Text

Radiological Environ Monitoring Rept,1983
	ML20100F810
Person / Time
Site:	Summer
Issue date:	12/31/1983
From:	Baehr W, Dixon O, Gowdy G; SOUTH CAROLINA ELECTRIC & GAS CO.
To:	James O'Reilly; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
	NUDOCS 8504040455
	Download: ML20100F810 (73)
	v • d • e

{{#Wiki_filter:~ SG-WI5h &P { Virgil C. Summer Environmental Surveillance Laboratory Jenkinsville, South Carolina RADIOLOGICAL ENVIROINENTAL MONITORING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPERATING PERIOD December 31, 1983 January 1, 1983 April 30, 1984 V. C. SUMMER NUCLEAR STATION SOUTH CAROLINA ELECTRIC AND GAS COMPANY Prepared by: Reviewed by: '/ Gregoup K dowdy, Su@rvisor William R. Baehr, Manager Radiological Environmental Programs Corporate Health Physics and Environmental Programs Appr ed O 8 / gh{1( = . Whitaker, Jr; Group.f shager Mark (tory and Suppott Serv)ces p"~ \\ Regula cyFICIAt. COPY 8504040455 831231EP. fcp ^=

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VIRGIL C. SUMMER NUCLEAR STATION [) RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT v TABLE OF CONTENTS Page

1.0 INTRODUCTION

1 1.1 Plant Location and Characteristics 1 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM. 5 5 2.1 Purpose. 2.2 Environmental Radiation Pathways. 5 2.3 Land Use Census (1983) 24 2.4 Program Changes from Previous Reporting Period. 28 2.4.1 Environmental' Laboratory Move. 28 2.4.2 Sampling Site Changes. 28 2.4.3 Analysis Changes. 30 2.5 Indicator and Control Samples 30 2.6 Operational Radiological Monitoring Results '. 32 2.7 Program Exceptions. 32 3.0 INTERPRETATION OF MONITORING FINDINGS AND CONCLUSIONS. 45 () 3.1 Airborne 45 3.1.1 Air Particulates 45 3.1.2-Air Radioiodine. 46 3.1.3 Direct (TLD) 46 3.2 Water borne. 47 3.2.1 Surface Water. 47 3.2.2 Ground Water 48 3.2.3 Drinking Water 49 3.3 Ingestion. 50 3.3.1 Milk. 50 3.3.2 Grass (Forage) 50 3.3.3 Food Products. 51 3.3.4 Fish 51 3.4 Aquatic. 52 3.4.1 Bottom Sediment. 52 4.0 GENERAL CONCLUSIONS. 52 t) I APPENDICES. 53 A. Preoperational Radiological Monitoring Results. 54 B. . Laboratory Intercomparisons with EPA. 66 (i)

E VIRGIL C. SUMMER NUCLEAR STATION h) RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT v LIST OF FIGURES i FIGURE Page l-1 Oontrol Site Iocations (50 Mile Radius around the Virgil C. Stumer Nuclear Station) 2 1-2 Radiologimi 2nitoring Program Ioml Indicator Sanple Sites (5 Mile Radius arcurd Virgil C. Stmer Nuclear Station) 3 1-3 Radiological Monitoring Program Local Indicator i Sanple Sites (On Site and up to 1 Mile Radius around Virgil C. Stumer Nuclear Station) 4 O t e i -(ii)

1 VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT LIST OF TAM PA TABLE Page 2-1 Radiological Envirortrental 2nitoring Program - Virgil C. Surmer Nuclear Station............ 7 2-2 Sampling Site Iomtions . 21 2-3 Census Verification - Septenber 1983......... 25 2-4 - Critical Receptors - 1983 Census........... 26 2-5 Radiological Environnental le nitoring Program Sumary - 1983 Operational Report. . 33 i 2-6 1983 Environnental Program Exceptions.......... 42 A-1 Radiological Envirormental mnitoring Program Summary - Preoperational (Baseline) Report..... . 55 B-1 Results of EPA Intercouparisons . 67 t (iii) l l .u.

4 4 L VIRGIL C. SUMMER NUCLEAR STATION i - RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

1.0 INTRODUCTION

The following report summarizes the Radiological Environmental i Monitoring Program conducted for the Virgil C. Summer Nuclear Station during the operating period, January 1,1983 through ' December. 31, 1983. The entire sampling, analysis and data-i interpretation program (including the preoperational baseline ' program) has been carried out "in-house" by South Carolina Electric and Gas Company (SCE&G). t i 1.1 Plant Location and Characteristics The Virgil C. Summer Nuclear Station (VCSNS) is a 900 MWe Westinghouse pressurized water 1 reactor located adjacent to the i Monticello Reservoir near Jenkinsville, South Carolina and i approximately 26' miles northwest of Columbia, South Carolina _-(see Figure 1-1). VCSNS achieved initial criticality October 22,:1982,. reached 50% power December:12, 1982 and 100% power June 10, 1983 following a-general steam generator modification. The Nuclear Station 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, excess generating l () capacity is used to pump water from the Parr Reservoir to the Monticello Reservoir which is approximately 150 ft. higher. The pump-turbine units operate ~in the generating mode to meet i peak system loads. Monticello Reservoir (approximately 6?00 acres) provides' condenser cooling water for-VCSNS. Intake and l-discharge structures are separated:by.a jetty'to ensure adequate circulation within the reservoir (see Figures 1-2 and .1-3). .There are two discharge points in Monticello Reservoir into which liquids are' released from the plant: 4 l-(1)' Circulating Water Discharge Canal j from: j-a) Unprocessed steam generator blowdown b) Non-nuclear drains -(2)LFairfield ' Pumped Storage Facility Penstocks I from: .a) Liquid waste processing system b) LProcessed ' steam generator ; blowdown 7 l-There are.two main radioactive gaseous waste release points i around VCSNS from which various plant vents, exhausts, ventila-l tors and relief valves are vented. ~ Radioactive liquid and gaseous releases from the: facility and their potential influ-ence on'the surrounding biota and man =are.the primary concern i of;the Radiological Environmental' Monitoring Program. - ( (1).

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VIRGIL C. SUMMER NUCLEAR STATION ( RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT The Virgil C. Summer Nuclear Station is located in Fairfield' County which, along with Newberry County, makes up the principle area within ten (10) miles.of the plant. This area is mainly forest with only about 30% devoted to small farming activities -- predominantly dedicated to small grains, pasture, feed crops and beef cattle. Within a twenty (20) mile radius of the plant, significant portions of Lexington and Richland Counties are encompassed. This area has generally the same make up as that within 10 miles of the plant. Within fifty (50) miles of the plant, Columbia (at 26 miles) is the only large city. Small agricultural concerns are predominant, but still make up less than half of the land area. The main 4 industrial activity is concentrated around Columbia and is 2 generally greater than 20 miles from VCSNS. 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2.1 Purpose The Radiological Environmental Monitoring Program has been designed to meet the following general commitments: () (1) To analyze selected samples in important anticipated pathways for the qualification n d quantification of radionuclides released to the surrounding environment. (2) To establish correlations between levels of environmental radioactivity and radioactive effluent from plant operation. The program utilizes the concepts of control-indicator and preoperational-operational intercomparisons in order to establish the adequacy of source control and to realistically verify the assessment of environmental levels and resultant human radiation dose. 2.2 Environmental Radiation Pathways Specific measurement, sampling and analysis methodology has been programmatically developed to sensitively monitor the pathways expected to represent the most significant sources of radiation exposure to the public and the environnent. Elements of the program monitor the impact of gaseous (airborne) and liquid effluents released f rom the Virgil C. Summer Nuclear Station. The specific methods used~in monitoring the pathways of these effluents leading to exposure of man based on existing [) demography may be summarized as follows: (5)

~.. VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT HUMAN EXPOSURE PATHWAYS (A) Gaseous Effluent Pathway Monitoring Media i Immersion Dose and Thermoluminescent Dosimetry other External Dose (TLD) Area Monitors Air Samples ( Particulate [ and Radioiodine) ( 2 . Vegetation-(Ingestion) Vegetation / Food Crop j Samples Air Samples Milk (Ingestion) Milk Samples Vegetation Samples Grass (Forage) Samples i Air Samples i j (B) Liquid Effluent Pathway Monitoring Media Fish (Ingestion) Surface Water Samples I Bottom Sediment Samples Fish Samples i Water & Shoreline TLD Area Monitors Exposure (Ingestion SurfaceJ Water Samples -and Immersion) Bottom Sediment Samples ll Drinking Water (Ingestion) Ground Water Samples i Drinking Water Samples l _ Site (VCSNS) related dispersion characteristics, demography, hydrology, land use, anticipated' source terms, and the critical pathways outlined above have been considerad in !~ the selection of sample media, sampling and analysis 1 j frequencies,' sample locations, and types of. analyses. These criteria were used to~ establish both the preoperational and ~ l operational phases of the radiological surveillance program. l The program that evolved during the preoperational l ( baseline) monitoring period, incorporating all 'of the elements in the Virgil C. Summer Technical Specifications ~ plus additional-i special. study' criteria, is detailed in Table 2-1. .The~ practices and~ guidance contained in USNRC -Regulatory Guide 4.15 are directly reflected in the procedures used in the' program.. The validity of i measurements 'is assured through various intercomparison and ' audit programs. The monitoring sites employed, and, their distance and i direction from;the reactor containment. building of'the' Virgil C. () Summer Nuclear Station, is presented in Table ~ 2-2.- i-(6) e w-

i> RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE PROGRAM . VIRGIL C. SUMMER NUCLEAR STATION TABLE 2-1 (1) - Exposure: Pathway Criteria for Selection.of Sampling-.and Sample' ' Type & Frequency and/or Sample Sample Number &-Location Collection Frequency Locations of Analysis 1 i AIRBORNE: I. -Particulates A) 3 Indicat'or samples tx) be Continuous-sampler 2 Gross beta taken:at locations (in dif-operation with weekly 5' following filter. ferent. sectors) beyond but collection 10 change; Monthlyt I as'close to the exclusion Composite ( by boundary as practicable 'where location)- f or -the highest offsite sector- - ganna isotopic al ground level concentra-tions are, anticipated. (2) 1. B) 1 Indicator sample to be 6 taken 'in the sector: beyond but.as close to the exclu- .sion boundary as practi-cable corresponding to'the G _ residence,having the high-L est anticipated offsite ground level concentration-or dose. (2) C) 1 Indicator sample to-be 14 taken at the. location of one of the dairies most -likely to be af fected. ( 2,4 )

D) 6fAdditional Indicator 1

samples:to beLtaken at 4 locations (in different 8 sectors) beyond but as 11 close to the exclusion 13 boundary as practicable and 15 nearer to the Plant than the nearest critical receptor-for the chosen sector. (2) Page 1 of 14

. = ("} f' I O d U RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 2-1 (Continued) (1) Exposure Pathway Criteria for Selection of Sampling and Sample Type & Frequency and/or-Sample Sample Number & Location Collection Frequency Locations of Analysis AIRBORNE (Cont'd ) E) 3 Control samples to be 16 taken at locations at 17 least 10 air miles from 18* the site and not in the most prevalent wind directions. (2) II. Radioiodine A) 3 Indicator samples to Continuous sampler 2 Gamma Isotopic be taken at two loca-operation with 5' for Iodine 131 tions as given in I(A) weekly cannister 10 a bove. collection B) 1 Indicator. sample to 6 be taken at the loca-S tion as given in I(B) ~ above. C) 1 Indicator sample to be 14 taken at the location as given in I(C) above. D) 2 Control samples to be 16 taken at locations 17 similar in nature to I(E) a bove. Page 2 of 14

O O O l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 2-1 (Continued) (1) Exposure Pathway Crit 0ria for Selection of Sampling and ' Sample Type & Fr eq uency and/or Sample Sample Number & Location Collection Frequency Locations of Analysis AIRBORNE (Cont'd) III. Direct' A) 13 Indicator stations Monthly or quarterly 1 Gamma dose to. form an inner ring exchange (5,7); two or 2 monthly of stations in the 13 more dosimeters at 3 or quarterly accessible sectors each location. 4 within 1 to 2 miles of 5 the plant. 6 7 8 9 10 29 30 47 B) 16 Indicator stations 12 to form an outer. ring 14 of stations in the 16 32 sectors within 3 to 5 33 miles of the plant. 34 35 36 37 41 42 43 45 46 49 53 55 i Page 3 of 14

O O O RADIOLOGICAL ENVIROtNENTAL MONITORING PROGRAM . VIRGIL C. SUMMER NUCLEAR STATION TABLE'2-1 (Continued) (1) Exposure Pathway.. Criteria for Selection'of Sampling ~and Sample Tye d & Frequency -' and/or Sample Sample Number & Location Collection Frequency Locations of Analysis-4 AIRBORNE (Cont'd)

- C) 20 Stations to be placed in 11 special interest areas such

.- 13 as population centers, nearby 15 residences, schools and in 2 16 or 3 areas to serve as 17 controls. 18 l 19 20 31 44 48 50 51 _g 52 54 56 57 58 59 60

D) 8 Stations to be placed 61-within the exclusion 62

~ boundary at the locations of 63 the onsite Pressurized. Ion 64 Chamber Detectors (Special 65 Study) 66 67 68 Page 4 of 14 4

A 1M-- u-+. -,d.h ~J4.4 ,-s+u -s 4=- -~.+E,4 +%-aw 4.A-- ui44.-_ E-M RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL.C. SUMMER NUCLEAR STATION TABLE 2-1 (Continued) t (1) Exposure Pathway Criteria for Selection of Sampling and Sample: Type & Fr eq uency and/or Sample' Sample Number & Location Collection Frequency Locations of Analysis AIRBORNE (Cont'd)

E) 3 Stations to be placed on 69 buoys on Monticello 70 Reservoir (Background 71 Study)

WATERBORNE: IV. Surface A) 1 Indicator sample downstream Time composite 21 Gamma isotopic Water to be taken at a location samples with (3,6) monthly with which allows for mixing and collection every quarterly com-dilution in the ultimate month. (5) posite ( by receiving river, location) or-monthly samplet to be, analyzed Z for tritium. B) 1 Control-sample to be taken 22(3) at a location on the re-ceiving river, sufficiently far up-stream such that no effects of pumped storage 4 operation are anticipated. Page 5 of 14

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM. VIRGIL C. SUMMER NUCLEAR STATION TABLE 2-1 (Continued) (1) Exposure Pathway. Criteria for Selection of Sampling and' Sample Typ e & Frequency j... and/or Sample ' Sample Number-& Location . Collection Frequencyt Locations of Analysis WATERBORNE (Cont'd)' C) 1 Indicator sample-from a 17 -location immediately upstream of the nearest downstream municipal water supply. -D) 1 Indicator sample to be' 23(3) taken in the upper' reservoir of the pumped storage. faci-lity at the plant discharge canal.

E) :L Indicator' sample.to be 25

-takenlin the upper reser-N voir at the intake of the

pumped storage facility'.

4 4 i F) 1: Indicator sample to be Grab sampling 24(3) As in IV (A) taken in the upper monthly (5) above reservoir's 1non-fluctuating recreational area. G) 1 Control sample to be 18(3) l .taken at'a' location on i a separated unaffected _~. watershed reservoir. 4 Page 6 of 14 1 j .~ }. r-wr 2 w m.m

O-O O RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 2-1 (Continued) (1) Exposure Pathway Criteria for Selection of Sampling and Sample Type & Freq uency and/or Sample Sample Number & Location Collection Frequency Locations of Analysis WATERBORNE (Cont'd) ll. Ground Water A) 2 Indicator samples to Quarterly grab 26 Gamma isotopic be'taken within the sampling (7) 27 and critium exclusion boundary and analyses qua r-in the direction of terly. potentially affected ground water supplies. B) 2 Control samples from 16 unaffected locations. 18* VI. Drinking A) 1 Indicator sample Monthly grab 28 Mo nthly Water from a nearby public sampling (5) gamma isotopic, ,,g ground water supply gross beta and source. tritium analysesi B) 1 Indicator (finished Monthly composite 17 water) sample from the sampling nearest downstream water supply. ( Page 7 of 14 i o i

o o o a RADIOLOGICAL ENVIRO!G4 ENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 2-1 (Continued) t 1 (1) Exposure. Pathway Criteria for' Selection of Sampling and . Sample Type-& Frequency 1 and/or Sample Sample Number & Location Collection Frequency Locations of Analysis . INGESTION: VII. Milk (4)' A) Samples f rom milking - Biweekly grab 14* Gamma isotopic animals in 3 loca-sample (8) tt To be supplied and I-131 tions within 5 km when milking analysis bi-having the highest animals are found weekly (8) tt dose potential.- If in accordance with there are none, then criteria'VII.A. 1 sample from i. milking animals in each of 3 areas 1 between 5 to 8 km O > distant where doses 6 are calculated to be greater than 1 j mrem per yaar.(10) i B) 1 Control sample to 16 [ be taken at the loca-tion of a dairy > 20 miles distant and not in the most prevalent i i wind direction. (2) i f T ? f 4 j-Page 8 of 11 i i 4 i

O O O RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ~~ VIRGIL C. SUMMER NUCLEAR STATION TABLE 2-1 (Continued) (1 Exposure Pathway Criteria for Selection of Sampling and Sample ) Type &. Frequency and/or Sample Sample Number & Location Collection Frequency Locations of Analysis INGESTION (Cont'd) C) 1 Indicator grass Monthly when available 6 Gamma Isotopic (forage) sample to be (5) taken at one of the locations beyond but as close to the exclusion boundary as practicable where the highest offsite sectoral' ground level C' concentrations are anticipated. (2) D) 1 Indicator grass 14* (forage) sample to be To be supplied taken at the location when milking of VII(A) above when animals are found animals are on in accordance with pasture. criteria VII.A. E) 1 Control grass (for-16 age) sample to be taken at the location of VII(B) above. Page 9 of 14 l

~ RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL.C. SUMMER NUCLEAR STATION TABLE 2-1 (Continued) (1) Exposure Pathway Criteria for Selection of Sampling and Sample Type & Frequency and/or Sample , Sample Number & Location Collection Frequency Locations of Analysis INGESTION (Cont'd) VIII. Food A) Four samples of broadleaf Monthly when available 2* Gamma Isotopic . Products vegetation grown in 1 (5) 5 on edible por-location of special 6 ,tions, interest and in the 3 8 nearest offsite locations of highest calculated annual average ground level D/Q if milk sampling is not performed within 3 km or if milk sampling is not 4 performed at a location within 5-10 km where the doses.are calculated to be e greater than 1 ~ mrem /yr(10)

B) l Indicator sample of each Annually during grow" 6

of the various types of ing season (11) foods grown in the area surrounding the plant. T Page 10 of 14 I

O-O O RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 2-1 (Continued) (1) E=posure Pathway Criteria for Selection of Sampling and Sample Type & Frequency ~ and/or Sample Sample Number & Location Collection Frequency Locations of' Analysis -INGESTION. Cont'd) C) 1 Control sample for the same as for VIII(A) 18(3) same foods in VIII (A) and or (3), as appropriate (B).taken at a location at least 10 miles-distant and not.in the most prevalent win'd direction. IX. Fish A) 1 Indicator sample to be Semi-annual (9) 23(3) Gamma isotopic taken at a. location in collection of the on edible por-the upper reservoir. .following specie tions semi-O types if available: annually 3 ba ss; bream, crappie; catfish, carp; forage fish (shad) . 'i f a 4 1 h i age 11 of 14 1 4.

s. 1 r'

R ADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 2-1 (Continued) (1) Exposure Pathway Criteria for Selection of Sampling and Sample Type & Fr equency and/or Sample Sample Number & Location Collection Frequency Locations of Analysis INGESTION (Cont'd) B) 1 Indicator sample 21 (3) to be taken at a loca-tion in the lower reservoir. C) 1 Indicator sample 24(3) to be taken at a loca-tion in the upper reservoir's non-fluctuating recreational area. h D) 1 Control sample to 22(3) be taken at a loca-tion on the receiving -river, sufficiently far upstream such that no effects of pumped storage opera-tion are anticipated. AQUATIC: X. Sediment A) 1 Indicator sample to Semi-annual grab 23(3) Gamma isotopic be taken at a location sample (9) in the upper reservoir. Page 12 of 14

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 2-1 (Continued) (1) Exposure Pathway Criteria for Selection of Sampling and Sample Type & Frequency and/or Sample Sample Number & Location Collection Frequency Locations of Analysis AQUATIC (Cont'd) B)'l Indicator sample 24(3) to be taken in the upper reservoir's non-fluctuating recreational area. C) 1 Indicator sample to 21(3) be taken on the shore-line of the lower reservoir. D) 1 Control sample to 22(3) be taken in the re-ceiving river, e ~ sufficiently far upstream such that no effects of pumped storage operation are anticipated, c Page 13 of 14

~ i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 2-1 (Continued) 1 NOTES .(1) Location numbers refer to Figures 1-1, 1-2, 1-3 and Table 2-2. (2) Sample site locations are based on the meteorological analysis for the period of record as presented in Chapters 5 and 6, Virgil C. Summer Operating License Environmental Report. (3) Though generalized areas are noted for simplicity of sample site enumeration, airborne, water and sediment sampling are done at the same location whereas biological sampling sites are generalized areas in order to reasonably assure availability of samples. (4) Milking animal and garden survey results will be analyzed annually. Should the survey indicate new activity the owners shall be contacted with regard to a contract for supplying sufficient samples. If contractual arrangements can be made, site (s) will be added for additional milk sampling up to a total of 3 Indicator Locations. (5) Not to exceed-35 days. (6) Time composite samples are samples which are collected with equipment capable of collecting an aliquot at time intervals which are short (e.g. hourly) relative to the compositing period, 4 b (7) At least once per 100 ' days. (8) At least once per 18 days. (9) At least once per 200 days. (10) The dose shall be calculated for the maximum organ and age group, using the guidance / methodology contained in Regulatory Guide 1.109, Rev. 1, and the parameters particular to the Site. (11) At least once per 400 days. (*) Not required by Technical Specifications. (**) Only 8 Stations required by Technical Specifications. (t) Technical Specification is quarterly. (tt) Technical Specifications require semi-monthly sampling when animals are on pasture, monthly at other times. Page 14 of 14

VIRGIL C. SIM4ER NUCLEAR STATION RADIOIOGICAL ENVIROMENTAL MONITORIE REPORT TAEE 2-2 SAMPLIE SITE LOCATIONS (1) (2) (3) Site # Description Distance Direction Sample Type (s) (Miles) 1 Borrow Pit 1.2 182.0 S AP,D4 2 Transnission Line 1.2 225.0 SN AP,RI,Di,GA 3 Firing Range 1.2 270.0 W Di 4 Pairfield Hydro 1.2 289.5 WNW AP,Di 5 Transnission Line Entrance 0.9 145.5 SE AP,RI, D4,GA 6 Env. Lab Garden 1.0 104.0 ESE AP,RI,Di,GR,GA 7 mnticello Pennisula 1.2 83.0 E D4 8 lenticello Res. S of Rd 224 1.5 63.0 ENE AP, D4,GA 9 Ball Park 2.2 44.0 NB Di 10 mteorological 'Ibwer #2 2.5 25.5 NNE AP,RI,D4 11 Ross Robinson 3.3 8.0 N AP,D4 12 Old Hwy 99 4.2 349.0 N D4 13 North Dam 2.9 334.0 NNN AP,Di 14 Graham's Dairy 5.1 270.0 W AP, RI, D4, MK,GR 15 Parr Village 2.5 204.0 SSW AP,Di

16 M Sinnis' Dairy 28.0 W

AP,RI,D4,G1,MK,GR

17 Columbia mter Works 24.7-SE AP,RI, D4, SW, N
18 Corley/Wyse (Lake Murray) (4) 16.5 S

AP, D4,SW,GW,GA

19 Smith (Little Saluda) 17.9 SSW Di
20 Itss (Whitmire) 22.0 W

Di 21 Parr Reservoir 2.7 19 9.5 SSW SW,FH,BS

22 Chrlisle/Neal Shoals (5) 24.0/30.0 NW SW,FH,BS 23 Discharge Canal (Mont. Res.)

0.5 104.5 ESE SN,FH,BS 24 Recreation Lake 5.5 2.0 N SN,FH,BS 25 Fairfield Punped Storage 0.9 302.0 WW SW (Monticello Res.) 26 On Site Well (P4) 265 FF 270.0 W GW 27 On Site Well (P5) 510 Fr 180.0 S GW 28 N.1 clear Training Center (EOF)(6) 2.4 168.0 SSE DW 29 Trans. Line WSW of VCSNS 0.9 248.0 WSW Di 30 Oak Tree North of 1.0 197.0 SSW D4 Borrow Pit 31 Itcrorey-Liston School 5.8 12.5 NNE D2 32 Dirt Rd off Rd 205 4.5 25.0 NNE DQ 33 Rd 48 near Hwy 213 4.2 70.0 ENE DQ 34 Rd 419 North of Hwy 60 4.8 112.5 ESE DQ 35 Unnamed Circle Road off 4.8 137.5 SE IQ Hwy 215 l f (21) l

VIRGIL C. SWMER NUCLEAR STATION d RADIOIOGICAL EWIROMENTAL MONITORItG REPORT i TABLE 2-2 (continued) l SAMPLING SITE IOCATIONS 7 (1) (2) (3) Site # Description Distance Direction Sample Type (s) (Miles) 36 kbods Behind Jenk. Post 3.1 151.5 SSE DQ -Office 37 Ruff House 4.9 305.5 m IX) 38 No Sampler 39 m Sanpler 40 No Sampler 41 End of Catwalk 3.9 185.0 S DQ 42 Wicker's Store 3.9 199.0 SSW IQ 43 Hwy 176 and Rd 435 5.2 236.0 SW 00 44 Rd 28 at Cannon's Creek 2.9 255.5 WSW DQ 45 Rd 33 at Pcrnaria 5.9 253.0 WSW DQ 46 Rd 28 at Heller's Creek. 3.7 292.5 WW DQ 47 Fairfield Tailrace 1.0 316.0 W DQ 48 Cemetary 2.3 318.5 W DQ 49 tbrth Rd 383-4.0 332.5 NW DQ 50 New Rd 99 (West Shore) 5.5 1.0 N IQ 51 New Rd 99 (East Shore) 5.5 5.0 N DQ 52 m nticello (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 2.8 94.0 E DQ 56 Jenkinsville Diner 2.0 144.0 SE DQ 57 Shealy (Hwy 213 and 215) 2.7 146.0 SE DQ 58 Zack Crunpton 2.5 158.0 SSE DQ 59 mclear Training Center (EOF)(6) 2.4 168.0 SSE DQ 60 Rd 98 near Rd 28 3.5 275.0 W DQ 61 Switchyard, SE Entrance 0.10 180.0 S IM to Plant 62 East of Training Bldg. 0.13 220.0 SW IM 63 East of Daniel's Office 0.17 270.0 W IM 64 Riprap W of Intake 0.13 .338.5 NW IM 65 Guard Tower 0.13 22.5 NNE IM 66 Jetty _ 0.6 33.0 NNE IM 67 Service Water Pond' O.5 72.0 ENE IM (East Side) 68 Fuel Oil Storage Tank 0.2 108.5 ESE IM 69 Exclusion Buoy NNW on 1.0 337.0 NW IM m nticello Res. 70 Exclusion Buoy N on 1.0 0.0 N IM mnticello Res. 71 Tenperature Buoy on 5.4 3.0 N IM mnticello Res. (22)

VIRGIL C. SINMER NU1 EAR STATION RADIOLOGICAL ENVIROtNEtirAL ENI'IDRIE REPORT TABLE 2-2 (continued) EOOTNOTES (*) Control Site. (1) Distance given is the distance between the site location and the center of the VCSNS reactor contairunent building. (2) Direction given is direction in degrees from true north-south line through center of reactor contairunent building. (3) Sanple Types: AP = Air Particulate Di = Drinking Water RI = Air Radiciodine MK = Milk Di = mnthly TLD GR = Grass (Forage) D2 = Quarterly TLD GA = Garden SW = Surface Water FH = Fish GW = Ground hhter BS = Bottom Sedinent (4) Site 18 consists of 4 locations in close prasimity next to Iake Murray. Air and TLD Samples are taken at the SCE&G employee recreation area at Pine Island. Ground water sanples are taken at the Corley residence. Garden product sa:rples are taken at the Wyse residence. Surface water is taken near the shoreline in Lake Murray. (5) Site 22 consists of 2 sanpling locations. A continuous surface water sanpler is co-located with IB3S at the Carlisle Highway 121 bridge over the Broad River. Fish and sediment sanples are taken upstream of this location at Neal Shoals. (6) Site 28 for drinking water and site 59 for quarterly TLD neasurements are co-located at the location of the SCE&G Nuclear Training Center which doubles as the Virgil C. Strrrner Station Energency Offsite Facility. 1 (23)

VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 2.3 Land Use Census (1983) l The annual land use census for 1983 was conducted from September 19 through September 28, 1983. The results of the 1983 census are summarized in Table 2-3. (For results of l previous surveys, see the 1982 Radiological Environmental Monitoring Report and the Preoperational Baseline Environmental Report.) Major points of. interest coming out of the 1983 census are as follows: 1. The Radiological Environmental Laboratory gardens are now located in the following sectors: a a. SW, 1.2 miles - Site #2 b. SE, 0.9 miles - Site #5 c. ESE, 1.0 miles - Site #6 d. ENE, 1.5 miles - Site #8 These locations reflect the results of the D/O calculations for critical receptors following the 1982 land use census (see the 1982 Radiological Environmental Monitoring Report). D/Q represents the annual average relative deposition of gaseous effluents released from VCSNS at the location occupied by the maximum exposed individual. These results have been reconfirmed following the 1983 census (see Table 2-4). Sites 5, 6 and 8 are used as the gardens required by Technical Specifications, Table 3.12-1, Item VIII.A. Site 2 is maintained in order to monitor the potential grazing area in that sector on the west side of Parr Reservoir. 2. Residential development of the shorelines of Monticello and Parr Reservoirs is increasing. 3. There are still no milking animals being milked within 5 miles of Virgil C. Summer Nuclear Station. 4. The nearest dairy activity is still in the west sector, 5.1 miles from Virgil C. Summer Nuclear Station. Changes f rom the 1982 land use census are noted on the summary Table 2-3. Upon completion of the census, dose calculations were performed using 1975 and 1979 meteorological data and source terms from the Virgil C. Summer Nuclear Station Final Safety Analysis Report to determine the critical receptor (maximum exposed individual) for each sector around the Virgil C. Summer Nuclear Station. The.results of these calculations are compiled in Table 2-4. (24)

TAB [.E 2-3 CEEUS VERIFICATION - SEPTEMBER 1983 l l nearest l l searest l l l m. l l l m. l l l Sector l Residence l Miles l Garden i Miles l Cattle l Milked l Milesl Goats l Milked Miles l l l l l l l l l l l l l ln l mrtin l 3.8 l M2rtin l 3.8 l l l l l l l lNm l McGill l 3.1 l Md3ill l 3.1 l Robinson l 0 l 3.5 l l l l l ne l Stonel l 2.1 l Stone 3 l 2.1 l Robinson l 0 l 2.9 l Stone l 0 l 2.1 l lEm l Johnson l 1.4 l winingham l 1.5 l l l l l l l lE l Anderson 1 l 1.4 l Martin l 1.5 l l l l l l l l ESE l Martin 1 l 1.1 l Martin l 1.1 l l l l l l l l SE l mite l 1.s l Sumner ,l 1.5 l l l l l l l 3 ll SSE I cr=9 ton l 2.s l Cr-ptw l 2.s l l l l l l l l Eargle l 3.9 l Eargle l 3.9 l Yarborcughl 0 l 3.8 l l l l ~ S lSu l wederi l 3.2 l Ash l 3.4 l Smith l 0 l 4.5 l l l l l sw loavis l 3.1 l oavis l 3.1 l Su-er4 l 0 l 3.1 l l l l lEw l Sumer l 3.3 l Sumner l 3.3 l Miller l 0 l 2.3 l l l l lw l Amick l 2.s l Amick l 2.s l Miller 4 l 0 l 2.3 l l l l lwm l ralmerl l 2.7 l ralner3 l 2.7 l williams

l l 4.s l Turki4l l 4.2 l

0 0 lW l wright l 3.9 l weight l 3.9 l Cole l 0 l 4.1 l l l l lNM lmrch2 l 2.9 l March l 3.0 l mrch l 0 l 3.0 l March

l 0

l 3.0 l l 1 I I I I I I I I l l l l l I I I I I I I l l

Milking Animal, Not Milked IChange in Closest Residence 3 Change in Closest Garden 2mme Change 4 Additional Incation

i i TAB [E 2-4 CRITICAL RE3 PIORS - 1983 NSUS 1975 ETEORO[OGICAL DATA 1979 ETEORCEOGICAL DATA DISTANCE DOSE RATE DOSE RA'IE Sta.;1w (Miles) 19@E PATHhRY . X/O D/Q mrenVyr X/Q D/Q mrsVyr i N 3.8

Martin Res/ Gar 2.3E-07 6.8E-10 1.9E-01 1.6E-07 4.8E-10 1.3E-01 4

( lee 3.1 Mr,ill Res/ Gar 4.lE-07 1.3E-09 3.5E-01 2.5E-07 8.6E-10 _2.3E-01 !aE 3.5

Robinson Res/ Gar / Beef 3.5E-07 9.6E-10 3.6E-01 2.0E-07 6.5E-10 2.4E-01 PE 2.1
Stone (l)

Res/ Gar / Goat 9.4E-07 3.6E-09 1.0E-01 6.2E-07 2.5E-09 6.6E-01 IE 2.9 Robinson Res/ Gar / Beef 5.0E-07 1.6E-09 6.0E-01 3.2E-07 1.2E-09 4.4E-01 DE 1.4 Johnson Des 1.8E-06 8.0E-09 6.9E-02 1.3E-06 5.6E-09 4.9E-02 DE 1.5

Willingham Res/ Gar 1.6E-06 6.8E-09 1.8E+00 1.lE-06 4.9E-09 1.3E+00 E

1.4 Anderson (1) Res 1.7E-06 6.6E-09 6.4E-02 1.3E-06 5.0E-09 4.9E-02 E 1.5

Martin Res/ Gar 1.5E-06 5.6E-09 1.5E+00 1.lE-06 4.4E-09 1.2C+00 ESE 1.1
Martin (l)

Res/ Gar 2.8E-06 8.2E-09 2.3E+00 1.5E-06 4.8E-09 1.3E+00 SE 1.5 ittite Res 2.lE-06 5.8E-09 7.8E-02 5.5E-07 2.0E-09 2.lE-02 _g SE 1.5

Suruner Res/ Gar 2.lE-06 5.8E-09 1.6E+00 5.5E-07 2.0E-09 5.4E-01 SSE 2.5
crunpton Res/ Gar 5.0E-07 1.2E-09 3.4E-01 1.2E-07 5.lE-10 1.4E-01 S

3.9

Eargle Res/ Gar 2.5E-07 3.6E-10 1.1E-01 8.2E-08 3.3E-10 8.8E-02 S

3.8 Yarborough Beef (3) 2.6E-07 3.9E-10 4.9E-02 8.6E-08 3.5E-10 3.8E-02 S9f 3.2 Weber (1) Res 3.3B-07 7.4E-10 1.2E-02 1.2E-07 6.4E-10 4.6E-03 S9i 3.4

Ash Res/ Gar 2.9E-07 6.4E-10 1.8E-01 1.1E-07 5.8E-10 1.5E-01 S9f 4.5 Snith Beef (3) 1.8E-07 3.5E-10 4.2E-02 6.3E-08 3.3E-10 3.5E-02 SW 3.1
Davis Res/ Gar 4.4E-07 1.2E-09 3.3E-01 1.5E-07 1.lE-09 2.8E-01 SW 3.1 Sunener Beef (3) 4.4E-07 1.2E-09 1.4E-01 1.5E-07 1.lE-09 1.2E-01 WSW 3.3
Summer Res/ Gar 3.lE-07 8.8E-10 2.4E-01(4) 9.0E-08 6.4E-10 1.6E-01( 4)

MSN 2.3 Miller Beef (3) 6.0E-07 2.0E-09 2.2E-01 2.0E-07 1.4E-09 1.50-01 W 2.3

Miller Res/ Gar /Baef 4.3E-07 1.4E-09 5.2E-01 2.3E-07 1.lE-09 4.0E-01 W

2.5 Amick Res/ Gar 3.6E-07 1.lE-09 3.0E-01 1.9E-07 9.2E-10 2.4E-01 i lett 2.7

Palner(l)

Res/ Garden 2.6E-07 7.9E-10 2.2E-01 1.6E-07 7.0E-10 1.8E-01 Wtti 4.5 Willians Res/ Gar / Beef 1.0E-07 _2.5E-10 9.51I-02 5.9E-08 2.3E-10 8.4E-02 l Wi@t 4.2 Turki Res/ Goat 1.lE-07 3.0s-10 7.7E-03 6.8E-08 2.7E-10 5.8E-03 Pet

3.9 itight Res/ Gar 1.7E-07 4.6E-10 1.3E-01 1.2E-07 4.0E-10

1. lE-01 taf 4.1

0 ole Res/ Gar /Baef 1.6E-07 4.lE-10 1.60-01 1.1E-07 3.7E-10 1.4E-01 NMt 2.9 J. March (2)

Residence 2.8E-07 4.0E-10 1.0E-02 3.0E-07 9.4E-10 1.1E-02 NMt 3.0

F. March Res/ Gar / Beef 2.7E-07 9.4E-10 3.5E-01' 2.8E-07 8.6E-10 3.2E-01 Ntti 3.0 P. March Res/ Gar / Goat 2.7E-07 9.4E-10 2.7E-01 2.8E-07 8.6E-10 2.5E-01 I

TABLE 2-4 (continued) CRITICAL RECEFERS - 1983 CENSUS Denotes Critical Receptor (maxinun egosed individual) for the Sector. (1) Change in Closest Residence. (2) Mune Change. (3) Residence as9 M in calculations. (4) Assuming Sunner eats beef fran his herd in the SW, Surmer's dose rate would be as follows: 0.36 wavyr (75 X/Q, D/Q), 0.27 wenVyr (79 X/Q, EVQ). Eb i i 1 )

VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 2.4 Program Changes from Previous Reporting Period 2.4.1 Environmental Laboratory Move On about March 1, 1983, the VCSNS Environmental Surveillance Laboratory completed the move of its entire facility from the old Parr Nuclear Plant Service Building to new quarters in the Virgil C. Summer Nuclear Training Center (NTC) located 2.4 miles SSE of VCSNS at the junction of highways 16 and 213. The new f acilities provide ~ 7000 sq. f t. of laboratory and count room space for both the Radiological and Non-Radiological Environmental Programs groups. Adequate of fice space, conference rooms and a Butler Building to house the TLD irradiator and company boats and trucks is also available at the new location. The Environmental Surveillance Laboratory is located next to the VCSNS Emergency Of fsite Facility (EOF) and its Technical Support Center in order to provide support for emergency functions necessary for the Virgil C. Summer Nuclear Station. 2.4.2 Sampling Site Changes 1. Site 5 As mentioned in Section 2.3, the garden located at Site 4 (1.2 miles WNW) in 1982 was relocated to Site 5 (0.9 miles SE) in 1983 reflecting the results of D/0 calculations from the 1982 land use census. The first garden sample from Site 5 was taken April 4, 1983. 2. Site 18 In 1982, the site 18 control air sampler and monthly TLD were located at the Corley residence near Lake Murray. Sale of the property on which these samplers were located and subsequent construction activity necessitated the movement of the samplers to a new location on Pine Island (an SCE&G recreational f acility) at Lake Murray - nearly the same distance and direction from VCSNS. The last air sample was collected at Corleys January 4, 1983 and the first air sample m (28) I

~ J 1 VIRGIL C. SUMMER. NUCLEAR STATION j RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT started at Pine Island January 12, 1983. The TLD location was switched during the t ' January 5,1983 changeout between the i December,1982 and January,1983 samples. I j '3. ' Site 28 t l The Jenkinsville grab drinking water sample taken at -the Mobile Diner (2.0 miles SE) was moved to the newly built NTC (2.4 miles SSE) housing the VCSNS Environmental Laboratory (see Section + 2.4.1) May 16,1983 when the Mobile Diner was j closed. The wrC and Mobile Diner are on the same t well system so the baseline data remains directly comparable. 4. Site 29 I A close look at the aerial photographs (see 1982 { Operational Radiological Environmental Monitoring Report) of the vicinity of VCSNS revealed that Site 29 was not located as indicated on the maps (Figures 1-2 and 1-3) and table (Table 2-2). During the normal changeout of monthly TLD's on January 5,1983, this situation was rectified by moving the TLD about 1500 feet northeast from the l edge of the Broad River to its present location on the Transmission Line (0.9 mile WSW of 1 i VCSNS). ) j 5. Site 59 1 i The quarterly TLD site located on private land l just north of highway 16, 2.2 miles SSE of VCSNS, { was moved across highway 16 to SCE&G property at the intersection of highways 16 and 213 during i i the normal quarterly changeout January 13, 1983. The new' location was at the front of the newly constructed NTC, 2.4 miles SSE of VCSNS. Once i the construction was completed and grass laid, the TLD was moved to its present location at the ] back of the wrC ~ (still 2.4 miles SSE) duriag the i next scheduled quarterly changeout on April 13, i 1983. 1 I j (29) } e. . -.. ~. - -.. - - ~

VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT i 2.4.3 Analysis Changes I With the full development of the liquid scintillation (tritium analysis) program in 1983, a monthly tritium sample count was instituted for all surface and drinking water samples. This is a change from the quarterly tritium composite samples previously analyzed and. required by Technical Specifications. Monthly tritium counting will allow Radiological Environmental Programs personnel to monitor the liquid effluent pathway for tritium in a more timely and sensitive manner. 2.5 Indicator and Control Samples In addition to comparisions between preoperational and operational data (Section 2.2), control-indicator comparisons are performed. The comparisons of operational control-indicator data are utilized to assess the probability that any observed high concentration estimate is due to random or regional fluctuations in measurements rather than to a true increase in local environmental concentrations. Indicator sites are generally within five miles of the p1' ant and are i j indicative of plant operating. conditions. (See Figures 1-2 and 1-3 for detailed maps of the indicator sampling locations around the Virgil C. Summer Nuclear Station and Table 2-2 for specific details.) Control sites are greater than ten miles f rom the plant and are intended to indicate conditio,ns. away from its influence. (See Figure 1-1 and Table 2-2 for j locations of control sites around VCSNS. ) Valuable information can be gained through multiple types of sampling and measurements at specific locations. As can be seen from Table 2-2, several multiple sampling combinations are in use around the Virgil C. Summer Nuclear Station. All air i sampling locations (Sites 1, 2, 4, 5, 6, 8, 10, 11, 13, 14, 15, 16, 17, 18) are also environmental dosimetry monitoring locations. At those points airborne plant ef fluent contribution is monitored for gamma immersion dose (noble gases), airborne particulates, and (at Sites 2, 5, 6, 10, 14, 16, 17 o nly ) radioiodine. Eight of these locations have i additional complementary sampling / measurement pathways for i monitoring plant effluents. Sites 2 (1.2 mi SW), 5 (0.9 mi i SE), and 8 (1.5 mi ENE) have broadleaf vegetation gardens for monitoring a gaseous effluent deposition and ingestion pathway. i The other five locations (three of them control sites) allow greater definition of existing specific pathways, i f (30) 4. ~. - -

VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT j Site 6 - Environmental, Lab Garden (1.0 mi ESE) Air Particulate Air Radioiodine Environmental TLD (Monthly) Broadleaf Vegetation other Food Crops Grass (Forage) Site 14 - Graham's Dairy (5.1 mi W) 4 Air Particulate 4 Air Radioiodine Environmental TLD (Monthly) Milk 4 Grass (Forage) 4 Site 16 - McGinnis' Dairy (28.0 mi W) Air Particulate l Air Radioiodine Environmental TLD (Monthly) Milk Grass (Forage) Ground Water Site 17 - Columbia Water Works (24.7 mi SE) 4 Air Particulate Air Radiciodine Environmental TLD (Monthly) Surface Water Drinking Water Site 18 - Corley/Wyse/ Pine Island (Lake Murray) - (16.5 mi S) Air Particulate Environmental TLD (Monthly) Broadleaf Vegetation 4 Other Food Crops surface Water Ground Water In addition, liquid effluents are monitored through three i pathways (fish, bottom sediment and surface water) at the three most probably af fected bodies of water around the plant - Site 21: Parr Reservoir (2.7 mi SSW), Site 23: Monticello Reservoir (0.5 mi ESE), and Site 24: Recreation Lake (5.5 mi N). The 2 control location for liquid effluent comparisons is at Site 22: q Carlisle/Neal Shoals (24.0/30.0 mi NNW on the Broad River). (31)

s s r .a aav -n I 4 VIRGIL C. SUMMER NUCLEAR STATION i RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT f 2.6 Operational Radiological Monitoring Results i The preoperational radiological monitoring for the VCSNS was conducted from November,1977 until plant start-up in October, 1982. The baseline data obtained f rom the preoperational program are summarized in Appendix A-1. The operating period for VCSNS covered in this report spans I the 1983 calendar year (January 1 - December 31, 1983). Table 2-5 summarizes the results of the Radiological Environmental Monitoring i Program for the 1983 period of VCSNS operation. Values given for baseline ranges are finalized values taken f rom baseline data (see Appendix A-1). 2.7 Program Exceptions certain samples and analyses were inadvertently omitted ora unavoidably lost or altered during the 1983 operational period. These exceptions are delineated in accordance with Technical Specification requirements and the reason for the omissions noted ( below and summarized by week and site in Table 2-6. Taking these program exceptions into account, the Virgil C. Summer Radiological 1 Environmental Surveillance Laboratory was still able to attain a j completion rate of greater than 984. Detailed analysis of.the impact of these omissions verified that program quality has not L been affected and there were no violations of Technical Specification requirements. l., Air Particulates Seventeen (17) of the 728 air particulate samples taken l during 1983 did not result in successful analyses. I a. Power outages and other equipment failures were the l causes of ten air particulate omissions due to an { insufficient volume of air passing through each ]

filter, b.

Wet or washed out particulates were'the cause of three l additional-omissions from the program. The affected j . air samplers have been modified to preclude this i difficulty in the future, i c. One sample was omitted due to planned relocation of the j air sampler (see Section 2.4). f d. Personnel error resulted in the loss of one sample and i l the invalidation of two additional related samples. (32) l

- _ ~ ~.. _ _.. _, - -,. ~... -., TArr 5 ^ RADI(R.0GICAL ENVIR3 MENTAL MONITIEtING PROGRAM SupeWtY Virgil C. Sasemer Nuclear Station Omeket No. 50-395 Fairfield County, South Caroline Reporting Period: 1/1/83 - 12/31/83' i Type and Louer Limit Number of i Medium or Pethuey Total Number of All Indicator Locatione Location with Hident Annuel Mean Control Lacetione .Noncoutine Seapled of Analysee Detection [1] Mean [2] Name Mean(2) Mean[2] Reported [3] (latit of Measurement) Performed Actuel(Mar.] (Rence) (Dietence and Direction] (Ra,.) (Re ) Measuremonte I Air Partp) ~ late Groes Bete 0.0035 0.026 (560/560) Site #13, North Dem 0.027 (52/52) 0.026 (151/151) 0 (pci/m (711) (0.01) . (0.011 - 0.053) (2.9 mi. NpW) (0.014-0.049) (0.0050 0.060) Gemme W (168) Be-7 0.15 0.14 (48/132) Site #10, Met Tomer #2 0.23 (4/12) 0.14 (13/36) O (0.067-0.52) (2.5 mi. NNE) (0.10-0.52) (0.077-0.22) I Co-134 0.0025 All < LLD i All < LLD 0 ) (0.05) i Co-137 0.0022 All < LLD All < LLD 0 (0.06) ~ m us %h \\ ~ AirRedigiodine 1-131 (354] 0.039' All < LLD(4) All < LLD 0 (pci/m ) (0.07) i k Direct (TLD) Gemme (264) 0.52[5] 9.1 (168/168) Site #9, Bell Park 13.0 (12/12) 10.7(96/96) O (edhr) Monthly (7.2 - 13.0) (2.2 mi. NE) (12.0 - 13.3) (7.1 - 13.0) i T Gemme (108) 0.52[5] .9.f,(108/108) Site #55, Ot. Barneben 13.7 (4/4) 0 ) Quarterly (6.0 - 13.7) Church (2.8 01 E) (12.7-14.5) / 4 i j Surface Water M-3 (90) 520 390 (57/64) Site #25, Fairfield 470 (12/13) All < LLD 0 (pC1/1) (2000) (12-890) Pumped Storage (130-860) l (0.9 mi. WNW) l f Gemme some(90) l j t sei-54 0.19(15) All < LLD All < LLD 0 t ) i Page ] of 9 ~

TABLE 2-5 (continued) RADIOLOGICAL ENVIROP# ENTAL MONITORING PROGRAM StMMARY Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Caroline Reporting Period: 1/1/83 - 12/31/83 Type and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nontoutine Sampled of Analyses Detection [1] Mean [2] Name Mean[2] Mean[2] Reported [3] (tmit of Measurement) Performed Actual (Max.] (Range) (Distance and Directhon) (Rancs) (Range) Measurements Surface Water Co-58 0.22(15) 0.36 (3/64) Site #21, Parr Reservoir 0.43 (1/13) All < LLD 0 (pCi/1) (0.31-0.43) (2.7 mi. SSW) (Single Value) (Continued) Fe-59 5.1 (30) All < LLD All < LLD 0 Co-60 0.18(15) All < LLD All < LLD 0 2n-65 0.44(30) All < LLD All < LLD 0 Ob Zr-95 0.56(30) All < LLD All < LtD 0 Nb-95 0.49(15) All < LLD All < LLD 0 Cs-134 0.20(15) All < LLD All < LLD 0 Cs-137 0.19(18) All < LLD All < LlD 0 Be-140 2.4(60) All < LLD All < LLD 0 La-140 0.76(15) All < LLD All < LID 0 Ra-226 81 19 (12/64) Site f 25, Fairfield 27 (2/13) 19 (3/26) 0 (1.4-50) Pumped Storage (25-29) (4.7-34) (0.9 mi. WNW) Page 2 of 9

TABLE 2-ontinued) RADIOLOGICAL ENVIROP# ENTAL MONITORING PROGRAM SIMMARY Virgil C. Summer Nuclear Station Docket No. 50-395 rairfield County, South Carolina Reporting Period: 1/1/83 - 12/31/83 4 Type and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nooroutine Sampled of Analyses Detection [1] Mean [2] Name Nan [2] Mean[2] Reported [3] (thit of Measurement) Performed Actual (Max. ) (Rance) (Distance and Direction) (Rance) (Range) Measurements Ground Water [6] H-3(19) 530 (2000) All < LLD All < LLD 0 (pC1/1) Camma Spee(191 Mn-54 2.3 (15) All < LLD All < LLD 0 Co-58 2.3(15) All < LLD All < LLD 0 re-59 4.5(30) All < LLD All < LLD 0 C w ~ Co-60 2.3(15) All < LLD All < LtD 0 Zn-65 5.6(30) All < LLD All < LtD 0 Zr-95 4.2(30) All < LLD All < LLD 0 Nb-95 3.0(15) All < LLD All < LtD 0 Cs-134 3.7(15) All < LLD All < LLD 0 Cs 137 2.6(18) All < LLD All < LLD 0 Ba-140 13.3(60) All < LLD All < LLD 0 La-140 3.6(15) All < LLD All < LLD 0 f I I I I l ? Page 3 of 9 ~

~.. _ -.. ~. -. _ - -. - _ _. . ~... -. - -. - TABLE 2-5 (continued) i RADIOLOGICAL ENVIRO > MENTAL MONITIRING PROGRAM StMMARY 4 Virgil C. Summer Nuclear Station Docket No. 50-395 - Fairfield County, South Caroline Reporting Period: 1/1/83 - 12/31/83 ' Type and Lower Lielt Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean control Locations Noncoutine i Sampled of Analyses - Detection [1] Mean [2] Name Mean[2] Mean[2] Reported [3] (thit of Measurement) Performed Actual (Mex ] (Range) (Dietence and Direction) (Range) (Rence) Measuremento Ground Water [6] Ra-226 80 31 (3/9) Site #26, Onsite Well 31 (3/9) 14 (2/10) 0 ' (PC1/2) (Continued) (13-56) (P4)(265 ft. W) (13-56) (12-15) Drinking Water [7,8] Gross Bete 0.96 (4) 8.5(30/30) Site #28, Nuclear Train-15(15/15) 0 (pci/1) (30) '(1.3-27) ing Center (2.4 mi. (9.9-27) SSE) .H-3 (30) 630 (2000). All < LLD 0 ?C: ! 3' Gamme Spec (27: j Mn 54 0.16 (15) All < LLD 0 1 ~ Co-58 0.18 (15) 0.30(1/27) Site #17, Columbia 0.30(1/14) O 4 (Single Value) Waterworks (24.7 mi SE) (Sincle Value} re-59 8.1 (30) All < LLD 0 i ~ Co-60 0.16 (15) All < LLD 0 3 Zn-65 0.39 (30) All < LLD o 1 i Zr-95 0.46 (30) All < LLD 0 ~Nb-95 0.37 (15) All.< LLD o 1 i l' age 4 o f 9 l i i s i m.

i TABLE 2 5 (continued) RADIOLOGICAL ENVIRONMENTAL MONITGtING PROGRAM SlMMARY virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/83 - 12/31/83 i Type and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analyses Detection [1] Mean [2] Name Mean[2] Mean[2] Reported [3] (Unit of Measurement) Performed Actual (Max) (Range) (Distance and Direction) (Range) (Rance) Measuremente Drinking Water [7,8] (pci/1) (Continued) I-131 0.56 (1) All < LLD 0 Cs-134 0.19 (15) All < LLD 0 Cs-137 0.17 (18) All < LLD 0 Ba-140 1.2 (60) All < LtD 0 La-140 0.40 (15) All < LLD 0 C d Ra-226 160 20 (2/27) Site #17 Columbia Water-20 (2/14) 0 (5.8-34) works (24.7 mi SE) (5.8-34) Milk Camma Spec (56) (pCi/1) K-40 91 1430 (28/28) Site #14, Graham's Dairy 1430 (28/28) 1410 (28/28) 0 (1330 - 1560) (5.1 mi W) (1330-1560) (1280-1530) I-131 0.62 (1) All < LLD [9] All < LtD 0 Cs-134 2.9 (15) ~ll < LLD A All < LtD 0 Cs-137 2.9 (18) All < LtD 5.5 (28/28) 0 (2.4 - 8.3) Ba-140 11 (60) All.< LlD All < LLD 0 4 Pana 4 nf Q

TABLE 2, scontinued) RADIOLOGICAL ENVIR0tMENTAL MONITORING PROGRAM SlNMARY Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/1/83 - 12/31/83 Type and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine . Saapled of Analyses Detection [1] Mean [2] Name Mean[2] Mean[2] Reported [3] (thit of Measurement) Performed Actual (Max.) (Range) (Distance and Direction) (Range) (Range) Measurements Milk (pCi/1) (Continued) La-140 2.0 (15) All < LLD All < LLD 0 Grass (pC1/kg wet) Gamme Spee(241 Be-7 520 380 (13/16) Site #14, Graham's Dairy 460 (8/8) 650 (7/8) 0 (100-800) (5.1 mi W) (290-800) (280-1030) K-40 540 5890 (16/16) Site #14, Graham's Dair) 6200 (8/8) 6420 (8/8) 0 (4160-7900) (5.1 mi W) (4960-7900) ($180-8140) I-131 26 (60) All < LLD All < LLD 0 Cs-134 16 (60) All < LLD All < LLD 0 Cs-137 18 (80) 12 (1/16) Site #6, Garden 12 (1/8) 52(1/8) 0 (Single Value) (1.0 mi ESE) (Single valuel (Single Value) e Broadleaf Vegetation Gamma Spee(401 (pC1/kg wet) t, Re-7 140 230 (9/31) Site f6, Garden 340 (3/7) 200 (4/9) 0 (90-570) (1.0 mi ESE) (170-570) (87-300) K-40 470 4540 (31/31) Site #2, Transmission 5080 (6/6) 4490 (9/9) 0 (2650-7640) Line (1.2 al SW) (2980-7640) (2940-5670) I-131 22 (60) All < LLD All < LtD 0 Page 6 of 9

TABLE 2-5 (continued) RADIOLOGICAL ENVIR0l# ENTAL MONITGtING PROGRAN SlMMARY Virgil C. Summer Nuclear Station Docket No. 50-395 -Fairfield County, South Caroline Reporting Period: 1/1/83 - 12/31/83 Type and Lower Limit Medium or Pathmey Total Number of All Indicator Locatione Location with Highest Annuel Mean Control Locatione Noncoutine haber of Sampled of Analyses Detection [1] man [2} Name han[2] han[2] Reported [3] ' (thit of Measurement) Performed Actuel(Mex.] (Ranos) (Dietence and Direction) (R - ) (Rs ) Mesouremente Broadleer Vegetation Co-134 14 (60) All < LLD (pci/kg met) All < LLD 0 -(Continued) Cs-137 14 (80) 19 (3/31) Site #5, Trane. Line 22 (1/10) (14-22) Entrmee (0.9 mi SE) (Single Value: All < LLD 0 Other Vegetation Gamme Spee(10] (pC1/kg met) Be-7 150 All < LLD All < LLD 0 h K-40 310 2450 (8/8) Site #6, Garden 2620 (3/3) 3280 (2/2) 0 (1520-4270) (1.0 mi ESE). (2300-2980) (2320-4230) Cs-134 13 (60) All < LLD All < LLD 0 Cs-137 12 (80) All < LLD All < LtD 0 Fish (pC1/kg met). Gamme Spec (37] K-40 260 3150 (30/30) Site #21, Parr Reservois 3190 (10/10) 2640 (7/7) 0 (1910-4390) (2.7 mi SSW) (2400-4120) (1220-3630) Co-134 12 (130) All < LLD All < LLD 0 Cs-137 14 (150) 21 (19/30) Site #24, Rec. Lake 25 (6/10) 20 (4/7) 0 (8.4-48) (5.5 mi N) (12-48) (14-26) Co-58 19 (130). All < LLD f All < LLD D l Page 7.of 9

m.___.._.._....m. .m _ _ _ _. -. _ _. _ _. _ _. _.... - _. _ 4 4 TABLE 2-5 (continued) ~ RADIOLOGICAL ENVIROWNTAL MONITGtING PROGRAM SlMMARY. Virgil C. Semmer Nuclear Station Docket No. 50-395 - Fairfield County, South Caroline Reporting Period: 1/1/83 - 12/31/83 i Type and Leuer Limit lumber, of Medium er Pathuey . Total Number of All Indicator Locatione Location uith Highest Annuel Mean Control Locatione ' Nontoutine. Sampled of Analysee . Detection [1] Mean [2] Name Meen[2] Mean[2]. Reported [3] (Iceit of Measurement) Performed Actual (Mex.] (Rance) (Dietens e and Direction] (Renos) (Range) Measurseente } 1 { Flah '(pC1/kg met) Co-58 19 (130) All < LLD All < LLD 0 (Centinued) .M 13 (130) All < LLD All < LLD 0 4 Fe-59 61 (260) All < LLD All < LLD 0 {3 o 2n-65 30 (260) All < LLD All < LLD 0 i 4 j Co-60 13 (130) All < LLD All < LLD 0 i l sosteent [lo] ceae. some(12] i (pC1/kg) i K-40 480 14100 (9/9) Site #24, Recreation 24000 (3/3) 18000 (3/3) 0 1 (7240-38200) take (5.5 mi N) (14500 38200] (17700-18400) i Co-134 46 (150) All < LLD All < LLD 0 i Co-137 17 (180) 150 (4/9) Site #21,' Peer Reservoin 260 (3'/3) 190 (3/3) 0 ~ } (19-330) (2.7 mi SSW) (200-330) (185-200) i I r Page 8 of 9 1 I

________.__7__._.__. VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT i TABLE 2-5 (Continued) FOOTNOTES i 1. LLD values given are values calculated from the program data analyses with maximum acceptable 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. 4. One sample exceeded maximum LLD. The calculated LLD was 0.072 pCi/m, 3 5. Detection sensitivity is approximately 5 mrem /yr (0.52 uR/hr) determined from the i analyses of five years of preoperational data. i 6. Elevated levels of Pb-214 and Bi-214 were observed in the ground water sample taken at Site.ll8, Corley's well. The values are not reported here because they j are naturally occurring (do not originate from VCSNS) and furnish no quantifiaMe j information of interest. ( 7 No control location specified for drinking water. 8 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 t occurring (do not originate'from VCSNS) and furnish no quantifiable information of l interest. 9.- One sample exceeded maximum LLD. The calculated LLD was 1.0 6 pCi/1. i 10. Elevated levels of Pb-214, Bi-214 plus other Ra-226 daughter products and Ac-228 i plus other Th-232 daughter products were observed in all sediment samples. The i values _are not reported here because they are naturally occurring (do not i ) originate from VCSNS) and furnish no quantifiable information of interest. f-i a 4 Page 9 of 9 i i 1 i

VIRGIL C. SUMMER NUCLEAR STATION i RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 2-6 1983 ENVIRONMENTAL PROGRAM EXCEPTIONS (1) 4 Sample Type Week [2] Site [3] Reason [4] Air Particulate / 2 18 Planned sampler move Radioiodine ,18 16 Personnel error

26 5

Blown fuse 27 11 Blown fuse 29 10 Personnel error 30 10 Personnel error 32 4 Wet particulate

32 5

Blown fuse { 33 4 Power disconnected 34 15 Blown fuse t34 2 Personnel error t35 10 Personnel error

35 17 Damaged transformer
38 16 Blown fuse

]

38 17 Blown fuse
41 5

Tranformer problems

43 5

Blown fuse t45 5 Switch failure 50 4 Washed out particulate 52 8 Washed out particulate Direct (TLD) [5] 5 70 Buoy broke loose 48 17 Destroyed by construction 52 17 Vandalism Surface Water [6] 6 22 Clogged tubing (grab) 9 23 Over required period (4 days) 15 22 Clogged tbbing (grab) 45 17 Missing week in composite

- 1 22 Sand in pump head (grab)

Ground Water 52 16 Pump frozen [7] l Drinking ~ Water [6] 28 17 Personnel error (grab) 45 17 Missing week in composite Broadleaf Vegetation 21 2 Late spring freeze l 21 5 Late spring freeze 21 6 Late spring freeze l 21 8 Late spring freeze 21 18 Late spring freeze 34 2 Garden sprayed with herbicide 38 2 Garden sprayed with herbicide 42 2 Garden sprayed with herbicide 43 6 Insect damage Fish 16 22 Shad not available j 42 22 Bass not available (42) s i .n,.

i I VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT ] TABLE 2-6 (Continued) i FOOTNOTES 4 Both air particulate and radioiodine. t - Air radiciodine only. Week 1 of 1984 l [1] Sample has been omitted unless otherwise specified. [2] Week in which sample was picked up (ending week for composite samples). [3] See Table 2-2 for site locations, j [4] See text of Section 2-7 for more explanation. j [5] Data available, but suspect. [6] Replacement sample (grab) or incomplete composite sample taken. [7] Replacement taken at nearest available well, about 250 yards south i of required location. 3 4 i I 1 4 1 1 a l-i Y i 4 i l (43) 4

.-.. ~. ~. ~ _ - - .~ a VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 4

2. _ Air Radioiodine Analysis of ten (10) of the 364 air radiciodine charcoal cartridge samples for 1983 was not completed.

a. Eight of the omitted air radiciodine samples related to power outages and equipment f ailures. b. Personnel error resulted in the loss of two additional samples. 3. Direct (TLD) Three (3) of the 504 TLD sticks (four TLD's each) had adversely affected TLD's during 1983. i' The January TLD readings for Site #70 were a. j accumulated at uncertain and variable locations due i to buoy anchor failure. l j b. The November TLD stick at Site #17 (Columbia Water Works) was knocked over by construction workers. 4 1 i c. The December TLD stick at Site #17 was vandalized and { one TLD was missing. i 4. Surface Water l All 90 surface water samples were taken during 1993, l although grab samples were used to replace composite samples in several instances. l a. Equipment failures and power outages'resulted in collection of three grab, rather than composite i

samples, i

b.- Technician illness resulted in exceeding the 35 day j maximum by 4 days for one sampling period, ~ c. The water level at Columbia Canal was very low the week of 10/20-10/27/83, necessitating the shut down of the composite. water pump. Thus one week of one water sample was omitted, i 5. Ground Water One sample was not taken at the designated well due to a j f rozen pump. A replacement sample was taken at the nearest well in that. area. I (44) i 4 -..r, e -._~._....v ..c.. ,.w.... .. ~.,,,,. - .mr.-, - +.

d i VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT A 6. Drinking Water Two variances, _one caused by personnel error (inadvertant reversal of tygon pump lines) and one due to low water (see 4c above) were experienced in 1983. lD I 7. Broadleaf vegetation i No samples were taken between January and March, 1983 as this is outside the normal growing season for this area of South Carolina. Crop damage due to insects, transmission line herbicide application, and a late j spring freeze resulted in the unavailability of nine scheduled samples. The media were re-established at all } locations as soon as practicable. I 8. Fish Quarterly sampling via electrofisher and nets did not j provide two required samples. It is to be expected that certain species may not be available during all sampling periods. 3.0 INTERPRETATIONS AND CONCLUSIONS OF MONITORING FINDINGS 3.1 Airborne { 3.1.1 Air Farticulates j The gross beta results for air particulates col-lected at indicator locations during the 1983 operational L period of the Virgil C. Summer Nuclear Station were below j preoperational levels and comparable to operational con-trol levels. These results can be summarized as follows: Average Gross Beta Air Particulate Concentrations (pCi/m3) Indicator Locations Control Locations 1983 1983 Preoperational Operational Preoperational Operational 4

2.9E-02 2.6E-02
3.0E-02 2.6E-02 f

(7.5E-02 with Chinese bomb (8 lE-02 with Chinese bomb l fallout) f allout ) l

Determined f rom September,1981 through October,198 2.

This period is more indicative of actual background conditions; the fallout from the Chinese bomb test observed early in 1981 l had become insignificant by September 1981. (45) I

VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT The preoperational-operational comparisons between individual indicator sites have similar relationships as those illustrat9d in the overall comparison above. The highest indicator sctivity during the 1983 operational period was found at bite #13, North Dam on Monticello 3 Reservoir (2.9 mi NNW) with 2.7E-02 pCi/m. The highest control location activity during the same period was f ound to be 2.7E-02 pCi/m3 at Site #16, McGinnis' Dairy (28.0 mi W). 1 Due to.the above observations, it is concluded that Virgil C. Summer Nuclear Station's operation has not resulted in increases of particulate beta activity in the environment. The monthly composite gamma spectroscopy analyses for the air particulate samples revealed only naturally occurring background activities: .Be-7 (f rom cosmic-ray production) and Ra-226 and K-4 0 (at essentially room background levels). No fission or activation products were observed. These observations are expected based on a comparison of environmental data with plant effluent release data reported in the 1983 Semiannual Ef fluent and Waste Disposal Reports for Virgil C. Summer Nuclear Station. The latter reports show releases of 26.9 uCi of particulate activity for the year 1983. Due to large dilution and dispersion f actors experienced in 1983 for atmospheric releases, the releases from VCSNS should not be detectable in environmental samples, as the data has i substantiated. 3.1.2 Air-Radioiodine None of the analyses showed measurable radiciodine. I The required maximum LLD of 7.0E-02 pCi/m3 was met by all but one of the 252 indicator and 101 control measurements. The Site #6 (1.0 mi ESE) charcoal filter collected 12/23 - 12/30/83 showed an LLD of 7.2 E-02 pCi/m3 4 due to low sample volume. Total I-131 releases in plant. effluents were limited to 20.5 uCi for 1983. This level of activity release is not discernable in environmental media j. upon applying 1983 dispersion / dilution factors. 3.1.3 Direct (Environmental TLD) The exposure rates observed from all environmental. TLD measurements during~1983 were the same (at the 9 9.5 percent confidence level) as-the preoperational TLD measurements.over the'same. seasonal time periods. . (~4 6 ) 1 ,+ v .~

l l l l VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Indicator and control TLD measurements showed no appreciable differences during plant operation. Site (5 5, St. Barnabas Church near Jenkinsville (2.8 mi E), was the indicator location showing the highest mean exposure rate of 13.7 uR/hr. This is comparable to the mean exposure rate of 13.6 uR/hr measured during the preoperational period. Gaseous ef fluent release data from the 1983 Semiannual Ef fluent and Waste Disposal Reports indicate a total of 388 Ci of measurnable gaseous effluents were released from Virgil C. Summer Nuclear Station during 1983. The main portion of this activity (380 Ci) was released in the first quarter when the contents of the j waste gas holdup tanks were released. An extensive search of environmental TLD data and meteorological data during these concentrated release periods, indicates n~o evidence

i of detection of the activity from the releases.

No effects of radiation released from the plant were discernable f rom observed natural background variations using this monitoring medium. 3.2 Waterborne 3.2.1 Surface Water-Tritium analyses of surf ace water samples during the 1983 operation of Virgil C. Summer Nuclear Station yielded the following results: 1. Total number of analyses performed - 90 1 2. Total number of analyses with measurable (>0) results - 80 3. Total. number of analyses with results above (mean) LLD - 15 l 4. Mean LLD - 520 pCi/l 5. Mean indicator value (57/64 samples) - 390 pCi/l 6. Mean control value (23/26 samples) - 220 pCi/l i The Laverage measured tritium results for both indicator ] and control sites are less than the mean calculated LLD. Only 15 of the 90 analyses exceeded the mean LLD, all of which were greater than 1000 pCi/l below'the maximum LLD. All values were comparable to preoperational values for the same location and to typical surface water tritium levels-for the Southeastern l United States '(eg. see CRC Handbook of Environmental Radiation). No releases from the plant were identifiable above l .the natural background observed in this sample medium.- The l dilution of the tritium by the body of water in which it was L released and inherent error in low level tritium analysis.does l not allow the 227.4 Ci of tritium released by VCSNS in.1983 to -(47) '~

N VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT be observed in environmental samples. Gamma spectroscopy analyses of surf ace water during 1983 yielded _(with 3 notable exceptions) concentrations less than the lower limit of detection (LLD). The only radionuclides seen in these samples above background levels were Ra-226 (12 of 64 samples) which comes f rom natural sources and Co-58 (3 of 64 samples). The Co-58 (an activation product) was observed in the December, 1983 composite samples f rom Site #21, Parr Reservoir.(2.7 mi SSW) and duplicate samples from Site #17, Columbia Water Works (24.7 mi SE). The results were as follows: Sample Collection Volume 4 Site 4 Location Dates (liters) Co-58 (pCi/1) 17 Columbia 12/8/83-1/6/84 18.55

0. 31 + 0.11 17 Columbia 12/8/83-1/6/84 17.52 0.33 T 0.15

~ 4 (duplicate) 21 Part 12/7/83-1/5/84 20.98 0.43 1 0.12 Parr. Reservoir is about 2.5 miles downstream of the VCSNS major liquid effluent release point at the Fairfield Pumped Storage Facility Penstocks (see Page 1 and Figure 1-3). - Columbia Water Works is about 22 miles further downstream on the Broad River..The liquid effluent ^ releases of gamma 4 emitters from VCSNS for December, 1983 were 880 mci (82% of the total for the fourth quarter) of which Co-58 was the major nuclide released (660 mci in the fourth quarter and about 540 mci in December). Our conclusion is that the presence of Co-58 (a-relatively short-lived radionuclide - 70.78 day half-life) is attributable to releases of liquid effluents from Virgil C. Summer Nuclear Station. The levels of Co-58 observed are just above the Environmental Laboratory routine LLD (0.22 PCi/1) but much lower than the maximum LLD of 15 pCi/1.- The reporting level for Co-58 in water : samples is 1000 pCi/1, 3000 times higher than observed concentrations. The estimated dose -(using ODCM methodology) to a member of the public would be about 1.1 X 10-3 mrem /yr and 8.6 X 10-4 mrem /yr near Parr Reservoir and-Columbia Water Works, respectively, assuming the Co-5 8 remains in the water for an entire year at-the reported level. l l 3.2.2 Ground Water Tritium and gamma spectroscopy analyses of ground water samples all yielded results less than the mean calculated LLD E i 2 (48) --.wE,no. n ---,s ,-,-ame ,,m- .. ~ w e eg 4-7

VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT values. The control site #18, Corley's Well near Lake Murray (16.5 mi S) showed much higher than background levels of the Pb-214 and Bi-214 daughters of Ra-22 6. This was also seen in the preoperational data and is attributable to the large amount of granite found in this part of South Carolina. The granite contributes uranium and hence Ra-226 and its daughters to the wells in this area. The Pb-214 and Bi-214 are major gamma emitting daughters in this chain, produced through the decay of dissolved Radon gas ( Rn-22 2 ) in the water. No evidence of radioactivity from operation of the plant is present. 3.2.3 Drinking Water Indicator water samples taken f rom the Jenkinsville and Columbia drinki'ng water supplies showed no measurable activities (with one notable exception) for any of the 12 important gamma-emitting radionuclides monitored during the 1983 operation of VCSNS. Activities of Ra-226, Pb-214 and Bi-214 from the decay chain of naturally occuring U-238 were observed in the Jenkinsville water samples at levels significantly above background values. These elevated levels of uranium and uranium daughter product radionuclides were also observed in tha preoperational program and appear to be attributable to a series of deep water wells in local granitic aquiters. These levels are similar, but more elevated than, those observed in the ground water from Corley's well near Lake Murray (see Section 3.2.2). The only radionuclide found other than the naturally occurring uranium daughter products seen in the Jenkinsivile Water System was observed in the Columbia composite sample f rom December, 1983. An activity of 0.30 1 0.07 pCi/l of Co-58 was observed in 20.68 liters of potable water taken 12/8/83-1/6/84 from the Columbia Drinking Water supply. This minute concentration of Co-58 can be attributed to l VCSNS, having followed the same pathway as the Co-58 f ound l in surface water at the same location. This, as with the l surface water,-is expected from the activation products i released in liquid effluents during December (see Section 3.2.1). The expected dose to an individual member of the public is as in Section 3.2.1 above, on the order of 8.6 X 10-d mrem /yr assuming the Co-53 remains in the water for an entire year at this reported level. Gross beta activities showed a similar trend - normal low beta concentrations at Columbia (with a slight upward shift in December) and elevated beta concentrations at Jenkinsville. : This data is again comparable to that f ound (49) _ _ _ _ _ _ - _ _ _ - - - - - _ ~ _ - _ _., e w

J VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT during the VCSNS preoperational period and is attributable to the naturally occurring uranium associated with the aquifer supplying the Jenkinsville water system. Tritium analyses showed no concentrations in excess of the LLD. I 3.3 Ingestion 3.3.1 Milk Gamma spectroscopy results for milk samples taken during the 1982 operational period were found to be comparable to the results observed in the preoperational program. During the operating period, no I-131, Ba-14 0, La-140 or Cs-134 was measured at either the control or indicator location. No Cs-137 was found at the indicator site. Cs-137 was observed in all 27 milk samples taken at the control dairy - Site #16, McGinnis' Dairy (28.0 mi W) - 4 but the mean and highest activities of 5.5 pCi/l and 6.3 pCi/l respectively, were both below the required LLD of 18 pCi/l and are typical of concentrations expected from old bomb test fallout. K-40-and Ra-226 were found in the same concentrations expected from measurements performed during the preoperational period. No radionuclides attributable to the plant were observed as expected from the concentrations of gaseous effluents released from VCSNS during 1983. 3.3.2 Grass (Forage) Grass samples were taken during the approximate season cows are expected on pasture ( April through October). Gamma spectroscopy analyses of these samples showed the presence of Be-7, K-40 and in one case Cs-137. No I-131 or Cs-134 i-were. observed. The naturally-occurring Be-7 and K-40 had comparable activity levels as those found in both preoperational and 1983 control data. The single observation of Cs-137 at 12 pCi/l (lower ' than both the actual and maximum LLD values) can be attributed to the-residual ef fects of old bomb f allout '(i.e. see the preoperational data on the last Chinese bomb test late in 1980). There is no indication of the presence of any-radionuclide in grass.due to the operation of VCSNS which I again supports the. findings presented in the Semiannual Ef fluent and Waste Disposal Reports for gaseous effluent releases in 1983. lv (50)

VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 3.3.3 Food Products Broadleaf vegetation from gardens at sites 2,5,6,8 and 18 were the main food products sampled during the 1983 operation of Virgil C. Summer Nuclear Station. No I-131 or Cs-134 was measured at any of the garden sites. Cs-137 was observed in one sample at Site #2 (20 pCi/kg) and Site #5 (22 PCi/kg)..These values were just above the actual LLD determined-for this type of sample / geometry (14 pCi/kg) and considerably below the required LLD (80 pCi/kg). These Cs-137 results are also consistent with preoperational findings (five samples were found to contain observable Cs-137) and are typical of concentrations due to old ~ fallout. Background contributions f rom Ra-226, K-4 0, Ac-228 and Be-7 have also been measured in-the operational samples. l All values observed for the indicator sites (2,5,6,8) are comparable to the results found in the preoperational program and at the control site (18). Other vegetation sampled in 1983 included squash and i. radishes (non-leafy vegetation), tomatoes (f ruit and corn) (grain) f rom Environmental Laboratory Garden Site #6 (1.0 mi ESE) and control garden at the Wyse residence at Lake Murray, Site #18 (16.5 mi S of VCSNS). Only naturally-occurring K-40 was observed in these samples in concentrations above normal room background. The indicator i site K-40 concentrations were consistent with the concentrations observed in preoperational and 1983 control samples of the same or similar type. No Cs-134 or Cs-137 which might be attributable to gaseous effluents released from VCSNS were found in the indicator (Site #6) or control (Site #18) samples. r No radionuclides found in any of the food products can be attributed to the operation of the Virgil C. Summer Nuclear-Station. 3.3.4 Fish Four species of fish (bass,. bream, shad, and catfish and/or carp) were sampled at three indicator locations, Site

21 Parr Reservior, Site #23 Monticello Reservoir and Site
24 Recreation Lake and one control location, Site #22 Neal i

Shoals in the spring and fall of 1983. No measurable ~ concentrations of' fission or activation products with the exception of Cs-137 were seen in any fish species. Cs-137 was found in most fish samples (21/27) at levels (average 19 pCi/kg) just above the calculated LLD of 13 pCi/kg. The highest concentrations, as expected,-were found in the shad (forage fish) and their predators, ba ss. High levels of (51) i-l

r VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT naturally occurring K-40 were also found in all fish 1 samples. The findings for fish at indicator locations are similar to those found at the same sites during the preoperational period and at the Neal Shoals control site in 1983. No effect of the December liquid effluent release from VCSNS was observed (no samples were collected in 1983 after the release alluded to in Sections 3.2.1 and 3.2.3). No l radionuclides attributable to the operation of the plant were I

observed, i

3.4 Aquatic 3.4.1 Bottom Sediment Sediment samples were taken from the bottom of the four bodies of water from which fish are sampled - indicator Sites #21, 23 and 24 and Control Site #22. As with the fish samples, no measurable concentrations of any radionuclides typical of plant effluents with the exception of Cs-137, were observed. Cs-137 was found in 11 of the 12 sediments sampled at concentrations near the maximum LLD value of 180 pCi/kg. The highest concentration was observed in Parr Reservoir, 330 -pci/kg maximum and 260 pCi/kg average. These concentrations are consistent with preoperational and i control data and concentrations expected f rom old f allout. Very high' K-40 concentrations are also seen. These are due l to the concentrating of organic matter in the sediment by gravity and filtration. The K-40 activities are comparable to the values observed in preoperational and control data. As gith the fish, no ef fect of the December activation prepuct release was seen because-no samples were collected in>1983 after the release. No evidence of radioactivity from operation of the plant is present in sediment. i 4.0 GENERAL CONCLUSIONS i - Based on the -data presented in Tables 2-5 and. A-1 (Appendix A) and the interpretations and conclusions discussed in Sections 3.1 through 3.4 (above), only minute concentrations of Co-58 in the Broad River can be attributed to the operation of Virgil C. Summer Nuclear Station in 1983. The results of this monitoring effort-verify the results reported earlier in the Semiannual Ef fluent and Waste Disposal Reports (January - June and July - December 1983) for VCSNS. The findings of the Environmental. Monitoring Program substantiate the continuing adequacy of source l control at Virgil C. Summer Nuclear Station. l I l i l (52) !4 I J.

VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT l APPENDICES 1 1 4 l l i (53) -m

2 t APPENDIX A a '1he baseline data from the preoperational nonitoring program for the Virgil C. Simmer NL1 clear Station is stemrized in Table A-1 e i f. O i l~ (54) I o

T. A-1 RADIOLOGICAL ENVIR0fMENTAL MONITORING PROGRAM StMMARY PREOPERATIONAL (8ASELINE) REPORT Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Caroline Reporting Period: 1/2/81 - 10/22/82 Type and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analyses Detection [1] Mean [2] Name Mean[2] Mean[2] Reported [3] (Unit of Measureeent) Performed Actual (Max.) (Range) (Distance and Direction) (Range) (Rance) Measurements Air Particulate Gross Beta 0.0045 0.075 (1021/1038)[4] Site #13, North Dam 0.13(53/53) 0.081(282/285) 0 l 3 (PC1/m ) (1323) (0.01) (0.011 - 0.55) (2.9 mi NNW) (0.021 0.55) (0.005-0.61) 0.029(540/549)[4] Site #8, Mont. Res. S 0.032(57/58) 0.030(172/174) I (0.011-0.06) of Rd 224 (1.5 ENE) (0.012-0.06) (0.006-0.12) Gamma Spec (307) Be-7 0.18 0.13(106/241) Site #13, North Dam 0.25(10/22) 0.13(30/66) 0 (0.010-0.95) (2.9 mi NNW) (0.048-0.52) (0.051-0.35) i l Zr-95 0.008 0.06(57/241) Site #13, North Dam 0.07(5/22) 0.06(16/66) 0 (0.03-0.11) (2.9 mi NW) (0.03-0.12) (0.009-0.12) Nb-95 0.03 0.33(64/241) Site #13, North Dam 0.45(7/22) 0.37(19/66) 0 (0.10-0.17) (2.9 al NW) (0.12-0.77) (0.10 0.92) + Ru-103 0.007 0.04(35/241) Site #2, Transa. Line 0.05(3/22) 0.04(8/66) 0 l (0.01-0.08) (1.1 mi SW) (0.03-0.07) (0.02-0.09) Ru/Rh-106 0.004 0.03(6/241) Site #10, Meteorological 0.04(1/22) 0.02(1/66) 0 (0.02-0.04) Tower #2 (2.4 mi NNE) (Single Value) (Single Value) Cs-134 0.003 All < LLD All < LLD 0 (0.01) Cs-137 0.003 0.003(21/241) Site #13, North Dam 0.005 (2/22) 0.004(5/66) (0.01) (0.002-0.005) (2.9 mi NNW) (0.004-0.006) (0.002-0.006) 0 l' l I I I Page 1 ofil

TABLE A-1 dontinued) RADIOLOGICAL ENVIRONENTAL MONITORING PROGRAM SLMMARY PREOPERATIONAL (BASELINE) REPORT Virgil C. Summer Nuclear Station Docket No. 50-395 rairfield County, South Carolina Reporting Period: 6/26/81 - 10/22/82 (Air Radiolodine) 11/77 - 10/82 (TLD) 12/79 - 10/82 (Surface Water) Type and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analyses Detection [1] Mean [2] Name Mean[2] Hean[2] Reported [3] (Unit of Measurement) Performed Actual (Max.) (Range) (Distance and Direction) (Range) (Range) Measurements Air Particulate Ce-141 0.005 0.04(22/241) Site #10, Meteorologica] 0.06(1/22) 0.04(6/66) 0 3 (pC1/m ) (0.01-0.07) Tower #2 (2.4 mi NNE) (Single Value] (0.002-0.07) (Continued) Ce-144 0.004 0.04(68/241) Site #13, North Dam 0.04(7/22) 0.04(18/66) 0 (0.01-0.07) (2.9 mi NNW) (0.02-0.07) (0.01-0.07) y Air Radioiodine I-131(482) 0.045 All < LLD All < LLD 0 3 (pC1/m ) (0.07) Direct (TLD) Gamma (1238) 0.52[5] 9.8(915/915) Site #13, North Oam 13.9(60/60) 9.9(295/295) 0 (uR/hr) Monthly (6.7-14.8) (2.9 mi NNW) (12.5 14.8) (6.0-14.0) Gamme(154) 0.52[5] 9.9(154/154) Site #55, St. Barnabas 13.6(7/7) Quarterly (5.3-14.7) Church (2.8 mi E) (11.4-14.7) O Surface Water M-3 (71) 1140 All < LLD All < LLD 0 (pCi/1) (2000) Gamma Spec (219) Mn-54 0.3 (15) All < LLD All < LLD 0 Co-58 0.3 (15) All < LLD All < LLD 0 l i l l 1 1 I l Page 2 of 11

m__ -. _ ~ ~ ~ _ _ _ _. _ _ _ - = _ _ _. _. _.. _ _ _. ~... _.. _ _ _. ~ -_ 4 TABLE A-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SIMMARY PREOPERATIONAL (BASELINE) REPORT Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 12/79 - 10/82 (Surface Water) 1/80 - 10/82 (Ground Water) Type and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean . Control Locations Noncoutine Sampled .of Analyses _ Detection [1] Mean [2] Name Mean[2] Mean[2] Reported [3] .i (tmit of Measurement) Performed Actual (Max.) (Ranos) (Distance and Direction) (Range) (Range) Measur - to Surface Water-Fe -59 0.7 (30) All < LLD All < LLD 0 I (pCi/1). (Continued) Co-60 0.3 (15) All < LtD All < LLD D Zn-65 0.8 (30) All < LLD All < LLD 0 G Zr 95 0.9 (15) All < LLD All < LLD 0 22 Nb-95 0.7 (15) All < LLD All < LLD 0 Cs-134 0.2 (15) All < LLD All < LLD 0 1 Cs-137 0.2 (18) All < LLD All < LLD 0 ~ Be-140 2.6 (60) All < LLD All < LLD 0 1 La-140 0.9 (15) All < LLD All < LLD 0 4 Ground water - H-3 (52) 1170 All < LtD All < LLD 0 (pCi/1) (2000) l Page 3 of II J D + m

. ~. _ - -. _ _.. ~...- - TABLE A-1 (continued) RADIOLOGICAL ENVIRONENTAL MONITGtING PROGRAM SLMMARY PREOPERATIONAL (BASELINE) REPORT Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Caroline Reporting Period: 1/80 - 10/82 Type and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nontoutine Sampled of Analyses Detection [1] Mean [2] Name Mean[2] Mean[2] Reported [3] (thit of Measurement) Performed Actual (Mex. ] (Range) (Distance and Direction) (Range) (Range) Measurements camma Spec cround water (62) (pC1/1) (Continued) th-54 4 (15) All < LLD All < LtD. l 0 Co-58 4 (15) All < LLD All < LLD 0 i Fe-59 9 (30) All < LLD All < LLD 0 -G Co-60 3 (15) All < LLD All < LtD 0 I t 2n-65 9 (30) All < LLD All < LLD 0 4 Zr-95 5 (15) All < LLD. All < LLD 0 Nb-95 4 (15) All < LLD All < LLD 0 [ Cs-134 4 (15) All < LLD All < LLD 0 i Cs-137 4 (18) All < LLD All < LLD 0 so-140 20 (60) All < LLD All < LLD 0 t La-140 7 (15) All < LLD All < LtD 0 Page 4 of il l

TA8LE A-1 (Continued) RADIOLOGICAL ENVIROMtENTAL MONITORING PROGRAM SlHMARY PREOPERATIONAL (BASELINE) REPORT Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/80 - 10/82 Type and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations Location with Hlohest Annual Mean Control Locations Nonroutine Sampled of Analyses Detection [1] Hean [2] Name Mean[2] Hean[2] Reported [3] (thit of Measurement) Performed Actual (Max.) (Range) (Distance and Direction) (Range) (Range) Measurements Drinking Water [6] Gross Beta (80) 1.7(2.0) 10.3 (100/109) Site #28, Jenkinsville 16.9(55/55) 0 (pCi/1) (1.1 - 55.1) Diner (2.0 mi SE) [7] (2.7 - 55.1) H-3 (22) 950(1000) All < LLD 0 Gamma Spec (80) g th-54 0.3 (15) All < LLD 0 Co-58 0.3 (15) All < LLD 0 Fe-59 8.9 (30) All < LLD 0 Co-60 0.3 (15) All < LLD 0 Zn-65 0.9 (30) All < LLD 0 Zr-953 0.8 (15) All < LLD 0 Nb-95 0.7 (15) All < LLD 0 I-131[8] 1.0(1.0) All < LLD 0 Page 5 of 11

.___._.-____.m_ _ _ _. _ _ _ _ _.. _.. _ _. _. _ _...- m.__ -- _ _., _ ___ TABLE A-1 s untinued) i RADIOLOGICAL ENVIROWENTAL MONITGtlNG PROGRAM StMMARY PRE (PERATIOhAL (8ASELINE) REPORT 4 Virgil C. Summer Nuclear Station Docket No. 50-395 2 Fairfield County, South Caroline ineporting Period: 1/80 - 10/82 (Drinking Water and Milk) Type and Lower Limit Number of. Medium or Pethmey Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Noncoutine j Sampled .of Analyses Detection [1] Mean [2] Nome Mean[2] Mean[2] Reportod[3] 't (thit of Mer-- - .t) Performed Actuel(Mex.] (Ranos) (Distance and Direction) (Range) (Rs.v.) Measurements 1 Drinking Water [6] Cs-134 0.2 (10) All < LLD 0 (pci/1), (Continied) Co 137 0.3 (18) All < LLD 0 i as-140 20 (60) All < LLD 0 i l La-140 2.4 (15) All < LLD l 0 3:o i~ Re-226 0.8 6.4(64/70) Site f28, Jenkinsville 7.3(27/35) 0 i (2.5-13) Diner (2.0 mi ESE) [7] (4.1-13) 1 j 55(10/10) Site #28, Jenkinsville 55(10/10) 0 -(28-84) Diner g2.0 mi ESE) [7] (28 84) j U-235 1.2 3.1(16/80) Site #28, Jenkinsville 3.1(16/45) 0 (2.1-4.5) Diner (2.0 mi ESE) [7] (2.1-4.5) L Milk Gamme Spec (pci/1) (144) r K-40 70 1372(72/72)' Site #14, Graham's Dairy 1372(72/72) 1393(72/72) 0 (233-1580) (5.1 mi W) (233-1580) (276-1590) I I-131 [8] 1.0(1.0) All < LLD All < LLD 0 ? i i Page 6 of il I

TABLE A-1 (Continued) RADIOLOGICAL ENVIROPOENTAL MONITGtING PROGRAM SLMMARY PREOPERATIONAL (BASELINE) REPORT Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 1/80 - 10/82 (Milk) 4/80 - 9/82 (Grass) Type and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analyses Detection [1] Mean [2] Name Mean[2] Mean[2] Reported [3] (thit of Measurement) Performed Actual (Max.] (Range) (Distance and Direction) (Range) (Range) Measurementa Milk Cs-134 1.0(15) All < LLD All < LLD 0 (pC1/1) (Continued) Cs-137 1.1(15) All < LLD 9.5(11/72) 0 (5.5-11.0) Ba-140 17 (60) All < LLD All < LLD 0 h La-140 3.2 (15) All < LLD All < LLD 0 .r 4 Grass (pCi/kg wet) Gamma Spec (84) 8e-7 290 1150 (42/53) Site #6, Env. Lab. Gar-1350(16/22) 1150(24/31) 0 (112-7070) den (1.0 mi ESE) (213-7070) (236-8350) K-40 750 6040(52/53) Site #14, Graham's Dairy 6500(29/30) 6780(29/31) 0 (1000 - 9540) (5.1 mi W) (3990-9540) (3290-11500) I-131 [8] 66(60) All < LLD All < LLD 0 Cs-134 27(60) All < LLD All < LlD 0 Cs-137 33(80) 39(13/53) Site #14, Graham's Dairy 59(5/30) 131(6/31) 0 (16-158) (5.1 al W) (16-158) (13-336) Page 7 of 11

.-.~. - ~. - - _--..- - TABLE A-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITGtlNG PROGRAN SlHMARY PREIPERATIONAL (8ASELINE) REPORT Virgil C. Stamer Nuclear Station Docket No. 50 395 fairfield County, South Carolina Reporting Period: 7/79 - 10/82 (Broadleaf Vegetation) 9/79 - 10/82 (Other Vegetation) Type and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analyses Detection [1] Mean [2] Name Mean[2] Mean[2] Reported [3] (Unit of Measurement) Performed Actual (Mex. ) (Renos) (Distance and Direction) (Range) (Rance) Measurements Broadleaf Vegetation Gamma Spee (pC1/kg wet) [10] (19) K-40 400 3800(15/15) Site f2, Trans. Line 4640(2/2) 6850(4/4) 0 (1780 - 5700) (1.2 mi SW) (3570-5700) (4180-9350) 1-131 [8] 35(60) All < LLD All < LLD 0 5 Co-134 19(80) All < LLD All < LLD 0 Cs-137 23(80) 31(2/15) Site f 2, Trans Line 31(2/2) 16(1/1) 0 (26.6-36.2) (1.2 mi SW) (26.6-36.2) (Single Value) [ Other Vegetation Gamma Spec (pC1/kg wet) (65) K-40 330 3140 (36/36) Site #6, Env. Lab. Gar-3140(36/36) 3600(29/29) 0 (1940 5430) den (1.0 mi ESE) (1940-5430) (2100-9750) Cs-134 11 (60) All < LLD All < LLD 0 Cs-137 13 (80) All < LLD 16(1/29) O E (Single Value) r Page 8 of II i 4

TA8LE A-1 (L..cinued) RADIOLOGICAL ENVIRONENTAL MONITGtING PROGRAM Slf4 MARY PREOPERAT10NAL (8ASELINE) REPORT Virgil C. Summer Nuclear Station Docket No. 50 395 Fairfield County, South Caroline. Reporting Period: 5/79 - 10/82 Type and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Noncoutine Sampled of Analyses Detection [l Mean [2] Name Mean[2] Mean[2] Reported [3] (tmit of Measurement) Performed Actual (Max.] (Range) (Distance and Direction] (Range) (Range) Measurements Fish (pCi/kg wet) [9] Gamma Spec (110) K-40 500 3410 (85/85) Site #24, Recreation 3410(27/27) 3650(25/25) 0 (20*)-7460) Lake (5.5 mi, N) (418 7460) (2450-6060) Cs-134 15(130) All < LLD All < LLD 0 8 Cs-137 25 (150) 29 (66/85) Site #24, Recreation 31 (20/27) 26 (21-25) 0 (9-101) Lake (5.5 mi N) (11-101) (10-79) Co-58 25 (130) All < LLD All < LLD 0 m-54 19 (130) All < LLD All < LLD 0-Fe-59 78 (260) All < LLD All < LLD 0 Zn-65 43 (260) All < LLD All < LLD 0 Co-60 18 (130) All < LLD All < LLD 0 Page 9 of II I

TABLE A-1 (Continued) RADI0 LOGICAL ENVIROPMENTAL MONIT(RING PROGRAM StHMARY PREOPERATIONAL (BASELINE) REPORT Virgil C. Summer Nuclear Station Docket No. 50-395 Fairfield County, South Carolina Reporting Period: 5/79 - 10/82 Type and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations location with Highest Annual Mean Control Locations Nontoutine Sampled of Analyses Detection [1] Hean [2] Name Mean[2] Mean[2] Reported [3: (Unit of Measurement) Performed Actual (Max.) (Range) (Distance and Direction) (Range) (Range) Measurements Sediment (pC1/kg) Gamma Spec (47) K-40 400 15900(32/35) Site #24, Recreation 18100(9/12) 15900(11/12) 0 (4450-89600) Lake (5.5 mi N) (12800-21600) (11100-20200) Cs-134 22(150) All < LLD All < LLD 0 5 b ~ Cs-137 25(180) 238(27/35) Site #23, Discharge 265(9/12) 365(12/12, 0 (12-1090) Canal (Mont. Res. ) (17-1090) (14-1010) (0.5 mi ESE) Page 10 of 11 \\

- ~_.. VIRGE C. SUPER MKLIRR :frNTION RADIOIOGICAL ENVIRC4ElffAL PONI'ITRI!G REPORT TAILE A-1 (Continued) FOOTNDPES 'I } i 1. LLD values given are values calculated from the program data analyses with maximm acceptable values allowed fran PRC guidelines given in parentheses. 2. Mean and range are based on detectable measurenents only. %e fractions of detectable measurements at specific locations are indicated in parentheses. 3. A Nonroutine Measurenent is any confirmed measured level of radioactivity in any environnental medium that exceeds ten times the control station value. 4. Se baseline values are high because of the fallout from the Chinese bomb test in 1980. h e second set of values reflects a better set of baseline numbers, essentially free of bomb test fallout. Wis latter set covers the period 9/4/81 - 10/22/82. 5. Detection sensitivity is approximately 5 mren/yr (0.52 uR/hr) determined frm the analyses of five years of

6.

preoperational data. .u 6. tb control location is specified for drinking water. 7. Bimodal distribution of values present; mean of 6.4 through first half of 1981 and after March,1982 and mean of 55 for a 10 month period beginning June,1981. These high Ra-226 values (also reflected in gross 1 - beta and U-235 measurements) appear to be due to high granite content in some wells added to the Jenkinsville water system during this period. Several individual determinations did not meet the required maxinum LID due to insufficient sanple volume 8. and/or delay in counting sanple after collection. 9. Detectable levels of natural U-235 were randomly found in sanples frm all fish sanpling locations.

10. Prior to the 1982 growing season there were only two gardens sanpled, one indicator, Site #6, Environnental Lab Garden, and one control, Site #18, Corley's Garden. In 1982 the control garden at Site #18 was moved down the street to Wyse's Garden (apprmimately the same distance and direction) and three additional indicator gardens were added (for broadleaf vegetation only) at Site #2, Transnission Line; Site #4 Fairfield Hydro; and Site #8, Penticello Reservoir South of Road 224. Penthly sanpling was begun on, broadleaf vegetation at Sites # 2, 4, 6 and 8 in Septenber,1982.

i Page 11 of 11

VIRGIL C. SUMMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT APPENDIX B The Virgil C. Summer Radiological Environmental Surveillance Laboratory (RESL) has participated in the EPA Laboratory Inter-comparison Program for the duration of the preoperational and operational periods of the Radiological Monitoring Program. .The RESL laboratory participation code for the intercomparison pro-gram is FL. The results of Environmental Laboratory analyses of EPA samples performed during the 1983 operational period of the Virgil C. Summer Nuclear Station are summarized in Table B-1. All results (with 3 exceptions, see table) show agreement with EPA values and are well within EPA control limits. (66)-

VIRGIL C. SlHMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 8-1 1983 RESULTS OF EPA INTERCOMPARISONS Cooperison Study EPA Control VCS Env. Lab. Dates _ Avg. of all (Measurement Unit) Date Nuclide Value Limite(I) Results Analyzed Contributors Individual Average Air filter 11/82 beta 59.2 8.7 75,76,70

73.7 1/27/83 66 (pCi/ filter)

Cs-137 27.0 8.7 33,30,31 31.7 1/28/83 30 3/83 beta 68 8.7 66,68,66 66.7 5/18/E.5 69 Cs-137 27 8.7 30,32,32 31.3 6/1-6/2/83 31 8/83 beta 36 8.7 44,43,41 42.7 11/4/83 35 Cs-137 15 8.7 19,17,17 17.7 8/31.9/1/83 19 Camma in Water 2/83 Cr-51 45 8.7 46,47,50 47.7 2/14.2/20/83 48 (pC1/ liter) Co-60 22 8.7 24,26,26 25.3 2/14-1/20/83 23 Zn-65 21 8.7 23,21,22 22.0 2/14-2/20/83 22 Ru-106 48 8.7 49,39,55 47.7 2/14-2/20/83 47 Cs-134 20 8.7 20,19,19 19.3 2/14-2/20/83 20 Cs-137 19 8.7 21,20,20 20.3 2/14-2/20/83 19 6/83 Cr-51 60 8.7 57,62,58 59.0 6/29-7/1/83 62 Co-60 13 8.7 15,14,14 14.3 6/29 7/1/83 14 Zn-65 36 8.7 39,33,41 39.7 6/29-7/1/83 37 Ru-106 40 8.7 48,45,45 46.0 6/29 7/1/83 40 Cs-134 47 8.7 46,46,42 45.0 6/29.7/1/83 44 Cs-137 26 8.7 28,27,29 28.0 6/ 29-7/1/83 28 10/83 Cr-51 51 8.7 50,59,54 54.3 10/21-10/22/83 48 'Co-60 19 8.7 22,18,20 20.0 10/21.10/22/83 19 Zn-65 40 8.7 40,40,42 40.7 10/21-10/22/83 40 Ru-106 52 8.7 51,55,54 53.3 10/21 10/22/83 48 Cs-134 15 8.7 15,14,14 14.3 10/21-10/22/83 15 Cs 137 22 8.7 23,24,21 22.7 10/21-10/22/83 22 Cross 8ets in Water 1/83 beta 31 8.7 26,22,24 24.0 2/12/83 32 (pC1/ liter) 5/83 beta 57 8.7 50,48,51 49.7 6/10/83 54 9/83 beta 9 8.7 8,9,8 8.3 11/11/83 10 Iodine in Water 4/83 I-131 27 10.4 29,30,30 29.7 4/5 4/7/83 26.5 (pCi/ liter) 8/83 1-131 14 10.4 15,11,14 13.3 8/15 8/17/83 14 12/83 I-131 20 10.4 21,18,21 20.0 12/21-12/27/83 20 (67)

~ VIRGIL C. StNMER NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE B-1 (continued) 1983 RESULTS OF EPA INTERCOMPARISONS Comparison Study EPA Control VCS Env. Lab. Dates Avg. of all (Measurement Unit) Date Nuclide Value Limitsd) Results Analyzed Contributors Individual Average Laboratory Blind 5/83 beta 149 12.4 132,140,122 +131.3 11/11/83 136 (pC1/11ter) Co-60 30 8.7 33,33,31 32.3 10/21/83 31 Cs-134 33 8.7 29,32,31 30.7 10/21/83 31 Cs-137 27 8.7 30,32,28 30.0 10/21/03 27 11/83 bets 63 8.7 52,50,52

51.3 12/14/83 58 Co-60 11 8.7 12,11,12 11.7 12/9-12/12/83 11 Cs 134 15 8.7 17,15,16 16.0 12/9 12/12/83 14 Cs-137 15 8.7 16,17,16 16.3 12/9-12/12/83 15 Radionuclides in Food 3/83 I-131 37 10.4 41,40,41 40.7 3/6-3/9/83 37.1 (pC1/kg)

Cs-137 31 8.7 37,36,37 36.7 3/6-3/9/83 32.9 <10,<12,<11 <11.0 3/6-3/9/83 0 Be-140 0 9adionuclides in Milk 2/83 I-131 55 10.4 57,58,58 57.7 3/4-3/8/83 54.5 (pCi/ liter) Ca 137 26 8.7 27,28,24 26.3 3/4 3/8/83 26.3 Be-140 0 <13,<19,<21 (17.7 3/4-3/8/83 0 6/83 1-131 30 10.4 30,32,31 31.0 6/21-6/25/83 30 Cs-137 47 8.7 49,47,46 47.3 6/21-6/25/83 47 10/83 I-131 40 10.4 42,40,44 42.0 11/8-11/11/83 41 Cs-137 33 8.7 36,35,37 36.0 11/8-11/11/83 34 Tritium in Water 4/83 H-3 3330 627 3260,3220,3150 3210 4/18-5/4/83 3298 (pCi/ liter) 6/83 H-3 1529 583 1460,1450,1330 1413 6/20/83 1552 B/83 H-3 1836 593 2050,2000,2090 2047 8/30/83 1864 10/83 H-3 1210 570 1200,1190,1340 1243 11/4-11/8/83 1226 eThese groes beta values, one air particulate (11/82) and two in water from Laboratory (Blind) Performance (5/83 and 11/83) are not within the EPA control limits. However, if the average of all contributors is considered, all three values are in agreement (using the EPA control limits). (68)

S. =4_.db.a... L44.. 4#-wJ a4JS,*J.4M sa$ ,J.-m d4 J s-43-> 44 -,43r.e.Ls.5.ed.AJ J 1.E&A4 u -6 u-.Apa '.4m4edma #_4m~&eh a41_a&- gi A.& ,.M .sa=- a-_g.s4,ag-,g ,,-,as,a.a a.ga_u.._w.wwaI i 4 s d 9 4 s 4 .f 1 e .f. a ? t 1 t T 4 1 l 4, a d s 1 4 I b i e 4 b l 1 J d d I E k, 4 4 6 i 2i I. i b 't i 4 1 i t fi i s i t i I i a f 1 t F i e 1 d i .i i 4 3-..t q, e,...-,--,..,,-m.-,. y y -- -17.m.,. .,-e..ww-

/T d2 &O u, wyr SOUTH CAROLINA ELECTRIC & GAS COMPA ~ 1 [L ,ost omce m cotuusia. sours c4=ocina momi e May 1, 1984 3 EU {3

o. w. oixos. ;a.

i vica ene. ion. NUCLEAR OpsnatioNS Mr. J. P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, N.W. Atlanta, GA 30303

Subject:

Virgil C. Summer *Nyclear Station Operating License /.P Docket No. 50/395 No. NPF-12 Radiological Environmental Monitoring Report

Dear Mr. O'Reilly:

Please find attached South Carolina Electric and Gas Company's (SCE&G) Radiological Environmental Monitoring Report as required by Regulatory Guide 4.8 and Sections 6.9.1.6 and 6.9.1.7 of the Virgil C. Summer Nuclear Station Technical Specifications. If there are any questions, please call us at your convenience. Very truly yours, O. Dixon, Jr. GMG/WRB/OWD/gj cc: V. C. Summer C. L. Ligon (NSRC) T. C. Nichols, Jr./O. W. Dixon, Jr. K. E. Nodland E. H. Crews, Jr. R. A. Stough E. C. Roberts G. Percival W. A. Williams, Jr. C. W. Hehl D. A. Nauman J. B. Knotts, Jr. Group Managers I& E Washington O. S. Bradham NPCF C. A. Price File D. A. Lavigne Mb tra,or.tce^' t I \\ h'W}}

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