ML20245L490
| ML20245L490 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/31/1988 |
| From: | Blue L, Bradham O, Hall G SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8905080056 | |
| Download: ML20245L490 (51) | |
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[ Virgil C. Summer Environmental Surveillance Laboratory Jenkinsville, South Carolina RADIOLOGICAL L ENVIRONMENTAL MONITORING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPERATING PERIOD JANUARY 1,1988 - DECEMBER 31,1988 APRIL 1989
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V. C. SUMMER NUCLEAR STATION SOUTH CAROUNA ELECTRIC AND GAS COMPANY l
Prepared by: Reviewed by:
1 Gregory G. Hall, Supervisor 'teldon A. Blue, Manager Radiological Analytical Services Corporate Health Physics and Environmental Programs ;
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' Executive Summary L 1. Results of the 1988 Land Use Census neither indicated significant movement of critical. .eceptors since the previous annual census, nor identified locations
-where'a. calculated dose exceeded limits specified in VCSNS Technical Specifications, Section 4.11.2.3.
- 2. There was no detection of radioactivity in environmental media attributed to gaseous effluent releases from VCSNS.
- 3. Activated corrosion products attributed to liquid effluent releases from VCSNS were detected in fish and sediment. Radiation dose to the general public attributed to this activity is a small fraction _of the observed variation in natural background radiation.
- 4. Detection of fission product activity in' environmental media is attributed to i :esidual fallout from the Chernobyl incident, atmospheric weapons testing and liquid effluent releases from VCSNS.
- 5. Results of the Radiological Environmental Monitoring Program substantiate the continuing adequacy of source control at VCSNS and conformance of,.
station operation to 10 CFR 50, Appendix I design goals.
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5-TABLE OF CONTENTS t
Pace i introduction - '1 f
Description of the Radiological Environmental Monitoring Program 2.
Results and Discussion 5 Conclusion' 45 -
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L . . . LIST OF FIGURES FIGURE
.,- Paae 1-1 Control Site Lrcations (50 mile radius around the Virgil C. Summer Nuclear Station) 9 12 Radiological Monitoring Program Local Indicator Sample Sites (5 mile radius around Virgil C. j Summer Nuclear Station) 10 1-3 Radiological Monitoring Program Local Indicator Sample Sites (1 mile radius around Virgil C. Summer i Nuclear Station) 11 s
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, f LIST OF TABLES TABLE Page 1 Monitoring Methods for Critical Radiation Exposure 2 Pathways 2 Results of the August 1988 Land Use Census 3 Verification 2a Critical Receptors in 1988 Based on FSAR/OLER 4 Projected Source Terms 3 Radiological Environmental Monitoring Program 6 Sampling Site Locations 4 Results of the 1988 EPA Intercomparison Program 12 5 Results of the 1988 Intracomparison Program 14 ,
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with VCSNS Count Room 6 Summary of the 1988Intercomparison Program 16 with SCDHEC 7 Results of the Environmental Dosimetry 17 Intercomparison Program with the NRC TLD Direct Radiation Monitoring Network l
8 Radiological Environmental Monitoring 18 Program Specifications '
9 Supplemental Radiological Environmental Monitoring 24 Program i 10 Radiological Environmental Monitoring Program 26 Summary 11 Radiological Environmental Monitoring Program 33 Preoperational(Baseline) Summary 12 Environmental Sampling Program Exceptions 40 13 1988 Activated Corrosion Produc t Activity in Fish 44 14 1988 Activated Corrosion Product Activity in Sediment 44 4
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. Introduction Virgil C. Summer Nuclear Station (VCSNS) utilizes a pressurized water reactor rated at 2775 MWt (900 MWe gross). The station is located adjacent to the Monticello Reservoir near Jenkinsville, South Carolina and approximately 26 miles northwest of Columbia. VCSNS achieved initial criticality on October 22, 1982, reached 50% power December 12,1982 and 100% power June 10,1983 following steam generator feedwater modifications. VCSNS completed its fourth fuel cycle on September 16,1988. Criticality for the fifth fuel cycle was achieved on December 27,1988 following a 102 day refueling and maintenance outage.
VCSNS 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 usod to pump water from Parr Reservoir to Monticello Reservoir.
Monticello Reservoir has a surface area of approximately 6800 acres and lies about 150 feet above Parr Reservoir whose full pool area is approximately 4400 acres. The pump-turbine units operate in the generating mode to meet peak system loads while Monticello Reservoir also provides condenser cooling water for VCSNS. Cooling water intake and discharge structures are separated by a ,
jetty to ensure adequate circulation within the reservoir.
VCSNS is located in Fairfield County which, along with Newberry County, makes up the principle area within a 10 mile radius of the plant. This area is mainly forest with only about 30% devoted to small farming activities principally producing small grains, feed crops and beef cattle. Significant portions of Lexington and Richland Counties are encompassed within the 20 mile radius of the plant and exhibit similar agricultural activities. Columbia, the state capital, is the only large city within the 50 mile radius of the plant. Small agricultural concerns are predominant, but makeup less than 50% of the land area. The 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 penstocks. Radioactive gaseous effluents from VCSNS are released from two i 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 Radiological Environmental Monitoring Program at VCSNS. This report summarizes the resJlts of the Radiological Environmental Monitoring Program conducted during 1988. Data trends, control / indicator and preoperational/
operational data intercomparisons and other data interpretations are presented.
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Description oj the Radiological Environmental Monitorino Program j The Radiological Environmental Monitoring Program is carried out in its l entirety by South Carolina Electric and Gas Company. The program has been designed to meet the following general commitments:
- 1. To analyze selected samples in important anticipated pathways for the qualification and quantification of radionuclides released to the environment surrounding )
VCSNS. I
- 2. To establish correlations between levels of environmental radioactivity and radioactive effluents from VCSNS operation.
The program utilizes the concepts of control / indicator and preoperational/
ooerationalintercomparisons in order to establish the adequacy of radioactivity scurce control and to realistically verify the assessment of environmental radioactivity levels and subsequent radiation dose to man.
Specific measurement, sampling and analysis methodology has been programmatically developed to sensitively monitor the pathways expected to s re;.esent the most significant source of radiation exposure to the public and the environment. Elements of the program monitor the impact of gaseous and liquid effluents released from VCSNS. Specific methods used in monitoring the pathways of these effluents which may lead to radiation exposure of the public, based on existing demography, are summarized in Table 1.
' "t Re ease Type 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 (In Sampling, Shoreline and Bottom immersion) gestion and Sediment Sampling DrinkhVater ~ Ground Water Sampling, Drinking (Ingestion) Water Sampling Table 1 - Monitoring Methods for Critical Radiation Exposure Pathways 2
. l Effluent dispersion characteristics, demography, hydrology, land use, anticipated source terms, and the critical paths specific to VCSNS have been considered in the selection of sample. media, sampling and analysis frequencies, sample locations and types of samn!es. These criteria were used to establish both the preoperational and operMional phases of the Radiological Environmental Monitoring Program. A census of land use, perhaps the most dynamic of the criteria,is performed within a 5 mile radius of VCSNS to verify the adequacy of the program. The results of the land use census performed in 1988 are included in Table 2. A verification of the critical receptor (maximum exposed individual) in each sector around VCSNS based on 1988 meteorological data, VCSNS Final Safety Analysis Report and VCSNS Operatino License Environmental Report source terms is included in Table 2a.
Nearest No.
Sector Residence Miles Nearest Garden Miles Cettle Milked Miles N Martin 3.8 Fuller 4.0 Robmson 0 3.3 NNE Crumblin 2.9 Crumblin (B) 2.9 Robinson 0 3.3 NE Stone 2.1 Robinson 2.9 Stone 0 2.1 ENE Johnson 1.4 Willingham 1.5 Martin 0 1.6 E Martin 1.5 Bank (B) 1.7 Boyd 0 1.7 ESE Martin 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 Cawley (B) 3.4 Miller 0 3.0 SW Davis 3.1 Nichols 3.3 Miller 0 2.8 ;
WSW Hope 3.1 Summer 3.3 Livingston 0 1.9 i
W Amick 2.5 Smith 2.5 Livingston 0 2.1 j
WNW Seeby(A) 2.6 Williams 4.5 Williams 0 4.5 NW Wnght 3.9 Cole 4.1 Cole 0 4.1 NNW March 2.9 March 3.0 March (C) 0 3.0 A. Change in closest residence B. Change in closest garden C. Cattle and goats not milked Table 2 - Results of the August 1988 Land Use Census Verification 3
r 1 1975 METEOROLOGICAL DATA 1988 METEOROLOGICAL DATA E
' SECTOR , NAME PATHWAY DOSE DOSE X/Q D/Q RATE X/Q D/Q RATE mrem /y mrem /y h 33 RONnson Beet (C) 2 0E -0 7 9 5E-10 1 0 E-01 3 5E-07 9 1 E-10 1 0 E -01 N 38 Ma rtin Res 1 SE -07 7 OE 10 5 7E 03 2 6E-07 6 6E-10 9 7E-03 N 40 F uller
- Res/ Gar 14E 07 6 2E-10 16E 01 2 4E-07 5 9E 10 1 7E -01 NNE 29 Crumbhn (8) RevGar 3 2E-07 15E-09 12E 02 3 9E-07 12E-09 3 3 E-01 NNE 36 R Robinson
- ReUGar Beef 21 E-07 8 9E 10 3 5E 01(E) 2 5E-07 7 2E 10 2 9E 01(E)
NE 21 Stone Res/8eef 6 BE-07 3 6E 09 3 BE 01 1 1 E -06 2 BE 09 3 2E 01 NE 29 J RMonson* Res/ Gar Beef 3 4E 07 1 7E-09 61E 01 5 SE-07 13E 09 5 OE 01 ENE 14 Johnson Res 1 4 E -06 8 OE-09 5 4E-02 2 SE-06 7 OE 09 9 3E 02 ENE 15 Withngha m
- Res, Gar 12 E-06 6 8E-09 1 BE + 00 21E 06 5 9E-09 16E + 00 ENE 16 R Marten Res/ Beet 11E 06 5 8E-09 6 2E 01 19E -06 5 IE 09 5 8 E -01 E 17 Bank * (8) Res/ Gar 8 4E 07 4 2E 09 1 1 E + 00 1 3 E-06 3 5E-09 9 7E 01 E 15 N Martin Res 1 1 E -06 5 6E 09 4 2E-02 1 7E-06 4 7E-09 6 3E -02 E 18 Boyd Res Beef 7 4E 07 3 6E-09 4 SE 01(M) 12E-06 3 OE-09 4 OE -01(m ESE 11 Jr Martin *(D) Res/Ga r 2 2E 06 8 4E 09 2 2E + 00 2 1 E-06 6 8E 09 19E + 00 !
SE 15 White Res 16E 06 5 8E-09 6 OE 02 6 9E 07 2 4E-09 2 6E-02 SE 15 Summer
- Res/ Gar 16E 06 5 BE-09 16E + 00 6 9E 07 2 4E 09 6 SE 01 SSE 25 Crumpton Res 3 5E-07 12 E-09 13 E-02 1 7E-07 6 I E 10 6 4E 03 SSE 27 Shealy ' Res/ Gar 3 OE 07 10E-09 2 7E 01 15 E-07 5 1 E -10 . 1 4 E -01 5 38 Yarborough Beef (C) 18E-07 3 BE 10 4 5E-02 91 E-08 3 4E 10 3 7E-02 5 38 Pinner Res 18E 07 3 8E 10 6 6E-03 91E 08 3 4E 10 3 4E 03 5 39 Eargle* Res/ Gar 17E 07 3 7E 10 1.1 E-01 8 6E-08 3 2E 10 8 6E 02 55W 32 Weoer Res 2 3E-07 7 5E 10 8 6E-03 16E-0 7 7 4E 10 61E 03 55W 34 Cd Sley*(B) Res/ Gar 2 OE-07 6 4E 10 1. 7E -01 14E-07 6 4E 10 17E 01 SSW 34 Miller Res, Beef 2 OE 07 6 4E 10 9 4E 02(F) 14E 07 6 4E 10 91 E -02(F)
SW 31 Davis Res 2 9E-07 12E 09 16E 07 1 1 E-02 11E 09 6 3E 03 SW 33 Nichols' Res/ Gar 2 6E-07 1 OE-09 2 7E-01 14E 07 9 SE-10 2 4E 01 1 SW 33 Miller Res 2 6E 07 10E 09 9 8E-03(J) 14E-07 9 5E-10 5 SE-03(1)
WSW 19 Livingston Beef (C) 6 4E-07 3 2E-09 3 4E-01 4 2E 07 2 BE-09 3 OE-01 WSW 31 Hope Res 2 3E-07 1 OE 09 8 7E-03 1 4 E-07 8 7E 10 5 5E 03 WSW 33 Summer
W 25 Amick Res 2 SE 07 1 1 E-09 95E43 2 4E-07 9 2E 10 91 E-03 W 25 Smith Res/ Gar 2 5E 07 1 1 E-09 2 9E 01 2 4E-07 9 2E-10 2 S E -01 W 27 Livingston
WNW 26 Seeby(A) Res 2 OE -0 7 8 4E-10 7 6E 03 18E-0 7 5 6E-10 6 7E 03 WNW A5 Wilha ms* Res/ Gar / Bee f 6 6E-08 2 SE 10 9 2E-02 5 BE 08 16E 10 6 OE-02 NW 39 Wright Res 1 1 E -07 4 6E-10 4 2E 03 1 SE 07 3 SE 10 5 6E-03 NW 41 Cole' Res/ Gar /8eef 9 2E-08 4 OE-10 1 SE-01 13 E-07 31E 10 12E-01 NNW 29 J W rch Res 19E-07 1 1 E-09 7 4E 03 4 6E-07 11E 09 1 7 E-02 I NNW 30 F March' Res/ Gar / Beef 1 8 E-07 9 7E-10 3 5 E -01 4 3E 07 1 OE-09 3 9E-01 Denotes Critical Receptor for the Sector. (G) Cattle assumed to graze at 21 miles W.
(A) Change in Closest Residence for the Sector (H) Cattle assumed to graze at 1.7 miles E.
(from 1987 Census). (1) Assuming Livingston eats beef from his herd in the WSW, (Q) Change in closest garden. Uvingston's dose rate would be as follows:
(C) Residence assumed in calculations. .56 mrem /y (*75 X/Q, D/Q), .48 mRern/y ('88 X/Q D/Q).
(D) Ma nim um exposed individual for the site . (J) Assuming Miller eats beef from his herd in the SSW, Miller's dose rate (E) Cattle assumed to grare at 3.3 miles NNE. would be as follows: .096 mrem /y ('75 X/Q, D/Q), .091 mRemfy ('88 X/Q, (F) Cattle assumed to graze at 3 0 miles $5W. D/Q)
Table 2a - Critical Receptors in 1988 Based on FSAR/OLER Projected Source Terms 4
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In addition to preoperational/ operational data intercomparisons, control /
indicator data intercomparisons are utilized to assess the probability that any observed abnormal measurement of radioactivity concentration is due to random or regional fluctuations rather than to a true increase in local environmental radioactivity concentration. Monitoring sites indicative of plant operating condi- l tions are generally located within a 5 mile radius of the plant as shown in taw .,
and Figures 1-2 and 1-3. Monitoring sites at distances greater than 10 m!!es from the plant are shown in Figure 1-1 and are indicative of conditions away from plant influence.
Valuable information is gained through multiple types of sampling and measurements at specific locations. Several multiple sampling combinations are in use around the VCSNS. All air sampling locations are also environmental dosimetry monitoring locations. At these points airborne plant effluents are monitored for gamma immersion dose (noble gases), airborne particulate and radiciodine. Three of these locations have additional complementary sampling / measurement pathways for monitoring plant effluents. Sampling locations 6 (1.0 mi ESE) and 8 (1.5 mi ENE) have broadlef vegetation gardens for monitoring the gaseous effluent deposition and ingestion pathway in the two sectors having the highest deposition coefficients (D/Q). Sampling location 18 (16.5 mi S) also has a broadleaf vegetation garden for monitoring the gaseous effluent deposition and ingestion pathway at a control location.
1 Liquid effluents are monitored through three pathways (fish, bottom sediment and surface water) at the three most probable affected bodies of water arou,id 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 control location for liquid effluent comparisons is at Site 22, Neal Shoals (30.0 mi NNW) on the Broad River.
The Radiological Environmental Monitoring Program participated in four laboratory intercomparison programs during 1988. Results of the 1988 EPA Intercomparison Program are included in Table 4. Results of an intracomparison program with the count room at VCSNS are included in Table 5. Results of an intercomparison program with SCDHEC outlined in Table 6 are reported by SCDHEC.
Results of an environmental dosimetry intercomparison with the NRC are included in Table 7. The results of each of these four quality control checks of the Radiological Environmental Monitoring Program verify the technical credibility of analytical data generated and reported by the program.
The program, as it has evolved since the preoperational(baseline) monitoring program, incorporating all the elements of the VCSNS Technical Specifications and additional special studies are detailed in Tables 8 and 9.
Results and Discussion The results of the Radiological Environmental Monitoring Program for 1988 are summarized in Table 10. For comparative purposes preoperational data is i summarized in Table 11. Certain samples were not collected during 1988 and are not included in the annual summary. A listing of these program exceptions and their respective causes are included in Table 12. Despite the program exceptions, the Radiological Environmental Monitoring Program was able to attain a completion rate of 99E Detailed analysis of the impact of these omissions verified that program quality has not been affected and there were no violations of l Technical Specification requirements.
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Distance t No. Description Direct,on2 Wles) i Sample Type (s)3 1 Borrow Pit 1.2 182.0 5 DM 2 Transmission Line 1.2 225.0 5W AP,RI DM 3 Firing Range 1.2 270.0 W DM 4 Fairfield Hydro 1.2 289.5 WNW DM S Transmission Line Entrance 0.9 145.5 SE AP,RI DM 6 Env. Lab Garden 1.0 104.0 ESE AP.RI,DM,G R,G A 7 Monticello Peninsula 1.2 83.0 E DM 'j 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 No.2 2.5 25.5 NNE AP,RI,D M i 11 Residence 3.3 8.0 N DM 12 Old Hwy 99 42 349.0 N DM 13 North Dam 2.9 334 0 NNW AP DM {
14 Da;ry 63 270 0 W AP,RI,D M,M K,G R 15 Part Village 2.5 204.0 SSW DM '
16 Dairy 28.0 281.0 W DM,GW,MK GR 17 Columbia Water Works 24.7 144.0 5 E AP,RI,DM,5W,0W,85 18 Residence / Pine Island Club 16.5 165.0 5 DM,5W,G A 19 Residence /Little 5aluda f
17.9 207.0 55W DM 20 Residence /Whitmire 22.0 310.0 NW. DM 21 Parr Reservior 2.7 199.5 55W SW,FH,85 22 Neal Shoals 30.0 343.0 NNW ' 5W,FH,85 23 Discharge Canal (Mont. Res.) 0.5 104.5 ESE SW,FH,85 24 Recreation Lake 5.5 2.0 N SW,FH,85 25 Fatrfield Pumped Storage (Monticello Res.) 0.9 302.0 WNW SW 26 On Site Well (P2) 460 Ft 270.0 W GW 27 On Site Well (PS) 510 Ft 180.0 5 GW 28 Nuclear Training Center (EOF) 2.4 168.0 55E DW 29 Trans. Line WSW of VCSNS 0.9 248 0 WSW DM 30 Oak Tree North of Borrow Pit 1.0 197.0 55W DM 31 McCrorey Liston School 5.8 12.5 NNE DQ 32 Dirt Rd off Rd 205 4.5 25.0 NNE DQ 33 Rd 48 near Hwy 213 4.2 70.0 ENE DQ ,
34 Rd 419 North of Hwy 60 4.8 112.5 ESE DQ f 35 Unnamed Circle Road off Hwy 215 4.8 137.5 SE DQ )
36 Woods Behind Jenk. Post Of fice 3.1 151.5 SSE DQ {
37 Residence 4.9 305.5 NW DQ 38 FP5F Trailrace 1.3 280.0 W B5 39 LMWTF 14.0 168.0 55E DW 40 No 5 ampler 41 End of Catwalk 3.9 185.0 5 DO 42 Store 39 199.0 55VV DQ 43 Hwy 176 and Rd 435 52 236.0 SW DO Table 3 - Sampling Site Locations 6
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. 5e Description Ds n es Direction 2 Sample Type (s)3
, 44 Rd 28 at Cannon's Creek 2.9 255.5 W5W DQ 45 Rd 33 at Pomaria 5.9 253.0 WSW DQ 46 Rd 28 at Heller's Creek 3.7 292.0 WNW DQ 47 Fairfield Taitrace 1.0 316.0 NW DQ 48 Cemetary 2.3 318.5 NW DQ 49 Northyd 383 4.0 332.5 NNW DQ 50 New Fjd 99 (West Shore) 5.5 1.0 N DQ 51 New Rd 99 (East Shore) 5.5 5.0 N DQ
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52 Monticello(Rd 11) 3.9 14.0 NNE DQ 53 Rd 359 3.0 l
48.0 N E DO
-- 54 Jenkinsville School 1.7 73.0 ENE DO 55 St. Barnabas Church 2.8 94.0 E DQ 56 Old Jenkinsville Diner 2.0 144.0 SE DQ 57 Residence / Highway 213 and 215 2.7 146.0 SE DQ 58 Residence 2.5 158 0 55E DQ 59 Nuclear T aining Center (EOF) 2.4 168.0 SSE DQ,AP 60 Rd 98 near Rd 28 3.5 2 75.0 W DQ 61 Switchyard, SE Entrart.e to Plant 0.1 180.0 5 DM 62 East of Training Bldg 0.13 220.0 SW DM 63 East of Daniel's Office 0.17 270.0 W DM 64 Riprap W of Intake 0.13 338.5 NNW D M ,85 65 Guard Tower 0.13 22.5 NNE D M ,85 66 Jetty 0.6 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 0.0 N DM 71 Temperature Buoy on Monticello Res. 5.4 3.0 N DM 72 Yard Drain Outf all 0.4 140.0 SE SW,85 73 Yard Drain Outfall 0.4 270.0 W SW,B5 74 Yard Drain Outf all 0.5 246.0 WSW SW,85 80 Congaree River 30.2 147.0 55E B5 81 Congaree River 30.1 147.0 SS E B5 82 Congaree River 30.0 147.0 55E B5 83 Congaree River 28 5 147.0 55 E B5 84 Congaree River 54.2 135.0 SE B5 85 Congaree River 53.8 135.0 5E B5 86 Congaree River 54.0 135.0 SE B5 87 Lake Marion 72.0 138.0 5E B5 88 Lake Marion 72.0 138.0 SE B5 89 Lake Marion 72.0 138.0 SE B5 e
Table 3 - Sampling Site Locations (continued) >
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- 1. Distance given is the distance between the site location and the center of the VCSNS reactor containment building. j i
- 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 3 R1 = Air Radioiodine MK = Milk DM = Monthly TLD GR = Grass (Forage)
DQ = QuarterlyTLD GA = Garden SW = Surface Water FH = Fish GW = Ground Water BS = Bottom Sediment i
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Table 3 - Sampling Site Locations (continued) ,
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. (Measurement Unf) ( lo) ( f 3 g) ment
. Air filter (pCi/ filter) 3/88 beta 50 (5) 60(6) Yes l Cs-137 16(5) 18(1) Yes 8/88 beta 29(5) 31(1) Yes Cs-137 12 (5) 14(1) Yes Gamma in Water (pCi/ liter) 2/88 Cr-51 Not tested Co-60 69(5) 73(2) Yes 2n-65 94(9) 99(3) Yes Ru-106 105(10) 102(8) Yes Cs-134 64(5) 63 (1) Yes Cs-137 94(5) 98(2) Yes 6/88 Cr-51 302 (30) 300(12) Yes Co-60 15(5) 16(0) Yes 2n-65 101(10) 104 (1) Yes Ru-106 195(20) 198(8) Yes' Cs-134 20(5) 20(2) Yes Cs-137 25(5) 26(1) Yes 10/88 Cr-51 251(25) 261(16) Yes Co-60 25(5) 25(1) Yes 2n-65 151(15) 151 (8) Yes Ru-106 152(15) 140(4) Yes Cs-134 25(5) 24(2) Yes Cs-137 15(5) 16(1) Yes Gross Beta in Water (pCi/ liter) 1/88 beta 8(5) 7(1) Yes 3/88 beta 13(5) 12(1) Yes 5/88 beta 11(5) 11(2) Yes 7/88 beta 4 (5) 7 (3) Yes 9/88 beta 10(5) 9 (0) Yes 11/88 beta 9 (5) 8 (1) Yes Table 4 - Results of 1988 EPA Intercomparison Program 12
Lab toy Comparison Study Date Nuclide EPA Value pesul Agree-(Measurement Un t) (1 10) ment (f $g) l lodine in Water l (pCi/ liter) 4/88 l-131 8 (1) 9 (1) Yes l 8/88 l-131 76(8) 76(4) Yes 12/88 l-131 115(12) 115(11) Yes Laborator (pCi/ liter) y Blind 4/88 beta 57(5) 46(2) Yes Co-60 50(5) 51 (2) Yes Cs-134 7 (5) 7 (1) Yes Cs-137 7 (5) 7 (1) Yes 10/88 beta 54(5) 47(2) Yes Co-60 Not tested Cs-134 15(5) 15(0) Yes Cs-137 15(5) 16(2) Yes ,
Radionuclides in Milk (pCi/ liter) 2/88 l-131 4 (1) 4 (0) Yes l 6/88 l-131 94(9) 103(2) Yes Cs-137 51 (5) 55(1) Yes 10/88 l-131 91(9) 93(4) Yes Cs-137 50(5) 51(1) Yes Tritium in Water (pCi/ liter) 2/88 H-3 3327(362) 3269(336) Yes 6/88 H-3 5565(557) 5596(129) Yes 10/88 H-3 2316(350) 2374(67) Yes Radionuclides in Food (pCi/kg) 1/88 1-131 102(10) 106(2) Yes Cs-137 91(5) 93(1) Yes 7/88 l-131 107(11) 114 (5) Yes Cs-137 49(5) 50(2) Yes ,
Table 4 - Results of 1988 EPA Intercomparison Program (continued) 13
, 6 l
.. Comparison Stud Laboratory VCSNS Count Date Nuclide Agree-(Measurement Un[t) Results1 ment Re u s1 1 li Gas Sample 3/88 Ar-41 4.06 E-4 3.56E-4 Yes (pCi/ml) Kr-85 8.17E-3 7.34E-3 Yes i Kr-85m 6.82E 6.78 E-3 Yes )
KR-87 1.13E 3 1.32 E-3 Yes l Kr-88 7.01 E-3 7.65 E-3 Yes j Xe 131m N/O 1.22 E-3 N/A l Xe-133 2.81 E- 1 2.19 E-1 Yes l Xe-133m 5.11 E-3 5.09E-3 Yes Xe-135 6.62 E-2 6.83 E-2 Yes Waste Monitor Tank 5/88 H-3 (distilled) 1.37E 1 1.32 E-1 Yes ,
Composite (pCi/ml)
{
H-3 (undistilled) 1.44 E-1 1.35 E-1 Yes NRC Liquid (pCi/ml) 6/88 H-3 (distilled) 1.81 E-5 1.71 E-5 Yes Gross Beta (pCi/ml) 6/88 N/A 2.42 E-3 2.70 E-3 Yes Gross Alpha 6/88 N/A 2.53 E-3 1.40 E-3 No2 (pCi/ml)
Charcoal Cannister 6/88 l-131 3.59E-1 3.20E-1 Yes (pCi/ml)
Gas Sample (pCi/ml) 6/88 Xe-133 7.47E0 7.39E0 Yes Kr-85 7.10E + 1 7.76E + 1 Yes ;
Xe-127 1.51 E0 1.49E0 Yes '
Waste Monitor Tank 8/88 H-3(Beckman 1.17 E-1 1.13 E-1 Yes Composite (pCi/ml) distilled)
H-3(Beckman 1.23 E-1 1.13 E- 1 Yes undistilled)
H-3(Packard 1.22 E-1 1.13 E-1 Yes distilled)
H-3(Packard 1.29 E- 1 1.13 E-1 Yes undistilled) i Gross Beta (pCi/ml) 9/88 N/A 1.01 E-3 1.09E-3 Yes Gross Alpha (pCi/ml) 9/88 N/A 5.82 E-5 8.57E-5 No2 Tritium (pCi/ml) 9/88 H-3 1.00E-3 1.10 E-3 Yes Table 5 - Results of 1988 Intracomparison Program with VCSNS Ccunt Room i
14
Comparison Study Laboratory VCSNS Count Date Nuclide Agree-(Measurement Unit) Results1 ment Results1 Gamma Isotopic Liquid 11/88 Na-22 1.82 E-4 1.97E 4 Yes
~
(pCi/ml) Cr-51 1.92 E-2 1.94E-2 Yes ,
Mn-54 2.06E 3 2.00E-3 Yes Co-57 1.67E 5 1.43 E-5 Yes Co 58 2.99 E-3 3.00E-3 Yes Fe-59 1.00E 2 9.81E 3 Yes i Co-60 1.05E-2 1.04E-2 Yes 2n 65 1.04E-2 1.01 E-2 Yes !
Cs-134 7.09E-3 7.13 E-3 Yes Cs-137 3.76E-3 3.62 E-3 Yes Ce 141 5.38 E-3 5.23E-3 Yes Ce-144 9.72E-3 9.37E-3 Yes Pr-144 8.99 E-3 8.18 E-3 Yes Silver Zeolite Cannister 12/88 l131 2.88E-1 2.38E-1 Yes (pCi/ml) ,
l Gas Sample (pCi/ml) 12/88 Xe-133 8.55E0 7.65E0 Yes Kr-85 9.08E + 1 8.38E + 1 Yes t
.1. N/O = not observed i
- 2. Differences limited to gross alpha determination which is not required by environ- '
mental technical specification. Corrective action is being taken to improve performance.
Table 5 - Results of 1988 Intracomparison Program with VCSNS Count Room 15
Pathway (Units) Sam e goc n Frequency Nuclide1 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 e 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 i
1.
Intercomparison results were not yet available for publication in this report.
Results will be reported by SCDHEC.
]
I Table 6 - Summary of 1988 Intercomparison Program with South Carolina Department of Health and Environmental Controls I
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Sa Media t ,c t n Cause for Exception (Wee No.)
Air ~6 October (40) Incomplete samples attributed to air sampler power outages
.10 January (4) or malfunctions September (39) {;
14 January (1)
IV'lk 16 April (10) Closing of control dairy Grass 6 January Seasonal Unavailability February November i' December 14 January Seasonal Unavailability -
February June 16 June Seasonal Unavailability Broadleaf Vegetation 6 March Seasonal Unavailability j April 1 l
]
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18- April Seasonal Unavailability Fish (bottom feeders) 24 October Seasonal Unavailability Table 12 - 1988 Environmental Sampling Program Exceptions i 40
r Airborne gross beta activity measured in air particulate samples collected at indicator locations around VCSNS were consistent with preoperational levels and comparable to operational control levels. Mean preoperational control and indicator levels were 2.9E-2 and 3.0E-2 pCi/m3, respectively. Mean indicator and control location measurements during 1988 were 2.2E-2 and 2.3E-2 pCi/m3, respectively. The highest site specific mean activity was measured at indicator location no.14 (Dairy, 6.3 mi, W) to be 2.4E-2 pCi/m3 The results indicate that operation of VCSNS has not resulted in detectable increases of airborne gross beta activity in the environment.
Gamma spectroscopy measurements of air particulate samples and activated charcoal cartridges support the gross beta activity trend. Only natural background activities of Be-7, Ra-226 and K-40 were detected. Minimum detectable activity (MDA) levels for C:-134, Cs-137 and 1-131 were 2.1E-3, 2.2E-3 and 2.7E-2 pCi/m3, respectively. The results agree with gaseous effluent release data reported in the 1988 Semiannual Effluent and Waste Disposal Reports for VCSNS. Only 8.8E-3 and 3.8E-3 Ci of particulate and iodine activities were released, respectively. These activity levels are not discernable in environmental media upon consideration of dispersion and dilution factors experienced during the releases. ;
Environmental dosimetry measurements during 1988 did not differ significantly from preoperational measurements over the same seasonal time-periods. Indicator and control dosimetry measurements also showed no appreciable differences during 1988. The lowest mean exposure rate of 6.410.5 pR/hr was observed at sampling location no. 43 near Pomaria. Sampling location no. 55 at St.
Barnabas Church near Jenkinsville (2.8 mi, E) was the indicator location showing the highest mean exposure rate of 14.0!0.6 pR/hr. This value compares favorably with the mean exposure rate of 13.6i2.2 pR/hr measured during the preoperational period and confirms the long-term stability of background levels measured at this monitoring location. Gaseous effluent release data reported for 1988 indicated a total of 3.3E + 2 Ci of fission and activation gases released from VCSNS. An extensive search of environmental dosimetry data and meteorological data during the release periods indicated no evidence of detectable activity attributable to the releases with only natural background variations evidenced.
Gamma spectroscopy measurements of surface water samples did not indicate the presence of activated corrosion and most fission products above the respective MDA's. All MDA's were less than the required respective LLD's. Liquid effluent release data reported for 1988 in the Semiannual Effluent and Waste Disposal Reports indicated a total of 7.5E-1 Ci of measureable fission and activated corrosion product activity was released from VCSNS; a level not discernable in environrnental media based upon consideration of dilution factors experienced during the releases and the detection limits of analytical methods.
Tritium analyses of surface water samples during 1988 yielded results which were not noticeably different from preoperational data. All but 5 of ' indicator tritium activity measurements were less than the mean calculated l\ .. salue of 4.4E + 2 pCi/ liter. The maximum indicator tritium activity of 6.0E + 2 pCi/ liter was measured in Parr Reservoir. Activity levels measured at the indicator locations are within the normal background variation for environmental tritium and consistent with the preoperational mean of 1.4E + 3 pCi/ liter. Total tritium released in liquid effluents during 1988 was reported to be 7.6E + 2 Ci; a level not discernable in environmental media upon consideration of dilution factors experienced during the releases and the detection limitations of analytical equipment.
41
t d
. Gamma spectroscopy measurements of ground water samples did not indicate the presence of activated corrosion or fission products above the MDA's for the respective radionuclides. All MDA's were less than the respective required LLD's. High background levels of Pb-214 and Bi-214, daughters of Ra-226, were again detected at control sampling location no.16 (28 mi, W). The presence of these radionuclides is attributed to the uranium found in the large amount of granite in this area of South Carolina. The radionuclides Pb-214 and Bi-214 are major gamma emitting daughters in the uranium series decay scheme produced through the decay of dissolved Rn-222 gas in the ground water. No evidence of radioactivity from VCSNS operation was detected.
Tritium analyses of ground water samples during 1988 yielded results which were less than the mean calculated MDA ef 4.3E + 2 pCi/ liter.
Gamma spectroscopy measurements of drinking water samples collected from the Jenkinsville and Columbia water supplies did not indicate the presence of activated corrosion or fission product activity above the MDA's of the respective radionuclides. The radionuclides Ra-225, 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 uranium associated with the aquifer supplying the Jenkinsville water system.
Drinking water tritium analyses, in all but three cases, showed no concentrations in excess of the mean calculated MDA for the indicator locations. An average detected activity of 5.2E + 2 pCi/ liter was found in Colurnbia drinking water.
This value is consistent with the preoperational mean activity of 7.8E + 2 pCi/ liter.
The MDA fu r tritium in drinking water was 4.3E + 2 pCi/ liter.
l Gamma spectroscopy measurements of milk samples collected in 1988 were l not significantly different from those observed during the preoperational program.
Naturally occurring K-40, Ra-226 and Cs-137 attributed to fallout was detected at both sampling locations at concentrations similar to those measured during the preoperational period. There were no identified radionuclides in milk attributed to VCSNS operation.
Gamma spectroscopy measurements of grass (forage) samples collected in 1988 indicated t 7e presence of Be-7 snd K-40 in all samples. The naturally occurring radionuclides Be-7 and K-40 were detected at leveis similar to those found during the preoperational program and in 1988 control data. There was no indication of the presence of any radionuclides 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 1988.
Broadleaf vegetation collected from gardens at location no's. 6, 8 and 18 were the principal food products analyzed during 1988. Gamma spectroscopy measurements revealed Cs-137 at an average concentration of 6.1E0 pCi/kg in two 42
e e d I samples collected at a control location. Naturally occurring contributions from Ra-
. 226, K-40, Ac 228 and Be-7 were also measured. All radionuclides measurements are comparable to and consistent with the results obtained during the preoperational program. Cesium-137 was detected at control and indicator locations during the preoperationalperiod. 1 Other vegetation sampled in 1988 included squash, corn, tomatoes and !
radish representing the non-leafy vegetation group. Naturally occurring K-40 was !
observed in all samples at concentrations consistent with those observed during the '
preoperational period. Detectable levels of Cs-137 were measured in squash and tomatoes collected from indicator and control gardens at levels of 6 0 and 7.5 pCi/kg, respectively. The levels of Cs-137 were consistent with preoperational data and attributed to residual fallout from atmospheric weapons testing and the 1986 Chernobylincident.
l Fish species sampled at three indicator and one control location included i bass, bream, shad, catfish and carp. Cesium-137 was detected in 29 of 31 samples collected at all four sampling locations and in all five species. The highest mean Cs- i 137 concentration of 2.2E + 1 pCi/kg was detected in bass. Cesium-134 was detected l in 16 of 31 samples and was limited to samples collected at all three indicator !
locations. The highest mean Cs-134 concentration of 1.4E + 1 pCi/kg was found in !
shad. Detectable levels of Co-58 and Co-60 were measured in shad and only in-samples collected from Parr Reservoir. The highest levels of Co-58 and Co-60 were !
1.5E + 1 and 8.2E0 pCi/kg, respectively, measured in samples collected in October, 1 1988. The levels of Cs-137 in both control and indicator locations were consistent with preoperational levels and are attributed to residual fallout from atrnospheric l wea aons testing and the 1986 Chernobyl incident. The presence of Cs-134 is attriauted to both residual fallout from the 1986 Chernobyl incident and, to some extent, liquid effluent releases during 1988 which included a total of 1,0E-1 Ci of Cs-134. Cesium-134 attributed to liquid effluent releases from VCSNS would be limited to Parr and Monticello Reservoirs. The detection of Co-58 and Co-60 in Parr Reservoir in the fall of 1988 is attributed to liquid effluent releases of activated corrosion products during the refueling and maintenance outage as the semiannual effluent release reports indicate. The activity of Co 58 and Co-60 released prior to and during the collection period was 2.3E-1 and 7.2E 2 Ci, respectively.
Radiation doses to man, corresponding to the mean concentrations of activated corrosion and fission product activity in fish, were calculated using Regulatory Guide 1.109 methodology. The results are included in Table 13.
Gamma spectroscopy measurements of sediment samples collected during 1988 also indicated the presence of activated corrosion and fission product activity.
Cesium-137 was detected in sediment from all indicator and control locations.
Cobalt-60 and Cs-134 activity was limited to Monticello and Parr Reservoirs. Cobalt-58 and Mn-54 activity was limited to Parr Reservoir. The highest mean concentrations, observed in Parr Reservoir, were 2.7E + 1,2.8E + 1,1.6E + 2,3.4E + 1 ;
and 2.5E + 2 pCi/kg for Mn-54, Co-58, Co-60, Cs-134 and Cs-137, respectively.
Naturally occurring K-40 was ubiquitous because of the concentration of organic matter in the sediment. Potassium 40 activity was consistent with preoperational and control measurements. Naturally occurring U-235 was also detected in sediment collected at all sampling locations at levels consistent with preoperational measurements. Cesium-137 concentrations were consistent with preoperational and control measurements and concentrations expected due to residual fallout from atmospheric weapons testing and Chernobyl. Cesium-134 activity limited to I
43
_ _ - - - - - _ - - - - )
. e ,
t 4 Parr and Monticello Reservoirs may be attributed to a combination of fallout from atmospheric weapons testing and Chernobyl and liquid effluent releases from VCSNS. Activated corrosion product activity detected in Parr and Monticello Reservoirs is attributed to liquid effluent releases from VCSNS. The relatively low activated corrosion product activity in Monticello Reservoir is attributed to the injection of the liquid waste stream directly into the penstocks during FPSF's generating mode and subsequent operation of the reversible pump-turbine units during periods of off-peak powerdemand.
Activity (pCi/kg) Corresponding Calculated Location Radionuclides Annual Total Body Deep Maximum Mean Dose Equivalent (mrem)
Parr Reservoir Co-58 1.5E + 1 1.5E + 1 5.1E-4 Co-60 8.2 E0 8.2 E0 6.7 E-4 Total 1.2 E-3 Table 13 - 1988 Activated Corrosion Product Activity in Fish I
Radiation doses to man, corresponding to the concentrations of activated corrosion product activity in sediment, were calculated using Regulatory Guide 1.109 methodology. A 400 hr/ year exposure to shoreline sediment containing mean detected concentrations of Mn-54, Co-58 and Co-60 was assumed. The results are included in Table 14.
Corresponding Calculated Annual Dose Location Radionuclides Activity (pCi/kg) Equivalent (mrem)
Maximum Mean Shallow Deep Monticello Co-60 1.2 E + 2 9.6E + 1 3.1 E-2 2.6 E-2 Reservoir Total 3.1 E-2 2.6E-2 Parr Reservoir Mn-54 2.7E + 1 2.7E + 1 2.5 E-3 3.0E-3 Co-58 2.8E + 1 2.3E + 1 3.0E-3 2.6E-3 Co-60 1.8E + 2 1.6E + 2 5.0 E-2 4.5E-2 Total 5.6E-2 5.1 E-2 Table 14 - 1988 Activated Corrosion Product Activity in Sediment 44
)
i s
i Conclusion 4
The BEIR Committee and the VCSNS Final Environmental Statement (NUREG-0719) both suggest that the conservatism inherent in the radiation exposure limits and calculated doses to man is also applicable to other biota. The calculated dose equivalent to man attributed to Mn-54, Co-58 and Co 60 in fish and sediment is a highly conservative estimate. The absence of any discernable ecological impact on biota substantiates the fact that species population stability has been unaffected by the activated corrosion product activity released from VCSNS. The absence of any impact is anticipated since the concentrations were much less than acceptable limits !
during 1988 and since most biotic species are not as radiosensitive as man.
Based on the data and the interpretations and conclusions discussed, the presence of activated corrosion product activity in fish from Parr Reservoir and sediment from Parr and Monticello Reservoir are environmental indicators which can be attributed to operation of VCSNS. The presence of fission product activity is attributed to residual fallout from the 1986 Chernobyl incident, atmospheric weapons testing, and to some extent, operation of VCSNS. The results of the Radiological Environmental Monitoring Program support the results reported in the Semiannual Effluent and Waste Disposal Reports for VCSNS during 1988. The calculated potential radiation dose to the public attributed only to activated corrosion product activity in Broad River media is 5.2E-2 mrem. The calculated _
potential radiation dose to the public attributed to Cs-134 activity in Broad River media is 4.2E-2 mrem. If it is assumed that all the Cs-134 activity in Broad River media is attributed to operation of VCSNS, then these figures compare favorably to the 2.2E 1 mrem dose reported in the 1988 Semiannual Efiluent and Waste Disposal Reports and are a small fraction of observed variations in local natural background.
These insignificant doses will not result in observable effects on the ecosystem or the public. The results of the Radiological Environmental Monitoring Program therefore substantiate the continuing adequacy of source control at Virgil C.
Summer Nuclear Station and conformance of station operation to 10 CFR 50, Appendix I design goals.
l f
45 i
o',.:,
o om? Br:dhim Sigth Carolins Etsctric & G:s Compiny gafjf"fo,sc29065 Nuclear Opeiations S- SCE&G 9
April 26, 1989 g_ . o scar f
Mr. S. D. Ebneter-Regional Administrator U. S. Nuclear Regulatory Commission.
Region II, Suite 2900 101 Marietta Street, N.W.
Atlanta, Georgia 30323 b
Subject:
Virgif(f Cy $ymmer Nuclear Station DocketNp.50/395 Operating Licensing No. NPF-12 Radiological Environmental Monitoring Report
Dear Mr. Ebneter:
s Enclosed is the South Carolina Electric & Gas Company (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 i Specifications. Also,. requirements as specified by Section 4.12.3 of the Technical Specifications have been included in the report l
If there are any questions, please call us '.t:your convenience.
Very truly yours, l
- 0. S. Bradham CJM/0SB: led Enclosure c: D. A.Nauman/0. W. Dixon, Jr./T. C. Nichols, Jr.
E. C. Roberts W. A. Williams, Jr. K. E. Nodland .
General Managers G. O. Percival !
L. A. Blue R. L. Prevatte R. B. Clary J. B. Knotts, Jr. 4 J. R. Proper Document Management Branch C. A. Price /R. M. Campbell ANI Library .
K. E. Nodland NSRC ]
J. C. Snelson NPCF i J. W. Cox RTS (RG 880009)
S. R. Hunt File (818.02-2)
' I
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