ML030300769

Radiological Environmental Monitoring Report for 2001

ML030300769
Person / Time
Site:	Summer
Issue date:	04/24/2002
From:	Halnon G South Carolina Electric & Gas Co
To:	Reyes L Region 2 Administrator
References
Download: ML030300769 (46)

Text

April 24, 2002 M r. L. A. Reyes Regional Administrator USNRC, Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street S W Suite, 23T85 Atlanta GA 30303-8931

Subject:

VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 OPERATING LICENSE NO. NPF-12 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT (RR 8300)

Enclosed is the South Carolina Electric & GasCompany (SCE&G) Annual Radiological Environmental Monitoring Report as required by Regulatory Guide 4.8 and Section 6.9.1.6 of the Virgil C. Summer Nuclear Station Technical Specifications.

If there are any questions, please contact Ms. Susan B. Reese at (803) 345-4591.

SBR/GHH/sr Enclosures c: N. 0. Lorick (w/o enclosures) K. M . Sutton T. G. Eppink (w!o enclosuresj INPO Records Center R. J. White (w/o enclosures) J&H Marsh & McLennan G. E. Edison NSRC M . Moses (402) RTS (O-L-99-01 12-l)

J. A. On (P40) File (818.02-2, RR 8300)

NRC Resident Inspector (502) DMS (RC-02-0072)

W , G. Wendland

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPERATING PERIOD _

JANUARY I,2001 - DECEMBER 31,200l APRIL 2002 Prepared by: 1 I\

I Al William A Smith Jr., liaalth%ysics Specialist Reviewed by: Approved by:

TABLE OF CONTENTS INTRODUCTION DESCRIPTION OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LANDUSECENSUS MONITORING RESULTS AND DISCUSSION CONCLUSION

EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report describes the V.G. Summer Environmental Monitoring Program and the program results for the calendar year 2001.

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 and applicable Health Physics Procedures. Required analyses were performed and detection limits met for all required samples. One thousand thirty samples were collected comprising one thousand two hundred and twenty two analysis performed to compile the data for the 2001 Environmental Report. One hundred thirteen supplemental samples comprising one hundred sixty three 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 2001 for V.C. Summer related radionuclide concentrations were within the range of concentrations observed in the past.

Review of the data showed that radioactivity concentrations in shoreline sediment was the only indicator with activity slightly greater than the detection LLD. This concentration is less than the level reported in the past and within the limits of the ODCM. The total body dose calculated to the maximum exposed member of the public, excluding TLD data calculated from shoreline sediment data was 2.25E-2 mrem/yr for 2001. It is therefore concluded that V.C. Summer Nuclear Station operations have no significant radiological impact on the health and safety of the public or the environment.

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LIST OF TABLES TABLE PAGE 1 Monitoring Methods for Critical Radiation Exposure 3 Pathways 2 2001 Activated Corrosion Product Activity in 7 Sediment 3 Radiological Environmental Monitoring Program 8 Required Sampling Site Locations 4 Results of the 2001 Environmental 10 Intercomparison with Independent Lab 5 Results of the 2001 Intercomparison Program with 13 Independent Lab 6 Summary of the 2001 Intercomparison Program 15 with SCDHEC 7 Results of the 2001 Land Use Census Verification 16 7a Critical Receptor Evaluation for 2001 17 8 Radiological Environmental Monitoring Program 18 Specifications 9 Supplemental Radiological Environmental 22 Monitoring IO Radiological Environmental Monitoring Program 25 Summary for 2001 11 Radiological Environmental Monitoring Program 31 Preoperational (Baseline) Summary 12 2001 Environmental Sampling Program Exceptions 37

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LIST OF FIGURES FIGURE PAGE l-l Control Site Locations (50 mile radius around the 38 Virgil C. Summer Nuclear Station)

I-2 Radiological Monitoring Program Local Indicator 39 Sample Sites (5 mile radius around Virgil C.

Summer Nuclear Station)

I-3 Radiological Monitoring Program Local Indicator 40 Sample Sites (1 mile radius around Virgil C.

Summer Nuclear Station)

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INTRODUCTION Virgil C. Summer Nuclear Station (VCSNS) utilizes a pressurized water reactor rated at 2900 MWt (990 MWe gross). The station is located adjacent to the Monticello Reservoir near Jenkinsville, South Carolina and approximately 28 miles northwest of Columbia. VCSNS achieved initial criticality on October 22, 1982, reached 50% power December 12, 1982 and 100% power June IO, 1983 following steam generator feedwater modifications. Steam generators were replaced in the fall of 1994. During the ninth refuel the plant was uprated to 2900 MWt (990 NlWe gross). VCSNS is currently operating in the 13h fuel cycle.

VCSNS is operating in conjunction with the adjacent Fairfield Pump Storage Facility (FPSF) which consists of eight reversible pump-turbine units of 80 MWe capacity each.

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

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

Liquid effluents from VCSNS are released into the Monticello/Parr Reservoirs at two discharge points: the Circulating Water Discharge Canal (CWDC) and the FPSF Penstocks. Nonnuclear 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 2001. Data trends, control/indicator and preoperational/operational data intercomparisons and other data interpretations are presented.

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DESCRIPTION OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmenta! 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 beWeen levels of environmental radioactivity and radioactive effluents from VCSNS operation.

The program utilizes the concepts of control/indicator and preoperational

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

nample media and analysis sensitivity requirements have been established to ensuri ihat the maximum dose pathways are mar itored and sensitivities repress- a small fraction of annual release limits. Effluent disperskjn characteristics, demograph, hydrology and land use have been considered in selection of environmental samp,:,lg 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 radiaffon 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 VCSNY Offsite Dose Calculation Manual (ODCM). Elements of the program monitor the impa~ of gaseous and liquid effluents released from VCSNS.

Table 1 - Monitoring Methods for Crltlcal Radiation Exposure Pathways Exposure Pathway Gaseous Immersion Dose and other External Dose Area Monitoring, Air Sampling Vegetation (Ingestion) Vegetation and Food Crop Sampling, Milk (Ingestion) Milk Sampling, Grass (Forage)

Sampling Liquid Fish (Ingestion)

Water & Shoreline Exposure (Ingestion and ling, Shoreline and Immersion) ent Sampling ,,,

Drinking Water (Ingestion)

Monitoring sites indicative of plant operating conditions are generally located within a 5 mile radius of the plant. Table 8 provides a list of ODCM required sampling locations.

Table 9 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 I-3. Figure l-l shows monitoring sites at distances greater than 10 miles from the plant. These locations indicate regional fluctuations in background radiation levels.

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

Environmental data is gathered through multiple types of sampling and measurements at specific locations. Several multiple sampling combinations are in use around the VCSNS. For example, all air mmpling 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. Three of these locations have additional complementary sampling/measurement pathways for monitoring plant effluents. Sampling locations 6 (1 .O rni ESE) and 7 (1 .O 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. Sampling location 18 (T6.5 mi 9) serves as a control location for direct radiation and garden monitoring.

Liquid effluents are monitored using three different monitoring media (fish, bottom sediment and surface water) at the two most probable affected bodies of water around the plant: Site 21. Parr Reservoir (2.7 mi SSW) and Site 23, Monticello Reservoir (0.5 mi ESE). The control location for liquid effluent comparisons is at Site 22, Neal Shoals (26.0 mi NNW) on the Broad River.

Quality of analytical measurements is demonstrated by participation in a laboratory intercomparison program. Results of the intercomparison program with an outside vendor and VCSNS Count Room are included in Table 4 and Table 5. The intercomparison program with South Carolina Department of Health and Environmental Control (SCDHEC) is outlined in Table 6. Results are reported by SCDHEC. The results of each of these three quality control checks of the Radiological Environmental Monitoring program verify the technical credibility of analytical data generated and reported by the program.

The Radiological Environmental Monitoring Program described in Tables 8 and 9 incorporates afl the elements of the VCSNS ODCM and includes numerous supplemental sampling locations.

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 2001 are included in Table 7. A verification of the maximum exposed individual location is presented in Table 7a. Identification of the Clighest offsite dose locations was performed by calculating a hypothetical dose based O:I predicted VCSNS source term from the Operating License Environmental Report which is higher than actual source terms and current 5 year average meteorological data. Exposure pathways used in the analysis were those identified during the land use census.

During the 2001 land use census, the location and pathway presently used in the ODCM for offsite organ dose calculations (E 1 .I miles - residence/garden - beef - goat) was found to have a calculated dose of 2.9E+O mrem/yr. In addition, the ODCM required environmental gardens (E I .O and ESE 1 .O miles) were found to have a calculated dose of 3.71 and 2.34 mrem/year which are higher calculated doses than garden locations of all real individuals. There were no milking animals or dairy activity found within 5 miles of VCSNS. Therefore, changes to the ODCM gaseous effluent calculations or garden sarnple locations are not indicated.

MONITORING RESULTS AND DISCUSSION The results of the Radiological Environmental Monitoring Program for 2001 are summarized in Table 10. For comparison, preoperational data are summarized in Table

11. During 2001, the Radiological Environmental Program attained a program compliance rate of approximately 98.6 %. A listing of program exceptions and their respective causes are included in Table 12. Analysis of the impact of these omissions verified that program quality has not been affected.

Airborne gross beta activity measured in air particulate samples collected at indicator locations around VCSNS were consistent with preoperational levels and no!

statistically different from control locations. Mean preoperational indicator and all IX ~:roI levels were 2.7E-2 and 2.8E-2 pCiim3, respectively. Mean indicator and control loc;,en measurements during 2001 were 2.18E-2 and 2.03E-2 pCi/m3, respectively.

The highest site specific mean activity (2.40E-2 pCi/m3) was measured at indicator location no. 7 ( Env. Lab Garden 1 .O E ). A comparison was performed between the 2001 results and the mean for the previous operational results. No statistically significant trends were observed. The results indicate that operation of VCSNS has not resulted in detectable increases of airborne gross beta activity in the environment.

Gamma spectroscopy measurements of air particulate samples and activated charcoal cartridges support the gross beta activity trend. Only natural background activities of Be %Ra and 9< were detected. The highest minimum detectable activity (MDA) levels for%s 37Cs and 13I were 1.85E-3, 2.03E-3 and 1.68E-2 pCi/m3, respectively. The average ma&urn results support the gaseous effluent release data reported in the 2001 Annual Effluent and Waste Disposal Reports for VCSNS. No measurable iodine or particulate were released.

Environmental dosimetry measurements during 2001 did not differ significantly from preoperational measurements. Indicator and control dosimetry measurements also showed no appreciable differences during 2001. Comparfson with other operational years shows no statistically significant difference. Sampling location no. 55. St. Barnabas Church ( 2.8 miles E ). was the indicator location showing the highest mean exposure rate of l.l9E+l @/hr. This value is slightly higher than in 2000 of l.l6E+OI @hr and consistent with the highest mean exposure rate of 1.4E+l pR/hr measured during the preoperatfonal period. Gaseous effluent release data reported indicated that no measurable fission and activation gases were released from VCSNS in 2001.

Gamma spectroscopy measurements of surface water samples did not indicate the presence of activated corrosion or fission products above the respective MDAs Measurements of surface water for trftium did not indicate any measurable concentration above MDA. The maximum MDA for surface water tritium at all indicator and control sites was 5.23E+2 pCi/l.

Gamma spectroscopy measurements of ground water samples did not indicate the presence of activated corrosion or fission products above the MDAs for the respective radionuclides. Trftium analysis did not indicate the presence of any tritium above the detectable levels. The maximum MDA for tritium at all indicator and control sites was 5.23E+2 pCi/l.

Gamma spectroscopy measurements of drinking water samples collected from the Jenkinsville and Columbia water supplies did not indicate the presence of activated corrosion or fission product activity above the MDAs of the respective radionuclides.

Naturally occurring radionuclides, 226Ra, 14Pb and 14Bi, were observed in the Jenkinsville water supply (site #28) at levels above those found in surface water. These elevated activity levels were also observed in the preoperational program and are attributed to several deep-water wells. The supply for Jenkinsville community water is located more than 5 miles fmm VCSNS.

The highest mean gross beta activity in drinking water was measured at site 28 (Jenkinsville) at a level of 2.94E+O pCi/liter. There was no detectable tritium in drinking water samples. The maximum tritium MDA value is 4.81 E+2 pCi/liter. The result compares to a preoperational mean of 7.8E+2 pCi/iiter.

There were no milk samples collected in 2001. Milk sampling is required to be performed at the three highest dose locations (> 1 mrem/year) within 5 miles of the piant.

Presently there are no locations meeting the criteria for indicator dairies.This reflects the reduction of control/indicator locations. Controls are in place where milk samples will be obtained 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, air samples at concentrations greater than required LLDs or within 5 miles of the plant..

Grass samples collected from indicator sites 2 and 7, with control site 18. Site 2 indicated 37Cs in 9 of 12 samples at concentrations ranging from l.O5E+l to 4.24E+l pCi/kg, below the maximum preoperational control activity of 3.4E+2 PC/kg. A review of site #2 air sample results indicated that no 13Cs was detected during 2001.

Broadleaf vegetation collected from gardens at location numbers 6, 7 and 18 were the principal food products analyzed during 2001. The highest minimum detectable activity (MDA) levels for 4Cs, 37Cs and 131were 1.44E+l, l.SSOE+l end 1.70E+l pCi/kg, respectively. No activation or fission products detected.

Other vegetation sampled in 2001 included corn, tomatoes and turnips representing the non-leafy vegetation group. No radionuclides were detected other than naturally occurring. Naturally occurring nuclides were observed in all samples at concentrations consistent with those observed during the preoperational period.

Fish species sampled at two indicator and one control location included bass, bream, catfish and carp. 37Cs was defected in lof 12 samples collected at indicator locations ( site 21 Parr Res. ) at a concentration of l.O7E+Ol pa/kg. At the control location (Neal Shoals, 26 mi, NNW) the 37Cs concentration were at MDA levels. Since the maximum MDA levels of 13Cs in fish at control location ( 1.74E+l pCi/kg ) and indicator location ( 1.49E+l pCi/kg ) are about the same but less than preoperational concentrations, the 13Cs radioactivity is attributed to residual fallout.

Gamma spectroscopy measurements of sediment samples collected during 2001 resulted in detection of 6oCo that is attributed to VCSNS operation. 6oCo was detected in two samples taken at the Discharge Canal at Lake Monticello (Site 23) and one sample at Parr Res. (Site 21) at mean concentrations of 2.26E+l and 1.21E+l pCi/kg, respectively.

37Cs was detected in all four indicator samples at a mean concentration of 1.47E+2 pCi/kg. The mean 37Cs concentration at the control location (Site 22) is 1.64E+2 pCi/kg, which is about the same as the mean indicator activity. Since the levels of 13Cs at the control location are about the same as the indicator locations, the Cs radioactivity is attributed to residual fallout. Note that preoperational mean level at control locations was 4.2E+2 pcilkg.

Radiation doses to man, corresponding to the concentrations of activity in sediment, were calculated using Regulatory Guide 1.109 methodology. A 500 hour/year ex osure to shoreline sediment containing maximum and mean concentrations of Co, and PCs, a shoreline width factor of I, and a sediment mass of 40 kg/m2 was assumed. The results are included in Table 2 and show a maximum dose to the public from contaminated sediment to be 2.25E-2 mrem/yr ( Co and 13Cs ) for 2001 based on sediment samples from Monticello Reservoir. This dose is conservative because 37Cs is used in the dose calculation when actually only 9.45E-3 mremlyr (%o) is from VCSNS.

Table 2 - 2001 Fission and Activated Corroslon Product Activity in Sediment Corresponding Calculated Annual Dose Equivalent Location Radionuciide Activity (pCilkg) (mremlyr)

. Total Body Monticello Maximum Fu lean MaXimum Mean Reservoir To 2.78E+l ,1 3: -.16E+l 9.45E-3 768E-3 (Site 23) %s 1.55E+2 , I.-19E+2 1.30E-2 1.25E-2 I Total I _-_ 2.25E-2 2.02E-2 Parr eocrm,ir bW,T 1 9 ?lE+l 1.21E+l 4.1lE-3 4.11E-3 I, i6E+2 1.46E+2 1.31E-2 1.23~~2

-- 1.72E-2 1.64E-2 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 fish and sediment.

No detectable fission or activation product activity attributed to VCSNS operation was observed in environmental media except for sediment samples from Lake Monticello and Parr Reservoir. The dose from sediment represents a small fraction of the observed variation in natural background and a small fraction of VCSNS effluent dose limits. The absence of an impact was expected since, historically, releases from VCSNS have been a small fraction of ODCM Specification limits. The dose calculated for the maximally exposed individual will not result in observable effect on the ecosystem or general public.

The results of the Radiological Environmental Monitoring Program, therefore, substantiate the continuing adequacy of source control at VCSNS and conformance of station operation to 10 CFR 50, Appendix I design objectives.

Table 3 - Required Sampling Site Locations 1 Dis$a~z 1 Direction 1 Sample Type(s) 1 3HWyYY 4.2 NY.,

w+h nnm 2.9 333 14 1 Dairy (Shealyr 6.5 277.OW 1i 22.0 ram neservoir 2.7 199.5 ss 1rHwy213 I 4.2 W3.U tNl

..,.....xthofHwy60 4.9 1 111.0 E!

14.u I 1 3.8 I 1 42 Broad River Rd (Residence Peak) 3.8 11 43 Hwy 176 and Rd 435 5.2 44 Rd 28 at Cannons Creek 2.8 45 Rd 33 at Pomaria 5.8 L3J.L 46 Rd 28 at Hell&s Creek 3.7 291.5~.~...

47 1 Fairfield Tailrace 1.0 316.0 NY 52 1 fvlonticello (Rd 11) 3.8 13.0 NNc Table 3 (Cont.) - Required Sampling Locations Distance given is the distance between the site location and the VCSNS reactor containment building.

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

Sample Types:

AP = Air Particulate 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)

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

Site 18 cunsists of 2 locations in close proximity to Lake Murray. Garden product samples are taken at the Wyse residence. The TLD is located on Pine island.

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.

Site 30 air sampler and TLD though not in line of sight are located in the same sector.

Table 4 results of 2001 Environmental intercomparison Program with Independent Lab, Analytics, Inc.

Comparison Study Qtr. Env Lab Agreemen (Measurement Unit) Results Gamma Isotonic 53 Yes Composite First 154 Yes Air Filters 117 Yes

@CO 120 Yes 136 Yes Gamma Isotopic Liquid 89 Yes 137(5 210 217 4 liters First Yes (pCi/l) tiMn 161 169 Yes 65Zn 156 159 Yes

@co 194~ 201 Yes Gross Beta Filter First N/A 66 61.4 Yes (pCi) -I_

Gamma Isotonic --iqe;- 0.270 0.253 Yes Sediment Second %r 0.372 0.364 Yes Density = 1 gmkc 13ks 0.222 0.207 Yes WW 13CS 0.328 0.358 Yes

%o 0.160 0.149 Yes Mn 0.250 0.245 Yes

• Fe 0.145 0.148 Yes qn 0.301 0.322 Yes wo 0.224 0.235 Yes Gamma Isotopic Liquid 9 79 - Yes 1 liter Second l4Ce 27344 237 Yes (pCi/l) 51Cr 322 332 Yes 3dcs 193 173 Yes 37cs 174 194 Yes

%o 139 143 Yes 54pAn 216 232 Yes 5gFe 126 136 Yes 65Zn 261 276 Yes 6OCo 194 208 Yes

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i-__-----I-Table 4 (Cont.) Results of 2001 Environmental Intercomparison Program with independent Lab, Analytics, Inc.

I Qtr.-- l-Nuclidez Vendor Env Lab Agreement Lab Results Results Alpha/Beta Liquid Second N/A 35 248 139 100 ml Jar Second 100 99 Yes

=I Second JH 7494 7170 Yes Third NIA 35 37.5 - Yes 248 --

Third 7494 +-

- I Tz- 193 175 YC?S Third 3CS 174 178 Yes 54Mn 216 240 Yes s5Zn 261 277 Yes

%o 194 212 Yes I

Gamma Isotopic 34cs 0.22?---

Sediment Third 3cs 0.328 Density = 1 gmicc %Mn 0.250 0.240 Yes WW Zn 0.301 0.339 Yes Oco 0.224 0.221 Yes

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Fourth 131 92 97 Yes Fourth N/A 57 57 Yes (pCi) -- -

Gamma Isotopic %e 225 Yes Composite Fourth %r 295 Yes Air Filters cs 118 Yes (PC0 -cs 281 Yes 58co 54 Yes 54Mn 88 Yes Fe 60 Yes I .-~----_-.- @Zn vo 122 362 Yes Yes

Table 4 (Cont.) Results of 2001 Environmental Intercomparison Program with Independent Lab, Analytics, Inc.

Cornparis& Study Qtr. auclides Vendor- Env Lab- Agreement (Measurement Unit) Lab Results

_ Results -- --

Gamma Isotopic Rock Ce 0.482 0.458 Yes Density =I .5 gm/cc Fourth %r 0.631 0.582 Yes pCi/g 34Cs 0.252 0.185 Yes 37cs 0.531 0.496 Yes 58co 0.115 0.120 Yes 54Mn 0.189 0.182 Yes 5gFe 0.129 0.132 Yes

%In 0.262 0.259 Yes

%o 0.449 0.431 Yes Gamma lsoto& Liquid -T--- 101 Yes 4 liters Fourth r4Ce :i?t 234 Yes (pCi/l) 51Cr 293 285 Yes

%s II? 108 Yes 37cs 188 200 Yes WO 53 61 Yes

%Mn 88 92 Yes 5gFe 60 65 Yes

@Zn 122 130 Yes To 209 211 Yes 1 Low due to coincidence summing. Note that %s in 4 liter sample is affected less by coincidence summing than in smaller close samples.

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Table 5 - Results of the 2001 Intercomparison Program with Independent Lab Qtr. Nuclides Env Lab iecond Lat igreement Results Results jecol Id 5H 1.42E-03 1.77E-03 Yes Gem

- Id N/A 1.40E-04 1.45E-04 Yes iecol Id We a.43B03 8.27E-03 Yes Cr 1.3OE-02 1.29E-02 Yes 34cs 3.lOE-03 3.39E-03 Yes

=cs 3.19E-03 2.99E-03 Yes sac0 3.40E-03 3.31E-03 Yes

%Mn 4.32E-03 3.99E-03 Yes 5QFe 4.01 E-03 3.65E-03 Yes 0SZn 5.39E-03 4.92E-03 Y0s

@co 3.55E-03 3.37E-03 Yes jecol nd Ce 4.85E-02 5.02E-02 Yes lCr 7.61 E-02 7.83E-02 Yes WCs 166E-02 2.06E-02 Yes

$Cs 1.87E-02 1.81E-02 Yes 5aco Z.OOE-02 2.01 E-02 Yes 5Mn 2.57E-02 2.42E-02 Yes 5gFe 2.42E-02 2.22E-02 Yes 65Zn 3.27E-02 2.98E-02 Yes

%o 2.06E-02 2.04E-02 Yes Gross Alpha Planchet jecol Id N/A 1 .OOE-03 Q&SE-04 Yes 1 The Second (Independent) Laboratory was Analytics, Inc. for 2001.

2 Results originally reported using incorrect units resulting in non agreement, when corrected results are in agreement.

Table 5 - Results of the 2001 Intercomparison Program with Independent Lab Qtr. Nuclides We j-izJcTr Env Lab Second La! A$, .;ement

-0urt I Cr 7.16E-02

%s 1.24E-02 37cs 2.49E-02 920 9.31E-03 Mn 1.29E-02

--I-5gFe 1.4E-02 65Zn 1.93E-02

%o 2.67E-02

%Xe 7 ourth *5Kr 88 33Xe a5Kr 5-i 33Xe 7 85Kr 86

=Xe 7 5Kr a7

-ourth

-ourth

ourth H undis Yes 3H dist Yes The Second (Independent) Laboratory was Analytics, Inc. for 2001 except for VCSNS tritium intercomparisons.

Fourth quarter results not available. Results will be provided when received from Analytics Inc.

Table 6 -Summary of 2001 intercomparison Program with South Carolina Department of Health and Environmental Control I I I Vegetation (pCi/kg) No. 6 Semiannually Mixed Gamma 1 Intercomparison results were not yet available for publication in this report.

Results will be reported by SCDHEC.

2 Sample from Site 21 was substituted in October due to lack of availability of Bass at Site 23.

Table 7 - Results of the 2001 Land Use Census Verification (A) CHANGE IN CLOSEST RESlDENCE (Et) CHANGE IN CLOSEST GARDEN (C) CHANGE IN CLOSEST BEEF CATTLE Table 7a - Critical Receptor Evaluation for 2001 NAME 1 SECTOR 1 MILES 1 PATHWAY 1 X/Q 1 D/Q I DOS& I mRemly Kelly Baulware S 3.6 Res, Gar 9.1758 4.28E-10 l.lZE-1 Shirley Counts S 5.0 Res, Gar, B 4.64E-8 2.06E-10 7 AR!=.,

lice Cawley ssw 3.3 Res 1.29E-7 7.55E-1 O-Nora Wicker Marvin Miller 3.71E+O 2.90EtO Res. Gar 2.89E-6 8.46E-9 2.33wo

._ Rare

.--, Gnr

--. 2.64E-6 8.62E-9 2.34E+O ESE 1.1 Res, Gar ZIOE-6 6.72E-9 1.83E+O ESE 5.0 Res. Gar, B 8.90E-8 1.94E-10 7.53E-2

_- - SF 44

• Fees, Gar 7.17E-7 2.69E-9 7.19e-1 rn Robertson 1 si I 4.7 I Res, Gar, B 1 6.18G8 1.70E-10 6.41E-2 SSE 1 2.5 Res, Gar 1 1.44E-7 6.28E. .I0 / 1.66E-1 1 Pathways:

Res = Residence B = Beef G= Goat Gar = Garden C/M = Cow/Milk (Infant)

Footnotes:

1 Maximum exposed individual.

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

x/Q and D/Q were derived from ODCM &year average meteorological data

f. ODCM required environmental gardens, Table 8 - Radiological Environmental Monitoring Program Specifications A) 3 Indicator samples to be Continuous sampler Operation Gmss bata fmwing mter with weekly coilecfion.

composite (by locatIon) for gamma isotopic.

C) 1 Indicator sampk to be Grms beta following fifkr taken at the of one composite (by location) for gamma isatopk.

Gross beta following filter change: cla*erfy composite (by location) for gamma isotopic.

Continuous sdmpkr operation 6 Gamma Isotopic for wilh weekly cNliSter Cdieclion. Iodine 131 weekly.

N/A Direct

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Table 8 (Cont.) - Radiological Environmental Monitoring Program Specifications Gamma isotopic monthly ivivl quarterlycomposne (by locatio) to be analyzed or triuum Bamma iso*opicmonthly nim qusrteily nmpasita

by location) to be ana@&

br tritium.

Gamma !sotopic monthly tith quarterly composite (by location) to ba analyzed ior IrifiUrn.

,) 2 Indicator samples to be taken within the exdusion boundary and in the direction of potentially amcted ground water supplies.

I) 1 Control ~mplelrom Gamma isotopic and trttium unsffaded location mslyses quarterly.

,) I hdicator semple lrom a nearby public ground water supply SOrce.

\nonthlQ gamma isotopic.

and gross beta and quarterly composite for trilium ansiyses.

Monthly gamma isotopic, Bd gross beta and quarterly compa*ite tar tritium analyses Table 8 (cont.) - Radiological Environmental Monitoring Program Specifications

\

i

/ ,

6) 1 Conlml sample to be takan Semimonthly when animals 16 Gamma isotopic and 1.131 at the lxstion of a dairy s SPBon pasture. monthly other analyds semImonthlya 20 miles dirtance and IW* in times5 when animals are on the most prevalent wind ps*ture. manmly other directton. time2 C) 1 ,dicatorgrsss (forsgs) Monthly tied available5 To be Gamma isotopic.

sample to be taken at the supplied location of one of the dairies when milk being sampled meeting the animsk are crtteria of V,,(A).above. found in when Bnimak are on pnsture accordance with critaria II.A.

D) 1 Contm, grass (fcnags) sample to be taken at the 16 Gamma isotopic.

tomtim of VII(B) above.

111.Food A) 2 Samples of broadleaf Monthly when available. 6 Gamma isotopic on edible Product* vegetation grown in the 2 7 pPLi0.

nearestofbite location of highest calculated annual average ground level OK! if milk sampling is no, performed withln 3 &m or if milk sampling is not performed at a location within S-6 km *em the doses are calculated to be greater than 1 mmlyr, BJ 1 Contml sample for the Monthly when available. 18 Gamma isotopic on edible same foods taken at least 10 pWU0.

miles distance and nd in the most prwatsnt wind direction tf milk sampling is not perfamed within 3 km or if mitk sampling is not performed at a locatica within 5 to 8 km where the doses are calclsted to be greater than 1 mreliyrQ

Table 8 (cont.) - Radiological Environmental Monitoring Program Specifications A) 1 Indicator sample to be taken st B location in the upper rasermir.

B) 1 Indicator sample 10 be 213 Gamma isotopic on edible taken at a location in the potions semiannually9.

lower mservoir.

2P Gamma isotopic on edible portions semiannually*.

river sufficiently far upstream such that no ekcts of pumped sfomge operatIm are anticipated 231 Gamma isotopic, S) 1 Indicator swnple to be Semiannual gfab sample. 21 Gamma isotopic.

take on or near the shoreline Of the blver rewvoir. 1 river sufmsntly far upstr&

such that no elf*& Of PnlPed *rage operation are anticipated FOOTNOTES

1. Reserved for future Use.

2. Sample site locations are based on 5 yearavergge 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 sampI@%

4. Milking animal and garden survey results will be analyzed annually. Should the survey indicate new dairying activity the owners shall be contacted with regard to a contract for supplying sufficient samples. If contractual arrangements can be made, site(s) will be added for additional milk sampling up to a total of 3 Indicator Locations.

5. Not to exceed 35 days.

6. Time composite samples are samples which are collected with equipment capable of collecting an aliauot at time intervals which are short Ce.o. ,I~ houdv)_. relative to the comoositina I.~~~~~~~.

oeriod.

7. Atleast once par 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.

Table 9 - Supplemental Radiological Environmental Monitoring S-l. Particulate A) 1 Indicator sample Continuous sampler monitoring the nearest operation with weekly community with the highest anticipated dose or ground level concentration.

Gamma isotopic for I-3-111. Direct 5 stations to be placed Quarterly exchange; two Gamma dose within tha exclusion or more dosimeten at each locatton.

B) 2 Stations to be placed Quarterly exchange; two amund VCSNS sludge or mcwe dosimeters at each location.

Gamma isotopic and wastewater discharge.

1 Indicator sample taken Daily sample with Gamma isotopic and monthly composite.

S-V. Groundwater A) 4 Indicator samples to be taken at NPDES monitoring wells.

1 control sample to be taken at NPDES monitoring welk.

Table 9 - Supplemental Radiological Environmental Monitoring Exposure Pathway Crlterla for Selection of Sampling and Sample Type & Frequency oi and/or Sample Sample Number & Location B Location Analysis INGESTION:

S-VII. Milk 0 1 Sample Worn one of the 14 Gamma isotopic and I.

nearest affected dairies at 131 analysis biweekly.

or beyond 5 miles.

1) 1 Control sample to be 'I6 Gamma isotopic and I-taken at the location of a 131 analysis biweekly.

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

) 1 Indicator grass (forage) Monthly when 14 Gamma isotoptc.

sample to be taken at the available.

location of S-VII(A) above.

1) 1 Control grass (forage) Mdnthly wh@n 16 S-VII. Milk4 av$lable.

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

i) 2 Indicator grass (forage) Monthly when available.

samples to be taken at 2 Gamma isotopic of the locations beyond but as doss to the exclusion boundary as practical where the highest offsite sectorial ground level concentra-tions are anticipated.

) 1 Control grass (forage) Monthly when available, 18 sample to be used for Gamma isotopic.

routine monitoring slang with S-IV(E) above.

j-VIII. Food ,) 1 Indicator sample of Anwatly during growing Gamma isotopic on Products various types of foods se~so. edible portion.

grown in the area SW rounding the plant (root.

fruit, grain).

!-0OTNOTES

1. Reserved for future use.

2. Reserved for future use.

3. Reserved for future use.

Table 9 (cant) - Supplemental Radiological Environmental Monitoring

4. Milking animal and garden survey results will be analyzed annually. Should the survey 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.

IO. Reserved for future use.

11. At least once per 400 days.

12. Reserved for future use.

13. Weekly, when circulating water is not operational.

14. Milk and grass (forage) sampling is not required unless VCSNS gaseous releases exceed 5% of quarterly organ dose limits or radionuclides (attributed to VCSNS operation) are detected in broadleaf vegetation, grass or air samples at concentrations greater than required LLD. Sampling should continue for 2 months after plant releases are reduced to less than trigger levels and milk contamination levels have returned to background levels.

t Reserved for future use.

+ The ODCM requires semimonthly sampling when animals are on pasture, monthly at other times.

Table IO - Radiological Environmental Monitoring Program Summary for 2001 LocaUon u,th Hlghast Annual Mean Number of Lower Limi, All lndlsalw Locatl~nm Control Lowdians NOnrWtii Of Mead (#blal W) N2lm Mean (#h&l #) Mean Wblal W) Rep&d tletectial (R=w) (Distance P Direction) w-w NW Measurement Adual (Max.

• MOE-3 Z.lEE-2 (253,253) Site 7 Environmental 2.40E-2 (W52) 2.03E-2 (5252) 0 (i.OE-2) (5.91E.3 to 1.96E-1) Lab Garden (9.06E-3 IO l.%E-1) (7.88E-3 to 3.42E-2)

(1.0 mi E )

Air Radioiodine Jl (305)

(pCim)

Direct (TLD) Gamma(l35)

(NW Quarterly Gamma(24)

Special hlteresl surfac.e water H (36)

(pcill) N/A Gamma Spec(36)

%n 1.88E+O Table 10 (Cont.) - Radiological Environmental Monitoring Program Summary for 2001 Sampled (Unil of Measurement) surface water (Continued)

Ground Water (pCi/l)

Table IO (Cont.)- Radiological Environmental Monitoring Program Summary for 2001 Table 10 (Cont.)- Radiological Environmental Monitoring Program Summary for 200 1 Location with HI best Annual Mean Number of T Contml Locations Mean (#/total #]

(Ransal NOflWditl~

Reported lksuremant 3.11E+i All < LLD All c LLD 8.OE+l 2.57E+l All < LLD All < LLD (6.OE+l) 3.6oE+l 2.54E+l (9124) Site 2 Env. Lab 2.54E+1(9/12) All < LLD

&OE+l l.O5E+l to 4.24E+i Garden (1 mi ESE) (l.O5E+l to 4,24E+l) i All < LLD All < LLD All c LLD I

l.l5E+ 1 All < LLD All < LLII All < LLD All z LLD All c LLD AlcUD All c LLD 0 Table IO (Cont.)- Radiological Environmental Monitoring Program Summary for 2001 Location with Highest Annual Mean Number of Medfum or Lowsr LlmR All lndloator Locations NonroutIne Pathway of Mean (u\otal e NaIlI Md (wtotal#) Report&

sampled (unit of Dei.?ctlon2 IRWP) (Distance a Direction) Nwl Mesaurement Meamment) Actual (Max.)

Fish (Cant) 1.84 E+l All < LLD N/A b;CO i.%E+l 1.91E+l (3/4)

N/A (1.2lE+l to 2.78E+l)

I t t CS 1.65E+i All < LLO (1.5E+2)

% r 1.47E+2 (4/4)

(1 .BE+2) (1.36E+2 to 1.56E+Z)

Table 10 ( cant ) - Radiological Environmental Monitoring Program Summary for 2001 Footnotes 1 Includes indicatir and control analyses. Does not include supplemental samples. Site 8 Air Particulates and Air Radioiodines are i,ncluded as indicators. All supplemental sample results were consistent with the tabulated results shown.

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 .O pR/hr).

6. Elevated levels of *14Pb and 14Bi were observed in all 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 24Pb and 24Bi plus other Ra daughter products and *AC 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. MaXiMUm MDA from control location used.

f All measurements had positive results, no MDA values calculated.

- 30 .

Table II- Radiological Environmental Program Preoperational (Baseline) Summary LocatIon ,v,th Hi@

Medium or Pathway Type and Total Lower Lift All Indicator Control Locations Sampled @Jnttof Numb of of Detecuon L0CaUOM Name (Distance 8 Mew+ (#tOtal a)

Nleasurement and Analyses Actual [Max.) Mesn (#/tOtal rr) DIrection) (Raw@

Reporting Period) P&omred IRange)

Air Patiiulate Gross Beta 4.1 E-3 1 .lE-1 (562/564) Site 13. North Dam 1.3E-1 (52/52) 1.2E-1 (153055)

(pciln?, (1300) (1 .OE-2) (1.3E-2 to ME-I) (2.9 mi NNW) (2.1E-2 to 5.5E-1) (7.9E-3 to 6.1E-1)

(1981-1982) 2.7E-2 (4561462) Site 8, Mon. Res. S of XOE-2 (42142) 2.8E-2 (125/126) ti- (9.3E-3 lo ME-21 I Rd 224 (1.5 ENE) (i.ZE-2 to &OE-2) (1.2E-2 to 5.8E-2)

Gamma Spec (307)

I %S 3.OE-3 All < LLD All < LLD 3.2E3 (221241) Site 10, Met Tower 3.8E-3 (2/Z%) 4.2E-3 (4166)

(IX-3 to 5.2E-31 (2.4 ml NNE) (2.5E-3 to 5.2E-3) f3.2E-3 to 5.6E-3)-

All c LLD All < LLD 9.9 (915/915) Site 13. North Dam 13.1 @l/61) 9.7 (305/305)

(6.7 to 14.7) (2.9 mi NNW) (12.2 to 14.2) (6.4 to 13.5) 10.2 (154/k%) Site 55, St. Barnabas 14.0(7/7)

I 16.8 to 14.7) Church (2.8 mi E) (13.1 to 14.7) 1.4E+3 (W29) Site 17, Columbia 1.6E+3 (2/7)

(l.lE+3 to 2,4E+3] Canal (24.7 mi. SE) (1.4E+3 to1,8E+3L

Table 11 (Cont.) - Radiological Environmental Program Preoperational (Baseline) Summary 0

0 0

0 0

(9.5E+2 to 2.3E+3)

Table 11 (Cont) - Radiological Environmental Program Preoperational (Baseline) Summary Table 11 (Cont) - Radiological Environmental Program Preoperational (Baseline) Summary (UnItof Number oiAalyses Measurement and Pscformed Reporting Period)

Milk Gamma Soec 1

i

Table 41(Cont.) - Radiological Environmental Program Preoperational (Baseline) Summary La -..-. . . est Annual Mea I 1 Numberof Medium or Palhwav Lower Llmn All Indicator Sampled (Unit of I Messurment ?md Reporting Perlod~

OtherVegetation (PCtM wt)

Sediment (pCilkg) Gamma Spec (24)

(1980-1982)

CS 2.3E+l All < LLD All < LLD 0 (15E+2)

• CS 24E+l l.fE+2 (lUi6) site 21, Parf ME+2 (6I6) 4.2E+2 (616) 0 (15E+2) (2.6E+l to 4.5E+2) Reservoir (2.6E+l to 4SE+2) (1.8E+l to 1 .OE+3)

(2.7 mi, SSW)

Table 11 (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 l/1/82 -

10122182.

5. Detection sensitivity is approximately 5 mrem/yr (0.5 pWhr) determined from the analyses of five years of preoperationaf data.

6. No control location was specified for drinking water during the preoperational monitoring period.

7. Inconclusive data.

- 36 -

Table 12 - 2001 Environmental Sampling Program Exceptions Sample Month Media Location (Week No.) Cause for Exception Site 7 March (12) Storm caused power outage Air Site 2 July (28) Fire ants in breaker site 7 August (33) Storm caused breaker to trip Site 2 August (34) Suspected high motor current

• Site 2 August (35) Suspected high motor current

• site 7 August (35) Suspected high motor current

• Site 7 August (38) Fire ants in receptacle Site 7 March (12) Storm caused power outage Air Site 2 July (28) Fire ants in breaker Radioiodine Site 7 August (33) Storm caused breaker to trip Site 2 August (34) Suspected high motor current

• Site 2 August (35) Suspected high motor current

• Site 7 August (35) Suspected high motor current l Site 7 August (36) Fire ants in receptacle Direct Site 9 September (39) TLD stolen from site Radiation

• Problems with air sampler sites although suspected to be motor related turned out to be fire ants in the receptacles. Once the Electrical Dept. cleared ants and sealed receptacle boxes the problem stopped.

N i

,.