ML20086R957
| ML20086R957 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/31/1990 |
| From: | Dinkins J SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| References | |
| NUDOCS 9201020326 | |
| Download: ML20086R957 (43) | |
Text
{{#Wiki_filter:- __________ _ ____________- ________ ____ -_________ _________ ______ Virgil C Summer Environinental Surveillance Laboratory O Jenkinsville, South Carotina RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT VIRGIL C. SUMMER NUCLE AR ST ATION FOR THE OPERATING PERIOD JANUARY 1,1990 - DECFMBER 31,1990 APRIL 1991 i
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V C. SUhihiEll NUCLEAR STKl'lON SOUTil CAllOLINA ELECTitlC AND GAS COMPANY Prepared by: Reviewed by: N ,LLL _A T Dirikins, Su pervisor on 'A. ilhue, Manager Radiological AnalyticalServices Corporate Health Physics and Environmental Programs
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1 E xecutive Summary
- 1. Results of the 1990 land Use Census indicated no significant movement of critical receptors except for a new maximally exposed individual 1.1 miles in the East sector. There were no locations identified where a calculated dose exceeded limits specified in VCSNS Technical 5pecifications, Section 4.112 3.
- 2. There was no detection of radioactivity in environmental media attributed to gaseous of fluent releases from VCSNS.
- 3. Activated coirction products attributed to liquid effluent releases from VCSNS were detecte.d in foi and sediment. Radiation do .e to the general oublic attributed to this activity is a small fraction of the observed variation in natural backgrouno radiatic o
- 4. Detection of f ssg,n 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 5, Results of the Radiological Environmental Monitoring Program substantiate the continuing adequacy of source control at VCSNS and conformance of station operation to 10 Cf R 50, Append . Idesign goals.
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l i i l i l. I TABLE OF CONTENTS ( khD2 ; Introduction . 1 Description of the Radiological Environmental Monitoring Program 2 I
- Results and Discussion 2
5 l Conclusion - 40 1 i e I P i l IO l l ! l l . i I .I I i 5
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l l l Introduction Virgil C. Summer Nuclear Station (VCSNS) utihres a pressurved water reactor rated at 2775 MWt (900 MWe gross) The station is located adjacent to the Monticello Reservoir near Jenkinsville, South Carolina, tnd approximately 26 miles northwest of Columbia. VCSNS achieved imtial criticality on October 22, 1982, reached 50% power on December 12,1982, and 100% power on June 10, 1983, following stearn generator feedwater preheater modifications. VC5NS is currently opera-ting in it: sixth fuel cycle. VCSNS is operated in conjunction with the adjacent Fairfield Pumped Storage Facihty (FP5F) which consists of eight reversible pump turbine units of 60 MWe capacity each. During periods of off ceak power demand, base load generatmg capacity is used to pump water f,om Parr Reservoir to Monticello Reservoir. Monticello Reservoir has a surMce yea of approximately 6800 acres and lies about 150 feet above Parr uwn er W i se full pool area is approumately 4400 acres. The pump-tulane ett verate in the generating mode to meet peak system loads, whik Montae: Reservoir also provides condenser coohng water for VCSN5. C o u ?. , - .ater intake and dischar structures are separated by a jetty to ensure adequate circulation within ge he reservoir. VCSNS is located in Fairfield County which, with Newberry County, make 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 prmcipally producing small grains, feed crops, and beef cattle. Significant portions of Lexington and Richland Counties are encompassed within the 20 mile radius of she plant and exhibit similar agricultural activities. Columbia, the state capital,is the only large city within the 50 mile radius of the plant. Small agricultural concerns are predominant, but make up 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/Parr Reservoirs at two discharge points the Circulating Water Discharge Canal (CWDC) and the FPSF Penstocks. Un arocessed steam generator blowdown and non nuclear drains are released to the CWDC. Effluent from the liquid waste processing system and processed steam generator blowdown is 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 are 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 1990. Data trends, control / indicator and preoperational/ operational data intercomparisons and other data interpretations are presented. 1
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l Efiluent dispersion characteristics, demography, hydrology, land use, anticipated i source terms, and the critical paths specific to VCSN5 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 establish both the preoperational and operational phases of the Radiological Environmental Monitormg Progtam A census of l 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 l performed in 1990 are included in Table 2. A verification of the critical receptor l (maximum exposed individual) in each sector around VCSNS based on 1990 l meteorological data, VCSN5 Firial Safety Arialysis Report, and VCSNS Operating ~ License Environmental Bepotj e source termiIiiiicluWdiriTablDa.
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Hse e Ga en M 6ed M ed l N M Mastm 3f M. Martm* s8 4. Robmson 0 33 NNI friimbim /9 i Rotunion* 34 11 Robinson 0 33 l N( HemdonW is LRobmson )t $tche 0 2.1 fNt Willinghamt'l 15 R Martm'8' 16 R Martm 0 16 t Joynertal 1,1 Joyner* 1.1 Boyd 0 18 1st W Martin 1.1 W.Martm 1.1 st Pearsontal 14 summer is
$$f Crumpton i5 sheaty 77 5 L. Y as bor ough 34 I as gle 39 H. Y as t,or oughM 8 0 39 ,
siW A shet* 8 33 Aeria 34 Millet 0 30 Csomet 0 34 5W N u htdst*8 33 NKholt 33 Millet 0 28 WSW Hope 31 Da vis* 3.1 tivingston 0 1.9 W 8 sm6thi'l 2s 8 smith 2s uvingston 0 27 WNW Weidemandl 42 Rategerd8 48 Grahamo -0 47 NW Wright 39 Cole 4.1 Cole 0 41 NNW L March 79 L March 30 f . Masth 0 30 A. Change in closest residenc e. B. Change in closest garden C Change in(losest beef cattle. Table 2 Results of the August 1990 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 and the E sector at 1.1 miles; there were no milking animals being rnilked within 5 miles of V. C. Summer Nuclear Station at the time of the census; the Radiological Analytical Services environmental garden is located E5E 1.0 miles from the plant, all other gardens analyzed are at local residences. 3 t _ . - - - . _ - . . ~ . -m_-._._ . _ _ _ _ , - - - - .%
I 19 76 Mill okot ocic At D A T A 1990 Ml110606 oGi( At D Ata S E C. Ol5TANC[ TOR (WCS) WM PATHWAY DO$f 00$l JLQ D/Q RAl[ OQ DQ R A11 mRemly mRemly 37 i Rotnnson 6erf(D) I l.t 4 7 7 4l 10 80102 24107 7 2( = 10 8 il 02 N 38 M Marten te)' Res Gar 1 $10 7 7 Ot 10 18101 2 710F 6 itt 10 19141 NNE 29 Ceum telin mes 3il47 15109 12102 3 il 47 12149 14142 NNI 33 I molenson sect (D) 25107 11149 1 il -01 30! 07 9 61-10 97102 NNI 13 iNotenson{B)* ResCar 2 $t 47 1 it 09 2 91 01 10147 861 10 24 t 01 NE 1$ He r ndon ( A) Res 14106 8 il 49 54102 19106 73109 7 il 42 Ni 21 Stone kes 9e el 6 si 07 3 61-09 38101 94147 32109 3&l41 Ni 28 J Rotanton' ResGar Beef 3 71-07 18109 65141 $ 2107 16109 60141 INI 15 Wdlingha m ( A) kes 1 21-06 668 09 46842 21146 68109 _ 7 91-02 l int 16 R Martin (8)* Pa s Gar Yeet 1 it 06 5 8 t -09 211 e 00 16106 $ 8149 2 it e 00 1 11 J Joyner ( A,B)* Res Gar 2 2t 06 1it 08 3 il e 00(I) 26106 8 Ji 09 21t e 00 l 17 M Boyd Beef $ 4t 47 4 2f ot (f ) 99f47 24149 (f ) I s e.m .-wiin- 4 ween agge-wg., t 18 M Boyd he6 Gar 74847 36109 1 41
- 00 47147 24109 9 $141 til 1.1 W Martin.Jr
- Res Gar 22106 64f 09 ill 4 00 18I 46 56149 168400 51 14 Pear son ( A) kes 19106 7 0E 09 71142 64147 23149 2 41-02 St 15 Summer
- Res Gar 16106 5 Ut 09 16tI 00 $$147 20149 i 4 t -01
$$f 26 Crumpton kes i St 47 121 09 13142 121-07 6 Di 10 46103 lit 27 Shealy ' Pes Gar 3 06-07 1 01-09 27141 10147 441 10 11141 5 34 t.Yattarcugh ses 2.11 07 5 ci in 786 03 98148 4 a 10 3 BI43 5 39 Iargle' R e s'Ga r 1 71-07 3 7! 10 1 il 41 74446 3 St.10 9il42 5 39 H Yarteusougb(C) Beef (D) 17107 3.7 t .10 43107 7di48 3 St 10 36142
"$5W 29 Maier Beef (0) 2 8t 47 10149 11141 191 07 14109 1 St 41 l$W 33 Ashe(A) Ret 21147 70110 7 9t>03 14107 1Ill 49 56143
'55 W 34 Ariad' mes-Ga r 2 Of 47 6 4t to 17141 1J847 981 10 ? $t 01
$W 28 Maler Beef (o) 36147 15t 09 _
16t 01 19147 1.7149 18141 SW 33 Nu hols ( A)' Res Gar 26147 1 Of 09 2 71-01 1.3 f 4 7 1.11 09 26101 Wsw i9 t iving ston' Beef (D) 6 41-07 3 ?! 09 3 a f -01 321-07 21149 2 21-01 W5W 3.1 Hope Net 2 II-07 1 DL 09 87843 1 il 07 66810 43143 WSW 3.1 Da vis (8) Res' Gar 23107 10109 26141 11f 07 66110 17141 W 25 6 5mith( A) ResGar 2 St -07 1.1i49 29t41 14847 63110 1.74 01 W 22 Livingston fleef 32107 1 St 49 (G) 18147 8 61 10 (G) W J.7 Uvingston* Re s' Gar 21147 9Ji 10 3 98-01 111-07 $ 11-10 23101 WNW 42 Weideman ( A) Res 76108 L9f-10 2 91-03 38148 14t10 14103 WNW 48 Ringes (8)' Re s-Ger ' 91 08 211 10 59102 29848 1 Ot 10 27102 WNW 49 Gr aham (C) 15ee f(D) $ 7f 08 21110 23142 28148 9 9f 11 1.11 02 NW 39 Wnght Ret 11107 4 6f 10 4 2I 03 93I48 30110 3 51-03 NW 4.1 Cole ' Res Gar 96148 4 it 10 1 i t 01 8 41-08 27110 7.3t 02 NNW J9 2 March Res 19107 1.1 t 09 7di43 33107 1 01-09 1it 02 NNW 30 f March' Res Gat teef 18847 984 10 35101 311-07 9 2t-10 34101 Denotes Critical Receptor for the sector. (E) Maximum exposed individual for the site. (A) Change of closest residence for the sector (F) Dose rate calculations based on residence & garden at 1.8 miles and i (from 1989 Census). beef cattle at 1.7 miles- (See Iast sector at t8 miles for dose rate.) (B) Change of closest garden for the sector. (G) Dose rate caiculations based on residence 8, garden at 2.7 miles and WChange of dosest beef cattle for the sector. beef cattle at 2.2 miles. (See West sector at 2.7 miles for dose eate.)
! lesidence assumed in calculations.
Table 2a - Critical Receptors in 1990 Based on FSAR/OLER Projected Source Termi l 4 i
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In addition to picoperational/ operational data intercomparisons, control / indicator data intercomparisons are utshied to assess the prcbabihty that any observed abnormal measurement of radioactivity concentration is due to random or regional fluctuations rather than to a true mcrease tri local environmental radioactivity concentration. Momtoring utes indicative of plant operating condi-tions are generally located withm a 5 mile radius of the plant as shown m Table 3 and figures 12 and 1-3. Monitoring utes at distances greater than 10 imles from the plant are shown in figure 11 and are indicative of conditions away from plant mfluence. Information is gained through multiple types of samplmg and measurements at specific locations. Several multiple umphng combinations are in use around the VCSNS. All air sampling locations are also environmental dosimetry monitoring locations At these pomis airborne plant ef fluents are monitored for gamma immersion dose (noble gases), airborne particulates, and radiciodme. Three of these locations have additional complementary sampimg/ measurement pathways for monitoring plant ef tLents. Sampling locations 6 (1.0 mi ESE) and 8 (1.5 mi ENE) have broadleaf vegetation gardens for momtoring the gaseous effluent deposition and ingestion pathway m the two sectors havmg the highest deposition coefficients (D/0). Sampling location 18 (16.5 mi 5) also has a broadleaf vegetation garden for monitormg the gaseous effluent deposition and mgestion pathway at a control location. I.iquid effluents are monitored through three pathways (fish, bottom sediment, and surface water) at the three most probable affected bodies of water around the plant: Site 21, Parr Reservoir (2 7 mi SSW); Site 23, Monticello Reservoir (0.5 mi ESE); and Site 24, Recreation take (5 5 mi N). The controllocation for hquid of 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 1990. Results of the 1990 EPA Intercomparison Program are ir.cluded in Table 4. Results of the intercomparison program with the count room at VCSNS are included in Table 5. Results of an intercom aarison program with SCDHEC outlined in Table 6 are reported by SCDHEC. Results of an environmental dosimetry intercomparison with the NRC are included in Table 7. The results of each of these four quality control checks of the Radiological Environmental Monitoring Program verify the technical credibility of analytical data generated and reported by the program. The program, as it has evolved since the preoperational(baseline) monitoring program, incorporating all the elements of the VCSNS Techmcal Specifications and additional special studies is detailed in Tables 8 and 9. Results and Discussion The results of the Radiological Environmental Monitonng Program for 1990 are summarized in Table 10 For comparative purposes, preoperational data is summarized in Table 11. Certain samples were not collected during 1990 and are not included in the annual summary. A listin() 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 99R Detailed analysis of the impact of these omissions verified that program quality has not been affected, and there were no violations of Technical Specification requirements. 5
l l Site Distance 1 No. Description (Miles) Direction? Sample Type (s)3 Borrow Pit 12 18205 DQ (V) 1 2 Sansmmion L.ine 12 125 0 SW AP,RI.DQ 3 iiting Range 12 270 0 W DQ 4 F airbeld Hydro 12 289 5 WNW DQ 5 1ransmission Line I ntrance 09 145 5St AP,RI,00 6 Env LabGarden 10 104 0L5[ AP.RI.DQ,G R,G A 7 Monticello Peninsula 12 83 0 t DO __ 8 Monticello Ret 5 of Rd 224 15 63 0 LN( AP,DQ,G A 9 Ball Par b 22 440NL 00 10 Meteorologi(al Tower #2 25 25 5 NNE AP,RI,DQ 11 Residence 33 80N 00 12 Old Hwy 99 42 349 0 N DQ 13 North Dam 29 334 0 NNW AP.DQ 14 Dairy 63 270 0 W AP RI,0Q,M K,GR 15 Part Village 25 204 0 55W DQ 1b Dairy 28 0 2810 W DQ,GW,MK,GR 17 Columbia Water Worb 5 24 7 144 05t AP RI,DQ,5W.DW,85 18 Residence / Pine 151and Club 4 16 5 16505 DQ,5W,G A 19 Residence /Little Saluda 17 9 207 0 55W DQ 20 ResidencetWhitmite 22 0 310 0 NW DQ 21 Part Reservior 27 199 5 55W SW,f H,B5 22 Neal 5hoalt t- 30 0 343 0 NNW 5W,f H,85 23 Discharge Canal (Mont Ret ) 05 104 5E5E $W,f H,85 (N 24 Recreation Lake 55 20N SW,f H,65 25 Iairfield Pumped Storage 09 302 0 WNW 5W (Montkello Ret ) 26 On Site Well (P2) 460it 270 0 W GW 17 On Site Well (PS) 510it 18005 GW 28 Nuclear Training Center (E OF)) ,4 168 0 55t DW 29 Trans Lme W5W of VC5N5 09 248 0 W5W DO 30 Oak Tree North of Borrow Pit 10 197 0 55W DO 31 McCrorey Litton School 58 12 5 NNL DQ 32 Dirt Rd of f Rd 205 45 25 0 NNL DQ 33 Rd 48 near Hwy 213 42 70 0 E NC DQ 34 Rd 419 North of Hwy 60 48 112 5ESE DQ 35 Unnarred Circle Road of f Hwy 215 48 137 SSE DQ 36 Woods Behind Jenk. Post Of f ace 31 1515 55L DQ 37 Residente 49 305 5 NW DQ 38 F P5f 1railrac e 13 280 0 W B5 39 LMWT F 14 0 168 0 55E DW 41 End of Catwalk 39 185.05 00 42 Store 39 199 0 55W DQ p Table 3 Sampling Site Location 5 k 6 1
Description , Dir e( tioni Sompte Type (s)) 43 Hwy 1/b anI! Rd 435 52 13b O 5W DQ ) 44 Rd 28 at Cannon's Cree 6 29 255 5 W5W DQ 45 Rd 33 at Pomaria 59 253 WSW DQ 46 RC128 at Heller's Cree 6 31 2'J2 0 WNW DQ 47 f airfield lailrace 10 316 0 NW DQ ) 48 Cemetary 23 318 5 N~W DQ j 49 North Rd 3H3 40 332 5 NNW DQ
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50 New Rd 99 (West Shore) 55 10N DQ
$1 New Rd 99 (last Shore) 55 50N DQ i 52 Monticello(Rd III 39 14 0 NNE DQ 53 Rd 359 30 48 0 Nt DQ 54 Jen6 insville Sc hool 11 73 0 ENE 00 55 St Barnabas Church 23 94 0 E DQ 56 Old Jenkinsville Diner 20 144 0 5E 00
$7 Residence / Highway 211 and 215 27 146 0 5E DQ
$8 Residence 25 158 0 55E DQ
$9 Nuclear Training Center (eof)s 24 168 0SSE DQ,AP 60 Rd 98 near Rd 28 35 2750 W DQ 61 Switchyard, $E intrance to Plant 01 18005 DJ 62 Eatt of Training Bldg 0.13 720.0 5W DO 63 East of Daniel's Of fice 0 17 270 0 W DQ 64 Riprap W of Intak e 0 13 338 5 NNW 0 0.85 65 Guard Tower 0 13 22 5 NNE DQ.05 66 Jetty 06 33 0 NNE DQ 67 Service Water Pond (iast Side) 05 720ENE DQ ~
68 f uel Oil Storage Tank 02 108 5 ESE DQ 69 E xclusion Buoy NNW on Monticello l'0 337 0 NN\, DQ Res. 70 E n(lusion Buoy N on Monticello Res 10 00N DO 71 Temperature Buoy on Monticello 54 30N DQ Res 72 Yard Drain Outf all 04 146 0 5E B5 73 Yard Drain Outf all 04 270 0 W B5 74 Yard Drain Outf all 05 246 0 W5W SW 15 Onsite Well(P) 265 ft. 270 0 W GW 76 Onsate Well(P) 270it 330 0 NNW GW 84 Congaree River 54 2 135 05E B5 85 Congaree River 53 8 135 0 5E B5 87 Lake Manon 72 0 138 0$E B5 88 Lak e Marion 72 0 138 0 SE B5 Table 3 - Sampling Site Locations (continued) 7
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FOOTNOTES
- 1. Distance given is the distance between the site location and the center of the VCSNS reactor containment buildmg
- 2. Direction given is direction in degrees from true north south hne through the center of the reactor containment building.
- 3. Sample Types:
AP = Air Particulate DW = Drinking Water RI = Air Radiciodine MK = Milk DO = Quarterly TLD GR = Grass (Forage) SW = Surface Water GA = Garder GW = Ground Water FH = Fish B5 = Bottom 5edirnent
- 4. Site 18 consists of 3 locationsin close proximity next to Lake Murray. Garden product samples are taken at the Wyse residence. Surf ace water is taken near the shoreline in Lake Murray. The TLD is located on Pine Island.
- 5. Si'e 28 for drinking water and site 59 for quarterly TLD measurements and continuous air sampling are co located at the location of the SCE&G Nuclear Tra;ning Center which also serves as the Virgil C. Summer Station Emergency Offsite Facility.
Table 3 - Sampling Site locations (continued) 8
Comperison Study E PA Value I.aboratory Agree-(Measurement Unit) Date Nuclide (precision) Results (ettor) ment Air filter (pCi/ filter) 3/90 alpha 5 (5) 6 (1) Yes beta 31(5 36 Yes 12 Yes ( ..........................
.gg . . C. 5 13 7. . .
7j . . .10 (5 10 (5) "" " " 13T1T '" "~Wi" beta 62(5) 68 2) Yes C5137 20(5) 25 1) Yes 80~ 3)-
~
' Gamma inVTdfeilpCi/IIlirT 7790~ ~B a7m- 74~(7) Yes Co 60 15(5) 15(1) Yes 2n 65 139(14) 142(6) Yes Ru 106 139(14) 129 (1) Yes Cs 134 18(5) 17 1) Yes
.Cs;137, . ,,,,,18 g1 ,,. , , , j 8, ,2 ), , , , . , , , Ye_s, , ,
6/90 Ba 1.43 99(10) 102(3) Yes Co 60 24(5) 23(2) Yes 2n 65 148(15) 144(4) Yes Ru 106 210 21) 207(1) Yes Cs134 24 5) 22(2) Yes Cs 137 25 5) 24(3) Yes
""'T10 (11)"' ""f f 312)"" ~ " Y(s" ~
10790' 'B a:133" Co 60 20(5) 22(2) Yes 2n 65 115(12) 113(5) Yes Ru 106 151(15) 144(9) Yes Cs134 12(5) 13(1) Yes Cs137 12(5) 12(0) Yes bross ATpTiWBela in Water (pCi/ liter) 1/90 alpha 12(5) 8 (2) Yes
.. beta .. .. .13(1) Y
.g . . . . .g12 '5) g
. . . g.e.s.. . .
w ..........................
. .gg . . . bet.a . .
g
. ..15 (5 30(1) No*
f 015 "" " " '6 ( 11 " " ~ " " Y 6s~ " beta 10(5) 16(1) Yes lodine in W51er (pCillRer) 2/90
. .gg . . 1 131. . . . . .106 g3 3g
}... ...111 ag }... . . . Ye. s . . .
ygg Laboratory BlindTpCi/ liter) Cs134 15(5) 15(0) Yes Cs-137 15(5) 17(2) Yes 10790' ' "alplid -' " "62Tf6)"" " " 53T3)" " ~ " ~ YFi " beta 53(5) 47(3) Yes Cs134 75) 8(0) Yes Cs 137 55) 6 (1)
~
Yes TWdionucIITesin Milk (pCi/ liter) 4/90 1131 99(10) 108(5) Yes
. . . .26(
s .... 24 (5) Y
. .gg . . C.g- 3 13 7. . . gg g ....
- g. 3 ) . . . . . .
. . . y.e g, s. . .
Cs-~f37- ~~~20T5) 22~(2P Yes Tritium in Water (pCi/ liter) ' ~2790- H3 4976T49'8F 3838125TF No+ 6/90 H3 2933(358) 2739(152) Yes 11790' "R7" " 77031720)" "lPT4f 146)" ~ ' " Ws~ "
- The results reported to the EPA were inadvertently switched. The actual results were within EPA acceptable range.
+ An instrument setting 3roblem caused the results to be biased low. The problem was subsequently correctec .
Table 4 Results of 1990 EPA Intercomparison Program 12
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E ntor Comparison Study 1aboratory 2nd Eab Agree-(Measurement Unit) Date Nuclide Results Results(1) ment Iritium (pCi/mi) (Analytin) h90 H3 2 50E 4 2 63E 4 Yes (itium (pCi/ml) (Analytns) 11/90 H3 189E 3 2 04E 3 Yes , I VC5NS) 12 <90 H 3 (undistilled) 2 37E 5 2 38E 5 Yes ] (VC5NS) 12/90 H-3 (distilled) 2 46E 5 2 40E 5 Yes Gross Beta liq uidTpCi'ml) 2/90 N/A ~ ~ ~ 125E 3 125E-3 Yes Gross Alpha liquid'(pCi/mlF~~2i90" ' N/A ~76~ 6U5 i ~9 /6E 5 Yes f Charcoal Canis cF(ii6 filter) Gross Beta (pCi/ml) 5,90 1131 N/A 186E;1 2 98E 1 No (2T-8/90 __2 28E-3 2 44E 3 Yes Gross ATpL (pct /ml) 8/90 N/A / 54l 4 7 98L 4 Yes Gamma Isotopic liquid 2/90 Ce 144 8 80E 3 8 73E-3 Yes (pCi/ml) Ce 141 8.40E 3 8.54E 3 Yes Cr-51 2 41E-2 2.31E 2 Yes Cs 134 5.23E 3 5.62 E -3 Yes Cs 137 413E 3 3 83E-3 Yes Mn 54 8 27E.3 7.99E 3 Yes Fe 59 1.21E 2 1.15E 2 Yes 2n-65 5.85E-3 5.5 5 E -3 Yes Co 60 125E 2 1.24E 2 Yes 5/90 Ce 144 1.19E 2 1.14 E 2 Yes Cc 141 4.49E 3 4.51 E -3 Yes Cr 51 1.68E-2 1.60E 2 Yes Cs 134 4.57E 3 4.79E 3 Yes Cs-137 6.15E 3 5.98E-3 Yes Co 58 4.17E 3 4.20E-3 Yes Mn 54 8.15 E -3 7.88 E -3 Yes { } Fe 59 8.41 E -3 8.04 E -3 Yes 2n 65 8 25E 3 8.01 E-3 Yes Co 60 1.13E 2 1.10 E -2 Yes 8/90 Ru 103 7.40E-3 7.14 E -3 Yes Cc 144 1.18E 2 1.10E 2 Yes Cc-141 1.04E 2 9.92E 3 Yes Cr-51 4.05E-2 4.23E 2 Yes Cs-134 6 26E 3 6.90 E -3 Yes Cs 137 5.65E 3 5.61 E -3 Yes Co 58 4 22E 3 410E-3 Yes Mn 54 8 25E-3 7.92 E - 3 Yes Fe 59 8.35E-3 7.94E 3 Yes 2n 65 131E 2 1.26E 2 Yes Co 60 8.93E 3 8.85E-3 Yes NRC Liquid (i Ci/ml) 10/90 H-3 (distilled) 4.96E 5 5 53E-5 Yes Gamma Isotopic 5/90 Ce 144 4.11 E -2 3.79E-2 Yes Point Source (pCi/ml) Ce-141 1.61 E -2 1.49 E - 2 Yes Cr-51 5.67E-2 5.30E 2 Yes Cs-134 1.56E 2 1.59E 2 Yes Cs-137 2.05E-2 1.98E 2 Yes Co-58 1.39E-2 1.39E 2 Yes Mn-54 2.75E-2 2.61 E 2 Yes Fe-59 2.75E-2 2.66E-2 Yes 2n-65 2.75E-2 2.65E 2 Yes Co 60 3 81E-2 3.65 E-2 Yes 13
Lnvir. Comparison Study Laboratory 2nd Lab Agree- _ l (Measurement Unit) Date Nuclide Results Results(1) ment iamma Isotopic Filter 8/90 Cc144 4.51E 2 4.24E 2 Yes _ spCilfi:ter) Ce 141 3.83E 2 3.83E 2 Yes Cr 51 1.54E 1 1.63E 1 Yes C5134 2.32E 2 2.66E 2 Yes ts 137 2.29E 2 2.17E 2 Yes Co 58 1.68E 2 1.58E 2 Yes Mn 54 3.43E 2 3.06E 2 Yes Fe 59 3.50E 2 3.06E 2 Yes 2n 65 5.58E 2 4.88E 2 Yes Co.60 3.54E 2 3.4 2 E-2 Yes Silver 2eolite Canister (pCi/ filter) 11/90 1131 3.45E 2 3.17E 2 Yes ~ bas 5 ample hiCil5@ $795'Te~TW' TUH6~" ~GNO Yes Kr85 9 30E + 1 8 27E 41 Yes (1) Independent Laboratory was Analytics,Inc., except for some tritium intercomparisons. (2) The charcoal canister was inadvertently counted on the wrong side, producing a low result. Table 5-Results of 1990 Intercomparison Program with Independent Lab
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Pathway (Units) Sarn e frequency Nuclidel t9c 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 Milk (pCi/litei) - 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 pubhcation in this report.
Results will be reported by SCDHEC. Table 6 Summary of 1990lntercomparison Program with South Carolina Department of Health and Environmental Control O 14
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LABORA- " " " NRC TLD #' TORY TLD ON STATION La&a- Pment Lawa- Pment La w a- Pe w t NO y9' yg( La w a- Pment Ng( yg( ng( tory Difference tory Difference tory Difference tory Diffe+ m e 1 42 11.4 6.7 -41.2 9.2 6.6 -28.3 10.6 ' 7.5 -29.2 9.6 6.9 -28.1 2 6 --- 7.6 - 9.0 7.5 -16.7 7.0 8.9 27.1 9.5 8.5 -10.5 5 54 9.6 10.6 10.6 10.2 10.7 4.9 88 12.2 38.6 11.0 79 -28.2 7 *53 11.6 11.3 -2.8 11.9 11.3 -50 10.9 13.1 20.2 12.8 11.9 -7.0 9 '52 12.8 11.7 -8.7 11.6 11.3 -2.6 12.2 12.6 3.3 11.9 12 2 25 11 *12 7.6 8.3 8.6 7.6 7.8 2.6 --- 9.9 -- 10.6 8.9 -16 0 13 13 11.8 11.4 -3.1 10.4 11.0 5.8 11.6 13.8 19.0 11.2 13.7 22 3 14 '44 -- 6.2 -- 9.1 5.9 -35.2 6.8 69 15 94 66 -29 8 19 *S6 9.0 8.1 -10.0 9.4 8.3 -11.7 8.9 9.0 1.1 9.6 E6 -10.4 22 58 8.6 5.8 -32.6 6.7 5.5 -17.9 8.2 6.2 -24 4 7.6 60 -21 0 24 41 8.9 8.3 -6.6 7.7 8.9 15.6 8.9 9.8 10.1 83 9.6 15.7 29 *60 10.8 10.6 -1.8 10.3 10.1 -1.9 10.3 11.5 11.7 11.2 10.6 -54 30 46 10.1 8.4 -17.2 10.5 7.8 -25.7 9.2 10.0 8.7 12.1 13.9 14.9 l
- Co-located dosimeters within 10 feet of NRC dosimeter.
Table 7 - Results of Environmental Dosimetry intercomparison with NRC TLD Direct Radiation Monitoring N( work Page 15
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) ) ) )
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Virgil C. Summer Nuclear Stat C Docket No. 50-395 Fairfield County, South Caroib Reporting Period: 1/1/SO-12/31/90 tower Limit of L"*T'0" ** D # "'** Med um or Pathway Type and Total Sampied(Unit of Mumberof Analyses Detecticar actua: Mean'IRangel name Me*a' Meaa'(Racce) WW Measurement) Perfom.d' (Mat) (Mame a, we) Ina v ) %,m. Air Particu: ate Gron Beta 2 TE-2 (260/260) 54te 14 Da ry 2 2E-2(52/52) 2 CE-2 (52/52) 0 (oCi/m3) (312)- (1.0E-2) (0 6E-2 to 5 OE-2) (6.3 mi W) (1 1E-2 to 4 3E 2) (0 BE-2 to 3 SE-2) Gamma spec (72) Cs-134 1 SE-3 All < LLD All < LLD 0 (5CE-2) Cs-137 2 OE-3 All < LLD AN < LLD 0 (6 OE-2) Air 8tacio odme I-131(312) 2 OE-2 All < LLD All < LLD 0 (pCi/m3) (7OE-2) Derect (TLD)5 Gamma (136) 9 2E0 8116/116) Site 55.5t Barnabas 13 2E0 (4/4) 9 2E0 (20/20) 0 (p 1/hr) 5 Quarterly SEO (6.1 E 0 to 12 9EO) Churtb (2 8 mi. E) (12 7EO to 13 8EO) (6 BE0 to 12 4EO) 2 Gamma (60) 9 3E0 (60/60) 5ite 13, North Dam 12 9E0 (4/4) MA 0
$ Socoaf Interest .5E0 (5 9EO to 12 9EO) (2 9 me. NNW1 (5 9EO to 12 9EO)
Surf ace Water M-3(84) 4.5E 4 2 5 7E + 2 (3,60) 5.te 21. Parr Rese<woer 6 9E + 2 (1/12) All < LLD 0 y w (oCin) (2 OE + 3) (5 TE + 2 to 6 9E + 2) (2 7 mr.55W) (< LLD to 6 9E + 2) LLD = 4 6E + 2
~
Gamma Spec (90) _ Mn-54 2 BE0 All < LLD All < LLD 0 (1 SE + 1) Co-58 3 4E0 A!! < LLD A!! < LLD 0 (1 SE + 1) F e-59 6 9EO A!! < LLD All < LLD 0 (3 OE + 11 Co-60 3 2E0 All < LLD A!! < LLD 0 (1.5E + 1) Zn-65 6 2E0 All < LLD Ait < LLD 0 (3 OE + 1) 2r-95 5 OE0 All < LLD All < LLD Q (3 OE + 1) Nb-95 3 4E0 A!I < LLD A!! < LLD 0 (1 SE + 1) Cs-134 2 6EO All < LLD A:I < LLD 0 (1 SE + 1) Cs-137 2.9EO All < LLD A!! < LLD 0 (1 SE + 1) Table 10 - 1990 Radiological Environmental Monitoring Program $ummary i
Virgil C. Summer Nuclear Staw Docket No. 50-395 Fairfield Cour;ty, South Caroliir Reporting Period: 1/1/90-12/31/90 4 Medium or Pathway Type and Total towe, Lima e, (MaMM with H@ Amewal Wan l # * * * " " " Sampled (Unit of Numberof Anafyses Detection 2 Actuet i Measurement) Perfo<med' (Maw.) (Dotaate & D.ent.on) taange) w ,,w, Ba-140 18E+1 All < LLD Ad < LLD 0 (6 OE + 1) i La-14D 6 OEO A!! < LLD All < LLD 0 (1.5E + 1) 1 Ground Water H-3(12) 47E2 All < LLD A 8 < LLD D (oCsM) (2 OE + 3) Gamma Spec (8) Ga nma Spec (4) i M n-54 3 4E0 All < tLD Ali < LLD 0 (1.5E + 1) Co-58 31EO All < LLD An < LLD 0 (1.5E + 1) Fe-59 6 9EO AH < LLD AM < LLD 0 (3 OE + 1) CoI>0 3 SEO All < LLD An < LLD 0 m (15E + 1) I $ Zn-65 7.2E0 AH < LLD ATI < LLD 0 l
% (3.0E + 1) l Zr-95 4 9E0 AU < LLD An < LLD 0
- (3 OE + 1) b-95 3 CEO AD < LLD All < LLD8 0 I
(: SE + 1)
- Cs-134 2 BE0 All < LLD Ai! < LLO O (1 SE + 1)
- Cs-137 3 2EO All < LLD AH < LLD 0 (1.8E + 1)
Ba-140 11E + 1 A!! < LLD An < LLD 0 (6 OE + 1) i La-140 5 TED Alt < LLD AM < LLDe C i (1.5E + 1) Drmking Water 6 Gross Beta (36) 2.1 EO 4 CEO(1&'20) Site 28. NTC 4 4E0 (10'13) 3 3E0(9'13) 0 (pCiM) (4 OED) (2.5E0 to 7.9EC) (2.4 mi. 55E) (2 8E0 to 7 9EO) (2 4E0 to 4 7EO) i H-3(36) 4 6E + 2 AM < LLD Ali < LLD 0 (2 OE + 3)
- Gamma Spec (36)
Mn-54 2.9E0 AH < LLD A! < LLD G (1.5E + 1) , 1 j Table 10 - 1990 Radiological Environmental Monitoring Program Summary i . . _ . -_ _-
g . s Virgil C. Summer Nuclear Stat Docket No. 50-395 (% Fairfield County, South Caroli,. Reporting Period: 1/1/90 -12/31/90 Medrum or Pathway Type and Total " towee L' -met of An etw ta a % contees tmate,s h oa-sampled (Unit of Numbetof Analyses Deention2 Actual , 3 , , , y, ,, y,,,, (uy} meoor,,e* u asurement) Performed' (Mat) (%tance a omtvl (ma v ) v.as . Co-58 3.1 E0 All < LLD AM < LLD 0 (1.5E + 1) Fe-59 7.1 E0 All < LLD An < LLD 0 (3 OE + 1) Co-60 3 2EO A!! < LLD Att < LLD 0 (1.5E + 1) Zn-65 6.5E0 Ali < LLD A!! < LLD 0 (3 OE + 1) Zr-95 5 2E0 Att < LLD An < LLD 0 (3 OE + 1) Nb-95 3 4E0 AH < LLD An < LLD 0 (1.5E + 1)
-131 b 6E-1 Ai1 < LLD AM < LLD 0 (1.0EO)
? C5-134 2.7EO All < LLD Art < LLD 0
$ (1.5E + 1)
N Cs-137 3 OED AM < LLD AM < LLD 0 (1 BE + 1) Ba-140 1 EE + 1 AH < LLD AM < LLD 0 (6 OE + 1) La-140 7.2:0 AU < LLD Ali < LLD 0 (1.5E + 1) M:!k Gamma Spec (52) (PO/l) 1-131 5 7E-1 AH < LLD AM < LLD 0 (1.0EO) Cs-134 3 2E0 AH < LLD AH < LLD 0 (1.5E + 1) Cs-137 3.7E0 3 CEO (13/26) Sr:e 14. Da ry 3 GEO (13/26) 2 CEO(C26) 0 (18E + 1) (17EO to 4 2ED) !6 3 mi W) (17EO to a 2EC) (1 JE0 to 2 6EO) Ba-140 11 SEO All < LLD All < LLD 0 (6 OE + 1) La-140 4 CEO AH < LLD AM < LLD 0 (1.5E + 1) G ass (pOAg wetJ :. Gamma Soec (35)l l i l l Table 10 - 1990 Radiological Environmental Monitonng Program 5ummary
i Viroil C. Summer Nuclear Sta, r Docket No. 50-395 Fairfield County,5outh Caroih.. Reporting Period: 1/1/90-12/31/90 j L'** " W **"**'"'** Med*um or Pathwey type end Total tower tsit of sempied tunit of Numbe< o' Aaa'rses octe<t.oaz Actuai Meawement) Performed-
* *Y' **' *** '
(Ma n.) Maage) i (Dotaace & Dwe< ten) u+,we. 1-131 2.1 E + 1 A!! < LLD Att < LLD 0 ) (6 0E + 1) Cs-134 1.7E + 1 All < LLD Ali < LLD 0 (6 OE + 1) Cs-137 19E + 1 Ali < LLD All < L LD 0 (8 OE + 1) Broadleaf Vegeta- Gamma Spec (36) tion (pCi/kg wet) I-131 17E + 1 All < LLD AH < LLD 0 (6 CE + 1) i Cs-134 1.3E + 1 All < LLD A!! < LLD 0 (6 OE + 1) C5-137 16E + 1 Al! < LLD A:1 < LLD 0 (8 CE + 1) l 2 Other Vegetation Gamma 5pe<(4) { g (pCo g wet) i 9 I-131 3OE+1 All < LLD An < LLD 0 (6 OE + 1) 'i CS-134 9 4E0 All < LLD A1: < LLD 0 (6 0E + 1) ! Cs- 137 9 6E0 All < LLD All < LLD C j (8 OE + 1) l Fes5 f oC4/kg wet) Gamma 5 pet (33) ' v n-54 11E+1 All < LLD All < LLD 0 (1.3E + 2) ! Co-58 1.1 E + 1 All < LLD A!! < LLD 0
- (13E + 2)
! Fe-59 2.7E + 1 All < LLD Atl < LLD 0 l (2 6E + 2) l Co-60 1 SE + 1 All < LLD AH < LLD 0 , (13E + 2) , Zn-65 3 4E + 1 A!! < LLD A!! < LLD 0 , (2.6E + 2)
~
! C5-134 9SE+1 A!! < Ll " A!! < LLD 0 (13E + 2)
- Table 10 1990 Radiological Environmental Monitoring Program Summary
O Virgil C. Summer Nuclear Sta'. Fairfield County, South Carolii._/ f~%.
)- Docket No. 50-395 Reporting Period: 1/1/90-12/31/90
[V )j
!.iecium or Pat.~uit y Type and Total Locats alth Highest AnnualMean Number M Lower Umit of Sampled (Unit of Number of A* *,ses Detection 2 Actual Measurement) Perfe medi (Man.) (Distan<e & Dwetten) (Range) MeasureWs Cs-137 1.2E + 1 1.8E + 1 (15/23) . Site 21, Parr Res .
2.1E + 1 (4/10) 1.5E + 1 (8/8) 0 (1.5E + 2) (9.3E0 to 3.5E + 0 (2 7mi,SSW) * (1.2F + 1 to 3 5E + 1) (9.7E0 to 2.3E + 1) Sediment (pCi/kg)7 Gamma Spec (16) M n-54 2 2E + 1 4.7E + 1 (1/12) Site 23. D:scharge 1.6E + ) (1/4) All < LLD 0 (Singie Value) Canal (Mont<eco mes 1 (Si vjfe Value) (0.5 mi, ESE) Co-58 2.3 E + 1 All < LLD All < LLD 0 Co-60 3SE+1 9.7E + 1 (8/12) Site 23, D 5(harge 1.1E + 2 (4/4) All < LLD 0 j (2 0E + 1 to 1.4E + 2) Canal (cont.cenoa cs) (6 SF + 1 to 1.4E + 2) (0.5 mi, ESE) Cs-134 2.5E + 1 3.9E + 1 (7/12) Site 23, Discharge 5.1E + 1 (3/4) All < LLD 0 (1.5E + 2) (1.1E + 1 to 8.6E + 1) Canat (vont<en oaes) (2.5E + 1 to 8 6E + 1) (0.5 mi, ESE) Cs-137 2.0E + 2 (12/12) Site 23, Drscharge 2.5E + 2 (4/4) 81E + 1 (4/4) 0 i g (1.BE + 2) (5 2E + 1 to 3 6E + 2) Canal (vo t<eno es m > (2.3E + 2 to 2.9E + 2) (31E + 1 to c (0.5 mi, ESE) 1.6E + 2) Tuble 10 - 1990 Radiological Environmental Monitoring Program Summary i i t
, /~ n
~
i Footnotes
- 1. Does not include supplemental samples. All r pplemental 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.
I
- 4. Any confirmed measured level of radioactivity in any environmental medium that exceeds the y reporting requirements of VCSNS Technical Specification 3.12.1.
Eo g 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 abserved in all Jenkinsville drinking water samples.
The values are not reported here because they are naturally occurring (do not originate from VCSNS) and furni'sh no quantifiable information of interest.
- 7. Elevated levels of Pb-214 and Bi-214 plus other Re-226 daughter products and Ac-228 plus othe
- Th-232 daughter products were observed in all sediment samples. The values are not reported here because they are naturaliy eccurring (do not originate from VCSNS) and furnish no l' quantifiable information of interest.
- 8. Maximum LLDs were not met in one co" '- I sample because of high Bi-214 and Pb-214 activits interference.
Table 10 - 1990 Radiological Environmental Monitoring Program Summe,ry
Medium or Pathway Type and Total G * "* 9 ^ " " " * ' **" G Sampled (Unit of Lower Limit of All Indicator Number of " ## ' "' " " ' " Detection 1 Locations Measurement and Analyses Name (Distance & Mean? Mean? (Range) Reported 3 Reporting Penod) Performed Actual (Max.) Mean2 (Range) Direction) (Range) Measurements 1.3E-1(52/52) 1.1 E-1 (562/564)4 Site 13, North Dam (21 E-2 to 1.2E-1 (153/155) Air Particulate t ( m -
- t 6M Gross Beta 4,1E-3 (pCi/m3)
(1300) (1.0E-2) Site 8, Mon. Res 5 of (1981-1982) 2.7 E-2 (456'462)4 3.0E-2(42/~2) 2.8E-2 (125/126) (9 3E-3 to 6 6E-2) Rd 224 (1.5 ENE) (12E-2 to (12E-2 to 5 BE-2) 6 OE-2) i 3amma 5pec (307) 3 Cs-134 g A!! < LLD AH < LLD 0 3.1E-3 3.2E-3 (22/241) Site 10. Met Tower 4 2E-3 (4/66) (1.0E-2) (1.5E-3 to 5 2E-3) (2 4 me NNE) (3 2E-3 to 5 6E-3) c [fE 3 . 3 C /m ) 92 3MM (7 2) Au < D An < uD 0 Gamma (1220) 9.9 915/915) Site 13. North Dam 13 1(61/61) 9.7(305/305) (u h) Monthly 05 (6 7 to14.7) (2 9 mi NNW) (12 2 to 14 2) (6 4 to 13 5) 0 (1978-1982) Gamma (161) 10.2(154/154) s.te 55. 5t Barnabas 14 0(7/7) Quarterly 0~5 0 (f. 8 t014 7) Church (2 8 mi E) (13 11o14 7) Surface Water 16E + 3 (2/7) 12E + 3 (6/14) ! (pCi/1) 1.1 E + 3 1.4E + 3 (18/29) Site 17. Co.! umbia I H-3(43) (2.OE + 3) (14E + 3 to (6 7E 4 2 to 0 (1981-1982) (1.1E + 3 to 2 4E + 3) Canal (24.7 mi. 5E) 1.8E + 3) 16E + 3) ' Gamma 5pec (140) 2 7E-1 M n-54 g ,) All < LLD AH < LLD 0 2 Co-58 AH < LLD AH < LLD 0 g 5E 1) Fe-59 AH < L L AU < LLD 0 (3 OE 1) Table 11 - Radiological Environmental Monitoring Pragram Summary Preoperational (Baschne) Summary . .. .. .. _ _ - _s
( (- EJ Location with H:ghest Annual Mean Number of Medium or Pathway Type and Total ,g f g "# ' ' " " "' Sampled (Unit of Number of Detection 1 Locations Vean2 (Range) Reported 3 Name (Distance & Mean2 Measurement and Analyses Yeasurements 2(Ra @ Direction) (Range) Reporting Penod) Performed All < LLD 0 Co-60 All < LLD 1 SE
^"
Zn-65 #" (3 OE 1) All < LtD 0 Zr-95 All < LLD E All < LLD 0 Nb-95 All < LLD O SE At! < LLD 0 Cs-134 All < LLD MbE All < LLD 0 Cs-137 All < LLD 08 Ba-140 #" (6 b + 1) 0 $ La-140 5 5E-1 ^" ^" l y (1982 only) (1.5E + 1)
* ( #
9OE+2 1.5E + 3 (16/16) Sete 26. Onsite Well (9 5E + 2 to (1.OE + 3 to O Ground Water I 9} P4 (265 ft, W) (pCi/1)( 1-1982) (2 OE + 3) (9.5E + 2 to 2.3E 4 3) f Gamma Spec (32) un-54 3 g, 5E + 1)
^"<"
3 8EO Au < uD 0 co-58 All < RD g,3 ,) 8 Au < @ 0 Fe-59 AH < RD (3 fE ,) 3 Au < uD 0 co-60 Au < uD (15 + 1) 8 Au < uD 0 2n-65 Au < uD g3 0 + 1) Table 11 - Radiological Environmental Monitoring Program Summary Preoperational (Baseline) Summary
Medium or Pathway Type and Total 9 ocauon wM Mghest Annual Mean 9 NumMr of Sampled (Unit of Lower Um? of All indicator Number of Control Locations Nonroutine Measurement and Analyses Dedn 1 Wtim Reported 3 Name (Distance & Mean2 Mean2 (Range) Reporting Penod) Performed AM Wj MMRg) (Range) Measurements Direction) Zr-95 ^" ^" ( SE + 1) Nb-95 ^"< ^"< (15 + 1) Cs-134 ^" ^" O SE + 1) Cs-137 All < LLD All < LLD 0 (18 Ba-140 E All < LLD All < LLD 0 (1982 only) (15 + 1)
"" "9 **
Gross Beta 7 (2 OEO) eo, (pCi/l)(1981-1982)
* (
6 3E + 2 7 8E + 2 (6/14) Site 28. Jenkinsville ,
-3 304) *
(1.0E + 3) (6 8E + 2 to 9.8E + 2) (2.0 mi SE)7 8E + Gamma Spec 0 (44) 3 Mn-54 All < LLD 0 0 5E E Co-58 g All < LLD 0 Fe-59 An 0 (30 + 1) 2 Co-60 {; 5E 1) Au < LL 0 Zn-65 All < LLD 0 (3OE 1) Zr-95 Ali < LLD 0 O 5E ) Table 11 - Radiological Environmental Mo..itoring Program Summary Preoperational (Baseline) Summary
-~.
\ _./ \s_/
\d
* "* 9 #5 ^"""#' '#" ""
Medium or Pathway Type and Total All Indicator Lower Limit of "" * "' "' "' Sampled (Unit of Number of Locations Reported 3 Detection 1 Name (Distance & Mean2 Mean2 (Range) Measurement and Analyses g 7 , Direction) (Range) Measurements Reporting Penod) Performed An < LLD 0 Nb-95 (1 SE 1) A!! < LLD 0 1-131 [1 OE0 Cs-134 ^" (1GE 1) 0 Cs-137 All < LLD 0bE Ba-140 #" (6 bE 1) La-140 4 4E-1 All < LLD 0 < l (1982 only) (1.5E + 1) Milk f u Gamma 5pec 6CiM #) f j (1981-1982) 63 An < LLD 0 U 1-131 0E0) An < LLD 33 All < LLD AH < LLD 0 Cs-134 gfE 9 41 EO (8/47) Site 14, Da ry 5.7EO (37/47) 54 37 4 6E0 (51 mi., W)
' (3 7EO to 9 2EO)
(1.5E 41) (2 8E0 to 61EO) 6 E0
*' AU < LLD 0 Ba-140 All < LLD
;)
All < LLD All < LLD 0 La-140 0E 1) Grass (pCi/kg wet) Gamma 5pec (1981-1982) (82) 6 All < LLD All < LLD 0 6-131 0 l Table 11 - Radiological Environmental Monitoring Program Summary l Preoperational (Baseline) Summary l
O Medium or Pathway Type and Total O L cation with Highest Annual Mean O Number of Lower Limit of All i.1dicator Sarapled (Unit of Number of " # "' " Detection 1 Locations Measurement and Analyses # # ' #" ' '" #"9 Reporting Period) Performed Actual (Max.) Mean2 4, Range) (Range) Measurements Direction) Cs-134 All < LLD All < LLD 0 { . 5.9E + 1 (5/29) 1.3E + 2 (6/31) 3.3E + 1 5 OE + 1 (13/51) Site 14, Dairy (8 OE + 1) (1.6E + 1 to 1.6E + 2) (5.1 mi W) 3 4E + 2 16E + 2) Broadleaf Vegetation (pCi/kg wet) Gamma Spec (10) (1980-1982) 1-131 All < LLD All < LLD 0 (6 E Cs-134 All < LLD All < LLD 0
* * " * * (
Cs-137 All < LLD 0 y (8 OE + 1) 11.8E + 1 to 3 6E + 1) (1.2 mi SW) (Sengte Value) y Other Vegetation Gamma 5pec w (pCi/kg wet)
" I '
(1980-1982) Cs-134 ^"< ^" (8 OE + 1) Cs-137 All < LLD All < LLD 0 Fish (pCi/kg wet) Gamma Spec (1980-1982) (92) Cs-134 All < LLD All < LLD 0 E I *' 8E+1 2 8E + 1 $0@ Me 24, Remation 7/23 g3 gE + 1 to C5-137 O (1.3E + 2) (1 1E + 1 to 1.0E + 2) Lake (5 5 mi. N) (1.2E + 11 7 9E + U 1 OE + 2) Co-58 All < LLD All < LLD 0 Table 11 - Radiological Environmental Monitoring Program Summary Preoperational(Baseline) Summary
Medium or Pathway Type and Total "# "* #' *" Sampled (Unit of Number of Lower Limit of All Indicator
' " * " Control Locations Nonroutine Measurement and Analyses Name (Distance & Mean2 Mean2 (Range) Reported 3
^ "8' # #" 9 Reporting Period) Performed Direction) (Range) Measurements Mn-54 All < LLD All < LLD 0 Fe-59 All < LLD All < LLD 0 Zn-65 All < LLD All < LLD 0 E )
Co-60 All < LLD All < LLD 0 Sediment (pCi/kg) Gamma Spec (1980-1982) (24) Cs-134 All < LLD Ali < LLD 0 5 m 24E+1 1.7E + 2 (12/18) Site 21, Parr Reservoir
' 8 *
(1.5E + 2) (2.6E + 1 to 4 SE + 2) (2.7 mi,55W) g g 0E 3 Table 11 - Radiological Environmental Monitoring Program Summary P eoperational(Baseline) Summary
'* f'~\
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 fractiuns of detectable measurements at specific locations are indicated in parentheses.
J 3. A nonroutine measurement is any confirmed measured level of radioactivity in any environmental medium that exceeds the ; l reporting requirements of VCSNS Technical Specification 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.
y S. Detection sensitivity is approximately 5 mrem /yr (0.5 pR/hr) determined from the t.nalyses of five years of preoperational e data. 10
$6. No controllocation was specified for drinking water during the preoperational monitoring period.
l
- 7. Inconclusive data. Refer to the Preoperational Radiological Environmental Monitoring Report.
Table 11 - Radiological Environmental Monitoring Program Summary Preoperational(Baseline) Summary _ _ _ _ U
Media Sam e th Cause for Exception toc n ( ek g,) Air 6 September (36) Incomplete samples attributed to air sampler power outages. Grass 6 January (02) Seasonal Unavailability February (07) November (45) December (50) Broadleaf Vegetation 6 April (15) Seasonal Unavailability November (46) 8 January (02) Seasonal Unavailability
~
Groundwater 16 September Third quarter sample exceeded 100 day limit. Sample was taken in October (All Activity
- LLD).
Surface Water 22 January (02) Grab <amples were taken May (19) instead of time composite June (23) samples due to equipment failure. Table 12 - 1990 Environmental Sampling Program Exceptions 36
Airborne gross beta activity measured in air particulate samples collected at (Q indicator locations around VCSNS were consistent with preoperational levels and comparable to operational control levels. Mean preoperational control and indicator levels were 2.8E-2 and 2.7E 2 pCi/m3, respectively. Mean indicator and control location measurements during 1990 were 2.0E 2 and 2.1E 2 pCi/m3, respectively. The highest site specific mean activity was measured at indicator location no.14 (Daiiy, 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 1-131 were 1.8E-3, 2.0E-3, and 2.0E 2 pCi/m3, respecove'" The results agree with gase< us effluent release data reported in the 1990 Semi ..nual Effluent and Waste Dist i Reports for VCSNS. Only 3,00E-2 and 1.33E 3 Ci of particulate and iodine ~oectively, were released. These activity levels are not discernable its , .s amt ' upon consideration of dispersion and dilution factors expere a .0 rek es. Environmental dosimetry meast 1990 did not differ
$ significantly from preoperational mea' o sarv.i seasonal time h periods. Indicator and control dosimetry nw .howed no appreciable 0 differences during 1990. Sampling locatior. . . .unabas Church near h Jenkinsville (2.8 mi, E) was the indicator loc; ..,o sn. g tiie highest mean ? exposure rate of 13.2 pR/hr. This value compares favorablymth the mean exposure rate of 14.0 pR/hr measured during the preoperational period and confirms the j& long term stability of background levels measured at this monitoring location.
(Q;h V Gaseous effluent release data reported for 1990 indicate p fission and activation gases released from VCSNS. An extensive search of fc 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 i.idicate the presence of activated corrosion and most fission products above the respective MDA's. Liquid effluent release data reported for 1990 in the Semiannual Effluent and Waste Disposal Reports indicated a total of 3.6E-1 Ci of measureable fission and 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 1990 yielded results which were not noticeably different from preoperational data. The highest mean indicator tritium activity of 6.9E + 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 preoperational mean of 1.4E + 3 pCi/ liter. Total tritium released in liquid effluents during 1990 was reported to be 4.2E + 2 Ci, a level not discernable in surface water upon consideration of dilution factors experienced during the releases and the detection limitation, 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 v 37
respective radionuclides. High background levels of Pb 214 and Bi 214, daughters of i 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 inis area of South Carolina. The radionuclides Pb-214 and Bi-214 are major gamma emitting daughters in the uranium series decay scheme produced through the decay of dissolved Rn 222 gas in the ground water. No evidence of radioactivity from VCSNS operation was detected.
Tritium analyses of ground water samples during 1990 yielded results which were not significantly different from preoperational results, or indicator significantly different than control. All results were below MDA's. Gamma spectroscopy measurements of drinking water samples collected from the Jenkinsville and Columbia water supplies did not indicate the presence of activated corrosion or fission product activity above the MDA's of the respective radionuclides. The radionuclides Ra-226, Pb 214, anci 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; normallow 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 occurnng uranium associated
' with the aquifer supplying the Jenkinsville water system.
N All drinking water tritium analyses were below MDA's. Gamma spectroscopy measurements of milk samples collected in 1990 were not significantly different from those observed during the preoperational prograrn. Naturally occurring K-40, Ra 226, and Cs 137 attributed to fallout was detected at both sampling locations at concentrations similar to those measured during the preoperational period. There were no identified radionuclides in milk attributed to - VCSNS operation. Gamma 53ectroscopy measurements of grass (forage) samples collected in 1990 indicated tie 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 the preoperational program. There was 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 1990.
- Broadleaf veoetation collected from gardens at location no's 6,8, and 18 were the principaf food pror' ats analyzed during 1990. Naturally occurring-contributions from Ra-226, K-40, :-228 and Be-7 were measured. All radionuclide measurements are comparable to and consistent with the results obtained during the preoperational program.
Other vegetation sampled in 1990 included squash, corn, tomatoes, and radishes representing the non-leafy vegetation group. Naturally occurring K-40 was observed in all samples at concentrations consistent with those observed during the preoperationalperiod. 38
Fish species sampled at three indicator and one controllocation included bass, bream, shad, catfish and carp. Cesium 137 was detected in 15 of 23 samples collected at all sampling locations and in all five species. The highest mean Cs 137 concentration was 2.1E + 1 pCi/kg (Parr Reservoir). 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 Chernobylincident. Liquid effluent releases are assumed to contribute to the presence of Cs 137. However, this contribution is not discernible from the levels of Cs 137 present due to fallout. Liquid offluent releases during 1990 included 3.2E-2 Ci of Cs-137. The presence of Cesium-137 attributed to liquid effluent releases from VCSNS would be limited to Parr and Monticello Reservoirs. Gamma spectroscopy measurements of sediment samples collected during 1990 also indicated the presence of activated corrosion and fission product activity. Cesium-137 was detected in sediment from all indicator and control locations. Cesit m 134 activity was found in Monticello and Parr, Cobalt-60 activity was limited to Monticello and Parr Reservoirs. Mn-54 activity was limited to Monticello. The highest mean concentrations, observed in Parr Reservoir, were 7.9E + 1, and 3.0E + 1 pCi/kg for Co 60, and Cs-134, respectively. The highest mean activity for Cs-137 was 2.5E + 2 pCi/kg found in Monticello. Naturally occurring K-40 was ubiquitous because of the concentration of organic matter in the sediment. Potassium 40 activity was consistent with preo aerational and control measurements, Naturally occurring U-235 was also detectec in sediment collected at all sampling locations at lavels 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 to liquid effluent releases from VCSNS. Activated corrosion product activity ditected in Parr and Monticello Reservoirs is attributed to liquid effluent releases from VCSNS. The relatively low activity in Monticello Reservoir is primarily 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 penods 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 500 hr/ year exposure to shoreline sediment containing mean detected concentrations of Co-60 and Cs 134 was assumed. The results are included in Table 13. ( 39
I O \ Corresponding Calculated AnnualDose Location Radionuclide Activity (pCi/kg) Equivalent (mrem) Maximum l Mean Whole Body Monticello Co 60 1.4 E + 2 1.1 E + 2 1.1E-2 Reservoir Cs-134 8,6E + 1 5.1 E + 1 3.7 E -3
~
Total 1.5E-2 Parr Reservoir Cs 134 4.8E + 1 3.0E + 1 2.1E-3
' ~
Co-60 1.2 E + 2 7.9E + 1 8.0E-3
~-
Total 1.0E-2 Table 13 - 1990 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 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 (O-) 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 1990 and since most biotic species are not as radiosensitive as man. The presence of Cs-137 activity is attributed to residual fallout from the 1986 Cherr 'byl incident, atmospheric weapons testing, and to some extent, operation of VCSNS. The results of the Radiological Environmental Monitoring Program support the results reported in the Semiannual Effluent and Waste Disposal Reports for VCSNS during 1990. The calculated potential radiation dose to the public attributed to activated corrosion product activity and Cs 134 in Broad River media is 2.5E-2 mrem. This figure compares with the 5.67E-2 mrem whole body dose reported ir the 1990 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 1C CrR 50, Appendix I design goals. \ 40
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