Text

Annual Radiological Environmental Operating Report
	ML25118A115
Person / Time
Site:	Summer
Issue date:	04/28/2025
From:	Denise Edwards; Dominion Energy South Carolina
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	25-125
	Download: ML25118A115 (1)
	v • d • e

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPERATING PERIOD JANUARY 1, 2024 - DECEMBER 31, 2024

Page l i TABLE OF CONTENTS LIST OF TABLES - APPENDIX A....................................................................................................................................... II LIST OF FIGURES - APPENDIX B..................................................................................................................................... III EXECUTIVE

SUMMARY

........................................................................................... 1 INTRODUCTION........................................................................................................ 2 DESCRIPTION OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM................................................................................................................. 3 TABLE 1 - MONITORING METHODS FOR CRITICAL RADIATION EXPOSURE PATHWAYS.............................................................................. 4 MONITORING RESULTS AND DISCUSSION...................................................... 5 LAND USE CENSUS................................................................................................ 8 CONCLUSION........................................................................................................... 8

Page l ii LIST OF TABLES - Appendix A Table TITLE 2

ODCM Required Sampling Site Locations 3

Supplemental Sampling Site Locations 4

Radiological Environmental Monitoring Program Specifications 5

Supplemental Radiological Environmental Monitoring 6

Radiological Environmental Monitoring Program Results Summary 7

Radiological Environmental Monitoring Program Pre-operational (Baseline) Summary 8

Environmental Inter-Comparison Program Results 9

Environmental Sampling Program Deviations 10 Land Use Census Results

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

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

Page l 1 EXECUTIVE

SUMMARY

This document is a detailed report of the V.C. Summer Nuclear Station (VCSNS) Unit 1 Radiological Environmental Monitoring Program (REMP) and the program results for the period of January 1st through December 31st of 2024. It is submitted in accordance with Technical Specification 6.9.1.6 and meeting the objectives outlined in (1) the Offsite Dose Calculation Manual (ODCM) and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

Included in this report are a summary of the scheduled sampling program, descriptions of sampling locations, types of analysis performed, tabulated results of those analyses, and interpretations of the results for the reporting period. Comparisons of results to pre-operational environmental data, operational control data, and historical trend data are used to assess the impacts of plant operation on the environment. Also included are the results of the land use census, a summary of the dose evaluation for potential exposure pathways, quality assurance data for analytical processes, and deviations from the sampling schedule.

Sampling activities were conducted as prescribed by the ODCM for VCSNS and applicable Health Physics procedures. Regulatory analyses were performed and detection limits met for required samples with deviations noted. Samples were collected comprising one thousand and eighty-eight analyses (1,088) performed to compile the data for the 2024 Environmental Report. Additional supplemental samples comprising two hundred ninety-five (295) analyses were performed for additional information. Based on the results from the annual land use census, the current sampling sites for V.C. Summer Nuclear Station are sufficient.

Radionuclides observed in the environment in 2024 from V.C. Summer effluent releases were within the range of concentrations observed in the past. Radiation dose calculated from sample results is less than observed with normal fluctuation in natural background. It is therefore concluded that VCSNS operations have no significant radiological impact on the health and safety of the public or the environment.

Page l 2 INTRODUCTION Virgil C. Summer Nuclear Station (VCSNS) operates a single unit 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 feed water modifications. VCSNS is currently operating in the 29th 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 principal area within a 10 mile radius of the plant. This area is mainly forest with 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 activities are the predominant concern; however, these activities make up less than 50%

of the land area. Industrial activity is concentrated around Columbia and is generally greater than 20 miles from the VCSNS.

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

In 2012, construction began on the Independent Spent Fuel Storage Installation (ISFSI) and concluded in January 2016. The first dry cask storage campaign began March 26, 2016, and finished in the first week of May 2016. Four casks were loaded during this evolution. Campaigns in the second quarter of 2019 and first quarter of 2022 have added eight additional casks for a current total of twelve casks. Area dosimetry monitoring has been established to trend and evaluate changes in conditions around the cask storage area.

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 2024. Data trends, control/indicator and pre-operational/operational data, inter-comparisons, and other data interpretations are presented.

Page l 3 DESCRIPTION OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program is carried out in its entirety by Dominion Energy South Carolina. The program has been designed to meet the following general commitments:

1. To analyze selected samples in 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 data trending and data inter-comparisons to evaluate the adequacy of radioactivity source control and to assess environmental radioactivity levels and subsequent radiation dose to man. Since background radiation levels vary across the monitoring area and even across time at a given location, both pre-operational/operational and control/indicator comparisons are utilized. This serves to assess the probability that any observed measurement of radioactivity concentration is due regional fluctuation rather than plant operation.

The presence of fission product activity attributed to residual fallout from atmospheric weapons testing and the Chernobyl accident were detected in environmental sample media during the pre-operational phase of VCSNS and continue to be detected, primarily in grass and sediment media. Comparisons to the pre-operational data provides a means to distinguish any activity related to VCSNS operation.

Sample location, 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.

The required Lower Limits of Detection (LLDs) are verified to have been met by calculating Minimum Detectable Activity (MDA) for each sample based on actual counting parameters relevant to each sample.

In all cases the achieved MDA was lower than the required LLD. Effluent dispersion characteristics, demography, hydrology, and land use have been considered in selection of environmental sampling locations. These elements were used to establish both the pre-operational and operational phases of the Radiological Environmental Monitoring Program. Sample media of the program were selected to monitor the impact of both gaseous and liquid effluents released from VCSNS.

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

Page l 4 Table 1 - Monitoring Methods for Critical Radiation Exposure Pathways Effluent Release Type Exposure Pathway Monitoring Media Gaseous Immersion Dose and other External Dose Thermoluminescent Dosimetry (TLD) Area Monitoring, Air Sampling, Vegetation (Ingestion)

Vegetation and Food Crop Sampling, Milk (Ingestion)

Milk Sampling, Grass (Forage) Sampling Liquid Fish (Ingestion)

Fish Sampling Water & Shoreline Exposure (Ingestion and Immersion)

Surface Water Sampling, Ground Water Sampling, Shoreline and Bottom Sediment

Sampling, Drinking Water (Ingestion)

Drinking Water Sampling Monitoring sites indicative of plant operation are generally located within a 5 mile radius of the plant. Table 2 provides a list of ODCM required sampling locations. Table 3 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.

Environmental data is gathered through various sampling media and analysis measurements. Some sampling sites listed in the tables and figures serve as a combination site for multiple sample types. The regulatory program, as prescribed by the ODCM, is outlined in Table 5, showing all required sample collections and analyses to be performed. Supplemental samples are collected and analyzed in accordance with VCSNS site procedures in addition to the required program as deemed beneficial for monitoring specific sites of interest or to aid in evaluation of regulatory program results. These samples and analyses are outlined in Table 6. Tables 5 and 6 also include designations for which sites are used as indicator data versus control data.

Air monitoring locations provide continuous sampling for air contaminants. At these locations, airborne plant effluents are monitored for gamma immersion dose (noble gases) and particulate radioactive material.

These samples are collected and analyzed weekly.

Area monitoring for direct gamma dose is performed using thermoluminescent dosimeters (TLDs). TLDs are changed out quarterly and are processed by a NVLAP accredited vendor. Vendor results are then

Page l 5 assessed by VCSNS staff. Prior to 2024, TLDs were processed by Mirion Technologies. Beginning with the first quarter of 2024, TLD processing was transferred to Radiation Detection Company (RDC).

Two garden locations (Sites 6 and 7) are sampled for broadleaf vegetation for the purpose of monitoring gaseous effluent deposition (ingestion pathway) in the two sectors having the highest deposition coefficients (D/Q) with real potential for exposure. Deposition coefficients are evaluated annually during the Land Use Census using real meteorological data to verify current sampling locations are appropriate.

Liquid effluents are monitored using surface water, groundwater, drinking water, fish, and bottom sediment media. Surface water, fish, and sediment are sampled at the two most probable affected bodies of water around the plant, Parr Reservoir and Monticello Reservoir. Groundwater wells are installed within the plant boundary in strategic locations based on the sites hydrology to monitor potentially affected groundwater supplies. Local and downstream drinking water supplies are also monitored. Control locations for liquid effluent comparisons include Neal Shoals, upstream on the Broad River, and multiple water supplies outside of VCSNS influence.

Quality of analytical measurements is demonstrated by participation in a laboratory inter-comparison program. Results of the inter-comparison program with an outside vendor and VCSNS Count Room were satisfactory in 2024. Results are summarized in Table 9. 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.

MONITORING RESULTS AND DISCUSSION The results of the Radiological Environmental Monitoring Program for 2024 are summarized in Table 6. For comparison, pre-operational data are summarized in Table 7. The Radiological Environmental Monitoring Program attained a program compliance rate of approximately 98.6%. A listing of program deviations and their respective causes are included in Table 9. Analysis of the impact of these omissions verified that program quality has not been affected. In all analyses performed, the observed MDAs were below the required LLD values, meeting all analytical requirements for detection capability.

Air Sampling The air sample collection rate for indicator and control samples was 98.4%. Gross beta activities measured in air particulate samples collected at indicator locations around VCSNS were consistent with pre-operational levels and not statistically significant from control locations. The highest site-specific mean activity of 2.21E-2 pCi/m3 was measured at supplemental indicator location, Site 8. This value is within the range of current and pre-operational control data. 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 results indicate that the operation of VCSNS has not contributed to detectable increases of airborne gross activity in the environment.

Page l 6 Direct Gamma The TLD sample collection rate for all indicator and control locations was 98.1%. Environmental dosimetry measurements did not indicate any significant increase from pre-operational measurements or previous historic average. Monitoring location Site 55 (St. Barnabas Church 2.8 miles E) was the indicator location showing the highest mean exposure rate of 1.393E+1 µR/hr. This value is consistent with the highest mean exposure rate of 1.40E+1 µR/hr measured during the pre-operational period. The annual average background for direct exposure as determined from control locations is 81.1 mrem/year. The annual average exposure for all indicator sites is 77.8 mrem/yr.

Independent Spent Fuel Storage Installation (ISFSI)

The impact of Independent Spent Fuel Storage Installation (ISFSI) operation, located within the VCSNS Protected Area, which began cask storage on March 26, 2016, was assessed using six TLD locations monitoring the perimeter of the ISFSI site. The TLD locations were monitored for three quarters prior to fuel storage and continued to be monitored through 2024 during which fuel storage casks were stored.

Analysis of monitoring results shows a statistically significant increase in ISFSI perimeter dose as a result of fuel storage. The monitoring location with the highest increase in exposure rate compared to pre-load data was the Southwest ISFSI Boundary with an annual average that is 10.4 mrem per standard quarter greater than the pre-fuel load average. Although the applicable limit for a member of the public applies to a real individual, a conservative analysis was used to demonstrate compliance with 40CFR190 and 10CFR72.104 by assuming an individual is located at the perimeter of the ISFSI Protected Area for 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> per year. In this case, the hypothetical individual would have received 9.5 mrem. This level of exposure would be well under the 40CFR190 limit of 25 mrem.

Surface Water The sample collection rate for all indicator and control surface water samples was 94.4%. Gamma spectroscopy measurements of surface water samples did not indicate the presence of activated corrosion or fission products for indicator sites. Tritium analysis identified 498 pCi/L in the fourth quarter composite sample for Site 23, Discharge Canal Monticello Reservoir. The activity aligns with data observed from supplemental Site 77, Combined Waste Water Discharge, throughout the fourth quarter which showed tritium levels ranging between 410 and 1170 pCi/L and is located upstream of Site 23. These values are all within or below the range of tritium levels observed in the pre-operational data; therefore, it is concluded that these results do not an indicate a change in environmental levels related to plant operations.

Ground Water Sample collection rate for ODCM indicator and control ground water samples was 100%. Gamma spectroscopy measurements of both ODCM required and supplemental ground water samples did not indicate the presence of activated corrosion or fission products. Tritium was detected within the site boundary at Site 112 (NPDES Well GW-09), in two of four quarterly samples at concentrations of 7.64E+2 pCi/L and 8.59E+2 pCi/L. Tritium was also detected within the site boundary at Site 123 (NPDES Well GW-

16) in three of four quarterly samples at concentrations of 1.07E+3 pCi/L, 1.51E+3 pCi/L, and 1.80E+3 pCi/L. GW-09 is a required monitoring well for the Waste Treatment Facility Settling Ponds. GW-16 is a

Page l 7 supplemental monitoring site also used to monitor around the Waste Treatment system. Groundwater wells at VCSNS are not used for drinking water, however, these values are significantly lower than 2.00E+4 pCi/L drinking water standard. These values are consistent with pre-operational data and historical trends; therefore, no changes in plant impact were identified.

Drinking Water The sample collection rate for all indicator and control drinking water samples was 100%. Gamma and tritium analyses for all ODCM and supplemental samples did not indicate the presence of activated corrosion or fission product activity. Gross beta results for indicator sites ranged between 289 and 485 pCi/L. Control location results ranged between 267 and 305 pCi/L. Pre-operational gross beta data is not available for drinking water; however, historical trends of control data are consistent with the levels observed in the indicator locations. Therefore, no plant related radioactivity was identified.

Milk No milk samples were collected in 2024. Milk sampling is required to be performed at the three highest dose locations within 5 kilometers of the plant or at 5 to 8 kilometers of the plant if doses are calculated to be greater than 1 mrem/year. Presently, there are no locations meeting these criteria for indicator dairies.

The closest dairy is approximately 7 kilometers from the plant (see Table 2). 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.

Broadleaf and Garden Products The sample collection rate for broadleaf vegetation was 100%. Gamma spectroscopy measurements of the broadleaf samples did not indicate the presence of activated corrosion or fission products.

Supplemental garden products for non-leafy vegetation included fruit and grain samples. Gamma spectroscopy measurements did not indicate the presence of activated corrosion or fission products.

Grass The sample collection rate for indicator and control supplemental grass was 100%. Gamma spectroscopy measurement of supplemental grass samples collected indicated 137Cs in 2 of 12 samples at Site 2 at concentrations of 3.67E+1 pCi/kg and 3.49E+1 pCi/kg. These results are within the lower range of pre-operational data and, therefore, are not contributed to plant operation.

Soil and Sediment The sample collection rate for indicator and control sediment samples was 100%. Gamma spectroscopy measurements of sediment samples indicated the presence of 137Cs in 2 of 4 indicator samples and in 1 of 2 control samples. Comparison of indicator to control and to pre-operational data did not indicate a change in activity levels. Supplemental sites 72 and 73 also indicated 137Cs at concentrations consistent with these results.

Page l 8 Fish and Corbicula The sample collection rate for fish sampling was 100%. Gamma spectroscopy measurements of fish samples collected did not indicate the presence of activated corrosion or fission products.

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

LAND USE CENSUS Annually a land use census is performed within a 5 mile radius of VCSNS to verify the appropriate siting of sample locations. In addition, the location of the maximum exposed individual (MEI) is identified to ensure the appropriate location is used for calculation of offsite dose impact from VCSNS gaseous effluents. The results of the land use census performed in 2024 are included in Table 10. Identification of the highest offsite dose locations was performed by calculating a hypothetical dose based on source term from the Operating License Environmental Report and 2024 meteorological data. Exposure pathways modeled in the analysis were those identified during the land use census.

The location and pathway presently used in the ODCM for offsite organ dose calculations (E 1.1 miles -

residence/garden) was found to have the highest calculated dose. In addition, the ODCM required environmental gardens (ESE 1.0 and E 1.0 miles) were found to have calculated doses higher than any real receptor. There were no milking animals or dairy activity found within 5 kilometers of VCSNS.

Therefore, changes to the ODCM gaseous effluent calculations or garden sample locations are not indicated.

CONCLUSION The 2024 REMP sampling results have undergone comparative analysis with pre-operational data, control data, and historical trends. In all cases where activity was detected above the MDA, concentrations were within the ranges of either pre-operational or control trends. It has, therefore, been determined that VCSNS operations have not resulted in observable effects on the environment or the general public. These results of the REMP substantiate the continued adequacy of source control at VCSNS and conformance of station operation to 10CFR50, Appendix I design objectives.

Appendix A: Data Tables A - 1 Table 2 - ODCM Sampling Site Locations Site No.

Description Distance1 (Miles)

Direction2 Sample Type(s)3 1

Borrow Pit 1.2 179.8 S DQ 2

Transmission Line 1.2 225.0 SW AP, 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, DQ, GW 7

Environmental Lab Garden 1.0 97.8 E AP, RI, DQ 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 16 Parr Pasture 28.0 278.6W DQ 16 Parr Dairy4 20.0 W

MK, GR 17 Columbia Water Works 25.0 144.0 SE AP, RI, DQ, DW 18 Pine Island Club 16.5 165.0 S DQ 19 Residence/Little Saluda 21.0 224.0 SSW DQ 20 Residence/Whitmire 22.0 309.5 NW DQ 21 Parr Reservoir 2.7 199.5 SSW SW, FH, BS 22 Neal Shoals 26.0 343.1 NNW SW, FH, BS 23 Discharge Canal (Monticello Reservoir) 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 Jenkinsville Post Office 2.8 170.2 SE DW 29 Trans. Line WSW of VCSNS 1.0 260.6 WSW DQ 30 Borrow Pit5 1.0 / 0.5 196.2 SSW AP, RI, DQ 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 Glenns Bridge Road 4.6 132.0 SE DQ

Appendix A: Data Tables A - 2 Table 2 - ODCM Sampling Site Locations Site No.

Description Distance1 (Miles)

Direction2 Sample Type(s)3 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 Facility6 11.9 157.0 SSE GR 41 Peak 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 Cannons Creek 2.8 256.6 WSW DQ 45 Rd 33 at Pomaria 5.8 253.2 WSW DQ 46 Rd 28 at Hellers 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 2.6 170.2 SSE DQ, GW 60 Rd 98 near Rd 28 3.5 274.6 W DQ 78 ISFSI - North 0.14 133 NW DQ 79 ISFSI - North East 266 Ft 102 WNW DQ 80 ISFSI - South East 256 Ft 61 WSW DQ 81 ISFSI - South 0.10 63 WSW DQ 82 ISFSI -South West 0.15 91 W DQ 83 ISFSI - North West 0.15 104 WNW DQ 101 Remediation Well (B-2) 300 Ft NNW GW

Appendix A: Data Tables A - 3 Table 2 - ODCM Sampling Site Locations Site No.

Description Distance1 (Miles)

Direction2 Sample Type(s)3 102 Remediation Well (B-6) 400 Ft NE GW 103 Remediation Well (DW-13) 80 Ft NE GW 106 Remediation Well (DW-7) 250 Ft SE GW 108 Remediation Well (DW-19) 250 Ft W

GW 110 Remediation Well (B-36) 300 Ft NW GW 112 NPDES Well (GW-9) 0.36 331 SSE GW 113 NPDES Well (GW-12) 0.33 332 SSE GW 114 NPDES Well (GW-13A) 0.39 317 SE GW 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 16 is not currently in use. If conditions change requiring a renewal of dairy sampling, this site will be reactivated.

5.

Site 30 consists of two locations in the same sector. The air sampler is located 0.5 miles from the reactor to support construction of a new facility. The TLD is located 1.0 mile from the reactor in the same sector.

6.

Site 40 (11.9 miles SSE) serves as a control location for garden monitoring.

Appendix A: Data Tables A - 4 Table 3 - Supplemental Sampling Site Locations Site No.

Description Distance1 (Miles)

Direction2 Sample Type(s)3 2

Transmission Line 1.2 SW GR 6

Environmental Lab Garden 1.0 ESE GA 7

Environmental Lab Garden 1.0 E

GA 8

Paul Etta Rd 1.5 ENE AP, RI 11 Robinson Pasture 3.4 N

DQ 14 Kinard Loop / Shealys Dairy4 6.5 W

MK, GR, DQ 15 Parr 2.5 SSW DQ 16 Parr Dairy4 20.0 W

MK, GR 23 Monticello Reservoir 0.5 ESE CL 25 FPSF Penstocks 0.9 WNW GR, SO 31 McCrorey Liston School 6.6 NNE DW 40 Emergency Operation Facility (EOF) Peak Exit 11.9 SSE GA, GR 49 Dave Cole Rd Power Line 4.1 NNW DQ 57 Jenkinsville Rd Residence 2.7 SE DQ 59 Retired Nuclear Training Center - Hwy 213 2.6 SSE DQ 61 Unit 1 Switchyard 0.1 S

DQ 62 Southwest of AAP 0.13 SW DQ 63 East of CTC 0.17 W

DQ 68 Fuel Oil Storage Tank 0.2 ESE DQ 72 Southeast Yard Drain Outfall 0.4 SE SW 73 Northwest Yard Drain Outfall 0.4 W

SW 77 Combined Waste Water Discharge 0.4 ESE SW 99 AAP / NNOB5 0.1 / 0.35 SW DQ, DW 107 Dewatering Well DW-2 175 ft WSW GW 111 NPDES Well GW-8A 0.27 SE GW 115 NPDES Well GW-15A 0.4 SSE GW 116 Dewatering Well DW-14 175 ft NE GW 117 Dewatering Well DW-15 175 ft N

GW 118 Dewatering Well DW-16 125 ft NNE GW 119 Dewatering Well DW-17 150 ft NW GW 120 Dewatering Well DW-18 150 ft W

GW

Appendix A: Data Tables A - 5 Table 3 - Supplemental Sampling Site Locations Site No.

Description Distance1 (Miles)

Direction2 Sample Type(s)3 121 Remediation Well B-23 550 ft S

GW 122 Dewatering Well DW-3 350 ft SSE GW 123 NPDES Well GW-16 0.34 SSE GW 124 Remediation Well B-22 349 ft S

GW 005A Sanitary Waste Sand Filter A 0.3 SE BS 005B Sanitary Waste Sand Filter B 0.3 SE BS 006A Alum Sludge Basin 0.3 SE BS 006B Waste Surge Basin 0.3 SE BS 008 Chemical Cleaning Pond 0.3 SE BS 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 SO = Soil DQ = Quarterly TLD MK = Milk BS = Bottom Sediment SW = Surface Water GR = Grass (Forage)

CL = Corbicula

4.

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

5.

Site 99 Drinking Water sample is collected from the New Nuclear Operation Building (NNOB). The TLD monitoring site is located behind the AAP security building.

Appendix A: Data Tables A - 6 Table 4 - Radiological Environmental Monitoring Program Specifications Exposure Pathway and/or Sample Criteria for Selection of Sample Number & Location Sampling and Collection Frequency Sample Location Type & Frequency of Analysis AIRBORNE:

I. Particulate A) 3 Indicator samples from locations close to the site boundary, in different sectors, of the highest calculated annual average ground level D/Q or dose.2 B) 1 Indicator sample to be taken close to the site boundary in the sector corresponding to the residence having the highest anticipated offsite ground level concentration or dose.2 C) 1 Indicator sample to be taken at the location of one of the dairies being sampled meeting the criteria of VII(A).2,4 D) 1 Control sample to be taken at a location at least 10 air miles from the site and not in the most prevalent wind directions.2 Continuous sampler operation with weekly collection.

Continuous sampler operation with weekly collection.

2 7

30 6

N/A 17 Gross beta following filter change; Quarterly composite (by location) for gamma isotopic.

Gross beta following filter change; Quarterly composite (by location) for gamma isotopic.

II. Radioiodine A) 3 Indicator samples to be taken at two locations as given in I(A) above.

B) 1 Indicator sample to be taken at the location as given in I(B) above.

C) 1 Indicator sample to be taken at the location as given in I(C) above.

D) 1 Control sample to be taken at a location similar in nature to I(D) above.

Continuous sampler operation with weekly canister collection.

2 7

30 6

N/A 17 Gamma Isotopic for Iodine 131 weekly.

Gamma Isotopic for Iodine 131 weekly.

Appendix A: Data Tables A - 7 Table 4 - Radiological Environmental Monitoring Program Specifications Exposure Pathway and/or Sample Criteria for Selection of Sample Number & Location Sampling and Collection Frequency Sample Location Type & Frequency of Analysis III. Direct A) 13 Indicator stations to form an inner ring of stations in the 13 accessible sectors within 1 to 2 miles of the plant.

B) 16 indicator stations to form an outer ring of stations in the 16 accessible sectors within 3 to 5 miles of the plant.

C) 11 Stations to be placed in special interest areas such as population centers, nearby residences, schools and in 4 or 5 areas to serve as controls.

D) 6 Stations to be placed around the ISFSI boundary.

Monthly or quarterly exchange5,7 two or more dosimeters at each location.

Quarterly exchange7; two or more dosimeters at each location.

1,2,3,4,5,6, 7,8,9,10,29, 30,47 12,13,32,33, 34,35,36,37, 41,42,43,44, 46,53,55,60 16,17,18,19, 20,31,45,52, 54,56,58 78,79,80,81, 82,83 Gamma dose monthly or quarterly.

Gamma dose monthly or quarterly.

Gamma dose quarterly.

Gamma & neutron dose quarterly.

WATERBORNE:

IV. Surface Water A) 1 Indicator sample downstream to be taken at a location which allows for Time composite samples6 with collection every month.5 213 Gamma isotopic monthly with quarterly composite (by location) to be analyzed for tritium.7

Appendix A: Data Tables A - 8 Table 4 - Radiological Environmental Monitoring Program Specifications Exposure Pathway and/or Sample Criteria for Selection of Sample Number & Location Sampling and Collection Frequency Sample Location Type & Frequency of Analysis mixing a dilution in the ultimate receiving river.

B) 1 Control sample to be taken at a location on the receiving river sufficiently far upstream such that no effects of pumped storage operation are anticipated.

C) 1 Indicator sample to be taken in the upper reservoir of the pumped storage facility at the plant discharge canal.

Time composite samples6 with collection every month.5 Time composite samples6 with collection every month.5 223 233 Gamma isotopic monthly with quarterly composite (by location) to be analyzed for tritium.7 Gamma isotopic monthly with quarterly composite (by location) to be analyzed for tritium.7 V. Ground Water A) 12 Indicator samples to be taken within the exclusion boundary and in the direction of potentially affected ground water supplies.

B) 1 Control sample from unaffected location.

Quarterly grab sampling.7 Quarterly grab sampling.7 6, 26, 27, 101-103,

106, 108,110, 112-114 59 Gamma isotopic and tritium analyses quarterly.7 Gamma isotopic and tritium analyses quarterly.7 VI. Drinking Water A) 1 Indicator sample from a nearby public ground water supply source.

B) 1 Indicator (finished water) sample from the nearest downstream water supply.

C) 1 Control (finished water) sample from an unaffected water supply.

Monthly grab sampling.5 Monthly composite sampling.

Monthly composite sampling.

28 17 39 Monthly5 gamma isotopic and gross beta analyses and quarterly7 composite for tritium analyses.

Monthly5 gamma isotopic and gross beta analyses and quarterly7 composite for tritium analyses.

Appendix A: Data Tables A - 9 Table 4 - Radiological Environmental Monitoring Program Specifications Exposure Pathway and/or Sample Criteria for Selection of Sample Number & Location Sampling and Collection Frequency Sample Location Type & Frequency of Analysis INGESTION:

VII. Milk4 A) Samples from milking animals in 3 locations within 5 km having the highest dose potential. If there are none then 1 sample from milking animals in each of 3 areas between 5 to 8 km distance where doses are calculated to be greater than 1 mrem per year.10 B) 1 Control sample to be taken at the location of a dairy > 20 miles distance and not in the most prevalent wind direction.2 C) 1 Indicator grass (forage) sample to be taken at the location of one of the dairies being sampled meeting the criteria of VII(A), above, when animals are on pasture.

D) 1 Control grass (forage) sample to be taken at the location of VII(B) above.

Semimonthly when animals are on pasture8, monthly other times.5 Semimonthly when animals are on pasture8, monthly other times.5,11 Monthly when available.5 Monthly when available.5,11 To be supplied when milk animals are found in accordance with criteria VII.A.

16 To be supplied when milk animals are found in accordance with criteria VII.A.

16 Gamma isotopic and I-131 analysis semimonthly8 when animals are on pasture, monthly other times.5 Gamma isotopic and I-131 analysis semimonthly8 when animals are on pasture, monthly other times.5 Gamma isotopic.

Gamma isotopic.

VIII. Food Products A) 2 samples of broadleaf vegetation grown in the 2 nearest offsite locations of highest calculated annual average ground level D/Q if milk sampling is not performed within 3 km or if milk sampling is not performed at a location within 5 to 8 km where the doses are calculated to be greater than 1 mrem/yr.10 Monthly when available.5 6

7 Gamma isotopic on edible portion.

Appendix A: Data Tables A - 10 Table 4 - Radiological Environmental Monitoring Program Specifications Exposure Pathway and/or Sample Criteria for Selection of Sample Number & Location Sampling and Collection Frequency Sample Location Type & Frequency of Analysis B) 1 Control sample for the same foods taken at least 10 miles distance and not in the most prevalent wind direction if milk sampling is not performed within 3 km or if milk sampling is not performed at a location within 5 to 8 km where the doses are calculated to be greater than 1 mrem/yr.10 Monthly when available.5 40 Gamma isotopic on edible portion.

IX. Fish A) 1 Indicator sample to be taken at a location in the upper reservoir.

B) 1 Indicator sample to be taken at a location in the lower reservoir.

C) 1 Control sample to be taken at a location on the receiving river sufficiently far upstream such that no effects of pumped storage operation are anticipated.

Semiannual9 collection.1 Semiannual9 collection.1 Semiannual9 collection.1 233 213 223 Gamma isotopic on edible portions semiannually.9 Gamma isotopic on edible portions semiannually.9 Gamma isotopic on edible portions semiannually.9 AQUATIC:

X. Sediment A) 1 Indicator sample to be taken at a location in the upper reservoir.

B) 1 Indicator sample to be taken on or near the shoreline of the lower reservoir.

C) 1 Control sample to be taken at a location on the receiving river sufficiently far upstream such that no effects of pumped storage operation are anticipated.

Semiannual grab sample.9 Semiannual grab sample.9 Semiannual grab sample.9 233 213 223 Gamma isotopic.

Gamma isotopic.

Appendix A: Data Tables A - 11 Table 4 - 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 are 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.

Appendix A: Data Tables A - 12 Table 5 - Supplemental Radiological Environmental Monitoring Exposure Pathway and/or Sample Criteria for Selection of Sample Number & Location Sampling and Collection Frequency Sample Location Type & Frequency of Analysis AIRBORNE:

S-I.

Particulate A) 1 Indicator sample monitoring the nearest community with the highest anticipated dose or ground level concentration.

Continuous sampler operation with weekly collection.

8 Gross beta following filter change; Quarterly Composite (by location) for gamma isotopic.

S-II.

Radioiodine A) 1 Indicator sample to be taken from the location of S-1(A) above.

Continuous sampler operation with weekly collection.

8 Gamma isotopic for I-131 weekly.

S-III.

Direct A) 5 stations to be placed within the exclusion boundary.

B) 2 stations to be placed around VCSNS sludge lagoons.

Quarterly exchange7; two or more dosimeters at each location.

61,62,63, 68 & 99 94,97 Gamma dose quarterly.

Gamma dose quarterly.

WATERBORNE:

S-IV.

Surface Water A) 1 indicator sample to be taken of the combined wastewater discharge.

B) 1 Indicator sample taken at each storm drain outfall.

Composite samples with monthly collection.13,5 Daily sample with monthly composite.

77 72,73 Gamma isotopic monthly and quarterly tritium composite.

Gamma isotopic monthly and quarterly tritium composite.

S-VI. Drinking Water A) 1 Indicator (finished water) sample to be taken on site.

B) 1 Indicator (finished water) sample of public system.

Monthly5.

99 31 Monthly gamma isotopic and gross beta and quarterly composite tritium analysis.

Monthly gamma isotopic and gross beta and quarterly composite tritium analysis.

Appendix A: Data Tables A - 13 Table 5 - Supplemental Radiological Environmental Monitoring Exposure Pathway and/or Sample Criteria for Selection of Sample Number & Location Sampling and Collection Frequency Sample Location Type & Frequency of Analysis INGESTION:

S-VII. Milk4 A) 1 Sample from one of the nearest affected dairies at or beyond 5 miles.

B) 1 Control sample to be taken at the location of a dairy greater than 20 miles distance and not in the most prevalent wind direction.

C) 1 Indicator grass (forage) sample to be taken at the location of S-VII(A) above.

D) 1 Control grass (forage) sample to be taken at the location of S-VII(B) above.

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

F) 1 Control grass (forage) sample to be used for routine monitoring along with S-VII(E) above.

G) 1 Indicator grass (forage) sample to be taken at location of penstock leak.

Biweekly grab sample.8,14,+

Monthly when available.14 Monthly when available.14 Monthly when available.

Monthly when available.

14 16 14 16 2,7 40 25 Gamma isotopic and I-131 analysis biweekly.

Gamma isotopic and I-131 analysis biweekly.

Gamma isotopic.

S-VIII. Food Products Corbicula A) 1 Indicator sample of various types of foods grown in the area surrounding the plant (root, fruit, grain).

B) 1 Control sample of various types of foods grown. (root, fruit, grain).

C) 1 Indicator sample of edible portions.

Annually during growing season.11 Annually during growing season.11 Semiannual.

6,7 40 23 Gamma isotopic on edible portion.

Gamma isotopic on edible portion.

Gamma isotopic.

Appendix A: Data Tables A - 14 Table 5 - Supplemental Radiological Environmental Monitoring Exposure Pathway and/or Sample Criteria for Selection of Sample Number & Location Sampling and Collection Frequency Sample Location Type & Frequency of Analysis S-IX.

Sediment/

Sludge A) 1 Indicator sample from each storm drain outfall.

B) 3 Indicator sludge samples taken at sludge lagoons.

C) 1 Indicator sample of topsoil from penstock spill area.

D) 1 indicator sample from each sand trap for the Sanitary Waste Pond.

Semiannually Semiannually Annually Semiannually 72,73 006A, 006B

& 008 25 005A &

005B Gamma isotopic.

Gamma isotopic.

Gamma Isotopic S-X. Ground Water A) 12 Indicator samples to be taken within the exclusion boundary and in the direction of potentially affected ground water supplies.

Quarterly grab sampling.7 107,111, 115 -124 Gamma isotopic and tritium analyses quarterly.7

Appendix A: Data Tables A - 15 Table 5 - 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.

Appendix A: Data Tables A - 16 Table 6 - Radiological Environmental Monitoring Program Summary for 2024 Medium or Pathway Sampled (Unit of Measurement)

Type and Total Number of Analyses Performed1 Lower Limit of Detection2 (Required)

All Indicator Locations Mean (f)

[Range]

Location with Highest Annual Mean Control Locations Mean3 (f)

[Range]

Number of Nonroutine Reported4 Measureme nts Name Distance & Direction Mean3 (f)

[Range]

Air Particulate (pCi/m3)

Gross Beta 306 5.57E-3 (1E-2) 2.21E-2 (255/255)

[5.13E-3 to 4.83E-2]

Site 8 1.5 miles ENE 2.26E-2 (50/50)

[8.83E-3 to 4.83E-2]

2.30E-2 (51/51)

[1.08E-2 to 5.11E-2]

0 Gamma Spec 24 134Cs 7.72E-4 (5E-2)

ML25118A115

Text

SUMMARY

SUMMARY

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