ML20034B726
| ML20034B726 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/31/1989 |
| From: | Blue L, Bradham O, Dinkins J SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 9004300257 | |
| Download: ML20034B726 (46) | |
Text
q S!uth C r:line Eihtric & Gas C:mpany oll'a S. Bradham -
[,ie-g Je r svit e GC 29065.
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April 25, 1990 f
Mr. S. D. Ebneter Regional Administr6 tor U. S. Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, N.W.
Atlanta, Georgia =30323
Subject:
Virgil C. Summer Nuclear Station-Docket No. 50/395
-Operating Licensing No. NPF-12 Radiological" Environmental Monitoring Report
Dear Mr. Ebneter:
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, requirements as'specified by Section 4.12.3 of the Technical i
Specifications have been included in the report If there are any questions, please call us at your convenience.
4 Very truly yours, n-
- 0. S. Bradham i'
CJM/0SB: led l
Enclosure
+
c:
- 0. W. Dixon, Jr./T. C. Nichols, Jr.
E. C. Roberts i
R. V. Tanner K. E. Nodland General Managers R. L. Prevatte J. J. Hayes, Jr.
J. B. Knotts, Jr.
C. A. Price Document Management Branch R. B. Clary ANI Library J. R. Proper NSRC K. E. Nodland NPCF J. C. Snelson RTS (RG890008)
G. G. Hall File (818.02-2)
S. R. Hunt 9004300257 891231 PDR ADOCK 03000395
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l Virgil C. Summer Environmental 5urveillance Laboratory Jenkinsville, South Carolina-t RADIOLOGtCAL ENVIRONMENTAL MONITORING REPORT VIRGIL C. SUMMER NUCLE AR STATION-1 FOR THE OPERATING PERIOD JANUARY 1,1989 - DECEMBER 31,1989 april 1990 y
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C V. C. SUMMER. NUCLEAR STATION SOUTH CAROLINA ELECTRIC AND GAS COMPANY
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Prepared by:
Reviewed by:
Y 1
a Jerff Durkins, Supervisor L#ldon A: BILb,Wanager.
Radiological Analytical Services Corporate Health Physics and-l Environmental Programs
s 6
Executive Summary l
1.
Results of the 1989 Land Use Census neither indicated significant movement of' critical receptors since the previous annual census, nor identified locations l
where a calculated dose exceeded limits specified in VCSNS Technical Specifications, Section 4.11.2.3.
I 2.
There was no detection of radioactivity in environmental media attributed to gaseous effluent releases from VCSNS.
i 3.
Activated cc,rrosion products attributed to liquid efflue' t releases from VCSNS n
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.-
t 4.
Detection of fission product activity in environmental media is attributed to liquid effluent releases from VCSNS and residual fallout from other sources.
Radiation dose to the general public attributed to.this activity is a small.
fraction of the observed variation in natural background.
t S.
Results of the Radiological Environmental = Monitoring Program substantiate the continuinc3 adequacy of source control at VCSNS and conformance' of-station operat, ion to 10 CFR 50, Appendix I design goals.
I k
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TABLE OF CONTENTS Pace.
Introduction 1
Description of the Radiological Environmental Monitoring Program 2
Results and Discussion 5-Conclusion 40 t
l l
(ii) e
s LIST OF FIGURES FIGURE,
Pace
.1-1 Control Site Locations (50 mile radius around i
the Virgil C. Summer Nuclear Station) 9 1-2 Radiological Monitoring Program LocalIndicator Sample Sites (5 mile radius around Virgil C.
Summer Nuclear Station) 10 1-3 Radiological Monitoring Program LocalIndicator Sample Sites (1 mile radius around Virgil C. Summer Nuclear Station) 11 1
i (iii)
'8 -
g s
LIST OF TABLES' l~
l 6
TABLE Pace-L 1
Monitoring Methods for Critical Radiation Exposure 2
Pathways 2
Results of the August 1989 Land Use Census 3-Verification l
2a Critical Receptors in 1989 Based on FSAR/OLER 4-
)-
Projected Source Terms l
3 Radiological Environmental Monitoring Program 6
Sampling Site Locations 4
Results of the 1989 EPA Intercomparison Program 12 S
Results of the 1989 Intracomparison Program 13 with VCSNS Count Room 6
Summary of the 1989 Intercomparison Program
' 14
- with SCDHEC 7
Results of the Environmental Dosimetry 15 Intercomparison Proaram with the NRC TLD Direct Radiation Monitoring Network 8
Radiological Environmental Monitoring 16 Program Specifications 9
Supplemental Radiological Environmental Monitoring.
21 Program 10 Radiological Environmental Monitoring Program 23 Summary 11 Radiological Environmental Monitoring Program '
29 Preoperational(Baseline) Summary l
12 Environmental Sampling Program Exceptions 36 r
13 1989 Activated Corrosion Product Activityin Sediment 40 l
(iv)
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4
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i 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 L
the Monticello Reservoir near Jenkinsville, South Carolina and approximately 26 I
miles northwest of Columbia. VCSNS achieved initial criticality on October 22, t
1982, reached 50% power December 12,1982 and 100% power June -10,= 1983 following steam generator feedwater modifications. VCSNS started its fifth refueling on March 24,1990. A 65 day refueling outage is planned.-
i VCSNS is used in conjunction with the adjacent Fairfield Pumped Storage Facility (FPSF) which consists of eight reversible pump turbinc units of 60 MWe capacity each. Dunng periods of off peak power demand,' base load generating
. capacity is used-to pump water from Parr Reservoir to.Monticello Reservoir.
Monticello~ Reservoir has a surface area of approximately 6800 acres and:lles 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 t
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 a concerns are predominant, but makeup less than 50% of the land area.gricultural.
The main industrial actwity is concentrated around Columbia and is generally greater than 20 miles from VCSNS.
Liquid effluents from VCSNS are released into the-Monticello/Parr Reservoirs-at two discharge points: the Circulating Water Discharge Canal (CWDC) and the FPSF Penstocks. Un 3rocessed steam generator blowdown and non nuclear drains are released to t1e 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 Environmental Monitoring Program at VCSNS. This report summarizes the results of the Radiological Environmental Monitoring Program conducted during 1989. Data trends, control / indicator and preoperational/
operational data mtercomparisons and other data interpretations are presented.
1
s i Description of the Radioloaical Environmental _Monitorina Program 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 l
- 1. To analyze selected samples in important anticipated pathways.for the qualification and..quantification of radionuclides released to the environment surrounding.
- 2. To establish correlations between levels of environmental radioactivity and radioactive effluents from VCSNS 1
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 environmentali 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-aathways of these effluents which may lead to radiation exposure of the public,.
aased on existing demography, are summarized in Table 1.
i Re ease ype 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 -
a 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 Pathways 2
1
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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 frec uencies,-
sample locations and types of samples. These criteria were used to estab ish 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 1989 are included -
in Table 2. A verification of the critical receptor (maximum exposed individual) in each sector around VCSNS based on 1989 meteorological data, VCSNS Final Safety i
Analysis Report and VCSNS Operatinci License Environmental Report source terms is included in Table 2a.
Nearest Nearest Nearest No, Sector Residence Miles Garden -
Miles Cattle Milked Miles N
Martin -
3.8 Fuller 40 Robinson 0
3.3 d
NNE Crumblin.
2.9 Crumblin 2.9 Robinson 0
3.3 NE-Stone 2.1 Robinson 2.9 Stone 0
2.1 ENE Johnson 1.4 Ginyard (B) -
1.6 Martin.
0 1.6 E
Martin (A)
' 1.5 Boyd (B) 1.8 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
Yarborough (A) 3.4 Eargle 3.9 Smith 0
3.8 SSW Weber
. 3.2 Ariail(B) 3.4 Miller 0
3.0 l
SW Davis 3.1 Nichols 3.3 Miller 0
2.8 W5W Hope 3.1 Eargle (B) 3.3 Livingston 0
1.9 -
W Amick 2.5 Smith 2.5 Livingston 0
2.1 WNW Seeby 2.6 Williams 4.5 Williams 0
4.5 l
NW Wright 3.9 Cole 4.1 Cole 0
4.1
,3 NNW.
March 2.9 March 3.0 March.
0 3.0 1
l.
A.
Changein closest residence B.
Change in cfosest garden Table 2 - Results of the August 1989 Land Use Census Verification The most notable census items are: the nearest resident and garden are still located in the ESE sector at 1.1 miles; there were no milking animals being milked within 5 miles of V. C. Summer Nuclear Station at the time of the census; the Radiological Analytical Services environmental garden is located ESE 1.0 miles from the plant, all other gardens analyzed are at local residence.
3
1975 METEOROLOGICAL DAT A 1989 ME TE OROLOGR VAT A DISTANCE SEfTOR (MdeO NAME PATHWAY DOSE DOSE X/Q D/Q RATE X/Q D/Q RATE l
mrem /y mrem /y N
33 Robinson BeetlC) 2 OE -0 7 9 sea 0 1 DE 01 3 5E 07 91E 10 1 OE o1 -
N 38 Martin Res 15E 07 7 0E-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 17E 01 NNE 29 Crumbbn Fes'Ga r 3 2E 07 1 SE 09 12E 02 3 9E 07 12E-09 3 3E 01 NNF 36 R Rob.nson' Res. Gar / Beef 2 IE 07 8 9E 10 3 $E.01(O 2 Si 07 7 2E 10 2 9E 01(E)
NE 21 Stone Resiseef 6 BE 07 3 6E 09 3 8E 01 11E u6 2 BE 09 3 2E 01 NE 29 J Robinson' RevGar' Beef 3 4E 07 17E 09 t,1E 01 5 SE.07 1 JE 09 5 OE 01
[NE 14 Johnson Res 1 AE 06 8 OE.09 5 4E 02 2 5E 06 7 DE-09 9 3E 02 ENE 16 Gin erd *(8)
Res/Ga r 11E 06 58E 09 15E + 00 17E 06 5 1E-09 14E
- 00 v
ENE 16 R Martin ResBeef 11E 06 5 BE 09 0 ?E 01 19E 06 51E 09 S BE 01 E
15 W Martin (A)
Res 1 1E 06 5 6E 09 4 2E-02 17E 06 4 7E 09 6 3E-02 E
18 Boyd'(8)
Res Gar: Beef 74t 07 3 6E 09 14E + 00(H) 12E -06 3 OE 09 12E + 00(H) i i
ESE 11 Jr Martin'{D)
MevGar 2 2t ob 8 4E 09 22E 00 21E 06 6 BE 09 19E + 00 SE 15 White Res 16E 06 5 BE-09 6 DE 02 6 9i 07 2 4E 09 2 6E-02 SE 15 Summer' Res/Ga c 10E 06 5 BE-09 16E + 00 6 9E 07 2 4E 09 6 SE 01 SSE 25 Crumpton Res 3 SE 07 12E 09 13 E-02 17E 07 61E 10 6 4E-03 SSE 27 Shealy' R es' Gar 3 0E 07 10E-09 2 7E -01 15E 07 5 1 E-10 14E 01 5
38 Y ar borough Beef (C) 18E 07 3 BE 10 4 SE-02 91 E-08 3 4E 10 3 7E 02 5
34 Ya r borough (A)
Res 21E 07 5 OE 10 7 BE 03 12E 07 4 4E 10 4 SE 03 5
39 E a rq;e '
ResGar 17E.07 3 7E 10 1 1 E 01 8 6E 08 3 2E 10 8 6E 02 SS A 32 W eber Res 2 3E 07 7 SE 10 8 6E 03 16E 07 7 4E 10 61E-03 55W 34 A ria d'{ B)
RetGar 2 OE-07 6 4E 10 17E 01 14E-07 6 4E 10 17E 01
$$W 34 Meer RetBeef 2 0E 07 6 4E 10 9 4E 02(F) 14E 07 6 4E 10 91E 02(F) 5W 31 Da vis Res 2 9E 07 12E 09 11E 02 16E 07 11E 09 6 3E 03 SW 33 N< hon
- RetGar 2 6E 07 10E 09 2 7E 01 1 4 E-07 9 5E 10 2 4E 01 5A 33 Miher Res 2 6E 07 1 OE-09 '
9 BE 030) 14E 07 9 5E i0 5 5E 030, W5A 19 Livingston Beef (C) 6 4E-07 3 2E 09 3 4E 01 4 2E 07 2 BE 09 3 OE 01 W5W 31 Hope Res 2 3E-07 10E 09 8 7E 03 14E 07 8 7E 10 5 SE 03 W5W 33 E a rq 6e '
Res/ Gar 2 OE 07 8 7E.10 2 3E 01 12 E-07 7 SE 10 19E 01 W
25 A mi(6 Res 2 5E 07 1 1E 09 9 SE-03 2 4E 07 9 2E-10 9 IE 03 W
25 Smith Res' Gar 2 SE 07 11E 09 2 9E -01 2 4E 07 9 2E 10 2 SE 01 W
27 L mngston
- RestGar Beef (G) 22E07 9 3E 10 4 2E 010) 2 OE 07 7 7E 10 3 5E 010)
WNW 26 Seeby Res 2 OE 07 8 4E 10 7 6E 03 1 BE 07 5 6E-10 6 7E 03 WNW 45 Wdhams' Res/ Gar Beef 6 6E-08 2 5E 10 9 2E 02 5 8E 08 16E 10 6 OE 02 NW 39 Wrig ht Res 1 I E-01 4 6E-10 4 2E 03 15E 07 3 SE-10 5 6E-03 NW 41 Cole '
RevGar beef 9 2E 08 4 0E 10 15E 01 13 E -07 31E 10 12E 01 NNW 29 J March Res 19E 07 11E 09 7 4E-03 4 6E 07 11E 09 17E 02 NNW 30 F March
- RevGar8eet 18E 07 9 7E 10 3 5E 01 4 3E 07 10E 09 3 9E 01 Denotes Critical Receptor f or the Sector.
(G)
Cattle assumed to grare at 2.1 mdes W.
(A)
Change in Closest Residence f or the Sector (H)
Cattle assumed to grare at 17 miles E.
(f rom 1988 Census)
(1)
Assuming Livingston eats beef from his herd in the W5W.
8)
Change m closest garden.
l 1C)
Residence assumed in (akulations.
Livingston's dose rate would be as follows:
56 mRemly ('75 EQ,D/Q). 48 mRemly('89 X/Q, D<Q).
0)
Masemum enposed individual f or the site -
(J)
Assuming Miller eats beef f rom has herd in the $$W, Miller's dose rate i
iE)
Cattle assumed to grate at 3.3 miles NNE.
would be as follows;.096 mrem /y (*75 X/Q, D/Q), 091 mrem'y ('89 UQ, (F)
Cattle assumed to grate at 3.0 miles $5W.
O 'Q).
Table 2a - Critical Receptors in 1989 Based on FSAR/OLER Projected Source Terms 4
i
t 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 inciease in local environmental 4
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 12 and 1-3. Monitoring sites at distances greater than 10 miles from the plant are shown in Figure 11 and are indicative of conditions away from plant mfluence.
Information is at specific locations. gained through multiple types of sampling and measurements Several multiple sampling combinations are in use around the VCSNS. 'All air sampling _ locations are also environmental-dosimetry monitoring locatiorn At these points airborne plant effluents are monitored for gamma immersion dose (noble gases), airborne particulates and radioiodine. Three of these locations have additional complementary sampling / measurement pathways for monitoring plant effluents. Sampling locations 6 (1.0 mi ESE) and 8 (1.9 mi ENE) have broadleaf 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 5) also has a broadleaf vegetation garden for monitoring the gaseous effluent deposition and ingestion pathway at a' control location.
Liquid effluents are monitored through three pathways (fish, bottom-sediment and surface water) at the three most nrobable affected bodies of water -
around the plant: Site 21, Parr Reservoir (2.7 mi d5W); Site 23, Monticello Reservoir (0.5 mi ESE); and Site 24, Recreation Lake (5.5 mi N). The control location for li effluent comparisons is at Site 22, Neal Shoals (30.0 mi NNW) on the Broad River. quid The Radiological Environmental Monitoring Program participated in four laboratory intercomparison.
Results of the 1989 EPA Intercomparison Program are. programs during 1989. included in Table 4..R 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 verif i
generated and reported by the program.y the technical credibility of analytical data i
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 1989 are summarized in Table 10.
For comparative purposes preoperational data is summarized in Table 11. Certain samples were not collected during 1989 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 Technica15pecification requirements.
5
, Site Distancel Sample No.
Description (Miles)-
Direction 2 Type (s)3 '
1 Borrow Pat 1.2 182.0 5 DM 2
Transmission Line 1.2 225.0 SW AP.RI.DM 3
Faring Range 1.2 270.0 W DM 4
Fairfield Hydro 1.2 289.5 WNW DM S
Transmission Line Entrance 0.9 145.5 5E AP.RI.DM 7
6 Env. Lab Garden 1.0 104.0 ESE AP,RI.DM GR,GA 7
Monticello Peninsula 1.2 83 0 E DM 8
Monticello Res 5 of Rd 224 1.5 63.0 ENE AP,DM,G A 9
Ball Park 2.2 44.0 NE DM 10 Meteorological Tower No.2 2.5 25.5 NNE AP.Rl,DM 11 Residence 3.3 80N DM 12 Old Hwy 99 4.2 349.0 N DM 13 North Dam 2.9 334.0 NNW AP,DM 14 Dairy 6.3 2 70.0 W -
{
15 Parr Village 2.5 204.0 55W DM 16 Dairy 28.0 281.0 W DM,GW,M K,G R 17 Columbia Water Works 24.7 144.0 5 E AP,RI,DM,5W,DW,85 18 Residence / Pane 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,F H,85 22 Neal Shoals 30 0 343.0 NNW 5W,F H,85 23 Discharge Canal (Mont. Res-)_
0.5 104.5 ESE SW,F H,85 24 Recreation Lake 5.5 2.0 N.
SW,FH,85 25 Fairfield Pumped Storage (Monticello Res.)
0.9 302.0 WNW-SW 26 On Site Well(P2) 460Ft 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 DO 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 35 Unnamed Circle Road off Hwy 215 4.8 137.5 5E DQ 36 Woods Behind Jenk. Post Ofi[ce 3.1 151.5 SSE DO 37 Residence 4.9 305.5 NW DQ l-38 FPSF Trailrace 1.3 280.0 W B5 39 LMWTF 14.0 168.0 55E DW 41 End of Catwalk 3.9 185.05 00 42 Store 3.9 199.0 55W 00 43 Hwy 176 and Rd 435 5.2 236.0 5W DQ Table 3 - Sampling Site Locations 6
A
- Si(e-Distance 1 Sample
~ t No.
Description -
(Miles)
Direction 2 Type (s)3 c
44 Rd 28 at Cannon's Creek 2.9 255.5 WSW 00 f
45 Rd 33 at Pomaria 5.9 253.0 WSW DQ i
46 Rd 28 at Heller's Creek 3.7 292.0 WNW DQ 47 Fairfield Tailrace 1.0 316.0 NW DQ L
48 Cemetary 2.3 318.5 NW DQ 49 North Rd 383 4.0 332.5 NNW DQ 50 New Rd 99 (West Shore) 5.5 1.0 N DQ 51 New Rd 99 (East Shore) 5.5 5.0 N DQ 52 Monticello(Rd 11) 3.9 14.0 NNE DO 53 Rd 359 3.0 48.0 NE DQ 54 Jenkinsville School 1.7 73.0 ENE DQ 55 St. Barnabas Church 2.8 94.0 E DQ 56 Old Jenkinsville Diner 2.0 144.0 5 E DO 57 Residence / Highway 213 and 215 2.7 146.0 S E DO 58 Residence 2.5 158.0 55E DO 59 Nuclear Trainin0 Center (EOF)5 2.4 168.0 55 E DQ,AP 60 Rd 98 near Rd 28 3.5 275.0 W DO 61 Switchyard 5E Entrance to Plant 0.1 180.0 5 DM 62 East of Training Bldg.
0.13 220.0 5W DM i
63 East of Daniel's Office 0.17 270.0 W DM 64 Riprap W of Intake 0.13 338.5 NNW DM.85 65 Guard Tower 0.13 22.5 NNE DM85 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 00N DM 71 Temperature Buoy on Monticello Res-54 30N DM 72 Yard Drain Outfall 0.4 146.0 S E SW,B5 73 Yard Drain Outfall 0.4 270 0 W SW.85 74 Yard Drain Outf all 0.5 246 0 WSW SW.85 75 On Site Well 265 ft.
270.0 W GW 76 On Site Well 2 70 ft.
330.0 NNW GW 84 Congaree River 54.2 135.0 5E B5 85 Congaree River 53.8 135.0 5E B5 87 Lake Marion 72.0 138.0 5E B5 88 Lake Marion 72.0 138.0 5E B5 l
i l
Table 3 - Sampling Site Locations (continued) l i
7
+
y
+
,.we,
e.
e
r 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 trt.e north south line through' center of reactor containment building.
l 3.
Sample Types:
AP = Air Particulate-DW = Drinking Water RI = Air Radioiodine MK = Milk-l DM = MonthlyTLD GR = Grass (Forage)
DQ = Quarterly TLD GA = Garden
' SW = Surface Water FH = Fish GW = Ground Water -
BS = Bottom Sediment 1
l l
l l-1 i.
Table 3 - Sampling Site Locations (continued) 8
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Comp::ris;n Study EPA Valu2 Laboratory Agree-(Measuramsnt Unit) Date Nuclido ( 10) Results ( t lo) ment - ~' Air filter (pCi/ filter) 3/89 beta. 62 (5) 74 (1) Yes-Cs-137 20(5) 23(0) Yes' 8/89 beta N/A N/A-Yes Cs 137-10(5) 10(0) Yes Gamma in Water (pCi/ liter) 2/89 Cr 51 235(24) 222(13) Yes Co-60 10(5) 11(1) Yes =; 2n 65 159(16) 159(6) Yes Ru 106-178(18) 160(12) Yes i Cs-134 10(5) 10(1) Yes Cs-137 10 (5)- 10(1) Yes 6/89 Ba-133 49(5) 53(2) Yes l Co 60 31(5) ' 32 (2). Yes - 2n 65.. 165(17) 168 (4) Yes Ru-106 - 128(13) 131(10) Yes Cs 134 39(5) 39(2) Yes ? Cs 137 20(5) 21(1) Yes 1 10/89 Ba 133 59(6) 65(2) - Yes Co 60-30(5) 31 (1) Yes 2n-65 129(13) 133 (4) Yes - Ru 106 161(16) 163(12)- Yes I-Cs134 29(5) 29(2) Yes l Cs 137 59(5) 64 (2) Yes Gross Beta in Water ~ (pCilliter) 1/89 beta 4(5) 5(0) Yes 5/89 beta 50(5) 45(1) Yes 9/89 beta 6 (5)' 7 (1) Yes lodine in Water (pCi/ liter) 2/89 l-131 106(11) 1.11(3) Yes 8/89 l-131 83(8) 86(2) Yes Laboratory Blind (pCi/ liter) 4/89 beta 57(5) 44 (1), .Yes Cs-134 20(5) 20 (2) - Yes Cs-137 20(5) 20(2) Yes 10/89 beta 32(5) 28(1) Yes Cs 134 5 (5) 4(1) Yes Cs-137 5 (5) 5 (1) Yes Radionuclides in Milk (pCi/ liter) 4/89 l131 4 (4) 5 (1) Yes Cs 137 50(5) 51(2) Yes-Tritium in Water (pCilliter) 2/89 H-3 ~ 2754 (356) 2261(235) Yes 6/89 H-3 4503(450) 3825(250) Yes 10/89 H3 3496(364) 2984(221) Yes Table 4 - Results of 1989 EPA intercomparison Program 12
Comparison Stud Labor tory 2nd Lab Agree-(Measurement Un t) Date Nuclide Results - Results(1) ment Tritium (pCi/ml) (Analytics) 2/89 H3 4.94E-4 5.99E 5 Yes (VCSNS) 4/89 H 3 (undistilled) 1.23 E-1 1.11 E 1 Yes (VCSNS) 4/89 H 3 (distilled) 1.19 E-1 1.02 E-1 Yes Gross Beta Liquid (pCi/ml) 2/89 N/A 7.61 E-4 7.90E-2 Yes Gross Alpha Liquid (pCi/ml) 2/89 N/A 1.43 E-4 2.31 E-4 Yes Charcoal Cannister (pCi/ml) 5/89 l-131 2.83E-1 2.64E-1 Yes Gross Beta (pCi/ml) 8/89 N/A 1.43E 2 1.36E 2 Yes Gross Alpha (pCi/ml) 8/89 N/A 1.46E 3 1.97 E-3 Yes Gamma Isotopic Liquid 2/89 Ce-144 2.04E-2 1.85 E-2 Yes (pCi/ml) Ce-141 1.36E 2 1.30E-2 Yes Cr 51 3.22E 2 3.3 5 E-2 Yes Cs 134 7.04E 3 7.25 E-3 Yes Cs 137 8.80E-3 8.48E 3 Yes Co-58 7.95E 3 7.91 E 3 Yes Mn 54 8.90E 3 8.67E-3 Yes Fe 59 1.17E 2 1.14 E-2 Yes 2n 65 1.51 E-2 1.49E-2 Yes Co 60 1.19 E-2 1.19 E-2 Yes 8/89 Ce 144 1.08E-2 1.11 E 2 Yes Ce-141 1.34E-2 1.34E 2 Yes Cr 51 4.46E-2 4.32E 2 Yes Cs 134 6.05 E-3 6.27E 3 Yes Cs-137 1.17 E-2 1.10 E-2 Yes Co-58 4.38E-3 4.35E 3 Yes Mn 54 1.01 E-2 9.56E-3 Yes Fe 59 1.50E-2 1.41 E-2 Yes 2n 65 1.74E-2 1.63E 2 Yes Co-60 1.58E 2 1.58E-2 Yes NRC Liquid (pCi/ml) 7/89 H-3 (distilled) 1.98E 5 2.69E-5 No2 Gamma Isotopic Filter (pCi/ml) 8/89 Ce 144 1.08E 2 1.11 E 2 Yes Ce 141 1.34E 2 1.34E-2 Yes Cr 51 4.46E 2 4.32 E-2 Yes Cs-134 6.05E 3 6.27E 3 Yes Cs-137 1.17E 2 1.10E 2 Yes Co-58 4.38E-3 4.3 5 E-3 Yes Mn-54 1.01 E-2 9.56E-3 Yes Fe 59 1.50E-2 1.41E 2 Yes 2n 65 1.74E 2 1.63 E-2 Yes Co 60 1.58E-2 1.58 E-2 Yes Silver Zeolite Cannister (pCi/ml) 10/89 l-131 2.85 E-1 2.67E 1 Yes Gas Sample (pCi/ml) 10/89 Xe-133 8.64E0 8.19E0 Yes Kr-85 9.38E + 1 8.67E + 1 Yes (1) Independent Laboratory was Analytics,Inc. except for some tritium intercomparisons. (2) M:mfacturer's specifications for initial setup of a new tritium analyzer resulted in a low bias of ~30%. Adjustments have been made to eliminate this bias. Table 5 - Results of 1989 Intercomparison Program with Independent Lab 13
t -i 1 I b** Pathway (Units) Frequency Nuclidel toc 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.17 Monthly Gross Beta lodine [ Mixed Gamma l L Milk (pCi/ liter) No.14 Monthly Mixed Gamma Sediment (pCilkg) No. 23 - Semiannually Mixed Gamma-Fish (pCi/kg) No 23 Semiannually Mixed Gamma Vegetation (pCi/kg) No.6 Semiannually Mixed Gamma-l l l 1 1. Intercomparison results were not yet available for publication in this report. l Results will be reported by SCDHEC. t l Table 6 - Summary of 1989 intercomparison Program with South Carolina Department of Health and Environmental Controls 14
l ~ i 1988 FOURTH QUARTER - 1989 FIRST QUARTER 1989 SECOND QUARTER 1989 THIRD QUARTER NRC TLD LABORA-RESULTS (uR/hr) RESULTS (uR/hr) RESULT 5 (uR/hr) RESOLT5(uR/hr) STATION TORY TLD NO. STATION NO. L bora-Percent Labora-Percent '#^ NRC NRC NRC NRC tory Difference tory Difference tory Dif ference tory' Differen(e i 1 42 10.7 6.9 -35.5 9.5 7.1 -25.3 11.2 7.1 -36.6 10.0 6.9 -31.0 i 2 6 8.6 8.1 -5.8 9.7 7.9 -18.6 8.9 8.1 -9.0 9.4 7.9 -16.0 5 54 9.5 10.9 14.7 10.7 11.6 8.4 9.5 11.5 21.0 11.0 11.3 3.0. h 7 '53 14.2 11.7 -17.6 12.8 12.0- -6.2 12.1 13.1 11.7 -10.7 9 '52 12.9 12.8 -0.8 12.4 13.2 12.4 -6.1 .12.1 12.3 1.8 g 11
- 12 9.7 8.9 7.9 8.6 8.9 8.3 8.5 2.0 13 13 L11.3 12.1 7.1 10.6 12.0 13.2 12.4 11.6'
-6.4 11.3 11.8 4.9 4 14 '44 9.7 6.7. -30.9 10.4 6.3 -39.4 10.0 6.61 -34.0 10.6 5.9 44.1-i 19
- S6 9.4 8.5
-9.6 9.5 8.5 -10.5 9.9 8.7 -12.1 9.4 : 8.2 - -12.8 t 22 58 8.4 6.0 -28.6 - 7.7 6.3 -18.2 9.6 6.2 -35.4 7.7 5.3 : -18.1 24' 41 8.9 9.0 1.1 8.9 9.4 5.6 9.7 9.3 -4.1 9.4 I 29
- 60 10.8 10.7-0.9 11.4 10.8
-5.3 11.3 11.4 0.9 11.2 10.7 -4.5 30 46 11.5 8.7 -24.3 15.0 9.1 -39.3 9.2 - 8.9
- Co. located dosimeters within 10 feet of NRC dosimeter.
Table 7 - Results of Environmental Dosimetry intercomparison with NRC TLD Direct Radiation Monitoring Network - 4 d + - - s s-
L Exposure Criteria for Selection Sampling and Sample Type & Frequencyc and/or Sample f 5 mple Number & Location Collection Frequency Location of Analysis AIRBORNE: l 1. Pditiculate A) 3 Indicator samples to be taken at locations (in Continuous sampler operation 2 Gross beta following filter dif ferent sectors) beyond but as close to the with weekly collection. 5 change; monthly composite j exclusion boundary as practicable where the 10 (by location) for gamma t highest ofIsite sectorial ground level isotopic. con <entrations are anticipated. B) 1 Indicator sarnple to be taken in the sector Continuous sampler operation 6 Gross beta following filter. . beyond but as close to the exclusion boundary with weekly collection. change; monthly (omposite as practicable correspondmg to the residence (by location) for gamma having the highest anticipated offsite ground isotopic. level concentration or dose. 1 C) 1 Indicator samp!e to be taken at the location Continuous sampler operation 14 Gross beta following filter. of one of the dairies most likely to be affected. with weekly collection (hange; monthly composite (by location) for gamma isotopic. I os D) 1 Control sample to be taken at a location at Continuous sampler operation 17 Gross beta following filter least 10 air miles from the site and not in the with weekly collection. change; monthly composite most prevalent wind directions. (bylocation) for gamma isotopic. II. Radiciodine A) 3 Indicator samples to be taken at two locations Continuous sampler operation 2 Gamma Isotopic for lodine - as given in 1(A) above. with weekly canister collection. 5 131 10 I B) 1 Indicator sample to be taken at the location Continuous sampler operation 6 Gamma isotopic for Iodine as given in 1(B) above. with weekly canister collection.- 131 C) 1 Indicator sample to be taken at the location Continuous sampler operation 14 Gamma Isotopic for lodine as given in 1(C) above. with weekly canister collection. 131 D) 1 Control sample to be taken at a location Continuous sampler operation 17 Gamma isotopic for lodine similar in nature to I(E) above. with weekly canister collection. 131 i.. Table 8 - Radiological Environmental Monitoring Program Specifications i 4 a - +, w m s ,ww
E osure Criteria for Selection Sampling and Sample Type & Frequency p and/or 5 mple of Sample Number & Location Collection Frequency Location of Analysis
- lli. Direct A) 13 indicator stations to form an inner ring of Monthly or quarterly exchange; 1,2,3,4, Gamma dose monthly or stations in the 13 accessible sectors within 1 to 2 two or more dosimeters at each 5,6,7,8, quart erly.
milesof the plant. location. 9,10,29, 30,47 8) 16 Indicator stations to form an inner ring of Monthly or quarterly enhange; 12.14.32, Gamma dose monthly or stations in the 16 accessible sectors within 3 to 5 two or more dosimeters at each 33,34,35 quarterly. miles of the plant. location. 36,37,41, 42,43,45; 46,49, 53,55 C) 20 Stations to be placed in special mterest areas Monthly or quarterly enhange; 11,13,15, Gamma dose monthly or such as population centers, nearby eesidences, two or more dosimeters at each 16,17,18, quarterly. schools and in 2 or 3 areas to serve as controls. location. 19,20,31, 44,48,50, 51,52,54, ~y 56,57,58 59,60 WATERBORNE: IV. Surface Water A) 1 fndicator sample downstream to be taken at a Time composite samples with 21. Gamma isotopic monthly location which allows for mixing and dilution in collection every month. with quarterly composite (by. 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 with 22 Gamma isotopic monthly the receiving river sufficiently far upstream collection every month. with quarterly composite (by such that no effects of pumped storage location)or monthly sample operation are anticipated. to be analyzed for tritium. C) 1 Indicator sample from a location immediately Time composite samples with 17 Gamma isotopic monthly upstream of the nearest downstream muniopal collection every month. with quarterly composite (by water supply.. loc 71on) or monthly sample to tyc analyzed for tritium. ' Table 8 - Radiological Environmental Monitoring Program Specifications c _
E sure p Criteria for Selection Sampling and Sample Type & Frequerycy i and/or 5 mple f S mple Number & Location Collection Fregt:ency Location of Analysis WATERBORNE: IV. Surface Water D) 1 Indicator sample to be taken in the upper Time composite samples with 23 Gamma isotopic monthly - (continued) reservoir of the pumped storage facility. collection every month. with quarterly composite (by-location) or monthly sample to be analyzed for tritium. E) 1 Indicator sample to be taken in the upper Grab sampling monthly 24 Gamma isotopic monthly. reservoir's non-fluctuating recreational area. with quarterly composite (by location) or monthly sample to be analyzed for tritium. F) 1 Control sample to be taken at a location on a Grab sampling monthly 18 Gamma isotopic monthly separate unaf fected watershed reservoir. with quarterly composite (by - location) or monthly sample to be analyzed for tritium : l V. Ground Water A) 2 indicator samples to be taken within the Quarterly grab sampling 26 Gamma isotopic and tritium exclusion boundary and in the direction of 27 analyses quarterly. 5 potentia!!y af fected ground water supplies-B) 1 Controf sample from unaffected location. Quarterly grab sampling 16 Gamma isotopic and tritium analyses quarterly. VI. Drinking A) 1 Indicator sample from a nearby public ground Monthly grab sampling 28 Monthly gamma isotopic, Water water supply source. gross beta and tritium analyses. B) 1 Indicator (finished water) sample from the Monthly composite sampling. 17 Monthly gamma isotopic, nearest downstream water supply. gross beta and tritium analyses. C) 1 Control (finished water) sample from the Monthly composite sampling. 39 Monthly gamma isotopic, nearest unaf fected public water supply. gross beta and tritium j analyses. 4 Table 8 - Radiological Environmental Monitoring Program Specifications
Ex s re pa Criteria for Selection Sampling and Sample Type & Frequency and/or Sample of Sample Number & Location Collection Frequency location of Analysis INGESTION: Vll. Milk A) Samples from milking animals in 3 locations Biweekly grab sample. Tee. w a Gamma isotopic and 1-131 within 5 km having the highest dose potential. analysis biweekly. .+ e If there are none then 1 sample from milking animalsin each of 3 areas between 5 to 8 km m.o distance where doses are calculated to be .a greater than 1 mrem per year. B) 1 Control sample to be taken at the location of Beweekly grab sample. 16 Gamma isotopic and I-131 a a dairy > 20 miles distance and not in the most prevalent wind direction. analysis biweekly. C) 1 Indicator grass (forage) sample to be taken at Monthly when available 6 Gamma isotopic. 4 one of the locations beyond but as close to the exclusion boundary as practicable where the highest offsite sectoria19round level concentrations are anticipated. D) 1 Indicator grass (forage) sample to be taken at Monthly when available 3.t w a Gamma isotopic. the location of Vil(A) above when animals are .a on pasture. .,0.,,.o. 1 e u.a E) 1 Control grass (forage) sample to be taken at Monthly when available 16 Gamma isotopic. 2 the location of Vil(B) above. Vlli. Food A) Two samples of broadleaf vegetation grown in Monthly when available. 6 Gamma Isotopic on edible Products 1 location of specialinterest and 1 in the near-8 portion est offsite location of highest calculated annual average ground level D/Q if milk sampling is not performed within 3 km or if milk sampling is not performed at a location within 5-10 km where the doses are calculated to be greater than 1 mrem /yr. B) 1 Control sample for the same foods in Vill (A) Same as for Vill (A), as appro-18 Gamma Isotopic on edit:1e taken at a location at least 10 miles distance priate. portion. and not in the most prevalent wind direction. . I l a Table 8 - Radiological Environmental Monitoring Program Specifications 4 g. P-1 n* V 9' '+'- r -h g m 9-r e e 4-
Ex(S Criteria for Selection Sampling and Sample Type & Frequerlcy. pa and/or Sample of 5 mple Number & Lecation Collection Frequency Location of Analysis IX. Fish A) 1 Indicator sample to be taken at a location in Semiannual collection of the . 23 Gamma isotopic on edible I the upper reservoir. followingspecietypesif avail-portions semiannually. able; bass; bream, crappie; catfish, cprp; forage fish (shad). B) 1 Indicator sample to be taken at a location in Semiannualcollectionof the 21 Gamma isotopic on edible the lower reservoir. following specie typesif avail-portions semiannually. able: bass; bream,(rappie; catfish, carp; forage fish (shad). C) 1 Indicator sample to be taken at a location in Semiannualcollectionof the 24 Gamma isotopic on edible the upper reservoir's non-fluctuating fo!!owing specie types if avail-portions semiannually. recreational area. able: bass; bream, crappie; catfish, carp; forage fish (shad). D) 1 Controf sample to be talien at a location on Semiannualcollectionof the 22 Gamma isotopic on edible the receiving river su f ficiently far upstream following specie types if avail-portions semiannually. such that no ef fects of pumped storage able; bass; bream, crappie; operation are anticipated. catfish, carp; forage fish (shad). AQUATIC: X. Sediment A) 1 Indicator sample to be taken at a location in Semiannual grab sample. 23' Gamma isotopic. the upper reservoir. B) 1 Indicator sample to be taken at a location in Semiannual grab sample. 24 Gamma isotopic. the upper reservoir's non-fluctuating recrea-tional area. C) 1 Indicator sample to be taken on the shoreline. Semiannual grab sample. 21 Gamma isotopic. of the lower reservoir. D) 1 Control samp!e to be taken at a location on Semiannual grab sample. 22 Gamma isotopic. the receiving river sufficiently far upstream - such that no ef fects of pumped storage opera-tion are anticipated. f Table 8 - Radiological Environmental Monitoring Program 5pecifications ^~ ~ ^ " ~ ~ ~ ^ ^ ~ ^
Ex Criteria for Selection Sampling and Sample Type & Frequency p a and/or Sample f Sample Number & Location Collection Frequency Location of Analysis AIRBORNE: 1. Particulate E) 3 Indicator sampies to be tak en at locations (en Contmuous sa. wier 8 Gross beta following filter different sectors) beyond but as close to the operation with weekly 13 (hange; Monthly Composite exclusion boundary as practicable and nearer collection. 59 (by location) for gamma to the plant than the nearest (ritical receptor isotopic. for the (bosen sector. Ill. Direct D) 8 Staticms to be placed within the exclusion Monthly or quarterly 61,62 Gamma dose monthly or boundary (Specia15tudy). exchange; two or more 63,64 quarterly. dosimeters at each 65,66 location. 67,68 E) 3 Stations to be placed on buoys on Monticello Monthly or quarterfy 69 Gamma dose monthly or l Reservoir (Background Study). exchange; two or more 70 quarterly. dosimeters at each 71 location. WATER 80RNE: IV. Suria(e Water G) 1 indicator sample to be taken in the upper Time composite samples 25 Gamma isotopic monthly reservoir at the intake of the pumped storage with collection every with quarterly composite (by facility. month. location) or monthly sample to be analyzed for intium INGESTION: Vll. Milk A) Samples from milking animals in 3 locations Biweekly grab sample 14 Gamma isotopic and 1-131 witbin 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 animals are on pasture. Table 9 - Supplemental R r-fiological Environmental Monitoring Program l
e 't i' . o c b le y le n i b d d i es e e i us n n qy o o l e a ic ip ip p c c c rF n p i A o o o o t t t t f o o o o eo s s s s i p i i i a n a n. a a y T mo mo m m i i mt mt m m r r ao ao a a Gp Gp G G n m e o a lpi 58 r t ma 6 8 7 8, 8, g 1 1 c 47 o aSo 88 r ~ l P g y in c g g e n n e r de in i l lp ito p w w n u o o m m n r r a a aq g g s s o e gr g g b b M n n a a linF i i g g a r r l n r r u u po l l t d d a a n mi u u t y y e ac n n l Se lan. ll n n m an o ns ns ia ia l uo uo n l n a m m o n a C e e e e r As As S S v i n e in E s l p d n a ye e e r t h t io nn e ig c c iw ev cnt o st i b R o on leac n ug loii c t t e t o o ad o e. l s r e n i iad r + ( dd ot s r s o o ta v n s sd e eai l i a p ga d l r d e n ar nc u e o oli i t n a oo h omw ae. mom R r iL t r n ny ace f tc f u e0t eep nk a n l s l e& os m1 e k h p r a ooL t l r h a t at u t ee c e as la n t f s s a v s a nd e Sb ar eor a ee e bmte ic o n e di a m r f e h l r om t t p t f u oh a oaa n a e r e f t t i l aN e ons ew t c t a os p l v er n oo lps la nl R p i lpi eim r e lpt el mn p p o ud u s t p aw mc e mui it ioa S a c oh ayi i o i s o al t le u d aB 9 Cm s r r r n dr r s r a og lotan otam a v t i s t t n e S ad. t o cd m 4 ae at ai ) r c l f iot n )c n i e ( n e b do n o (l d dme ew a a r Inf a Clin I mt o a e n uk T t f l Va r op 1 1 1 is F t b ) )C D ) ) E F e s t lp cu am d a o t r n S P e r d Cm a /o o I i xEpd o Td F Ae n l. U S a i Q. l V AX y i ii! i;, j
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reportmg Period: 1/1/89-12/31/89 Medium or Pathway Type and 70tal t ower twnit of location with HWst AnnualMean M Id sampled (unit of Number of Ana#yses octection: Actua Measueement) Performed' (Ma n.) (Distante & Dwettson) (Range) g,,,,,,,.t. Air Partstulate Gross Beta 2 OE-2 (259/259) Site 14 Dairy 2.2E-2(52/52) 2.1 E-2 (52/52) 0 (pCi/m3) (311) (1.0E-2) (0.4E-2 to 4.3E-2) (6 3 mi W) (1 OE-2 to 4.1E-2) ( SE-2 to 4.3E-2) i Gamma Spec (72) Cs-134 1.2E-3 All < LLD All < LLD 0 (5DE-2) C5-137 1.0E-3 All < LLD All < LLD 0 (6.0E-2) Air Radioeodine I-131(310) 1.5E-2 All < LLD All < LLD 0 (pCi/m3) (7.0E-2) Direct (TLD)5 Gamma (264) 7.3E0(168/168) Site 9, Ball Park 10.3E0 (12/12) 81E0 (96/96) 0 (pR/hr) Monthly .5E0 (5.4E0 to 11.0EO) (2.2 mi, NE) (9 9EO to 11 OEO) (5 2E0 to 11 OEO) Gamma (108) 8 3E0(60<60) Site 55,St Barnabas 11.8E0 (4/4) 7.9E0 (48/48) 0 Quarterly .5E0 (4 8E0 to 12 OEO) Church (2.8 mi E) (11 OE0 to 14 SEO) (5 TE0to 11 OEO) Sur f a(e Water H-3(84) 4.0E + 2(60/60) Site 21, Parr Reservoer 4.4E + 2 (12/12) 3 9E + 2 (24/24) 0 (pC /I) (2.0E + 3) (1.9E + 2 to 8.3E + 2) (2.7 mi,55W) (3.3E + 2 to 8 IE + 2) (1.9E + 2 to 8 4E + 2) Gamma Spet (87) Mn-54 1.1E-1 All < LLD All < LLD D (1.5E + 1) Co-58 1.1E-1 All < LLD All < LLD 0 (1.5E + 1) Fe-59 4.1 EO All < LLD All < LLD 0 (3 OE + 1) Co 60 1.6E-1 All < LLD All < LLD 0 (1.5E + 1) Zn-65 1.3E-1 All < LLD All < LLD 0 (3.0E + 1) Zr-95 2.0E-1 All < LLD All < LLD 0 (3 OE + 1) Nb-95 1.1E-1 All < LLD All < LLD 0 (1.5E + 1) Cs-134 1.0E-1 All < LLD All < LLD 0 (1.5E + 1) Cs-137 1.2E-1 All < LLD All < LLD 0 (18E + 1) Table 10 - 1989 Radiological Environmental Monitoring Program Summary . ~..
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/89-12/31/89 Med+vm or Pathway Type and Total 1 owe, tu' nd of AllInde<ator 1o<ations Sampled (Umt of Number of Analyses Detectd Actual Controllocations None t Mean (Range) Name Meant Mean'(Range) ReportetP' Measurement) Perf semed' (Man.) (p,stante & Dwe< tion) (Range) feessure.w... i Ba-140 4.5E-1 All < LLD All < LLD 0 (6 OE + 1) La-140 1 7E-1 All < LLD All < LLD 0 (1.5E + 1) Ground Water H-3(12) 4.6E + 2 (8/8) Site 26, Well 4 6E + 2(4/4) 4.5E + 2(4/4) 0 (pCi/l) (2.0E + 3) (3.2E + 2 to 8 2E + 2) (460 f t., W) (3 3E + 2 to 7.7E + 2) (3 2E + 2 to 7.9E + 2) Gamma spec (12) M n-54 1.7E0 All < LLD All < LLD 0 (1.5E + 1) Co-58 1.7E0 All < LLD All < LLD 0 (1.5E + 1) Fe-59 4 3E0 All < LLD All < LLD 0 (3 OE + 1) Co-60 2.2E0 All < LLD All < LLD 0 (1.5E + 1) y 2n-65 4 6ED All < LLD All < LLD 0 (3 OE + 1) Zr-95 3.0E0 All < LLD All < LLD 0 (3.0E + 1) Nb-95 1.8E0 All < LLD All < LLD 0 (1.5E + 1) C5-134 1.8E0 All < LLD All < LLD 0 (1.5E + 1) i Cs-137 1.8E0 All < LLD All < LLD 0 (1.8E + 1) Ba-140 7.1E0 All < LLD All < LLD 0 (6 OE + 1) La-140 2.8E0 All < LLD All < LLD 0 (1.5E + 1) Drinking Water 6 Gross 8 eta (36) 3 8E0(24/24) Site 28, NTC 5 2E0(12/12) 2.6E0 (12/12) 0 (pCill) (4OEO) ( SEO to 9 8EO) (2.4 mi,55E) (2.6E0 to 9 8EO) (.5E0 to 6.1E0) H-3(36) 3 6E + 2(24/24) Site 17. Columbia 3 9E + 2 (12/12) 4.0E + 2 (12/12) 0 (2.0E + 3) (1.9E + 2 to 8 4E + 2) Waterworks (24.7 mi, (3 2E + 2 to 8 4E + 2) (1.8E + 2 to SE) 8 OE + 2) Gamma Spec (36) Table 10 - 1989 Radiological Environmental Monitoring Program 5ummary
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/89-12/31/89 Medium or Pathway Typc and Total Lower Limit of IC(80""'th Highest AnnualMean O' Sampled (Unit of Number of Analyses DetectW Actual Measurement) Performed' (Man.) (Destan<e & Direction) (Range) u,,,,,,,,,,,,, Mn-54 1.2E-1 All < LLD All < LLD 0 (1.5E + 1) Co-58 1.2E-1 All < LLD All < LLD 0 (1.5E + 1) Fe-59 5.6E0 All < LLD ~ All < LLD 0 (3 OE + 1) Co-60 1.6E-1 All < LLD All < LLD 0 ~ (1.5E + 1) Zn-65 3.5E-1 All < LLD All < LLD 0 (3 OE + 1) Zr-95 2.3E-1 All < LLD All < LLD 0 (3 OE + 1) Nb-95 14E-1 All < LLD All < LLD 0 (1.5E + 1) 1-131 1.8E-1 All < LLD All < LLD 0 m (1.0EO) C5-134 1.2 E-1 All < LLD All < LLD 0 (1.5E + 1) Cs-137 1.2E-1 All < LLD All < LLD 0 (1.8E + 1) Ba-140 4.7E0 All < LLD All < LLD 0 (6.0E + 1) La-140
- 1. 8 E-1 All < LLD All < LLD 0
(1.5E + 1) Milk Gamma Spec (52) (pCi/1) I-131 3.7E-1 All < LLD All < LLD 0 (1.0E0) Cs-134 1.0E0 AII < LLD All < LLD 0 (1.5E + 1) Cs-137 2 9E0 2.7E0(22/26) Site 14, Dairy 2.7E0 (22/26) 2.3E0(5/26) 0 1 3 (18E + 1) (2.1E0 to 4 SEO) (6 3 mi W) (2.1 E0 to 4.5E0) (1.7E0 to 3 4EO) Ba-140 4 OE0 All < LLD All < LLD 0 (6 OE + 1) ) La-140 1.5E0 All < LLD All < LLD 0 (1.5E + 1) Table 10 - 1989 Radiological Environmental Monitoring Program Summary {
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/89-12/31/89 ~ Medeum or Pathway Type and Total Lower timst of 1Ma@with HegMst AnmsalWan d Sampled (Unet of Numberof Analyses Detettion2 Attual Measueement) Petformed' (Ma n.) (Destance & Directeon) (Range) Measveemem. Grass (pCi/kg wet) Gamma Spec (35) 1-131 8 7EO All < LLD All < LLD 0 (6 DE + 1) Cs-134 7.8E0 All < LLD All < LLD 0 (6 OE + 1) Cs-137 8 8E0 1.9E + - (1/35) Site 6 Garden) 1.9E + 1 (1/35) All < LLD 0 (8 OE + 1) (Singte Sample) (1 mile ESE) (Single Sample) i 8roadleaf Vegeta-Gamma Spec (36) tion (pCi/kg wet) 1-131 7.7E0 All < LLD All < LLD 0 (6 OE + 1) Cs-134 5 8E0 All < LLD All < LLD 0 (6 OE + 1) Cs-137 6 6EO All < LLD All < LLD 0 (8.0E + 1) Other Vegetation Gamma 5pe<(5) (pCi/k g wet) 1-131 1.3E + 1 All < LLD All < LLD 0 (6 OE + 1) Cs-134 5 6EO All < LLD All < LLD 0 (6 OE + 1) Cs-137 6.2E0 All < LLD All < LLD 0 (8 OE + 1) l Fish (pCi/kg wet) Gamma 5pe((31) Mn-54 6.3E0 All < LLD All < LLD 0 (1.3E + 2) Co-58 6.5E0 All < LLD All < LLD 0 (1.3E + 2) Fe-59 1.9E + 1 All < LLD All < LLD 0 (2.6E + 2) Co-60 1.4E0 All < LLD All < LLD 0 (1.3E + 2) Zn-65 (2 6E + 2) All < LLD All < LLD 0 Cs-134 6 4E0 9 6E0 (12/23) Site 23, Monticello 1.1E + 1 (5/8) All < LLD 0 (13E + 2) (2.7E0 to 2.9E + 1) Reservoir (.5 mi, SES) (5.5E0 to 2.9E + 1) Table 10 - 1989 Radiological Environmental Monitoring Program 5ummary ~
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/89-12/31/89 Medium or Pathway Type and Total Lower Limit of Allind cator Locations sampled (Unit of P umber of Analyses Detection 2 Actual C0"I'08 L"80"5 ,p 3 y,,,(n g ) pepoe d Measurement) Performed' (Man 1 (Destance & Derettson) (Range) Measur;-.;.-3 C5-137 6 7E0 1.7E + 1 (21/23) Site 24, Rec Lake 2.4E + 1 (5/8) 1.2E + 1 (8/8) 0 (1.5E + 2) (5.6E0 to 5.0E + 1) (5.5mi,N) (1.6E1 to 3.7E + 1) (1.3E0 to 2.7E + 1) Sediment (pCi/kg)7 Gamma Spec (16) Mo-54 1.2E + 1 1.6E + 1 (1/12) 5'se 21, Parr Res. 1.6E + 1 (1/4) All < LLD 0 (Single Value) (2.7 mi, SSW) (Singte Value) Co-58 1.5E + 1 2.3E + 1 (3/12) Site 21, Parr Reservoer 5.0E + 1 (1/4) All < LLD 0 (7.8E0 to 5 OE + 1) (2.7mi,55W) (Single Value) Co-60 1.8E + 1 4 6E + 1 (6/12) Site 21, Parr Reservotr 1.7E + 2 (4/4) All < LLD 0 (3.5E + 11o 3.3E + 2) (2.7mi. SSW) (7.7E + 1 to 3.3E + 2) Cs-134 1.7E + 1 3.4E + 1 (9/12) Site 21, Parr Reservoer 61E + 1 (4/4) 5 4E0(1/4) . O i (1.5E + 2) (5.0E0 to 1.0E + 2) (2.7mi, SSW) (4 2E + 11o 1.0E + 2) (Senale Value) Cs-137 2.7E + 2 (12/12) Site 24. Recreation 3.9E + 2 (4/4) 2.0E + 2 (4/4) 0 I (18E + 2) (1.3E + 1 to 5.5E + 2) Lake (5.5mi, N) (1.2E + 2 to 5.5E + 2) (6.0E + 1 to 5.5E + 2) l 0 1 1 J Table 10 - 1989 Radiological Environmental Monitoring Program Summary. 1 w r 14..e- . w. 3 +v w = w -. rs ,, -=*i..i,-, .w.---. -.~ .m_m,a-.._
Footnotes 1. Does not include supplemental samples. All supplemental sample results were consistent with the tabulated results shown. 2. Values given are MDA values calculated from the program data analyses with maximum acceptable LLD values allowed from NRC guidelines given in parentheses. 3. Mean and range are based on detectable measurements only. The fractions of detectable measurements at specific locations are indicated in parentheses. 4. Any confirmed measured level of radioactivity in any environmental medium that exceeds the reporting requirements of VCSNS Technical Specification 3.12.1. E$ 5. Detection sensitivity is approximately 5 mrem /yr (0.5 pR/hr) determined from the analyses of five years of preoperational data. 6. Elevated levels of Pb-214 and Bi-214 were observed in all Jenkinsville drinking water samples. The values are not reported here because they are naturally occurring (do not originate from VCSNS) and furnish no quantifiable information of interest. 7. Elevated levels of Pb-214 and Bi-214 plus other Ra-226 daughter products and Ac-228 plus other Th-232 daughter products were observed in all sediment samples. The values are not reported here because they are naturally occurring (do not originate from VCSNS) and furnish no quantifiable information of interest. Table 10 - 1989 Radiological Environmental Monitoring Program Summary
IV.edium or Pathway Type and Total Location with Highest Annual Mean Number of ,g g sampled (Unit of Number of Detection 1 Locations Control Locaties Nerwth, Measurement and Analyses Name (Distance & Meanz Mean2 (Range) Reportedi d& R@ Reporting Penod) Performed Direction) (Range) Measurements 1.3E-1(52/52) { 1.1E-1 (562/564)a Site 13, North Dam (2_1 E-2 to 1.2E-1 (153/155) Air Particulate I ' * " " I I ~ Gross Beta 4 IE-3 (1300) 0.0E-2) 0 981-1982) 2.7E-2 (456/462)8 Site 8, Mon. Res 5 of 3 OE-2(42/42) 2.8E-2 025/126) (9.3E-3 to 6 6E-2) Rd 224 (1.5 ENE) (1.2E-2 to (12E-2 to 5 8E-2) 6OE-2) Gamma 5pec (307) l Cs-134 All < LLD All < LLD 0 3.1E-3 3.2E-3 (22/241) Site 10, Met Tower 8E-3 (2/22) N 4 2E-3 (4/66) (* (1.0E-2) (1.5E-3 to 5.2E-3) (2 4 mi NNE) 5 2E-3) I ~ t'"*";fga 'i ) i-'3"290) ^ " < = ^ " < = o nect (M)5 Gamma (1220) 9.9(915/915) Site 13, North Dam 13 1(61/61) 9.7(305/305) I Monthly (6 7 to14.7) (2.9 mi NNW) (12 2 to 14 2) (6 4 to 13 5) l 8 84 Gamma (161) U 5' ' 'S i 0.5 Quarter!y (6 81o14.7) Church (2.8 mi E) 03.1 to 14.7) 0 4 Surface Water 1.6E + 3 (2/7) 1.2E + 3 (6/14) (pCi/l) H-3(43) (1.4E + 3 to (6 7E + 2 to 0 0 981-1982) (2 OE + 3) (1.1E + 3 to 2.4E + 3) Canal (24 7mi,SE) 1.8E + 3) 1.6E + 3) Gamma spec (140) 27 M n-54 All < LLD 4 g 5E 1) All < LLD 0 i Co-58 All < LLD All < LLD 0 g y Fe-59 AH < (3 0 + 1) An < 0 Table 11 - Radiological Environmental Monitoring Program 5ummary Preoperational(Baseline) Summary - ~~
Medium or Pathway Type and Total , w e Li it of AH Indsstor Location with Highest Annual Mean Number of Sampled (Unit of Number of Detection 1 Locations Controllocations Nontoutine. Measurement an W Name (Distance & Mean2 Mean2 (Range) Reported 3 Reporting Period) PerIormed Actual (Man ) Mean2(Rat ge) Direction) (Ra"9e) Measurements 24 t co-60 AH < LLD An < uD 0 ,3 5E 1) Zn-65 AH < uD AH < uD 0-(3OE 1) (f5E Zr-95 All < tLD ) All < tLD 0 i Nb-95 AH < LLD AH < LLD 0 O SE 1) 1 i Cs-134 All < LLD (1 SE 1) AII < RD 0 C5-137 All < iLD All < LLD 0 gg t g Ba-140 AH < i (6 OE + 1) AH < u 0 i AH < {1982 only) (1SE 1) AH < RD 0 Ground Water 9OE+2 1.5E + 3 (16/16) Site 26. Onsite Well 6E + 3(W L3E + 3 (13/13) (pCs/I)(1981-1982) (2.0E + 3) (9.5E + 2 to 2.3E + 3) P4 (265 f t, W) ( ( 3E + 3) 9E 3 i Gamma spec (32) 3 7E0 Mn-54 All < LLD AH < LLD 0 gj 3 i) 38 co-58 An < nD AH < RD 0 (15E + 1) Fe-59 ^ " < (3 0 + 1) ^ " < 38 co-60 AH < nD AH < uD 0 (15E + 1) 8 Zn-65 AH < n AH < 0 (3 0E + 1) 1 Table 11 - Radiological Environmental Monitoring Program Summary + Preoperational(Baseline) Summary
4 Medium or Pathway Type and Total location with Highest Annual Mean Numberof - l 4 g g,, Sampled (Unit of Number of Detection 1 Locations CmtrhWms NeretW Measurement and Analyses Name(Distance & Mean2 Mean2(Range) Reported 3 l i al M W h 2(R M Reporting Penod) Performed Direction) (Range) Measurements i Zr-95 All < LLD (15 + 1) All < LLD 0 Nb-95 All < LLD All < LLD 0 (15 + 1) Cs-134 All < LLD All < LLD 0 g ,y ) Cs-137 All < LLD All < LLD 0 08 [ All < LLD All < LLD 0 i Ba-140 ^ " < (1982 only) (15 + 1) ^ " < " rn ng ater6 2'. Gross Beta 7 (2.0EO) (pCi/t)(1981-1982) 1 6.3E + 2 7 8E + 2(6/14) Site 28. Jenkinswile 8 4E + 2M "~(' I0* (1 OE + 3) (6 8E + 2 to 9 BE + 2) (2 0 mi SE)7 9 8E + 2) Gamma 5pec (44) 0 Mn-54 All < LLD ) 0 i Co-58 AH < O SE 1) 0 t Fe-59 AH (3 0 + 1) 0 f Co-60 AH < (1 SE 1) 0 [ Zn-65 All < LLD l 3 OE 0 j Zr-95 All < LtD 0 O SE Table 11 - Radiological Environmental Monitoring Program 5ummary Prcoperational(Baseline) Summary f I 2.
l . l Medium or Pathway Type and Total location with Heghest Annual Mean Number of l g l Sampled (Unit of Number of Detection 1 Locations ontrd Waboos hwh Measurement and Analyses Name (Distance & Meanz Mean2 (Range) Reported 3 g Reporting Persod) Performed Direction) (Range) Measutements i Nb-95 All < LLD 0 SE 1-131 All < LLD 0 l DEO Cs-134 All < LLD 0 O CE C5-137 All < Lt D g 0 Ba-140 All < LLD 0 (6 E 1) La-140 4 4E-1 All < LLD (1982 only) (1.5E + 1) 0 j Melk i M (pC /I) (1981-1982) i 1 1-131 All < LLD All < LLD 0 i ( OE0 Cs-134 All < LLD All < LLD 0 t E+0 4.
- N 5.7EO (37/47)
Cs-137 (2 8E0 to 0 (1.5E + 1) (2.8E0 to 61EO) (51 mi., W) (. O to 9 2EO) { 61EO) Ba-140 All < LLD all. LtD 0 E La-140 All < LLD All < LLD 0 (1SE 1) Geass (pCia g wet) Gamma Spec i (1981-1982) (82) e I-131 All < LLD All < LLD 0 6 ) i, Table 11 - Radiological Environmental Monitoring Program 5ummary Prcoperational(Baseline) Summary
l l Medium or Pathway Type and Total Location with Highest Annual Mean Number of WW AllIMe Sampled (Unet of Number of Detection 1 Locations Measurement and Analyses Name(Dist Yxe & Mean? Mean2 (Range) Reportedi t A m al W ) MMRM l Reportmg Penod) Performed Direction) (Range) Measurements l l Cs-134 All < LLD All < LLD 0 E+
- I I
3 3E + 1 5 OE + 1 (13/51) Site 14. Dairy ( I (8.OE + 1) (16E + 1 to 1.6E + 2) (51 mi W) l 16E + 2) 3 4E + 2) Broadleaf Vegetation (pCi/h g wet) Gamma 5pec (10) (1980-1982) l l-131 A!! < LLD All < LLD 0 E Cs-134 All < LLD All < LLD 0 E + 1) 2E + 1 5 4 + 1 (2/7) Ste 2, Trans. Une 3 6E + 1(1/1) I Cs-137 All < LLD 0 (8 OE + 1) (1.8E + 1 to 3 6E + 1) (12 mi SW) (Single Value) Other Vegetation 5 (pCi/> g wet) (32) (1980-1982) 1 i Cs-134 All < LLD All < LLD 0 (8 E 1) Cs-137 All < LLD All < LLD 0 l Fish (pCi/kg wet) Gamma Spec ] (1980-1982) (92) [ Cs-134 All < LLD All < LLD 0 18E+1 2 BE + 1(50/71) Site 24, Re(reation 17/23) 7 (1 CE + 1 0 (1.3E + 2) (1 1E + 1 to 1.0E + 2) Lake (5.5 mi, N) (12E + 1 t 7.9E + 1) 1.0E + 2) Co-58 All < LLD All < LLD 0 E+ Table 11 - Radiological Environmental Monitoring Program Summary Preoperational(Baseline) 5ummary P-w 2 ~-v e su --____;*---__m_ m.- m w Www'-Cm'
4 J Medium or Pathway Typeand Total L (ation with Highest Annual Mean Numberof
- rU AH W e Sampled (Unit of Number of Detection 1 Locations Measurement and Analyses Name (Distance &
Mean2 Mean2 (Range) Repoeted3 Reporting Penod) Performed d& 2 RM Direction) (Range) Measurements Mr>54 All < LLD All < LLD 0 ) OE Fe-59 AII < LLD All < LLD 0 Zn-65 All < LLD All < LLD 0 ) 1.8E + 1 Co-60 AH < D (1.3E + 2) AH < LLD 0 5ediment (pCi/kg) Gamma Spec i (1980-1982) (24) G-134 All < LLD E+ All < LLD 0 w 2.4E + 1 1.7E + 2(12/18) Site 21, Parr Reservoer .6E + 2 W6) 4 2E + 2(W b'I3 (2.6E + 1 to (1.8E + 1 to 0 (1.5E + 2) (2.6E + 1 to 4.5E + 2) (2.7 mi,55W) 1 4 SE + 2) 1.0E + 3) l i I a i l i i i i i Table 11 - Radiological Environmental Monitoring Program Summary Preoperational(Baseline) Summary 1 5 ,s -.n ~, ~. -.,,, .-w ,.e ,--.,,aa,. . ~, -.,,...,,,..,,_
Footnotes 1. Values given are MDA values calculated from the program data analyses with maximum aueptable 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 nonroutine measurement is any confirmed measured level of radioactivity in any environmental medium that exceeds the reporting requirements of VCSNS Technical 5pecification 3.12.1. 4. The baseline values are high because of the fallout from the Chinese bomb test in 1980. The first set of data reflects the 1981 baseline. The second set of data reflects the 1982 baseline, essentially free of bomb test fallout. The 1982 data covers the period 1/1/82-10/22/82. 5. Detection sensitivity is approximately 5 mrem /yr (0.5 pR/hr) determined from the analyses of five years of preoperational data. g 6. No control location was specified for drinking water during the preoperational monitoring period. 7. Inconclusive data. Refer to the Preoperatio4al Radiological Environmental Monitoring Report. 4 Table 11 - Radiological Environment il Monitoring Program Summary Preoperational(Baseline) Summary
l o l Sa e th Media toc n ( ek N,) Cause for Exception j Air 6 October (39) Incomplete samples attributed to air sampler power outages. Grass 6 January Seasonal Unavailability l April December Broadleaf Vegetation 6 April Seasonal Unavailability 8 April Seasonal Unavailability Fish (bottom feeders) 24 October Seasonal Unavailability l r Table 12 - 1989 Environmental Sampling Program Exceptions L P 36
i j e s Airborne gross beta activity measured in air particulate samples collected at l 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 i control location measurements during 1989 were 2.0E 2 and 2.1E 2 pCi/m3, respectively. The highest site specific mean activity was measured at indicator location no.14 (Dairy, 6.3 mi, W) to be 2.2E 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 Cs 134, Cs 137 and 1131 were 1.2E 3,1.0E 3 and 1.SE 2 aci/m3, respectively. The results agree with gaseous effluent release data reportec in the 1989 Semiannual Effluent and Waste Disposal Reports for VCSNS. Only 1.3E 6 and 4 1.6E-3 Ci of particulate and iodine activities were released, respectively. These activity levels are not discernable in atmospheric samples upon consideration of dispersion and dilution f actors experienced during the releases. Environmental dosimetry measurements during 1989 did not differ significantly from preoperational measurements over the same seasonal time periods. Indicator and control dosimetry measurements also showed no appreciable differences during 1989. Sampling location no. 9 at the Ball Park near Jenkinsville (2.2 mi, NE) was the indicator location showing the highest mean exposure rate of 10.310.6 pR/hr. This value compares favorably with the mean exposure rate of 13.612.2 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 1989 indicated a total of 1.8E3 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 spectrosco ay measurements of surface water samples did not indicate the presence of activatec corrosion and most fission products above the respective MDA's. Uquid effluent release data reported for 1989 in the Semiannual Effluent and Waste Disposal Reports indicated a total of 1.36E0 Ci of measureable fission and ,i activated corrosion product activity was released from VCSNS; a level not discernable in surface water based upon consideration of dilution factors experienced during the releases and the detection limits of analytical methods. Tritium analyses of surface water samples during 1989 yielded results which were not noticeably different from preoperational data. The highest mean indicator l tritium activity cf 4.4E + 2 pCi/ liter was measured at Site 21, Parr Reservoir (2.7 mi, SSW). Activity levels measured at the indicator locations are within the normal background variation for environmental tritium and consistent with the i preoperational mean of 1.4E + 3 pCi/ liter, Total tritium released in liquid effluents i during 1989 was reported to be 6.9E + 2 Ci; a level not discernable in surface water 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 37
i 6 respective radionuclides. 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 uramum 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 1 produced through th6 decay of dissolved Rn 222 gas in the ground water. No evidence of radioactivity from VCSNS operation was detected. l Tritium analyses of ground water samples during 1989 yielded results which were not significantly different from preoperational results, or indicator i significantly different than control. i Gamma spectroscopy measurements of drinking water samples collected from r 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 i daughters; normallow beta activity at Columbia (surface water source) and elevated beta activity at Jenkinsville (deep well source). This data is again comparable to the l preoperational data and is attributed to the naturally occurring uranium associated with the aquifer supplying the Jenkinsville water system. The highest drinking water tritium analyses, showed an average detected activity of 3.9E + 2 3Ci/ liter m Columbia drinking water. This value is consistent with the preoperationa mean activity of 7.8E + 2 pCi/ liter. Gamma spectroscopy measurements of milk samples collected in 1989 were [ i not significantly different from those observed during the preoperational program. l Naturally occurring K 40, Ra 226 and Cs 137 attributed to fallout was detected at l both sampling locations at concentrations similar to those measured during the 1 preoperational period. There were no identified radionuclides in milk attributed to l VCSNS operation. Gamma ssectroscopy measurements of grass (forage) samples collected in 1989 indicated t1e presence of Be 7 and K 40 in all samples. The naturally occurring radionuclides Be 7 and K 40 were detected at levels similar to those found during t the preoperational program. Cs 137 was identified in a single sample at a level consistent with preoperational baseline results and is attributed to fallout from atmosaheric weapons testing and possibly the 1986 Chernobylincident. There was no incication 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 1989. P Broadleaf vegetation collected from gardens at location no's. 6,8 and 18 were the principal food products analyzed during 1989. Naturally occurring contributions from Ra 226, K 40, Ac 228 and Be 7 were measured. All radionuclide measurements are comparable to and consistent with the results obtained during the preoperational program. 38
l o* Other vegetation sampled in 1989 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. Fish species sampled at three indicator and one controllocation included bass, bream, shad, catfish and carp. Cesium 137 was detected in 21 of 23 samples collected at all sampling locations and in all five species. The highest mean Cs 137 concentration was 2.4E + 1 pCi/kg (Recreation Lake). Cesium 134 was detected in 12 of 23 samples and was limited to samples collected from Monticello and Parr reservoirs. The highest mean C5134 concentration was 9.6E0 pCi/kg. The levels of Cs 137 in both control and indicator locations were consistent with preoperational levels and are primarily attributed to residual fallout from atmospheric weapons testing and the 1986 Chernobyl incident. The presence of C5134 is primarily attributed to liquid effluent releases during 1989 which included a total of 3.3E 2 Ci of Cs 134. Liquid effluent releases are assumed to also contribute to the presence of C5 137. However, this contribution is not discernible from the levels of Cs 137 present due to fallout. Liquid effluent releases during 1989 included 4.2E 2 Ci of C5-137. The presence of Cesium 134 and 137 attributed to liquid effluent releases from VC5NS would be limited to Parr and Monticello Reservoirs. Gamma spectroscopy measurements of sediment samples collected during 1989 also indicated the presence of activated corrosion and fission product activity, Cesium 137 was detected in sediment from all indicator and control locations. Cesium 134 activity was found in Monticello, Parr and a single anomalous indication at the control site (Neal Shoals). Cobalt 60 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 1.6E + 1, 5.0E + 1, 1.7E + 2, and 6.1E + 1 pCi/kg for Mn 54, Co 58, Co 60, and Cs 134, respectively. The highest mean activity for Cs 137 was 3.9E + 2 pCi/kg found at the Recreation Lake. 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. The contribution of Cs 137 from VCSNS liquid effluents is not discernible from the levels of Cs 137 present due to fallout. Cesium 134 activity limited to Parr'and Monticello Reservoirs may be attributed liquid effluent releases from VCSNS. Activated corrosion product activity detected in Pa., and Monticello Reservoirs is attributed to liquid effluent releases from VCSNS. The relatively low 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 activity in sediment, were calculated using Regulatory Guide 1.109 methodology. A 400 hr/ year exposure to shoreline sediment contaming mean detected concentrations of Mn 54, Co 58, Co-60 and Cs 134 was assumed. The results are included in Table 13. 39
o l g 0 Corresponding Calculated Annual Dose Location Radionuclide Activity (pCilkg) Equivalent (mrem) Maximum Mean Whole Body Monticello Co 60 5.0E + 1 5.0E + 1 1.4E 2 l Reservoir t Cs 134 2.0E + 1 1.1 E + 1 2.1 E 3 Total 1.6E 2 Parr Reservoir Mn 54 1.6 E + 1 - 1.6E + 1 1.8E 3 C5134 1.0E + 2 6.1 E + 1 1.2E 2 Co 58 5.0E + 1 5.0E + 1 4.6E 3 Co 60 3.3E + 2 1.7 E + 2 4.8E 2 Total 6.6E 2 Table 13 1989 Activated Corrosion Product and Cs 134 Activity in 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 Mn 54, Co 58, Co 60 and Cs 134 in sediment is a highly conservative estimate. The absence of any discernible ecological impact on biota substantiates the fact that species population stability has been unaffected by the activated corrosion and fission product activity released from VCSNS. The absence of any impact is anticipated since the concentrations were much less than acceptable limits during 1989 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 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 Radclogical Environmental Monitoring Program support the results reported in the Semiannual Effluent and Waste Disposal Reports for VCSNS during 1989. The calculated potential radiation dose to the public attributed to activated corrosion product activity and Cs 134 in Broad River media is 9.5E 2 mrem. This figure compares with the 1.07E 1 mrem dose reported in the 1989 Semiannual Effluent and Waste Disposal Reports and is a small fraction of ob>erved 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 Idesign goals. 40}}