ML16187A317
| ML16187A317 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 06/29/2016 |
| From: | Ryan Justice South Carolina Electric & Gas Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML16187A317 (46) | |
Text
Robert L. Justice General Manager, Nuclear Plant Operations 803.345.4707
~SCE&G@ A SCANA COMPANY June 29, 2016 Document Control Desk U. S.'.Nuclear Regulatory Commission Washington, DC 20555
Dear Sir/Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
Reference:
Letter from Robert L. Justice to Document Control Desk dated, April 7, 2016, Radiological Environmental Operating Report, ML16104A028 South Carolina Electric & Gas Company hereby submits a revised Annual Radiological Environmental Operating Report for the VCSNS for 2015. The report submitted in the April 7, 2016, letter (Reference) did not contain Figures 1-1, 1-2, 1-3, 1-4 and 1.5. This issues has been documented in the station's Corrective Action Program as CR-16-03163.
The submittal of this report is required by Section 6.9.1.6 of the VCSNS Technical Specifications.
If there are any questions, please contact Ms. Susan B. Reese at (803) 345-4591.
Very truly yours, SBR/RLJ/wt Enclosure c: K. B. Marsh (w/o enclosure) NRC Resident Inspector S. A. Byrne M. Coleman J.B. Archie M. E. Jordan N. S. Carns K. M. Sutton J. H. Hamilton (w/o enclosure) C. S. Logan J. W. Williams (w/o enclosure) D. A. Solley (SCDHEC)
S. M. Shealy (w/o enclosure) NSRC W. M. Cherry (w/o enclosure) RTS '(LTD 312, CR-16-03163)
C. Haney File (818.02-2, RR 8300)
S. A. Williams PRSF (RC-16-01110)
V. C. Summer Nuclear Station
- P. 0. Box 88
- Jenkinsville, SC* 29065
- F(803) 941-9776
(.
A SCANA COMPANY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPERATING PERIOD JANUARY 1, 2015 - DECEMBER 31, 2015 June 2016 Prepared by:
Brett Williams Health Physics Specialist Michael Jordan 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 2015.
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 sixty two analyses (1,262) performed to compile the data for the 2015 Environmental Report. Supplemental samples comprising two hundred fifty eight (258) 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 2015 from V.C. Summer related radionuclide concentrations were* within the range of concentrations observed in the past. 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 2015 Fission and Activated Corrosion Product Activity in 6 Sediment 3 Required Sampling Site Locations 8 4 Results of the 2015 Land Use Census Verification 11 5 Critical Receptor Evaluation for 2015 12 6 Radiological Environmental Monitoring Program 13 Specifications 7 Supplemental Radiological Environmental Monitoring 18 8 Radiological Environmental Monitoring Program Summary 22 for 2015 9 Radiological Environmental Monitoring Program 28.
Preoperational (Baseline) Summary 10 Results of 2015 Environmental Inter-comparison Program 33 with Independent Lab, Eckert & Ziegler Analytics, Inc.
11 2015 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 23rd fuel cycle.
VCSNS is operating in conjunction with the adjacent Fairfield Pump Storage Facility (FPSF) which consists of eight reversible pump-turbine units of *50 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 structur~s 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.
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 2015. Data trends, control/indicator and preoperational/operational data inter-comparisons, 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 inter-comparisons 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 Exposure Pathway Monitoring Media Gaseous Immersion Dose and other Tliermoluminescent 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 (lnQestion) DrinkinQ Water SamplinQ 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 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 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 inter-comparison program. Results of the inter-comparison program with an outside vendor and VCSNS Count Room were satisfactory in 2015. 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 2015 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 2015 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/gan;:len) was found to have a calculated dose of 2.35E+O 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 2.07E+O and 2.98E+O 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 2015 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 99.4%. 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 (2.34E-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, 137 Cs and 131 1 were 2.54E-3, 2.58E-3 and 1.59E-2 pCi/m 3 , respectively. The average maximum results support the gaseous effluent release data reported in the 2015 Annual Radiological Effluent Release Report for VCSNS. 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 1.28E+1 µR/hr. This is similar to the 2014 value of 1.14E+1 µR/hr and consistent with the highest mean exposure rate of 1.40 E+1 µR/hr measured during the preoperational period. 99% 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 above MDA in three samples at Site 21 (Parr Reservoir 2.7 mi. SSW), at concentrations of 7.65E+2 pCi/L, 8.04E+2 pCi/L, and 6.25E+2 pCi/L. The presence of tritium was also detected in three samples at Site 23 (Monticello Reservoir 0.5 mi. ESE). The tritium, concentrations were 6.86E+2 pCi/L, 7.81E+2 pCi/L, and 9.65E+2 pCi/L. 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 was detected in four supplemental ground water samples at Site 123 (NPDES Well GW-16 0.34 SSE), at concentrations of 1.79E+3 pCi/L, 1.55E+3 pCi/L, 2.26E+3 pCi/L, and 3. 79E+3 pCi/L. 100% 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 above MDA in four samples taken at Site 17 (Columbia Water Works 25.0 mi. SE) at concentrations of 6.37E+2 pCi/L, 6.54E+2 pCi/L, 8.01 E+2 pCi/L, and 5. 71 E+2 pCi/L.. The highest indicator and control site-specific gross beta activity was measured at Site 28 (New Nuclear Deployment 2.6 mi. SSE) at a level of 4.30E+O pCi/I. 97.2% of indicator/control drinking water samples were collected.
There were no milk samples collected in 2015. Milk sampling is required to be performed at the three highest dose locations within 5 kilometers of the plant or at 5 to 8 kil.ometers 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.
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Gamma spectroscopy measurement of supplemental grass samples collected indicated 137Cs in 3 of 12 samples at Site 2 (transmission line 1.2 mi. SW) at concentrations of 2.18E+1 pCi/kg, 2.35E+1 pCi/kg, and 2.85E+1 pCi/kg. The maximum preoperational control activity was 3.40E+2 pCi/kg. 100% of indicator/control supplemental grass samples were collected.
l 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 137 Cs in 2 of 4 indicator samples. Site 21 (Parr Res. 2.7 mi. SSW) at concentrations of 2.27E+2 and 1.28E+2 pCi/kg were detected. 137 Cs was also detected in 2 of 2 control samples taken at Site 22 (Neal Shoals 26 mi. NNW) at concentrations of 5.99E+1 and 5.70E+1 pCi/kg. All required indicator/control sediment samples were collected.
Table 2 - 2015 Fission and Activated Corrosion Product Activity in Sediment Corresponding -Calculated Location Radionuclide Activity (pCi/kg) Annual Dose Equivalent (mrem/yr)
Total Body Maxim,um Mean- Maximum Mean Parr Reservoir 137Cs 2.27E+2 1.78E+1 1.91E-2 1.50E-2 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 four drinking water samples taken at site 17 (Columbia Water Works 25.0 mi. SE) and two supplemental samples taken at site 99 (Nuclear Operations Bldg). Concentrations were well below drinking water standards.
- Co-60 and Cs-137 was detected in one supplemental soil sample taken at Site 25 (Fairfield Pumped Storage Penstocks 0.9 WNW).
- Tritium in all four supplemental ground water samples taken at Site 123 (NPDES Well GW-16 0.34 mi. SSE).
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 Distance 1 Description Direction 2 Sample Type(s) 3 No. (Miles) 1 Borrow Pit 1.2 179.8 s DQ 2 Transmission Line 1.2 225.0 SW AP, RI, DQ 3 Firing Range 1.2 270.0W DQ 4 Fairfield Hydro 1.2 289.5WNW DQ 5 Transmission Line Entrance 0.9 144.0 SE DQ 6 Environmental Lab Garden 1.0 111.0 ESE AP,Rl,GA,DQ,GW 7 Environmental Lab Garden 1.0 97.8 E AP,Rl,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 6.5 277.0W MK,GR 16 Dairy (Parr) 4 20.0 275.5W MK,GR 16a TLD Location 28.0 278.6W DQ 17 Columbia Water Works 25.0 144.0 SE AP,Rl,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 270.0W GW 27 On Site Well (PS) 510 Ft 180.0 s GW 28 New Nuclear Deployment° 2.6 170.2 SSE ow 29 Trans. Line WSW of VCSNS 1.0 260.6WSW DQ 30 Oak Tree North of Borrow Pit0 1.0 I 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 ow 40 Emergency Operations Facility' 11.9 157.0 SSE GA,GR 8
Table 3 (cont) - Required Sampling Site Locations Site Distance 1 Description 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 2.8 256.6WSW DQ 45 Rd 33 at Pomaria 5.8 253.2WSW DQ 46 Rd 28 at Heller's Creek 3.7 291.5WNW 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 2.5 197.0 SSE DQ 59 New Nuclear Deployment° 2.6 170.2 SSE DQ,GW 60 Rd 98 near Rd 28 3.5 274.6W DQ 101 Remediation Well (8-2) 300 Ft NNW GW 102 Remediation Well (8-6) 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 (8-36) 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 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 OW = 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. Th.e 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.
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Table 4 - Results of the 2015 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 Essie 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 KenNirg Graham (*) 0 4.98 Steve All 0 4.83 w Jerry Cassada 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 (A) Change In Closest Residence
(*) Keneth and Virgil Graham cows grazed in the W and WSW 11
Table 5 Critical Receptor Evaluation for 2015 SECTOR MILES DIQ DOSE*
NAME PATHWAY X/Q mRem/y P. Oliver N 3.73 Res 1.90E-07 5.40E-10 7.08E-03 Thomas K. Crumblin NNE 2.9 Res 4.30E-07 1.40E-09 1.61E-02 Eddie Robinson NNE 3.99 B,Gar 2.30E-07 6.60E-10 2.39E-01 Gregrey Guinyard Jr. NE 1.55 Res 2.00E-06 6.80E-09 7.51E-02 Rufus (Ruddy) Pearson NE 2.66 Res, Gar 6.30E-07 1.90E-09 5.21 E-01 Bessie Greaa ENE 1.56 Res 1.70E-06 6.10E-09 6.40E-02 1
Essie Mae Glenn ENE 1.68 Res,Gar 1.50E-06 5.00E-09 1.35E+OO Garden-7 ** E 1 Res,Gar 3.30E-06 1.1 OE-08 2.98E+OO Sheryl A. Colley E 1.2 Res 2.10E-06 7.00E-09 7.88E-02 Garden-6 ** ESE 1 Res,Gar 2.20E-06 7.70E-09 2.07E+OO Carrie Lee Martin ESE 1.1 Res 1.80E-06 6.00E-09 6.75E-02 James Pearson ESE 1.36 Res,Gar 1.1 OE-06 3.50E-09 9.53E-01 Mary White SE 1.44 Res, Gar 5.50E-07 2.60E-09 6.80E-01 Sim Roberts SE 4.7 Res,Gar,B 4.50E-08 1.60E-10 5.90E-02 Ronnie Mann SSE 2.39 Res, Gar 1.40E-07 9.30E-10 2.38E-01 Kelly Boulware s 3.56 Res,Gar 7.50E-08 5.50E-10 1.40E-01 Shirley Counts s 5 Res,Gar,B 3.70E-08 2.60E-10 9.20E-02 NND Construction Site SSW 0.49 Res 7.90E-06 8.50E-08 3.26E-01 Nick Bates SSW 3.11 Res 1.30E-07 1.30E-09 5.31 E-03 Joe Smith SSW 4.73 Res,B 5.50E-08 5.00E-10 5.18E-02 Marvin Miller SW 3.3 Res,Gar 1.1 OE-07 8.90E-10 2.25E-01 Ron Hope WSW 2.9 Res 1.20E-07 7.20E-10 4.66E-03 Steve All WSW 4.83 Res,Gar,G 4.10E-08 2.30E-10 6.21E-02 KenNirg Graham WSW 4.98 B 3.80E-08 2.10E-10 2.09E-02 Jerrv Cassado w 2.55 Res 1.10E-07 6.1OE-10 4.25E-03 Marion Livingston w 2 B 1.90E-07 1.1 OE-09 1.10E-01 Marion Livingston w 2.8 Res, Gar 9.00E-08 4.90E-10 1.27E-01 Marion Livingston w Res,Gar,B BOTH BOTH 2.37E-01 KenNirg Graham w 5 Res,Gar,B,C/M 2.70E-08 1.30E-10 1.62E-01 Unknown Resident WNW 2.53 Res 8.80E-08 4.00E-10 3.35E-03 Ronnie Leitzsey WNW 4.15 C/M,B,G/M,G 3.10E-08 1.30E-10 1.29E-01 Ronnie Leitzsey WNW 4.72 Res, Gar 2.40E-08 9.70E-11 2.57E-02 Ronnie Leitzsey WNW Res,Gar,C/M,B,G/M,G BOTH BOTH 1.55E-01 Louise Workman NW 3.9 Res 9.80E-08 3.30E-10 3.68E-03 Frank March NNW 2.9 Res,Gar,B 2.90E-07 8.40E-10 3.15E-01 ODCM Organ Dose E 1.1 Res,Gar 2.60E-06 8.70E-09 2.35E+OO Pathway Res = Residence B =Beef G =Goat Gar= Garden C/M = Cow/Milk(lnfant) G/M = Cow/Milk(lnfant)
Footnotes:
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 Sample Type & Frequency of Criteria for Selection of Sampling and Collection Pathway and/or Location Analysis Sample Number & Location Frequency Sample 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 2
are anticipated.
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 NIA 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 ofVll(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.
2 prevalent wind directions.
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.
13
Exposure Sampling and Collection Sample Type & Frequency of Criteria for Selection of Pathway and/or Location Analysis Sample Number & Location Frequency Sample Ill. Direct A) 13 Indicator stations to Monthly or quarterly 1,2,3,4,5,6, Gamma dose monthly or 5
form and inner ring of exchange *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 5
an outer ring of stations in exchange '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.
7 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 6 3 IV. Surface A) 1 Indicator sample Time composite samples with 21 Gamma isotopic monthly 5
Water downstream to be taken at collection every month. with quarterly composite a location which allows for (by location) to be 7
mixing a dilution in the analyzed for tritium.
ultimate receiving river.
6 3 Gamma isotopic monthly B) 1 Control sample to be Time composite samples with 22 5 with quarterly composite taken at a location on the collection every month.
(by location) to be receiving river sufficiently analyzed for tritium.
7 far upstream such that no effects of pumped storage operation are anticipated.
6 3 C) 1 Indicator sample to be Time composite samples with 23 Gamma isotopic monthly 5 with quarterly composite taken in the upper reservoir collection every month.
of the pumped storage (by location) to be 7
facility at the plant analyzed for tritium.
discharge canal.
7 V. Ground Water A) 12 Indicator samples to be Quarterly grab sampling. 6, 26, 27, Gamma isotopic and taken within the exclusion 101-103, tritium analyses 7
boundary and in the 106, quarterly.
direction of potentially 108,110, affected ground water 112-114 supplies.
7 B) 1 Control sample from Quarterly grab sampling. 59 Gamma isotopic and unaffected location. tritium analyses 7
quarterly.
14
Exposure Sampling and Collection Sample Type & Frequency of Criteria for Selection of Pathway and/or Frequency Location Analysis Sample Number & Location Sample 5
VI. Drinking A) 1 Indicator sample from a Monthly grab sampling. 28 Month!/ gamma isotopic Water nearby public ground water and gross beta analyses supply source. and quarter!/ composite for tritium analyses.
B) 1 Indicator (finished water) Monthly composite sampling. 17 Month!/ gamma isotopic sample from the nearest and gross beta analyses downstream water supply. and quarter!/ composite for tritium analyses.
C) 1 Control (finished water) Monthly composite sampling. 39 Month!/ gamma isotopic sample from an unaffected and gross beta analyses water supply. and quarter!/ 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 pastures, 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, 5
there are none then 1 found in monthly other times.
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 10 per year.
B) 1 Control sample to be Semimonthly when animals 16 Gamma isotopic and I-taken at the location of a are on pastures, monthly other 131 analysis dairy> 20 miles distance times. 5' 11 semimonthlys when and not in the most animals are on pasture, 2 5 prevalent wind direction. monthly other times.
5 C) 1 Indicator grass (forage) Monthly when available. 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 VII.A.
5 11 D) 1 Control grass (forage) Monthly when available.
- 16 Gamma isotopic.
sample to be taken at the location ofVll(B) above.
15
Exposure Sample Type & Frequency of Criteria for Selection of Sampling and Collection Pathway and/or Frequency Location Analysis Sample Number & Location Sample 5
VIII. Food A) 2 Indicator samples of Monthly when available. 6 Gamma isotopic on edible Products broad leaf 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 10 than 1 mrem/yr.
5
- 8) 1 Control sample for the Monthly when available. 40 Gamma isotopic on edible same foods taken at least portion.
1O 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.
9 1 3 IX. Fish A) 1 Indicator sample to be Semiannual collection. 23 Gamma isotopic on edible 9
taken at a location in the portions semiannually.
upper reservoir.
9
- 8) 1 Indicator sample to be Semiannual collection. 1 21 3
Gamma isotopic on edible 9
taken at a location in the portions semiannually.
lower reservoir.
9 1 3 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:
9 3 X. Sediment A) 1 Indicator sample to be Semiannual grab sample. 23 Gamma isotopic.
taken at a location in the upper reservoir.
9 3 B) 1 Indicator sample to be Semiannual grab sample. 21 Gamma isotopic.
taken on or near the shoreline of the lower reservoir.
9 3 C) 1 Control sample to be Semiannual grab sample. 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 Vll(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-1. 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-11. Radioiodine A) 1 Indicator sample to be taken from the location of S-1(A) above.
Continuous sampler operation with weekly collection.
7
[] Gamma isotopic for 1-131 weekly.
S-111. Direct A) 5 stations to be placed Quarterly exchange ; two 61,62,63, Gamma dose within the exclusion or more dosimeters at 68 & 99 quarterly.
boundary. each location.
7 B) 2 stations to be placed Quarterly exchange ; 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 13 5 Water taken of the combined monthly collection. ' 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 Collection Frequency Location Analysis INGESTION:
4 A) 1 Sample from one of the 8iweekl¥ grab 14 Gamma isotopic and S-Vll. Milk nearest affected dairies at sample. '1'1,+ 1-131 analysis or beyond 5 miles. biweekly.
- 8) 1 Control sample to be 8iweekl¥ grab 16 Gamma isotopic and taken at the location of a sample. ,1'1,+ 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.
14 sample to be taken at the available.
location of S-Vll(A) above.
4 D) 1 Control grass (forage) Monthly when 16 Gamma isotopic.
S-Vll. Milk 14 sample to be taken at the available.
location of S-Vll(8) 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-Vll (E) above.
G) 1 Indicator grass (forage) Quarterly when available. 25 Gamma isotopic.
sample to be taken at location of penstock leak.
S-Vlll. Food A) 1 Indicator sample of Annually during growing 6,7 Gamma isotopic on 11 Products various types of foods season. edible portion.
grown in the area surrounding the plant (root, fruit, grain).
- 8) 1 Control sample of various Annually during growing 40 Gamma isotopic on 11 types of foods grown. (root, season. edible portion.
fruit, grain).
Corbi cu la C) 1 Indicator sample of edible Semiannual. 23 Gamma isotopic.
portions.
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, 0068 &
008.
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.
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 2015 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 Name Mean3 (#/~ota*I #) 3 4 Mean3 (#/total #) Mean (#/total #) Reported (Unit of Analyses Actual (Distance & Direction) (Range)
(Range) (Range) Measurements Measurement) Performed 1 (Max.)
Air Particulate Gross Beta 6.30E-3 2.09E-2 (256/258) Site 7, Environmental 2.34E-2 (50/51) 1.87E-2 (51/52) 0 (pCi/m 3) (310) (1.0E-2) (5.15E-3 to 4.50E-2) Lab Garden, (8.40E-3 to 3.54E-2) (5.71 E-3 to 2.93E-2)
(1.0 mi. E)
Gamma Spec (72)
'""Cs 2.54E-3 All< LLD All< LLD 0 (5.0E-2)
"Cs 2.58E-3 All< LLD All< LLD 0 (6.0E-2)
Air Radioiodine '"'I (310) 1.59E-2 All< LLD All< LLD 0 (oCi/m3 ) (7.0E-2)
Direct (TLD) 5 Gamma(135) 8.62E+O (115/115) Site 4, Fairfield 1.28E+1 (4/4) 8.55E+O (20/20) 0
(µR/hr) Quarterly N/A (5.19E+O to 1.30E+1) Hydro, (1.2 mi. WNW) (1.22E+1 to 1.30E+1) (5.14+0 to 1.17E+1)
Gamma(24) 9.16E+O (24/24) ,Site 52, Monticello Rd. 1.19E+1 (4/4) N/A 0 Special Interest N/A (5.29E+O to 1.25E:t1) 11, (3.8 mi. NNE) (1.14E+1to1.25E+1)
Surface Water ~H (36) 4.32+2 7.71E+2 (6/24) Site 23, Monticello Res, 8.11 E+2 (3/12) All< LLD 0 (oCi!I) (2.0E+3) {6.25E+2 to 9.65+2) (0.5mi. ESE) (6.86E+2 to 9.65E+2)
Gamma Soec(36) b4Mn 2.24E+O All< LLD All< LLD 0 (1.5E+1)
Meo 2.42E+O All< LLD All< LLD 0 (1.5E+1)
""Fe 5.25E+O All< LLD All< LLD 0 (3.0E+1) ouGo* 2.26E+O All< LLD All< LLD 0 (1.5E+1) oozn 4.56E+O All< LLD All <LLD 0 (3.0E+1) *'
0
" Zr 3.35E+O All< LLD All< LLD 0 (3.0E+1) 0
" Nb 3.37E+O All< LLD All< LLD 0 (1.5E+1)
'""Cs 1.95E+O All< LLD All< LLD 0 (1.5E+1) 22
Table 8 (cont.) - Radiological Environmental Monitoring Program Summary for 2015 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Non routine 3
Pathway Number of of Mean (#/total #) Name Mean 3 (#/total #) 3 Mean (#/total #) Reported 4 2
Sampled (Unit of Analyses Detection (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed1 Actual (Max.)
1 Surface Water "'Cs 2.44E+O All< LLD All< LLD 0 (Continued) (1.8E+1)
,..vBa 2.58E+1 All< LLD All< LLD 0 (6.0E+1) iquLa 5.24E+O All< LLD All< LLD 0 (1.5E+1)
Ground Water "H (52) 4.32E+2 All< LLD All< LLD 0 (pCill) 2.00E+3 Gamma Spec (51) 0 "Mn 6.65E+O All< LLD All< LLD 0 (1.5E+1) ooco 6.15E+O All< LLD All< LLD 0 (1.5E+1) 0
\IFe 1.33E+1 All< LLD All< LLD 0 (3.0E+1)
OU Co 4.64E+O All <LLD All< LLD 0 (1.5E+1) bozn 6.43E+O All< LLD All< LLD 0 (3.0E+1) 0
" Zr 8.31E+O All< LLD All< LLD 0 (3.0E+1) 0
" Nb 5.68E+O All< LLD All< LLD 0 (1.5E+1)
'".. Cs 5.28E+O All< LLD All< LLD 0 (1.5E+1)
,..vBa 2.71E+1 All< LLD All< LLD 0 (6.0E+1)
-,,.uLa 8.16E+O All< LLD All< LLD 0 (1.5E+1) 23
Table 8 (Cont.) - Radiological Environmental Monitoring Program Summary for 2015 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine Reported 4 3 3 3 Pathway Number of of Mean (#/total #) Name Mean (#/total #) Mean (#/total #)
Sampled (Unit of Analyses Detection 2 (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed1 Actual (Max.)
Drinking Water6 Gross Beta (35) 1.40E+O 2.41 E+O (21/24) Site 28, New Nuclear 2.62E+O (10/12) 2.22E+O (9/11) 0 (pCi/I) (4.00E+O) (1.55E+O to 4.30+0) Deployment, (1.64E+O to 4.30+0) (1.51 E+O to 3.00E+O)
(2.6 mi, SSE)
~H (35) 4.31E+2 6.66E+O (4/24) Site 17, Columbia 6.66E+O (4/12) All< LLD 0 (2.0E+3) (5.71 E+2 to 8.01 +2) Water Works (5.71 E+2 to 8.01 +2)
(25.0 mi, SE)
Gamma Spec (70) 9
""Mn 2.52E+O All< LLD All< LLD 0 (1.5E+1) ooco* 2.64E+O All< LLD All< LLD 0 (1.5E+1)
""Fe 6.86E+O All< LLD All< LLD 0 (3.0E+1) bu Co 4.62E+O All< LLD All< LLD 0 (1.5E+1)
""Zn 5.35E+O All< LLD All< LLD 0 (3.0E+1)
""Zr 6.04E+O All< LLD All< LLD 0 (3.0E+1)
""Nb 3.64E+O All< LLD All< LLD 0 (1.5E +1) oa I 4.22E-1 All< LLD All< LLD 0 (1.0E+O)
,~4cs 2.61E+O All< LLD All< LLD 0 (1.5E+1) 1
"" Cs 3.18E+O All< LLD All< LLD 0 (1.8E+1)
Hu8a 1.76E+1 All< LLD All< LLD 0 (6.0E+1)
...Ula 4.10E+O All< LLD All< LLD 0 (1.5E+1) 24
Table 8 {Cont.) - Radiological Environmental Monitoring Program Summary for 2015 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 3
Mean (#/total #)
3 Mean (#/total #) Reported 4 2
Sampled (Unit of Analyses Detection (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed1 Actual !Max.)
Broad leaf Gamma Spec Vegetation (36)
(pCi/ki:i wet) l::Sll 2.12E+1 All< LLD All< LLD 0 (6.0E+ 1) i::s4Cs 1.58E+1 All< LLD All< LLD 0 (6.0E+ 1) i::srcs 2.24E+1 All< LLD All< LLD 0 (8.0E+1)
Fish 7 Gamma Spec (pCi/ki:i wet) (18) 4
" Mn 2.01E+1 All< LLD All< LLD 0 (1.3E+2)
"~co 2.15E+1 All< LLD All< LLD 0 (1.3E+2)
"\!Fe 4.86E+1 All <LLD All< LLD 0 (2.6E+2) ouco 2.29E+1 All< LLD All< LLD 0 (1.3E+2) t:i"zn 5.33E+1 All< LLD All< LLD 0 (2.6E+2)
'".. Cs 2.04E+1 All< LLD All< LLD 0 (1.3E+2) ov*cs 1".66E+1 All< LLD All< LLD 0 (1.5E+2) 25
Table 8 (Cont.) - Radiological Environmental Monitoring Program Summa!"Y for 2015 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Non routine Reported4 3 3 3 Pathway Number of of Mean (#/total #) Name Mean (#/total #) Mean (#/total #)
2 Sampled (Unit of An*a1yses Detection (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed 1 Actual
'(Max.)
Sediment Gamma Spec (6)
(pCilkg) 6 0
'1Mn 1.93E+1 All< LLD All< LLD 0 NIA 0
"Co 1.11E+1 All< LLD All< LLD 0 NIA ouco 1.51E+1 All <LLD All< LLD 0 NIA
'"~Cs 1.53E+1 All< LLD All< LLD 0 (1.5E+2)
- v*cs 1.24E+1 1.78E+2 (214) Site 21, Parr 1.78E+2 (2/2) 5.85E+1 (212) 0 (1.8E+2) (1.28E+2 to 2.27E+2) Reservoir, (2. 7 mi. (1.28E+2 to 2.27E+2) (5.70E+1 to 5.99E+1)
SSW) 26
Table 8 (cont) - Radiological Environmental Monitoring Program Summary for 2015 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 NRG 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 µR/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 levels of 214Pb and 214 Bi plus other 226 Ra daughter products and 228Ac plus other 232 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.
131
- 8. Drinking water resin prepared and counted for 1 as separate sample.
27
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 Mean 2 (#/total #) Nonroutine Detection 1 Actual Locations Mean 2 (Range)
Mean2 (#/total #)
Reported 3 Measurement and Analyses (Distance & Direction)
(Max.) (#/total#) (Range) (Range)
Reporting Period) Performed Measurements Air Particulate Gross Beta 4.1E-3 1.1 E-1 (562/564) 4 Site 13, North Dam, 1.3E-1 (52/52) 1.2E-1 (1531155) 0 3
(pCi/m ) (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 6.1E-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)
'"qCs 3.0E-3 All< LLD All< LLD 0 (1.0E-2)
- V<cs 3.1 E-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 mi NNE) (2.5E-3 to 5.2E-3) (3.2E-3 to 5.6E-3)
Air Radioiodine "I (290) 3.6E-2 All< LLD All< LLD 0 3
(pCi/m ) (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
(µR/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 Qua rte riv N/A (6.8 to 14. 7) Church, (2.8 mi E) (13.1to14.7)
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) (2.0E+3) (1.1 E+3 to 2.4E+3) Canal, (24.7 mi, SE) (1.4E+3 to1.8E+3) (6. 7E+2 to 1.6E+3)
Gamma Spec (140)
"4Mn 2.7E-1 All< LLD All< LLD 0 (1.5E+1)
""Co 2.9E-1 All< LLD All< LLD 0 (1.5E+1) 0
~Fe 6.0E+O All< LLD All< LLD 0 (3.0E+1) au Co 2.4E-1 All< LLD All< LLD 0 (1.5E+1) oozn 7.9E-1 All~ LLD All< LLD 0 (3.0E+1)
""Zr 5.2E-1 All< LLD All< LLD 0 (1.5E+1)
""Nb 3.3E-1 All< LLD All< LLD 0 (1.5E+1)
Location with HiQhest Annual Mean Medium or Pathway Type and Total Number of Lower Limit of All Indicator Control Locations Sampled (Unit of Number of Name Mean 2 (#/total #) Nonroutine Detection1 Actual Locations Mean2 Mean2 (#/total #) Reported 3
- Measurement and Analyses (Distance & Direction) (Range) (Range)
(Max.) (#/total#) (Range) Measurements Reportini:i Period) Performed 1 1
" Cs 2.2E-1 All< LLD All< LLD 0 (1.8E+1)
'"u8a 2.2E+O All< LLD All< LLD 0 (6.0E+1) l .. Ula 5.5E-1 All< LLD All< LLD 0 (1982 only) (1.5E+1)
Ground Water Site 26, Onsite Well 3 9.0E+2 1.5E+3 (16/16) 1.6E+3 (8/8) 1.3E+3 (13/13)
(pCi/I) H (29) P4, 0 (2.0E+3) (9.5E+2 to 2.3E+3) (9.5E+2 to 2.3E+3) (1.0E+3 to 1.9E+3)
(1981-1982) (265 ft, W)
Gamma Spec (32) 4
" Mn 3.7E+O All< LLD All< LLD. 0 (1.5E+1)
"°Co 3.BE+O All< LLD All< LLD 0 (1.5E+1) 0 "Fe 7.8E+O All< LLD All< LLD 0 (3.0E+1) buCO 3.8E+O All< LLD All< LLD 0 (1.5E+1)
UV'-00 8.1E+O All< LLD All< LLD 0 (3.0E+1)
""Zr 6.8E+O All< LLD All< LLD 0 (1 :sE+1) 0
" Nb 4.6E+O All< LLD All< LLD 0 (1.5E+1) 1
""Cs 3.7E+O All< LLD All< LLD 0 (1.5E + 1)
'"'Cs 3.8E+O All< LLD All< LLD 0 (1.8E + 1)
"'ula 5.0EO All< LLD All< LLD 0 (1982 only) (1.5E+1)
Drinking Water6 Gross Beta7 (2.0E+O)
(pCi/ll (1981-1982)
"H (14) 6.3E+2 7.8E+2 (6/14) Site 28, Jenkinsville, 8.4E+2 (3/7) 0 (1.0E+3) (6.8E+2 to 9.8E+2) (2.0 mi SE) 7 (7.0E+2 to 9.8E+2)
Gamma Spec (44) -
""Mn 3.0E-1 All< LLD 0 (1.5E+1) ooco 2.?E-1 All< LLD 0 (1.5E+1) 29
Location with Hiohest Annual Mean Medium or Pathway Type and Total Number of Lower Limit of All Indicator Control Locations Sampled (Unit of Number of Name Mean 2 (#/total #) Nonroutine Detection1 Actual Locations Mean2 Mean 2 (#/total #)
Measurement and Analyses (Distance & Direction) (Range) Reported 3 (Max.) (#/total #) (Range) (Range)
Reporting Period) Performed Measurements 0
~Fe 9.6EO All< LLD 0 (3.0E+1) ouco 2.6E-1 All< LLD 0 (1.5E+1) 00£.n 3.4E-1 All< LLD 0 (3.0E+1)
~bzr 4.8E-1 All< LLD 0 (1.5E+1)
"I 3.4E-1 All< LLD 0 (1.5E+1)
~"Nb 7.4E-1 All< LLD 0 (1.0E+O)
- v~cs 2.2E-1 All< LLD 0 (1.0E+1)
'"'Cs 2.4E-1 All< LLD 0 (1.8E+1)
,..vBa 2.5EO All< LLD 0 (6.0E+1) 1<ivLa 4.4E-1 All< LLD 0 (1982 only) (1.5E+1)
Milk Gamma Spec (pCi/I) (94)
(1981-1982)
'"'I 6.3E-1 All< LLD All< LLD 0 (1.0E+O) 4 1d Cs 3.3E+O All< LLD All< LLD 0 (1.5E+1) 1"'Cs 4.6EO 4.1E+O (8/47) Site 14, Dairy, 4.1 E+O (8/47) 5.7E+O (37/47) 0 (1.5E+1) (2.8E+O to 6.1 E+O) (5.1 mi., W) (2.8E+O to 6.1 E+O) (3.7E+O to 9.2E+O) l'!u8a 1.1 E+1 All< LLD All< LLD 0 (1.5E + 1)
,..vLa 4.4E+O All< LLD All< LLD 0 (1.5E+1)
Grass (pCi/kg wet) Gamma Spec (1981-1982) (82)
'"'I 6.7E+1 All< LLD All< LLD 0 (6.0E+1)
'"~Cs 2.7E+1 All< LLD All< LLD 0 (8.0E+1)
."j/Cs 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 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 Number of Lower Limit of All Indicator Control Locations Sampled (Unit of Number of Name Mean 2 (#/total #) Non routine Detection1 Actual Locations Mean 2 Mean 2 (#/total #)
Measurement and Analyses (Distance & Direction) (Range) Reported 3 (Max.) (#/total #) (Range) (Range)
Reporting Period) Performed Measurements Broadleaf Gamma Spec (10)
Vegetation (pCi/kg wet)
(1980-1982) 1611 3.7E+1 All< LLD 0 (6.0E+1)
- 16"Cs 1.9E+1 All< LLD 0 (8.0E+1)
Mr cs 2.1 E+1 3.1 E+1 (2/7) Site 2, Jrans. Line, 3.6E+1 (1/1) All< LLD 0 (8.0E+1) (1.8E+1 to 3.6E+1) (1.2 mi SW) (Sinale Value)
Other Vegetation Gamma Spec (pCi/kg wet) (32)
(1980-1982) 1;;s4Cs 8.4E+O All< LLD All< LLD 0 (8.0E+1) 1;;srcs 1.0E+1 All< LLD All< LLD 0 (8.0E+1)
Fish (pCi/kg wet) Gamma Spec (1980 - 1982) (92) 16"Cs 1.4E+1 All< LLD All< LLD 0 (1.3E+2) 161cs
- 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 1.0E+2) (1.0E+1 to 7.9E+1) ooco 2.6E+1 All< LLD All< LLD 0 (1.3E+2) b4Mn 1.8E+1 All< LLD All< LLD 0 (1.3E+2) 0
~Fe 9.0E+1 All< LLD All< LLD 0 (2.6E+2) oozn 4.1 E+1 All< LLD All< LLD 0 (2.6E+2) ouCo 1.8E+1 All< LLD All< LLD 0 (1.3E+2)
Sediment (pCi/kg) Gamma Spec (24)
(1980-1982) 16'1Cs 2.3E+1 All< LLD All< LLD 0 (1.5E+2) 1;;,Cs 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 mi, SSW) 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 NRG guidelines given in parenthe.ses.
- 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 µR/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 2015 Environmental lntercomparison Program with Independent Lab, Eckert & Ziegler Analytics, Inc.
Comparison Study Vendor Lab Env Lab Date Nuclides Agreement (Measurement Unit) Results Results Gamma Isotopic Liquid 4/1 1J11 96.7 109 Yes 1 Liter 141Ce 139 148 Yes (pCi/I) s1Cr 366 384 Yes 134Cs 126 120 Yes 131Cs 167 174 Yes ssco 180 188 Yes 54Mn 159 171 Yes seFe 195 225 Yes 6szn 299 329 Yes 6oco 328 325 Yes Gamma ,composite Filter 9/24 141Ce 138 137 Yes (pCi) s1cr 350 337 Yes 134Cs 138 110 Yes 131Cs 166 176 Yes SB co 171 171 Yes 54Mn 188 209 Yes seFe 147 176 Yes 6szn 229 271 Yes 6oco. 214 214 Yes Alpha/Beta Water 4/14 Alpha 118 116 Yes (pCi/I) Beta 281 283 Yes Gamma Isotopic 3/26 141Ce 3.06E-1 3.07E-1 Yes Pulverized s1c*r 8.06E-1 7.38E-1 Yes Soil 134Cs 2.77E-1 2.35E-1 Yes (pCi/g) 131Cs 4.46E-1 3.67E-1 Yes ssco 3.96E-1 3.84E-1 Yes s4Mn 3.49E-1 3.56E-1 Yes seFe 4.29E-1 4.47E-1 Yes 6szn 6.58E-1 6.58E-1 Yes 6oco 7.23E-1 7.09E-1 Yes 1-131 Solid 3/26 i ;jl I 86.5 85.3 Yes (pCi) 33
Comparison Study Vendor Lab Env Lab Date Nuclides Agreement (Measurement Unit) Results Results Tritium 3/30 jH 12600 14400 Yes (pCi/I)
Gross Beta Filter 10/11 NIA 91.7 90.1 Yes (pCi)
Charcoal Cartridge 9/17 ljl I 81.5 84.9 Yes (pCi)
/
Gamma Isotopic Liquid 9/24 ljll 96.7 107 Yes 4 Liter 141Ce 199 218 Yes (pCi/I) s1cr 502 543 Yes 134Cs 198 208 Yes 131Cs 238 263 Yes ssco 246 273 Yes 54Mn 271 311 Yes 59Fe 211 244 Yes 65zn 330 371 Yes 6oco 308 344 Yes 34
Table 11 -2015 Environmental Sampling Program Exceptions Sample Month Media Location (Week No.) Cause for Exception Air Particulate Site 7 Mar (13) Flow meter set in wrong sampling mode.
And Radioiodine Site 6 Sep (40) Loss of power.
Ground Water Site 103 Mar (25) Equipment malfunction.
One TLD missing and one TLD TLD Site 41 Apr (16) damaged.
Drinking Sampler drain valve unintentionally Site 39 Oct (45)
Water opened.
35
~
N 1
\_EGE ND SAMPLE LOCATlOl-.JS 0 CONTROL TE SITE
-AIR PARTICULA -
~=DIRECT <TLOJ SITE SITE I =AIRBORNE RAOIOIOO!NE
\./=WATER SITE ROOUCTS, FISH, O= 0 THER CGARDEN SEDIMEN Tp* GRASS, MI L\()
REFERENCE~OR
, THIS MAP W~SG~~~GIA, THE IJASEOF USGS STl'ITE 0 POATJON PARED FROM 1970. A 1 Electric & Gos Co.
South Coro mo N leor Stot1on Virgil C. Sum mer uc Region ol Location Mop Figure 1-1
LEGEND
- PRIMARY SAMPLE LOCATIONS A = AIR PARTICULATE SAMPLE SITE D =DIRECT CTLD> SAMPLE SITE I =AIRBORNE RAO!O!ODINE SAMPLE SITE w= WATER SAMPLING LOCATION 0 = OTHER I = TLD
.*__ c,,
& Gas Co.
V11*g1l C. Summer Nuoleor Stot1on RADIOLOGICAL MONITORING PROGRAM LOCAL INDICATOR SAMPLE SITES Figure 1-2
- PEV. OhTE I~
- I
LEGEND FIGURE 1-3
.... - *-** **- ..... e PRIMARY SAMPLE LOCATIONS A = AIR PARTICULATE SAMPLE SITE D DIRECT <TLDI SAMPLE SITE <OUARTERL Yl AIRBORNE RADIOIOD!NE SAMPLE SITE W = WATER SAMPLING LOCATION 0 OTHER
LEGEND
- Groundwater Well
.o CJ 109 26 N
W-4$ . . E s
- - - -r~~--- -
....----- -::::-=-'l' D
i15 South Carolina Elecfric & Gas Co Virgil C Summer Nuclear Station D
0 RADIOLOGICAL MONITORING PROGRAM
~l--*
SECURITY AREA GROUNDWATER SITES
...... .,. Figure 1-4
CWPH LEGEND
- Gl'oundwater Wells 000 Cooling Tower HolWorehtM.111 0
Rad W11te Yard MalrDlogy Bulldlng Hat Mlehlne N
W~.-E Shop Fuel Handling Bulldlng s
y....--*- ~ 103 0 ..... ( f.S2
'""~ ~/)~~
- 108 0
_ _. i _ _.i.__ _ _ln - la_rm
_adlate
, Building '1 -=* 1 Conlrol Bulldlng
~-=--~--~--~~-- __J 106
- @ min Wiler k
'-../
Aux Service Bullding Turbine Building Moth Mllnl Shop 107
- Service Bulldlng Whs. C Accesa Portal
~hlcleAcca:11;--_,fl-------L---;:::============-:__!..._ ______________J BuMdlng
-..ll... South Carolina Elech'ic & Gas Co Virgil C Summel' Nuclear Station RADIOLOGICAL MONITORING PROGRAM PROTECTED AREA GROUNDWATER SITES Figure 1-5