RC-97-0093, Radiological Environ Monitoring Rept VC Summer Nuclear Station for Operating Period 960101-1231
| ML20196G151 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/31/1996 |
| From: | Byrne S, Gowdy G, Sowell J SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| RC-97-0093, RC-97-93, NUDOCS 9705140287 | |
| Download: ML20196G151 (49) | |
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{{#Wiki_filter:- - - _ - _ - - i South Carolina Dectric & Gas Company Virgil C. Sumrner Nuclear Station. Stephm A.Byrns b $ Je ki sville SC 29065 t redan
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{E$$$$U April 30, 1997 RC-97-0093
'97 MAY -5 P3 :13 Mr. L. A. Reyes Regional Adminstrator U. S. Nuclear Regulatory Commission Region ll, Suite 2900 101 Marietta Street, N.W.
Atlanta, GA 30323
Dear Mr. Reyes:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 L RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT (ANN 3400) Enclosed is the South Carolina Electric & Gas Company (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 Sation Technical Specifications. If there are any questions, please contact Ms. Susan B. Reese at (803) 345-4591. Very truly yours, S &5 Stephen A. Byrne SBR: sbr Enclosure f,/ r c: J. L. Skolds (w/o enclosure) NRC Resident inspector R. R. Mahan J. B. Knotts / [ R. J. White (w/o enclosure) (w/o enclosure) NSRC1 f >/ , 1 A. R. Johnson DMS (RC-97-0093) l 6 J. W. Sowell RTS (ANN 3400) l M. E. Jordan File (818.02-2) k l
- 9. n i.lllll1.11'Il.it1.11.I ll NUCLEAR EXCELLENCE - A SUMMER TRADITIONI \
9705140287 961231 PDR ADOCK 05000395 R PDR 3(g3 .
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l Virgil C. Summer Environmental Surveillance Laboratory Jenkinsville, South Carolina i RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPERATING PERIOD l JANUARY 1,1996 - DECEMBER 31,1996 APRIL 1997 J V. C. SUMMER NUCLEAR STATION SOUTH CAROLINA ELECTRIC AND GAS COMPANY Prepared by: br). l [Jerr[4N. Sowell, Health PI1ysicist Reviewed by: Approved by , k C.A. Blue, Manager G.M. dowdy, C Health Physicist Health Physics and Radwaste Services
s Executive Summarv
- 1. Results of the 1996 Land Use Census indicated no significant movement of critical receptors since the previous annual census, and no identified locations where a calculated dose exceeded limits specified in VCSNS Offsite Dose Calculation Manual, Section 1.4.2
- 2. During the ninth refuel the plant was uprated to 2900 MWt (990 MWe gross).
- 3. During 1995 an extensive effort was under.taken to reduce the number of control / indicator locations. This project included controls to reinstate samples as needed depending upon plant operations. These new controls are reflected in the station Offsite Dose Calculation Manual. The reduction begin in 1996.
- 4. There was no detection of radioactivity in environmental media attributed to gaseous effluent releases from VCSNS.
- 5. Activated corrosion products attributed to liquid effluent releases from VCSNS were detected in sediment. Radiation dose to the general public attributed to this activity is a small fraction of the observed variation in natural background radiation.
- 6. Detection of fission product activity in environmental media is attributed to liquid effluent releases from VCSNS and residual fallout from other sources. Radiation dose to the general public attributed to this activity is'a small fraction of the observed variation in natural background.
-7. Results of the Radiological Environmental Monitoring Program substantiate the continuing adequacy of source control at VCSNS and conformance of station operation to 10 CFR 50, Appendix I design goals.
I _a
1 s l 1 i h
- 1 TABLE OF CONTENTS l'
j Egagg l t introduction 1 i l Description of the Radiological Environmental Monitoring Program 2 l J l Land Use Census 4 . j- Monitoring Results and Discussion 5 i j Conclusion 8 f. 4 i l 1 I li a
s i e LIST OF TABLES i TABLE Paae 1 Monitoring Methods for Critical Radiation Exposure 2 , Pathways 2 Radic logical Environmental Monitoring Program 9 Required Sampling Site Locations
- 3 Results of the 1996 EPA Intercomparison Program 11 3a Results of the 1996 Environmental 13 l Intercomparison with Independent Lab 4 Results of the 1996 Intercomparison Program with 14 Independent Lab l 2
5 Summary of the 1996 Intercomparison Program 16 with SCDHEC i 6 Results of the Environmental Dosimetry 17 Intercomparison with the NRC TLD Direct Radiation Monitoring Network 7 Results of the 1996 Land Use Census Verification 18 1 7a Critical Receptor Evaluation for 1996 19 1 8 Radiological Environmental Monitoring Program 20 Specifications 9 Supplemental Radiological Environmental 25 Monitoring 10 Radiological Environmental Monitoring Program 28 Summary for 1996 11 Radiological Environmental Monitoring Program 34 Preoperational(Baseline) Summary 12 1996 Environmental Sampling Program Exceptions 40 13 1996 Activated Corrosion Product Activity in 8 Sediment iii l I
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I LIST OF FIGURES Fiaure Paae : 1-1 Control Site Locations (50 mile radius around the 41 l Virgil C. Summer Nuclear Station) 1-2 Radiological Monitoring Program Local Indicator 42 , Sample Sites (5 mile radius around Virgil C. Summer Nuclear Station) 1-3 Radiological Monitoring Program Local Indicator 43 Sample Sites (1 mile radius around Virgil C.
- l. summer Nuclear Station) ,
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I INTRODUCTION l Virgil C. Summer Nuclear Station (VCSNS) utilizes a pressurized water reactor rated at 2900 MWt (990 MWe gross). The station is located adjacent to the Monticello Reservoir near Jenkinsville, South Carolina and approximately 26 miles northwest of Columbia. VCSNS achieved initial criticality on October 22,1982, reached 50% power December 12,1982 and 100% power June 10, 1983 following steam generator feedwater modifications. Steam generators were replaced in the fall of 1994. During the ninth refuel the plant was uprated to 2900 MWt (990 MWe gross). VCSNS is currently operating in its tenth fuel cycle. VCSNS is operating in conjunction with the adjacent Fairfield Pump Storage Facility (FPSF) which consists of eight reversible pump-turbine units of 60 MWe capacity each. During periods of off-peak power demand, base load generating capacity is used to pump water from Parr Reservoir to Monticello Reservoir. Monticello 1 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. Unprocessed steam generator blowdown and 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. 1
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 1996. Data trends, control / indicator and preoperational/ operational data intercomparisons and other data interpretations are presented. 1 DESCRIPTION OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program is carried out in its entirety by South Carolina Electric and Gas Company. The program has been designed to meet the following general commitments:
- 1. To analyze selected samples in important anticipated pathways for the qualification and quantification of radionuclides released to the environment surrounding VCSNS.
- 2. To establish correlations between levels of environmental radioactivity and radioactive effluents from VCSNS operation.
The program utilizes the concepts of control / indicator and preoperational
/ operational intercomparisons in order to establish the adequacy of radioactivity source control and to realistically verify the assessment of environmental radioactivity levels :
and subsequent radiation dose to man. During 1995 an extensive effort was under taken to reduce the number of control / indicator locations. This project included controls to reinstate samples as needed dependent upon plant operations. These new controls are reflected in the I station Offsite Dose Calculation Manual. The reduction was implemented January, l 1996.
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l Sample media and analysis sensitivity requirements have been established to ; ensure that the maximum dose pathways are monitored and sensitivities represent a I small fraction of annual release limits. Effluent dispersion characteristics, demography, ; hydrology and land use have been considered in selection of environmental sampling ! locations. These criteria were used to establish both the preoperational and operational phases of the Radiological Environmental Monitoring Program. Elements of the program monitor the impact of gaseous and liquid effluents released from VCSNS. Specific methods used in monitoring the pathways of these effluents which may lead to radiation exposure of the public, based on existing demography, are summarized below in Table 1. Requirements of the Radiological Environmental Monitoring Program are specified in the VCSNS Offsite Dose Calculation Manual (ODCM). Elements of the program monitor the impact of gaseous and liquid effluents l released from VCSNS. l l i 2
Effluent Release Tvoe Exposure Pathway Monitorina Media Gaseous immersion Dose and other Thermoluminescent Dosimetry (TLD), External Dose Area Monitoring, Air Sampling Vegetation (Ingestion) Vegetation and Food Crop Sampling, Air Sampling Milk (Ingestion) Milk Sampling, Vegetation Sampling, Grass (Forage) Sampling, Air Sampling I Liquid Fish (Ingestion) Surface Water Sampling, Bottom l Sediment Sampling, Fish Sampling Water & Shoreline TLD Area Monitoring, Surface Water Exposure (Ingestion and Sampling, Shoreline and Bottom Immersion) Sediment Sampling ) Drinking Water (Ingestion) Ground Water Sampling, Drinking I Water Sampling ; Table 1 - Monitoring Methods for Critical Radiation Exposure Pathways l I Monitoring sites indicative of plant operating conditions are generally located i within a 5 mile radius of the plant. Table 2 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 l from VCSNS are presented as Figures 1-2 and 1-3. Figure 1-1 shows monitoring sites at distances greater than 10 miles from the plant. These locations indicate regional I fluctuations in background radiation levels. In addition to preoperational/ operational 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 l concentration. Environmental data is gathered through multiple types of sampling and measurements at specific locations. Several multiple sampling combinations are in use ! around the VCSNS. For example, all air sampling locations serve as environmental dosimetry monitoring locations. At these locations, airborne plant effluents are monitored for gamma immersion dose (noble gases), in addition to air contsminants. Three of these locations have additional complementary sampling / measurement pathways for monitoring plant effluents. Sampling locations 6 (1.0 mi ESE) and 7 (1.0 mi E) have broadleaf vegetation gardere for monitoring gaseous effluent deposition and ingestion pathway in the two sectors having the highest deposition coefficients (D/Q) with real potential for exposure. Sampling location 18 (16.5 mi S) serves as a control location for direct radiation, surface water and garden monitoring. 3
_ _ ___._-_ _ _ _ _-_ _ _ ~..__._ _ _.._ _.._._ _ _ _ _ l; i 1 Liquid effluents are monitored using three different monitoring media (fish, l
. bottom sediment and surface water) at the two most probable affected bodies of water j 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 (30.0 mi NNW) on the Broad River. 1 Quality of Analytical measurements is demonstrated by participation in five
- laboratory intercomparison programs. Results of the 1996 EPA Intercomparison Program are included in Table 3. Table 3a gives results of the intercomparison with an ;
} independent vendor used to supplement the more limited EPA program available in
[ 1996. Results of the intercomparison program with the VCSNS count room and an outside vendor are included in Table 4. The intercomparison program with South l Carolina Department of Health and Environmental Control (SCDHEC) is outlined in l Table 5. Results are reported by SCDHEC. Results of an environmental dosimetry l q intercomparison with the NRC are shown as Table 6. Only one result showed 3 j disagreement in the 1996 data, gross alpha liquid from 3/12/96 in Table 3a The levels
- tested were extremely low (10 pCi/l) and, thus hard to measure accurately. In addition, the environmental program has no requirement for gross alpha mMsurements, so there i is no impact on the environmental program. The results of each cf these five quality control checks of the Radiological Environmental Monitoring program verify the l technical credibility of analytical data generated and reported by the program.
l The Radiological Environmental Monitoring Program described in Tables 8 and 9 incorporates all the elements of the VCSNS ODCM and includes numerous supplemental sampling locations. , a
- LAND USE CENSUS i l !
l 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 1996 are included in Table 7 A verification of the maximum exposed individual location is presented in Table 7a. Identification of the highest offsite dose locations was performed by calculating a hypothetical dose based on predicted VCSNS source term (Operating License Environmental Report) and 5 year average meteorological data. Exposure pathways used in the analysis were those identified during the land use census.
During the 1996 land use census, the location and pathway presently used in the i ODCM for offsite organ dose calculations (E1.2 miles - residence / garden) was found to have a calculated dose of 2.33E+0 mrem /yr. In addition, the ODCM required environmental gardens (E 1.0 and ESE 1.1 miles) were found to have a calculated dose i of 3.71E+ 0 and 2.34E+0 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 VCSNB. Therefore, changes to the ODCM gaseous effluent [ calculations or garden ssmple locations are not indicated. l 4 4
4 l MONITORING RESULTS AND DISCUSSION The results of the Radiological Environmental Monitoring Program for 1996 are 1- summarized in Table 10. For comparison, preoperational data is summarized in Table j 11. During 1996, the Radiological Environmental Program attained a program - compliance rate of approximately 99%. A listing of program exceptions and their i respective causes are included in Table 12. Detailed analysis of the impact of these
- omissions verified that program quality has not been affected. ,
l Airborne gross beta activity measured in air particulate samples collected at j indicator locations around VCSNS were consistent with preoperational levels and not ' i statistically different from control locations. Mean preoperational control and indicator i levels were 2.7E-2 and 2.8E-2 pCi/m , respectively. Mean indicator and control location i measurements during 1996 were 1.90E-2 and 1.97E-2 pCi/m , respectively. The I highest site specific mean activity (1.94E-2 pCi/m ) was measured at indicatcr location j no. 8 (Monticello Res. South of Rd 224). A comparison was performed between the , 1996 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. i
- Gamma spectroscopy measurements of air particulate samples and activated
! charcoal cartridges support the gross beta activity trend. Only natural background I activities of Be-7, Ra-226 and K-40 were detected. Minimum detectable activity (MDA) ;
- levels for Cs-134, Cs-137 and 1-131 were 2.51E-3, 2.63E-3 and 2.15E-2 pCi/m , ,
i respectively. The results support the gaseous effluent release data reported in the 1996 [ Annual Effluent and Waste. Disposal Reports for VCSNS. During 1996,1.73E-6 Cl of iodine and 6.83E-6 Cl of particulates were released.~ These releases are not discernible in atmospheric samples due to atmospheric dispersion during these releases. 3 l During the second quarter of 1996 a problem with the reading and data reduction
- provided by_ an offsite vendor resulted in the loss of second quarter environmental j
- dosimetry measurements. This is reflected in Table 6. Results of the NRC l environmental dosimetry measurements are shown Results were also obtained from
- the South Carolina Department of Health and Environmental Control. The results from ,
these two sources were consistent with historical averages for the locations. t Environmental dosimetry measurements during 1996 did not differ significantly from preoperational measurements. Indicator and control dosimetry measurements also showed no appreciable differences during 1996. Comparison with other operational years shows no statistically significant difference. Sampling location no. 4
- (Fairfield Hydro 1.2 mi, WNW) was the indicator location showing the highest mean j exposure rate of 1.2E+1 R/hr. This value is higher than in 1995 due to the monitoring j site being moved to a higher background location, but is still consistent with the highest mean exposure rate of 1.4E+1 pR/hr measured during the preoperational period.
!{ Gaseous effluent release data reported for 1996 indicated a total of 5.9E-1 Ci of fission and activation gases released from VCSNS Radioactive gaseous effluent at this level ! l I 5 4
J would not be expected to produce a discernible increase in direct radiation dose above ; background levels. ' ! Gamma spectroscopy measurements of surface water samples did not indicate the presence of activated corrosion or fission products above the respective MDA's (MDA's are maintained below required LLD's). Liquid effluent release data reported for 1996 in the Semiannual Effluent and Waste Disposal Report indicated a total of 1.45E-1 Ci of measurable fission and activated corrosion product activity were released from VCSNS; a level not discernible in surface water due to dilution available during the releases and the detection limits of analytical methods used during gamma j spectroscopy analysis. There was no surface water tritium activity measured in any indicator or control , samples for 1996. The minimum detectable activity (MDA) levels for tritium measured at all indicator locations was 4.80E+2 pCiMiter. This compares to preoperational and 1982-1995 operational means of 1.4E+3 and 7.8E+2 pCiMiter, respectively. Total tritium release in liquid effluents during 1996 was reported to be 5.79E+2 Ci; a level not - usually discernible in surface water due to dilution available during the releases and the detection limitations of analytical equipment used for tritium analysis. Gamma spectroscopy measurements of ground water samples did not indicate the presence of activated corrosion or fission products above the MDA's for the respective _ radionuclides. Tritium analysis ~ did not indicate the presence of any tritium above the detectable levels. Minimum detectabic activity (MDA) levels for tritium at all indicator and control sites was 4.80E+2 pCIA. 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 MDA's of the respective radioauciides. Naturally occurring radionuclides, Ra-226, Pb-214 and Bi-214, were observed in the , Jenkinsville water supply 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 from VCSNS. The highest mean gross beta activity in drinking water was measured at site 28 (Jenkinsville) at a level of 3.20E+0 pCi/ liter, about the same as last year. There was no detected tritium in drinking water samples with a mean MDA of 4.62E+2 pCiMiter. The result compares to a preoperational mean of 7.8E+2 pCiMiter. There were no milk samples collected in 1996. This ref% cts 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 VCSNS operations ) are detected in broadleaf vegetation, grass, or air samples at concentrations greater than required LLD's. Sampling shou'd continue for 2 months after plant releases are reduced to less than the trigger levels , and milk contamination has returned to background levels. ! i 6 .
l Broadleaf vegetation collected from gardens at location numbers 6, 7 and 18 were the principal food products analyzed during 1996. Minimum detectable activity (MDA) levels for Cs-134, Cs-137 and 1-131 were 2.23E+1,2.73E+1 and 2.57+1 pCi/kg, respectively. The minimum detactable activity (MDA) level concentrations are lower than the 3.6E+1 value observed in the preoperational period. 4 Other vegetation sampled in 1996 included corn, tomatoes and turnips representing the non-leafy vegetation group. Naturally occurring K-40 was observed in all samples at concentrations consistent with those observed during the preoperational l period. There was an indication of Cs-137 in one of the indicator sites with an average i of 9.54E+0 pCi/kg. This is most likely attributable to environmental background from old fallout remaining in the soil. There was no indication of any other radionuclides. l Fish species sampled at two indicator and one control location included bass, bream, catfish and carp. Cesium-137 was detected in 2 of 3 samples collected at all sampling locations including the control location. The highest mean Cs-137 concentration was 1.1E+1 pCi/kg (Discharge Canal, site #23,0.5 mi, ESE). There was no detected activity at the centrol site (Neal Shoals,30 mi, NNW). This compares with the highest mean MDA for Cesium-137 of 1.6E+ 1 pCi/kg. Since the levels of Cs-137 in fish at control and indicator locations is not significantly different, most of this radioactivity is attributed to residual fallout. Liquid effluent releases are assumed to l also contribute to the presence of Cs-137. However, this contribution is barely j discernible from the levels of Cs-137 present due to fallout. LiquH effluent releases I curing 1996 included 7.0E-4 Ci of Cs-137. The presence of Cesium-137 attributed to I liquid ' effluent releases from VCSNS would be limited to Parr and Monticello Reservoirs. Assuming an adult consumes 21 kg of fish a year from site #23 which contains 1.1E + 1 pCi/kg of Cs-137, the dose to an adult with the highest Cs-137 concentrations would be 2.5E-2 mrem /yr (liver). Gamma spectroscopy measurenvm of sediment samples r,ollected during 1996 resulted in detection of activation and i Mon products attributcf to VCSNS operation. Co-60 and Cs-137 were detected in two samples at Parr (Site 21) and in two samples in Monticello Reservoir (Site 23) . Cs-137 had an average concentration of 1.85E+2 and 2.25E+2 pCi/kg, respectively, for the two sites where it was detected an average concentration of 2.05E+02 pCi/kg. Thit. ;ompares to an average Cs-137 concentration in control sediment of 3.4E+2 pCi/kg with a rang of 3.0E+2 to 3.86E+2 pCi/kg. The slightly higher level of Cs-137 at Site 23 may be attributed to VCSNS operation but both sites were lower than the control samples. Co-60 had concentrations of 1.13E+2 and 7.57E+1 pCi/kg, respectively, and an average for the two sites of 9.44E+1 pCi/kg. Radiation doses to man, corre:,ponding to the concentrations of activity in sediment, were calculated using Regulatory Guide 1.109 methodology. A 500 hour / year exposure to shorc <,e sediment containing maximum and mean concentrations of Co-60, and Gs-137, a shorTline width factor of 1 and a sediment mass of 40 kg/m2was assumed. The results are included in Table 13 and show a maximum dose to the public from contaminated cediment to be 7.9E-2 mrem for 1996 based on sediment samples from Parr Reservoir. 7
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I- , i-
- Corresponding i Calculated Annual
}' Location Radionuclide Act!vity (pCi/kg) Dose Equivalent (mromlyr) Total Body-- Monticello Maximum Mean Maximum Mean i Reservoir Co-60 8.66E+1 7.57E+ 1 i
- (Site 23) Cs-137 2.77E+2 2.25E+2 Total 3.63E+2 -
5.27E-2 4.46E-2 ! Parr Reservoir Coy 0 1.69E+2 1.13E+2 i (Site 21) Cs-137 260E+2 1.85E+2
- Total 4.29E+2 -
7.93E-2 5.39E-2 I 3 ! 1 Table 13 - 1996 Fission and Activated Corrosion Product Activityin Sediment CONCLUSION i As in previous years of VCSNS operation, the presence of fission _ product activity attributed to residual fallout from atmospheric v;eapons testing and the r Chernobyl accident were detected in environmental media in::luding fish and sediment. l No detectable fission or activation product activity attributed to VCSNS operation : ] was observed in environmental media except for fish and sediment samples from i
- Monticello and Parr Reservoir. Conservative calculation of radiation dose received by .
! an exposed individual (sumding on the shore, Site 21 and eating fish from Site 21) is [ 1.0E-1 mrem. This dose represents a small fraction of the observed variation in natural ' ! background and a small fraction of VCSNS effluent dose limits. The reported whole I body and c.rgan dose for liquid effluents during 1996 was 7.4E-2 and 4.0E-2 mrem, respectively (VCSNS Annual Effluent Release Report,1996). The absence oi an impact was expected .3lnce, historically, releases from VCSNS have been a small fraction of ODCM Specliication 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 Envi'conmental Monitoring Program, therefore, substantiate the continuing adequacy of source control at VCSNS and conformance of station operation to 10 CFR 50, Appendix ! design objectives. ; 1 I l i 8 e . _
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4 J d i . l Site Description Distance' Direction' Sample Type (s)* ,
- No. (Miles) i Borrow Pit 1 1.2 1.79.8 S DQ j 2 Transmission Line 1.1 225.0 SW AP, RI, DO
- 3 Firing Range 1.2 270.0 W
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DQ j 4 Fairfield Hydro 1.2 289.5 WNW DO 5 Transmission Line Entrance 0.9 144.0 SE DQ 6 Env. Lab Garden 1.0 111.0 ESE AP,RI, ,GA, DQ j 7 Environmental Lab Garden .10 97.8 E AP RI,DQ, GA i 8 Monticello Res. S of Rd 224 1.5 62.0 ENE DO ! 9 Ball Park 2.3 41.6 NE DQ i , 10 Meteorological Tower #2 2.5 25.5 NNE DQ i 12 Old Why 99 4.2 349.4N DQ 13 North Dam 2.9 333.0 NNW DQ ! 14 Dairy (Shealy)* 6.5 277.0 W MK,GR , 16 Dairy (Parr) 20.0 275.5 W MK,GR 16a TLD Location 28.0 278.6W DQ 17 Columbia Water Works 25.0 144.0 SE AP,RI,DO,DW l 18 Residence / Pine Island Club
- 16.5 165.0 S DQ,GA 19 Residence /Little Saluda 21.0 224.0 SSW DQ l 20 Residence /Whitmire 22.0 309.5 NW DQ j 21 Parr Reservoir 2.7 199.5 SSW SW,FH,BS l 22 Neal Shoals 26.0 343.1 NNW SW,FH,BS !
23 Discharge Canal (Mont, Res.) 0.5 104.5 ESE SW,FH,BS l l l 26 On Site Well (P2) 460 Ft 270.0 W GW j 27 On Site Well(PS) 510 Ft 180.0 S GW ' 28 Nuclear Training Center (EOF)* 2.6 170.2 SSE DW 29 Trans. Line WSW of VCSNS 1.0 260.6 WSW DQ
- 30 Oak Tree North of Borrow Pit 1.0 196.2 SSW DQ,AP,R1 31 McCrorey-Liston School 6.6 11.5 NNE DQ i 32 Clark Bridge Road and Brooks Drive 4.6 24.0 NNE DQ 1 33 Rd 48 near Hwy 213 4.2 68.0 ENE DO 34 Rd 419 North of Hwy 60 4.9 111.0 ESE DO ,
35 Glenn's Bridge Road 4.6 132.0 SE DQ 36 Woods Behind Jenk. Post Office 3.1 151.0 SSE DQ j 37 Residence 4.9 304.8 NW DQ 39 LMWTF 14.0 168.0 SSE DW 41 Below Catwalk at Trestle 3.8 182.0 S DQ 42 Broad River Rd (Residence Peak) 3.8 198.0 SSW DO Table 2 - Required Sampling Site Locations i 9
l Site Description Distance' Direction' Sample Type (s)3 No. (Miles) 43 Hwy 176 and Rd 435 5.2 236.0 SW DO 44 Rd 28 at Cannon's Creek 2.8 256.6 WSW DO 45 Rd 33 at Pomaria 5.8 253.2 WSW DO 46 Rd 28 at Heller's Creek 3.7 291.5 WNW DQ i 316.0 NW DQ 47 Fairfield Tailrace 1.0 52 Monticello (Rd 11) 3.8 13.0 NNE DQ 53 Rd 359 3.0 46.5 NE DQ 54 Jenkinsville School 1.7 72.5 ENE DQ 55 St. Bamabas Church 2.0 91.5 E DQ 56 Old Jenkinsville Dinner 2.0 144.0 SE DQ 58 Residence 2.5 157.0 SSE DQ l 59 Nuclear Training Center (EOF)* 2.6 170.2 SSE DQ.AP.GW 60 Rd 98 near Rd 28 3.5 274.6 W DQ 8 Table 2 (continued) - Required Sampling Site Locations Footnotes
- 1. Distance given is the distance between the site location and the VCSNS reactor containment building.
- 2. Direction given in degrees from true north-south line through center of reactor containment building.
- 3. Sample Types:
AP = Air Particulate GW = Ground Water GA = Garden RI = Air Radioiodine DW = Drinking Water FH = Fish DQ = Quarterly TLD MK = Milk BS = Bottom Sediment SW = Surface Water GR = Grass (Forage)
- 4. Site 14 is not presently in use. If conditions change, requiring a renewal of dairy sampling (per criterion Vll.A in ODCM), this site will be reactivated.
- 5. Site 18 consists of 3 locations in close proximity next to Lake Murray. Garden product samples are taken at the Wyse residence. Surface water is taken near the shoreline in Lake Murray. The TLD is located on Pine Island.
- 6. Site 28 for drinking water and site 59 for quarterly TLD measurements and con-tinuous air sampling 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.
10
Comparison Study " Date Nuclide EPA Value Laboratory Agree-(Measurement Unit) (controllimits) Results ment (iio) Gamma in Water 06/07 Ba-133 745 783 Yes (pCi/ liter) (615-875) Co-60 99 100 Yes (90-108) Zn-65 300 320 Yes (248-352) Cs-134 79 75 Yes (70-88) Cs-137 197 213 Yes (180-214) 11/08 Ba-133 64 65 Yes (54-74) Co-60 44 44 Yes (35-53) Zn-65 35 40 Yes (26-44) Cs-13a 11 10 Yes (2-20) Cs-137~ 19 21 Yes (10-28) Gross Beta in Water 07/19 Beta 45 41 Yes (pCilliter) (36-54) 10/25 Beta 35 33 Yes (26-43) lodine in Water 10/04 1-131 27 29 Yes (pCi/ liter) (17-37) Laboratory Blind 04/16 Alpha 75 58 Yes* (pCilliter) (42-107) Beta 167 153 Yes (124-210) Co-60 31 33 Yes (22-40) Cs-134 46 45 Yes (37-55) Cs-137 50 54 Yes (41-59) E Table 3 - Results of the 1996 EPA Intercomparison Program 11
Comparison Study Date Nuclide EPA Value Laboratory 1 Agree-(Measurement Unit) (controllimits) Results ment (iio) Laboratory Blind 10/15 Alpha 59 41 Yes (pCl/ liter) (33-85) Beta 112 93 Yes (83-141) Co-60 15 15 Yes (6-24) Cs-134 20 18 Yes (11-29) Cs-137 30 31 Yes (21-39) Tritium in Water 08/09 H-3 10879 10681 Yes (pCi/ liter) (8991 -12767) Footnotes (*) These are corrected laboratory results from a reanalysis. The original results transmitted to the EPA were a factor of 10 off, actual results of 58 were in agreement. Table 3 (cont.) - Results of the 1996 EPA Intercomparison Program 12
Comparison Study Date Nuclide(s) Vendor Lab Env Lab Agree-(Measurement Unit) Results' Results ment Tritium (pCl/l) 03/12 H-3 2982 2870 Yes Gross Beta Liquid (pCill) 03/12 N/A 98 92 Yes Gross Alpha Liquid (pCi/l) 03/12 N/A 10 18 No' Gamma Isotopic Liquid,4 liter 03/12 1-131 36 45 Yes (pCl/l) Ce-141 88 94 Yes Cr-51 322 320 Yes , Cs-134 58 59 Yes Cs-137 64 64 es Co-58 48 50 Mn-54 31 34 Yes Fe-59 83 84 Yes Zn-65 97 100 Yes Co-60 76 77 Yes Charcoal Cartridge (pCI) 06/12 1-131 81 90 Yes Gross Beta Air Filter (pCi)- 06/12 N/A 24 22 Yes Gamma isotopic Composite 06/12 Ce-141 362 361 Yes Air Filters (pCi) Cr-51 949 1010 Yes Cs-134 280 252 Yes Cs-137 691 740 Yes Co-58 156 ' 163 es Mn-54 506 552 152 Yes Fe-59 131 2n-65 97 108 Yes Co-60 142 149 Yes Gamma Isotopic Liquid,4 liter 12/12 1-131 39 45 Yes (pCl/l) Ce-141 272 292 Yes )
, Cr-51 209 268 Yes Cs-134 172 165 Yes Os-137 191 210 i
l Co-58 119 122 217 Yes Mn-54 202 Fe-59 48 59 Yes Zn-65 91 89 Yes Co-60 108 117 Yes Gamma Isotopic Soil 12/12 Ce-141 456 469 Yes (p=1 g/cc) (pCl/kg) Cr-51 352 407 Yes Cs-134 289 258 Yes Cs-137 442 498 Yes Co-58 200 203 es Mn-54 340 362 75 Yes Fe-59 81 153 174 Yes Zn-65 Co-60 181 198 Yes The Independent Laboratory was Analytics, Inc. for 1996. This data is supplemental to the EPA Intercomparison Program (Table 3). See discussion in text (page 4). Table 3a - Results of the 1996 EnvironmentalIntercomparison Pmgram with Independent Lab 13
Comparison Study Qtr. Nuclide Env Lab Second Lab Agree-(Measurement Unit) Results Results' ment Tritium ( Ci/ml) (Analytics) First H-3 1.77E-3 1.83E-3 Yes ' Gross Beta Liquid (pCi/mi) First N/A 4.81 E-4 5.14E-4 Yes Gross Alpha Liquid ( Cl/ml) First N/A 1.69E-4 1.90E-4 Yes Gamma Isotopic Filters, Second Ce-141 4.11 E-2 4.15E-2 Yes Composite Air (pCl) Cr-51 1.27E-1 1.23E-1 Yes Cs-134 1.46E-2 1.64E-2 Yes Cs-137 4.10E-2 3.95E-2 Yes Co-58 1.25E-2 1.23E-2 Yes Mn-54 3.31 E-2 3.09E-2 Yes Fe-59 1.37E-2 1.24E-2 Yes Zn-65 6.52E-3 6.07E-3 Yes Co-60 8.24E-3 8.12E-3 Yes Charcoal Cartridge (pCi) Second 1-131 1.79E-1 1.66E-1 Yes Gross Alpha Filter ( Ci) Third N/A ,_ 3.14E-3 3.27E-3 Yes Gross Beta Filter ( Ci) Third N/A 3.24E-3 2.86E-3 Yes Gamma Isotopic Liquid,1 liter Third Ce-141 1.24E-2 1.20E-2 Yes ( Ci/ml) Cr-51 2.08E-2 2.03E-2 Yes Cs-134 4.65E-3 4.81 E-3 Yes Cs-137 3.65E-3 3.59E-3 Yes Co-58 3.56E-3 3.62E-3 Yes , Mn-54 4.17E-3 4.05E-3 Yes Fe-59 1.23E-3 1.21 E-3 Yes Zn-65 1.66E-3 1.61 E-3 Yes , Co-60 2.45E-3 2.44E-3 Yes Gamma Isotopic Liquid,4 liter Third Ce-141 1.24E-2 1.20E-2 Yes ( Ci/ml) Cr-51 2.13E-2 2.03E-2 Yes Cs-134 4.63E-3 4.81 E-3 Yes Cs-137 3.82E-3 3.59E-3 Yes Co-58 3.75E-3 3.62E-3 Yes Mn-54 4.40E-3 4.05E-3 Yes Fe-59 1.29E-3 1.21 E-3 Yes Zn-65 1.80E-3 1.61 E-3 Yes Co-60 2.59E-3 2.44E-3 Yes Gamma Isotopic Liquid,100 ml Third Ce-141 1.16E-2 1.20E-2 Yes ( Cl/ml) Cr-51 1.96E-2 2.03E-2 Yes Cs-134 4.22E-3 4.81 E-3 Yes Cs-137 3.49E-3 3.59E-3 Yes Co-58 3.46E-3 3.62E-3 Yes Mn-54 4.06E-3 4.05E-3 Yes Fe-59 1.25E-3 1.21 E-3 Yes Zn-65 1.69E-3 1.61 E-3 Yes Co-60 2.40E-3 2.44E-3 Yes
' The Second (Independent) Laboratory was Analytics, Inc. for 1996.
4 Table 4 - Results of the 1996 Intemompanson Program with Independent Lab f 14
O , I Comparison Study Qtr. Nuclide Env Lab Second Lab Agree-(Measurement Unit) Results Results' ment Gamma Isotopic Filter,57mm Fourth Ce-141 9.53E-2 8.39E-2 Yes ( Ci) Cr-51 7.57E-2 7.15E-2 Yes Cs-134 2.67E-2 3.06E-2 Yes Cs-137 3.54E-2 3.32E-2 Yes Co-58 2.86E-2 2.69E-2 Yes Mn-54 4.34E-2 3.73E-2 Yes Fe-59 1.52E-2 1.28E-2 Yes Zn-65 2.03E-2 1.71 E-2 Yes Co-60 2.06E-2 1.89E-2 Yes l Gamma Isotopic Filter,47 mm Fourth Ce-141 8.23E-2 8.38E-2 Yes ; (pCi) Cr-51 6.68E-2 7.15E-2 Yes ! Cs-134 2.17E-3 3.05E-2 Yes ! Cs-137 3.24E-3 3.32E-2 Yes Co-58 2.60E-3 2.69E-2 Yes j Mn-54 4.15E-3 3.72E-2 Yes ! Fe-59 1.46E-3 1.28E-2 Yes : Zn-65 2.03E-3 1.71 E-2 Yes Co-60 1.91 E-3 1.89E-2 Yes Silver Zeolite Cartridge (pCi) Fourth 1-131 3.81 E-1 4.02E-1 Yes Gas Sample,1 liter (pCi) Fourth Xe-133 2.23E-1 1.89E-1 Yes Kr-85 2.84E+0 2.62E+0 Yes Tritium (pCl/ml) (VCSNS) Fourth H-3 (distilled) 3.29E-5 3.34E-5 Yes ; (pCi/ml) (VCSNS) H-3 (undistilled) 3.19E-5 3.41 E-5 Yes l
' The Second (Independent) Laboratory was Analytics, Inc. except for VCSNS tritium intercomparisons.
Table 4 (cont.) - Results of the 1996 Intercomparison Program with Independent Lab i l l 15 . i
Pathway (Units) Sample Frequency Nuclide' Location Surface Water No. 21 Monthly 3H (pCi/ liter) Mixed Gamma No. 22 Monthly 3H Mixed Gamma Air (pCi/m') No.6 Monthly Gross Beta, lodine, Mixed Gamma No.17 Monthly Gross Beta, lodine, Mixed Gamma Sediment (pCl/kg) No. 23 Semiannually Mixed Gamma , Fish (pCi/kg) No. 23 Semiannually Mixed Gamma Vegetation (pCl/kg) No.6 Semiannually Mixed Gamma
' Intercomparison results were not yet available for publication in this report.
Results will be reported by SCDHEC. Table 5 - Summary of 1996 Intercomparison Program with South Carolina Department of Health and Environmental Control 16
NRC LABOR- 1996 FIRST OUARTER 1996 SECOND QUARTER 1996 THIRD QUARTER 1996 FOURTH QUARTER TLD ATORY RESULTS (pR/hr) RESULTS( R/hr) RESULTS( R/hr) RESULTS( R/hr) STA- TLD TION STATION NO. NO. NRC Laboratory NRC Laboratory NRC Laboratory NRC Laboratory 1 42 21.1 18.3 13.9 21.1 14.3 2 6 17.6 15.3 20.9 17.7 16.3 21.9 - 14.9 5 54 19.4 22.5 24.1 19.7 22.7 23.4 21.6 7 *53 23.1 24.0 28.7 " 25.5 24.4 28.6 25.7
" 22.7 9 *52 26.2 23.4 25.0 26.0 26.0 24.9 -
11 *12 20.9 16.4 26.7 24.9 17.7 26.3 16.5 13 13 24.5 22.7 24.4 25.3 24.5 23.8 23.1 14 *44 17.2 12.9 21.3 18.8 12.6 20.7 Missing TLD 19 *56 19.5 16.5 21.9 20.2 17.7 22.0 15.7 22 58 19.1 15.1 18.3 18.5 12.2 17.4 10.9 24 41 19.2 18.1 18.1 20.1 19.5 18.7 16.3 a 29 *60 21.6 20.7 23.2 23.9 17.4 23.4 20.3 30 46 22.4 17.4 25.3 No Data 17.9 No Data Mtssing TLD 1
- Co-located dosimeters within 10 feet of NRC dosimeter.
** No Laboratory data available due to vendor processing problem Table 6 - Results of Environmental Dosimetry Intercomparison with NRC TLD Direct Radiation Monitoring Network l
i ) 1
Nearest Miles Nearest Miles Nearest No. Nearest No. Sector Residence Garden Cattle Milked Miles Goat Milked Miles N Edna Fuller 4.0 John Robinson 0 3.4 NNE Bessie Crumblin 2.9 Bessie Crumblin 2.9 Bessie Crumblin 0 2.9 NE Ella B. Hemdon 1.5 David Stone (B) 2.1 David Stone 0 2.1 ENE Robert Martin (A) 1.6 Robert Martin (B) 1.6 Robert Martin (C) 0 1.6 Robert Martin 0 1.6 E George Mosley 1.2 George Mosley (B) 1.2 ESE Walter Martin 1.1 Walter Martin 1.1 Glover / Kennedy 0 5.0 SE Loyld Green (A) 1.6 LoyId Green 1.6 Sim Roberts (C) 0 4.7 SSE Toney Taffer (A) 2.5 Tony Taffer (B) 2.5 S Walter Barker (A) 4.0 Walter Barker (B) 4.0 J H. Yarborough 0 3.8 SSW Eldon Money 3.3 G.A. Mayers (B) 4.7 G.A. Mayers (C) 0 4.7 SW Marvin Miller 3.3 Marvin Miller 3.3 Marvin Miller 0 3.3 g WSW Ron Hope 2.9 Mary Davis 3.0 Steve Aut! O 4.5 W Mr. Livingston 2.8 Mr. Uvingston 2.8 Mr. Livingston 0 2.0 W KenWirg Graham 90 5.0 _W NW Claude Ringer 4.8 Claude Ringer 4.8 Claude Ringer 0 4.8 Carrol Leitzey 0 4.8 NW Louise Workman 3.9 Louis Workman (B) 3.9 Ida Cole 0 4.1 NNW Frank March (A) 2.9 Frank March (B) 2.9 Frank March (C) 0 2.9 (A) CHANGE IN CLOSEST RESIDENCE (B) CHANGE IN CLOSEST GARDEN (C) CHANGE IN CLOSEST BEER CATTLE , Table 7- Results of the 1996 Land Use Census Verification v 1
l NAME SECTOR MILES PATHWAY X/Q D/Q Dose
- mrem /y J H. Yarborough S 38 Res,B 8.02E-08 3.71E-10 3.69E - 02 Walter Barker S 4.0 Res, Gar, 7.23E-08 3.32E-10 8.70E - 02 Shirley Counts S 5.0 Res, Gar, B 4.64E48 2.06E-10 7.48E - 02 Eldon Money SSW 3.3 Res 1.29E-07 7.55E-10 5.00E - 03 G.A. Mayer SSW 4.7 Res, Gar. B 6.27E-08 3.51E-10 1.25E - 01 ;
Evelyn Nichols SW 3.3 Res Gar 1.31E-07 9.60E-10 2.44E - 01 Marvin Miller SW 3.3 Res, Gar, B 1.31E-07 9.60E-10 3.39E - 01 Ron Hope WSW 2.9 Res 1.43E-07 9.27E-10 5.60E - 03 Mary Davis WSW 3.0 Res, Gar 1.33E-07 8.58E-10 2 20E - 01 Steve Aull WSW 4.5 Res,B 5.80E-08 3.53E-10 3.73E - 02 Marion Living ston W 2.0 Res, Gar, B 3.42E-07 1.53E-09 3.38E - 01 KenNirgil Gra lam W 5.0 Res, Gar, B C/M 5.21E-08 1.97E-10 1.06E 01 Carroll Leitzey WNW 4.8 Res, Gar, G 3.90E-08 1.27E-10 1.56E - 02 Claude Ringer WNW 4.8 Res, Gar, B 3.90E-08 1.27E-10 4.70E - 02 . Louise Workman NW 3.9 Res, Gar 1.11E-07 3.21E-10 8.84E - 02 Ida Cole NW 4.1 Res,B 1.01 E-07 2.88E-10 3.26E - 02 Frank March NNW 2.9 Res. Gar, B 3.51E-07 9.68E-10 3.65E - 01 John Robinson N 3.4 Res.B 2.83E-07 8.13E-10 8.15E - 02 Edna Fuller N 4.0 Res 2.07E-07 5.70E 10 7.70E 03 Bessie Crumblin NNE 2.9 Res, Gar, B 3.76E-07 1.13E-09 4.24E - 01 William Robinson NNE 3.4 Res, Gar, B 2.75E-07 7.93E-10 2.98E - 01 Ella B. Herndon NE 1.5 Res. 2.01E-06 6.73E-09 7.55E-02 David Stone NE 2.1 Res, Gar, B 9.68E-07 2.98E-09 1.11 E+00 James E. Robinson NE 2.8 Res, Gar, B 5.34E-07 1.51 E-09 5.69E - 01 Robert Martin ENE 1.6 Res, Gar, B G 1.82E-06 5.20E-09 2.01E + 00 W. Hollins ENE 1.7 Res, Gar 1.59E-v5 4.47E-09 1.24E+00
**VCS Garden #7 E 1.0 Res, Gar 4.43E-06 1.36E-08 3.71E+00 ODCM Assumed MEl E 1.1 Res Gar 3.50E-06 1.10E-08 3.00E+0u Johnnie Joyner E 1.2 Res 2.89E-06 8.46E-09 1.08E - 01 George MosleyW E 1.2 Res, Gar 2.89E-06 8.46E-09 2.33E+00 **VCS Garden #6 ESE 1.0 Res, Gar 2.64E-06 8.62E-09 2.34E+00 Walker Martin ESE 1.1 Res. Gar 2.10E-06 6.72E-09 1.83E+00 Glover / Kennedy ESE 5.0 Res, Gar, B 8.90E-08 1.94E-10 7.53E 02 LoyId Green SE 1.6 Res, Gar 5.65E-07 2.07E-9 5.55E-01 Sim Roberts SE 4.7 Res,B 6.18E-8 1.70E 10 1.93E-02 Tony Taffer SSE 2.5 Res. Gar 1.44E-07 6.28E-10 1.66E - 01 Pathways:
Res = Residence B = Beef G= Goat Gar = Garden C/M = Cow / Milk (Infant) i Footnotes' I Maximum exposed individual. Hypothetical dose based on Operating License Environmental Report Source Term. X/O and D/O were derived from ODCM 5-year average meteorological data 1 ODCM required environmental gardens. Table 7a - Critical Receptor Evaluation for 1996 19 l l
Exposure Pathway Criteria for Selection Sampling and Sample Type & Frequency and/or Sample of Sample Number & Location Collection Frequency Location of Analysis AIRBORNE:
- 1. Particulate A) 3 Indicator samples to be Continuous sampler operation 2 Gross beta following filter taken at locations (in with weekly collection. 7 change; Quarterly different sectors) beyond but 30 composite (by location) for as close to the exclusion gamma isotopic.
boundary as practicable where the highest offsite sectorial ground level concentrations are anticipated.2 B)1 Indicator sample to be Continuous sampler operation 6 Gross beta following filter taken in the sector beyond with weekly collection. change; Quarterly but as close to the exclusion composite (by location) for boundary as practicable gamma isotopic. corresponding to the residence having the highest anticipated offsite ground level concentratien or dose.2 C) 1 Indicator sample to be Continuous sampler operation N/A Gross beta following filter taken at the location of one with weekly collection. Change; Quarterly of the dairies being sampled composite (by location) for rneetin the criteria of gamma isotopic. Vil(A).g4 D) 1 Control sample to be Continuous sampler operation 17 Gross beta following filter taken at a location at least with weekly collection, change; Quarterly 10 air miles from the sRe composite (by location) for and not in the most gamma isotopic. prevalent wind directions.2
- 11. Radioiodine A) 3 Indicator samples to be Continuous sampler operation 2 Gamma Isotopic for lodine taken at two locations as with weekly canister collection. 7 131 weekly.
given in 1(A) above 30 B) 1 Indicator sample to be Continuous sampler operation 6 Gamma isotopic for lodine taken at the location as with weekly canister collection. 131 weekly. given in 1(B) above. C) 1 Indicator sample to be Continuous sampler operation N/A Gamma isotopic for lodine taken at the location as with weekly canister collection. 131 weekly. given in 1(C) above. D) 1 Control sample to be Continuous sampler operation 17 Gamma isotopic for lodine taken at a location similar in with weekly canister collection. 131 weekly, nature to l(D) above. Ill. Direct A) 13 Indicator stations to form Monthly or quarterly 1,2,3,4 Gamma dose monthly or and inner ring of stations in exchange'7; two or more 5,6,7,8 quarterly the i3 accessible sectors dosimeters at each location. 9,10,29, within 1 to 2 miles of the 30,47 plant. B) 16 Indicator stations to form Monthly or quarterly 12,13,32, Gamma dose monthly or an inner ring of stations in exchange'#; two or more 33,34,35, quarterty the 16 accessible sectors dosimeters at each location. 36,37,41, within 3 to 5 miles of the 42,43,44, plant 46,53, , 55,60 l
\
l ! t Table 8 - Radiological Environmental Monitoring Program Specifications \ l 20
Exposure Pathway Criteria for Selection Sampling and Sample Type & Frequency and/or Sample of Sample Number & Location Collection Frequency Location of Analysis C) 11 Stations to be placed in Monthly or quarterly 16,17,18, Gamma dose monthly or specialinterest areas such exchange'7; two or more 19,20,31, quarterty as population centers, dosimeters at each location. 45.52 nearby residences, schools 54,56,58 and in 4 or 5 areas to serve as controls. WATERBORNE IV. Surface A) 1 Indicator sample Time composite samples with f Gamma isotopic monthly Water downstream to be taken at a collection every month' with quarterly composite location which allows for (by location) to be 7 mixing a dilution in the analyzed for tritium ultimate receiving river. B) 1 Control sample to be Time composite samples with 22' Gamma isotopic monthly taken at a location on the collection every month' with quarterly composite receiving river sufficiently far (by location) to be 7 upstruam such that no analyzed for tritium . effects of pumped storage operation are anticipated. C) 1 Indicator sample to be Time composite samples with 23' Gamma isotopic monthly taken in the upper reservoir colbction every month' with quarterly camposite of the pumped storage (by location) to be 7 facility at the plant discharge analyzed for tritium , canal. 7 V. Ground A) 2 Indicator samples to be Quarterly grab sampling 26 Gamma isotopic and tritium 7 Water taken within the exclusion 27 analyses quarterfy . boundary and in the direction of potentially affected ground water supplies. 7 B) 1 Control sample from Quarterly grab sampling 59 Gamma isotopic and tntium 7 unaffected location analyses quarterty . VI. Drinking A) 1 Indicator sample from a Monthly grab sampling'. 28 Monthly' gamma isotopic, 7 Water nearby public ground water gross beta and quarterly supply source, composite for tntium analyses. B) 1 Indicator (finished water) Monthly composite sampling. 17 Monthly' gamma isotopic, sample from the nearest and gross beta and 7 downstream water supply. quarterly composite for tritium analyses. C) 1 Control (finished water) Monthly composite sampling. 39 Month!y' gamma isotopic, sample from an unaffected and gross beta and water supply. quarterty7 composite for tritium analyses [ Table 8 (cont.) - Radiological Envimnmental Monitoring Program Specifications l l 21
- l l
l Exposure Pathway Criteria for Selection Sampling and Sample Type & Frequency ) and/or Sample of Sample Number & Location Collection Frequency Location of Analysis 1 INGESTION: l Vll. Milk' A) Samples from milking Semimonthly when animals To be Gamma isotopic and 1-131 animals in 3 locations within are on pasture' monthly other supplied analysis semimonthly' 5 km having the highest times' when milk when animals are on dose potential. If there are animals are pasture, monthly other none then 1 sample from found in times' milking animals in each of 3 accordance areas between 5 to 8 km with criteria i distance where doses are Vll.A. l calculated to be greater than ! 1 mrem per year." l
)
B) 1 Control sample to be Semimonthly when animals 16 Gamma isotopic and 1131 taken at the location of a are on analysis semimonthly' dairy > 20 miles distance times'gasture' monthly other when animals are on and not in the most pasture, monthly other prevalent wind direction'. times' C) 1 Indicator grass (forage) Monthly when available' To be Gamma isotopic. , sample to be taken at the supplied I location of one of the dairies when milk ' being sampled meeting the animals are criteria of Vil(A),above, found in when animals are on accordance pasture with criteria Vll.A. J D) 1 Control grass (forage) Monthly when available'" 16 Gamma isotopic. sample to be taken at the location of Vil(B) above. Vill. Food A) 2 Samples of broadleaf Monthly when available'. 6 Gamma isotopic on edible Products vegetation grown in the 2 7 portion. nearest offsite location of highest calculated annual average ground level D/Q if milk sampling is not performed within 3 km or if milk sampling is not performed at a location within 5-8 km where the doses are calculated to be greater than 1 mrem /yr* B) 1 Control sample for the Monthly when available'. 18 Gamma isotopic on edible same foods taken at least portion. 10 miles distance and not in the most prevalent wind direction if milk sampling is not performed within 3 km or if milk sampling is not performed at a location within 5 to 8 km where the doses are calculated to be greater than 1 mrem /yr" Table 8 (cont.) - Radiological Environmental Moniton'ng Program Specifications 22
. -. - - ~ ~ . _ ~ . - , - . _ _ . . . - - _ _ . - . - . - - . _ - - . . - - - - _ . . . - . - ,
l i $ Exposure . 1 Pattway Criteria for Selection Sampling and Sample Type & Frequency I and/or Sample of Sample Number & Location Collection Frequency Location of Analysis 8 IX. Fish A) 1 Indicator sample to be Semiannual' collection of the 23 Gamma isotopic on edible l taken at a location in the following specie types if portions semiannually'. j upper reservoir. available: bass; bream, 1 crappie; catfish, carp. 8 ! B) 1 Indicator sample to be Semiannual' collection of the 21 Gamma isotopic on edible 1 taken at a location in the following specie types if portions semiannually'. lower reservoir, available: bass; bream, , crappie; catftsh, carp. C) 1 Control sample to be Semiennual' collection of the 22' Gamma isotopic on edible taken at a location on the following specie types if portions semiannually'.
- receiving river sufficiently far available
- bass; bream,
- upstream such that no crappie; catfish, carp.
effects of pumped storage i operation are anticipated ] [ ! AQUATIC: X. Sediment A) 1 Indicator sample to be Semiannual grab sample.' 238 - Gamma isotopic. taken at a location in the i upper reservoir. ] s B) 1 Indicator sample to be Semiannual grab sample? 21 Gamma isotopic. taken on or near the shoreline of the lower l reservoir. ; 8 C) 1 Control sample to be semiannual grab sample? 22 Gamma isotopic. j taken at a location on the . i receiving river sufficiently far upstream such that no effects of pumped storage , operation are anticipated. FOOTNOTES ,
- 1. Reserved for future use.
- 2. Sample site locations are based on 5 year average meteorological analysis.
- 3. Though generalized areas are noted for simplicity of sample site enumeration, ,
airborne, water and sediment sampling is done at the same location whereas biological sampling sites are generalized areas in order to reasonably assure i availability of samples. t
- 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 l Locations. l n ; I Table 8 (cont.) - Radiological Environmental Monitoring Program Specifications j 23 1
._ .__ _._._...____.___-~._____-m -
i~
- 5. Not to exceed 35 days. .
. 6. Time composite samples are samples which are collected with. equipment
- capable of collecting an aliquot at time intervals which are short (e.g. hourly)
- relative to the compositing period. .i r
- 7. At least once per 100 days.
- 8. At least once per 18 days.
- 9. . At least once per 200 days.
1
- 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. . i
- 11. Milk and forage sampling at the control location is only required when locations meeting the criteria of Vil(A) are being sampled.
E i l o i l i
~
Table 8 (cont.) - Radiological Environmental Moniton'ng Program Specifications 4 3 24 l i
l Exposure Pathway Criteria for Selection of Sampling and Sample Type & Frequency of and/or Sample Sample Number & Location Collection Frequency Location Analysis AIRBORNE: S.I. Particulate A) 1 Indicator sample Continuous sampler 8 Gross beta following monitoring the nearest operation with weekly filter change; Monthly + community with the collection. Composite (by highest anticipated dose location) for gamma l or ground level isotopic. concentration. S-II. Radiolodine A) 1 Indicator sample to be Continuous sampler 8 Gamma isotopic for I. taken from thelocation of operation with weekly 131 weekly. S-1(A) above. collection. S-Ill. Direct A) 5 stations to be placed Quarterly exchange 7; 61,62,63, Gamma dose within the exclusion two or more dosimeters 68 & 99 quarterly. boundary, at each location. B) 2 stations to be placed Quarterly exchange 7; 94,97 Gamma dose around VCSNS sludge two or more dosimeters quarterly, lagoons. at each location. WATERBORNE: S-IV. Surface A) 1 indicator sample to be Composite samples with 77 Gamma isotopic and Water taken of the combined monthly collection.13,5 tritium. wastewater discharge. B) 1 Indicator sample taken Daily sample with 72,73 Gr mma isotopic and at each storm drain monthly composite. tritium. outfall. S-V. Groundwater A) 4 Indicator samples to be Semiannual GW-9, Gamma isotopic, taken at NPDES GW-12, tritium and other as monitoring wells. GW-13A, directed. (Reference 2.5) GW15 B) 1 Control sample to be Semiannual GW-8 Gamma isotopic, taken at NPDES tritium and other as . monitoring wells. directed. l l INGESTION: A) 1 Sample from one of the Biweek grab 14 Gamma isotopic and l-S-Vil. Milk 4 nearest affected dairies at sample. 14.+ 131 analysis biweekly. or beyond 5 miles. B) 1 Control sample to be Biweekly grab 16 Gamma isotopic and l-taken at the location of a sample.o,14.+ 131 analysis biweekly. dairy greater than 20 miles distance and not in the most prevalent wind direction. C) 1 Indicator grass (forage) Monthly when 14 Gamma isotopic. sample to be taken at the available.14 location of S-Vil(A) above. Table 9 - Supplemental Radiological Environmental Monitoring 25
Exposure Pathway Criteria for selection of sampling and sample Type & Frequency of 4 and/or sample sample Number & Location Collection Frequency Location Analysis S-Vil. Milk4(cont.) D) 1 Control grass (forage) Monthly when 16 Gamma isotopic. , sample to be taken at the available.14 location of S-Vil(B) above.
- E) 2 indicator grass (forage) Monthly when available. 2,7 Gamma isotopic.
i samples to be taken at 2 { of the locations beyond but as close to the exclusion boundary as practicalwhere the highest offsite sectorial ground level concentra-f tions are anticipated. ] F) 1 Control grass (forage) Monthly when available. 18 Gamma isotopic. 4 sample to be used for
- routine monitoring along with S-IV(E) above.
S-Vill. Food A) 1 Indicator sample of Annually during growing 6,7 Gamma isotopic on '. Products various types of foods season.11 edible portion. grown in the area sur-rounding the plant (root, l fruit, grain). . FOOTNOTES l 1. Reserved for future use.
- 2. Sample site locations are based on the meteorological analysis for the period of i record as presented in the Offsite Dose Calculation Manual (ODCM).
i 3. Though generalized areas are noted for simplicity of sample site enumeration, airborne, water and sediment sampling is done at the same location whereas , biological sampling sites are generalized areas in order to reasonably assure availability of samples.
- 4. Milking animal and garden survey results will be analyzed annually. 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.
Table 9 - Supplemental Radiological Environmental Monitoring 26
- 6. Time composite samples are samples which are collected with equipment capable of collecting an aliquot at time intervals which are short (e.g. hourly) relative to the compositing period.
- 7. At least once per 100 days.
- 8. At least once per 18 days.
- 9. At least once per 200 days.
- 10. The dose shall be calculated for the maximum organ and age group, using the guidance / methodology contained in Regulatory Guide 1.109, Rev.1 and the parameters particular to the Site. The locations are selected based on potential for highest exposure (see NRC letter Docket # 50/395).
- 11. At least once per 400 days,
- 12. Milk and forage sampling at the control location is only required when locations meeting the criteria of Vil(A) are being sampled.
- 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 LLDis. Sampling should continue for 2 months after plant releases are reduced to less than trigger levels and milk contamination levels have retumed to background levels.
f ODCM defined quarterly, f The ODCM requires semimonthly sampling when animals are on pasture, monthly at other times. I Table 9 - Supplemental Radiological Environmental Monitoring 27
; ~. - .- -- . ._ . _, _.
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/96 -12/31/96 . Location with Hghest Annual Mean Number of Control Locations Nontoutine Medium or Pathway Type and Total Lower 1.irrut A:n Indicator Locations Name Mean' (#/ total #) Reported' . Sampled (Unit of Number of Analyses of Mean'(#! total #) Mean* (#/ total #) 2 (Range) (Range) (Range) Measumments Measurement) Performed' Detechon (Distance & Direction) Actual (Max.) Site 8 Monticello Res. 1.94E-2 (53/53) 1.97E-2 (53/53) 0 Air Particulate Gross Beta 4.57E-3 1.90E-2 (263/263) (pCi/m3) (316) (1.0E-2) (4.56E-3 to 3.37E-2) S of Rd 224 (9.12E-3 to 3.37E-2) (1.02E-2 to 3.36E-2) (1.5 mi ENE) Gamma Spec (72) All < LLD All < LLD 0 ; Cs-134 2.51E-3 (5.0E-2) All < LLD All < LLD 0 CS-137 2.63E-3 (6.0E-2) AI! < LLD All < LLD 0 i Air Radioicdine 1-131(316) 2.15E-2 (pCi/m3) (7.0E-2) Site 4, Fair. Hydro. 1.24E+1 (3/3) 8.55E+0 (14/14) 0 Direct (TLD)5 Gamma (115) 1.00E+0 8.86E+0 (101/101) Quarterly N/A (5.26E+0 to 1.40E+1) (1.2 mi.,WNW) (1.10E+1 to 1.39E+1) (5.86+0 to 1.18E+1) ( R/hr) ' Site 52 Monticello, 1.13E+13/3) N/A 0 Gamma (17) 1.00E+0 8.97E+0 (17/17) y SpecialInterest N/A 4.80E+2 (5.66E+0 to 1.26E+1) All < LLD Road 11 (13mi., NNE) (1.00E+1 to 1.26E+1) All < LLD 0 Surface Water H-3(36) (pCi/I) N/A Gamma Spec (36) I 1.82E+0 All < LLD All < LLD 0 Mn-54 (1.5E+1) ' 1.95E+0 All < LLD All < LLD 0 Co-58 (1.5E+1) 4.81E+0 All < LLD All < LLD 0 Fe-59 (3.0E+1) All < LLD All < LLD 0 Co-60 2.00E+0 l (1.5E+1) 4.44 E+0 All < LLD All < LLD 0 Zn-65 (3.0E+1) I 3.46E+0 All < LLD All < LLD 0 Zr-95 (3.0E+1) 254E+0 All < LLD All < LLD 0 Nb-95 (1.5E+1) 1.66E+0 All < LLD All < LLD 0 - Cs-134 (1.5E+1) Table 10 - Radiological Environmental Monitoring Program Summary for 1996 t _ _ ._m. _ _._ _ _ . _ _ _ _ . . -_.___-.m. - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ - _ ___m_ ___._____a _- - - _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ .____
.. , = _ . . ... . . . . .- .. .-. - ~ _ - ... ._- . - , _ . . . - . - .. . - . . .~ . . . . . . ..
Virgil C. Summer Nuclear Station Docktt No. 50-395 ' i Fairfie!d County, South Carolina Reporting Period: 1/1/96 -12/31/96 - Location with Highest Annual Mean Number of Mediurn or Type and Total Lower Linut Allindicator Locations Control Locabons Nontoutine 8 Reported * ' Pathway Nurnber of of Mean' (#/ total #) Name Mean (#/ total #) Mean' (#/ total #) r Sampled (Unit of Analyses Detection' (Range) (Distance & Directen) (Range) (Range) Measurements Measurement) Performed' Actual (Max.) Surface Water Cs-137 4.34E+0 All < LLD All < LLD 0 (Continued) (1.8E+1) Ba-140 1.25E+1 All < LLD All < LLD 0 , (6.0E+1) La-140 4.42E+0 All < LLD All < LLD 0 ! (1.5E+1) t Ground Water 4.80E+2 All < LLD All < LLD 0 H-3(12) (pCi/I) N/A Gamma Spec (12) ! Mn-54 1.76E+0 All < LLD All < LLD 0 (1.5E+1) Co-58 1.78E+0 A1: < LLD All < LLD 0 to (1.5E+1) Fe-59 3.63E+0 All < LLD All < LLD 0 (3.0E+1) ' Co-60 1.99E+0 All < LLD All < LLD 0 (1.5E+1) Zn-65 3.86E+0 All < LLD All < LLD 0 (3.0E+1) Zr-95 3.27E+0 All < LLD All < LLD 0 (3.0E+1) Nb-95 1.88E+0 Ali < LLD All < LLD 0 (1.5E+1) Cs-134 1.69E+0 All < LLD All < LLD 0 (1.5E+1) Cs-137 1.87E+0 All < LLD All < LLD 0 (1.8E+1) Ba-140 5.88E+0 All < LLD All < LLD 0 (6.0E+1) La-140 2.47E+0 All < LLD All < LLD 0 (1.5E+1) Table 10 - Radiological Environmental Monitoring Program Summary for 1996 i
Virgil C. Summer Nuclear Statiors Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/96 -12/31/96 Location with Highest Annual Mean Number of All Indicator Loca'.ans Control Locations Nonroutine Medium or Type and Total Lower Limit Narne Mean* (#/ total #) Mean' (#/ total #) Reported' Pathway Number of of Mean' (*n. sal #) Detr.ctien* ; Range) (Range) (Range) Measurements Sampled (Unit of Analyses (Distance & Diredion) Measuremer:0 Performed' Actual (I Aax.) ' 2.55'd+0 Site 28, Nuc. Tmg. 4.14E+0 (12/12) 2.34E+0 (11/12) 0 , Drinking Water
- Gross Beta (36) 3.20E+0 (23/24)
(pCi/l) (4.05+G) (1.40E+0 to 7.12E+0) Center (2.57E+0 to 7.12E+0) (1.80E+0 to 2.91E+0) (2.6 mi. SSE) 4.76E+2 All < LLD All < LLD H-3 (36) (2.OE+3) Gamrna Spec (36) 3.66E+ 0 All < LLD All < LLD 0 Mn-54 (1.5E+ 1) 3.72E+ 0 All < LLD All < LLD 0 Co-58 (1.5E+ 1) Fe-59 7.09E+ 0 All < LLD All < LLD 0 (3.0E+ 1) 4.06E+ 0 All < LLD All < LLD 0 Co-60 ca (1.5E+ 1) Zn-65 7.98E+0 All < LLD All < LLD 0 (3.0E+ 1) Zr-95 6.13E+ 0 All < LLD All < LLD 0 (3.0E+ 1) Nb-95 5.42E+ 0 All < LLD All < LLD 0 (1.5E + 1) ; l-131 4.36E-1 All < LLD All < LLD 0 (1.0E+ 0) Cs-134 3.72E+ 0 All < LLD All < LLD 0 (1.5E + 1) Cs-137 3.74E+ 0 All < LLD All < LLD 0 (1.8E + 1) Ba-140 1.38E+ 1 All < LLD All < LLD 0 (6.0E+ 1) ; La-140 5.08E+ 0 All < LLD All < LLD 0 (1.5E+ 1) Table 10 - Radiological Environmental Monitoring Program Summary for 1996
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/96 - 12/31/96 - Location with Highest Annual Mean Number of Medium or Type and Total Lower Lirnd All Indicator Locations Control Locations Nonroutine i Pathway Number of cf Mean* (#/ total #) Name Mean* (#/ total #) Mean' (#Rotal #) Reported
- Sampled (Unit of Analyses Detection2 (Range) (Distance & Diredion) (Range) (Range) Measurements Measurement) Performed Actual (Max.)
Grass Gamma Spec (pCi/kg wet) (35) 1-131 3.52E+1 All < LLD All < LLD 0 (6.0E+1) Cs-134 2.83E+1 All < LLD All < LLD 0 (6.0E+1) Cs-137 3.97E+1 3.99E+1 (8/23) Site 2 Env. Lab 3.99E+1 (8/11) 3.12E+1 (3/12) 0 (8.0E+1) (1.30E+1 to 5.68E+1) Garden (1 mi ESE) (1.36E+1 to 5.68E+1) (2.62E+1 to 3.90E+1) Broadleaf Gamma Spec Vegetation (36) (pCi/kg wet) 1-131 2.57E+ 1 All < LLD All < LLD 0 (6.0E+ 1) Cs-134 2.23E+ 1 All < LLD All < LLD 0 G) (6.0E+ 1) Cs-137 2.73E+ 1 All < LLD All < LLD 0 (8.0E+ 1) Other Vegetation Gamma Spec (pCi/kg wet) (14) 1-131 1.52E+ 1 All < LLD All < LLD 0 (6.0E+ 1) Cs-134 9.87E+ 0 All < LLD All < LLD 0 (6.0E+ 1) Cs-137 1.22E+ 1 9.54E+0 (2/10) Site 6 Env. Lab 9.54E+0 (2/6) All < LLD 0 (8.0E + 1) (9.40E+0 to 9.68E+0) Garden (1 mi ESE) (9.40E+0 to 9.68E+0) Fish 7 Gamma Spec (pCi/kg wet) (18) Mn-54 1.66E+ 1 All < LLD A!! < LLD 0 (1.3E+ 2) Co-58 2.20E + 1 All < LLD All < LLD 0 (1.3E+ 2) Fe-59 5.92E+ 1 All < LLD All < LLD 0 (2.6E+ 2) Table 10 - Radiological Environmental Monitoring Program Summary for 1996
9 Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/96 - 12/31/96
- Location with Highest Annual Mean Number of Medium or Type and Total Lower Limit AllIndicator Locations 8 Control Locations Nonroutine Pathway Number of of Mean (#/ total #) Name 3 Reported
- Mean (#! total #) Mean' (#/ total #)
Sampled (Unit of Analyses Detection2 (Range) (Destance & Direction) (Range) (Range) Measurements Measurement) Performed Actual (Max.) Fish' (Cont) Co-60 1.85E+1 All < LLD All < LLD 0 (1.3E+2) Zn-65 4.28E+1 All < LLD All < LLD 0 (2.6E+2) Cs-134 1.52E+1 All < LLD All < LLD 0 (1.3E+2) Cs-137 1.74E+1 1.05E+1 (2/12) Site 23. Disc 1.05E+1 (2/6) All < LLD 0 (1.5E+2) (6.04E+0 to 1.50E+1) Canal (Mont. Res.) (6.04E+0 to 1.50E+1) (0.5 mi ESE) Sediment Gamma Spec (6) (pCi/kg)* Mn-54 1.72E+1 All < LLD All < LLD 0 N/A Co-58 1.59E+1 All < LLD All < LLD 0 W N/A Co-60 1.88E+1* 9.44E+1 (4/4) Site 21 Parr Res. 1.13E+2 (2/2) All < LLD 0 N/A (5.72E+1 to 1.69E+2) (2.7 mi SSW) (5.72E+1 to 1.69E+2) Cs-134 1.38E+1 All < LLD All < LLD 0 (1.5E+2) Cs-137 2.05E+2 (4/4) Site 23, Disc 2.25E+2 (2/2) 0 3.41E+2 (2/2) (1.8E+2) (1.09E+2 to 2.77E+2) Canet (Mont. Res.) (1.72E+2 to 2.77E+2) 2.96E+2 to 3.86E+2) (0.6 mi ESE) Table 10 - Radiological Environmental Monitoring Program Summary for 1996
1
- 1. Includes indicator and control analyses. Does not include supplemental l samples. 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 (1.0 pR/hr).
- 6. Elevated levels of Pb-214 and Bi-214 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 Pb-214 and Bi-214 plus other Ra-226 daughter products and Ac-228 plus other Th-232 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.
All measurements had positive results, no MDA values calculated. Table 10 Radiological Environmental Monitoring Program Summary for 1996 33
~
Locaton with Hghest Annual Mean Number of Medium or Pathway Type and Total Lower Limit AllIndicator Locatens Control R, cations Nonroutine Sampled (Unit of Number of of Detection' 2 2 2 Mean (#/ total #) Name (Distance & Mean (#/ total #) Mean (#/ total #) Reported 3 Measurement and Ana!yses Actual (Max.) (Range) Directron) (Range) (Range) Measure-Reporting Penod) Performed ments Air Particulate Gross Beta 4.1 E-3 1.1E-1 (562/564)' Site 13, North Dam 1.3E-1 (52/52) 0 1.2E-1 (153/155) (pCi/m3) (1300) (1.0E-2) (1.3E-2 to 5.5E-1) (2.9 mi NNW) (2.1E-2 to 5.5E-1) (7.9E-3 to 6.1E-1) (1981-1982) 2.7E-2 (456/462)* Site 8. Mon. Res. S of 3.0E-2 (42/42) 2.8E-2 (125/126) (9.3E-3 to 6.6E-2) Rd 224 (1.5 ENE) (12E-2 to 6.0E-2) (1.2E-2 to 5.8E-2) Gamma Spec (3G7) Cs-134 3.0E-3 All < LLD All < LLD 0 (1.0E-2) Cs-137 3.1 E-3 3.2E-3 (22/241) Site 10. Met Tower 3.8E-3 (2/22) 0 4.2E-3 (4/66) (1.0E-2) (1.5E-3 to 5.2E-3) (2.4 mi NNE) (2.5E-3 to 5.2E-3) (3.2E-3 to 5.6E-3) Air Radioiodine 1-131(290) 3.6E-2 All < LLD All < LLD 0 (pCi/m3) (1982) (7.0E-2) Direct (TLD)* Gamma (1220) 0.5 9.9 (915/915) Site 13, North Dam 13.1 (61/61) 0 9.7(305/305) ( R/hr) Monthly N/A (6.7 to 14.7) (2.9 mi NNW) (122 to 14.2) (6.4 to 13.5) (1978-1982) Gamma (161) 0.5 10.2 (154/154) Site 55, St. Bamabas 14.0(7/7) 0 (a Quarterly N/A (6.8 to 14.7) Church (2.8 mi E) (13.1 to 14.7) Surface Water 0 (pCi/I) H-3(43) 1.1 E+3 1 AE+3 (18/29) Site 17, Columbia 1.6E+3 (2/7) 1.2E+3 (b/14) (1981-1982) (2 OE+3) (1.1E+3 to 2.4E+3) Canal (24.7 mi. SE) (1.4E+3 to1.8E+3) (6.7E+2 to 1.6E+3) Gamma Spec (140) Mn-54 2.7E-1 All < LLD All < LLD 0 (1.5E+1) Co-58 2.9E-1 All < LLD A!! < LLD 0 (1.5E+1) Fe-59 6.0E+0 A!! < LLD All < LLD 0 (3.0E+1) Co-60 2.4E-1 All < LLD All < LLD 0 (1.5E+1) Zn-65 7.9E-1 All < LLD All < LLD 0 (3.0E+1) Table 11 - Radiological Environmental Monitoring Program Preopemtional (Baseline) Summary Q
Locabon with Hghest Annual Mean Nurnber of Medium or Pathway Type and Total Lower Limst AllIndicator Control Locations Nonroutine Sampled (Unit of Number of Analyses of Locations Name Mean* (#, total #) z Reported
- a Mean (#! total *)
Measurement and Performed Detectx)n' Mean (#/ total #) (Distance & (Range) (Range) Measure-Reporting Penod) Actual (Max.) (Range) Diredion) ments Zr-95 5.2E-1 All < LLD All < LLD 0 (1.5E+1) ! Nb-95 3.3E-1 All < LLD All < LLD 0 (1.5E+1) Cs-134 3.0E-1 All < LLD All < LLD 0 (1.5E+1) Cs-137 2.2E-1 All < LLD All < LLD 0 (1.8E+1) Ba-140 2.2E+0 All < LLD All < LLD 0 (6.0E+1) La-140 5.5E-1 All < LLD All < LLD 0 (1982 only) (1.5E+1)
* e 6. Onsde 9.0E+2 1.5E+3 (16/16) 1.6E+3 (8/8) 1.3E+3 (13/13) l 0 (198 1982) (2.0E+3) (9.5E+2 to 2.3E+3) (25 (9.5E+2 to 2.3E+3) (1.0E+3 to 1.9E+3)
Gamma Spec
$ (32)
Mn-54 3.7E+0 All < LLD A', < LLD 0 (1.5E+1) Co-58 3.8E+0 All < LLD All < LLD 0 (1.5E+1) Fe-59 7.8E+0 All < LLD All < LLO O (3.OE+1) Co-60 3.8E+0 All < LLD All < LLD 0 (1.5E+1) - Zn-65 8.1 E+0 All < LLD A!! < LLD 0 (3.0E+1) Zr-95 6.8E+0 All < LLD All < LLD 0 (1.5E+1) Nb-95 4.6E+0 All < LLD All < LLD 0 (1.5E+1) Cs-134 3.7E+0 All < LLD All < LLD 0 (1.5E + 1) Cs-137 3.8 E+0 All < LLD All < LLD D (1.8E + 1) Table 11 - Radiological Environmental Monitoring Program Preoperational (Baseline) Suramary
m A Location with Highest Annual Mean Nismber of I Medium or Pathway Type and Total Lower Limit AB Indicator Locations Controi Locations Nonroutine Sampled (Unit of 2 Number of Analyses of Mean (#itotal#) Name Mear,' (#! total #) 2 Reported' Mean (#! total #) Measurement and Performed Detecton' (Range) (Distance & (Range) (Range) Measure-Reporting Penod) Actual (Max.) Direction) ments Ba-140 1.9E+1 All < LLD All < LLD 0 (6.0E+1) La-140 5.0E0 All < LLD All < LLD 0 (1982 only) (1.5E+1) Dnnking Water' Gross Beta' (2.0E+0) (DCill) (1981-1982) H-3(14) 6.3E+2 7.8E+2 (6/14) Site 28, 8.4E+2 (3/7) 0 (1.0E+3) (6.8E+2 to 9.8E+2) Jenkinsville (7.0E+2 to 9.8E+2) (2.0 mi SE)7 Gamma Spec i (44) Mn-54 3.0E-1 All < LLD 0 (1.5E+1) Co-58 2.7E-1 All < LLD 0 (1.5E+1) Fe-59 9.6E0 All < LLD 0 w (3.0E+1) Co-60 2.6E-1 All < LLD 0 (1.5E+1) Zn-65 3.4E-1 All < LLD 0 (3.OE+1) Zr-95 4.8E-1 All < LLD 0 (1.5E+1) Nb-95 3.4E-1 All < LLD 0 (1.5E+1) 1-131 7.4 E-1 All < LLD 0 (1.0E+0) C -134 2.2E-1 All < LLD 0 (1.0E+1) Cs-137 2.4E-1 All < LLD 0 (1.8E+1)
, Ba-140 2.5E0 All < LLD 0 (6.0E+1)
La-140 4.4E-1 All < LLD 0 (1982 only) (1.5E+1) Table 11 - Radiological EnvironmentalMonitoring Program Preoperational(Baseline) Summary
Location with Highest Annual Mean Number of Medium or Pathway Type and Total Lower Limit All Indicator Locations Control Locations Nonroutine Sampled (Unit of 2 Numberof Analyses of Mean (#, total #) Name 2 Mean (#/ total #) z Reported' Mean (#/ total #) Measurement and Performed Detection' (Range) (Distance & (Range) (Range) Measure-Reporting Period) Actual (Max.) Directen) ments Milk Gamma Spec (pCi/l) (94) (1981-1982) I-131 6.3E-1 All < LLD All < LLD 0 (1.0E+0) Cs-134 3.3E+0 All < LLD All < LLD 0 (1.5E+1) Cs-137 4.6E0 4.1 E+0 (8/47) Site 14. Dairy 4.1 E+0 (8/47) 0 5.7E+0 (37/47) (1.5E+1) (2.8E+0 to 6.1E+0) (5.1 mi., W) (2.8E+0 to 6.1E+0) (3.7E+0 to 9.2E+0) Ba-140 1.1 E+1 A!! < LLD All < LLD 0 (1.5E + 1) La-140 4.4E+0 A!! < LLD All < LLD 0 (1.5E+1) Grass (pCi/kg wet) Gamma Spec (1981-1982) (82) 1-131 6.7E+1 All < LLD All < LLD 0 ca (6.0E+1) Cs-134 2.7E+1 All < LLD All < LLD 0 (8.0E+1) Cs-137 3.3E+1 5.0E+1 (13/51) Site 14, Dairy 5.9E+1 (5/29) 1.3E+2 (6/31) 0 (8.0E+1) (1.6E+1 to 1.6E+2) (5.1 mi W) (1.6E+1 to 1.6E+2) (1.3E+1 to 3.4E+2) Broadleaf Gamma Spec (10) Vegetation (pCi/kg wet) (1980-1982) 1-131 3.7E+1 All < LLD 0 (6.0E+1) Cs-134 1.9E+1 All < LLD 0 (8.0E+1) Cs-137 2.1 E+1 3.1 E+1 (2/7) Site 2. Trans. 3.6E+1 (1/1) All < LLD 0 (8.0E+1) (1.8E+1 to 3.6E+1) Line (Single Value) (1.2 mi SW) Table 11 - Radiological Environmental Monitoring Program Preoperational(Baseline) Summary
Location wrth Highest Annual Mean Number of Medrum or Pathway Type and Total Lower Lirnit AllIndicator Locations Control low 4 Nonroutine Sarnpled (Unit of Nurnber of Analyses a z of Mean (#/ total #) Name Mean (#/ total #) Mean* (#! total #) Reported 3 Measurement and Performed Detection' (Range) (Distance & (Range) (Range) Measure-Reporting Period) Actual (Max.) Direction) ments Other Vegetation Gamma Spec (pCi/kg wet) (32) (1980-1982) Cs-134 8.4E+0 All < LLD All < LLD 0 (8.0E+1) Cs-137 1.0E+1 All < LLD All < LLD 0 (8.0E+1) Fish (pCi/kg wet) Gamma Spec (1980-1982) (92) l Cs-134 1.4E+1 All < LLD All < LLD 0 (1.3E+2) Cs-137 1.8E+1 2.8E+1 (50/71) Site 24, 3.4E+1 (17/23) 3.1E+1 (19/21) 0 (1.3E+2) (1.1E+1 to 1.0E+2) Recreation 1.2E+1 to 1.0E+2) (1.0E+1 to 7.9E+1) Lake (5.5 mi. N) y Co-58 2.6E+1 All < LLD All < LLD 0 (1.3E+2) Mn-54 1.8E+1 All < LLD All < LLD 0 (1.3E+2) Fe-59 9.0E+1 All < LLD All < LLD 0 (2.SE+2) Zn-65 4.1E+1 All < LLD All < LLD 0 (2.6E+2) Co-60 1.8E+1 All < LLD All < LLD 0 (1.3E+2) Sediment (pCi/kg) Gamma Spec (24) (1980-1982) Cs-134 2.3E+1 All < LLD All < LLD 0 (1.5E+2) Cs-137 2.4E+1 1.7E+2 (12/18) Site 21 Parr 2.6E+2 (6/6) 4.2E+2 (6/6) 0 (1.5E+2) (2.6E+1 to 4.5E+2) Reservoir (2.6E+1 to 4.5E+2) (1.8E+1 to 1.0E+3) (2.7 mi, SSW) l Table 11 - Radiological Environmental Monitoring Program Preoperational(Baseline) Summary
l Footnotes j
- 1. Vrlues giver are MDA values calculated from the program data analyses with maximum acceptable LLD values allowed from NRC guidelines given in l pniciitheses.
- 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 measurerr.ent is any confirmed meas'/:ed level of radioactivity in an environmental medium that exceeds the repo: ting 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 l covers the period 1/1/82 -10/22/82.
- 5. Detection sensitivity is approximately 5 mrem /yr (0.5 pR/hr) determined from the analyses of five years of preoperational data.
- 6. No control location was specified for drinking water during the preoperational monitoring period.
- 7. Inconclusive data.
Table 11 - Radiological Environmental Monitoring Program Preoperational(Baseline) Summary 39
l Sample Month Media Location (Week No.) Cause for Exception Air 30 March (13) incomplete sample, power outage. 30 April (17) Incomplete sample, power outage. 6 August-(35) Incomplete sample, power outage. 30 September (38) Sample not collected; damaged filter paper. i 6 October (42) Incomplete sample, loose fitting. Air Radioiodine 30 March (13) Incomplete sample, power outage. 30 . April (17) Incomplete sample, power outage. 6 August (35) incomplete sample, power outage. 6 October (42) Incomplete sample, loose fitting. Surface Water 22 August (31) Incomplete sample. Drinking Water 39 July (28) Grab instead of monthly composite, breaker tripped. 17 August (32) Incomplete sample, water found tumed off. 39 September (36) Incomplete sample, breaker tripped. Grass 2 November (46) Collected but not analyzed, computer anomaly. Direct Radiation 16 First Quarter Lost 32 First Quarter Lost 44 First Quarter Found on ground 46 First Quarter Found on ground 20 Second Quarter Found on ground 10 Third Quarter Found on ground 1 46 Third Quarter Lost 49 Third Quarter Lost 53 Third Quarter Found on ground ' 54 Third Quarter Found on ground 31 Fourth Quarter Lost 33 Fourth Quarter Found on ground 56 Fourth Quarter Found on ground Table 12 - 1996 Environmental Sampling Program Exceptions 40 I o
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