radiological g environmental program monitoringsampling locations for the sses rad'iological...

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Susquehanna Steam Electric StationUnits 1 5 2

Radiologicalg Environmental Monitoring

Program

1980 Annual Report

9i05060230 9i0430PDR ADOCK 05000387

~ ~ ~

Pennsylvania Power 5 Light CompanyAllentown, PA

April 1SS1

Section

TABLE OF CONTENTS

Title ~Pa e

Executive Summary

Introduction

A.B.

C.D.E.

Site and Station DescriptionFundamentals of Radiological EnvironmentalMonitoring ProgramsObjectives of the SSES REMP

Regulatory OverviewScope of the SSES REHP

II-1II-4II-5II-5

Program Description III-1

IV. Monitoring Methods

A.B.C.D.

Ambient RadiationSurface WaterDrinking WaterAlgae

H.I.J.K.

E. FishF. Shoreline and FlocculatedG. 'round (Well) Water

Airborne Particulates andMilkSoil (Top and Bottom) andFood Products

Sediment

Air Iodine-131/Precipitation

Vegetation

IV-1

IV-1IV-1IV-1IV-2IV-2IV-2IV-2IV-3IV-3IV-4IV-4

V. Summary and Discussion of 1990 Analytical Results V-1

A.B.C.D.E.F.G.H.I.J.K.L.

Ambient RadiationSurface WaterDrinking WaterAlgaeFishShoreline and Flocculated SedimentGround WaterAir Particulates/Air Iodine-131/PrecipitationMilkSoil (Top and Bottom) and VegetationFood ProductsCalculated Dose to the Maximally Exposed Individual

V-1V-8V-14V-17V-20V-22V-25V-28V-33V-37V-41V-43

Section

TABLE OF CONTENTS

Title ~Pa e

VI. Deviations from the Technical Specifications SampleSchedule and LLDs

VII. Program Changes

VI-1

OVII-1

VIII. Conclusion VIII-1

IX. Summary Table IX-1

X. Land Use Census X-1

XI. References XI-1

XII. Data Tables XII-1

Appendix A USEPA Intercomparison Program Results A-1

Appendix B Summary of Analytical methods

Appendix C Data Reporting Conventions

B-1

C-1

11

IS OF T BLES

Tabl eNumbers ~Pa e

2.

3.

5.

'.

8.

9.

10.

12.

Annual Analytical Schedule forthe Susquehanna Steam ElectricStation (SSES) RadiologicalEnvironmental Monitoring Program-(REHP) 1990

TLD Monitoring Locations for theSSES Radiological EnvironmentalMonitoring Program — 1990

Sampling Locations for the SSESRad'iological Environmental MonitoringProgram — 1990

Summary of Data for the SSES OperationalRadiological Environmental MonitoringProgram - 1990

Nearest Residence, Garden and DairyAnimal in each of the 16 MeteorologicalSectors within a 5-Mile Radius of theSusquehanna Steam Electric Station - 1990

Environmental ThermoluminescentDosimetry Results —

. SSES 1990

Gross Alpha, Gross Beta, Tritium,Iodine-131 and Gamma SpectroscopicAnalysis of Surface Water — SSES 1990

Gross Alpha, Gross Beta, Tritium,Iodine-131, and Gamma SpectroscopicAnalysis of Drinking Water — SSES 1990

Gamma Spectroscopic Analysis of Algae-SSES 1990

Gross Beta and Gamma SpectroscopicAnalysis of Fish — SSES 1990

Gross Alpha, Gross Beta and GammaSpectroscopic Analyses of Shoreline andFlocculated Sediment — SSES 1990

Gross Alpha, Gross Beta,'Tritium andGamma Spectroscopic Analyses of Ground(Well) Water — SSES 1990

III-3

III-6

III-14

IX-1

X-2

XII-1

XII-7

XII-12

XII-15

XII-16

XII-17

XII-18

LIST OF TABLES

Tablegumbers

13.

14.

15.

16.

17.

18.

19.

20.

21.

Gross Beta Analyses of Air ParticulateFilters — SSES 1990

Gross Alpha and Gamma SpectroscopicAnalyses of Composited Air ParticulateFilters — SSES 1990

Gross Alpha, Gross Beta, Tritium andGamma Spectroscopic Analyses ofPrecipitation — SSES 1990

Gross Beta Minus K-40, Iodine-131 andGamma Spectroscopic Analyses of Milk-SSES 1990

Gamma Spectroscopic Analyses of Soil-SSES 1990

Gamma Spectroscopic Analyses of Vegetation-SSES 1990

Gamma Spectroscopic Analyses of FoodProducts (Fruits, Vegetables and Honey)-SSES 1990

Gamma Spectroscopic Analyses of Game,Poultry, and Eggs — SSES 1990

Typical Lower Limits of Detection ofNuclides Searched for but not found byGamma Spectroscopic Analysis in the Vicinityof Susquehanna Steam Electric Station — 1990

XII-21

XII-23

XII-25

XII-27

XII-34

XII-35

XII-36

XII-38

XII-39

FigureNumbers

2.

3.

4.

6.

LIST OF IGURES

Tltle

Exposure Pathways to Humans

1990 TLD Monitoring Locations withinOne Nile of the SSES

1990 TLD Monitoring Locations from One toFive Miles of the SSES

1990 TLD Monitoring Locations Greater thanFive Miles from the SSES

1990 Environmental Sampling Locations withinOne Mile of the SSES

1990 Environmental Sampling Locations fromOne to Five Miles of the SSES

~Pa e

II-3

III-11

III-12

III-13

III-21

III-22

7. 1990 Environmental Sampling Locations Greater III-23than Five Miles from the SSES

8.

9.

10.

12.

13.

14.

15.

16.

17.

18.

Ambient Radiation Levels Based on TLD Data

PIC/TLD quarterly Data Comparison-Berwick City Hall

PIC/TLD quarterly Data Comparison—Energy Information Center

PIC/TLD quarterly Data Comparison-Nanticoke Municipal Building *

PIC quarterly Comparison — All Sites

Gross Beta Activity in Surface Mater

Tritium Activity in Surface Mater

Gross Beta Activity in Drinking Mater

Gross Beta Activity in Air Particulates

Gross Alpha Activity in Air Particulates

Iodine-131 Activity in Milk

V-3

V-5

V-6

V-7

V-9

V-11

V-13

V-16

V-29

V-31

V-36

yakC

w

I. EXECUTIVE SUMMARY~

~

In 1990, there we re approximately 2000 routine samples collected at 140locations, and about 3000 routine analyses performed in support of theRadiological Environmental Monitoring Program (REMP). The extent ofthe sampling met or exceeded the requirements of the technicalspecifications for the Susquehanna Steam Electric Station (SSES). Thetypes of analyses performed on these samples for the identification andquantification of radioactivity also met or exceeded SSES technicalspecifications requirements. The result of this effort was verificationof the SSES Effluent Monitoring Program data that indicate that theoperation of SSES has no deleterious effect on the health and safety ofthe public or the environment.

The amounts of the radionuclides detected in 1990 are so small, as in pastyears, that the maximum dose to an individual in the general public isonly a small fraction of a percent of the dose limits established by theNuclear Regulatory Commission as stated in 10CFR50, Appendix I. Themaximum potential off-site dose from all pathways was calculated to beless than 0.01 millirem/year. This is negligible compared to the public'sexposure from natural background radiation of approximately 300millirem/year effective dose equivalent.

1-1

The preoperational radiological environmental monitoring program(REHP) for Pennsylvania Power 5 Light Company (PP&L) at theSusquehanna Steam Electric Station (SSES) was conducted from April1972 to September 1982. On September 10, 1982, Unit ¹1 becamecritical, thereby initiating the operational phase of the program.The preoperational phase of the program, as well as the initial phaseof the operational program (September 10, 1982 through June 1983),was conducted by Radiation Management Corporation (RMC). NUS

Corporation conducted the REHP from June 1983 until August 1984 whenTeledyne Isotopes (TI) took over the operational REHP. Theanalytical program was conducted under contract with PennsylvaniaPower 8 Light Company by Teledyne Isotopes during January andFebruary of 1990 and by Controls for Environmental Pollution for theremainder of 1990. Starting in August 1984, IchthyologicalAssociates (PPIIEL's biological consultants) assumed responsibility forthe sample .collection portion of the program. In June 1985, EcologyIII became PP8L's biological consultants (essentially utilizing thesame staff) and they continued to perform sample collectionactivities through 1990.

This report covers the period from January 2, 1990 throughJanuary 2, 1991. Teledyne Isotopes and Controls for EnvironmentalPollution performed all the analyses except the thermoluminescentdosimetry (TLD) program which is conducted by PPKL. A detailedguality Control and guality Assurance Program is conducted along withthe Radiological Program. Data from programs conducted in prioryears have been presented in a series of annual reports. (1-13, 21,27, 28, 31, 34).

A. Site and Station Descri tion

The Susquehanna Station contains two BWR generating units, eachwith a capacity of about 1050 HWe. Unit ¹I achieved initialcriticality on September 10, 1982. Unit ¹2 achieved initialcriticality on May 8, 1984. The site is located on anapproximately 1500 acre tract along the Susquehanna River, fivemiles northeast of Berwick in Salem Township, Luzerne County,Pennsylvania.

The area surrounding the site can generally be characterized asrural, with forest and agricultural lands predominating. Morespecific information on the demography, hydrology, meteorologyand land use characteristI~S of the local area may be found inthe Enyipnmental Report', the Final Safety ApgysisReport' and the Final Environmental Statement' for theSSES.

B. Fundamentals of Radiolo ical Enviro mental Honitorin Pro rams

Radioactive materials are present in man's environment as theresult of both natural processes and of man's technologicaldevelopments. Normally, people and organisms are continuallyexposed to naturally occurring radiation and radionuclides from

internal, terrestrial, and cosmic sources. The main contributionto the exposure of members of the general public from man-madesources is from the medical services field (x-rays, radioactivemedical treatments, etc.).

Background levels vary with time and location as they areinfluenced by external events such as cosmic ray bombardment,weapons test fallout, and seasonal variations. These levels alsocan vary significantly within relatively short distances due tovariations in the mineral composition of the earth's crust andother factors. Because of these spatial and temporal variations,the environmental radiological surveys in the vicinity of the

'SSES are divided into preoperational and operational phases. Thepreoperational phase of the program of sampling and measuringradioactivity in various media permits a characterization of theradiation levels and concentrations prior to plant operationalong with an indication of the degree of natural variation to beexpected. The operational phase of the program obtains datawhich, when considered along with the data obtained in thepreoperational phase, assist in the evaluation of theradiological impact of plant operation.

From a nuclear power plant'such as the SSES, there are threebasic pathways in which a member of the public has the potentialto be exposed to radioactivity. Figure I depicts these pathwaysof radioactive material uptake: I) inhalation (breathing); 2)ingestion (eating, drinking); and 3) whole body irradiationdirectly from the plant or from immersion in airborne effluents

To effectively monitor the radioactivity in the environment,media are sampled which have the potential to affect the humanbody either directly or indirectly. Hedia normally sampled tomeet radiological environmental monitoring program requirementsmay be categorized as either atmospheric or aquatic.

FIGURE 1

EXPOSURE PATHMAYS TO HUMANS

GASEOUS EFFLUENT

NUCLEAR POWER PLANT

Ol

oCO

0V.

0

0

0Q0Co.

OCO

O~

0

CaP+~«mwAll ~ Illy) gglly/p+

gfgl/villfP'e ut'e tylltNp ug, etjgg

~ 6on

oe'"y,io

Q45 <"Ch6b

C

C'

~O

LlQU10EFFLUENT

DirectIrradiation

FUEL TRANSPORT

Shoreiine p">ordure

r,i)g<o~

l

~egxlo /o4y

0

~r+

VI

0

0'0

Atmos heric Sam lin - Air is sampled to evaluate potentialradiation exposures from inhaled radionuclides in gaseous(iodine) or particulate form. Direct radiation and airsubmersion exposures are also monitored. Precipitation issampled to follow the movement of radionuclides from air toterrestrial and aquatic media.

Terrestrial Sampling - Plant life, primarily in the form of foodproducts (fruits, vegetables, etc.), is sampl.ed because it is a

primary source for ingestion of radionuclides. Common gameanimals normally hunted for food (deer, squirrels) are alsosampled.

Dairy products are sampled because th'ey are widely consumed.Hilk is one of the few foods commonly consumed soon afterproduction which may therefore contain relatively short-livedradionuclides when consumed.

Soil samples are also collected to provide an additional means ofmonitoring the air-to-ground pathway.

A uatic Sam lin — River water is sampled to verify the resultsof any liquid releases of radionuclides from the facility, anddrinking water supplies are sampled to identify and evaluate anypotential radiation exposure through ingestion.

Fish are sampled since they are a primary. aquatic food source.Algae and sediment are collected since they are indicators andaccumulators of radionuclides in the aquatic system.

Ob 'ectives of the SSES RENP

The objectives of the SSES Operational Radiological EnvironmentalHonitoring Program are:

1. To identify, measure and evaluate existing radionuclides inthe environs of the SSES, and to determine whether anysignificant increase occurs in the concentration ofradionuclides in critical pathways.

2. To verify that SSES operations have adequate reactor effluentcontrol.

3. To assess actual or potential dose impacts to the public.

4. To verify that SSES operations have no detrimental effects onthe health and safety of the public or on the environment.

5. To fulfill the obligations of the radiological environmentalsurveillance sections of the SSES Technical Specifications.

D. lator Overvie

United States Nuclear Regulatory Commission (USNRC) regulationsrequire that nuclear power plants be designed, constructed, andoperated to keep levels of radioactive material in effluents tounrestricted areas as low as reasonably achievable (ALARA) (10CFR 50.34 and 10 CFR 20. lc). To ensure that these criteria aremet, each license authorizing reactor operation includestechnical specifications (10 CFR 50.36a) which containrequirements governing radioactive effluents.

In-plant monitoring is used to ensure that predetermined releaselimits are not exceeded. However, as a precaution againstunexpected and undefined processes which might allow undueaccumulation of radioactivity in any sector of man's environment,a program for monitoring the environment in the vicinity of theSSES is also included in the SSES Technical Specifications. Theregulations governing the quantities of radioactivity in reactoreffluents allow nuclear power plants to contribute, at most, onlya few percent increase above normal background radioactivity.

The SSES REMP was designed on the basis of the USNRC RadiologicalAssessment Branch Technical Position on radiologicalenvirq~yqntal monitoring as described in Revision 1, November1979.' PP8L has expanded the basic program required by theNRC to aid in the characterization of area radiation levels andany possible impact from the SSES operation.

E. Sco e of the SSES REMP

In 1990, the SSES Radiological Environmental Monitoring Programincluded the measurement of ambient gamma radiation bythermoluminescent dosimetry; the determination of the activitiesof gamma emitters and gross alpha and gross beta activities inshoreline and flocculated sediments; the determination of theactivity of gamma emitters and gross beta activity in fish; thedetermination of gross beta and gross'lpha activities, and theactivities of gamma emitters in airborne particulates, and themeasurement of airborne iodine-131 activity; the measurement ofgross beta and gross alpha activities, and the activities ofgamma emitters, iodine-131 and tritium in water; the measurementsof gross beta and gross alpha activities, and the activities ofgamma emitters, and tritium in precipitation; the measurement ofiodine-131 activity, gross beta minus potassium-40 activity,strontium-89/90 activities, and the activities of gamma emittersin cow milk; and the determination of the activities of gammaemitters in game, poultry, eggs, various fruits and vegetables,algae, and in soil and vegetation.

Sampling locations are selected on the basis of local ecology,meteorology, physical characteristics of the region, anddemographic and land use features of the site vicinity.

There were approximately 2,000 types of routine samplescollected, and about 3,000 routine analyses performed in supportof the REHP program in 1990. The numbers exclude measurements ofambient gamma radiation by thermoluminescent dosimetry, duplicateand split samples and analyses, other quality control samples,analyses performed'*,independently by Pennsylvania StateUniversity, and other non-routine samples and analyses.

11-6

III. PROGRAN DESCRIPTION

One-hundred forty 1

The operational environmental radiological program for the SSES issummarized in Table 1. Tables 2 and 3 describe monitoring locations,associated media, and approximate distances and directions from thesite. Figures 2, 3, 4, 5, 6, and 7 illustrate the locations ofsampling stations relative to th'e SSES.

In addition to the described analytical program, a milk animal,vegetable garden, and residence survey was performed in 1990. Thissurvey identified the dairy animals within the five-mile radius of theSSES and the nearest garden and residence in each sector. These landuse parameters are used in the assessment of potential radiologicaldoses to hypothetical individuals and populations of the statedregions.

ocations were included in the SSES monitoringprogram for 1990. Environmental sampling locations were divided intotwo classes, indicator and control. Indicator- samples are thosecollected at locations which are expected to manifest station effects,if any exist, and were selected on the basis of distance from the site,topography, hydrology, meteorology, demogr'aphy, and drainagecharacteristics. Control samples are collected at locations which areexpected to be less likely to be affected by station operation. Thesecontrol samples provide a basis on which to evaluate fluctuations inradioactivity at indicator locations in relation to natural phenomenaand fallout. The number and locations of monitoring points weredetermined by considering the locations where the highest off-siteenvironmental concentrations have been predicted from plant effluentsource terms, site hydrology, and site meteorological conditions.Other factors considered were applicable regulations, populationdistribution, ease of access to sampling stations, security and futureprogram integrity.

Intentionally Left Blank

TABLE 1

(Page 1 of 3)

Annual Analytical Schedule for theSusquehanna Steam Electric Station (PP5L)

Radiological Environmental Monitoring Program - 1990

Media 5 CodeNo. of SampleLocations Freq.(a)

AnalysesRequired

AnalysisFreq.(b)

AirborneParticulates

AirborneIodine

Sediment

FlocculatedSediment

Fish

Surface(d)Water

Well (ground) Water

Drinking (e)Water

12

12

SA

SA

SA

HCor H

HC

Gross Beta (c)Gross AlphaGamma Spectrometry

I-131

Gro'ss AlphaGross BetaGamma Spectrometry

Gross AlphaGross BetaGamma Spectrometry

Gross BetaGamma Spectrometry(on edible portion)

Gross AlphaGross BetaI-131Gamma SpectrometryTritium

Gross AlphaGross BetaGamma SpectrometryTritium

Gross AlphaGross BetaI-131Gamma SpectrometryTritium

QC

QC

SASASA

SASASA

SASA

Note: See footnotes at end of table.

TABLE 1

(Page 2 of 3)

Annual Analytical Schedule for theSusquehanna Steam Electric Station (PPLL)

Radiological Environmental Monitoring Program — 1990

Media L CodeNo. of SampleLocations Freq.(a)

AnalysesRequired

AnalysisFreq.(b)

Precipitation

Cow Milk

Food Products(Various Fruitsand Vegetables)

Game

Poultryand Eggs

12

10

16

2

M, SM(f)

Gross AlpaGross Beta QGamma Spectrometry Q

Tritium Q

Gross Beta-K-40 SM, M

Strontium-89/90 SM, M (g)I-131 SM, M

Gamma Spectrometry SM, M

Gamma Spectrometry A



Soil

Vegetation

10 A

10 A



Note: See footnotes at end of table.

TABLE 1

(Page 3 of 3)

Annual Analytical Schedule for theSusquehanna Steam Electric Station (PPSL)

Radiological Environmental Monitoring Program - 1990

Media 5 CodeNo. of SampleLocations Freq.(a)

AnalysesRequired

AnalysisFreq.(b)

'irect

Radiation92

1

TLDTLD

Algae Gamma Spectrometry H

(a) W weekly, H monthly, SH semi-monthly, g quarterly, gC quarterlycomposite, SA = semi-annually, A - annually, HC monthly composite.

(b) Codes are the same as for sample frequency.,

(c)

g (<)

(e)

If the gross beta activity is greater than 10 (ten) times the yearly meanof the control sample, gamma analysis should be performed on theindividual filter. Gross beta analysis is performed 24 hours or morefollowing filter change to allow for radon and thoron daughter decay.

Stations 6S6 and 6S7 are checked weekly to assure automatic compositesampler operation which is time proportional. Stations 5S8 and 6S5 aregrab sampled weekly. Individual composites of the weekly samples aremade on a monthly basis (HC) and analyzed.

Water from stations 12H2 RAW and 12H2 TREATED is collected weekly.Individual composite samples of the weekly collections are made on amonthly basis (HC) and analyzed. 12H2 RAW is a time proportionalautomatic composite sampler. 12H2 TREATED is a daily grab sample.

(f) Stations 12B2, 14B1, 10D1, 9D3, 13E3 and 10G1 are analyzed semi-monthlyfrom April through October. 10D3 replaced 12B2 in October, 1990.

(g) Beginning in Harch 1990, Strontium-89/90 analyses were performed on allmilk samples instead of gross beta minus K-40 analyses. This changeoccurred following the award by PP&L of the contract for theradioanalyses of radiological environmental monitoring program samples toa different laboratory.

TABLE 2Page 1 of 5

TLD Monitoring Locations for the SSESRadiological Environmental Monitoring Program - 1990

Location Distance DirectionCode (miles)

DescriPtion

Less Than One Mile from the SSES'~

1S2

2S22S32S5

3S33S4

4S14S3

0.2

0.90 '0.9

0.90.3

1 ~ 00.2

(See Figure 2)

N Perimeter Fence

NNE Energy Information CenterNNE Perimeter FenceNNE Energy Information Center (PIC 2)

NE Recreational AreaNE Perimeter Fence

ENE Susquehanna River Flood PlainENE Perimeter Fence

5S1

5S7

6S46S86S9

7S6

8S2

9S2

10S110S2

11S211S311S6

12S3

13S213S413S5

0.80.80.3

0.20.20.2

0.2

0.2

0.2

0.40.2

0.40.30.5

0.4

0.40.40.4

EEE

ESEESEESE

SE

SSE

SSWSSW

SWSWSW

WSW

WW

W

North of Biological ConsultantsWest of Biological Consultants

- Perimeter Fence

Perimeter FenceSite Pole No. 44316/N34036Perimeter Fence (south)

Perimeter Fence

Perimeter FenceI

Security Fence

Perimeter FenceSecurity Fence

Golomb House (44016/N33986)Security FenceSW REMP Garden

Perimeter Fence

Perimeter FenceSecurity Fence

(LLRWHF-south)'"'ecurity

Fence (LLRWHF-north)'

TABLE 2Page 2 of 5



Description

14851486

15S415S5

0.50.7

0.60.4

(See Figure 2)

Site Pole No. 43996/N34230Site Pole No. 43869/N34174

Transmission LinePerimeter Fence

16811682

6A4

7A17A2

8A3

15A3

16A2

0.30.3

0.6

0.40.6

0.9

0.9

0.8

NNWNNW

ESE

SESE

SSE

NNW

Perimeter Fence (east)Perimeter Fence (west)

former State Police

Kline ResidenceBell Bend Pole No. 44437/N33887

PP&L Wetlands Sign

Serafin Farm

Rupinski Farm

Prom One to Pive Miles from the SSES~"(See Figure 3)

1B1

2B32B4

4B1

5B2

1.4

1 ~ 31.4

1.2

1.4

N

NNENNE

ENE

Mingle Inn Road

Durabond CorporationDurabond Corporation

Stone Crusher TrailPa. Route 239 Intersection

6B2

7B37B4

8B28B3

1 '

1 ~ 71.5

1.41.5

ESE

SESE

SSESSE

Wapwallopen

Council CupHeller's Orchard Store

Lawall ResidenceWapwallopen Post Office

TABLE 2Page 3 of 5



Description

9B1 1.3

(See Figure 3)

Transmission Line east of Rte. 11

10B210B310B4

12B412B5

13B1

14B1

2.01.71.4

1.71 '

1.3

1.8

SSWSSWSSW

WSWWSW

Algatt ResidenceGeneral Tank Equip. Co.General Tank Equip. Co.

Shultz FarmIntersection (Pole N43401/N33620)

Walker Run Creek

Stola Farm

15B1

16B2

11C1

1D2

3D1

8D3

9D4

10D2

12D3

1E11E2

4E1

5E2

1.7

1.61.7

2.0

4.0

3 '

4.0

3.6

3.0

3.7

4.54.2

4.8

4.5

NNWNNW

SW

N

NE

SSE

SSW

WSW

NN

ENE

E

Mingle Inn Trailer Park

Walton Power LineHigh Tension Lines

Salem Township Fire Company

near Mocanaqua Substation

Pond HillMowry Residence

Smith Farm

Ross Ryman Farm

Dagostin Residence

Lane ResidenceShickshinny Municipal Bldg.(PIC 3)

Ruckles Hill Rd.(Pole N46422/N35197)

Bloss Farm

TABLE 2Page 4 of 5

TLD Monitoring Locations for the SSESRadiological Environmental Monitoring Program — 1990

ILocation Distance Direction

Code (miles)Description

(See Figure 3)

6E1

7E1

llE112E1

13E4

14E1

4.7

4.2

4.7

4.7

4.1

4 ~ 1

ESE

SE

SW

WSW

St. James Church

Harwood Trans. Line Pole g2

Shifflett Residence

Berwick Hospital

Kessler Farm

Canouse Farm

Greater than Five Miles from the SSES~"(See Figure 4)

2F1

3F13F2

8F2

12F212F4

15Fl

16F1

3G2

3G33G4

4G1

7G17G2

5.9

9.19.9

8.5

5.25.2

5.4

7.8

10 '

1617

14

1412

NNE

NENE

SSE

WSWWSW

NNW

NE

NENE

ENE

SESE

St. Adalberts Cemetery

Valania ResidenceSheatown IntersectionHuff Residence

Berwick SubstationBerwick City Hall (PIC 1)

Zawatski Farm

Hidlay Residence

Nanticoke Municipal Bldg.(PIC 4)

WB Horton St. SubstationWB Service Center

Mountaintop — Industrial Park

Hazleton Chem LabHazleton (Pole N31852-H)

iTABLE 2

Page 5 of 5



Description

12G112G4

1510

(See Figure 4)

WSW PPEL Service Center, BloomsburgWSW Naus Residence

a) All distances from the SSES to monitoring locations aremeasured from the standby gas treatment vent at 44200/N34117(Pa. Grid System). The location codes are based on bothdistance and direction from the SSES. The letters in thelocation codes indicate if the monitoring locations are onsite (within the site boundary) or, if they are not on site,the approximate distances of the locations from the SSES asdescribed below:

SA-BCD

on site(1 mile

1-2 miles2-3 miles3-4 miles

EFGH

4-5 miles5-10 miles

10-20 miles)20 miles

The numbers preceding the letters in the location codes providethe directions of the monitoring locations from the SSES byindicating the sectors in which they are located. A total of16 sectors (numbered 1 through 16) equally divide an imaginarycircle on a map of the SSES and its vicinity, with the SSES atthe center of the circle. The middle of sector 1 is, directeddue north (N).. Moving clockwise from sector 1, the sectorimmediately adjacent to sector 1 is sector 2, the middle ofwhich is directed due north, northeast (NNE). Continuing tomove clockwise, the sector numbers increase to 16, which is thenorth, northwest sector.

The numbers following the letters in the location codes areused to differentiate sampling locations found in the samesectors at approximately the same distances from the SSES.

b) LLRWHF is the Low Level Radioactive Waste Handling Facility.

NORTK

FIGURE 2

1990 TLD MONITORING LOCATIONSWITHIN ONE MILE OF THE SSES

GI

OULDSLAND

15 16A2

iSA3

PC2~( SS);S2 3

~3S3

I14 iSS4

14SS

13SS ~

13S2 ~ ~13S4

12

SITEBOUNDARY

16S2 I /16Si

~oxi lj' 4S3

~ SS7

iwg,6540/; a'".'„,

1 NILE

BA3a

8

iiS3 ~ 9S2 6S2

1HS MSl~ Q

7lll'AKE

~TAW4S

SSi

SS4 o

6A4

I'

~

LI.

SUSQUEFIA YNARIVER

FIGURE 31990 TLD MONITORING LOCATIONS

FROM ONE TO FIVE MILES OF THE SSES

SUSQUEHANNARIVER

NORTH

15

1Ei o

SHICKSHINNY '8PIC 3o

182(IE2)

MOCANAQUA

LILY,I,A

14

o 14Ei o 1681a1482

6-a 1682 ~ 284 ~

8

1681

a 481

~ 301

4E1 o 4

13E4 1381 a

~ 1284a 1285

SSESml

1 NILE

~ 582

SE20

~ 12E1

o 1283

784a

~783a 1084 ~ 882

Ci 082 10

6E1 a

NESCOPECK0

11Ei

iom' NILES

SD4

883

7Ei

5 NILES

FIGURE 41990 TLD MONITORING LOCATIONS

GREATER THAN FIVE hfILES FROM THE SSES

NORTH

1516Fi

15Flg

/SUSQUEHANNA

RIVER

/

3 &3G3

NANTICOKE'PIC 4

(362)

GLEN LYON 3Fi..

14S ICKSHINNY

hfOCANAQUAOA

4~4CI

POND HILL

PIC 1(12F4) e

12F2

BER WIG K

12MIFFLINVILLE

te11

NESCOPECK /ee.

5 NILES

WAPWALLOPEN

18 EXILES

SF2 ~

CONYNGHAhfr /7~ 7G2

IIAZLE'I'ON

OR te. ~7G193

(hei

'TABLE 3Page 1 of 7

Sampling Locations for the SSESRadiological Environmental Monitoring Program - 1990


Description

Less Than One Mile from the SSES~~i(See Figure 5)

SURFACE WATER

5S86S56S66S7LTAW

0.80.90.80.4

E Area under power lineESE Outfall AreaESE River water intake lineESE Cooling tower blowdown line

NE — ESE Lake Took-A-,While (on site)

0.8

0.9

E

ESE

ALGAE

Above the river water intake—surface

Below the discharge diffuser-surface

6ALTAW

0.9

SEDIMENT

ESE Discharge diffuser pipeNE — ESE Lake Took-A-While (on site)

GROUND WATER

2S63S54S24S4

11S5

0.90.90.50.50.5

NNENE

ENEENE

SW

Energy Information CenterRiverlands Security OfficePeach Stand (on site)Training CenterEOF Building

AIR/PRECIPITATION

2S23S25S4

11S2

0.90.50.80.40.4

NNENEESW

WSW

Energy Information CenterSSES Backup Met TowerWest of Biological ConsultantsGolomb House (44016/N33986)EOF Building

TABLE . 3Page 2 of 7

Sampling Locations for the SSESRadiological Environmental Monitoring Program — 1990


Description

(See Figure 5)

15S4 0 '

AIR/PRECIPITATION(continued)

Transmission Line

SOIL/VEGETATION

3S75S5

11S415S4

0.50.80.40 '

NEESWNW

Backup Met TowerWest of Biological ConsultantsGolomb HouseTransmission Line

PISH

LTAW NE-SSE 'Lake Took-A-While

5S6S

EESE

GAME(c)

SSES (on site)SSES (on site)

Prom One to Five Miles Prom the SSES(See Figure 6)

1D3 3.9 N

SURPACE WATER

Mocanagua Bridge

IND 0.9 — 1.4 ESE

PISH<b>

At or below the discharge structure

TABLE 3Page 3 of 7



Description

(See Figure 6)

SEDIMENT<"

2B 1.67B . 1.2

11C . 2.6

NNESESW

Gould IslandBell BendHess Island

FLOCCULATED SEDIMENT~ ~

2B7B

1.61.2

NNESE

Gould IslandBell Bend

12E4 4 ' WSW

GROUND WATER

Berwick Hospital

AIR/PRECIPITATION

9B11D23D1

12El

1.34 '3.44 '

SNNE

WSW

Transmission Line east of Rte. 11Near Mocanagua SubstationPond HillBerwick Hospital

MILK

12B212B314B1

8D49D3

10D110D3

1 ~ 72.01.83.53.83.03.5

WSWWSWWNWSSE

SSSWSSW

'hultz FarmYoung FarmStola FarmChapin FarmBroyan FarmRoss Ryman FarmDrasher Farm

of 7TABLE 3



Description

(See Figure 6)

12D213E3

+Ii~~~'y p/~H tiff

3.75.0

MILK.(co@tinued) „

WSW Dagostin FarmW Dent Farm

SOIL/VEGETATION

9B21D43D2

12E2

1.34.03.44.7

SN

:NE =j

WSW

Transmission Line east of Rte. 11Near Mocanaqua SubstationPond. HillBerwick Hosp'ital

7B212B1

14B15B8D49D2

11Dl13E4

1.51.31.32.23.53.23 '4.1

SEWSWWNW

NWSSE

SSWW

FOOD

Heller's Orchard StoreKisner FarmMoskaluk ResidenceGibbons ResidenceChapin FarmRyman's Farm -ProductZehner FarmKessler Farm

MEATi POULTRY'GGS

12B110D1

1 33 0

WSWSSW

Kisner FarmRoss Ryman Farm

GAME(c>

2B8B

1.61-2

NNESSE

Gould IslandOff-site

of 7TABLE 3


LocationCode

Distance Direction(miles)

,Description

Greater Than Five Miles from the Site~'i(See Figure 7)

12F112G212H1

5.31726

SURFACE WATER

WSW Berwick BridgeWSW US Radium Site, BloomsburgWSW Merck Co.

DRINKING WATER

12H2R12H2T

2626

WSW Danville Water Co. (raw)WSW Danville Water Co. (treated)

FISH~bi

2H 30 NNE Near Falls, Pa.

2F

12F

6.4

6.9

SEDIMENT~ i

NNE Between Shickshinny and RetreatState Correctional Institution

WSW Old Berwick Test Track

12F3 5.2

GROUND WATER

WSW Berwick Water Co.

7G112G1

1415

AIR/PRECIPITATION

SE - Hazleton Chem LabWSW PP&L Service Center, Bloomsburg

PageTABLE 3

Sampling Locations for the SSESRadiological Environmental Monitoring Program — 1990


Description

(See Pigure 7)

MILK

10G1 14 SSW Davis Farm

7G112G3

1415

SOIL/VEGETATION

SE Hazleton Chem LabWSW PP&L Service Center, Bloomsburg

7F110F110F211F112F412F516F2

2H1

6.75.76.05.65.87.57.8

21

POOD

SE Burger FarmSSW Miller FarmSSW Karchner Farm

SW . Mangan ResidenceWSW Montgomery ResidenceWSW Seesholtz FarmNNW Hidlay ResidenceNNE Yalicks Residence

15F16F

5-105-10

NW Off-siteNNW Off-site

a) All distances from the SSES to monitoring locations aremeasured from the standby gas treatment vent at 44200/N34117(Pa. Grid System. The location codes are based on bothdistance and direction from the SSES. The letters in thelocation codes indicate if the monitoring locations are onsite (within the site boundary) or, if they are not on site,the approximate distances of the locations from the SSES asdescribed below:

of 7TABLE 3


SABCD

on site(1 mile

1-2 miles2-3 miles3-4 miles

EFGH

4-5 miles5-10 miles

10-20 miles)20 miles

The numbers preceding the letters in the location codes providethe directions of the monitoring locations from the SSES byindicating the sectors in which they are located. A total of16 sectors (numbered 1 through 16) equally divide an imaginarycircle on a map of the SSES and its vicinity, with the SSES atthe center of the circle. The middle of sector 1 is directeddue north (N). Moving clockwise from sector 1, the sectorimmediately adjacent to sector 1 is sector 2, the middle ofwhich is directed due north, northeast (NNE). Continuing tomove clockwise, the sector numbers increase to 16, which is thenorth, northwest sector.

The numbers following the letters in the location codes areused to differentiate sampling locations found in the samesectors at approximately the same distances from the SSES.

No actual location is indicated since fish are sampled overan area which extends through 3 sectors (5, 6, 7) near theoutfall area.

c) No permanent locations exist; samples are taken based onavailability. Consequently, it is not necessary to assign anumber following the letter in the location code.

III-20

FIGURE 5

1990 ENVIRONMENTALSAMPLING LOCATIONSWITHIN ONE MILE OF THE SSES

+NORTH

GOULDISLA&D

15mo'4>3

LTAU 355

i4

LJ

LSITEeaUVDnRV

ma,4'()0

1155

/j

o . /oi

11S2 'Qs

sm'gm

1 NILE

455

B

LAKETAW

554/+555 ~'E.sss@

@AG3558

$ 6S6

f+655-/~sa— AC4

SUSQUEHANNARIVER

SURFACE WATER

SEDIMENT

FISH

DRINKING IIATER

GROUND IIATER

Als

ta PRECIPITATION

MILK

sson

SOIL

~y VEGETATION

~ ~

, e CAME

MEAT, POULTRY,EGGS

AG ALGAE

FIGURE 61990 ENVIRONMENTALSAMPLING LOCATIONS

FROM ONE TO FIVE MILES OF THE SSES

SUSQUEHANNARIVER

NORTH

i5

oSHICKSHINNYi'io2 Fee

iD3

emlp'OCANAQUA-

LILY,I.A

301"

332It~

i43~33

13E3 ~»41481

13E4

12E1V &4

1281 ~-1282%~ 128399

11CA

SEES

i NILE@ -~

232

13ERWICK

11D1r ~ - o'

NESCOPECK~ r.

3 EXILESipoi ~

1OD3332

EO4 'yg

SURFACE WATER

+3 SEDIMENT

FISII

DRINKING WATER

GROUND WATER

5 HELES

9

Are

PRECIPITATION

MILK

roon

SOIL

VEGETATION

CAME

MEAT, POULTRY,

EGGS

FIGURE 71990 ENVIRONMENTALSAMPLING LOCATIONSGREATER THAN FIVE MILES FROM THE SSES

NaVH

16F2 ~ 3SUSQUEHANNA / NA T ICPKE

RIVER " '

GLEN LYON

14S ICKSHINNY

MOCANAQUAQ4

„

POND HILL

12' O1262 Qf12Hi Qf12R2RLT

12FS 4 QMIFFLINVILLE~ 5 ggf ESIh+

1071+

1774 @11

+ BERWICK+Pte 12F @12F1,. /i NESCOPECK

11Fi w Rte.

WAPWALLOPEN

0

771+

CONYNGHAM

g IOOIg10 BILES

HAZLETON

Rte. ~7G1

sw SURFACE WATER

SEDIMENT

FISII

DRINKING WATER

8ew GROUND WATER

AIR

PRECIPITATION

MILK

FOOD

SOIL

VEGETATION

c+ GAME

~ ~blEAT, POULTRY,EGGS

IV. MONITORING METHODS

A. Ambient Radiation

Thermoluminescent dosimeters (TLDs) were used to determine theambient radiation levels at ninety-two monitoring points as describedin Tables 1 and 2. TLDs were retrieved quarterly and processed.

The area around the station was divided into sixteen radial sectorsof 22.5 degrees each. TLDs were placed in all sectors. Monitoringlocations were chosen according to the criteria given in the USNRC

Branch Technica)lfqsition on Radiological Monitoring (Revision 1,November 1979).' The TLDs were placed at locations selected byconsidering local meteorological and topographical characteristicsand population distribution characteristics. The control locationswere 3G2, 3G3, 3G4, 4Gl, 7Gl, 7G2, 12G1, and 12G4.

In 1990, direct radiation measurements were made using Panasonic UD-801 TLDs containing crystals of calcium sulfate activated withthulium.

B. Surface Water

Surface water was sampled from the Susquehanna River at eightlocations and Lake-Took-a-While (LTAW) adjacent to the River in 1990.Time proportional automatic composite samples were picked up monthlyat location 12Hl and picked up weekly at locations 6S6 and 6S7.Monthly samples were also composited from weekly grab samples atlocations 5S8 and 6S5. Locations 5S8 and 6S5, although routinelysampled, provide alternate data for locations 6S6 and 6S7,respectively, in the event that water can not be obtained from theautomatic sampl'ers. Monthly grab samples were collected at locations1D3, 12Fl, 12G2, and LTAW. Locations 1D3, and 5S8 were the controllocations.

Surface water samples were analyzed monthly for gross alpha and betaactivities, the activities of gamma-emitting radionuclides, andiodine-131 and tritium activities.

C. Drinking Water

Drinking water (RAW) samples were collected at location 12H2 by meansof a time proportional automatic composite sampler and picked upweekly in 1990 from the Danville Municipal Water Authority facilityon the Susquehanna River. Daily grab samples (TREATED) were also

* taken by Danville Municipal Water Authority personnel, composited,and picked up weekly. RAW water is taken directly from theSusquehanna River intake structure while TREATED water is drawn fromthe supply line after processing. The Danville Municipal WaterAuthority facility is the closest drinking water facility on theSusquehanna River downstream of the SSES which could be affected byplant discharges.

Monthly composites of both the RAW and TREATED samples were analyzedseparately for gross alpha and beta activities, the activities ofgamma-emitting radionuclides, and iodine-131 and tritium activities.

D. Algae

In 1990, algae samples were collected monthly from control locationAG3 and indicator location AG4. Algae is collected passively byallowing the flow of Susquehanna River water to deposit it on aplexiglass collector.

E. Fish

Fish sampling on the Susquehanna River was conducted in the springand the fall of 1990 at two locations. An indicator location INDdownstream of the SSES and a control location 2H upstream of the SSES

were selected. Fish samples were also taken by electrofishing fromthe indicator location LTAW.

The fish were filleted and the edible portions were analyzed forgross beta activity and the activity of gamma-emitting radionuclides.

F. Shoreline and Flocculated Sediment

Shoreline sediment (0 to 4 ft. of water) samples were collected inApril and November of 1990 at locations 2B, 7B, llC, 2F, and 12F onthe Susquehanna River and at the LTAW location. =Locations 2B and 2

are the control locations for sediment.

Flocculated sediment was also collected at locations 2B and 7B inApril 1990. Flocculated sediment is the top, loose layer of sedimentin the river, that is easily moved and'shifted by the water.Flocculated sediment is composed of finer particles than theshoreline sediment.

All sediment samples are analyzed for gross alpha and beta activitiesand the activities of gamma-emitting radionuclides.

G. Ground (Well) Water

Ground water was sampled monthly from wells at locations 2S6, 3S5,4S2, 4S4, 4S5, 11S5, 12E4, and 12F3. Location 12F3 is a controllocation. Location 4S5 is an alternate for location 4S2 when wateris unavailable from that location. Samples can only be obtained fromlocation 3SS during the portion of the year when temperatures do notnormally drop below freezing.

During 1990, water samples obtained from locations 4S5 and 12F3 wereuntreated. From November 1990 through the end of the year, samplesobtained from location 2S6 were untreated. Untreated is used todescribe water that has not undergone filtering, softening, etc.

Ground water samples were analyzed for gross alpha and betaactivities, the activities of gamma-emitting radionuclides, andtritium activity.

Airborne Particulates and Air Iodine/Precipitation

Airborne pathways to man were examined by analyzing air particulates,air iodine, and precipitation.

Airborne Particulates and Air Iodine

Air samples were collected in 1990 at locations 2S2, 5S4, 11S2, 15S4,9B1, 1D2, 3D1, 12E1, 7G1, and 12G1. Locations 7G1 and 12G1 were thecontr ol locations.

Air particulates were collected on Gelman type-A/E, glass fiberfilters with low-volume air samplers. Air iodine samples werecollected with one-inch deep Science Applications, Inc. charcoalcartridges in series with the air particulate filters at alllocations.

The air samplers were run continuously and the filters and charcoalcartridges exchanged weekly. The elapsed time of sampling wasrecorded on an elapsed-time meter. Air sample volumes were measuredwith temperature-compensated dry-gas meters.

Air filters were analyzed weekly for gross beta activity, thencomposited quarterly and analyzed for gross alpha activity and theactivities of gamma-emitting radionuclides. The charcoal cartridgeswere analyzed weekly for iodine-131.

Precipitation

Precipitation samples were collected at least monthly in 1990 fromthe same locations as airborne samples were obtained and werecomposited quarterly.

Precipitation was analyzed for gross alpha and beta activities, theactivities of gamma-emitting radionuclides, and tritium activity.

Hilk

Cow milk samples were collected in 1990 from locations 1282, 12B3,SD4, 9D3, 10D1, 10D3, 12D2, 13E3, 14B1, and 10GI. Samples werecollected semi-monthly from April through October at six of theselocations; otherwise, samples were collected monthly. Location 10G1was a control location.

Throughout the year all samples were analyzed for iodine-131 activityand the activities of gamma-emitting radionuclides. During Januaryand February, all samples were analyzed for gross-beta-minus-potassium-40 activity. From Harch through December, all samples wereanalyzed for strontium-89/90.

J. Soil (top and bottom) and Vegetation

Soil (top and bottom) and vegetation samples were collected inSeptember 1990 at locations 2S4, 5S5, 11S4, 15S4, 9B2, 1D4, 3D2,12E2, 7G1, and 12G3. Locations 7G1 and 12G3 were control locations.

These samples were taken by compositing twelve plugs at eachlocation. The top soil consists of the first two inches of soil, andthe bottom soil is from a depth of two to six inches. These sampleswere analyzed for the activities of gamma-emitting radionuclides.

K. Food Products

Various types of fruits and vegetables were collected =in 1990 fromsixteen locations within the vicinity of the SSES. These locationsare identified in Table 3. Location 2Hl was a control location.

All fruit and vegetable samples were analyzed for the activities ofgamma-emitting radionuclides.

Poultry and Eggs

Duck, chicken, and egg samples were collected in 1990 from locations10Dl and 12B1 respectively. The edible portions were analyzed forthe activities of gamma-emitting radionuclides.

Game

Deer, rabbit, woodchuck, and squirrel samples were collected inSeptember and October of 1990 at locations identified in Table 3.The flesh was analyzed for the activities of gamma-emittingradionuclides.

IV-4

V. SUMMARY AND DISCUSSION OF 1990 ANALYTICALRESULTS

The analytical methods used by Teledyne Isotopes and Controls forEnvironmental Pollution are capable of meeting the lower limit ofdetection (LLD) requirements set forth in the Susquehanna Steam ElectricStation Technical Specifications. The procedures and an explanation ofthe analytical calculation methods used in the laboratory for theseanalyses are summarized in Appendix B. Data from the radiologicalanalyses of environmental media are tabulated and discussed below.

Radiological analyses of environmental media characteristically approachand freq~~ntly fall below the limits of state-of-the-art measurementmethods. For the gamma spectrometric results listed in this report,only those r adionuclides positively detected are listed in the tables. Apositively detected radionuclide is one for which the activity is greatertha~ the critical value. The critical value is equivalent to half theLLD . However, due to the presence of naturally-occurring radionuclidessuch as beryllium-7, potassium-40, radium-226, and thorium-228 inbackground gamma spectrometric results, naturally-occurring radionuclidesare reported only if their levels exceed their LLDs. Typical LLDs ofselected radionuclides searched for by gamma spectrometry are listed inTable 21.

For analyses other than gamma spectrometry, < is used in the data tableswhere activity was not positively detected. The number following < is theresult of a calculation as defined in Appendix B.

Tables 6 thr ough 20 give the radioanalytical results for individualsamples. A statistical summary of the results based only on positivelydetected activities appears in Table 4.

A. AMBIENT RADIATION

Thermoluminescent dosimeters (TLDs) included in the RadiologicalEnvironmental Monitoring Program (REMP) in 1990 were placed at 85indicator locations and 8 control locations. Sixteen of theselocations were co-located with TLDs belonging to the NuclearRegulatory Commission. A description of PPSL's TLD system may befound in Appendix B.

Totals of 329 indicator TLD readings and 32 control TLD readings weobtained from quarterly processings during 1990. The detailedresults of these TLD readings can be found in Table 6. The means oquarterly TLD readings for 1990 are compared to the ranges and meansof the yearly average TLD readings at indicator and control locationsduring the preoperational and operational periods 1978-1981 and 1982-1989, respectively, in the Table below.

AMBIE RADIATIO LEVELS AS MEASURED BY TLDS mR STD TR

LocationPeriod

IndicatorPPP ti lII~lti

~978-8 1982-89 1990

ControlPppti I II1978-81 1982-89 1990

~Ren e

, Mean18.5-19.218.9

17.3-19.218.3 17.9

15.0-17.9 17.3-19.216.3 17.8 18.1

Refer to Figure 8 which trends both indicator and control quarterlydata from 1973 through 1990.

Oakley'alculates an ionizing radiation dose equivalent of 82mrem/year from natural sources for the Wilkes-Barre area. SinceOakley's values represent averages covering wide geographical areas,the measured ambient radiation averages of 72 mrem/year for bothindicator and control locations in the vicinity of the SSES areconsistent with Oakley's observations. Significant variations occbetween geographical areas as a result of geological composition analtitude differences. Temporal variations result from changes incosmic radiation intensity and factors such as ground cover and soilmoisture.

Pressurized Ion Chambers

In 1990, pressurized ion chamber (PIC) data were collectedcontinuously at locations in Berwick (12F4/PIC 1), Nanticoke(3G2/PIC 4), Shickshinny (lE2/PIC 3), and at the Susquehanna EnergyInformation Center (2S5/PIC 2). TLD data was also obtained at theselocations.

PIC measurements at all locations are currently recorded on paperstrip charts that are periodically reviewed and then archived. Animproved collection method for this data began in December, 1988. Adatalogger was connected to the output of PIC 2 at the EnergyInformation Center to allow for the digital storage of PIC data.Near the end of July, 1990, dataloggers were also connected to theoutputs of PICs 1,', and 4 at the Berwick Town Hall, the ShickshinnyMunicipal Building, and the Nanticoke Municipal Building,respectively. Data collected and stored by the dataloggers forperiods of approximately one month each have been retrieved during1990 and analyzed. The dataloggers have been programmed to providehourly results for each monitoring period. From this information,overall hourly averages have been obtained for each monitoringperiod, as well as the maximum and minimum hourly levels within eaperiod.

V-2

MR/STD QTR50

FIGURAMBIEtT BAD.

BASED ON DATA

PRE OPERATIONAL OPERATIONAL

30

UhllT 2 CRlTlCALlTY

20

15

10

5

0, I I I I I ~ I I I I I I I I I I I I

1973 1975 1977 1979. 1981 1983 . 1985 1987. 1989

I ndicotor

Control

1991

The tables below summarize the overall average radiation levels inunits of milliRoentgen per standard quarter for each quarter, asconverted from hourly data, of 1990 that the respective dataloggerswere recording PIC measurements at PIC locations 1, 2, 3, and 4.

IC 1 - Berwick Town HallANBIENT RADIATIOM LEVELS AS NEASURED BY IC mR STD TR

Calendar u rter Overall

16.618.1

*Indications from a review of the data are that this value isprobably erroneous.

PIC 2 - Sus uehanna Ener Informatio CenteANBIENT RADIATION LEVELS AS NEASURED BY PIC mR STD TR

Calendar uarter

1

23

Overall

16.716.216.416.8

IC 3 - Shickshinn Nunici al BuildinNBIE RADIA IO LEVELS S NEASURED B PIC mR STD TR

C 1 da u te ~0ve all

18.318.4

PIC - ant co e Nunici al BuildinIO EVELS AS NEASURED BY PIC mR STD TR

Calendar arter Overall

17a518.4

Figures 9, 10, and 11 compare the quarterly average radiation levels asdetermined from TLD readings with the levels determined by PICs 1, 2, and 4 atlocations 12F4, 2SS, and 362, respectively. (No figure is included for PIC 3at the Shickshinny Municipal Building because TLD data for comparison with thePIC data only exists for the third quarter.) Either a positive or negativebias of PIC data relative to TLD data is consistently observed at eachlocation; PICs 2 and 4 display positive biases while PIC 1 displays a negativebias.

V-4

FIGUR 9PIC/TLD QTRLY DATA CGMPARISGN

Berwick City Hall

Exposure Rate {mR/qtr)30

20 /

+ PlC data logger wasnot installed until the

. third quarter.Data'as

unavailable prio'rto the third quarter.

10

0

/ji

/

2 3

Calendar Quarter,1s90

//

/

//

//

/ q

: Legend~ P.IC

CZI TLD

20

FIGUR 10PIC/TLIRT QTRLY DATA CGMPARISGM

Energy information Center

Exposure Rate (mR/qtr)

10

03

Calendar Quarter]SSO

/' LegendP.IC

CEl TLD

FIGUR 11

PIC/TLD QTRLY DATA COMPARISONNanticoke Municipal Building

20Exposure Rate (mR/qtr)

+ PlC data logger- wasnot installed until thethird quarter. Data .

was unavailable priorto the third quarter.

10

0

~ ~

2 3

Calendar Quarter.]990

.'egendPlC

UZI TLD

The table below compares the annual average radiation levelsseparately for indicator and control locations as determined by TLDdata from all 93 monitored locations and PIC data from the fourmonitored locations.

ANNUAL AVERAGE AMBIENT RADIATION LEVELS mR STD TR

IndicatorControl

TLD

17.918.1

PIC

17.218.0*

*PIC 4 at the Nanticoke Municipal Building is considered to bethe control.

Figure 12 compares PIC data from all four locations for all quartersfor which such information is available. The range of radiationlevels measured by all PICs in any quarter is less than twomilliRoentgen per standard quarter.

SURFACE WATER

Surface water was sampled monthly or composited monthly from ninelocations including three control locations. Samples were analyzedfor gross alpha, gross beta, iodine-131, tritium, and gamma-emittingradionuclides. A total of 108 routine (excluding non-routine grabsamples) surface water samples were analyzed. Seventy-two indicatorsamples were collected and 36 control samples were obtained. Thedetailed results of these analyses can be found in Table 7.

Eleven out of 71 surface water indicator samples and 7 out of 36surface water control samples analyzed for gross alpha activityyielded positive values (above the lower limit of detection or LLD)in 1990. LLDs for gross alpha analyses ranged from 0.8 to 2 pCi/1 in1990. This may be compared to the ranges, means, and medians ofyearly average gross alpha activities at surface water indicator andcontrol locations during the period 1984 through 1989 in the tablebelow.

U C TE GROSS ALPHA ACTIVITIES Ci

~Loc tio Indicator Control

Period" pan~

~Mea *

o

1984-891.8-4.32.6(2.5)

1990

1.0

1984-891.5-3.12.1(2.0)

1990

1.2

*The numbers in parentheses to the right of the means arethe respective medians.

The fact that the 1990 average results for both indicators andcontrols are below the low end of the range of previous annualaverages for gross alpha activity may be due to the change inlaboratories performing the analyses.

V-8

FIGURE 12PIC QUARTERLY COMPARISON

All Sites "uneveileble.

Exposure Rate (mR/qtr)20

10

02 3

Calendar Quarter1990

LegendKD BERWICKC2I ENERGY INFO. CENTER

EZ5 NANTICOKE23 SHICKSHINNY

Gross beta activity was positively detected in 49 out of 71 indicatorsamples and 27 out of 36 control samples in 1990. The means of grossbeta activities in surface water for 1990 are compared to the rangesand means (medians) of yearly average gross beta activities atindicator and control locations during the preoperational andoperational periods 1978-1981 and 1982-1989 respectively in the tablebelow.

SURFACE MATER GROSS BETA ACTIVITIES Ci 1

Location

Period

Indicator~tt 1 ~dt 1

~978-8 ~198 -89 '1990

Control~tt 1 ~d

19798-8, 1982-89 1990

~Ran e~can (median)

3.2-4.93.8(3.6)

3.0-7.75.4(5.4) 4.3

2.9-5.2 2.9-4.84.0(3.9) 3.7(3.7) 3.6

The average beta activity for indicator locations in 1990 is withinthe range of activities for the previous operational andpreoperational periods at the SSES. Refer to Figure 13 which trendsgross beta activities separately for surface water indicator andcontrol locations from 1975 through 1990.

Results from indicator location 6S7, the cooling tower blowdowndischarge line sample point, are an indicator of the concentration ofthe activity of the water that is periodically discharged to theriver. Since the activity at this sample location is not likely tobe representative of the activity in the river water more than a fewfeet -from the discharge pipe, it is of interest to compare the meanactivity of indicator locations excluding that of 6S7 in 1990 withthe mean gross beta activities at control locations during thepreoperational period 1978-81. The mean gross beta activity of theindicator locations for 1990 in the table above becomes 3.4 when 6S7is excluded. One can compare this mean activity with the mean ofyearly average gross beta activity for the control locations duringthe preoperational period.

Iodine-131 was positively detected in one surface water indicatorsample and one control sample during 1990. The ranges and means(medians) of yearly average iodine-131 activities at indicator andcontrol locations during the preoperational and operational periods1979-1981 and 1982-1989, respectively, are presented in the tablebelow.

SURFACE MATE IODINE-131 ACTIVITIES Ci l

Location Indicator1 d ~P

1979-81 1982-89 1990

~Ran e 0.24-0.37 0.17-0.60pean (median)0.29(0.25) 0.35(0.29) 0.6

ControlP

1979-81 1982-89 1990

0.29-0.43 0.18-0.550.36(0,36) 0.30(0.23) 1.0

FIGURE 3GROSS BETA ACTIVITY SURFACE 'FATER

PCI/LITER20

18 PREOPERATIONAL OPERATIONAL

16

12

UlGT 2 CRITiCALITY

1975 1977I I I I I I

1979 1981 1983I I I I I

1985 1987 1989 199'l

l ndictato'r

Control

Tritium was positively detected in'1 out of 70 indicator surfacewater samples and in 18 out of 36 control samples in 1990. The meansof tritium activities in surface water for 1990 are compared to theranges and means (medians) of yearly average tritium activities atindicator and control locations during the preoperational andoperational periods 1978-1981 and 1982-1989, respectively, in thetable below.

SU ACE WATER TRITIU ACTIVITIES Ci 1

~LocatioPeriod

~die~to ~Co trol~tt 1 1 I~It 1 ~Pt I~I»tl1978-81 1982-89 1990 1978-81 1982-89 1990

Ran<ac 101-122Mean (median) 109(106)

126-366290(308) 1228

119-319 „ 90-212171(123) 136(124) 631

Some of the reported tritium values for 1990 may have beenerroneously high due to contaminants in the sample aliquot counted.(A number of sample aliquots were neither filtered nor distilledprior to liquid scintillation counting.) Consequently, the 1990averages reported in the table above may be inflated by the resultsof these sample analyses.

The tritium activities reported throughout 1990 at location 6S7, thecooling tower blowdown discharge line, tend to inflate the meanactivity reported for all indicator locations, just as the 6S7 grossbeta activities inflated the mean indicator gross beta activity. Ifthe tritium activities from location 6S7 are excluded from the dataused to calculate the mean indicator tritium activity, the meanindicator tritium activity becomes 769 pCi/liter. Refer to Figure 14which trends tritium activities separately for surface waterindicator and control locations from 1972 through 1990. Note thattwo factors combined to create the unusually high second quarteraverage indicator tritium activity. High activity in the coolingtower,blowdown line and below minimum detectable or critical levelactivities for the other sampling locations account for this. Thisis because activities below these levels are not included in theaverage. Consequently, a greater proportion of the average activityfor this quarter was determined by the cooling tower blowdowndischarge line..In spite of the fact that the tritium activities reported for 6S7 arefrom the discharge line prior to dilution in the river, the highesttritium activity reported at 6S7 during 1990 is well below the NRCnon-routine reporting levels of 20,000 pCi/liter when a drinkingwater pathway exists or 30,000 pCi/liter when no drinking waterpathway exists. The calculated dose to the maximally exposedindividual due to tritium released to the Susquehanna River by way ofthe discharge line is presented in Section V-L.

V-12

2800

2600

2400

2200

2000

1800

A4

TRITIUMACTIVITYI URFACE WATERPCI LITER

1600

1400

1200

1000

800

600

400

200


UNIT 2 CRITICALITY

I ndicator

Coriirol

1972I I I I I I I I I I I I I I I ~ ~ I

1974 1976 1978 1980 1982 1984 1986 1988 1990

No anthropogenic gamma-emitting radionuclides were positivelydetected in surface water in 1990 that are attributable to the SSESoperation.

The anthropogenic (man-made) radionuclide cesium-137,was not reportedfor any indicator samples or control samples. The ranges and meansof yearly average cesium-137 activities at indicator and controllocations during the operational period 1983-1989 are presented inthe table below.

SURFACE WATER CESIUM-137 ACTIVITIES Ci 1

LocationPeriod

Indicator1983-89

Control1983-89

~Ran e~Mea

2.1-4.63.6

2.8-4.03.5

In 1983, 1984, and 1990, cesium-137 was below the lower limit ofdetection in all indicator and control samples. Since 1983, cesium-137 has been reported in 11 indicator samples and 15 control samples.Cesium-137 is attributed to fallout from previous atmospheric nuclearweapons testing and the Chernobyl incident.

DRINKING WATER

Twenty-three composite drinking water samples were analyzed during1990 from the Danville Water Company's facility 26 miles WSW of SSESon the Susquehanna River. The detailed results of the analyses ofthe samples can be found in Table 8.

Half of the composited drinking water samples are normally takenprior to treatment of the water. These are refe} red to as the rawwater samples. The remainder of the samples are normally taken aftertreatment and are referred to as the treated water samples. In 1990,no composite raw water sample was obtainable during December becauseof pump problems.

From 1977 (when drinking water samples were first collected) through1984, drinking water samples were also obtained from the BerwickWater Company at location 12F2 (12F3), -5.2 miles WSW of SSES. Thedrinking water supply for the Berwick Water Company is not, however,water from the Susquehanna River; it is actually well water.

Since there are no drinking water supplies on the Susquehanna Riverupstream of the SSES that would be appropriate to serve as a controllocation, the Danville drinking water samples may be compared tosurface water control samples.

V-14

Gross alpha activity has been monitored in drinking water since 1980Since 1980, alpha activity has been observed most years in a smallminority of these samples. In 1981, 1987, 1989, and 1990 nocomposite samples yielded any alpha activity above the lower limit ofdetection. Gross alpha activity was reported in one raw water grabsample collected in February. The yearly average gross alphaactivities during the preoperational and operational periods 1980-1981 and 1982-1989, respectively, are presented in the table below.

DRINKING WATER GROSS ALPHA ACTIVITIES Ci 1

,Period

~Ran ePean (median)

Prep er tio al1980-81

1.3

~0

1982-89 1990

1.2 — 10.03.7 (2.1) 'LO

Gross beta activity was reported above the lower limit of detectionin only 8 out of 23 composite drinking water samples in 1990. Themean of gross beta activity in drinking water for 1990 is compared tothe ranges and means of yearly average gross beta activities duringthe preoperational and operational periods 1977-1981 and 1982-1989respectively in the table below.

DRINKING WATE GROSS BETA ACTIVITIES Ci 1

Period Pr eo erational1977-81 1982-89 1990

Rancae~ea (median)

I

202 — 3022.7 (2.6)

2.4 — 5.43.5 (3.4) 2.6

It should be noted that the average drinking water gross betaactivity in 1990 is less than the mean gross beta activities ofsurface water control locations during the preoperational period ofthe SSES. Therefore, 'the gross beta activities in drinking watersamples for 1990 are not attributable to the operation of the SSES.Refer to Figure 15 which trends gross beta activities in drinkingwater samples from 1977 through 1990.

No iodine-131 was detected in drinking water samples for 1990. Thisis the same result that was obtained each year from 1985 through1990. Since 1980, iodine-131 has only been detected in drinkingwater four years out of ten years.

V-15

10

GROSS BETA ACTIVITYIN RIiNIGNG WATER

CI/L

PREOPERATIOLN'ALc

OPERATIONAL

UilIT2 CRITICALITY

0,1977

I

1979I

1981 1983 1985 1987 1989 1991

Tritium was positively detected in 9 out of 24 samples in 1990. 'Themean of tritium activity in drinking water for 1990 is compared tothe ranges and means of yearly average tritium activities during thepreoperational and operational per iods 1977-1981 and 1982-1989respectively in the table below.

DRINKING WATER TRITIUM ACTIVITIES Ci l

Period Prep erational1977-81

~t. i1982-89 1990

~ancae 101 — 194Mean (median) 132 (120)

83 - 220127 (113) 125

ALGAE

A total of 12 algae samples were collected from May through Octoberof 1990 at two locations on the Susquehanna River. Half of thesamples were collected at the indicator location AG4 below the SSESdischarge diffuser, and the other half of the samples were obtainedat the control location AG3 above the SSES river water intakestructure. The algae samples were analyzed by gamma spectrometry.The detailed results of the analyses of these samples can be found'nTable 8.

The naturally-occurring radionuclides beryllium-7, potassium-40,radium-226 and thorium-232, were positively detected in algae samplesin 1990. With the exception of beryllium-7, which is cosmogenic inorigin (produced by the interaction of cosmic radiation in thea'tmosphere), these radionuclides are terrestrial in origin (found inthe earth's crust).

Beryllium-7 was positively detected in 3 out of 6 indicator and 2 outof 6 control samples in 1990. The means of beryllium-7 activities inalgae for 1990 are compared to the ranges and means (medians) ofyearly average beryllium-7 activities at indicator and controllocations during the period 1984 through 1989 in the table below.

LG E BERYLLIUM-7 ACTI ITIES Ci dr

Location~Pe ~o

g~~ea (medi an)

4.1 — 20.78.2 (6.2) 8.0

4.3 — 18.98.1 (6.1) 5.6

Indicator Control1984-89 1990 1984-89 1990

Potassium-40 was positively detected in 4 of 6 indicator samples andin 3 out of 6 control algae samples in 1990. The means of potassium-40 activities'n algae for 1990 are compared to the ranges and means(medians) of yearly average potassium-40 activities at indicator andcontrol locations during the period 1984 through 1989 in the tablebelow.

LG 0 ASSIU - 0 AC VI IES Ci dr

~Locat on ~Indi cato ~Contre~eood 1984-89 1990 1984-89 . 1990

~Ran e 12.0 — 89.7~e (median) '9.1 (13.8)

10.6 - 80.844.3 27.2 (15.1) 111

Radium-226 was positively detected in 1 out of 6 indicator and 2 outof 6 control algae samples in 1990. The means (medians) of yearlyaverage radium-226 activities at indicator and control locationsduring the period 1985-1989 are given in the table below.

LG E DIUN»226 CTIVITIES C d

~toc tio Indicator ~Contre~Per od 1985-89 ~990 1985-89 1990

Rarge 3.2 — 7.1 3.1 — 6.3~e (median) 4.8 (4.4) 3. 1 4.3 (3.6) 5.3

Thorium-232 was positively detected at an activity level of 4.2pCi/gram (dry) in 1 out of 6 control algae samples in 1990 and in noindicator samples.

None of the activity of the naturally-occurring radionuclides isattributable to the SSES operation.

The fission-product radionuclides cesium-137 and iodine-131 werepositively detected in algae in 1990. Iodine-131 was detected in 1

out of 6 control samples and 1 out of 6 indicator samples in 1990.Iodine-131 has been positively detected in a portion (typically lessthan half) of both indicator and control samples each year from 1984through 1990. The iodine-131 activities in algae for 1990 arecompared to the ranges and means (medians) of yearly average iodine-131 activities at indicator and control locations during the period1984 through 1989 in the table below.

LocationPeriod

LG E ODI E- 31 AC IVI IES C'

Indicator Control1984-89 1990 1984-89 1990

~Ran e 0.55 - 1.32 0.70 — 1.10Mean (median) 0.94 (0.95) 8.4 0.97 (0.89) 9.9

As in past years, the presence of iodine-131 in algae does not appearto be from the SSES operation, but from medical sources upstream ofthe SSES. Iodine-131 has been found more times in control algaesamples each year than it has been found in indicator algae samplessince algae began to be monitored in 1984.

Cesium-137 was detected in 1 out of 6 control algae samples, and itwas found in 1 out of 6 indicator algae samples in 1990. The meansof cesium-137 activities in algae for 1990 are compared to the rangesand means (medians) of, yearly average cesium-137 activities at algaeindicator and control locations during the period 1984 through 1989in the table below.

ALGAE CESIU -137 CTIVI IES Ci d

~Loc tioPeriod

~diect(~1984-89 1990

~Co trol1984-89 1990

~Ran e 0.19 — 0.48 0.21 - 0.82~ea (median) 0.31 (0.30) 0.15 0.34 (0.25) 0.15

Cesium-137 in the environment comes from fallout resulting from pastatmospheric nuclear weapons tests. As algae data continues to beaccumulated, assuming that atmospheric nuclear testing is notresumed, a decline in cesium-137 activity should eventually beobserved. No trend in cesium-137 activities in algae since 1984 hasyet been apparent.

The activation-product radionuclide manganese-54 was seen in 2 out of6 indicator algae samples and 1 out of 6 control algae samples in1990. This is the first year that manganese-54 has been detected inan algae control sample. Hanganese-54 was observed in a controlsample from Hay at an activity level of 0. 13 pCi/gram (dry).

The mean of manganese-54 activity in algae for the indicator locationin 1990 is compared to the range and mean of yearly averagemanganese-54 activities for the period 1984-89 in the table below.

ALGAE NANGANESE-54 ACTIVITY Ci dr

Period

Ran<ac

~e (median)

1984-89*

0.5-2.00.9 (0.6)

1990

0.9

*No manganese-54 was reported in 1984 and 1989.

The manganese-54 in the indicator sample is attributable to theradioactive liquid discharges from the SSES. However, the manganese-54 activity at the control location (AG3) is difficult to explain interms of SSES liquid releases to Susquehanna River. The controllocation is 0.8 miles upstream from the SSES River water intakestructure. Hanganese-54 has been detected in airborne releases fromthe SSES in 1990, but not during the month of Hay when it wasobserved in the control algae sample. The closest month prior to Haywhen it was reported in airborne releases was February, 1990.

V-19

The activation-product radionuclide cobalt-60 was observed in 1 outof 6 indicator samples and no control samples in 1990. Cobalt-60 hasnot been detected in AG4 indicator samples since 1987 and has neverbeen reported in control algae samples. The mean of cobalt-60activity in algae for the indicator location in 1990,is compared tothe range and mean of yearly average cobalt-60 activities for theperiod 1984-1989 in the table below.

LGAE COBALT-60 ACTIVI Ci dr

~er od

Ran~~e (median)

E. FISH

984-89

0.5-1.10.8 (0.9)

1990

1.0

Four different species of fish were collected at three differentlocations during April, Hay, June, and November 1990. The speciesincluded smallmouth bass, largemouth bass, channel catfish, and whitesucker. The largemouth bass was obtained from Lake Took-a-While(LTAW) located on PPKL property on the opposite side of Route 11 fromthe station. LTAW is considered an indicator location even though itdoes not receive flow from the Susquehanna River below the SSES

cooling tower blowdown line to the river. The smallmouth bass,channel catfish and white sucker were all obtained from theSusquehanna River at a control location 30 miles NNE near Falls,Pennsylvania and at an indicator location between 0.9 and 1.4 milesESE of the site, at or below the discharge structure. The detailedresults of these analyses can be found in Table 10.

As in every fish sample taken since the Spring of 1984, when grossbeta analyses first began to be performed on fish flesh, all 9indicator samples and all 6 control samples showed gross betaactivity above the lower limit of detection (LLD).

The means of gross beta activities in fish for 1990 are compared tothe ranges and means (medians) of yearly average gross betaactivities at indicator and control locations during the period 1984-1989 in the table below.

ISH GROSS BETA ACTIVITIES Ci wet

LocationPeriod

Indicator1984-89 1990

Control1984-89 1990

Range 3.7 — 5.6~ea (median) 5.0 (5.2) 4.8

2.2 — 6.84.9 (5.3) 4.2

Although the indicator mean for 1990 is greater than the 1990 controlmean, it is less than both the indicator and control means for 1989.The gross beta activities in fish for 1990 are not attributable tothe SSES operation.

V-20

Gamma spectrometry of fish in 1990 did not positively detect anygamma-emitting radionuclide except for potassium-40. Naturally-occurring potassium-40 was positively detected in all indicator andcontrol samples.

The means of potassium-40 activities in fish for 1990 are compared tothe ranges and means of yearly average potassium-40 activities atindicator and control locations during the preoperational andoperational periods 1977-1981 and 1982-1989, respectively, in thetable below.

FISH POTASSIUM-40 ACTIVITIES Ci wet

LocationPeriod

~Indi cato Control~Pi ~t'1977-81 1982-89 1990 1977-81 ~982-89 1990

~Ran e 2.7 - 3.5 3.1 — 4.2 — 2.8 — 3.6 3.1 — 4.1Bean (median) 3.2 (3.2) 3.7 (3.7) 5.3 3.2 (3.4) 3.6 (3.7) 3.4

Note that the means of the potassium-40 activities for thepreoperational period and the operational period prior to 1990 areessentially identical. The indicator mean potassium-40 activity for1990 is outside the range of yearly average potassium-40 activitiesfor the prior operational years at the indicator locations andgreater than the mean potassium-40 activity at the control locationin 1990. However, the naturally-occuring potassium-40 is notattributable to the SSES operation.

By comparison to the potassium-40 activities, cesium-137 activitiesin any given year appear very small. Cesium-137 was not positivelydetected in any indicator or control samples in 1990.

The ranges and means of yearly average cesium-137 activities atindicator and control locations during the preoperational andoperational periods 1977-1981 and 1982-1989, respectively, arepresented in the table below.

FIS CESIUM-137 ACTIVITIES Ci wet

LocationPeriod

Indicator Control~P

~19 7~8 1982-89 1990 1977-81 1982-89 1990

Rancae .010 — .042 .009 — .020Mean (median) .021 (.016) .013 (.012) LLD

.012 — .016 .006 — .015

.013 (.012) .010 (.010) LLD

Note that the highest mean of cesium-137 activities in the tableabove is from the preoperational period at the indicator locations.

V-21

As in all other environmental media monitored, the source of thecesium-137 activity detected since 1977 has been attributed to theresidual fallout from previous atmospheric nuclear weapons tests.

F. SHORELINE AND FLOCCULATED SEDIMENT

Shoreline sediment was sampled in April and November 1990 at fourindicator locations and two control locations. The sediment wasanalyzed for gross alpha activity, gross beta activity, and theactivity of gamma-emitting radionuclides. The detailed results ofthese analyses can be found in Table 11.

Gross alpha activities in sediment have been determined every yearsince 1982. Gross alpha activity was positively detected in 6 out of6 indicator samples and 3 out of 3 control samples in 1990. Note.that analyses for gross alpha and beta activities were not performed.for one control and two indicator samples obtained in November.These samples were inadvertently discarded at the radioanalyticallaboratory prior to these analyses being performed.'he means ofgross alpha activities in sediment for 1990 are compared to theranges and means (medians) of yearly average gross alpha activitiesat indicator and control locations during the period 1982 through1989 in the table below.

SEDINENT GROSS ALPHA ACTIYITIES Ci dr

~oc tio ~die~to ~CootroPeriod 1982-89 1990 1982-89 1990

/~an e~can (median)

6.0 — 17.011.3 (12.2) 0.23

5.7 — 13.011.4 (11.8) 0.15

Note that the means of the gross alpha activity at the indicator andcontrol locations in 1990 are significantly below the respectiverange of the yearly average gross alpha activities at those locationsfor the prior period of the SSES operation. The low values in 1990are believed to result from the difference in methods of analysisbetween this and previous years. The method used in 1990 (by adifferent radioanalytical laboratory), unlike the previously usedprocedure, involves leaching and ashing the sediment. This processremoves any organic, volatile, and insoluble material in the sampleprior to counting. Consequently, no useful information is providedby comparing 1990 values with those of previous years except,perhaps, for an appreciation of the different results produced by thetwo methods.

Gross beta analyses have been performed on sediment every year since1984. Gross beta activity has been positively detected in allindicator and control sediment samples since 1984.

V-22

The means of gross beta activities in sediment for 1990 are comparedto the ranges and means (medians) of yearly average gross betaactivities at indicator and control locations during the period 1984through 1989 in the table below.

SEDIMENT GROSS BETA AC IVITIES Ci dr

LocationPeriod

Indicator1984-89 ~990

Control1984-89 1990

~Ran e 19.7 — 35.5~ea (median) P27.7 (27.6)

20.5 — 33.00.36 27.4 (27.8) 0.30

Similar to the observed 1990 gross alpha activities, the 1990 grossbeta activities, as suggested by the averages presented in the tableabove, were also considerably lower than those of previous years..Once again, the reason is the differences in the methods of analysis.

Gamma spectrometry in 1990 identified the following naturally-occur ring radionuclides in sediment at levels above their lowerlimits of detection: beryllium-7, potassium-40, thorium-232, andradium-226. With the exception of beryllium-7, which was reported in1 out of 8 indicator samples and 2 out of 4 control samples, theother three radionuclides were found in every indicator and controlsample in 1990.

The means of the activities of beryllium-7, potassium-40, and radium-226 in sediment for 1990 are compared to the corresponding ranges andmeans of the yearly average activities of these radionuclides atindicator and control locations during the preoperational andoperational periods 1978-1981 and 1982-1989, respectively, in thetables below.

SEDIMENT BERYLLIUM-7 ACTIVI IES Ci dr

LocationPeriod

Indicator

1978-81 1982-89 1990

Control~P

1978-81 1982-89 1990

Ra~cae 0.4 — 0.6 0.7 — 2.7Mean (median)0.9 (0.5) 1.4 (1.0) 0.4

0.3 - 0.4 0.4 - 1.70.4 (0.4) 0.8 (0.6) 0.3

SEDIMENT POTASSIUM-40 ACTIVITIES Ci dr

~tocatio Indicatordd ~P

1978-81 1982-89 1990

Ran<ac 8.6 — 10.4 7.6 — 13.2~

~

~ ~

~ ~Mean (median)9.3 (9.1) 10.4 (10.9) 7.4

Control

1978-81 1982-89 1990

7.5 — 11.0 8.7 - 12.59.4 (9.5) 10.6 (10.6) 6.2

V-23

~LocatioPeriod

SEDIMENT RADIU -226 ACTIVITIES

~id'cater ControlPPPti I 01 I I ~PdIi IIe tt1978-81 1982-89 1990 1978-81 1982-89 1990

~Ran e 0. 5 — 0. 7Hean (median) 0.6 (0.7)

0.6 — 1.9 — 0.6, - 1.91.4 (1.7) 0.5 0.7 (0.7)

0.7 - 2.11.5 (1.6) 0.4

Thorium-232 has not been reported in sediment since 1983. From 1984through 1989, thorium-228 was reported instead. Thorium-228 is partof the same naturally-occurring decay chain as thorium-232. Themeans of thorium-232 activities in sediment for 1990-are compared tothe ranges and means of yearly average thorium-232 activities atindicator and control locations during the preoperational andoperational periods 1978-1981 and 1982-1983, respectively, in thetable below.

SED IME THORIUM-232 ACTIVITIES Ci d

~Locatio IndicatorP I 0 ~Pi I ~dti

~978-8 1982-83 1990

Control~P

1978-81 1982-83 1990

ganqeHean

0.7 — 0.9 0.8 0.7 — 0.90.8 0.8 0.5 0.8 0.8 0.5

Cesium-137 was detected in 7 out of 8 indicator samples and allcontrol samples. The means of cesium-137 activities in sediment for1990 are compared to the ranges and means (medians) of yearly averagecesium-137 activities at indicator and control locations during thepreoperational and operational periods 1978-1981 and 1982-1989,respectively, in the table below.

SEDIME CESIU -137 C IVI IES Ci dr

LocationPeriod

~id 'catott ~ddt

~978-81 1982-89 1990

Control~0

1978-81 1982-89 1990

~Ran e 0.08 - 0.15 0.07 - 0.17 — 0.08 - 0.21 0.09 - 0.21Hean (median) 0.10 (0.09) 0.12 (0.12) 0.04 0.13 (O.ll) 0.14 (0.13) 0.06

The 1990 indicator and control activities are below the ranges of themeans for both the preoperational and operational periods at thecontrol locations.

The cesium-137 activities in sediment are the result of fallout fromprevious atmospheric nuclear weapons tests. The cesium-137 activityin sediment is not attributed to the SSES operations.

V-24

Hanganese-54 was detected in one control and one indicator sample in1990. The means of manganese-54 activities in sediment for 1990 arecompared to the ranges and means of yearly average manganese-54activities at indicator and control locations during the operationalperiod 1985-1989,in the table below.

SEDINENT NANGANESE-54 ACTIVITIES Ci dr

LocationPer od

Indicator1985-1989 1990

Control1985-1989 1990

Rancae~Mea

0.03 — 0.3 0.020.12 '0.02 0.02 .02

During the preoperational period of the SSES, manganese-54 wasdetected only once, at an activity level of 0.02 pCi/g (dry), in1978. It has been detected at indicator locations during theoperational period in five different years, including 1990.Manganese-54 activity has only been detected at control locationsonce in 1989 and once in 1990. Because manganese-54 has beenreported at low levels in both the waterborne and airborne effluentsfrom the SSES in 1990, its presence in sediment in 1990 may beattributed to SSES operation.

Cobalt-60 was reported in one indicator sediment sample in 1990 at anactivity level of 0.010 pCi/g (dry). The only previous year in whichcobalt-60 has been reported in sediment was 1985 when it was alsoreported in one indicator sample. Cobalt-60 in indicator sedimentsamples is attributable to SSES operation..

Flocculated sediment (floe) samples have been collected on a trialbasis since 1986 at one control location and one indicator locationon the Susquehanna River. Floe is the top, loose layer of sedimentin the river that is easily moved and shifted by the water. It isthought that perhaps material carried by the water might betransferred most readily to this floe. The data collected to date donot point to the appearance of radionuclides in the floe that haven'also been identified in the underlying sediment.

G. GROUND MATER

Ground water was sampled monthly at seven locations in 1990,including one control location. A total of 67 indicator samples and12 control samples were collected. The detailed results of theanalyses of these samples can be observed in Table 12.

Gross alpha activity has been analyzed in ground water since 1980.It is usually positively detected in a small number of samplesannually. In 1990, gross alpha activity was positively detected in12 out of 67 indicator samples and 2 out of 12 control samples. Theranges and means (medians) of yearly average gross alpha activitiesat indicator and control locations during the preoperational andoperational periods 1980-1981 and 1982-1989 respectively arepresented in the table below.

V-25

OU D G OSS L HA CTIVITIES Ci

~Loc tIoperiod

~Ind cator

~980-81 3982-89 Iggp ~gyp 8I

Control

1982-89 1990

RancaeMean" (median) 2.7 (2.1)

1.5 - 4.52.7,(2.1) 1.3

LLDLLD

1.2 - 2.71.8 (1.4) 1.4

Gross beta activity has been analyzed in ground water since 1977. Itis positively detected in a majority of samples every year. In 1990,gross beta activity was positively detected in 23 out of 67 indicatorsamples and it was found above the LLD in 6 out of 12 controlsamples.

The means of gross beta activities in ground water for 1990 arecompared to the ranges and means (medians) of yearly average grossbeta activities at indicator and control locations during thepreoperational and operational periods 1980-1981 and 1982-1989,respectively, in the table below.

Location~Peri d

G OUND M TE G OSS BET AC I ITIES Ci 1

~Id teeter~ti ~o t i ~P

~98(~ 199!8-8'} ~90 ~98 -8

/~an e 3.2 - 3.4 2.1 - 3.7 — 1.9 — 3.0~Me (median) 3.3 (3.3) 2.6 (2.3) 2.3 2.5 (2.5)

Controlti

198P~ 99

1.8 — 2.52.2 (2.2) 2.1

It is interesting to note that the means of gross beta activities atboth indicator and control locations for the operational period arelower than their corresponding means during the preoperationalperiod. Therefore, the gross beta activity in ground water is notattributable to the SSES

operation.'ritium

activity has been positively detected in some ground watersamples every year from 1972 through 1990. In 1990, tritium waspositively detected in 24 out of 67 indicator samples and in 5 out of12 control samples.

The means of tritium activities in ground water for 1990 are comparedto the ranges and means (medians) of yearly average tritiumactivities at indicator and control locations during thepreoperational and operational periods 1980-1981 and 1982-1989,respectively, in the table below.

V-26

GROUND WATER TRITIUM ACTIVITIES Ci 1

LocationPeriod

Ran<ac 93 — 109~~ar1 (median) 101 (101)

98 — 180—122 (111) 143

Indicator~P'~ti1980-81 1982-89 1990

Control~Pit1980-81 1982-89 1990

117 - 119 105 — 260118 (118) 145 (117) 162

Note that for both preoperational and operational periods the meansof tritium activities at the control locations exceed those at theindicator locations, although the difference does not appear to besignificant.

Gamma spectrometry of ground water has yielded few positivelydetected radionuclides since it was begun in 1979. The naturallyoccurring radionuclides potassium-40 and thorium-228 have beendetected occasionally in ground water samples. Potassium-40 wasfound in 1979, 1981, and 1985. Thorium-228 was observed in 1985 and1986. No naturally-occurring radionuclides were positively detectedin ground water in 1990.

Cesium-137 was not positively detected in any indicator or controlsamples in 1990. The ranges and means (mediums) of yearly averagetritium activities at indicator and control locations during theoperational period 1982-1989 in the table below.

G OUND WA E CESIUM-137 activit es Ci 1

LocationPeriod Prep erational

1980-81

~Ran e LLDMean (median) LLD

3.0 - 4.63.8 (3.8) LLD

Indicator

~Pter

1982-89 1990reo erational

1980-81

LLDLLD

Control~ll t.l

1982-89 1990

2.42.9(2.9) LLD

Cesium-137 activity is attributed to the fallout from previousatmospheric nuclear weapons tests.

Manganese-54 was positively detected in one indicator sample and twocontrol samples in 1990 at low levels. This is the first year thatmanganese-54 has been reported in ground water samples.Interestingly, the average manganese-54 activity level, 6 pCi/1, atthe control location is greater than the 3.8 pCi/1 reported in theone indicator location sample. It is highly unlikely thatcontamination of ground water with manganese-54 at the SSES sitewould manifest itself at the Berwick Water Company location,especially since it was not observed at four indicator locations inmuch closer proximity to the SSES. It would be expected thathydrological conditions at these locations would be much morefavorable to the spread of any such contamination. Anotheralternative, the airborne pathway is similarly difficult to imagine.The manganese-54 may be falsely positive.

V-,27

H. AIR PARTICULATE

The results of a total of 520 routine air samples collected at 12locations during 1990 are included in this report. Four hundredsixteen samples were collected at 10 indicator locations and 104samples were collected at 2 control locations. The detailed resultsof these analyses. can be found in Tables 13 and 14.

Air particulate filters were collected weekly and analyzedindividually for gross beta activity. quarterly, the particulatefilters were composited and analyzed for gross alpha activity and theactivity of specific radionuclides identified by gamma spectrometry.

Gross beta activity was positively detected in all 520 weeklysamples, which includes both indicators and controls. The mean ofgross beta activities in air samples in 1990 is compared to the rangeand mean (median) of yearly average gross beta activities atindicator and control locations during the preoperational andoperational periods 1978-1981 and 1982-1989, respectively, in thetable below.

IR ARTICULATE GROSS BETA ACTIVITIES E-3 Ci

m'ocation

PeriodIndicator

t1978-81 1982-89 1990

Controlt

1978-81 1982-89 1990

Qan~e 24 — 97 13 — 29~can (median) 61 (62) 18 (17) 17

24 - 10262 (61)

12 - 2817 (16)

The yearly average of 97 E-3 pCi/m'as obtained twice for theindicator locations in the preoperational years 1978 and 1981. Since1981, the highest gross beta activity occurred in 1986 due to theChernobyl incident. Prior to this, the unusually high gross betaactivities may generally be attributed to fallout from atmosphericnuclear weapons tests. Refer to Figure 16 which trends gross betaactivity in air particulates separately for indicators and controlsfrom 1974 through 1990.

Gross alpha activity was positively detected in all but one quarterlyindicator analyses and all control analyses in 1990. The range andmean of gross alpha activities at both indicator and controllocations in 1990 is compared to the range and mean (median) ofyearly average gross alpha activities at indicator and controllocations during the preoperational and operational periods 1980-1981and 1982-1989, respectively, in the table below.

I PAR ICULATE GROSS ALPHA ACTIVITIES E-3 Ci

~Locat'onPeriod

~Ind'cater2cmmttLt

t~t'980-811982-89 1990

Control~t ~tti1980-1981 1982-89 1990

~Ran e~ea (median)

2.8-3.13.0(3.0)

2.4-6.84.0(3.7) 1.4

V-28

2.2-3.52.9(2.9)

2.5-9.04.1(3.3) 1.6

GROSS BETA AFIGURE j.

IN PARTI S

500

450

400

E:-Os Pa/M3


CHINESE YEAPON TEST,A —6/17/74B —9/26/76C —11 17 7.6

E —S/14/7e-7 —10 15 e0

A350 - l

300

250

200

150

C 'NIT2 CRITICALITY

100

0

. 1974I I I ~ I, I I I I I I I I I ' I

'976 1978 1980.. 1982 . 1984 1986 1988 1990-

1ndicator

Control

The yearly average gross alpha activities in air samples, especiallyindicator air samples, are lower than those reported during thepreoperational years 1980 and 1981. Refer to Figure 17 trendinggross alpha activity in air particulates separately for indicatorsand controls from 1980 through 1990.

Gamma-emitting radionuclides are monitored in quarterly compositesamples. Gamma spectrometry positively detected the naturally-occurring radionuclides beryllium-7 and potassium-40 in air samplesin 1990. Beryllium-7 was found in all quarterly analyses of controlsamples and in 30 out of 34 indicator samples in 1990.

The mean of activities for indicator and control locations in 1990 iscompared to the range and mean (median) of beryllium-7 yearly averageactivities at indicator and control locations during thepreoperational and operational periods 1978-1981 and 1982-1989,respectively, in the table below.

BERYLLIUM-7 ACTIVITIES E-3 Ci

m'ocation

PeriodIndicator~Pti 1 ~oft

1978-81 1982-89 1990

Control~Pt. i1978-1981 1982-89 1990

Rancae 69 — 81 62 — 76 59 - 85 53 - 68

~ ~

Mean (median) 76 (76) 66 (65) 104 72 (73) 61 (63) 114

The annual average beryllium-7 activity levels for 1990 are elevatedprimarily due to the unusually high levels reported during the firsttwo calendar quarters. Results during the last two quarters of theyear were within the expected ranges.

Potassium-40 was positively detected in only 8 out of 34 indicatoranalyses and 3 out of 8 control analyses in 1990. The mean ofpotassium-40 activities for indicator and control locations in 1990is compared to the range and mean (median) of potassium-40 yearlyaverage activities at indicator and control locations from 1983through 1989 in the table below.

POTASSIUN-40 ACTIVITIES E-3 Ci

m'ocation

PeriodIndicator

1983-89 1990 1983-89Control

1990

~Ran eMean (median)

LLD — 12 - LLD - 5.86.0(5.0) 800 4.6 (4.9) 1043

These values are certainly well above the means for previous years.The elevated averages for 1990 are believed to be the result oferrors in analyses. In any case, potassium-40 in the air is notattributable to SSES operation.

Nanganese-54 (Nn-54) was the only anthropogenic radionuclidepositively detected in 1990. )n-54 was observed at the very lowlevel of 0.0009 t 0.0006 pCi/m in the fourth quarter composite of

V-30

y GROSS ALPHA ACTIVITYIl IR PARTICULATESF—03 PCI/M3

20

PRE-OPEBATlONAL OPERATIONAL

10 UNIT 2 CRITICALITY

0 I I I I I I I I I I

1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991

indicator

Control

weekly samples from location 5S4. This manganese-54 may beattributed to the operation of the SSES. Manganese-54 was lastreported in two indicator air samples in 1981, prior to SSESoperation, a$ activity levels of .0016 t .0008 pCi/m and 0.0021 t0.0014 pCI/m .

AIR IODINE

Routine iodine-131 analyses by gamma spectrometry of 520 charcoalcartridges did not positively detect iodine-131 in any air samples in1990. Iodine-131 was detected infrequently from 1976, when it wasfirst monitored, through 1989. Since operation of SSES began in1982, iodine-131 has only been positively detected in air sampling in1986 due to the Chernobyl incident.

PREC I P ITATION

Precipitation samples from ten indicator locations and two controllocations were analyzed quarterly in 1990 for gross alpha activity,gross beta activity, tritium activity, and the activity of gamma-emitting radionuclides identified by gamma spectrometry. Thedetailed results of these analyses can be found in Table 15.

Gross alpha activity was detected in only 1 out of 33 indicatorsamples and in no control samples in 1990. The gross alpha activityin precipitation for 1990 is compared to the corresponding ranges andmeans (medians) from 1984 through 1989 in the table below.

PRECIPITATION G OSS LPHA ACTIVITY Ci 1

LocationPeriod


Control1984-89 1990

~Ran eMean (median)

0.6-1.3 0.6 — 1.10.9(0.8) 1.9 0.9 (1.0) LLD

The data above do not indicate any gross alpha activity attributableto the operation of the SSES.

Gross beta activity was detected in 24 out of 33 indicatorprecipitation samples and in 5 out of 7 control precipitation samplesin 1990. The means of gross beta activities in precipitation for1990 at both indicator and control locations are compared to thecorresponding ranges and means (medians) from 1984 through 1989 inthe table below.

ECI IT TION G OSS BETA CTIVI Ci

~LocatioPeriod

~Ind'c to~984-89 1990

Control~984-89 1990

~Ran eMean (median)

2-5-4.33.5(3.5) 4.8

3.4-5.84.1(4.1) 3.9

V-32

The data in the table above do not indicate any gross beta activityattributable to the operation of the SSES. Although the indicatormean activity is higher than the control mean activity for 1990, itis still within the range of previous annual mean activities forcontrol locations.

Tritium activity was positively detected in 11 out of 32 indicatorsamples, and it was observed in 4 out of 7 control samples in 1990.The means of tritium activities in precipitation for 1990 at bothindicator and control, locations are compared to the correspondingranges and means (medians) during the preoperational and operationalperiods 1980-1981 and 1983-1989 respectively, in the table below.

RECIPI ATION ITIU C I I C

~tocatioPeriod

~indicate~PP t~t1980-81 1983-89 1990

Controlpppti 1 e ti1980-1981 1983-89 1990

~Ran e~ea (median)

119-213 94-200 99-135 92-530166(166) 136(128) 323 117(117) 196(137) 362

The data in the table above do not indicate any tritium activityattributable to the operation of the SSES.

Gamma spectrometry was first performed on precipitation samples in1980. The only gamma-emitting radionuclides positively detected inprecipitation in 1990 were naturally-occurring potassium-40 andradium-226. These radionuclides were observed in one sample.

Cesium-137 was not detected in any indicator precipitation samples-orcontrol samples in 1990. Cesium-137 has been positively detected inprecipitation samples from indicator and/or control locationspreviously'in 1981, 1985, 1986, 1987 1988, and 1989. The cesium-137activity during the years it has been detected is attributable toprevious atmospheric nuclear weapons tests.

HILK

Hilk was sampled at a total of nine indicator locations and onecontrol location in 1990. The frequency of sampling was monthly,except for six locations where sampling was semi-monthly from Aprilthrough October. In 1990, a total of 131 indicator milk samples and19 control milk samples from cows were routinely analyzed for iodine-131 activity, and the activity of gamma-emitting radionuclides bygamma spectrometry. The detailed results of these analyses can befound in Table 16.

In January and February 1990, gross-beta-minus-potassium-40 analyseswere also performed on milk samples. Naturally-occurring potassium-40 normally accounts for the large majority of the activity of betaemitting radionuclides in milk. Removing this activity beforeperforming a gross beta analysis can provide a more sensitive andaccurate method for measuring the activities of other beta emittersthat may be present, such as strontium-90.

V-33

If any milk samples had shown gross beta minus potassium-40 activityat 15 pCi/liter or higher, those samples also would have beenanalyzed for strontium-89 and strontium-90 activity. From Marchthrough December 1990, all samples were routinely analyzed forstrontium-89/90 activity and no samples were analyzed for gross-beta-minus-potassium-40 activity. Prior to 1990, strontium-89/90 analyseshad not been routinely performed on milk samples since the period1978 through 1981.

Gross beta minus potassium-40 was positively detected in 16 out of 16indicator samples and in 2 out of 2 control samples. The mean ofgross beta minus potassium-40 activities in milk for 1990 is comparedto the range and mean (median) of yearly average gross beta minuspotassium-40 activities at indicator and control locations during theoperational period 1985-89 in the table below.

MILK GROSS B A INUS PO ASSIUM-40 ACTIVITIES Ci l

LocationPeriod


Control1985-89 1990

~Ran eMean (median)

7.1-7.8 7.6-10.07.4(7.3) 6.1 9.3(9.7) 10.7

Strontium-89/90 analyses were done on 115 indicator samples and 17control samples in 1990. Strontium-89 was reported in 14 out 115indicator samples and 1 out of 17 control samples. Strontium-89 hasnot been reported in milk samples since 1981.

The means of strontium-89 activities in milk for 1990 are compared tothe ranges and means (medians) of yearly average strontium-89activities at indicator and control locations during thepreoperational and operational periods 1976-1981 and 1982-1989,respectively, in the table below.

ILK STRONTIUM-89 ACTIVITIES Ci

~LocatioPeriod

~idicatorPpptl1976-81 1982-89 1990

ControlP

1976-1981 1982-89 1990

~Ran e 2.4-33 LLD 2.8-7.5 LLDPean (median) 9.7 (3.6) LLD 2.2 4.5 (3.2) LLD 2.3

Strontium-89 has a relatively short half-life (- 50 days) and wouldnot be expected to be detected in the environment in 1990 as a resultof fallout from atmospheric nuclear weapons testing in 1980 orbefore, unlike other fission products such as strontium-90 andcesium-137. Interestingly, strontium-89 was not detected followingChernobyl, even when elevated levels of such radionuclides as iodine-131 were observed. Typically, the presence of strontium-89 above thelower limit of detection would suggest the SSES as the origin.However, problems of the radioanalytical laboratory used for theseanalyses with their strontium procedure in 1990 raise some doubtsabout the validity of these positive results. Note that the average

V-34

strontium-89 activity level for the indicator locations isessentially the same as the activity level reported once for thecontrol location.

Strontium-90 was reported in 69 out of 115 indicator samples and 14out of 17 control samples. The mean of strontium-90 activities inmilk for 1990 are compared to the ranges and means (medians) ofyearly average strontium-90 activities at indicator and controllocations during the preoperational and operational periods 1978-1981and 1986-1989 respectively, in the table below.

ILK S RONTIUM-90 AC IVI IES Ci 1

~LocatioPeriod

Ittd i~at ~Cntro~p1 e i 1 p~19 8-8 ~98 -89 ~190 ~19 8-81 1982-89 ~990

~Ran e 4.3-5.3 5.2-6.8 1.7-7.5 5.7-6.9~Hea (median) 4.9(4.5) 5.9(5.7) 3.3 5.0(5.4) 6.3(6.3) 3.5

The 1990 indicator mean for strontium-90 a'ctivity is below the rangeof yearly average activities reported for the indicator locationsduring the preoperational period and also below the 1990 average forthe control location. The source of the strontium-90 before SSESoperation and since criticality appears to be the Chinese atmosphericnuclear weapons tests, referred to in previous REHP annual reports,that took place in 1972, 1974, 1976, 1977, 1978, and 1980.

Iodine-131 has been chemically separated in the milk samples andcounted routinely since 1977. (Refer to Figure 18 trending iodine-131 activity in milk separately for indicators and controls from 1977through 1988.) Typically, iodine-131 is not positively detected inany milk samples during a monitored year. The 1990 monitoring yearwas no exception; no iodine-131 above the lower limit of detectionwas observed in either indicator or control samples. Thepreoperational years 1976, 1978, and 1980 were exceptional years inthe sense that activity was positively detected due to fallout.Iodine-131 activity was also detected in milk samples in 1986 in thevicinity of SSES as a result of the Chernobyl incident.

Gamma spectrometry of milk samples in 1990 positively detectednaturally-occurring potassium-40 in all but two indicator samples.The mean of potassium-40 activities in milk for 1990 is compared tothe range and mean (median) of yearly average potassium-40 activities,at indicator and control locations during the preoperational andoperational periods 1978-1981 and 1985-1989 respectively, in thetable below.

V-35

IODIIUE—131 ACTIV@'NMILK

120pci/uzR


100CHINESE lYEAPON TZ9/1V VV

80

60

20 CHINESE WEAPON TZ3/14 78

CHINESE W10 15 80

APON TE

UNIT 2 CRITICALITY

CHERNOBYL4/26 86

1977 1979 1981 1983 1985 1987 1989 1991

LocationPeriod

MILK POTASSIUM-40 ACTIVITIES Ci 1

Indicator Control.pppti i n i 1 ~p~ i i1978-81 1985-89 1990 1978-81 1985-89 1990

~Ran e 1222-1500 1241-1350 — 1273-1500 1273-1356~ea (median)1353(1346) 1297(1258) 1422 1390(1393) 1326(1320) 1472

Cesium-137 was detected in 1990 in only 6 out of 131 indicatorsamples and was not reported for any control samples in 1990. Themeans of cesium-137 activity for indicator and control in milk in1990 are compared to the ranges and means (medians) of yearly average

, cesium-137 activity at indicator and control locations during thepreoperational and operational periods 1978-1981 and 1982-1989respectively in the table below.

MILK CESIUM-137 ACTIVITIES Ci l

ocat'onPeriod

Indicator~pti 1 n ti1978-81 1982-89 1990

ControlPp'pl 1

~Otal

1978-81 1982-89 1990

~Ran e 2.3-5.2 1.6-9.6 3.3-4.9 1.9-7.4Mean (median) 3.4(3.0) 4.7(4.6) 4. 1 3.9(3.8) 4.3(4.2) LLD

~

~

~

~

~

~

~

~ ~

~ ~

~ ~

~

~

~

Cesium-137 in milk is the result of the fallout from previousyears'tmosphericnuclear weapons tests and Chernobyl fallout. The only

years during the Radiological Environmental Monitoring Program thatcesium-137 was not positively detected in milk were in 1973 and 1984.Cesium-137 remains in the environment following fallout for arelatively long time because of its 30 year half-life.Zinc-65 was reported in one milk sample at an activity level of 8.5 +6.0'Ci/1 in 1990. This is the first time that it has ever beendetected in any milk samples. This zinc-65 may be attributable tothe SSES operation. Its detection is evidence of the sensitivity ofthe SSES REMP.

Cesium-134 is the only other anthropogenic radionuclide that has beendetected by gamma spectrometry in milk samples. Cesium-134 wasdetected once in June 1986 following the Chernobyl incident.

J. SOIL (TOP AND BOTTOM) AND VEGETATION

Soil (top and bottom) and vegetation, usually grass, were sampledonce at each of eight REMP indicator locations and two REAP controllocations during 1990. The locations for sampling soil andvegetation are the same as those for sampling air. The soil andvegetation samples were. analyzed by gamma spectrometry. The detailedresults of these analyses can be found in Tables 16 and 17.

V-37

Sixteen indicator soil samples and four control soil samples werecollected in 1990. Half of the soil samples were "top" samples takfrom the top two inches of soil The other half of the soil sampleswere gathered from a depth of two to six inches and are called"bottom" samples.

Naturally-occurring potassium-40, radium-226, and thorium-232 werepositively detected in all indicator and control soil samples in1990. The means of the activities of potassium-40 and radium-226 insoil for 1990 are compared to the corresponding ranges and means(medians) of the yearly average activities of these radionuclides atindicator and control locations during the preoperational andoperational periods 1979 & 1981 and 1982-1989 respectively, in thetables below.

LocationPeriod

SOIL POTASSIUM-40 ACTIVITIES Ci dr

Indicator, ControlpPPti 1 e i 1 ~~Petii i1 I~li 1

1979&81 1984-89 1990 1979&81 1984-89 1990

~Ran e 9.2 - 9.7 9.4 - 12.4~e (median) 9.5 (9.5) 10.7 (10.6) 14.3

9.1 - 11.0 7.4 — 1I.G10.1 (10.1) 10.2 (10.8) 14.1

SOIL DIUM-226 AC IVITIES C

~oc ~ti~Pe iod

IrrId'~at ~Co tro~G i ~P t i 1 ~0

1979&81 1984-89 1990 1979&81 1984-89 1990

Rancae 0. 8 — 1. 3 1. 5 — 2. 5~Pea (median) 1.1 (1.1) 1,9 (1.8) 0.8

0.8 — 1.2 1.7 — 2.01.0 (1.0) 1.8 (1.8) 1.0

Thorium-232 has not been reported in soil since the preoperationalyears 1979 and 1981. from 1984 through 1989, thorium-228, anothermember of the naturally-occurring decay chain of thorium-232, was,reported. The average thorium-232 activity levels at indicator andcontrol locations for the 1979 and 1981 period were 1.1 and 1.0 pCi/g(dry), respectively. The thorium-232 average activity levels forindicator and control locations in 1990 were 1.0 and 1.2 pCi/g (dry),respectively.

Cesium-137 activity has been identified in all indicator and controlsoil samples in 1990 except for a bottom sample from indicatorlocation 1D4. The means of cesium-137 activities in soil for 1990are compared to the ranges and means (medians) of yearly averagecesium-137 activities at indicator,and control locations duringpreoperational and operational periods 1979 &. 1981 and 1982-1989respectively, in the table below.

V-38

SOIL CESIUM-137 ACTIVITIES Ci dr

Location~

~

PeriodIndicator~PU 1 ~a

1979&81 I 1982-89 1990

Control~P

1979&81 1982-89 1990

~Ren e 0.5 — 0.7 0.3 - 0.5 — 0.2 - 1.2 0.2 — 1.2Mean (median) 0.6 (0.6) 0.4 (0.4) 0.3 0.7 (0.7) 0.6 (0.6) 0.3

Due to the relatively small activities of cesium-137 in soil and therelatively large variability associated with cesium-137 activitiesand their means, it is difficult to attempt to draw any conclusionsabout possible changes of the activities with time or about possibledifferences between indicator and control locations.

The cesium-137 activity in soil is the result of fallout fromprevious atmospheric nuclear weapons tests. No other anthropogenicradionuclides were identified in soil in 1990.

Soil samples were also obtained in 1990 for the purpose of monitoringthe site of disposal of SSES sewage sludge. This site is the Moweryfarm in Lycoming County, Pennsylvania.

Since the fall of 1987, the SSES sewage sludge has been disposed ofthere to permit its utilization for agricultural purposes.Honitoring on an annual basis is expected to continue indefinitely toverify that there is no increase in the presence of radionuclides atthe site or in the levels of radionuclides already found to exist atthat location. The results of the 1990 monitoring in three areas atthe Howery farm may be found in Table 16 identified as Areas 1, 2and 3.

The only gamma-emitting radionuclides positively detected in samplesfrom the Mowery farm in 1990 were potassium-40, thorium-232, radium-226, cesium-137 and manganese-54. The -activity levels of the gamma-emitting radionuclides identified in the Howery farm soil samples in1990 were at essentially the same magnitudes as those reported insoil samples from the vicinity of the SSES.

The activity level of manganese-54, 0.02 k 0.01 pCi/g(dry), reportedin a bottom soil sample from area 3 at the Howery farm in 1990, maybe compared with the level of manganese-54, 0.01 + 0.02 pCi/g (dry)reported in a topsoil sample from area 2 at the Howery farm in 1989.As noted in last year's report, manganese-54 has only been reportedin two soil samples from the vicinity of the SSES — one sample in1987 and another sample in 1988. In two of the three years, 19881989, and 1990, that soil samples have been collected from the Howeryfarm, manganese-54 has been reported in samples from the farm.

During the preoperational years 1974, 1975, 1977, and 1981,manganese-54 was reported in air samples from the vicinity of theSSES, but it was not reported in any preoperational soil sampleswhich were obtained only in the years 1979 and 1981. Manganese-54has not been detected in the quarterly composites of anyenvironmental air samples since SSES has been operational, although

V-39

it has been identified in both airborne and waterborne effluents fromthe SSES. Manganese-54 also has not been reported in any pre-disposal samples of sewage sludge from the SSES. The relativelyshort 312-day half-life of manganese-54 and its lack of detection inpreoperational soil samples suggest, however, that it might be theresult of SSES operation. Nevertheless, its detection is infrequentand at very low levels.

Naturally-occurring potassium-40 was positively detected in allvegetation indicator and control samples in 1990. Naturally-occurring beryllium-7 was detected in all but one vegetation sample.The means of the activities of beryllium-7 and potassium-40 invegetation for 1990 are compared to the corresponding ranges andmeans (medians) of the yearly average activities of theseradionuclides at indicator and control locations during the period1986-1989 in the tables below.

VEGETATION BERYLLIUM-7 ACTIVITIES Ci wet

~toc tioPeriod

~indic tor1986-89 1990

~Contre1986-89 1990

Ran<as 0.6 - 2.6Mean (median) 1.2 (0.8) 1.3

0.6 - 2.21.4 (1.4) 1.3

VEG A IO PO ASSIUM-40 CTIVI IES Ci wet

~toc tioPeriod

/eddic tor1986-89 1990 1986-89

Control1990

~Ran e 6.2 — 6.3~Hea (median) 5.9 (6.2)

4.9 - 7.29.6 5.7 (5.4). 16.0

Note that the unusually large indicator and control potassium-.40annual averages for 1990 are believed to be due to analysis of thevegetation samples by a different laboratory than was used for sampleanalysis in the 1986-1989 period.

Cesium-137 was not detected in any indicator or control vegetationsamples in 1990. The ranges and means (medians) of yearly averagecesium-137 activities at indicator and control locations during theperiod 1986-89 are presented in the table below.

VE 0 CESIU -137 C IV IES Ci wet

~Loc tiPeriod

~ind'cato~1986- ~990

Control1986-89 1990

~Ran e .01 — .06Mean (median) .03 (.02) LLD

J

The cesium-137 in the table above isprevious atmospheric nuclear weapons

.01 — .04

.02 (.02) LLD

attributable to fallout fromtests.

V-40

K.

No other gamma-emitting radionuclides were positively detected invegetation in 1990, except for the naturally-occurring radium-226which was reported in less than half of the samples.

FOOD PRODUCTS

Ninety-four fruit and vegetable samples and 10 game/poultry/eggsamples were analyzed by gamma spectrometry during 1990. Twenty-sixtypes of fruits and vegetables were sampled in 1990 from 16 differentlocations and 11 different sectors.

Four types of game animals were sampled in 1990. In addition,.samples were obtained of duck, chicken and eggs. Together 8locations in 8 different sectors were sampled.

RU AND VEGETAB S

Sample collection began in June and ended in November. Collectiontook place at one control location and 16 indicator locations. Theonly gamma-emitting radionuclides positively detected in 1990 werenaturally-occurring potassium-40, radium-226, and thorium-232. Thefallout radionuclide cesium-137 was not reported in 1990.

Potassium-40 was positively detected in 70 out of 82 indicatorsamples and ll out of 12 control samples in 1990. The means of theactivities of potassium-40 in fruits and vegetables for 1990 arecompared to the ranges and means (medians) of the yearly averageactivities of those radionuclides at indicator and control locationsduring the preoperational and operational periods 1980-1981 and 1982-1989, respectively, in the table below.

FRUITS VEGETABLES POTASSIUN-40 ACTIVITIES Ci wet

LocationPeriod

Indicator ~Co troPppti 1 ~ll i 1 ~P t. i1980-81 1982-89 1990 1980-81 1982-89 1990

3.0-3.13.1(3.1)

Rancae 2.5-3.0Mean (median) 2.8(2.8)

2.2-2.82.5(2.4) 14.9

GA OUL A D GG

2.0-4.23.2(3.4) 9.5

Potassium-40 levels'in the samples routinely vary considerably over arange of more than an order 'of magnitude. Although a wide range ofpotassium-40 levels is typically observed every year, this year'range was greater than usual due to some unusually high levelsreported. This year's results exceed the maximum levels reported forall previous years by factors greater than two. This is believed tobe an artifact of the laboratory performing the analysis.

Woodchuck, rabbit, squirrel, and deer were sampled between August andOctober and analyzed for the activities of gamma-emittingradionuclides in 1990. Naturally-occurring potassium-40 waspositively detected in all but one game sample. The falloutradionuclide cesium-137 was not reported in any game samples in 1990.

In only one other year (1977), since the REAP began in 1972, hascesium-137 not been detected. in game. No other gamma-emittingradionuclides were reported in game samples in 1990.

The mean of naturally-occurring potassium-40 activities in game for1990 is compared to the ranges and means (medians) of the yearlyaverage activities of potassium-40 in samples from the preoperationaland operational periods 1972-1981 and 1982-1989, respectively, in thetable below.

GA E PO SSIUM-40 ACTIVI IES Ci wet

~eiod eo e tional197 -8

~ti~98 -89 1990

Ramae 1.8 — 4.8 2\7 3e7~e (median) 2.8 (2.5) 3.0 (2.9) 11.9

As with the potassium-40 levels reported for fruits and vegetables inthe previous section of this discussion, these results are unusuallyhigh. As before, these values appear to be the result of an artifactof the laboratory analysis. Note that there are no control locationsdesignated for game as there are for the other environmental mediasampled. The reasons for this have been, not only that specificlocations for game (especially game such as deer — the range of oneindividual may span a significant distance) is usually impossible tospecify, but also that most game samples in the past have beenobtained in relatively close proximity to the SSES due to the means(such as "road" kills) with which many deer samples are collected.

The ranges and means (medians) of the yearly average activities ofcesium-137 in samples from the preoperational and operational periods1972-1981 and 1982-1989, respectively, in the table below.

GAME CESIUM-137 ACTIVITIES Ci wet

~ej od

~Ra ~g~e (median)

Prep er tional1972-81

0.0 — 8.81.9 (1.1)

~tl ti1982-89 1990

0.5 — 1.60.8 (0.9) LLD

Since 1986, there appears to be a constant downward trend in thecesium-137 levels in game.

A duck from a farm at location 10D1 and a chicken and eggs fromlocation 12Bl were also sampled in 1990. As in 1988 and 1989, noanthropogenic radionuclides were reported in 1990.

V-42

CALCULATED DOSE TO THE HYPOTHETICAL MAXIMALLYEXPOSED INDIVIDUAL

Th'e dose to a hypothetical maximally exposed individual wasdetermined by summing the contributions to dose from the aquatic,airborne, and terrestrial pathways, as applicable. The doses fromeach pathway were'determined according to the methodology of theOffsite Dose Calculation Manual.

The only radionuclide from the 1990 SSES operation that was detectedin the surface water portion of the aquatic pathway was tritium. Asdescribed previously, tritium was frequently observed in the coolingtower blowdown line in 1990 at levels exceeding those found at thecontrol locations. For the purpose of performing the tritium dosecalculation, tritium was assumed to be present continuously in thecooling tower blowdown line throughout 1990 at an activity levelequivalent to the difference between the blowdown line's 1990 averagelevel and the 1990 average tritium activity level for surface watercontrol locations. Calculations performed using the LADTAP II codeand conservative discharge volume estimates indicated that themaximally exposed age group would be the child. The whole body doseto a child at the nearest downriver municipal water supplier via thedrinking water, shoreline, and fish pathways was determined to beless than 0.001 millirem.

Manganese-54 was the only radionuclide detected in the airbornepathway from the SSES operation in 1990. It was detected in onecomposited air sample from the fourth quarter of 1990. For thepurpose of performing the dose calculation based on inhalation of themanganese-54, it was assumed that the radionuclide was presentcontinuously throughout the 92-day period at the level at which itwas detected in the composite sample. Calculations performed usingthe TRACES software (version 1.3, August 1987) indicated that themaximally exposed age group for the whole body would be the child.The whole body dose to the child was determined to be less than0.00001 millirem. These calculations also indicated that themaximally exposed age group for the critical organ would be theteenager. The lung (critical organ) dose to the teenager would beless than 0.001 millirem.

Zinc-65 was the only radionuclide detected in the terrestrial pathwayfrom the SSES operation in 1990. It was detected in one milk samplefrom September 1990. For the purpose of performing the dosecalculation based on ingestion of the zinc-65, it was assumed thatthe zinc-65 was present continuously in the milk at the level it wasdetected and that the milk was consumed for the 30 days fromSeptember 1 through September 30, 1990. Calculations performed usingthe TRACES software (version 1.3, August 1987) indicated that themaximally exposed age group would be the infant. The whole body doseto the infant was determined to be less than 0.01 millirem. Theliver (critical organ) dose to the infant would be less than 0. 1

millirem.

The maximally exposed age group from the airborne/terrestrial pathwayin 1990 was the infant. The maximum possible whole body dose fromthis pathway was determined to be less than 0. 1 percent of the 10

V-43

millirem limit (as expressed in 10 CFR 50, Appendix I) for two unitreactor operation. The maximally exposed age group from the aquaticpathway in 1990 was the child. The maximum possible whole body dose~from this pathway was determined to be less than 0.01 percent of the~6 millirem limit (as expressed in 10 CFR 50, Appendix I) for two unitreactor operation. These values can also be compared to the averageannual value of approximately 300 mil,lirem effective dose-equivalentreceived by the U.S. population from exposure'to natural backgroundradioactivity.

V-44

DEVIATIONS FROM THE TECHNICAL SPECIFICATIONS SAMPLE SCHEDULE AND LLDs-1990

Deviations occurred in the monitoring of ambient radiation, surfacewater, drinking water, ground water, air, milk, and food. Thesedeviations are discussed below and specifically documented in Tables 6,7, 8, 12, 13, 16, and 19.

Several TLDs, which were posted at monitoring locations required byTechnical Specifications, were lost during 1990 while in the field. OneTLD was lost during the second calendar quarter of 1990 and two morewere lost during the fourth calendar quarter.

Problems with automatic composite samplers (ACSs) at two surface waterlocations (6S6 and 6S7) and one drinking water location (12H2RAW) led tointervals when no water was being collected, intervals when insufficientwater was being collected, and intervals when too much water was beingcollected. These instances resulted in samples that were not asproportionally representative of their entir e sampling periods asdesirable. However, samples were collected and analyzed for allscheduled sample periods. In certain instances, grab samples wereobtained during weeks that ACSs were malfunctioning.

A SSES Significant Operating Occurrence Report (SOOR) ¹1-90-184 waswritten on July 5, 1990, because of a problem with the ACS that samplesthe cooling tower blowdown discharge line, location 6S7. Because ofdebris clogging the suction of the ACS pump, no sample was beingobtained for approximately two days between July 2 and July 5, 1990.Another SOOR, ¹1-90-376, was written on November 16, 1990, because theACS pump at location 6S7 became inoperable due to a worn coupler betweenthe pump and the motor. This resulted in no sample being collectedbetween November 8 and November 15, 1990.

Significant down time was experienced in 1990 with the ACS that samplesuntreated drinking water at the Danville Municipal Water Facility,referred to as location 12H2RAW. Frequent fluctuations of water levelsin the pit from which the pump obtains sample water (some resulting fromcleaning efforts on the part of the facility's personnel) contributed tothe interference of mud with sampling efforts. Delays in bringing theACS back on line were experienced as the result of changes in the PPKL

personnel who perform maintenance on the pump and the unfamiliarity ofthese new persons with the equipment. Eventually the pump had to bereplaced with a spare on-hand. While the ACS was inoperable, grabsamples were taken weekly to maintain monitoring of the drinking water.

Air sample results were declared invalid for one sample location duringone sample period in June, 1990, as a result of the unusually low volumeof sample that was collected. The low volume was collected because ofthe loss of electrical power to the air sampler for an interval of abouttwo days during this'eriod. Also, a hole was found in an airparticulate filter being retrieved from a sampler in June, although itdid not appear to have significantly affected the results.

The analysis sensitivities (LLDs) required by the TechnicalSpecifications were not met for all samples in 1990. Technical-Specifications-required LLDS were not met for various types of samplesand analyses. The reasons for not meeting these sensitivities includesuch factors as longer-than-normal decay times between sample collectionand counting, smaller-than-normal aliquots of sample being analyzed,lower-than-normal chemical recoveries, and lower-than-normal countingefficiencies.

LLDs were most frequently missed or not reported for the gamma-spectroscopically analyzed radionuclides barium-140 and lanthanum-140,with half-lives of 12.8 days and 40.2 hours, respectively, due to longdecay times between sample collection and counting. Sensitivities alsowere missed for iodine-131, with an eight-day half-life, that wasanalyzed both radiochemically and by gamma spectroscopy. In the case ofthe iodine-131 radiochemical analyses, low chemical recoveries orcounting efficiencies were typically important factors contributing tomissed sensitivities.

The deviations described above did not significantly affect the REHP'sability to monitor the environment for any possible effects from theSSES operation.

VI-2

VII. PROGRA CHANGES — 1990

The radioanalytical laboratory contracted to analyze REHP samples forthe SSES RENP Program changed in March of 1990. The formerlaboratory used by the program was replaced as a result ofcompetitive bidding.

2. In addition to various changes in the paperwork used to document theparticulars of sample collection and accounting for samples duringshipment to the radioanalytical laboratory, a change was made in theanalyses performed on milk samples. Gross-beta-minus-potassium-40analyses were discontinued, and routine strontium-89/90 analyses wereinitiated. Under the regimen practiced while doing business with theformer laboratory, when the results for the gross-beta-minus-potassium-40 analyses of samples exceeded an action level of 15pCi/1, the samples would be analyzed for strontium-89/90. Becausethe prices of the two different analyses were very similar, it wasfelt that analyzing all milk samples for strontium-89/90 would bemore cost effective.

3. A change was made in the conduct of the annual Land Use Census toensure that, not only would the latest information on the nearestresidences, gardens, and locations possessing dairy animals in thevarious sectors in the vicinity of the SSES be obtained, but alsothat information is acquired with regard to the consumption of allmeat, dairy products, and fruits/vegetables produced at thoselocations, in addition to the product(s) for which the location isclassified as the nearest in the sector. 'This practice will supportaccurate dose calculations from any radioactive contaminants thatmight be identified, by ensuring that all appropriate pathways to manare considered.

4.

5.

Consideration of Land Use Census results and meteorological dataobtained in 1989 indicated the existence of several nearest-sectorgardens that were at more sensitive locations for the detection ofany radioactive materials that might be released from the SSES thanseveral of those that had been sampled during the harvest season of1989. As a result, the owners of these gardens were contacted in thespring of 1990 to determine if they would be willing to supplysamples for analysis. It was determined from one of these contactsthat the garden in sector 8, which had been identified in the 1989Land Use Census, would not be planted during the 1990 growing season.However, one of these gardens, the garden planted at the MoskalukResidence (14B), was eventually sampled in 1990.

An effort was initiated in 1990 to ensure that ground water samplesare obtained where possible, prior to undergoing any treatment, suchas water softening. Beginning in November of 1990, untreated waterbegan to be sampled at location 2S6, the Energy Information Center.Water sampled at location 12F3, the Berwick Mater Company, andlocation 4S5, the Whitehouse, in 1990 was also untreated. Effortsare continuing to ensure that untreated water will be sampled atlocations 3S5, the Riverlands, and 11S5, the SSES EmergencyOperations Facility. Untreated ground water can not be obtained from

locations 4S4, the SSES Training Center and 12E4, the BerwickHospital.

6. The locations of two air sample and precipitation collector stationswere changed in 1990. The station formerly at location 2S2, theEnergy Information Center, was moved to location 3S2, near the BackupMeteorological Tower on-site on September 21, 1990. The reason forthis move was that an addition was being built onto the InformationCenter that would have interfered with sample collection at thislocation. The station formerly at llS2, the Golomb House, wasrelocated in mid-November to 12S2, the Emergency Operations Facility,for two reasons. Those reasons were the constant concern aboutoverhanging tree leaves at. the former llS2 location and themeteorological data indicating that the new 12S2 location is a moresensitive monitoring location than the old location llS2.

7. One milk sampling location was changed during 1990 because the farmersupplying milk from the former location went out of business. TheShultz farm, location 12B2, was replaced with the Drasher farm,location 10D3, at the beginning of October 1990.

8. TLD location 3S6, at the Backup Meteorological Tower on site, wasadded at the beginning of October. This was added because of theplacement of the air sample and precipitation collector stationreferred to above.

VII-2

CONCLUSIO

In 1990, REMP detected the naturally occurring radionuclides beryllium-7, potassium-40, radium-226, and thorium-232 in the environment.Beryllium-7 was observed in algae, sediment, air, and vegetation.Although beryllium-7 is usually observed in some fruit/vegetablesamples each year, it was not reported in this sample medium in 1990.Potassium-40 was reported for all media except surface water, groundwater, and drinking water. Radium-226 was reported routinely insediment and soil samples as expected, and, in addition, it wasreported in one precipitation sample, in one sample of fruit, and fourvegetation samples. The radium-226 detections in precipitation andfruit are believed to be the result of contamination of the samples,probably from soil. Thorium-232 was routinely reported in sediment andsoil as expected. Thorium-232 was also reported in one vegetablesample and two vegetation samples.

The 1990 REMP also reported the following eight man-made radionuclidesin the environment: tritium, manganese-54, cobalt-60, zinc-65,strontium-89, strontium-90, iodine-131, and cesium-137.

Strontium-89 and strontium-90 were reported in 1990 milk samples.Strontium-90 (like cesium-137) is a long-lived radionuclide present inthe environment as a result of the fallout from atmospheric nuclearweapons tests. Strontium-89, although also produced by nuclearweapons, is short-lived and should not still be detectable as falloutfrom previous atmospheric tests. However, based on SSES effluentreporting, it is not believed to be measurable in the environment'as aresult of SSES operation either. Although strontium-89 has beenanalyzed for in milk samples in previous preoperational and operationalyears, it has not been reported since the preoperational years, 1976through 1981. In 1990, it is believed to be an artifact of thelaboratory performing the analysis, rather than actually being presentin the environmental samples.

Iodine-131 was found in surface water samples from the SusquehannaRiver, both upstream and downstream of the SSES. It is believed to bepresent as the result of medical usage. Cesium-137, from the falloutof previous atmospheric nuclear weapons testing, was reported in algae,milk, sediment, and soil. It was not reported in a variety of othermedia, such as game, in which it is normally observed during the courseof a monitoring year. (This is believed to be an artifact of thelaboratory performing the analyses.) The fission products strontium-90, iodine-131, and cesium-137 are typically observed in the mediadescribed above in any given year and are attributed to sources otherthan the SSES.

Tritium was observed in all four types of water samples collected in1990 as is usual. Manganese-54 was identified in one air sample, onesoil sample (from the SSES sewage sludge disposal site), two coarsesediment samples, two flocculated sediment samples, and several groundwater samples. Cobalt-60 was observed in one algae sample and in onesediment sample. Zinc-65 was reported in one milk sample.- These man-made radionuclides may all be attributed to SSES operation, although

the appearance of manganese-54 in the ground water, is questionable froma pathway analysis standpoint.

1

The man-made radionuclides tritium, manganese-54, and zinc-65 were usto estimate the offsite dose impact from the aquatic, airborne, andterrestrial pathways, respectively. (Cobalt-60 was not used because nodemonstrable pathway has been observed from algae to man.) Theresulting conservatively calculated radiation dose to a hypotheticallyexposed individual was less than 0.01 millirem to the whole body. Thisconfirms the negligible impact of the SSES operation presented in theSemiannual Effluent and Waste Disposal report for the SSES in 1990(39).

Monitoring the ambient radiation levels in the vicinity of the SSES bythermoluminescent dosimetry has similarly demonstrated no significantimpact on the health and safety of the public living around the SSES.The annual dose-equivalent of about 72 millirem indicated by REMP TLDmonitoring can not be determined to be different from the exposure dueto natural background radiation.

VIII-2

SWHARY FOR THE SSES

OPERATIONAL RADIOL06ICAL E . EHTAL HONITORIK6 PROGRAM - 1990NAHE OF FACILITY: SUS()UEHAHHA STEAN ELECTRIC STATION

LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORTING PERIOD: JANUARY 2, 1990 TO JANUARY 2, 1991

PAGE 1 of 6

MEDIWOR PAT%AY

SANPLED

(UNIT OF

liEASUREVENT

ANALYSIS AND

TOTAL NWBEROF ANALYSESPERFORNEO

LOVER LINITOF

DETECTION

LD 2

L INDICATOR LOCATIONS

HEAN (f) (3)RANGE

LOCATION VITH HIGHEST NEAN

HAHE NEAN(f)(3)DISTANCE AND DIRECTION RANGE

CONTROL LOCATIOHHEAH (f) (3)

RANGE

NWBER OF

NOHROUTINE

REPORTED

HEASNEHENTS 4

Surface Vater(pCi/'l)

Gross 107Alpha

Gross 107Beta

Tritium 105

Iodine- 108131

Ganna 108Spec

Ambient Radiation TLD 361(mR/std. qtr.)

2000

LLD

17.9 (329/329)(12 ' - 26.8)

1 ~ 0 (11/71)(0.3 - 1 ')4.3 (49/71)(1 ' - 14.0)

1228 (41/70)(99 - 8418)

0.6 (1/72)

Station 9S20 ' miles S

Station 5SB

0.8 miles E

Station 6S7Discharge

Station 6S7

Discharge

Station 1033 ' miles N

24 ' (4/4)(22 '-26.8)

1 ' (3/12)(0.6 - 2 ')7.3 (9/12)(2 ' - 13.0)

2480 (11/11)(281 - 8418)

1 ' (1/12)

18.1 (32/32)(13 ' - 22.4)

1 ~ 2 (7/36)(0.5 - 2 ')

. 3 ' (27/36)(1.3 - 14 ')631 (18/35)(62 - 3985)

1 ' (1/36)

LLD

Potable Vates(pci/1)

Algae(pCi/g dry)

Gross 23Alpha

Gross 23Beta

Tritium 23

Iodine- 23131

Gamsa 23Spec

Ganma 12

Spec

2000

LLD

2 ' (8/23)(1 ' - 4 ')

'

125 (9/23)(93-215)

LLD

LLD

Station 12H2 .

Treated26 miles VSM

Station 12H2Treated26 miles VSV

2 ' (6/12)(1.2 - 4 ')136 (5/12)(93-215)

Only IndicatorStations Sampledfor this Hedium

= 0

TABLE 4SUHHARY OF DATA FOR THE SSES

OPERATIONAL RADIOLOGICAL ENVIRONHENTAL HONITORING PROGRAH - 1990NAHE OF FACILITY: SUSQUEHANNA STEAN ELECTRIC STATION

LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORTIN6 PERIOD: JANUARY 2, 1990 TO JANUARY 2, 1991

PAGE 2 of 6

HEOIUHOR PATHMAY

SAHPLEO

(UNIT OF

HEASUREHENT

ANALYSIS AND

TOTAL NUHBER

OF ANALYSES

P RFORHEO I

LOMER LIHITOF

DETECTION

L 2

ALL INDICATOR LOCATIONS

HEAN (f) (3)RANGE

LOCATION MITH HIGHEST HEAN

NAHE HEAN(f) (3)DISTANCE AND DIRECTION RANGE

CONTROL LOCATIONHEAN (f) (3)

NUHBER OF

NONROUTINE

REPORTED

IiEASUREHENTS 4

Fish(pCi/g wet)

Sediment(pCi/g dry)

Be-7

K-40

Hn-54

Co-60

1-131

Cs-137

Ra-226

Th-232

Gross 15Beta

Ganma 15

Spec

K-40

Gross 9Alpha

Gross 9Beta

Gast 12

Spec

8.0 (3/6)(1.8 - 11.8)

44.3 (4/6)(11.4 - 105)

0.9 (2/6)(0.13 - 1.7)

1.0 (1/6)

8.4 (1/6)

0.15 (1/6)

3.1 (1/6)

LLD

4.8 (9/9)(1.6 - 8.1)

5.3 (9/9)(3.3 - 10.8)

0.23 (6/6)(0.04 - 0.36)

0.36 (6/6)(0.04 - 0.061)

Station AG4

0.9 miles ESE

Station AG3

0.8 miles E

Station AG4

0.9 miles ESE

Station AG4

0.9 miles ESE

Station AG3

0.8 miles E

Station AG3

0.8 miles E

Station AG3

0.8 miles E

Station AG3

0.8 miles E

Station IND0.9 - 1.4 miles ESE

Station LTAM

0.8 miles NE

Station 12F6.9 miles MSM

tion LTAM'te NE-ESE

8.0 (3/6)(1.8 - 11.8)

111 (3/6)(11.5 - 235)

0.9 (2/6)(0.13-1.7)

1.0 (1/6)

9.9 (1/6)

0.15 (1/6)

5.2 (2/6)(4.5 - 6.0)

4.2 (1/6)

5 1 (6/6)(1.6 - 7.8)

6.3 (3/3)(4.0 - 10.8)

0.36 (1/1)

0.57 (1/1)

5.6 (2/6)(1.8 - 9.3)

111 (3/6)(11.5 - 235)

, 0.13 (1/6)

LLD

9.9 (1/6)

0.15 (1/6)

5.2 (2/6)(4.5 - 6.0)

4.2 (1/6)

4.2 (6/6)(2.2 - 6.8)

3.4 (6/6)(2.6 - 4.2)

0.15 (3/3)(0.04 - 0.22)

0.30 (3/3) 0(0.06 - 0.51)

4SINHARY OF OR THE SSES

OPERATIOHAL RADIOLOGICAL ENV TAL NONITORIHG PROGRAN - 1990HAHE OF FACILITY: SUSQUEHANNA STEAN ELECTRIC STATION

LOCATION OF FACILITY: LUZERHE COUNTY, PENNSYLVANIAREPORTIHG PERIOD: JANUARY 2, 1990 TO JANUARY 2, 1991

PAGE 3 of 6

NEDIWOR PAT%AY

SANP LED(UNIT OF

ASNENENT

ANALYSIS AHD

TOTAL NINBEROF ANALYSES

PERFORNED I

LOMER LINITOF

DETECTION

L 0

IHDICATOR LOCATIONS

NEAN (f) (3)LOCATIOH VITH HIGHEST NEAN

NANE NEAN(f) (3)DISTANCE AND DIRECTION RANGE

CONTROL LOCATIONNEAN (f) (3)

RANGE

NNBER OF

NOHROUTI HE

REPORTED

NEASNENEHTS 4

Floe(pCi/dry)

Be-7

K-40

Mn-54

Co-60

Cs-137

Ra-226

Th-232

Gross 2

Alpha

Gross 2Beta

Gasma 4

Spec

K"40

Hn-54

Cs-137

Ra-226

0.18

0.4 (I/8)

7.4 (8/8)(4.6 - 13.9)

0.02 (I/8)

0.01 (1/8)

0.04 (7/8)(0.01 - 0.08)

0.47 (8/8)(0.29 - 0.88)

0.52 (8/8)(0.38 - 0.89)

1.3 (I/I)

3.1 (1/1)

124 (1/2)

0.2 (1/2)

LLD

3.0 (1/2)

Station 281.6 miles HHE

Station 781.2 miles SE

Station 12F6.9 miles WSM

Station 11C

2.6 miles SM

Station 2F6.4 miles NHE






Station 281.6 miles NHE

Station 281.6 miles HHE


0.41 (1/2)

10.4 (2/2)(6.9 - 13.9)

0.02 (1/2)

0.01 (1/8)

0.06 (2/2)(0.04 - 0.08)

0.66 (2/2)(0.45 - 0.88)

0.72 (2/2)(0.54 - 0.89)

1.3 (1/1)

3.1 (I/1)

124 (1/2)

0.3 (I/2)

0.3 (1/2)

3.0 (1/2)

0.26 (2/4)(0.11 - 0.41)

6.2 (4/4)(5.6 - 6.9)

0.02 (1/4)

LLD

0.06 (4/4)(0.04 - 0.08)

0.44 (4/4)(0.36 - 0.52)

0.48 (4/4)(0.40 - 0.60)

1.1 (1/1)

3.1 (1/1)

32.3 (1/2)

0.3 (1/2)

0.3 (1/2)

LLD

TABLE 4SiSKARY OF DATA FOR THE SSES

OPERATIONAL RADIOLOGICAL ENVIRONNENTAL NONITORING PROGRAH - 1990NAME OF FACILITY: SUSQUEHANNA STEAN ELECTRIC STATION

LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORTING PERIOD: JANUARY 2, 1990 TO JANUARY 2, 1991

PA6E 4 of 6

NEDIlNOR PATHWAY

SANPLEO

(UNIT OF

NEASNENENT

ANALYSIS AND LOWER LINITTOTAL Nil(BER OF

OF ANALYSES DETECTIONP FORNEO D


NEAN (f) (3)RANGE

LOCATION WITH HIGHEST NEAN

NANE NEAN(f) (3)DISTANCE AND DIRECTION RANGE

CONTROL LOCATIONNEAN (f) (3)

RANGE

NiWBER OF

NONROUTINE

REPORTED

NEASlRE NTS 4

Ground Mater(pci/1)

Air Particulates(E-03 pCi/m )

Air Iodine(E-03 pCi/m )

Air ParticulatesquarterlyComposite(E-03 pCi/m )

Precipi(pCi/l

Th-232

Gross 79Alpha

Gross 79Beta

Tritium 79

Gamna 79Spec

Mn-54

Gross 520Beta

Gasma 520Spec

Gross 42Alpha

Gamna 42Spec

Be-7

K-40

Gross 39Alpha

Gross 39Beta

2000

10

70

3.1 (1/2)

1.3 (12/67)(0.6 - 2.4)

2.3 (23/67)(1.2 - 4.7)

143 (24/67)(57 - 378)

3.8 (1/67)

17 (415/415)(7-20)

LLO

1.4 (33/34)(0.4 - 4.5)

104 (30/34)(30-270)

800 (8/34)(130 - 1960)

1.9 (1/32)

4.8 (24/32)(3.0 - 6.2)


Station 12E44.7 miles MSM

Station 12E44.7 miles WS'M

Station 4S20.5 miles ENE

Station 12F35.2 miles WSM

Station 12S20.4 miles MS'M

Station 3S20.5 miles NE

Station 1D2

4.0 miles N

Station 15S40.6 miles NW

tation 3D1

4 miles NE

Station 15S40.6 miles NW

3 1 (I/2)

1.5 (3/12)(1.3 - 1.8)

2.6 (4/12)(1.7 - 4.7)

230 (4/12)(93 - 378)

6.0 (2/12).(3.9 - 8.1)

24 (6/6)(20-29)

3.3 (2/4)(2.1 - 4.5)

158 (3/4)(54-210)

1960 (1/4)

1.9 (1/4)

5.6 (3/4)(5.2 - 5.9)

LLD

1.4 (2/12)(1.2 - 1.6)

2.1 (6/12)(1.3 - 12.4)

162 (5/12)(130-185)

6.0 (2/12)(3.9 - 8.1)

16 (104/104)(7-39)

LLD

1.6 (8/8)(0.8 - 2.8)

114 (8/8)(49-220)

1043 (3/8)(770-1320)

LLD 0

3.9 (5/7) 0(2.5 - 5.4)

4SWHARY FOR THE SSES

OPERATIONAL RADIOLOGICAL E NTAL HONITORIN6 PR06RAH - 1990NAHE OF FACILITY: SUSq NA STEAH ELECTRIC STATION

LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORTIN6 PERIOD: JANUARY 2, 1990 TO JANUARY 2, 1991

PA6E 5 of 6

HEDIUHOR PATHWAY

SAHP LEO

(UNIT OF

HEASUREHENT

ANALYSIS AND

, TOTAL NtWBEROF ANALYSES

PERFORHED

LOWER LIHITOF ALL NDICATOR LOCATIONS

DETECTION HEAN (f) (3)D RANGE

LOCATION WITH HIGHEST HEAN

NAHE HEAN(f) (3)DISTANCE AND OIRECl'ION RANGE


RANGE

NlWBER OF

NONROUTINE

REPORTED

HEASNEHENTS 4

Hilk(pci/1)

OCI

Soil(pCi/9 dry)

Tritium 39

Ganna 39Spec

K-40

Ra-226

Gross Beta 18Hinus K40

I-131 132

Sr-89 132

Sr-90 132

Gasma 132Spec—

K-40

Zn-65

Cs-137

Gambia 20Spec

18

323 (11/32)(61-768)

1824 (1/32)

43 (1/32)

6.1 (16/16)(2.5 - 14)

LLD

2.2 (14/115)(0.6 - 6.9)

3.3 (69/115)(0.6 - 25.9)

1422 (129/131)(411 - 10,080)

8.5 (1/131)

4.1 (6/131)(3.2 - 4.9)

Station 12EI4.7 miles WSW

Station 12E14.7 miles WSW

Station 12E14.7 miles 'MSM

Station 12832.0 miles WSW

Station 10Dl3.0 miles SSW

Station 12832.0 miles 'MSW

Station 12821.7 miles WSW

Station 12821.7 WSW

Station 14B11.8 miles WNW

625 (2/4)(481-768)

1824 (1/4)

43 (1/4)

12.5 (2/2)(11-14)

6.9 (1/17)

7.1 (6/17)(1.9 - 25.9)

1934 (15/15)(463 - 10,080)

8.5 (1/15)

4.9 (1/17)

362 (4/7)(128-955)

LLO

LLD

10.7 (2/2)(9.3 12.0)

LLD

2.3 (1/17)

3.5 (14/17)(0.8 - 11.0)

1472 (19/19)(345 - 6819)

LLD

LLD

0

K-40 14.3 (16/16) Station 15S4(9.6 - 23.2)- 0.6 miles NW

23.2 (2/2) 14.1 (4/4)(10.8 „- 19.4)

TABLE 4SUHHARY OF DATA FOR THE SSES

OPERATIONAL RADIOL06ICAL ENVIRONHENTAL HONITORING PRDGRAH " 1990NAHE OF FACILITY: SUSQUEHANNA STEAH ELECTRIC STATION

LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORTIHG PERIOD: JANUARY 2, 1990 TO JANUARY 2, 1991

PA6E 6 of 6

HEDIUH

OR PATWAYSAHPLED

(UNIT OF

LREHENT

ANALYSIS AND " LOVER LIHITTOTAL NINBER OF

OF ANALYSES DETECTIONPERFORHED 0


HEAN (f) (3)RANGE

LOCATION MITH HIGHEST HEAN

NAHE HEAN(f)(3)DISTAN AND DIRECTION RANGE


RANGE

NiNBER OF

NONROUTINE

REPORTED

HEASNEHENTS 4

Vegetation(pCi/g wet)

Food Products(pCi/g wet)

Game, Poultry,Eggs(pCi/g wet)

Cs-137

Ra-226

Th-232

Ganna 10Spec

Be-7

K-40

Ra-226

Th-232

Ganma 94Spec

K-40

Ganma 10Spec

0.3 (15/16)(0.06 - 0.67)

0.8 (16/16)(0.57 - 1.10)

1.0 (16/16)(0.08 - 1.50)

1.3 (7/8)(0.8 - 2.4)

9.6 (8/8)(2.6 - 19.7)

0.3 (3/8)(0.2 - 0.5)

0.3 (2/8)(0.2 - 0.3)

9.4 (70/82)(0.73 - 42.21)

11.9 (9/10)(0.4 - 35.1)

Station 9821.3 miles S

Station 15S40.6 miles NM

Station 15540.6 miles Nil

Station SSS

0.8 miles E

Station 7G1

14 miles SE

Station 5S50.8 miles E

Station 3570.5 miles NE

Station 1481.3 miles MNM

Station 6S

Onsite ESE

'.66(2/2)

(0.64 - 0.67)

1.10 (2/2)

1.30 (2/2)(1.10 " 1.50)

2.4 (1/1)

24.9 (1/1)

0.5 (1/1)

0.3 (1/1)

23.36 (5/5)(11.7 - 40.38)

35.1 (1/1)

0.3 (4/4)(0.10 - 0.42)

1.0 (4/4)(0.09 - 1.00)

1.2 (4/4)(1.00 - 1.30)

1.3 (2/2)(1.2 - 1.5)

16.0 (2/2)(7.2 - 24.9)

0.5 (1/2)

LLD

14.9 (11/12)(2.58 - 34.45)

Only IndicatorStations Sampledfor this Hedium

The t number of analyses does not include duplicates or splits or repeat a

2. The al Specifications LLO is given when applicable3. Hean anges are based upon detectable activities only. (f) is the rati4. USNRC orting levels as specified in the Technical Specifications.

ses.

itive results to the number of samples analyzed.

X. ~LANOUE E U

The USNRC Branch Tech'nical Position on "An Acceptable RadiologicalEnvironmental Honitoring Program" (November 1979, Revision 1), states that"a census shall be conducted annually during the growing season todetermine the location of the nearest milk animal and nearest gardengreater than 50 square meters (500 sq. ft.) producing broad leafvegetation in each of the 16 meteorological sectors within a distance of 8km (5 miles)." To comply with this requirement, a land-use survey wasconducted for the Susquehanna SES during the period July 16, 1990 throughAugust 30, 1990. The closest garden (greater than 50 square meters,producing broad leaf vegetation) and residence in each radial sector wasdetermined and all dairy animals within five (5) miles were identified.

Table 5 lists the nearest dairy animals, the nearest garden, and nearestresidence in each sector identified during the survey. These land-useparameters are used in the assessment of potential radiological doses toindividuals and populations of the stated regions.

TABLE 5

Nearest residence, garden, and dairy animal in each of the 16meteorological sectors within a 5-mile radius of the Susquehanna-Steam Electric Station, 1990.

Sector Direction NearestResidence

NearestGarden

NearestDairy Animal

1

2

3

5

6

7

8

9

10

ll12

13

14

15

16

N

NNE

NE

ENE

E

ESE

SE

SSE

S

SSW

SW

WSW

W

WNW

NW

NNW

1.3 mi

0.9 mi

2.3 mi

2.2 mi

1.4 mi

0.5 mi

0.4 mi

0.7 mi

1.1 mi

1.2 mi

1.5 mi

1.2mi'.8

mi

0.7 mi

0.9 mi

0.7 mi

3.3 mi

1.3 mi

2.3 mi

2.2 mi

1.4 mi

2.0 mi

0.6 mi

0.9 mi

1.1 mi

1.2 mi

1.8 mi

1.2mi'.5

mi

0.5 mi

2.2 mi

4.0 mi

>5.0 mi

>5.0 mi

>5.0 mi

3 ' ml

4.5 mi

2 ' mi

2.6 mi

3.5 mi

3.9 mi

3.0 mi

>5.0 mi

1.7 mi

5.0 mi

1.8 mi

>5.0 mi

4.2 mi

'Chickens raised for consumption at this location.Fruits/vegetables grown for consumption at this location.

'Eggs consumed from chickens raised at this location.

X-2

~

~ ~

~ ~

~

~ ~

XI. REFERENC S

1. Radiation Management Corporation, "Susquehanna Steam ElectricStation, Radiological Environmental Honitoring Program, Report ¹1(April — December'972)" RHC-TR-73-14, July 1973.

2.

3.

5.

6.

7.

8.

9.

10.

12.

13.

Radiation Management Corporation, "Susquehanna Steam ElectricStation, Pre-operational Radiological Environmental MonitoringProgram 1973," RMC-TR-74-07, Hay 1974.

Radiation Management Corporation, "Susquehanna Steam ElectricStation, Preoperational Radiological Environmental MonitoringProgram, 1974 Annual Report," RHC-TR-75-07, April 1975.

Radiation Management Corporation, "Susquehanna Steam ElectricStation, Radiological Environmental Monitoring Program, 1975 AnnualReport," RHC-TR-76-05, Hay 1976.

Radiation Management Corporation, "Susquehanna Steam ElectricStation, Radiological Environmental Monitoring Program, 1976 AnnualReport," RHC-TR-77-04, March 1977.

Radiation Management Corporation, "Susquehanna Steam ElectricStation, Radiological Environmental Monitoring Program, 1977 AnnualReport," RHC-TR-78-01, Hay 1978.

Radiation Management Corporation, "Susquehanna Steam ElectricStation, Radiological Environmental Monitoring Program, 1978 AnnualReport," RMC-TR-79-01, April 1979.

Radiation Management Corporation, "Susquehanna Steam ElectricStation, Radiological Environmental Monitoring Program, 1979 AnnualReport," RHC-TR-80-01, March 1980;

Radiation Management Corporation, "Susquehanna Steam ElectricStation, Radiological Environmental Monitoring Program, 1980 AnnualReport," .RMC-TR-81-02, July 1981.

Radiation Management Corporation, "Susquehanna Steam ElectricStation, Radiological Environmental Monitoring Program, 1981 AnnualReport," RHC-TR-82-03, July 1982.

Radiation Management Corporation, "Susquehanna Steam ElectricStation, Radiological Environmental Monitoring Program, 1982Preoperational Report," RHC-TR-83-01, April 1983.

Radiation Management Corporation, "Susquehanna Steam ElectricStation, Radiological Environmental Monitoring Program, 1982Operational Report." RHC-TR-83-02, April 1983.

NUS Corporation, "Susquehanna Steam Electric Station, RadiologicalEnvironmental Monitoring Program, 1983 Annual Report," NUS-4516 March1984.

14.

15.

16.

17.

18.

19.

20.

21.

Pennsylvania Power and Light Company, "Susquehanna Steam ElectricStation, Environmental Report, Operating License Stage," Hay 1978.

Pennsylvania Power and Light Company, "Susquehanna Steam ElectricStation, Final Safety Analysis Report".

United States Nuclear Regulatory Commission, Office of NuclearReactor Regulation, "Final Environmental Statement Related to theOperation of Susquehanna Steam Electric Station, Units 1 and 2,"Docket Nos. 50-387 and 50-388, June 1981.

United States Nuclear Regulatory Commission, "An AcceptableRadiological Environmental Monitoring Program," RadiologicalAssessment Branch Technical Position, November 1979, Revision 1.

National Council on Radiation Protection and Measurements,"Environmental Radiation Measurement," NCRP Report No. 50,Washington, D.C., December 27, 1976.

Oakley, D.C., "Natural Radiation Exposure in the United States,"ORP/SID 72-1 Office of Radiation Programs, U.S. Environmental.Protection Agency, Washington, D.C., June 1972.

Denham, D.H., Roberts, H.C., Novitsky, W.H., Testa, E.D.,"Investigation of Elevated Cesium-137 Concentrations in Small Game inLuzerne County, Pennsylvania." Proceedings of Papers presented atHealth Physics Society Tenth Midyear Topical Symposium, October 11-13, 1976, pgs 271-279.

Teledyne Isotopes, "Susquehanna Steam Electric Station, RadiologicalEnvironmental Monitoring Program, 1984 Annual Report," April 1985.

22. Currie L.A., "Lower Limit of Detection: Definition and Elaborationof a Proposed Position for Radiological Effluent and EnvironmentalMeasurements," NUREG/CR-4007, September 1984.

23.

24.

25.

26.

27.

Pennsylvania Power and Light Company, "Susquehanna Steam ElectricStation, Semi-annual Effluent Waste Disposal Report, Data Period:January — June 1986", August 1986.

Pennsylvania Power and Light Company, "Susquehanna Steam ElectricStation, Semi-annual Effluent Waste Disposal Report, Data Period:July —

. December 1986," February 1987.

Pennsylvania Power and Light Company Technical SpecificationsSusquehanna Steam Electric Station, Units no. 1 and 2; Docket no. 50-387 and 50-388 Appendix A to License no. NPF-14, April 91 and NPF-22,April 91.

Teledyne Isotopes, "Susquehanna Steam Electric Station, RadiologicalEnvironmental Monitoring Program, 1985 Annual Report", April 1986.

Teledyne Isotopes, "Susquehanna Steam Electric Station, RadiologicalEnvironmental Monitoring Program, 1986 Annual Report," April 1987.

28.

29.

30.

31.

32.

33.

Pennsylvania Power and Light Company, "Susquehanna Steam ElectricStation, Semi-annual Effluent Waste Disposal Report, Data Period:January — June 1987, August 1987.

Pennsylvania Power and, Light Company, "Susquehanna Steam ElectricStation, Semi-annual Effluent Waste Disposal Report, Data Period:July — December 1987, February 1988.

Pennsylvania Power & Light Company, "Susquehanna Steam ElectricStation, Radiological Environmental Honitoring Program, 1987 AnnualReport," April 1988.

Pennsylvania Power & Light Company, "Susquehanna Steam ElectricStation, Semi-annual Effluent Waste Disposal Report, Data Period:January-June 1988," August 1988.

Pennsylvania Power & Light Company, "Susquehanna Steam ElectricStation, Semi-annual Effluent Waste Disposal Report, Data Period:July-December 1988," February 1989.

Pennsylvania Power & Light Company, "Susquehanna Steam ElectricStation, Radiological Environmental Monitoring Program, 1988 AnnualReport," April 1989.

34.

35.

Pennsylvania Power & Light Company,Station, Semi-annual Effluent WasteJanuary-June 1989," August 1989.

.Pennsylvania Power & Light Company,Station, Semi-annual Effluent WasteJuly-December 1989," February 1990.

"Susquehanna Steam ElectricDisposal Report, Data Period:

"Susquehanna Steam ElectricDisposal Report, Data Period:

36.

37.

38.

Pennsylvania Power & Light Company, "Susquehanna Steam ElectricStation, Radiological Environmental Monitoring Program, 1989 AnnualReport," April 1990.

Pennsylvania Power & Light Company, "Susquehanna Steam ElectricStation, Semi-annual Effluent Waste Disposal Report, Data Period:January-June 1990," August 1990.

Pennsylvania Power & Light Company, "Susquehanna Steam ElectricStation, Semi-annual Effluent Waste Disposal Report, Data Period:July-December, 1990," February 1991.

XI-3

ENVIRONMENTAL THERNOLUSUS(UEHANNA STEAN

6ENT DOSIMETRY RESULTS (1)

CTRIC STATION — 1990

Results are in mR/std. qtr. +/-2sPage 1 of 6

Location First quarter1/8/90

to4/5/90

Second quarter4/3/90

to6/20/90

Third quarter6/18/90

to10/4/90

Fourth quarter10/2/90

to1/ll/91

TLDs WITHIN PPEL PROPERTY BOUNDARY

+ 1S22S2

+ 2S32S5(EIC)3S3

+ 3S43S64Sl

+ 4S35S15S4

+ 5S7+ 6S4

6S8+ 6S9+ 7S6+ 8S2+ 9S2+ 10S1

10S211S

+ 11S3

17.4i1.815.010.616.811.012.921.314.310.615.810.9

N/A12.7il.l18.6%0.913.440.714.222.115.0X0.420.0il.l14.6%1.318.0%1.217.9+1.619.010.722.0il.515.6+0.921.4+1.4213.7+1.122.0+0.5

20.3i1.817.4%2.119.110.515.440.317.4%0.418.710.6

N/A16.1%0.623.0i1.215.8i0.217.4%0.918.8i1.022.8i2.217.8il.l19.9+0.421.1+0.920.7il.426.8%1.418.0+1.023.9+1.517.1%0.724.9+2.1

17.3%1.614.9i0.516.910.912.5%0.513.8%i.l15.510.9

N/A12.710.618.6%1.213.2il.o14.4%1.915.1i1.320.2%0.714.5+1.218.6+1.318.1%1.318.421.723.3+0.915.4+1.221.5+0.813.2+1.222.0+1.6

19.6il.618.6il.218.0i0.615.0i0.917.2il.517.3i1.817.6il.615.620.221.8%0.715.2il.l17.5j0.8

(2)22.420.517.2il.l19.621.920.7+1.120.2i1.425.9il.317.621.623.6+1.816.0il.O24.7+2.6

See footnotes at end of table

TABLE 6ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY RESULTS (I)

SUSQUEHANNA STEAN ELECTRIC STATION — 1990

Results are in mR/std. qtr . +/-2sPage 2 of 6


to4/5/90


to6/20/90


to10/4/90


to1/11/91

llS6+ 12S3+ 13S2

13S413S5

+ 14S514S615S4

+ 15S5+ 16S1+ 16S2

14.320.921.2i1.318.4il.522.3i1.321.2i1.618.810.818.7i1.714.7%0.417.522.517.5%0.518.6i1.3

17.3il.l24.4i2.121.9i2.025.4i1.524.8i2.221.5%0.821.1i2.316.610.719.910.920.1%1.521.2%0.9

14.410.621.810.818.4il.821.9il.721.410.818.9i1.518.2%0.814.3%1.717.8il.O17.9il.O18.510.8

16.7il.l23.6%2.521.2i1.825.2%1.723.7il.o21.1i2.020.311.216.5%1.119.lil.l19.8il.321.3%1.0

0-1 MILE OFFSITE

+ 6A47Al7A28A315A316A2

16.5i1.514.5i1.615.421.516.8%0.317.3%1.114.3%1.5

20.2%0.6

17.912.2'9.2i0.7

19.4+1.519.8%0.817.1il.3

'16.4+1.314.820.515.410.916.6%1.016.8il.l14.1il.l

19.8%0.217.9i1.419.3%0.619.6i2.119.5%0.917.021.3


TENVIRONNENTAL THERNOLUN

SUS(UEHANNA STEANNT DOSINETRY RESULTS (1)

TRIG STATION — 1990



to4/5/90


to6/20/90


to10/4/90


to1/ll/91

1-2 PILES OFFSITE

*181+ 283

*284*481*582*682

783*784

+ 882*883

98110821083

*10841284

*1285*1381*1481*1581

1681*1682

17.1%1.416.7il.716.110.615.6i2.317.121.617.521.615.811.417.1i1.215.9il.O17.010.615.110.913.121.213.910.916.721.915.521.515.9i3.015.710.817.120.915.821.314.621.215.3+0.9

18.910.918.520.719.7il.418.2il.219.9i1.518.2i1.7

(2)18.910.818.8%0.419.021.616.911.015.7i2.916.4i1.319.5+1.417.5%0.617.7il.217.5i2.118.9+2.117.3%1.216.811.218.3+2.9

17.021.715.521.615.4%i.715.321.416.521.717.lil.315.210.816.7i1.416.210.916.421.014.8%1.012.910.913.520.617.2i1.915.8%0.815.8i1.615.5i0.616.4%1.015.3il.O14.0i1.314.7+0.9

18.3il.l18.011.8 .

18.7i2.717.8il.420.2il.518.5%1.717.7i1.918.8+2.319.0+0.618.9i1.317.010.915.2%2.616.5i2.318.5%1.017.320.717.7+0.817.5%0.917.911.116.9+0.816.0+0.517.9+2.2


TABLE 6ENVIRONMENTAL THERMOLUNINESCENT DOSIMETRY RESULTS (1)

SUS(UEHANNA STEAN ELECTRIC STATION — 1990



to4/5/90


to6/20/90


to10/4/90


to1/ll/91

2-3 MILES OFFSITE

*11Cl

3-4 MILES OFFSITE

+ 1D2+ 3D1+ 8D3+ 9D4+ 10D2

12D3

4-5 MILES OFFSITE

1E11E2 (SHK)

+ 4El+ 5E2+ 6El+ 7El+ llE1+ 12El+ 13E4

— 4El*

18.4%0.9

17.5i2.018.5i1.516.5il.l17.6i1.417.0i2.016.310.8

15.0i0.8N/A

16.7%1.517.441.319.5%1.817.621.013.4+0.216.410.816.4+1.017.6+0.2

20.5il.l

19.410.720.4%0.519.020.820.621.219.221.519.0i1.2

16.3%0.714.310.919.310.919.5i1.521.4+1.520.9i1.316.6+0.9

(2)18.5+1.619.8+

18.321.6

16.9i1.717.8%1.416.7i1.217.7%0.716.421.1

(2)

14.4il.lN/A

16.310.917.5%0.719.9i1.217.810.713.410.216.010.816.1+0.717.1+0.9

20.3i1.7

19.5i1.220.010.718.7i0.819.5%2.019.0i0.319.921.8

16.2il.2N/A

19.7%1.519.221.120.9i1.320.3+2.216.1i1.518.8%0.818.7+1.322.2+2


T 6ENVIRONMENTAL THERMOLUN NT DOSIMETRY RESULTS (1)

SUS(UEHANNA STEAN RIG STATION — 1990



to4/5/90

Second l}uarter4/3/90

to6/20/90


to10/4/90


to1/11/91

5-10 MILES OFFSITE

+ 2Fl+ 3Fl

*3F28F212F212F4(BER)

+ 15F1+ 16F1

16.211.015.7%1.818.4+1.315.010.0 (5)17.821.722.010.317.6%1.318.7%1.2

18.1%0.916.911.020.1%2.216.310.719.ill.l24.613.320.012.122.2il.4

15.4+0.515.0i2.217.211.614.810.617.612.721.722.217.1i1.317.6%1.3

18.311.517.211.2

(2)16.710.918.921.724.6%2.518.921.020.912.0

10-20 MILES OFFSITE

3G2(NAN)+ 3G3

3G4+ 4Gl+ 7Gl

*7G2+ 12G1

12G4

15.3+1.018.1%0.617.221.719.6%0.318.122.017.1i1.014.3%i.l16.7%1.0

16.3il.l21.6il.220.4%1.022.4+0.920.3%0.520.1+0.816.9il.220.0+0.6

13.9i1.517.511.216.0+1.319.0+1;017.5il.317.011.314.0+0.4

'16.6+0.7

16.4il.320.122.019.1%0.922.010.420.2+1.419.911.417.4+0.118.7+1.8


TABLE 6 .-

ENVIRONHENTAL THERHOLUHINESCENT DOS IHETRY RESULTS (1)SUS(UEHANNA STEAN ELECTRIC STATION - 1990



to4/5/90


to6/20/90


to10/4/90

Fourth quartet10/2/90

to1/11/91

lt

IndicatorAverage(3)

ControlAverage (3)

16.814.4

17.1%3.3

19.1%6.4

19.814.2

16.614.7

16.413.5

19.114.7

19.223.5

OTES

(1) Uncertainties for individual measurements are two standard deviations of the average of four readingsper station.

(2) TLD Hissing.(3) Uncertainties of column averages are two standard deviations calculated from the mean of each.(4) Hean is average of 3 TLD elements.(5) Hean is average of 2 TLD elements.

(+) Tech Spec Locations(*) 'RC Co-Located Stations: 2B4 (1), 1Bl(2), 16B2(3), 15B1(4), 14Bl(5), 13B1(6),

12B5(7), 11C1(8), 10B4(9), 3F2(19), 4B1(23), 5B2(24)6B2(25), 7B4(26), 8B3(27), 7G2(35).


Pag f 5

TABLE 7GROSS ALPHA, GROSS BETA, TRITIUM, AND

GAMMA+ SPECTROSCOPIC ANALYSES OF SURFACE WATERSUSQUEHANNA STEAM ELECTRIC STATION - 1990

Results in pCi/1 + 2s

LOCATION COLLECTION DATE GROSS ALPHA GROSS BETA H-3 (7) COMMENTS

6S65S81D312Fl12G2LTAW6S76S512Hl

6S65S81D312Fl12G2LTAW6S76S512H1

6S65S81D312Fl12G2LTAW6S76S512H1

Ol/02/90 to 02/05/90Ol/08/90 to 02/05/90

01/03/90Ol/03/90Ol/03/90Ol/03/90

Ol/02/90 to 02/05/9001/08/90 to 02/05/90Ol/02/90 to 02/05/90

02/05/90 to 03/05/9002/12/90 to 03/05/90

02/05/9002/05/9002/05/9002/06/90

02/05/90 to 03/05/9002/12/90 to 03/05/9002/05/90 to 03/05/90

03/05/90 to 04/09/9003/12/90 to 04/09/90

03/05/9003/05/9003/05/9003/05/90

03/05/90 to 04/09/9003/12/90 to 04/09/9003/05/90 to 04/09/90

< 1.0< 1.0< 1.0< 1.0< 1.0< 2.0< 2.0< 1.0< 2.0

1.0 + 0.41.4 + 0.5< 1.0< -2.0< 2.0< 2.0

1.2 + 0.71.0 + 0.4< 0.3

< 0.7< 0.7

0.9 + 0.40.9 + 0.40.3 + 0.30.4 + 0.4< 2.0< 0.7< 0.8

4.0 +4.1 +3.4 +4.4 +4.3 +5.6 +

14.0 +3.9 +3.2 +

2.54.06.3

10.09.73.62.85.11.8

1.4 +1.3 +2.1 +2.3 +3.3 +3.7 +7.2 +2.2 +1.4 +

0.91.01.01.11.11.22.00.9O.l

0.91.01.11.01.41.00.91.00.9

0.70.70.90.90.91.00.90.70.7

110 + 5094 + 53

190 + 50690 + 60 .

340 + 50180 + 50

1300 + 100< 80< 70

< 121< 135< 70< 90< 90

160 + 60487 + 161

< 131181 + 152

571 + 79< 60< 125< 127

142 + 153150 + 149

2340 + 89< 63

164 + 78

* Only kaama eeltters detected are reported: typical LLD values are found ln Table 21.




Page 2 of 5


6S65S81D312F112G2LTAW6S76S512Hl

6S65S81D312F112G2LTAW6S76S512H1

04/09/90 to 05/07/9004/16/90 to 05/07/90

04/09/9004/09/9004/09/9004/09/90

04/09/90 to 05/07/9004/16/90 to 05/07/9004/09/90 to 05/07/90

05/07/90 to 06/04/9005/14/90 to 06/04/90

05/07/9005/07/9005/07/9005/07/90

05/07/90 to 06/04/9005/14/90 to 06/04/9005/07/90 to 06/04/90

< 0.6< 0.7< 0.7< 0.7< 0.7< 1.0< 1.7< 0.6< 0.6

< 0.40.6 + 0.3< 0.7< 0.7< 0.7< 0.9

0.8 + 0.61.1 + 0.4< 0.4

2.8 + 0.94.1 + 0.91.4 + 0.71.7 + 0.72.6 + 0.73.2 + 0.88.6 + 1.12.1 + 0.91.8 + 0.8

1.8 + 0.8< 1.2

1.5 + 0.82.8 + 0.93.0 + 0.94.5 + 1.05.8 + 1.02.1 + 0.81.7 + 0.8

< 118< 61< 62

196 + 74356 + 79

< 116< 112

< 79< 76< 111-< 121< 119< 113

8418 + 129< 81< 71

(13)

(1,13)

(8,9)(8,9)(8,9)(8 9)(8,9)(8,9)(1,8,9)(8,9)(8,9)

6S65S81D312F112G2LTAW6S76S512Hl

06/04/90 to 07/09/90 < 1.2 3.9 + 1.606/ll/09 to 07/09/90 < 1.2 < 2.3

06/04/90 0.5 + 0.3 1.4 + 0.806/04/90 < 0.4 1.0 + 0.806/04/90 1.7 + 0.5 4.3 + 0.9

112 + 79< 61< 77< 73< 92

(2,10,12)(10)(10)(10)(10)

06/04/90 1.2 + 0.5 2.4 + 0.8 < 7206/04/90 to 07/09/90 < 2.1 7.9 + 1.8 4706 + 87

(10)(1,10)

06/11/90 to 07/09/90 < 1.2 < 2.3 118 + 87 (10)06/04/90 to 07/09/90 < 1.2 2.9 + 1.5 < 62 (12)

&&&&WWWWWWWKWWWWWWWH&&&W~~WWWWWW&WW&WWWWWWW&&WWWW&WW&&WW&WWWW~~~~~~~~~++W

gamaa eeirrers detected are reporred: typical Li.D values are foun able 21.

,,GROSS ALPHA, GROSS BETA, TRITIUM, AND



Page f 5

LOCATION

6S65S81D3.12Fl12G2LTAW6S76S512Hl

6S66S6(G)6S6(G)6S6(G)5S81D312Fl12G2LTAW6S76S512Hl

COLLECTION DATE

07/09/90 to 08/06/9007/16/90 to 08/06/90

07/09/9007/09/9007/09/9007/09/90

07/09/90 to 08/06/9007/16/90 to 08/06/9007/09/90 to 08/06/90

08/06/90 to 08/20/9008/27/9008/30/9009/04/90

08/13/90 to 09/04/9008/06/9008/06/9008/07/9008/06/90

08/06/90 to 09/04/9008/13/90 to 09/04/9008/06/90 to 09/04/90

GROSS ALPHA

< 1.4< 1.4< 1.2< 1.2< 1.2< 1.3< 2.3< 1.4< 1.4

< 1.1< 1.1< 1.1< 1.1< 1.1< 1.4< 1.4< 1.4< 1.1< 2.2

1.2 + 0.8< 1.1

GROSS BETA

2.6 + 1.53.4 + 1.56.3 + 1.73.8 + 1.6

< 2.32.2 + 1.56.7 + 1.73.6 + 1.55.3 + 1.6

4.1 + 1.52.1 + 1.44.3 + 1.54.2 + 1.55.1 + 1.53.1 + 1.5

< 2.36.7 + 1.7

< 2.811.0 + 1.8

5.8 + 1.65.3 + 1.6

H-3 (7)

356 + 115< 56< 59< 63< 58

216 + 1042522 + 120

486 + 82305 + 82

1412 + 201< 170

264 + ill< 128

582 + 66765 + 81655 + 135198 + 67333 + 94287 + 59191 + 125584 + 137

COMMENTS

(8,9,10)(8,9,10)(10)(10)(10)(10)

(1,8,9,10)(8;9,10)(8,9,10)

(8,9)(8,9)(8,9)(8,9)(4)

* Only gaana emitters detected are reported> typical U.D values are found ln Table 21.

TABLE 7

GROSS ALPHA, GROSS BETA, TRITIUM, ANDGAMMA+ SPECTROSCOPIC ANALYSES OF SURFACE VATER

SUSQUEHANNA STEAM ELECTRIC STATION - 1990Results in pCi/1 + 2s

Page 4 of 5


6S66S6(G)5S81D312F112G2LTAW6S76S512H1

6S66S6(G)5S81D312F112G2LTAW6S76S512H1

09/04/90 to 10/08/9010/01/90

09/10/90 to 10/08/9009/04/9009/04/9009/04/9009/04/90

09/04/90 to 10/08/9009/10/90 to 10/08/9009/04/90 to 10/08/90

10/08/90 to 11/05/9010/08/90

10/15/90 to ll/05/9010/08/9010/08/9010/08/9010/08/90

10/08/90 to ll/05/9010/15/90 to ll/05/9010/08/90 to 11/05/90

< 1.4< 1.4< 1.4< 1.1< 1.1< 1.1< 1.2< 1.8< 1.4< 1.4

1.3 + 0.9< 1.4

2.6 + 1.3< 1.4< 1.4< 1.4< 1.5

1.4 + 1.2< 1.3< 1.3

4.1 + 1.8< 2.6< 2.7

4.2 + 1.5< 2.6

3.3 + 1.7< 2.6

2.7 + 1.7< 2.7< 2.6

4.7 + 1.7< 2.6

14.2 + 2.1< 2.6< 2.6< 2.6

3.7 + 1.613.0 + 2.2

3.4 + 1.82.8 + 1.8

639 + 871096 + 921135 + 66

765 + 81163 + 74

2182 + 105875 + 76

5597 + 1755314 + 1243923 + 131

67 + 51592 + 50121 + 81

3985 + 1193880, + 114

247 + 125284 + 128281 + 46

< 8899 + 82

(8)

(8,9)(8,9)(8,9)(8,9,11)(1)

(4,6)

(4)

6S65S81D312F112G2LTAW6S76S5

Hl

11/05/90 to 12/03/90ll/12/90 to 12/03/90

11/05/9011/05/9011/05/9011/05/90

ll/05/90 to 12/03/90ll/12/90 to 12/03/90ll/05/90 to 12/03/90

WWWW\WWW\WWWWWW\WWWWWWWW~WW

Sanma emLrrers derecred are reported; ryp1ca1

1.0 < 2.7< 1.0 < 2.7< 1.4 2.7 + 1.6

< 119< 117

213 + 42(4)

< 1.2 < 2.8 < 136< 1.2 < 2.8 < 100< 1.3 < 2.8 99 + 90< 1.1 < 2.7 984 + 119 (6)< 1.0 < 2.7 < 118< 1.0 < 2.7 < 117

Mu&WWW&&ww&&WW&&&&wwW&&W&ww~w&www&WW&m&W&W C" QM

LLD values are fou b1e 21.

Page f 5




'6S65S81D312F112G2LTAW6S76S512H1

12/03/90 to 12/31/9012/10/90 to 12/31/90

12/03/9012/03/9012/03/9012/03/90

12/03/90 to 12/31/9012/10/90 to 12/31/9012/03/90 to 12/31/90

< 0.9< 1.0< 1.0< 1.0< 1.0< 1.2< 0.9< 0.9

< 2.4< 2.4

3.4 + 1.86.3 + 1.9

< 2.7< 2.7< 2.4

2.9 + 1.5

62 + 74180 + 73

< 117< 118< 121< 118

356 + 86346 + 145

(13)

* Only gaama emltters detected are reported< typical LLD values are found ln Table 21.

COMMENTSl.'he automatic composi,te sampler(ACS), sample collection container vas overfloving.2. No vater vas running through the ACS 06/11/90> corrected 06/18/90. About 4 gallons accumulated in the sample collection tank 06/11/90.3. On 07/04/90 the ACS vas dovng pump pressure restored 07/05/90.4. A large volume of vater vas found in the sample collection container.5. The ACS vas pumping 0 ml./stroke 10/15,22,29/90. The ACS vas repaired 10/31/90.6. On 11/12/90 at 1008 the ACS pump vent dovn. Pump vas restored 11/08/90. On 11/19/90 the REHP side vas pumping 0 ml/stroke.7. Less-thans (<), for H-3 correspond to critical levels. (LLDs vould be tvice these values)8. Technical Specification LLD vas not reported for La-140. „9. Technical Specification LLD for Ba-140 vas exceeded.10. Technical Specification LLD for Ba-140 and La-140 vas exceeded.ll. Technical Specification LLD for Pe-59 vas exceeded.12. Technical Specification LLD for Nb-95 vas exceeded.13. Sample vas inadvertently discarded at sample laboratory.

of 3


GAMMA SPECTROSCOPIC ANALYSES OF DRINKING MATER


LOCATION COLLECTION DATE

12H2R Ol/02/90 to Ol/22/9012H2R (G) 02/05/9012H2R (G) 01/29/9012H2T 01/02/90 to 02/05/90

GROSS

ALPHA

< 2.0< 2.0< 2.0< 2.0

GROSS

BETA

1.7 + 0.88.0 + 1.24.9 + 1.01.8 + 0.8

H-3

< 80< 70< 80

93 + 43

COMMENTS

12H2R (G)12H2R (G)12H2R12H2T

12H2R12H2T

12H2R12H2T

12H2R1'2H2T

02/12/9002/20/90

02/21/90 to 03/09/9002/05/90 to 03/05/90

03/05/90 to 04/09/9003/05/90 to 04/09/90

04/09/90 to 05/07/9004/09/90 to 05/07/90

05/07/90 to 06/04/9005/07/90 to 06/04/90

< 0.50.8 + 0.4

< 0.6< 0.6

< 0.4< 0.4

< 0.6< 0.6

< 1.4< 1.4

< 1.62.9 + 1.1

< 1.62.3 + 1.0

< 1.21.2 + 0.7

< 1.4< 1.4

< 2.6< 2.6

< 123< 136< 129< 121

< 112< 114

< 108215 + 127

< 82< 77

2,4.3,4

12H2R 06/04/90 to 06/25/90 1.1 < 2.612H2R (G) 07/02/90 <12 . <3412H2R (G) 07/09/90 < 1.1 < 3.412H2T 06/04/90 to 07/09/90 < 1.1 < 2.6

< 71< 61< 74< 65

6

6,87,97

~mmmwmmmm~mwmoemm~mmmmmmmmmmmmmmmwmmmmwwmmmmmmmwmmwm~mmmm~mmm~mmm~mmmmmmmmmwmmwmma~w&

* Only detected galena emltters are reported: typical LLD values are found ln Table 21.


GAMMA'PECTROSCOPIC ANALYSES OF DRINKING RATERSUSQUEHANNA STEAM ELECTRIC STATION - 1990


LOCATION

12H2R12H2R (G)12H2R (G)12H2T

12H2R (G)12H2R (G)12H2R12H2T

12H2R12H2R (G)12H2R (G)12H2R (G)12H2T

12H2R (G)12H2R (G)12H2R (G)12H2R12H2T

COLLECTION DATE

07/09/90 to 07/30/9007/30/9008/06/90

07/09/90 to 08/06/90

08/13/9008/20/90

08/23/90 to 09/04/9008/06/90 to 09/04/90

09/04/90 to 09/24/9009/24/9010/01/9010/08/90

09/04/90 to 10/08/90

10/15/9010/22/9010/29/90

10/29/90 to 11/05/9010/08/90 to ll/05/90

GROSS

ALPHA

< 1.7< 1.7< 1.7< 1.8

< 1.0< 0.9< 1.0< 1.0

< 1.4< 1.4< 1.3< 1.4< 1.5

< 1.3< 1.4< 1.3< 1.4< 1.5

GROSS

BETA

< 3.9< 3.9< 3.9< 3.9

< 2.1< 2.1< 2.1< 2.1

3.4 + 1.01.8 + 1.01.9 + 1.01.9 + 1.02.6 + 1 ~ 0

< 2.43.5 + 1.6

< 2.4< 2.4< 2.4

H-3

< 71< 68< 72

137 + 75

97 + 76242 + 76121 + 75

< 64

102 + 78< 77< 62

166 + 77< 64

209 + 77< 62< 61

128 + 91112 + 71

COMMENTS

104,115

24

4,11

5,13

12H2R (G)12H2R (G)12H2R (G)

11/12/9011/19/9011/26/90

< 1.2 3.3 + 1.6 110 + 81 4< 1.2 < 2.3 264 + 80 4< 1.2 2.2 + 1.5 — 338 + 83 5

* Ouly detected gaaana emltters are reported; typical LLD values are fouud in Table 21.

of 3

TABLE 8

GROSS ALPHA, GROSS BETA, TRITIUM, ANDGAMMA SPECTROSCOPIC ANALYSES OF DRINKING WATER


LOCATION COLLECTION DATEGROSS

ALPHAGROSS

BETA H-3 COMMENTS

12H2R (G)12H2T

12/03/90ll/05/90 to 12/03/90

< 1.2< 1.4

4.6 + 1.64.4 + 1.6

< 110121 + 77 14

12H2R (G)12H2R (G)12H2R12H2R (G)12H2T

12/10/9012/17/90

12/17/90 to 12/26/9012/31/90

12/03/90 to 12/31/90

< 1.1<'1.2< 0.9

1.2< 0.9

< 2.54.5 + 1.5

< 2.46.4 + 1.73.3 + 1.6

155 + 75189 + 80100 + 76

< 60< 58

15

16

* Only detected gssssa emitters are reportedl typical LLD values are found in Table 21.

COMMENTS1. No vater floved through the sampler on 01/22/90 ~

2. No vater floved through the sampler, but 1 gal. of vater vas found in the collection container on 02/12/90.3. Sample pump turned off> pump had been restarted on 02/16/90.4. Technical specifications LLD exceeded for Ba-140 and La-140 because of a long decay time betveen laboratory sample receipt and count

dates.5. Technical specifications LLD exceeded or LLD not reported because of a long decay time betveen labratory sample receipt and count dates.6. Technical specifications LLD exceeded for Fe-59, Nb-9S, Ba-140, and La-140 because of a long decay time betveen laboratory sample receipt

and count dates.7. Technical specifications LLD exceeded for Co-58, Fe-59, 2r-9S, Nb-95, Ba-140, and La-140 because of a long decay time betveen laboratory

sample receipt and count dates.8. Trim valve found closed by a plant operator on 06/27/90> valve vas left closed. Sample drain appeared to bs clogged.9. Mud vas flushed from the sampler.10. Sampling vas interrupted 0900 - 1230 vhlle DER installed a filter in the supply line to the sampler.11. Sample pump vas not operating 07/30/90 to 08/20/90, 10/29/90, and 11/05/90 to 12/17/90.12. Sample pump vas restarted on 08/23/90.13. Sample vas lost for the 09/04/90 to 09/10/90 sampling interval due to sample collector error.14. Sample vas short 1 day during the 11/05/90 to 11/12/90 sampling period.1S. Sample pump shutdovn due to a leak in the sample line.16. One day's sample vas lost during the 12/26/90 to 12/31/90 sampling period because of holiday observance.

Paelof 1

TABLE 9

GAMMA SPECTROSCOPIC ANALYSES OF ALGAE

SUSQUEHANNA STEAM ELECTRIC STATION - 1990Results in pCi/g (dry) + 2s

LOCATION

AG 3

AG 4

AG 3AG 4

AG 3x AG4I

g AG3AG 4

AG 3

AG 4

COLLECTION DATE

04/29/90 to 06/04/9004/29/90 to 06/04/90

06/04/90 to 07/09/9006/04/90 to 07/09/90

07/09/90 to 08/06/9007/09/90 to 08/06/90

08/06/90 to 09/04/9008/06/90 to 09/04/90

09/04/90 to 10/08/90

09/04/90 to 10/08/90

K-40

11.5 + 7.611.4 + 8.6

105.2 + 26.6

234.5 + 14.0

42.9 + 16.7

Be-7

1.8 + 0.41.8 + 0.5

11.8 + 6.0

9.3 + 3 '

10.3 + 5;3

I-131

9.9 + 5.8

8.4 + 5.3

Cs-137

0.15 + 0.060.15 + 0.06

OTHER

Mn-54: 0.13 + 0.06Mn-54: 0.13 + 0.06

Ra-226: 6.0 + 1.4Th-232: 4.2 + 1.3Co-60: 1.0 + 0.5Mn-54: 1.7 + 0.5

AG 3

AG 410/08/90 to ll/05/90 88.4 + 22.710/08/90 to ll/05/90 17.6 + 16.2

Ra-226: 4.5 + 2.3Ra-226: 3.1 + 1.8

* Only detected gscssa enltters are reported> typical LLD values are found ln Table 21.

of 1

TABLE 10GROSS BETA AND GAMMA SPECTROSCOPIC ANALYSES. OF FISH

SUSQUEHANNA STEAM ELECTRIC STATION - 1990Results in pCi/g (wet) + 2s

LOCATION SAMPLE TYPECOLLECTION

DATE GROSS BETA K-40

2H2H2H

Channel Catfish 04/25/90White Sucker 04/24/90Smallmouth Bass 04/24/90

2.4 + O.l 3.7 + 0.62.2 + O.l 3.0 + 1.52.2 + 0.1 3.1 + 1.6

INDINDIND

LTAWLTAW

2H2H2H

Channel Catfish 04/03/90White Sucker 06/05/90Smallmouth Bass 06/04/90

Channel Catfish 05/30/90Largemouth Bass 05/30/90

Channel Catfish ll/02/90White Sucker ll/01/90Smallmouth Bass ll/01/90

1.6 + 0.12.7 + 0.17.8 + 0.2

2.1 + 0.12,5 + 0.1

5.2 + 0.16.3 + 0.26.8 + 0.2

3.3 + 0.74.6 + 1.34.5 + 1.0

4.2 + 0.84.0 + 0.7

4.2 + 0.83.8 + 0.72.6 + 1.0

IND Channel Catfish ll/06/90IND White Sucker 11/05/90IND Smallmouth Bass 11/05/90

5.0 + 0.16.7 + 0.26.7 + 0.2

4.7 + 1.23.9 + 1.57.3 + 1.2

LTAW Largemouth Bass ll/07/90 8.1 + 0.2 10.8 + 0.6

Only detected gaaaaa ecsltters are reported> typical LLD values are found in Table 21.

TABLE 12GROSS ALPHA, GROSS BETA, TRITIUM AND

GAMMA" SPECTROSCOPIC ANALYSES OF GROUND (WELL) WATER


Page 1 of 3

LOCATION

12F32S64S24S411S512E4

2S64S24S411S512E412F3

COLLECTIONDATE

01/03/9001/03/90Ol/03/9001/03/9001/03/9001/03/90

02/06/9002/06/9002/06/9002/06/9002/05/9002/05/90

GROSS ALPHA

< 2.0< 1.0< 2.0< 1.0< 2.0-< 2.0

1.02.01.02.02.02.0

GROSS BETA

2.6 + 1.3< 1.0

2.0 + 1.31.9 + 1.0

< 2.02.0 + 1.2

< 1.01.6 + 1.02.7 + 0.91.7 + 0.91.9 + 0.92.3 + 1.0

H-3(1)

160 + 50140 + 60320 + 50140 + 50120 + 50170,+ 60

< 8093 + 4457 + 3499 + 52< 80

130 + 60

Mn-54

12F32S64S24S411S512E4

03/05/9003/06/9003/06/9003/06/9003/06/9003/05/90

1.20.91.61.00.61.3

+ 0.6+ 0.4+ 0.6+ 0.6+ 0.4+ 1.0

2.1 + 0 '1.3 + 0 '2.0 + 0 '1.5 + 0.91.2 + 0.91.7 + 0.9

< 112< 113< 115< 118< 120< 115

12F32S64S24S411S512E4

04/09/9004/09/9004/09/9004/09/9004/09/9004/09/90

< 0.9< 0.7< 1.2< 0.7< 1.2< 0.9

1.3 + 0.8< 1.2< 1.2< 1.2< 1.2< 1.2

< 107< 101< 105< 104< 86< 104

* Only detected kaama emltters are reported> typical LLD values are found ln Table 21.

O


GAMMA SPECTROSCOPIC ANALYSES OF GROUND (WELL) WATERSUSQUEHANNA STEAM ELECTRIC STATION - 1990


Page 3

LOCATIONCOLLECTION

DATE GROSS ALPHA GROSS BETA H-3(1) Mn-54

12F32S63S54S24S411S512E4

05/07/9005/07/9005/07/9005/07/9005/07/9005/08/9005/07/90

0.80.8+ 0.40.60.90.60.80.7

< 1.4< 1.4< 1.1< 1.4< 1.4< 1.4< 1.4

< 82< 86< 85< 86< 85

197 + 101< 83

8.1 + 8.0

12F3 (2)2S6 (2)3S5 (2)4S2 (2)4S4 (2)11S5 (2)12E4 (2)

12F3 (2,3)2S6 (2)3S5 (2)4S2 (2)4S4 (2,3)11S5 (2)12E4 (2,3)

12F3 (2,3)2S6 (2,3)3S5 (2,3)4S2 (2,3)4S4 (2,3)11S5 (2,3)12E4 (2,3)

06/04/9006/04/9006/04/9006/04/9006/04/9006/04/9006/04/90

07/09/9007/09/9007/09/9007/09/9007/09/9007/09/9007/09/90

08/06/9008/06/9008/06/9008/06/9008/06/9008/06/9008/06/90

0.6< 0.5< 0.4

1.2 + 0.6< 0.5< 0.6< 0.5

< 0.7< 0.6< 0.6

1.4 + 0.7< 1.5< 1.0< 0.7

< 1.12.4 + 0.9

< 1.51.4 + 0.9

< 1.0< 1.3

1.8 + 0.9

< 1.1< 1.1< 1.1< 1.1-< 1.1< 1.1< 1.1

1.3 + 0.8< 1.2

1.3 + 0.8< 1.2

2.5 + 0.8< 1.2< 1.2

< 2.4< 2.6< 2.4< 2.4< 2.4< 2.4< 2.6

164 + 76< 63

75 + 81378 + 81

83 + 7576 + 75

121 + 77

< 71< 68< 67< 69< 70< 68< 70

171 + 80< 68

235 + 81< 67< 68< 68< 66

3.8 + 2.7

* Only detected gasma emltters are reported: typical LLO values are found ln Table 21.

of 3

LOCATION


GAMMA SPECTROSCOPIC ANALYSES OF GROUND (MELL) VATERSUSQUEHANNA STEAM ELECTRIC STATION - 1990

GROSS ALPHA

Results in pCi/1 2sCOLLECTION

DATE GROSS BETA H-3(1) Mn-54

12F3'2,3)2S6 (2,3)3S5 (2,3)4S2 (2,3)4S4 (2,3)11S5 (2,3)12E4 (2,3)

12F3 (2,3)2S63S54S24S411S512E4 (2)

12F3 (2)2S6 (2)3S5 (2,3)4S2 (2)4S4 (2)11S5 -(2)12E4 (2)

09/04/9009/04/9009/04/9009/04/9009/04/9009/04/9009/04/90

10/08/9010/08/9010/08/9010/08/9010/08/9010/08/9010/08/90

11/05/9011/06/9011/05/9011/06/9011/06/9011/06/9011/05/90

< 0.8< 1.2< 0.7< 1 ~ 4< 0.7< 0.9< 1.3

< 1.5< 1.3< 1.3< 1.2< 1.3< 1.6< 1.5

1.6 + 1.0< 1.3< 1.3< 1.6< 1.4< 1.7< 1.5

< 2.3< 2.3< 2.3< 2.3< 2.3< 2.3< 2.3

< 2.72.7 + 1.53.0 + 1.52;8 + 1.53.1-+ 1.8

< 2.7< 2.7

< 3.2< 3.2< 3.2< 3.2< 3.2< 3.2< 3.2

< 68< 76< 66< 64

108 + 77< 69< 69

< 71102 + Sl

< 62< 71< 66

148 + 90108 + 73

185 + 82< 58

178 + 78131 + Sl

< 65206 + 78

79 + 75

3.9 + 4.5

2.8 + 1.42.5 + 1.42.2 + 1.43.1 + 1.43.3 + 1.44.7 + 1.5

12F3 12/03/90 < 1.12S6 12/03/90 < 0.94S2 12/03/90 < 1.24S4 12/04/90 < 1.011S5 12/04/90 < 1.212E4 12/03/90 1.5 + 0.9WWWWWM&MWWWW~WWWW~WWWWWWWW\WWWWWWW

nly derected gamna emitters are reported; typical. LLD values are fo = Table 21.ENTS

Less-than (<) values for 8-3 represenr. critical valuues eqivalent to alf the lover

< 61137 + 72

< 60< 63< 60< 60

limits of detection2. La-1CO LLD vas not reported because of a long decay time ( g La-140 half-lives) berwen laboratory sample receipt and sample count dates3. Ba-140 Technical Specification LLD exceeded because of long decay time betveen laboratory sample receipt and sample count dates.

-Page 1 of

TABLE 13GROSS BETA ANALYSES OF AIR PARTICULATE FILTERS

SUSQUEHANNA STEAM ELECTRIC STATION - 1990RESULTS IN E-03pCi/cubic meter

'MONTH COLLECTION DATE 7Gl 12G1 2S2 5S4 '1S2 15S4 9B1 1D2 3D1 12El

JAN 01/02/90 to Ol/09/9001/09/90 to Ol/16/9001/16/90 to Ol/23/90Ol/23/90 to Ol/30/90

201210

8

29131310

24 +14 +14 +11 +

23+213+213+213+2

23 +12 +15 +11 +

191210

9

23131311

22210

24 +12 +13 +ll +

24 + 2 23ll + 2 1310 + 2 109+2 10

FEB

OC

IMAR

01/30/90 to 02/06/9002/06/90 to 02/13/9002/13/90 to 02/20/9002/20/90 to 02/27/90

02/27/90 to 03/06/9003/06/90 to 03/13/9003/13/90 to 03/21/9003/21/90 to 03/27/90

81310

8

24211522

12141312

29271623

221"2

12 +16 +13 +10 +

26 +31 +16 +23 +

2 13+22 16+22 13+23(1)10 + 2(2)

28+230+216+123+2

12 +13 +12 +12 +

28 +24 +15 +19 +

2'

12

10141310

28281524

12141312

26321622

ll151312

29281624

29261621

+2 30+2 28+1 16+2 23

9+2 ll14 + 2 1412 + 2 1211 + 2 12

APR 03/27/90 to 04/03/9004/03/90 to 04/10/9004/10/90 to 04/17/9004/17/90 to 04/24/90

171822

10172023

10+ 116+1'21+ 126+ 2

10+ 115+121+ 126+ 2.

8+15 +20 +25 +

10171924

12172026

11161927

8141923

+1 10+1 15+1 21+2 25

MAY 04/24/90 to 05/01/9005/Ol/90 to 05/08/9005/08/90 to 05/15/9005/15/90 to 05/22/9005/22/90 to 05/29/90

151512

710

191817

8ll

20 +23 +16 +

7 +12 +

21+ 127+215+18+1

11+ 1

22 +23+15 +

7 +ll +

201815

7ll

232214

713

212116

814

202015

710

+ 1+ 1+1=+ 1+ 1

202216

812

JUN 05/29/9006/05/9006/12/9006/19/90

to 06/05/90to 06/12/90to 06/19/90to 06/26/90

10ll13ll

14182113

12 +13 +20 +12 +

11+ 114+ 118+ 112+ 1

12 +15 +19 +12 +

12131812

13+116+117+1

(4)

14151912

12 + 1 1210 + 1(3)1516 + 1 2210 + 1 13

TABLE 13GROSS BETA ANALYSES OF AIR PARTICULATE FILTERS

- SUSQUEHANNA STEAM ELECTRIC STATION - 1990RESULTS IN E-03pCi/cubic meter

Page 2 of

MONTH

2S2COLLECTION DATE 7G1 '2G1 (3S2) 5S4

11S2(12S2) 15S4 9B1 1D2 3D1 12E1

JUL

AUG

SEP

OCT

NOV

DEC

06/26/90 to 07/03/9007/03/90 to 07/10/9007/10/90 to 07/17/9007/17/90 to 07/24/9007/24/90 to 07/31/90

07/31/90 to 08/07/9008/07/90 to 08/14/9008/14/90 to 08/21/9008/21/90 to 08/28/90

08/28/90 to 09/05/90-09/05/90 to 09/11/9009/11/90 to 09/18/9009/18/90 to 09/25/9009/25/90 to 10/02/90

10/02/90 to 10/09/9010/09/90 to 10/16/9010/16/90 to 10/23/9010/23/90 to 10/30/90

10/30/90 to 11/06/9011/06/90 to ll/13/90ll/13/90 to ll/20/90-ll/20/90 to ll/27/90

ll/27/90 to 12/04/9012/04/90 to 12/11/9012/ll/90 to 12/18/90=12/18/90 to 12/26/9012/26/90 to 01/02/91

16+116+ 112+122+ 115+ 1

13+119+121+ 113+1

19+119+112+ 121+ 120+ 1

14+ 120+120+118+1

19+ 116+116+117+133+ 215+123+125+ 1

19+119+122+119+117+1

25+122+ 116+121+ 1

39+217+128+ 130+ 2

24+ 219+ 125+ 123+124+ 2

20 + 1 36 + 221 + 2 34 + 223 + 1 26 + 114 + l(5)15 + 127 + 2 27 + 1

17 +18 +14 +21 +18 +

1 171 181 101 231 '16

27 +29 +32 +

.29 +35 +

24 +21 +18 +2i +

36 +16 +24 +26 +

21 +21 +25 +21 +22 +

1 272 302(6) 282(7)152(8)34

2 251 221 191 21

2 351 171 241 29

1 221 221 241 211 24

16 + 1 1521 + 1 2024 + 1 . 2118 + 1 18

+ 1+ 1+ 1+ 1+ 1

+ 1+ 1+ 1+ 1

+ 1+ 2+ 2+ 1+ 2

+ 1+ 1+ 1+ 1

+ 2+ 1+ 1+ 2

+ 1+ 1+ 1+ 1+ 2

16+ 117+110+ 122+ 116+114+ 120+ 122+ 118+ 1

31+ 235+ 229+217+133+223+122+119+121+ 1

36+ 216+128 + 2(9)29 + 2(10)

22+ 120+ 124+ 121+ 125+ 2=

17 +16 +11 +22 +15 +

15 +19 +21 +15 +

23+126+227+113+127+121 +15 +16 +17 +

35 +14 +23 +24 +

20 +19 +23 +20 +23 +

18 +18 +12 +24 +17 +

14212418

30 +40 +28 +15 +34 +

22191822

361623 +27 +

2220232123

1818142418

16192317

3227291535

25211823

341724 +29 +

23222426

1 24

16 +17 +ll +20 +15 +

15 +14 +20 +16 +

22 +27 +25 +14 +29 +

21 +19 +17 +19 +

31 +16 +24 +26 +

1 20+11 20+1

21 +21 +20 +

1717122216

15+119+122+118+12833301629

25201923

36162527

2320252226

CONNE((TE(I) 21 0 I 102 N 2 I 2(21 (1020.1001). YII~ \ %) 0 I KI

'(2) Electricity vas out of service on 2/23 (0855-0930).(3) h hole vas found ln the air filter. Rubbish might have been burning near the air sampling station.(a) Data vas considered to be invalid due to the very lov sample volume recorded.(5) paint chips vere found on the air filter.

Air sample station at. 2$ 2 shutdovn 9/16/90.ir sample station 3S2 sampled period 9/16/90 through 9/21/90 and 9/ through 9/26/90. The resultsir sample station 3S2 sampled for the period 9/26/90 through 10/2/

Alr sample station 11S2 shutdovn 11/16/90.) Air sample station 12S2 started up 11/20/90.

for 9/16/90 through 9/21/90 vere

f 2

TABLE 14GROSS ALPHA AND GAMMA'PECTROSCOPIC ANALYSES OF COMPOSITED AIR PARTICULATE FILTERS

SUSQUEHANNA STEAM ELECTRIC STATION - 1990Results in E-03pCi/cubic meter + 2s

LOCATION

7G112G112El3Dl1D29B115S411S25S42S2

7Gl12G112El3D11D29Bl15S411S25S42S2

COLLECTION DATE

02/27/90 to 04/03/9002/27/90 to 04/03/9012/27/90 to 04/03/9002/27/90 to 04/03/9002/27/90 to 04/03/9002/27/90 to 04/03/9002/27/90 to 04/03/9002/27/90 to 04/03/9002/27/90 to 04/03/9002/27/90 to 04/03/90 .

04/03/90 to 07/03/9004/03/90 to 07/03/90-04/03/90 to 07/03/9004/03/90 to 07/03/9004/03/90 to 07/03/9004/03/90 to 07/03/9004/03/90"to 07/03/9004/03/90 to 07/03/9004/03/90 to 07/03/9004/03/90 to 07/03/90

GROSS ALPHA

0.9 + 0.40.8 + 0.20.5 + 0.10.7 + 0 '0.6 + 0.10.7 + 0.11.4 + 0.20.9 + 0.10.7 + 0.11.3 + 0.2

0.9 + 0.10.8 + 0.10.5 + 0.10.5 + 0.10.4 + 0.10.6 + 0.10.6 + 0.10.7 + O.l0.4 + 0.1

< 0.5

Be-7

220 + 60220 + 40220 + 40180 + 60210 + 40270 + 60240 + 70200 + 60

190 + 46060 + 2090 + 20

100 + 20210 + 40100 + 10130 + 30130 + 20100 + 20

90 + 20

K-40

1320 + 1201040 + 40

470 + 7701890 + 150

130 + 120

140 + 120

770 + 2901240 + 110

410 + 70

1960 + 160

160 + 70WWWWWW~~W~WWWWW~WWWWWW~~&www~&&\W&Wwww&W\WW~W~W&&WWWWWWWWW&w&W~~MWW~W&~~~

taaraa eeitters are reported: typical LLD values are found ln Table 21.* Only detected

of 2

TABLE 14GROSS ALPHA AND GAMMA SPECTROSCOPIC ANALYSES OF COMPOSITED AIR PARTICULATE FILTERS

SUSQUEHANNA STEAM ELECTRIC STATION - 1990Results in E-03pCi/cubic meter + 2s

LOCATION COLLECTION DATE GROSS ALPHA Be-7 K-40

7G112G112El3D11D29B115S411S25S42S23S2

7G112Gl12El3D11D29B115S411S25S4(1)3S212S2

07/03/90 to 10/02/9007/03/90 to 10/02/9007/03/90 to 10/02/9007/03/90 to 10/02/9007/03/90 to 10/02/9007/03/90 to 10/02/9007/03/90 to 10/02/9007/03/90 to 10/02/9007/03/90 to 10/02/9007/03/90 to 10/02/9007/03/90 to 10/02/90

10/02/90 to 01/02/9110/02/90 to Ol/02/9110/02/90 to Ol/02/9110/02/90 to Ol/02/9110/02/90 to 01/02/9110/02/90 to Ol/02/9110/02/90 to 01/02/9110/02/90 to Ol/02/9110/02/90 to Ol/02/9110/02/90 to 01/02/9110/02/90 to 01/02/91

2.8 + 0.22.8 + 0.22.8 + 0.21.3 + 0.11.7 + 0.22.4 + 0.22.3 + 0.21.9 + 0.23.9 + 0.22.4 + 0.24.5 + 0.9

2.2 + 0.21.8 + 0.21.0 + O.l1.7 + 0.22.4 + 0.21.1 + 0.12.3 + 0.21.5 + 0.21.6 + 0.22.1 + 0.21.3 + 0.2

60 + 3249 + 2857 + 3049 + 18

< LLD71 +

35'8

+ 2958 + 2141 + 1883 + 38

57 + 1253+853+957+854+ 953+ 1345+930 + 1750 + 1062+968 + 23

~~wwwmww~ww~ww~ww&www&~wwwwWwW&WWWWW&W~~WWM~~WWWW~WWWWW&&WM~WWWWW&WWMW* Only detectedCOMMENTS1. Manganese-Sa

6aaraa emltters are reported; typical LLD values are found in Table 21.

uas reported in this composite sample at an activity level of 8.6 s S.7E-04 pCiim'.

of 2

GROSS ALPHA, GROSS

TABLE 15BETA, TRITIUM, AND GAMMA'PECTROSCOPIC ANALYSES OF PRECIPITATION


LOCATION

7G112G1(2)2S258411S215S49B11D23Dl12E1

2S25S411S215S49Bl1D23Dl12El7G112Gl

COLLECTION PERIOD

01/02/90 to 04/03/90Ol/02/90 to 04/03/90Ol/02/90 to 04/03/9001/02/90 to 04/03/9001/02/90 to 04/03/9001/02/90 to 04/03/9001/02/90 to 04/03/9001/02/90 to 04/03/9001/02/90 to 04/03/90Ol/02/90 to 04/03/90

04/03/90 to 07/03/9004/03/90 to 07/03/9004/03/90 to 07/03/9004/03/90 to 07/03/9004/03/90 to 07/03/9004/03/90 to 07/03/9004/03/90 to 07/03/9004/03/90 to 07/03/9004/03/90 to 07/03/9004/03/90 to 07/03/90

GROSS ALPHA

< 0.5

0.50.50.50.50.50.50.50.5

0.60.60.70.70.6.0.61.30.60.60.6

GROSS BETA

2.5 + 0.8

5.3 + 0.96.1 + 0.95.2 + 0.95.9 + 0.96.1 + 0.95.2 + 0.94.0 + 0.84.1 + 0.8

4.8 + 0.94.2 + 0.95.6 + 0.95.2 + 0.95.3 + 0.93.0 + 0.84.8 + 1.64.5 + 0.92.7 + 0.8'5.0 + 0.9

H-3(1)

128 + 149

< 118< 125

420 + 242< 124< 122< 122< 124

481 + 223

< 60760 + 80259 + 78

< 68< 64

120 + 79< 64

768 + 75955 + 84168 + 76

* Only detected guava emltters are reported> typical LLD values are found in Table 21.

of 2

TABLE 15

GROSS ALPHA, GROSS BETA, TRITIUM, AND GAMMA'PECTROSCOPIC ANALYSES OF PRECIPITATIONSUSQUEHANNA STEAM ELECTRIC STATION - 1990


LOCATION COLLECTION PERIOD GROSS ALPHA GROSS BETA H-3

7Gl12G12S25S411S215S49B1lD23D112E1

7G112G13S25S411S215S49Bl1D23D112El12S2

07/03/90 to 10/02/9007/03/90 to 10/02/9007/03/90 to 09/21/9007/03/90 to 10/02/9007/03/90 to 10/02/9007/03/90 to 10/02/9007/03/90 to 10/02/9007/03/90 to 10/02/9007/03/90 to 10/02/9007/03/90 to 10/02/90

10/02/90 to 01/02/9110/02/90 to 01/02/9110/02/90 to 01/02/9110/02/90 to 01/02/9110/02/90 to ll/16/9010/02/90 to Ol/02/9110/02/90 to 01/02/9110/02/90 to Ol/02/9110/02/90 to 01/02/9110/02/90"to 01/02/91ll/16/90 to 01/02/91

< 1.5< 1.5< 1.5< 1.5< 1.5< 1.5< 1.5< 1.8< 1.5< 1.5

< 1.0< 0.9< 1.2< 0.9< 1.0< 0.9< 0.9< 0.9

1.9 + 0.8< 0.9< 0.9

< 3.1< 3.1< 3.1< 3.1< 3.1< 3.1< 3.1< 3.1< 3.1< 3.1

4.1 + 1.55.4 + 1.74.6 + 1.63.6 + 1.6

< 2 '5.8 + 1.73.8 + 1.64.9 + 1.76.2 + 1.73.9 + 1.64.2 + 1.6

< 60196 + 63140 + 84178 + 82269 + 64

61 + 69< 48< 68.< 52< 69

< 67< 67< 64< 68< 69< 70< 65< 67< 69< 69

99 + 76WWW~WWWW~WOSWWIW&~WWW~&WWWM~&W~WW~~W~WWW&&&WW~W&&WMW&&WW~WW~WWWW~&WWWW* Only detected Sasrsa emltters are reported: typical LLD values are found in Table 21.COMMENTSl. Less-thans (<), for 8-3 represent critical levels equivalent to one-half M)CS.2. Sample uas lost during shipment to radloanalytical laboratory.

of 7

TABLE 16GROSS BETA MINUS K-40, I-131, AND

GAMMA SPECTROSCOPIC ANALYSES OF MILKSUSQUEHANNA STEAM ELECTRIC STATION - 1990


COLLECTIONLOC. DATE

GROSS BETAMINUS K-40 K-40 Sr-89 Sr-90 OTHER

10G112B29D313E310D114B112B38D412D2

01/02/9001/02/9001/02/9001/02/9001/02/9001/02/9001/02/9001/02/9001/02/90

12.0 + 2.04.0 + 1.65.2 + 1.75.9 + 1.78.0 + 1.88.8 + 2.0

14.0 + 2.03,3 + 1.63.3 + 1.6

1240 + 1201420 + 1401310 + 1301430 + 140

. 1390 + 1401310 + 1301110 + 1101320 + 1301250 + 120

Cs-137: 4.1 + 3.8Cs-137: 4.9 + 3.2

Cs-137: 4.4 + 4.4

10G112B29D313E310D114B112B38D412D2

02/05/9002/05/9002/05/9002/05/9002/05/9002/05/9002/05/9002/05/9002/05/90

'.35.55.43.96.64 '

11.05.42.5

+ 1.9+ 1.8.+ 1.8+ 1.7+ 1.8+ 1.8+ 2.0+ 1.8+ 1.6

115013801170138014001300120012801230

+ 120+ 140+ 120+ 140+ 140+ 130+ 120+ 130+ 120

Cs-137: 3.8 + 3.1

Cs-137: 3.2 + 3.3

WWW~\WW&WWWW~&WW~WWW~WmmmmWWW~WWWWW\m&Ww&WWWWWMWMWWWW

* Only detected gasraa emltters are reported'ypical LLD values are found in Table 21.




Page 4 Of 7

LOC.

10G112B29D313E310D114B1

10G112B29D313E310D114B112B38D412D2

COLLECTIONDATE

06/18/9006/17/9006/18/9006/17/9006/18/9006/17/90

07/05/9007/05/9007/05/9007/05/9007/05/9007/05/9007/06/9007/05/9007/05/90

K-40

1399 + 2801123 + 179

588 + 218725 + 217666 + 239

1164 + 124

1240 + 1821367 + 282

635 + 2431410 + 142

782 + 2201248 + 1231166 + 1831697 + 284

763 + 241

Sr-89 Sr-90.

0.8 + 0.64.0 + 3.04.6 + 2.8

12.8 + 4.73.7 + 0.6

1.7 + 0.5

1.2 +1.1'.0

+ 0.4

3.2 + 0.55.1 + 2.92.1 + 2.1

OTHER

10G112B29D313E310D114Bl

07/23/9007/23/9007/23/9007/23/9007/23/9007/23/90

737 + 2441404 + 184

808 + 2211473 + 1421480 + 278

893 + 222

8.3 +1.6 +2.3 +1.7 +4.7 +3.3 +

0.80.60.60.60.80.7

* Only detected kaama emitters are reported'ypical LLD values are found in Table 21.




Fage 5 .Of 7

LOC.

10G112B29D313E310D114B112B38D412D2

OC

10G112B29D313E310D114B1

10G112B29D313E310D114B112B38D412D2

COLLECTIONDATE

08/06/9008/06/9008/06/9008/06/9008/06/9008/06/9008/06/9008/06/9008/06/90

08/20/9008/20/9008/20/9008/20/9008/20/9008/20/90

09/04/9009/04/9009/04/9009/04/9009/04/9009/04/9009/04/9009/04/9009/04/90

K-40N

1252 + 123755 + 218

1448 + 1431276 + 181

879 + 2241320 + 278

587 + 219828 + 244

1168 + 181

6819 + 52910080 + 700

592 + 2194960 + 1183216 + 3283903 + 80

3223 + 3413884 + ill

520 + 2555095 + 1656854 + 5469567 + 724

< 5921438 + 529

413 + 255

Sr-89 Sr-90

3 ' + 1.0

0.7 + 0.71.3 + 0.71.1 + 0.72.9 + 0.83.5 + 0.7

1.2 + 0.7

2.7 + 0.61.5 + 0.7

< 0.82.4 + 0.93.0 + 0.62.9 + 0.6

1.9 + 0.6

2.9 + 1.21.6 + 1.41.9 + 0.6

5.1 + 1.9

OTHER

&~WW~WWWW~W~WWWW~WWWWW&W~WWWWWWIW~&W&W~~W\MWM~M~~WW&WWWWWWWW~W~WW~WWWWWWWW&WWW~~~~~~values are found ln Table 21 ~gaaana emltters are reported; typical LLD* Only detected


GAMMA'PECTROSCOPIC ANALYSES OF MILKSUSQUEHANNA STEAM ELECTRIC STATION - 1990


Page 6 Of 7

LOC.

10G112B29D313E310D114B1

10G19D313E3 .

10D114Bl12B38D412D210D3

10G110D39D313E310D114Bl

COLLECTIONDATE

09/17/9009/17/9009/17/9009/17/9009/17/9009/17/90

10/01/9010/01/9010/01/9010/01/9010/01/9010/01/9010/01/9010/Ol/9010/01/90

10/15/9010/15/9010/15/9010/15/9010/15/9010/15/90

K-40

345 + 2071304 + 164

833 + 1951448 + 133

821 + 256872 + 200

848 + 1971497 + 146

885 + 2732999 + 2972581 + 971124 + 1641366 + 134

685 + 2501369 + 229

1319 '+ 2132858 + 299

686 + 198908 + 253

1152 + 158525 + 197

Sr-89

1.8 + 1.5

Sr-90

2.4 + 0.6

1.7 + 0.6

3.8 + 0.92.7 + 1.23.1 + 1.03.1 + 0.91.8 + 0.63.3 + 1.01.2 + 1.32.6 + 1.26.4 + 1.0

4.5 + 1.3

OTHER

Zn-65: 8.5 + 6.0

* OnLy detected gassua eeltters are reported'yplcaL LLD values are Sound ln Table 2L.

7


GAMMA'PECTROSCOPIC ANALYSES OF MILKSUSQUEHANNA STEAM ELECTRIC STATION - 1990

Results in pCi/1 + 2s .

LOC.COLLECTION

DATE K-40 Sr-89 Sr-90 OTHER

10G110D39D313E310D114B112B38D412D2

11/05/9011/05/9011/05/90ll/05/9011/05/9011/05/9011/05/9011/05/9011/05/90

2379 + 931209 + 2101574 + 239

871 + 1991148 + 1602704 + 2971617 + 215

680 + 249757 + 200

1.1+ 0 ~ 51.8 + 0.5

0.8 + 0.71.4 + 0.8

2.0 + 0.8

1.8 + 0.8 Cs-137: 4.3 + 3.0

10G110D39D313E310D114Bl12B38D412D2

12/03/9012/03/9012/03/9012/03/9012/03/9012/03/9012/03/9012/03/9012/03/90

1390 + 1681133 + 2031600 + 224

582 + 2033443 + 3131297 + 1342591 + 101

665 + 202705 + 262

2.3 + 0.8 2.2 + 0.7

1.8 + 0.6

2.0 + 0.6

Only detected ganaa emltters are reported'ypicaL LLD values are found ln Table 21.

3. Technical Specificationscount date.Technical Specifications

LLD vas exceeded

LLD vas exceeded

COMMENTS1. Tcchnical Speclflcatlons LLD vas exceeded

recovery obtained.2. La-140 LLD vas not reported due to a long

for the T-131 analyses because of relatively small alhquot analyted and relatively lov chemical

decay time betvecn. laboratory sample receipt date and sample count date.for Ba-140 analysis because of a long decay tice betveen laboratory sample receipt date and sample

for 1-131 analysis because of lov counting efficiencies.

of 1

TABLE 17GAMMA SPECTROSCOPIC ANALYSES OF SOIL

SVSQVEHANNA STEAM ELECTRIC STATION - 1990Results in pCi/g (dry) + 2s

OC

IGJ

LOCATION

7G1 - TOP

7G1 - BOT

12G3 - TOP12G3 - BOT

3S7 - TOP

3S7. - BOT

5S5 - TOP5S5 - BOT

11S4 - TOP11S4 - BOT

15S4 - TOP

15S4 - BOT

9B2 - TOP

9B2 - BOT

1D4 - TOP

1D4 - BOT

3D2 - TOP

3D2 - BOT

12E2 - TOP

12E2 - BOT

AREA 1 - TOP

AREA 1 - BOT

AREA 2 - TOP

AREA 2 - BOT

AREA 3 - TOP

AREA 3 - BOT

SAMPLINGDATE

09/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/90

08/29/9008/29/9008/29/9008/29/9008/29/9008/29/90

K-40

14.419.411.610.816.514.612.410.410.511.523.223.215.8

9.711.811.59.6

20.913.612.9

0.91.00.71.20.90.80.91.01.00.81.30.60.51.01.10.91.31.30.91.0

24.1 + 1.532.7 + 1.97.1 + 0.6

15.3 + 0.315.9 + 0.510.2 + 0.7

Cs-137

0.28 + 0.030.42 + 0.040.20 + 0.030.10 + 0.040.08 + 0.030.06 + 0.020.12 + 0.030.15 + 0.040.27 + 0.040.17 + 0.030.08 + 0.030.10 + 0.020.67 + 0.030.64 + 0.040.06 + 0.03

< 310.67 + 0.060.49 + 0.040.16 + 0.030 '2 + 0.03

0.33 + 0.040.26 + 0.020.33 + 0.020.26 + 0.02.0.24 + 0.02

Ra-226

0.09 + 0.101.00 + 0.100.90 + 0.081.00 + 0.120.72 + 0.090.84 + 0.080.62 + 0.090.74 + 0 '00.57 + O.ll0.69 + 0.081.10 + O.ll1.10 + 0.060.74 + 0.050.59 + 0.090.88 + 0.120.70 + 0.090.68 + 0.131.00 + 0.120.84 + 0.090.78 + 0.08

0.84 + 0.11

Th-232

1.00 + 0.121.30 + 0.121.10 + 0.101.20 + 0.171.00 + 0.141.04 + 0.100.88 + O.ll0.95 + 0.140.85 + 0.120 '7 + 0.101.10 + 0.101.50 + 0.080.08 + 0.070.67 + 0.141.00 + 0.140.84 + 0.121.00 + 0.181.20 + 0.140.98 + 0.111.00 + O.ll

1.04 + 0.10

Mn-54

0.02 + 0.01

~~~~~mw~w&&WWWW&W&w&w\w&WWWWWWWW&WWWwwW&WWW&WWMIw\WWwMW&WWWW&&WW~WW&WW&w&w&W&WW&WW&wWWWWWWWWWWWWWWWWW&HWWHW&WWmm&WW

Only ed gasIaa emfrters are reporred: typical LLD values're found in Tabl

of 1

TABLE 18GAMMA SPECTROSCOPIC ANALYSES OF VEGETATION


LOCATION

7G112G33S75S511S415S49B21D43D212E2

COLLECTIONDATE

09/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/9009/28/90

Be-7

1.5 + 0.51.2 + 0.40.8 + 0.22.4 + 0.41.1 + 0.41.4 + 0.40.9 + 0.31.0 + 5.7

1.4 + 0.3

K-40

24.9 + 2.57.2 + 1.3

12.7 + 0.819.7 + 2.26.1 + 1.43.9 + 1.65.0 + 1.02.6 + 2.3

11.6 + 2.115.4 + 0.9

Ra-226

0.5 + 0.2

0.2 + 0.10.5 + 0.2

0.2 + O.l

Th-232

0.3 + 0.1-

0.2 + 0.1

* Ouly detected Csaxsa emltters are reported> typical LLD values are found lu Table 20.

of 2

TABLE 19GAMMA SPECTROSCOPIC ANALYSES OF FOOD PRODUCTS

SUSQUEHANNA STEAM ELECTRIC STATION - 1990Results in pCi/g, (wet) + 2s

LOCATION SAMPLE TYPE SAMPLE DATE K-40 LOCATION SAMPLE TYPE SAMPLE DATE K-40

2H1 (1)2Hl13E413E412B112B17B2 (1)7B2

12F4

Cortland AppleMcIntosh AppleRed Delicious AppleMcIntosh AppleRed Delicious AppleMcIntosh AppleCortland AppleMcIntosh Apple

Jerusalem Artichoke

10/28/9010/28/9010/29/9010/29/9010/29/9010/29/9010/29/9010/29/90

11/02/90

11.70 + 1.567.45 + 0.58

23.34 + 0.91< 1.47

0.73 + 0.66< 2.06< 1.71< 1.37

4.06 + 0.74

2H19D211D116F29D2

-2H111D19D210F114B12F47F1

(1)

(1)=

(1)

(1)(1)

Green BeanYellow BeanGreen BeanGreen BeanGreen Bean

Red BeetRed -BeetRed BeetRed BeetRed BeetRed BeetRed Beet

08/20/9007/23/9007/23/9009/04/9011/27/90

08/20/9007/23/9007/23/9008/07/9008/27/9009/16/9009/17/90

10.68 + 0.36< 1.46

2.14 + 0.8434.53 + 2.922.01 + 1.00

2.58 + 1.025.74 + 1.092.70 + 0.911.82 + 0.82

16.81 + 0.585.02 + 0.784 '3 + 0.88

11F1 (1)

2Hl9D2llD110F27F1

Blueberries

CabbageCabbageCabbageCabbageCabbage

07/23/90

08/20/9007/23/9009/04/9009/10/9009/17/90

1.39 + 1.05

17.28 + 0.651.18 + 0.18

25.08 + 0.9023.97 + 0.90

1.26 + 0.96

14B Canteloupe 08/27/90 40.38 + 3.0011D1 Canteloupe 09/04/90 15.19 + 0.52

WWW&W WWWWWWWWW&WW&WWWWWWWW&W&&\WWW&WWWWWWWW&WW&W&W&&W

~ On l red rafnaa emlrrers are reporred: ryplcal LLD values are found ln Ta

15B12F4

9D27Fl12B1

2Hl11D110F115B7F1

2H111Dl9D210F114B15B10F2

. 7F1

10F27F1

9D2

2H1

9D214B10F27F1

CarrotCarrot

CauliflowerCauliflowerCauliflower

Sweet CornSweet CornCornCornSweet Corn

CucumberCucumberCucumberCucumberCucumberCucumberCucumberCucumber

EggplantEggplant

Kohlrabi

Lettuce

OnionOnionOnionOnion

08/27/9011/03/90

07/23/9009/17/9010/29/90

08/20/9007/23/9008/07/9008/27/9009/17/90

08/20/9007/23/9007/23/9008/07/9008/27/9008/27/9009/10/9009/17/90

09/10/9009/17/90

06/25/90

08/20/90

06/25/9008/27/9009/10/9009/17/90

4.14 + 1.721.88 + 1.26

2.71 + 0.521.88 + 0.61

< 1.76

< 0.823.44 + 0.621.79 + 0.60

< 2.181.87 + 0.92

17. 67 + 0. 641.42 + 0.660.87 + 0.612.16 + 0.49

19.88 + 1.7333.98 + 2.63

< 1.401.50 + 0.72

35.83 + 2.76< 1.20

6.74 + 1.21

29.53 + 2.33

2.86 + 0.5628.45 + 2.5512.46 + 0.42

2.90 + 1.15

&W&&WWIHW&&&WWW&&&&&&&WWWWWW&WW&&w&%WWW WWW&&%Ww&&&

TABLE19GAMMA+ SPECTROSCOPIC ANALYSES OF FOOD PRODUCTS


9D210F1

PeachPeach

2H1 Sweet Pepper11D1 „ Sweet Pepper10F2 Sweet Pepper7F1 (2) Sweet Pepper

10F27F1 (1,3)

4 2H111D19D2 (1)10F115B16F210F27F1 (1)8D4

PlumPlum

PotatoPotatoPotatoPotatoPotatoPotatoPotatoPotatoPotato

LOCATION SAMPLE TYPE

9D2 Snow Pea16F2 Snow Pea

C

SAMPLE DATE

06/25/9006/26/90

07/23/9008/07/90

08/20/9007/23/9009/10/9009/17/90

09/10/9009/17/90

08/20/9007/23/9007/23/9008/07/9008/27/9009/04/9009/10/9009/17/9010/01/90

K-40

1.66 +1.65 +

2.02 +42.21 +

9.61 +31.79 +

3.03 +6.36 +

1.121.12

0.620.79

1.421.522.240.45

34.453.394.44

39.411.85

12.944.554.89

13.94

+ 2.51+ 1.32+ 1.14

0.801.010.372.031.071.28

( 1.1611.52 + 1.41

LOCATION SAMPLE TYPE SAMPLE DATE

TomatoTomatoTomatoTomatoTomatoTomatoTomatoTomato

2H1llD110F112F414B16F210F27F1

7F1 (1) Watermelon

ZucchiniZucchiniZucchiniZucchiniZucchiniZucchini

2H111D19D216F210F27F1

08/20/9007/23/9008/07/9008/27/9008/27/9009/04/9009/10/9009/17/90

09/17/90

08/20/9007/23/9007/23/9009/04/9009/10/9009/17/90

12.591.544.10

23.0411.27

2.5210.913.23

K-40

+ 0.41+ 1.19+ 1.32+ 0.82+ 1.45+ 1.06+ 0.38+ 1.02

1.61 + 0.42

10.232.41

12 '67.43

+ 1.26+ 0.530.88+ 0.43+ 0.981.06

COMMENTS

(1) NRC Technical Specifications for T-131 vere exceeded.(2) Saaple activity of 0.08 * 0.03 pCi/g vas reported for Th-232.(3) Sea@le activity of 0.20 * 0.10 pcl/g vas reported for Ra-226.

16F2 Rhubarb

7Fl (1) Butternut Squash

12F2 Strawberry12F5 Strawberry9D2 Strawberry

06/26/90

09/17/90

06/04/9006/16/9006/25/90

3.21 +

3.40 +

11.87 +0.92 +1.67 +

0.78

0.92

0.700.990.94

~ Only detected gaaraa emltters are reported; typical LLD values are f'ound in Table 21.

of 1

TABLE 20GAMMA SPECTROSCOPIC ANALYSES OF GAME, POULTRY, AND EGGS


LOCATION SAMPLE TYPE COLLECTION DATE K-40

10D1 DUCK

12Bl EGGS

12B1 CHICKEN

8B DEER

10/16/90

09/05/90

10/16/90

10/16/90

8.0 + 0.9

27.5 + 2.3

3.2 + 0.8

0.4 + 0.3

5S46S15F

2B

16F5S4

RABBITRABBITRABBIT

GRAY SQUIRREL

WOODCHUCK

WOODCHUCK

09/04/9009/04/9010/29/90

10/30/90

08/28/9009/13/90

22.6 + 0.735.1 + 1.3

2.6 + 0.7

undetected

2.1 + 0.35.1 + 0.7

* Only detected gamaa emittera are reportable> typical LLD values are found in Table 21.

TABLE 21

LOVER LIMITS OF DETECTION BY GAMMA SPECTROMETRY

Page 1 of 1

Isotope

Milk,(2)Water

(pCi/1)

Water30-Day

Composite(pCi/1)

Air (3)Particulate

(pCi/m3)Vegetation(1)

(pCi/kg+)

Algae,(1)Animal Soil,(1)Tissue Mud/Silt

(pCi/kg) (pCi/kg)

>C

I

Potassium-40Chromium-'51Manganese-54Cobalt-58Iron-59Cobalt-60Zinc-65Zirconium/Niobium-95Ruthenium/Rhodium-106Iodine-131Cesium-134Cesium-137Barium/Lanthanum-140Cerium-144

2695066125126 (4)

54

105614(4)

47

31385781861510

65

4267

75

0.0590.0240.0010.0020.0050.0010.0030.003

0.010

0 F 0010 F 0010,057

0.006

1473244292963286532

248

482629104

212

836631717381739

'9

146

28151961

130

108971191943244622

169

31182468

135

NOTE: Naturally occurring, radionuclides are not listed.

(1)(2)(3)(4)

COMMENTS

Based on 1.0 kg (net weight).Based on 4 liter.Based on 5200m3 volume of air (quarterly composite).Total for parent and daughter.

of 4

~Stud Date arameter

'TABL -1

EPA CROSS-CHECK PROGRAM - 1990CONTROLS FOR ENVIRONMENTAL POLLUTION

GROSS ALPHA/BETA IN WATER

EPAAcceptableR~IL CEP Mean

Value Ci L n 3

01/26 Gross Alpha

Gross Beta

12.0 2 5.0

12.0 2 5.0

3.3 ~ 20.7

3.3 ~ 20.7

7.33 i 0.58

14.00 t 1.00

'Stud

DateCEP Mean

Value Ci L n 3Parameter

GROSS ALPHA/BETA, STRONTIUM 90 AND CESIUM 137 IN AIR FILTERS

EPAAcceptableR~hl

03/30 Gross Alpha

Gross Beta

Strontium 90

Cesium 137

5.0 i 5.0

31.0 2 5.0

10.0 i 1.5

10;0 i 5.0

0.0 ~ 13.7

22.3 ~ 39.7

7.4 ~ 12.6

1.3 ~ 18.7

4.67 2 0.55

29.67 2 0.87

7.33 2 1.53*

15.0 i 1.19

This new filter type (thick, spongy, styrofoam material), submitted by EPA starting March, 1989, is not thesame type or thickness used by PP8L. This styrofoam filter caused interference with the analysis when adirect count of the filter was performed.

EPA CROSS-CHECK PROGRAM - 1990

TRITIUM IN WATER

~Stud Date

02/23

EPA ValueCi L i ls

4976 i 498

EPAAcceptable

Rane Ci L

4113.4 ~ 5838.6

CEPRe orted Values

4828

4838

4880

CEP MeanValue Ci L n 3

4849 R 28

of 4

EPA CROSS-CHECK PROGRAN - 1990

GANNA IN MATER

~Stud Date Parameter

02/09 Cobalt-60

EPAEPA Value Acceptable

IILDBL * 1 ~IL15 2 5 6.3 ~ 23.7

CEPe orted Values

16.017.018.0

CEP NeanValue Ci L n 3

17 t 1

Zinc-65

Ruthenium-106

Cesium-134

Cesium-137

Barium-133

139 2 14

139 i 14

18 2 5

18 2 5

74k 7

114.8 ~ 163.2

114.8 ~ 163.2

9.3 ~ 26.7

9.3 ~ 26.7

61.9 ~ 86.1

137.0147.0153.0

142.0145.0159.0

18.016.020.0

17.020.024.0

72.074.081.0

146 R 8

149 i 9

18%2

20 k 4

76 2 5

of 4

August 10, 1990: Iodine in Water

EPA CROSS-CHE ROGRAM - 1990

June 8, 1990: Gamma in Water

Co-60Zn-65RU-106Cs-134Cs-137Ba-133

June 22, 1990: Tritium in Water

September 21, 1990:

Gross AlphaGross Beta

September 14, 1990: Strontium 89 in Water

September 14, 1990: Strontium 90 in Water

August 31, 1990: Air Filter

AlphaBetaCs-137

EPA Value

39.0 +/- 0.6

24.0148.0210.024.025.099.0

2933.0

10.010.0

10.0

9.0

10.062.020.0

~CE Value

41.7 +/- 0.6

23. 0134. 7198.722.723.384.7

3052.7

6.09.7

13.3

11.7

9.064.025.0

Acceptable~EPA Va ue

28.6 to 49.4

15.3 - 32.7122 — 174173.6 — 264.415.3 - 32.716.3 — 33.781.7 — 116.3

2319.9 to 3554.1

1.3 to 18.7.1.3 to 18.7

1.3 to 18.7

0.3 to 17.7

1.3 to 18.753.3 to 7.0711.3 to 28.7

of 4

September 28, 1990

EPA CROSS-CHECK PROGRAM — 1990

NUCLIDES IN NILK

Sr-89

Sr-90

1-131

Cs-137

TOT.K

EPA Va ue

16.0

20.0

58.0

20.0

1700.0

CEP alue

15.7

20.7

52.7

22.0

1565.0

AcceptableEPA Value

7.3 to 24.7

11.3 to 28.7

47.6 to 68.4

11.3 to 28.7

1552.5 to 1847.5

October 5, 1990

GANN IN MATER

Co-58

Co-60

Ru-106

Ba-133

Cs-134

Cs-137

20.0

115.0

151.1

110.0

12.0

12.0

20.3

112.0

130.7

101.7

11.3

12.7

11.3 to 28.7

94.2 to 135.8

125.0 to 177.0

90.9 to 129.1..

3.3 to 20.7

3.3 to 20.7

October 19, 1990

/tbd2443o(26)

7203.0

TRITIUN IN MATER

7173.7 5953.8 to 8452.2

APPENDIX B

SUMNRY OF ANALYTICALMETHODS

The following section contains brief descriptions of the analytical laboratoryprocedures and the calculational methods used by Teledyne Isotopes andControls for Environmental Pollution for sample analyses. These areconsidered proprietary and are published for informational purposes only.

A further discussion on data reporting conventions can be found in Appendix C.

TLD NEASURENENTS

During the four quarters of 1986, a PPKL dosimetry system was used whichconsists of a Panasonic UD-710 reader and UD-801 badges. The UD-801 badgeshave two elements of lithium borate (Cu) and two elements of calcium sulfate(Tm). Only the calcium sulfate (Tm) elements are used for environmentalmeasurements. This phosphor was .chosen for its characteristic high lightoutput, minimal thermally induced signal loss (fading) and negligible self-dosing.

In handling, the badges are kept clean, and the element phosphors are nottouched. The badges are stored and transported in plastic bags or othercontainers.

Before going to the field, the dosimeters are read twice (separated by onehour) in which the second reading is used as an inherent (background) readingfor each element. After the inherent read, the badges are placed in sealedplastic bags, to aid in preventing moisture contacting the TLDs, labeled withthe sampling location and taken immediately out to the field. Upon removalfrom the field, the TLDs are inspected for any damage and read outimmediately. In-transit TLDs are not used because of the short time periodbetween the inherent reading and field placement.

An element correction factor has been calculated for each element, and thereader is calibrated using TLDs exposed to a cesium-137 source.

B-2

DETERNINATION OF GROSS ALPHA AND/OR GROSS BETA ACTIVITYTELEDYNE ISOTOPES

iOne liter aliquots of water samples are treated with about one millilter ofconcentrated nitric acid and evaporated to near dryness in beakers. Theremaining volumes (approximately five milliters or less) are transferred,tostainless steel planchets and evaporated to dryness.

Two hundred or more grams of each fish sample are dried and then ashed in amuffle furnace. One gram of each ashed sample is then transferred to astainless steel planchet.

Approximately 50 grams of each soil or sediment sample is dried by heat lampover a period of a couple days. One gram of each dried sample is thentransferred to a stainless steel planchet.

All planchets are counted in low background gas-flow proportional counte} s.Calculations of both gross alpha and beta activities include the use ofempirical self-absorption correction curves to account for changes ineffective counting efficiency occurring as a result of changes in the massesof residue being counted.

Weekly air particulate filters are placed into planchets as received andcounted in low background gas-flow proportional counters. No corrections aremade for beta self-absorption when calculating the gross beta activities, of

~

~ ~the air particulate filters because of the impracticality of weighing thedeposit and because the penetration depth of the deposit into the filter isunknown.

CONTROLS FOR ENVIRONMENTAL POLLOTION

The wet ash method is used in the determination of gross alpha and betaactivities, without the identification of specific nuclides, for all samplesexcept air particulate filters.One liter aliquots of water samples are treated with about ten milliliters ofconcentrated nitric acid and are then evaporated to dryness. The residues arethen wet ashed with hydrogen peroxide and nitric acid. After wet ashing, theresidues are transferred by washing to stainless steel planchets. Theplanchets are flamed until red hot.

Approximately 200 gram aliquots of soil, sediment, and fish samples are dried,ground, and muffled to remove organic material. The samples are then leachedwith hydrochloric acid, and filtered. After the leachates are evaporated todryness, the residues are wet ashed using nitric acid and hydrogen peroxideand transferred to stainless steel planchets. The planchets are flamed untilred hot.

All planchets are counted in low background gas-flow proportional counters.~ ~

~

~

~

Calculation of gross alpha activities includes the use of an empirical self-absorption correction curve. No corrections are made for self-absorption in

8-3

the calculation of gross beta activities. It is assumed that the beta self-absorption is negligible with the masses of residue involved.

quarterly composites of the weekly air particulate filters are counted forgross alpha activities. Preparation for counting involves the dissolution ofthe filters and the eventual transfer of the residue from filter deposits ontostainless steel planchets. As with the calculation of other gross alphaactivities, corrections are made for sample self-absorption of alpha particlesduring counting.

CALCULATION OF THE SNPLE ACTIVITY

—+ RbC

C —Rp 2 tpCi b t

unit volume or mass 2.22(V) (8) 2.22(V) (E)

net activity random uncertainty

where: C - total counts for samplet count time for sample/background (minutes)Rb background count rate of counter (cpm)2. 22 ~d

pCiV(N) - volume or mass of sample analyzedE efficiency of the counter (cpm/dpm)

Calculation of the ess-Than L.T. Value

If the net activity is less than or equ'al to 4.66 times the standard deviationof the background count rate, then the L.T. value is reported.

4.66r,.r.—

2.22(V) (Z)

RADIOCHENICAL DETERMINATION OF I-131IN MILK AND WATER SAMPLES

TELEYDYNE ISOTOPES

A four liter aliquot of sample is first equilibrated with stable iodidecarrier. Following a period of time sufficient for equilibration, anionexchange resin is added to the aliquot to capture the iodide ions present.The iodide ion is subsequently removed from the resin using sodiumhypochlorite. Hydroylamine hydrochloride is then used to produce free iodine.The resulting free iodine is then extracted from the aqueous phase bydissolution in carbon tetrachloride. This is followed by a reduction back tothe iodide form using sodium bisulfite and back-extraction to the aqueousphase. Once in the aqueous phase again, the iodide is precipitated aspalladium iodide following the addition of palladium chloride.

Another aliquot of the sample is used to determine the stable iodide contentof the milk by the use of a specific-ion electrode. This information is thenused to correct the chemical yield determined from the mass of the driedprecipitate obtained.

The dried precipitate is beta counted on a low-level counter.

CONTROLS FOR ENVIRONNENTAL POLLUTION

Different methods are used for the analyses of water and milk samples byControls for Environmental Pollution (CEP).

Stable iodide carrier is added to four liter aliquots of each water sampletogether with sodium nitrite and carbon tetrachloride. Free iodide isproduced that then preferentially dissolves in the carbon tetrachlorideportion of the mixture. Hydrazine solution is then added to the portioncontaining the free iodine and carbon tetrachloride, effectively pulling theiodine out of solution in the carbon tetrachloride and back to the aqueousphase. From the aqueous phase, the iodine is precipitated as silver iodide.

Stable iodide carrier is added to four liter aliquots of each milk sampletogether with anion exchange resin which captures the iodide ions that arepresent. The iodide ions are subsequently removed from the resin with sodiumperchlorate. The iodine is'then precipitated as silver iodide.

The dried precipitates resulting from the procedures for both water and milkanalyses described above are beta counted on low-level counters.

B-5

CALCULATION OF THE SAMPLE ACTIVITY

+ R~C

C —R~ 2pCi B t

2.22 (V) (y) (DF) (E) 2.22 (V) (y) (DF) (E)


where: C total counts from sample

" counting time for sample (min)

Rb background count rate of counter (cpm)

2. 22 ~d

pCi

V volume of sample analyzed (liters)

y chemical yield of the mount or sample counted

DF - decay factor from the collection to the mi'd count time

E efficiency of the counter for the I-131 betas.

Note: Efficiency is determined by counting an I-131 standard.

Calculation of t e L. . a ue

If the net activity is less than or equal to one-half the value of 4.66 timesthe standard deviation of the background count rate, then the L.T. value isreported.

Rgt

2 22 (V) (/) (DF) (E)

"

B-6

DETERMINATION OF TRITIUM BY GAS COUNTING

TELEDYNE ISOTOPES

A 2 ml aliquot is redu'ced into hydrogen gas and collected in an activatedcharcoal trap. The hydrogen is then transferred into a previously evacuatedone liter proportional counter. Non tritiated hydrogen and ultra-high puritymethane is added and the mixture is counted. Backgrounds and standards arecounted in the same gas mixture as the samples.

Calculation of the sample activity:

[(CPM) —BKG i 2 . G + Buni t vol. CPM~V,

where: (TU)N the tritium units of the standard

VN- volume of the standard used to calibrate the efficiency

of the detector - in psia

V - volume of the sample loaded into the detector — inpsia

(CPH) the cpm activity of the standard of volume VN

(CPM) the gross activity of the sample of volume VS and thedetector background

BKG = the background of the detector in cpm

3.234 = conversion factor changing TU to pCi/1

= counting time for the sample

sG

sB

standard deviation of the gross activity of the sampleand the detector. background, in cpm

- standard deviation of the background, in cpm

B-7

Calculation of the Less-Than L.T. Value

If the net activity, [(CPM) - BKG], is equal to or less than 3.3 times thestandard deviation of the nit.count rate, the activity on the collection dateis below the limits of detection and is called "less than" (L.T.).

3.3 x 3.234 x (Tgn x Vn x G'B'CPM)Nx V~

where: G standard deviation of the gross activity of the sample andthe detector background, in cpm

B - standard deviation of the background, in cpm

B-8

DETERMINATION OF TRITIUM IN WATER

BY LIQUID SCINTILLATION COUNTING

TELEDYNE ISOTOPES

Teledyne Isotopes uses electrolytic enrichment of the sample prior to liquidscintillation counting to 'increase the sensitivity of the analysis.Approximately 55 milliters of the sample undergoes enrichment byelectrolysis.. Water molecules containing only protium (hydrogen with a massnumber of one) decompose electrolytically at a faster rate than thosetritiated water molecules. The non-electrolyzed water which remains becomesenriched in tritium as a result. Electrolytic enrichment typically produces 3

to 5 milliliters of water in which the tritium is concentrated.

After the enriched water is distilled for purification purposes, threemilliliters is mixed with liquid scintillation material and counted fortypically 100 minutes to determine its activity.

CALCULATION OF THE SNPLE ACTIVITY FOR TRITIUM

pCi——RC

b

—+ RbCt

Vc vcVp vz


V

EFE

V,Vf

Calculation of the Less- han L.T. Value

where: C - total counts from samplet count time for sample (minutes)Rb = background count rate of counter (cpm)2. 22 ~d

pciinitial volume before enrichment (liters)

- enrichment factor (unitless)efficiency of the counter for tritium (cpm/dpm)volume counted by liquid scintillation

- final volume at the end of enrichment

If the net activity is equal to or less than one-half the value of 4.66 timesthe standard deviation of the background count rate, then the L.T. value isreported.

B-9

L. T.4 ~ 66 t

(2.22) (V) (EF) (E) ( —)VZ

CONTROLS FOR ENVIRONMENTAL POLLUTION

Electrolytic enrichment is not currently available to Controls forEnvironmental Pollution (CEP). Consequently, larger aliquots of sample andlonger counting times are employed to achieve the same sensitivities asTeledyne. CEP first filters and/or distills an aliquot of each sample,depending on the samples'ppearances and the likelihood that contaminants arepresent that might interfere with the liquid scintillation process. Followingany purification steps that may be employed, 9 milliliters of the sample istypically counted for 1,000 minutes.

CALCULATION OF THE SAMPLE ACTIVITY FOR TRITIUM

Rs Rb R +Rs b~Cd E. Eb t

2 ~ 22 {V) (DF) 2 ~ 22 {V) { ) {Es)


where: R, = sample count rate (cpm)Rb background count rate (cpm)E, sample counting efficiency (cpm/dpm)Eb - background counting efficiency (cpm/dpm)2. 22 ~d

pCiV volume of aliguot counted (liter)DF decay factor from collection to mid-count time (unitless)T sample/background count time (minutes)

Calcu ation the Less- an L. . Value

If the net activity is equal to or less than one-half of 4.66 times thestandard deviation of the background counting rate, then the L. T. value isreported.

4.66

2'22 {V) (Es) {D

B-10

DETERMINATION OF GAMMA EMITTING RADIOISOTOPES

TELEDYNE ISOTOPES AND CONTROLS FOR ENVIRONMENTAL POLLUTION

Gamma emitting radionuclides are determined with the use of a lithium-driftedgermanium (Ge(Li)) and high purity germanium detectors with high resolutionspectrometry in specific media, such as, air particulate filters, charcoalfilters, milk, water, vegetation, soil/sediments, biological media, etc. Eachsample is prepared and counted in standard geometries such as one liter orfour liter wrap-around Harinelli containers, 300 ml or 150 ml bottles, two-inch filter paper source geometries, etc.

Samples are counted on large ( 55 cc volume) germanium detectors connected toNuclear Data 6620 data acquisition and computation systems. All resultantspectra are stored on magnetic tape.

The analysis of each sample consists of calculating the specific activities ofall detected radionuclides or the detection limits from a standard list ofnuclides.. The germanium detection systems are calibrated for each standardgeometry using certified radionuclide standards traceable to the Nat'ionalBureau of Standards.


Net pCi/vol or mass— [C-B] 2 C+B2.22 (V) (E) (GA) (DF) (t) 2.22 (V) (E) (GA) (DF) (t)


where: C area, in counts, of a spectral region containing a gammaemission of the nuclide of interest

Note: if the detector exhibits a peak in this regionwhen counting a blank this background (BB) issubtracted from N before using the above equation.BB is the count rate of the blank in thebackground peak.

B background counts in the region of interest, calculatedby fitting a straight line across the region connectingthe two adjacent regions..

t counting interval of sample (minutes)

2.22 - dpm/pCi

V volume or mass of sample analysed

E efficiency of counter at the energy region of interest

GA gamma abundance of the nuclide at the gamma emissionenergy under consideration

DF = decay factor from sample collection time to midpoint ofthe counting interval

Calculat on 0 he Less Tha L.T. Value

2.22 (V) (Z) (GA) (DF) (t')

The width of the spectral band around the emission energy is calculateddifferently from the case of an identified peak, so that the value of N usedin the two equations may differ.

A detection limit or "less than" (LT) value is reported if no activity isfound. If no spectral lines are identified at the energies appropriate to anuclide, the LT value is calculated by the above equation. If spectral linesfor man-made radionuclides are identified but the random uncertainty in thefirst equation is greater than 60X of the net activity, then a LT value isalso assigned by the second equation. When the random uncertainty exceedsonly 30X for naturally occurring radionuclides, the LT value is assigned.

The analyst's judgement is exercised in the decision to report an activity ora L.T: The agreement between various spectral lines of the same nuclide, andpossible interference from other nuclides, are considered in this decision.

B-12

DETERMINATION OF GROSS BETA MINUS K-40ACTIVITY IN MILK SAMPLES

TELEDYNE ISOTOPES

This procedure describes a radiochemical method for measuring the gross betaactivity of milk after removing natural K-40.

One fourth liter of milk sample is curdled by adding trichloroacetic acid(TCA) solution. The curd is removed by vacuum filtration. Radioactivespecies are co-precipitated with natural calcium as oxalates by addition ofoxalic acid and ammonia (leaving potassium in solution). The precipitate iscollected by vacuum filtration on a polycarbonate (Hillipore) filter, then isashed in a muffle furnace to remove organic material. The ash is dissolved inhydrochloric acid and solids are removed by filtration. Oxalates are againprecipitated and collected on a polycarbonate filter. After drying, theprecipitate is removed from the filter and crushed to a powder, the placed ina 2-inch stainless steel counting planchet.

Precipitate mass is determined by weighing the planchet before and aftermounting the sample. The planchet is counted for beta activity on anautomatic proportional counter. Results are calculated using an empiricalself-absorption curve which allows for the change in effective countingefficiency caused by the residue mass.


TELEDYNE ISOTOPES

— Rb 2 —+ RbC

pCi t t2.22 (V) (E) '.22 (V) (E)


where: C

t2.22-

E

total counts from sample (counts)counting time for sample (min)background count rate of counter (cpm)~d

pCivolume of sample analyzed (liters)efficiency of the counter (cpm/dpm)

Establishing and reporting activities that are equal to or, less than thedetection limit:

B-13

Calculat on o t e Less-Than L. . Value

If the net activity is equal to or is less than 4.66 times the standarddeviation of the background count rate, the activity is below the limits ofdetection and is called "less than" (L.T.).

4.66

2.22 (V) (E)

B-14

RADIOCHEMICAL DETERNINATION OF STRONTIUM-90 IN MILKCONTROLS FOR ENVIRONMENTAL POLLUTION

Cation exchange resin is added to one liter aliquots of the milk samples toremove strontium. The strontium is subsequently stripped from the resin withnitric acid, the resulting solution is evaporated, and the residue is wetashed with hydrogen peroxide and concentrated nitrate acid. Following the wetashing, the residue is redissolved with hydrochloric acid and stripped ofyttrium-90 with di-2-ethylhexyl-phosphoric acid. Subsequently, yttriumcarrier is added and yttrium-90 is allowed to build up for approximately twoweeks. Following the buildup period, yttrium, including any yttrium-90 thatis present, is once again stripped from the sample. Yttrium is thenprecipitated as yttrium oxalate and counted in a low background beta counterfor 100 minutes.

'CALCULATION OF SANPLE ACTIVITY

pCi(C+ B)

t22.22 (t) (V) (E) (I') (DF) (Y ) (Y ) 2.22 (V) (E) (I') (DF) (Y ) (Y„)


where: C total counts for the sample8 background counts

2. 22 ~d

pCit count time for sample/background (minutes)V volume of sample aliquot analyzed (liters)E counter efficiency (cpm/dpm)I yttrium-90 ingrowth factor (unitless)Df decay factor from collection to midpoint of count (unitless)Y = yield (recovery) of strontium (unitless)Yd yield (recovery) of yttrium (unitless)

Calculation of t e Less-T a L.T. Value


4.66L. T.

t22.22 (V) (E) (X) (DF) (Yp) (Y~)

8-15

RADIOCHEMICAL DETERMINATION OF STRONTIUM-89 IN MILK

CONTROLS FOR ENVIRONMENTAL POLLUTION

Solution saved from the strontium-90 procedure is evaporated and, the residueis wet ashed with nitric acid and hydrogen peroxide to remove organics. Thestrontium is precipitated as a nitrate, redissolved, and precipitated onceagain. After redisolving again, the strontium is finally precipitated as anoxalate. The precipitate is counted in a low background beta counter fortotal strontium. Strontium-89 activity is determined from the differencebetween the count of the total strontium and the strontium-90 count.

CALCULATION OF SAMPLE ACTIVITY

C +B' 1+ I'g() Ng()

pCQ (C —B — [1+(B (E, ) ]N )2

t22 22 { t) {V) {E) {DF) {Ysr) 2 22 (V) {E) {DF) (Ysr)

where: C total counts for the sampleB background counts2. 22 ~d

pcit count time for sample/background (minutes)v volume of sample aliquot analyzed (liters)E counter efficiency for strontium-89 (cpm/dpm)DF - decay factor from collection to midpoint of count (unitless)Y,„ yield (recovery) of strontium (unitless)I yttrium-90 ingrowth into strontium-89 portion (unitless)E~o

- strontium-90 counting efficiencyN~o net strontium-90 counts

Calculatio of the Less-Than L.T. Value


L. T.4 66 (B + [1+(I') (E90) ] N-90)

t22,22 (V) (E) (DF) (Ysr)

B-16

APPENDIX C

DATA REPORTING CONVENTIONS

Results of analyses are generally reported to two significant figures. Randomuncertainties of counting are reported to the same decimal place as theresult.

In the tables presenting analytical measurements, a calculated value isreported with the random uncertainty of counting at 2 standard deviations (2s)calculated by considering both the sample and background count rates. Theuncertainty of an activity is influenced by the volume or mass of the sample,the background count rate, the count times, the method used to round off thevalue obtained to reflect its degree of significance,and other factors. Theuncertainties of activities determined by gamma spectrometric analyses arealso influenced by the relative concentrations of the radionuclides in thesample, the energies and intensities of the gammas emitted by thoseradionuclides, and the assumptions used in selecting the radionuclides to bequantitatively determined.

Results reported as less than (() in a data table are below the minimumdetectable concentration (HDC) or the critical level, depending on theanalysis type. The HDC is an estimate of the detection capabilities of theoverall measurement method, taking into account not only the counting system,but also the characteristics of the sample being counted. When the HDC isused as the level to decide whether or not to enter a measured value into a

~

~

~

~

~

~ ~

~

~

~

table, there is a 5OX chance that the value will be entered when the actualsample activity is equivalent to the HDC. There is only a five percent chancethat a value representing a fluctuation in background activity will be enteredas sample activity in such an instance.

When the critical level (equivalent to one-half the HDC) is used as the levelto decide whether or not to enter a measured value in the table, the chancebecomes 95X that a measured value will be entered in the table when sampleactivity is equivalent to the HDC. For most of the 1990 data, the criticallevel criterion was applied to the data for the results of specificradionuclide analyses (all analyses, except gross alpha and beta analyses).

radiological g environmental program monitoringsampling locations for the sses rad'iological...

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