RC-98-0096, Radiological Environmental Monitoring Rept for Period Jan-Dec 1997
| ML20217R039 | |
| Person / Time | |
|---|---|
| Site: | Summer |
| Issue date: | 12/31/1997 |
| From: | Gowdy G, Lavigne D, Orr J SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| RC-98-0096, RC-98-96, NUDOCS 9805130126 | |
| Download: ML20217R039 (48) | |
Text
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South Carolina Electric & Gas Company w
A' g
Virgil C. Summer Nuclear Station Jenkinsvdle. SC 29065
- "' D" "
SCE&G
%$Elisi ese.w.cmuy April 30, 1998 RC-98-0096 Mr. L. A. Reyes Regional Adminstrator U. S. Nuclear Regulatory Commission Region 11, Suite 2900 I
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 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT (RR 8300)
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, rs Y#
David A. Lavig e sbr Enclosure c:
J. L. Skolds (w/o enclosure)
W. F. Conway R. R. Mahan (w/o enclosure)
J. B. Knotts, Jr.
R. J. White (w/o enclosure)
INPO Records Center L. M. Padovan J&H Marsh & McLennan J. W. Sowell NSRC J. A. Orr DMS (RC-98-0096) l
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NRC Resident inspector File (818.02-2) 9805130126 971231 7
PDR ADOCK 05000395 X, k R
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, NUCLEAR EXCELLENCE - A SUMMER TRADITION!
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s VIRGIL C. SUMMER ENVIRONMENTAL SURVEILLANCE LABORATORY JENKINSVILLE, SOUTH CAROLINA RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPERATING PERIOD JANUARY 1,1997 - DECEMBER 31,1997 APRll 1998
-an TSCE&G A SCANA COMPANY Prepared by:
seph A. Orr, Health Physicist Reviewed by:
Approved by:
k.
l G.M. dowdy, Health Physicist [
1..A. Blue Man'Afer~
Health Physics and Radwaste Services 1
s Executive Summarv 1.
Results of the 1997 Land Use Census indicated that the critical receptor (E,1.2 mi) no longer keeps a garden. Thus, the previous second highest receptor (ENE,1.6 mi) is the new critical receptor. There were 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.
There was no detection of radioactivity in environmental media attributed to gaseous effluent releases from VCSNS.
4.
Activated corrosion products attributed to liquid effluent releases from VCSNS were detected in only one sediment sample. Radiation dose to the general public attributed from this activity is a small fraction of the observed variation in natural background radiation.
5.
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.
6.
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.
1 1
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4 BBJ.E OF CONTENTS Page l
Introduction 1
l Description of the Radiological Environmental Monitoring Program 2
Land Use Census 4
Monitoring Results and Discussion 5
Conclusion 8
li
LIST OF TABLES TABLE P_ age 1
Monitoring Methods for Critical Radiation Exposure 3
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Pathways 2
Radiological Environmental Monitoring Program 9
I Required Sampling Site Locations 3
Results of the 1997 EPA Intercomparison Program 11 3a Results of the 1997 Environmental 13 Intercomparison with Independent Lab l
4 Results of the 1997 Intercomparison Program with 14 Independent Lab 5
Summary of the 1997 Intercomparison Program 16 with SCDHEC 6
Results of the Environmental Dosimetry 17 Intercomparison with the NRC TLD Direct Radiation Monitoring Network 7
Results of the 1997 Land Use Census Verification 18 7a Critical Receptor Evaluation for 1997 19 8
Radiological Environmental Monitoring Program 20 l
Specifications 9
Supplemental Radiological Environmental 25 Monitoring l
10 Radiological Environmental Monitoring Program 28 l
Summary for 1997 11 Radiological Environmental Monitoring Program 34 Preoperational(Baseline) Summary 12 1997 Environmental Sampling Program Exceptions 40 i
13 1997 Activated Corrosion Product Activity in 7
Stdiment ill
LIST OF FIGURES Figure 1-1 Controi site Locations (50 mile radius around the Virgil C. Summer Nuclear Station) 1-2 Radiological Monitoring Program Local Indicator Sample Sites (5 mile radius around Virgi. C.
Summer Nuclear Station) 1-3 Radiological Monitoring Program Local Indicator Sample Sites (1 mile radius around Virgil C.
summer Nuclear Station) 1 Iv j
INTRODUCTION Virgil C. Summer Nuclear Station (VCSNS) utilizes a pressurized water reactor rated at 2900 MWt (990 MWe gross). The station is located adjacent to the Monticello Reservoir near Jenkinsville, South Carolina and approximately 26 miles northwest of Columbia. VCSNS achieved initial criticality on October 22,1982, reached 50% power December 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 (spring of 1996), the plant was uprated to 2900 MWt (990 MWe gross). VCSNS is currently operating in its eleventh fuel cycle.
VCSNS is operating in conjunction with the adjacent Fairfield Pump Storage Facility (FPSF) which consists of eight reversible pump-turbine units of 60 MWe capacity each.
During periods of off-peak power demand, base load generating capacity is used to pump water from Parr Reservoir to Monticello Reservoir. Monticello Reservoir has a surface area of approximately 6800 acres and lies about 150 feet above Parr Reservoir whose full pool area is approximately 4400 acres. The pump-turbine units operate in the generating mode to meet peak system loads while Monticello Reservoir also provides condenser cooling water for VCSNS. Cooling water intake and discharge structures are separated by a jetty to ensure adequate circulation within the reservoir.
VCSNS is located in Fairfield County which, along with Newberry County, makes up the 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 j
greater than 20 miles from the VCSNS.
1 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.
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 1997. 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.
Sample media and analysis sensitivity requirements have been established to ensure that the maximum dose pathways are monitored and sensitivities represent a small fraction of annual release limits.
Effluent dispersion characteristics, demography, hydrology and land use have been considered in selection of environmental sampling locations. These criteria were used to establish both the preoperational and operational phases of the Radiological Environmental Monitoring Program. Elements of the program monitor the impact of gaseous and liquid effluents released from VCSNS.
Specific methods used in monitoring the pathways of these effluents which may lead to radiation exposure of the public, based on existing demography, are summarized below in Table 1. Requirements of the Radiological Environmental Monitoring Program are specified in the VCSNS Offsite Dose Calculation Manual (ODCM). Elements of the program monitor the impact of gaseous and liquid effluents released from VCSNS.
Monitoring sites indicative of plant operating conditions are generally located 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 Figure 1-1 shows the 50-mile i
ingestion pathway zone for the plant with monitoring sites at distances greater than 10
. miles from the plant.
These locations indicate regional fluctuations in background radiation levels. Figure 1-2 shows environmental sampling locations within 10 miles of the plant. Figure 1-3 is a detailed map showing monitoring locations in close proximity to the plant (site boundary and closer).
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l Effluent ReleasfLIyp.e Exoosure Pathway Monitoring 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 (Forege) Sampling, Air Sampling Liquid Fish (Ingestion)
Surface Water Sampling, Bottom 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 Water Sa npling Table 1 - Monitoring Methods for Critical Radiation Exposure Pathways 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 l' cal environmental radioactivity concentration.
Environmental data is gathered through muliple types of sampling and measurements at specific locations. Several multipin %mpling combinations are in use around the VCSNS.
For example, all air sarr.pling 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 (1.0 mi ESE) and 7 (1.0 mi E) have broadleaf vegetation gardens 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.
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 controi location for liquid effluent comparisons is at Site 22, Neal Shoals (30.0 mi NNW) on the Broad River.
Quality of Analytical measurements is demonstrated by participation in five laboratory intercomparison programs. Results of the 199/ EPA Intercomparison Program are included in Table 3.
Table 3a gives results of the intercomparison with an 3
l l
Independent vendor used to supplement the more limited EPA program available since 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 Carolina Department of Health and Environmental Control (SCDHEC) is outlined in Table 5.
Results are reported by SCDHEC.
Results of an environmental dosimetry intercomparison with the NRC are shown as Table 6.
Several disagreements between environmental count room and vendor results were noted in 1997. First quarter results showed a greater than factor of two difference in gross beta air filter values. Numerous i
recounts and discussions with the vendor could not resolve this difference.
The conservative value obtained by the environmental count room shows that the protection of the public is not jeaporidized by potential problems with this counting system. Follow up checks will be made in 1998 to reestablish the reliability of this system. '3'l in liquid was also in disagreement. This was attributed to the small amount of *1 in the sample and long wait between reference time and count time. A detailed reevaluation gave much closer, but still conservative results. Both gamma isotopics in the third quarter missed
- Ce. Changing the software analysis sensitivity produced small peaks at the "'Ce energy. This may i icate a need to lower sensitivity parameters set for some analyses.
The results of each^ f these five quality control checks of the Radiological Environmental Monitoring progr verify the technical credibility of analytical data generated and reported by the ogram.
I 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 1997 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 1997 land use census, the critical pathway location to be used in the ODCM for offsite organ dose calculations was changed from 1996 E,1.2 miles - residence / garden to ENE,1.6 miles - residence / garden / beef / goat due to removal of the garden from the E,1.2 mile location. The new critical pathway location was found to have a calculated dose of 2.01E+0 mrem /yr. In comparison, the ODCM required environmental gardens (E 1.0 and ESE 1.1 miles) were found to have calculated doses of 3.71E+0 and 2.34E+0 mrem / year, higher than calculated doses for any garden locations of real individuals. In addition, there were no milking animals or dairy activity found within 5 miles of VCSNS. Therefore, 4
changes to the ODCM gaseous effluent calculations or garden sample locations are not indicated.
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)
O MONITORING RESULTS AND DISCUSSION 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. The results of the Radiological Environmental Monitoring Program for 1997 are summarized in Table 10. For comparison, preoperational data is summarized in Table 11.
During 1997, the Radiological Environmental Program attained a program compliance rate of approximately 99%.
A listing of program exceptions and their respective causes are included in Table 12. Detailed analysis of the impact of these omissions verified that program quality has not been affected.
Airborne gross beta activity measufed in air particulate samples collected at indicator locations around VCSNS were consistent with preoperational levels and not statistically different from control location 9.
Mean preoperational control and indicator levels were 2.7E-2 and 2.8E-2 pCl/m, respectively. Mean indicator and control location measurements during 1997 were 1.90E 2 and 1.96E-2 pCi/m, respectively. The highest site specific mean activity (1.96E-2 pCi/m ) was measured at indicator location no. 8 (Monticello Res. South of Rd 224). A comparison was performed between the 1997 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 22 era and *K were detected. Minimum detectable activity (MDA) levels 7
for'dCs, ' 7Cs a'nd ' 'I were 8.77E-3, 8.72E-3 and 1.71E-2 pCi/m, respectively. The results support the gaseous effluent release data reported in the 1997 Annual Effluent and Waste Disposal Reports for VCSNS. During 1997,7.01E-5 Cl of iodine and 5.00E-5 Ci of particulates were released. These releases are not discernible in atmospheric samples due to atmospheric dispersion during these releases.
Environmental dosimetry measurements during 1997 did not differ significantly from preoperational measurements.
Indicator and control dosimetry measurements also showed no appreciable differences during 1997. Comparison 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 1.17E+1 R/hr. This value is slightly lower than in 1996 and 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 1997 indicated a total of 2.55E-1 Ci of fission and activation gases released from VCSNS. Radioactive gaseous effluent at this level 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 5
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are maintained below required LLD's). Liquid effluent release data repoded for 1997 in 1
the Annual Effluent and Waste Disposal Repod indicated a total of 4.36E-2 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 spectroscopy analysis.
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Surface water tritiurn activity was detected in 3 of 12 samples from site 23 Lake Monticello Discharge canal. The activity ranged from 5.28E+2 to 6.40E+2 pCi/ liter only slightly above the MDA value of 5.27E+2pCl/ liter.
This activity is less than the l
preoperational mean of 1.4E+3 pCl/ liter. Total tritium release in liquid effluents during l
1997 was reported to be 8.22E+2 Ci; a level not usually discernible in surface water due to dilution available during the releases and the detection limitations of analytical equipment i
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 detectable activity (MDA) levels for tritium at all indicator and control sites was 5.00E+2 pCi/l.
l-Gamma spectroscopy measurements of drinking water samples collected from the Jenkinsville and Columb!a water supplies did not indicate the presence of activated corrosion or fission product activitg above the MDA's of the respective radionuclides.
Naturally occurring radionuclides, 2 Ra,2"Pb and "Bi, were observed in the Jenkinsville 2
water supply (sample #28) at levels above those found in surface water. These elevated l
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 1
than 5 miles from VCSNS.
The highest mean gross beta activity in drinking water was measured at site 28 (Jenkinsville) at a level of 2.55E+0 pCi/ liter, about the same as last year. There was no detectable tritium in drinking water samples. The tritium MDA value is 5.07E+2 pCl/ liter.
The result compares to a preoperational mean of 7.8E+2 pCi/ liter.
There were no milk samples collected in 1997. This reflects the reduction of control / indicator locations in 1996. 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, l
grass, or air samples at concentrations greater than required LLD's. Sampling should continue for 2 months after plant releases are reduced to less than the trigger levels and milk contamination has returned to background levels.
Grass samples collected from sites 2 and 7 with site 18 as a control. Site 2 indicated ' 7Cs in 9 of 12 samples at concentrations ranging from 1.73E+1 to 6.23E+1 pCl/kg, below the required MDA of 8.00E+1 pCi/ kg and maximum preoperational control 6
activity of 3.4E+2 pCl/kg. A review of site #2 air sample results indicated that no '37Cs was detected during 1997.
Broadleaf vegetation collected from gardens at location numbers 6,7 and 18 were the principal food p'roducts analyzed during 1997. Maximum minimum detectable activity (MDA) levels for
'Cs, 137Cs and ' 'I were 1.91E+1, 3.97E+1 and 1.62+1 pCi/kg, respectively. '37Cs was detected at Site 6 in 2 of 12 samples ranging from 7.3E+0 to 1.46E+1 pCi/kg, well below the required MDA of 8.0E+1 pCi/kg and below the preoperational indicator range of 1.8E+1 to 3.6E+1 pCi/kg. Site 6 air sample results
(
indicated that no ' 7Cs was detected.
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Other vegetation sampled in 1997 included corn, tomatoes and tumips representing the non-leafy vegetation group.
Only naturally-occurring radionuclides were detected during the year in any vegetation sample at concentrations consistent with those observed during the preoperational period..
Fish species sampled at two indicator and one control location included bass, I
bream, catfish and carp. ' 7Cs was detected in 3 of 12 samples collected at indicator locations and 1 of 6 at the control location. The highest mean ' 7Cs concentration was
'7 1.05E+1 pCi/kg (Parr Res 2.7 mi SSW).
Cs was detected at the control site Shoals,30 mi, NNW) at a concentration of 1.14E+1 pCi/kg. Since the levels of Cs in l
fish at control location is greater than the indicator locations and not significantly different L
from 1996 results, the ' 7Cs radioactivity can be attributed mainly to residual fallout.
Gamma spectroscopy measurements of sediment samples collected during 1997 resulted in detection of "Co that is attributed to VCSNS operation. "Co was detected in i
one sample taken at the Discharge Canal at Lake Monticello (Site 23) at a concentration of 9.76 pCi/kg. "Co was detected in Parr Res. (site 21) and Monticello Res. (site 23) in 1996 at an average concentration of 9.44E+01 pCi/kg, a factor of 10 higher. '37Cs was' detected in all four indicator samples at an average concentration of 1.06E+2 pCi/kg. The average ' 7Cs concentration at the control location (site 22) was 1.18E+02 pCi/kg, greater than the average indicator activity.
Radiation doses to man, corresponding to the concentrations of activity in sediment, were calculated using Regulaton' tuide 1.109 methodology. A 500 hourg/ ear exposure to shoreline sediment containing maximum and mean concentrations of Co, and'7Cs, a shoreline width factor of 1 and a sediment mass of 40 kg/m was assumed.
2 The results are included in Table 13 and show a maximum dose to the public from contaminated sediment to be 2.54E-2 mrem for 1997 based on sediment samples from Monticello Reservoir.
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Corresponding Calculated Annual l
Location Radionuclide Activity (pCilkg)
Dose Equivalent (mremlyr)
Total Body Monticello Maximum Mean Maximum Mean Reservoir "Co 9.76E+0 9.76E+0 l
(Site 23)
- Cs 6.00E+1 5.13E+1 Total 6.98E+1 2.54E-2 2.47E-2 Parr Reservoir "Co (Site 21)
"Cs 1.92E+2 1.62E+2 Total 1.92E+2 1.61 E-2 1.36E-2 Table 13 - 1997 Fission and Activated Conosion Product Activityin 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 one sediment sample from Lake Monticello. 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 reported whole body and organ dose for liquid effluents during 1997 was 9.80E-3 and 1.09E-2 j
mrem, respectively (VCSNS Annual Effluent Release Report,1997). 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 I
adequacy of source control at VCSNS and conformance of station operation to 40CFR190 i
and 10CFR50, Appendix I design objectives.
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Site Description Distance' Direction Sample Type (s)"
d No.
(Miles) 1 Borrow Pit 1.2 1.79.8 S DQ 2
Transmission Line 1.1 225.0 SW AP, Rl, DQ 3
Firing Range 1.2 270.0 W DQ 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 7
Environmental Lab Garden 1.0 97.8 E AP RI,DO, GA 8
Monticello Res. S of Rd 224 1.5 62.0 ENE DQ 9
Ball Park 2.3 41.6 NE DQ 10 Meteorological Tower #2 2.5 25.5 NNE DQ 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,DQ,DW 18 Residence / Pine Island Club
- 16.5 165.0 S DQ,GA 19 Residence /Little Saluda 21.0 224.0 SSW DQ 20 Residence /Whitmire 22.0 309.5 NW i DQ 21 Parr Reservoir 2.7 199.5 SSW SW,FH,BS 22 Neal Shoals 26.0 343.1 NNW SW,FH.BS 23 Discharge Canal (Mont, Res.)
0.5 104.5 ESE SW,FH,BS 26 On Site Well (P2) 460 Ft 270.0 W GW 27 On Site Well(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,RI 31 McCrorey-Liston School 6.6 11.5 NNE DQ 32 Clark Bridge Road and Brooks Drive 4.6 24.0 NNE DQ 33 Rd 48 near Hwy 213 4.2 68.0 ENE DQ 34 Rd 419 North of Hwy 60 4.9 111.0 ESE DQ 35 Glenn's Bridge Road 4.6 132.0 SE DQ 36 Woods Behind Jenk. Post Office 3.1 151.0 SSE DQ 37 Residence 4.9 304.8 NW DO 39 LMWTF 14.0 168.0 SSE DW 41 Below Catwalk at Trestle 3.8 182.0 S DO 42 Broad River Rd (Residence Peak) 3.8 198.0 SSW DQ 43 Hwy 176 and Rd 435 5.2 236.0 SW
'DQ 44 Rd 28 at Cannon's Creek 2.8 256.6 WSW DQ 45 Rd 33 at Pomaria 5.8 253.2 WSW DQ 46 Rd 28 at Heller's Creek 3.7 291.5 WNW DQ 47 Fairfield Tailrace 1.0 316.0 NW 1 DQ 52 Monticello (Rd 11) 3.8 13.0 NNE DQ Table 2 - Required Sampling Site Locations 9
l Site Description Distance' Direction" Sample Type (sf No.
(Miles) 53 Rd 359 3.0 46.5 NE DQ 54 Jenkinsville School 1.7 72.5 ENE DQ 55 St. Bamabas Church 2.8 91.5 E DQ 56 Old Jenkinsville Dinner 2.0 144.0 SE DQ 58 Residence 2.5 157.0 SSE DQ 59 Nuclear Training Center (EOF)*
2.6 170.2 SSE DQ.AP,GW 60 Rd 98 near Rd 28 3.5 274.6 W DQ Table 2 - Required Sampling Site Locations Footnotes i
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 Radiciodine 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 the ODCM), this site will be reactivated.
1 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.
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6.
Site 28 for drinking water and site 59 for quarterly TLD measurements and con-I tinuous air sampling are co-located at the location of the SCE&G Nuclear Training l
Center which also serves as the Virgil C. Summer Station Emergency Offsite Facility.
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Comparison Study Date Nuclide EPA Value Laboratory Agree-(Measurement Unit)
(controllimits)
Results ment (tio)
Gamma in Water 06/06 "Ba 25 25 Yes (pCl/ liter)
(16-33.7)
"Co 18 17.3 Yes (9.3-26.7)
"Zn 100 105 Yes (82.7-117.3) j
'"Cs 22 20.3 Yes I
(13.3-30.7) i "Cs 49 52 Yes (40.3-57.7) 11/07 "Ba 99 98 Yes (81.7-116.3)
"Co 27 26 Yes (18.3-35.7)
"Zn 75 78 Yes (61.9-88.9)
- Cs 10 10 Yes (1.3-18.7)
- Cs 74 77 Yes (65-83)
Gross Beta in Water 07/19 Beta 15 15 Yes*
(pCl/ liter)
(6-23) 07/18 Beta 15 16 Yes (6-24) lodine in Water 02/07
- l 86 90 Yes (pCi/ liter)
(70-102) 09/19
'3'l 10 12 Yes (0.0-24)
Laboratory Blind 04/15 Alpha 48 35 Yes (pCi/ liter)
(27-69)
Beta 102 101 Yes*
(76-127)
"Co 21 21 Yes*
(12-30)
- Cs 31 27 Yes*
(22-40)
"Cs 22 21 Yes*
(13-31)
Table 3 - Results of the 1997 EPA Intercomparison Program (Lab Code FL) 11
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l Comparison Study Date Nuclide EPA Value Laboratory Agree-j (Measurement Unit)
(control limits)
Results ment (iio)
Laboratory Blind 10/15 Alpha 50 41 Yes (pCl/ liter)
(28-72)
Beta 143 118 Yes (106-181)
"Co 10 10 Yes
]
l (3-17)
- Cs 41 38 Yes (32-50)
"'Cs 34 35 Yes (25-43)
Tritium in Water 03/07 "H
7900 7703 Yes (pCi/ liter)
(6529-9270) 09/08 11010 10970 Yes (10000-12920) l Footnotes l
(*)
These are corrected laboratory results from a reanalysis. The original results transmitted to the EPA were calculated using incorrect volume.
Table 3 (cont.) Results of the 1997 EPA Intercomparison Program (Lab Code FL) l l
l 12 l
Comparison Study Date Nuclide(s)
Vendor Lab Env Lab Agree-(Measurement Unit)
Results' Results ment Gross Beta Air Filter (pCl) 03/20 N/A 28 59 No' Gamma Isotopic Liquid,4 liter 03/20
"'I 25 48 No' (pCl/l)
"'Ce 251 255 Yes
Cr 419 429 Yes
'"Cs 155 144 Yes
' 'Cs 123 132 Yes ssCo 86 95 Yes "Mn 190 202 Yes "Fe 155 178 Yes esZn 179 193 Yes "Co 190 195 Yes Gamma Isotopic Soil 03/20
"'Ce 170 153 Yes (p=1.5 g/cc) (pCi/kg) 5'Cr 284 262 Yes
'"Cs 105 82 Yes
'7Cs 210 174 Yes saCo 58 52 Yes "Mn 129 113 Yes "Fe 105 114 Yes
- Zn 121 126 Yes "Co 129 114 Yes Gamma Isotopic Composite 03/20
"'Ce 227 237 Yes Air Filters (pCl) 5'Cr 380 402 Yes
'"Cs 140 119 Yes
~
'37Cs 111 119 Yes "Co 78 88 Yes "Mn 173 191 Yes 5'Fe 141 157 Yes 85Zn 162 198 Yes "Co 173 181 Yes Charcoal Cartridge (pCi) 09/18
- l 60 62 Yes Gamma Isotopic Liquid,1 liter 09/18
- l 94 108 Yes (pCi/l)
"'Ce 60 N/O No'
Cr 239 248 Yes
'"Cs 80 75 Yes
'*7Cs 84 90 Yes seCo 47 53 Yes "Mn 69 77 Yes 5'Fe 94 104 Yes
'5Zn 154 176 Yes "Co 155 162 Yes Gamma Isotopic Soil 09/18
"'Ce 134 N/O No' (p=1.0 g/cc) (pCi/kg)
Cr 533 530 Yes
'"Cs 179 166 Yes
' 'Cs 188 181 Yes
Co 106 115 Yes "Mn 155 142 Yes
Fe 209 197 Yes
- Zn 345 329 Yes "Co 346 338 Yes
' The Independent Laboratory was Analytics, Inc. for 1997. This data is supplemental to Table 3.
- See discussion in text (page 4). N/O is not observed in sample count.
Table 3a - Results of the 1997 EnvironmentalIntercomparison Program with Independent Lab 13
Comparison Stt;dy Qtr.
Nuclide Env Lab Second Lab Agree-(Measurement Unit)
Results Results' ment Tritium ( Ci/ml) (Analytics)
First "H
4.48E-3 4.68E-3 Yes Gross Beta Liquid ( Ci/ml)
First N/A 5.01 E-4 5.34E-4 Yes Gross Alpha Liquid (pCi/ml)
First N/A 1.52E-3 1.57E-3 Yes Charcoal Cartridge ( Ci)
Second
"'I 1.48E-1 1.50E-1 Yes Gross Alpha Filter ( Ci)
Second N/A 1.88E-3 1.91 E-3 Yes Gross Beta Filter ( Ci)
Second N/A 4.69E-3 4.58E-3 Yes Gas Sample,1 liter ( Ci)
Second "Xe 7.26E+0 6.52E+0 Yes 85Kr 1.02E+2 9.90E+1 Yes Gamma Isotopic Liquid,4 liter Third "Ce 4.49E-3 4.32E-3 Yes
( Ci/ml) 5'Cr 1.96E-2 1.90E-2 Yes
'"Cs 3.17E-3 3.32E-3 Yes j
'7Cs 3.56E-3 3.41 E-3 Yes I
Co 2.70E-3 2.50E-3 Yes s8 "Mn 3.19E-3 2.98E-3 Yes i
SSFe 6.28E-3 5.75E-3 Yes esZn 7.32E-3 6.73E-3 Yes 80Co 6.53E-3 6.32E-3 Yes Gamma isotopic Simulated Third "Ce 2.55E-2 2.60E-2 Yes Gas (pCi/ml) 5'Cr 1.12E-1 1.14E-1 Yes "Cs 1.77E-2 2.00E-2 Yes
'37Cs 1.96E-2 2.05E-2 Yes seCo 1.48E-2 1.50E-2 Yes "Mn 1.72E-2 1.79E-2 Yes
'SFe 3.38E-2 3.46E-2 Yes 85Zn 3.90E-2 4.05E-2 Yes 5 Co 3.51 E-2 3.80E-2 Yes Tritium ( Ci/ml) (VCSNS)
Third "H (distilled) 4.37E-2 4.55E-2 Yes
( Ci/ml) (VCSNS)
H (undistilled) 4.60E-2 4.75E-2 Yes Silver Zeolite Cartridge (pCi)
Fourth "I
4.86E-1 4.02E-1 Yes Gamma Isotopic Soil / Rock Fourth "Ce 2.14E-2 2.06E-2 Yes (pCi) 5'Cr 4.93E-2 4.55E-2 Yes
'"Cs 1.15E-2 1.21 E-2 Yes
'37Cs 1.33E-2 23E-2 Yes seCo 9.07E-3 0.03E-3 Yes "Mn 1.11 E-2 1.01 E-2 Yes SSFe 1.15E-2 1.02E-2 Yes esIn 2.03E-2 1.81 E-2 Yes e Co 1.19E-2 1.11 E-2 Yes
' The Second (Independent) Laboratory was Analytics, Inc. for 1997 Table 4 - Results of the 1996 Intercomparison Program with Independent Lab 14
Comparison Study Qtr.
Nuclide Env Lab Second Lab Agree-(Measurement Unit)
Results Results' mer.t Gamma Isotopic Filter,57mm Fourth
'"Ce 4.27E-2 4.31 E-2 Yes
( Ci) 5'Cr 9.19E-2 9.51 E-2 Yes
' 'Cs 2.10E-2 2.53E-2 Yes
'37Cs 2.61 E-2 2.56E-2 Yes saCo 1.79E-2 1.68E-2 Yes 5dMn 2.28E-2 2.12E-2 Yes 58Fe 2.38E-2 2.14E-2 Yes 55Zn 4.18E-2 3.78E-2 Yes 5 Co 2.31 E-2 2.31 E-2 Yes Gamma Isotopic Filter, 47mm Fourth
'"Ce 4.11 E-2 4.15E-2 Yes
( Cl) 5'Cr 1.27E-1 1.23E-1 Yes
'3dCs 1.46E-2 1.64E-2 Yes
'37Cs 4.10E-2 3.95E-2 Yes seCo 1.25E-2 1.23E-2 Yes 5dMn 3.31 E-2 3.09E-2 Yes 58Fe 1.37E-2 1.24E-2 Yes 55Zn 6.52E-3 6.07E-3 Yes 5 Co 8.24E-3 8.12E-3 Yes 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 15
Pathway (Units)
Sample Frequency Nuclide' l
Location Surface Water No. 21 Monthly
'H I
(pCi/ liter)
Mixed Gamma No.22 Monthly
'H Mixed Gamma Air (pCi/m")
No.6 Monthly Gross Beta, lodine, Mixed Gamma No.17 Monthly Gross Beta, lodine, Mixed Gamma Sediment (pCi/kg)
No.23 Semiannually Mixed Gamma Fish (pCi/kg)
No.23 Semiannually Mixed Gamma Vegetation (pCi/kg)
No.6 Semlannually Mixed Gamma
' Intercomparison results were not yet available for publication in this report.
Results will be reported by SCDHEC.
Tabla 5 - Summary of 1997 Intercomparison Program with South Camlina Department of Health and Environmental Control 16
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NAME SECTOR MILES PATHWAY X/Q D/Q Dose
- mRemly J.H. Yarborough S
3.8 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 4.64E-08 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 Nicholt 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 Livingston W
2.0 Res, Gar, B 1.66E-07 1.53E-09 3.38E-01 Ken / Virgil Graham 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 1.11 E-07 3.21 E-10 8.84E-02 Ida Cole NW 4.1 Res,B 1.01E-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 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 Bessia 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. Hemdon NE 1.5 Res, Gar 2.01E-06 6.73E-09 1.82E-00 David Stone NE 2.1 Res., B 9.68E-07 2.98E-09 3.34E-01 James E. Robinson NE 2.8 Res, Gar, B 5.34E-07 1.51E-09 5.69E-01 Robert MartinW 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-06 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+00 Johnnie Joyner E
1.2 Res 2.89E-06 8.46E-09 1.08E-01 George Mosley E
1.2 Res 2.89E-06 8.46E-09 1.08E-01 "VCS Garden #6 ESE 1.0 Res, Gar 2.64E-06 8.62E-09 2.34E+00 Walker Manin 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 Andrew Wilson SE 1.5 Res, Gar 6.54E-07 2.43E-09 6.50E-01 Sim Roberts SE 4.7 Res Gar B 6.18E-08 1.70E-10 6.41 E-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)
Footnotes:
Maximum exposed individual, Hypothetical dose based on Operating License Environmental Report Source Term, X/Q and D/O were derived from ODCM 5-year average meteorological data ODCM required environmental gardens.
Table 7a - Critical Receptor Evaluatic1 for 1997 19
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 (bylocation) as close to the exclusion for gamma isotopic.
boundary as practicable where the highest offsite sectorial ground level concentrations are anticipated.8 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) boundary as practicable for gamma isotopic.
corresponding to the residence having the highest anticipated offsite ground level concentration or dose.8 C) 1 Indicator sample to be Continuous sampler operation N/A Gross beta following filter taken at the location of one with weeklycollection.
change; Quarterly of the dairies being sampled composite (by location) meeting the criteria of for gamma isotopic.
Vil(A).8d 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 site composito (bylocation) and not in the most for gamma isotopic, prevalent wind directions.2
- 11. Radiolodine A) 3 Indicator samples to be Continuous sampler operation 2
Gamma Isotopic for taken at two locations as with weekly canister collection.
7 lodine 131 weekly, givenin 1(A)above 30 B) 1 Indicator sample to be Continuous sampler operatiori 6
Gamma Isotopic for taken at the location as with weekly canister collection.
lodine 131 weekly.
given in 1(B) above.
C) 1 Indicator sample to be Continuous sampler operation N/A Gamma Isotopic for taken at the location as with weekly canister collection.
lodine 131 weekly, j
given in 1(C) above.
D) 1 Control sampio to be Continuous sampler operation 17 Gamma Isotopic for taken at a location similarin with weekly canister collection.
lodine 131 weekly.
nature to l(D) above.
Ill. Direct A) 13 Indicator stations to form Monthly or quarterly 1,2,3,4,5,6, Gamma dose monthly or 87 and inner ring of stations in exchange ; two or more 7,8,9,10,29, quarterly the 13 accessible sectors dosimeters at each location.
30,47 within 1 to 2 miles of the plant.
B) 16 Indicator stations to form Monthly or quarterly 12,13.32,33, Gamma dose monthly or an inner ring of stations in exchange'7; two or more 34,35,36,37, quarterly the 16 accessible sectors dosimeters at each location.
41,42,43,44, within 3 to 5 miles of the 46,53,55,60 plant Table B - Radiological Environmental Monitoring Program Specifications 20
Exposure Pathway Criteria for Selection Sampling and Sample Type & Frequency and/or Sample of Sample Number & Location Collection Frequency Location of Analysis WATERBORNE IV. Surface A) 1 Indicator sample Tirr.s composite samples with 21 e Gamma isotopic monthly 3
s Water downstream to be taken at a collection every month w th quarterly composite i
location which allows for (by location) to be 7
mixing a dilution in the analyzed for tritium ultimate receiving river.
J 3
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 s
receiving river sufficiently far (by location) to be analyzed for tritium'.
upstream such that no effects of pumped storage operation are anticipated.
Receptor Evaluation C) 1 Indicator sample to be 23 for 1997 2
taken in the upper reservoir of the pumped storage Time composite samples with s
facility at the plant discharge collection every month canal.
Gamma Isotopic monthly with quarterly composite (by location) to be analyzed for tritium' 1
I V. Ground A) 2 Indicator samples to be Quarterly grab sampling' 26 Gamma Isotopic and tritium Water taken within the exclusion 27 analyses quarterty'.
boundary and in the direction of potentially affected ground water
]
supplies.
B) 1 Control sample from Quarterly grab sampling' 59 Gamma isotopic and tritium 7
unaffected location analyses quarterly.
VI. Drinking A) 1 Indicator sample from a Monthly grab sampling'.
28 Monthly' gamma isotopic, Water nearby public ground water gross beta and quarterly' supply source.
compcsite for tritium analyses.
s B) 1 Indicator (finished water)
Monthly composite sampling.
17 Monthly gammaisotopic, sample from the nearest and gross beta and downstream water supply.
quarterly' composite for tritium analyses.
C) 1 Control (finished water)
Monthly composite sampling.
39 Monthly' gamma isotopic, sample from an unaffected and gross beta and water supply.
quarterty' composite for tritium analyses Table B (cont.) - Radiological Environmental Monitoring Program Specifications 21
l l
Exposure Pathway Criteria for Selection Sampling and Sample Type & Frequency end/or Sample of Sample Number & Location Collection Frequency Location of Analysis INGESTION:
l Vil Milk' A) Samples from milking Semimonthly when animals To be Gamma isotopic and 1-131 s
l animals in 3 locations within times' pasture, monthly othersupplied analysis semimonthly' are on l
5 km having the highest when r'tilk when animals are on dose potential. If there are animals are pasture. monthly other i
none then i sample from found in times' l
milking animals in each of 3 accordance areas between 5 to 8 km with criteria distance where doses are Vll.A.
calculated to be greater than l
1 mrem per year."
B) 1 Control sample to be Semimonthly when animals 16 Gamma isotopic and 1-131 are on gasture monthly other analysis semimonthly'
)
taken at the location of a times'-
when animals are on dairy > 20 miles distance and notin the most pasture, monthly other 8
prevalent wind direction.
times' C) 1 Indicator grass (forage)
Monthly when available' To be Gamma isotopic, i
sample to be taken at the supplied 4
I location of one of the dairies when milk being sampled meeting the animals are l
criteria of Vil(A),above, found in l
when animals are on accordance l
pasture with criteria j
Vll.A.
D) 1 Control grass (forage)
Monthly when available'"
16 Gamma isotopic, sample to be taken at the location of Vil(B) above.
Vllt. 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/O 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 l
doses are calculated to be d
greater than 1 mrem /yr.
s
- 8) 1 Control sample for the Monthly when available.
18 Gamma isotopic on edible same foods taken at least portion.
10 miles distance and n)t 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 Monitoring Program Specifications 22
Exposure Pathway Criteria for Selection Sampling and Sample Type & Frequency and/or Sample of Sample Number & Location Collection Frequency Location of Analysis IX. Fish A) 1 Indicator sample to be Semiannual' collection of the 23 Gamma isotopic on edible 8
taken at a location in the following specie types if portions semiannually'.
upper reservoir, available: bass; bream, crapple; catfish, carp.
B) 1 Indicator sample to be Semiannual' collection of the 21 Gamma isotopic on edible 8
taken at a location in the following specie types if portions semiannually'.
lower reservoir, available: bass; bream, crapple; catfish, carp.
C) 1 control sample to be Semiannual' 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 operation are anticipated AQUATIC:
X. sediment A) 1 Indicator sample to be Semiannual grab sample.'
23 Gamma is3 topic.
8 taken at a location in the upper reservoir.
B) 1 indicator sample to be Semiannual grab sample.s 21 Gamma isotopic.
8 taken on or near the shoreline of the lower reservoir.
8 C) 1 Control sample to be Semiannual grab sample.'
22 Gamma isotopic, taken at a location on the receiving river sufficiently far upstream such that no effects of pumped storage operation are anticipated.
FOOTNOTES 1.
Reserved for future use.
2.
Sample site locations are based on 5 year average meteorological analysis.
3.
Though generalized areas are noted for simplicity of sample site enumeration, airborne, water and sediment sampling is done at the same location whereas biological sampling sites are generalized areas in order to reasonably assure availability of samples.
4.
Milking animal and garden survey results will be analyzed annually. 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.
Table 8 (cont.) - Radiological Environmental Monitoring Program Specifications 23
~
)
)
5.
Not to exceed 35 days.
1 6.
Time composite samples are sampies 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 paiticular to the Site.
11.
Milk and forage sampling at the control location is only required when locations meeting the criteria of Vil(A) are being sampled.
I l
l Table 8 (cont.) - Radiological Environmental Monitoring Program Specifications 24 l
l Exposure Pathway Criteria for Selection of Sampling and Sample Type K. Frequency of and/or Sample Sample Number & Logtlon Collection Frequency Location Analysis AIRBORNE:
1 S-l.
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 or ground level isotopic.
concentration.
S-II. Radiolodine A) 1 Indicator sample to be Continuous sampler 8
Gamma isotopic for 1 taken from the location of operation with weekly 131 weekly.
S-1(A) above.
collection.
I 7
S-Ill. Direct A) 5 stations to be placed Quarterly exchange ; two 61,62,63, Gamma dose within the exclusion or more dosimeters at 68 & 99 quarterly.
boundary.
each location.
7 B) 2 stations to be placed Quarterly exchange ; two 94,97 Gamma dose around VCSNS sludge or more dosimeters at quarterly.
lagoons.
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."
wastewater discharge.
B) 1 Indicator sample taken Daily sample with 72,73 Gamma isotopic and at each storm drain monthly composite.
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.
q Table - 9 Supplemental Radiological Environmental Monitanng
\\
l 25
Exposure Pathway Criteria for selection of Sampling and sample Type & Frequency of
__and/or Samp:e Sample Number & Location Collection Frequency Location Analy sis INGESTION:
S-Vil. Milk A) 1 Sample from one of the Biweekl 14 Gamma isotopic and l-sample.ygrab 4
4 nearest a'fected dairies at 131 analysis biweekly.
or beyond 5 miles.
)
B) 1 Control sample to be Biweekl 16 Gamma isotopic and l-sample.{ grab 4
taken at the loca'.!on of a 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."
location of S-Vil(A) above.
S-Vil. Milk D) 1 Control grass (forage)
Monthly wjen 16 4
sample to be tsken at the available.
Gamma Isotopic.
location of S-Vil(B)above.
E) 2 indicator grass (forage)
Monthly when available.
2,7 samples to be taken at 2 Gamma isotopic.
of the locations beyond but as close to tha exclusion boundary as practical where the highest offsite sectorial ground level concontra-tions are anticipated.
F) 1 Control grass (forage)
Monthly when available.
18 sample to be used for Gamma isotopic.
routine monitoring along i
with S IV(E) above.
S-Vill. Food A) 1 Indicator sample of Annually'during growing 6,7 Gamma isntopic on Products various types of focds season.
edible portion.
grown in the area sur-rounding the plant (root, fruit grain).
FOOTNOTES 1.
Reserved for future use.
2.
Sample site locations are based on the meteoroiogical analysis for the period of record as presented in the Offsite Dose Calculation Manual (ODCM).
3.
Though generalized areas are noted for simplicity of sample site enumeration, airborne, water and sediment sampling is done at the same location whereas Table - 9 Supplemental Radiological Environmental Monitoring 26
F 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 l
sufficient samples. if contractual arrangements can be made, site (s) will be added for l
additional milk sampling up to a total of 3 Indicator Locations.
1 5.
Not to exceed 35 days.
I 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 loast cnce 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.
l 12.
Milk and forage sampling at the control location is only required when locations meeting the criteria of Vil(A) are being sampled.
i 13.
Weekly, when circulating water is not operational.
l 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 returned to background levels.
t ODCM defined quarterly.
f The ODCM requires semimonthly sampling when animals are on pasture, monthly at other times.
Table - 9 Supplemental Radiological Environmental Monitoring 27
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Footnotes 1.
Includes indicator and control analyses. Does not include supplemental samples. All j
supplemental sample results were consistent with the tabulated results shown.
1 2.
Values given are maximum MDA values for indicer locations calculated from the program data analyses with maximum acceptable LLD values allowed from NRC guidelines are given in parentheses.
1 3.
Mean and range are based on detectable measurements only.
The
. is of detectable measurements (i.e.,
number of positive results/ total 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 censitivity is approximately 10 mrem /yr (1.0 R/hr).
214 214 6.
Elevated levels of Pb and 81 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.
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7.
Fish include 3 groups (Bass, Bream / Crappie, Catfish / Carp).
J 214 214 228 8.
Elevated levels of Pb and 81 plus other 22 era daughter products and Ac plus 232 other Th 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 1997 33
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o 8 a Footnotes 1.
Values given are MDA values calculated from the program data analyses with maximum acceptable LLD values allowed from NRC guidelines given in parentheses.
2.
. Mean and range are based on detectable measurements only. The fractions of detectable measurements at specific locations are indicated in parentheses.
3.
A non-routine measurement is any confirmed measured level of radioactivity in an environmental medium that exceeds the reporting requirements of VCSNS ODCM, Section 1.4.1.2.
4.
The baseline values are high because of the fallout from the Chinese bomb test in 1980.
The first set of data reflects the 1981 baseline. The second set of data reflects the 1982 baseline, essentially free of bomb test fallout. The 1982 data covers the period 1/1/82 -
10/22/82.
5.
Detection sensitivity is approximately 5 mrem /yr (0.5 R/hr) determined from the analyses of five years of preoperational data.
6.
No control location was specified for drinking water during the preoperational monitoring period.
/
7.
Inconclusive data.
1 Table 11 - Radiological Environmental Program Preoperational(Baseline) Summary 39
1 e
Sample Month Media Location (Week No.)
Cause for Exception Air 17 March (13)
Dump truck crushed air sampler.
Air Radiolodine 17 March (13)
Dump truck crushed air sampler.
Broadleaf 18 November (46)
Sample not available Direct Radiation 31 First Quarter Missing 44 First Quarter Missing 45 Second Quarter Missing 47 Second Quarter Missing 31 Third Quarter Missing 11 Fourth Quarter Missing Table 12 - 1997 Environmental Sampling Pmgmm Exceptions 40
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