ML20154D843
| ML20154D843 | |
| 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 8805200004 | |
| Download: ML20154D843 (52) | |
Text
{{#Wiki_filter:-. _ _ _ _ _ _ _ _ _ _ _ _ g ..\ Virgil C. Summer Environmental Surveillance Laboratory Jenkinsville, South Carolina RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT VIRGIL C. SUMMER NUCLE AR STATION FOR THE OPER ATING PERIOD JANUARY 1,1987 - DECEMBER 31,1987 APRIL 1988 V. C. SUMMER NUCLEAR STATION SOUTH CAROLINA ELECTRIC AND GAS COMPANY Prepared by: Reviewed by: hb ( l ~ Giegory G. Hall, Supervisor Leldon A. Blue, Manager Radio Sgical AnalyticalServices Corporate Health Physics and Environmental Programs jT 2( 8805200004 871231 </ DR ADOCK 05000395 DCD (, _ _ _ _ _ _ _ l
, \
Executive Summary
- 1. Results of the 1987 Land Use Census neither indicated 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 radioactivit,in environmental media attributed to gaseous ef fluent 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 Monitoring Program substantiate the continuing adequacy of source ccotrol at VCSNS and conformance of station operation to 10 CFR 50, Appendix I design goals.
(i)
i -) TABLE OF CONTENTS Introduction 1 Description of the Radiological Environmental Monitoring Program 2 Results and Discussion Conclusion 44 (ii)
, i, l
J l v i LIST OF FIGURES 4 FIGURE h 11 Control Site Locations (50 Mile Radius around 4 the Virgil C. Summer Nuclear Station) 9 ; i 12 Radiological Monitorina Program Locallndicator ! Sample Sites (5 Mile Radius around Virgil C. Summer Nuclear Station) 10 . 4 13 Radiological Monitoring Program Localindicator t Sample Sites (1 Mile Radius Around Virgil C. Summer ! Nuclear Station) 11 , l I i, t i a { j i r I t I 1 I i l i I !
- I i !
i ! I i < r ) [ $ f j (iii) I t
e, , , LIST OF TABLES TA8LE h l 1 Monitoring Methods for Critical Radiation Exposure 2 Pathways j 2 Results of the August 1987 Land Use Census 3 Verification i 2a Critical Receptors in 1987 Based on FSAR Projected 4 l Source Terms l t 3 Radiolo ical Ensironmental Monitoring Program 6,7,8 ; Samplin Site locations ' 4 Results of the 1987 EPAIntercomoarison Program 12,13 ; 5 Results of the 1987 Intracomparison Program 14 ! with VCSNS Count Soom 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 Supplementa! Radiological Environmental Monitoring 23 i 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 Activityin Sediment 44 (iv)
, s Introd @
Virgil C. Summer Nuclear Station (VCSNS) utilizes a pressurized watcr reactor rated at 2775 MWt (900 MWe gross), The station is located adjacent to the Monticello Reservoir near Jenkinsville, South Carolina and approximately 26 miles northwest of Columbia. VCSNS achieved initial criticality on October 22, 1982, reached 50% power December 12,1982 and 100% power June 10,1983 following steam generator feedwater modifications. VCSNS completed its third fuel cycle on March 6,1987. The fourth fuel cycle began after criticality was achieved on June 6,1987 following a 94 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 6800 acres and lies about 150 feet above Parr Reservoir whose full pool area is approximately 4400 acres. The pump turbine units operate in the generating mode to meet peak system loads while Monticello Reservoir also provides condenser cooling water for VCSNS. Cooling water intake and discharge structures are separated by a jetty to ensure adequate circulation within the reservoir. VCSNS is located in Fairfield County which, along with Newberry County, rnakes 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 stoducing small 5 rains, feed crops and beef cattle. Significant portions of
.exington and Ric11and Counties are encompassed within the 20 mile radius of the plant and exhibit similar agricultural activities. Columbia, the state capital,is the only larae 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 Environmental Monitoring Program at VCSNS. This report summarizes the results of the Radiological Environmental Monitoring Program conducted during 1987. Data trends, control / indicator and preoperational/ operational data intercomparisons and other data interpretations are presented. Page 1
Descriptien of the Radiological Environmental Monitorino Program The Radiological Environmental Monitoring Program is carried out in its entirety by South Carolina Electric and Gas Company. The program has been designed to meet the following general commitments:
- 1. To analyze selected samples in important anticipated pathways for the qualification and quantification of radionuclides released to the environment surrounding VCSNS.
- 2. To establish correlations between levels of environmental '
radioactivity and radioactive effluents from VCSNS operation. The program utilizes the concepts of control / indicator and preoperational/ 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 pathway; of these effluents which may lead to radiation exposure of the public, based on existing demography, are summarized in Table 1. 4 Re e seType 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) Surf ace Water Sampling, Bottom Sediment Samphng, Fish Sampling Water & Shoreline TLD Area Monitoring, Surface Water Exposure (Ingestion and Sampling, Shorekne and Bottom immersion) Sediment Sampling Drinking Water Ground Water Sampling, Drinking (Ingestion) Water Sampling Table 1 Monitoring Methods for Critical Radiation Exposure Pathways Page 2
Effluent dispersion characteristics, demography, hydrology, land use, anticipated source terms, and the entical paths specific to VCSNS have been considered in the selection of sample media, sampling and analysis frequencies, sample locations and ty aos of samples. These criteria were used to establish both the preoperational anc operational phases of the Radic, logical 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 r m. 1 in Table 2. A verification of the critical receptor (maximum exposo d; ) in each sector around VCSNS based on 1987 meteorologicaldata and b AM aal Safety Analysis Report source terms is included in Table 2a. Sector Miles Nearest Garden Miles Cattle ' R idence M ed N Martin 38 Fuller 40 Robinson 0 33 NNE Crumblin 29 Robinson (8) 33 Robinson 0 33 NE 5 tone 21 Robinson 29 Stone 0 21 ENE Johnson 14 Willingham 15 E Martin 15 Pearson 31 E5E Martin ( A) 1,1 Martin 11 SE White 1.5 Summer 15 55F Crumpton 25 Snesiy 27 5 Pinner 38 Eargle 39 Yarborough 0 38
$$W Weber 32 / Ash (B) 34 %!!er 0 30 SW Davis 31 Nichols 33 Summer 0 25
- W5W Hope 31 Summer 33 Livingston 0 1.9 W Amick 2f Smith 25 Livingston 0 21 WNW Palmer 27 Williams 45 Williamsic) 0 45 i NW Wright i9 Cole (B) 41 Cole 0 41 l
gNNW March 29 March 30 March 0 30 1 l A. Thange in closest residence B Change in closest garden
! C Milk ir.0 animal not milk ed Table 2 - Results of the August 1987 Land Use Census Verification I
j Page 3 f
- s .
1975 Ylif 060 LOGICAL DATA 196 7 M[ 7tCROLOG C AL DAT A Di$fANCE SECTOR q* 'l NAME PATHWAY DOSE DO5E M Q RATE EQ FC RATE m Rem /y mrem /y N 33 Ret..nsor Be et 11 2 Lt 07 1 St-lu 1 ut 01 2 e t -0 7 7 e t .10 $ st 02 N 38 Y a rt ,r> kes 15407 7Ut 10 5 7t 43 2't07 5 7L -10 7 el U3 N 40 p uer' Res Gar I et -0 7 t, 21 - 10 1 t t 01 19i07 51110 14t01 NNi 29 Crwm btn Nes 32607 1 S i 4> A 1 26-02 3 t i -0 7 I it os I at 02 NNE 33 i Ret 2,nsan ResGar 25107 1 i f -uw 29101 2 t l -0 7 79i ") . Ji 01 NNi 36 R k tunsen' resGarbeef 2 tt 07 89610 3 Si 0;ti, . 3t V7 t, Si le 2 ei vi i le Ni 21 5tt .r e Nes bee f t, b E '0 7 3 tt Od 3 et ul b st O' 2 tt Od 2 9f -01 Ni 29 J H a t. r son ' M es Gar steef 3 ef '0 7 1 76-09 6 1 f -01 4 tE 07 12[ Oir 4 t E v1 E Pei 14 memsmn hes 1 di ut 8 ut 08 5 4E 02 2 4E 06 f> vi 09 9 Of v2 ENE 15 4.anp a *
- Res Gar 12i46 t. 6 t v i t hf u0 21 E M $ bt 09 i t i . 00 E 31 Pwo m* Res Gar 24i 47 9ti 10 25101 4 at 07 s JE 10 2 71-0)
E i5 N Y a 't e Res i 1 ! t ti 5 CE 03 4 21-02 2 i t -Ot. 5 3( 09 7 8i 02 (si 11 Jr Yartm' M A)- R es Ger 2 21 Ot, 6 4E U9 2 'I . 00 2 C E Ot. 7 di 09 2 Ot Ga SE 15 At te kes 1 t.E Ot ! bl Of 6 Of 02 8 BE OF 3 2f 0) 3 Af O. 51 15 Swm tr e r ' ResGar 1 ti et 5 ti -u s 1fE+00 88107 3 Ji Os 8 t 1 -o ' 55E 25 Cr# ptsn 6es 3 SE-07 12E vs 1 3 t -02 1 S E -9 7 69110 5 7 L -0 3 SSE 27 Stea:r' 6esGar 3 0t 07 I ul os 2 7f 01 13E 07 5 6E 10 1 51 -v1 5 38 e a r d. ,r g, see t (O 1 tE 07 3 ei lu 4 SE 02 8 sf utt 3 b t 10 4 if 02 5 34 bnn er Res ibE07 3 et 1v t t[ 03 8 9t 08 3 of 10 3 41 ol 5 39 Ear; e* Ris ; er 1 7[ 07 3 ?t 10 11 01 4 41 ve 3 tt 10 9 Si 02 55A 32 Atter R es 23607 ' 5E 10 8(L 03 14107 7 2i 10 5 al Os 55 A 34 Ast*J) kes Gar 2 OE 07 t, 4 E 10 1 'E 01 1.i 07 t di 10 1 t l 01 55 /n 34 M Let mes Pt et 2 Of vi t 4[ 10 vJiU2d) 1 J i -v 7 t, 2 t l u a7L02J) 54 25 5.rn rt et SectiC) 4 t.( 0 ? 1 Vi 09 2 I f 01 27107 1 if vy 1 tl Q1 5A 3i Das s Art 2 9t 0 7 12t 99 1 ' t 6. 1710' 1 ut Vy t. t t 0 3 SA 33 N,ct m ' hes Ge' 261 07 10109 2't+' 1 51-0? 91f 'O 23t01 5A 33 Y ser ses 2 t L -0 7 1 ut us 9 f t 0 3,. i i $l 07 v II 10 5 tE v3.J A5A .9 UrnQstan ovetiC) b4[47 3 2f 09 3 Aiv1 4 a f -0 7 3 et 0) 3 26 v1 ASA 11 nwe kes 13tol l ut ev *s i t -u s 15t 47 9 tt 'o t vi os 654 33 W eP k es G a r 2 0t -0 7 a 7t 10 i st u1M 13E O' 6 Jt to 3 8t vim eV 2S A m .( k M es 2 Si 47 1 il Os v 5t vi 3 2E 07 12f 09 21-02 6 25 seit krs Gar 25147 1 't u J 9t a.1 326-07 1 ; f -0v 3 Of 01 A 27 L . . r%,r. ' des Ga Beet (G) 22E47 13E 10 4 J E 01 % 2 76-07 1 ( 6 -us 4 t t 01 % ANA 27 Ga v er wes 16E4? 7 tf 50 t ei-0 3 13E t? 4 h6 'O 41603 A N .. 45 A i .a ms' E e s Gr idret 6 (f e6 2 5F 10 42i 01 4 ef ve i tl 'O 5 et O2 NA 39 nr ei Fes 11607 4 t i 10 4 of OJ 12t v7 34610 4 51 O s NA 45 Co e*,bi #es G a r beef y 2 t -O fi 4 Of Su 15101 1 It 0? ! L E 10 1 I t 01 NNA 29 J Y a'c h *=s 19107 11604 7 Al 03 3 ti V7 9 If 'O 1 jf 02 NN A 10 & Vau m' ertGar vee
- 18f 47 y 'F 'O 15E m 3 4F 47 9 af to 1 Ji 01 Denotes Cnt <al Receptor for the Sector (G) Cattle assumed to giase at 21 miles W Change m Closest mes.dence for the Sector
~
(0) (M) Astummg Leemgiton eats beef erom h.: herd m the W5 A.Liemgston s (from 1986 Census) dose rate wow dh a n olk,a s : (t) Change m c6osest garden 56 meem y ( 75 A Q. L 57 mrem y ('87 CO. @) (C) sesiden<e assumeo m takutations (i) Assummg 5emmer eats beef trom Ns herd en the 5W. 5wmmer's done rate (D) Ma aim um e s posed mdividwaltor the sete (19 75 met date) (I) Cattte assumed to graae at 3 3 maes Nhl mowws 42 mkemtw as touqwy y ('75 A Q, @t 18 mnem y ( 47 al Q) tr> Cartie assemedio siaae ai 3 o maei S5w (i) A ssommg u.n
-s mm em , n5 <
p ., t et easi brev tenm ha hergog55W, uaier i dos.e
- i. 0.. mse m , < u Table 2a - Critical Receptors in 1987 Based on FS AR Projected Source Terms 4
~
t in addition to preopersticatal/ operational data intercomparisons, control / ; indicator data intercomparisons are utilized to assess the probability that any ! observed abnormal measurement . radioactivity concentration isdue to random or regional fluctuations rather than to a true increase in local environmental l radioactivity concentration. Monitoring sites indicative of plant operating condi-l tions are generally located within a 5 mile radius of the plant as shown in Table 3 ' and Figures 12 and 13. Monitoring sites at distances greater than 10 miles from
- the plant are shown in Figure 11 ana aie indicative of conditions away from plant influence.
Valuable information is gained through multiple types of samphng and measurements at specific locations Several multiple sampling combinations are in l J use around the VCSNS ' H air samphng locations are also environmental dosimetry i monitoring locations c, " tse points airborne plant effluents are monitored for gamma immersion di P ble gases), airborne particulates, and at selected sites, , radiciodine. Four os m m. locations have additional complementary sampling / measurement pathwe or monitoring plant effluents. Sampling locations 6 (1.0 mi ESE) and 8 (1.5 mi (NE) have broadleaf vegetation gardens for monitoring the the gaseous effluentcoefficients highest deposition deposition andSamphng (D7Q). ingestion pathway locations 5 (0.9 in mi theSE) twoand sectors 18 having(16.5 mi 5) also have broadleaf vegetation gardens for nmnitoring the gasecus effluent deposition and ingestion pathway at an indicator t J antrollocation, respectively. l Liquid effluents are monitored through ti . pathways (fish, bottom sediment and surface water) at the three most probable affected bodies of water i i around the plant: Site 21, Parr Reservoir (2.7 mi SSW); Site 23, Monticello Reservoir i (0.5 mi ESE); and Site 24, Recreation Lake (5.5 mi N). The controllocation for liquid , j ef fluent 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 ! i program wita the count room at VCSNS are included in Table 5. Results of an
- intercompanson program with SCDHEC outlined in Table 6 are reported by SCDHEC Results of an environmental dosimetry intercomparison with the NRC are included 1
in Table 7. The results of each of these fc.ur quality control checks of the Radiological Environmental Monitoring Program verify tne technical cred:bility 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.
1 Results and Discussion i The results of the Radiological Environmental Monitonng Program for 1987
- are summarized in Table 10 For comparative purposes preoperational data is summanzed in Table 11. Certain samples were not collected during 1987 and are j not included in the annual summary A listing of these program exceptions and
, their respective causes are included in Table 12. Despite the program enceptions, a the Radiological Environmental Monitoring Program was able to attain a 1 completion rate of 97% Detailed analyus of the impact of these omissions venfied that program quahty has not been affected and there were no violations of j Technical Specification requirements 5
l I Description Ds n Direc. ion 2 Sample Type (s)3 b[8 es 1 Borrow Pit 1.2 182.0 5 DM 2 Transmission Line 1.2 225.0 SW AP,RI,DM 3 Firing Range 1.2 270.0 W DM 4 Fairfield Hydro 1.2 289 5 WNW DM 5 Transmission Line Entrance 09 145 5 SE AP,RI,DM 6 Env. Lab Garden 1.0 104.0 ESE AP.RI,DM,G R,G A 7 Monticello Peninsula 1.2 83.0 E DM 8 Monticello Res.5 of Rd 224 1.5 63 0 ENE AP,DM GA 9 Ball Park 2.2 44 0 NE DM 10 Meteorological Tower No 2 2.5 25.5 NNE AP,RI,DM
~
11 Residence 33 8ON DM 12 Old Hwy 99 42 349.0 N DM 13 North Dam 2.9 334 0 NNW AP.DM 14 Daily 63 270 0 W AP,RI,DM,MK GR 15 Parr Village 2.5 204 0 SSW 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.D M,5W, DW,B 5 18 Residence / Pine Island Club 16 5 16505 D M,5W.G A 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,65 ' 23 Discharge Canal (Mont. Res ) 0.5 104 5 ESE SW,F H,85 24 Recreation Lake 55 2.0 N SW,FH.B5 25 Fairfield Pumped Storage (Monticello Res ) 0.9 302.0 WNW SW 26 On Site vVall (P2) 460Ft 2 70.0 W GW 27 On Site Well (PS) 510 Ft 180.0 5 GW 28 Nuclea Iraining Center (EOF) 2.4 168 0 SSE DW 29 Trans Line WSW of VCSNS 0.9 248.0 W5W DM 30 Oak Tree North of Borrow Pit 1.0 197.0 SSW DM 31 McCrorey Liston School 5.8 12.5 NNE DQ 32 Dirt Rd of f Rd 205 4.5 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 4.8 137.5 5E DQ 36 Woods Behind Jenk. Post Of fice 3.1 151.5 SSE DQ 37 Residence 49 305.5 NW DQ 38 FP5F Traitrace 13 280.0 W B5 39 LMWTF 14 0 168.0 SSE DW 40 No Sampler 41 End of Catwalk 39 185.0 5 DQ 42 Store 39 199 0 55W DQ 43 Hwy 176 and Rd 435 52 236 0 5W DO Table 3 - Sampling Site Locations 6
g Description Direction 2 Sample Type (s)3 es 44 Rd 28 at Cannon's Creek 2.9 255.5 WSW DQ 45 Rd 33 at Pomaria 5.9 253 0 WSW DQ 46 Rd 28 at Heller's Creek 37 292.0 WNW DQ 47 Fairfield Tailrace 1.0 316.0 NW CQ 48 Cemetary 2.3 318.5 NW DQ 49 North Rd 383 40 332.5 NNW DQ 50 New Rd 99 (West Shore) 5.5 1.0 N DQ 51 New Rd 99 (East Shore) 55 5.0 N ' DQ 52 Monticello (Rd 11) 3.9 14.0 NNE DQ 53 Rd 359 3.0 48.0 NE DQ 54 Jenkinsville School 1.7 73.0 ENE DQ 55 St. Barnabas Church 28 94 0 E DQ 56 Old Jenkinsville Dinec 2.0 144 OSE DQ 57 Residence / Highway 213 and 215 2.7 146 0 SE DQ 58 Residence 25 158.0 SSE DQ 59 Nuclear Training Center (EOF) 2.4 168 0 SSE DQ,AP 60 Rd 98 near Rd 28 35 275 0 W DQ 61 Switchyard, SE Entrance to Plant 0.1 180.0 5 DM 62 East of Training Bldg 0.13 220 0 SW DM 63 East of Daniel's Office 0 17 270 0 W DM 64 Riprap W of Intake 0.13 338 5 NNW DM.B5 65 Guard Tower 0.13 22.5 NNE DM,B5 66 Jetty 0.6 33.0 NN E DM 67 Service Water Pond (East Side) 0.5 72.0 ENE DM 68 Fuel Oil Storage Tank 0.2 108.5 ESE DM 69 Exclusion Buoy NNW on Monticello Res. 1.0 337.0 NNW DM 70 Exclusion Buoy N on Monticello Res. 1.0 00N DM 71 Temperature Buoy on Monticello Res 54 30N DM 72 Yard Drain Outf all 04 146.0 SE SW 73 Yard Drain Outf all 04 270 0 W SW 74 Yard Drain Outf all , 0.5 246 0 WSW SW 80 Congaree River 30.2 147.0 55E B5 81 Congaree River 30.1 147.0 SSE B5 82 Congaree River 30.0 147.0 SS E B5 83 Congaree River 28.5 147.0 SS E SS 84 Congaree River 54 2 135 0 SE B5 85 Congaree River 53 8 135 0 SE B5 86 Congaree River 54 0 135.0 SE B5 87 Lake Marion 72 0 138 0 5E B5 88 Lake Marion 72.0 138 0 SE B5 89 Lake Marion , 72 0 138 OSE B5 Table 3 - Sampling Site Locations (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 = Air Radiciodine MK = Milk DM = Monthly TLD GR = Grass (Forage) DQ = QuarterlyTLD GA = Garden ' SW = Surface Water FH = Fish GW = Ground Water BS = Bottom Sediment Table 3 - Sampling Site Locations (continued) i 8
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Comparison Study Lab Date Nuclide EPA Value pesults Agree-(Measurement Unit) ( lo) ment ( 10) 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 2n-65 10(5) 11 (1) Yes Ru-106 75(5) 74 (4) Yes Cs-134 40(5) 36(2) Yes Cs-137 80(5) 79(4) Yes 10/87 Cr-31 70(5) 63(8) Yes Co-60 15(5) 16(1) Yes 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 Jross Beta in Water (pCi/ liter) 1/87 beta 10(5) 12 (P', Yes 3/87 beta 13(5) 11(0 Yes 5/87 beta 7 (5) 8 (1) Yes 7/87 beta 5 (5) 5 (0) Yes 9/87 beta 12(5) 11(1) Yes 11/87 beta 19(5) 15(2) Yes Table 4 - Results of 1987 EPA Intercomparison Program 12
Comparison Stud Lab tog Date Nuclide EPA Value pesul Agree-(Measurement Unf) ( t lo) (f gg) ment lodine in Water (pCi/ liter) 4/87 l-131 7 (1) 7 (2) Yes 8/87 l-131 48(6) 49(2) Yes 12/87 l-131 26(6) 26(2) Yes Laboratory Blind (pCi/ liter) 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 10/87 beta 72(5) 65(1) Yes Co 60 16(5) 16(1) Yes Cs-134 16(5) 16(0) Yes Cs-137 24(5) 25(1) Yes Radionuclides in Milk (pCi/ liter) 2/87 l-131 9 (1) 9 (1) Yes 6/87 l-131 59(6) 68(3) Yes Cs-137 74(5) 78(2) Yes Tritium in Water (pCi/ liter) 2/87 H-3 4209(421) 4650(321) Yes 6/87 H-3 2895(357) 2798(116) Yes 10/87 H-3 4492(449) 4582(91) Yes l Radionuclides in Food (pCi/kg) 1/87 l-131 78(8) 86(2) Yes Cs-137 84(5) 94(2) Yes 7/87 l-131 80(8) 84(3) Yes Cs-137 50(5) 54(2) Yes Table 4 - Results of 1987 EPA Intercomparison Program (continued) l 13 i
Comparison Study Laboratory E Agree-Date Nuclide Room (Measurement Unit) Results1 Results1 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-131 m 6.93 E-4 7.12 E-4 Yes Xe-133 6.15 E-2 7.36E-2 Yes Xe-133m 8.96 E-4 9.64E-4 Yes Xe-135 5.81 E-4 6.40E-4 Yes 1 i Liquid Sample 7/87 Cr-51 1.22 E-6 N/O N/A (pCi/ml) Mn-54 7.79E-7 6.3 3 E-7 Yes Co-57 1.10 E-7 N/O N/A Co-58 1.47E-5 1.23 E-5 Yes Co-60 5.46E-6 4.08E-6 Yes N b-95 4.48E-7 3.11 E-7 Yes Cs-134 1.04E-7 N/O N/A Cs-137 1.24E 7 N/O N/A Am-241 1.07 E-4 1.3 7 E-4 Yes Charcoal Filter 9/87 Co-57 2.3 5 E-2 1.81 E-2 Yes (pCi/m3) Co-60 4.53 E-2 3.56E-2 Yes Y-88 2.15E-2 1.69 E-2 Yes Cd-109 1.25 E0 1.01 E0 Yes Sn-113 1.57E-2 1.31 E-2 Yes Cs-137 5.30E-2 4.2 5 E-2 Yes Ce-139 1.23 E-2 9.53E-3 Yes Hg-203 2.41 E-3 1.89 E-3 Yes 25 ml Gas Sample 10/87 Ar-41 1.67E-4 2.16E-3 No2 (pCi/ml) Kr-85 4.03 E-3 N/O N/A Kr-85m 9.896-5 1.11 E-4 Yes Kr 87 4.60E-5 4.43 E- 5 Yes Kr-88 1.41 E-4 1.74 E-4 Yes Rb 88 2.19 E-2 2.60E-3 No2 Xe-131m 1.2 2 E-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 6.18 E-2 Yes Y-88 1.38E-3 1.44E-3 Yes Cd-109 6.50E-1 7.86E-1 Yes Sn 113 1.45 E-3 1.58 E-3 Yes Cs 137 7.78E 2 8.08 E-2 Yes Ce-139 1.51 E-3 1.66 E-3 Yes
- 1. N/O = not observed
- 2. Disagreement attributed to differences in 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 Nuclidel LocIt 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.
l Results will be reported by SCDHEC. l Table 6 - Summary of 1987 Intercomparison Prog m with South Carolina Department of Health and Environmental Controls 15
I 1986 FOURT H QUARTER RESULT 5 1987 FIRST QUARTER 1987 SECOND QUART ER RESULT 5 1987 THIRD QUARTER 8 NRC TLD LABORA- (uR/hr) RESULTS (uR/hr) (uR/hr) RESULTS (uR/hr) STATION TORY TLD NO STATION NO NRC Laboratory " # '# 'Y N a oratory N a ratory Df re (e Df rence Df rence Df rence 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
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cn 9 *52 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 *S6 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 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
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30 46 10.6 10.2 3.8 11.9 9.9 16.8 10.0 10.0 0 17.6 10.2 42 Co-located dosimeters within 10 f t. of NRC dosimeter. Table 7 - Results of Environmental Dosimetry intercomparison wi th NRC TLD Direct Radiation Monitoring Network
Exposure Pathway Criteria for SClection Sampling and Sample Type & Frequ:;ncy and/or Sample of Sample Numbcr & Location Collection Frequency Location of Analysis - AIRBORNE:
- 1. Particulate A) 3 Indicator samples ta be taken at locations (in Continuous sampler 2 Gross beta following filter dif ferent sectors) beyond but as close to the operation with weekly 5 change; Monthly Composite exclusion boundary as practicable where the collection. 10 (by location) for gamma highest of fsite sectoral ground level isotopic.
(oncentrations are anticipated. B) 1 Indicator sample to be taken in the sector Continuous sampler 6 Gross beta following filter beyond but as (iose to the exclusion boundary operation with weekly change; Monthly Composite as practicable (orresponding to the residence collection. (by location) for gamma having the highest antic; pated of fsite ground isotopic. level concen:tation or dose. C) 1 Indicator sample to be taken 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 weekly change; Monthly Composite most prevalent wind directions. collection. (by location) for gamma isotopic.
- 11. Radioiodine A) 3 indicator samples to oe taken at two Continuous sampler 2 Gamma Isotopic for lodine locations as given in 1( A) above. operation with weekly 5 131 canister collection. 10 B) 1 Indicator sample to be taken at the location Continuous sampler 6 Gamma Isotopic for lodine as given in 1(B) above. operation with weekly 131 canister collection.
C) 1 Indicator sample to be taken at the location Continuous sampler 14 Gamma Isotopic for lodine as given in f(C) above. operation with weekly 131 canister col?cction. D) 1 Control sample to be taken at a location Continuous sampler 17 Gamma Isotopic for fodine simitar in nature to f(E) above. operation vdth weekly 131 canister collection. Table 8 - Radiological Environmental Monitoring Program Specifications
Exposure Pathway Criteria for Selectior. Sampling and Sample Typ2 & Frequ:ncy and/or Sample of Sample Number & Location Collection Frequency Location of Analysis . 111. 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 accessible sectors within 1 to exchange; two or more 5,6,7,8, quarterly. 2 miles of the plant. dosimeters at each location. 9,10,29, 30,47 B) 16 Indicator stations to form an inner ring of Monthly or quarterly 12,14,32, Gamma dose monthly or stations in the 16 accessible sectors within 3 to exchange; two or more 33,34,35 quarterly. 5 miles of 1he plant. dosimeters at each location. 36,37,41, 42,43,45, 46,49, 53,55 C) 20 5tations to be pla< ed in special interest Monthly or quarterly 11,13,15, Gamma dose monthly or areas such as popu:ation centers, nearby exchange; two or more 16,17,18, quarterly residences, schools and in 2 or 3 areas to serve dosimeters at each to(ation, 19,20,31, I as controis. 44,48,50, l 51,52,54, E; 56.57,58 59,60 1 1 Table 8 - Radiological Environmerital Monitoring Program Specifications L__-----__-----_-___-_ _
Exposure Pathw:.y Crit:ria for Se!ecti:n Sampling and Sample Type & Frequ:ncy arid /or Sample of Sample Number & Location Collection Frequency Location of Analysis . WAIERBORNE: IV Surface Water A) 1 Indicator sample downstream to be taken at Time composite samples 21 Gamma isotopic monthly a location which allows for mixing and dilution with collection every 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 ficiently far up-stream with collection every month. with quarterly composite (by such that no effects of pumped storage location) or monthly sample operation are antiopated. to be analyzed for tritium. C) 1 Indicator sample from a location imniediately Time composite samples 17 Gamma isotopic monthly upstream of the nearest downstream with collection every month. with quarterly composite (by I municipal water supply. location) or monthly sample to be analyzed for tritium. D) 1 Indicator sample 1o be taken in the upper Time composite sample, 23 Gamma isotopic monthly reservoir of the pumped storage faolity at the , with collection every m. nth. with quarterly composite (by plant discharge canal location) or monthly samp!e
- to be analyzed for tritium.
w 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 J location) or monthly sample i ! to be analyzed for tritium. l l F) 1 Controf sample to be talen at a location on a Grab sampling monthly 18 Gamma isotopic monthly l separated unaf fected 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 boundary and in the direction of 27 analyses quarterly. l potentially af fected ground water supplies. ; r i B) 1 Control sampfe from unaffected location. Quarterly grab sampling 16
- Gamma isotopic and tritium analyses quarterly.
1 Table 8 - Radiological Environmental Monitoring Program Specifications
1 Exposure Pathway Criteria for Selection Sampling and Sample Type & Frequ:ncy - cnd/or Sampl2 of Sample Number & Location Collection Frequency Location of Analysis . VI Drinking Water A) 1 Indicator sample from a nearby public Monthly grab sampling 28 Monthly gamma isotopic, ground water supply source. gross beta and tritium analyses.
- 8) 1 Indicator (finished water) sample from the Monthly composite 17 Monthly gamma isotopic, nearest downstream water supply. sampling gross beta and tritium analyses.
C) 1 Control (finished water) sample irom the nearest unaffected pubhc wate' supply. Monthly composite 39 Monthly gamma isotopic, sampling gross beta and tritium l analyses. INGESTION: VII Milk A) Samples from milking animals er. 3 locations Biweekly grab ia. Gamma isotopic and 1-131 within 5 km having the highest dose potential. sample. -a% analysis biweekly. If there are none then 1 sample from milking . ,,,na , animals in each of 3 areas between 5 to 8 km w.a . .. $ distance where doses are calculated to be <, va . greater than 1 mrem per year. B) 1 Control sample to be taken at the location of Biweekly grab 16 Gamma isotopic and 1-131 a dairy > 20 miles distance and not in the most sample. analysis biweekly. prevalent wind direction. C) 1 Indicator grass (forage) sample to be taken at Monthly when 6 Gamma isotopic. one of the locations beyond but as close to the available exclusion boundary as practicable where the highest of fsite sectoral ground level (on(entrations are anticipated D) 1 Indicator grass (forage) sample to be taken at Monthly when vo t. wi Gamma isotopic. the lo(ation of Vil( A) above when animals are available o i. .m on pasture. ..w,,,
.u o.. . ..ee.
(ftt.f 44 ( W 46 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 Pathway Criteria f:r Selection Sampling and Sampla Type & Frequency and/or Sample of Samply Number & Location Coll:ction Frequency Location of Analysis . Vill. food Prodacts A) Two samples of broadleaf vegetation grown in Monthly when available. 6 Gamma Isotopic on edible 1 location of specialinterest and in the 1 near- 8 portion. est offsite location of highest (alculated annua; average ground level D/Q if milk j sampling is not performed within 3 km or if ! l milk sampling is not performed at a location within 5-10 krr 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 18 Gamma Isotopic on edible taken at a location at least 10 miles distance appropriate. portion. and not in the most prevalent wind direction. l l IX. Fish A) 1 Indicator sample to be taken at a location in Semiannual collection of the 23 Gamma isotopic on edible the upper reservoir. following specie types if portions semiannually. available: bass; bream, I C crappie; catfish, carp; 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 types ei portions semiannually. available: bass; bream, crappie; catfish, carp; forage fish (shad). C) 1 Indicator sample to be taken at a location in Semiannual collection of the 24 Gamma isotopic on edible the upper reservoir's non-iluctuating following specie types if portions semiannually. re(reational area. available: bass; bream, crappie; catfish, carp; forage fish (shad). D) 1 Control sample to be taken at a location on Semiannual collection of the 22 Gamma isotopic on edible the receiving river suf ficiently far upstream following specie types if portions semiannually. such that no ef fects of pumped storage available; bass; bream, operation are anticipated crappie; catfish, carp; forage fish (shad). Table 8 - Radiological Environmental Monitoring Program Specifications
Exposure Pathway Criteria for Selection Sampling and Sample Type & Frcs quency and/or Sample of Sample Number & Location Collection Frequency Lt, cation of Analysis . AQUAllC: 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 tak en at a location in Semiannual grab sample. 24 Gamma isotopic. the upper reservoir's non-fluctuating recreational area C) 1 Indicater sample to be taken on the shoreline Semiannual grab sample. 21 Camma 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 suf ficiently far upstream such that no eff e(ts of pumped storage operation are anticipated. N 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 tan en at locations (in Continuous sampler 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 critical receptor isotopic.
for the chosen sector. 111. Direct D) 85tatioas to be placed within the exclusion Monthly or quarterly 61,62 Gamma dose monthly or boundary (Special $tudy). 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 quarterly 69 Gamma dose monthly or Reservoir (Background Study) exchange; two or more 70 quarterly. dosimeters at each location. 71 WATERBORNE: IV. Surface Water G) 1 indicator sample to be taken in the upper Time composite samples 25 Gamma isotopic monthly y reservoir at the intake of the pumped storage with collection every month. with quarterly composite (by w facilsty. location) or monthly sample to be analyzed for tritium. INGESTION: VII. Milk A) Samples from milking animals in 3 locations Biweekly grab sample 14 Gamma isotopic and 1-131 within 5 k m having the highest dose potential. analysis biweekly. If there are none then 1 sample from milking animalsin each of 3 areas between 5 to 8 km distance where doses are cal (u?ated 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 Radiological Environmental Monitoring Program
o # Exposure Pathway Criteria for Selection Sampling and Sample Type & Frequency and/or Sample of Sample Number & Location Collection Frequency Location of Analysis Vill. Food Products C) 1 Indicator sample of each of the various types Annually during growing 6 Gamma Isotopic on edible of foods grown in the area surrounding the season. portion. plant. D) 1 Control sample of the same foods collected in Annually 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. X. 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 VC5N5 liquid effluent discharge point. y G) Ten (10) additional indicator samples to be Semiannual grab sample. 80,81 Gamma isotopic.
- 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 . YPe and Total Location with Highest Annual Mean Number of Medium or Pathway Lower Limit of AllIndicator Number of Control Le itions Nonroutine sampled (Unit of Analyses e e(tion 1 tm tions (Name, Distance & Mean2 Mean2 (Range) Reported 3 Measurement) p g9 Actual (Max ) Mean2 (Range,r (Range) Direction) Measurements Asr P2 ct:( late Gross Beta 4 4 4E-3 2.4 E-2 (468/468) Site 13, North Dam 6W2/52) 23E-2 ( W4M W (pC:/m3) ( ' (570) O OE-2) (0 8E-2 to 4 9E-2) (2.9 mi NNW) , Gamma Spet 0 32) Cs-134 All < LLD All < LLD 0
)
Cs- 137 All < LLD All < LLD 0 (6 O Air Radiciodine) 3.1E-2 f oCi/m i) 3 3 All < LLD All < LLD 0 (7 OE-2) Direct (ILD)6 Gamma (164) 5 2E-1 ( 0 / 04) Site 9. Bau Park 12.3 O In U 9 8(60/60) 0 (pR/hr) Monthly (6 8 to 12.9) (2.2 mi, NE) (12.0 to 12.9) (6 4 to 12.9) Gamma (108) % OO M 08) Sate % R Barna %s 14.3(4/4) 5 ,g_ , 9 Ouarterly (6 0 to 14 9) Church (2.8 mi. F) 03 6 to 14.9) , surface Water 4.3E + 2 Site 17, Columbia + 2 (2n 3) 5.5E + 2 (3/63) (pCi/I) "~ I09} (4.8E + 2 to 6 6E + ,2) Canal (24.7 mi, SE)
* ^ <
(2.0E + 3) (b 6E +) Gamma Spec (89) Mn-54 All < LLD All < LLD 0 5 2 0E Co-58 g5 All < LLD Ah < LLD 0 6 Fe-59 All AU < 0 (3 0E 1) 2 4E-1 Cc-60 All < LLD All < LLD 0 g, Zn-65 All < LLD All < LLD 0 (3 0E 3 Zr-95 All < LLD All < LLD 0 3 0E Nb-95 All < LLD All < LLD 0 O SE 8 C5- 134 All < LLD All < LLD 0 0 E 1 Table 10 - 1987 Radiological Environmental Monitoring Program Summary 1
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/87-12/31/87 . Type and Total I Location with Highest Annual Mean Number of Medium or Pathway Number of L wer U it of AH Indicator Sampled (Unit of Detection 1 Locations Control Locations Nonroutine AnalUes (Name, Distance & Mean? Mean2 (Range) Reported 3 Measurement) Actual (Max.) Mean2 Nnge) Performed Direction) (Range) Measurements 2.0E-1 8.3E-1 (5/63)
*^ Resen 6 M to AH < RD 5 (1.8E + 1) (7.2E-2 to 1.0E0)
(2.7 mi SSW) 1.0E0) Site 25, Fairfield 1.0E0 (1/12) Pumped Storage (Single (0.9 mi., WNW) Value) Ba-140 (6 bE + 1)
^"< ^"
65 La-140 g All < LLD All < LLD 0 3 Ground Water 4.3E + 2 Site 26, Onsite Well 6.8E + 2 (2/4) 6 8E + 2 (2/8) (pCi/1) ' (2.0E + 3) (5 3E + 2 to 8.3E + 2) ( * ^"< P4 (265 f t. W) 3E + 2) Gamma Spec y (12) M n-54 gf q All < LLD All < LLD 0 Co-58 O SE + 1)
^" ^"
F e-59 All < LLD All < LLD 0 30 Co-60 gf All < LLD All < LLD 0 Zn-65 AH < AH < 0 (3 0 + 1) Zr-95 (3 b + 1)
^" ^"
3 Nb-95 AH < D AH < RD 0 (15 + 1) Cs-134 AU AH < 0 O SE + 1) Cs-137 gg All < LLD All < LLD 0 Ba-140 [ All < LLD All < LLD 0 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 . Type and Total location v.ith Highest Annual Mean Number of Medium or Pathway L wer Limit of AH Indicator Sampled (Unit of Number of Control Lo(ations Nonroutine Detectiori 1 LMations (Name, Distance & Mean2 Anal Mean? (Range) Reported 3 Measurement) Perfor ed (tua (M () Me (Range) Direction) (Range) Measurements La-140 AH D AH < @ 0 (15 + 1) Drinking Wzter7 2.5E0 6 OE0 (18/25) Site 28, NTC "' (pCill) (4 OEO) (2.4E0 to 12E + 1) (2.4 mi, SSE) 1.2E + 1) 1.'7 E + 1) 4.3E + 2 5.0E + 2 (3/38)
"~
(2 OE + 3) (4 7E + 2 to 5.2E + 2)
* ^" ~
SE) 5 2E + 2) Gamma Spec (38) Mn-54 ^"< ^"< (1 SE 1) Co-58 E All < LLD All < LLD 0 $ Fe-59 (3 0 + 1) AH AH 0 2 Cv 60 AH < LL AH < LL 0 g 5E D Zn-65 ^"< ^"< (3 OE 1) Zr-95 All < LLD All < LLD 0 30 4 Nb-95 All < LLD All < LLD 0 O SE 1) 1-131 All < LLD All < LLD 0 00 I Cs-134 AH < D AH < RD 0 (1 SE 1) Cs-137
- 1. 7 E- 1 All < LLD
' 0 (1.8E + 1) (Single Value)
Ba-140 AH < AH < D 0 (60 + 1) La-140 All < LLD All < LLD 0 0 E Mdk Gamma Spec (pCi/l) (51) 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 . Type and Total L cation with Highest Annual Mean Number of gg, ,p, Lower Limit of All Indicator
"* ' ' Locations sampled (Unit of Detection 1 (Name, Distance & Mean', Mean2 (Range) Reported 3 Analyses Measurement) Performed
^< U8I I '" I '" "9'I Direction) (Range) Measurements I-131 All < LLD All < LLD 0 OE0 3 2E0 1.4E0 (1/26) Site 14, Dairy
( "9
^"
(1.5E + 1) (Single Value) (6 3 mi W) y Site 14 Dairy . O U W26) 3 SEO 3 4E0(IW26) 4.1 E0 (14/25) (1 BE + 1) ,I SE0 to 7.1E0) (6.3 mi W) (1.7E0 to 8.4E0) 0 Ba- 140 , All < LLD All < LLD 0
)
La-140 AH < AH < D 0 (15 + 1) Grass (pCi/kg wet)
"***f P $ l-131 6
All < LLD All < LLD 0 Cs-134 All < LLD All < LLD 0 ( 19E + 1 7 IE0 (2/16) Site 6 Garden 5.3E0 (2/10) (8 OE + 1) (5 6E0 to 8 6EO) (1.0 mi ESE) (5 2E0 to 5.3EO) 6EO Broadicat vegetation Gamma Spa ( (24) (pC /kq wet) 1-131 All < LLD All < LLD 0 E+ Cs- 134 All < LLD All < L - D _ 0
* *'I' I Cs-137 All < LLD O (8 OE + 1) (Single Value) l Other Vegetation (pCi/k o wet) 1-131 All < LLD All < LLD 0 9 6E0 Site 6 Garden 2 8E0 U/2) 2 8E0 (1/2)
~
(6 OE + 1) (Single Value) (1.0 mi ESE) ( "9 #" < y Table 10 - 1987 Radiological Environmental Monitoring Program Summary 1
Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, south Carolina Reporting Period: 1/1/87-12/31/87 . Type and Total Location with Highest Annual Mean Number of Medium or Pathway g Lower Limit of All Indicator Sampled (Unit of Detection 1 Locations Control Locations Nonroutine Anal e (Name, Distance & Mean2 Mean2 (Range) Reported) Measurement) P for ed ctual(Mat) Mean2(Range) Direction) (Range) Measurements
' Site 6 Garden ($ n 1 All < LLD 1
( 1) ($ ng e alue) (10 mi ESE) Value) Fish (pCs/k9 wet) (31) Mn-54 All < LLD All < LLD 0 1.8E + 1 4.4E + 1 (1/24) Site 21, Parr Res (. 9 ^" (1.3E + 2) (Single Value) (2.7 mi, SSW) y F e-59 gy All < LLD All < LLD 0 1.6E + 1 1.8E + 1 (2/24) Site 21 Parr Res. (1.3E + 2) (2.7 mi,55W) ( * ^"< (1.3E + 1 to 2.2E + 1) fE Zn-65 g, All < LLD All < LLD 0 Site 21, Parr Cs-134 All < LLD 9 (1.3E + 2) (5 2E0 to 1.3E + 1) (2.7mi,55W) (5 3E0 to 1.3E + 1) Cs-137 Site 24, Rec Lak e O (1.5E + 2) (1.0E + 1 to 5.6E + 1) (5 Sms,N) (' * ( ' ' 5 6E + 1) Sediment (pC:/) g)8 M n-54 1.9E + 1 All < LLD All < LLD 0 Co-58 2.2E + 1
* ' ' #" * (
Reservoir All < LLD 7 (7.4E0 to 5 6E + 1) (7.8E0 to (2.7mi,55W) 5 6E + 1) 6 4E + 1 6 OE + 1 (15/37) Site 21, Parr (11/16) Co 60 76E + 1 All < LLD 15 (1.5E + 1 to 1.2E + 2) Reservoir (1.5E + 1 to (2.7mi, SSW) 1.2E + 2) Table 10 - 1987 Radiological Environmental Monitoring Program Summary
. a Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/87-12/31/87 .
Type and Total ' Medium or Pathway L wer Limit of All indicator location with Highest Annual Mean Jumber of sampled (Unit of W m W of Control Locations Nonroutine Detection 1 Locations AnalY (Name, Distance & Mean2 Mean2 (Range) Reported 3 Measurement) p ,g Actual (Max ) Mean2(Range) Direction) (Range) Measurements Site 21, Parr 1.bE + 1 (7/1b) 2.0E + 1 1.2E + 1 (12/37) 1.1E + 1 (1/5) Cs-134 Reservoir (7.5E0 to 0 (1.5E + 2) (5.7E0 to 2.5E + 1) (Single value) (2.7mi. 55W) 2.3E + 1) Cs-137 1.E+1 1.1E + 2 (37/37) Me 21, Pan (W 1.2E + 2 (5/5) (7.8E + 1 to 0 (1.8E + 2) (61E0 to 3 OE + 2) Re:ervoir (4.6E + 1 t (2.7mi,55W) 1.9E + 2) 3.0E + 2) Table 10 - 1987 Radiological Environmental Monitoring Program Summary
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. Any confirmed measured level of radioactivity in any environmental medium that exceeds ten times the control station value.
Radioactivity attributed to the Chernobylincident was not reported as non-routine measurements provided measurements f rom control locations were pusitive 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
- 5. One sample exceeded maximum LLD because of low sarnple volume. 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.
w 7. Elevated levels of Pb-214 and Bi-214 were observed in all Jenkinsville drinking water samples. The values are not reported
~
here because they are naturally occurring (do not originate from VCSNS) and furnish no quantifiable information of interest.
- 8. Elevated levels of Pb-214 and Bi-214 plus other Ra-226 daughter products and Ac-228 plus other Th-232 daughter products were observed in all sediment samples. The values are not reported here because they are naturally occurring (do not originate from VCSNS) and furnish no quantifiable information of interest.
Table 10 - 1987 Radiological Environmental Monitoring Program Summary
g o
~
Medium or Pathway Type and Total L cation with Highest Annual Mean Number of I Sampied (Unit of Lower Limit of All Indicator Number of '
* "5 "' "*
Detection 1 Locations Measurement and Analyses (Name, Distance & Mean2 Mean2 (Range) Reported 3 Reporting Peric,d) Actual (Max.) Mean2 (Range) Performed Direction) (Range) Measurements 1.3E-1(52/52; 1.1E-1 (562/564)4 Site 13,16rth Dam (2.1 E-2 to 1.2E-1 (153/155) Air Particulate (1.3E-2 to 5.5E-1) (2.9 mi NNW) 55E-1) (7.9E-3 to 6.1 E-1) G Bm 41E-3 (1300) (1.0E-2) (1981 82) 2.7E-2 (456/462)8 Site 8, Mon. Res 5 of 3.0E-2(42/42) 2.8E-2 (125/126) (9.3E-3 to 6 6E-2) Rd 224 (1.5 ENE) (1.2E-21o (1.2E-2 to 5.8E-2) 6.0E-2) Gamma 5pec (307) Cs-134 All < LLD All < LLD 0 3.1E-3 3.2E-3 (22/241) Site 10, Met Tower 3.8 -3(2/22)
~
4.2E-3 (4/66) (1.0E-2) (1.5E-3 to 5 2E-3) (2.4 mi NNE) (3.2E-3 to 5.6E-3)
-3
-131(290) All < LLD All < LLD 0 C/m 8 [7 hr Gamma (1220) 9.9(915/915) Site 13, North Dam 13.1I61/61) 9.7(305/305) 0.5 0 Monthly (6.7 t014.7) (2.9 mi N NW) (12.2 to 14.2) (6 4 to 13.5)
(1978-1982) Gamma (161) '
- d'"' 35 0.5 0 Quarterly (6 81014.7) Church (2.8 mi E) (13.1 to 14.7) ur ace ater I * *
(pCi/l) 1.1 E + 3 1.4E + 3 (18/29) Site 17, Columbia H-3(43) ( * * * * (2 OE + 3) (1.1 E + 3 to 2.4E + 3) Canal (24.7 mi, $E) a (1981-1982) 1.8E + 3) 1.6E + 3) Gamma Spec (140) 2 7E-1 Mn-54 g All < LLD All < LLD 0 2 Co-58 (j 5E 1) All < LLD All < LLD 0 All < LLD All < LLD 0 (3 0 + 1) . Table 11 - Radiological Environmental Monitoring Program Summary Preoperational(Baseline) Summary
Medium or Pathway Type and Total Location with Highest Annual Mean Number of Sampled (Unit of Lower Limit of All indicator Number of U" ' * "' " Detection 1 Lo(ations Measurement and Analyses (Name, Distance & Mean2 Me3n? (Range) Reported 3 Performed
! Mm? (Rany)
Reporting Penod) Direction) (Range) Measurements Co-60 All < LLD All < LLD 0 0 5E 1) Zn-65 #'H AH < LLD 0 (3 OE 1) Zr-95 All < LL9 All < LLD 0 5 N b-95 All < LLD All < LLD 0 05 3 OE 1 Cs-134 g All < LLD All < LLD 0 C5-137 All < LLD ' All < LLD 0 08 Ba-140 Al < LLD All <' LLD 0 6 +0 La-140 5.5E-1 (1982 only) All < LLD All < LLD 0 (1.5E + 1) Ground Water 9.0E + 2 1.5E + 3 (16/16) Site 26. Or. site Well 1.6E + 3 (&8) L3E + 3 W3)
"' (9 * ( *
(pCi/l)(1981-1982) (2.0E + 3) (9.5E + 2 to 2.3E + 3) P4 (265 f t, W) 3+3 9 +3 Gamma spec (32) 0 M n-54 g All < LLD All < LLD 0 38 Co-58 4, 5E + 0 All < LLD All < LLD 0 l Fe-59 AH < AH < LLD 0 (3 OE + 1) Co-60 All < LLD All < LLo 0 0 5 + 1) 8 Zn-65 All < LLD All < LLD 0 (3 0E + 1) Table 11 - Radiological Environmental Monitoring Program Summary Preoperational(Baseline) Summary I
Medium or Pathway Type and Total "# "* "9# ^"""#' '#" "" ' Sampled (Unit of Lower Limit of All Indicator Number of " U # " U"' " "* Detection 1 Locations Measurement and Analyses # ** #" # ##" #"9 # Actual (Max ) Mean2 (Range) Reporting Period) Performed Direction) (Range) Measurer ents 6 Zr-95 AH AU < D 0 (3 5 + 1) N b-95 All < LLD All < LLD 0 O5 0 Cs-134 An AH < 0 O SE + 1) Cs-137 gg y All < LLD All < LLD 0 B a-140 All < LLD All < LLD 0 { (198 only) (15 + 1)
^" #" < 0 Drinking Watert-Gross Beta 7 (2.0E0)
(pCi/1)(1981-1982)
. + e 8,JenUnsWHe
+ 1)
H-3(14) {7OE+ t (1.0E + 3) (6 BE + 2 to9 BE + 2) (2.0 mi SE)7 gg Gamma 5pec (44) 0 3o Mn-54 gg All < LLD 0 Co.58 g2 7E;1 p All < LLD 0 Fe-59 ^"< (3 0 + 1) 2 6E-1 co-60 g, All < LLD 0
)
3 Zn-65 (30E;O All < LLD 0
#8 Zr-95 All < LLD 0 O$E 1)
Table 11 - Radiological Environmental Monitoring Program Summary Preoperational(Baseline) Summary
Medium or Pathway l Type and Total # 9 ^"""#' ##" Sampled (Unni of Lower Limit of All Indicator Number of Control Locations Nonroutine Measurement and Analyses Des 1 Wim (Name, Distance & Mean2 Mean? (Range) Reported 1 Reporting Period) Performed MU 2 RM Direction) (Range) Measurements Nb-95 ^"< (1 SE 1) l-131 All < LLD 0 OE0 Cs-134 All < LLD 0 00 C5-137 g g All < LLD 0 Ba-140 All < LLD 0 6 E+4 La- 140 4 4E-1 All < LLD 0 (1982 only) (1.5E + 1)
, Gamma 5pec
$ (1981-1982) 1-131 All < LLD All < LLD 0 00 Cs-134 g j ,y All < LLD All < LLD 0 4.6E0 4.1 E0 (8/47) Site 14, Dairy 4.1 0(&47) 5.7E0 (37/47)
(1.5E + 1) (2 8E0 to 6.1EO) (5.1 mi., W) 0to 12 W 61E0) Ba-140 All < LLD All < LLD 0
)
La-140 ^" #" < (1 SE + 1) Grass (pCi/kg wet) Gamma 5pec (1981-1982) (82) 1-131 All < LLD All < LLD 0 Table 11 - Radiological Environmental Monitoring Program Summary Preoperational (Baseline) Summary
~
Medium or Pathway l Type and Total 9 ^ "#' #" " Sampled (Unit of Lower Limit of All Indicator Number of Control Location > Nonroutine DNim 1 Miom Measurement and Analyses (Name, Distance & Mear.2 Mean2 (Range) Reported 3 Reporting Penod) Performed M M W (R M Direction) (Range) Measurements Cs-134 , All < LLD All < LLD 0 3 3E + 1 Site 14, Dairy 5.9E + 1 (W9) 1.3E + 2 W31) 5.0E + 1 (13/51) (8.0E + 1) (16E * ' (' ' (1.6E + 1 to 1.6E + 2) (5.1 mi W) f E+ 3 Broadleaf Vegetation (pCi/k g wet) Gamma Spec (10) (1980-1982) 1-131 g All < LLD All < LLD 0
+
C5-134 All < LLD All < LLD 0 E+ 2.1 E + 1 Site 2, Trans Line 3.6E + 1 (1/1) 5.1E + 1 (2/7)
~
( g AH < LLD 0 (8 OE + 1) (1.8E + 1 to 3.6E + 1) (1.2 mi SW) Other Vegetation Gamma Spec (pCi/b g wet) ( ' (1980-1982) Cs-134 All < LLD All < LLD 0 (8 OE + 1) Cs-137 All < LLD All < LLn 0 Fish (pC /kg wet) Gamma Spec (1980-1987) (92) Cs-134 All < LLD All < LLD 0 8E+1
- 2.8E + 1 NO 9e 24, Rmeation 7/23)
C5-137 (1.0E + 11 0 (1.3E + 2) (1.1E + 1 to 1 OE + 2) Lake (5.5 mi, N) (1.2E + 11 7.9E + 1) 1.0E + 2) Co-58 All < LLD All < LLD 0 Table 11 - Radiological Environmental Monitoring Program 5ummary Preoperational(Baseline) Summary ,
Medium or Pathway Type and Total L cation with Highest Annual Mean Number of Sampled (Unit of r i it d All IMicator Number of " ' # "$ "' "* Detection 1 Locations Measurement and Analyses (Name, Distance & Mean2 Mean2 (Range) Reported 3 Reporting Penod) Performed A l(Ma) Me-M N @ Direction) (Range) Measurements Mn-54 All < Li D All < LLD 0 { ) Fe-59 All < LLD All < LLD 0 ( 6 ) Zn-65 [) All < LLD All < LLD 0 Co-60 All < LLD All < LLD 0 5ediment (pCi/kg) Gamma Spec (1980-1982) (24) Cs-134 All < LLD All < LLD 0 5 e , an + + 6) 2.4E + 1
- 1.7E + 2 (12/18)
(1'SE + 2) (2.6E + 1 to 4.5E + 2)
* (~ * * *
$ (2.7 m;.55W) 4.5E + 2) 1.0E + 3) Table 11 - Radiological Environmental Monitoring Program Summary Preoperational(Baseline) Summary
4 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 nonroutine measurement is any confirmed measured level of radioactivity in any environmental medium that exceccds ten times the control station value.
- 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 g data.
- 6. No control location was specified for drinking water during the preoperational monitoring period.
- 7. Inconclusive data. Refer to the Preoperational Radiological Environmental Monitoring Report.
Table 11 - Radiological Environmental Monitoring Program Summary Preoperational(Baseline) Summary
l
- l s a l
l 4 Media Sam e nth tgc n ek N ,) 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 I Milk 16 April (10) Closing of control dairy Grass 6 January Seasonal Unavailability February March April October December 14 January Seasonal Unavailabiliiy 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 (brean1) 22 May Seasonal Unavailability Table 12 - 1987 Environmental Sanipling Program Exceptions 39
1 I i , Airborne gross beta activity measured in air particulate samples collected at indicator locations around VCSNS were consistent with preoperational levels and comparable to operational control levels. Mean preoperational control and indicator levels were 2.9E 2 and 3.0E 2 pCi/m3, respectively. Mean indicator and control location measurements during 1987 were 2.4E 2 and 2.5E 2 pCi/m3, 4 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 2.6E 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 1-131 were 2.3E 3, 2.4E 3 and 3.1E 2 3Ci/m3, respectively. The results agree with gaseous effluent release 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 and dilution factors experienced during the releases. Environmental dosimetry measurements during 1987 did not differ significantly from preoperational measurements over the same seasonal time a ' periods. Indicator and control dosimetry measurements also showed no appreciable differences during 1987. The lowest mean exposure rate of 6.210.5 pR/hr was observed at sampling location no 58 (residence in Jenkinsville). Sampling location no 55 at St. Barnabas Church near Jenkinsville (2.8 mi, E) was the indicator location i 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 preoperational period and confirms the long term stability of background levels measured at this monitoring location. Gaseous effluent release data reported for j 1987 indicated a total of 6.3E + 2 Ci of fission and activation gases released from VCSNS. An extensive search of environmental dosimetry data and meteorological data during the release periods indicated no evidence of detectable activity attributable to the releases with only natural background variations evidenced. . Gamma spectroscopy measurements of surface water samples did not indicate the presence of activated corrosion and most fission aroducts above the respective MDA's. All MDA's were less than the requirec respective LLD's. Analytical results of five surface water samples collected in Monticello and Parr , Reservoirs during August and September,1987 indicated a mean Cs-137 l 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 i VCSNS, a level not discernable in environmental media based upon consideration of l dilution factors experienced during the releases and the detection lirnits of i analytical methods. The presence of Cs 137 is, therefore, attributed to residual j fallout from atmospheric weapons testing and the 1986 Chernobylincident. l Tritium analyses of surface water samples during 1987 yielded results which were not noticeably different from preoperational data. All but 3 of 63 indicator I tritium activity measurements were less than the mean calculated MDA value of 1 4.3E + 2 pCi/ liter. The maximum indicator tritium activity of 6.6E + 2 pCilliter was l measured in Columbia Canal. Activity levels measured at the indicator locations are l l 40 l n
I o .
.I 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 1937 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 .'or the respective radionuclides. All MDA's were less than the respective required LLD's. High background levels of Pb-214 and Bi-214, daughters of Ra-226, were again detected at control sampling location no 16 (28 mi, W). The presence of these radionuclides is attributed to the uranium found in the large amount of granite in this area of South Carolina. The radionuclides Pb-214 and Bi-214 are major gamma emitting daughters in the uranium series decay scheme produced through the decay of dissolved Rn 222 gas in the ground water. No evidence of radioactivity from VCSNS operation was detected. 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 pCilliter; a level consistent with the preoperational mean of 1.5E + 3 pCilliter. Gamma spectroscopy measurements of drinking water samples collected from the lenkinsville 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 4.3E + 2 pCi/ liter. 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 1986 Chernobylincident. Naturally occurring 41
s . .t 6 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 1987. Gamma spectroscopy measurements revealed Cs-137 at a concentration of 2.0E + 1 pCilkg in one sample 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 samp'es at concentrations consistent with those observed during the preoperational period. Detectable levels of Cs-134 and Cs-137 were rneasured in squash collected from the indicator garden location (no.6,1 mi., ESEi at levels of 2.8 and 6.0 pCi/kg, respectively. The level of Cs-137 was consistent with preoperational data and attributed to residual fallout from atmospheric weapons testing and the 1986 Chernobylincident. The detection of Cs-134 was attributed to residua! fallout from the 1986 Chernobyl incident. 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 samphng 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 iridicator 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 were 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 primarily attributed to residual fallout from the 1986 Chernobylincident and, to a much lesser exte,t, liquid effluent releases during the first six months of 1987 which included a tota of 1.7E 2 Ci of Cs 134. The hmitation of Cs-134 from residual fallout to indicator It :ations 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 take. Sedimentation in lakes and reservoirs which characterize the indicator sampling locations is less 42
o .
.t O
dynamic relative to that in a river which characterizes the control sam aling location. Cesium 134 attributed to liquid effluent releases from VCSNS woulc be limited to Parr and Monticello Reservoirs. '.he 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 during the refueling and maintenance outage as the semiannual effluent release reports indicate. The activity of Co 58 and Co 60 released prior to and during the collection period wcs 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 1.5E-3 Co-60 2.2 E + 1 1.8E + 1 1.8 E-3 Total 3.3 E-3 Table 13 - 1987 Activated Corrosion Product Activity in Fish Gamma spectroscopy measurements of sediment samples collected during 1987 also indicated the presence of activated corrosion and fission product activity Cesium-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 vs as 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 areoperational and control measurements and concentrations expected due to resic ual 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 FP5F's generating mode and subsequent operation of the reversible pump turbine units during periods of off-peak powerdemand. Radiation doses to man, corresponding to the concentrations of activated corrosion product activity in sediment, were colculated using Regulatory Guide 1.109 methodology. A 400 hr/ year exposure to shoreline sediment contaimng mean detected concentrations of Co-58 and Co 60 was assumed. The results are included in Table 14. 43
o o-ee C Corresponding Calculated AnnualDose Location Radionuclide Activity (pCi>kg) Equivalent (mrem) Maximum Mean Shallow Deep Monticello Co 58 7.4E0 7.4 F0 9.3 E-4 8.6E-4 Reservoir Co 60 7.0E + 1 5.6E + 1 1.8E 2 1.5E 2 Total 1.9E 2 1.6E 2 Parr Reservoir Co 58 5.6E + 1 3.5E + 1 4.6E-3 4.0E-3 , Co-60 1.2 E + 2 6.4E + 1 2.0E 2 1.8E 2 Total 2.5E 2 2.2E 2 Table 14 - 1987 Activated Corrosion Product 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 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 Reservon and sediment from Parr and Monticello Reservoir are the only environmentalindicators 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 small fraction of observed variations in local natural background. These insignificant doses will not result in observable effects on the ecosystem or the public. The results of the Radiological Environmental Monitoring Program therefore substantiate the continuing adequacy of source control at Virgil C. Summer Nuclear Station and conformance of station operation to 10 CFR 50, Appendix I design goals. 44
R s.aq l gth Car ins Electric & Gas Company Jenkinsvipe. SC 29065 Nuclear Operations . SCE&G A*" !
' " ~ '
April 27,1988
.2 ~. : : 54 :
Dr. J. Nelson Grace Regional Administrator ! U. S. Nuclear Regulatory Commission , Region ll, Suite 2900 , 101 Marietta Street, N.W. : Atlanta, Georgia 30323 ! t
Subject:
Virgil C. Summer Nuclear Station l Docket No. 50/395 L Operating Licensing No. NPF-12 Radiological Environmental Monitonng Report !
Dear Dr. Grace:
Enclosed is the South Cerolina Electiic & Gas Company (SCE&G) Annual Radiological Envi onmental Monitoring Re aort as required by Regulatory Guide 4.8 and Sections 6.9.1.6 and 6.9.1.7 of the Virgi C. Summer Nuclear Station Technical Specifications. Also, ' requirements as specified by Section 4.12.3 of the Technical Specifications have been included in the report ! If there are any questions, please call us at your convenience. l l Very truly yours, i l 0//b 8 / D. A. Nauman DCB: DAN:mn Enclosure , , c: J. G. Con nelly, Jr./O. W. Dixo n, J r/T. C. Nich ois, J r. 1 E. C. Roberts ! W. A. Williams, Jr. 5. R. H u nt l
- General Managers K. E. Nodland [
L A. Blue G. O. Percival j
; R. B. Clary R. L. Prevatte ;
J. R. Proper J. B. Knotis, Jr. R. M. Campbell Document Managernent 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) l W. R. Baehr
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