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SusqueHanna Steam Electric StationUnits 1 & 2

RadiologicalEnvironmental Monitoring

Program1988 Annual Report

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Pennsylvania Power 8 Light CompanyAllentown, PA

April 1989

II

I

I

Section

TABLE OF CONTENTS

Title ~Pa e

Executive Summary

Introduction

A.B.

C.D.E.

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

Regulatory OverviewScope of the SSES REMP

II-2

II-2II-6II-7II-8

Program Description I I I-1

IV. Monitoring Methods IV-1

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

Ambient RadiationSurface WaterDrinking WaterAlgaeFishShoreline and Flocculated SedimentGround (Well) WaterAirborne Particulates and Air Iodine-131/PrecipitationMilkSoil (Top and Bottom) and VegetationFood Products

IY-1IV-1IV-2IV-3IV-3IV-4IV-4IV-5IV-6IV-6IV-7

V. Summary and Discussion of 1988 Analytical Results V-1

A"'.

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

Ambient RadiationSurface WaterDrinking WaterAlgaeFishShoreline and Flocculated SedimentGround WaterAir Parti cul ates/Air Iodine-131/Preci pi tationMilkSoil (Top and Bottom) and VegetationFood ProductsCalculated Dose to the Maximally Exposed Individual

V-2V-5V-14V-19V-24V-27V-32V-36V-45V-50V-55V-61

Section

TABLE OF CONTENTS

Title ~Pa e

VI. Deviations from the Program VI-1

VII. Program Changes VII-1

VIII. Conclusion VIII-1

IX. Summary Tabl e IX-1

X. , Land Use Census X-1

XI. References XI-1

XII. Data Tables XII-1

Appendix A USEPA Intercomparison Program Results A-1

Appendix B Summary of Analytical Methods B-1

Appendix C Data Reporting Conventions C-1

LIST OF TABLES

TableNumbers Title ~Pa e

2.

3.

4.

5.

6.

7:

8.

9.

10.

12.

Annual Analytical Schedule forthe Susquehanna Steam ElectricStation (SSES) RadiologicalEnvironmental Monitoring Program-(REMP) 1988

I

Sample Locations and Media for theSSES Radiological EnvironmentalMonitoring Program - 1988

Summary of Data for the SSES OperationalRadiological Environmental MonitoringProgram - 1988

Nearest Residence, Garden and DairyAnimal in each of the 16 MeteorologicalSectors within a 5-Mile Radius of theSusquehanna Steam Electric Station - 1988

Direct Radiation - Environmental Thermo-luminescent Dosimetry Results - SSES 1988

Gross Alpha, Gross Beta, Tritium,Iodine-131 and Gamma SpectrometricAnalysis of .Surface Water - SSES 1988

Gross Alpha, Gross Beta, Tritium,Iodine-131, and Gamma SpectrometricAnalysis of Drinking Water - SSES 1988

Gamma Spectrometric Analysis of Algae-SSES 1988

Gross Beta and Gamma SpectrometricAnalysis of Fish - SSES 1988

Gross Alpha, Gross Beta and GammaSpectrometric Analyses of Shoreline andFlocculated Sediment - SSES 1988

Gross Alpha, Gross Beta, Tritium andGamma Spectrometric Analyses of Ground(Well) Water - SSES 1988

Gross Beta Analyses of Air ParticulateFilters - SSES 1988

III-3

III-6

IX-1

X-2

XII-1

XII-5

XII-9

XII-10

XII-11

XII-12

XII-13

XII-15

111

LIST OF TABLES

TableNumbers Title ~Pa e

13.

14.

15.

16.

17.

18.

19.

20.

Gross Alpha and Gamma SpectrometricAnalyses of Composited Air ParticulateFilters - SSES 1988

Gross Alpha, Gross Beta, Tritium andGamma Spectrometric of Analyses inPrecipitation - SSES 1988

Gross Beta Minus K-40, Iodine-131 andGamma Spectrometric Analyses of Milk-SSES 1988

Gamma Spectrometric Analyses of Soi 1-SSES 1988

Gamma Spectrometric Analyses of Vegetation-SSES 1988

Gamma Spectrometric Analyses of FoodProducts (Fruits, Vegetables and Honey)-SSES 1988

Gamma Spectrometric Analyses of Game,Poultry, and Eggs - SSES 1988

Typical Lower Limits of Detection ofNuclides Searched for but not found byGamma Spectrometry in the Vicinity ofSusquehanna Steam Electric - 1988

XII-17

XII-18

XII-19

XII-23

XII-24

XII-25

XII-30

XII-31

FigureNumbers Title

LIST OF FIGURES

~Pa

e'.

3.

5.

6.

7.

8.

9.

10.

Exposure Pathways to Humans

On-site Environmental SamplingLocations-SSES

Off-site Environmental- SamplingLocations-SSES

Ambient Radiation Levels

Gross Beta Activity in Surface Water

Tritium Activity in Surface Water

Gross Beta Activity in Drinking Water

Gross Beta Activity in Air Particulates

Gross Alpha Activity in Air Particulates

Iodine-131 Activity in Milk

II-4

III-14

III-15

V-4

V-7

V-12

V-17

V-38

V-40

V-48

III

I

I. EXECUTIVE SUSQRY

In 1988, there were more than 2000 routine samples collected at 161

locations, and over 3000 routine analyses performed in support of the

Radiological Environmental Monitoring Program (REMP). The extent of

the sampling and the types and sensitivities of the analyses performed

met and exceeded the requirements of the technical specifications for

the Susquehanna Steam Electric Station (SSES). The result of this

effort was verification of the SSES Effluent Monitoring Program data

that indicate that the operation of SSES has no deleterious effect on

the health and safety of the public or the environment.

Of the three pathways (airborne, wat'erborne, and terrestrial) by which

man can be exposed to radioactivity, only the waterborne pathway was

found to contain radionuclides which could be attributable to the

operation of the SSES. In the waterborne pathway, however, there was a

decrease in the levels of radionuclides detected from those seen in

1987.

The amounts of the radionuclides detected in 1988 are so small, as in

past years, that the maximum dose to an individual in the general

public is only a small fraction of a percent of the dose permitted by

the Nuclear Regulatory Commission as stated in 10CFR50, Appendix I.The maximum potential off-site dose via the aquatic pathway was

calculated to be less than 0.001 millirem/year. This is negligible

compared to the public's exposure from natural background radiation of

approximately 300 millirem annual effective dose equivalent.

~

g i

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I

I

II. INTRODUCTION

The preoperational radiological environmental monitoring program (RENP)

for Pennsylvania Power 8 Light Company (PPSL) at the Susquehanna Steam

Electric Station (SSES) was conducted from April 1972 to September 1982.

On September 10, 1982, Unit 81 became critical, thereby initiating the

operational phase of the program. The preoperational phase of the

pr ogram, as wel 1 as the initia 1 phase of the operati ona1 program

(September 10, 1982 through June 1983), was conducted by Radiation

Nanagement Corporation (RNC). NUS Corporation conducted the RENP from

June 1983 until August 1984 when Tel.edyne Isotopes (TI) took over the

operational RENP. The analytical program is now being conducted by

Teledyne Isotopes under contract with Pennsylvania Power 5 Light Company.

Starting in August 1984, Ichthyological Associates (PPSL's biological

consultants) assumed responsibility for the sample collection portion of

the program. In June 1985, Ecology III became PP8L's biological

consultants (essentially utilizing the same staff) and they continued to

perform sample collection activities through 1988.

This report covers the period from January 4, 1988 through January 6,

1989. Teledyne Isotopes performed all the analyses except the

thermoluminescent dosimetry (TLD) program which is conducted by PP8L. A

detailed Quality Control and Quality Assurance Program is conducted along

with the Radiological Program. Data from programs conducted in prior

years have been presented in a series of annual reports. (1-13, 21, 27,

28, 31).

A. Site and Station Descri tion

The Susquehanna Station contains two'NR generating units, each with

a capacity of about 1050 MWe. Unit ¹1 achieved initial criticalityon September 10, 1982. Unit ¹2 achieved initial criticality on May

8, 1984. The site is located on an approximately 1500 acre tract

along the Susquehanna River, five miles northeast of Berwick in Salem

Township, Luzerne County, Pennsylvania.

The area surrounding the site can generally be characterized as

rural, with forest and agricultural lands predominating. More

specific information on the demography, hydrology, meteorology and

land use characteristics of the local area may be found in the

Environmental Report , the Final Safety Analysis Report( and(14)

the Final Environmental. Statement for the SSES.

B. Fundamentals of Radiolo ical Environmental Monitorin Pro rams

Radioactive materials are present in man's environment as the result

of both natural processes and of man's technological developments.

Normally, people and organisms are continually exposed to naturally

occurring .radiation and radionuclides from, terrestrial and cosmic

sources. The main contribution to the exposure of members of the

general public above natural background exposure is from the medical

services field (x-rays, radioactive medical treatments, etc.).

Background levels vary with time and location as they are influenced

by external events such as cosmic ray bombardment, weapons test

fallout, and seasonal variations. These levels also can vary

significantly within relatively short distances due to variations in

geological composition and other factors. Because of these spatial

and temporal variations, the environmental radiological surveys in

the vicinity of the SSES are divided into preoperational and

operational phases. The preoperational phase of the program of

sampling and measuring radioactivity in various media permits a

characterization of the radiation levels and concentrations prior to

plant operation along with an indication of the degree of natural

variation to be expected. The operational phase of the program

obtains data which, when considered along with the data obtained in

the preoperational phase, assist in the evaluation of the

radiological impact of plant operation.

From a nuclear power plant such as the SSES, there are three basic

pathways in which a member of the public has the potential to be

exposed to radioactivity. Figure 1 depicts these pathways- ofI

radioactive material uptake: 1) inhalation (breathing); 2) ingestion

(eating, drinking); and 3) whole body irradiation directly from the

plant or from immersion in airborne effluents.

To effectively monitor the radioactivity in the environment, media

are sampled which have the potential to affect the human body either

directly or indirectly. Media normally sampled to meet radiologicalv

environmental monitoring program requirements may be categorized as

either atmospheric or aquatic.

I

I

I

FIGURE 1

EXPOSURE PATHMAYS TO HUMANS

GASEOUS EFFLUENT

NUCLEAR POWER PLANT

Ol

0

5o.V'.

Pro0

0

0Q0Co.

O0

0 C,0

0)

~O

i ation ~If)tris

ngetion /

Pytp'

CD

O~

O~0

C,4'«-mwNil ~ llgi g JJJjf/P+

Hlf(/+l(fP" de~'use r~u~pelri.

tip'id'5

tion

~4n9e

%tio

rl~ Q+c'

ChW

k~C

Ll QUIDEFFLUENT

DirectIrradiation

FUEL TRANSPORT

Shoreline p>"~'u e

o'

I

1

I

I

Atmos heric Sam lin - Air is sampled to evaluate potential radiation

exposures from inhaled radionuclides in gaseous (iodine) or

particulate form. Direct radiation and air submersion exposures are

also monitored. Precipitation is sampled to follow the movement of

radionuclides from air to terrestrial and aquatic media.

Terrestrial Sampling - Plant life, primarily in the form of food

products (fruits, vegetables, etc.), is sampled because it is a

primary source for ingestion of radionuclides. Common game animals

normally hunted for food (deer, squirrels) are also sampled.

Dairy products are sampled because they are widely consumed. Milk is

one of the few foods commonly consumed soon after production which

may therefore contain relatively short-lived radionuclides when

consumed.

Soil samples are also collected to provide an additional means of

monitoring the air-to-ground pathway.

A uatic Sam lin - River water is sampled to verify the results of

any liquid releases of radionuclides from the facility, and drinking

water supplies are sampled to identify and evaluate any potential

radiation exposure through ingestion.

Fish are sampled since they are a primary aquatic food source. Algae

and sediment are collected since they are, indicators and accumulators

of radionuclides in the aquatic system.

C. Ob ectives of the SSES REMP

The objectives of the SSES Operational Radiological Environmental

Monitoring Program are:

1. To identify, measure and evaluate existing radionuclides in the

,environs of the SSES, and to determine whether any significant

increase occurs in the concentration of radionuclides in

critical pathways.

2. To verify that SSES operations have adequate reactor effluent

control.

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

4. To verify that SSES operations have no detrimental effects on

the health and safety of the public or on the environment.

5. To fulfill the obligations of the radiological environmental

surveillance sections of the SSES Technical Specifications.

D. Re ulator Overview

United States Nuclear Regulatory Commission (USNRC) regulationsI

require that nuclear power plants be designed, constructed, and

operated to keep levels of radioactive material in effluents to

unrestricted areas as low as 'reasonably achievable (ALARA) (10 CFR

50.34 and 10 CFR 20;1c). To ensure that these criteria are met, each

license authorizing reactor operation includes technical

specifications (10 CFR 50.36a) which contain requirements governing

radioactive effluents.

In-plant monitoring is used to ensure that predetermined release

limits are not exceeded. However, as a precaution against unexpected

and undefined processes which might allow undue accumulation of

. radioactivity in any sector of man's environment, a program for

monitoring the environment in the vicinity of the SSES is also

included in the SSES Technical Specifications. The regulations

governing the quantities of radioactivity in reactor effluents allow

nuclear power plants to contribute, at most, only a few percent

increase above normal background radioactivity.

The SSES REMP was designed on the basis of the USNRC Radiological

Assessment Branch Technical Position on radiological environmental

monitoring as described in Revision 1, November 1979. PPSL has

expanded the basic program required by the NRC to aid in the

characterization of area radiation levels and any possible impact

from the SSES operation.

E. Sco e of the SSES RENP

In 1988, the SSES Radiological Environmental Monitoring Program

included the measurement of ambient gamma radiation by

thermoluminescent dosimetry; the determination of the activities of

gamma emitters and gross alpha and gross beta activities in shoreline

and flocculated'sediments; the determination of the activity of gamma

emitters and gross beta activity in fish; the determination of gross

beta and gross alpha activities, and the activi.ties of gamma emitters

in airborne particulates, and the measurement of airborne iodine-131

activity; the measurement of gross beta and gross alpha activities,and the activities of gamma emitters, iodine-131 and tritium in

water; the measurements of gross beta and gross alpha activities, and

the activities of gamma emitters, and tritium in precipitation; the

measurement of iodine-131 activity, gross beta minus potassium-40

activity, and the activities of gamma emitters in cow milk; and the

determination of the activities of gamma emitters in game, poultry,

honey, eggs, various fruits and vegetables, algae, and in soil and

vegetation.

Sampling locations are selected on the basis of local ecology,

meteorology, physical characteristics of the region, and demographic

and land use features of the site vicinity.

There were more than 2000 types of routine samples collected, and

over 3000 routine analyses performed in support of the RENP program

in 1988. The numbers'xclude measurements of ambient gammaradiation'y

thermoluminescent dosimetry, duplicate and split samples and

analyses, other quality control samples, analyses performed

independently by Pennsylvania State University, and other non-routine

samples and analyses.

I

I

II

I

III., PROGRAM DESCRIPTION

One-hundred sixty-one locations were included in the SSES

monitoring program for 1988., Environmental sampling locations were

divided into two classes, indicator and control. Indicator samples

are those collected at locations which are expected to manifest

station effects, if any exist, and were selected on the basis of

distance from the site, topography, hydrology, meteorology,

demography, and drainage characteristics. Control samples are

collected at locations which are expected to be less l,ikely to be

affected by station operation. These control samples provide a

basis on which to evaluate fluctuations in radioactivity at

indicator locations in relation to natural phenomena and fallout.

The number and locations of monitoring points were determined by

considering the locations where the highest off-site environmental

concentrations have been predicted from plant effluent source

terms, site hydrology, and site meteorological conditions. Other

factors considered were applicable regulations, population

distribution, ease of access to sampling stations, security and

future program integrity.

The operational environmental radiological program for the SSES is

summarized in Table 1. Table 2 describes sample locations,

associated media, and approximate distance and direction from the

site. Figures 2 and 3 illustrate the locations of sampling

stations relative to the SSES.

In addition to the described analytical program, a milk animal,

vegetable garden, and residence survey was performed in 1988. This

survey identified the dairy animals within the five-mile radius of

the SSES and the nearest garden and residence in each sector.

These land use parameters are used in the assessment of potential

radiological doses to hypothetical individuals and populations of

the stated regions.

111-2

TABLE 1(Page 1 of 3)

Annual Analytical Schedule for theSusquehanna Steam Electric Station (PPKL)

Radiological Environmental Monitoring Program - 1988

Media 8 CodeNo. of Samp eLocations Freq.(a)

na ysesRequired

Ana ysisFreq.(b)

AirborneParticulates(AP)

AirborneIodine(c)

Sediment(SH)

FlocculatedSediment (SS)

Fish(FI)

Surface (d)Water(WT)

Well (ground) Water(WG)

Drinking( )Water

(PW)

10

10

SA

SA

SA

MC or M

Gross Beta (c)Gross AlphaGamma Spectrometry

I-131

Gross AlphaGross BetaGamma'pectrometry

Gross AlphaGross BetaGamma Spectrometry

F'rossBetaGamma Spectrometry(on edible portion)

Gross AlphaGross BetaI-131Gamma SpectrometryTritium

Gross AlphaGross BetaGamma SpectrometryTritium

Gross AlphaGross BetaI-131Gamma SpectrometryTr itium

QC

QC

W

SASASA

SASASA

SASA

M

M

M

M

M

Note: See footnotes at end of table.

TABLE. 1(Page 2 of 3)

Annual Analytical Schedule for theSusquehanna Steam Electric Station (PP8L)


Media 8 CodeNo. of SampleLocations Freq.(a)

AnalysesRequired

AnalysisFreq.(b)

Precipitation(WP)

10 QC Gross Alpa QGross Beta QGamma Spectrometry QTri tium Q

Cow Milk(M)

M, SM(f) Gross Beta-K-40I-131Gamma Spectrometry

SM, M

SM, M

SM, M

Food Products (g)(FD,FL,FV,FP,FR)Various Fruitsand Vegetables

Game(AG,AS,AW,AN) (g)

Poultryand Eggs(PO,E)

Soil(s)

Vegetation(VT)

18

10

10

Gamma Spectrometry A






TABLE 1(Page 3.of 3)

Annual Analytical Schedule for the'Susquehanna Steam'Electric Station (PP8L)


Media 8.Code0 ~ 0 amp e

Locations Freq.(a)na yses

Requiredna ysls

Freq.(b)

DirectRadiation(m)

Algae(VA)

911

TLDTLD

Gamma Spectrometry N

(a) W = weekly, N = monthly, SN = semi-monthly, g = quarterly, gC = quarterlycomposite, SA = semi-annually, A = annually, NC = monthly composite.

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

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

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

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

(f) 'Stations 12B2, 14B1, 10D1, 5E1, 13E3 and 10G1 are analyzed semi-monthlyfrom April through October.

(g) See Table 2, Page 8 of 8, for a complete definition of codes.

TABLE 2(Page 1 of 8),

Sample Locations and Media for the SSESRadiological Environmental Monitoring Program - 1988

LocationCode

Description Sample. Type

IND(

1S2

2S(c)2S22S32S42S6

-3S(')3S33S43S5

0.2 mile N, Perimeter Fence

NNE, SSES site location0. 9 mi 1 e NNE, Energy Informati on Center0.2 mile NNE, Perimeter Fence0.9 mile NNE, Energy Information Center0.9 mile NNE, Energy Information Center

NE, SSES0.9 mile0.3 mile0.9 mile

site locationNE, Recreational AreaNE, Perimeter FenceNE, Riverlands Security Office

I

0.9-1.4 mile ESW, at or below Discharge Structure FI

TQ

AG

AP,C,TQ,WP,TQS,VT

AS

TQTQWG

4S14S24S34S4

5S(')5S15S45S55S75SB

6S46S56S66S76SB6S9

1.0 mile0.5 mile0.2 mile0.5 mile

E, SSES,0.8 mile0.8 mile0.8 mile0.3 mile0.8 mile

0.2 mile0.9 mile0.8 mile0.4 mile0.2 mile0.2 mile

ENE, Susquehanna River Flood PlainENE, Site - Peach StandENE, Perimeter FenceENE, Training Center

site locationE, North of Biological ConsultantsE, West of Biological ConsultantsE, West of Biological ConsultantsE, Perimeter FenceE, Area under power line

ESE, Perimeter FenceESE, Outfall AreaESE, River water intake lineESE, Cooling tower blowdown discharge lineESE, Site Pole No. 44316/N34036ESE, Perimeter Fence (south)

TQWG

TQWG

AG

TQAP,C,TQ,WP,FRS,VTTQWT

TQWT

WT

WT

TQTQ

7S57S6 „

0.4 mile SE, REMP Garden0.2 mile SE, Perimeter Fence

FD

TQ

8S2

9S2

0.2

0.2

mile

mi1 e

SSE, Perimeter Fence

S, Security Fence TQ



Sample Locations and Media for the SSESRadiological Environmental Monitoring'Program - 1988

LocationCode

Description Sample Type

10S110S2

11S211S311S411S511S6

12S3

13S213S413S5

14S514S6

15S415S5

16S116S2

LTAW

AG3AG4

1A(')

6A4

7A17A2

BA3

15A3

0.4 mile SSW, Perimeter Fence0.2 mile SSW, Security Fence

0.4 mile SW, Golomb House (44016/N33986)0.3 mile SW, Security Fence0.4 mile SW, Golomb House0.5 mile WSW, EOF Building0.5 mile SW, SW REMP Garden

0.4 mile WSW, Perimeter Fence

0.4 mile W, Perimeter Fence)

d)0.4 mile W, Security Fence LLRWHF-south)d)0.4 mile W, Security Fence LLRWHF-north)

0.5 mile WNW, Site Pole No. 43996/N342300.7 mile WNW, Site Pole No. 43869/N34174,

0.6 mile NW, Transmission Line0.4 mile NW, Perimeter Fence

0.3 mile NNW, Perimeter Fence east)0.3 mile NNW, Perimeter Fence west)

Lake Took-a-while, NE to ESE on site

0.8 mile E, above River Water Intake - surface0.9 mile ESE, below Discharge Diffuser - surface

N, 0-1 miles off-site

0.6 mile ESE, former State Police

0.4 mile 'SE, Kline Residence0.6 mile SE Bell Bend Pole No. 44437/N33887

0.9 mile SSE, PPSL Wetlands Sign

0.9 mile NW, Serafin Farm

TQTQ

AP,C,TQ,WPTQS,VTWG

TQ

TQ

TQTQTQ

TQTW

AP,C,TQ,WP,S,VTTQ

TQTQ

WT,SH,FI

VAVA

AG

TQ

TQTQ

TQ

Note: See footnotes at end of tab e.

TABLE 2„(Page 3 of 8)


LocationCode

16A2

Description

II

0.8 mile NNW, Rupinski Farm

Sample Type

TQ

181

2B(')2832B4,

38

4Bl

5B2

6B2

7B(c)7B27B37B4

8828B3

9B19B29B3

10B210831084

128112B212B312B41285

13B1

1.4 miles N, Mingle Inn Road

1.6 miles NNE, Gould Island1.3 miles NNE, DuraBond Corporation1.4 miles NNE, DuraBond Corporation

NE, 1-2 miles off-site

1.2 miles ENE, Stone Crusher Trail

1.4 miles E, Pa. Route 239 Intersection

1.4 miles ESE, Wapwallopen

1.2 miles1.5 miles1.7 miles1.5 miles

1.4 miles1.5 miles

SE, Bell BendSE, Heller's OrchardSE, Council CupSE, Heller's Orchard Store

SSE, Lawall ResidenceSSE, Wapwallopen Post Office

1.3 miles1.7. miles2.0 miles1.7 miles1.8 miles

WSW, Kisner FarmWSW, Shultz FarmWSW, Young FarmWSW, Shultz FarmWSW, Intersection (Pole 0'43401/N33620)

1.3 miles W, Walker Run Creek

1.3 miles S, Transmission Line east of Route 111.3 miles S. Transmission Line east of Route 111.1 miles S, Campbell Residence

2.0 miles SSW, Algatt Residence1.7 miles SSW, General Tank Equip. Co.1.4 miles SSW, General Tank Equip. Co.

TQ

SH,SS,AGTQTQ

AG

TQ

TQ

TQ

SH,SSFR,FHTQTQ

TQTQ

AP,C,TQ,WPS,VTFL

TQTQTQ

E,FM

M

TQTQ

TQ



Sample Locations and Media for the SSESRadiological Environmental Monitor ing Program - 1988

LocationCode


1481

15B1

16B116B2

6C1

llcllcl

1.8 miles WNW, Stola Farm

1.7 miles NW, Mingle Inn Trailer'ark

1.6 miles1.7 miles

2.7 miles

NNW, Walton Power LineNNW, High Tension Lines

ESE, Moyer Farm'.6

miles SW, Hess Island2.0 miles SW, Salem Township Fire Company

M, TQ

TQ

TQTQ

SH

TQ

1D21D31D4

3D13D2

4.0 miles3.9 miles4.0 miles

3.4 miles3.4 miles

N, near Mocanaqua SubstationN, Mocanaqua BridgeN, near Mocanaqua Substation"

NE, Pond HillNE, Pond Hill

AP,C,TQ,WPWT

S, VT

AP,C,TQ,WPS,VT

8D3 4.0 mile, SSE Mowry Residence TQ

9D19D2

10Dl10D2

11D1

12D212D31204

3.6 miles3;2 miles

3.0 miles3.0 miles

3.3 miles

3.7 miles3.7 miles3.4 miles

S, Smith FarmS, Ryman's Farm Product

SSW, Ross Ryman FarmSSW, Ross Ryman Farm

SW, Zehner Farm

WSW,. Dagostin FarmWSW, Dagostin ResidenceWSW, Ber-View Farm

TQFD

M,POTQ

FD

TQF

1E1 4.5 miles N, Lane Residence TQ

4E1

5E(c)5E15E2

E, 4-5 miles off-site4.5 miles E, Bloss Farm4.5 miles E, Bloss Farm

AG

TQ

4.8 miles ENE, Ruckles Hill Rd. (Pole 046422/N35197) TQ

ote: See footnotes at end o tab e.



LocationCode


6E1

7E1

llE1

4.7 miles ESE, St. James Church

4.2 miles SE, Harwood Trans. Line Pole k2.

4. 7 mi 1 es SW, Shi fflett Res idence

TQ

TQ

TQ

12E112E212E4

13E313E4

14E1

2F(')

2F1

'3F13F2

7F1

8F2

10Fl10F2

llF1

12F( )

12F112F212F312F412F5

15F1

6.9 miles5.3 miles5.2 miles5.2 miles5.8 miles7.5 miles

WSW, Old Berwick Test TrackWSW, Berwick BridgeWSW, Berwick SubstationWSW, Berwick Water Co.WSW, Montgomery ResidenceWSW, Seesholtz Farm

5.4 miles NW, Zawatski Farm

4. 7 'miles WSW, Berwi ck Hospital„4.7 miles WSW, Berwick Hospital4.7 miles WSW, Berwick Hospital

5.0 miles W, Dent Farm4.1 miles W, Kessl er Farm

4.1 miles WNW, Canouse Farm

6.4 miles NNE, between Shickshinny and RetreatState Correctional Institution

5.9 miles NNE, St. Adalberts Cemeteryt

9. 1 miles NE, Valania Residence9.9 miles NE, Sheatown Intersection

6.7 miles SE, Burger Farm

8.5 miles SSE, Huff Residence

5.7 miles SSW, Miller Farm6.0 miles SSW, Karchner Farm

SW, 5-10 miles off-site5.6 miles SW, Mangan Residence

AP,C,TQ,WPS,VTWG

M

TQ

SH

TQ

TQTQ

FD

TQ.

FDFD

ASFD

SHWT

TQWG

FDFR

TQ



Sample Locations and Media for the SSESRadiological Environmental Monitoring Program — 1988

LocationCode


16F16Fl16F216F3

3G33G4

4G1

'Gl

7G2

10G1

NNW, 5-10 miles off-site7.8 miles NNW, Hidlay Residence7;8 miles NNW, Hidlay Residence8.5 miles NNW, Soya Residence

16 miles NE, WB Horton St. Substation17 miles NE, WB Service Center

14 miles ENE, Mountaintop - Industrial Park

14 miles SE, Hazleton Chem Lab12 miles SE, Hazleton (Pole 0'31852-H)

14 miles SSW, Davis Farm

AG

TQF

FD, AG

TQTQ

TQ

AP,C,TQ,WP,S,VTTQ

12G112G212G312G4

15 miles17 miles15 miles10 miles

WSW, PPSL Service Center, BloomsburgWSW, US Radium Site, BloomsburgWSW, PP8L Service Center, BloomsburgWSW, Naus Residence

AP,C,TQ,WPWT

S,VTTQ

13G1

2H(')2H1

12H112H2RAW12H2TREATED

PIC 1PIC 2,PIC 3PIC 4

13 miles W, Jacobsen Residence

30 miles NNE, near Falls, PA21 miles NNE, Yalicks Residence

26 miles WSW, Merck Co.26 miles WSW, Danville Water Co.26 miles WSW, Danville Water Co.

20 miles off-site

6.2 miles WSW, Berwick City Hall0.9 mile NNE, Energy Information Center4.2 miles N, Shickshinny Municipal Building10.7 miles NE, Nanticoke Municipal Building

FD,AS

FIF

WT

PW

PW

AG

TQTQTQTQ

Note: See footnotes at en o ta e.



Footnotes:

All distances measured from standby gas treatment vent at 44200/N34117(PA Grid System).

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

E

Station code is omitted because no permanent locations exist; samples aretaken based on availability.

Low Level Radwaste Holding Facility.(d)



Location Codes:

The location codes are based on direction and distance from the site. Thefirst two numbers identify the monitored sector. There are 16 sectors of 22.5degrees each, with their origin centered at the station release point. Sectorone in Figure 3 is divided evenly by a line heading true north from thestation release point. Sectors are numbered in a clockwise direction; i.e.,2=NNE, 3=NE, 4=ENE, etc. Following the first number is a letter whichrepresents the radial distance from the station. Locations within the siteboundary are designated with an S. Locations outside the site boundary aredesignated as follows:

A = 1 mile or lessB = 1-2 milesC = 2-3 milesD = 3-4 miles

E

F

G

H

= 4-5 mi 1 es= 5-10 miles= 10-20 miles= ~20 miles

(

The last number is the station numerical designation within each sector andzone, e.g., 1, 2, 3, .................Site is defined as that area within PPINL's property boundary.

Sam le T e Codes

AG = Animals(Game)AP = Air Particulate FiltersAS = Animals/SquirrelC = Charcoal FiltersE = EggsFD = Food/Garden CropsFH = Food/Garden Crops - HoneyFI = FishFL = Food/Garden Crops - Green Leafy Vegetables (cabbage, lettuce, spinach

swiss chard, etc.)FM = Feed and Forage - Milk Producers (pasture grass)FP = Food/Garden Crops - PotatoesFR = Food/Garden Crops - Fruit (apples, strawberries, melons)FV = Food/Garden Crops - Vegetables (sweet corn, green beans, tomatoes, spinach)M = MilkPO = PoultryPW = Potable WaterS = SoilSH = Sediment/Shoreline (0-4'f water)SS = Sediment/Silt (Floe)TQ = TLDVA = Vegetation - AquaticVT = Vegetation - TerrestrialWG = Water - Ground (Well)WP = Water - PrecipitationWT = Water - Surface

I

III

I

I

FIGURE 2

ON-SITE ENVIRONMENTALSAMPLING LOCATIONS - SSES

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Sei2s 282%1

~ 3$ 33$ 5

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F.,IGURE 3

Ol F SITE ENVIRONMENTAL SAMPLING LOCATIONS - SUS(UEHANNA SES

16M

(ZOJ al. Froe Site)

ZHL(tl e1. f Site)

WEST N

(30 4LL. from sita)

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1261112~~LZF3(15 c1. from site

1001

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tSl ~26 at. I+a.stle?LSfft(ts al. froa site)

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J'/ /rrr

IV. MONITORING METHODS

A. Ambient. Radiation

Thermoluminescent dosimeters (TLDs) were used to determine the

ambient radiation levels at ninety-two monitoring points as

described in Tables. 1 and 2. TLDs were retrieved quarterly and

processed.

The area around the station was divided into sixteen radial

sectors of 22;5 degrees each. TLDs were placed in all sectors.

Monitoring locations were chosen according to the criteria given

in the USNRC Branch Technical Position on Radiological Monitoring

(Revision 1, November 1979). The TLDs were placed at(17)

locations selected by considering local meteorological and

topographical characteristics and population distribution

characteristics. The control locations were 3G2, 3G3, 3G4, 4Gl,

7G1, 7G2, 12G1, and 12G4.

In 1988, direct radiation measurements were made using Panasonic

UD-801 TLDs containing crystals of calcium sulfate activated with

thulium.

B. Surface Water

Surface water was sampled from the Susquehanna River at eight

locations and Lake-Took-a-While (LTAW) adjacent to the River in

1988. Time proportional automatic composite samples were picked

up monthly at location 12H1 and picked up weekly at locations 6S6

=and 6S7. Monthly samples were also composited from weekly grab

samples at locations 5S8 and 6S5. Locations 5S8 and 6S5,

although routinely sampled, provide alternate data for locations

6S6 and 6S7, respectively, in the event that water can not be

obtained from the automatic samplers. Monthly grab samples were

collected at locations 1D3, 12Fl, 12G2, and LTAW. Locations 1D3,

5S8, and 6S5 were the control locations.

Surface water samples were analyzed monthly for gross alpha arid

beta activities, the activities of gamma-emitting radionucl ides,

and iodine-131 and tritium activities.

C. 'Drinking Water

Drinking water (RAW) samples were collected at location 12H2 by

means of a time proportional automatic composite sampler and

picked up weekly in 1988 from the Danville Municipal Water

Authority facility on the Susquehanna River. Daily grab samples

(TREATED) were also taken by Danville Municipal Water Authority

personnel, composited, and picked up weekly. RAW water is taken

directly from the Susquehanna River intake structure while

TREATED water is drawn from the supply line 'after processing.

The Danvi lie Municipal Water Authority facility is the closest

drinking water facility on the Susquehanna River downstream of

the SSES which could be affected by plant discharges.

Monthly composites of both the RAW and TREATED samples were

analyzed separately for gross alpha and beta activities, the

activities of gamma-emitting radionuclides, and iodine-131 and

tritium activities.

D. Algae

In 1988, algae samples were collected monthly from control

location AG3 and indicator location AG4. Algae is collected

passively by allowing the flow of Susquehanna River water to

deposit it on a plexiglass collector.

E. Fish

Fish sampling on the Susquehanna River was conducted in the

spring and the fall of 1988 at two'locations. An indicator

location IND downstream of the SSES and a control location 2H

upstream of the SSES were selected. Fish samples were also taken

by electrofishing 'from the, indicator location LTAW.

The fish were filleted and the edible portions were analyzed 'for

gross beta activity and the activity of gamma-emitting

radionuclides.

IV-3

F. Shoreline and Flocculated Sediment

Shoreline sediment (0 to 4 ft. of water) samples were collected

in June and December of 1988 at locations 2B, 7B, llC, 2F, and

12F on the Susquehanna River and at the LTAW location. Locations

2B and 2F are the control locations for sediment.

Flocculated sediment was also collected at locations 2B and 7B in

June 1988. Flocculated sediment is the top, loose layer of

sediment in the river, that is easily moved and shifted by the

water. Flocculated sediment is composed of finer particles than

the shoreline sediment.

All sediment samples are analyzed for gross alpha and beta

activities and the activities of gamma-emitting radionuclides.

G. Ground (Well) Water

Ground water was sampled monthly from wells at locations 2S6,

3S5, 4S2, 2S4, 11S5, 12E4, and 12F3. Location 12F3 is a control

location.

Ground water samples were analyzed for gross alpha and beta

activities, the activities of gamma-emitting radionuclides, and

tritium activity.

IV-4

H. Airborne Particulates and Air Iodine/Precipitation

Airborne pathways to man were examined by analyzing air

particulates, air iodine, and precipitation.

Airborne Particulates and Air Iodine

Air samples were collected in 1988 at locations 2S2, 5S4, 11S2,

15S4, 9B1, 1D2, 3Dl, 12El, 7Gl, and 12Gl. Locations 7G1 and 12G1

were the control 1 ocati ons.

Air particulates were collected on Gelman type-A/E, glass fiber

filters with low-volume air samplers. Air iodine samples were

collected with one-inch deep Science Applications, Inc. charcoal

cartridges in series with the air particulate filters at all

locations.

The air samplers were run continuously and the filters and

charcoal cartridges exchanged weekly. The elapsed time of

sampling was recorded on an elapsed-time meter. Air sample

volumes were measured with temperature-compensated dry-gas

meters.

Air filters were analyzed weekly for gross beta activity, then

composited quarterly and analyzed for gross alpha activity and

the. activities of gamma-emitting radionuclides. The charcoal

cartridges were analyzed weekly for iodine-131.

IV-5

Precipitation

Precipitation samples were collected at least monthly in 1988

from the same locations as airborne samples were obtained and

were composited'uarterly.

Precipitation was analyzed for gross alpha and beta activities,

the activities of gamma-emitting radionuclides, and tritium

acti vity.

I. Milk

Cow milk samples were collected in 1988 from locations 12B2,

12B3, 6Cl, lOD1, 12D2, 5E1, 13E3, 14Bl, and 10G1. Samples were

collected semi-monthly-from April through October at six of these

locations; otherwise, samples were collected monthly. Location

10G1 was a control location.

All samples were analyzed for gross beta minus potassium-40

activity, iodine-131 activity, and the activities of

gamma-emitting radionuclides.

J. Soil (top and bottom) and Vegetation

Soil (top and bottom) and vegetation samples were collected in

September 1988 at locations 2S4, 5S5, 11S4, 15S4, 9B2, 1D4, 302,

12E2, 7Gl, and 12G3. Locations 7G1 and 12G3 were control

locations.

IV-6

These samples were taken by compositing twelve plugs at each

location. The top soi 1 consists of the first two inches of soil,

and the bottom soi 1 is from a depth of two to six inches. These

'ampleswere analyzed for the activities of gamma-emitting

radionuclides.

K. Food Products

Various types of fruits and vegetables were collected in 1988

from eighteen locations within the vicinity of the SSES. These

locations are identified in Table 2. Location 2H1 was a control

location.

All fruit and vegetable samples were analyzed for the activities

of gamma-emitting radionuclides.

Poultry and Eggs

Duck and egg samples were collected in 1988 from locations lOD1

and 1281 respectively. The edible portions were analyzed for

the activities of gamma-emitting radionuclides.

Game

Deer, rabbit, woodchuck, and squirrel samples were collected

from August through November of 1988 at locations identified in

Table 2. The flesh'was analyzed for the activities of

gamma-emitting radionuclides.

IV-7

V. SUMMARY AND DISCUSSION OF 1988 ANALYTICALRESULTS

The analytical methods used by Teledyne Isotopes meet the lower limit of

detection (LLD) requirements set forth in the Susquehanna Steam Electric

Station Technical Specifications. The procedures, specifications and anJ

explanation of the analytical calculation methods used in the laboratory

for these analyses are summarized in Appendix B. Data from the

radiological analyses of environmental media are tabulated and discussed

bel ow.

Radiological analyses of environmental media characteristically approach

and frequently fall below the limits of state-of-the-art measurement

methods. for the gamma spectrometric results listed in this report,18

only those radionuclides positively detected are listed in the tables. A

positively'detected radionuclide is one in which the activity is greater

than a critical value. The critical value is equivalent to half the

LLD. However,'due to the presence of naturally-occurring radionuclides22

such as beryllium-7, potassium-40, radium-226, and thorium-228 in

background gamma spectrometric results, naturally-occurring radionuclides

are reported only if their levels exceed their LLDs. Typical LLDs of

selected radionuclides searched for by gamma spectrometry are listed inI

Table 20.

For analyses other than gamma spectrometry, ."LT" is used in the data

tables where activity was not positively detected. The use of "LT" in the-

data tables in Section XII is the equivalent of the less than symbol (< ).The number following "LT" is a result of calculation as defined in

Appendices B and C.

V-1

Tables 5 through 19 give the'adioanalytical results for individual

samples. ,A statistical summary of the results based only on positively

detected activities appears in Table 3.

A. AMBIENT RADIATION

Thermoluminescent dosimeters (TLDs) included in the Radiological

Environmental Monitoring Program (REMP) in 1988 were placed at 84

indicator locations and 8 control locations. Sixteen of these

locations were co-located with TLDs belonging to the Nuclear

Regulatory Commission. A description of PPSL's TLD system may be

.found in Appendix B.

Totals of 333 indicator TLD readings and 32 control TLD readings were

obtained from quarterly processings during 1988., The detailed

results of these TLD readings can be found in Table 5. The means of

quarterly TLD readings for 1988 are compared to the ranges and means

of the yearly average TLD readings at indicator and control locations

during the preoper ational and operational periods 1978-1981 and

. 1982-1987 respectively, in the Table below.

AMBIENT RADIATION LEYELS AS MEASURED BY TLDS (mR/STD TR

Location

Period

Indicator

~Pi 1 P~l

Control

~Pi 1 ~P

1978-81 , 1982-87 1988 1978-81 1982-87 1988

~Ren e

Mean 18.9 18.4 18.5 16.3 17.7

18.5-19.2 . 17.3-19.2 — 15.0-17.9 17.3-19.2

18.5

V-2

Refer to Figure 4 which trends both indicator and control quarterly

data from 1973 through 1988.

Oakley calculates an ionizing radiation dose equivalent of 8219

mrem/year from natural sources for the Wilkes-Barre area. Since

Oakley's values represent averages covering wide geographical areas,

the measured ambient radiation averages of 74 mrem/year for both

indicator and control locations in the vicinity of the SSES are

consistent with Oakley's observations. Significant variations occur

between geographical areas as a result of geological composition and

altitude differences. Temporal variations result from changes in

cosmic radiation intensity, local human activities, and factors such

as ground cover and soil moisture.

Pressurized Ion Chambers

In 1988, pressurized ion chamber (PIC) data were collected

continuously at locations in Berwick ( 12F4), Nanticoke (3G2),

Shickshinny (1E2), and at the Susquehanna Energy Information Center

(2S5). TLD data was also obtained at these locations. The two

monitoring methods agreed well enough to provide additional

corroboration of the ability of the PPSL TLD network to

satisfactorily monitor the ambient radiation levels in the vicinityof the SSES.

PIC measurements are currently recorded on paper strip charts that

are periodically reviewed and then archived. An improved collection

method for this data began in December, 1988. A Rustrak datalogger

has been connected to the output of the PIC at the EnergyV-3

l

ll'

I

50

FIGUR 4AMBIENTRADIATIONLEVELS

40 PREOPERATIONAL OPERATIONAL

~~ 30c25

20

UNlT 2 CRITlCALlTY

10

01973 - 1975

I

1977 1979 1981 1983 1985 1987 1989

indicator

control

Information Center. Data collected and stored by the datalogger for

durations of approximately one month are being retrieved and analyzed

using software developed especially for the datalogger. Plans are to

install similar dataloggers at the other PIC locations'in the future.

These dataloggers greatly enhance the ability to accurately process,

analyze, and report data obtained from the PICs as compared to the

use of the strip charts, for this pur pose. Data obtained from the

PICs using the dataloggers should permit more detailed comparisons of

PICs and TLDs in future annual REMP reports.

B. SURFACE WATER

Surface water was sampled monthly or composited monthly from nine

locations including three control locations. Samples were analyzed

for gross alpha, gross beta, iodine-131, tritium, and gamma emitting

radionuclides. A total of 109 surface water samples were analyzed.

Seventy-two indicator samples were collected'nd thirty-seven control

samples were obtained. The detailed results of these analyses can beI

found in Table 6.

No, surface water indicator or control samples analyzed for gross

alpha activity yielded positive values (above the lower limit of

detection or LLD) in 1988. LLDs for gross alpha analyses ranged from

0.5 to 2 pCi/1 in 1988. This may be compared to the ranges, means,

and medians of yearly average gross alpha activities at surface water

indicator and control locations during. the, period 1984 through 1987

in the table below.

V-5

SURFACE WATER GROSS ALPHA ACTIVITIES Ci/1

Location

Period

Indicator

1984-87 1988

Control

1984-87 1988

~Ran e

Mean*

1.8-4.3

2.8(2.6) LLD

*The numbers in parentheses to the right

the respective medians.

1.5-3.1

2.3(2.2) LLD

of the means are

Gross beta activity was positively detected in all samples from both

indicator and control locations, in 1988. The means of gross beta

activities in surface water for 1988 are compared to the ranges and

means (medians) of yearly average gross beta activities at indicator

and control locations during the preoperational and operational

periods 1978-1981 and 1982-1987 respectively in the table below.

SURFACE WATER GROSS BETA ACTIVITIES Ci/1

Location

Period

Indicator

~P" i 1 ~P

1978-81 1982-87 1988

Control

~0

1978-81 1982-87 1988

Ramae 3.2-4.9 3.0-7.7

Mean* (median) 3.8(3.6) 5.2(4.7) 6.0

2.9-5.2 2.9-4.8

4.0(3.9) 3.7(3.8) 3.7

The range of gross beta activities for indicator locations in 1988 is

within the range of activities for the previous operational period at

the SSES, 1982 through 1987. Refer to Figure 5 which trends gross

beta activities separately for surface water indicator and control

locations from 1975 through 1988.

V-6

raFIGUR

GROSS BETA ACTIVITYIN SURFACE WATER

20

18

16

PRE(PERATIONAL OPERATIONAL

12

Ld-I—10

0CL

UNIT 2 CRITICALITY

1975 1977I

1979 1981 1983I

1985I

1987 1989

I ndicator

Control

Results from indicator location 6S7, the cooling tower blowdown

discharge line sample point, are an indicator of the concentration of

the activity of the water that is periodically discharged to the

river. Since the activity at this sample location is not likely to

be representative of the activity in the river water more than a few

feet from the discharge pipe, it is of interest to compare the mean

activity of indicator locations excluding that of 6S7 in 1988 with

the mean gross beta activities at control locations during the

preoperational period 1978-81. The mean activity at the indicator'I

locations for 1988 in the table above becomes 4.0 and one can compare

this mean activity with the mean of yearly average gross beta

activity for the control locations during the preoperational period.

V

In 1988, strontium-89 and strontium-90 analyses were also performed

in seven out of twelve monthly samples from location 6S7. In each

case, no strontium-89 or strontium-90 was positively detected.

Strontium analyses are performed when gross, beta activities exceed 15

pCi/liter.

Iodine-131 was positively detected in surface water twice at each of

two indicator locations and twice at one control location during

1988. Detection at each of the three locations occurred in January

and July. The means of iodine-131 activities in surface water for

1988 are compared to the ranges and means (medians) of yearly average

iodine-131 activities at indicator and control locations during the

preoperational and operational periods 1979-1981 and 1982-1987

respectively in the table below.

V-8

SURFACE WATER IODINE-131 ACTIVITIES Ci/l

Location

Period Prep erational

1979-81

Indicator

0 erational

1982-87 1988

Control

~0

1979-81 1982-87 1988

~Ren e 0.24-0.37 0.17-0.60

Mean (median) 0.29(0.25) 0.35(0.26) 0.32

0.29-0.43 0.19-0.55

0.36(0.36) 0.32(0.24) 0.18

Note how the 1988 mean activity of the indicator locations compares

to the means of the control locations for the preoperational and

operational periods prior to 1988.

It should be noted that no iodine-131" was positively detected in any

6S7 (the coolin'g tower blowdown line to the Susquehanna River)

samples. In addition, analyses of samples of undiluted batches of

liquid radwaste prior to release to the blowdown line did not result

in any positive detections of iodine-131. The iodine-131 activityobserved in surface water cannot therefore be attributable to the

operation of the SSES. Alternate sources of iodine concentrations in

surface water are medical uses in the area.

Tritium was positively detected in 46 out of 72 indicator surface

water samples and in ll out of 36 control samples in 1988. The means

of tritium activities in surface water„for 1988 are compared to the

ranges and means (medians) of yearly average tritium activities at

indicator and control locations during the preoperational and

operational periods 1978-1981 and 1982-1987 respectively in the table

bel ow.

V-9

Location

SURFACE WATER TRITIUM ACTIVITIES Ci/l

Indicator Control


1978-81

~Ran e 101-122

Mean (median) 109(106)

0 erational

1982-87 1988

126-366

264(285) 341

1978-81 1982-87 1988

119-319 90-212

171(123) 141(132) 135

The tritium activities reported throughout 1988 at location 6S7, the

cooling tower blowdown discharge line, tend to inflate the mean'I

activity reported for all indicator locations just as the 6S7 gross .

beta activities inflated the mean indicator gross beta activity. Ifthe tritium activities from location 6S7 are excluded from the data

used to calculate the mean indicator tritium activity, the mean

indicator tritium activity becomes 152 pCi/liter. This value can be

compared to the range of mean tritium activities in control samples

for the pr eoperational period in the table. above. Refer to Figure 6

which trends tritium activities separately for surface water

indicator and control locations from 1972 through 1988.

In spite of the fact that the tritium activities reported for 6S7 are

from the discharge line prior to dilution in the river, the highest

tritium activity reported at 6S7 during 1988 is well below the NRC

non-routine reporting levels of 20,000 pCi/liter when a drinking

water pathway exists or 30,000 pCi/liter when no drinking water

pathway exists. The calculated. dose to the maximally exposed

individual-due to tritium and any other radionuclides identified in

the discharge pathway is presented in Section V-L.

Gamma spectrometry positively detected naturally-occurring

potassium-40 in 1 out of 72 indicator s'amples and 2 out of 36 control

samples. The means of potassium-40 activities in surface water for

1988 are compared to the ranges and means of yearly average

potassium-40 activities at indicator and control locations during the

operational period 1983-1987 in the table below.

SURFACE WATER POTASSIUM-40 ACTIVITIES Ci/1

Location Indicator Control

Period

Ran<ac

Mean 36 34

1983-87 1988

15-57 24-49

33 4.2

1983-87 1988

In 1983 and 1984., potassium-40 activity was below the lower limit of

detection in all indicator and control samples. Since 1983,

potassium-40 has been reported in 15 indicator samples and 10 control

samples.

The anthropogenic radionuclide cesium-137 was also positively

detected in 1 out of 72 indicator samples and 2 out of 36 control

samples. The means of cesium-137 activities in surface water for1988 are compared to the ranges and means of yearly average

cesium-137 activities at indicator and control locations during the

operational period 1983-1987 in the table below.

WP' I

FIGUR'RITIUMACTIVITYIN SURFACE WATER

2000

1800

1600

PREOPERATIONAL OPERATIONAL

1400,

1200CL

I—1000

OCL

800

UNIT 2 CRITICALITY

600

400

200

0,1972 1974

I I I I I I I I I I I

1976 1978 1980 1982 1984 1986 1988

I ndicator

Control

I

I

1

~

gi

~

I

Location

Period

~Ran e

Mean 4.6 3.0

SURFACE WATER CESIUM-137 ACTIVITIES Ci/l

Indicator

1983-87 1988

4.5-4.6

3.3 4.0

Control

1983-87 1988

2.7-4.0

In 1983 and 1984 cesium-137 was below the lower limit of detection in

all indicator and control samples. Since 1983, cesium-137 has been

reported in 6 indicator samples and 12 control samples. Cesium-137

is attributed to fallout from previous atmospheric nuclear weapons

testing and the Chernobyl incident.

The only two anthropogenic gamma-emitting radionuclides which were

positively detected in surface water in 1988 that are attributable to

the SSES operation were chromium-51 and manganese-54. These

radionuclides were each positively detected once in 1988 at the

indicator location 6S7 (the cooling tower blowdown line to the

Susquehanna River).

GAMMA-EMITTINGRADIONUCLIDES IN SURFACE WATER ATTRIBUTABLE TO THE SSES

OPERATION Ci/1

Radionuclide

Period

Chromium-51

Manganese-54

~Ran e

1983-87

22-130

3.8-4.5

79

12

8.6

1.3

Mean

1983-87 1988

Since 1983, chromium-51 has been reported in 10 samples and

manganese-54 has been reported in 19 samples.

The calculated dose to the maximally exposed individual due to

radionuclides resulting from the SSES operation is presented in

SectionV-L.'.

DRINKING WATER

Twenty-six drinking water samples were analyzed during 1988 from the

Danville Water Company's facility 26 miles WSW of SSES on the

Susquehanna River. The detailed results of the analyses of the

samples can be found in Table 7.

Fourteen of the drinking water samples were taken prior to treatment

of the water. These are referred to as the raw water samples. The

remainder of the samples were taken after treatment and are referred

to as the treated water samples.

From 1977 (when drinking water samples were first collected) through

1984, drinking water samples were also obtained from the Berwick

Water Company at location 12F2 ( 12F3), 5.2 miles WSW of SSES. The

drinking water supply for the Berwick Water Company is not, however,

water from the Susquehanna River; it is actually well water.

Since there are no drinking water supplies on the Susquehanna River

upstream of the SSES that would be appropriate to serve as a control

location, the Oanville drinking water samples may be compared to

surface water control samples.

V-14

Gross alpha activity has been monitored in drinking water since 1980.

Alpha activity was positively detected in .only one non-routine (grab)

drinking water sample in 1988. This was a 12H2 RAW (untreated)

sample. The corresponding routine 12H2 TREATED water sample for this

period showed no positive result for gross alpha activity. Since

1980, alpha has been observed each'year in a small minority of these

samples except for the years 1981 and, 1987 when no samples yielded

any alpha activity above the lower limit of detection. Gross alpha

activity was not found in any surface water control samples in 1988.

The mean of gross alpha activity in drinking water for 1988 is

compared to the range and means (medians) of yearly average gross

alpha activities during the preoperational and operational periods

1980-1981 and 1982-1987, respectively in the table below.

DRINKING WATER GROSS ALPHA ACTIVITIES Ci/l

Period Prep erational 0 erational

~Ran e

Mean (median)

1980-81

1.3

1982-87 1988

1.2 - 10.0

3.3 (1.6) 5.3

Gross beta activity*was detected in all 26 drinking water samples in

1988. The mean of gross beta activity in drinking water for 1988 is

compared to the ranges and means of yearly average gross beta

activities during the preoperational and operational periods

1977-1981 and 1982-1987 respectively in the table below.

V-15

DRINKING WATER GROSS BETA ACTIVITIES Ci/1

Period

~Ren e

Mean (median)

Prep erational

1977-81

2.2 - 3.2

2.7 (2.6)

0 erational

2.4 - 5.4

3.4 (3.1) 3.9

1982-87 1988

It should be noted that the average drinking water gross beta

activity in 1988 was elevated by a gross beta activity of 16 pCi/1

reported in a 12H2 Raw grab sample from November. This sample was

taken due to problems with the automatic composite sampler. It also

should be noted that the average drinking water gross beta activityin 1988 is less than the mean gross beta activities of surface water

control locations during the preoperational period of the SSES.

Refer to Figure 7 which trends gross beta activities in drinking

water samples from 1977 through 1988.

The gross beta activities in drinking water samples for 1988 are not

attributable to the operation of the SSES.

Strontium-89 and strontium-90 analyses were performed on one grab

sample from 12H2 Raw collected in November 1988. No strontium-89 or

strontium-90 was positively detected. These analyses were performed

because the gross beta activity of the November grab sample exceeded

15 pCi/1.

No iodine-131 was detected in drinking water samples for 1988. This

is the same result that was.,obtained for 1985, 1986, and 1987. Since

FIGUGROSS BETA ACTIVITYIN DRINKING WATER

10


6

OCL UNIT 8 CRITICALITY

1 I I I I I I

1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989

l

II

I

I

I

1980, iodine-131 has only been detected in drinking water four years

out of nine years.

Tritium was positively detected in 8 out of 26 samples in 1988. The

mean of tritium activity in drinking water for 1988 is compared to

the ranges and means of yearly average tritium activities during the



DRINKING WATER TRITIUM ACTIVITIES Ci/1


1977-81

0 erational

1982-87 1988

~Ran e 101 - 194

Mean (median) 132 (120)

83 - 220

133 (117) 94

Note that the average drinking water tritium activity in 1988 is less

than the mean of the yearly average drinking water tritium activities

during the preoperational period of the SSES.. It also should be

noted that the average drinking water tritium activity in 1988 is

less than the mean tritium activities of surface water control

locations during both preoperational and operational periods of the

SSES.

The tritium activities in drinking water samples for 1988 are not

attributable to the operation of the SSES.

V-18

The only gamma-emitting radionuclides positively detected in drinking

water samples in 1988 were the naturally-occurring potassium-40 and

the anthropogenic cesium-137. Potassium-40 was detected at an

activity of 76 pCi/1 in one grab sample in November 1988. Since

1980, potassium-40 has only been reported, previously in 1985 and 1986

at activities of 43 and 56 pCi/1, respectively.

Cesium-137 was found once in December's raw water sample. Cesium-137

has only been reported in drinking water in two other years, once

each in 1985 and 1986. The cesium-137 activity, 3.7 pCi/1, in the

1988 sample exceeded the activities reported in 1985 and 1986, 2.9

and 3.4 pCi/1, respectively. It should be noted, however, that the

1988 cesium-137 activity reported is less than the mean cesium-137

activity reported for surface water control locations in 1988.

The cesium-137 activity in drinking water is not attributed to the

operation of the SSES.. This activity results from the fallout of

previous atmospheric nuclear weapons tests.

D. ALGAE

A total of 14 algae samples were collected from May through November

of 1988 at two locations on the Susquehanna River. Half of the

samples were collected at the indicator location AG4 below the SSES

discharge diffuser and the other half of the samples were obtained at

the control location AG3 above the SSES river water intake structure.

The algae samples were analyzed by gamma spectrometry. The detailed

results of the analyses of these samples can be found in Table 8.

The naturally-occurring radionucl ides beryllium-7, potassium-40,

thorium-228, and radium-226 were positively detected in algae samples

in 1988. With the exception of beryllium-7, which is cosmogenic in

origin (produced by the interaction of cosmic radiation in the

atmosphere), these radionuclides are terrestrial in origin (found in

the earth's crust).

Beryllium-7 was positively detected in 6 out of 7 indicator samples

and in 6 out of 7 control samples in 1988. The means of beryllium-7

activities in algae for 1988 are compared to the'anges and means

(medians) of yearly average beryllium-7 activities at indicator and

control locations during the period 1984 through 1987 in the table

below.

ALGAE BERYLLIUM-7 ACTIVITIES Ci/ dr

Location

Period

Indicator

1984-87 1988 1984-87

Control

1988

~Ran e

Mean (median)

5.2 - 20.7

9.7 (6.4)

5.6 - 18.9

4.1 9.7 (7.1) 4.3

Potassium-40 was positively detected in all indicator and control

algae samples in 1988. The means of potassium-40 activities in algae

for 1988 are compared to the ranges and means (medians) of yearly

average potassium-40 activities at indicator and control locations

during the period 1984 through 1987 in the table below.

V-20

ALGAE POTASSIUM-40 ACTIVITIES Ci/ dr

Location

Period

~Ran e

Mean (median)

Indicator Control

1984-87

12.1 - 89.7

33.0 (15.9)

1988 1984-87

10.6 - 80.8

12.0 30.6 (15.6)

1988

13.5

Thorium-228 was positively detected in 4 out of 7 indicator, algae

samples and in 4 out of 7 control algae samples in 1988. The means

of thorium-228 activities in algae for 1988 are compared to the

ranges and means (medians) of yearly average thorium-228 activitiesat indicator and control locations during the period 1985-1987 in the

table below.

Location

ALGAE THORIUM-228 ACTIVITIES Ci dr

Indicator Control

Period

Ran<ac

Mean (median)

1985-87

0.9 - 1.4

1.2 (1.2)

'1988 1985-87

1.1 - 1.2

1.2 (1.2)

1988

1.0

Radium-226 was positively detected in 1 out of 7 indicator algae

samples and in 2 out of 7 control algae samples in 1988. The means

of radium-226 activities in algae for 1988 are compared to the ranges

and means (medians) of yearly average radium-226 activities ate

indicator and control locations during the period 1985-1987 in the

table bel ow.

V-21

ALGAE RADIUM-226 ACTIVITIES Ci/ . dr

Location

Period

~Ran e

Mean (median)

ControlIndicator

1985-87

3.2 - 7.1

5.3 (5.6)

1988 1985-87

3.1 - 6.3

3.2 4.7 (4.7)

1988

3.6

None of the activity of the naturally-occurring radionuclides is

attributable to the SSES operation.,

The fission-product radionuclides cesium-137 and iodine-131 were

positively detected in algae in 1988. Iodine-131 was detected in 5

out of 7 control samples and 3 out of 7 indicator samples in 1988.

Iodine-131 has been positively detected in a portion (typically less

than half) of both indicator and control samples each year from 1984

through 1988. The means of iodine-131 activities in algae for 1988

are compared to the ranges and means (medians) of yearly average

iodine-131 activities at indicator and control locations during the

period 1984 through 1987 in the table below.

Location,

ALGAE IODINE-131 ACTIVITIES Ci/ dr )

Indicator Control

Period

Ra~cae

Mean (median)

1984-87

0.55 - 1.32

,0.99 (1.10)

1988 1984-87

0.70 - 1.10

0.75 1.10 (1.'30)

1988

0.44

As in past years, the presence of iodine-131 in algae does not appear

to be from the SSES operation, but from medical sources upstream of

V-22

the SSES. With the exception of 1984, iodine-131 has been found more

times in control algae samples each year than it has been found in

indicator algae samples.

Cesium-137 was detected in 2 out of 7 control algae samples, and itwas found in 1 out of 7 indicator algae samples in 1988. The means

I

of cesium-137 activities in algae for 1988 are compared to the ranges

and means (medians) of yearly average cesium-137 activities at algae

indicator and control locations during the period 1984 through 1987

in the table below.

ALGAE CESIUM-137 ACTIVITIES Ci/ dr


Period 1984-87 1988 1984-87 1988

~Ran e

Mean (median)

0.19 - 0.48

0.32 (0.31)

0.22 - 0.82

0.18 0.43 (0.34) 0.13

Cesium-137 in the environment comes from'fallout resulting from past

atmospheric nuclear weapons tests. As algae data continues to be

accumulated, assuming that atmospheric nuclear testing is not

resumed, a decline in cesium-137 activity should eventually be

observed. No trend in cesium-137 activities in algae since 1984 has

yet been apparent.

The activation-product radionuclide manganese-54 was seen in two

indicator algae samples in 1988. (It should be noted that

manganese-54 also was observed in a surface water sample from the

cooling tower blowdown line to the Susquehanna River.) The mean of

V-23

manganese-54 activity in algae for the indicator loc'ation in 1988 is

compared to the range and mean (median) of yearly average.

manganese-54 activities for the period 1984-87 in the table below.

Note that manganese-54 has never been detected in any algae control

samples.

ALGAE MANGANESE-54 ACTIVITY Ci/ dr

Period 1984-87 1988

Rancae 0.55 - 2.00

Mean (median) 1.07 (0.65) 0.46

The manganese-54 observed in algae is attributable to the SSES

operation.

E. FISH

A total of four different species of fish were collected at three

different locations during April, May, June and November 1988. The

species included smallmouth bass, largemouth bass, channel catfish

and white sucker. The largemouth bass was obtained from

Lake-Took-a-While (LTAW) located on PPSL property on the opposite

side of Route 11 from the station. LTAW is considered an indicator

location even though it does not receive flow from the Susquehanna

River below the SSES cooling tower blowdown line to the river. The

smallmouth bass, channel catfish and white sucker were all obtained

from the Susquehanna River at a control location 30 miles NNE near

Falls, Pennsylvania and at an indicator location between 0.9 and 1.4

miles ESE of the site, at or below the discharge structure. The

detailed results of these analyses can be found in Table 9.V-24

As in every fish sample taken since the Spring of 1984, when gross

beta analyses first began to be performed on fish flesh, all 9

indicator samples and all 6 control samples showed gross beta

activity above the lower limit of detection (LLD). The means of

gross beta activities in fish for 1988 are compared to the ranges and

means (medians) of yearly average gross beta activities at indicator

and control locations during the period 1984-1987 in the table below.

FISH GROSS BETA ACTIVITIES Ci/ wet


Period 1984-87

~Ran e 3.7 - 5.6

Mean (median) 4.8 (4.9)

1988

5.1

1984-87

2.2 - 6.8

4.8 (5.0)

1988

5.2

Note that the control mean of gross beta activities in fish exceeds

the indicator mean for 1988 in the table above, and both the control

and indicator means for 1988 are within the ranges of previous means

at those locations. The difference between the control and indicator

means in the table above does not appear to be significant, however,

when the uncertainties associated'with each of the means is

considered.

The gross beta activities in fish for 1988 are not attributable to

the SSES operation.

- Gamma spectrometry of fish in 1988 did not positively detect anyf

gamma-emitting radionuclides except for potassium-40 and cesium-137.t

Naturally-occurring potassium-40 was positively detected in all

V-25

indicator and control samples. The means of potassium-40 activities

in fish for 1988 are compared to the ranges and means of yearly

average potassium-40 activities at indicator and control locations

during the preoperational and operational periods 1977-1981 and

1982-1987 respectively in the table below.

Location

FISH POTASSIUM-40 ACTIVITIES Ci/ wet

Indicator Control


1977-81

Ran<ac 2.7 - 3.5


0 erational

1982-87 1988

Prep erational

1977-81

3.1 - 3.9 2.8 - 3.6

3.5 (3.6) 4.2 '.2 (3.4)

0 erational

1982-87 1988

3.1 - 4.0

3.6 (3.6) 3.7

Note that the means of the potassium-40 activities for the

preoperational period and the operational period prior to 1988 are

essentially identical. The indicator mean potassium-40 activity for

1988 exceeds both the range of yearly average potassium-40 activities

for the prior operational years as well as the control mean gross

beta activity for 1988. Considering the uncertainties associated

with the means in the table above, however, the differences do not

appear to be significant.

By comparison to the potassium-40 activities, the cesium-137

activities appear very small, roughly two orders of magnitude

smaller. Cesium-137 was positively detected in 6 out of 9 indicator

samples and in 3 out of 6 control samples. The means of cesium-137

activities in fish for 1988 are compared to the ranges and means of

yearly average cesium-137 activities at indicator and control

V-26

locations during the preoperational and operational periods 1977-1981

and 1982-1987 respectively in the table below.

FISH CESIUM-137 ACTIVITIES Ci/ wet



1977-81

0 erational

1982-87 1988

Prep erational

1977-81

~tl

1982-87 1988

~Ren e .010 - .042 .010 - .020 .012 - .016

Mean (median) .021 (.016) .014 (.012) .014 .013 (.012)

.006 - .015

.010 (.010) .011

Note that the highest mean of cesium-137 activities in the table

above is from the preoperational period at the indicator locations.

Once again, the differences in the means of gross beta activities in

the table above are not considered to be significant when the

uncertainties in these means are taken into account.

As in all other environmental media monitored, the sour ce of the

cesium-137 activity detected during 1988 is the residual fallout from


F. SHORELINE AND FLOCCULATED SEDIMENT

Shoreline sediment was sampled in June and December 1988 at four

indicator locations and two control locations. The sediment was

analyzed for gross alpha activity, gross beta activity, and the

activity of gamma-emitting radionuclides. The detailed results of

these analyses can be found in Table 10.

V-27

Gross alpha activities in sediment have been determined every yearT

since 1982. Gross alpha activity was positively detected in 8 out of

8 indicator samples and 4 out of 4 control samples in 1988. The

means of, gross alpha activities in sediment for 1988 are compared to

the ranges and means (medians) of yearly average gross alpha

activiti'es at indicator and control locations during the period 1982

through 1987 in the table below.

SEDIMENT GROSS ALPHA ACTIVITIES Ci/ dr


Period 1982-87 1988 1982-87 1988

~Ren e

Mean (median)

6.0 -,14.6

10.0 (9.8) '3.55.7 - 13.0

10.3 (10.9) 13.0

Note that the means of the gross alpha activities at both the

indicator and control locations in 1988 are within the ranges of the

means of the yearly average gross alpha activities at those locations

for the prior period of the SSES operation.

Gross beta'nalyses have been performed on sediment every year since

1984. Gross beta activity has been positively detected in all

indicator and control sediment samples since 1984. The means of'rossbeta activities in sediment for 1988 are compared to the ranges

and means (medians) of yearly average gross beta activities at

indicator and control locations during the period 1984 through 1987

in the table below.

V-28

Location

SEDIMENT GROSS BETA ACTIVITIES Ci/ dr

Indica tor Control

Period

Rancae

Mean (median)

1984-87

19.7 - 31.0

25.4 (25.4)

1988 1984-87

20.5 - 30.0

35.5 26.3 (27.4)

1988

33.0

Note that the means of the gross beta activities for both indicator

and control locations in 1988 are outside the ranges of the yearly

average gross beta activities at those locations during the previous

operational years when gross beta activity was monitored. It should

be pointed out that, when the variability of the gross beta activityin sediment is considered, the differences between the indicator and

control activities in 1988 or any of the other years appears to be

insignificant. However, there is the suggestion of a possible upward

trend in the gross beta activities at both the indicator and control

locations since it first began to be monitored.

Gamma spectrometry, in 1988 identified the following

naturally-occurring radionuclides in sediment at levels above their

lower limits of detection: beryllium-7, potassium-40, thorium-228,

and radium-226. With the exception of beryllium-7, which was

detected in 5 out of 8 indicator samples and 3 out of 4 control

samples, the other three radionuclides were found in every indicator

and control sample in 1988.

The means of the activities of beryllium-7, potassium-40,

thorium-228, and radium-226 in sediment for 1988 are compared to the

corresponding ranges and means of the yearly average activities of

V-29

these radionuclides at indicator and control locations during the


respectively in the tables below.

SEDIMENT BERYLLIUM-7 ACTIVITIES Ci/ dr


P ddt1978-81

~Ran e 0.4 - 0.6

0 erational

1982-87 1988

0.7 - 2.7 '.6Mean (median)0.9 (0.5) 1.5 ( 1.0)

~P

1978-81

0.3 - 0.4

0.4 (0.4)

0 erational

1982-87 1988

0.4 - 0.8

0.6 (0.6) 1.7

SEDIMENT POTASSIUM-40 ACTIVITIES Ci/ dr


P ddt 0 erational Prep erational 0 erational

1978-81 1982-87 1988 1978-81 1982-87 1988

~Ran e 8.6 - 10.4 7.6 - 13.2

Mean (median)9.3 (9.1) 10. 1 (9.7) 11.2

7.5 - 11.0 8.7 - 12.5

9.4 (9.5) 10.7 (10.7) 10.8

SEDIMENT THORIUM-228 ACTIVITIES Ci/ dr

Location

Period

Ran<ac

Indicator

1984-87

1.1 - 1.3

1988


1984-87

1.2 - 1.4

1.3 (1.3)

Control'988

It should be noted that prior to 1984 (except for 1982) thorium-232

activities were reported instead of thorium-228 activities. The

reported thorium-232 activities, as a whole, for the period 1974

through 1983 tended to be lower than the thorium-228 activities

reported in the last five years.V-30

SEDIMENT RADIUM-226 ACTIVITIES Ci/ dr


P 1 d ~P "1 1 0~ii ~i" 1 ~di 1'

1978-81 1982-87 1988 1978-81 1982-87 1988

~Ran e 0. 5 - 0. 7 0. 6 - 1. 9 — 0. 6 - 1. 9 0. 7 - 2. 1 —gMean (median) 0.6 (0.7) 1.3 (le4) 1.7 0.7 (0.7) 1.5 (1.7) 1.7

Cesium-137 was detected in 6 out of 8 indicator samples and allcontrol samples. The means of cesium-137 activities in sediment for

d





Location

SEDIMENT CESIUM-137 ACTIVITIES Ci/ dr )

Indicator Control

P 1 d ~ddi 1 ~d

1978-81 1982-87 1988

~Ran e 0.08 - 0.15 0.07 - 0.15

Mean (median) 0.10 (0.09) 0.11 (0.11) 0.17

~di 1 d~i1978-81 1982-87

0.08 — 0.21 0.09 - 0.21

0.13 (0.11) 0.15 (0.15)

1988

0.10

Note that, although the mean cesium-137 activity at the indicator

locations for 1988 exceeds the ranges at the indicator locations forboth the preoperational and prior operational periods, the activityis within the ranges of the means for both the preoperational and

operational. periods at the control locations.

V-31

The cesium-137 activities in sediment are the result of fallout from

previous atmospheric nuclear weapons tests. The cesium-137 activity

in sediment is not attributed to the SSES operations.

Manganese-54 was detected in one indicator sample at an activity of

0.04 pCi/g (dry). Manganese-54 has,been detected previously in

indicator samples in 1978, 1985, and 1987. The manganese-54 activityfound in 1988 is within the range (0.02 to 0.29 pCi/g dry) of

previously detected activities. The manganese-54 detected in the one

sediment sample in 1988 is attributable to the operation of the SSES.

Flocculated sediment (floe) samples have been being collected on a

trial basis since 1986 at one control'ocation and one indicator

location on the Susquehanna River. Floe is the top, loose layer of

sediment in the river that is easily moved and shifted by the water.

It is thought that perhaps material carried by the water might be

transferred most readily to this floe. The limited data collected in

1986, 1987, and 1988 do not point to the appearance of radionucli des

in the floe that haven't also been identified in the underlying

sediment.

G. GROUND WATER

Ground water was sampled monthly at seven locations in 1988,

including one control location. A total of 67 indicator samples and

12 control samples were collected. The detailed results of the

analyses of these samples can be obseryed in Table 11.

" V-32

Gross alpha activity has been analyzed in ground water since 1980.

It is usually positively detected in a small number of samples

limit of detection (LLD) in only 1 out of 67 indicator samples, and

it was not greater than the LLD in any control samples. As in 1987,

the gross alpha activity was positively detected only at location

4S2. The means of gross alpha activities in ground water for 1988

are compared to the ranges and means (medians) of yearly average

gross alpha activities at indicator and control locations during the



lannually. In 1988, gross alpha activity was detected above the lower

Pl L

Location

GROUND WATER GROSS ALPHA ACTIVITIES Ci/1

Indicator Control - IPeriod ~Pi 1 ~P

1980-81 1982-87 1988

~Ren e 1.5 - 4.0

Mean (median) 2. 1 (2. 1) 2.4 (2.0) 4.5

1980-81

LLD

LLD

~P

1982-87 19

1.2 - 2.7 LLD

1.8 (1.4) LLD

Gross beta activity has been analyzed in ground water since 1977. Itis positively detected in a majority of samples every year. In 1988,

gross beta activity was positively detected in 48 out of 67 indicator

samples and it was found above the LLD in all 12 control samples. As

was the case with gross alpha activity, the location with the highest

gross beta activity is the indicator location 4S2. The means of

gross beta activities in ground water for 1988 are compared to the

ranges and means (medians) of yearly average gross beta activities at


V-33 '


bel ow.

GROUND WATER GROSS BETA ACTIVITIES Ci/1


Period Prep erational 0 erational Prep erational 0 erational

1980-81

~Rae e 3.2 - 3.4

1982-87 1988

1.8 - 2.5

1980-81

1.9 - 3.0

2.3 2.5 (2.5)Yean (median) 3.3 (3.3) 2.7 (2.5)

1.8 - 2.5

2.2 (2.2) 2.2

1982-87 1988

It is interesting to note that the means of gross beta activities at

both indicator and control locations for the operational period are

lower than their corresponding means during the preoperational

period.

The gross beta activity in ground water is not attributable to the

SSES operation.

Tritium activity has been positively detected in some ground water

samples every year from 1972 through 1988. In 1988, tritium was

positively detected in 28 out of 67 indicator samples and in 5 out of

12 control samples. The means of tritium activities in ground water


average tritium activities at indicator and control locations during

the 'preoperational and operational periods 1980-1981 and 1982-1987


'lt-34

Location

Period

~Ran e

Mean (median)

i�~Pi1O

1982-87 1988

105 - 260

117

ControlIndicator

Prep erational

1980-81

117 - 119

~Pi 1 ~0

1980-81 1982-87 '98893 - 109 98 - 180

101 (101) .125 (112) 104 118 (118) 155 (123)

GROUND WATER TRITIUM"ACTIVITIES Ci/1

Note that for both preoperational and operational periods the means

of .tritium activities at the control locations exceed those at the

indicator locations.

Gamma spectrometry of ground water has yielded few positively

detected radionuclides since it was begun in 1979. The naturally

occurring radionuclides potassium-40 and thorium-228 have been

occasionally detected in ground water samples. Potassium-40 was

found in 1979, 1981, and 1985. Thorium-228 was observed in 1985 and

1986. No naturally-occurring radionuclides were positively detected/

in ground water in 1988.

Cesium-137 was positively detected once in 1988, in September samples

at each of two locations, control location 12F3 and indicator

location 4S2.

GROUND WATER CESIUM-137 activities Ci/1

Location

Period

Indicator

~PPP i 10~001 i " 10~PPi " P

Control

0 erational

1980-81 1982-87 1988 1980-81

~Ran e

Mean (median)

LLD

LLD

'.0 - 4.3

3.7 (3.7)

LLD

4.6 LLD

LLD — iLLD 2

V-35

Cesium-137 activity is attributed to the fallout from previous

atmospheric nuclear weapons tests.

H. AIR PARTICULATE

The results of a total of 519 routine air samples collected at 10

locations during 1988 are included in this report. 415 samples were

collected at 8 indicator locations and 104 samples were collected at

2 control locations. The detailed results of these analyses can be

found in Tables 12 and 13.

Air particulate filters were collected weekly and analyzed

individually for gross beta activity. quarterly,, the particulate

filters were composited and analyzed for gross alpha activity and the

activity of specific radionuclides identified by gamma spectrometry.

Gross beta activity was positively detected in all 519 weekly

samples, which includes both indicators and controls. The mean of

gross beta activities in air samples in 1988 is compared to the range

and mean (median) of yearly average gross beta activities at

indicator and control locations'uring the preoperational and


below.

V-36

AIR PARTICULATE GROSS BETA ACTIVITIES E-3 Ci/m

Location

Period

Indicator

~Pi 1 ~tl

Control

1978-81 1982-87 1988

~Ran e 24 - 97 13 - 29

Mean (median) 61 (62) 18 (16) 17

1978-81 1982-87 1988

24 - 102 12 - 28

62 (61) ; 17 (16) 17

The yearly average of 97 E-3 pCi/m3 was obtained twice for the

indicator locations in the preoperational years 1978 and 1981. Since

1981, the highest gross beta activity occurred in 1986 due to the

Chernobyl incident. Prior to this, the unusually high gross beta

activities may generally be attributed to fallout from atmospheric

nuclear weapons tests. Refer to Figure 8 which trends gross beta

activity in air particulates separately for indicators and controls

from 1974 through 1988.

Gross alpha activity was positively detected in all quarterly

indicator analyses and control analyses in 1988. The range and mean

of gross alpha activities at both indicator and control locations in

1988 is compared to the range and mean (median) of yearly average

gross alpha activities at indicator and control locations durihg the



V-37

GROSS BETA ACTIVITYI

W W WPARTICULATES

500

450

400 PREOPE RATIONAL OPERATIONAL

CHINESE WEAPON TESTX —6/17/74B —9/26/76C —11 17 763 —9 1777E —3/14/78F —10 15 80

350

300

C3CL 250

D200I

150 UNIT 2 CRITICALITY

100

50

0,1974 1976 1978

I

1980I

1982I

1984I

1986I

1988

indicator.

control

I

II

IIII

I

I

AIR PARTICULATE GROSS ALPHA ACTIVITIES E-3

Ci/m'ocation

Indicator Control

Period ~Pi 1 a~i ~Pi 1 ~D

1980-81 1982-87 1988

~Ren e 2.8-3.1 3.3-6.8

Mean (median) 3.0(3.0) 4.5(3.7) 2.4

1980-1981

2.2-3.5

2.9(2.9)

1982-87 1988

2.9-9.0

4.6(3.9) 2.5

The yearly average gross alpha activities in air samples in 1988 are

not appreciably different from those reported during the

preoperational years 1980 and 1981. It might also be noted that no

correlation is obvious between high gross beta activities and high

gross alpha activities in air. Refer to Figure 9 trending gross

alpha activity in air particulates separately for indicators and

controls from 1980 through 1987.

Gamma-emitting radionuclides are monitored in quarterly composite

samples. Gamma spectrometry positively detected only two

naturally-occurring r'adionuclides, beryllium-7 and potassium-40, in

air samples in 1988. No anthropogenic (man-made) radionuclides were

positively detected. Beryllium-7 was found in all quarterly analyses

of indicator and control samples in 1988. The mean of activities for

indicator and control locations in 1988 is compared to the range and

mean (median) of beryllium-7 yearly average activities at indicator



V-39

I

I

I

FIGURGROSS ALPHA ACTIVITYIN AIR PARTICULATES

20

15


Y3

VCL >0Y)D

I

UNIT 2 CRITICALITY

1980 1981I I I I

1982 1983 1984 1985 1986 1987 1988 1989

indicator

control

. BERYLLIUM-7 ACTIVITIES, E-3 Ci/m

Location

Period

Indicator

~Pti 1 ~O

Control

~Pi 1 ~0

~Ran e

1978-81

69 - 81

Mean (median) 76 (76)

1982-87 1988

62 - 76

69 (69) -64

1978-1987 1982-87 1988

59 - 85 53 - 68

72 (73) 63 (64) 60

Potassium-40 was positively detected in only 13 out of 32 indicator

analyses and 2 out of 8 control analyses in 1988. The mean of

potassium-40 activities for indicator and control locations in 1988

is compared to the range and mean (median) of potassium-40 yearly

average activities at indicator and control locations from'983

through 1987 in the table below.

Location

POTASSIUM-40 ACTIVITIES E-3 Ci/m3

Indicator Control

Period

Rancae.

Mean (median)

" 1983-87 1988

LLD - 12

6.9(5.5) 4.7

1983-87

LLD - 5.8

4.6 (4.4)

1988

3.2

None of the results from the analyses of air particulate filtersindicate radioactivity attributable to the operation of SSES.

AIR IODINE

Routine iodine-131 analyses by gamma spectrometry of 519 charcoal

cartridges did not positively detect that radionuclide in any air

samples in 1988. Iodine-131 was detected infrequently from 1976,

when it was first monitored, through 1987. Since operation of SSES

began in 1982, iodine-131 has only been positively detected in air

sampling in 1986 due to the Chernobyl incident.

PRECIPITATION

Precipitation samples from eight indicator locations and two controlr

locations were analyzed quarterly in 1988 for gross alpha activity,gross'eta activity, tritium activity, and the activity of

gamma-emitting radionuclides identified by gamma spectrometry. The

detailed results of these analyses can be found in Table 14.

Gross alpha activity was detected in 24 out of 32 indicator samples

and all 8 control samples in 1988. The means of gross alpha

activities in precipitation for 1988 at both indicator and control

locations are compared to the corresponding ranges and means

(medians) from 1984 through 1987 in the table below.

PRECIPITATION GROSS ALPHA ACTIVITY Ci/1

Location

Period

Ra~cae

Mean (median)

Indicator

1984-87 1988

0-6-1.3

1.0(1.0) 0.6

Control

1984-87

0.9 - 1.1

1.0 (1.0)

1988

0.8

The data in the Table above do not indicate any gross alpha activityattributable to the operation of the SSES.

Gross beta activity was detected in all 32 indicator precipitation

samples and all 8 control precipitation samples in 1988. The means

of gross beta activities in precipitation for 1988 at both indicator

and control locations are compared to the corresponding ranges and

means (medians) from 1984 through 1987 in the table below.V-42

PRECIPITATION GROSS BETA ACTIVITY Ci/1

Location

Period

Ran<ac

Mean (median)

Indicator

1984-87 1988

2-5-4.3

3.5(3.5) 3.8

1984-87

3.4-5.2

4.2(4.1)

Control

1988

0.8

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

Tritium activity was positively detected in 20 out of 32 indicator

samples, and it was observed in 3 out of 8 control samples -in 1988.

The means of tritium activities in precipitation for 1988 at both

'indicator and control locations are compared to the corresponding

ranges and means (medians) during the preoperational and operational1


Location

PRECIPITATION TRITIUM ACTIVITY Ci/1

Indicator Control

P 10 - ~Pi 1 ~0 ~Pi 1 P~i1980-81

~Ran e 119-213

Mean (median) 166( 166)

1983-87 1988

94-200

140(139) 114

1980-81 1983-87 1988

99-135 92-530

117(117) 199(114) 183

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

Gamma spectrometry was first performed on precipitation samples in

1980. The only gamma-emitting radionuclides positively detected in

V-43

precipitation in 1988 were the naturally-occurring radionucl ides

beryllium-7 and potassium-40 and man-made cesium-137. Beryllium-7

was found in one indicator sample in 1988. With the exception of

1987, beryllium-7 has been positively detected every year since 1980.

The means of beryllium-7 activities in precipitation for 1988 at both

indicator and control locations are compared to the corresponding

ranges and means (medians) during the preoperational and operational


PRECIPITATION BERYLLIUM-7 ACTIVITY Ci/1

Location

Period

Indicator

~P. I I ~P

Control

~Pi I ~P

~Ren e

1980-81

24- 47

Mean (median) 36(36)

1982-87 1988

25 - 47

33 (27) 46

1980-81 1982-87 1988

34 - 40 9 - 52

37 (37) 34 (38) LLD

Potassium-40 was positively detected in one control precipitation

sample in 1988 at an activity of 10 pCi/liter. Potassium-40 has been

positively detected in precipitation previously in 1985, 1986, and

1987. The single activity reported in 1988 is within 'the range of

previously reported activities.

Cesium-137 was detected in only one indicator precipitation sample in

1988 at an activity of 2.3 pCi/liter. Cesium-137 has been positively

detected in precipitation previously in 1981, 1985, 1986, and 1987.

The single activity reported in 1988 also is within the range of

previously reported activities. This activity is attributable to


V-44

I. MILK

In 1988, 131 indicator milk samples and 19 control milk samples from

cows were routinely analyzed for gross beta minus potassium-40

activity, iodine-131 activity, and the activity of gamma-emitting

radionuclides by gamma spectrometry. Any milk samples showing gross

beta minus potassium-40 activity at 15 pCi/liter or higher were also

analyzed for strontium-89 and strontium-90.

Milk was sampled at a total of 8 indicator locations and 1 control

location in 1988. The frequency of sampling was monthly, except for

6 locations where it was sampled semimonthly from April through

October. The detailed results of these analyses can be found in

Table 15.

Since naturally-occurring, beta-emitting potassium-40 normally

accounts for the large majority of the activity in milk, removing

this activity before performing a gross beta analysis provides a more

sensitive method for detecting the activities of other beta emitters

that may be present, such as strontium-90.

Gross beta minus potassium-40 was positively detected in 123 out of

131 indicator samples and in 18 out of 19 control samples. The mean

of gross beta minus potassium-40 activities in milk for 1988 is

compared to the range and mean (median) of yearly average gross beta

minus potassium-40 activities at indicator and control locations

during the operational period 1985-87 in the table below.

V-45

MILK GROSS BETA MINUS POTASSIUM-40 ACTIVITIES Ci/1

Location

Period

~Rao e

Mean (median)

Indicator

1985-87 1988

7.1-7.8

7.4(7.3) 7.2

Control

1985-87 1988

7.6-9.8

8.9(9.2) 10.0

Strontium-,90 analyses were done on 8 indicator samples in 1988. All

8 analyses positively detected strontium-90. The mean of

strontium-90 activities in milk for 1988 is compared to the range and

mean (median) of yearly average strontium-90 activities at indicator



Location

Period

MILK STRONTIUM-90 ACTIVITIES Ci/1

Indicator

~P" i 1 ~0

Control

~0

1978-81

Ramae 4.3-5.3

Mean (median) 4.9(4.5)

1986-87 1988

6.7-6.8

6.7(6.7) 5.2

1978-81

1.7-7.5

5.0(5.4)

1986-87 1988

From 1978 through 1981, strontium-90 analyses were routinely

performed on milk samples regardless of the levels of gross beta

minus potassium-40 activity in the milk samples. The 1988 mean

strontium-90 activity is within the range of activities reported for

both indicator and control locations during this preoperational

period. The source of the strontium-90 before SSES operation and

a

IPg

V-46

since criticality appears to be the Chinese atmospheric nuclear

weapons tests, referred to in previous RENP annual reports, that took

place in 1972, 1974, 1976, 1977, 1978, and 1980.

Iodine-131 has been chemically separated in the milk samples and

counted routinely since 1977. (Refer to Figure 10 trending

iodine-131 activity in milk separately for indicators and controls

from 1977 through 1988.) Typically, iodine-131 is not positively

detected in any milk samples during a monitored year. The 1988

monitoring year was no exception; no iodine-131 above the lower limitof detection was observed in either indicator or control samples.

The preoperational years 1976, 1978, and 1980 were exceptional years

in the sense that activity was -positively detected due to fallout.Iodine-131 activity was also detected in milk samples in 1986 in the

vicinity of SSES .as a result of the Chernobyl incident.

Gamma spectrometry of milk samples in 1988 positively detected

naturally-occurring potassium-40 in all indicator and control

samples.

The mean of potassium-40 activities in air for 1988 is compared to

the range and mean (median) of yearly average potassium-40 activities

at indicator and control locations during the preoperational and


below.

V-47

FIGUR 0IODINE—131 ACTIVITYIN MILK

120

PRE OPERATIONAL OPERATIONAL100

CHINESE WEAPON TEST9 1777

80

CtLdI—

60

C3CL

20 CHINESE WEAPON TEST31478

CHINESE YEA10 15 80

ON TEST

UNIT 2 CRITICALITY

CHERNOBYL4 26 86

1977 1979 1981 1983 1985 1987 1989

I

i~

1

~

I

MILK -POTASSIUM-40 ACTIVITIES Ci/l

Location

Period

Indicator

~Pi 1 ~0

Control

~P, 1 1 ~0

1978-81 1985-87 1988

~Ran e 1222-1500 1241-1350

1978-81 1985-87 1988

1273-1500 1273-1320

Mean (medi an) 1353(1346) 1283(1258) 1250 1390(1393) 1304(1318) 1356

In 1988, gamma spectrometry also positively detected cesium-137 in

milk from the fallout of previous years'tmospheric nuclear weapons0

tests and Chernobyl fallout. The only years during the'adiological

Environmental Monitoring Program that cesium-137 was not positively

detected in milk were in 1973 and 1984. Cesium-137 remains in the

environment following fall'out for a relatively long time because of

its 30 year half-life.

Location

Period

Indicator Control

~PPP i1 ~001i 10~PP" Pi " 1P~00i 0

Cesium-137 was detected in 1988 in only 18 out of 131 indicator

samples. No cesium-137 was positively detected in any control

samples in 1988. The mean cesium-137 activity in milk for 1988 is

compared to the range and mean (median) of yearly average cesium-137

activity 'at indicator and control locations during the preoperational

and operational periods 1978-1981 and 1982-1987 respectively in the

table below.

MILK CESIUM-137 ACTIVITIES Ci/1

1978-81

~Ran e, 2.3-5.2


1982-87 1988

1.6-9.6

4.9(4.8) 4.6

1978-81

3.3-4.9

3.9(3.8)

1982-87 1988

1.9-7.4

4.0(4.2) LLD

V-49

No other gamma-emitting radionuclides have been positively detected

in milk in 1988 or any other year that the REMP was conducted, except

for 1986. Cesium-134 was detected once in June 1986 following the

Chernobyl incident.

No radioactivity identified in milk is attributed to SSES operation.i

J. SOIL (TOP AND BOTTOM) AND VEGETATION

Soil (top and bottom) and vegetation, usually grass, were sampled

once at each of eight REMP indicator locations and two REMP control

locations during 1988. The locations for sampling soil and

vegetation are the same as those for sampling air. The soil and

vegetation samples were analyzed by gamma spectrometry. The detailed

results of these analyses can be found in Tables 16 and 17.

Sixteen indicator soil samples and four control soil samples were

collected in 1988. Half of the soil samples were "top" samples taken

from the top two inches of soil The other half of the soil samples

were gathered from a depth of two to six inches and are called

"bottom" samples.

Naturally-occurring potassium-40, thorium-228, and radium-226 were

positively detected in all indicator and control soil samples in 1988

with one exception. Potassium-40 was not reported in one top sample

(from control location 12G3).

V-50

The means of the activities of potassium-40, thorium-228, and

radium-226 in soil for 1988 are compared to the corresponding ranges

and means (medians) of the yearly average activi,ties of these

radionuclides at indicator and control locations during the

preoperational and operational periods 1979 & 1981 and 1982-1987

respectively in the tables below.

SOIL POTASSIUM-40 ACTIVITIES Ci/ dr

Location

Period

Indicator

~Pi 1 ~P

Control

~Pi 1 ~P

~Ran e

-1979&81

9.2 - 9.7

1982-87 1988

10 0 - 12 4

1979&81 1982-87 1988

9.1 - 11.0 7.4 - 11.3

Mean (median) 9.5 (9.5) 10.9 (10.6) 9.4 ,10.1 (10.1)'* 9.5 (9.6) 11.6

Location

SOIL THORIUM-228 ACTIVITIES Ci/ dr

Indicator Control


1979&81

~P

1982-87 1988

~Pi 1 ~P

1979&81 1982-87 1988

~Ran e 0.9 - 1.3


1.1 - 1.3

1.2 (1.2) 0.9 1.0 (1.0)

1.0 - 1.2

1.1 (1.2) 1.0

Location

SOIL RADIUM-226 ACTIVITIES Ci/ dr

Indicator Controlll

Period Prep erational 0 erational Prep erational

1979&81

~Ran e 0.8 - 1.3


1982-87 1988

1.7 - 2.5 0.8 - 1.2 1.8 - 2.0

1.9 (1.9) 1.71.2 (1.2) " 1.5 1.0 (1.0)

1979&81 1982-87 1988

Cesium-137 activity has been identified in all indicator and control

soil samples in 1988.'he means of cesium-137 activities in soil for


cesium-137 activities at indicator and control locations during

preoperational and operational periods 1979 & 1981 and 1982-1987


Location

SOIL CESIUM-137 ACTIVITIES Ci/ dr

Indicator Control


1979&81

~0

1982-87 1988

Prep erational

1979&81 1982-87 1988

0 erational

~Ren e 0.5 - 0.7


0.3 - 0.4 0.2 - 1.2

0.3 (0.3) 0.5 0.7 (0.7)

0.6 - 1.2

0.9 (0.8) 0.2

Due to the relatively small activities of cesium-137 in soil and the

relatively large variability associated with cesium-137 activitiesand their means, it is difficult to attempt to draw any conclusions

about possible changes of the activities with time or about possible

differences between indicator and control locations.

The cesium-137 activity in soil is the result of fallout from


The anthropogenic radionuclides manganese-54 and cerium-141 were also

both been identified in soil in 1988. Manganese-54 was reported at

0.01 pCi/gram (dry) in a bottom sample from indicator location 982 in

1988. This is the second year„ that manganese-54 has been reported in

soil. It was first detected last year (1987) in a bottom sample from

V-52

another location. This year's activity is half of that reported last

year.

Cerium-141 was reported for the first time in a bottom soi 1 sample at

an activity of 0.09 pCi/gram (dry)'from indicator location 3D2.

Because of the relatively short half-life of cerium-141 (about 32

days), it is difficult to attribute, its presence to previous

atmospheric nuclear weapons tests or to the Chernobyl incident of

1986.

Since neither manganese-54 nor cerium-141 have been identified in any

„of the REMP air samples in 1988 or any other years since the SSES

,.operation, began, it is also difficult to attribute their presence to

the SSES. (Both manganese-54 and cerium-141 were identified in RENP

air samples during a number of the preoperational years.)

Considering the very low activities at which both manganese-54 and

cerium-141 were reported in the soil in 1988 and the previous

comments, the possibility remains that their activities may have

actual ly been . fa 1 se pos itives.

Soil samples were also obtained in 1988 for the purpose of monitoring

the site of disposal for the SSES sewage sludge.'his site is the

Mowery farm in Lycoming County, Pennsylvania. Since the Fall ofI

1987, the SSES sewage sludge is. being disposed of there to permit itsutilization for agricultural purposes. Monitoring on an annual basis

is expected to continue indefinitely to verify that there is no

increase in the presence of radionuclides at the site or in the

levels of radionuclides already found to exist at that

V-53

location. The results of the 1988 monitoring in three areas at the

Mowery farm may be found in Table 16 identified as Areas 1, 2 and 3.

The only gamma-emitting radionuclides positively detected in samples

from the Mowery farm in 1988 were potassium-40, thorium-228,

radium-226, and cesium-137. These radionuclides and their levels of

activity indicate that there is no detectable contribution to the

radioactivity of the soi 1 at the Mowery farm due to the disposal of

the SSES sewage sludge taking place there.

Naturally-occurring beryllium-7 and potassium-40 were positively

detected in all vegetation indicator and control samples in 1988.

The means of the activities of beryllium-7 and potassium-40 in

vegetation for 1988 are compared to the corresponding ranges and

means (medians) of the yearly average activities of these

radionuclides at indicator and control locations during the period

1986-1987 in the tables below.

VEGETATION BERYLLIUM-7 ACTIVITIES Ci/ wet


Period

Ran<ac

1986-87

0.8' 2.6


1988

0.6'986-872.0 - 2.2

2.1 (2.1)

1988

0.6

VEGETATION POTASSIUM-40 ACTIVITIES Ci/ wet

Location

Period

~Ran e

Indicator

1986-87 1988

6.3Mean (median) 6.2 (6.2)

1986-87

4.9 - 7.2

6.1 (6.1)

Control

1988

5.9

V-54

Cesium-137 was detected in two indicator and one control vegetation

samples in 1988. The means of cesium-137 activ'ities in vegetation


average cesium-137 activities at indicator and control locations

during the period 1986-87 in the table below.

VEGETATION CESIUM-137 ACTIVITIES Ci/ wet


Period 1986-87

~Ren e ..02 — .06

Mean (median) .04 (.04)

1988 1986-87

.03 - .04

.01 .04 (.04)

1988

.01

The cesium-137 in the table above is attributable to fallout from


No other garana-emitting radionuclides were positively detected in

vegetation in 1988.

K.. FOOD PRODUCTS

A total of 133 fruit/vegetable/honey samples and 24 game/poultry/egg

samples were analyzed by gamma spectrometry during 1988. This was an

increase in the scope of sampling from 1987. In addition to an

increase in the number of samples, there also was a significant

increase in the number of, sampling locations from five to eighteen.

. The number of geographical sectors from which samples were obtained

increased from four in 1987 to nine in 1988. The variety of

fruits/vegetables/honey increased from ten types in 1987 to

thirty-one in 1988.V-55

The sampling of game also was increased. Woodchucks and rabbits

added to the types of game sampled. The numbers of game samples

increased from six in 1987 to twenty-two in 1988. The number of

sampling locations increased from six in 1987 to eleven in 1988.

number of geographical sectors 'from which samples were obtained

increased from five in 1987 to eight in 1988.

were

yl

FRUITS, VEGETABLES, AND HONEY

Sample collection began in May and ended in October. Collection took

place at one control location and seventeen indicator locations. The

only gamma-emitting r adionuclides positively detected in 1988 were

naturally-occurring beryllium-7, potassium-40, and thorium-228, and

the fallout radionuclide cesium-137. Gamma-emitting r'adionuclides

positively detected in 1987 were naturally occurring beryllium-7 and

potassium-40 and the fallout radionuclide cesium-137.

4

Cosmogenic beryllium-7 was observed in seven lettuce and spinach

samples at indicator locations in 1988. Beryllium-7 was not reported

at any control locations in 1988. Beryllium-7 is normally only found

in a small portion of the total samples each year. Potassium-40 was

positively detected in every indicator and control sample in 1988.

Potassium-40 was found at the highest levels in spinach and at the

lowest levels in apples. Potassium-40 levels in the samples vary

considerably over a range of about one order of'agnitude.

Thorium-228 was detected at an activity of 0.08 pCi/gram (wet) in

only one sample of head lettuce from an indicator location in 1988.

Thorium-228 was found in food products once before in a 1986 food

sample.V-56

The means of the activities of beryllium-7 and potassium-40 in

fruits/vegetables/honey for 1988 are compared to the ranges and means

(medians) of the yearly average activities of those radionuclides at


operational periods 1980-'1981 and 1982-1987 respectively in the

tables below.

FRUITS/VEGETABLES/HONEY BERYLLIUM-7 ACTIVITIES Ci/ wet


Period ~PI 1 1 ~PtPi 1Petti t

~Ran e

Mean (median) 1.6 0.4(0.3) 0.3

1980-81 1982-87 1988

0.2-1.0

1980-81

LLD

LLD LLD LLD

1982-87 1988

LLD

Note the higher beryllium-7 activity reported in one indicator sample

in 1981.

FRUITS/VEGETABLES/HONEY POTASSIUM-40 ACTIVITIES Ci/ wet


Period Pl~it ~PtP i 11~Pl

1980-81 1982-87 1988 1980-81 1982-87 1988

~Ran e 2.5-3.0


2. 0-4.2

3.4(3.7) 3.4

3.0-3.1

3.1(3.1)

2.2-2.8

2.5(2.5) 2.5

Cesium-137 was observed in a total of ten samples of apples,

artichokes, yellow beans, carrots, honey, lettuce, and zucchini from

indicator locations in 1988. No cesium-137 was reported in samples

from control locations in 1988. Like beryllium-7, cesium-137 is

V-57

normally detected in only a small fraction of the total samples for

the year. Cesium-137 has been detected though. in honey every year

from 1981 through 1988, except 1986, at higher activities than in any

fruits or vegetables in which the radionuclide has been positively

detected. As with potassium-40, a wide variation (more than one

order of magnitude) in the activities of cesium-137 was observed in

samples in 1988.

The means of cesium-137 activities in fruits/vegetables/honey for

1988 are compared to the„.ranges and means (medians) of yearly average


preoperational arid operational periods 1980-1981 and 1982-1987


Location

Period

FRUITS/VEGETABLES/HONEY CESIUM-137 ACTIVITIES Ci/ wet

Indicator Control

P i 1~~aa ii 1~~P~ ii 1~o~Oi

~Ren e

1980-81 1982-87 1988

0.02-0.14

1980-81 1982-87 1988

LLD

Mean (median) 0.04(0.04) 0.05(0.03) 0.03 LLD 0.01 LLD

A total of four samples of bean leaves and potatoes leaves were

analyzed for carbon-14 in 1988. The average activity was 8.4 pCi/g

'carbon in 1988. This compares to an average of 8.5 pCi/g carbon in

samples from 1987, the only other year that this analysis has been

done..

V-58

GAME, POULTRY AND EGGS

Woodchuck, rabbit, squirrel, and deer were the game sampled and

analyzed for the activities of gamma-emitting radionuclides in 1988.

Naturally-occurring potassium-40 was positively detected in all of

the game samples'. The fallout radionuclide cesium-137 was found in

four out of seven woodchuck samples, one out of five rabbit samples,

four out of five squirrel sam'ples and all of. the deer samples. As in

the past years, some of the squirrel samples showed higher cesium-137

activity than the other game samples. No other gamma-emitting

radionuclides were reported in game samples in 1988.

The mean of naturally-occurring potassium-40 activities in game for

1988 is compared to the ranges and means (medians) of the yearly

average activities of potassium-40 in samples from the preoperational


table below.

GAME POTASSIUM-40 ACTIVITIES Ci/ wet

Period Prep erational 0 erational

~Ran e

1972-81

1.8 - 4.8


1982-87 '1988

27-322.9 (2.9) 3.7

Note that there are no control, locations designated for game as there

.are for the other environmental media sampled. The reasons for this

have been not only that specific locations for game (especially game

V-59

such as deer - the range of one individual may span a significant

distance) is usually impossible to specify, but also that most game

samples in the past have been obtained in relatively close proximity

to the SSES due to the means (such as "road" kills) with which many

deer samples are collected. In 1988, however, two deer samples were

obtained from location 16H, a distance of more than twenty miles from

the SSES. It may be of interest to compare the results of the

analyses of these samples with ones 'from samples taken closer to the

SSES. In the case of naturally-occurring potassium-40, the mean

activity of the two deer samples from 16H is 2.8 pCi/g wet. This

compares to the mean potassium-40 activity of 3.6 pCi/g (wet) from

three deer samples taken at distances much closer to the SSES in

1988.

The mean activity of the fallout radionuclide cesium-137 in game for

1988 is compared to the ranges and means (medians) of the yearly

average activities of cesium-137 in samples from the preoperational


table below.

GAME CESIUM-137 ACTIVITIES Ci/ wet

Period

~Ran e

Mean (median)

Prep erational

1972-81

0.0 - 8.8

1.9 (1.1)

0 erational

1982-87 1988

Oe5 - 1.6

1.0 (1.0) 0.4

As with potassium-40, it= might be of interest to compare the mean of

. cesium-137 activities in the two deer samples at location 16H (more

V-60

than twenty miles from the SSES) with the mean of the activities from

three deer samples collected in relatively close proximity to the

SSES. The mean cesium-137 activity in deer from location 16H in 1988

was approximately 0.8 pCi/g (wet) while the mean cesium-137 activity

from the three deer samples much closer to the SSES was about 0.2

pCi/g (wet).

A duck from a farm at location 10D1 and eggs from location 1281 were

also sampled in 1988. As in 1987, no anthropogenic radionuclides

were reported in 1988, and potassium-40 activities in 1988 for the

two samples were correspondingly similar to the values reported in

1987.

L. CALCULATED DOSE TO THE HYPOTHETICAL MAXIMALLYEXPOSED INDIVIDUAL

Radioactivity from the SSES operation was detected in the surface1

water pathway of the environment in 1988. As described previously,

tritium was frequently observed in the cooling tower blowdown line in

1988 at levels exceeding those found at the control locations.

Manganese-54 and chromium-51 were each seen once in 1988 in different

samples from location 6S7, the cooling tower blowdown line to the

Susquehanna River.

For the purpose of performing dose calculations according to theN

methodology of the Offsite Dose Calculation Manual, the radionuclides

just referred to, except for tritium, were assumed to be present

continuously in the discharge during each month that they were

detected, at activities equivalent to the yearly means of the

tactivities at which they were measured in 1988. These activities can

be found in the REMP summary presented in Table 3. The activity, 750

pCi/liter, of tritium on which dose calculations were actually based

was equal to the mean tritium activity, 885 pCi/liter, at location

6S7 less the mean tritium activity, 135 pCi/liter, for the control

locations during 1988.

Calculations performed using the LADTAP II code and conservative

discharge volume estimates indicated that the maximally exposed age

group would be the child. The calculated dose to a child at the

nearest downriver municipal water supplier via the drinking water,

shoreline, and fish pathways was less than 0.001 millirem to the

total body. This dose is less than 0.02 percent of the 6 mi llirem

limit (as expressed in 10CFR50, Appendix I) to the maximally exposed

individual. This value can also be compared to the value of

approximately 300 millirem annual effective dose equivalent that each

iindividual receives from natural background radioactivity.

V-62

VI. DEVIATIONS FROM THE PROGRAM — 1988

The analysis sensitivities required by the Nuclear Regulatory Commission

were met throughout 1988. The program sampling schedule was followed,

except as discussed below or footnoted in Tables 5, 6, 7 12, and 14.

Deviations affected monitoring or sampling of ambient radiation, surface

water, drinking water, flocculated sediment, air, and precipitation.

A total of four TLDs were lost at four different locations during 1988 due

to vandalism or other occurrences beyond control. The locations are

footnoted in Table 5.

Problems with automatic composite samplers at two surface water locations

(6S6 and 6S7) and one drinking water location ( 12H2 Raw) led to relatively

brief intervals when no water was being collected, intervals when

insufficient water was being collected, and intervals when too much water

was collected. These instances resulted in samples that were not as

proportionally representative of their entire sampling periods as

desirable. However, samples were collected and analyzed for all scheduled

sample periods. In certain instances, grab samples were obtained during

weeks that automatic composite samples were malfunctioning to ensure that

monthly composite samples would be as nearly representative of the entire

month as possible.

In 1988, deviations occurred five times at location 6S6, six times at

location 6S7, and five times at location 12H2 Raw. The problems that

occurred and the times of occurrence are footnoted at the appropriate

locations in. Tables 6 and 7.

No air samples were missed in 1988. Substantially smaller volumes than

normal were reported for two air samples in 1988, but the air samples were

still analyzed. Holes were reported in air particulate filters on three

occasions in 1988 with no significant effect on the results being

apparent. These instances are all footnoted at the appropriate locations

in Table 12.

Two dry gas meters used at air sampl'ing locations llS2 and 5S4 did not

meet the acceptable standards of accuracy (plus or minus two percent) at

their annual calibrations in September and October of 1988., The meters

could not be repaired and consequently were not returned to service.

(They were replaced in the field by spares with current'calibrations.)

out-of-calibration evaluation was performed to assess the impact of the

out-of-calibration conditions of these meters on air sampling results at— these locations. The evaluation determined that these meters did not

result in any NRC sensitivity level requirements or NRC reporting levels

being exceeded.

An apparent problem with sticking digits on a dry gas meter at location

981 during the period January 27, 1988 through February 2, 1988 eventually

required that the results for the air sample during that period be

declared invalid.

Loss of various amounts of collected precipitation occurred in three

samples in 1988. In addition, large amounts of precipitation collected

VI-2

during three different periods at two different locations in 1988 required

the deliberate elimination of amounts of sample volume to ensure

proportional representation was maintained during compositing. These

occurrences are all footnoted in Table 14.

None of the above deviations, singularly or collectively, compromised the

REHP's ability to monitor the environment for any effects from the SSES

operation.

VI-3

~

~

~

~

k

4

1

~

5

I

I

VII. PROGRAM CHANGES - 1988

1. Sampling of food products was increased significantly in 1988

compared to 1987. Increases occurred in the types of food products

and game sampled as well as in the locations and sectors from which

the samples were obtained. See Subsection K of Section V for more

details.

2. Two TLD locations were changed in 1988. The location of the TLD at

9D1, the Smith farm, was moved to a walnut tree along the driveway

near its previous location because the pole on which a TLD had been

hung previously had been removed. The TLD located at 8A2, the Bell

Bend pole, was moved across Route 11 to the Wetlands sign. This TLD

location was changed because the TLD had been repeatedly stolen at

its previous location.

3. The vendor used to calibrate dry gas meters installed at the .air

sampling stations was changed in 1988. The reason for the change was

to obtain the services of a vendor on or able to be placed on PPSL's

Approved Suppliers guality List (ASgL). The new vendor is Laboratory

Commercial Services of Jackson, Michigan. Accompanying the change in

the supplier of calibration services, was a change in the standard

used to calibrate the meters from a Bell Prover to a sonic venturi.

l

I

I

VIII. CONCLUSION

In 1988, REMP detected the naturally occurring radionuclides

beryllium-7, potassium-40, radium-'226, and thorium-228 in th'

environment. Potassium-40 was seen in all media except ground water.

Beryllium-7 was observed in algae, sediment, air, vegetation, and

lettuce and spinach. Radium-226 and thorium-228 were only found in

algae, sediment, soil and one sample of head le'ttuce.

The 1988 REMP also determined the presence of the following six

man-made radionuclides in the environment: tritium, chromium-51,

manganese-54, strontium-90, iodine-131, and cesium-137. The cesium-137

from weapons testing fallout was found in all media except air.

Tritium was seen in all four water media in which it was monitored.

Strontium-90, another fallout radionuclide, was only observed in milk.

(The only other medium that was analyzed for strontium-90 was surface

water on those occasions when gross beta activities increased to 15

pCi/liter or more.) The remaining three man-made radionuclides

(chromium-51, manganese-54, and iodine-131) were observed in either

surface water, algae, sediment, or soil. Of these three man-made

radionuclides detected, iodine-131 is not attributed to the operation

of the SSES. Iodine-131 was found in five algae control samples and

three algae indicator samples. Iodine-131 also was found in two

surface water control samples and two surface water indicator samples.

The man-made radionuclides detected in surface water, as sampled at the

cooling tower blowdown discharge line, were used to estimate the

off-site dose impact. The resulting conservatively calculated

radiation dose to a hypothetically exposed individual was less than

0.001 mrem to the whole body. This calculated dose is essentially in

agreement with the corresponding value presented in the Semiannual

Effluent and Waste Disposal'reports for the SSES in 1988 (32 and 33).

Monitoring the 'ambient radiation levels in the vicinity of the SSES by

thermoluminescent dosimetry has similarly demonstrated no significant

impact on the health and safety of the public living around the SSES.

The annual dose-equivalent of about 74 mrem indicated by REMP TLD

monitoring can not be determined to be different from the exposure due

to natural background radiation.

VII1-2

QUAKY OP DATA FOR THE SSES OPERAXI MONIT(HUNG PROGRAM - 1.988

Name of Facility: Susquehanna Steam Electric StationLocation of Facility: Luzerne County, Pennsylvania

Reporting Period: January 4, 1988 to January 6~ 1989

Page 1 of 11

MEDIUM

OR PATHWAY

SAMPLED (UNITOP MEASUREMENT)

ANALYSIS AND LOWER LIMITTOTAL NUMBER OP

OP ANALYSES DETECTION

PERFORMED(1) (LLD) (2)

ALL INDICATOR LOCATIONS

MEAN (f)(3)(RANGE)

NlMER OP

LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NONROUTINE

NAME MEAN(f)(3) MEAN (f)(3) REPORTED

DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS(4)

Ambient Radiation TLD 365(mR/std. qtr.)

18.5 (333/333)(13.5-25.1)

Station 13S4

0.4 miles W

24.0(4/4)(22.9-25.1)

18.5 (32/32)(14.0"24.1)

Surface Water(pci/I)

Gross 109Alpha

LLD

Gross 109Beta

Tritium 109 2000

6.0 (72/72)(1.7-21.0)

341 (46-72)(83-1900)

Station 6S7

Discharge

Station 6S7

Discharge

16.0 (12/12)(9.8 - 21.0)

885 (12/12)(160-1900)

3.7 (37/37)(2.1-6.3)

135 (11/37)(71-490)

Iodine- 109131

0.32 (4/72)(0.19-0.56)

Station 12G2

17 miles WSW

0.39 (2/12)(0.22-0.56)

0.18 (2/37)(0.14-0.22)

Sr-89 7

Sr"90 7

Gamma 109

SpecK-40

10.3

LLD

LLD

34 (1/72) Station 5S8

0.8 miles E

Only One

Indicator StationSampled.

56 (1/12) 42 (2/37)(28-56)

Mn-54 15 1.3 (1/72) Station 6S7

Discharge1.3 (1/12)

Cr-51 8.6 (1/72) Station 6S7

Discharge8.6 (1/12) LLD

NOXE: SEE THE POOXNOXES AT THE END OP THE TABLE

SUMlRY OF DATA HR THE SSES OPERATI(ML RADIOLOGICAL H3NIXORING PROGRAM - 1988


Reporting Period: January 4, 1988 to January 6 1989

Page 2 of 11

MEDIUM

OR PATHWAY

SAMPLED (UNITOF MEASUREMENT)

ANALYSIS AND LOWER LIMITTOTAL NUMBER . OF

OF ANALYSES DETECTION

PERFORMED(l) (LLD) (2)


MEAN (f)(3)(RANGE)

LOCATION WITH HIGHEST MEAN

NAME MEAN(f)(3)DISTANCE AND DIRECTION (RANGE)

NUMBER OF

CONTROL LOCATIONS NONROUTINE

MEAN (f)(3) REPORTED

(RANGE) MEASUREMENTS(4)

Surface Water(pCi/1)

Cs-137 18 3.0 (1/72) Station 5S8

0.8 miles E

4.0 (2/12)(3.3-4.7)

4.0 (2/37)(3.3-4.7)

Potable Water Gross 26

AlphaGross 26

Beta

5.3 (1/26)

3.9 (26/26)(2.0-5.1)

Station 12H2RAW

Station 12H2RAW

26 miles WSW

5.3(1/14)

4.5(14/14)(2.5-16)

Only IndicatorStationssampled forthis medium

Tritium 26 2000 94(8/26)(70-140)

Station 12H2RAW

26 miles WSW

113 (3/14)(89"140)

I-131 26

Gamma 26

SpecK-40

Cs-137 18

76 (1/26)

3.7 (1/26)

Station 12H2RAW

26 miles WSW

Station 12H2RAW

26 miles WSW

76 (I/14)

3.7 (1/14)

Sr-89

N SEE

MSUMMARY OF DAXA FOR THE SSES OPERAXI MONIXORING HRGIQH - 1988

Name of Facility: Suscpxehanna Steam Electric StationLocation of Facility: Luzerne County, Pennsylvania

Reporting Period: January 4, 1988 to January 6, 1989

Page 3 of H.

MEDIUM

OR PATHWAY


ANALYSIS AND LOWER LIMITTOTAL NUMBER OF



ALL 'INDICATOR LOCATIONS

MEAN (f)(3)(RANGE)

NUMBER OF




Potable Water Strontium- 0.390

Algae(pCi/g dry)

Gamma 14SpecBe-7

K-40

4.1 (6/7)(2.9-6.8)12.0(7/7)(7.4-2.O)

Station AG3

0.8 miles E

Station AG3

0.8 miles ESE

4.3 (6/V)(2.6-7.5)13.5(v/v)(10.7-17.3)

4.3 (6/7)(2.6-v.5)13.5(7/7)(1O.7-17.3)

Mn-54 0.46 (2/7)(0.39-0.53)

Station AG4

0.9 miles ESE

0.46 (2/v)(0.39-0.53)

LLD

I-131 o.v5 (3/v)(0.42-1.00)

Station AG4

0.9 miles ESE

o.v5 (3/v)(0.42-1.00)

0.44 (5/7)(0.12-1.01)

Cs-137

Ra-226

0.18 (1/7)

3.2 (1/V)

Station AG4

0.9 miles ESE

Station AG3

0.8 miles E

0.18 (1/7)

3.6 (2/V)(3.0-4.3)

0.13 (2/7)(0.09-0.17)

3.6 (2/7)(3.O-4.3)

Fish(pCi/g wet)

Th-228

Gross 15Beta

1.1 (4/V)(0.9-1.4)5.1 (9/9)(3.3-11.0)

Station AG4

0.9 miles ESE

Station IND

0.9-1.4 miles ESE

1.1 (4/V)(0.9-1.4)5.2 (6/6)(3.3-u..o)

1.0 (4/7)(0.9"1.3)5.2 (6/6)(3.0-7.6)

NOTE; SEE THE FOOINOTES AX XHE END OF XHE XABLE

SPShRY OF DATA FOR THE SSES OPERATIONAL RADIOLOGICAL MONIXOIGNG PROGlRH - 1988

Name of Facility: Susquehanna Steam Electric StationLocation of Facility: Luaerne County, Pennsylvania

Reporting Period: January 4, 1988 to January 6, I989

Page 4 of 11

MEDIUH ANALYSIS AND LOWER LIHITOR PATHWAY TOTAL NUMBER OF

SAMPLED (UNIT " OF ANALYSES DETECTION

OF MEASUREMENT) PERFORMED(l) (LLD) (2)


HEAN (f)(3)(RANGE)



NUMBER OF




Fish(pCi/g wet)

Gamma 15

Spec

K"40 4.2 (9/9)(3.5-4.7)

Station LTAW

0.8 miles NE

4.3 (3/3)(4.2-4.5)

. 3.7 (6/6)(3.2-4.2)

Cs-137 0.15 0.014 (6/9)(0.009-0.022)

Station IND0.9-1.4 miles ESE

0.014 (5/6) 0.011 (3/6)(0.009-0.022) (0.010-0.013)

0

Sediment

(pCi/g dry)Gross 12Alpha

13.5 (8/8)(9.4-23)

Station 12F

6.9 miles WSW

16 (2/2)(9.8-23)

13.0 (4/4)(9 '-17)

Gross 12Beta

35 '(8/8)(23-44)

Station 7B

1.2 miles SE

40.0 (2/2)(36-44)

33.0 (4/4)(22-47)

Gamma 12

Spec

Be-7 1.6 (5/8)(0.7-2.9)

Station 12F

6.9 miles WSW

2.4 (2/2)(2.0-2.9)

1.7 (3/4)(0.4-4.0)

K"40 11.2 (8/8)(7.9-14.8)

Station 2B

1.6 miles NNE

13.9 (2/2)(11.8-16.0)

10.8 (4/4)(7.6-16.0)

lfn-54 0.04 (1/8) Station 12F

6.9 miles WSW

0.04 (1/2)

Sl9%QRY OF DATA FOR XHE SSES OPERATI ICAL MONITORING HRGRAM - 1988

Name of Facility: Suscpmhanna Steam Electric StationLocation of Facility: Luzerne County, Pennsylvania


Page 5 of 11

MEDIUM

OR PATHWAY


ANALYSIS AND LOWER LIMITXOTAL NUMBER OF




MEAN (f)(3)(RANGE)

NUMBER OFLOCATION WITH HIGHEST-MEAN CONTROL LOCATIONS NONROUTINE



Sediment

(pci/g dry)Cs-137 0.18 0.17 (6/8)

(0.07-0.28)Station 12F6.9 miles WSW

0.21 (2/2)(0.14-0.28)

0.10 (4/4)(0.06-0.19)

Ra-226 1.65 (8/8)(1.18-2.26)

Station LTAW

0.8 miles NE

1.91 (2/2)(1.74-2.08)

1.73 (4/4)(1.06-2.23)

Th-228 1.07 (8/8)(0.85-1.44)

Station 2B

1.6 miles NNE

1.28 (2/2)(1.11"1.44)

1.05 (4/4)(0.68-1.44)

Floe(pCi/g dry)

Gross 2

Alpha11 (1/1) Station 2B

1.6 miles NNE

16 (1/1) 16 (1/1)

Gross 2

Beta45 (I./1) Station 7B

1.2 miles SE

45 (1/1) 44 (1/1)

Gamma 2

Spec

Be-7 1.87 (1/1) Station 7B

1.2 miles SE

1.87 (1/1) LLD

K-40 14.8 (1/1) Station 7B

1.2 miles SE

14.8 (1/1) 12.9 (1/1)

Cs-137 0.16 (1/1) Station 7B

1.2 miles SE

0.16 (1/1) 0.12(1/1)

NOTE: SEE XHE FOOTNOTES AT THE END OF THE TABLE

SURGERY OF DATA FOR THE SSES OPERATIONAL RADIOMGICAL

Name of Facility: Susquehanna Steam Electric StationLocation of Facility: Luzerne County~ Pennsylvania


Page 6 of 13.

MEDIUM

OR PATHWAY






MEAN (f)(3)(RANGE)



NUMBER OF




Floe(pCi/g dry)

Ra-226 LLD

Th-228 0.96 (1/1) Station 2B

1.6 miles NNE

1.03 (1/1) 1.03 (1/1)

Ground Water(pCi/I)

Gross 79

Alpha4.5 (1/67) Station 4S2

0.5 miles ENE

4.5 (1/67)

Gross 79

Beta2.3 (48/67)(1.3-4.7)

Station 4S2

0.5 miles ENE

3.0 (12/12)(1.9-4 ') 2.2 (12/12)

(0.7-1.3)

Tritium 79 2000 104 (28/67)(54-170)

Station 2S6

0.9 miles NNE

134 (2/12) 117 (5/12)(97-170) (61-180)

Gamma 79

SpecCs-137 18 4.6 (1/67) Station 4S2

0.5 miles ENE

4.6 (1/12) 2.4 (1/12)

Air Particulates (5)

(E-03pCi/ms)Gross 519 10Beta

17.1 (415/415)(8-38)

Station ID24.0 miles N

18.0 (52/52) 17.2 (104/104)(9-37) (6-37)

Air Iodine(E-03pCi/ms)

Gamma 519

SpecLLD

Q9%RRY OF DATA FOR THE SSES OPERATI MNIXORING PISGRAM — 1988

Name of Facility: Susysehanna Steam Electric StationLocation of Facility: Luzerne County, Pennsylvania


Page 7 of ll

MEDIUM

OR PATHWAY






MEAN (f)(3)(RANGE)

NUMBER OF


NAlE MEAN(f)(3) MEAN (f)(3) REPORTED


Air ParticulatesQuarterlyComposite(E-03pCi/ms)

Gross 40AlphaGamma 40Spec

2.4 (32/32)(1.6-3.1)

Station 12Gl15 miles WSW

2.7 (4/4)(2. 2-3. 2)

2.5 (8/8)(1.8-3.2)

MI

Precipitation(pci/I)

Be-7

K-40

Gross 40Alpha

64 (32/32)(46-84)

4.7 (13/32)(3.2-7.9)

0.63 (24/32)(0.33-1.0)

Station 9B1

1.3 miles S

Station 2S2

0.9 miles NNE

Station 12G1

15 miles WSW

66 (4/4)(56-83)

6.9 (1/4)

1.0 (4/4)(0.71-1.5)

60 (8/8)(49-73)

3.2 (2/8)

0.83 (8/8)(0.36-1.5)

Gross 40Beta

3.8 (32/32)(2.1-5.9)

Station 12G1

15 miles WSW

4.9 (4/4)(3. 2-6.6)

4.8 (8/8)(3.2-6.6)

Tritium 40 2000 114 (20/32)(69-190)

Station 7Gl14 miles SE

240 (1/4) 183 (3/8)(130-240)

Gamma 40

SpecBe-7 46 (1/32) Station 1D2 (1/4) 46 (1/4)

4.0 miles N

K-40 LLD Station 7G1

14 miles SE

10.3 (1/4) 10.3 (1/8)

NOTE: SEE THE FOOTNOTES AT THE END OR GATE TABLE

SBRQRY OF DATA FOR THE SSES OPERATIONAL RADIOLOGICAL MONITORING HIRAM - 1988


Reporting Period: January 4~ 1988 to January 6, 1989

Page 8 of ll

MEDIUM

OR PATHWAY

SAMPLED (UNITOF MEASUREHENT)



-PERFORMED(l) (LLD) (2)


MEAN (f)(3)(RANGE)



NUMBER OF



(RANGE) MEASUREHENTS(4)

Precipitation(pci/1)

Cs-137 18 2.3 (1/32) Station 1D2

4.0 miles N

2.3 (I/4) LLD

Milk(pCi/I)

Gross 150BetaHinusK-40

7.2 (123-131)(2.7-21)

Station 12B3

2.0 miles WSW

15.7 (12/12) 10.0 (18/19)(9.9-21) (1.3-14)

I-131 150 LLD

Sr-89

Sr-90

8 LLD

4.7 (8/131)(1.2-8.5)

Station 12B3

2.0 miles WSW

5.1 (7/12)(1.2-8.5)

Only One

IndicatorStationsSampled

Gamma 150SpecK-40 1250 (131/131)

(1010-1660)Station 13E3

5.0 miles W

1370 (19/19) 1356 (19/19)(1220-1610) (1190-1590)

Cs-137 18 4.6 (18/131)(2.9-7.5)

Station 14B1=1.7 miles WNW

5.7 (3/19) LLD

(4.9-6.1)0.

SUMMARY OF DATA FOR IHE SSES OPHthTI MONITORING PIRClULM - 1988

Name of Facility: Susquehanna Steam Electric StationLocation of Facility: Luxerne County, Pennsylvania

Reporting Period: January 4~ 1988 to January 6, 1989

Page 9 of 11

MEDIUM

OR PATHWAY






MEAN (f)(3)(RANGE)

NUMBER OF




Soil(pCi/g dry)

Gamma 20

SpecK-40 9.4 (16/16)

(7.9-11.0)Station 7G1 Bot14 miles SE

13 (1/1) 11.6 (3/4)(9.8-13.0)

MI

Mn-54

Cs-137

0.01 (1/16)

0.45 (16/16)(0.10-2.01)

Station 9B2 Bot1.3 miles S

Station llS4 Top0.4 miles SW

0.01 (1/1)

2.01 (1/1) 0.19 (4/4)(0.14-0.23)

Ce-141 0.09 (1/16) Station 3D2 Bot3,4 miles NE

0.09 (1/1)

Ra-226 1.5 (15/16)(1.1-2.7)

Station 3D2 Top3.4 miles NE

2.7 (1/1) 1.7 (4/4)(1.6-1.9)

Th"228 0.89 (16/16)(0.53-1.70)

Station 3D2 Top3.4 miles NE

l..7 (1/1) 0.99 (4/4)(0.90-1.20)

0-

Vegetation(pCi/g wet)

Gamma 10Spec

Be-7 0.63 (8/8)(0.31-1.32)

Station 3D2

3.4 miles NE

1.32 (1/1) 0.63 (2/2)(0.42-0.83)

K-40 6.33 (8/8)(3.83-10.60)

Station 11S4

0.4 miles SW

10.6 (1/1) 5.86 (2/2)(5.25-6.46)

NOTE: SEE THE FOOTNOTES AT 33K END OF THE TABLE

SUMMARY OF DATA FOR THE SSES OPERATIQQL RADIOLOGICAL

Name of Facility: Susquehanna Steam Electric StationLocation of Facility:, Luzerne County~ Pennsylvania

Reporting Period: January 4, 1988 to January 6, -1989

Page 10 of ll

MEDIUM

OR PATHWAY






MEAN (f)(3)(RANGE)



NUMBER OF




Vegetation(pCi/g wet)Food Products(pCi/g wet)

Cs-137

Gamma 133

SpecBe-7

0.014(2/8)(0.011-0.016)

0.26 (7/105)(0.14-0.35)

Station 11S4

0.4 mile SW

Station 12F4

5.8 miles WSW

0.020(1/11) 0.010(1/1)

0.35 (1/4) 0

K-40 3.44 (105/105)(0.70-8.87)

Station llF1-5.6 miles SW

5.92 (2/2)(2.97-8.87)

2.45 (28/28)(0.70-5.45)

Cs-137 0.08 0.027 (10/105)(0.006-0.141)

Station 7B2

1.5 miles SE

0.090 (2/2)(0.030-0.141)

0

Th-228 0.08 (1/105) Station 7Fl6.7 miles SE

0.08 (1/10)

Food Products(pCi/g Carbon)

Game, Poultry,Eggs

(pCi/g wet)

C-14

Gamma 24

SpecK-40

Cs-137

8.4 (4/4)(7.7-10.0)

3.7 (24/24)

. (1.1-6.6)

0.44 (14/24)(0.006-1.8)

Station 11Dl3.3 miles SW

Station 5E14-5 miles E

Station 11F5-10 miles SW

8.6 (3/3)(7.8 - 10.0)

6.6 (1/1)

1.8 (1/1)

Only Indicator 0Station SamplesAnalyzed for C-14.

Only Indicatorstationssampled forthis medium

QBIQRY OF DATA FOR THE SSES OPERATI0%lL RhDIOLOGICAL HNZHHGNG HIGRhH - 1988

Name of Facility: Susquehanna Steam Electric StationLocation of Facility= Luzerne County, Pennsylvania


Page llof ll .

1. The total number of analyses does not include duplicates or splits or repeat analyses.

2. The Technical Specifications LLD is given when applicable.7

3. Neans and ranges are based upon detectable activities only. (f) is the ratio of positive results to the number of samples analyzed.

4. USNRC reporting levels as specified in the Technical Specifications.

5. The indicator mean was determined without including a value from location 981 for the period January 27, 1988 through February 2,1988. This value, which is included in Table 12, was considered invalid, See the footnote at the bottom of Table 12 and thediscussion in Section VI "Deviations."

r

Rad/EnvMonPro/3

X. LAND USE CENSUS

The USNRC Branch Technical Position on "An Acceptable Radiological

Environmental Nonitoring Program" (November 1979, Revision 1), states that

"a census shall be conducted annually during the growing season to

determine the location of the nearest milk animal and nearest garden

greater than 50 square meters (500 sq.'t.) producing broad leaf

vegetation in each of the 16 meteorological sectors within a distance of 8

km (5 miles)." To comply with this requirement, a land-use survey was

conducted for the Susquehanna SES during the period June 14, 1988 through

Sept. 26, 1988. The closest garden (greater than 50 square meters,

producing broad leaf vegetation) and residence in each radial sector was

determined and all dairy animals within five (5) miles were -identified.

Table 4 lists the nearest dairy animals, the nearest garden, and nearest

residence in each sector identified during the survey. These land-use

parameters are used in the assessment of potential radiological doses to

individuals and populations of the stated regions.

TABLE 4

Nearest residence, garden, and dairy animal in each of the 16meteorological sectors within a 5-mile radius of the SusquehannaSteam Electric Station, 1988.

Sector Direction NearestResidence

NearestGarden

NearestDair y Animal

1

2

3

4

5

6

7

8

9

10

11

12

13

14

15

16

N

NNE

NE

ENE

E

ESE

SE

SSE

S

SSW

SW

WSW

W

WNW

NW

NNW

1.3 mi

0.9 mi

2,3 ml

2.1 mi

1.4 mi

0;5 mi

0.4 mi

0.7 mi

1.1 mi

1.2 mi

1.5 mi

1.2 mi

0.8 mi

0.7 mi

0.9 mi

0.6 mi

1.3 mi

)5.0 mi.2+3 ml

2;2 ml

1.4 mi

2.0 mi

0.4 mi

0.7 mi

1.1 mi

1.2 mi

1.8 mi

1.2 mi

1.5 mi

0.5 mi

2.2 mi

4.0 mi

~ 5.0 mi

~5.0 mi

~5.0 mi

2.7 mi

., 4.5 mi

2.5 mi

2.6 mi

3.5 mi

3.9 mi

3.0 mi

r 5.0 mi

1.7 ml

5.0 mi

1.8 mi

>5.0 mi

4.2 mi

X-2

XI. REFERENCES

1. Radiation Management Corporation, "Susquehanna Steam Electric

Station, Radiological Environmental Monitoring Program, Report Pl

(April - December 1972)" RMC-TR-73-14, July 1973.


Station, Pre-operational Radiological Environmental Monitoring

Program 1973," RMC-TR-74-07, May 1974.


Station, Preoperational Radiological Environmental Monitoring

Program, 1974 Annual Report," RMC-TR-75-07, April 1975.

CI


Station, Radiological Environmental Monitoring Program, 1975 Annual

Report," RMC-TR-76-05, May 1976.



Report," RMC-TR-77-04, March 1977.



Report," RMC-TR-78-01, May 1978'.



Report," RMC-TR-79-01, April 1979.



Report," RMC-TR-80-01, March 1980.



Report," RMC-TR-81-02, July 1981.



Report," RMC-TR-82-03, July 1982.

ll. Radiation Management Corporation, "Susquehanna Steam Electric

Station, Radiological Environmental Monitoring Program, 1982

Preoperational Report," RMC-TR-83-01, April 1983.


Station, Radiological Environmental Monitoring Program, 1982

Operational Report." RMC-TR-83-02, April 1983.

13. NUS Corporation, "Susquehanna Steam Electric Station, Radiological

Environmental Monitoring Program, 1983 Annual Report," NUS-4516 March

1984.

XI-2

14. Pennsylvania Power and Light Company, "Susquehanna Steam Electric

Station, Environmental Report, Operating License Stage," May 1978.


Station, Final Safety Analysis Report," 1978.

16. United States Nuclear Regulatory Commission, Office of Nuclear

Reactor Regulation, "Final Environmental Statement Related to the

Operation of Susquehanna Steam Electric Station, Units 1 and 2,"

Docket Nos. 50-387 and 50-388, June 1981.

17. United States Nuclear Regulatory Commission, "An Acceptable

Radiological Environmental Monitoring Program," Radiological

Assessment Branch Technical Position, November 1979, Revision 1.

18. National Council on Radiation Protection and Measurements,

"Environmental Radiation Measurement," NCRP Report No. 50,

Washington, D.C., December 27, 1976.

19. Oakley, D.C., "Natural Radiation Exposure in the United States,"

ORP/SID 72-1 Office of Radiation 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 of Elevated Cesium-137 Concentrations in Small Game in

Luzerne County, Pennsylvania." Proceedings of Papers presented at

Health Physics Society Tenth Midyear Topical Symposium, October

11-13, 1976, pgs 271-279.

XI-3

21. Teledyne Isotopes, "Susquehanna Steam Electric Station, Radiological

Environmental Monitoring Program, 1984 Annual Report," April 1985.

22. Currie L.A., "Lower Limit of Detection: Definition and Elaboration

of a Proposed Position for Radiological Effluent and Environmental

Measurements," NUREG/CR-4007, September 1984.


Station, Semi-annual Effluent Waste Disposal Report, Data Period:

January - June 1986", August 1987.

24. Pennsylvania Power and Light Company, "Susquehanna, Steam Electric


July - December 1986," February 1987.


Station, Offsite Dose Calculation Manual," Docket nos. 50-387 and

50-388. November 22, 1985.

26. Pennsylvania Power and Light Company Technical Specifications

Susquehanna Steam Electric Station, Units no. 1 and 2; Docket no.

50-387 and 50-388 Appendix A to License no. NPF-14, July 82 and

NPF-22, March 84.

27. Teledyne Isotopes, "Susquehanna Steam Electric Station, Radiological

Environmental Monitoring Program, 1985 Annual Report", April 1986.

28. Teledyne Isotopes, "Susquehanna Steam Electric Station, Radiological,

Environmental Monitoring Program, 1986 Annual Report," April 1987.

29. Pennsylvania Power and Light Company, '"Susquehanna Steam Electric

'tation, Semi-annual Effluent Waste Disposal Report, Data Period:

January - June 1987, August 1987.



July - December 1987, February 1988.

31. Pennsylvania Power 8 Light Company, "Susquehanna Steam Electric

Station, Radiological Environmental Nonitoring Program, 1987 Annual

Report," April 1988.

32. Pennsylvania Power 5 Light Company, "Susquehanna Steam Electric


January-June 1988," August 1988.

33. Pennsylvania Power 5 Light Company, "Susquehanna Steam Electric .

Station, Semi-Annual Effluent Waste Disposal Report, Data Period:

July-December 1988," February 1989.

XI-5

III

I

TABLE 5

ENVIRONMENTAL THERMOLVMINESCENT DOSIMETRY RESULTS 1

SSES 1988

(mR/std. qtr. +/-2s)Page 1 of 4

i Location First quarter1/6/88

to3/29/88

Second quarter3/28/88

to6/30/88

Third quarter6/28/88

to9/30/88

Fourth quarter9/29/88

to1/5/89

TLDs WITHIN PPSL PROPERTY BOUNDARY

+ 1S22S2

+ 2S33S3

+ 3S44S1

+ 4S35S15S4

+ 5S7+ 6S4

6S8+ 6S9

+ 8S2+ 9S2+ 10S1

10S211S2

+ 11S311S6

+ 12S3+ 13S2

13S413S5

+ 14S514S615S4

+ 15S5+ 16S1+ 16S2

18.0+1.115.6+1.217.3+0.915.4+0.716.4+0.614.1+1.518.2+0.614.0+0.616.4+1.515.6+0.722.1+0.515.9+1.218.5+0.917.1+0.719.7+0.522.9+1.616.6+0.522.3+0.714.6+0.923.0+0.515.1+0.822.1+0.719.6+1.022.9+1.422.2+1.919.5+0.220.5+2.415.6+0.618.6+1.119.4+1.120.0+0.5

18.8+0.716.8+1.118.4+0.617.0+2.416.9+0.415.8+2.019.6+0.415.2+0.417.1+0.617.5+1.022.7+0.617.5+1.218.4+1.117.9+0.919.8+0.823.6+1.017.5+0.822.2+1.016.5+2.023.0+1.016.5+0.823.6+1.020.5+0.924.7+1.6(4)22.5+0.220.9+0.5(4)20.4+0.816.2+2.019.1+0.919.5+1.220.2a1.0

18.7+2.316.1+1.417.6+0.514.7+1.116.5+0.914.0+0.4(4)17.8+0.814.2+0.515.9+0.2(4)15.4+0.920.7+0.815.2+1.318.5+0.918.8+1.118.9+1.023.6+0.916.4+1.321.5+1.313.9+0.622.9+1.315.3+1.622.5+1.419.0+1.623.1+0.922.1+1.3(4)19.8+1.518.9+1.014.7+0.817.9+0.6(4)19.2+0.920.1+0.3(4)

21.4+1.118.7+0.519.3+1.218.7+2.518.9+0.717.6+1.822.2+0.917.2+1.019.6+0.919.2+0.723.5+1.318.8+0.821.5+1.521.7+1.322.2+0.921.7+1.318.7+1.024.4+0.718.1+1.425.9+1.417.4+0.623.9+1.621.9+1.125.1 2.0(4)24.7+0.822.1+1.021.6+0.817.4+0.320.4+1.120.8+1.121.6~0.6

iL

ee footnotes at end of table

TABLE 5

DIRECT RADIATION — THERMOLUMINESCENT DOSIMETRY RESULTS (1)

SSES 1987

Page 2 of 4

Location First guar ter1/5/87

to4/3/87


to6/26/87


to9/30/87


to1/1/88

0-1 MILE OFFSITE

+ 6A47Al7A28A315A316A2

0.19+0.010.16+0.010.17+0.00(4)0.16+0.010.17+0.010.15+0.01

0.22+0.010.19+0.01,0.20+0.02

(2)0.21+0.000.19+0.01

0.20+0.010.18+0.010.19+0.00(4)

(2)0.20+0.010.17+0.01

0.22+0.010.19+0.020.20+0.01

(2)0.21+0.010.18+0.01

1-2 MILES OFFSITE

*181+ 283*284*481*582*682

783*784

+ 882*883

981-10821083

*10841284

*1285*1381*1481*1581

1681*1682

2-3 MILES

*11C1

0.17+0.020.17+0.030.17+0.010.16+0.010.19+0.010.18+0.010.16+0.010.18+0.010.18+0.010.19+0.020.16+0.010.15+0.000.14+0.010.18+0.01(4)0.17+0.010.17+0.010.19+0.030.21+0.02(4)0.18+0.020.14+0.010.17+0.03(4)

OFFSITE

0.20+0.00

0.19+0.010.19+0.020.18+0.010.18+0.010.19+0.010.20+0.020.19+0.010.19+0.010.19+0.010.19+0.010.18+0.020.16+0.01

(2)0.19+0.000.18+0.010.18+0.020.19+0.020.19+0.030.18+0.020.18+0.020.18+0.01

0.22+0.01

0.20+0.010.18+0.01(4)0.18+0.020.18+0.020.20+0.010.20+0.010.18+0.010.20+0.000.18+0.010.18+0.020.18+0.010.16+0.010.16+0.010.20+0.000.18+0.020.18+0.020.19+0.00

(2)0.18+0.020.16+0.010.18+0.00(5)

0.22+0.01

0.19+0.010.19+0.000.19+0.020.18+0.010.19+0.020.19+0.010.19+0.020.20+0.010.19+0.000.20+0.010.18+0.010.17+0.01'(4)0.19+0.05(4)0.19+0.000.18+0.010.18+0.020.19+0.010.20+0.010.18+0.010.17+0.010.17+0.01

0.22+0.00

See footnotes at end of table

TABLE 5

ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY RESULTS (1

SSES 1988

(mR/std. qtr. + 2s)Page 3 of 4

Location First quarter1/6/87

to3/29/88


to6/30/88


to9/30/88

Fourth quarter. 9/29/88

to1/5/89

3-4 MILES OFFSITE

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

12D3

18.4+0.118.7+0.517.3+0.617.8+0.517.5+0.818.7+1.1

18.9+1.1(4)20.0+1.118.0+0.9(4)19.9+0.9(4)18.3+0.719.2+1.2

18.3+1.019.3+0.917.5+0.4

(2)17.3+0.2(4)18.7+0.9(4)

21.7+1.621.9+1.019.8+0.320.1+1.120.1+1.221.320.9

4-5 MILES OFFSITE

1E1+ 4E1+ 5E2+ 6E1+ 7E1+ 11El+ 12E1+ 13E4+ 14El

15.7+0.617.3+0.618.0+0.720.1+0.617.9+0.814.5+0.316.7+1.418.420.517.4+1.1

16.5+0.3(4)19.2+0.0518.7+0.720.8+0.8(4)19.3+1.4(416.0+0.418.4+0.820.7+0.4(4)18.7+0.7 4)

14.8+0.617.8+1.817.8+0.820.310.918.7+0.8(4)14.4+0.916.7+1.118.8+0.9(4)18.4+1.3

17.5+1.419.9+1.220.6+1.722.1+1.722.2+1.317.6+1.120.4+1.221.4+1.221.0+0.9

+ 2F1+ 3F1*3F2

8F212F2

+ 15F1+ 16Fl

16.4+0.316.4+0.918.1+0.216.6+0.6(4)18.1+1.217.1+1.018.9+1.0

17.7+0.6(4)17.1+0.418.9+1.0(4)16.3+0.719.6+0.9(4)18.3+1.2(4)18.8+0.8

16.3+0.815.6i0.817.5+1.416.2+1.217.6+0.2

18.3+0.3 4

20.6+1.618.9+1.221.3~0.618.3+1.920.7+0.520 6+0 322.1+1.6

See footnotes at end of table

XII-3

TABLE 5

ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY RESULTS 1

SSES 1988

(mR/std. qtr. + 2s)Page 4 of 4

Location First quarter1/6/88

to3/29/88


to6/30/88


to9/30/88


to1/5/89

10-20 MILES OFFSITE

+ 3G33G4

+ 4G1+ 7G1

*7G2+ 12G1'2G4

17.6+0.718+0.819.3+0.418.9+0.417.2+0.814.3+1.117.4+0.5

19.6+0.919.0+0.820.6+1.319.2+1.319.3+1.3(4)16.3+0.519.8+0.7(4)

19.0+0.6(4)18.0+1.720.3+1.218.2+0.517.3+1.3(4)14.0i0.518.1+0.7(4)

20.9+0.921.2+1.124.1+1.221.6+0.921.2+1.117.7+1.621.8+0.6

PIC LOCATIONS

12F42S51E23G2

22.8+1.314.'1.0.'3(4)

N/A15.1+0.9

23.2+2.815.2+1.214.7+0.315.7+1.4

22.0+0.813.5+1.1

N/A14.6+0.5(4)

24.9+1.9(5)16.8+0.8

N/A17.7+0.5

IndicatorAverage(3)

ControlAverage (3)

17.7+4.4

17.2+3.4

18.5+4.2

18.7+3.4

17.6+4.4

17.4+4.2

20.3+4.0

20.8a4.3

NOTES

( 1) Uncertainties for individual measurements are two standard deviations of theaverage of four readings per station.

(2) TLD Missing.3) Uncertainties of row averages are two standard deviations calculated from the

mean of each.(4) Mean is average of 3 TLD elements.(5) Mean is average of 2 TLD elements.

+) Tech Spec Locations*) NRC Co-Located Stations: 284 (1), 181(2), 1682(3), 1581(4) 1481(5), 1381(6),

1285(7, 11C1(8), 1084(9, 3F2(19, 481(23), 582(24)682(25 , 784(26), 883(27 , 7G2(35 .

XII-4I'

of 4

TABLE 6GROSS ALPHA, GROSS BETA, TRITIUM, IODINE-131 AND GAMMA* SPECTROMETRIC ANALYSIS OF SURFACE MATER

SUSOUEHANNA STEAM ELECTRIC STATION-1988

Results are in units of pCi/g (dry)+ 2s

'OCATIONCOLLECTION

DATE

Gross Gross

Alpha Beta Tritium I-131 K-40 Mn-54 Cr.51 Cs-137

SB

S6(1)103

S5

S7(2)(3)LTAW

12F1

12G2

01/11/88 to01/04/88 to01/05/8801/11/88 to01/04/88 to01/05/8801/05/8801/05/8801/04/88 to

02/08/8802/08/88

02/08/8802/08/88

02/08/88

LT 2

LT 2

LT 2

LT 1

LT 2

LT 2

LT 2

LT 2

LT1

5.3 + 1.12.4 + 0.93.2 + 0.93.4 + 0.9

14.0 + 2.04.8 + 1 '2.6 + 0.83.0 + 0.83.5 + 0.8

LT 70

LT 90

490 + 60

LT 90

950 + 60

130 + 50

90+ 41

120 + 40

LT 70

0.22 + 0.10

0.32 + 0.100.56 + 0.10

34+ 18

8.6 + 7.4

SB

S6(4)1D3

S5

'S7(2)LTAW

02/15/88 to02/15/88 to02/09/8802/15/88 to02/08/88 to02/09/8802/09/8802/09/8802/08/88 to

03/07/8803/07/88

03/07/8803/07/88

03/07/88

LT 1

LT 1

LT 2

LT 1

LT 2

LT 2

LT 2

LT 2

LT 1

2.6 + 0.93.1 + 0.92.8 + 0.82.7 + 0.9

18.0 + 2.05.3 + 1.13.4 + 0.83.8 + 0.92.3 + 0.9

83+ 39

LT 60

LT 100

190 + 30

700+ 90

LT 90

LT 70

LT 50

84 + 37

'SB

S6(5)1D3

LTAW

2F1

2G2

2H1

03/14/88 to03/07/88 to03/07/8803/14/88 to03/07/88 to03/08/8803/08/8803/07/8803/07/88 to

04/04/8804/04/88

04/04/8804/04/88

04/04/88

LT 1

LT 0.5LT 2

LT 0.9LT 1

LT 1

LT 1

LT 1

LT 1

4.2 + 0.93.7 + 0.93.0 + 1.1

2.5 + 0.811.0 + 2.02.9 + 0.91.7 + 0.83.7 + 1.02.3 + 0.9

LT 80

LT 90

120 + 30

LT 90

600 + 60

170 + 30

85 + 39

140 + 40

84+ 54

3.0 + 2.3

g$ 8

1D3'5S7(2)(6)TA'W

12F1

04/11/88 to04/04/88 to04/05/8804/11/88 to04/04/88 to04/05/8804/04/8804/04/8804/04/88 to

05/09/8805/09/88

05/09/8805/09/88

05/09/88

LT 0.8LT 0.8LT 0.7LT 0.8LT 2

LT 1

LT 1

LT 1

LT 0.8

3.1 + 0.92 ' + 0.83.6 + 0.92.3 + 0.9

19.0 + 2.05.1 + 1.13.0 + 0.83.6 + 0.92.8 + 0.9

LT 80

LT 70

LT 70

LT 70

240 + 50

120 + 40

120 + 50

LT 100

90 + 47

gamna emitters detected are reported; typical LLD values are found in Table 20.

TABLE 6

„ GROSS ALPHA, GROSS BETA, TRITIUM, IODINE-131 AND GAMMA» SPECTROMETRIC ANALYSIS OF SURFACE WATER

SUSQUEHANNA STEAM, ELECTRIC STATION-1988

Results are in units of pCi/g (dry)+ 2s Page 2 of 4

LOCATION

COLLECTION

DATE

Gross GrossAlpha Beta Tri tiun 1-131 K-40 Mn-54 Cr-51 Cs-137

'SB

6S6

1D3

6SS

6S7

LTAW

12F1

12G2

12H1

05/16/88 to05/09/88 to05/09/8805/16/88 to05/09/88 to05/09/8805/09/8805/09/8805/09/88,to

06/06/8806/06/88

06/06/8806/06/88

06/06/88

LT 1

LT 1

LT 0.8LT 2

LT 2

LT 2

LT 0.8LT 0.8LT 2

4.22.12.93.89.84.72.42.33.3

+ 1.2+ 1.1+ 0.9+ 1 '+ 1.9+ 1 3+ 0.9+ 0.9+1 ~ 1

LT 70

LT 80

LT 90

LT 80

1200 + 100

130 + 50

LT 60

120 + 50

LT 70

56 + 29

28+ 21

1.3 + 0.7

5SB

6S6

1D3

6S5

6S7

LTAW

12FI

12G2

12H1

06/13/88 to06/06/88 to06/07/8806/13/88 to06/06/88 to06/07/8806/07/8806/07/8806/06/88 to

07/05/8807/05/88

07/05/8807/05/88

07/05/88I

LT 0.8LT 2

LT 2

LT 0.9

4.25.54.34 '

LT 2

LT 2

LT 1

LT 2

6.84.13.63.9

LT 0.9 12.0

+ 1.1+ 1.2+ 1.2+ 1.1+ 2.0+ 1.5+ 1.2+ 1 ~ 2+ 1.0

LT 80

110 + 40

80 + 48100+ 40

1400 + 100

120 + 50

LT 80

170 + 50

110 + 50

4.7 + 3.1

5SB

6S6

103

6SS

'S7(2)

LTAW

12F1

12G2

12H1

5SB

6S6(7)1D3

6S5

6S7(2)LTAW

12F1

12G2

12H1

07/11/88 to07/05/88 to07/05/8807/11/88 to07/05/88 to07/05/8807/05/8807/05/8807/05/88 to

08/15/88 to08/15/88 to08/06/8808/15/88 to08/08/88 to08/06/8808/06/8808/06/8808/08/88 to

08/08/8808/08/88

08/08/8808/08/88

08/08/88

09/06/8809/06/88

09/06/8809/06/88

09/06/88

LT 2

LT 2

LT 2

LT 2

LT 2

LT 2

LT 2

LT 2

LT 2

LT 1

.LT1LT 'I

LT 1

LT 2

LT 1

~ LT 1

LT 1

LT 1

4.32.16.35.4

21.06.44.76.03.6

5.33.54.44 '

17.06.33.95.24.6

+ 1.1+ 0.3+ 1.2+ 1.2+ 3

+ 1.2+1 ~ 1

+ 1.2+ 1.0

+ 1.2+ 1.0+ 1-1+1 ~ 1

+ 2.0+ 1.2+ 1.1+ 1.1+ 1.1

LT 60

71 + 36

110 + 50

110 + 50

160 + 40

170 + 50

340 + 130

340 + 130

LT 50

LT 60

99 +56'T

70

83 + 46

810 + 60

100 + 40

95 + 56

380 + 50

100 + 50

0.14 + 0.08

0.19 + 0.080.22 + 0.09

* Only gamna emitters detected are reported; typical LLD values are found in Table 20.

of 4

TABLE 6GROSS ALPHA, GROSS BETA, TRITIUM, IODINE-131 AND GAMMA SPECTROMETRIC ANALYSIS OF SURFACE WATER

SUSQUEHANNA STEAM ELECTRIC STATION.1988

Results are in units of pCi/g (dry)+ 2s

COLLECTION

DATE

Gross Gross

Alpha Beta Tritiun I -131 K-40 Mn-54 Cr-51 Cs.137

k1D3

5

7(2)(8)LTAW

FI

G2

H1

09/12/88 to 10/03/8809/06/88 to 10/03/8809/06/8809/12/88 to 10/03/8809/06/88 to 10/03/8809/06/8809/06/8809/06/8809/06/88 to 10/03/88

LT 2

LT 1

LT 1

LT 1

LT 2

LT 1

LT 1

LT 1

LT 1

4.9 + 1.15.5 + 1.13.9 + 1.04.8+ 1.1

18.0 + 2.06.7 + 1.34.0 + 1.04.3 + 1.04.3 + 1.0

LT 70

LT 70

LT 60

120 + 50

1900 + 100

88 + 52

140 + 40

110 + 50

LT 70

1D3

5

7(2)(9)AW

12F1

10/10/8810/03/8810/04/8810/10/8810/03/8810/04/8810/03/8810/03/8810/03/88

TO 11/07/88TO 11/07/88

TO 11/07/88TO 11/07/88

TO 11/07/88

LT 2

LT 2

LT 1

LT 2

LT 2

LT 1

LT 1

LT 1

LT 2

3.4 + 1.1

3.4 + 1.14.1 + 1.1

4.4 + 1.220.0 + 3.0

5 .9 + 1.23.8 + 1.05.3 + 1 '4.2 + 1.2

LT 60

LT 70

LT 80

LT 60

1600 + 100

110+ 50

LT 50

120 + 50

LT 90

3.3 + 2.6

'8

6(10)6S6(GRAB)~

3

5

7(2)(11)LTAW

R.",12H1

11/07/88 TO 12/05/8811/07/88 TO 12/05/8812/05/8811/08/8811/07/88 TO 12/05/8811/07/88 TO 12/05/8811/08/8811/07/8811/07/8811/07/88 TO 12/05/88

LT 0.8LT 0.8LT 0.8LT 1

LT 0.8LT 2

LT 2

LT 1

LT 1

LT 0.8

3 ' + 0.62.8 + '0.62 ' + 0.65.4 + 1.22.9 + 0.6

19.0 + 2.06.0 + 1.35.3 + 1.24.4 + 1.12.8 + 0.6

75+ 45

LT 90

LT 60

LT 80

LT 60

680 + 50

LT 50

LT 70

LT 70

LT 80

* Only gamna enitters detected are reported; typical LLD values are found in Table 20.

IXII-7

TABLE 6GROSS ALPHA, GROSS BETA, TRITIUM, IODINE-131 AND GAMMA* SPECTROMETRIC ANALYSIS OF

SUSQUEHANNA STEAM ELECTRIC STATION-1988Results are in units of pCi/g (dry)+ 2s

SURFACE WATER

Page 4 of 4

LOCATION

5SB

6S6

1D3

6SS

6S7

LTAW

12F1

12G2

12H1

COLLECTION

DATE

12/12/88 TO 01/03/8912/05/88 TO 01/03/8912/06/8812/12/88 TO 01/03/8912/05/88 TO 01/03/8912/06/8812/05/8812/05/8812/05/88 TO 01/03/89

GrossAlpha

LT 1

LT 1

LT 0.8LT 1

LT 2

LT 1

LT 0.8LT 0.8LT 1

GrossBeta

2.5 + 0.72.3 + 0.62.1 + 0.62 ' + 0.7

13.0 + 1.06.1 + 0.82.4 + 0.62.7 + 0.62.5 + 0.7

Tritien

160 + 5089 + 44

LT 70380 + 50

LT 70

LT 70LT 70

LT 90LT 90

I -131 K-40 Mn-54 Cr-51 Cs-137


(1) Intermittent sampling by the automatic composite sampler (ACS) - 02/04/88 to 02/09/88.

(2) Sr-89 and Sr-90 ana(yses were performed; results were less than LLD.

(3) Pump out of service - 01/25/88.

(4) No water flow through sampler - 02/08/88 to 02/15/88. Less than normal ~ater flow - 02/15/88 to 02/17/88./

<5) Excess water in collestion Jug - 03/10/88. Collection jug overflowing 03/14/88 and 03/16/88. ACS out of servicefor maintenance 03/16/88 to 03/17/88

'6)

Insufficient sample volune being collected - 04/07/88. ACS out of service briefly on 04/12/88 and 04/18/88.

(7) Sample not collected (sample hose outside of collecting Jug) - 08/29/88 to 09/01/88.

(8) Pump out of service - 09/07/88 to 09/08/88. ACS burping - 09/27/88 to 10/03/88. See section VI of this report.

(9) Pump out of service approximately five hours on 10/17/88. ACS burping.

(10) Insufficient sample collected by ACS; grab sample obtained on 12/05/88.

('ll) ACS burping.

(12) Pump out of service - 12/08/88. No sample collected 12/23/88 to 12/26/88. ACS burping.

XII-8

TABLE 7GROSS ALPHA, GROSS BETA, TRITIUM, IODINE-131, AND GAMMA SPECTROMETRIC* ANALYSES OF DRINKING 'MATER

SUSQUEHANNA STEAM ELECTRIC STATION. 1988Results are in units of pCi/l + 2s

LOCATION COLLECTION DATE

GrossAlpha

GrossBeta Tritium Cs-137 K-40

12H2R(1) 01/04/88 to 02/08/8812H2T 01/04/88 to 02/08/88

LT 1

LT 1

3.1 + 0.92.6 + 0.8

LT 90LT 70

12H2R

12H2T

02/08/88 t'o 03/07/8802/08/88 to 03/07/88

LT 1

LT 'I

2.8 + 0.92.4 + 0.9

140 + 30LT 80

12H2R12H21'3/07/88 to 04/04/8803/07/88 to 04/04/88

LT 0.9LT 1

3 ~ 2+ 0.82.3 + 0.8

LT 8075+ 36

12H2R

12H2T

04/04/88 TO 05/09/8804/04/88 TO 05/09/88

LT 0.8LT 0.8

2.8 + 0.92.0 + 0.8

110 + 50

100 + 40

12H2R(2) 05/09/88 TO 06/06/8812H2T 05/09/88 TO 06/06/88

LT 1

LT 1

4.6 + 1.23.5 + 1.1

LT 90LT 80

12H2R

12H2T

06/06/88 TO 07/05/8806/06/88 TO 07/05/88

LT 2LT 2

4.5'+ l.15.1+ 1 ~ 1

LT 90LT 60

12H2R

12H2T

08/08/8808/08/88

12H2R(3) 07/05/8812H2T 07/05/88

TO 08/08/88TO 08/08/88

TO 09/06/88TO 09/06/88

LT 2

LT 1

LT 1

LT 1

4.0 + 1.03.7 +,0.9

5.1 + 1.23.4 + 1.0

89 + 4983 +'41

LT 80LT 80

12H2R(4) 09/06/88 TO 10/03/8812H2T 09/06/88 TO 10/03/88

LT 1

LT 1

4.6+ 1.14.4 + 1.0

LT 8082 + 46

12H2R

12H2T

10/03/88 TO 11/07/8810/03/88 TO 11/07/88

LT 2LT 2

3.2 + 1.14.2 + 1.2

LT 80

LT 80

12H2R(5) 11/07/88 TO 12/05/8812H2T(6) 11/07/88 TO 12/05/88

12H2R(G) 11/21/8812H2R(G) 11/28/88

LT 1

LT 1

5.3 + 2.6LT 1

2.8 + 0.63.1 + 0.6

16.0 + 1.03.7 + 0.6

LT 6070 + 39

LT 70

LT 80

76+ 31

12H2R

12H2T

12/05/88 TO 01/03/8912/05/88 TO 01/03/89

LT 1

LT 1

2.5 + 0.72.4 + 0.7

LT 100 3.7 + 3.2LT 100

* Only gamna emitters detected are reported; typical LLD values are found in Table 20.(1) Collection jug found overflowing at sampling location 02/01/88 and 02/08/88. Timer was set at too

short an interval so that water was being sampled too frequently.(2) Pump out of service (turbidity line found closed); no sample was collected from 05/26/88 to 05/31/88.(3) Punp out of service - 07/18/88 to 07/22/88. Repairman left timer set improperly.(4) Too nach water being sampled. Mater Company personnel diverted hose from jug on 09/25/88.

.(5) Insufficient sample being collected by ACS ~ Grab samples obtained on 11/21/88 and 11/28/88.(6) Sr-89 and Sr-90 analyses were performed; results were less than LLD.

TABLE 8GAHHA* SPECTROHETRIC ANALYSIS OF ALGAE

SUSQUEHANNA STEAH ELECTRIC STATION - 1988

Results are in units of pCi/l (dry) + 2s

COLLECTION

LOCATION DATE Be-7 K-40 Hn-54 I -131 Cs-137 Ra-226 Th-228

AG-3 05/06/88 to 06/06/88AG-4 05/06/88 to 06/06/88

5.8 + 1.04.6+ 1.2

17.3 + 2.112.5 + 2.2 0.53 + 0.14 0.83 + 0 ~ 18 0.18 + 0.11 1.06 + 0.14

AG-3 06/06/88 to 07/05/88AG-4 06/06/88 to 07/05/88

14.3 + 2.47.4 + 2.5 0.39 + 0.15

0.51 + 0.27

AG-3

AG-4>C

AG-3

D AG-4

07/05/88 to 08/08/88 3.2 + 0.8 13.3 + 1.607/05/88 to 08/08/88 2.9 + 0.8 8.5 + 1 '

08/08/88 to 09/06/88 3.1 + 0.8 12.5 + 1.808/08/88 to 09/06/88 2.9 + 1.0 12.7 + 1.8

0.12 + 0.11 3.03 + 1.63 0.92 + 0.16

0.14 + 0.132 0.09 + 0.09 4.25 + 1.64 0.98 + 0.103.15 + 1.62'.85 + 0.13

AG-3

AG-4

09/06/88 to 10/03/88 2.6 + 1.4 10.7 + 2.209/06/88 to 10/03/88 3.6 + 1.3 14.8 + 2.4

0.40 + 0.160.42 + 0.14

0.17 + 0.19 0.97 + 0.151.39 + 0.20

AG-3

AG 4

10/03/88 TO 11/07/8810/03/88 TO 11/07/88

7.5 + 1.56.8 + 1.8

12.7+ 2.47.9 + 2.8

1.01 + 0.251.00 + 0.23

AG 3

AG 4

11/09/87 to 12/07/87 3.89 + 1.4 14.0 + 2.411/09/87 to 12/07/87 3.54 + 1.5 20.0 + 2.7

1.29 + 0.280.93 + 0.28

* Only gamna enitters detected are reported; typical LLD values are found in Table 20.

TABLE 9

GROSS BETA AND GAMMA» SPECTROMETRIC AHALYSIS OF FISH

SUSQUEHANNA STEAH ELECTRIC STATION - 1988

Results are in units of pCi/g (wet) + 2s

SAMPLE TYPE LOCAT I OH

COLLECTION GrossDATE Beta K-40 Cs-137

CHANNEL CATFISH

SMALLHOUTH BASS

WHITE SUCKER

2H

2H

2H

04/26/88 ,4.5 + 0.104/25/88 3.0 + 0.104/25/88 5 ' + 0.1

3.2 + 0.33.6 + 0.44.0 + 0.4

0.010 + 0.001

CHANNEL CATFISH

SMALLHOUTH BASS

WHITE SUCKER

IND

IND

IND

05/12/8805/12/8805/12/88

3.6 + F 1

3.9 + F 1

5.6 + 0.1

4.1 + 0.44.3 + 0.4,4.5 + 0.5

0.022 + 0.0080.012 + 0.010

CHANNEL CATFISH

LARGEMOU'IH BASS

LTAW

LTAW

06/01/8806/01/88

3.4 + 0.16.5 + 0.1

4 ' + 0.44.5 + 0.5 0.014 + 0.008

SMALLMOUTH BASS

CHAHNEL CATFISH

WHITE SUCKER

2H

2H

2H

11/09/8811/09/8811/09/88

3.5 + 0.17.6 + 0.37.5 + 0.2

3.7 + 0.43.6 + 0.44.2 + 0.4

0.013 + 0.0080.010 + 0.007

SMALLMOUTH BASS IND

WHITE SUCKER IHD

11/14/8811/14/88

11.0 + 1.03.3 + 0.1

4.3 + 0.44.7 + 0.5

0.012 + 0.0090.009 + 0.008

CHAHNEL CATFISH

LARGEMOUTH BASS

IND

LTAW

11/15/8811/15/88

3.8 + 0.14.6 + 0.1

3 ~ 5+ 0.44.3, + 0.4

0.014 + 0.007

* Only ganma emitters detected are reported; typical LLD values are found in Table 20

TABLE 10GROSS ALPHA, GROSS BETA, AND GANMA SPECTROMETRIC» ANALYSES OF SHORELINE AND FLOCCULATED SEDIHENT

Susquehanna Stean Electric Station- 1988Results in Units of pCi/g (dry) + 2 s

Page 1 of 1

COLLECTION

LOCATION DATE»»»28 06/02/882F 06/02/8878 06/02/88LTAM 06/04/8811C 06/03/8812F 06/06/88

GrossAlpha

»»»»»9.8 + 5.3

12.0 + 6.09.4 + 5.3

11.0 + 6.09.8 + 5.39.8 + 5.3

GrossBeta

31 +-322+ 336+ 332+ 323+ 333+ 3

Be-7

0.66 + 0.340.42 + 0.131.82 + 0.31

1.95 + 0.24

L'-40

11.8 + 1.27.93 + 0.799.77 + 0.9811.6 + 1.27.93 + 0.7910.8 + 1.1

Hn-54 Cs-137

0.08 + 0.040.08 + 0.010.20 + 0.03

0.07 + 0.030.1C + 0.02

Ra-226

1.51 + 0.551.06 + 0.211.18 + 0.402.08 + 0.331.70 + 0.51.45 + 0.34

Th-228

1.11 + 0.110.68 + 0.070.90 + 0.081.02 + 0.100.85 + 0.090.98 + 0.10

2B2F78LTAII11C

12F

12/12/8812/12/8812/12/8812/12/8812/12/8812/12/88

28(FLOG) 06/02/88

78(FLOG�)

06/02/8816.0 + 2.011.0 + 5.0

17.0 + 6.013.0 + 5.020.0 + 6.014 ' + 5.011.0 + 5.023.0 + 7.0

44+ 345+ 3

47+ 332+ 344+ 339+ 333+ 344+ 3

1.87 + 0.73

4.01 + 0.43

0.87 + 0.33

0.68 + 0.282.86 + 0.79

12.9 + 1.314.8 + 1.5

16.0 + 1.67.56 + 0.7612.7 + 1.312.5 + 1.39.38 + 0.941C.B + 1.5

0.12 + 0.07O.16 + O.OB

0.19 + 0.030.06 + 0.2-0.18 + 0.03

0.13 + 0.030.04 + 0.05 0.28 + 0.06

2.12 + 0.542.23 + 0.351.77 + 0.551.7C + 0.451.04 + 0.942.26 +.0.93

1.03 + 0.100.96 + 0.10

1.44 + 0.140.98 + 0.101.20 + 0.121.28 + 0.130.90 + 0.091.44 + 0.14

* Only gaama emitters detected are reported; typical LLD values are found on Table 20.

TABLE 11

GROSS ALPHA, GROSS BETA, TRITIUH, AND GAHHA SPECTROHETRIC» ANALYSES OF GROUND (MELL) MATER

Susquehanna Steam Electric Station- 1988Results in pCi/l + 2 s

LOCATION

12F3

2$64S2

4$411$ 5 .

12E4

COLLECTIOH

DATE

01/05/8801/05/8801/05/8801/05/8801/05/8801/05/88

GrossAlpha

LT 2

LT 2LT 2

LT 1

LT 2

LT 1

GrossBeta

2.6 + 0.9LT 0.9

2.3 + 1.02.0 + 0.7

LT 1

2.3 + 0.9

H-3

130 + 50LT 80

130 + 50

LT 70LT 70

170 + 40

Cs-137

'2F3

2$64$ 2

4S4

11$ 5

12E4

02/09/8802/09/8802/09/8802/09/88

"02/09/8802/09/88

LT 2LT 0.9LT 2

LT 0.8LT 2LT 2

2.0 + 1.1.LT1

3.2+ 1.31.4 + 0.8

LT 2

3.0 + 1.2

LT 80LT 70LT 80

LT 70LT 70

88 + 45

12F3~ 2$ 64$ 2

4S4

11$ 5

12E4

03/07/8803/08/8803/08/8803/07/8803/07/8803/07/88

LT 1

LT 1

LT 2

LT 0.9LT 2

LT 2

2.4 + 0.92.5 + 0.94.7 + 1.31.6 + 0.8

LT 1

2.6 + 1.1

180+ 4097+ 4485 + 45

LT 60120 + 4089 + 40

12F3

2$63S5

4$ 2

4S4

11$ 5

12E4

04/05/8804/05/8804/05/8804/05/8804/05/8804/05/8804/04/88

LT 1

LT 0.9LT 0.7LT 2LT 0.7LT 2

LT 1

1.8 + 1.1LT 1

1.8 + 0.82.2+ 1.31.3 + 0.8

LT 22.2+ 1 ~ 1

86+ 43LT 80LT 90

100 + 50LT 90LT 80

140 + 50

12F3

2$63SS

4S2

4S4'11$ 5

12F4

05/09/8805/09/8805/09/8805/09/8805/09/8805/10/8805/09/88

LT 1

LT 0.9LT 0.4LT 1

LT 0.7LT 2LT 2

1.8 + 1.0LT 1

1.8 + 0.81.9+ 1.11.3 + 0.8

LT 1

1.7+ 1.0

LT 70LT 60LT 90LT 90

120 + 5090 + 4985 + 49

12F32S6

3S54$ 2

4$4

11$ 5

12E4

06/07/8806/07/8806/07/8806/07/8806/07/8806/07/8806/07/88

LT 2LT 1

LT 0.84 ' + 2.7

LT 0.8LT 2LT 2

2.4 + 1.3LT 1

2.5 + 0.92.5 + 1.21.6 + 0.8

LT 1

2.7 + 1.3

LT 70LT 80LT 80LT 80LT 90LT 90LT 90

* Only kamsa emitters detected are reported; typical LLD values are found in Table 20.

XII-13

GROSS ALPHA, GROSS

TABLE 11

BETA, TRITlUH, AHD GAHHA SPECTROHETRIC* AHALTSES OF GROUND (MELL> MATER

Susquehanna Stean Electric Station- 1988Results in pCi/l + 2 s

LOCATlONSSR 0

12F3

2$ 63SS

4S24S4

11$ 5

12E4

COLLECTlOH

DATESRCCRRRCR

07/05/8807/05/8807/06/8807/05/8807/05/8807/05/8807/05/88

GrossAlphaRESS@ 8

LT 2LT '1

LT 1

LT 2LT 1

LT 2LT 2

GrossBets

2.5 + 1.0LT 2

1.8 + 0.73.6+ 1 ~ 22.2 + 0.8

LT 1

3.1+ 1.1

H-3

130 + 40170 + 50100 + 50150+ 50110 + 5080 + 39

130 + 40

Cs-137

12F3

2$ 63S54$ 24S4

11$ 5

12E4

08/09/8808/06/8808/06/8808/06/8808/09/8808/09/8808/06/88

LT 2LT 1

LT 0.8LT 2

LT 0.9LT 2LT 2

2.5 + 1.0LT 1

1.9 + 0.74 ~ 1+ 1.23.3 + 0.8

LT 1

2.3 + 0.9

LT 80LT 60LT 70

54 + 33120 + 40

LT 8067 + 37

12F3

2$63$ 5

4$ 2

4S4

11$ 5

12E4

09/06/8809/07/8809/07/8809/06/8809/07/8809/07/8809/06/88

LT 2

LT 0.9LT 0.8LT 2LT 2LT 2

LT 2

2.5 + 1.01.1 + 0.72.5 + 0.82.5 + 1.13.2+ 1.2

LT 1

2.7+ 1.1

61+ 37LT 80LT 80LT 60LT 70

74+ 4486+ 47

2.4 + 2.1

4.6 + 3.3

12F32$ 63S5

4S2

4S4

11$ 5

12E4

10/03/8810/04/8810/04/8810/04/8810/04/8810/04/8810/03/88

LT 2LT 0.9LT 0.8LT 2LT 0.8LT 2

LT 2

2.3 + 1.11.0 + 0.72.3 + 0.83.3 + 1.22.0 + 0.'8

LT 1

1.6 + 1.0

LT 80LT 80

100 + 50

LT 80LT 80LT 70

77 + 44

12F32S6

4$ 24$411$ 5

12E4

11/07/8811/08/8811/08/8811/08/8811/07/8811/07/88

LT 2

LT 1

LT 2LT 1

LT 2LT 2

1.9 + 1.12.4 + 0.93.2 + 1.32.0 + 0.9

LT 22.1 + 1.1

LT 60LT 80

120 + 50

LT 70LT 80LT 60

12F32$64$ 24S4

11$ 5

12E4

12/06/8812/06/8812/06/8812/06/8812/06/8812/06/88

LT 1,

LT 0.8LT 2LT 1

LT 2LT 1

2.0 + 0.71.0 + 0.52.3 + 0.81.9 + 0.6

LT 1

2.3 + 0.7

LT 80LT 70

59 + 33LT 80LT 90

91 + 51

~ Only ganma emitters detected are reported; typical LLD values are found in Table 20.

XII-14

TABLE 12GROSS BETA ANALYSES OF AIR PARTICULATE FILTERS

Susquehanna Steam Electric Station- 1988Resuits in E-03 pCi/cubic meter + 2 s

Page 1 of 2

HON IN

JAN

COLLECTION OA'TE

Ol/05/88 to 01/12/8801/12/88 to 01/19/8801/19/M to 01/27/8801/27/M to 02/02/88

TG1

24+ 220+ 221+26+ 2

12G1

25+224+215+222+2

2S2

23+222+ 215+ 219+ 2

5S4

24+ 222+ 215+220+ 2

11S2

25+222+215+217+ 2

15S4

24+ 221+215+219+ 2

9B1 1D2

24 + 2 26 + 224+2 23+216 + 2 1T + 2

110 + 10(1) 18 + 2

3D1

25+ 221 + 215+ 218+ 2

12E1

25+ 224+ 225+ 221+2

FEB 02/02/8& to 02/09/8802/09/88 to 02/16/M02/16/M to 02/23/M02/23/88 to 03/01/88

HAR 03/01/88 to 03/08/8803/08/88 to 03/15/8803/15/88 to 03/22/8803/22/88 to 03/29/8803/29/88 to 04/05/88

APR 04/05/88 to 04/12/8804/12/88 to 04/19/8804/19/88 to 04/26/8804/26/88 to 05/03/M

20+ 218+ 213+ 215+2

17+ 211+210+214+ 217+ 2

T+214+ 215+ 211+2

22+ 221 + 213+ 214+ 2

16+ 212+210+ 215+219+ 2

9+214+ 214+ 210+ 2

24+ 223+ 213+215+2

16+ 212+ 210+ 215+ 216+ 2

9+213+216+ 211+ 2

19+ 220+ 212+ 213+ 2

16+ 212+ 29+2

15+ 218+ 2

9+213+ 214+ 28+2

21+219+ 215+ 214+ 2

15+ 211+ 210+ 21&+ 218+ 2

9+214+ 216+ 28+2

22+ 218+ 213+ 213+ 2

16+ 211+210+ 216+ 216+ 2

9+213+214+29+ 2

22 t19+ 214+ 214+ 2

18+ 213+210+216+ 216+ 2

9+216+ 216+ 210+ 2

23+ 219+ 213+ 215+2

16+ 213+210+ 216+ 217+ 2

9+212+ 215+210+2

20+ 219+ 211+ 2-14+2

16+ 211+ 211+ 215+ 216+ 2

8+213+ 213+29+2

23+220+ 214+ 214+ 2

16+ 212+ 29+2

15+216+ 2

8+215+ 215+ 29+2

HAY 05/03/8805/10/8805/17/8805/24/8805/31/88

to 05/10/88to 05/17/88tP 05/24/Mto 05/31/88to 06/07/88

14+210+ 210+ 21&+ 215+2

14+212+ 29+ 2

19+ 213+ 2

15+212+ 210+ 215+213+ 2

13+ 211+ 210+216+ 212+2

12+ 211+210+ 217+212+ 2

14+212+ 210+ 214+ 212+ 2

13+ 213+211+ 217+ 213+ 2

13+212+211+217+ 213+ 2

12+ 211+ 2ll + 218+ 211+ 2

11+ 211+ 212+ 216+ 212+ 2

JUNE 06/07/88 to 06/14/8806/14/88 to 06/21/8806/21/M to 06/28/8806/28/88 to 07/05/88

JULY 07/05/88 to 07/12/8807/12/88 to 07/19/8807/19/88 to 07/26/8807/26/SS to OS/O2/SS

14 + 224+215+211+ 2

31+ 217+ 212+ 223+ 2

18+ 229+ 316+ 212+ 2

37+ 319+ 215+224+ 2

16+ 226+ 216+ 210+ 2

36+315+ 214+223+ 2

15+ 224+ 214+29+ 2

37+ 318+ 214+222+ 2

15+223+ 315+29+2

32.+ 3'16+ 213+ 222+ 2

15+ 225+ 214+ 29+2

33 + 2(2)17+ 214+224+ 2

17+ 226+ 215+210+ 2

38+318+ 215+222+ 2

17+ 225+ 216+ 211+2

37+ 318+215+222+2

19+ 225 + 2(2)15+ 210+2

34 + 3(2)17+ 214+224+ 2

16+ 228+ 316+ 212+ 2

34+ 315+ 214+ 222+ 2

TABLE 12GROSS BETA ANALYSES OF AIR PARTICULATE FILTERS

Susquehanna Steam Electric Station- 1988Results in E-03 pCi/cubic meter + 2 s

Page 2 of 2

HONTH

AUG

COLLEC'IION DATE

08/02/88 to 08/09/8808/09/88 to 08/16/8808/16/88 to 08/23/8808/23/88 to 08/30/8808/30/88 to 09/06/88

7G1

14+ 227 + 2.13+ 219+ 214+ 2

12G1

16+ 231+214+220+214+2

2S2

17+ 229+ 215+217+ 214+ 2

5S4

15+ 229+ 215+ 218+ 213+ 2

11S2

16+ 228+ 212+ 218+ 212+2

15S4

16+ 229+ 215 + 2(3)

LT 215+2

981

15+ 230+ 215+ 217+ 214+ 2

102

16+ 229+ 214+220+ 213+ 2„

3D1

14+229+ 214+219+ 214+ 2

12E1

13+ 232+ 214+ 219+ 213+ 2

SEPT 09/06/88 to 09/13/8809/13/88 to 09/20/8809/20/88 to 09/27/8809/27/88 to 10/04/88

OCT 10/04/88 to 10/11/8810/11/88 to 10/18/8810/18/88 to 10/25/8810/25/88 TO 11/01/88

17+ 217+ 218+ 221+ 2

14+ 215+ 210+ 217+ 2

19+ 2„16+ 2

18+ 22'I+2

15+ 221+211+217+ 2

16+ 216+ 217+ 222+ 2

17+ 216+ 211+216+ 2

18+ 215+214+219+ 2

12+ 217+ 211+215+2

19+ 216+ 216+ 221+ 2

13+ 215+ 212+217+ 2

18+ 217+ 217+ 221+2

14+ 215+212+ 218+ 2

17+ 217+ 216+ 221+2

14+ 217+ 211+ 218+ 2

18+ 218+ 215+222+2

14+218+ 228+ 217+ 2

18+ 214+ 215+ 222+ 2

13+215+29+2

16+ 2

17+ 215+215+221+ 2

15+219+ 212+ 216+ 2

NOV 11/01/88 TO 11/08/8811/08/88 TO 11/15/8811/15/88 TO 11/22/8811/22/88 TO 11/29/8811/29/88 TO '12/06/88

16+ 214+ 216+ 220+ 221+ 2

17+ 216+ 217+ 223+ 221+2

17+ 217+ 217+ 221+221+2

16+ 213+ 216+221+ 221+2

17+ 213 + 2(4)16+ 220+222+ 2

16+ 215+216+ 223+222+ 2

16+ 214+ 217+ 223 + 2(5)24+ 2

19+ 216+ 218+ 221+ 224+2

17+ 21'1+215+219+ 222+ 2

17+ 215+ 218+ 222+ 223+ 2

DEC '12/06/88 TO 12/13/88'12/13/88 TO 12/20/8812/20/88 to '12/27/8812/27/88 to 01/03/89

21+ 220+ 219+ 229+ 3

23+ 221 + 219+ 230+ 2

22+ 222+ 220+ 226+ 2

22+222+ 2

15 + 2(6)27+ 2

21+221+218+ 229+ 3

21+219+ 217+ 229+ 2

24+221+218+ 230+ 2

24+ 223+ 221+228+ 2

24+ 223+ 219+ 226+ 3

24+ 223+ 217+ 230+ 2

(1) Low volune indicated on dry gas meter - voiune indicated is thought to be lover than voiune sarpied due to stickingdigits on dry gas meter. Result reported is invalid.

(2) Hole in air filter.(3) Electricity out of service - 08/24 to 08/30/88.(4) Electricity out of service for approximately 20 minutes - 11/15/88.(5) Electricity out of service for approximately 15 minutes - 11/23/88.(6) Electricity out of service for approximately 30 minutes - 12/09/88.

of 1

TABLE 13

GROSS ALPHA AND GAMMA SPECTROMETRIC» ANALYSES OF COMPOSITED AIR PARTICULTE FILTERS

Susquehanna Steam Electric Station- 1988Results in E-03 pCi/cubic meter + 2 s

LOCATION

7G1

12G1

2S2

SS4

11S2

15S4

981

1D2

301

12E1

COLLECTION DATE

01/05/88 to 04/05/8801/05/SS to 04/05/8801/05/88 to 04/05/M01/05/88 to 04/05/8801/05/88 to 04/05/8801/05/88 to 04/Q5/8801/05/88 to 04/05/N01/05/88 to 04/05/8801/05/88 to 04/05/8801/05/88 to 04/05/88

Gr ossAlpha

S

2.0 + 0.32.3 + 0.32.6 + 0.32.8 + 0.32.3 + 0.32.3 + 0.32.5 + 0.32.4 + 0.32.8 + 0.32.9 + 0.4

Be-7=mama

54+ 5

60+ 662+ 662+ 664+ 659+ 659+ 663+663+659+6

K-CQ

3.2 + 1.7

3.5 + 1.6

7G1

12G1

2S2

SS4

11S2

15S4

9811D2

301

12E1

QC/05/88 to 07/05/N,04/05/88 to 07/05/8804/05/88 to 07/05/88OC/05/88 to 07/05/8804/05/88 to 07/05/8804/05/88 to OF/05/8804/05/88 to 07/05/8804/05/88 to 07/05/8804/05/88 to 07/05/8804/05/SS to 07/05/88

1.8 + 0.32.2 + 0.42.1 + 0.32.1 + 0.41.9 + 0.31.8 + 0.31.8 + 0.31.3 + 0.11.3 + 0.32.1 + 0.3

68+ 773+772+ 784+ 870+ 783+ 883+881+874+ 776+ 8

3.2 + 1.83.2 + 1.86.9 + 1.84.0 + 1.75.0 + 2.74.4 + 2.04.4 + 2.0

6.0 + 2.2

7G1

12G1

2S2

5S4

11S2

15S4

9B1

1D2

3D1

12E1

701

12Gl2S25S4

~ 11S215S4

9B1

1D2

301

12E1

07/05/88 to 10/QC/8807/05/88 to 10/04/8807/05/88 to 10/04/M07/05/88 to 10/04/8807/05/88 to 10/04/8807/05/Ss to 10/04/SS07/05/88 to 10/04/8807/05/88 to 10/04/8807/05/N to 10/04/M07/05/88 to 10/05/M

10/04/88 TO 01/03/8910/04/88 TO 01/03/8910/04/88 TO 01/03/8910/04/88 TO 01/03/8910/04/88 TO 01/03/8910/Q4/88 TO 01/03/8910/04/88 TO 01/03/8910/04/88 TO 01/03/8910/04/88 TO 01/03/8910I04/88 TO 01/03/89

2.8 + Q.C

3.0 + 0.52.7 + 0.43.1 + 0.42.6 + 0.42.9 + 0.42.5 + 0.42.8 + 0.41.6 + 0.32.4 + 0.4

2.3 + 0.43.2 + 0.42.8 + 0.42.9 + 0.52.7 + 0.52.1 + 0.52.4 + 0.42.5 + 0.52.6 + 0.63.0 + Q.6

65+ 759+ 664+666+ 760+653+ 568+ 766+ 765+76&+7

H

C9+ 555+ 654+ 546+ 553+ 5

54+ 556+ 651+ 5

53+ 5

ss+ 6

3.5 + 1.95.6 + 2.37.9 + 2.13.8+ 1.7

4.8 + 1.3

~ Only gamna emitters detected are reported; typical LLD values are found in Table 20.

LOCATION COLLECTION PERIODSS SS SS S SSS

7G1 01/05/88 to 04/05/8812G1(1)(2)01/05/88 to 04/05/882$ 2 01/05/88 to 04/05/N5S4 01/05/88 to 04/05/8811S2 01/05/SS to 04/05/N15S4(3) 01/05/88 to 04/05/N981 01/05/88 to 04/05/881o2 01/05/SS to 04/05/88301 01/05/SS to 04/05/SB12E1 01/05/88 to 04/05/88

Gross AlphaS S SS SSS

0.71 + 0.330.84 + 0.300.94 + 0.321.0 + 0.3

LT 0.60.77 + 0.280.33 + 0.17

LT 0.60.65 + 0.27

LT 0.6

Gross Beta TritiunSSS

4.5 + 0.7 LT 2004.8 + 0.7 LT 805.6 + 0.8 LT 804.8 + 0.7 LT 904.8 + 0.7 130 + 503.3 + 0.6 LT 605.1 + 0.8 LT 903.7 + 0.7 LT 603.7 + 0.7 LT 704.9 + 0.7 LT 80

Be-7

TABLE 14

GROSS ALPHA, GROSS BETA, TRITIUH, AND GAHHA SPECTROMETRIC» ANALYSES

Susquehanna Steam Electric Station- 1988Results in pCi/l + 2 s

I(-40

Page 1 of 1

Cs-137

OF PRECIPITATION

70112G'I

2S25S411S2

15S4(4)(5981102

30112E1

04/05/8804/05/8804/05/8804/05/8804I05ISS

)04/05/BS04/05/8804/05/8804/05/8804/05/88

to 07/05/Nto 0?/05/88to 07/05/88to 07/05/Nto 07/05/88to 07/05/88to 07/05/88to 07/05INto 07/05/Nto 07/05/88

0.75 + 0.261.1 + 0.3

LT 0.30.52 + 0.24

LT 0.30.46 + 0.240.35 + 0.220.57 + 0.210.46 + 0.210.71 + 0.24

5.5 + 0.86.6 + 0.95.3 + 0.94.9 + 0.83.9 + 0.85.9 + 0.94.1 + 0.83.9 + 0.73.5 + 0.74.5 + 0.8

240 + 40180 + 50190 + 50160 + 50120 + 40190 + 50160 + 50

69+ 41

110 + 5095+ 52

46 + 2&

10.3 + 4.3

7G1

1201

2S2SS4'L1S2

15S4(6)9811023D1

12E1

07/05/8807/05/8807/05/8807/05/880?/05/8807/05/8807/05/8807/05/8807/05/8807/05/88

TO 10/04/88TO 10/04/88TO 10/04/88TO 10/04/88TO 10/04/88TO 10/04/88TO 10/04/88TO 10/04/88To 10/04/88To 10/04/88

0.66 + 0.271.5 + 0.3

0.78 + 0.420.63 + 0.24

LT 0.60.88 + 0.270.?3 + 0.260.97 + 0.290.51 + 0.230.89 + 0.28

5.8 + 0.94.8 + 0.84.6 + 0.85.0 + 0.83.7 + 0.83.8 + 0.84.9 + 0.84.2 + 0.83.3 + 0.74.4 + 0.8

LT 80LT 60

M+3677+ 45

100 + 50110 + 40

LT 100LT 60LT. 60LT 60

7G1

12G1

2S2

5$411S2

15S4

981

1D2

3D1

12E1

10/04/8810/04/8810/04/8810/04/8810/04/8810/04/8810/04/8810/04/8810I04/8810/04/S8

TO 01/03/89To 01/03/89TO 01/03/89To 01/03/89TO O1/O3/89To 01/03/89TO 01/03/89TO 01/03/89TO 01/03/89TO 01/03/89

I'.36

+ 0.280.71 + 0.320.63 + 0.330.57 + 0.31

LT 0.40.59 + 0.310.39 + 0.28

LT 0.30.44 + O.280.45 + 0.28

3.4 + 0.53.2 + 0.54.0 + 0.62.7 + 0.52.1 + 0.53.5 + 0.53.2 + 0.52.4 + 0.52.3 + 0.53.2 + 0.5

LT 80130 + 50100+ 40120 + 5089+ 29

140 + 5073+ 39

LT 9071 + 3691 + 57

2.3 + 2.5

* Only ganrna emitters detected are reported; typical LLD's are found in TabLe 20.(1) All but one gallon Lost due to cracked jug - 02/02/SS to 02/09/88.(2) Corryositors draw dow to one. half volune to accomodate coLlections.(3) All but one gallon Lost due to leaking spigot - 02/16IN to 03/29/88.(4) Leak in collection tray - 04/19/N to 05/03/88.(5) Corrpositors draw dow to one. half voLune to accomodate collections.(6) Compositors draw dow to either one-half or one-fourth volune to acccmodate collections.

XII-18

TABLE 15

GROSS BETA MINUS K-40, IODINE-131, AND GAMMA SPECTROMETRIC ANALYSES OF MILKSusquehanna Steam Electric Station- 1988

Results in pCi/l + 2 s Page 1 of 4

LOCATION

10G1

1282

1283

6C1

10D1

12D2

5E1

13E3

14B1

COLLECTION

DATE

01/04/8801/04/8801/04/8801/04/8801/04/8801/04/8801/04/8801/04/8801/04/88

Gross Betaminus K-40

6.3 + 2.84.2 + 1.7

12.0 + 2.03.9 + 1.87.4 + 1.82.9 + 1.65.1 + 1,84.9 + 2.07.0 + 1.8

K-40

1300 + 130

1290 + 1301010 + 100

1290 + 1301260 + 130

1310 + 130

1150 + 110

1220 + 120

1070 + 110

Cs-137 Sr-90

10G1

1282

1283

6C1

1001

1202

SE1

13E3

1481

02/08/8802/09/8802/08/8802/08/8802/08/8802/08/8802/08/8802/08/8802/08/88

9.9 + 2.04.6 + 1.7

15 ~ 0 + 2.06.3 + 1.88.0 + 1.83.7 + 1.68.0 + 1.92.8 + 1.65.4 + 1.9

1350 + 1301290 + 130

1090 + 110

1090 + 1101250 + 120

1340 + 1301060 + 110

1360 + 140

1190 + 120

3.1 + 2.83.7 + 2.6 3.9 + 0.8

10G1

1282

1283

6C1

1001

12D2

SE1

13E3

1481

03/07/8803/07/8803/07/8803/07/8803/07/8803/07/8803/07/8803/07/8803/07/88

14.0 + 2.05.7 + 2.0

20.0 + 3 '9.0 + 2.29.6 + 2.25.4 + 1.75.6 + 2.06.9 + 2.15.6 + 2.1

1290 + 1301380 + 140

1280 + 1301280 + 130

1100 + 110

1110 + 1101270 + 130

1260 + 130

1260 + 130

3.2 + 2.97.9 + 1.1

'IOG1

1282

1283

6C1

1001

1202SE1

13E3

14B1

04/04/8804/04/8804/04/8804/04/8804/04/8804/04/8804/04/8804/04/8804/04/88

12.0 + 2.02.9 + 1.79.9 + 2.07.3 + 2.08.2 + 2.03.1 + 1.75.8 + 1.9,2.9 + 1.75.9 + 2.0

1190 + 120

1430 + 140

1310 + 130

1220 + 120

1140 + 110

1240 + 120

1210 + 1201290 + 1301190 + 120

3.9 + 3.14 + 3.2

10G1

128210D1

5E1

13E3

1481

04/18/8804/18/8804/18/8804/18/8804/04/8804/18/88

LT 4

LT 4

LT 4

LT 4LT 4

LT 4

1280 + 130

1400 + 140

1060 + 110

1340 + 130

1320 + 130

1190 + 120

2.9 + 1.6


TABLE 15

GROSS BETA MINUS K-40, IODINE-131, AND GAMMA SPECTROMETRIC ANALYSES OF MILKSusquehanna Steam Electric Station- 1988


LOCATION

10G1

12821283

6C1

10D1

1202SE1

13E3

1481

COLLECTION

DATE

05/09/8805/09/8805/09/8805/09/8805/09/8805/09/8805/09/8805/09/8805/09/88


11.0 + 2.0.3.5+ 1.720.0 + 2.07.7 + 1.89.1 + 2.04.7 + 1.65.6 + 1.84.0 + 1.78.0 + 1.8

K-40

1230 + 120

1210 + 120

1300 + 130

1300 + 1301260 + 1301080 + 110

1330 + 1301340 + 1301190 + 120

Cs-137 Sr-90

5.8 + 0.9

10G1

12821001

SE1

13E3

1481

10G1

1282

12836C1

10D1

12025E1

13E3

14B1

05/23/8805/23/8805/23/8805/23/8805/24/8805/23/88

06/06/8806/06/8806/06/8806/06/8806/06/8806/06/8806/06/8806/06/8806/06/88

9.9 + 2.19.5 + 3.39.2 + 2.28.3 + F 1

2.7 + 1 '10.0 + 2.0

14.0 + 2.03.6 + 2.0

17.0 + 2.07.6 + 2.16.0 + 2.13.3 + 1.95.3 + 2.04.9 + 2.0

12.0 + 2.0

1360 + 1401340 + 1301270 + 1301260 + 1301340 + 130

1360 + 140

1460 + 150

1580 + 160

1180 + 1201180 + 1201370 + 140

1310 + 1301320 + 1301520 + 150

1340 + 130

3.5 + 3.3

4.9 + 3.4

5.4 + 3.48.5 + 0.9

10G1

12821001

5E1

13E3

1481

06/20/8806/20/8806/20/8806/20/8806/20/8806/20/88

9.3 + 2.24.0 + 2.06.2 + 2 '5.1 + 2.03.9 + 1.99.3 + 2.2

1260 +130'370

+ 140

1470 + 1501390 + 140

1610 + 160

1260 + 130

4.3 + 4.0

10G1

1282

12836C1

10D1

12D2

5E1

13E3

1481

07/05/8807/05/8807/05/8807/05/8807/05/88

'7/05/8807/05/8807/05/8807/05/88

11.0 + 2.03.6 + 2.1

16.0 + 3.08.9 + 2 '5.0 + 2.03.5 + 2.05,5 t 2.05.2 + 2.09.1 + 2.2

1400 + 140

1400 + 140

1270 + 1301380 + 1401420 + 140

1310 + 1301410 +,1401310 + 1301350 + 140 6.1 + 3.2

6.1 + 0.9

* Only garnna emitters detected are reported; typical LLD values are found in Table 20.

TABLE 15

GROSS BETA HINUS K-40, IODINE-131, AND GAHHA SPECTROHETRIC* ANALYSES OF HILKSusquehanna Steam Electric Station- '988


LOCATION

1001

1282

10D1

5E1

13E3

1481

COLLECTION

DATE

07/20/8807/20/8807/20/8807/20/8807/20/8807/20/88


11.0 + 3.0LT 3

7.1 + 2.216.0 + 2.04.8 + 2.08.3 + 2.5

K-40

1240 + 120

1400 + 140

1310 + 130

1540 + 150

1410 + 140

1420 + 140

Cs-137

5.2 + 4.6

Sr-90

2.2 + 0.7

10G1

1282

1283

6C1

1001

12D2

SE1

13E3

1481

08/06/8808/06/8808/06/8808/06/8808/06/8808/06/8808/06/8808/06/8808/06/88

9.2 + 1.93.5 + 1.6

18.0 + 2.09.0 + 1.97.4 + 1.73.9 + 1.65.1 + 1.75.7 + 1.7

10.0 + 2.0

1340 + 130

1570 + 1601340 + 130

1370 + 140

1340 + 130

1390 + 140

1310 + 1301450 + 150

1410 + 140

2.2 + 0.8,

10G1

1282

1001

5E1

13E3

1481

08/22/8808/22/8808/22/8808/22/8808/22/8808/22/88

6.8 + 1.83.8 + 1.77.1 + 1.95.3 + 1.75.6 + 1.86.8 + 1.8

1500 + 150

1660 + 170

1330 + 1301660 + 1701390 + 140

1500 + 150

10G1

12B2

12836C1

10D1

12D2

5E1

13E3

1481

09/06/8809/06/8809/06/8809/06/8809/06/8809/06/8809/06/8809/06/8809/06/88

8.2 + 2 'LT 3

13.0 + 2.012.0 + 2.06.2 + 1.97.1 + 1.99.7 + 2.03 ' + 1 '7.0 + 2 '

1430 + 1401490 + 1501370 + 1401310 + 1301380 + 140

1380 + 140

1310 + 130

1300 + 1301250 + 120

5.5 + 3.9

10G1

1282

1001

5E1

13E3

1481

09/19/8809/19/8809/19/8809/19/8809/19/8809/19/88

9.2 + 2.04.8 + 1.99.3 + 2.05.8 + 1.96.5 + 2.0

11.0 + 2.0

1330 + 130

1440 + 140

1200 + 120

1400 + 140

1400 +. 1401300 + 130

5.1 + 4 '

10G1

1282

12836C1

10/03/8810/03/8810/03/8810/03/88

7.5 + 1.76.4 + 1.6

14.0 + 2.07.9 + 1.7

1510 + 1501380 + 1401260 + 1301400 + 140


.TABLE 15

GROSS BETA HINUS K-40, IODINE-131, AND GAHHA SPECTROHETRIC* ANALYSES OF HILKSusquehanna Steam Electric Station- 1988

Results in pci/l + 2 s Page 4 of 4

COLLECTION Gross BetaLOCATION'ATE minus K-40 K 40 Cs-137 Sr-90

10D1

12D2

5E1

13E3

14B1

10/03/8810/03/8810/03/8810/03/8810/03/88

12.0 + 2.08.2 + 1.86.7 + 1.76.4 + 1.78.2 + 1.8

1320 + 130

1090 + 110

1390 + 140

1450 + 140

1160 + -120

4.8 + 4.7

10G1

12821001

5E1

13E3

14B1

10/17/8810/17/8810/17/8810/17/8810/17/8810/17/88

9.6 + 2.612.0 + 2.010.0 + 3.09.2 + 2.67.0 + 2.5

14.0 + 2.0

1590 + 160

1500 + 150

1270 + 1301340 + 130

1370 + 1401310 + 130

10G1

1282

12836C1

10D1

1202

5E1

13E3

1481

11/07/8811/07/8811/07/8811/07/8811/07/8811/07/8811/07/8811/07/8811/07/88

13.0 + 3.08.1 + 3.3

21.0 + 4.05.3 + 2.8

13.0 + 3.03.0 + 1.97.6 + 3.06.7 + 3.0

10.0 + 3.0

1370 + 1301330 + 130

1120 + 1101420 + 140

1380 + 1401310 + 130

1200 + 1201390 + 1401360 + 140

7.5 + 4.9 1.2 + 0.5

3.2 + 3.5

10G1

12821283601

10D1

1202

5E1

13E3

1481

12/05/8812/05/8812/05/8812/05/8812/05/8812/05/8812/05/8812/05/8812/05/88

7.8 + 2.67.6 + 2.7

13.0 + 3.04.7 + 2.69.3 + 2.8

LT 4

5.5 + 2.6F 1 + 2.65.3 + 2.6

1340 + 130

1540 + 1501090 + 1101330 + 130

1400 + 140

1320 + 130

1310 + 130

1280 + 130

1310 + 130 6.1 + 4.2


XII-22

TABLE 16

GAMMA SPECTROHETRIC* ANALYSES OF SOIL

Susquehanna Steam Electric Station- 1988

Results in pCi/g (dry) s 2 s

Page 1 of 1

LOCATION

COLLECTION

DATE K-40 Cs-137 Ra-226 Th.228 Other Activity

7G1 BOTTOM

7G1 TOP

09/30/8809/30/88

13 s 1

12'0.23 s 0.040.21 x 0.04

1.6 s 0.61.9 s 0.7

0.95 s 0.100.90 s 0.09

12G3 BOTTOH

12G3 TOP

09/30/8809/30/88

9.8 s 1.0 0.14 s 0.040.16 s 0.04

1.8 s 0.51.6 s 0.6

1.2 I 0.10.90 s 0.09

2S4 BOTTOM

2S4 TOP

09/29/8809/29/88

9.8 s 1.010 s 1

0.14 'x 0.020.11 s 0.03

1.1s031.2 s 0.4

0.75 s 0.080.79 s 0.08

5S5 BOT'TOH

5SS TOP

09/29/8809/29/88

10+ 1

9.3 s 0.90.12 s 0.020'.11 s 0.03

1.41.2

s 0.4s 0.4

0.85 s 0.090.79 s 0.08

11S4 BOTTOH

11S4 TOP

09/30/8809/29/88

8.5 s 0.98.6 s 0.9

0.27 * 0.052.01 s 0.20

Ilf

1.4s06 0.53 s 0.050.76 s 0.09

15S4 BOTTOH

15S4 TOP

09/30/8809/30/88

8.6 s 0.98.9 s 0.9

0.10 s 0.030.19 s 0.03 .

1.8 s 0.61.6 s 0.5

0.81 s 0.090.81 x 0.09

982 BOTTOH 09/30/88982 TOP . 09/30/88

8.6 s 0.98.9 s 0.9

0.32 s 0.030.26 s 0.04

1.2 s 0.31.1 s 0.6

0.60 s 0.06 Mn-54 0.01 + 0.010.60 s 0.06

1D4 BOTTOH

1D4 TOP

09/29/8809/29/88

7.9 s 0.811 s 1

0.66 s 0.070.39 s 0.05

2.0 x 0.81.2 s 0.6

1.2 s 0.10.94 s 0.09

3D2 BOTTOH 09/29/88 9.8 s 1.03D2 TOP 09/29/88 9.2 s 0.9

0.43 s 0.040.81 s 0.09

" 2.5 s 0.52.7 s 0.5

1.7 s 0.2 Ce-141 0.09 s 0.061.7 s 0.2

12E2 BOTTOH 09/30/88 11 x 1

12E2 TOP 09/30/88 11 s 1

0.59 s 0.060.74 s 0 ~ 08

1.3 s 0.41.3 s 0.6

0.76 s 0.080.69 x 0.07

AREA 1 TOP 08/19/88 8.0. s 0.8AREA 1 BOTTOM 08/19/88 7.7 x 0.8

0.29 s 0.030.31 s 0.03

2.5 s 0.41.6 s 0.4

0.87 s 0.090.92 s 0.09

AREA 2 TOP 08/19/88 9.1 s 0.9 0.32 s 0.04AREA 2 BOTTOH 08/19/88 9.0 s 0.9 ,0.34 s 0.03

2.2 s 0.5 1.0 s 0.12.1 s 0.5 0.97 i 0.10

AREA 3 TOP 08/19/88 7.8 s 0.8 0.36 s 0.03AREA 3 BOTTOH 08/19/88 7.8 s 0.8 0.30 s 0.03

1.9 s 0.4 0.90 s 0.091.9 s 0.3 0.92 s 0 '9

* Only gamna emitters detected are reported; typical LLD values are found on Table 20.

XII-23

TABLE 17GAMMA SPECTROMETRIC» ANALYSES OF VEGETATION

Susquehanna Stean Electric Station- 1988Results in pCi/g (wet) + 2 s Page 1 of 1

COLLECTION

LOCATION DATE Be-7»»»»»»$ $ »»»»»»»» »$ $ » »»»»

7G1 09/30/88 0.83 + 0.1212G3 09/29/88 0.42 + 0.09.2S4 09/29/BS 0.58 + 0.135SS 09/29/88 0.31 + 0.1311S4 09/30/88 0.59 + 0.1015S4 09/30/88 0.52 + 0.12982 09/30/88 0.58 + 0.13104 09/29/SS 0.71 + 0.10302 09/29/88 1.32 + 0.1312E2 09/30/88 0.45 + 0.11

K.40

6.46 + 0.655.25 + 0.525.72 + 0.575.04 + 0.5010.6 + 1.103.S3 + 0.388.27 + 0.834.05 + 0.407.79 + 0.785.30 + 0.53

Cs-137»»»»»»» »»

0.01 + 0.01

0.02 + 0.01

0.01 + 0.01

* Only gwnae emitters detected are reported; typical LLO values are found in Table 20.

XII-24

TABLE 18 Page 1 of 5

GAMMA SPECTROMETRIC* ANALYSES OF FOOD PRODUCTS (FRUITS, VEGETABLES, AND HONEY)

Susquehanna Steam Electric Station- 1988

Results in pCi/g (wet) + 2 s

LOCATION/TYPE

2H1 APPLES CORTLAND

2H1 APPLES MACINTOSH

2H1 APPLES MACIN'TOSH

2H1 APPLES CORTLAND

5S4 APPLES

11D1 APPLES

12B1 APPLES CORTLAND

1281 APPLES MACINTOSH

782 APPLES CORTLAND

782 APPLES MACINTOSH

782 APPLES MACIN'TOSH

782 APPLES CORTLAND

1281 APPLES CORTLAND

12B1 APPLES MACINTOSH

COLLECTIO

DATE

10/03/8810/03/8810/05/8810/05/8809/06/8809/07/8810/03/8810/03/8810/04/8810/04/8810/06/8810/06/8810/06/8810/06/88

N

K-40

0.70 + 0.101.00 + 0.100.80 + 0.100.70 + 0.100.10 + 0.01,0.96 + 0.131.25 + 0.120.70 + 0.100.90 + 0.100.80 + 0.101.09 + 0.110.80 + 0.100.80 + 0.100.90 + 0.20

Cs-137

0.011 + 0.009

C-14 Other Activity

12F4 ARTICHOKES 10/15/88 5.11 + 0.51 0.012 + 0.008

11D'I BEAN LEAVES

11D1 BEAN LEAVES

11F1 BEAN LEAVES

08/09/8808/11/88

,08/22/88

7.8 + 0.210.0 + 0.27.7 + 0.2

2H1 GREEN BEANS

2H1 GREEN BEANS

1101 GREEN BEANS

11D1 GREEN BEANS

7F1 GREEN BEANS

16F2 GREEN BEANS

1281 GREEN BEANS

07/06/8809/06/8807/07/8807/19/8808/07/8808/07/88,09/07/88

2.00 + 0.202.22 + 0 '22.01 + 0.206.01 + 0.602.84 + 0.282.43 + 0.242.56 + 0.26

2H1 YELLOW BEANS

11D1 YELLOW BEANS

13G1 YELLOW BEANS

07/05/88 2.02 + 0.2007/19/88 6.70 + 0.6709/06/88 2.74 + 0.27 0.007 + 0.007

2H1 REO BEETS

2H1 RED BEETS

7F1 RED BEETS

10F1 RED BEETS

11D1 RED BEETS

11D1 REO BEETS

16F2 RED BEETS

7S5 RED BEETS

12B1 RED BEETS

07/05/8807/20/8807/18/8807/19/8807/19/8807/20/8809/05/8809/06/8809/07/88

4 ~ 12 + 0.414.27 + 0.434.73 + 0.473.46 + 0.357.11 + 0.715.07 + 0.515.95 + 0.593.86 + 0.394.24 + 0.42

* Only garnna emitters detected are reported; typical LLO values are found in Table 20

'II-25

TABLE 18GANNA SPECTROMETRIC* ANALYSES OF FOOD PRODUCTS (FRUITS,

Susquehanna Steam Electric Station-Results in pCi/g (wet) + 2

VEGETABLES, AND HONEY)

1988

Page 2 of 5

LOCATION/TYPE

COLLECTION

DATE K-40 Cs-137 C-14 Other Activity

2H1 BROCCOLI

2H1 BROCCOLI

10F1 BROCCOLI

7F1 BROCCOLI

07/05/8808/08/8807/19/8808/07/88

3.47 + 0.355.45 + 0 '44.79 + 0.484.33 + 0.43

'2H1 CABBAGE

2H1 CABBAGE

10F1 CABBAGE

7F1 CABBAGE

16F2 CABBAGE

11D1 CABBAGE

08/08/8808/11/8807/19/8808/07/8808/08/8808/09/88

3.26 + 0.331.14 + 0.132.80,+ 0.284.45 + 0.452.61 + 0.262.25 + 0.23

11D1 CANTALOUPE

11D1 CANTALOUPE

1281 CANTALOUPE

08/09/88 2.64 + 0.2608/11/88 2.03 + 0.2009/07/M 3.45 + 0.34

2H1 CAULIFLOWER

16F3 CAULIFLOWER

08/08/88 2.64 + 0.2607/06/88 4.02 + 0.40

12F4 CARROTS 09/07/88 4.04 + 0 '0 0.01 + 0.01

10F2 S'NEET CHERRIES

902 S'WEET CHERRIES

1101 SWEET CHERRIES

07/05/88 2.24 + 0.2207/19/88 3.11 + 0.3107/19/M 2.73 + 0.27

10F2 SOUR CHERRIES 07/05/88 2.23 + 0.22

2H'I SWEET CORN

2H1 SWEET CORN

983 SWEET CORN

902 SWEET CORN

7F1 SWEET CORN

10F2 SWEET CORN

10F1 SWEET CORN

11D1 SWEET CORN

11D1 SWEET CORN

13G1 S'NEET CORN

1281 SWEET CORH

08/08/8808/11/8807/19/8807/19/8807/19/8807/19/8807/19/8807/19/8808/10/8809/06/8809/07/88

2.01 + 0.202.55 + 0.253.04,+ 0.303.05 + 0.313.04 + 0.303.07 + 0.314.65 + 0.462.M + 0.292.86 + 0.293.17 + 0.323.26 + 0.33


XII-26'

TABLE 18 Page 3 of 5GAMMA SPECTROMETRIC" ANALYSES OF FOOD PRODUCTS (FRUITS, VEGEtABLES, AND HOHEY)

Susquehanna Steam Electric Station- 1988Results in pCi/g (wet) + 2 s

LOCATION/TYPE

COLLECTION


2H1 CUCUMBERS

902 CUCUMBERS

10F1 CUCUMBERS

7F1 CUCUMBERS

11D1 CUCUMBERS

13G1 CUCUMBERS

16F2 CUCUMBERS

.08/08/SS07/19/8807/19/8808/07/8808/09/8808/09/8809/05/88

1.64 + 0.162.22 + 0.222.29 + 0.232.63 + 0.262.15 + 0.222.40 + 0.242.48,+ 0.25

782 HONEY

7B2 HONEY

10/04/88 1.24 + 0.1310/06/88 1.24 + 0.12

0.030 + 0.0090.141 + 0.014

2H1 LETTUCE

2H1 LETTUCE

16F3 LETTUCE

11F1 LETTUCE

7S5 LETTUCE

16F3 LETTUCE

11D1 LETTUCE

12F4 LETTUCE

07/05/8807/06/8805/23/8805/25/8807/06/8807/06/8807/07/8807/19/88

4.78 + 0.483.93 + 0.395.37 + 0.542.97 + 0.308.46 + 0.856.94 + 0.694.69 + 0.473.35 + 0.34

0.006 + 0.0070.013 + 0.010

Be.7 0.14 + .06Be-7 0.31 + .09

Be.7 0.25 + .09Be.7 0.35 + .11

7F1 HEAD LETTUCE

13G1 HEAD LETTUCE

16F3 ONIONS

11D1 ONIOHS

11D1 PEACHES

16F3 PEAS

07/18/88 4.47 + 0.45 0.027 + 0.013

07/19/88 5.79 + 0.58

07/06/88 1.79 + 0.1808/09/88 0.95 + 0.10

07/19/88 2.75 + 0.27,

07/06/88 2.49 + 0.25

Th-228 0.08 + .03Be-7 0.34 + .10

2H1 PEPPERS

7F1 PEPPERS

11D1 PEPPERS

12D4 PEPPERS

13G1 PEPPERS

1281 PEPPERS

09/06/8808/07/8808/09/88OS/09/8809/06/8809/07/88

1.87 + 0.192.55 + 0.251.52 + 0.152 '0 + 0.222.15 + 0.212.80 + 0.28

11D1 PLUMS 07/19/88 1.86 + 0.19


XII-27

TABLE 18GAMMA SPECTROMETRIC* ANALYSES OF FOOD PRODUCTS (FRUITS,

Susquehanna Steam Electric Station-Results in pCi/g (wet) + 2

VEGETABLES, AND HONEY)

1988

Page 4 of 5

LOCATION/TYPE

2H1 POTATO

11D1 POI'ATO

1204 POTATO

10F2 POTATO

11D1 POTATO

11D1 POI'ATO

09/09/8808/09/8808/09/8809/07/8809/07/8809/09/88

4.90 + 0.493.67 + 0.373.35 + 0.333.73 + 0.373.83 + 0.382.82 + 0.28

COLLECTION


11D1 POTATO LEAVES 08/09/88 8.0 + 0.2

7F1 RED POTATOES

10F1 RED POTATOES

07/18/88 4.76 + 0.4807/19/88 4.70 + 0.47

2H1 RADISHES

13G1 RADISHES WASHED

07/05/88 3.39 + 0.3407/19/88 6.61 + 0.66

16F3 SPINACH

16F2 SPINACH

11F1 SPINACH

05/23/88 7.65 + 0.7705/24/88 6.81 + 0.6806/06/88 8.87 + 0.89

Be-7 0.16+ .06Be-7 0.28 + .08

2H1 STRAWBERRY

2H1 STRA'WBERRY

2H1 STRA'WBERRY

12F5 STRAWBERRY

10F2 STRAWBERRY

06/06/8806/09/8806/10/8806/06/8806/06/88

1.40 + 0.141.39 + 0 ~ 14

0.91 + 0.111.64 + 0.161.11 + 0.14

13G1 ACORN SQUASH

13G1 BUTTERNUT SQUASH

09/06/88 4.31 + 0.43

09/06/88 2.97 + 0.30

16F3 YELLOW SQUASH

10F1 YELLOW SQUASH

7F1 YELLOW SQUASH

13G1 YELLOW SQUASH

07/06/8807/19/8808/07/8808/09/88

3.74 + 0.372.91 + 0.291.72 + 0.172.33 + 0.23

2H1 TOMATO

2H1 TOMATO

11D1 TOMATO

„11D1 TOMATO

13G1 TOMATO

1281 TOMATO

1204 TOMATO

12F4 TOMATO

08/08/8808/11/8808/09/8808/10/8809/06/8809/07/8809/07/8809/07/88

2.39 + 0.241.29 + 0.132.21 + 0.222.63 + 0.263.78 + 0.382.98 + 0.302.40 + 0.243.05 + 0.31

* Only ganma emitters detected are reported; typical LLD values are found in Table 20.

XII-28

TABLE 18 Page 5 of 5GAHHA SPECTROMETRIC* AHALYSES OF FOOO PRODUCTS (FRUITS, VEGETABLES, AHD HONEY)

Susquehanna Steam Electric Station- 1988Results in pCi/g (wet) + 2 s

LOCATION/TYPE

COLLECTION


2H1 ZUCCHINI

16F3 ZUCCHINI

7S5 ZUCCHINI

902 ZUCCHINI

10F1 ZUCCHINI

16F2 ZUCCHINI

08/08/8807/06/8807/19/8807/19/8807/19/8809/05/88

2.37 + 0.243.20 + 0.322 '5 + 0.222.40 + 0.242.25 + 0.221.86 + 0.19

0.011 + 0.009

* Only ganae emitters detected are reported; typical LLO values are found in Table 20.

XII-29

TABLE 19

GAMMA ~ SPECTROMETRIC ANALYSIS OF GAME, POULTRY, AND EGGS

SUSQUEHAHNA STEAM ELECTRIC STATION - 1988

Results are in units of pCi/g (wet) + 2s

SAHPLE

TYPE LOCATION

COLLECTION

DATE K-40 Cs-137

WOODCHUCK

WOODCHUCK

WOODCHUCK

WOODCHUCK

WOODCHUCK

WOODCHUCK

WOODCHUCK

16F

16F

16F

16F

16F

16F

16F

08/31/8809/01/8809/03/8809/05/8809/06/8809/08/8809/23/88

3.0 + 0.322.5 + 0 '53.4 + 0.342.7 + 0.263.6 + 0.364.2 + 0.424.1 + 0.41

0.040 '50.480.15

+ 0.007+ 0.02+ 0.05+ 0.02

RABBIT

RABBIT

RABBIT

RABBIT

RABBIT

16F

16F

16F

28

28

09/06/8809/08/8809/26/8811/08/8811/08/88

3.7 + 0.374.5 + 0.464.6 + 0.462.4 + 0.593.8 + 0.52

0.01 + 0.01

DEER

DEER

DEER

DEER

DEER

2S

1A

2S

16H

16H

10/11/8810/26/8810/27/8811/29/8811/28/88

3.9 + 0.393.5 + 0.353.5 + 0.353.0 + 0.302.6 + 0.26

0.310.0060.180.650.88

+ 0.03+ 0.005+ 0.02+ 0.07+ 0.09

SQUIRREL

SQUIRREL

SQUIRREL

SQUIRREL

SQUIRREL

3B

11F

5E

3S

13G

09/12/8809/12/8809/26/8810/26/8809/23/88

4.2 + 0.564.9 + 0.496.6 + 0.836.5 + 0.652.3 + 0.79

1.80.090.051.4

+ 0.18+ 0.07+ 0.03+ 0.14

POULTRY

EGGS

10D

1281

11/08/88

10/03/88

F 1 + 0.30

1.1 + 0.10

*Only gamna emitters detected are reported; typical LLD values are found in Table 20.

XII-30

TABLE 20

TYPICAL * LOWER LIHITS OF DETECTION OF NUCLIDES SEARCHED fOR BUT NOT FOUND BY GAHHA SPECTROMETRY

IN THE VICINITY OF SUSQUEHANNA STEAN ELECTRIC STATION, 1988

NUCLIDE

Hn-54Co-58Fe-59Co-60Zn-65Zr-95Nb-95Ru-103I-131**Cs-134Cs-137Ba-140La-140Ce-141

FISH( Ci/ wet

0.0180.0280.0560.0180.0410.0510.0360.0260.740.0260.0220.41-0.150.050

SEOINENT

( Ci/ dr )

0.0710.0800.220.0710.180.190.920.0940.140.0840.0830.760.520.16

SURFACE WATER

( Ci/I

6.46.6ll6.3

1214

7.46.90.266.26.1

311014

GROUND WATER

( Ci/1)

5.15.985.8ll

106.87.3195.86.0

308.6

14

POTABLE WATER

Ci/l

6.26.3

116.18.'8

116.87 ~ 80:327.26.8

301016

RAIN WATER

( Ci/1

4.75.1

105.398.65 '5.7

225.15.1

291010

NUCLIDE AIR PARTICULATES MILK(10-3 Ci/m3) ( Ci/1

FRUITS/VEG.( Ci/ wet)

ALGAECi/ dr

ANO EGGS

( Ci/ wetSOIL

( Ci/ dr

Nn-54Co-58Fe-59Co-60Zn-65Zr-95Nb-95Ru-1031-131**Cs-134Cs-137Ba-140La-140Ce-141

0.410.480.660.470.940.950.500.334.00.410.433.41.60.48

6.86.939

16167.66.10.128.27.7

318.9

10

0.0200.0170.0460.0200.0490.0480.190.0210.0270.0210.0200.0710.0390.037

0.0290.280.700.380.740.570.300.240.520.360.350.920.550.35

0.0230.0340.0800.0230.0490.0710.0420.300.290.0250.0260.870.300.66

0.0820.0910.270.0760.150.180.0970.0800.510.0940.0950.630.290.13

* Typical refers to mean plus two standard deviations.** Iodine-131 in surface water, potable water and milk is determined by radiochemical methods. See appendix B-5.

APPENDIX A

US EPA INTERCOMPARISON PROGRAM RESULTS

1. Introduction

The quality assurance program of the Radiological Laboratory of Teledyne

Isotopes (TI) is briefly described in this appendix.

Information on each incoming sample is entered in a permanent log book. A

sample number is assigned to each sample at the time of receipt. This

sample number uniquely identifies each sample

Laboratory counting instruments are calibrated, using radionuclide

standards obtained from the National Bureau of Standards, the EPA, and

reliable commercial suppliers, such as Amersham-Searle. Calibration of

counting instruments is maintained by regular counting of radioactive

reference sources. Background counting rates are measured regularly on

all counting instruments. Additional performance checks for the gamma-ray

scintillation spectrometer include regular checks and adjustment, when

necessary, of energy calibration.

Blank, spiked (known quantities of radioactivity added), and replicate

samples are processed periodically to determine analytical precision and

accuracy.

2. Laborator Anal ses for ualit Assurance

guality control samples amounted to about 7.7'4 of all samples analyzed.

Teledyne Isotopes participates in the U.S. Environmental Protection Agency

Radioactivity Intercomparison Studies (Cross-check) Program. The TII

results of.analyses performed on samples and the known values are listed

in Table A-1.

A-2

TABL -1

INTER-LABORATORY COHPAR I SONS, 1988

TELEDYNE ISOTOPES

Page 1 of 5

CollectionDate Hedia Nuclide EPA-Results a

TeledyneIsoto es Results

All ParticipantsHean i 2 s.d.

01/08/88

01/22/88

01/29/88

Water

Water

Food(c)

Sr-89Sr-90

Gross AlphaGross Beta

Sr-89SI -90I-131Cs-137K

46.0055.00

102.0091.00

1231.00

8.664.76

17.678.66

1106.52

30.00 i 8.6615.00 k 2.60

4.00 i 8.668.00 i 8.66

40.6754.3385.6798.67

1210.00

7.564.76

15.3922.92

1453.00

27.33 i 1.7416.00 i 3.00

3.67 a 1.748.33 a 1.74

(d)(e)

27.7614.33

3.878.30

41. 5452. 5998.7591.05

1217.57

11.263.12

3.244.22

x. 25.78a 11.32

16.1813.04

1243.36

02/05/88 Water Co-60Zn-65Ru-106Cs-134Cs-137

69. 0094.00

105.0064.0094.00

8.66a 16.28

18.198.668.66

65.0091.0089.0055.0091.00

7.95a 13.10

23.82a 15.87

10.83

(f)(9)

69.2896.0799.5960.6694.16

10. 2214.6225.4810.0012.70

02/12/88

02/26/88

03/18/88

03/25/88

04/08/88

04/25/88

Water

Hi lk

Water

Air Particulate

Water

Water

N-3

I-131


Gross AlphaGross BetaSr-90Cs-137

I-131

Gross AlphaGross BetaSr-89Sr-90Co-60Cs-134

46.0057.005.005.00

50.007.00

a 19.058.668. 66.2.608.668.66

3327.00 1627.00

4.00 R 0.69

6.00 2 8.6613.00 i 8.66

20.00 4 8.6650.00 i 8.6617.00 % 2.6016.00 f 8.66

7.50 a 1.30

4.0015.67

24.0046.3317.0016.33

8.67

70.6767.67

4.675.00

53.008.33

0.001 ~ 74

0.003.450.001.74

1 ~ 74 (h)

1.746.241.740.006.003.45

3266.67 1173.19

4.33 k 1.74 4.17

5 '812.90

22.6253.2917.0917.72

7.52

44.8357.805.565.13

50.787.20

1.82

1.734.46

9.4412.014.866.10

2.50

24.5212.583.722.088.083.26

3358.36 1675.60

TABLE A-1

INTER-LABORATORY COHPARISONS, 1988

TELEDYNE ISOTOPES

Page 2 of 5

CollectionOate

05/06/88

05/20/88

Hedia

Mater

Mater

Nucl ide

Cs-137

Sr-89Sr-90


EPA-Results a

7.00 E 8.66

20.00 i 8.6620.00 t 2.60

11.00 i 8.6611.00 i 8.66

4.6713.67

1.741.74

TeledyneIsoto es Results

9.00 i 3.00

16.67 I 6.2419.67 i 3.45

All ParticipantsHean i 2 s d.

8.04 i 3.14

18.84 i 11.6818.36 i 7.00

9.40 i 5.2011.88 i 4.38

06/03/88 Mater Cr-51Co-60Zn-65Ru-106Cs-134Cs-137

302.0015.00

101.00195.0020.0025.00

i 51.968.66i 17.32i 34.648.668.66

313.6718.00

109.33184.67

19.3330.33

60. 936.00i 31.50j 60.096.24

22.65

304.64 a15.95 i

103.14 i190.83 i

19.30 i25.91 i

63.604.30

14.7632.064.066.10

06/13/88 Water

07/22/88 'aterH-3


5565.00 %964.75

15.00 J 8.664.00 i 8.66

8.336.00

1.740.00

5900.00 i599.97 5393.85i1009.86

12.23 i 5.747.74 i 3.88

07/24/88 Hi lk Sr-89Sr-901-131Cs-137K

40.0060.0094.0051.00

1600.00

8.665.20i 15.598.66

%138.56

36.3361.00

101.6753.67

1656.67

i 7.566.00

22.929.18

i165.21

33. 8856.1696.0251.91

1588.86

23.8420.20-17.847.20

i275.86

07/29/88

08/05/88

08/26/88

Food(c)

Water

Water

1-131Cs-137K

I-131

Gross AlphaGross BetaSr-90Cs-137

107.00 i 19.0549.00 i 8.66

1240.00 i107.39

-76.00 i 13.96

8.00 i 8.6629.00 i 8.668.00 s 2.60

12.00 i 8.66

86.00 7.95

9.33 i 1.7425.67 i 4.59

7.67 i 1.7411.00 i 1.73

103.33 i 34.6551.33 i 7.56

1220.00 4103.92

107.54 i 15.5848.11 i 5.64

1224.74 i 100;60

77.29 i 15.18

8.89 i 3.5428.71 i 7.02

7.79 i 3.2812.64 i 5.38

TABLE -1I


TELEDYNE ISOTOPES

Page 3 of 5

CollectionOate Hedia Nuclide EPA-Results a

TeledyneIsoto es Results b

All ParticipantsHean i 2 s.d.

09/23/88

10/07/88

10/14/88

10/18/88

Water

Mater

Water

Water


Cr-51Co-602n-65Ru-106Cs-134Cs-137

H-3

Gross AlphaGross BetaSr-89Sr-90

8.00 i 8.6610.00 i 8.66

251.0025.00

151.00152.0025.0015.00

i 43.38.66

N 25.98i 25.988.668.66

2316.00 i606.22

41.00 f 17.3254.00 L 8.6611.00 i 8.6610.00 i 2.60

9.00 i 0.0011.33 i 1.74

236.0028.00

165.67159.6727.6717.33

i 87.63 .

0.0016.53

a 36.664.599.81

2300.00 i300.00

38.67 i 3.4553.33 i 7.568.67 i 1.749.00 i 0.00

7.58 i 4.0010.45 i 4.36

248.7425.51

151.82144.1724.0515.77

s 48.044.70i 18.40i 35.00-4.324.64

2317.56 i477.02

38.96 i 18.6250.42 I 11.829.91 i 5.529.46 i 2.68

10/28/88 Hi lk Sr-89Sr-90I-131Cs-137K

40.0060.0091.0050.00

1600.00

8.661 5.20x 15.59

8.66i138.56

28. 3352.0087.6751.33

1578.33

1.74 (n)10.38 (n)3.454.59

70.89

31. 7355.8489.9549.88

1622.27

24.3611.48i 15.987.52

i197.0611/25/88

12/09/88

Mater

Mater


I-131

9.00 N 8.669.00 i 8.'66

115.00 L 20.78

10.00 i 0.0011.00 i 3.00

106.67 i 17.31

8.83 i 4.749.66 i 4.52

115.54 i 28.96

TABLE A-1

INTER-LABORATORY COMPARISONS, 1988

TELEDYNE ISOTOPES

Page 4 of 5

CollectionDate

Notes:

Hedi a Nuc 1 ide EPA-Results aTeledyne

Isoto es Results bAll Participants

Mean i 2 s d.

(a)

(b)

(c)

(d)

(e)

(9)

(h)

EPA Results-Expected laboratory precision (3 sigma). Units are pCi/S for water and milk except K is in mg/S.Units are total pCi for air particulate filters.Teledyne Results - Average a three sigma. Units are pCi/S for water and milk except K is in mg/S. Units are totalpCi for air particulate filters.Units for food analysis are pCi/kg except K which is mg/kg.

The average result of 86 pCi/kg was lowered by one analysis of 80 pCi/kg, in which I-131 may have been lostin processing. If this analysis is discarded and the higher results of the other 2 aliquots are taken, theaverage becomes 94 pCi/kg which is more favorable (-1.1 sigma for 2 determinations). The investigationrevealed no systemic reason for the low I-131 (-2.77 sigma for 3 determinations). Moreover, the previousperformance for this analysis shows no systematic bias.

There is no apparent reason for the deviation. Although there is a bias high, the bias does not appear to bechanging significantly. Starting with the 01/13/86 data, the ratio is the average TI results to the EPAresult is 1.27, 1.10, 1.08 and 1.15.

The ruthenium-106 results (as well as other isotopes in the EPA sample) for February 5, 1988 EPA sample were basedon a new standard (Amersham) used in the December 1987 annual. calibrations. A calculation using the previousNBS standard efficiencies gave an average of 98.0 pCi/liter having a normalized deviation of -1. 15. A secondAmersham standard in a Marinelli was prepared and agreed with the NBS standard. These efficiencies are in usecurrently.The cesium-134 results (as well as the other isotopes in the EPA sample) for February 5, 1988 EPA samplewere based on a new standard (Amersham) used in the December 1987 annual calibrations. A calculation usingthe previous NBS standard efficiencies gave an average of 60.2 pCi/liter having a normalized deviation of-1.80. A second Amersham standard in a Marinelli was prepared and agreed with the NBS standard. Theseefficiencies are in use currently,

An investigation was conducted and there is no apparent reason for the deviation. The samples contained anunusually high concentration of stable iodide (3.6 mg/liter) as determined by electrode readings which wasverified at that time. The chemical yields were properly calculated taking these readings into account. Nocorrective action is necessary since these results fall within the EPA 3 sigma control limits and no trendson previous I-131 intercomparison results are evident.

Dr. Frank Novielli of the EPA states that the EPA takes energy correction into account. Ne mailed usa document which indicates how this is achieved. Teledyne Isotopes implemented the EPA method forenergy correction.

TABLE -1


TELEDYNE ISOTOPES

Page 5 of 5

CollectionDate

Notes:

Hedi a Nuclide EPA-Results aTeledyne

Isoto es Results bAll Participants

Hean a 2 s.d.

(k)

High concentration of Co-60 in the same (50 pCi/1) resulted in false beta counts on the Tennelec countersfrom Co-60 gamma. Dr. Frank Norelli of the EPA stated that the EPA will discontinue using Co-60 in Per-formance Evaluation samples (effective October 1988) because of this problem.

Low alpha caused by presence of chlorides in the sample residue increases self-absorption. In the futurethe sample will be evaporated with more nitric acid to convert chlorides to nitrates. These reported resultsfall within the EPA 3 sigma control limits.

(1) The deviation noted is due to unusually high self-absorption characteristics of EPA water spikes. Correctiveaction involves applying the self-absorption curve derived by an analysis of EPA water in a 1976 CollaborativeStudy instead of the usual curve when calculating EPA cross-check samples.

(m) Faulty stable iodide yield correction, probably caused by a chemical in the sample which interferes with theiodide electrode. The high electrode reading was verified by repeating several times ~ Without yield cor-rection the average result would have been 77 pCi/1. The original reported results is within the EPA 3 sigmaacceptance region.

(n) There was a possible loss of the radiostrontium in the initial TCA seperation step ~ The presence of calciumon the final strontium mount has been ruled out by an experiment in which the strontium mounts were repurifiedand recounted giving the same results. Further study is being performed to determine whether radiostrontiumbecomes bound to the protein or fat components of the milk.

DETERMINATION OF GROSS ALPHA AND/OR GROSS BETA ACTIVITY

IN bfATER SAMPLES, AIR PARTICULATE FILTERS, COMPOSITED AIR

PARTICULATE FILTERS OR SEDIMENTS

TELEDYNE ISOTOPES

This described the process used to measure the overall alpha and/or beta

radioactivity of water samples, air particulate filters, composited air

particulate filters or sediments without identifying the radioactive species

present. No chemical separation techniques are involved. One liter of the

water sample is evaporated on a hotplate. The evaporated sample is rinsed

into a 2-inch diameter stainless steel planchet which is stamped with a

concentric ring pattern to distribute residue evenly. Final evaporation to

dryness takes place under heat lamps. Residue mass is determined by weighing

the planchet before and after mounting the sample. In the case of an airparticulate sample, the filter is mounted directly on a 2-inch stainless steel

planchet. Composited air filter samples are leached with nitric acid to bring

the deposit into solution. The solution is filtered and an aliquot is

evaporated and then mounted on a 2-inch stainless steel planchet. Sediment

samples are dried and a I-gram aliquot is mounted directly on a 2-inch

stainless steel planchet.

The planchets are then counted for alpha and/or beta activity in a

low-background gas flow proportional counter. Calculation of activityincludes an empirical self-absorption correction curve which allows for the

change in effective counting efficiency caused by the residue mass. Self

absorption is not considered in the case of air particulate filters because of

the impracticality of accurately weighing the deposit, and because the

penetration depth of the deposit into the filter is unknown.

B-3'

CALCULATION OF THE SAMPLE ACTIVITY

Net Ci on collection date =

unit vo ume or wt.N - 8t

2.22 V E

net activity

2 N + 8tt

2.22 E

counter

random uncertainty4

where: N = total counts for sample (counts)

. t = counting time for sample (min)

8 = background rate of counter (cpm)

2.22 = ~dmpCi

V(w) = volume'or weight of sample analyzed

E = efficiency of the

Calculation'of .the L.T. Value

A "less than" (LT) value is reported if no activity is found. If net

activity, as calculated above, is less than or is equal to 4.66 times the

standard deviation of the background counting rate, then the LT value isN

reported.

Thus LT = 4.66 8

8-4

DETERMINATION OF I-131 IN MILK AND WATER SAMPLES

BY RADIOCHEMISTRY

TELEDYNE ISOTOPES

This described the radiochemical methods for determining I-131 activity in

milk and water samples.

Two liters of sample are first equilibrated with stable iodide carrier. A

batch treatment with anion exchange resin is used to remove iodide from the

sample. The iodide is then stripped from the resin with sodium hypochlorite

solution, is reduced with hydroxylamine hydrochloride, and is extracted into

carbon tetrachloride as free iodine. It is then back-extracted as iodide into

sodium bisulfite solution and is precipitated as palladium iodide. The

precipitate is weighed for chemical yield and is mounted on a nylon planchet

which is then analyzed on a low level beta counting system. The chemical

yield is corrected by measuring a stable iodide content of the milk with a

specific ion electrode.

'B-5


Net Ci on collection date = N - B

t2 N + Bt

tliter 2;22 V y DF E

net activity

2.22 V y D E

Random uncertainty

where: N = total counts from sample (coun'ts)

counting time for sample (min)

2022

V

DF

Note:

background rate of counter (cpm)

~dmpCi

volume of sample analyzed (liters)chemical yield of the mount or sample counted

'\

decay factor from the collection to the mid count time

efficiency of the counter for the I-131 betas.A

Efficiency is determined by counting an I-131 standard.

Calculation of the L.T. Value

If the net activity, N - 8, is equal to or is less than 4.66 times the

standard deviation of the background counting rate the activity on the

collection date is below the limit of detection and is called "less than"

(L l )

L.T. = 4.66 B

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

DETERMINATION OF TRITIUM BY GAS COUNTING

TELEDYNE ISOTOPES

A 2 ml aliquot is reduced into hydrogen gas and collected in an activated

charcoal trap. The hydrogen is then transfe'rred into a previously evacuated

one liter proportional counter. Non tritiated hydrogen and ultra-high purity

methane is added and the mixture is counted. Backgrounds and standards are

counted in the same gas mixture as the samples.

Calculation of the sample activity:

(CPM)G - BKG + 2 G + B'Net Ci~ unit vol.

3.234x(TU)N x VNCPMN x V

where: (TU) = the tritium units of the standardN

= volume of the standard used to calibrate the efficiency

of the detector - in psia

Vs= volume of the sample loaded into the detector - in

psia

(CPM)N = the cpm activity of the standard of volume VN

(CPM) = the gross activity of the sample of volume VS and the

detector background

BKG = the background of the detector in cpm

3.234 = conversion factor changing TU to pCi/1

B-7

= counting time for the sample

G = standard deviation of the gross activity of the sample

and the detector background, in cpm

B = standard deviation of the background, in cpm


If the net activity, [(CPM)G - BKG], is equal to or less than 3.3 times the

standard deviation of the net counting rate the activity on the collection

date is below the limits of detection and is called "less than" (L.T.).

thus L.T. = 3.3 x 3.234 x (TU)n x Vn x sG + sB

N s

where: G = standard deviation of the gross activity of the sample and

the 'detector background, in cpm

8 = standard deviation of the background, in cpm

B-8

Determination of Tritium in Water by .

Electrolytic Enrichment and Liquid Scintillation Counting

Teledyne Isotopes

Approximately 55 mi lliliters of the sample undergoes enrichment by

electrolysis. The electrolysis decomposes the water into elemental hydrogen

and oxygen. Water molecules containing only protium (hydrogen with a mass

number of one) decompose electrolytically at a faster rate than those

tritiated water molecules. The nonelectrolyzed water remaining becomes

enriched in tritium as a result. Electrolytic enrichment typically produces 3

to 5 millititers of water in which the tritium is concentrated. After the

, enriched water is distilled for purification'urposes, three mi lliliters is

mixed with liquid scintillation material and counted for its activity.

CALCULATION OF THE SAMPLE ACTIVITY FOR TRITIUM

~Net Ciunit vol.

N - B

tN + B

2 t+ t

net activityrandom uncertainty

where: N = total counts from sample (counts)

t = counting time for sample (min)

B = background rate of counter (cpm)

2.22 = ~dm

pCi

B-9

EF = enrichment factor

E = efficiency of the counter for tritium


If the net activity, N - B, is equal to or less than 4.66 times the standardtdeviation of the background counting rate, the activity on the collection date

is below the limit of detection and is called "less than" (L.T.)

L.T. = 4.66

2.22 V EF E cV7

Where Vc = Volume counted by liquid scintillation

Vf = Final volume at the end of enrichment

B-10

DETERMINATION OF GAMMA EMITTING RADIOISOTOPES

TELEDYNE ISOTOPES

Gamma emitting radioisotopes are determined with the use of a lithium-drifted

germanium (Ge(Li)) and high purity germanium detectors with high resolution

spectrometry in specific media, for example, air particulate filters, charcoal

filters, milk, water, vegetation, soil/sediments, biological media, etc. Each

sample to be assayed is prepared and counted in standard geometries such as'L

one liter wrap-around Marinelli containers, 300 ml or 150 ml bottles, or

two-inch filter paper source geometries.

Samples are counted on large ( 55 cc volume) germanium detectors connected to

Nuclear Data 6620 data acquisition and computation systems. All resultant

spectra are stored on magnetic tape.

The analysis of each sample consists of calculating the specific activities of

all detected radionuclides or the detection limits from a standard list of

nuclides. The germanium detection systems are calibrated for each standard

geometry using certified radionuclide standards traceable to the National

Bureau of Standards


AND RANDOM UNCERTAINTY

Net pCi/vol or mass = N-B +'" 2 N+82.22 V E G DF t) 2.22 V E G DF

net activity random uncertainty

where: N = area, in counts,. of a spectral region containing a gamma

emission of the nuclide of interest

Note: if the detector exhibits a peak in this region

when counting a blank this background (BB) is

subtr acted from N before using the above equation.

BB is the count rate of the blank in the

background peak.

B = background counts in the region of interest, calculated

by fitting a straight line across the region connecting

the two adjacent regions.

t = counting interval of sample, minutes

2.22 = dpm/pCi

V = volume'or mass of sample analysed

E = efficiency of counter at the energy region of interest

GA = gamma abundance of the nuclide at the gamma emission

energy under consideration

DF = decay factor from sample collection time to midpoint of

the counting interval

B-12

CALCULATION OF THE L.T. VALUE

L.T. (pCi/vol or mass) = 4.66 N

2. 2 V E G DF tThe width of the spectral band around the emission energy is calculated

differently from the case of an identified peak, so that the value of N used

in the two equations may differ.

A detection limit or "less than" (LT) value is reported if no activity is

found. If no spectral lines are identified at the energies appropriate to a

nuclide, the LT value is calculated by the above equation. If spectral lines

for man-made radionuclides are identified but the random uncertainty in the

first equation is greater than 60% of the net activity, then a LT value is

also assigned by the second equation. When the random uncertainty exceeds

only 30Ã for naturally occurring radionuclides, the LT value is assigned.

The analyst's judgement is exercised in the decision to report an activity or

a L.T. The agreement between various spectral lines of the same nuclide, and

possible interference from other nuclides, are considered in this decision.

8-13

DETERMINATION OF GROSS BETA MINUS K-40

ACTIVITY IN MILK SAMPLES

TELEDYNE ISOTOPESI

This procedure describes a radiochemical method for measuring the gross beta

activity of milk after removing natural K-40.

One fourth liter of milk sample is curdled by adding trichloroacetic acid

(TCA) solution. The curd is removed by vacuum filtration. Radioactive

species are co-precipitated with natural calcium as oxalates by addition of

oxalic acid and ammonia (leaving potassium in solution). The precipitate is

collected by vacuum filtration on a polycarbonate (Millipore) filter, then is

ashed in a muffle furnace to remove organic material. The ash is dissolved in

hydrochloric acid and solids are removed by filtration. Oxalates are again

precipitated and collected on a polycarbonate filter. After drying, the

precipitate is removed from the filter and crushed to a powder, the placed in

a 2-inch stainless steel counting planchet.

Precipitate mass is determined by weighing the planchet before and after

mounting the sample. The planchet's counted for beta activity on an

automatic proportional counter. Results are calculated using an empirical

self-absorption curve which allows'or the change in effective countingll

efficiency caused by the residue mass.

B-14


TELEDYNE ISOTOPES

Net Ciunit vo ume

N - B

2.22 V E

net activity

2 N + B+ . t

2.22 E

random uncertainty

where: N = total counts from sample (counts)

counting time for sample (min)

background rate of counter (cpm)

2.22 = ~dm~pi

V = volume of sample analyzed

E = efficiency of the counter

H

Establishing and reporting activities that are equal to or less than the

detection limit:

N - BIf the net activity, t ,is equal to or is less than 4.66 times2.22 V E)

the standard deviation of the background counting rate, the activity is below

the limits of detection and is called "less than" (L.T.).

L.T. =B

4.66 t2.

8-15

I

I

II

I

I

APPENDIX C

DATA REPORTING CONVENTIONS

The results from Teledyne Isotope's analyses are generally reported to two

significant figures. Random uncertainties of counting are reported to the

same decimal place as the result. If the uncertainty has no digit before the

third figure in the result, the uncertainty is rounded up to the second

significant figure. If the uncertainty is less than 10K of the result, an

uncertainty of 10$ of the result is reported. Detection limits are rounded to

one significant figure.

In the tables presenting analytical measurements, a calculated value is

reported with the random uncertainty of counting at 2 standard deviations (2s)

calculated by considering both the sample and background count rates. The

uncertainty of an activity is influenced by the volume or mass of the sample,

the background count rate, the count times, the method used to round off the

value obtained to reflect its degree of significance,and other factors. The

uncertainties of activities determined by gamma spectrometric analyses are

also influenced by the relative concentrations of the radionuclides in the

sample, the energies and intensities of the gammas emitted by those

radionuclides, and the assumptions used in selecting the radionuclides to be

quantitatively determined.

Results reported as less than (LT) are below the lower limit of detection

(LLD) or the critical level in the case of anthropogenic gamma-emitting

radionuclides. The LLD is defined as the smallest concentration of a specific

radioactive material in a sample that will be detected with only a 5 percent

probability of nondetection. At the critical level, there is only a 5 percent

probability that a fluctuation in background activity could be confused as the

activity of a specific anthropogenic gamma-emitting radionuclide.

iI

0)C-2

I)

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