· tableof contents summitryandconclusions introduction. ambientradiationmonitoring....

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Units 1 8 2

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1996 ANNUALR PORT

RadiologicalEnvironmental

IVlonitoringProgram

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629Pennsylvania Power 8 Light Company

Allentown, PA

APRIL 1997e70502000e 970e29PDR ADQCK 05000387R

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TABLEOF CONTENTS

SUMMITRYAND CONCLUSIONS

INTRODUCTION.

AMBIENTRADIATIONMONITORING.

AQUATICPATHWAYMONITORING

ATMOSPHERIC PATHWAYMONITORING.

TERRESTMAL PATHWAYMONITORING

GROUND WATERMONITORING.

REFERENCES

1

5

18

23

38

43 '

50

52

APPENDICES

A. 1996 REMP CHANGES

B. 1996 REMP MONITORINGSCHEDULE

C. 1996 REMP MONITORINGLOCATIONDESCRIPTIONS

D. 1996 LANDUSE CENSUS RESULTS

E. SUMMARYDESCRIPTION OF SSES REMP ANALYTICALMETHODS

A-1

B-1

C-1

D-1

E-1

F. 1996 EXCEPTIONS TO THE SSES TECHNICALSPECIFICATIONS SAMPLE SCHEDULE, METHODSAND ANALYSISSENSITIVITIES

F-1

G. 1996 SSES REMP SUMMARYOF DATA G-1

H. COMPARISON OF INDICATORAND CONTROL 1996REMP ANNUALMEANS FOR SELECTED MEDIAANALYSISRESULTS WITHMEANS FROMPREOPERATIONAL AND PRIOR OPERATIONALPERIODS

H-1

SPECIFIC ANALYSISRESULTS TABULATEDBY MEDIAAND SAMPLINGPERIOD

EPA ENVIRONMENTALRADIOACTIVITYPERFORMANCEEVALUATIONSTUDIES PROGRAM - 1996

LIST OF FIGURES

FigureNumbers Title ~Pa e

Exposure Pathways to Humans

2. 1996 Radiation Level Monitoring Locations within One Mile of theSSES

12

1996 Radiation Level Monitoring Locations from One to Five Milesof the SSES

13

1996 Radiation Level Monitoring Locations Greater than Five Milesfrom the SSES

14

1996 Environmental Sampling Locations within One Mile of theSSES

15

1996 Environmental Sampling Locations from One'to Five Miles ofthe SSES

16

1996 Environmental Sampling Locations Greater than Five Milesfrom the SSES

17

10.

12.

13.

Ambient Radiation Levels Based on TLD Data

Gross Beta Activityin Surface Water

Tritium Activityin Surface Water

Gross Beta Activityin Drinking Water

Gross Beta Activityin AirParticulates

Iodine-131 Activityin Milk

22

35

36

37

42

49

''SUMMARYAND CONCLUSIONS

Radiolo ical Dose Im act

The extent of the 1996 RadiologicalEnvironmental Monitoring Program(REMP) sampling met or exceeded therequirements of the Susquehanna SteamElectric Station (SSES) TechnicalSpecifications. The types ofanalysesthat were performed on these samplesfor the identification and quantificationof radioactivity also met or exceeded theSSES Technical Specificationrequirements during the 1996 REMP.The result of this effort was theverification of the SSES EfHuentMonitoring Program data that indicatethat the SSES operation has nodeleterious effect on the health and

'afetyof the public or the environment.

detected in environmental samplesduring 1996 were very small, as in pastyears. Based on the radionuclide levelsmeasured by the REMP, the maximumwhole body dose or maximum organdose to a member of the public fromSSES operation is estimated to be less

than one-tenth ofone percent of the perunit dose limits established by theNuclear Regulatory Commission (NRC)as stated in 10 CFR 50, Appendix I.The maximum potential off-site wholebody and organ doses fromradionuclides detected by the REMPand attributable to the SSES operationswere calculated to be approximately0.00037 mrem/year.

The amounts of the radionuclides By contrast, potassium-40, a very long-

DOSE COMPAMSONSUSQUEHAlVNA-RELATEDVERSUS OTHER SOURCES

ConsumerMedical products

16% 3o/,

SSES(0 01o/o

Natural

The above figure shows the whole body dose from SSES operation relative to theaverage dose to people from all sources, including natural background, medical, and

consumer products.

1996 Radiological Environmental Monitoring Rcport

Summa and Conclusions

lived, naturally occurring radionuclidefound in everyone's body, is estimatedto deliver an average annual dose to theblood forming organs of individuals inthe United States ofabout 27 millirem.While a small portion of the backgrounddose from natural radiation sources, thepotassium-40 dose is still more than70,000 times the estimated maximumwhole body dose and the maximumorgan dose to a hypothetical member ofthe public from ingestion of *

radionuclides attributable to the SSES.

The maximum direct radiation dosefrom SSES operation to a member ofthe public was determined to be 0.0034millirem/year. The total whole bodydose &om both ingested radionuclidesand direct radiation is negligiblecompared to the public's exposure fromnatural background radiation ofapproximately 300 millirem/yeareffective dose equivalent.

Identified Radionuclidesand Their DoseContributions

1Vaturally OccurringRadionuclidesIn 1996, the SSES REMP reported thenaturally occurring radionuclidesberyllium-7, potassium-40, radium-226,and thorium-228 in the environment atlevels exceeding the minimum detectableconcentrations (MDCs) for theirrespective gamma spectroscopicanalyses. Beryllium-7 was identified insediment, air, precipitation, and lettuce.Potassium-40 was observed in surfacewater, fish, sediment, air, milk, soil, fruitand vegetables, and game. Thorium-228was found in sediment and soil.

, Radium-226 also was seen in sedimentand soil. None of these results wereunexpected, and they are not related tothe operation of the SSES. Doses fromthe presence of these radionuclides werenot included in the estimate ofthe dosefrom SSES attributable radionuclides.

Man-made RadionuclidesAlthough not all due to SSES operation,the following man-made radionuclideswere reported at levels in theenvironment in excess of the MDCs fortheir respective analyses: tritium,iodine-131, and cesium-137. Theseradionuclides, with the exception ofcesium-137, were'identified in surfacewater. Tritium was measured in allwaters analyzed except precipitation.Iodine-131 was identified only in surfacewater. Cesium-137 was observed insediment, soil, and game.

Tritium is the only man-maderadionuclide attributed to the SSESoperation. The presence of the otherman-made radionuclides was attributedto non-SSES sources. Tritium in mediaother than Susquehanna river waterdownstream of the SSES was attributedto'both natural production by theinteraction ofcosmic radiation with the

upper atmosphere and previousatmospheric testing ofnuclear weapons.Cesium-137 was considered to bepresent only as residual fallout fromatmospheric weapons testing. Iodine-131 was believed to be found only in theaquatic pathway as the result of thedischarge ofmedical waste to theSusquehanna River through. sewagetreatment plants upstream of the SSES.

Allofthe man-made radionuclidesmentioned above were not analyzed for

1996 Radiological Environmental Monitoring Report


in all media. For example, no analyseswere performed in an efFort to determineiodine-131 levels in ground water.When selecting the types ofanalysesthat would be performed, considerationwas given to the potential importance of

, difFerent radionuclides in the pathwaysto man and'the regulatory analysisrequirements for various environmentalmedia.

AQUATICPATHWAY

SEDIMENT

Manmade:non-SSESp Manmade;SSES

0.0%

Relative Radionuclide ActI'vityLevels in Selected MediaSome media monitored in theenvironment are significant for thenumbers ofgamma-emittingradionuclides routinely measured atlevels exceeding analysis MDCs.Sediment in the aquatic pathway and soilin the terrestrial pathway are two suchmedia.

The followingpie graphs show therelative activity contributions for thetypes ofgamma-emitting radionuclidesreported at levels above the analysisMDCs in sediment and soil at indicatorlocations during 1996.

Natural99.4%

TERRESTRIAL PATHWAY

SOIL

Manmade:non-SSES15% ~~ pp

, Natural98.5%

Naturally occurring radionuclidesaccount for 99.4% of the gamma-emitting activity in sediment and 98.5%of the gamma-emitting activity in soil.Man-made radionuclides ofnon-SSESorigin account for most of the rest of thegamma-emitting activity in sediment andall of the remaining activity in soil.Generally, the activity for naturally-occumng radionuclides reported insediment and soil dwarfs the activity ofthe man-made radionuclides also

reported, especially those originatingfrom the SSES.



Dose Significance ofRadionuclidesOfthe three man-made radionuclidesreported in the environment by theSSES REMP, only one of these (tritium)is attributable to the SSES operation'.

The one man-made radionuclide thatwas attributable to the SSES operationand'was also considered in estimatingthe dose to members of the public fromREMP identified radionuclides wastritium. This radionuclide was includedin the dose calculation because it wasidentified in the water being dischargedto the river. The presumed exposurepathways to the public from thisradionuclide were drinking water takenfrom the Susquehanna River at Danville,PA and eating fish caught near the SSES

discharge to the river. Exposure fromtritium was only assumed to occurthrough the eating offish and theconsumption ofdrinking water. Thisassumption is b'ased on the fact thattritium does not emit gamma radiationand the beta radiation emitted by tritiumis not suf6ciently penetrating to reach an

individual on the shore.'


Radioactive MaterialsReleases

Radioactive MaterialsGenerationThe SSES produces the thermal powerto generate electricity using two boilingwater reactors (BWRs). Radioactivematerials are produced at the SSES bythe fissioning ofuranium and theactivation ofmaterials inside the coresof these nuclear reactors. When verysmall quantities offission products

. escape through the cladding of thecore's fuel rods, they enter the waterwith the activation products circulatingthrough the reactor.

The radioactive 'material released as

gaseous efHuent from the SSES may bedivided into the following threecategories noble gases (xenons and

hyptons), iodines and particulates, andtritium (a radioactive isotope ofhydrogen) for the purposes oftrackingthe amounts ofradioactive material

Since the mid-1980s, improvements inthe manufacture ofnuclear fuel,improvements in PP&L's fuelconditioning (to minimize heat stresseson the fuel), reductions in the numbersof reactor scrams (rapid control rodinsertions) that put stresses on the fuel,and maintenance ofgood waterchemistry in the reactors have allcontributed to minimization of theescape of radioactive materials from thefuel to the reactor core's circulatingwater. This has been responsible forsignificant reductions in the alreadyrelatively small amounts ofsomeradioactive materials released in bothgaseous and liquid efHuents from theSSES.

being released from the SSES andmonitoring the SSES releaseperformance. Reduction of the amountsofradioactivity otherwise destined to bereleased with the gaseous efHuentdepends on the category into which theradioactive material fits.

Short-lived noble gas activity is reducedby radioactive waste processing systemswhich delay the release ofgases to theenvironment to permit them to decayprior to release. Iodine and particulateradioactivity in the gaseous efHuent arereduced by adsorption in charcoal bedsand capture in particulate filters,respectively. There is a total of74 tonsofcharcoal distributed in five beds thatthe gaseous efHuent must pass throughprior to release. A delay time ofat least41 days for some ofthe gases is

Gaseous EffluentsIn boiling water reactors (BWRs), suchas the SSES Units 1 and 2, some

TRODU,CTl,ON:";"-'"'~'"'g.j--"'."..--."-",.-. -"."'.-..";.-':;::-;.

&action ofthe radioactive materials thatenter the circulating water are vaporizedand others are entrained in the steam,

canying over to the turbines andeventually the condensers. In turn,some &action ofthe radioactivematerials in the condensers are removed&om them with the offgas. Offgas iseventually released to the atmospherethrough turbine building vents. Otherpathways also exist for the release ofgases through each offive continuouslymonitored rooftop vents at the SSES.

1996 Radiological Environmenta Monitoring Report

Introduction

expected as a result ofthe charcoalbeds, providing a significant amount ofdecay time prior to release. Thisprovides for a significant reduction inthe radioactivity levels ofthe gasesbefore release. The charcoal is typicallyvery efficient at capturing the iodine.Similarly, the particulate filters areexpected to have capture efficiencies ofmore than 99.7% for particles 0.3microns or larger in size.

Unfortunately, no practical means yetexists to eliminate tritium from thegaseous efHuent. Some elimination oftritium in the form of tritiated watervapor by chilling of the offgas andsubsequent collection of the condensateprior to passage through the charcoaladsorbers does occur. But, the primarypurpose of this chilling is to reduce themoisture entering the charcoal beds sothat they willmaintain their efficiencyfor the removal of iodine.

LiquidEffluentsMaintaining the quality ofwatercirculating through the reactor core atacceptable levels and capturing waterthat leaks from reactor systems, resultsin the generation ofwaste water at theSSES. This waste water also containsradioactivity that has escaped from fuelrod cladding. In order to minimize the

'eleaseof this water to the environment,as much of it as is practical is cleaned upand recycled. Because this watersometimes contains chemicals that maybe harmful to the reactor ifrecycled,some water must be released in batchesto the Susquehanna River.

materials are divided into two groups,tritium being one group, and all otherradioactive materials constituting theother. Prior to releasing water to theriver, a significant effort is made toreduce the level ofradioactivity in wastewater to levels which are as low as

practicable by filtering the water throughmedia, such as diatomaceous earth, an4passing it through ion exchangematerial, similar in function tohousehold water softeners. Thesemethods are effective to varying degreeswith all of the radioactive materialsexcept tritium, which can't be removedfrom water by either method. For mostradionuclides, the ion exchange mediamay be expected to have a removalefficiency of roughly 99%.

Controlling Radioactive ReleasesNRC regulations (10 CFR 50.34 and 10

CFR 20.1101b) require that nuclearpower plants be designed, constructed,and operated to keep levels ofradioactive materials in efHuents to areasunrestricted to the public as low as

reasonably achievable (ALARA). Toensure that these criteria are met, eachlicense authorizing reactor operationincludes technical specifications (10CFR 50.36a) that contain requirementsgoverning radioactive efHuents.Instantaneous, as well as quarterly andannual limits, have been set based on thedose that the maximally exposedindividual in the public could beexpected to receive. During routineoperation of the SSES, doses are kept as

much below these actual limits as

possible.

For the purpose of tracking radioactivereleases and monitoring SSES releaseperformance, liquid efHuent radioactive

The NRC release limits are far below theapproximately 300 millirem dosereceived on average each year by


Introduction

residents of the United States &om allnatural background sources. On theother hand, the allowable limits are farabove the doses estimated for the levelsofradioactivity actually being releasedfrom the SSES. The actual doses are

typically small fractions ofone milliremor less per year ofSSES operation.Such doses are far below the levels atwhich any effects would be expected tobe observed in the exposed population.

MonitoringReleases'Roof top vents from which gaseousreleases take place are continuouslymonitored to detect any excessive ratesofradioactivity release that might occurwell before any release limits arereached. Also, discharge rates ofradioactively contaminated water to theSusquehanna River are carefullycontrolled to remain as far below thedischarge limits as possible. Dischargesare monitored by radiation detectors sothat iflevels of radioactivity in the waterwould inadvertently approach the limitsofpermissible levels, the dischargescould be stopped quickly.

Radiological EnvironmentalMonitorin

In addition to the steps taken to controland to monitor radioactive effluentsfrom the SSES, the SSES TechnicalSpecifications also require a program forthe radiological monitoring of theenvironment in the vicinityof the SSES.The objectives of the SSES REMP areas follows:

~ Fulfillment ofSSES TechnicalSpecifications'adiological

environmental surveillanceobligations,

~ Verification ofno detrimentaleffects on public health and safetyand the environment from SSES

operations,

~ Assessment ofdose impacts to thepublic, ifany,

. ~ Verification ofadequate SSESradiological effluent controls, and

Identification, measurement,trending, and evaluation ofradionuclides and theirconcentrations in criticalenvironmental pathways near theSSES.

PPM. has maintained a RadiologicalEnvironmental Monitoring Program(REMP) in the vicinityof the existingSusquehanna Steam Electric StationUnits 1 and 2 since April, 1972, prior toconstruction ofboth units and ten yearsprior to the initial operation ofUnit 1 inSeptember, 1982. The SSES is locatedon an approximately 1500 acre tractalong the Susquehanna River, five milesnortheast ofBerwick in SalemTownship, Luzerne County,Pennsylvania. The area around the siteis primarily rural, consistingpredominately offorest and agriculturallands. (More specific information on thedemography, hydrology, meteorology,and land use characteristics of the areain the vicinityofthe SSES can be foundin the Environmental Report (14), theFinal Safety Analysis Report (15), andthe Final Environmental Statement (16)for the SSES.) The purpose ofthepreoperational REMP (April, 1972 to


Introdaction

September, 1982) was to establish abaseline for radioactivity in the localenvironment that could be comparedwith the radioactivity levels observed invarious environmental media throughoutthe operational lifetime ofthe SSES..This comparison facilitates assessmentsto be made ofthe radiological impact ofthe SSES operition.

The SSES REMP was designed on thebasis ofthe NRC's RadiologicalAssessment Branch Technical Positionon radiological environmentalmonitoring, as described in Revision 1,November 1979.(17) However, theREMP conducted by PPM. for theSSES exceeds the monitoring suggestedby the NRC's branch technical position,as well as the requirements of the SSESTechnical Specifications in terms of thenumber ofmonitoring locations, thefrequency ofcertain monitoring, thetypes ofanalyses required for thesamples, and the achievable analysissensitivities.

Potential Exposure PathwaysThe three pathways through whichradioactive material may reach thepublic from nuclear power plants are theatmospheric, terrestrial, and aquaticpathways. (Figure 1 depicts thesepathways for the intake ofradioactivematerials.) Comprehensive radiologicalenvironmental monitoring must samplemedia from all ofthese pathways.

Mechanisms by which people may beexposed to radioactivity and radiation inthe environment vary with the pathway.Three mechanisms by which a memberof the public has the potenital to beexposed to radioactivity or radiation

&omnuclear power plants such as theSSES,are as follows:

~ inhalation (breathing)(

g

~ ingestion (eating and drinking), and .

~ whole body irradiation directly &oma plant or'&om immersion inefHuents.

REMP Scope'uringthe operational period ofthe

'SSES, it has been important to establishtwo diFerent categories ofmonitoringlocations, called control and indicatorlocations, to further assist in assessingthe impact ofthe station operation. So-- .

called control monitoring locations have'.

been situated at sites where it isconsidered unlikely that radiation orradioactive material from normal stationoperation would be detected. Indicatormonitoring locations are sited where it isexpected that radiation and radioactivematerial that might originate from thestation would be most readilydetectable.

Control locations for the atmosphericand terrestrial pathways are more than10 miles from the station. Preferably,the controls also are in directions &omthe station less likely to be exposed towind blowing &om the station than arethe indicator locations. Controlmonitoring locations for the aquaticpathway, the Susquehanna River, areupstream ofthe station's discharge tothe river.

Indicator monitoring locations areselected primarily on the basis ofproximity to the station, althoughfactors such as meteorology,


Introduction

topography, and sampling practicalityalso are considered. Indicator locationsfor the atmospheric and terrestrialpathways are typically less than 10 milesfrom the station. Most often,,they arewithin 5 miles ofthe station. Indicatorlocations in the Susquehanna River aredownstream ofthe station's discharge.Monitoring results from indicatorlocations are compared with resultsfrom control locations. Thesecomparisons are made to discern anydifferences in the levels and/or types of

monitored and analyses performed aresummarized in the table below. Figures2 through 7 display the REMP TLDsand sampling locations in the vicinityofthe SSES. Appendix C providesdirections, distances, and a brief

~ description ofeach of the locations inFigures 2 through 7.

Regulatory agencies also participate in'onitoringthe SSES environment and

also oversee PP&L's monitoring efforts.The State ofPennsylvania's Department

T e of MonitorinSSES REMP

Media MonitoredGross Alpha Activity

Gross Beta Activity

Gamma-Emittin Radionuclide ActivitiesTritium ActivitIodine-131 Activity

Exposure Rates(b TLD &, Pressurized Ion Chamber

Allwaters except ground water andprecipitation & Course and FlocculatedSedimentAllWaters except Ground Water andPrecipitation, AirParticulates, Coarse &Flocculated Sediment &FishAllMediaAllWatersSurface Water, Drinking Water, Air&MilkAmbient Radiation Levels

radioactive material and/or radiation thatmight exist between indicators andcontrols and that could be attributable tothe station.

In 1996, the SSES REMP collectedmore than 1,000 samples at more than50 locations and performed more than2,000 analyses. In addition, the REMPmonitors ambient radiation levels usingthermoluminescent dosimeters (TLDs)at 86 indicator and control locations,making as many as 344 radiation levelmeasurements each year. The media

ofEnvironmental Protection (PADEP)monitors air for radioactive particulatesand radioactive iodine, milk, fruits andvegetables, surface and drinking water,fish, river sediments, and ambientradiation levels. PADEP makes thisdata available to the NRC. The NRCalso conducts an independentmonitoring program of the ambientradiation levels near the SSES.Inspectors from the NRC regularly visitboth PP&L's Corporate Office and theSSES to review procedures and records,.conduct personnel interviews, observe


Introduction

activities first-hand, and generallyexamine the programs supporting theefauent and environmental monitoringfor the SSES.

REMP MonitoringSensitivityThe sensitivity of the SSES REMP wasdemonstrated in 1986, following theproblem with the Chernobyl reactor inthe former Soviet Union. When theChernobyl incident occurred, the SSESREMP was able to detect a relativelysmall increase in the level ofgross betaactivity in air samples at both controland indicator locations, as well as thepresence of some specific radioactivematerials that are not normally observed.Detection of radiation and radioactivematerial from the SSES in the

„, environment is complicated by thepresence ofnaturally occurring radiationand radioactive materials from bothterrestrial and cosmic sources, as well asman-made radiation and radioactivematerial from non-SSES sources, suchas nuclear fallout from p'revious nuclearweapons tests and medical wastes.Together, this radiation and radioactivematerial present background levels fromwhich an attempt is made to distinguishrelatively small contributions from theSSES. This effort is complicated by thenatural variations that typically occurfrom both monitoring location tolocation and with time.

The naturally occurring radionuclidespotassium-40, beryllium-7, radium-226,and thorium-228 are routinely observedin certain environmental media.Potassium-40 has been observed in allmonitored media and is routinely seen atreadily detectable levels in such media asmilk, meat, fish, and fruits andvegetables. Seasonal variations in

beryllium-7 in air samples are regularlyobserved. Man-made radionuclides,such as cesium-137 and strontium-90leftover from nuclear weapons testingare often observed as well. In addition,the radionuclide tritium, produced byboth cosmic radiation interactions in theupper atmosphere'as well as man(nuclear weapons), is anotherradion'uclide typically observed.

Radioactivity levels in environmentalmedia are usually so low that theirmeasurements, even with state-of-the-art measurement methods, typically havesignificant degrees ofuncertaintyassociated with them.(18) As a result,expressions are often used whenrefemng to these measurements thatconvey information about the levelsbeing measured relative to themeasurement sensitivities. Terms suchas "minimum detectable concentration"(MDC) are used for this purpose. Whenthe value of the MDC for a specificmeasurement is compared to the valueof the actual measurement, thecomparison provides information aboutthe difficultyin differentiating theactivity being measured frombackground activity. The formulas usedto calculate MDCs may be found inAppendix E.

The methods ofmeasurement for sampleradioactivity levels used by PP&L'scontracted REMP radioanalyticallaboratory are capable ofmeeting theanalysis sensitivity requirements found inthe SSES Technical Specifications.Summary descriptions of the analyticalprocedures and the accompanyingcalculational methods used by thelaboratory can be found in Appendix E.

10 1996 Radiological Environmental Monitoring Report

Exposure Pathways to Humans

0

0

C

Gaseous EfflueutK

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0

SQ Ill~0-C~ 0 00'

DirectIrradiation

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Figure 1

FIGURE 2

1996 RADIATIONLEVEL MONITORINGLOCATIONSWITHINONE MILE OF THE SSES

GOULDISLAND

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. FIGURE31996 RADIATIONLEVEL MONITORINGLOCATIONS

FROM ONE TO FIVE MILES OF THE SSES

SUSQUEHANNARl VER

2

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FIGURE 41996 RADIATIONLEVEL MONITORING LOCATIONS

GREATER THAN FIVE MILES FROM THE SSES

15Fi

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SUSQUEHANNARIVER

I

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FIGURE 51996 ENVIRONMENTALSAMPLING LOCATIONS

WITHINONE MILEOF THE SSES

I

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RTRRAX TRRRR

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FIGURE 6

1996 ENVIRONMENTALSAMPLING LOCATIONSFROM ONE TO FIVE MILES OF THE SSES

NORTHSHICKSHINNY

SUSqlJEHANN A

RIVER

2

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FIGURE 7

1996 ENVIRONMENTALSAMPLING LOCATIONSGREATER THAN FIVE MILES FROM THE SSES

l6HX 2

LNANTICOKESUSQUEHANNA

RIVER-rg

GLEN LYON

148 ICKSHINN

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-A'MBIKNTRADIATIONMONITORING

INTRODUCTION

The principal or primary method for theSSES REMP's measurement ofambientradiation levels is the use ofthermoluminescent dosimeters (TLDs).The TLDs are crystals (calcium sulfate)capable ofdetecting and measuring lowlevels of radiation by absorbing a

portion of the radiation's energy that isincident upon them and storing thecaptured energy until the TLDs areprocessed (read). Processing involvesheating the TLDs to release their storedenergy in the form oflight and

measuring the intensity of the light thatthey emit. The intensity of the emittedlight is proportional to the amount ofradiation to which they were exposed.Calibration of the TLD processorspermits a reliable relationship to beestablished between the light emittedand the amount of radiation dosereceived by the TLD's; the resultpermits accurate measurements of theambient radiation in the environment.

Environmental TLDs are continuallyexposed to natural radiation from theground (terrestrial radiation) and fromthe sky'(cosmic) radiation. In

addition,'hey

also may be exposed to non-natural(man-made) radiation. Most of theenvironmental TLD's natural radiationexposure comes from sources in theground. These terrestrial sources varynaturally with time due to changes insoil moisture, snow cover, etc. Thenatural-radiation picture is complicatedbecause these factors affectin radiationreaching the TLDs from the ground varydifferently with time from one location

to another due to locational differencesin such factors as soil characteristics(amounts oforganic matter, particlesize, etc.), drainage opportunities, and

exposure to sunlight. EnvironmentalTLDs can also be affected by directradiation (shine) from the SSES turbinebuildings during operation, radwastetransfer and storage, and radioactivegaseous effluents from the SSES.

Unfortunately, TLDs do not have anyinherent ability to indicate the source ofthe radiation to which they'are exposed.The placement ofnumerous TLDs in theenvironment can facilitate decision-making about the possible radiationsources to which TLDs are exposed.However, a method for evaluating TLDdata is still required. The SSES REMPrelies on a statistically-based approachto simultaneously compare indicatorTLD data with control TLD data andoperational TLD data withpreoperational TLD data. Thisapproach permits the flagging ofenvironmental TLD doses that mighthave been produced by both non-naturalsources of radiation, as well as naturalradiation sources. It also provides a

means for attributing a portion of thetotal TLD dose to SSES operation ifappropriate. Appendix E, pages E-6through E-10, provides a description ofthe process for evaluating the results ofTLD measurements.

1996 Environmental Radiological Monitoring Rcport 18

Ambient Radiation Monitorin

~Sco e

TLDsThe area around the SSES was dividedfor monitoring purposes into sixteensectors radiating outwards from theplant site, each encompassing an areadescribed by an arc of22.5 degrees.TLDs were placed in all 16 sectors at

varying distances from the plant.Monitoring locations were chosenaccording to the criteria presented in theNRC Branch Technical Position onRadiological Monitoring (Revision 1,

November, 1979).(17) The locationsfor the TLDs were selected byconsidering factors such as localmeteorological, topographical, andpopulation distribution characteristics.

At the end of 1996, the SSES REMPhad 78 indicator TLD locations andeight control TLD locations. This levelofmonitoring exceeds that which isrequired by the Nuclear RegulatoryCommission. The indicator TLDsnearest the SSES are positioned at thesecurity or perimeter fences surroundingthe site. This is the closest that a

member of the public would be able toapproach the station. The control TLDsare the most distant from the SSES,ranging from 10 to 20 miles from thesite.

The PIC data at each monitoringlocation were collected and stored bydataloggers for successive periods ofapproximately one month each during1996 and analyzed. The dataloggerswere programmed to provide hourly

- results for each monitoring period.From.this information, overall hourlyaverages were obtained for eachmonitoring period.

Monitorin Results

TLDsTLDs were retrieved and processedquarterly in 1996. Average ambientradiation levels measured byenvironmental TLDs increased eachquarter of 1996 from the first throughthe fourth quarters, with the exceptionof the second quarter when themeasured exposures were less thanthose from the first quarter at bothindicator and control locations as shownin the figure below. Refer to Figure 8

which trends both indicator and controldata quarterly from 1973 through 1996.

PICsPressurized ion-chamber (PIC) data wascollected continuously at locations inBerwick (PIC 1), Nanticoke (PIC 4),Shickshinny (PIC 3), and at theSusquehanna Energy Information Center(PIC 2) in 1996. Nanticoke was thecontrol location.

19 1996 Environmental Radiological Monitoring Report

Ambient Radiation Monitorin

;::.'<''." <'.-'.i1 896 HEMP,.'Qua ite'irlg'TL'0<Ice'ra'ge's''>"!~<%~j<~%'"'-"""'~'"""a'si""I'~34~~)." k6""':"""-""'.

h<m„

4>)@

The 1996 annual average exposures forindicator and control locations were18.1 mR/std. qtr. and 18.6 mR/std. qtr.,respectively. The 1996 annual averageexposure for indicator locations exceedsthe corresponding 1995 annual averageexposure by 0.8 mR/std. qtr. The 1996annual average exposure for controllocations exceeds the corresponding1995 annual average exposure by 1.2mR/std. qtr. The 1996 annual averageexposures at both indicator and controllocations are within the ranges ofannualaverages for the prior operational periodat each type ofmonitoring location.However, the 1996 indicator average isbelow the corresponding range ofaverages for the preoperational period,while the 1996 control average is aboveits corresponding range for thepreoperational period. Refer to Figure 8

at the end of this section which trendsquarterly TLD results for bothpreoperational and operational periodsat the SSES. Refer to Appendix H,Table H 1, page H3 for a comparison ofthe 1996 mean indicator and controlTLD results with the means for thepreoperational and prior operationalperiods at the SSES.

When indicator environmental TLDresults for 1996 were examinedquarterly on an individual location basisand compared with both current controllocation results and preoperational data,very small SSES exposure contributions.

'eresuggested at onsite location 9S2 inquarters 1, 2, and 4 and onsite locationIIS3 in all fourquarters of1996. It is

possible that these SSES attributableexposures were actually not the result ofSSES operations, but, in fact, resultedfrom fluctuations in backgroundradiation levels. Refer to Appendix E,page E-6, for a discussion of"TLDData Interpretation." TLD results forall locations for each quarter of 1996may be found in Appendix I, Table I-1,beginning at page I-2.

The estimated quarterly exposurecontributions were summed by locationfor the entire year. The largest dosesuggested was 3.4E-3 millirem at anonsite monitoring location, 11S3, 0.3mile southwest of the SSES. This dosewas used for determining compliancewith SSES Technical SpecificationLimit3.11.4 for annual efHuentreporting purposes. This dose amountsto only 0.014% of the 25 mrem whole-

1996 Environmental Radiological Monitoring Rcport 20

Ambient Radintion Monitorin

body dose limitofSSES TechnicalSpecification 3.11.4.

PICs

PIC data for 1996 resulted in annualaverages for indicator and controllocations of 17.7mR/std. qtr. and17.9 mR/std. qtr., respectively. The1996 indicator mean is 0.3 mR/std. qtr.above the 1995 indicator mean, whilethe 1996 control mean is the same as thecontrol mean for 1995.

Comparisons of the absolute TLDmeasurements with the absolute PICmeasurements must consider thesignificant diAerences in the above-ground elevations ofPICs and

'nvironmentalTLDs. (PICs are locatedat higher above-ground elevations thanthe TLDs.) Comparisons ofchanges inPIC and TLD data are probably mostuseful in the sense that increases ordecreases in either TLD or PIC data

may be confirmed by similar changes inthe other.

21 1996 Environniental Radiological Monitoring Report

e

50

45

40

AMBIENTRADIATIONLEVELSBASED ON TLDDATA

Exposure Rate (mR/STD QTR)

35

30

25

20

P REOP ERATIONAL OP ERATIONAL

UNIT2CRITICALITY

10

0I I I I I I I I I I

@b @b @be

—indicator —ControlFIGURE 8 - HGWlRemp96.prs

II',Vy;iI~tIIggyV~+CV, rVm NW~VVNgWg~M,~YC~

j.';:;:."'':,":"'.'".':-'":=":.-.-""'':A'"QUA]"IC.'pATH'6?A'Y,'.""MOM-'ROMNG~','"."-;„-",'~„.:„-'„";

INTRODUCTION

The followingmedia were monitored in1996 by the SSES REMP in the aquaticpathway: surface water, drinking water,fish, and sediment. Some ofthe media

(e.g.; drinking water and fish) provideinformation that can be especially usefulto the estimation ofpossible dose to thepublic from potentially ingestedradioactivity, ifdetected. Other media,such as sediment, can be useful fortrending radioactivity levels in theaquatic pathway primarily because oftheir tendency to assimilate certainmaterials that might enter the surfacewater to which they are exposed. Theresults from monitoring all of thesemedia provide a picture ofthe aquaticpathway that is more clear than thatwhich could be obtained ifone or morewerc not included in the REMP.

Fruits or vegetables that are grown infields irrigated with surface water wouldalso be in the aquatic pathway. A landuse census (Reference 55) conducted inl996 looked at farms. within 10 milesdownstream of the SSES. No farmswere found to have irrigated during the1996 growing season.

monitoring results. The potential existsfor radioactive material that might be,,present in SSES airborne releases toenter the Susqueltanna River. upstreamofthe plant through either direct

~ deposition (e;g., settling or washout) orby way ofrunofffrom deposition onland adjacent to the river. Directdeposition and runoffare considered to

'e

potentially insignificant as means ofentry for SSES radioactivity into theSusquehanna River when compared toliquid discharges under normalconditions.

Lake Took-a-While(LTAW),which is .

'ocatedin PPM.'s RiverlandsRecreation Area adjacent to theSusquehanna River, is also consideredto be part ofthe aquatic pathway formonitoring purposes. Although it is notin a position to receive water dischargedto the river from the SSES, it canreceive storm runofffrom the SSES.Storm runofffrom the SSES site shouldnot normally contain any measurableradioactivity from the plant. However,the SSES REMP, consistent with otheraspects ofaquatic monitoring and theREMP, in general, goes beyond itsrequirements by monitoring LTAW.

Thc aquatic pathway in the vicinityofthc SSES is the Susquehanna River.Monitoring ofall of the aquatic media,except drinking water, is conducted bothdownstream and upstream of thelocation from which occasional SSESlow-level radioactive discharges enterthe river. The upstream monitoringlocations serve as controls to providedata for comparison with downstream

1996 Radiological Environmental Monitoring Report 23

A uatic Pathwa Monitorin

~Sco e

Surface WaterSurface water was routinely sampledfrom the Susquehanna River at fourindicator locations (6SS,'12F1, 12G2,and 12H1), in the SSES discharge lineto the river (6S7), Lake Took-A-While(LTD), and two control locations(1D3 and 6S6) during 1996.

Drinking WaterDrinking water samples were collectedat location 12H2, the Danville MunicipalWater Authority's treatment facility onthe Susquehanna River, in 1996.Treated water is collected from the endof the processing flowpath, representingfinished water that is suitable fordrinking. This is the nearest pointdownstream of the SSES discharge tothe River at which drinking water isobtained. No drinking water controllocation is sampled. For all intents andpurposes, control surface watersampling locations would be suitable forcomparison

FishFish were sampled from theSusquehanna River in the spring and fallof 1996 at one indicator location, IND,downstream of the SSES liquiddischarge to the River and one controllocation, 2H, sufficiently upstream toessentially preclude the likelihood thatthe fish caught there would spend anytime below the SSES discharge, Inaddition, fish were also sampled fromPPEcL's Lake Took-a-While, locationLTAW. This location is notdownstream of the SSES discharge. Itis sampled because of its potential for

receiving runoff'rom the SSES. LTAWis considered an indicator location.

SedimentSediment sampling was performed in thespring and fall at indicator locations 7B,11C, and 12F and control locations 28and 2F on the Susquehanna River. Inaddition, sediment was also obtainedfrom location.LTAW.

Sam lin

Surface WaterWeekly grab sampling was performed atthe indicator location 6S5. Weekly grabsamples were composited both monthlyand biweekly at this location. Location6SS was considered a backup forlocation 6S7 in the event that watercould not be obtained from theautomatic sampler at this location.Nevertheless, 6SS was sampledroutinely throughout 1996, since it is theclosest downstream sampling point tothe SSES discharge.

Indicator location 6S7, the SSESCooling Tower Blowdown Discharge(CTBD) line, and control location 6S6,the SSES River Water Intake structure,were sampled time proportionally usingautomatic continuous samplers. Thesamplers were set to obtain 30-60 mlaliquots every 20 minutes. Weekly, thewater obtained by these samplers wasretrieved for either biweekly or monthlycompositing. Composite sampling alsowas performed at location 12H1, theMerck Chemical Company, by Merckpersonnel.

The other surface water monitoringlocations (1D3, 12F1, 12G2; and

199G Radiological Environnicntal Monitoring Rcport

II

LTAW)were grab sampled once eachmonth.

Drinking 8'aterTreated water was sampled timeproportionally by an automatic sampler.The sampler was set to obtain 30-60 mlaiiquots every twenty minutes. Weekly,the water obtaihed by this sampler wasretrieved for either biweekly or monthlycomp ositing.

FishFish were obtained by electrofishing.Electrofishing stuns the fish and allowsthem to float to the surface so that thoseof the desired species and su6icient sizecan be sampled. Sampled fish includerecreationally important species, such as

smallmouth bass, and also channelcatfish and white suckers. The fish arefilleted and the edible portions are keptfor analysis.

SedimentShoreline sediment, ob't'ained to depthsof four feet ofwater. was collected at allsediment sampling locations. Inaddition, sediment referred to as"flocculated" was also sampled at oneindicator location, 7B, and one controllocation, 2B. Flocculated sedimentcomprises the top, loose layer in theriver that is easily moved and shifled bythe water. It is composed of finerparticles with greater surface area tovolume ratios than the particles ofshoreline sediment. Flocculatedsediment is believed to be more in touchwith water, giving it more potential topick up any radionuclides that the watermay be carrying.

A uatic Pathwa" Moniforin

Sample Preservationand Anal sis

Surface and Drinking Water;- .Surface and drinking water sampleswere analyzed monthly for gross alphaand beta activities, the activities ofgamma-emitting radionuclides, andtritium activities. Iodine-131 wasanalyzed biweekly for compositesamples and monthly for the grabsamples.

To optimize the accuracy of thesesample analyses, preservatives wereadded to the samples as soon aftercollection as practical. Nitric acid wasadded to sample aliquots destined forgross alpha and beta activity.analysisand the analysis ofgamma-emittingradionuclide activity analysis. Sufficientacid was added to reduce the pH ofthese sample aliquots to approximatelytwo in order to reduce the potential forradionuclides leaving the water anddepositing on the sides of the samplecontainers.

Sodium bisulfite was added to samplealiquots destined for iodine-131 analysisin amounts equivalent to one gram pereach gallon ofwater. This amount wasrecommended by the radioanalyticallaboratory (Teledyne BrownEngineering) analyzing the samples.The purpose for sodium bisulfiteaddition is to reduce the potential forvolatilization and loss of iodine fromsamples by maintaining it in a chemicallyreduced form.

Sediment and FishFish are frozen until shipment. Allsamples are analyzed by gamma

1996 Radiological Enrirontncntal Monitoring Rcport 25

uatic Pathw Monitorirt

spectroscopy for the activities ofanygamma emitting radionuclides that maybe present. Fish are also analyzed forgross beta activity levels. This analysiswould be ofbenefit in the unlikely eventthat man-made, non-gamma emittingradionuclides might appear in fishwithout the simultaneous occurrence ofdetectable man-made gamma-emittingradionuclides. In addition, elevatedgross beta activity levels could indicatethe need for more sensitive gammameasurements to be performed.

Monitorin Results

Surface 8'aterResults &om specific sample analyses ofsurface water may be found in

'ablesI-2 and I-3 ofAppendix I. Asummary ofthe 1996 surface water datamay be located in Table G ofAppendixG. Comparisons of 1996 monitoringresults with those ofpast years may befound in Tables H 2 through H 5 ofAppendix H.

The Nuclear Regulatory Commission(NRC) requires that averages of theactivity levels for indicatorenvironmental monitoring locations andfor control environmental monitoringlocations ofsurface water, as well asother monitored media, be reported tothe NRC annually. Data from thefollowing six surface water monitoringlocations were averaged together asindicators for reporting purposes: fourlocations ( 6SS, 12F1, 12G2, and 12H1)on the Susquehanna River downstreamof the SSES, Lake-Took-a While(LTAW)adjacent to the river, and theSSES cooling tower'lowdowndischarge (CTBD) linc to the river(6S7).

Technically, the CTBD line is not part ofthe environment. The CTBD line'is abelow ground pipe to which the publichas no access, contraty to the other=:environmental monitoring locations onthe Susquehanna River to which thepublicdoeshaveaccess. However, it

'urrentlyis required that the water'thatis discharged to the Susquehanna Riverthrough the CTBD line &om the SSESbe included as an indicator monitoringlocation in the radiologicalenvironmental monitoring program.

Most ofthe water entering theSusquehanna River through the SSESCTBD line is simply water that wastaken &om the river upstream oftheSSES, used for cooling purposeswithout being radioactivelycontaminated, and returned to the river.Nevertheless, batch discharges ofrelatively small volumes ofslightlyradioactively contaminated water aremade to the river through the SSESCTBD at times throughout each year.The water is released &om tanks ofradioactively contaminated water on siteto the CTBD and mixes with thenoncontaminated water already presentin the CTBD. How rates from the tankscontaining radioactively contaminatedwater being discharged to the CTBD arelimited to a maximum of200 gpm. Inaddition, the. minimum flow rate for thereturning water in the CTBD ismaintained at a flow rate of5,000 gpmor higher. These requirements are inplace to ensure adequate dilution ofradioactively contaminated water by thereturning noncontaminated water in theCTBD prior to entering the river.At the point that CTBD water enters theriver, additional, rapid dilution ofthe

26 1996 Radiological Environmental Monitoring Reporth

A uatic Palhwa Moniforin

discharged water by the river ispromoted by releasing it through adiffuser. The diffuser is a large pipewith numerous holes in it that ispositioned near the bottom ofthe river.CTBD discharges exit the diffuserthrough the many holes, enhancing themixing ofthe discharge and river waters.

'he

concentrations ofcontaminants arereduced significantly as the dischargedwater mixes with the much larger flowofriver water. The mean flow rate ofthe Susquehanna River in 1996 wasapproximately 10,400,000 gpm. This ismore than 2,000 times the requiredminimum flow rate through the CTBDfor discharges to be permitted.

The amounts ofradioactivelycontaminated water being dischargedare small. Nevertheless, sensitiveanalyses of the water samples can offendetect the low levels ofcertain types ofradioactivity in the CTBD waterfollowing dilution. Though the levels ofradioactivity measured in the CTBDwater are generally quite low, they tendto be higher than those in the riverdownstream of the SSES. Mostradionuclides discharged from the SSESCTBD are at such low levels in thedownstream river water that, even withthe sensitive analyses performed, theycannot be detected.

When the radioactivity levels from theCTBD samples throughout the year areaveraged with those obtained fromactual downstream monitoring locations,the result is an overall indicator locationaverage that is too high to berepresentative of the actual averageradioactivity levels of the downstreamriver water. As the followingdiscussions are reviewed, consideration

should be given to this inflation ofaverage radioactivity levels from theinclusion ofCTBD gocation 6S7)results in the indicator data that isaveraged.

The 1996 data for gross alpha activityanalyses ofsurface water are similar tothose of 1995. The 1996 mean gross,

. alpha activity of0.76 pCi/liter forindicator locations is only slightly higher .

than the 0.6 pCi/liter for the 1995indicator mean gross alpha activity.Both ofthese annual means are wellbelow the average ofthe annual meansfor gross alpha activity at indicatorlocations reported for the previousSSES operational period '1984 through1995. No annual mean gross alphaactivities for surface water are availablefor comparison from the preoperationalperiod. The 1996 mean gross alphaactivity of0.45 pCi/liter for controllocations also is slightly greater than the1995 control mean gross alpha activityof0.3 pCi/liter. Once again, the 1995and 1996 annual means for gross alphaactivities at control locations are bothwell below the average ofthe annualmeans for the prior operational period ofthe SSES.

Although, the low annual mean gross'lphaactivity for indicator locations is

higher than the mean gross alpha activityfor control locations in 1996, this is notbelieved to be the result of the release ofman-made, alpha emitting radionuclidesfrom the SSES. Effluent monitoring atthe SSES has not reported the dischargeofany alpha emitting radionuclides fromthe SSES. The observed levels ofgrossalpha activity for both indicator andcontrol locations are thought to resultfrom the presence ofnaturally occurring

1996 Radiological Environmental Monitoring Rcport 27


alpha emitting radionuclides that arepart ofthe uranium-238 and thorium-232 decay chains.

The 1996 data for gross beta activityanalyses ofsurface water are similar tothose of 1995. The 1996 mean grossbeta activity of5.6 pCi/liter for indicatorlocations is the same as the 1995indicator mean gross beta activity. Bothofthese mean activities areapproximately the same as the averageofthe annual means for the previousoperational period of the SSES, buthigher than the range ofannual meansfor the preoperational period. The 1996mean gross beta activity of3.7 pCi/literfor control locations is slightly higherthan the 3.5 pCi/liter for the 1995control mean gross beta activity. It iswithin the ranges ofthe annual meansfor the previous operational andpreoperational periods. Refer toFigure 9 which trends gross betaactivities separately for surface waterindicator and control locations quarterlyfrom 1975 through 1996.

calculation ofthe 1996 mean gross betaactivity for indicator locations, the meanindicator activity drops from5.6 pCi/liter to 4.4 pCi/liter. This meanactivity is more representative ofthegross beta activity in river waterdownstream of the SSES than the meanindicator activity with data from location6S7 included. The activity dischargedto the Susquehanna River by the SSEShas little measurable impact on the grossbeta activity levels ofthe SusquehannaRiver.

The 1996 means for iodine-131 activityat indicator and control surface watermonitoring locations were 0.13 pCi literand 0.15 pCi/liter, respectively. Boththe 1996 indicator and control means foriodine-131 activity are lower than1995's corresponding activity means.Both 1996's indicator and control meanactivities are less than the averages ofthe annual means for both indicator andcontrol locations for both the prioroperational period of the SSES as wellas the preoperational period.

Comparison of the 1996 indicator meanto the 1996 control mean as well as

comparison of the 1996 indicator meanto the average ofannual means forindicator locations during thepreoperational period indicates a

contribution ofbeta activity from theSSES. This is primarily because of theinfluence of the gross beta activitiesmeasured in samples obtained fromindicator location 6S7, the SSEScooling tower blowdown discharge(CTBD) line, on the average ofallindicator locations.

Ifgross beta activities measured for 6S7samples are excluded from the

Throughout the course ofa year, iodine-131 is typically measured at levels inexcess ofanalysis MDCs in somesamples obtained from control surfacewater monitoring locations on theSusquehanna River upstream of theSSES as well as indicator locationsdownstream of the SSES. Asdetermined by measurements ofsamplesobtained by the SSES REMP, the meaniodine-131 activity level from the CTBDfor all of 1996 was approximately0.32 pCi/liter. This may be compared tothe activity level of0.15 pCi/liter forcontrol surface water monitoringlocations in 1996.


A uatic Pathtva Monitorin

Iodine-131 from the discharge ofmedical wastes into the SusquehannaRiver upstream ofthe SSES is drawninto the SSES cooling tower basinsthrough the SSES River Water IntakeStructure. It is not unreasonable toassume that concentration of the alreadyexisting iodine-131 in the cooling towerbasins occurs as it does for othersubstances found in the river. Forexample, the SSES routinely assumesconcentrations factors in the basin forcalcium offour to five times theconcentrations in the river waterentering the basins, based on pastmeasurements. This concentratingeffect occurs because of the evaporationof the water in the basins, leaving behindmost dissolved and suspended materialsin the unevaporated water remaining inthe basins. Ifa concentration factor offour for iodine-131 were to be appliedto the 1996 mean iodine-131 activitylevel for the control samples from theSusquehanna River, a meanconcentration of0.60 pCi/liter foriodine-131 in the basin water and thewater being discharged from the basinswould be expected. The actual 1996mean for the CTBD iodine-131 activitylevel was less than this.

Because iodine-'131 is radioactive,unlike th'e calcium that has beenmeasured, iodine-131 is removed fromthe water while it is in the basinsthrough the radioactive decay. process.Thus, it might be expected that the netconcentration factor for iodine-131would be somewhat less than that forcalcium, considering this additionalremoval process. The extent to whichthe iodine-131 concentration factor isless than that for calcium would dependon the mean residence time for the water

in the basins compared to iodine-131'sradioactive half-life - the greater theratio ofthe mean residence time to thehalf-life, the smaller the concentrationfactor. Amean residence time forwaterin the basins is expected to be about twodays. This is only about one-fourth ofthe approximately eight-day half-life ofiodine-131. Thus, the concentrationfactor for iodine-131 is not expected tobe much below four. Therefore, thedifference between the 1996 meaniodine-131 activity ofabout0.32 pCi/liter in the CTBD and the 3996mean iodine-131 activity for the controllocations of0.15 pCi/liter may be, atleast partially, accounted for throughconcentration in the basins.

No iodine-131 was identified in SSESliquid efHuent during 1996. None oftheiodine-131 activity measured in excessofthe analysis MDCs in environmentalsurface water samples in 1996 isattributed to SSES operation.

The 1996 mean tritium activity forindicator locations was less than halfofthe corresponding 1995 mean while the1996 mean tritium activity for controllocations was greater than the

1995'ontrol

mean. The 1996 means fortritium activity at indicator and controllocations were 310 pCi/liter and8 pCi/liter, respectively. The 1996indicator mean is less than the averageof the annual means reported for theoperational period of the SSES. The1996 control mean is lower than theaverages of the annual means reportedfor both prior operational andpreoperational monitoring periods.Refer to Figure 10 which trends tritiumactivity levels separately for surface

1996 Radiological Environtncntal Monitoring Rcport 29


water indicator and control locations&om 1972 through 1996.

The 1996 indicator mean tritium levelfor all surface water locations can bemisleading for those interested in themean tritium level in the SusquehannaRiver downstream ofthe SSES for1996. The much higher levels oftritiumobs'erved in the CTBD (location 6S7),when averaged with the low levels fromthe downstream sample analysis results,distort the real environmental picture. Ifthe tritium activities &om location 6S7are excluded from the data used tocalculate the 1996 indicator meantritium activity level for surface water,the mean becomes approximately20 pCi/liter.

In spite ofthe fact that the tritiumactivity levels reported for 6S7 are fromthe discharge line prior to dilution in theriver, the highest quarterly averagetritium activity reported at 6S7 during1996 was 2,509 pCi/liter for the secondquarter, well below the NRC non-routine reporting levels for quarterlyaverage activity levels of20,000 pCi/liter when a drinkingpathway exists or 30,000 pCi/liter whenno drinking water pathway exists.

The tritium activity reported in theCTBD line from location 6S7 isattributable to the SSES. Refer to the"Dose from the Aquatic Pathway"discussion at the end of this section foradditional information on the projecteddose to the population from tritium andother radionuclides in the aquaticpathway attributable to the SSES.

The only gamma-emittingradionuclide measured in surface waterat an activity'level exceeding an analysisMDC in 1996 was naturally occurringpotassium-40. Potassium-40 was seenabove an analysis MDC in one sample

~ during 1996.

Drinking 8'aterDrinking water was monitored during1996 at the Danville Water Company's .

facility26 miles WSW ofthe SSES onthe Susquehanna River. From 1977(when drinking water samples were Grstcollected) through 1984, drinking watersamples were also obtained from theBerwick Water Company at location12F2 (12F3), 5.2 miles WSW oftheSSES. The drinking water supply forthe Berwick Water Company is not,however, water from the SusquehannaRiver; it is actually well water.

There are no known drinking watersupplies in Pennsylvania on theSusquehanna River upstream of theSSES and therefore no drinking watercontrol monitoring locations. DanvilleDrinking water analysis results may becompared to the results for surfacewater control monitoring locations.

Results from specific sample analyses ofdrinking water may be found inTable IQ ofAppendix I. A summary ofthe 1996 drinking water data may belocated in Table G ofAppendix G.Comparisons of 1996 monitoring resultswith those ofpast years may be found inTables H 6 through H 8 ofAppendix H.

Gross alpha activity has been monitoredin drinking water since 1980. Grossalpha activity has been observed atlevels above the analysis MDCs in a

30 1996 Radiological Environmental Monitoring Rcport

A uatic Pafhwa Monitorin

small minority ofthe samples during. most years since 1980. In 1996, as in

1995, no samples were reported withgross alpha activity levels above theanalysis MDCs. The 1996 mean grossalpha activity level for drinking waterwas 0.17 pCi/liter. The 1996 meanalpha activity is significantly below theaverage ofthe corresponding annualmean for both the prior operationalyears as well as the preoperationalperiod. The mean gross alpha activity islower than the means ofmost of theprevious years because ofthe averagingmethod used since 1991.

The 1996 mean gross alpha activity fordrinking water is less than the 1996gross alpha activity level of0.45 pCi/liter for surface water controllocations. No gross alpha activity indrinking water during 1996 is attributedto liquid discharges from the SSES tothe Susquehanna River. I

Gross beta activity has been monitoredin drinking water since 1977. Grossbeta activity is typically measured atlevels exceeding the MDCs in drinkingwater samples. The 1996 mean grossbeta activity level for drinking water was2.4 pCi/liter. The 1996 mean is belowthe 1995 mean gross beta activity levelfor drinking water but within the rangesof the corresponding annual means forthe prior operational and preoperationalperiods of the SSES. Refer to Figure 11

which trends gross beta activity levelsseparately for drinking water indicatorand control locations from 1977 through1996.

The 1996 mean gross beta activity fordrinking water is less than the 1996gross beta activity level of3.7 pCi/liter

for surface water control locations. Nogross beta'ctivity in drinking waterduring 1996 is attributed to liquiddischarges from the SSES to theSusquehanna River.

Iodine-131 was not measured in excessofanalysis MDCs'in any drinking watersamples in 1996. This compares withresults from three samples for whichanalysis MDCs were exceeded in 1995.The 1996 mean iodine-131 activity levelin drinking water samples was0.045 pCi/liter. This is less than the1995 mean drinking water activity levelof0.07 pCi/liter and less than the 1996mean of0.15 pCi/liter for surface watercontrol locations. No iodine-131activity in drinking water during 1996 is

'ttributedto liquid discharges from theSSES to the Susquehanna. River.

Tritium was measured in excess ofananalysis MDC only one time in '1996.

The 1996 mean tritium activity level fordrinking water was 39 pCi/liter. The1996 mean tritium activity level isslightly higher than the 1995 mean of26 pCi/liter, but less than the averagesof the corresponding annual means forboth the prior operational andpreoperational periods of the SSES.The mean tritium activity is lower thanthe means ofmost of the previous yearsbecause of the averaging method usedsince 1991.

The low 1996 mean tritium activity level .

for drinking water is higher than the1996 mean tritium activity level of8 pCi/liter for surface water controllocations. This difference is probablydue to liquid discharges from the SSESand is, therefore, attributable to theSSES operation. The very small dose


A uatrc Pathw 'Monitonn

resulting to the public has beenaccounted for by estimations based onthe levels oftritium measured by theREMP during 1996 in the CTBD linewhich discharges to the SusquehannaRiver. Refer to the "Dose &om theAquatic Pathway" discussion at the endofthis section ("Aquatic PathwayMonitoring") ofthis report.

No gammawmitting radionuclides weremeasured above the analysis MDCs forgamma spectroscopic analyses ofdrinking water samples during 1996.

FishResults from specific sample analyses offish may be found in Table I 5 ofAppendix I. A summary ofthe 1996

'ishdata may be located in Table G ofAppendix G. Comparisons of 1996monitoring results with those ofpastyears may be found in Tables H 9 andH 10 ofAppendix H.

Four species offish were sampled ateach ofone indicator location and onecontrol location on the SusquehannaRiver in June, 1996 and again inOctober, 1996. The species includedthe following white sucker, smallmouthbass, and channel catfish and redhorse.In addition, one largemouth bass wassampled from PP&L's LTAWinOctober, l996. A total of 13 fish werecollected and analyzed.

As in every fish sample taken since thespring of 1984, when gross betaanalyses first began to be performed onfish flesh, all fish samples hadmeasurable gross beta activity levels inexcess ofanalysis MDCs. The 1996indicator and control means for grossbeta activity levels in fish were

essentially the same at 5.9 pCi/gram and5.8 pCi/gram, respectively. The 1996indicator and control means are1.6 pCi/gram and 2.9 pCi/gram higherthan the 1995 corresponding means.-.'.

The 1996 indicator and control meansare within the corresponding ranges of .

annual means for the indicator andcontrol location for previous years. 'Nogross beta activity in fish during 1996 isattributed to liquid discharges fi.om the =

'SESto the Susquehanna River.

The only gammawmitting radionuclidemeasured in excess ofanalysis MDCs infish during 1996 was naturally occuiringpot~ium-40., The 1996 indicator andcontrol means for the activity levels of

'otassium-40in fish are essentially equalat 3.5 pCi/gram. The 1996 indicatorand control means are slightly lowerthan the 1995 indicator and controlmeans. Both tbe 1996 indicator andcontrol means are within the ranges oftheir corresponding annual means forprior operational and preoperationalyears. Naturally occurring potassium-40in fish is not attributable to the liquiddischarges from the SSES to theSusquehanna River.

SedimentBoth the shoreline and flocculatedvarieties ofsediment were sampled inJune, 1996 and again inNovember, 1996. Results from specificsample analyses ofsediment may befound in Table I-6 ofAppendix I. Asummary ofthe 1996 sediment data maybe located in Table G ofAppendix G.Comparisons of 1996 monitoring resultswith those ofpast years may be found inTables H 11 through H 14 ofAppendix H.

, ~


A aattc athw Wonitorin

Naturally occturing potassium-40,radium-226 and thorium-228 weremeasured at activity levels aboveanalysis MDCs in all shoreline sedimentsam les in 1996. Naturall occurrin.P y gberyllium-7 was found above analysisMDCs in seven 1996 samples.

h

The 1996 indicator and control meansfor potassium-40 activity levels inshoreline sediment were 11.4 pCi/gramand 12.2 pCi/gram, respectively. The1996 indicator and control means forpotassiumQO activity are slightly lowerthan their corresponding 1995 means.These 1996 means were higher,however, than the averages of thec'orresponding annual means for all prioroperational as well as preoperationalyears.

The 1996 indicator and control meansfor radium-226 activity levels inshoreline sediment were 1.7 pCi/gramand 1.9 pCi/gram, respectively. The1996 indicator mean radium-226 activityis slightly lower than the corresponding1995 mean while the 1996 control meanis slightly higher than its corresponding1995 mean. Similar to thc situation withpotassiumAO, these 1996 radium-226means werc higher than the averages ofthe corresponding annual means for allprior operational as well as

preoperational years, but within thecorresponding ranges ofannual meansfor the prior operational period.

The 1996 indicator and control meansfor thorium-228 activity levels inshoreline sediment were 1.0 pCi/gramand 1.2 pCi/gram, respectively. Thesemeans are essentially the same as, oridentical to the averages of thecorresponding means for 1995 and for

'prior operational years. The naturallyoccurring radionuclides in sedimentdiscussed above are not attributable tothe liquid discharges &om the SSES tothe Susquehanna River.

Cesium-137 was the only man-maderadionuclide measured at activity levelsin shoreline sediment exceeding analysis

. 'MDCs during 1996. The 1996 indicatorand control means for cesium-137

~ activity levels in sediment were0.088 pCi/gram and 0.084 pCi/gram,respectively. The 1996 indicator meanis slightly higher than the 1995 indicatormean, while the 1996 control mean isslightly lower than the 1995 controlmean. The 1996 indicator and controlmeans are less than the averages ofcorresponding annual means for bothprior operational as well as

preoperational years. This cesium-137in the sediment is attributed to residualfallout from past atmospheric nuclearweapons tests.

The results for the monitoring offlocculated sediment in 1996 weresimilar to those for the monitoring ofshoreline sediment.

Dose from the AquaticPathwa

Tritium was the only radionuclideidentified in 1996 by the SSES REMP inthe aquatic pathway that was bothattributable to SSES operation and alsoincluded in the pathway to man.

The maximum whole-body and organdoses to hypothetical maximally exposedindividuals in four age groups (adult,teenager, child, and infant) weredetermined according to the

1996 Radiological Environmental Monitoring Report 33


methodology ofthe Offsite DoseCalculation manual using the LADTAPIIcode. This is in accordance withSSES Technical Specification 3/4.11.1.2which requires consistency in liquidefHuent dose calculations with NRCRegulatory Guide 1.109.

For the purpose ofperforming the dosecalculation, tritium was assumed to bepresent continuously in the CTBD linethroughout 1996 at a level equivalent tothe difference between the annual meanactivity level of 1,760 pCi/liter for theCTBD line and the annual mean activitylevel of8 pCi/I for control surface watermonitoring locations. The annual meanflow rate for the CTBD line of7,990gpm was multiplied times this differencein mean activity levels to obtain anequivalent annual discharge ofabout 28curies oftritium in 1996. (This is about5.5 curies less than the total amount oftritium reported to have been released in1996 from SSES efHuent monitoring.)

Doses were estimated at the nearestdownriver municipal water supplier viathe drinking water pathway and near theoutfall of the SSES discharge to theSusquehanna River via the fish pathway.The maximum whole body and organdoses were estimated to be less than0.0004 mrem to an adult and an adult'slower large intestine.


PCI/LITER20

18

GROSS BETA ACTIVITYINSURFACE WATER

-16

14P REOP ERATIONAL OP ERATIONAL

10 UNIT 2CRITICALITY

I I

FIGURE 9 - HGWlRemp96.prs

I I

o~)e

—Indicator —Control

0TRITIUMACTIVITYIN SURFACE WATER

PCI/LITER2200

2000

1800

1.600

1400

1200

1000

800

600

400

200

0

P REOP ERATIONAL

~~

OP ERATIONAL

UNIT2CRITICALITY

I I I

pbbs. qh q% <P q5 qb qS q'b gQ

1990 Data is not included in this figure because the data was suspect.

FlGURE 10 - HGINRemp96.prs —Indicator— —Control—

10PCI/LITER

GROSS BETA ACTIVITYINDRINKINGWATER

P REOP ERATIONA7

OPERATIONAL

UNIT2CRITICALITY

FIGURE 11 - HGlNRemp96.prs

INTRODUCTION

-„",:;.-~,'.;;::. ATMOSPHERIC PATHWAY'MO~MTORING,"

additional information concerning thischange in air monitoring locations.

Atmospheric monitoring by the SSESREMP involves the sampling andanalysis ofair and precipitation.Because the. air is the first medium thatSSES vent releases enter in the'pathwayto man, it is fundamental that it bemonitored. Mechanisms do exist for thetransport ofairborne contaminants toother media and their concentration inthem. For example, airbornecontaminants may move to the terrestrialenvironmental and concentrate in milk.Concentrations ofradionuclides canmake the sampling and analysis ofmedialike milk more sensitive approaches forthe detection of radionuclides, such asiodine-131, in the pathway to man thanthe monitoring ofair directly. (PPEcLalso samples milk; refer to theTerrestrial Pathway Monitoring sectionof this report.) Nevertheless, thesensitivity ofair monitoring can beoptimized by the proper selection ofsampling techniques and the choice of

'he

proper types ofanalyses for thecollected samples.

~sco e

Air samples were collected onparticulate filters and charcoal cartridgesat indicator locations 3S2, 5S4, 7S7,10S3, 12S1, 13S6, 9B1, and 12E1 andcontrol locations 6G1, 7G1 and 8GI. Inaddition, precipitation was collected atall of the air sampling locations.Location 7G1 was monitored until theend ofMarch when it was replaced bylocation 8G1. Refer to Appendix A for

Sam lin and Anal sis

AirAt all times during the year, the SSES,REMP was monitoring the air at least,eight indicator locations and two controllocations. The SSES TechnicalSpecifications require monitoring at onlya total offive sites. Monitoring isrequired at three locations at the SSESsite boundary in different sectors withthe greatest predicted sensitivities forthe detection ofSSES releases. Also,monitoring must be performed at thecommunity in the vicinity of the SSESwith the greatest predicted sensitivityand a control monitoring location that isexpected to be unaffected by any routineSSES releases. SSES TechnicalSpecifications do not require themonitoring ofprecipitation.

Airborne particulates were collected onglass fiber filters using low volume(typically 2.0 to 2.5 cfm sampling rates)air samplers that run continuously. Airiodine samples were collected oncharcoal cartridges, placed downstreamof the particulate filters.

Particulate filters and charcoal cartridgeswere exchanged weekly at the airmonitoring sites. Sampling times wererecorded on elapsed-time meters. Airsample volumes for particulate filtersand charcoal cartridges were measuredwith temperature-compensated dry-gasmeters.


Atmos herie Pathiipa Monitorin

Airfilters were analyzed weekly forgross beta activity, then composited=

quarterly and analyzed for the activitiesofgamma-emitting radionuclides. Thecharcoal cartridges were analyzedweekly for iodine-131.

PrecipitationPrecipitation samples were collected atleast. monthly in 1996. During thoseperiods with higher precipitation levels,collection containers may have beenemptied more frequently than once permonth to prevent a loss ofsample due tooverflowing collection containers.Precipitation collections werecomposited at the end of the applicablecalendar quarters and the quarterlycomposites were analyzed.

Precipitation was analyzed for theactivities ofgamma-emittingradionuclides and tritium activity.Sample portions were preserved thesame as other water samples, dependingon the types ofanalyses they were toundergo. Refer to the Aquatic PathwayMonitoring section of this report for a

description of the appropriatepreservation techniques.

prior to SSES operation, before 1982,the unusually high gross beta activitieswere generally attributable to falloutfrom atmospheric nuclear weapons-tests.Typical gross b'eta activities measuredon air particulate filters are the result of

.naturally occurring radionuclidesassociated with dust particles suspendedin the sampled air. They are thusterrestrial in origin.

'I

Particulate gross beta activity levels foreach monitoring location and monitoringperiod in 1996 are presented inTable I-8 ofAppendix I. Comparisonsof 1996 gross beta analysis results withthose ofprevious years may be found inTable H 15 ofAppendix H. Annualmeans for the beta activities oftheindicator and control locations in 1996of 15.6 pCi/m and 14.7 pCi/m',respectively, are near the low end ofthecorresponding ranges ofpreviousoperational yearly averages. 1996annual means are significantly below th'

corresponding lower ends oftheirpreoperational yearly averages. Nocontribution ofradioactivity from theSSES is discernible from 1996 airbornegross beta data.

Monitorin Results

AirParticulatesGross beta activity is always measuredat levels in excess ofthe analysis MDCson the fiber filters. The highest grossbeta activity levels that have beenmeasured during the operational periodof the SSES were obtained in 1986following the Chernobyl accident in theformer Soviet Union. Figure 12 trendsthe quarterly mean indicator and controllocation gross beta activities separatelyfrom 1974 through 1996. Note that

Quarterly gamma spectroscopicmeasurements ofcomposited filtersoften show the naturally occurringradionuclide beryllium-7. Occasionally,other naturally occurring radionuclides,potassium-40 and radium-226 are alsoobserved. Beryllium-7 is cosmogenic inorigin, being produced by the interactionofcosmic radiation with the earth'atmosphere. The other two gamma-emitting radionuclides originate fromsoil and rock.

1996 Radiological Enrironmcntal Monitoring Rcport 39

Atmos heric Pathwa Monitorin

Betyllium-7 was measured aboveanalysis MDCs for all quarterlycomposite samples in 1996. The 1996indicator and control means forberyllium-7 activity were 132 E-3 pCi/m', and 126E-3 pCi/m',respectively. The 1996 indicator andcontrol means exceeded the range ofallcorresponding annual means for prioroperational and preoperational years.Beryllium-7 activity levels for each 1996calendar quarter at each monitoringlocation are presented in Table I-9 ofAppendix I. Comparisons of 1996beryllium-7 analysis results withprevious years may be found inTable H 16 ofAppendix H.

Potassium-40 was seen in excess ofanalysis MDCs in some quarterlycomposites during 1996. The 1996indicator and control means forpotassium-40 activity were 5.4E-4 and4.5 E-5 pCi/m', respectively. Thesevalues are both below the averages ofcorresponding annual means forprevious years. No other gamma-emitting radionuclides were reported forair in 1996. Beryllium-7 and potassium-40 are not attributable to SSESoperation.

AirIodineIodine-131 has been detectedinfrequently from 1976, when it was firstmonitored, through 1996. Sinceoperation of the SSES began in 1982,iodine-131 has only been positivelydetected in air samples in 1986 due tothe Chernobyl accident. No iodine-131was reported for the 1996 airmonitoring results.

PreeipitadonGamma spectroscopic measurementswere first performed on precipitationsamples during the preoperational year1980. Normally, beryllium-7 is the onlygamma-emitting radionuclide that isseen in precipitation. It is observed onlyin a minority ofsamples during each

monitoring year at levels exceeding theMDCs for its analyses. Beryllium-7 is

naturally occurring, produced by cosmic.radiation. Occasionally, other naturallyoccurring, gamma-emittingradionuclides, such as potassium-40,which is terrestrial in origin, are alsoobserved in a small number ofsamplesthroughout the year. Theseobservations are likely the results ofdustparticles in the precipitation, eitherwashed from the atmosphere by theprecipitation or entering theprecipitation collector as the result ofsettling of the dust particles from the air.

The man-made, gamma-emittingradionuclide cesium-137 has beenidentified in precipitation samples atlevels exceeding analysis MDCsinfrequently. In fact, not since 1989 hascesium-137 been measured in excess ofan analysis MDC. Prior to 1989,cesium-137 had previously beenobserved in precipitation samples fromindicator and/or control locations in1981, 1985, 1986, 1987, 1988, and1989. Its observation in precipitationfrom 1986 through 1989 may have beenthe result of residual cesium-137 in theatmosphere from the Chernobylaccident. Otherwise, the observances ofthe relatively long-lived (30-year half-life) cesium-137 are attributable toprevious atmospheric nuclear weaponstesting.


Atmos herie Pathwn Monitorin

The only year in which other man-maderadionuclides were reported inprecipitation by the SSES REMP wasthe preoperational year 1981. That yearthe fission product radionuclideszirconium-95, niobium-95, ruthenium-103, cerium-141, and cerium-144 werereported. These radionuclides wereprobably the result ofChineseatmospheric nuclear weapons testing in1980. They could not have beenproduced by the SSES because neitherunit at the station had been in operationyet.

The only gamma-emitting radionuclidemeasured at activity levels in excess ofthe MDCs for analyses in 1996 was thenaturally occurring beryllium-7;

Comparisons ofannual means for tritiumactivity measurements with'the annualmeans from previous years may befound in Table H 17 ofAppendix H.The 1996 indicator and control meantritium activity levels were -7 pCi/I and-4 pCi/1, respectively. The 1996indicator mean is below thecorresponding range for the annualmeans ofprevious years. The 1996control mean is within thecorresponding range for the annualmeans ofprevious years. AnalysisMDCs were not exceeded for anyindicator or control analyses in 1996.

The mean level (-7 pCi/I) of tritium inprecipitation for indicator locations is

negative. Consequently there is noreason to consider a dose estimate to thepublic for tritium in precipitation.

1996 Radiological Environrncntal Monitoring Rcport 41

E-03 PCl/M3

GROSS BETA ACTIVITYINAIRPARTICULATES

500

450

400A

350P REOP ERATIONAL OP ERATlONAL

CHINESEWEAPONS TEST

A - 06/17/74B - 09/26/76C - 11/17/76D - 09/17/77E - 03/14/78F - 10/15/80

300

250

200 D

150

100

50

0

UNIT 2CRITICALITY

CHERNOBYL4/26/86

—indicator—Control

FlGURE 12 - HGINRemp96.prs

,

' 'TKIO&STRIALPATHWAYMONITORING

INTRODUCTION

The following media were monitored inthe Terrestrial Pathway in 1996: soil,milk, fruits and vegetables, and game.

Soil can be a great accumulator ofman-made radionuclides that enter it. Theextent of the accumulation in the soildepends ofcourse on the amount of theradionuclides reaching it, but it alsodepends on the chemical nature of thoseradionuclides and the particularcharacteristics of the soil. For example,the element cesium, and, therefore,cesium-137 can be bound very tightly toclay in soils. The amount ofclay in soilcan vary greatly from one location toanother. In highly clay soils, cesium-137 may move very slowly and also maybe taken up vary slowly in plants as theyabsorb soil moisture.

Any medium, such as soil, that tends toaccumulate radioactive materials canalso provide more sensitivity forradionuclide detection in the .

environment than those media thatdon'. Such a medium facilitates theearly identification of radionuclides inthe environment, as well as awareness ofchanges that subsequently may occur inthe environmental levels of the identifiedradionuclides.

The SSES REMP samples soil near allthe REMP air sampling stations. Thepurpose for soil sampling near the airsampling sites is to make it easier tocorrelate air sampling results with soilsampling results ifany SSES related

radioactive material were found in eithermedium. Sampling is performed atdifferent depths near the surface to help

'rovide information on how recentlycertain radioactive materials may haveentered the soil. Sampling at more thanone depth also may help ensure thedetection ofmaterials that moverelatively quickly through the soil. Suchquick-moving materials may havealready passed through the topmostlayer of soil at the time of sampling.

Milkwas sampled at four locations andfruit and vegetable samples wereobtained at seven more locations thanrequired in 1996. SSES TechnicalSpecifications only require that theSSES REMP sample milk at the threemost sensitive monitoring locations nearthe SSES and one control locationdistant from the SSES. SSES TechnicalSpecifications only require that fruit andvegetables be sampled at locationsirrigated by Susquehanna River frompoints downstream of the SSESdischarge to the River. There are onlytwo locations within ten milesdownstream of the SSES that have beenknown to irrigate with water from theSusquehanna River during unusually dryperiods. These locations do not irrigateevery year. No irrigation was performedat any of the farms surveyed in the 1996Land Use Census (reference 55).

No requirement exists for the SSESREMP to monitor soil and game. Allmonitoring of the terrestrial pathwaythat is conducted by the SSES REMP inaddition to milk and certain fruit andvegetables is voluntary and reflects

1996 Radiological Environnicntal Monitoring Rcport 43

Terrestrial Pnthiva Monitorin

PP&L's willingness to exceed regulatoryrequirements, ifnecessary, to ensurethat the public and the environment are

protected.

~Sco e

SoilSoil was sampled once, in accordancewith their scheduled annual samplingfre'quencies, at each of the ten REMP airsampling locations, 3S2, SS4, 7S7,10S3, 12S1, 13S6, 9B1, 12E1, 6G1,and 8G1 in September 1996. Locations6G1 and 8G1 were control samplinglocations; the remaining sampling siteswere indicator locations.

Top and bottom soil plugs were taken,representing soil to a depth oftwoinches in the first case and soil from a

depth of two inches to six inches in thesecond case, at a total of 10 monitoringlocations in 1996. Twelve plugs'romeach layer were composited for analysisat each location, as is routine. A total of20 soil samples were analyzed in 1996.

MilkMilkwas sampled at least monthly at thefollowing four locatidns in 1996: 10DI,10D2, 10G1, and 12B3.

Milkwas sampled semi-monthly fromApril through October when cows weremore likely to be in the pastures. Theselocations are believed to be the mostsensitive monitoring sites available forthe detection of any radionuclides thatmight be released from the SSES andfind their way into milk from local dairyfarms. Location 10G1 is the one controllocation that is sampled by the SSESREMP. A total of76 milk samples from

both indicator and control locationswere analyzed in 1996.

Fruits and VegetablesFruits and vegetables were sampled atnine locations in eight different sectorssurrounding the SSES during theharvest season. Sixteen different kindsoffruits and vegetables were obtainedfor a total of43 samples. Samples wereobtained from the following locations:2BS, 8A4, 9B4, 10BS, 11D1, 12S7,12F7, 13G2, and 14B3. Location 13G2was the control location

The availability offruits and,vegetablesfrom growers typically varies from oneyear to the next. For example,gardeners may grow different plants orchoose not to plant gardens. Anattempt is made each year to obtainsamples from the most sensitivelocations. This leads to the intentionalsubstitution ofsome gardens for othersbased on consideration ofannualmeteorological data and availablegardens as indicated in the Land UseCensus from the previous year.

Two growers at locations 11D1 and12F7 are required to be monitored everyyear because they have been identifiedas having irrigated with SusquehannaRiver water from downstream of theSSES at some time in the past. Thesegrowers are sampled each year eventhough there are oAen years withadequate rainfall when no irrigation isperformed.

GameThirteen different game samples werecollected from nine different sectors atthe following nine locations in 1996:


Terrestrial Pat'hiva Monitorin

2B, 3S, SS, 7S, 10S, 11S, 13G, 16F,and 16H.

Game samples in 1996 included deer,squirrel, and rabbit. The samplingmethod for deer is typically recovery ofthe flesh from road-killed animals.Small game samples are usually obtainedby hunting. While picking up road killsis not particularly time intensive, huntingsmall game frequently is time intensive.Factors that determine the opportunitiesfor sampling are complex, and, for themost part, beyond the sampler's control.As a result, it is dif5cult to be able toensure that the same numbers and typesofgame samples are collected each year.

Sample Preservation'ndAnal sis

The only sample medium monitored inthe terrestrial pathway in whichpreservatives are used is milk. Sodiumbisulfite is added to milk samples at therate of40 grams per gallon. This bothhelps maintain iodine in a reduced formand reduces the spoilage rate.

All media in the terrestrial pathway areanalyzed for the activities ofgamma-emitting radionuclides using gammaspectroscopy. The other analysis that isroutinely performed is the radiochemicalanalysis for iodine-131 in milk.

Mon itorin Results

The only man-made radionuclidesnormally measured at levels in excess ofanalysis MDCs in the terrestrial pathwayare strontium-90 and cesium- 137.Strontium-90 analyses are not nowroutinely performed for any media

samples in the terrestrial pathway.Strontium-90 activity would be expectedto be found routinely in milk as theresult offallout from previous nuclearweapons tests ifanalyses. were beingperformed for it. SSES TechnicalSpecifications do not require that milk.be analyzed for strontium-90.Strontium-90 analyses may beperformed at any time ifthe results ofother milk analyses would showdetectable levels of fission productactivity which might suggest the SSESas the source. Cesium-137 normally hasbeen measured in excess ofanalysisMDCs in most soil samples. Cesium-137 has also been seen oAen at levelsabove the MDCs in game. Thisradionuclide also is present in theenvironment as a residual from previousatmospheric nuclear weapons testing.

Certain naturally-occurringradionuclides are also routinely foundabove analysis MDCs in terrestrialpathway media. Potassium-40, a

primordial and very long-livedradionuclide, which is terrestrial inorigin, is observed in all terrestrialpathway media exceeding analysisMDCs. Other naturally-occurringradionuclides oAen observed aboveMDCs are thorium-228 and radium-226in soil, and beryllium-7 in vegetation andin fruits and vegetables.

The results of the 1996 terrestrialpathway monitoring resemble those ofthe past. Results for specific sampleanalyses of terrestrial pathway mediamay be found in Tables I-l 1 throughI-14 ofAppendix I. A summary of the1996 terrestrial monitoring data may belocated in Appendix G. Comparisons of1996 monitoring results with those of

1996 Radiological Environntcntal Monitoring Rcport 45

Terrestrial'Pathwa Monitorin

past years may be found in Tables H 18

through H 25 ofAppendix H.

SoilThe 1996 analysis results for all gamma-emitting radionuclides, naturallyoccurring potassium-40, radium-226,and thorium-228 and man-made cesium-137, that are routinely measured in soilat levels exceeding analysis MDCs weresimilar to those for previous years. Noother gamma-emitting radionuclideswere reported at levels above analysisMDCs in soil in 1996.

The 1996 means for indicator andcontrol location sample potassium-40activity were 10.7 pCi/gram and13.6 pCi/gram, respectively. Bothmeans were within the ranges ofcorresponding means for prioroperational years, but higher than theranges ofpreoperational means. This isnot the result ofSSES operationbecause the potassium-40 is naturallyoccurring. The 1996 indicator mean forpotassium-40 was slightly less than thecorresponding 1995 mean, while the1996 control mean was higher than itscorresponding 1995 mean.

The 1996 means for indicator andcontrol location sample radium-226activity were 1.5 pCi/gram and1.6 pCi/gram, respectively. Thesemeans are within the ranges of theannual means for the previousoperational period of the SSES,although they are above thecorresponding ranges of annual meansobtained during the preoperationalperiod. This is not the result of SSESoperation because the radium-226 is

naturally occurring.

The 1996 means for indicator andcontrol location sample thorium-228activity were 0.8 pCi/gram and1.0 pCi/gram, respectively. The 1996indicator and control means for thorium-228 are both lower than thecorresponding 1995 means. Both the1996 indicator and control means arewithin their ranges ofcorrespondingmeans for the previous operationalperiod ofthe SSES. However, the 1996indicator mean is below the range ofcorresponding means for thepreoperational period. Thorium-228 insoil is not the result ofSSES operationbecause it is naturally occurring.

The 1996 means for indicator andcontrol location sample cesium-137activity were 0.2 pCi/g and 0.4 pCi/g,respectively. These means are withinthe corresponding ranges of annualmeans for prior operational years. The1996 indicator mean is below the rangeof the corresponding range ofannualmeans for preoperational years.Cesium-137 levels in soil samplestypically vary widely from sample tosample. Levels ofcesium-137 activity in1996 samples varied by more than a

factor of ten over the entire range.Cesium-137 in soil, although man-made,is not from the operation of the SSES.It is residual fallout from previousatmospheric nuclear weapons testing.

MilkIodine-131 has been chemicallyseparated in milk samples and countedroutinely since 1977. Refer to Figure 13

which trends iodine-131 activity in milkseparately for indicator and controllocations from 1977 through 1996.

Typically, iodine-131 is not reported atlevels exceeding the MDCs for the


Terrestrial Palht'va Monit'orin

analyses in any milk samples during a

monitored year. The 1996 monitoringyear was no exception; no iodine-131above the analysis MDCs were observedin either indicator or control samples.

The preoperational years 1976, 1978,and 1980 were exceptional years in thesense that iodine-131 activity wasobserved in excess ofMDCs due tofallout from atmospheric nuclearweapons testing. Iodine-131 activitywas also measured at levels exceedingMDCs in milk samples in 1986 in thevicinity of the SSES as a result of theChernobyl incident. Subsequent levelsobserved near the baseline ofFigure 13

in 1991 and 1992 represent backgroundfluctuations in data that appear as a

result ofaveraging methods. Noiodine-'31

levels exceeding analysis MDCswere observed in milk during theseyears.

Fruits and VegetablesWith the exception of the measurementofnaturally occurring beryllium-7 in onevegetable sample, naturally occurringpotassium-40 was the only gamma-emitting radionuclide reported in fruitsand vegetables at activity levels inexcess ofanalysis MDCs. The 1996means for indicator and control locationsample potassium40 activity were2.0 pCi/gram and 1.9 pCi/gram,respectively. The 1996 indicator andcontrol means are less than thecorresponding 1995 means and less thanthe averages of the annual potassium-40means for both prior operational yearsand preoperational years. The 1996control mean is below the range ofannual means for both prior operationaland preoperational periods. Potassium-40 in fruits and vegetables is notattributable to SSES o'peration becauseit is a naturally occurring radionuclide.

With the exception of the naturallyoccurring potassium40, no gamma-emitting radionuclides were measured inexcess ofanalysis MDCs in 1996. The1996 means for indicator and controllocation sample potassium-40 activitywere 1325 pCi/liter and 1295 pCi/liter,respectively. The 1996 indicator andcontrol means were less than thecorresponding 1995 means. The 1996indicator and control means forpotassium-40 activity were within theranges of annual means for bothprevious operational years andpreoperational years. The potassium-40activity in milk is not attributable to theSSES operation because it is naturallyoccurring.

GarneThe only two gamma emittingradionuclides measured in game in 1996were the naturally occurring potassium-40 and the man-made radionuclidecesium-137. The 1996 means forindicator and control location samplepotassium-40 activity were 3.5 pCi/gramand 3.3 pCi/gram, respectively. The1996 annual indicator mean is within therange ofprior operational annual meansand the range ofpreoperational annualmeans for potassium-40 activity ingame. Normally, control game samplesare not obtained. In 1996, however,two samples were collected at distancesbeyond 10 miles from the SSES. To beconsistent with the application of thedistance criterion in categorizing othersamples/locations, these samples wereconsidered to be controls. The


Terrestrial Pathiva Monitorin

potassium-40 in game is not attributableto SSES operation because it is naturallyoccurring.

The 1996 mean for indicator locationsample cesium-137 activity was0.2 pCi/gram. This is identical to thecorresponding 1995, 1994 and 1993

means and less than the averages of theannual means for both prior operationalyears as well as preoperational years.

Cesium-137 activities normally varygreatly between game samples,especially between types ofgame. Forexample, in 1996 the indicator meancesium-137 activities were as follows:0.51 pCi/gram for squirrels,0.033 pCi/gram for deer, and0.0023 pCi/gram for rabbits. This is

probably the result ofdifferences in thetypes of food consumed. Acorns andmushrooms have been found to havehigher levels ofcesium-137 than otherpotential foodstuffs. These would bepart of the diets ofdeer and especiallysquirrels, but not routinely eaten byrabbits. Cesium-137 levels measured inexcess ofanalysis MDCs in game arenot attributable to SSES operationbecause they are present principally as

. the result of fallout from previousatmospheric nuclear weapons tests.


IODINE-131 ACTIVITYINMILK'00

PCI/LITER

90 PRE OPERATIONAL OP ERATIONAL

80

70Chinese Weapon Test

9/12/77

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I I

UNIT 2CRITICALITY

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FIGURE 13- HGINRemp96.prsE9lndicator KHControl-

:GROUND WATER'MONIT'ORING,

INTRODUCTION. ~Sco e

Normal operation ofthe SSES does notinvolve the release of radioactivematerial to ground water directly orindirectly through the ground. As a

result, there are no efHuent monitoringdata to verify or to compare with REMPground water monitoring results.Ground water could conceivablybecome contaminated by the washout ordeposition of radioactive material thatmight be airborne. Ifdeposited on theground, precipitation/soil moisture couldaid in the movement of radioactivematerials through the ground to water.that could conceivably be pumped fordrinking purposes. (No use ofgroundwater for irrigation near the SSES hasbeen identified.)

Because routine SSES operationreleases primarily isotopes ofxenon andkrypton and tritium to the air, noradionuclides attributable to SSESoperation are expected to be observed inground water. Iodine and particulatereleases to the air are negligible.Gaseous xenon and krypton tend toremain airborne; deposition or washoutof these would be expected to be veryminimal. Tritium would be the mostlikely radionuclide to reach the groundwith precipitation and, ifnot lost tostreams (surface water) by runoA; movereadily through the soil to the groundwater.

In spite of the improbability ofmeasuring any radioactivity attributableto SSES operation'in the ground waterin the SSES vicinity, it was sampled

, monthly at four indicator locations (2S6,4S4, 4SS, and 12S1) and one controllocation (12F3) during 1996.

With the exception oflocation 4S4,untreated ground water was sampled.Untreated meaning that the water has

not undergone any processing such as

filtration, chlorination, or softening. Atlocation 4S4, the SSES Training Center,well water actually is obtained from on-site and piped to the Training CenteraAer treatment. This sampling is

performed as a check to ensure that thiswater has not been radioactivelycontaminated. Sampling is performed atthe Training Center to facilitate thesample collection process.

Sample Preservation 4,Anal sis

All samples (except the aliquotsassigned for tritium analyses) werepreserved with nitric acid the same as

described in the section of this report onAquatic Pathway Monitoring.

Ground water samples were analyzedfor the activities ofgamma-emittingradionuclides and tritium activity.Gamma spectrometric analyses ofground water were begun in 1979 andtritium analyses in 1972, both prior toSSES operation.


Ground Water Monitorin

Monitorin Results

Tritium activity levels in ground waterhave typically been observed to be lowerthan surface water tritium levels. Anoticeable decline occurred between1992 and 1993 in the ground watertritium levels. Fewer measurements oftritium resulted in levels above theanalysis sensitivities in 1993 than in1992.

Gamma spectrometric analyses haveidentified and measured gamma-emittingradionuclides in excess ofMDCs in onlya few samples in all the years that theseanalyses have been being performed.The naturally occurring radionuclidespotassium-40 and thorium-228 havebeen measured above their MDCsoccasionally in ground water.Potassium-40 has been measured aboveMDCsin 1979, 1981, 1985, 1991,1992, and 1993. Thorium-228 has beenobserved above MDCs.in 1985 and1986. The man-made radionuclidecesium-137 has been measured aboveMDCs only occasionally since'979. Itspresence has always been attributed toresidual fallout from previousatmospheric nuclear weapons tests.

During 1996, tritium levels weremeasured in excess ofanalysis MDCs inground water samples on only fouroccasions. The 1996 mean tritiumactivity levels for indicator and controlground water monitoring locations were22 pCi/liter and 27 pCi/liter,respectively. These levels are bothhigher than those for 1995 when theindicator and control ground watermonitoring location means were11 pCi/liter and 17 pCi/liter,respectively. Both the 1996 and 1995indicator and control mean tritiumactivity levels are significantly below thecorresponding averages ofannual meansfor prior operational and preoperationalyears. A decline in tritium averages forvarious waters, including ground water,-first occurred in 1991 when dataaveraging methods changed. Anotherdecline in tritium averages was noted in1993 for waters generally.

No gamma-emitting radionuclides weremeasured at levels in excess ofanalysisMDCs in 1996 in ground water samples.The results from gamma spectroscopicanalyses indicated that no radioactivity

'ontributionsto ground water from theSSES were identifiable in 1996.

The results of the 1996 REMP groundwater surveillance resemble those of thepast. Results for specific ground watersample analyses may be found inTable I-7 ofAppendix I. A summary ofthe 1996 ground water monitoring datamay be located in Appendix G.Comparisons of 1996 monitoring resultsfor tritium with those ofpast years maybe found in Table H 26 ofAppendix H.


RKFKRENCES ":,''.:,-'.

Radiation Management Corporation, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, Report 81 (April-December 1972)" RMC-TR-73-14, July 1973.

Radiation Management Corporation, "Susquehanna Steam Electric Station, Pre-operational Radiological Environmental Monitoring Program 1973," RMC-TR-74-07, May 1974.

Radiation Management Corporation, "Susquehanna Steam Electric Station,Preoperational Radiological Environmental Monitoring Program, 1974 AnnualReport," RMC-TR-75-07, April 1975.

Radiation Management Corporation, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1975 Annual Report,"RMC-TR-76-05, May 1976.

Radiation Management Corporation, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1976 Annual Report,"RMC-TR-77-04, March 1977.

Radiation Management Corporation, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1977 Annual Report,"RMC-TR-78-01, May 1978.

Radiation Management Corporation, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1978 Annual Report,"RMC-TR-79-01, April 1979.

Radiation Management Corporation, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1979 Annual Report,"RMC-TR-80-01, March 1980.

Radiation Management Corporation, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1980 Annual Report,"RMC-TR-81-02, July 1981.

10. Radiation Management Corporation, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1981 Annual Report,"RMC-TR-82-03, July 1982.

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


Re erenees

12. Radiation Management Corporation, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1982 Operational Report."RMC-TR-83-02, April 1983.

13. NUS Corporation, "Susquehanna Steam Electric Station, Radiological'Environmental Monitoring Program, 1983 Annual Report," NUS-4516March 1984.

14. Pennsylvania Power and Light Company, "Susquehanna Steam Electric Station,Environmental Report, Operating License Stage," May 1978.

15. Pennsylvania Power and Light Company, "Susquehanna Steam Electric Station,Final Safety Analysis Report".

16. United States Nuclear Regulatory Commission, OEice ofNuclear ReactorRegulation, "Final Environmental Statement Related to the Operation ofSusquehanna Steam Electric Station, Units 1 and 2," Docket Nos. 50-387 and50-388, June 1981.

17. United States Nuclear Regulatory Commission, "An Acceptable RadiologicalEnvironmental Monitoring Program," Radiological Assessment Branch TechnicalPosition, November 1979, Revision 1.

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

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

20. Denham, D.H., Roberts, M.C., Novitsky, W.M., Testa, E.D., "Investigation ofElevated Cesium-137 Concentrations in Small Game in Luzerne County,Pennsylvania." Proceedings ofPapers presented at Health Physics Society TenthMidyear Topical Symposium, October 11-13, 1976, pgs 271-279.

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

22. Currie L.A., "Lower LimitofDetection: Definition and Elaboration ofa ProposedPosition for Radiological EfHuent and Environmental Measurements,"NUREG/CRA007, September 1984.


Re erences

23.

24.

Pennsylvania Power and Light Company, "Susquehanna Steam Electric Station,Semi-annual EfHuent Waste Disposal Report, Data Period: January - June 1986",

August 1986.M

Pennsylvania Power and Light Company, "Susquehanna Steam Electric Station,Semi-annual EfHuent Waste Disposal Report, Data Period: July-December 1986," February 1987.

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

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

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

28. Pennsylvania Power and Light Company, "Susquehanna Steam Electric Station,Semi-annual EfHuent Waste Disposal Report, Data Period: January - June 1987,August 1987.

29. Pennsylvania Power and Light Company, "Susquehanna Steam Electric Station,Semi-annual EfHuent Waste Disposal Report, Data Period: July - December 1987,February 1988.

30. Pennsylvania Power & Light Company, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1987 Annual Report,"April 1988.

31. Pennsylvania Power & Light Company, "Susquehanna Steam Electric Station,Semi-annual EfHuent Waste Disposal Report, Data Period: January-June 1988,"August 1988.

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

33. Pennsylvania Power & Light Company, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1988 Annual Report,"April 1989.

34 Pennsylvania Power & Light Company, "Susquehanna Steam Electric Station,Semi-annual EfHuent Waste Disposal Report, Data Period: January-June 1989,"August 1989.


Re erenees

35. Pennsylvania Power &Light Company, "Susquehanna Steam Electric Station,Semi-annual EfHuent Waste Disposal Report, Data Period: July-December 1989,"

February 1990.

36. Pennsylvania Power &Light Company, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1989 Annual Report,"April 1990.

37. Pennsylvania Power &Light Company, "Susquehanna Steam Electric Station,Semi-annual EfHuent Waste Disposal Report, Data Period.-'anuary-June 1990,"August 1990.

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

39. Pennsylvania Power &Light Company, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1990 Annual Report,"April 1991.

40. Pennsylvania Power & Light Company, "Susquehanna Steam Electric Station,Semi-Annual EfHuent Waste Disposal Report, Data Period: January - June 1991,"August 1991.

41. Pennsylvania Power & Light Company, "Susquehanna Steam Electric Station,Semi-Annual EfHuent Waste Disposal Report, Data Period: July I-December, 1991," February 1992.

4'7

43.

Pennsylvania Power & Light Company, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1991 Annual Report,"April 1992.

Pennsylvania Power & Light Company, "Susquehanna Steam Electric Station,Semi-Annual EfHuent Waste Disposal Report, Data Period: January - June 1992,"August 1992.

44.

45.

Pennsylvania Power & Light Company, "Susquehanna Steam Electric Station,Semi-Annual EfHuent Waste Disposal Report, Data Period: July I-December 1992," February 1993.

4

Pennsylvania Power & Light Company, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1992 Annual Report,"April 1993.


Re erences

46. Pennsylvania Power &Light Company, "Susquehanna Steam Electric Station,Annual EQluent &Waste Disposal Report, Data Period: January - December1993, March 1994.

47. Pennsylvania Power & Light Company, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1993 Annual Report,"April, 1994.

48. Pennsylvania Power &Light Company, "Susquehanna Steam Electric Station,Annual EQluent &Waste Disposal Report," Data Period: January-December .

1994, March, 1995.

49. Ecology III, Inc., "Susquehanna Steam Electric Station, 1994 Land Use Census,"November, 1994.

50. Pennsylvania Power & Light Company, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1994 Annual Repo'rt,"April, 1995.

51. Pennsylvania Power & Light Company, "Susquehanna Steam Electric Station,Annual ENuent &Waste Disposal Report," Data Period: January-December 1995, March, 1996.

52. Ecology III, Inc., "Susquehanna Steam Electric Station, 1995 Land Use Census,"October, 1995.

53. Pennsylvania Power & Light Company, "Susquehanna Steam Electric Station,Radiological Environmental Monitoring Program, 1995 Annual Report,"April, 1996.

54. Pennsylvania Power & Light Company, "Susquehanna Steam Electric Station,Annual ENuents & Waste Disposal Report," Data Period: January - December1996, March 1997.

55. Ecology III, Inc., "Susquehanna Steam Electric Station, 1996 Land Use Census,"November, 1996.


APPENDIX A

1996 RKMP CHANGES


A endix A

Ambient Radiation Level Monitorin

Environmental TLDs were added at location 8G1, PP&L's System Facilities Center at

the Humbolt Industrial Park, which is situated 12 miles south southeast of theSusquehanna SES, on April9, 1996, at the beginning ofthe second calendar quarter ofmonitoring. These TLDs were added as control TLDs when the air sampling station atlocation 7G1, the Hazleton PP&L Complex 14 miles southeast of the SSES, was movedto location 8G1. They were added to be consistent with the SSES REMP's practice ofmaintaining TLDs at all of its air sampling stations.


Sampling of the SSES Cooling Tower Blowdown Discharge (CTBD) line was initiatedat an additional location, 2S7, on February 5, 1996. A portable ACS was installed at thislocation, which is near the North Gatehouse at the SSES and within the security fence ofthe SSES, in the latter halfof 1994. This sampling location was created as a replacementfor the original CTBD line sampling location 6S7, which is the SSES Sewage TreatmentPlant (STP). Years ofsampling problems at location 6S7 have been attributed in part tothe undesirable characteristics of the CTBD line flow at that location. It is believed thatthe relatively steep gradient of the pipe at 6S7 oflen result in a relatively low depth ofwater and a turbulent flow. In turn, these conditions are believed to promote theintroduction ofair into the sampling line that causes difficulties in controlling thesampling rate. The CTBD line at location 2S7 is believed to maintain a greater depth ofwater than is found at location 6S7 for the same rate offlow, avoiding the turbulencethat is experienced at 6S7.

I

The portable ACS at location 2S7 has the capability to sample in either the time or flowproportional modes. The availability ofa flow signal at location 2S7 due to theproximity ofa flow sensor installed in the CTBD offered the option to sample in a flowproportional mode, rather than be limited to the time proportional sampling that has

always been performed at location 6S7. It was planned to sample in the timeproportional mode at location 2S7 for three months, then switch to flow proportionalsampling at 2S7 for the next three months, while continuing to sample from location6S7. It was intended that simultaneous sampling at both locations might reveal anysignificant differences in data between the two locations that could be attributed to an

artifact ofsampling differences between the locations rather than changes in the eEuent.Sampling problems at both locations in 1996 limited the amount ofdata that actually wasavailable for c'omparison; however, the results that were obtained showed no significantdifference in the data from one location to the other.

Tritium and gross beta results were chosen for this comparison because gross betaactivity is always detected above the analysis MDCs and tritium activity is usuallymeasured in excess ofMDCs. Data for comparison when the ACS was operating in theflow proportional mode was limited because it only operated in that mode betweenJune 3 and August 2, 1996. Operation in the flow proportional mode for the ACS at

1996 Radiological Eniironmcntal Monitoring Rcport A-2

A endixA

2S7 was limited to this period because ofquestions about the reliability ofthe fiow signalbeing obtained during the remainder ofthe year. Data for comparison was furtherlimited by the periods when both ACSs were not operating or were not believed to be

sampling representatively. Nevertheless, a comparison of the data that was availableshowed no significant differences between the two locations. Consequently, changes inthe activity levels ofstation eNuent in the future would not be expected to be maskedwhen comparisons offuture data from location 2S7 are made with past data obtainedfrom location 2S7. It is intended that location 2S7 normally willprovide the sample forthe CTBD line, with location 6S7 being available for sampling when collections atlocation 2S7 are not possible.

'notherchange to the monitoring of the aquatic pathway in 1996 was the elimination ofmonthly algae sampling and analysis at the beginning of 1996. Algae had been sampledat one indicator location and one control location from 1984 through 1995, riverconditions permitting. Algae samples were analyzed for the activities ofgamma-emittingradionuclides. Algae is a very sensitive medium for the detection of radionuclidesreleased in liquid efHuent from the SSES; however, although algae is theoretically in thefood chain leading to man, no transfer of the radionuclides detected in algae has beendemonstrated from fish to man by the SSES REMP.

Periphyton, which include algae, continue to be monitored in the in the SusquehannaRiver near the SSES by the Academy ofNatural Sciences ofPhiladelphia (ANSP) forPP&L as part of the Safety Net Program conducted by the ANSP. This monitoring ismuch more extensive and rigorous than that which had been conducted as part of theSSES REMP. SSES Technical Specifications does not require the sampling and analysisof algae as part of the SSES REMP. In the unlikely event that radionuclides attributableto the SSES would begin to be observed in fish, algae sampling and analysis could bereinstituted as part of the SSES REMP in an effort to better understand the mechanisms .

by which such activity would be taken up by the fish.

Atmos heric Pathwav Monitorin

Thc air sampling station at location 7G1, the Hazleton PP&L Complex 14 milessoutheast of the SSES, was moved to location 8G1, PP&L's System Facilities Center atthe Humbolt Industrial Park, which is situated 12 miles south southeast of theSusquehanna SES. Sampling was terminated at 7G1 and began at 8G1 on March 27,1996. This change was made to obtain a sampling environment more conducive to

, obtaining representative samples. Over a period ofyears, trees that were in relativelyclose proximity to the air sampling station at location 7G1 had grown quite tall.

Gross alpha analyses ofquarterly air particulate filter composites were discontinued atthe beginning of 1996. These gross alpha analyses ofair particulate filter compositeshave been performed since the preoperational year 1980. Gross alpha activity isnormally measured at levels in excess of analysis MDCs. This alpha activity has not beenattributable to the SSES operation; it is terrestrial in origin, resulting from long-lived,

A-3 1996 Radiological Environmental Monitoring Report

A endix A

naturally occumng radionuclides that are part of the dust particles normally suspended inthe air at low concentrations. Analyses for gross beta activity and the activity ofgamma-emitting radionuclides continue to be performed on air particulate filters. Gross alphaactivity analyses ofair particulate filter composites are not required to be performed bySSES Technical Specifications.

Gross alpha and beta analyses ofquarterly composite precipitation samples werediscontinued at the beginning of 1996. Gross alpha activity measurements ofprecipitation have usually produced activity levels higher than analysis MDCs. Grossbeta activity measurements ofprecipitation always produced'activity levels above MDCs.Although no preoperational data from the SSES REMP is available for gross alpha andbeta activity levels in precipitation, comparisons of results from indicator and controllocations during the operational period does not suggest any contribution from the SSES

'peration.Precipitation sampling and analysis is not required to be performed as part ofthe REMP by SSES Technical Specifications. Ifair monitoring in the SSES vicinitysuggests that elevated alpha and/or beta activity may be expected in precipitation in thefuture, gross alpha and beta analyses may be reinstituted.

Terrestrial Pathwa Moriitoriri

Vegetation sampling was discontinued at the beginning of 1996. Vegetation samplingwas performed annually at 10 different soil sampling locations when available from 1986through 1995. Vegetation consisted'of whatever grass and weeds were growing at thesampling sites. The only radionuclides that were identified in vegetation were naturallyoccurring beryllium-7 and potassium-40. The only analyses performed on vegetationwere for gamma-emitting radionuclides. SSES Technical Specifications does not requirethe sampling and analysis ofvegetation. Soil continues to be monitored. Ifradionuclidesattributable to SSES operation appear in air samples or in the soil, vegetation samplingand analysis may be reconsidered. However, being grass and weeds, the vegetations rolein the pathway to man is questionable. In the event ofunusual releases ofactivity fromthe SSES, pasture grass would be a more important medium to monitor.

Fruits and vegetables were sampled at three locations in 1996 that were not sampled in1995. These locations were as follows: 8A4, the Butz residence 0.9 miles southsoutheast of the SSES; 9B4, the Cope residence 1.1 miles south of the SSES; and 14B3,the Moskaluk residence 1.3 miles west northwest of the SSES. Fruit and vegetablesampling in 1996 did not take place at two locations sampled in 1995. These locationswere 8A5, the Allen residence 0.8 miles south southeast of the SSES, and 15A3, theKrisanda residence 0.9 miles northwest of the SSES. Such year-to-year changes aretypical.

Sampling at two of six milk sampling locations from which collections were made at theend of 1995 was discontinued at the beginning of 1996. These locations were 10D3 and10D4. Location 10D3 was the Drasher farm 3.5 miles south southwest of the SSES.Location 10D4 was the Kishbaugh farm 3.8 miles south southwest of the station. Two

1996 Radiological Enrironmcntal Monitoring Rcport A-4

A endix A

milk sampling locations south southwest ofthe SSES, closer to the SSES than locations10D3 and 10D4, continue to be sampled. Sampling at the remaining two farms southsouthwest ofthe station should provide an adequate means to detect any signiQcantreleases ofactivity in that direction from the plant ifit would occur. Milksampling andanalysis in the vicinityofthe SSES continues to meet the requirements ofthe SSESTechnical Specifications.

Sampling eggs annually at location 10D1, the R. 8c C. Ryman farm 3.0 miles southsouthwest of the SSES, was discontinued at the beginning of 1996. No radioactivityattributable to the SSES operation was ever reported in the eggs being sampled. SSESTechnical Specifications does not require the sampling and analysis ofeggs..

Game sampling locations varied as usual between 1995 and 1996. Sampling includes therecovery ofroad-killed animals and hunting. Factors that determine the opportunities forsuch sampling are complex, and to some extent beyond the sampler's control. As a

result, sampling locations vary from year to year as well as the numbers and types ofgame sampled.

Ground Water Monitorin

Gross alpha and beta analyses ofground water were discontinued at the beginning of1996. These analyses were performed from the preoperational year 1980 through 1995.Gross alpha activities were usually measured above the MDCs in a small number ofsamples annually. The activities seen during the SSES operational period have b'een

similar to those observed during the preoperational period. The observed activities havenot been attributable to the SSES operation. Although gross beta activities weremeasured at levels above the analysis MDCs in a majority ofthe samples each year, thedetected activities were not attributed to the SSES operation. Gross beta activitiesmeasured during the operational period were similar to those seen during thepreoperational phase of the SSES REMP.

Analyses for tritium and the activities ofgamma-emitting radionuclides in ground watercontinue to be performed. Gross alpha and beta analyses ofground water can bereinstituted as part of the REMP ifthere is reason to believe from the other analysesbeing performed or from occurrences at the SSES that there is a potential for non-gamma-emitting radionuclides from the SSES entering the ground water. Ifthis shouldbe necessary, a significant data base is available from past monitoring for comparison andfacilitation ofthe evaluation ofthe results ofsuch sampling and analysis. SSESTechnical Specifications does not require that ground water in the vicinityof the SSESbe sampled and analyzed for gross alpha and beta activity.

A-5 1996 Radiological Environmental Monitoring Report

APPENDIX 8

1996 RKMP MONITORINGSCHEDULE(SAMPLINGAND ANALYSIS)


A endix 8

TABLEI(Page 1 of3)

Annual Analytical Schedule for theSusquehanna Steam Electric Station (PPAL)

Radiological Environmental Monitoring Program - 1996

No. of Sample AnalysisMedia 8c Code Locations Fre . a Anal ses Re uired Fre . b

AirborneParticulates

Gross Beta (c)Gamma Spectrometry

WQC

Airborne Iodine

Sediment

FlocculatcdSediments

SA

SA

I-131

Gamma Spectrometry

Gamma Spectrometry

SA

SA

Fish SAA

Gross BetaGamma Spectrometry(on edible portion)

SASA

Surface Water(d)

10 MC, M,orBWC

Gross AlphaGross Beta1-131

Gamma SpectroscopyTritium

MMBWMM

Well (ground)Water

Gamma SpectroscopyTritium

MM

Drinking Water(c)

MC, BWC Gross AlphaGross Beta1-131

Gamma Spcctromct tyTritium

MMBWMM

Note: See footnotes at end of table.

1996 Radiological Environmental Monitoring Rcport B-2

A endix B

TABLE 1

(Page 2 of3)

Annual Analytical Schedule for theSusquehanna Steam Electric Station (PPdkL)


No. of SampleMedia & Code Locations Fre .' Anal sesRe uired

AnalysisFre. b

Precipitation QC Gamma SpectrometryTritium

Q .

Q

Cow Milk M, SM(0 I-131Gamma Spectrometry

SM,MSM,M

Food Products(Various Fruitsand Vegetables)

Gamma Spectrometry

Game

Soil 10

Gamma Spectrometry

Gamma Spectrometry

Direct Radiation

PIC Monitors

86 TLD

(a) W = weekly, BW = bi-weekly, BWC = bi-weekly composite, M = monthly, SM =semi-monthly, Q = quarterly, QC = quarterly composite, SA =. semi-annually, 'A =annually, MC = monthly composite.

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


A endix 8

TABLE 1

(Page 3 of3)

Annual Analytical Schedule for theSusquehanna Steam Electric Station (PP&L)


(c) Ifthe gross beta activity were greater than 10 times the yearly mean of the controlsample, gamma analysis would be performed on the individual filter. Gross betaanalysis was performed 24 hours or more following filter change to allow'for

'adonand thoron'daughter decay.

(d) Stations 6S6, 6S7, and 2S7 were checked at least weekly to ensure that theautomatic composite samplers were operational. Time proportional sampling wasperformed at locations 6S6 and 6S7 the entire year. Flow proportional samplingwas conducted at location 2S7 from June 3 through August 2, 1996. Theremainder of the year time proportional sampling was conducted at location 2S7.Station 6S5 was grab sampled weekly. Individual composites of the weeklysamples were made both monthly (MC) and biweekly for analysis.

(e) Water from station 12H2 TREATED was retrieved weekly. Composite samplesof the weekly collections at this location were made both monthly (MC) andbiweekly (BWC) for analysis. Sampling at 12H2 TREATED was performed usingan automatic continuous sampler (ACS) that was operated in the time proportionalmode.

(f) Stations 12B3, 10D 1, IOD2, and 10GI were sampled semi-monthly from Aprilthrough October.

1996 Radiological Environmental Monitoring Rcport B-4

APPENDIX C

1996REMP MONITORINGLOCATIONDESCRIPTIONS

1996 Radiological Environmental Monitoring Rcport C-1

A endix C

TABLEC 1

(Page 1 of5)

Radiation Level Monitoring Locations for the SSESRadiolo cal Environmental Monitorin Pro ram - 1996

Less Than One Mile from the SSES 'See Fi ure 2

LocationCod b

1S2

Distancemiles0.2

Direction

N Perimeter Fence

Description

'S2

2S3

PIC2

3S2

3S3

3S4

4S3

4S6

SS4

SS7

0.9

0.2

0.9

0.5

0.9

0.3

0.2

0.7

0.8

0.3

NNE Ener Information Center

Perimeter Fence

Ener Information Center

SSES Backu Met TowerRiverlands (N. Comfort Station)/ANSP Riverlands Garden

Post, West ofSSES Access Processin Facili

Perimeter Fence

Riverlands Pack irdhouse Post

West ofEnvironmental Laborato

Perimeter Fence

6S4

6S9

7S6

7S7

7SS

SS2

9S2

10S1

10S2

10S3

11S3

11S7

0.2

0.2

0.2

0.4

0.4

0.2

0.2

0.4

0.2

0.6

0.3

0.4

ESE

ESE

SE

SE

SE

SSE

SSW

SSW

SSW

SWSW

Perimeter Fence

Perimeter Fence south

Perimeter Fence

End ofKline's Road

Kline Residence

Perimeter Fence

Securi Fence

Post - south ofswitchin station

Securit Fence

Confer's Lane - south ofTowers Club

Securit Fence

SSES Access Road Gate ¹5012S1 0.4 WSW SSES Emer en 0 erations Facili


A endix C

TABLEC I(Page 2 of5)


Less Than One Milefrom the SSES 'See Fi re2

'

LocationCode

12S3

12S4

12S5

12S6

12S7

13S2

13S4

13S5

Distancemiles0.40.4

0.40.4

0.40.4

0.4

Direction

WSWWSWWSWWSWWSW

Perimeter FencePerimeter Fence

Perimeter Fence

Perimeter Fence

Kisner Residence

Perimeter FencePerimeter FencePerimeter Fence

Description

13S6

14S5

14S6

15SS

16S 1

16S2

6A4

15A3

16A2

0.4

0.5

0.7

0.4

0.3

0.3

0.6

0.9

0.90.8

SSE

Former La down Area - west ofConfer's LaneBeach Grove Road/Confer's Lane oleBeach Grove Road concrete structure

Perimeter Fence

Perimeter Fence east

Perimeter Fence west

Riverside Restaurant

PP&L Wetlands Si . S. Route 11

Kxisanda Residence

Ru inski Residence

From One to Five Miles from the SSES 'See Fi ure 3

IB12B3

1.4

1.3

N Min'

Inn Road

Durabond Co oration1.4 NNE U.S. Route 11/Min e Inn Road Intersection

SB3

8B2

1.6

1.5

1.4

SE

SSE

PP&L Switch ard

Heller's Orchard StoreLawall Residence

8B3 1.5 SSE Wa wallo en Post Ofhce

C-3 1996 Radiological Environmental Monitoring Report

A endix C

TABL'KC 1

(Page 3 of5)'I

Radiation Level.Monitoring Locations for the SSESRadiolo cal Environmental Monitorin Pro ram - 1996

From One to Five Miles from the SSES' See Fi ure3

LocationCode b

9B1

10B2

10B3

10B4

12B4

13B1

14B3

15BI

16B2

1 lcl1DS

6Dl8D3

10DI

12D2

14D1

3El

6El

Distancemiles

1.3

2.01.7

1.4

1.7

1.3

1.3

1.7

1.7

2.0

4.0

3.5

4.03.6

3.0

3.7

3.6

4.7

4.7

4.5

4.7

Direction

SSWSSWSSW

WSW

SWN

ESE

SSE

SSWWSW

ESE

Description

Transmission Line - east ofRoute 11

Al att Residence

Castek Inc.U. S. Route 11/River Road Intersection

Shultz FarmWalker Run Creek ele. Pole A'36

Moskaluk Residence

Coun Estates Trailer Park .

Walton Power LineSalem Townshi Fire Com an

Shickshinn /Mocana ua Sewa e Treatment Plt.

St. Peters Church - Hobbie

Mo Residence

Coun Folk Store

R. & C. R an Farm

Da ostin Residence

Moore's Hill/Min le Inn Roads IntersectionWebb Residence - Lill LakeRuckles Hill/Pond HillRoads Intersection

Bloss Farm

St. James Church


A endix C

TABLEC1(Page 4 of5)

Radiation Level Monitoring Locations for the SSESRadiolo 'cal Environmental Monitorin Pro ram - 1996

From One to Five Miles from the SSES ' See Fi ure 3

LocationCode

11E1

Distancemiles4.2

4.7

Direction

SE

SW

Description

Harwood Transmission Line Pole P2

Thomas Residence

12E1

13E4

4.7

4.1

WSW Berwick Hos ital. Kessler Farm

G~ater than Five Miles from the SSES' See Figure 4

2F1 5.9 NNE St. Adalberts Cemete

8.5 SSE HufFResidence

12F2

PIC1

15FI

16F1

PIC43G4

5.2

5.2

7.8

10.7

17

WSW Berwick Substation

WSW Berwick Ci HallZatwatski Farm

NNW Hidla Residence

Nanticoke Munci al BuildinWilkes Barre Service Center

4Gl6Gl7G1

7G2

]413.5

14

12

ESE

SE

SE

Mountainto - Crestwood Industrial Park

Freeland Substation

Hazleton PP&L Com lex

Hazleton Cemete - 7th Street ole Ai31852-

8G1

12G1

12G4

12

15

10

SSE PP&L SFC - Humbolt Industrial ParkWSW PP&L Service Center, BloomsburWSW Naus Residence


A endix C

TABLEC 1

(Page 5 of5)


a) Alldistances Rom the SSES to monitoring locations are measured &om the standby

gas treatment vent at 44200/N34117 (Pa. Grid System). The location codes are

based on both distance and direction from the SSES. The letters in the location codes

indicate ifthe monitoring locations are on site (within the site boundary) or, iftheyare not on site, the approximate distances ofthe locations Rom the SSES as

described below:

S - on siteA- <I mileB - 1-2 milesC - 2-3 rmles

D -3-4 miles

E- 4-SmilesF- 5-10milesG - 10-20 milesH- >20miles

The numbers preceding the letters in the location codes provide the directions ofthemonitoring locations from the SSES by indicating the sectors in which they arelocated. A total of 16 sectors (numbered 1 through 16) equally divide an imaginarycircle on a map ofthe SSES and its vicinity, with the SSES at the center ofthe circle.The middle ofsector 1 is directed due north (N). Moving clockwise from sector 1,

the sector immediately adjacent to sector 1 is sector 2, the middle ofwhich is directeddue north, northeast (NNE). Continuing to move clockwise, the sector numbersincrease to 16, which is the north, northwest sector.

The numbers following the letters in the location codes are used to differentiatesampling locations found in the same sectors at approximately the same distancesfrom the SSES.

b) Radiation level monitoring is performed by thermoluminescent dosimetry (TLD) at alllocations except those identified as PIC I, PIC2, PIC3, and PIC4. Locationsidentified by the designation code PIC are not monitored by TLDs. PIC locations aremonitored by pressurized ion chamber instruments.

1996 Radiological Enrironmcntal Monitoring Rcport

A endix C

TABLEC 2(Page 1 of5)

Sampling Locations for. the SSESRadiolo cal Environmental Monitorin Pro ram - 1996

Less Than OneMile from the SSES' See Fi ure5

LocationCode

DistancemiIes

Direction Description

2S75S96SS

6S66S7

0.1

0.8

0.9

0.80.4

ESEESEESE

URFACE WATER';""""''''"-"-""':""" ': "'"'.- '" '"',.

Coolin Tower Blowdown LineEnvironmental Lab Boat RamOutfall AreaRiver Water Intake LineCoolin Tower Blowdown Line

LTAW NE - ESE Lake Took-A-While on site

LTAW

LTAW

3S2 0.5

0.8

NE - ESE Lake Took-A-While on site

SEDIMEN0'E

- ESE Lake Took-A-While on site

AHR/PRECIPITATIONSSES Backu Meteorolo 'cal TowerWest ofSSES Environmental Laborato

7S7 0.4 SE End ofKline's Road

10S3

12S1

13S6

3S2

0.6

0.4

0.4

0.5

SSW East ofConfer's Lane, South ofTowers Club

WSW EOF BuildinFormer La down Area, West ofConfers Lane'OILSSES Backu Meteorolo 'cal Tower

7S70.8

0.4 SEWest ofSSES Environmental LaboratoEnd ofKline's Road

10S3

12S1

13S6

0.60.4

0.4

SSW East ofConfer's Lane South ofTowers ClubWSW EOF Buildin

Former La down Area, West ofConfers Lane


A endix C

TABLEC2(Page 2 of5)

Sampling Locations for the SSESRadiolo cal Environmental Monitorin Pro ram - 1996

Less Than OneMile from the SSES' See Fi ure5

LocationCode

Distancemiles


8A4

3S

SS

0.9

on site

on site

FRUITS/VZGETABLES'" '""'--'

SSE Butz ResidenceGAME<'>

SSES on site

SSES on site

7S

10S

11S

on site

on site

on site

SE

SSW

SW

SSES on site

SSES on site

SSES on site

2S2

4S5

0.9

0.5

0.5

GROUND WATEREner Information Center

Trainin Center

ENE White House

12S1 0.5 SW EOF Buildin

From One to Five Miles From the SSES- See Fi ure 6

SURFACE WATERID3

2B

3.9

0.9 - 1.4

1.6

Mocana uaBrid e

HSa»ESE At or Below the SSES Dischar e DifIuser

SEDIMENT 'i

NNE Gould Island

1.2 SE Bell Bend

11C

2B

2.6

1.6

1.2

SW Hess Island

FLOCCULATEDSEDIMEXd'>NNE Gould Island

SE Bell Bend

1996 Radiological Enrironmental Monitoring Report

A endix C


Sampling Locations for the SSESRadiolo 'cal Environmental Monitorin Pro ram - 1996

From One to Five Miles from the SSES' See Fi ure 6

LocationCode

Distancemiles


9B1

12El1.3

4.7

AIIVPRECIPITATION/SOIL"'->'""''--:-":.""

S Transmission Line - East ofRoute 11

WSW Berwick Hos ital

10D1

10D2

12B3

12S7

2BS

10BS

14B3

11DI

3.0

3.1

2.0

1.2

1.3

3.3

SSW

SSWWSW

WSW

SSW

SW

R &C. R anFarmRussell R FarmYoun Farm

/VEGETABLESKisner Residence

Proto Residence

Co e Residence

Bodnar Residence

Moskaluk Residence

Zehner FarmGAME<'

h

2B 1.2 NNW Offsite

Greater than Five Miles from the SSES" - See Figure 7

SURFACE WATER12F1 5.3 WSW Berwick Brid e


A endix C


Sampling Locations for the SSESRadiolo 'cal Environmental Monitorin Pro ram - 1996

Greater than Five Miles from the SSES ' See Fi re 7

LocationCode

Distancemiles


12G2

12H1

12H2T

17

26

26

SURFACE WATER cont; "-",':.'SW

US Radium Site BloomsburWSW Merck Co

DRIIGGNGWATER '

WSW Danville Water Co. treatedHSIIt'l

2F

30

6.4

30 Near Falls, Pa

SEDIMEYI'etweenShickshinny and Retreat State Correctional

Institution12F 6.9

13.5

WSW Old Berwick Test TrackAIR/PRECIPITATION/SOILESE Freeland Substation

7G1 14 SE PP&L's Hazleton Chemist Lab8G1 12 SSE PP&L SFC - Humbolt Industrial Park

10G1

12F7

13G2

13G

16F

16H

12F3

14

8.3

16

10-20

5-10

>20

5.2

SSW Davis Farm

FRUITS/VEGETABLESWSW Lu ini Farm

W KileFarm

GAME'ff

sitNNW offsite

off

sitGROUND WATER

WSW Berwick Water Com an


A endix C

TABLEC2(Page 5 of5)

Sampling Locations for the SSESRadiolo cal Environmental Monitorin Pro ram - 1996

a) Alldistances from the SSES to monitoring locations are measured from the standbygas treatment vent at 44200/N34117 (Pa. Grid System. The location codes are based

on both distance and direction from the SSES. The letters in the location codesindicate ifthe monitoring locations are on site (within the site boundary) or, iftheyare not on site, the approximate distances ofthe locations &om the SSES as

described below:

S - on siteA- (1 mileB - 1-2 milesC - 2-3 rmles

D - 3-4 miles

E- 4-SmilesF - 5-10 milesG - 10-20 milesH- )20miles

The numbers preceding the letters in the location codes provide the directions ofthemonitoring locations from the SSES by indicating the sectors in which they arelocated. A total of 16 sectors (numbered 1 through 16) equally divide an imaginarycircle on a map ofthe SSES and its vicinity, with the SSES at the center ofthe circle.The middle ofsector 1 is directed due north (N). Moving clockwise from sector 1,

the sector immediately adjacent to sector I is sector 2, the middle ofwhich is directeddue north, northeast (NNE). Continuing to move clockwise, the sector numbersincrease to 16, which is the north, northwest sector.

The numbers following the letters in the location codes are used to differentiatesampling locations found in the same sectors at approximately the same distancesfrom the SSES.

b) No actual location is indicated since fish are sampled over an area which extendsthrough 3 sectors (5, 6, 7) near the outfall area.

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

C-11 1996 Radiological Environmental Monitoring Rcport

APPENDIX D

1996 LANDUSK CENSUS RESULTS

1996 Radiological Environtncntal Monitoring Rcport

A endix D

1996 LANDUSE CENSUS RESULTS

The SSES Technical Specifications require that a census be conducted annually during, the growing season to determine the location ofthe nearest milk animal; residence, and

garden greater than 50 m (=500 6 ) producing broad leaf vegetation in each ofthe 16

meteorological sectors within a distance of8 km (=5 miles) in each of the 16'eteorologicalsectors surrounding the SSES. To comply with this requirement, a land-

use survey was conducted for the SSES during 1996. The closest qualified gardens andresidences and all dairy animals within five miles ofSSES in each of the 16 sectors wereidentified.

Table 5 lists the results ofthe census. The results are used in conjunction with the mostrecent year's meteorological data to determine ifany changes in required REMPsampling locations for milk must be made. These results are also used to determine theoptimum sampling locations for fruits and vegetables and to make changes in suchsampling locations ifwarranted and practical. Such changes ensure that the mostsensitive monitoring locations are included in the REMP. Land use census results arealso used in the assessment ofpotential radiological doses to individuals and populationsliving in the vicinityof the SSES.

The following changes from 1995 to 1996 in the nearest gardens in sectors I, 8 and 15

and the owner ofthe nearest garden in sector 2 were identified by the 1996 Land UseCensus.

~ In sector 1, the nearest garden changed from that belonging to R. Smith, 1.3 milesnorth of the SSES, to that owned by J. Wojcik, 3.2 miles from the SSES.

~ In sector 2, the nearest garden, located 1.1 miles north northeast of the SSES,changed owners from L. Proto to V. Woodruff.

~ In sector 8, the nearest garden changed from that belonging to R. Allen, 0.8 milessouth southeast of the SSES, to that. owned by F. Butz, 0.9 miles from the SSES.

~ In sector 15, the nearest garden changed from that belonging to D. Krisanda,0.9 miles northwest ofthe SSES, to that owned by L. Gensil, 0.8 miles from theSSES.

A change from 1995 to 1996 also was identified by the 1996 Land Use Census as havingoccurred in the animals raised for consumption at the nearest garden in sector 4,2.4 miles east northeast of the SSES, which belongs to G. Dennis. In addition to thechickens and geese previously identified as being raised for consumption at this site,ducks were also identified as being raised at this site for consumption in 1996.

1996 Radiological Environmental Monitoring Rcport D-2

A endix D

TABLE5

Nearest residence, garden, and dairy animal in each ofthe 16 meteorological sectorswithin a 5-mile radius ofthe Susquehanna Steam Electric Station, 1996.

NEAREST NEARESTSECTOR DIRECTION RESIDENCE GARDEN

NEARESTDAIRYANGINAL

10

12

13

]4

15

16

N

ESE

SE

SSE

'SSW

SW

WSW

1.3 mi

1.0 mi

2.3 Inl

2.1 mi

1.4 mi

0.5 mi

0.4 mi

0.6 mi

1.0 mi

0.9 mi

1.5 mi

1.1 mi

1.2 mi

0.8 mi

0.8mi'.6

mi

3.2 11ll .

t

1.1 mi

2.3 Hu

24mi"'.4

mi

2.5 mi

0.6 mi

0.9 mi

1.1 mi

1.2 mi

1.9 mi

1.1 mi

1.2 mi

1.3 mi

0.8 mi

4.0 mi

>5.0 mi

>5.0 mi

>5.0 mi

>5.0 mi

4.5Ims'2.7

mis

2.6 mis

>5.0 mi

3.9 mi~

3 0 mia,b,c,d,eg

>5.0 mi

2.0 mi<

5.0mi'5.0

mi

>5.0 mi

4.2 mi

Chickens raised for consumption at this location.

Ducks raised for consumption at this location.IEggs consumed from chickens raised at this location.

Geese raised for consumption at this location.

'Pigs raised for consumption at this location.

Turkeys raised for consumption at this location.«

'Fruitslvegetables grown for consumption at this location.

""Rabbits raised for consumption at this location«

'Beef cattle raised for consumption at this location.

«No locations were identified as raising turkeys and rabbits during 1996.

D-3 1996 Radiological Environmental Monitoring Report

APPENDIX E

SUMMARYDESCRIPTION OF SSKS REMPANALYTICALMETHODS


A endix E

TLD MEASUREMENTS

The PPM. dosimetry system used for monitoring ambient radiation levels in theenvironment consists ofPanasonic 710A readers and Panasonic UD-814 TLDs. The.UD-814 TLD badges each contain four elements. Elements 2, 3, and 4 in each badge aremade ofcalcium sulfate with 800 mg/cm offiltering and element 1 is composed oflithium tetraborate with filtering of25 mg/cm . Only the calcium sulfate elements arenormally used for environmental measurements because oftheir higher light output perunit ofradiation exposure relative to the lithium tetraborate and, consequently, greater .

sensitivity for the detection and measurement ofradiation.

Note: Element 1 would be ofvalue in the event ofan unusually large release ofnoble gases, especially xenon, that would produce relatively low-energyX-ray or gamma emissions. This is because the lithium tetraborate doesnot over-respond to such low-energy emissions as does the calciumsulfate.

The TLD element manufacturers'ttempt to make each element as similar as possible toeach of the other elements in each batch that is produced. Nevertheless, each elementends up somewhat different in its response to radiation. In order to minimize the effectof these inherent differences when comparing actual monitoring results for differentelements, Element Correction Factors (ECFs) are determined for each element. TheECFs are used to effectively normalize the readings of the field elements placed atparticular monitoring locations for given monitoring periods to the average of thereadings that would be expected ifso-called reference elements were to be placedsimultaneously at those individual locations. Reference elements are elements that havebeen demonstrated to display superior measurement performance.

The selection process for reference elements involves repeatedly irradiating a large set ofelements, processing them, calculating the mean response for each set ofelements, andevaluating the deviation ofeach individual element response from the mean response;AAer this process has been repeated at least several times, the elements with the leastvariability in their responses and with mean responses nearest to the mean response ofthe entire population ofelements are chosen as reference elements.

To determine ECFs for individual field elements, the elements are first exposed to knownamounts of radiation (100 mR) and processed, a minimum ofthree times each. Eachelement reading is then divided by the mean of the readings obtained from referenceelements (typically 30 to 35) that were exposed to the same amounts of radiation as theelements for which the ECFs are being determined and that were processed at the sametime as these elements. The mean quotient (ratio) is then calculated for each element bysumming the quotients obtained for each processing and then dividing by the totalnumber of the processings performed.


A endix E

The following equation shows how ECFs are calculated:

E,

ECF = i-i E

where

E, an uncorrected exposure reading for the element.

n = the total number of individual element exposures averaged.-

E„< = the mean ofthe ECF-corrected exposure readings ofthe reference

elements.

Irradiated control TLDs are processed (read) with the batches ofTLDs from the field toprovide both processing calibration information and quality control. Field control TLDs,which accompany the field TLDs when they are being taken to their monitoring locationsand subsequently retrieved from these locations, and cave control TLDs, which arestored with the field TLDs for the periods between annealing and field distribution and.between retrieval from the field and processing, are also read with the field TLDs toprovide checks on the exposures that the field TLDs might receive on their way.to andfrom their monitoring locations and while in storage, respectively.

The raw data from the field TLD processings is Run Calibration Factor (RCF) correctedusing the irradiated control TLD data. The irradiated control TLDs are exposed to 100mR from a cesium-l37 source at the University ofMichigan. The irradiated TLDs areaccompanied enroute to and from the University ofMichigan by transit control TLDs.An estimate of the exposures received by the irradiated TLDs in-transit is obtained byprocessing the transit controls and determining the transit control mean by the followingequation:

where

a

ECF( „E„=n

E„= the mean of the elementally corrected'exposure readings ofallthe transit control elements.

the uncorrected exposure reading ofeach individual transitcontrol element.

1996 Radiological Environmental Monitoring Report4

A endix E

ECF, = 'he elemental correction factor ofeach individual transit controlelement.

n = the total number of individual element exposures averaged.

The mean of the transit control exposures is then subtracted from each of the elementallycorrected exposures ofthe irradiated elements to obtain the net exposures for each

element resulting from the irradiation. The mean ofthese net exposures is then dividedby the known exposure (100 mR) from the irradiation to determine the RCF. Thefollowing equation describes the calculations performed:

E,i EECF,

where

RCF = the run correction factor for an individual field monitoring element.

E, = the exposure reading ofeach individual irradiated control element.

ECF, = the elemental correction factor ofeach individual irradiated controlelement.

n= the total number of individual element exposures averaged.

KE„= the known exposure for each of the irradiated control elements.

Exposure readings for individual field monitoring elements are corrected using theappropriate mean transit exposure and the elemental and run correction factors asfollows:

UE„—ETc

ECF„x RCF„

where

CE. = the corrected exposure reading for field monitoring element x.

UE„= the uncorrected exposure reading for field monitoring element x.

1996 Radiological Environtncntal Monitoring Rcport

A endix E

ECF„= the elemental correction factor for field monitoring element x.

E~ = mean transit exposure

RCF, = the run correction factor for field monitoring element x.

NOTE: The mean transit exposure is determined from the elements of the TLDs thataccompany the field TLDs during transportation to and from the fieldlocations.

The exposure representing each environmental monitoring location and monitoringperiod is normally the mean of the corrected exposure readings for a total ofsix calciumsulfate elements, three from each oftwo different TLDs at each location. The followingequation shows the calculation of this exposure:

where

FACE,.

E,=™~ al

ll

E, = the mean ofthe corrected exposure readings for a given monitoringlocation and period.

CF., = the corrected exposure reading ofan individual element for a givenmonitoring location and period.

n= the total number of individual element exposures averaged.

The mean of the corrected exposure readings for a given location and period may becalculated using less than the six calcium sulfate elements ifthe reading from one of theelements is more than two standard deviations from the mean. In this situation, the meanwould be recalculated with only five element readings, excluding the element readingthat was more than two standard deviations from the originally calculated mean. Themean may be automatically calculated by the dosimetry software with as few as fourelement readings before the data is flagged. The following calculation is used todetermine the standard deviation of the corrected elemental exposure readings:

S cv

g(CE, —Z,)~ ~ I

where

E-5 1996 Radiological Environmental Monitoring Rcport

A endix E

the standard deviation ofthe corrected exposure readings from a

given monitoring location and period for (n-1) degrees offreedom.

the mean of the corrected exposure readings for a given monitoringlocation and period.

CE, = the corrected exposure reading ofan individual element for a given ~

monitoring location and period.

the total number of individual element exposures averaged.

The standard monitoring period for the reporting ofTLD exposures is the calendarquarter. The calendar quarter is defined as a period of91.25 days. The actualmonitoring periods for TLDs in the field are often for times other than 91.25 days. Themeans of the corrected exposures for these nonstandard periods must be normalized tothe standard calendar quarter. The following equations shows how the normalization is

performed:

E, x 91.25

MP

where

NF. = mean corrected exposure normalized to a standard calendar quarter of91.25 days.

E, = the mean of the corrected exposure readings for a given monitoringlocation and period.

Mp = the actual TLD monitoring period (time in the field) in days.

TLD DATA INTERPRETATION

Pre-operational and operational data are compared for the purpose ofdeterminingwhether or not TLD data may indicate a dose contribution from SSES operation.Between 1979 and 1994, both TLD types and TLD processing systems changed morethan once. In order to avoid possible confusion in data interpretation as a result of thesechanges, ratios ofTLD doses for specific indicator locations to the average of the TLDdoses for control locations from operational periods compared to their counterparts fromthe preoperational period. Comparison of these ratios is performed in lieu ofcomparingthe actual operational and preoperational doses. The following equation shows howthese ratios are calculated:

r, =d, —:d.


A endix E

where

r; - is the indicator-to-control-average dose ratio for a

particular location and calendar quarter,

d; - is the quarterly dose for a particular indicator location, and

d, - .is the average quarterly dose for certain control locations.

Note:

The r; are the quotients of the indicator doses to the average doses of thefollowing control locations: 3G4, 4G1, 7G1, 12G1, and 12G4. Only these

control locations are used because they were the only ones existing during thepreoperational period.

Operational r; for indicator locations that do not have preoperational histories are

compared with the range ofpreoperational control-to-control-average dose ratios (r,)experienced at control locations. It can be safely assumed that the preoperational rangeof these r, at control locations are the result ofvariations in the levels ofbackgroundradiation at those locations. Any operational indicator r; for an indicator locationwithout a preoperational history that is above the uppermost range expected at controllocations based on preoperational data is assumed to suggest a possible contributionfrom the SSES operation. 'he following equation shows how r, is calculated:

r,=d,—:d,

where

r, - is the control-to-control-average dose ratio for a particularlocation and calendar quarter,

d, - is the quarterly dose for a particular control location, and

d, - is the average quarterly dose for certain control locations.

Flagging Environmental TLD Measurements for Possible Non-Natural DoseContributions

Confidence ranges, within which 95% ofenvironmental TLD doses resulting fromnatural, background radiation are expected to be, have been derived for each location


A endix E

with a preoperational history by multiplying the standard deviation (S) of the r; for thelocation by the appropriate t score (t) based on the applicable degrees offreedom foreach location. (Degrees of freedom (df) are equal to the number of ratios that wereaveraged less one.) The product of the t score and the standard deviation (tS) was thensubtracted from the mean (x) to determine the lower end of the 95% confidence range

(R) and added to the mean to obtain the upper end ofthe range (R) as indicated by thefollowing equation:

R= r-t+S to r+t+S

The following t scores were used in the range calculations:

dft SCORES

to.o5

12.7064.3033.1822.7762.5712.4472.365

For indicator locations with no preoperational history, TLD results are flagged forpotential non-natural dose contributions to TLD measurements based on comparisons tothe maximum expected variation in control-to-control-average dose ratios (r,) for controllocations. The expected ranges of r, for each control location for each calendar quarterduring the 1980-81 preoperational period have been calculated. The highest expected r,for all the preoperational control locations is 1.22.Ratios for indicator locations greater. than 1.22 are flagged for possible SSES directradiation dose contributions.

Calculation of SSES Attributable Direct Radiation Dose based on Onsite IndicatorTLD Measurements

For TLD locations where direct radiation dose contributions from the SSES areindicated, these calendar quarter doses are estimated based on the amounts referred to as

the excess ratios. Excess ratio for each location's r; for a particular calendar quarter isthe amount by which that r; exceeds the high end of its range ofpreoperational r; . Theexcess ratio at a specific location is multiplied times both the average dose for controllocations measured during that calendar quarter and an occupancy factor based on a


A endix E

reasonable estimate of the portion of the calendar quarter that a MEMBER OF THEPUBLIC might spend near an onsite TLD location. The following is a table ofoccupancy factors that are used:

Environmental TLD Monitorin LocationsOnsiteOffsite other than Private ResidencesPrivate Residences

OccupancyFactors4.56E-43.65E-3

The following equation is used for obtaining direct radiation doses attributable to theSSES at indicator TLD locations when preoperational data exists for those locations:

where

D»as - isthedoseattributableto SSES fuel cycleoperations,

is the indicator-to-control average ratio for a particularlocation and calendar quarter,

is the indicator-to-control average ratio corresponding to theupper end of the 95% confidence range for a particularlocation for the preoperational period, and

Dc* - is the average quarterly dose for control locations.

OF - istheoccupancy factor.

The equation below is used for obtaining direct radiation doses attributable to the SSESat indicator locations when preoperational datadoes not exist for those locations:

Q =(r, —1.22)xD „xOF

where

D»F~ - is the dose attributable to SSES fuel cycle operations,


A endix E

r; - is the indicator-to-control average ratio for a particularlocation and calendar quarter,

1.22 - is the highest expected r, for control locations due tovariations in natural radiation levels based on preoperationaldata. Refer to location 12G4 in Attachment 1.

t

DcA - is the average quarterly dose for control locations.

OF - is the occupancy factor.

Each year, the SSES attributable doses calculated for each calendar quarter are summedfor all calendar quarters at each location to obtain annual doses by location.

1996 Radiological Environmental Monitoring Rcport E-10

A endix E

DETERMINATIONOF GROSS ALPHAAND/ORGROSS BETA ACTIVITY

TELEDYNE BROWN ENGINEERINGENVIRONMENTALSERVICES

One liter aliquots ofwater samples are treated with about one milliliterofconcentratednitric acid and evaporated to near dryness in beakers. The remaining volumes(approximately five milliliters or less) are transferred to stainles's steel planchets and

evaporated to dryness.

Two hundred or more grams ofeach fish sample are dried and then ashed in a mufme

furnace. One gram of each ashed sample is then transferred to a stainless steel planchet.

Approximately 50 grams ofeach soil or sediment sample is dried by heat lamp over a

period ofa couple ofdays. One gram ofeach dried sample is then transferred to a

stainless steel planchet.

Allplanchets are counted in low background gas-flow proportional counters.Calculations ofboth gross alpha and beta activities include the use ofempirical self-absorption correction curves to account for changes in effective counting efficiencyoccurring as a result ofchanges in the masses ofresidue being counted.

Weekly air particulate filters are placed into planchets as received and counted in lowbackground gas-flow proportional counters. No corrections are made for beta self-absorption when calculating the gross beta activities of the air particulate filters becauseof the impracticality ofweighing the deposit and because the penetration depth of thedeposit into the filter is unknown.

Quarterly composites of the weekly air particulate filters are counted for gross alphaactivities. Preparation for counting involves the dissolution of the filters and the eventualtransfer of the residue from filter deposits onto stainless steel planchets. As with thecalculation ofother gross alpha activities, corrections are made for sample self-absorption ofalpha particles during counting.

E-11 1996 Radiological Environmental Monitoring Report

A endix E

CALCULATIONOF THE SAMPLE ACIIVI'IY

C—+gt

unit volume or mass 2.22 (V)(E)net activity .

2.22 (V) (E)'andomuncertainty

where: C = total counts for sample

t = count time for sample/background (minutes)

R = backgroundcountrateofcounter(cpm)

2.22 = ~dmpCi

V(M)= volume or mass ofsample analyzed

E = eAiciency of the counter (cpm/dpm)

alculation of the Minimum Detectable Concentration MDC Value

2.22 (V) (E)

1996 Radiological Eniironmcntal Monitoring Rcport E-12

A endix E

RADIOCHEMICALDETERMINATIONOF I-131IN MILKANDWATER SAMPLES


A four-liter aliquot ofsample is first equilibrated with stable iodide carrier. Following a ~

period of time sufficient for equilibration, anion exchange resin is added to the aliquot tocapture the iodide ions present. The iodide ion is subsequently removed from the resinusing sodium hypochlorite. Hydroylamine hydrochloride is then used to produce freeiodine. The resulting free iodine is then extracted from the aqueous phase by dissolutionin toluene. This is followed by a reduction back to the iodide form using sodium bisulfiteand back-extraction to the aqueous phase. Once in the aqueous phase again, the iodideis precipitated as palladium iodide following the addition ofpalladium chloride.

Another aliquot of the sample is used to determine the stable iodide content of the milkby the use ofa specific-ion electrode. This information is then used to correct thechemical yield determined from the mass of the dried precipitate obtained.

The dried precipitate is beta counted on a low-level counter.

CALCULATIONOF THE SAMPLE ACTIVITY

—-ab

C 2.22(v)(y)(DF)(E) 2.22(V)(y)(DF)(E)

net activity random uncertainty

where: C = total counts from samplet = counting time forsample(min)

R = background count rate ofcounter(cpm)

2.22 = ~dmpCi

V = volume ofsampleanalyzed(liters)

y = chemical yield of the mount or sample counted

DF = decay factor from the collection to the mid-count time


A endix E

E = efficiency of the counter for the I-131 betas.

Note: Efficiency is determined by counting an I-131 standard.

Calculation of the MDC

MDC =2. 22(V)(y)(DF)(E)


A enrlix E

DETERMINATIONOF TRITIUMIN WATERBY LIQUIDSCINTILLATIONCOUNTING

TELEDYNEBROWN ENGINEERINGENVIRONMENTALSERVICES

Ten millilitersofwater is mixed with liquid scintillation material and counted for typically200 minutes to determine its activity.

CALCULATIONOF THE SAMPLE ACTIVI'IYFOR TRITIUM

—-Pb 2

2.22(V)(E) 2.22(V)(E)

net activity

where: C = 'otal counts from sample

random uncertainty

t = count time for sample (minutes)

R, = backgroundcountrateofcounter(cpm)

2.22 = ~mpCi

V = initial volume before enrichment (liters)

E, = efficiency of the counter for tritium (cpm/dpm)

Calculation of the MDC

(2. 22)(V)(L)


A endix E

DETERMINATIONOF GAMMAEMITTINGRADIOISOTOPES


Gamma emitting radionuclides are determined with the use ofa lithium-driftedgermanium (Ge(Li)) and high purity germanium detectors with high resolutionspectrometry in specific media, such as, air particulate filters, charcoal filters, milk,water, vegetation, soiVsediments, biological media, etc. Each sample is prepared and

counted in standard geometries such as one liter or four liter wrap-around Marinellicontainers, 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 resultant spectra arestored on magnetic tape.

The analysis ofeach sample consists ofcalculating the specific activities ofall detected~radionuclides as well as the minimum detectable concentration for a standard list ofnuclides. The germanium detection systems are calibrated for each standard geometryusing certified radionuclide standards traceable to the National Institute ofStandards andTechnology.


[C- 8] 2~C+ B

2.22(V)(l.:)(GA)DF)(I) 2.22(V)(E)(GA)(DF)(I)

net activity random uncertainty

where: C = area, in counts, of a spectral region containing a gamma emissionof the nuclide of interest

Note (1): Ifthe detector exhibits a peak in this region whencounting a blank, the counts from that peak aresubtracted from C before using the above equation.

Note (2): Ifno peaks are exhibited, the counts in the channelswhere the predominant peaks for gammas fromselected radionuclides would be expected aresummed for C and used in the calculation of "net"

activity.


A endix E

B = background counts in the region of interest, calculated by fittinga straight line across the region connecting the two adjacentregions.

Note: Ifno peak exists in a region from which a "net"

activity is being calculated, background is

represented by the average of the counts in onechannel from each side of that region.

t = counting interval ofsample (minutes)

2.22

V

dpm/pCi

volume or mass ofsample analyzed

eAiciency ofcounter at the energy region of interest

GA gamma abundance of the nuclide at the gamma emission energyunder consideration

DF = decay factor from sample collection time to midpoint of thecounting interval

Calculation OfThe MDC

MDC (pCi / vol or mass) = 4.t 6JC2.22(V)(E)(GA)(DF)(r)

The width of the region around the energy where an emission is expected is calculateddiA'erently for MDCs than it is for the width of a peak that is actually identified.Consequently, the value ofC used in the two equations may diAer.

'The analyst's judgment is exercised in the decision to report an activity. The agreementbetween various spectral lines of the same nuclide, and possible interference from othernuclides, are considered in this decision.


A endix E

DETERMINATIONOF RADIOSTRONTIVMIN MILK*AND WATER


Strontium-89/90 analyses may be performed on water samples for PP8cL. The first stepin the preparation ofmilk and water for analysis is the addition ofstrontium camer. Theaddition ofstable strontium facilitates the precipitation ofany radioactive strontium thatmay be present and provides sufficient quantities ofstrontium to be able to reliablydetermine the amount ofradioactive strontium recovered &om the samples for counting.

'ubsequentsteps in the preparation ofboth the water and the milk samples for countinginvolves a number ofphysical and chemical separations to isolate any radioactivestrontium that might be in the samples originally, as well as the stable strontium that isadded to the sample aliquots to be analyzed. The isolation removes other metallicelements that may be present in both the water and the milk and organic materials thatare present in the milk in significant quantities.

Strontium is precipitated twice, first as strontium nitrate and second as strontium sulfate,in the preparation of the water samples. This permits the removal ofradium and othernaturally occurring radioactive materials as the result ofthe first precipitation and iron byway of the second precipitation.

Milkis first evaporated and ashed to remove organic materials. The residue is thenredissolved with an aqueous solution ofhydrochloric acid and filtered to removeinsoluble materials, aAer which strontium is precipitated as a phosphate to remove otherunwanted materials. The phosphate precipitate then is redissolved with an aqueoussolution ofnitric acid and the resulting solution is passed through a chromatographiccolumn. The strontium is retained on the column, allowing other unwanted material topass through. The strontium is later removed from the column by passing deionizedwater through it.

Following all of the purification steps for both water and milk, stable yttrium carrier isadded to the purified portions remaining to facilitate the precipitation ofany radioactiveyttrium-90 that appears in the processed sample from the radioactive decay ofstrontium-90. The yttrium camer also aids in the yield determination for yttrium-90. Theseportions are then allowed to stand for at least five days to permit yttrium-90 ingrowth.AAer the yttrium-90 ingrowth period, yttrium is precipitated as an oxalate and strontiumis precipitated as a carbonate. Each is then collected on separate filter discs forgravimetric yielding and beta counting.

«No milk was analyzed for strontiums 89 and 90 in 1996.

1996 Radiological Environmental Monitoring Report E-18

A emlix E

The filter discs are mounted on planchets prior to counting. Strontium-89 activity is

determined by counting the strontium planchets while they are covered with 80 mg/cmaluminum absorbers to eliminate interference from the strontium-90 betas. Strontium-90activity is inferred by counting the yttrium planchets.


II

2 —+-unit volume mass 2.22(V)(yi)(y2)(DF)(IF)(E) 2.22(Vxyi)(y2)(DFXIF)(E)

C = total counts from sample

counting time for sample (background)

R = background count rate

f = ash fraction (gm ash/gm milk)

V = volume ofsample analyzed

y, = chemical yield ofyttrium

y, = chemical yield ofstrontium

DF = decay factor ofyttrium from the milking time to the mid-counttime

IF = Ingrowth factor for Y-90 from scavenge time to milking time

E = efficiency of the counter for Y-90

Calculation of the Minimum Detectable Concentration Value

Rb4.66

2.22(V)(vl )(y2)(DF)(IF)(E)


A endix E

CALCULATIONOF THE SAMPLE SR-89 ACTIVI'rY

C——Bc —BA 2f —+ Bc+ BA / tC

pCiunit volume (mass) 2.22(V)(Y.)(DF~ -89>(E~ -89) 2.22(V)(Y.)(DF~ -89)(E -89)

where

Bc

total counts from sample

counting time for sample

background rate ofcounter using absorber configuration

BA background addition from Sr-90 and Y-90 ingrowth

(cpm)

V

ash fraction (gm ash/gm milk)

volume ofsample analyzed

Ys chemical yield ofstrontium

DFs,.89 = decay factor from the mid-collection date to the countingdate for Sr-89

efficiency of the counter for SR-89 with the 80 mg/cm

aluminum absorber

'Note that BA is a calculated value.

Calculation of the Minimum Detectable Concentration Value

4g6f [8 +B]MDC =

2.22(V)(Y,)(DF~ «)

1996 Radiological Enrirontncntal Monitoring Rcport E-20

APPENDIX F

1996 EXCEPTIONS TO THK SSKS TECHNICALSPECIFICATIONS SAMPLE SCHEDULE,

METHODS AND ANALYSISSENSITIVITIES


A endix F

Exceptions to the SSES Technical Specifications occurred in the monitoring ofthefollowing media: surface water, drinking water, and air. These exceptions involved

sample collections that did not take place for the required periods, sampling that was

performed in a manner not-stated in the Technical Specifications, and required analysis

sensitivities that were not met. Generally, they were caused by equipment malfunctionsand events taking place in the vicinityofmonitoring stations that interfered in some waywith the normal course ofsampling. These exceptions are discussed in this appendix and

specifically documented in the comments column of the tables ofAppendix I.

Surface Water

Monitoring at control location 6S6, the SSES River Water Intake Structure, and eitherindicator locations 6S7 or 2S7, the SSES Cooling Tower Blowdown Discharge (CTBD)to the Susquehanna River, are the only environmental surveillances ofsurface waterrequired by SSES Technical Specifications. The other five SSES REMP routine surfacewater monitoring locations on the Susquehanna River, both upstream and downstreamfrom the SSES discharge to the river, and the monitoring location at LTAWare notrequired. They have been monitored to provide added assurance that the environment is

not being compromised by radiological releases resulting from the SSES operation.

Sampling at locations 6S6 and 6S7 or 2S7 is required to be performed by the collectionofaliquots at time intervals that are small compared to the compositing period.Composite samples from these locations are required to be analyzed monthly and areexpected to be representative of the streams from which they are collected. Problems in1996 with automatic composite samplers (ACSs) at these sampling locations led toperiods when no water'was'being collected and to periods when water was beingcollected at an uncontrolled and indeterminate rate, resulting in samples that were not as

representative of the water flowing in the sampled streams as desired. In some cases, theACSs were deliberately removed from service to permit performing maintenance on thesamplers. In other cases, the ACSs were unable to sample because maintenance wasbeing performed on related equipment or systems. Grab samples were obtained at therequired locations or alternate locations at weekly intervals when an.ACS was known tobe inoperative or operating in an uncontrollable or indeterminate fashion and automaticsampling could not be performed using other equipment.

The sampling performance at location 6S7 during 1996 was not nearly as good as it wasin 1995 when 97% of the monitoring year was represented by continuously collectedsamples. Only 59% of the 1996 monitoring year was represented by continuouslycollected samples for location 6S7. This was the worst performance in recent years andsince a quantification of this performance began in 1993. In spite of this poorperformance, only one grab sample was collected at this location on January 29, 1996,when insufIicient water had been collected for analysis. This is because continuously'collected samples of the CTBD were also available from location 2S7 for most of theyear. However, one additional grab sample was collected on October 7, 1996 when nosample could be collected from either location 6S7 or location 2S7. This sample was

1996 Radiological Environmental Monitoring Rcport F-2

A endix F

obtained from location 6SS downstream ofthe SSES discharge for liquid effluents to theSusquehanna River. Location 6SS is an alternate sampling location for 6S7 that is used

when no water can be collected from the CTBD. Sampling could not be performed atlocation 6S7 from October 4 through October 10, 1996 because ofa loss ofwaterresulting from River Water Makeup Line Replacement Project work.

In addition to the period during the River Water Makeup Line Replacement Project, thefollowing times and periods occurred in 1996 when no water could be obtained from theACS at location 6S7: January 29, July 19 through August 5, October 21 throughOctober 24, and November 7 through November 11. These occurrences were the resultofeither low pressure or zero pressure from the pump supplying the ACS at location6S7. The ACS also was unable to receive water for a briefperiod on June 24, 1996when the pump'that supplies water to the ACS was deliberately turned ofF to allowpreventative'maintenan'ce to be performed.

No sample was collected from location 6S7 at other times when the flow rate to the ACScould not be controlled as the result ofvarying pump pressure, air, and, at least in oneinstance, silt in the line leading to the ACS. Samples were not collected for analysisduring these times because the samples were not considered to be appropriatelyrepresentative of the entire sampling interval. The following are periods during 1996when the amount ofwater collected per unit of time by the ACS at location 6S7 couldnot be controlled: February 8, May 13 through June 3, August 5 through September 3,and November 11 through December 2.

The ACS at location 6S7 was inoperative from February 12 through March 28, 1996

because ofa malfunctioning electrical timer. This extended period occurred because ofthe length of time required to obtain a replacement timer.

Fortunately, in spite of the poor sampling record at location 6S7 in 1996, samples ofCTBD line water were able to be collected continuously for most of the year at location2S7. On February 5, 1996 time proportional sampling at location 2S7 was begun. Timeproportional sampling at location 2S7 continued until June 3, 1996 when flowproportional sampling was initiated. Sampling at location 2S7 was flow proportionalfrom June 3 through August 2, 1996. Flow proportional sampling would have been

performed for a longer period of time in 1996 at location 2S7 ifa reliable flow signalcould have been obtained.

The sampling performance at location 2S7 in 1996 was significantly better than theperformance at location 6S7. For the portion of 1996 that operation of the ACS atlocation 2S7 was attempted, continuously collected samples were obtainable for 89% ofthe time. This is considered especially good for the first year of the ACS's operation.Only one grab sample (August 5, 1996) was collected at location 2S7 during 1996.

F-3 1996 Radiological Environmental Monitoring Report

A endix F

Although the sample analysis results obtained for collections at location 2S7 were usedto represent the CTBD for more than halfof 1996, there were some problems withsampling at this new location. These problems occurred because ofelectrical powerinterruptions, pump tubing failures, and pump jamming and pump motor failures. Theelectrical interruptions had a minor impact ifany on the sampling performance oftheACS at location 2S7 during 1996. The performance log for the sampler indicates thatthere were a total of 13 power failures affecting the ACS operation between May 6 andDecember 5, 1996. Eight ofthese power failures were for periods ofa minute or less,with the longest being only eight minutes. The total period oftime affected by these

. power failures was 34 minutes in 1996. Because the ACS is prograinmed to collectaliquots every 25 minutes, no aliquots may have been missed in most, ifnot all instances.A line conditioner has been installed on the power supply to the ACS in order to lessenthe chances that voltage spikes that might occur when power is restored could impactthe programmed operation ofthe ACS. Efforts willcontinue in 1997 to determine thecause(s) of the power interruptions. Power to the ACS at location 2S7 was interruptedintentionally for eight minutes on July 29, 1996 for the installation ofa light.

No significant interruptions in sampling time due to difficulties with pump tubingoccurred in 1996. An unexpectedly high rate ofwear in the pump tubing was observedduring 1996. Silastic tubing was used for almost the entire portion of 1996 that the ACSwas operated. This tubing is desirable because it is quite flexible and ensures goodcompressions willbe achieved by the peristaltic pump used to draw water. However,silastic tubing wears faster than the less flexible vinyl tubing that was tried as pumptubing for a briefperiod from June 6 through June 20, 1996. Use ofvinyl tubing wasdiscontinued because ofconcerns about pump jams that might occur because of therigidityof the tubing and its resistance to being compressed. Lubrication of the pumptubing was begun on June 14, 1996, with the hope that the life ofthe pump tubing mightbe extended. In order to minimize the opportunity for failure of the pump tubing duringa sampling period and the consequent loss ofsampling time, the tubing is inspectedweekly and replaced at regular intervals as a precaution.

Sampling with the ACS at location 2S7 was interrupted from September 3 throughOctober 7, 1996 because of the failure ofa pump motor. An insufficient volume ofsample was obtained for the period October 14 through October 21, 1996 as the resultof a pump jam. Maintenance was quickly performed and the pump was restarted onOctober 21. Sampling was also interrupted at location 2S7 from August 2 throughAugust 5, 1996 because the ACS was used for obtaining an NPDES sample and was notproperly returned to operation aAerwards.

Location 2S7 willbe the primary sampling location for the CTBD line in 1997. Location6S7 willnot normally be sampled but is expected to be available as a backup whensampling can't be performed at location 2S7.


A endix F

Approximately 82% of 1996 was represented by continuously collected samples fromlocation 6S6. Grab samples were collected in 1996 at control monitoring location 6S6

on the following six occasions: January 29, April22, May 6, and May 20, September 9

and September 16. In,addition, grab samples were collected at the alternate samplinglocation SS9 on the following four occasions when no water could, be obtained atlocation 6S6: February 26, March 4, April 15, and October 7. Grab samples werecomposited on two separate occasions prior to analysis. Grab samples obtained in 1996from location 5S9 on February 26 and March 4 were composited for analysis. Grabsamples collected in 1996 at location 6S6 on'September 9 and September 16 also were,composited before being analyzed.

No water was flowing to the ACS at location 6S6 on six different occasions in 1996. OnApril 15 and April 17 flow apparently was interrupted because ofdebris clogging thesample line leading to the ACS. This was the result ofhigh river water and additionalamounts ofmaterial that are found in the river during rainy periods. On October 4 and

again during the period October 7 through October 10 water could not reach the ACS atlocation 6S6 because of interruptions resulting from the River Water Makeup LineReplacement Project. Insufficient water for analysis was available in the ACS's samplecollection container on January 29 and May 20, necessitating the collection ofgrabsamples. The sample collection container for the ACS'at location 6S6 was overflowingon April 22, May 6, September 9, and September 16, also requiring that grab samples betaken. The ACS at location 6S6 was deliberately placed out ofservice for a period ofnearly 12 hours between May 23 and May 24 while maintenance was being performed.

~D'i W

Approximately 94% of l996 was represented by continuously collected samples fromlocation 12H2T. Nevertheless, problems also were experienced in 1996 with theautomatic continuous sampler (ACS) located at the drinking water sampling location12H2T, the Danville Municipal Water Authority. Grab samples at location 12H2T werecollected on the following three occasions in 1996: June 17, September 9, andSeptember 23. In all three situations, the sample collection container at the ACS wasfound to be overflowing because water was flowing into the collection containerbetween the collection ofaliquots. In the first two'nstances, water was entering thecontainer at other than the desired times because the sampling arm was unable to fullyreturn to its non-sampling position. Replacement ofa cotter pin was needed in bothcases to correct the problem. In the last case, water was entering the sample collectioncontainer at times other than those desired because the sample tubing had ruptured,allowing water to spray over to the collection side of the ACS's diverter chamber.

Iodine-131 analysis results for a drinking water sample for the period from May 13

through May 28, 1996 were not obtainable because ofan error made by a technicianperforming the analysis. Too much acid was added to the sample when attempting toadjust pH. This resulted in a chemical yield ofzero for the analysis. Thus, no count wasable to be performed.

F-5 1996 Radiological Environincntal Monitoring Rcport

A endix F

Air

Out of520 station-weeks (10 different stations collecting 52 weekly samples) ofair.sampling in 1996, nothing unplanned occurred during 513 (almost 99%) ofthose station-weeks. Ofthe problems associated with the collection ofair samples in 1996, all but onewere attributable to a loss ofelectrical power supplying the air sampling stations. The.

following instances ofelectrical power loss occurred in 1996: on January 4 at location10S3, on January 24 at location 7G1, on July 17 at location 10S3, and at locations 8G1on October 25, November 8, and December 17. In addition, power was interrupted atlocation SS4 on September 16 for about 45 minutes for preventative maintenance'. Theloss ofpower to the air sampling equipment at location 10S3 on January 4, 1996 resultedin such a small sample volume that the sample was not analyzed. Sample volumes wereso small as the result of the power losses occurring at 7G1 on January 24, SG1 onOctober 25, and 8G1 on November 8 that the required sensitivities for gross betaanalyses were not met for the associated samples. In addition, the required analysissensitivity for iodine-131 was not achieved for the sample collected at 7G1 on January24, 1996.

The only other unplanned event affecting air sampling in 1996 was the result ofaninadvertent action by a sampling person. A sampling head that contained an airparticulate filter and charcoal cartridge which had been used for collection at location6GI for the period from June 26 through'July 2, 1996 was accidentally installed for a

period ofa little more than two hours at another control location SG1. The effect of thismistake is thought to have been negligible since the volume ofair seen by the filter andcartridge at 8G1 was only 280 ft'. This represents only a small fraction of the 19,200 ftofair seen by the filter and cartridge at location 6G1.


APPENDIX G

1996 SSES REMP SUMMARYOF DATA


A endix (7

The averages for indicator and control locations reported in the Summary ofData Table,which summarizes the entire year's results for the SSES REMP, were calculated using allmeasured values, whether or not they were reported in Appendix I tables. Values belowthe MPCs, even zeroes and negatives, were part of the averaging process for these

analysis results.

Preferably, the averages reported in the Summary ofData table for analysis results ofsample media that are normally collected continuously are determined using only thoseresults from continuously collected samples. Occasionally, grab samples are taken forthese media when equipment malfunctions or some other anomaly precludes orotherwise perturbs routine continuous sampling. These grab samples are taken tominimize the time periods when no sampling is being performed, or, in some instances,when continuous sampling is considered to be nonrepresentative.

Because grab samples best represent snapshots of the sampled media for the relativelybrief periods during which they are typically collected, it is normally preferable not toaverage the analysis results of these samples with those for continuously collectedcomposite samples. However, when equipment malfunctions are protracted, relativelylarge periods of time could be entirely unrepresented by averages ifthe results from grabsample analyses are not considered together with those representing continuouslysampled periods.

Allowinganalysis results for grab samples to be weighted equally with those representingrelatively large periods of time would tend to bias the resulting averages unjustifiablytowards the conditions at the times that the grabs are obtained. Averages obtained inthis way might less accurately reflect the conditions for the combined period ofcontinuous sampling and grab sampling than ifonly the results from continuous samplingwere used, On the other hand, using weighting factors for the analysis results ofgrabsamples derived from the actual time it takes to collect those samples would lead to thegrab sample analysis results having a negligible eflect on the overall average and notjustifying the effort involved.

Grab samples collected in lieu ofnormal continuous sampling are typically obtained at. regular intervals corresponding to the intervals at which the continuously collectedsamples would usually be retrieved for eventual compositing. For example, grab samplesare collected once a week and composited monthly in place ofcontinuously collectedsamples that would normally be retrieved weekly and composited monthly. Since eachgrab sample is used to represent an entire week, albeit imperfect, it is reasonable toweight the analysis results the same. Thus, the results ofone weekly grab are givenapproximately one-fourth the weight of the results for a monthly composite samplecollected continuously for each of the four weeks in a month. Similarly, the analysisresults of a composite of four weekly grab samples would carry the same weight as theanalysis results for a composite of four weeks ofcontinuously collected sample.


TABLEGSUMMARYOF DATAFOR THE SSES

OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1996NAMEOF FACIUTY: SUSQUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORTING PERIOD: JANUARY 02, 1996 TO JANUARY 06. 1997

MEDIUMOR PAT)DVAY 'RXfALNUMBER OFSAMPLED OF ANALYSES DETECTION

(UNII'FMEASUREMEÃ0 PERFORMED(l) (UD) (2lMEAN(3)RANGE

NAME MEAN(3)DISTANCE AND DIRECTION RANGE

CONIROL LOCATION NONROIJHNEMEAN(3) REPORTEDRANGE MEASUREMENIS(4)

Ambient Radhtion TLD 34 1

(mR/std. qtr.)

Surface Water(pCI/))

Gross A)pha 110

Gloss Beta I 10

Tritium 110 2000

iodine-131 159

Strontium-89 6

Strontium-90 6

Gamma SpecK-40 110

Mn-54 110 15

Co-58 110 15

Fe-59 110 30

Co-60 110 15

30Zn-65 110

18.1(310)(13.1 - 23.9)

0.8(76)(-1.3 - 5.5)

4 5.6(76)(1.3 - 33)

310(76)(-170 - 18000)

0. 1(1 15)(-0.1 - 1.9)

-0. 0007(4)(-0.5 - 0.4)

0.07(4)(-0.7 - 4.9)

-60(76)(-250 - 41)

0.3(76)(-4.5 - 3.3)

-0.2(76)(-2.0 - 1.8)

0.8(76)(-4.0 - 5.4)

0.5(76)(-1.8 - 3.5)

0.6(76). (-13 - 6.6)

11S3On site

6S7/2S7Discharge

6S7/2S7Discharge

6S7/2S7Discharge

6S7/2S7Discharge

12F15.3 ml WSW

6S7/2S7Discharge

1D33.9 ml N

687/2S7Discharge

12H126 mt WSW

6S7/2S7Discharge

12F15.3 mt WSW

6S7/2S7Discharge

22.9(4)(22.2 - 23.9)

1. 1(12)(-1.3 - 3.8)

1 1(17)(8.7 - 33)

1760(17)(150 - 18000)

0.3(30)(-0.1 - 1.9)

0.3(1)(0.3 - 0.3)

0.6(2)(0.09 - 4.9)

-32(1 1)(-140 - 18)

1.5(17)(-0.4 - 3.3)

-0.07(12)(-1.6 - 1.0)

1.8(11)(-1.1 - 5.4)

0.7(12)(-0.7 - 2.5)

1.4(12)(-4.3 - 6.6)

18.6(31)(15.2 - 22.8)

0.5(34)(-2.7 - 9.1)

3.7(34)(1.0 - 24)

8.3(34)(-160 - 130)

0.2(44)(-0.2 - 1.8)

-0.2(2)(-0.5 - 0.02)

0.07(2)(0.08 - 0.2)

-58(34)(-770 - 18)

0.4(34)(-2.0 - 2.0)

-0.3(34)(-1.8 - 1.5)

1.0(34)(-1.8 - 4.9)

0.3(34)(-1.0 - 2.3)

0.5(34)(-4.4 - 8.3)


OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1996NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORTING PERIOD: JANUARY 02, 1996 TO JANUARY 06. 1997

MEDIUMOR PATIBVAY IUTALNUMBER OFSAMPLED OF ANALYSES DETECTION

IUNII'FMEASUREMErrD PERFORMFDI I) (LLD) I2)MFANI3)RANGE

CONIROL IOCATION NONROUIINENAME MEAN(3) MEAN(3) REPORTED

DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTSI4)

30

Nb-95 110 15

Cs-134 1 10 15

Cs-137 1 10 18

Ba-140 I 10 60

La-140 1 10 15

Potable Water(pCI/I)

Gross Alpha 17

Gross Beta 17

iodine-131 28

Tritium 17 2000

Gamma SpecK-40 17

Mn-54 17 15

Surface Water Cont. Zr-95 1 10 1.0(76)(-7.7 - 7.7)

1.2(76)(-.5.8 - 4.7)

0.006(76)(-3.4 - 2.4)

0.9(76)(-5.4 - 3.4)

0.4 (76)(-7.0 - 8.0)

-0.4(76)(-7.5 - 3.6)

0.2(17)(-0.6 - 0.9)

2.4(17)(1.6 - 3.6)

0.04(28)(-0.1 - 0.2)

39(17)(-100 - 150)

-63(17)(-170 - -4.8)

0.5(17)(-0.9 - 1.7)

12F15.3 ml WSW

ID33.9 ml N

12F15.3 ml WSW

1D33.9 ml N

LTAWNE - ESE

12G217 mt WSW

12H2T26 ml WSW

12H2T26 ml WSW

12H2T26 mt WSW

12H2T26 mt WSW

12H2T26ml WSW

12H2T26 mt WSW

2.2(12)(-1.1 - 7.2)

1.7(l 1)(-0.34 - 3.5)

0.4(12)(-0.8 - 2.0)

1.9(11)(0 - 3.8)

2. 1(12)(-0.8 - 8.0)

0.5(11)(-0.6 - 1.5)

0.2(17)(-0.6 - 0.9)

2.4(17)(1.6 - 3.6)

0.04(28)(-0.1 - 0.2)

39(17)(-100 - 150)

-63(17)(-170 - -4,8)

0.5(17)(-0.9 - 1.7)

1.9(34)(-3.4 - 9.1)

1.5(34)(-0.7 - 3.5)

'0.2(34)(-4.0 - 2.2)

1.2(34)(-2.8 - 3.8)

-0.02(34)(-8.1 - 5.8)

-0.3(34)(-2.6 - 2.5)

0

0

Only Indicator 0stations sampled forthis medium.


OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1996NAME OF FACIUTY: SUSQUEHANNA STPAM EIZCTRIC STATION

LOCATIONOF FACILITY: LUZERNE COUNTY. PENNSYLVANIAREPORllNG PER)OD: JANUARY 02. 1996 TO JANUARY 06. 1997

MEDIUMOR PAIIPVAY ImALNUMBER OFSAMPLED OF ANALYSES DEIECIION

IUNrl'FMEASUREMEND PERFORMED(I) IIELD) I2)MFANI3)RANGE

CONIROL IDCAIION NONROUIINENAME MEAN(3) MEAN(3) REPORTED

DISTANCE AND DIRECIlON RANGE RANGE MEASUREMENTSI4)

Fe-59 17 30

Co-60 17 15

Zn-65 17 30

Zr-95 17 30

Nb-95 17 15

Cs-134 17 15

Cs-137 17 18

Ba-140 17 60

LQ-140 17 15

Potable Water Cont. Co-58 17 15pCI/I)

-0.4(17)(-2.5 - 2.4)

1.4(17)(-1.0 - 4.6)

-0.07(17)(-1.6 - 2.4)

1.2(17)(-3.4 - 5.4)

1.3(17)(-6.4 - 5.2)

1.5(17)(0.7 - 3.4)

0.6(17)(-1.5 - 2.3)

1.4(17)(-3.6 - 5.1)

-0.3 (17)(-7.0 - 5.2)

-0.3(17)(-3.1 - 1.0)

12H2T26 ml WSW

12H2T26ml WSW

12H2T26m) WSW

12H2T26ml WSW

12H2T26 ml WSW

12H2T26 ml WSW

12H2T26 ml WSW

12H2T26 ml WSW

12H2T26 m) WSW

12H2T26 ml WSW

-0.4(17)(-2.5 - 2.4)

1.4(17)(-1.0 - 4.6)

-0.07(17)(-1.6 - 2.4)

1.2(17)(-3.4 - 5.4)

1.3(17)(-6.4 - 5.2)

1.5(17)(0.7 - 3.4)

0.6(17)(-1.5 - 2.3)

1.4(17)(-3.6 - 5.1)

-0.3(17)(-7.0 - 5.2)

-0.3(17)(-3.1 - 1.0)

ThaLE GSUMMARYOF DATAFOR THE SSES

OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1996NAME'OF FACILITY: SUSQUEHANNA STFMM EIZCTRIC STATION

LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORllNG PERIOD: JANUARY 02, 1996 TO JANUARY 06, 1997

MEDIUMOR PATIIWAY TOTALNUMBER OFSAMPLED OF ANALYSES DETECllON

IUNH'F MEASUREMF2fg PERFORMEDI I) (ILD)QlMMNI3)RANGE

CONfROL IDCATION NONROIJIINENAME MEAN(3) MEANI3) REPORTED

DISTANCE AND DIRECTION RANGE RANGE MEASUREMENISI4)

FIsh(pCI/g wet)

Mn-54 13 0.13

Co-58 13 0. 13

Fe-59 13 0.26

Co-60 13 0.13

Zn-65 13 026

Zr-95 13

Nb-95 13

Gross Beta 13

Gamma SpecK-40 13

5.9(7)(2.1 - 10)

3.5(7)(2.9 - 4.2)

LTAWOn site NE-ESE

LTAWOn site NE-ESE

-0.005(7)(-0.02 - 0.004)

. 0.005(7)(0.0003 - 0.009)

2H30 ml NNE

2H30 ml NNE

0.0008(7) LTAW(-0.005 - 0.005) On site NE-ESE

0.0002(7) IND(-0.007 - 0.009) 0.9-1.4 ml ESE

0.003(7) IND(-0.01 - 0.02) 0.9-1.4 ml ESE

0.0006(7) 2H(-0.003 - 0.005) 30 ml NNE

0.005(7) IND(-0.01 - 0.01) 0.9-1.4 ml ESE

6.3(1)(6.3 - 6.3)

3.6(1)(3.6 - 3.6)

0.002(1)(0.002 - 0.002)

0.0005(6)(-0.007 - 0.009)

0.003(6)(-0.01 - 0.02)

0.004(6)(-0.009 - 0.01)

0.006(6)(-0.01 - 0.01)

0.001(6)(-0.02 - 0.02)

0.007(6)(0.0009 - 0.01)

5.8(6)(3.7 - 8.7)

3.5(6)(2.9 - 4.2)

. 0.001(6)(-0.003 - 0.006)

-0.0005(6)(-0.003 - 0.004)

-0. 009 (6)(-9.02 - 0.003)

0.004(6)(-0.009 - 0.01)

0.004(6)(-0.01 - 0.01)

" 0.001(6)(-0.02 - 0.02)

0.007(6)(0.0009 - 0.01)

Cs-134

Cs-137

13 0.13

13 0.15

0.003(7) 2H(-0.0005 - 0.008) 30 ml NNE

0.003(7) 2H(-0.006 - 0.008) 30 ml NNE

0.005(6)(0.002 - 0.009)

0.005(6)(0.003 - 0.007)

0.005(6)(0.002 - 0.009)

0.005(6)(0.003 - 0.007)

La-140 13

Ba-140 13 0.005(7)(-0.03 - 0.02)

LTAWOn site NE-ESE

-0.0005(7) 2H(-0.01 - 0.01) 30 ml NNE

0.007(1)(0.007 - 0.007)

0.0003(6)(-0.005 - 0.01)

0.0002(6)(-0.01 - 0.008)

0.0003(6)(-0.005 - 0.01)


OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1996NAMEOF FACIIITY: SUSQUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACIIJ1T: LUZERNE COUNTY, PENNSYLVANIAREPORTING PERIOD: JANUARY 02, 1996 TO JANUARY 06. 1997

MEDIUMOR PATIfWAY IUTALNUMBER OFSAMPLED OF ANALYSES

DETECTION

IUNfl OF MEASUREMENT) PERFORMED(l) le) I2)MEANI3)RANGE

CONTROL LOCATION NONROUIINENAME MEAN(3) MEANI3) REPORTED

DISTANCE AND DIRECTION RANGE RANGE MEASUREMElff@4)

Sedhneat(pCI/g dry)

K-40 12

Mn-54 12

Co-58 12

Fe-59 12

Co-60 12

Zn-65 12

Zr-95 12

Nb-95 12

Cs-134 12 0.15

Cs-137 12 0.18

Ba-140 12

La-140 12

Gamma SpecBe-7 12 0.9(8) 12F

(0.05 - 3.4) 6.9 ml WSW

11(8)(8.5 - 16)

2B1.6 mt NNE

0.009(8) 11C(-0.012 - 0.024) 2.6 ml SW

-0. 006(8)(-0.02 - 0.007J

-0.0002(8)(-0.04 - 0.03)

0.005(8)(-0.006 - 0.03)

0.01(8)(-0.03 - 0.07)

0.08(8)(-0.08 - 0.2)

0.03(8)(-0.002 - 0.04)

12F6.9 ml WSW

2B1.6 ml NNE

12F6.9 ml WSW

2B1.6 mi NNE

12F6.9 ml WSW

2B1.6 mi NNE

0.003(8)(-0.05 - 0.07)

-0.02(8)(-0.08 - 0.02)

2B1.6 ml NNE

2F6.4 ml NNE

0.04(8) LTAW(0.02 - 0.07J On site NE-ESE

0.09(8) 12F(-0.002 - 0.121) 6.9 ml WSW

1.9(2)(0.3 - 3.4)

14 (2)(14 - 15)

0.02(2)(0.01 - 0.02)

0.0007(2)(-0.006 - 0.007)

0.02(2)(-0.01 - 0.06)

0.02(2)(0.009 - 0.03)

0.04(2)(-0.01 - 0.09)

0.1(2)(0.09 - 0.1)

0.04(2)(0.03 - 0.05)

0.07(2)(0.07 - 0.07)

0.1(2)(0.1 - 0.1)

0.03(2)(0.02 - 0.03)

0.003(2)(0.0 - 0.006)

0.9(4)(0.09 - 2.3)

12(4)(9.6 - 15)

0.007(4)(-0.0007 - 0.02)

-0.005(4)(-0.01 - 0.004)

0.01(4)(-0.01 - 0.06)

-0.003(4)(-0.02 - 0.01)

0.02(4)(-0.01 - 0.09)

0.06(4)(-0.01 - 0.2)

0.03(4)(0.02 - 0.05)

0.04(4)(0.03 - 0.05)

0.1(4)(0.07 - 0.1)

0.004(4)(-0.03 - 0.03)

-0.01(4)(-0.03 - 0.006)


OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1996NAMEOF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORTING PERIOD: JANUARY 02. 1996 TO JANUARY 06, 1997

MEDIUMOR PAT) lWAY lmALNUMBER OFSAMPLED OF ANALYSES DETECTION

(UN(I'F MEASUREMEWO PERFORMED(I) OLD) (2)MFA(3)RANGE

CONmOL LOCATION NONROUIINENAME MEAN(3) MEAN(3) REPORIED

DISTANCE AND DIRECITON RANGE RANGE . MEASUREMEWIS(4)

Sedtment Cont. Ra-226(pCI/g dry)

Th-228

12

12

1.7(8)(1.2 - 2.1)

1.0(8)(0.8 - 1.3)

2B1.6 ml NNE

2B1.6 ml NNE

2.1(2)(2.0 - 2.1)

1.3(2)(1.2 - 1.4)

1.9(4)(1.6 - 2.1)

1.2(4)(0.9 - 1.4)

Floe(pCI/g dry)

00

Gamma SpecBe-7,

K-40

Mn-54

Co-58

Fe-59

Co-60

Zn-65

Zr-95

Nb-95

Cs-134

Cs-137

1.9(2)(0.3 - 3.6)

13(2)(7.2 - 20)

0.04(2)(0.02 - 0.06)

-0.02(2)(-0.02 - -0.01)

0(2)(-0.05 - 0.05)

-0.001(2)(-0.006 - 0.004)

0.07(2)(0.05 - 0.1)

O.l(2)(0.1 - 0.1)

0.06(2)(0.05 - 0.08)

0.04(2)(0.01 - 0.06)

0.1(2)(0.03 - 0.2)

7B1.2 ml SE

7B1.2 ml SE

7B1.2 ml SE

1.2 m( SE

7B1.2 mt SE

2B1.6 ml'NE

1.2 mt SE

2B1.6 ml NNE

7B1.2 mt SE

2B1.6 ml NNE

2B1.6 mt NNE

1.9(2)(0.3 - 3.6)

13(2)(7.2 - 20)

0.04(2)(0.02 - 0.06)

-0.02(2)(-0.02 - -0.01)

0(2)(-0.05 - 0.05)

0.01(2)(-0.002 - 0.03)

0.07(2)(0.05 - 0.1)

0.2(2)(0.2 - 0.3)

0.06(2)(0.05 - 0.08)

0.05(2)(0.03 - 0.08)

0.1(2)(0.08 - 0.2)

1.3(2)(0.3 - 2.4)

11(2)(7.7 - 14)

0.01(2)(-0.01 - 0.03)

-0.03(2)(-0.04 - -0.03)

-0.06(2)(-0.1 - -0.02)

0.01(2)(-0.002 - 0.03)

0.04(2)(-0.03 - 0.1)

0.2(2)(0.2 - 0.3)

0.06(2)(0.05 - 0.07)

0.05(2)(0.03 - 0.08)

0.1(2)(0.08 - 0.2)

TABLEQSUMMARYOF DATAFOR THE SSES

OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1996NAMEOF FACILITY: SU8QUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACIuTY: LUZERNE COUNTY. PENNSYLVANIAREPORTING PERIOD: JANUARY 02. 1996 TO JANUARY 06. 1997

Floe Cont.(pCI/g dry)

Ba-140 4

La-140

Ra-226

Th-228

MEDIUMOR PA11PVAY 'RXI'ALNUMBER OFSAMPLED OF ANALYSES DETECTION

(UNITOF MEASUREMENT) PERFORMED(I) GAUD) (2lMEAN(3)RANGE

0.04(2)(0.0l - 0.07J

-0.04(2)(-0.05 - -0.04)

0;5(2)(-0.5 - 1.4)

0.8(2)(0.6 - 1.1)

7B1.2 ml SE

2B1.6 ml NNE

2B1.6 ml NNE

7B1.2ml SE

0.04(2)(0.1 - 0.07J

-0.03(2)(-0.06 - 0.005)

0.5(2)(-O.l - 1.1)

0.8(2)(0.6 - 1.1)

0.02(2)(-0.06 - 0.1)

-0.03(2)(-0.06 - 0.005)

0.5(2)(-0.14 - 1.1

0.8(2)(0.6 - 1.0)

CONSOL IDCA'DON NONROIJTINENAME MEAN(3) MEAN(3) REPORIED

DISTANCE AND DIREC11ON RANGE RANGE MEASUREMENTS(4)

Ground Water(pCI/1)

Mn-54 60

Co-58 60

Fe-59 60

Co-60 60

Zn-65 60

Zr-95 60

Nb-95 60

Gamma SpecK-40 60

15

15

30

15

30

30

15

-54(48)(-280 - 68)

0.27(48)(-3.1 - 2.4)

-0.6(48)(-2.6 - 2.5)

1. 1(48)(-4.6 - 4.7J

0.4(48)(-4 - 3.3)

1.9(48)(-6.3 - 14)

1.4(48)(-7.1 - 7.8)

2.7(48)(-1.0 - 7.9)

4S40.5 ml ENE

4840.5 ml ENE

12810.4 ml WSW

4840.5 ml ENE

2820.9 ml NNE

12F35.2 ml WSW

4850.5 ml ENE

12F35.2 ml WSW

-22(12)(-69 - 67)

0.7(12)(-1.0 - 2.4)

0.02(12)(-1.7 - 2.5)

1.4(12)(-1.2 - 4.7)

1. 1(12)(-0.3 - 3.3)

4.4(12)(-2.2 - 12)

2.2(12)(-2.7 - 4.9)

5.1(12)(1.1 - 8.5)

-27(12)(-59 - 28)

0.6(12)(-0.9 - 2.4)

-0.9(12)(-3.5 - 0.7)

0.7(12)(-2.5 - 5.7)

0.2(12)(-2.3 - 3)

4.4(12)(-2.2 - 12)

0.7(12)(-7.4 - 6)

5.1(12)(1.1 - 8.5)


OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1996NAMEOF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACIIITY: LUZERNE COUNTY, PENNSYLVANIAREPORllNG PERIOD: JANUARY 02. 1996 TO JANUARY 06, 1997

Ground Water cont. Cs-134 60(pCI/1)

15

Cs-137 60 18

Ba-140 60 60

La-140 60 15

H-3 60 2000

AirParticulates Gross Beta 518(E-03 pCI/m3)

10

AirIodine(E-03 pCI/m3)

1-131 518 70

MEDIUMOR PATIDVAY imALNUMBER OFSAMPLED OF ANALYSES DETECTION

(UNIT OF MEASUREMENT) PERFORMED(I) (LLD) (2lMFA(3)RANGE

0.05(48)(-2.2 - 2.9)

0.8(48)(-4.4 - 4.1)

0.2(48)(-7.6 - 8.1)

0.09(48)(-3.9 - 3.3)

22(48)(-130 - 140)

16(4 15)(7.3 - 34)

0.2(415)(-6.8 - 120)

4S50.5 ml ENE

12F15.3 ml WSW

4S50.5 ml ENE

4S40.5 ml ENE

4S40.5 ml ENE

SS40.8 ml

0.2(12)(-1.4 - 1.4)

1.7(12)(-1.2 - 4.4)

1.6(12)(-3.6 - 4.4)

0.3(12)(-1.2 - 1.8)

55(12)(-9 - 130)

16(52)(8 - 32)

13860.4 ml

2.4(52)(-4.8 - 120)

NAME MEAN(3)DISTANCE AND DIRECTION RANGE

CONTROL LOCATION NONROIJTINEMEAN(3) REPORTEDRANGE MEASUREMENTS(4)

0.1(12)(-4.1 - 2.5)

1.7(12)(-1.2 - 4.4)

'1.5(12)(-6.2 - 5.2)

-0.3(12)(-4.3 - 1.3)

27(12)(-90 - 150)

'5(103)

(7.5 - 31)

-0.4(103)(-7 - 3.4)

K-40 40

Mn-54 40

Co-58 40

Fe-59 40

AirParticulates Gamma SpecQuarterly Composite(E-03 pCI/m3) Be 7 40 132 (32)

(78 - 176)

0.5(32)(-6.4 - 16)

0.03(32)(-0.1 - 0.2)

-0.04(32)(-0.3 - 0.2)

-0. 1(32)(-0.8 - 0.4)

3S20.5 ml NE

12S10.4 ml WSW

12S10.4 ml WSW

7G114 ml SE

6G113.5 ml ESE

143(4)(97 - 165)

1.8(4)(-6.4 - 16)

0.05(4)(0.01 - 0.1)

O.l(1)(O.l - 0.1)

0.2(4)(0 - 0.7)

126(8)(76 - 176)

0.05(8)-(-1.5 - 2.6)

-0.01(8)(-0.2 - 0.08)

0.02(8)(-0.08 - 0.1)

0.01(8)(-0.6 - 0.7)


OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1996NAMEOF FhCIUTY: SUSQUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACILITY: LUZERNE COUNTY. PENNSYLVANIAREPORllNG PERIOD: JANUARY 02. 1996 TO JANUARY 06. 1997

MEDIUMOR PA'AWAY 1UTALNUMBER OFSAMPLED OF ANALYSES DETECllON

IUNn'F MEASUREMEh 11 PERFORMEDI I) IUD) t2)MFA(3)RANGF.

CONTROL IDCATION NONROVIINENAME MEAN(3) MEAN(3) REPORTED

DISTANCE AND DIRECIlON RANGE RANGE MEASUREMENTSI4)

AlrPaxticuIates cont.Quarterly Composite Co-60 40(E-03 pCI/m3)

Zn-65 40

7r-95 40

Nb-95 40

Cs-134 40

Cs-137 40

Ba-140 40

La-140 40

50

60

-0.002(32)(-0.1 - 0.1)

0.03(32)(-0.4 - 0.4)

0.09(32)(-0.5 - 0.6)

0.07(32)(-0.2 - 0.3)

0.001(32)(-0.1 - 0.1)

0.04(32)(-0.1 - 0.2)

0.8(32)(-7.3 - 7.8)

-0.3(32)(-4.4 - 3.9)

7S70.4 ml SE

6GI13.5 ml ESE

12SI0.4 ml WSW

13S60.4 ml W

8GI12 ml SSE

9BI1.3ml S

12SI0.4 ml WSW

IOS30.6 m) SSW

0.03(4)(-0.007 - 0.08)

0. 1(4)(0.06 - 0.3)

0.3(4)(0.2- 0.6)

0. 1(4)(0.07 - 0.2)

0.07(3)(0.04 - 0.08)

0. 1(4)(0.02 - 0.2)

3.5(4)(0 - 7.6)

1.2(4)(-0.8 - 3.4)

-0.00003(8)(-0.2 - 0.2)

0.07(8)(-0.07 - 0.3)

0.02(8)(-0.2 - 0.2)

0.06(8)(-0.08 - 0.2)

0.02(8)(-0.07 - 0.09)

0.04(8)(-0.08 - 0.2)

-0.6(8)(-3.7 - 3.8)

0.3(8)(-2.3 - 2.2)

TABLEQSUM)NARYOF DATAFOR THE SSES

OPERATIONALRADIOLOGICALENVIRONMENTALMONrI'ORING PROGRAM - 1996NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPO)mNG PER)OD: JANUARY 02. 1996 TO JANUARY 06, 1997

MEDIUMOR PATIIWAY mTALNUMBER OFSAMPLED OF ANALYSES DETECnON

(UN'F MEASUREMENI) PERFORMED(I) (LLD) I2)MFANI3)RANGE

NAME MEANI3)DISTANCE AND DIRECI1ON RANGE

CONIROL LOCATION NONROIJTINE.MEAN(3) REPORTEDRANGE MEASUREMENTSI4)

Preclpltatlon(pCI/)) H-3 40

K-40 40

Mn-54 40

Co-58 40

Fe-59 40

Co-60 40

Zn-65 40

Zr-95 40

Nb-95 40

Cs-134 40

Cs-137 40

Ba-140 40

Gamma SpecBe-7 40

-7.4 (32)(-170 - 130)

32(32)(12 - 64)

-62(32)(-350 - 18)

0.4(32)(-2.3 - 2)

-0. 1(32)(-2.1 - 1.3)

1.7(32)(-3 - 6.7J

0.09(32)(-1.5 - 1.8)

1.3(32)(-2.6 - 4.9)

0.9(32)(-3.4 - 5.7)

1.3(32)(-1.7 - 3.4)

0. 1(32)(-3.2 - 3.7J

1. 1(32)(-3.1 - 3.9)

-0.3(32)(-8.4 - 6.6)

7GI14 ml SE

IOS30.6ml SSW

7GI14 ml SE

SGI12 ml SSE

8GI12 ml SSE

IOS30.6 ml SSW

12EI4.7 ml WSW

7GI14 ml SE

3820.5 ml NE

12EI4.7 ml WSW

5S40.8 ml E

8GI12ml SSE

3820.5 ml NE

39(1)(39 - 39)

38(4)(18 - 53)

-4.2(1)(-4.2 - -4.2)

1.4(3)(0.7 - 2.5)

0.3(3)(-0.5 - 1.5)

2.8(4)(0.6 - 6)

0.9(4)(0.3 - 1.6)

4(1)(4 -4)

2.0(4)(-0.2 - 5.7)

2.3(4)(1.5 - 2.9)

1.4(4)(-1.0 - 3.7J

2.2(3)(1.8 - 3)

2.3(4)(-0.3 - 6.6)

-4(8)(-100 - 51)

22(8)(4.6 - 50)

-39(8)(-100 - 27J

~ 0.8(8)(0.04 - 2.5)

-0.04(8)(-1.0 - 1.5)

1.8(8)(-0.8 - 3)

0.2(8)(-1.1 - 1.0)

-0.3(8)(-5.7 - 4)

0.8(8)(-2.6 - 2.6)

1.1(8)(0.3 - 3.1)

-0.4(8)(-3 - 0.8)

1.7(8)(-1.1 - 3.2)

1.1(8)(-1.7 - 6.2)


OPERATIONALRADIOLOGICALENVIRONMENTALMONITORING PROGRAM - 1996NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORllNG PERIOD: JANUARY 02, 1996 TO JANUARY 06. 1997

MEDIUMOR PATIPVAY ImTALNUMBER OFSAMPLED OF ANALYSES DETECTION

(UNII'FMEASUREMEÃll PERFORMF D(I) (LLD) (2)MFA'(3)RANGE

CONIROL LOCATION NONROU11NENAME MEAN(3) MEAN(3) REPORTED

DISI'ANCE AND DIRECI1ON RANGE RANGE MEASUREMENTS(4)

Mlllr(pCI/l)

1-131 76

Gamma SpecK-40 76

Mn-54 76

Co-58 76

Fc-59 76

Co-60 76

Zn-65 76

Zr-95 76

Nb-95 76

Cs-134 76

Cs-137 76

Prcclpitatlon cont La-140 40(pCI/I)

-0.09(32)(-3.0 - 4.7)

1 0.004(57)(-0.2 - 0.2)

1325(57)(1080 - 1540)

0.4(57)(-1.8 - 2.8)

-0.2(57)(-2.5 - 2.0)

0.03(57)(-5.3 - 3.3)

0.3(57)(-2.1 - 3.0)

0.3(57)(-7.7 - 7.4)

0.7(57)(-5.0 - 6.1)

1.0(57)(-3.0 - 3.4)

15 0. 1(57)(-2.3 - 3.4)

18 1.8(57)(-0.8 - 4.9)

12sl0.4 ml WSW

10D23.1 ml SSW

10Dl3 ml SSW

12B32.0 ml WSW

12B32.0 ml WSW

10G114 ml SSW

10G114 ml SSW

10D13 ml SSW

10D13 mi SSW

12B32.0 ml WSW

10D23.1 ml SSW

10D23.1 ml SSW

0.9(4)(-0.6 - 4.7)

0.01(19)(-0.2 - 0.2)

1396(19)(1170 - 1540)

0.6(19)(-1.7 - 2.8)

-0. 1(19)(-1.8 - 1.3)

1. 1(19)(-3.2 - 4.6)

0.9(19)(-2.8 - 3.9)

0.8(19)(-4.9 - 6.9)

1.2(19)(-3.3 - 4.8)

1.5(19)(-1.2 - 3.4)

0.4(19)(-1.4 - 3.4)

2.1(19)(-0.2 - 4.9)

-0.4(8)(-2.6 - 3.3)

-0.008(19)(-0.1 - 0.07)

1295(19)(1180 - 1420)

0.5(19)(-0.4 - 1.9)

-0.4(19)(-1.9 - 0.7)

1. 1(19)(-3.2 - 4.6)

0.9(19)(-2.8 - 3.9)

0.01(19)(-5.2 - 6.8)

0.001(19)(-6.5 - 5.0)

1. 1(19)(-3.5 - 3.5)

0.4(19)(-1.8 - 3.7)

1.2(19)(-5.3 - 3.5)


OPERATIONALRADIOLOGICALENVIRONMENTALMONITORING PROGRAM - 1996NAME OF FACILITY: SUSQUEHANNA STEAM EIZCTRIC STATION

LOCATIONOF FACILITY) LUZERNE COUNTY. PENNSYLVANIAREPOIWNG I'ERIOD: JANUARY 02, 1996 TO JANUARY 06, 1997

MEDIUMOR PAT)fWAY lmTALNUMBER OFSAMPLED OF ANALYSES DETECIlON

IUNITOF MEASUREMENI) PERFORMEDI I) OLD) I2)MEANI3)RANCE

CONTROL LOCA11ON NONROIJI1NENAME MEAN(3) MEANI3) REPORTED

DISTANCE AND DIRECTION RANCE RANGE ~ MEASUREME)rISI4)

MIIIt.Cont.(pCI/I

Soll(pCI/g dry)

Ba-140 76

La-140 76

Mn-54 20

Co-58 20

Fe-59 20

Co-60 20

Zn-65 20

Zr-95 20

Nb-95 20

Cs-134 20

Cs-137 20

Ba-140 . 20

Gamma SpecK-40 20

60

15

O. I (57)(-6.4 - 7.9)

-0.03(57)(-2.1 - 2.7)

11(16)(8.9 - 14)

0.003(16)(-0.01 - 0.01)

-0.008(16)(-0.02 - 0.004)

0.005(16)(-0.03 - 0.04)

0.002(16)(-0.01 - 0.01)

0.007(16)(-0.03 - 0.07)

0.05(16)(-0.03 - 0.2)

0.03(16)(0.003 - 0.06)

0.03(16)(0.007 - 0.06)

0.2(16)(0.02 - 0.4)

-0.003(16)(-0.05 - 0.04)

IODI ~

3.0 m) SSW

12B32.0 ml WSW

6GI13.5 ml ESE

6GI13.5 ml ESE

5840.8ml E

9BI1.3 ml S

5S40.8 ml E

3S20.5 ml NE

IOS30.6 ml SSW

12SI0.4 ml WSW

6GI13.5 ml ENE

6GI13.5 ml ENE

9BI1.3 ml S

0.7(19)(-2.3 - 3.9)

0.1(19)(-1.3 - 2.7)

19(2)(18 - 21)

0.02(2)(0.01- 0.02)

0.004(2)(0.004 - 0.004)

0.02(2)(-0.002 - 0.04)

0.01(2)(0.008 - 0.01)

0.03(2)(-0.007 - 0.07)

0.1(2)(0.06 - 0.2)

0.04(2)(0.03 - 0.06)

0.05(2)(0.05 - 0.06)

0.6(2)(0.09 - 1.2)

0.02(2)(0.02 - 0.03)

-0.2(19)(-9.1 - 5.9)

-0.2(19)(-2.0 - 1.8)

14 (4)(7.0 - 21)

0.02(4)(0.01 - 0.02)

-0.009(4)(-0.02 - 0.002)

-0.01(4)(-0.03 - -0.002)

. 0.002(4)(-0.01 - 0.02)

-0.03(4)(-0.07 - -0.01)

0.008(4)(-0.06 - 0.04)

0.02(4)(-0.01 - 0.05)

0.05(4)(0.04 - 0.06)

0.4(4)(0.09 - 1.2)

-0.008(4)(-0.06 - 0.05)


OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1996NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACiuTY: LUZERNE COUNTY. PENNSYLVANIAREPOImNG PERIOD: JANUARY 02. 1996 TO JANUARY 06. 1997

MEDIUMOR PATIWAY 1mAL NUMBER OFSAMPLED OF ANALYSES DETECTION

(UNH'F MEASUREMEÃD PERFORMFD(ll (lLD) (2)MEAN(3)RANGF.

NAME MEAN(3)DISTANCE AND DIRECI1ON RANGE

CONIROL LOCA'11ON NONROU11NEMEAN(3) REPORIEDRANGE MEASUREMENTS(4)

Soil ConL(pCI/g dry)

Food/GardenCrops(pCI/g wet)

La-140 20

Ra-226 20

Gamma SpecBe-7 43

K-40 43

Mn-54 43

Co-58 43

Fe-59 43

Co-60 43

Zn-65 43

Zr-95 44

Nb-95 43

Th-228 20

-0.02(16)(-0.04 - 0.02)

1.5(16)(0.9 - 2.4)

0.8(16)(0.6 - 1.4)

0.02(35)(-0.02 - 0.2)

2.0(35)(0.6 - 3.5)

0.00003(35)(-0.005 - 0.004)

-0.001(35)(-0.005 - 0.001)

0.0009 (35)(-0.006 - 0.01)

0. 0005 (35)(-0.002 - 0.007)

0.0001(35)(-0.01 - 0.01)

0. 003 (36)(-0.01 - 0.02)

0.002(35)(-0.009 - 0.005)

9B11.3 ml S

10S30.6 ml SSW

6G113.5 ml ENE

8A40.9 m! SSE

12F78.3 ml WSW

SA40.9 ml SSE

9B41.1 ml S

SA40.9 ml SSE

SA40.9 ml SSE

12F78.3 ml WSW

12F78.3 ml WSW

9B41.1 ml S

0.005(2)(-0.01 - 0.02)

2.2(2)(2.0 - 2.4)

1.2(2)(1.2 - 1.3)

0.04(3)(-0.009 - 0.07)

2.6(2)(2.0 - 3.3)

0.002(3)(0.002 - 0.004)

-0.0001(2)(-0.001 - 0.001)

0.004(3)(0.0002 - 0.009)

0.004(3)(0.0004 - 0.007)

0.003(2)(-0.002 - 0.009)

-0.01(4)(-0.04 - 0.03)

1.6(4)(1.0 - 2.3)

'.0(4)

(0.7 - 1.3)

0.001(8)(-0.02 - 0.02)

1.9(8)(1.0 - 3.3)

0.00004(8)(-0.004 - 0.004)

-0.001(8)(-0.006 - 0.0004)

0.002(8)(-0.004 - 0.009)

0.0006(8)(-0.003 - 0.003)

0.003(8)(-0.004 - 0.008)

0.003(2)(0.003 - 0.004)

0.002(8)- (0.0001 - 0.004)

0.006(2) 0.002(8)(0.005 - 0.007) ' (-0.008 - 0.007)

0

TABLEGSUMhGQIY OF DATAFOR THE SSES

OPERATIONALRADIOLOGICALENVIRONMENTALMONITORING PROGRAM - 1996NAME OF FACIuTYI SUSQUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACILITY: LUZERNE COUNTY. PENNSYLVANIAREPOlmNG PERIOD: JANUARY 02, 1996 TO JANUARY 06. 1997

MEDIUMOR PAT((WAY mTALNUMBER OFSAMPLED OF ANALYSES DETECIlON

(UNO'F MEASUREMENII PERFORMED(I) (Lu)) l2lMFAN(3)RANGE

CONIROL LOCATION NONROIJIINENAME MEAN(3) MEAN(3) REPORIED

DISTANCE AND DIRECIION RANGE RANGE MEASUREMENTS(4)

I

CJl

Food/Garden Cant.Crops(pCI/g wet)

Antnutls(pCI/g wet)

1-131

Cs-134

Cs-137

Ba-140 43

La-140 43

Gamma SpecK-40 12

Mn-54 12

Co-58 12

Fe-59 12

Co-60 12

Zn-65 12

Zr-95 12

0.0007(35)(-0.01 - 0.009)

-0.0005(35)(.0.02- 0.006)

3.5(10)(2.4 - 4.7)

0.001(10)(-0.002 - 0.005)

0.0002(10)(-0.003 - 0.003)

-0.002(10)(-0.008 - 0.006)

0.0002(10)(-0.004 - 0.004)

0.003(10)(-0.005 - 0.02)

0.003(10)(-0.002 - 0.009)

Nb-95 12 0.003(10)(0.0003 - 0.004)

43 0.06 -0.000 I (35)(.0.004 - 0.004)

43 0.06 -0.0007(35)(-0.006 - 0.004) ~

43 0.08 0.002(35)(-0.003 - 0.007)

13G216m( W

13G216ml W

12F78.3 ml WSW

13G216ml W

12F78.3 ml WSW

3SOnslte NE

3SOnslte NE

3SOnslte NE

3SOnslte NE

3SOnslte NE

IOSOnsite SSW

13G10-20 ml W

16F5-10 mt NNW

0.001(8)(-0.0009 - 0.008)

0.0002(8)(-0.002 - 0.004)

0.003(2)(0.003 - 0.003)

0.009(8)(-0.003 - 0.05)

0.006(2)(0.005 - 0.006)

4.7(1)(4.7 - 4.7)

0.005(1)(0.005 - 0.005)

0.003(1)(0.003 - 0.003)

0.006(1)(0.006 - 0.006)

0.003(1)(0.003 - 0.003)

0.01(1)(0.01 - 0.01)

0.009(1)(0.009 - 0.009)

0.004(1)(0.004 - 0.004)

0.001(8)(-0.0009 - 0.008)

0.0002(8)(-0.002 - 0.004)

'.002(8) 0(-0.0002 - 0.005)

0.009(8)(-0.003 - 0.05)

-0.003(8)(-0.03 - 0.003)

3.3(2)(2.3-4.3)

0.0005(2) 0(-0.0008 - 0.002)

-0. 002(2)(-0.004 - 0)

0.0006(2)(-0.002 - 0.003)

0.002(2)(0 - 0.003)

-0.004(2)(-0.02 - 0.009)

0.005(2) 0(-0.0004 - 0.009)

0.002(2)(0'.002 - 0.002)

TABLE0SUMMARYOF DATAFOR THE SSES

OPERATIONALRADIOLOGICALENVIRONIHENThL'MONITORINOPROGRAM - 1996NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREI'OKllNG I'EftlOD: JANUARY 02. 1996 TO JANUARY 06. 1997

MEDIUMOR PATIIWAY 'mfALNUMBER OFSAMPLED OF ANALYSES DETECTION

(UN(I'OF MEASUREMENf) PERFORMED(ll (LLD)(2)MDLN(3)RANGE

CONfROL LOCATION NONROIJHNENAME MEAN(3) MEAN(3) REPORfED

DISTANCE AND DIRECf(ON RANGE RANGE MEASUREMEhKQ4)

An(mals Ccau(pCI/g wet)

Cs-137 12

13a-) 40 12

La-140 12

Cs-134 ~ 12 0.0002(10)(-0.003 - 0.002)

0.2(10)(0.00 1 - 1.2)

0.002(10)(-0.004 - 0.006)

-0.0007(10)(-0.01 - 0.005)

7SOnslte SE

16F5-10 int NNW

16H>20 ml NNW

10SOnslte SSW

0.002(2)(0.002 - 0.002)

1.2(1)(1.2 - 1.2)

0.03(1)(0.03 - 0.03)

0.004(1)(0.004 - 0.004)

-0.0009(2) 0(-0.001 - -0.0006)

0.03(2)(0.01 - 0.05)

0.02(2)(0.006 - 0.03)

0.002(2)(0.0004 - 0.004)

1. The total number of analyses does not Include dupl(cates, splits or repeated analyses.2. The Technical Spec(Acat(on LLD's are shown when appl(cable.3. The means are based on all analysis resu(ts.4. USNRC reporting levels are specIAed In the Technical SpeclAcat(ons.

APPENDIX H

COMPARISON OF INDICATORAND CONTROL1996 REMP ANNUALMEANS FOR SELECTEDMEDIAANALYSISRESULTS WITHMEANS

FROM PRKOPERATIONALAND PRIOROPERATIONALPERIODS

1996 Radiological Environmental Monitoring Rcport H-1

A endix H

The data presented in the following tables were included ifspecific analysis resultsroutinely exceeded the applicable MDCs in 1996 and/or routinely may have done so inprevious years. While the comparisons may be useful for observing any step changesthat may occur in the environment over a wide area, the importance attached to thesecomparisons should be tempered by the understanding that changes in methods ofanalysis, typical MDCs achieved by the analyses, and averaging methods over the yearsmay tend to blur the picture in some cases.

Note that medians are presented in these tables in addition to means ~onl when thereappears to be a significant difference between them.

1996 Radiological Environnicntal Monitoring Rcport 8-2

A endix H

AMBIENTRADIATIONMONITORING

TABLEHI'''A'MBIENT:'R'ADIATION:LEVELSAS'.MEA'SURED.'BY<TLDSN iiiR/STD," XR

Fi;'ocation

'eriod Pre-0Indicator

0 erational Pre-0Control

0 erational197S-81 1982-95 1996 1978-81 1982-95 1996

Ran e 18.5-19.2 14.1-19.2 15.0-17.9 14.8-19.2Mean 18.9 17.6 18.1 16.3 17.4 18.6

A VATICPATHWAYMONITORING

TABLEH2'SURFACE WATER GROSS 'ALPHA''CTDITHES'Ci/l"""""':.~-'""'"''''

~~'ocation

PeriodRan e

Mean

1984-95

0.4 - 4.31.5

Indicator1996

0.76

1984-95

0.2 - 3.1

1.2

Control1996

0.45

TABLEH3SURFACE WATER GROSS BETAACTIVITIES Ci/l

LocationPeriod Pre-0

Indicator0 erational Pre-0

Control0 erational

1978-81 1982-95 1996 1978-81 1982-95 1996

Ran e

Mean3.2-4.9

3.83.0-7.7

5.5 5.62.9-5.2

4.02.9-4.8

3.7 3.7

TABLEH4SURFACE WATER IODINE-131 ACTIVITIES Ci/l



Control0 erational

1979-81 1982-95 1996 1979-81 1982-95 1996Ran e

Mean0.24-0.37

0.290.06-0.60

0.28 0.130.29-0.43

0.360.03-1.0

0.27 0.15

H-3 1996 Radiological Environmental Monitoring Rcport

A endix H

TABLEHS

<~VV":i":FFiY4i."'~~8"',@"'-'SURFA'CE'WATERTIUTIUM'ACI'IVITIES'. Ci/1 '-""'-'mVl~&9$N;-:~!~%+Z~R-'','ocation

Period Pre-0Indicator


0 erational1978-81 1982-95 1996 1978-81 1982-95 '1996

Ran e

Mean 109 482101-122 126-1068

310119-319

171

-11-21290

*1990 results were not averaged with 1982-95 data because the validity of the1990 values is questionable in some instances. Laboratory analysis error issuspected. See the 1990 Annual Report.

TABLEH6DRINKINGWATER GROSS ALPHAA'CTIVITIES'Ci/1-

Period

Ran e

Meanmedian **

Preo erational1980- 81

1.3

0 erational1982 - 95

0.1 - 10.0

2.11.2

1996

0.17

TABLEH 7

DRINKINGWATER GROSS BETA ACTIVITIES Ci/1

Period

Ran e

Mean


2.2 - 3.22.7

0 erational1982- 95

2.4 - 5.43.3

1996

2.4

~ TABLEH 8

DRINKINGWATER TRITIUMACTIVITIES Ci/IPeriod

Ran e

Mean

Preo erational1977 - 81

101 - 194

132

0 erational1982- 95

1.5 - 22095

1996

39

1996 Radiological En>ironrncntal Monitoring Rcport HA

A @radix H

TABLEH9i::,"*'-,:"4!'i!i''!';::i!i*,"WlllSK'GROSS:BETA KCINIIBtl '::iFet ~4@h>4>4i-~R44~4'~4@

IndicatorLocationPeriod 1984- 95

Ran e 3.7 - 6.1

1996

Control1984- 952.2- 6.8

1996

Mean 5.0 5.9 4.6 5.8

TABLEHIO'SH POTASSIUM-40 A

LocationPeriod

ControlIndicatorPre-0 0 erational Pre-0 0 erational1977-81 1982-95 1996 1977-81 1982-95 1996

Ran e

Mean 3.2 3.82.7 - 3.5 3.1 - 5.3 2.8 - 3.6 . 3.1 - 4.2

3.5 3.2 3.6 3.5

TABLEHIISEDIMENT POTASSIUM-40 ACTIVI'.HES'i/ d



Control0 erational

Ran e

1978-81

8.6-10.41982-95

7.4-13.21996 1978-81

7.5-11.01982-95

6.2-13.01996

9.3 10.3 11.4 9.4 10.5 12.2

TABLEH 12SEDIMENT RADIUM-226ACI'IVITIES Ci/ d

Location



0 erational1978-81 1982-95 1996 1978-81 1982-95 1996

Ran e

Mean0.5-0.7

0.60.5-1.9

1.4 1.7

0.6-1.90.7

0.4-2.11.5 1.9

TABLEH 13

SEDIMENTTHORIUM-228 ACTIVI'1'IES Ci/ dLocationPeriodRan e

Mean

Indicator1984- 95%

1.0 - 1.3

1996

1.0

Control1984 -

95'.0

- 1.4

1996

1.2

'Th-232 was reported instead ofTh-228 in 1990.

H-5 1996 Radiological Environmental Monitoring Report

andi'

TABLEHI4

IndicatorLocation

'EBS''IO'"RM'"MOMERTCMOM137KGSIVPIBE 'C.g:"PQ a~ 'VPB'P'g TGROC'jgCQCTA~~B'~'@~g~)

ControlPeriod Pre-0 0 erational P~ 0 erational

1978-81 1982-95 1996 1978-81 1982-95 '996Ran e

Mean0.08-0.15 0.04-0.17

0.10 0.10'0.08.21 0.06-0.21

0.088 0.12 0.12 0.084

TMOSPHERIC PATHWAYM NITORING.

TABLEH15

AOIPARIICIIEATSGROSS SETA'CBVIIBB '11'ocation


0 erationalControl

Pre-0 0 erational1978-81 1982-95 1996 1978-81 1982-95 1996

Ran e

Mean24-97

61

13-2917 16

24» 102 12-2862 16 15

TABLEH 16

AIRPARTICULATEBERYLLIUM-7ACITVEHES 3 Ci/mLocationPeriod

IndicatorPre-0 0 erational Pre-0

1996 1978-811978-81 1982-95

Control0 erational

1982-95 1996 .

Ran e

Mean69- Sl

7662- 124

83 132

59- 85

7253 - 119

79 126

~ l990 results were not averaged with 1982-95 data because the validity ofthe1990 values is questionable in some inst'ances. Laboratory analysis error issuspected. See the 1990 Annual Report.

1996 Radiological Eaviroatacatal Moaitoriag Rcpart

A endir H

TABLEH17':-PRECIPITATIONTIKIIUMACIXVH'IES' Ci/1:

LocationPeriod Pre-'0

Indicator0 erational

ControlPre-0 0 erational

'980-$ 1 1983-95 1996 1980-$ 1 1983-95 1996.

Ran e 119- 213 13 - 200 99 - 135. -25 - 530Mean 166 97 -7 117

~1990 results were not average'd with 1982-95 data because the validity of the1990 values is questionable in some instances. Laboratory analysis error issuspected. See the 1990 Annual Report.

TERRESTRIAL PATHWAYMONITORING .

TABI.EH 1SSOIL POTASSIUM<0 ACTIVH'IES Ci/ d


Indicator0 erational

ControlPre-0 0 erational

1979&81 1984-95 1996 1979&81 1984-95 1996Ran e

humean

9.2 - 9.79.5

9.4-14.310.7

9.1-11.0 7.4-14.110.1 10.5 13.6

Location

TABl.EH 19

SOIL RADIUM-226ACTIVITIES Ci/ d

Indicator ControlPeriod

Ran e

Pre-01979&810.8 - 1.3

1984-95

0.8 - 2.5

19960 erational Pre-0

1979&810.8-

1.2'984-951.0 - 2.1

19960 erational

humean 1.6 1.5 1.0 1.8 1.6

TABI.EH 20SOIL THORIUM-228 ACTIVITIES Ci/ d



Control0 erational.

1979&81 1984-95 1996 1979&81 1984-95 1996Ran e

Mean0.9 - 1.3 0.8 - 1.3

1.0 0.8 1.00.9 - 1.2

1.0

H-7 1996 Radiological Environmental Monitoring Report

TABLEHZl@~>+"WA~5'l..%5,:'SO@'CESIUM-137,'A'i/ '8 Pp~a4~43>~'+s~p'~i~aP+44

Location Indicator ControlPeriod Pre-0

1979481 1996 1979Ec81 1982-951982-95 19960 rational P~ 0 erational

0.6MeanRan e 0.5 - 0.7 0.2 - 0.5

0.30.2 - 1.2 0.2 - 1.2

0.2 0.7 0.5 0.4

Location

TABLEH22'MILKPOTASSIUM-40 A

Indicator ControlPeriod Pre-0

1978-81 19961985-950 erational

1978-81 1985-95 1996

Pre-0 0 erational

Ran e

Mean1222-1500

1325

1241-13571325 1325

1273-1500 1247-13631390 1334 1295

TABLEH23FRUHS/VEGETABLES POTASSIUM<0 ACX'IVITXES Ci/ wet '"'.".-"-'' '"8



Control0 erational

1980-81 1982-95 1996 19SO-S1 1982-95 1996Ran e

Mean2.5 - 3.0

2.82.~.2

2.9 2.03.0- 3.1

3.12.2 - 2.8

2.5 1.9

' 990 results were not average with 1982-95 data because the validity ofthe)990 values is questionable in some instances. Laboratory analysis error issuspected. See the 1990 Annual Report.

TABLEH 24.

GAME POTASSIUM-40 ACI'IVITIES Ci/ wetPeriod

Ran e

Mean

Preo erational1972 - 81

1.8 - 4.82.8

0 erational1982- 95

2.7 - 3.83.1

1996

3.5

~1990 results were not averaged with 1982-95 data because the validity ofthe1990 values is questionable in some instances. Laboratory analysis error issuspected. See the 1990 Annual Report.


A endir H

TABLEH2$.GAME CESIUM-137 ACTDZllES'Ci/ wet

Period

Ran e

Meanmedian


0.0 - 8.8

1.9

1.1

0 erational1982- 95

0.1 - 1.6

0.6

1996'

0.2

"TABLEH26GROUND WATER TRITIUMACTIVI'I'IES CU1


Indicator0 erational 'Pre-0

Control0 erational

1980-81 1982-95 1996 1980-81 1982-95 1996Ran e

Mean94-109

101

11 - 180

91 22 118 110

117- 119 17- 260

27.'-9

l996 Radiological Environmental Monitoring Report

APPENDIX I

SPECIFIC ANALYSISRESULTS TABULATEDBYMEDIAAND SAMPLINGPERIOD


A endix I

Results ofanalyses are generally reported in the following tables to two significantfigures. Random uncertainties ofcounting are reported to the same decimal place as theresult.

Calculated values for analysis results in the tables that followare reported with therandom uncertainty ofcounting at two standard deviations (2S), determined byconsidering both the sample and background count rates. The uncertainty ofan activityis influenced by the volume or mass of the sample, the background count rate, the counttimes, the method used to round offthe value obtained to reflect its degree ofsignificance, and other factors. The uncertainties ofactivities determined by gammaspectrometric analyses are also influenced by the relative concentrations ofthe-radionuclides in the sample, 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 these tables are below the minimum detectableconcentrations (MDCs). The MDC is an estimate of the detection capabilities of theoverall measurement method, taking into account not only the counting system, but alsothe characteristics of the sample being counted. When the MDC is used as the level todecide whether or not to enter a measured value into a table, there is a 50% chance thatthe value willbe entered when the actual sample activity is equivalent to the MDC.There is only a five percent chance that a value representing a fluctuation in backgroundactivity willbe entered as sample activity in such an instance.

Measured values for the activities of specific radionuclides, such as the man-madegamma-emitting radionuclides beryllium-7 and cesium-l37, only appear in the followingtables for each specific medium when the levels that are measured exceed the MDCvalues for those measurements and those radionuclides are actually identified as presentin the samples. Measured values for the analyses that are not radionuclide specific, suchas gross alpha and beta analyses, also are presented in the tables for specific media onlywhen the levels that are measured actually exceed the MDCs.

1996 Radiological Environmental Monitoring Rcport I-2

TABLEI-I

ENVIRONMENTALTHERMOLUMINESCENTDOSIMETRY RESULTS

SUSQUFJ IANNASTEAM ELECTRIC STATION - 1996

Results (I) are in mR/std. qtr. (2) + 2S (3)

Page I of7

First Quarter

I/16/96

to

~4/ /96

TLDs W THI PAL BOU R

Second Quarter

4/9/96

to

~/I I/96

Third Quarter

7/10/96

to

/0//0/96

Fourth Quarter

10/8/96

to

I/14/97

IS2 +2S2

2S3 +

3S2

3S3-

3S4 +4S3 +4S6

5S4

5S7 +6S4 +6S9 +7S6 +7S7

7S8

8S2 +9S2 +

18.2 + 0.5

18.0 4 0.6

16.8 + 0.6

16.8 + 1.1

16.3 + 0.9

15.9 + 1.6

19.4 6 0.8

16.7 + 1.2

15.0 *0.7

15.6 + 0.8

21.1 4 0.8

19.2 4 0.8

18.1 + 1.0

16.2 + 0.9

16.3 + 0.6

19.0 + 0.3

23.2 + 1.3

17.5 + 1.3

17.3 + 0.4

17.0 + I.O

15.9 + 1.0

16.1 + 0.7

15.5 + 0.7

18.8 + 1.3

17.0 6 0.9

15.0 + 1.0

15.7 + 0.9

20.9 + 1.0

19.7 + 1.4

17.8 + 1.0

15.7 + 1.0

16.1 + 0.9

18.5 + 1.4

22.4 + 0.5

17.4 + 1.1

19.0 + 0.6

16.6 + 0.5

16.2 + 0.4

17.8 + 0.6

15.1 + 0.9

18.8 + 0.7

18.4 + 0.6

14.7 6 1.0

15.6 + 0.6

20.7 + 1.1

18.7 + 1.2

18.8 + 0.6

17.3 + 0.8

17.2 + 0.7

18.1 + 1.1

22.0 + 1.2

18.2 + 1.2

19.3 + 1.0

17.7 + 0.8

16.6 + 1.4

17.8 * 1.1

16.2 + 1.0

19.8 + 1.4

18.3 + 0.6

16.3 + 1.3

16.7 + 1.1

22.4 6 1.6

19.8 + 1.1

20.1 + 1.5„

17.6 + 0.8

17.5 6 1.4

19.6 6 1.7

23.7 6 2.3

See the comments at the end ofthe table.

TABLEI-I

ENVIRONMENTALTIIERMOLUMINESCENTDOSIMETRY RESULTS

SUSQUF3 IANNAS f7~ ELECTRIC STATION - 1996


+ca~tin

First QuarterI/16/96

to4/I I/96

Second Quarter4/9/96

fo

7/I I/96

Third Quarter7/10/96

to/0//0/96

Fourth Quarter10/8/96

toI/14/97

IOSI +

IOS2

IOS3

IIS3 +

IIS712SI

12S3 +

12S4

12S5

12S6

12S7

13S2 +

13S4

13S5

13S6

14S5 +

14S6

15S5 +16SI +16S2 +

15.1 + 0.9

21.2 + I.I15.3 + 1.0

23.0 + 1.6

16.9 + 0.6

18.2 + 0.8

20.2 + 1.2

20.1 + I.I18.7 + 0.8

17.6 + 0.9

16.4 + 2.1

19.2 + 1.1

20.2 + 0.6

21.3 + 0.6

19.6 + 1.4

20.0 + 1.0

18.5 6 0.6

17.6 + 1.1

17.9 + 1.0

19.7 A 1.5

14.9 + 1.0

21.0 + 1.3

15.5 + 0.9

22.2 + 1.3

17.6 + 1.6

17.9 + I.l21.2 + 1.6

21.4 + 0.9

18.7 + 1.0

17.9 + 0.6

15.5 A 1.0

18.9 + 1.4

19.7 + 1.4

21.0 + 1.4

19.5 +0.819.3 A 0.7

18.6 + 1.3

17.9 4 1.1

18.3 + 0.7

19.3 + I.I

14.7 + 0.6

20.2 + 0.7

14.9 + 1.2

22.4 + I.I17.3 + 0.8

18.0 + 1.2

21.4 + 1.3

21.3 + 1.4

18.9 + 1.3

18.2 + 1.2

15.4 + 0.9

18.5 + 0.5

20.2 6 0.9

20.6 + 0.9

20.1 6 1.4

19.8 + 0.8

18.9 + 0.4

17.9 6 0.6

17.6 + 0.8

19.6 + 0.9

15.6 + 1.3

22.6 + 1.3

16.0 + 1.3

23.9 + 1.0

18.8 + 0.9

19.0 6 1.5

22.8 + 0.7

22.8 + 1.4

19.8 + 1.0

19.3 + 1.3

17.0 + 0.5

19.7 + 1.5

21.5 + 1.3

22.7 + 1.6

21.3 + 0.8

20.6 + 1.3

20.1 + 2.2

19.0 + 0.7

18.8 A 0.9

20.6 + 1.6

See the comments at the end of this table.

of7

TABLE I-I

ENVIRONMENTALTHERMOLUMINESCENT DOSIMETRY RESULTS

SUSQUEf IANNASTEAM ELECTRIC STATION - 1996


~Loca//o

0-1 MILK0

First Quarter

I/16/96

to

~4/ I/96

Second Quarter

4/9/96

to

~7/ I/96

Third Quarter

7/10/96

tol0/l0/06

Fourth Quarter

10/8/96

to

~I/14/9

6A4 +8A3

15A3

16A2

17.9 + 0.9

16.2 + 1.0

16.9 + 0.9

14.9 4 0.7

17.4 + 1.3

16.2 + 0.3

17.2 + 1.5

15.7 + 0.9

18.9 + 0.7

17.4 + 0.6

(5)15.6 +0.6

18.8 + 0.5

17.7 + 1.0

17.9 * 1.2

16.2 + 1.1

1-2 MILES OFFSITE

1BI

2B3 +2B4

5B3

7B2

17.0 + 0.6

17.0 + 1.4

16.9 + 1.0

15.9 + 0.6

17.5 + 0.8

17.3 + 1.3

16.8 + 1.2

16.9 + 1.7

15.2 + 0.5

17.2 *0.8

17.8 + 1.1

16.6 + 0.5

21.2 + 1.3

16.7 + 0.8

17.6 + 0.6

18.7 * 1.4

19.1 + 1.5

18.9 + 0.7

16.3 + 0.8

18.4 + 1.1

See the comments at the end ofthis table.

TABLEI-I


SUSQUEI IANNASTFAM ELECTRIC STATION - 1996

Results (1) are in mR/std. qtr, (2) + 2S (3)

Page 4 of7

+c~atlo

8B2 +

8B3

9B1

10B2

IOB3

10B4

12B4

13BI

14B3 +15BI 0

16B2

2D MILES OFFSITE

First QuarterI/16l96

to

~4/ /96

16.3 + 0.7

18.1 + 1.3

16.3 + 1.0

14.3 + 0.6

14.9 A 0.8

18.0 + 0.7

16.9 A 0.5

17.2 + 0.8

16.5 6 1.2

16.3 + 1.1

15.3 + 0.5


to

~/I/96

15.5 + 0.8

16.8 6 0.4

15.5 + 1.1

15.0 A 0.9

13.5 + 0.6

18.0 + 0.8

16.6 + 0.6

16.5 + I.l16.9 + 0.5

16.8 + 1.2

15.3 + 0.8

Third Quarter7/10/96

to

~0/I OI96

16.3 6 0.3

18.8 + 0.8

17.0 + 0.7

13.1 + 0.7

16.2 + 0.8

19.5 + 0.6

16.5 + 0.9

16.8 + 0.8

16.1 + 0.9

16.6 + 1.2

15.3 + 0.5

Fourth Quarter10/8/96

to

JJ/4/97

16.9 + 0.6

18.9 + 0.7

16.8 + 1.4

14.8 + 0.9

16.0 + 0.8

19.2 + 0.5

17.9 + 0.9

18.4 + 1.2

18.6 + 0.6

18.1 + 1.3

16.7 + 0.9

11CI 19.0 + 1.2 19.5 + 1.1 20.0 + 3.2 20.9'+ 1.0


TABLE I-I


Page 5 of7

SUSQUEI IANNASTEAM ELECTRIC STATION - 1996


Qc~atlo

I ILES OFFSIT

First Quarter

I/16/96

to

4/II/96

Second Quarter

4/9/96

to

7/I I/96

Third Quarter

7/IO/96to

IOIIOI96

Fourth Quarter

10/8/96

toI/l4/97

ID5+,'DI

8D3 +

9D4 +

IODI +

12D2

14DI

(7)19.3 + I.O

17.9 4 1.4

18.2 + 1.0

17.6 + 0.7

18.9 + I.I18.7 + 1.0

19.0 + 0.8

18.9 6 1.0

17.8 A 0.4

18.1 + 0.8

16.9 + 0.8

19.7 + 0.9

18.2 + 0.6

21.0 + 0.9

18.8 + O.l

18.8 + 0.7

20.1 +0.817.5 + 1.0

19.5 + I.I18.3 + 0.8

20.5 + 0.8

20.3 + 0.8

18.0 + 0.5

19.8 + 1.2

18.3 * 1.6

21.0 + 1.4

19.7 1.2

4-5 MILES OFFSITE

3EI4E2

5E2 +6EI +7EI +I IEI +

12EI+,'3E4

+

15.6 + 0.7

19.2 6 1.0

18.9 + 0.9

20.5 + 0.7

19.0 + 1.0

15.4 + 1.0

16.5 + 0.9

17.8 + 0.7

15.0 + 0.8

19.1 + 1.1

17.6 + 1.1

19.6 + 0.8

18.3 + 1.2

14.9 + 0.4

16.6 + 0.4

17.8 6 1.7

15.6 + 1.2

19.1 + 1.1

19.5 + 0.7

20.5 + 0.7

19.8 + 0.5

15.1 + 0.3

16.1 6 0.7

16.5 + 0.7

16.8 + 1.6

20.5 6 1.3

19.5 + 0.9

21.0 + 2.2

19.3 + 1.7

16.2 6 0.9

17.5 + 0.8

18.4 + 1.2


TABLE1-1


Page 6 of7

SUSQUEI IANNASTEAM ELECTRIC STATION - 1996

Results (I) are in mRJstd. qtr. (2) + 2S (3)

~a~tlo

0 I ESOFFSI

First Quarter

I/16/96to

~4/ /96

Second Quarter

4/9/96

to

~7/ I/96

Third Quarter

7/10/96

to

JO//0/96

Fourth Quarter

10/8/96

to

J//I4 7

2FI +

8F2

12F2

15F I +

16F I +

17.5 4 1.0

17.4 + 1.7

18.2 + 1.3

19.1 + 0.9

20.2 4 0.7

. 17.3 +0.616.4 + 0.8

17.8 + 0.7

18.9 6 0.6

19.3 *0.9

17.7 + 0.9

18.7 + 0.7

17.4 + 0.9

19.0 + 0.4

19.2 + 1.5

18.2 + I.I17.6 6 1.2

19.7 + 1.1

20.8 + 1.3

21.5 + 1.4

0-20 ILES OFFSITE

3G4

4GI +

6GI7GI +

7G2

8GI

12GI +

12G4

18.3 + 1.0

20.2 % 1.4

21.2 + 1.7

17.9 + 1.4

17.2 + 0.7

(4)15.9 4 0.6

19.0 + 0.9

— 17.1 + 1.1 ~

19.6 + 0.9

20.4 + 0.7

17.2 + 0.9

17.3 4 1.0

15.2 + 1.0

15.7 4 0.7

18.5 + 0.6

19.3 + 0.7

21.5 + 0.9

22.8 6 0.9

18.9 + 0.8

19.4 + 0.6

17.1 + 0.5

15.0 6 0.8

18.3 6 0.9

18.5 + 0.9

21.2 + 1.2

22.4 + 1.2

18.9 + 1.5

18.6 + 1.4

16.6 + 1.5

16.6 + 1.5

20.9 + 1.1


I00

TABLEI-IPage7of7


SUSQUEI IANNASTF~ ELECTRIC STATION - 1996


+catfon

First QuarterI/16/96

to

4/11/96


to

~7/ 1/96

Third Quarter7/IO/96

to/0//0/96

Fourth QuarterIO/8/96

fo1/14/97

IndicatorAverage (6) 17.9 + 0.6 17.7 + 0.7 18.1 + 0.8 '9.1 + 0.8

Control

Average (6) 18.5 + 0.8 17.6 4 0.4 19.0 + 0.3 19.2 + 0.4

COMMENTS

(I) Individual monitor location results are normally the average of the elemental doses ofsix calcium elements fromthe two TLDs assigned to each monitoring location.

(2) A standard (std.) quarter (qtr.) is considered to be 91.25 days. Results obtained for monitoring periodsofother durations are normalized by multiplying them by'91.25/x, where x is the actual duration in days ofthe period.

(3) Uncertainties for individual monitoring location results are two standard deviations of thc elementaldoses ofsix calcium elements Irom the two TLDs assigned to each monitoring location, representingthe variability between the elemental doses ofeach of the six TLD elements.

(4) TLDs were not in the field at this monitoring location during this quarter. Refer to Appendix Aof this report for anexplanation ofprogram changes to the REMP.

(5) No measurement could be made because the TLDs were lost, stolen, or damaged.

(6) Uncertainties associated with quarterly indicator and control averages are two standard deviations,representing the variability between the results of the individual monitoring locations.

(7) Data were invalidated for this period because ofan unacceptably high coefficient ofvariation among element readings.+ ODCM -listed locations.~ NRC co-located monitoring stations.

ILD

TABLE I-2

GROSS ALPHA. GROSS BETh. TRITHJM. AND GAMMA'PECTROSCOPIC ANALYSES OF SURFACE WATER

SUSQUEHANNA STEAM ELECTRIC STATION - 1996

Results In pCI/liter k 28

Page 1 of 7

LOCATION COLLECTION DATE OR-ALPHA OR-BETh TRITIUM OTHER ACTIVITY COMMENTS

ID36S66S66S66S56S76S76S7LTAW12FI12G212H I

ID3SS96S62S76S56876S7LTAW12FI12G212H I

ID36862S76856S7LTAW12FI12G212H I

01/15/96Ol/02/96-01/23/9601/29/9601/29/96-02/05/9601/09/96-02/05/96Ol/02/96-01/23/9601/29/9601/29/96-02/05/9601/15/9601/15/9601/15/9601/02/96.02/05/96

02/12/9602/26/96-03/04/9602/05/96-02/20/9602/05/96-03/04/9602/13/96-03/04/9602/05/96-02/08/9602/05/96-03/04/9602/12/9602/12/9602/12/9602/05/96-03/04/96

03/11/9603/06/96-04/Ol/9603/04/96-04/01/9603/11/96-04/01/9603/28/96-04/01/9603/11/9603/11/9603/11/9603/04/96-04/01/96

<I2.5a 1.3

< 0.70.80 k 0.76

<23.8k 2.4

< I<2<2

2.4 X 1.2

<21.5 R 1.0

< 0.92.7 2 2.21.0 k 0.9

<2

<2<2<2< 0.9

<2< I<2< I<2<2<2<2< I

2.3 X 0.912% 2

2.5 X 0.84.2 i 1.0ll k.233k 39.6 k 1.54.0 X 1.01.9 i 0.9

7.1 X 1.2

2.8 i 0.94.2 X 1.01.8 i 0.99.4 i 1.78.I i 1.39.3 i I.I

4.3 k 1.04.6 1 1.03.8 i 1.04.0 i 1.0

2.7 i 0.92.4 R 0.99.8 X 1.22.4 i 0.99.5 X 1.13.6 R 1.05.1 k 1.13.3 f 0.92.9 % 0.9

130 2 70< 100< 100< 100

640 2 100240 R 90

2000 1 100150 k 70

< 100

«100

< 100< 100< 100

450 k 90< 100( 100

< 100< 100( 100( 100

< 100< 100

970 k 110< 100< 100< 100< 100< 100< 100

I

CO

Gamma cmttters are only reported when acUvlUes exceed the MDC's: typtcal MDC values are found tn Table 1-15.

TABLE 1-2

GROSS ALPHA. OROSS BETh. TRITIUM.AND GAMMA'PECTROSCOPIC ANALYSES OF SURFACE WATER

SUSQUEHANNA STEAM ELECI'RIC Sl'ATION - 1996

Results In pCI/Itter i 2S

Page 2 of 7

LOCATION

ID35S96S66S66S62S76S56S7LTAW12FI12G212H I

ID36S66S66S66862S76SS6876S7LTAW12FI12G212HI

ID36S62876856S7LTAW12FI12G212HI

COLLECTION DATE

04/15/9604/15/9604/01/96-04/08/9604/22/96-04/29/9604/22/9604/01/96-05/06/9604/08/96-05/06/9604/01/96-05/06/9604/15/9604/15/9604/15/9604/01/96-05/06/96

05/13/9605/06/9605/06/96-05/13/9605/20/9605/20/96-06/03/9605/06/96-06/03/9605/13/96-06/03/9605/06/96-05/13/9605/13/96-06/03/9605/13/9605/13/9605/13/9605/06/96-06/03/96

06/10/9606/03/96-07/01/9606/03/96-07/01/9606/10/96-07/01/9606/03/96-07/01/9606/10/9606/10/9606/10/9606/03/96-07/01/96

OR-ALPHA

9.1 R 3.4(2

0.70 i 0.66< 0.7

2.1 E 1.31.9 R 1.2

« I<2( I< I( 0.8

4.9 i 2.51.1 i 0.9

< I< I< I<2

3.1 i 1.82.7 2 1.9

<25.5 a 2.94.2 2 2.4

< I

< 0.9< 0.9<2< 0.9<2

1.1 k 0.91.4 i 1.1

< I1.1 2 0.9

OR-BETh

4.2 i 1.024i 2

< I2.3 i 0.83.6 I 0.9l2i I6.6 i 1.213k I

3.2 i 1.13.0 i 0.94.0 i 1.04.2 i 1.0

17% 22.6 i 0.93.5 i 0.93.6 i 1.01.9 2 0.99.2 i 1.77.4 k 1.313% I

4.4 2 1.122i 2152 2

4.8 i 1.1

2.4 i 0.93.7 i 1.0132 2

2.7 j 1.0132 2

2.9 i 1.02.2 i 1.04.7 i 1.23.6 i 1.0

TRITIUM

< 100< 100( 100< 100< 100

750 % 100< 100

590 2 90< 100< 100< 100< 100

< 100( 100( 100< 100< 100

3400 i 200< 100

500 i 100

< 100< 100< 100< 100

< 100< 100

1000 i 300< 100

860 i 100140 i 80

< 100< 100< 100

OTHER ACTIVITY COMMENTS

8910

121314

15

16

17

Gamma emttters are only reported when acuvtues exceed the MDC's: typtcal MDC values are found tn Table 1-15.

TABLEI-2

GROSS ALPHA GROSS BETh, TImIUM.AND GAMMA'PECTROSCOPIC ANALYSES OF SURFACE WATER

SVSgVEHANNA STEAM ELECTRIC SI'ATION - 1996

Results In pCI/liter i 2S

Page S of 7

LOCATION COLL1KZIONDATE GR-ALPHA OR-BETA TRITIUM OTHER ACTIVITY COMMENTS

ID36S62S76S56S7LTAW12FI12G212H I

07/15/9607/01/96-08/05/9607/01/96-08/02/9607/08/96-08/05/9607/01/96-07/19/9607/15/9607/15/9607/15/9607/01/96-08/05/96

<2< I< I< I<2<2<2<2< I

2.6 i 0.91.7 i 0.8Il i I

2.4 i 0.9.Il i 23.5 i 1.02.8 i 0.92.9 i 0.94.2 i 1.0

110 i610 i510 i250 i120 i150 i

701009010090807070100

K-40 107 i 3218

19

ID36S62872S76856S7LTAW12FI12G212HI

1D36866S62S76S5687LTAW12FI12G212H I

08/12/9608/05/96-09/03/9608/05/9608/05/96-09/03/9608/12/96-09/03/9608/05/96-09/03/9608/12/9608/12/9608/12/9608/05/96-09/03/96

09/09/9609/09/96-09/16/9609/16/96-10/04/9609/03/96-10/07/9609/09/96-10/07/9609/03/96-10/04/9609/09/9609/09/9609/09/9609/03/96-10/07/96

< I<2

2.1 i<I< I< I

1.4

I<2< I<I<2

< I< I<2<2

1.4 i 1.3<2< 0.9

1.4 i 0.82.1 i 0.98.7 i 1.7II i 2

3.3 i 1.0

2.8 i 0.92.8 i 0.93.1 i 1.03.8 i 1.0

3.0 i 1.14.0 i 1.13.0 i 1.0

5.0 i 1.29.8 i 1.74.9 i 1.22.9 i 1.14.2 i 1.23.7 i 1.1

< 100< 100< 100< 100

< 100< 100< 100

3300 i180 i120 i

1002008010070100

< 100< 100

14000 i 10001600 i 100

< 100

20

21

222324

25

I

Gamma emitters are only reported eben acttviues exceed the MDC's: typical MDC values are found in Table 1-15.

TABLE I-2

OROSS ALPHA, CROSS BETh. TRITIUM.AND OAMMA'PECTROSCOPIC ANALYSES OF SURFACE WATER

SUSQUEHANNA SR&M ELECl'RIC STATlON - 1996

Results tn pCI/Itter 2 2S

Page4of7

LOCATION COLLECTION DATE OR-ALPHA OR-BETA TRITIUM OTHER ACTIVITY COMMENTS

ID36S66SS2S72S7SS9

12H I6S56S76S7LTAW12FI12G2

ID36S62S76S56S7687LTAW12FI12G212H I

ID36S6287

. 6S5687LTAW12FI12G212H I

10/15/9610/10/96-11/04/9610/07/9610/07/96-10/14/9610/21/96-11/04/9610/07/96

10/07/96-11/04/9610/14/96-11/04/9610/14/96-10/21/9610/24/96-11/04/9610/15/9610/15/9610/15/96

11/11/96I I /04/96-12/02/96II/04/96-12/02/9611/12/96-12/03/96I I /04/96-1 I /07/9611/07/96-12/02/9611/11/9611/11/9611/11/9611/04/96-12/02/96

12/16/9612/02/96-01/06/9712/02/96-01/06/9712/09/96-01/06/9712/02/96-01/06/9712/16/9612/16/9612/16/9612/02/96-01/06/97

< I<2« 0.9< 0.09< I< 0.9

<2«2< 3< I< I< I< I

<2< I

1.0 i 0.62.1 R 0.61.2 k 0.8

< I< I( 0.8< I

( 0.6< I<2< I< I< 0.9( 0.6< 0.7< I

3.5 x 1.02.9 i 0.92.5 X 1.0I61 2

9.9 i 0.93.2 j 1.0

4.0 i 1.04.9 i 1.111 i 211 i I

4.9 k I.l2.6 k 1.0

4.23 i 1.1

4.0 d: 0.93.1 X 0.99.3 R 1.58.3 R 1.3IOE I

4.6 X 1.13.2 R 0.93.5 i 0.94.3 2 1.0

I.8% 0.82.4 R 0.714% 2

3.0% 0.813% 21.5 i 0.91.3 R 0.83.5 i 0.92.9 d: 0.8

< 100< 100< 100

150 d: 804200 d: 200

< 100

< 100'< 10018000 2 1000

170 d: 80160 i 70

< 100< 100

( 100< 100

730 k 110< 100< 100

< 100< 100< 100( 100

< 100< 100

710 k 110150 d: 80630 d: 110

< 100< 100< 100< 100

2625272823

2929

313030

32

I

Gamma emttters are only reported when acttvtttes exceed the MDC's: typtcat MDC values are found tn Table 1-15.

TABLE I-Q

GROSS ALPHh GROSS BETh. TRITIUM.AND GAMMA SPECTROSCOPIC ANALYSES OF SURFACE WATER

SUSQUEIIANNA SHAWM ELECI'RIC SIATION - 1996

Page 5 of7

I.2.

3.

4.

10.

12.

13.

14.

Sampling could not be performed at locations I D3 and 12G2 on I/15/96 because the Susquehanna River was frozen.No water was flowing through the ACS at location 6S6 on I/29/96. Insufhcient water was in the sample collection container for analysis.A grab sample was collected on I/29/96 to represent mek 4 (I/23 - I/29/96) ofthe monthly compositing period.Grab samples were not collected from 6S5 on I/15/96 and I/23/96. Grab samples were collected from shore on I/9/96 and 2/5/96.No water was flowing through thc ACS at location 6S7 on I/29/96. InsuScient water was found in the sample collection container foranalysis. A grab sample was collected.No water was flowing through the ACS at 6S6 on 2/20/96. Grab samples were collected at location 5S9 on 2/26/96 and 3/4/96 to representweeks 3 and 4 (2/20 - 3/4/96) ofthe monthly compositing period. These grab samples were composited and sent for analysis. Flow wasrestored to thc ACS on 3/6/96.TheACS at location 6S7 was found tobesampling veryirrcgularlyon2/8/96. Flowcouldnotbecontrolledwith valvingchanges. Pumppressure was extremely variable and air was observed in the sample linc. The sample collection container and overflow jug were almostoverflowing. Flow to thc ACS was stopped to prcvcnt overflow.The ACS at location 6S7 was inoperable due to a malfunctioning timer from 3/4 - 3/28/96 ofthe monthly composi ting period. The ACStimer was repaired on 3/28/96.No water was flowing through the ACS at location 6S6 on 4/15/96. A grab sample was collected at location 5S9 in lieu ofobtaining asample from location 6S6 for week 2 (4/8 - 4/15/96) of the monthly compositing period. Debris was removed from the sampling line andflow was restored on 4/15/96.No flow was observed through the ACS at location 6S6 on 4/17/96. Debris was removed. The sample collection container at location 6S6

'asfound to be overflowing on 4/22/96. A grab sample was collected on 4/22/96 to represent week 3 (4/15 - 22/96), ofthe monthlycompositing period. Valves were readjusted.Apparent interruptions in electrical power supplying the sampler at location 2S7 occurred on 4/30/96. Each of these interruptions lasted lessthan one minute.The sample collection container at location 6S6 was found to be overflowing on 5/6/96. A grab sample was collected on 5/6/96 to representweek 5 (4/29 - 5/6/96) of the monthly compositing period.The ACS at location 6S6 was observed to be collecting only 5 ml aliquots on 5/20/96. Insuflicient water was in the sample collectioncontainer for analysis. A grab sample was collcctcd on 5/20/96 to rcprescnt week 2 (5/13 - 20/96) of the monthly compositing period.The ACS at location 6S6 was turned offfrom 2200 on 5/23/96 to 0950 on 5/24/96 to permit maintenance to be performed.No liquid was detected in the sampling line at location 2S7 at 0634 on 5/29/96.

TABIDI-Q

GROSS hLPIIh. GROSS BETh. TIOTlUM.AND GUUHbGV SPECTROSCOPIC hNALYSES OF SURFACE WATER

SUSQUEttANNA STEAM ELECTRlC STAllON - 1996

Page 6 of7

15.

16.

17.

18.

19.

20.

21.

22.

23.

24.25.

Erratic, pulsating sample flowwas obscrvcd at location 6S7 for weeks 2, 3, and 4 (5/13 - 6/3/96) ofthe monthly compositing period. Airand silt were seen in the sampling line, apparently contributing to the erratic flow. No grab samples were collected because ofthe samplingofthe CTBD being simultaneously performed at location 2S7. Maintenance was performed and the ACS was returned to service on 6/3/96.Sampling at location 2S7 was flow proportional for thc monthly compositing period (6Q - 7/1/96). No liquid was detected in the samplingline at 0307, 0536, and 0547 on 6/4/96 and again at 1420 on 6/26/96. A crack in the pump tubing was found on 6/6/96 and the tubing wasreplaced.

The pump supplying water to the ACS at location 6S7 was turned oF briefly on 6/24/96 for preventative maintenance.Sampling at location 2S7 was flow proportional for the compositing period from 7/1/96 through 8/2/96. No liquid was detected in thesampling line for the ACS at location 2S7 at 1652 on 7/3/96, at 0709 on 7/14/96, and at 1828 on 7/21/96. Power was shut offto the ACSfrom 1414 to 1422 on 7/29/96 while a new lighting fixture was installed.The pressure from thc pump supplying water to the ACS at location 6S7 was observed to be zero at 1130 on 7/19/96. A composite samplerepresenting weeks 1 and 2 and part ofwcck 3 for the normal monthly compositing period (7/1 - 8/5/96) was sent for analysis. No waterwas collected for weeks 4 and 5 of the monthly compositing period ending 8/5/96. No grab sample was collected because sampling is beingperformed simultaneously at CTBD sampling location 2S7.At 1033 on 8/2/96, a technician leA the ACS at location 2S7 in "standby" followingcollection ofan NPDES sample. No water wascollected from 8/2/96 until 8/5/96. A grab sample was collected on 8/5/97.The ACS at location 6S7 was not functioning regularly throughout the monthly compositing period (8/5 - 9/3/96). No grab samples werecollected. Representative sampling of the CTBD was occurring at location 2S7.The collection container for the ACS at location 6S6 was found overflowing on 9/9/96 and 9/16/96( the ends ofweeks 1 and 2 ofthe normalmonthly compositing period (9/3 - 10/7/96). Water seemed to be leaking into the collection container between the timed aliquot collections.Grab samples were collected on 9/9/96 and 9/16/96 and composited.Flow to the ACS at location 6S6 was interrupted on 10/4/96 by the river water makeup linc replacement project. A grab sample wascollected from the alternate location 5S9 on 10/7/96.The ACS at location 2S7 was inoperative and being repaired during thc entire monthly compositing period from 9Q/96 through 10/7/96.No water was flowing to the ACS at location 6S7 from 10/4/96 to 10/7/96 because of the river water makeup line replacement project. Agrab sample was collected from the sampling location 6S5 on 10/7/96.

TABLE I-2

GROSS ALPHA, GROSS BETA. TRITIUM.AND GAMMA'PECTROSCOPIC ANALYSES OF SURFACE WATER

SUSQUEIIANNA SIAM ELECfRIC STATION - 1996

Page 7 of 7

26. No water was fiowing to thc ACS at location 6S6 from 10/7/96 to 10/10/96, the first part ofweek l ofthe normal monthly compositing~ period (10/7/96 - I I/4/96), duc to the river water makeup line replacement project.

27. The loss ofpower to the ACS at location 2S7 occurred on 10/8/96 from 0322 to 0326 and again from 0329 to 0330. The sample fromlocation 2S7 was used to represent the CTBD from 10/7/96 to 10/14/96 because water was not being collected at location 6S7 for thisperiod.

28. InsuAicicnt sample volume for analysis was collected at location 2S7 for the period 10/14/96 through 10/21/96 (week 2) ofthe normalmonthly compositing period (10/7 - I I/4/96), because thc ACS's pump jammed. Maintenance was performed on the pump and it wasrestarted on 10/21/96.

29. No water was flowing to the ACS at location 6S7 from 10/7/96 to 10/10/96 (week I) of the monthly compositing period, because of theriver water makeup line rcplaccment project. (Sampling of thc CTBD was being performed during the period 10/7/96 through 10/14/96 atlocation 2S7.) No flow to thc ACS occurred from 10/21/96 to 10/24/96 due to low pump pressure.

30. No water was flowing to thc ACS at location 6S7 on 11/7/96. Pump pressure was inadequate(4-5 psig). The PCS was not able to providea representative sample for thc period 11/I I/96 through 12/2/96, weeks 2 through 4 ofthe monthly compositing period. No grab sampleswere collected at location 6S7 during this period because the CTBD was being sampled successfully from location 2S7.

31. The grab sample for location 6S5 on 12/2/96 was collected from shore.32. The grab samples for locations 6S5 on 12/16/96 and 12/23/96 were collected from shore.

TABLE I-3

IODINE-131 ANALYSES OF SURFACE WATER

SVSQVEHANNA STEAM ELECI'RIC Sl'ATION - 1996

Results In pCI/liter 2 2S

Page 1 of 9

LOCATION

1D36S66S66SS6S76S7LTAW12F112G212H 1

1D36S66S62S76S56S56S76S7LTAW12F112G212H112H1

COLLECTION DATE

01/15/9601/09/96-01/23/9601/29/9601/09/96-01/23/9601/09/96-01/23/9601/29/9601/15/9601/15/9601/15/9601/09/96.01/23/96

02/12/9601/29/96-02/05/9602/05/96.02/20/9602/05/96-02/20/9601/30/96.02/05/9602/13/96-02/20/9601/29/96-02/05/9602/05/96-02/08/9602/12/9602/12/9602/12/9601/23/96-02/05/9602/05/96-02/20/96

I-131

< 0.2< 0.2

0.67 R 0. 17< 0.2< 0.08

0.17 k 0.06

< 0.2

< 0.1< 0.1< 0.2

0.32 k 0.13< 0.1< 0.1< 0.2< 0.2< 0.1< 0.1< 0.09< 0.2< 0.2

COMMENTS

TABLEMIODINE-1$I ANALYSESOP SVRPhCE WATER

SUSQUEHANNA SPERM ELECTRIC STATION - 1996

Results tn pCI/liter 2 2S

Page2of9

LOCATION

1D3SS96S66S66S62S72S72576556SS6S56S76S7

COLIZCTIONDATE

03/11/9602/26/96-03/04/9602/20/96-03/04/9603/06/96-03/18/9603/18/96-04/01/9602/20/96-03/04/9603/04/96-03/18/9603/18/96-04/01/9602/27/96-03/04/9603/11/96-03/18/9603/26/96-04/01/9602/20/96-03/04/9603/04/96-03/18/96

1-1$ 1

< 0.1< 0.2

0.39 k 0.14< 0.2

~< 0.20.78 2 0.19

< 0.2< 0.1< 0.2< 0.2

COMMENTS

I

OO

6S7LTAW12F112G212H112HI12HI

1D3SS96S66S66862S72876S56S56S76S7LTAW12F112G212H112H1

03/28/96-04/01/9603/11/9603/11/9603/11/9602/20/96-03/04/9603/04/96-03/18/9603/18/96-04/01/96

04/15/9604/15/9604/Ol/96-04/08/9604/22/9604/22/96-04/29/9604/01/96-04/15/9604/15/96-04/29/9604/08/96-04/15/9604/22/96-04/29/9604/01/96-04/15/9604/15/96-04/29/9604/15/9604/15/9604/15/9604/01/96-04/15/9604/15/96-04/29/96

0.18 2 0.09< 0.1

0.19 2 0.06< 0.2< 0.2< 0.2

< 0.1< O.l< 0.2< 0.2< 0.2< 0.2< 0.2< 0.1< 0.2< 0.2< 0.2< O.l< O.l< 0.1< 0.2< 0.2

10

121213

TABLEINIODINE 131 ANALYSES OF SURFACE WATER

SUSQUEHANNA SIEAM ELECI RIG STATION - 1996

Results tn pCI/liter k 2S

Page 8 of9

LOCATION

ID36S66S66S66S62S72S72S76SS6SS6S76S7

LTAW12FI12G212HI12HI

ID36S66S66S62S72S72S76S56SS6S76S7687LTAW12FI12G212HI12HI12HI

COLLECTION DATE

05/13/9605/06/9605/06/96-05/13/9605/20/9605/20/96.05/28/9604/29/96.05/13/9605/13/96-05/28/9605/28/96.06/03/9605/06/96-05/13/9605/20/96-05/28/9604/29/96-05/13/9605/20/96-05/28/96

05/13/9605/13/9605/13/9604/29/96-05/13/9605/13/96-05/28/96

06/10/9605/28/96-06/10/9606/10/96-06/24/9606/24/96-07/08/9606/03/96-06/10/9606/10/96-06/24/9606/24/96-07/08/9606/03/96-06/10/9606/17/96-06/24/9606/03/96-06/10/9606/10/96-06/24/9606/24/96-07/08/9606/10/9606/10/9606/10/9605/28/96-06/10/9606/10/96-06/24/9606/24/96-07/08/96

I-131

< 0.09< 0.2< 0.2< 0.2< 0.2< 0.2< 0.2< 0.2« 0.1< 0.4< 0.2

< 0.1< 0.09< 0.1< 0.2< 0.2

0.30 2 0.08< 0.2< 0.2< 0.2

0.87 R 0.110.51 k 0.190.53 k 0.16

0.2 f 0.1< 0.2

0.69 k 0.090.63 2 0.160.20 k 0.10

< 0.10.24 2 0.070.24 2 0.08

< 0.2< 0.2< 0.2

COMMENTS

1414151617

18

19

20

21

22

23

TABLEMIODINE-131 ANALYSESOF SURFhCE WhTER

SUSQUEHANNA STFAM ELECTRIC STATION - 1996

Results In pCI/Itter f 2S

Page 4 of9

IDCATION

ID36S66S62S72S76S56856S56S76S7LTAW12FI12G212HI12HI

ID36S66862S72S72S76S56S56S76S7LTAW12F112G212HI12HI

COLLECTION DhTE

07/15/9607/08/96.07/22/9607/22/96-08/05/9607/08/96-07/22/9607/22/96-08/05/9607/01/96-07/08/9607/15/96-07/22/9607/29/96-08/05/9607/08/96-07/19/9607/22/96-08/05/9607/15/9607/15/9607/15/9607/08/96.07/22/9607/22/96-08/05/96

08/12/9608/05/96-08/19/9608/19/96-09/03/9608/05/9608/05/96-08/19/9608/19/96-09/03/9608/12/96-08/19/9608/26/96-09/03/9608/05/96-08/19/9608/19/96-09/03/9608/12/9608/12/9608/12/9608/05/96-08/19/9608/19/96-09/03/96

1-131

< 0.09< O.l< 0.1

0.19 k 0.080.19 k 0.080.22 4 0.11

< 0.1« O.l< 0.1

< 0.1< 0.09< 0.1< O.l< 0.1

< 0.070.64 2 0.15

< O.l< 0.1

1.9 2 0.20.30 2 0.150;18 2 0.10

< 0.1

< 0.070.092 k 0.043

0.23 4 0.060.43 R 0.14

< 0.1

COMMENTS

2425

2627

25

2828

TABIDINIODINE-131 ANALYSES OF 8URFACE WATER

SUSQUEHANNA STEAM ELECTRIC STAllON - 1996


Page 5 of9

LOCATION

ID36S66S66S66S62S72876SS6SS6S76S7LTAN12FI12G212H112H1

1D35S96S66S62872876S56S56S56S76S7LTAW12F112G212H112HI

COILECTION DATE

09/09/9609/03/96-09/16/9609/09/96.09/16/9609/16/96-09/30/9609/30/96-10/04/9609/03/96-09/16/9609/23/96-09/30/9609/09/96-09/16/9609/23/96-09/30/9609/03/96-09/16/9609/16/96-09/30/9609/09/9609/09/9609/09/9609/03/96-09/16/9609/16/96-09/30/96

10/15/9610/07/9610/10/96-10/14/9610/14/96-10/28/9610/07/96-10/14/9610/21/96-10/28/9610/07/9610/07/96-10/14/9610/21/96-10/28/9609/30/96-10/04/9610/14/96-10/21/9610/15/9610/15/9610/15/9609/30/96-10/14/9610/14/96-10/28/96

I-13I

1.8 i 0.2

0.43 f 0.10< 0.1< 0.2

0.84 k0.14'.16

2 0.100.41 R 0.130.33 k 0.13.

< 0.081.1 a 0.1

0.15 k 0.05< 0.1< 0.09

< 0.1< 0.4< 0.1< 0.1

0.60 2 0.13< 0.1

0.33 k 0.13< 0.1< 0.1< 0.3

0.50 2 0.20< 0.09< 0.1< 0.1< 0.1< 0.1

COMMENTS

29

313030

3131

. 323533

3334

TABLEINIODINE-ISI ANALYSESOF SURFACE WATER


Results tn pCI/ltter i 2S

Page 6 of9

LOCATION

ID36S66S62S76S56S56S76S7LTAW12FI12G212HI12HI

ID36866866S62872S72S76S56S56856S76876S7LTAW12FI12G212HI12HI12H I

COARCT ION DATE

11/11/9610/28/96-1 I/ I I /96I I / I I /96-1 I /25/9610/28/96-1 I/ I I /9611/04/96-1 I /12/96I I /19/96-1 I /25/9610/28/96-1 I /07/96I I / I I /96-1 I /25/96I I /I I/9611/11/9611/11/9610/28/.96-1 I/ I I /96I I / I I /96-1 I /25/96

12/16/96I I /25/96-12/09/9612/09/96-12/23/9612/23/96-01/06/9711/25/96-12/09/9612/09/96-12/23/9612/23/96-01/06/9712/03/96-12/09/9612/16/96-12/23/9612/23/96-01/06/9712/02/96-12/09/9612/09/96-12/23/9612/23/96-01/06/9712/16/9612/16/9612/16/96I I /25/96-12/09/9612/09/96-12/23/9612/23/96-0 I /06/97

1-131

< 0.1< O.l< 0.1< 0.1< 0.1< 0.1< 0.1

< 0.08< 0.07< 0.06< O.l< O.l

< 0.09< 0.1< 0.1< 0.1< 0.5< 0.1< 0.1< 0.1< O.l< 0.1< O.l< 0.1< O.l< 0.09< 0.07< 0.07< 0.2< 0.1< O.l

COMMENTS

3637

3940

38

TABIRINIODIm-1S1 ANALYSES OF SURFhCE WhTER

SUSQUEHANNA STEAM ELECTRIC STATION - l996

Page 7 of9

I.2.

3.4

5.

6.

9.10.

11.

12.

13

'4.

Sampling could not be performed at locations I D3 and 12G2 on I/15/96 because the Susquehanna River was frozen.No water was flowing through the ACS at location 6S6 on I/29/96. Insufficient water was in the sample collection container for analysis.A grab sample was collected on I/29/96 to represent week 2 (I/23 - I/29/96) of the biweekly compositing period.Grab samples were not collected from 6S5 on I/15/96 and I/23/96 due to hazardous conditionsNo water was fiowing through the ACS at location 6S7 on I/29/96. Insufficient water was found in the sample collection container foranalysis. A grab sample was collected.A grab sample was collected from shore on 2/5/96.The ACS at location 6S7 was found to be sampling very irregularly on 2/8/96. Flow could not be controlled with valving changes. Pumppressure was extremely variable'and air was observed in the sample line. The sample collection container and overflow jug were almostoverflowing. Flow to the ACS was stopped to prevent overflow.No water was fiowing through the ACS at 6S6 aAer 2/20/96. Grab samples were collected at location 5S9 on 2/26/96 and 3/4/96 torepresent weeks I and 2 (2/20 - 3/4/96) of the biweekly compositing period. These grab samples were composited and sent for analysis.Flow was restored to the ACS on 3/6/96.The ACS's timer at location 6S7 was found to be malfunctioning on 2/12/97. No grabs samples were collected at this location for theperiod that the timer was malfunctioning because the CTBD was being successfully sampled from location 2S7.The ACS at location 6S7 was inoperable due to a malfunctioning timer from 3/4 - 3/18/96 of the biweekly compositing period.The timer for the ACS at location 6S7 was repaired on 3/28/96.The sample from location 12F I for 3/11/96 was lost during shipment to Teledyne for analysis.No water was flowing through the ACS at location 6S6 on 4/15/96. A grab sample was collected at location 5S9 in lieu ofobtaining asample from location 6S6 for week 2 (4/8 - 4/15/96) of the biweekly compositing period. Debris was removed from the sampling line and

flowwas restored on 4/15/96.No fiow was observed through the ACS at location 6S6 on 4/17/96. Debris was removed. The sample collection container at location 6S6was found to be overflowing on 4/22/96. A grab sample was collected on 4/22/96 to represent week 3 (4/15 - 22/96) ofthe monthlycompositing period. Valves were readjusted.The sample collection container at location 6S6 was found to be overflowing on 5/6/96. A grab sample was collected on 5/6/96 to representweek I (4/29 - 5/6/96) of the biweekly compositing period (4/29/96 - 5/13/96).

M

TABLE INlODOfE-ISl ANALYSESOF SVRFhCE %hTER

SUSQUFttANNA SADISM EI.FCl'RIC Sl'ATION - 1996

Page S of9

15.

16.

17.

18.

19.

20.

21.22.18.

23.

24.25.

26.

27.28.

Thc ACS at location 6S6 was observed to be collecting only 5 ml aliquots on 5/20/96. InsuKcient water was in the sample collectioncontainer for analysis. A grab sample was collected on 5/20/96 to represent week 1 (5/13 - 20/96) ofthe biweekly compositing period (5/13- 28/96).Thc ACS at location 6S6 was turned offfrom 2200 on 5/23/96 to 0950 on 5/24/96 to permit maintenance to be performed.Apparent interruptions in electrical power supplying the sampler at location 2S7 occurred on 4/30/96. Each of these interruptions lasted lessthan one minute.No liquid was detected in the sampling linc at location 2S7 at 0634 on 5/29/96.Erratic, pulsating sample flow was observed at location 6S7 for week 1 (5/13 - 20/96) of the biweddy compositing period. Airand silt werescen in thc sampling line, apparently contributing.to the erratic flow. No grab samples were collected because of the sampling ofthe CTBDbeing simultaneously pcrformcd at location 2S7.Sampling was changed from thc time to the fiow proportional mode at location 2S7 on 6/3/96. No liquid was detected in the sampling line at0307, 0536, and 0547 on 6/4/96. A crack in the pump tubing was found on 6/6/96 and the tubing was replaced.No liquid was dctectcd in the sampling linc for the ACS at location 2S7 at 1420 on 6/26/96 and at 1652 on 7/3/96.Maintenance was performed on the ACS at location 6S7 to correct thc problems with erratic flow and it was returned to service on 6/3/96.Sampling at location 2S7 was flowproportional for the corn positing period from 7/1/96 through 8/2/96. No liquid was detected in thesampling line for the ACS at location 2S7 at 1652 on 7/3/96, at 0709 on 7/14/96, and at 1828 on 7/21/96.The pump supplying water to thc ACS at location 6S7 was turned offbriefly on 6/24/96 for preventative maintenance.No liquid was detected in the sampling line for the ACS at location 2S7 at 0709 on 7/14/96 and at 1828 on 7/21/96.Power was shut offto the ACS at location 2S7 from 1414 to 1422 on 7/29/96 while a new lighting fixture was installed. Insufficient samplevolume was collected from 7/22/96 to 8/2/96. At 1033 on 8/2/96, a technician left the ACS in "standby" followingcollection ofan NPDESsample. No water was collected from 8/2/96 until 8/5/96. A grab sample was collectedon 8/5/97.The pressure from the pump supplying water to the ACS at location 6S7 was observed to be zero at 1130 on 7/19/96. A composite samplerepresenting week 1 and part ofweek 2 for the normal biweekly compositing period (7/8 - 22/96) was sent for analysis. 'No grab samplewas collected because sampling is being performed simultaneously at CTBD sampling location 2S7.No water was collected for the entire biweekly compositing period (7/22/96 - 8/5/96).The ACS at location 6S7 was not functioning regularly throughout the monthly compositing period (8/5 - 9/3/96). No grab samples werecollected. Representative sampling ofthe CTBD was occurring at location 2S7.

TABLEINIODINE-IS I ANALYSES OF SURFhCE liVhTKR

SUSQUEIIANNA Sl1MM ELECMC STATION - l996

Page 9 of9

~Inning

29.

30.

31.

32.

33.

34.

35.

36.37

39.40.

The collection container for the ACS at location 6S6 was found overflowing on 9/9/96 and 9/16/96( the ends ofweeks 1 and 2 ofthebiweekly compositing period (9/3 - 16/96). Water seemed to be leaking into the collection container between the timed aliquot collections.Grab samples were collcctcd on 9/9/96 and 9/16/96 and composited.Thc ACS at location 2S7 was inoperative and being repaired during the entire biweekly compositing periods from 9/3/96 through 9/16/96and 9/16/96 through 9/30/96.Flow to thc ACS at location 6S6 was interrupted on 10/4/96 by the river water makeup line replacement project. No water was fiowing tothc ACS at location 6S6 for the period 10/4/96 through 10/10I96 due to maintenance on the river water makeup line. A grab sample wmcollected from the alternate location 5S9 on 10M/96.The loss ofpower to thc ACS at location 2S7 occurred on 10/8/96 from 0322 to 0326 and again from 0329 to 0330. The sample fromlocation 2S7 was used to represent thc CTBD from 10/7/96 to 10/14/96 because water was not being collected at location 6S7 for thisperiod.No water was flowing to thc ACS at location 6S7 from 10/4/96 to 10/10/96 because ofthe river water makeup line replacement project. Agrab sample was collected from 6S5, the altematc sampling location for 6S7 on 10M/96. Sampling ofthe CTBD was being performedduring the period 10/7/96 through 10/14/96 at location 2S7.No flow to the ACS at location 6S7 occurred from 10/21/96 to 10/24/96 due to low pump pressure. The CTBD was being sampled fromlocation 2S7 during the period 10/21/96 through 10/28/96, the second week of the scheduled biweekly compositing period.Insufhcient sample volume for analysis was collected at location 2S7 for the period 10/14/96 through 10/21/96 (week 1) ofthe normalbiweekly compositing period (10/14 - 28/96), because the ACS's pump jammed. Maintenance was performed on the pump and it wasrestarted on 10/21/96.No water was flowing to the ACS at location 6S7 on 11/7/96. Pump pressure was inadequate(4-5 psig).The ACS at location 6S7 was not able to provide a representative sample for the bi~wklycompositing period 11/11/96 through 11/25/96.No grab samples were collected at location 6S7 during this period because thc CTBD was being sampled successfully from location 2S7.The ACS at location 6S7 was not able to provide a representative sample for week 1 (1 1/25/96 - 12/2/96) ofthc biweekly compositingperiod 1 l/25/96 through 12/9/96. No grab samples were collected at location 6S7 during this period bccausc thc CTBD was being sampledsuccessfully from location 2S7.The grab sample for location 6S5 on 12/3/96 was collected from shore because the river lcvcl @as very high.The grab samples for locations 6S5 on 12/16/96 and 12/23/96 were collected from shore.

TABLE I-4

GROSS hLPHA,'ROSS BETh. TImIUM.IODINE-ISI AND GAMMA'PECTROSCOPIC ANALYSES OF DRINKINQWATER

SUSQUEHANNA STEAM ELECI'RIC SI'ATION - 1996


Page 1 of 2

IOCATION COLLECTION DATE OR-ALPHA OR-BETh TRITIUM OTHER ACTIVHT COMMENTS

12H2 T

12H2 T

12H2 T

12H2 T

12H2 T

12H2 T

12H2 T

12H2 T

12H2 T

12H2 T

12H2 T

12H2 T

12H2 T

12H2 T

12H2 T

12H2 T

12H2 T

01/02/96-02/05/96

02/05/96.03/04/96

03/04/96-04/0 l /96

04/01/96-05/06/96

05/06/96-06/03/96

06/03/96.06/ I 0/96

06/17/96 (G)

06/17/96-07/01/96

07/01/96-08/05/96

08/05/96-09/03/96

09/09/96 (G)

09/09/96-09/16/96

09/23/96 (G)

09/23/96-10/07/96

10/07/96-11/04/96

11/04/96-12/02/96

12/02/96-01/06/97

< 0.9

< 0.9

( 0.8

< 0.9

<2

<2

<2<2

< 0.9

<2

2.0 X 0.8

1.6 i 0.9

2.6 X 0.9

1.7 X 0.8

1.8 X 0.8

1.8 R 0.9

2.5 i 0.9

2.5 2 0.9

2.5 i 0.9

3.0 a 1.0

2.9 k 1.1

3.1 R 1.0

3.5 R 1.0

2.8i 1.0

3.6 R 1.0

2.2 2 0.8

2.7 i 0.8

< 100

< 100

< 100

< 100

< 100

< 100

« 100

< 100

< 100

< 100

< 100

< 100

< 100

< 100

< 100

< 100

150 k 70

Grab sample+Gamma emttters are only reported rvhen acttvtttes exceed the MDC's: typtcal MDC values are found tn Table 1-15.

ThBLE 1-4

GROSS hLPHh, GROSS BETh, TRITIUM,IODINE-131 hND GhMMh'PECTROSCOPIC hNhLYSES OF DRINKINGWhTER

SUSQUEltANNA SHAWM ELECTRIC STATlON - 1996

Page 2 of2

omfllen

The sample collection container was overflowing on 6/17/96. Water was flowing into the container between aliquot collections because thesampling arm could not return to its non~pling position. A cotter pin was replaced in the ACS, eliminating the problem, and the samplerwas returned to scMce. A grab sample was collected to represent week 2 ofthe scheduled monthly compositing period (6/3 - 7/1/96) andveek 1 of the scheduled biweekly compositing period (6/10 - 24/96).Thc sample collection container was overflowing on 9/9/96. Water was flowing into the container between aliquot collections because thesampling arm could not return to the non~pling position. A cotter pin was replaced in the ACS, eliminating the problem, and the samplerwas returned to service. A grab sample was collected to represent week 1 ofthe scheduled monthly compositing period (9/3 - 10M/96) andweek 1 ofthe scheduled biweekly compositing period (9/3 - 9/16/96).The sample collection container was overflowing on 9/23/96. Water was flowing into the container between aliquot collections because the

sampling tubing was ruptured. A grab sample was collected to represent week 3 of the scheduled monthly compositing period (93 - 10M/96)and week 1 ofthe scheduled biweekly cornpositing period (9/16 - 30/96).

TABlZI-5

GROSS. BETAAND GAMMA'PECTROSCOPIC ANALYSES OF FISH


Results In pCI/gm (wet) f 2S

LOCATION SAMPLE TYPE COLD~ON DATE GR-BETA KRO

2H Smallmouth Bass2H While Sucker2H Channel Catfish

IND Smallmouth BassIND White SuckerI ND Channel CatAsh

2H Redhorse2H Smallmouth Bass2H Channel CatAsh

IN D RedhorseIND Smallmouth BassIND Channel Catlbh

LTAW Largemouth Bass

06/20/9606/20/96

06/20/96-06/21/96

06/13/9606/13/96

06/11/96-06/12/96

10/17/9610/I?/96

10/17/96-10/18/96

10/16/9610/15/96-10/16/9610/15/96-10/16/96

10/15/96

3.7 2 0.14.4 k 0.18.7 R 0.2

3.3 k O.l2.1 k 0.17.5 i 0.3

6.0 i 0.26.1 k 0.15.8 % 0.2

5.9 i 0.26.1 R 0.210% I

6.3 i 0.2

3.51 k 0.354.15 k 0.413.35 k 0.33

4.16 % 0.423.76 2'.383.49 k 0.35

3.53 R 0.352.93 i 0.293.37 i 0.34

2.90 X 0.293.51 % 0.353.10 k 0.31

3.562 0.36

Ganuna ernttters are ordy reported when acttvtttes erceed the MDC's: typtcal MDC values are found tn Table 1-15.

TABLEIAGAMMA'PECTROSCOPIC ANALYSES OF SHORELINE AND FLOCCUIATED SEDIMENT

SUSgUEHANNA STEMR ELECTRIC STATION - 1996

Results ln pCI/gm (dry) 2 2S

Psgelofl

LOCATION COLU~ON DATE

66/04/9606/04/96

K-40

7.65 2 0.777.16% 0.73

Ca-IS7 Ra-226 Th-228

0.63 k 0.060.59 k 0.07

2B2F7BI IC12FLTAW

2B2F7BI IC12F

-LTAW

06/04/9606/04/9606/04/9606/04/9606/04/9606/04/96

11/07/9611/07/96

11/07/9611/06/9611/07/9611/06/9611/06/9611/06/96

13.92 149.55 X 0.968.54 ~ 0.858.58 i 0.869.62 X 0.9613.6 i 1.4

14.0 i 1.419.5 R 1.9

14.9 R 1.510.5 k 1.014.1 t 1.410.5 i I.I16.2 k 1.610.4 2 1.0

0.12 t 0.030.07 X 0.030.06 k 0.030.08 2 0.020.09 k 0.03

0.16 k 0.07

0.07 k 0.030.12 2 0.030.12 2 0.030.11 t 0.040.12 k 0.04

2.02 E 0.531.70 k 0.541.18 k 0.541.53 t 0.451.84 2 0.511.47 R 0.68

1.39 R 0.78

2.10 k 0.571.64 2 0.61.56 2 0.461.92 2 0.502.05 R 0.772.12 t 0.7

1.16 k 0.120.85 R 0.090.75 2 0.080.85 t 0.090.81 k 0.081.00 t 0.10

0.98 R 0.011.09 2 0.1 I

1.43 k 0.141.24 2 0.121.25 k 0.130.96 k 0.101.26 k. 0.131.07 k 0.11

Be-7 0.60 k 0.20

Be-7 2.36 k 0.62Be-7 3.56 2 0.57

Be-7 2.27 k 0.34Be-7 0.81 2 0.30Be-7 2.57 k 0.31

Be-7 3.37 k 0.46

Gamma emttters are only reported when acttvtttes exceed the MDC's: typtcal MDC values are found tn Table 1-15.

TABLE I-7

TRITIUM..ANDGAMMA'PECTROSCOPIC ANALYSES OF OROUND WATER

SUSQUEltANNA SIAM ELECI'RIC STATION - 1996


LOCATION COLLECTION DATE TRITIUM OTHER hCTIV1TT

12F32S24S4 Treated4S512S1

. 12F32S24S4 Treated4S512S1





01/15/9601/15/9601/15/9601/15/9601/15/96

02/12/9602/12/9602/12/9602/12/9602/12/96

03/11/9603/11/9603/11/9603/11/9603/11/96

04/15/9604/15/9604/15/9604/15/9604/15/96

05/13/9605/13/9605/13/9605/13/9605/13/96

06/10/9606/10/9606/10/9606/10/9606/10/96

c 100< 100c 100c 100< 100

< 100< 100< 100< 100< 100

100< 100< 100< 100< 100

< 100< 100< 100< 100< 100

c 100< 100< 100< 100< 100

< 100< 100< 100< 100< 100

I

CO


TABLE I-7

TRITIUM.AND GAMMA'PECTROSCOPIC ANALYSES OF GROUND WATER

SUSQUEHANNA SPAM ELECTRIC STATION - 1996


LOCATION COLLECTION DATE TRITIUM OTHER ACTIVITY

12F32S24S4 Treated

.4S512SI


12F32S24S4 Treated4S512sl

12F312S12S24S4 Treated4S5

12F312s12S24S4 Treated4SS

12F32S24S4 Treated4S512sl

07/15/9607/15/9607/15/9607/15/9607/15/96

08/12/9608/12/9608/12/9608/12/9608/12/96

09/09/9609/09/9609/09/9609/09/9609/09/96

10/15/9610/15/9610/15/9610/15/9610/15/96

11/11/9611/11/9611/11/9611/11/9611/11/96

12/16/9612/16/9612/16/9612/16/9612/16/96

< 100< 100< 100< 100< 100

< 100< 100< 100< 100140 X 70

< 100< 100< 100< 100< 100

1502 70< 100< 100< 100< 100

< 100< 100< 100< 100< 100

< 100< 100130% 80< 100< 100

I

Gamma emttters are only reported when acttvtttes mceed the MDC's: typtcal MDC values are found tn Table 1-15.

TABLE I-8

GROSS BETh ANALYSES OF AIR PhRTICUIATE FILTERS


Results tn E-03 PCI/Cu.M. i2S

Page 1 ofS

MONTH DATE Ill 701/801 601 382 1281 1386 9B1 787 1083

01/04-01/1001/10-01/1701/17-01/2401/24.01/31

21i 228i 215i 2( 7 (2)

22i 231i 216i 217i 2

25i 234t 219i 214i 2

24 i32 i17 i14 t

2222,

23i 230t 216i 214t 2

24i 233i 218i 217i 2

24i 230i 217 i 214i 2

22i 230i 216i 216i 2

())32i 218i 217i 2

25i 232 i 216i 215i 2

01/31-02/0702/07-02/1402/14-02/2102/21-02/28

22i 213i 212i 2

8.0i 1.6

23i 215i 210 i 211 i 2

24t 216 i 213i 2ll i 2

23i 218 i 212i 2lit 2

22k 215 i 213 k 2

9.2i 1.6

23i 213i 2ll i 2ll i 2

21i 2 20i 215 i 2 15i 2lli2 loi 2

9.5 i 1.7 I I i 2

2li 214i 212i 2

9.6i 1.7

22i 216 i 213i 2lli 2

MAR 02/28-03/0503/05-03/1303/13-03/2003/20.03/27

16 i 213i 216 k 210 t I t3)

19i 216 i 219 i 212 i 2

20 i17 i17 iI I i

17i 214i 219K 2

8.7 i 1.6

17i 214k 2I7i 2lli2

18 i15 i17 i

9.1 i2221.6

18 i 2 18 i 214 i 2 16 i 218i 2 19i 2

9.3 * 1.6 9.7 i 1.7

19 i 215i 217i 2loi 2

18 i 214i 218i 2lli2

APR 03/27-04/0204/02-04/1004/10-04/1704/17-04/2404/24-05/01

15 i 2lli28.7i 1.816i 2

8.9 i 1.6

Isi 213i 214i 216i 2

8.5 i 1.6

16i 215i 2Ioi 218i 2Io< 2

16 i 212i 2loi 216t 2lli2

16i 213i 2ll i 217i 2

9.5 i 1.6

16i 213 i 2

8.5 i 1.715i 2

9.8i 1.7

16 i 214i 210 i 215i 2ll i 2

17 i 214i 211 i 217i 2

8.4 i 1.7

16i 214i 2Ioi 217i 2

8.0i 1.6

18 i 213t 2

8.6 i 1.716 i 2loi 2

MAY 05/01-05/07 11 i 205/08-05/15 8.9 i 1.705/15-05/22 13 i 205/22-05/29 12 i 2

lli 29.3 i 1.7Ioi 210 i 2

12t 212i 214i 212t 2

13i 215i 216 i 212i 2

13 i 2loi 215i 2lli2

12 i 2ll i 214i 212i 2

12 i 215i 215i 212i 2

13i 211 i 216i 212 i 2

12i 213i 214 i 212i 2

13t 2Ioi 215i 212 i 2

JUN 05/29-06/0506/05-06/1206/12-06/1906/19-06/2606/26-07/02

9.6i 1.412i 216 i 2loi 2lli2

12i 212i 215i 210i 212 i 2')

13i 2lli 214i 212 i 212i 2

13 i 213 i 216i 212i 213i 2

12 i 2 13 i 2II i 2 13 i 215 i 2 19 i 214i 2 9.4i 1.612i 2- 15i 2

12 i 212i 217 i 2ll i 213i 2

12 i 211 i 216i 211 i 212 i 2

12i 2ll i 211 i 2

9.8i 1.611 i 2

11 i 29.9 i 1.517i 2lli 212i 2

ItAM

TABLE I-S

GROSS BETAANALYSES OF AIRPARTICULATEHLTERS

SUSQUEHANNA SRWM ELECTRIC SI'AT(ON - 1996

Results In E-03 pCI/Cu.M. i2S

Page 2 ofS

CO 0MONTH DA'IR (I) 7Q1/SQ1 SS2 1281 13S6 9B1 767 10S3 12E1

JUL 07/02-07/1007/10-07/1707/17-07/2407/24-07/31

I7i 215 i 2122 2IOR 2

16 k 214i 212i 2

9.8X 1.6

15i 213% 2132 215 i 2

17'14i 2)6x 213% 2

17i 2141 213i 2IIX 2

14i 214i 215i 2Ili 2

17i 212i 214i 210 i 2

152 2152 214% 213i 2

17% 213'(5)14 i 2

9.9 i 1.7

162 213i 2.12i 214% 2

AUG 07/31-08/0708/07-08/1408/13-08/2108/21-08/2808/28-09/03

21i 214i 217% 223i 222k 2

2li 2lsi 217% 222k 222 i 2

16% 216k 2I9% 222i 223i 2

21 i 2 '1 i 216 i 2(6) 13 i 219% 2 20% 223i 2 22i 223' 231 2

18 i14 i15 i21 i20 2

22222

19i 216i 220% 222i 224i 2

18 i 213 k. 219i 220% 223i 2

17k 2132 220% 219% 222i 2

19% 215i 219% 224k 222k 2

SEP 09/03-09/ I I09/11-09/1809/18-09/2509/25-10/02

ISi 2Ilj217i 215i 2

19 i 2 22 i 29.5 i 1.6 I I i 222i 2 20i 215 A 2 14 N 2

24k 212 S 2(7)19i 213% 2

20% 210% 222i 216% 2

21 t10%19 214 i

24k 2 19i 2 .212 212 i 2 13 i 2 9.6i. 1.721% 2 22k 2 22k 214i 2 142 2 152 2

18212 J20 J15 k

10/02-10/0910/09-10/1610/16-10/2210/22-10/30

ll i I16% 2152 214 m 4(8)

Ili I14i 217i 220% 2

)3 i 216% 218i 220'

I3i 216i 220i 219% 2

13i 215i 217i 218i 2

IIX 214i 221'192 2

13 i 2 13 k 2 13 i 215 i 2 15 i 2 15 i 2192 2 18i 2 20% 221i 2 19i 2 20% 2

12* 215% 218% 219i 2

NOV 10/30-1 I /0611/06-11/1311/13-11/2011/20-11/2611/26-12/03

21% 2I I i 4 (9)15 k 212% 213i 2

19% 27.5 i 1.316k 213i 213i 2

20% 28.9 i 1.4ISi 214i 213% 2

19k 28.0 i 1.4ISi 213% 213k 2

20i 28.0 i 1.319% 215k 214 i 2

19 i8.0 i19 k14 i15 R

2 . 21i 2 22k 2 20i 21.4 9.5 i 1.4 7.3 i 1.3 8.7 N 1.42 18i2 2022 18222 14 i 2 14 i 2 14 i 22 12% 2 16% 2 12% 2

22i 28.2 R 1.319i 212i 215% 2

DEC 12/03-12/1012/10-12/1812/18-12/2612/26-01/02

13 t 2 11 i I7.7t 1.3(10) 8.6i 1.219% 2 ISA 215 E 2 17 i 2

14k 2 13i 27.7 i 1.3 8.8 i 1.322i 2 23i 221 i 2 21 i 2

I4i 28.9 i 1.424i 219% 2

14i 2 15i 2 14% 2 15i 28.9 2 1.3 9.2 i 1.3 8.2 k 1.3 8.3 i 1.322k 2 22k 2 24k 2 23i 222+ 2 21% 2 19% 2 21i 2

14i 28.8 k 1.222 i 219% 2

TABLE I S

OROSS HKTAANALYSESOt AIR PARTICUlJLTE FILTERS

SUSQUEHANNA STEAM ELECTRIC Sl ATION - l996

Page S of9

Electrical power ms lost to the sampler at location 10S3 on I/4/96 aAer only about 2 hours ofoperation. A low volume ofonly about 280A'fair was sampled. InsuAicicnt sample volume vm collected for analysis.Electrical power was lost to the sampler at location 7G I on I/24/96 aAer only about four hours ofoperation. A low volume ofabout 560 ftofair was sampled. Thc sample +as analyzed but the required sensitivities for both the gross beta and the iodine-131 analyses could not bemct.

Sampling at location 7G I vas terminated on 3/27/96 and sampling at location 8G I began on 3/28/96. This change was made to obtain abcttcr sampling cnvironmcnt. Large trees were in too close proximity to the sampler at location 7G I.The particulate filterand charcoal cartridge used for sample collection at location 6G I for the period from 6/26/96 to 7/2/96 wereaccidentally installed at location 8G I for the nc'xt sampling period. The mistake was realized and the filterand cartridge were removed fromthc sampler and rcplaccd w'th a fresh filterand cartridge aAer being in use for two hours and 10 minutes. 19,200 ft'fair was sampled atlocation 6G I with thc filter and cartridge and an additional 280 fI'ere sampled with them at location 8GI.Electrical power >ms lost to thc sampler at location 10S3 prior to the scheduled end ofthe sampling period on 7/17/96. The electrical timerindicated that the sampler ran for nearly 156 hours. Sampling appears to have stopped some time in the early morning of7/17/96.A moth was found adhering to the particulate filterused for sampling at location 5S4 for the period 8/7/96 to 8/13/96.The electrical power to the sampler at location 5S4 was interrupted for 45 minutes on 9/16/96.Electrical power was lost to the sampler at location 8G I on 10/25/96 based on the run time of less than 53 hours indicated by the electricaltimer. A low volume ofabout 7,590 fI'fair was sampled. The required sensitivity for the gross beta analysis was not achieved.Electrical power was lost to the sampler at location 8G I on I I/8/96 based on the run time of less than 47 hours indicated by the electricaltimer. A low volume ofabout 6,240 fI'fair was sampled. The required sensitivity for the gross beta analysis was slightly exceeded.Electrical power was lost to the sampler at location 8G I in the morning on 12/17/96 based on the run time indicated by the electrical timerofnearly 161 hours. A suf6cient volume ofair was sampled to meet thc sensitivities for the gross beta and iodine-131 analyses.

TABUllI-9

QlQHMA'PECTROSCOPIC ANALYSESOF COMPOSITED AIR PARTICUIATEFILTERS

SUSQUEHANNA SIAM ELECTRIC Sl'ATION - 1996

Results In E-03 pCI/Cu. M. k 2S

Page I of2

LOCATION COILlrCTIONDATE Be-7 K-40 OTHER ACTIVITY

6G I7G I7S7

IOS33S2SS49BI

12EI12SI13S6

01/04/96-04/03/9601/04/96-03/28/96Ol/04/96-04/02/96Ol/10/96-04/02/9601/03/96-04/02/96Ol/03/96-04/02/9601/04/96-04/02/96OI/04/96-04/03/96Ol/04/96-04/02/96Ol/03/96-04/02/96

136 k 14116 k 12138 i 14139 a 14152 2 I I127 f 13128 k 13155 R 16136 2 14158 2 16

4.80 % 1.93

6GI8GI7S7

IOS33S25S49BI

12EI12SI13S6

04/03/96-07/02/9603/28/96-07/02/9604/02/96-07/02/9604/02/96-07/02/9604/02/96-07/02/9604/02/96-07/02/9604/02/96-07/02/9604/03/96-07/02/9604/02/96-07/02/9604/02/96-07/02/96

176 2 18142 2 14137 i 14162 2 16165 i 16157 '6

"176 k 18155 2 15153 R 15147 2 15

3.05 k 1.68

Gamma emitters are only reported when acttvtttes exceed the MDC's: typtcal MDC values are found tn TabIe 1-15.

TABLEI-9

GAMlHA'PECTROSCOPIC ANALYSES OF COMPOSITED AIR PARTICULATEFILTERS

SUSQUEHANNA STEAM ELECTRIC Sl'ATION - 1996

Results In E-03 pCI/Cu. M. k 2S

Page 2 of2

LOCATION COLLECTION DATE Be-7 K-40 OTHER ACTIVITY

6GISGI7S7

IOS33S25S49BI

12EI12SI13S6

07/02/96-10/02/9607/02/96-10/02/96'07/02/96-10/02/9607/02/96-10/02/9607/02/96-10/02/9607/02/96-10/02/9607/02/96-10/02/9607/02/96-10/02/9607/02/96-10/02/9607/02/96-10/02/96

148 R 15126 X 13128 R 13162 k 16157 R 16142 k 14163 k 16138 k 14132 k 13121 k 12

4.96 R 1.91

6GISGI7S7

IOS33S25S49BI

12EI12SI13S6

10/02/96-01/02/9710/02/96-01/02/9710/02/96-01/02/9710/02/96-01/02/9710/02/96-01/02/9610/02/96-01/02/9710/02/96-01/02/9710/02/96-01/02/9710/02/96-01/02/9710/02/96-01/02/97

75.5 i 7.684.6 k 8.582.4 2 8.284.8 2 8.596.7 i 9.795.6 R 9.682.0 k 8.281.6 f 8.278.2 R 7.880.1 2 8.0

3.18% 1.86

16.3 k 2.63.29 R 1.79

I

Gamma emttters are only reported when acMttes acceed the MDC's: typtcal MDC mdues are found tn Table 1-15

TABLEI-IO

TRITIUM.AND GAMMA'PECTROSCOPIC ANALYSES OF PRECIPITATION

SUSQUEHANNA STFAM ELECTRIC SfATION - 1996

Results In pCI/Itter i 2S

IDCATION COLIZX:TIONDATE TRITIUM BF 7 K-40 COMMENTS

6G17G17S7

10S33S25S4981

12E112sl13S6

6G 1

8G17S7

10S33S25S4981

12E112S113S6

12/27/95-03/27/9612/27/95-03/27/9612/27/95-03/27/9612/27/95-03/27/9612/27/95-03/27/9612/27/95-03/27/9612/27/95-03/27/9612/27/95-03/27/9612/27/95-03/27/9612/27/95-03/27/96

03/27/96-06/26/9603/28/96-06/26/9603/27/96-06/26/9603/27/96-06/26/9603/27/96-06/26/9603/27/96-06/26/9603/27/96-06/26/9603/27/96-06/26/9603/27/96-06/26/9603/27/96-06/26/96

< 100< 100< 100< 100< 100< 100< 100< 100< 100< 100

< 100«100< 100< 100< 100< 100< 100< 100< 100< 100

45.9 i 24.5

51.7 i 24.1

42.9 i 18.9

49.8 i 25.063.6 i 23.9

49.9 i 21.0

48.7 i 18.443.0 i 17.749.9 i 28.3

I


TABLE I-10

TRITIUM.AND GAMMA'PECTROSCOPIC ANALYSES OP PRECIPITATION

SUSQUEHANNA SIAM ELECTRIC STATION - 1996

Results In pCI/liter k 2S

LOCATION COLIZCTIONDATE TRITIUM BE-7 K-40 COMMENTS

6G ISG I7S7

1053352SS4981

12EI12SI13S6

6GISGI7S7

IOS33S25S49BI

12EI12SI13S6

06/26/96-10/02/9606/26/96-10/02/9606/26/96-10/02/9606/26/96-10/02/9606/26/96-10/02/9606/26/96-10/02/9606/26/96-10/02/9606/26/96-10/02/9606/26/96-10/02/9606/26/96-10/02/96

10/02/96.01/02/9710/02/96-01/02/9710/02/96-01/02/9710/02/96-01/02/9710/02/96-01/02/9710/02/96-01/02/9710/02/96-01/02/9710/02/96-01/02/9710/02/96-01/02/9710/02/96-01/02/97

<100<100<100<100(100<100«100<100<100<100

<100<100<100<100<100<100<100<100<100<100

'3K 24

46k 2457% 26

LA

Gamma emitters are only reported when acttvtttes exceed the MDC's: typtcal MDC values are found tn Table 1-15.

TABLEI-11

IODINF 131. AND QAMMA'PECTROSCOPIC ANALYSES OF MILK



Page 1 of S

LOCATION COLUGCTION DATE KRO OTHER ACTIVITY

IOG IIODIIOD21283

IOG IIOD IIOD21283

IOG IIODIIOD21283

IOG IIODIIOD21283

IOGIIOD I10D21283

IOGIIODIIOD21283

IOG IIODIIOD21283

01/11/9601/10/9601/10/9601/09/96

02/06/9602/06/9602/06/9602/06/96

03/05/9603/05/9603/05/9603/05/96

04/08/9604/08/9604/08/9604/08/96

04/22/9604/22/9604/22/9604/22/96

05/06/9605/06/9605/06/9605/06/96

05/20/9605/20/9605/20/9605/20/96

1400 x1330 a1450 X1210 i1220 f1400 i1470 X1210 i1360 R1420 21290 21260 2

1320 a1480 R1370 R1350 k

1370 k1540 a1320 i1370 2

1240 21320 21350 21200 2

1320 i1490 R1230 i1080 f

140130140120

120140150120

140140130130

130150140130

140150130140 -=-.

120130130120

130150120110

Gamma emitters are only reported when actMttes exceed the MDC'st typtcal MDC values are found tn Table 1-15.

TABUllI-11

IODINE-1$1, AND GAMMA'PECTROSCOPIC ANALYSES OF MILK

SUSQUEHANNA STEAM ELECmIC STATION - 1996

Results tn pCI/ltter k 2S

Page 2 of$

LOCATION COLLECTION DATE KQO OTHER ACTIVITY

IOG IIODIIOD21283

IOG IIODIIOD21283

06/03/9606/03/9606/03/9606/03/96

06/19/9606/19/9606/19/9606/19/96

1260 k1340 i1240 X1380 a

1210 X1500 a1320 %

1390 %

130130120140

120150130140

IOG IIOD IIOD21283

IOG IIODIIOD21283

IOGIIODIIOD21283

1283IOD2IOGI10DI

1283IOD2IOGI10DI

07/09/9607/09/9607/09/9607/09/96

07/23/9607/23/9607/23/9607/23/96

08/06/9608/06/9608/06/9608/06/96

08/20/9608/20/9608/20/9608/20/96

09/03/9609/03/9609/03/9609/03/96

1180 a1170 k1170 i1320 X

1280 i.1450 R1150 a1230 i1250 X1400 21150 a1270 j1260 k1290 i1260 i1420 2

1280 21380 i1290 X1450 i

120120120130

130150110120

130140110130

130130130140

130140130150

Gamma emttters are only reported when acttvtttes «xceed the MDC's: typtcal MDC values are found tn Table I-15.

TABLE I-11

IODINE-131. AND GAMMA'PECmOSCOPIC ANALYSES OF MILK

SUSQUEHANNA Sl'EAM ELECI RIG STATION - 1996

Results In pCI/liter k 2S

Page S of S

LOCATION

IOG IIODIIOD21283

IOG IIOD IIOD21283

1283IOD2IOG IIOD1

1283IOD2IOG IIODI

IOG1IOD1IOD21283

COLUrCTION DATE

09/17/9609/17/9609/18/9609/18/96

10/07/9610/07/9610/07/9610/07/96

10/21/9610/21/9610/21/9610/21/96

I I /04/9611/04/9611/04/9611/04/96

12/10/9612/10/9612/10/9612/10/96

K-40

1300 i 1301390 i 1401280 R 1301230 2 120

1310 k 1301260 2 1301350 R 1401210 k 120

1360 I 1401460 2 1501420 k 1401360 R 140

1330 R 1301330 2 1301320 R 1301350 2 130

1290 k 1301460 R 1501210 k 1201220 2 120

OTHER ACTIVITY

Gamma cutters are only reported when acttvtttes exceed the MDC's: typtcal MDC values are found tn Table 1-15.

TABLEI-12

GAMMA'PECTROSCOPIC ANALYSES OF SOIL

SUSQUEIIANNA STEAM ELECI'RIC STATION - 1996

Results ln PCt/gm (dry) f 2S

Pago 1 of 1

LOCATION COIJZCTION DATE KQO Cs-137 Ra-226 T}L-228

6G 1 TOP6GI BOT

8GI TOPSG I

BOI'S2

TOP3S2 BOI

5S4 TOPSS4 BOT

981 TOP981 BOT

12EI TOP12EI

BOI'2SI

TOP12SI

BOI'3S6

TOP13S6 BOT

7S7 TOP7S7

BOI'OS3

TOPIOS3

BOI'9/23/96

09/23/96

09/23/9609/23/96

09/23/9609/23/96

09/23/9609/23/96

09/23/9609/23/96

09/23/9609/23/96

09/23/9609/23/96

09/23/9609/23/96

09/23/9609/23/96

09/23/9609/23/96

18.2 i 1.820.6 f 2.1

S.68 x 0.877.03 a 0.7

13.8 k 1.4I 3.9 i 1.4

10.1 i 1.09.21 i 0.9

9.00 k 0.908.87 i 0.89

I 1.2 2 1.1108 i 1.1

10.0 i 1.09.65 X 0.97

12.1 2 1.2I 1.3 k 1.1

9.32 R 0.939.29 R 0.93

I 1.5 a 1.210.5 k 1.0

1.15 X 0.110.09 k 0.03

0.16 k 0.040:13 i 0.03

0.05 R 0.02

0.18 k 0.040.15 i 0.03

0.35 k 0.040.30 k 0.04

0.29 i 0.030.28 k 0.03

0.11 % 0.020.08 k 0.03

0.05 E 0.030.05 k 0.03

0.21 k 0.040.18 k 0.03

0.38 k 0.060.30 2 0.04

2.30 k 0.701.36 i 0.64

1.88 k 0.581.02 k 0.43

2.00 k 0.481.34 % 0.52

1.58 2 0.491.73 k 0.43

.1.35 1 0.38

1.51 k 0.38-1.39 k 0.40

1.51 k 0.461.02% 0.48

1.46 R 0.431.06% 0.41

1.43 R 0.521.59 R 0.38

2.36k 0.842.01 k 0.66

1.20 k 0.121.25 k 0.12

0.76 k 0.080.66 2 0.07

1.00 2 0.100.88 k 0.09

0.87 k 0.090.92 k 0.09

0.65 X 0.070.69 R 0.07

0.76 2 0.080.74 2 0.07

0.76* 0.080.69 k 0.07

0.77 R 0.080.76 2 0.08

0.91 2 0.090.65 2 0.07

1.06 k 0.111.35 2 0.14

bamma «mitters are only reported when acttvtttes rsrceed the MDC's: typtcal MDC values are found tn Table 1-15.

TABLE 1-1$

GAMMA'PECTROSCOPIC ANALYSES OF FOOD PRODUCTS (FRUITS ANDVEGETABIZS)

SUSQUEHANNA STEAM ELECTRIC Sl'ATION - 1996

Results In pCI/gm (wet) 2 2S

Page I of 2

IDCATION COUZCTION DhTE K-40 OTHER ACTIVITY

10858A4

12S7

12F71085

~ 1483

13G210851483

13G211D1

13G211D112S71483

13G210851483285

11D1

1085

ApplesApplesApples

Broccoli

Can talou peCantaloupe

CornCornCornCorn

CucumberCucumberCucumberCucumberCucumber

Lettuce

09/23/9609/23/9610/07/96

07/16/9608/19/96

08/27/96

07/29/9607/16/9608/27/96

08/27/9608/19/96

08/27/9608/19/9608/19/9608/27/96

07/29/9607/16/9607/23/9607/30/9608/19/96

07/16/96

0.88 k 0.090.56 i 0.080.79 k 0.08

1.97 2 0.202.12 k 0.21

3.15 k 0.31

1.86 k 0.191.58 % 0.161.69 2 0.17

3.27 R 0.331.90 R 0.19

2.30 i 0.232.43 R 0.242.64 k 0.261.93 k 0.19

1.96 2 0.201.85 k 0.191.57 % 0.161.33 k 0.131.35 2 0.14

2.75 k 0.28 Be-7 0.21 k 0.05

Gamma emtt ters are only reported when acttvt ttes exceed the MDC'a: typtcal MDC values are found tn Table 1-15.

TABLEI-IS

GAMMA'PECmOSCOPIC ANALYSESOF FOOD PRODUCTS (FRUITS ANDVEGETABIZS)

SUSQUEHANNA STEAM ELECTRIC STATlON - 1996

Results In pCI/gm (wet) k 2S

Page 2 of2

LOCATION COLLECTION DATE K-40 OTHER ACTIVITY

13G21483285

8A414831085

12F711Dl

11D112S7

13G2285

1085

13G211D11085

SA4984

1483

13G29B4

11DI

OnionOnionOnion

PearsPeppersPeppers

PotatoesPotatoes

PumpkinPumpkin

SquashSquashSquash

TomatoesTomatoesTomatoesTomatoesTomatoesTomatoes

ZucchlnlZucchlnlZucchlnt

07/29/9607/23/9607/30/96

09/23/9607/23/9608/19/96

09/03/9609/23/96

09/23/9610/07/96

07/29/9607/30/9608/19/96

08/27/96. 08/19/9608/19/9608/19/9608/26/9608/27/96

08/27/9607/16/9608/19/96

1.04 k 0.101.20 k 0.121.54 k 0.15

1.23 R 0.121.72 R 0.171.32 R 0.13

3.32 R 0.333.46 R 0.35

3.03 k 0.302.06 k 0.21

1.64 k 0.161.73 k 0.171.82 k 0.18

2.35 R 0.231.75 k 0.173.12 i 0.312.40 k 0.242.80* 0.282.37 A 0.24

1.17 k 0.121.82 k 0.181.80 2 0.18

Gamma emttters are only reported svhen aettvtttes exoeed the MDCs: typtcal MDC values are found In Table 1-15.

TABLE I-14

GAMMA'PECTROSCOPIC ANALYSES OP QAME


Results In IsCI/gm (wet) 2 2S

Page 1 of 1

LOCATION

13G5S7S

IIS

16H3SSS7S

2B5S

IOS.16F

RabbitRabbitRd>bitRabbit

White-Tall DeerWhite-Tall DeerDeerWhite-Tall Deer

SquirrelSquirrelSquirrelSquirrel

COLIZCTION DATE

10/25/9610/04/9610/01/9610/02/96

12/18/9602/08/9605/23/9601/30/96

10/25/9610/23/9610/24/9610/24/96,

KRO

2.32 i 0.233.37 k 0.343.00 k 0.302.43 R 0.24

4.32 R 0.434.65 R 0.473.89 2 0.393.95 k 0.40

3.28 R 0.333.572 0.363.27 2 0.333.33 % 0.33

CS-137

0.01 2 0.005

-O.OS k 0.007

0.062 0.010.03 % 0.005

0.36 2 0.040.01 k 0.0060.52 k 0.051.15 R 0.11

Gamma emit ters are only reported when activities cspeed the MDC's: typical MDC values are found in Table 1-15.

TABLEI-15

TYPICAL~ MINIMUMDEIZCTABLECONCElMT1VlTIONSOF NUCLIDES SEARCHED FOR BUT NOT FOUND BY GAMIHASPECTROMETRY

IN THE VICINITYOF SUSQUEHANNA STEAM ELECTRIC STATION, 1996

Nuclide

Mn-54Co-58Fe-59Co-60Zn-65Zr-95Nb-95Ru-1031-131"Cs-134Cs-137Ba-140La-140Ce-141

Fish/ wet)

0.0220.0220.0440.0250.0420.0420.0250.0250.0420.0250.0290.0770.0310.039

Sediment/ )

0.0500.0480.1060.0480.1120.1130.0550.0510.1000.0600.0710.1960.0770.092

Surface Water( /I)

4.14.18.74.59.38.74.4497.54.94.9

136.18.0

Ground Water( /I)-

4.34.18.94.69.78.84.94.96.64.95.0

135.88.3

Potable Water( i/I)

4.23.88.94.59.39.04.7499.24.84.8

187.48.3

Rain Water( i/1)

4.244

10 .

4.59.89.25.15.29.15.15.2

197.08.8

Nuclide

Mn-54Co-58Fe-59Co-60Zn-65Zr-95Nb-95Ru-103I-131"Cs-134Cs-137

Ba-140'a-140

Ce-141

AirParticulate(1OS /mS)

0.340.501. 140.310.761.020.520.78

590.310.34

219.31.6

Milk(pCi/1)

4.74.59.95.2ll9.14.84.90.175.05.2ll5.28.7

Fruit/Veg.(pCi/ wet)

0.0090.0080.0210.0090.0220.0170.0090.0090.0150.0090.0090.0340.0120.014

Floe(pCi/ dxy)

0.0950.0980.2750.0970.2000.2750.1080.0950.2250.1080.1110.3000 2250.113

Game(pCi/ wet)

0.0100.0110.0260.0110.0250.0230.0110.012 .0.0360.0110.0420.0510.0200.022

Soil(pCi/ dxy)

0.0480.0450.1030.0490.1010.1020.0570.0550.1390.0590.0960.2440.0870.089

Typical refers to mean plus two standard deviations.lodin -131 in surface water, potable water and mQk is determined ~ radiochemical methods. See appendix E-13.

APPENDIX S

PERFORMANCE SUMMARYFOR THE ..'."'".-'ADIOANALYSESOF SPIKED

ENVIRONMENTALSAMPLE MEDIA.-1996-

TELEDYNEBROWN ENGINEERING RESULTS.


f

t

0

A endix J

The data in the tables that follows show how well Teledyne performed in the analysis ofradioactively spiked environmental sample media. Table J-1 permits an evaluation ofTeledyne's performance in the analyses ofspiked samples supplied by the EPA relative to.the EPA and other participants in the "EPA Environmental Radioactivity PerformanceEvaluation Studies Program" during 1996.

Table J-2 shows the agreement ofTeledyne's analysis results with the levels ofradioactivity reported by Analytics, Inc., for spiked samples procured by Teledyne as

part of its QC Spike Program. Table J-3 presents the analysis results ofTeledyne andthe levels of radioactivity reported by Analytics for spiked environmental sample mediaprocured from Analytics by PP&L as part of its quality control for the PP&LRadiological Environmental Monitoring Program (REMP). The spiked samplesrepresented in both Tables J-2 and J-3 are prepared by Analytics as part of itsEnvironmental Radioactivity Cross Check Program.

1996 Radiological Eniironmcntal Monitoring Rcport J-2

k

~ /f

0:

TABIZJ-1EPA ENVIRONMENTALRADIOACllVITYPERFORMANCE EVALUATIONSIVDIES PROGRAM - 1996

TELEDYNE BROWN ENGINEERING ENVIRONMENTALSERVICES(Bye I ot2)

Collection SequenceDate No. Media Nuclide EPA Reiulta(a)

Teledyne Nornmlixed Devtation AllParticipantsBrown . Results(b) Gmnd A . Known Mean k 2 s.d.

0 I /26/96 674 Water

02/02/96 676 Water

03/08/96 677 Water

04/16/96 678 Water

06/07/96 679 Water

Gr-AlphaGr.Beta

I-131

H-3

Gr-BetaSr-89Sr-90Co.60Cs-134Cs-137-Gr-Alpha

Co-60Zn-65Cs-134Cs-137Ba-133

0l /23/96 675 Water Sr-89Sr-90

73.0 t 8.665.0 a 8.66

12.1 i 8.667.0 k 8.66

67.0 i 12.12

22002.0 k 3810.5

166.9 R 43.343.0 i 8.6616.0 R 8.6631.0 i 8.6646.0 R 8.6650.0 i 8.6674.8 R 32.39

99.0 i 8.66300.0 i 51.96

79.0 X 8.66197.0 R 17.32745.0 R 129.9

73.67 X 9.635.00 k 0.00

19.00 i 3.007.13 R 0.63

71.67 k 9.18

22000.00 2 0.00

160.00 t 0.0041.33 R 6.9315.33 2 1.7431.67 k 3.4542.33 R 4.5952.33 R 4.5963.67 2 8.67

99.00 k 5.19309.33 k 6.24

69.67 k 4.59202.00 k 7.95711.00 2 214.26

1.070.07

2.46-0.47

0.77

0.34

0.090.09

-0.020.02

-0.270.40

-0.47

0.300.00

-1.130.21

-0.21

0.230.00

2.390.05

1.15'.00

-0.48-0.58-0.230.23

-1.270.81

-1.03

0.000.54

-3.230.87

-0.79

70.58 R 18.285.2 a 3.5

11.90 2 5.04(c)8.5M 3.88

158.64 241.09 215.39 231.60 243.10 R51.17 268.69 2

34.508.424.984.206.226.6224.0

98.12 2 11.18309.37 R 34.98

72.92 2 11.0(d)200.79 2 20.06720.13 2 79.06

68;53 k 9.86

21573.18 M549.62

07/12/96 683 Water

07/19/96 681 Water

08/09/96 682 Water

10/02/96 686 Water

Sr-89Sr-90

Gr-AlphaGr-Beta

H-3

1-131

25.0 k 8.6612.0 t 8.66

24.4 R 10.56~ 44.8 R 8.66

10879.0 21884.47

27.0 i 10.39

22.67 R 4.5912.33 R 3.45

22.67 2 1.7445.33 k 6.24

9800.00 21039.23

26.33 R 6.93

-0.420.19

0.850.33

1.26

-0.37

-0.810.12

-0.490.18

-1.72

-0. 19

23.88 211.79 2

7.464.94

19.67 R 9.3644.38 2 11.30

10590.90 2 1442.9

27.61 2 6.16

TABLEJ-1EPA ENVIRONMENTALRADIOACIlVflYPERFORMANCE EVALUATIONSTUDIES PROGRAM - 1996

TELEDYNE DROWN ENGINEERING ENVIRONMENTALSERVICES(Pay. 2af 2)

CoIIection 8equcncoDate No. MedIA Nuclide EPh Results(a)

TeledyneBrown . Results(b)

Normalized DeviationGrand h . Known

h11 ParticipantsMean 2 2 s.d.

10/15/96 688 Water

10/25/96 684 Water

11/08/96 687 Water

Gr-AlphaGr-BetaSr-89Sr-90Co.60Cs-134Cs-137

Gr-AlphaGr-Beta

Co-60Zn-65Cs-134Cs-137Ba-133

59.1 s 25.63111.8 i 29.10

lo.o ~ 8'.6625.0 i 8.6615.0 i 8.6620.0 i 8.6630.0 2 8.66

10.3 i 8.6634.6 2 8.66

44.0 i 8.6635.0 j 8.6611.0 X 8.6619.0 f 8.6664.0 i 10.39

55.671 X 15.09110.0 t 0.009.00 k 0.00

26.00 i 3.014.67 i 4.5919.67 i 3.4529.33 R 3.45

9.03 k 2.1639.67 i 1.74

44.67 X 1.7438.67 i 1.7412.00 k 0.0020.67 R 3.4556.67 R 9.63

-0.500.23

-0.470.80

-0.200.42

-0.40

0.061.52

0.050.900.480.1 I

-1.36

0.40-0.19-0.350.35

-0.12-0. 12

A.23

-0.441.76

0.231.270.350.582.12

59.91 k107.72 R

10.36 223.68 R15.24 218.45 k30.50 2

8.86 235.29 k

44.53 236.08 110.62 220.36 261.39 R

22.2821.96

6.546.343.503.504.28

5.788.94

5.748.903. 103.867.4(e)

Zuuimhs

(a) EPA Results - Expected laboratory pression (3 sigma). Units are pCI/I for water and milk except K Is In mg/l.

(b) Teledyne Results - Average k 3 sigma. Units are pCI/I Ior water and milk except K is in mg/l. Units are total pCI for air'parUculate Alters.

(c) The variation was due to self-absorption properties of the EPA sample matrix. On future EPA water samples of this type, we will determine theoverall alpha counUng efAciency by spiking the matrix with '%-230 In accordance with their recent advisory.

(d) To verify thc cause for thc dcvfaUon. a Cs-134 standard has been purchased. Ifthe Cs-134 cNciency is lower than the eNcfency at 604 KeV and 795KeV, then rather than change those cNciencfes (which may be needed Ior other isotopes of comparable energies) the Cs-134 branching intensityshall be ad]usted.

(e) Thc cause Ior thc deviation could not be speciAcally determined. Samples were analyzed in trfplicate on three diffcrcnt HPGe detectors providingresults with good precision (less than 11% deviation). The values calculated by the software for each discrete energy line of Ba-133 were also ina cement indicating an excellent efAciency versus energy calibraUon AL Use of a valid branching ratio in the calcu(aUon was veriAed. The initial

quot was veriAcd and the Co-60, Cs-134. and Cs-137 values werc in excellent agreemcnt with the known.. A speciAc trend over time was notapparent in the data. however the normalized deviation calculated from thc EPA appears to decrease as the known activity fncreases. No correctiveactions are anUcipated at this time. Future analyses will be monitored to idenUfy any potential trend toward an out of control condition.

TAB%J-2ANALYllCSENVIRONMENTALRADIOACI1VfIYCROSS CHECK PROGRAM - 1996

TELEDYNE QC SPIKE PROGRAMTELEDYNE DROWN ENGINEERING ENVIRONMEVI'ALSERVICES

IR~ I of2)

Collection IdentiiicationDate No. Media Nuclide

hnalyticsResults

TeledyneBrown . Results(a R tioIc)

03/12/96 EO633-396 WaterTI¹ I 1912

03/12/96 EO 635-396 M IlkTI¹ 11914

03/12/96 EO632-396 WaterTI¹ 1191 I

1-131Ce. 14 ICr-51Cs-134Cs-137Co-58Mn-54Fe-59Zn-65Co-60

1-131Ce-141Cr-51Cs-134Cs-137Co-58Mn-54Fe-59Zn-65Co-60

Sr-89Sr-90

36k 288k 4

322 k 1658k 364k 348k 231% 283% 497k 576k 4

13k I234 k 12858 R 43154 % 8170 i 9128 k 684% 4

223 k 11260 k 13204 2 10

24k I211 I

39 k89 2

330 253 265 249k37 k93 k100281 k

16%240 R880 k150 k180 2140 293 k

250 k260 2220 2

30%23 k

59

3057549

108

620902020109

303020

1.081.011.020.911.021.021. 191. 121.031.07

1.231.031.030.971.061.091.111.121.001.08

1.251. 10

03/12/96 EO634-396 MI]IcTI¹11914

Sr-89Sr-90

311 216% I

30%17%

0.971.06

03/12/96 EO636-396 WaterTI¹11913

H-3 2982 k 149 2800 k 200 0.94

06/19/96 EO746-396 Air FtlterTI¹19220

Gr-AlphaGr-Beta

35k 2144 i 7

37 k150 2

310

1.061.04

06/19/96 EO747-396 Air FilterTI¹ 19221

Ce-141Cr-51Cs-134

400 2 201048 2 52310 k 16

500 k1200 2310 k

5010030

1.251.151.00

TABLEJ-2ANALmCS ENVIRONMENTALRADIOACTIVrTYCROSS CHECK PROGRAM - 1996

TELEDYNE QC SPIKE PROGRAMTELEDYNE BROWN ENGINEERING ENVIRONMENTALSERVICES

~2 of 2)

Collection IdentiecatlonDate No. Media

06/19/96 EO747-396 Alr Filter

TINI9221

Nuclide

Cs-137Co-58Mn-54Fe-59Zn-65Co-60

AnalytlcsResults

764 k 38173 i 9559 X 28144 a 7108 i 5156 i 8

TeledyneBrown . Results(a

910 2 90210 2 20690 2 70190 i 20140 k 10.180 2 20

Ratio (c)

1.191.211.231.321.301.15

(a) Teledyne Results - counting error is two standard devlatlons. Units are pCI/liter for water and milk. For gamma results. Iftwo standard devlatlons areless than I%6, then a INb ermr Is reported. Units arc total pCI for air particulate Alters.

(b) Analytlcs Results - counting error Is three standard devlatlons. Units are pCI/liter for water and milk. Units are total pCI for air particulate Alters.

(c) Ra(to ol'Teledyne Brown Englneerlng to Analytlcs results.

0-TABLEJ-3

ANALYllCSENVIRONMENTALRADIOACTIVflYCROSS CHECK PROGRAM - 1996PAL QC SPIKE PROGRAM

TElEDYNE BROWN ENGINEERING ENVIRONMENTALSERVICESthy' of4)

Collection IdentillcationDate No. Media Nuclide

AxmlyUcsCalculated Results (b)

TeledyneBrown . Results(a) Ratio (c)

June/1996 E0764-186 MilkSept/1996 E0845-186Dec/1996 E0910-186

June/1996 E0764- 186 M Ilk

Sept/1996 E0845-186 Mtlk

Dec/1996 E0910-186 Milk

1-131

Ce-141Cr-51Cs-134Cs-137Co-58Mn-54Fe-59Zn-65Co-60

Ce-141Cr-51Cs-134Cs-137Co-58Mn-54Fc-59Zn-65Co-60


15% I22k I59k 3

2151 8563 k 19166 2 6410 % 1493k 4

300 k 1077k 358'84k 3

318 2 11486 k 16222 k 8169 i 6131 k 5180 R 637k 270% 3

114% 4

277 k 12214% 9175 k 7194 i 8121 R 5206 k 849k 293k 4

110% 5

15227 262 k

215 2611 k169 i471 1104 i354 2

92 k67 i92 i

281 k494 2192 k168 k119 k173 k45k69 2

113 k

272 k233 k159 2191 k128 k220 k58k

107 2115 k

I1010

2261174710351299

2850191712171012ll274316191322101412

1.001.231.05

1.001.091.021.151.121. 181.191.161. 10

0.881.020.860.990.910.961.220.990;99

0.981.090.910.981.061.071.181.151.05

TABLEJNANALYllCSENVIRONMENTALRADIOACllVl1YCROSS CHECK PROGRAM - 1996

PAL QC SPIKE PROGRAMTELEDYNE BROWN ENGINEERING ENVIRONMENTALSERVICES

thee 2 of 4)

Collection IdentiacathmDate No. Nuclide

AmlyticsCalculated Results (b)


Sept/1996 E0846-186 AP Ftlter846



Ce-141Cr-51Cs-134

. Cs-137Co-58Mn-54Fe-59Zn-65Co-60



235 k ~ 12359 k 18164 k 9125% 797% 5

133 t 728k 252k 384k 5

239 i 12365 R 19166 % — 9127% 798K 5

135% 728% 253k 3851 5

242 t 13369 i 19168% 9128% 799k 5

137% 728k 253'86k 5

221 i369 2139 2134 k95 R

143 a33 256%84 2

263 k385 k149 k149 k107 k165 k37 k67 k97 k

273 i467 2162 k152 k112 k173 k38k70 k

100 2

223714131014789

26391515111688

10

2747161511179

1010

i j! .i

0.941.030.851.070.981.081.181.081.00

1.101.050.901.171.091.221.321.261.14

1.131.270.961.191.131.261.361.321.16

OO

5 0TABLZJN

ANAI.Yl1CS ENVIRONMEhfMI.RADIOACllVflYCROSS CHECK PROGRAM - 1996PAL gC SPIKE PROGRAM

TELEDYNE DROWN ENGINEERING ENVIRONMENTALSERVICES

(Page 3 ot 4)

Collection Identi6catlonDate No. Media

Dec/1996 E0911 ~ 186 AP Ftlter911

Nuclide

Cc-141Cr-51Cs-134Cs-137'o-58

Mn-54Fe-59Zn-65Co 60

278 i215 k176 k196 k122 k207 i

49 k93 2

I I I k

1197859245

hmLIyticsCalculated Results (b)

344 k274 k174 k240 k145 k275 266k

118 0128 k

343317241527101213


1.241.270.991.221.191.331.351.271.15

Dec/1996 E0912-186 AP Ftlter912

Dec/1996 E0913-186 AP Ftltcr913

Ce-141Cr-51Cs-134Cs-137Co-58Mn-54Fc-59Zn-65Co-60


227 k175 i144 2159 2100 2169 240 R76 k90 k

229 k177 k145 i161 k101 k171 k41 +77 k91 k

976747234

9767

7234

287 k256 k129 2199 R120 k228 *56k

110 2105 k

257 k204 2133 k191 kill2216 2

54 k95 k

102 2

295413201223121110

26251319ll22

71010

1.261.460.901.251.201.35

1.17

1.121.150.921.191.101.261.321.231.12

gjll ~

TABLEJNANALYTICSENVIRONMEtfl'ALRADIOACllVflYCROSS CHECK PROGRAM - 1996

PP&L QC SPIKE PROGRAMTELEDYNE DROWN ENGINEERING ENVIRONMENTALSERVICES

thyme 4 of 4)I

CoIlection IdentiQcationDate No. media

June/1996 E0766-186 Filter766

E0767-186 Filter767

Nuclide

1-131

1-131

Anmdytics,Calculated Results (b

83% 3

81% 3

TelectyneBtown . Results(a

83 2 8.

83% 8

Ratio (c)

1.00

1.02

0.92872 3

(b) Analytlcs Results - counting error Is three standard devlatlons. Units are pCI/)lter for'w'ater and milk. Units are total pCI Ior att pttrttculate Alters.

(c) Ratio of Teledyne Brown Englneerlng to Analytlcs results.

E0768.186 Filter I-'131 802 8768

(a) Teledyne Results - counting error Is two standard devlatlons. Units are pCI/Ilier, Ior water and milk. For gamma results, lfNro standard devlattons.attless than I NS, then a IN&error Is reported. Units are total pCI for air particulate Alters.

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