ML20153B640
| ML20153B640 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/31/1987 |
| From: | Blue L, Hall G, Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8805060048 | |
| Download: ML20153B640 (50) | |
Text
._.
3.-
-- Virgil C. Summer Environmental Surveillance Laboratory Jenkinsville, South Carolina l
RADIOLOGICAL ENVIRONM ENTAL MONITORING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPER ATING PERIOD JANUARY 1,1987 - DECEMBER 31,1987 APRIL 1988 M
\\w V. C. S'UMMER NUCLEAR STATION SOUTH CAROLINA ELECTRIC AND GAS COMPANY Prepared by:
Reviewed by:
d Gregory G. Hall, Supervisor Leldon A. Blue, Manager Radiological Analytical Services Corporate Health Physics and Environmental Programs K
so 35
3 s l
l l
Executive Summary 1.
Results of the 1987 Land Use Census neitherindicated significant movement of critical receptors 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.
4.
Detection of fission product activity in environmental media is attributed to residual fallout from the Chernobyl incident and atmospheric weapons testing.
5.
Results of the Radiological Environmental Mo'nitoring Program substantiate the continuing adequacy of source control at VCSNS and conformance of station operation to 10 CFR 50, Appendix I design goals.
3. '.-
TABLE OF CONTENTS Pace Introduction 1
Description of the Radiological Environmental Monitoring Program 2
Results and Discussion 5
Conclusion 44 d
I~
s I
(ii)
i.
Q s
LIST OF FIGURES FIGURE Paae 1-1 Control Site Locations (50 Mile Radius around the Virgil C. Summer Nuclear Station) 9 1-2 Radiological Monitoring Program Locallndicator Sample Sites (S Mile Radius stound Virgil C.
Summer Nuclear Station) 10 1-3 Radiological Monitoring Program Localindicator Sample Sites (1 Mile Radius Around Virgil C. Summer Nuclear Station) 11 i
(iii)
] :
LIST OF TABLES TABLE Pace 1
Monitoring Methods for Critical Radiation Exposure 2
Pathways 2
Results of the August 1987 Land Use Census 3
Verification 2a Critical Receptors in 1987 Based on FSAR Projected 4
Source Terms 3
Radiological Environmental Monitoring Program 6,7,8 Sampling Site locations 4
Results of the 1987 EPA Intercomparison Program 12,13 5
Results of the 1987 Intracomparison Program 14 with VCSNS Count Room 6
Summary of the 1987 Intercomparison Program 15 with SCDHEC 7
Results of the Environmental Dosimetry 16 Intercomparison Program with the NRC TLD Direct Radiation Monitoring Network 8
Radiological Environmental Monitoring 17 Program Specifications 9
Supplemental Radiological Environmental Monitoring 23 Program 10 Radiological Environmental Monitoring Program 25 Summary 11 Radiological Environmental Monitoring Program 32 Preoperational(Baseline) Summary 12 Environmental Sampling Program Exceptions 39 13 1987 Activated Corrosion Produc t Activity in Fish 43 14 1987 Activated Corrosion Product Activity in Sediment 44 (iv)
t e
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 c,n October 22, 1982, reached 50% power December 12,1982 and 100% power June 10,1983 following steam generator feedwater modifications. VCSNS completed its third fuel cycle on March 6,1987. The fourth fuel cycle began after criticality was achieved on June 6,1987 following a 69 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 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 p.ool 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 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 Environmen al Monitoring Program at VCSNS.
This report summarizes the results of toe Radiological Environmental Monitoring Program conducted during 1987. Data trends, control / indicator and preoperational/
operational data mtercomparisons and other data interpretations are presented.
Page 1
Description of the Radioloaical Environmental Monitorina Proaram The Radiological Environmental Monitoring Pro entirety by South Carolina Electric and Gas Company. gram is carried out in its The program has been designed to meet the following general commitments:
- 1. To analyze selected samples in important anticipated pathways for the qualification and quantification of radionuclides released to the environment surrounding VCSNS.
- 2. To establish correlations between levels of environmental radioactivity and radioactive effluents from VCSNS operation.
The program utilizes the concepts of control / indicator and preoperational/
operationalintercomparisons in order to establish the adequacy of radioactivity source control and to realistically verify the assessment of environmental radioactivity levels and subsequent radiation dose to man.
Specific measurement, sampling and analysis methodology has been programmatically developed to sensitively monitor the pathways expected to represent 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 oathways of these effluents which may lead to radiation exposure of the public, aased 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 immersion) gestion and Sampling, Shoreline and Bottom Sediment Sampling Drinking Water Ground Water Sampling, Drinking (Ingestion)
Water Sampling Table 1 Monitoring Methods for Critical Radiation Exposure Pataways Page 2
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 samples. These criteria were used to establish both the preoperational and operational 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 1987 are included in Table 2. A verification of the critical receptor (maximum exposed individual) in each sector around VCSNS based on 1987 meteorologicaldata and VCSNS Final Safety Analysis Report source terms is included in Table 2a.
Sector Miles Nearest Garden Miles Cattle R id n M ed N
Martin 38 Fuller 40 Robinson 0
33 NNE Crumblin 2.9 Robinson (8) 3.3 Robinson 0
3.3 NE Stone 2.1 Robinson 29 Stone 0
2.1 ENE Johnson 1.4 Willingham 1.5 E
Martin 1.5 Pearson 31 ESE Martin (A) 1.1 Martin 1.1 SE White 1.5 Summer 1.5 SSE Crumpton 2.5 Shealy 2.7 5
Pinner 38 Eargie 39 Yarborough 0
3.8 SSW Weber 32 Ash (B) 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 25 Livingston 0
2.1 WNW Palmer 2.7 Williams 4.5 Williams (C) 0 45 NW Wright 3.9 Cole (8) 4.1 Cole 0
4.1 NNW March 2.9 March 30 March 0
30 A.
Change in closest residence B
Change in closest garden C.
Milking animal not milked Table 2 Results of the August 19871.and Use Census Verification Page 3
1975 ME 7EOROLOGICAL DA7A 1987 ME TEOROLOGiCAL DA 7A D
SECTOR NAME PATHWAY OOSE DOSE X/Q D/Q RATE X/Q O/Q RATE mrem /y mrem /y N
33 Rotanson Beet C) 2 0E -0 7 9 5E 10 10E 01 2 8E-07 18E 10 8 9E42 N
38 Ma rtin Res 15E 07 7 0E 10 5 7 E -0 3 2 1 E -07 5 7E 10 7 8E 03 N
40 F ulle r '
Res.Ga r 14E 07 6 2E 10 16E -01 1 9 E -07 5 I E 10 1 4 E -01 NNE 29 Crum bhn Res 3 2E-07 1 S E-09 12E 02 3 6E-07 1 1 E -09 14E42 NNE 33 i Rotunson ResGar 2 SE-07 11E49 2 9E 01 2 BE-07
? 9E 10 2 2 E-01
%E 36 R Robinson' RescGar Beef 2 IE-07 8 9E-10 3 5E Oaf,
.3E47 6 3E 10 2 6E-u16E s NE 21 Stone Res, Bee f 6 8E-07 3 6E 09 3 8E -01 6 9 E -0 '
2 6E-03 2 9 E -01 NE 29 J Rco.nson' Res Gar Beef 3 4E-07 1 7E-09 61E 01 4 6E47 12E09 4 6E 01 ENE 14 Jonnscn Res 14 E -06 8 0E 09 5 4E-02 2 4E -06 6 9E-09 9 0E -02 ENE 15 Aishngnam' Res Gar 12E 06 6 8E-09 1 BE + 00 21E 06 5 BE 09 16E +00 E
31 Pearson' ResGar 2 4 E -0 7 9 6E 10 2 S E 41 4 8E-07 9 3E 10 2 7E-01 E
15 N Martin Res 11E46 5 6E-09 4 2E-02 2 1 E-06 5 3E 09 7 8E 02 ESE 11 fr Martin *(DMA)
RerGar 2 2E 06 8 4E-09 22 E + 00 2 6E 06 7 4E-09 2 OE - 00 SE 15 Ahite Res 16 E -06 5 8E-09 6 0E-02 8 8E -0 7 3 2E49 3 3E-02 SE 15 Summer' RerGar 16E-06 5 8E49 16 E + 00 88E47 3 2E-09 8 6E 41 SSE 25 Crumoton Res 3 5E-07 12 E -u9 13E42 1 5 E -07 6 9E 10 5 7E-03 SSE 27 Sheaty' Res/ Gar 3 0E-0 7 10E 49 2 7E-01 13 E -0 7 5 8E 10 1 5 E-01 5
38 rarbarou9h Sect (C) 18507 3 BE 10 45E42 89E48 3 8E 10 4 IE-02 5
38 Pinner Res 1 BE-07 3 BE 10 6 6E43 8 9E-08 3 Bi 10 3 4E-03 5
39 Earg e' ResGar 17E 07 37610 11E41 6 4E 06 3 6E-10 9 SE-02 SSW 32 Aeoer Res 2 3E 07 7 SE 10 8 6i-03 14E 07 7 2E 10 5 4E 03 SSW 34 Ash'(8)
RerGar 2 GE-07 6 4E 10 1 7E 01 12E 07 6 2E 10 1 6 E-01 55W 34 Mille r Res8eef 2 GE 47 6 4E 10 9 4E 02tFs 12 E -07 6 2E 10 8 7E -02(F)
SW 25 Summer Seef(C) 4 6E-07 19E 49 2 1 E -01 2 7E47 17E 49 18E 01 SW 31 Davis Res 2 9E-07 12E49 1 1 E -02 17E 07 10E Os 6 6E 03 SW 33 Nichols' ResGar 2 6E-07 10E -09 2 7E-01 1 SE47 91E 10 2 3E-01 SW 33 MJler Res 2 6E-07 10E -09 9 8E43W 15 E-07 91E 10 5 8E-03ul WSW 19 Lmnaston Beef (C) 64E47 3 2E-09 3 4E-01 4 4E-07 3 OE 09 3 2E 01 ASW 31 Hope Res 2 3E-07 1 OE-09 8 7E-03 15E47 9 sea 0 5 9E 03 W5W 33 Summ r' RevGar 2 OE-07 8 7E-10 2 3E-01(1) 13E 07 8 2E 10 3 8E-010) e W
25 Amic k Res 2 SE-07 1 1 E -09 9 5E43 3 2E 07 12E49 1 2 E -02 W
25
$mitn RescGar 2 SE-07 1 1 E-09 2 9E 01 3 2E-07 12E49 3 2 E -01 W
27 Lie rngston '
R es< Gar. Bee f (G) 2 2E 07 9 3E 10 4 2E-01(M) 2 7E-07 10E 49 4 SE-01(H)
WNW 27 Raimer Res 18E-07 7 6E 10 6 6E-03 1 3 E -07 4 8Ea0 4 9E 03 ANA 45 Wilhams' ReUGar Beef 6 6E48 2 SE.10 9 2E 02 4 6E 08 1 SE 10 5 6E 02 l
NW 39 Wright Res 11E 07 4 6E 10 4 2 E -03 12E 07 3 4E 10 4 SE 03 NA 41 Coie *(8)
ResGar 8eef 9 2E-08 4 0E 10 1 5 E -01 11E 07 3 0E 10 1 1E 01 l
NNA 29
, Marcn Res 19 E-0 7 1 IE 09 7 4E 03 3 6E 07 9 IE 10 13E 02 NNA 30 F Varcn*
ReuG a r see' 18E47 9 7E 10 3 SE 01 34E 07 8 4E 10 3 2 E 01 Denotes Criticai Receptor f or the Sector.
(G)
Cattle assumed to grate at 21 miles W.
(Q)
Change in Closest Residence for the Sector (H)
Assuming tivingston eats beef from his herd in the W5W. Eivingston's (f rom 1986 Census)-
f8)
Change in closest garden dose rate wound.kr aLf ollows:
.56 mrem /y(*75 A Q,0-Q). 57 mRerrt y('87 AT D7).
C)
Residence a ssumed in calculations.
(i)
D)
Ma simum e s posed individuai f or the srte (1975 met data)
Aisuming Summer eatt beef from his herdin the SW, Summer's dose rate i
1 IE)
Cattle assumed to grate at 3 3 miles NNE.
would be a s f oliqq.i.
42 mrem /y f 75 A Q, Ol), 38 mrem y ( 87 AT.R)
(r>
Caetie assumedio gra e ai 3 0 mis i 55W (3) e Asiuming usiier eati deef f,om his he,d in ig55W. Marier's do uid be as follows 096mmem'y ('75 A 0,
) 088 mrem y 087,,
~~~
Table 2a - Critical Receptors in 1987 Based on FSAR Projected Source Terms i
4 l
in addition to preoperational/ operational data intercomparisons, control /
indicator data intercomparisons are utilized to assess the probability that any observed abnormal measurement of radioactivity concent' ', tion is due to random or regional fluctuations rather than to a true increase a local environmental radioactivity concentration. Monitoring sites indicative of plant operating condi-tions are generally located within a 5 mile radius of the plant as shown in Table 3 and Figures 1-2 and 1-3. Monitoring sites at distances greater than 10 miles 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 particulates, and at selected sites, radiciodine. Four of these locations have additional complementary sampling /
measurement oathways for monitoring plant effluents. Sampling locations 6 (1.0 mi ESE) and 8 (1.5 mi ENE) have broadleaf vegetation gardens for monitoring the gaseous effluent deposition and in estion pathway in the two sectors having the J
highest deposition coefficients (D/Q). Sampling locations 5 (0.9 mi SE) and 18 (16.5 mi 5) also have broadleaf vegetation gardens for monitoring the gaseous effluent deposition and ingestion pathway at an indicator and controllocation, respectively.
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 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 1987. Results of the 1987 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 contro! 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 1987 are summarized in Table 10. For comparative purposes preoperational data is summarized in Table 11. Certain samples were not collected during 1987 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 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.
5
Description 5 M Direction 2 Sample Type (s)3 es 1
Borrow Pit. -
12 182.0 5 DM 2
Transmission i.ine 12 225.0 SW AP.RI.DM 3
Firing Range 12 270.0 W DM 4
Fairfield Hydro 12 289 5 WNW DM 5
Transmission Line Entrance 09 145.5 SE AP.RI.DM 6
Env Lab Garden 10 104.0 ESE AP, RI,DM.G R,G A 7
Monticello Peninsula 12 83 0 E DM 8
Monticello Res. 5 of Rd 224 1.5 63.0 ENE AP.DM.G A 9
Ball Park 22 44 0 NE DM 10 Meteorological Tower No 2 2.5 25.5 NNE AP.RI,DM 11 Residence 33 80N DM 12 Old Hwy 99 42 34S.0 N DM 13 North Dam 29 334 0 NNW AP.DM 14 Dairy 63 270 0 W AP RI,DM.MK.GR 15 Parr Village 2.5 204 0 55W DM 16 Dairy 28 0 281.0 W DM.G W,M K.G R 17 Columbia Water Works 24.7 144 0 5E AP,RI.DM,5W.DW B5 18 Residence / Pine Island Club 16 5 165.05 DM,5W,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 SW,FH,85 22 Neal Shoals 30 0 343.0 NNW SW.FH,85 23 Discharge Canal (Mont Res )
0.5 104.5 ESE SW,FH,85 24 Recreation take 55 2.0 N SW,FH,85 25 Fairfield Pumped Storage (Monticello Res )
0.9 302.0 WNW SW 26 On Site Wolf (P2) 450 Ft 270 0 W GW[
27 On *.ite Well (PS) 510 Ft 180.05 GW
-[t' Nuclear Training Center (EOF) 2.4 168.0 55E DW Ys Trans. Line WSW of VCSNS 09 248 0 W5W DM 30 Oak Tree North of Borrow Pit 10 197 E5W DM 31 McCrorey Liston School 58 12.5 NNE DO
~
32 Dirt Rd ott Rd 205 45 25 0 NNE DQ 33 Rd 48 near Hwy 213 42 70 0 ENE DQ 34 Rd 419 North of Hwy 60 48 112.5 ESE DQ 35 Unnamed Circle Road off Hwy 215 48 137.5 5E DO 36 Woods Behind Jenk. Post Office 3.1 151.5 SSE DQ 37 Residence 49 305.5 NW DO 38 FPSF Tra,lrace 13 280 0 W 85 39 LMWTF 14 0 168.0 55E DW 40 No 5amoter 41 End of Catwalk 39 18505 DO 42 Store 39 199 0 55W DQ 43 Hwy 176 and Rd 435 52 236 0 5W DO Table 3 Sampling Site Location 5 fA
i Description Ds n Direction 2 Sample Type (5)3 g
e 44 Rd 28 at Cannon's Creek 29 255.5 WSW 00 45 Rd 33 at Pornaria 59 253.0 WSW 00 46 Rd 28 at Heller's Creek 37 292.0 WNW DQ 47 Fairfield Tailrace 1.0 316.0 NW 00 48 Cemetary 2.3 318.5 NW 00 49 North Rd 383 40 332.5 NNW DO 50 New Rd 99 (West Shore) 5.5 1.0 N DO 51 New Rd 99 (East Shore) 55 50N DQ 52 Monticello(Rd 11) 3.9 14.0 NN E DO 53 Rd 359 3.0 48.0 N E DO 54 Jenkinsville SchcAl 1.7 73.0 ENE 00 55 St. Barnabas Church 28 94 0 E DQ 56 Olc' Jenkinsville Diner 20 144.0 S E DO 57 Residence / Highway 213 and 215 2.7 146 O SE DQ 58 Residence 2.5 158.0 55E DO 59 Nuclear Training Center (EOF) 24 168.0 55 E DQ,AP 60 Rd 98 near Rd 28 3.5 2750 W 00 61 Switchyard. 5E Entrance to Plant 01 180.0 5 DM 62 East of Training Bldg.
0.13 220.0 5W DM 63 East of Daniel's Office 0 17 270.0 W DM 64 Riprap W of Intak e 0.13 338 5 NNW D M,85 65 Guard Tower 0.13 22.5 NNE DM,85 66 Jetty 0.6 33.0 NNE DM 67 ServMe Water Pond (East Side) 0.5 72.0 ENE DM 68 Fuel Oil Storage Tann 0.2 108.5 ESE DM 69 Exclus:on Buoy NNW on Mor'ticello Res.
1.0 337.0 NNW DM 70 Exclusion Buoy N on MontKello Res.
1.0 00N DM 71 Temperature Buoy on Monticello Fxs 54 3.0 N DM 72 Yard Drain Outf all 0.4 146.0 5E SW 73 Yard Drain Outf all 0.4 270.0 W SW 74 Yard Drain Outfall 0.5 246 0 WSW SW i
80 Congaree River 30.2 147.0 55E B5 81 Congaree River 30.1 147.0 SSE BS 82 Congaree River 30 0 147.0 nE B5 83 Congaree River 28.5 147.0 SSE B5 84 Congaree River 54.2 135 0SE B5 85 Congaree River 53 8 13 5.0 SE B5 86 Congaree River 54 0 135 OSE B5 87 Lake Manon 72.0 138.0 5E B5 88 Lake Marion
~~
72.0 138 OSE BS 89 Lake Marion 72 0 138 0SE BS i
Table 3 - Sampling Site Locattora (continued) 7
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 = AirRadioiodine MK = Milk DM = Monthly TLD GR = Grass (Forage)
DQ = Quarterly TLD GA = Garden SW = Su face Water FH = Fish' GW = Ground Water BS = Bottom Sediment i
i Table 3 Sampling Site Locations (continued) r 8
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Companson Study U
(Measurement Unit)
Date Nuclide FA Value Result Agree-( lo)
( 3 3 g) ment Air filter (pCi/ filter) 4/87 beta 43(5) 56(0)
Yes Cs-137 8 (5) 9 (0)
Yes 8/87 beta 30(5) 34(1)
Yes Cs 137 10 (5) 10 (1)
Yes Gamma in Water (pCi/ liter) 2/87 Cr-51 Not tested Co-60 50(5) 56(2)
Yes 2n 65 91(5) 101(5)
Yes Ru-106 100 (5) 111(4)
Yes Cs-134 59(5) 60(2)
Yes Cs-137
- 87. (5) 94(5)
Yes 6/87 Cr 51 41(5) 40(3)
Yes Co-60 64(5) 65(2)
Yes Zn-65 10(5) 11(1)
Yes Ru 106 75(5) 74(4)
Yes Cs 134 40(5) 36(2)
Yes Cs137 80(5) 79(4)
Yes 10/87 Cr 51 70(5) 63(8)
Yes Co 60 15(5) 16(1)
YJs 2n 65 46(5) 45(1)
Yes Ru 106 61 (5) 55(4)
Yes Cs 134 25(5) 22(1)
Yes Cs-137 51(5) 49(2)
Yes Gross Beta in Water (pCi/ liter) 1/87 beta 10(5) 12(0)
Yes 3/87 beta 13 (5) 11(1)
Yes 5/87 beta 7 (5) 8 (1)
Yes 7/87 beta 5(5) 5 (0)
Yes l
9/87 beta 12(5) 11(1)
Yes 11/87 beta 19 (5) 15(2)
Yes Table 4 Results of 1987 EPA Intercompanson Program qs>
Lab tog Comparison Stud EPA Value (Measurement Unf)
Date Nuclide pesul Agree-(tlo) ment
(
gg) lodine in Water (pCi/ liter) 4/87 l131 7 (1) 7 (2)
Yes 8/87 l131 48(6) 49(2)
Yes 12/87 l-131 26(6) 26(2)
Yes Laborator (pCi/ liter) y Blind 4/87 beta 66(5) 58(2)
Yes Co 60 8 (5) 9 (0)
Yes Cs-134 20(5) 18(1)
Yes Cs 137 15(5) 16(1)
Yes l
10/87 beta 72 (5) 6 5 (1.'
Yes Co 60 16(5) 16(1)
Yes Cs 134 16(5) 16(0)
Yes Cs137 24(5) 25(1)
Yes Radionuclides in Milk (pCi/ liter) 2/87 l-131 9 (1) 9 (1)
Yes 6/87 I131 59(6) 68(3)
Yes Cs-137 74(5) 78(2)
Yes Tritium in Water (pCi/ liter) 2/87 H3 4209(421) 4650(321)
Yes 6/87 H3 2895(357) 2798(116)
Yes 10/87 H3 4492 (449) 4582(91)
Yes Radionuclides in Food (pCi/kg) 1/87 l-131 78(8) 86(2)
Yes Cs-137 84(5) 94(2)
Yes 7/87 l131 80(8) 84 (3)
Yes Cs137 50(5) 54(2)
Yes Table 4 - Results of 1987 EPA Intercomparison Program (continued) 13
O 8
Comparison Study VCSNS Count (Measurement Unit)
Date Nuclide Laboratory Agree-Results1 Re 51 ment 25 ml Gas Sample 3/87 Kr 85 4.51 E 4 N/O N/A (pCi/ml)
Kr 85m 2.97E 5 1.33E 5 Yes Xe 131m 6.93E 4 7.12 E-4 Yes Xe 133 6.15E 2 7.36E 2 Yes Xe-133m 8.96E-4 9.64E-4 Yes Xe 135 5.81E 4 6.40E 4 Yes 11 Liquid Sample 7/87 Cr 51 5.22E 6 N/O N/A (pCi/ml)
Mn 54 7.79E 7 6.33E 7 Yes Co 57 1.10E 7 N/O N/A Co 58 t47E 5 1.23E 5 Yes Co-60 5.46E 6 4.08E 6 Yes Nb 95 4.48 E-7 3.11E 7 Yes Cs 134 1.04E 7 N/O N/A Cs 137 1.24E 7 N/O N/A Am 241 1.07E 4 1.37E 4 Yes Charcoal Filter 9/87 Co 57 2.35E 2 1.81E 2 Yes (pCi/m3)
Co 60 4.53E 2 3.56E 2 Yes Y 88 2.15E 2 1.69E 2 Yes Cd 109 1.25E0 1.01 E0 Yes Sn 113 1.57E 2 1.31E 2 Yes Cs 137 5.30E 2 4.25E 2 Yes Ce 139 1.23E 2 9.53E 3 Yes Hg 203 2.41 E-3 1.89E 3 Yes 25 ml Gas Sample 10/87 Ar 41 1.67E-4 2.16E 3 No2 (pCi/ml)
Kr 85 4.03E 3 N/O N/A Kr 85m 9.89c 3 1.11E 4 Yes Kr 87 4.60E 5 4.43E 5 Yes Kr 88 1.41E 4 1.74 E-4 Yes Rb 88 2.19E 2 2.60E 3 No2 Xe 131m 1.22E 3 N/O N/A Xe 133 5.55E 2 5.95E 2 Yes Xe-133m 3.20E-4 3.48E 4 Yes Xe-135 2.18E 3 2.23E-3 Yes Xe-135m N/O 2.48E 5 N/A Cs 138 N/O 1.39 E-4 N/A Filter Paper 12/87 Co-57 4.94E 3 5.66E 3-Yes (pCi/m3)
Co 60 5.94E-2 6.18E 2 Yes Y 88 1.38E 3 1.44E 3 Yes Cd 109 6.50E 1 7 86E-1 Yes Sn 113 1.45E 3 1.58E 3 Yes Cs 137 7.78 E-2 8.08E 2 Yes Ce 139 1.51E 3 1.66E 3 Yes 1.
N/O = not observed 2.
Disagreement attnbuted to differencesin extrapolation of respective calibration curves at high energies. Corrective action is being taken to resolve discrepancy.
Table 5 - Results of 1987 Intracomparison Program with VCSNS Count Room 14
Pathway (Units)
Frequency Nuclidet 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 1.
Intercomparison results were not yet available for publication in this report.
Results will be reported by SCDHEC.
Table 6 - Summary of 1987 Intercomparison Program with South Carolina Department of Health l
and Environmental Controls 15
1986 FOURTH QUARTER RESULIS 1987 FikST QUARTER 19875ECOND QUART ER RESUL15 1987 THIRD QUARTER NRCTLD LABORA-(uR/hr)
RESULTS(uR/hr)
(uR/hr)
RESULTh (uR/hr) 51AllON TORY TLD A ONNO NRC Laboratory
'#* 'Y
'** 'Y a ratory D f eren(e Df rence Df rence Df ten e 1
42 10.6 7.7 27.4 9.1 7.6 16.5 10.6 7.9 25.0 9.6 7.5 21.9 2
6 8.7 8.7 0
9.2 8.4 8.7 8.4 8.7
-3.4 9.4 8.1 13.8 5
54 11.2 12.7
-13.4 10.5 11.5
-9.5 12.3 11.1 11.8
-6.3 7
'53 13.4 12.5 6.7 11.8 12.5
-5.9 13.4 12.6 6.0 13.1 12.5 4.6
(
9
- S2 13.2 13.5
-2.3 13.1 12.9 1.5 12.7 13.1
-3.1 12.8 12.8 0
11
- 12 9.7 9.7 0
8.9 9.5
-6.7 9.4 13.0 9.2 29.2 13 13 11.5 12.5
-8.7 10.7 12.3
-15.0 12.0 12.4
-3.3 11.7 12.2
-4.3 14
'44 7.4 10.2 7.0 31.4 8.9 7.4 16.9 11.1 7.1 35.8 19
'56 9.1 9.2
-1.1 10.0 9.3 7.0 8.9 9.7
-9.0 10.5 9.2 12.4 22 58 8.1 6.3 22.2 7.6 6.2 18.4 8.4 6.6 21.0 7.8 6.0 23.1 24 41 9.0 9.2
-2.2 7.8 9.1
-16.7 9.5 9.2 3.2 8.8 9.4
-6.8 l
29
- 60 11.0 11.6
-5.5 10.8 12.1
-12.0 11.3 12.0
-6.2 11.0 11.7
-6.4 30 46 10.6 10.2 3.8 11.9 9.9 16.8 10.0 10.0 0
17.6 10.2 42 3
Co-located dosimeters within 10 ft. of NRC dosimeter.
Table 7 - Results of Environmental Dosimetry Intercomparison with NRC TLD Direct Radiation Monitoring Network
n 1 Exposure Pathway Criteria for Selection Sampling and Simple Type & Frequency 1
l and/or Sample of Sample Number & Location Collection Frcqu:ncy Location of Analysis AIRBORNE:
1 Parti (utate A) 3 Indicator samples to be tak en at locations (in Continuous sampler 2
Gross beta following filter dif ferent sectors) beyond but as (lose to the operation with weekly 5
(hange; Monthly Composite entusion boundary as practicable where the collection.
10 (by location) for gamma highest of fsite sectoral ground level isotopic.
c on(entrations are anticipated.
B) 1 Indicator sample 1o be 1aken in the sector Continuous sampler 6
Gross beta following filter beyond but as (lose to the entusion boundary operation with weekly (hange; Monthly Composite as practicable (or responding to the residence (ollection.
having the highest anticipated of fsite ground (by location) for gamma level (oncenteation or dose.
isotopic.
C) 1 Indicator sample to be tak en at the location Continuous sampler 14 Gross beta following filter of one of the dairies most likely to be af fe(ted operation with weekly change; Monthly Composite collection (by location) for gamma isotopic Z
D) 1 Control sample to be taken at a location at Continuous sampler 17 Gross beta following filter least 10 air miles from the site and not in the operation with week ly change; Monthly Composite most prevalent wind directions.
(ollection.
(bylocation) for gamma isotopic.
11 Radioiodine A) 3 Indicator samples to be taken at two Continuous sampler 2
Gamma isotopic ior lodine locations as given in 1(A) above.
operation with week'ly 5
131 canister colle(tion 10 B) 1 Indecator sample to be taken at the location Continuous sampler 6
Gamma isotopic for lodine as given its 1(B) above.
operation with weekly 131 canister (ollection C) 1 Indicator sample to be taken at the location Continuous sampler 14 Gamma Isotopic for lodine as given in 1(C) above operation with weekly 131 canister (ollection D) 1 Controf sample to be taken at a location Continuous sampler 17 Gamma Isotopic for lodine similar in nature to f(E) above.
operation with weekly 131 (anister collection.
Table 8 - Radiological Environmental Monitoring Program Specifications
Exposure P thway Criteria for Selecti n Sampling and Sample Type & Frequ:ncy
~
and/or Sample of Sample Number & Location Collection Frequency Location of Analysis ill Direct A) 13 Indicator stations to form an inner ring of Monthly or quarterly 1,2,3,4, Gamma dose monthly or stations in the 13 auessible sectors within 1 to exchange; two or more 5,6,7,8 quar terly.
2 miles of the plant dosimeters at each location.
9,10,29, 30,47 l
B) 16 Indicator stations to form an inner ring of Monthly or quarterly 12,14,32, Gamma dose monthly or stations in the 16 auessible settors within 3 o exchange; two or more 33,34,35 quarterly i
5 miles of the plant dosimeters at each location.
36,37,41, 42,43,45, 46,49, 53,55 C) 20 5tations to be pla< ed in specal interest Monthly or quarterly 11,13,15, Gamma dose monthly or areas such as population centers, near by exchange; two or more 16,17,18, quarterly residences, schools and in 2 or 3 areas to serve dosimeters at each lotation.
19,20,31, as contr015.
44,48,50, 5
51,52,54, 56,57,58 59,60 Table 8 - Radiological Environmental Monitoring Program Specifications
Exposure Pathw:y Criteria for Selecti:n Sampling and Sampi:?
Type & Frequency
~
and/or Sample of Sample Number & Location Ccliection Frequency Location of Analysis WAl[RBORNE:
IV Surf a(e Water A) 1 Indicator sample downstream 1o be taken at Time composite samples 21 Gamma isotopic monthly a location which allows for mixing and dilution with collection every month with quarterly composite (by in the ultimate receiving river location) or monthly sample 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 suf f aciently far up-stream with collection every month such that no elfects of pumped storage with quarterly composite (by operation are antiopated.
location) or monthly sample to be analyzed for tritium C) 1 Indgator sample f rom a location immediately Time composite samples 17 Gamma isotopic monthly upstream of 1he nearest downstream with collection every month.
with quartedy composite (by municipal water supply.
locatior.) or monthly sample to be analyzed for tritium.
D) 1 Indicator sample 1o be taken in the upper Time (omposite samples 23 Gamma esotopic monthly reservoir of the pumped storage facility at the with collection every momb with quarterly composite (by plant dis (harge canal location) or monthly sample e
1o be analyzed for tritsum.
E) 1 Inds(ator sample to be taken in the upper Grab sampling montbly 24 Gamma isotopg monthly reservoir's non-fluctuating r ecreational area with quarterly composite (by location)or monthly sample to be analyzed for tritium.
F) 1 Control sample 1o be taken at a location on a Grab sampling montbly 18 Gamma isotopic monthiy separated unalfected watershed reservoir.
with quarterly composite (by location) or monthly sample to be analyzed for tritium V Ground Water A) 2 Indicator samples to be taken within the Quarterly grab sampling 26 Gamma isotopic and tritium exclusion boundarf and in the direction of 27 analyses quarterly.
potentially af fected ground water supplies B) 1 Control sample from unaf fe(ted location Quar terly grab sampling 16 Gamma isotopic and tritium analyses quarterly.
Table 8 - Radiological Environmental Monitoring Program Specifications
Exposure Pcthway Crit:ria for Selection Sampling and Sample Type & Frequ:ncy i
and/or Sample of Sample Number 8 Location Collection Frequency Location of Analysis VI Onnking Water A) 1 lodgator sample from a nearby pubhc Monthly grab sampling 28 Mont hly gamma isotopic, ground water supply source.
gross beta and trotsum analyses B) 1 Indgator (finished water) sample from the Monthly composite 17 Monthly gamma isotopic, nearest downstream water supply.
sampling gross beta and tritium analyses i
C) 1 Control (finished water) sample itom the nearest unaf f ected public water supply.
Monthly (omposite 39 Monthly gamma isotopK.
samphng gross beta and tratium analyses.
INGESTION:
Vil Milk A} Samples f rom milking animals in 3 locations Biweekly grab Gamma isotopic and 1-131 u t.
a within 5 km having the highest dose potential.
sample.
analysis biweekly if there are none. hen 1 sample from milking
.. w animals in each of 3 areas between 5 to 8 f,m o"
distance where doses are calculated to be
..v..
greater than 1 mrem per year 8) 1 Control sample to be taken at the location of B: weekly grab 16 Gamma isotopK and 1-131 a dairy > 20 miles distance and not in the most sample.
analysis biweekly.
prevalent wind dire (tion.
C) 1 Indgator grass (forage) sample to be taken at Monthly when 6
Gamma asotopK.
one of the lo(ations beyond but as (lose to the available exclusion boundary as practKable where the highest of fsete sectoral ground level con (entrations are anticipated D) 1 Indicalor grass (forage) sample to be taken at Monthly when i.e.
,4 Gamma isotopic the location of Vil(A) above when animals are available on pasture.
.. s mo.u..
..t..
E) 1 Control grass (forage) sample to be taken at Monthly when 16 Gamma isotopic.
the location of Vil(B) above.
available Table 8 - Radiological Environmental Monitoring Program Specifications
Exposure Pathw:y Crit:ris f:r Selecti n Sampling and Sample Type & Frequency cnd/or Sample of Sampla Number & Location Cellecti:n Frequ ncy Location of Analysis Vitt Food Products A) Two samples of broadleal vegetation grown in Monthly when available.
6 Gamma isotopic on edible 1 location of specialinterest and in 141 near-8 portion.
est of f5ite location of highest calculated annual average ground level D/Q if milk sampling is not performed within 3 km or o f milk sampling is not performed at a location within 5-10 k m where the doses are calcelated to be greater than 1 mrem /yr.
B) 1 Control sample for the same foods in Vill (A)
Same as for Vill (A), as 18 Gamma Isotopic on edible taken at a location at least 10 miles distance apprcmriate.
portion.
and not in the most prevalent wind direction.
IX Fish A) 1 Indicator sample to be taken at a location in Semiannualcollection of the 23 Gamma isotopic on edible the upper resuvoir.
following specie typesif portions semiannual;y.
U available: bass; bream, crappie; catfish, carp; forage fesh (shad).
3) 1 Indgator sample to be taken at a location in Semiannualcollectionof the 21 Gamma isotopic on edible the lower reservoir.
following specie types if portions semiannually.
available: bass; bream, crappie; catfish, carp; forage fish (shad).
C) 1 Indgator sample to be taken at a location in Semiannual collection of 1he 24 Gamma isotopic on edible the upper reservoir's non-fluctuating following specie types if portions semiannually.
recreational area.
available: bass; bream, crappie; catfish, carp; forage fish (shad).
D) 1 Control sample to be taken at a location on 5emiannualcollectionof the 22 Gamma imtopic on edible the receiving nyer suf fKiently far upstream followmg specie types if portions semiannually.
such that no eflects of pumped 51orage available; bass; bream, operation are anticipated crappie; catfish, carp; forage issh (shad).
Table 8 - Radiological Environmental Monitoring Program Specifications
Exposure Pcthway Criteria for Selection Sampling cnd Sampl2 Type & Frequency and/or Sample of Sample Number G Loccti:n Collection Frequ::nc,r Loccti:n of Analysis AQUAllC:
X Sediment A) 1 Indicator sample 1o be 1ak en at a location in Semiannual grab sample 23 Gamma isotopic.
the upper reservoir.
(
B) 1 Indi<ator sample to be taken at a location in Semiannual grab sample.
24 Gamma isotopic.
the upper reservoir's non-fluctuating recreational area e
C) 1 Indicator sample to be taken on the shoreline semiannual grab sample 21 Gamma isotopic.
of thelower reservoir.
D) 1 Control sample to be taken at a location on Semiannual grab sample.
22 Gamma isotopic.
the receiving river suf ficiently far upstream such that no effects of pumped storage operation are anticipated.
'M Table 8 - Radiological Environmental Monitoring Program Specifications
Exposure Pathway Criteria for Selection Sampling and Sample Type & Frequency and/or Sample of Sample Number & Location Collection Frequency Location of Analysis AIRBORNE:
1.
Particulate E) 3 Indicator samples to be tak en at locations (in Continuous sampler 8
Gross beta following filter dif ferent sectors) beyond but as (lose to the operation with weekly 13 change; Monthly Composite exclusion boundary as practicable and nearer collection.
59 (bylocation) for gamma to the plant than the nearest critical receptor isotopic.
for the chosen sector.
111 Direct D) 85tations to be placed within the exclusion Monthly or quarterly 61,62 Gamma dose monthly or boundary (Special 5tudy).
exchange; two or more 63,64 quarterly.
dosimeters at each location.
65,66 67.68 E) 3 5tations to be placed on buoys on Monticello Monthly or qu,$r terly 69 Gamma dose monthly or Reservoir (Background Study).
exchange; two or more 70 quarterly.
dosimeters at each location.
71 WATER 80RNE:
IV. Surface Water G) 1 indecator 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 month.
with quarterly composite (by g
w facility.
locat on) or monthly sample to be analyzed for tritium.
INGESTION:
Vil Milk A) Sarrples from milksng animals in 3 locations Biweekly grab sample 14 Gamma isotopic and 1-131 within 5 km having the highest dose potential analysis biweekly if there are none then 1 sample from milking animals in each of 3 areas between 5 to 8 km distance where doses are calculated to be greater than 1 mrem per year.
D) 1 Indicator grass (forage) sample to be taken at Monthly when available 14 Gamma isotopic the location of Vil(A) above when ansmais are on pasture.
Table 9 - Supplemental Radiological Environmental Monitoring Program
Exposure Pathway Criteria for Selection Sampling and Sample Type & Frequency and/or Sample of Sample Number & Location Collection Frequency Location of Analysis Vill Food Produ(ts C) 1 Indicator sample of each of the crious ty,_es Annually during growing 6
Gamma Isotopic on edible of foods grown in the area surroumhng the season plant.
portion.
D) 1 Control sample of the same foods collected in Anroually during growing 18 Gamma Isotopic on edible Vill (c) at a location at least 10 miles distance season.
portion.
and not in the most prevalent wind direction.
AQUATIC:
E) 1 Indicator sample to be taken at a location Semiannual grab sample.
17 Gamma isotopic.
M.
Sediment immediately upstream of the nearest downstream municipal water supply.
F) 1 Indicator sample to be taken at a location Semiannual grab sample.
38 Gamma isotopic.
immediately downstream of the VCSNS liquid ef fluent discharge point.
y G) Ten (10) additional indicator sampf es to be Semiannual grab sample.
80,81 Gamma isotopK.
A taken at various locations on Congaree River 82,83 between Broad River and Lake Marion.
84,85 86,87 88,89 Table 9 - Supplemental Radiological Environmental Monitoring Program
Virgil C. Summer Nuclear Station Docket No. 50-395
~
Fairfield County, South Carolina Reporting Period: 1/1/87-12/31/87 P' #
Medium or Pathway Lower Limit of AllIndicator wation with Highest Annual Mean Number of Sampled (lJnst of Detection 1 Locations Measurement)
Analyses (Name, Distance &
M ean*,
Mean2 iRange)
Reportedi Performed AC "*I I '" I
'8" I 8"9'I Direction)
(Rai.ge)
Measurements Air Particulate Gross Beta
Site 13, North Dam
.6E-2 M 2) 23E-2 U M/IM)
(pC /mi)
(570)
(1 OE-2)
(2.9 mi NNW) 46-)
Gamma Spec 0 32)
C5-134 All < LLD (5 0 -
All < LLD 0
Cs-137 All < LLD 60 All < LLD 0
Aer Radiosodane5 3 g[.2 3
fpCa/m )
(7 OE-2)
Derect (T LD)6 Gamma (164)
( 03/2 M )
Site 9, bah Park 12.301/14 9 8 @W
- 5. 2E-1 (pR/ht)
Monthly (6 81012.9)
(2 2 mi, NE)
O2.0 to 12 9)
(6 4 to 12.9) 0 Gamma 008)
WOM)
%te %,W 8arnabas 14.3(4/4) 5,7,,
Quarterly (6 0 to 14 9)
Church (2 8 me, E) 03 6 to 14.9) 9 m
Surf a(e Water 4.3E + 2 5 5E + 2 (3/63)
Site 17, Columbia
+
2/13)
" (
(pCill)
(2.0E + 3)
(4 SE + 2 to 6 6E + 2)
Canal (24 7 mi, SE)
^"
6E +
Gamma Spec (89) 8 Mn-54 All < LLD 0 5E
)
All < LLD 0
2 0E g 5( }
3 E 4 2 4E g 5(;1 Co-60 All < LLD All < LLD 0
4 6E 1 zn-65 All < LLD All < LLD 0
gg Zr-95
^ " <
^ " <
(3 OE 1)
O SE I
BE 1 Cs-134 All < LLD All < LLD 0
l j
Table 10 - 1987 Radiological Environmental Monitoring Program Summary
]
Virgil C. Summer Nuclear St, tion Docket Nn. 50-395 Fairfield County, South Crrolina R: porting Period: 1/1/87-12/31/87 P' #
Medium or Pathway Lower Limit of Allindstator Location with Highest Annual Mean Number of Sampled (Unit of Detection 1 Locations
^"#
Measurement)
Actual (Max.)
Mean2 (Range)
Performed Direction)
(Range)
Measurements Site 21, Part 1.OE0 (2/13)
Cs-137 Reservoir (9 6E-1 to All < LLD 5
(1.BE+1)
(7.2E-2 to 1.0E0)
(2.7 mi 55W) 1 OE0) i
$ste 25, Fairfield 1 OE0(1/12)
Pumped Storage (Single (0.9 mi, WNW)
Value)
=- 140 AH < LLD (6 0 + 1)
AH < LLD 0
La-140 All < LLD
{j j)
All < LLD 0
Ground Water 4.3E + 2 6 8E + 2 (2/8)
Site 26. Onsite Well 6.8E + 2 (2/4)
"' I' I (pCi/l)
(2.0E + 3)
(5 3E + 2 to 8.3E + 2)
P4 (265 f t. W)
(
^ " <
, y)
Gamma 5 pet m,
(12) i o
,)
All < LLD 0
g $f,0 Co-58 AH < @
3)
AH < HD 0
fe-59 3 bE All < LLD All < LLD 0
g, g
Zn-65 AH AH D
^"
^"
g$
j}
g$
^"
0 8E + 1)
Table 10 - 1987 Radiological Environmental Monitoring Program Summary
Virgil C. Summer Nuclear Station Docket No. 50-395
~
Fairfield County. South Carolina Reporting Period: 1/1/87-12/31/87 Medium or Datbway Lower Limit of All IndKator
<ation with Highest Annual Mean Number of s
Number of Sampled (Unit of Dete(tion 1 Locations Controf Locations Nontoutine Measurement)
Actual (Max )
Mean2(Range)
(Name, Distan(e &
Mean?
Mean? (Range)
Reportedi p
Direction)
(Range)
Measurements
([5 La-140 All < llD 1)
All < LLD 0
Dnnk ing Water 7 2.5E0 6 OE0 (18/25)
Site 28 NTC 0(12/12) 51EO (7/U)
(pCill)
(4 OEO)
(2 4E0 to 12E + 1)
(2 4 mi,55E) 1.2E + 1) 1.7E + 1) 4 3E + 2 5 OE + 2 (3/38)
I' I *
- I #' I (2 OE + 3)
(4 7E + 2 to 5 2E + 2) aterwods(24 7 mi, R7E + 2 to AH < UD 0
SE) 5 2E + 2)
Gamma 5pec (38) 16[-1 Mn-54 AH < D (1 SE + 1)
AH < LLD 0
M fe-59 (3 b + 1)
AH < RD AH < LLD 0
Zn-65 All < LLD 0E All < LLD 0
Zr-95 All < LLD 3 OE All < LLD 0
00 Cs-134 All < LLD All < LLD 0
0(1/13)
(1 BE + 1) 0 (Single Value)
Mil 6 Gamma Spec (pCs/1)
(51) i Table 10 - 1987 Radiological Environmental Monitoring Program Summary
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/87-12/31/87 Medium or Pathway Lower Limit of AllIndicator (a son with Highest AnnualMean Number of Number of Sampled (Unit of Detection 1 Iocations Controf Locations Nonroutine g
(Name, Distance &
Mean2 Measueement)
A' " I IM#" I
- "I 9'I Mean '(Rotege)
Reported!
Performed Direction)
(Range)
Measurements 5 OL-1 g.131 All < LLD (1 OEO)
All < L LD 0
14E0( /26) 3 2E0 14E0(1/26)
Site 14 Dairy (3,334 (1.5E + 1)
(Single Value)
(6 3 mi W) 9 All < LLD O
l Value) 3 SEO 3 4E0(18/26)
Site 14. Dairy 0 (W26) 41EO (14/25)
('
(1.8E + 1)
(1 SEO to 7.1EO)
(6 3 mi W)
(1.7E0 to 8 4E0) 0)
La-140 All < LLD g$
,y All < LLD 0
Grass (pCi/k g wet)
- P
(26) 1-131 All < LLD All < LLD 0
O(2/7) 19E + 1 71EO (2/16)
$ste 6, Garden 5 3E0(2/10) 1 (8 OE + 1)
(5 6EO to 8 6EO)
(10 mi ESE) -
8 6EO)
Broadleaf Vegetatson g
7 (pC#/kg wet) 1-131 All < LLD All < LLD 0
Cs-134 All < Lt.D All < LLD 0
14E + 1 c,,3 37 All < LLD 18 0F + 1)
O (Single Value)
Other Vege ation (pCs/kq wet) 1-131 All < LLD All < LLD 0
0(1/2) 9 6EO 2 8E0 (1/2)
$ste6, Garden
(
"9
^ " <
(6 OE + 1)
(Single Value)
(1.0 mi E SE)
Table 10 - 1987 Radiological Environmental Monitoring Program Summary
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/87-12/31/87 bPe and Total Medium or Pathway Lower Limit of All inde(ator Location with Nghest Annual Mean Number of sampled (Urut of Detection 1 Locations Measurement)
Analyses (Name, Distance &
Meany Mean1(Range)
Reportedi AC "'I
- I
" IR8"9'I Periormed Direction)
(Range)
Measurements 1.0E + 1 6 OE0 (1/2) 6 OLO (1/2)
(8 OE + 1)
(single Value)
Site 6, Garden (Single All < LLD 1
j (10 mi ESE)
Value)
Fesh (PCs/b g wet) 6#* **SP'C (31)
1.8E + 1 4 4E + 1 (1/24)
Site 21, Parr Res
(. 9 I
(1.3E + 2)
(Single Value)
(2 7 me,$5W) y Fe-59 All < LLD All < LLD 0
~
1.6E + 1 1 BE + 1 (2/24)
Site 21, Parr Res
+ to AH < UD 2
(1.3E + 2)
(1.3E + 11o 2 2E + 1)
(2 7 mi,55W)
Zn-65 All < LLD E+
All < LLD 0
Site 21. Parr 11E+1 7 3E0 (9/24)
Reservoir 9.1E 0 (2/8) g, 9 34 All < LL D 9
(13E + 2)
(5 2E0 to 1.3E + 1)
(2 7ms,55W)
(5 3E0 to 13E + 1) 4 Cs-137 Site 24, Rec Lake O
(1 SE + 2)
(1 OE + 1 to 5.6E + 1)
('
(
(5 Smi, N) 5 6E + 1)
('
Co-SS 2 2E + 1 All < LLD 7
(7 4Elto 5 6E + 1)
Reservoir (7.8E0 to (2.7mi,55W) 5 6E + 1) 64L+1 6 OE + 1(15/37)
Site 21 P.srr (11/16)
Co-60 2 6E + 1 All < LLD 15 (1 SE + 1 to 1.2E + 2)
Reservoer (1.5E + 1 to (2 7mi,55W) 12E + 2)
Table 10 - 1987 Radiological Environmental Monitoring Program Summary
l Virgil C. Summer Nucle:r St: tion Docket No. 50-395
~'
Fairfield Ccunty, South Ccrolins R: porting Period: 1/1/87-12/31/87 ype and Total Medium or Pathway tower Limit of Allindicator mation with MgMt Annual Mean Whd Number of Sampled (Unit of l 8 5
Control Locations Nonroutine Measurement)
Analyses (Name, Distance &
Mean?
Mean2 (Range)
Reported 3 A'
8I IM8" I M'8" I
- 9'I Performed Direction)
(Range)
Measurements 2 OE + 1 1.2E + 1 (12/37)
Site 21, Parr 1.bE + 1(7/16)
Cs-134 Reserv it (7.5E0 to 1.1E + 1 (1/5)
(1.5E + 2)
(5.7EO to 2 3E + 1) 0
($sn9Maiue)
(2.7mi,55W) 2.3E + 1)
+1 1 n + 2(37/37)
Ste 21, Parr
(
6 Cs-137 (7 h E + 1 (18E + 2)
(6 IE0 to 3 OE + 2)
Reservoir (4 6E + 1 t 0
1.9E + 2)
(2.7mi,55W) 3 OE + 2)
U Table 10 - 1987 Radiological Environmental Monitoring Program Summary
8 1
Footnotes 1.
Values given are MDA values calculated from the program data analyses with maximum acceptable LLD values allow NRC guedelines given in parentheses.
2.
Mean and range are based on detectable measurements only. The fractions of detectable measurements at specific loc are indicated in parentheses.
3.
Any confirmed measured level of radioactivity in any environmental medium that exceeds ten times the control station valud Radioactivity attributed to the Chernobyl incident 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 2.3E-2,1.49E-2,1.02E-2 and 5.13E-2 pCi/m3 S.
One sample exceeded maximum LLD because of low sample v.:ume. The calculated LLD was 1.53E-1 pCi/m3 6.
Detection sensitivity is approximately 5 mrem /yr (0.5 pR/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 m
~
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 Ft3-226 daughter products and Ac-228 plus other Th-232 daughter products were r,oserved 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.
i I
Table 10 - 1987 Radiological Environmental Monitoring Program Summary
Medsum or Pathway Type and Total g
g Location with Highest Annual Mean Number of Sampled (Unit of Number of Detection 1 Locations Measurement and Analyses al (Name, Distance &
Mean?
Mean2 (Range)
Reported i Reporteng Period)
Per formed 2 Ra@
Dsrection)
(Range)
Measurements 1.3E-1(52/52) 1 1 E-1 (562/564)*
Site 13, North Dam (21E-2 to 1.2E-1 (153/155)
Air Parti (ulate 8m M-3 (1.3E-2 to 5.5E-1)
(2 9 mi NNW) 5 SE-1)
(7.9E-3 to 6.1 E-1)
'E (1981-1982)
(1300)
(1.0E-2) 2 7E-2 (456/462)4 Site 8, Mon. Res 5 of 3 OE-2(42/42) 2 8E-2(125/126)
(9.3E-3 to 6 6E-2)
Rd 224 (1.5 ENE)
(1.2E-2 to (1.2E-2 to 5 8E-2) 6 OE-2)
Gamma Spec (307)
3.1E-3 3 2E-3 (22/241)
Site 10, Met Tower I# I 4 2E-3 (4/66)
N (1.0E-2)
(1.5E-3 to 5 2E-3)
(2 4 mi NNE)
S 2E-3)
'( 9 '
^"
C/m 2
(
2)
^"
Gamma (1220) 9 9(915/915)
Site 13, North Dam 13.1(61/61) 9 7(305/305)
M nthly (6 7 tol4 7)
(2 9 mi NNW)
(12 2 to 14 2)
(6 4 to 13 5) 8 83 Gamma (161) 10 2(154/154)
Site 55,St Barnabas -
14 0(7/7) 0.5 0
Quarterly (681014 7)
Church (2.8 mi E)
(13.I to 14 7)
"'I # '
1.1 E + 3 14E + 3 (18/29)
Site 17, Columbia I
(
(1981-1982)
(2 OE + 3)
(1.1E + 3 to 2 4E + 3)
Canal (24.7 mi, SE) 18E + 3) 16E + 3)
Gamma 5pec (140)
2 9E;1 Co-58 All < LLD
( i All < LLD 0
g 6
30 0
Table 11 - Radiological Environmental Monitoring Program Summary Preoperational(Baseline) Summary
Medeum or Pathway Type and Total r
tM AH Wier L (ation with Highest Annual Mean Sampled (Unit of Numt>er of Number of Dmion 1 Watsons Control Locations Nonroutine Measurement and Analyses
- "9' Reporting Penod)
Performed Actual (Max )
Mean?(Range)
Direction)
(Range)
Measurements 2 4E Co-60 All < LLD g5 A!! < LLD 0
7.9E-1 Zn-65 All < L LD (3 OE + 1)
All < LLD
)
All < LLD 0
Nt>-95 All < LLD E
All < LLD 0
0E Cs-134 All < LLD All < LLD 0
Cs-137 All < LLD 08 All < LLD 0
Ba-140 All < LLD 6
O All < LLO O
La-140
- 5. 5 E-1 AH (1982 only)
(1.5E + 1)
AH < LLD 0
Ground Water 9.0E + 2 1.5E + 3 (16/16)
Site 26. Onsate Well 16E + 3 (M) 1.3E + 3 (W13)
"" ( '
(pCs/lH 1981-1982)
(2 OE + 3)
(9 SE + 2 to 2 3E + 3)
P4 (265 f t. W)
('g 3
Gamma Spet (32) 3 E0 M n-54 All < LLD All < LLD 0
g 3 8E0 Co-58 All < LLD All < LLD 0
g, 3.,)
Fe-59
^"
^ " <
(30 + 1) 38 Co 60 AH < LLD AH < LLD 0
(15E + 1)
3 0E 1)
Table 11 - Radiological Environroental Monitoring Program Summary Preoperaticnal(Baseline) Summary
~
Medium or Pathway Type and Total
^"'
Location with Highest Annual Mean Number of sampled (Unit of Number of Control Locations Nontoutine Measurement and Arialy es (Name,' Distance &
Mean2 Mean2 (Range)
Reportedi
^' "#
"9' Reporting Period)
Performed Direction)
(Range)
Measurements 6BE0 Zr-95 All < LLD (1 SE + 1)
All < LLD 0
4 f,E0 Nb-95 All < LLD (1 SE + 1)
All < LLD
,0 3 7E0 Cs-134 All < LLD (1.5E + 1)
All < LLD 0
All < LLD 0
Ba-140 All < LLD 0
All < LLD 0
La-140 5 OE0 All < LLD (1982 only)
(1.5E + 1)
All < LLD 0
Donking Water 6 Gross Beta 7 (2 OEO)
(pCs/I)(1981-1982) w 8 M + 2 (3m 6 3E + 2 7.8E + 2 (6/14)
Site 28, Jenkinsville 0*
(1 OE 4 3)
(6 BE + 2 to 9 BE + 2)
(2 0 mi SE)7 98 +
Gamma Spec (44) 3U (1 bE I O Mn-54 All < LLD 0
2 7E Co-58 All < LLD 0
g5 Fe-59 AH < RD 0
(3 0 + 1) 2 6E 1 Co-60 All < LLD 0
g 3
zn-65 All < LLD 0
(3 0E 1)
Zr-95 All < LtD 0
O SE
)
Table 11 - Radiological Environmental Monitoring Program Summary Prcoperational (Baseline) Summary
~
Medium or Pathway Type and Tota!
r it M AllIMier L cation with Highest Annual Mean Number of sampled (Unit of Number of Detection 1 Locations otr I atio m Nonrouhne Measurement and Analyses (Name, Distance &
Mean2 Mean? (Range)
Reportedl Ocporting Period)
Performed Direction)
(Range)
Measurements
{3 $( }'9)
Nb-95 All < LLD g
3-131 All < LLD 00
,O 2 2E l Cs-134 All < LLD g
i) 0 2
0 Ba-140 All < LLD 6 E+0 0
La-140 4 4E-1 All < LLD (1982 only)
(1.5E + 1) 0 Milk Gamma 5pec (pC /l)
I' I M
(1981-1982) 8-131 All < LLD (1 OE0 All < LLD 0
3 3E0 C5-134 f,,)
(
)
ste 14, Dairy f 0(37/47)
(2 BE0 0
(1 SE + 1)
(2 BE0 to 61EO)
(5.1 mi. W)
(3.7E0 to 9 2EO)
4 La-140 All < LLD All < LLD 0
05 U
Grass (pCi/b g wet)
Gamma 5pec (1981-1982)
(82) 1-131 All < LLD All < LLD 0
6 O
Table 11 - Radiological Environmental Monitoring Program Summary Preoperational (Baseline) Summary
~
r e
Medium or Pathway Type and Total e
M AH W ar L (ation with Highest Annual Mean Number of Sampled (Unit of Number of Dete(tion 2 Lo(ations Measurement and Analyses (Name. Destance &
Mean?
Mean2 (Range)
Reported 3 y
Qeporting Period)
Performed Direction)
(Range)
Measurements 2 7E + 1 Cs-134 All < LLD (8 OE + 1)
All < LLD 0
3 3E + 1 5 OE + 1(13/51)
Site 14. Dairy 5 9E + 1 (5/29) 1.3E + 2 (6/31)
(1.6E + 1 to (t3E + t to
'O (8 0E + 1)
(16E + 1 to 16E + 2)
(51 me W) 16E + 2) 3 4E + 2)
Broadleaf Vegetation (pCi/6 g wet)
Gamma Spec (10)
(1980-1982) 1-131 All < LLD (60 All < LLD 0
Cs-134 A!! < LLD 0
All < LLD 0
21E+1 5.1E + 1 (2/7)
Site 2. Trans tene 3.6E + 1 (1/1)
( ng AH <
D 0
(8 OE + 1)
(1 BE + 1 to 3.6E + 1)
(1.2 mi SW) y Other Vegetation (pC /kg wet)
Gamma Spe(
(37)
(1980-1982)
Cs-134 AH <
(8 OE + 1)
AH < RD 0
E Fish (pCs/kg wet)
Gamma Spe(
(1980-1982)
(92)
Cs-134 All < L1D All < LLD 0
)
18E+1 2 8E + 1(50/71) 5de 24. Recreation 17/23 Cs-137 (t OE + 1 to O
(1.3E + 2)
(1.1E + 1 to 1.0E + 2)
Lake (5.5 mi. N)
(1.2E + 11 19E + 0 1 OE + 2)
Table 11 - Radiological Environmental Monitoring Program Summary Preoperational(Baseline) Summary
~
0 Medium or Pathway Type and Total r Li of Alll@ator Location with Highest Annual Mean Sampled (Unet of Number of Number of Detection 1 Locations Measurement and Analyses (Name, Distance &
Mean?
Mean2 (Range)
Reportedi W
Reporting Pernod)
Performed a 2 Rg)
Direction)
(Range)
Measurements Mn-54 All < LLD All < LLD 0
- O Zn-65 All < LLD E+
All < LLD 0
Sedement (pCi/kg)
Gamma Spec (1980-1982's (24)
Cs-134 All < LLD 5
All < LLD 0
2 4E + 1 1.7E + 2 (12/18) y (1.5E + 2)
(2 6E + 1 to 4.5E + 2)
(2.7 mi.55W) 4.5E + 2) 1.0E + 3)
Table 11 - Radiological Environmental Monitoring Program Summary Preoperational(Baseline) Summary
'e l
9 Footnotes 1.
Values given are MDA values calculated from the program data analyses with maximum acceptable LLD values allowed from NRC guidelines given in parentheses.
2.
Mean and range are based on detectable measurements only. The fractions of detectable measurements at specific locations are indicated in parentheses.
3.
A nontoutine measurement is any confirmed measured level of radioactivity in any environmental medium that exceeds ten times the control station value.
The t aline values are high because of the fallout f:om the Chinese bomb test in 1980. The first set of data reflects the 4.
198) *saseline. The second set of data reflects the 1982 baseline, essentially free of bomb test fallout. The 1982 data covers the period 1/1/82-10/22/82.
S.
Detection sensitivity is approximately 5 mrem /yr (0.5 pR/hr) determined from the analyses of five years of preoperational data.
g l
6.
No (ontrol location was specified for drinking water during the preoperational monitoring period.
7.
Inconclusive data. Refer to the Preoperational Radiological Environmental Monitoring Report.
l l
l l
l l
l Table 11 - Radiological Environmental Monitoring Program Summary l
Preoperational(Baseline) Summary l
~
~ ~ -
~
~~'
'~
~ ~ ' ' ~
~
.,o s Media Sample Month location (Week No.)
Cause for Exception Air Particulate 16 April (13)
Missed LLD due to low sample Gross Beta 14 July (30) volume or incomplete samples 15 May (15) attributed to air sampler June (26) power outages Dosimeter 9
April Lost Milk 16 April (10)
Closing of control dairy Grass 6
January Seasonal Unavailability February March April October December 14 January Seasonal Unavailability February December 16 January Seasonal Unavailability February December Broadleaf Vegetation 5
May through Seasonal Unavailability December 6
May through Seasonal Unavailability October 8
April through Seasonal Unavailability November 18 April Seasonal Unavailability May August September Fish (bream) 22 May Seasonal Unavailability Table 12 1987 Environmental Sampling Program Exceptions 39 f
4
!.*s I
4 i
Airborne gross beta activity measured in air particulate samples collected at i
indicator locations around VCSNS were consistent with preoperational levels and i
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 1987 were 2.4E 2 and 2.5E 2 pCi/m3, i
respectively.
The highest site specific mean activity was measured at indicator location no.13 (North Dam,2.9 mi, NNW) to be 2.6E 2 pCi/m3. The highest mean control activity was also measured to be 2.GE 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 j
charcoal cartridges support the gross beta activity trend. Only natural background activities of Be 7, Ra 226 and X 40 were detected. Minimum detectable activity (MDA) levels for Cs 134, Cs 137 and 1131 were 2.3E 3,2.4E 3 and 3.1E 2 oCi/m3, respectively. The results agree with gaseous effluent releMe data reportec in the 1987 Semiannual Effluent and Waste Disposal Reports for VCSNS. Only 2.6E 4 and 4.5E 4 Ci of particulate and iodine activity was released, respectively. These activity levels are not discernable in environmental media upon consideration of dispersion i
and dilution factors experienced during the releases.
Environmental dosimetry measurements during 1987 did not differ 3
significantly from preoperational measurements over the same seasonal time t
periods. Indicator and control dosimetry measurements also showed no appreciable differences during 1987. The lowest mean exposure rate of 6.2 20.5 pR/hr was 4
observed at sampling location no 58 (residence in Jenkinsville). Sampling location j
no 55 at St. Barnabas Church near Jenkinsville (2.8 mi, E) was the indicator location showing the highest mean exposure rate of 14.311.1 pR/hr. This value compares favorably with the mean exposure rate of 13.612.2 pR/hr measured during the i
j preoperational period and confirms the long term stability of background levels j
measured at this monitoring location. Gaseous effluent release data reported for 1987 indicated a total of 6.3E + 2 Ci of fission and activation gases released from 3
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, t
1 Gamma spectroscopy measurements of surface water samples did not indicate the presence of activated corrosion and most fission products above the i
respective MDA's. All MDA's were less than the required respective LLD's, Analytical results of five surface water samples collected in Monticello and Parr l
t i
Reservoirs during August and September,1987 indicated a mean Cs 137 concentration of 1.0 pCi/ liter. Liquid effluent release data reported for 1987 in the Semiannual Effluent and Waste Disposal Reports indicated a total of 4.9E 1 Ci of i
measureable fission and activated corrosion product activity was released from VCSNS, a level not discernable in environmental media based upon consideration of l
i l
dilution factors experienced during the releases and the detection limits of j
analytical methods. The presence of Cs 137 is, therefore, attributed to residual fallout from atmospheric weapons testing and the 1986 Chernobylincident.
i Tritium analyses of surface water samples during 1987 yielded results which were not noticeably different from preoperational data. All but 3 of 63 indicator l
tritium activity measurements were less than the mean calculated MDA value of
)
4.3E + 2 pCi/ liter. The maximum indicator tritium activity of 6.6E + 2 pCi/ liter was
)
measured in Columbia Canal. Activity levels measured at the indicator locations are i
l
)
4, 40
]
l 1
,.. ~
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 1987 was reported to be 736.4 Ci; a level not discernable in environmental media upon consideration of dilution factors experienced during the releases and the detection limitations of analytical equipment.
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 emittir'g 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. One ground water sampling location (No. 26) was relocated to a location still within the 1 mile radius of VCSNS. Leakage of rainwater into the collection well was rendering the samples unrepresentative of ground water activity.
Most tritium analyses of ground water samples during 1987 yielded results which were less than the mean calculated MDA of 4.3E + 2 pCi/ liter. Two ground water samples collected at the onsite well (No. 26) prior to the relocation indicated the presence of tritium at an average concentration of 6.8E + 2 pCi/ liter; a level consistent with the preoperational mean of 1.5E + 3 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 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 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 5.0E + 2 pCi/ liter was found in Columbia drinking water.
This value is consistent with the preoperational mean activity of 7.8E + 2 pCi/ liter.
The MDA for tritium in drinking water was 4.3:i y 2 pCi/ liter.
l With the exception of Cs-134, gamma spectroscopy measurements of milk samples collected in 1987 were not significantly different from those observed during the preoperational program. Cesium-134 was detected on one occasion in milk collected at an indicator location. The detected activity of 1.4 pCilliter is attributed to residual fallout from the 1586 Cherr obylincident. Naturally occurring 41
e' r
K-40, Ra-266 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 1987 indicated the presence of Be-7 and K-40 in all samples. Detectable levels of Cs-137 were found in indicator and control grass samples. The naturally occurring radionuclides Be 7 and K-40 were detected at levels similar to those found during the preoperational program and in 1987 control data. The observation of Cs-137 activity in indicator and control grass samples is attributed to residual fallout from atmospheric weapons testing and the 1986 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 1987.
Broadleaf vegetation collected from gardens at location no's. 5,6,8 and 18 were the principal food products analyzed during.f 2 0E + 1 pCi/kg in one 1987. Gamma spectroscopy measurements revealed Cs 137 at a concentration o collected at a controllocation Naturally occurring contributions from Ra 226, K 40, Ac-228 and Be-7 were also measured. All radionuclide 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.
Other vegetation sampled in 1987 included squash, corn, 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-134 and Cs-137 were measured in squash collected from the indicator garden location (no.6,1 mi., ESE) at levels of 2.8 and 6.0 pCi/kg, respectively. The level of Cs 137 was consistent with preoperational data and attnbuted to residual fallout from atmospheric weapons testing and the 1986 Chernobylincident. The detection of Cs 134 was attributed to residual fallout from the 1986 Chernobylincident.
Fish species sampled at three indicator and one control location included bass, bream, shad, catfish and carp. Cesium 137 was detected in 22 of 31 samples collected at all four sampling locations and in all five species. The highest mean Cs-137 concentration of 3.1E + 1 pCi/kg was detected in bass. Cesium-134 was detected in 9 of 31 samples collected primarily during the spring of 1987 and only at one indicator location. The highest mean Cs 134 concentration of 9.4 pCi/kg was also found in bass. Detectable levels of Co-58 and Co 60 werc measured in shad and only in samples collected from Parr Reservoir. The highest levels of Co 58 and Co-60 were 4.4E + 1 and 2.2E + 1 pCi/kg, respectively, measured in samples collected in M ay, 1987. The levels of Cs-137 in both control and indicator locations were consistent with preoperational levels and are attributed to residual fallout from atmospheric weapons testing and the 1986 Chernobylincident. The presence of Cs-134 is primanly attributed to residual fallout from the 1986 Chernobylincident and, to a much lesser extent, liquid effluent releases during the first six months of 1987 which included a total of 1.7E-2 Ci of Cs-134. The limitation of Cs-134 from residual fallout to indicator locations may be attributed to a different rate of sediment accumulation in the Broad River at Neal Shoals relative to the indicator locations at Parr Reservoir, Monticello Reservoir and the Recreation Lake. Sedimentation in lakes and reservoirs which characterize the indicator sampling locations is less 42
e
.,, a w l
dynamic relative to that in a river which characteriz ?s the control sam aling location.
Cesium 134 attributed to liquid effluent releases from VCSNS woulc be limited to Parr and Monticello Reservoirs. The detection of Co-58 and Co-60 in Parr Reservoir in the spring of 1987 is attributed to liquid effluent releases of activated corrosion products dunng 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 1.9E-1 and 6.5E-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.
Activity (pCilkg)
Corresponding Calculated Location Radionuclide Annual Total Body Deep Maximum Mean Dose Equivalent (mrem)
Parr Reservoir Co-58 4.4E + 1 4.4E + 1 1.5 E-3 Co 60 2.2E + 1 1.8E + 1 1.8E 3 Total 3.3 E-3 Table 13 - 1987 Activated Corrosion Product Activityin Fish Gamma spectroscopy measurements of sediment samples collected during 1987 also indicated the presence of activated corrosion and fission product activity.
Cesiura-134 and Cs-137 were detected in sediment from all indicator and control locations. Detection of Co 58 and Co 60 was limited to Parr and Monticello Reservoirs. The highest mean concentrations, observed in Parr Reservoir, were 3.5E + 1, 6.4E + 1,1.6E + 1 and 1.7E + 2 pCi/kg for 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 a mean concentration of 8.9E + 1 pCi/kg; a level 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. 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 power demand.
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 l
detected concentrations of Co 58 and Co-60 was assumed. The results are included in Table 14.
O
, v A.
Corresponding Calculated Annual Dose Location Radionuclide Activity (pCi/kg)
Equivalent (mrem)
Maximum Mean Shallow Deep Monticello Co 58 7.4E0 7.4E0 9.3 E-4 8.6 E-4 Reservoir Co 60 7.0E + 1 S.6E + 1 1.8 E-2 1.5 E-2 Total 1.9 E-2 1.6E-2 Parr Reservoir Co 58 S.6E + 1 3.5E + 1 4.6E 3 4.0E-3 Co 60 1.2E + 2 6.4E + 1 2.0E-2 1.8E-2 Total
^
2.SE-2 2.2 E-2 Table 14 - 1987 Activated Corrosion Product Activityin Sediment Conclusion 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 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 1987 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 the only environmental indicators which can be attributed to operation of VCSNS. The presence of all other fission product activity is attributed to residual fallout from the 1986 Chernobyl incident and atmospheric weapons testing. The results of the Radiological Environmental Monitoring Program support the results reported in the Semiannual Effluent and Waste Disposal Reports for VCSNS during 1987. The calculated potential radiation dose to the public attributed to activated corrosion product activity in Broad River media is 2.5E 2 mrem. This figure compares favorably to the 6.3E 2 mrem dose reported in the 1987 Semiannual Effluent and Waste Disposal Reports and is a smc I 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.
44
W joutn Cuonna Electne & G 4 Comoany an A f umn Jenkinsvme SC 2X65 Nuclear Ooerations SCE&G t8" 3 * "
~~
April 27,1988 Dr. J. Nelson Grace Regional Administrator U. S. Nuclear Regulatory Commission Region i:, Suite 2900 101 Marietta Street, N.W.
Atlanta, Georgia 30323
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating Licensing No. NPF-12 Radiological Environmental Monitoring Report
Dear Dr. Grace:
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 Specifications. Also, req uirements 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,
$bw/E D. A. Nauman DCB: DAN:mn Enclosure c:
J. G. Con n elly, J r./O. W. Dixon, Jr./T. C. Nich ols, Jr.
E. C. Roberts W. A. Williams, Jr.
S.R. Hunt General Managers K. E. Nodland L. A. Blue G. O. Percival R. B. Clary R. L. Prevatte J. R. Proper J. B. Knotts, Jr.
R. M. Campbell
. Document Management Branch K. E. Nodland ANI Library J. C. Snelson NSRC W. R. Higgins NPCF J.W.Cox RTS (RG 87009)
C. A. Price File (818.02-2)
W.R.Baehr III d