ML18116A687

Submittal of Annual Radiological Environmental Operating Report for 2017

ML18116A687
Person / Time
Site:	Summer
Issue date:	04/25/2018
From:	Ryan Justice South Carolina Electric & Gas Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML18116A687 (47)

Text

Robert L. Justice General Manager, Nuclear Plant Operations 803.345.4707 April 25, 2018 SCE&G 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 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, SBR/RLJ/wm w/o enclosures unless noted c: J. E. Addison K. T. Ellison W. K. Kissam T. D. Riley J. B. Archie K. M. Sutton J. H. Hamilton C. S. Logan (w/enclosures)

G. J. Lindamood Anu Nair-Gimmi (w/enclosures)

W. M. Cherry NSRC C. Haney RTS (LTD 312)

S. A. Williams File (818.02-2, RR 8300)

NRC Resident Inspector PRSF(RC-18-0062) (w/enclosures V. C. Summer Nuclear Station

• P. 0. Box 88

• Jenkinsville, South Carolina

• 29065

• F (803) 941-9776

• www.sceg.com

SCE&G A SCANA COMPANY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPERATING PERIOD JANUARY 1, 2017 - DECEMBER 31, 2017 Brett Williams, Specialist Health Physics Approved by:

imothy D. Riley, Supervisor Todd Ellison, Manager Health Physics Health Physics and 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 2017.

Included are the identification of sample locations, descriptions of environmental sampling and type of analysis. Comparisons of present environmental radioactivity levels and preoperational environmental data, land use census evaluation, doses calculated from environmental measurements, and a summary of environmental radiological sampling results are presented. 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 deviations noted. Samples were collected comprising one thousand two hundred seventy one analyses (1,271) performed to compile the data for the 2017 Environmental Report. Supplemental samples comprising two hundred forty nine (249) 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.

Radionuclides observed in the environment in 2017 from V.C. Summer effluent releases were within the range of concentrations observed in the past. Radiation dose calculated from sample results is less than observed with normal fluctuation in natural background. 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 8 ii

LIST OF TABLES TABLE PAGE 1 Monitoring Methods for Critical Radiation Exposure 3 Pathways 2 2017 Fission and Activated Corrosion Product Activity in 7 Sediment 3 Required Sampling Site Locations 9 4 Results of the 2017 Land Use Census Verification 12 5 Critical Receptor Evaluation for 2017 13 6 Radiological Environmental Monitoring Program 14 Specifications 7 Supplemental Radiological Environmental Monitoring 19 8 Radiological Environmental Monitoring Program Summary 23 for 2017 9 Radiological Environmental Monitoring Program 29 Preoperational (Baseline) Summary 10 Results of 2017 Environmental Inter-comparison Program 34 with Independent Lab, Eckert & Ziegler Analytics, Inc.

11 2017 Environmental Sampling Program Deviations 36 iii

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

1-5 Radiological Monitoring Program Protected Area Ground Water Sites and Independent Spent Fuel Storage Installation (ISFSI).

iv

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 24th 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 blow down 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 ground level releases.

In 2012 construction began on the Independent Spent Fuel Storage Installation (ISFSI), and concluded in January 2016. Dry Cask Storage began March 26, 2016 and finished in the first week of May 2016. Four casks were loaded during this evolution. The second campaign is scheduled to begin in 2019.

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 2017. Data trends, l

control/indicator and preoperational/operational data, inter-comparisons, and other data interpretations are presented.

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 inter-comparisons in order to evaluate 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. These required Lower Limits of Detection (LLD's) are verified to have been met by calculating Minimum Detectable Activity (MDA) for each sample based on actual counting parameters relevant to each sample. In all cases the achieved MDA was lower than the LLD. 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 both 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).

2

Table 1 - Monitoring Methods for Critical Radiation Exposure Pathways Effluent Release Exposure Pathway Monitoring Media Type Gaseous Immersion Dose and Thermoluminescent Dosimetry other External Dose (TLD) 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 Drinking Water Sampling (Ingestion)

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. Background radiation levels vary across the monitored area of interest.

In addition to preoperational/operational data inter-comparisons, control/indicator data inter-comparisons 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 mile ESE) and Site 7 (1.0 mile 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 miles S) serves as a control location for direct radiation and Site 40 (11.9 miles 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 miles SSW) and Site 23, Monticello Reservoir (0.5 miles ESE). The control location for liquid effluent comparisons is at Site 22, Neal Shoals (26.0 miles NNW) on the Broad River.

3

Quality of analytical measurements is demonstrated by participation in a laboratory inter-comparison program. Results of the inter-comparison program with an outside vendor and VCSNS Count Room were satisfactory in 2017 and are summarized in Table 10. 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.

LAND USE CENSUS Annually a land use census is performed within a 5 mile radius of VCSNS to verify the appropriate siting of sample locations. In addition, the location of the maximum exposed individual (MEI) is identified to ensure the appropriate location is used for calculation of offsite dose impact from Summer Station gaseous effluents. The results of the land use census performed in 2017 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 source term from the Operating License Environmental Report and 2017 meteorological data.

Exposure pathways modeled 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 the highest calculated dose. In addition, the ODCM required environmental gardens (E3E 1.0 and E 1.0 miles) were found to have calculated doses higher than any real receptor. 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 2017 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 99.8%. A listing of program deviations 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 gamma emitting nuclides were detected.

Gross beta activities measured in air particulate samples collected at indicator locations around VCSNS were consistent with preoperational levels and not statistically significant from control locations. The highest site-specific mean activity (2.32E-2 pCi/m3) was measured at indicator location Site 7 (Lab Garden 1.0 mile E). The results indicate that the operation of VCSNS has not contributed to detectable increases of airborne gross beta activity in the environment.

4

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 2.04E-3, 2.19E-3 and 1.88E-2 pCi/m3, respectively and all met program analytical requirements for detection capability. Air sample collection rate for indicator/control air samples was 100%.

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 miles WNW) was the indicator location showing the highest mean exposure rate of 1.19E+1 p,R/hr. The 2016 value was also 1.19E+1 pR/hr and consistent with the highest mean exposure rate of 1.40 E+1 pR/hr measured during the preoperational period. In April of 2015 six TLD sites were added to the Environmental Dosimetry program. These added TLD's were placed around the boundary of the Independent Spent Fuel Storage Installation (ISFSI) which began cask storage on March 26, 2016. To date there has been no statistically significant increase in dose rate above background from Dry Cask Storage activities. TLD sample collection rate for all indicator/control was 99.4%.

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 above MDA in 4 samples at Site 21 (Parr Reservoir 2.7 miles SSW), and 2 samples at Site 23 (Monticello Reservoir 0.5 miles ESE). The Site 21 (Parr Reservoir 2.7 miles SSW) samples were at concentrations of 7.10E+02 pCi/L, 9.32E+2 pCi/L, 6.44E+2 pCi/L, and 4.74E+2 pCi/L. Site 23 (Monticello Reservoir 0.5 miles ESE) samples were at concentrations of 6.10E+02 pCi/L and 6.80E+2 pCi/L. Additionally, 1 of 12 supplemental samples from Site 73 (0.4 miles W), an outfall within the site boundary, had a tritium activity of 1,430 pCi/L. Assuming an individual obtained all of his drinking water from Parr Reservoir and the tritium concentration remained at 9.32E+2 pCi/L, the resulting dose would be less than 0.1 mrem/year based on consumption of 730 liters per year. Sample collection rate for all indicator/control surface water samples was 100%.

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 was detected within the site boundary in two shallow supplemental ground water samples at Site 123 (NPDES Well GW-16 0.34 SSE), used to monitor for chemical contaminants around the Industrial and Sanitary Waste Treatment System, at concentrations of 2.72E+3 pCi/L and 2.51E+3 pCi/L. These levels are substantially less than the 2.00E+4 pCi/L drinking water standard. Sample collection rate for indicator/control ground water samples was 100%.

Gamma spectroscopy measurements of drinking water samples collected from the Jenkinsville water supply and Site 17 (Columbia Water Works 25.0 miles SE) did not indicate the presence of activated corrosion or fission product activity above the respective MDAs. Tritium analysis indicated the presence of tritium above MDA in four samples taken at Site 17 (Columbia Water Works 25.0 miles SE) at concentrations of 7.82E+2 pCi/L, 4.49E+2 pCi/L 6.48E+2 pCi/L, and 6.48E+2 pCi/L. The highest indicator and control site-specific gross beta activity was measured at Site 28 (New Nuclear Deployment 2.6 miles 5

SSE) at a level of 6.34E+0 pCi/l. As discussed above, radiation dose from consumption of drinking water at the maximum tritium concentration would be less than 0.1 mrem/year.

Sample collection rate for indicator/control drinking water samples was 100%.

There were no milk samples collected in 2017. 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/year. Presently there are no locations meeting this criteria for indicator dairies. The closest dairy is approximately 7 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 137Cs in 3 of 12 samples at Site 2 (transmission line 1.2 miles SW) at concentrations of 2.57E+1 pCi/kg, 2.02E+1 pCi/kg, and 2.90E+1 pCi/kg. The maximum preoperational control activity was 3.40E+2 pCi/kg. Sample collection rate for indicator/control supplemental grass was 100%.

Gamma spectroscopy measurements were performed on supplemental grass and soil samples collected in response to a liquid effluent spill in 2011 at Site 25 (Fairfield Pump Storage Remediation Area 0.9 miles WNW). None of the grass samples collected indicated the presence of activated corrosion or fission products above the respective MDAs. One soil sample detected 60Co at 3.05E+1 pCi/kg and 137Cs at 1.64E+1 pCi/kg.

Dose calculation assuming a shoreline dose model resulted in a dose of approximately 0.01 mrem/year.

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 all fish samples collected did not indicate the presence of activated corrosion or fission products above the respective MDA. All of the required indicator/control fish samples were collected.

Gamma spectroscopy measurements of sediment samples indicated the detection of 137Cs in 2 of 4 indicator samples. Site 21 (Parr Res. 2.7 miles SSW) at concentrations of 4.13E+1 and 1.22E+2 pCi/kg were detected. 137 Cs was also detected in 2 of 2 control samples taken at Site 22 (Neal Shoals 26 miles NNW) at concentrations of 2.87E+1 pCi/kg and 3.17E+1 pCi/kg. Historically 137Cs levels at the control site have ranged from 1.8E+1 pCi/kg to 1.0E+3 pCi/kg. The level of 137Cs observed at Site 21 (Parr Res. 2.7 miles SSW) is consistent with background conditions in the environment. However if the 137Cs was attributed to Summer Station the dose would be 1.02E-2 mrem/year. All required indicator/control sediment samples were collected.

6

Table 2 - 2017 Fission and Activated Corrosion Product Activity in Sediment Corresponding Location Radionuclide Activity (pCi/kg) Calculated Annual Dose Equivalent (mrem/yr)

Tota Body Maximum Mean Maximum Mean Parr Reservoir 137Cs 1.22E+2 8.17E+1 1.02E-2 6.86E-3 Corresponding Location Radionuclide Activity (pCi/kg) Calculated Annual Dose Equivalent (mrem/yr)

Tota Body Maximum Mean Maximum Mean Site 25 137Cs 1.64E+1 1.64E+1 1.38E-3 1.38E-3 0.9 miles WNW 60Co 3.05E+1 3.05E+1 1.04E-2 1.04E-2 Total 1.18E-2 1.18E-2 7

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 drinking water samples taken at Site 17 (Columbia Water Works 25.0 miles SE), and site 99 (Nuclear Operations Bldg. 0.1 miles W)

• Tritium in surface water samples taken at Site 21 (Parr Res. 2.7 miles SSW),

site 23 (Monticello Reservoir 0.5 miles ESE), and site 73 (Yard Drain Outfall 0.4 miles W). All tritium sample concentrations were well below drinking water standards and using conservative assumptions with offsite surface and drinking water samples result in radiation dose less than 0.1 mrem.

• Tritium in supplemental ground water samples taken at Site 123 (NPDES Well GW-16 0.34 miles SSE).

• Co-60 and Cs-137 were detected in one supplemental soil sample taken at Site 25 (Fairfield Pumped Storage Penstocks 0.9 WNW) with calculation of dose assuming shoreline pathway results in dose of approximately 0.01 mrem/year.

The average natural background for direct exposure as determined from control locations is 71.1 mrem/year. The hypothetical calculated maximum exposure for drinking water and sediment exposure is well within the normal fluctuations of natural terrestrial and cosmic background. This dose would not be expected to 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.

8

Table 3 - Required Sampling Site Locations Site Distance1 Description Direction2 Sample Type(s)3 No. (Miles) 1 Borrow Pit 1.2 179.8 S DQ 2 Transmission Line 1.2 225.0 SW AP, Rl, 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 (Shealy)4 6.5 277.0 W MK,GR 16 Dairy (Parr)4 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 ofVCSNS 1.0 260.6 WSW DQ 30 Oak Tree North of Borrow Pit6 1.0/0.5 196.2 SSW DQ, AP, Rl 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 Facility7 11.9 157.0 SSE GA, GR 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 9

Table 3 (cont) - Required Sampling Site Locations Site Distance1 Description Direction2 Sample Type(s)3 No. (Miles) 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 Deployment5 2.6 170.2 SSE DQ, GW 60 Rd 98 near Rd 28 3.5 274.6 W DQ 78 ISFSI - North 0.14 133 NW DQ 79 ISFSI - North East 266 Ft 102 WNW DQ 80 ISFSI - South East 256 Ft 61 WSW DQ 81 ISFSI - South 0.10 63WSW DQ 82 ISFSI -South West 0.15 91 W DQ 83 ISFSI-North West 0.15 104 WNW 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 NPDES Well (GW-13A) 0.39 317 SE GW 10

Table 3 (cont) - Required Sampling Site Locations Footnotes Distance given is the distance between the site location and the VCSNS reactor containment building.

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

Sample Types:

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

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

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 1.0 mile from the reactor in the same sector.

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

11

Table 4 - Results of the 2017 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 Rufus Pearson 2.66 ENE Bessie Gregg 1.56 Essie Mae Glenn 1.68 E Sheryl A. Colley 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 Joe Smith 0 4.73 sw Marvin Miller 3.3 Marvin Miller 3.3 WSW Ron Hope 2.9 Steve All 4.83 Ken/Virg Graham (*) 0 4.98 Steve All 0 4.83 w Jerry Cassado 2.55 Marion Livingston 2.8 Marion Livingston 0 2 w Ken/Virg Graham (*) 90 5 WNW C.C. Mann 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 12

Table 5 Critical Receptor Evaluation for 2017 DOSE*

NAME SECTOR MILES PATHWAY XIQ D/Q mrem/y P. Oliver N 3.73 Res 1.90E-07 6.30E-10 7.13E-03 Thomas K. Crumblin NNE 2.9 Res 5.00E-07 1.60E-09 1.87E-02 Eddie Robinson NNE 3.99 B,Gar 2.60E-07 7.70E-10 2.79E-01 Gregrey Guinyard Jr. NE 1.55 Res 2.30E-06 7.80E-09 8.63E-02 Rufus (Ruddy) Pearson NE 2.66 Res,Gar 7.30E-07 2.10E-09 5.79E-01 Bessie Gregg ENE 1.56 Res 1.90E-06 6.50E-09 7.14E-02 Essie Mae Glenn 1 ENE 1.68 Res,Gar 1.60E-06 5.50E-09 1.48E+00 Garden-7 ** E 1 Res,Gar 3.90E-06 L 1.30E-08 3.52E+00 Sheryl A. Colley E 1.2 Res 2.50E-06 8.20E-09 9.37E-02 Garden-6 ** ESE 1 Res,Gar 2.70E-06 8.40E-09 2.29E+00 Carrie Lee Martin ESE 1.1 Res 2.10E-06 6.60E-09 7.86E-02 James Pearson ESE 1.36 Res,Gar 1.30E-06 3.80E-09 1.05E+00 Mary White SE 1.44 Res,Gar 5.70E-07 2.50E-09 6.58E-01 Sim Roberts SE 4.7 Res,Gar,B 4.70E-08 1.60E-10 1.76E-03 Ronnie Mann SSE 2.39 Res,Gar 1.30E-07 7.40E-10 1.91E-01 Kelly Boulware S 3.56 Res,Gar 7.20E-08 4.50E-10 1.15E-01 Shirley Counts S 5 Res,Gar,B 3.60E-08 2.10E-10 7.50E-02 NND Construction Site ssw 0.49 Res 5.50E-06 5.10E-08 2.23E-01 Nick Bates ssw 3.11 Res 9.40E-08 7.60E-10 3.75E-03 Joe Smith ssw 4.73 Res,B 3.90E-08 3.00E-10 3.13E-02 Marvin Miller sw 3.3 Res,Gar 7.40E-08 8.00E-10 2.00E-01 Ron Hope wsw 2.9 Res 7.70E-08 6.30E-10 3.08E-03 Steve All wsw 4.83 Res,Gar,G 2.60E-08 2.00E-10 5.07E-02 KenA/irg Graham wsw 4.98 B 2.50E-08 1.9QE-10 1.89E-02 Jerry Cassado w 2.55 Res 1.20E-07 6.30E-10 4.62E-03 Marion Livingston w 2 B 2.00E-07 1.10E-09 1.09E-01 Marion Livingston w 2.8 Res,Gar 9.70E-08 5.10E-10 1.32E-01 Marion Livingston w Res,Gar,B BOTH BOTH 2.41E-01 KenA/irg Graham w 5 Res,Gar,B,C/M 2.90E-08 1.40E-10 1.75E-01 C C Mann WNW 2.53 Res 1.10E-07 4.30E-10 4.16E-03 Ronnie Leitzsey WNW 4.15 C/M,B,G/M,G 3.90E-08 1.40E-10 1.40E-01 Ronnie Leitzsey WNW 4.72 Res,Gar 3.00E-08 1.10E-10 2.95E-02 Ronnie Leitzsey WNW Res,Gar,C/M,B,G/M,G BOTH BOTH 1.69E-01 Louise Workman NW 3.9 Res 8.80E-08 3.20E-10 2.98E-03 Frank March NNW 2.9 Res,Gar,B 3.40E-07 9.90E-10 3.18E-01 ODCM Organ Dose E 1.1 Res,Gar 3.10E-06 1.00E-08 2.72E+00 Pathway Res = Residence B = Beef G = Goat Gar = Garden C/M = Cow/Milk(lnfant) G/M = Goat/MiIk(Infant)

Footnotes:

1 Maximum exposed individual.

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

• • ODCM required environmental gardens.

13

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 AIRBORNE:

1. Particulate A) 3 Indicator samples from Continuous sampler operation 2 Gross beta following filter locations close to the site with weekly collection. 7 change; Quarterly boundary, in different 30 composite (by location) sectors, of the highest for gamma isotopic.

calculated annual average ground level D/Q or dose.2 B) 1 Indicator sample to be Continuous sampler operation 6 Gross beta following filter taken close to the site with weekly collection. change; Quarterly boundary in the sector composite (by location) corresponding to the for gamma isotopic.

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).2,4 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 for gamma isotopic.

prevalent wind directions.2 II. 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 l(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 l(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 l(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 l(D) above.

14

Exposure Criteria for Selection of Sampling and Collection Sample Type & Frequency of Pathway and/or Sample Number & Location Frequency Location Analysis Sample III. 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 exchange7; 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.

D) 6 Stations to be placed Quarterly exchange7; two or 78,79,80,81, Gamma & neutron dose around the ISFS1 more dosimeters at each 82,83 quarterly.

boundary. location.

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.

B) 1 Control sample to be Time composite samples6 with 223 Gamma isotopic monthly taken at a location on the collection every month.5 with quarterly composite (by location) to be receiving river sufficiently analyzed for tritium.7 far upstream such that no effects of pumped storage operation are anticipated.

C) 1 Indicator sample to be Time composite samples6 with 233 Gamma isotopic monthly taken in the upper reservoir collection every month.5 with quarterly composite of the pumped storage (by location) to be facility at the plant analyzed for tritium.7 discharge canal.

V. Ground Water A) 12 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 15

Exposure Criteria for Selection of Sampling and Collection Sample Type & Frequency of Pathway and/or Sample Number & Location Frequency Location Analysis Sample VI. Drinking A) 1 Indicator sample from a Monthly grab sampling.5 28 Monthly5 gamma isotopic Water nearby public ground water and gross beta analyses supply source. and quarterly7 composite for tritium analyses.

B) 1 Indicator (finished water) Monthly composite sampling. 17 Monthly5 gamma isotopic sample from the nearest and gross beta analyses downstream water supply. and quarterly7 composite for tritium analyses.

C) 1 Control (finished water) Monthly composite sampling. 39 Monthly5 gamma isotopic sample from an unaffected and gross beta analyses water supply. and quarterly7 composite for tritium analyses.

INGESTION:

VII. Milk4 A) Samples from milking Semimonthly when animals To be Gamma isotopic and I-animals in 3 locations are on pasture8, 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 VILA.

where doses are calculated to be greater than 1 mrem per year.10 B) 1 Control sample to be Semimonthly when animals 16 Gamma isotopic and I-taken at the location of a are on pasture8, monthly other 131 analysis dairy > 20 miles distance times.5,11 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 Vll(A),above, when animals accordance are on pasture. with criteria VILA.

D) 1 Control grass (forage) Monthly when available.5,11 16 Gamma isotopic.

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

16

Exposure Criteria for Selection of Sampling and Collection Sample Type & Frequency of Pathway and/or Sample Number & Location Frequency Location Analysis Sample VIII. Food A) 2 samples of broadleaf Monthly when available.5 6 Gamma isotopic on edible Products vegetation grown in the 2 7 portion.

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 to 8 km where the doses are calculated to be greater than 1 mrem/yr.10 B) 1 Control sample for the Monthly when available.5 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 greater than 1 mrem/yr.10 IX. Fish A) 1 Indicator sample to be Semiannual9 collection.1 233 Gamma isotopic on edible taken at a location in the portions semiannually.9 upper reservoir.

B) 1 Indicator sample to be Semiannual9 collection.1 213 Gamma isotopic on edible taken at a location in the portions semiannually.9 lower reservoir.

C) 1 Control sample to be Semiannual9 collection.1 223 Gamma isotopic on edible taken at a location on the portions semiannually.9 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.

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

taken on or near the shoreline of the lower reservoir.

3 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.

17

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.

18

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

S-1(A) above. collection.

S-lll. Direct A) 5 stations to be placed Quarterly exchange7; 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.

19

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

S-VII. Milk4 A) 1 Sample from one of the Biweekly grab 14 Gamma isotopic and nearest affected dairies at sample.8'14-"1" 1-131 analysis or beyond 5 miles. biweekly.

B) 1 Control sample to be Biweekly grab 16 Gamma isotopic and taken at the location of a sample.8'14'"1" 1-131 analysis dairy greater than 20 miles biweekly.

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.

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

S-VII. Milk4 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. 40 Gamma isotopic.

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

G) 1 Indicator grass (forage) Quarterly when available. 25 Gamma isotopic.

sample to be taken at location of penstock leak.

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

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

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

fruit, grain).

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

portions.

20

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.

C) 1 Indicator sample of Annually 25 Gamma isotopic.

topsoil from penstock spill area.

S-X. Ground Water A) 11 Indicator samples to be taken Quarterly grab sampling.7 107,111, Gamma isotopic and within the exclusion boundary 115-123 tritium analyses and in the direction of potentially quarterly.7 affected ground water supplies.

21

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.

22

Table 8 - Radiological Environmental Monitoring Program Summary for 2017 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 Detection2 Name Mean3 (#/total #)

Mean3 (#/tota! #) Mean3 (#/totai #) Reported4 (Unit of Analyses Actual (Distance & Direction) (Range)

(Range) (Range) Measurements Measurement) Performed1 (Max.)

Air Particulate Gross Beta 6.07E-3 2.20E-2 (260/260) Site 7, Environmental 2.32E-2 (52/52) 2.18E-2 (52/52) 0 (pCi/m3) (312) (1.OE-2) (7.03E-3 to 4.80E-2) Lab Garden, (1.16E-2 to 4.67E-2) (7.08E-3 to 5.27E-2)

(1.0 miles E)

Gamma Spec (72) 134Cs 2.04E-3 All < LLD All < LLD 0 (5.OE-2) 137Cs 2.19E-3 All < LLD All < LLD 0 (633E-2)

Air Radioiodine 1311 (312) 1.88E-2 All < LLD All < LLD 0 (pCi/m3) (7.OE-2)

Direct (TLD)5 Gamma(135) 8.28E+0 (116/116) Site 4, Fairfield 1.19E+1 (4/4) 8.11E+0 (19/19) 0 (pR/hr) Quarterly N/A (4.95E+0 to 1.31E+1) Hydro, (1.2 miles WNW) (1.11E+1 to 1.31E+1) (5.06+0 to 1.07E+1)

Gamma(24) 8.58E+0 (24/24) Site 52, Monticello Rd. 1.10E+1 (4/4) N/A 0 Special Interest N/A (4.95E+0 to 1.18E+1) 11, (3.8 miles NNE) (1.06E+1 to 1.18E+1)

Surface Water 3H (36) 4.33+2 6.75E+2 (6/24) Site 21, Parr Reservoir, 6.90E+2 (4/12) All < LLD 0 (pCi/I) (2.0E+3) (4.74E+2 to 9.32+2) (2.7 miles SSW) (4.74E+2 to 9.32E+2)

Gamma Spec(36) 54Mn 1.60E+0 All < LLD All < LLD 0 (1.5E+1) 58Co 1.78E+0 All < LLD All < LLD 0 (1.5E+1) 59Fe 3.93E+0 All < LLD All < LLD 0 (3.0E+1) 60Co 1.99E+0 All < LLD All < LLD 0 (1.5E+1) 65Zn 4.20E+0 All < LLD All < LLD 0 (3.0E+1) 95Zr 3.73E+0 All < LLD All < LLD 0 (3.0E+1) 95Nb 2.39E+0 All < LLD All < LLD 0 (1.5E+1) 134Cs 1.58E+0 All < LLD All < LLD 0 (1.5E+1) 23

Table 8 (cont.) - Radiological Environmental Monitoring Program Summary for 2017 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine Pathway Number of of Mean3 (#/total #) Name Mean3 (#/total #) Mean3 (#/total #) Reported4 Sampled (Unit of Analyses Detection2 (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed1 Actual (Max.)

Surface Water 137Cs 1.97E+0 All < LLD All < LLD 0 (Continued) (1.8E+1) 140Ba 1.56E+1 All < LLD All < LLD 0 (6.0E+1) 140La 3.79E+0 All < LLD All < LLD 0 (1.5E+1)

Ground Water 3H (52) 4.33E+2 All < LLD All < LLD 0 (pCi/l) 2.00E+3 Gamma Spec (52) 54Mn 4.42E+0 All < LLD All < LLD 0 (1.5E+1) 58Co 4.41E+0 All < LLD All < LLD 0 (1.5E+1) 59Fe 8.44E+0 All < LLD All < LLD 0 (3.0E+1) 60Co 5.16E+0 All < LLD All < LLD 0 (1.5E+1) 65Zn 1.14E+1 All < LLD All < LLD 0 (3.0E+1) 95Zr 8.61E+0 All < LLD All < LLD 0 (3.0E+1) 95Nb 4.78E+0 All < LLD All < LLD 0 (1.5E+1) 134Cs 5.50E+0 All < LLD All < LLD 0 (1.5E+1) 137Cs 5.54E+0 All < LLD All < LLD 0 (1.8E+1) 140Ba 3.12E+1 All < LLD All < LLD 0 (6.0E+1) 140La 6.51E+0 All < LLD All < LLD 0 (1.5E+1) 24

Table 8 (Cont.) - Radiological Environmental Monitoring Program Summary for 2017 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine Pathway Number of of Mean3 (#/total #) Name Mean3 (#/total #) Mean3 (#/total #) Reported4 Sampled (Unit of Analyses Detection2 (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed1 Actual (Max.)

Drinking Water6 Gross Beta (36) 1.63E+0 2.56E+0 (16/24) Site 28, New Nuclear 3.11E+0 (7/12) 2.11E+0 (9/12) 0 (pCi/l) (4.00E+0) (1.51E+0 to 6.34+0) Deployment, (1.66E+0 to 6.34+0) (1.45E+0 to 3.53E+0)

(2.6 miles, SSE) 3H (36) 4.15E+2 6.32E+2 (4/24) Site 17, Columbia 6.32E+2 (4/12) All < LLD 0 (2.0E+3) (4.49E+2 to 7.82+2) Water Works (4.49E+2 to 7.82E+2)

(25.0 miles, SE)

Gamma Spec (72)9 54Mn 2.27E+0 All < LLD All < LLD 0 (1.5E+1) 58Co 2.71E+0 All < LLD All < LLD 0 (1.5E+1) 59Fe 5.09E+0 All < LLD All < LLD 0 (3.0E+1) 60Co 2.88E+0 All < LLD All < LLD 0 (1.5E+1) 65Zn 5.59E+0 All < LLD All < LLD 0 (3.0E+1) 95Zr 5.19E+0 All < LLD All < LLD 0 (3.0E+1) 95Nb 2.55E+0 All < LLD All < LLD 0 (1.5E +1) 1311 5.08E-1 All < LLD All < LLD 0 (1.0E+0) 134Cs 3.34E+0 All < LLD All < LLD 0 (1.5E+1) 137Cs 2.82E+0 All < LLD All < LLD 0 (1.8E+1) 140Ba 1.66E+1 All < LLD All < LLD 0 (6.0E+1) 140La 4.15E+0 All < LLD All < LLD 0 (1.5E+1) 25

Table 8 (Cont.) - Radiological Environmental Monitoring Program Summary for 2017 Location with Hiejhest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine Pathway Number of of Mean3 (#/total #) Name Mean3 (#/total #) Mean3 (#/total #) Reported4 Sampled (Unit of Analyses Detection2 (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed1 Actual (Max.)

Broadleaf Gamma Spec Vegetation (36)

(pCi/kg wet) 1311 2.13E+1 All < LLD All < LLD 0 (6.0E+ 1) 134Cs 1.63E+1 All < LLD All < LLD 0 (6.0E+ 1) 137Cs 2.47E+1 All < LLD All < LLD 0 (8.0E+1)

Fish7 Gamma Spec (pCi/kg wet) (18) 54Mn 1.86E+1 All < LLD All < LLD 0 (1.3E+2) 58Co 1.65E+1 All < LLD All < LLD 0 (1.3E+2) 59Fe 3.81E+1 All < LLD All < LLD 0 (2.6E+2) 60Co 1.45E+1 All < LLD All < LLD 0 (1.3E+2) 65Zn 4.43E+1 All < LLD All < LLD 0 (2.6E+2) 134Cs 1.16E+1 All < LLD All < LLD 0 (1.3E+2) 137Cs 1.69E+1 All < LLD All < LLD 0 (1.5E+2) 26

Table 8 (Cont.) - Radiological Environmental Monitoring Program Summary for 2017 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine Pathway Number of of Mean3 (#/total #) Name Mean3 (#/total #) Mean3 (#/total #) Reported4 Sampled (Unit of Analyses Detection2 (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed1 Actual (Max.)

Sediment Gamma Spec (6)

(pCi/kg)8 54Mn 1.65E+1 All < LLD All < LLD 0 N/A 58Co 1.38E+1 All < LLD All < LLD 0 N/A 60Co 1.34E+1 All < LLD All < LLD 0 N/A 134Cs 8.63E+0 All < LLD All < LLD 0 (1.5E+2) 137Cs 9.56E+0 8.17E+1 (2/4) Site 21, Parr 8.17E+1 (2/2) 3.02E+1 (2/2) 0 (1.8E+2) (4.13E+1 to 1.22E+2) Reservoir, (2.7 miles (4.13E+1 to 1.22E+2) (2.87E+1 to 3.17E+1)

SSW) 27

Table 8 (cont) - Radiological Environmental Monitoring Program Summary for 2017 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 214Pb and 214Bi 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, Cat fish/Carp.)

8. Elevated levels of 214Pb and 214Bi plus other 226Ra daughter products and 228Ac plus other 232Th 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 for1311 as separate sample.

28

Table 9- Radiological Environmental Monitoring Program Preoperational (Baseline) Summary Location with Highest Annual Mean Medium or Pathway Type and Total Number of Lower Limit of All Indicator Control Locations Sampled (Unit of Number of Name Mean2 (#/total #) Nonroutine Detection1 Actual Locations Mean2 Mean2 (#/total #)

Measurement and Analyses (Distance & Direction) (Range) Reported3 (Max.) (#/totaI #) (Range) (Range)

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/m3) (1300) (1.0E-2) (1.3E-2 to 5.5E-1) (2.9 miles, NNW) (2.1E-2 to 5.5E-1) (7.9E-3 to 6.1E-1)

(1981-1982) 2.7E-2 (456/462)4 Site 8, Mon. Res. S of 3.0E-2 (42/42) 2.8E-2 (125/126)

(9.3E-3 to 6.6E-2) Rd 224, (1.5 ENE) (1.2E-2 to 6.0E-2) (1.2E-2 to 5.8E-2)

Gamma Spec (307) 134Cs 3.0E-3 All < LLD All < LLD 0 (1.0E-2) 137Cs 3.1E-3 3.2E-3 (22/241) Site 10, Met Tower, 3.8E-3 (2/22) 4.2E-3 (4/66) 0 (1.0E-2) (1.5E-3 to 5.2E-3) (2.4 miles, NNE) (2.5E-3 to 5.2E-3) (3.2E-3 to 5.6E-3)

Air Radioiodine 1311 (290) 3.6E-2 All < LLD All < LLD 0 (pCi/m3) (1982) (7.0E-2)

Direct (TLD)5 Gamma (1220) 0.5 9.9 (915/915) Site 13, North Dam, 13.1 (61/61) 9.7 (305/305) 0 (pR/hr) Monthly N/A (6.7 to 14.7) (2.9 miles, 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 miles, E) (13.1 to 14.7)

Surface Water 0 (pCi/l) 3H (43) 1.1E+3 1.4E+3 (18/29) Site 17, Columbia 1.6E+3 (2/7) 1.2E+3 (6/14)

(1981-1982) (2.0E+3) (1.1E+3 to 2.4E+3) Canal, (24.7 mile SE) (1.4E+3 to1.8E+3) (6.7E+2 to 1.6E+3)

Gamma Spec (140) 54Mn 2.7E-1 All < LLD All < LLD 0 (1.5E+1) 58Co 2.9E-1 All < LLD All < LLD 0 (1.5E+1) 59pe 6.0E+0 All < LLD All < LLD 0 (3.0E+1) 60Co 2.4E-1 All < LLD All < LLD 0 (1.5E+1) 65Zn 7.9E-1 All < LLD All < LLD 0 (3.0E+1) 95Zr 5.2E-1 All < LLD All < LLD 0 (1.5E+1) 95Nb 3.3E-1 All < LLD All < LLD 0 (1.5E+1) 134Cs 3.0E-1 All < LLD All < LLD 0 (1.5E+1) 29

Location with Highest Annual Mean Medium or Pathway Type and Total Number of Lower Limit of All Indicator Control Locations Sampled (Unit of Number of Name Mean2 (#/total #) Nonroutine Detection1 Actual Locations Mean2 Mean2 (#/total #)

Measurement and Analyses (Distance & Direction) (Range) Reported3 (Max.) (#/total #) (Range) (Range)

Reporting Period) Performed Measurements 137Cs 2.2E-1 All < LLD All < LLD 0 (1.8E+1) 140Ba 2.2E+0 All < LLD All < LLD 0 (6.0E+1) 140La 5.5E-1 All < LLD All < LLD 0 (1982 only) (1.5E+1)

Ground Water Site 26, Onsite Well 1.6E+3 (8/8) 1.3E+3 (13/13) 9.0E+2 1.5E+3 (16/16) 0 (pCi/l) 3H (29) P4, (9.5E+2 to 2.3E+3) (1.0E+3 to 1.9E+3)

(2.0E+3) (9.5E+2 to 2.3E+3)

(1981-1982) (265 ft, W)

Gamma Spec (32) 54Mn 3.7E+0 All < LLD All < LLD 0 (1.5E+1) 58Co 3.8E+0 All < LLD All < LLD 0 (1.5E+1) 59Fe 7.8E+0 All < LLD All < LLD 0 (3.0E+1) 60Co 3.8E+0 All < LLD All < LLD 0 (1.5E+1) 65Zn 8.1E+0 All < LLD All < LLD 0 (3.0E+1) 95Zr 6.8E+0 All < LLD All < LLD 0 (1.5E+1) 95Nb 4.6E+0 All < LLD All < LLD 0 (1.5E+1) 134Cs 3.7E+0 All < LLD All < LLD 0 (1.5E + 1) 137Cs 3.8E+0 All < LLD All < LLD 0 (1.8E + 1) 140Ba 1.9E+1 All < LLD All < LLD 0 (6.0E+1) 140La 5.0E0 All < LLD All < LLD 0 (1982 only) (1.5E+1)

Drinking Water6 Gross Beta7 (2.0E+0)

(pCi/l) (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 miles, SE)7 (7.0E+2 to 9.8E+2)

Gamma Spec (44) 54Mn 3.0E-1 All < LLD 0 (1.5E+1) 58Co 2.7E-1 All < LLD 0 (1.5E+1) 30

Location with Highest Annual Mean Medium or Pathway Type and Total Number of Lower Limit of All Indicator Control Locations Sampled (Unit of Number of Name Mean2 (#/total #) Nonroutine Detection1 Actual Locations Mean2 Mean2 (#/totai #)

Measurement and Analyses (Distance & Direction) (Range) Reported3 (Max.) (#/totai #) (Range) (Range)

Reporting Period) Performed Measurements 59Fe 9.6E0 All < LLD 0 (3.0E+1) 60Co 2.6E-1 All < LLD 0 (1.5E+1) 65Zn 3.4E-1 All < LLD 0 (3.0E+1) 95Zr 4.8E-1 All < LLD 0 (1.5E+1) 1311 3.4E-1 All < LLD 0 (1.5E+1) 95Nb 7.4E-1 All < LLD 0 (1.0E+0) 134Cs 2.2E-1 All < LLD 0 (1.0E+1) 137Cs 2.4E-1 All < LLD 0 (1.8E+1) 140Ba 2.5E0 All < LLD 0 (6.0E+1) 140La 4.4E-1 All < LLD 0 (1982 only) (1.5E+1)

Milk Gamma Spec (pCi/l) (94)

(1981-1982) 1311 6.3E-1 All < LLD All < LLD 0 (1.0E+0) 134Cs 3.3E+0 All < LLD All < LLD 0 (1.5E+1) 137Cs 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+0 to 6.1E+0) (5.1 miles, W) (2.8E+0 to 6.1E+0) (3.7E+0 to 9.2E+0) 140Ba 1.1E+1 All < LLD All < LLD 0 (1.5E + 1) 140La 4.4E+0 All < LLD All < LLD 0 (1.5E+1)

Grass (pCi/kg wet) Gamma Spec (1981-1982) (82) 1311 6.7E+1 All < LLD All < LLD 0 (6.0E+1) 134Cs 2.7E+1 All < LLD All < LLD 0 (8.0E+1) 137Cs 3.3E+1 5.0E+1 (13/51) Site 14, Dairy, 5.9E+1 (5/29) 1.3E+2 (6/31) 0 (8.0E+1) (1.6E+1 to 1.6E+2) (5.1 miles, W) (1.6E+1 to 1.6E+2) (1.3E+1 to 3.4E+2) 31

Location with Highest Annual Mean Medium or Pathway Type and Total Number of Lower Limit of All Indicator Control Locations Sampled (Unit of Number of Name Mean2 (#/total #) Nonroutine Detection1 Actual Locations Mean2 Mean2 (#/totaI #)

Measurement and Analyses (Distance & Direction) (Range) Reported3 (Max.) (#/total #) (Range) (Range)

Reporting Period) Performed Measurements Broadleaf Gamma Spec (10)

Vegetation (pCi/kg wet)

(1980-1982) 131 j 3.7E+1 All < LLD 0 (6.0E+1) 134Cs 1.9E+1 All < LLD 0 (8.0E+1) 137Cs 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 miles, SW) (Single Value)

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

(1980-1982) 134Cs 8.4E+0 All < LLD All < LLD 0 (8.0E+1) 137Cs 1.0E+1 All < LLD All < LLD 0 (8.0E+1)

Fish (pCi/kg wet) Gamma Spec (1980- 1982) (92) 134Cs 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) (1.1E+1 to 1.0E+2) Lake, (5.5 miles, N) 1.2E+1 to 1.0E+2) (1.0E+1 to 7.9E+1) 58Co 2.6E+1 All < LLD All < LLD 0 (1.3E+2) 54Mn 1.8E+1 All < LLD All < LLD 0 (1.3E+2) 59Fe 9.0E+1 All < LLD All < LLD 0 (2.6E+2) 65Zn 4.1E+1 All < LLD All < LLD 0 (2.6E+2) 60Co 1.8E+1 All < LLD All < LLD 0 (1.3E+2)

Sediment (pCi/kg) Gamma Spec (24)

(1980-1982) 134Cs 2.3E+1 All < LLD All < LLD 0 (1.5E+2) 137Cs 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 1.0E+3)

(2.7 miles, SSW) 32

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 pR/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.

33

Table 10 - Results of 2017 Environmental Intercomparison Program with Independent Lab, Eckert & Ziegler Analytics, Inc.

Comparison Study Vendor Lab Env Lab Date Nuclides Agreement (Measurement Unit) Results Results Gamma Isotopic Liquid 3/20 1311 97.7 102 Yes 1 Liter 141Ce 145 144 Yes (pCi/l) 51Cr 291 323 Yes 134Cs 120 118 Yes 137Cs 140 156 Yes 58Co 150 169 Yes 54Mn 165 182 Yes 59Fe 129 146 Yes 65Zn 200 230 Yes 60Co 183 193 Yes Gamma Composite Filter 10/5 141Ce 90.0 94.0 Yes (pCi) 51Cr 224 218 Yes 134Cs 208 Yes 174 137Cs 178 196 Yes 58Co 121 126 Yes 54Mn 127 142 Yes 59Fe 130 152 Yes 65Zn 190 228 Yes 60Co 263 271 Yes Alpha/Beta Water 4/19 Alpha 106 103 Yes (pCi/I) Beta 280 285 Yes Gamma Isotopic 4/16 141Ce 224 265 Yes Pulverized 51Cr 449 515 Yes Soil 134Cs 186 181 Yes (pCi/kg) 137Cs 216 251 Yes 58Co 232 264 Yes 54Mn 254 298 Yes 59Fe 199 244 Yes 65Zn 309 323 Yes 60Co 283 309 Yes 1-131 Solid 3/22 1311 98.2 100 Yes (pCi) 34

Comparison Study Vendor Lab Env Lab Date Nuclides Agreement (Measurement Unit) Results Results CO Tritium 4/17 X 9980 11000 Yes (pCi/l)

CM Gross Beta Filter 9/29 49.3 45.5 Yes

^ <

£°w (pCi) 92.2 84.1 Yes N- CO Charcoal Cartridge CT> C\J 64.6 64.9 Yes (pCi)

S Gamma Isotopic Liquid 9/26 4 Liter (pCi/l)

/N ft ft ° J=

CNj-r-COCOCMLOCOCO^-CM 0 0 0 0 0 0 0 0 0 0 OOOOO^L c

° LOLOCOCOOOCOCMCO ( / ) < / ) ( / ) < / ) < / ) < / ) ( / ) ( / ) < / ) < / )

Oot-CNOSICMT-T-T-CMCO >->->->->->->->->->-

I^a>CNJCMT-v-T-^CMC\i N O

Table 11 -2017 Environmental Sampling Program Deviations Sample Month Media Location (Week No.) Cause for Deviation Site 19 Apr (15) TLD missing.

• TLD Site 94 Jul (28) Missing 1 of 2 TLD's Site 10 Oct (41) Missing 1 of 2 TLD's Site 94 Oct (41) Missing 1 of 2 TLD's

• Control location 21 miles from Summer Station 36

xoej<

ENS ° JC JT5^

'anc'AOTER

'fUrt-HAM&W hs (V/,Oj

\l \,?u .c*rrs mr"-':

"?j

a V. J /. ax*~-\i*M+I. \ \

I,'>>fl //ifv<<\ bvUljtntM

,."v

,' ftAUR \ r> C.W

' >ll-lil*iyHT ,1 SHAW "tfi A R LINl t'.I /

Tiff*'/>><<>££>>

" LEGEND

'(tfpw/twC; 0 CONTROL SAMPLE LOCATIONS A=AIR PARTICULATE SITE D = DIRECT (TLD) SITE OJD'A ((Vp.liO.wi i< /. -h.

• AV/SW V ESE-\^A-1 = AIRBORNE RADIOIODINE SITE TCH L A, W=WATER SITE

" SOMV E'R LtEXING 0= OTHER (GARDEN PRODUCTS, FISH, SEDIMENT, GRASS, MILK)

MWWMl Cf^HbUN \v noon REFERENCE!

THE BASE FOR THIS MAP WAS PREPARED FROM A PORTION OF USDS STATE OF GEORGIA, 1070.

'.50 Miles.

h trior* 57ATUTC *<<vC£

'W^TTiirirjA

/*; BARNWEI/L LAKE MOULVnlr South Carolina Electric & Gas Co.

Virgil C. Summer Nuclear Station Regional Location Map Figure 1-1 HEV. DATE l?.-e

lVl\

w 315?'-

C-°'M i X/

W. ^ OHEEII WEER RESERVOI (Aj.D)/

1\\

VFnlRFIELD//

• /* PUMPED ,

I I

E#

t STORAGE,'/ i

,"j FACILITY// I,

/ ...i r / 'i!

r.. *2s§d.

//  ?

/ LAKE xt TEMP (,pN 4 '-/.

Hotiiron Yx

,))

<*JL V- <m i

""W^k

/'<'* i w,.

)w  !* -x-,V:\ '*< SEWACE

&B3

• y -A 3 I PLANT TREATMENT-" /'.p.

SAMPLER //

'/ 1 \v>

9UBSWTI0M e"01 -"-*v access rd.

• 77(W) "*=--*'

V'%')'t(Dy Li-CONTINUOUS SAMPLER pflwgn Hues /

. .v/

2^-M (D) 6>>/;, aO ?X~-7 (A,I,D,0)/

^ if

\\\ POWER

\\\ LINES V

w Mr im \ X. ji^nOOD BLOCKED^!/f/'l jI j j y/^

XX*'.*.. ffl/fOHEIT LIKES I If I /

135°

,JX [

"X! ( D)

Jf c r v J /

WPOUER LINES J6 y/X'SGRF I: \

M  ;

f

/ i^Wik 7

" # ,u\/ *7 180'

\M LEGEND FIGURE 1-3 4>> = PRIMARY SAMPLE LOCATIONS jr - A = AIR PARTICULATE SAMPLE SITE

• w# D = DIRECT (TLD)SAMPLE SITE (QUARTERLY) \\

ffl ft/*

/ V I = AIRBORNE RADIOIODINE SAMPLE SITE 3CIUTH CAROLINA LLICCTRIC IU C1A3 O if TO PARR- W = WATER SAMPLING LOCATION . V.C. SLIMMER NUCLEAR STATION oil SITE TLP'PLACEMENT ftjfEA MAP '

B>>iK6^"MlTO>>6uM. ILOtCM?* trWLIK) 3 0 = OTHER

\ \. Mx

3

<Q e

© South Carolina Electric & Gas Co Virgil C Summer Nuclear Station RADIOLOGICAL MONITORING PROGRAM SECURITY AREA GROUNDWATER SITES

-n