Text

Radiological Environ Monitoring Rept for VC Summer Nuclear Station for Operating Period 920101-1231
	ML20056C320
Person / Time
Site:	Summer
Issue date:	12/31/1992
From:	Dinkins J, Riley T, Gabe Taylor; SOUTH CAROLINA ELECTRIC & GAS CO.
To:	Ebneter S; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
	RC-93-0116, RC-93-116, NUDOCS 9305180326
	Download: ML20056C320 (48)
	v • d • e

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South Carolina Dectric & Gas Company n nagm

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Virgil C. Sammer Nuclear Station. Nud ra H:nt oper;tions

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Aoflip"/30,51993 n . . ,

1 RIeYert'o:jRC93'Oll-6 Mr. S. D. Ebneter Regional Administrator U. S. Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, N.W.

Atlanta, GA 30323

Dear Mr. Ebneter:

Subject:

VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSING N0. NPF-12 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT (ANN 3400)

Enclosed is the South Carolina Electric & Gas Company (SCE&G) Annual Radiological Environmental Monitoring Report as required by Regulatory Guide 4.8 and Sections 6.9.1.6 and 6.9.1.7 of the Virgil C. Summer Nuclear Station Technical Specifications.

If there are any questions, please contact Mr. Michael J. Zaccone at (803) 345-4328.

Very truly yours, Gary ' ylo MJZ:smd Enclosure c: 0. W. Dixon Jr. (w/oEnclosure)

R. R. Mahan (w/o Enclosure)

R. J. White G. F. Wunder NRC Resident Inspector J. B. Knotts Jr.

ANI Library NSRC RTS (ANN 3400)

File (818.02-2) 170156 i

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9305180326 921231 gDR ADOCK 0500 5

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'g, Virgil C. Summer Environmental Surveillance Laboratory Jenkinsville, South Carolina RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT VIRGIL C. SUMMER NUCLEAR STATION FOR THE OPERATING PERIOD JANUARY 1,1992 - DECEMBER 31,1992 APRIL 1993

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. pm 3 UEZZE V. C. SUMMER NUCLEAR STATION SOUTH CAROLINA ELECTRIC AND GAS COMPANY Prepared by:

,, i u 4N Jerty Dinkins, Supervisor Radiological Analytical Services Reviewed by: Approved by:

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. aba,fw T. D. Riley, Asst. Staff W. R. Baehr, Manager Health Physicist Health Physics and Radwaste Services

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l Executive Summary

1. Results of the 1992 Land Use Census indicated no significant movement of critical receptors since the previous annual census, and no identified locations where a calculated dose exceeded limits specified in VCSNS Offsite Dose Calculation Manual, Section 1.2.4.2

2. There was no detection of radioactivity in environmental media attributed to gaseous effluent releases from VCSNS.

3. Activated corrosion products attributed to liquid effluent releases from VCSNS were detected in fish and sediment. Radiation dose to the general public attributed to this activity is a small fraction of the observed variation in natural background radiation. '

4. Detection of fission product activity in environmental media is attributed to liquid effluent releases from VCSNS and residual fallout from other sources.

Radiation dose to the general public attributed to this activity is a small fraction of the observed variation in natural background.

5. Results of the Radiological Environmental Monitoring Program substantiate the continuing adequacy of source control at VCSNS and conformance of station operation to 10 CFR 50, Appendix l design goals.

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TABLE OF CONTENTS Page introduction 3 Description of the Radiological Environmental Monitoring Program 2 Results and Discussion 5 ,

Conclusion 39 t

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(ii)

l LIST OF FIGURES i

FIGURE Page l 1 -1 Control Site Locations (50 mile radius around the Virgil C. Summer Nuclear Station) 10 l l

1-2 Radiological Monitoring Program Local Indicator j Sample Sites (5 mile radius around Virgil C.

Summer Nuclear Station) 11 ;

I 1-3 Radiological Monitoring Program Local Indicator '

Sample Sites (1 mile radius around Virgil C. Summer Nuclear Station) 12 l l

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LIST OF TABLES .

l i TABLE Page 1 Monitoring Methods for Critical Radiation Exposure 2 Pathways i i '

2 Results of the August 1992 Land Use Census 3 Verification 5

2a Critical Receptors in 1992 Based on OLER Projected 4 Source Terms l 3 Radiological Environmental Monitoring Program 6 Sampling Site Locations 3a Sample Site Locations by Region 9 4 Results of the 1992 EPA Intercomparison Program 13 5 Results of the 1992 Intercomparison Program 15 with VCSNS Count Room 6 Summary of the 1992 Intercomparison Program 16 ,

with SCDHEC 7 Results of the Environmental Dosimetry 17 Intercomparison Program with the NRC TLD Direct '

Radiation Monitoring Network 8 Radiological Environmental Monitoring 18 .

Program Specifications 9 Supplemental Radiological Environmental Monitoring 22 Program 10 Radiological Environmental Monitoring Program 23 Summary 11 Radiological Environmental Monitoring Program 29 1 Preoperational(Baseline) Summary l 12 Environmental Sampling Program Exceptions 35 !

13 1992 Activated Corrosion Product Activity in Sediment 39 -

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Introduction Virgil C. Summer Nudear Station (VCSNS) utilizes a pressurized water reactor rated at 2775 MWt (900 MWe gross). The station is located adjacent to the Monticello Reservoir near Jenkinsville, South Carolina and approximately 26 miles northwest of Columbia. VCSNS achieved initial criticality on October 22, 1982, reached 50% power December 12,1982 and 100% power June 10,1983 following steam generator feedwater modifications. VCSNS is currently operat-ing in its seventh fuel cycle.

VCSNS is operated in conjunction with the adjacent Fairfield Pumped Storage Facility (FPSF) which consists of eight reversible pump-turbine units of 60 MWe capacity each. During periods of off-peak power demand, base load generating capacity is used to pump water from Parr Reservoir to Monticello Reservoir. Monticello Reservoir has a surface area of approximately 6800 acres and lies about 150 feet above Parr Reservoir whose full pool area is approximately 4400 acres. The pump-turbine units operate in the generating mode to meet peak system loads while Monticello Reservoir also provides condenser cooling water for VCSNS. Cooling water intake and discharge structures are separated by a jetty to ensure adequate circulation within the reservoir.

VCSNS is located in Fairfield County which, along with Newberry County, makes up the principle area within a 10 mile radius of the plant. This area is mainly forest with only about 30% devoted to small farming activities principally producing small grains, feed crops and beef cattle. Significant portions of Lexington and Richland Counties are encompassed within the 20 mile radius m the plant and exhibit similar agricultural activities. Columbia, the state capital, is the only large city within the 50 mile radius of the plant. Small agricultural concerns are predominant, but make up less than 50% of the land area. The main industrial activity is concentrated around Columbia and is generally greater than 20 miles from VCSNS.

Liquid effluents from VCSNS are released into the Monticello/Parr Reservoirs at two discharge points: the Circulating Water Discharge Canal (CWDC) and the FPSF Penstocks. Un 3rocessed steam generator blowdown and non-nuclear drains are released to tle CWDC. Effluent from the liquid waste processing system and processed steam generator blowdown are released through the penstocks. Radioactive gaseous effluents from VCSNS are released from two main points: the Main Plant Vent and the Reactor Building Purge Exhaust, both considered to be ground level releases.

Radioactive liquid and gaseous releases from the facility and their poten-tial influence on the surrounding biota and man are the primary concern of the Radiological Environmental Monitoring Program at VCSNS. This report sum-marizes the results of the Radiological Environmental Monitoring Program 1992. Data trends, control / indicator and preoperational/

conducted operational data m tercomparisons and other data interpretations are presented.

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Description of the Radiological Environmental Monitoring Program The Radiological Environmental Monitoring Program is carried out in its entirety by South Carolina Electric and Gas Company. The program has been designed to meet the following general commitments:

1. To analyze selected samples in important anticipated pathways for the qualification and quantification of radio-nuclides released to the environment surrounding VCSNS. :

2. To establish correlations between levels of environmental radioactivity and radioactive effluents from VCSNS opera-tion.

The pr,ogram utilizes the concepts of control / indicator and preoperational/

operational intercomparisons in order to establish the adequacy of radioactivity source control and to realistically verify the assessment of environmental radioactivity levels and subsequent radiation dose to man.

Specific measurement, sampling and analysis methodology has been prograrnmatically developed to sens,itively monitor the pathways expected to represent the most significant source of radiation exposure to the public and the environment. Elements of the program monitor the impact of gaseous and liquid effluents released from VCSNS. Specific methods .used in monitoring the aathways of these effluents which may lead to radiation exposure of the public, aased on existing demography, are summarized in Table 1. Requirements of the Radiological Environmental Monitoring Program are specified in the VCSNS Offsite Dose Calculation Manual (ODCM).

Effluent Release Type Exposure Pathway Monitoring Media Gaseous immersion Dose and Thermoluminescent Dosimetry (TLD) other External Dose Area Monitoring, Air Sampling Vegetation (Ingestion) Vegetation and Food Crop Sampling, Air Sampling Milk (Ingestion) Milk Sampling, Vegetation Sampling, Grass (Forage) Sampling, Air Sampling Liquid Fish (Ingestion) Surface Water Sampling, Bottom Sediment Sampling, Fish Sampling Water & Shoreline TLD Area Monitoring,SurfaceWater Exposure (Ingestion and Sarr.pling, Shoreline and Bottom immersion) Sediment Sampling Drinking Water Ground Water Sampling, Drinking (Ingestion) Water Sampling Table 1 - Monitoring Methods for Critical Radiation Exposure Pathways 2

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. .- l Effluent dispersion characteristics, demography, hydrology, land use, I anticipcted source terms, and the critical paths specific to VCSNS have been !

considered in the selection of sample media, sampling and analysis l frequencies, sample locations and types of samples. These cnteria were used :

to establish both the preoperational and operational phases of the ;

Radiological Environmental Monitoring Program. A census of land use, 'l perhaps the most dynamic of the criteria,is performed within a 5 mile radius 1 of VCSNS to verify the adequacy of the program. The resuits of the land use l census performed in 1992 are included in Table 2. A verification of the !

critical receptor (maximum exposed individual) in each sector around VCSNS '

based on 1992 meteorological data, and VCSNS Operatino ' License ;

Environmental Report source terms is included in Table 2a. l Nearest Nearest N o'. N o.

Sector Residence Miles Garden Miles Cattle Milked Miles Goat Miiked Miles l

N E. Fuller (A) 4.0 E. Fuller (A) 4.0 J. Robinson 0 3.4 l

NNE crumblin 2.9 L Robin on 3.3 E. Robinson 0 3.3 l

NE Herndon 1.4 las. Robinson 3.0 stone 0 2.1 l

- ENE willingham 1.5 R. Martin (B) 1.6 R. Martin (B) 0 1.6 [

E soyner 1.1 Boyd 1.1 Boyd 0 1.8 f ESE w. Martin 1.1 w. Martin (s) 1.8 l

SE Pearson 1.4 Summer 1.5 ;

SSE crumpton 2.4 Shealy 2.7 'f 5 L.Yarborough 3.4 Eargle 3.9 H.Yarborough 0 3.7 _!

SSW Shuttr 3.3 Ariail 3.4 Miller 0 2.9 !

SW Nichols 3.3 Nichols 3.3 Miller 0 2.8 l WSW Hope 2.9 Davis 3.1 uvingston 0 1.9 l

W wm. smith 2.5 Wm. Smith 2.5 uvingston 0 2.2 Leitzey 0 4.7 l WNW weideman 4.2 Ringer 4.7 h t

NW Wright 3.9 cote 4.1 cole 0 4.1 ;

NNW J. March 2.9 March 3.0 March 0 3.0

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. A. Change in closest residence, f B. Change in maximally exposed individual (MEI). j Table 2 - Results of the August 1992 Land Use Census Verification !

s The most notable census items are: the nearest residences are located in the ESE and E sectors at 1.1 miles; the maximum exposed individual is ,

located in the ENE sector at 1.6. miles; there were no milting animals being !

milked within 5 miles of V. C. Summer Nuclear Station at the time of the l census; the Radiological Analytical Services environmental gardens are

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located ESE 1.0 miles and E 1.0 miles from the plant which represents the two highest locations for dose potential. All other gardens included in the Environmental Monitoring Program are located at local residences. The i garden location at E 1.0 males consistently has a higher calculated dose than ;

any other real receptor location and therefore is used as the controlling !

location for offsite dose calculations.

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, , 1975 METEOROLOGICAL DATA 1992 TMTEOROLOGICAL DATA SEC- DI CE NAME PATHWAY DOSE *

DOSE **

TOR ) X/Q D/Q RATE X/Q D/Q RATE mRemly mRemly N 3.4 J. Robinson Beef (B) 1.9E-07 8.9E-10 9.6E-02 2.7 E-07 7.1 E-10 8.1 E-02 N 4.1 E. Fuller

Res/ Gar 1.4E-07 6.2E-10 1.6E-01 1.9 E-07 4.7E-10 1.3E-01 NWE 3.0 Crumblin Res 3.2 E-07 1.5E-09 1.2 E-02 3.4E-07 9.8E-10 1.3E-02 l

NNE 3.4 1. Robinson

Res/ Gar 2.5 E-07 1.1 E-09 2.9E-01 2.6E-07 7.3E-10 2.0E-01 NNE 3.7 E. Robinson Beef (B) 2.5E-07 1.1 E-09 1.2 E-01 2.6E-07 7.3E-10 8.3E-02 NE 1.4 Herndon Res 6.5E-06 9.7E-09 2.4E-01 2.1 E-06 7.5E-09 7.9E-02 NE 2.1 Stone Res/ Beef 6.8E-07 3.6E-09 3.8E-01 1.0E-06 3.3E-09 3.7E-02 f NE 3.0 Jas. Robinson

Res/ Gar / Beef 3.2 E-07 1.6E-09 5.8E-01 4.8E-07 1.4E-09 5.3E-01 ENE 1.5 Willingham Res 1.2 E-06 6.8E-09 4.6E-02 1.7E-06 6.9E-09 6.4E-02 ENE 1.6 R. Martin ( A)* Res/ Gar / Beef 1.1 E-06 5.8E-09 2.1 E + 00 1.5E-06 5.9E-09 2.2E + 00 l

l E 1.1 J. Joyner Res 2.2E-06 1.2E-08 8.5E-02 3.0E-06 1.1 E-08 1.1 E-01 l

E 1.7 M.Boyd Beef 8.4E-07 4.2 E-09 (C) 1.1 E-06 3.7E-09 (C) ,

E 1.8 M.Boyd* Res/ Gar 7.4E-07 3.6E-09 1.4E + 00 1.0E-06 3.2E-09 1.2E + 00 ESE 1.1 W. Martin Jr.* Res/ Gar 2.2 E-06 8.4E-09 2.2 E + 00 2.0E-06 6.9E-09 1.9E + 00 SE 1.4 Pearson Res 1.9E-06 7.0E-09 7.2 E-02 7.3E-07 2.7E-09 2.8E-02 SE 1.5 Summer

Res/ Gar 1.6E-06 5.8E-09 1.6 E + 00 6.3 E-07 2.3 E-09 6.2E-01 .

SSE 2.4 Crumpton Res 3.8E-07 1.3E-09 1.4E-02 1.2 E-07 6.2E-10 4.6E-03 SSE 2.7 Sheaty* Res/ Gar 3.0E-07 1.0E-09 2.7E-01 9.8E-08 5.2 E-10 1.3 E-01 5 3.4 L. Yarborough Res 2.1 E-07 5.0E-10 7.8E-03 E.8E-08 4.8E-10 3.4E-03 ;

5 4.0 Eargle* Res/ Gar 1.7E-07 3.7E-10 1.1 E-01 6.6E-08 3.5E-10 9.1 E-02 5 3.8 H. Yarborough Beef (B) 1.8E-07 4.1 E-10 4.8E-02 6.6E-08 3.5E-10 3.7E-02 SSW 2.9 Miller Beef (B) 2.8E-07 1.0E-09 1.1 E-01 1.6E-07 1.1 E-09 1.2E-01 SSW 3.3 Shultz Res 2.1 E-07 7.0E-10 7.9E-03 1.2E-07 8.5E-10 4.7E-03 SSW 3.4 Ariail' Res/ Gar 2.0E-07 6.4E-10 1.7E-01 1.1 E-07 8.0E-10 2.0E-01 SW 2.8 Miller Beef 3.6E-07 1.5E-09 (D) 2.1 E-07 1.6E-09 (D)

SW 3.3 Miller

Res/ Gar 2.6E-07 1.0E-09 4.2 E-01 1.5E-07 1.1 E-09 4.4E-01 SW 3.3 Nichols Res/ Gar 2.6E-07 1.0E-09 2.7E-01 1.5E-07 1.1 E-09 2.8 E-01 WSW 1.9 Livingston* Beef (B) 6.4E-07 3.2 E-09 3.4E-01 2.9 E-07 2.5E-09 2.6E-01 WSW 2.9 Hope Res 2.6E-07 1.2E-09 9.9E-03 1.1 E-07 9.1 E-10 4.4E-03 WSW 3.1 Davis Res/ Gar 2.3 E-07 1.0E-09 2.6E-01 9.9E-08 7.8E-10 2.0E-01 ;

W 2.5 Wm. 5 mith Res/ Gar 2.5E-07 1.1 E-09 2.9E-01 1.5E-07 8.7E-10 2.2 E-01 W 2.2 Livingston Beef 3.2E-07 1.5E-09 (E) 2.0E-07 1.2 E-09 (E)

W 2.7 Livingston* Res/ Gar 2.2 E-07 9.2 E-10 3.9E-01 1.3 E-07 7.3E-10 3.1 E-01 WNW 4.2 Weideman Res 7.6E-08 2.9E-10 2.9E-03 4.4E-08 1.6E-10 1.7E-03 >

WNW 4.7 Ringer

Res/ Gar 6.1 E-08 2.3E-10 6.1 E-02 3.4 E-08 1.2 E-10 3.2E-02 NW 3.9 Wright Res 1.1 E-07 4.6E-10 4.2 E-03 7.3E-08 2.6E-10 2.7E-03 WW 4.1 Cole

Res/ Gar / Beef 9.6E-08 4.1 E-10 1.5E-01 6.6E-08 2.3E-10 8.5E-02 NNW 2.9 J. March Res 1.9E-07 1.1 E-09 7.4E-03 2.6E-07 7.9E-10 9.7E-03 NNW 3.0 March

Res/ Gar / Beef 1.8E-07 9.8 E-10 3.5E-01 2.4E-07 7.3E-10 2.7E-01

Denotes Controlling Receptor for the sector. (D) Dose rate calculations based on residence & garden at (A) Maximum ex posed individual for the site. 3.3 miles and beef cattle at 2.8 miles. (See South West (B) Residence assumed in calculations. sector at 3.3 miles for dose rate.)

(C) Dose rate calculations based on residence & (E) Dose rate calculations based on residence & garden garden at 1.8 miles and beef cattle at 1.7 miles. at 2.7 miles and beef cattle at 2.2 miles.(See West (See East sector at 1.8 miles for dose rate.) sector at 2.7 miles for dose rate.)

Hypothetical dose rate calculated using source l term from Operating License Environmental Report Table 5 t2.

Table 2a - Critical Receptors in 1992 .

Based on OLER Projected Source Terms 4

I In addition to preoperational/o aerational data intercomparisons, control /

indicator data intercomparisons are uti ized. This is done to assess the probability that any observed abnormal measurement of radioactivity concentration is due to ,

random or regional fluctuations rather than to a true increase in local environmental radioactivity concentration. Monitoring sites indicative of plant operating condi-tions are generally located within a 5 mile radius of the plant as shown in Table 3 '

and Figures 1-2 and 1-3. Monitoring sites at distances greater than 10 miles from the plant are shown in Figure 1-1. These locations indicate regional fluctuations in background radiation levels. Table 3a gives a summary of sample locations by !

j region. ,

. Environmental data is gathered through multiple types of sampling and measurements at specific locations. Several multiple sampling combinations are in use around the VC5NS. For example, all air sampling locations also serve as environ-mental dosimetry monitoring locations. At these points airborne plant effluents are !

monitored for gamma immersion dose (noble gases), airborne particulates and i radioiodine. Three of these locations have additional complementary sampling / -

i measurement pathways for monitoring plant effluents. Samp.ing locations 6 (1.0 mi ;

ESE) and 7 (1.0 mi E) have broadleaf vegetation gardens for monitoring the c aseous ;

effluent deposition and ingestion pathway in the two sectors having the lighest ;

deposition coefficients (D/Q) with real potential for exposure. Environmental

, garden at site #7 was implemented in 1992 and replaces the garden at site #8. .

Sampling location 18 (16.5 mi 5) serves as a control locatio 1 for direct radiation, ;

lJ surf ace water and garden monitoring.

Liquid effluents are monitored through three pathways (fish, bottom sediment and surface water) at the three most probable affected bodies of water ,

i around the plant: Site 21, Parr Reservoir (2.7 mi SSW); Site 23, Monticello Reservoir ;

1 (0.5 mi ESE); and Site 24, Recreation Lake (5.5 mi N). The control location for liquid :

1 effluent comparisons is at Site 22, Neal Shoals (30.0 mi NNW) on the Broad River. [

The Radiological Environmental Monitoring Program participated in four ;

laboratory intercomparison programs during 1992. Results of the 1992 EPA i Intercomparison Program are included in Table 4. Results of the intercomparison l program with the count room at VCSNS and an outside vendor are included in Table '

5. Results of an intercomparison program with South Carolina Department of i Health and Environmental Control (SCDHEC) outlined in Table 6 are reported by v SCDHEC. Results of an environmental dosimetry intercomparison with the NRC are included in Table 7. The results of each of these four quality control checks of the Radiological Environmental Monitoring Program verify the technical credibility of l analytical data generated and reported by the program.

The program, as it has evolved since the preoperational(baseline) monitoring program, incorporates all the elements of the VCSNS ODCM and additional special !

studies and is detailed in Tables 8 and 9.

Results and Discussion

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e l The results of the Radiological Environmental Monitoring Program for 1992

! are summarized in Table 10. For comparative purposes preoperational data is summarized in Table 11. In some cases, required samples were not collected during 1992 and therefore are not included in tne annual summary. A listing of these '

i program exceptions and their respective causes are included in Table 12. Despite the -

program exceptions, the Radiological Environmental Monitoring Program was able to attain a completion rate of 99% of required samples. Detailed analysis of the impact of these om,issions verified that program quality has not been afTected and there were no violations of ODCM requirements.

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Site Distance 1 Sample .

No. Description (Miles) Direction 2 Type (s)3 ;

1 Borrow Pit 1.2 182.0 5 DQ 2 Transmission Line 1.2 225.0 SW AP,RI,DQ 3 Firing Range 1.2 270.0 W DQ 4 Fairfield Hydro 1.2 289.5 WNW DQ 5 Transmission Line Entrance 0.9 145.5 SE AP,RI,DQ 6 Env. Lab Garden 1.0 104.0 ESE AP,RI.GR GA, DQ 7 Env. Lab Garden 1.0 96.0 E DQ, G A, G R 8 Monticello Res. 5 of Rd 224 1.5 63.0 ENE AP.DQ 9 Ball Park 2.2 44.0 NE DQ 10 Meteorological Tower No.2 2.5 25.5 NNE AP,RI,DQ 11 Residence 3.3 8.0 N DQ 12 Old Hwy 99 4.2 349.0 N DQ 13 North Dam 2.9 334.0 NNW AP.DQ 14 Dairy 6.5 277.0 W AP,RI,DQ,MK GR 15 Parr Village 2.5 204.0 SSW DQ 16 Dairy 20.0 275.0 W GW,M K,G R 16a Dairy (Kinard) 28.0 279.0 W DQ 17 Columbia Water Works 24.7 144.0 SE AP,RI,DQ,5W,DW,B5 18 Residence / Pine island Club 4 16.5 165.0 5 DQ,5W,GA 19 Residence /Little 5aluda 17.9 207.0 55W DQ 20 Residence /Whitmire 22.0 310.0 NW DQ 21 Parr Reservoir 2.7 199.5 SSW SW,FH,B5 22 NealShoals 30.0 343.0 NNW SW,FH,B5 23 Discharge Canal (Mont. Res.) 0.5 104.5 ESE SW,FH,B5 24 Recreation Lake 5.5 2.0 N SW,FH,B5 l 25 Fairfield Pumped Storage (Monticello Res.) 0.9 302.0 WNW SW 460 Ft 270.0 W GW 26 On Site Well(P2) f 27 On Site Well(PS) 510Ft 180.0 5 GW 28 Nuclear Training Center (EOF)5 2.4 168.0 SSE DW 29 Trans. Line WSW of VCSNS 0.9 248.0 WSW DQ I 30 Oak Tree North of Borrow Pit 1.0 197.0 55W DQ 31 McCrorey Liston 5chool 5.8 12.5 NNE DQ 32 Dirt Rd off Rd 205 4.5 25.0 NNE DQ t 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 l 35 Unnamed Circle Road off Hwy 215 4.8 137.5 SE DQ 36 Woods Behind jenk. Post Office 3.1 151.5 55E DQ f 37 Residence 4.9 305.5 NW DQ 38 FPSF Tailrace 1.3 280.0 W B5 39 LMWTF 14.0 168.0 55E DW Table 3 - Sampling Site Locations 6

Site Distance 1 Sample No. Description (Miles) Direction 2 Type (s)3 ,

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41 End of Catwalk 3.9 185.0 5 DQ 42 Store 3.9 199.0 55W DQ

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43 Hwy 176 and Rd 435 5.2 236.0 5W DQ

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44 Rd 28 at Cannon's Creek 2.9 255.5 WSW DQ 45 Rd 33 at Pomaria 5.9 253.0 WSW DQ 46 Rd 28 at Heller's Creek 3.7 292.0 WNW DQ 47 Fairfield Tailrace 1.0 316.0 NW DQ 48 Cemetery 2.3 318.5 NW DQ 49 North Rd 383 4.0 332.5 NNW DQ 50 New Rd 99 (West Shore) 5.5 1.0 N DQ 51 New Rd 99 (East Shore) 5.5 5.0 N DQ 52 Monticello (Rd 11) 3.9 14.0 NNE DQ 53 Rd 359 3.0 48.0 NE DQ 54 Jenkinsville School 1.7 73.0 ENE DQ 55 St. Barnabt Church 2.8 94.0 E DQ 56 O!d Jenkinsville Diner 2.0 144.0 SE DQ F/ Residence / Highway 213 and 215 2.7 146.0 SE DQ

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58 Residence 2.5 158.0 55E DQ l

59 Nuclear Training Center (EOF)5 2.4 168.0 SSE DQ,AP 60 Rd 98 near Rd 28 3.5 275.0 W DQ i 61 Switchyard, SE Entrance to Plant 0.1 180.05 DQ 62 South of AAP 0.13 220.0 SW DO 63 East of Craft Training 0.17 270.0 W DQ 64 W ofintake 0.13 338.5 NNW DQ,85 65 East of Intake 0.13 22.5 NNE DQ,B5 66 Jetty 0.6 33.0 NNE DQ 67 Service Water Pond (East Side) 0.5 72.0 ENE DQ 68 Fuel Oil 5torage Tank 0.2 108.5 ESE DQ 69 Exclusion Buoy NNW on Monticello Res. 1.0 337.0 NNW DQ 70 Exclusion Buoy N on Monticello Res. 1.0 0.0 N DQ 71 Temperature Buoy on Monticello Res. 5.4 3.0 N DQ 72 Yard Drain Outfall 0.4 146.0 SE SW,05 73 Yard Drain Outfall 0.4 270.0 W SW,B5 75 On Site Well 265 f t. 270.0 W GW ,

76 On Site Well 270 f t. 330.0 NNW GW 84 Congaree River 54.2 135.0 SE B5 85 Congaree River 53.8 135.0 SE B5 87 Lake Marion 72.0 138.0 SE B5 88 Lake Marion 72.0 138.0 SE B5 1

Table 3 - Sampling Site Locations (continued) 7 l

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FOOTNOTES l

1. Distance given is the distance between the site location and the center of the l VCSNS reactor containment building. l l

2. Direction given is direction in degrees from true north-south line through center of reactor containment building. ,

3. Sample Types:

AP = Air Particulate DW = Drinking Water RI = Air Radiciodine MK = Milk DQ = QuarterlyTLD GR = Grass (Forage) [

SW = Surface Water GA = Garden GW = Ground Water FH = Fish BS = Bottom Sediment ,

4. Site 18 consists of 3 locations in close proximity next to Lake Murray. Garden ;

product samples are taken at the Wyse residence. Surface water is taken ;

near the shoreline in Lake Murray. The TLD is located on Pine island. l t

5. Site 28 is drinking water and site 59 for quarterly TLD measurements and continuous air sampling are co-located at the location of the SCE8G Nuclear Training Center which also serves as the Virgil C. Summer Station Emergency i Offsite Facility.

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Table 3 - Sampling Site Locations (continued) 8 ;

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REGION SAMPLE SITE NO.

Summer Station 23,26,27,61,62,63,64,65,66,67,68, 69,70,72 and 73 Exclusion Area 8oundary 1,2,3,4,13,25,29,30 and 47 Monticello Reservoir 5,6,7,8,9,10,11,12,24,31,32,48, 49,50,51,52,53 and 71 ,

Southeast Quadrant 28,33,34,35,36,54,55,56,57,58 and 59 West Bank Parr Reservoir 14,15,21,37,41,42,43,44,45,46, and 60 Control Locations 16,17,18,19,20,22 and 39 Congaree River 84,85,87 and 88 i

SCE&G Co-located Sites !

1. Nuclear Regulatory Commission 12, 44,53,56, and 60.

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S CONTROL SAMPLE LOCATIONS
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4 4 Comparison Study EPA Value Laboratory Agree-(Measurement Unit) Date Nuclide ( 30) Results ( 10) ment Air filter (pCi/ filter) 3/92 beta 41(5) 40(1) Yes Cs-137 10(5) 13(1) Yes 8/92 beta 69(10) 83(4) Yes Cs-137 18(5) 22(1) Yes Gamma in Water (pCi/ liter) 2/92 Ba-133 76(8) 80(5) Yes Co-60 40(5) 41 (1) Yes Zn-65 148(15) 156(5) Yes Ru-106 203(20) 202(5) Yes Cs-134 31 (5) 30(1) Yes Cs-137 49(5) 52(1) Yes 6/92 Ba-133 98(10) 100(6) Yes Co-60 20(5) 21 (2) Yes Zn-65 99(10) 106(7) Yes Ru-106 141(14) 140(9) Yes Cs-134 15(5) 14(1) Yes Cs-137 15(5) 16(1) Yes 10/92 Ba-133 74(7) 79(3) Yes Co-60 10(5) 10(1) Yes Zn-65 148(15) 166(1) Not Ru-106 175(18) 178(10) Yes Cs-134 8 (5) 7 (1) Yes Cs-137 8 (5) 9 (1) Yes Gross Beta in Water (pCi/ liter) 1/92 beta 30(5) 25(1) Yes t investigations showed no apparent cause of the agreement problems. Subsequent intercomparison analysis have been in agreement.
Table 4 - Results of 1992 EPA Intercomparison Program 13
Comparison Study EPA Value Laboratory Agree-(Measurement Unit) Date Nuclide ( 30) Results( 10) ment Gross Beta in Water (pCi/ liter)(continued) 5/92 beta 44(5) 43(2) Yes 9/92
beta 50(5) 38 (11) Yes lodine in Water (pCi/ liter) 2/92 1-131 59(6) 60(1) Yes 8/92 1-131 45(6) 47(1) Yes ,
Laboratory Blind 4/92 alpha 40(10) 57 (2) No**
(pCi/ liter) >
beta 140(21) 106(7) No**
Co-60 56(5) 57 (1) Yes Cs-134 24(5) 24(1) Yes Cs-137 22(5) 23(3) Yes 10/92 alpha 29(7) 29(3) Yes beta 53 (10) 43(2) Yes Co-60 15(5) 15(0) Yes Cs-134 5 (5) 5 (0) Yes Cs-137 8 (5) 9 (0) Yes:
Radionuclides in Milk (pCi/ liter) 4/92 1-131 78(8) 86(1) Yes Cs-137 39(5) 44(1) Yes 9/92 1-131 100(10) 108(3) Yes [
Cs-137 15(5) 16(1) Yes Tritium in Water (pCi/ liter) 2/92 H-3 7904(790) 7944(384) Yes 6/92 H-3 2125(347) 2103 (128) Yes 10/92 H-3 5962(596) 5700(235) Yes
Lab results were not reported to the EPA. The analysis was performed after the EPA due date because of equipment problems.

the Alpha and Beta salt load correction factor was misapplied.
Table 4 (continued)- Results of 1992 EPA Intercornparison Program 14
. i Comptrissn Study Envir.Lcbsrs- 2nd tzb Agres-(Mscsurem;nt Unit) Dxte Nuclida tory Results Results(1) m :nt Tritium (pCi/ml) (Analytics) 2/92 H-3 1.39E-3 1.55E-3 Yes I (pCi/mt) (VCSNS) 12/92 H-3 (distilled) 1.25E-1 1.32 E-1 Yes (pCi/ml) (VCSNS) 12/92 H-3 (undistilled) 1.36E-1 1.38E-1 Yes Gross Beta Liquid (pCi/ml) 2/92 N/A 1.08E-3 1.22E-3 Yes i Gross Alpha Liquid (pCi/ml) 2/92 N/A 4.32E-4 4.94E-4 Yes ,
Gamma Isotopic Liquid 2/92 Ce-144 1.21 E-2 1.06E-2 Yes j (pCi/mi) 1 liter Marinelli Ce-141 6.33E-3 6.19E-3 Yes Cr-51 2.79E-2 2.60E-2 Yes Cs-134 3.32E-3 3.32E-3 Yes Cs-137 8.52E-3 7.89E-3 Yes Mn-54 5.18E-3 4.82 E-3 Yes Fe-59 1.23 E-2 1.12E-2 Yes Zn-65 1.01 E-2 8.61 E-3 Yes Co-60 6.20E-3 5.91 E-3 Yes Gamma Isotopic Liquid 2/92 Ce-144 1.03E-2 1.06E-2 Yes (pCi/ml) 100 ml Resin Vial Ce-141 5.95E-3 6.19E-3 Yes Cr-51 2.50E-2 2.60E-2 Yes -
Cs-134 3.09E-3 3.32E-3 Yes Cs-137 7.77E-3 7.89E-3 Yes Mn-54 4.74E-3 4.82E-3 Yes i fe-59 1.13 E-2 1.12 E-2 Yes .
Zn-65 9.06E-3 8.61 E-3 Yes ,
Co-60 5.64E-3 5.91 E-3 Yes i Gamma Isotopic Liquid 11/92 Ce-144 8.91 E-3 8.15E-3 Yes l (pCi/ml) 1 liter Marinelli Ce-141 1.42E-2 1.42 E-2 Yes
, Cr-51 2.17E-2 2.25E-2 Yes Cs-134 3.33E-3 3.48E-3 Yes Cs-137 8.66E-3 8.74E-3 Yes Co-58 4.54E-3 4.69E-3 Yes M n-54 4.66E-3 4.49E-3 Yes Fe-59 6.92E-3 6.60E-3 Yes t Zn-65 5.34E-3 4.85E-3 Yes l Co-60 9.15 E-3 9.42E-3 Yes Gross Beta Filter (pCi) 5/92 N/A 5.21 E-3 5.57E-3 Yes Gross Alpha Filter (pCi) 5/92 N/A 2.02 E-3 1.66E-3 Yes Gamma isotopic Filter (pCi) 5/92 Ce-144 3.92E-2 3.36E-2 Yes Ce-141 5.32E-2 4.68E-2 Yes i Cr-51 1.23E-1 1.10E-1 Yes
Cs-134 2.57E-2 2.77E-2 Yes i Cs-137 3.70E-2 3.22E-2 Yes Co-58 3.10E-2 2.73E-2 Yes Mn-54 1.71 E-2 1.44E-2 Yes Fe-59 4.33E-2 3.55E-2 Yes Zn-65 5.90E-2 4.84E-2 Yes l Co-60 3.48E-2 3.21 E-2 Yes Charcoal Canister (pCi) 8/92 1-131 1.98E-1 2.02E-1 Yes Silver Zeolite Canister (pCi) 11/92 1-131 2.85 E-1 2.52E-1 Yes Gas 5 ample (pCi) 8/92 Xe-133 7.05E + 0 7.03 + 0 Yes !
Kr-85 1.13E + 2 1.12 + 2 Yes Gamma isotopic 5olid 11/92 Ce-144 3.86E-2 3.41 E-2 Yes (pCi) 100 ml Resin Vial Ce-141 6.30E-2 5.95E-2 Yes i Cr-51 1.00E-1 9.40E-2 Yes Cs-134 1.54 E-2 1.45 E-2 Yes t Cs-137 3.88E-2 3.65E-2 Yes' Co-58 2.08E-2 1.96E-2 Yes Mn-54 2.06E-2 1.88E-2 Yes Fe-59 3.10E-2 2.76E-2 Yes ,
Zn-65 2.36E-2 2.03E-2 Yes Co-60 4.16E-2 3.93E-2 Yes I (1) Independent Laboratory was Analytics, Inc. except for some tritium intercomparisons.
(2) Manufacturer's specifications for initial setup of a new tritium analyzer resulted in a low bias ;
of ~30%. Adjustments have been made to eliminate this bias.
Table 5 - Results of 1992 Intercomparison Program with Independent Lab i
15
i Sample Pathway (Units) Location Frequency Nuclide1 Surface Water No. 21 Monthly 3H (pCi/ liter) Mixed Gamma No. 22 Monthly 3H Mixed Gamma Air (pCi/m3) No. 6 Monthly Gross Beta lodine Mixed Gamma i No.17 Monthly Gross Beta lodine -
Mixed Gamma Milk (pCi/ liter) No.14 Monthly Mixed Gamma Sediment (pCi/kg) No. 23 Semiannually Mixed Gamma Fish (pCi/kg) No. 23 Semiannually Mixed Gamma Vegetation (pCi/kg) No. 6 Semiannually Mixed Gamma
1. Intercomparison results were not yet available for publication in this report.
Results will be reported by SCDHEC.
Table 6 - Summary of 1992 Intercomparison Program with South Carolina Department of Health and Environmental Controls 3
16
i i I s I ,
i v
1991 FOURTH QUARTER 1992 FIRST QUARTER 1992 SECOND QUARTER 1992 THIRD QUARTER RESULT 5 (uRthr) RESULTS(uR/br) RESULTS (uR/hr) RESULTS (uR!hr)
Percent Percent Percent Percent i labo. Differ- Labo- Differ. Labo- Differ. Labo- Differ.
NRC ratory ente NRC ratory ente NRC ratory ence NRC ratory ence
[
1 42 8.3 5.6 -32.5 9.3 6.3 -32.3 7.8 6.2 -20.5 10.0 6.2 '38.0
- t i
2 6 8.2 7.3 -11.0 10.1 7.0 -30.7 8.0 7.1 -11.3 9.7 7.2 -25.8 l
5 54 9.2 8.6 -4.4 10.7 9.9 -7.5 9.4 10.0 6.4 11.1 9.6 -13.5
53 11.0 9.8 -10.9 12.2 -17.2 10.7 10.7 0.0 12.5 10.0 -20.0 7 10.1 j 9 *52 13.6 9.9 -27.2 12.1 10.8 -10.7 12.2 10.7 -12.3 11.9 10.7 -10.1 )
i 11 *12 11.2 7.7 -31.3 11.8 8.4 -28.8 10.1 7.8 22.8 11.6 7.9 -31.9 ;
I 13 13 12.5 10.0 -20.0 ' 11.5 11.0 -4.3 '
11.5 11.3 -1.7 11.1 10.5 -5.4 l 14 *44 6.9 5.0 -27.5 8.1 5.9 -27.2 8.2 5.9 -28.0 9.7 5.3 -45.4 19 *56 9.4 7.0 -25.5 10.6 7.5 -29.2 9.6 7.3 -24.0 9.8 7.5 -23.5 22 58 9.3 5.0 -46.2 7.7 5.5 -28.6 8.2 5.1 -37.8 8.0 5.7 -28.8 ;
24 41 9.6 7.0 -27.1 8.0 7.9 -1.3 9.1 8.0 -12.1 8.4 7.7 -8.3 t
29 *60 11.3 8.1 -28.3 11.4 9.5 -16.7 10.6 9.1 -14.2 11.4 9.5 -16.7 !
l 8.0 -22.3 ** 7.6 **
30 46 11.1 6.9 -37.8 11.0 8.0 -27.3 10.3 i
Co. located dosimeters within 10 feet of NRC dosimeter.
l
*NRC results not available.
l i
Table 7 - Results of Environmental Dosimetry intercomparison with !
NRC TLD Direct Radiation Monitoring Network i
1 I
l 17 ;
_ . ,- .~
m - -
_+.: -u e , %
I Exposure j Pathway Cnteria for Selection Sampling and Sample Type & Frequency l End/or Sample of Sample Number & Location Collection Frequency Location of Analysis i 1
i AIRBORNE'
1. Particulate A) 3 indicator samples to be taken at Continuous sampler operation with 2 Gross beta following filter ;
locations (in different sectors) be- weekly collection- 5 change; monthly composite (by l yond but as close to the exclusion 10 location) for gamma isotopic. ;
boundary as practicable where the !
highest of fsite sectorial ground level j concentrations are anticipated l l
B) 1 Indaator sample to be taken in the Continuous sampler operation with 6 Gross tata following filter I sector beyond but as close to the weekly colicction. chai,ge; monthly composite (by exclusion boundary as pract; cable location) for gamma isotopic.
corresponding to the residence 7 having the highest anticipated !
offsrte ground level concentration or ;
dose. >
i C) 1 Indgator sample to be taken at the Continuous sampler operation with 14 Gross beta followmg filter !
location of one of the dairies most weekly collection. change; monthly composite (by j likely to t,e affetted location) for gamma isotopic.
D) 1 Control sample to be taken at a Continuous sampler operation wrth' 17 Gross beta following filter location at least 10 air miles from the weekly collection. change; monthly composrte (by ;
1 srte and not in the most prevalent location) for gamma isotopic. l wind directions. ;
i f
II. Radiciodine A) 3 indicator samples to be taken at Continuous sampler operation with 2 Gamma isotopic for lodine 131 two locations as given m f(A) above. weekly canister collection. 5 weekly (
10 A k B) 1 Indicator sample to be taken at the Continuous sampier operation wrth 6 Gamma isotopic for lodine t3' i d
location as given in f(B) above. weekly canister collection. weekly. i l
C) 1 Indicator sample to be taken at the Contmuous sampler operation wrth 14 Gamma isotopic for lodine 131 [
location as given in 1(C) above. weekly canister collection. weekly. l D) 1 Control sample to be taker, at a Continuous sampler operation with 17 Gamma isotopic for lodine 131 it. cation similar in nature to f(D) wc ekly canister co!!ection. weekly. l above v
Ill Direct A) 13 Indicator stations to form an inner Monthly or quarterly exchange; two 1,2,3,4, Gamma dose monthly or !
ring of stations in the 13 accessible or more dosimeters at each location. 5,6,7,B, quarterly ;
sectors within 1 to 2 miles of the 9,10,29, plant. 30,47 l B) 16 Indicator stations to form an inner Monthly or quarterly exchange; two 12,14,32, Gamma dose monthly or !
a ring of stations in the *S accessible or more dosimeters at each location. 33,34,35 quarterly. !
1 sectors wrthin 3 to 5 miles of the 36,37,41, i plant. 42,43,45, !
46,49, 53,55 ;
C) 20 5tations to be placed in special Monthfy or quarterly exchange; two 11,13,15, Gamma dose monthly or inte,est areas such as population or more dosimeters at each location. 16.17,1B, quarterly.
centers, nearby residences, schools 19,20,31, ,
44,48,50, !
and m 2 or 3 areas to sere as controts. 51,52,54, 56,57,58 59,60 !
f Table 8 - Radiological Environmental Monitoring Program Specifications Page 18 i
i
._ ., l a
i i
. Exposure ;
Pathway Criteria for Seledion Sampling and Sample Type & Frequency >
and/or Sample of Sample Number & Location Collection frequency location of Analysis WATERBORNE:
! N. Surface A) 1 Indicator sample downstream to be Time composite samples with collet- 21 Gamma isotopic monthly wrth -
Water taken at a location which allows for tion every month quarterly composrte (by loca- l rmaing and dilution in the ultimate tion) or monthly sample to be receiving river. analyzed for tntium. t i
B) 1 Control sample to be taken at a Time temposite samples with collet- 22 Gamma isotopic monthly with location on the receiving river tion every month quarterly composste (by loca- [
sufficiently far upstream such that no tion) or monthly tample to be i effects of pumped storage operation analyzed for tritium. ;
a re anticipated.
[
C) 1 Indicator sample from a location Time composite samples with collec- 17 Gamma isotopic. monthly with !
immediately upstream of the nearest tion every month. quatterly composite (by loca- ;
downstream municipal vwater suppfy. tion) or monthly sample to be l analyzed for tritium. [
l D) 1 Indicator sample so be taken in Time composite samples with collec- 23 Gamma isotopic monthly with j the upper reservoir of the tien every month. quarterly composite (by loca- ;
pumped storage facihty. tion) or monthly sample to be ,
analyzed for tntium.
E) 1 Indkator sample to be taken in the Grab samphng monthly 24 Gamma esotopic monthly with ,
upper reservoir's nonfluctuating quarterly composite (by loca.
recreational area- tion) or monthly sample to be [
analyzed ior tritium. l F) 1 Control sample to be taken at a Grab samphng monthly. 1B Gamma isotopic monthly with location on a separate unaffected quarterly compoute (by loca-water.hed reservoir. tion) or monthly sample to be ;
analyzed for tntsum. j r
G) 1 Indicator sample to be taken in the Time composite samples wrth collec- 25 Gamma isotopic monthly with l upper reservoir at the intake of the tion every month. quarterly composite '(by loca- j of the pumped storage facihty. tion) or monthly sample to be ;
analyzed for tritium. (
i V. Ground A) 2 indicator samples to be taken with- Quarterly grab samphng 26 Gamma isotopic and tritium )
Water in the endusion boundary and in the 27 analyses quarterly.
direction of potentially affected .
ground water supphes. 6 C
B) 1 Control sample from unaffected Quarterly grab samphng . 16 Gamma isotopic and tritium i location analyses cuarterly l VI. Drinking A) 1 Indicator sample from a nearby Monthly grab samphng 28 Monthly gamma isotopic. gross l Water pubhc ground water supply source. beta and tritium analyses. !
! B) 1 Indicator (finished water) sample Monthly composite sampling 17 Monthly gamma isotopic, gross [
l from the nearest dcwnstream water beta and tritium analyses.
suppfy.
e i
C) 1 Control (finshed water) sample Monthly composite sampling. 39 Monthly gamma isotopic, gross ;
i from the nearest unaffected public beta and tritium analyses. !
water supoly.
1 Table 8 - Radiological Environmental Monitoring Program Specifications f i
i i Page _19 ,
f
1 Exposure l Pathway Criteria for Selection Sampling and Sample Type & Frequency and/or Sample of Sample Number & Location Collection Frequency Locatiot of Analysis ,
INGESTION:
Vll. Mdk A) Samples from milking animals in 3 Biweekly grab sar- To be Gamma isotopic and 1-131 locations within 5 km having the supplied analysis biweekly.
highest dose potential. If there are . when milk none then 1 sample from milking l animals are ,
anirrais in each of 3 areas between 5 found in l to 8 km distance where doses are atrardance i calculated to be greater than 1 mrem pith criteria ,
per year. Vll.A. l B)
Control sample to be taken at the Biweekly grab sample. 16 Gamma isotopic and 1-131 [
location of a dairy > 20 miles analysis b weekly. i distance and not in the most prevalent wind direction.
?
C) 1 indicator grass (forage) sample to Monthly when available 6 Gamma isepic. ,
be taken at one of the locations [
beyond but as close to the exclusion boundary as practicable where the j highest of fsite sectorial ground level concentrations are anticipated.
D) 1 Indicator grass (forage) sample to Monthly when available. To be Gamma isotopic.
be taken at the location of Vil(A) supphed ,
above when animals are on pasture. when milk l animals are i found in accordance mth criteria i Vll.A. l E) 1 Control grass (forage) sample to be Monthly when available. 16 Gamma isotopic. ;
tan en at the location of Vil(B) above. 3 6
Vill. Food A) Two samples of broadleaf vegetation Month!y when available. 6 Gamma isotopic on edible Products grown in the . 2 nearest offsite B portion. )
location of highest alculated annual average ground level D/Q if milk ['
samnhng is not performed within 3 km or if milk sampling is not ;
performed at a location within 5-10 I km where the doset are (alculated to !
he greater than 1 mremlyr. .
f B) 1 Control sample for the same foods Same as for Vill (A), as appropriate. 18 Gamma isotopic on edible [
in Vili(A) taken at a location at least portion. i 10 miles distance and not in the most [
prevalent wind direction. .l, IX. Fish A) 1 Indicator sample to be taken at a Semiannual collection of the 23 Gamma isotopic on edible
location in the upper reservoir. following specie types if available; portions semiannually. ,
bass; bream, crappie; catfish, carp; forage fesh (shad).
B) 1 Indicator sample to be tamen at a Semiannual collection of the follow- 21 Gamma isotopic on edide location in the lower reservoir. ing specie types if available: bass; portions semiannually.
bream, crappie; catfish, carp; forage fish (shad). l 1
1 Table 8 - Radiological Environmental Monitoring Program Specifications !
i Page 20 I
i l
l I
Exposure )
Criteria for Selection
{ Sampling and Sample Type & Frequency Pathway ;
and/ca Sample of Sample Number & Location Collection Frequency Location of Analysis i
J fx Fish i (cont ) C) 1 Indicator sample to be taken at a Semiannual collection of the 24 Gamma isotopic on edible ;
location in the upper reservoir's non- following specie types if available: portions semiannually. l fluctuating recreational area. bass; cream, crappie; catfish, carp; j f orage fish (shad). !
D) 1 Control sample to be taken at a Semiannual collection of the 22 Gamma esotopic on edible {
location on the receiving fiver .N!!owing specie types if available: portions semiannuany. !
4 suf ficiently far upstream auch that no bass; bream, uappie; catfish, carp; effects of pumped storage operation forage fish (shad).
are antionated.
AQUATIC:
X. Sediment A) 1 Indicator sample to be taken at a Semiannual grab sample. 23 Gamma isotopic.
location m the upper reservoir.
I I
B) 1 Indaator sample to be taken at a Serr.iannual grab sample. 24 Gamma isotopic. j location in the upper reservoir's j nonfluctuating recreational area. !
l C) 1 Indicator sample to be taken on the Semiannual grab sample. 21 Gamma isotopic. {
shoreline of the lower reservoir. l D) 1 Control sample to be taken at a Semiannual grab sample. 22 Gamma isotopic. {
location on the receiving river i suf ficiently far upstream such that no ;
effects of pumped storage opera- _,
tion are anticipated j i
t I
l i
it
i 1 i l
i i j !
', f i
Table 8 - Radiological Environmental Monitoring Program Specifications i Page 21 !
-i l
- . 1
Exposure ,
Pathway Sample Type & Frequency Criteria for Selection Sampling and !
and/or Collection Frequency Location of Analysi5 i of Sample Number & Location Sample
]
AIRBORNE: !
s L Particulate E) 3 Indicator samples to be taken at Continuous sampler opera- B Gross beta following filter change; !
locations (m different sectors) beyond tion with weekly 13 Monthly Composite (by location) for l but as close to the esclusion boundary collection. 59 gamma isotopic. j as practicable and nearer to the plant tha n the nearest criticai receptor for the choten sector.
lit. Direct D) 8 Stations to be placed withm the Monthly or quarterly 61,62 Gamma dose monthly or quarterly. -[
exclusion bo undary (Special Study). exchange; two or more 63,64 {
dosimeters at each 65,66 ;
location. 67,68 !
E) 3 Stations to be placed on buoys on Monthly or quarterly 69 Gamma dose monthly or quarterly, '
Montuello Reservoir (Background exchange; two or more i Study) dosimeters at each i; location. l WATERBORNE:
I 1 indicator sample to be taken in the Time composite sampfes 25 Gamma isotopic monthly with IV. Surface G) l Water upper reservoir at the intake of the with collection every quarterly composite (by location) or i pumped storage facihty. month. monthly sample to be analyzed for tritium. [
! INGESTION:
a Vll. Milk A) Samples from milking animals in 3 loca- Biweekly grab sample 14 Gamma isotopic and 1-131 analysis ,
I tions within 5 km having the highest biweekly.
dose potential if there are nonethen 1 t sample from milking animals in each of l 3 areas between 5 to 8 km distance [
where doses are calculated to be greater than 1 mrem per year. ;
D) 1 Indicator grass (forage) sample to be Monthly when available 14 Gamma isotopic.
taken at the location of Vll(A) above i when animals are on pasture.
i Vill. Food C) 1 Indicator sample of each of the Annually bring growing 6 Gamma isotopic on edible portion.
Products various types of foods grown in the area season. ,
surrounding the plant. ,
t D) 1 Control sample of the same foods Annually during growing 18 Gamma isotopic on edible portion. {
collected in VI!!(c) at a location at least season. l 10 miles distance and not in the most l prevalent wind direction.
i 4
AQUATIC: E) 1 Indicator sample to be taken at a Semiannual grab sample. 17 Gamma isotopic _ j X. Sediment location immediately upstream of the ,
nearest downstream municipal water supply. ,
F) Four (4) additional indicator samples to Semiannual grab sample. 84,85 Gamma isotopic, be taken at various locations on 87,88 l
Congaree River between Broad River l and Lake Marion ;
Table 9 - Supplemental Radiological Environmental Monitoring Program j 22 ;
i
Virgil C. Summer Nuclear Station Docket No. 50-395 -
Fairfield County, South Carolina Reporting Period: 1/1/92-12/31/92 L we U t Number of ,
Medium or Pathway Type and Total Location with Highest Annual Mean Sampled (Unit of Number of Analyses
" " '"9 *** #" *" *"9 Measurement) Performed 1 (Range)
Attual(Max.) (Distante & Direction) Measurements Air Particulate Gross Beta 1.8E-2 (260/260) Site 14 Dairy 1.9E-2 (52/ 52) 1.8E-2 (51/52) 0 (pCi/m3) (311) (1.0E-2) (5.1E-3 to 5.0E-2) (6.3 miW) (6.5E-3 to 4.4E-2) (6.1E-3 to 4.4E-2)
Gamma Spec (72)
Cs-134 2.5E-3 All < LLD All < LLD 0 (5.0E-2)
Cs-137 2.7E-3 All < LLD All < LLD 0 4
(6.0E-2)
Air Radioiodine I-131(316) 5.1E-2 All < LLD All < LLD 0 (pCi/m3) (7.0E-2)
Direct (TLD)5 Gamma (136) 7.1(116/116) Site 55, St. Barnabas 10.0(4/4) 7.1(20/20) 0 (pR/hr) Quarterly .5E0 (4.8 to 10.0) Church (2.8 mi, E) (9.5 to 10.4) (5.3 to 9.1)
Gamma (104) 5.8(104/104) Site 52, Monticello 9.5 (4/4) N/A 0 SpecialInterest .5E0 (2.7 to 9.5) (3.9 mi, NNE) (8.4 to 10.5)
Surface Water H-3(93) 5.1 E + 2 5.1 E + 2 (2/48) Site 21, Parr Res. 5.1 E + 2 (2/48) All < LLD 0 (pCi/l) (2.0E + 3) (4.9E + 2 to 5.4E + 2) (2.7mi, SSW) (4.9E + 2 to 5.4E + 2) 4 w Gamma Spec (93)
Mn-54 2.0E0 All < LLD All < LLD 0 (1.5E + 1)
Co-58 2.2E0 All < LLD All < LLD 0 t
(1.5E + 1)
Fe-59 5.1 E0 All < LLD All < LLD 0 (3.0E + 1)
Co-60 2.4E0 All < LLD All < LLD 0 (1.5E + 1)
Zn-65 4.4E0 All < LLD All < LLD 0 (3.0E + 1)
Zr-95 4.0E0 All < LLD All < LLD 0 (3.0E + 1)
Nb-95 3.0E0 All < LLD All < LLD 0 (1.5E + 1)
Cs-134 1.9E0 All < LLD All < LLD 0 (1.5E + 1)
Cs-137 2.2E0 All < LLD All < LLD 0 (1.8E + 1)
Table 10- Radiological Environmental Monitoring Program Summary
Virgil C. Summer Nuclear Station Docket No. 50-395 -
Fairfield Ccunty, South Carolina Reporting Period: 1/1/92-12/31/92
tmation with Highest Annual Mean Number of .
Medium or Pathway Type and Total sampled (Unit of Numberof Analyses
" " *"9 ' " " "9 Measurement) Performed 1 (Range)
Attual(Max.) (Distante & Direction) Measurements Surf ace Wtr. Ba-140 1.7E + 1 All < LLD All < LLD 0 (continued) (6.0E F 1)
La-140 6.4E0 All < LLD All < LLD 0 (1.5E + 1)
Ground Water H-3(12) 5.6E + 2 All < LLD All < LLD 0 (pCill) (2.0E + 3) __ _
Gamma Spec (12)
Mn-54 5.5E0 All < LLD All < LLD 0 (1.5E + 1)
Co-58 5.4E0 All < LLD All < LLD 0 (1.5E + 1)
Fe-59 1.0E + 1 All < LLD All < LLD 0 (3.0E + 1)
Co-60 5.7E0 All < LLD All < LLD 0 (1.5E + 1)
L Zn-65 1.2E + 1 All < LLD All < LLD 0
? (3.0E + 1)
Zr-95 9.6E0 All < LLD All < LLD 0 (3.0E + 1)
Nb-95 8.2E0 All < LLD All < LLD 0 (1.5E + 1)
Cs-134 5.3E0 All < LLD All < LLD 0 (1.5E + 1)
Cs-137 5.5E0 All < LLD All < LLD 0 (1.8E + 1)
Ba-140 2.2 E + 1 All < LLD All < LLD 0 (6.0E + 1)
La-140 8.3E0 All s LLD All < LLD 0 (1.5E + 1)
Drinking Water 6 Gross Beta (36) 2.7E0 4.8E0 (17/24) Site 28, Nuc. Trng. 5.5E0 (11/12) 4.100(9/12) 0 (pCill) (4.0E0) (2.2E0 to 7.1 E0) Center (2.4 mi, SSE) (2.3E0 to 7.1 E0) (2.7E0 to 6.4EO)
H-3(36) 4.7E + 2 All < LLD 4.7E + 2 (1/12) 0 (2.0E + 3) (Single Value) l' Gamma Spec (36)
Table 10 - Radiological Environmental Monitoring Program Summary
Virgil C. Summer Nuclear Station Doc &tet No. 50-395 -
Fairfield County, South Carolina Reporting Period- 1/1/92-12/31/92 L m Limit Loc.ation with Highest Annual Mean * ' '
Medium of Pathway Type and Total Sampled (Unit of Number of Analyses g , ,
Measurement) Performed 1 (Range)
~
Actual (Mas.) (Distante & Direttion) Measurements Drinking Water 6 M n-54 6.6E0 All < LLD All < LLD 0 (pCill)(continued) (1.5E + 1)
Co-58 6.2E0 All < LLD All < LLD 0 (1.5E + 1)
Fe-59 1.2 E + 1 All < LLD All < LLD 0 (3.0E + 1)
Co-60 6.8E0 All < LLD All < LLD 0 (1.5E +- 1)
Zn-65 1.3 E + 1 All < LLD All < LLD 0 (3.0E + 1)
Zr 95 1.1 E 4 1 All < LLD All < LLD 0 (3.0E + 1)
Nb-95 1.0E + 1 All < LLD All < LLD 0 (1.5 E + 1) 4 l-131 6.3 E- 1 All < LLD All < LLD 0 l yi (1.0EO)
Cs-134 6.6E0 All < LLD All < LLD 0 t (1.5E + 1)
Crr137 6.5E0 All < LLD All < LLD 0 (1.8E + 1)
Ba-140 2.4E + 1 All < LLD All < LLD 0 (6.0E + 1)
La-140 8.2E0 All < LLD All < LLD 0 (1.5E + 1)
Milk (pCill) Gamma Spec (52) 1-131 6.6E-1 All < LLD All < LLD 0 (1.0EO)
Cs-134 2.3E0 All < LLD All < LLD 0 (1.5E + 1)
Cs-137 3.0E0 2.0E0 (16/26) Site 14, Dairy 2.0E0 (16/26) 2.1 E0 (5/26) 0 (1.8E + 1) (1.5E0 to 5.8EO) (6.3 mi W) (1.5E0 to 5.8EO) (1.2E0 to 3.3EO)
Ba-140 9.6E0 All < LLD All < LLD 0 (6.0E + 1)
Table 10 - Radiological Environmental Monitoring Program Summary
_ . _ . _ . _ _ . _ _ _ _ . . . _ . _ _ _ ~ . . _ _ . _ _. , . _ _ ._. -_ __ _ . _ . _
Virgil C. Summer Nuclear Station Docket No. 50-395 -
Fairfield County, South Carolina Reporting Period: 1/1/92-12/31/92 L Lim t location with Highest Annual Mean Numberof .
Medium of Pathway Type and Total ,
Sampled (Unit of Number of Analy es Measurement) Performed 1 Attual(Max.) (Distante & Direction) (Range) Measurements Milk (pCill) La-140 3.3 E0 All < LLD All < LLD 0 (Continued) (1.5E + 1)
Grass (pCi/kg wet) Gamma Spec (35) 1-131 4.9E + 1 All < LLD All < LLD 0 (6.0E F 1)
Cs-134 1.5E + 1 All < LLD All < LLD 0 (6.0E F 1)
Cs-137 1.6E + 1 2.2E + 1 (4/22) Site 6, Env. Lab. Gar. 3.3 E + 1 (2/9) 1.1 E + 1 (1/13) 0 ;
(8.0E + 1) (9.5E0 to 5.3E + 1) (1.0 mile ESE) (1.2E + 1 to 5.3E + 1) Single Value Broadleaf Vegeta- Gamma Spec (25) tion (pCi/kg wet) 1131 2.7E + 1 All < LLD All < LLD 0 (6.0E + 1)
Cs-134 1.3 E + 1 All < LLD All < LLD 0 4 (6.0E + 1)
? Cs-137 1.7 E + 1 All < LLD All < LLD 0 (8.0E + 1)
Other Vegetation Gamma Spec (5)
(pCi/kg wet) 1-131 5.3E + 1 All < LLD All < LLD 0 (6.0E + 1)
Cs-134 1.2E + 1 All < LLD All < LLD 0 (6.0E + 1)
Cs-137 1.3E + 1 All < LLD All < LLD 0 (8.0E + 1)
Fish (pCi/kg wet) Gamma Spec (32)
Mn-54 1.7E + 1 All < LLD All < LLD 0 (1.3E + 2)
Co-58 2.7E + 1 All < LLD All < LLD 0 (1.3E + 2)
Fe-59 9.7 E + 1 All < LLD All < LLD 0 (2.6E + 2)
Co-60 1.1 L + 1 5.1 E + 1 (1/24) Site 21, Parr Reservoir 5.1 E + 1 (1/24) All < LLD 0 (1.3E + 2) Single Value (2.7 mi SSW) Single Value Table 10 - Radiological Environmerital Monitoring Program Summary
Virgil C. Summer Nuclear Station Docket No. 50-395 -
Fairfield County, South Carolina Reporting Period: 1/1/92-12/31/92 L we t Location with Highest Annual Mean Number o.f .
Medium of Pathway Type and Total Samp.d(Unit of Number of Analyses Measurement) Performed 1 -
(Range)
Actual (Man.) (Distance & Direction) Measurements Fish (pCi/kg wet) Zn-65 4.3E + 1 All < LLD All < LLD 0 (continued) (2.6E + 2)
Cs-134 1.4E + 1 All < LLD All < LLD 0 (1.3 E + 2)
Cs-137 2.1 E + 1 1.3E + 1 (16/24) Site 23, Discharge 1.5 E + 1 (5/8) 1.6E + 1 (6/8) 0 (1.5E + 2) (6.4E0 to 2.1E + 1) Canal (Mont. Res. (6.4E0 to 2.1 E + 1) 7.6E0 to 2.7E + 1 0.5 mi, ESE)
Sediment (pCi/kg)1 Gamma Spec (16)
M n-54 1.6E + 2 6.3 E + 1 (1/16) Site 23, Discharge 6.3E + 1 (1/14) All < LLD 0 Single Value Canal (Mont. Res. Single Value 0.5 mi, ESE)
Co-58 3.1 + 1 All < LLD All < LLD 0 Co-60 3.6E + 1 9.9E + 1 (8/12) Site 23, Discharge 1.5E + 2 (4/4) All < LLD 0 (3.6E + 1 to 2.1E + 2) Canal (Mont. Res. (1.2E + 2 to 2.1 E + 2)
. 0.5 mi, ESE)
U '
Cs-134 2.3 E + 1 2.1 E + 1 Site 21, Parr Reservoir 2.1 E + 1 All < LLD 0 (1.5E + 2) Single Value (2.7 mi SSW) Single Value Cs-137 2.3E + 2 (12/12) Site 23, Discharge 3.4E + 2 (4/4) 1.4E + 2 (4/4) 0 (1.8E l- 2) (1.0E + 2 to 3.5E + 2) Canal (Mont. Res. (3.3E t 2 to 3.5E+2) (5.6E+ 1 to 0.5 mi, ESE) 2.0E + 2)
Table 10 - Radiological Environmental Monitoring Program Summary l
. . - . __ _--... ___ . _ _ - _ . _ - . _ _ . _ _ _ _ _ _ _ . - - . - - . _ _ _ . _ _ _ _ _ _ - - - _. ~
Footnotes r i
1. Does not include supplemental samples. All supplemental sample results were consistent with the tabulated results shown.
2. Values given are MDA values calculated from the program data analyses with i maximum acceptable LLD values allowed from NRC guidelines given in parentheses.
3. Mean and range are based on detectable measurements only. The fractions of detectable measurements at specific locations are indicated in parentheses.
4. Any confirmed measured level of radioactivity in any environmental medium I that exceeds the reporting requirements of ODCM, Section 1.4.1.2.
i
5. Detection sensitivity is approximately 5 mrem /yr (0.5 pR/ht) determined from i the analyses of five years of preoperational data.
6. Elevated levels of Pb-214 and Bi-214 were observed in all Jenkinsville drinking i les. The values are not reported here because they are naturally water samp(do not originate from VCSNS) and furnish no quantifiable occurring information of interest. .
7. Elevated levels of Pb-214 and Bi-214 plus other Ra-226 daughter products and i Ac-228 plus other Th-232 daughter products were observed in all sediment samples. The values are not reported here because they are naturally :
occurring (do not originate from VCSNS) and furnish no quantifiable I information of interest.
l l
i Table 10 (continued)- Radiological Environmental Monitoring Program Summary 28 .
Medium or Pathway Type and Total oca on w g s Annual Wan %mber of Lower Limit of AllIndicator Sampled (Unit of Number of Control Locations Nonroutine Detection 1 Locations Measurement and Analyses Namc (Distance & Mean2 Mean2 (Range) Reported 3 '
Actual (Max.) Mean2 (Range)
Reporting Penod) Performed Direction) (Range) Measurements 1.3 E-1(52/52) 1.1 E-1 (562/564)4 Site 13, North Dam (2.1E-2 to 1.2E-1 (153/155)
Air Particulate Gross Beta 4.1E-3 D (23 mi NNM W- D (7E3 to 6E1)
(pCi/m3)
(1300) (1.0E-2 Site 8, Mon. Res. 5 of (1981-1982) 2.7E-2 (456/462)4 3.0E-2(42/42) 2.8E-2 (125/126)
(9.3E-3 to 6.6E-2) Rd 224 (1.5 ENE) (1.2E-2 to (1.2E-2 to 5.8E-2) 6.0E-2)
Gamma Spec (307)
Cs-134 All < LLD All < LLD 0
)
Site 10, Met Tower 3.8E-3 (2/22) 3.1 E-3 3.2E-3 (22/241) 4.2 E-3 (4/66)
(1.0E-2) (1.5E-3 to 5.2E-3) (2.4 mi NNE) 5 2E-3 I' C/m 92
( 2)
^" ^"
D c DP e 13, North Dam Gamma (1220) 0.5 13.1(61/61) 9.7(305/305) 0
) Monthly (6.7 to14.7) (2.9 mi NNW) (12.2 to 14.2) (6.4 to 13.5)
(1978-1982)
Gamma (161) 0.2M4/ M We M, St. Barnabas 14.0(7/7) 0.5 0 Quarterly (6.8 told 7) Church (2.8 mi E) (13.1 to 14.7)
Surf ace Water Site 17, Columbia 1.6E + 3 (2/7) 1.2E F 3 (6/14) 1.1 E + 3 1.4E + 3 (18/29)
(PCill) H-3(43) Canal (24.7 mi, SE)
(2.0E + 3) (1.1 E + 3 to 2.4E + 3)
(1981-1982) 1.8E + 3) 1.6E + 3)
Gamma 5pec (140) 2 7E 1 Mn-54 g3 E g All < LLD All < LLD 0 9E 1 Co-58 All < LLD All < LLD 0 E 5)
Fe-59 ^"< ^"<
(3UE 1) 2 4E 1 Co-60 g g 3) All < LLD AH < LLD 0 79 zn-65 g3 gE 1) AH < @ AH < a 0 Table 11 - Radiological Environmental Monitoring Program Preoperational (Baseline) Summary
Medium or Pathway Type and Total L cation with Highest Annual Mean Number of Lower Limit of Allindicator Sampled (Unit of Number of " ' # "$ "U"' " "'
Detection 1 Locations Measurement and Analyses N me( s ante can eae) (Range) Reported 3 ~
Actual (Max.) Mean2 (Range)
Reporting Period) Performed Direction) (Range) Measurements 2
Zr-95 All < LLD All < LLD 0 g g Nb-95 All < LLD All < LLD 0 OSE-)
3 Cs-134 All < LLD All < LLD 0 g 5E- )
Cs-137 All < LLD All < LLD 0 0 8E 1)
Ba 140 ^"< ^"<
(6bEf1)
^"< ^"<
(1982 only) (1 SE 1)
Ground Water 9.0E4 2 1.5E + 3 (16/16) Site 26, Onsite Well
+(
( P4 (265 f t, W)
(pCi/l)(1981-1982) (2.0E + 3) (9.5E + 2 to 2.3E i- 3) 2 3E 13) 19E 3)
. Gamma Spec (32) 3 7E0 Mn-54 gf All ( LLD All < LLD 0 3) 3 8E0 Co-58 gfg 3) All < LLD All < LLD 0 Fe-59 ^"< ^"<
(3 bE + 1) 3 8E0 co.60 All < LLD All < LLD 0 g 5E 1E l zn-65 (3ffg +0 AH < RD AH < LLD 0 3)
Zr-95 All < LLD All < LLD 0 O NE 1)
Nb-95 All < LLD All < LLD 0 O 5E 1)
Cs-134 ^"< ^"<
(1 hE+1) 8 Cs-137 An < uD AH < s 0 (1fbE41) l l
Table 11 - Radiological Environmental Monitoring Program Preoperational(Baseline) Summary
Medium or Pathway Type and Total L c tion with Highest Annual Mean Number of Number of Lower Limit of AllIndicator Nonroutine Sampled (Unit of Control Locations Detection 1 Locations Measurement and Analyses Name (Distance & Meanz Mean2 (Range) Reported 1-Actual (Max.) Mean2 (Range)
Reporting Period) Performed Direction) (Range) Measurements B a-140 All < LLD All < LLD 0 (1982 only)
^"< ^"<
(15 & 1)
"" "9
Gross Beta 7 (2.0E0)
(pCell)(1981-1982) 6.3E + 2 7.8E + 2 (6/14) Site 28, Jenkinsville + (#'
"~ (
(1.0E + 3) (6.8E + 2 to 9.8E + 2) (2.0 mi SE)7 Gamma Spec 0
(44)
Mn-54 All < LLD 0 O SE )
Co-58 All < LLD 0 (1 E 1)
Fe-59 (3 bE + 1)
^"
G Co-60 g E O All < LLD 0 Zn-65 All < LLD 0 (3 OE 1)
E Zr-95 O 5E j)
All < LLD 0 3
Nb-95 All < LLD 0
{ 5E
^
1-131 All < LLD 0
([0E0) 2 E1 Cs-134 g 0E All < LLD 0 2
Cs-137 g 8E 1)
All < LLD 0 Ba-140 ^"<
(6 bE + 1)
La-140 4.4E-1 All < LLD 0 (1982 only) (1.5E + 1)
Table 11 - Radiological Environmental Monitoring Program Preoperational (Baseline) Summary
Medium or Pathway Type and Total Location with Highest Annual Mean Number of Lower Limit of AllIndicator "
Sampled (Unit of Number of ' "' " ' " " '
Detection 1 Locations Reported 3 -
Measurement and Analyses Name (Distance & Mean2 Mean2 (Range)
Performed M ad h 2 g e) (Range) Measurements
( Reporting Period) Direction)
Gamma 5pec (1981-1982) 63 0 1-131 All < LLD All < LLD 00)
Cs-134 All < LLD All < LLD 0 O SE D 4.6E0 4 M O(8/4D Me 14, Daky 53E0 (37/47) 0 Cs-137 (5.1 mi., W) (2 8E0 to (1.5E + 1) (2.8E0 to 6.1 EO) (3.7E0 to 9.2E0) b.1EO)
Ba-140 All < LLD All < LLD 0 La-140 All < LLD All < LLD 0 0 SE+ U Grass (pCi/kg wet) Gamma Spec
, (1981-1982) (82) 6 1-131 All < LLD All < LLD 0 2
Cs-134 All < LLD All < LLD 0 8
+1 5.0E + 1 (13/51) Site 14, Dairy (5/2 ) 0 (13E 4 to Cs-137 (8.0E + 1) (1.6E + 1 to 1.6E + 2) (5.1 mi W) (1.6E + 1 t 3.4E + 2) 1.6E + 2)
Broadleaf Vegetation (pCi/kg wet) Gamma Spec (10)
(1980-1982) 3 1-131 All < LLD All < LLD 0 60 Cs-134 All < LLD All < LLD 0 El
+ + (' ' ' '# " 5' "' ' + ( All < LLD 0 Cs-137 (Single Value)ll (8.0E + 1) (1.8E + 1 to 3.6E + 1) (1.2 mi SW)
Other Vegetation Gamma Spec (pCi/kg wet)
(32)
'(1980-1982)
Table 11 - Radiological Environmental Monitoring Program Preoperational(Baseline) Summary
Medium or Pathway Type and Total L cation with Highest Annual Mean Number of Lower Limit of AllIndicator '
Sampled (Unit of Number of Controllocations Nonroutine Detection 1 Locations Measurement and Analyses ame an e n can angd Repord
Actual (Max.) Mean2 (Range)
Reporting Period) Performed Direction) (Range) Measurements Cs-134 AH < LLD AH < RD 0 (8 bE41)
Cs-137 All < l LD All < LLD 0
)
Fish (pCi/kg wet) Gamma Spec (1980-1982) (92)
Cs-134 g All < LLD All < LLD 0
)
8H1 2.8H 160/74 Re 24, Recreation 7/23 Cs-137 (1.3E + 2) (1.1 E + 1 to 1.0E + 2) Lake (5.5 mi, N) (1.2E + 1 t (f.0E41 to 0 7.9E + 1) 1.0E + 2)
Co-58 All < LLD All < LLD 0 Mn-54 All < LLD All < LLD 0
)
Fe-59 All < LLD All < LLD 0 All < LLD All < LLD 0 Zn-65 4 )
E Co-60 All < LLD All < LLD 0 E
Sediment (pCi/kg) Gamma Spec (1980-1982) (24) 2.
Cs-134 All < LLD All < LLD 0 3
Site 21, Parr Reservoir 2.6E + 2 (6/6) 4.2E + 2 (6/6) 2.4E + 1 1.7E + 2 (12/18) 5 (1.5E + 2) (2.6E + 1 to 4.5E + 2) (2.7 mi,55W) (2 + o (1 p 1OE+3 Table 11 - Radiological Environmental Monitoring Program Preoperational(Baseline) Summary
F
, i s
i Footnotes 1 i
i
1. Values given are MDA values calculated from the program data analys,es with l maximum acceptable LLD values allowed from NRC guidelines given m ;
parentheses. .
l
2. Mean and range are based on detectable measurements only. The fractions: i of detectable measurements at specific locations are indicated in parentheses. :
3. A nonroutine measurement is any confirmed measured level of radioactivity l in any environmental medium that exceeds the reporting requirements of l
, VCSNS ODCM, Section 1.4.1.2. i 4 ,
4. The baseline values are high because of the fallout from the Chinese bomb !
test in 1980. The first set of data reflects the 1981 baseline. The second set of j data reflects the 1982 baseline, essentially free of bomb test fallout. The 1982 i data covers the period 1/1/82-10/22/82. :
5. Detection sensitivity is approximately 5 mrem /yr (0.5 pR/hr) determined from l the analyses of five years of preoperational data. l
6. No control location was specified for drinking water during the preopera- ,
tional monitoring period.
7. Inconclusive data. Refer to the Preoperational Radiological Environmental Monitoring Report. i Table 11 - Radiological Environmental Monitoring Program Preoperational (Baseline) Summary i
4.
34
~
Sample Month Media Location (Week No.) Cause for Exception Air 6 March (11) incomplete samples due to equipment failures.
17 March (11) 17 April (14) 6 August (31)
Grass 6 January (01) Seasonal Unavailability.
6 November (45) Seasonal Unavailability.
6 December (49) Seasonal Unavailability. i Broadleaf 18 July (29) Seasonal Unavailability.
Vegetation 18 August (33) Seasonal Unavailability.
18 September (37) Seasonal Unavailability.
Surface 23 September (36) Low sample volume due to equipment Water failure.
21 September (39) Low sample volume due to equipment 17 failure.
17 November Equipment failure. Grab samples taken.
December Equipment failure. Grab samples taken.
Drinking 17 November Equipment failure. Grab samples taken.
Water 17 December Equipment f ailure. Grab samples taken.
TLD 49 September TLD missing from the site.
Table 12 - 1992 Environmental Sampling Program Exceptions ,
35
Summary of Table 10 Airborne gross beta activity measured in air particulate samples collected at indicator locations around VCSNS were consistent with preoperational levels and not statistically different from control locations. Mean prec,perational control and indicator levels were 2.9E-2 and 3.0E-2 pCi/m3, respectively. Mean indicator and control location measurements during 1992 were 1.8E-2 and 1.8E-2 pCi/m3, respectively. The highest site specific mean activity was measured at indicator location no.14 (Dairy,6.3 mi, W) to be 1.9E-2 pCi/m3. A comparison was performed between the 1992 results and the mean for the previous operational results. No statistically significant trends were observed. The results indicate that operation of VCSNS has not resulted in detectable increases of airborne gross beta activity in the environment.
Gamma spectroscopy measurements of air particulate samp!?s and activated charcoal cartridges support the gross beta activity trend. Only natural background activities of Be-7, Ra-226 and K-40 were detected. Minimum detectable activity (MDA) levels for Cs-134, Cs-137 and 1-131 were 2.5E-3, 2.7E-3 and 5.1E-2 pCi/m3, respectively. The results support the gaseous effluent release data reported in the 1992 Semiannual Effluent and Waste Disposal Reports for VCSNS. Dunng 1992 only 2.14E-4 Ci of iodine were released. These releases are not discernible in atmospheric samples due to atmospheric dispersion during the releases.
Environmental dosimetry measurements during 1992 did not differ significantly from preoperational measurements when compared. Indicator and control dosimetry measurements also showed no appreciable differences during 1992. Comparison with other operational years shows no statistically significant difference. Sampling location no. 55 at St. Barnabas Church near Jenkinsville (2.8 mi, E) was the indicator location showing the highest mean exposure rate of 10.0 pR/hr.
This value compares favorably with t1e mean exposure rate of 14.0 pR/hr measured during the preoperational period and confirms the long-term stability- of background levels measured at this monitoring location. Gaseous effluent release data reported for 1992 indicated a total of 3.38E+2 Ci of fission and activation gases released from VCSNS. An extensive search of environmental dosimet'y data and '
meteorological data during the release periods indicated no evidence of detectable activity attributable to the releases with only natural background variations evidenced.
Gamma spectrosco ay measurements of surface water samples did not indicate the presence of activatec corrosion or fission products above the respective MDA's (MDA's are maintained below required LLD's). Liquid effluent release data reported t for 1992 in the Semiannual Effluent and Waste Disposal Reports indicated a total of 2.23E-1 Ci of measurable fission and activated corrosion product activity were released from VCSN5; a level not discernible in surface water due to dilution available during the releases and the detection limits of analytical methods used during gamma spectroscopy analysis.
Tritium analyses of surface water samples during 1992 yielded results which were not statistically significant from preoperational data. The highest mean ,
indicator tritium activity of 5.1E+2 pCi/ liter was measured at Site 21, Parr Reservoir -l (2.7 mi SSW). Activity levels measured at the indicator locations are within the normal background variation for environmental tritium and consistent with the preoperational mean of 1.4E+3 pCi/ liter and the mean of previous operational' years. Total tritium released in liquid effluents during 1992 was reported to be 36
6.08E +2 Ci; a level not discernible in surface water due to dilution available during the releases and the detection limitations of analytical equipment used for tritium analysis.
Gamma spectroscopy measurements of ground water samples did not indicate the presence of activated corrosion or fission products above the MDA's for the respective radionuclides. High background levels of Pb-214 and Bi-214, daughters of Ra-226, were again detected at control sampling location no.16 (28 mi, W). The presence of these radionuclides is attributed to the uranium found in granite in this ,
area of South Carolina. The radionuclides Pb-214 and Bi-214 are major gamma emitting daughters in the uranium series decay scheme produced through the decay '
of dissolved Rn-222 gas in the ground water. As in previous years, no evidence of radioactivity from VCSNS operation was detected.
Tritium analyses of ground water samples during 1992 showed no statistically significantly trend from preoperational results or previous operational history.
Differences were not observed between control and indicator location. All values '
were reported less than the MDA.
Gamma spectroscopy measurements of drinking water samples collected from the Jenkinsville and Columbia water supplies did not indicate the presence of activated corrosion or fission product activity above the MDA's of the respective radionuclides. Naturally occurring radionudides, Ra-226, Pb-214 and Bi-214, were ,
observed in the Jenkinsville water supply at levels above those found in surface !
water. These elevated activity levels were also observed in the preoperational :
program and are attributed to several deep water wells.
Gross beta activity in drinking water at site 28 (Jenkinsville) showed a slight increase to 5.5E0 pCi/l from 4.0 pCi/f. This amount is not significantly different from I preoperational, control or previous operational results. -
All drinking water tritium analyses were below MDA's.
Gamma spectroscopy measurements of milk samples collected in 1992 were not significantly different from those observed during the preoperational program or previous operational years. Naturally occurring K-40 and Ra-226 along with Cs-137 attributed to fallout, were detected at both sampling locations at ,
concentrations similar to those measured during the preoperational period. There were no identified radionuclides in milk attributed to VCSNS operation. :
Consistent with gamma spectroscopy measurements of milk samples, gamma spectroscopy measurements of grass (forage) samples collected in 1992 indicated the -
presence of K-40 in all samples. The naturally occurring radionuclides Be-7 and K-40 were detected at levels similar to those found during the preoperational program and previous operational results. Cs-137 attributed to fallout was found at both .
indicator and control locations. There was no indication of the presence of any i radionuclide in grass due to the operation of VCSNS.
Broadleaf vegetation collected from gardens at location numbers 6,7 and 18 .
were the principal food products analyzed during 1992. Naturally occurring .
contributions from Ra-226, K-40, Ac-228 and Be-7 were measured. All radionuclide ,
measurements are comparable to results obtained during the preoperational ;
program and previous operational years.
i 37 i
s .. , ,
Other vegetation sampled in 1992 included squash, corn, tomatoes and turnips representing the non-leafy vegetation group. Naturally occurring K-40 was observed m all samples at concentrations consistent with those observed during the preoperational period.
Fish species sampled at three indicator and one control location included bass, bream, shad, catfish and carp. Cesium-137 was detected in 18 of 32 samples collected at all sampling locations including the control location. The highest mean ,
Cs-137 concentration was 1.3E+1 pCi/kg (Recreation Lake, Site #24,5.5 mi, N). A single sample with detectable Co-60 (5.1E+1 pCi/kg) was observed from Site #21, Parr Reservoir. The levels of Cs-137 in both control and indicator locations were consistent with preoperational levels and other operational years and are primarily !
attributed to residual fallout. The presence of Co-60 is primarily attributed to liquid effluent releases during 1992 which included a total of 5.0E-2 Ci of Co-60. Liquid effluent releases are assumed to also contribute to the presence of Cs-137. However, this contribution is not discernible from the levels of Cs-137 present due to fallout. t Liquid effluent releases during 1992 included 8.6E-3 Ci of Cs-137. The presence of Cobalt-60 and Cesium-137 attributed to liquid effluent releases from VCSNS would be limited to Parr and Monticello Reservoirs. Assuming an individual consumes 21 kg of fish per year containing 51 pCi/kg Cobalt-60, the maximum organ dose would be 0.04 mrem / year.
Gamma spectroscopy measurements of sediment samples collected during 1992 also indicated the presence of activated corrosion and fission product activity. ,
Cesium-137 was detected in sediment from all indicator and control locations.
Cobalt-58 activities were less than LLD at all locations. The highest mean activity for Cs-137 was 3.4E+2 pCi/kg found at the Monticello Reservoir. Cobalt-60 was detected in sediment from both Parr and Monticello Reservoirs with the highest .
mean activity observed at Monticello Reservoir (1.5E2 pCi/kg). Cs-134 and Mn-54 were only detected in two separate samples. One sample obtained from Parr ,
Reservoir had detectable Cs-134 activity of 2.1E1 pCi/kg. One sample obtained from :
Monticello Reservoir had detectable Mn-54 activity of 6.3E1 pCi/kg. Naturally occurring K-40 was consistent with preoperational, control measurements and operational values. Naturally occurring U-235 was also detected in sediment '
collected at all sampling locations at levels consistent with preoperational values and with previous operational values. Cs-137 levels in sediment at indicator locations-were higher than controls during 1992 by an average of 90 pCi/kg. Elevated levels of Cs-137 in sediment have been observed since 1988 and can be attributed to VCSNS operation. Cesium-134 activity may be attributed to liquid effluent releases from VCSNS. Activated corrosion product activity sediment detected in Parr and Monticello Reservoirs is attributed to liquid effluent releases from VCSNS. The relatively low activity in Monticello Reservoir is attributed to the injection of the liquid waste stream directly into the penstocks during FPSF's generatmg mode and !
subsequent operation of the reversible pump-turbine units during penods of off- !
peak power demand.
Radiation doses to man, corresponding to the concentrations of activity in sediment, were calculated using Regulatory Guide 1.109 methodology. A 500_ ;
hr/ year exposure to shoreline sediment containing mean detected concentrations of !
Co-60, Cs-134 and Mn-54, a shoreline width of 1, and a sediment mass of 40 kg/m2, was assumed. The results are included in Table 13 and show a maximum dose to the .
public from contaminated sediment to be 5.7E-2 mrem based on sediment samples
, from Monticello Reservoir. The average calculated dose to the public from '
contaminated sediment in the Broad River is 2.2E-2 mrem.
38
l Corresponding Calcu-l lated Annual Dose Location Radionuclide Activity (pCi/kg) Equivalent (mrem)
{
Maximum Mean Whole Body Monticello Mn-54 6.28 E + 1 6.28E + 1 7.3 E-3 Reservoir Co-60 2.1 E + 2 1.46E + 2 5.0E-2 ,
Total --- ---
5.7 E-2 Parr Reservoir Co-60 7.44 E + 1 5.10E + 1 1.7 E-2 ,
Cs-134 2.11 E + 1 2.11 E + 1 5.1 E-3 Total --- ---
2.2 E-2 Table 13 - 1992 Activated Corrosion Product and Cs-134 Activity in Sediment ,
Conclusion !
As in previous years of VCSNS operation, the presence of fission product activity attributed to residual fallout from atmosphenc weapons testing and the Chernobyl accident were detected in environmental media including fish, milk and l sediment. .
No detectable fission or activation product activity attributed to VCSNS operation was observed in environmental media except for sediment samples from s
Monticello and Parr Reservoir and one fish sample obtained from Parr Reservoir.
Radiation dose received by the maximum exposed individual (0.08 mrem maximum organ), calculated using average results from environmental samples and very conservative assumptions, is a small fraction of the observed variation in natural .
background and a small fraction of VCSNS effluent dose limits. The absence of an i impact was expected since, historically, releases from VCSNS have been a small ,
fraction of Technical Specification and ODCM Specification limits. The dose calcu- ;
lated for the maximally exposed individual will not result in observable effect on the !
ecosystem or general public. The results of the Radiological Environmental i i Monitoring Program therefore substantiate the continuing adequacy of source i control at VCSNS and conformance of station operation to 10 CFR 50, Appendix I design objectives. ,
l !
b l
j 39 l
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RC-93-0116, Radiological Environ Monitoring Rept for VC Summer Nuclear Station for Operating Period 920101-1231

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RC-93-0116, Radiological Environ Monitoring Rept for VC Summer Nuclear Station for Operating Period 920101-1231

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