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TABLEOF CONTENTS

SUh8rfARYAND CONCLUSIONS.

INTRODUCTION.

AMBIENTRADIATIONMONITORING.......

AQUATICPATHWAYMONITORING. ~

ATMOSPHERIC PATHWAYMONITORING.

TERRESTRIAL PATHWAYMONITORING.

GROUND WATERMONITORING.

REFERENCES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

'~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

....18

.. 23

......... 41

......... ~ ................. 49

.....58........................... 6 1

APPENDICES

A. 1994 REMP CHANGES

B. 1994 REMP MONITORINGSCHEDULE

C. 1994 REMP MONITORINGLOCATIONDESCRIPTIONS

D. 1994 LANDUSE CENSUS RESULTS

E. SUMMARYDESCRIPTION OF SSES REMP ANALYTICALMETHODS

A-1

B-1

C-1

D-1

E-1

F. 1994 EXCEPTIONS TO THE SSES TECHNICALSPECIFICATIONS SAMPLE SCHEDULE, METHODSAND ANALYSISSENSITIVITIES

F-1

G. 1994 SSES REMP SUIVSCARY OF DATA

H. COMPARISON OF INDICATORAND CONTROL 1994REMP ANNUALMEANS FOR SELECTED MEDIAANALYSISRESULTS WITHMEANS FROMPREOPERATIONAL ANDPRIOR OPERATIONALPERIODS

G-1

H-1

SPECIFIC ANALYSISRESULTS TABULATEDBYMEDIAAND SAMPLINGPERIOD

EPA EIAMONMENTALRADIOACTIVITYPERFORMANCEEVALUATIONSTUDIES PROGRAM - 1994

LIST OF FIGURES

FigureNumbers Title

Exposure Pathways to Humans

1994 TLDMonitoring Locations within One Mileof the SSES

~Pa e

12

1994 TLDMonitoring Locations &om One to Five Miles oftheSSES

13

1994 TLDMonitoring Locations Greater than Five Miles from theSSES

14

5. 1994 Environmental Sampling Locations within One Mile oftheSSES

15

1994 Environmental Sampling Locations from One to Five Miles ofthe SSES

16

1994 Environmental Sampling Locations Greater than Five Milesfrom the SSES

17

Ambient Radiation Levels Based on TLDData

Gross Beta Activityin Surface Water

22

38

10. TritiumActivityin Surface.,Water 39

11. Gross Beta Activityin Drinking Water 40

12.

13.

14.

Gross Beta Activityin AirParticulates

Gross Alpha Activityin AirParticulates

Iodine-131 Activityin Milk

47

48

57

Radiolo ical Dose Im act

The extent ofthe 1994 RadiologicalEnvironmental Monitoring Program(REMP) sampling met or exceeded therequirements ofthe Susquehanna SteamElectric Station (SSES) TechnicalSpecifications. The types ofanalysesthat were performed on these samplesfor the identification and quantification .

ofradioactivity also met or exceeded theSSES Technical Specificationrequirements during the 1994 REMP.The result ofthis effort was theverification of the SSES EfnuentMonitoring Program data that indicatethat the SSES operation has nodeleterious efFect on the health andsafety ofthe public or the environment.

The amounts ofthe radionuclides

detected in environmental samplesduring 1994 were so small, as in pastyears, that the maximum whole bodydose or maximum organ dose to a

member ofthe public &om SSESoperation is less than one-tenth ofone .,

percent ofthe dose limits established bythe Nuclear Regulatory Commission(NRC) as stated in 10 CFR 50,Appendix I. The maximum potentialoF-site whole body and organ dosesfrom radionuclides detected by theREMP and attributable to the SSESoperations were calculated to be lessthan 0.003millirem/year and less than0.01 millirem/year, respectively.

By contrast, potassium-40, a very long-lived, naturally occurring radionuclide

P

DOSE COMPARISONSUSQUEHANNA-RELATED VERSUS OTHER SOURCES

consumerMedicdl Products

16% S%

SSES/(0.01%

Ndturdl82%

The above figure shows the whole body dose &om SSES operation relative to theaverage dose to people &om all sources, including natural background, medical, andconsumer products.

1994 Radiological Environmental Monitoring Report

Sum and Conclusions

found in everyone's body, is estimatedto deliver an average annual dose to theblood forming organs ofindividuals inthe United States ofabout 27 millirem.While a small portion ofthe backgrounddose &om natural radiation sources, thepotassium-40 dose is still more than9,000 times the estimated maximumwhole body dose and more than 2,700times the maximum organ dose to ahypothetical member ofthe public &omingestion ofradionuclides attributable tothe SSES.

The maximum direct radiation dosefrom SSES operation to a member ofthe public was determined to be 0.0034millirem/year. The total whole body

'ose &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

Naturally OccurringRadionuclidesIn 1994, the SSES REMP reported thenaturally occumng radionuclidesberyllium-7, potassium-40, radium-226,and thorium-228 in the environment atlevels exceeding the minimum detectableconcentrations tMDCs) for theirrespective gamma spectroscopicanalyses. Beryllium-7 was identified inalgae, sediment, air, precipitation,vegetation, and fruits and vegetables.Potassium-40 was observed in surfacewater, algae, fish, sediment, groundwater, air, precipitation, soil, vegetation,

&uit, game, and eggs. Thorium-228 wasfound in algae, sediment, and soil.,Radium-226 was seen in sediment andsoil. None ofthese results were .

unexpected, and they are not related tothe operation ofthe SSES. Doses &omthe presence ofthese radionuclides werenot included in the estimate ofthe dosefrom SSES attributable radionuclides.

Manmade RadionuclidesAlthough not all due to SSES operation,the followingman-made radionuclideswere reported at levels in theenvironment in excess ofthe MDCs fortheir respective analyses: tritium,manganese-54, cobalt-60, strontium-90,iodine-131, and cesium-137. Allofthese radionuclides, with the exceptionofcesium-137, were identified in surfacewater. Except for tritium andstrontium-90, all ofthese radionuclideswere measured in algae growing in theSusquehanna River. Tritium wasmeasured in all waters analyzed,including drinking water, ground water,airborne water vapor, and precipitation.Strontium-90 was also found in milk.Iodine-131 was identified in drinkingwater. Cesium-137 was observed insediment, soil, and game.

The presence ofthe other man-maderadionuclides were attributed to non-SSES sources. Tritium in media otherthan Susquehanna river waterdownstream ofthe SSES was attributed'o both natural production by theinteraction ofcosmic radiation with theupper atmosphere and previousatmospheric testing ofnuclear weapons.Strontium-90 and cesium-137 wereconsidered to be present only as residualfallout &om atmospheric weaponstesting. Iodine-131 was believed to be

1994 Radiological Environmental MonitorinReport

Summa and Conclusions

found only in the aquatic pathway as theresult ofthe discharge ofmedical wasteto the Susquehanna River throughsewage treatment plants upstream oftheSSES.

Allofthe man-made radionucHdesmentioned above were not analyzed forin all media. For example, no analyseswere performed in an effort to determinetritium or strontium-90 levels in algae.Consideration was given to the potentialimportance ofdifferent radionuclides inthe pathways to man, as well as theregulatory analysis requirements forvarious environmental media, inselecting the types ofanalyses thatwould be performed.

AQUATICPATHWAY

Algae

Manmade:non-SSES Manmade:SSES'.5% 1.1%

Natural97.4%

Sediment

Manmade:no~SES Manmade:SSES0.4% 0.0%

Relative Radionuclide ActivityLevels in Selected MediaSeveral media monitored in theenvironment are significant for thenumbers ofgamma-emitting radionuclides routinelymeasured at levels exceeding analysisMDCs. Thosemedia are algae and sediment in theaquatic pathway and soil in theterrestrial pathway.

Natural99 6%

TERRESTRIAL PATHWAY

Soil

The followingpie graphs show therelative activity contributions for thetypes ofgamma-emitting radionuclidesreported in those media during 1994.

Manrnad:no~SES Manmade:SSES1 5% 00%

Natural98 5%

Naturally occurring radionuclidesaccount for the following percentages ofgamma-emitting activity in the mediadepicted above: algae - 97.4%,sediment - 99.6%, and soil- 98.5%.


Summa and Conclusions

Manmade radionuclides ofnon-SSESorigin account for most ofthe rest ofthegamma-emitting activity in algae and allofthe remaining activity in sediment andsoil. Only 1.1% ofthe gamma-emittingactivity in algae is attributed to theSSES. It should be noted that theactivity for naturally-occurringradionuclides reported in these mediadwarfs the activity ofthe man-maderadionuclides also reported, especiallythose originating &om the SSES.

Dose Significance ofRadionaclidesOfthe six man-made radionuclidesreported in the environment by theSSES REMP above, only tritium,manganese-54, and cobalt-60 were usedin the estimation ofthe dose impactfrom the operation ofthe SSES. Thedose calculations were performed onlyfor the aquatic pathway to man. Thereasons for this were that manganese-54and cobalt-60 were only found insurface water discharged to theSusquehanna River by the SSES andonly tritium in the Susquehanna Riverdownstream ofthe SSES was attributedto SSES operation."

The annual average for tritium activitylevels in the discharge to theSusquehanna River was orders ofmagnitude greater than the annualaverages for manganese-54 and cobalt-60. Nevertheless, the dose contributionfrom the other radionuclides was still asignificant fraction ofthe very smalltotal, because the dose per unit oftritium activity in the body iscomparatively very small.


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 coresofthese nuclear reactors. When verysmall quantities offission productsescape through the cladding ofthecore's fuel rods, they enter the waterwith the activation products circulatingthrough the reactor.

Since the mid-l980s, improvements inthe manufacture ofnuclear fuel,improvements in PP&L's fuelconditioning (to minimize heat stresseson the fuel), reductions in the numbersofreactor scrams (rapid control rodinsertions) that put stresses on the fuel,and maintenance ofgood waterchemistry in the reactors have allcontributed to minimization oftheescape ofradioactive 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 effluents &om theSSES.

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

&action ofthe radioactive materials thatenter the circulating water are vaporizedand others are entrained in the steam,carrying over to the turbines andeventually the condensers. In turn,

'ome fraction 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.

The radioactive material released as

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

kryptons), iodines and particulates, andtritium (a radioactive isotope ofhydrogen) for the purposes oftrackingthe amounts ofradioactive materialbeing released from the SSES andmonitoring the SSES releaseperformance. Reduction ofthe amountsofradioactivity otherwise destined to bereleased with the gaseous effluentdepends on the category into which theradioactive material fits.

Short-lived noble gas activity is reduced

by radioactive'waste processing systemswhich delay the release ofgases to the

. environment to permit them to decayprior to release. Iodine and particulateradioactivity in the gaseous effluent arereduced by adsorption in charcoal bedsand capture in particulate filters,respectively. There is a total of74 tonsofcharcoal distributed in five beds thatthe gaseous effluent must pass throughprior to release. A delay time ofat least


Introduction

41 days for some ofthe gases isexpected 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 eQicient at capturing the iodine.Similarly, the particulate filters areexpected to have capture eQiciencies ofmore than 99.7% for particles 0.3microns or larger in size.

Unfortunately, no practical means yetexists to eliminate tritium &om thegaseous eQluent. Some elimination oftritium in the form oftritiated watervapor by chilling ofthe offgas andsubsequent collection ofthe condensateprior to passage through the charcoaladsorbers does occur. But, the primarypurpose ofthis chilling is to reduce themoisture entering the charcoal beds sothat they willmaintain their efficiencyfor the removal ofiodine.

LiquidEffluentsMaintaining the quality ofwatercirculating through the reactor core at "acceptable levels and capturing waterthat leaks from reactor systems, resultsin the generation ofwaste water at theSSES. This waste water also containsradioactivity that has escaped &om fuelrod cladding. In order to minimize therelease ofthis water to the environment,as much ofit 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.

performance, liquid eQluent radioactivematerials 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, andpassing it through ion exchangematerial, similar in function tohousehold water sofieners. Thesemethods are effective to varying degreeswith all ofthe radioactive materialsexcept tritium, which can't be removed&om water by either method. For mostradionuclides, the ion exchange mediamay be expected to have a removalefficiency ofroughly 99%.

Controlling Radioactive ReleasesNRC regulations (10 CFR 50.34 and 10CFR 20.1c) require that nuclear powerplants be designed, constructed, andoperated to keep levels ofradioactivematerials in eQluents 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 eQluents.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 ofthe SSES; doses are kept as

much below these actual limits as

possible.

For the purpose oftracking radioactivereleases and monitoring SSES release

The NRC release limits are far below-theapproximately 300 millirem dose

1994 Radiological Environmental MonitoringReport

Introduction

received on average each year byresidents ofthe United States from allnatural background sources. On theother hand, the allowable limits are farabove the doses estimated for the levelsofradioactivity actually being releasedRom the SSES. The actual doses aretypically in the thousandths ofonemillirem or less per year ofSSESoperation. Such doses are far below thelevels at which any sects would beexpected to be observed in the exposedpopulation.

MonitoringReleasesRoof top vents from which gaseousreleases take place are continuouslymonitored to detect any excessive ratesofradioactivity release that might occurwell before any release limits arereached. Discharge rates ofradioactively contaminated water to theSusquehanna River are carefullycontrolled to remain as far below thedischarge limits as possible also.Discharges are monitored by radiationdetectors so that iflevels ofradioactivityin the water would inadvertentlyapproach the limits ofpermissible levels,the discharges could be stopped quickly.

Radiological EnvironmentalMonitorin

In addition to the steps taken to controland to monitor radioactive e61uentsfrom the SSES, the SSES TechnicalSpecifications also require a program forthe radiological monitoring oftheenvironment in the vicinityofthe SSES.The objectives ofthe SSES REMP areas follows:

~ Fulfillment ofSSES TechnicalSpecifications'adiologicalenvironmental surveillanceobligations,.

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

operations,

~ Assessment ofdose impacts to the..public, ifany,

~ Verification ofadequate SSESradiological e61uent controls, and

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

PAL has maintained a RadiologicalEnvironmental Monitoring Program(REMP) in the vicinityofthe 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 p'rimarily rural, consistingpredominately offorest and agriculturallands. (More specific information on thedemography, hydrology, meteorology,and land use characteristics ofthe areain the vicinityofthe SSES can be foundin the Environmental Report (14), theFinal Safety Analysis Report (15), andthe Final Environmental Statement (16)


Introduction

for the SSES.) The purpose ofthepreoperational REMP (April, 1972 toSeptember, 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 operation.

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 PP&L for theSSES exceeds the monitoring suggestedby the NRC's branch technical position,as well as the requirements ofthe SSESTechnical Specifications in terms ofthenumber ofmonitoring locations, thefrequency ofcertain monitoring, thetypes ofanalyses required for thesamples, and the achievable analysissensitivities.

Potential Exposure Patlw ays„The following three mechanisms exist bywhich a member ofthe public has thepotential to be exposed to radioactivityor radiation from nuclear powerplants such as the SSES:

~ inhalation (breathing)

~ ingestion (eating and drinking), and

~ whole body irradiation directly froma plant or from immersion inairborne efHuents.

The three pathways through whichradioactive material may reach thepublic from nuclear power plants are theatmospheric, terrestrial, and aquaticpathways. (Figure 1 on page 11 depictsthese pathways for the intake ofradioactive materials.) Comprehensiveradiological environmental monitoringmust sample media from all ofthesepathways.

REMP ScopeThe SSES REMP collects nearly 2,000samples &omwell over 100 locationsand performs thousands ofanalyses onthese samples annually. The mediamonitored and analyses performed aresummarized in the table on the followingpage.

The environmental monitoring locationsare classified as either indicator orcontrol locations. Indicator locationsare those at which radioactive materialor radiation from the SSES might beexpected to be detectable if present.These locations are selected primarily onthe basis ofproximity to the SSES,although other factors such as

meteorology; topography, and samplingpracticality may be important as well.Control locations are those sites whereit is considered unlikely to detectradioactive material or radiationresulting from normal SSES operation.Figures 2 through 7 on pages 12through 17 display the REMPthermoluminescent dosimeters (TLDs)and sampling locations in the vicinityofthe SSES. Appendix C providesdirections, distances, and a briefdescription ofeach ofthe locations inFigures 2 through 7.


introduction

Regulatory agencies also participate inmonitoring the SSES environment andalso oversee PP&L's monitoring efForts.The State ofPennsylvania's DepartmentofEnvironmental Resources (PADER)monitors air for radioactive particulatesand radioactive iodine, milk, fruits andvegetables, surface and drinking water,fish, river sediments, and ambientradiation levels. PADER makes thisdata available to the NRC. The NRCalso conducts an independent

REMP MonitoringSensitivityThe sensitivity ofthe 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 ofsome specific radioactivematerials that are not normally observed.

e ofMonitorinSSES REMP

Media MonitoredGross Alpha Activity

Gross Beta Activity

AllWaters, AirParticulates, &Coarse &Flocculated SedimentAllWaters, AirParticulates, Coarse &Flocculated Sediment &Fish

Gamma-Emittin Radionuclide Activities AllMediaTritium ActiviIodine-131 Activity

Strontium-89/90 ActivitiesExposure Rates

TLD &Pressurized Ion Chamber

AllWatersSurface Water, Drinking Water, Air&MilkMilkAmbient

monitoring program ofthe 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, observeactivities first-hand, and generallyexamine the programs supporting theeffluent and environmental monitoringfor the SSES.

Detection ofradiation and radioactivematerial from the SSES in theenvironment 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 previous nuclearweapons tests and medical wastes.Together, this radiation and radioactivematerial present background levels fromwhich an attempt is made to distinguishrelatively small contributions from the

1994 Radiological Environmental Monitoring Report 9

Introduction

SSES. This effort is complicated by thenatural variations that typically occurfrom both monitoring location tolocation and with.time.

The naturally occurring radionuclidespotassium40, 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 as

meat, fish, and Suits and vegetables.Seasonal variations in beryllium-7 in airsamples are regularly observed. Man-made radionuclides, such as cesium-137and strontium-90 leftover from nuclearweapons testing are often observed aswell. In addition, the radionuclidetritium, produced by both cosmicradiation interactions in the upperatmosphere as well as man (nuclearweapons), is another radionuclidetypically observed.

to 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.Suminary descriptions ofthe analyticalprocedures and the accompanyingcalculational methods used by thelaboratory can be found in Appendix E.

'adioactivity

levels in environmentalmedia are usually so low that theirmeasurements, even with state-of-the-art measurement methods, typically have .

significant degrees ofuncertaintyassociated with them.(18) As a result,expressions are often used whenreferring 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 ofthe MDC for a specificmeasurement is compared to the valueofthe actual measurement, thecomparison provides information aboutthe difficultyin dIfferentiating theactivity being measured frombackground activity. The formulas used

10 1994 Radiological Environmental Monitoring Rcport

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1994 TLD MONITORING LOCATIONS

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FIGURE 31994 TLD MONITORING LOCATIONS

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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 ofradiation by absorbing a

portion ofthe 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 andmeasuring the intensity ofthe light thatthey emit. The intensity ofthe emitted

'ightis proportional to the amount ofradiation to which they were exposed.Calibration ofthe TLD processorspermits a reliable relationship to beestablished between the light emittedand the amount ofradiation dosereceived by the TLD's; the resultpermits accurate measurements oftheambient radiation in the environment.

Environmental TLDs are continuallyexposed to natural radiation from theground (terrestrial radiation) and fromthe sky (cosmic) radiation. In addition,they 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 affecting 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) &om the SSES turbinebuildings during operation, radwastetransfer and storage, and radioactivegaseous eEuents &om 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 ofradiation, as well as naturalradiation sources. It also provides ameans for attributing a portion ofthetotal TLD dose to SSES operation ifappropriate. Appendix E, pages E-6through E-10, provides a description ofthe process for evaluating the results ofTLD measurements.

1994 Environmental Radiological Monitoring Report 18

Ambient Radiation Monitorin

~sco e

TLDsThe area around the SSES was dividedfor monitoring purposes into sixteensectors radiating outwards &om theplant site, each encompassing an areadescribed by an arc of22.5 degrees.TLDs were placed in all 16 sectors atvarying distances &om 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 beginning of 1994, the SSESREMP had 85 indicator TLD locationsand seven control TLD locations. Thislevel ofmonitoring 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 amember ofthe public would be able toapproach the station. The control TLDsare the most distant from the SSES,ranging from 10 to 20 miles from thesite. Changes were made to a number ofTLD locations at the beginning ofthe1994 fourth calendar quarter. (Refer toAppendix A for a description ofthesechanges and the reasons for them.)

In addition, TLDs were placed for thefirst two calendar quarters ofthe year atfour different locations wherepressurized ion chambers (PICs) arestationed. The purpose ofthese TLDs

was to permit the comparison ofexposure measurements made by thePICs with those obtained &om theTLDs. These TLDs were positioned atthe same elevations as the PICs, whichdiffered significantly &om the elevationsat which the other environmental TLDsare positioned. For this reason, theexposures measured by the PIC co-located TLDs were not averaged withthose &om the environmental TLDs.

=PICs .

Pressurized 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 1994. Nanticoke was thecontrol location.

The PIC data were collected and storedby dataloggers for periods ofapproximately one month during 1994and analyzed. The dataloggers wereprogrammed to provide hourly resultsfor each monitoring period. From thisinformation, overall hourly averageswere obtained for each monitoringperiod.

Monitorin Results

TLDsTLDs were retrieved and processedquarterly in 1994. Average ambient

~ . radiation levels measured byenvironmental TLDs increased duringeach. successive quarter of 1994 at bothindicator and control locations as shownin the figure below. Refer to Figure 8on page 22 which trends both indicatorand control data quarterly &om 1973through 1994.

19 1994 Environmental Radiological Monitoring Report


1994 REMP Quarterly TLDAverages

15

10ee

c2

1 2

ga

Calendar Quarters

@%Ax)+erh~y~g@a) . ax~<>x~%%~Q'Qg~x n

i'"4@~+ @hdioator

g Control

The first quarter averages for indicatorand control locations were exceptionallylow, apparently due to the unusuallylong period ofsnow cover during theearly part of 1994. Pressurized ion-chamber (PIC) average exposure ratesfor February and March also wereunusually low as well.

The 1994 annual average exposures forindicator and control locations were14.7+ 2.3 mPJstd. qtr. and 14.8 2 2.0mR/std. qtr., respectively. Theseexposures were 0.8 mR/std. qtr. and 1.1

mR/std. qtr. below the 1993 averageexposures for indicator and controllocations. However, ifthe 1994 firstquarter exposures were not averagedwith the remaining 1994 quarters, theindicator and control averages for theremainder ofthe year each are within0.1 mR/std. qtr. of the corresponding1993 averages. Refer to Figure 8 at theend ofthis section which trendsquarterly TLD results for bothpreoperational and operational periodsat the SSES. Refer to Appendix H,Table H 1, page H-3 for a comparisonofthe 1994 mean indicator and control

TLD results with the means for thepreoperational and prior operationalperiods at the SSES.

When indicator environmental TLDresults for 1994 were examinedquarterly on an individual location basisand compared with both current controllocation results and preoperational data,very small SSES exposure contributionswere suggested for some onsitelocations identified in the table below.It is possible that these SSESattributable exposures were actually notthe result ofSSES operations, but, infact, resulted Rom fluctuations inbackground radiation levels. Refer toAppendix E, page E-6, for a discussionof"TLDData Interpretation." TLDresults for all locations for each quarter

, of 1994 maybe 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 3.37 E-3 millirem at anonsite monitoring location, 11S3, 0.3mile southwest ofthe SSES. This dose

1994 Environmental Radiological Monitoring Report 20


was used for determining compliancewith SSES Technical SpecificationLimit3.11.4 for annual eQluentreporting purposes.

PICsPIC data for 1994 resulted in annualaverages for indicator and control

the TLDs.) Comparisons ofchanges inPIC and TLD data are probably mostuseful in the sense that increases ordecreases in either TLD or PIC datamay be confirmed by similar changes inthe other.

1994 ENVIRONMENTALTLDMONITORINGLOCATIONS%ITH SSES ATTRIBUTABLE

EXPOSURES"Calendar Quarters

6S49S210S2llS3

9S211S312S4

13S2

9S210S2llS312S413S2

9S211S3

~A11 ofthese locations are on the SSES site.

locations of 17.2 mR/std. qtr. and16.5 mR/std. qtr., respectively. Thesemeans are 0.7 and 1.5 mR/std. qtr.below the indicator and control means,respectively from 1993. Similar to thedrop in TLD means for 1994, thedecline in PIC means can be attributed,at least, in part to the snow covering theground during the months ofFebruaryand March. When 1994 PIC data isexamined on a monthly basis,significantly lower averages for themonths ofFebruary and March areobservable.

Comparisons ofthe absolute TLDmeasurements with the absolute PICmeasurements must consider thesignificant differences in the above-ground elevations ofPICs andenvironmental TLDs. (PICs are locatedat higher above-ground elevations than

21 1994 Environmental Radiological Monitoring Report

AMBIENTRADIATIONLEVELSBASED ON TLD DATA

Exposure Rate (mR/STD QTR)50

45—

40—

35—

30—

25—

20—

15—

10—

PREOPERATIONAL OPERATIONAL

UNIT 2CRITICALITY

I I

—Indicator —Control

I I

1973 1975 1977 1979 1981 1983 1985 1987 1989 1991 1993 1995

INTRODUCTION

The followingmedia were monitored in1994 by the SSES REMP in the aquaticpathway: surface water, drinking water,algae, fish, and sediment. Some ofthemedia ( e.g., drinking water and fish)provide information that can beespecially useful to the possibleestimation ofdose to the public from

'otentiallyingested radioactivity, ifdetected. Other media (e.g,, algae andsediment) can be useful for trendingradioactivity levels in the aquaticpathway primarily because oftheirtendency to assimilate certain materialsthat might enter the surface'water towhich they are exposed. The resultsfrom monitoring all ofthese mediaprovide a picture of the aquatic pathwaythat is more clear than that which couldbe obtained ifone or more were notincluded in the REMP.

Fruits or vegetables that are grown infields irrigated with surface water wouldalso be in the aquatic pathway. A landuse census (Reference 49 on page 65)conducted in 1994 identified no farmswithin 10 miles downstream oftheSSES as having irrigated during the1994 growing season due to,theabundance ofrain during the summer.

locations serve as controls to providedata for comparison with downstreammonitoring results. The potential existsfor radioactive material that might bepresent in SSES airborne releases to

'nterthe Susquehanna River upstreamofthe plant through either directdeposition (e.g., settling or washout) orby way ofrunofF &om deposition onland adjacent to the river. Directdeposition and runoffare considered tobe potentially insignificant as means ofentry for SSES radioactivity into theSusquehanna River when compared toliquid discharges under normalconditions.

Lake Took-a-While (LTAW),which islocated in PP&L'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 of aquatic monitoring and theREMP, in general, goes beyond itsrequirements by monitoring LTAW.

The aquatic pathway in the vicinityofthe SSES is the Susquehanna River.Monitoring ofall ofthe aquatic media,except drinking water, is conducted bothdownstream and upstream of thelocation from which occasional SSESlow-level radioactive discharges enterthe river. 'he upstream monitoring


A uatic Path~ Monitorin

~Sco e

Surface WaterSurface water was routinely sampled&om the Susquehanna River at Gveindicator locations (6SS, 6S7, 12Fl,

'2G2,and 12H1) and two controllocations (1D3 and 6S6) during 1994.

Drinking WaterDrinking water RAW and TREATEDsamples were collected at location12H2, the Danville Municipal WaterAuthority's treatment facilityon theSusquehanna River, in 1994. RAWdrinking water is obtained &om the riverwater inlet to the facility, prior to anywater processing. TREATED water iscollected &om the end ofthe processingflowpath, representing Gnished waterthat is suitable for drinking. This is thenearest point downstream ofthe SSESdischarge to the River at which drinkingwater is obtained. No drinking watercontrol location is sampled. For allintents and purposes, control surfacewater sampling locations would besuitable for comparison.

AlgaeAlgae samples were collected monthly(river conditions permitting) from oneindicator location, AG4, near the SSESliquid discharge point to theSusquehanna River and at one controllocation, AG3, upstream ofthedischarge.

FishFish were sampled from theSusquehanna River in the spring and fallof 1994 at one indicator location, IND,downstream ofthe SSES liquiddischarge to the River and one control

location, 2H, sufmciently upstream toessentially preclude the likelihood thatthe fish caught there would spend anytime below the SSES discharge. Inaddition, fis were also sampled fromPP&L's Lake Took-a-While, locationLTAW. This location is notdownstream ofthe SSES discharge. Itis sampled because ofits potential forreceiving runofF &om 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 2Band 2F on the Susquehanna River. Inaddition, sediment was also obtainedfrom location LTAW.

Sam lin

Surface WaterWeekly grab sampling was performed atthe indicator location 6SS. 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 &om theautomatic sampler at this location.Nevertheless, 6SS was sampledroutinely throughout 1994, 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 twenty minutes. Weekly,the water obtained by these samplers

24 1994 Radiological Environmental Monitoring Report

A uatr'c Path~ Monitorin

was retrieved for either biweekly ormonthly compositing. Compositesampling also was performed at location12H1, the Merck Chemical Company,by Merck personnel.

The other surface water monitoringlocations (1D3, 12F1, 12G2, andLTAW)were grab sampled once eachmonth.

Drinking 8'aterRAW drinking water samples were, ~

collected at location 12H2 timeproportionally by an automaticcontinuous sampler. The sampler wasset to obtain 30-60 ml aliquots everytwenty minutes. Weekly, the waterobtained by this sampler was retrievedfor either biweekly or monthlycompositing. TREATED water at 12H2was obtained by Danville MunicipalWater Authority personnel daily in theforni ofone liter grab samples, whichwere composited and retrieved weekly.

AlgaeAlgae was collected passively byallowing the Susquehanna River's *

natural flow to deposit it on plexiglasscollectors. Algae collectors were onlyplaced in the River from the springthrough the fall (typically a period offive or six months).'ampling at othertimes ofthe year was impractical due tothe risk of losing samplers because of iceand other debris in the River. Algaegrowth and, thus, the potential for theuptake ofany radionuclides that mightbe in the river water during such periodsis reduced because ofthe shorter daysand colder temperatures.

Fish, Fish were obtained by electrofishing

which stuns the fish and allows them toQoat to the surface so that fish ofthedesired species and suf5cient size can besampled. Pish sampled 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, obtained to depthsoffour 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 shifted bythe water. It is composed offinerparticles than the shoreline sediment,and is believed to be more in touch withwater, giving it the potential to pick upany radionuclides that the water may becarrying more easily.

Sample Preservationand Anal sis

Surface and Drinking 8'aterSurface 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 ofthesesample analyses, preservatives were


A uatic Pathw Monitorin

added to the samples as soon aftercollection as practical. Nitricacid 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 ofthe 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.

Algae, Sediment, and FishAlgae is dried, pulverized, and passedthrough a sieve prior to being sent for,analyses. Fish and sediment are frozenuntil shipment. Allsamples are analyzed

by gamma spectroscopy for the activitiesofany. gamma emitting radionuclidesthat may be present. Fish and sedimentare also analyzed for gross beta activitylevels. In addition, sediment is analyzedfor its gross alpha activity level. Theseanalyses would be ofbenefit in theunlikely event that man-made non-gamma emitting radionuclides mightappear in these media without thesimultaneous occurrence ofdetectableman-made gamma-emittingradionuclides. In addition, elevatedgross alpha or beta activity levels could

indicate the need for more sensitivegamma measurements to be performed.

Monitorin Results

Surface 8'aterResults from specific sample analyses ofsurface water may be found in Tables I 2and I 3 ofAppendix I. A summary ofthe 1994 surface water data may belocated on pages 1 and 2 ofTable G in"Appendix G. Comparisons of 1994monitoring results with those ofpastyears may be found in Tables H 2through H 5 on pages H-3 and H-4 ofAppendix H.

Because data from four indicatormonitoring locations (6SS, 12F1, 12G2,and 12H1) on the Susquehanna Riverdownstream ofthe SSES, data fromLTAW,and data from the SSES coolingtower blowdown discharge (CTBD) lineto the river, location 6S7, are averagedtogether, the means obtained for analysisresults do not represent ofthe activitylevels in the river at locationsdownstream ofthe SSES as well as

might be desired. (SSES TechnicalSpecifications currently require that theCTBD, location 6S7, be sampled.) Thedata averaging is required for thepurpose ofannually reportingenvironmental measurements to theNuclear Regulatory Commission (NRC)as either indicator or control means.However, technically, the samplesobtained from the Susquehanna Riverare truly samples from the environment,while the CTBD samples actually shouldbe considered effluent samples. (TheCTBD line is a below ground pipe towhich the public does not have access.)

26 1994 Radiological Environmental MonitoringReport

A uatic Pathma Monitorin

Batch discharges ofslightlyradioactively contaminated water aremade to the SSES CTBD throughoutthe year. Flow rates &om the tanksbeing discharged to the CTBD are keptbelow a maximum rate of200 gpm toensure adequate dilution by the CTBDwater prior to being released to theSusquehanna River. To be assured thatsufficient dilution ofradioactivelycontaminated water takes place prior toentering the Susquehanna River aminimum flow rate of5,500 gpm ismaintained for CTBD water for theduration ofall releases.

Results'from location 6S7, the CTBDline, indicate the concentration oftheactivity ofthe water that is periodicallydischarged to the Susquehanna River.The activity levels or concentrations atthis sample location are not likely to berepresentative ofthe activities in theriver water more than a few feet fromthe diffuser through which the CTBDdischarge enters the river. The diffuseris a pipe with numerous holes in itpositioned near the bottom ofthe river.CTBD discharges exit the'diffuserthrough the many holes to enhancemixing ofthe discharge with the riverwater. The concentrations ofcontaminants are reduced significantlyas the discharged water mixes with theriver water. The much larger flow rateofthe river significantly dilutes thewater being released through thediffuser. The mean flow rate oftheSusquehanna River in 1994 wasapproximately 9,200,000 gpm. This ismore than 1,500 times the requiredminimum discharge rate from the CTBDthrough the diffuser when releases areoccurring. Consequently, the followingdiscussions ofsurface water monitoring

results in terms ofindicator meansshould consider the effect oflocation6S7 data, representing discharge waterrather than river water, in inflatingaverages.

The 1994 data for gross beta activityanalyses ofsurface water are similar tothose of 1993. The 1994 mean grossbeta activity of5.6 pCi/liter for indicatorlocations is essentially the same as the ..5.5 pCi/liter for the 1993 indicator meangross beta activity. Both ofthese meanactivities are approximately the same as

the average ofthe annual means for theprevious operational period oftheSSES, but higher than the range ofannual means for the preoperationalperiod. The 1994 mean gross betaactivity of3.4 pCi/liter for controllocations is lower than the 3.9 pCi/literfor the 1993 control mean gross betaactivity and also slightly lower than theaverages ofthe annual means for theprevious operational and preoperationalperiods. Refer to Figure 9 on page 38which trends gross beta activitiesseparately for surface water indicatorand control locations quarterly from1975 through 1994.

Comparison ofthe 1994 indicator meanto the 1994 control mean as well as

comparison ofthe 1994 indicator meanto the average ofannual means forindicator locations during thepreoperational period indicates acontribution ofbeta activity from theSSES. This is primarily because of theinfluence ofthe gross beta activities .

measured in samples obtained &omindicator location 6S7, the SSEScooling tower blowdown discharge(CTBD) line, on the average ofallindicator locations.

1994 Radiological Environmental Monitoring Rcport 27

A uatic Pathwa Monitorin

Ifgross beta activities measured for 6S7samples are excluded &om thecalculation ofthe 1994 mean gross betaactivity for indicator locations, the meanindicator activity drops &om 5.6pCi/liter to 3.9 pCi/liter. This meanactivity is more representative ofthegross beta activity in river waterdownstream ofthe SSES than the meanindicator activity with data &om location6S7 included. This mean activity isessentially the same as the average ofthe annual mean gross beta activities forcontrol locations at sites upstream oftheSSES during the preoperational period.Thus, the activity discharged to theSusquehanna River by the SSES hasbasically no measurable impact on thegross beta activity levels oftheSusquehanna River.

The 1994 means for iodine-131 activityindicator and control surface watermonitoring locations were both 0.1pCi/liter. The 1994 indicator meaniodine-131 activity is lower than 1993'scorresponding mean activity. The 1994control mean iodine-131 activity is the.same as 1993's control mean activity.Both 1994's indicator and control meanactivities are less than the averages ofthe annual means for both indicator andcontrol locations for both the prioroperational period ofthe SSES as wellas the preoperational period.

Throughout the course ofa year, iodine-131 is typically measured at levels inexcess ofanalysis MDCs in somesamples obtained &om control surfacewater monitoring locations on theSusquehanna River upstream oftheSSES as well as indicator locationsdownstream ofthe SSES. As

determined by measurements ofsamplesobtained by the SSES REMP, the meaniodine-131 activity level &om the CTBDfor all of 1994 was approximately 0.3pCi/liter. This may be compared to theactivity level of0.1 pCi/liter for controlsurface water monitoring locations in1994.

Iodine-131 &om 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 ofthe 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 Gve times theconcentrations in the river waterentering the basins, based on pastmeasurements. This concentratingeFect occurs because ofthe evaporationofthe water in the basins, leaving behindmost dissolved and suspended materialsin the unevaporated water remaining inthe basins. Ifa concentration factor of .

four for iodine-131 were to be appliedto the 1994 mean iodine-131 activitylevel for the control samples from theSusquehanna River, a meanconcentration of0.4 pCi/liter for iodine-131 in the basin water and the waterbeing discharged from the basins wouldbe expected. The actual 1994 mean forthe CTBD iodine-131 activity level wasless than this.

Because iodine-131 is radioactive,unlike the calcium that has beenmeasured, iodine-131 is removed &omthe water while it is in the basins



through 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 tim'e for the waterin 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 for waterin 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, asizable portion ofthe difference betweenthe 1994 mean iodine-131 activity ofabout 0.3 pCi/liter in the CTBD and the1994 mean iodine-131 activity for thecontrol locations of0.1 pCi/liter may beaccounted for through concentration inthe basins.

is the highest'annual mean reported forthe entire operational period oftheSSES as well as the preoperationalperiod. The 1994 control mean is thelowest annual mean reported for bothprior operational and preoperationalmonitoring periods. Refer to Figure 10

on page 39 which trends tritium activitylevels separately for surface waterindicator and control locations &om1972 through 1994.

The 1994 indicator mean tritium levelfor all surface water locations can bemisleading for those interested in themean tritium level in the SusquehannaRiver downstream ofthe SSES for1994. The much higher levels oftritiumobserved in the CTBD gocation 6S7),when averaged with the low levels &omthe downstream sample analysis results,distort the real environmental picture. Ifthe tritium activities from location 6S7are excluded &om the data used tocalculate the 1994 indicator meantritium activity level for surface water,the mean becomes 66 pCi/liter.

No iodine-131 was identified in SSESliquid eEuent during 1994. None oftheiodine-131 activity measured in excessof the analysis MDCs in environmentalsurface water samples in 1994 isattributed to SSES operation.

The 1994 mean tritium activity forindicator locations was approximatelytwice the corresponding 1993 mean,while the 1994 mean tritium activity forcontrol locations remained essentiallythe same as the 1993 control mean. The1994 means for tritium activity atindicator and control locations were1,068 pCi/liter and -5 pCi/liter,respectively. The 1994 indicator mean

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 during .

1994 was 8,590 pCi/liter for the secondquarter, well below, the NRC non-routine reporting levels for.quarterly,average activity levels of20,000pCi/liter when a drinking pathway existsor 30,000 pCi/liter wh'en no drinkingwater 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 ofthis section foradditional information on the projecteddose to the population &om tritium andother radionuclides in the aquaticpathway attributable to the SSES.

Strontium-90 activity was measured inexcess ofthe analysis MDC once by theREMP analysis laboratory at the verylow activity level of0.58 2 0.21 pCi/literin a sample for the period March 7through April4, 1994 &om the

CTBD,'ocation

6S7. Strontium-90 is not .. „

routinely identified in surface watersamples in general or CTBD samples in,particular. Generally, surface watersamples are not analyzed for the activityofstrontium isotopes.

Surface water samples only are analyzedfor possible strontium-89/90 activity inthe event that higher than normal levelsofgross beta activity are observed insurface water samples that can't beexplained by the presence ofotherradionuclides emitting both beta andgamma radiation. This situation occursinfrequently for surface water samples ingeneral. Seven samples from theCTBD, location 6S7, were analyzed forstrontium-89/90 in 1994.

When nonroutine strontium analyses areperformed, no strontium-89 orstrontium-90 activity is usuallymeasured above analysis MDCs.

'owever,strontium-90, a long-lived(half-lifeofabout 28 years)radionuclide, is present in theenvironment as the result offallout fromprevious atmospheric nuclear weaponstests. It can be routinely measured inmilk samples for example.

Because strontium-89, a relatively short-lived (half-lifeofabout 50 days)radionuclide, was not reported at a levelin excess ofthe analysis MDC in thewater sample Rom March, 1994, it isnot considered likely that the source ofthe strontium-90 in that sample was theSSES. Fresh strontium-90 from theSSES would be expected to beaccompanied by strontium-89.

No strontium analyses were performed. on surface water control samples for theMarch, 1994 period. However, thenormal gross beta activity levels inMarch's control samples did not suggestthat strontium-90 would be likely tohave been measurable in them.Nevertheless, the isolated report ofstrontium-90 in the 6S7 sample appearsto have been most probably the result ofresidual strontium-90 Rom old fallout.SSES eQluent monitoring for this perioddid not include measurable levels ofeither strontium-89 or strontium-90.

Strontium typically tends to be relativelyinsoluble in its usual forms in water. Itis possible that the strontium-90 in thesample was contained in suspended.sediment that had been deposited in thecooling tower basins or CTBD line inthe past from water taken from theSusquehanna River upstream oftheSSES for cooling purposes. Thestrontium-90 might then have becomeresuspended with the sediment in the

. water prior to'sampling due to aphenomenon such as turbulent waterflow. This strontium-90 would then befrom previous nuclear weapons tests.No strontium-90 was reported in SSESefHuent in March, 1994. The strontium-90 identified in the March CTBD (6S7)



sample is not attributed to SSESoperation.

The only gamma-emittingradionudides measured in surfacewater at activity levels exceedinganalysis MDCs in 1994 were naturallyoccurring potassium-40 and manmademanganese-54 and cobalt-60.Potassium-40 was seen above analysisMDCs in five samples during 1994.Manganese-54 and cobalt-60 were bothobserved above analysis MDCs in onlyone sample from location 6S7, a grabsample collected on January 10, 1994.

Neither manganese-54 nor cobalt-60have been measured above analysisMDCs in surface water samples since1988, when manganese-54 was foundabove its analysis MDC in one samplefrom the CTBD line at location 6S7.The last time that cobalt-60 wasmeasured above analysis MDCs was in1987, when it was observed in twosamples from the CTBD line at location6S7. Both manganese-54 and cobalt-60were measured in excess ofanalysisMDCs in samples from the CTBD line inthe years 1983, 1985, 1986, and 1987.During the preoperational period, onlycobalt-60 was measured above ananalysis MDC in one downstreamsample in 1981.

The activity levels ofmanganese-54 andcobalt-60 in the 1994 sample werereported as 47 pCi/liter and 24 pCi/liter,respectively. The highest-levelspreviously were reported in 1983 whenmanganese-54 was reported at 45pCi/liter and cobalt-60 was reported at12.8 pCi/liter in CTBD line samples. Allofthe reported manganese-54 and,cobalt-60 is attributable to the SSES

operation. Refer to the "Dose &om theAquatic Pathway" discussion at the end

ofthis section for additional informationon the projected dose to the population&om tritium and other radionuclides inthe aquatic pathway attributable to theSSES.

Drinking 8'aterDrinking water was monitored during1994 at the Danville Water Company's ..

facility26 miles WSW ofthe SSES onthe Susquehanna River. From 1977

(when drinking water samples were firstcollected) through 1984, drinking watersamples were also obtained &om 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 drinking water supplies onthe Susquehanna River upstream oftheSSES 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 in Table I4 ofAppendix I. A summary ofthe1994 drinking water data may be locatedon pages 2 and 3 ofTable G inAppendix G. Comparisons of 1994monitoring results with those ofpastyears may be found in Tables H 6through 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


A uatic Pathar Monitorin

small minority ofthe samples duringmost years since 1980. In 1994, onlyfour samples out of38 had gross alphaactivity levels above the analysis MDCs.The 1994 mean gross alpha activity levelfor drinking water was 0.2 pCi/liter.The 1994 mean alpha activity is thesame as the mean for 1993 andsignificantly below the averages ofthecorresponding annual means for both theprior operational years as well as thepreoperational period. The mean grossalpha activity is lower than the means of ..most ofthe previous years because ofthe averaging method used since 1991.

The 1994 mean gross alpha activity fordrinking water is less than the 1994gross alpha activity level of0.3 pCi/literfor surface water control locations. Nogross alpha activity in drinking waterduring 1994 is attributed to liquiddischarges &om the SSES to theSusquehanna River.

Gross beta activity has been monitoredin drinking water since 1977. Grossbeta activity is typically measured atlevels exceeding the MDCs in drinkingwater samples. The 1994 mean grossbeta activity level for drinking water was2.5 pCi/liter. The 1994 mean is belowthe 1993 mean gross beta activity levelfor drinking water and also below theaverages ofthe corresponding annualmeans for the prior operational andpreoperational periods ofthe SSES.Refer to Figure 11 on page 40 whichtrends gross beta activity levelsseparately for drinking water indicatorand control locations from 1977 through1994.

The 1994 mean gross beta activity fordrinking water is less than the 1994

gross beta activity level of3.4 pCi/literfor surface water control locations. Nogross beta activity in drinking waterduring 1994 is attributed to liquiddischarges &om the SSES to theSusquehanna River.

Iodine-131 was measured in excess of'he

analysis MDCs in only nine drinkingwater samples in 1994. This is the samenumber that exceeded analysis MDCs asin 1993. The 1994 mean iodine-131activity.level in drinking water sampleswas 0.07 pCi/liter. This is slightly lessthan both the 1993 mean drinking wateractivity level of0.1 pCi/liter and the1994 mean of0.1 pCi/liter for surfacewater control locations. No iodine-131activity in drinking water during 1994 isattributed to liquid discharges &oin theSSES to the Susquehanna River.

Tritiumwas measured in excess oftheanalysis MDCs only once in 1994. The1994 mean tritium activity level fordrinking water was 20 pCi/liter. The1994 mean tritium activity level issignificantly higher than the 1993 meanof 1.5 pCi/liter, but less than theaverages of the corresponding annualmeans for both the prior operational andpreoperational periods ofthe SSES. Themean tritium activity is lower than themeans ofmost ofthe previous yearsbecause of the averaging method used'since 1991.

The low 1994 mean tritium activity levelfor drinking water is higher than the1994 mean tritium activity level of-5.pCi/liter for surface water controllocations. This diQerence is probablydue to liquid discharges &om the SSESan is, therefore, attributable to the SSESoperation. The very small dose resulting



to the public has been accounted for byestimations based on the levels oftritiummeasured by the REMP during 1994 inthe CTBD line which discharges to theSusquehanna River. Refer to the "Dose&om the Aquatic Pathway" discussion atthe end ofthis section ("AquaticPathway Monitoring") ofthis report.

No gamma-emitting radionuclides weremeasured above the analysis MDCs forgamma spectroscopic analyses ofdrinking water samples during 1994.

AlgaeResults from specific sample analyses ofalgae maybe found in Table I 5 ofAppendix I. A summaty ofthe 1994algae data may be located on pages 4and 5 ofTable G in Appendix G.Cemparisons of 1994 monitoring resultswith those ofpast years may be found inTables H 9 through H 15 on pages H-5and H-6 ofAppendix H.

The following seven gamma-emittingradionuclides were measured at activitylevels in excess ofanalysis MDCs insome or all ofthe six monthly algaesamples collected from May throughOctober 1994: beryllium-7, potassium-40, manganese-54, cobalt-60, iodine-131, cesium-137, and thorium-228.With the exception ofthe manmaderadionuclides manganese-54 and cobalt-60, the naturally occurring radionuclidesberyllium-7, potassium40, and thorium-228, as well as the manmaderadionuclides iodine-131 and cesium-137 were found at both the indicatormonitoring location, AG-4, and thecontrol monitoring location, AG-3.

¹turally occumng beryllium-7 andpotassium40 were found at activity

levels exceeding analysis MDCs in allalgae samples in 1994 and naturallyoccumng thorium activity levelsexceeded analysis MDCs in all but one1994 sample. The 1994 indicator andcontrol means for beryllium-7 activitylevels were essentially identical at 5.3

pCi/gram and 5.4 pCi/gram,respectively. These 1994 means forberyllium-7 were somewhat below boththeir corresponding 1993 means as well..as the averages oftheir correspondingannual means for prior operationalyears. The 1994 indicator and controlmeans for potassium-40 activity levelswere 20.9 pCi/gram and 19.1 pCi/gram,respectively. These 1994 means forpotassium40 were well above both theircorresponding 1993 means as well asthe averages oftheir correspondingannual means for prior operationalyears. The 1994 potassium-40 means arealso above the corresponding ranges forprior annual means. The 1994 indicatorand control means for thorium-228activity levels were 1.2 pCi/gram and0.8 pCi/gram, respectively. The 1994indicator mean thorium-228 activity isslightly larger than the 1993 indicatormean, while the 1994 control mean isthe same as its 1993 counter part.Nevertheless, both the 1994 indicatorand control means for thorium-228 inalgae are below the averages oftheircorresponding annual means for all prioryears. The 1994 control mean is at thelow end ofthe range ofprevious annualmeans.

Although the potassium-40 activities,were higher than normal in 1994, thedifference from prior years was notenough to suggest a change inlaboratory practices or the environmentwas responsible. The fact that increases



were not observed for all ofthe naturallyoccurring gamma-emitting radionuclideslends support to this belief. Theobserved variation is most likely theresult ofa natural phenomenon. Noneofthese naturally occumngradionuclides found in algae nor thevariations in their activity levels areattributable to the SSES operation.,

The manmade fission product iodine-131 was found at activity levels inexcess ofanalysis MDCs in three control.algae samples and two indicator samplesin 1994. Except for 1993, iodine-131has been found in control algae samplesmore often than it has be seen inindicator algae samples since algaebegan to be monitored in 1984. The1994 indicator and control means foriodine-131 were each 0.3 pCi/gram.These means are both well below theircorresponding 1993 means as well asthe averages oftheir correspondingannual means obtained since theoperational year 1984. The 1994control mean for algae is below therange ofprevious annual means. Aspreviously, the presence of iodine-131 in.algae does not appear to be from theSSES operation, but from medicalsources upstream ofthe SSES.

The manmade fission product cesium-137 was found at activity levels inexcess ofanalysis MDCs in threeindicator samples and three controlsamples in 1994. The 1994 indicatorand control means for cesium-137 inalgae were 0.17 pCi/gram and 0.18pCi/gram, respectively. These meansare slightly higher than theircorresponding 1993 means but belowtheir corresponding ranges for priorannual means. This cesium-137 in the

algae is attributed to residual falloutfrom past atmospheric nuclear weaponstests.

The manmade activation productsmanganese-54 and cobalt-60 weremeasured at activity levels exceedinganalysis MDCs in an indicator samplefrom May, 1994 and an indicator sample&om September, 1994. The 1994 meanactivity level for manganese-54 was 0.2.,pCi/gram. This 1994 mean is below the1993 indicator mean and the range ofannual means &om previous years formanganese-54 activity levels in algae.

'he

1994 mean activity level for cobalt-60 was 0.2 pCi/gram. This 1994 meanis below the 1993 indicator mean andthe range ofannual means from previousyears for cobalt-60 activity levels inalgae also. Both manganese-54 andcobalt-60 activities in algae areattributable to the liquid discharges &omthe SSES to the Susquehanna River.No transfer ofmanganese-54 andcobalt-60 from algae to fish has beenobserved. Consequently, no dose toman is believed to result from theirpresence in algae.

FishResults from specific sample analyses offish may be found in Table I 6 ofAppendix I. A summary of the 1994fish data may be located on pages 5 and6 ofTable G in Appendix G.Comparisons of 1994 monitoring resultswith those ofpast years may be found inTables H 16 and H 17 on pages H-6 andH-7 ofAppendix H.

Three species offish were sampled ateach ofone indicator location and onecontrol location on the SusquehannaRiver in May, 1994 and again in



October, 1994. The species includedthe following: white sucker, smallmouthbass, and channel catfish. In addition,one largemouth bass was sampled &omPP&L's LTAWin October, 1994. Atotal of 13 fish were collected andanalyzed.

As in every Gsh sample taken since thespring of 1984, when gross betaanalyses first began to be performed onfish flesh, all Gsh samples hadmeasurable gross beta activity levels inexcess ofanalysis MDCs. The 1994indicator and control means for grossbeta activity levels in fish were6.1 pCi/gram and 4.8 pCi/gram,respectively. The 1994 indicator meanis a full pCi/gram higher than the 1993indicator mean while the 1994 controlmean is slightly lower than its 1993counterpart. The 1994 indicator mean isslightly above the range ofpreviousindicator annual means but within therange ofannual means for the controllocation for previous years. The 1994control mean is the same as the averageofthe annual means for previous years.No gross beta activity in fish during1994 is attributed to liquid dischargesfrom the SSES to the SusquehannaRiver.

The only gamma-emitting radionuclidemeasured in excess ofanalysis MDCs infish during 1994 was naturally occurringpotassium-40. The 1994 indicator andcontrol means for the activity levels ofpotassium40 in Gsh are 3.9 pCi/gramand 3.6 pCi/gram, respectively. The1994 indicator mean is slightly higherthan the 1993 indicator mean while the1994 control mean is slightly below the1993 control mean. Both the 1994indicator and control means are

essentially the same as the averages oftheir corresponding annual means forprior operational years. The indicatorand control average annual means forprior operational years both exceed thecorresponding average annual means forthe preoperational period. Naturallyoccurring potassium-40 in fish is notattributable to the liquid discharges &omthe SSES to the Susquehanna River.

SedimenfResults from specific sample analyses ofsediment may be found in Table I 7 ofAppendix I. A summary ofthe 1994fish data may be located on pages 6through 9 ofTable G in Appendix G.Comparisons of 1994 monitoring resultswith those ofpast years may be found inTables H 18 through H23 on pages H-7and H-8 ofAppendix H.

Both the shoreline and flocculatedvarieties ofsediment were sampled inMay, 1994 and again in late October andearly November, 1994. Gross alphaactivity levels were measured above theanalysis MDCs for all shoreline sedimentsamples in 1994 as is typical. The 1994indicator and control means for grossalpha activities ofsediment were11.8 pCi/gram and 14.0 pCi/gram,respectively. Both the 1994 indicatorand control means were lower than theircorresponding 1993 means, higher thanthe averages ofthe correspondingannual means for prior operationalyears, but within the correspondingranges ofthe annual means for theoperational period. Gross alpha activityanalyses have been performed forsediment every year since 1982. Nogross alpha activity in sediment during1994 is attributed to liquid discharges


A uatic Path~a Monitorin

&om the SSES to the SusquehannaRiver.

Gross beta activity levels were measuredabove analysis MDCs for all shorelinesediment samples in 1994. The 1994indicator and control means for grossbeta activities ofsediment were31.4 pCi/gram and 34.3 pCi/gram,respectively. Both the 1994 indicatorand control means were higher thantheir corresponding 1993 means andalso the averages ofthe correspondingannual means for prior operationalyears. Although the 1994 indicatormean gross beta activity was within therange ofprevious annual indicatormeans, the 1994 control mean grossbeta activity was above the range ofearlier annual control means. Gross betaanalyses have been performed forsediment every year since 1984. Nogross beta activity in sediment during1994 is attributed to liquid dischargesfrom the SSES to the SusquehannaRiver.

Naturally occurring potassium-40 andthorium-228 were measured at activitylevels above analysis MDCs in allshoreline sediment samples in 1994.Naturally occurring radium-226 wasmeasured at activity levels exceedinganalysis MDCs in all but one sedimentsample in 1994. Naturally occurringberyllium-7 was found above analysisMDCs in five 1994 samples.

The 1994 indicator and control meansfor potassium40 activity levels inshoreline sediment were 11.0 pCi/gramand 11.2 pCi/gram, respectively. The1994 indicator mean potassium40activity is slightly lower that thecorresponding 1993 mean while the

1994 control mean is slightly higher thanits corresponding 1993 mean. These1994 means were higher than theaverages ofthe corresponding annualmeans for all prior operational as well as

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

The 1994 indicator and control meansfor radium-226 activity levels inshoreline sediment were 1.6 pCi/gramand 2.0 pCi/gram, respectively. The1994 indicator mean radium-226 activityis slightly lower that the corresponding1993 mean while the 1994 control meanis slightly higher than its corresponding1993 mean. Similar to the situation withpotassium40, these 1994 radium-226means were 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 1994 indicator and control meansfor thorium-228 activity levels inshoreline sediment were 1.0 pCi/gramand 1.1 pCi/gram, respectively. Thesemeans are essentially the same as, oridentical to the averages of thecorresponding means for 1993 and forprior operational years. The naturallyoccurring radionuclides in sedimentdiscussed above are not attributable tothe liquid discharges from the SSES tothe Susquehanna River.

The only man-made radionuclidemeasured at activity levels in shorelinesediment exceeding analysis MDCsduring 1994 was the fission productcesium-137. The 1994 indicator andcontrol means for cesium-137 activity


A uatic Palhw Monitorin

levels in sediment were 0.05 pCi/gramand 0.10 pCi/gram, respectively. Thesemeans are less than their corresponding1993 means. The 1994 indicator andcontrol means also are less than theaverages ofcorresponding annual meansfor both prior 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 1994 weresimilar to those for the monitoring ofshoreline sediment.

Dose from the AquaticPathwa

Tritium, manganese-54, and cobalt-60were the only radionuclides identified in1994 by the SSES REMP in the aquaticpathway which were attributed to SSESoperation.

The maximum whole-body and organdoses to hypothetical maximally exposedindividuals in four age groups (adult,teenager, child, and infant) weredetermined according to themethodology of the Quite DoseCalculation manual using the LADTAPIIcode.

somewhat less than the total amount oftritium reported to have been released in1994 &om SSES efHuent monitoring.)

Because the manganese-54 and cobalt-60 were observed above analysis MDCsin a grab sample from the CTBD linerepresenting one week and were notidentified in any other samples during1994, these radionuclides were assumed

to have been discharged at thosemeasured activity levels for only oneweek in 1994. The activities ofmanganese-54 and cobalt-60, 47pCi/liter and 24 pCi/liter, respectively,were multiplied by the mean monthlyCTBD line flow rate, 7,350 gallons perminute for January, 1994 to obtain thetotal activity ofeach radionuclidedischarged in 1994. Those activitieswere 0.013 Ci for manganese-54 and0.0067 Ci for cobalt-60.

Doses were estimated at the nearestdownriver municipal water supplier viathe drinking water pathway and near theoutfall ofthe SSES discharge to theSusquehanna River via the shoreline (formanganese-54 and cobalt-60) and fishpathways. The maximum whole body .

dose was estimated to be 0.00292millirem to a teenager and the maximumorgan dose was estimated to be 0.00966millirem to the lower large intestine ofand adult.

For the purpose ofperforming the dosecalculation, tritium was assumed to bepresent continuously in the CTBD linethroughout 1994 at its annual meanactivity'level of6,097 pCi/liter. Theannual mean flow rate for the CTBDline of7,270 gpm was multiplied timesthe annual mean activity level to obtainan equivalent annual discharge of88curies oftritium in 1994. (This is


GROSS BETA ACTIVITYINSURFACE WATER

PCI/LITER20

16—

14—

12—

10—


UNIT2CRITICALITY

I I

1975 1977 1979 1981 1983 1985 1987 1989 1991 1993 1995

FIGURE 9—Indicator —Control

2200PCI/LITER

TRITIUMACTIVITYINSURFACE WATER

2000—

1800—

1600—

1400—

1200—

1000—

800—

600—

400—

200—


1972 1974 1976 1978 1980 1982 1984 1986 1988 1990 1992 1994

FIGURE 10—Indicator — —Control—

10PCI/LITER

GROSS BETA ACTIVITYIND G WATER


UNIT2 CRITICALITY

1977 1979 1981 1983 1985 1987 1989 1991 1993 1995

FIGURE 11

l .,-'.'',; ','.":,A'TM

INTRODUCTION

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 theconcentration ofairborne contaminantsin other media in the terrestrialenvironment, such as milk. Suchconcentrations can make the samplingand analysis ofmedia like milkmoresensitive approaches for the detection ofradionuclides, such as iodine-131, in thepathway to man than the monitoring ofair directly. (PP&L also samples milk;refer to the Terrestrial PathwayMonitoring section ofthis report.)¹vertheless, the sensitivity ofairmonitoring can be optimized by theproper selection ofsampling techniquesand,the choice ofthe proper types ofanalyses for the collected samples.

~Sco e

Airsamples were collected onparticulate filters and charcoal cartridgesat indicator locations 3S2, SS4, 7S7,10S3, 12S1, 13S6, 15S4, 9B1, 1D2,3Dl, and 12E1 and control locations7G1 and 12G1. Airtritium sampleswere also collected at location 3S2. Inaddition, precipitation was collected atall ofthe air sampling locations. Threeofthe indicator locations (15S4, 1D3,and 3D1) were monitored until themiddle ofJuly when they were replacedby indicator locations 7S7, 10S3, and13S6. Refer to Appendix A for a

discussion ofthese changes in airmonitoring locations.

Sam lin and Anal sis

AirAt all times during the year, the SSESREMP was monitoring the air at eightindicator locations and two controllocations. The SSES TechnicalSpecifications require monitoring at onlya total offive sites, three locations at theSSES site boundary in difFerent sectorswith the greatest predicted sensitivitiesfor the detection ofSSES releases, thecommunity in the vicinityofthe SSESwith the greatest predicted sensitivity,and 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 downstreamofthe particulate filters. Airtritiumsamples were collected on silica gelcolumns approximately one-foot longand two-and-a-half inches in diameterfrom a difFerent sampling stream usingindependent sampling equipment.Tritiated water was recovered from thecolumns by distillation.

Particulate filters, charcoal cartridges,and silica gel columns were exchangedweekly at the air monitoring sites.Elapsed sampling times were recorded


Atmo heric Pathw Monitorin

on elapsed-time meters. Airsamplevolumes for particulate filters andcharcoal cartridges were measured withtemperature-compensated dry-gasmeters. Airsample volumes for silicagel columns were determined by lowrate times time calculations. Availabledry gas meters weren't used fordetermining sample volumes whensampling for tritium because ofthemuch lower flow rates at which tritiumsamples were collected.

Airfilters were analyzed weekly forgross beta activity, then compositedquarterly and analyzed for gross alphaactivity and the activities ofgamma-emitting radionuclides. The charcoalcartridges were analyzed weekly foriodine-131.

PrecipitadonPrecipitation samples were collected atleast monthly in 1994. During thoseperiods with higher precipitation levels,collection containers may have beenemptied a number oftimes prior to theend ofthe sampling period to prevent aloss ofsample due to overflowingcollection containers. In thoseinstances, the precipitation collected atvarious times were composited at theend ofthe applicable calendar quartersand the composites were analyzed.

Precipitation was analyzed for grossalpha and beta activities, the activities ofgamma-emitting radionuclides, andtritium activity. Sample portions werepreserved the same as other watersamples, depending on the types ofanalyses they were to undergo. Refer tothe Aquatic Pathway Monitoring sectionofthis report for a description oftheappropriate preservation techniques.

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 onpage 47 trends the quarterly meanindicator and control location gross betaactivities separately from 1974 through1994. Note that prior to SSESoperation, before 1982, the unusuallyhigh gross beta activities were generallyattributable to fallout from atmosphericnuclear weapons tests. Typical grossbeta activities measured on airparticulate filters are the result ofnaturally occurring radionuclidesassociated with dust particles suspendedin the sampled air. They are thusterrestrial in origin.

Particulate gross beta activity levels foreach monitoring location and monitoringperiod in 1994 are presented in Table I 9ofAppendix I. Comparisons of

1994'ross

beta analysis results with those ofprevious years may be found inTable H 24, page H-9 ofAppendix H.Annual means of 16 E-3 pCi/m for thebeta activities ofboth indicator andcontrol locations in 1994 are well withinthe ranges ofprevious operational andpre-operational yearly averages. Nocontribution ofradioactivity from theSSES is discernible from 1994 airbornegross beta data.

Gross alpha activity is normallymeasured at levels exceeding fiber filteranalysis MDCs for air particulates also.


Atmo heric Pathwa Monitorin

MDCs for gross alpha activity analysesofthe filters are typically very lowbecause of the electively large samplevolumes obtained as the result ofquarterly filtercompositing prior to,analysis. This alpha activity is terrestrialin origin as well, the result of long-lived,naturally occurring radionuclides thatare part ofthe dust particles normallysuspended in the air at lowconcentrations.

Figure 13 on page 48 trends thequarterly mean indicator and controllocation gross alpha activities separatelyfrom 1980 through 1994. Particulategross alpha activity levels for eachmonitoring location and period in 1994are presented in Table I 10 ofAppendix I. Comparisons of 1994 grossalpha analysis results with previousyears may be found in Table H25, pageH-9 ofAppendix H.

Annual means of3.0 E-3 pCi/m for thealpha activity ofindicator locations and2.7 E-3 pCi/m'or the alpha activity ofcontrol locations in 1994 are nearlytwice the corresponding 1993 means.However, the 1994 mean gross activitiesfor both indicator and control locationsare within the ranges ofpreoperationalannual means for indicators andcontrols, respectively. Consequently, nocontribution ofactivity from the SSES isindicated from the 1994 gross alphadata.

Quarterly gamma spectrometricmeasurements ofcomposited filtersoften see the naturally occurringradionuclide beryllium-7. Occasionally,other naturally occurring radionuclides,potassium-40 and radium-226 are alsoobserved. Beryllium-7 is cosmogenic in

origin, being produced by the interactionofcosmic radiation with the earth'atmosphere. The other two gamma-emitting radionuclides originate fromsoil and rock.

Beryllium-7 was measured aboveanalysis MDCs for all quarterlycomposite samples in 1994. Potassium-40 was seen in excess ofanalysis MDCsin some quarterly composites. The 1994indicator and control means forbetyllium-7 activity were 124 E-3pCi/m, and 118 pCi/m', respectively.The 1994 indicator mean exceeded therange ofall annual means for prioroperational and preoperational years.The 1994 control mean equaled thehighest previous annual mean. The1994 indicator and control means forpotassium-40 activity were 4.0E-3pCi/m'nd 2.6 E-3 pCi/m', respectively.These values are both below theaverages ofcorresponding annual meansfor previous years. Comparisons of1994 beryllium-7 analysis results withprevious years may be found inTable H 26 on page H-9 ofAppendix H.No other gamma-emitting radionuclideswere reported for air in 1994.Beryllium-7 and potassium-40 are notattributable to SSES operation.

AirIodineIodine-131 has been detectedinfrequently from 1976, when it was firstmonitored, through 1994. Sinceoperation ofthe 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 1994 airmonitoring results.


Atmo heric Pathos Monitorin

AirTrMumPP&L is not required to monitorairborne tritium levels in theenvironment. However, PP&L hasmonitored tritium in airborne watervapor since 1988, when it was initiatedon a trial basis. The first sampler wasinstalled at the SSES EnvironmentalLaboratory and designated as locationSS4. In 1994, one indicator samplinglocation was maintained at the SSESBackup Meteorological Tower,designated as monitoring location 3S2;This site was selected as a monitoringlocation based on its expected sensitivityfor detecting any tritium that might bereleased &om the SSES, as well as theconvenience afforded by the availabilityofelectrical power at this locati'on.

This is the third year that airbornetritium monitoring results have been

'ncludedin this report. Because thismonitoring willbe discontinued in 1995,air tritium results willno longer bepresented in this report.

Tritium activity levels for eachmonitoring location and period in 1994are presented in Table I 11 ofAppendix I. The 1994 average tritiumactivity level present in the form oftritiated water vapor at location 3S2 was1.3 pCi/m ofair. This is identical to the1993 average level for tritium in watervapor and within the range ofpreviousannual means which have variedbetween 1.3 and 1.6 pCi/m . Themeasured activity levels throughout1994 for the weekly samples ranged upto a little more than 5 pCi/m in air, justas they did in 1993.

Although the SSES releases tritium as agaseous effluent, it is difficultto

determine ifthe environmentalmonitoring results are higher because ofthe SSES effluent without control datato permit comparisons. Unfortunately,no preoperational data is available forcomparison either. However,comparison with the earlier operationalmonitoring data shows no trends, eitherincreasing or decreasing.

PrecipitattonGross alpha activity measurements ofprecipitation samples usually yieldactivity levels above the analysis MDCs.Gross beta activity measurementsalways produce activity* levels aboveMDCs. Typically, gross beta activitiesare measured at levels in the range offive to ten times the gross alpha activitylevels.

Although no preoperational data &omthe SSES REMP is available for grossalpha and beta activity levels inprecipitation, comparisons ofresultsduring the operational period forindicator and control locations indicatesthat these measurements do not suggestany detectable contribution from SSESoperation. The observed alpha and betaactivities in precipitation appear to bedue to the presence ofnaturallyoccurring radionuclides. However, thesensitivity ofgross alpha and betaactivity measurements bodes well for theearly detection ofany significant SSEScontributions to these activities in thefuture should they occur.

Results for the analyses ofprecipitationsamples in 1994 are presented inTable I 12 ofAppendix I. Comparisonsof 1994 annual means for gross alphaactivity measurements with the annualmeans from previous years may be


Atmo heric Pathwa Monitorin

found in Table H 27 on page H-10 ofAppendix H. The 1994 mean grossalpha activities for precipitation atindicator and control locations were 0.6pCi/I and 0.5 pCi/I, respectively. The1994 indicator mean for gross

alpha'ctivity

is at the bottom ofthe range ofannual means for those ofprevious yearswhile the 1994 control mean is belowthe range ofannual means for earlieryears. Although the indicator mean isgreater than the control mean in 1994,the difference is not believed to be,significant. No SSES contribution tomeasured precipitation gross alphaactivity is believed to be indicated by the1994 data.

Comparisons ofannual means for grossbeta activity measurements with theannual means from previous years maybe found in Table H 28 on page H-10 ofAppendix H. The 1994 mean gross betaactivities for precipitation at indicatorand control locations were 4.3 pCi/I and4.0 pCi/I, respectively. Both ofthesemean gross beta activities are within theranges ofannual means for previousyears. Again, the amount by which the1994 indicator mean exceeds the controlmean is believed to be insignificant,suggesting no SSES contribution tomeasured airborne gross beta activity.

Gamma spectrometric 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 eachmonitoring year at levels exceeding theMDCs for its analyses. Beryllium-7 isnaturally occurring, produced by cosmicradiation. Occasionally, other naturally

occurring, 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 &om the atmosphere by theprecipitation or entering theprecipitation collector as the result ofsettling ofthe dust particles from the air.

The man-made, gamma-emittingradionuclide cesium-137 has beenidentified in precipitation samples atlevels exceeding analysis MDCsin&equently. 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 &omindicator and/or control locations in1981, 1985, 1986, 1987, 1988, and1989. Its observation in precipitationfrom 1986 through 1989 may have beenthe result ofresidual 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.

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 neither

1994 Radiological Environmental Monitoring Report 4S

Atmo heric Pathiv Monitorin

unit at the station had been in operationyet.

The only gamma-emitting radionuclidesmeasured at activity levels in excess ofthe MDCs for their analyses in 1994were the naturally occurring beryllium-7and potassium-40.

Comparisons ofannual means for tritiumactivity measurements with the annualmeans &om previous years may befound in Table H 32 on page H-9 ofAppendix H. Results similar to thosefor 1993 were obtained in 1994 for theanalyses oftritium in precipitation. The1994 indicator and control mean tritiumactivity levels were 28 pCi/1 and -25pCi/I, respectively. The 1994 indicatormean is within the range for the annualmeans ofprevious years, and the 1994

. control mean is below the range for theannual means ofearlier years. In both1994 and 1993, low positive'"activitylevels for the annual indicator

means'ith

corresponding negative activitylevels for the control means suggest apossible SSES contribution. However,because the positive indicator means forboth years are so low, analysis MDCswere exceeded for only two out of 128indicator analyses in 1994, it can'readily be concluded that such acontribution actually has occurred.


GROSS BETA ACTIVITYINAIRPARTICULATES

E-03 PCI/M3500

450

400

350

300

250

200


CHINESEWEAPONS TESTA - 6/17/74B - 9/26/76C - 11/17/76D - 9/17/77E - 3/14/78F - 10/15/80

150

100

50

CB Chernobyl

4/26/86UNIT2

CRITICALITY

—Indicator—Control

1974 .1976 1978 1980 1982 1984 1986 1988 1990 1992 1994

GROSS ALPHAACTIVITYINAIRPARTICULATES

E-03 PCI/M320

15—PRE-OP OPERATIONAL

10— UNIT2CRITICALITY

1980 1982 1984 1986 1988 1990 1992 1994

—Indicator —Control

FIGURE 13

INTRODUCTION

The followingmedia were monitored inthe Terrestrial Pathway in 1994: soil,vegetation, milk, &uits and vegetables,game, and eggs.

Soil can be a great accumulator ofman-made radionuclides that enter it. Theextent ofthe accumulation in the soildepends ofcourse on the amount ofthe-radionuclides reaching it, but it alsodepends on the chemical nature ofthoseradionuclides and the particularcharacteristics ofthe 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 theenvironment than those media thatdon'. Such a medium facilitates theearly identification ofradionuclides inthe environment, as well as awareness ofchanges that subsequently may occur inthe environmental levels ofthe identifiedradionuclides.

The SSES REMP samples soil near allthe REMP air sampling stations.

The'urposefor soil sampling near the airsampling sites is to make it easier tocorrelate air sampling results with soil

sampling results ifany SSES relatedradioactive material were found in eithermedium. Sampling is performed atdifferent depths near the surface to helpprovide 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 ofsoil at the time ofsampling.

Vegetation also is sampled at all the soil'onitoringlocations, with the exception

ofone control location, where there isinsufficient growth to obtain samples.This vegetation, which is primarily a

mixture ofwhatever grass and weedsmay be growing at the soil sampling"sites, may show radioactive material thatsettled &om the air but has not yetreached the soil, or also could representmaterial that was present in the soil andwas taken up by the roots ofthevegetation. In either case, vegetationsampling and analysis helps to completethe picture ofthe radiological status ofa

location that may have already begun tobe painted by air and soil sampling.Sampling of the other media (milk, fruitsand vegetables, poultry and eggs, and

game) provide a more direct view ofthepossible impact on man ofradioactivematerials in the terrestrial environment.

Milkwas sampled at four more locationsthan required and fruit and vegetablesamples were obtained at 13 morelocations than required in 1994. SSESTechnical Specifications only require


Terrestrial Pathw Monitorin

that the SSES REMP sample milkat thethree most sensitive monitoringlocations near the SSES and one controllocation distant &om the SSES. SSESTechnical Specifications only requirethat &uitand vegetables be sampled atlocations irrigated by SusquehannaRiver from points downstream oftheSSES discharge to the River. There areonly two locations within ten milesdownstream ofthe SSES that have beenknown to imgate with water from theSusquehanna River during unusually, dryperiods. These locations do not irrigateevery year and, in fact, did not irrigate atall in 1994 according to the 1994 LandUse Census (reference 49).

No requirement exists for the SSESREMP to monitor soil, vegetation, eggs,and game. Allmonitoring oftheterrestrial pathway that is conducted bythe SSES REMP in addition to milk andcertain fruit and vegetables is voluntaryand reflects PP&L's willingness toexceed regulatory requirements, ifnecessary, to ensure that the public andthe environment are protected.

~Sco e

Soil and VegetationSoil and vegetation, with only oneexception, were each sampled once, inaccordance with their scheduled annualsampling frequencies, at each ofthe tenREMP air sampling locations, 3S2, 5S4,7S7, 10S3, 12SI, 13S6, 9BI, 12EI,7GI (soil only), and 12GI, in October,1994. Locations,7GI and 12GI'erecontrol sampling locations; theremaining sampling sites were indicatorlocations. No vegetation was collectedat 7GI because there is none available.

Locations 7S7, 10S3, and 13S6 weresampled for soil and vegetation for thefirst time in 1994. These locations werereplacements for locations 15S4, ID2,and 3DI, which had been sampled inprevious years. Soil sampling at thesethree locations was discontinued in July,1994 and the air sampling equipment atthese sites was moved to locations 7S7,10S3, and 13S6.

Top and bottom soil plugs were taken,representing soil to a depth oftwoinches in the first case and soil Rom adepth oftwo inches to six inches in thesecond case, at a total of 10 monitoringlocations in 1994. Twelve plugs fromeach layer were composited for analysisat each location, as is routine. Totals of18 soil and 10 vegetation samples wereanalyzed in 1994.

MilkMilkwas sampled at least monthly at thefollowing eight locations in 1994, withone exception: 6CI, 10DI, 10D2,IOD3, 10D4, 10GI, 12B3, Gnd 13E3.Location 10D2 was not sampled prior toMarch, 1994. This location replacedlocation 14B I, which was last sampledin January, 1994. Sampling wasdiscontinued at location 14B I becausethe farmer went out ofthe dairybusiness; the farmer's cows were soldfollowing the collapse ofthe barn usedfor the cows.

Milkwas sampled semi-monthly fromApril through October at locations10DI, 10D2, 10GI, and 12B3 whencows were more likely to be in thepastures. These locations are believedto be the most sensitive monitoring sitesavailable for the detection ofanyradionuclides that might be released


Terrestrial Pathwa Monitorin

from the SSES and find their way intomilk&om local dairy farms. Location10G1 is the one control location that issampled by the SSES REMP. A total of123 milk samples &om both indicatorand control locations were analyzed in1994.

Fruits and Vegetables,Fruits and vegetables were sampled at

. 15 locations in 10 different sectorssurrounding the SSES during theharvest season. Twenty-four differentkinds of&uits and vegetables wereobtained for a total of69 samples.Samples were obtained from thefollowing locations: 2BS, 7B2, 8A4,8AS, 9D2, 10BS, 10F2, 11D1, 12B1,12FS, 12F7, 13E4, 13G2, 14B3, and15A3. Location 13G2 was the onlycontrol location.

The availability of&uits and vegetables&om growers typically varies from oneyear to the next. For example,

'ardenersmay grow diFerent 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.

performed. In 1993, additionalmonitoring was performed at fields thatwere known to have been flooded by theSusquehanna River during an unusuallyrainy period.

GameEleven different game samples werecollected &om five different sectors atthe following seven locations in 1994:

2S, 2H, 3S, SS, 15S, 16S, and 16F.Location 2H may be considered a

control location because ofitssubstantial distance &om the SSES.

Game samples in 1994 included deer,squirrel, and rabbit. The samplingmethod for deer is typically recovery ofthe flesh &om road-killed animals.Small game samples are usually obtained

by 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 difficultto be able toensure that the same numbers and typesofgame samples are collected each year.

Woodchucks were not sampledintentionally in 1994. It was decided todelete them from terrestrial monitoringbecause their consumption by the public

's expected to be very infrequent.

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

Eggs'ggs were sampled only once at

location 10D1 during 1994.


Terrestrial Pathw Monitorin

Sample Preservationand Anal 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.

Allmedia in the terrestrial pathway areanalyzed for the activities ofgamma-emitting radionuclides using gammaspectroscopy. The only other analysesthat are routinely performed are theradiochemical analyses for iodine-131and strontiums 89 and 90 in milk.

Monitorin Results

The only man-made radionuclidesnormally measured at levels in excess ofanalysis MDCs in the terrestrial pathwayare strontium-90 and cesium-137.Strontium-90 has been measured abovethe analysis MDCs, but at low levels, inmilk samples, and cesium-137 hasnormally been measured exceedinganalysis MDCs in most soil samples.Cesium-137 has also been seen often atlevels above the MDCs in game. Theseradionuclides are both present in theenvironment as residuals from previousatmospheric nuclear weapons testing.

Certain naturally-occurringradionuclides are also routinely foundabove analysis MDCs in terrestrialpathway media. Potassium-40, aprimordial and very long-livedradionuclide, which is terrestrial inorigin, is observed in all terrestrialpathway media exceeding analysis

MDCs. Other naturally-occurringradionuclides often observed aboveMDCs are thorium-228 and radium-226in soil, and betyllium-7 in vegetation andin fruits and vegetables.

The results ofthe 1994 terrestrialpathway monitoring resemble those ofthe past. Results for specific sampleanalyses ofterrestrial pathway mediamay be found in Tables I 13 throughI 17 ofAppendix I. A summary ofthe1994 terrestrial monitoring data may belocated in Appendix G. Comparisons of1994 monitoring results with those ofpast years may be found in Tables H 30through H 40 on pages H-11 through H-14 ofAppendix H.

$0IlThe 1994 analysis results for all gamma-emitting radionuclides, naturallyoccurring potassium-40, radium-226,and thorium-228 and manmade 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 1994. ~

The 1994 means for indicator andcontrol location sample potassiumAOactivity were 10.7 pCi/gram and9.6 pCi/gram, respectively. Both meanswere slightly lower than their respective1993 means and the average ofannualmeans for the previous operationalperiod ofthe SSES, but within theranges ofcorresponding means for prioroperational years. The 1994 indicatormean for potassium-40 was slightlyhigher than the range ofpreoperationalmeans, as was the 1993 indicator mean.This is not the result ofSSES operation



because the potassium40 is naturallyoccurring.

The 1994 means for indicator andcontrol location sample radium-226activity were 1.5 pCi/gram and1.8 pCi/gram, respectively. Thesemeans are essentially the same as theaverage ofannual means for theprevious operational period oftheSSES, although the 1994 indicator meanis slightly above the range ofindicatorannual means obtained during thepreoperational period, as was the 1993indicator mean. This is not the result ofSSES operation because the radium-226is naturally occurring.

The 1994 means for indicator andcontrol location sample thorium-228activity were 0.8 pCi/gram and0.9 pCi/gram, respectively. Thesemeans are essentially the same as thecorresponding 1993 annual means andequal to or below the bottom oftherange ofprevious annual means for boththe previous operational andpreoperational periods, as applicable.Thorium-228 in soil is not the result of-SSES operation because it is naturallyoccurring.

The 1994 means for indicator andcontrol location sample cesium-137activity were essentially the same as thecorresponding 1993 annual means andequal to or below the averages ofannualmeans for previous operational andpreoperational periods, as applicable.The highest cesium-137 activity for aspecific sample in 1994 was obtainedfrom the composite oftop soil plugsfrom control location 7G1. Cesium-137levels in soil samples typically varywidely &om sample to sample. The

results for the 1994 monitoring yearwere no exception in this regard. Levelsofcesium-137 activity in 1994 samplesvaried by more than a factor often overthe entire range. Cesium-137 in soil,although man-made, is not &om theoperation ofthe SSES. It is residualfallout from previous atmosphericnuclear weapons testing.

VegetadonThe 1994 analysis results for thegamma-emitting radionuclides, naturallyoccurring beryllium-7 and potassium-40,that are routinely measured in vegetationat levels exceeding analysis MDCs weresimilar to those for previous years. Noother gamma-emitting radionuclideswere reported at levels above analysisMDCs in vegetation in 1994.

The 1994 means for indicator andcontrol location sample beryllium-7activity were 2.9 pCi/gram and1.9 pCi/gram, respectively. These areequal to or below the corresponding1993 annual means, but above theaverages ofthe means ofprevious years,which are available only for theoperational period ofthe SSES.Beryllium-7 levels in vegetation are notattributable to the SSES operationbecause it is a naturally occurringradionuclide.

The 1994 means for indicator andcontrol location sample potassium-40activity were 4.6 pCi/gram and3.1 pCi/gram, respectively. These aresignificantly below the corresponding1993 annual means and are also belowthe averages ofthe means for previousyears, which are available only for theoperational period ofthe SSES.Potassium<0 levels in vegetation are

1994 Radiological Environmental Monitoring Rcport 53

TerrestriaI Pathw Monitorin

not attributable to the SSES operationbecause it is a naturally occumngradionuclide.

MilkIodine-131 has been chemicallyseparated in milk samples and countedroutinely since 1977. Refer to Figure 14which trends iodine-131 activity in milkseparately for indicator and controllocations Rom 1977 through 1994.

Typically, iodine-131 is not reported atlevels exceeding the MDCs for the,analyses in any milk samples during amonitored year. The 1994 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 thevicinityofthe SSES as a result oftheChernobyl incident. Subsequent levelsobserved near the baseline ofFigure 14in 1991 and 1992 represent backgroundfluctuations in data that appear as aresult ofaveraging methods. No iodine-131 levels exceeding analysis MDCswere observed in milk during theseyears.

Strontium-89 was not reported in anymilk samples during 1994. Nostrontium-89 has been reported in SSESgaseous efBuents since the end of 1989.Strontium-89 has a relatively short half-life (= 50 days) and would not beexpected to be reported inenvironmental samples in 1994 as a

result offallout Rom atmosphericnuclear weapons testing in 1980 orbefore, unlike other Gssion productssuch as strontium-90 and cesium-137.Interestingly, strontium-89 was notdetected followingChernobyl, evenwhen elevated levels ofsuchradionuclides as iodine-131 wereobserved. Typically, the presence ofstrontium-89 above analysis MDCswould suggest the SSES as the origin ifit were to be seen.

The 1994 means for indicator andcontrol location sample strontium-90activity were 2.7 pCi/liter and3.3 pCi/liter, respectively. These meanswere slightly lower than thecorresponding 1993 means and alsolower than the averages ofthe means forboth prior SSES operational years aswell as preoperational years. Althoughstrontium-90 is a manmade radionuclide,it is not attributable to the operation ofSSES. The strontium-90 reported inmilk samples is a residue from previousatmospheric weapons testing.

With the exception ofthe naturallyoccurring potassium40, no gamma-emitting radionuclides were measured inexcess ofanalysis MDCs in 1994. The1994 means for indicator and controllocation sample potassium40 activitywere 1356 pCi/liter and 1328 pCi/liter,respectively. The 1994 indicator meanwas almost identical to the 1993

- indicator mean and the control meanwas somewhat lower. The 1994indicator and control means forpotassium-40 activity were within theranges ofannual means for bothprevious operational years andpreoperational years. The potassium40activity in milk is not attributable to the



SSES operation because it is naturallyoccumng.

not attributable to SSES operationbecause it is naturally occurring.

Fruits and VegetablesWith the exception ofthe measurementofnaturally occurring beryllium-7 in asmall number of&uitand vegetablesamples, naturally occurring potassium-40 was the only gamma-emittingradionuclide reported in &uits andvegetables at activity levels in excess ofanalysis MDCs. The 1994 means forindicator and control location sample.potassium-40'activity were 2.2 pCi/gramand 2.6 pCi/gram, respectively. The1994 indicator mean is equal to thecorresponding 1993 indicator mean andless than the averages ofthe annualpotassium40 means for both prioroperational years and preoperationalyears. The 1994 control mean isessentially identical to the corresponding1993 control mean and the average ofthe annual means for all prioroperational years; it is less than theaverage ofthe annual means forpreoperational years. Potassium-40 infruits and vegetables is not attributableto SSES operation because it is a

naturally occurring radionuclide.

GameThe only two gamma emittingradionuclides measured in game in 1994were the naturally occurring potassium-40 and the manmade radionuclidecesium-137. The 1994 mean forindicator location sample potassium40activity was 3.8 pCi/gram. The 1994annual indicator mean is higher than therange ofprior operational annual means,but within the range ofpreoperationalannual means for potassium-40 activityin game. The potassium40 in game is

The 1994 mean for indicator locationsample cesium-137 activity was0.2 pCi/gram. This is identical to thecorresponding 1993 mean and less thanthe averages ofthe annual means forboth prior operational years as well as

preoperational years.

1994 was an exceptional year for themonitoring ofgame because a deersample was obtained from an unusuallylarge distance ofmore than 20 milesfrom the SSES. Because of thisrelatively large distance, the sampleobtained may be considered as a controlsample that is not likely to be affectedby routine releases &om the SSES.

Typically, no game samples aredesignated as controls during a

monitoring year because most gamesamples are obtained near the SSES. Inmany cases, such as deer sampling, theflesh is taken from road kills over whichno control ofavailable kills is possible.

While the potassium-40 activity,,4.1 pCi/gram, of the sample from thedistant control location was more thanthe mean (3.8 pCi/gram) of the 1994indicator sampling locations'otassium-40 activities, the control cesium-137activity level of0.05 pCi/gram was lessthan the indicator mean activity (3.8pCi/gram). Nevertheless, this shouldnot be interpreted as indicating acontribution from SSES operation.

Cesium-137 activities normally varygreatly between game samples,especially between types ofgame. Forexample, in 1994 the mean potassium-40 activities were as follows:


Terrestrial Path~ Monitorin

0.4 pCi/gram for squirrels, 0.2 pCi/gramfor deer, and 0.007 pCi/gram for rabbits.This is probably the result ofdifferencesin the types offood consumed. Acornsand mushrooms have been found tohave higher levels ofcesium-137 thanother potential foodstuffs. These wouldbe part ofthe diets ofdeer andespecially squirrels, but not routinelyeaten by rabbits.

The cesium-137 activities in sixindicator samples exceeded the activityofthe control sample which was a deer.Comparing just cesium-137 activitylevels in deer, since the control samplewas a deer, it can be observed that theindicator deer samples obtained closerto the SSES than the control have lowerlevels ofcesium-137. Cesium-137 levelsmeasured in excess ofanalysis MDCs ingame are not attributable to SSESoperation because it is naturallyoccurring.

EggsEggs were sampled &om one indicatorlocation in 1994. Potassium-40 was theonly gamma-emitting radionuclidepresent at a level exceeding an analysisMDC. The potassium-40 in the eggswas not attributable to SSES operationbecause it is naturally occurrin.


IODINE-131 ACTIVITYIN MILK

100—

90—

PCI/LITER


80—

70—

60—

Chinese Weapon Test9/12/77

50

40—30—

20—

10—

0 —i I I



UNIT2CRITICALITY

Chernobyl4/26/86

mIndicator KIControl

Ground 8'ater Monitorin

radionuclides, and tritium activity.Gross beta analyses ofground watersamples in the area where the SSES islocated today were initiated in 1977,prior to SSES operation. Similarly,gamma spectrometric analyses ofground water were begun in 1979 andgross alpha analyses were started in1980, both prior to SSES operation.Refer to tables H 44 through H 46 onpage H-16 in Appendix H forcomparisons ofthe 1994 ground watermonitoring results with those ofprevious years.

"

Monitorin Results

Gross alpha activities are usuallymeasured above the MDCs in a smallnumber ofsamples annually. Theactivities seen during the SSESoperational period have been similar tothose observed during thepreoperational monitoring period.These gross alpha activities have notbeen attributable to SSES operation inthe past.

Gross beta activities are measured atlow levels, which are nevertheless inexcess ofanalysis MDCs, in a majorityofthe samples collected each year.Gross beta measurements are verysensitive measurements, capable ofattaining MDCs at activity levels wellbelow the MDCs for gammaspectrometric measurements. Grossbeta activities measured during theSSES operational period have beensimilar to those seen during thepreoperational monitoring phase oftheSSES REMP. They have not beenattributable to SSES operation.

Tritiumactivity 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 levels oft'ritiumwere measured above the analysissensitivities in 1993 than in 1992.

Gamma spectrometric analyses haveidenti6ed 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 1979. Itspresence has always been attributed toresidual fallout from previousatmospheric nuclear weapons tests.

The results ofthe 1994 REMP groundwater surveillance resemble those of thepast. Results for specific ground, watersample analyses may be found in Table I8 ofAppendix I. A summary ofthe1994 ground water monitoring data maybe located in Appendix G. Comparisonsof 1994 monitoring results with those ofpast years may be found in Tables H 41through H43 on page H-14 of-Appendix H.

The 1994 annual mean for gross alphaactivity of0.3 pCi/liter at indicatorlocations is higher than the 1993 meanof0.2 pCi/liter, which was the lowest


Ground Water Monitorin

annual mean obtained at indicatorlocations since the analyses were firstperformed. Nevertheless, it is wellbelow the mean gross alpha activity of2.7 pCi/liter for the preoperationalperiod and near the low end ofthe rangefor such activities calculated for prioroperational years. The 1994 yearlymean gross alpha activity for controllocations of0.5 pCi/liter was somewhathigher than the 1993 indicator mean.Although the 1994 control mean forgross alpha activity is ten times the 1993mean, it is well below the mean activityfor prior operational years of 1.1

pCi/liter. No contribution ofgross alphaactivity from the SSES is indicated bythe 1994 data.

The 1994 annual mean for gross betaactivity of 1.6 pCi/liter at indicatorlocations is slightly higher than, but notsignificantly difFerent from, the 1993mean of 1.4 pCi/liter. The 1994 yearlymean gross beta activity for controllocations of2.8 pCi/liter is identical tothe 1993 mean. The 1994 mean grossbeta activities for both indicator andcontrol locations are within or belowannual means obtained from the SSESpreoperational monitoring period. Nocontribution ofgross beta activity fromthe SSES is indicated by the 1994 data.

means for prior operational and

preoperational years. The 1994 means

are the lowest annual means everobtained for ground water tritium. Adecline in tritium averages for variouswaters, including ground water, firstoccurred in 1991 when data averagingmethods changed. Another decline intritium averages was noted in 1993 forwaters generally.

The only gamma-emitting radionuclidemeasured at levels in excess ofanalysisMDCs in 1994 in ground water sampleswas the naturally occurring potassium-40. It was observed to exceed the MDCin 5 samples collected in 1994. Theresults &om gamma spectroscopicanalyses are in agreement with thoseobtained for the gross alpha and betameasurements; no radioactivitycontributions to ground water from theSSES in 1994 are indicated.

The 1994 mean tritium activity levels forindicator and control ground watermonitoring locations were 23 pCi/literand 34 pCi/liter, respectively. Theselevels are similar to those for 1993 whenthe indicator and control ground watermonitoring location means were 27pCi/liter and 44 pCi/liter, respectively.Both the 1994 and 1993 indicator andcontrol mean tritium activity levels aresignificantly below the corresponding


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

2. 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.


J

Re erences

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, RadiologicalEnvironmental 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, Of5ce 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.

18.

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

1

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 72-1Office 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.

Currie L.A., "LowerLimitofDetection: Definition and Elaboration ofa ProposedPosition for Radiological EQluent and Environmental Measurements,"NUREG/CR-4007, September 1984.

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


Re erences

24. Pennsylvania Power and Light Company, "Susquehanna Steam Electric Station,Semi-annual Effluent 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, April91 and NPF-22, April91.

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

27.

28.

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

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

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

32.

33.

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

C

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 Effluent Waste Disposal Report, Data Period: January-June 1989,"August 1989.

35. Pennsylvania Power &Light Company, "Susquehanna Steam Electric Station,Semi-annual Effluent Waste Disposal Report, Data Period: July-December 1989,"February 1990.


Re erences


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

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


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

41. Pennsylvania Power &Light Company, "Susquehanna Steam Electric Station,Semi-Annual Effluent Waste Disposal Report, Data Period: July 1-December, 1991," February 1992.

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

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

44 Pennsylvania Power &Light Company, "Susquehanna Steam Electric Station,Semi-Annual Effluent Waste Disposal Report, Data Period: July 1-December 1992," February 1993.


46. Pennsylvania Power &Light Company, "Susquehanna Steam Elecaic Station,Annual Effluent &Waste Disposal Report, Data Period: January - December

'993,March 1994.


Re erences

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-December1994, March 1995.

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


A endix A

Ambient Radiation Level Monitorin

The followingTLD locations were eliminated &om the SSES REMP at the end ofthe1994 third calendar quarter ofmonitoring: 1E1, 3D1, 3F1, 3G5, 4B1, 5S1, 6S8, 7A2,11S6, 12B5, and 16B1.

The following SSES REMP TLD location moves took place at the end ofthe 1994 thirdcalendar quarter ofmonitoring: 1D2 m 1D5, 4E1 m 4E2, 6B2 m 6D1, 11S2 m 11S7,

14B2 m 14D1, and 14E1 m 14B3. The new locations indicated to the right ofthearrows are described as follows:

1DS:4E2:6D1:

, 11S7:14D1:14B3:

Shickshinny/ Mocanaqua Sewage Treatment Plant, 4.0 miles N ofSSES,Ruckles Hilland Pond HillIntersection, 4.7 miles ENE ofSSES,St. Peters Church in Hobbie, 3,5 miles ESE ofSSES,SSES access road gate 050 south of the Tower's Club, 0.4 miles SW ofSSES,Moore's Klland Mingle Inn Road Intersection, 3.6 miles WNW ofSSES, andMoskaluk Residence, 1.3 miles WNWofSSES.

The followingTLD locations were added to the SSES REMP at the beginning ofthe1994 fourth calendar quarter ofmonitoring: 7S7, 10S3, and 13S6. These new locationsare described as follows:

7S7: End ofIQine's Road, 0.4 miles SE ofSSES,10S3: Confer's Lane - south ofTower's Club, 0.6 miles SSW ofSSES, and13S6: Former Laydown Area - west ofConfer's Lane, 0.4 miles W ofSSES.

In addition, the following changes involving TLD locations also were made: the TLDpresent at location 15F1 was repositioned to a post and box at the beginning of the 1994fourth calendar quarter, the TLD at location 4S3 was moved from the perimeter fence toa post west ofthe SSES'Access Processing Facility during the second calendar quarter,and the co-location ofTLDs at the PIC monitoring locations was discontinued at thebeginning ofthe third calendar quarter.

The reasons for these changes varied from location to location, but generally they weremade to promote one or more ofthe following: the safety ofenvironmental samplingpersonnel, the eKciency with which TLD locations are accessed in the field, and theability ofthe TLDs to accurately monitor radiation levels in the environment.

Safety concerns about the former TLD locations included the following: dif5cult accesswhen roads become slippery or snow covered, close proximity to high voltageequipment, close proximity to highways with no convenient areas ofF-highway to parkvehicles, close proximity to potentially electrifiable fencing, poor footing due to thepresence ofrocks and deadfall, and the need to use ladders to reach the TLDs.

1994 Radiological Environmental Monitoring Report A-2

A endix A

Ofprimary concern with regard to monitoring accuracy was the representivity oftheTLD field sites relative to their general surroundings. In accordance with ANSIN545-1975 ( American National Standard Performance, Testing, and Procedural Specificationsfor Thermoluminescence Dosimetry (Environmental Applications)) guidelines, an eFortwas made to ensure that TLDs were not shielded by adjacent structures.

- TLD locations were eliminated ifno suitable replacement locations were found.Considerations prior to relocating the TLDs were their elevations above the ground, theavailability ofpreoperational data for old and new field locations, co-location with otheragencies such as PADER and the NRC, and the potential for disturbance ofTLDs in thefield by curious individuals or those deliberately intending to vandalize TLD locations..

Negligible impact on TLD data was expected due to changes in TLD elevations. Anattempt was made with relocated TLDs, new TLDs, and TLDs attached to fences, evenifnot new or relocated, to position them at heights of 1.0 meter 2 0.3 meter above theground, in accordance with the guidelines ofANSIN545-1975. TLDs at the followinglocations were lowered but remained at the same sites: 2B3, 3G4, 4G1, 7Gl, 9S2, 9B1,11S3, 12S3, 12E1, 12E2, 12G1, 13S2, 14S6, 16S1, N1d 16S2.

Environmental TLD uarterl Data Inte retation

Anew approach was instituted in 1994 to determine possible exposure contributionsfrom SSES operation to individual environmental TLD exposure measurements on aquarterly basis. Data evaluations by calendar quarter for previous years were limited tocomparisons ofaverage TLD exposures for selected indicator locations to averageexposures at control locations. Indicator locations were selected according to theirdistances &om the SSES, with those at similar distances being grouped together forpurposes ofdetermining average exposures. Ratios ofgrouped indicator averages tocontrol averages were then calculated, and it was assumed that any ratios significantlygreater than one would be indicative ofSSES'exposure contributions. Significant wasnot defined; no specific magnitudes for ratios had been established that would indicateexposure contributions from the SSES when exceeded. The former approach was morequalitative (subjective) than quantitative (objective), even though ratios ofaverages werecalculated.

The new approach is more quantitative, and therefore more objective. It establishesspecific, decision-making criteria for the ratios of individual indicator location exposuresto control location average exposures. When'a ratio is exceeded for'n onsitemonitoring location, it is assumed to indicate an SSES exposure contribution. Inaddition, preoperational data was considered when establishing the criteria. The newapproach should be more sensitive to the detection ofSSES contributions that mightoccur at only one location or a small number oflocations because such contributionswould not be mask'ed by data from unaFected locations. The new approach appears tobe more likely to err in the conservative direction by assigning a SSES contribution whennone has actually occurred than the old approach would have been.

A-3 1994 Radiological Environmental Monitoring Report

A endix A

The new approach also establishes a method for. the calculation ofthe SSEScontributions when ratios and criteria indicate that such contributions may have beenmade. Refer to Appendix E; pages E-7 through E-11, for additional detail on the newapproach for the evaluation ofenvironmental TLD data.

Drinlan Water Sam lin

Prior to November, 1993, untreated drinking water was continuously sampled at theDanville Municipal Drinking Water AuthorityFacility Rom settling well ¹18 throughwhich Susquehanna River water first enters the facilityprior to any treatment orprocessing. In November, 1993, the continuous sampling point for the untreated waterwithin the facilitywas changed to another well downstream in an attempt to avoidsampling pump clogging from the relatively large amounts ofsediment and debris thattend to accumulate in well ¹18 and, also, to ensure that untreated drinking water isalways sampled, whether well ¹18 or an alternate well, ¹16, is'being used by the facilityfor its intake. Later that month, failure ofa small in-line pump that was installed in aturbidity line to permit sampling from the downstream well caused sampling to revertback to well ¹18 until March, 1994, when a replacement in-line pump was installed andsampling was'returned to the downstream well.

Observations ofthe small in-line pump operation and the less-than-satisfactory watercollection between March and June, 1994, indicated that new problems, which had notbeen experienced with the original sampling setup, were occurring with the modifiedsampling arrangement and were interfering with the sampling process. In early June, thein-line pump did not appear to be running smoothly, as indicated by changes in the soundemitted by the pump. Inspection ofthe tygon tubing leading to the automatic continuoussampler (ACS) suggested that air might be being mixed with the water being sampled.Further credence was lent to this idea when it was observed that the water beingdischarged from the tygon tubing was-also observed to be varying in flow rate slightly.In addition, a dark material could be seen clinging to portions ofthe inside ofthe tygontubing leading to the ACS.

Although the sources of the problems were not known for sure, possible causes wereadvanced. It was suggested that the varying flow rates might result from air entering thesampling line from the large vertical section ofpipe from which the sampling water wasbeing obtained. Also, the dark material inside the tygon tubing was believed to becarbon that is continuously introduced into the water as part ofthe treatment processdownstream ofthe sampling point. Itwas postulated that, although the carbon is beingadded downstream ofthe sampling point according to normal flow, the carbon mightenter the sampling stream during briefperiods following pump restarts, at which timeslugs ofwater might be sent in a direction counter to normal flow. Because oftheseobservations and the expected reasons for them, the sampling arrangement was changedagain.


A endix A

Sampling ofuntreated water was switched back to weH ¹18 on June 6, 1994. Shortlythereafter, provision was made to allow water to be drawn &om either well ¹18 or well¹16, depending on which is in use. Danville Municipal Water Authority personnelagreed to change valve alignments to permit sampling ofthe in-use well as necessary.

Further changes in the sampling point for untreated water at Danville are likely in 1995,followingcompletion ofthe installation by the Authority oftraveling screensdownstream ofwell ¹18 for the purpose ofdebris removal. Modi6cations willbe madeto allow water to be sampled downstream ofthese screens to lessen the possibility forpump clogging that exists at the pumps current location in well ¹18.

A~is

Airsampling was discontinued at three locations (1D2, 3D1, and 15S4) in July, )994.Airsampling was initiated at three new locations, 13S6, 10S3, and 7S7, on July 12, 13,and 14, respectively. The locations that were dropped &om the SSES REMP wereremoved because ofchanges in the sampling environment that could compromise thequality ofthe sampling performed. These changes involved activities taking place inclose proximity to the sampling equipment such as the movement oflarge vehicles andthe associated large quantities ofdust in the air, trash burning, and dumping at two ofthethree monitoring sites. Problems associated with the third location were the growth ofatree limb overhanging the sampling station and &equent deterioration ofthe access roadto the site as a result ofa combination ofthe terrain at the location and bad weatherconditions.

The three replacement air sampling locations were selected with the idea ofoptimizingmonitoring sensitivity, avoiding future deterioration ofthe replacement sites, and thepracticality ofsupplying power to the sampling equipment. Other factors, such as thelocations ofother REMP air sampling stations and the usefulness ofair sampling stationdata in the event ofan emergency event at the SSES, were also considered:Optimization ofmonitoring sensitivity relied on an evaluation ofmeteorological data forthe 16 radial sectors surrounding the SSES.

Soil Sam lin

Soil sampling was not performed at locations 1D2, 3D1, and 15S4 in 1994. Instead, soilwas sampled in the fall at the three new air sampling locations 7S7, 10S3, and 13S6because ofthe installation ofair sampling equipment at those sites.

MilkSam lin

The Stola farm (14B1), located 1.8 miles WNW ofthe SSES, was replaced by theRussell Ryman farm (10D2), located 3.1 miles SSW ofthe SSES, as a REMP milksampling location in March, 1994. The reason for this change was the Stola farm goingout of the dairy fanning business, at least temporarily. The Stola farm went out of

A-5 1994 Radiological Environmental MonitoringReport

A endix A

business because ofthe collapse ofthe Stola barn and the subsequent selling ofthefarm's milk cows.

Monitorin Location Desi ations

A change was made at the end of 1994 to the TLD monitoring location designation forthe Kline residence (7A1), located 0.4 miles SE ofthe SSES. This designation waschanged to 7S8 because it was determined that the Kline residence is within the SSESsite boundary.


APPENDIX B

-;::;-:::".-.,"~+4::"1,994,'REMP::,MGNlTORING;;SCHEDULE"'-"""""<'i':~""l


A endix B

TABLE 1

(Page 1 of3)

Annual Analytical Schedule for theSusquehanna Steam Electric Station (PAL)

Radiological Environmental Monitoring Program - 1994

No. of Sample AnalysisMedia Ec Code Locations Fre . a Anal ses Re uired Fre .

AirborneParticulates

13 W Gross Beta (c)Gross AlphaGamma Spectrometry

WQCqC

Airborne Iodine 13 W I-131 W

Airborne Tritium W W

Sediment SA Gross AlphaGross BetaGamma Spectrometry

SASASA

FlocculatedSediments

SA Gross AlphaGross BetaGamma Spectrometry

SASASA

Fish SA Gross BetaGamma Spectrometry(on edible portion)

SASA

Surface Water(d)

MC,M,orBWC

Gross AlphaGross BetaI-131Gamma SpectroscopyTritium

MMBWMM

Well (ground)Water-

Gross AlphaGross Beta

~ Gamma SpectroscopyTritium

MMMM

Drinking Water(e)

MC, BWC Gross AlphaGross BetaI-131Gamma SpectrometryTritium

MMBWMM

Note: See footnotes at end oftable.


A endix B

TABLE1

(Page 2 of3)

Annual Analytical Schedule for theSusquehanna Steam Electric Station (PPEcL)


No. of SampleMedia dk Code Locations Fre . a Anal ses Re uired

AnalysisFre. b

Precipitation 13 QC Gross AlphaGross BetaGajjnma SpectrometryTritium

Q.QQQ

Cow Milk M, SM(0 Gross Beta-K-40Strontium-89/90I-131Gamma Spectrometry

SM,MSM,MSM,MSM,M

Food Products(Various Fruitsand Vegetables)

15 A Gamma Spectrometry A

Game

Poultry and Eggs

Soil

Vegetation

Direct Radiation

Algae

'10

10

1064

A

A

A

QQ/A~

Gamma Spectrometry

Gamma Spectrometry

Ganuna Spectrometry

Gamma Spectrometry

TLDPIC/TLD

Gamma Spectrometry

A

A

A

A

QQ/A

(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 B

TABLE1

(Page 3 of3)

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


(c) Ifthe gross beta activity is greater than 10 times the yearly mean ofthe controlsample, gamma analysis should be performed on the individual filter. Gross betaanalysis is performed 24 hours or more followingfilterchange to allow for radonand thoron daughter decay.

(d) Stations 6S6 and 6S7 are checked weekly to ensure automatic composite sampleroperation which is time proportional. Station 6SS is grab sampled weekly.Individual composites ofthe weekly samples are made both monthly (MC) andbiweekly for analysis.

(e) Water fi'om stations 12H2 RAW and 12H2 TREATED is collected weekly.Individual composite samples ofthe weekly collections are made both monthly(MC) and biweekly for analysis. 12H2 RAW is a time proportional automaticcomposite sampler. 12H2 TREATED is a daily grab sample.

(f) Stations 12B3, 10D1, 10D2, and 10G1 were analyzed semi-monthly from Aprilthrough October.

(g) The TLD at PIC3 is only exchanged once per year (end ofsecond quarter). TLDsat all other PIC locations were exchanged quarterly for the first two quarters ofthe year. Location ofTLDs at PIC sites was discontinued at the end ofthe secondcalendar quarter.


APPENDIX C

;:RENIP„':,INONslTOR'ING~I'."''OCA'TIO¹'DE


A endix C

TABLEC 1

(Page 1 of5)

TLDMonitoring Locations for the SSESRadiolo 'cal Environmental Monitorin Pro ram - 1994

Less Than One Milefrom the SSES 'See Fi re 2

LocationCode1S2

Distancemiles0.2

Direction

N Perimeter Fence

Description

2S2

2S3

PIC2

0.90.2

0.9

NNE Ener Information CenterPerimeter Fence

Ener Information Center3S23S3

3S4

4S1

4S3

5S1

SS4

SS7

6S4

0.50.90.3

1.0

0.2

0.80.80.3

0.2

NE'SE

SSES Backu Met TowerRiverlands . Comfort StationPost, West ofSSES Access Processin FaciliSu uehanna River Flood PlainPerimeter Fence

North ofEnvironmental LaboratoWest ofEnvironmental LaboratoPerimeter Fence

Perimeter Fence6S8 0.2 ESE Site Pole No. 44316/N340366S9

7S6

7S7

7S8 i

8S2

9S2

10S1

0.2

0.20.4

0.4

0.2

0.2

0.4

ESESESE

SE

SSE

SSW

Perimeter Fence south

Perimeter Fence

End ofKline's RoadKline Residence

Perimeter Fence

Securi Fence

Post - south ofswitchin station10S2

10S3

0.20.6

SSW Securi FenceSSW Confer's Lane - south ofTowers Club

11S2

11S3

11S6

11S7

0.40.3

0.5

0.4

SWSWSWSW

Towers ClubSecuri Fence

Location offormer SW ANSP GardenSSES Access Road Gate 850

12S1 0.4 WSW SSES Em en 0 erations Facili

1994 Radiological Environmental Monitoring Report C-2

TABLEC 1

(Page 2 of5)

TLDMonitoring Locations for the SSESRadiolo cal Environmental Monitorin Pro ram - 1994

Less ThanOneMilefromtheSSES' SeeFi re2

LocationCode12S3

12S412SS

12S6

13S2

13S4

13S5

Distancemiles0.4

0.40.40.4

0.40.40.4

Direction

WSW'SW

WSWWSW

WWW

Perimeter Fence

Perimeter FencePerimeterFencePerimeter Fence

Perimeter FencePerimeter FencePerimeter Fence

Description

13S6

14SS

14S6

15S4

15SS

16S1

16S2

6A4

15A3

16A2

0.4

0.5

0.7

0.60.4

0.3

0,3

0.6

0.6

0.9

0.9

0.8

ESESE

SSE

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

Perimeter Fence east

Perimeter Fence westRiverside RestaurantU.S. Route. 11 - south ofState Police BuildinPP&L Wetlands Si . S. Route 11

Krisanda Residence

Ru inski Residence

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

1B1 1.4 N Mn eInnRoad

4B1

1.3

1.4

1.2

NNE Durabond Co orationNNE U.S. Route 11/Min e Inn Road IntersectionENE Stone Crusher Trail Entrance

SB2 1.4

1.4

1.5

1.7

ESESESE

PA Route 239/Ruckles KllIntersectionPalmisano Shootin Ran e EntranceHeller's Orchard StoreCouncil Cu Overlook

C-3 1994 Radiological Environmental Moaitoring Report

A endix C

TABLEC 1

(Page 3 of5)

TLDMonitoring Locations for the SSESRadiolo 'cal Environmental Monitorin Pro ram - 1994

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

LocationCode9Bl

Distancemiles

1.3

Direction Description

Transmission Line - east ofRoute 11

10B210B3

10B4

12B412B5

2.01.7

1.4

1.7

1.8

SSW Al att Residence

SSW Castek Inc.SSW U. S. Route 11/River Road IntersectionWSW Shultz FarmWSW Shutz Farm Intersection ole ¹43401/N33620

13B1 1.3 W Walker Run Creek ele. Pole ¹3614B2

14B3

15B1

16Bl'6B2

1.7

1.3

1.7

1.6

1.7

W|AV Stone Church Road ole ¹43364/N334380WNW Moskaluk Residence

Coun Estates Trailer ParkNNW Walton Power LineNNW Walton Power Line

1 lcl1D2

1DS

2.0

4.04.0

SWN

Salem Townshi Fire Com an

Mocana ua AirSam lin StationShickshinn /Mocana ua Sewa e Treatment Plt.

3D1 3.4 NE Pond Kll

8D3

3.5

4.03.6

ESESSE

St. Peters Church - HobbieMo Residence

Coun Folk Store10D1

12D2

14D1

1E1

3.0

3.7

3.6

4.5

SSW R. &C. R FarmWSW Da ostin Residence

WMV Moore's Kll/Min e Inn Roads IntersectionLane Residence

PIC3 4.2 N Shickshinn Munici al Buildin4E1 4.8

4.7

4.5

4.7

ENE Ruckles KllRoadENE Ruckles Kll/Pond HillRoads Intersection

Bloss FarmESE St. James Church


A endix C

TABLECl(Page 4 of5)

TLDMonitoring Locations for the SSESRatholo 'cal Environmental Monitorin Pro ram - 1994

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

LocationCode

DistancemBes


4.2 SE 'aiwood Transmission Line Pole ¹211E1 4.7 SW Thomas Residence

12E1 4.7 WSW 'Berwick Ho ital13E4 4.1 W Kessler Farm14E1 4.1 WNW Canouse Farm

Greater than Five Miles from the SSES 'See Figure 4

3F1

5.9

9.1

NNE St. Adalberts Cemet

Valania Residence9.9

8.5 SSE

Sheatown Intersection

HufFResidence

PIC1

15F1

16F1

PIC43G43G5

4G1

5.2

5.2

5.4

7.8

10.7

17

16

14

WSW Berwick Substation

WSW Berwick Ci HaH

Zatwatski FarmNNW Hidla Residence-NE = Nanticoke Munci al Buildin

Wilkes Barre Service CenterPanish Street Substation

Mountainto - Crestwood Industrial Park7G1

7G214

12

SESE

Hazleton PP&L Com lexHazletonCemete -7th Street ole¹31852-

12G1

12G4

15

10

WSW PP&L Service Center BloomsburWSW Naus Residence

C-5 1994 Radiological Environmental Monitoring Report

A endix C

TABLEC 1

(Page 5 of5)

TLDMonitoring Locations for the SSESRadiolo cal Environmental Monitorin Pro ram - 1994

a) Alldistances &om the SSES to monitoring locations are measured &om the standbygas treatment vent at 44200/N34117 (Pa. Grid System). The location codes arebased on both distance and direction &om 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 of the locations &om the SSES as

described below:

S-onsiteA- <1 mileB - 1-2 rmlesC -2-3 rmiesD -34 miles

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

The numbers preceding the letters in the location codes provide the directions of themonitoring locations &om the SSES by indicating the sectors in which they'relocated. 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 &om 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 distances&om the SSES.

b) 7S8 was improperly designated as 7A1.


A endix C

l 4

TABLEC2(Page 2 of5)

Sampling Locations for the SSESRadiolo 'cal Environmental Monitorin Pro ram - 1994

Less Than OneMilefrom the SSES' SeeFi re5

LocationCode

8A4

15A3

DistancemQes

0.9

0.8

0.9

Direction

SSE

SSE

/VEButz Residence

AllenResidence

Krisanda Residence

Descnptton

2S

3S

SS

15S

16S

on site

on site

on site

on site

on site

NNE SSES on site

SSES on site

SSES on site

SSES on site

NNW SSES on site

2S2

3SS

4SS

12S1

0.9

0.9

0.5

0.5

0.5

Ener Information Center

Riverlands Sto e Closet

Trainin CenterWhite House

SW EOF Buildin

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

1D3 3.9 N Mo uaBrid e

IND 0.9- 1.4 ESE At or Below the SSES Dischar e DifRser":i.".,',"'.".".<.'i':i-::"::-"'::k-"""-'--~h'"st~~"::.-'=~,",.'.-":b.':

1.6 NNE Gould Island

1.2 SE Bell Bend11C 2.6 SW Hess Island

2B 1.6 NNE Gould Island7B 1.2 SE Bell Bend


A endix C

TABLEC 2(Page 4 of5)

Sampling Locations for the SSESRadiolo cal Environmental Monitorin Pro ram - 1994

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

LocationCode

DistancemBes


cb@„':;,4,"8,(-"j~"~jK"„.;;g .. ~~gj$+~%gp~ePj~gg+$ P>~~":SURFA~~>~ATER'<'onti $,,<>$ ~+(fj;,.cgjggr„.<',„'pe'j,",.c~~gvPr:>'~j;,gmgp~P':j<<v,~,y~

12G2 17 WSW US Radium Site Bloomsbur1281 26 WSW Merck Co.

,: c + '< . g '.,'~. zggct>~+A~'4+ %y~~c Q$ 'y&R.; 5 „:iQ:., AMpg+ccg@, DRINKING)~ATERQp+"ig;" 'pe'$ >w':j ~ ppr'+ grjo., ++3 gx~+M );.:jp@

12H2R 26 WSW Danville Water Co. raw12H2T 26 WSW Danville Water Co. treated

2H 30 30 Near Falls, Pa.

6.4 Between Shickshinny and Retreat State CorrectionalInstitution

WSW Old Berwick Test Track6.9

7G1 14 SE PP&L's Hazleton Chemi Labt'2G115 WSW PP&L Service Center, Bloomsbur

'''> /)g< yk,'j. S .(P'g ';( gC'PgjMRC~5').,:.$ )P';:.,"jy+j@gyg,:Q<,r4+gffgQ 5'j@C'g)K/1(,.'8CgyCP~jg+%j{'<jr3$@(qgPSA:4 >Pj(<j p jS$j.;'.P,.<C)%QS.

10G1 14 SSW Davis Farm

12F-",: Ri''- i.:-~e'4Ã'-''~i'-'''''.".'::A'1R/PRECIPITATION/SOII'iVEGETATIONN"''-:-;4@".i""-'""-''"'''':"'":~YP'"'-"'~"'"."'::"":;~

10F2

12FS

12F7

13G2

6.0

7.5

8.3

16

SSWWSWWSW

W

Karchner Farm

Seesholtz FarmLu ini FarmKileFarm

2H. 30 NNE Near Falls PA16F 5-10 NNW OfF-Site

., ~ <':Pq.,:~~".',"„". 'vi<":;p':~P'j%~N>'cj':;jg4jj3'gjg~j~",~cog~'dGROUND ~ATERq~s;.w,'",;5':.~o~gig~ pg%)~>jjY~":~+jkj'',;< ..i~%&'~%~A)k»': 'r

12F3 5.2 WSW Berwick Water Com an

1994 Radiological Environmental Monitoring Report C-10

A endix C

TABLEC2(Page 5 of5)

Sampling Locations for the SSESRadiolo cal Environmental Monitorin Pro ram - 1994

a) Alldistances &om the SSES to monitoring locations are measured &om the standbygas treatment vent at 44200/N34117 (Pa. Grid System. The location codes are basedon both distance and direction &om the SSES. The letters in the location codesindicate ifthe monitoring locations are on site (within the site boundaty) or, iftheyare not on site, the approximate distances of-the-locations &om the SSES asdescribed below:

S-onsiteA- <1mileB - 1-2 milesC-2-3 tmlesD -34 miles

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

The numbers preceding the letters in the location codes provide the directions ofthemonitoring locations &om 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 &om 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 difFerentiate. sampling locations found in the same sectors at approximately the same distances&om 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 followingthe letter in the location code.

d) Vegetation is not available at this locations.

C-11 1994 Radiological Environmental Monitoring Report

APPENDIXD


A endix D

1994 LAIMUSE CENSUS RESULTS

The SSES Technical Specifications require that a census be conducted annually duringthe growing season to determine the location ofthe nearest milkanimal, residence, andgarden greater than 50 m (=500 ft ) producing broad leaf vegetation in each of the 16

meteorological sectors within a distance of8 km (~5 miles) in each ofthe 16meteorological sectors surrounding the SSES. To comply with this requirement, a land-use survey was conducted for the SSES during 1994. The closest qualified gardens andresidences and all dairy animals within five miles ofthe SSES in each ofthe 16 sectorswere identified.

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 milkmust 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.

1994 Radiological Environmental Monitoring Report 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, 1994.

NEAREST MD,RESTSECTOR DIRECTION RESIDENCE GARDEN

NEARESTDAIRYANHNAL

10

12

13

14

15

16

NNNE

E

ESE

SE

SSE

S

SSW

SW

WSW

W

WNW

NW

NNW

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

1.3 mi

1 ~ 1mi

2.3 lnl

2Ami'.4

mi

0.5 mi

0.6 mi

0.8 mi

1.2 mi

1.9 mi

1.1 mi

1.2 mi

1.3 mi ~

0.9 mi

4.0 mi

>5.0 mi

>5.0 mi

>5.0 mi

>5.0 mi

4.5 mis

2.7 mis

2.6 mi~

>5.0 mi

3.9 mis

3 0 mia,b,c,e,g,

>5.0 mi

2.0 mia

5.0 mia

>5.0 mi

>5.0 mi

4.2 mis

~ ~

Chickens raised for consumption at this location.

Ducks raised for consumption at this location.C

Eggs consumed from chickens raised at this location.d

Geese raised for consumption at this location.

'Pigs raised for consumption at this location.

Turkeys raised for consumption at this location.

'Fruits/vegetables grown for consumption at this location.

'Rabbits raised for consumption at this location

D-3 1994 Radiological Environmental Monitoring Report

APPENDIX E

1994 Radiological Environmental Monitoring Rcport

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. TheUD-814 TLDbadges each contain four elements. Elements 2, 3, and 4 in each badge aremade ofcalcium sulfate with 800 mg/cm ofGltering and element 1 is composed oflithium tetraborate with Gltering 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, greatersensitivity 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 ofthe other elements in each batch that is produced. Nevertheless, each element

. ends up somewhat different in its response to radiation. In order to minimize the effectofthese inherent differences when comparing actual monitoring results for differentelements, element correction factors (ECFs) are determined for each element. The ECFsare used to effectively normalize the readings ofthe Geld elements placed at particularmonitoring locations for given monitoring periods to the average ofthe readings thatwould be expected ifso-called reference elements were to be placed simultaneously atthose individual locations. Reference elements are elements that have been demonstratedto 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.After this process has been repeated at least sev'eral 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 ofradiation (100 mR) and processed, a minimum ofthree times each. Eachelement reading is then divided by the mean ofthe readings obtained &om referenceelements (typically 30 to 35) that were exposed to the same amounts ofradiation 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 a'nd then dividing by the totalnumber ofthe processings performed.


A endix E

The followingequation shows how ECFs are calculated:

where

E, an uncorrected exposure reading for the element.

n = the total number ofindividual 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 Geld distribution andbetween retrieval &om the Geld 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 Rom 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-137 source at the University ofMichigan. The irradiated TLDs areaccompanied enroute to and from the University ofMichigan by transit control TLDs.An estimate ofthe exposures received by the irradiated TLDs in-transit is obtained byprocessing the transit controls and determining the transit control mean by the followingequation:

where

n

ECF, „tc n

the mean of the elementally corrected exposure readings ofallthe transit control elements.

E, = the uncorrected exposure reading ofeach individual transitcontrol element.

1994 Radiological Environmental Monitoring Report '

A endix E

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

n= the total number ofindividual element exposures averaged.

The mean ofthe transit control exposures is then subtracted &om each ofthe elementallycorrected exposures ofthe irradiated elements to obtain the net exposures for eachelement resulting &om the irradiation. The mean ofthese net exposures is then dividedby the known exposure (100 mR) &om the irradiation to determine the RCF. Thefollowing equation describes the calculations performed:

E/ECF/

where

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

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


EE„= the known exposure for each ofthe irradiated control elements.

Exposure readings for individual field monitoring elements are corrected using both theelemental and run correction factors as follows:

CE, = UE»

ECF, x RCF„

where

CE = the corrected exposure reading for field monitoring element x.1

E = 'he uncorrected exposure reading for field monitoring element x.

ECF, = the elemental correction factor for Geld monitoring element x.


A endix E

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

The exposure representing each environmental monitoring location and monitoringperiod is normally the mean ofthe corrected exposure readings for a total ofsix calciumsulfate elements, three &om each oftwo diFerent TLDs at each location. The followingequation shows the calculation ofthis exposure:FACE,

where

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

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


The mean ofthe corrected exposure readings for a given location and period may becalculated using less than the six calcium sulfate elements ifthe reading &om one oftheelements 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 ofthe corrected elemental exposure readings:

n-1

where

S„= the standard deviation ofthe corrected exposure readings from a

given monitoring location and period for (n-1) degrees of&eedom.

E =C

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

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


A endix E

the total number ofindividual element exposures averaged.

The standard monitoring period for the reporting ofTLD exposures is the calendar

quarter. 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 ofthe 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

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

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

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

TLD DATAINTERPRETATION

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 ofthesechanges, 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:

l I

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


A endix E

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

Note:

The r; are the quotients ofthe indicator doses to the average doses ofthefollowingcontrol locations: 3G4, 4G1, 7Gl, 1261, and 12G4. Only thesecontrol locations are used because they were the only ones existing during thepreoperational period.

Operational r; for indicator locations that do not have preoperational histories arecompared with the range ofpreoperational control-to-control-average dose ratios (r,)experienced at control locations. It can be safely assumed that the preoperational rangeofthese 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 contributionRom the SSES operation. The following equation shows how r, is calculated:

PC C C

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 locationwith a preoperational history by multiplying the standard deviation (S) ofthe r; for thelocation by the appropriate t score (t) based on the applicable degrees of&eedom for,each location. (Degrees offreedom (df) are equal to the number ofratios that wereaveraged less one.) The product ofthe t score and the standard deviation (tS) was thensubtracted &om the mean (x) to determine the lower end ofthe 95% confidence range(R) and added to the mean to obtain the upper end ofthe range (R) as indicated by thefollowing equation:


A endir E

R= x—t+S to x+ t+S

The following t scores were used in the range calculations:

dftSCORES

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 ofr, 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 asthe excess ratios. Excess ratio for each location's r; for a particular calendar quarter isthe am'ount 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 areasonable estimate of the portion ofthe calendar quarter that a MEMBEROF THEPUBLIC might spend near an onsite TLD location. The following is a table ofoccupancy factors that are used:

Environmental TLDMonitorin LocationsOnsiteOffsite other than Private ResidencesPrivate Residences

Occupan'cyFactors.4.56E-43.65E-3

i994 Radiological Environmental Monitoring Rcport

A endix E

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

where

Dasss - is the dose attributable to SSES fuel cycle operations,

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

r, - is the indicator-to-control average ratio corresponding to theupper end ofthe 95% con6dence range for a particularlocation for the preoperational period, and

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

OF - is the occupancy 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:

=(r,—1.22)xD xOF

where

Dashes - is the dose attributable to SSES fuel cycle operations,

- 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.

D~ - is the average quarterly dose for control locations.


A endix E

OF - is the occupancy factor.

Each year, the SSES attributable doses calculated for each calendar quarter are summed

for all calendar quarters at each location to obtain annual doses by location.

1994 Radiological Environmental Monitoring Rcport E-10

A endix E

DETERMINATIONOF GROSS ALPHAAND/ORGROSS BETAACTIVITYTELEDYNE ISOTOPES

One liter aliquots ofwater samples are treated with about one milliliterofconcentratednitric acid and evaporated to near dryness in beakers. The remaining volumes(approximately five millilitersor less) are transferred to stainless steel planchets andevaporated to dryness.

Two hundred or more grams ofeach fish sample are dried and then ashed in a mufHefurnace. One gram ofeach ashed sample is then transferred to a stainless steel planchet.

Approximately 50 grams ofeach soil or sediment sample is dried by heat lamp over aperiod ofa couple ofdays. One gram ofeach dried sample is then transferred to astainless 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 eKciencyoccurring 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 ofthe air particulate filters becauseofthe impracticality ofweighing the deposit and because the penetration depth ofthedeposit into the filter is unknown.

Quarterly composites ofthe weekly air particulate filters are counted for gross alphaactivities. Preparation for counting involves the dissolution ofthe 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.


A endir E

CALCULATIONOF THE SAMPLE ACTIVITY

—+gCt

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

2.22 (V) (E)random

uncertainty

where: C = total counts for sample

t = count time for sample/background (minutes)

R, = background count rate ofcounter (cpm)

2.22 = ~dmpCi

V(M)= volume or mass ofsample analyzed

E = efficiency ofthe counter (cpm/dpm)

Calculation of the Minimum Detectable Concentration Value

2.22 (V) (E)


A endix E

RADIOCHEMICALDETERMINATIONOF I-131INMILKANDWATER SAMPLES

TELEDYNEBROWN ENGINEERINGENVIRONMENTALSERVICES

A four-liter aliquot ofsample is first equilibrated with stable iodide carrier. Following aperiod oftime sufBcient for equiTibration, anion exchange resin is added to the aliquot tocapture the iodide ions present. The iodide ion is subsequently removed &om the resinusing sodium hypochlorite. Hydroylamine hydrochloride is then used to produce Beeiodine. The resulting &ee iodine is then extracted &om 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 ofthe sample is used to determine the stable iodide content ofthe milkby the use ofa specific-ion electrode. This information is then used to correct thechemical yield determined &om the mass ofthe dried precipitate obtained.

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

CALCULATIONOF THE SAMPLE ACTIVITY

C—-Rb, 2

C—+Rb

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

net activity random uncertainty

where C = total counts from samplet = counting timeforsample(min)

R = background countrateofcounter(cpm)

2.22 ~dmpCi

volume ofsample analyzed (liters)

chemical yield of the mount or sample counted


A endix E

DF =, decay factor &om the collection to the mid-count time

E = efBciency ofthe counter for the I-131 betas.

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

Calculation of the MDC

2.22(V)(Y)(DF)(E)

1994 Radiological Environmental Monitoring Report E-14

A endix E

. DETERMINATIONOF TRITIUMINWATERBY LIQUIDSCINTILLATIONCOUNTING


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

CALCIJLATIONOF THE SAMPLE ACTiWXXYFOR TRITIUM

—-Rr 2

C—+Ra

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

net activity

where: C = total counts &om sample

random uncertainty

t = count time for sample (minutes)

background count rate ofcounter (cpm)

2.22 =

pCi

initial volume before enrichment (liters)

ef6ciency ofthe counter for tritium (cpm/dpm)

Calculation of the MDC

(2.22)(V)(E)


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, soil/sediments, biological media, etc. Each sample is prepared andcounted in standard geometries such as one liter or four liter wrap-around Marinellicontainers, 300 ml or 150 ml bottles, two-inch filterpaper source geometries, etc.

Samples are counted on large ( 55 cc volume) germanium detectors connected toNuclear Data 6620 data acquisition and computation systems. Allresultant 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.

CALCULATIONOF THE SAMPLE ACTIVI'IY

[C B]j -2JC+B2.22(V)(E)(GA)DF)(/) 2.22(V)(E)(GA)(DF)(1)

net activity random uncertainty

where: C = area, in counts, ofa spectral region containing a gamma emissionofthe 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 are

. summed for C and used in the calculation of "net"

activity.


A endix E

background counts in the region ofinterest, calculated by fittinga straight line across the region connecting the two adjacentregions.

Note: Ifno peak exists in a region &om which a "net"activity is being calculated, background isrepresented by the average ofthe counts in onechannel &om each side ofthat region.

t = counting interval ofsample (minutes)

2.22 = dpm/pCi

V = volume or mass ofsample analyzed

ef5ciency ofcounter at the energy region ofinterest

GA gamma abundance ofthe nuclide at the gamma emission energyunder consideration

DF = decay factor &om sample collection time to midpoint ofthecounting interval

Calculation OfThe MDC

4.t sJcMDC (pCi Ivol or mass) =2.22(V)(E)(GA)(DF)(t)

The width ofthe region around the energy where an emission is expected is calculateddifferently for MDCs than it is for the width ofa peak that is actually identified.Consequently, the value ofC used in the two equations may differ.

~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 RADIOSTRONTIUMINMILKANDWATER


Strontium-89/90 analyses are routinely performed on milk samples and occasionallyperformed on water samples for PP&L. The first step in the preparation ofmilk andwater for analysis is the addition ofstrontium carrier. The addition ofstable strontiumfacilitates the precipitation ofany radioactive strontium that may be present and providessufBcient quantities ofstrontium to be able to reHably determine the amount ofradioactive strontium recovered &om the samples for counting.

Subsequent steps 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 ofthe 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 ofthe 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 carrier 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.After 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.


A endix E

The Biter discs are mounted on planchets prior to counting. Strontium-89 activity isdetermined by counting the strontium planchets while they are covered with 80 mg/cmaluminum absorbers to eliminate interference &om the strontium-90 betas. Strontium-90activity is inferred by counting the yttrium planchets.

CALCULATIONOF THE SAMPLE ACTIVHY

—-Rs 2

unit volume mass 2.22(V)(yi)(yz)(DF)(IF)(E) 2.22(V)(yi)(y2)(DF)(IF)(E)

C = total counts &om sampleI

t = counting time for sample (background)

R = background count rate

f = ash&action(gmash/gmmilk)

V = volume ofsample analyzed

y, = chemical yield ofyttrium

y2= chemical yield ofstrontium

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

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

E = ef5ciency ofthe counter for Y-90


. Rb4.66

'.22( )(Y>)(Y2)(D)(I)( )


A endix E

CALCULATIONOF THE SAMPLE SR-89 ACTIVITY

C—-Bc-BA 2f —+Bc+ BA / iCpCi g f

unit volume (mass) 2.22(V)(Y.)(DF -ei(F - m) 2.22(V)(Y,)(DF ~)(~ t|,)

where

Bc

total counts &om sample

counting time for sample

background rate ofcounter using absorber con6guration

B„= background addition from Sr-90 and Y-90 ingrowth

(cpm)

ash fraction (gm ash/gm milk)

volume ofsample analyzed

Ys = chemical yield ofstrontium

DFs„a~ = decay factor from the mid-collection date to the countingdate for Sr-89

E$ $9= efficiency ofthe counter for SR-89 with the 80 mg/cm

aluminum absorber

*Note that BA is a calculated value.


4 (jgf [Bc+BAI

~C=2.22(V)(Y.)(DF» - «)


1

APPENDIX FgvkVk'ke(k . kkM<8 . ~N,(kgb�'tvk:wrCV(W+rWPgNPPYr! ., v.~r.y.PPrCrNW X(CVkVvw@vgYu(Cww'k'.%

@gal v.:P'kvwk k.,wkwwkrP >v,.sgk.'Vvk wkwgvvwvV"kvk

-:::;-:,',,';:.:1994'.EXCv'-EPTIONS,-:,,TO„-,TH'EE':SSES";:;:T~EC~:-HNkICAI':,""::;"',,':.'",.';'- .-.':I';:-::'-::,":-).""SP,

':-"i"'"';:"'-.':"""',iMKT'HOD'8'i'A''ND'<ANA''L'YSI'S,'S'ENSIT>IV)XTIESi""'.j'''':";Nj~


A endix F

Exceptions to the SSES Technical Specifications occurred in the monitoring ofthefollowingmedia: ambient radiation, surface water, drinking water, air, and milk. Theseexceptions are discussed in this appendix and specifically documented in the tables ofAppendix I.

These exceptions involved the following: sample collections that did not take place for, the required periods; sampling that was performed in a manner not stated in theTechnical Specifications; and analysis sensitivities that exceeded those required. Theseproblems generally occurred because ofequipment malfunctions, sampling personneloversights, and events taking place in the vicinityofmonitoring stations that interfered insome way with the normal course ofsampling.

Ambient Radiation

The only exception that occurred at ODCM-listed environmental TLD monitoringlocations in 1994 was at control monitoring location 3GS. TLDs that had been placedin the field for the monitoring period April6 through July 12, 1994, at this location werenot able to be retrieved. The TLDs were missing and presumed to have been stolen.TLD monitoring at location 3GS was discontinued at the end of the 1994 third calendarquarter; this location was removed from the ODCM list ofrequired environmental TLDmonitoring locations. Refer to Appendix Aofthis report for a discussion ofchangesaffecting environmental TLD monitoring locations.

Surface Water

Monitoring at control location 6S6, the SSES River Water Intake Structure, andindicator location 6S7, the SSES Cooling Tower Blowdown Discharge (CTBD) to theSusquehanna River, are the only environmental surveillances ofsurface water requiredby SSES Technical Specifications. The other six surface water monitoring locations ofthe SSES REMP on the Susquehanna River, both upstream and downstream from theSSES discharge to the river, are not required, but are performed to provide addedassurance that the environment is not being compromised by radiological releasesresulting from the SSES operation.

Sampling at locations 6S6 and 6S7 is required to be continuous. Composite samplesfrom these locations are required to be analyzed monthly and are expected to berepresentative ofthe streams from which they are collected. Problems in 1994 withautomatic composite samplers (ACSs) at these sampling locations led to periods whenno water was being collected and to periods when water was being collected at anuncontrolled and indeterminate rate, resulting in samples that were not as representativeofthe water flowing in the sampled streams as desired. In some cases, the ACSs weredeliberately removed from service to permit performing maintenance on the samplers. Inother cases the ACSs were taken out ofservice because maintenance was beingperformed on related equipment or systems. Grab samples were obtained at the required

1994 Radiological Environmental Monitoring Report F-2

A endix F

locations at weekly intervals when the ACSs were known to be inoperative or operatingin an uncontrollable or indeterminate fashion.

An improvement was made in 1994 over the 1993 sampling performance at 6S7; 6S7was represented by continuously collected samples for more than 86% ofthe year. Atotal of6 grab samples were collected at 6S7 in 1994, as well as two other grabs at analternate location in January and October when no water could be obtained from 6S7 inthe form ofgrabs.

On January 24 and October 10, 1994, no grab samples could be collected at 6S7 becausethe pump supplying water to the ACS was completely inoperative. Grab samples were,obtained directly &om the Susquehanna River, at location 6SS, on these dates as analternative. The event on January 24, 1994 triggered the writing ofa SignificantOperating Occurrence Report (SOOR 894-073) and steps were promptly initiated toreturn the pump and ACS to operating condition. During the period from October 9through October 14, 1994, the ACS at 6S7 was not operating to permit routinepreventative maintenance to be performed by PP&L personnel.

The ACS at 6S7 was considered to be sampling unrepresentatively for the followingperiods in 1994: January 10 through 17, June 27 through July 5, and July 25 throughAugust 8, 1994. Grab samples were collected at 6S7 on the following dates in 1994:January 10 and 31, July 5, August 1 and 8, and October 17. Grabs Rom August 1 and 8were composited and analyzed as one sample.

A new ACS was purchased an'd installed in December, 1994, to sample the CTBD at anew location. Because ofthe greater depth ofwater that is expected at the newsampling location, the reduced turbulence ofthe water as a result ofthe lower watervelocity expected there, and the reduction in the mixing ofair with the water at the newlocation, a significant reduction in sampling problems is anticipated. Functional testingand trial operation ofthe new ACS have been delayed; pending the solution ofproblems 'involved with the creation ofa signal from a recently installed flow sensor that willbeused to enable operation ofthe new ACS in a flow proportional mode. It is nowexpected that the new ACS willbecome operational before the middle of 1995.

Grab samples were collected at control location 6S6 the following seven times in 1994because ofquestions about the representativeness ofcontinuous sampling for the normalcollection periods: January 10, 17, 24, and 31, February 28, March 7, and April4. Allofthe grabs collected at 6S6 in January were composited and analyzed as one sample.The February 28 and March 7 grabs at 6S6 also were composited and analyzed as onesample.

The ACS at 6S6 was inoperative for briefperiods on February 4 and May 3, 1994, toallow for maintenance. The ACS down time at 6S6 during the sampling week ofMay 2through May 9 contributed to less than one gallon ofwater being collected that week.As a result, only 124 ounces rather than a full 128 ounces'(one gallon) ofwater was

1994 Radiological Environmental MonitoringReport

A endix F

composited with one gallon aliquots from each ofthe remaining weeks ofthecompositing period May 2 through June 6, 1994. The only other unusual occurrencewith the ACS at 6S6 in 1994 was on May 24 when it was observed that no water wasflowing through the ACS. This situation was corrected the same day and the ACSresumed sampling. f

Allrequired analyses of6S6 and 6S7 samples were performed with only one exception.,Although all samples were analyzed by gamma spectroscopy for gamma-emittingradionuclides and by liquid scintillation specifically for tritium with a frequency equal toor greater than required, radiochemical analysis for iodine-131 was inadvertently omittedfor the January 10, grab sample from location 6S7. Radiochemical analysis for iodine- .

131 is not specifically required, but is performed to attain greater sensitivity in themeasurement ofiodine-131 activity levels than could be achieved practically using onlygamma spectroscopy. This analysis method is used for iodine-131 to ensure that theanalysis sensitivity of 1 pCi/1 required by Technical Specifications is met.

Analysis sensitivities required by Technical Specifications were met for all 6S6 and 6S7samples but one in 1994. Gatnma spectroscopic analysis sensitivities for the parentradionuclide barium-140 and its daughter lanthanum-140 were not met when a 6S7 grabsample from January 10, 1994 was analyzed. The reason for not meeting these analysissensitivities was the unnecessarily long time between collection and analysis ofthesample. The sample was not sent to the radioanalytical laboratory untilFebruary 8, 1994, and was not counted'until February 16, 1994. This length oftimepermitted appreciable decay ofthe relatively short-lived parent radionuclide, which whencombined with other factors, made it virtually impossible to meet the requiredsensitivities. As a result, a MDC of70 pCi/I was achieved for barium-140 instead oftherequired 60 pCi/1 and a MDC of30 pCi/1 was obtained for lanthanum-140 instead oftherequired 15 pCi/1. The group responsible for sample collection has been reminded oftheneed to send grab samples that willnot be composited with other grab samples to theradioanalytical laboratory as soon as practical.

Drinkin Water

Problems also were experienced in 1994 with the ACS located at the drinking watersampling location 12H2, the Danville Municipal Water Authority. Both raw (untreated)and treated water are sampled at this facility. However, an ACS is used only for thesampling of the raw water. Raw water sampling is designated as 12H2R.

Sampling at 12H2R was more troublesome in 1994 than it had been in 1993, despiteefforts to improve the sampling situation. Only 62% ofthe sampling was represented bycontinuously'collected samples; the remainder being comprised ofgrab samples, some ofwhich were composited. Reasons for departure from the desired continuous sampling atthis location throughout 1994 were varied. In some cases, the pump supplying water tothe ACS was deliberately shutdown or stopped pumping because ofclogging caused bysediment and/or other debris so that no water could reach the ACS. In one instance, no


A endix F

water was being collected by the ACS because a sample collection person left the intaketubing to the ACS attached to the piping that supplies tap water for flushing the ACS. Inother cases, water did reach the sampler during the sampling period, but the low ratewas uncontrolled, resulting in the collection ofsamples that were not properlyrepresentative ofthe entire sampling period. In these instances, water either wasobserved to be overflowing from the sample collection container or found to be presentin insufBcient quantities in the containers at the time ofthe weekly water pickups. Bothconditions indicate that the flowrate varied during the week from that at which thesampler was set at the beginning ofthe week.

The pump supplying water to the ACS was shutdown on April25 to permit disassemblyand cleaning ofthe sampler by Ecology-III sampling personnel and also on December 15

to permit the removal ofsediment by a PP&L Construction crew &om piping connectingthe pump to the ACS. Again, the pump supplying water to the ACS was turned ofFbyDanville Municipal Water Authority personnel on December 19, 1994, to permit cleaningofwell ¹18. Well ¹18 is one oftwo wells (the other well is the downriver well ¹16) atthe Danville facility through which water Grst enters the facility. Because the purpose ofthese wells is to provide for the settling out ofsediment and debris from the water priorto further processing ofthe water, the wells require removal ofaccumulated materialsfrom time to time.

Grab samples were collected at 12H2R and analyzed in place ofcontinuously collectedsamples on the following dates because the collection tank was found to be overflowing:March 21, May 9, 16, 23, and 31, July 18, September 26, and November 28. Grabsamples also were collected at this location on the following dates because oflower thanexpected volumes in the collection tank: March 14, March 18, April4 and 18, andMay 2. In addition, grab samples were obtained on the following dates because no waterwas reaching the ACS: February 28, July 25, August 15, and September 6. The onlyinstance in 1994 when neither a continuously collected. sample nor a grab sample wereobtained at 12H2R was on February 22, when the sampling pump was inoperative andno grab sample could be collected from the river due to hazardous, weather-relatedconditions.

Whenever grab samples were collected on consecutive weeks, these samples werecomposited and analyzed as one sample. The following periods were represented bycomposited grab samples: March 21 through April4, April 18 through May 2, May 9through June 6, and July 18 through July 25.

Varying flow rates and other sampling problems experienced at 12H2R in 1994 hadvarious causes, depending on the sampling arrangement at any given time. Raw watersamples were taken from January through the middle ofMarch, 1994 and again &omJune through the end ofthe year out ofwell ¹18 at the Danville facility. For theremainder ofthe year (mid-March until the beginning ofJune), water was obtained &oma turbidity line downstream ofwell ¹18. Neither location was ideal and both contributedto the sampling dif5culties that were experienced.

F-5 1994 Radiological Environmental MonitoringReport

A endix F

Turbidity line sampling created dUBculties because ofair and carbon that entered theACS, contributing to erratic flows and occasionally clogging ofthe sampling lines. Well¹18 sampling presented problems because ofclogging ofthe pump and sampling lines bysediment. Elimination ofthese impediments to continuous, representative sampling isnow anticipated near the end of 1995, pending the installation oftraveling screens at theDanville facility. This modification by the Danville Water Authority, which wasoriginally planned for th'e fall of 1994, willpermit sampling at a location downstream ofthe screens that is expected to be minimally affected by sediment and debris and free ofthe air and carbon that hampered turbidity line sampling. Refer to Appendix A foradditional information concerning the 1994 changes in sampling at 12H2R.

Air

Problems associated with the collection ofair samples in 1994 were attributable to lossofelectrical power supplying air sampling stations and the malfunction ofequipment.Malfunctions included electrical shorts in an electrical timer at one sampling station andin an underground service wire at another station. Interruptions in air monitoring tookplace during 1994 at the following ODCM-listed sampling locations: 3S2, SS4, and7G1.

Sampling was disrupted at indicator location 3S2 during the monitoring periods April 13

through April 19, 1994 and May 4 through May 11, 1994. In April, power was lost tothis location, resulting in no sampling from April 16 through April 19, as estimated bythe time recorded by the electrical timer. This resulted in a much reduced volume (8,290ft ) ofair being sampled. On May 11, 1994, sampling also was terminated prematurely(only about 40 minutes early) due to a loss ofelectrical power. The result was only asmall loss ofsampling time and very little effect on the total volume ofair sampled.

Sampling was interrupted at indicator location 5S4 during the monitoring periodsMarch 8 through March 16, 1994 and July 27 through August 3, 1994. The interruptionin April resulted in sampling being performed only from March 8 through March 10 andthe sampling ofonly 5,800 ft'fair. The cause ofthis premature termination was anelectrical short in the station's underground service wire. Electricity was intentionallyshut offto the station on July 29, 1994 for a briefperiod while work activity was takingplace nearby. Even with the brief interruption, air was sampled for 168 hours during thatsampling period.

Sampling at control location 7G1 was stopped by a loss ofelectrical power onSeptember 14, 1994. A total ofonly 2,100 ft'fair was sampled. No sampling tookplace for the rest ofthe intended sampling period ofSeptember 14 throughSeptember 21, 1994. Power was lost to the station due to a breaker trip caused by ashort in the electrical timer box.


A endix F

Even with the unusuaHy small sample volumes obtained in the instances mentionedabove, Technical Specification required sensitivities were met for the iodine-131 analysesofall charcoal cartridges. In the instance oflocation 7G1 for the September 14 sample,the charcoal cartridge was analyzed radiochemically rather than by gamma spectroscopyin order to be able to meet the required analysis sensitivity.

In spite ofthe relatively small number ofexceptions that occurred in 1994 with airsampling, the air monitoring in the SSES vicinity included well over 400 normal samplescollected at indicator locations near the SSES. SSES Technical Specifications requirethat sampling be conducted at only three locations where any airborne activity that mightoriginate &om the SSES would most likelybe observed. The SSES RadiologicalEnvironmental Monitoring Program maintained eight indicator monitoring locations in1994, as well as two control monitoring locations.,

Milk

Sampling did not occur as scheduled at location 14B1 on February 7, 1994, because nomilkwas available. Because ofa collapse ofthe fatmer's barn brought on by harshwinter conditions, the farmer sold his cows, getting out ofthe dairy farming business.This location was promptly replaced by 10D2, which was sampled first in March, 1994.

F-7 1994 Radiological Environmental MonitoringReport

APPENDIX 6

~

'994

Radiological Environmental Monitoring Report

A endix

6'he

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 H tables. Valuesbelow the MPCs, even zeroes and negatives, were part ofthe 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 ofthe sampled media for the relativelybriefperiods during which they are typically collected, it is normally preferable not toaverage the analysis results ofthese samples with those for continuously coHectedcomposite samples. However, when equipment malfunctions are protracted, relativelylarge periods oftime could be entirely unrepresented by averages ifthe results &om 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 oftime 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 &om 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 effect on the overall average and notjustifying the effort involved.

Grab samples collected in lieu ofnormal continuous sampling are typically obtained atregular 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 each

grab 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 ofthe results for a monthly composite samplecollected continuously for each ofthe four weeks in a month. Similarly, the analysisresults ofa composite offour weekly grab samples would carry the same weight as theanalysis results for a composite offour weeks ofcontinuously collected sample.


TABLEGSUMMARYOF DATAFOR THE SSES

OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1994NAMEOF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORTING PERIOD: JANUARY05, 1994 TO JANUARY09. 1995

Page I of 19

Surface Water(pCl/I)

GrossAlpha 110

MEAN(3)RANGE

14.7(334)(10.1 - 21.0)

0.4(81)(-1.3 - 3.8)

Gross Beta 110 4 5.6(81)(1.8 - 27)

TriUum 110 2000 .1068(81)(-100 - 24000)

1 0.1(119)(-0.'1 - 0.7)

Iodine-131 160

Strontium-89 8

StronUum-90 8

Gamma SpecK-40 110

-0.3(8)(-2.4 - 0.3)

0.3(8)(-0.4 - 0.6)

-39(81)(-310 - 98)

Co-58

Fe-59

Co-60

Zn-65

110

110

110

110

110

15 0.5(81)(-1.6 - 47)

15 -0.3(81)(-2.2 - 1.9)

30 0.5(81)(-4.0 - 8.7)

15 0.8(81)(-2.8 - 24)

30 0.7(81)(-6.3 - 9.2)

ANALY I AND LOWER LIMfrMEDIUMOR PATHWAY TOTALNUMBER OF

SAMPLED OF ANALYSES DETECTION(UNfrOF MEASUREMENI) PERFORMED(1) (LLD) (2)

Ambient Radiation 'ILD 359(mR/std. qtr.)

9S2On Site

5S90.8 ml E

5S90.8mi E

6S7Discharge

5S90.8m( E

6S7Discharge

6S7Discharge

12Fl5.3 ml WSW

6S7Discharge

5S90.8mi E

5S90.8ml E

LTAWOn site WSW

6S50.9ml ESE

19.0(4)(16.1 - 21.0)

0.7(1)(0.7 - 0.7)

9.5(1)(9.5 - 9.5)

6097(20)(0.0 - 24000)

0.4(l)(0.4 - 0.4)

-0.3(8)(-2.4 - 0.3)

0.3(8)(-0.4 - 0.6)

-22(12)(-140 - 98)

3.0(20)(-0.7 - 47)

1.3(1)(1.3 - 1.3)

1.2(1)(1.2 - 1.2)

1.1(12)(-2.8 - 4.1)

1.3(12)(-1.2 - 3.8)

NAME MEAN(3)DISTANCEAND DIRECTION RANGE

Only indicatorstaUons weremeasured forStronUum 0

-47(29)(-200 - 22)

0.4(29)(-1.0 - 2.2)

-0.3(29)(-3.0 - 1.4)

0.2(29)(-5.9 - 6.23)

0.3(29)(-1.6 - 1.9)

0.4(29)(-5.4 - 2.9)

NUMBER OFCONIROL LOCATION NONROUTINE

MEAN(3) REPORTEDRANGE MEASUREMENIS(4)

14.9(25)(10.9 - 18.6)

0.3(29)(-0.6 - 1.3)

3.4(29)(1.5 - 5.7)

-5(29)(-120 - 70)

0.1(41)(-0.08 - 0.5)



LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORTING PERIOD: JANUARY05, 1994 TO JANUARY09. 1995

Page 2 of 19

ANALYSISAND LOWER LIMITMEDIUMOR PATHWAY mTALNUMBER OF

SAMPLED OF ANALYSES DEIECIION(UNITOF MEASUREMENII PERFORMED(1) (LLD) (2)

MEAN(3) =

RANGENAME MEAN(3)

DISTANCEAND DIRECIION RANGE

N ROCONIROL LOCATION NONROUIINE


Nb-95 110 15

1.4(81)(-7.6 - 6.6)

1.1(81)(-3.0 - 4.0)

Cs-134 110

Cs-137 110

Ba-140 110

15 0.2(81)(-3.3 - 3.2)

18 0.7(81)(-4.9 - 3.9)

60 -0.2(81)(-16„- 26)

La-140 110 15 -0.2(81)(-4.0 - 5.0)

Potable Water(pCI/I)

Gross Alpha 38

Gross Beta 38

Iodine-131 62

0.2(38)(-0.7 - 2.0)

4 2.5(38)(1.5 - 26)

1 0.07(62)(-'0.1 - 0.5)

Tr(((urn 38 2000 20(38)(-88 - 120)

Gamma SpecK-40 38

Mn-54 38 15

-24(38)(-160 - 25)

0.3(38)(-1.0 - 1.8)

Surface Water Cont. Zr-95 110 30 12G217mi WSW

LTAWOn site WSW

12G217m( WSW

1D33.9ml N

1D33.9ml N

5S90.8ml E

12H2T26ml WSW

12H2T26ml WSW

12H2T26ml WSW

12H2R26ml WSW

12H2R26ml WSW

12H2T26ml WSW

2.2(11)(0. 1 - 4.7)

1.5(12)(-1.1 - 3.9)

0.5(11)(-1.1 - 3.2)

1.6(12)(-2.6 - 3. 1)

2.0(12)(-3.4 - 11)

1.4(1)(1.4 - 1.4)

0.3(12)(-0.7 - 1.4)

3.5(12)(1.5 - 7.1)

0.09(26)(-0.09 - 0.5)

24(12)(-88 - 120)

-18(26)(-113 - 12)

0.3(12)(-0.5 - 1.3)

0.1(29)(-14 - 8.7)

0.9(29)(-3.5 - 3.7)

0.3(29)(-2.4 - 2.8)

0.7(29)(-3.3 - 3.1)

0.8(29)(-4.9 - 11)

-0.2(29)(-8.0 - 3.3)

0

0

Only Indicator 0stations sampled forthis medium.


OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1994NAMEOF FACILITY: SUSgUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORTING PERIOD: JANUARY05, 1994 TO JANUARY09, 1995

Page 3 of 19

ANALYSISAND LOWER LIMITMEDIUMOR PATHWAY TOTALNUMBER OF

SAMPLED OF ANALYSES DEIECIION(UNITOF MEASUREMENI) PERFORMED(1) (LLD) (2)

MEAN(3)RANGE

NAME MEAN(3)DISTANCEAND DIRECIION RANGE

NUMBER OFCOWIROL LOCATION NONROUTINE

MEAN(3) REPORIEDRANGE MEASUREMENTS(4)

PotabIe Water Cont. Co-58pCI/I)

Fe-59

Co-60

Zn-65

Zr-95

Nb-95

Cs-134

Cs-137

Ba-140

La-140

38

38

38

38

38

38

38

38

38

38

15

30

15

30

30

15

15

18

60

15

-0.2(38)(-2.3 - 1.7)

0.8(38)(-4.1 - 6.0)

0.5(38)(-1.9 - 2.3)

0.2(38)(-11 - 5.5)

0.5(38)(-.9.3 - 7.7)

0.9(38)(-0.7 - 3.2)

0.1(38)(-7.9 - 3.6)

0.6(38)(-4.3 - 3.6)

0.07(38)(-12 - 20)

-0.2(38)(-7.5 - 4.4)

12H2R26m( WSW

12H2T26m( WSW

12H2T26ml WSW

12H2R26ml WSW

12H2T26m( WSW

12H2T26ml WSW

12H2R26ml WSW

12H2T26ml WSW

12H2R26m( WSW

12H2R26ml WSW

-0.2(26)(-1.9 - 1.7)

0.8(12)(-4.1 - 5.9)

0.8(12)(-0.4 - 1.9)

0.4(26)(-11 - 5.5)

1.0(12)(-7.4 - 5.1)

1.3(12)(-0.4 - 3.0)

0.3(26)(-1.8 - 1.8)

0.9(12)(-0.9 - 2.5)

0.3(26)(-12 - 20)

-0.2(26)(-2.4 - 2.0)




Page 4 of 19

ANALYSISAND WER LIMITMEDIUMOR PATHWAY TOTALNUMBER OF

SAMPLED OF ANALYSES DETECIION(UNITOF MEASUREMENII PERFORMED(1) (LLD) (2)

MEAN(3)RANGE


MBE 0CONTROL LOCATION NONROUTINE

MEAN(3) REPORTEDRANGE MEASUREMENTS(4)

AIgaepCI/g dry)

Gamma SpecBe-7 12

K-40 12

12

Co-58 12

Co-60 12

Zn-65 12

Zr-95 12

Nb-95 12

1-131 12

Cs-134 12

Cs-137'2

Ba-140 12

Fe-59 12

5.3[6)(3.4 - 6.9)

21(6)(8.9 - 29)

0.2(6)(0.06 - 0.3)

-0.004(6)(-0.09 - 0. 1)

-0.08(6)(-0.3 - 0.1)

0.2(6)(0.005 - 0.4)

0.06(6)(-0.03 - 0.2)

0.08(6)(-0.1 - 0.3)

0.06(6)(-0.05 - 0.2)

0.3(6)(0.05 - 0.6)

0.02(6)(-0.02 - 0.1)

0.2(6)(0.1 - 0.2)

0.05(6)(-0.1 - 0.2)

AG-30.8mt E

AG-40.9 mt ESE

AG-40.9m( ESE

AG-40.9 mt ESE

AG-30.8ml E

AG-40.9 mt ESE

AG-40.9m( ESE

AG-40.9 mt ESE

AG-40.9 mt ESE

AG-30.8mt E

AG-30.8ml E

AG-30.8ml E

AG-4.9 mt ESE

5.4(6)(3.9 - 7.5)

21(6)(8.9 - 29)

0.2(6)(0.06 - 0.3)

-0.004(6)(-0.09 - 0.1)

-0.05(6)(-0.2 - 0.07)

0.2(6)(0.005 - 0.4)

0.06(6)(-0.03 - 0.2)

0.08(6)(-0.1 - 0.3)

0.06(6)(-0.05 - 0.2)

0.3(6)(0.08 - 0.6)

0.06(6)(0.01 - 0.1)

0.2(6)(0.09 - 0.2)

0.05(6)(-0.1 - 0.2)

5.4(6)(3.9 - 7.5)

19(6)(10 - 24)

0.04(6)(-0.02 - 0.08)

0

.0

-0.04(6)(-0.07 - -0.004)

-0.05(6)(-0.2 - 0.07)

0.03(6)(0.0 - 0.1)

0.03(6)(-0.2 - 0.2)

0.05(6)(-0.2 - 0.3)

0.05(6)(0.002 - 0.1)

0.3(6)(0.08 - 0.6)

0.06(6)(0.01 - 0.1)

0.2(6)(0.09 - 0.2)

-0.009(6) 0(-0.07 - 0.07)


OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1994NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION

LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORI'ING PERIOD: JANUARY05, 1994 TO JANUARY09, 1995

Page5of19

YSI AND LOWER LIMITMEDIUMOR PATHWAY TIALNUMBER OF

SAMPLED OF ANALYSES DETECflON(UNITOF MEASUREMEND PERFORMED(1) (LLD) (2)

MEAN(3)RANGE

NAME MEAN(3)DISI'ANCEAND DIRECIION RANGE

NUMBER0CONIROL LOCATION NONROUTINE


Algae Cont.

Fish(pCI/g wet)

La-140 12

Ra-226 12

Th-228 12

Gross Beta 13

Gamma SpecK-40 13

Mn-54

Co-58

Fe-59

Co-60

Zn-65

Zr-95

-0.02(6)(-0.1 - 0.05)

0.6(6)(-0.6 - 1.9)

1.2(6)(0.5 - 1.6)

6.1(7)(3.1 - 9.1)

3.9(7)(2.9 - 5.1)

13 0.13 0.0005(7J(-0.002 - 0.005)

13 0.13 -0.0002(7)(-0.004 - 0.003)

13 0.26 0.0008(7)(-0.02 - 0.01)

'3

0. 13 0.002(7)(-0.002 - 0.007)

13 0.26 0.006(7J(-0.008 - 0.02)

0.005(7)(-0.02 - 0.03)

13

AG-40.9 ml ESE

AG-40.9m( ESE

AG-40.9ml ESE

IND0.9-1.4 ml ESE

IND0.9-1.4 mi ESE

2H30m( NNE

LTAWOnsite NE-ESE

LTAWOnslte NF ESE

LTAWOnslte NE-ESE

LTAWOnslte NE-ESE

IND0.9-1.4 ml ESE

-0.02(6)(-0.1 - 0.05)

0.6(6)(-0.6 - 1.9)

1.2(6)(0.5 - 1.6)

6.5(6)(3.1 - 9.1)

3.9(6)(2.9 - 5.1)

0.003(6)(0.0 - 0.007J

- 0.002(1)(0.002 - 0.002)

0.006(1)(0.006 - 0.006)

0.007(l)(0.007 - 0.007J

0.008(1)(0.008 - 0.008)

0.005(6)(-0.02 - 0.03)

-0.03(6)(-0.2 - 0.06)

-0.2(6)(-2.8 - 1.2)

1.0(6)(0.5 - 1.3)

4.8(6)(2.5 - 6.5)

3.6(6)(3.5 - 3.8)

0.003(6)(0.00 - 0.007J

-0.002(6)(-0.006 - 0.0009)

0.004(6)(-0.02 - 0.02)

0.001(6)(-0.003 - 0.004)

0.005(6)(-0.009 - 0.02)

-0.008(6)(-0.03 - 0.01)



LOCATIONOF FACILITY: LUZERNE COUNTY. PENNSYLVANIAREPORTING PERIOD: JANUARY05, 1994 TO JANUARY09, 1995

Page 6 of 19

ANALYSISAND LOWER LIMI'fMEDIUMOR PATHWAY TOTALNUMBER OF

SAMPLED OF ANALYSES DETECI1ON(UNITOF MEASUREMENI) PERFORMED(l) (LLD) (2)

MEAN(3)RANGE

N MBER OFCONIROL LOCATION NONROIJIINE

NAME MEAN(3) MEAN(3) REPO RIEDDISI'ANCEAND DIRECI1ON RANGE RANGE MEASUREMENIS(4)

Hsh cont.(pCI/g wet)

Sedhnent(pCI/g chy)

Nb-95 13 0.004(7)(-0.002 - 0.009)

Cs-134

Cs-137

Ba-140 13 0.02(7)(-0.02 - 0.08)

La-140 13

Gross Alpha 12

Gross Beta 12

Gamma SpecBe-7 12

K-40 12

-0.001(7)(-0.02 - 0.01)

12(8)(8.1"- 16)

31(8)(24 - 38)

0.5(8)(-0.03 - 1.3)

11(8)(7.6 - 14)

Mn-54

Co-58

Fe-59

12

12

12

0.01(8)(-0.02 - 0.03)

-0.01(8)(-0.02 - -0.002)

-0.02(8)(-0.07 - 0.03)

'3

0.13 -0.004(7)(-0.02 - 0.003)

13 0.15 0.004(7)(-0.006 - 0.03)

LTAWOnslte NE-ESE

2H30ml NNE

2H30m( NNE

LTAWOnslte NE-ESE

IND0.9- 1.4m( ESE

2B1.6mi NNE

2B1.6m( NNE

12F6.9 ml WSW

LTAWOnslte NE-ESE

12F6.9 ml WSW

2B1.6ml NNE

12F6.9ml WSW

0.009(l)(0.009 - 0.009)

0.002(6)(-0.008 - 0.02)

0.006(6)(-0.004 - 0.01)

0.02(1)(0.02 - 0.02)

0.002(6)(-0.01 - 0.01)

17(2)(15 - 19)

44(2)(43 - 44)

0.9(2)(0.6 - 1.3)

14(2)(14 - 14)

0.02(2)(0.02 - 0.03)

0.005(2)(-0.002 - 0.01)

-0.002(2)(-0.03 - 0.03)

0.003(6)(-0.001 - 0.008)

0.002(6)(-0.008 - 0.02)

0.006(6)(-0.004 - 0.01)

0.005(6)(-0.007 - 0.03)

-0.0002(6)(-0.003 - 0.005)

14(4)(9.2 - 19)

34(4)(23 - 44)

0.3(4)(0.0 - 0.6)

11(4)(7.5 -15)

0.01(4)(-0.001 - 0.04)

0.0007(4)(-0.03 - 0.02)

0 04(4)(-O. 1 - 0.02)

I00




Page 7 of 19

ANALYSISAND LOWER LIMrrMEDIUMOR PATHWAY TOTALNUMBER OF

SAMPLED OF ANALYSES DETECrlON(UN% OF MEASUREMENQ PERFORMED(1) (LLD) (2)

MEAN(3)RANGE


NUMBE 0CONTROL LOCATION NONROUTINE


SecBment Cont.(pCI/g dry)

FIoc(pCl/g dry)

Co-60 12

Zn-65 12

Zr-95 12

Nb-95 12

Cs-134 12

Cs-137 12

Ba-140 12

La-140 12

Ra-226 12

Th-228 12

Gross Beta 4

Gross Alpha 4

-0.001(8)(-0.01 - 0.01)

0.006(8)(-0.06 - 0.1)

0.06(8)(-0.07 - 0.1)

0.03(8)(0.003 - 0.06)

0. 15 0.04(8)(0.02 - 0.06)

0.18 0.05(8)(-0.002 - 0.1)

0.01(8) ~

(-0.08 - 0.1)

-0.003(8)(-0.05 - 0.07)

1.6(8)(1.3'- 2.0)

1.0(8)(0.7 - 1.2)

11(2)(10- 11)

26(2)(25 - 27)

12F6.9mi WSW

7B1.2ml SE

7B1.2ml SE

LTAWOnslte NE-ESE

LTAWOnslte NE-ESE

2B1.6ml NNE

12F6.9m! WSW

2B1.6ml NNE

2B1.6mi NNE

2B1.6m( NNE

2B1.6ml NNE

2B1.6m( NNE

0.005(2)(-0.002 - 0.01)

0.05(2)(0.0 - 0.1)

0.1(2)(0.1 =0.1)

0.04(2)(0.03 - 0.06)

0.05(2)(0.04 - 0.06)

0.2(2)(0.1 - 0.2)

0.03(2)(-0.04 - 0. 1)

0.06(2)(-0.05 - 0.2)

2.0(2)(1.6 - 2.4)

1.2(2)(1.0 - 1.3)

11(2)(9.6 - 12)

40(2)(34 - 45)

-0.002(4)(-0.01 - 0.02)

0.02(4)(-0.04 - 0.08)

0.09(4)(0.04 - 0.1)

0.03(4)(0.009 - 0.05)

0.04(4)(0.03 - 0.06)

0.1(4)(0.04 - 0.2)

-0.07(4)(-0.2 - 0.04)

0.02(4)(-0.06 - 0.2)

2.0(4)(1.6 - 2.5)

1.1(4)(1.0 - 1.3)

11(2)(9.6 - 12)

40(2)(34 - 45)



LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORllNG PERIOD: JANUARY05, 1994 TO JANUARY09, 1995

Page 8 of 19

ANALYSI AND LOWER LIMITMEDIUMOR PATHWAY mTALNUMBER OF

SAMPLED = OF ANALYSES DETECIION(UNITOF.MEASUREMENQ PERFORMED(1) (LLD) (2)

MEAN(3)RANGE


NUMBER0CONTROL LOCATION NONROUllNE


I

CD

Floe(pCI/g dry)

Gamma SpecBe-7

K-40

Mn-54

Co-58

Fe-59

Co-60

Zn-65

Zr-95

Nb-95

Cs-134

Cs-137

Ba-140

La-140

0.5(2)(0.4 - 0.6)

9.7(2)(9.1 - 10)

0.02(2)(0.007 - 0.04)

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

0.03(2)(-0.003 - 0.07)

0.002(2)(-0.002 - 0.006)

0.0(2)(-0.1 - 0.1)

0.2(2)(0.2 - 0.3)

0.06(2)(0.04 - 0.07)

0.04(2)(0.008 - 0.07J

0.09(2)(0.07 - 0.1)

-0.03(2)(-0.2 - 0.2)

0.08(2)(-0.05 - 0.2)

2B1.6m( NNE

2B1.6m( NNE

2B1.6ml NNE

2B1.6ml NNE

7B1.2ml SE

2B1.6ml NNE

7B1.2ml SE

7B1.2ml SE

2B1.6ml NNE

2B1.6ml NNE

2B1.6ml NNE

2B1.6m( NNE

7B1.2ml SE

1.1(2)(0.5 - 1.7)

12(2)(9.1 - 15)

0.06(2)(0.05 - 0.07J

-0.03(2)(-0.05 - 0.0)

0.03(2)(-0.003 - 0.07J

0.02(2)(0.01 - 0.03)

0.0(2)(-O.l - O.l)

0.2(2)(0.2 - 0.3)

0.06(2)(0.02 - 0.1)

0.06(2)(0.008 - 0.1)

0.09(2)(0.04 - 0.1)

-0.004(2)(-0.008 - 0.0)

0.08(2)(-0.05 - 0.2)

1.1(2)(0.5 - 1.7J

12(2)(9.1 - 15)

0.06(2)(0.05 - 0.07)

-0.03(2)(-0.05 - 0.0)

-0.1(2)(-0.1 - -0.07)

0.02(2)(0.01 -.0.03)

-0.05(2)(-0.08 - -0.02)

0.1(2)(0.06 - 0.1)

0.06(2)(0.02 - 0.1)

0.06(2)(0.008 - 0.1)

0.09(2)(0.04 - 0.1)

-0.004(2)(-0.008 - 0.0)

-0.04(2) 0(-0.1 - 0.02)



LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORI1NG PERIOD: JANUARY05, 1994 TO JANUARY09, 1995

Page 9 of 19


SAMPLED OF ANALYSES DETECflONIUNfl'FMEASUREMENI) PERFORMEDI1) ILLD) 12)

MEAN(3)RANGE


NUMBER OFCOÃfROL LOCAT1ON NONROUTINE


Floe Cont.(pCI/g dry)

Ground Water(pCI/I)

Th-228

Gross Alpha 67

Gross Beta 67

Gamma SpecK-40 67

Mn-54 67

Co-58 67

Fe-59 67

Co-60 67

Zn-65 67

Zr-95 67

Nb-95 67

Ra-226 4

15-

15

30

15

30

0.7(2)(-0.1 - 1.6)

0.8(2)(0.7 - 1.0)

0.3(55)(-0.9 - 1.6)

1.6(55)(-0.2 - 6.2)

-37(55)(-310 - 57)

0.3(55)(-2.7 - 2.0)

-0.5(55)(-2.3 - 1.9)

1.0(55)(-4.3 - 6.4)

0.1(55)(-14 - 3.3)

1.0(55)(-4.6 - 11)

15 1.6(55)(-2.1 - 5.1)

30 0.6(55)(-9.0 - 7.9)

2B1.6ml NNE

2B1.6 m) NNE

12F35.2ml WSW

12F35.2 ml WSW

4S40.5mi ENE

12F35.2ml WSW

12S10.4 ml WSW

3S50.9ml NE

12S10.4 ml WSW

4S40.5ml ENE

12F35.2m) WSW

3S50.9ml NE

1.6(2)(1.2 - 1.9)

1.1(2)(0.7 - 1.4)

0.5(12)(-0.1 - 1.0)

2.8(12)(1.6 - 4.5)

-17(12)(-82 - 52)

0.6(12)(-2.6 - 2.1)

-0.1(12)(-1.1 - 1.9)

1.4(7)(-0.3 - 3.6)

0.7(12)(-0.6 - 2.4)

1.9(12)(-0.6 - 9.2)

3.0(12)(-2.7 - 8.3)

2.6(12)(0.6 - 4.2)

1.6(2)(1.2 - 1.9)

1.1(2)(0.7 - 1.4)

0.5(12)(-0.1 - 1.0)

2.8(12)(1.6 - 4.5)

-51(12)(-160 - 7.8)

0.6(12)(-2.6 - 2. 1)

-0.3(12)(-1.9 - 1.0)

-0.3(12)(-2.5 - 2.6)

0.2(12)(-2.7 - 2.1)

1.7(12)(-1.8 - 7.0)

3.0(12)(-2.7 - 8.3)

2.5(12)(-2.4 - 4.5)

0




Page 10 of 19


SAMPLED OF ANALYSES DETECIIONIUNITOF MEASUREMENII PERFORMED(1) ILLD) I2)

MEAN(3)RANGE

MBER 0CONIROL LOCATION NONROU11NE

NAME MEAN(3) MEAN(3) REPORTEDDISI'ANCEAND DIRECIION RANGE RANGE MEASUREMENISI4)

67

67

Ba-140 67

La-140 67

H-3 67

AirParticulates(E-03 pCI/m3)

Gross Beta 520

AirIodine(E-03 pCI/m3)

1-131 520

AtrParticulatesQuarterly Composite(E-03 pCI/m3)

Gross Alpha 40

Gamma SpecBe-7, 40

K-40 40

Mn-54 40

Ground Water Cont. Cs-134(pCI/I)

Cs-137 18

60

15

2000

10

70

0.8(55)(-4.7 - 4.9)

-0.4(55)—(-7.9 - 6.7)

-0.3(55)(-4.9 - 5.6)

23(55)(-100 - 100)

16(416)(8. 1'-.- 52)

-0. 1(416)(-4.9 - 8.1)

3.0(32)(1.3 - 4.2)

124(32)(99 - 153)

4.0(32)(-4.4 - 29)

0.009(32)(-0.1 - 0.1)

15 0.1(55)(-2.3 - 2.8)

5S40.6ml NW

3S50.9ml NE

12F35.2ml WSW

12SI0.4 mt WSW

3S50.9ml NE

13360.4ml W

5S40.8ml E

1D24.0ml N

3D13.4ml NE

13S60.4ml W

12SI0.4 ml WSW

0.5(12)(-1.7 - 2.4)

1.7(7J(-1.4 - 3.0)

1.9(12)(-3.7 - 5.5)

0.1(12)(-2.0 - 3.4)

51(7J(12 - 100)

18(25)(8.7 - 27J

0.1(52)(-4.3 - 8.1)

3.8(2)(3.7 - 3.8)

136(2)(126 - 146)

17(2)(5.0 - 28)

0.06(4)(-0.009 - 0. I)

-0.2(12)(-2.2 - 1.3)

0.9(12)(-1.9 - 5.1)

1.9(12)(-3.7 - 5.5)

-0.03(12)(-1.4 - 1.4)

34(12)(-59 - 130)

16(104)(8.4 - 48)

-0.4(104)(-5.3 - 7.3)

2.7(8)(1.4 - 3.6)

118(8)(97 - 149)

2.6(8)(-7.2 - 23)

0.02(8)(-0.03 - 0.1)



LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORI'ING PERIOD: JANUARY05. 1994 TO JANUARY09. 1995

Page 11 of 19

ANALYSISAND LOWER UMffMEDIUMOR PATHWAY TQTALNUMBER OF

SAMPLED =OF ANALYSES DEIECIlON

(UNITOF MEASUREMENI) PERFORMED(1) (LLD) (2)MEAN(3)RANGE

NUMBEROFCONTROL LOCATION NONROUTINE

NAME MEAN(3) MEAN(3) REPORTEDDISTANCEAND DIRECIION RANGE RANGE MEASUREMENIS(4)

Co-60 40

Zn-65 40

Zr-95 40

Nb-95 40

Cs-134 40

Cs-137 40

Ba-140 40

La-140 40

AIrborne Water Vapor H-3(pCI/m3)

52

AirParticulates conL Co-58 40Quarterly Composite(E-03 pCI/m3)

Fe-59 40

-0.04(32) - 7G1(-0.4 - 0.2) 14mi SE

0.002(32)(-0.6 - 0.7)

0.02(32)(-0.1 - 0.2)

0.06(32)(-0.5 - 0.5)

0.09(32)(-0.7 - 0.9)

0.05(32)(-0.2 - 0.3)

13S60.4ml W

5S40.6ml NW

1D21.3ml S

7S70.6ml NW

7S70.6ml NW

0.6(32)(-7.4 - 11)

-0.5(32)(-6.3 - 4.8)

1.3(52)(-0.8 - 5.2)

15S40.6ml NW

13S60.4mi W

3S20.5ml NNE

50 0.009(32) 3Dl(-0.2 - 0.1) 3.4ml NE

60 0.05(32) 10S3(-0.09 - 0.2) 0.6 ml SSE

0.08(4)(0.0 - 0.3)

0.6(2)(0.5 - 0.7)

0.06(4)(-0.04 - 0.2)

0.2(2)(0.2 - 0.3)

0.6(2)(0.3 - 0.9)

0.3(2)(0.2 - 0.3)

0.06(2)(0.06 - 0.06)

0.1(2)(0.06 - 0.2)

5.3(2)(-0.4 - 11)

0.9(2)(0.4 - 1.4)

1.3(52)(-0.8 - 5.2)

0.04(8)(-0.3 - 0.3)

-0.1(8)(-0.9 - 0.4)

0.02(8)(-0.06 - 0.1)

0.06(8)(-0.1 - 0.2)

0.03(8)(-0.2 - 0.3)

0.06(8)(-0.07 - 0.2)

0.03(8)(-0.01 - 0.09)

0.02(8)(-0.06 - 0.07)

0.02(8)(-5.0 - 3.2)

-0.2(8)(-3.8 - 3.5)

Only Indicatorstations sampled forthis medium.

0


OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1994NAME OF FACILITY: SUSgUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPOimNG PERIOD: JANUARY05, 1994 TO JANUARY09, 1995

Page 12 of 19

ANALYSISAND LOWER UMITMEDIUMOR PATHWAY 'ImALNUMBER OF

SAMPLED OF ANALYSES DETECIION(UNITOF MEASUREMENQ PERFORMED(1) (LLD) (2)

MEAN(3)RANGE

NUMBER OFCONIROL LOCATION NONROIINE

NAME MEAN(3) MEAN(3) REPOR1EDDISTANCEAND DIRECIION RANGE RANGE MEASUREMEÃIS(4)

Precipitation(pC(/))

Gross Alpha 40

H-3 40

Gamma SpecBe-7 40

K-40 40

Mn-54 40

Co-58 40

Fe-59 40

Co-60 40

7e-65 40

Zr-95 40

Nb-95 40

Cs-134 40

Gross Beta 40

0.6(32)(0.2 - 1.2)

4.3(32)(2.4 - 6.8)

28(32)(-73 - 200)

28(32)(3.1 - 68)

-42(32)(-220 - 64)

0.8(32)(-1.3 - 2.9)

-0.2(32)(-2.2 - 2.6)

0.4(32)(-7.2 - 5.9)

0.5(32)(-1.4 - 3.1)

1.6(32)(-1.7 - 5.6)

0.3(32)(-16 - 7.0)

1.5(32)(-0.6 - 2.8)

-0.03(32)(-4.1 - 2.0)

1D2 1.1(2)4.0ml N

1D24.0ml N

13S604m( W

1D24.0ml N

9B11.3ml S

9B11.3ml S

10S30.6ml SSW

12El0.6ml NW

10S30.6ml SSW

12El4.7ml WSW

jsj0.6ml NW

12E14.7ml WSW

3S20.5ml NE

1.1(8)(1.0 - 1.2)

5.4(2)(4.3 - 6.5)

86(2)(-28 - 200)

47(2)(40 - 55)

12(4)(-25 - 64)

1.8(4)(1.1 - 2.9)

0.7(2)(-0.3 - 1.7)

2.6(4)(0.0 - 5.9)

1.3(2)(1.2 - 1.4)

2.9(4)(1.2 - 4.0)

3.2(2)(2.0 - 4.4)

2.3(4)(1.5 - 2.8)

0.8(4)(0.2 - 1.7)

0.5(8)(0.4 - 0.7)

4.0(8)(2.6 - 5.1)

-25(8)(-83 - 66)

35(8)(15 - 56)

-35(8)(-75 - -2.2)

0.4(8)(-1.4 - 1.9)

-0.3(8)(-1.3 - 0.9)

1.6(8)(-1.0 - 4.2)

-0.6(8)(-7.6 - 2.8)

1.8(8)(-1.2 - 6.0)

1.2(8)(-0.4 - 2.6)

0.5(8)(0.0 - 1.2)

-0.2(8)(-1.0 - 0.6)

0



LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPOKllNG PERIOD: JANUARY05, 1994 1m JANUARY09, 1995

Page 13 of 19

YSIS AND LOWERLIMll'EDIUMOR PATHWAY TOTALNUMBER OF

SAMPLED - OF ANALYSES DEIECIION(UNITOF MEASUREMENII PERFORMED(1) (LLD) (2)

MEAN(3)RANGE


NUMBECONIROL LOCATION NONROUIINE

MEAN(3) REPORTEDRANGE MEASUREMElfIS(4)

Precipitation(pCI/I)

(pCI/I)

Cs-137 40

Ba-140 40

La-140 40

1-131 123

Sr-89 123

Sr-90 123

Mn-54 123

Co-58 123

Fe-59 123

Co-60 123

Zn-65 123

Zr-95 123

Nb-95 123

Gamma SpecK-40 123

0.5(32)(-6.1 - 3.3)

-0.5(32)(-7.5 - 10)

-1.0(32)(-6.1 - 3.4)

-'0.01(104)(-0.2 - 0.09)

0.1(104)(-2.0 - 1.3)

2.7(104)(1.8 - 6.6)

1356(104)(1140 - 1610)

0.3(104)(-2.6 - 3.3)

-0. 1(104)(-2.1 - 2.1)

0.9(104)(-4.2 - 7.8)

0.3(104)(-6.7 - 3.6)

0.5(104)(-8.0 - 10)

0.7(104)(-13 - 7.0)

1.1(104)(-4.6 - 4.7)

12E14.7 ml WSW

12G215m( WSW

12S10.4ml WSW

14B11.8 mi WNW

10D23.3ml SSW

14Bl1.8ml WNW

13E35.0mi W

13E35.0ml W

12B32.0ml WSW

10D33.5m( SSW

14Bl1.8 mi WNW

13E35.0ml W

14B11.8 ml WNW

14B11.8m( WNW

2.1(4)(-0.08 - 3.3)

3.5(4)(-0.2 - 7.9)

0.6(4)(0.1 - 1.4)

0.06(1)(0.06 - 0.06)

0.3(17)(-1.7 - 1.1)

4.0(1)(4.0- 4.0)

1488(12)(1420 - 1610)

1.0(12)(-0.9 - 3.3)

0.4(19)(-1.5 - 1.7)

1.7(12)(-1.1 - 4.6)

2.8(1)(2.8 - 2.8)

1.6(12)(-2.1 - 10)

1.7(l)(1.7 - 1.7)

3.8(1)(3.8 - 3.8)

0.1(8)(-2.0 - 2.1)

1.6(8)(-2.9 - 7.9)

-0.7(8)(-3.5 - 0.9)

-0.01(19)(-0.09 - 0.07)

0.2(19)(-1.0 - 0.9)

3.3(19)(2.5 - 5.1)

1328(19)(1170 - 1480)

0.5(19)(-1.9 - 2.3)

-0.4(19)(-1.7 - 1.4)

1.2(19)(-1.3 - 3.6)

0.3(19)(-1.5 - 2.7)

0.5(19)(-5.7 - 5.4)

1.3(19)(-2.0 - 6.9)

1.5(19)(-0.4 - 4.6)

0



LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORTlNG PERIOD: JANUARY05. 1994 TO JANUARYQ9, 1995

Page 14 of 19

ANAIYSIS AND LOWERLIMI'I'EDIUM

OR PATHWAY TOTALNUMBER OFSAMPLED OF ANALYSES DEIECTION

(UNITOF MEASUREMENII PERFORMED(1) (LLD) (2)MEAN(3)RANGE


BER OFCONIROL LOCATION NONROUTINE

MEAN(3) REPOKIEDRANGE MEASUREMENIS(4)

Milltcant.(pCl/1)

- (pCl/g dry)

Cs-137 123

Ba-140 123

La-140 123

Gamma SpecK-4Q 2Q

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-134 123 -0.04(104)(-4.5 - 2.6)

1.8(104)(-3.2 - 6.4)

0.5(104)(-6.2 - 8.8)

-0. 1(104)(-3.9 - 4.0)

11(16)(8.7 - 14)

0.006(16)(-0.008 - 0.02)

-0.006(16)(-0.02 - 0.06)

-0.01(16)(-0.06 - 0.04)

0.002(16)(-0.01 - 0.02)

0.05(16)(-0.02 - 0.2)

0.07(16)(-0.01 - 0.2)

0.03(16)(0.02 - 0.05)

0.03(16)(0.001 - 0.05)

10D43.8 ml SSW

10D13.0 ml SSW

13E35.0ml W

14B11.8mi WNW

13S604m( W

5S40.8mi E

5S40.8ml E

9B11.3ml S

7Gl14mi SE

9B11.3ml S

10S30.6ml SSW

9B11.3m! S

10S30.6ml SSW

0.6(12)(-1.4 - 2.4)

2.6(19)(-2.0 - 6.4)

3.3(12)(-2.9 - 8.8)

1.5(1)(1.5 - 1.5)

13(2)(13 - 14)

0.01(2)(0.005 - 0.02)

0.003(2)(0.0 - 0.006)

0.03(2)(0.01 - 0.04)

0.01(2)(0.007 - 0.02)

0.1(2)(0.05 - 0.2)

0.1(2)(0.1 - 0.2)

0.04(2)(0.04 - 0.05)

0.04(2)(0.04 - 0.05)

-0.09(19)(-1.7 - 2.0)

1.6(19)(-1.0 - 3.7)

-0.8(19)(-5.8 - 2.3)

0.2(19)(-3.4 - 4.9)

9.6(4)(7.4 - 12)

0.01(4)(0.006 - 0.01)

-0.002(4)(-0.004 - 0.0)

0.003(4)(0.001 - 0.005)

0.01(4)(-0.004 - 0.02)

0.03(4)(-0.008 - 0.08)

0.06(4)(0.03 - 0.1)

0.04(4)(0.03 - 0.04)

0.03(4)(0.02 - 0.04)

0


OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1994NAME OF FACILITY: SUSgUEHANNA STEAM ELECTRIC STATION

LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORllNG PERIOD: JANUARY05. 1994 TO JANUARY09, 1995

Page 15 of 19

ANALYSISAND LOWERLIMfl'EDIUMOR PATHWAY TOTALNUMBER OF

SAMPLED OF ANALYSES DEIECIION(UNITOF MEASUREMENI) PERFORMED(1) (LLD) (2)

MEAN(3)RANGE

UMBER 0CONIROL LOCATION NONROUTINE

NAME MEAN(3) MEAN(3) REPORTEDDISI'ANCEAND DIRECIION RANGE RANGE MEASUREMENIS(4)

Soll cont.(pCl/g dry)

Vegetation(pC(/g wet)

Ba-140 20

La-140 20

Ra-226 20

Th-228 20

Gamma SpecBe-7 9

K-40

Mn-54

Co-58

Fe-59

Co-60

Zn-65

Zr-95

Nb-95

Cs-137 — 20 0.2(16)(0.04 - 0.4)

-0.001(16)(-0.08 - 0.07)

-0.02(16)(-0.05 - 0.04)

1.5(16)(1.1 - 2.0)

0.8(16)(0.6 - 1.0)

2.9(8)(1.2 - 5.8)

4.6(8)(3.3 - 7.8)

0.003(8)(-0.005 - 0.01)

0.002(8)(-0.008 - 0.01)

-0.003(8)(-0.02 - 0.01)

0.002(8)(-0.006 - 0.01)

0.003(8)(-0.009 - 0.03)

0.01(8)(-0.008 - 0.06)

0.008(8)(-0.01 - 0.021

7Gl14m) SE

12E14.7m( WSW

5S40.8m( E

12G115ml WSW

12G115ml WSW

12S10.5ml WSW

7S70.5ml SE

jsj0.5ml SE

3S20.5ml NE

12G115m( WSW

5S40.8mi E

12E14.7 mi WSW

5S40.8m( E

5S40.8m( E

1.0(2)(0.8 - 1.2)

0.03(2)(-0.02 - 0.07)

0.007(2)(-0.02 - 0.04)

2.0(2)(1.8 - 2.2)

1.0(2)(1.0 - 1.1)

5.8(1)(5.8 - 5.8)

7.8(1)(7.8 - 7.8)

0.01(1)(0.01 - 0.01)

0.01(1)(0.01 - 0.01)

0.03(1)(0.03 - 0.03)

0.01(1)(0.01 - 0.01)

0.03(1)(0.03 - 0.03):

0.06(1)(0.06 - 0.06)

0.02(1)(0.02 - 0.021

.0.5(4)(0.06 - 1.2)

0.02(4)(-0.02 - 0.07)

-0.01(4)(-0.03 - 0.0)

1.8(4)(1.3 - 2.2)

0.9(4)(0.8 - 1.1)

1.9(l)(1.9 - 1.9)

3.1(1)(3.1 - 3.1)

-0.008(1)(-0.008 - -0.008)

-0.0008(1)(-0.0008 - -0.0008)

0.03(1)(0.03 - 0.03)

-0.006(1)(-0.006 - -0.006)

0.0(1)(0.0 - 0.0)

0.006(1)(0.006 - 0.006)

0.01(1)(0.01 - 0.011




Page 16 of 19


SAMPLED OF ANALYSES DEIECI1ON(UNITOF MEASUREMENI) PERFORMED(l) (LLD) (2)

MEAN(3)RANGE

NUMBER OFCONTROL LOCATION NONROUTINE

NAME MEAN(3) MEAN(3) REPORTEDDISTANCEAND DIRECI1ON RANGE RANGE MEASUREMENIS(4)

I

CO

Ba-140

Food/GardenCrops(pCI/g wet)

La-140

Gamma SpecBe-7 69

K-40 69

69

Co-58 69

Fe-59 69

Co-60 69

Zn-65 69

Zr-95 69

Nb-95 69

Vegetation Cont. Cs-134 9(pCI/g wet)

Cs-137

0.0005(8)(-0.03 - 0.02)

0.008(8)(-0.01 - 0.02)

0.0006(8)(-0.03 - 0.006)

-0.004(8)(-0.02 - 0.004)

0.02(58)(-0.03 - 0.4)

2.2(58)(0.8 - 11)

0.0008(58)(-0.008 - 0.005)

-0.0006(58)(-0.008 - 0.003)

0.0004(58)(-'0.009 - 0.01

0.001(58)(-0.003 - 0.006)

0.003(58)(-0.01 - 0.02)

0.003(58)(-0.01 - 0.02)

0.002(58)(-0.005 - 0.01)

5S40.8ml E

3320.5ml NE

10S30.6m( SSW

12El4.0ml WSW

14B32.0ml WNW

14B32.0 ml WNW

8A50.8ml SSE

2B51.1 ml NNE

12F57.5m! WSW

2B51.1 ml NNE

7B21.5ml SE

7B21.5ml SE

15A30.9m( NW

0.02(1)(0.02 - 0.02)

0.02(1)(0.02 - 0.02)

0.006(1)(0.006 - 0.006)

0.004(1)(0.004 - 0.004)

0.07(7)(-0.01 - 0.4)

3.8(7)(1.6 - 11)

0.003(3)(0.002 - 0.005)

0.0008(2)(-0.0001 - 0.002)

0.003(l)(0.003 - 0.003)

0.004(4)(0.003 - 0.006)

0.01(2)(0.002 - 0.02)

0.01(2)(0.002 - 0.02)

0.004(1)(0.004 - 0.004)

-0.008(1)(-0.008 - -0.008)

0.01(1)(0.01 - 0.01)

-'0.007(1)(-0.007 - -0.007)

0.001(1)(0.001 - 0.001)

0.02(11)(-0.01 - 0.1)

2.6(11)(1.4 - 4.0)

0.0002(11)(-0.005 - 0.004)

-0.0004(11)(-0.005 - 0.001)

0.001(11)(-0.003 - 0.008)

0.002(1 1)(-0.0002 - 0.006)

,0.002(1 1)(-0.005 - 0.01)

0.003(11)(-0.004 - 0.01)

0.0009(1 1)(-0.009 - 0.004)

0



LOCATIONOF FACILITY: LUZERNE COUNTT, PENNSYLVANIAREPORTING PERIOD: JANUARY05, 1994 TO JANUARY09, 1995

Page 17 of 19

ANALYSISAND LOWERLIMfl'EDIUM

OR PATHWAY TOTALNUMBER OFSAMPLED OF ANALYSES DETECIION

(UNII'FMEASUREMENI) PERFORMED(1) (LLD) (2)MEAN(3)RANGE



MEAN(3) REPOR1KDRANGE MEASUREMENTS(4)

69 0.06

69 0.06

— Cs-137 69 0.08

Ba-140- 69

la-140 69

Anhnala(pCI/g wet)

Gamma SpecK-40 11

Co-58

Fe-59

Co-60

Zn-65

Zr-95

Nb-95

Food/Garden Cont. 1-131Crops(pCl/g wet)

Cs-134

-0.0005(58)(-0.007 - 0.006)

-0.0002(58)(-0.008 - 0.004)

0.002(58)(-0.005 - 0.01)

0.003(58)(-0.01 - 0.03)

0.00008(58)(-0.007 - 0.006)

3.8(10)(3.2 - 7.2)

0.0002(10)(-0.002 - 0.003)

-0.001(10)(-0.006 - 0.003)

0.001(10)(-0.007 - 0.01)

-0.00006(10)(-0.005 - 0.004)

0.0003(10)(-0.01 - 0.01)

0.004(10)(-0.007 - 0.01)

0.003(10)(0.0 - 0.006)

12B10;5mi WSW

12F57.5 ml WSW

8A50.8ml SSE

15A30.9ml NW

12Bl1.3ml WSW

3SOnslte NE

15SOnslte NW

5SOnsite E

15SOnslte IAV

5SOnslte E

2H>20m( NNE

15SOnslte NW

3SOnslte NE

0.002(3)(0.0009 - 0.003)

0.004(1)(0.004 - 0.004)

0.007(3)(0.004 - 0.01)

0.01(l)(0.01 - 0.01)

0.002(1)(0.001 - 0.004)

7.2(1)(7.2 - 7.2)

0.003(l)(0.003 - 0.003)

0.0006(3)(-0.002 - 0.003)

0.01(l)(0.01 - 0.01),

0.002(3)(0.002 - 0.004)

0.01(l)(0.01 - 0.01)

0.01(1)(0.01 - 0.01)

0.006(1)(0.006 - 0.006)

-0.001(11)(-0.006 - 0.004)

-0.0002(11)(-0.005 - 0.003)

0.003(11) 0(-0.0005 - 0.006)

0.002(11)(-0.006 - 0.01)

-0.00006(11)(-0.005 - 0.003)

4.1(l)(4.1 - 4.1)

-0.00009(1) 0(-0.00009 - -0.00009)

-0.003(1)(-0.003 - -0.003)

0.002(1)(0.002 - 0.002)

0.002(1)(0.002 - 0.002)

0.01(1)(0.01 - 0.01)

0.007(l)(0.007 - 0.007)

0.003(l)(0.003 - 0.003)



LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORI'ING PERIOD: JANUARY05, 1994 TO JANUARY09, 1995

ANALYSISAND LOWER LIMfrMEDIUMOR PATHWAY TOrALNUMBER OF I

SAMPLED OF ANALYSES DElECI1ON(UNITOF MEASUREMEN1) PERFORMED(1) (LLD) (2)

MEAN(3)RANGE

Page IS of 19

INAME MEAN(3)

DISI'ANCEAND DIRECIION RANGE


MEAN(3) REPORIEDRANGE MEASUREMEN1$(4)

Anhnals cont.(pCl/g wet)

Eggs(pCl/g wet)

Cs-134

Cs-137

Ba-140

La-140

Gamma SpecK-40

Mn-54

Co-58

Fe-59

Co-60

Zn-65

Zr-95

Nb-95

-0.0001(10)(-0.007 - 0.008)

0.2(10)(0.0 - 0.8)

0.001(10)(-0.008 - 0.01)

-0.002(10)(-0.01 - 0.003)

1.3(1)(1.3- 1.3)

0.005(l)(0.005 - 0.005)

0.003(l)(0.003 - 0.003)

0.003(l)(0.003 - 0.003)

0.003(1)(0.003 - 0.003)

0.002(1)(0.002 - 0.002)

-0.001(l)(-0.001 - -0.001)

0.006(1)(0.006 - 0.006)

15SOnslte NW

15SOnslte NW

3SOnsite NE

3SOnslte NE

10D13.0ml SSW

10D13.0m( SSW

10D13.0mi SSW

10D13.0m( SSW

10D13.0m( SSW

10D13.0ml SSW

10D13.0m( SSW

10D13.0m( SSW

0.008(1)(0.008 - 0.008)

0.6(1)(0.6 - 0.6)

0.01(l)(0.01 - 0.01)

0.003(1)(0.003 - 0.003)

1.3 (1)(1.3 - 1.3)

0.005(1)(0.005 - 0.005)

0.003(1)(0.003 - 0.003)

0.003(1)(0.003 - 0.003)

0.003(l)(0.003 - 0.003)

0.002(1)(0.002 - 0.002)

-0.001(1)(-0.001 - -0.001)

0.006(1)(0.006 - 0.006)

0.0009(l)(0.0009 - 0.0009)

0.05(l)( 0.05 - 0.05)

-0.003(1)(-0.003 - -0.003)

-0.003(1) 0(-0.003 - -0.003)

Only Indicatorstations sampled forthis medium.


OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM - 1994NAMEOF FACILITY'USgUEHANNASTEAM ELECTRIC STATION

LOCATIONOF FACILITY: LUZERNE COUNTY, PENNSYLVANIAREPORTING PERIOD: JANUARY05. 1994 TO JANUARY09, 1995


SAMPLED OF ANALYSES DEIECIIONIUNITOF MEASUREMEÃ1) PERFORMEDII) ILLD)I2)

MEAN(3)RANGE

Page 19 of 19

NAME MEANI3)DISFANCE AND DIRECIION RANGE


MEAN(3)- REPORIEDRANGE MEASUREMENIS(4)

Eggs Cont.(pCI/g wet)

Cs-134 1

Cs-137

Ba-140

La-140

-0.002(1)'-0.002- -0.002)

0.005(l)(0.005 - 0.005)

0.001(1)(0.001- 0.001)

0.007(l)(0.007- 0.007)

10D13.0ml SSW

10D13.0m! SSW

10D13.0ml SSW

10D13.0 ml SSW

-0.002(1)(-0.002 - -0.002)

0.005(1)(0.005 - 0.005)

0.001 (1)0.001- 0.001)

0.007 (1)(0.007- 0.007)

Only Indicator 0stations sampled forthis medium.

1. The total number ofanalyses does not include duplicates, splits or repeated analyses.2. The Technical Spec)Acatlon LLD's are shown when applicable.3. The means are based on all analysis results.4. USNRC reporung levels are specified In the Technical Specifications.

APPENDIXHV w>kh vwyvC:y"<v >'. wvv~&v)vr, rgp>yvyp)wvCdpg'+'pyWAw~ (NvSv v> XC'%CATE'{>M(MOX(@pg,"~+ C~)~w vow+ vga( gg&M+r45yC )g+)Wpr &vyvw

""'':"COMPARISO>Ã=rOF.".-''V'tDICA'.T~OR-'>AND~CONTRO>I""'"':;':.~":::=';I'994'-:'.,REMP'-',:A'NP'O'JA

"':.=.."'Am9X4.-ANAXVSS'RXSULTl:S;%ma:MZANS:.'-::.'::-8

1994 Radiological Environmental Monitoring Report H-1

A endix H

The data presented in the following tables were included ifspecific analysis resultsroutinely exceeded the applicable MDCs in 1994 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.


A endix H

AMBIENTRADIATIONMONITORING

TABLE HII'AMBIENT~RA'DIA'TXONlLEVELS"A'S'MEA'SUR19))SY='TRDS!'R/STD'. TR t''i

LocationPeriod Pre-0

Indicator0 erational Pre-0

Control0 erational

Ran e

1978-81

18.5-19.2

1982-93

15.5-19.2

1994 1978-81 1982-93

15.0-17.9 15.9-19.2

1994

Mean 18.9 17.9 14.7 16.3 17.7 14.8

A UATICPATHWAYMONITORING

TABLEH2: 'I ~'".%'."..':!'";:-"".--'''-SURFA'CE:WATER';GROSS~'ALPHA~A'CTIVZHZ~S!'i/l 4'"-'i'"'""'-"'.—:4'-'-:-:"""'~

LocationPeriodRan e

Mean

Indicator19S4-93

0.4 - 4.31.8

1994

0.4

1984-93

0.2 - 3.1

1.4

Control1994

0.3

TABLEH3Z""5''. '"'j'.SURFACE"'WATER"'GROSS''.BETA''i'A'CIIVITIESi'Ci/l',: i'i'5'~i"""''i!„: 'i(".,",""'q';g



Control0 erational

1978-81 1982-93 1994 1978-81 1982-93 1994

Ran e

Mean3.2-4.9

3.83.0-7.7

5.4 5.62.9-5.2

4.02.9-4.8

3.7 3.4

TABLEH4'"'. '':l'":". "

'::"""'~!':."".,'". ''SURFA'CE"WATER:IODINE-'.".131.A'CTIVI'I'IES 'Ci/1::"'';::!!q'gi"',::':~::i".':i:'"';:,"',

LocationPeriod

Ran e

Pre-0Indicator

0 erational1979-81 1982-93 1994

0.24-0.37 0.06-0.60

Pre-01979-81

0.29-0.43

1982-93

0.03-1.01994

Control0 erational

Mean 0.29 0.30 0.1 0.36 0.30 0.1

H-3 1994 Radiological Environmental Monitoring Report

A cadiz H

TABLEH5::.,:.':.:'::":.:.'""'-;.".-:::::i'";::"""'4"".,':.".'."SURFA'CE:%ATER~TRH'IUM"ACXIVXTIES'.''Ci/1<4~ i~<'.".''>"-"'"-'l''i'i

LocationPeriod

IndicatorPre-0 0 erational Pre-0

Control0 erational

Ran e

Mean

1978-81 1982-93101-122 126-581

109 409

1994

1068

1978-81

119-319171

1982-93

46-212107

1994

-5

~1990 results were not averaged with 1982-93 data because the validity ofthe 1990 values is questionable in some instances. Laboratory analysiserror is suspected. See the 1990 Annual Report.

TABLEH6i'::iii:::ilia"':":i!!DIIBIKIN|'WA'TER'GROSKRLPKllA'CI1VITIM

Period

Ran e

Meanmedian ""

Preo erational1980- 81

1.3

0 erational1982- 93

0.1 - 10.02.51.2

1994

0.2

TABLEH7'i:: i'"'"';":4%".':::j.".i"'DRINKINC'WATER',GROSSBETA'"A'CTIVHXES "Ci/l';ail~".-„:.'k."„e%'g,'":.i

Period

Ran e

Mean

Preo erational1977 - 81

2.2 - 3.22.7

0 erational1982- 93

2.4 - 5.43.3

1994

2.5

TABLEH8"~"': ""'. " ".".4k"".'DRINKING'WATER'~TRITIUM',A'CTIVITIES':"Ci/1 ',":,'.:.~',

Period

Ran e

Mean

Preo erational1977- 81

101 - 194

132

0 erational1982 - 93

1.5 - 220107

1994

20


A endix H

TABLEH9;.',«jy,;.';,:~ -qs~g<y'8';,".;.CABAL'GAE;BERYLLIUM'-'7:A'.CTIVFHES'Cil'"d ' '"4

LocationPeriodRan e

Mean

Indicator1985- 93

4.1 - 9.06.4

1994

5.3

Control1985- 93

4.3 - 7.76.1

1994

5.4

TABLEH10k8%'.: 4»'.~gg:;-gÃ~%A'L'GAE'POTA'SSIUMAO 'ACTIVITIES'Cil':.d" 'i'k$ 8~',4:,;,:4i"",..'.";i

LocationPeriodRan e

Mean

Indicator1985- 93

9- 18

13.9

1994

20.9

Control1985 - 93

11 - 17

13.7

1994

19.1

~1990 results were not averaged with 1982-93 data because the validity ofthe1990 values is questionable in some instances. Laboratory analysis error issuspected. See the 1990 Annual Report.

TABLEH11..'":::;"-'":.'6'..'."':!":.4$"":;:::-".',:-':":-'l'i"'A'L'GA'E:,THORIUM-'.228'"A'CTIVITIES'Cil-":d"'-.i::."';).'-",'..;:.:''"+'.""0":::l..".:::".,::.'".'..':.'::"':.'N

LocationPeriodRan e

Mean

Indicator1985 - 93

0.8 - 1.5

1994

1.2

Control1985 - 93

0.8 - 1.4

1994

1.0

TABLEH12-. -: '-.-'.-'-''-< "*.—A.':.-~:.:, ';4'0'ALGAE IODINE-'131!A'CTIVITIES'; Ci/ 'd '>'+'&"-~4"">-'"-"':~~V'%'""'-5':

LocationPeriodRan e

Mean

Indicator1984 - 93

0.3 - 3.21.2

1994

0.3

Control1984 - 93

0.3 - 3.1

1.2

1994

0.3

~1990 results were not averaged with 1982-93 data because the validity ofthe 1990 values is questionable in some instances. Laboratory analysiserror is suspected. See the 1990 Annual Report.


A endix H

TABLEH13'.Ã%Ãke~.'RAYi'.""Fk>C'4AI'.GAE':CESIUM-"137,'ACTIVXIIES; Ct/ 'd:;.;;-.'..-.="""-'.:";.i":..5>'~:=,7-",'';

LocationPeriod

Indicator1984- 93 1994

Control1984 » 93 1994

Ran e

Mean0.15 - 0.48

0.26 0.170.15 - 0.82

0.31 0.18

TABLEH14N%'::"-:!"".::: 5~%':@O'A'LGAX'MA'NGA'NESE='54";A'CI'IVXXY.'Ci/""d'"'~»'"-'"'"'@""

":.';;P>.'!:',7:"'ocation

PeriodRan e

Mean median

1984-93

0.3 - 2.00.8

Indicator1994

0.2

TABLE HIS%;-".:.''.-:; ~ ..",:";:.'"'k%.":- '<%~~~A'L?GAK:COBA'LY-'60."A'CIIVXZY."'i'/",'d".'N59P~,~<,-'.i~~! i4';'gg!~,'~~gg~

LocationPeriodRan e

Mean

1984-930.3-1.1

0.8

Indicator1994

0.2

TABLEH16"'"'""":":~"'> """~~;~."..'FISH:;GROSS;BETA".A'Cm?I'IIES': "Ci/ 'w'et 0'..";-."'kP~".~+:%!"k'!-".~-'::-:.ikey',

LocationPeriod'Ran e

Mean

Indicator1984 - 93

3.7 - 5.85.0

1994

6.1

Control1984 - 93

2.2 - 6.84.8

1994

4.8


A endix H

TABLEH17.:Fa'.P';:ski:-".-:-:.::;:.:::<BK3XSH3',OTASSIUM-40'AClIVXIKS> 'Ci/";nyet ': AÃ5!':;:-".,;.~''',:-".""..':",,:l

Location Indicator ControlPeriod Pre-0 0 erational

1977-81 1982 93 1994

Ran e 2.7-3.5 3.1-5.3

Pre-01977-81

2.8 - 3.6

1982-93

3.1 - 4.1

19940 erational

Mean 3.2 3.8 3.9 3.2 3.7 3.6

TABLEH18:"'"'" i:i'"i':a:"-':<"-"""':"''SEDIMENT!GROSS'ALPEN''(YIVITIES'i/"d" 'l'"''i" '"X"'~"''."

'":""-"."'ocation

Period

Indicator

1982 - 93

Ran e 6.0 - 17.0Mean

1994

11.8

Control

1982 - 93

5.7 - 14.5

11.2

1994

14.0


TABLEH 19.~':;:, ":!i,'.I"",'::,"":;",SEDIMENT;GROSS'BETA'".A'CTIVITIES'''i/"'d" 'l'l8~"'":":""'"""''<)I~"5'"-'j

LocationPeriodRan e

Mean

Indicator1984 - 93

19.7 - 35.528.8

1994

~ 31.4

Control1984 - 93

20.5 - 33.028.2

1994

34.3

*1990 results were not averaged with 1982-93 data because the validity ofthe 1990 values is questionable in some instances. Laboratory analysiserror is suspected. See the 1990 Annual Report.


A endix H

TABLEH20:",s4":.'.kk''.":.''.-""8,'".~C"'~!'SEDIMENT.'POTASSIUM-'40"A'ocation

PeriodIndicator

Pre-0 0 erational Pre-0Control

0 erational

Ran e

1978-81 1982-93

8.6-10.4 7 4-13.21994 1978-81

7.5-11.0

1982-93

6.2-12.51994

Mean 9.3 10.2 11.0 9.4 10.2 11.2

TABLEH21kl8'. Z'9'~A5e@le~~':!SEDIMENT.:R'ADIUM-.'226'ACXIVIIXES'Cil"':":d"

'.:."k%';:;-"x%':-".:>%''.'::-':-':-:.'h)~: i;:

Location Indicator ControlPeriod

Ran e

Pre-01978-81

0.5-0.7

0 erational Pre-0 0 erational

0.6-1.9 0.4-2.10.5-1.919941982-93 1994 1978-81 1982-93

Mean 0.6 1.4 1.6 0.7 1.5 2.0

TABLEK22-',":<~Sr~~'"'ll".~SEDIMENT.'THORHM-'.228A'CTIVITIES'Cil .'d 5+ ~C":%c>-"-';:!'-.",-'.l

LocationPeriodRan e

Mean

Indicator1984 - 93"

1.0 - 1.3

1994

1.0

Control1984 - 93*

1.0- 1.4

1994

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

TABLEH23''"': ll': ''""'."."'","SEDIMENT'CESIUM '137 A'CHVITIES" Cil ""d"'



Control0 erational

Ran e

Mean

1978-81

0.08-0.150.10

1982-93

0.04-0.170.10

1994

0.05

1978-81

0.08-0.210.12

1982-93

0.06-0.210.12

1994

0.10


A endix H

ATMOSPHERIC PATHWAYMONITORING

TABLEH24>Ni':~,"i'',",'":eccl><~iNCR@c%'.'>As>':.c»>>>>'HC~'~~>%~i"~<"r'~~~ <:i':, '.quip>,@ c ~S'4%'4"<'~%&~%';cg>".,~ ~V~K$<'c.cÃj<>~~ >',~C<c't:*')iiiiii'!ilia'c>>>>>'R><C>t%<X!<RQ<c>IE>AA-1>VI>l>S!- - >><"',.:::ll'i'll'i':.',

Ran e

Mean24-97

61


1978-81


13 -2917 16

24 «10262

1982-93 1994 1978-81 1982-93

12-2816

1994

16

Control0 erational

TABLEH2$,;..''<'~:„.,'.c,',:gggN; N>'(&g~r..::rA'c>>;S>4'cj»"cd<"A'".<~A<qK>.:c-'~>ca:R"c~4"- . ~>S. ?w~Z S "rw>MW!4C>R8X<X')~+>c0:;~44!,';;;i~N~A'IR'.PA'RTICULATEiGROSS!'A''LPHA'""..A'CTIVXFIES ",3; Cij'iii",-;. '-4'::;:.':;"-:5

LocationPeriod

Ran e

Pre-01980-81

2.8 - 3.1

Indicator0 erational

1982-93 1994

1.6 - 6.8

Pre-0198(481

2.2- 3.5

Control0 erational

1982-93 1994

1.4 - 9.0Mean 3.0 3.6 3.0 2.9 3.7 2.7

«1990 results were not averaged with 1982-93 data because the validity ofthevalues is questionable in some instances. Laboratory analysis error issuspected.

TABLEH26<t<" '.~'rid% ~;: ".>A.".ci>c.'::K$'> 'n'(~<X% <»:<C>>;.. '2c>'Cc'~><> .>>.;2 '. ~»'<2~~~<><.. >rm< .'.A ":>>:ccrc<"c<~cx<g'Mw+~NÃP:."~:;":..c:.''

'5'-"-'".-''--:.'-FAIR'PA>'RTICULATE:BERYL<L<IUM-:7-'A'CTIVITIES'"''3:"'ilin"!.-"'<':;-:,"::>;::.":;.',"<':-'.--:,:



19941978-81 1982-93Pre-01978-81

Control0 erational

1982-93 1994

Ran e

Mean69- 81

76

62- 113

76 124

59- 85

7253 - 118

72 118

*1990 results were not averaged with 1982-93 data because the validity ofthe1990 values is questionable in some instances. Laboratory analysis error issuspected. See the 1990 Annual Report.


A endix H

TABLEHZ7«%c%i"-'' "":('."'!;<9k.",%PRECIPITATION-'.GROSSIA'LPEA.A'CTIVITY»"'Ci/l '4''".";':~;:=~%;"':';:-'-".:::;"::K

LocationPeriodRan e

Mean

Indicator1984- 93

0.6- 1.3

0.9

1994

0.6

Control1984 - 93

0.6- 1.1

0.9

1994

0.5

TABLEHZS

NiY'..F>~k'>~<4".;%VX'FRECIPITATIO¹GROSS':SETA'"'A'CTXVXEY'CitlY4%"",-.'.7(K%:::"-''"':

Location Indicator ControlPeriod 1984 - 93

Ran e 2.5 - 4.4

1994 1984- 93

3.4 - 5.8

1994

Mean 3.9 4.3 4.2 4.0

TABLEH29" ''>@ '4"~~'Pk.~~""''':PRECIPITATXO¹TRITIUM~A'CTIVXIW<S 'C ~4~:;F;;:-','.':".lg.:5':".%."!

LocationPeriod ~ Pre-0


Control0 erational

1980-81 1983-93 1994 1980-81 1983-93 1994Ran e

Mean 109166

119 - 213 13 - 20028

99- 135

117

-18 - 530137 -25


TERRESTRIAL PATHWAYMONITORING

TABLEH30>~~""~"'<-<":.'".N~"'-.""'~SOIL'!POTA'SSIUMAO'A'CTIVITIES' Cil 'd" "

':E5.',~'.,:":.A>$".,",;<"',",".':.-,":.-."!~F-:.';:.",


1979&81

Indicator Control0 erational Pre-0 0 erational

19941984-93 1994 1979&81 1984-93

Ran e

Mean9.2 - 9.7

9.59.4-14.3

11.2 10.79.1-11.0

10.1

7.4-14.110.5 9.6


A endix H

TABLEH3I"~"".":4'::.Xu'..":'::~"."~.",i:i~.::~iSOIL"::RA'DHJM-;226"'ACTLVXXXES' Cil 'd "

'Nr:,:;i'».'".!'!'-'.".'.'~."''.~::.;,'.k~'.."i'ocation

PeriodIndicator

Pre-0 0 erational Pre-0Control

0 erational1979&81 1984-93 1994 '979&81 1984-93 1994

Ran e

Mean0.8 - 1.3 0.8 - 2.5

1.6 1.5

0.8 - 1.2

1.0

1.0 - 2.1

1.8 1.8

TABLEH32::'O'.-'::6!XN''"-":5";=':;:,"::";:::",-::.::.";-':SOIL"',THORHJM-'2? 8ACXIVIIIES'. 'i/ '"d '".~~4~%~

"""'""~P~"~-'"""'ocation

Period Pre-01979&81

Ran e 0.9 - 1.3

1984-93

0.8 - 1.3

1994


Control0 erational

19941979&81 1984-93

1.0 - 1.2Mean 1.0 0.8 1.0 0.9

TABLEH33-"''-'-"'-:- ""'-'::.""-'-: "-": '<"'" '.",':SOIL"':.'.CESIUM-'137;-A'CIPHER'IES', 'Ci/".d'";" RC>84~7)~PM"'K%55



Control0 erational

Ran e

1979&810.5 - 0.7

1982-93

0.2 - 0.5

1994 1979&810.2 - 1.2

1982-93

0.2- 1.2

1994

Mean 0.6 0.3 0.2 0.7 0.5 0.5

k

TABLEH34;- -':-,:~ P~~Ã''-'EGETATION:SERVLLIUM-'7,ACTIVI'HXS< "Cil - w'et .,'&%5%I~'"".i

LocationPeriodRan e

Mean

Indicator1986 - 93

0.6 - 3.1

1994

2.9

Control1986- 93

0.4 - 2.21.3

1994

1.9


A endir H

TABLEH3$N~;".'.:;".::,"Y9"'Ps%'.-...VEGETATION!POTASSIUMAOA'CTBPXX'IES','"Ci/ ''wet

'..:;:.."::"::~::0N'3"'-:":"'.'ocation

Indicator ControlPeriod 1986- 93*

Ran e 6.0- 8.8

1994 1986- 93*

4.3 - 7.2

1994

Mean 6.6 4.6 5.8 3.1

«1990 results were not averaged with 1981-93 data because the validityofthe1990 values is questionable in some instances. Laboratory analysis error issuspected. See the 1990 Annual Report.

TABLEH36'.":::.-,:.=.'":.::"'..";"»:;>%FRUITS/VEGETA'BLESPEA'SSIUM-'."40,"-A'CTVQTIES." 'Ci/';iiet "'."",~~X,"5F,''

LocationPeriod

Ran e

Pre-01980-81

2.5 - 3.0


1982-93 19942.0-4.2

Pre-0Control

0 erational1994

3.0 - 3.1 2.2 - 2.8

1980-81 1982-93

Mean 2.8 3.0 2.2 3.1 2.5 2.6

«1990 results were not average. with 1982-93 data because the validity ofthe1990 values is questionable in some instances. Laboratory analysis error issuspected. See the 1990 Annual Report.

TABLEH37'~)"':~" ":,''""":"""'""'<~'~~~""MILK'STRONTIUM-".90'A'CTllITIIES"."Ci/l 'P''"~4~~""4 "'"":i"':'"""'5"ii'l@~



Control0 erational

1978-81 1982-93 1994 1978-81 1982-93 1994Ran e

Mean4.3 - 5.3

4.91.5 - 6.8

4.6 2.71.7 - 7.5

5.01.7 - 6.9

44 3.3

«1990 results were not averaged with 1982-93 data because the validity ofthe1990 values is questionable in some instances. Laboratory analysis error issuspected. See the 1990 Annual Report.


A endix H

TABLEH38'""'i"'""'~~'i)'"'::'-'@'""-"""'""::""~'""'MLK.POTASSIUM'40'"ACTIVI'HES't/1'l""'~""':ltd''":~"'~"7s""' "

"'ocationIndicator Control

Range 1222-1500

Period Pre-01978«81

0 erational Pre-0 0 erational1985-93

1241-1357

1994 1978-81 1985-93

1273-1500 1247-1363

1994

Mean 1353 1321 1356 1390 1335 1328

TABLEH395'-".'.:'k4.":::."'"i;-'t':::;Z4::."N.:::'"'".GAMEiPOTA'SSIUM-"40lA'CIIVITXESI'Ci/"';wii't;:.'"':""'."'~@'4'i-""""'4""Ni~~

Period

Ran e

Mean


1.8 -'4.82.8


2.7 - 3.73.0

1994

3.8

*1990 results were not averaged with 1982-93 data because the validity ofthe1990 values is questionable in some instances. Laboratory analysis error issuspected. See the 1990 Annual Report.

TABLEH40.'""';- -'"..'-"::::!~a':.'-"'",::-'4'."GAME"CESIUM-:.137!A'CI'IVITIES;: Ci/',''w'et '("'""~>"-"'""''~''""""-""~

Period

Ran e

Meanmedian


0.0 - 8.8

1.91.1


0.1 - 1.6

0.6

1994

0.2

TABLEH41""'"'.%i"'. GROUND.WATER,GROSS;ALPHA"'ACTIVITKS'' "

Ci/l '»",":iU.'ig„''5~j~j



Control0 erational

Ran e

1980-81 1982-93 1994 1980-81

0.2 - 4.5

1982-93

0.05 - 2.7

1994

Mean 2.7 1.9 0.3 <MDC 0.5


A endix H

TABLEH42>,':: ~,'.",':~"",:,:::."".j.@~GROUN9k%ATER"GROSSlSETA''-'.A'CFIVXXKS:'(p'Cdl)'"..„"„'"-~"''„~"'Pf,:ji>'"."LiicotToii%isiv:::.':;-oYRt-'.::mtri~diciitor',",:::"at~<'~i'A'iig@roggk.::-'..K!'Coiitrol'."'ii~o3:"~mt'~.:

Period Pre-0 0 erational Pre-0 0 erational1980-81 1982-93 1994 1980-81 1982-93 1994

Ran e 3.2 - 3.4 1.2 - 3.7 1.9 - 3.0 1.8 - 2.8Mean 3.3 2.3 1.6 2.5 2.3 2.8

TABLEH49o 'C)i~ "QRO~'~+TER TRITIUMQjCTO~' Qg ~o j re


1980-81


1982-93 1994Pre-01980-81

Control0 erational

1982-93 1994Ran e

Mean93-109

101

" 27-180104 23 118 124

117 - 119 44 - 26034


APPENDIXIWy«y y@h)pylyppyv~l)yvwvvvAv)w w /vying v hy ~ pAyv~qygrpAw/vvw gvpv4 gyAgv g@jh ~VAsyg (yy/ivypvgfyp@Aygy pg yr~~p$y gyy g Yyg

"'SPECI'FXC<-,„-"A''NALYSIS:.'"';RESKI:.


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 ofthe sample, the background count rate, the

count'imes,

the method used to round ofF the value obtained to reflect its degree ofsignificance, and other factors. The uncertainties ofactivities determined by gammaspectrometric analyses are also influenced by the relative concentrations oftheradionuclides in the sample, the energies and intensities ofthe 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 ofthe detection capabilities oftheoverall measurement method, taking into account not only the counting system, but alsothe characteristics ofthe 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 ofspecific radionuclides, such as the man-madegamma-emitting radionuclides beryllium-7 and cesium-137, 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.

1994 Radiological Environmental Monitoring Report I-2

TABLEI-I

ENVIRONMENTALTHERMOLUMINESCENTDOSIMETRYRESULTS

SUSQUEHANNA STEAM ELECTRIC STATION- 1994

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

Page I of7

Lomflon

First Quarter

I/10/94

to

4n/94

Second Quarter

4/5/94

to

7/14/94

Third Quarter

7/l2/94

to

IO/6/94

Fourth Quarter

IO/4/94

to

I/12/95

TLDs WITHINPPEcL BOUNDARY

IS2 +282 0

2S3 +382

383

3S4 +4SI

4S3 +5SI

5S4

5S7 +6S4 +688

6S9 +7S6 +7S7

7S8 (7AI)8S2 +9S2 +

11.8 +0.512.9 +0.511.5 +0.312.3 +0.312.0 +0.512.1 +0.110.7 +0.514.5 +0.410.4 +0.211.3 +0.412.2 +0.215.3 +0.410.9 +0.313.1 +0.514.3 +0.5

(4)11.6 +0.314.3 +0.416.1 +0.4

15.1 +0.615.2 +0.914.8 +0.814.7 +0.912.9 + 1.1

14.2 +0.612.0 +0.316.5 +0.4

- 12.5 +0.713.9 +0.513.9 +0.617.9 + 1.0

13.8 +0.716.0 +0.816.3 +0.8

(4)13.1 +0.916.3 +0.518.6 +0.8

16.1 + 1.2

15.6 +0.515.9 +0.915.1 +0.713.5 +0.514.8 +0.613.0 + 1.0

16.9 +0.813.0 +0.414.3 +0.814.4 +0.618.6 +0.814.3 +0.417.3 +0.616.7 + 0.6

(4)14.1 + 0.5

17.4 + 0.5

20.3 + 0.7

16.2 + 1.6

15.8 +0.915.9 + 1.5

15.2 +0.714.1 +0.614.6 +0.913.1 +0.917.3 +1.3

(4)14.5 + 1.0

14.8 + 1.0

19.1 + 1.4

(4)18.1 +0.516.6 +0.915.0 + 1.3

14.1 +0.717.4 + 1.1

21.0 + 1.6

See the comments at the end ofthe table.

TABLEI-I


SUSQUEHANNA STEAM ELECTRIC STATION - 1994

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

Page 2 of7

IOSI +IOS2

IOS3

I IS2I IS3 +I IS6

I IS7

12SI

12S3 +12S4

12S5

12S6

13S2 +13S4

13SS

13S6

14SS +14S6

15S4

15S5 +16SI +16S2 +

First QuarterI/10/94

to4/7/94

I I.l + 0.3

15.7 +0.5(4)

11.0 +0.414.7 +0.410.5 +0.4

(4)

(4)143 +2.913.0 +0.4I 1.7 + 0.3

I 1.7 + 0.3

13.2 +0.313.5 +0.214.2 +0.3

(4)13.0 + 0.5

12.3 +0.310.7 +0.212.8 +0.412.7 +0.414.1 +0.4

Second Quarter4/5/94

to7/14/94

13.3 +0.618.0 + 1.3

(4)12.7 +0.719.8 + 1.5

12.8 +0.8(4)

(4)18.2 +0.918.4 +0.916.7 + 1.0

16.3 +0.416.9 +0.917.4 +0.718.0 +0.5

(4)16.4 + 1.3

16.2 +0.913.4 +0.615.8 +0.715.8 +0.817.0 +0.9

Third Quarter7/12/94

to10/6/94

13.9 +0.519.3 +0.7

(4)14.3 + 1.0

20.2 +0.713.7 +0.7(4)

16.6 +0.318.6 +0.919.7 + 1.7

17.5 +0.917.2 + 1.0

17.7 *0.918.4 + 1.4 (7)19.2 + 1.0

(4)17.6 + 0.6

16.8 4 1.2

(4) +16.3 + 1.1

17.1 + 1.1

17.8 + 1.3

Fourth Quarter10/4/94

to/l2/95

14.1 +0.919.5 +0.913.9 + 1.6

(4)20.5 + 1.6

(4)16.2 + 0.8

17.0 + 0.7

19.6 + 1.6

19.9 + 0.6

17.7 + 1.0

16.9 + 1.2

17.9 + 1.5

18.1 +0.819.1 + 1.4

18.2 + 1.3

17.4 + I.I17.2 + 1.1

(4)16.7 %0.6

16.7 + 0.7

18.5 + 1.0

See the comments at the end ofthis table.

TABLEI-1


Page 3 of7



Location

0-1 MILEOFFSITE

First Quarter

I/10/94to

4/7/94

Second Quarter

4/5/94

to

7/14/94

Third Quarter

7/12/94

to

10/6/94

Fourth Quarter

10/4/94

to

/12/95

6A4 +7A2

8A3

15A3

16A2

12.6 %0.3

12.1 +0.4I 1.7 + 0.2

I 1.9 + 0.3

10.2 +0.4

16.6 + 0.9

14.3 +0.813.7 +0.415.1 +0.613.1 +1.0

15.5 +0.315.5 +0.914.3 +0.916.0 +0.714.2 + I.I

15.9 + 1.0

(4)14.5 + 1.4

15.4 *1.114.2 + 0.8

1-2 MILESOFFSITE

IBI2B3

2B4

4BI5B2 0

6B2

7B2

7B3

12.2 +0.412.0 +0.1I 1.6 + 0.3

1 1.4 + 0.2

12.7 +0.812.2 +0.61 1.3 + 0.4

I 1.1 + 0.4

14.8 +0.514.3 + 0.7

14.1 + 1.1

13.5 +0.914.6 +0.814.4 +0.914.1 +0.414.1 +0.6

15.2 + 0.7

15.3 +0.814.9 + 1.0

14.7 + 0.7

15.5 +0.9 (7)15.3 +0.715.1 +0.913.6 + 1.0

15.2 +0.915.4 + 1.2

15.1 +0.5(4)

16.2 + 1.3

(4)15.4 +0.714.7 + 1.4


TABLEI-I



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

Page4of7

Location

8B2 +8B3 i9BI10B2

IOB3

10B4

12B4

12B5 0

13BI

14B2

14B3

15BI 0

16BI

16B2

2Q MILESOFFSITE

First Quarter1/10/94

to

an/94

12.2 +0.314.1 +0.311.0 +0.210.7 +0.210.6 +0.511.7 +0.211.7 + 0.3

12.1 +0.511.7 +0.511.7 +0.6

(4)11.0 +0.210.3 +0.310.8 +0.2

— Second Quarter4/5/94

to

7/14/94

12.9 +0.614.7 + I.I13.8 +0.812.0 +0.711.9 +0.814.8 +0.9143 +0.514.0 + 1.2

14.5 +0.414.8 + 1.2

(4)13.9 + 0.6

12.5 +0.513.5 +0.5


to

10/6/94

13.8 +0.916.2 +0.814.0 + 0.7

12.3 +0.812.1 +0.515.2 4 1.2

14.6 + 0.8

14.6 + 1.3

14.8 +0.815.5 +0.6

(4)14.2 *1.412.9 + 1.0

14.1 +0.9


I/12/95

14.5 + 0.8

16.2 + 1.2

14.2 + 1.1

13.4 +1.412.6 + 0.9

15.4 + 0.7

15.5 + 1.4

(4)15.0 + 0.5

(4)15.7 + 1.1

14.8 + 0.6

(4)14.9 + 1.3

I ICI 13.4 +0.3 16.2 +0.5 17.0 + 1.0 17.8 + 0.6


TABLEI-I




Page 5 of7

~initio

First Quarter

I/10/94to

4/7/94

Second Quarter

4/5/94

to7/14/9

Tidrd Quarter

7/12/94

to10/6/94

Fourth Quarter

10/4/94

to

/ 5

ID2 'iID53DI +~

6DI8D3 +9D4 +IODI +12D2

14DI

12.0 +0.5(4)

12.8 + 0.4

(4)11.4 +0.411.5 *0.312.2 +0.212.3 +0.3

(4)

15.3 +0.6(4)

17.1 +0.7(4)

14.7 + 1.3

14.9 + 0.6

14.3 +0.815.8 +0.4(4)

17.0 +0.9(4)

18.8 +0.9(4)

15.8 +0.915.9 +0.515.3 +0.816.4 +0.9

(4)

(4)18.0 +0.8(4)

17.1 +0.915.8 +1.016.1 +1.116.2 +0.717.0 +0.816.1 +1.1

4-5 MILESOFFSITE

IEI4EI +4E2

5E2 +6EI +7EI +IIEI +12EI +,i13E4 +14EI + ~

11.4 +0.312.5 +0.4

(4)12.7 + 0.4

14.2 +0.112.0 +0.210.2 +0.311.5 +0.412.5 +0.4I 1.7 + 0.3

13.1 +0.514.5 +1.0(4)

15.3 + 1.0

16.7 +0.815.5 +0.811.6 +0.714.1 +0.814.3 +0.515.4 +0.6

13.7 +0.915.7 +0.8

(4)16.0 + I.I17.8 + I.l16.8 +0.812.5 +0.414.8 +0.515.1 +0.516.8 +0.7

(4)

(4)16.8 + 0.7

16.5 +1.617.7 6 1.1

16.9 +0.810.1 +0.715.1 +0.615.3 +0.8

(4)


TABLEI-I


SUSQUEHANNA STEAMELECIIuC STATION- 1994

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

Page 6 of7

Location

5-10 MILES OFFSITE

First Quarter

1/10/94

fo4n/94

Second Quarter

4/5/94

to

7/14/94

Third Quarter

7/12/94

to10/6/94

Fourth Quarter

10/4/94

toI/12/95

2FI +3FI +3F2

8F2

12F2 0

15FI +16FI +

12.0 +0.411.6 +0.713.8 +0.411.2 +0.312.6 + 0.6

11.8 +0.311.2 +0.3

13.8 +0.913.6 +0.814.6 +0.313.5 +0.814.9 +0.715.5 +0.815.5 +1.2

14.8 + 1.5

14.3 +1.215.4 + 1.2

14.4 +0.715.9 +0.416.0 +0.716.6 +0.8

15.1 +0.8(4)

16.4 +0.814.6 + 1.2

16.9 +1.217.4 +0.916.7 + 1.0

10-20 MILESOFFSITE

3G4

3G5 +4GI +7GI +7G2

12GI .+12G4

13.9 +0.513.9 +0.312.6 + 0.6

13.3 +0.511.2 +0.310.9 +0.311.6 +0.2

14.7 + 1.0

(5)17.0 + 1.1

15.1 + 0.7

14.5 + 0.4

13.3 + 1.1

13.9 + 0.4

15.7 +0.717.9 + 1.5

17.8 + 1.8

16.1 +1.115.7 +0.914.1 +0.815.2 +0.5

16.0 +1.1(4)

18.6 +0.816.6 + 0.7

16.2 +0.914.6 + 0.6

(5)


TABLEI-1


SUSQUEHANNA STEAM ELECTRIC STATION- 1994

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

Page 7 of7

Location

First Quarter1/10/94

to

4/7/94

Second Quarter4/5/94

to7/14/94


to10/6/94


to1/12/95

IndicatorAverage 12.2 + 2.6 14.9 +3.4 15.7 + 3.6 16.2 + 3.7

ControlAverage 12.5 +2.5 14.8 +2.5 16.1 +2.7 16.4 A2.9

COMMENTS

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

(2) Astandard (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 ofthe elementaldoses ofsix calcium elements from the two TLDs assigned to each monitoring location, representingthe variabilitybetween the elemental doses ofeach ofthe six TLDelements.

(4) TLDs were not in the field at this monitoring location during this quarter. Refer to section VIIof 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 ofthe individual monitoring locations.

(7) 'Ihese results are the average ofelemental doses Irom only these calcium elements for only one TLDassignedto the monitoring location. The other TLDwas damaged by exposure to water in the field.

+ ODCM -listed locations. ~ NRC co-located monitoring stations.

TABLEI-2

GROSS ALPHA. GROSS BETA, TRITIUM,AND GAMMA'PECTROSCOPIC ANALYSESOF SURFACE WATER


Results ln pCI/Itter 2 2S

Page I of 6

LOCATION COLLECTIONDATE GR-ALPHA GR-BETA TRITIUM OTHER ACTIVITY COMMENTS

1D36866S66S56S76S76S76S7LTAW12Fl12G212H1

1D36866866356S7LTAW12F112G212H1

1D36S66S56S7LTAW12Fl12G212H1

01/10/9401/10/94-01/31/9401/31/94-02/07/9401/10/94-02/07/94Ol/10/9401/10/94-01/17/9401/31/9401/31/94-02/07/94Ol/10/94Ol/10/9401/10/9401/03/94-02/07/94

02/14/9402/07/94-02/22/9402/28/94-03/07/9402/14/94-03/07/9402/07/94-03/07/9402/14/9402/14/9402/14/9402/07/94-03/07/94

03/14/9403/07/94-03/28/9403/14/94-04/04/9403/07/94-04/04/9403/14/9403/14/9403/14/9403/07/94-04/04/94

<1<1< 1

<1<2< 1

<2<2<1< 1

<2<1

< 0.8<1<2

< 0.9<2<2<1

Not collected< 0.9

<1<1

< 0.9<2<1<1<1< 1

3 1 k 1.03.1 2 0.93.3 % 0.83.5 i 0.927k 27.5 2 1.315% 216% 2

4.9 R 1.23.7 i 1.04.8 k 1.23.9 i 0.9

4.0 i 0.92.7 i 0.71.5 0 0.92.5 2 0.621% 24.8 % 1.12.8 2 0.8

3.2 R 0.7

3.0% 0.83.7 2 0.62.9 R 0.6182 2

2.8 2 0.92.9 R 0.82.7 2 0.82.9 2 0.6

< 100< 100< 100

110 2 701800 2 100

23000 i 1000250-R 70

3100 k 100150 k 70110 R 70220 R 70

< 100

< 100< 100< 100< 100

3500 2 100990 t 90

< 100

< 100

< 100< 100< 100

8500 2 200160 2 70

< 100< 100< 100

Mn-544715 Co-60 24%4

K-40 48 2 24

Sr-90 0.58 k 0.21

(1)(2)(3)(4)(6)(5)

(7)

(8)

Gamma emltters are only reported when acUvlUes exceed the MDC's: typical MDC values are Iound In Table 1-18.

0

TABLEI-2

GROSS ALPHA, GROSS BETA, TRITIUM,AND GAMMA'PECTROSCOPIC ANALYSES OF SURFACE WATER


Results ln pCI/liter 2 2S

Page 2 of 5

LOCATION COLLECTIONDATE GR-ALPHA GR-BETA TRITIUM OTHER ACTIVHT COMMENTS

1D36S66S66S56S7LTAW12F112G212H1

1D36S66S56sjLTAW12F112G212H1

1D36S66S56S7LTAW12F112G212H1

04/11/9404/04/9404/04/94-05/02/9404/11/94-05/02/9404/04/94-05/02/9404/ll/9404/ll/9404/ll/9404/04/94-05/02/94

05/16/9405/02/94-06/06/9405/09/94-06/06/9405/02/94-06/06/9405/16/9405/16/9405/16/9405/02/94-06/06/94

06/13/9406/06/94-07/11/9406/13/94-07/11/9406/06/94-06/27/9406/13/9406/13/9406/13/9406/06/94-07/11/94

1.0 2 0.51.3 2 0.8

< 0.9<1<2

< 0.70.5 2 0.41.3 R 0.6

< 0.9

<1<1<1<2<1<1<1<1

<1< 0.9< 0.9<2< I< I<1

< 0.8

3.3 i 0.65.7 2 0.72.7 i 0.83.3 i 0.9132 2

3.2 2 0.72.7 2 0.62.7 2 0.62.3 2 0.8

2.8 2 0.92.3 2 1.03.0 2 1.0Ilk 1

3.8 R 1.08.4 2 1.32.9 i 0.92.7 2 1.0

3.3 R 0.73.4 k 0.43.3 2 0.9ilk 23.6 i 0.73.5 2 0.73.8 2 0.73.5 k 0.9

< 100< 100< 80< 100

11000 i 1000110 2 60

< 100< 100< 100

< 100< 100

130 k 7012000 2 1000

< 100< 100< 100< 100

< 100< 100< 100

5000 t 200110 2 70

< 100110 2 60

< 100

K-40 98 2 33

K-4038 2 19

(9)

(10)

Gamma emltters are only reported when acttvtUes exceed the MDC's: typical MDC values are found In Table 1-18.

TABLEI-2

GROSS ALPHA, GROSS BETA, TRITIUM,AND GAMMA'PECTROSCOPIC ANALYSES OF SURFACE WATER


Results In pCI/liter 2 2S

Page 3 of 5

LOCATION

1D36866S66S66S56876S76S7LTAW12F112G212Hl

COLLECTIONDATE GR-ALPHA

<2<2collected< 1

<1<2<2<2<2<2<2< 1

07/ll/9407/05/9407/11/94-07/25/94 Not07/11/94-08/08/9407/18/94-08/08/9407/05/9407/05/94-07/11/9407/11/94-07/25/9407/11/9407/ll/9407/11/9407/11/94-08/08/94

GR-BETA

4.1 2 0.93.7 2 0.9

3.2 R 0.95.4 2 1.0132 2Ilk 2

9.8 i 1.74.4 i 1.14.6 i 1.04.3 k 1.03.7 R 0.9

TRITIUM

< 70< 100

< 100280 R 70

< 100230 R 90

1500 2 100< 100< 70< 100< 100

OTHER ACTIVITY

K-40 49.2R 27.4

COMMENTS

1D36S66S56S76S7LTAW12F112G212H1

1D36S66S56S7LTAW12Fl12G212H1

08/15/9408/08/94-09/06/9408/15/94-09/06/9408/01/94-08/08/9408/08/94-09/06/9408/15/9408/15/9408/15/9408/08/94-09/06/94

09/12/9409/06/94-10/03/9409/12/94-10/03/9409/06/94-10/03/9409/12/9409/12/9409/12/9409/06/94-10/03/94

<1<1<1<2<2<1

< 0.8< 0.9< 1

<1<2<2<2<1<1<1<1

4.5k 1.04.7 2 1.04.5 i 1.012% 211% 2

5.6 2 1.13.0 2 0.93.7 i 1.03.9 2 0.9

4.7k 1.14.4 i 1.04.5 k 1.0152 2

4.6 2 1.13.2 i 1.04.0 i 1.13.9 k 1.0

< 100< 100< 100

24000 R 1000600 k 100

< 100< 100< 100< 100

< 100< 100< 100

1200 2 100< 100< 100< 100< 100

K-40 98 2 30

(12)(13)

Gamma emltters are only reported when acttvtoes exceed the MDC's: typical MDC values are found tn Table I-18.

TABLEI-2

GROSS ALPHA, GROSS BETA, TRITIUM,AND GAMh9V SPECTROSCOPIC ANALYSESOF SURFACE WATER

SUSQUEHANNA STEAM ELECTRIC Sl'ATION - 1994

Results in pCI/liter 2 2S

Page 4 of 5


1D35896S66366356856S7687687LTAW12F112G212Hl

1D36S6685687LTAW12F112G212Hl

1D36366856S7LTAW12F112G212H1

10/ll/9410/10/9410/03/94-11/07/9410/17/9410/10/9410/ll/94-11/07/9410/03/94-10/09/9410/17/9410/17/94-11/07/9410/11/9410/11/9410/ll/9410/03/94-11/07/94

ll/14/9411/07/94-12/05/9411/14/94-12/05/9411/07/94-12/05/94ll/14/94ll/14/94ll/14/9411/07/94-12/05/94

12/13/9412/05/94-01/03/9512/12/94-01/03/9512/05/94-01/03/9512/12/9412/12/9412/13/9412/05/94-01/03/95

< 2<1<2<1<1<2<2<2<2<2<2<2<2

<2<1<1<2<2<2<2<1

<1<1<1

3.4 2 1.4<2<1<1<1

3.1 k 1.09.5 t 1.32.5 2 0.93.8 2 1.13.3 2 1.03.5 k 0.9

.8.9 R 1.1132 212% 1

3.7 i 1.02.3 i 0.94.3i 1.12.9 2 0.9

3.4 2 0.85.7 1 1.13.8 2 1.0152 1

4.6 2 1.04.1 i 0.93.2 i 0.84.4 2 1.0

2.3 R 0.82.6 2 0.92.4 2 0.9152 2

4.2 2 1.02.9 2 0.82.5 i 0.81.8 2 0.9

< 100< 100< 100< 100

130 A 60< 100

690 2 90< 100

1600 k 100< 100< 100< 100< 100

< 100< 100< 100

3800 k 200< 100< 100< 100< 100

< 100< 100

240 2 807200 2 200

190 k 70< 100< 100< 100

(14)

(14)

I

Col

Gamma emltters are only reported when acttvt ties exceed the MDC's: typical MDC values are found tn Table 1-18.

CorOCme ts

TABLEI-2

GROSS ALPHA, GROSS BETA. TRITIUM,AND GAMED SPECTROSCOPIC ANALYSES OF SURFACE WATER


Page S of 5

3.

4,

5.6.

7.

8.9.

10.

12.

13.

14.

Onlyonegallonwasobservedinthe6S6collectlontankon January10,1994. Thetrimvalvewasfoundciosed. Grabsampleswerecollected. The 6S6 collection tank was found overflowing on January 17, 24, and 31, 1994 and grab samples were collected on each ofthese dates because of questionable sample representativeness for the intendedThe ACS at 6S6 was Inoperative for a brief period on February 4, 1894 to permit routine cleaning and flushing of the ACS to beperformed.No sample was obtainable for 6S5 on January 17, 1994 due to hazardous river conditions. Samples were collected from shore, insteadof by boat as Is normal, on January 10, 24, and 31 and February 7, 1994 because of safety concerns due to the river conditions.No water was flowing through the ACS at 6S7 on January 10, 1004. A grab sample was collected because of questionable samplerepresentatlveness for the intended sampling period. Required analysis sensitivities were not attained for barium-140 and lanthanum-140 when the January 10 grab sample was analyzed because of the unusually long period between sample collection and analysis onFebruary 16, 1994. The sample was not shipped until February 8, 1994. The delay between collection and analysis was sufficiently long,considering half-lives of these radionuclides to preclude achieving their required analysis sensitivities.The ACS at 6S7 was observed to be sampling irregularly from January 10 through Januaty 17.The ACS at 6S7 was Inoperative on January 24, 1994 and no water could be obtained at this location for a grab sample. The collectiontank at 6S7 was observed to be overflowing on January 31, 1994. A grab sample was collected because of questionable samplerepresentativeness for the Intended sampling period.The ACS at 6S6 was not sampling adequately on February 28 and March 7, 1994. Grab samples were collected on these dates becauseof questionable sample representativeness for the intended sampling period. These grabs were composited and analyzed as onesample.

— No sample could be obtained at 12G2 on February 14, 1984 because the river was frozen.The collection tank at 6S6 was observed to be overflowing on April4, 1994. A grab sample was collected because of questionablesample representatlveness for the Intended sampling period.The ACS at 6S6 was not operating on May 3, 1994 to allow for maintenance to be performed. Only124 ounces, instead of one gallon,of water from the first week of the sampling period May 2 through June 6 were composited with one gallon amounts from the other weeksof the sampling period. On May 24, 1994, it was observed that no water was flowing through the ACS.The collection tank at 6S7 was observed to be overflowing on July 5, 1994. A grab sample was collected because of questionablesample representativeness for the intended sampling period.The ACS at 6S7 was not collecting water most of the time from July 28 through August 1, 1994 and August 3 through August 5, 1994because of sedilment blocking the sampling line. Grab samples were collected on August 1 and August 8, 1994, composlted andanalyzed as one sample.No water was observed to be being collected by the ACS at 6S7 on August 18, 1994. The amount ofwater in the collection tank also wasobserved to be less than expected. The water was collected and composited with other water collected for the period August 8 throughSeptember 6, 1894, neyerlheless.

The ACS at 6S7 was tumed off for routine preventative maintenance on October 9, 1994. The ACS remained inoperative from October9 through October 14, 1994. Because no water could be collected at 6S7 on October 10, 1994, alternative sampling was performed at6S5 by collecting a grab sample there. The ACS was restarted on October 14, 1994 but did not collect any water through October 17,1984. On October 17, 1994, the ACS's valves were readjusted and a grab sample was collected.

TABLE I-3

IODINE-131 ANALYSES OF SURFACE WATER

SUSQUEHANNA Sl'EAM ELECTRIC STATION - 1994

Results In pCI/ltter 2 2S

Page 1 ot7

LOCATION


1D36866S66866S56S56S76S76S7LTAW12F112G212H112H1

1D36866S66S66S56S56856S7

COLLECTION DATE

01/11/9401/10/94-01/17/9401/17/9401/24/9401/24/9401/10/94-01/17/9401/17/94-01/22/94Ol/10/9401/10/9401/10/9401/10/94-01/25/94

02/14/9401/31/9401/31/94-02/07/9402/07/94-02/22/9401/31/94-02/07/9402/14/94-02/22/9401/31/9401/31/94-02/07/9402/07/94-02/22/9402/14/9402/14/9402/14/9401/25/94-02/07/9402/07/94-02/22/94

03/14/9402/28/94-03/07/9403/07/94-03/21/9403/21/94-03/28/9402/28/94-03/07/9403/14/94-03/21/9403/28/94-04/04/9402/22/94-03/07/94

I-131

< 0.06Sample not collected

0.34 2 0.120.28 k 0.070.32 R 0.070.72 2 0.180.76 A 0.11

< 0.07< 0.06< 0.07

0.52 2 0.12

0.43 2 0.06< 0.2< 0.2< 0.2

0.32 2 0.110.47 k 0.140.79 2 0.170.53 R 0.120.65 2 0.15

< 0.070.46 k 0.06

Sample not collected0.23 2 0.120.29 2 0.13

< 0.06< O.l< 0.2< 0.2< O.l< 0.2< 0.1

0.28 2 0.09

COMMENTS

(1)(1)(2)(3)(4)

(1)(5)

.(6)

(7)

TABLEI-3




Page2of7

LOCATION

6S76S7LTAW12F112G212H112H112H1

1D36866S66S66S56S56S76S7LTAW12F112G212H112H1


-12H1

COLLECTIONDATE

03/07/94-03/21/9403/21/94-04/04/9403/14/9403/14/9403/14/9402/22/94-03/07/9403/07/94-03/21/9403/21/94-04/04/94

04/ll/9404/04/9404/04/94-04/18/9404/18/94-05/02/9404/11/94-04/18/9404/25/94-05/02/9404/04/94-04/18/9404/18/94-05/02/9404/ll/9404/11/9404/ll/9404/04/94-04/18/9404/18/94-05/02/94

05/16/9405/02/94-05/16/9405/16/94-05/31/9405/09/94-05/16/9405/24/94-05/31/9405/02/94-05/16/9405/16/94-05/31/9405/16/9405/16/9405/16/9405/02/94-05/16/9405/16/94-05/31/94

I-131

< 0.2< 0.2< 0.05< 0.08< 0.06< 0.2< 0.1< 0.2

< 0.08< O.l< 0.2< 0.1< 0.1< O.l< 0.2< 0.1< 0.06< 0.06< 0.07< 0.1< 0.2

< 0.06< 0.2< 0.1< 0.1< O.l< 0.2< O.l< 0.06< 0.06< 0.06< 0.2< 0.2

COMMENTS

(8)

(9)(10)

TABLEI-S



Results In pCI/liter k 2S

Pege S of7

LOCATION COLLECTION DATE I-131 COMMENTS

1D36866866S66856S56S76S7LTAW12Fl12G212H112H112H1

1D36866366866S56S56S56S76876376S7LTAW12F112G212HI12H1

06/13/9405/31/94-06/13/9406/13/94-06/27/9406/27/94-07/11/9406/06/94-06/13/9406/20/94-06/27/9405/31/94-06/13/9406/13/94-06/27/9406/13/9406/13/9406/13/9405/31/94-06/13/9406/13/94-06/27/9406/27/94-07/11/94

07/11/9407/05/9407/11/94-07/25/9407/25/94-08/08/9407/05/94-07/11/9407/18/94-07/25/9408/01/94-08/08/9407/05/9407/11/94-07/25/9407/05/94-07/11/9408/01/94-08/08/9407/ll'/9407/ll/9407/11/9407/11/94-07/25/9407/25/94-08/08/94

< 0.09< 0.1< 0.1

0.21 k 0.10< 0.1< 0.1< 0.2< 0.2< 0.06< 0.08

0.09 k 0.04< 0.2< O.l< 0.2

0.50 k 0.06< 0.2< 0.1< 0.2

0.36 2 0.10< 0.09

0.30 k 0.07< 0.1

0.45 2 0.100.33 2 0.070.50 2 0.08

< 0.080.60 2 0.060.55 2 0.06

< 0.2< 0.2

(12)

TABLEI-3


SUSQUEHANNA STEAM ELECTRIC SI'ATION - 1994

Results in pCI/liter k 2S

Page 4 of 7

LOCATION COLLECTIONDATE I-131 COMMENTS

ID36S66S66S56S56S76S7LTAW12F112G212H112H1

1D36S66S66S56S56S76S7LTAW12F112G212H112Hl

08/15/9408/08/94-08/22/9408/22/94-09/06/9408/15/94-08/22/9408/29/94-09/06/9408/08/94-08/22/9408/22/94-09/06/9408/15/9408/15/9408/15/9408/08/94-08/22/9408/22/94-09/06/94

09/12/9409/06/94-09/19/9409/19/94-10/03/9409/12/94-09/19/9409/26/94-10/03/9409/06/94-09/19/9409/19/94-10/03/9409/12/9409/12/9409/12/9409/06/94-09/19/9409/19/94-10/03/94

0.23 2 0.050.13 2 0.09

< 0.2< O.l< O.l

0.74 i 0.110.47 2 0.11

< 0.070.34 R 0.060.43 2 0.06

< 0.2< 0.1

< 0.060.27 2 0.09

< 1.00.43 k 0.090.27 2 0.090.55 k 0.11

0.4 2 0.2< 0.06< 0.08< 0.08< 0.2< 0.1

(13)

I

CO

TABLEI-S




Page 6 of 7

LOCATION

1D35S96S66866S66S56S56S5

~ 6876S76S7LTAW12F112G212H112H I

1D36S66S66866856S56S76S76S7LTAW12F112G212H112H112H I

COLLECTIONDATE

10/11/9410/10/9410/17/9410/03/94-10/17/9410/17/94-10/31/9410/10/9410/ll/94-10/17/9410/24/94-10/31/9410/03/94-10/09/9410/17/9410/17/94-10/31/9410/11/9410/11/9410/ll/9410/03/94-10/17/9410/17/94-10/31/94

11/14/9410/31/94-11/14/9411/14/94-11/28/9411/28/94-12/12/9411/07/94-11/14/9411/21/94-11/28/9410/31/94-11/14/9411/14/94-11/28/9411/28/94-12/12/9411/14/94ll/14/9411/14/9410/31/94-11/14/9411/14/94-11/28/9411/28/94-12/12/94

I-131

0.27 k 0.060.36 4 0. 1 1

0.25 R 0.07< 0.2< 0.2

0.46 k 0.120.33 R 0.08

< 0.1< 0.2

0.88 2 0.090.65 2 0.10

< 0.070.36 2 0.060.30 R 0.05

< 0.2< 0.2

< 0.6< 0.2< 0.2< 0.2< O.l< O.l

0.20 2 0.13< 0.1< 0.1< 0.07< 0.07< 0.07< 0.2< 0.2< 0.2

COMMENTS

(14)

(14)(14)

TABLEI-S

IODINE-1S1 ANALYSES OF SURFACE WATER


Results In pCI/liter i 2S

Page Bof7

LOCATION

1D36S66S66S56S56S56S76sj

. LTAW12FI12G212H112H1

COLLECTIONDATE

12/13/9412/12/94-12/27/9412/27/94-01/09/9512/05/94-12/12/9412/19/94-12/27/9401/03/95-01/09/9512/12/94-12/27/9412/27/94-01/09/9512/12/9412/12/9412/13/9412/12/94-12/27/9412/27/94-01/09/95

I-131

< 0.2< 0.2< 0.1< 0.1< 0.2< 0.08< 0.2< 0.2< 0.08< 0.08< 0.2< 0.2< O.l

COMMENTS

TABLEI-3



Page 7 of 7

Comments

3.4.

6.7.

8.

9.

10.11.

12.

13.

14.

The 6SB collection tank was found overflowing and a grab sample was collected because of questionable sample representatlveness forthe Intended sampling period.No sample was obtainable for 6S5 on January 17, 1994 due to hazardous river conditions. Samples were collected from shore, insteadof by boat as Is normal, on January 24, 1994 because of safety concerns due to the river conditions.The ACS at BS7 was observed to be sampling irregularly from January 10 through January 17.Water was collected from this location on January 21 and January 24, 1994. The ACS at 6S7 was inoperative on January 24, 1994 andno water could be obtained at this location for a grab sample. The end of the sample collcetion period was uncertain.The ACS at 6SB was inoperative for a brief period on February 4, 1994 to permit routine cleaning and flushing of the ACS to beperformed.No sample could be obtained at 12G2 on February 14, 1994 because the river was frozen.The ACS at 6SB was not sampling adequately on February 28 and March 7, 1994. Grab samples were collected on these dates becauseof questionable sample representativeness for the Intended sampling period. These grabs were composited and analyzed as onesample.The collection tank at 6S6 was observed to be overflowing on April4, 1994. A grab sample was collected because of questionablesample representativeness for the intended sampling period.The ACS at 6S6 was not operating on May 3, 1994 to allow for maintenance to be performed. Only 1940 ml of water from the first week,May 2 through June 6, of the composiiting period were composited with 2000 ml from the second week of the sampling period.On May 24, 1994, it was observed that no water was flowing through the ACS at location 6S6.The collection tank at 6S7 was observed to be overflowing on July 5, 1994. A grab sample was collected because of questionablesample representativeness for the intended sampling period.The ACS at 6S7 was not collecting water most of the time from July 28 through August 1, 1994 and August 3 through August 5, 1994because of sedIIment blocking the sampling line. Grab samples were collected on August 1 and August 8, 1994, composited andanalyzed as one sample.No water was observed to be being collected by the ACS at 6S7 on August 18, 1994. The amount of water fn the collection tank also wasobserved to be less than expected. The valves were adjusted and the ACS continued to sample. The water for the period August 15through August 22, 1994 was collected and composited with other water collected for the period August 8 through August 22, 1994,nevertheless.The ACS at 6S7 was tumed off for routine preventative maintenance on October 9, 1994. The ACS remained Inoperative from October

- 9 through October14, 1994. Because no water could be collected at BS7 on October 10, 1994, alternative sampling was performed at6S5 by collecting a grab sample there. The ACS was restarted on October 14, 1994 but did not collect any water through October 17,1994. On October 17, 1994, the ACS's valves were readjusted and a grab sample was collected.

TABLEI-4

GROSS ALPHA, GROSS BETA, TRITIUM,IODINE-181 AND GAMMA'PECTROSCOPIC ANALYSES OF DRINKINGWATER

SUSQUEHANNA SIAM ELECTRIC SI'ATION - 1994

Results ln pCI/liter k 2S

Page I of4


12H2 R

12H2 R

12H2 R12H2 R

12H2 T12H2 T12H2 T

01/03/94-01/19/9401/10/94-01/19/9401/25/9401/25/94-02/07/9401/03/94-02/07/9401/10/94-01/25/9401/25/94-02/07/94

<1<1< 1

8.8 i 1.4

3.6 R 0.92.6 2 1.1

2.4 2 1.2

< 100

< 100

< 100

< 100

1-131

1-131

I-131

1-131

1-131

0.44 2 0.150.29 2 0.060.33 2 0.13

0.52 k 0.120.31 k 0.16

(2)

(3)

12H2 R12H2 R12H2 T

02/07/94-02/14/9402/28/9402/07/94-03/07/94

<1<1<2

2.6 2 0.92.1 k 0.82.6 A 0.9

< 100< 100< 100

(4)(5)

12H2 R

12H2 R

12H2 R12H2 T

03/01/94-03/07/9403/07/94-03/14/9403/21/94-04/04/9403/07/94-04/04/94

<1< 0.9<2

< 0.9

2.5R 0.92.02 0.84.8 2 1.0

5.3 2 0.9

< 100

< 100< 100< 100

(6)(7)

12H2 R12H2 R

12H2 T

04/04/94-04/11/94 < 0.804/18/94-05/02/94 1.2 R 0.904/04/94-05/02/94 1.4 2 1.0

2.1 2 0.73.2 2 0.92.7 R 0.8

< 100< 100< 100

(8)

12H2 R

12H2 T

12H2 R12H2 T

05/09/94-06/06/9405/02/94-06/06/94

06/06/94-07/11/9406/06/94-07/11/94

< 0.9< 0.9

3.2 2 0.92.5 2 0.8

3.62 0.93.2i 0.9

< 100< 100

< 100< 100

(9)

(Gl Grab sample~ Gamma emttters are only reported when actlvltles exceed the MDCs: typical MDC values are found ln Table I-18.

I

TABLEI-4

GROSS ALPHA, GROSS BETA, TRITIUM,IODINF 131 AND GAMMA~SPECTROSCOPIC ANALYSES OF DRINIUNGWATER



Page 2 of4


12H2 R

12H2 R12H2 T

07/18/94-07/25/94 1.0 2 0.907/25/94-08/08/94 < 1

07/11/94-08/08/94 < 1

3.9 2 1.0

4.4 2 1.0

3.5 i 0.9

< 100

< 100

< 100

(10)

12H2 R12H2 T12H2 R

08/15/9408/08/94-09/06/9408/15/94-08/29/94

<2<2

3.4 2 0.93.7 2 0.94.2 R 0.9

< 100

< 100

< 100

I-131 0.53 2 0.11

12H2 R

12H2 R12H2 R12H2 R12H2 R12H2 T

09/06/9409/12/9409/12/94-10/03/9409/12/94-09/19/9409/19/94-10/03/9409/06/94-10/03/94

< I2.0 % 1.3

< I

<2

3.7 i 0.83.7 2 1.0

4.0 k 1.0

3.8 2 1.0

< 100< 100< 100

< 100

I-1311-131

0.10 k 0.060.29 k 0.12

(12)(13)

12H2 R12H2 R12H2 T

10/03/94-10/17/9410/03/94-11/07/9410/03/94-11/07/94

<2<2

3.2 i 0.93.3 2 0.9

120 R 70< 100

1-131 0.24 k 0.10

12H2 T12H2 R12H2 R12H2 R

11/07/94-12/05/9411/07/94-11/21/9411/28/94-12/05/9411/28/94

<1<1<1<1

7.1 k 1.24.7 2 1.0

4.6 i 1.0

5.0 2 1.1

< 100< 100< 100< 100 (14)

IG) Grab sampleGamma emltters are only reported when actlvltles exceed the MDC's: typical MDC values are found ln Table I-IB.

TABLEI-4

GROSS ALPHA, GROSS BETA, TRITIUM,IODINE-181 AND GAMMA'PECTROSCOPIC ANALYSES OF DRINKINGWATER



Page S of4


12H2 R12H2 R12H2 R12H2 T

12/19/9412/05/94-12/12/9412/20/94-01/03/9512/05/94-01/03/95

< 0.08< 0.07

<2<2

2.02 0.82.1 k 0.81.8 i 0.91.5 k 0.9

< 100< 100

< 100< 100

(15)(15)

(G) Grab sample~ Gamma em! tters are only reported when actlvltles exceed the MDC's: typical MDCvalues are found ln Table 1-18.

Comments

TABLEI-4

GROSS ALPHA. GROSS BETA. TRITIUM,IODINF 131 AND GAMMA~SPECTROSCOPIC ANALYSES OF DRINKINGWATER


Page 4 of4

2.3.4,

5.6.7.

9.

10.

12.

13.

14.

15.

Weekly retrieval of water from 12H2R was delayed from January 17 to Januaty 19, 1994 due to a snowstorm and resulting hazaIdousroad conditions. The pump supplying water to the ACS stopped the morning of January 19, 1994 prior to retrieving the sample.The pump supplying water to the ACS at 12H2R was reprimed and started on January 25, 1994. A grab sample was collected.Danville personnel did not collect the daily grab for 12H2T on January 18, 1994.The pump at 12H2R was found inoperative on February 22, 1994. A grab could not be obtained manually using the ACS nor could agrab be collected from the river because of hazardous river conditions and snow.The pump at 12H2R continued to be Inoperative on February 28, 1994. It was started on March 1, 1994.The volume of water in the collection tank at 12H2R was less than expected on March 14, 1994.The collection tank at 12H2R was observed to be overflowing on March 21, 1994. A grab sample was collected on this date because ofquestionable sample representativeness for the intended sampling period. Inadequate volumes ofwater were found ln the collection tankon March 28 and April4, 1994. Grab samples were collected on each of these dates. The grab samples for March 21 and 28 and April4were composited as one sample and the composite sample was analyzed.The valve permitting water to flow through the ACS at 12H2R was found closed on April 18, 1994: Insuflicient water was present in thecollection tank for the desired analyses. A grab sample was collected on April 18, 1994. The ACS was disassembled for maintenance onApril25, 1994 and a grab sample was collected. On May 2, 1994, an Insufficient amount of water was found ln the ACS's collection tankand a grab sample was collected at that time. The grabs on April 18 and 25 and May 2 were composited and the composite sample wasanalyzed.The collection tank at the 12H2R ACS was observed to be overflowing on May 9, 16, 23, and 31 and June 6, 1994. Grab samples werecollected because of questionable sample representativeness for the Intended sampling period. The grabs were all composited and thecomposite sample was analyzed.The collection tank at the 12H2R ACS was observed to be overflowing on July 18, 1994. The water in the collection tank was observedto be muddy. An additional sample line had been installed to the downrlver well at the facilityearlier In the week. In addition, a poweroutagehadstoppedthepumpneartheendofintheweek. Agrabsamplewascollectedat thislocatlonon July18,1994. Nowaterwasbeing collected by the ACS on July 25, 1994. A grab sample was collected on that date. The grab samples from July 18 and 25 werecomposited and analyzed as one sample.The ACS at 12H2R was found not to be collecting water on August 15, 1994 due to sediment clogging. Water was present In thecollection tank but due to uncertainty concerning the sampling period and variability In the rate of sampling, It was considered to benonrepresentative. The ACS was backflushed and a grab sample was collected.The ACS at 12H2R was found to not be collecting water on September 6, 1994 because the sampler had left the ACS Intake attached tothe line for flushing the ACS with tapwater at the end of the previous week's collection.A grab sample was collected at the 12H2R ACS on September 12, 1994 because of questionable sample representativeness for theintended sampllfng period.The collection tank at 12H2R was observed to be overflowing on November 28, 1994. A grab sample was collected on this date becauseof questionable sample representativeness for the Intended sampling period.A PP8L construction crew cleaned the line from the sampling pump to the ACS because it was completely blocked by sediment onDecember15, 1994. A grab sample was collected from the river on December19, 1994. The ACS began sampling again on December20, 1994.

TABLEI-5

GAMMA'PECTROSCOPIC ANALYSESOF ALGAE


Results In pCI/gm (dry) 2 2S

Page 1 of 1

LOCATION COLLECTIONDATE Be-7 K-40 I-131 Cs-137 Th-228 Other

AG-3 05/07/94-06/06/94 3.86 R 1.01 10.3 R 1.5AG-4 05/07/94-06/06/94 4.01 R 1.15 8.86 i 1.59

0.17% 0.09 0.51 k 0.12Mn-54 0.24 2 0.12Co-60 0.39 2 0.15

AG-3AG-4

06/06/94-07/11/94 5.00 R 0.63 19.9 R 2.0 0.49 R 0.13 0.23 2 0.06 1.21 2 0.1206/06/94-07/11/94 5.84 A 0.73 25.3 2 2.5 0.48 2 0.14 0.18 R 0.07 1.27 R 0.13

AG-3 07/11/94-08/08/94 5.38 2 1.12 18.1 2 1.8 0.57 i 0.15 0.87 R 0.13AG-4 07/11/94-08/08/94 6.94 k 0.95 23.6 k 2.4 0.63 2 0.14 0.22 2 0.09 1.19 k 0.12

AG-3AG-4

AG-3AG-4

AG-3AG-4

08/08/94-09/12/9408/08/94-09/12/94

09/12/94-10/03/9409/12/94-10/03/94

10/03/94-11/07/9410/03/94-11/07/94

4.09 2 0.925.58 2 1.42

22.4k 2.219.4 R 2.4

6.62 2 1.43 23.6 2 2.53.36 2 1.27 28.5 k 2.9

7.452 1.15 20.1 R 2.06.01 k 1.01 19.6 k 2.0

0.54 j 0.240.20 R 0.09

0.20 k 0.12

1.10 k 0.161.30 2 0.15

0.88 k 0.121.14 k O.ll

1.25 k 0.141.60 k 0.21

Mn-54 0.35 2 0.11Co-60 0.41 2 0.12

Gamma emltters are only reported when acUvttles exceed the MDC's: typical MDC values are found tn Table 1-18.

g

TABLEI-6

GROSS BETAAND GAMMA'PECTROSCOPIC ANALYSES OF FISH


Results ln pCI/gm (wet) 2 2S

LOCATION SAMPLE TYPE COLLECTIONDATE GR-BETA K-40

2H White Sucker2H Smallmouth Bass

IND White SuckerIND Smallmouth BassIND Channel Catllsh

2H Channel Catllsh

05/31/9405/31/94

05/26/9405/27/9405/27/94

06/01/94

6.5 R 0.24.9 2 0.1

9.1 i 0.27.1 2 0.26.1 i 0.2

6.1 k 0.2

3.66 i 0.373.49 2 0.35

5.09 k 0.513.98 A 0.402.87 k 0.29

3.50 k 0.35

IND White SuckerIND Smallmouth BassIND Channel Catfish

2H White Sucker2H Smallmouth Bass2H Channel Catfish

LTAW Largemouth Bass

10/25/9410/25/9410/26/94

10/27/9410/27/9410/28/94

10/28/94

7.0 R 0.23.1 k O.l6.5 i 0.2

4.5k 0.14.4i O.l2.5i 0.1

3.6 R 0.1

4.01 k 0.404.01 k 0.403.50 2 0.35

3.67 2 0.373.65 2 0.363.81 k 0.38

3.59 2 0.36

~ Gamma emltters are only reported when acttvtttes exceed the MDC's: typical MDC values are found ln Table 1-18.

I

'V

TABLEI-7

GROSS ALPHA, GROSS BETA, AND GAMINA'PECTROSCOPIC ANALYSES OF SHORELINE AND FLOCCULATED SEDIMENT


Results ln pCI/gm (dry) 2 2S

Page 1 of 1

LOCATIONCOLLECTIONDATE GR-ALPHA GR-BETA K-40 Cs-137 Ra-226 Th-228 Be-7

2BFLOC 05/09/947BFLOC 05/09/94

9.6 2 4.111% 4

34% 327k 3

9.1 2 1.19.1 i 1.1

0.13 2 0.07 1.91 k 1.09 0.66 2 0.080.99 2 0.10

2B2F7B11C12FLTAW

05/09/9405/10/9405/09/9405/11/9405/10/9405/10/94

19% 79.2 2 4.28.1 R 4.78.62 4.8162 611% 5

43k 423k 334k 328% 335k 3382 4

13.3 k 1.37.45 2 0.7510.0 2 1.07.59 2 0.7611.4 2 1.114.4 2 1.4

0.14 2 0.050.06 2 0.030.07 t 0.03

0.07 k 0.03

1.60 2 0.861.55 R 0.471.42 R 0.551.35 2 0.391.64 2 0.531.42 2 0.44

1.27 R 0.130.99 k 0.100.90 k 0.090.65 2 0.071.15 k 0.121.17 2 0.12

0.62 2 0.33

0.59 R 0.27

2B FD3C7B FLOG

10/31/9410/31/94

122'5 45k 3IOR 5 25% 3

15.3 2 1.510.2 2 1.0 1.56 2 0.71

1.44 k 0.150.69 2 0.07

1.72 k 0.89

2B2F7B11C12FLTAW

10/31/94ll/01/9410/31/94ll/Ol/94ll/01/9411/01/94

151 6122 516% 1

9.7 2 5.1122 6132 6

44k 327k 329k 324k 326k 337k 3

14.5 R 1.59.41 2 0.9410.6 k 1.19.38 A 0.9410.2 k 1.014.2 2 1.4

0.18 k 0.04

0.11 2 0.040.06 2 0.020.06 2 0.03

2.43 R 0.832.48 2 0.681.70 E 0.611.31 R 0.391.99 2 0.481.63 R 0.47

1.06 2 O.ll0.97 2 0.100.99 k 0.100.76 k 0.080.88 k 0.091.15 k 0.12

0.61 R 0.31079% 031

1.30 R 0.29

Gamma emitters are only reported when activities exceed the MDC's: typical MDC values are found In Table I-18.

TABLEI-8

GROSS ALPHA, GROSS BETA, TRITIUM,AND GAMMA'PECTROSCOPIC ANALYSES OF GROUND WATER



Page 1 of$

LOCATION

12F32S23S5

(a)'S4

Treat4S51281

COLLECTIONDATE

Ol/10/9401/10/94

01/10/94Ol/10/94Ol/10/94

GR-ALPHA

<2< 1

<1<2<2

GR-BETA

3.5 2 1.1<1

2.3 2 0.8<1

1.7 2 1.0

TRITIUM

< 100< 100

< 100< 100< 100

OTHER ACTIV1TF

K-40 38 a 21

12F32S23S5 (a)4S4 Treat4S51281

02/14/9402/14/94

02/14/9402/14/9402/14/94

<2<1

< 1

<2<2

2.4 2 1.0<1

2.3 R 0.8<1

1.8 % 0.9

< 100< 100

( 100< 100«100 K-40 35 R 18

12F32S23S5 (a)4S4 Treat4S51281

12F32S23854S4 Treat4S51281

03/14/9403/14/94

03/14/9403/14/9403/14/94

04/ll/9404/ll/9404/ll/9404/11/9404/11/9404/ll/94

<2<1

<1<2<2

<1( 0.6

1.2 i 0.6< 0.5< 0.9<1

4.5 i 1.2<1

2.9 2 0.81.5 2 0.92.0 2 1.0

2.5 2 0.7< 0.7

2.9 R 0.62.5 2 0.6

< 0.91.0 i 0.6

< 100< 100

< 100( 100< 100

< 100< 100< 100( 100( 100< 100

12F32823S54S4 Treat4S512S1

05/16/9405/16/9405/16/9405/16/9405/16/9405/16/94

<2< 0.9< 0.5< 0.7<1<1

3.4 2 1.1<1

1.3 2 0.61.1 2 0.7<1

2.2 2 1.0

< 100< 100< 100< 100< 100( 100

Ia) Sample not available.Gamma emltters are only reported when actlvloes exceed the MDCs: typical MDC values are found ln rable I-18.

I

TABLEI-8

GROSS ALPHA. GROSS BETA, TRITIUM,AND CdLMMA'PECTROSCOPIC ANALYSES OF GROUND WATER



Page 2 oES

LOCATION COLLECTIONDATE GR-ALPHA GR-BETA TRITIUM OTHER ACTIVIST

12F32S23854S4 Treat4S51281

12F32S23854S4 Treat4851281

12F32823854S4 Treat4851281

12F32823S54S4 Treat48512sl

12F32823S54S4 Treat4851281

06/13/9406/13/9406/13/9406/13/9406/13/9406/13/94

07/11/9407/ll/9407/ll/94

- 07/ll/9407/11/9407/11/94

08/15/9408/15/9408/15/9408/15/9408/15/9408/15/94

09/12/9409/12/9409/12/9409/12/9409/12/9409/12/94

10/11/9410/11/9410/11/9410/11/9410/11/9410/ll/94

<2<1< 0.7< 0.9<1<2

<2<2< 0.9<1<2<2

< I< 0.7< 0.5< 0.9<I<1

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

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

<2<2

1.2 R 0.71.7 R 1.0<2

2.2 k 1.4

2.0 R 1.21.8 i 1.01.3 2 0.81.5 k 0.9<I<2

2.1 2 0.9<I

2.6 2 0.72.8 i 0.92.5 E 1.01.3 2 0.9

3.8 k 1.11.5 i 0.71.5 k 0.72.1 2 0.8<I

2.2 2 0.9

2.1 k 1.0< 1

1.3 k 0.76.2 k 1.1<I

1.5 R 1.0

< 100< 100

100 R 60< 100< 100< 100

< 100< 100< 100< 100< 100< 100

< 100< 100< 100< 100< 100< 100

< 100< 100< 100< 100< 100< 100

< 100< 100< 100< 100< 100< 100

K-40 47 2 23

K-40 57 K 26

Gamma emltters are only reported when acttvtttes exceed the MDC's: typfcal MDC values are found In Table 22.

- ~

TABLEI-S

GROSS ALPHA, GROSS BETA, TRITIUM,AND GAMMA~SPECTROSCOPIC ANALYSES OF GROUND WATER



Page S ofS

LOCATION COLLECTIONDATE GR-ALPHA GR-BETA TRITIUM OTHER ACTIVHT

12F32S23S5 (a)4S4 Treat4851281

11/14/94ll/14/94

ll/14/9411/14/94ll/14/94

<2< 1

<1<2<2

2.3 2 1.01.2 2 0.8

2.1 2 0.92.8 k 1.0-<1

< 100< 100

< 100< 100< 100

K-40 51.8 R 24.8

12F32S23S5 (a)4S4 Treat48512S1

12/12/9412/12/94

12/12/9412/12/9412/12/94

<2< I

<2<2<2

2.9 R 1.01.1 k 0.7

3.0 2 1.01.8 i 1.01.4 2 0.9

< 100< 100

< 100< 100< 100

Gamma emltters are only reported when acttvlttes exceed the MDC's: typical MDC values are found ln Table 22.I

TABLEI-9

GROSS BETAANALYSES OF AIRPARTICULATEFILTERS


Results In E-03 pCI/Cu.M. 2 2S

Page I ofS

COILKCTIONMONTH DATE I)) 7QX 12Q1 382 1281 9B1 1D2 8D1 12E1

JUN

01/05-01/1101/11-01/1901/19-01/2701/27-02/02

02/02-02/0902/09-02/1602/16-02/2202/22-03/02

03/02-03/0803/08-03/1603/16-03/2303/23-03/29

03/29-04/0604/06-04/1304/13-04/1904/19-04/2704/27-05/04

05/04-05/1105/11-05/1805/18-05/2505/25-06/01

06/01-06/0806/08-06/1506/15-06/2206/22-06/28

15k 216% 222k 213k 2

21t 217k 221k 214% 2

16% 213% 211% 2

9.5 2 1.8

16% 2llf 214 t 2132 2

9.3 t 1.4

13% 29.8 t 1.611% 214% 2

8.6 A 1.613% 2182 213% 2

14k 2191228k 215% 2

22k 217% 1

24k 21322

182 217k 212% 211% 2

19k 214% 2132215k 212% 2

132 214% 2

8.4t 1.316k 2

9.5R 1.913k 218% 2162 2

16k 223t 229k 216% 2

251 2182 223k 217% 2

15k 215% 211 i 212k 2-

16% 214% 212 t 2I3)16% 1llt 2

12 t 2[4)8.1 2 1.612% 2122 2

8.8 S 1.614% 2202 212% 2

161219%227%216k 2

22t 2192225k 215k 2

17t214 X 2I2)12% 213%2

14% 214% 2llk 21912

9.4k 1.5

15 a 2I4)9.4i 1.511% 213% 2

9.8 t 1.6111 219% 214% 2

15% 221% 226k 2142 2

222 21St 222k 2142 2

17% 2151 2112 210% 2

15K 216% 211% 2

-16% 210% 2

14% 210% 211 t 213% 2

8.8 t 1.611 t 219% 213% 2

16% 220% 227k 214% 2

19% 217% 224t 213% 2

18% 2131 212% 2

9.5f 1.6

16% 214% 214% 217% 2

9.6R 1.6

13%29.8R 1.711% 214% 2

8.1 i 1.713% 218% 212% 2

16k 221% 228k 216% 2

21% 220% 224 t 214k 2

18k 215t 212% 212k 2

16% 215% 211% 216k 2

9.4 t 1.6

15% 2I4)11% 213t 215% 2

8.5 t,1.611 k 219% 213k 2

16k 223 i 227k 2152 2

24k 221t225k 215% 2

18% 213% 212% 213% 2

15% 213% 2llk 219k 2

9.7k 1.6

15% 211% 211% 2132 2

9.1 I 1.611 i 218% 214% 2

16% 221k 224% 213% 2

20% 219% 222k 215% 2

17% 215% 212% 210% 2

13% 213% 311% 216% 2llt 2

12% 2lit 212% 213% 2

8.8 t 1.714% 218% 2141 2

17% 225k 226t 213% 2

23k 219% 226k 218% 2

19% 216k 212% 212% 2

14% 214% 212% 220% 28.4 t 1.7

12% 29.5 N 1.4 ~

13% 214% 2

ll t 211 t 219k 215% 2

TABLEI-9

GROSS BETAANALYSES OF AIRPARTICULATEFILTERS


Results In E-03 pCI/Cu.M. k 2S

Page 2 ofS

COLLECTIONMONTH DATE 7G1 12Gl 382 1281

15841386 9Bl 787

3D11083 12E1

JUL

AUG

SEP

NOV

DEC

06/28-07/0607/06-07/1307/13-07/2007/20-07/2707/27-08/03

08/03-08/1008/10-08/1708/17-08/2308/23-08/3108/31-09/07

09/07-09/1409/14-09/2109/21-09/2709/27-10/05

10/05-10/1210/12-10/1910/19-10/2610/26-11/02

11/02-11/0911/09-11/1511/15-11/2111/21-11/2911/29-12/07

12/07-12/1412/14-12/2012/20-12/2812/28-01/05

14% 2152 222k 213% 216% 2

13% 215% 2141 219k 2152 2

212 248k I.lm8.4 i 1.68.4 i 1.3

15% 220k 2182 215% 2

22k 222k 217% 213% 1

23k 2

15% 214k 222k 2142 2

142 2152 222k 216% 2172 2

14k 220% 2lit 219% 214% 2

21% 229k 2112 2152 2

142 219%225k 222k 2

202 223k 220% 2142 226k 2

13K 2182 226k 219% 2

132 1

151 223k 215% 220% 2

15% 215% 2122 220% 213% 2

192 220% 29.8 2 1.7112 1

16% 220% 2202 217% 2

20% 221 k 263)162 215% 225k 2

152 2162 224k 220% 2

112 1

142 222k 213% 219 2 2{e)

132 215% 213k 219% 214% 2

182 226k 2112 212% I

16% 2192 2212 219% 2

19 R 2(12)24k 2162 216% 225k 2

162 2172 224k 218X 2

122 1

15% 223k 2142 216% 2

11% 2„152 211% 2182 213% 2

20% 222k 28.5 i 1.711% 1

132 219% 2191 2172 2

192 223k 216% 215% 222k 2

141 216% 225k 219% 2

13 k 213% 222k 2152 2l7% 2

13%2172 2lit220% 217% 2

24k 224k 28.7% 1.712% 1

152 220 2 2(s)22 R 2[9)18 k 2{10)

22k 222k 216k 2152 226k 2

14% 217% 227k 217% 2

14% 215% 222k 214k 218% 2

12% 215K 2lit 217% 212% 2

22k 223k 2102 2

9.9 2 1.5

12% 219% 222k 216% 2

21% 2202 217% 213% 1

23k 2

14% 216% 225k 221%. 2

14% 215k 2l9% 2152 217% 2

14% 217+ 2112 222k 214% 2

201 224k 2102 2102 1

14k 219% 221% 2181 2

21%224k 216% 214% I22k 2

162 2162 224% 218k 2

15% 2152 224k 215% 219% 2

12% 2162 2122 2201 214% 2

21% 2242 2llk 212% I

15% 221% 2201 218 t 2()1)

22k 223k 2182 214% 1

22k 2

162 216% 226k 220% 2

13% 1

15% 223k 2152 220% 2

14% 2162 213% 2201 214% 2

20% 224k 212% 2llk 1

182 221% 219% 219% 2

22k 223k 218% 214% 1

26k 2

161 218% 227k 219% 2

Co~rOCents

TABLE I-9

GROSS BETAANALYSESOF AIRPARTICULATEFILTERS


Page 8 ofS

2.

4.

5.6.7.

9.

10.

12.

13-

Sampling periods for some sampling locations may vary by a day or two at both the beginnings and ends of the periods from those datespresented In the this table. The periods stated were selected because they represented the sampling periods for most of the samplinglocations.Airwas sampled at location 5S4 only from March 8 through March 10, 1994 rather than the intended sampling period from March 8through March 16, 1994. Electdcal power to the sampling station was lost on March 10 and not restored until March 16, 1994. Thesampling stop date and time were determined from the elapsed time recorded on the timer box at the sampling station. Only 5,800 ft ofair were sampled. However, all required analysis sensitivities were attained.Airwas sampled at location 3S2 only from April 13 through April16, 1994 rather than the Intended sampling period from April 13 throughApril 19, 1994. Electrical power to the sampling station was lost on April 16. The sampling stop date and time were determined from theelapsed time recoiled on the timer box at the sampling station. Only 8,290 fi of air were sampled. However, all required analysissensitivities were attained.Electrical power was lost to sampling stations at locations 3S2, 5S4, and 9B1 from 0805 to 0845 on May 11, 1994. Stop dates and timeswere determined using the elapsed times obtained from the timer boxes at the stations.Sampling at locations 13SB, 10S3, and 7S7 was initiated on July 12, July 13, and July 14, respectively.Electrical power was shut off briefly to the sampling station at location 5S4 on July 29, 1994. ~

Electrical power to the sampling station at location 7G1 was lost on September14, 1994 due to a breaker trip causedby a short ln theelectrical timer box. Stop date and time were determined using the elapsed time obtained from the station's timer box. However, thistime appears to be ln error. The dry gas meter at the station indicated that 2,100 ft'fair were sampled. In spite of this small volume,Tech Spec required analysis sensitivities were attained for both the gross beta analysis of the particulate filterand the iodine-131 analysisof the charcoal caitridge. The cartridge was analyzed radiochemfcally rather than by gamma spectroscopy. The unusually high gross

. beta may be the result of deposition resulting from construction activities taking place near the air sampling station during this period.However, sampling personnel did not note that the particulate filterhad any unusual appearanceThe deposition on the air particulate filterfrom location 13S6 for the sampling period October 12 through October 19, 1994 wasobserved to be much lighter In color than is normal.The deposition on the air particulate filter from location 13SB for the sampling period October 19 through October 26, 1994 wasobsterved to be an unusual color.The deposition on the air particulate filterfrom location 13S6 for the sampling period October 2B through November 2, 1994 wasobserved to be lighter ln color than is normal.The dry gas meter reading from location 10S3 for the sampling period October 26 through November 2, 1994 was suspect. Samplevolume for the period was calculated by a flow rate times time calculation.The deposition on the air particulate filter from location 5S4 for the sampling period November 2 through November 9, 1994 was

'bserved to be lighter in color than is normal. The observation was also made that a stone pile had been dumped In the area of themonitor.Large equipment was observed to have been moving eaith and stones ln the vicinityof location 3S2 during the November 9 throughNovember 15, 1994 sampling period.

TABLEI-10

GROSS ALPHAAND GAMMA'PECTROSCOPIC ANALYSES OF COMPOSITED AIRPARTICULATEFILTERS


Results In E-03 pCI/Cu. M. k 2S

Page 1 of2

LOCATION COLLECTION DATE GR-ALPHA Be-? K-40 OTHERACTIVITY'G1

12G11D23D13S25S49B1

12E112S115S4

12/28/93-03/29/9412/28/93-03/28/9412/28/93-03/29/9412/28/93-03/29/9412/28/93-03/29/9412/28/93-03/29/9412/28/93-03/29/9412/28/93-03/28/9412/28/93-03/29/9412/28/93-03/29/94

3.6 2 0.42.6 R 0.43.8 l 0.43.4 2 0.44.2 A 0.54.1 2 0.43.5 i 0.43.6 2 0.43.3 2 0.43.2 R 0.4.

97.4 2 9.7110 2 11113 2 11126 2 13120 2 12109 2 11128 k 13117 2 12118 2 12ill2 11

22.7 k 2.7

2.78 2 1.473.22 k 1.713.63 2 1.63

7G112G11D23Dl3S25S49B1

12E112sl15S4

03/29/94-06/28/9403/28/94-06/28/9403/29/94-06/28/9403/29/94-06/28/9403/29/94-06/28/9403/29/94-06/28/9403/29/94-06/28/9403/28/94-06/27/9403/29/94-06/28/9403/29/94-06/28/94

3.3 i 0.4.2.9 2 0.33.7 2 0.52.9 R 0.43.3 k 0.42.5 2 0.53.4 2 0.42.7 i 0.43.3 k 0.43.9 k 0.5

132 2 13149 2 15144 2 14146 2 15132 t 13153 2 15133 2 13153 2 15146 2 15141 2 14

5.02 2 1.711.71 k 1.0029.1 % 3.4

7.24 k 2.57

3.46 t 1.63

Gamma emlttezs are only reported when actlvltles exceed the MDC's: typical MDC values are found In Table 1-18.I

TABLEI-10

GROSS ALPHAAND GAMMA»SPECTROSCOPIC ANALYSES OF COMPOSITED AIRPARTICULATEFILTERS

SUSQUEHANNA Sl'EAM ELECTRIC STATION - 1994

Results tn E-03 pCI/Cu. M. i2S

Page 2 of2

LOCATION COLLECTION DATE GR-ALPHA Be-7 K-40 OTHER ACTIVITY

7G112Gl1D2/7S73D1/10S3

3S25S49B1

12El12S115S4/13S6

06/28/94-09/28/9406/27/94-09/26/9407/13/94-09/28/9407/13/94-09/27/9406/28/94-09/27/9406/28/94-09/27/9406/28/94-09/27/9406/28/94-09/27/9406/28/94-09/27/9407/13/94-09/27/94

3.0 2 0.53.1 2 0.53.4 i 0.73.0 2 0.53.6 2 0.63.6 R 0.63.3 i 0.52.8 i 0.53.0 2 0.53.9 k 0.7

114 i 11112 i 11114 i 11107 i 11133 i 13116 i 12

99.2 i 9.9130 2 13122 2 12114 i 11 28.2 k 3.8

7Gl12Gl1D2/7S73D1/10S33S25S49B1

12El12S115S4/13S6

09/28/94-01/04/9409/26/94-01/03/9409/27/94-01/04/9409/27/94-01/04/9409/27/94-01/04/9409/27/94-01/04/9409/27/94-01/04/9409/27/94-01/04/9409/27/94-01/04/9409/27/94-01/04/94

1.6 i 0.31.4 k 0.21.8 i 0.31.8 R 0.31.8 R 0.31.4 2 0.21.3 2 0.22.1 R 0.31.4 i 0.21.6 R 0.3

122 i 12110 i 11124 i 12113 k 11109 k 11112 i 11104 k 10139 2 14126 i 13ill2 11

3i 2

25k 33 i 2

5k 2

~ Gamma emttters are only reported when actlvltles exceed the MDC's: typical MDC values are found in 'I@hie I-18.t

TABLE1-11

TRITIUMANALYSES OF AIRBORNE WATER VAPOR


Results In pCJ/Cu. M. 2 2S

LOCATION COLLECTION DATE H-3 COMMENTS

3S2

362SS2382362

12/29/93-01/05/94

01/05/94-01/11/9401/11/94-01/20/9401/20/94-01/27/9401/27/94-02/02/94

0.83 R 0.25

0.68 2 0.190.61 2 0.170.64 2 0.210.77 2 0.23

3623623S23S2

02/02/94-02/08/9402/08/94-02/15/9402/15/94-02/24/9402/24/94-03/02/94

0.58 R 0.190.4

0.87 2 0.291.3 2 0.3

3823823623S2362

362362SS23S2

03/02/94-03/09/9403/09/94-03/16/9403/16/94-03/23/9403/23/94-03/30/9403/30/94-04/06/94

04/06/94-04/12/9404/12/94-04/20/9404/20/94-04/27/9404/27/94-05/04/94

0.7 2 0.30.91 k 0.30

2.5 i 0.45.2 2 0.71.1 2 0.4

1.2 R 0.41.3 R 0.61.3 k 0.51.6 2 0.6

SS2382362362

05/04/94-05/10/9405/10/94-05/17/9405/17/94-05/25/9405/25/94-05/31/94

1.3 2 0.51.0 2 0.51.1 k 0.71.9 k 0.7

362SS23623623S2

05/31/94-06/07/9406/07/94-06/15/9406/15/94-06/21/9406/21/94-06/28/9406/28/94-07/06/94

1.7 2 0.723

2.4 2 1.12

TABLEI-lITRITIUMANALYSES OF AIRBORNE WATERVAPOR


Results fn pCI/Cu. M. k 2S

LOCATION COLLECTION DATE H-3 COMMENTS

3823823S2382

07/06/94-07/13/9407/13/94-07/20/9407/20/94-07/26/9407/26/94-08/03/94

382382382382382

3S2382382382

08/03/94-08/09/9408/09/94-08/16/9408/16/94-08/23/9408/23/94-08/31/9408/31/94-09/07/94

09/07/94-09/13/9409/13/94-09/20/9409/20/94-09/28/9409/28/94-10/04/94

1.9 i 0.93.0 R 1.2

21.9 k 1.0

1

1

1.6 i 1.02

1.1 2 0.6

382382382382

10/04/94-10/12/9410/12/94-10/18/9410/18/94-10/25/9410/25/94-11/01/94

2.8 i 0.61.3 k 0.52.1 R 0.71.9 2 0.5

3823823823823S2

382382382

11/01/94-11/08/9411/08/94-11/16/9411/16/94-11/23/9411/23/94-11/30/9411/30/94-12/06/94

12/06/94-12/13/9412/13/94-12/20/9412/20/94-12/28/94

2.3 R 0.6< 0.7< 0.7

1.4 i 0.31.3 2 0.4

1.1 2 0.80.7 2 0.31.3 2 0.7

TABLE1-12

GROSS ALPHA, GROSS BETA. TRITIUM,AND CdLMMA'PECTROSCOPIC ANALYSES OF PRECIPITATION



Page lof2

LOCATION COLLECTIONDATE

COMMENTS

GR-ALPHA GR-BETA TRITIUM BE-7 K-40

7G112G1

1D23D13825849B1

12E1128115S4

12/28/93-03/29/9412/28/93-03/28/9412/28/93-03/29/9412/28/93-03/29/9412/28/93-03/29/9412/28/93-03/29/9412/28/93-03/29/9412/28/93-03/28/9412/28/93-03/29/9412/28/93-03/29/94

0.44 2 0.270.63 R 0.290.96 R 0.330.42 2 0.250.87 R 0.330.33 R 0.250.95 2 0.430.56 2 0.280.39 R 0.250.78 k 0.31

5.1 2 0.63.9 2 0.54.3 k 0.52.9 X 0.53.7 2 0.53.3 2 0.53.2 i 0.84.0 k 0.53.2 R 0.53.2 % 0.5

< 100< 100< 100< 100< 100< 100< 100< 100< 100< 100

56.1 k 23.9

40.0 R 23.3

51.9 k 22.164.3 R 30.9

7G112G1

1D23D13S25S49B1

12E112S115S4

03/29/94-06/28/9403/28/94-06/27/9403/29/94-06/28/9403/29/94-06/28/9403/29/94-06/28/9403/29/94-06/27/9403/29/94-06/28/9403/28/94-06/28/9403/29/94-06/28/9403/29/94-06/28/94

< 0.50.68 k 0.47

1.2 k 0.60.99 i 0.520.73 2 0.460.55 2 0.43

< 0.50.80 t 0.48

< 0.50.99 k 0.53

4.9 i 0.84.9 i 0.86.5 i 0.96.0 2 0.95.1 i 0.84.9 i 0.84.1 i 0.85.0 R 0.85.6 A 0.86.8 2 0.9

< 100< 100< 100< 100< 100< 100< 100< 100< 100< 100

53.3 2 25.921.1 2 12.354.9 R 24.241.5 2 21.1

68.1 2 27.6

34.2 R 20.0

1D23Dl

1584

06/28/94-07/14/9406/28/94-07/13/9406/28/94-07/12/94

< 0.42.1 R 0.71.2 2 0.6

3.4 2 0.717 2 1.0

7.4 2 1.0

< 100< 100< 100

67.7 2 28.2143 2 22

53.9 * 23.0

Gamma emltters are only reported when actlvlnes exceed the MDC's: typfcal MDC values are found In Table 1-18.I

TABLE1-12

GROSS ALPHA, GROSS BETA, TRITIUM,AND GAMMA'PECTROSCOPIC ANALYSES OF PRECIPITATION



LOCATION COLLECTION DATE

COMMENTS

GR-ALPHA GR-BETA TRITIUM BE-7 K-40

7G112Gl1D2/7S73D1/10S3

3S25S49B1

12El12S1

15S4/13S6

06/28/94-09/28/9406/27/94-09/26/9407/14/94-09/28/9407/13/94-09/27/9406/28/94-09/27/9406/27/94-09/27/9406/28/94-09/28/9406/28/94-09/28/9406/28/94-09/27/9407/12/94-09/27/94

0.39 E 0.290.62 k 0.350.59 k 0.34

< 0.30.57 2 0.34

1.0 k 0.40.82 2 0.390.67 2 0.350.36 i 0.280.66 k 0.36

2.6 i 0.64.0 2 0.74.7 i 0.83.8 R 0.74.5 R 0.85.5 i 0.83.4 2 0.73.8 i 0.74.7 i 0.83.8 i,0.7

< 100< 100< 100< 100< 100< 100< 100< 100< 100< 100

36.8 2 20.5

C

52.4 R 21.9

7Gl12G11D2/7S73D1/10S3

3S25S49B1

12E112S1

15S4/13S6

09/28/94-12/28/9409/26/94-12/27/9409/28/94-12/28/9409/27/94-12/28/9409/27/94-12/27/9409/27/94-12/27/9409/28/94-12/28/9409/28/94-12/28/9409/27/94-12/28/9409/27/94-12/28/94

0.62 2 0.43< 0.4< 0.4

0.87 % 0.460.76 2 0.45

< 0.40.51 2 0.400.51 2 0.380.76 2 0.450.59 k 0.44

3.8 2 0.73.1 2 0.73.8 2 0.74.3 i 0.83.2 R 0.73.7 k 0.75.0 2 0.82.4 i 0.64.0 i 0.83.9 i 0.8

< 100< 100< 100< 100< 100

130 k 70< 100< 100< 100

200 2 70

~ Gamma emltters are only reported when actlvlUes exceed the MDC's: typical MDC values are found ln Table 1-18.I ~'I

TABLEI-ISIODINE-131, STRONTIUM-90, AND GAMMA'PECTROSCOPIC ANALYSES OF MILK


Results ln pCl/liter k 2S

Page I of4

LOCATION COLLECTIONDATE K-40 Sr-90 OTHER ACTIVITY

10G16C1

10D110D310D412B313E314B1

Ol/03/94Ol/03/9401/03/94Ol/03/94Ol/03/9401/03/94Ol/03/9401/03/94

1340 R1240 21260 21320 R1370 k1310. 21520 R1370 2

130120130130140130150140

3.2 2 0.22.4 R 0.22.6 2 0.22.8 R 0.32.8 i 0.22.2 2 0.22.7 i 0.24.0 i 0.2

10G16C1

10D110D310D412B313E314Bl

02/07/9402/07/9402/07/9402/07/9402/07/9402/07/9402/07/9402/07/94 (I) ~

1400 R1310 21420 R1410 k1270 21300 21480 2

140130140140130130150

Sample not collected

-3.4 2 0.22.1 k 0.22.6 2 0.22.5 R 0.22.5 i 0.22.3 2 0.21.8 2 0.2

10G16C1

10D110D210D310D412B313E3

10G16C1

10D110D210D310D412B313E3

03/07/9403/07/9403/07/9403/07/9403/07/9403/07/9403/07/9403/07/94

04/04/9404/04/9404/04/9404/05/9404/04/9404/04/9404/04/9404/04/94

1330 21330 i1380 R1350.21400,21260'R1330 21490 2

1410 k1300 21320 21250 R1370 k1430 k1370 "2

1490 j

130130140140140130130150

140130130130140140140150

2.7 2 0.22.2 R 0.32.3 2 0.22.5 2 0.22.3 R 0.22.0 2 0.22.1 i 0.22.4 2 0.2

4.0 k 0.32.4 2 0.22.7 2 0.22.6 2 0.32.2 2 0.22.9 2 0.32.1 2 0.32.3 2 0.3

Gamma emltters are only reported when acUvlUes exceed the MDCs: typical MDC values are found In Table 1-18.

TABLEI-13

IODINE-131, STRONTIUM-90, AND CdLMMA'PECTROSCOPIC ANALYSES OF MILK



Page 2 of 4

LOCATION COLLECTIONDATE K-40 Sr-90 OTHER ACTIVHT

10G110D110D212B3

10G16C1

10D110D210D310D412B313E3

10G110D110D2 .

12B3

10G16C1

10D110D210D310D412B313E3

04/20/9404/20/9404/20/9404/20/94

05/09/9405/09/9405/09/9405/09/9405/09/9405/09/9405/09/9405/09/94

05/23/9405/23/9405/23/9405/23/94

06/07/9406/06/9406/06/9406/06/9406/06/9406/06/9406/07/9406/07/94

1410 21440 21430 21350 R

1370 21250 21400 k1310 21210 21290 21400 21440 k

1250 R1350 i1300 k1330 i1290 21290 i1310 k1400 21300 X1390 21340 k1420 R

140140140130

140130140130120130140140

120130130130

130130130140130140130140

3.5 i 0.22.6 2 0.22.5 R 0.21.9 i 0.2

5.1 A 0.23.4 % 0.22.9 2 0.22.6 R 0.22.8 2 0.22.7 2 0.23.1 R 0.21.8 A 0.2

3.9 2 0.23.3 R 0.25.0 k 0.41.9 R 0.2

3.3 i 0.22.5 A 0.22.9 R 0.33.3 i 0.22.2 k 0.22.2 i 0.34.2 R 0.32.4 R 0.2

10G110D110D212B3

06/20/9406/20/9406/20/9406/20/94

1310 2 1301400 2 1401270 k '1301470-2 150

3.9 R 0.22.7 R 0.22.6 2 0.24.7 i 0.2

Gamma emltters are only reported when acttvtoes exceed the MDC's: typical MDC values are found ln Table 1-18.

TABLEI-13

IODINE-131, STRONTIUM-90, AND GAMMA~SPECTROSCOPIC ANALYSES OF MILK



Page 3 of4

LOCATION COLLECTIONDATE K-40 Sr-90 OTHER ACTIVITT

10G16C1

IOD110D210D310D412B313E3

IOG110D110D212B3

07/05/9407/05/9407/05/9407/05/9407/05/9407/05/9407/05/9407/05/94

07/20/9407/20/9407/20/9407/20/94

1390 21320 i1250 21320 i1400 k1300 21410 k1610 2

1310 21540 i1460 i1380 2

140130130130140130140160

130150150140

3.4 2 0.22.9 i 0.22.3 R 0.22.1 i 0.22.0 2 0.22.0 2 0.24.0 2 0.32.0 2 0.2

2.5 i 0.22.6 k 0.22.2 R 0.22.9 i 0.3

10G I6C1

10D110D210D310D412B313E3

08/08/94- 08/08/9408/08/9408/08/9408/08/9408/08/9408/08/9408/08/94

1170 2 1201360 k 1401370 2 ~ 1401490 2 1501140 2 1101480 k 1501440 k 1401450 2 150

3.2 i 0.22.4 2 0.22.7 R 0.22.7 2 0.22.6 2 0.22.7 E 0.23.5 2 0.24.1 R 0.2

10G110D110D212B3

10G16C1

10D110D210D310D412B313E3

08/22/9408/22/9408/22/9408/22/94

09/06/9409/06/9409/06/9409/06/9409/06/9409/06/9409/06/9409/06/94

1330 i1330 21240 21300 2

1480 21350 21450 i1490 21330 i1410 k1170 i1530 i

130130120130

150140150150130140120150

3.3 2 0.22.0 2 0.23.1 2 0.22.5 4 0.2

3.4 2 0.22.8 2 0.21.8 t 0.26.6 R 0.32.2 2 0.22.5 R 0.23.1 2 0.22.1 i 0.2

Gamma emt tters are ordy reported when acttvttles exceed the MDC's: typical MDC values are found In Table 1-18.

TABLEI-13

IODINE-181, STRONTIUM-90, AND GAMMA~SPECTROSCOPIC ANALYSES OF MILK



Page 4 of4

LOCATION COLLECTIONDATE K-40 Sr-90 OTHER ACTIVITY

10G110D110D212B3

10G16C1

10D110D210D310D412B313E3

10G110D110D212B3

10G16C1

10D110D210D310D412B313E3

10G16C1

10D110D210D310D412B313E3

09/19/9409/19/9409/19/9409/19/94

10/03/9410/03/9410/03/9410/03/9410/03/9410/03/9410/03/9410/03/94

10/17/9410/17/9410/17/9410/17/94

ll/07/9411/07/94ll/07/94ll/07/94ll/07/9411/07/94ll/07/9411/07/94

12/05/9412/05/9412/05/9412/05/9412/05/9412/05/9412/05/9412/05/94

1250 k 1201330 2 1301250 t 1301220 2 120

1250 i 1201320 t 1301340 R 1301420 2 1401270 2 1301210 2 1201270 2 1301490 2 150

1380 k 1401440 2 1401370 2 1401340 2 130

1270 2 1301350 2 1401350 t 1301340 k 1301450 2 1501250 k 1201370 k 1401470 k 150

1290 2 1301270 2 1301290 R 1301310 k 1301310 2 1301220 2 1201290 2 1301470 E 150

3.0 i 0.22.1 R 0.22.8 k 0.22.4 % 0.2

2.5 R 0.22.5 i 0.32.2 R 0.22.6 2 0.32.3 E 0.33.0 k 0.33.2 2 0.23.0 2 0.3

2.5 2 0.22.0 2 0.22.3 E 0.23.3 R 0.2

2.6 k 0.22.4 2 0.22.8 2 0.22.9 2 0.32.5 2 0.33.0 i 0.53.4 2 0.22.4 R 0.2

3.1 R 0.22.5 R 0.23.4 R 0.23.1 R 0.34.8 2 0.43.2 2 0.33.2 i 0.32.5 R 0.2

(I) Barn collapsed. Farmer sold cows. No milk was available. Sampling location wasreplaced In March by 10D2.Gamma emltters are only reported when actlvltles exceed the MDCs: typical MDC values are found ln Table 1-18.

TABLE1-14

GAMMA'PECTROSCOPIC ANALYSES OF SOIL


Results in pCI/gm (dry) 2 2S

Page 1 of 1

LOCATION

7G1 TOP7Gl BOT

12G1 TOP12G1 BOT

3S2 TOP3S2 BOT

5S4 TOP5S4 BOT

9B1 TOP9B1 BOT

12El TOP12El BOT

12Sl TOP12S1 BOT

13S6 TOP13S6 BOT

7S7 TOP7S7 BOT

10S3 TOP10S3 BOT

COLLECTIONDATE

10/19/9410/19/94

10/19/9410/19/94

10/19/9410/19/94

10/19/9410/19/94

10/19/9410/19/94

10/19/9410/19/94

10/19/9410/19/94

10/19/9410/19/94

10/19/9410/19/94

10/19/9410/19/94

K-40

7.44 2 0.748.10 2 0.81

11.3 2 1.111.5 2 1.2

11.1 2 1.1=12.5 k 1.2

9.06 2 0.919.49 2 0.95

10.0 2 1.09.48 R 0.95

11.8 2 1.210.9 2 1.1

10.7 2 1.110.7 f 1.1

12.9 k 0.1313.6 2 0.14

9.67 2 0.978.7.1 2 0.87

9.06 2 0.9111.0 % 1.1

Cs-137

1.19 k 0.120.80 2 0.08

0.10 2 0.030.06 2 0.03

0.04 2 0.020.07 R 0.02

0.17 2 0.040.18 2 0.04

0.37 R 0.040.27 f 0.04

0.22 k 0.030.21 R 0.04

0.09 k 0.030.10 k 0.03

0.04 2 0.02

0.28 2 0.040.32 2 0.04

0.25 2 0.040.24 R 0.03

Ra-226

1.79 2 0.601.27 R 0.55

1.82 2 0.492.16 k 0.51

" 1.22 k 0.541.56 k 0.38

1.28 2 0.471.50 k 0.54

1.39 2 0.591.68 k 0.61

1.20 2 0.411.37 k 0.51

1.88 k 0.62-1.27 R 0.53

1.23 2 0.45

1.57 2 0.651.17 2 0.47

2.02 k 0.591.71 R 0.42

Th-228

0.83 2 0.080.89 2 0.09

0.98 2 0.101.09 2 O.ll

0.74 2 0.070.78 k 0.08

0.77 2 0.080.78 2 0.08

0.66 2 0.070.66 k 0.07

0.76 2 0.080.70 2 0.07

0.78 k 0.080.70 2 0.07

0.76 2 0.080.91 2 0.09

0.75 2 0.080.65 k 0.07

0.85 E 0.091.02 2 0.10

Gamma emitters are only reported when acUvlnes exceed the MDC's: typical MDC values are found In Table I-18.I

TABLEI-15

GAMMA'PECTROSCOPIC ANALYSES OF VEGETATION


Results In pCI/gm (wet) k 2S

Page 1 of 1

LOCATION COLLECTION DATE Be-7 K-40 COMMENTS

VT- 7G1VT- 12G1VT- 1D2/7S7VT- 3D1/10S3VT- 3S2VT- 5S4VT- 9B1VT- 12E1VT- 12S1VT- 15S4/13S6

10/03/9410/03/9410/03/9410/03/9410/03/9410/03/9410/03/9410/03/9410/03/9410/03/94

1.88 2 0.193.89 R 0.393.04 2 0.301.46 2 0.154.43 2 0.441.23 k 0.121.49 2 0.155.83 2 0.582.13 2 0.21

3.14 2 0.317.78 R 0.787.39 2 0.743.29 2 0.33

5.0 2 0.53.25 2 0.323.76 2 0.386.30 R 0.633.91 2 0.39

Comments:

1 Insuflicient vegetation to obtain a sample at this location

(I) Insuflldent vegetatton to obtain a sample at this location.

TABLEI-16

GAMMA'PECTROSCOPIC ANALYSES OF FOOD PRODUCTS (FRUITS ANDVEGETABLES)



Page 1 of S

LOCATION SAMPLE TYPE COLLECTIONDATE K-40 OTHER ACTIVITY

10B512F513G2

13G2

13G211Dl

2B513E410B512F7

14B3

13G211D112F7

2B5

13G212Bl11Dl9D2

10F214B310B5

8A513G2

9D2

14B3

StrawberriesStrawberriesStrawberries

Peas

BeansBeans-IrrigatedBeansBeansBeansBeans

Lettuce

'otatoPotatoPotato

Onion

CornCornCornCornCornCornCorn

Red BeetsRed Beets

Wax Beans

Peppers

06/20/9406/20/9406/27/94

06/27/94

07/25/9407/18/9408/02/9408/09/9408/22/9408/30/94

07/12/94

08/29/9408/30/9409/07/94

07/12/94

07/26/9408/09/9408/15/9408/.15/9408/16/9408/22/9408/22/94

07/12/9407/12/94

07/18/94

08/22/94

1.49 k 0.151.35 k 0.131.99 2 0.20

2.07 2 0.21

2;ll 2 0.211.77 2 0.181.76 k 0.182.59 k 0.262.34 R 0.231.97 2 0.20

5.59 2 0.56

3.84 R 0.383.89 2 0.394.06 2 0.41

1.75 k 0.17

3.31 k 0.331.22 k 0.122.36 2 0.242.54 2 0.252.69 R 0.272.41 2 0.242.62 k 0.26

4.63 R 0.463.51 k 0.35

2.27 R 0.23

1.64 2 0.16

Be-7 0.432 0.13

Be-7 0.102 0.05

Gamma emitters are only reported when acttvitles exceed the MDC's: typical MDC values are found In Table l-ls.I

TABLE1-16

GAMMA'PECTROSCOPIC ANALYSES OF FOOD PRODUCTS (FRUITS ANDVEGETABLES)


Results ln pCI/gm (wet) k 2S

Page 2 of 3

LOCATION SAMPLE TYPE COLLECTIONDATE KAO OTHER ACTIVITT

2B513E411D19D2SA5

10B510F214B313G2

2B510B515A313E411Dl9D2

10F214B3SA4

13G2

14B3SA5

10F210B5

14Bl11D110F213G29D2

10B511D113G2

CucumberCucumberCucumber-IrrigatedCucumberCucumberCucumberCucumberCucumberCucumber

TomatoesTomatoesTomatoesTomatoesTomatoesTomatoesTomatoesTomatoesTomatoesTomatoes

CabbageCabbageCabbageCabbage

ZucchlnlZucchlnlZucchlnlZucchlnlZucchlnl

SquashSquash/Butter NutSquash/Winter

07/12/9407/12/9407/18/9407/18/9408/02/9408/02/9408/16/9408/22/9408/29/94

08/02/9408/02/9408/02/9408/09/9408/15/9408/15/9408/16/9408/22/9408/22/9408/29/94

07/12/9407/12/9407/18/9408/02/94

07/12/9407/18/9407/18/9407/25/9408/15/94

08/22/9408/30/9409/20/94

1.41 2 0.141.52 k 0.151.65 R 0.172.15 k 0.221.40 k 0.141.92 2 0.191.49 2 0.151.91 2 0.191.41 k 0.14

3.62 R 0.362.37 2 0.241.91 k 0.193.30 2 0.331.56 2 0.162.40 2 0.241.93 k 0.192.34 % 0.232.77 R 0.282.59 k 0.26

2.24 2 0.222.26 2 0.231.86 k 0.191.96 k 0.20

2.17 k 0.221.95 k 0.191.91 2 0.191.76 2 0.181.82 k 0.18

1.31 2 0.132.15 2 0.213.99 2 0.40

I

oo

Gamma emltters are only reported when actlvlnes exceed the MDC's: typical MDCvalues are found in Table 1-18.

TABLEI-16

GAMIHA'PECTROSCOPIC ANALYSES OF FOOD PRODUCTS (FRUITS AND VEGETABLES)



Page S of S

LOCATION COLLECTIONDATE K-40 OTHER ACTIVITY

12B1

9D2

13E411D19D2

11D112B1

12B18A47B2

8A47B2

Watermelon

Egg Plant

CantaloupeCantaloupeCantaloupe

PumpkinPumpkin

ApplesApplesApples

PearsPears

08/22/94

07/18/94

08/09/9408/15/9408/15/94

09/26/9409/26/94

08/09/9409/26/9409/26/94

09/26/9409/26/94

1.72 2 0.17

1.94 t 0.19

3.45 1 0.342.56 k 0.262.21 2 0.22

3.63 2 0.363.48 2 0.35

1.09 2 0.110.83 2 0.080.78 2 0.08

0.94 k 0.090.79 2 0.08

Be-7 0.07 2 0.03

Be-7 0.09 k 0.03

~ Gamma «mltters are only reported when acttvtttes exceed the MDC's: typical MDC values are found ln Table 1-18.

TABLEI-17

GAMMA'PECTROSCOPIC ANALYSESOF GAME, POULTRY, AND EGGS


Results In pCI/gm (wet) t 2S

Page 1 of 1

LOCATION SAMPLE TYPE COLLECTIONDATE KAO CS-137

2S2H5S3S

5S2S

16F

16F15S5S

16F

10D1

White-Tall DeerWhite-Tall DeerWhite-Tall DeerWhite-Tall Deer

RabbitRabbitRabbit

SquirrelSquirrelSquirrelSquirrel

Eggs

02/21/9410/28/9411/07/9412/12/94

ll/05/9411/01/9411/10/94

10/19/9410/24/9410/31/9411/02/94

10/17/94

3.61 2 0.364.12 2 0.413.92 R 0.397.22 2 0.72

3.41 k 0.343.18 2 0.323.32 R 0.33

3.65 2 0.373.45 2 0.343.20 2 0.323.43 2 0.34

1.30 2 0.13

0.01 t 0.0030.05 k 0.008

0.57 k 0.057

0.02 2 0.007

0.41 k 0.040.59 R 0.060.02 2 0.0050.77 2 0.08

Gamma emitters are only reported when acttvlttes exceed the MDCs: typical MDC values are tound ln Table 22.

TABLE1-18

TYPICAL ~ MINIMUMDETECTABLE CONCENTRATIONS OF NUCLIDES SEARCHED FOR BUT NOT FOUND BY GAMMASPECTROMETRY

IN THE VICINITYOF SUSgUEHANNA STEAM ELECTRIC STATION, 1994

Nuclide

Mn-54Co-58Fe-59Co-60Zn-65Zr-95Nb-95Ru-103I-131"Cs-134Cs-137Ba-140La-140Ce-141

Fish(p Ci/g wet)

0.0250.0250.0430.0250.0440.0460.0240.0260.0760.0240.0260.1040.0390.034

Sediment(pCi/g dry) (pCl/1)

0.0530.0550.160.0510.110.160.0700.0700.720.0630.0750.620.340.16

Surface Water(pCi/1)

4.64.49.34.79.29.04.75.2

254.74.8

27ll9.0

Ground Water(pCl/1)

4.64.69.54.59.79.45.05.1

10.95.05.1

19.27.88.9

Potable Water(pci/1)

4.04.49.94.28.49.14.65.4

4.44.7

1510

Rain Water

4.64.79.94.7

109.75.15.6

135.05.2

8.89.3

Nuclide

Mn-54Co-58Fe-59Co-60Zn-65Zr-95Nb-95Ru-103I-131"Cs-134Cs-137Ba-140La-140Ce-141

Air Particulate(10-$ pCl/m3)

0.330.471.400.370.781.12

~ 0.550.77

810.360.33

26ll1.2

(pCl/I)

4.84.9

115.3ll9.55.05.29.15.15.3

187.09.2

Fruite/Veg.(pCl/g wet)

0.0110.0100.0260.0120.0280.0230.0120.0120.0190.0120.0120.0380.0150.018

Algae(pCl/g dry)

0.300.280.540.300.600.540.300.280.500.280.300.900.430.34

Game, Poultry & Eggs(pCl/g wet)

0.0170.0110.0390.0170.0390.0330.0120.0170.0240.0170.0560.0490.0220.027

Soll(pci/g dry)

0.0430.0420.0950.0440.1060.1020.051 .

0.0440.1010.0500.0990.2240.0760.078

Typical refers to mean plus two standard deviatlons.—Iodine-131 in surface water, potable water and milk is determined by radiochemical methods. See appendix B-5.

APPENDIX J


A endix J

The data in the table that follows shows how well Teledyne's analysis results forradioactively spiked environmental sample media compared with the analysis results ofthe EPA and those ofother laboratories receiving the spikes for analysis in 1994.Teledyne is contractually required by PPEcL to participate in the EPA's program and tosupply PPkL with the results ofthat participation for quality control purposes.

1994 Radiological Environmental Monitoring Report J-2

0TABLEJ

EPA ENVIRONMENTALRADIOACTIVITYPERFORMANCE EVALUATIONSTUDIES PROGRAM - 1994TELEDYNE BROWN ENGINEERING ENVIRONMENTALSERVICES

(Page I of4)

Collection SequenceDate No. Media NucHde EPA Results(a)

TeledyaeIsoto es Results(b)

NormaHxed DeviationGrand Av . Known

AllParticipantsMean k 2 s.d.

01/14/94 638 Water

01/28/94 636 Water

02/04/94 637 Water

03/04/94 639 Water

04/19/94 642 Water

Sr-89Sr-90

Gr-AlphaGr-Beta

I-131

H-3

Gr-BetaSr-89Sr-90Co-60Cs-134Cs-137Gr-Alpha

25.0 215.0 k

15.0 262.0 k

119.0 2

8.668.66

8.6617.32

20.78

117.0 220.0 214.0 k20.0 234.0 229.0 286.0 2

31.188.668.668.668.668.66

38.11

4936.0 2 855.63

102.6719.0013.0023.6734.0034.0078.00

19.293.000.009.635.197.959.00

24.0 2 3.0015.67 2 4.59

21.67 2 1.7472.33 k 11.37

110.33 2 0.00

4833.33 2 458.25

0.090.37

2.742.80

-1.59

-0.04

-0.400.18

-0.391.230.880.98

-0.50

-0.350.23

2.311.79

-1.30

-0.36

-1.38-'0.35-0.351.270.001.73

-0.63

120.99 2 20.36

4844.97 2 955.34

106.8618.4914.1320.1231.4531.'1784.40

30.947.384.283.665.444.80

29.26

23.74 k 8.0214.59 k 4.34

13.75 k 8.50 (c)56.14 R 28.30

06/10/94 643 Water Co-60Zn-65Ru-106Cs-134Cs-137Ba-133

50.0 2134.0 2252.0 2

40.0 249.0 298.0 2

8.6622.5243.30

8.668.66

17.32

43.0013.33

201.3329.3349.6785.00

6.001.74

27.8711.374.599.00

-2.34-16.96

-1.05-2.65-0.94-0.25

-2.42-16.08

-3.51-3.700.23

-2.25

49.77. 2 7.64 (d)140.62 2 19.16 (e)216.56 k 57.04 (f)

36.99 2 6.28 (g)52.38 2 7.2286.46 R 16.62 (h)

07/22/94 645 Water

08/05/94

08/26/94

646 Water

648 Air Filter

07/15/94 647 Water Sr-89Sr-90

Gr-AlphaGr-Beta

H-3

Gr-AlphaGr-BetaSr-90Cs-137

30.0 k20.0 R

32.0 210.0 k

8.668.66

13.868.66

35.0 k56.0 220.0 215.0 2

15.5917.328.668.66

9951.0 21723.39

26.00 k 5.1919.00 k 0.00

25.33 2 8.6716.00 2 0.00

9700.00 R 300.12

31.33 k 6.2459.33 2 9.6318.00 2 3.0017.00 2 5.19

-0.990.07

-0.950.38

0.08

-1.070.04

-0.540.14

-1.39-0.35

-1.442.08

-0.44'0.71

0.58-0.690.69

28.84 2 12.1218.80 k 5.60

29.74 2 20.2214.91 R 7.48 (I)

9651.86 %1393.24

36.89 2 13.2459.08 2 14.4619.57 k 5.5216.59 R 4.84

10/07/94 650 Water I-131 79.0 t 13.86 71.00 4 9.00 -1.92'1.73 79.89 2 13.58

TABLEJEPA ENVIRONMENTALRADIOACTIVITYPERFORMANCE EVALUATIONSTUDIES PROGRAM - 1994

TELEDYNE BROWN ENGINEERING ENVIRONMENTALSERVICES(Page 2 of4)

Collection SequenceDate No. Media NucHde EPA Results(a)

TeledyneIsoto s Results(b)

NormaHzed DeviationGrand Av . Known

AllParticipantsMean 2 2 s.d.

09/30/94 651 Ml]k Sr-89Sr-901-131Cs-137K

25.0 2 8.6615.0 2 8.6675.0 2 13.8659.0 k 8.66

1715.0 2 148.96

24.33 k 7.5617.67 2 4.5981.67 2 17.5870.33 2 13.86

1740.00 R 461.85

0.740.871.472.750.79

-0.230.921.443.930.50

22.19 2 10.2215.15 E 4.9674.89 2 11.1662.39 2 7.44 (j)

1700.90 2 218.0010/28/94 652 Water Gr-Alpha

Gr-Beta57.0 R 24.2423.0 k 8.66

47.00 225.33 2

9.004.59

-0.66-0.63

-1.240.81

52.30 2 27.9827.16 2 10.46

10/18/94 653 Water Gr-BetaSr-89Sr-90Co-60Cs-134Cs-137Gr-Alpha

142.0 2 36.3725.0 2 8.6615.0 2 8.6640.0 2 8.6620.0 2 8.6639.0 2 8.6657.0 R 24.25

120.00 k24.67 214.33 241.00 221.67 k41.67 +51.33 2

0.006.243.453.004.596.934.59

-0.460.58

-0.200.551.11

-0.02-0.66

-1.81-0.12-0.230.350.580.92

-0.70

125.5722.9914.9239.4318.4541.7356.68

27.848.324.545.303.565.32

19.66

11/04/94 654 Water Co-60Zn-65Cs-134Cs-137Ba-133

59.0 E 8.66100.0 R 17.3224.0 2 8.6649.0 2 8.6673.0 k 12.12

52.00 2 0.0081.33 2 21.0619.67 R 7.5454.33 2 6.9358.33 + 8.67

-2.38-4.04-1.140.84

-3.09

-2.42-3.23-1.501.85

-3.63

58.87 2 9.18 (k)104.68 2 15.90 (k)22.95 2 4.5451.92 k 7.2270.81 2 12.26 (k)

~P00 otes

(a) EPA Results - Expected laboratory precfsfon (3 sfgma). Units are pCf/I for water and milk except K Is In mg/I.

(b) Teledyne Results - Average 2 3 sfgma. Units are pCI/I for water and mflk except K fs ln mg/I. Unfts are total pCI for afr partfculate fllters.

(c) There appears to be varfatfon fn self-absorptfon matrfx. The EPA conflrms that the composltfon of thefr tap water from Lake Mead, varfes seasonallywhich can cause varfatlon In alpha, beta results. No correctfve actfon requfred at thfs tfme sfnce results are wfthln k 3 sfgma control llmfts.

(d) A second alfquot was analyzed. paying partfcular attentfon to volume allquoted. The result, 52 pCI/I, was fn good agreement wfth the EPA. Thethree orfgfnal results. each counted on a dffferent detector, showed good preclsfon. The measurement of Co-60 has not been a problem. FutureEPA cross-checks wfll be weighed and results followed to check for a possfble trend "out of control".

TABLEJEPA ENVIRONMENTALRADIOACTIVI1YPERFORMANCE EVALUATIONSTUDIES PROGRAM - 1994

TELEDYNE BROWN ENGINEERING ENVIRONMENTALSERVICES(Page 3 of4)

(e) The average value of three analyses on the "Report of Analysis" was 133 pCI/liter which is In good agreement with the EPA. Apparently, Incorrectresults were entered Into the EPA computer. Future data will be printed from the computer screen to check entries.

(f) The EPA has Indicated that the Radiation Quality Assurance Program has been experiencing problems with the ruthenium-106 analysis. Seeattached letter from EPA.

(g) The first aliquot, prepared according to EPA dilution Instructions was counted on four detectors In the 1 liter Marinelli geometry with Cs-134results (based on the 796 KeV peak) ln pCI/I of 32.0, 25.1. 31.7, and 30.8. The 31.7 result was not reported. Had that been reported instead of25.1, the average would have been 31.5 and the normalized deviation would have been -2.94 Instead of -3.70. A second aliquot was prepared and asingle measurement was made with the result of 31.1 pCI/I. An undiluted aliquot was measured In a 150 ml geometry with the result of 33.5 pCI/l.That result Is comparable with the Marinelll results. Thus none of: sample preparation (dilution, volume determination, maintaining correct pH,etc.), sample geometry, or detector emciency seem to be the cause of the low results.

(h) There Is no apparent reason for the low result, however the average value, 85 pCI/I Is In good agreement to the grand average (86.46). Nocorrective action planned.

(I) EPA results for gross beta ln water were corrected for 20% crosstalk into the beta channel from the Th-230 alpha spike. Recent measurementsshow that the crosstalk can be much higher (37% for gamma products counter ¹1). The normalized deviation from the grand average was only 0.38.Future results willbe corrected with specIIIc crosstalk values determined by counUng Th-230 standards.

(j) The milk sample was counted four Umes. The reported Cs-137 values were based on one aliquot of 1 liter volume and an aliquot of 0.865 litercounted two times. It Is suspected that the 0.865 liter volume was IncorrecUy determined. If 1 liter (the usual volume for counUng milk samples)Is used In the calculation, then the average of three results equals 63.6 pCI/I which gives a normalized deviation to the Known of 1.59. The fourthcount (a I liter aliquot) had a Cs-137 equal to 64.2 pCI/I which Is In good agreement with the average of the other three. Teledyne will set up a logfor recording aliquots used for EPA samples and record how the aliquot volume was determined.

(k) The EPA requires that water samples be diluted bei'ore gamma analysis. That Imposes a feature not appropriate for the handling of environmentalsamples. As ln the 06/10/94 water sample, It appears that the Arst aliquot may not have been accurately prepared. A second aliquot was preparedand counted three Umes with results In pCI/I and normalized deviation of:

Co-60 60.6 +0.55Zn-65 100. 0.0

Cs-134 22.9 -0.38

TABLEJEPA ENVIRONMENTALRADIOACTIVITYPERFORMANCE EVALUATIONSTUDIES PROGRAM - 1994

TELEDYNE BROWN ENGINEERING ENVIRONMENTALSERVICES

(Page 4 of4)

Cs-137 58.5 +3.29Ba-133 69.8 -0.79

Four of the five are now ln good agreement with the EPA results. The Cs-137 is high, but within the control limits when compared to the grandaverage deviation of all laboratories of 2.89. The grand average was 51.9 pCI/I. For future samples of this type we will have two technlclans each

prepare an aliquot and compare the counting results to check for preparation technique differences.

· tableof contents suh8rfaryandconclusions. introduction. ambientradiationmonitoring..........

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