Radiological Environmental Monitoring Program · SSES Radiological Environmental Monitoring...
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SusqueHanna Steam Electric StationUnits 1 & 2
RadiologicalEnvironmental Monitoring
Program1988 Annual Report
S~05020202 S90q27PDR ADOCK 050003S7R PDC
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Pennsylvania Power 8 Light CompanyAllentown, PA
April 1989
II
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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
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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.
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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.
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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
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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.
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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)
Radiological Environmental Monitoring Program - 1988
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
Gamma Spectrometry A
Gamma Spectrometry A
Gamma Spectrometry A
Gamma Spectrometry A
Note: See footnotes at end of table.
TABLE 1(Page 3.of 3)
Annual Analytical Schedule for the'Susquehanna Steam'Electric Station (PP8L)
Radiological Environmental Monitoring Program - 1988
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
Note: See footnotes at end of table.
TABLE 2(Page 2 of 8)
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)
Sample Locations and Media for the SSESRadiological Environmental Monitoring Program - 1988
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
Note: See footnotes at end of table.
TABLE 2(Page 4 of 8)
Sample Locations and Media for the SSESRadiological Environmental Monitor ing Program - 1988
LocationCode
Description Sample Type
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.
TABLE 2(Page 5 of 8)
Sample Locations and Media for the SSESRadiological Environmental Monitoring Program - 1988
LocationCode
Description Sample Type
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
Note: See footnotes at end of table.
TABLE 2(Page 6 of 8)
Sample Locations and Media for the SSESRadiological Environmental Monitoring Program — 1988
LocationCode
Description Sample Type
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.
TABLE 2(Page 7 of 8)
Sample Locations and Media for the SSESRadiological Environmental Monitoring Program - 1988
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)
TABLE 2(Page 8 of 8)
Sample Locations and Media for the SSESRadiological Environmental Monitoring Program - 1988
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
lel I
2
id.
03
O
285
Sei2s 282%1
~ 3$ 33$ 5
l3,
r-l3S 2 I3SS
I384l2S3
I 4 / '584
~ isS5l4S5 ~ 2S3 3S4 ~
iIS2 j ~I
83
~ 5$ 7'0
4SI
~BC~o
5SI
5$ 4585
$ 0
/Boundary
I VALE
~+g+
pNORTH
MILE
I
I
III
I
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)
16F2L6F3 I,
I'/
//r
3FZ
HANTICOKE354
'(ll ?8?1. fram 1 te)363 ~H,
(16 al, IJO?I 1 telFIC 4
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LSFI ~
16F
SHLCKSHIN Y
Fl23 .FlFLC 3 ~
IEI
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oLIZFI
ANAOUA
g%'ZF
oLL"
Y LLlLf,wg jk?/If
doI
3F
~81$ GL
I(13,11 a1
f/or 1'lt II1I
13E3
14 EL r/III
/
1581
'18
11481
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ISA3 A
14
481
301 r3D2 J
I/4 EL
I~ ~/Ir/
)3 13E41181
?ZS'tstg
I 8$ /I
(13 af from siteLXL
12E1FIC I 12FS IZEZ
12E4BEBYfKtt
ZG4
1204IICI
1C1202
1203al. roa 1te)
IP J?
llr . /S!2F4 ,,:(~ re?rr'It! 132 ~ ~g"
1261112~~LZF3(15 c1. from site
1001
IODZ
tSl ~26 at. I+a.stle?LSfft(ts al. froa site)
1084
SI982
903
FAL
~902
1 AG3I 582
Ig. AG4
f 682
38$24383P
882
23
803~ ~
6CI
~ TEL
r8/IJ
SE ~
SEISE2
r/621
FFI ~
///r/
r
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I IFI
LLF
I I
IOF IIOF2
LOGI (14 mf. !Iam Sltel
I'
I
(8I?'8.5al froa s )tel
I8
FG2(12 al. froa site)
( r J
(14 m1, I~ site) I8 Ar
J'/ /rrr
I
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
l
l
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
I'
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
lI
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
Period Prep erational
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
PREOPERATIONAL OPERATIONAL
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
preoperational and operational periods 1977-1981 and 1982-1987
respectively in the table below.
DRINKING WATER TRITIUM ACTIVITIES Ci/1
Period Prep erational
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
Location Indicator Control
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
Location Indicator Control
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
Period Prep erational
1977-81
Ran<ac 2.7 - 3.5
Mean (median) 3.2 (3.2)
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
Location Indicator Control
Period Prep erational
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
previous atmospheric nuclear weapons tests.
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
Location Indicator Control
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
preoperational and operational periods 1978-1981 and 1982-1987
respectively in the tables below.
SEDIMENT BERYLLIUM-7 ACTIVITIES Ci/ dr
Location Indicator Control
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
Location Indicator Control
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
Mean (median) 1.2 (1.2)
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
Location Indicator Control
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
1988 are compared to the ranges and means (medians) of yearly average
cesium-137 activities at indicator and control locations during the
preoperational and operational periods 1978-1981 and 1982-1987
respectively in the table below.
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
preoperational and operational periods 1980-1981 and 1982-1987
respectively in the table below.
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
indicator and control locations during the preoperational and
V-33 '
operational periods 1980-1981 and 1982-1987 respectively in the table
bel ow.
GROUND WATER GROSS BETA ACTIVITIES Ci/1
Location Indicator Control
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
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 1980-1981 and 1982-1987
respectively in the table below.
'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
operational periods 1978-1981 and 1982-1987 respectively in the table
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
preoperational and operational periods 1980-1981 and 1982-1987
respectively in the table below.
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
and control locations during the preoperational and operational
periods 1978-1981 and 1982-1987 respectively in the table below.
V-39
I
I
I
FIGURGROSS ALPHA ACTIVITYIN AIR PARTICULATES
20
15
PREOPERATIONAL OPERATIONAL
Y3
VCL >0Y)D
I
UNIT 2 CRITICALITY
1980 1981I I I I
1982 1983 1984 1985 1986 1987 1988 1989
indicator
control
I
. 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
periods 1980-1981 and 1983-1987 respectively in the table below.
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
periods 1980-1981 and 1982-1987 respectively in the table below.
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
previous atmospheric nuclear weapons tests.
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
and control locations during the preoperational and operational
periods 1978-1981 and 1986-1987 respectively in the table below.
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
operational periods 1978-1981 and 1985-1987 respectively in the table
below.
V-47
l
I
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
Mean (median) 3.4(3.0)
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
Period Prep erational
1979&81
~P
1982-87 1988
~Pi 1 ~P
1979&81 1982-87 1988
~Ran e 0.9 - 1.3
Mean (median) 1.1 (1.1)
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
Mean (median) 1.1 (1.1)
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
1988 are compared to the ranges and means (medians) of yearly average
cesium-137 activities at indicator and control locations during
preoperational and operational periods 1979 & 1981 and 1982-1987
respectively in the table below.
Location
SOIL CESIUM-137 ACTIVITIES Ci/ dr
Indicator Control
Period Prep erational
1979&81
~0
1982-87 1988
Prep erational
1979&81 1982-87 1988
0 erational
~Ren e 0.5 - 0.7
Mean (median) 0.6 (0.6)
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
previous atmospheric nuclear weapons tests.
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
Location Indicator Control
Period
Ran<ac
1986-87
0.8' 2.6
Mean (median) 1.7 (1.7)
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
for 1988 are compared to the ranges and means (medians) of yearly
average cesium-137 activities at indicator and control locations
during the period 1986-87 in the table below.
VEGETATION CESIUM-137 ACTIVITIES Ci/ wet
Location Indicator Control
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
previous atmospheric nuclear weapons tests.
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
indicator and control locations during the preoperational and
operational periods 1980-'1981 and 1982-1987 respectively in the
tables below.
FRUITS/VEGETABLES/HONEY BERYLLIUM-7 ACTIVITIES Ci/ wet
Location Indicator Control
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
Location Indicator Control
Period Pl~it ~PtP i 11~Pl
1980-81 1982-87 1988 1980-81 1982-87 1988
~Ran e 2.5-3.0
Mean (median) 2.8(2.8)
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
cesium-137 activities at indicator and control locations during the
preoperational arid operational periods 1980-1981 and 1982-1987
respectively in the table below.
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
and operational periods 1972-1981 and 1982-1987 respectively in the
table below.
GAME POTASSIUM-40 ACTIVITIES Ci/ wet
Period Prep erational 0 erational
~Ran e
1972-81
1.8 - 4.8
Mean (median) 2.8 (2.5)
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
and operational periods 1972-1981 and 1982-1987 respectively in the
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
Name of Facility: Susquehanna Steam Electric StationLocation of Facility: Luzerne County, Pennsylvania
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)
ALL INDICATOR LOCATIONS
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
SAMPLED (UNITOF MEASUREMENT)
ANALYSIS AND LOWER LIMITTOTAL NUMBER OF
OF ANALYSES DETECTION
PERFORMED(1) (LLD) (2)
ALL 'INDICATOR LOCATIONS
MEAN (f)(3)(RANGE)
NUMBER OF
LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NONROUTINE
NAME MEAN(f)(3) MEAN (f)(3) REPORTED
DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS(4)
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)
ALL INDICATOR LOCATIONS
HEAN (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)
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
Reporting Period: January 4, 1988 to January 6, 1989
Page 5 of 11
MEDIUM
OR PATHWAY
SAMPLED (UNITOF MEASUREMENT)
ANALYSIS AND LOWER LIMITXOTAL NUMBER OF
OF ANALYSES DETECTION
PERFORMED(1) (LLD) (2)
ALL INDICATOR LOCATIONS
MEAN (f)(3)(RANGE)
NUMBER OFLOCATION WITH HIGHEST-MEAN CONTROL LOCATIONS NONROUTINE
NAME MEAN(f)(3) MEAN (f)(3) REPORTED
DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS(4)
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
Reporting Period: January 4, 1988 to January 6, 1989
Page 6 of 13.
MEDIUM
OR PATHWAY
SAMPLED (UNITOF MEASUREMENT)
ANALYSIS AND LOWER LIMITTOTAL NUMBER OF
OF ANALYSES DETECTION
PERFORMED(1) (LLD) (2)
ALL INDICATOR LOCATIONS
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)
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
Reporting Period: January 4, 1988 to January 6, 1989
Page 7 of ll
MEDIUM
OR PATHWAY
SAMPLED (UNITOF MEASUREMENT)
ANALYSIS AND LOWER LIMITTOTAL NUMBER OF
OF ANALYSES DETECTION
PERFORMED(1) (LLD) (2)
ALL INDICATOR LOCATIONS
MEAN (f)(3)(RANGE)
NUMBER OF
LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NONROUTINE
NAlE MEAN(f)(3) MEAN (f)(3) REPORTED
DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS(4)
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
Name of Facility: Susquehanna Steam Electric StationLocation of Facility: Luzerne County, Pennsylvania
Reporting Period: January 4~ 1988 to January 6, 1989
Page 8 of ll
MEDIUM
OR PATHWAY
SAMPLED (UNITOF MEASUREHENT)
ANALYSIS AND LOWER LIMITTOTAL NUMBER OF
OF ANALYSES DETECTION
-PERFORMED(l) (LLD) (2)
ALL INDICATOR LOCATIONS
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) 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
SAMPLED (UNITOF MEASUREMENT)
ANALYSIS AND LOWER LIMITTOTAL NUMBER OF
OF ANALYSES DETECTION
PERFORMED(l) (LLD) (2)
ALL INDICATOR LOCATIONS
MEAN (f)(3)(RANGE)
NUMBER OF
LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NONROUTINE
NAME MEAN(f)(3) MEAN (f)(3) REPORTED
DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS(4)
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
SAMPLED (UNITOF MEASUREMENT)
ANALYSIS AND LOWER LIMITTOTAL NUMBER OF
OF ANALYSES DETECTION
PERFORMED(l) (LLD) (2)
ALL INDICATOR LOCATIONS
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)
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
Reporting Period: January 4, 1988 to January 6, 1989
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
I
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.
2. Radiation Management Corporation, "Susquehanna Steam Electric
Station, Pre-operational Radiological Environmental Monitoring
Program 1973," RMC-TR-74-07, May 1974.
3. Radiation Management Corporation, "Susquehanna Steam Electric
Station, Preoperational Radiological Environmental Monitoring
Program, 1974 Annual Report," RMC-TR-75-07, April 1975.
CI
4. Radiation Management Corporation, "Susquehanna Steam Electric
Station, Radiological Environmental Monitoring Program, 1975 Annual
Report," RMC-TR-76-05, May 1976.
5. Radiation Management Corporation, "Susquehanna Steam Electric
Station, Radiological Environmental Monitoring Program, 1976 Annual
Report," RMC-TR-77-04, March 1977.
6. Radiation Management Corporation, "Susquehanna Steam Electric
Station, Radiological Environmental Monitoring Program, 1977 Annual
Report," RMC-TR-78-01, May 1978'.
7. Radiation Management Corporation, "Susquehanna Steam Electric
Station, Radiological Environmental Monitoring Program, 1978 Annual
Report," RMC-TR-79-01, April 1979.
8. Radiation Management Corporation, "Susquehanna Steam Electric
Station, Radiological Environmental Monitoring Program, 1979 Annual
Report," RMC-TR-80-01, March 1980.
9. Radiation Management Corporation, "Susquehanna Steam Electric
Station, Radiological Environmental Monitoring Program, 1980 Annual
Report," RMC-TR-81-02, July 1981.
10. Radiation Management Corporation, "Susquehanna Steam Electric
Station, Radiological Environmental Monitoring Program, 1981 Annual
Report," RMC-TR-82-03, July 1982.
ll. Radiation Management Corporation, "Susquehanna Steam Electric
Station, Radiological Environmental Monitoring Program, 1982
Preoperational Report," RMC-TR-83-01, April 1983.
12. Radiation Management Corporation, "Susquehanna Steam Electric
Station, Radiological Environmental Monitoring Program, 1982
Operational Report." RMC-TR-83-02, April 1983.
13. NUS Corporation, "Susquehanna Steam Electric Station, Radiological
Environmental Monitoring Program, 1983 Annual Report," NUS-4516 March
1984.
XI-2
14. Pennsylvania Power and Light Company, "Susquehanna Steam Electric
Station, Environmental Report, Operating License Stage," May 1978.
15. Pennsylvania Power and Light Company, "Susquehanna Steam Electric
Station, Final Safety Analysis Report," 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.
23. Pennsylvania Power and Light Company, "Susquehanna Steam Electric
Station, Semi-annual Effluent Waste Disposal Report, Data Period:
January - June 1986", August 1987.
24. Pennsylvania Power and Light Company, "Susquehanna, Steam Electric
Station, Semi-annual Effluent Waste Disposal Report, Data Period:
July - December 1986," February 1987.
25. Pennsylvania Power and Light Company, "Susquehanna Steam Electric
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.
30. Pennsylvania Power and Light Company, "Susquehanna Steam Electric
Station, Semi-annual Effluent Waste Disposal Report, Data Period:
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
Station, Semi-annual Effluent Waste Disposal Report, Data Period:
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
Second quarter4/3/87
to6/26/87
Third quarter6/26/87
to9/30/87
Fourth quarter9/30/87
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
Second quarter3/28/88
to6/30/88
Third quarter6/28/88
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
Second quarter3/28/88
to6/30/88
Third quarter6/28/88
to9/30/88
Fourth quarter9/29/88
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'
Page 1 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.
Page 3 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
* Only gamna emitters detected are reported; typical LLD values are found in Table 20.
(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.
Page 1 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
* Only gamna emitters detected are reported; typical LLD values are found in Table 20.
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 2 of 4
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
Gross Betaminus K-40
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
Results in pCi/l + 2 s Page 3 of 4
LOCATION
1001
1282
10D1
5E1
13E3
1481
COLLECTION
DATE
07/20/8807/20/8807/20/8807/20/8807/20/8807/20/88
Gross Betaminus K-40
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
* Only gamna 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- 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
~ Only gamna emitters detected are reported; typical LLD values are found in Table 20.
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
* Only gamna emitters detected are reported; typical LLD values are found in Table 20.
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
DATE K-40 Cs-137 C-14 Other Activity
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
~ Only gamna emitters detected are reported; typical LLD values are found in Table 20.
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
DATE K-40 Cs-137 C-14 Other Activity
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
DATE K-40 Cs-137 C-14 Other Activity
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.
I
1
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 Beta
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
Gross AlphaGross Beta
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
Gross AlphaGross Beta
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
INTER-LABORATORY COHPARISONS, 1988
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
Gross AlphaGross Beta
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
Gross AlphaGross Beta
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
INTER-LABORATORY COHPARISONS, 1988
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.
t
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
CALCULATION OF THE SAMPLE ACTIVITY
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
Calculation of the L.T. Value
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
Calculation of the L.T. Value
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
CALCULATION OF THE SAMPLE ACTIVITY
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
CALCULATION OF THE SAMPLE ACTIVITY
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
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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
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