ML13120A003

Annual Radiological Environmental Operating Report for the Year 2012

ML13120A003
Person / Time
Site:	Summer
Issue date:	04/23/2013
From:	Lippard G South Carolina Electric & Gas Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13120A003 (46)

Text

George A. Lippard GeneralManager,Nuclear Plant Operations 803.345.4810 April 23, 2013 A SCANA COMPANY Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Enclosed is the South Carolina Electric & Gas Company Annual Radiological Environmental Operating Report as required by Regulatory Guide 4.8 and Section 6.9.1.6 of the Virgil C. Summer Nuclear Station Technical Specifications.

If there are any questions, please contact Ms. Susan B. Reese at (803) 345-4591.

Very truly yours, George A. Lippard SBR/GAL/ts Enclosure c: K. B. Marsh (w/o enclosure) NRC Resident Inspector S. A. Byrne M. Coleman J. B. Archie M. E. Jordan N. S. Cams K. M. Sutton J. H. Hamilton (w/o enclosure) C. D. Stewart J. W. Williams (w/o enclosure) NSRC W. M. Cherry (w/o enclosure) RTS (LTD 312)

V. M. McCree File (818.02-2, RR 8300)

E. A. Brown PRSF (RC-13-0063)

Virgil C.Summer Station

• Post Office Box 88 . Jenkinsville, SC - 29065 . F (803) 345-5209

A SCANA COMPANY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPERATING PERIOD JANUARY 1, 2012 - DECEMBER 31, 2012 April 2013 Prepared by:

Brett Williams Health Physics Specialist Reviewed by: ",X/// Michael Roberts Health Physics Supervisor Approved by:

Moses Coleman Manager Health Physics & Safety Services

EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report describes the V.C. Summer Environmental Monitoring Program and the program results for the calendar year 2012.

Included are the identification of sample locations, descriptions of environmental sampling and type of analysis. Comparisons of present environmental radioactivity levels and pre-operational environmental data, land use census comparisons of doses calculated from environmental measurements, and a summary of environmental radiological sampling results. Quality assurance practices, sampling deviations and unavailable samples are also discussed.

Sampling activities were conducted as prescribed by the Offsite Dose Calculation Manual (ODCM) for V.C. Summer Nuclear Station (VCSNS) and applicable Health Physics Procedures. Required analyses were performed and detection limits met for required samples with exceptions noted. Samples were collected comprising one thousand two hundred seventy three analyses (1,273) performed to compile the data for the 2012 Environmental Report. Supplemental samples comprising two hundred thirty five (235) analyses were performed on some media for additional information. Based on the results from the annual land use census, the current number of sampling sites for V.C. Summer Nuclear Station is sufficient.

Concentrations observed in the environment in 2012 from V.C. Summer related radionuclide concentrations were within the range of concentrations observed in the past.

Review of the data indicated that very low tritium concentration in surface water was the only indicator with VCSNS produced radioactivity. This activity was well below the applicable reporting level requirements of the ODCM. It is therefore concluded that VCSNS operations have no significant radiological impact on the health and safety of the public or the environment.

TABLE OF CONTENTS PAGE INTRODUCTION 1 DESCRIPTION OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2 LAND USE CENSUS 4 MONITORING RESULTS AND DISCUSSION 4 CONCLUSION 7 ii

LIST OF TABLES TABLE PAGE 1 Monitoring Methods for Critical Radiation Exposure 2 Pathways 2 2012 Fission and Activated Corrosion Product Activity in 6 Sediment 3 Required Sampling Site Locations 8 4 Results of the 2012 Land Use Census Verification 11 5 Critical Receptor Evaluation for 2012 12 6 Radiological Environmental Monitoring Program 13 Specifications 7 Supplemental Radiological Environmental Monitoring 18 8 Radiological Environmental Monitoring Program Summary 22 for 2012 9 Radiological Environmental Monitoring Program 28 Preoperational (Baseline) Summary 10 Results of 2012 Environmental Intercomparison Program 33 with Independent Lab, Eckert & Ziegler Analytics, Inc.

11 2012 Environmental Sampling Program Exceptions 35 iii

LIST OF FIGURES FIGURE PAGE 1-1 Control Site Locations (50 mile radius around the 36 Virgil C. Summer Nuclear Station) 1-2 Radiological Monitoring Program Local Indicator Sample 37 Sites (5 mile radius around Virgil C. Summer Nuclear Station) 1-3 Radiological Monitoring Program Local Indicator Sample 38 Sites (1 mile radius around Virgil C. Summer Nuclear Station) 1-4 Radiological Monitoring Program Security Area Ground 39 Water Sites.

1-5 Radiological Monitoring Program Protected Area Ground 40 Water Sites.

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INTRODUCTION Virgil C. Summer Nuclear Station (VCSNS) utilizes a pressurized water reactor rated at 2900 MWt (990 MWe gross). The station is located adjacent to the Monticello Reservoir near Jenkinsville, South Carolina and approximately 26 miles northwest of Columbia. VCSNS achieved initial criticality on October 22, 1982, reached 50% power December 12, 1982 and 100% power June 10, 1983 following steam generator feedwater modifications. Steam generators were replaced in the fall of 1994. During the ninth refuel the plant was uprated to 2900 MWt (990 MWe gross). VCSNS is currently operating in the 2 1 st fuel cycle.

VCSNS is operating in conjunction with the adjacent Fairfield Pump Storage Facility (FPSF) which consists of eight reversible pump-turbine units of 60 MWe capacity each.

During periods of off-peak power demand, base load generating capacity is used to pump water from Parr Reservoir to Monticello Reservoir. Monticello Reservoir has a surface area of approximately 6800 acres and lies about 150 feet above Parr Reservoir whose full pool area is approximately 4400 acres. The pump-turbine units operate in the generating mode to meet peak system loads while Monticello Reservoir also provides condenser cooling water for VCSNS. Cooling water intake and discharge structures are separated by a jetty to ensure adequate circulation within the reservoir.

VCSNS is located in Fairfield County which, along with Newberry County, makes up the principle area within a 10 mile radius of the plant. This area is mainly forest with only about 30% devoted to small farming activities principally producing small grains, feed crops and beef cattle. Significant portions of Lexington and Richland Counties are encompassed within the 20 mile radius of the plant and exhibit similar agricultural activities. Columbia, the state capital, is the only large city within the 50 mile radius of the plant. Small agricultural concerns are predominant, but make up less than 50% of the land area. The main industrial activity is concentrated around Columbia and is generally greater than 20 miles from the VCSNS.

Liquid effluents from VCSNS are released into the Monticello/Parr Reservoirs at two discharge points: the Circulating Water Discharge Canal (CWDC) and the FPSF Penstocks. Non-nuclear drains are released to the CWDC. Effluent from the liquid waste processing system and processed steam generator blowdown are released through the penstocks. Radioactive gaseous effluents from VCSNS are released from two points: the Main Plant Vent and the Reactor Building Purge Exhaust, all considered to be ground level releases.

Radioactive liquid and gaseous releases from the facility and their potential influence on the surrounding biota and man are the primary concern of the Radiological Environmental Monitoring Program at VCSNS. This report summarizes the results of the Radiological Environmental Monitoring Program conducted during 2012. Data trends, control/indicator and preoperational/operational data intercomparisons, and other data interpretations are presented.

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DESCRIPTION OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program is carried out in its entirety by South Carolina Electric and Gas Company. The program has been designed to meet the following general commitments:

1. To analyze selected samples in important anticipated pathways for the qualification and quantification of radionuclides released to the environment surrounding VCSNS.

2. To establish correlations between levels of environmental radioactivity and radioactive effluents from VCSNS operation.

The program utilizes the concepts of control/indicator and preoperational

/operational intercomparisons in order to establish the adequacy of radioactivity source control and to realistically verify the assessment of environmental radioactivity levels and subsequent radiation dose to man.

Sample media and analysis sensitivity requirements have been established to ensure that the maximum dose pathways are monitored and sensitivities represent a small fraction of annual release limits. Effluent dispersion characteristics, demography, hydrology and land use have been considered in selection of environmental sampling locations. These criteria were used to establish both the preoperational and operational phases of the Radiological Environmental Monitoring Program. Elements of the program monitor the impact of gaseous and liquid effluents released from VCSNS.

Specific methods used in monitoring the pathways of these effluents which may lead to radiation exposure of the public, based on existing demography, are summarized below in Table 1. Requirements of the Radiological Environmental Monitoring Program are specified in the VCSNS Offsite Dose Calculation Manual (ODCM). Elements of the program monitor the impact of gaseous and liquid effluents released from VCSNS.

Table 1 - Monitoring Methods for Critical Radiation Exposure Pathways Effluent Release Type I -Exposure Pathway Monitoring Media Gaseous Immersion Dose and other Thermoluminescent Dosimetry (TLD),

External Dose Area Monitoring, Air Sampling, Vegetation (Ingestion) Vegetation and Food Crop Sampling, Milk (Ingestion) Milk Sampling, Grass (Forage)

Sampling Liquid Fish (Ingestion) Fish Sampling, Water & Shoreline Surface Water Sampling, Ground Exposure (Ingestion and Water Sampling, Shoreline and Immersion) Bottom Sediment Sampling, Drinking Water (Ingestion) Drinking Water Sampling 2

Monitoring sites indicative of plant operating conditions are generally located within a 5 mile radius of the plant. Table 6 provides a list of ODCM required sampling locations.

Table 7 provides a list of supplemental sampling locations. Maps showing radiological environmental sampling locations within a radius of approximately 5 miles from VCSNS are presented as Figures 1-2 through 1-5. Figure 1-1 shows monitoring sites at distances greater than 10 miles from the plant. These locations indicate regional fluctuations in background radiation levels.

In addition to preoperational/operational data intercomparisons, controVindicator data intercomparisons are utilized. This is done to assess the probability that any observed abnormal measurement of radioactivity concentration is due to random or regional fluctuations rather than to a true increase in local environmental radioactivity concentration.

Environmental data is gathered through multiple types of sampling and measurements at specific locations. Several multiple sampling combinations are in use around the VCSNS. For example, all air sampling locations serve as environmental dosimetry monitoring locations. At these locations, airborne plant effluents are monitored for gamma immersion dose (noble gases), in addition to air contaminants. Monitoring locations Site 6 (1.0 mi. ESE) and Site 7 (1.0 mi. E) have broadleaf vegetation gardens for monitoring gaseous effluent deposition (ingestion pathway) in the two sectors having the highest deposition coefficients (D/Q) with real potential for exposure. Monitoring location Site 18 (16.5 mi. S) serves as a control location for direct radiation and Site 40 (11.9 mi.

SSE) serves as a control location for garden monitoring.

Liquid effluents are monitored using three different monitoring media (fish, bottom sediment and surface water) at the two most probable affected bodies of water around the plant: Site 21, Parr Reservoir (2.7 mi. SSW) and Site 23, Monticello Reservoir (0.5 mi.

ESE). The control location for liquid effluent comparisons is at Site 22, Neal Shoals (26.0 mi. NNW) on the Broad River.

Quality of analytical measurements is demonstrated by participation in a laboratory intercomparison program. Results of the intercomparison program with an outside vendor and VCSNS Count Room were satisfactory in 2012. The results of each of these quality control checks of the Radiological Environmental Monitoring program verify the technical credibility of analytical data generated and reported by the program.

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LAND USE CENSUS Annually a land use census is performed within a 5 mile radius of VCSNS to verify the adequacy of sample locations. In addition, the location of the maximum exposed individual (MEI) is identified. The results of the land use census performed in 2012 are included in Table 4. A verification of the maximum exposed individual location is presented in Table 5. Identification of the highest offsite dose locations was performed by calculating a hypothetical dose based on predicted VCSNS source term from the Operating License Environmental Report and 2012 meteorological data. Exposure pathways used in the analysis were those identified during the land use census.

The location and pathway presently used in the ODCM for offsite organ dose calculations (E 1.1 miles - residence/garden) was found to have a calculated dose of 2.94E+0 mrem/year. In addition, the ODCM required environmental gardens (ESE 1.0 and E 1.0 mile) were found to have a calculated dose of 2.17E+0 and 3.73E+0 mrem/year.

There were no milking animals or dairy activity found within 5 kilometers of VCSNS.

Therefore, changes to the ODCM gaseous effluent calculations or garden sample locations are not indicated.

MONITORING RESULTS AND DISCUSSION The results of the Radiological Environmental Monitoring Program for 2012 are summarized in Table 8. For comparison, preoperational data are summarized in Table 9.

The Radiological Environmental Program attained a program compliance rate of approximately 98.3%. A listing of program exceptions and their respective causes are included in Table 11. Analysis of the impact of these omissions verified that program quality has not been affected.

Corbicula harvest for possible human consumption was observed in Lake Monticello in 2005. Since that time Corbicula analysis has been incorporated in the Supplemental Sampling Program. Samples were collected and analyzed for gamma emitting isotopes.

No measurable gamma emitting nuclides were detected above minimum detectable activity (MDA).

Gross beta activities measured in air particulate samples collected at indicator locations around VCSNS were consistent with preoperational levels and not statistically different from control locations. The highest site-specific mean activity (2.27E-2 pCi/m 3) was measured at indicator location Site 7 (Lab Garden 1.0 mi. E). The results indicate that the operation of VCSNS has not contributed to detectable increases of airborne gross beta activity in the environment.

Gamma spectroscopy measurements of composited air particulate samples and activated charcoal cartridges support the gross beta activity trend. Only natural background activities were detected. The highest MDA levels for 134Cs, 137Cs and 1311 were 2.33E-3, 2.02E-3 and 2.05E-2 pCi/m 3 , respectively. The average maximum results support the gaseous effluent release data reported in the 2012 Annual Effluent and Waste Disposal Reports for VCSNS. No measurable iodine or particulate were released. 99.4% of the required indicator/control air samples were collected.

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Environmental dosimetry measurements did not differ significantly from preoperational measurements. Indicator and control dosimetry measurements also showed no appreciable differences. Comparison with other operational years shows no statistically significant difference. Monitoring location Site 4 (Fairfield Hydro 1.2 mi. WNW) was the indicator location showing the highest mean exposure rate of 1.16E+1 pR/hr. This is similar to the 2011 value of 1.14E+1 ptR/hr and consistent with the highest mean exposure rate of 1.40 E+1 pR/hr measured during the preoperational period. 98.1% of the required TLDs were collected.

Gamma spectroscopy measurements of surface water samples did not indicate the presence of activated corrosion or fission products above the respective MDA for indicator sites. Tritium analysis indicated the presence of tritium in four indicator samples. Site 21 (Parr Reservoir 2.7 mi. SSW) had concentrations of 8.90E+2, and 6.93E+2 pCi/I. Site 23 (Discharge Canal Monticello Reservoir 0.5 mi. ESE) had tritium concentrations of 7.48E+2, and 7.47E+2 pCi/I. All concentrations were well below the reporting limit. 100% of indicator/control surface water samples were collected.

Gamma spectroscopy measurements of the ODCM required ground water samples did not indicate the presence of activated corrosion or fission products above the respective MDAs. Tritium analysis did not indicate the presence of tritium above MDA.

90.3% of indicator/control ground water samples were collected.

Gamma spectroscopy measurements of drinking water samples collected from the Jenkinsville water supply and Site 17 (Columbia Water Works 25.0 mi. SE) did not indicate the presence of activated corrosion or fission product activity above the respective MDAs.

Tritium analysis indicated the presence of tritium in three samples from Site 17 (Columbia Water Works 25.0 mi. SE) at concentrations of 8.09E+2, 6.86E+2, and 6.32E+2 pCi/I.

These concentrations are below the required LLD. The highest indicator and control site-specific gross beta activity was measured at Site 39 (Lake Murray Water Treatment Facility 14.0 mi. SSE) at a level of 4.74E+0 pCi/I. 100% of indicator/control drinking water samples were collected.

There were no milk samples collected in 2012. Milk sampling is required to be performed at the three highest dose locations within 5 kilometers of the plant or at 5 to 8 kilometers of the plant, if doses are calculated to be greater than 1 mrem per year.

Presently there are no locations meeting this criteria for indicator dairies. The closest dairy is approximately 8 kilometers from the plant (see Table 4). Milk samples will be obtained from this dairy if gaseous releases from the plant exceed 5% of quarterly organ dose limits or radionuclides (attributed to the operation of VCSNS) are detected in broadleaf vegetation, grass or air samples at concentrations greater than required LLDs.

Gamma spectroscopy measurement of supplemental grass samples collected indicated 137 Cs in 11 of 12 samples at Site 2 (transmission line 1.2 mi. SW) at concentrations ranging from 1.18E+1 to 1.20E+2 pCi/kg. The maximum preoperational control activity was 3.40E+2 pCi/kg. 100% of indicator/control supplemental grass samples were collected.

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Gamma spectroscopy measurements of the broadleaf samples collected did not indicate the presence of activated corrosion or fission products above the respective MDAs. All of the required indicator/control broadleaf samples were collected.

Gamma spectroscopy measurements of all non-leafy (other vegetation) supplemental samples collected did not indicate the presence of activated corrosion or fission products above the respective MDA.

Gamma spectroscopy measurements of the fish samples collected did not indicate the presence of activated corrosion or fission products above the respective MDAs. All of the required indicator/control fish samples were collected.

Gamma spectroscopy measurements of sediment samples indicated the detection of 13 7Cs in 2 of 4 indicator samples. At Site 21 (Parr Res. 2.7 mi. SSW) 137 Cs at a concentration of 2.35E+1 and 6.77E+1 pCi/kg was detected. 137 Cs was detected in 2 of 2 control samples taken at Site 22 (Neal Shoals 26 mi. NNW) at a concentration of 1.63E+2 and 1.64E+1 pCi/kg. All required indicator/control sediment samples were collected.

Table 2 - 2012 Fission and Activated Corrosion Product Activity in Sediment Corresponding Calculated Location Radionuclide Activity (pCilkg) Annual Dose Equivalent (mrem/yr)

Total Body Maximum Mean Maximum Mean Parr 137 Reservoir Cs 6.77E+1 4.56E+1 5.69E-3 3.83E-3 6

CONCLUSION As in previous years of VCSNS operation, the presence of fission product activity attributed to residual fallout from atmospheric weapons testing and the Chernobyl accident were detected in environmental media including sediment and grass.

No detectable fission or activation product activity attributed to VCSNS operations was observed in environmental media with the exception of:

• Tritium in surface water samples at Site 21 (Parr Res. 2.7 mi. SSW) and surface water samples at Site 23 (Discharge Canal Monticello Reservoir .5 mi. ESE).

" Cs-137 in one sediment sample Site 21 (Parr Reservoir 2.7 mi. SSW).

The dose calculated for the maximum exposed individual will not result in observable effect on the ecosystem or general public. The results of the Radiological Environmental Monitoring Program, therefore, substantiate the continuing adequacy of source control at VCSNS and conformance of station operation to 10 CFR 50, Appendix I design objectives.

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Table 3 - Required Sampling Site Locations Site Description Distance Direction2 Sample Type(s) 3 No. (Miles) 1 Borrow Pit 1.2 179.8S DQ 2 Transmission Line 1.1 225.0 SW AP, RI, DQ 3 Firing Range 1.2 270.0 W DQ 4 Fairfield Hydro 1.2 289.5 WNW DQ 5 Transmission Line Entrance 0.9 144.0 SE DQ 6 Environmental Lab Garden 1.0 111.0 ESE AP,RI,GA,DQ,GW 7 Environmental Lab Garden 1.0 97.8 E AP,RI,DQ, GA 8 Monticello Res. S of Rd 224 1.5 62.0 ENE DQ 9 Ball Park 2.3 41.6 NE DQ 10 Meteorological Tower #2 2.5 25.5 NNE DQ 12 Old Hwy 99 4.2 349.4N DQ 13 North Dam 2.9 333.0 NNW DQ 14 Dairy (ShealXj) 4 6.5 277.0 W MK,GR 16 Dairy (Parr) 20.0 275.5 W MK,GR 16a TLD Location 28.0 278.6W DQ 17 Columbia Water Works 25.0 144.0 SE AP,RI,DQ,DW 18 Pine Island Club 16.5 165.0 S DQ 19 Residence/Little Saluda 21.0 224.0 SSW DQ 20 Residence/Whitmire 22.0 309.5 NW DQ 21 Parr Reservoir 2.7 199.5 SSW SW,FH,BS 22 Neal Shoals 26.0 343.1 NNW SW,FH,BS 23 Discharge Canal (Mont, Res.) 0.5 104.5 ESE SW,FH,BS 26 On Site Well (P2) 460 Ft 270.0 W GW 27 On Site Well (P5) 510 Ft 180.0 S GW 28 New Nuclear Deployment5 2.6 170.2 SSE DW 29 Trans. Line WSW of VCSNS 1.0 260.6 WSW DQ 30 Oak Tree North of Borrow Pitb 1.0 / 0.5 196.2 SSW DQ, AP, RI 31 McCrorey-Liston School 6.6 11.5 NNE DQ 32 Clark Bridge Road and Brooks Drive 4.6 24.0 NNE DQ 33 Rd 48 near Hwy 213 4.2 68.0 ENE DQ 34 Rd 419 North of Hwy 60 4.9 111.0 ESE DQ 35 Glenn's Bridge Road 4.6 132.0 SE DQ 36 Woods at Jenkinsville Post Office 3.1 151.0 SSE DQ 37 Residence 4.9 304.8 NW DQ 39 Lake Murray Water Treatment Facility 14.0 168.0 SSE DW 40 Emergency Operations Facility' 11.9 157.0 SSE GA, GR 8

Table 3 (cont) - Required Sampling Site Locations Site Description Distance Direction 2 Sample Type(s) 3 No. (Miles) 41 Below Catwalk at Trestle 3.8 182.0 S DQ 42 Broad River Rd (Peak Residence) 3.8 198.0 SSW DQ 43 Hwy 176 and Rd 435 5.2 236.0 SW DQ 44 Rd 28 at Cannon's Creek 2.8 256.6 WSW DQ 45 Rd 33 at Pomaria 5.8 253.2 WSW DQ 46 Rd 28 at Heller's Creek 3.7 291.5 WNW DQ 47 Fairfield Tailrace 1.0 316.0 NW DQ 52 Monticello (Rd 11) 3.8 13.0 NNE DQ 53 Rd 359 3.0 46.5 NE DQ 54 Jenkinsville School 1.7 72.5 ENE DQ 55 St. Barnabas Church 2.8 91.5 E DQ 56 Old Jenkinsville Dinner 2.0 144.0 SE DQ 58 Residence 2.5 157.0 SSE DQ 59 New Nuclear Deployment 5 2.6 170.2 SSE DQ, GW 60 Rd 98 near Rd 28 3.5 274.6 W DQ 101 Remediation Well (B-2) 300 Ft NNW GW 102 Remediation Well (B-6) 400 Ft NE GW 103 Remediation Well (DW-13) 80 Ft NE GW 106 Remediation Well (DW-7) 250 Ft SE GW 108 Remediation Well (DW-19) 250 Ft W GW 110 Remediation Well (B-36) 300 Ft NW GW 112 NPDES Well (GW-9) 0.36 331 SSE GW 113 NPDES Well (GW-12) 0.33 332 SSE GW 114 NPDESWeIl(GW-13A) 0.39 317 SE GW 9

Table 3 (cont) - Required Sampling Site Locations Footnotes

1. Distance given is the distance between the site location and the VCSNS reactor containment building.

2. Direction given in degrees from true north-south line through center of reactor containment building.

3. Sample Types:

AP = Air Particulate GW = Ground Water GA = Garden RI = Air Radioiodine DW = Drinking Water FH = Fish DQ = Quarterly TLD MK = Milk BS = Bottom Sediment SW = Surface Water GR = Grass (Forage)

4. Sites 14 and 16 are not presently in use. If conditions change, requiring a renewal of dairy sampling these sites will be reactivated.

5. Site 28 for drinking water and Site 59 for quarterly TLD measurements are co-located at the location of the SCE&G New Nuclear Deployment.

6. Site 30 consists of two locations in the same sector. The air sampler is located 0.5 miles from the reactor to support construction of a new facility. The TLD is located at the site boundary in the same sector.

7. Site 40 (11.9 mi. SSE) serves as a control location for garden monitoring which is the location of the Station's Emergency Operating Facility.

8. Sites 100 (B-i), 104 (B-9), 105 (DW-11), 107 (B-28), 109 (B-35), 111 (GW-8), and 115 (GW-15) have been removed from required ground water sampling due to site construction activities and hydrogeological evaluations.

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Table 4 - Results of the 2012 Land Use Census Verification No. No.

Sector Nearest Residence Miles Nearest Garden Miles Nearest Cattle Milked Miles Nearest Goat Milked Miles N P. Oliver 3.73 NNE Thomas K. Crumblin 2.9 Eddie Robinson 3.99 Eddie Robinson 0 3.99 NE Gregrey.Guinyard Jr. 1.55 Edna Richards 3.21 ENE Essie Gregg 1.56 Essie Mae Glenn 1.68 E Lynn Mincy 1.2 ESE Carrie Lee Martin 1.1 James Pearson 1.36 SE Mary White 1.44 Mary White 1.44 Sim Roberts 0 4.7 SSE Ronnie Mann 2.39 Ronnie Mann 2.39 S Kelly Boulware 3.56 Kelly Boulware 3.56 Shirley Counts 0 5 SSW Nick Bates 3.11 Nora Wicker 3.77 Joe Smith 0 4.73 SW Marvin Miller 3.3 Marvin Miller 3.3 WSW Ron Hope 2.9 Steve All 4.83 KenNirg Graham (*) 0 4.98 Steve All 10 4.83 W Jerry Cassado 2.55 Marion Livingston 2.8 Marion Livingston 0 2 W KenNirg Graham (*) 90 5 WNW Unknown Residence 2.53 Ronnie Leitzey 4.72 Ronnie Leitzey 1 4.15 Ronnie Leitzey 15 .4.15 NW Louise Workman 3.9 NNW Frank March 2.9 Frank March 2.9 Frank March 0 2.9

(*) Keneth and Virgil Graham cows grazed in the W and WSW 11

Table 5 Critical Receptor Evaluation for 2012 MILES PATHWAY X/Q D/Q DOSE*

NAME SECTOR

_mRem/y P. Oliver N 3.73 Res 2.30E-07 6.50E-10 8.57E-03 Thomas K. Crumblin NNE 2.9 Res 4.60E-07 1.50E-09 1.72E-02 Eddie Robinson NNE 3.99 B,Gar 2.40E-07 7.10E-10 2.57E-01 Gregrey Guinyard Jr. NE 1.55 Res 1.90E-06 6.90E-09 7.16E-02 Edna Richards NE 3.21 ResGar 4.10E-07 1.20E-09 3.30E-01 Bessie Gregg ENE 1.56 Res 1.70E-06 5.90E-09 6.39E-02 1 Essie Mae Glenn ENE 1.68 ResGar 1.40E-06 4.90E-09 1.32E+00

- Garden-7 E 1 ResGar 3.60E-06 1.40E-08 3.73E+00 Lynn Mincy E 1.2 Res 2.30E-06 9.OOE-09 8.69E-02 Garden-6 ESE 1 ResGar 2.20E-06 8.10E-09 2.17E+00 Carrie Lee Martin ESE 1.1 Res 1.70E-06 6.30E-09 6.41 E-02 James Pearson ESE 1.36 ResGar 1.1OE-06 3.70E-09 1.OOE+00 Mary White SE 1.44 ResGar 6.OOE-07 2.60E-09 6.85E-01 Sim Roberts SE 4.7 Res,Gar,B 4.80E-08 1.60E-10 5.93E-02 Ronnie Mann SSE 2.39 ResGar 1.30E-07 6.10E-10 1.60E-01 Kelly Boulware S 3.56 ResGar 8.OOE-08 4.40E-10 1.14E-01 Shirley Counts S 5 Res,Gar,B 4.OOE-08 2.10E-10 7.54E-02 NND Construction Site SSW 0.49 Res 8.1OE-06 6.60E-08 3.24E-01 Nick Bates SSW 3.11 Res 1.40E-07 9.80E-10 5.51E-03 Nora Wicker SSW 3.77 ResGar 9.40E-08 6.40E-10 1.63E-01 Joe Smith SSW 4.73 Res,B 5.90E-08 3.90E-10 4.11E-02 Marvin Miller SW 3.3 Res,Gar 9.20E-08 7.80E-10 1.97E-01 Ron Hope WSW 2.9 Res 8.50E-08 6.50E-10 3.37E-03 Steve All WSW 4.83 Res,Gar,G 2.90E-08 2.10E-10 5.59E-02 KenNirg Graham WSW 4.98 B 2.70E-08 1.90E-10 1.88E-02 Jerry Cassado W 2.55 Res 1.40E-07 7.20E-10 5.38E-03 Marion Livingston W 2 B 2.40E-07 1.30E-09 1.30E-01 Marion Livingston W 2.8 ResGar 1.10E-07 5.80E-10 1.50E-01 Marion Livingston W 2 & 2.8 Res,Gar,B BOTH BOTH 2.80E-01 KenNirg Graham W 5 Res,GarB,C/M 3.40E-08 1.60E-10 8.65E-02 Unknown Resident WNW 2.53 Res 1.1OE-07 4.60E-10 4.17E-03 Ronnie Leitzsey WNW 4.15 C/M,B,G/M,G 3.80E-08 1.50E-10 1.45E-01 Ronnie Leitzsey WNW 4.72 ResGar 2.90E-08. 1.10E-10 2.94E-02 Ronnie Leitzsey WNW 4.15 & 4.72 Res,Gar,C/M,B,G/M,G BOTH BOTH 1.79E-01 Louise Workman NW 3.9 Res 9.70E-08 3.30E-10 3.64E-03 Frank March NNW 2.9 Res,Gar,B 3.70E-07 1.10E-09 4.12E-01 ODCM ORGAN DOSE E- 1.1 ResGar 2.90E-06 1.10E-08 2.94E+00 Pathway Res = Residence B = Beef G = Goat Gar = Garden C/M = Cow/Milk(Infant) G/M = Goat/Milk(Infant)

Footnotes:

1 Maximum exposed individual.

• Hypothetical dose based on Operating License Environmental Report Source Term.

• • ODCM required environmental gardens.

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Table 6 - Radiological Environmental Monitoring Program Specifications Exposure Criteria for Selection of Sampling and Collection Sample Type & Frequency of Pathway and/or Sample Number & Location Frequency Location Analysis Sample i____________________ iiI AIRBORNE:

I. Particulate A) 3 Indicator samples to be Continuous sampler operation 2 Gross beta following filter taken at locations (in with weekly collection. 7 change; Quarterly different sectors) beyond 30 composite (by location) but as close to the for gamma isotopic.

exclusion boundary as practicable where the highest offsite sector ground level concentrations are anticipated.2 B) 1 Indicator sample to be Continuous sampler operation 6 Gross beta following filter taken in the sector beyond with weekly collection, change; Quarterly but as close to the composite (by location) exclusion boundary as for gamma isotopic.

practicable corresponding to the residence having the highest anticipated offsite ground level concentration or dose.2 C) 1 Indicator sample to be Continuous sampler operation N/A Gross beta following filter taken at the location of one with weekly collection. change; Quarterly of the dairies being composite (by location) sampled meeting the for gamma isotopic.

criteria of VII(A).' 4 D) 1 Control sample to be Continuous sampler operation 17 Gross beta following filter taken at a location at least with weekly collection. change; Quarterly 10 air miles from the site composite (by location) and not in the most 2 for gamma isotopic.

prevalent wind directions.

I1.Radioiodine A) 3 Indicator samples to be Continuous sampler operation 2 Gamma Isotopic for taken at two locations as with weekly canister collection. 7 Iodine 131 weekly.

given in I(A) above. 30 B) 1 Indicator sample to be Continuous sampler operation 6 Gamma Isotopic for taken at the location as with weekly canister collection. Iodine 131 weekly.

given in I(B) above.

C) 1 Indicator sample to be Continuous sampler operation N/A Gamma Isotopic for taken at the location as with weekly canister collection. Iodine 131 weekly.

given in I(C) above.

D) 1 Control sample to be Continuous sampler operation 17 Gamma Isotopic for taken at a location similar with weekly canister collection. Iodine 131 weekly.

in nature to I(D) above.

13

Exposure Criteria for Selection of Sampling and Collection Sample Type & Frequency of Pathway and/or Sample Number & Location Frequency Location Analysis Sample _______________________.1__________

Ill. Direct A) 13 Indicator stations to Monthly or quarterly 1,2,3,4,5,6, Gamma dose monthly or form and inner ring of exchange5 7, two or more 7,8,9,10,29, quarterly.

stations in the 13 dosimeters at each location. 30,47 accessible sectors within 1 to 2 miles of the plant.

B) 16 indicator stations to form Monthly or quarterly 12,13,32,33, Gamma dose monthly or an outer ring of stations in exchange5 '7 two or more 34,35,36,37, quarterly.

the 16 accessible sectors dosimeters at each location. 41,42,43,44, within 3 to 5 miles of the 46,53,55,60 plant.

C) 11 Stations to be placed in Quarterly exchange'; two or 16,17,18,19, Gamma dose quarterly.

special interest areas such more dosimeters at each 20,31,45,52, as population centers, location. 54,56,58 nearby residences, schools and in 4 or 5 areas to serve as controls.

WATERBORNE IV. Surface A) 1 Indicator sample Time composite samples6 with 213 Gamma isotopic monthly Water downstream to be taken at collection every month.5 with quarterly composite a location which allows for (by location) to be mixing a dilution in the analyzed for tritium.7 ultimate receiving river.

6 B) 1 Control sample to be Time composite samples with 223 Gamma isotopic monthly 5

taken at a location on the collection every month. with quarterly composite (by location) to be 7 receiving river sufficiently analyzed for tritium.

far upstream such that no effects of pumped storage operation are anticipated.

6 C) 1 Indicator sample to be Time composite samples with 233 Gamma isotopic monthly 5

taken in the upper reservoir collection every month. with quarterly composite of the pumped storage (by location) to be 7 facility at the plant analyzed for tritium.

discharge canal.

V. Ground Water A) 15 Indicator samples to be Quarterly grab sampling.7 6, 26, 27, Gamma isotopic and taken within the exclusion 101-103, tritium analyses boundary and in the 106, quarterly.7 direction of potentially 108-110, affected ground water 112-114 supplies.

B) 1 Control sample from Quarterly grab sampling.7 59 Gamma isotopic and unaffected location. tritium analyses quarterly.7 14

Exposure Criteria for Selection of Sampling and Collection Sample Type & Frequency of Pathway and/or Sample Number & Location Frequency Location Analysis Sample SampleNumber_&_Location Fe ncLo io VI. Drinking A) 1 Indicator sample from a Monthly grab sampling.5 28 Monthly 5 gamma isotopic Water nearby public ground water and gross beta analyses supply source. and quarterly 7 composite for tritium analyses.

B) 1 Indicator (finished water) Monthly composite sampling. 17 Monthly 5 gamma isotopic sample from the nearest and gross beta analyses downstream water supply. and quarterly 7 composite for tritium analyses.

C) 1 Control (finished water) Monthly composite sampling. 39 Monthly 5 gamma isotopic sample from an unaffected and gross beta analyses water supply. and quarterly 7 composite for tritium analyses.

INGESTION:

VII. Milk 4 A) Samples from milking Semimonthly when animals To be Gamma isotopic and I-animals in 3 locations are on pasture 8, monthly other supplied 131 analysis within 5 km having the times.5 when milk semimonthly8 when highest dose potential. If animals are animals are on pasture, there are none then 1 found in monthly other times.5 sample from milking accordance animals in each of 3 areas with criteria between 5 to 8 km distance VII.A.

where doses are calculated to be greater than 1 mrem per year.1' B) 1 Control sample to be Semimonthly when animals 16 Gamma isotopic and I-taken at the location of a are on pasture 8' monthly other 131 analysis dairy > 20 miles distance times."' semimonthly8 when and not in the most animals are on pasture, prevalent wind direction. 2 monthly other times.5 C) 1 Indicator grass (forage) Monthly when available.5 To be Gamma isotopic.

sample to be taken at the supplied location of one of the when milk dairies being sampled animals are meeting the criteria of found in VII(A),above, when animals accordance are on pasture. with criteria VII.A.

Monthly when available.5 1 D) 1 Control grass (forage) 16 Gamma isotopic.

sample to be taken at the location of VII(B) above.

15

Exposure Criteria for Selection of Sampling and Collection Sample Type & Frequency of Pathway and/or Sample Number & Location Frequency Location Analysis Sample J 5

VIII. Food A) 2 Indicator samples of Monthly when available. 6 Gamma isotopic on edible Products broadleaf vegetation grown 7 portion.

in the 2 nearest offsite location of highest calculated annual average ground level D/Q if milk sampling is not performed within 3 km or if milk sampling is not performed at a location within 5-8 km where the doses are calculated to be greater than 1 mrem/yr. 10 5

B) 1 Control sample for the Monthly when available. 40 Gamma isotopic on edible same foods taken at least portion.

10 miles distance and not in the most prevalent wind direction if milk sampling is not performed within 3 km or if milk sampling is not performed at a location within 5 to 8 km where the doses are calculated to be 10 greater than 1 mrem/yr.

IX. Fish A) 1 Indicator sample to be Semiannual9 collection.' 233 Gamma isotopic on edible 9

taken at a location in the portions semiannually.

upper reservoir.

9 B) 1 Indicator sample to be Semiannual collection.' 21' Gamma isotopic on edible taken at a location in the portions semiannually.9 lower reservoir.

C) 1 Control sample to be Semiannual" collection.' 22' Gamma isotopic on edible 9

taken at a location on the portions semiannually.

receiving river sufficiently far upstream such that no effects of pumped storage operation are anticipated.

AQUATIC:

X. Sediment A) 1 Indicator sample to be Semiannual grab sample.9 233 Gamma isotopic.

taken at a location in the upper reservoir.

9 B) 1 Indicator sample to be Semiannual grab sample. 213 Gamma isotopic.

taken on or near the shoreline of the lower reservoir.

C) 1 Control sample to be Semiannual grab sample.9 22' Gamma isotopic.

taken at a location on the receiving river sufficiently far upstream such that no effects of pumped storage operation are anticipated.

16

Table 6 (cont) - Radiological Environmental Monitoring Program Specifications FOOTNOTES

1. Fish include 3 groups (Bass, Bream/Crappie, Catfish/Carp.)

2. Sample site locations are based on 5-year average meteorological analysis.

3. Though generalized areas are noted for simplicity of sample site enumeration, airborne, water and sediment sampling is done at the same location, whereas biological sampling sites are generalized areas in order to reasonably assure availability of samples.

4. Milking animal and garden survey results will be analyzed annually. If the survey should indicate new activity the owners shall be contacted with regard to a contract for supplying sufficient samples. If contractual arrangements can be made, site(s) will be added for additional milk sampling up to a total of three Indicator locations.

5. Not to exceed 35 days.

6. Time composite samples are samples which are collected with equipment capable of collecting an aliquot at time intervals which are short relative to the compositing period.

7. At least once per 100 days.

8. At least once per 18 days.

9. At least once per 200 days.

10. The dose shall be calculated for the maximum organ and age group, using the guidance/methodology contained in Regulatory Guide 1.109, Rev. 1 and the parameters particular to the site.

11. Milk and forage sampling at the control location is only required when locations meeting the criteria of VII(A) are being sampled.

17

Table 7 - Supplemental Radiological Environmental Monitoring Exposure Pathway Criteria for Selection of Sampling and Sample Type & Frequency of and/or Sample Sample Number & Location Collection Frequency Location Analysis AIRBORNE:

S-I. Particulate A) 1 Indicator sample Continuous sampler 8 Gross beta following monitoring the nearest operation with weekly filter change; Monthly community with the highest collection. Composite (by anticipated dose or ground location) for gamma level concentration. isotopic.

S-Il. Radioiodine A) 1 Indicator sample to be Continuous sampler 8 Gamma isotopic for I-taken from the location of operation with weekly 131 weekly.

S-1 (A) above, collection.

S-Ill. Direct A) 5 stations to be placed Quarterly exchange 7 ; two 61,62,63, Gamma dose within the exclusion or more dosimeters at 68 & 99 quarterly.

boundary. each location.

B) 2 stations to be placed Quarterly exchange7 ; two 94,97 Gamma dose around VCSNS sludge or more dosimeters at quarterly.

lagoons. each location.

WATERBORNE:

S-IV. Surface A) 1 indicator sample to be Composite samples with 77 Gamma isotopic and Water taken of the combined monthly collection. 13 ' 5 tritium.

wastewater discharge.

B) 1 Indicator sample taken at Daily sample with 72,73 Gamma isotopic and each storm drain outfall. monthly composite. tritium.

S-VI. Drinking A) 1 Indicator (finished water) Quarterly. 99 Quarterly gamma Water sample to be taken on site. isotopic, gross beta and tritium analysis.

B) 1 Indicator (finished water) Quarterly. 31 Quarterly gamma sample of public system. isotopic, gross beta and tritium analysis.

18

Exposure Pathway Criteria for Selection of Sampling and Sample Type & Frequency of and/or Sample Sample Number & Location j[ Collection Frequency Location Analysis INGESTION:

S-VII. Milk 4 A) 1 Sample from one of the Biweeklygrab 14 Gamma isotopic and I-nearest affected dairies at sample.U.14,+ 131 analysis biweekly.

or beyond 5 miles.

B) 1 Control sample to be Biweekl X.rab 16 Gamma isotopic and I-taken at the location of a sample. 131 analysis biweekly.

dairy greater than 20 miles distance and not in the most prevalent wind direction.

C) 1 Indicator grass (forage) Monthly when 14 Gamma isotopic.

sample to be taken at the available.14 location of S-VII(A) above.

S-V. Milk 4 D) 1 Control grass (forage) Monthly when 16 Gamma isotopic.

sample to be taken at the available. 14 location of S-VII(B) above.

E) 2 Indicator grass (forage) Monthly when available. 2,7 Gamma isotopic.

samples to be taken at 2 of the locations beyond but as close to the exclusion boundary as practical where the highest offsite sectorial ground level concentrations are anticipated.

F) 1 Control grass (forage) Monthly when available. 18 Gamma isotopic.

sample to be used for routine monitoring along with S-VII(E) above.

S-VIII. Food A) 1 Indicator sample of Annually during growing 6,7 Gamma isotopic on Products various types of foods season. 1 edible portion.

grown in the area surrounding the plant (root, fruit, grain).

B) 1 Control sample of various Annually during growing 18,40 Gamma isotopic on types of foods grown. (root, season."1 edible portion.

fruit, grain).

C) 1 Indicator sample of edible Corbicula portions. Semiannual. 23 Gamma isotopic.

19

Exposure Pathway Criteria for Selection of Sampling and Sample Type & Frequency of and/or Sample Sample Number & Location Collection Frequency Location Analysis S-IX. Sediment/ A) 1 Indicator sample from Semiannually. 72,73 Gamma isotopic.

Sludge each storm drain outfall.

B) 3 Indicator sludge Semiannually. On site Gamma isotopic.

samples taken at sludge lagoons 006A, 006B &

008.

S-X. Ground Water A) 9 Indicator samples to be taken Quarterly grab sampling. 107,111, Gamma isotopic and within the exclusion boundary 115 -121 tritium analyses and in the direction of potentially quarterly. 7 affected ground water supplies.

20

Table 7 (cont) - Supplemental Radiological Environmental Monitoring FOOTNOTES

1. Reserved for future use.

2. Reserved for future use.

3. Reserved for future use.

4. Milking animal and garden survey results will be analyzed annually. If the survey should indicate new activity the owners shall be contacted with regard to a contract for supplying sufficient samples. If contractual arrangements can be made, site(s) will be added for additional milk sampling up to a total of 3 Indicator locations.

5. Not to exceed 35 days.

6. Reserved for future use.

7. At least once per 100 days.

8. At least once per 18 days.

9. At least once per 200 days.

10. Reserved for future use.

11. At least once per 400 days.

12. Reserved for future use.

13. Weekly, when circulating water is not operational.

14. Milk and grass (forage) sampling is not required unless VCSNS gaseous releases exceed 5% of quarterly organ dose limits or radionuclides (attributed to VCSNS operation) are detected in broadleaf vegetation, grass or air samples at concentrations greater than required LLD. Sampling should continue for two months after plant releases are reduced to less than trigger levels and milk contamination levels have returned to background levels.

+ The ODCM requires semimonthly sampling when animals are on pasture, monthly at other times.

21

Table 8 - Radiological Environmental Monitoring Program Summary for 2012 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine Pathway Sampled Number of of Detection 2 Mean 3 (#/total #) Name Mean 3 (#/total #) Mean 3 (#/total #) Reported4 (Unit of Analyses Actual (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed' (Max.) (Range) _(Range)_Measurements Air Particulate Gross Beta 6.06E-3 2.20E-2 (258/258) Site 7, Environmental 2.27E-2 (52/52) 1.97E-2 (50/52) 0 (pCi/m 3) (310) (1.OE-2) (1.01 E-2 to 4.15E-2) Lab Garden, (1.16E-2 to 3.80E-2) (8.60E-3 to 3.54E-2)

(1.0 mi. E _

Gamma Spec (72) 104Cs 2.33E-3 All < LLD All < LLD 0 (5.OE-2)

Cs 2.02E-3 All < LLD All < LLD 0 (6.OE-2) I I I Air Radioiodine 1Jil(310) 2.05E-2 All < LLD All < LLD 0 (pCi/m )

3 (7.0E-2) I I Direct (TLD)5 Gamma(134) 8.43E+0 (116/116) Site 4, Fairfield 1.16E+1 (4/4) 8.30E+0 (18/20) 0 (jiR/hr) Quarterly N/A (5.50E+O to 1.18E+1) Hydro, (1.2 mi. WNW) (1.16E+1 to 1.17E+1) (5.80+0 to 1.18E+1)

Gamma(23) 9.03E+0 (23/24) Site 52, Monticello Rt. 1.18E+1 (4/4) N/A 0 Special Interest N/A (5.26E+O to 1.22E+1) . 11, (3.8 mi. NNE) (1.15E+1 to 1.22E+1)

Surface Water 3H (36) 5.30+2 7.70E+2 (4/24) Site 21, Parr Res., 7.92E+2 (2/12) All < LLD 0 (pCi/I) (2.OE+3) 6.93E+2 to 8.90E+2 (2.7 mi. SSW) 6.93E+2 to 8.90E+2 Gamma Spec(36) 4Mn 2.33E+0 All < LLD All < LLD 0

_ _ _ _ _(1.5E+1) 2.46E+0 All < LLD All < LLD 0 (1.5E+1) týFe 5.84E+0 All < LLD All < LLD 0 buco (3.0E+1) bUCo 2.48E+0 All < LLD All < LLD 0 (1.5E+1) bbZn 4.71 E+0 All < LLD All < LLD 0 (3.OE+1) 9bZr 4.16E+0 All < LLD All < LLD 0 (3.OE+l) 9Nb 2.91 E+0 All < LLD All < LLD 0 1 4 (1.5E+1) 3 Cs 2.06E+0 All < LLD All < LLD 0 (1.5E+1) 22

Table 8 (cont.) - Radiological Environmental Monitoring Program Summary for 2012 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine4 Pathway Number of of Mean 3 (#/total #) Name Mean 3 (#/total #) Mean 3 (#/total #) Reported Sampled (Unit of Analyses Detection2 (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed' Actual (Max.)

1 Surface Water *Cs 2.22E+O All < LLD All < LLD 0 (Continued) (1.8E+1) 14uBa 1.36E+1 All < LLD All < LLD 0 (6.OE+1)

-4 ULa 6.26E+0 All < LLD All < LLD 0 (1.5E+1)

Ground Water 3H (56) 5.30E+2 All < LLD All < LLD 0 (pCi/I) 2.OOE+3 Gamma Spec (56)

'Mn 7.88E+O All < LLD All < LLD 0 (1.5E+1) bUCo 8.04E+O All < LLD All < LLD 0 (1.5E+1)

• Fe 1.46E+1 All < LLD All < LLD 0 (3.OE+1) bUCo 9.62E+0 All < LLD All < LLD 0 (1.5E+1) bbZn 1.99E+1 All < LLD All < LLD 0 (3.OE+1)

'Zr 1.21E+1 All < LLD All < LLD 0 (3.OE+1) bNb 1.03E+1 All < LLD All < LLD 0 (1.5E+1) 14Cs 7.59E+0 All < LLD All < LLD 0 (1.5E+1) 1Cs 7.34E+0 All < LLD All < LLD 0 (1.8E+1) 74 UBa 2.60E+1 All < LLD All < LLD 0 (6.OE+1) 14ULa 1.03E+1 All < LLD All < LLD 0 (1.5E+1) 23

Table 8 (Cont.) - Radiological Environmental Monitoring Program Summary for 2012 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine4 Pathway Number of of Mean' (#/total #) Name Mean 3 (#/total #) Mean3 (#/total #) Reported Sampled (Unit of Analyses Detection2 (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed1 Actual (Max.)

Drinking Water6 Gross Beta (36) 1.35E+O 2.67E+O (18/24) Site 28, New Nuclear 3.16E+O (8/12) 2.64E+O (9/12) 0 (pCi/I) (4.OOE+0) (1.66E+O to 4.60E+O) Deployment, (2.20E+0 to 4.60E+0) (1.52E+0 to 4.74E+0)

(2.6 mi, SSE) 3 H (36) 5.13E+2 7.09E+2 (3/24) Site 17, Columbia 7.09E+2 (3/12) All < LLD 0 (2.OE+3) (6.32E+2 to 8.09E+2) Water Works, (6.32E+2 to 8.09E+2)

(25 mi, SE)

Gamma Spec (72)9 b4Mn 5.15E+ 0 All < LLD All < LLD 0 (1.5E+ 1)

- 7Co 5.06E+ 0 All < LLD All < LLD 0 (1.5E+ 1) bvFe 1.00E+ 1 All < LLD All < LLD 0 (3.OE+ 1)

UUCo 5.22E+ 0 All < LLD All < LLD 0 (1.5E+ 1)

.bZn 1.11E+1 All < LLD All < LLD 0 (3.OE+ 1) 9bZr 8.76E+ 0 All < LLD All < LLD 0 (3.0E+ 1)

UNb 7.16E+ 0 All < LLD All < LLD 0

_____________ (1.5E + 1) _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1611 5.12E-1 All < LLD All < LLD 0 134 (1.OE+ 0)

ý Cs 4.76E+ 0 All < LLD All < LLD 0 (1.5E + 1)

'4 t Cs 5.02E+ 0 All < LLD Ali < LLD 0 (1.8E + 1) 1.85E+ 1 All < LLD All < LLD 0 4

(6.OE+ 1) 1 1 ULa 6.61E+ 0 All < LLD All < LLD 0 (1.5E+ 1) 24

Table 8 (Cont.) - Radiological Environmental Monitoring Program Summary for 2012 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine4 Pathway Number of of Mean 3 (#/total #) Name Mean 3 (#/total #) Mean 3 (#Itotal #) Reported Sampled (Unit of Analyses Detection 2 (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed' Actual (Max.)

Broadleaf Gamma Spec Vegetation (36)

(pCi/kg wet) 11 2.03E+1 All < LLD All < LLD 0 1

(6.OE+ 1) 4Cs 2.06E+1 All < LLD All < LLD 0 (6.OE+ 1) lICs 2.44E+1 All < LLD All < LLD 0 (8.OE+ 1)

Fish 7 Gamma Spec (pCi/kg wet) (18)

'4Mn 5.71 E+1 All < LLD All < LLD 0 (1.3E+ 2) bdCo 5.99E+1 All < LLD All < LLD 0 (1.3E+ 2) b9Fe 1.66E+2 All < LLD All < LLD 0 (2.6E+ 2) bUCo 6.90E+1 All < LLD All < LLD 0 3

(1.3E+2) b Zn 1.12E+2 All < LLD All < LLD 0

-Z_ (2.6E+2) 1 4 Cs 5.35E+1 All < LLD All < LLD 0 (1.3E+2) 1Cs 6.22E+1 All < LLD All < LLD 0 (1.5E+2) 25

Table 8 (Cont.) - Radiological Environmental Monitoring Program Summary for 2012 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine4 Pathway Number of of Mean 3 (#/total #) Name Mean 3 (#/total #) Mean 3 (#/total #) Reported Sampled (Unit of Analyses Detection2 (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed' Actual (Max.)

Sediment Gamma Spec (6)

__8 (pCi/k 1Mn 1.55E+1 All < LLD All < LLD 0 N/A bdCo 1.50E+1 All < LLD All < LLD 0 N/A bUCo 2.15E+1 All < LLD All < LLD 0 N/A 1

-Cs 1.30E+1 All < LLD All < LLD 0 (1.5E+2)

Cs 1.54E+1 4.56E+1 (2/4) Site 21, Parr 4.56E+1 (2/2) 8.97E+1 (2/2) 0 (1.8E+2) (2.35E+1 to 6.77E+1) Resevoir, (2.7 mi. (2.35E+1 to 6.77E+1) (1.64E+1 to 1.63E+2)

SSW) 26

Table 8 (cont) - Radiological Environmental Monitoring Program Summary for 2012 Footnotes

1. Includes indicator and control analyses. Site 8, Air Particulates and Air Radioiodines are included as indicators. Does not include other supplemental samples.

2. Values given are maximum MDA values for indicator locations calculated from the program data analyses. The maximum acceptable LLD values allowed from NRC guidelines are given in parentheses.

3. Mean and range are based on detectable measurements only. The fractions of detectable measurements (i.e., number of positive results/total number of measurements) at specific locations are indicated in parentheses.

4. Any confirmed measured level of radioactivity in any environmental medium that exceeds the reporting requirements of ODCM, Section 1.4.1.2.

5. Detection sensitivity is approximately 10 mrem/yr (1.0 pR/hr).

6. Elevated levels of 214 Pb and 214 Bi were observed in Jenkinsville drinking water samples.

The values are not reported here because they are naturally occurring (do not originate from VCSNS) and furnish no quantifiable information of interest.

7. Fish include 3 groups (Bass, Bream/Crappie, Catfish/Carp.)

8. Elevated 23 2 levels of 2 14 Pb and 2 14 Bi plus other 2 26 Ra daughter products and 22 8Ac plus other Th daughter products were observed in all sediment samples. The values are not reported here because they are naturally occurring (do not originate from VCSNS) and furnish no quantifiable information of interest.

9. Drinking water resin prepared and counted for 1311 as separate sample.

27

Table 9- Radiological Environmental Monitoring Program Preoperational (Baseline) Summary Location with Highest Annual Mean Medium Med or (Unithway Pathway Type and Total Numbe of Lower Limit of All Indicator 2 (#/to Control Locations Number of Nonrou Sampled (Unit of Number of Detection' Actual Locations Mean2 Name Mean tal #) Mean 2 (#/total #) Nonroutine Measurement and Analyses (Max.) (#/total #) (Range) (Distance & Direction) (Range) (Range) Reported' Reporting Period) Performed Measurements Air Particulate Gross Beta 4.1E-3 1.1E-1 (562/564)4 Site 13, North Dam, 1.3E-1 (52/52) 1.2E-1 (153/155) 0 (pCi/m 3) (1300) (1.0E-2) (1.3E-2 to 5.5E-1) (2.9 mi NNW) (2.1 E-2 to 5.5E-1) (7.9E-3 to 6.1 E-1)

(1981-1982) 2.7E-2 (456/462)4 Site 8, Mon. Res. S of 3.OE-2 (42/42) 2.8E-2 (125/126)

(9.3E-3 to 6.6E-2) Rd 224, (1.5 ENE) (1.2E-2 to 6.OE-2) (1.2E-2 to 5.8E-2)

Gamma Spec 43o7 IICs 3.OE-3 All < LLD All < LLD 0 (1.OE-2)

Cs 3.1E-3 3.2E-3 (22/241) Site 10, Met Tower, 3.8E-3 (2/22) 4.2E-3 (4/66) 0 (1.OE-2) (1.5E-3 to 5.2E-3) (2.4 mi NNE) (2.5E-3 to 5.2E-3) (3.2E-3 to 5.6E-3)

Air Radioiodine 1 (290) 3.6E-2 All < LLD All < LLD 0 3

(pCi/m ) (1982) (7.OE-2) 5 Direct (TLD) Gamma (1220) 0.5 9.9 (915/915) Site 13, North Dam, 13.1 (61/61) 9.7 (305/305) 0 (p.R/hr) Monthly N/A (6.7 to 14.7) (2.9 mi NNW) (12.2 to 14.2) (6.4 to 13.5)

(1978-1982)

Gamma (161) 0.5 10.2 (154/154) Site 55, St. Barnabas 14.0(7/7) 0 Quarterly N/A (6.8 to 14.7) Church, (2.8 mi E) (13.1 to 14.7)

Surface Water 0 3

(pCi/I) H (43) 1.1 E+3 1.4E+3 (18/29) Site 17, Columbia 1.6E+3 (2/7) 1.2E+3 (6/14)

(1981-1982) (2.OE+3) (1.1E+3 to 2.4E+3) Canal, (24.7 mi, SE) (1.4E+3 tol.8E+3) (6.7E+2 to 1.6E+3)

Gamma Spec Mn 2.7E-1 All < LLD All < LLD 0 (1.5E+1)

• Co 2.9E-1 All < LLD All < LLD 0 (1.5E+1) b9Fe 6.OE+0 All < LLD All < LLD 0 (3.OE+1) bUCo 2.4E-1 All < LLD All < LLD 0 (1.5E+1) bZn

. 7.9E-1 All < LLD All < LLD 0 (3.OE+1) 9tZr 5.2E-1 All < LLD All < LLD 0 (1.5E+1)

. Nb. 3.3E-1 All < LLD All < LLD 0

=

................... (1.5E+1)

Cs 3.OE-1 All < LLD All < LLD 0

________ ______ _____ (1 .5E+1) _ _ _ _ _ _ _ _ _

28

Location with Highest Annual Mean Medium or Pathway Type and Total Lower Limit of All Indicator Control Locations Number of Sampled (Unit of Number of Deecio1 cta 2 ea=Mean2 Lcaios Name Mean 2 (#/total #) (#Itotal #) Reotd Nonroutine Measurement and Analyses D o a l L#ctons Mean (Distance & Direction) (Range) (Range) Reported3 Reporting Period) Performed (Max.) (#/total #) (Range) (Range) Measurements 1

3(Cs 2.2E-1 All < LLD All < LLD 0 (1.8E+1) 14UBa 2.2E+0 All < LLD All < LLD 0 (6.OE+1)

.4ULa 5.5E-1 All < LLD All < LLD 0 (1982 only) (1.5E+l)

Ground Water Site 26, Onsite Well 1.6E+3 (8/8) 1.3E+3 (13/13)

(pCi/I) H (29) 9o0E+2 1.5E+3 (16/16) P4, (9.5E+2 to 2.3E+3) (1.0E+3 to 1.9E+3) 0 (1981-1982) (2.0E+3) (9.5E+2 to 2.3E+3) (265 ft, W)

Gamma Spec

ýMn 3.7E+0 All < LLD All < LLD 0 (1.5E+1)

=Co 3.8E+0 All < LLD All < LLD 0 (1.5E+1) 7Fe 7.8E+0 All < LLD All < LLD 0 (3.0E+1) bUCo 3.8E+0 All < LLD All < LLD 0 (1.5E+1)

=n 8.1E+0 All < LLD All < LLD 0 (3.0E+1) v!Zr 6.8E+0 All < LLD All < LLD 0 (1.5E+1)

. Nb. 4.6E+0 All < LLD All < LLD 0 lr ý(1.5E+1) 1 Cs 3.7E+0 All < LLD All < LLD 0 (1.5E + 1) 1Cs 3.8E+0 All < LLD All < LLD 0 (1.8E + 1) All < LLD 0 l 4UBa 1.9E+1 All < LLD All<LLD 0 (6.OE+1) 4 1 ULa 5.OEO All < LLD All < LLD 0 (1982 only) (1.5E+1)

Drinking Water" Gross Beta7 (2.OE+0)

(pCi/I) (1981-1982) 3H (14) 6.3E+2 7.8E+2 (6/14) Site 28, Jenkinsville, 8.4E+2 (3/7) 0 (1.OE+3) (6.8E+2 to 9.8E+2) (2.0 mi SE) 7 (7.OE+2 to 9.8E+2)

Gamma Spec (44) 3.OE-1 All < LLD 0 (1.5E+1) bCo 2.7E-1 All < LLD 0 1__ _(1.5E+1) I I 29

Location with Highest Annual Mean Medium or Pathway Type and Total Lower Limit of All Indicator 2 Control Locations Number of 2

Sampled (Unit of Number of Detection Actual Locations MeanMean total#) Nonroutine Measurement and Analyses (eax,) (#1tons Mean (Distance & Direction) (Range) Meange) Reported 3 Reporting Period) Performed (Max.) (#/total #) (Range) (Range) Measurements b9Fe 9.6E0 All < LLD 0 (3.0E+1) bUCo 2.6E-1 All < LLD 0 (1.5E+1) 3.4E-1 All < LLD 0 (3.0E+1)

'Zr 4.8E-1 All < LLD 0 (1.5E+1) 1JII 3.4E-1 All < LLD 0 (1.5E+1)

. Nb. 7.4E-1 All < LLD 0 I =

................ (1.0E+0) 1 Cs 2.2E-1 All < LLD 0 (1.0E+I) 5Cs 2.4E-1 All < LLD 0 (1.8E+1) 14

.Ba 2.5E0 All < LLD 0 (6.0E+1)

... La 4.4E-1 All < LLD 0 (1982 only) (1.5E+1)

Milk Gamma Spec (pCi/I) (94)

(1981-1982) lii1 6.3E-1 All < LLD All < LLD 0 (1.0E+0)

• Cs 3.3E+0 All < LLD All < LLD 0 I =

................. (1.5E+1)

Cs 4.6E0 4.1E+0 (8/47) Site 14, Dairy, 4.1E+0 (8/47) 5.7E+0 (37/47) 0 (1.5E+1) (2.8E+to 6.1E+0) (5.1 mi., W) (2.8E+O to 6.1E+0) (3.7E+O to 9.2E+0) l4UBa 1.1E+1 All < LLD All < LLD 0 (1.5E + 1)

La 4.4E+0 All < LLD All < LLD 0 (1.5E+1)

Grass (pCi/kg wet) Gamma Spec (1981-1982) (82) 6.7E+1 All < LLD All < LLD 0 (6.OE+1) 7Cs 2.7E+1 All < LLD All < LLD 0 (8.OE+1)

Cs 3.3E+1 5.OE+1 (13/51) Site 14, Dairy, 5.9E+1 (5/29) 1.3E+2 (6/31) 0 (8.OE+1) (1.6E+1 to 1.6E+2) (5.1 mi W) (1.6E+1 to 1.6E+2) (1.3E+1 to 3.4E+2) 30

Location with Highest Annual Mean Medium or Pathway Type and Total Lower Limit of All Indicator 2 Control Locations Number of Sampled (Unit of Number of Name Mean (#/total #) Nonroutine Measurement and Analyses Detection' Actual Locations Mean (Distance & Direction) (Range) 2 Mean (#/total #) Reported 3 Reporting Period) Performed (Max.) (#/total #) (Range) (Range) Measurements Broadleaf Gamma Spec (10)

Vegetation (pCi/kg wet)

(1980-1982) loll 3.7E+1 All < LLD 0 lr =(6.0E+1) 1 4

• Cs 1.9E+1 All < LLD 0 I -CS(8.0E+1) 2.1E+1 3.1E+1 (2/7) Site 2, Trans. Line, 3.6E+1 (1/1) All < LLD 0 (8.0E+1) (1.8E+1 to 3.6E+1) (1.2 mi SV) (Single Value)

Other Vegetation Gamma Spec (pCi/kg wet) (32)

(1980-1982) 14 3 Cs 8.4E+0 All < LLD All < LLD 0 1 1 (8.OE+1) 6 Cs 1.0E+1 All < LLD All < LLD 0 (8.0E+1)

Fish (pCi/kg wet) Gamma Spec (1980-1982) 1_2)

• Cs 1.4E+1 All < LLD All < LLD 0 (1.3E+2) 137Cs 1.8E+1 2.8E+1 (50/71) Site 24, Recreation 3.4E+1 (17/23) 3.1E+1 (19/21) 0

=

................ (1.3E+2) (1.1 E+1 to 1.0E+2) Lake, (5.5 mi, N) 1.2E+1 to 1.OE+2) (1.0E+1 to 7.9E+1)

• Co 2.6E+1 All < LLD All < LLD 0 (1.3E+2) 1Mn 1.8E+1 All < LLD All < LLD 0 (1.3E+2) bUFe 9.0E+1 All < LLD All < LLD 0 (2.6E+2) bZn 4.1E+1 All < LLD All < LLD 0 (2.6E+2) bUCo 1.8E+1 All < LLD All < LLD 0 (1.3E+2)

Sediment (pCi/kg) Gamma Spec (24)

(1980-1982)

• 5Cs 2.3E+1 All < LLD All < LLD 0 (1.5E+2) 1 3tCs 2.4E+1 1.7E+2 (12/18) Site 21, Parr 2.6E+2 (6/6) 4.2E+2 (6/6) 0 (1.5E+2) (2.6E+1 to 4.5E+2) Reservoir, (2.6E+1 to 4.5E+2) (1.8E+1 to 1.OE+3) 1____ _ _(2.7 mi, SSW) I I I 31

Table 9 (Cont.)- Radiological Environmental Monitoring Program Preoperational (Baseline) Summary Footnotes

1. Values given are MDA values calculated from the program data analyses with maximum acceptable LLD values allowed from NRC guidelines given in parentheses.

2. Mean and range are based on detectable measurements only. The fractions of detectable measurements at specific locations are indicated in parentheses.

3. A non-routine measurement is any confirmed measured level of radioactivity in an environmental medium that exceeds the reporting requirements of VCSNS ODCM, Section 1.4.1.2.

4. The baseline values are high because of the fallout from the Chinese bomb test in 1980.

The first set of data reflects the 1981 baseline. The second set of data reflects the 1982 baseline, essentially free of bomb test fallout. The 1982 data covers the period 1/1/82 -

10/22/82.

5. Detection sensitivity is approximately 5 mrem/yr (0.5 fiR/hr) determined from the analyses of five years of preoperational data.

6. No control location was specified for drinking water during the preoperational monitoring period.

7. Inconclusive data.

32

Table 10 - Results of 2012 Environmental Intercomparison Program with Independent Lab, Eckert & Ziegler Analytics, Inc.

Comparison Study VendorLab EnvLab (Measurement Unit) Date Nuclides Results Results Agreement Gamma Isotopic Liquid 3/22 1 94 88 Yes 141 1 Liter Ce 184 188 Yes (pCi/I) 51Cr 309 310 Yes 134Cs 106 100 Yes 137 Cs 113 126 Yes 58 Co 93 101 Yes 54 Mn 138 160 Yes 59 Fe 119 125 Yes 65 Zn 60Co 235 275 Yes 197 214 Yes Gamma Filter 10/3 141Ce 166 166 Yes (pCi) 51 1 34Cr Cs 251 109 238 Yes 93 Yes 137Cs 176 172 Yes 58 Co 102 103 Yes 54 Mn 198 210 Yes 59 Fe 154 179 Yes 65Zn 195 232 Yes 6 0Co 154 154 Yes Alpha/Beta Water 3/28 Alpha 221 216 Yes (pCi/I) Beta 297 312 Yes Gamma Isotopic 3/27 11Ce 3.67E-1 3.22E-1 Yes Pulverized 51Cr 6.15E-1 5.12E-1 Yes Soil 134 Cs 2.11E-1 1.78E-1 Yes (pCi/g) 137 Cs 3.12E-1 2.66E-1 Yes 58 Co 1.86E-1 1.48E-1 Yes 54 Mn 2.75E-1 2.31E-1 Yes 59 Fe 2.37E-1 2.21E-1 Yes 65 60Co Zn 4.69E-1 4.17E-1 Yes 3.93E-1 3.37E-1 Yes 1-131 Solid 3/22 1311 94 90 Yes (pCi) 33

Comparison Study Date Nuclides VendorLab Env Lab (Measurement Unit) Results Results Agreement Tritium 4/3 3H 4470 6620 No (pCi/I)

Gross Beta Filter 9/20 N/A 92 90 Yes (pCi)

Charcoal Cartridge 9/24 1311 97 106 Yes (pCi)

Gamma Isotopic Liquid 9/21 1311 100 121 Yes 4 Liter 141Ce 251 291 Yes (pCi/I) 51 134CrCs 380 166 455 187 Yes Yes 13 7 CS 267 305 Yes 58 Co 154 182 Yes 54 Mn 300 344 Yes 59 Fe 233 274 Yes 65 Zn 60 Co 295 337 Yes 233 267 Yes Tritium comparison was not in agreement.

The probable cause of this event was contamination of the outside of the sample vial with cocktail during sample preparation. Four new samples were prepared using the remaining sample and analyzed. The results averaged 4.35E+3 pCi/L with a range of 4.09E+3 to 4.71E+3 pCi/L. This has an agreement between 92 and 105% which is well within the required range of 85 to 115%. (CR-12-03529) 34

Table 11 -2012 Environmental Sampling Program Exceptions Sample Month Media Location (Week No.) Cause for Exception Air Particulate Site 2 Feb (09) Human error. Air sampler was not And restarted after change out.

Radioiodine Ground Water Site 107 Mar (12) Well dry.

Site 107 Jun (25) Well dry.

Site 111 Jan (04) Well dry. Tritium only.

Site 111 Apr (16) Well dry. Tritium only.

Site 115 Jan (04) Well dry.

Site 115 Apr (16) Well dry.

TLD Site 58 Jan (02) Human error. TLD was not changed out.

It was left in the field.

Site 20 Jul (28) TLD missing.

Site 30 Jul (28) Site 30 TLD was temporarily relocated /2 mile closer to the site due to New Nuclear construction.

Site 20 Oct (38) TLD missing.

35

i N

LEGEND

• CONTROL SAMPLE LOCATIONS A=AIR PARTICULATE SITE D=OIRECT (TLD) SITE I=AIRBORNE RADIOIODINE SITE W=WATER SITE O=OTHER (GARDEN PRODUCTS.FISH, SEDIMENT, GRASS, MILK)

REFERENCEt THE BASEFOR THIS MAPWASPREPARED FROMA PORTION OF USGSSTATE OF GEORGIA. I970.

90 0 10 so South Carolina Electric & Gas Co.

VIrgil C. Summer Nuclear Station Regional Location Map Figure 1-1 I

I REVDATE 12-e

LEGEND ......tt o*

,VSt.

wPRIMARY SAMPLE LOCATIONSN

_.4 ..... 215 A= AIR PARTICULATE SAMPLE SITE *oý ":: I* :::.1 D =DIRECT (TLD) SAMPLE SITE 'Fhp 42 1 =AIRBORNE RADIDIODINE SAMPLE SITE32!

W=WATER SAMPLING LOCATION otiI*)

0: OTHER f 0= TLD (0) SAMPLING LOCATIONSStMak 351 -

St*rl Mill

'Ne.Ho ....... ~ N jMo.

• ~L21 7 fth 176 8 $ 4

• 70 -00 Ch S1 J., -~ PARRta~o Ch '25B 9 . .ý 3.w S. LtJo.

EX US N

-om -

• can*ý . -- '.5 ON.h

• ., x 9R Staio \5Vr9 C umrNcla tto ARR - S 73 44.1 <7  %- "176ER IA AIL GCA OIOIN6 0 RGA

", 2 Fidgre Ch.

315' 1/

90*

,AMPLER (A,I, 135' t" 4, LEGEND f FIGURE 1-3 I 0 A

PRIMARY SAMPLE LOCATIONS AIR PARTICULATE SAMPLE SITE MM'S COV91IIIDM- HjL.0-ADWITIOVAL NO COWTRO. LOCATIONS MESWAILABI.

D DIRECT (TLD) SAMPLE SITE (QUARTERLY)

I AIRBORNE RADIOIODINE SAMPLE SITE

/ W WATER SAMPLING LOCATION 0 OTHER D nmllt Trr=u*' I C

El CPS 10

-Ai w EI Wet Wast T/tmt } '

• 1 * "14 .......

I mI [] ... .. ....... .. ......................... 1 Carolina Eletuc & Gas Co South........

RADIOLOGICAL MONITORING PROGRAM Ul SECURiTY AREA GROUNDWATER SITS Figure 1-4

Cooling Tower N

W+E s

g I A' ~

l yE South Carolina Electric & Gas Co Virgil C Summer Nuclear Station RADIOLOGICAL MONITORING PROGRAM PROTECTED AREA GROUNDWATER SITES Figure 1-5 J.