ML20210B461
| ML20210B461 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/31/1986 |
| From: | Baehr W, Hall G, Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8705050329 | |
| Download: ML20210B461 (62) | |
Text
{{#Wiki_filter:Virgil C. Summer Environmental Surveillance Laboratory Jenkinsville, South Carolina RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPERATING PERIOD January 1,1986 - December 31,1986 April 1987 { V. C. SUMMER NUCLEAR STATION SOUTH CAROLINA ELECTRIC AND GAS COMPANY Prepared by: Reviewed by: f4Gm k h b d~ William R. Baehr, Manager Gregory G.1/lall, Associate Manager Radiological Analytical Services Corporate Health Physics and Environmental Programs !DR OK O 395 R PDR IE.5,4
'Ie
TABLE OF CONTENTS Pace introduction 1 VCSNS and the Radiological Environmental Monitoring Program 1 Results of the Radiological Environmental Monitoring Program 3 Conclusions 4 Appendix A - Radiological Environmental Monitoring Program Sampling Site Locations A-1 Appendix B - Radiological Environmental Monitoring Program Specifications B-1 Appendix C - Radiological Environmental Monitoring Program Summary C-1 Appendix D - Environmental Sampling Program Exceptions D-1 Appendix E - Radiological Environmental Monitoring Program Preoperational(Baseline) Summary E-1 Appendix F - Results of the 1986 EPA Intercomparison Program F-1 Appendix G - Results of the 1986 Intracomparison Program with VCSNS Count Room G-1 ( Appendix H - Summary of the 1986 Intercomparison Program with SCDHEC H-1 Appendix l- Results of the Environmental Dosimetry Intercomparison Program with the NRC TLD Direct Radiation Monitoring Network l-1 Appendix J - Results of the 1986 Land Use Census Verification J-1 Appendix K - Results of the 1986 International Environmental Dosimetry Intercomparison K-1 (i)
LIST OF FIGURES FIGURE Page 1-1 Control Site Locations (50 Mile Radius around the Virgil C. Summer Nuclear Station) A-4 1-2 Radiological Monitoring Program Local Indicator Sample Sites (5 Mile Radius around Virgil C. Summer Nuclear Station) A-5 1-3 Radiological Monitoring Program Local Indicator Sample Sites (On Site and up to 1 Mile Radius ' around Virgil C. Surnmer Nuclear Station) A-6 ( i I i l l I i I (ii)
LIST OF TABLES TABLE Pace 1 Monitoring Methods forCritical Radiation Exposure Pathways 3 2 Average Gross Beta Air Particulate Concentrations 4 3 1986 Corrosion and Fission Product Activity in Sediment 9 J-1 Results of the 1986 Census Verification J-2 J-2 Critical Receptors in the 1986 Census J-3 ? l (iii) l L
, introduction
- This report summarizes the results of the. Radiological Environmental Monitoring Program conducted for the Virgil C. Summer Nuclear Station (VCSNS) during 1986. Control / indicator and preoperational/ operational data comparisons are made and, along with other data interpretations, are presented herein. Analyses of trends are similarly provided in the text that follows.
VCSNS and the Radioloaical Environmental Monitorino Program Virgil C. Summer Nuclear Station is a 900 MWe Westinghouse pressurized water reactor located adjacent to the Monticello Reservoir near Jenkinsville, South Carolina. The site is approximately 26 miles northwest of Columbia. VCSNS achieved initial criticality October 22, 1982, reached 50% power December 12,1982 and 100% power June 10,1983 followin a steam generator feedwater modification. VCSNS was in its third nuclear fuel cle during 1986. The nuclear station is used in conjunction with the adjacent Fairfield Pumped 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 6200 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 l producing small grains, feed crops and beef cattle. Significant portions of Lexington and Richland Counties are encompassed within the 20 mile radius of i 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 I concerns are predominant, but makeup less than 50% of the land area. The l main industrial activity is concentrated around Columbia and is generally greater than 20 miles from VCSNS. Liquid effluents from VCSNS are released into the Monticello Reservoir at
- two discharge points
- the Circulating Water Discharge Canal (CWDC) and the
/ FPSF Penstocks. Unprocessed steam generator blowdown and non nuclear drains are released to the CWDC. Effluent from the liquid waste processing system and processed steam generator blowdown are released through the i penstocks. Radioactive gaseous effluents from VCSNS are released from two main points: the Main Plant Vent and the Reactor Building Purge Exhaust, both considered to be ground level releases. Radioactive liquid and gaseous releases from the facility and their poten-tialinfluence on the surrounding biota and man are the primary concern of the l Radiological Environmental Monitoring Program at VCSNS. The program, which Page1 l
E i I i i~ is carried out in its entirety by South Carolina' Electric and Gas Company, has
.been designed to meet the following general commitments:
l i - -
-1. To analyze selected samples in important anticipated i pathways-for the qualification and quantification of j radionuclides released to the surrounding environment.
f 2. To establish correlations between levels of environmental j radioa,ctivity and radioactive. effluents from plant
- operation.
i The program utilizes the concepts of control / indicator and preoperational/ i operational intercomparisons in order to establish the adequacy of source con-i trol and to realistically verify the assessment of environmental levels and
- subsequent radiation dose to man. -
4 Specific measurement, sampling and analysis methodology has been l programmatically developed to sensitively monitor the pathways expected to j represent the most significant source of radiation exposure to the public and the environment. Elements of the program monitor the impact of gaseous and j 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 in Table 1.
i Site (VCSNS) related dispersion characteristics, demography, hydrology, . land use, anticipated source terms, and the critical pathways hsted in Table 1 have been considered in the selection of sample media, sampling and analysis frequencies, sample locations, and types of analyses. These criteria were used to . establish both the preoperational and operational phases of the radiological i surveillance program. Results of the 1986 land use verification census are ) included in Appendix J.
- l In addition to preoperational/ operational data intercomparisons, control /
indicator data intercomparisons are utilized to assess the probability that any observed abnormal concentration estimate is due to random or regional !. fluctuations in measurements rather than to a true increase in local
- environmental concentrations. Indicator sites are generally within 5 miles of the t
! plant, as shown in Appendix A, Figures 1-2 and 1-3, and are indicative of plant
! operating conditions. Control sites are greater than 10 miles from the plant, as
- shown in Appendix A, Figure 1-1, and are intended to indicate conditions away l from its influence.
! Valuable information is gained through multiple types of sampling and j measurements at specific locations." Several multiple sampling combinations are i i in use around the VCSNS. All air sampling locations are also environmental i- dosimetry monitoring locations. At these points airborne plant effluents are ! i monitored for gamma immersion dose (noble gases), airborne particulates, and ! at selected sites, radioiodine. Seven of these locations have additional i complementary effluents. Sites 2 1.2 (sampling mi SW),5 (0.9 / measurement pathways mi SE),6 (1.0 mi ESE), andfor monitoring 8 (1.5 plant mi ENE) have
- broadleaf vegetation gardens for monitoring the gaseous effluent deposition j and ingestion pathway. The other four locations (two of them control sites) l allow greater definition of existing specific pathways. ,
i ! Page 2 l l l_ -,___ _.-. _ . _ _____._.
' "t Re ease Typg Exposure Pathway . Monitoring Media Gaseous immersion Dose and Thermoluminescent Dosimetry (TLD) other 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 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 Sediment Sampling Immersion)
_ Drinking Water Ground' Water Sampling, Drinking (Ingestion) Water Sampling Table 1 - Monitoring Methods for Critical Radiation Exposure Pathways in addition, liquid effluents are monitored through three pathways (fish, bottom sediment and surface water) at the three most probable affected bodies of water around the plant: Site 21, Parr Reservoir (2.7 mi SSW); Site 23, Monticello Reservoir (0.5 mi ESE); and Site 24, Recreation Lake (5.5 mi N). The controllocation for liquid effluent comparisons is at Site 22, Carlisle/Neal Shoals (24.0/30.0 mi NNW) on the Broad River. The program that evolved during the preoperational (baseline) monitoring program, incorporating all the elements of the VCSNS Technical Specifications plus additional special study criteria, is detailed in Appendix B. The monitoring sites and their distance and direction from the reactor building at VCSNS are listed in Appendix A. Results of the Radiological Environmental Monitorina Program The results of the Radiological Environmental Monitoring Program for 1986 are summarized in Appendix C. For comparative purposes preoperational data is summarized in Appendix E. Certain samples were not collected during 1986 and are not included in the annual summary. A listing of these program exceptions and their respective causes are included in Appendix D. Despite the program exceptions, the Radiological Environmental Surveillance Program was able to attain a completion rate of 97%. Detailed analysis of the impact of these omissions verified that program quality has not been affected and there were no violations of Technical Specification requirements. Page 3
The results of the Radiological Environmental Monitoring Program's . participation in various intracomparison and intercomparison programs are summarized in Appendices F, G, H,I and K. The consistency in these performance checks verifies the technical credibility of the data presented herein. Increases in environmental radioactivity levels were noted during the week of May 12, 1986; three weeks after the Chernobyl accident which began April 26,1986. Unusual levels of radioactivity were previously reported in accordance with IE Information Notice No. 86-32 (May 2,1986). The results are summarized in this report, but are not identified as "Non-routine Reported Measurements" in Appendix C because of similar observations at control sampling sites. Conclusions
- 1. AIRBORNE PARTICULATES Gross beta results for air particulates collected at indicator locations around VCSNS during 1986 were below preoperationallevels and comparable to operational control levels. The comparison summary is shown in Table 2.
Intercomparisons at each indicator location showed similar relationships. Indicator Locations Control Locations Preoperational* 1986 Preoperational* 1986 2.9E-2 (7.5E-2) 2.2 E-2 *
- 3.0E-2 (8.1 E-2) 2.4E-2 *
- 2.5E-2 * *
- 2.6 E-2 * * *
- Determined from September,1981 through October,1982.
Values in parentheses include fallout from Chinese bomb testing prior to September,1981.
*
- January 1,1986 to May 12,1986
* *
- June 23,1986 to December 31,1986 Table 2 - Average Gross Beta Air Particulate Concentrations (pCi/m 3)
Airborne gross beta activity began to increase during the week of May 12, 1986. A maximum average level (3.8E-1 pCi/m3) seventeen times greater than normal was reached during the week of May 26,1986. Airborne gross beta activity levels returned to normal by June 23,1986. The highest site specific average indicator activity during 1986 was found at sample site no. 5, Transmission Line (0.9 mi SE) with 6.2E-2 pCi/m . The highest average control 3 location activity during the same period was found to be 3.6E 2 pCi/m3 . Higher gross beta activity at indicator locations, apparent only during the five weeks of increased airborne activity following the Chernobylincident,is attritubed to the presence of radon daughters Bi-214 and Pb-214. Due to the above observations, it is concluded that operation of VCSNS has not rcsulted in detectable increases of particulate beta activity in the environment. Page 4
The monthly composite gamma spectroscopy analyses for the air
; . particulate samples revealed only naturally occurring background activities of Be-7, Ra-226 and K-40 except during May and June,1986, during which time concentrations of Cs-134, Cs-137,1-131 and. Ru-103 were observed. Mean
+
concentrations of these fission products for all indicator and control sites were 6.8E-3,1.4E-2,1.3E-2 and 1.2E-2 pCi/m3, respectively. These observations are expected based on a comparison of environmental data with plant gaseous effluent release data reported in the 1986 Semiannual Effluent and Waste Disposal Reports for VCSNS. There was no reported particulate activity in gaseous effluent released during 1986. Fission product activity detected during May and June agreed with results reported by SCDHEC and neighboring utilities and is attributed to the Chernobyl event. II. AIRBORNE RADIOIODINE Air sample analyses also showed no measurable radioiodine activity during most of 1986. Total 1-131 in the gaseous effluent releases was reported to be 29.92 uCi for 1986; a level not discernable in environmental media upon consideration of dispersion and dilution factors experienced during the releases.
- Airborne radioiodine was detected in four consecutive weekly samples beginning with the week of May 12,.1986. A mean activity of 3.0E-1 pCi/m3 (1-4 131) was observed during the first week and decreased to less than 2.9E-2 pCi/m3 1 by the end of the fourth week. Significant radioiodine activity was observed at indicator and controllocations alike.
111. DIRECT EXPOSURE Exposure rates observed from all environmental dosimetry measurements during 1986 were not significantly different from preoperational measurements over the same seasonal time periods. Indicator and control dosimetry measurements also showed no appreciable differences during 1986. The lowest
- mean exposure rates for monthly and quarterly dosimetry locations (7.1
- 0.9
! uR/hr and 6.410.8 uR/hr, respectively), were observed at sample site no's. 2 (1.2
; mi, SW) and 58 (residence in Jenkinsville). Sample site no. 55 at St. Barnabas Church near Jenkinsville (2.8 mi, E) was the indicator location showing the highest mean exposure rate of 14.41. 0.4 uR/hr. This value compares favorably with the mean exposure rate of 13.612.2 uR/hr measured during the preoperational period and confirms the long-term stability of background values observed at this site. Gaseous effluent release data reported for 1986 indicated a total of 13.9 Ci of measurable gaseous activity was released from VCSNS. An extensive search of environmental dosimetry data and meteorological data l during the release periods indicated no evidence of detectable activity
- attributable to the releases with only natural background variations evidenced.
! Environmental dosimetry results generated during the second quarter, 1986 indicated seven new historical high exposure rates were monitored. Exposure rates were 11.4,11.9,8.1,7.4,10.6,7.0 and 9.7 uR/hr for site no's. 33, 34,42,44,46,58, and 59, respectively. The increase in quarterly dose at these locations was less than 1.0 mR and is attributed to atmospheric fallout following l the Chernobyl event. l l Page 5
i IV. SURFACE WATER 4 .
. Tritium analyses of surface water samples during 1986 yielded results which were not noticeably different from preoperational data. All but 6 of 64 F indicator tritium activity determinations were less than the mean calculated LLD 1 value. The maximum indicator tritium activity of 5.3E + 2 pCi/ liter was found in
! the Recreation Lake. Activity levels found at the indicator locations are within ! the normal background variation for environmental tritium and less than the 2 preo perational LLD value of 1.1E + 3 pCi/ liter. Tritium activity found at one con-trol location (5.2E + 2 pCi/ liter) provides further indication that the indicator ! tritium activity may not be directly attributed to VCSNS operation. Total tritium i released in liquid effluents during 1986 was reported to be 374.5 Ci; a level not
- discernable in environmental media upon consideration of dilution factors experienced during the releases and the detection limitations of analytical i equipment.
! Gamma spectroscopy analyses of indicator surface water during 1986 yielded concentrations less than the mean calculated LLD's for all fission and i activated corrosion products. Liquid effluent release data reported for 1986 in the Semi annual Effluent and Waste Disposal Reports indicated a total of 0.33 Ci of measurable fission and activated corrosion product activity was released from j VCSNS, a level not discernable in environmental media based upon consideration oldilution factors experienced during the releases and the detection limitations i of analytical methods. Analytical results from one control surface water sample i
- collected May 19,1986 did indicate the presence of l-131 at a concentration of 7.0E-1 pCi/ liter; fission product activity presumably from Chernobyl.
V. GROUNDWATER ! With the exception of one sample, tritium analyses of ground water j samples during 1986 yielded results which were all less than the mean calculated i t ! LLD of 4.5E + 2 pCi/ liter. An onsite well sample collected in December,1986 did l indicate the presence of tritium at a concentration of 2.8E + 3 pCi/ liter. Three , l separate analyses, one involving sample distillation, verified the tritium ! concentration to be just above the required LLD of 2.0E + 3 pCi/ liter. Although i this tritium concentration is higher than control or preoperational indicator levels,2.8E + 3 pCi/ liter is well within acceptable background levels. Gamma spectroscopy analyses of ground water samples yielded results less than the mean calculated LLD values. T1e control sam ale site no.16 (28 mi, W)
- showed high background levels of Pb 214 and Bi 214,c aughters of Ra 226. This was also seen in preoperational data and is attributed to the large amount of granite found in this part of South Carolina. The granite contributes uranium, *
, hence Ra-226 and its daughters, to the wells in the area. The radionuclides Pb-l 214 and Bi-214 are maior gamma emitting daughters in the uranium series decay
- scheme produced through the decay of dissolved Rn-222 gas in the water. No l evidence of radioactivity from VCSNS operation was detected.
VI. DRINKING WATER i Indicator water samples taken from the Jenkinsville and Columbia l drinking water supplies showed no measurable activities of VCSNS related 4 i Page 6 I i e
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gamma emitting radionuclides during 1986. Activities of Ra-226, Pb-214 and Bi-214 from the naturally occurring uranium series decay scheme 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 a series of deep water wells in local granite aquifers. Gross beta activity showed a trend similar to the uranium series decay scheme daughters; normal low beta activity at Columbia (surface water source) and elevated beta activity at Jenkinsville (deep well source). This data is again comparable to the preoperational data and is attributed to the naturally occurring uraniurn associated with the aquifer supplying the Jenkinsville water system. Drinking water tritium analyses, in all but two cases, showed no concentrations in excess of the mean calculated LLD for the indicator locations. An average detected activity of 6.2E + 2 pCi/ liter was found in Columbia drinking water. This value is within the range of preoperational tritium concentrations and less than the preoperational mean calculated LLD. This value was also not significantly different from tritium activity levels found in samples from control locations which averaged 5.1 E + 2 pCi/ liter. Vll. MILK With the exception of detected concentrations of I-131 and Cs 134, gamma spectroscopy results for milk samples taken during 1986 were not significantly different from those observed in the preoperational program. Naturally occurring K-40 and Ra-226 were found at both locations in concentra-tions similar to those seen during the preoperational period. Cesium 137 was found at the controllocation at concentrations similar to those found during the preoperational period. Radioactive iodine (1-131) was detected in three separate weekly milk samples from each of the indicator and control dairy locations during May and June,1986. Maximum activities were 6.1 and 3.8 pCi/ liter at the indicator and control locations, respectively. Cesium-134 was detected on two separate occasions in indicator milk samples and on one occasion in a control milk sample. Mean detected Cs-134 activities were 2.4 and 3.0 pCi/ liter for indicator and control locations, respectively. There were no identified radionuclides in 1986 milk samples that are attributed to VCSNS operation. This observation confirms the previously reported 1986 effluent measurements. This presence of Cs-137 was attributed to residual fallout from atmospheric weapons testing and the Chernobyl incident. Cesium 134 and 1-131 were also attributed to Chernobyl. Gamma spectroscopy analyses of grass (forage) samples showed the presence of Be 7 and K 40 in all samples. Detectable levels of I 131, Cs 134, Cs-137, Ru-103 and La 140 were found in indicator and control grass samples during May and June,1986. The naturally occurring Be-7 and K 40 were detected at levels similar to those found during the preoperational program and in 1986 control data. The observation of fission product activity in indicator and control grass samples is attributed to the Chernobyl incident. There is no indication of the presence of any radionuclide in grass due to the operation of VCSNS which again supports the findings presented in the Semiannual Effluent and Waste Disposal Reports for gaseous effluent releases in 1986. Page 7
Vill. FOOD PRODUCTS Broadleaf vegetation from gardens at sample site no's. 2,5,6,8 and 18 were the principal food products sampled during 1986. Detectable levels of Ru-103,1-131, Cs-134 and Cs-137 were observed in samples from one indicator location during May and June,1986. Radioiodine was also detected in vegetation collected from one control location during the same time penod. Naturally occurring contributions from Ra-226, K-40, Ac-228 and Be-7 were also measured. All values observed for naturally occurring radionuclides in samples from the indicator locations are comparable to and consistent with the results found during the preoperational program and at the control location. Fission product activity was attributed to the Chernobyl incident. Other vegetation sampled in 1986 included squash, tomato, and radish representing the non-leafy vegetation group. Naturally occurring K 40 was observed in samples at concentrations above normal detector background. The indicator site K-40 concentrations were consistent with the concentrations observed during the preoperational period and 1986 control samples of the same or similar type. There were no detectable levels.of I-131 or Cs-134 measured which might be attributed to gaseous effluents released from VCSNS. Cesium 137 activity detected in tomatoes from the indicator location (4.9 pCi/kg) was attributed to either. residual fallout from nuclear weapons testing or the Chernobylincident. IX. FISH Species of fish sampled at three indicator and one controllocation in 1986 included bass, bream, shad, catfish and/or carp. Cs 137 was detected in most fish samples (25 of 32) and in all four species at a mean level of 1.5E + 1 pCi/kg; just above the mean calculated LLD of 1.0E + 1 aci/kg. Cesium 134 was detected in bass, shad and bream samples (4 of 24) co lected during the fall of 1986 from indicator locations at a mean concentration of 9.3 pCi/kg. Naturally occurring K-40 was also found in all fish samples. With the exception of Cs-134, the results of fish sample analyses from indicator locations are similar to those from the same sites during the preoperational and operational periods and at the 1986 control sam ale site. The four non-routine measured activities of Cs 134 were attributed to t1e Chernobyl incident and subsequent bioaccumulation of cesium in this aquatic organism pathway. X. SEDIMENT Sediment samples were taken from the same four bodies of water from which fish were sampled. Sediment sample analyses did not indicate the presence of Cs-134. Cs 137 was detected in all sediment samples. The highest concentration was observed in Parr Reservoir at 3.1E + 2 pCi/kg with a mean of 2.6E + 2 pCi/kg. The Cs 137 concentrations are consistent with preoperational and control data and concentrations expected from atmospheric weapons testing. Naturally occurnng K 40 concentrations were also detected due to the concentration of organic matter in the sediment. The K-40 activities are similar to those observed in the preoperational program and control data. Naturally occurring U 235 was also detected in sediment from all sampling locations at an average concentration of 1.1E + 2 pCi/kg; a level consistent wit;1 that observed Page 8
during the preoperational program. Detectable levels of Mn-54, Co-58 and Co-60 were observed in sediment samples from Monticello Reservoir, Parr Reservoir and Columbia Canal during 1986. Radioiodine was detected in sediment collected from the discharge canal on Monticello Reservoir April 25,1986. The average activity concentration of I-131 was 1.1E + 2 pCi/kg. The results are summarized in Table 3 with corresponding doses to man calculated using methodology found in Regulatory Guide 1.109 and assuming an individual is exposed to shoreline sediment containing Mn-54, Co-58, Co-60 and 1-131 at the mean detected concentrations for 400 hours a year. Activity (pCi/kg) Corresponding Calcula-ted Annual Radio Dose to Man (mrem) Location nuclide Maxi-mum Mean Wholebody Skin Monticello Reservoir Co-58 9.5 E0 9.5E0 1.1 E 3 1.2E 3 Co 60 1.0E + 2 5.6E + 1 1.5E 2 1.8 E-2 1131 1.4E + 2 1.1 E + 2 4.9 E-3 6.0E-3 Total 2.1 E 2 2.5E 2 Parr Reservoir Mn-54 5.0E + 1 2.9E + 1 2.7E-3 3.2 E-3 Co-58 5.0E + 1 3.0E + 1 3.4E-3 3.9E 3 Co-60 4.3 E + 2 1.2 E + 2 3.3 E-2 3.8E-2 Total 3.9 E-2 4.5E-2 Columbia Canal Mn-54 3.2E + 1 2.6E + 1 2.4E-3 2.8E-3 Co 58 9.0E + 1 6.0E + 1 6.7E 3 7.9E 3 Co 60 2.0E + 2 1.2 E + 2 3.3 E-2 3.8E-2 Total 4.2E 2 4.9E 2 Table 3 1986 Corrosion and Fission Product Activity in Sediment. l The presence of corrosion product activity is attributed to liquid effluent releases from VCSNS. The relatively low corrosion product activity in Monticello Reservoir is attributed to the injection of the liquid waste stream directly into the penstocks only during FPSF's generating mode and then subsequent operation of the reversible pump turbine unitsduring periods of off peak power demand. The presence of I 131 in Monticello Reservoir is attributed to steam generator blowdown releases through the circulating water discharge canal in February,1986. The BEIR Committee and the VCSNS Final Environmental Statement (NUREG 0719) both suggest that the conservatism inherent in the radiation Page 9 i I l l
ex posure limits and calculated doses to man is also applicable to other biota. The calculated dose to man attributed to Mn-54, Co-58, Co-60 &nd 1-131 in sediment is a highly conservative estimate. The absence of any discernable ecological impact on biota during 1985 (refer to the Final Environmental Report for VCSNS for SCDHEC and NRC, Dames and Moore,1985), when activated corrosion product activity was first detected, substantiated the fact that species population stability was unaffected by the activated corrosion product activity released to the environment at that time. The absence of any impact during 1986 is anticipated since the concentrations were much less than acceptable limits during 1986 and since most biotic species are not as radiosensitive as man. XI. OVERALL CONCLUSIONS Based on the data and the interpretations and conclusions discussed, the presence of activated corrosion product activity in Monticello Reservoir and Broad River media and the presence of I-131 in Monticello Reservoir sediment are the only environmental indicators which can be attributed to operation of VCSNS. The presence of all other fission product activity is attributed to the Chernobylincident. The results of the radiological monitoring program support the results reported in the Semiannual Effluent and Waste Disposal reports for VCSNS during 1986. The calculated potential radiation dose to the public attributed to activated corrosion product activity in Broad River media is 4.2E-2 mrem whole body. This figure assumes the person is exposed to sediment in Columbia Canal as a result of a fishing occupation. This figure compares favorably to the 4.4E 2 mrem dose reported in the 1986 Semiannual Effluent and Waste Disposal Reports and is a small fraction of observed variations in local natural background. These insignificant doses will not result in observable effects on the ecosystem or the pu ofic. The results of the radiological monitoring program therefore substantiate the continuing adequacy of source control at Virgil C. Summer Nuclear Station and conformance of station operation to Appendix Idesign goals. Page 10
APPENDIX A SAMPLING SITE LOCATIONS Description g"es Direction 2 Sample Type (5)3 1 Borrow Pit 1.2 182.0 5 DM 2 Transmission Line 1.2 225 0 SW AP RI,DM,GA 3 Firing Range 1.2 270.0 W DM 4 Fairfield Hydro 1.2 289.5 WNW DM 5 Transmission Line Entrance 0.9 145.5 $E AP,RI,DM,GA 6 Env. Lab Garden 1.0 104 0 ESE AP Rl,DM,GR.GA 7 Monticello Peninsula 1.2 83 0 E DM 8 Monticello Res 5 of Rd 224 1.5 63.0 ENE AP,DM.GA 9 Ball Park 2.2 44.0 NE DM 10 Meteorological Tower #2 2.5 25.5 NNE AP.RI DM 11 Residence 3.3 80N DM 12 Old Hwy 99 4.2 349.0 N DM 13 North Dam 2.9 334 0 NNW AP,DM 14 Dairy 5.1 270 0 W AP,RI,DM.M K,G R 15 Parr Village - 2.5 204 0 55W AP.DM 16 Dairy 4 28.0 2810 W AP,RI,DM,GW,M K,G R 17 Columbia Water Works 24.7 144.0 SE AP,RI,DM,5W.DW,B5 18 Residence / Pine Island Club') 16.5 16505 DM,5W,GW,GA 19 Residence /Little 5aluda 17.9 207.0 55W DM 20 Residence /Whitmire 22 0 310 0 NW DM 21 Parr Reservior 2.7 199 5 55W $W,F H,85 22 Carlisle/Neal Shoalso 240/300 343 0 NNW SW,FM,85 23 Discharge Canal (Mont Res ) 0.5 104 5 ESE $W,FH,B5 24 Recreation Lake 5.5 20N SW,F H,85 25 Fairfield Pumped storage (Monticello Res ) 09 302.0 WNW SW 26 On Site Well (P4) 265 Ft 270.0 W GW 27 On Site Well (PS) 510 Ft 18005 GW 28 Nuclear Training Center (EOF)/ 24 168 0 55E DW 29 Trans. Line W5W of VC5N5 09 248.0 W5W DM 30 Oak Tree North of Borrow Pit 10 197 0 55W DM 31 McCrorey Liston School 58 12.5 NNE DO 32 Dirt Rd of f Rd 205 45 25 0 NNE 00 33 Rd 48 near Hwy 213 42 70 0 ENE 00 34 Rd 419 North of Hwy 60 48 112 5 ESE DQ 35 Unnamed Circle Road of f Hwy 215 48 137.5 SE 00 36 Woods Behind Jenk. Post Of fice 3.1 1515 55E DQ 37 Residence 49 305 5 NW DQ 38 FP5F Trailrace 1.3 280 0 W B5 39 LMWTF 14 0 168 055E DW 40 No 5 ampler 41 End of Catwalk 39 18505 DO 42 5 tore 39 199 0 55W DQ 4I Hwy 176 and Rd 435 52 236d5W 00 A-1
APPENDIX A (continued) SAMPLING SITE LOCATIONS Description {
"",', Direction 2 Sample Type (s)3 44 Rd 28 at Cannon's Creek 2.9 255.5 WSW DO 45 Rd 33 at Pomaria 5.9 253.WSW DQ 46 Rd 28 at Heller's Creek 3.7 292.0 WNW DQ 47 Fairfield Tajlrace 1.0 316.0 NW DQ 48 Cemetary 2.3 318.5 NW DQ 49 North Rd 383 4.0 332.5 NNW DQ 50 New Rd 99 (West Shore) 5.5 1.0 N DQ 51 New Rd 99 (East Shore) 5.5 5.0 N DQ 52 Monticello(Rd II) 3.9 14.0 NNE DQ 53 Rd 359 3.0 48 0 NE DQ 54 Jenkinsville School 1.7 73 0 ENE 00 55 St. Barnabas Church 28 94 0E DO 56 Old Jenkinsville Diner 2.0 144.0 $E DO 57 Residence / Highway 213 and 215 2.7 146.0 SE DQ 58 Residence 2.5 158 0 55E DQ 59 Nuclear Training Center (EOF)/ 2.4 168.0 SSE DQ,AP 60 Rd 98 near Rd 28 3.5 275.0 W DO 61 Switchyard, SE Entrance to Plant 0.1 180.0 $ DM 62 East of Training Bldg 0.13 720.0 SW DM 63 East of Daneet's Of fice 0 17 270.0 W DM 64 Reprap W of Intake 0 13 338.5 NNW D M ,85 65 Guard Tower 0.13 22.5 NNE DM,85 66 Jetty 06 33.0 NNE DM 67 Service Water Pond (East Side) 0.5 72.0 ENE DM 68 Fuel Oil Storage Tank 0.2 108 5 ESE DM 69 Exclusion Buoy NNW on Monticello Res. 1.0 337.0 NNW DM 70 Exclusion Buoy N on Monticello Res. 1.0 00N DM 71 Temperature Buoy on Monticello Res 54 30N DM 72 Yard Drain Outf all 04 146 0 5E SW 73 Yard Drain Outfall 04 270 0 W SW 74 Yard Drain Outf all 0.5 246 0 WSW SW
, 80 Congaree River 30.2 147.0 SSE BS l 81 Congaree River 30.1 147.0 SS E B5 82 Congaree River 30.0 147.0 SSE B5 83 Congaree River 28.5 147.0 SSE B5 84 Congaree River St.2 135 0SE B5 85 Congaree River 54 8 135 0 SE B5 86 Congaree River 54 0 135 0 SE B5 87 Lake Marion 72 0 138 0 SE B5 88 Lake Marion 72 0 138 0SE B5 89 Lake Marion 72 0 138 0SE B5 l i A-2 i
APPENDIX A FOOTNOTES
- 1. Distance given is the distance between the site location and the center of the VCSNS reactor containment building.
- 2. Direction given is direction in degrees from true north-south line through center of reactor containment building.
- 3. Sample Types:
AP = Air Particulate DW = Drinking Water RI = Air Radioiodine MK = Milk DM = MonthlyTLD GR = Grass (Forage) DQ = QuarterlyTLD GA = Garden SW = SurfaceWater FH = Fish GW = Ground Water BS = Bottom Sediment
- 4. Site 16 consists of 3 sampling locations. A continuous air sampler and TLD are located off Route 560. Ground water samlales are taken at a residence 1 mile west of the air sampler. Grass and mi:k samples are taken from a relocated dairy approximately 4 miles west of the air sampler.
S. Site 18 consists of A locations in close proximity next to Lake Murray. Ground water samples are taken at the Corley residence. 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 22 consisted of 2 sampling locations through August,1986. A continuous surface water sampler was co located with USGS at the Carlisle Highway 121 bridge over the Broad River, but was decommissioned by USGS sometime in September,1986. Fish and sediment samples are taken j upstream of this location at Neal Shoals. All samples are presently collected j at Neal Shoals.
I 7. Site 28 for drinking water and site 59 for quarterly TLD measurements and
- continuous air sampling are co located at the location of the SCE&G Nuclear l Training center which also serves as the Virgil C. Summer Station Emergency Offsite Facility.
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l APPENDIX B VIRGilC. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SPECIFICATIONS l Exposure Pathway Cnteria for Selection Sampling and Sample 1 Type & Frequency and'or Sample of Sample Number & Location Collection Frequency Location of Analysis maoau: I Particata e A) 3 Ind cator samples to be tak en at locations (in Continuous sampler 2 Gross beta following filter different sectors) beyond but as close to the operat,on with weekly 5 change; Monthlyt e scluson boundaqr as practicable wbere the coilectiort 10 Composite (by location) for l highest of fsate sectoral ground level gamma isotopic. Concentrat2ons are anticpated 2 l B) 1 Indicator sample to be ta6 en m the sector Continuous sampler 6 Gross beta following filter beyond but as dose to the excluson boundary operation with weekly change; Monthlyt i as practicable correspondmg to the resadence co!!ection Composite (by location) for hasng the highest anticipated offsite ground gamma isotopic. level concentration or dose.2 C) 1 Indicator sample to be tak en at the location Continuous sampler 14 Gross beta following filter of one of the da4rtes most lekely to be affected operation with weekly change; Month!yt 2* collectiort Composite (by location) for gamma isotopic.
*D) 4 Additional Ind:cator sampfes to be taken at Continuous sampler 8 Gross beta following filter locations (in dif ferent sectors) beyond but as operation with weekly 13 change; Monthlyt cfose to the eaclusion boundary as practicable co!!ection. 15 Composite (by Iocation) for and nearer to the plant than the nearest 59 gamma isotopic.
cntocal receptor for the chosen sector.2 E) 2 Control samples to be taken at locations at Continuous sampler 16 Gross beta following filter least 10 air miles from the site ar'd not in the operation with weekly 17 change; Monthlyt most prevalent wind d.rections.2 collectiort Composite (by location) for gamma isotopic.
I l APPENDIX B VIRGIL C.5UMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SPECIFICATIONS Exposure Pathway Criteria for Selection Sampling and Sample 1 Type & Frequency and/or Samp!e of Sampie Number & Location Collection Frequency Location of Analysis il Rad.o od re A) 3 Irdicator sampres to be taken at two Continuous sampler 2 Gamma Isotopic for lodine locations as given in 1(A) above. operation with weekly 5 131 canister collection. 10 B) 1 Indicator sampie to be taken at the location Continuous sampler 6 Gamma Isotopic for Iodine as g sen in 1(B) above. operation with weekly 131 canister colIectson. C) 1 Indicator sampfe to be tak en at the location Continuous sampler 14 Gamma Isotopic for lodine as given in f(C) above operation with weekly 131 canester collection. D) 2 Control samples to be taken at two locations Continuous sampler 16 Gamma Isotopic for Indine s.milar in nature to f(E) above. operation with weekly 17 131 canester totlection
APPENDIX B VIRGIL C. 5UMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SPECIFICATIONS Exposure Pathway Criteria for Selection Sampling and Sample 1 Type & Frequ,ency and/or Sample of Sample Number & Location Collection Frequency Location of Analysis lit. Direct A) 13 Indicator stations to form an inner ring of Month!y or quarterly 1,2 Gamma dose monthly or stations in the 13 accessible sectors within 1 to exchange 5.7; two or more 3,4 quarterty. 2 miles of the p! ant. dosimeters at each location. 5.6 7,8 9,10 29,30 47 B) 16 Indicator stations to form an inner ring of Monthly or quarterly 12,14 Gamma dose monthly or stations in the 16 accessible sectors within 3 to exchange 5.7; two or more 32,33 quarterly. 5 miles of the plant. dosimeters at each location. 34,35 t 36,37 41,42 43,45 46,49 53.55
- C) 20 Stations to be placed in special interest Monthly or quarterly 11,13 Gamma dose monthly or areas such as population centers, nearby exchange 5.7 two or more 15,16 quarterly.
residences, schools and in 2 or 3 areas to serve dosimeters at each location. 17,18 as controls. 19,20 31,44 48.50 51,52 54,56 57,58 I 59,60
*D) 8 Stations to be placed within the exclusion Monthly or quarterly 61,62 Gamma dose monthly or l boundary at the locations of the onsite exchange 5 7; two or more 63,64 quarterly.
I Pressurized Ion Chamber Detectors (Special dosimeters at each location. 65,66 Study). 67,68
- E) 3 5tations to be placed on buoys on Monticello Monthly or quarterly 69 Gamma dose monthly or Reservoir (Background Study) exchange 5 7; two or more 70 quarterly.
dosimeters at each location. 71
i APPENDIX B VIRGIL C. 5UMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SPECIFICA.TiONS Exposure Pathway Criteria for Selection Sampling and Sample 1 Type & Frequency and/or Sample of Sample Number & Location Collection Frequency Location of Analysis WATERBORNE: IV SurfaceWater A) 1 Indicator sample downstream to be taken at Time composite samples 21 Gamma isotopic monthly a location which allows for mixing and dilution with collection every with quarterly composite (by an the ultimate receiving river.3.6 month.5 location) or monthly samplet to be analyzed for tritium. B) 1 Control sample to be taken at a location on Time composite samples 22 Gamma isotopic monthly the receiving river, suffacie"fy far up-stream with co!!ection every with quarterly composite (by such that no effects of pumped storage month.5 location) or monthly samplet operation are anticipated.3 to be analyzed for tritium. C) 1 Indicator sample from a location immediately Time composite samples 17 Gamma isotopic monthly upstream of the nearest downstream with collection every with quarterly composite (by municipal water supply. month.5 location) or monthly samplet to be analyzed for tritium. D) 1 Indicator sample to be taken in the upper Time composite samples 23 Gamma isotopic monthly reservoir of the pumped storage facility at the with collection every with quarterly composite (by plant discharge canal.3 month.5 location) or monthly samplet to be analyzed for tritium.
*E) 1 Indicator sample to be taken in the upper Time composite samples 25 Gamma isotopic monthly reservoir at the intake of the pumped storage with collection every with quarterly composite (by facility. month.5 location) or monthly samplet to be analyzed for tritium.
7 F) 1 Indicator sample to be taken in the upper Grab sampiing monthly 5 24 Gamma isotopic monthly i reservoir's non-fluctuating recreational area.3 with quarterly composite (by d location) or monthly samplet to be analyzed for tritium. 1 G) 1 Control sample to be taken at a location on a Grab sampling monthly 5 18 Gamma isotopic monthly separated unaffected watershed reservoir.3 with quarterly composite (by location) or monthly samplet to be analyzed for tritium i
APPENDIX B VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SPECIFICATIONS Exposure Pathway Criteria for Selection Sampling and Sample 1 Type & Frequency and/or Sample of Sample Number & Location Collection Frequency Location of Analysis V. Ground Water A) 2 Indicator samples to be taken within the Quarterly grab sampling 7 26 Gamma isotopic and tritium exclusion boundary and in the direction of 27 analyses quarterly. potentially affected ground water supplies. B) 2 Control samples from unaf fected locations. Quarterly grab sampling 7 16 Gamma isotopic and tritium 18* analyses quarterly. i VI. DrinkingWater A) 1 Indicator sample from a nearby public Monthly grab sampling 5 28 Monthly gamma isotopic, 9round water supply source. gross beta and tritium analyses.t B) 1 Indicator (finished water) sample from the Monthly composite 17 Monthly gamma isotopic, I nearest downstream water supply. sampling. gross beta and tritium analyses.t l
- C) 1 Control (finished water) sample from the nearest unaffected public water supply. Monthly composite 39 Monthly gamma isotopic, sampling, gross beta and tritium analyses.t t
APPENDIX B VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SPECIFICATIONS Exposure Pathway Criteria for Selection Sampling and Sample 1 Type & Frequency and/or Sample of Sample Number & Location Collection Frequency location of Analysis INGESTION: Vll. Milk 4 A) Samples from milking animals in 3 locations Biweekly grab 14* Gamma isotopic and 1-131 within 5 km having the highest dose potential. sample.8,
- i.e. w d analysis biweekly.s*
If there are none then 1 sample from milking .a w s animals in each of 3 areas between 5 to 8 km - %.d . distance where doses are calculated to be .aora.ac. .mn greater than 1 mrem per year.10 ne. v= 4 ; B) 1 Control sample to be taken at the location of Biweekly grab 16 Gamma isotopic and 1-131 < a dairy > 20 miles distance and not in the most sample.8,
- analysis biweekly.8*
prevalent wind direction.2 C) 1 Indicator grass (forage) sample to be taken at Monthly when 6 Gamma isotopic. one of the locations beyond but as close to the available 5 exclusion boundary as practicable where the highest of fsite sectoral ground level concentrations are anticipated.2 D) 1 Indicator grass (forage) sample to be taken at Monthly when 14* Gamma isotopic. the location of Vil(A) above when animals are available 5 i e. .w 4 on pasture. .wo m .n s a .refound .
.nord.nre omh I
camert.vm A. E) 1 Control grass (forage) sample to be taken at Monthly when 16 Gamma isotopic. the location of Vlil,B) above. available 5
APPENDIX B VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SPECIFICATIONS Exposure Pathway Criteria for Selection Sampling and Sample 1 Type & Frequency and/or Sample of Sample Number & Location Collection Frequency Location of Analysis Vill. Food Products A) Four samples of broadleaf vegetation grown in Monthly when available.s 2* Gamma Isotopic on edible l location of special interest and in the 3 5 portion. nearest offsite locations of highest calculated 6 annual average ground level D/Q if milk 8 sampling is not performed within 3 km or if milk sampling is not performed at a location
! within 5-10 km where the doses are calculated i to be greater than 1 mrem /yr.10
*B) 1 Indicator sample of each of the various types Annually during growing 6 Gamma Isotopic on edible of foods grown in the area surroundin g the season.11 portion.
plant. C) 1 Control sample for the same foods irs Vill (A) Same as for Vill (A) or (B), as 18 Gamma isotopic on edible and (B) taken at a location at least 10 rniles appropriate. portion. i distance and not in the most prevalent wind . direction.3 f ) )
APPENDIX B VIRGIL C. SUMMER NUCLEAR STATION R ADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SPECIFICATIONS Exposure Pathway Criteria for Selection Sampling and Sample 1 Type & Frequency and/or Sample of Sample Number & Location Collection Frequency Location of Analysis IX. Fish A) 1 Indicator sample to be taken at a location in Semiannualcollectionof the 23 Gamma isotopic on edible the upper reservoir.3 following specie typesif portions semiannually. available: bass; bream, crappie; catfish, carp; forage fish (shad). B) 1 Indicator sample to be taken at a location in Semiannualcollectionof the 21 Gammaisotopic on edible the lower reservoir.3 following specie types if portions semiannually. available: bass; bream, crappie; catfish, carp; forage fish (shad). C) 1 Indicator sample to be taken at a location in Semiannualcollectionof the 24 Gamma isotopic on edible the upper reservoir's non-fluctuating following specie types if portions semiannually. recreational area.3 available: bass; bream, crappie; catfish, carp; forage fish (shad). D) 1 Control sample to be taken at a location on Semiannual collection of the 22 Gamma isotopic on edible the receiving river. sufficiently far upstream following specie typesif portions semiannually. such that no effects of pumped storage available: bass; bream, operation are anticipated.3 crappie; catfish, carp; forage fish (shad).
APPENDIX B VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SPECIFICATIONS Exposure Pathway Criteria for Selection Sampling and Sample 1 Type & Frequency and/or Sample of Sample Number & Location Collection Frequency Location of Analysis AQUAIIC: X. Sediment A) 1 Indicator sample to be taken at a location in Semiannual grab sample.9 23 Gamma isotopic. the upper reservoir.3 B) 1 Indicator sample to be taken at a location in Semiannual grab sample.9 24 Gamma isotopic. the upper reservoir's non-fluctuating recreational area.3 C) 1 Indicator sample to be taken on the shoreline Semiannual grab sample.9 21 Gamma isotopic. of the lower reservoir.3 D) 1 Control sample to be taken at a location on Semiannual grab sample.9 22 Gamma isotopic. the receiving river sufficiently far upstream such that no effects of pumped storage operation are anticipated.3
# E) 1 Indicator sample to be taken at a location Semiannual grab sample.9 17 Gamma isotopic.
immediately upstream of the nearest downstream municipal water supply.3
# F) 1 Indicator sample to be taken at a location Semiannual grab sample.9 38 Gamma isotopic.
immediately downstream of the VCSNS liquid effluent discharge point.
#G) Ten (10) additional indicator samples to be Semiannual grab sample.9 80,81 Gamma isotopic.
taken at various locations on Congaree River 82,83 between Broad River and Lake Marion. 84,85 86,87 i 88,89
1 APPENDIX B FOOTNOTES l 1. Location numbers refer to Figures 1-1,1-2,1-3 in Appendix A.
- 2. Sample site locations are based on the meteorological analysis for the period of record as presented in Chapters 5.
and 6, Viroil C. Summer Operatina License Environmental Report. l , 3. water and sediment i Though sampfinggeneralized is done at the areas samearelocation noted for simplicity whereas of sample biological site enumeration, sampling airborne, d areas in order to sites are generalize i reasonably assure availability of samples. - l 4. Milking animal and garden survey results will be analyzed annually. Should the survey indicate new activity the. I owners shall be contacted with regard to a contract for supplying sufficient samples. It 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. i 6. Time composite sarhples 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.
l 10. Tne dose shall be calculated for the maximum organ and age group, using the guidance / methodology contained in Regulatory Guide 1.109, Rev. I and the parameters particular to the Site.
- 11. At least once per 400 days.
Not required by Technical Specifications.
- Only 8 Stations required by Technical Specifications.
j t Technical Specification is quarterly.
- Technical Specifications require semi-monthly sampling when animals are on pasture, monthly at other times.
# Special Study only. Not required by Technical Specifications. Results not included in this report.
l l APPENDIX C 1986 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/86-12/31/86 Type and Total Location with Highest Annual Mean Number of Medium or Pathway Lower Limit of All Indicator Sampled (Unit of Detection 1 Control Locations Nonroutine Locations Analyses (Name, Distance & Mean2 Mean2 (Range) Reported 3 l Measurement) Actual (Max.) Mean2 (Range) Performed Direction) (Range) Measurements Air Particulate Gross Beta 4 4.0E-3 Site #5, Transmission 6.2E-2(52/52) 3.6E2 (104/104 4.9E-2 (467/468) (pCi/m 3) (6 ( ' (572) (1.0E-2) (5.8E-3 to 6.9E-1) Line (0.9 mi SE) 6 9E-Gamma 5pec (131) Site #59, NTC
* '( '
i 1.2E-1 (94/108) 1.2E-1 (18/24) (5.0E-2 to 2.0E-1) (2.4 mi, SSE) (5.1E-2 to 2.0E-1) ( [0E- )
' ' ('#' }
4.9 E-3 7.9E-3 (15/108) Site 15, Parr Village 6 9E-3 (4/24) 0 (5.0E-2) (9.0E-4 to 1.5E-2) (2.5 mi, SSW) I(9 y (2.2E-3 to 1.4E-2) Site #5, Transmission 2.2 E-2 (2/12) 4.7 E-3 1.4E-2 (18/108) 1.4E-2 (4/24) Line (0.9 mi, SE) I (6.0E-2) (2.3 E-3 to 3.0E-2) (3.9E-3 to 2.7E-2) 3 OE-2 Air Radioiodine Site #5, Transmission 1.4 E-1 (4/52) 2.3 E-2 1.2E-1 (20/260) 1.3E-1 (8/104) (pCi/m3) 1 ( 64) (7.0 E-2) (1.0E-2 to 3.6E-1) Line (0.9 mi, SE) I (1.9E-2 to 3.1 E-1) 3 6E-Site # 9, Ball Park Direct (TLD)6 Gamma (264) .5( 04/204) (2.2 mi, NE) 12 3 (24/24) 9.7(60/60) 5.2 E-1 0 (pR/hr) Monthly (6.0 to 13.9) Site # 13, Nofth Dam (4.3 to 13.9) (6.4 to 12.4) (2.9 mi, NNW) 8 i
.\
APPENDIX C 1986 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/86-12/31/86 Type and Total L c tion with Highest Annual Mean Number of Medium or Pathway
""* Lower Limit of AllIndicator Sampled (Unit of Detection 1 Locations Control Locations Nonroutine
^"#'YS*' (Name, Distance & Mean2 Mean2 (Range) Reported 3 Measurement) Actual (Max.) Mean2 (Range)
Performed Direction) (Range) Measurements Site # 55,5L Gamma (107) 10.0(108/108) 34,4(4,4) 2E4 Barnabas Church (2.8 O Quarterly (5.7 to 14.6) (14.1 to 14.6) mi,E) Gamma Monthly Site #61,5witchyard 4.8(132/132) (0.1 mi,5) 5.6(24/24) I.' I (3.5 to 6.7) Site #62, Training (4.4 to 6.7) Special Study Bldg (0.1 mi, SW)
- I Surface Water 4.5E + 2 5.1 E + 2 (6/64) Site #24, Rqcreation 5.2E + 2 (1/25)
(pCi/l) H- (89) Lake (5.5 mi, N)
- 0 (2.0E + 3) (4.3E + 2 to 6.5E + 2) (Single Value)
( b SE + Gamma Spec (89) l Mn-54 gj# All < LLD All < LLD 0 E ) Co-58 gjE All < LLD All < LLD 0
)
Fe-59 (3 OE ; 1) All < LLD All < LLD 0 Co-60 gjE All < LLD All < LLD 0 Zn-65 All < LLD All < LLD 0 3 E ) Zr-95 All < LLD All < LLD 0 (3OE 1)
APPENDIX C 1986 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/86-12/31/86 ] Type and Total location with Highest Annual Mean Number of Medium or Pathway ; ;g g umber of Control Locations Nonrout_ne i Sampled (Unit of Detection 1 Locations
^"*'Y$'5 (Name, Distance & Mean2 Mean2 (Range) Reported 3 Meast,rement) Actual (Max.) Mean? (Range)
Performed Direction) (Range) Measurements 8 Nb-95 jE All < LLD All < LLD 0
)
C5-134 gjl 6E-1 ) All < LLD All < LLD 0 C5-137 All < LLD All < LLD 0 Ba-140 AH < LLD AH < LLD 0 (6.5 + 1) La-140 All < LLD All < LLD 0 0 E 1) Ra 226" 5.5E + 1
+( ) e# . ecreation 1 /13) 4.1 E + 1 t 0 (3.5E + 1 to 9.0E + 1) Lake (5.5 mi, N) (5.2E + 11 8.3E + 1) 9.0E + 1)
Ground Water 4.5E + 2 Site #26, Onsite Well .8E + 3 (1/4)
! 2.8E + 3 (1/8)
H- 6) ng e AH < 0 (pCi/l) (2.0E + 3) (Single Value) P4 (265 f t. W) ,)
- Gamma Spec i
(16) 3 , Mn-54 g ;4E 1) All < LLD All < LLD 0
. 58 ,,3spo,, Aii < LLD Aii < LLD 0 I
I APPENDIX C 1986 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Caro'ina Reporting Period: 1/1/86-12/31/86 i Type and Total L tion with Highest Annual Mean Number of Medium or Pathway Lower Limit of All Indicator Number of Control Locations Nonroutine Sampled (Unit of Detection 1 Locations Analyses (Name, Distance & Mean2 Mean2 (Range) Reported 3 Measurement) Actual (Max.) Mean? (Range) Performed Direction) (Range) Measurements Fe-59 ^"< ^"< (3 bE + 1) 33 0 Co-60 g All < LLD All < LLD 0
)
0 Zn-65 All < LLD All < LLD 0 0 Zr-95 AH < AH < 0 (3 bE + 1) 4 0 Nb-95 g All < LLD All < LLD 0 Cs-134 All < LLD All < LLD 0 0 bE + 4 0 Cs-137 All < LLD All < LLD 0 Ba-140 {) All < LLD All < LLD 0 La-140 All < LLD All < LLD 3 E + 1) 6.1E + 1 (2/8) Site #27, Onsite Well
+1( ) 6.5E + 1 (2/8)
Ra-226" 1.1 E + 2 ( + 1 to (18E + 1 to 0 (5.9E + 1 to 6.2E + 1) (PS) (510 ft. 5) 6 2E + 1) 7.2E + 1)
APPENDIX C 1986 RADIOLOG' CAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/86-12/31/86 Type and Total L c tion with Highest Annual Mean Number of Medium or Pathway Lower Limit of All Indicator Sampled (Unit of
" * ' ' " Control Locations Nonroutine Detection 1 Locations
^"# ' Y 5 (Name, Distance & Mean2 Mean2 (Range) Reported 3 Measurement) Actual (Max.) Mean2 (Range)
Performed Direction) (Range) Measurements
+
Drinking Water 7 2.1 E0 1.0E + 1 (26/26) Site #28, NTC (13/13) (pCill) Gr ss eta (39) (2.4 mi, SSE) I ' (4.0E0) (1.5E0 to 8.1 E + 1) (8.5E0 t 2OE+ 8.1 E + 1) Site # 17, Columbia 6.2E + 2 (2/13) 5.1 E + 2 (2/13)
"~ ( ( 3) (5.2h + 2 to 7 3E + 2)
# * ( ' ** * (
- SE) 7.3E + 2) 5.6E + 2)
Gamma 5pec (39) Mn-54 All < LLD All < LLD 0 OE ) l Co-58 (l 5E ; 1) All < LLD All < LLD 0 Fe-59 ^"< ^"< (3 b + 1) S Co-60 A I < LLD All < LLD 0 E ) Zn-65 All < LLD All < LLD 0 (3OE 1) Zr-95 All < LLD All < LLD 0 3 OE ) Nb-95 All < LLD All < LLD 0 (1 E 1) l
1 I APPENDIX C 1986 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/86-12/31/86 Medium or Pathway Type and Total Lower Limit of AH Indicator Numkr of Sampled (Unit of Number of Control Locations Nonroutine Detection 1 Locations Analyses (Name, Distance & Mean2 Mean2 (Range) Reported 3 Measurement) Actual (Max.) Mean2 (Range) Performed Direction) (Range) Measurements
#I 1-131 bCE0 All < LLD Al < LLD 0 l
Cs-134 gjE All < LLD All < LLD 0 l Cs-137 AH < AH < 0 (I8E 1) Ba-140 AH < D AH < RD 0 (6 bE + 1) 3 La-140 {j5E;1) ^"< ^"< 5.6E + 1 Site #17, Columbia 6.2E + 1 (12/13) Ra-226*
- 2.1 E + 2 (4.fE + 11 8 E 1)
### ( ' * *
(4IE to (. +1t 0 SE) 8.2E + 0 8.3E + 1) ! Milk Gamma Spec (pCi/l) (60) K-40** 4'3E0*
- 1. +( ) 5 e# , ah 0/30 1*3E + 3 t 0 (1.3E + 3 to 1.5E + 3) (5.1 mi W) (1.3E + 3 to 3.5E + 3) 1.5E + 3) 1-131
.1 0(3/30) Mte # 14, Daky 3E- to . 0(3/30) 0
- (1.0EO) (5.4E-1 to 3.8E0) (5.1 mi W) 61EO)
(5. - to 3.8E0)
APPENDIX C 1986 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/86-12/31/86 Type and Total Location with Highest Annual Mean Number of Medium or Pathway ,; ;g g ,g; fJumber of Control Locations Nonroutine Sampled (Unit of Detection 1 Locations Analyses (Name D; stance & Mean2 Mean2 (Range) Reported 3 l Measurement) Actual (Max.) Mean2 (Range) Performed Direction) (Range) Measurements ! 3.0E0 Site # 14, Dairy 2.4E0 (2/30)
- 2 4E0 (2/30) 3.0E0 (1/30)
(I 6E (Single Value) 0 (1.5E + 1) (1.6E0 to 3.2E D) (5.1 mi W) 3 E0 2.6E0 Site #14, Dairy 4.9E0 (14/30) 4.9E0 (14/30) 5.5E0 (30/30) I 0 ! (1.8E + 1) (1.6E0 to 3.3E + 1) (5.1 mi W) 3 3E (2.8E0 to 8.5E0) Ba-140 All < LLD All < LLD 0 6 E+U La-140 All < LLD All < LLD 0 OhE Gamma Spec Grass (pCi/kg wet) (42) Be-7 9'3E + 1
*( } '# * # 'Y 2.2 E 2t 0 (1.1E + 1 to 1.6E + 3) (5.1 mi W) (1.2E + 2 t 3.0E + 3) 1.5E + 3) 4 6
5.4E + 3 (28/28) Site #14, Dairy + K-40 *
- 4.3E0* 5/15 0 (4.1E + 3 to 8.5E + 3) (5.1 mi W) '
(4.2E + 3 to
- l 8.5E + 3) t i
., I i APPENDIX C 1986 RADIOLOGlCAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
l Virgil C. Surnmer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/86-12/31/86 Typ n Total n th Wghest Annual Mean Number of Medium or Pathway Lower Limit of AllIndicator Sampled (Unit of Control Locations Nonroutine Detection 1 Locations AnMyse (Name, Distance & Mean2 Mean? (Range) Reported 3 Measurement) Actual (Max ) Mean2 (Range) P r d Direction) (Range) Measurements 9 + 1 (4/15) 1.3E + 2 (4d4) 18E + 1 7.3E + 1 (3/28) Site #14, Dairy I' ' ( E* (6.0E + 1) (1.1E + 1 to 2 2E + 2) (5.1 mi W) E+) 19E + 2) 13E + 1 Site #14, Dairy 1.6E + 1 (5/15) Cs-134 1.5E + 1 (7/28) 2.0E + 1(6/14) (8.0E0 t 0 (6.0E + 1) (7.9E0 to 2.8E + 1) (5.1 mi W) 2.8E + 1 (6.0E0 to 3.1E + 1 1.4E + 1 Site #14, Dairy 3.0E + 1 (7/15) 4.7E + 1 (6/14) Cs-137 2.5E + 1 (13/28) (8.3E0 to (2.4E + 1 to 0 (8 0E + 1) (7.7E0 to 5.1E + 1) (5.1 mi W) 5.1 E + 1) 9.0E + 1) Broadleaf Vegetation Gamma 5pec (41) (pCi/kg wet) 2.1E + 2 (19/32) Site #5, Garden
* (# '~ * ( #9}
Be4 7.0E + 1 * ( * (6.2E + 1 to 6.0E + 2) (0.9 mi, SE)
"'.0E+2) 6 3.1E + 2) 5.2E + 3 (3/3) 4.5E + 3 (9/9)
K-40** 4.3E0* ( + to (3.2E + 3 to 0 (2.6E + 3 to 7 9E + 3) (.2 i SVV) 5.5E + 3) 6.9E + 3) 1.2E + 1 3.2E + 1 (3/32) Site #6, Garden * ' I # I' 3.3E + 1 (1/9)
' 0+
(6.0E + 1) (2.0E + 1 to 5.0E + 1) (1.0 mi ESE) ( f 0E + (Si"9t ' v*l"') 9.1 7. 3E0 (1/13)
- 7. 3E0 (1/32) S.ite #6, Garden C5-134 (Single All < LLD 1 (6.0E + 1) (Single Value)
(1.0 mi ESE) Value)
I i APPENDIX C 1986 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/86-12/31/86 y an o at n h Nghest Annual Mean Number of Medium or Pathway Lower Limit of All Indicator Sampled (Unit of Detection 1 Control Locations Nonroutine Locations nMYS (Name, Distance & Mean2 Mean2 (Range) Reported 3 Measurement) pg{ , ed Actual (Max.) Mean2 (Range) Direction) (Range) Measurements 9.2 1.2E + 1 (1/13) 1.2E + 1 (1/32) Site #6, Garden (Single All < LLD 0 (8 OE + 1) (Single Value) (1.0 mi ESE) Value) Other Vegetation Gamma 5pec3 (pCi/k g wet) 8 2E + 1 All < LLD Be-7 2.7E + 3 (3/3) Site #6, Garden
- I '
K-40* " 8 8E0 (1.6E + 3 to 4.4E + 3) (1.0 mi ESE) 4 4E + 3) 2 + 1-131 All < LLD
*l Cs-134 All < LLD 1.1 E + 1 4.8E0 (1/3)
- 4 8E0 (1/3) Site #6, Garden (Single (8.0E + 1) (Single Value)
(1.0 mi ESE) Value) Gamma Spec Fish (pCi/kg wet) (31) Site #21, Parr 3.1E 4 3 (8/8) 3.0E + 3 (7/7) K-40* *
- 8.8E0* .0E + 3 (24/24) Reservoir (1.9F + 3 to (2.5E + 3 to O (1.8E + 3 to 3.6E + 3) (2.7mi, SSW) 3 6E + 3) 3.5E + 3) 9 7E0 Mn-54 All < LLD All < LLD 0 05E 7)
e APPENDIX C 1986 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/86-12/31/86 pe d otal c h Highest Annual Mean Number of Medium or Pathway Lower Limit of AllIndicator Sampled (Unit of
f Detection 1 Locations Control Locations Nonroutine Ana es (Name, Distance & Mean2 Mean2 (Range) Reported 3 Measurement) p f Actual (Max ) Mean2 (Range)
Direction) (Range) Measurements Co-58 All < LLD All < LLD 0 E Fe-59 { All < LLD All < LLD 0 0 Co-60 , All < LLD All < LLD 0 2 Zn-65 All < LLD All < LLD 0 Site #21, Parr
+
1.1 E + 1 9.30E0 (4/24) Reservoir Cs-134 (2.7mi, SSW) (Single All < LLD 4 (1.3E + 2) (4.0E0 to 1.4E + 1) Value) 1.0E + 1 1.7E + 1 (7/8) 1.5E + 1 (18/24) Site #24, Rec. Lake 1.6E + 1 (7/8) (9 0E0 t 0 (1.5E + 2) (6 8E0 to 3.6E + 1) (5.5m,,i N) (9.1E0 to 3.0E + 1) 3.6E + 1) Gamma 5pec Sediment (pCi/kg)B Ste #21, Parr 1.4E + 4 (70/70) 1 6 K-40*** 8.8E0* g1.4E 4 t 0 (6.1E + 3 to 2.2E + 4) Reservoir (1.2E + 4 to (2 7mi, SSW) 2.2E + 4)
~
*}
i
APPENDIX C J
\
1986 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/86-12/31/86 Type and Total U Numkr of l Medium or Pathway Lower Limit of All indicator Control Locations Nonroutine
"* ' Detection 1 Locations Sampled (Unit of Mean2 (Range) Reported 3 Measurement)
^"#'Y Actual (Max.) Mean2 (Range) (Name, Distance & Mean; l Performed (Range) Measurements Direction) 2.7E + 1 (14/70) Site #21, Part 2.9E + 1 (5/16)
Mn-54 1.8E + 1 All < LLD 14 1.2E + 1 to 5.0E + 1) Reservoir 1.2E + 1 to (2.7mi, SSW) 5.0E + 1) Site #17, Columbia 6.0E + 1 (7/16) 3.9E + 1 (17/70) + to AH < RD 17
~
- Canal (25 mi, SE) (1.
(9.0E0 to 9 OE + 1) 9.0E + 1) Site #21, Parr 8 AH < 60
-60 L6E + 1 $
(96E0t 3E + 2) 7 i 55 ) (3. E + to 4.3E + 2) Cs-134 All < LLD All < LLD 0
.)
* ('
1.9E + 1 1.4E + 2 (68/70) Site #21, Parr 16/16
(1.8E + 2) (1.5E + 1 to 3.1E + 2) Reservoir (2.0E + 2 t
( + 6E + 2) (2 7mi, SSW) 3.1E + 2) l i l l
1
?
APPENDIX C 1986 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Footnotes
- 1. LLD values given are values calculated from the program data analyses with maximum acceptable 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. Any confirmed measured level of radioactivity in any environmental medium that exceeds ten times the control station value. Radioactivity attributed to the Chernobylincident was not reported as non-routine measurements provided measurements from control locations were positive for fission product activity.
- 4. Four samples exceeded maximum LLD because of low sample volume. The calculated LLD's were 1.2E-2,2.3E-2,1.2E-2 and 2.0E-2 pCi/m3
- 5. One sample exceeded maximum LLD. The calculated LLD was 7.8E-2 pCi/m3
- 6. Detection sensitivity is approximately 5 mrem /yr (0.52 uR/hr) determined from the analyses of five years of preoperational data.
- 7. 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.
- 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.
- LLD values for K-40 in milk, vegetation, fish and sediment samples are calculated using data from respective background analyses and the methodology for calculating LLD outlined in the footnotes of VCSNS Technical 5pecifications, Table 4.12-1.
** Gamma spectroscopy system background levels for Ra-226 and K-40 were 6.4E + 1 and 5.6E + 1 pCi/ liter, respectively.
Reported levels of Ra-226 and K-40 have not been background corrected.
*** Gamma spectroscopy system background level for K-40 was 1.1E + 2 pCi/ liter. Reported level of K-40 has not been background corrected.
APPENDIX D 1986 ENVIRONMENTAL 5AMPLING PROGRAM EXCEPTION 51 Sample Type Week 2 Site 3 Cause for Exception Air Particulate 4 Grass 2,6,10,49 6 Seasonal Unavailability 6,10,28 14 Seasonal Unavailability 2.5,10,28 16 Seasonal Unavailability Broadleaf Vegetation 2,6,10,15,19, 2 Seasonal Unavailability 27,31,36,40 6,10,15,19 5 Seasonal Unavailability 2,6,10,15 6 Seasonal Unavailability 6,10,15,19 8 Seasonal Unavailability 6,11,15,31 18 Seasonal Unavailability Fish (bass) fall 22 Seasonal Unavailability
- 1. Sample has been omitted unless otherwise specified.
- 2. Week in which sample was picked up (ending week for composite samples).
- 3. Referto Appendix A forsitelocations.
- 4. All samples were collected, but 17 of 572 continuous weekly samples were partial samples attributed to air sampler power outages.
APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
PREOPERATIONAL (BASELINE)
SUMMARY
l Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 5/79-10/82 ' T nd Totaf th Mghest Annual Mean Number of Medium or Pathway , Lower Limit of AllIndicator Sampled (Unit of b Detection 1 Control Locations Nonroutine Locations Y5 '5 (Name, Distance & Mean2 Mean2(Range) Reported 3 Measurement) p g, Actual (Max.) Mean2 (Range) d Direction) (Range) Measurements 1.3E-1(53/53) 7.5E-2 (1021/1038)4 Site #13, North Dam (2.1 E-2 to 8.1 E-2 (282/285) Air Particulate Gross Beta 4.5 E-3 (1 to iS H (2.9 mi NM 5.5 E-1) 60E-3 to 61EW (pCi/m3) (1323) (1.0E-2) 2.9E-2 (540/549)4 Site #8, Mon. Res. 5 3.2E-2 (57/58) 3.0E-2 (172/174) (1.1 E-2 to 6.0E-2) of Rd 224(1.5 ENE) (1.2E-2 to (6.0E-3 to 1.2E-1) 6.0E-2) Gamma 5pec (307) Site #13, North Dam 2.5E-1 (10/22) 1.3 E-1 (106/241) 1.3E-1 (30/66) 8E 0 (1.0E-2 to 9.5E-1) (2.9 mi NNW) (f pE (5.1 E-2 to 3.5E-1) Site # 13, North Dam .0E-2 (5/22) r 8 OE-3 6.0E-2 (57/241) 6.0E-2 (16/66) ( 0 (3.0E-2 to 1.1 E-1) (2.9 mi NNW) (9.0E-3 to 1.2E-1) E m .. 3.3M (64/241) Site #13, North Dam
' 3.7E (19/66)
Nb-95 3.0E-2 ( E- to 0 (1.0E-2 to 1.7E-1) (2.9 mi NNW) 7.7E-1) ( -1to12EW 0
.0 62(35/241) Site #2, Transm. Une '
~( }
Ru-103 7.0E-3 (3 E-2 to O (1.0E-2 to 8.0E-2) (1.1 mi SW) ( .0E-2 to 9.0E2) 7.0E-2)
.062 W2W Me o ogIcal 6)
Ru/Rh-106 4'OE-3 (Sin 0 (2.0E-2 to 4.0E-2) Tower #2 (2.4 m.i (Single Value) Value) NNE) 3 Cs-134 All < LLD All < LLD 0
)
3.0E-3 Site #13 North Dam .0E3 (2/22) 3.0E-3 (21/241) 4.0E-3 (5/66) 0 ( f 0E-3 (' 5 (1.0E-2) (2.0E-3 to 5.0E-3) (2.9 mi NNW) '
APPENDIX E : RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
PREOPERATIONAL (BASELINE)
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 5/79-10/82 Medium or Pathway Type and Total Lower Limit of All Indicator Numkr of Number of Control Locations Nonroutine Sampled (Unit of Detection 1 Locations Measurement) ^"*'Y Actual (Max.) Mean2 (Range) (Name, Distance & Mean2 Mean2 (Range) Reported 3 Performed Direction) (Range) Measurements Me orological ' E-2 (1/22) 4.0E-2 (22/241) 4.0E-2 (6/66) Ce-141 5.0E-3 (1.0E-2 to 7.0E-2) Towe/ #2 (2.4 mi Ib 9 (2.0E-3 to 7.0E-2) O
- y NNE) 4.0E-2 (68/241) Site # 13, North Dam
~
~( ' 4.0E-2 (18/66)
- 0 O (1.0E-2 to 7.0E-2) (2.9 mi NNW) ( j 0E-2) (1.0E-2 to 7.0E-2) pCi/ l-131(482) All < LLD All < LLD 0
)
Direct (TLD)5 Gamma (1238) 9.8(915/915) Site #13, North Dam 13.9(60/60) 9.9(295/295) Monthly 0.52 0 (uR/hr) (6.7-14.8) (2.9 mi NNW) (12.5-14 8) (6.0-14.0) Site # 55, St. i Gamma (154) 9.9(154/154) 13.6(7/7) 052 *'"* *' " Quarteriy l (5 3-14.7) (11.4-14.7) mi E) H-3(71) { All < LLD All < LLD 0 Ci 4 Gamma Spec (219) I Mn-54 All < LLD All < LLD 0 (1f5E1) O Co-58 g E All < LLD All < LLD 0 Fe-59 AH < D AH < RD 0 (3OE 1) Co.60 3s,oE;1 All < LLD All < LLD 0 9) Zn-65 (3 OE ; 1) All < LLD All < LLD 0 O Zr-95 gj E 1) All < LLD All < LLD 0
APPENDlX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
PREOPERATIONAL (BASELINE)
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 5/79-10/82 Type and Total L c tion with Highest Annual Mean Number of Medium or Pathway Lower Limit of All Indicator Number of Control Locations Nonroutine Sampled (Unit of Detection 1 Locations
#"*'Y5 (Name, Distance & Mean2 Mean2(Range) Reported 3 Measurement) Actual (Max.) Mean2(Range)
Performed Direction) (Range) Measurements O Nb-95 All < LLD All < LLD 0 E ) 0 Cs-134 ggE All < LLD All < LLD 0 Cs-137 All < LLD All < LLD 0 0 8E Ba-140 All < LLD All < LLD 0 6 bE + 1) O La-140 All < LLD All < LLD 0 E ) gpCi H-3(52) All < LLD All < LLD 0 E Gamma Spec (62) 40 Mn-54 g, fE D All < LLD All < LLD 0 40 Co-58 gjE 1) All < LLD All < LLD 0 0 Fe-59 ^"< ^"< (3 fE + 1) 3 ! Co-60 g; 5E + U All < LLD All < LLD 0 Zn-65 ^"< A" < (3 OE + 1) 0 Zr-95 gfE D All < LLD All < LLD 0 Nb-95 ^"< ^"< (15E + 1)
#0 Cs-134 g fE + 1) All < LLD All < LLD 0 l
j
APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
PREOPERATIONAL (8 ASELINE)
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 5/79-10/82 l Type and Total Locatioriwith Highest Annual Mean Number of Medium or Pathway r LimiW MIIMi e Sampled (Unit of
""" ' Control Locations Nonroutine Detection 1 Locations Analyses (Name, Distance & Mean2 Mean2 (Range) Reported 3 Measurement) Actual (Max.) Mean2 (Range)
Performed Direction) (Range) Measurements 40 Cs-137 g f, 0 ) All < LLD All < LLD 0 Ba-140 All < LLD All < LLD 0 (6 ) O La-140 g E 1) All < LLD All < LLD 0 1.7E + 1 Drinking Water 6 0 1.0E + 1 (100/109) Me #28, Jenkinsville (55/55) (pCill) Gross Beta (80) 0 (2.0E0) (1.1E0 to 5.5E + 1) Diner (2.0 mi SE)7 (2.7E0 to 5.5E + 1) H-3(22) 950(1000) All < LLD 0 Gamma 50ec 9.5E + 2 (80) (1.0E + 3) Mn-54 All < LLD 0 O SE O Co-58 All < LLD 0 E Fe-59 ^"< (3 bE + 1) O ' Co-60 All < LLD 0 E ) Zn-65 All < LLD 0 3 E 8 Zr-95 g 5E All < LLD 0
)
O Nb-95 All < LLD 0 E 1-1318 All < LLD 0 i
APPENDIX E . RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
PREOPERATIONAL (B ASELINE)
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 5/79-10/82 Medium or Pathway Type and Total Lower Limit of All Indicator NumW of Sampled (Unit of
""* Detection 1 Locations nu I cadons Nonroudne Analyses (Name, Distance & Mean2 Mean2 (Range) Reported 3 i Measurement) Actual (Max.) Mean2 (Range)
Performed Direction) (Range) Measurements 0 Cs-134 gfE All < LLD 0 Cs-137 A < LLD 0 0 8E
+
Ba-140 All < LLD 0 6 +) La-140 AH < 0 15E 1) 7.3E0 (27/35) I Site #28, Jenkinsville 6.4E0 (64/70) 3E (2.5E0 to 1.3E + 1) Diner (2.0 mi ESE)7 Ra-226 8.0E-1 0 5.5E + 1 (10/10) Site #28. Jenkinsville (2.8E + 1 to 8 4E + 1) Diner (2.0 mi ESE)7 f1 10) (2.8E + 1 to 8.4E + 1) 3.1 E0 (16/80) Site #28, Jenkinsville 3.1 E0 (M ( 0o O (2.1 E0 to 4.5E0) Diner (2.0 mi ESE)7 Milk Gamma Spec l (pCi/l) (144) 1.4 + ( a) ite #14, Dairy 2n2 K-40 7OE+1 2~BE + 2 0 (2.3E + 2 to 1.6E + 3) (5.1 mi W) (2.3E + 2 to j.6E + 3) 1.6E + 3) 1-1318 All < LLD All < LLD 0
)
0 Cs-134 jE + 0 All < LLD All < LLD 0
- 1. O 9.5E0(11/72)
Cs-137 All < LLD g (1.5E + 1) ,(5.5E0 to 1.1E + 1) i l
APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
PREOPERATIONAL (BASELINE)
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 5/79-10/82 y d Total ghest Annual Mean Number of Mediurn or Pathway , Lower Limit of All Indicator Sampled (Unit of Detection 1 Locations Control Locations Nonroutine (Name, Distance & Mean2 Mean2 (Range) Reported 3 Measurement) Actual (Max.) Mean2 (Range) Perfofme$ d Direction) (Range) Measurements E* Ba-140 All < LLD All < LLD 0 E 3 La-140 g 5E + 0 All < LLD All < LLD 0 Gamma Spec Grass (pCi/kg wet)
+ ( te # 16, Env. Lab 1 22 2.{E + 2 t Be-7 2'9E + 2 0 (1.1 E + 2 to 7.1E + 3) Garden (1.0 mi ESE) (2.1 E + 2 t 8.4E + 3) 3.1E + 3) 6.0E + 3 M53) We M, Dairy /30
; K-40 7.5E + 2 3 3E + 3 to O (1.0E + 3 to 9.5E + 3) (5.1 mi W) (4.0E + 3 t
, 9.5E + 3)
IhE 4 6 ' 1-1318 All < LLD All < LLD 0 E 2
- Cs-134 All < LLD All < LLD 0 6
3.3E + 1 Site #14, Dairy .9E + 1 (5/30) 1.3E + 2 W3 0 5^ 3.9E + 1 (13/53)
+ to 0.3E + 1 to 0 (8.0E + 1) (1.6E + 1 to 1.6E + 2) (5.1 mi W) 1.6E + 2) 3.4E 4 2)
Broadleaf Vegetation Gamma Spec (19) (pCi/kg wet)10 4 + 3 (2/2) 6.8E + 3 (4/4) 3.8E + 3 (15/15) Site #2, Trans. Line I O 4.0E + 2 (1.8E + 3 to 5.7E + 3) (1.2 mi SW) (. + t (4.2E + 3 to 0
- 5.7E + 3) 9.4E + 3) 3
- 1-1318 All < LLD All < LLD 0 6
Cs-134 All < LLD All < LLD 0
APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
PREOPERATIONAL (BASELINE)
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 5/79-10/82 Medium or Pathway bpe a tal Numkr of Lower Limit of All Indicator Sampled (Unit of ""* Control Locations Nonroutine Detection 1 Locations Measurement) ^"*'Y Actual (Max.) Mean2 (Range) (Namd, Distance & Mean2 Mean2 (Range) Reported 3 Performed Direction) (Range) Measurements Cs-137
^ * * *#* " "5 ' '
(2 7E + 1 to I~ *II'#I) 0 (8.0E + 1) (2.7E + 1 to 3.6E + 1) (1.2 mi SW) 3.6E + 1)
"9 8'"'}
Other Vegetation Gamma 5pec (pCi/kg wet) (65) I Site # 6, Env. Lab. 6
.6E + 3 (29/29)
- 3.1E + 3 (36/36) 3 (2 *
(1.9E + 3 to 5.4E + 3) Garden (1.0 mi ESE) (1.9E + 3 to 8E + 3) 5 4E + 3) Cs-134 All < LLD All < LLD 0 E
- 1. E + 1 (1/29)
C5-137 All < LLD O i (8 OE + 1) (Single Value) Fish (pCi/kg wet)9 ( 10
+ ( 89 Ste #24, Remation 7/27 K-40 74E+31 0 5'OE + 2 (2.1E + 3 to 7.5E + 3) Lake (5.5 mi, N) (4.2E + 2 t 6.1E + 3) 7.6E + 3)
Cs-134 E All < LLD All < LLD 0
.5E + 1 2SE + 1 (66/85) Site #24, Remation 0/27)
Cs-137 Lake (5.5 mi, N) 1.0E + 1 t 0 l (1.5E + 2) (9.0E0 to 1.0E + 2) (1.1E + 11 7.9E + 1) i 1.0E + 2) Co-58 All < LLD All < LLD 0 3 Mn-54 [ Ali < LLD All < LLD 0 Fe-59 , All < LLD All < LLD 0 J
APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
PREOPERATIONAL (B ASELINE)
SUMMARY
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 5/79-10/82 b n otal , th Wghest Annual Mean Number of Medium or Pathway Lower Limit of All Indicator Sampled (Unit of f Control Locations Nonroutine Detection 1 Locations na (Name, Distance & Mean2 Mean2 (Range) Reported 3 Measurement) p ,fo med Actual (Max.) Mean2 (Range) Direction) (Range) Measurements
#3*
Zn-65 All < LLD All < LLD 0 6 Co-60 { All < LLD All < LLD 0 Gamma Spec Sediment (pCi/kg) Site #24, Recreation
- I '
1.6E + 4 (32/35)
-0 4.0E + 2 (4.4E + 3 to 9.0E + 4) Lake (5.5 mi, N) ( + ( +
2.0E + 4) 2.0E + 4) Cs-134 22 ' All < LLD All < LLD 0 (, 5E 2) e# , sc arge 2.6E + 2 @2) 3.6E + 2 M2) 2.5E + 1 2.4E + 2 (27/35) 5' (1.8E + 2) (1.2E + 1 to 1.1E + 3) nal nt es) (1. + 1 to (L4E + 1 to 0 (0.5 mi ESE) 1.1 E + 3) 1.0E + 3) l 1 j i
! APPENDIX E I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SUMM ARY l PREOPERATIONAL (BASELINE)
SUMMARY
3 j Footnotes ) 1. LLD values given are values calculated from the program data analyses with maximum acceptable values allowed from NRC l guidelines given in parentheses. I 2. Mean and range are based on detectable measurements only. The fractions of detectable measurements at specific
- locations are indicated in parentheses.
- 3. A nonroutine measurement is any confirmed measured level of radioactivity in any environmental medium that exceeds ten times the control station value.
. 4. The baseline values are high because of the fallout from the Chinese bomb test in 1980. The second set of values reflects a
- better set of baseline numbers, essentially free of bomb test fallout. This latter set covers the period 9/4/81 - 10/22/82.
i 5. Detection sensitivity is approximately 5 mrem /yr (0.52 uR/hr) determined from the analyses of five years of preoperational l data. ! 6. No control location is specified for drinking water. ! 7. Bimodal distribution of values present; mean of 6.4 through first half of 1981 and after March,1982 and mean of 55 for a
- 10 month period beginning June,1981. These high Ra-226 values (also reflected in gross beta and U-235 measurements) appear to be due to high granite content content in some wells added to the Jenkinsville water system during this period.-
- 8. Several individual determinations did not meet the required maximum LLD due to insufficient sample volume and/or delay in counting sample after collection.
i
- 9. Detectable levels of natural U-235 were randomly found in samples from all fish sampling locations.
l 10. Prior to the 1982 growing season there were only two gardens sampled, one indicator, Site #6, Environmental Lab Garden, and one control, Site # 18, Corley's Garden. In 1982 the control garden at Site # 18 was moved down the street to Wyse's Garden (approximately the same distance and direction) and three additional indicator gardens were added (for broadleaf vegetation only) at Site #2, Transmission Line; Site #4, Fairfield Hydro; and Site #8, Monticello Reservoir South of Road j 224. Monthly sampling was begun on broadleaf vegetation at Sites #2,4,6 and 8 in September,1982. I I J i
APPENDIX F - RESULTS OF 1986 EPA INTERCOMPARISON PROGRAM Comparison Stud EPA Value Agree-
-(Measurement Unft) Date Nuclide
( lo) Result { g jg) ment Air filter (pCi/ filter) 4/86 beta 47(5) 61(2) Yes Cs-137 10(5) 11(2) Yes 9/86 beta 66(5) 79(4) Yes Cs-137 22(5) 26(1) Yes Gamma in Water 2/86 Cr-51 38(5) 39(8) Yes (pCi/ liter) Co-60 18(5) 19(1) Yes - Zn-65 40(5) 40(3) Yes Ru-106 0 (5) < 22 Yes Cs-134 30(5) 30(2) Yes Cs-137 22(5) 22(1) Yes 6/86 Cr-51 0(5) < 48 Yes Co-60 66(5) 66(3) Yes Zn 65 86(5) 87(5) Yes Ru-106 50(5) 48(4) Yes Cs-134 49(5) 46(1) Yes Cs-137 10(5) 10(0) Yes 10/86 Cr-51 59(5) 48(9) Yes Co-60 31(5) 33(1) Yes Zn-65 85(5) 94(4) Yes Ru-106 74(5) 71(5) Yes Cs-134 28(5) 27(1) Yes Cs-137 44(5) 48(3) Yes Gross Beta in Water 1/86 beta 7(5) 7(1) Yes (pCi/ liter) 3/86 beta 8 (5) 10(1) Yes 5/86 beta 15(5) 10(5) Yes 7/86 beta 18(5) 18(1) Yes 9/86 beta 8 (5) 9 (0) Yes 11/86 beta 20(5) 20(1) Yes F-1
)
APPENDIX F - RESULTS OF 1986 EPA INTERCOMPARISON PROGRAM (continued) Comparison Stud EPA Value l t y Date Nuclide Resul Ag ree-(Measurement Unft) ( t lo) ( f 3 g) ment lodme in Water 4/86 1-131 9 (6) 8 (1) Yes (pCi/ liter) 8/86 l-131 45(6) 46(2) Yes Laboratory Blind 4/86 beta 35(5) 34(0) Yes (pCi/ liter) Co-60 10(5) 10(1) Yes Cs-134 5 (5) 5 (0) Yes Cs-137 5 (5) 5 (1) Yes 10/86 beta 51 (5) 47(2) Yes Co-60 24(5) 24(2) Yes Cs-134 12(5) 11(0) Yes Cs-137 8 (5) 8 (1) Yes i Radionuclides in Milk 2/86 l-131 9 (6) 9 (1) Yes (pCi/ liter) 6/86 l-131 41(6) 46(3) Yes Cs-137 31(5) 37(2) Yes 10/86 l-131 49(6) 53(2) Yes Cs-137 39(5) 43(1) Yes Tritium in Water 2/86 H-3 5227(523) 5460(187) Yes (pCi/ liter) 6/86 H-3 3125(360) 3250(191) Yes 10/86 H-3 5973(597) 6300(191) Yes Radionuclides in Food 1/86 l-131 20(6) 20(2) Yes (pCi/kg) Cs-137 15(5) 18(0) Yes 7/86 l-131 29(1) 36(6) Yes Cs-137 20(5) 23(2) Yes F-2
APPENDlX G - RESULTS OF 1986 INTRACOMPARISON PROGRAM WITH VCSNS COUNT ROOM Comparison Study Laboratory VCSNS Count Agree-Date Nuclide Room Results ment (Measurement Unit) Results Mixed Gamma in 1 liter 3/86 Ar-41 2.35 E-6 2.18E-6 Yes Gas (uCi/ml) Kr-85m 1.29E-5 1.38E-5 Yes Kr-88 1.70E-5 1.76E-5 Yes Xe-133 4.73 E-4 5.04E-4 Yes Xe-133m 1.05E-5 1.18E-5 Yes Xe-135 2.01 E-4 2.14 E-4 Yes lodine in Silver Zeolite 6/86 l-131 3.73E-1 3.17E-1 Yes1 Cartridge (uCi) 1-131 1.97E-1 1.81 E-1 Yes2 Tritium in Water 9/86 H-3 2.02E-1 1.90E-1 Yes (uCi/ml) Alpha in Water (uCi/ml) 12/86 Alpha 5.65E-4 6.90E-4 Yes
- 1. Face loaded cartridge.
- 2. Body loaded cartridge. ,
G-1
~ _ _ _ - - , . - - - _ - - -
APPtWDIX H -
SUMMARY
OF 1986 INTERCOMPARISON PROGRAM WITH SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROLS 1 Pathway (Units) Frequency Nuclide Loc t n Surface Water No. 21 Monthly' 3H (pCi/ liter) Mixed Gamma No. 22 Monthly 3H Mixed Gamma Air (pCi/m3) No. 6 Monthly Gross Beta lodine Mixed Gamma .- No.13 Monthly Gross Beta Mixed Gamma No.17 Monthly Gross Beta lodine Mixed Gamma Milk (pCi/ liter) No.14 Monthly Mixed Gamma Sediment (pCi/kg) No. 23 Semiannually Mixed Gamma Fish (pCi/kg) No. 23 Semiannually Mixed Gamma Vegetation (pCi/kg) No. 6 Semiannually Mixed Gamma , Direct (mR/hr) No. 4 Quarterly Exposure l No. 6 Quarterly Exposure l No. 8 Quarterly Exposure j No.15 Quarterly Exposure I 1. i l 1. Intercomparison results are reported by SCDHEC. l l l H-1 _ - _ _ . - - = _ - - _ _ _ - . _ . . . . . - . - . - . .
i
- APPENDIX l- RESULTS OF ENVIRONMENTAL DOSIMETRY INTERCOMPARISON WITH NRC TLD DIRECT RADIATION MONITORING NETWORK 1985 FOU RTH QUARTER RESULTS 1986 FIRST QUARTER 1986 SECOND QUARTER RESULTS 1986 THIRD QUARTER NRC TLD LABORA. (uR/hr) RESULTS (uR/hr) (uR/hr) RESULTS(uR/hr)
STATION TORY TLD NRC Laboratory '" 7 Df rence # '# 7 # '# 7 Df rence D ff rence Df rence 1 42 10.2 7.5 26.5 10.6 7.2 32.1 7.1 8.1 -14.1 9.4 7.6 19.1 2 6 8.3 7.8 6.0 11.4 7.6 33.3 8.1 8.7 -7.4 9.2 8.8 4.3 5 54 11.3 11.5 -1.8 11.9 11.3 5.0 8.1 12.7 -56.8 11.0 12.2 -10.9 7 *53 13.1 12.5 4.6 13.5 11.9 11.9 6.8 12.5 -83.8 12.5 14.0 -12.0
- 9 *52 12.9 12.0 7.0 13.6 12.4 8.8 9.2 13.3 -44.6 13.1 12.2 6.9 11 *12 9.4 9.1 3.2 10.6 9.0 15.1 11.4 9.7 14.9 9.8 9.9 -1.0 13 13 12.2 12.8 -4.9 12.4 12.0 3.2 7.5 13.1 -74.7 11.0 12.7 -15.5 14 *44 8.4 6.9 17.9 8.8 6.5 26.1 7.5 7.4 1.3 10.7 7.3 31.8 i
19 *56 9.3 9.4 -1.1 10.6 7.9 25.5 6.9 9.4 -36.2 9.6 9.4 2.1 22 58 9.0 6.3 30.0 8.4 6.2 26.2 10.2 7.0 31.4 8.1 6.2 23.5 24 41 9.1 9.2 -1.1 9.0 8.7 3.3 8.3 9.4 -13.3 9.0 10.1 -12.2 l 29 *60 11.1 11.3 -1.8 11.2 11.1 0.9 8.6 11.6 -34.9 11.0 12.2 -10.9 30 46 -- 10.0 -- 13.6 9.8 27.9 7.4 10.6 -43.2 13.6 10.5 22.8
- Co-located dosimeters within 10 ft. of NRC dosimeter.
APPENDIX J - RESULTS OF THE 1986 LAND USE CENSUS VERIFICATION 4 The annualland use census for 1986 was conducted from August 5 through August 19,1986. The results of the 1986 census are summarized in Table J-1.
- 1. The Radiological Environmental Laboratory gardens remained located in the following sectors:
- a. SW,1.2 miles- Site #2
- b. SE,0.9 miles-Site #5
- c. ESE,1.0 miles-Site #6
- d. ENE,1.5 miles-Site #8 These locations reflect results of the D/Q_q.alculations for critical receptors following the 1982 land use census. D/O represents the annual average relative deposition of gaseous effluents released from VCSNS at the location occupied by the maximum exposed individual. These results have been reconfirmed following the 1983,1984 and 1985 census. Sites 5,6 and 8
. , are used as the gardens required by Technical Specifications, Table 3.12-1, item Vill.A. Site 2 is maintained in order to monitor the potential grazing area in that sector on the west side of Parr Reservoir.
- 2. Residential development of the shorelines of Monticello and Parr Reservoirs and the Jenkinsville area was increasing.
- 3. There were still no milking animals being milked within 5 miles of VCSNS.
The nearest dairy activity was still in the west sector,5.1 miles from VCSNS.
- 4. One change in closest residence resulted from the resident's move from the j east to the east southeast sector.
I 5. The two changes in closest gardens both resulted in garden locations further i away from VCSNS. j 6. There was no significant movement of critical receptors since the 1985
- census nor milking activity which resulted in identification of new locations j yielding calculated doses 20% greater than doses at currently sampled locations.
Upon completion of the census, dose calculations were performed using 1975 and 1986 meteorological data and source terms from the VCSNS Final Safety Analysis Report to determine the critical receptor (maximum exposed individual) for each sector around VCSNS. The results of these calculations are compiled in Table J-2. I i 4
APPENDIX J, TABLE J RESULTS OF THE 1986 CENSUS VERIFICATION, AUGUST 1986 Sector Miles Nearest Garden Miles Cattle Miles Goats Miles
; nce N Martin 3.8 Fuller 4.0 Robinson 0 3.3 NNE R. Crumblin 2.9 Crumblin 2.9 Robinson 0 3.3 NE Stone 2.1 Robinson 2 2.9 Stone 0 2.9 Stone 0 2.1 ENE Johnson 1.4 Willingham 1.5 E Martini 1.5 Pearson2 3.1 ESE Sanders 3 1.1 Martin 1.1 SE White 1.5 Summer 1.5 SSE Crumpton 2.5 Shealy 2.7 5 Pinner 3.8 Eargle 3.9 Yarborough 0 3.8 SSW Weber 3.2 Ariail 3.4 Miller 0 3.0 SW Davis 3.1 Nichols 3.3 Summer 0 2.5 WSW Hope 3.1 Summer 3.3 Livingston 0 1.9 W Amick 2.5 Smith 2.5 Livingston 0 2.1 WNW Palmer 2.7 Williams 4.5 Williams 4 0 4.5 i NW Wright 3.9 Wright 3.9 Cole 0 4.1 NNW J. March 2.9 F. March 3.0 F. March 0 3.0 F. March 0 3.0 l .
- 1. Change in closest residence.
- 2. Change in closest garden. !
- 3. Name change only.
- 4. Milking animal, but not milked.
l Appendix J, Table J2 - Critical Receptors in 1986 Census 1975 METEOROLOGICAL DATA 1986 METEOROLOGICAL DATA DISTANCE SECTOR NAME PATHWAY DOSE DOSE _X/Q D/Q . RATE X/Q D/Q RATE mR/yr mR/yr N J3 Robinson Beef (C) 20E47 9 5E 10 10E-01 2 0E-07 6 9E-10 7 6E-02 N 38 Martin Res 15E-07 7 0E-10 5 7E-03 15E -07 51 E-10 5 6E-03 N 40 F ulle r
- Res/ Gar 14E-07 6 2E-10 16E-01 13E-07 4 SE-10 12 E-01 NNE 29 Crumblan* RerGar 3 2E-07 1 SE-09 3 9E 01 2 SE-07 1 OE-09 2.7 E-01 j NNE 36 Robinson Res/ Gar, Beef 21 E-07 8 9E-10 3 4E-01(E) 16E-07 6 IE-10 2 SE-01(E)
NE 21 Stone Res 8eef 6 8E-07 3 6E-09 3 8E-01 8 OE-07 3 OE-09 3 3E-01 l NE 29 Robinson *(8) RerGar 8eef 3 4E-07 1. 7 E-09 61 E-01 4 OE-07 14E-09 5 2E-01 ENE 14 Johnson Res 14E-06 8 OE-09 5 4E-02 2 4E-06 8 9E-09 9 OE-02 ENE 15 Willing ha m
- Res/ Gar 12 E-06 6 8E-09 18E + 00 2 OE-06 7 SE-09 2 OE + 00 E 31 Pearson*(8) Res, Gar 2 4E-07 9 6E 10 2 SE-01 2 3E-07 8 2E-10 2 2E-01 E 15 Martin (A) Res 1 1 E -06 5 6E 09 4 2E42 12E-06 4 6E-09 4 5E-02 ESE 11 Sanders Res 2 2E-06 8 4E-09 8 3E-02 16E-06 6 OE-09 6 OE-02 ESE 1.1 Martin *(D) Res/ Gar 2 2E-06 8 4E-09 2.2E + 00 16E-06 6 OE-09 16E + 00 SE 15 White Res 16E-06 5 8E-09 6 OE-02 7.1 E-0 7 3 IE-09 2 7E-02 SE 15 Summer
- RevGar 16E-06 5 8E-09 16E + 00 7.1 E-07 31 E-09 8 2E-01
< SSE 25 Crumpton Res 3 SE-07 12 E-09 13E-02 1 1 E-06 7 3E-10 4 3E-03 SSE 27 $healy* RevGar 3 0E-07 10E-09 2 7E-01 9 5E-08 61 E-10 16E-01 5 38 Yarborough Beef (C) 18E-07 3 8E-10 4 SE-02 6 6E-08 3 9E-10 41E 02 i
5 38 Penner Res 1 BE-07 3 8E-10 6 6E-03 6 6E 08 3 9E 10 2 6E-03 5 39 Eargle* Res/ Gar 1 7E -07 3 7E-10 1 1 E-01 6 3E-08 3 7E-10 9 SE-02 SSW 32 Weber Res 2 3E-07 7 SE-10 8 6E-03 91 E-08 7 6E-10 3 6E-03 SSW 34 Ariail' Res/ Gar 2 OE-07 6 4E-10 1 7 E -01 8 OE-08 6 6E-10 1 7 E-01 55W 34 Miller Res, Beet 2 OE-07 6 4E-10 9 3E-2(F) 8 OE-08 6 6E-10 91 E-02(F) i SW 25 Summer Beef (C) 4 6E-07 19E-09 21E-01 2 OE-07 21E-09 2 2E-01 SW 31 Davis Res 2 9E-07 12E-09 1 1 E-02 13 E-07 1.3 E-09 5 3E-03 SW 33 N4hols' RevGar 2 6E-07 10E-09 2 7E-01 1 1 E -07 1 1E 09 2 8E-01 { SW 33 Miller Res 2 6E-07 1 OE-09 9 8E-03(J) 1 IE-07 1.1 E-09 4 SE-030) W5W 19 Livingston Beef (C) 6 4E-07 3 2E-09 3 4E-01 2 9E-07 3 OE-09 31 E-01 W5W 31 Hope Res 2 3E-07 10E -09 8 7E-03 9 5E-08 9 3E-10 3 9E-03 W5W 33 summer
- RevGar 2 OE-07 8 7E-10 2 3E-01(1) 8 3E-08 8 1 E -10 2 OE-01(l)
W 25 Amak Res 2 SE-07 1 1 E -09 9 SE-03 1 SE-07 9 6E-10 5 9E-03 l W 25 $mith HerGar 2 SE-07 1 1 E -09 2 9E 01 1 SE-07 9 6E 10 2 SE 01 W 27 Livingston Res/ Gar ' Beef (G) 2 2E-07 9 3E-10 4 2E-01(H) 1 3 E -0 7 8 OE-10 3 4E-01(H) WNW 27 Palmer Res 1 8 E-07 7 bE 10 6 8E 03 7 OE-08 4 1 E -10 2 7E-03 WNW 45 Williams' RerGar '8eef 6 6E-07 2 SE-10 9 2E-02 2 4E-08 13E-10 4 7E-02 NW 39 Wrig h t
- RerGar 1 1 E-07 4 6E-10 1 2 E -01 6 SE-08 2 8E-10 7 4E-02 NW 41 Cole Res< Beef 9 7E-08 4 1 E -10 4 5E 02 5 8E-08 2 5E 10 2 7E-02 RNW 29 J March Res 19E 07 1 1 E-09 7 4E-03 19E-07 7 6E 10 7 2E-03 NNW 30 F March
- Res/ Gar / Beef 18E-07 9 7E-10 3 5E 01 18E-0 7 7 OE 10 2 6E-01 NNW 30 F March HevGar/ Goat 1 8 E -07 9 7E 10 2 6E-01 18E 07 7 OE 10 19E-01 Oenutes Critetai 6eceptor for trie 5euvr (W Cattie assumea tu grare at ; i mues W
, (A) Change in Cosest Residence for the Sector (H) Assuming Livingston eats beef from his herd in the W5W, Livingston's (f rom 1985 Census) dose rate would be as follows (B) C hange in (losest garden $1 mR/y ('75 X'Q. D Q) 50 mRty ('86 X/Q, D.Q)
(C) Residence assumed in (alculations (1) Assuming Summer eats beef from his herd in the SW. Summer's dose rate (D) Manium esposed individual for the site would be as follows (E) Cattle assumed to graze at 3 3 miles NNE 42 mR/y ('75 x.Q, D'Q). 41 m R/y ('86 X,Q. D Q) (F) Cattle assumed to grare at 3 0 miles 55W 0) Assuming Maler eats beef from his herd in the 55W. Miller's dose rate would be as folicws. 10 trR>y ('75 UQ D 0) 09 mRey ('86 x Q. DC)
I APPENDIX K - RESULTS OF 1986 INTERNATIONAL ENVIRONMENTAL DOSIM ETRY INTERCOMPARISON Deh.vered Avera e of Radiation Ex re Laboratory Percent al Percent Source Results(mR)1 Difference Parti nts Difference Field Site No. 29.711.5 33.918.0 14.1 28.9 i 6.2 2.7 1 (Chester, N.J.) Field 5ite No. 10.410.5 10.913.9 4.8 10.1 4.5 2.9 2 (Sandy Hook, N.J.) Laboratory 17.210.9 17.616.4 2.3 16.213.4 5.8 (Cesium-137) l
- 1. Includes 5% uncertainty for fade correction.
I K-1 y-e ---i---- . - , , . -w. , . - * - - - - y- ,-,,----..w-- - - . - , -
r- l
/o c.rA Sb. 3G Electric & Gas Company Den A.
Co um 29218 Nuclear Opections sceso 4 ==um April 30, 1987 Dr. J. Nelson Grace Regional Administrator U. S. Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, N.W. Atlanta, Georgia 30323
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Radiological Environmental Monitoring Report
Dear Dr. Grace:
Please find attached South Carolina Electric and Gas Company's (SCE&G) Annual Radiological Environmental Monitoring Report as required by Regulatory Guide 4.8 and Sections 6.9.1.6 and 6.9.1.7 of the Virgil C. Summer Nuclear Station Technical Specifications. Also, requirements as specified by Section 4.12.3 of the Technical Specifications have been included in the report. If there are any questions, please call us at your convenience. Very truly yours,
. A. Nauman ;
DCB/ DAN:jez c: 0. W. Dixon, Jr./T. C. Nichols, Jr. w/ attachment E. C. Roberts W. A. Williams, Jr. Group Managers
- 0. S. Bradham W. R. Higgins J. W. Cox C. A. Price w/ attachment S. R. Hunt C. L. Ligon (NSRC) w/ attachment K. E. Nodland R. A. Stough G. O. Percival R. L. Prevatte J. B. Knotts, Jr. w/ attachment I&E Washington ANI Library NPCF File g(
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