12.6 2009, ,,NA '14.6 _ _ _ _ _ _ _

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 was one deviation from the REMP pertaining to measuring quarterly gamma doses during 2009. In second quarter, the TLDs at Station 17 on the Savannah River Site were found on the ground. The result from this deviation passed Chauvenet's Criterion and was included in the data set.

The standard deviation for the quarterly result for each badge was subjected to a self imposed limit of 1.4. This limit is based upon the standard deviations obtained with the Panasonic UD-814 badges during 1992 and is calculated using a method developed by the American Society of Testing and Materials (ASTM Special Technical Publication 15D, ASTM Manual on Presentation of Data and Control Chart Analysis, Fourth Revision, Philadelphia, PA, October 1976). The limit serves as a flag to initiate an investigation. To be conservative, readings with a standard deviation greater than 1.4 are excluded 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: V23B Second Quarter: None Third Quarter: V42B Fourth Quarter: None However, for the cases when only one badge exceeded a standard deviation of 1.4, the companion badges were available and were used for determining the quarterly doses. The badges exceeding the self-imposed limit were visually inspected under a microscope and the glow curve and test results for the anneal data and the element correction factors were reviewed. No reason was evident for the high standard deviation.

4-16

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

Gamma isotopic and 1-131 analyses are performed on each milk sample. No man-made radionuclides were identified by gamma isotopic analysis in 2009. The MDC and RL for Cs-137 in milk are 18 and 70 pCi/1, respectively. During preoperation and each year of operation through 1991, Cs-137 was found in 2 to 6% of the samples at concentrations ranging from 5 to 27 pCi/l. During preoperation, Cs-134 was detected in one sample and in the first year of operation, Zn-65 was detected in one sample. Figure 4.4-1 and Table 4.4-1 provide the historical trending of the Cs- 137 concentration in milk.

Figure 4.4-1 Average Annual Cs-137 Concentration in Milk 20 - I - U - I - U - I - I - U - I - U - I - U - I - U - U - U - I - U - U - I - U - I - I -

181 16 I&

14 12 0

~10 0 6 4

2 0- - - - - - - --

96 97 98- 99 - 00 - - -

89 90 91 92 93 94 95 PoP0 8787 88 88 89 90 91 92 93 94 95 96 97 98 99 S0 01 02 03 04 05 06 07 08 09 Year I # Indicator -N- Control - MDC I 4-17

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

Pre-op 18.5 18 1987 NDM 10.4 1988 NDM 6.9 1989 NDM 7 1990 NDM 17 1991 NDM 14.2 1992 NDM NDM 1993 NDM NDM 1994 NDM NDM 1995 NDM NDM 1996 NDM NDM 1997 NDM NDM 1998 NDM NDM 1999 NDM NDM 2000 NDM NDM 2001 NDM NDM 2002 NDM NDM 2003 NDM NDM 2004 NDM NDM 2005 NDM NDM 2006 NDM NDM 2007 NDM NDM 2008 NDM NDM 2009 NDM NDM During 2009, 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 2009, one sample (34.6 pCi/kg-wet) out of the 24 samples collected at the indicator stations was positive for the man-made radionuclide, Cs-137. No Cs-137 was identified in the twelve control station samples. Cs-137 is often detected in environmental samples as a result of atmospheric weapons testing and the Chernobyl incident.

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

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

The naturally occurring radionuclide Be-7 is typically detected in indicator and control station vegetation samples. Be-7 was not detected in gaseous effluents in 2009, 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 60 500 400 C300 0

I

~200 0

L-)

100 0

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

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

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

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

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

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

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

A gamma isotopic analysis is conducted on each monthly sample. As in all previous years, there were no gamma emitting radionuclides of interest detected in the 2009 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 1203 pCi!l which was 982 pCi/I greater than the average at the control station (221 pCi/1). The difference between the indicator and the control station was less than the calculated MDD (3551 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 352 pCi/l to 1080 pCi/l with an average of 614 pCi/l. The difference between the average concentration at the control station and the average at the special station was less than the calculated MDD of 1373 pCi/l. The decrease in tritium concentration between the indicator station and the special station is due to the additional dispersion over the 0.9 miles that separates the two stations. In the first two years of operation, the tritium concentration at the special station was somewhat greater than that at the indicator station. In recent years, the level at the special station has generally become less than the level at the indicator station.

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

4-22

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

Figure 4.6-1 Average Annual H-3 Concentration in River Water 0

0 0

C 0

C)

Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 Year

-Indicator--- Control A 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/1) 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 2009 614 1203 221 982 3551 1224 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 2009, the indicator station average gross beta concentration in the raw drinking water was 3.28 pCi/l which was 1.02 pCi/l greater than the average gross beta concentration at the control station (2.26 pCi/1). This difference is not statistically discernible since it is less than the calculated MDD of 1.39 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 2009, the indicator station average gross beta concentration in the finished drinking water was 2.53 pCi/l which was 0.40 pCi/l more than the average gross beta concentration at the control station (2.13 pCi/1). This difference is not statistically discernible since it is less than the MDD of 0.70 pCi/l. The gross beta concentrations at the indicator stations ranged from 1.28 to 4.79 pCi/l while the concentrations at the control station ranged from 1.20 to 3.83 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 8 Water 7

C 0

02i C

0 Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 Year 1-4-ndiato -U--Control -MDCI 4-26

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

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

Figure 4.7-2 Average Monthly Gross Beta Concentration in Finished Drinking Water 4.5 0.5 0

Po 87 88 89 go 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 Year

-I-ndicator -*----Control

-M---C 4-28

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

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

_ 2.53 _____ _ __2.13-___

4-29

As provided in Table 3-1, there were no positive results during 2009 for the radionuclides of interest from the gamma isotopic analysis of the monthly collections for both raw and finished drinking water. Only one positive result has been found since operation began. Be-7 was found at a concentration of 68.2 pCi/l in the sample collected for September 1987 at Station 87. During preoperation Be-7 was found in about 5% of the samples at concentrations ranging from 50 to 80 pCi/l. The MDC assigned for Be-7 in water is 124 pCi/l. Also during preoperation, Cs-134 and Cs-137 were detected in about 7% of the samples at concentrations on the order of their MDCs which are 15 and 18 pCi/1, 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 2009 raw drinking water indicator stations average tritium was 602 pCi/I which was 15 pCi/l greater than the average of the one positive concentration found at the control station (587 pCi/1). Application of the modified Student's t-test shows that the difference between the average at the indicator stations and the single value at the control station was not statistically discernible. 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 2009 was 579 pCi/l which was 88 pCi/l less than the one positive concentration found at the control station (667 pCi/l). Application of the modified Student's t-test shows that the difference between the average at the indicator stations and the single value at the control station is not statistically discernible.

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

4-30

Figure 4.7-3 Average Annual H-3 Concentration in Raw Drinking Water C) 0 Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 Year

-- 1 Indicator -- IF- Control - MDC 4-31

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

I I_ Control (pCi/I)

Pre-op 2300 400 1900 1987 2229 316 1913 793 1988 2630 240 2390 580 1989 2508 259 2249 1000 1990 1320 266 1054 572 1991 1626 165 1461 834 1992 1373 179 1194 353 1993 955 NDM 955 NA 1994 871 NDM 871 NA 1995 917 201 716 NA 1996 1014 207 807 151 1997 956 230 726 61 1998 791 160 631 NA 1999 908 NDM 908 NA 2000 1020 373 647 704 2001 889 525 364 NA 2002 938 304 634 284 2003 563 203 360 NA 2004 585 220 365 204 2005 463 393 70 301 2006 690 451 239 394 2007 462 357 105 NA 2008 726 386 340 269 2009 .602 587 15. NAý1' 4-32

Figure 4.7-4 Average Annual H-3 Concentration in Finished Drinking Water 350( 0 0

300(

0 S250(

C.

0 c 200(

0 C1500 C

8100(

500 Po 87 88 89 90 91 92 93 94 95 ea 9r7 98 99 00 01 02 03 04 05 06 07 08 09

Indicator --- Control -MDC 4-33

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

Control (pCi/A)

Pre-op 2900 380 2520 1987 2406 305 2101 1007 1988 2900 270 2630 830 1989 2236 259 1977 627 1990 1299 404 895 1131 1991 1471 225 1246 647 1992 1195 211 984 427 1993 993 NDM 993 NA 1994 880 131 749 270 1995 847 279 568 NA 1996 884 168 716 NA 1997 887 221 666 383 1998 713 180 533 NA 1999 920 263 657 NA 2000 1043 251 792 833 2001 1037 516 521 NA 2002 1060 340 720 416 2003 473 196 277 NA 2004 531 255 276 314 2005 546 223 323 NA 2006 688 710 22 NA 2007 494 229 265 NA 2008 661 391 270 468 2009" ý579, 667 88 ý,NNA 4-34

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

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

Anadromous fish were not collected during the spring spawning season because of high river water levels during the span of collection time (late winter to early spring). In all but three previous years of operation, no radionuclides were detected in anadromous fish samples. In 2005, Cs-137 was detected in the anadromous fish sample at a low level of 28.8 pCi/kg-wet. In 1987, as well as in 1991, Cs-137 was found in a single sample of American Shad at concentrations of 10 and 12 pCi/kg-wet, respectively.

The dates and compositions of the semi-annual catches at the indicator and control stations during 2009 are shown below. Due to high river water levels in the fall, electrofishing was not possible during the second semi-annual collection period.

Date Indicator Control June 9 Largemouth Bass Largemouth Bass Second Semi-Annual None None Collection Period I I I 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 5 of the 137 samples collected during operation and in all but 5 of the 32 samples collected during preoperation. As provided in Table 3-1, there was no Cs-137 detected in the one sample from the indicator station and 30.4 pCi/kg-wet was detected in the one sample at the control station. No discernible difference between the indicator and control stations has occurred for any year of operation or during pre-operation.

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

4-35

Figure 4.8-1 Average Annual Cs-137 Concentration in Fish 900-800---

700--------------------------------------- - ---

500 300 00 0

Po 87 88 89 90 91 92 93 94 98 99\ 00 01 02 03 04 05 08 07 08 09 1 - -Indicator -U-n Contitl - 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 1.2009 NDM 30.4 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 21 and October 6, 2009 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 2009 samples were Be-7, Co-60, and Cs-137.

Be-7, which is abundant in nature, was not identified in. plant liquid effluents during 2009. However, it continues to be trended in river sediment in the REMP report. In 2009, the average at the indicator station was 2011 pCi/kg-dry and at the control station the average concentration was 1131 pCi/kg-dry. The difference (880 pCi/kg-dry) is not statistically discernible because it is less than the calculated MDD of 13560 pCi/kg-dry. Due to the low number of samples, the variability of Be-7 activity found in them, and the high standard deviation the MDD value is very high. Because Be-7 has not been identified in plant effluents for the past several years and because there continues to be no significant difference between the indicator and control station, the Be-7 found at the indicator station is not attributed to plant releases.

For Cs-137, the average concentration at the indicator station during 2009 was 127.7 pCi/kg-dry which was 24.5 pCi/kg-dry greater than that at the control station (103.2 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 640 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 2009, Co-60 was not detected in any of the four sediment samples.

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

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

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.

4-38

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.

Figure 4.9-1 Average Annual Be-7 Concentration in Sediment 3500-3000 --

~2500----------------------

.0 1000 -

0 Pao 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 Year

-- *-Indicator -Control -MDC 4-39

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

Pre-op 580 500 1987 987 543.

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

Figure 4.9-2 Average Annual Co-58 Concentration in Sediment 300 250 200 C,n 150 0

w cc E100 850

/~ / t/

0 Po 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 Year 1 $Indicator --U--Control - MDC I 4-41

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

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

Figure 4.9-3 Average Annual Co-60 Concentration in Sediment 400 350 300 V

250 200 0

150 IQ.

0 0

100 50 7R 0

Po 87 88 89 90 91 92 93 94 95 98 99 00 01 02 03 04 05 06 07 08 09

-ear 9 1* Indicator -U11--Control -MDC 4-43

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

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

Figure 4.9-4 Average Annual Cs-137 Concentration in Sediment 600 500 p400 C 300 0

200 I-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 09 Year

--- Indicator -U--Control - MDC 4-45

Table 4.9-4 Average Annual Cs-137 Concentration in Sediment MDC=180 pCi/kg Year Indicator Control 1(pCi/kg) (pCi/kg)

Pre-op 320 150 1987 209 111 1988 175 175 1989 230 125 1990 155 140 1991 246 100 1992 259 111 1993 345 115 1994 240 118 1995 357 123 1996 541 93 1997 184 98 1998 316 122 1999 197 97 2000 138 218 2001 252 118 2002 189 60 2003 171 90 2004 149 100 2005 263 89 2006 142 68 2007 125 83 2008 66.2 60.9 2009 103..2 Table 4.9-5 Additional Sediment Nuclide Concentrations Nuclide YEAR Indicator Control MDC I (pCi/kg-dry) (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 Contamination Events, 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 2009 are graphed in Figures 4.10-1, 4.10-2, and 4.10-3. The February 2008 sampling event appears to be an outlier, however, more data is needed to determine seasonal changes and typical fluctuations in tritium concentration due to rain washout and recharge of the aquifer. None of the tertiary aquifer wells have shown tritium concentrations above background.

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

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

In 2009, tritium concentrations observed in the Vogtle groundwater monitoring wells were fairly stable. As more data is collected, seasonal variations can be identified. Well 805-A has "silted in" and is only being used for groundwater level data. The tertiary aquifer wells (27, 29, and 1014) and deep production well (MU-1) continue to show background tritium concentrations.

4-48

VEGP GW Wells in PA FIGURE 4.10-1 1400 1200 1000 800 --- LT-1B

-J C.)

- LT-7A a.- LT-12 X* LT-13 600 400 200 0 --

Aug-07 Nov-07 Feb-08 Jun-08 Sep-08 Dec-08 Mar-09 Jul-09 Oct-09 Jan-10 4-49

Existing Water Table Wells (Zeroes are below MDA)

FIGURE 4.10-2 1400 1200 1000

--- 802A 803A 800 805A

(.) 806B a.

-E-808 600 ---- OW-1013

-+--OW-1015

-OW-1004 400 200 0

Aug-07 Nov-07 Feb-08 Jun-08 Sep-08 Dec-08 Mar-09 Jul-09 Oct-09 Jan-10 4-50

New Water Table Wells (Zeroes are below MDA)

FIGURE 4.10-3 1200 1000 800 7 .. '. . R -

- R-2

- R-3

* , --x- R-4

,. 600- to R-5 "I" ' R-6

'--- R-7 400R 200 0

Aug-07 Nov-07 Feb-08 Jun-08 Sep-08 Dec-08 Mar-09 Jul-09 Oct-09 Jan-10 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).

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 EL analyzed 9 samples for 35 parameters in 2009. These analyses included tritium, gross beta and gamma emitting radio-nuclides in different matrices. The attached results indicate all analyses are acceptable for precision and one analysis outside the acceptance limits for accuracy. The activity recovery of Fe-59 in air filter was above the upper acceptance limit for accuracy.

The analysis of Fe-59 is performed by gamma spectroscopy, with the value determined by a weighted average of the three germanium detectors. In a 2005 investigation a positive bias was determined to exist in the analysis based on summing of nuclides in the calibration standard. The detectors are calibrated on a three year geometry rotation. The air filter geometry calibration is scheduled and will be completed in 2010. The 2009 sample will be reanalyzed with the new calibration to verify calibration accuracy.

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 IValue IDeviation EL Analytics (3S) of Variation Deviation Gross Beta 09/17/09 85.00 85.80 1.68 0.48[ 5.21 -0.19 GAMMA ISOTOPIC ANALYSIS OF AN AIR FILTER (pCi/filter)

Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide P Value Deviation EL Analytics (3S) of Variation Deviation Ce- 141 09/17/09 204.10 193.00 8.07 1.08 5.02 1.08 Co-58 09/17/09 75.60 69.90 3.81 0.39 7.23 1.05 Co-60 09/17/09 117.10 113.00 2.15 0.63 3.78 0.92 Cr-51 09/17/09 194.50 155.00 2.1 0.86 13.61 1.49 Cs-134 09/17/09 83.90 86.50 1.48 0.48 3.99 -0.77 Cs-137 09/17/09 142.40 130.00 4.01 0.72 4.46 1.95 Fe-59 09/17/09 131.30 103.00 6.51 0.58 6.86 3.14 Mn-54 09/17/09 160.10 145.00 0.86 0.81 3.44 2.74 Zn-65 09/17/09 176.20 143.00 7.22 0.80 6.35 2.97 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 06/18/09 286.50 284.00 22.86 1.58 8.94 0.10 Co-58 06/18/09 97.40 91.90 3.44 0.51 8.17 0.69 Co-60 06/18/09 326.50 312.00 9.4 1.74 4.73 0.94 Cr-51 06/18/09 415.30 400.00 48.83 2.23 15.87 0.23 Cs-134 06/18/09 178.10 166.00 6.63 0.92 5.65 1.20 Cs-137 06/18/09 205.20 192.00 15.72 1.07 9.03 0.71

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 I Value [Deviation EL Analytics (3S) of Variation Deviation Fe-59 06/18/09 144.10 122.00 3.6 0.68 7.69 1.99 1-131 06/18/09 116.00 102.00 7.01 0.57 9.34 1.29 Mn-54 06/18/09 138.80 137.00 17.49 0.76 13.97 0.09 Zn-65 06/18/09 194.90 175.00 3.54 0.981 8.45 1.21 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 03/19/09 119.10 120.00 9 0.67 9.54 -0.08 Co-58 03/19/09 145.30 151.00 9.04 0.84 8.18 -0.48 Co-60 03/19/09 193.70 180.00 4.54 1.00 4.44 1.60 Cr-51 03/19/09 406.90 387.00 12.63 2.15 9.69 0.50 Cs-134 03/19/09 122.20 119.00 6.96 0.66 7.42 0.35

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 I Deviation EL Analytics (3S) of Variation Deviation Cs-137 03/19/09 152.00 141.00 9.57 0.79 8.05 0.90 Fe-59 03/19/09 142.00 127.00 2.78 0.70 6.68 1.58 1-131 03/19/09 76.10 69.00 3.21 0.38 7.95 1.18 Mn-54 03/19/09 179.10 162.00 3.05 0.90 4.90 1.95 Zn-65 03/19/09 210.40 197.00 4.72 1.10 6.91 0.92 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 06/18/09 96.40 99.10 10.4 0.55 11.94 -0.24

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 2009, there was one instance in which the indicator station readings were statistically discernible from the control station readings. This is discussed in detail below. No discernible radiological impact upon the environment or the public as a consequence of plant discharges to the atmosphere and to the river was established for any other REMP samples.

Cesium-137 was found in vegetation in one of 24 samples at the indicator stations 34.6 pCi/kg-wet) and not found in any of the 12 samples at the control station.

The potential dose to an individual who could receive the highest dose (an adult) was 0.060 mrem in a year. This dose is <1% of the regulatory limit of 15 mrem per year to any organ due to gaseous effluents.

The radiological levels reported in 2009 were low. The REMP trends over the course of time from preoperation to the present are generally decreasing or have remained fairly constant. This supports the conclusion that there is no adverse radiological impact on the environment or to the public as a result of the operation of Plant Vogtle.

6-1

NL-10-0905, Enclosure 3 - Vogtle, Units 1 and 2, Annual Radiological Environmental Operating Report for 2009

Contents

Text

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

6.0 CONCLUSION

Navigation menu

NL-10-0905, Enclosure 3 - Vogtle, Units 1 and 2, Annual Radiological Environmental Operating Report for 2009

Text

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

6.0 CONCLUSION

Navigation menu

Search