ML092960482

Radiological Environmental Operating Report, for the Period January 1, 2007 Through December 31, 2007

ML092960482
Person / Time
Site:	Summer
Issue date:	04/23/2008
From:	Gatlin T South Carolina Electric & Gas Co
To:	Mccree V NRC/RGN-II
References
RG 4.008
Download: ML092960482 (40)

Text

Jper-Thomas D. Gatlin GeneralManager,Nuclear Plant Operations 803.345.4342 A SCANA COMPANY April 23, 2008 Mr. Victor M. McCree Acting Regional Administrator USNRC, Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street SW Suite, 23T85 Atlanta, GA 30303-8931

Subject:

VIRGIL C. SUMMER NUCLEAR STATION 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, Thomas D. Gatlin SBR/TDG/sr Enclosure c: K. B. Marsh (w/o enclosure) K. M. Sutton S. A. Byrne E. Everett N. S. Cams INPO Records Center J. H. Hamilton (w/o enclosure) J&H Marsh & McLennan R. J. White (w/o enclosure) NSRC Document Control Desk LTD (312)

R. E. Martin File (818.02-2, RR 83( )0)

M. Coleman PRSF (RC-08-0058)

M. B. Roberts NRC Resident Inspector SCE&G I Virgil C.Summer Nuclear Station - P.0.Box 88

• Jenkinsville, South Carolina 29065 *T (803) 345.5209

• www.sceg.com

A SCANA COMPANY RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPERATING PERIOD JANUARY 1, 2007 - DECEMBER 31, 2007 April 2008 Prepared by:

Brett Williams Health Physics Specialist Reviewed by:

Michael Roberts Health Physics Supervisor Approved by:

Paul Mothena 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 2007.

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 eighteen analyses (1,318) performed to compile the data for the 2007 Environmental Report. Supplemental samples comprising one hundred seventy four (174) 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 2007 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 radioactive concentration in groundwater and drinking water were the only indicators with VCSNS produced radioactivity. These activities were well below the 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.

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TABLE OF CONTENTS PAGE INTRODUCTION 1 DESCRIPTION OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2 LAND USE CENSUS 3 MONITORING RESULTS AND DISCUSSION 4 CONCLUSION 7 ii

LIST OF TABLES TABLE PAGE 1 Monitoring Methods for Critical Radiation Exposure 2 Pathways 2 2007 Fission and Activated Corrosion Product Activity in 6 Sediment 3 Required Sampling Site Locations 8 4 Results of the 2007 Land Use Census Verification 11 5 Critical Receptor Evaluation for 2007 12 6 Radiological Environmental Monitoring Program 13 Specifications 7 Supplemental Radiological Environmental Monitoring 18 8 Radiological Environmental Monitoring Program Summary 21 for 2007 9 Radiological Environmental Monitoring Program 27 Preoperational (Baseline) Summary 10 Results of 2007 Environmental Intercomparison Program 32 with Independent Lab, Analytics, Inc.

11 2007 Environmental Sampling Program Exceptions 34 iii

LIST OF FIGURES FIGURE PAGE 1-1 Control Site Locations (50 mile radius around the 35 Virgil C. Summer Nuclear Station) 1-2 Radiological Monitoring Program Local Indicator Sample 36 Sites (5 mile radius around Virgil C. Summer Nuclear Station) 1-3 Radiological Monitoring Program Local Indicator Sample 37 Sites (1-mile radius around Virgil C. Summer Nuclear Station) 1-4 Radiological Monitoring Program Security Area Ground 38 Water Sites.

1-5 Radiological Monitoring Program Protected Area Ground 39 Water Sites.

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INTRODUCTION Virgil C. Summer Nuclear Station (VCSNS) utilizes a pressurized water reactor rated at 2900 MWt (990 MWe gross). The station is located adjacent to the Monticello Reservoir near Jenkinsville, South Carolina and approximately 26 miles northwest of Columbia. VCSNS achieved initial criticality on October 22, 1982, reached 50% power December 12, 1982 and 100% power June 10, 1983 following steam generator feedwater modifications. Steam generators were replaced in the fall of 1.994. During the ninth refuel the plant wasuprated to 2900 MWt (990 MWe gross). VCSNS is currently operating in the 1 6 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 three points:

the Main Plant Vent, the Reactor Building Purge Exhaust and the Oil Incineration Facility, 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 2007. Data trends, control/indicator and preoperational/operational data intercomparisons and other data interpretations are presented.

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

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

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

The program utilizes the concepts of control/indicator and preoperational

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

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

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

Table 1 - Monitoring Methods for Critical Radiation Exposure Pathways Effluent Release Type 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 and 1-5. Figure 1-1 shows monitoring sites at distances greater than 10 miles from the plant. These locations indicate regional fluctuations in background radiation levels.

In addition to preoperational/operational data intercomparisons, controlAndicator 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 garden monitoring.

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

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

Quality of analytical measurements is demonstrated by participation in a laboratory intercomparison program. Results of the intercomparison program with an outside vendor and VCSNS Count Room were satisfactory in 2007. 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 2007 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 2007 meteorological data. Exposure pathways used in the analysis were those identified during the land use census.

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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 3.23E+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 2.23E+0 and 4.28E+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 2007 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 99.3%. A listing of program exceptions and their respective causes are included in Table 11. Analysis of the impact of these omissions verified that program quality has not been affected.

Corbicula harvest for possible human consumption was observed in Lake Monticello in 2005. Since that time Corbicula analysis has been incorporated in the Supplemental Sampling Program. Samples were collected and analyzed for gamma emitting isotopes. No measurable gamma emitting nuclides were detected above background.

Gross beta activities measured in air particulate samples collected at indicator locations around VCSNS were consistent with preoperational levels and not statistical, different from control locations. The highest site-specific mean activity (2.41E-2 pCi/mi) was measured at indicator location Site 7 (Lab Garden 1.0 mi. E). The results indicate that the operation of VCSNS has not contributed to detectable increases of airborne gross beta activity in the environment.

Gamma spectroscopy measurements of composited air particulate samples and activated charcoal cartridges support the gross beta activity trend. Only natural background activities were detected. The highest minimum detectable activity (MDA) levels for 134Cs, 137Cs and 1311 were 2.09E-3, 2.09E-3 and 2.03E-2 pCi/m 3 , respectively.

The average maximum results support the gaseous effluent release data reported in the 2007 Annual Effluent and Waste Disposal Reports for VCSNS. No measurable iodine or particulate were released. 100% 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 4 (Fairfield Hydro 1.2 mi. WNW), was the indicator location showing the highest mean exposure rate of 1.1 7E+1 gR/hr. This is similar to the 2006 value of 1.22E+1 pR/hr and consistent with the highest mean exposure rate of 1.4E+1 4iR/hr measured during the preoperational period. 98.1% of the required TLDs were collected.

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Gamma spectroscopy measurements of surface water samples did not indicate the presence of activated corrosion or fission products above the respective MDA's for indicator sites. 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 three indicator samples. All three of these samples were collected from site 112 (0.36 mi. SSE onsite adjacent to plant holding ponds). The tritium concentrations at site 112 were 5.45E+2, 5.95E+2, and 9.53E+2 pCi/I. All required indicator/control ground water samples were collected.

Gamma spectroscopy measurements of drinking water samples collected from the Jenkinsville water supply did not indicate the presence of activated corrosion or fission product activity above the respective MDAs. Gamma spectroscopy analysis indicated the presence of 131, slightly above MDA in 1 indicator sample. Site 17 (Columbia Water Works 25.0 mi. SE) had an 1311 concentration of 5.41E-1 pCi/l. The highest MDA for 1311 at all indicator and control sites was 4.20E-1 pCi/l. The highest indicator and control site-specific gross beta activity was measured at Site 28 (Nuclear Training Center 2.6 mi. SSE) at a level of 4.65E+0 pCi/I. 97.2% of indicator/control drinking water samples were collected.

There were no milk samples collected in 2007. Milk sampling is required to be performed at the three highest dose locations within 5 kilometers of the plant or at 5 to 8 kilometers of the plant, if doses are calculated to be greater than 1 mrem per year.

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

Gamma spectroscopy measurement of supplemental grass samples collected indicated 137 Cs in 11 of 12 samples at Site 2 (transmission line 1.1 mi. SW) at concentrations ranging from 2.26E+1 to 2.59E+2 pCi/kg. The maximum preoperational control activity was 3.4E+2 pCi/kg. A review of Site 2 air sample results indicated that no137CS was detected. 97.2% of indicator/control grass samples were collected.

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. All required indicator/control non-leafy (other vegetation) samples were collected.

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Gamma spectroscopy measurements of the fish samples collected at indicator and control sites indicated the presence of 137 Cs in 2 samples. Indicator site 23 (Monticello Res. 0.5 mi. ESE) had a 137Cs concentration of 1.31 E+1 pCi/kg. And control site 22 (Neal Shoals Reservoir, 26.0 mi. NNW) had a 137 CS concentration of 1.57E+1 pCi/kg. These activities are below the preoperational mean of 2.8E+1 pCi/kg and well below the preoperational max of 1.OOE+2 pCi/kg for fish samples. All required indicator/control fish samples were collected.

Gamma spectroscopy measurements of sediment samples indicated the detection of 13 7 Cs in 3 Of 4 indicator samples taken. At Site 21 (Parr Res. 2.7 mi. SSW) at concentrations of 4.52E+1 and 7.26E+1_pCi/kg, and Site 23 (Monticello Res. 0.5 mi. ESE) at a concentration of 8.75E+1 pCi/kg. 13 Cs was detected in 2 of 2 control samples taken at Site 22 (Neal Shoals 26 mi. NNW) at concentrations of 9.15E+0 and 6.14E+1 pCi/kg.

All required indicator/control sediment samples were collected.

Radiation doses to man, corresponding to the concentrations of activity in sediment were not calculated. 137Cs was the only activity identified at concentrations below the preoperational levels.

Table 2 - 2007 Fission and Activated Corrosion Product Activity in Sediment Location Radionuclide Activity (pCi/kg)

Maximum Mean Monticello 13 7 Reservoir CS 8.75E+1 8.75E+1 13 7 Parr Cs 7.26E+1 5.89E+1 Reservoir Neal Shoals 1 3 7 CS 6.14E+1 3.53E+1 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 except for tritium in ground water at site 112 (0.36 mi. SSE, onsite adjacent to plant holding ponds) which was well below the EPA drinking water standard. Drinking water from Columbia Water Works contained 1311 at a concentration of 5.41 E-1 pCi/I; this is below the required LLD for drinking water, and below the concentrations identified on several occasions at our surface water control site upstream of the drinking water intake. 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 maximally 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 DescriptionDistance Direction 2 Sample Type(s) 3 No. DMiles) 1 Borrow Pit 1.2 179.8S DQ 2 Transmission Line 1.1 225.0 SW AP, RI, DQ 3 Firing Range 1.2 270.0 W Do 4 Fairfield Hydro 1.2 289.5 WNW DO 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 Bail Park 2.3 41.6 NE DO 10 Meteorological Tower #2 2.5 25.5 NNE DO 12 Old Hwy 99 4.2 349.4N DQ 13 North Dam 2.9 333.0 NNW DQ 14 Dairy (ShealXp4 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 Club5 16.5 165.0 S DQ,GA 19 Residence/Little Saluda 21.0 224.0 SSW DO 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 Nuclear Training Center (EOF)6 2.6 170.2 SSE DW 29 Trans. Line WSW of VCSNS 1.0 260.6 WSW DQ 30 Oak Tree North of Borrow Pit7 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 DO 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 Behind Jenk. Post Office 3.1 151.0 SSE DQ 37 Residence 4.9 304.8 NW DQ 39 LMWTF 14.0 168.0 SSE DW 8

Site DescriptionDistance Direction 2 Sample Type(s)3 No. DMiles) 41 Below Catwalk at Trestle 3.8 182.0 S DQ 42 Broad River Rd (Residence Peak) 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 DO 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 DO 56 Old Jenkinsville Dinner 2.0 144.0 SE DO 58 Residence 2.5 157.0 SSE DQ 59 Nuclear Training Center (EOF)6 2.6 170.2 SSE DQ, GW 60 Rd 98 near Rd 28 3.5 274.6 W DQ 100 Remediation Well (B-1) 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 (B-7) 80 Ft NE GW 104 Remediation Well (B-9) 175 Ft NE GW 105 Remediation Well (B-12) 100 Ft ESE GW 106 Remediation Well (B-14) 250 Ft SE GW 107 Remediation Well (B-28) 400 Ft SW GW 108 Remediation Well (B-33) 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-1 5) 0.39 330 SSE GW 9

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. Site 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 2 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 Nuclear Training Center which also serves as the Virgil C. Summer Station Emergency Offsite Facility.

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.

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Table 4 - Results of the 2007 Land Use Census Verification No. No.

Sector Nearest Residence Miles Nearest Garden Miles Nearest Cattle Milked Miles Nearest Goat Milked Miles N P. Oliver 3.73 John Robinson 0 3.4 Thomas K. Crumblin Wi/Charles NNE (A) 2.9 Virgil Harrison 3.21 Coleman 0 4.97 Gregrey Guinyard Jr.

NE (A) 1.55 David Stone 2.1 David Stone 0 2.1 ENE Robert Martin 1.53 Essie Mae Glenn 1.68 Robert Martin 0 1.53 E Lynn Mincy 1.2 Lynn Mincy 1.2 ESE Carrie Lee Martin 1.1 SE Mary White 1.44 Mary White 1.44 Sim Robertson 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 G.A. Mayers 0 4.7 SW Marvin Miller 3.3 Marvin Miller 3.3 Shakkori 0 4.7 WSW Ron Hope 2.9 Mary Davis 3 KenNirg Graham 0 4.98 Steve All 4.83 W Jerry Cassado 2.55 Marion Livingston 2.8 Marion Livingston 0 2 W KenNirg Graham 90 5 WNW Randy Wedaman (A) 4.24 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

(*) Unknown 11

Table 5 Critical Receptor Evaluation for 2007 NAME SECTOR MILES PATHWAY X/Q D/Q DOSE*

mRem/y John Robinson N 3.4 B 2.7E-07 7.3E-10 7.32E-02 P. Oliver N 3.73 Res 2.2E-07 5.9E-10 8.18E-03 Thomas K. Crumblin NNE 2.9 Res 4.1E-07 1.3E-09 1.53E-02 Virgil Harrison NNE 3.21' ResGar 3.3E-07 1.OE-09 2.74E-01 Will/Charles Coleman NNE 4.97 B 1.4E-07 3.9E-10 3.91 E-02 Gregrey Guinyard Jr. NE 1.55 Res 1.9E-06 6.3E-09 7.13E-02 David Stone NE 2.1 Res,Gar,B 9.6E-07 3.OE-09 1.12E+00 Robert Martin ENE 1.53 Res,G 2.1E-06 6.8E-09. 1.60E-01 Essie Mae Glenn ENE 1.68 Res,Gar 1.7E-06 5.4E-09 1.47E+00 Garden-7 ** E 1 Res,Gar 4.3E-06 1.6E-08 4.28E+00 Lynn Mincyl E 1.2 Res,Gar 2.8E-06 9.8E-09 2.64E+00 Garden-6 ** ESE 1 Res,Gar 2.3E-06 8.3E-09 2.23E+00 Carrie Lee Martin ESE 1.1 Res 1.9E-06 6.5E-09 7.14E-02 Mary White SE 1.44 ResGar. 6.OE-07 2.8E-09 7.33E-01 Sim Robertson SE 4.7 Res,B 4.9E-08 1.8E-10 1.98E-02 Ronnie Mann SSE 2.39 Res,Gar 1.3E-07 7.6E-10 1.96E-01 Kelly Boulware S 3.56 ResGar 7.8E-08 5.OE-10 1.28E-01 Shirley Counts S 5' Res,Gar,B 3.9E-08 2.4E-10 8.54E-02 Nick Bates SSW 3.11 Res 1.2E-07 8.6E-10 4.73E-03 Nora Wicker SSW 3.77 Res,Gar 7.8E-08 5.5E-10 1.40E-01 G.A. Mayers SSW 4.7 Res,Gar,B 4.9E-08 3.4E-10 3.57E-02 Marvin Miller SW 3.3 ResGar 8.9E-08 8.9E-10 2.23E-01 Shakkori SW 4.7 Res,G 4.2E-08 4.OE-10 .6;47E-03 Ron Hope WSW 2.9 Res 1.OE-07 8.7E-10, 4.02E-03 Mary Davis WSW 3 ResGar 9.3E-08 8.1E-10 2.04E-01 Steve All WSW 4.83 Res,G, M 3.4E-08 2.8E-10 2.52E-01 KenNirg Graham WSW 4.98 B 3.2E-08 2.6E-10 2.84E-02 Jerry Cassado W 2.55 Res 1.1 E-07 6.7E-10 4.28E-03 Marion Livingston W 2 B 1.8E-07 1.2E-09 1.19E-01 Marion Livingston W 2.8 ResGar 8.6E-08 5.4E-10 1.38E-01 Marion Livingston W 2 & 2.8 Res,Gar,B Both Both 2.57E-01 KenNirg Graham W 5 Res,Gar,B,M 2.6E-08 1.5E-10 2.84E-02 Randy Wedaman WNW 4.24 Res 3.9E-08 1.6E-10 1.48E-03 Ronnie Leitzsey WNW 4.15 M, B, G 4.1E-08 1.7E-10 1.69E-01

-Ronnie Leitzsey WNW 4.72 Res,Gar 3.2E-08 1.3E-10 3.45E-02 Ronnie Leitzsey WNW Res,Gar,M,B,G Both Both 2.04E-01 Louise Workman NW 3.9 Res 6.7E-08 2.7E-10 2.54E-03 Frank March NNW 2.9 ResGar,B 2.8E-07 8.8E-10 3.28E-01 ODCM ORGAN DOSE E 1.1 ResGar 3.4E-06 1.2E-08 3.23E+00 Pathway Res = Residence B = Beef G = Goat Gar = Garden M = Milk(Infant)

Footnotes:

1 Maximum exposed individual.

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

X/Q and D/Q were derived from 2007 data

• • ODCM required environmental gardens.

Evaluated conservatively 12

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

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

exclusion boundary as practicable where the highest offsite sector ground level concentrations 2

are anticipated.

B) 1 Indicator sample to be Continuous sampler operation 6 Gross beta following filter taken in the sector beyond with weekly collection. change; Quarterly but as close to the composite (by location) exclusion boundary as for gamma isotopic.

practicable corresponding to the residence having the highest anticipated offsite ground level 2 concentration or dose.

C) 1 Indicator sample to be Continuous sampler operation N/A Gross beta following filter taken at the location of one with weekly collection, change; Quarterly of the dairies being composite (by location) sampled meeting the for gamma isotopic.

criteria of VII(A).294 D) 1 Control sample to be Continuous sampler operation 17 Gross beta following filter taken at a location at least with weekly collection, change; Quarterly 10 air miles from the site composite (by location) and not in the most for gamma isotopic.

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

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

given in 1(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. I 13

Exposure Criteria for Selection of Sampling and Collection Sample Type & Frequency of Sample Sample Number & Location Frequency Location Analysis 1II. 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 exchange 5 , 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 5 with quarterly composite a location which allows for (by location) to be 7 mixing a dilution in the analyzed for tritium ultimate receiving river.

B) 1 Control sample to be Time composite samples6 with 223 Gamma isotopic monthly 5

taken at a location on the collection every month with quarterly composite 7

recevingrive receiving river sufficiently suficietlyanalyzed for tritium (by location) to be .

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

6 C) 1 Indicator sample to be Time composite samples with 23' 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 sampling7 59 Gamma isotopic and unaffected location tritium analyses quarterly 7 .

14

Exposure Criteria for Selection of Sampling and Collection Sample Type & Frequency of Pathway and/or Sample Number & Location Frequency Location Analysis Sample i I______________I ______I ___________

VI. Drinking A) 1 Indicator sample from a Monthly grab sampling5 . 28 Monthly 5 gamma isotopic, 7 Water nearby public ground water gross beta and quarterly supply source. composite for tritium analyses.

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

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

VII. Milk 4 A) Samples from milking Semimonthly when animals To be Gamma isotopic and I-animals in 3 locations are on pasture8' monthly other supplied 131 analysis within 5 km having the times 5 when milk semimonthly 8 when highest dose potential. If animals are animals are on pasture, 5

there are none then 1 found in monthly other times sample from milking accordance animals in each of 3 areas with criteria between 5 to 8 km distance VII.A.

where doses are calculated to be greater than 1 mrem per year.' 0 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 1 semimonthly 8 when and not in the most animals are on pasture, prevalent wind direction2 monthly other times5 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 accordance animals are on pasture with criteria VII.A.

D) 1 Control grass (forage) Monthly when available 5 " 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 Ii Ii _____ _________

VIII. Food A) 2 Samples of broadleaf Monthly when available 5 . 6 Gamma isotopic on edible Products vegetation grown in the 2 7 portion.

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

B) 1 Control sample for the Monthly when available 5 . 18 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_

IX. Fish A) 1 Indicator sample to be Semiannual9 collection of'the 23' Gamma isotopic on edible taken at a location in the following specie types if portions semiannually 9 .

upper reservoir, available: bass; bream, crappie; catfish, carp.

B) 1 Indicator sample to be Semiannualg collection of the 213 Gamma isotopic on edible taken at a location in the following specie types if portions semiannually 9 .

lower reservoir, available: bass; bream, crappie; catfish, carp.

C) 1 Control sample to be Semiannual 9 collection of the 223 Gamma isotopic on edible taken at a location on the following specie types if portions semiannually 9 .

receiving river sufficiently available: bass; bream, far upstream such that no crappie; catfish, carp.

effects of pumped storage operation are anticipated AQUATIC:

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

taken at a location in the upper reservoir.

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

taken on or near the shoreline of the lower reservoir.

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

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

16

FOOTNOTES

1. Reserved for future use.

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 dairying 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. Time composite samples are samples which are collected with equipment capable of collecting an aliquot at time intervals which are short (e.g. hourly) 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 Ty & Frequency of and/or Sample Sample Number & Location 1[ Collection Frequency ( Location j[ 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 operation with weekly 131 weekly.

of S-1(A) above, collection.

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

boundary. each location.

B) 2 stations to be placed Quarterly exchange 7 ; 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.135 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 analysist 18

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

S-VII. Milk 4 A) 1nearest Sample from one of the Biweeklygrab 14 Gamma isotopic and I-affected dairies at sample. 814+ 131 analysis biweekly.

or beyond 5 miles.

B) 1 Control sample to be Biweeklx arab 16 Gamma isotopic and I-taken at the location of a sample. 4+ 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 sample to be taken at the available. 14 Gamma isotopic.

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-IV(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 1 edible portion.

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

Corbicula B) Indicator sample of edible Semiannual 23 Gamma isotopic portions 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 Soil: A) 1 Indicator sample to be Annual grab sample." 98 Gamma isotopic.

S-X. Topsoil taken at the waste oil incinerator.

19

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 2 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.

20

Table 8 - Radiological Environmental Monitoring Program Summary for 2007 Location with Hi hest Annual Mean Number of Medium or Type and Total Lower Limit Indicator Locations Control Locations Nonroutine Pathway Sampled Number of of Detection 2 Meanl3 (#total #) Name Mean 3 (#/total #) R (Unit of Analyses Actual Meanta) (Distance & Direction) (Range) Mean (#total g #) Reported 4 Measurement) Performed' (Max.) (Range) (Range) Measurements Air Particulate Gross Beta 6.30E-3 2.20E-2 (260/260) Site 7 Environmental 2.41 E-2 (52/52) 2.07E-2 (52/52) 0 (pCi/m 3 ) (312) (1.OE-2) (9.54E-3 to 4.20E-2) Lab Garden (1.38E-2 to 3.96E-2) (1.09E-2 to 3.49E-2)

(1.0 mi E)

Gamma Spec 1Cs 2.09E-3 All < LLD All < LLD 0 S(5.OE-2) 2.09E-3 All < LLD All < LLD 0 1 (6.0E-2)

Air Radioiodine I 1 il (312) 2.03E-2 All < LLD All < LLD 0 (pCi/m 3 ) (7.0E-2)

Direct (TLD) 5 Gamma(133) 8.26E+0 (114/114) Site 4, Fairfield Hydro 1.17E+1 (4/4) 8.18E+0 (19/19) 0 (gR/hr) Quarterly N/A (5.21 E+0 to 1.23E+1) (1.2 mi., WNW) (1.08E+1 to 1.23E+1) (5.44+0 to 1.11 E+1)

Gamma(24) 8.73E+0 (24/24) Site 52 Monticello Rt. 1.09E+1 (4/4) N/A 0 Special Interet N/A (5.10OE+0 to 1.18E+1) 11 (3.8 mi., NNE) (1.01 E+1 to 1.18E+1)

Surface Water 4H (35) 5.34E+2 All < LLD All < LLD 0 (pCi/l/ _2._E+3_

Gamma Spec(35)

OfMn 2.20E+0 All < LLD All < LLD 0 (1.5E+1) bdCo 2.37E+O All < LLD All < LLD 0 (1.5E+1) buFe 5.89E+0 All < LLD All < LLD 0 (3.OE+l) All < LLD 0 bUCO 2.66E+0 All < LLD (1.5E+1) All < LLD 0 bt'Zn 4.86E+0 All < LLD (3.OE+1) All < LLD 0 9bZr 4.35E+0 All < LLD (3.OE+1)

• bNb 2.99E+0 All < LLD All < LLD 0 1

(1.5E+1)

,Cs 2.03E+0 All < LLD All < LLD 0 (1.5E+l) 21

Table 8 (cont.) - Radiological Environmental Monitoring Program Summary for 2007 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine4 Pathway Number of of Mean 3 (#Itotal #) Name Mean 3 (#/total #) Mean 3 (#Itotal #) Reported Sampled (Unit of Analyses Detection (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed1 Actual (Max.)

1 Surface Water *'Cs 2.41 E+0 All < LLD All < LLD 0 (Continued) 1 (1.8E+1) 4Ba 1.47E+1 All < LLD All < LLD 0 4

(6.OE+1) 1 01a 6.11 E+0 All < LLD All < LLD 0 (1.5E+1)

Ground Water 4H (80) 5.34E+2 6.98E+2 (3/76) Site #112 NPDES 6.98E+2 (3/4) All < LLD 0 (pCi/I) N/A (5.45E+2 to 9.53E+2) Well (GW-9) (5.45E+2 to 9.53E+2)

(0.36mi, SSE)

Gamma Spec 80)

_____ ____ I __ _

Mn 4.98E+0 1.5E+1 _ _

All

<_ LLD All

< LLD 0 _ _

btCo 4.93E+0 All < LLD All < LLD 0 (1.5E+I)

WFe 9.36E+0 All < LLD All < LLD 0 (3.OE+l) bOCo 5.32E+0 All < LLD All < LLD 0 (1.5E+1) bbZn 1.06E+1 All < LLD All < LLD 0 (3.OE+1)

YbZr 8.14E+0 All < LLD All < LLD 0 13.0E+1) 9bNb 7.50E+0 All < LLD All < LLD 0 (1.5E+l)

• U4Cs 5.09E+0 All < LLD All,< LLD 0 (1.5E+1)

• Cs 5.05E+0 All < LLD All < LLD 0 (1.8E+1) 14uBa 1.84E+1 All < LLD All < LLD 0 (6.OE+1) l1uLa 6.65E+0 All < LLD All < LLD 0 (1.5E+1) I I I I 22

Table 8 (Cont.) - Radiological Environmental Monitoring Program Summary for 2007 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations 3 Control3 Locations Nonroutine4 Number of of Mean 3 (#/total #) Name Mean (#Itotal #) Mean (#/total #) Reported Pathway Sampled (Unit of Analyses Detection 2 (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed' Actual (Max.)

Drinking Water6 Gross Beta (35) 1.41E+0 2.35E+0 (20/24) Site 28, NTC 2.57E+0 (10/12) 2.12E+0 (11/12) 0 (pCi/I) (4.OOE+0) (1.47E+0 to 4.65E+0) (2.6 mi, 170.2 SSE) (1.61 E+0 to 4.65E+0) (1.60E+0 to 2.67E+0)

• H (35) 5.13E+2 All < LLD All < LLD 0 (2.OE+3)

Gamma Spec 170) 5Mn 3.93E+ 0 All < LLD All < LLD 0 (1.5E+ 1) b6Co 3.84E+ 0 All < LLD All < LLD O (1.5E+ 1)

• Fe 7.68E+ 0 All < LLD All < LLD 0 (3.OE+ 1)

OCo 4.04E+ 0 All < LLD All < LLD 0 (1.5E+ 1) 5Zn 7.70E+0 All < LLD. All < LLD 0 (3.0E+ 1)

UIZr 5.94E+ 0 All < LLD All < LLD 0 (3.OE+ 1) v*Nb 5.19E& 0 All < LLD All < LLD 0

.11 (1.5E 1) 4.03E-1

+

5.41E-1 (1/24) Site 17, Columbia 5.41 E-1 (1/12) All < LLD 0 (1.OE+ 0) (5.41 E-1 to 5.41 E-1) Water Works (5.41 E-1 to 5.41 E-1)

______________ __ ___ _______ _____ 25 mi,_SE)_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1 5Cs 3.61E+ 0 All < LLD All < LLD 0 (1.5E + 1)

Cs 3.78E+ 0 All < LLD All < LLD 0 4

(1.8E + 1) l UBa 1.48E+ 1 All < LLD All < LLD 0 O6.0E+ 1) l'uLa 5.50E+ 0 All < LLD All < LLD 0 (1.5E+ 1) 23

Table 8 (Cont.)- Radiological Environmental Monitoring Program Summary for 2007 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control3 Locations Nonroutine4 Pathway Number of of 2 Mean 3 (#/total #) Name Mean 3 (#/total #) Mean (#Itotal #) Reported Sampled (Unit of Analyses Detection (Range) (Distance & Direction) (Range) (Range) Measurements 1

Measurement) Performed Actual (Max.)

Broadleaf Gamma Spec Vegetation (36)

(pCi/kg wet) lii1 2.24E+ 1 All < LLD All < LLD 0

( OE+ 1)

Cs 2.10E+ 1 All < LLD All < LLD 0 (6.OE+ 1) ljCs 2.38E+ 1 All < LLD All < LLD 0 (8.OE+ 1)

Fish 7 Gamma Spec (pCi/kg wet) _18_

lMn 1.52E+ 1 All < LLD All < LLD 0 (1.3E+ 2)

WSCo 1.88E + 1 All < LLD All < LLD 0 (1.3E+ 2) buFe 4.24E+ 1 All < LLD All < LLD 0 (2.6E+ 2) bUCo 2.09E+1 All < LLD All < LLD 0 (1.3E+2) bZn 4.31 E+1 All < LLD All < LLD 0 (2.6E+2) 14Cs 1.50E+1 All < LLD All < LLD 0 (1.3E+2) I I 13(Cs 1.85E+1 1.31 E+1 (1/12) Site 23 Monticello 1.31 E+1 (1/6) 1.57E+1 (1/6) 0 (1.5E+2) 1 .85E_______ (1.31E+1

_(0.5 to 1.31E+1)

____ Reservoir (1.31E+1 to 1.31E+1) (1.57E+1 to 1.57E+1) m i ES E) I I I 24

I , I Table 8 (Cont.)- Radiological Environmental Monitoring Program Summary for 2007 Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine Pathway Number of of 2 Mean 3 (#/total #) Name 3 Mean (#/total #) Mean 3 (#/total #) Reported 4 Sampled (Unit of Analyses Detection 2 (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed' Actual (Max.)

Sediment Gamma Spec (6)

(pCi/kg) 8 5Mn 2.10E+1 All < LLD All < LLD 0

___ _ _N/A

'Co 1.81 E+1 All < LLD Ail < LLD 0 N/A

'Co 2.76E+1 All < LLD All < LLD 0 N/A

'4Cs 1.69E+1 All < LLD All < LLD 0 (1.5E+2)

Cs 1.55E+1 6.84E+1 (3/4) Site 23 Monticello 8.75E+1 (1/2) 3.53E+1 (2/2) 0 (1.8E+2) (4.52E+1 to 8.75E+1) Reservoir (8.75E+1 to 8.75E+1) (9.15E+0 to 6.14E+1)

(0.5 mi ESE) 25

Table 8 ( cont ) - Radiological Environmental Monitoring Program Summary for 2007 Footnotes

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

2. Values given are maximum MDA values for indicator locations calculated from the program data analyses with 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 gR/hr).

6. Elevated levels of 2 14 Pb and 2 14 Bi were observed in Jenkinsville drinking water samples.

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

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

8. Elevated levels of 2 14 Pb and 2 14 Bi plus other 22 6 Ra daughter products and 22 8Ac 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. Reserved for future use.

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

11. Reserved for future use.

All measurements had positive results, no MDA values calculated.

26

Table 9- Radiological Environmental Program Preoperational (Baseline) Summary Location with Hilhest Annual Mean Medium or Pathway Type and Total Lower Limit of All Indicator Control Locations Number of 2

Sampled (Unit of Number of Detection' Actual Locations Mean 2 Name Mean (# /tota Nonroutine Analyses (oa l (#ctions Meang (Distance & Direction) (Range) Mean e)3 Measurement and Reporting Period) Performed (Max.) (#Itotal #) (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) (1.0Eo2) (1.3E-2 to 5.5E-1) (2.9 mi NNW) (2.1E-2 to 5.5E-1) (7.9E-3 to 6.1E-1)

(1981-1982) 2.7E-2 (456/462)4 Site 8, Mon. Res. S of 3.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 "Cs 3.OE-3 All < LLD All < LLD 0 (1.OE-2) 3.1 E-3 3.2E-3 (22/241) Site 10, Met Tower 3.8E-3 (2/22) 4.2E-3 (4/66) 0 (1.0E-2) (1.5E-3 to 5.2E-3) (2.4 mi NNE) (2.5E-3 to 5.2E-3) (3.2E-3 to 5.6E-3)

Air Radioiodine "1*1(290) 3.6E-2 All < LLD All < LLD 0 (pCi/m 3) (1982) (7.OE-2)

Direct (TLD)5 Gamma (1220) 0.5 9.9 (915/915) Site 13, North Dam 13.1 (61/61) 9.7 (305/305) 0 (pR/hr) Monthly N/A (6.7 to 14.7) (2.9 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 (pCi/I) 3H (43) 1.1E+3 1.4E+3 (18/29) Site 17, Columbia 1.6E+3 (2/7) 1,2E+3 (6/14)

(1981-1982) (2.OE+3) (1.1 E+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 Q40)

Mn 2.7E-1 All < LLD All < LLD 0 (1.5E+I1 6Co 2.9E&1 All < LLD All < LLD 0 (1.5E+1) b'Fe 6.OE+0 All < LLD All < LLD 0

_(3.OE+1)

WCo 2.4E-1 All < LLD All < LLD 0 (1.5E+1)

`Zn 7.9E-1 All < LLD All < LLD 0 (3.OE+1)

`Zr 5.2E-1 All < LLD All < LLD 0 (1.5E+1) 5Nb 3.3E-1 All < LLD All < LLD 0 (1.5E+1)

Cs 3.OE-1 All < LLD All < LLD 0 (1.5E+1) I I_ II _L__ _I 27

Location with Hi~lhest Annual Mean Medium or Pathway Type and Total Lower Limit of All Indicator 2 Control Locations Number of 2 2 Sampled (Unit of n

Mesrmn Number nlss of Detection' Actual Locations Mean2 (DistanceName

& Direction) (#/total #)

Mean(Range) Men(toa otal #)) Nonroutine Reported33 Measurement and Analyses ) Rage (ane Reportedta Reporting Period) Performed (Max.) (#/total #) (Range) (Range) Measurements 5Cs 2.2E-1 All < LLD All < LLD 0 14_______ ______ (1.8E+1) All < LLD_0 uBa 2.2E+0 All < LLD All<LLD 0 14 _ (6.OE+1) All <_LLD_0 4

u uLa 5.5E-1 All < LLD All<LLD 0 (1982 only) (1.5E+1)

Ground Water ( 9.02+2 1.5E+3(16/16) Site 26, Onsite Well 1.6E+3 (8/8) 1.3E+3 (13113)

(1981-1982) H(2(2.0E+3) (9.5E+2 to 2.3E+3) (265 ft, W) (9.5E+2 to 2.3E+3) (1.0E+3 to 1.9E+3)

Gamma Spec

/32) 5Mn 3.7E+0 All < LLD All < LLD 0 (1.5E+I) bbco 3.8E+0 All < LLD All < LLD 0 (1.5E+1) bYFe 7.8E+0 All < LLD Ail < LLD 0 (3.0E+1) bUCo 3.8E+0 All < LLD All < LLD 0 (1.5E+I) 652n 8.1E+0 All < LLD All < LLD 0 (3.0E+1) 9*Zr 6.8E+0 All < LLD All < LLD 0 (1.5E+1) vbNb 4.6E+0 All < LLD All < LLD 0 (1.5E+1)

F*Cs 3.7E+0 All < LLD All < LLD 0 (1.5E + 1) 1Cs 3.8E+0 All < LLD All < LLD 0 (1.8E + 1) 4 l uBa 1.9E+1 All < LLD All < LLD 0 (6.0E+1) 14uLa 5.0E0 All < LLD All < LLD 0 (1982 only) (1.5E+1)

Drinking Water 6 Gross Beta' (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 (1.0E+3) (6,8E+2 to 9.8E+2) (2.0 mi SE)7 ,7.0E+2 to 9.8E+2)

Gamma Spec (44)

Mn 3.0E-1 All < LLD 0 (1.5E+1) bdCo 2.7E-1 All < LLD 0 (1.5E+1) 28

Location with Hi hest Annual Mean Medium or Pathway Type and Total Lower Limit of All Indicator Control Locations Number of Sampled (Unit of Number of 2 Name Mean 2 (#total #) I Nonroutine3 Measurement and Analyses Mean Mean (total #)rted Reporting and Performed (Max.) (#/total #) (Range) (Distance & Direction) (Range) (Range) Measurements "Fe 9.6E0 All < LLD 0 (3.OE+l) buCo 2.6E-1 All < LLD 0 (1.5E+1)

Win 3.4E-1 All < LLD 0 (3.OE+l)

YbZr 4.8E-1 All < LLD 0 (1.5E+I) liuI 3.4E-4 All < LLD 0 (1.5E+1) 9bNb 7.4E-1 All < LLD 0 1

(1.OE+0) jCs 2.2E-1 All < LLD 0

_1.0E+I) 13/Cs 2.4E-1 All < LLD 0 (1.8E+l) 14UBa 2.5E0 All < LLD 0 (6.OE+1) 14uLa 4.4E-1 All < LLD 0 (1982 only) (1.5E+1) I Milk Gamma Spec (pCi/I) (94)

(1981-1982) __ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _

1(9 18 6.3E-1 All < LLD All < LLD .0.

_1.OE+0) 1Cs 3.3E+0 All < LLD All < LLD 0 (1.5E+1) li/Cs 4.6E0 4.1 E+O (8/47) Site 14, Dairy 4.1 E+O (8/47) 5.7E+0 (37/47) 0 14 (1.5E+1) (2.8E+O to 6.1E+0) (5.1 mi., W) (2.8E+O to 6.1E+0) (3.7E+0 to 9.2E+0) 4 v

UBa 1.1E+1 All < LLD All < LLD 0 (1.5E + 1) l4 uLa 4.4E+0 All < LLD All <ILLD 0 (1.5E+1)

Grass (pCi/kg wet) Gamma Spec (1981-1982) (82I) 6.7E+1 All < LLD All < LLD 0 (6.OE+l) 1,Cs 2.7E+1 All < LLD All < LLD 0 (8.OE+1) 1Cs 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) 29

1{ 1,) 1 Location with Higghest Annual Mean Medium or Pathway Type and Total Lower Limit of All Indicator Number of Sampled (Unit of Number of MeasurementctuaandcatialysesnDetection' Actual Locations Mean 2 Name Mean 2 (#Itotal #) Control#Locations Mean 2 (#Itotal #) Nonroutine Rpotd Measurement and Analyses (Max.) (#/total #) (Range) (Distance & Direction) (Range) (Range) Reparted3 Reportingl Period) Performed Measurements Broadleaf Gamma Spec (10)

Vegetation (pCi/kg wet)

(1980-1982) 1.1l 3.7E+1 All < LLD 0 (6.0E+1) 14Cs 1.9E+1 All < LLD 0 (8.OE+1) 1J(Cs 2.1E+1 3.1E+1 (2/7) Site 2, Trans. Line 3.6E+1 (1/1) All < LLD 0 (8.0E+1) (1.8E+1 to 3.6E+1) (1.2 mi SW) (Single Value)

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

(1980-1982) 1,Cs 8.4E+0 All < LLD All < LLD 0 (8.0E+1) 1J[Cs 1.0E+1 All < LLD All < LLD 0 (8.OE+1)

Fish (pCi/kg wet) Gamma Spec (1980-1982) Q2)

Cs 1.4E+1 All < LLD All < LLD 0 (1.3E+2) ltCs 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) 0I.0E+1 to 7.9E+1)

• Co 2.6E+1 All < LLD All < LLD 0 (1.3E+2) 5Mn 1.8E+1 All < LLD All < LLD 0 (1.3E+2) 59Fe 9.0E+1 All < LLD All < LLD 0 (2.6E+2) bbZn 4.1E+1 All < LLD All < LLD 0 (2.6E+2) 60Co 1.8E+1 All < LLD All < LLD 0 (1.3E+2)

Sediment (pCi/kg) Gamma Spec (24)

/1980-1982 _ _ _ _ _ _ _ ________ _________ _________ ______

( 8Cs 2.3E+1 All < LLD All < LLD 0 (1.5E+2)

]JCs 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)

(2.7 mi, SSW) 30

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 !R/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.

31

Table 10 - Results of 2007 Environmental Inter-comparison Program with Independent Lab, Analytics, Inc.

Comparison Study Vendor Lab Env Lab (Measurement Unit) Results Results Gamma Isotopic Liquid 9/19 1311 80 91 Yes 14 1 4 Liter Ce 182 212 Yes (pCi/I) 51Cr 249 295 Yes 134CS 127 136 Yes 1370S 112 137 Yes 58Co 98 111 54 Mn Yes 144 172 Yes 59 Fe 95 109 Yes 65 Zn 174 193 Yes 60Co 127 142 Yes Gamma Filter 9/25 141Ce 192 182 Yes (pCi) 51Cr 263 281 Yes 1340S 134. 107 Yes 1370S 119 125 Yes 58 Co 104 104 Yes 54 Mn 152 167 Yes 59 Fe 101 125 Yes 65 Zn 184 222 Yes 60 Co 135 135 Yes Alpha/Beta Water 4/19 Alpha 112 107 Yes (pCi/I) Beta 100 131 Yes Gamma Isotopic 4/11 141Ce 3.13E-1 3.13E-1 Yes Pulverized 51Cr 2.58E-1 2.16E-1 Yes Soil 134cS 1.18E-1 1.09E-1 Yes (pCi/g) 1370s 3.45E-1 3.86E-1 Yes 58Co 1.04E-1 1.15E-1 Yes 54 Mn 1.92E-1 1.83E-1 Yes 59 Fe 1.11E-1 1.42E-1 Yes 65 Zn 1.05E+0 1.12E+0 Yes 60 Co 1.60E-1 1.59E-1 Yes 1-131 Solid 4/11 11- 99 122 Yes (pCi) 32

Comparison Study Date Nuclides Vendor Lab Env Lab Agreement (Measurement Unit) Results Results Tritium 4/23 3H 5010 5140 Yes (pCi/I)

Gross Beta Filter 9/24 N/A 88 79 Yes (pCi)

Charcoal Cartridge 9/19 1311 70 76 Yes (pCi) 33

Table 11 - 2007 Environmental Sampling Program Exceptions Sample Month Media Location (Week No.) Cause for Exception Direct Site 47 Jul (30) TLD missing Radiation Site 9 Oct (41) TLD missing Site 20 Oct (41) TLD missing Drinking Site 17 Jul (32) Breaker trip caused by storm Water Surface Site 21 Feb (8) Power failure during modification to Parr Water Hydro Results included in Table 8 due to low levels of 1-131 identified.

34