ML20153C626

Annual Radiological Environ Surveillance Rept,CY87

ML20153C626
Person / Time
Site:	Vogtle
Issue date:	12/31/1987
From:	GEORGIA POWER CO.
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NUDOCS 8805060266
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Georgia Power d ENCLOSURE PLANI V0GTLE - UNIT 1 HRC DOCKET 50-424 OPERATING LICENSE IlPF-68 ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT CALENDAR YEAR 1987 8805060266 880429 DR ADOCK 0500 4

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T GEORGIA POWER COMPANY V0GTLE ELECTRIC GENERATING PLANT i

ANNUAL RADIOLOGICAL ENVIRONMENTAL: SURVEILLANCE REPORT CALENDAR' YEAR 1987 NRC 00CKET NO. 50-424 4

NRC OPERATING LICENSE NO. NPF-68 l

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V0GTLE ELECTRIC GENERATING PLANT l

RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT TABLE OF CONTENTS i

SECTION TITLE PAGE 1

1.0 I NTROD UCTION......................

1 -1 t

2.0

SUMMARY

DESCRIPTION......-............

2-1 3.0 RESULTS

SUMMARY

....................3-1 i

4 4.0 DISCUSSION OF RESULTS

.................4-1 4.1 Airborne......................

4-3 4.2 Direct Radiation

..................4-5 i

4.3 Milk........................

4-7 4.4 Yegetation.....................4-8 4.5 Ri ve r Wate r.....................

4-10 4.6 O ri nki ng Wate r....................

4-11 1

4.7 Fish........................4-12 4.8 Sediment......................4-13 p

5.0 INTERLABORATORY COMPARISON PROGRAM,..........

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6.0 CONCLUSION

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i APR 2 91988

o TABLE OF CONTENTS (Continued)

LIST OF TABLES l

TABLE TITLE PAGE 2-1 SUtHARY DESCRIPTION OF RADIOLOGICAL 2-2 thru 2-6 ENVIRONMENTAL MONITORING PROGRAM 2-2 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS 2-7 thru 2-9 3-1 RADIOLOGICAL ENVIRONMENTAL 3-2 thru 3-12 MONITORING PROGRAM ANNUAL SUPNARY 4-1 LAND USE CENSUS RESULTS 4-2 5-1 CROSSCHECK PROGRAM RESULTS FOR AIR FILTERS 5-2 5-2 CROSSCHECK-PROGRAM RESULTS FOR MILK SAMPLES 5-3 5-3 CROSSCHECK PROGRAM RESULTS FOR WATER SAMPLES 5-4 thru 5-5 11 APR 2 9 29 l

TABLE OF CONTENTS (Continued)

LIST OF FIGURES FIGURE TITLE PAGE 2-1 TERRESTRIAL STATIONS NEAR SITE BOUNDARY 2-10 2-2 TERRESTRIAL STATIONS BEYOND SITE BOUNDARY 2-11

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OUT TO APPROXIMATELY FIVE MILES ANO l

AQUATIC STATIONS J

2-3 TERRESTRIAL STATIONS BEYOND FIVE MILES 2-12 2-4 DRINKING WATER STATIONS 2-13 4

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APR 2 9 988 1

ACRONYMS CSRA Central Savannah River Area EPA Environmental Protection Agency GE Greater Than or Equal to GPC Georgia Power Company LLD Lower Limit of Detection LT Less Than MDD Minimum Detectable Difference NA Not Applicable.

NDM No Detectable Measurement NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual OLSER Operating License Stage Environmental Report REMP Radiological Environmental Monitoring Program RL Reporting Level s

Standard Deviation SRP Savannah River Plant TLD Thermoluminescent Dosimeter TS Technical Specifications for Unit 1 YEGP Vogtle Electric Generating Plant iv APR 2 9 M)39

o V0GTLE ELECTRIC GENERATING PLANT RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT

1.0 INTRODUCTION

This is the initial annual Radiological Environmental Surveillance Report for the Vogtle Electric Generating Plant (VEGP).

It covers activities of the operational phase of the Radiological Environmental Monitoring Program (REMP) during calendar year 1987.

Hence all dates in this report are for the year 1987 unless othemise indicated.

Activities of the preoperational phase of the REMP which began in 1981 and extended into 1987 are documented in the Preoperational Radiological Environmental Surveillance Report.

The objective of the REMP is to ascertain the levels of radiation and the concentrations of radioactivity in the environs of the VEGP and to evaluate any radiological impact to the environment due to plant operations. A comparison between the results obtained during the preoperational and operational phases provides some basis for such an evaluation. A comparison between the results obtained at control stations (locations where radiological levels are not expected to be significantly affected by plant operations) and at indicator stations (locations where it is anticipated that radiological levels are more likely to be affected by plant operations) provides a further bas'; for the evaluation.

The specifications for the operational phase of the REMP are provided by Section 3/4.12 of the Technical Specifications for Unit 1 (TS) while the specifications for the preoperational phase were provided by Section 6.1.5 of the Operating License Stage Environmental Report (0LSER).

The transition from the preoperational phase to the operational phase hinged about initial criticality for Unit I which occurred on March 9.

Practical considerations regarding sample collections (type, schedule and composite period) and radioactive effluent releases (type, composition, date of initiation and magnitude) rendered a need for some flexibility in detemining the demarcation date for each type sample.

The release of radioactive gases at measurable levels was initiated on fiarch 20.

All of the gaseous releases during the first quarter were due to the venting of waste gas tanks; a total of only 16.7 microCuries of short lived (half lives less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />) noble gases were released.

There were no gaseour' releases of iodines, particulates or tritium during the first quarter. Because the gaseous releases during the first quarter could be considered as trivial and innocuous, the demarcation date for the samples which monitor gaseous releases - dust filters, charcoal cartridges, themoluminescent dosimeters (TLDs), milk and vegetation - was deemed to be the end of the first quarter.

The only samples that could have been affected by the first quarter gaseous releases were the TLDs. This demarcation date also fit neatly with sampling schedules and compos.' ting periods.

1 -1 tm 29 M9

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Although the quantity of radioactive liquids released during the first quarter was small, it might be considered more than trivial.

For each 4

of the samples which monitor liquid releases (river water, drinking water, fish and sediment) the demarcation date is deemed to be the last i

collection date before initial criticality.

A summary description of the (operational phase of the) REMP is provided in Section 2.

This includes maps showing the sampling locations; the maps are keyed to a table indicating the distance and direction of each sampling location from a point midway between the two reactors, A summary of the main laboratory analysis results obtained from the samples utilized for environmental monitoring for this report period is presented in Section 3.

A discussion of the results including assessments of any radiological impacts upon the environment is provided i

in Section 4.

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The results of the Interlaboratory Comparison Program are presented in Section 5.

The chief conclusions are stated in Section 6.

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SUMMARY

DESCRIPTION A summary description of the (operational phase of the) REMP is provided in Table 2-1.

This table portrays the program in the manner by which it is being regularly carried out; it is essentially a copy of Table 3.12.1-1 of the TS which delineates the program's requirements.

Sampling locations specified by Table 2-1 are described in Table 2-2 and are shown on maps in Figures 2-1 through 2-4.

This description of the sample locations closely follows that found in the table and figures of Section 3.0 of the Offsite Dose Calculation Manual (00CM).

It is stated in Footnote (1) of Table 3.12-1 of the TS that deviations are permitted from the required sampling schedule which is delineated in Table 2-1 herein, if specimens are unobtainable due to circumstances, such as, hazardous conditions, seasonal uhavailability, and malfunction of sampling equipment. Any deviations are accounted for in the discussions for each particular sample type in Section 4.

During 1987, all the laboratory analyses except for the reading of the TLDs were performed by Georgia Power Company's (GPC's) Central Laboratory in Smyrna, Georgia.

The reading of the TLDs was provided by Teledyne Isotopes Midwest Laboratory in Northbrook, Illinois.

The Center for Applied Isotope Studies at the University of Georgia in Athens, Georgia, which provided much of the laboratory analyses during the preoperational phase of the REMP, now serves as a backup laboratory to the Central Laboratory, a

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TABLE 2-1 (SHEET 10F 5) l

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l

EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND TYPE AND FREQUENCY l

AND/OR SAMPLE AND SAMPLE LOCATIONS COLLECTION FREQUENCY OF ANALYSIS

1. Direct Radiation (l)

Thirty-eight routine monitoring Quarterly Gamma dose quarterly stations with two or more dosimeters placed as follows:

An inner ring of stations, one in each meteorological sector in the general area of the site boundary; An outer ring of stations, one in O'

each meteorological sector in the 6 mile range from the site; and The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.

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TABLE 2-1 (SHEET 2 0F 5) i SUl#MRY DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAWLES SAWLING AND TYPE AND FREQUENCY AND/OR SAWLE AND SAMLE LOCATIONS COLLECTION FREQUENCY OF ANALYSIS

2. Airborne i

Radiofodine and Samples from seven locations Continuous sampler oper-Radioiodine Cannister:

Particulates ation with sample collec-I-131 analysis weekly.

tion weekly, or more l

Five samples from close to the frequently if required by l

five site boundary locations, dust loading Particulate Sampler:

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in different sectors; Gross beta radioactivity analysis folloy{ng filter change;L i and y

gaena i ggpic w

analysis 3 of composite (by location) quarterly.

One sample from the vicinity of I

I a community having the highest calculated annual average ground-level D/Q; and One sample from a control location, as for example a population center 10 to 20 miles distant and in the least prevalent wind direction.

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TABLE 2-1 (SHEET 3 0F 5)

SUMMARY

DESCRIPTION GF RADIOLOGICAL ENVIRONMENTAL NONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMLES SAWLING AND TYPE AND FREQUENCY AND/0R SAWLE AND SAW LE LOCATIONS COLLECTION FREQUENCY OF ANALYSIS

3. Waterborne

a. SurfaceI4)

One sample upriver Composite sampi over Ganuma isotopic analysis (3) 1-month periodi I

monthly. Composite for Two samples downriver tritium analysis quarterly. 4

b. Drinking Two samples at each of the two Composite sample of I-131 analysis on each nearest water treatment plants river water near intake sample when the dose that could be affected by plant at each water treatment calculated for the di scharges.

plant 9yer 2-week consumption of the water is :

7 periodtM when I-131 Two samples at a control analysis is perforined, yearg(3than 1 mres per grea Composite for location.

monthly composite other-gross beta and g wise; and grab sample of isotopic analyses finished water at each monthly. Composite for water treatment plant tritturi analysis quarterly.

every 2 weeks or monthly, as appropriate.

c. Sediment from One sample from downriver area Semiannually Gamuna isotopic analysis (3)

Shorelfr.e with existing or potential semiannually.

recreational value.

One sample from upriver area with existing or potential recreational value.

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l TABLE 2-1 (SHEET 4 0F 5) l SIM ERY DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMLES SAMLING AND TYPE AND FREQUENCY AND/0R SAM LE AND SAMLE LOCATIONS COLLECTION FREQUENCY OF ANALYSIS.

4. Ingestion

a. Milk Two samples from milking animalsI7)

Biweekly Gesuna is9gog{Jc at control locations about 10 miles analysist

.O biweekly distant or beyond and preferably in a wind direction of lower prevalence.

b. Fish At least one sample of any commer-Semiannually Gasuna isotopic analysisI3) cially or recreationally fraportant on edible portions species in vicinity of plant semiannually m

4, discharge area.

l At least one sample of any species in areas not influenced by plant discharge.

At least one sample of any During spring spawning anadromous species ir. vicinity of season.

j plant discharge.

c. Grass or Leafy One sample from twe onsite locations Monthly during growing Gasuna i go{Jmonthly c

Vegetation near the site bour.dary in different

season, analysis sectors.

One sample from a location that yielded a calculated dose conunitment 20% greater

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than site boundary locations.

l One sample from a control location rx; at about 15 or more miles distance.

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TABLE 2-1 (SHEET 5 0F 5)

TABLE NOTATIONS (1)

One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a TLO is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.

Film badges shall not be used as dosimeters for measuring direct radiation.

(2)

Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay.

If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be perfomed on the individual samples.

(3)

Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

(4)

The "upriver sample" shall be taken at i distance beyond significant influence of the discharge.

The "downriver" sanple shall be taken in an area beyond but near the mixing zone.

(5)

Composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g.,

monthly) in order to assure obtaining a representative sample.

(6)

The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

(7)

A milking animal is a cow or goat producing milk for human consumption.

(8)

If gamma isotopic analysis is not sensitive enough to meet the Lower i

Limit of Detection for I-131, a separate analysis for 1-131 will be performed.

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TABLE 2-2 (SHEET 10F 3)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Station Station Descriptive Direction (2) Distance (2)

Sample Number Type (1) location (miles)

Type (3) l 1

I Hancock Landing Road N

1.1 0

2 I

River Bank NNE 0.8 0

3 I

Discharge Area NE 0.6 A

3 I

River Bank NE 0.7 0

4 I

River Bank ENE 0.8 0

5 I

River Bank E

1.0 0

6 I

Plant Wilson ESE 1.1 0

7 I

Simulator Building SE 1.7 D,V,A 8

I River Road SSE 1.1 0

9 I

River Road S

1.1 0

10 I

Met Tower SSW 0.8 A

10 I

River Road SSW 1.1 D

11 I

River Road SW 1.2 0

12 I

River Road WSW 1.1 0,A 12 I

Trailer Park WSW 1.3 V

13 I

River Road W

1.3 0

14 I

River Road WNW 1.8 D

15 I

Hancock Landing Road NW 1.5 0,Y t

16 I

Hancock Landing Road NNW 1.4 0,A 17 0

Savannah River Plant River Road N

5.4 D

18 0

Savannah River Plant D Area NNE 5.0 0

19 0

Savannah River Plant Road A.13 NE 4.6 0

20 0

Savannah River Plant Road A.13.1 ENE 4.8 0

21 0

Savannah River Plant Road A.17 E

5.3 0

j 22 0

River Bank Downstream of Buxton Landing ESE 5.2 0

23 0

River Road SE 4.7 0

24 0

Chance Road SSE 4.9 0

25 0

Chance Road and Highway 23 S 5.2 0

26 0

Highway 23, mile 15.5 SSW 4.6 0

27 0

Highway 23 mile 17 SW 4.8 D

28 0

Claybon Road WSW 5.0 0

29 0

Claxton-Lively Road W

5.0 0

30 0

Nathaniel Howard Road WNW 5.0 0

31 0

River Road at Allen's Church Fork NW 5.0 0

32 0

River Bank NNW 4.8 0

33 0

Nearby Permanent Residence SE 3.3 0

34 0

Girard Elementary School SSE 6.3 D

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TABLE 2-2 (SHEET 2 0F 3) l i

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS l

I Station Station

. Descriptive Direction (2) Distance (2)

Sample Number Type (1) location (miles)

Type (3) l

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35 0

Girard SSE 6.6 D,A

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Waynesboro WSW 14.9 D,A i

37 C

Substution (Waynesboro)

WSW 17.5 D,Y i

43 0

Employees Recreation Area SW 2.2 0

f 80 C

Augusta Water Treatment i

Plant NNW 24.5 W(4)

I 81 C

Savannah River N

2.2 F(5),S(6) 82 C

Savannah River (RM 151.2)

NNE 0.8 R

83 I

Savannah River (RM 150.6)

ENE 0.8 R,S(6)

-i 84 0

Savannah River (RM 149.5)

ESE 1.6 R

85 I

Savannah River ESE 5.0 F(5) 87 I

Beaufort-Jasper County i

Water Treatment Plant; a

Beaufort, SC SE 76 W(7) 3 88 I

Cherokee Hill Water Treatment Plant; j

Port Wentworth, GA SSE 72 W(8) 98 C

W. C. Dixon Dairy SE

9. 8 H

99 C

Boyceland Dairy W

24.5 M

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i TABLE NOTATION:

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(1)

Station Types C - Control l

I - Indicator 0 - Other (2)

Direction and distance are reckoned from a point midway between the two 1

reactors l'

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(3)

Sample Types A - Airborne Radioactivity i]

D - Direct Radiation l

4 F - Fish M - Milk R - River Water i

S - River Shoreline Sediment W - Drinking Water (at water treatment plant)

Y - Vegetation i

(4)

The intake for the Augusta Water Treatment Plant is located on the t

i Augusta Canal. The entrance to this canal is at River Mile (RM) 207 on l

the Savannah River.

The canal effectively parallels the river. The intake to the pumping station is 3.6 miles down the canal and only a j

tenth of a mile across a narrow neck of land to the river.

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TABLE 2-2 (SHEET 3 0F 3)

RADIOLOGICAL ENVIRONMENTAL CAMPLING LOCATIONS l

TABLE NOTATIONS (Continued) 4 (5)

About a five mile stretch of the river is generally needed to obtain adequate fish samples. Samples are normally gathered between RM 153 and 158 for upriver collections and between RM 144 and 149.4 for downriver collections, j

(6)

Sediment is collected at locations with existing or potential recreational value. Because high water shifting of the river bottom or other reasons could cause a suitable location for sediment collection to become unavailable or unsuitable, a stretch of the river between RM 4

l 149.7 and 150.7 is designated for downriver collections while a stretch 1

between RM 153 and 154 is designated for upriver collections.

In j-practice, collections are normally made at RM 150.2 for downriver cellections and at RM 153.2 for upriver collections.

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(7)

The intake for the Beaufort-Jasper County Water Treatment Plant is l

l locate 3 at the end of a canal which begins at RM 39.2 on the Savannah River.

This intake is about 16 miles by line of sight down the canal from its beginning on the Savannah River.

(8)

The ' intake for the Cherokee Hill Water Treatment Plant is located on i

Abercorn Creek which is about one and a quarter creek miles from its i

i mouth on the Savannah River at RM 29.

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/mrts TERRESTRIAL STATIONS

' "' "^ 'i N PLANT BEYOND 5 MILES

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UNIT 16 ND UNIT 2 FIGURE 2-3 mR 2 9 n^o 433 9 2-12

h AUGUSTA WATER TREATMENT PLANT 80 SAVANNAH river PLANT VEGP (

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Weser to seeveert I'

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PLANT 4

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vooTLE ORINKING WATER STATIONS ELECTRIC GENE RATING PLANT Georgia Power unit uNo unit FIGURE 2-4

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3.0 RESULTS

SUMMARY

In accordance with Section 6.8.1.3 of the TS, summarized and tabulated results of all of the regular radiological environmental samples and radiation measurements taken during the report period at the designated indicator and cuntrol stations are presented in Table 3-1 in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November,1979.

Naturally occurring radionuclides which are not included in the plant's effluents are nct required to be reported: Of particular note is naturally occurring Be-7 which is produced in the VEGP reactor and is released in the liquid effluents; its levels were closely watched in the samples which monitor liquid effluents - river water, drinking water, fish and sediment.

Results for samples collected at locations other than indicator or control stations or in addition to those stipulated by Table 2-1 are included in Section 4, the discussion of results section, for the type sample.

3-1 rno o o in-e

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nt TABLE 3-1 (SHEET 10F 11) i i

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM. ANNUAL SUM 4ARY Vogtle Electric Generating Plant, Docket No. 50-424 i

Burke County Georgia, Report Period 1987 (a)

Medium or Type and Lower Limit All Indicator Location with Highest Control Locations Number of -

l Pathway Sampled Total Number of Locations Annual Mean Mean (c)

-Nonroutine.

(Unit of of Analyses Detection (b)

Mean (c)

Name Mean (c)

-Range Reported Measurement)

Performed (LLO)

Range Distance &

Range

-(Fraction) i

{

(Fraction)

Direction (Fraction)

Measurements h

Airborne Gross Beta 10 26.3 No. 10 27.8 23.6 0

i Particulates 234 5-21 3 Met Tower 11-213 14-37 i

(fCi/m3)

(195/195) 0.8 miles (39/39)

(39/39)

SSW 3

Gamma Isotopic i

18 I

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Cs-134 50 NDM(d)

NDM NDM 0

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Cs-137 50-8.0 No. 10 12.9 NDM 0

i 1.7-12.9 Met Tower 12.9-12.9 (6/15) 0.8 miles (1/3)

SSW Airborne I-1 31 70 NDM NDM NDM 0

Radioindine 234 i

(fCi/m3) s 4 Direct Gamma Dose NA(e) 17.6 No. 1 23.7 "17.9l 0

I Radiation 54 13.1-24.3 Han Lan Rd.

22.9-24.3 15.4-20.0

V (mrem /91 dys)

(48/48) 1.1 miles-(3/3)

(6/6)

)o y

l?,

TABLE 3-1 (SHEET 2 0F 11)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket No. 50-424 Burke County, Georgia, Report Period 1987 (a)-

tiedium or Type and Lower Limit All Indicator Location with Highest Control Locations Number of Pathway Sampled Total Number of Locations Annual Mean Mean (c).

Nonroutine (Unit of of Analyses Detection (b)

Hean (c)

Name Mean (c)

Range Reported Measurement)

Performed (LLD)-

Range Distance &

Range

_(Fraction)

Measurements :

(Fraction)

Direction (Fraction)

Milk Gamma Isotopic (pCi/1) 39 Zn-65 30(f)

NA No. 99 25 25 0

l u, Boyceland 25-25 25-25

' J, 24.5 miles (1/20)

(1/39) l Cs-134 15 NA NDM NDM 0

Cs-137 18 HA No. 98 10.8 10.4 0~

Dixon Dairy 10.8-10.8 9.9-10.8 9.8 miles (1/19)

(2/39)

SE Ba-140 60 NA NDM NDM La-140 15 NA NDM NDM 0

I-1 31 1

NA NDM NDM 0

39 w

n>

(O

]a

TABLE 3-1 (SHEET 3 0F 11)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket No. 50-424 Burke County, Georgia, Report Period 1987 (a) i Medium or Type and Lower Limit All Indicator Location with Highest Control Locations Number of 3

l Pathway Sampled Total Number of Locations Annual Mean Mean (c)

Nonroutine (Unit of of Analyses Detection (b)

Mean (c)

Name Mean (c)

Range Reported Measurement)

Performed (LLD)

Range Distance &

Range (Fraction)

Measurements (Fraction)

Direction (Fraction)

Grass Gamma Isotopic (pCi/kg wet) 30 I-1 31 60 NDM NDM NDM 0

Cs-134 60 NDM NDM NDM 0

u, 1

Cs-137 80 24.4 No. 37 61. 5 61. 5 0

11.1-44.4 Substation 38.0-85.0 38.0-85.0 (7/22) 17.5 miles (2/8)

(2/8) i WSW River Water Gamma Isotopic (pCi/1) 20 Be-7 80(g)

NDM NDM NDM 0

Mn-54 15 NDM NDM NDM 0

Fe-59 30 NDM NDM NDM 0

Co-58 15 NDM NDM NDM 0

i$

m DJ US sn

o i

f TABLE 31 (!!iEET 4 0F 11)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL SUtNARY l

Vogtle Electric Generating Plant, Docket No. 50-424 Burke County, Georgia, Report Period 1987 (a) l Medium or Type and Lower Limit All Indicator Location with Highest Control Locations Number of Pathway Sampled Total Number of Locations Annual Mean Mean (c)

Nonroutine I

(Unit of of Analyses Detection (b)

Mean (c)

Name Mean (c)

Range Reported l

Measurement)

Perfomed (LLD)

Range Distance &

Range (Fraction)

Measurements j

(Fraction)

Direction (Fraction) l Co-60 15 NDM NDM NDH 0

Zn-65 30 NDM NDM NDM 0

l Zr-95 30 NDM NDM NDM 0

l l"4 Nb-95 15 NDM NDM NDM 0

I-131 15 NDM NDM NDM 0

Cs-134 15 NDM NDM NDH 0

Cs-137 18 NDM NDM NDM 0

Ba-140 60 HDM NDM NDH 0

La-140 15 NDM NDM NDM 0

Tritium 3000 680 No. 83 6P.0 524 0

8 391-1010 Downriver 391-1010 465-622 (4/4) 0.3 miles (4/4)

(4/4) l W

00 (O

Tz s

O TABLE 3-1 (SHEET 5 0F 11)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Yogtle Electric Generating Plant, Docket No. 50-424 ggy Burke County, Georgia, Report Period 1987 (a)

Medium or Type and Lower Limit All Indicator Location with Highest Control Locations Number of Pathway Sampled Total Number of Locations Annual Mean Mean (c)

Nonroutine (Unit of of Analyses Detection (b)

Mean (c)

Name Mean (c)

Range Reported Measurement)

Performed (LLD)

Range Distance &

Range (Fraction)

Measurements (Fraction)

Direction

' Fraction)

Water Near Gross Beta 4

2.2 No. 80 5.5

5. 5 0

Intakes to Water 30

1. 0-3. 7 Augusta 1.3-15.5 1.3-15.5 Treatment Plants (20/20)

Upriver (10/10)

(10/10)

}'(pCi/l) 56 miles Gamma Isotopic 30 Be-7 80(g)

NDM NDM NDM 0

Mn-54 15 NDM NDM NDM 0

Fe-59 30 NDM NDM NDM 0

Co-58 15 NDM NDft NDM 0

Co-60 15 NDM NDM NDM 0

Zn-65 30 NDM NDM NDM 0

Zr-95 30 NDM NDM NDM 0

7 d$

Nb-95 15 NDM NDM NDM 0

n, to 3

~

TABLE 3-1 (SHEET 6 0F 11)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Yogtle Electric Generating Plant, Docket No. 50-424 Burke County, Georgia, Report Period 1987 (a)

Medium or Type and Lower Limit All Indicator Location with Highest Control Locations Number of Pathway Sampled Total Number of Locations Annual Mean Mean (c)

Nonroutine (Unit of of Analyses Detection (b)

Mean (c)

Name Mean (c)

Range Reported Measurement)

Performed (LLD)

Range Distance &

Range (Fraction)

Measurements (Frac tion)

Direction (Fraction) a 1

1-1 31 15 NDM NDM NDM' 0

Cs-134 15 NDM NDM NDM 0

Cs-137 18 NDM NDM NDM 0

Ba-140 60 NDM NDM NDM 0

La-140 15 NDM NDM NDM 0

1 Tritium 3000 2229 No. 88 2345 316' 0

12 1190-2840 Port Wentworth 1620-2840 205-433 (8/8)

Downriver (4/4)

(4/4) 122 miles Finished Water at Gross Beta 4

2.1 No. 88 2.4 1.8 0

l Water Treatment 30 1.2-4.3 Port Wentworth 1.2-4.3 1.4-2.6 Plants (20/20)

Downriver (10/10)

(9/10) l (pCi/1) 122 miles i

j>

bb m

U3 iso

l l

l 1

TABLE 3-1 (SHEET 7 0F 11) l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Yogtle Electric Generating Plant, Docket No. 50-424 Burke County, Georgia, Report Period 1987 (a) l l

Medium or Type and Lower Limit All Indicator Location with Highest Control Locations-Number of l

Pathway Sampled Total Number of Locations Annual Mean Mean (c)

Nonroutine (Unit of of Analyses Detection (b)

Mean (c)

Name Mean (c)

Range Reported l

Measurement)

Performed (LLD)

Range Distance &

Range.

(Fraction)

Measurements l

(Fraction)

Direction (Fraction)

Gamma Isotopic l

30 l

Be-7 80(g) 68 No. 87 68 NDM 0

!Y 68-68 Beaufort 68-68 l*

(1/20)

Downriver (1/10) l 112 miles Mn-54 15 NDM NDM NDM 0

Fe-59 30 NDM NDM NDH 0

Co-58 15 NDM NDM NDM 0

Co-60 15 NDM NDM NDM 0

l Zn-65 30 NDM NDM NDM 0

Zr-95 30 NDM NDM NDM 0

l l

Nb-95 15 NDM NDM NDM 0-l 3

I-l31 15(h)

NDM NDM NDM 0

Cs-134 15 NDM NDM NDM 0

2" I

l l

e TABLE 3-1 (SHEET 8 0F ll)

RADIOLOGICAL ENVIRONMENTAL MONITCRING PROGRAM ANNUAL SUPNARY Vogtle Electric Generating Plant, Docket No. 50-424 Burke County. Gectgia, Report Period 1987 (a) 1 Medium or Type and Lower Litit All Indicator Location with Highest Control Locations Number of Pathway Sampled Total Number of Locations Annual Mean Mean (c)

Nonroutine (Unit of of Analyses Detection (b)

Mean (c)

Name Mean (c)

Range Reported Measurement)

Performed (LLD)

Range Distance &

Range (Fraction)

Measurements (Fraction)

Direction (Fraction)

Cs-137 18 NDM NDM NDM

.0 Ba-140 60 NDM NDM NDM 0

Y La-140 15 NDM NDM NDM 0

e Tritium 2000 2406 No. 88 2758 305 0

12 1300-3920 Port Wentworth 1300-3920 227-374 (8/8)

Downriver (4/4)

(4/4) 122 miles Antdromous Fish Gamma Isotopic (pCf/kg wet) 3 Be-7 100(g)

NDM NDM NA 0

Mn-54 130 NDM NDM NA 0

Fe-59 260 NDM NDM NA 0

Co-58 130 NDM NDM NA 0

h Co-60 130 NDM NDM NA 0

na O

O

-.. =

TABLE 3-1 (SHEET 9 0F 11)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL SUPNARY Yogtle Electric Generating Plant, Docket No. 50-424 Burke County, Georgia, Report Period 1987 (a)

Medium or Type and Lower Limit All Indicator Location with Highest Control Locations Number of Pathway Sampled Total Number of Locations Annual Mean Mean (c)

.Nonroutine (Unit of of Analyses Detection (b)

Mean (c)

Name Mean (c)

Range Reported Metsurement)

Perfcmed (LLD)

Range Distance &

Range (Fractien)

Measurements (Fraction)

Direction (Fraction)

Zn-65 260 NDM NDM NA 0

Cs-134 130 NDM NDM NA 0

'f Cs-137 150 10 No. 81 10 NA 0

E" 10-10 Upriver 10-10 (1/3) 2.2 miles (1/3)

Fish Gamma Isotopic (pCi/kg wet) 6 Be-7 100(g)

NDM NDM NDM 0

Mn-54 130 NDM NDM NDM 0

Fe-59 260 NDM NI M NDM 0

Co-58 130 NDM NDM NDM 0

Co-60 130 NDM NDM NDM 0

N 2)

Zn-65 260 NDM NDM NDM 0

N-(O 5

+

o TABLE 3-1 (SHEET 10 0F 11)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket No. 50-424 Burke County, Georgia, Report Period 1987 (a)

Medium or Type and Lower Limit All Indicator Location with Highest Control Locations Number of Pathway Sampled Total Number of Locations Annual Mean Mean (c)

Nonroutine (Unit of of Analyses Detection (b)

Mean (c)

Name Mean (c)

Range Reported l

Measurement)

Performed (LLD)

Range Distance &

Range (Fraction)

Measurements (Fraction)

Direction (Fraction)

Cs-134 130 NDN NDP NDM 0

Cs-137 150 337 No. 85 337 119 0

228-446 Downriver 228-446 39-178 (2/3) 3.9 miles (2/3)

(3/3)

Sediment Gamma Isotopic (pCi/kg dry) 4 Be-7 300(g) 987 No. 83 987 543 0

593-1380 Downriver 593-1380 146-940 (2/2) 0.7 miles (2/2)

(2/2)

Cs-134 150 NDM NDM NDM 0-Cs-137 180 209 No. 83 209 111 0

174-243 Downriver 174-243 94-128 (2/2) 0.7 miles (2/2)

(2/2)

T' m

n-

'O

TABLE 3-1 (SHEET 110F 11)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL SUMMAP.Y Yogtle Electric Generating Plant, Docket No. 50-424 Burke County, Georgia, Report Period 1987 (a)

TABLE NOTATIONS a.

The report period began around the time of initial criticality (March

9) but varied with sample type.

See Section 1.0.

b.

The LLD is defined in table notation 3 of Table 4.12-1 of the TS.

Except as noted otherwise, the values listed in the column are those found in that table.

c.

Mean and range are based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parenthesis, d.

No Detectable Measurements.

e.

Not Applicable, f.

This is the value listed in Table 4.12-1 of the TS for water; none was provided for milk.

g.

The Central Laboratory has determined that this value may be routinely attained.

No value was provided in Table 4.12-1 of the TS.

h.

In accordance with Item 3b of Taole 3.12-1 of the TS, an I-131 analysis was not performed on these samples since the dose calculated from the consumption of water was less than 1 mrem per year.

t 3-12

.r 7 e,,,,

4.0 DISCUSSION OF RESULTS An interpretation and evaluation, as appropriate, and an analysis of the laboratory results for each type sample are included in this section.

Relevant comparisons are made between the difference in average values for indicator and control stations and the calculated Minimum Detectable Difference (MDD) between these two groups at the 99-percent confidence level.

The MDD is determined using the standard Student's t-test. A difference in the average values which is less than the MDD is considered to be statistically indiscernible.

Pertinent results are also compared with results obtained from collections during preoperations. To provide perspective, a result might also be compared with its LLD or Reporting Level (RL). Attempts are made to explain any RLs or other high radiological levels found in the samples.

There were no failures in the laboratory analyses of each of the samples in attaining the LLDs required by Table 4.12-1 of the TS for this report period.

Extra sample collections and/or analyses were conducted on air particulate filters, milk and vegetation in response to gaseous releases from the Savannah River Plant (SRP) of tritium on July 31 and of Cs-137 during the +.hird and/or fourth weeks of November.

The results of these extraneous nnalyses are discussed in Sections 4.1, 4.3 and 4.4.

A land use census was conducted on April 27 and 28.

The locations of the nearest milk animal, residence and garden of greater than 500 square feet producing broad leaf vegetation in each of the 16 meteorological sectors within a distance of 5 miles are tabulated in Table 4-1.

Land within SRP was excluded from the census. The consequences of the results of the land use census upon sample collections are discussed in Sections 4.3 and 4.4 The results of the annual survey conducted downstream of the plant to determine whether water from the Savannah River is being used for drinking or irrigation purposes are presented in Section 4.5.

4-1

- ' c EC

_ _ _ _ _ _ - _ _ - _ - = _ _ - _ _ _ _ - __

t TABLE 4-1 LAND USE CENSUS RESULTS Distance in Miles to Nearest Locations in Each Sector SECTOR MILK RESIDENCE LEAFY ANIMAL GARDEN N

NNE NE ENE E

ESE SE 3.3 4.8 SSE 4.6 S

4.4 SSW 4.7 SW 1.3 3.1 WSW 1.2 1.3 W

1.4 4.2 WNW 1.8 4.6 NW 2.2 4.1 kNW

• None within 5 miles and outside of SRP.

4-2

/TR ' 9 1993

/

4.1 Airborne As indicated by Table 2-2, airborne particulates and airborne radioiodine are collected at 5 indicator stations (Nos. 3, 7, 10, 12, and 16) which encircle the site boundary, at a nearby community (No. 35) and at a control station (No. 36). At these locations, air is continuously drawn through a dust filter and a charcoal canister in sequence to retain airborne particulates and airborne radiofodine, respectively.

The filters and canisters are collected weekly.

Each of the air particulate filters is counted for gross beta activity. A gama isotopic analysis is perfomed quarterly on a composite of the air particulate filters for each station.

As seen in Table 3-1, the average gross beta agtivity over the report period for the indicator stations is 2.7 fCi/mJ greater than that for the control station.

However, this difference is not disgernable since it is less than the MOD which was calculated as 4.3 fCi/m.

o The gross beta activity for the samples collected on November 24 at the five indicator stations averaged several times that nomally found; for the collections on December 1, only two stations had above average readings. A gamma isotopic analysis was perfomed on each of the individual particulate filters collected on November 24 and on the individual particulate filters collected on December 1 at Stations 3 and 7 only; the fission product, Cs-137, was found to be present. The gross beta and Cs-137 levels in units of fCi/m3 were as follows.

Station Gross Beta Cs-137 11/24 12701 11/24 1 2 / 01 3 Discharge Area 107 44 98 73 7 Simulator Building 76 48 41 36 10 Met Tower 21 3 23 170 12 River Road 176 18 130 16 Hancock Landing Road 140 24 87 35 Girard 38 24 LT 13 36 Waynesboro 28 15 LT 13 Anomalous air particulate readings of the same order of magnitude were found during this period by several others in the Central Savannah River Area (CSRA) who implemert REMPs.

These high readings were due to a release from SRP.

By excluding the hign gross beta readings (those obtained from filters where a gamma isotopic analysis was perfomed), the average gross beta activity for the report period for the indicator stations is significantly reduced.

The average activities in units of fCi/m3 for the indicator stations, the community station and the control station become as follows.

4-3

.g7 4_-

y y---

y-m---e-

,,w,w i------ir-yg+

v --

vww

~, -,

-*,y-

-v-v--m-www s.

v-r--

Group Without With Exclusion Exclusion Indicator Stations 26.3 23.0 Community Station 22.7 22.3 Control Station 23.6 23.5 The average activity levels with the exclusion are believed to provide a more realistic indication of any impact of plant operations upon the environment; note that the average activity for the control station becomes higher than that for any other group.

Except for the fourth quarter, the only positive result from the gamma isotopic analyses of the quarterly composites of the air particulate filters was for the second quartgr at Station 3 where Cs-137 was measured at a level of 1.7 fCi/m3 For the fourth quarter the positive results reflected those for individual filters given above. At each station, except the contrgl station, Cs-137 was found at levels ranging from 2.1 to 12.9 fCf /mJ. The required LLD and the RL as given 3

in the TS are 60 and 20,000 fCi/m, respectively.

During the second quarter of 1986, as a consequence of the Chernobyl incident positive levels of Cs-137 were foynd at about half of the stations; the highest level found was 84 fCi/m3 Outside of the second quarter of 1986, the highest level found on a quarterly composite during preoperations was 11 fC1/md.

The charcoal cartridges used for adsorbing iodine from the atmosphere are analyzed for I-131 by gamma spectroscopy.

1-131 was not detected in any of the samples during the report period.

The maximum allowed LLD is 70 fCi/m3; however, the LLD usually attained was about a third or a fourth of this value.

A-4 IJ:R : ? G:'

4.2 Direct Radiation Direct (external) radiation is measured by TLDs.

A TLD badge is placed at each station; each badge contains 4 calcium sulfate cards.

Hence, each of the TLD badges consists of 4 dosimeters.

Two TLD stations are established in each of the 16 meteorological sectors about the plant.

The inner ring of stations (Nos.1 through 16) is located near the site boundary, while the outer ring (Nos.17 through

32) is located at a distance of about 5 miles. The 16 stations forming the inner ring are designated as the indicator stations.

The 2 control stations (Nos. 36 and 37) are well over 10 miles from the plant.

Special interest areas consist of a nearby permanent residence (No. 33),

the Girard Elementary School (No. 34), the Town of Girard (No. 35), and the GPC employees' recreational area (No. 43).

As may be seen from Table 3-1, the average quarterly dose acquired at the indicator stations (inner ring) over the report period was 0.3 mrem less than that acquired at the control stations; this difference was not discernable, however, since it was less than the MDD of 2.6 mrem.

The quarterly doses acquired at the outer ring stations ranged from 14.1 to 26.1 mrem with an average of 16.7 mrem for the report period which is 0.9 mrem less than that found for the inner ring.

There was no discernable difference between the averages of the inner and outer rings since this difference was less than the MDD of 1.3 mrem.

The quarterly doses in units of mrem acquired at the special interest areas were as follows.

Station No.

Average Minimum Maximum 33 21.3 20.5 22.6 34 20.1 19.3

21. 7 35 18.5 17.3 19.8 43 15.2 14.7 15.9 The doses acquired at the special interest stations are seen to be somewhat typical and within the range of those acquired at the other stations.

Two TLD exposure locations implemented during the latter years of the preoperations phase of the REMP and not stipulated as a part of the operations phase were nevertheless continued to be used during the second calendar quarter of 1987.

These extraneous locations were:

former Station 38 (WSW at 17.5 miles) which was located adjacent to Station 37 and was used to enhance the baseline data; and fonner Station 91 (WNW at 2.8 miles) which was located adjacent to a onetime pasture for a milk animal. The doses for the second quarter were 19.8 and 14.2 mrem at former Stations 38 and 91 respectively; these doses are also seen to be within the range of those found at the regular sampling locations.

4-5

?c y

1 Frequently, TLDs are lost due to theft and damaged due to-vandalism.

A-total of 3 badges from 2 different stations was found to be missing-during the report period.

9 1

t!

I t

i i

I t

I 1

i i

h 4

5 1

1 I

t e

i f

4-6 hYb h hh 1

0 4.3 Milk As indicated by Table 2-2, milk is collected biweekly from two control locations, Dixon's Dairy (No. 98) and the Boyceland Dairy (No. 99).

Gamma isotopic and I-131 analyses are perfomed on each sample.

No sample was available from Dixon's Dairy on May 26 due to a failure to reach the Dixons beforehand to place an order for the milk.

Milk has not been available from locations within 5 miles of the plant since April 1986 when the cow from which milk was being obtained went dry and was subsequently removed from the area.

As indicated by Table 4-1, no milk animals were found in the land use census conducted in April. A milk animal is a cow or goat that is producing milk for human consumption.

The availability of milk within 5 miles of the plant was meager throughout preoperations.

Dixon's Dairy is believed to be the closest location of milk animals to the plant.

There was no positive results obtained from the I-131 analyses of the milk samples throughout the report period.

However, three positive results were obtained from the gamma isotopic analyses.

On July 14, Cs-137 was found in the samples from both stations; the levels were 10.8 and 9.9 pCi/1 at Dixon's and Boyceland, respectively.

On August 25, Zn-65 was found in the sample from Boyceland at a level of 25 pCi/1.

These levels are below their LLDs which are 15 and 30 for Cs-137 and i

2n-65, respectively, On July 31, a gaseous release of tritium occurred at SRP.

In an endeavor to detect any substantial increase of the tritium level in milk in the VEGP environs which might be attributed to this release, samples were collected at both of the milk stations on August 4.

Tritium analyses were perfomed on these extra samples, as well as, upon those collected on August 11 which was the next regularly scheduled collection date.

The tritium levels in units of pC1/1 found in these collections are I

compared below with the averages and ranges found at these locations during preoperations.

Collections Dixon's Boyceland August 4 269 133 August 11 797 41 8 Preop Average 1200 300

[

Preop Range 100 - 5000 100 - 600 It is seen that the levels for these extraneous analyses are generally below the averages found during preoperations.

4-7 i

I:

.~ 5 E '

a

4.4 Yegetation The TS call for the gama isotopic analysis of grass or leafy vegetation collected monthly from two onsite locations near the site boundary (Stations 7 and 15) and one control location at about 15 or more miles from the plant (Station 37).

Grass is collected at each of these locations. There was a failure in obtaining adequate samples at Stations 15 and 37 in November due to a lack of rain; the plots had been reseeded the previous month.

In the land use census which was conducted during the second quarter and was the first census to be conducted since plant operations began, a small scanty garden producing broad leaf vegetation was identified in the WSW Sector at 1.3 miles.

This garden tended by the Lapsley family was located in a trailer park.

The calculated dose comitment for this location was greater than 20% of that for any of the other locations at which vegetation was then being sampled.

In accordance with Section 3.12.2.b of the TS, this new location (Station 12) was added to the REMP.

Broad leaf vegetation samples were collected from the lapsley's garden in June and July, after which no samples were available.

This is a normal occurrence in this locale with hot dry summers.

In October, leafy vegetation samples became available from the Caughmans who are neighbors of the Lapsleys and whose garden is in the same sector at approximately the same distance.

Hence the same station number is applicable.

Samples were available for the remainder of the year.

As indicated in Table 3-1, Cs-137 was the only manmade radionuclide

{

detected. The avarage level at the control station is seen to be 37.1 pCi/kg wet f or 16?%) greater than tnat at the indicator stations.

The difference between these average values is not discernable, however, i

since this difference is less than the MDD of 39 pCi/kg wet. Not included in the results delineated in Table 3-1 is the result for an extra scmpic collected at Caughnans on December 1 in response to the release at SRP during the latter part of November.

In this sample, Cs-137 was detected at a level of 43.7 pCi/kg wet.

On August 4, extra grass samples were collected at Stations 7,15 and 37 for tritium analyses as a consequence of the gaseous release of tritium at SRP on July 31.

Tritium analyses were also performed on the samples collected on August 18 (the regularly scheduled collection date) at these stations.

The tritium levels in units of pCi/kg wet found in these samples are compared below with the averages and ranges found at these locations during preoperations.

Collections Station 7 Station 15 Station 37 August 4 247 198 381 August 18 849 1675 71 0 Preop Average 1800 1900 900 Preop Range 100-16,000 200-11,000 700-7,300 4-8 p

,E C

s It is seen that the levels for these_ extraneous analyses are below the averages found during preoperations.

It is also noted that the level for each of the extra samples collected on August 4 is substantially lower than that for the August 18 collections.

i k

J

i I

I 5

I 5

f 3

I 4-9 1

t rr; ^ p, - -

t f

0 4.5 River Water Surface water is composited from the Savannah River at three locations using automatic sampling machines.

Small quantities of river water are collected at intervals not exceeding a few hours. River water collected by these mschines is picked up monthly; quarterly composites are composed of the monthly collections.

The collection points consist of a control station (No. 82) which is located about 0.3 miles upriver of the plant intake structure, an indicator station (No. 83) which is located about 0.3 miles downriver of the plant discharge structure and a special station (No. 84) which is located about 1.4 miles downriver.

A gamma isotopic analysis was made on each monthly collection but no radionuclides were detected.

A tritium analysis was performed on each quarterly composite.

A positive result was obtained from each analysis.

As indicated in Table 3-1, the average level at the indicator station is 156 pCi/1 greater than that at the control station but this difference is not discernable because it is less than the MDD of 416 pCi/1.

At Station 84, the results ranged from 725 to 1620 pCi/l with an average of 1411 pCi/1.

During preoperations, samples were also collected at Stations 81 and 85 which are respectively 2.2 miles upriver and 4.2 miles downriver.

Collections at these two locations continued through the second quarter.

The first and second quarter tritium levels for this r6 port period - the first quarter consisted of the month of March only - were respectively 422 and 470 pCi/1 for Station 81 and 1010 and E670 pC1/1 for Station 05.

The average tritium levels obtained during the report period at Stations 81 through 85 were respectively 446, 524, d80,1411 and 1840 pCi/1.

This profile of increasing tritium level with downriver location is 1

similar to that found during preoperations.

J i

On September 16 the annual survey of the Savannah River was conducted downriver of tne plant for approximately 130 river miles to identify any 4

parties who may use river water for purposes of drinking or irrigation.

The only parties found to be withdrawing river water for drinting purposes were the two downriver water treatment plants (Stations 87 and

88) from which samples are collected monthly. As in all previous surveys, no intakes for irrigation use were observed.

On September 22, it tas confirmed by contacting the Georgia Environmental Protection Division and the South Carolina Department of Health and Environmental Control that the only water treatment plants downriver of VEGP which are permitted to use river water for drinking purposes are the two mentioned l

above and that no other surface water withdrawal permits are issued for Savannah River water use downriver of VEGP.

4-10

. c.

4.6 Drinking Water Samples were collected at a control station (No. 80), the Augusta Water Treatment Plant in Augusta, Georgia, which is located about 56 miles upriver and at two indicator stations (Nos. 87 and 88), the Beaufort-Jasper County Water Treatment Plant near Beaufort, South Carolina and the Cherokee Hill Water Treatment Plant near Fort Wentworth, Georgia, which are respectively located about 112 and 122 miles downriver. These upriver and downriver distances in river miles are the distances from VEGP to the point in the river where water is diverted to the intake for each of these water treatment plants.

At each of the water treatment plants, monthly collections were made of riverwater which was composited near the plant's intake (raw drinking water) and of grab samples of finished drinking water, Gross beta and i

gamma isotopic analyses were performed on each of the samples collected monthly.

Tritium analyses were perfonned on quarterly composites.

As indicated by Table 3-1, the average gross beta activity for raw drinking water was 3.3 pCi/1 greater for the control station than for the indicator stations.

However, this difference was not discernable because it was less than the MDD of 4.4 pCi/1.

Tne high average reading at Station 80 is attributed to sediment being drawn into a few of the samples.

For finished drinking water, the average gross beta activity was 0.3 pCi/1 greater for the indicator stations than for the control station.

This difference was not discernable because it was less than the HDD of 0.7 pCi/1.

Although no positive results were obtained from the gama isotopic analyses of any of the monthly collections, positive results were obtained from the tritium analysis of each of the quarterly ce.mpcaites.

Furthermore, there was a discernable difference between tne average i

values for the two type stations for both the raw and finished drinking water since these differences were each greater than their itDDs, As indicated by Table 3-1, the average values of the tritium levels for the indicator stations were 1913 and 2101 pCi/1 greater than those for the control station for raw and finished drinking water respectively while the fiDDs were correspondingly 793 and 1007 pCf /1.

Similar results were obtained during preoperations.

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4.7 Fish The TS call for the collection of at least one sample of any anadromous species of fish in the vicinity of the plant discharge during the spring spawning season.

The TS also call for semiannual collections of any commercially or recreationally important species in the vicinity of the plant discharge area and in areas not influenced by plant discharge.

Furthermore, the TS call for a gamma isotopic analysis on the edible portions of each sample collected.

About a five mile stretch of the river is generally needed to obtain adequate fish samples.

For the semiannual collections, the control station (No. 81) extends from approximately 2 to 7 miles upriver of the plant intake structure and the indicator station (No. 85) extends from about 1.5 to 7 miles downriver of the plant discharge structure.

For the anadromous species all collection points can be considered as indicator stations.

American shad, an anadromous species which may also be considered as commercially or recreationally important, was collected at Station 81 on March 17 and at Stations 81 and 85 on April 21.

Channel catfish was also collected at Station 85 on April 21.

On October 19, chain pickerel was collected at Station 81 while redear sunfish and largemouth bass were collected at both Station 81 and Station 85.

As indicated by Table 3-1, Cs-137 was the only radionuclide found in any of the fish samples.

It was identified in only one of the anadromous fish samples (the March 17 collection) at a barely detectable level and in all but one (the channel catfish) of the other fish collected.

The average level for the indicator station is seen to be 218 pCi/kg wet greater than that for the control station bet this difference is not discernable since the MDD is 442 pCi/kg wet. Higher Cs-137 levels of this order were observed in fish collected downriver during preopera-tions. The LLD for Cs-137 in fish is 150 pCi/kg wet and the RL is 2000 pCi/kg wet.

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4.8 Sediment i

Sediment was collected along the shoreline of the Savannah River on April 13 and October 12 at Stations 81 and 83.

Station 81 is a control station located about 2.3 miles upriver of the plant intake structure while Station 83 is an indicate. station located about 0.7 miles downriver of the plant discharge structure. A gamma isotopic analysis was performed on each sample.

As indicated by Table 3-1, positive results were obtained for Be-7 and Cs-137 <n each of the regular samples collected.

The average levels at the indicator and the control stations for each of these radionuclides, the differences between these two values, the MDDs and LLDs were as follows:

Radionuclide Indicator Control Dif ference MMD LLD Be-7 987 543 444 2403 300 Cs-137 209 111 98 269 200 It is seen that for each of these radionuclides there is no discernable difference between their average levels in the upriver and downriver collections.

During preoperations sediment was also collected at Station 82 which was a control station located about 0.3 miles upriver.

A sample was also i

collected at this location on April 13 in which Be-7 and Cs-137 were found at levels of 838 and 141 pCi/kg dry, respectfully.

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5.0 INTERLABORATORY COMPARIS0N PROGRAM Section 3.16.3 of the TS requires that analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Nuclear Regulatory Commission (NRC).

The Environmental Protection Agency's (EPA's) Environmental Radioactivity Laboratory Intercomparison Studies (Crosscheck) Program conducted by the Environmental Monitoring and Support Laboratory in Las Vegas, Nevada is such a program and it has been approved by the NRC.

Analyses were perfomed only where the type analysis and sample in the EPA Crosscheck Program were the same as that delineated in Table 2-1.

Reported herein are the results of participation in the EPA Crosscheck Program by the Central Laboratory.

Any results for which disagreement was established using the NRC's "Criteria for Comparing Analytical Measurements" as described in to this section were investigated to determine the cause of the disagreement.

Corrective actions were taken as warranted.

The results of any such investigations and corrective actions are reported in this section.

Since all of the results reported herein are presented in the same tabular format, an explanation of the column headings is provided.

"Date" means the collection date given by the EPA.

Known" refers to the EPA known value + one standard deviation, s.

"Result" is the average value measured by the laboratory + experimental s.

"Recolution" is detemined by dividing the knowa Yalue by its s value.

"Ratio" equals the "result" (value detemined by the laboratory) divided by the "known" l

(value determined by EPA).

An explanation is provided in the text for any of the comparisons showing ' Disagreement."

It should be noted that 3

4 whenever the EPA known value is zero or the laboratory-dotermined result is a less than (LT) value, or the calculated resolution value is less than 3, a comparison by the NRC criteria cannot be made.

The results of the gross beta and Cs-137 analyses of air filters are given in Table 5-1.

Listed in icble 5-2 are the results of the I-131 and gamma analyses of milk tan 1 ?s. Table 5-3 presents the results of j

tne gross beta, ganma and tritium analyses of wate Disagreement was not established with any of the comparisons.

However, the results of the ganna isotopic analysis of the October 9 water sample for Ru-106 were 40, 48 and LT 46 pCi/1.

By using only the positive results, agreement was established.

The size of the samples to be counted is being increased from 0.45 to one liter; this will improve the counting statistics.

A result outside of 2s suggests a bias in its measurement.

Whenever this occurs, the Central Laboratory is required by procedure to investigate and follow-up with corrective actions, as needed.

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9 TABLE 5-1 CROSSCHECK' PROGRAM RESULTS FOR AIR FILTERS (pCi/ filter)

Date Known Result Resolution Ratio

' Gross Beta 4/10/87 43 + 5 43.0 + 0.0 8.6 1.00 8/28/87 3035 28.011.0 6.0 0.93

_Cs-137 4/10/87 8+5 12.0 + 1. 7 1.6 1.50' 8/28/87 1015 9.7}2.1 2.0 0.97 i

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CROSSCHECK PROGRAM RESULTS FOR MILK SAMPLES (pCi/1)

'Date' Known Result Resolution Ratio I

I-1 31 2/27/87' 9.0 + 0.9 8.7 +-1.2 10.0

.0.96 6/26/87 59.016.0 67.335.7 9.8 1.14 i

Cs-137

'6/26/87 74.0 _+ 5.0 78.0 + 5.9 14.8 1.05 i

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-t TABLE 5-3 CROSSCHECK PROGRAM RESULTS FOR WATER sal @LES (pCi/1)

A Date Known Result Resolution Ratio Gross Beta i

1/23/87-10.0 + 5.0

'11.0 + 0.0 2.0 1.10 3/20/87 13.075.0 12.3 T 0.6 2.6 0.95 5/22/87 7.0 7 5.0 6.3 7 0.6 1.4 0.90 7/24/87 5.0 T 5.0 6.0 T 1.0 1.0 1.20 9/18/87 12.0 7 5.0 12.3 7 1.5 2.4 1.03 11/20/87 19.075.0 16.71 0.6 3.8 0.88 t

Crr 51 6/05/87

41. 0 + 5. 0 48.0 + 27.9 8.2 1.17

-10/09/87 70.0 7 5.0 66.7726.1 14.0 0.95 Co-60

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2/06/87 50.0 + 5.0 58.0 + 4.6 10.0 1.16 6/05/87 64.0 7 5.0 63.0 7 5.3 12.8 0.98 10/09/87 15.015.0 13.7-1 2.3 3.0

0. 91 2n-65 t

2/06/87 91.0 + 5.0 95.7 + 5.9 18.2 1.05 6/05/87 10.0 T 5.0 10.7 7 3.2 2.0 1.07 10/09/87 46,015.0 53.0113.5 9.2 1.15 i

Ru-106 4

i 2/06/87 100.0 + 5.0 130.0 + 40.0 20.0 1.30 6/05/87 75.0 7 5.0 75.7 7 7.4 15.0 1.00 10/09/87 61.075.0 44.0 7 5.6*

12.2 0.72 Cs-134 4

2/06/87 59.0 + 5.0 57.0 + 2.0 11.8 0.97 6/05/87 40.0 T 5.0 38,0 7 1.0 8.0 0.95 i

L 10/09/87 25.0 7 5.0 25.7 1 4.0 5.0 1.03 l

t Cs-137 t

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2/06/87 87.0 + 5.0 86.7 + 5.7 17.4 1.00 l

6/05/87 80.0 7 5.0 79.3 7 7.1 16.0 0.99 10/09/87 51.015.0 49.336.7 10.2 0.97 t

l

• Result is based upon two positive values, i

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TABLE 5-3 (Continued)

CROSSCHECK PROGRAM RESULTS FOR WATER SAMPLES (pCi/1)

Date Known Result Resolution Ratio a.

H-3 i-2/13/87-4209.0 + 421.0 4137.0 + 30.6 10.0 0.98 6/12/87 2895.0 7 357.0 2677.0 7 60.3 8.1 0.92 l

10/16/87 4492.03449.0 4253.0180.2 10.0 0.95 4

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.o ATTACHMENT 1 Criteria for Comparing Analytical Measurements This attachment provides criteria for comparing results of capability tests and verification measurements.

The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this program.

In these criteria, the judgment limits are variable in relation to the comparison of the Reference Laboratory's value to its associated one sigma uncertainty. As this comparison, referred to as "Resolution", increases, the acceptability of a licensee's measurement should be more selective.

Conversely, poorer agreement should be considered acceptable as the resolution decreases. The values in the ratio criteria may be rounded to fewer significant figures to maintain statistical consistency with the number of significant figures reported by the Reference Laboratory, unless such rounding will result in a narrowed category of acceptance. The acceptance category reported will be the narrowest into which the ratio fits for the resolution being used.

RESOLUTION RATIO = LICENSEE VALUE/ REFERENCE VALUE Possible Possible Agreement Agreement "A" Agreement "B" LT 3 No Comparison No Comparison No Comparison GE* 3 and LT 4

0.4

- 2.5 0.3

- 3.0 Ne Comparis(n GE 4 and LT 8

0. 5

- 2.0 0.4

- 2.5 0.3

- 3.0 GE 8 and LT 16 0.6

- 1.67 0.5

- 2.0 0.4

- 2.5 GE 16 and LT 51 0.75 - 1.33 0.6

- 1.67 0.5

- 2.0 GE 51 and LT 200 0.80 - 1.25 0.75

- 1.33 0.6

- 1.67 GE 200 0.85 - 1.18 0.80

- 1.25 0.75

- 1.33 l

• GE means greater than or equal to "A" criteria are applied to the following analyses:

Gamma spectrometry where principal gamma energy used for identification is greater than 250 key.

Tritium analyses of liquid samples.

"B" criteria are applied to the following analyses:

Gamma spectrometry where principal gamma energy used for identification is less than 250 key.

Sr-89 and Sr-90 determination.

Gross beta where samples are counted on the same date using the same reference nuclide.

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6.0 CONCLUSION

S This report has shown the licensee's confonnance with Section 3/4.12 of the TS during the report period.

It has shown that the data were carefully examined.

A summary and a discussion of the results of the laboratory analyses for each type sample collected were presented.

No measurable radiological impact upon the environment as a consequence of plant discharges to the atmosphere or to the river was established.

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