Nuclear Regulatory CommissionP RID RITY l~ (ACCELERATEDRIDS PROCESSING~ REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester

P RID RITY l~(ACCELERATED RIDS PROCESSING~

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester GAUTH.NAME AUTHOR AFFILIATION

MECREDY,R.C. Rochester Gas & Electric Corp.RECIP.NAME RECIPIENT AFFILIATION

DOCKET05000244

SUBJECT: "1994 Annual Radio 'viron Operating Rept RE GinnaNuclear Plant." /950428 r.

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AND

ROCHESTER GASANDEIECTRIC CORPORATION ~ 89 EASTAVENUE, ROCHESTER, N. Y Iddd9-000I AREA CODE7I6 Sd6-2r"00

ROBERT C. MECREDYVice PresidentNvdeor Operations

April 28, 1995

U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, DC 20555

Subject: Annual Radiological Environmental Operating ReportR.E. Ginna Nuclear Power PlantDocket No. 50-244

Dear Sirs:The enclosed information is being submitted in accordance with therequirement of Technical Specification Section 6.9.1.3.This information is a summary of all analyses performed as part ofthe Radiological Environment Monitoring requirements of Section3.16 of the R.E. Ginna Technical Specifications. Trend plots ofgross beta data for air and selected water samples are included forthe years of 1993 and 1994 and the years of 1968 to 1994.From the data collected, there does not appear to be any measurableeffect to the environment from the operation of the R.E. Ginnaplant.

Very truly yours,

Robert C. Mec edy

tt

0202'C4 Os @SRgg05 pgoC ~Ay

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C II

')v g,E

Copies to:

Mr. Thomas T. MartinRegional AdministratorU.S. Nuclear Regulatory CommissionRegion 1475 Allendale RoadKing of Prussia, PA 19406

Resident NRC InspectorGinna Station

Ms. Donna RossNew York State Energy OfficeEmpire State PlazaAlbany, NY 12223

Mr. James C. HuangNew York State Dept. of HealthEmpire State PlazaAlbany, NY 12237

David John PerssonNew York State Dept. of

Environmental Conservation6274 E. Avon-Lima RoadAvon, NY 14414

American Nuclear InsurersMAELU29 S. Main StreetSuite 3005West Hartford, CT 06107-2445ATTN: Winthrop Hayes

Central Records, Ginna StationCategory 2.22.2

1 994

ANNUALRADIOLOGICALENVIRONMENTAL

OPERATING REPORT

R.E. Ginna Nuclear Plant

Rochester Gas 8 Electric Corporation

Docket No. 50-244

I-950S02025p

TABLE OF CONTENTS

1.0 SUMMARY

2.0 SURVEILLANCE PROGRAM

2.1 Regulatory Limits

2.2 Regulatory Fulfillment

2.3 Deviations from the Sampling Schedule

3.0 DATA SUMMARY'.1

Analytical Results

3.2 Air Samples

3.3 Water Samples

3.4 Milk Samples

3.5 Fish Samples

3.6 Vegetation Samples

3.7 External Penetrating Radiation

4.0 LAND USE CENSUS

5.0 EXTERNAL INFLUENCES

6.0 EPA INTERLABORATORYCOMPARISON STUDY

Page

15

15

16

29

45

47

51

53

58

58

LIST OF TABLES

Table No. Page

2-1

2-22-32-42-53-1 A3-1 B3-2 A3-2 B3-3 A

3-3 B

3-3 C

3-3 D

3-43-5 A3-5 B3-5 C3-6

3-73-83-93-103-113-12 A3-12 B

, 3-133-143-153-163-173-186-1

Environmental Radiological MonitoringProgram SummaryTech Spec Table 3.16-1Environmental Monitoring ProgramTech Spec Table 4.10-1 Maximum Values of LLDLower Limit of Detection (LLD Detector 1)Lower Limit of Detection (LLD Detector 2)Direction and Distance to Sample PointsOnsite Samplers, January - JuneOnsite Samplers, July - DecemberOffsite Samplers, January - JuneOffsite Samplers, July - December13 Week Composite Gamma IsotopicAnalyses First Quarter13 Week Composite Gamma IsotopicAnalyses Second Quarter13 Week Composite Gamma IsotopicAnalyses Third Quarter13 Week Composite Gamma IsotopicAnalyses Fourth QuarterCharcoal Cartridges for IodineEnvironmental Water Samples Gross Beta AnalysesEnvironmental Water Samples Gross Beta AnalysesFalloutOntario Water District Water GammaIsotopic AnalysesCirc. Outlet Water Gamma Isotopic AnalysesRussell Station Water Gamma Isotopic AnalysesTap Water Gamma Isotopic AnalysesWell "B" Water Gamma Isotopic AnalysesDeer Creek Water Gamma Isotopic AnalysesEnvironmental Water Samples Tritium AnalysesFallout Tritium AnalysesIodine in WaterMilkFish Samples'Lake SamplesVegetation SamplesExternal Penetrating RadiationEPA Interlaboratory Comparison Program

679

101118192021

22

23

24

2526313233

363738394041424344464850525459

LIST OF MAPS

Onsite Sample LocationsOffsite Sample LocationsWater Sample and Milk Farm LocationsLand Use Census

Page

12131457

LIST OF TREND PLOTS

Onsite vs. Offsite Air Monitors, Gross Beta AnalysisAnnual Trending of Air ActivityEnvironmental Water Samples,

Gross Beta AnalysisAnnual Trending of Environmental WatersExternal Penetrating Radiation,

Thermoluminescent DosimetryEPA Interlaboratory Comparison Program, Gross Alpha-BetaEPA Interlaboratory Comparison Program, Gamma Isotopic

2728

343555

6162

RADIOLOGICALENVIRONMENTALSURVEY

January - December 1994

SUMMARY

During 1994, there were no measurable influences from radioactive effluentreleases. Routine measurements continually are taken in the areas surroundingthe R.E. Ginna Nuclear Power Plant to determine if man-made radioactivity isreleased at a level that would cause an influence to the environs surrounding theplant. These measurements detected no measurable activity above establishedbackground levels. Samples are collected on an established schedule for regulartesting to determine if measurable levels of activity exist that may be attributedto the operation of the plant. The information obtained from measurements ofthese environmental samples is compared to the calculated levels of potentialactivity at the sampling locations from normal plant releases as determined bymonitors within the plant effluent streams.

Samples of water, air, fallout, fish, vegetation, milk and direct radiation arecollected from locations near the plant that were determined to be at the point ofhighest concentration from releases through the plant and containment vents.Samples are also collected from additional locations at distances ranging out toeighteen miles. Reference samples for background measurements are collectedconcurrently from locations calculated to have radioactivity concentrations lessthan 1% of those from the closer sampling locations. These background samplesprovide continuous background data which makes it possible to distinguishbetween significant radioactivity introduced into the environment from theoperation of the plant and that introduced from other sources.

During 1994, 1471 samples were collected for 1900 analyses for beta and gammaemitters through gross activity counting techniques and gamma spectroscopy.These total 931 air samples, 298 water samples, 21 fish samples, 8 vegetationsamples, 57 milk samples, 2 special lake samples and 154 thermoluminescentdosimeter measurements. As part of a required quality control program, 9 EPAInterlaboratory Comparison Studies samples (spiked at levels expected to beobserved for plant releases) were analyzed and reported.

A summary of the data collected indicating the results of all data for indicator andcontrol locations is given in Table 1-1.

ENVIRONMENTALRADIOLOGICALMONITORING PROGRAM SUMMARY ROCHESTER GAS AND ELECTRIC CORPORATIONR.E. GINNA NUCLEAR POWER PLANT - DOCKET NO. 50-244WAYNE, NEW YORK REPORTING PERIOD 1994

'„-:'„"';L''OCATIONiWITH.HIGHEST~/ANNUAL"'EAN::

(pCi/Cu.M.)

Iodine

DIRECT RADIATION: (3)TLD(mrem/QUARTER)

WATER: Drinking(pCi/Liter)

Surface(pCi/liter)

MILK:

Rainfall(pCi/m /day)

(pCi/Liter)

FISH:(pCi/Kg)

VEGETATION:

(I CNg)

~Y!i;":;PATHWAY:SAMPLED.''.-'."';UNIT::„OF..MEASUREMENT, ';:

AIR: Particulate

,""'jTYPE',AND':TOTAL""iNUMER:":„;;'',"".P OF,,'ANALYSES;;-"„::;::,;;,:':';::

Gross Beta 620

Gamma Scan 48

Gamma Scan 311

Gamma 154

Gross Beta 76

Gamma Scan 50

Iodine 36

Gross Beta 162

Gamma Scan 50

Iodine 47

Gross Beta 60

Iodine 57

Gamma Scan 57

Gamma Scan 21

Gamma Scan 8

:.'„: L'L'D':".:

0.003

(2)

0.02-0.06

5.0

1.2

(2)

0.45

1.2

(2)

0.45

1.2

0.45

(2)

(2)

(2)

i;; INDICATOR'.LOCATIONS;..';if',"".MEAN;{1)RANGE'"".;";:i,',

0.016 (362/362)0.0074.033

< LLD

< LLD

13.8 (68/68)9.6 - 32.1

3.24 (76/76)1.41 - 5.58

Ra-226 29 (12/50)9-34

< LLD

2.69 (111/111)1.37 - 5.52

Ra-266 15 (8/38)10-24< LLD

4.11 (24/24)0.96 - 10.58

< LLD

< LLD

Cs-137 29 (8/10)14-65< LLD

'::,;,.,NAMEj"'DISTANCE'-,,.',;-,:

:".":."".".AND:DIRECTION':l"-'„.'..:,'':.'.

Onsite Location ¹ 13A690 M 194

Onsite Location ¹13230 M 292

Well "B"

640 M 150

Well "B"

640 M 150

Deer Creek200 M 135

Deer Creek200 M 135

Station ¹3420 M 110

Discharge Plume

':~.,"::,:MEAN (1)'RANGE~:,;.

0.018 (51/51)0.008 - 0.030

20 (4/4)12.6 - 32.1

4.53 (12/12)3.23 - 5.58

Ra-226 24 (12/12)9-34

3.74 (12/1 2)2.21 - 5.52

Ra-226 15 (8/12)10-24

5.18 (12/12)0.96 - 10.58

:;:.,'::i'CONTROL"':;L'OCATIONS,"."

2.0 SURVEILLANCE PROGRAM

2.1 Regulatory Limits

The Technical Specification requirements for the radiological environmental

monitoring program are:

Monitorin Pro ram

The radiological environmental monitoring program shall be conducted as

specified in Table 3.16-1 at the locations given in the ODCM.

Ifthe radiological environmental monitoring program is not conducted as specifiedin Table 3.16-1, prepare and submit to the Commission, in the AnnualRadiological Environmental Operating Report, a description of the reasons for notconducting the program as required and the plans for preventing a recurrence.(Deviations are permitted from the required sampling schedule if specimens areunobtainable due to hazardous conditions, seasonal availability, or to malfunctionof automatic sampling equipment. If the latter, efforts shall be made to completecorrective action prior to the end of the next sampling period.)

lfmilk or fresh leafy vegetable samples are unavailable for more than one sampleperiod from one or more of the sampling locations indicated by the ODCM, adiscussion shall be included in the Semiannual Radioactive Effluent Report whichidentifies the cause of the unavailability of samples and identifies locations forobtaining replacement samples. If a milk or leafy vegetable sample locationbecomes unavailable, the locations from which samples were unavailable maythen be deleted from the ODCM, provided that comparable locations are addedto the environmental monitoring program.

Land Use Census

A land use census shall be conducted and shall identify the location of thenearest milk animal and the nearest residence in each of the 16 meteorologicalsectors within a distance of five miles.

An onsite garden located in the meteorological sector having the highest historicalD/Q may be used for broad leaf vegetation sampling in lieu of a garden census;otherwise the land use census shall also identify the location of the nearestgarden of greater than 500 square feet in each of the 16 meteorological sectorswithin a distance of five miles. D/Q shall be determined in accordance withmethods described in the ODCM.

Interlaborato Com arison Pro ram

Analyses shall be performed on applicable radioactive environmental samplessupplied as part of an interlaboratory comparison program which has beenapproved by NRC, if such a program exists.

2.2 Regulatory Fulfillment

The fulfillmentof the Technical Specification requirements shall be demonstrated

when:

S ecification

The radiological environmental monitoring samples shall be collected pursuant to

Table 3.16-1. Acceptable locations are shown in the ODCM. Samples shall be

analyzed pursuant to the requirements of Tables 3.16-1 and 4.10-1.

A land use census shall be conducted annually (between June 1 and October 1).

A summary of the results obtained as part of the required InterlaboratoryComparison Program shall be included in the Annual Radiological EnvironmentalOperating Report.

2.3 Deviations from the Sampling Schedule

Deviations from the sampling schedule are allowed when samples are unavailabledue to hazardous conditions, seasonal variations or malfunction of automaticsampling equipment. There were no deviations from the sampling scheduleduring 1994. The minimum number of samples required in Tech Spec Table3.16-1 were collected for all pathways.

Table 2-1

TECHNICAL SPECIFICATION TABLE 3-16.1

RADIOLOGICALENVIRONMENTALMONITORING PROGRAM

Page 1 of 2

."-::;,",EXPOSURE PATHNAY„.'';,.i~':,:-:::.AND/OR;S'O'MPL'E'":."".:.,:,:

1. AIRBORNEa. Radio nuclide

;".,'NUMBER!OF,;.:,'SAMPL'ES!'B'::SAMPL'E,L'OCATIONS

2 indicator2 control

Continuous operation ofsampler with sample collectionat least once per 10 days

Radionuclide canister. Analyze within 7 days of collection ofl-131.

b. Particulate

2. DIRECTRADIATION

3. WATERBORNEa. Surface

7 indicator5 control

18 indicator10 control11 placed greater than 5miles from plant site.

1 control (RussellStation)1 indicator (CondenserWater Discharge)

Same as above

TLDs at least quarterly

Composite* sample collectedover a period of < 31 days.

Particulate sampler. Analyze for gross beta radioactivity >

24 hours following filter change. Perform gamma isotopicanalysis on each sample for which gross beta activity is >

10 times the mean of offsite samples. Perform gammaisotopic analysis on composite (by location) sample at leastonce per 92 days.

Gamma dose quarterly.

Gross beta and gamma isotopic analysis of each compositesample. Tritium analysis of one composite sample at leastonce per 92 days.

Same as above

b. Drinking 1 indicator (OntarioWater District Intake)

Same as above

* Composite sample to be collected by collecting an aliquot at intervals not exceeding 2 hours.

i „jl

Table 2-1

TECHNICALSPECIFICATION TABLE 3-16.1

RADIOLOGICALENVIRONMENTALMONITORING PROGRAM

Page 2 of 2

:.'::;:EXPOSURE;.PATHWAY"'"",,:

',',":-':;;,AND/OR'.SAMPL'Ei,:";':-'.

INGESTIONa. Milk 1 control

3 indicatorJune thru October eachof 3 farms

At least once per 15 days

"NUNIBER:.,OF,.;::,SANPL'ES:, .,':~=.'-,;::;'',,":.::;.;:'-;;.SANIPLING'AND:::::~-':'.':;:-„'-,:::

':;8i:;SAMPLE':,L'''OC'ATlONS;:,::,"',::-',COL'L'ECTION,''FREQUENCY':,::,

:;.'-,::,':,";.TYPE",AND':FREQUENCY.;,OF,:.::,ANALYSIS '.";,

Gamma isotopic and 1-131 analysis of eachsample.

1 control1 indicatorNovember thru May onof the farms

At least once per 31 days Gamma isotopic and 1-131 analysis of eachsample.

b. Fish

c. Food Products

4 control4 indicator (Off shore atGinna)

1 control2 indicator (On site)

Twice during fishing seasonincluding at least four species.

Annual at time of harvest.Sample from two of thefollowing:1. apples2. cherries3. grapes

Gamma isotopic analysis on edible portionsof each sample.

Gamma isotopic analysis on edible portion ofsample.

1 control1 indicator(On site garden ornearest offsite gardenwithin 5 miles in thehighest D/Qmeterological sector)

At time of hadst. One sampleof:1. broad leaf vegetation2. other vegetable

Gamma isotopic analysis on edible portion ofsample.

(6)

Table 2-2 Page 1 of 2

The maximum LLD values as defined by Tech Specs Table 4.10-1 are:

.:.'';.", Analysis,':,:,".%'::;,; Watei',: (pCill)',,:,:: '::j~::Particiilate''.'or'" i:,,'-.",i';~(pCi/kg '.::,:::,:,

':::"';.::-:;;:;wet)".;:-':;::;,

.:,,ij'j:,;::::-",;:!Milk''::::i':'i:::,~j:.",',: „'.",.',::,': PaitIculateI.",I>,

::,,:;.'„,":.;;".,(pCi/I)j

Table 2-2 Page 2 of 2

LLD TABLE NOTATION

The LLD is the smallest concentration of radioactive material in a sample that willyield

a net count (above system background) that will be detected with 95% probability with

only 5% probability of falsely concluding that a blank observation represents a"real"

signal.

For a particular measurement system (which may include radiochemical separation):

4.66 S5E V 2. 22 Y exp [ (-~C) A,]

whereLLD is the lower limitof detection as defined above (as pCi per unit mass or volume)

Sb is the standard deviation of the background counting rate or of the counting rateof a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per disintegration)

V is the sample size (in units of mass or volume)

2.22 is the number of disintegrations per minute per picocurie

Y is the fractional radiochemical yield (when applicable)

A is the radioactive decay constant for the particular radionuclide

R t is the elapsed time between sample collection and analysis for plant effluents.For environmental samples, sample time is the end of the sampling period.

The value of Sb used in the calculation of the LLD for a particular measurement systemshall be based on the actual observed variance of the background counting rate or thecounting rate of the blank samples (as appropriate) rather than on an unverifiedtheoretically predicted variance. In calculating the LLD for a radionuclide determined bygamma-ray spectrometry, the background shall include the typical contribution of otherradionuclides normally present in the samples (e.g., potassium-40 in milk samples).

Analyses shall be performed in such a manner that the stated LLDs will be achievedunder routine conditions. Occasionally, background fluctuations, unavoidably smallsample sizes, the presence of interfering nuclides, or other uncontrollable circumstancesmay render these LLDs unachievable.

ROCHESTER GAS AND ELECTRIC

Table 2-3LOWER LIMITOF DETECTION (LLD)

Environmental Detector ¹ 1

Sample Size

Ave. Decay(c)

AirFilters(a)pCi/M3

3500 M3/Qtr

WaterpCi/liter

3.5 liters

Milk Fish Vegetation(a)pCi/liter pCi/kg pCi/kg3.5 liters 2 kg 2 kg

55 days 0.5 d 8 days 0.5 d 6 days 0.5 days

Be-7 0.020 37 37

K-40 0.037

Cr-51 0.037 40 40 86 71

Mn-54

Fe-59

Co-58

Co-60

Zn-65

Zr-95,

0.002

0.005

0.002

0.001

0.003

0.004

18

20

15

16

20

14

Nb-95 0.003

RU-103

RU-106

0.003

0.013 41 28 77 76

l-131 0.02 (b) 5 Gamma0.8 Gamma (d)

0.2 Beta

5 Gamma 180.5 Gamma (d)

0.2 Beta

Cs-134

Cs-137

BaLa-140

Ce-141

Ce-144

Ra-226

0.002

0.001

0.005

0.008

16

42

3

17

30

16 47

21

85

31

18

84

16

Beta 0.004 1.2

(a) LLDvalue willvary due to different sample sizes. Data based on 1994 background sample spectra.

(b) Charcoal Cartridge

(c) Ave. decay-normal period from midpoint of sampling period to counting time.The true LLD is not decay corrected; therfore, these values may exceed the required maximum values of table 2-2.

(d) Separation by anion exchange on resin(9)


Table 2-4LOWER LIMITOF DETECTION (LLD)

Environmental Detector ¹ 2

Sample Size

Ave. Decay(c)

Air Filters(a)pCi/M3

3500 M3/Qtr

WaterpCi/liter3.5 liters

Milk Fish Vegetation(a)pCi/liter pCi/kg pCi/kg3.5 liters 2 kg 2 kg

55 days 0.5 d 8 days 0.5 d 6 days 0.5 days

Be-7 0.010 12 31

K-40 0.018

Cr-51 0.019 13 24 50 40

Mn-54

Fe-59

Co-58

Co-60

Zn-65

0.001

0.003

0.001

0.001

0.002

12

14 14

Zr-95 0.002

Nb-95 0.002

Ru-103

RU-106

0.002

0.007 14 23 39 38

l-131 0.01(b) 2 Gamma0.5 Gamma (d)

5 3 Gamma 110.4 Gamma (d)

Cs-134

Cs-137

BaLa-140

Ce-141

Ce-144

Ra-226

0.001

0.001

0.002

0.004

13

12

25

10

39

10

16

38

10

(a) LLDvalue willvary due to different sample sizes. Data based on 1994 background sample spectra.

(b) Charcoal Cartridge

(c) Ave. decay-normal period from midpoint of sampling period to counting time.The true LLD is not decay corrected; therfore, these values may exceed the required maximum values of table 2-2.

(d) Separation by anion exchange on resin(10)

Table 2-5

DIRECTION AND DISTANCE TO SAMPLE POINTS

All directions given in degrees and all distances given in meters

¹2 87 320j ':,..IAlrSample:.Stations,:.':,'.j~~:.~j

¹2 87 320¹3¹4

¹6

¹8

110

140

185

232

257

258

420

250

'60225

220

19200

¹3¹4

¹6¹7¹8

110

140

185

232

257

258

420

250

160

225

220

19200

¹9¹10

235 11400

185 13100 ¹10235

185

11400

13100

¹11 123 11500 ¹11 123 11500

¹12¹13

'ater,,Sam'pie';.Locatlo'ns';i,

Russell Station

Ontario Water Dist Intake

Circ Water Intake

Circ Water Discharge

Deer Creek

Well B

Tap

Rainfall ¹3Rainfall ¹5Rainfall ¹8

Rainfall ¹10

93 25100

194 690

;!'.,:..;-;:,Dlr'ectiori':„;:,;.',>,.,:.:, .',:,'':;.:.;.'„.';:I,::.;:,Distanc'e;,';:: i",:.

270 25600

70 2200

0 420

15 130

105 260

150 640

On site Sink

110 420

185 160

258 19200

185 13100

¹12¹13¹14

¹15¹16¹17¹18¹19¹20¹21¹22¹23¹24¹ 25

93

292

292

272

242

208

193

177

165

145

128

107

90

247

25100

230

770

850

900

500

650

400

680

600

810

680

630

14350

Rainfall ¹12 93 25100

:;::!~Milk':Sa'mple':Lo'catioris'::.'-.'",", '",."''.;,'",',"',':!Dlrectio'ri''fbi::'„.:.'44',"4Distanc'e'!„'W';':::.,';;:.

Farm A 113 9500

¹ 26¹27

¹28

223

202

145

14800

14700

17700

Farm B

Farm C

Farm D

242,

156

132

5450

4950

21000

¹29¹30¹ 31¹32

104

103

263

246

13800

20500

7280

6850

Indicator Samples Lake Ontario Discharge Plume ¹33 220 7950Background Samples Russell Station

Indicator Samples Grown on property surrounding Plant

Background Samples Purchased from farms > 10 miles

¹34¹35

¹36¹ 37¹38¹ 39¹40

205

193

174

158

137

115

87

6850

7600

5650

6000

7070

6630

6630

MAP 2-1

GINNA STATION

LAKE ONTARIO

Q Air Monitoring StationT2 Thermoluminescent Dosimeter Locations

T15 T7T6 +T3

T24

23

T16T17

19T21

Lake RoadT22

T20

O0a'

O0Ul

0z

'0DolYIQCIO0cOC0

Miles

0 . 0.1 0.2 0.3 0.4

UNE 1992 Cauter for Governmental Research iac.

o ~

o ~ ~ ~ ~

'

I I

~~

I

g g ~P~ ]g, H

~e,l s

Qi

Map 2-3

Water Sample and Milk FarmLocations

~/

IS HiLF:8-- .

Graceful Sejm

R

2I S~ILZ

LAKE 0NTA R~p IO MILES

WE ST 1 ~ ~ ~

1

I

P NFI

0

LWO

W LLI SONa

AA 0

SNQ

0 U

ghto

C fgTO

OXX

3.0 DATA SUMMARY

3.1 Anal tical Results

The values listed on the following tables include the uncertainties stated as 2

standard deviations (95% confidence level).

Ke Definitions

Curie (Ci): The quantity of any radionuclide in which the number ofdisintegrations per second is 37 billion.

Picocurie (pCi): One millionth of a millionth of a curie or 0.037 disintegrationsper second.

Cubic Meter (M ): Approximately 35.3 cubic feet.

Liter (L): Approximately 1.06 quarts.

Lower Limit of Detection

The Nuclear Regulatory Commission has requested that reported values becompared to the Lower Limitof Detection (LLD)for each piece of equipment. TheLLD for the equipment is established by the measurement of a blank sample.Table 2-3 and 2-4 are a listing of the LLD values for gamma isotopes using ourGe(Li) multichannel pulse height detector system. These values are before thecorrection for decay. Decay correction is applied from the end of the samplingperiod to the counting time, not from the midpoint of the sampling period. An

-explanation of the calculation of the LLD is included with Table 2-2. Grossdetection limits are as follows:

Beta:

Air

Water

0.003 pCi/M gross beta for 400 m sample.

0.7 pCi/L gross beta for 1 liter sample.

Milk

Fallout

Gamma:

0.45 pCi/L iodine 131 for 4 liter sample.

1.1 pCi/m /day for 0.092 M collection area.

Air 0.03 pCi/m iodine 131 on charcoal cartridge for 400 M sample.

Radiation:5 millirem/quarter for one quarter exposure (TLD).

(15)

There are two intrinsic Ge crystals used for the environmental program. One

detector has a higher efficiency and therefore, the LLD values are lower. The

variation on the tables of the reported LLD is due to counting samples on the

different detectors.

3.2 A~iS

Radioactive particles in air are collected by drawing approximately one cfm

through a two inch diameter particulate filter. The volume of air sampled is

measured by a dry gas meter and corrected for the pressure drop across thefilter. The filters are changed weekly and allowed to decay for three days priorto counting to eliminate most of the natural radioactivity such as the short half-life

daughter products of radon and thoron. The decay period is used to give a moresensitive measurement of long-lived man-made radioactivity.

A ring of 6 sampling stations is located on the plant site from 150 to 300 metersfrom the reactor near the point of the maximum annual average ground levelconcentration. In addition, there is a ring of 5 sampling stations locatedapproximately 7 to 17 miles from the site that serve as background stations.

Based on weekly comparisons, there was no statistical difference between the on-site and the background radioactive particulate concentrations. The averageconcentrations for the on-site and background samples were 0.018 and 0.016pCi/m respectively for the period of January to December, 1994. Maximumweekly concentrations for each station were less than 0.033 pCi/m .

3

The major airborne activities released from the plant are noble gases, tritium,radioiodines and carbon-14. Most of this activity is released in a gaseous form,however, some radioiodine is released as airborne particulate. For airborneparticulates, the average calculated concentration of particulate at the siteboundary due to measurable plant releases would be 9.9E-7 pCi/m or 0.019%of the average release concentration of 5.9E-3 pCi/m . The surve~ cannot detectsuch a concentration which is (0.03% of the LLD of 0.003 pCi/m .

Tables 3-1A, 3-1B are a list of gross beta analyses values for the on-sitesamplers. Tables 3-2A, 3-2B are a list of gross beta analyses values for the off-site samplers.

The particulate filters from each sampling location were saved and a 13 weekcomposite was made. A gamma isotopic analysis was done for each samplinglocation and corrected for decay. The results of these analyses are listed inTables 3-3 A to D.

Iodine cartridges are placed at six locations. These cartridges are changed andcounted each week. No positive analysis was found on any sample. A list ofvalues for these cartridges is given in Table 3-4.

(16)

A trend plot of the 1994 Onsite vs. Offsite air filter data is included. Additionally,a trend plot of the annual averages measured since 1968 is included to show thevariation of data during the years that the R.E. Ginna Nuclear Power Plant hasbeen operational. The peak activities measured correspond to the years whenatmospheric tests of nuclear weapons were being conducted.

Rochester Gas and Electric

Table 3-1 AOn-Site AirParticulate Samplers

Gross Beta Results in pCi/m3WeekEnding

74an1@Jan

21-Jan

2Wan4-Feb

11-Feb18-Feb

25-Feb4-Mar

11-Mar18-Mar25-Mar

1-Apr8-Apr

15-Apr22-Apr29-Apr6-May

13-May20-May27-May

34un1Mun174un24-Jun

14ul

Sta. ¹20.015 j 0.0010.020 + 0.0020.021 j 0.0010.029 + 0.0020.017 + 0.0010.021 j 0.0010.025 j 0.0010.018 j 0.0010.021 j 0.0010.020 + 0.0010.019 + 0.0010.013 j 0.0010.011 j 0.0010.013 j 0.0010.014 + 0.0010.013 + 0.0010.014 + 0.0010.013 + 0.0010.014 + 0.0010.007 j 0.0010.012 j 0.0010.013 j 0.0010.012 j 0.0010.014 + 0.0010.016 + 0.0010.009 + 0.001

Sta. ¹30.015 j 0.0010.020 j 0.0010.022 + 0.0010.028 j 0.0010.018 j 0.0010.021 + 0.0010.025 + 0.0010.019 j 0.0010.021 j 0.0010.021 j 0.0010.020 j 0.0010.014 + 0.0010.011 j 0.0010.016 j 0.0010.014 j 0.0010.014 j 0.0010.016 j 0.0010.0'13 j 0.0010.013 + 0.0010.008 + 0.0010.011 + 0 '010.013 j 0.0010.012 j 0.0010.014 j 0.0010.015 j 0.0010.009 + 0.00'1

Sta. ¹40.018 j 0.0010.020 j 0.0010.024 + 0 '010.032 j 0.0020.018 j 0.0010.023 j 0.0010.025 + 0.00'10.019 + 0.0010.021 j 0.0010.019 j 0.0010.021 j 0.0010.014 + 0.0010.010 + 0.0010.016 j 0.0010.0'l5 j 0.0010.016 j 0.0010.016 j 0.0010.013 j 0.0010.014 j 0.0010.008 j 0.0010.012 + 0.0010.014 + 0.0010.012 j 0.0010.015 j 0.0010.017 j 0.0010.010 j 0.001

Sta. ¹50.015 + 0.0010.0'l9 j 0.0010.021 + 0.0010.024 j 0.0010.018 j 0.0010.021 j 0.0010.021 j 0.0010.017 j 0.0010.021 j 0.0010.019 j 0.0010.019 j 0.0010.012 + 0.0010.012 j 0.0010.015 j 0.0010.012 j 0.0010.016 j 0.0010.013 j 0.0010.015 j 0.0010.012 + 0.0010.007 + 0.0010.012 j 0.0010.013 j 0.0010.014 j 0.0010.015 j 0.0010.017 j 0.0010 '08 + 0.001

Sta. ¹60.017 + 0.0010.021 j 0.0010.015 + 0.0030.024 + 0.0020.018 j 0.0010.021 + 0.0010.025 + 0.0020.015 j 0.0010.020 + 0.0010.018 j 0.0010.018 + 0.0010.012 + 0.0010.011 j 0.0010 '15 j 0.0010.012 + 0.0010.016 j 0.0010.013 j 0.0010.015 j 0.0010.012 + 0.0010.007 + 0.0010.012 j 0.0010.013 j 0.0010.014 j 0.0010.014 j 0.0010.017 j 0.0010.009 j 0.001

Sta. ¹70.017 j 0.0020.020 + 0.0020.02'l + 0.0020.025 j 0.0020.018 j 0.0020.021 + 0.0020.025 + 0.0020.017 + 0.0020.023 j 0.0020.0'19 j 0.0020.020 + 0.0020.012 j 0.0020.013 j 0.0020.015 j 0.0020.013 + 0.0020.014 j 0.0020.014 j 0.0020.015 j 0.0020.013 j 0.0020.007 j 0.00'10.013 j 0.0020.014 j 0.0020.014 j 0.0020.014 + 0.0020.018 j 0.0020.008 j 0.00'1

Sta ¹13A0.018 j 0.0010.023 j 0.0020.023 j 0.0020.030 + 0.0020.021 + 0.0020.025 + 0.0020.027 j 0.0020.020 j 0.0010.026 + 0.0020.022 j 0.0020.023 + 0.0020.014 j 0.0010.014 j 0.0010.017 j 0.0010.013 j 0.0010.016 j 0.0010.016 j 0.0010.018 j 0.0010.015 j 0.0010.008 j 0.0010.015 j 0.0010.015 j 0.0010.015 j 0.0010.017 j 0.0010.018 + 0.0010.009 j 0.001

Average0.0160.0200.0210.0270.0180.0220.0250.0180.0220.0200.0200.0130.0120.0150.0130.0150.0150.0150.0130.0070.0120.0140.0130.0150.0170.009

Maximum

AverageMinimum

0.0290.0160.007

+ 0.002 0.028 j 0.001 0.032 j 0.0020.016 0.017

+ 0.001 0.008 + 0.008 0.008 j 0.0010.0240.0160.007

j 0.001+ 0.001

0.0250.0160.007

+ 0.002 0.025 j 0.002 0.030 j 0.0020.016 0.018j 0.001 0.007 j 0.001 0.008 j 0.001


Table 3-1 BOn-Site AirParticulate Samplers


&Jul1&Jul22-Jul29Jul5-Aug

12-Aug19-Aug26-Aug

2-Sep9-Sep

16-Sep23-Sep30-Sep

7-Oct14-Oct21-Oct28-Oct4-Nov

11-Nov18-Nov25-Nov

2-Dec9-Dec

16-Dec23-Dec30-Dec

Sta. ¹20.013 g 0.0010.0'l3 g 0.0010.017 g 0.0010.013 g 0.00'I0.018 g 0.0010.011 g 0.0010.014 g 0.0010.016 g 0.0010.020 g 0.0010.013 g 0.0010.019 j 0.0010.020 g 0.0010.012 g 0.0010.008 g 0.0010.018 g 0.0010.018 g 0.0010.012 g 0 '010.017 g 0.0010.022 g 0.0010.018 g 0.0010.015 g 0.0010.015 g 0.00'I0 '23 ~ 0.0010.017 g 0.0010.02'I g 0.0010.022 g 0.001

Sta. ¹30.013 g 0.0010.014 g 0.0010.018 + 0.0010.014 g 0.0010.021 g 0.0010.012 g 0.0010.015 + 0.0010.017 g 0.00'I0.021 g 0.0010.013 g 0.0010.018 g 0.0010.023 g 0.00'I0.010 + 0.0010.008 g 0.0010.017 g 0.0010.018 g 0.0010.013 g 0.0010.017 g 0.0010.023 g 0.0010.019 g 0.0010.015 g 0.0010.015 + 0.0010.025 + 0.0010.015 g 0.0010.022 g 0.0010.023 g 0.001

Sta. ¹40.015 g 0.0010.015 + 0.0010.019 g 0.0010.014 g 0.0010.022 + 0.0010.014 + 0.0010.016 g 0.0010.018 g 0.0010.021 f 0.0010.014 + 0.0010.021 + 0.0010.023 + 0.0010.012 g 0.0010.008 f 0.0010.019 g 0.0010.018 g 0.0010.012 g 0.0010.019 + 0.0010.024 + 0.0010.019 + 0.0010.016 + 0.0010.016 g 0.0010.025 g 0.0010.016 g 0.0010.022 g 0.0010.023 + 0.001

Sta. ¹50.019 g 0.0010.016 g 0.0010.019 g 0.0010.016 + 0.0010.019 g 0.0010.015 g 0.0010.018 g 0.0010.018 g 0.0010.017 g 0.0010.015 g 0.0010.020 g 0.00'I0.023 ~ 0.0010.009 g 0.0010.011 g 0.0010.024 g 0.0010.017 g 0.0010.013 g 0.0010.021 g 0.0010.022 g 0.0010.018 g 0.0010.017 g 0.0010.017 g 0.0010.028 g 0.0020.019 g 0.0010.025 g 0.0020.025 g 0.002

St0.0180.0'l70.0190.0180.0210.0160.0190.0180.0180.0140.0200.0230.0100.0100.0330.0160.0110.0210.0210.0190.015

0.0250.0180.02'I0.020

a. ¹6~ 0.001g 0.001~ 0.001~ 0.001g 0.001g 0.001+ 0.001g 0.001g 0.001g 0.001g 0.002+ 0.002+ 0.001g 0.001g 0.003g 0.001g 0.001g 0.0022 0.002g 0.002+ 0.002

-g 0.002g 0.0022 0.002g 0.002

. ¹70.0020.0020.0020.0020.0020.0020 '020.0020.0020.0020.0020.0020.0010.0010.0020.0010 '010.0010.0020.0010.0010.0010.00'I0.0010.0010.001

Sta0.018 g0.017 g0.019 +0.016 f0.020 20.0140.016 +0.019 +0.019 R0.016 g0.019 g0.021 +0 '09 +0.0110.022 i0.017 g0.0110.021 +0.023 +0.020 +0.016 +0.016 +0.025 +0.017 g0.023 g0.022 +

Sta. ¹13A0.017 + 0.0010.015 g 0.0010.021 + 0.0010.017 + 0.0010.022 g 0.0010.014 g 0.0010.018 g 0.0010.020 + 0.0010.018 + 0.0010.017 g 0.0010.021 < 0.0010.022 g 0.0020.011 + 0.0010.011 + 0.0010.023 + 0.0010.0'l7 g 0.0010.013 g 0.0010.022 g 0.0010.021 g 0.0010.019 g 0.0010.016 g 0.001

0.025 g 0.0010.017 + 0.0010.023 g 0.0010.022 g 0.001

Average0.0160.0150.0190.0150.0200.0140.0170.0180.0190 ~ 015

0 '200.0220.0100.0100.0220.0170.0120.0200.0220.0190.0160.0160.0250.0170.0220.022

Maximum

AverageMinimum

0.0230.0160.008

g 0.001

g 0.001

0.025 g 0.0010.0170.008 g 0.001

0.025 g 0.0010.0180.008 + 0.001

0.0280.0190.009

g 0.002

g 0.001

0.0330.0180.010

g 0.003 0.025 g 0.001 0.025 g 0.0010.018 0.018

g 0.001 0.009 g 0.001 0.011 g 0.001

* Sampler out of service.


Table 3-2 AOff-Site AirParticulate Samplers


74an1+Jan21 dan28-Jan4-Feb

11-Feb18-Feb25-Feb

4-Mar11-Mar

18-Mar25-Mar

1-Apr8-Apr


13-May20-May27-May

&Jun1(klun174un2@Jun

14ul

Sta. ¹80.013 g 0.0010.017 + 0.0010.019 2 0.0010.021 R 0.0020.015 g 0.0010.019 g 0.0010.021 g 0.0010.014 g 0.0010.019 g 0.0010.017 g 0.0010 '19 g 0.0010.013 ~ 0.0010.013 g 0.0010.014 g 0.0010.012 g 0.0010.013 g 0.002

0.014 g 0.0010.012 g 0.0010.006 g 0.0010.012 g 0.0010.013 g 0.0010.014 g 0.0010.015 g 0.0010.015 g 0.0010.009 g 0.001

0.0200.0130.0180.0160.0170.0110.0110.0150.0120.0130.0130.0130.0110 F 0060.0110.0120.0130.0140.0160.009

+ 0.001g 0.001g 0.001g 0.001+ 0.001g 0.001g 0.001g 0.001g 0.001+ 0.001+ 0.001+ 0.001g 0.001i 0.001g 0.001+ 0.001g 0.001g 0.001+ 0.001+ 0.001

Sta.¹90.012 g 0.0010.014 g 0.0010.018 g 0.0010.019 g 0.0010.015 + 0.0010.017 g 0.001

Sta0.0140.0180.0180.0200.0150.0180.0200.0130.0180.0160.0170.0110.0'100.0'13

0.0110.0130.0130.0140.0'10

0.0060.0120.0110.0120.0130.0160.008

. ¹10+ 0.001+-0.001g 0.001+ 0.001+ 0.001+ 0.001+ 0.00'I

g 0.001+ 0.001+ 0.001+ 0.001+ 0.001g 0.001+ 0.001+ 0.001+ 0.001+ 0.00'1

g 0.001+ 0.001+ 0.001g 0.001g 0.001+ 0.001+ 0.001+ 0.001

g 0.001

Sta0.0150.0210.0230.0250.0150.0210.0210.0170.0240.0200.0200.0120.0130.0150.0130.0160.0160.0170.0120.0060.0130.0120.0130.0170.0160.008

. ¹112 0.002+ 0.002g 0.002g 0.0022 0.0022 0.002i 0.002g 0.002+ 0.002R 0.002g 0.002g 0.002g 0.002+ 0.002+ 0.002g 0.002g 0.002g 0.002g 0.002g 0.0022 0.002+ 0.002+ 0.002+ 0.002g 0.002~ 0.002

Sta.¹120.017 + 0.0010.020 g 0.0010.024 g 0.0020.026 g 0.0020.021 g 0.0020.024 g 0.0020.024 g 0.0010.020 + 0.0010.023 + 0.0020.019 g 0.0010.022 g 0.0020.013 g 0.00'10.013 g 0.0010.015 + 0.0010.012 g 0.0010.014 g 0.0010.013 g 0.0010.014 g 0.0010.011 g 0.0010.007 g 0.0010.013 g 0.0010.013 + 0.0010.013 + 0.0010.013 + 0.0010.016 g 0.0010.007 g 0.001

Average0.0140.0180.0200.0220.0160.0200.0210.0150.0200.0180.0190.0120 ~ 0120.0140.0120.0140.0140.0140.0110.0060.0120.0120.0130.0140.0160.008

Maximum

AverageMinimum

0.0210.0150.006

g 0.001

~ 0.001

0.020 + 0.0010.0140.006 g 0.001

0.0200.0140.006

g 0.001

+ 0.001

0.0250.0160.006

g 0.002

g 0.002

0.0260.0160.007

g 0.002

g 0.001

* Sampler out of service.

(20)


Table 3-2 BOff-Site AirParticulate Samplers


Mul1&Jul224ulPaul5-Aug

12-Aug

19-Aug26-Aug

2-Sep9-Sep

16-Sep23-Sep

30-Sep7-Oct

14-Oct21-Oct28-Oct4 Nov

11-Nov18-Nov

25-Nov2-Dec9-Dec

16-Dec23-Dec

30-Dec

-Sta. ¹80.015 g 0.0010.0'l4 g 0.0010.020 + 0.0020.014 2 0.0010.018 + 0.0010.012 g 0.0010.016 g 0.001

0.012 + 0.0010.015 g 0.0010.020 g 0.0010.022 g 0.0020.010 g 0.0010.010 + 0.0010.021 g 0.0010.0'17 g 0.00'I0.012 ~ 0.0010.020 ~ 0.0010.023 g 0.0010.019 g 0.0010.016 g 0.0010.015 g 0.0010.026 + 0.0010.017 2 0.0010.022 + 0.0010.024 + 0.001

Sta. ¹90.016 g 0.0010.014 g 0.0010.0'16 g 0.0010.014 + 0.0010.017 + 0.0010.012 ~ 0.0010.015 g 0.0010.018 g 0.0010.016 g 0.0010.014 + 0.0010.018 + 0.0010.019 g 0.0010.010 g 0.0010.009 g 0.0010.019 + 0.0010.015 + 0.0010.011 + 0.0010.017 g 0.0010.020 g 0.0010.017 g 0.0010.015 g 0.0010.015 R 0.0010.022 ~ 0.0010.0'l5 + 0.0010.018 + 0.0010.023 g 0.002

Sta. ¹100.015 + 0.0010.013 f 0.0010.016 g 0.0010.014 g 0.0010.015 g 0.0010.013 g 0.0010.014 + 0.0010.016 + 0.0010.015 + 0.0010.012 g 0.0010.016 g 0.0010.019 + 0.0010.008 + 0.0010.009 + 0.0010.018 g 0.0010.016 g 0.0010.013 g 0.0010.020 g 0.0010.022 + 0.0010.019 g 0.0010.016 + 0.0010.016 + 0.0010.023 + 0.0010.016 g 0.0010.021 g 0.0010.022 g 0.001

Sta. ¹110.015 + 0.0020.016 + 0.0020.018 g 0.0020.016 g 0.0020.019 + 0.0020.012 g 0.0020.015 + 0.0020.016 + 0.0020.016 + 0.0020.014 g 0.0020.021 + 0.0020.019 g 0.0020.008 + 0.0020.009 + 0.0020.016 + 0.0020.017 g 0.0020.010 + 0.0020.020 + 0.0020.023 + 0 '020.020 g 0 '030.015 + 0.0010.015 + 0.0010.024 + 0.0010.016 g 0.0010.022 + 0.0010.023 + 0.001

Sta0.0140.0130.0190.0140.0180.0120.0'l50.0170.0170.0130.0200.0190.0100.0100.0200.0160.0110.0190.0190.0150.0130.0130.0210.0130.0180.019

. ¹12i 0.001-g 0.001+ 0.001g 0.001g 0.001+ 0.001+ 0.001

~ 0.001g 0.001g 0.001+ 0.001+ 0.001+ 0.001g 0.001g 0.001g 0.001g 0.001+ 0.001+ 0.001+ 0.001g 0.001g 0.001g 0.001g 0.001g 0.001+ 0.001

Average0.0150.0140.0180.0140.0170.0120.0150.0170.0150.0140.0190.0200.0090.0090.0190.0160.0110.0190.0210.0180.0150.0150.0230.0150.0200.022

Maximum

AverageMinimum

0.026 g 0.0010.0170.010 g 0.001

0.0230.0160.009

+ 0.002

g 0.001

0.0230.0160.008

g 0.001

g 0.001

0.0240.0170.008

+ 0.001

2 0.002

0.0210.0160.010

g 0.001

+ 0.001

Sampler out of service.

(21 )


Table 3-3 A13 Week Composite

Gamma Isotopic AnalysisResult in pCi/m3

First Quarter

sta. ¹2 sta. P3 Sta. ¹4 sta. ¹5 sta. ¹6 sta. ¹7 sta. ¹S Sta. ¹9 Sta. ¹10 Sta. ¹11 Sta. ¹12 Sta. ¹13A

Be.7 .101 + .008 .123 + .005 .105 g .007 .011 Q,005 .098 f .010 .101 g .008 .090 j .008 .103 f .004 .109 f .013 .102 f .009 .127 + .008«.001


Table 3-3 B13 Week Composite

Gamma Isotopic AnalysisResult in pCI/m3Second Quarter

Sta. ¹2 Sta. ¹3 Sta. ¹4 Sta. ¹5 Sta. ¹6 Sta. ¹7 Sta. ¹8 Sta. ¹9 Sta. ¹10 Sta. ¹11 Sta. ¹12 Sta. ¹13A

.116 f .007 .115 f .007 .122 f .007 .119 g .007 .115 g .006 .129 + .007 .117 + .OOB .113 + .007 .112 + .006 .119 g .006 .117 + .OOB


Table 3-3 C13 Week Composite

Gamma Isotopic AnalysisResult in pCi/m3

Third Quarter


Be-7 .104 $ ,004 .095 g .009 .103 g .009 .113 + .010


Table 3-3 D13 Week Composite

Gamma Isotopic AnalysisResult in pCI/m3Fourth Quarter


Bc-7 .055 + .007 .097 f .004 .083 g .010 .095 g .005«.007


Table 3-4Charcoal Cartridges Gamma Analysis for Iodine

Results in pCi/m3WeekEnding

?dan1+Jan21 Jan28-Jan4-Feb11-Feb18-Feb25.Feb4.Mar11-Mar18-Mar25-Mar1-Apr8-Apr15-Apr22-Apr29-Apr6-May13-May20.May2?-May34un1(&un1?Gun2+Jun14uljul1&Jul224ul294ul5-Aug12-Aug19-Aug26-Aug2-Sep9-Sep16-Sep23-Sep30-Sep7-Oct14-Oct21-Oct28-Oct4-Nov11-Nov18-Nov25-Nov2-Dec9-Dec16-Dec23-Dec30-Dec

Sta. ¹2

R.E. GINNA NUCLEAR POWER STATION

Onsite vs Offsite AirMonitors

.030

GROSS BETA ANALYSIS

.025PC

.020

.015U

ME .010T

.005

.000

OlCOo4T

'CtCD

CO

CD

CO

CD CD

CO

lO

CD

CD

CD

C4CD

CD

ID

WEEK

GlCD

CO

CD

CD

CD

CD CD

CtCt

CV

CD

~ Oesite ~ Offsite(27)

0.350

ANNUALTRENDING OF AIRACTIVITY

GROSS BETA ANALYSIS

0.300

0.250PC

'.2OOILI

T 0.150

ER

0.100

0.050

0.000CO 0) O ~ bl COCO CO

CO N CO Ch O v- CV CO C 0) CO > CO 0) O ~ CVh W h W OD OO CO OO CO CO CO CO CO CO Q) 0) Q) 0) 0)

YEARS 1968 - 1994~ ONSITE ~ OFFSITEPEAKS ARE INDICITAVEOF NUCLEARDETONATIONS IN THE ATMOSPHERE

(26)

3.3 W~tS

Water samples are collected on a regular schedule from locations surrounding the

plant to demonstrate that there is no measurable influence or contamination of

drinking or irrigation water from liquid effluent releases or deposition from gaseous

effluent releases.

Composite samples are collected weekly from Lake Ontario, upstream (Russell

Station) and downstream (Ontario Water District Plant- OWD), and analyzed for

gross beta activity. There was no significan difference between the upstreamand downstream sample concentrations. The 1994 averages were 2.45 and 2.68

pCi/liter for the upstream and downstream samples respectively.

Weekly composite samples are taken from the plant circulating water intake (Circ

In) and discharge canal (Circ Out). The yearly averages were 2.53 and 2.56

pCi/liter for the intake and discharge canal respectively. These are essentially thesame as the upstream and downstream values as they fall within the + 2 sigmaerror band and range of the measurement. A gamma isotopic analysis ofbiweekly composites of the OWD and the discharge canal is performed.

For all batch releases, the average concentration in the discharge canal from theidentified activity during 1994 was 0.16 pCi/liter. The normal 2 sigma variation forthe activity calculation of composite samples is 0.67 pCi/liter or 4 times theaverage concentration added by releases from the plant.

Samples of tap water, the nearest well, and the creek which crosses the site arecollected and analyzed monthly. The results show no indication of plantinfluence. Results for all water beta analyses are listed in Tables 3-5A, 3-5B.

Gamma isotopic analysis is done on each monthly sample and each biweekly ormonthly composite ofweekly samples. These are listed in Tables 3-6 to 3-11 andseparated by source of sample.

Trend plots are included to show the weekly upstream and downstream betaactivities. Peaks up to 5 pCi/liter occur when the lake is stirred up by wind andthe sample includes large quantities of suspended silt. A trend plot showing theannual average activity measured during the years since 1968 is included to showthe data during the years the R.E. Ginna Nuclear Power Plant has been inoperation. The peaks correspond to the years when atmospheric testing ofnuclear weapons occurred.

(29)

Fallout

Fallout is a term used to denote radioactive material settling from the atmosphereto the ground. At the sampling stations, the fallout settles as dust or is collectedwith rainfall by a funnel and bottle. There are two on-site sampling stations andthree off-site. Fallout generally increases in the spring months due to transfer offission products from the upper to the lower atmosphere in conjunction withincreased rainfall. Station ¹12 is surrounded by trees and often gives resultshigher than other locations due to the increase of organic materials. Gammaisotopic analysis has not shown any positive activity attributed to the plant. Theonsite average and the offsite average were 4.11 and 5.82 pCi/m /day

~ 2

respectively. There is no real significant difference between on-site and off-sitesamples for the period of January through December, 1994. Table 3-5C lists thevalues for fallout samples.

Tritium Anal sis

Tritium analysis is done on all water samples on a monthly basis. Compositesare made from the weekly composites and a portion distilled for analysis toremove interfering elements or activity. Tritium data is given in Tables 3-12 A 8B.

iodine Anal sis

All monthly composite water samples except the fallout samples are analyzed foriodine-131. The analysis allows the determination of iodine-131 activity of < 1pCi/liter. iodine data is given in Table 3-13. Any positive counts and the 2 sigmaerror are reported. All negative counts after background correction are reportedas


Table 3-5 AEnvironmental Water Samples Gross Beta Analysis

Results in pCi / I

WeekEnding

74an14Jan214an2Wan4 Feb

11-Feb

18-Feb

25-Feb4-Mar

11-Mar18-Mar

25-Mar

1-Apr8-Apr


13-May

2Mhay27-May

3Jun1OJun174un24Jun

14ul

Russell

2.61 g 0.722.25 + 0.742.44 i 0.712.08 g 0.702.93 + 0.724.06 t 0.661.62 2 0.752.31 R 0.78

A3.22 2 0.742.58 + 0.722.80 g 0.732.69 g 0.733.52 2 0.762.75 g 0.712.63 + 0.712.08 + 0.681.61 + 0.722.55 + 0.752.56 ~ 0.732.40 2 0.722.15 g 0.721.86 g 0.712.01 I 0.702.15 + 0.722.95 + 0.85

O.W.D.

3.'12 g 0.772.69 g 0.732.73 g 0.743.04 g 0.734.74 2 0.692.93 g 0.811.81 g 0.762.58 i 0.723.34 g 0.752.98 2 0.743.27 2 0.763.14 g 0.752.32 2 0.712.86 g 0.723.21 g 0.732.99 g 0.732.99 g 0.731.98 g 0.731.84 g 0.732.08 2 0.721.99 g 0.722.08 g 0.722.46 2 0.722. 11 ~ 0.722.50 + 0.751.74 R 0.71

Circ In

3.01 2 0.742.17 R 0.702.49 g 0.724.10 g 0.762.98 g 0.721.62 g 0.752.08 ~ 0.772.15 g 0.772.19 2 0.70

BBBB

3.45 2 0.743.50 g 0.743.04 g 0.722.91 g 0.731.78 2 0.722.11 g 0.741.70 I 0 702.35 g 0.732.65 2 0.742.55 g 0.732.15 2 0.722.96 g 0.752.28 g 0.74

Circ Out

2.43 2 0.712.52 2 0.742.84 g 0.732.89 2 0.742.93 + 0.711.48 2 0.751.37 2 0.741.75 g 0.763.22 + 0.742.68 g 0.722.37 2 0.712.85 2 0.743.68 g 0.783.52 ~ 0.743.63 2 0.753.37 g 0.743.41 2 0.752.57 2 0.762.18 2 0.742.50 2 0.742.37 g 0.732.29 g 0.732.14 ~ 0.722.86 g 0.741.93 I 0.712.58 2 0.75

Deer Creek

2.82 + 0.72

2.21 g 0.73

4.13 + 0.75

4.05 ~ 0.77

2.50 R 0.72

3.44 + 0.72

Tap

2.53 g 0.72

3.84 i 0.64

2.65 g 0.72

2.62 + 0.70

2.18 g 0.74

1.41 + 0.68

Well

'B'.23

+ 0.77

4.78 g 0.77

5.58 g 0.80

4.32 2 0.75

4.53 i 0.784.04 g 0.75

Maximum

AverageMinimum

4 '62.511.61

g 0.66

g 0.75

4.742.671.74

g 0.69

+ 0.71

4 ~ 10

2.561.62

g 0.76

g 0.75

3.68 ~ 0.782.631.37 g 0.74

4 ~ 13 + 0.753.192.21 g 0.73

3.84 + 0.642.541.41 + 0.68

5.58 2 0.804.413.23 + 0.77

Allvalues given as < are less than the LLD corrected for decay.

A) Sample lost during analysis.B) Circ-in pumps out of service.


Table 3-5 BEnvironmental Water Samples Gross Beta Analysis

Results in pCi / I

WeekEnding

Mul1&Jul22-Jul29Jul5-Aug

12-Aug19-Aug28-Aug

2-Sep9-Sep

16-Sep23-Sep30-Sep

7-Oct14-Oct21-Oct28-Oct4Nov

11-Nov18-Nov

25-Nov2-Dec9-Dec

16-Dec23-Dec30-Dec

Russell

2 '82.192.342.622.883.052.582.142.532.422.341.821.822.21'l.952.241.622.612.212.722.352.512.502.772.952.57

+

+

++

0.690.710.730.710.720.690.720.730.730.730.740.730.710.730.720.73

g 0.73g 0.74g 0.75g 0.74

~ 0.73+ 0.70g 0.71g 0.75g 0.74+ 0.74

2.092.782.392.382.943.562.972.322.862.172.242.472.392.212.342.532.573.173.522.424.043.262 ~ 15

2.233.582.73

g 0.73g 0.72g 0.71~ 0.74g 0.74g 0.74g 0.72g 0.72~ 0.74g 0.70g 0.71~ 0.72g 0.74g 0.74i 0.75g 0.74g 0.78g 0.75g 0.76~ 0.71g 0.79g 0.76i 0.72g 0.73g 0.78g 0.74

O.W.D.

2.112.532.532.182.492.302.832.841.943.022.771.81

0.730.710.710.730.720.710.710.740.690.730.730.68

2.141.712.242.024.572.852.644.072.822.242.542.482.72

0.740.580.720.750.810.740.730.790.740.720.730.730.74

Circ In Circ Out

2.11 g 0.732.28 + 0.713.02 ~ 0.732.63 g 0.752.07 + 0.693.06 g 0.733.01 ~ 0.722.68 ~ 0.742.72 g 0.722.93 + 0.732.49 + 0.722.21 g 0.7'l2.03 g 0.73'l.99 g 0.742.58 + 0.762 '4 + 0.732.18 + 0.762.37 + 0.723.24 + 0.752.80 g 0.732.79 g 0.732.26 g 0.723.17 2 0.762.24 + 0.721.99 + 0.711.87 g 0.71

Deer Creek

4.10 + 0.74

5.52 + 0.80

3.53 + 0.73

3.33 g 0.75

4.50 g 0.77

4.78 2 0.78

Tap

2.87 + 0.73

2.83 g 0.73

2 '3 + 0.70

2.64 g 0.75

1.83 + 0.71

2.32 2 0.72

Well

'B'.00

2 0.74

5.04 R 0.76

5.42 2 0.80

4.08 g 0.80

4.85 2 0.78

4.48 2 0.78

Maximum

AverageMinimum

3.052.391.62

g 0.81

+ 0.74

4.042.702.09

g 0.79

g 0.73

4.572.581.71

0.81

0.58

3.24 + 0.752.501.87 g 0.71

5.52 + 0.804.293.33 g 0.75

2.87 + 0.73 5.42 ~ 0.802.49 4.651.83 g 0.71 4.00 g 0.74

All values given as ( are less than the LLD corrected for decay.

B) Circ-in pumps out of service.

(32)


Table 3-5 CFallout Gross Beta Analysis

Results in pCi/ m'/ Day

Month of

January

February

March

April

May

June

July

August

September

October

November

December

Station 3

9.36 x 0.80

5.97 2 0.80

5.17 R 0.63

7.73 2 0.62

5.81 k 0.63

2.73 2 0.59

1.54 i 1.7410.58 i 0.654.84 a 0.61

3.14 i 0.684.27 R 0.59

0.96 R 0.53

Station 5

4.29 a 0.75

1.84 a 0.68

2.58 a 0.57

2.49 a 0.53

4.62 k 0.62

2.78 a 0.60

1.16 k 1A5

2.61 a 0.55

2.98 a 0.57

2.18 i 0.665.32 k 0.60

3.58 x 0.59

Station 8

6.10 R 0.75

1.57 a 0.58

3.26 a 0.56

5.86 2 0.59

3.16 a 0.59

2.98 R 0.58

1.39 a 0.62

5.86 k 0.58

2.23 x 0.57

OAS a 0.57

3.83 a 0.55

4.61 R 0.60

Station 10

5.33 a 0.65

0.92 t 0.53

3.07 a 0.56

8.47 i 0.611.82 i 0.55

Station 12

2.06 a 0.55

2AO a 0.58

3.27 a 0.57

7.12 a 0.67

7.89 a 0.80

3.60 a 0.60 32.14 a 0.60

0.94 a 1.13 6.69 a 0.88

3.52 a 0.60

3.72 R 0.77

1.79 j 0.522.34 x 0.56

25.23 a 1.04

9.25 a 1.09

10.70 k 0.64

1.69 a 0.56

7.79 a 0.64 16.57 k 0.78

MaximumAverageMinimum

10.58 a 0.65

5.18

0.96 a 0.53

5.32 a 0.60

3.04

1.16 a 1A5

6.10 i 0.75 8.47 a 0.61 32.14 4 0.603A4 3.61 10.42OA5 a 0.57 0.92 a 0.53 1.69 x 0.56

Allvalues given as < are less than the LLD corrected for decay.

* Higher beta activity at Station 12 associated with large insect and leaf collection in sample bottle dueto location. Samples regularly discolored by organic materials. Gamma scan of sampledid not identify any gamma emitter. Reanalysis of sample gave same result.

(33)

R.E. GINNANUCLEAR POWER STATION

ENVIRONMENTALWATER SAMPLES

GROSS BETAANALYSIS FOR 1994

5.00

4.50

4.00

" 3.50CI

3.00

I2.50

L'.OOTER 1.50

1.00

0.50

0.00r CVCOOOCO&COSO~CVCOOOCDt COOtO~hlCOCOCOh COSOw80)'ct'OCOh COROT ACOCOCDF COSOwblw w w w r w v- bl 8 bl CV hl CV CV bl bl Ol CO CO CO CO CO CO tO CO CO 0) 4 'ct' 0- 'ct' C 4 4 0 0 0 Q

WEEK NUMBER~ OWD ~ RUSSELL(34)

12.00

ANNUALTRENDING OF ENVIRONMENTALWATER

GROSS BETA ANALYSIS

10.00

P 800CI

IL 600I

TER 4.00

2.00

0.00CO CD 0 ~ bl CO 4 0 CO h. CO CD 0 r CV CO W 0 CO(0 CO W h 0 W W 0 W W W W CO CO CO CO CO CO CO

YEARS 1968 - 1994

CO CD O r blCO CO CO CD CD CD CD CD~ RUSSELL ~ DWD

(35)


Table 3-6Ontario Water District Water Gamma Isotopic Analyses

Results in pCi/Liter

Between Dates Of 7Be 51Cr 54Mn 59Fe 58Co 60Co 65Zn 95Zr 95Nb 103Ru 106Ru 134Cs 137Cs 140Ba 141Ce 144Ce 226Ra

31-Dec14Jan2Man11-Feb25-Feb11-Mar

25-Mar

8-Apr22-Apr6-May

20-May3Jun

174un14ul

1&JulPaul

12-Aug26-Aug

9-Sep23-Sep

7-Oct21-Oct4Nov

18-Nov

2-Dec16-Dec

1+Jan2Man11-Feb25.Feb11-Mar25-Mar

8-Apr22-Apr6-May

20-May3-Jun

174un1 Jul

15-Juljul12-Aug26-Aug

9-Sep23-Sep

7-Oct21-Oct4-Nov

18-Nov2-Dec

16-Dec30-Dec


Table 3-7Circ. Outlet Water Gamma Isotopic Analyses


Between Dates Of 7Be 51Cr 54Mn 59Fe 58Co 60Co 65Zn 95Zr 95Nb 103Ru 106Ru 134Cs 137Cs 140Ba 141Ce 144Ce 226Ra

29-Dec12Jan26Jan9-Feb

23-Feb9-Mar

23-Mar6-Apr

20-Apr

4May18-May

1 Jun1SJun2gJun1SJul27Jul

10-Aug24-Aug

7-Sep21-Sep

5-Oct19-Oct2-Nov

16-Nov

30-Nov14-Dec

12Jan28Jan9-Feb

23-Feb9-Mar

Z3-Mar

6-Apr20-Apr4-May

18-May1 Jun

1SJun2gJun1SJul27Jul

10-Aug

24Aug7-Sep

21-Sep5-Oct

19-Oct2-Nov

16-Nov30-Nov14-Dec28-Dec


Table 3-8Russell Station Water Gamma Isotopic Analyses


Month of 7Be 51Cr 54Mn 59Fe 58Co 60Co 65Zn 95Zr 95Nb 103Ru 106Ru 134Cs 137Cs 140Ba 141Ce 144Ce 226Ra

Jan-94Feb-94

Mar-94

Apr-94May-94Jun-94Jul-94

Aug-94Sep-94Oct-94Nov-94Dec-94


Table 3-9Tap Water Gamma Isotopic Analyses



Jan-94Feb-94Mar-94Apr-94May-94Jun-94Jul-94

Aug-94Sep-94Oct-94Nov-94

Dec-94


Table 3-10Well "8" Water Gamma Isotopic Analyses


Month of 78e 51Cr 54Mn 59Fe 58Co 60Co 65Zn 95Zr 95Mb 103Ru 106Ru 134Cs 137Cs 1408a 141Ce 144Ce 226Ra

Jan-94Feb-94Mar-94

Apr-94

May-94Jun-94Jul-94

Aug-94Sep-94Oct-94Nov-94Dec-94


Table 3-11Deer Creek Water Gamma Isotopic Analyses



Jan-94Feb-94

Mar-94

Apr-94May-94Jun-94Jul-94

Aug-94Sep-94Oct-94Nov-94

Dec-94


Table 3-12 AEnvironmental Water Samples Tritium Analysis

Results in pCi/L

Month of

January

February

March

Russell


Table 3-12 BFallout Tritium Analysis

Results in pCi/L

Month of

January

February

March

Station 3


Table 3-13Iodine in WaterResults in pCi/L

Month of

January

February

March

Russell

3A ~Mlk 5

There are three dairy herds located three to five miles from the plant. Milk

samples are collected monthly during November through May from one of the

three and biweekly during June through October from each. A control farm

sample is taken for each monthly sample and once during each biweekly period.

The milk is analyzed for iodine-131 and also gamma scanned for major fission

products.

All positive counts and the 2 sigma error are reported. All negative counts after

background correction are reported as


Table 3-14Milk

Results in pc VLiter

Farm

CDB

DADCDBDACB

DACB

DAC

BDACB

DACB

0ACB

DACBDACB

DACB

0ACB

0ACB0AB

D

Date

19@an2lhJan15-Feb16-Feb16-Mar18-Mar12-Apr15-Apr11-May12-Maythun74un94un1+Jun164un21 dun23Jun284unXWun6-Juljul124ul1Mul194ul21 jul2&Jul28-Jul2-Aug4-Aug9-Aug11-Aug16-Aug18-Aug23-Aug25-Aug30-Aug1-Sep6-Sep8-Sep13-Sep15-Sep20-Sep23-Sep27-Sep29-Sep4-Oct6-Oct11-Oct13-Oct18-Oct20-Oct25-Oct27-Oct15-Nov17-Nov13-Dec14-Dec

l-131

Indicator fish are caught in the plume from the Discharge Canal and tested forradioactivity ingested from liquid effluent releases from the plant. The fish arefilleted to represent that portion which would normally be eaten. Additional fishare caught more than 15 miles away to be used as background indicators and areprepared in the same manner.

Four different species of fish are analyzed during each half year from the indicatorand background locations if they are available.

There was no real difference in the activity of the fish caught between theindicator and background locations.

Isotopic gamma concentrations (pCi/kilogram wet) are listed in Tables 3-15A, 3-15B.

Samples of algae (cladophora) and sand were obtained from the lake bottom inthe discharge plume area. Results of the gamma scan are included in Table 3-16.

Fish are caught by an outside group and given to us after being held for periodsof less than one week for counting by gamma scan. The LLD value for theshorter half life isotopes became large. This is the case for most of thechromium, iodine and barium data in the table. The data is also affected by smallfish samples (< 2000 grams) in some species.

(47)


Table 3-15Fish Samples Gamma Isotopic Analysis

Results in pCI/kgm Wet

Description

Indicator Fish

First Half 1994

40K 51Cr 54Mn 59Fe 58Co 60Co 65Zn 95Zr 95Nb

Rainbow TroutBrown TroutLake TroutFreshwater Drum

4265 g 104


Table 3-15Fish Samples Gamma Isotopic Analysis

Results in pCi/kgm Wet

Description

Indicator Fish

First Half 1994

103Ru 106Ru 131I 134Cs 137Cs 140Ba 141 Ce 144Ce 226Ra

Rainbow TroutBrown TroutLake TroutFreshwater Drum

(10«34


Table 3-16Lake Samples Gamma Isotopic Analysis

Results in pCi/kgm

Description

Cladophora

Lake Bottom

1486 g 29

8838 g 79

3.6 Ve etation Sam les

Crops are grown on the plant property and samples of the fruits and grains arecollected at harvest time for testing. Background samples are purchased fromfarms greater than 10 miles from the plant. There was no indication in thesamples of any measurable activity other than naturally occuring K-40. Gammaisotopic data is given in Table 3-17.


Table 3-17Vegetation Samples Gamma Isotopic Analysis

Results in pCi/kgm Wet

Description 40K 51Cr 54Mn 59Fe 58Co 60Co 65Zn 95Zr 95Nb

Lettuce

ApplesCherries

GrapesSquashCabbage

5805 + 208745 g 235

1366 g 625167 + 583298 + 4211836 + 110

«166

3.7 External Penetratin Radiation

Thermoluminescent dosimeter (TLD) with a sensitivity of 5 millirem/quarter are

placed as part of the environmental monitoring program. Thirty-nine TLD badgesare currently placed in four rings around the plant. These rings range from lessthan 1000 feet to 15 miles and have been dispersed to give indications in each

of the nine land based sectors around the plant should an excessive releaseoccur from the plant. Badges are changed and read after approximately 3 monthsexposure.

TLD location 47 is influenced by its close proximity to the ContaminatedEquipment Storage Area established in 1983 and will normally read 20-30mRem/quarter. For the year of 1994, omitting location 7, on-site exposure rangedbetween 9.6-32.1 mrem/quarter, with an average exposure of 13.8 mrem/quarterand off-site 9.3 - 15.0 mrem/quarter with an average exposure of 12.1mrem/quarter. TLD location 13 indicates a high reading for the third and fourthquarters after a contaminated heat exchanger was placed within 75 feet of thislocation for storage. Table 3-18 gives TLD readings for each quarter.

A trend chart with a comparison of data for each location for the years of 1993and 1994 is included. The data plotted is the average quarterly dose measured.

The NRC also obtains TLD measurements around the plant. The following is acomparison of the data for each quarter of 1994 using NRC data from NUREG-0837 Vol. 13, No. 1, 2, 3, and 4. Results in mrem/quarter:

GINNA NRC

1st 2nd 3rd 4th< 2 miles 11.4 13.9 15.2 14.52-5 miles 10.4 12.7 13.9 12.7>5 miles 100 122 128 121

1st 2nd 3rd 4th12.0 13.9 14.4 14.111.7 12.9 13.8 13.312.3 13.8 13.4 13.7

There are six stations that are co-located. The differences in the comparison of co-located TLDs may be because the NRC uses model 801 TLDs and Ginna usesmodel 814s. These comparisons are:

ABCDEF

11 0 " 147 1309 8 11.1 12 5 11.5

10.2 11.8 13.0 11.79.3 13.1 14.0 12.99.7 11 4 12.6 12.09.5 10.9 11.6 12.2

12.6 15.4 15.5 16.012.4 13.1 15.1 13.412.7 15.3 15.4 15.911.0 13.0 14.8 13.810.7 11.2, 12.0 11.812.6 13.8 13.9 13.7

* Dosimeter Missing

(53)


Table 3-18

External Penetrating Radiation

ermoluminescent Dosimetry 1992

Units mRem/91 Day Quarter

¹2- ¹7 plus ¹13 areon-site near the lineof the highest annualaverage ground level

concentration.

¹8 - ¹12 are offsite ata distance of 8 to 15 miles.

¹14- ¹16 are locatedalong a line 3000 ft. westof the plant.¹17- ¹21 are locatedalong Lake Road.

¹22 - ¹24 are locatedalong the east siteboundary line.¹25- ¹30 are offsiteat a distance of 8to 15 miles.

¹31 - ¹40 are locatedin an arc at a distanceof 4 - 5 miles.

A) TLD's missing at time of collection.

~ocatio

2345678910

11

12

13

14

15

16

17

18

19

2021

22232425262728293031

323334353637383940

1s

11.211.4

11.8

12.5

9.617.1

10.7

9.510.210.6

9.412.6

10.8

12.7

11.310.812.3

11.210.611.311.711.3

11.49.99.6

10.2

9.89.3

10.7

11.0

9.8

11.010.510.810.2

10.711.3

9.3

9.7

~uaderj 2.8j 2.9+ 3.0j 31j 2.4+ 4.3j 27+ 2.4j 2.6+ 2.7+ 2.4j 3.2j 2.7j32j 2.9+ 2.7j 3.1j 2.8j 27+ 2.8+ 2.9j 2.8j 2.9j 2.5j 2.4j 2.6j 2.5j 2.4j 27j 2.8j 2.5j 2.8j 2.6

2,7j 2.627j 2.9j 2.4j 2.4

2~nd uader13.8 j 3.513.7 j 3.414.2 + 3.614.3 + 3.612.3 j 3.124.3 j 6.112.0 j 3.010.9 + 2.712.0 j 3.012.3 + 3.111.5 j 2.915.0 j 3.813.4 + 3.414.5 j 3.614.1 j 3.612.9 j 3.214.9 j 3.813.9 j 3.514.4 j 3.614.0 j 3.513.3 j 3.414.1 j 3.513.9 j 3.512.5 j 3.111.5 + 2.912.8 j 3.214.3 j 3.612.2 j 3.112.5 j 3.2

A11.1 j 2.8131 j 3313.9 + 3.513.8 j 3.511.8 j 3.012.2 j 3.114.1 j 3.513.1 j 3.311.4 j 2.9

~duaraeu14.0 j 3.515.2 j 3.815.4 j 3.915.1 j 3.813.0 j 3.324.2 + 6.113.4 j 3.411.6 j 2.9123 j 3113.2 j 3.311.8 j 3.020.6 j 5.214.5 j 3.615.9 j 4.015.1 j 3.814.4 j 3.615.9 j 4.015.1 j 3.815.1 j 3.814.9 j 3.714.1 j 3.515.1 j 3.814.9 j 3.8123 j 3112.1 j 3.013.9 j 3.514.6 j 3.712.7 j 3.213.0 j 3.314.7 j 3.712.5 j 3.114.8 j 3.714.5 j 3.715.0 j 3.813.0 j 3.312.9 j 3.314.6 j 3.714.0 j 3.512.6 j 3.2

4th uarter132 j 3314.0 j 3.514.2 j 3.613.8 j 3.512.4 j 3.122.4 j 5.612.4 j 3.112.2 j 3.111.8 j 3.012.1 j 3.111.4 j 2.932.1 j 8.113.5 j 3.414.0 j 3.513.8 j 3.512.8 j 3.214.4 j 3.613.1 j 3.310.0 j 2.514.0 j 3.513.0 j 3.313.6 j 3.413.8 j 3.5

A11.6 j 2.912.7 j 3.213.4 j 3.411.9 j 3.011.8 j 3.013.0 j 3.311.5 j 2.913.3 j 3.413.6 j 3.4132 j 3311.7 j 2.911.7 j 2.913.6 j 3.412.9 j 3.312.0 j 3.0

(54)

25.0

EXTERNALPENETRATING RADIATION

THERMOLUMINESCENTDOSIMETRY

A 20.0

VE

m 150Rem

I 10.0

QTR 5 0

0.0

2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40

TLD LOCATION NUMBER~ 1993 ~ 1994(55)

4.0 LAND USE CENSUS

A land use census is done each year to determine any major changes in the useof the land within 5 miles of the plant. There were no major changes during 1994.The land use remains mainly agricultural in nature. There were several privatehomes constructed, but no new housing developments or large businessconstruction projects. The three dairy operations nearest the plant continued inoperation with an average of 40 to 70 milking cows. There are no goats used formilk on a regular basis within the 5 mile radius. Beef cattle are still raised on 3farms within 2 miles of the plant as in the past.

A copy of the Land Use Census is attached.

(56)

~ nuzEALLOIT~ CORN FIELDS~ am+ ZZZLDS

LEGEND

W muuGEORCSIAROS

XXVZXiSA MSZXXSSaxcaxahoxxz, aaxas

OI!AAATTATI

E

SH PHE ROA

WOODARD

B G

ON

KESI0E

WI I

iTAiT BRI

0V

350

FVANACE

ISHEA

0NE

S

0

RD

ATOM ROAD

TVCKAH0E

R

WOODS RD.

SALT

R0AD

E

T

R0A

U "I''' II"" ' T - 0N

~OTTTAIAATAITI .Aplll,lii,liI li,

RD

K E

PARK

RDAI 0

AD

ONTARIOSCHOOLS

0A

TAAIIXA~AIR

R0

0

ATAT

ALM0M

CAEEK

STATE ROAD

LINE

R0AD

R0AD

NG

ALBRIGHT

HENNESSEY RD.

GOCO

LFVASE

flNLEYROAD

AR80R

A0AD

TRUMMONDS ROAD

PEASE

R0AD

CHAPEL

R0A

ENGLS

D

04 RD.AI0G

E

EDDYRD

SMIIIHIILLROAD

A0

RICE RD.

5.0 EXTERNAL INFLUENCES

During 1994, there were no external influences such as atmospheric weapons

testing or accidents at other nuclear facilities which caused an influence on the

data reported. The annual trending graphs for air and water indicate a level effect

in the measured activity.

6.0 EPA INTERLABORATORYCOMPARISON STUDY

An indication of the laboratory's ability to analyze samples and achieve results

consistent with other laboratories is the aim of the EPA Interlaboratory Comparison.Selected unknowns are received and analyzed by our procedures and the results

are sent to the EPA Environmental Monitoring Systems Laboratory. A report isreturned from them indicating the concentrations with which the samples were

spiked and how we compared to other laboratories analyzing the same samples.Table 6-1 is a tabulation of the Ginna results of samples analyzed during 1994.

Graphs showing a statistical analysis and trend of the results of RGB E's analysisand all reporting laboratories is included after the table. The sigma value is smallerthan that calculated by EPA for a single laboratory. The graphs indicate that ouragreement with other laboratories for the analysis is good.

Following Table 6-1 is a statistical analysis and trend of RG8E's comparison to allnon-outlier laboratories participating in the 1993 and 1994 EPA InterlaboratoryComparison program. Normalized standard deviation (Z-score) statistic is used toassess RGBE's accuracy and precision relative to the other laboratories and isdefined by the following equation.

Z soore ( Gi nna mean )-(Grand Avg . of'abs )(Standard Deviation of'abs)Upper and lower control limits are set at Z-scores equivalent to z 3 standarddeviations respectively. Upper and lower warning limits are set at Z-scoresequivalent to z 2 standard deviations respectively. Z-scores within the controllimits are assessed to have accuracy of agreement and Z-scores outside thecontrol limits are assessed to have accuracy of disagreement. Z-score trends withno more than 2 consecutive Z-scores outside the warning limits are assessed tohave acceptable precision, otherwise precision is assessed as a bias trending lowor high. All Z-scores have an accuracy of agreement and acceptable precision.

(58)


TABLE6-1

EPA INTERLABORATORYCOMPARISON PROGRAM - 1994

Description Date

Sample

Analysis

Experimental

Data

EPA Value

a1 Sigma

Alpha/Beta in Water 1/28/94

(Results in pCi/1)

Alpha

Beta

11 9 958 58 66

15g562 g 10

7/22/94 AlphaBeta

28 31 30

20 17 1832g810g5

10/28/94 Alpha

Beta

37 39 37

31 32 31

57 g 1423g5

Gamma in Water

(Results in pCI/I)

6/10/94 Co%0

Zn%5RU-106

Cs-134Cs-137

Ba-133

48 49 50

140 134 143

181 190 197

33 40 39

48 51 48

84 87 82

50g5134 g 13252 g 2540g549g598 R 10

11/4/94 Co@0Zn-65Cs-134Cs-137

Ba-133

57 55

103 97

21 20

47 46

67 68

56

9621

48

64

59g5100 g 1024g549g57317

Gamma in water (6/1 0/94) Ru-106-Respondents'verage was 21 6 x 28.EPA has chosen to discontinue this isotope because of continuingproblems in the analysis.

Iodine-131 in Water 3/18/94

(Results In pCI/1)10/7/94

I-131

1-131

124 125 124

78 84 81

119 g 12

79 + 8

(59)


TABLE6-1 (Cont'd)

EPA INTERLABORATORYCOMPARISON PROGRAM - 1994

Description Date

Sample

Analysis

Experimental

Data

EPA Value

a1 Sigma

AirFilters(Results in pCI/filter)

Alpha

Beta

Cs-137

45 47 4470 68 72

23 17 18

35g956 g1015g5

Milk

(Results in pCI/1)

9/30/94 I -131

Cs-137K-40

70 73 69

57 58 58

1760 1720 1730

75g859g5

1715 g 86

(60)

EPA tnterlaboratory Comparison Program, Gross Alpha-Beta

Sam le/MonthpCi/Ibeta

Grand Average

of LabspCi/Ial ha

Ginna MeanpCi/lal ha

\

pCi/lbeta

Normalized Deviation of Ginna Mean

from Grand Average of Labs

al ha beta

Wator/Jan93Water/July93Water/0ct93Water/Jan94Water/Juiy94Water/Oct94Filter/Aug93Filter/Aug94

17.09 41.9912.06 37.6514.08 17.0113.75 56.1429.74 14.9152.3 27.16

20.00 49.3236.89 59.08

15.6710.0012.67

I 9.6729.6737.6723 3345.33

20.33 I' -0.2751.33 ( -0.4818.00

i

-0.49

-7.501.610.34

60.67 -1.42 0.78'1 8.33,

~

-0.02 1.1931.33 „; -1.81 1.4552.67 ~ 1.16 1.16

70 I I', 1.62 1.89

1993-)994 Gross Alpha-Beta Trends

4.00

3.00UCL

2.00t0

1.00

Cl0.00

N

E -1.000z

-2.00

-3.00

UML

LWL

LCL

O alphaQ beta

-4.00Lr

L

R

L

UCL n Upper Control uma. UWL ~ Upper Wernettt limitLCL ~ Lower Control umn, LWL > Lower Wernettt umit

Note: Water/Jan93 low bias was duo to using a set of 20 ml aliquots of sample,because tho original set of four 200 ml aliquots became contaminated.

EPA Interlaboratory Comparison Program, Gamma Isotopic

Sam e/MonthWater/Feb 93

Water/June 93Water/oct 93Water/Nov 93Water/Feb 94Water/June 94Water/Oct 94Water/Nov 94Mitt/Sept 93Milk/Sept 94Fetor/Aug 93Fetor/Aug 94

117.6876.45 29.72 54.42 42.14

120.9986.46 49.77 36.99 5228

79.8970.81 58.87 22.95 51.92

50.02 120.1262.39 74.8910.0016.59

1674.071700.90

Grand Average of LabspCi/I pCUI pci/I pCi/I pCI/I mg/IBa-133 Co4IO Cs-134 Cs-137 I-131 K&0

101.3696.74 14.90 5.39 5.76

pci/I pCUIRu.106 Znes

103.87 107.54 104.00 16.67 4.00 6.00112.33

175.18 156.07 81.00 29.67 54.00 44.67124.33

216.56 140.62 . 84.33 49.00 37.33 49.00

107.00 107.33

159.67 149.33

189.33 139.00

104.6881.00

66.33 56.00 20.67 47.0047.67 114.33 1719.6757.67 70.67 1736.6713.0019.33

98.67

Ginna MeanpCi/I pci/I pCUI pCUI pCUI mg/I pCI/I pCUIBa-133 Co@0 Cs-134 Cs-137 I-131 K&0 Ru-106 Zn-65

109.67

Normalized Devtation of Ginna Mean

from Grand Average of Labs

1.26 0.61

0.99 %.02

%.37 %.27

~ 1.11 41.99

1.44%.48 0.08

4.774I.14 0.88

0.480.12 -1.17

0.2441.79 .1.70

41.81 4I.831.64 4.92

1.040.95

0.940.72

0.45 %.04

-1.34 %.78

~ 1.89 %.22

Ba.133 Co.60 Cs-134 Cs 137 1-131 KXO Ru.106 Zn.65

1993 - 1994 Gamma Isotopic Trends

4.00

3.00

2.00CO

1.00

O0.00

Oee

g -1.00ISz

-2.00

aga-13oC0-60a Cs-13oCB-13~ I-131aK-40aRu-10a Zn-65

-3.00

-4.00

ucl Veeee Ceeeei Ueel VWL ueyee Weche LiesLCI. Lew Ceeeeluwl LwL Ieeee weewea Ueie

(62)

Documents

Nuclear Regulatory CommissionP RID RITY l~ (ACCELERATEDRIDS PROCESSING~ REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester