ML20138F085

Annual Radiological Environ Surveillance Rept,For 1996

ML20138F085
Person / Time
Site:	Vogtle
Issue date:	12/31/1996
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20138F075	List: ML20138F070 ML20138F085 ML20138F093 ML20138F100
References
NUDOCS 9705050259
Download: ML20138F085 (57)

Text

.. . . _. _- . . - -. . . -. . .__. . . . .

III VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 l 1996 ANNUAL REPORT- PART 2 i

l ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT l

l I

(

l l

l 9705050259 970428 PDR ADOCK 05000424 R PDR l

i i

e i

?

VOGTLE ELECTRIC GENERATING PLANT  !

RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT l i

i r

TABLE OF CONTENTS SECTION TITLE PAGE

1.0 INTRODUCTION

1-1  !

2.0

SUMMARY

DESCRIPTION 2-1 3.0 RESULTS

SUMMARY

3-1 4.0 ' DISCUSSION OF RESULTS 4-1 4.1 Airborne 4-4 4.2 Direct Radiation 4-8 4.3 Milk 4-10 1 4.4 Vegetation 4-11  !

4.5 River Water 4-12  !

4.6 Drinking Water 4-14  !

4.7 Fish 4-18 4.8 Sediment 4-20 5.0 INTERLABORATORY COMPARISON PROGRAM 5-1

6.0 CONCLUSION

S 6-1 l

[

t i

i-l t

i l

LIST OF TABLES .

l TABI.E TITLE PAGE ,

2-1

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2-2 i 2-2 RADIOLOGICAL ENVIRONMENTAL .

I SAMPLING LOCATIONS 2-7 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING

PROGRAM ANNUAL

SUMMARY

3-2 l

l 4-1 LAND USE CENSUS RESULTS 4-2  :

i  !

5-1 INTERLABORATORY COMPARISON PROGRAM RESULTS 5-2 l

l

)

i l i i I i

i i

k 4

i 1

ii i i

-_44 ._..-A m - ._4... # . s,s.. .. ,+.....am.u...+As-i.-

e ..a .

& . - .u. - 4 u .4_ -..x a ...,.u......u.4.m-,3 ..-_5.

)

LIST OF FIGURES FIGURE TITLE PAGE 2-1 TERRESTRIAL STATIONS NEAR SITE BOUNDARY 2-10 2-2 TERRESTRIAL AND AQUATIC STATIONS WITilIN SIX MILES 2-11 2-3 TERRESTRIAL STATIONS BEYOND SIX MILES 2-12 2-4 DRINKING WATER STATIONS 2-13 I

i

(

l i

lii )

l

ACRONYMS A2LA American Association of Laboratory Accreditation ASTM American Society for Testing and Materials CL Confidence Level EL Environmental Laboratory EPA Environmental Protection Agency GPC Georgia Power Company IPC Interlaboratory Comparie.;n Program MDC Minimum Detectable Concentration MDD Minimum Detectable Difference NA Not Applicable NDM No Detectable Measurement (s)

NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual REMP Radiological Environmental Monitoring Program QA Quality Assurance QC Quality Control RL Reporting Level RM River Mile SRS Savannah River Site TLD- Thermoluminescent Dosimeter TS Technical Specifications VEGP Alvin W. Vogtle Electric Generating Plant iv

VOGTLE ELECTRIC GENERATING PLANT RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT

1.0 INTRODUCTION

The objectives of the Radiological Environmental Monitoring Program (REMP) are to ascertain the levels of radiation and concentrations of radioactivity in the environs of the Alvin W. Vogtle Electric Generating Plant (VEGP) and to assess any radiological impact upon the environment due to plant operation.

The bases for such an assessment include appropriate comparisons between results obtained at control stations (locations where radiological levels are not expected to be significantly affected by plant operation) with those obtained at indicator stations (locations where it is anticipated that radiological levels are more likely to be affected by plant operation), and comparisons between results obtained during preoperation with those obtained during operation.

The preoperational stage of the REMP started in August of 1981 when initial collections of samples were made. There was a phase-in period of a few years before the preoperational program was fully iruplemented. The transition from the preoperational stage to the operational stage hinged about initial criticality of Unit 1 which occurred on March 9,1987.

The REMP is conducted in accordance with Technical Specifications (TS) 6.7.4.g and Chapter 4 of the Offsite Dose Calculation Manual (ODCM). The REMP activities for 1996 are reported herein in accordance with TS 6.8.1.3 and ODCM 7.1. All dates in this report are for 1996 unless otherwise indicated. I A summary description of the IEMP is provided in Section 2 of this report; maps showing the sampling stations are keyed to a table indicating the direction and distance of each station from a point midway between the two reactors. An annual

{

summary of the main laboratory analysis results obtained from the samples j utilized for environmental monitoring is presented in Section 3. A discussion of the results, including assessments of any radiological impacts upon the environment and the results of the land use census and the river survey, is provided in Section 4. The results of the Interlaboratory Comparison Program (IPC) are presented in Section 5. Conclusions are stated in Section 6.

1 l

l l

I l-1

• 1 l

l 2,0

SUMMARY

DESCRIPTION A summary description 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. Table 2-1 is a representation ofODCM Table 4-1 which delineates the program's requirements. The sampling locations required 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 follows the table and figures in ODCM 4.2.

In accordance with ODCM 4.1.1.2.1, deviations from the required sampling schedule as set forth in Table 2-1 are permitted if specimens are unobtainable due to hazardous conditions, unavailability, inclement weather, equipment malfunction or otherjust reasons. Any deviations are accounted for in the discussions for the particular sample types in Section 4. ,

All laboratory analyses were performed by Georgia Power Company's (GPC)

Environmental Laboratory (EL) in Smyrna, Georgia. Since 1987, the EL has been accredited by the American Association of Laboratory Accreditation (A2LA) for radiochemistry. The A2LA is a nonprofit, nongovernmental, public service, membership society dedicated to the formal recognition of competent laboratories and related activities. Accreditation is based upon internationally accepted criteria for laboratory competence (ISO /IEC Guide 25,1990, General Reauirements for the_Comnetence of Calibration and Testing Laboratories).

2-1

TABLE 2-1 (SHEET 1 OF 5)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Samole Samples and Samole Locations Collection Frecuency ofAnalysis

1. Direct Radiation Thirty nine 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 each meteorological sector

',o at approximately 5 miles from the site: and Special interest areas, such as population centers, nearby recreation areas, and control stations.

s k

TABLE 2-1 (SHEET 2 OF 5)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samoles and Sample Locations Collection Frequency ofAnalysis

2. Airborne Radiciodine and Samples from seven locations: Continuous sampler Radioiodine canister:

Particulates operation with sample I-131 analysis, weekly Five locations close to the collection weekly, or site boundary in different more frequently if Particulate sampler:

sectors; requimd by dust Gross beta analysis (1) loading following filter change A community having the highest and gamma isotopic calculated annual average analysis (2) of composite ground-level D/Q: and (by location), quarterly u

0 A control location near a population center at a distance of about 14 miles.

3. Waterborne

a. Surface (3) One sample upriver Composite sample over Gamma isotopic analysis (2),

one month period (4) monthly. Composite for Two samples downriver tritium analysis, quarterly

- _ _ _ _ . . - _ _ _ - _ _ . . _ ~ - . _ - . - - _ _ _ _ - - _ _ _ _ _ - _ -

f TABLE 2-1 (SHEET 3 OF 5)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative- Sampling and Type and Frequency and/or Samole Samples and Samole Locations Collection Freauency ofAnalysis

b. Drinking Two samples at each of the two Composite sample of I-131 analysis on each sample ,

nearest water treatment plants river water near the when the dose calculated for that could be affected by intake ofeach water the consumption of the water plant discharges treatment plant over is greater than 1 mrem per two week period (4) year (5). Composite for Two samples at a control when 1-131 analysis gross beta and gamma isotopic location is required for each analyses (2) on raw water, sample; monthly monthly. Gross beta, gamma composite otherwise; isotopic and I-131 analyses and grab sample of on grab sample of finished finished water at water, monthly. Composite for w each water treatment tritium analysis on raw and A plant every two weeks finished water, quarterly.

or monthly, as appropriate.

c. Sediment from One sample from downriver area Semiannually Gamma isotopic analysis (2), ,

Shoreline with existing or potential semiannually recreational value One sample from upriver area with existing or potential recreational value

4. Ingestion

a. Milk Two samples from milking Biweekly Gamma isotopic analysis (2,7),

animals (6) at control biweekly locations at a distance of about 10 miles or more

TABLE 2-1 (SHEET 4 OF 5)

SUMMARY

DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

~

Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Samnle Samoles and Samole Locations Collection Freauency ofAnalysis

b. Fish At least one sample of any Semiannually Gamma isotopic analysis (2) i commercially or recreationally on edible portions, ,

important species near the semiannually plant discharge At least one sample of any commercially or recreationally important species in an area not influenced by plant discharges t) c At least one sample of any During the spring Gamma isotopic analysis (2) <

• - anadromous species near the spawning season on edible portions, annually ,

plant discharge ,.

c. Grass or One sample from two onsite Monthly during the Gamma isotopic analysis (2,7),  ;

Leafy locations near the site growing season monthly Vegetation boundary in different sectors  ;

One sample from a control location at a distance of t about 17 miles i

L

_ _ _ _ - - - _ - - - - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ - . _ _ _ _ - - - - _ _ _ _ - _ - - - - _ _ = - - _ - - _ - - _ . - _ _ _ - - - -____ - - -..__ _.-- _. _-._ - - - - _ _ _ - _ _ _ -

TABLE 2-1 (SHEET 5 OF 5)

SUMMARY

DESCRIPTION OF ~

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

NOTATIONS i

I (1). Airbome particulate sample filters shall be analyzed for gross beta j 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 i daughter decay. If gross beta activity in air particulate samples is greater

than 10 times the yearly mean of control samples, gamma isotopic analysis j shall be performed on the individual samples 3 (2) Gamma isotopic analysis means the identification and quantification of

gamma-emitting radionuclides that may be attributable to the effluents from 4 the facility.

1- The upriver sample is taken at a distance beyond significant influence of the (3)

I discharge. The downriver samples are taken in areas beyond but near the

mixing zone, e

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

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

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

(7) If the gamma isotopic analysis is not sensitive enough to meet the Minimum Detectable Concentration (MDC) for I-131, a separate analysis for I-131 may be performed.

2-6

i

l i )

i i

TABLE 2-2 (SHEET 1 OF 3)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS i

Station Station Descriptive Direction Distance Sample

- Number Tyne (1) Location (2) (miles) (2) Tv_n e (3) 1 I Hancock Landing Road N 1.1 D 2 I River Bank NNE 0.8 D r '3 Discharge Area I NE 0.6 A 3 I River Bank NE 0.7 D 4 I River Bank ENE 0.8 - D i 5 I River Bank E 1.0 D

6 I Plant Wilson ESE 1.1 D l 7 I Simulator Building SE 1.7 ADV l

River Road 8 I SSE 11 D '

i' 9 I River Road S 1.1 D l 10 I Meteorological Tower SSW 0.9 A j i 10 I River Road SSW l.1 D i j 11 I River Road SW l.2 D i j 12 I River Road WSW 1.2 AD

. 13 I River Road W l.3 D

14 I River Road WNW 1.8 D 2

15 I Hancock Landing Road NW l.5 DV i 16 I Hancock Landing Road NNW l4 AD 1 17 O Savannah River Site i 4 (SRS), River Road N 5.4 D J

! 18 O SRS, D Area NNE 5.0 D

! 19 O SRS, Road A.13 NE 4.6 D i

!. 20 0 SRS, Road A.13.1 ENE 4.8 D

21 0 SRS, Road A.17 E 5.3 D ,

l 22 O River Bank ESE 5.2 D i i 23' O River Road SE 4.6 D '

. 24 O Chance Road SSE 4.9 D I 25 O Chance Road near j Highway 23 S 5.2 D 26 O Highway 23 and Ebenezer Church Road SSW . 4.6 D

!. 27- O Highway 23 opposite

' Boll Weevil Road SW 4.7 D

'8 O Thomas Road WSW 5.0 D l 29 O Claxton-Lively Road W 5.1 D ,

30 0 Nathaniel Howard Road WNW 5.0 D '

31 O River Road at  ;

1 Allen's Chapel Fork NW 5.0 D  !

j 32 O River Bank NNW 4.7 D 1 33- O Hunting Cabin SE 3.3 D

35 O Girard SSE 6.6 AD 1

i l 1

l 2-7

-. - - -. - . - - - - - ~ - . - - _ _ - - . . . -

d l

1 TABLE 2-2 (SHEET 2 OF 3) l RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Station Station Descriptive Direction Distance Sample  !

Number Type (1) Location (2) (miles) (2) Tyne (3)

\

36 0 GPC Waynesboro Op IIQ WSW 13.9 AD '

37 C Waynesboro Substation WSW 16.7 DV i 43 O Employee's Rec Area SW 2.2 D 47 C Oak Grove Church SE 10.4 D i' d

48 C McBean Cemetery NW 10.2 D a 80 C Augusta Water

,' Treatment Plant NNW 29.0 W(4) )

,  !!! C Savannah River N 2.5 F(5)S(6) 82 C Sav River (RM 151.2) NNE 0.8 R 83 I Sav River (RM 150.4) ENE 0.8 RS(6) 84 O Sav River (RM 149.5) ESE 1.6 R 85 I Savannah River ESE 4.3 F(5)

, 87 I Beaufort-Jasper County _

! Water Treatment Plant, j Beaufort, SC SE 74 W(7)

! 88 1 Cherokee Hill Water i' ' Treatment Plant, Port Wentworth, G A SSE 71 W(8) 98 C W. C. Dixon Dairy SE 9.8 M 2.

99 C Boyceland Dairy W 20.9 M i

NOTATIONS (1) Station Types ,

C - Control  !

4 1 - Indicator 0 - Other (2) Direction and distance are reckoned from a point midway between the two two reactors.

1 (3) Sample Types

A - Airborne Radioactivity D - Direct Radiation i F - Fish M - Milk R - River Water 4 S - River Shoreline Sediment i W - Drinking Water V - Vegetation 7

2-8 l

.- . - - . - . - - - . - - . - - . - - _ . - - . - . . . . ~ _ - - . - - . . - _ . . . . .

j i.

J 1

TABLE 2-2 (SHEET 3 OF 3) l RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS i

NOTATIONS (CONTINUED) i 4

- (4) The intake for the Augusta Water Treatment Plant is located on the Augusta Canal.

} The entrance to the canal is at River Mile (RM) 207 on the Savannah River. The a

canal effectively parallels the river. The intake to the pumping station is about 4 miles j down the canal and only a tenth of a mile from the river (across land).

4 i' (5) A 5 mile stretch of the river is generally needed to obtain adequate fish samples. l 1 Samples are normally gathered between RM 153 and D8 for upriver collections and  ;

i between RM 144 and 149.4 for downriver collections. '

(6) Sediment is collected at locations with existing or potential recreational value. l l Because high water, shifting of the river bottom, or other reasons could cause a j suitable location for sediment collections to become unavailable or unsuitable, a 4

stretch of the river between RM 148.5 and 150.5 was designated for downriver 1-2 collections while a stretch between RM 153 and 154 was designated for upriver l collections. In practice, collections are normally made at RM 150.2 for downriver i collections and RM 153.3 for upriver collections. .j 1

(7) The intake for the Beaufort-Jasper County Water Treatment Plant is located at the end of a canal which begins at RM 39.3 on the Savannah River. This intake is about 16

! miles by line of sight down the canal from its beginning on the Savannah River.

/

i (8) The intake for the Cherokee Hill Water Treatment Plant is located on Abercorn Creek i which is about one and a quarter creek miles from its mouth on the Savannah River at i

! RM 29.

I i

! I i '. ,

1 i

i i

4 I

i I

I 2-9 l

4

_ , ,. ws,q e -,- s_.~, .,---,--r m -..- -, y.,. .

, . ._.r.

_s- ---

/

P

! um -_

n. __.~~ff

.g mR / x y'* v l g. g im.-v. .iny e

/

-4 2 i . O , g

• • -N. I_F - , 7 7 7 WAY 4'[='/.l ' A' ~~J ~'/\/~r-g}; ,

,v l i -,

lI j'4 & i.j d ,/f~

{ '

y o\! n. .w J,M ww ,/ d l .

gI /

= -

$ 4 , 1 :. Y j -

Q&,/ I i -

=/  ; A, j . ?.' ~ -

r gN3

c

{ -

y v. . ..j. .

, v, i

..g'-

. u 1 e

1. . sk

% {

\b /

h

'Ti L l(< s .; ,

e pa y e ;m.. t n. e P.7

! \ .

b} .1 .

N won,A 9

i -

- s,',- ,;d1// nM'., =.( ';s_w'n'.r. -

-p ' ,' , ,,l3 9(,

s g .g k ->. s. s -

r, (; [,e . .

s ff

\ ;$ (i) s,,

'

-lr'.),i'IT w .

s ,

9 _

'q s,'. / ;~.% p.' !(,' i 1

ij sF 4;~r;y.f' - -.

t  ! -

).x'=:;h)!...

s' ~ -

W.

w  :.-::: Ly

. pt^:v.7 FIGURE 2-1 TERRESTRIAL STATIONS NEAR SITE BOUNDARY 2-10

~

- _ _ = , . - _ . = . _ , ~. .- - , . . . . . - .

1 I

4 sea.s l

• . 9 4 4

., r , ---- - .... .

a 1 s> '.

L~ y d/ ,, . s*.--

g &$e ^

0 t

2 1

4 i

h i

f _

4 /

WILES V L;kJ:

V\ .

s

[ . e. . :

,- x x ,

o,-

@3-N- f,," 4 .

+

)

i

'  :*  %. . m ** M'Au 83 ,

th ' hh E. $

C' \

' s

x. ,

/ h

, s x as -

84 '

M. , ,. . g s ( .

3 or- I Y + / ... % a .

J

. A- .g. -

/,  ? .. r g ,- ,

, i 8

f- \ #

e 4 , y .. I ek # / 2

• / .. 'if

. r- i 1 6 to

'u,

, a pQ .

~@ .

6-19.:

. . + ,. . :

~

fg '

i ,/

' k. s ',3 8

_ ,,/', , , , .

.n

- . .h, r

\

l' r

, . r

.)fr

.- t ., .

in .

) l e ' ^ !~,.;.3' ,, ,

k i

sne '

1. .Y * .f, 4 CNAfl0 * . #<4, #

~*

j - . M. 4 p . ,, b . .f FIGURE 2-2 TERRESTRIAL AND AQUATIC STATIONS WITHIN SIX MILES i 2-11 W

j .

\ ) 4,

(

/

• Q a+4, R D

~

A "d m s

. n, d o '

S I

@b D R

A S

s 2 3 f [ 0 2 TE 1 NL .

AT tg '

o ~

_. v

• a R l E D

N

- - A 2 X E

M L

• O A '

b B

s E

(,*

k 8

A E

C

(

1

's' W

A B W 3

4't) _

1. MA m g/

f '

8 0 6

,/

E I" L ~

t '

o

. n ' a mI N3a F A. e o$ 6b $ ha 5

I l

2 l

i AUGUST A W AT ER TRE ATMENT PLANT l B

8 .

' MMHu%Up

,,y,,,,,

mivEn PLANT 4

VEGP(

J l j s'

I Coast to supply River ,

wewei seeviers , j t*

l

' I seewtee: Jasper County l Weser Truesment Plant

\

- *,,~

. t GEORGIA {*" p

,,,,.s e

• 1. ' 87 k km b

y o io ao ao E 4 cuinoxEE witt y WATER TRE ATMENT b+

PLANT 4 iPoRT wENTwontui 0 sAvAwNA T C a.

t l

FIGURE 2-4 DRINKING WATER STATIONS 2-13 4

I l

l 3.0- RESULTS

SUMMARY

In accordance with ODCM 7.1.2.1, sununarized and tabulated results for all of the  !

regular samples collected for the year at the designated indicator and control i stations are presented in Table 3-1 in a format similar to that found in Table 3 of the Nuclear Regulatory Commission (NRC) Radiological Assessment Branch ,

. Technical Position, Revision 1, November 1979. Since no reportable occurrences t were called for during the year, the column entitled " Number of Reportable Occurrences" has been excluded from Table 3-1. Results for samples collected at locations other than indicator or control stations or in addition to those stipulated by Table 2-1 are discussed in Section 4 for the particular sample type. 1 Only the naturally occurring radionuclides which are found in the plant's effluent  ;

releases need be reported. The radionuclide, Be-7, which occurs abundantly in  ;

nature is also produced in the reactors. Minuscule quantities are found in the  ;

liquid releases. No other naturally occurring radionuclides have been found in 4 ,

plant's effluent releases. Hence, the radionuclides ofinterest for the samples  ;

monitoring liquid releases (river water, drinking water, fish and river shoreline  !

sediment) are man-made radionuclides plus Be-7, while only man-made i radionuclides are ofinterest for the other REMP samples. l.

l l

?

I l

h f

.i P

i 3-1 l

t

._ _ - . . _ . . . _ . . .l

i

{

TABLE 3-1 (SHEET I OF 10) ,

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

l Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 [

Burke County, Georgia l Indicator Location with Highest Control  !

Medium or - Type and Minimum Locations Annual Mean Locations }

Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) Mean (b) l (Unit of .

' of Analyses Concentration Range Distance & Range Range  !

Measurement) Performed (MDC) (a) (Fraction) Direction (Fraction) (Fraction) t Airborne Gross Beta 10 23.3 No.16 30.6 21.0 Particulates 318 6-527 Han Lan Rd 12-527 8-32  :

3 '

(fCi/m ) (265/265) 1.4 miles (53/53) (53/53)

NNW l u' I ia Gamma Isotopic .

24 i Cs-134 50 NDM (c) NDM NDM Cs-137 60 NDM NDM NDM Airbome I-131 70 NDM NDM NDM Radioipine 318  ;

(fCi/m )

Direct Gamma Dose NA (d) 12.3 No. 36 14.8 12.2 Radiation 80 8-17 GPC Op Hq 14-16 10-16 i (mR/91 days) (64/64) 13.9 miles (4/4) (16/16)

WSW i

i

. , - . . - . . . . - . _ . . , . . _ . - . - . . - _ . _. . . . _ . _ _ . . , . . _ _ _.- .__ _ . _ . - _ . . . - . _.-__ ....,_...,, - . _ _ . . ~ .

t L

TABLE 3-1 (SHEET 2 OF 10)

- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia t

Indicator Location with Highest Control Medium or Type and Minimum Locations Annual Mean Locations Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) Mean (b) [

(Unit of ofAnalyses Concentration . Range Distance & Range Range t Measurement) Performed (MDC) (a) (Fraction) Direction (Fraction) (Fraction) i t

Milk Gamma Isotopic (pCi/l) 54  :

Cs-134 15 NA NDM NDM  ;

Cs-137 18 NA NDM NDM w  !

& Ba-140 60 NA NDM NDM La-140 15 NA NDM NDM I-l31 1 NA No.99 0.244 0.244 54 Boyceland 0.244-0.244 0.244-0.244  ;

20.9 miles (1/27) (l/54)

W  !

Vegetation Gamma Isotopic (pCi/kg wet) 36  ;

I-131 60 NDM NDM NDM j r

Cs-134 60 NDM NDM NDM Cs-137 80 NDM NDM NDM -[

t

t TABLE 3-1 (SHEET 3 OF 10) - l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

' Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 ,

Burke County, Georgia  !

i Indicator Location with Highest Control .

Medium or Type and Minimum Locations Annual Mean Locations  !

Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) Mean (b) l (Unit of ofAnalyses Concentration Range Distance & Range Range- +

Measurement) Performed (MDC) (a) ' (Fraction) Direction (Fraction) (Fraction) i River Water Gamma Isotopic -  !

(pCi/l) 24 ,

Be-7 124 (e) NDM NDM NDM  !

Mn 15 NDM NDM NDM i w -

L Fe-59 30 NDM NDM NDM t t

Co 15 NDM NDM NDM t t

Co-60 15 NDM NDM NDM l Zn-65 30 NDM NDM NDM NDM. NDM NDM Zr-95 30 Nb-95 15 NDM NDM NDM I-131- 15 NDM NDM NDM  !

Cs-134 15 NDM NDM NDM Cs-137 18 NDM NDM NDM i Ba-140 60 NDM NDM NDM l

I k

.. m _... _ . ___ . . . . . . _ . _ _ _ . . ___ - ._ . _. - . _ . . . ~ . .__ _ . - _ . ._ _ m TABLE 3-1 (SHEET 4 OF 10)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Indicator Location with Highest Control Medium or Type and Minimum Locations Annual Mean - Locations Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) Mean (b)

(U_ nit of ofAnalyses Concentration Range Distance & Range Range Measurement) Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction) t La-140 15 NDM NDM NDM Tritium 3000 1187 No. 83 1187 387 8 498-2250 Downriver 498-2250 293-480 m (4/4) 0.4 miles (4/4) (2/4) in Water Near Gross Beta 4 5.83 No. 87 8.16 3.02 Intakes to 36 1.9-25.0 Beaufort 1,9-25.0 1.6-4.6

• Water (23/24) Downriver (12/12) (12/12)

Treatment i12 miles Plants (pCi/l)

Gamma Isotopic  ;

36  :

Be-7 124 (e) NDM NDM NDM Mn-54 15 NDM NDM NDM ,

(

Fe-59 30 NDM NDM NDM Co-58 15 NDM NDM NDM Co-60 15 NDM NDM NDM

- . _ _ - _ _ - _ _ . - _ - - . _ _ _ _ _ _ . - - - - . . . . - - __.-.--.-___.-,--_-..-_-.-_-----_-._-,._---w_m-- ,e -- r -w. s.--+-.ms~ ~- m

I i

TABLE 3-1 (SHEET 5 OF 10)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

' Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia f

Indicator Location with Highest Control Medium or . Type and .

Minimum Locations Annual Mean Locations ,

Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) Mean (b)

(Unit of ofAnalyses Concentration Range Distance & Range Range Measurement) Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction) ~ j Zn-65 30 NDM NDM NDM .

Zr-95 30 NDM NDM NDM l-131 (f) 15 NDM NDM NDM 5 Cs-134 15 NDM NDM NDM  ;

Cs-137 18 NDM NDM NDM ,

Ba-140 60 NDM NDM NDM La-140 15 NDM NDM NDM '

i Tritium 3000 1014 No. 88 1027 207  !

12 853-1190 Port Went 904-1170 206-208  !

(8/8) Downriver (4/4) (2/4) 122 miles t Finished Water Gross Beta 4 2.19 No. 87 2.40 2.21 at Water 36 LO-3.8 - Beaufort 1.2-3.8 1.0-4.2 Treatment (23/24) Downriver - (11/12) (10/12) .

Plants 112 miles (pCi/l) ,

t

_m. m_ .___.___m_ . _ _ __m_-.__-_..._1___ _ . . . _ _ _ _.________..m.-__..__...____._._.._m.-___.___m.mm_mm.-.._m__ _.-____-_______-m-__.__m . ___ _ _ . _ _ _ _ . _ _ _ _ u

TABLE 3-1 (SHEET 6 OF 10)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Indicator Location with Highest Control Medium or Type and Minimum Locations Annual Mean Locations Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) Mean (b)

(Unit of ofAnalyses Concentration Range Distance & Range Range Measurement) Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction)

Gamma Isotopic 36 Be-7 124 (e) NDM NDM NDM Mn-54 15 NDM NDM NDM

$ Fe-59 30 NDM NDM NDM Co-58 15 NDM NDM NDM Co-60 15 NDM NDM NDM Zn-65 30 NDM NDM NDM Zr-95 30 NDM NDM NDM Nb-95 15 NDM NDM NDM Cs-134 15 NDM NDM NDM Cs-137 18 NDM NDM NDM Ba-140 60 NDM NDM NDM La-140 15 NDM NDM NDM

.._.m. . . _ _ _ _ . . _ _ . _ . _ _ _ _ _ . _ . . . . _ , _ . _ . _ . . ~ . _ . _ _ _ . _ _ . . . _ _ . _ . . . . m ... . . . _

TABLE 3-1 (SHEET 7 OF 10) - i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Indicator Location with Highest Control Medium or Type and Minimum Locations Annual Mean Locations ,

Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) . Mean (b) l (Unit of ofAnalyses Concentration Range. Distance & Range Range Measurement) Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction)  !

I-131 1 NDM NDM NDM  !

36.

Tritium 2000 884 No. 87 921 168  ;

w 12 440-1330 Beaufort 707-1220 168-168 i do (8/8) . Downriver (4/4) (1/4)  !

I12 miles t

+

4 Anadromous Gamma Isotopic  ;

Fish I (pCi/kg wet) Be-7 655 (e) NDM NDM NA  :

Mn-54 130 NDM NDM NA  ;

Fe-59 260 NDM NDM NA [

Co-58 130 NDM NDM NA' i Co-60 130 NDM NDM NA Zn-65 .260 NDM NDM NA  !

t t

Cs-134 130 NDM NDM NA .

i 1

e E

Y L

_ - -. - .__ __ - - _. - . _ _ - ~ - . . . -- _ _ - . _

-._..__-_,.___---____-__-___--_---__-N

TABLE 3-1 (SHEET 8 OF 10)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 -

Burke County, Georgia Indicator - Location with Highest Control Medium or Type and Minimum . Locations Annual Mean Locations -

Pathway Sampled Total Number Detectable Mean (b) Name Mean(b) Mean (b)

(Unit of ofAnalyses Concentration Range Distance & Range .

Range Measurement) Performed (MDC)(a) (Fraction) - Direction (Fraction) (Fraction)

Cs-137 -150 NDM NDM NA Fish Gamma Isotopic (pCi/kg wet) 8 m Be-7 655 (e) NDM NDM NDM 4>

Mn-54 130 NDM NDM NDM Fe-59 260 NDM .NDM NDM Co-58 130 NDM NDM NDM Co-60 130 NDM NDM NDM Zn-65 260 NDM NDM NDM Cs-134 130 NDM NDM NDM Cs-137 150 193.5 No. 81 404.1 404.1 21-677 Upriver 41-1030 41-1030 (4/4) 4.7 miles (3/4) -(3/4)

TABLE 3-1 (SHEET 9 OF 10)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Indicator Location with Highest Control Medium or Type and Minimum Locations Annual Mean Locations Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) Mean (b)

(Unit of ofAnalyses Concentration Range Distance & Range Range Measurement) Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction)

Sediment Gamma lsotopic (pCi/kg dry) 4 Be-7 655 (e) 1925 No. 83 1925 83I i110-2740 Downriver 1110-2740 807-854 (2/2) 0.6 miles (2/2) (2/2) 5 Co-58 43 (e) 274 No. 83 274 NDM 274-274 Downriver 274-274 (1/2) 0.6 miles (1/2)

Co-60 70 (e) 344 No. 83 344 NDM 222-466 Dovmriver 222-466 (2/2) 0.6 miles (2/2)

Cs-134 150 NDM NDM NDM Cs-137 180 541 No. 83 541 93 499-583 Downriver 499-583 80-107 (2/2) 0.6 miles (2/2) (2/2)

TABLE 3-1 (SHEET 10 OF 10)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia NOTATIONS

a. The MDC is defined in ODCM 10.1. Except as noted otherwise, the values listed in this column are the detection capabilities required by ODCM Table 4-3. The values listed in this column are a priori (before the fact) M DCs. In practice, the a posteriori (after the fact) MDCs are generally lower than the values listed. Any a posteriori MDC greater than the value listed in this column is discussed in Section 4.

b. Mean and range are based upon detectable measurements only. The fraction of all measurements at a specified location which is detectable is placed in parenthesis,

c. No Detectable Measurement (s).

d. Not Applicable.

e. The EL has determined that this value may be routinely attained under normal conditions. No value is provided in ODCM Table 4-3.

f. Item 3 of ODCM Table 4-1 im alies that an I-131 analysis is not required to be performed on these samples w1en the dose calculated from the consumption ofwater is less then 1 mrem per year.

3-11

4.0 DISCUSSION OF RESULTS An interpretation and evaluation, as appropriate, of the laboratory results for each type sample are included in this section. Relevant comparisons were made between the difference in average results for pairs of station groups (such as, indicator and control stations) and the calculated Minimum Detectable Difference (MDD) between these pairs at the 99 percent Confidence Level (CL). The MDD was determined using the standard Student's t-test. A difference in the average values which was less than the MDD was considered to be statistically indiscernible.

Pertinent results were also compared with past results including those obtained during preoperation. The results were examined to perceive any trends. To

, provide perspective, a result might also be compared with its Reporting Level (RL) or Mimmum Detectable Concentration (MDC) whose nominal values are found in ODCM Tables 4-2 and 4-3, respectively. Attempts were made to explain any high radiological levels found in the samples. During the year, there were no failures in the laboratory analyses for any of the samples in attaining the MDCs required by ODCM Table 4-3.

Unless otherwise indicated, any reference made in this section to the results of a previous period are results which have been purged of any obvious extranea.is short term impacts. During preoperation, these included the nuclear weap ns test in the fall of 1980 (apparently the last in a series of atmospheric tests conducted on mainland China over o 9 year period), abnormal releases from the Savannah River Site (SRS), and the Chernobyl incident in the spring of 1986. After operation commenced, short term impacts included abnormal releases from SRS during 1987 and 1991. A significant component of the Cs-137 which has often been found in various samples over the years (and continues to be found) is attributed to these nuclear weapons tests.

All results were tested for conformance to Chauvenet's criterion (G. D. Chase and J. L. Rabinowetz, Principles of Radioisotooe Methodology, Burgess Publishing Company,1962, pages 87-90) to flag any values which might differ from the others in its set by a relatively large amount. Identified outliers were investigated to determine the reason (s) for the deviation from the norm. If due to an equipment malfunction or other valid physical reason, the anomalous result was deemed non-representative and excluded from the data set. No datum was excluded for failing Chauvenet's criterion only. Any exclusions are discussed in this section under the appropriate sample type. ,

The annual land use census as required by TS 6.7.4.g(2) and ODCM 4.1.2 was conducted on December 10,1996 to determine the locations of the nearest permanent residence, milk animal 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; the locations of the nearest beef cattle in each sector were also determined. A milk animal is a cow or goat producing milk for human consumption. Land within SRS was excluded from the census. The census results are tabulated in Table 4-1.

4-1

I l

i 1 3- I

! TABLE 4-1 1

LAND USE CENSUS RESULTS i 1

j Distance in Miles to Nearest Location in Each Sector '

+

SECTOR RESIDENCE MILK ANIMAL BFFF CATTLE GARDEN i N * * *

• l NNE * * * * '

.NE * * *

• ENE * * *

• i E * * *

• ESE' 4.2 * * *

'i SE 4.3

• 4.9 4.9

, SSE 4.6

• 4.3

• S 4.3 * * *

.i SSW 4.7

• 4.6

• l 1

SW 2.8

• 2.8

• WSW l.2

• 2.8

• l

-W 3.7

• 4.4 *

' i WNW l.7

• 1.7 3.3 NW l.6

• 1.8

• i NNW l.5 * * * '

)

l- -

• None within 5 miles and outside the SRS.

1 l

1 a

i i

i 1

i j

l i

i 4-2

I ODCM 4.1.2.2.1 requires a new controlling receptor in ODCM 3.4.3, if the land use census identifies a location that yields a calculated dose greater than that currently being calculated. An analysis of the census results showed there was none.

ODCM 4.1.2.2.2 require's that whenever the land use census identifies a location which would yield a calculated dose (via the same ingestion pathway) 20 percent I greater than that from a current indicator station, the new location must become a REMP station (if samples are available). None of the gardens yielded a calculated dose 20 percent greater than that for any of the current indicator stations for l vegetation. No milk animals were found in the census. l The annual survey of the Savannah River downstream of the plant for 1 approximately 104 miles was conducted on September 17,1996 to identify those  !

who use water from the river for purposes of drinking or irrigation. As in all previous surveys, no intakes for drinking water or irrigation were observed. This

)

result was corroborated by information obtained from the Georgia Department of Natural Resources on September 19,1996 and the South Carolina Department of IIealth and Environmental Control on September 23,1996; it was confirmed that no water withdr,wal permits for drinking water or irrigation purposes had been issued for the Savannah River. The two water treatment plants used as indicator stations for drinking water are located further downriver.

4-3

4.1 Airborne in accordance with Tables 2-1 and 2-2, airborne particulates and airborne radiciodine are collected at 5 indicator stations (Nos. 3,7,10,12 and 16) which encircle the site and are on the site periphery, at a nearby community station (No.

35), and at a control station (No. 36) which is about 14 miles from the plant. At these locations air is continuously drawn in sequence through a Gelman Type A/E glass fiber filter and a SAIC CP-200 charcoal canister to retain airborne particulates and to adsorb airborne radioiodine, respectively.

The filters and canisters are collected weekly. Each of the air particulate filters is counted for gross beta activity. A gamma isotopic analysis is performed quarterly on a composite of the air particulate filters for each station. Each charcoal canister is analyzed for I-131 by gamma spectroscopy.

There were local power outages of several hours duration on a number of occasions throughout the year. Longer outages occurred at Station 36 as a result i oflightning damage to the wiring, a blown fuse caused by the lightning and the replacement of the power cable. The gross beta results for each of the affected samples were found to conform with Chauvenet's criterion; so none of the results were excluded from the data base. The affected stations and exposure periods (identified by the collection dates), and the hours out of service were as follows.

Station 02/06 05/26 07/09 08/06 08/13 09/04 11/19 No. 3 4.8 6.6 6.5 No. 7 4.8 9.0 6.6 No.10 4.8 5.4 6.5 No.12 4.8 7.0 6.4 No. 35 4.6 No. 36 57.9 87.3 7.0 As seen in Table 3-1, the averag,e weekly gross beta activity during 1996 for the indicator stations was 2.3 fCi/m greater than that for the control station.

However, this difference was not discernible, since it was less than the MDD, calculated as 4.8 fCi/m . During the 9 year period from 1987 through 1995, the average $eekly activity for the year 3at the indicator stations randomly varied from 1.0 fCi/m greater than to 0.6 fCi/m less than that for the control station. The average weekly activity for the indicator stations over this entire 9 year period 3

exceeded that for the control station by approximately 0.1 fCi/m . The overall average weekly activity for the indicator stations during preoperation was 0.8 fCi/m greater than that for the control station.

3 The average weekly gross beta activity in units ofICi/m for the indicator, control and community stations during 1996 are compared below with those during the l previous years of operation, with the entire preoperation period (which began in

! September 1981 for the air monitoring stations) and with the range of annual averages during preoperation.

J 4-4 l

Period Indicator Control Community 1996 23.3 21.0 20.0 1995 21.1 20.7 20.7 1994 20.1 20.3 19.8

~

1993 21.2 21.4 20.3 l992 18.7 19.3 18.0 1991 19.3 19.2 18.6 1990 19.6 19.4 18.8 1989 19.1 18.2 18.8 1988 24.7 23.7 22.8 1987 23.0 23.5 22.3 Preop Overall 22.9 22.1 21.9 Preop Range 18.1-28.1 18.3-26.5 18.3-26.5 The above tabulation shows the average activities for all the station groups were fairly flat for the 8 year period (1989 through 1996), except the 1996 average fog the indicator stations was a littig higher . This is due to an activity of 527 fCi/m with an uncertainty of 20 fCi/m at the 95% CL found for the October 15,1996 collection at Station 16 which is located in the NNW sector at 1.4 miles. If this result)were excluded, the gverage for the indicator stations would become 21.4 fCi/m and only 0.4 fCi/m greater than the control station average this difference 3

would not be discernible since it is less than the MDD of 1.9 fCi/m .

The gross beta activities for the October 15,1996 collection at the other 6 stations were normal. A gamma isotopic analysis was performed on the Station 16 sample. i The manmade radionuclides detected, along with the activity foynd and its uncertainty, the RL and routine MDC for each in units of fCi/m , and their half lives were as follows.

Radionuclide Activity 95% CL RL MDC Halflife I-131 3.8 1.4 900 70 8.07 days Cs-137 21.6 4.0 20,000 60 30.2 years Ba-140 84.2 10.0 7,000 118 12.8 days La-140 99.8 10.0 30,000 46 40.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> The radiological levels for three of these radionuclides is seen to be less than their MDCs and just over twice its MDC for the other one. A scrutiny of the spectrum indicates that other fission products at very low levels (Cs-134 & Ce-141) and traces of Co-60 may have also been present. The EL does not use Ba-140/La-140 and does not use Cs-134 or Ce-141 calibration standards with the gas proportional counter.

The process for handling effluent air filters and the environmental samples within the EL were reviewed. The effluent samples are processed in a separate lab and do not come in contact with the environmental samples. The environmental samples remain in the collecting dishes until they are counted. If this had been a contamination event, more than one environmental filter would likely have been affected since all filters are manipulated and counted on the same run.

4-5

l i

The EL performs analyses on glass fiber filters and charcoal canisters for the I plants' gaseous efiluents and water samples from the plants' waste tanks for liquid  !

effluents. These analyses are performed for Alabama Power Company's Farley Nuclear Plant and GPC's Hatch Nuclear Plant as well as for VEGP. Whereas the

. gaseous releases generally include I-131 and often Co-60 and Ce-141, the liquid  !

effluents generally include all of the radionuclides mentioned above associated  !

. with the Station 16 particulate filter collected on October 15,1996. This ofitself I indicates the possibility of contamination, (although a very slim one considermg )

the strict procedures and good practices followed by the EL).  ;

Actions taken by the EL to assure the validity of the analyses results regarding the )

sample collected at Station 16 on October 15,1996 were as follows: l The sample was recounted to verify the count rate; i The instrument QCs were recounted to verify there were no shifts in the  !

instruments; i The sample was counted in a different holder to assure no contamination 1

was present; The sample was surveyed with a GM counter and found to contain three times the background count rate; .

The sample was recounted on the gamma system for 40,000 seconds to obtain good counting statistics and to verify the identity of the radionuclides; The activities found verified the Ba-140 and La-140 were in equilibrium and A recount of the sample verified the La-140 halflife.

A review of the plant's meteorological data for the one week period ending at the time of the collection on October 15,1996, showed the wind blew into the NNW sector for only about 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />;3the depleted X/Q for Station 16 over this period was determined to be 9 E-8 sec/m . The gaseous releases from the plant during the week were as follows.

Radionuclide: Cr-51 Co-58 Co-60 Nb-95 I-131 Activity (uCi): 0.586 0.871 0.414 0.172 19.0 i

The only measured radionuclide released from the plant which appeared on the j particulate filter was 1-131. Ilowever, the quantity released during this period  ;

would have had to have been more than three orders of magnitude greater to {

account for the level fWnd in the particulate filter.

The particulate samples collected a week later on October 22,1996 showed the gross beta results at all stations to be normal. A gamma isotopic analysis was performed on the Station 16 sample; no manmade radionuclides were detected. ,

On October 29,1996, grass and soil samples were collected at Station 16 for >

gamma isotopic analysis; no manmade radionuclides were detected in the grass  !

sample and only Cs-137 at a background level of 88.7 pCi/ kg dry was found in ,

the soil sample. l l

4-6

i l

l i

During the one week period ending on October 15,1996, there were no abnormal l releases from SRS and only normal readings were found at nearby sampling l

stations operated by SRS or the State of Georgia. These nearby negative results for the same time period indicate that the source of the activity is not in the

environment.

In conclusion, the radiation levels found in the particulate sample collected on October 15 at Station 16 are believed to be genuine. Plant releases as a cause are ruled out. By climination, laboratory contamination remains a possibility although no obvious causes of cross contamination were discovered. This incident and the importance of avoiding cross contamination were reviewed with laboratory

. personnel to avoid reoccurrence.

During 1996 as in all previous years of operation except 1987, no man-made radionuclides were detected from the gamma isotopic analysis of the quarterly composites of the air particulate filters. Dyring 1987, Cs-137 was found in one ,

indicator composite at a level of 1.7 fCi/m . During preoperation, Cs-137 was l 2

found in an eighth of the indicator composites and a seventh of the control j 3

composites with average levyls of 1.7 and 1.0 fCi/m , respectively; the MDC for J l

airborne about 8 percentCs-137 is 6') tUi/m o{tl e ir/.iicator . Also, composites; duringlevel the average preoperations, was 1.2 fCi/m its Cs-134 was MDC is 50 fCi/m As during previous years of operation, airborne 1-131 was not detected in any sample during 1996. During preoperation, positive results were obtained only i during the Chernob 1 incident when levels as high as 182 fCi/m3 were obtained. l 3

The MDC and RL or airborne I-131 are 70 and 900 fCi/m , respectively.

I 4-7

l I

4.2 Direct Radiation Direct (external) radiation is measured with thermoluminescent dosimeters (TLDs). Two Panasonic UD-814 TLD badges are placed at each station. Each badge contains three phosphors which a e composed of calcium sulfate (with thulium impurity) ;rystals. The gamma dose at each station is nominally based upon the average readings of the phosphors from the two badges. The two badges for each station are sealed in a thin plastic bag for protection from moisture while in the field. The badges are nominally exposed for pcriods of a quarter of a year (91 days).

Two TLD stations are established in each of the 16 meteorological sectors about the plant forming two concentric rings. The stations comprising the inner ring (Nos. I through 16) are located near the site boundary, while those comprising the outer ring (Not 17 through 32) are located at distances of about 5 miles. The 16 stations fonning the inner ring are designated as the indicator stations. Each of the 4 control stations (Nos. 36,37,47 and 48)is over 10 miles from the plant. Special interest areas consist of a hunting cabin (No. 33), the town of Girard (No. 35), and the employees' recreational area (No. 43).

As shown in Table 3-1, the average quarterly exposure acquired at the indicator stations (inner ring) during 1996 was 0.1 mR greater than that acc.uired at the control stations. This difference was not discernible since it was : ess than the .

MDD of 1.0 mR. During the 9 year period from 1987 through 1995, the average quarterly exposure for the year at the indicator stations randomly varied from 0.7 mR greater than to 0.5 mR less than that for the control stations. The average quarterly exposure for the control stations over this period was greater than that for the indicator stations by less than 0.1 mR. The overall average quarterly exposure for the control stations during preoperation was 1.2 mR greater than that for the indicator stations.

The quarterly exposures acquired at outer ring stations during 1996 ranged from i 9.7 to 18.5 mR; the average (to 3 significant figures) was 12.3 mR, the same as that for the inner ring stations. The average for the outer ring stations was actually i 0.0026 mR greater than that for the inner ring stations; however there was no discernible difference between the averages for the inner and outer ring stations, I since the difference was less than the MDD of 9.7 mR. For the 9 year period 1 beginning in 1987, the average quarterly exposure for the year at the inner ring i stations varied from 0.9 mR greater than to 0.3 less than that at the outer ring i stations. The average quarterly exposure for the inner ring stations over this 9 year i period was about 0.4 mR greater than that for the outer ring stations. The overall l average quarterly exposure for the inner ring stations during preoperation was 0.6 ,

mR greater than that for the outer ring stations. I Listed below for the indicator, control and outer ring stations, are the average quarterly exposures in units of mR obtained during each year of operation, the entire period of preoperation (which began in August 1981 for TLD stations), and the range of annual averages obtained during the calendar years of preoperation.

4-8

Pened Indicator Control Outer Rine 1996 12.3 12.2 12.3 1995 12.0 12.5 12.3 t

1994 12.3 12.I 11.9 1993 12.4 12.4 12.1 1992 12.3 12.5 12.1 1991 16.9 17.1 16.7 1990 16.9 16.6 16.3 1989 17.9 18.4 17.2 1988 16.8 16.1 16.0 1987 17.6 17.9 16.7 4

Preop Overall 15.3 16.5 14.7 Preop Range 15.1-16.9 14.1-18.2 12.5-16.2 The average quarterly exposures in units of mR at the special interest areas for the same periods as given above are listed below. These exposures are within the

, range of those acquired at the other stations.

Penod Station 33 Station 35 Station 43 i 1996 13.0 13.6 12.I 1995 13.3 13.5 12.3 1994 12.6 13.6 12.0 1993 12.9 13.3 12.1 l 1992 12.8 13.5 12.0 i l991 17.3 19.6 17.0 1990 16.8 18.9 16.2 1989 21.2 18.7 17.4 j 1988 19.7 18.1 14.8  !

1987 21.3 18.5 15.2 I Preop Overall 16.6 15.1 15.3 Preop Range 13.6-19.9 12.6-17.6 13.9-25.0 l Although, there were no failures at any station in obtaining a measurement of the quarterly gamma dose during 1996, the reading for TLD 14A for the third quarter was deemed unacceptable as it had a standard deviation greater than the self imposed limit of 1.4; a higher value is interpreted as an indication of a suspect TLD. Consequently, the reading for the companion badge only was used to determine the exposure for the third quarter at this station. No reason was found for the high standard deviation. It was visually inspected under a microscope; the glow curve and test results for the anneal data and the element correction factor were reviewed.

The standard deviation limit of 1.4 was calculated using a method developed by the American Society for Testing and Materials (ASTM Special Technical Publication 15D, ASTM Manual on Presentation of Data and Control Chart Analysis, Fourth Revision, Philadelphia, PA, October 1976). The calculation was based upon the standard deviations obtained with the UD-814 badges during 1992.

4-9

4.3 Milk In accordance with Tables 2-1 and 2-2, milk samples are collected biweekly from two control stations, the W. C. Dixon Dairy (No. 98) and the Boyceland Dairy (No. 99). Gamma isotopic and I-131 analyses are performed on each sample.

Milk has not been available from an indicator station (a location within 5 miles of I the plant) since April 1986 when the cow from which milk was being obtained  !

went dry and was subsequently removed from the area. The availability of milk  !

within 5 miles of the plant was meager throughout preoperation and an adequate I location is yet to be obtained during operation. As discussed in Section 4.0, no l' milk animals were found in the 1996 land use census.

No man-made radionuclides were found from the gamma isotopic analysis of the milk samples during 1996. During preoperation and each year of operation j through 1991, Cs-137 was found in 2 to 6 percent of the samples at levels ranging  ;

from 5 to 27 pCi/1. The MDC and RL for Cs-137 in milk are 18 and 70 pCi/1, respectively. During preoperation, Cs-134 was detected in one sample and in the first year of operation, Zn-65 was detected in one sample.

! I-131 may have been detected in one of the 1996 milk samples - that collected at Station 99 on April 24 where the results of the isotopic analysis rendered a 1-131 I level of 0.244 pCill with an uncertainty of 0.316 pCi/l at the 95% CL. This i sample is suspect because its uncertainty is somewhat greater than its activity. I In 1990, I-131 was reported in two samples but its presence was questionable due  !

to large counting uncertainties.1-131 was not detected during other years of operation. During preoperation, positive I-131 results were found only during the Chernobylincident when the levels ranged from 0.53 to 5.07 pCi/1. The MDC and

RL for 1-131 in milk are 1 and 3 pCi/l, respectively.

e f

I A

4-10

4.4 Vegetation in accordane .. Tables 2-1 and 2-2, gamma isotopic analysis is perfbrmed on each grass sa.. ,4e collected monthly at two indicator stations which are located onsite near the site boundary in different meteorological sectors (Nos. 7 and 15) and at one control station located about 17 miles from the plant (No. 37). To enhance the statistical base for the indicator stations, samples continued to be collected on a trial basis during the year from two additional grass plots; one is in the E sector at 0.9 milesjust north of Plant Wilson, the other is in the SW sector at 1.2 miles adjacent to Gate 1, No man-made radionuclides were detected during 1996; only Cs-137 has been detected during operation. The average level of Cs-137 found in units of pCi/kg wet along with the fraction of detectable measurements at the indicator and control i stations is shown below for each year of operation and the period of preoperation.

Indicator Stations Control Station  ;

Ecried Average Entetton Average Fraction 1996 0.0 0.000 0.0 0.000 1995 57.8 0.083 179.0 0.083 1994 20.7 l

0.083 57.4 0.083 0 1993 46.4 0.333 34.1 0.083 l 1992 38.1 0.250 144.0 0.083 1991 35.3 0.208 62.4 0.083 i 1990 30.0 0.083 102.0 0.167 i 1989 9.7 0.042 0.0 0.000 i 1988 38.7 0.280 0.0 0.000 j 1987 24.4 0.318 61.5 0.250 i Preop 54.6 0.573 43.7 0.193 l

No trend is recognized in these data. The MDC and RL for Cs-137 in vegetation samples are 80 and 2000 pCi/kg wet, respectively.  !

1 During preoperation as a consequence of the Chernobyl incident, I-131 was found l in nearly all the samples collected (some at elevated levels) for a period of several weeks. During this period Cs-137 was also found in nearly all the sampleE  !

collected, and Co-60 was found in one of the samples.

Chapter 10 of the ODCM specifies that the frequency for a monthly surveillance (such as, the collection of grass samples) is at least once per 31 days. The maximum allowed extension is not to exceed 25% of the surveillance interval.

Thus the maximum interval between two consecutive collections of grass is less than 39 days. The grass collections on two occasions - January 30 and December 31,1996 - were each 42 days after the previous collection. Each of these deviations occurred because the earlier collection was advanced a week without considering how the interval to the next collection would be affected. Collection personnel were counseled on this issue to avoid reoccurrence.

4-11

4.5 River Water Surface water is composited from the Savannah River at three locations using ISCO automatic samplers. Small quantities are collected at intervals not exceeding a few hours. River water samples collected by these machines are picked up monthly; quarterly composites are made from the monthly collections.

1 The collection points consist of a control station (No. 82) which is located about 0.4 miles upriver of the plant intake structure, an indicator station (No. 83) which  !

is located about 0.4 miles downriver of the plant discharge strt : ture, and a special station (No. 84) which is located approximately 1.3 miles downriver of the plant discharge structure. A discernible increase in the radiological levels found m samples collected at the indicator station over those collected at the control station might be attributed to the plant radiological releases. Radiological levels found at the special station might represent those for the river as a whole (plant releases combined with those from other sources).

A gamma isotopic analysis is conducted on each monthly collection. As in all previous years of operation, there were no gamma emitter radionuclides ofinterest detected in the river water samples collected during 1996.

A tritium analysis is perfonned on each quarterly composite. As indicated in Table 3-1, the average level found at the indicator station was 800 pCi/l greater i than that found at the control station. However, this difference was not discemible  !

since it was less than the calculated MDD of 2147 pCi/1, and on this basis, the l increase is not attributed to plant releases. At the special station, the results ranged from 558 to 1090 pCi/l. The MDC for tritium in river water is 3000 pCi/1; the RL is 10 times greater.

Listed below for each year of operation are the average tritium levels found at the special, indicator and control stations, along with the increase in the average level at the indicator station over that for the control station, the MDD between these two stations, and the total liquid releases of tritium from the plant. All of these values are in units of pCill except for the releases which are in units of Ci.

. Xear Special Indicator Control Increase MDD Releases 1996 719 1187 387 800 2147 1637 1995 699 597 236 361 766 968 1994 774 1258 257 1001 2009 1052 1993 616 712 238 474 1526 761 1992 929 1064 371 693 714 1481 1991 1298 1299 828 471 626 1094 1990 1081 1142 392 750 766 1172 1989 1268 1293 538 755 518 918 1988 1430 843 427 416 271 390 1987 1411 680 524 156 416 321 4-12

\

l i

The following observations are noted regarding the above data tabulation.

1. The tritium released from the plant increases the overall tritium level in the river; these releases could account for the increases in the levels found at the indicator station over those at the control station.  !

2. The releases for 1996 are higher than any in a previous year.

3. There is not a good correlation between the releases and the increases.

4. No trend is recognized in the levels at any of the stations or in the quantity of the releases.

5. There was a discernible difference between the indicator and control stations I only during 1988 and 1989. This may be explained by the higher MDD values l found in subsequent years which result from greater variability found in the quarterly tritium levels.

I

6. In the first two years of operation, the tritium level at the special station was l somewhat greater than that at the indicator station; whereas in recent years, the i level at the special station has generally become less than or about the same as that at the indicator station. This is interpreted as an indication that contributions from other tritium sources have diminished while plant releases have become a larger percentage of the total source.

i The maximum annual whole body dose that an individual member of the public (a  !

child) would receive from drinking river water downriver of the plant with an j average tritium concentration of 800 pCi/l(the possible plant contribution) was  !

conservatively calculated to be 0.083 mrem or 2.8 percent of the 3 mrem limit for ,

releases from one unit as stipulated by ODCM 2.1.3.  !

The annual downriver survey of the Savannah River to determine if river water is ,

being used for purposes of drinking or irrigation is discussed in Section 4.0.  !

4-13

4

-l i

i l

4.6 Drinking Water i i Samples are collected at a control station (No. 80), the Augusta Water Treatment i Plant in Augusta, Georgia, which is located about 56 miles upriver, and at two ,

j indicator stations (Nos. 87 and 88), the Beaufort-Jasper County Water Treatment l

. Plant near Beaufort, South Carolina and the Cherokee Hill Water Treatment Plant  ;

near Port Wentworth, Georgia, which are respectively located approximately 112 and 122 miles downriver. These upriver and downriver distances in river miles are the distances from the plant to the point on the river where water is diverted to the intake for each of these water treatment plants.

j At each of the water treatment plants, monthly collections are made of river water )

which is composited near the intake of the water treatment plant (raw drinking i water) and of grab samples of finished drinking water; quarterly composites are

! made from the monthly collections. Gross beta and gamma isotopic analyses are i conducted on each of the samples collected monthly. Tritium analysis is '

conducted on the quarterly composites. Although an I-131 analysis is not required to be conducted on these samples as the dose calculated from the consumption of

water is less than 1 mrem per year (see ODCM Table 4-1), an 1-131 analysis is conducted on each of the grab samples of the monthly collections of finished water

! since a drinking water pathway exists.

i Listed below for each year of operation are the average gross beta levels in units of

pCi/l found in the monthly collections for raw and finished drinking water at the

. indicator and control stations, along with the increases in the average levels for the indicator stations over those for the control station, and the calculated MDD j between these two station groups.

. Period Indicator Control Increase MDD i  !

j - RAW  !

1996 5.83. 3.02 2.81 3.28 E

1995 3.06- 4.90 -1.84 1.30 1994 3.51 3.47 0.04 1.24 1993 3.17 2.83 0.34 1.09 .

l 1992 2.73 2.70 0.03 0.96

] 1991 2.83 3.08 -0.25 2.47

-1990 2.53 2.55 -0.02 0.72 i 1989 2.93 3.05 -0.12 0.85 1988 2.67 3.04 -0.37 1.36

1987 2.20 5.50 -3.30 4.40 I

b l 4

4 4

4 J- 4-14 4

)

4

4 i

i i Period Indicator Control Increase MDD l FINISilED  !

1996 2.19 2.21 -0.02 0.71 l 1995 2.74 2.32 0.42 0.72

! 1994 2.40 2.68 -0.28 2.40

[

1993 1992 2.23 2.09 2.30 1.67

-0.07 0.42 2.23 i 0.44

^

? 1991 1.90 1.53 0.37 0.47 i 1990 2.08 1.92 0.16 0.58 1989 2.36 2.38 -0.02 0.57

1988 2.28 2.35 -0.07 0.88 l 1987 2.10 1.80 0.30 0.70 i

The readings for the raw drinking water at the indicator stations for 1996 are seen l to be much higher than in previous years of operation. The raw drinking water

' samples collected at Beaufort for September through December were muddy; the sediment content was an order of magnitude greater than that at the other stations. i The gross beta readings for these 4 samples ranged from 8.96 to 24.95 pCi/l with  !

an average of 17.97 pCi/l whereas the reading for the other 8 samples at this i ' station ranged from 190 to 4 48 pCi/l with an average of 3 26 pCi/1 None of i these high readings were excluded from the data base as each conformed with 8

Chauvenet's criterion. The intake line for the raw drinking water rested on a i

concrete floor; apparently sediment had recently built up on the floor. In January l

1997, the intake 1me was shortened to get it off the bottom; clearer samples are l

l expected to return subsequently.

j No trend is recognized from the data in the above tabulation. In all previous years

of operation, except 1995, there was no discernible difference between the i average levels at the indicator and control stations for both the raw and the  !

! finished water since the MDD was greater than the difference. In 1995 however, a  ;

!. discernible difference was found in the average results for raw water between the l 3 two station groups; the higher result was found for the control station. No i- significance is perceived from this finding. The MDC for gross beta in water is 4 7

pCi/1.

l As indicated in Table 3-1, there were no positive results for the radionuclides of i

interest from the gamma isotopic analysis of the monthly collections of both raw

' and finished drinking water. Only one positive result has been found since operation began; Be-7 was found at a level of 68.2 pCi/l in the sample collected for September 1987 at Station 87. The MDC assigned for Be-7 in water is 124 pCi/1.

As indicated in Table 3-1, there were no positive results from the I-131 analysis of the finished drinking water samples. Similar results were obtained in previous years of operation. The MDC and RL for I-131 in drinking water are 1 and 2  !

pCi/1, respectively. i 4-15

- - - . . . ~ - _ . _ - . . - .-.-. . - - .- - - --.. -

l I

J l

Listed below for each year of operation are the average tritium levels in units of pCi/l found in the quarterly composites of raw and finished drinking water collected at the indicator and control stations, along with the increases in the average levels at the indicator stations over those at the control station, and the calculated MDDs between these two station groups. The average levels at the  ;

indicator stations for 1991 and 1992 have been purged of the impact of the inadvertent release at SRS of 7500 Ci of tritium to the Savannah River about 10 miles downriver of VEGP between December 22 and 25,1991.

Penod Indicator Control Increase MDD RAW 1996 1014 207 807 151 1995 917 201 716 NA 1994 871 NDM NA NA 1993 955 NDM NA NA 1992 1131 179 952 353 1991 1471 165 1306 834 1990 1320 266 1054 572 1989 2508- 259 2249 1000 1988 2630 240 2390 580 1987 2229 316 1913 793 FINISHED 1

1996 884 324 560 NA 1995 847 279 568 NA 1994 880 131 749 270 1993 993 NDM- NA ~ NA I 1992 1162 211 951 427 1991 1240 225 1015 647 l 1990 1299 404 895 1131 l 1989 2236 259 1977 627 1988 2900 270 2630 830 1987 2406 305 2101 1007 l From Table 3-1, it may be seen that a detectable measurement of tritium was i found in only one of the samples collected at the control station during 1996 for the finished drinking water. A modified t-test that compared the single positive result from the control station with the average result from the indicator stations was employed to determine if there was a discernible difference between the two data groups for both the raw and finished drinking water. It was determined that there was no discernible difference. A MDD cannot be determined with the modified t-test calculation; therefore, not applicable (NA) is entered in the MDD column above for the finished drinking water.

4-16

I The above data tabulations show that except for the finished drinking water in .

1990, there has been a detectable difference between the two station groups for i both raw and finished drinking water during every previous year of operation (whenever detectable measurements were made for both station groups).

The above tabulations show that in recent years, the tritium levels in the drinking  !

water sam ales, both raw and finished, at the indicator stations have become less '

than half tiose found during the first three years of operation.

c

?

i l

h t

I i

i I

s i

J l

l l

4-17  ;

4.7 Fish Table 2-1 calls for the collection of at least one sam ple of any anadromous species of fish in the vicinity of the plant discharge during the spring spawning season, and for the semiannual collections of at least one sample of any commercially or recreationally important species in the vicinity of the plant discharge area and in an area not influenced by alant discharges. Table 2-1 also calls for a gamma isotopic analysis on the ec ible portions of each sample collected.

As stated in Table 2-2 a stretch of the river of about 5 miles 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 1.4 to 7 miles downriver of the plant discharge structure. For anadromous species, all collection I points can be considered as indicator stations.

On March 29,1996 American shad, an anadromous species, was collected. As in all but two previous years of operation, no positive results for the radionuclides of

)

j interest were detected in 1996 from the gamma isotopic analysis, in 1987 as well 1 as in 1991, Cs-137 was found in a single sample of American shad at minuscule  !

levels of 10 and 12 pCi/kg wet, respectively. J The dates and compositions of the semiannual catches at the indicator and control stations during 1996 were as shown below.

Date Indicator Control April 23-24 Channel Catfish Largemouth Bass l Largemouth Bass Redear Sunfish 1 October 15 Channel Catfish ' Channel Catfish Largemouth Bass Largemouth Bass As indicated in Table 3-1, Cs-137 was the only radionuclide ofinterest found in the semiannual collections. It has been found in all but two of the 85 samples collected during operation. In Table 3-1, the average level at the indicator station is seen to be 210.6 pCi/kg wet less than that at the control station. This difTerence is not discernible, however, since it is less than the calculated MDD of 1093 pCi/kg wet; a discernible difference has not occurred since operations began.

At each of the stations, the Cs-137 level found in one of samples during 1996 was ~ )

the second highest attained at that station during operation A level of 677 pCi/kg i wet was found in the largemouth bass sample collected in April at the indicator station; the previous high was 1050 pCi/kg wet in 1993. In October 1996, a level of 1030 pCi/kg wet was found in the largemouth bass sample at the control station; -

the previous high was 1300 pCi/kg wet in 1990.

Listed below for each year of operation are the average levels of Cs-137 in units of pCi/kg wet found in fish samples at the indicator and control stations.

4-18

.Yggt Indicator Control 1996 194 404

.1995 125 96 1994 165 200 1993 360 84 1992 178- 80 1991 105 211 1990 103 249 1989 117 125 1988 66 116.

1987 337 119

. No trend is recognized in the above tabulation of 10 years of data. The average Cs-137 level at the indicator station was greater than that at the control station for four of the years. Over the entire 10 year period, the average level at the indicator station was 6.6 pCi/kg wet greater than that found at the control station. The MDC and RL for Cs-137 in fish are 150 and 2000 pCi/kg wet, respectively.

The only other radionuclide ofinterest found in fish samples during past years of operation is I-131. In 1990, it was found in one sample at both the indicator and control stations at levels of 13 and 12 pCi/kg wet, respectively; in 1989, it was found in one sample at the indicator station at a level of 18 pCi/kg wet. The MDC assigned to I-131 is 53 pCi/kg wet.

l 1

i 4-19

l l

l l

l i

i 4.8 Sediment i Sediment was collected along the shoreline of the Savannah River on April 2 and October 7,1996 at Stations 81 and 83. Station 81 is a control station located about  :

2.5 miles upriver of the plant intake structure while Station 83 is an indicator '

station located about 0.6 miles downriver of the plant discharge structure. A gamma isotopic analysis was performed on each sample.  :

i l Listed below for each year of operation are the average levels in units of pCi/kg l dry for the radionuclides ofinterest found in the regular samples collected at the )

indicator and control stations along with the fractions of detectable measurements j and the MDCs. Each of these radionuclides is found in the plant's liquid releases.  ;

Xggg Indicator Fraction Control Fraction j Be-7, MDC=655 l 1996 1925 1.0 831 1.0

' 1995 1865 1.0 1575 1.0 1994 1203 l

1.0 964 1.0 1 1993 711 1.0 902 1.0 '

l 1992 2038 1.0 380 1.0 1991~ 826 1.0 427 1.0 l 1990 465 1.0 545 1.0 1 1989 1300 1.0 . 415 1.0 l 1988 970 1.0 810 1.0 1987 987 1.0 543 1.0 L Mn-54, MDC=42 l

1994 32 0.5 NDM- 0.0 1989 18 0.5 NDM 0.0 1988 22 0.5 NDM 0.0 .l l Co-58, MDC=43 '

l 1996 274 0.5 NDM 0.0 1995 42 0.5 NDM 0.0 1994 18 0.5 NDM 0.0 l

1992 124 0.5 NDM 0.0 1990 140 0.5 NDM 0.0 1989 135 1.0 NDM 0.0 1988 190 1.0 NDM 0.0 t

4-20 l

1

.Ycar Indicator Fraction Control Fraction Co-60, MDC=70 1996 344 1.0 NDM 0.0 1995' 267 1.0 NDM 0.0 1994 85 1.0 NDM 0.0 1993 66 1.0 NDM 0.0 1992 60 1.0 NDM 0.0 l 1991 113 0.5 NDM - 0.0 1990 46 0.5 NDM 0.0 1989 46 1.0 NDM 0.0 1988 62 0.5 NDM 0.0 1-131, MDC=53 1994 51 0.5 41 0.5 1992 194 0.5 20 0.5 Cs-137, MDC=180 1996 541 1.0 93 1.0 1995 357 1.0 123 1.0 1994 240 1.0 118 1.0 1993 345 1.0 115 1.0 1992 259 1.0 111 1.0 1991 246 1.0 100 1.0 1990 155 1.0 140 1.0 1989 230 1.0 125 1.0 1988 175 1.0 175 1.0 1987 209 1.0 111 1.0 Although no trend is recognized in the above tabulation of 10 years of data, the levels at the indicator station generally predominate those at the control station.

As in all previous years of operation, positive results for Be-7 and Cs-137 were found in each sample. Although Mn-54 and I-131 were not detected during 1996,  ;

new highs for Co-58, Co-60 and Cs-137 were found at the indicator station. l For Be-7, the average level at the indicator station during 1996 was 1094 pCi/kg dry greater than that at the control station; however, this difference is not i discernible as it is less than the calculated MDD of 5679 pCi/kg dry. There .

continues to be no discernible difference between the indicator and control stations  ;

for Be-7 and on this basis its presence at the indicator station is not attributed to plant releases.

4-21

..m. ,. ,m._ - _ . ..

For Cs-137, the average level at the indicator station during 1996 was 448 pCi/kg dry greater than that at the control station; this difference is discernible as it is

. greater than the MDD of 307 pCi/kg dry. This is the first occasion during operation when a discernible difference was found. The above tabulation shows the average level at the control station was never greater than that at the indicator station. The average level at the indicator station over this entire 10 year period was 155 pCi/kg dry greater than that at the control station.

The persistently higher levels of Cs-137 found at the indicator station, plus the contmuing presence of Co-60 and the frequent presence of Co-58 at the indicator station and their absence at the control station are indicative of plant releases. The annual whole body dose to an individual by direct radiation from sediment with the average concentrations of these 3 radionuclides found at the indicator station less any found at the control station was estimated (employing the methodology and parameters of NRC Regulatory Guide 1.109, Revision 1, October 1977), to be approximately 13.8 microrem or about 0.46 percent of the 3 mrem limit for liquid releases from one unit as stipulated by of ODCM 2.1.3. This extremely low dose, although calculable, is insignificant with respect to radiation dose and regulatory limits.

4 4-22

5.0 INTERLABORATORY COMPARISON PROGRAM In conformance with TS 6.7.4.g(3) and ODCM 4.1.3, the EL participates in an ICP which satisfies the requirements of Regulatory Guide 4.15, Revision 1, " Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment", February 1979. The guide indicates that the ICP is to be conducted with the EPA's (Environmental Protection Agency)

Environmental Radioactivity Laboratory Intercomparison Studies (Cross-check)

Program or an equivalent program, and that the ICP should include all of the determinations (sample medium /radionuclide combinations) that are both offered by the EPA and included in the REMP. The ICP had been conducted utilizing the EPA program through the end of 1995 when it became unavailable to utilities.

Like the EPA program, the replacement ICP which was initiated at the beginning of 1996 is a third party blind testing program which provides a means to ensure independent checks are performed on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices. It includes essentially the same determinations with the same frequencies that had been utilized with the EPA program.

The replacement ICP is conducted by Analytics, Inc. of Atlanta, Georgia.

Analytics has a documented QA (Quality Assurance) program and the capability to prepare QC (Quality Control) materials in a manner that ensures tracability to the National Institute of Standards and Technology. Aralytics provides the cross check samples to the EL who performs the laboratory analyses and sends their results to Analytics for statistical analyses. The documented evaluations provided by Analytics can be helpful to the EL in identifying any instrument or procedural problems.

Reported herein, as required by ODCM 4.1.3.3 and 7.1.2.3 is a summary of the results of the EL's participation in the ICP. Summarized in Table 5-1 are the results obtained during 1996 for: the single analyses of beta-ray and gamma-ray emitters in air filters and gamma-ray emitters in milk; the two analyses for tritium and gamma-ray emitters in water samples; and the three gross beta analyses of water samples.

Delineated in Table 5-1 for each of the media / analysis combinations are: the specific radionuclides, Analytics's preparation dates, the known values, the expected precisions, the average results obtained with their standard deviations, and the resultant normalized deviations and normalized ranges. The normalized deviations and normalized ranges are calculated using the methodology of the EPA program.

The normalized deviation from the known value provides a measure of the central tendency of the data (accuracy). The normalized range is a r' "mre of the dispersion of the data (precision). An absolute value of 3 s' adard deviations for the normalized deviation and for the normalized range was established by the EPA as the control limit. An absolute value of 2 standard deviations was established by the EL as the warning limit. Investigations are undertaken whenever any value exceeds the warning or control limits.

5-1

TABLE 5-1 (SHEET 1 OF 3)

INTERLABORATORY COMPARISON PROGRAM RESULTS Expected Reported Standard Normalized Normalized Specific Date Known Ranee Value Precision Averace Deviation Deviation Radionuclide Prenared  !

Beta-ray Emitters in Air Filters (pCi/ filter) 7.00 107.0 5.70 -5.05 0.97  ;

Sr-89 09/26/96 132.0 5.00 42.0 1.41 -3.11 0.30 Sr-90 09/26/96 53.0 Gamma-ray Emitters in Air Filters (pCi/ filter) l 11.00 190.0 6.80 -3.31 0.69 211.0 Cr-51 12/12/ %  !

10.00 205.0 1.70 0.17 0.19 Mn-54 12/12/96 204.0 w

s> 1.73 0.92 12/12/96 49.0 5.00 54.0 3.90 Fe-59 6.00 115.0 4.00 . -1.45 0.73 l Co-58 12/12/96 120.0 5.50 104.0 ~ 2.10 -1.57 0.45 Co-60 12/12/96 109.0 ,

5.00 99.0 4.70 2.42 1.19 Zn-65 12/12/96 92.0 9.00 138.0 2.60 -6.73 0.33 Cs-134 12/12/96 173.0 10.00 182.0 2.80 -1.73 0.29 Cs-137 12/12/96 192.0 14.00 244.0 3.70 -3.70 0.31 Ce-141 12/12/96 274.0 i

1

_ _ - - - - - . = __ _ _ _ _ _ - _ - _ - _ _ _ _ - - _ _ __-_________- -___ _____-_ ____________-___ -_____.__-__ _ -_____________-_____-- _ -__-_- - ____--

i TABLE 5-1 (SHEET 2 OF 3) t INTERLABORATORY COMPARISON PROGRAM RESULTS Date Known' Expected Reported Standard Normalized - Normalized -

Specific Deviation Value Precision Averane Deviation ~ Range Radionuclide Prepared  :

Gamma-ray Emitters in Milk (pCi/l) 06/19/96 563.0 28.00 561.0 43.68 -0.12 2.52 Cr-51 06/19/96 300.0 15.00 299.0 10.50 -0.12 0.83  :

Mn-54  :

1.80 6.24 0.39  !

Fe-59 06/19/96 77.0 5.00 95.0 06/19/96' 93.0 5.00 90.0 2.40 -1.04 0.39 l Co-58  ;

I 84.0 5.00 78.0 5.14 -2.08 1.14 Co-60 06/19/96 10.86 <

79.0 26.87 7.27

$ Zn-65 06/19/96 58.0 5.00

?

166.0 8.30 151.0 26.70 -3.13 0.19 .

Cs-134 06/19/96 06/19/96 410.0 20.50 398.0 144.60 -1.01 0.60  ;

Cs-137  ;

215.0 10.75 206.0 4.16 -1.45 0.41 t Ce-141 06/19/96 Gross Beta in Water (pCi/I) 03/12/96 98.0- 5.00 118.0 9.10 6.92 3.15 t (Mixture 6.40 2.99 0.26 ofCs-137 06/19/96 174.0 8.70 189.0 70.0 5.00 79.0 7.85 3.11- 0.95 l

& Am-241) 09/26/96 Tritium in Water (pCill) 06/19/96 4915.0 491.50 4930.0 64.55 0.05 0.17 >

H-3 2686.0 268.60 2687.0 1 % .90 0.01- 0.35 [

12/12/96  ;

l

TABLE 5-1 (SHEET 3 OF 3)

INTERLABORATORY COMPARISON PROGRAM RESULTS Specific Date Known Expected Reported Standard Normalized Normalized  :

Radionuclide Prepared Value Precision Average Deviation Deviation Range Gamma-ray Emitters in Water (pCill)

Cr-51 03/12/96 322.0 16.10 323.0 17.00 0.11 1.48 09/26/96 646.0 32.00 596.0 50.51 -2.70 3.83 r

Mn-54 03/12/96 31.0 5.00 32.0 1.73 0.35 0.39 09/26/96 239.0 12.00 227.0 16.52 -1.73 1.93 Fe-59 03/12/96 83.0 5.00 89.0 3.50 2.08 2.85 09/26/96 50.0 5.00 66.0 81.90 5.54 1.09 Co-58 03/12/96 48.0 5.00 49.0 6.00 0.35 0.85 m 0.70 1 09/26/ % 174.0 9.00 159.0 5.51 -2.89 Co-60 03/12/96 76.0 5.00 75.0 2.65 -0.35 0.63 09/26/96 151.0 8.00 148.0 5.29 -0.65 0.72 Zn-65 03/12/96 97.0 5.00 96.0 9.29 -0.35 1.44 09/26/96 93.0 5.00 91.0 10.26 -0.69 3.50 Cs-134 03/12/96 58.0 5.00 55.0 5.00 -1.04 0.27 09/26/96 295.0 15.00 257.0 2.31 -4.39 0.32 Cs-137 03/12/96 64.0 5.00 62.0 5.00 -0.69 1.43 09/26/ % 225.0 11.00 214.0 13.80 -1.73 1.78 Ce-141 03/12/96 88.0 5.00 83.0 5.00 -1.73 1.28 09/26/96 423.0 21.00 382.0 12.12 -3.38 0.68 i

l i

The program supplied by Analytics, although similar to the EPA's, did possess differences that posed problems in the analyses. These differences are outlined below along with the investigative determinations and any planned corrective actions.

The control limits of the normalized deviation for both Sr-89 and Sr-90 were exceeded in the analysis for the beta-ray emitters in air filters. The activity l recovery for both radionuclides was low. QC spikes were prepared to evaluate the I self absorption curves. The curves were found to be valid. The cross-check water sample for Sr-89/90 (used for the effluents program) was analyzed with excellent results; these accurate results indicate a processing problem with the air filters.

The air filters were packaged with a plastic wrap. The wrap was not dissolved with the filter. In the future, the filter wrap will be processed with the filter; also, the counting time may be increased.

The warning and control limits for the normalized deviation of the analysis for gamma-ray emitters in air filters were exceeded for one and three of the radionuclides, respectively. The Analytic's air filters contained nine gamma-ray emitters whereas Cs-137 was the only the gamma-ray emitter in the EPA air filters. The standard used in calibrating the detectors was recounted and the activity recovery exceeded 95%. Geometry differences were ruled out. The background corrections for the germanium detectors are being reviewed as a possible source of bias.

For the gross beta analyses it; water: the warning limit for the normalized deviation was exceeded once while the control limit was exceeded twice; also, the warning limit for the norrnalized range was exceeded once. The samples from Analytics consisted of demineralized water; they did not contain ions for solidification as those from EPA had. A self absorption curve was used in determining the efficiency of the samples based on the samples' solid content. A sample containing no solids reduces t 1e use of the self absorption curve to only its value at the intercept. In the future, a beta standard is to be processed with the analysis; in determming the activity of the sample, the efTiciency of the standard will be used in lieu of the self absorption curve.

Regarding the analysis for the gamma-ray emitters in milk: the warning limit for the normalized deviation was exceeded for one radionuclide while the control limit was exceeded for three radionuclides; the warning and control limits for the normalized range were each exceeded for one radionuclide. For the two analyses of the gamma-ray emitters in water: the warning and control limits for the normalized deviation were each exceeded for three radionuclides; the warning and control limits for the normalized range were respectively exceeded for one and two of the radionuclides. Each milk and water sample contained the same nine gamma-ray emitters as the air filters. Analytics provided diluted one liter samples of milk and water. The one liter sample may be replaced with a 4 liter sample to improve the statistics. The background corrections for the germanium detectors are being reviewed as a possible source of bias.

5-5

I I

l r A low concentration of1-131 was also present in the milk sample but not in the

! water samples. The concentration was substantially reduced by decay due to the 5 days in transit from Analytics to the EL. The level had become too low for detection by the gamma detectors; it could have been detected by the chemical separation process, however. With the EPA samples, the activity had always been sufficient for measurement by the gamma detectors. Plans for a larger sample and longer counting times will improve the probability of detecting I-131 on the gamma counters.

I i

i l

i ..

! 5-6  !

l l

-,. = , . . - , , . - . - . -

6.0 CONCLUSION

S This report confirms the licensee's conformance with TS 6.7.4.g and Chapter 4 of the ODCM during 1996. A summary and discussion of the results of the laboratory analyses for each type sample collected were presented.

The increased levels of tritium in river water, and of Co-58, Co-60 and Cs-137 in shoreline sediment at a short distance downriver from the discharge structure is

! indicative of plant releases. The consequent doses were shown to be small 4

fractions of the ODCM limits and pose no measurable radiological impact to the environment or the public.

The other REMP samples did not show any discernible radiological impact upon the environment or public as a consequence of plant discharges to the atmosphere and to the river.

4 4

i s

6-1