ML030300769
| 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 Mr. L. A. Reyes Regional Administrator USNRC, Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street SW Suite, 23T85 Atlanta GA 30303-8931
Dear Mr. Reyes:
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)
T. G. Eppink (w!o enclosuresj R. J. White (w/o enclosures)
G. E. Edison M. Moses (402)
J. A. On (P40)
NRC Resident Inspector (502)
W, G. Wendland K. M. Sutton INPO Records Center J&H Marsh & McLennan NSRC RTS (O-L-99-01 12-l)
File (818.02-2, RR 8300)
DMS (RC-02-0072)
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:
INTRODUCTION TABLE OF CONTENTS 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.
_i.
LIST OF TABLES TABLE 1
2 3
4 5
6 7
7a 8
9 IO 11 12 Monitoring Methods for Critical Radiation Exposure Pathways 2001 Activated Corrosion Product Activity in Sediment Radiological Environmental Monitoring Program Required Sampling Site Locations Results of the 2001 Environmental Intercomparison with Independent Lab Results of the 2001 Intercomparison Program with Independent Lab Summary of the 2001 Intercomparison Program with SCDHEC Results of the 2001 Land Use Census Verification Critical Receptor Evaluation for 2001 Radiological Environmental Monitoring Program Specifications Supplemental Radiological Environmental Monitoring Radiological Environmental Monitoring Program Summary for 2001 Radiological Environmental Monitoring Program Preoperational (Baseline) Summary 2001 Environmental Sampling Program Exceptions PAGE 3
7 8
10 13 15 16 17 18 22 25 31 37
- Ill -
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 Sample Sites (5 mile radius around Virgil C.
Summer Nuclear Station) 39 I-3 Radiological Monitoring Program Local Indicator Sample Sites (1 mile radius around Virgil C.
Summer Nuclear Station) 40
- 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 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.
-l-
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 Gaseous Liquid Exposure Pathway Immersion Dose and other External Dose Vegetation (Ingestion)
Milk (Ingestion)
Fish (Ingestion)
Water & Shoreline Exposure (Ingestion and Immersion)
Drinking Water (Ingestion)
Area Monitoring, Air Sampling Vegetation and Food Crop Sampling, Milk Sampling, Grass (Forage)
Sampling ling, Shoreline and ent Sampling 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 13 I 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 131 were 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 P osure to shoreline sediment containing maximum and mean concentrations of Co, and Cs, 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.
Location Monticello Radionuciide Activity (pCilkg)
Maximum Fu lean Corresponding Calculated Annual Dose Equivalent (mremlyr)
Total Body
. 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 1.21 E+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 Table 2 - 2001 Fission and Activated Corroslon Product Activity in Sediment 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 1 i 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 1 1 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 (Measurement Unit)
Gamma Isotonic Composite Air Filters
@CO Gamma Isotopic Liquid 4 liters (pCi/l)
Gross Beta Filter (pCi)
Gamma Isotonic Sediment Density = 1 gmkc WW Gamma Isotopic Liquid 1 liter (pCi/l)
Qtr.
First First First Second Second 137(5 tiMn 65Zn
@co 210 161 156 194~
N/A
--iqe;-
%r 13ks 13CS
%o Mn
- Fe qn wo 9
l4Ce 51Cr 3dcs 37cs
%o 54pAn 5gFe 65Zn 6OCo 66
-I_
0.270 0.372 0.222 0.328 0.160 0.250 0.145 0.301 0.224 27344 322 193 174 139 216 126 261 194 Env Lab Results 53 154 117 120 136 Agreemen Yes Yes Yes Yes Yes 89 217 169 159 201 Yes Yes Yes Yes Yes 61.4 Yes 0.253 Yes 0.364 Yes 0.207 Yes 0.358 Yes 0.149 Yes 0.245 Yes 0.148 Yes 0.322 Yes 0.235 Yes 79 Yes 237 Yes 332 Yes 173 Yes 194 Yes 143 Yes 232 Yes 136 Yes 276 Yes 208 Yes
-lO-
Table 4 (Cont.) Results of 2001 Environmental Intercomparison Program with independent Lab, Analytics, Inc.
I Alpha/Beta Liquid 100 ml Jar I
Gamma Isotopic Sediment Density = 1 gmicc WW (pCi)
Gamma Isotopic Composite Air Filters (PC0 I.-~----_-.-
Qtr.--
Second Second Second Third Third Third Third Fourth Fourth Fourth Nuclidez i -__
N/A Vendor Lab Results 35 248 139 100 JH 7494 NIA 35 248 7494 Tz-3CS 54Mn s5Zn
%o 193 174 216 261 194 34cs 0.22?---
3cs 0.328
%Mn 0.250 Zn 0.301 Oco 0.224 131 92 N/A 57
%e
%r cs
-cs 58co 54Mn Fe
@Zn vo 225 295 118 281 54 88 60 122 362 l-Env Lab Agreement
I-Results 99 =I Yes 7170 Yes 37.5 Yes
+-
I 175 YC?S 178 Yes 240 Yes 277 Yes 212 Yes 0.240 Yes 0.339 Yes 0.221 Yes
-I:
97 Yes 57 Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes
Table 4 (Cont.) Results of 2001 Environmental Intercomparison Program with Independent Lab, Analytics, Inc.
Cornparis&
Study (Measurement Unit)
Gamma Isotopic Rock Density =I.5 gm/cc pCi/g Gamma lsoto&
Liquid 4 liters (pCi/l)
Qtr.
Fourth Fourth auclides Ce
%r 34Cs 37cs 58co 54Mn 5gFe
%In
%o
-T---
r4Ce 51 Cr
%s 37cs WO
%Mn 5gFe
@Zn To Vendor-Lab
_ Results 0.482 0.631 0.252 0.531 0.115 0.189 0.129 0.262 0.449
- i?t 293 II?
188 53 88 60 122 209 Env Lab-Results Agreement 0.458 Yes 0.582 Yes 0.185 Yes 0.496 Yes 0.120 Yes 0.182 Yes 0.132 Yes 0.259 Yes 0.431 Yes 101 234 285 108 200 61 92 65 130 211 Yes Yes Yes Yes Yes Yes Yes Yes Yes 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.
- IZ-
Table 5 - Results of the 2001 Intercomparison Program with Independent Lab Qtr.
Nuclides Env Lab Results 1.42E-03 iecond Lat Results 1.77E-03 igreement Yes Gross Alpha Planchet jecol Gem iecol jecol nd jecol Id Id Id Id 5H N/A We Cr 34cs
=cs sac0
%Mn 5QFe 0SZn
@co Ce lCr WCs
$Cs 5aco 5Mn 5gFe 65Zn
%o N/A 1.40E-04 a.43B03 1.3OE-02 3.lOE-03 3.19E-03 3.40E-03 4.32E-03 4.01 E-03 5.39E-03 3.55E-03 4.85E-02 7.61 E-02 166E-02 1.87E-02 Z.OOE-02 2.57E-02 2.42E-02 3.27E-02 2.06E-02 1.OOE-03 1.45E-04 8.27E-03 1.29E-02 3.39E-03 2.99E-03 3.31E-03 3.99E-03 3.65E-03 4.92E-03 3.37E-03 5.02E-02 7.83E-02 2.06E-02 1.81E-02 2.01 E-02 2.42E-02 2.22E-02 2.98E-02 2.04E-02 Q&SE-04 1 The Second (Independent)
Laboratory was Analytics, Inc. for 2001.
Yes Yes Yes Yes Yes Yes Yes Yes Y0s Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes 2
Results originally reported using incorrect units resulting in non agreement, when corrected results are in agreement.
Table 5 - Results of the 2001 Intercomparison Program with Independent Lab Qtr.
-0urt ourth
-ourth
-ourth
- ourth I
Nuclides We Cr
%s 37cs 920 Mn 5gFe 65Zn
%o
%Xe
- 5Kr 33Xe a5Kr 33Xe 85Kr
=Xe 5Kr H undis 3H dist Env Lab Second La!
A$,.;ement j-izJcTr 7.16E-02 1.24E-02 2.49E-02 9.31E-03
--I-1.29E-02 1.4E-02 1.93E-02 2.67E-02 7
88 5-i 7
86 7
a7 Yes 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 Kelly Baulware S
mRemly 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 Res, Gar Res. Gar, B Fees, Gar 3.71E+O 2.90EtO 2.89E-6 8.46E-9 2.33wo 2.64E-6 8.62E-9 2.34E+O ZIOE-6 6.72E-9 1.83E+O 8.90E-8 1.94E-10 7.53E-2 7.17E-7 2.69E-9 7.19e-1 1.70E-10 6.41E-2 rn Robertson 1
si I
4.7 I
Res, Gar, B 1 6.18G8 SSE 1
2.5 Res, Gar 1 1.44E-7 6.28E.
Res. Gar Rare Gnr ESE ESE SF 1.1 5.0 44
.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 taken at the of one Grms beta following fifkr 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
- 18.
Table 8 (Cont.) - Radiological Environmental Monitoring Program Specifications
,) 2 Indicator samples to be taken within the exdusion boundary and in the direction of potentially amcted ground water supplies.
I) 1 Control ~mplelrom unsffaded location
,) I hdicator semple lrom a nearby public ground water supply SOrce.
Gamma isotopic monthly ivivl quarterlycomposne (by locatio) to be analyzed or triuum Bamma iso*opic monthly nim qusrteily nmpasita
- by location) to be ana@&
br tritium.
Gamma !sotopic monthly tith quarterly composite (by location) to ba analyzed ior IrifiUrn.
Gamma isotopic and trttium mslyses quarterly.
\\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 SPB on pasture. monthly other Gamma isotopic and 1.131 at the lxstion of a dairy s 20 miles dirtance and IW* in times5 analyds semImonthlya when animals are on the most prevalent wind directton.
ps*ture. manmly other 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 tomtim of VII(B) above.
16 Gamma isotopic.
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 taken at a location in the lower mservoir.
river sufficiently far upstream such that no ekcts of pumped sfomge operatIm are anticipated 213 2P 231 Gamma isotopic on edible potions semiannually9.
Gamma isotopic on edible portions semiannually*.
Gamma isotopic, S) 1 Indicator swnple to be Semiannual gfab sample.
21 take on or near the 1
Gamma isotopic.
shoreline Of the blver rewvoir.
river sufmsntly far upstr&
such that no elf*&
Of PnlPed
- rage operation are anticipated FOOTNOTES
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
- 10.
- 11.
Reserved for future Use.
Sample site locations are based on 5 yearavergge meteorological analysis.
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@%
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.
Not to exceed 35 days.
Time composite samples are samples which are collected with equipment capable of collecting an aliauot at time intervals which are short Ce.o. houdv) relative to the comoositina oeriod.
Atleast once par 100 days.
,I~
I.~~~~~~~.
At least once per 18 days.
At least once per 200 days.
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.
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 within tha exclusion Quarterly exchange; two or more dosimeten at each locatton.
Gamma dose B) 2 Stations to be placed Quarterly exchange; two amund VCSNS sludge or mcwe dosimeters at each location.
wastewater discharge.
1 Indicator sample taken Daily sample with monthly composite.
Gamma isotopic and Gamma isotopic and 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 and/or Sample INGESTION:
S-VII. Milk S-VII. Milk4 j-VIII.
Food Products
-0OTNOTES Crlterla for Selection of Sample Number & Location 0
1 Sample Worn one of the nearest affected dairies at or beyond 5 miles.
- 1) 1 Control sample to be taken at the location of a dairy greater than 20 miles distance and not in the most prevalent wind direction.
- )
1 Indicator grass (forage) sample to be taken at the location of S-VII(A) above.
- 1) 1 Control grass (forage) sample to be taken at the location of S-VII(S) above.
i) 2 Indicator grass (forage) samples to be taken at 2 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) sample to be used for routine monitoring slang with S-IV(E) above.
,)
1 Indicator sample of various types of foods grown in the area SW rounding the plant (root.
fruit, grain).
Sampling and B
Monthly when available.
Mdnthly wh@n av$lable.
Monthly when available.
Monthly when available, Anwatly during se~so.
growing Sample Location 14
'I6 14 16 18 Type & Frequency oi Analysis Gamma isotopic and I.
131 analysis biweekly.
Gamma isotopic and I-131 analysis biweekly.
Gamma isotoptc.
Gamma isotopic Gamma isotopic.
Gamma isotopic on edible portion.
- 1.
Reserved for future use.
- 2.
Reserved for future use.
- 3.
Reserved for future use.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
IO.
- 11.
- 12.
- 13.
- 14.
t
+
Table 9 (cant) - Supplemental Radiological Environmental Monitoring 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.
Not to exceed 35 days.
Reserved for future use.
At least once per 100 days.
At least once per 18 days.
At least once per 200 days.
Reserved for future use.
At least once per 400 days.
Reserved for future use.
Weekly, when circulating water is not operational.
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.
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 Air Radioiodine (pCim)
Direct (TLD)
(NW Jl (305)
Gamma(l35)
Quarterly surfac.e water (pcill)
Gamma(24)
Special hlteresl H (36)
Gamma Spec(36)
%n Lower Limi, Of tletectial (Max.
Adual MOE-3 (i.OE-2)
N/A 1.88E+O All lndlsalw Locatl~nm Mead (#blal W)
(R=w)
Z.lEE-2 (253,253)
(5.91E.3 to 1.96E-1)
LocaUon u,th Hlghast Annual Mean Number of N2lm Control Lowdians NOnrWtii (Distance P Direction)
Mean (#h&l #)
w-w Mean Wblal W)
Rep&d NW Measurement Site 7 Environmental 2.40E-2 (W52)
Lab Garden 2.03E-2 (5252) 0 (9.06E-3 IO l.%E-1)
(1.0 mi E )
(7.88E-3 to 3.42E-2)
Sampled (Unil of Measurement) surface water (Continued)
Ground Water (pCi/l)
Table 10 (Cont.) - Radiological Environmental Monitoring Program Summary for 2001
Table IO (Cont.)- Radiological Environmental Monitoring Program Summary for 2001
Table 10 (Cont.)- Radiological Environmental Monitoring Program Summary for 200 1 3.11E+i All < LLD 8.OE+l 2.57E+l All < LLD i
(6.OE+l) 3.6oE+l 2.54E+l (9124)
&OE+l l.O5E+l to 4.24E+i I
l.l5E+
1 All < LLD Location with HI best Annual Mean T
Site 2 Env. Lab Garden (1 mi ESE) 2.54E+1(9/12)
(l.O5E+l to 4,24E+l)
Contml Locations Mean (#/total #]
(Ransal All c LLD All < LLD All < LLD All < LLD All < LLD All c LLD All < LLII All < LLD All z LLD All c LLD AlcUD All c LLD Number of NOflWditl~
Reported lksuremant 0
Table IO (Cont.)- Radiological Environmental Monitoring Program Summary for 2001 Medfum or Pathway sampled (unit of Meamment)
Fish (Cant)
Lowsr LlmR All lndloator Locations of Mean (u\\otal e Dei.?ctlon2 IRWP)
Actual (Max.)
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)
Location with Highest Annual Mean NaIlI Md (wtotal#)
(Distance a Direction)
Nwl Number of NonroutIne Report&
Mesaurement
Table 10 ( cant ) - Radiological Environmental Monitoring Program Summary for 2001 Footnotes 1
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
f 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.
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.
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.
Any confirmed measured level of radioactivity in any environmental medium that exceeds the reporting requirements of ODCM, Section 1.4.1.2.
Detection sensitivity is approximately 10 mrem/yr (1.O pR/hr).
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.
Fish include 3 groups (Bass, Bream/Crappie, Catfish/Carp).
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.
MaXiMUm MDA from control location used.
All measurements had positive results, no MDA values calculated.
- 30.
Table II-Radiological Environmental Program Preoperational (Baseline)
Summary Medium or Pathway Sampled @Jnttof Nleasurement and Reporting Period)
Air Patiiulate (pciln?,
(1981-1982)
Type and Total Lower Lift Numb of of Detecuon Analyses Actual [Max.)
P&omred ti-Gross Beta 4.1 E-3 (1300)
(1.OE-2)
I Gamma Spec (307)
I
%S 3.OE-3 All Indicator L0CaUOM Mesn (#/tOtal rr)
IRange) 1.lE-1 (562/564)
(1.3E-2 to ME-I) 2.7E-2 (4561462)
(9.3E-3 lo ME-21 All < LLD 3.2E3 (221241)
(IX-3 to 5.2E-31 All c LLD 9.9 (915/915)
(6.7 to 14.7) 10.2 (154/k%)
I 16.8 to 14.7) 1.4E+3 (W29)
(l.lE+3 to 2,4E+3]
LocatIon,v,th Hi@
Name (Distance 8 DIrection)
Site 13. North Dam (2.9 mi NNW)
Site 8, Mon. Res. S of Rd 224 (1.5 ENE)
Site 10, Met Tower (2.4 ml NNE)
Site 13. North Dam (2.9 mi NNW)
Site 55, St. Barnabas Church (2.8 mi E)
Site 17, Columbia Canal (24.7 mi. SE) 1.3E-1 (52/52)
(2.1E-2 to 5.5E-1)
XOE-2 (42142)
(i.ZE-2 to &OE-2) 3.8E-3 (2/Z%)
(2.5E-3 to 5.2E-3) 13.1 @l/61)
(12.2 to 14.2) 14.0(7/7)
(13.1 to 14.7) 1.6E+3 (2/7)
(1.4E+3 to1,8E+3L Control Locations Mew+ (#tOtal a)
(Raw@
1.2E-1 (153055)
(7.9E-3 to 6.1E-1) 2.8E-2 (125/126)
(1.2E-2 to 5.8E-2)
All < LLD 4.2E-3 (4166) f3.2E-3 to 5.6E-3)-
All < LLD 9.7 (305/305)
(6.4 to 13.5)
Table 11 (Cont.) - Radiological Environmental Program Preoperational (Baseline)
Summary (9.5E+2 to 2.3E+3) 0 0
0 0
0
Table 11 (Cont) - Radiological Environmental Program Preoperational (Baseline)
Summary
Table 11 (Cont) - Radiological Environmental Program Preoperational (Baseline)
Summary (UnItof Measurement and Reporting Period)
Milk Number oiAalyses Pscformed Gamma Soec 1
i
Table 41(Cont.)
- Radiological Environmental Program Preoperational (Baseline)
Summary Medium or Palhwav Sampled (Unit of I Messurment
?md Reporting Perlod~
OtherVegetation (PCtM wt)
La -..-...
Lower Llmn All Indicator est Annual Mea I
1 Numberof Sediment (pCilkg)
(1980-1982)
Gamma Spec (24)
- CS 2.3E+l (15E+2) 24E+l (15E+2)
l.fE+2 (lUi6) site 21, Parf ME+2 (6I6) 4.2E+2 (616) 0 (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.
2,
- 3.
- 4.
- 5.
- 6.
- 7.
Values given are MDA values calculated from the program data analyses with maximum acceptable LLD values allowed from NRC guidelines given in parentheses.
Mean and range are based on detectable measurements only. The fractions of detectable measurements at specific locations are indicated in parentheses.
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.
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.
Detection sensitivity is approximately 5 mrem/yr (0.5 pWhr) determined from the analyses of five years of preoperationaf data.
No control location was specified for drinking water during the preoperational monitoring period.
Inconclusive data.
Table 12 - 2001 Environmental Sampling Program Exceptions Media Air Air Radioiodine Sample Month Location (Week No.)
Cause for Exception Site 7 March (12)
Storm caused power outage 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 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 l
Site 7 August (36)
Fire ants in receptacle Direct Radiation Site 9 September (39)
- 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
,.