RC-17-0047, Annual Radiological Environmental Operating Report
| ML17107A406 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/15/2017 |
| From: | Ryan Justice South Carolina Electric & Gas Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RC-17-0047 | |
| Download: ML17107A406 (46) | |
Text
Robert L. Justice General Manager, Nuclear Plant Operations 803.345.4707 SCE&G April 15, 2017 A SCANA COMPANY Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir/Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Enclosed is the South Carolina Electric & Gas Company Annual Radiological Environmental Operating Report as required by Regulatory Guide 4.8 and Section 6.9.1.6 of the Virgil C. Summer Nuclear Station Technical Specifications.
If there are any questions, please contact Ms. Susan B. Reese at (803) 345-4591.
Very truly yours SBR/RLJ/bb Enclosure c:
K. B. Marsh (w/o enclosure)
S. A. Byrne J. B. Archie J. H. Hamilton (w/o enclosure)
J. W. Williams (w/o enclosure)
S. M. Shealy (w/o enclosure)
W. M. Cherry (w/o enclosure)
C. Haney S. A. Williams N. S. Cams NRC Resident Inspector K. T. Ellison M. E. Jordan K. M. Sutton C. S. Logan D. A. Solley (SCDHEC)
File (818.02-2, RR 8300)
PRSF (RC-17-0047)
V. C. Summer Nuclear Station
- P. 0. Box 88
- Jenkinsville, South Carolina
- 29065
- F (803) 941-9776
- www.sceg.com
SGflrdfrG A SCANA COMPANY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPERATING PERIOD JANUARY 1, 2016 - DECEMBER 31, 2016 April 2017 Prepared by:
Brett Williams Health Physics Specialist Reviewed by:
/ Michael Jordan Health Physics Supervisor W/7 Approved by:
Todd Ellison 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 2016.
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 deviations noted. Samples were collected comprising one thousand two hundred seventy three analyses (1,273) performed to compile the data for the 2016 Environmental Report. Supplemental samples comprising two hundred sixty seven (267) 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 2016 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 3
Pathways 2
2016 Fission and Activated Corrosion Product Activity in 6
Sediment 3
Required Sampling Site Locations 8
4 Results of the 2016 Land Use Census Verification 11 5
Critical Receptor Evaluation for 2016 12 6
Radiological Environmental Monitoring Program 13 Specifications 7
Supplemental Radiological Environmental Monitoring 18 8
Radiological Environmental Monitoring Program Summary 22 for 2016 9
Radiological Environmental Monitoring Program 28 Preoperational (Baseline) Summary 10 Results of 2016 Environmental Inter-comparison Program 33 with Independent Lab, Eckert & Ziegler Analytics, Inc.
11 2016 Environmental Sampling Program Deviations 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 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 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 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. The first Dry Cask Storage Campaign began March 21, 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 2016. 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 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.
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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. 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.
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 2016. 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 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 2016 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 2016 meteorological data. Exposure pathways used in the analysis were those identified during the land use census.
The location and pathway presently used in the ODCM for offsite organ dose calculations (E 1.1 miles - residence/garden) was found to have a calculated dose of 2.55E+0 mrem/year. In addition, the ODCM required environmental gardens (ESE 1.0 and E 1.0 mile) were found to have a calculated dose of 2.27E+0 and 3.26E+0 mrem/year.
There were no milking animals or dairy activity found within 5 kilometers of VCSNS.
Therefore, changes to the ODCM gaseous effluent calculations or garden sample locations are not indicated.
MONITORING RESULTS AND DISCUSSION The results of the Radiological Environmental Monitoring Program for 2016 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 99.5%. 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 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 (2.54E-2 pCi/m3) 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.
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, 137Csand 131l were 2.07E-3, 2.33E-3 and 2.11E-2 pCi/m3, respectively. The average maximum results support the gaseous effluent release data reported in the 2016 Annual Radiological Effluent Release Report for VCSNS. 99.4% of the required indicator/control air samples were collected.
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 1.19E+1 pR/hr. This is similar to the 2015 value of 1.28E+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). In May 2016 four Casks were loaded during the first Used Fuel Loading Outage (UFLO) campaign. To date there has been no increase in above background from Dry Cask Storage activities. 99.4% 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 one sample at Site 23 (Monticello Reservoir 0.5 mi. ESE). The tritium concentration was 4.41 E+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 five supplemental ground water samples at Site 123 (NPDES Well GW-16 0.34 SSE), at concentrations of 2.63E+3 pCi/L, 2.36E+3 pCi/L, 2.35E+3 pCi/L, 3.81 E+3 pCi/L and 2.99E+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 Waterworks 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 one sample taken at Site 17 (Columbia Water Works 25.0 mi. SE) at a concentration of 6.23E+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 1.24E+1 pCi/l. 100% of indicator/control drinking water samples were collected.
There were no milk samples collected in 2016. Milk sampling is required to be performed at the three highest dose locations within 5 kilometers of the plant or at 5 to 8 kilometers of the plant, if doses are calculated to be greater than 1 mrem per year.
Presently there are no locations meeting this criteria for indicator dairies. The closest dairy is approximately 8 kilometers from the plant (see Table 4). Milk samples will be obtained from this dairy if gaseous releases from the plant exceed 5% of quarterly organ dose limits 5
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 2 of 12 samples at Site 2 (transmission line 1.2 mi. SW) at concentrations of 1.83E+1 pCi/kg, and 3.17E+1 pCi/kg. The maximum preoperational control activity was 3.40E+2 pCi/kg. 100% of indicator/control supplemental grass samples were collected.
Gamma spectroscopy measurements of supplemental grass and soil samples are collected in response to a liquid effluent spill in 2011 at Site 25 (Fairfield Pump Storage Remediation Area 0.9 mi. WNW). 1 of 4 grass samples detected 137Cs at 2.17E+1 pCi/kg.
1 of 1 soil sample detected 6°C0 at 2.67E+1 pCi/kg.
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 mi. SSW) at concentrations of 6.16E+1 and 5.90E+1 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 2.02E+1 pCi/kg. All required indicator/control sediment samples were collected.
Table 2 - 2016 Fission and Activated Corrosion Product Activity in Sediment Location Radionuclide Activity (pCi/kg)
Corresponding Calculated Annual Dose Equivalent (mrem/yr)
Location Radionuclide Activity (pCi/kg)
Total Body Parr Reservoir 137Cs Maximum Mean Maximum Mean Parr Reservoir 137Cs 6.16E+1 6.03E+1 5.17E-3 5.07E-3 6
CONCLUSION As in previous years of VCSNS operation, the presence of fission product activity attributed to residual fallout from atmospheric weapons testing and the Chernobyl accident were detected in environmental media including sediment and grass.
No detectable fission or activation product activity attributed to VCSNS operations was observed in environmental media with the exception of:
- Tritium in one surface water sample taken at site 23 (Monticello Reservoir 0.5 mi. ESE).
- Tritium in five supplemental ground water samples taken at Site 123 (NPDES Well GW-16 0.34 mi. SSE).
- All tritium sample concentrations were well below drinking water standards.
- Co-60 was detected in one supplemental soil sample taken at Site 25 (Fairfield Pumped Storage Penstocks 0.9 WNW).
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 No.
Description Distance1 (Miles)
Direction2 Sample Type(s)3 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 of VCSNS 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 8
Table 3 (cont) - Required Sampling Site Locations Site No.
Description Distance1 (Miles)
Direction2 Sample Type(s)3 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 63 WSW 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 9
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 Rl = Air Radioiodine DQ = Quarterly TLD SW = Surface Water GW = Ground Water DW = Drinking Water MK = Milk GR = Grass (Forage)
GA = Garden FH = Fish BS = Bottom Sediment
- 4.
Sites 14 and 16 are not presently in use. If conditions change, requiring a renewal of dairy sampling these sites will be reactivated.
- 5.
Site 28 for drinking water and Site 59 for quarterly TLD measurements are co-located at the location of the SCE&G New Nuclear Deployment.
- 6.
Site 30 consists of two locations in the same sector. The air sampler is located 0.5 miles from the reactor to support construction of a new facility. The TLD is located 1.0 miles from the reactor in the same sector.
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 2016 Land Use Census Verification Sector Nearest Residence Miles Nearest Garden Miles Nearest Cattle No.
Milked Miles Nearest Goat No.
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 Unknown Residence 2.53 Ronnie Leitzey 4.72 Ronnie Leitzey 1
4.15 Ronnie Leitzey 15 4.15 NW Louise Workman 3.9 NNW Frank March 2.9 Frank March 2.9 Frank -March 0
2.9
(*) Keneth and Virgil Graham cows grazed in the W and WSW 11
Table 5 Critical Receptor Evaluation for 2016 NAME SECTOR MILES PATHWAY X/Q D/Q DOSE*
mRem/y P. Oliver N
3.73 Res 2.20E-07 6.60E-10 8.22E-03 Thomas K. Crumblin NNE 2.9 Res 5.00E-07 1.60E-09 1.87E-02 Eddie Robinson NNE 3.99 B,Gar 2.70E-07 7.70E-10 2.80E-01 Gregrey Guinyard Jr.
NE 1.55 Res 2.20E-06 6.70E-09 8.22E-02 Rufus (Ruddy) Pearson NE 2.66 Res,Gar 6.80E-07 1.80E-09 5.02E-01 Bessie Gregg ENE 1.56 Res 2.10E-06 6.70E-09 7.86E-02 Essie Mae Glenn 1 ENE 1.68 Res,Gar 1.70E-06 5.60E-09 1.52E+00 Garden-7 **
E 1
Res,Gar 3.70E-06 1.20E-08 3.26E+00 Sheryl A. Colley E
1.2 Res 2.40E-06 7.60E-09 8.98E-02 Garden-6 **
ESE 1
Res,Gar 2.50E-06 8.40E-09 2.27E+00 Carrie Lee Martin ESE 1.1 Res 1.90E-06 6.50E-09 7.14E-02 James Pearson ESE 1.36 Res,Gar 1.20E-06 3.80E-09 1.03E+00 Mary White SE 1.44 Res,Gar 6.10E-07 2.90E-09 7.58E-01 Sim Roberts SE 4.7 Res,Gar,B 4.90E-08 1.80E-10 6.62E-02 Ronnie Mann SSE 2.39 Res,Gar 1.20E-07 7.30E-10 1.87E-01 Kelly Boulware S
3.56 Res,Gar 6.80E-08 4.70E-10 1.20E-01 Shirley Counts S
5 Res,Gar,B 3.40E-08 2.20E-10 7.81 E-02 NND Construction Site SSW 0.49 Res 6.10E-06 5.70E-08 2.47E-01 Nick Bates SSW 3.11 Res 1.OOE-07 8.50E-10 4.01 E-03 Joe Smith SSW 4.73 Res.B 4.20E-08 3.30E-10 3.44E-02 Marvin Miller sw 3.3 Res,Gar 7.30E-08 7.50E-10 1.87E-01 Ron Hope wsw 2.9 Res 7.40E-08 8.90E-10 3.10E-03 Steve All wsw 4.83 Res,Gar,G 3.20E-08 2.80E-10 7.38E-02 KenA/irg Graham wsw 4.98 B
3.00E-08 2.70E-10 2.68E-02 Jerry Cassado w
2.55 Res 1.20E-07 6.50E-10 4.63E-03 Marion Livingston w
2 B
2.00E-07 1.20E-09 1.19E-01 Marion Livingston w
2.8 Res,Gar 9.40E-08 5.20E-10 1.34E-01 Marion Livingston w
Res,Gar,B BOTH BOTH 2.53E-01 KenA/irg Graham w
5 Res,Gar,B,C/M 2.80E-08 1.40E-10 1.74E-01 Unknown Resident WNW 2.53 Res 9.50E-08 4.70E-10 3.64E-03 Ronnie Leitzsey WNW 4.15 C/M,B,G/M,G 3.30E-08 1.50E-10 1.49E-01 Ronnie Leitzsey WNW 4.72 Res,Gar 2.60E-08 1.20E-10 3.15E-02 Ronnie Leitzsey WNW Res,Gar,C/M,B,G/M,G BOTH BOTH 1.81 E-01 Louise Workman NW 3.9 Res 7.90E-08 3.00E-10 2.98E-03 Frank March NNW 2.9 Res,Gar,B 3.10E-07 8.40E-10 3.18E-01 ODCM Organ Dose E
1.1 Res,Gar 2.90E-06 9.40E-09 2.55E+00 Pathway Res = Residence B = Beef G = Goat Gar = Garden C/M = Cow/Milk(lnfant)
G/M = Cow/Milk(lnfant)
Footnotes:
1 Maximum exposed individual.
Hypothetical dose based on Operating License Environmental Report Source Term.
ODCM required environmental gardens.
12
Table 6 - Radiological Environmental Monitoring Program Specifications Exposure Pathway and/or Sample Criteria for Selection of Sample Number & Location Sampling and Collection Frequency Sample Location Type & Frequency of Analysis AIRBORNE:
- 1. Particulate A) 3 Indicator samples from locations close to the site boundary, in different sectors, of the highest calculated annual average ground level D/Q or dose.2 Continuous sampler operation with weekly collection.
2 7
30 Gross beta following filter change; Quarterly composite (by location) for gamma isotopic.
B) 1 Indicator sample to be taken close to the site boundary in the sector corresponding to the residence having the highest anticipated offsite ground level concentration or dose..2 Continuous sampler operation with weekly collection.
6 Gross beta following filter change; Quarterly composite (by location) for gamma isotopic.
C) 1 Indicator sample to be taken at the location of one of the dairies being sampled meeting the criteria of VII(A).2'4 Continuous sampler operation with weekly collection.
N/A Gross beta following filter change; Quarterly composite (by location) for gamma isotopic.
D) 1 Control sample to be taken at a location at least 10 air miles from the site and not in the most prevalent wind directions.2 Continuous sampler operation with weekly collection.
17 Gross beta following filter change; Quarterly composite (by location) for gamma isotopic.
II. Radioiodine A) 3 Indicator samples to be taken at two locations as given in l(A) above.
Continuous sampler operation with weekly canister collection.
2 7
30 Gamma Isotopic for Iodine 131 weekly.
B) 1 Indicator sample to be taken at the location as given in l(B) above.
Continuous sampler operation with weekly canister collection.
6 Gamma Isotopic for Iodine 131 weekly.
C) 1 Indicator sample to be taken at the location as given in l(C) above.
Continuous sampler operation with weekly canister collection.
N/A Gamma Isotopic for Iodine 131 weekly.
D) 1 Control sample to be taken at a location similar in nature to 1(D) above.
Continuous sampler operation with weekly canister collection.
17 Gamma Isotopic for Iodine 131 weekly.
13
Exposure Pathway and/or Sample Criteria for Selection of Sample Number & Location Sampling and Collection Frequency Sample Location Type & Frequency of Analysis 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 ISFSI 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 a location which allows for mixing a dilution in the ultimate receiving river.
collection every month.5 with quarterly composite (by location) to be analyzed for tritium.7 B) 1 Control sample to be taken at a location on the receiving river sufficiently far upstream such that no Time composite samples6 with collection every month.5 223 Gamma isotopic monthly with quarterly composite (by location) to be analyzed for tritium.7 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 14
Exposure Pathway and/or Sample Criteria for Selection of Sample Number & Location Sampling and Collection Frequency Sample Location Type & Frequency of Analysis VI. Drinking Water A) 1 Indicator sample from a nearby public ground water supply source.
Monthly grab sampling.5 28 Monthly5 gamma isotopic and gross beta analyses and quarterly7 composite for tritium analyses.
B) 1 Indicator (finished water) sample from the nearest downstream water supply.
Monthly composite sampling.
17 Monthly5 gamma isotopic and gross beta analyses and quarterly7 composite for tritium analyses.
C) 1 Control (finished water) sample from an unaffected water supply.
Monthly composite sampling.
39 Monthly5 gamma isotopic and gross beta analyses and quarterly7 composite for tritium analyses.
INGESTION:
VII. Milk4 A) Samples from milking animals in 3 locations within 5 km having the highest dose potential. If there are none then 1 sample from milking animals in each of 3 areas between 5 to 8 km distance where doses are calculated to be greater than 1 mrem per year.10 Semimonthly when animals are on pasture8, monthly other times.5 To be supplied when milk animals are found in accordance with criteria VILA.
Gamma isotopic and I-131 analysis semimonthly8 when animals are on pasture, monthly other times.5 B) 1 Control sample to be taken at the location of a dairy > 20 miles distance and not in the most prevalent wind direction.2 Semimonthly when animals are on pasture8, monthly other times.5,11 16 Gamma isotopic and I-131 analysis semimonthly8 when animals are on pasture, monthly other times.5 C) 1 Indicator grass (forage) sample to be taken at the location of one of the dairies being sampled meeting the criteria of VII(A),above, when animals are on pasture.
Monthly when available.5 To be supplied when milk animals are found in accordance with criteria VII.A.
Gamma isotopic.
D) 1 Control grass (forage) sample to be taken at the location of VII (B) above.
Monthly when available.5,11 16 Gamma isotopic.
15
Exposure Pathway and/or Sample Criteria for Selection of Sample Number & Location Sampling and Collection Frequency Sample Location Type & Frequency of Analysis VIII. Food Products A) 2 samples of broadleaf vegetation grown in the 2 nearest offsite location of highest calculated annual average ground level D/Q if milk sampling is not performed within 3 km or if milk sampling is not performed at a location within 5-8 km where the doses are calculated to be greater than 1 mrem/yr.10 Monthly when available.5 6
7 Gamma isotopic on edible portion.
B) 1 Control sample for the same foods taken at least 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 Monthly when available.5 40 Gamma isotopic on edible portion.
IX. Fish A) 1 Indicator sample to be taken at a location in the upper reservoir.
Semiannual9 collection.1 23° Gamma isotopic on edible portions semiannually.9 B) 1 Indicator sample to be taken at a location in the lower reservoir.
Semiannual9 collection.1 213 Gamma isotopic on edible portions semiannually.9 C) 1 Control sample to be taken at a location on the receiving river sufficiently far upstream such that no effects of pumped storage operation are anticipated.
Semiannual9 collection.1 223 Gamma isotopic on edible portions semiannually.9 AQUATIC:
X. Sediment A) 1 Indicator sample to be taken at a location in the upper reservoir.
Semiannual grab sample.9 233 Gamma isotopic.
B) 1 Indicator sample to be taken on or near the shoreline of the lower reservoir.
Semiannual grab sample.9 2 f 3 Gamma isotopic.
C) 1 Control sample to be taken at a location on the receiving river sufficiently far upstream such that no effects of pumped storage operation are anticipated.
Semiannual grab sample.9 223 Gamma isotopic.
16
Table 6 (cont) - Radiological Environmental Monitoring Program Specifications FOOTNOTES
- 1.
Fish include 3 groups (Bass, Bream/Crappie, Catfish/Carp.)
- 2.
Sample site locations are based on 5-year average meteorological analysis.
- 3.
Though generalized areas are noted for simplicity of sample site enumeration, airborne, water and sediment sampling is done at the same location, whereas biological sampling sites are generalized areas in order to reasonably assure availability of samples.
- 4.
Milking animal and garden survey results will be analyzed annually. If the survey should indicate new activity the owners shall be contacted with regard to a contract for supplying sufficient samples. If contractual arrangements can be made, site(s) will be added for additional milk sampling up to a total of three Indicator locations.
- 5.
Not to exceed 35 days.
- 6.
Time composite samples are samples which are collected with equipment capable of collecting an aliquot at time intervals which are short relative to the compositing period.
- 7.
At least once per 100 days.
- 8.
At least once per 18 days.
- 9.
At least once per 200 days.
- 10.
The dose shall be calculated for the maximum organ and age group, using the guidance/methodology contained in Regulatory Guide 1.109, Rev. 1 and the parameters particular to the site.
- 11.
Milk and forage sampling at the control location is only required when locations meeting the criteria of VII(A) are being sampled.
17
Table 7 - Supplemental Radiological Environmental Monitoring Exposure Pathway Criteria for Selection of Sampling and Sample Type & Frequency of and/or Sample Sample Number & Location Collection Frequency Location Analysis AIRBORNE:
S-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-ll.
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.
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 and/or Sample Criteria for Selection of Sample Number & Location Sampling and Collection Frequency Sample Location Type & Frequency of Analysis INGESTION:
S-VII. Milk4 A) 1 Sample from one of the nearest affected dairies at or beyond 5 miles.
Biweekly grab sample.8'14'+
14 Gamma isotopic and 1-131 analysis biweekly.
B) 1 Control sample to be taken at the location of a dairy greater than 20 miles distance and not in the most prevalent wind direction.
Biweekly grab sample.814*
16 Gamma isotopic and 1-131 analysis biweekly.
C) 1 Indicator grass (forage) sample to be taken at the location of S-VII(A) above.
Monthly when available.14 14 Gamma isotopic.
S-VII. Milk4 D) 1 Control grass (forage) sample to be taken at the location of S-VII(B) above.
Monthly when available.14 16 Gamma isotopic.
E) 2 Indicator grass (forage) 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.
Monthly when available.
2,7 Gamma isotopic.
F) 1 Control grass (forage) sample to be used for routine monitoring along with S-VII(E) above.
Monthly when available.
40 Gamma isotopic.
G) 1 Indicator grass (forage) sample to be taken at location of penstock leak.
Quarterly when available.
25 Gamma isotopic.
S-VIII. Food Products A) 1 Indicator sample of various types of foods grown in the area surrounding the plant (root, fruit, grain).
Annually during growing season.11 6,7 Gamma isotopic on edible portion.
B) 1 Control sample of various types of foods grown, (root, fruit, grain).
Annually during growing season.11 40 Gamma isotopic on edible portion.
Corbicula C) 1 Indicator sample of edible portions.
Semiannual.
23 Gamma isotopic.
19
Exposure Pathway and/or Sample Criteria for Selection of Sample Number & Location Sampling and Collection Frequency Sample Location Type & Frequency of Analysis S-IX.
Sediment/
Sludge A) 1 Indicator sample from each storm drain outfall.
Semiannually.
72,73 Gamma isotopic.
B) 3 Indicator sludge samples taken at sludge lagoons 006A, 006B &
008.
Semiannually.
On site Gamma isotopic.
C) 1 Indicator sample of topsoil from penstock spill area.
Annually 25 Gamma isotopic.
S-X.
Ground Water A) 11 Indicator samples to be taken within the exclusion boundary and in the direction of potentially affected ground water supplies.
Quarterly grab sampling.7 107,111, 115-123 Gamma isotopic and tritium analyses quarterly.7 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 2016 Medium or Pathway Sampled (Unit of Measurement)
Type and Total Number of Analyses Performed1 Lower Limit of Detection2 Actual (Max.)
Location with Highest Annual Mean Control Locations Mean3 (#/total #)
(Range)
Number of Nonroutine Reported4 Measurements Medium or Pathway Sampled (Unit of Measurement)
Type and Total Number of Analyses Performed1 Lower Limit of Detection2 Actual (Max.)
All Indicator Locations Mean3 (#/total #)
(Range)
Name (Distance & Direction)
Mean3 (#/total #)
(Range)
Control Locations Mean3 (#/total #)
(Range)
Number of Nonroutine Reported4 Measurements Air Particulate (pCi/m3)
Gross Beta (310) 7.05E-3 (1.OE-2) 2.34E-2 (258/258)
(8.96E-3 to 5.12E-2)
Site 7, Environmental Lab Garden, (1.0 mi. E) 2.54E-2 (51/51)
(1.34E-2 to 4.82E-2) 2.30E-2 (52/52)
(7.46E-3 to 4.59E-2) 0 Gamma Spec (72) 134Cs 2.07E-3 (5.OE-2)
137Cs 2.33E-3 (6.OE-2)
Air Radioiodine (pCi/m3) 131 i (310) 2.11E-2 (7. OE-2)
Direct (TLD)5 (uR/hr)
Gamma(135)
Quarterly N/A 8.47E+0 (115/115)
(5.52E+0 to 1.24E+1)
Site 4, Fairfield Flydro, (1.2 mi. WNW) 1.19E+1 (4/4)
(1.15E+1 to 1.24E+1) 8.20E+0 (20/20)
(4.98+0 to 1.14E+1) 0 Gamma(24)
Special Interest N/A 8.93E+0 (24/24)
(5.13E+0 to 1.20E+1)
Site 52, Monticello Rd.
11, (3.8 mi. NNE) 1.16E+1 (4/4)
(1.12E+1 to 1.20E+1)
N/A 0
Surface Water (pCi/l) 3H (36) 4.34+2 (2.0E+3) 4.41 E+2 (1/24)
(4.41 E+2 to 4.41+2)
Site 23, Monticello Res, (0.5mi. ESE) 4.41 E+2 (1/12)
(4.41 E+2 to 4.41 E+2)
All < LLD 0
Gamma Spec(36) 54Mn 1.83E+0 (1.5E+1)
58Co 2.16E+0 (1.5E+1)
59Fe 5.26E+0 (3.0E+1)
60Co 2.02E+0 (1.5E+1)
65Zn 4.29E+0 (3.0E+1)
95Zr 3.11E+0 (3.0E+1)
95Nb 2.31 E+0 (1.5E+1)
134Cs 1.45E+0 (1.5E+1)
22
Table 8 (cont.) - Radiological Environmental Monitoring Program Summary for 2016 Medium or Pathway Sampled (Unit of Measurement)
Type and Total Number of Analyses Performed1 Lower Limit of Detection2 Actual (Max.)
Location with Highest Annual Mean Control Locations Mean3 (#/total #)
(Range)
Number of Nonroutine Reported4 Measurements Medium or Pathway Sampled (Unit of Measurement)
Type and Total Number of Analyses Performed1 Lower Limit of Detection2 Actual (Max.)
All Indicator Locations Mean3 (#/total #)
(Range)
Name (Distance & Direction)
Mean3 (#/total #)
(Range)
Control Locations Mean3 (#/total #)
(Range)
Number of Nonroutine Reported4 Measurements Surface Water (Continued) 137Cs 2.10E+0 (1.8E+1)
140Ba 1.92E+1 (6.0E+1)
140 La 5.30E+0 (1.5E+1)
Ground Water (pCi/l) 3H (55) 4.21 E+2 2.00E+3 All < LLD All < LLD 0
Gamma Spec (55) 54Mn 5.91 E+0 (1.5E+1)
58Co 4.73E+0 (1.5E+1)
59Fe 8.06E+0 (3.0E+1)
60Co 6.51 E+0 (1.5E+1)
6SZn 1.05E+1 (3.0E+1)
95Zr 6.92E+0 (3.0E+1)
95Nb 5.35E+0 (1.5E+1)
134Cs 5.56E+0 (1.5E+1)
137Cs 5.24E+0 (1.8E+1)
140Ba 2.74E+1 (6.0E+1)
140 La 5.20E+0 (1.5E+1)
23
Table 8 (Cont.) - Radiological Environmental Monitoring Program Summary for 2016 Medium or Pathway Sampled (Unit of Measurement)
Type and Total Number of Analyses Performed1 Lower Limit of Detection2 Actual (Max.)
All Indicator Locations Mean3 (#/total #)
(Range)
Location with Highest Annual Mean Control Locations Mean3 (#/total #)
(Range)
Number of Nonroutine Reported4 Measurements Medium or Pathway Sampled (Unit of Measurement)
Type and Total Number of Analyses Performed1 Lower Limit of Detection2 Actual (Max.)
All Indicator Locations Mean3 (#/total #)
(Range)
Name (Distance & Direction)
Mean3 (#/total #)
(Range)
Control Locations Mean3 (#/total #)
(Range)
Number of Nonroutine Reported4 Measurements Drinking Water*
(pCi/i)
Gross Beta (36) 1.63E+0 (4.00E+0) 4.33E+0 (15/24)
(1.33E+0 to 1.24+1)
Site 28, New Nuclear Deployment, (2.6 mi, SSE) 5.22E+0 (7/12)
(2.08E+0 to 1.24+1) 3.92E+0 (9/12)
(1.50E+0 to 1.08E+1) 0 3H (36) 4.34E+2 (2.0E+3) 6.23E+2 (1/24)
(6.23E+2 to 6.23+2)
Site 17, Columbia Water Works (25.0 mi, SE) 6.23E+2 (1/12)
(6.23E+2 to 6.23+2)
All < LLD 0
Gamma Spec (72)3 54Mn 3.69E+0 (1.5E+1)
58Co 2.39E+0 (1.5E+1)
59Fe 6.13E+0 (3.0E+1)
60Co 2.95E+0 (1.5E+1)
S5Zn 5.90E+0 (3.0E+1)
95Zr 4.90E+0 (3.0E+1)
95Nb 2.15E+0 (1.5E+1)
1311 4.46E-1 (1.0E+0)
134Cs 2.81 E+0 (1.5E+1)
137Cs 3.42E+0 (1.8E+1)
140Ba 1.28E+1 (6.0E+1)
143 La 3.61 E+0 (1.5E+1)
24
Table 8 (Cont.) - Radiological Environmental Monitoring Program Summary for 2016 Medium or Pathway Sampled (Unit of Measurement)
Type and Total Number of Analyses Performed1 Lower Limit of Detection2 Actual (Max.)
Location with Hig hest Annual Mean Control Locations Mean3 (#/total #)
(Range)
Number of Nonroutine Reported4 Measurements Medium or Pathway Sampled (Unit of Measurement)
Type and Total Number of Analyses Performed1 Lower Limit of Detection2 Actual (Max.)
All Indicator Locations Mean3 (#/total #)
(Range)
Name (Distance & Direction)
Mean3 (#/total #)
(Range)
Control Locations Mean3 (#/total #)
(Range)
Number of Nonroutine Reported4 Measurements Broadleaf Vegetation (pCi/k.q wet)
Gamma Spec (36) 1311 1.70E+1 (6.0E+ 1)
134Cs 1.47E+1 (6.0E+ 1)
137Cs 1.86E+1 (8.0E+1)
Fish7 (pCi/kg wet)
Gamma Spec (18) 54Mn 3.33E+1 (1.3E+2)
58Co 3.65E+1 (1.3E+2)
59Fe 7.03E+1 (2.6E+2)
60Co 4.44E+1 (1.3E+2)
s5Zn 1.01E+2 (2.6E+2)
134Cs 3.31 E+1 (1.3E+2)
137Cs 3.74E+1 (1.5E+2)
25
Table 8 (Cont.) - Radiological Environmental Monitoring Program Summary for 2016 Medium or Pathway Sampled (Unit of Measurement)
Type and Total Number of Analyses Performed1 Lower Limit of Detection2 Actual (Max.)
All Indicator Locations Mean3 (#/total #)
(Range)
Location with Hig hest Annual Mean Control Locations Mean3 (#/total #)
(Range)
Number of Nonroutine Reported4 Measurements Medium or Pathway Sampled (Unit of Measurement)
Type and Total Number of Analyses Performed1 Lower Limit of Detection2 Actual (Max.)
All Indicator Locations Mean3 (#/total #)
(Range)
Name (Distance & Direction)
Mean3 (#/total #)
(Range)
Control Locations Mean3 (#/total #)
(Range)
Number of Nonroutine Reported4 Measurements Sediment (pCi/kg)8 Gamma Spec (6) 54Mn 1.78E+1 N/A All < LLD All < LLD 0
58Co 1.67E+1 N/A All < LLD All < LLD 0
60Co 1.21 E+1 N/A All < LLD All < LLD 0
134Cs 1.41E+1 (1.5E+2)
137Cs 1.21 E+1 (1.8E+2) 6.03E+1 (2/4)
(5.90E+1 to 6.16E+1)
Site 21, Parr Reservoir, (2.7 mi.
SSW) 6.03E+1 (2/2)
(5.90E+1 to 6.16E+1) 4.01 E+1 (2/2)
(2.02E+1 to 5.99E+1) 0 26
Table 8 (cont) - Radiological Environmental Monitoring Program Summary for 2016 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 p.R/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.
27
Table 9-Radiological Environmental Monitoring Program Preoperational (Baseline) Summary Medium or Pathway Sampled {Unit of Measurement and Reporting Period)
Type and Total Number of Analyses Performed Lower Limit of Detection1 Actual (Max.)
All Indicator Locations Mean2
(#/total #) (Range)
Location with Highest Annual Mean Control Locations Mean2 (#/total #)
(Range)
Number of Nonroutine Reported3 Measurements Medium or Pathway Sampled {Unit of Measurement and Reporting Period)
Type and Total Number of Analyses Performed Lower Limit of Detection1 Actual (Max.)
All Indicator Locations Mean2
(#/total #) (Range)
Name (Distance & Direction)
Mean2 (#/total #)
(Range)
Control Locations Mean2 (#/total #)
(Range)
Number of Nonroutine Reported3 Measurements Air Particulate (pCi/m3)
(1981-1982)
Gross Beta (1300) 4.1E-3 (1.OE-2) 1.1 E-1 (562/564)"
(1.3E-2 to 5.5E-1) 2.7E-2 (456/462)"
(9.3E-3 to 6.6E-2)
Site 13, North Dam, (2.9 mi NNW)
Site 8, Mon. Res. S of Rd 224, (1.5 ENE) 1.3E-1 (52/52)
(2.1 E-2 to 5.5E-1) 3.0E-2 (42/42)
(1.2E-2 to 6.OE-2) 1.2E-1 (153/155)
(7.9E-3 to 6.1 E-1) 2.8E-2 (125/126)
(1.2E-2 to 5.8E-2) 0 Gamma Spec (307) 134Cs 3.0E-3 (1.OE-2)
137Cs 3.1 E-3 (1.0E-2) 3.2E-3 (22/241)
(1.5E-3 to 5.2E-3)
Site 10, Met Tower, (2.4 mi NNE) 3.8E-3 (2/22)
(2.5 E-3 to 5.2E-3) 4.2E-3 (4/66)
(3.2E-3 to 5.6E-3) 0 Air Radioiodine (pCi/m3) (1982) 1311 (290) 3.6E-2 (7. OE-2)
Direct (TLD)5 (pR/hr)
(1978-1982)
Gamma (1220)
Monthly 0.5 N/A 9.9 (915/915)
(6.7 to 14.7)
Site 13, North Dam, (2.9 mi NNW) 13.1 (61/61)
(12.2 to 14.2) 9.7 (305/305)
(6.4 to 13.5) 0 Gamma (161)
Quarterly 0.5 N/A 10.2 (154/154)
(6.8 to 14.7)
Site 55, St. Barnabas Church, (2.8 mi E) 14.0(7/7)
(13.1 to 14.7) 0 Surface Water (pCi/l)
(1981-1982) 3H (43) 1.1 E+3 (2.0E+3) 1.4E+3 (18/29)
(1.1 E+3 to 2.4 E+3)
Site 17, Columbia Canal, (24.7 mi, SE) 1.6E+3 (2/7)
(1.4E+3 to1.8E+3) 1.2E+3 (6/14)
(6.7E+2 to 1.6E+3) 0 Gamma Spec (140) 54Mn 2.7E-1 (1.5E+1)
58Co 2.9E-1 (1.5E+1)
59Fe 6.0E+0 (3.0E+1)
60Co 2.4E-1 (1.5E+1)
65Zn 7.9E-1 (3.0E+1)
95Zr 5.2E-1 (1.5E+1)
95Nb 3.3E-1 (1.5E+1)
134Cs 3.0E-1 (1.5E+1)
28
Medium or Pathway Sampled (Unit of Measurement and Reporting Period)
Type and Total Number of Analyses Performed Lower Limit of Detection1 Actual (Max.)
Location with Highest Annual Mean Control Locations Mean2 (#/total #)
(Range)
Number of Nonroutine Reported3 Measurements Medium or Pathway Sampled (Unit of Measurement and Reporting Period)
Type and Total Number of Analyses Performed Lower Limit of Detection1 Actual (Max.)
All Indicator Locations Mean2
(#/total #) (Range)
Name (Distance & Direction)
Mean2 (#/total #)
(Range)
Control Locations Mean2 (#/total #)
(Range)
Number of Nonroutine Reported3 Measurements 137Cs 2.2E-1 (1.8E+1)
140Ba 2.2E+0 (6.0E+1)
i4°La (1982 only) 5.5E-1 (1.5E+1)
Ground Water (pCi/l)
(1981-1982) 3H (29) 9.0E+2 (2.0E+3) 1.5E+3 (16/16)
(9.5E+2 to 2.3E+3)
Site 26, Onsite Well P4, (265 ft, W) 1.6E+3 (8/8)
(9.5E+2 to 2.3E+3) 1.3E+3 (13/13)
(1.0E+3 to 1.9E+3) 0 Gamma Spec (32) 54Mn 3.7E+0 (1.5E+1)
58Co 3.8E+0 (1.5E+1)
59Fe 7.8E+0 (3.0E+1)
6QCo 3.8E+0 (1.5E+1)
S5Zn 8.1 E+0 (3.0E+1)
95Zr 6.8E+0 (1.5E+1)
95Nb 4.6E+0 (1.5E+1)
134Cs 3.7E+0 (1.5E + 1)
137Cs 3.8E+0 (1.8E + 1)
140Ba 1.9E+1 (6.0E+1)
140La (1982 only) 5.0E0 (1.5E+1)
Drinking Water6 (pCi/l) (1981-1982)
Gross Beta7 (2.0E+0) 3H (14) 6.3E+2 (1.0E+3) 7.8E+2 (6/14)
(6.8E+2 to 9.8E+2)
Site 28, Jenkinsville, (2.0 mi SE)7 8.4E+2 (3/7)
(7.0E+2 to 9.8E+2) 0 Gamma Spec (44) 54Mn 3.0E-1 (1.5E+1)
All < LLD 0
58Co 2.7E-1 (1.5E+1)
All < LLD 0
29
Medium or Pathway Sampled (Unit of Measurement and Reporting Period)
Type and Total Number of Analyses Performed Lower Limit of Detection1 Actual (Max.)
Location with Highest Annual Mean Control Locations Mean2 (#/total #)
(Range)
Number of Nonroutine Reported3 Measurements Medium or Pathway Sampled (Unit of Measurement and Reporting Period)
Type and Total Number of Analyses Performed Lower Limit of Detection1 Actual (Max.)
All Indicator Locations Mean2
(#/total #) (Range)
Name (Distance & Direction)
Mean2 (#/total #)
(Range)
Control Locations Mean2 (#/total #)
(Range)
Number of Nonroutine Reported3 Measurements 59Fe 9.6E0 (3.0E+1)
All < LLD 0
60Co 2.6E-1 (1.5E+1)
All < LLD 0
652n 3.4E-1 (3.0E+1)
All < LLD 0
95Zr 4.8E-1 (1.5E+1)
All < LLD 0
1311 3.4E-1 (1.5E+1)
All < LLD 0
95Nb 7.4E-1 (1.0E+0)
All < LLD 0
134Cs 2.2E-1 (1.0E+1)
All < LLD 0
137Cs 2.4E-1 (1.8E+1)
All < LLD 0
140Ba 2.5E0 (6.0E+1)
All < LLD 0
140 La (1982 only) 4.4E-1 (1.5E+1)
All < LLD 0
Milk (pCi/1)
(1981-1982)
Gamma Spec (94) 1311 6.3E-1 (1.0E+0)
134Cs 3.3E+0 (1.5E+1)
137Cs 4.6E0 (1.5E+1) 4.1 E+0 (8/47)
(2.8E+0 to 6.1 E+0)
Site 14, Dairy, (5.1 mi., W) 4.1 E+0 (8/47)
(2.8E+0 to 6.1 E+0) 5.7E+0 (37/47)
(3.7E+0 to 9.2E+0) 0 140Ba 1.1E+1 (1.5E + 1)
i4°La 4.4E+0 (1.5E+1)
Grass (pCi/kg wet)
(1981-1982)
Gamma Spec (82) 1311 6.7E+1 (6.0E+1)
134Cs 2.7E+1 (8.0E+1)
137Cs 3.3E+1 (8.0E+1) 5.0E+1 (13/51)
(1.6E+1 to 1.6E+2)
Site 14, Dairy, (5.1 mi W) 5.9E+1 (5/29)
(1.6E+1 to 1.6E+2) 1.3E+2 (6/31)
(1.3E+1 to 3.4E+2) 0 30
Medium or Pathway Sampled (Unit of Measurement and Reporting Period)
Type and Total Number of Analyses Performed Lower Limit of Detection1 Actual (Max.)
Location with Highest Annual Mean Control Locations Mean2 (#/total #)
(Range)
Number of Nonroutine Reported3 Measurements Medium or Pathway Sampled (Unit of Measurement and Reporting Period)
Type and Total Number of Analyses Performed Lower Limit of Detection1 Actual (Max.)
All Indicator Locations Mean2
(#/total #) (Range)
Name (Distance & Direction)
Mean2 (#/total #)
(Range)
Control Locations Mean2 (#/total #)
(Range)
Number of Nonroutine Reported3 Measurements Broadleaf Vegetation (pCi/kg wet)
(1980-1982)
Gamma Spec (10) 1311 3.7E+1 (6.0E+1)
All < LLD 0
134Cs 1.9E+1 (8.0E+1)
All < LLD 0
137Cs 2.1 E+1 (8.0E+1) 3.1 E+1 (2/7)
(1.8E+1 to 3.6E+1)
Site 2, Trans. Line, (1.2 mi SW) 3.6E+1 (1/1)
(Single Value)
All < LLD 0
Other Vegetation (pCi/kg wet)
(1980-1982)
Gamma Spec (32) 134Cs 8.4E+0 (8.0E+1)
137Cs 1.0E+1 (8.0E+1)
Fish (pCi/kg wet)
(1980-1982)
Gamma Spec (92) 134Cs 1.4E+1 (1.3E+2)
137Cs 1.8E+1 (1.3E+2) 2.8E+1 (50/71)
(1.1 E+1 to 1.0E+2)
Site 24, Recreation Lake, (5.5 mi, N) 3.4E+1 (17/23) 1.2E+1 to 1.0E+2) 3.1 E+1 (19/21)
(1.0E+1 to 7.9E+1) 0 58Co 2.6E+1 (1.3E+2)
54Mn 1.8E+1 (1.3E+2)
59Fe 9.0E+1 (2.6E+2)
65Zn 4.1E+1 (2.6E+2)
60Co 1.8E+1 (1.3E+2)
Sediment (pCi/kg)
(1980-1982)
Gamma Spec (24) 134Cs 2.3E+1 (1.5E+2)
137Cs 2.4E+1 (1.5E+2) 1.7E+2 (12/18)
(2.6E+1 to 4.5E+2)
Site 21, Parr Reservoir, (2.7 mi, SSW) 2.6E+2 (6/6)
(2.6E+1 to 4.5E+2) 4.2E+2 (6/6)
(1.8E+1 to 1.0E+3) 0 31
Table 9 (Cont.)- Radiological Environmental Monitoring Program Preoperational (Baseline) Summary Footnotes
- 1.
Values given are MDA values calculated from the program data analyses with maximum acceptable LLD values allowed from NRC guidelines given in parentheses.
- 2.
Mean and range are based on detectable measurements only. The fractions of detectable measurements at specific locations are indicated in parentheses.
- 3.
A non-routine measurement is any confirmed measured level of radioactivity in an environmental medium that exceeds the reporting requirements of VCSNS ODCM, Section 1.4.1.2.
- 4.
The baseline values are high because of the fallout from the Chinese bomb test in 1980.
The first set of data reflects the 1981 baseline. The second set of data reflects the 1982 baseline, essentially free of bomb test fallout. The 1982 data covers the period 1/1/82 -
10/22/82.
- 5.
Detection sensitivity is approximately 5 mrem/yr (0.5 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.
32
Table 10 - Results of 2016 Environmental Intercomparison Program with Independent Lab, Eckert & Ziegler Analytics, Inc.
Comparison Study (Measurement Unit)
Date Nuclides Vendor Lab Results Env Lab Results Agreement Gamma Isotopic Liquid 3/24 1311 88.9 88.7 Yes 1 Liter 141Ce 118 110 Yes (pCi/l) 51Cr 293 296 Yes (pCi/l) 134Cs 157 148 Yes 137Cs 194 218 Yes 58Co 141 146 Yes 54Mn 140 162 Yes 59Fe 157 181 Yes 65Zn 215 230 Yes 60Co 293 311 Yes Gamma Composite Filter 9/28 141Ce 65.3 62.5 Yes (pCi) 51Cr 165 173 Yes (pCi) 134Cs 95.1 81.1 Yes 137Cs 83.0 87.3 Yes 58Co 68.2 63.8 Yes 54Mn 107 118 Yes 59Fe 63.5 77.5 Yes 65Zn 125 145 Yes 60Co 94.4 94.8 Yes Alpha/Beta Water 4/19 Alpha 135 138 Yes (pCi/l)
Beta 250 255 Yes Gamma Isotopic 3/29 141Ce 2.68E-1 2.80E-1 Yes Pulverized 51Cr 6.62E-1 7.10E-1 Yes Soil 134Cs 3.54E-1 3.39E-1 Yes (pCi/g) 137Cs 4.38E-1 4.78E-1 Yes (pCi/g) 58Co 3.19E-1 3.17E-1 Yes 54Mn 3.17E-1 3.67E-1 Yes 59Fe 3.56E-1 4.27E-1 Yes 65Zn 4.85E-1 5.65E-1 Yes 60Co 6.63E-1 6.95E-1 Yes 1-131 Solid (pCi) 3/28 1311 95.7 89.8 Yes 33
Comparison Study (Measurement Unit)
Date Nuclides Vendor Lab Results Env Lab Results Agreement Tritium (pCi/l) 4/11 3H 4630 5060 Yes Gross Beta Filter 9/22 241Am 49.9 45.5 Yes (pCi) 137Cs 45.6 45.1 Yes Charcoal Cartridge 9/26 1311 60.0 62.7 Yes (pCi)
Gamma Isotopic Liquid 9/23 1311 49.0 56.1 Yes 4 Liter 141Ce 85.2 94.7 Yes (pCi/l) 51Cr 215 236 Yes (pCi/l) 134Cs 124 127 Yes 137Cs 108 120 Yes 58Co 89.0 95.8 Yes 54Mn 139 161 Yes 59Fe 82.8 96.3 Yes 65Zn 163 191 Yes 60Co 123 136 Yes 34
Table 11 -2016 Environmental Sampling Program Deviations Media Sample Locatio n
Month (Week No.)
Cause for Deviation Air Particulate And Radioiodine Site 30 Site 7 Site 6 Jan (03)
Jan (04)
Jul (30)
Insufficient volume.
Loss of power due to breaker trip.
Loss of power due to problem with transmission line. Power restored by line crew.
TLD N/A Apr (17)
TLD change out exceeded 100 days of previous change out due to a shipping error.
Site 47 May (18)
TLD missing.
35
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REFERENCE:
THE BASE FOR THIS MAP WAS PREPARED FROM A PORTION OF USGS STATE OF GEORGIA, 1S70.
57.VTUTC Wii EC South Corohno Electric & Gas Co.
Virgil C. Summer Nuclear Station Regional Location Map Figure 1-1 REV. DATE It-S
South Carolina Electric & Gas Co.
Virgil C. Summer Nuclear Stotion RADIOLOGICAL MONITORING PROGRAM LOCAL INDICATOR SAMPLE SITES Figure (-2 PEV, OM-SRA-R
CQ C
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LEGEND ISFSI TLD Location Groundwater Wells South Carolina Electric & Gas Co Virgil C Summer Nuclear Station RADIOLOGICAL-MONITORING PROGRAM PROTECTED AREA SITES n
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