ML12118A230

Submittal of Radiological Environmental Operating Report

ML12118A230
Person / Time
Site:	Summer
Issue date:	04/24/2012
From:	Lippard G South Carolina Electric & Gas Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12118A230 (46)

Text

George A. Lippard General Manager,Nuclear Plant Operations 803.345.4810 April 24, 2012 A SCANA COMPANY Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Enclosed is the South Carolina Electric & Gas Company (SCE&G) 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, Georg A. Lippard SBR/GAL/wm Enclosure c: K. B. Marsh (w/o enclosure) NRC Resident Inspector S. A. Byrne M. Coleman J. B. Archie M. B. Roberts N. S. Cams K. M. Sutton J. H. Hamilton (w/o enclosure) C. D. Stewart R. J. White (w/o enclosure) NSRC W. M. Cherry (w/o enclosure) RTS (LTD 312)

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

R. E. Martin PRSF (RC-12-0067)

Virgil C.Summer Station - Post Office Box 88

• Jenkinsville, SC - 29065 . F (803) 345-5209 J76

A SCANA COMPANY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPERATING PERIOD JANUARY 1, 2011 - DECEMBER 31, 2011 April 2012 Prepared by: / Brett Williams Health Physics Specialist Reviewed by: '/4 Michael Roberts Health Physics Supervisor Approved by:

Moses Coleman Manager Health Physics & Safety Services

EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report describes the V.C. Summer Environmental Monitoring Program and the program results for the calendar year 2011.

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 three hundred two analyses (1,302) performed to compile the data for the 2011 Environmental Report. Supplemental samples comprising one hundred ninety six (196) 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 2011 from V.C. Summer related radionuclide concentrations were within the range of concentrations observed in the past.

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

i

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 2011 Fission and Activated Corrosion Product Activity in 6 Sediment 3 Required Sampling Site Locations 8 4 Results of the 2011 Land Use Census Verification 11 5 Critical Receptor Evaluation for 2011 12 6 Radiological Environmental Monitoring Program 13 Specifications 7 Supplemental Radiological Environmental Monitoring 18 8 Radiological Environmental Monitoring Program Summary 22 for 2011 9 Radiological Environmental Monitoring Program 28 Preoperational (Baseline) Summary 10 Results of 2011 Environmental Intercomparison Program 33 with Independent Lab, Eckert & Ziegler Analytics, Inc.

11 2011 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.

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 2 0 th fuel cycle.

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

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

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

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

Radioactive liquid and gaseous releases from the facility and their potential influence on the surrounding biota and man are the primary concern of the Radiological Environmental Monitoring Program at VCSNS. This report summarizes the results of the Radiological Environmental Monitoring Program conducted during 2011. Data trends, control/indicator and preoperational/operational data intercomparisons, and other data interpretations are presented.

1

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

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

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

The program utilizes the concepts of control/indicator and preoperational

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

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

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

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

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

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

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

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

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

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

SSE) serves as a control location for garden monitoring. In the past Site 18 which is a private residence, was used as the control location for garden monitoring. The land owner declined to renew the lease and the control garden was relocated to Site 40 which is the location of the Station's Emergency Operating Facility.

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

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

Quality of analytical measurements is demonstrated by participation in a laboratory intercomparison program. Results of the intercomparison program with an outside vendor and VCSNS Count Room were satisfactory in 2011. 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.

3

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 2011 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 2011 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 3.46E+0 mrem/yr. In addition, the ODCM required environmental gardens (ESE 1.0 and E 1.0 mile) were found to have a calculated dose of 2.20E+0 and 4.26E+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 2011 are summarized in Table 8. For comparison, preoperational data are summarized in Table 9.

The Radiological Environmental Program attained a program compliance rate of approximately 98.4%. 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 (2.24E-2 pCi/mi3) 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 indicated 137 Cs at 1 of 12 samples taken at indicator location, Site 2 (transmission line 1.2 mi. SW) at a concentration of 2.33E-3 pCi/m 3 . This activity is below the required LLD of 6.OOE-2 pCi/Im 3 .

4

Activated charcoal cartridges indicated 1311 activity in 21 of 259 samples at all five indicator sites with concentrations ranging from 1.68E-2 to 1.76E-1 pCi/m 3 . Control Site 17 (Columbia Water Works 25 mi. SE) also indicated 1311 in 4 of 51 samples at concentrations ranging from 2.56E-2 to 1.39E-1 pCi/m 3 . 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 locations Site 4 (Fairfield Hydro 1.2 mi. WNW) and Site 17 (Columbia Water Works 25 mi. SE) were the indicator locations showing the highest mean exposure rate of 1.14E+1 ptR/hr. This is similar to the 2010 value of 1.14E+1 pR/hr and consistent with the highest mean exposure rate of 1.40 E+1 pR/hr measured during the preoperational period. 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 two indicator samples. Site's 21 (Parr Reservoir 2.7 mi. SSW) and Site 23 (Discharge Canal Monticello Reservoir 0.5 mi. ESE) had tritium concentrations of 7.34E+2 and 7.32E+2 pCi/I respectively. All concentrations were well below the reporting limit. 97.2% of indicator/control surface water samples were collected.

Gamma spectroscopy measurements of the ODCM required ground water samples did not indicate the presence of activated corrosion or fission products above the respective MDAs. Tritium analysis indicated the presence of tritium above MDA in one indicator sample. Site 112 (NPDES Well GW-9 0.36 mi. SSE) had a tritium concentration of 5.42E+2 pCi/l. This is an on-site well. 91.3% of indicator/control ground water samples were collected.

Gamma spectroscopy measurements of drinking water samples collected from the Jenkinsville water supply and Site 17 (Columbia Water Works 25.0 mi. SE) did not indicate the presence of activated corrosion or fission product activity above the respective MDAs with the exception of one sample from Site 17 (Columbia Water Works 25.0 mi. SE) which had an 1-131 concentration of 5.34E-1 pCi/I. This concentration is below the required LLD.

The highest indicator and control site-specific gross beta activity was measured at Site 17 (Columbia Water Works 25.0 mi. SE) at a level of 7.45E+0 pCi/I. 100% of indicator/control drinking water samples were collected.

There were no milk samples collected in 2011. Milk sampling is required to be performed at the three highest dose locations within 5 kilometers of the plant or at 5 to 8 kilometers of the plant, if doses are calculated to be greater than 1 mrem per year.

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

5

Gamma spectroscopy measurement of supplemental grass samples collected indicated 13 7Cs in 6 of 9 samples at Site 2 (transmission line 1.2 mi. SW) at concentrations ranging from 1.63E+1 to 3.38E+1 pCi/kg. 1 of 11 samples taken at control Site 40 (Emergency Operations Facility 11.9 mi. SSE) indicated 13 7Cs at a concentration of 1.29E+1 pCi/kg. The maximum preoperational control activity was 3.40E+2 pCi/kg. 91.7%

of indicator/control supplemental grass samples were collected.

Gamma spectroscopy measurements of the broadleaf samples collected indicated 1311 in 1 of 12 samples at Site 6 (Environmental Lab Garden 1.0 mi. ESE), and one of twelve samples at Site 7 (Environmental Lab Garden 1.0 mi. E), at concentrations of 9.69E+0 and 1.94E+1 pCi/kg respectively. These concentrations are below the required LLD. All of the required indicator/control broadleaf samples were collected.

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

Gamma spectroscopy measurements of the fish samples collected did not indicate the presence of activated corrosion or fission products above the respective MDAs for indicator sites. 1 of 6 control samples taken from Site 22 (Neal Shoals 26 mi. NNW) indicated 137 Cs at a concentration of 1.17E+1 pCi/kg. All of the required indicator/control fish samples were collected.

Gamma spectroscopy measurements of sediment samples indicated the detection of 137Cs in 1 of 4 indicator samples. At Site 21 (Parr Res. 2.7 mi. SSW) 137Cs at a concentration of 1.08E+2 pCi/kg was detected. 137 Cs was detected in 2 of 2 control samples taken at Site 22 (Neal Shoals 26 mi. NNW) at a concentration of 7.93E+1 and 1.43E+2 pCi/kg. All required indicator/control sediment samples were collected.

Table 2 - 2011 Fission and Activated Corrosion Product Activity in Sediment Corresponding Calculated Location Radionuclide Activity (pCi/kg) Annual Dose Equivalent (mrem/yr)

Total Body Maximum Mean Maximum Mean Monticello 137 Reservoir Cs 1.08E+2 1.08E+2 9.07E-3 9.07E-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, fish and grass.

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

" Tritium in two surface water samples at Site 21 (Parr Res. 2.7 mi. SSW) and Site 23 (Discharge Canal Monticello Reservoir .5 mi. ESE), and one ground water sample, Site 112 (NPDES Well GW-9 0.36 mi. SSE) which were well below the EPA drinking water standard.

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

Sediment samples at Control Site 22 (Neal Shoals 26.0 mi. NNW) also contained CS-1 37.

Samples obtained from all Control and Indicator air sample Sites, drinking water at Site 17 (Columbia Water Works 16.5 mi. S), broadleaf vegetation at Site 6 (Environmental Lab Garden 1.0 mi. ESE), and Site 7 (Environmental Lab Garden 1.0 mi. E), identified detectable concentrations of 1-131 that could be related to operation of VCSNS. Given the following facts, the detectable concentrations are not a result of VCSNS operation:

" The quantities of radioactive airborne effluents from VCSNS operations during 2011 did not increase significantly compared to 2010.

" Prior REMP sample results have not detected the presence of these isotopes in composited air particulate, activated charcoal cartridges, or broadleaf samples.

" The concentrations being detected in the indicator samples were also identified in the control samples for air samples.

As such, the atypical detection of these radionuclides is credibly attributed to the trans-Pacific transport of airborne releases from Dai-lchi, Fukushima following the March 11, 2011 Tohoku earthquake and is not related to the operations of VCSNS.

The dose from this activity represents a small fraction of VCSNS effluent dose limits. The absence of an impact was expected since historically, releases from VCSNS have been a small fraction of ODCM Specification limits.

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.

7

Table 3 - Required Sampling Site Locations Site Description Distance Direction 2 Sample Type(s) 3 No. (Miles) 1 Borrow Pit 1.2 179.8 S DQ 2 Transmission Line 1.1 225.0 SW AP, RI, DQ 3 Firing Range 1.2 270.0 W DQ 4 Fairfield Hydro 1.2 289.5 WNW DQ 5 Transmission Line Entrance 0.9 144.0 SE DQ 6 Environmental Lab Garden 1.0 111.0 ESE AP,RI,GA,DQ,GW 7 Environmental Lab Garden 1.0 97.8 E AP,RI,DQ, GA 8 Monticello Res. S of Rd 224 1.5 62.0 ENE DQ 9 Ball Park 2.3 41.6 NE DQ 10 Meteorological Tower #2 2.5 25.5 NNE DQ 12 Old Hwy 99 4.2 349.4N DQ 13 North Dam 2.9 333.0 NNW DQ 14 Dairy (Shealy 6.5 277.0 W MK,GR 16 Dairy (Parr) 20.0 275.5 W MK,GR 16a TLD Location 28.0 278.6W DQ 17 Columbia Water Works 25.0 144.0 SE AP,RI,DQ,DW 18 Residence/Pine Island Club 5 8' 16.5 165.0 S DQ,GA 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 Deploymentb 2.6 170.2 SSE DW 29 Trans. Line WSW of VCSNS 1.0 260.6 WSW DQ 30 Oak Tree North of Borrow Pit' 1.0 / 0.5 196.2 SSW DQ, AP, RI 31 McCrorey-Liston School 6.6 11.5 NNE DQ 32 Clark Bridge Road and Brooks Drive 4.6 24.0 NNE DQ 33 Rd 48 near Hwy 213 4.2 68.0 ENE DQ 34 Rd 419 North of Hwy 60 4.9 111.0 ESE DQ 35 Glenn's Bridge Road 4.6 132.0 SE DQ 36 Woods at Jenkinsville Post Office 3.1 151.0 SSE DQ 37 Residence 4.9 304.8 NW DQ 39 Lake Murray Water Treatment Facility 14.0 168.0 SSE DW 40 Emergency Operations Facility8 11.9 157.0 SSE GA, GR 8

Table 3 (cont) - Required Sampling Site Locations Site Description Distance Direction 2 Sample Type(s)3 No. I (Miles) 41 Below Catwalk at Trestle 3.8 182.0 S DQ 42 Broad River Rd (Peak Residence) 3.8 198.0 SSW DQ 43 Hwy 176 and Rd 435 5.2 236.0 SW DQ 44 Rd 28 at Cannon's Creek 2.8 256.6 WSW DQ 45 Rd 33 at Pomaria 5.8 253.2 WSW DQ 46 Rd 28 at Heller's Creek 3.7 291.5 WNW DQ 47 Fairfield Tailrace 1.0 316.0 NW DQ 52 Monticello (Rd 11) 3.8 13.0 NNE DQ 53 Rd 359 3.0 46.5 NE DQ 54 Jenkinsville School 1.7 72.5 ENE DQ 55 St. Barnabas Church 2.8 91.5 E DQ 56 Old Jenkinsville Dinner 2.0 144.0 SE DQ 58 Residence 2.5 157.0 SSE DQ 59 New Nuclear Deployment 6 2.6 170.2 SSE DQ, GW 60 Rd 98 near Rd 28 3.5 274.6 W DQ 100 Remediation Well (B-I) 450 Ft NW GW 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 104 Remediation Well (B-9) 175 Ft NE GW 105 Remediation Well (DW-11) 100 Ft ESE GW 106 Remediation Well (DW-7) 250 Ft SE GW 107 Remediation Well (B-28) 400 Ft SW GW 108 Remediation Well (DW-19) 250 Ft W GW 109 Remediation Well (B-35) 450 Ft NW GW 110 Remediation Well (B-36) 300 Ft NW GW 111 NPDES Well (GW-8) 0.27 320 SE 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 115 NPDES Well (GW-15) 0.39 330 SSE GW 9

Table 3 (cont) - Required Sampling Site Locations Footnotes

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

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

3. Sample Types:

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

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

5. Site 18 consists of two locations in close proximity to Lake Murray. Garden product samples are taken at the Wyse residence. The TLD is located on Pine Island.

6. 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.

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

8. Site 40 (11.9 mi. SSE) serves as a control location for garden monitoring. In the past Site 18 which is a private residence, was used as the control location for garden monitoring. The land owner declined to renew the lease and the control garden was relocated to Site 40 which is the location of the Station's Emergency Operating Facility.

10

Table 4 - Results of the 2011 Land Use Census Verification No. No.

Sector Nearest Residence Miles NearestGarden Miles Nearest Cattle Milked Miles NearestGoat Milked Miles N P. Oliver 3.73 Edna Fuller 4.01 John Robinson 0 3.4 NNE Thomas K. Crurnblin 2.9 3.21 Wi/Charles Coleman 0 4.97 NE Gregrey Guinyard Jr. 1.55 Edna Richards 3.21 ENE Essie Gregg (A) 1.56 Essie Mae Glenn 1.68 E Lynn Mincy 1.2 Lynn Mincy 1.2 ESE Carmie Lee Martin 1.1 James Pearson 1.36 SE Mary White 1.44 Mary White 1.44 Sim Roberts 0 4.7 SSE Ronnie Mann 2.39 Ronnie Mann 2.39 S Kelly Boulware 3.56 Kelly Boulware 3.56 Shirley Counts 0 5 SSW Nick Bates 3.11 Nora Wicker 3.77 Joe Smith 0 4.73 SW Marvin Miller 3.3 Marvin Miller 3.3 WSW Ron Hope 2.9 Steve All 4.83 Ken/Virg Graham (*) 0 4.98 Steve All 10 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 (A) Change In Closest Residence

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

Table 5 Critical Receptor Evaluation for 2011 DOSE*

NAME SECTOR MILES PATHWAY X/Q D/Q mRem/y John Robinson N 3.4 B 2.60E-07 8.OOE-10 8.01E-02 P. Oliver N 3.73 Res 2.20E-07 6.50E-10 8.21E-03 Thomas K. Crumblin NNE 2.9 Res 4.OOE-07 1.40E-09 1.50E-02 Will/Charles Coleman NNE 4.97 B 1.40E-07 4.30E-10 4.31E-02 Gregrey Guinyard Jr. NE 1.55 Res 2.OOE-06 6.60E-09 7.50E-02 Edna Richards NE 3.21 Res,Gar 4.40E-07 1.20E-09 3.33E-01 Bessie Gregg ENE 1.56 Res 1.80E-06 6.40E-09 6.77E-02 Essie Mae Glenn ENE 1.68 ResGar 1.50E-06 5.30E-09 1.43E+00 Garde n-7 E 1 Res,Gar 4.1OE-06 1.60E-08 4.26E+00 Lynn Mincy E 1.2 Res,Gar 2.60E-06 1.00E-08 2.67E)00 Garden-6 ESE 1 ResGar 2.30E-06 8.20E-09 2.20E+00 Carrie Lee Martin ESE 1.1 Res 1.80E-06 6.40E-09 6.77E-02 James Pearson ESE 1.36 ResGar 1.10E-06 3.70E-09 1.00E+00 Mary White SE 1.44 ResGar 7.20E-07 3.00E-09 7.94E-01 Sim Roberts SE 4.7 Res,Gar,B 6.00E-08 1.90E-10 7.07E-02 Ronnie Mann SSE 2.39 ResGar 1.50E-07 8.10E-10 2.10E-01 Kelly Boulw are S 3.56 ResGar 7.90E-08 4.00E-10 1.04E-01 Shirley Counts S 5 Res,Gar,B 4.00E-08 1.90E-10 6.86E-02 NND Construction Site SSW 0.49 Res 8.10E-06 6.40E-08 3.23E-01 Nick Bates SSW 3.11 Res 1.40E-07 9.50E-10 5.50E-03 Nora Wicker SSW 3.77 ResGar 9.60E-08 6.20E-10 1.59E-01 Joe Smith SSW 4.73 Res,B 6.00E-08 3.70E-10 3.91E-02 Marvin MViller SW 3.3 ResGar 1.00E-07 8.50E-10 2.14E-01 Ron Hope WSW 2.9 Res 1.10E-07 6.90E-10 4.29E-03 Steve All WSW 4.83 Res,Gar,G 3.70E-08 2.20E-10 5.92E-02 KenNirg Graham WSW 4.98 B 3.50E-08 2.10E-10 2.08E-02 Jerry Cassado W 2.55 Res 1.10E-07 6.60E-10 4.27E-03 Marion Livingston W 2 B 1.90E-07 1.20E-09 1.20E-01 Marion Livingston W 2.8 Res,Gar 9.00E-08 5.30E-10 1.36E-01 Marion Livingston W 2 & 2.8 Res,Gar,B BOTH BOTH 2.56E-01 KenNirg Graham W 5 Res,Gar,B,CIM 2.70E-08 1.40E-10 7.57E-02 Unknown Resident WVNW 2.53 Res 7.90E-08 3.80E-10 3.02E-03 Ronnie Leitzsey WNW 4.15 C/M,B,GIM,G 2.80E-08 1.20E-10 1.20E-01 Ronnie Leitzsey WNW 4.72 ResGar 2.20E-08 9.20E-11 2.43E-02 Ronnie Leitzsey WNW 4.15 & 4.72 Res,Gar,C/M,B,G/M,G BOTH BOTH 1.44E-01 Louise Workman NW 3.9 Res 8.50E-08 3.OOE-10 3.20E-03 Frank March NNVV 2.9 Res,Gar,B 2.80E-07 8.80E-10 3.28E-01 ODCM ORGAN DOSE E 1.1 ResGar 3.30E-06 1.30E-08 3.46E-00 Pathway Res = Residence B = Beef G = Goat Gar = Garden C/M = Cow/Milk(Infant) G/M = Cow/Milk(Infant)

Footnotes:

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 Criteria for Selection of Sampling and Collection Sample Type & Frequency of Pathway Pt and/or yam dle Sample Number & Location o Frequency Location Analysis AIRBORNE:

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

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

practicable corresponding to the residence having the highest anticipated offsite ground level concentration or dose.2 C) 1 Indicator sample to be Continuous sampler operation, N/A Gross beta following filter taken at the location of one with weekly collection, change; Quarterly of the dairies being composite (by location) sampled meeting2 4the for gamma isotopic.

criteria of VII(A). '

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

prevalent wind directions.

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

given in I(B) above.

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

given in I(C) above.

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

in nature to I(D) above.

13

Exposure Criteria for Selection of Sampling and Collection Sample Type & Frequency of Pathway and/or Sample Number & Location Frequency Location Analysis Sample ____________________ ti _________i 11 Ill. Direct A) 13 Indicator stations to Monthly or quarterly 12,3,4,5,6, Gamma dose monthly or form and inner ring of exchange 5s 7 two or more 7,8,9,10,29, quarterly.

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

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

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

C) 11 Stations to be placed in Quarterly exchange 7; two or 16,17,18,19, Gamma dose quarterly.

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

WATERBORNE IV. Surface A) 1 Indicator sample Time composite samples 6 with 213 Gamma isotopic monthly Water downstream to be taken at collection every month. with quarterly composite a location which allows for (by location) to be mixing a dilution in the analyzed for tritium.7 ultimate receiving river.

B) 1 Control sample to be Time composite samples 6 with 223 Gamma isotopic monthly taken at a location on the collection every month.5 with quarterly composite receiving river sufficiently (byz oatrioto 7 that no far upstream such effects of pumped storage operation are anticipated.

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

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

V. Ground Water A) 19 Indicator samples to be Quarterly grab sampling.7 6, 26, 27, Gamma isotopic and taken within the exclusion 100-115 tritium analyses boundary and in the quarterly. 7 direction of potentially affected ground water supplies.

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

Exposure Sample Criteria Sample for Selection Number of

& Location 11 Sampling and Collection Frequency Sample "

Location Type & Frequency of Analysis VI. Drinking A) 1 Indicator sample from a Monthly grab sampling.5 28 Monthly 5 gamma isotopic Water nearby public ground water and gross beta analyses supply source, and quarterly 7 composite for tritium analyses.

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

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

INGESTION:4 VII. Milk A) Samples from milking Semimonthly when animals To be Gamma isotopic and I-5 animals in 3 locations are on pasture8 monthly other supplied 131 analysis 5

within 5 km having the times. when milk semimonthly 8 when highest dose potential. If animals are animals are on pasture, there are none then 1 found in monthly other times.5 sample from milking accordance animals in each of 3 areas with criteria between 5 to 8 km distance VlI.A.

where doses are calculated to be greater than 1 mrem per year. 10 B) 1 Control sample to be Semimonthly when animals ,16 Gamma isotopic and I-taken at the location of a are on pasture8' monthly other 131 analysis dairy > 20 miles distance times.5 "' semimonthly8 when and not in the most animals are on pasture, prevalent wind direction.2 monthly other times.5 C) 1 Indicator grass (forage) Monthly when available. 5 To be Gamma isotopic.

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

511 Monthly when available.

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

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

15

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

VIII. Food A) 2 Indicator samples of Monthly when availabl6. 6 Gamma isotopic on edible Products broadleaf vegetation grown 7 portion.

in the 2 nearest offsite location of highest calculated annual average ground level D/Q if milk sampling is not performed within 3 km or if milk sampling is not performed at a location within 5-8 km where the doses are calculated to be greater than 1 mrem/yr.10 5 12 B) 1 Control sample for the Monthly when available. ' 18,40 Gamma isotopic on edible same foods taken at least portion.

10 miles distance and not in the most prevalent wind direction if milk sampling is not performed within 3 km or if milk sampling is not performed at a location within 5 to 8 km where the doses are calculated to be greater than 1 mrem/yr.10 IX. Fish A) 1 Indicator sample to be Semiannual9 collection.' 233 Gamma isotopic on edible taken at a location in the portions semiannually. 9 upper reservoir.

B) 1 Indicator sample to be Semiannual 9 collection.' 213 Gamma isotopic on edible 9

taken at a location in the. portions semiannually.

lower reservoir.

9 C) 1 Control sample to be Semiannual collection.' 223 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 X. Sediment A) 1 Indicator sample to be Semiannual grab sample. 233 Gamma isotopic.

taken at a location in the upper reservoir.

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

taken on or near the shoreline of the lower reservoir.

9 C) 1 Control sample to be Semiannual grab sample. 223 Gamma isotopic.

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

16

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

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

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

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

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

5. Not to exceed 35 days.

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

7. At least once per 100 days.

8. At least once per 18 days.

9. At least once per 200 days.

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

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

12. Site 40 serves as a control location for garden.monitoring. In the past Site 18 which is a private residence, was used as the control location for garden monitoring. The land owner declined to renew the lease and the control garden was relocated to Site 40 which is the location of the Station's Emergency Operating Facility.

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 FrequencyI Location Analysis AIRBORNE:

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

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

S-1(A) above, collection.

S-Ill. Direct A) 5 stations to be placed Quarterly 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 collection13,5 tritium.

wastewater discharge.

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

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

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

18

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

S-VII. Milk 4 A) 1 Sample from one of the Biweeklygrab 14 Gamma isotopic and I-nearest affected dairies at sample.b14,+ 131 analysis biweekly.

or beyond 5 miles.

B) 1 Control sample to be Biweeklygrab 16 Gamma isotopic and I-taken at the location of a sample.8 14 131 analysis biweekly.

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

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

sample to be taken at the available.

location of S-VII(A) above.

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

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

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

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

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

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

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

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

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

fruit, grain).

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

19

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

Sludge each storm drain outfall.

B) 3 Indicator sludge Semiannually. 006A, Gamma isotopic.

samples taken at sludge (Reference 2.6) 006B &

lagoons. 008 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 2011 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine Pathway Sampled Number of of Detection2 Mean 3 (#ItotaI #) Name Mean (#/total # Mean3 (#/total #) Reported 4 (Unit of Analyses Actual (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed' (Range)

Air Particulate Gross Beta 6.25E-3 2.15E-2 (256/258) Site 7, Environmental 2.24E-2 (51/51) 2.06E-2 (51/51) 0 (pCi/m 3 ) (309) (1.0E-2) (3.41E-3 to 3.39E-2) Lab Garden, (1.17E-2 to 3.24E-2) (2.60E-3 to 3.20E-2)

(1.0 mi. E _

Gamma Spec

/72) 104Cs 2.40E-3 All < LLD All < LLD 0 (5.OE-2)

U*Cs 2.85E-3 2.33E-3 (1/60) Site 2, Environmental 2.33E-3 (1/60)9 All < LLD 0 (6.OE-2) (2.33E-3 to 2.33E-3) Lab Garden, (2.33E-3 to 2.33E-3) 1 (1.2 mi. SW)

Air Radioiodine 1111 (310) 1.87E-2 6.48E-2 (21/259) Site 30, Site Boundry, 8.23E-2 (4/52)ý 6.80E-2 (4/51)ý 0 (pCi/m3) (7.OE-2) (1.68E-2 to 1.76E-1) (0.5 mi. SSW) (2.40E-2 to 1.76E-1) (2.56E-2 to 1.39E-1)

Direct (TLD) 5 Gamma(135) 8.30E+0 (116/116) Site 4, Fairfield 1.14E+1 (4/4) 8.38E+0 (19/19) 0

([ R/hr) Quarterly N/A (5.27E+0 to 1.18E+1) Hydro, (1.2 mi. WNW) (1.09E+1 to 1.18E+1) (5.69+0 to 1.22E+1)

Gamma(24) 8.76E+0 (24/24) Site 52, Monticello Rt. 1.16E+1 (4/4) N/A 0 Special Interest N/A (5.11E+O to 1.19E+1) 11, (3.8 mi. NNE) (1.12E+1 to 1.19E+1)

Surface Water 3H (36) 5.10+2 7.33E+2 (2/24) Site 21, Parr Res., 7.34E+2 (1/12) All < LLD 0 (pCi/I) (2.OE+3) 7.32E+2 to 7.34E+2 (2.7 mi. SSW) 7.34E+2 to 7.34E+2 Gamma Spec(36)

ýMn 2.30E+0 All < LLD All < LLD 0 (1.5E+1) buCo 2.53E+0 All < LLD All < LLD 0 (1.5E+1) bvFe 5.83E+0 All < LLD All < LLD 0 (3.OE+1) buCo 2.39E+0 All < LLD All < LLD 0 (1.5E+1) bbZn 4.98E+0 All < LLD All < LLD 0 (3.OE+1) 9bZr 4.76E+0 All < LLD All < LLD 0 (3.OE+1)

VNb 2.81 E+0 All < LLD All < LLD 0 1

(1.5E+1) 34Cs 2.09E+0 All < LLD All < LLD 0 (1.5E+1) 22

Table 8 (cont.) - Radiological Environmental Monitoring Program Summary for 2011 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations 3 Control3 Locations Nonroutine4 Pathway Number of of Mean 3 (#/total #) Name Mean (#/total #) Mean (#/total #) Reported Sampled (Unit of Analyses Detection (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed' Actual (Max.)

1 Surface-Water JCs 2.29E+0 All < LLD All < LLD 0 (Continued) 4 (1.8E+1) 1 UBa 1.50E+1 All < LLD All < LLD 0 (6.OE+1)

La 6.69E+0 All < LLD All < LLD 0 (1.5E+1)

Ground Water 3H (73) 5.1OE+2 5.42E+2 (1/69) Site 112 NPDES Well 5.42E+2 (1/12) All < LLD 0 (pCi/I) 2.00E+3 5.42E+2 to 5.42E+2 GW-9, (.36 mi. SSE) 5.42E+2 to 5.42E+2 Gamma Spec (67)

M*n 5.60E+0 All < LLD All < LLD 0 (1.5E+1) btCo 5.43E+0 All < LLD All < LLD 0 (1.5E+1)

• Fe 1.09E+1 All < LLD All < LLD 0 (3.0E+1) bUCo 5.73E+0 All < LLD All < LLD 0 (1.5E+1) bbZn 1.24E+1 All < LLD All < LLD 0 (3.OE+1) 9Zr 9.36E+O All < LLD All < LLD 0 (3.0E+1)

=Nb 8.56E+0 All < LLD All < LLD 0 14 (1.5E+1) 3 Cs 5.04E+0 All < LLD All < LLD 0 (1.5E+1) l*3Cs 5.36E+0 All < LLD All < LLD 0 4 (1.8E+1) l UBa 2.35E+1 All < LLD All < LLD 0 (6.OE+1) 14ULa 9.09E+0 All < LLD All < LLD 0 (1.5E+1) 23

Table 8 (Cont.) - Radiological Environmental Monitoring Program Summary for 2011 Location with Hi hest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine4 Pathway Number of of Mean 3 (#/total #) Name 3 Mean (#/total #) Mean 3 (#/total #) Reported Sampled (Unit of Analyses Detection2 (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed' Actual (Max.)

Drinking Water" Gross Beta (36) 1.39E+0 2.44E+0 (15/24) Site 17, Columbia 2.57E+0 (9/12) 2.09E+0 (10/12) 0 (pCi/I) (4.OOE+0) (1.29E+0 to 7.45E+0) Water Works, (1.29E+O to 7.45E+0) (1.45E+0 to 2.88E+0)

(25 mi, SE) 6H (36) 5.11E+2 All < LLD All < LLD 0 (2.OE+3)

Gamma Spec (72)1 b4Mn 2.96E+ 0 All < LLD All < LLD 0 (1.5E+ 1) bbCo 2.96E+ 0 All < LLD All < LLD 0 (1.5E+ 1)

• Fe 5.81 E+ 0 All < LLD All < LLD 0 (3.OE+ 1)

• UCo 3.25E+ 0 All < LLD All < LLD 0 (1.5E+ 1) bbZn 6.88E+0 All < LLD All < LLD 0 (3.OE+ 1)

YbZr 5.18E+ 0 All < LLD All < LLD 0 (3.OE+ 1)

U5Nb 4.90E+ 0 All < LLD All < LLD 0 (1.5(E + 1) 1411 6.36E-1 5.34E-1 (1/24) Site 17, Columbia9 5.34E-1 (1/12) All < LLD 0 (1.OE+ 0) (5.34E-1 to 5.34E-1) Water Works, (5.34E-1 to 5.34E-1)

__________25 mi, SE _ _ __ _ _

1 1-Cs 3.20E+ 0 All < LLD All < LLD 0 (1.5E + 1)

I&Cs 3.20E+ 0 All < LLD All < LLD 0 (1.8E + 1) 140 Ba 1.31E+ 1 All < LLD All < LLD 0 (6.OE+ 1) 4.45E+ 0 All < LLD All < LLD 0 (1.5E+ 1) 24

Table 8 (Cont.) - Radiological Environmental Monitoring Program Summary for 2011 Location with Highest Annual Mean Number of Medium or Type and Total Lowerof Limit All Indicator Locations Mean3 (#/total #) Name Mean 3 (#/total #) Control Mean3 Locations

(#/total #) Nonroutine Reported 4 Pathway Number of 2 Sampled (Unit of Analyses Detection2 (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed' Actual (Max.)

Broadleaf Gamma Spec Vegetation (38)

(pCi/kg wet) ______ __________ __________ __________

1w. 1 2.11E+1 1.45E+1 (2/24) Site 7, Environmental 1.94E+1 (1/12) All < LLD 0 (6.OE+ 1) (9.69E+O to 1.94E+1) Lab Garden, (1.94E+1 to 1.94E+1)

(1.0 mi. E _

1Cs 1.93E+1 All < LLD All < LLD 0 (6.0E+ 1) 2.42E+1 All < LLD All < LLD 0

_____________ (~~~~8.0E+

1) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Fish7 Gamma Spec (pCi/kg wet) (18)

`Mn 1.75E+1 All < LLD All < LLD 0 (1.3E+ 2)

• Co 1.77E+1 All < LLD All < LLD 0 (1.3E+ 2) b9Fe 3.89E+1 All < LLD All < LLD 0 (2.6E+ 2) bUCo 1.95E+1 All < LLD All < LLD 0 (1.3E+2)

. Zn. 4.08E+1 All < LLD All < LLD 0 134C_ (2.6E+2) 144 Cs 1.62E+1 All < LLD All < LLD 0 (1.3E+2) jCs 1.76E+1 All < LLD 1.17E+1 (1/6) 0 (1.5E+2) (1.17E+1 to 1.17E+1) 25

Table 8 (Cont.) - Radiological Environmental Monitoring Program Summary for 2011 Location with Hiclhest Annual Mean Number of 3

Medium Pathwayor Type and Total Number of Lowerof Limit 2 All Mean Indicator Locations

(#1total #) Name Mean3 (#/total #) Mean 3 (#/total Control Locations#) Reported 4 Nonroutine Sampled (Unit of Measurement) Analyses Performed' Detection2 Actual (Range) (Distance & Direction) (Range) (Range) Measurements (Max.)

Sediment 8 Gamma Spec (6)

(pCi/kg) __________4 ________ _____________ ________ ____

5 Mn 1.63E+1 All < LLD All < LLD 0 NIA b-Co 1.49E+1 All < LLD All < LLD 0 N/A WUCo 2.48E+1 All < LLD All < LLD 0 N/A

-14 Cs 1.32E+1 All < LLD All < LLD 0 (1.5E+2) 13Cs 1.55E+1 1.08E+2 (1/4) Site 22, Neal Shoals, 1.11E+2 (2/2) 1.11E+2 (2/2) 0 (1.8E+2) (1.08E+2 to 1.08E+2) (26 mi. NNW) (7.93E+1 to 1.43E+2) (7.93E+1 to 1.43E+2) 26

Table 8 (cont) - Radiological Environmental Monitoring Program Summary for 2011 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 1 iR/hr).

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

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

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

8. Elevated 23 2 levels of 2 14 Pb and 2 14 Bi plus other 22 6 Ra daughter products and 22 8Ac plus other Th daughter products were observed in all sediment samples. The values are not reported here because they are naturally occurring (do not originate from VCSNS) and furnish no quantifiable information of interest.

9. Samples obtained from these locations during 2011 identified detectable concentrations of isotopes that could be related to operation of VCSNS. Given the following facts, the detectable concentrations are not a result of V.C. Summer Generating Station operation:

(1) The quantities of radioactive airborne effluents from VCSNS operations during 2011 did not increase significantly compared to 2010.

(2) Prior REMP sample results have not detected the presence of these isotopes in composited air particulate, activated charcoal cartridges, or broadleaf samples.

(3) The concentrations being detected in the indicator samples were also identified in the control samples for activated charcoal cartridges.

As such, the atypical detection of these radionuclides is credibly attributed to the trans-Pacific transport of airborne releases from Dai-Ichi, Fukushima following the March 11, 2011 Tohoku earthquake and is not related to the operations of VCSNS.

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

27

Table 9- Radiological Environmental Program Preoperational (Baseline) Summary Location with Highest Annual Mean Medium or Pathway Type and Total Lower Limit of All Indicator Control Locations Number of Sampled (Unit Sapeoff Ui Number off Nme Detection1 Actual Locations Mean2 Name aeMa MeanL #ttl# #) Cotal Mean2 (#1total #) Nonroutine Reotd Measurement and Analyses (M a l (#/tons Mean (Distance & Direction) (Range) Meange) Reported3 Reporting Period) Performed (max.) (#/total #) (Range) (Range) Measurements Air Particulate Gross Beta 4.1E-3 1.1E-1 (562/564)4 Site 13, North Dam, 1.3E-1 (52/52) 1.2E-1 (153/155) 0 (pCi/m 3 ) (1300) (1.OE-2) (1.3E-2 to 5.5E-1) (2.9 mi NNW) (2.1 E-2 to 5.5E-1) (7.9E-3 to 6.1 E-1)

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

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

Gamma Spec 14Cs 3.OE-3 All < LLD All < LLD 0 (1.OE-2) 1 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.OE-2) (1.5E-3 to 5.2E-3) (2.4 mi NNE) (2.5E-3 to 5.2E-3) (3.2E-3 to 5.6E-3)

Air Radioiodine 1j11 (290) 3.6E-2 All < LLD All < LLD 0 3

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

(1978-1982)

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

Surface Water 0 3

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

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

Gamma Spec (140)

Mn 2.7E-1 All < LLD All < LLD 0 (1.5E+1) I Co 2.9E-1 All < LLD All < LLD 0 (1.5E+1) b9Fe 6.OE+0 All < LLD All < LLD 0 6=

.................. (3.OE+1) bUCo 2.4E-1 All < LLD All < LLD 0 (1.5E+1) bbZn 7.9E-1 All < LLD All < LLD 0 (3.OE+1) 9tZr 5.2E-1 All < LLD All < LLD 0 (1.5E+1)

. Nb

. 3.3E-1 All < LLD Ail < LLD 0 I =

............... (1.5E+1) 1 3Cs 3.OE-1 All < LLD All < LLD 0

__ ___ ______ _____ (1 .5E+1) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

28

Location with Highest Annual Mean Medium or Pathway Type and Total Lower Limit of All Indicator 2 (#/to Control Locations Number of Sampled (Unit of Number of Detection' Actual Locations Mean2 Name Mean tal #) on 1tro Nonroutine3 Measurement and Analyses (M a l (#/tons #) (Rtage) (Range) Reported Reporting Period) Performed (Max.) (#/total #) (Range) (Range) Measurements I*3Cs 2.2E-1 All < LLD All < LLD 0 14 (1.8E+1) uBa 2.2E+O All < LLD All < LLD 0 (6.0E+1)

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

Ground Water Site 26, Onsite Well 3

(pCi/I) H (29) 9.OE+2 1.5E+3 (16/16) P4,1.6E+3 (8/8) 1.3E+3 (13/13)

(2.05+3) (9.5E+2 to 2.3E+3) (265 ft, (9.5E+2 to 2.3E+3) (1.OE+3 to 1.9E+3)

(1981-1982)

Gamma Spec (32)

• qMn 3.7E+0 All < LLD All < LLD 0

_(1.5E+1)

• Co 3.8E+0 All < LLD All < LLD 0

_ (1.5E+1) 77e 7.8E+0 All < LLD All < LLD 0 (3.OE+1) bUCo 3.8E+0 All < LLD All < LLD 0 (1.5E+1) bbf 8.1E+0 All < LLD All < LLD 0 (3.OE+1) vbZr 6.8E+0 All < LLD All < LLD 0 (1.5E+1)

. Nb. 4.6E+0 All < LLD All < LLD 0 11=(1.5E+1) 14 Cs 3.7E+0 All < LLD All < LLD 0 (1.5E + 1) 131Cs 3.8E+0 All < LLD All < LLD 0 (1.8E + 1) 140 Ba 1.9E+1 All < LLD .0 (6.OE+1) l4ULa 5.OEO All < LLD All < LLD 0 (1982 only) (1.5E+1)

Drinking Water" Gross Beta 7 (2.0E+0)

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

Gamma Spec (44) 0"Mn 3.OE-1 All < LLD 0

=____

................ (1.5E+1) bCo 2.7E-1 All < LLD 0 (1.5E+1) I 29

Location with Highest Annual Mean Medium or Pathway Type and Total Lower Limit of All Indicator Control Locations Number of Sampled (Unit of Number of Name MeanM(#/total #) Nonroutine Reporting Period) Performed (Max.) (#/total #) (Range) (Distance & Direction) (Range) (Range) Measurements bFe 9.6E0 All < LLD 0 (3.OE+1) buCo 2.6E-1 All < LLD 0 (1.5E+1)

=fn 3.4E-1 All < LLD 0

= _(3.OE+1)

UZr 4.8E-1 All < LLD 0 (1.5E+1)

• 1 1 3.4E-1 All < LLD 0 (1.5E+1)

=Nb 7.4E-1 All < LLD 0 (1.0E+O) 1 4

• Cs 2.2E-1 All < LLD 0 (1.OE+I)

ICs 2.4E-1 All < LLD 0 (1.8E+1) 14

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

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

Milk Gamma Spec (pCi/I) (94)

(1981-1982)

J11 6.3E-1 All < LLD All < LLD 0 (1.OE+0) 14 J Cs 3.3E+0 All < LLD AlR.< LLD 0 (1.5E+1)

Cs 4.6E0 4.1E+0 (8/47) Site 14, Dairy, 4.1E+0 (8/47) 5.7E+O (37/47) 0

-77r-- (1.5E+1) (2.8E+0 to 6.1 E+0) (5.1 mi., W) (2.8E+0 to 6.1 E+0) (3.7E+0 to 9.2E+0) 4 l UBa 1.1E+1 All < LLD All < LLD 0 (1.5E + 1) 14uLa 4.4E+0 All < LLD All < LLD 0 (1.5E+1)

Grass (pCi/kg wet) Gamma Spec (1981-1982) (82)_ _

6.7E+1 All < LLD All < LLD 0 (6.OE+l) 134Cs 2.7E+1 All < LLD All < LLD 0

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

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

Vegetation (pCi/kg wet)

(1980-1982) 1311 3.7E+1 All < LLD 0 (6.OE+1)

Cs 1.9E+1 All < LLD 0 (8.0E+1)

IfCs 2.1E+1 3.1EE+1 (2/7) Site 2, Trans. Line, 3.6E+1 (1/1) All < LLD 0 (8.0E+1) . (1.8E+1 to 3.6E+1) (1.2 mi SW) (Single Value)

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

(1980-1982) ________ ________ _ _ _ _ _ _ _ _ _ _________

( 1rCs 8.4E+0 All < LLD All < LLD 0 (8.0E+1)

T"Es 1.0E+1 All < LLD All < LLD 0 (8.OE+1)

Fish (pCi/kg wet) Gamma Spec (1980- 1982) /92) 1.5Cs 1.4E+1 All < LLD All < LLD 0 14 (1.3E+2)

J Cs 1.8E+1 2.8E+1 (50/71) Site 24, Recreation 3.4E+1 (17/23) 3.1E+1 (19/21) 0 (1.3E+2) (1.1E+1 to 1.OE+2) Lake, (5.5 mi, N) 1.2E+1 to 1.OE+2) (1.0E+1 to 7.9E+1) bUCo 2.6E+1 All < LLD All < LLD 0 (1.3E+2)

. Mn. 1.8E+1 All < LLD All < LLD 0 (1.3E+2) b9Fe 9.0E+1 All < LLD All < LLD 0 (2.6E+2) bZn 4.1E+1 All < LLD All < LLD 0 (2.6E+2)

-UCo 1.8E+1 All < LLD All < LLD 0 (1.3E+2)

Sediment (pCi/kg) Gamma Spec (24)

(1980-1982) _

14Cs 2.3E+1 All < LLD All < LLD 0 (1.5E+2) iCs 2.4E+1 1.7E+2 (12/18) Site 21, Parr 2.6E+2 (6/6) 4.2E+2 (6/6) 0 (1.5E+2) (2.6E+1 to 4.5E+2) Reservoir, (2.6E+1 to 4.5E+2) (1.8E+1 to 1.OE+3) 1__ _ _ _(2.7 1____ mi, SSW) I I _II 31

Table 9 (Cont.)- Radiological Environmental 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 jR/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 2011 Environmental Intercomparison Program with Independent Lab, Eckert & Ziegler Analytics, Inc.

Comparison Study VendorLab EnvLab (Measurement Unit) Date Nuclides Results Results Agreement Gamma Isotopic Liquid 3/23 1311 94 112 Yes 51 1 Liter Cr 196 231 Yes (pCi/I) 134 Cs 85.6 85.6 Yes 1370S 135 153 Yes 58 Co 74.4 82.5 Yes 54Mn 59 175 202 Yes Fe 115 140 Yes 65 Zn 60Co 172 189 Yes 113 117 Yes Gamma Filter 9/30 141Ce 72.0 73.0 Yes (pCi) 51Cr 244 304 Yes 134 Cs 139 120 Yes 13 7Cs 123 135 Yes 58Co 105 112 Yes 54 Mn 163 186 Yes 59 Fe 59.2 54.0 Yes 65 Zn 60 Co 195 223 Yes 170 175 Yes Alpha/Beta Water 4/26 Alpha 238 224 Yes (pCi/I) Beta 205 230 Yes Gamma Isotopic 3/21 '1Cr 4.80E-1 3.74E-1 Yes Pulverized 134 Cs 2.1OE-1 1.64E-1 Yes Soil 13 7 Cs 4.19E-1 4.06E-1 Yes (pCi/g) 58 Co 1.82E-1 1.59E-1 Yes 54 Mn 4.28E-1 3.73E-1 Yes 59 Fe 2.81E-1 2.72E-1 Yes 65 Zn 4.20E-1 3.82E-1 Yes 60Co 2.76E-1 2.41E-1 Yes Yes 1-131 Solid 3/31 128 123 Yes (pCi) 33

Comparison Study Ncid Vendor Lab Env Lab (Measurement Unit) Date uies Results Results Agreement Tritium 4/7 3H 4530 4620 Yes (pCi/l)

Gross Beta Filter 10/19 N/A 80 76.3 Yes (pCi)

Charcoal Cartridge 9/26 1311 80.5 95 Yes (pCi)

Gamma Isotopic Liquid 9/29 1311 80.1 102 Yes 4 Liter 141Ce 91.5 109 Yes (pCi/I) 51Cr 310 347 Yes 134Cs 176 197 Yes 1 37 CS 156 183 Yes 58 Co 134 160 Yes 54Mn 59 207 251 Yes Fe 75.2 91.3 Yes 65 Zn 60 Co 247 294 Yes 215 241 Yes Gamma Simulated Gas 9/15 141Ce 415 398 Yes 4 Liter 51Cr 1410 1340 Yes (pCi/I) 134 Cs 798 809 Yes 137Cs 708 714 Yes 58 Co 607 626 Yes 54 Mn 939 972 Yes 59 Fe 341 391 Yes 65 Zn 1120 1150 Yes 60 Co 977 969 Yes 34

Table 11 - 2011 Environmental Sampling Program Exceptions Sample Month Media Location (Week No.) Cause for Exception Air Particulate Site 7 Feb (05) Filter not centered on sample head.

And Site 17 Nov (47) Power out due to construction.

Radioiodine Site 8 Nov (48) Breaker tripped.

Ground Water Site 111 Feb (07) The station has experienced issues Site 115 Feb (07) with ground water intrusion into plant Site 115 May (20) buildings and structures. In 2008, a Site 107 Jun (25) modification was implemented to Site 111 Aug (33) install fourteen dewatering wells. This Site 115 Aug (33) lowered the water table in the area Site 107 Sep (38) below the level of the existing wells.

Site 111 Nov (46)

Site 115 Nov (46)

Site 107 Dec (51)

TLD Site 20 Apr (14) TLD missing.

Surface Water Site 21 Aug (33) Sampler did not collect complete sample due to power outages.

Grass Site 2 Jan (04) Sample not available.

Site 7 Jan (04) Sample not available.

Site 18 Feb (07) Sample not available.

35

LEGEND

• CONTROL SAMPLE LOCATIONS A=AIR PARTICULATE SITE D=DIRECT (TLD) SITE

]=AIRBORNE RADIOIODINE SITE W=WATER SITE O=OTHER (GARDEN PRODUCTS, FISH, SEDIMENT, GRASS, MILK)

REFERENCEs THE BASEFORTHIS MAPWASPREPARED FROMA PORTION OF USGS STATE OF GEORGIA. 1970.

0 0 South Carolina Electric & Gas Co.

Virgil C. Summer Nuclear Statlon Reglonal Location Map Fiqure 1-1

. REVDArE m-e

LEGEND '

Ch 215

• PRIMARY SAMPLE LOCATIONS M N13 4 1

A AIR PARTICULATE SAMPLE SITE D =DIRECT (TLO) SAMPLE SITE I= AIRBORNE RADIOIODINE SAMPLE SITE Ch

• D MT L0 "

W= WATER SAMPLING LOCATION m. 1\

0 OTHER 0= TLD (D) SAMPLING LOCATIONS S\

........... 5t. JoemMill C7°"0', 9,EO ,"* ,-e C! , *I4 97 0 me. p .. ....

,. oN.. * . Il-o,* ... * .

1760

.-- C..

SL --." ' - 270"N-00,90O A00 44 ,41

• 1tw fChh.----

f 5 30(A.

9 1 OAIAVLE

• y *4" C2 4

• ~R .. '0 .'

4. N$2. Ch.e "..\ýA * - Ch.

4 04OO 0 PA O ~~-400 ot idroli8Eeti ~ o a I. 7 IA'Vri C umrNcla tto KI-P 4ý ESt Pah -I ' ADOOGCL OITRNGPOGA 5 C. LOCL-NDIATR-SMPE-STE

- aigure71-1

p 4

(I /Hwdy 21 II' (AY.D~ I

/13 90*

ýAMPLER 135' LEGEND FIGURE 1-3 PRIMARY SAMPLE LOCATIONS MAP Cove~t3 "4 HL 0-I ADD1!ITINA AIR PARTICULATE SAMPLE SITE NOCCONTROL LOCATIONS ARE WAIMIAO DIRECT (TLD) SAMPLE SITE (0UARTERLY)

AIRBORNE RADIOIODINE SAMPLE SITE

/ WATER SAMPLING LOCATION V.C.St**fR NUCLEAR STATION i OTHER ON SITE WELLS ----4 -22,052

o CT

-- i______-

_--~I~

_Ed 26 VA~S Acom PotlFacf w114 ...

• ~ i 113m*/..

Emis

• South Carolina Electric & Gas Co

~Virgil C Summer Nuclear Station

• RADIOLOGICAL MONITORING PROGRAM U' SECURITY AREA GROUNDWATER SITES

]Figure 1-4

CwPH N

W+E s

VO4Cd,Aý South Carolina Electric & Gas Co Virgil C Summer Nuclear Station RADIOLOGICAL MONITORING PROGRAM PROTECTED AREA GROUNDWATER SITES Figure 1-5