ML092860167
| ML092860167 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/29/2009 |
| From: | Gatlin T South Carolina Electric & Gas Co |
| To: | Reyes L Region 2 Administrator |
| References | |
| Download: ML092860167 (45) | |
Text
Thomas D. Gatlin General Manager,Nuclear Plant Operations 803.345.4342 April 29, 2009 A-SCANA COMPANY Mr. Luis A. Reyes.
Regional.Administrator USNRC, Region 11.
Sam Nunn Atlanta* Federal, Center 61 Forsyth Street SW Suite, 23T85 Atlanta, GA 30303 8931%
Dear Mr. Reyes:
q,
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 VirgilC.- Summer Nuclear Station Technical Specifications.
If there are any questions, please contact Ms. Susan B. Reese at (803) 345-4591.,
Very trul yours Thomas D. Gatlin" SBR/TDG/sr Enclosure.:
c: K. B. Marsh.. (w/o enclosure) M. B. Roberts S..A.. Byrne K. M. Sutton N: S. Cams. E. Everett.
J.. H. HaUilton (w/o enclosure) INPO RecordsCenter R. J. White2, K. J. (w/o enclosure) Marsh USA, Browne,: (w/o enclosure), NSRC'.
Document Control Desk LTD (312)'
R. E.. Martin;, File (818.02-2, RR :8300),.
NRC Resident .Inspector PRSF (RC-09-0053)
P. A. Mothena,,-
SCE&G I Virgil C Summer Nudear Station.o P0. Box:88',Jenkinsville, South Carolina 290654T (803) 345.5209 ,ww.Swca.conC 1'ýý
ýC/
.U.. I 1 10q
A SCANA COMPANY RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPERATING PERIOD.
JANUARY 1,2008- DECEMBER 31,. 2008; April: 2009.
Prepared by:-
Brett Williams Health, Physics Specialist Reviewed by:
Michael Roberts-Health Physics Supervisor .
Approved, by:-
Paul Mot hena 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 2008.
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 twenty seven analyses (1,327) performed to compile the data for the 2008 Environmental Report. Supplemental samples comprising one hundred ninety one (1.91) 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 2008 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 concentrations in surface water and sediment were the only indicators with VCSNS produced radioactivity. These activities were well belowthe applicable reporting level requirements of the ODCM. It is therefore concluded that VCSNS operations have no significant radiological :impact on the health and safety of the public ,or the environment.
i
TABLE OF CONTENTS PAGE INTRODUCTION 1 DESCRIPTION OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2 LAND USE CENSUS 3 MONITORING RESULTS AND DISCUSSION 4 CONCLUSION 7 ii
LIST OF TABLES TABLE PAGE I Monitoring Methods for Critical Radiation Exposure 2 Pathways 2 2008. Fission and Activated Corrosion ProductActivity in 6 Sediment 3 Required Sampling Site Locations 8 4 Results of the 2008 Land Use Census: Verification 11 5 Critical Receptor Evaluation for 2008 12 6 Radiological Environmental Monitoring Program 13 Specifications 7 Supplemental Radiological Environmental Monitoring 18
- 8. Radiological Environmental Monitoring Program Summary 21 for 2008 9 Radiological Environmental Monitoring Program 27 Preoperational (Baseline) Summary 10 Results of 2008 Environmental Intercomparison Program 32 with Independent Lab, Analytics, Inc.
11 2008 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 (51 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.
iv
INTRODUCTION Virgil C. Summer Nuclear Station (VCSNS) utilizes a pressurized water reactor rated at 2900 MWt (990 MWe gross). The station is located adjacent to the Monticello Reservoir near Jenkinsville, South Carolina and approximately 26 miles northwest of Columbia. VCSNS achieved initial criticality on October 22, 1982, reached 50% power December 1.2, 1982 and: 100% power June 10, 1983 following steam generator feedwater modifications. Steam generators were replaced. inz the fall of 1994. During the ninth refuel the plant was uprated to 2900 MWt (990 MWe gross). VCSNS is currently operating in the 1 7 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 locatedý 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. Colurmbia, 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 2008. Data trends, control/indicator and. preoperational/operational data inter-comparisons and other data interpretations are presented.
1
DESCRIPTION OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program is carried out in: its entirety by:
South Carolina Electric and Gas Company. The program has been designed. to meet the, following general commitments:
- 1. To analyze selected samples in important anticipated pathways, for the qualification and quantification of radionuclides released to the environment surrounding VCSNS.
- 2. To establish correlations between levels of environmental radioactivity and radioactive effluents: from VCSNS operation.
The program Utilizes the concepts of control/indicator and preoperational
/operational inter-comparisons in order to establish the adequacy of radioactivity source:
control and to realistically verify the assessment of environmental radioactivity levels and subsequent radiation dose to man.
Sample media and analysis sensitivity requirements have been established to ensure that the maximum dose pathways are monitored. and sensitivities represent a small fraction of annual release limits. Effluent dispersion characteristics, demography, hydrology and land use have: been considered in selection of environmental sampling locations. These criteria were used to establish both: the preoperational and operational phases of the Radiological Environmental Monitoring Program. Elements of the program monitor the impact of gaseous and liquid effluents released from VCSNS.
Specific methods, used in monitoring the pathways of these effluents which may lead to radiation exposure of the public, based on existing demography, are summarized below in Table 1. Requirements of the Radiological Environmental Monitoring Program are specified in the, VCSNS Offsite Dose Calculation Manual (ODCM). Elements of the program monitor the impact, of gaseous and liquid effluents: released from VCSNS.
Table 1- Monitoring Methods for Critical Radiation Exposure Pathways Effluent ReleaseType .. Exposure Pathway Monitoring Media Gaseous Immersion Dose and other Thermoluminescent Dosimetry (TLD),
Extemal 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/operationaI 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 Iocation for liquid effluent comparisons is at. Site 22, Neal Shoals (26,0 mi. NNW) on the Broad River.
Quality of analytical measurements is demonstrated by, participation in a laboratory inter-comparison program. Results of the inter-comparison program with an outside vendor and VCSNS Count Room were satisfactory in 2008. 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 2008 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 2008, meteorological data, Exposure pathways used in the analysis were those identified during the land use census.
3
The location and pathway presently used in the ODCM for offsite organ dose calculations (E 1.1 miles - residence/garden) was found to have a calculated dose of 3.46E+0 mrem/yr. In addition, the ODCM required environmental gardens (ESE 1.0 and E 1.0 mile) were found to have a calculated dose of 2.12E+0 and 4.27E+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 2008 are summarized in Table 8. For comparison, preoperational data are summarized in Table 9.
The Radiological Environmental Program attained a program compliance rate of approximately 98.6%w 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 inh the Supplemental Sampling Program. Samples were collected. and analyzed for gamma emitting isotopes. No measurable gamma emitting nuclides were detected above minimum detectable activity (MDA).
Gross beta activities measured in air particulate samples collected at indicator locations around VCSNS were consistent with preoperational levels and not statistical*,
different from control locations. The highest site-specific mean activity (2.27E-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 activit .trend. Only natural background activities were detected. The highest MDA levels for' Cs, 13 7 Cs and "'11were 5.21E-3, 2.22E-3 and 1.82E-2 pCi/m 3 , respectively. The average maximum results support the gaseous, effluent release datat reported in the 2008 Annual Effluent and Waste Disposal Reports for VCSNS. No measurable iodine or particulate were released.. 99.1%
of the required .indicator/control air samples were collected.
Environmental dosimetry measurements did not differ significantly from preoperational measurements. Indicator and control dosimetry ýmeasurements 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 1.19E+1/pR/hr. This is similar to the 2007 value of 1.1 7E+1 tJR/hr and consistent with the highest mean exposure rate of 1.40 E+1 p*Rlhr measured during the preoperational period. 98.8% of the required TLDs Were collected.
4
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. Tritium analysis indicated the presence of tritium above MDA in six indicator samples. Three samples were collected from site 21 (Parr Reservoir 2.7 ml.
SSW) and three samples were collected from site 23 (Lake Monticello Reservoir 0.5 mi.
ESE). The tritium concentrations at site 21 were 5.80E+2, 6.78E+2, and 4.74E+2 pCi/I.
The tritium concentrations at site 23 were 6.07E+2, 6.73E+2,, and 6.94E+2 pCi/I. All concentrations were well below the reporting limit. All required 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. 93.8% of indicator/control ground water samples were collected.
Gamma spectroscopy measurements of drinking water samples collected from the Jenkinsville water supply and Site 17 (Columbia Water Works 25.0 mi. SE) did not indicate the presence of activated corrosion or fission product activity above the respective MDAs. The highest indicator and control site-specific gross beta activity was measured at Site 39 (Lake Murray Water Treatment Plant 14.0 mi. SSE) at a level of 3.28E+0 pCi/l. All required indicator/control drinking water samples were collected.
There were no milký samples collected in 2008. Milk sampling is required to be performed atthe 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 ý Cs in twelve of twelve samples at. Site 2 (transmission line 1.1 mi. SW) at concentrations ranging from 1.25E+1 to 1.59E+2 pCi/kg. The maximum preoperational control activity was 3.4E+2 pCi/kg. A review of Site 2 air sample results indicated that no 137 Cs was detected. All required 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.
5
Gamma spectroscopy measurements of the fish samples collected at the control site indicated the presence of 137Cs in one sample. Control site 22 (Neal Shoals Reservoir, 26.0 mi. NNW) had a 137 Cs concentration of 1.15E+1 pCi/kg. This activity is below the preoperational mean of 2.8E+1 pCi/kg and well below the preoperational max of I1.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 137Cs in two of four indicator samples and 6°Co in oneý indicator sample. At Site 21 (Parr Res. 2.7 mi. SSW)137Cs at concentrations of 1.46E+2 and 5.81E+1 pCi/kg, and 60Co at a concentration of 2.19E+1 pCi/kg were detected. 137'Cs was detected in two of two control samples taken at Site 22 (Neal Shoals 26 mi. NNW) at concentrations of 7.06E+0 and 1.65E+2 pCi/kg. All required indicator/control sediment samples were collected.
Tritium analysis indicated the presence of tritium above MDA in four of twenty four supplemental surface water samples. These samples were collected from site 72 ,(storm drain ouffall 0.4 mi. SE). and site 73 (storm drain ouffall 0.4 mi. W.) The tritium concentrations at site 72 were 6.89E+2 and 4.94E+2 pCi/I, The tritium concentrations at site 73 were 5.14E+2 and 7.OOE+2 pCi/l. All concentrations were well below the reporting limits and are attributed to wash out from plant gaseous :releaseS.
Table 2 - 2008 Fission and Activated Corrosion Product Activity in Sediment Corresponding Calculated Location Radionuclide Activity (pCilkg) Annual Dose Equivalent (mrem/yr)
Total Body Maximum. Mean Maximum Mean Parr 5°Co 2.19E+1 '2.19E4- 7.45E-3 7.45E-3 Reservoir 3mt Cs 1.46E+2 1.02E+2 1.23E-2 '8.57E,-3 Total 1.98E-2 1.60E-2 6
CONCLUSION As in previous years of VCSNS operation,. the presence, of fission product activity attributed to residual fallout from atmospheric. weapons testing and the Chernobyl accident were detected in environmental media including sediment, fish and grass.
No detectable fission or activation product activity attributed to VCSNS operations was observed in environmental media except for tritium in surfacewater samples at sites 21 (Parr Res. 2.7 mi. SSW), 23 (Lake Monticello Reservoir 0.5 mi. ESE), 72 (storm drain outfall 0.4 mi. SE): and site 73 (storm drain outfall 0.4 mi. W.) which was well below the EPA drinking water standard, and 60 Co in one sediment. sample at site 21 (Parr Res. 2.7 mi. SSW). 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 thel 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.
7
Table 3- Required Sampling Site Locations site Description Direction 2 Sample Type(s)3 No. (Miles) 1 Borrow Pit 1.2 179.8 S DQ 2 Transmission Line 1.1 225.0 SW AP, RI, DQ
- 3. Firing Range 1.2 270.0 W DQ 4 Fairfield Hydro 1.2 289.5 WNW DQ
.5 Transmission Line Entrance 0.9 144.0 SE DQ 6 Environmental Lab Garden 1.0 111.0 ESE AP,RI,GA,DQ,GW 7 Environmental Lab Garden 1.0 97.8 E AP,RI,DQ, GA 8: Monticello Res. S of Rd 224 1.5 62.0 ENE DQ 9 Ball Park 2.3 41.6 NE DQ 10 Meteorological Tower #2 :2.5 25.5 NNE DO 12 Old Hwy 99 4.2 349.4N DQ 13 North Dam 2.9 333.0 NNW DQ 14 Dairy (Sheal ) 4 .. 6.5 277.0W MKGR 16 Dairy (Parr)4 20.0 275.5 W MK,GR 16a TLD Location 28.0 278.6W DQ 17 Columbia Water Works 25.0 144.0 SE AP,RIDQ,DW 18 Residence/Pine Island Club" 16.5 165.0 S DQ,GA 19 Residence/Little Saluda 21.0 224.0 SSW DQ 20 Residence/Whitmire , 22.0 309.5 NW` DQ 21 Parr Reservoir 2.7 199.5 SSW SW,FH,BS.......
22 Neal Shoals 26.0, 343.1 NNW SW,FH,BS 23 Discharge Canal (Mont, Res.) 0.5 104.5 ESE SW,FH,BS .
- 26 On Site Well( P2) 460 Ft 270.0 W GW 27 On Site Well (P15) 510 Ft 180.0 S GW 28 Nuclear Training Center (EOF)t 2.6 170.2 SSE DW 29ý Trans. Line WSW..of VCSNS 1.0 260.6 WSW: DO 30 Oak Tree:North of Borrow Pit" 1'.0 /0.5 196.2 SSW. DQ, AP, RI 31 McCrorey-Liston School 6.6 11.5 NNE DQ 32 Clark Bridge Road and Brooks Drive 4.6 24.0 NNE DO
- 33. Rd 48 near Hwy 213 . . 4.2 68.0 ENE DO 34 Rd.419 North of Hwy 60 4.9. 111.0 ESE DO.
35 Glenn's Bridge Road 4.6 132.0 SE DO
ý36' Woods Behind Jenk..Post Office 3.1 151.0 SSE DO 37 Residence 4.9 304.8 NW DQ 39 LMWTF 14.0 168.0 .S.SE DW 8
Table 3 (cont) - Required Sampling Site Locations site Site..
NDescription ... ..Distance' Mile Direction22.... Sample Type(s) 3
___________________ (Miles) ______________
41 Below Catwalk at Trestle, 3.8 182.0 S DO 42 Broad River Rd (Residence Peak) 3.8 198.0 SSW DO 43 Hwy 176 and Rd 435 5.2 236.0 SW DQ 44 Rd 28 at Cannon's Creek 2.8 2566 WSW DO 45 Rd 33 at Pomaria 5.8 253.2 WSW. DO 46 Rd 28 at'Heller's Creek 3.7 291.5 WNW DO 47 Fairfield Tailrace 1.0 316.0 NW DO 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 DO 55 St Bamabas:Church 2.8 91.5 E DO 56 Old Jenkinsville Dinner 2.0 144.0 SE DO 58 Residence 2.5 157.0 SSE DO 59 Nuclear Training Center (EOF)" 216 170.2 SSE DQ, GW 60 Rd.98nearRd 28 3.5 .274.6 W DO 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 (DW-13), 80 Ft NE GW 104 Remediation Well (B-9) 175 Ft NE GW 105 Remediation Well (DW-1 1) 100 Ft ESE GW 106 Remediation Well (DW-7) 250Ft SE. GW 107 Remediation Well (B-28) 400 Ft SW GW 108 Remediation Well (DW-19) 250 Ft W GW 109 Remediation Well (B-35): 450 Ft: NW GW 110 Remediation Well (B-36) 300 Ft NW GW 111 NPDES Well (GW-8) 0.27 320 SE GW 112 NPDES Well (GW-91 0.36 33.1 SSE GW 113 NPDES Well (GW-12) 0.33 332. SSE GW 114 NPDES Well. (GW-13A) 0.39 317 SE GW 115 NPDES Well (GW-15) 0.39 330. SSE GW 9
Table 3 (cont) - Required Sampling Site Locations Footnotes
- 1. Distance given is the distance between the site location and the VCSNS reactor containment building.
- 2. Direction given in degrees from true north-south line through center of reactor containment building.
- 3. Sample Types:
AP = Air Particulate GW = Ground Water GA = Garden RI = Air Radioiodine DW = Drinking Water FH = .Fish DQ = Quarterly TLD MK = Milk BS = Bottom Sediment SW = Surface Water GR = Grass (Forage)
- 4. 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 two locations in close proximity to Lake Murray. Garden product samples are taken at the Wyse residence. The TLD is located on Pine Island.
- 6. Site 28 for drinking water and site 59 for quarterly TLD measurements are co-located at the location of the SCE&G 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.
10.
Table 4 - Results of the 2008 Land Use Census Verification No. No.
Sector NearestResidence Miles NearestGarden Miles Nearest Cattle Milked Miles NearestGoat Milked Miles N P.:Oliver 3.73 Edna Fuller (A) 4.01 John Robinson 0 3.4A . .......
NNE Thomas K. Crumtlin 2.9 Virgil Harrison 3.21 Wi/haitesColeman 0 4.97 .....
NE Gregrey Gulnyar'd Jr. 1.55 Edna Richards (A) 3.21 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 Carie Lee Martin 1.1A SE' Mary White 1.44 Mary White! 1.44 SSE Ronnie Mann 2.39 RonnieMann 2.39 S Kelly Boulwam, 3.56 Kelly Boutware 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 WSW Ron Hope 2.9 Steve A:l (A) 4.83: KentIV/ Graham. 4.98 Steve All 4.83 W Jerny.Cassado 2.55 Marion Livingston 2.8 Marion Livlngston 0 2 W Ken/ Vrg Graham 90 5 WNW Randy Wedaman. 4.24 Ronnie Leitzey 4.72 Ronnie Leltzey 1 4.15 Ronnie Leitzey , , 4.15 NW ILouise Workman 3.9 .....
NNW Frank March 2.9 Frank March 2.9 Frank March 0 2.9 (A) Change In Nearest Garden 11
Table 5 Critical Receptor Evaluation for 2008 SECTOR MILES PATHWAY X/Q* DIQ DOSE*
NAME
, mRem/y John Robinson N 34 B 2.80E-07 810E-10 8.70E-021 P. Oliver N 3.73 Res 2.30E-07 7.10E-10 8.60E-03 Edna Fuller N 4.01 Res,Gar 2.OOE-07 6.OOE-10 1.64E-01 Thomas K. Crumblin. NNE 2.9 Res 4.OOE-07 1.40E-09 i.50E&02 Wrgil Harrison NNE 3.21 Res, Gar 3.30E-07 1.10E-09 2.98E-01 Will/Charles Coleman NNE 4.97 B 1.40E-07 4.30E-1:0 4.31 E-02 Gregrey Guinyard Jr. NE 1.5 Res 1.90E-06 6.50E-09 7.14E-02 Edna Richards NEý 3.21 Res,Gar 4.20E-07 1.10E-09,. 3.07E-011 Robert Martin ENE 1.53 ResG 1.90E-06 6.50E-09 1.49Ew01 Essie Mae Glenn ENE 1.68 Res,Gar 1.50E-06 5.16E-09 1,38E+00 Garden-7 G* E I "Res,Gar 4.20 E-06 1.60&E-08 4.27E+00
'Lynn Mincy E 1.2 Res,Gar 2.70E-06 1.OOE-08 2.68E+00 Garden-6 ESE 1 Res,Gar 2.00E-06 8.00E-09 2.12E+00 Carmie Lee Martin ESE 1.1 Res 1.60E-06 6.30E-09 6.05E-02 MaryWhite SE 1.44 ResGar. 4.90E-07 2.50E-09 6.50E-01 Ronnie Mann SSE 2.39 ResGar 1 .20E-07 7.00E-10 1.80E-01 Kelly Boulware S 3.56 Res,Gar 6.90E-08 4.40E-10 1.13E-01 Shirley Counts S 5 Res,Gar,B 3.40E-08 2.1OE-10 7.486-02 Nick.Bates SSW. 3.11. Res 1.20E-07 9.40E-10 4.77E-03' Nora Wicker SSW 3.77 Res,Gar 7.70E-08 6.1OE-10 1.54E&01 G.A. Mayers SSW 4.7" Res,B 4:.90E-08 3.70E-10: 3.87E-02 Marvin Miller SW 3.3 Res,Gar 8.80E-08 9.16E-10 227E-01 Ron Hope WVSW 2.9 Res 9.20E-08 8.40E-10 3.72E-03 Steve All: WSW 4.83 ResG 3.10E-08 2.70E-10 71 2E-02 Kenfirg Graham WSW 4.98 B 3.00&-08 2.50E-10 2.48E-02 Jerry Cassado W 2.55 Res 9.170E08 .6.70EA10 3..81E-03 Marion Livingston W 2 B 1.70E-07 1.20E-09 1.1 9E-01 Marion Livingston W 2.8 Res,Gar 7.90E-08 5.40E-10 1.38E-01 Marion Livingston W . 2 &:2.8 ResGarB BOTH BOTH 2.57E&01 Ken/Airg Graham W 5 Res,Gar,BC/M 2.40E-08 1:.50E-10 8.1 5E-02 Randy Wedaman WNW 4.24 Res 2.60E&08 1.40E-10 1.00E-03 Ronnie Leitzsey WNW 4.15 C/M,BjG/M,G 2.70E-08 1.50E-10 1.50E-01 Ronnie Leitzsey WNW 4.72 Res,Gar 2.1 0E-08 1.10E-10 2.85E-02 Ronnie Leitzsey WNW Res,Gar,C/M,BG/M,G _ BOTH BOTH 1.78E-01 Louise Workman NW 3.9 Res 7.50E&08 2.50E-10 2.81 E-03 Frank March NNW 2.19 Res,GarB 2.60E-07 7.50E-10 2.82E-01 ODCM ORGAN DOSE E 1.1 ResGar 3.30E-06 1.30E-08 3.46E+00 Pathway Res = Residence B = Beef G = Goat Gar Garden C/M = Cow/lAk(Infant) GOM = Cow/Milk(Infant)
Footnotes:
Maximum exposed individual.
- Hypothetical dose based on Operating License Environmental Report Source Term.
- ODCM required environmental gardens.
12
Table 6 - Radiological Environmental Monitoring Program Specifications Exposure Pathway and/or Criteria for Selection of Sampling and Collection sample Type & Frequency of Pahayla Sample Number & Location Frequency Locaion Analysis Sample: _________________
AIRBORNE:
I. Particulate A) 3 Indicator samples to.be Continuous sampler operation 2 Gross beta following filter taken at locations (in with weeklycollection. 7 change;, Quarterly different sectors): beyond 30 composite (by location) but as close to the forgamma isotopic.
exclusion boundary as practicable where the highest offsite sector ground level concentrations, are anticipated. 2 B) 1 Indicator sample"to be Continuous sampler operation 6 Gross beta following filter takenin the sector beyond with weekly collection. chahge; Quarterly but as close to the composite (by location) exclusion boundaryas for gamma isotopic.
practicable corresponding to the residence having the highest anticipated offsite ground level 2 concontration or dose.
C) 1 Indicator sample to~be Continuous sampler operation N/A Gross beta following filter taken at the location of one with weeklycpollection. change;, Quarterly of the dairies being composite (by location) sampled meeting.the 4 forgamma isotopic.
Criteria of VII(A)2'.
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 thesite composite (by location) and niot in the most forgamma isotopic.
2 prevalent wind directions&
I.!,Radioiodine A) 3 I.ndicator samples to be1 ContinudUs.6sampler operation. 2 Gamma Isotopic for takenmat 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) I Indicator sample to be Continuoussampler operation N/A Gamma isotopic for taken at the location as with weekly canister collection. Iodihe 131 weeklyl.
given in I(C) above.
D) 1 Control sample to be Continuous sampler operation 17 Gamma Isotopic for taken.at.a Iocation~similar with weekly canister collection. iodine 131 weekly.
in nature to I(D).,above.
13.
Exposure Criteria for'Selection-of Sampling and Collection Sample Type & Frequency of Pathway Sampleandlor Sample
,o Number, & Location Frequency Location Analysis, Ill. Direct A) 13 Indicator stations to Monthly or quarterly, 1,2,3,4,56, Gamma dose monthly or form and Inner ring of' exchange"' 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 dng of stations in exchange5 ' 7 two or more 34,35,3637. quarterly the 16 accessible sectors dosimeters at each location. 41 42A,43,44, Within 3 to 5 miles ot the 46,53.55,60 plant.
C) 11 Stations to be placed in Quarterly exchange7, twoor 16,17,18,19; Gamma dose quarterly.
specialrinterest 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 samplesa with 213 Gamma isotopic monthly Water downstream to be taken at collection every month5 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 samples with 223 'Gamma isotopic monthly takenat a location on the. collection every months with quarterly composite (by location),to 0b.
receiving river sufficiently (nbIyzad.for tritiUm7.
far upstream such that-non effects of pumped storage operation'.are anticipated..
C) 1 Indicator sample to0be Time composite samples~with 233 Gamma Isotopic monthly taken in the upper reservoir collection every months with quarterly composite of the pumpedstorage (by location) to: be facility at the plant: analyzed. fortritnumT, discharge canal.
V. Ground Water A)z 19 Indicator samples to be Quarterly grab sampling7 6, 26, 27, Gamma isotopic and taken within the exclusion 1.00-115, tritium analyses boundary and in the quarterly'.
direction of potentially affected ground water supplies.
B) I Control sample from Quarterly grab sampling 7 59 Gamma isotopicand unaffected locationý tritium analyses 7
quarterly 14
Exposure ..
EPathwaiOr Sam ale .
teria for Selection of Sample Number & Location Sampling and Collection Sample Type & Frequency of
. Frequency Location Analysis.
Sml . i i __=....... .
VI. Drinking A) I Indicator sample from a Monthly grab sampling 5. 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 MonthlyV 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 Monthly5 gamm aisotopic, sample from: an~unaffected and gross7 betaand water supply; quarterly composite for tritium analyses INGESTION:
ViI. Milk 4 A) Samples from~milking Semimonthly when animals To be Gamma isotopic-and IP animals in 3 locations are on pasture.- monthly other supplied 131 analysis within 5 km having the times5 when milk semimonthly5 when highest dose potential. If: animals are* animals are on pasture, there are none then 1 found in monthly other times5 sample from milking accordanCez animals in each of 3 areas with criteria betweeh 5 to8 kmi distance VII.AX where doses are; calculated to be greater 10 thaný 1 mrem per year.
B) 1 Control sample to be Semimonthly when animals 16 Gamma isotopic and I-takenat the location of a areon pasture8' monthly other 131 analysis dairy > 20 miles distance times5, 1 semimonthly8 when and not in the most animals are on pasture, prevalent wind direction2 monthly other timess C) I Indicator grass (forage) Monthly when availables To be Gamma isotopic, sample to betaken atthe supplied location of one of.the when milk dairies being sampled .animals are-meeting the criteria of found In VIl(A),aboveý When accordance.
animals are on pasture with criteria VIIA; Monthly when available 5" 1 D) I Controlgrass (forage) 16 :Gamma isotopic.
sample to be taken at the location of VII(B): above.
15
Exposure Criteria for Selection of Sampling and Collection Sample Type &:Frequency of Pathway andlor Sample Number & Location Frequency Location Analysis
.Sample __ , _ _
VIIll Food A) 2 Samples of broadleaf Monthly when available5. 6 Gamma isotopic on edible Products vegetation grown in the 2 7 portion.
nearest offsite location of highestcalculated 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 arecalculated to be greater than I mrem/yrl".
5 B), 1 Control sample for the Monthly when available . 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 kMi or if milk sampling is not performed at a location within5 to 8*km where the doses are calculated to be 10 greater than 1 mrem/yr '
9 IX. Fish A)ý 1 4Indicator sample,to be Semianrnual collection of the 23i Gamma isotopic on edible.
9 taken at a;location iinthe following'specle types if portions semiannually .
upper reservoir. available: bass; bream; crappie; catfish, carp.
B)- 1 I ndica'tor sample to be Semiannua' collection of the 21' Gamma isotopic on edible 9
taken at a location in the following specie types if portions semiannually .
lower reservoirs available: bass; bream,.
crappie; catfish, carp.
C) 1 Control sample to be Semiannualo collection. of, the 223 Gamma isotopic on edible taken at a location on the following specie types if portions semiannually'.
receiving river sufficiently available: bass; bream, far upstream.such that no crappie; catflsh;.carp.
effects of pumped storage operation are, anticipated AQUATIC:
X. Sediment A) 1 Indicator sample to be Semiannual grab sample.9 233 Gammaisotopic.
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.' 22: Gamma isotopic.
taken at a location on the receiving river sufficiently far upstream such that no effects of;pumped storage operation.are anticipated.
16
Table 6 (cont) - Radiological Environmental .Monitoring ,Program Specifications FOOTNOTES
- 1. 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. Ifthe 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 three Indicator Locations.
- 5. Not to exceed ý35 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 Type & Frequency of and/or Sample Sample Number & Location Collection Frequency Location Analysis AIRBORNE:
S-I. Particulate A) 1 Indicator sample Continuous sampler 8 Gross beta following monitoring the nearest operation with weekly filter change; Monthly community with the highest collection. Composite (by anticipated dose or ground location) for gamma level concentration. isotopic..
S-IL. Radioiodine A) 1 Indicator sample to be Continuous sampler; 8 Gamma isotopic for I-taken from the location of operationwith weekly 131 weekly.
S-I (A) above. collection.=
S-Ill. Direct A) 5 stations to be placed Quarterly exchange7; two 61,62,63, Gamma dose within the exclusion or more dosimeters at 68 & 99 quarterly.
boundary.. each location.
B) :2 stations to be placed Quarterly exchange7 ; two 94,97 Gamma dose around VCSNS sludget or more dosimeters at quarterly..
lagoons. each location.
WATERBORNEf S-IV. Surface A) 1 indicator sample to be Composite samples with 77 Gamma isotopic and Water taken of the combined monthly collection.1 3'5 tritium.
wastewater discharge.
B) 1 Indicator sample taken at Daily sample with 72,73 Gamma isotopic and each storm drain outfall, monthly composite. tritium.
S-V4. 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 Criteria for Selection of Sampling and .Sample Type & Frequency of andlor Sample, Sample Number & Location Collection Frequency Location Analysis INGESTION:
S-VII. Milk 4 A) 1 Sample from one of the Biweekl grab 14 Gamma isotopic and I-nearest affected dairies at sample. 131 analysis biweekly.
or beyond 5 miles.
B) 1 Control sample to be Biweekly grab 16 Gamma isotopic and I-taken at the locationo0f a sample.'- 131 analysis biweekly.
dairy greater than 20 miles distance and not in the most. prevalent wind direction.
C)% I Indicator grass (forage) Monthly when, 14 Gamma isotopic.
sample to be taken at the available.14 location of S-VII(A) aboveý D) 1 Control grassf(forage). Monthly when 16, S-VII. Milko sample to. be -taken at'the available.14 Gamma isotopic.
location of. S-VII(B): above.
E) 2Indicator grass (forage) Monthly whenavailable., 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." edible portion.
grown inmthe area surrounding the plant (root, fruit, grain)..
Corbicula B) Indicator sample ofedible Semiannual 23 Gamma isotopic portions S-iX. Sedimentl A) 1 indicator sample from Semiannually 72,73 Gamma isotopic Sludge each stor0 dran.outfall.
B) 3 indicator sludge Semiannually 006A, Gamma isotopic samples taken at, sludge (Reference 2.6) 006B &
lagoons. 008 SOIL:
S-X. Topsoil A) 1 Indicator sample to be Annual grab sample.," 98 Gamma iSot0pic.
taken at the waste oil incinerator.,
19
Table 7 (cont) - Supplemental Radiological Environmental Monitoring FOOTNOTES
- 1. Reserved for future use.
- 2. Reserved for future use.
- 3. Reserved for future use.
- 4. Milking. animal and garden survey results will be analyzed annually. If the survey should indicate new activity the owners shall be contacted with regard to a contract for supplying:
sufficient samples. If contractual arrangements can be made, site(s) will be added for additional milk sampling up to a total of 3 Indicator Locations.
- 5. Notto 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.
1.2. 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.
20
Table 8- Radiological Environmental Monitoring Program Summary for 2008 Location with Highest Annual Mean Number of Type2and M r Total Lower Lmit A Indicator Locations Control Locations Nonroutine Pathway Sampled Number of Of Detection 3 Name Mean3 (#(total,#) Mean' (It/total #J Reported' (Unit of Analyses1 Actual (Rane Direction) (Range) (Ran. )istance&
Measurement) Performed (Max.) (Range) (Range), Measurements Air Particulate Gross Beta 6.01 E.3 2.13E-2 (262/262) Site 7 Environmental 2-27E-2 (53/53) 1.99E-2 (53/53), 0
- (pCi/m). (315) (1.oE-2) (6.79E-3 to 8.77E-2) Lab Garden (9.88E-3 to 3.92E-2) (7.05E-3 to 3.55E-2)
(1.0 mi E)
Gamma Spec CS 5&21E-3 All < LLD All -c<LLD .0 (5.OE-2) 4
,Cs 2.22E-3, All < LLD All< LLD 0 (6.0E-2)
AiriRadiidine "'1 l315) 2)All < LLD 170E All.<.LLD a 0
Direct (TLD) Gamma(134) 8.38E+0 (114/114) Site 4, Fairfield: Hydro; 1.19E+1 (414) 8.34E+0 (20/20) 01
(.jRlhr) Quarterly N/A (5,64E+O to 1.22E+1) (1.2 mi., WNW) (i.16E+1I to 1.22E+1) (5.91+0 to 104E+1)
Gamma(24) 8.90EO (24/24) Site 52 Monticell0Rt. 1.12E+1 (4/4) N/A 0 Special Interest N/A (5.36E+0 to 1 17E+1) 11 (3.8 mi., NNE) (1.07E+1 to 1.17E+1)
Surface.Water -OH (36) 4.94E+2 6.18E+2 (6/24) Site 23 Monticello Res. 6.58E+2 (3/12) All < LLD 0 (pCi/I): (2.OE+3) 4.74E+2 to 6.94E+2 (0.5 mi., ESE) 6.07E+2 to 6.94E+2 Gamma Spec(36).
_(1 5E+1)
.Fe.................. E0AAI! LLD 0
_____ _______ _____ 1.5E+1) __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ _ _ _ _ _
.Zn 5.14E+0 AII<tLLD All< LLD 0
___ _____ ________ (3'.OE+l) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
1ýzr 4.29E+O All.< LLD All< LLD 0 (3.OE+,1)
. .. . Nb 3.31 E+O AII < LLD All <LLD 0 "Cs 2.08E+0 Alli-LLD All-< LLD 0 (1.5E+*)
,21
Table 8 (cont.) - Radiological Environmental Monitoring Program Summary for 2008 Location with Hi"hest'Annual Mean Number of
,Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine Pathway Number of of Mean 3 (#/total #) Name Mean3 (#/total #) Mean 3 (#/total ) Reporteý 4 Sampled (Unit of Analyses Detection? (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed' Actual (Max _.)............... .. ...."_.... ...
1 Surface Water d(Cs 2.39E+0 AN < LLD All < LLD 0 (Continued) (1.8E+1.)
R'Ba 1.61E+1 All <, LLD All < LLD 0 O6.E+l)
'4La 5.68E+0 All:< LLD All < LLD 0
____________ (1 .5E+1)__ _ _ _ _ _ _ ___ _ _ _ _ _
3 Ground Water H (75) 4.94E+2 All < LLD All < LLD 0 (pCi/I) N/A Gamma.Spec
_A75)
ýMn 5.61E+0 All < LLD All < LLD 0 (1.5E+1) 5Co 5.45E+0 All < LLD All < LLD 0 (1.5E+1) . . ..
..Fe 1.07E+1 All <,5 LLD All < LLD 0 O3.E+I)
'Co 6.04E+0 All < LLD All < LLD 0 (1.5E+1)
- Zn 1.21E+1 All < LLD All < LLD- 0 (3.0E+I)
_(3.OE+1) bNb 8.02E+0 All < LLD All < LLD 0
___ ____ ________ (i.5E-i-1)_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
JMCs 5.38E+0 All < LLD All < LLD: 0 (1.5E+1)
IVES 5.71E+0 All < LLD Al < LLD 0
______ ______ (1 *8E+1) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
1 Ba 2.38E+1 All < LLD All< LLD 0 (6.OE+1)._
"wLa 8.87E+0 All < LLD All< LLD 0 (1S5E+1) 22
Table 8 (Cont. - Radiological EnvironmentalMonitoring Program Summary for 2008 Location with Hi hest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine Pathway Number of of Mean 3 (#Itotal #) Name 3 Mean (#/total #) Mean 3 (#ttoal#) Reported' Sampled (Unit of Analyses Detection2 (Range): (Distance & Direction) (Range) (Range) Measurements Measurement) Performed' Actual (Maxý)
DrinkingWatero Gross Beta (36) 1.48E+O 2.110E+0 (23/24) Site 28, NTC 2.13E+O0(11/12) 1.99E+0 (12/12) 0 (pCi/I) (4.OOE+0) (1.39E+0 tO 3.09E+0) (2.6 mhi 170.2 SSE) (1.39E40 to 3.09E+0) (1.33E+O to 3.28E+0)-
AH (36) 4.98E*2 All < LLD. All < LLD 0 (2.OE+3)
Gamma Spec Mn 2.62E+ 0 All < LLD (1.5E+
0 1)
All < LLD 0
=Co 2.71E+ 0. All LLD AIl < LLD 0 "
(1.5E÷ I)
ý'Fe- 5.06E+ 0 All- < LLD AIl -5 LLD 0 (3.OE+
- Co 2.98E+ 0 1)
All < LLD All < LLD 0 (1.5E+ 1)
'Zn 5.92E+O All < LLD All < LLD 0 (3.OE+ 1)
.Z" 4134E+ 0 All < LLD All < LLD 0
... . 3.94E-1 All < LLD AlNLED
<0
... Cs 2.77E+ 0 All < LLD All < LLD 0O "l.E +1
'UBa 1.16E+ 1 AI I< LLD All < LLD 0 (6.0E+ 1) ,,,
1La 4.22E+ :0 All < LLD All < LLD 0 0(195E+ 1) 23
Table 8 (Cont.)- Radiological Environmental Monitoring Program Summary for 2008 MLocation with :Hi lhest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine Pathway Number of of Mean- (#/total #) Name Mean' (#/total #) Mean3 (#Itotal #) Reported' Sampled (Unit of Analyses Detection2 (Range) (Distance & Direction) (Range) (Range) Measurements Measurement) Performed1 Actual (Max.)
Broadleaf Gamma Spec..
Vegetation. (36)
(pCi* wet) I_.
1 2.14E+1 All < LLD Alt < LLD 0 (6.0E+ 1),,
.CS 1.89E+1 All < LLD All < LLD: 0 (6.OE+ 1) 2.35E+1 All < LLD AlI < LLD 0 (8.OE+ 1)
FishT Gamma Spec (pCi/kg wet) , (1_8)
Mn 1.66E+1 All < LLD All< LLD 0 (1.3E+ 2) , .....
-- Co ..... 1.81E+1 All < LLD Aii< LLD 0 (1.3E+ 2)
"Fe. 4.76E+1 All <LLD AIl< LLD 0 (2.6E+ 2)
-Z4A38E+1 A LLD All < LLD 0 (2.6E+2) l*Cs- 1.47E+1 All < LLD Al! < LLD 0
- ,, (1.3E+2) 1.78E+1 All < LLD 1.15E+1 (1/6) 0 (1.5E+2) (1.15E+1 to 1.15E+1) 24
Table 8,(Cont)- Radiological Environmental Monitoring Program Summary for 2008 T.Location with Hi hest Annual Mean Number of Medium or Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine Pathway Number of of Mean 3 (#/total #) Name Mean3 (#itotal #) Mean 3 (#,total #) Reported' Sampled (Unit of Measurement)
Analyses, Performed1 Detection2 Actual (Max.) .
(Range) (Distance & Direction) (Range)
I (Range) Measurements Sediment Gamma Spec (6)
(pCi/kg)__,
- Co 2.02E+1 All < LLD All < LLD 0 N/A WC0 2.51E+1 2.19E+1 (1/4) Site 21 Parr Reservoir ;2.19E+1 (1/2) All < LLD 0
........... N/A 2.19E+1 to 2.19E+1 (2.7 mi SSW) 2.19E+1 to 2.19E+1 ImCs 1.86E+1 All ,c LLD All < LLD 0 (1.5E+2) 1-WCs 1.42E+1 1.02E+2 (2/4) Site 21 Parr Reservoir 1.02E+2 (2/2) 8&61E+1 (2/2) 0 (1.8E+2) (5.81 E+1 to 1.46E+2) (2.7 mi SSW) (5.81 E+1 to 1.46E+2) (7.06E+0 to 1.65E+2) 25
Table 8 (cont) - Radiological Environmental Monitoring Program Summary for 2008 Footnotes
- 1. Includes; indicator and control analyses. Site 8 Air Particulates and Air Radioiodines are included as indicators. Does not include other supplemental samples.
- 2. Values given are maximum MDA values for indicator locations calculated from the program data analyses 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 1.R/hr).
- 6. Elevated levels of 214 Pb and 214 Bi Were observed in Jenkinsville drinking water samples.
The values are not reported here because they are naturally occurring (do not originate from VCSNS) and furnish no quantifiable information of interest.
- 7. Fish include 3 groups (Bass, Bream/Crappie, Catfish/Carp.)
- 8. Elevated levels of 214 Pb and 214 Bi plus other 226Ra daughter products, and 228Ac plus other 232Th daughter products were observed in all sediment samples. The, values are not reported here because they are naturally occurring (do not originate from VCSNS) and furnish no quantifiable information of interest.
- 9. 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 Hig hest Annual Mean Medium or Pathway Type and Total Lower Lfmft f Ali Indicator trW Locaons Number of Sampled (Unit Mesuemntan" of .....
Anlyesof Number Detection' Actual Locations l n Mean2 Meano2LowertoA DitneDreio).Rae)mean; Name Mean 2 (#/total #) Men 2 (#/total #)
otNonroutine onotnReported3 3
Measur~ement and Analyses (a Repoace&rtedton Reporting Period) Performed (Max.) (#/total,) (Range) nge (Range) Measurements Air Particulate Gross Beta 4.1E-3 1.1E-1 (5621564)4 Site 13, North Dam I,3E-1 (52/52) 1.2E-1 (1531155) 0 (pCi/m 3): (1300) (!.OE-2) (1.3E-2 to 5.5E-1) (2.9 mi NNW) (2,1:E-2 to 5.5E-1) (7.9E-31to 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
- 307)
Cs 3.OE-3 All < LLD All < LLD 0 0.&10E2) . ...
13 Cs 3.1E-3 312E-3 (22/241) Site 10, Met Tower 3.8E-3 (2122) 4.2E-3 (4/66) 0 I1.OE-2) (1.5E-3 to 5.2E-3) (2.4 mi NNE) (2.5E-3 to 5.2E-3) (3.2E-3 to 5.6E-3)
Air Radioiodine 1J11 :(290) 3.6E-2 All < LLD All < LLD 0 (i982) (poi/mn)
(7.OE-2)
Direct (TLD)ý 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) 01978-1982)
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) . (13A1to 14.7)
Surface Water 0 (pCi/i) WH (43) 1.1E+3 1.4E+3 (18/29) Site 17, Columbia 1.6E+3 (2/7) 1 .2E+3 (6/14)
.(1981-1982) (2.OE+3) (1.1E+3 to 2.4E+3) Canal (24.7 mi, SE) (11.4E+3 tol.8E+-3) (6.7E+2 to 1 6E+3)
Gamma Spec Mn " 2.7E-1 All, LLD All < LLD 0 (1.5E+. ) _ ,_,_.,.
MCo 2.9E-1 All < LLD All < LLD 0 (1.5E+1)
-'Fe 6.OE+O All < LLD All < LLD 0
.3.0E-_(3.OE 1).. .i ECo 2A4E-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 ýcLLD All.< LLD 0 (1;.5E+1) ,,
wtNb 3.3E-1 All <.LLD All < LLD 0 (1.5E+1) 3.0E-1 IDCs All;< LLD . All < LLD 0 (1.5E+1) 27
Location with Hilhost Annual Mean Medium or Pathway Typo and Total Lower Limit of All Indicator Control Locations Number of Sampled (Unit of Number of oetrctionmiActuao Locations Mean2 Name Mean 2 #)
-e(total n Nonroutino Measurement and Analyses La R4 (Distance & Direction) (Range) M Range)o13 Measurements Reporting Peiod) Performed (Max(.) ( #) (Range) 0ol 13t Cs 2.2E-1 AI < LLD All < LLD 0 (1.8E+i1 1
4Ba 2,2E+O All - LLD. Al <LLD 0 La :5.5E-1 All< LLD AI < LLD 0 (1982 only) (!"5E +II ...... ...... . . ... ........... . . .
Ground Water Site 26, Onsite Well 3H (29) 9.OE+2 1.5E+3 (16/16) 1
(.6E+3 (8)8) 1,03E+3 (13/13)
(pCiAI)
(265 ft, W) (9.5E+.2 to 2.3E+3) (1.OE+3 to 1.9E+3) 0 (1981-1982) (2.0E+3) (9.5E+2 to 2.3E+3)
Gamma Spec (32) 0Mn 3.7E+O All < LLD All < LLD 0 (1.51E+1)
(3.0E+1* .
WC0 3.8E-0 All <LLD All.<LLD 0
_______________ (1.5E+!) ..... _ _ __ _ _ _ _ __ _ _ _ _ _ _ __ _ _ _ _ __ _ _ _ _ _ __ _ _ _ _ _ _
8.1E+0 All < LLD All < LLD 0 (3.OE+i) 6.8E+0 All <LLD All < LLD 0 (1.5E+11 "M 4.6E+0 All <ý LLD All < LLD 0 (1t.5E+I)
Cs 3.7E+0 All:< LLD All < LLD 0.
(1.5E + 1). , ....
GS 3.8E+0 Ali< LLD All < LLD 0
_ _1.8E + 1) 1UBa 1.9E+1 All< LLD All < LLD 0
,, (6:0E+1,)
l"uLa 5.OEO All.< LLD All<LLD All <, LLD0 (19 82 only_ _ _ _ _1:5E+1):
Drinking Waterz Gross Beta (2 OE+O)
(pCi/i) (1981-1982)
`H (14) 6.3E+2 7.8E+2 (6114) Site 28, Jenkinsville 8.4E+2 (3f7) 0 Gamma Spec (1.OE+3) , (6.8E+2 to 9.8E+2) (2.0 mi SE)7 (7.OE+2 to 9.8E+2) .....
Gamma Spec
'Mn ý3.OE-l All < LLD 0 (1.5E+1l`
'Co 2.7E-1 All < LLD 0 (1.5E+1) 28
Location with Hl-hestAnnualMean Medium or Pathway Type and Total Lower Limit o All Indicato Control Lotions Number of Sampled (Unit of Number of Iator Name Mean 2 (#/total #) Mean2#/ta) 1 Nonroutine Measurement and Analyses Actual Locations Mean (Detection& Direction)
(Distance (Range) Mnt Reported)
ReportinPeriod) Perormedl (Max.): (#/total #) (Range) (Range) MeaSurements 0
" Fe 9.6E0 All < LLD 0 1(30E+1) , ,
lCo 2.6E-1 All < LLD 0 (1.5E-t1*
3.4E-1 All D.
LLD, 0 7Zr 4.8E-1 All < LLD 0 11l1 3.4E-1 All < LLD 0
,,(1.5E+1i)
- Nb. 7.4E.1 All < LLD 0
___ ___ ___ ___ (1 .OE4.O)
-2.2E-1 All < LLD 0 97s (1.OE+I)
- .2,4&1 All < LLD 0 1
Ba 2.5E0 All .< LLD 0 (6.OE+1) _
14ULa 4A4E-1 All < LLD 0 (1982 only) (1.5E&1)
Milk Gamma Spec (pCi/I) (94)
(1981-1982) .......
-1 " 6.3E-1 All < LLD All< LLD 0 (Ii.0E+0)
I4Cs 3..3E+0 All < LLD All < LD. 0 (1.5E+1).
1
- Cs 4.6E0 4.1EE+0 (8147) Site 14, Dairy 4-!E+0 (8/47) . 5.7E+0 (37/47) 0 140 (1.5E+1) (2.8E+0 to 6.1E+0) (5.1 m.,*.'W) (2.8E+0 to 6.1E+0) (3.7EtO to 9.2E+0) ....
4Ba !1.1E+! A!!< LLD ... .. .. All < LLD 0
+15E 1,)
"'YLa 4.4E+0 AlIl< LLD All < LLD 0
..... _ _ _ _(1.5E+1)
Grass (pCi/kg wet) Gamma Spec (1981-1 982) _ _ _
6.7E+1 All< LLD All < LLD 0 (6.0E+1)
[qCs 217E+1 All <.LLD AJI < LLD 0 (8.0E+1)
Cs 3.3E+1 5.OE+1 (13/51) Site 14, Dairy, 5.9E+1 (5/29) 1.3E+2 (6/31). 0 (8.0E+i) (1.6E+1 to 1.6E+2) (5.1 mi W) (1.6E+1 to 1.6E+2), (1.3E+1 to13.4E+2) 29
Location with Hi host Annual Mean Medium or Pathway Type and Total Lower Limit of All Indicator Number of Sampled (Unit of Number of Detection' Actual Locations Mean 2 Name Mean2 (U/total #) onol Lotion Nonroutine Measurement and A.nalyses; Dtcin(Max.) cul Lctos #) (Range) (Distance & Meanma2 Direction) (Range) (#/ftotal # eprtd Measre Repora(Range)
Reporting Period) Performeda (#/total Broadleaf Gamma Spec (10).
Vegetaptin (pCi/kg wet)
(1980-1982) 141 3.7E+1 :All < LLD 0
________________ ~~~~(6.0OE+
1;) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
1.9E+1 All < LLD 0 ltCs 2.1E+1 3.1E+1 (217) Site 2, Trans. Line 3.6E+1 (1/1) All < LLD 0 (8.OE+1)l (1.8E+i to 3.6E+1) (1.2 mi SW) (Single-Value)
Other Vegetation Gamma Spec (pCi/kg wet) (32)
(1980-1982) 1 Cs 8.4E+O All < .LLD All < LLD 0
.{8,0E+1)
Cs !.0E+1 All <.ILLD All cLLD 0 (8.0E+1)
Fish (pCi/kg wet) Gamma Spec (1980 1982) Q2) 1Cs
.4E+1 All, < LLD All < LLD 0 (1.3E÷-2) 11ýC 8E+1 2.8E+i. (50M71) Site 24, Recreation 3.4E+1i (17/23) .3.1E41 (19/21) 0 (1,3E+2) (1.IE+1 to 1.0E+2): Lake (5.5 mi, N) 1.2E+1 to 1.OE+2) (1.0E+1 to 7.9E+1) 2.6,E+1 All < LLD, Ali < LLD 0 (1t.3E+2)
Mn 1.8E+1 All <c LLD All < LLD 0
_(1.3E+2)
"Fe 9:0E+1 All <LLLD. All < LLD 0
_ __ __ ___ _ _ _ __ _ _ 2.65+2;) ...... __ _ _ _ _ __ _ _ _ ___ _ __ _ _ _
rZn 4.1E+1 All < LLD. All < LLD 0 (2;6E+2)
WCO 1.8E+1 All < LLD All < LLD 0 0 _.3E÷2)
Sediment (pCi/kg) Gamma Spec (24)
(.1980-1982*) _________
(19Cs ..
.. .2.3E+1 All < LLD All< LLD 0 0.(.5E+2) ....
tCs. 2.4E+1 1.7E+2 (12/18) Site 21,:Parr 2.6E+2 (6/6) 4.2E+2 (6/6) 0 (1.5E42) (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 -
10122/82.
- 5. Detection sensitivity is approximately 5 mrem/yr (0.5 i.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 2008 Environmental Inter-comparison Program with Independent Lab, Analytics, Inc.
Comparison Study Vendor Lab Env Lab Agreement Date Nuclides Results Results, ... ..
(Measurement Unit)
Gamma Isotopic. Liquid 9/25 1311 105 122 Yes 4 Liter 141Ce 107 120 Yes (pCi/I) 51Cr 279 351 Yes 134Cs 154 156 Yes 137 CS 107 125 Yes 58 co 118 133 Yes 54 Mn 110 1.32 Yes, 59 Fe 95.6 111 Yes 65Zn 211 239 Yes 60Co 155 169 Yes Gamma Filter 10/6 Ce 141 148 Yes (pCi) 51Cr 367 355 Yes 134Cs 202 157 Yes 137 Cs 141 140 Yes 58 Co 156 158 Yes.
- Mn 59 Fe 145 165 Yes 126 148 Yes 65 Zn 278 307 Yes 60Co 204 202 Yes Alpha/Beta (pCi/i)Water 3/27 Alpha 104 110 Yes Beta 209 224 Yes Gamma Isotopic 4/1 ce 2.87E-1 2.73E-1 Yes Pulverized 51Cr 4.14E-1 3.99E-1 Yes Soil 13CS 1.44E-1 1.18E-1 Yes (pCi/g) 13 7 Cs 2..80E-1 2.74E-1 Yes 58CO 8.15E-2 8.12E-2 Yes
'Mn 1.08E-1 7.22E-2 No*
59Fe. 1.18E-1 1.22E-1 Yes 6 §Zn I.58E-1 1.43E+0 Yes 6°Co 2.72E-1 2.47E-1 Yes k1131 Solid. 3/25 'jl'1 135 1"53 Yes (pCi) 32
Comparison Study Date Nuclides Vendor Lab Env Lab Agreement (Measurement Unit) Date Results Results Tritium 5/3 H 4010 3990 Yes (pCi/I)
Gross Beta Filter 10/6 N/A 116 114 Yes (pCi)
Charcoal Cartridge 9/26 86.6 92.7 Yes (pCi)
S54Mn in the Pulverized Soil analysis did not fall within the two sigma acceptance criteria. A second analysis using another detector gave-an acceptable comparison ratio of 0.99. 54Mn is reported for sediment, in Table 8, but does not have an ODCM required maximum LLD.
33
Table 11 - 2008 Environmental Sampling Program Exceptions Sample; Month Media. Location (Week No.). Cause for Exception Direct Site 44 Oct (41) TLD missing Radiation Site 47 Oct (41) TLD missing Air Particulate Site 6 Mar (12) Breaker trip caused by storm.
And Site.,30 Mar (12) Breaker trip caused by storm.
Radioiodine Site 8 Aug. (32)ý Equipment failure.
Groundwater Site 106 Jun (26) The station has:experienced issues Site 105 Sep (38) with groundwater intrusion into plant Site 103 Sep (39) building and structures. In 2008, a Site 106 Sep (39) modification was implemented to Site 107 Dec (52) install fourteen dewatering wells. This lowered the water table in the area below the level of the existing wells.
34
T LEGEND V. CONTROL SAMPLE LOCATIONS AzAIR PARTICULATE SITE
=ObIRECT (TLD) SITE I =AIRBORNE RADIOIODINE SITE W=WATER SITE
.O='OTHER (OARDEN PROOUCTS, FISH, SEDIMENT, GRASS. MILK)
REFEAENCEs THE BASEFORTHISHAPWASPItE0PAEFROMA emfmO (j LSGS,STATE OF GEORGIA.1971L South Carolina Electric & Gas Co.
Virgil C. Summer Nuclear StUtaon Regiona.b.Location Map Figure 1-1 REV. WEl 1?.-
LEGENID SPRIMARY SAMPLE LOCATIONS .,
A AIR PARTICULATE SAMPLE S1TE 0 DIRECT (.tLD) SAMPLE. SITE IAIRBORNE ýRADIOJODINE SAMPLE SITE v*1 K[s M4TIC LLD. 2
.WTWATER SAM~PLING LOCATION . ...k 0 = OTHER Tf Dt (0) SAMPLING LOCATIONS * ,
- 1351 4_ .... Mill, 7 1 4 wb
- 4 -V 176
,4 (a> EI(~~SuhC~on Ic~i a o Jimgi NA'~ C:Sute Sot
~ cv ~~4 KI8LER'.
AIOOICL OITRNGPOGA Figur00,
4 SKINl'j unci (Alm) tl meI i'
t=ER a
'A.
135'
.4 I',
-LEGEND FIGURE: 'i-3
,%l PRIMARY SAiMPLE LOCATIONS A a AIR PARTICULATE SAMPLE SITE FIGURE. 1-3
- i ODITIUIM.NWS COVOWS04 Ic~e.i N, no COTEW.L~A1DN PM WALS.i D ' DIRECT (TLDISAMPLE SITE (QUARTERLY) X",
I AIRBORNE RAOIOIOOIINE SA*IPLE SITE
,., TO PARR-\ .W WATER' SAMPLING LOCATION O OTKER O l utui -I
t N
N CWPH 26 F)
W44~E
$ I,,
/
//
L__
- - ITR
/
'~, I' I
F-- /7/ l~I
~K N
.1 :fll //
~N N I!
.1~
~ ~ i/
I 113 .
1"12 3'"
U South Carolina Electric & Gas Co Virgil C Summer Nuclear'Station U RADIOLOGICAL MONITORING PROGRAM U SECURITY AREAGROUNDWATER SITES I
Figure 1-4.
16 LEGEND Groundwater Welis N
W+ E
,l V3/4 kuxFidler \
Iistorage
\\ I' illii¸ l * . . ..
!*iiii!ii~i
- *. i~iii~iii*'i!*iii* * -
.4 . , - -- - .
...-... iii --.-
V~.ko B~iIdh~
South Carolina Electric & Gas Co K, .1I Virgil C Summer.Nuclear Stadion RADIOLOGICAL MONITORING PROGRAM PROTETEDI AREA GROUNDWATER SITES Figure 1-5