United States
           Environmental Protection
           Agency
                  National Air and Radiation
                  Environmental Laboratory
                  540 South Morris Avenue
                  Montgomery, AL 36115-2601
EPA-402-R-03-004
August 2003
           Office of Radiation and Indoor Air
 V>E;PA
Radiological Survey at the
Naval Nuclear Power
Training Unit - Charleston
                 Internet Address (URL)  http://www.epa.gov
Recycled/Recyclable  Printed with Vegetable Oil Based Inks on Process Chlorine Free Recycled Paper (minimum 50% Postconsumer)

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             Radiological Survey at the

Naval Nuclear Power Training Unit - Charleston
                         Prepared by

                        Ted W. Fowler

                            and

                     Samuel W. Poppell, Jr.



                         August 2003
                U.S. Environmental Protection Agency
                  Office of Radiation and Indoor Air
           National Air and Radiation Environmental Laboratory
                     540 South Morris Avenue
                   Montgomery, AL 36115-2601

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                                 CONTENTS


EXECUTIVE SUMMARY	v

ACKNOWLEDGMENTS	  vii

ILLUSTRATIONS	ix

TABLES	xi

ABBREVIATIONS	xiii

1.0  INTRODUCTION	1
      1.1 Site Description and History	1
      1.2 Survey History 	2
      1.3 Contaminants of Concern	2
      1.4 Study Objectives	2

2.0 SAMPLING, MEASUREMENT, AND ANALYSIS	3
      2.1 Sampling and Measurement Strategy	3
            2.1.1 Sample Identification  	4
            2.1.2 Background Sampling Locations	5
            2.1.3 Nuclear Power Training Unit (NPTU) Survey Site  	5
      2.2 Sample Collection, Preparation and Analysis	5
            2.2.1 Sample Collection and Preparation	5
            2.2.2 Sample Analysis	9
      2.3 External Measurements	9
      2.4 Locational Data 	10

3.0  RESULTS AND DISCUSSION	15
      3.1 Water Samples 	15
            3.1.1 Surface Water	15
            3.1.2 Drinking Water	15
      3.2 Sediment and Sediment Core Samples	15
            3.2.1 River-Bottom and Intertidal Shoreline Sediment	15
            3.2.2 Sediment Core Samples  	16
      3.3 Biota  Samples	16
      3.4 External Radiation Measurements	 17

4.0  QUALITY ASSURANCE/QUALITY CONTROL (QA/QC)	19
      4.1  The Quality Assurance Program  	19
      4.2  Quality Control Samples 	19
                                      in

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      4.3 Performance Evaluation Programs	,	20




5,0 CONCLUSIONS	21




6.0 REFERENCES	23




APPENDIX 	25
                                   IV

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                               EXECUTIVE SUMMARY

This report presents results of a radiological survey conducted in May 1999 by the National Air
and Radiation Environmental Laboratory (NAREL) to assess levels of environmental
radioactivity around the Naval Nuclear Power Training Unit (NPTU) near Charleston, SC. The
purpose of the survey was to assess whether the operation of two nuclear reactors on Moored
Training Ships has created elevated levels of radioactivity that could expose nearby populations
or contaminate the environment.

During this survey 55 samples were collected: 40 at the NPTU study site; 10 from background
locations; and 5 near the outfall of the public water treatment plant. Samples included drinking
water, harbor water, sediment, sediment cores, and biota. All samples were analyzed for gross
alpha and beta activities and gamma emitting radionuclides. Water samples were also analyzed
for tritium. In addition to sample collection and analysis, radiation surveys were performed using
portable survey instruments to detect gamma radiation.

No radioactivity attributable to the operation of the training reactors was detected. All
radioactivity detected in the 55 samples taken during the survey is attributed to naturally
occurring radionuclides or fallout from atmospheric nuclear tests and the Chernobyl reactor
accident in 1986.  External radiation measurements did not detect any increased radiation above
background levels. Based on this radiological survey, practices regarding nuclear-powered
training operations at NPTU have resulted in no increases in radioactivity causing population
exposure or contamination of the environment.

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                              ACKNOWLEDGMENTS

The authors gratefully acknowledge the many staff who participated in this study and who helped
prepare this report. The detailed planning, support, and assistance of the Nuclear Power Training
Unit personnel was much appreciated.  The EPA survey team consisted of Ted Fowler, Sam
Poppell, Jim Moore, Ed Mantiply, and Bob Trefethen from NAREL and Jon Richards from EPA
Region 4 in Atlanta, GA.   Ed Mantiply and Bob Trefethen provided the computer technical
expertise in the preparation of figures for the sample locations.  Chuck Petko edited the report.
Finally, we thank the EPA  staff who served as technical peer reviewers of the manuscript.
                                    DISCLAIMER

Mention of trade names or commercial products does not constitute endorsement or
recommendation for use.
                                         vn

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                             ILLUSTRATIONS




                                                                     Page




1. NPTU Area Map and Sample Locations	7




2. NPTU Sample and External Measurement Locations	8
                                    IX

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                                    TABLES

Table                                                                       Page

1.   Sample and Measurement Locations	,	11

2.   External Gamma Radiation Measurements	18

A.1  Gamma-Emitting Radionuclides in Water	29

A.2  Public Water Treatment Outfall: Gamma-Emitting Radionuclides in Water 	30

A3  Background: Gamma-Emitting Radionuclides in Water	30

A.4  Thorium Chain and Other Gamma-Emitting Radionuclides in Sediment	31

A.5  Uranium and Actinium Chain Gamma-Emitting Radionuclides in Sediment	32

A.6  Public Water Treatment Outfall: Thorium Chain and Other Gamma-Emitting
      Radionuclides in Sediment  	33

A.7  Public Water Treatment Outfall: Uranium and Actinium Chain Gamma-Emitting
      Radionuclides in Sediment  	33

A.8  Background: Thorium Chain and Other Gamma-Emitting Radionuclides in Sediment .. 34

A.9  Background: Uranium and Actinium Chain Gamma-Emitting Radionuclides in
      Sediment 		34

A. 10 Thorium Chain and Other Gamma-Emitting Radionuclides in Sediment Cores	35

A.I 1 Uranium and Actinium Chain Gamma-Emitting Radionuclides in Sediment Cores	37

A. 12 Thorium Chain and Other Gamma-Emitting Radionuclides in Biota	40

A. 13 Uranium and Actinium Chain Gamma-Emitting Radionuclides in Biota	40

A.14 Background: Thorium Chain and Other Gamma-Emitting Radionuclides in Biota	41

A.I 5 Background: Uranium and Actinium Chain Gamma-Emitting Radionuclides in
      Biota	41

A.16 Tritium in Water	42
                                        XI

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A.17 Public Water Treatment Outfall: Tritium in Water	42




A. 18 Background: Tritium in Water	42




A.19 Gross Alpha and Beta Activities in Water	43




A.20 Public Water Treatment Outfall: Gross Alpha and Beta Activities in Water  	43




A.21  Background: Gross Alpha and Beta Activities in Water	43




A.22  Gross Alpha and Beta Activities in Sediment	44




A.23  Public Water Treatment Outfall: Gross Alpha and Beta Activities in Sediment	45




A.24  Background: Gross Alpha and Beta Activities in Sediment 	45




A.25  Gross Alpha and Beta Activities in Sediment Cores	;	46




A.26  Gross Alpha and Beta Activities in Biota  	48




A.27  Background: Gross Alpha and Beta Activities in Biota	48
                                         Xll

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                          ABBREVIATIONS

cm	Centimeter
GPS 	Global Positioning System
IAG	Inter-Agency Agreement
L	Liter
m 	Meter
uR	Microroentgen (10~6 roentgen of y-ray exposure)
uR/hr  	Microroentgen per hour
MDC  	Minimum Detectable Concentration
MTS	Moored Training Ship
NAREL  	National Air and Radiation Environmental Laboratory
NAVSEA	Naval Sea Systems Command
ND 	Not Detected
NPTU	Nuclear Power Training Unit
pCi	Picocurie (10"u curies of radioactivity)
pCi/g	Picocuries per gram-dry-weight
pCi/g-ash 	Picocuries per gram-ashed-weight
pCi/g-wet	Picocuries per gram-wet-weight
pCi/L	 Picocuries per liter
PIC	Pressurized lonization Chamber
TLD 	Thermoluminescent detector
TSB 	Training Support Building
USEPA	United States Environmental Protection Agency
                                  xiu

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1.0 INTRODUCTION

The National Air and Radiation Environmental Laboratory (NAREL) of the United States
Environmental Protection Agency (EPA) in cooperation with the United States Naval Sea
Systems Command (NAVSEA) has previously surveyed facilities serving nuclear-powered
warships. These surveys began in 1963 and have been conducted on the Atlantic and Pacific
coasts, on the Gulf of Mexico within the Continental United States, and at Pearl Harbor, HI. In
1996, an interagency agreement (LAG) was signed with NAVSEA for NAREL to perform
radiological surveys over the next five years at active facilities serving nuclear-powered
warships. These surveys assess whether the construction, maintenance, overhaul, refueling or
operations of nuclear-powered warships and training reactors have created elevated levels of
radioactivity that could expose nearby populations or contaminate the environment.

The first four environmental surveys performed under the interagency agreement were: Puget
Sound Naval Shipyard (PSNS) at Bremerton, WA, and the Naval Submarine Base (NSBB) near
Bangor, WA during 1996 (Fo98); San Diego Bay, CA  (Go99) and Portsmouth Naval Shipyard at
Kittery, ME during 1997 (SmOl); and Pearl Harbor Naval Complex (PHNC), HI during 1998
(PoOl). The fifth environmental survey under the LAG  was performed May 3-6,1999 at the
Naval Nuclear Power Training Unit (NPTU) near Charleston, SC.

A pre-survey trip to NPTU was made March 21-23,1999 to develop a sampling and survey
work plan with the assistance of knowledgeable site personnel and  EPA radiation program
representatives from EPA-NAREL and EPA Region 4. Staff from NAVSEA and NPTU
provided NAREL with information on past and present NPTU radiological operations and
procedures. All requested information was freely provided verbally and/or in writing.  Based on
the information received and that derived from previous EPA studies, a work plan (EPA99) was
developed to describe the approach for assessing the radiological condition of the NPTU and
nearby aquatic environments.

1.1 Site Description and History (NNSOO)

The Naval Nuclear Power Training Unit (NPTU), Charleston, is located on the Cooper River
within the confines of the approximately 9,000 acre Naval Weapons Station Charleston. The
Naval Weapons Station is situated within the city limits of Goose Creek, in Berkley County,
while the southern end of the Weapons Station resides in Charleston County.  Goose Creek is
located approximately 15 miles NNW of Charleston. NPTU occupies a 3.5-acre site consisting
of two Moored Training Ships (MTS), two support barges, a training barge and a training support
building. A Moored Training Ship is a fleet ballistic missile submarine that has been modified to
be an operational propulsion-training platform.

NPTU was established in 1989 and operates under the control of the Director, Naval Nuclear
Propulsion Program. The primary mission of the NPTU is the training of naval personnel for
assignments in the fleet. However, with this type of training, additional services are needed to

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maintain the MTS fully functional.  Services performed at NPTU include: (1) operation and
maintenance of the nuclear power plant, propulsion systems, and auxiliaries on the MTS, (2)
operation of a radioactive liquid processing system to facilitate reuse of reactor plant water, and
(3) short-term storage of mixed (hazardous and radioactive) waste awaiting shipment for
processing and/or disposal.

1.2 Survey History

NPTU has not been surveyed previously by the EPA. During 1985, a survey was performed at
the nearby Charleston Naval Weapons Station as well as the Charleston Naval Base and Shipyard
and there was no detectable radioactivity in any samples due to nuclear operations at the shipyard
or weapons station  (Sm87). NPTU was not operational at the time of the 1985 EPA survey of
Charleston Harbor.

1.3 Contaminants of Concern

The results of previous harbor surveys indicate that cobalt-60 is the predominant radionuclide
one would find in environmental media if radioactivity were present as a result of naval nuclear
propulsion plant operations (Ca77, Ca87). Therefore, environmental sampling during this study
emphasized detection of cobalt-60. Other radionuclides of concern in liquid effluents or
encountered during maintenance work include tungsten-187, chromium-51, iron-59, iron-55,
nickel-63, niobium-95, zirconium-95, manganese-54, and cobalt-58 (ANS99). Water samples
were also analyzed  for tritium since this radionuclide is known to be produced in the coolant of
light-water nuclear  reactors.

1.4 Study Objectives

The objectives of the study were to determine if radioactive material related to U.S. Navy
nuclear-powered training operations is present at measurable levels in the river samples collected
and, as deemed appropriate, to estimate potential doses to the public.

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2.0 SAMPLING, MEASUREMENT, AND ANALYSIS

The following terms will be used in the discussion of the collection of samples and
measurements:

       Survey Site:                The geographical area in and around NPTU that was
                                 studied.

       Measurement Location:      A location in or near the survey site where gamma-ray
                                 exposure rates were measured.

       Background Location:       A selected sampling location where representative levels of
                                 naturally occurring or existing radionuclides, not likely to
                                 be related to NPTU, were measured.

       Sampling Location:         A location within or near the study site from which samples
                                 were collected.

2.1 Sampling and Measurement Strategy

This study was intended to determine the concentrations of cobalt-60 and other selected
radionuclides that could be present due to the operations performed at NPTU and other selected
radionuclides that may be present at or near the study site but originated from off-site locations.
The sampling locations selected were those where the Navy presently conducts environmental
monitoring and locations selected by NAREL to more comprehensively characterize the study
site.

Background sampling locations were selected to obtain baseline radionuclide levels that are
characteristic of the area. The data from the study site were compared directly to the background
concentrations when background data were available or to appropriate standards, such as those in
the national drinking water regulations (EPA76). Three locations were selected for background
sampling.

Field duplicate samples were either co-located (adjacent) with the original samples or the original
samples were split. Biota, bottom sediment, and water samples were typically composited at the
sampling location upon collection and then split into duplicate samples. However, duplicate core
samples and shoreline samples were collected as adjacent samples at  the same sampling location.
Duplicates of different media (e.g., biota, sediment, etc.) were taken at 5 sampling locations
resulting in 18 samples (9 duplicate pairs).

At selected locations, primarily public access areas, radiation surveys were performed using
portable survey instruments to detect gamma radiation.  Three types of gamma measuring
instruments were used: a Ludlum Model 19 Micro-R radiation survey instrument, a GENITRON

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 GM survey instrument, and a Reuter-Stokes pressurized ionization chamber (PIC). Instrument
 serial numbers and calibration dates are available on the field data sheets.
 Samples were taken as close to piers as situations permitted when a distance was not specified.
 Sometimes barges, ships, and other equipment prevented collecting a sample close to the pier,
 and an alternate location was selected. Geographic positions (latitude and longitude) were
 determined by commercially available Geographic Positioning System (GPS) units.  These units
 had a typical accuracy ranging from 30 to 100 meters.

 2.1.1 Sample Identification

 Each sample collected or measurement taken during the survey was marked with a unique code
 which denoted:

             Location
             Matrix or Measurement type
              Sample type detail (e.g., field duplicate, background, sewer outfall)

 The sample identification (ID) code has the form NPTUxxx-yyyy[-zz], where 'xxx' indicates the
 sampling site ID number, 'yyyy' identifies the measurement type or matrix (and species for biota
 samples),  and (zz) provides additional descriptive information: 'DU' if the sample was a
 duplicate or 'BK' if the sample was a background location. Not all samples required the use of
 all characters.  The following table explains the codes used for the different sample types.

                           Sample and Measurement Codes
Code
S
L
C
BO
Sample or Measurement Type
River Sediment
Shoreline Sediment
Sediment Core
Oysters
Code
BMG
W
D
E
Sample or Measurement Type
Marsh Grass
River Surface Water
Drinking Water
External Exposure Rate
Coding for a typical sample might be as follows: an NPTU river-bottom sediment sample taken
at location 11 is coded 'NPTU011-S'.  If the sample were a duplicate at NPTU location 24, it
would be 'NPTU024-S-DU'.  A duplicate water sample taken at NPTU location 31 (a
background location) is labeled 'NPTU031-W-DU-BK'. A non-duplicate marsh grass sample
taken at NPTU location 15 is labeled 'NPTU015-BMG'. A second water sample taken at the
depth of the sewer outfall has an additional identifier of "02" after the location number to
indicate that this is the second water sample collected at this location, but at a different depth
than the first water sample, e.g. 'NPTU028-02-W. "Navy" location ID's with "S" prefixes are
sediment sample location ID's, "W" prefixes are water sample location ID's, "B" prefixes are

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biota sample ID's, and "TLD" prefixes are thermoluminescent detector (TLD) monitoring
location CD's.

2.1.2 Background Sampling Locations

The background locations were selected during the pre-survey visit (March 1999) to the study
site and are located far enough away from the study site so that operations there would not have
impacted these locations. There are three background locations for NPTU: at Channel Marker 89
on the Cooper River across from the Bushy Park entrance (location NPTU031); on the shore of
the Cooper River across from Bushy Park entrance (location NPTU032) (see Fig. 1 and Table 1);
and, for drinking water, at a motel in North Charleston, SC.

2.1.3 Nuclear Power Training Unit (NPTU) Survey Site

The NPTU survey site is on the Cooper River at Goose Creek, SC and the surrounding environs
including the Goose Creek and Yellow House Creek dredging spoils areas.  Specific
measurement and survey locations are listed in Table 1 and shown in Figures 1 and 2. Sampling
locations presently used by the Navy and sampling locations added by NAREL were used during
this survey. A description of each sampling location and the type of sample collected are
presented in Table 1.  During this survey, 40 samples were collected at 25 locations at the NPTU
study site. An additional 10 samples were collected from 3 background locations, and 5 samples
were collected near the outfall of the public water treatment plant near the NPTU North pier.

2.2 Sample Collection,  Preparation and Analysis

Shoreline (intertidal) sediment, river bottom sediment (grab and core), water (river surface,
sewage outfall, and drinking waters), and biota were collected. By previous agreement between
USEPA-NAREL and the Navy, most samples were split for routine independent comparisons by
the Navy. The samples collected from NPTU are listed in Table 1.  Approximately 5 percent of
all samples collected for each sample type were quality control duplicates. The locations where
duplicate samples were taken are noted in the Table 1. All samples were analyzed for gross
alpha and beta activities and gamma emitting radionuclides. Water samples were analyzed for
tritium.

2.2.1 Sample Collection and Preparation

River Water.  Samples were collected by lowering a Wildco horizontal water sampling bottle
(alpha bottle) to a depth of 1  m (two samples at the public sewer outfall north of NPTU were
collected at the depth of the outfall pipe) and then closing the bottle by releasing a "messenger"
that activated a tripping mechanism. This process was repeated until 5 L of water were obtained.
About 4 L of water were poured into a plastic sample container and acidified to a pH of < 2 with
nitric acid.  The acidified water sample was analyzed for gross alpha and beta activities and
gamma emitting radionuclides. One fourth liter of the water sample was poured into a glass
container and, without being acidified, was analyzed for tritium. A total of 14 river water

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 samples were collected, of which 3 were duplicate samples. Two samples were taken at the
 sewer outfall depth. The second sample (NPTU028-03-W) was taken at the sewer outfall as the
 outfall pipe was not located at the time the initial sample was taken. Two samples were taken
 from background locations.

 Drinking Water.  Samples were collected from 2 taps representing the water supplies of North
 Charleston and NPTU.  The 5 L drinking water sample collected at each location was divided
 into two sample containers and analyzed in the same manner as were the river water samples.

 River Bottom Sediment. Sixteen river bottom sediment samples were obtained during this study.
 Sediment sampling from boats was performed using a Peterson dredge to sample approximately
 the top 10 cm of sediment. Each sample consisted of approximately 4 liters. Samples collected
 included two background locations and two duplicate samples. No sediment was collected at
 location NPTU030. A second sediment sample (NPTU028-02-S) was collected at the public
 water treatment outfall because the outfall pipe had not been located when the original sample
 was taken.

 Shoreline Sediment. Samples were collected with a small trowel or scoop and consisted of
 approximately 4 liters of surface soil collected from the intertidal shoreline near the low tide line.
 Stones and organic debris were excluded as much as possible.  Any remaining debris was
 removed by sieving with a 16-mesh sieve during sample preparation at the laboratory.  A total of
 9 shoreline samples were collected, of which 2 were background and 2 were duplicate samples.

 Sediment Core. Each sediment core consists of a 5 cm diameter cylinder of sediment up to 51
 cm in length. Sediment core samples were obtained to evaluate the vertical distribution of
 radioactivity in sediment.  Samples were collected by pushing the plastic tube vertically into the
 river bottom or dredging spoils as far as possible, then capping the ends. Excess water was
 decanted from the top of each core. The cores were frozen  prior to shipping and remained frozen
 during shipping. Before analysis, the frozen cores were cut into a maximum of 5 segments per
 core with each segment having a minimum length of 5 cm.  Each section was oven dried. A total
 of 8 core samples were collected, of which 1 was a duplicate sample collected for quality
 assurance purposes. Except for the three cores collected by the EPA sampling team at the
 dredging spoils areas, core samples were collected by Navy divers.  During the course of the
 survey, a second core sampling location at the Goose Creek dredging spoils area was added
 (NPTU025-C-02) adjacent to location NPTU025.

Biota.  Eight biota samples were collected, each consisting  of approximately 4 liters of one
species of marine life.  Samples were collected from as small a region as possible. Marsh grass
was collected on the shoreline by the EPA sampling team and oysters were  collected by divers.
Biota samples were homogenized in the field, frozen for shipping and thawed for radioanalysis.
Because of the interest in iodine-131, all biota samples were counted wet by gamma spectroscopy
within 7 days after collection. Of the 8 biota samples collected, 2 were duplicates samples
collected for quality assurance purposes. One biota sample and a duplicate sample were
collected from a background site.

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Fig. 1. NPTU Area Map and Sample Locations

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I
 i
 p
 u
I
CM
          x

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2.2.2 Sample Analysis

Samples for each location were analyzed for gamma emitting radionuclides and for gross
alpha/beta activities. Of particular interest was cobalt-60 in the sediment samples and iodine-
131 in the water samples.  All water samples were analyzed for tritium. Specific isotopic
analyses were performed on selected samples.

Gamma Spectrometry. This procedure allows for characterization of the gamma-emitting
radionuclides present in the sample without separating them from the sample matrix. The
limit of detectability of this method is a function of the sample size, counting geometry,
detector efficiency, background, counting time, gamma photon energy of the nuclide, and
branching ratio (percent abundance). Liquid samples are acidified and soil or sediment
samples are ground and sieved to ensure the homogeneity of the samples. Biota samples are
homogenized prior to analysis to ensure uniformity of the sample.

Gross Alpha/Beta.  This procedure, which provides a rapid screening measurement, was used
as a gross approximation of the alpha and beta activity present in the sample. Low energy and
volatile radionuclides such as tritium, carbon-14, and iodine will not be detected by this
method. In addition, polonium and cesium may be lost if the procedure requires flaming of
the sample. For water  samples, a known amount of the sample is evaporated to a small
volume then transferred to a small container and farther evaporated for measurement. For
solid samples, a known amount of the sample is placed on the planchet.  Water is added and
the sample is dried to provide even distribution.  The sample is weighed and counted on a gas
proportional counter. These analyses are not as accurate as their isotopic counterparts.

Tritium Analysis.  Water samples are distilled and are incorporated into a counting mixture
consisting of a primary solvent, emulsifier, and fluors. The tritium is assayed in a liquid
scintillation spectrometer.

2.3 External Measurements

External radiation measurements were made along the shoreline and on the water at NPTU
with emphasis on areas accessible to the public.  External radiation measurement locations
are presented in Table  1 and Figures 1  and 2.  Measurements were recorded every 10 minutes
during the survey with a Genitron Instruments Gamma TRACER GM type survey instrument,
and readings were downloaded at each external monitoring location. External exposure
readings were also taken for 5 to 10 minutes at each location with a Reuter-Stokes  pressurized
ion chamber (PIC). Results of the external radiation measurements are shown in Table 2. No
radiation levels above normal background which could be attributable to radiation associated
with nuclear-powered operations were detected.  The highest reading at a stone-stabilized
shoreline was attributed to higher levels of naturally occurring radioactivity in the stone than
in the surrounding terrain.

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2.4 Locational Data

For each sample and measurement location, the approximate geographical position (latitude
and longitude) of the location was determined in the field. At 19 of the 33 locations
Communications Systems International Model GBX-12R differential Geographic Positioning
System (GPS) units were used. These units have a typical accuracy of about 3 meters. GPS
readings were supplemented by measuring line-of-sight distances to nearby landmarks. The
distances were measured using a Bushnell YardagePro 400 laser rangefinder, which is
accurate to within about two meters.
                                        10

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           TABLE 1
Sample and Measurement Locations
1 Location ID
001
002
003
004
005
006
007
008
009
010
Oil
M *-/
*!
S2/W2

Bl
S5

S3
S4/W3

SB
S6
7/W4
Position"
r 2: T^
II t
o- S
 8-
32 56.729' 79 55.760'
32 56.703' 79 55.747'
32 56.7 IT 79 55.778'
32 56.692' 79 55.753'
32 56.685' 79 55 .749'
32 56.707' 79 55.727'
32 56.669' 79 55.720'
32 56.632' 79 55.705'
32 56.624' 79 55.7 14'
32 56.644' 79 55.681*
32 56.600' 79 55.681'
o
e
"SL
n'
ta
*+
n











1 Background











Samples and
Measurements "^
09 &
 o g ^ 1
 o 5  3
n  ST 5 ?
= 1
s w
s c
B
S
s c
s
s w
s c
s
s
s w

Location Description
Pier X-ray North finger pier, taken at aft end of IX-516.
Under MTS-635 mid-brow between Pier X-ray North and MTS-
635.
North end of Pier X-ray North, 98 m from NE corner of TSB,
second metal piling 39 m from MTS-635.
Pier X-ray North, west side of pier, 30 m down the pier, 6 m out
from pier.
Previous location of Rad Con Barge, Pier X-ray North, west side
of pier, 45 m down the pier 6 m out from pier.
Pier X-ray North, taken at the east side of MTS-635, 50 m down
the pier, 15m out from the reactor compartment.
Pier X-ray North , taken 12 m aft of MTS-635.
Under MTS-626, mid-brow between Pier X-ray South and MTS-
626.
Pier X-ray South, west side of pier, 48 m down the pier, 5 m out
from pier.
Pier X-ray South, est side of MTS-626, 68 m down the pier, 15 m
out from the reactor compartment.
Pier X-ray South, 12 m aft of MTS-626.

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TABLE 1 - Continued
ID
012
013
014
015
016
017
018
019
020
021
022
023
024
025
025-02
NAVY






TLD3
TLD1
TLD2



W5/S
9


Latitude
32 56.7 12'
32 56.676'
32 56.7 16'
32 56.7 16'
32 56.685'
32 56.528'
32 56.681'
32 56.650'
32 56.630'
32 56.647'
32 56. 160'
32 56.328'
32 56.442'
32 55.007'
32 55.014'
Longitude
79 55.715'
79 55.687'
79 55.666'
79 55.807'
79 55.797
79 55.732'
79 55.841'
79 55.806-
79 55.7531
79 55.8 16'
80 02.844'
79 56.090'
79 55.7 19'
79 56.997'
79 57.021'
DU




DU





DU

DU


BK










BK




Samples & Measurements
E
E
E
L B E
L B E
L B E
E
E
E
D
D
E
S C W
L C
C
Location Description
Pier X-ray North, 47 m east of MTS-635 reactor compartment
shields.
Midpoint between MTS635 and MTS-626, 91 m from NE comer
of Pier X-ray South, 213m from SE corner of TSB.
Pier X-ray South, 55 m east of MTS-626 rector compartment
shields, 70 m to SE corner of Pier X-ray South.
Shoreline, 64 m from south end of IX-516, 83 m from NE corner of
TSB.
Shoreline, 59 m from NE corner of TSB, 66 m from SW corner of
Pier X-ray North.
Southern point of NPTU, 69 m from SE corner of Building 43, 147
m from S end of Pier X-ray South.
52 m N of NE corner of TSB, 143 m from S end of Pier X-ray
North, at corner of the fence S of Pier X-ray North entrance.
5 m from SE corner of TSB, outside perimeter fence E side of SE
entrance of TSB at the perimeter fence across from SE entrance of
TSB
Eastern most point of the southern boundary fence, 98 m N of
Building 43.
NPTU TSB canteen sink.
Best Western Inn, 7401 Northwoods Blvd., North Charleston, SC
On the shoreline rocks, 47 m N from NE corner of Wharf Alpha.
Intersecting lines between Wharf Alpha and Pier X-ray North (line
1 : center of channel, line 2: Wharf Alpha north end to inlet on east
side of river south of fork).
Goose Creek Dredging Spoils Area.
Goose Creek Dredging Spoils Area - approximately 20 m S of
NPTU025-C.

-------
                                                    TABLE 1 -- Continued
ID
026
027
028
028-02
028-03
029
030
031
032
033
NAVY

TLD5




Wl/S
1



Latitude
32 55.866'
32 56.828'
32 56.972'
32 56.972'
32 56.986'
32 56.965'
32 57.223'
32 58. 195'
32 58. 178'
32 56.8 14'
Longitude
79 56.088'
79 55.548'
79 55.875'
79 55.901'
79 55.901'
79 55.9 18'
79 55.660'
79 55.7 18'
79 55.754'
79 55.923'
DU







DU
DU

BK







BK
BK

Samples & Measurements
L C
E
S W
S W
W
L B E
W
S W
L B E
E
Location Description
Yellow House Creek Dredging Spoils Area, 132 m from sampling
point to shoreline (312NW).
370 m WSW 256 from IX-516 Barge, at post across Cooper River
from MTS-635.
Near sewer outfall pipe, 9 m from shore.
At sewer outfall pipe opening, 9 m from shore.
Sewer outfall 9 m from shore, at depth of outfall pipe on pipe
opening.
Shoreline 263 m SE of buoy 80, 623 m from marker 82 bearing 75
ENE from shoreline, approximately 366 m N of the NPTU North
pier.
North of Pier X-ray North, intersecting lines between government
sign and pier of house.
At the green Channel Marker 89 across from the Bushy Park
entrance on the Cooper River.
Shoreline at green channel marker 89 across from Bushy Park
entrance on the Cooper River.
Picnic area near NPTU, 99 m N of NE corner of Mallard Pond
' Navy symbols used in the tables are explained on page 4.
* Latitude and longitude are given in degrees and decimal minutes.
c Sample and measurement type codes are explained on page 4.
d Water samples were collected at a depth of 1 m unless otherwise specified.

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3.0 RESULTS AND DISCUSSION

The radioanalytical results for the NPTU samples collected during this survey are reported in the
Appendix. The tables were generated from Data Quality Packages (DQPs) produced from
radioanalytical results. The quality assurance/quality control (QA/QC) results for the laboratory
analyses and field sample QA/QC were presented in the DQPs for the sample analyses, and the
results were within acceptable limits as specified in the Quality Assurance Project Plan (EPA97)
for this survey.  Some of the reported radionuclide activity results are negative.  Negative results
occur whe'n a previously determined background value is subtracted from a sample value that is
less than the background value. Negative values represent a portion of the statistical distribution
of negative and positive values around zero for samples containing very little or no detectable
radioactivity.

3.1 Water Samples

3.1.1 Surface Water

Eleven surface water samples were collected.  These consisted of 6 site location samples
(including a duplicate); 1 background sample and duplicate; and 3 samples at the public water
treatment outfall. The gamma analysis results are shown in Tables A.I - A.3. Only naturally
occurring radionuclides were detected  in water samples. Tritium analyses were performed on all
water samples, and results are presented in Tables A. 16 - A. 18. Tritium concentrations in the
water samples collected at NPTU were similar to those collected at background locations. The
minimum detectable concentration (MDC) of tritium was about  140 pCi/L for the water samples.

Results of the gross alpha and beta analyses of water samples are presented in Tables
A. 19 - A.21.  Samples collected from NPTU have concentrations similar to those found in the
background samples and samples at the public water treatment outfall.

3.1.2 Drinking Water

Three drinking water samples, which included a background with duplicate sample, were
collected.  The NPTU  drinking water sample had a gross alpha concentration of -0.290.43
pCi/L (Table A. 19) which indicates that this sample had little or no radioactivity. The National
Drinking Water Regulations (EPA76)  state that the maximum allowed gross alpha particle
radioactivity in community water systems is 15 pCi/L (including radium-226, but excluding
radon and uranium).

3.2 Sediment and Sediment Core Samples

3.2.1  River-Bottom and Intertidal Shoreline Sediment

A total of 25 river bottom and intertidal shoreline sediment samples were collected. Of the 16
river bottom samples collected: 12, including one duplicate, were collected at the survey

                                           15

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 location; 2 were collected at the public water treatment outfall; and 2, including one duplicate,
 were collected at the background location. Nine shoreline sediment samples were collected: 7
 including, one duplicate sample, at the survey location and 2 background samples, which
 included one duplicate sample.  The gamma analysis results are shown in Tables A.4 - A.9.
 Gamma emitting radionuclides  measured in the sediment samples were naturally occurring
 radionuclides or fallout from atmospheric nuclear tests (EPA73). No cobalt-60 was detected in
 any of the  sediment samples collected at NPTU. The cobalt-60 MDCs for sediment samples
 were in the range of 0.015 to 0.03 pCi/g-dry due to the detector used and the sample size.  All
 samples were counted on a germanium detector for 1000 minutes.

 Results of the gross alpha and beta analyses of sediment samples are presented in Tables
 A.22 - A.24. The maximum total gross alpha and beta concentrations were 175.1  pCi/g-dry and
 274.2 pCi/g-dry, respectively, in samples collected from NPTU; 7.83.5 pCi/g-dry and 193.9
 pCi/g-dry in samples collected at the public water treatment outfall; and 124.6 pCi/g-dry and
 234.1 pCi/g-dry, respectively, in samples from background locations.  In summary, sediment
 samples from NPTU have concentrations similar to the background and public water treatment
 outfall samples.

 3.2.2 Sediment Core Samples

 Eight sediment core samples were taken at 6 sites. Gamma analysis results for the sediment core
 samples are shown in Tables A.I 0 and A.I 1. No cobalt-60 was detected in any of the sediment
 core samples collected at NPTU. All radionuclides identified in the 8 cores were attributed to
 naturally occurring radionuclides or fallout.  The radionuclide content of the core samples
 showed no significant differences with depth or from the dredge samples taken in the same
 general area.

 Results of the gross beta and alpha analyses of sediment core samples are shown in Table A.25
 for NPTU.  The results of the samples from NPTU are generally consistent, with only a  few
 samples showing elevated gross beta concentrations. The elevated gross beta concentrations are
 attributable to elevated concentrations of naturally occurring radionuclides as seen in the gamma
 spectrometry analyses (See Tables A. 10 and A.I 1).

 3.3 Biota Samples

 Eight biota samples were collected: 6 (including 2 duplicates) were collected at the survey
 location and 2 (including 1  duplicate) were collected as background. The gamma analysis results
 for these samples are shown in Tables A. 12 - A. 15.  Essentially only naturally occurring
radionuclides were detected with the exception of trace amounts of Cs-137, which is most likely
present due to fallout.

Results of the gross alpha and beta analyses of biota samples are presented in  Tables A.26  and
A.27. The samples collected at NPTU showed concentrations of alpha emitting radionuclides
above those from background samples, but based on the  gamma spectrometry results these

                                           16

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elevated readings at the NPTU site are most likely caused by elevated concentrations of
naturally-occurring radionuclides in the biota. The slightly elevated beta concentrations from the
NPTU samples as compared to background are caused by slightly elevated K-40 in the NPTU
samples, and thus are also due to naturally occurring radionuclides.

3.4 External Radiation Measurements

External radiation measurements were made along the shoreline and on the water at NPTU with
emphasis on areas accessible to the public. Measurements were recorded every 10 minutes
during the survey with a Genitron Instruments Gamma TRACER GM type survey instrument.
Readings were downloaded at each external monitoring location. External exposure readings
were also taken for 5-10 minutes at each location with a Reuter-Stokes pressurized ion chamber
(PIC). A Ludum Model-19 was also used to measure variation in exposure rates along the
shoreline at each location.  The Ludlum Model-19 does not respond linearly in response to
gamma rays of different energies as do the other instruments. Due to this difference in response,
the Ludlum Model-19 may provide what appears to be inconsistent results, and will frequently
indicate higher radiation readings than the other detectors  due to this nonlinear response.  Results
of the external radiation measurements are shown in Table 2. No radiation levels above normal
background which could be attributable to radiation associated with nuclear-powered operations
were detected. Radiation levels measured were due to naturally occuring radionuclides. The
highest reading at a stone-stabilized shoreline was attributed to higher levels of naturally
occurring radioactivity in the stone than in the surrounding terrain.
                                           17

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                                   TABLE 2
                     External Gamma Radiation Measurements
Location ID
NPTU012-E
NPTU013-E
NPTU014-E
NPTU015-E
NPTU016-E
NPTU016-E-DU
NPTU017-E
NPTU018-E
NPTU019-E
NPTU020-E
NPTU023-E
NPTU027-E
NPTU029-E
NPTU032-E-BK.
NPTU032-E-DU-BK
NPTU033-E
PIC Exposure Rates
|iR/hr
2.2-5.2
3.5-4.8
3.5-4.8
6.3 - 8.3
5.6 - 10.0
5.5 - 7.7
2.7-7.8
4.9-11.2
2.4 - 8.2
5.5-6.6
9.9 - 14.2
3.8-5.1
7.8 - 9.6
3.5-4.5
3.5-4.9
6.7 - 9.7
GENITRON Exposure
Rates
llR/hr
71
61
51
101
41
101
91
101
91
61
25 T
51
101
31
51
81
Ludlum Model-19
Exposure Rates
|lR/hr
1
1
1
8
8-9
8-10
8-9
7-8
8-10
3-4
20 - 23"
1-2
8-10
1
1
8
The GENITRON and the Ludlum Model-19 read much higher than the PIC because they were
on the rocks and the PIC was sitting on a tripod about 1  m above the rocks.
                                       18

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4.0 QUALITY ASSURANCE/QUALITY CONTROL (QA/QC)

4.1 The Quality Assurance Program

The NAREL Quality Assurance (QA) Plan applies to all work performed at NAREL. The
purpose of the quality assurance program is to ensure that all measurements performed at
NAREL are valid, scientifically defensible, and of known precision and accuracy. The NAREL
Quality Assurance Project Plan (QAPP) for the U.S. Navy Environmental Studies (EPA 97) was
prepared in accordance with the requirements described in "EPA Requirements for Quality
Assurance Project Plans for Environmental Data Operations" (EPA94).

Quality Assurance/Quality Control (QA/QC) for the laboratory analyses performed for this
survey is detailed in the QAPP (EPA97).  Quality control (QC) samples are analyzed in
conjunction with routine samples to ensure the quality of the analytical results.  Corrective
actions must be taken when it is shown by the results of QC samples that the radioanalytical
procedure is beyond predetermined control limits. Quality assurance is equally important in the
sample collection process. All documentation including chain-of-custody forms were properly
completed.  Sampling equipment was in good working order and field measurement equipment
was calibrated and properly maintained.

4.2 Quality Control Samples

Field and laboratory quality control samples were included with site samples to help evaluate the
entire sampling and analysis process. Evaluation of QC samples allows assessment of the
accuracy and precision of the analytical procedures.  In the field, for each matrix and batch of up
to 20 samples, a field duplicate was collected. The field duplicate results assess the consistency
of the sampling process and the representativeness of the samples collected.

In the laboratory, samples were grouped in batches for quality control purposes, with a maximum
of 20 samples per matrix per analysis type. For each batch, the laboratory analyzed a reagent
blank, a matrix spike, a matrix spike duplicate, and a laboratory replicate sample. However, for
gamma spectrometry and gross alpha and beta analyses, only a recount (duplicate) or split was
performed for batch QC.  Results of these QC samples were reviewed with sample results as part
of the data verification and review process. Specific criteria for acceptance were included in the
QAPP (EPA97).  All blank results were maintained on control charts by analyst, matrix, and
analyte. Warning and rejection limits were used to assess acceptance of the blank results. No
substantial corrective actions were required during the processing and analysis of the samples for
this survey. Radioanalytical sample results complied with the terms and conditions of the QAPP
as certified by the NAREL Quality Assurance Coordinator and Chief, Monitoring and Analytical
Services Branch.
                                          19

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4.3 Performance Evaluation Programs

It is NAREL policy to participate in many intralaboratory comparisons of radioactivity
measurements and cross-check programs. NAREL participates in intercomparison QA studies
with the National Institute of Science and Technology (NIST) in Gaithersburg, MD; the World
Health Organization (WHO) in Le Vesinet, France; the International Atomic Energy Agency
(IAEA), Vienna, Austria; the U.S. Department of Energy (DOE) Radiological Environmental
Science Laboratory in Idaho Falls, ID; the DOE Environmental Measurements Laboratory (EML)
in New York, NY; and with Analytics, a commercial company in Atlanta, Georgia.
                                        20

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5.0 CONCLUSIONS

The radiological survey at the NPTU provides the basis for the following conclusions:

1.      All radioactivity detected in the 55 samples taken during the survey is attributed to
       naturally occurring radionuclides or fallout from atmospheric nuclear tests and the
       Chernobyl reactor accident in 1986.  Water samples from NPTU contained no detectable
       levels of radioactivity other than those occurring naturally. No cobalt-60 was detected in
       any of the sediment or sediment core samples collected at NPTU.

2.      External radiation measurements did not detect any increased radiation exposure above
       natural background levels with the exception of a higher external radiation reading at a
       stone-stabilized shoreline which may be attributed to higher levels of naturally occurring
       radioactivity in the stone than in the surrounding terrain.

3.      Based on the results presented in this study, practices regarding nuclear-powered
       operations at NPTU have resulted in no detectible increases in radioactivity causing
       population exposure or contamination of the environment.
                                            21

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6.0 REFERENCES

ANS99       American Nuclear Society, 1999, Radioactive Source Term for Normal
             Operations of Light Water Reactors, ANSI/ANS-18.1-1999.

Ca77         Callis, R.S., Windham, S.T., and Phillips, C.R., 1977, Radiological Survey of
             Puget Sound Naval Shipyard, Bremerton, Washington and Environs, U.S.
             Environmental Protection Agency Report, February 1977, EPA 520/5-77-001.

Ca87         Callis, R. S., 1987, Radiological Survey of the Pearl Harbor Naval Shipyard
             and Environs, Honolulu, Hawaii, USEPA Report, June 1987, EPA 520/5-87-
             010.

EPA76       U.S. Environmental Protection Agency, Office of Water Supply, 1976,
             "National Interim Primary Drinking Water Regulations", EPA-570/9-76-003
             (also, Federal Register, Vol. 41, No. 133, National Interim Primary Drinking
             Water Regulations, Final Rule, pp. 28402-28409,41 FR 28402, July 9,1976).

EPA94       U.S. Environmental Protection Agency, Quality Assurance Management Staff
             (now Quality Assurance Division),  1994, EPA Requirements for Quality
             Assurance Project Plans for Environmental Data Operations, U.S.
             Environmental Protection Agency Report, Draft Interim Final, August 1994,
             EPA QA/R-5.

EPA97       U.S.  Environmental Protection Agency, 1997, Work Plan for Environmental
             Surveys at U.S. Naval StationsQuality Assurance Project Plan, U.S. Navy
             Environmental Surveys, National Air and Radiation Environmental
             Laboratory, Draft, September 5,1997,  IAG/QAPP-1.

EPA99       U.S.  Environmental Protection Agency, 1999, Work Plan for Environmental
             Survey at the Charleston Naval Nuclear Power Training Unit and Kings Bay
             Naval Submarine Base, National Air and Radiation Environmental
             Laboratory, April 28,1999.

EPA03       U.S. Environmental Protection Agency, Environmental Radiation Data
             (ERD), Reports 1-103,1973-2000.  http://www.epa.gov/narel/erams/
             erdonline.html. Reports accessible are 75-102. Other reports can be obtained
             from NAREL (March 2003).

Fo98        Fowler, T.W. and Cox, C., 1998, Radiological Survey at the Puget Sound
             Naval Shipyard and Naval Submarine Base - Bangor, U.S. Environmental
             Protection Agency Report, July 1998, EPA-402-R-98-003.
                                        23

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 Go99        Goodman, R.A., 1999, Radiological Survey of Naval Facilities on San Diego
             Bay, U.S. Environmental Protection Agency Report, January 1999, EPA-402-
             R-98-011.

 NNSOO      Norfolk Naval Shipyard, 2000,  Historical Radiological Assessment for Naval
             Weapons Station Charleston, Volume I. November 2000.

 PoO 1         Pohl, K. R., 2001, Radiological Survey of the Pearl Harbor Naval Complex,
             U.S. Environmental Protection Agency Report, November 2001, EPA402-R-
             01-014.

 Sm87        Smith, J. M., 1987, Radiological Survey of the Charleston Naval Base and
             Shipyard and the Charleston Naval Weapons Station, U.S. Environmental
             Protection Agency Report, June 1987, EPA 520/5-87-009.

SmO 1         Smith, J. M. and Lloyd, V.D., 2001, Radiological Survey of Portsmouth Naval
             Shipyard, U.S. Environmental Protection Agency Report, November 2001,
             EPA-402-R-01-013.
                                      24

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      APPENDIX
Radioanalytical Results for




       May 1999




     NPTU Samples
           25

-------
                General Information for NAREL Analytical Methods

                  as Reported in the NAREL Data Quality Packages
Gamma Spectrometry

Gamma analysis was done on all collected samples. The activity and 2-sigma uncertainty for
radionuclides measured by gamma spectroscopy are reported only if the nuclide is detected.
Nuclides that are not detected do not appear in the report, with the exception of barium-140,
cobalt-60, cesium-137, iodine-131, potassium-40, radium-226, and radium-228. If one of
these seven nuclides is undetected, NAREL reports it as "Not Detected" or "ND".

Due to potential spectral interferences and other possible problems associated with the
determination of the activity for certain radionuclides, the activities for thorium-234,
protactinium-234m, radium-226, and uranium-235 are subject to greater possible error than
other commonly reported radionuclides.  Note that this potential error is not included in the
2-sigma counting error reported with each activity. Although in this report we do provide the
calculated activities for these radionuclides, we recommend that the results be used only as a
qualitative means of indicating the presence of these radionuclides and not as a quantitative
measure of their concentration.  The results for these nuclides are not used in the evaluation
of quality control samples. Furthermore, because of mutual interference between radium-226
and uranium-235, NAREL's gamma analysis software tends to overestimate the amounts of
these nuclides whenever both are present in a sample. Lower estimates for radium-226
activities can be obtained  from the reported activities of its decay products, lead-214 and
bismuth-214, which could be somewhat  less than the radium-226 activity because of the
potential escape of radon gas.

NAREL's gamma spectroscopy software corrects activities and MDCs for decay between
collection and analysis, but only up to a limit often half-lives. So, if the decay time for a
sample is more than ten half-lives of a radionuclide, that nuclide will almost for certain be
undetected, and the reported MDC v/ill be meaningless. This is usually a problem only for
short-lived radionuclides, such as iodine-131 and barium-140, when there is a long delay
between collection and analysis.

Gross Alpha and Beta Analysis

In comparison to the methods employed to determine radionuclide-specific activities, the
method employed by NAREL to determine gross alpha and beta activity has the potential for
greater analytical bias.  This is especially true for soils.  Note that this potential analytical
error is not included in the 2-sigma counting error term. Therefore, gross alpha and beta
results should be used as gross approximations of the alpha and beta activity present.
                                         27

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                                                        TABLE A.1
                                         Gamma-Emitting Radionuclides in Water
SAMPLE ID
NPTU001-W
NPTU007-W
NPTUOM-W
NPTTJ021-D
NPTU024-W
NPTU024-W-DU
NPTU030-W
NAREL ID
99.02364
99.02368
99.02372
99.02420
99.02413
99.02416
99.02377
Activity (pCi/L  2
-------
                                                                 TABLE A.2
                                   Public Water Treatment Outfall: Gamma-Emitting Radionuclides in Water
SAMPLE ID
NPTU028-W
NPTU028-02-W
NPTU028-03-W
NAREL ID
99.02415
99.02418
99.02419
Activity (pCi/L  2o counting error)
"Co
ND
ND
ND
'"I
ND
ND
ND
"7Cs
ND
ND
ND
K
58.20*15.86
94.40*17.37
32.50*14.03
"'Ra
ND
ND
ND
"*Ra
ND
ND
ND
mRa
ND
ND
ND
2llpb
ND
ND
ND
"Tl
ND
ND
ND
           Note: ND indicates radionuclide was not detected by gamma spectrometry.
U>
O
                     TABLE A.3
Background: Gamma-Emitting Radionuclides in Water
SAMPLE ID
NPTU022-D-BK
NPTU022-D-DU-BK
NPTU031-W-BK
NPTU031-W-BK-DU
NAREL ID
99.02379
99.02380
99.02375
99.02376

*Co
ND
ND
ND
ND

u, ,
ND
ND
ND
ND

"7Cs
ND
ND
ND
ND
Activity (pCi/L  2a counting error)
40K
ND
ND
ND
ND
'"Ra
ND
ND
ND
ND
2MRa
ND
ND
ND
ND
"Ra
ND
ND
ND
ND
IUPb
ND
ND
ND
ND
IOT1
ND
ND
ND
ND
           Note: ND indicates radionuclide was not detected by ga nma spectrometry.

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                                                       TABLE A.4
                          Thorium Chain and Other Gamma-Emitting Radionuclides in Sediment
SAMPLE ID
NPTU 001 -S
NPTU002-S
NPTU004-S
NPTU 005-S
NPTU006-S
NPTU 007-S
NPTU 008-S
NPTU009-S
NPTU010-S
NPTUOII-S
NPTU 024-S
NITU024-S-DU
NPTUOIS-L
NPTI.IOI6-L
NniJ()1f.-l.-nt)
NPTU 01 7-1.
NPTU 025-1,
NPTU 026-L
NI'TU 029-1.
NAREL ID
W.02363
99.02411
99.02365
99.02410
99.02366
99.02367
99.02414
99.02369
09.02370
99.02371
99.02408
W.024I2
99.02346
99.02345
W.02344
99.02347
99.02348
99.02407
99.02378

"'Ra
0.790.06
1.00*0.07
0.830.06
0.98*0.07
0.79*0.06
0.890.07
0.83*0.06
1.00*0.07
0.66*0.05
0.79*0.06
1.42*0.09
1.52*0.10
2.54*0.15
0.44*0.04
ft.33tO.04
0.76*006
1.16*0.08
0.76*0.05
0.43*0.04

IWRa
0.32*0.31
0.90*0.30
0.68*0.27
0.90*0.35
0.57*0.34
0.87*0.34
ND
0.60*0.33
0.76*0.27
ND
1.26*0.25
1.18*0.33
2.50*0.37
0.48*0.23
0.3R10.22
0.55*0.33
ND
0.49*0.26
0.46*0.19
Activity (pCi/g-dry  2o counting error)
"'Pb
1.10*0.07
1.16*0.07
1.16*0.07
1.40*0.09
1.08*0.07
1.17*0.08
0.92*0.06
1.28*0.08
0.870.06
1.02*0.07
1.60*0.10
1.72*0.11
285*0.17
0.61*0.04
0.4.U0.03
0.99*0.07
1.25*0.08
0.82*0.05
0.52*0.04
"'Bi
1.14*0.17
1.02*0.17
1.28*0.19
1.33*0.19
0.98*0.24
1.09*0.16
0.78*0.15
1.23*0.17
0.64*0.13
1.00*0.20
1.55*0.17
1.56*0.17
2.44*0.23
0.58*0.17
0.3610.13
1.04*0.16
1.10*0.20
0.76*0.12
0.57*0.11
IOITI
0.36*0.03
0.370.03
0.38*0.03
0.43*0.03
0.34*0.03
0.38*0.03
0.2R0.02
0.42*0.03
0.26*0.02
0.30*0.02
0.51*0.03
0.54*004
0.91*0.06
0.20*0.02
0.15t0.02
0.33*003
0.40*0.03
0.26*0.02
0.16*0.01
'Be
1.02*0.13
ND
1.05*0.12
0.14*0.10
1.47*0.15
0.75O.I2
ND
0.96*0.13
0.62*0.10
0.61*0.12
ND
0.07*0.07
ND
0.43*0.09
0.16+0.06
1.08*0.12
0.13*0.11
ND
Nl>
"Co
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND .
Nl>
ND
ND
ND
ND
IJ'Cs
0.15*0.02
0.15*0.02
0.13*0.01
0.13*0.02
0.14*0.02
0.14*0.02
0.13*0.02
0.08*0.01
0.07*0.01
0.09*0.01
0.05*0.01
0.02*0.01
ND
0.04*0.01
0.03*0.01
0.12*0.01
0.16*0.02
ND
ND
K
8.24*0.54
8.07*0.52
8.61*0.55
9.55*0.62
7.95*0.55
7.820.52
6.66*0.45
9.92*0.63
5.02*0.34
6.42*0.44
3.44*0.24
3.21*0.25
4.12*0.29
3.96*0.35
3.20*0.30
7.70*0.52
7.97*0.53
3.17*0.23
3.97*0.28
,,
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Note: ND indicates radionuclidc was not detected by gamma spectrometry.

-------
                                                      TABLE A.5
                       Uranium and Actinium Chain Gamma-Emitting Radionuclides in Sediment
SAMPLE ID
NPTU001-S
NPTU002-S
NPTU004-S
NPTU 005-S
NPTU006-S
NPTU 007-S
NPTU 008-S
NPTU009-S
NPTU010-S
NPTUOII-S
NPTU 024-S
NPTU 024-S-DU
NPTUOI5-L
NPTU016-L
NPTUOI6-L-DU
NPTU017-L
NPTU025-L
NPTU 026-L
NPTU 029-1,

INAKhL ID
99.02363
99.02411
99.02365
99.02410
99.02366
99.02367
99.02414
99.02369
99.02370
99.02371
99.02408
99.02412
99.02346
99.02345
99.02344
99.02347
99.02348
99.02407
99.02378
Activity (pCi/g-dry  2o counting error)
Th
0.74*0.23
2.30*0.28
1.55*0.23
2.36*0.30
2.36*0.20
1.59*0.24
2.66*0.32
3.24*0.37
1.80*0.26
1.12*0.26
2.05*0.23
1.5910.27
2.08*0.35
1.06*0.24
0.64*0.19
1.75*0.28
2.80*0.31
1.14*0.23
0.55*0.17
""Pa
1.43*1.36
2.71*1.34
2.22*1.24
2.41*1.45
2.41*1.46
2.38*1.41
3.51*1.55
3.08*1.33
2.80*1.16
1.64*1.28
0.88*0.88
ND
2.01*1.24
ND
ND
2.30*1.44
3.05*1.69
1.43*0.93
ND
'"Ra
3.06*0.36
0.41*0.29
4.03*0.39
5.29*0.47
3.70*0.42
4.04*0.39
6.69*0.51
5.70*0.49
4.14*0.40
3.66*0.37
3.15*0.32
3.07*0.34
3.94*0.42
1.62*0.28
1.13*0.25
3.16*0.35
3.65*0.41
3.25*0.33
0.88*0.20
IUPb
1.20*0.08
1.49*0.09
1.55*0.10
1.99*0.12
1.13*0.07
1.32*0.08
2.85*0.17
2.32*0.14
1.78*0.11
1.23*0.08
1.29*0.08
1.48*0.00
1.79*0.11
0.46*0.04
0.34*0.03
0.76*0.05
2.48*0.15
1.56*0.09
0.40*0.03
2UBi
1.13*0.07
1.33*0.08
1.44*0.09
1.78*0.11
1.04*0.07
1 .27*0.08
2.68*0.16
2.16*0.13
1.59*0.10
1.11*0.07
1.16*0.07
1 .33*0.08
1.65*0.10
0.43*0.04
0.30*0.03
0.68*0.05
2.27*0.14
1.43*0.09
0.37*0.03
J"U
0181*0.022
0.223*0.022
0.241*0.023
0.319*0.028
0.218*0.025
0.244*0.024
0.398*0.031
0.347*0:030
0.250*0.024
0.219*0.022
0.188*0.019
ND
0.238*0.026
ND
0.066*0.015
0.192*0.021
0.222*0.025
0.195*0.020
ND
'"Pa
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
I13Ra
ND
ND
ND
0.260*0.070
ND
ND
0.114*0.068
0.162*0.070
0.154*0.055
ND
ND
ND
ND
ND
ND
ND
0.264*0.067
ND
ND
Note: ND indicates radionuclide was not detected by gamma spectrometry.

-------
                                                      TABLE A.6
         Public Water Treatment Outfall: Thorium Chain and Other Gamma-Emitting Radionuclides in Sediment
SAMPLE ID
NPTU 028-02-S
NPTU028-S
NARCL ID
99.02417
99.02409
Activity (pCi/g-dry  2O counting error)
"'Ra
l.260.08
0.800.06
"4Ra
0.970.26
0.740.26
'"Pb
l.350.08
0.940.06
211Bi
I.35O.I6
0.92O.I5
IQTI
0.43*0.03
0.31 0.02
'Be
ND
0.21 0.09
"Co
ND
ND
'Cs
ND
0.01 0.01
40K
7.81 0.49
5.520.38
1)1,
ND
ND
Nolf. ND indicates radionuclide was not detected by gamma spectrometry.
                                                     TABLE A.7
       Public Water Treatment Outfall: Uranium and Actinium Chain Gamma-Emitting Radionuclides in Sediment
SAMPLE ID
NPTU 028-02-S
NPTU028-S
NAREL ID
99.02417
99.024W
Activity (pCi/g-dry  2O counting error)
1MTh
2.32*0.26
0.500.20
lM-Pa
2.27*I.JI
ND
"*Ra
4.19*0.36
!.920.27
"4Pb
1.99*0.12
0.83*0.05
1UBI
1.79*0.11
0.76*0.05
"JU
0.25*0.022
0.12*0.016
"'Pa
ND
ND
MJRa
ND
0.06*0.047
Nolf. ND indicates radionuclide was not detected by gamma spectrometry.

-------
                                                     TABLE A.8
                  Background: Thorium Chain and Other Gamma-Emitting Radionuclides in Sediment
SAMPLE ID
NPTU031-S-nK
NI'TUOJl-S-HK-nU
NPTU 032-L-BK
NPTU032-L-DU-BK
NAREL ID
99.02374
W.02373
99.02381
99.02382
Activity (pCi/g-dry  2o counting error)
"Ra
0.93*007
0.81*0.06
0.75*0.06
0.70*0.05
'Ra
0.99*020
0.<>9t0.2<>
0.51*0.28
0.76*0.22
i.ipb
1.29*0.08
1.00*0 06
1.00*0.07
0.97*0.06
!"Bi
1.22*0.16
1.01 0.1 4
0.84*0.15
0.93*0.15
IOIT,
0.390.03
0.340.02
0.32*0.02
0.30*0.02
7B
O.lOiO.OR
0.14*0.07
1.38*0.14
1.19*0.11
"Co
<002
<0.02
<0.03
<0.02
UTCs
0.02O.OI
ND
0.20*0.02
0.33*0.02
"K
7.3'J0.48
6.40*0.43
7.58*0.51
7.56*0.49
111 1
ND
ND
ND
ND
Note: ND indicates rodionuclidc was noi delected by gamma spectrometry.
                                                      TABLE A.9
                 Background: Uranium and Actinium Chain Gamma-Emitting Radionuclides in Sediment
SAMPLE ID
NPTU03I-S-BK
NPTU031-S-I1K-DU
NI'TU 032-L-HK
NPTU 032-L-DU-niC
NAREL ID
99.02374
99.02373

-------
                                                   TABLE A.10

                        Thorium Chain and Other Gamma-Emitting Radionuclides in Sediment Cores
SAMPLE ID
NI'TtJ002-C-A
NPTU 002-C-Q
NI'TU 002-C-C
NPTU 002-C-D
NPTU 002-C-E
NPTU 005-C-A
NPTU 005-C-B
NIMTJ 005-C-C
NPTU005-C-D
NPTUOOS-C-A
NPTU 008-C-H
NPTU 008 -C-C
NI'TU 008-C-D
NPTU008-C-E
NPTVJ 024-C-A
NPTU 024-C-B
NPTU 024-C-C
NPTU 024-C-D
NPTU024-C-E
NITU 024-C-OU-A
NP'IU024-C-DU-I
NI'n)024-C-DU-C
Core
Slice
(cm)
0-5
6-10
11-15
16-30
31-52
0-5
6-10
11-15
16-20
0-5
6-10
11-15
16-29
30-43
0-5
6-10
11-15
16-27
28O9
0-5
6-10
11-16
NAREL
ID
W.024<)2
99.02493
99.02494
99.02495
99.024%
99.02488
99.02489
W.02490
99.02491
99.02502
99.02503
09.02504
99.02505 .
99.02506
99.02497
99.02498
99024'W
99.02500
99.02501
'W.024K5
99.02486
99.024 X7
Activity (pCi/g-dry  2o counting error)
1J1Ra
0.
ND
ND
u>
I/I

-------
                                                      TABLE \AQ-Contintied
SAMPLE ID
NPTU 025-C-A
NPTU 025-C-B
NPTU025-C-C
NPTU 025-C-D
NPTU 025-C-02-A
NPTU 025-C-02-B
NPTU 025-C-02-C
NPTU 025-C-A
NPTU 026-C-B
NPTU 026-C-C
Core
Slice
(cm)
0-5
6-10
\\-\S
16-23
0-5
6-10
11-15
0-5
6-10
11-15
NARELID
99.02481
99.02482
99.02483
99.02484
99.02478
99.02479
99.02480
99.02507
99.02508
99.02509
Activity (pCi/g-dry  2o counting error)
"'Ra
1.07*0.12
0.6940.08
0.970.10
0.85*0.07
0.73*0.09
0.720.08
0.730.08
0.60*0.07
0.68*0.07
0.82*0.06
M4Ra
ND
0.530.62
0.53*0.51
0.93*0.41
0.73*0.53
0.82*0.45
ND
0.48*0.41
ND
0.63*0.30
JI1Pb
1.02*0.09
0.70*0.07
0.99*0.08
0.87*0.06
0.83*0.07
0.83*0.07
0.78*0.06
0.75*0.06
0.72*0.06
0.86*0.06
'"Bi
1.30*0.34
0.57*0.28
0.99*0.32
0.61*0.27
0.58*0.35
0.78*0.26
0.94*0.26
0.84*0.23
0.75*0.21
0.86*0.18
1WTI
0.33*0.04
0.23*0.03
0.30*0.03
0.24*0.03
0.23*0.04
0.22*0.03
0.21*0.03
0.24*0.03
0.24*0.03
0.25*0.02
TBe
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
"Co
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
'"Cs
0.17*0.03
0.04*0.02
0.04*0.02
0.05*0.02
ND
ND
ND
ND
ND
ND
40K
8.34*0.75
4.66*0.46
10.80*0.81
6.43*0.50
4.32*0.58
4.83*0.49
ND
3.31*0.38
2.82*0.34
2.12*0.23
ui,
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Note: ND indicates radionuclide was not detected by gamma speclrometry.

-------
                            TABLE A. 11
Uranium and Actinium Chain Gamma-Emitting Radionuclides in Sediment Cores
SAMPLE ID
NPTU002-C-A
Top 5 cm
NPTU 002-C-B
Second 5 cm
NPTU 002-C-C
Third 5 cm
NPTU 002-C-D
Fourth 1 5 cm
NPTU 002-C-B
Bottom 22 cm
NPTU 005-C-A
Top 5 cm
NI'TIJ OOS-C-H
Second 5 cm
NPTU 005-C-C
Third 5 cm
NPTU 005-C-D
Bottom 5 cm
NAREL ID
99.02492
99.02493
99.02494
99.02495
99.024%
99.02488
99.02489
99.02490
99.02491

lwTh
ND
2.64I.3I
3.830.69
2.40*0.61
1.5) 0.39
3.02*0.99
l.830.79
2.2210.81
2.8041.13
Activity (pCi/g-dry  2o counting error)
"Pi
ND
7.98*9.18
ND
ND
ND
3.49*6.47
ND
ND
3.63*7.73
"'Ra
3.773.30
4.0941.66
5.08*1.73
4.18*0.83
3.84*0.66
ND
5.31*1.11
5.42*1.11
4.49*1.44
"4Pb
l.000.30
1.11*0.17
1.41*0.15
1.39*0.11
1 .240.09
1.90*0.16
2.04*0.16
1.95*0.16
1.46*0.16
2HBi
0.86*0.32
1.07*0.17
1.36*0.17
1.21*0.10
1.11*0.09
1.70*0.16
1.70*0.15
1.69*0.15
1.33*0.16
1MU
0.240*0.199
0.256*0.100
ND
ND
0.231*0.040
0.311*0.077
0.325*0.067
0.334*0.067
0.285*0.0X6
131 Pa
ND
ND
ND
ND
ND
ND
ND
ND
ND
"JRa
ND
ND
ND
ND
ND
0.351*0.245
ND
ND
N

-------
                                                  TABLE A.11- Continued
SAMPLE ID
NPTU 008-C-A
Top 5 cm
NP'ITJ OOg-C-B
Second S cm
NPTU 008-C-C
Third 5 cm
NPTU 008 -C-D
Fourth 14cm
NPTUOOS-C-r:
Bottom 1 4 cm
NPTU 024-C-A
Top 5 cm
NPTU024-C-B
Second 5 cm
NPTU 024-C-C
Third 5 cm
NPTU024-T-D
l:uunh 12 cm
NPTU 024-C-E
Bottom 1 2 cm
NARF.L ID
99.02502
09.02 50 1
09.02504
99.02505
09.02506
99.02497
99.02498
99.02499
99.02500
99.02501
Activity (pCi/g-dry  2O eounling error)
lMTh
3.491.38
ND
NO
1.71 0.39
2.92*0.49
I.I90.43
1.10*0.38
064*0.34
0.57*0.23
0540.19
'"Pa
ND
ND
ND
2.40*2.97
ND
ND
ND
ND
1.09*1.26
ND
"*Ra
10.70*2.06
2.591.30
6.021 66
4.I6055
4.13*0.76
3.64*0.56
2.56*0.52
2.77*0.51
2.27*0.31
I.330.29
114Pb
4.50OJ3
1.05*0.13
2.20*0.22
1.34*0.09
I.42O.I2
1.78*0.12
1.37*0.09
1.25*0.09
1.03*0.07
0.64*0.05
'"Bi
4.15*0.32
0.81*0.15
1.91*0.22
1.19*0.09
1.29*0.13
1.57*0.10
1 .22*0.09
1.0410.08
0.98*0.06
0.60*0.04
"!U
0.663*0.124
ND
ND
0.244*0.032
0.251*0.045
0.217*0.033
ND
ND
0.134*0.018
0.083*0.017
"'Pa
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
'"Ra
ND
ND
ND
ND
ND
ND
ND
ND
0.080*0.053
ND
oo

-------
                                                                   TABLE A.11- Continued
SAMPLE ID
NPTU024-C-DU-A
Top 5 cm
NPTU024-C-DU-B
Second 5 cm
NPTU024-C-DU-C
Bottom 6 cm
NPTU 025-C-A
Top 5 cm
NPTU 025-C-B
Second 5 cm
NPTU025-C-C
Third 5 cm
NPTU 025-C-D
Bottom 8 cm
NPTU 025-C-02-A
Top 5 cm
NPTU 025-C-02-B
Second 5 cm
NPTU 025-C-02-C
NPTU 026-C-A
Top 5 cm
NPTU 026-C-B
Seconds cm
NPTU026-C-C
Bottom 6 cm
NAREL ID
99.02485
99.02486
99.02487
99.02481
99.02482
99.02483
99.02484
99.02478
99.02479
99.02480
99.02507
99.02508
99.02509
Activity (pCi/g-dry  2o counting error)
"*Th
ND
1.64*0.49
1.95*0.37
1.210.50
4.520.55
1.63*0.38
4.660.43
3.880.44
3.390.42
3.70*0.44
1.12*0.27
0.87*0.34
2.27*0.27
<*Pa
ND
3.433.65
5.132.54
ND
8.233.11
4.693.32
7.342.49
4.71*3.33
6.21 2.58
5.772.18
2.40*2.35
2.32*2.32
2.201.60
2"Ra
4.33*0.66
4.300.73
4.730.59
4.550.72
8.60*0.81
5.710.62
10.500.79
7.840.73
4.48*0.59
5.19*0.68
2.95*0.46
2.860.46
4.340.42
2,4pb
2.300.15
1.620.13
2.050.13
1.630.12
6.450.38
2.18*0.14
4.390.26
3.290.21
3.860.23
4.39*0.26
1.59*0.10
1.570.10
2.160.13
IUBi
1.980.14
1.510.14
1.850.13
1.500.12
5.820.35
2.000.14
3.940.24
3.090.20
3.600.22
3.880.24
1.440.10
1.44*0.10
1.950.12
"5U
ND
0.250.04
0.290.04
0.280.04
0.440.05
0.350.04
0.610.05
0.470.04
0.300.04
0.32*0.04
0.18*0.03
0.170.03
0.260.03
"'Pa
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND

2"Ra
ND
ND
0.15*0.13
ND
0.38*0.11
ND
0.31*0.11
ND
0.28*0.11
ND
0.12*0.08
ND
ND
u>
            Note: ND indicates radionuclide was not detected by gamma spectrometry.

-------
                                                       TABLE A.12
                            Thorium Chain and Other Gamma-Emitting Radionuclides in Biota
SAMPLE ID
NPTU003-BO
NPTU015-BMG
NPTU016-BMG
NPTU016-BMG-DU
NPTU017-BMG
NPTU -29-BMG
NARELID
99.02359
99.02342
99.02343
99.02361
99.02341
99.02360
Activity (pCi/g-wet  2o counting error)
"Ra
0.060.01
ND
ND
ND
ND
ND
'"Ra
0.070.05
ND
ND
ND
ND
ND
2"Pb
0.060.01
0.02O.OI
0.01 0.01
O.OliO.Ol
0.020.01
0.01 0.01
!1IBi
0.050.02
ND
ND
ND
ND
ND
"Tl
0.02*0.00
0.00*0.00
0.00*0.00
0.000.00
0.01 0.00
ND
7Be
0.050.0t
0.480.04
0.47*0.04
0.34*0.04
0.34*0.03
0.15*0.03
"Co
ND
ND
ND
ND
ND
ND
137Cs
ND
0.01 0.00
ND
ND
0.000.00
ND
K
0.88*0.06
4.180.25
3.740.24
3.800.24
3.170.20
3.580.23
131,
ND
ND
ND
ND
ND
ND
Note: ND indicates radionuclide was not detected by gamma spectrometry.
                                                       TABLE A.13
                          Uranium and Actinium Chain Gamma-Emitting Radionuclides in Biota
SAMPLE ID
NPTU 003-BO
NPTU015-BMG
NPTUOI6-BMG
NPTUOI6-BMG-DU
NPTU017-BMG
NPTU-29-BMG
NAREL ID
99.02359
99.02342
99.02343
99.02361
99.02341
99.02360
Activity (pCi/g-wet  2o counting error)
Th
ND
ND
ND
ND
ND
ND
U4Mpa
ND
ND
ND
ND
ND
ND
R
0.170.06
ND
ND
ND
ND
ND
2"Pb
0.06*0.01
ND
ND
ND
ND
ND
2UBi
0.070.01
ND
ND
ND
ND
ND
USJJ
ND
ND
ND
ND
ND
ND
'Pa
ND
ND
ND
ND
ND
ND
2"Ra
ND
ND
ND
ND
ND
ND
Note: ND indicates radionuclide was not detected by gamma spectrometry.

-------
                                                     TABLE A.I4
                    Background: Thorium Chain and Other Gamma-Emitting Radionuclides in Biota
SAMPLE ID
NI'TU 032-BMG-BK
NPTU032-BMG-DU-BK
NAREL ID
99.02406
99.02362
Activity (pCi/g-wet  2o counting error)
"'Ra
ND
ND
1MRa
ND
ND
1IJPb
ND
0.01O.OI
"JBi
ND
ND
1MTI
ND
ND
'Be
0.31*0.04
0.240.04
"Co
ND
ND
'"Cs
ND
ND
"K
3.13*0.20
3.46*0.22
iiij
ND
ND
Note: ND indicates radionuclidc was not detected by gamma spcctrometry.
                                                  TABLE A. 15
                Background: Uranium and Actinium Chain Gamma-Emitting Radionuclides in Biota
SAMPLE ID
NPTU 032-BMG-BK
NPTU 032-BMG-DU-BK
NAREL ID
99.02406
99.02362
Activity (pCI/g-wct  2o counting error)
>MTh
ND
ND
IMMpa
ND
ND
l"Ra
ND
ND
"4Pb
ND
ND
"4Bi
ND
ND
J"U
ND
ND
"'Pa
ND
ND
"JRa
ND
ND
Note.' ND indicates rattiouurlide was not deleftfd by gamma ipectrometiy.

-------
                TABLE A. 16
              Tritium in Water
SAMPLE ID
NPTUOOI-W
NPTU 007-W
NPTUOI1-W
NPTU021-D
NPTU 024-W
NPTU 024-W-DU
NPTU 030-W
NAREL ID
99.02364
99.02368
99.02372
99.02420
99.02413
99.02416
99.02377
Activity (pCi/L  2O counting error)
8985
15487
8485
194*89
120S6
5783
7t84
               TABLE A.17
Public Water Treatment Outfall: Tritium in Water
SAMPLE ID
NPTU 028-W
NPTU 028-02-W
NPTU 028-03-W
NAREL ID
99.02415
99.02418
99.02419
Activity (pCi/L  2O counting error)
IOI85
12287
8785
               TABLE A. 18
        Background: Tritium in Water
SAMPLE ID
NPTU 022 -D-BK
NPTU 022-D-DU-BK
NPTU031-W-BK
NPTU031-W-BK-DU
NAREL ID
99.02379
99.02380
99.02375
99.02376
Activity (pCi/L  20 counting error)
6284
2I289
I0985
15187
                    42

-------
                          TABLE A.19
              Gross Alpha and Beta Activities in Water
SAMPLE ID
NPTU001-W
NPTU 007-W
NPTU011-W
NPTU02I-D
NPTU 024- W
NPTU 024-W-DU
NPTU 030-W
NAREL ID
99.02364
99.02368
99.02372
99.02420
99.02413
99.02416
99.02377
Activity (pCi/L  20 counting error)
Gross Alpha
-16.39*13.34
9.1825.88
-19.9544.10
-0.290.43
-3.94*20.07
-21.30*42.60
-10.06*13.38
Gross Beta
82.20*76.48
1.64*63.54
4.43*92.66
2.66*1.26
50.53*68.89
126.82103.87
48.06*67.84
                          TABLE A.20
Public Water Treatment Outfall: Gross Alpha and Beta Activities in Water
SAMPLE ID
NPTU 028-W
NPTU 028-02-W
NPTU 028-03-W
NAREL ID
99.02415
99.02418
99.02419
Activity (pCi/L  2O counting error)
Gross Alpha
6.04*29.36
-7.28*43.67
0.00*10.57
Gross Beta
57.07*76.30
190.46*107.22
34.76*17.22
                          TABLE A.21
        Background: Gross Alpha and Beta Activities in Water
SAMPLE ID
NPTU 022-D-BK
NPTU 022-D-DU-BK.
NPTU031-W-BK
NPTU03I-W-BK-DU
NAREL ID
99.02379
99.02380
99.02375
99.02376
Activity (pCi/L  20 counting error)
Gross Alpha
0.38*0.60
-0.02*0.35
-7.41*18.43
2.43*24.62
Gross Beta
2.41*1.25
2.21*1.07
-20.96*66.95
-16.21*67.29
                               43

-------
             TABLE A.22
Gross Alpha and Beta Activities in Sediment
SAMPLE ID
NPTUOOI-S
NPTU 002-S
NPTU 004-S
NPTU 005-S
NPTU 006-S
NPTU 007-S
NPTU 008-S
NPTU 009-S
NPTU010-S
NPTU01I-S
NPTU 024-S
NPTU 024-S-DU
NPTUOI5-L
NPTU016-L
NPTUOI6-L-DU
NPTUOI7-L
NPTU025-L
NPTU 026-L
NPTU029-L
NAREL 10
99.02363
99.02411
99.02365
99.02410
99.02366
99.02367
99.02414
99.02369
99.02370
99.02371
99.02408
99.02412
99.02346
99.02345
99.02344
99.02347
99.02348
99.02407
99.02378
Activity (pCi/g-dry2o counting error)
Gross Alpha
9.76*3.91
11.59*4.42
1 6.055.I6
11.58*4.23
14.704.76
12.624.60
15.10*4.92
17.105.13
8.183.59
12.27*4.35
9.613.96
6.063.52
I0.004.21
3.79*3.10
2.93*2.51
11.104.30
16.71 4.99
5.33*3.25
5.58*3.49
Gross Beta
20.28*3.96
17.74*3.89
22.89*4.30
20.92*3.89
21.28*4.00
19.68*3.91
26.27*4.31
26.65*4.31
17.26*3.81
24.15*4.22
14.33*3.54
15.35*3.57
23.02*4.15
9.57*3.23
7.55*3.02
16.60*4.30
26.74*4.22
17.42*3.73
11.26*3.38
                44

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                           TABLE A.23
Public Water Treatment Outfal: Gross Alpha and Beta Activities in Sediment
SAMPLE ID
NPTU 028-02-S
NPTU 028-S
NAREL ID
99.02417
99.02409
Activity (pCi/g-dry2o counting error)
Gross Alpha
7.47*3.95
7.85*3.49
Gross Beta
I9.273.87
10.42*3.28
                            TABLE A.24
        Background: Gross Alpha and Beta Activities in Sediment
SAMPLE ID
NPTU03I-S-BK
NPTU03I-S-BK-DU
NPTU 032-L-BK
NPTU 032-L-DU-BK
NAREL ID
99.02374
99.02373
99.023S1
99.02382
Activity (pCl/g-dry2o counting error)
Gross Alpha
10.27*4.14
8.253.79
12.26*4.60
9.79*3.98
Gross Beta
19.05*4.03
13.243.S3
20.90*4.10
23.124.I3
                                45

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                TABLE A.25
Gross Alpha and Beta Activities in Sediment Cores
SAMPLE ID
NPTU002-C-A
Top 5 cm
NPTU 002-C-B
Second 5 cm
NPTU002-C-C
Third 5 em
NPTU 002-C-D
Fourth 1 5 cm
NPTU002-C-E
Bottom 22 cm
NPTU005-C-A
Top 5 cm
NPTU005-C-B
Second 5 cm
NPTUOOJ-C-C
Third 5 cm
NPTU005-C-D
Bottom 5 cm
NPTU008-C-A
Top 5 cm
NPTU OOS-C-B
Second 5 cm
NPTU008-C-C
Third 5 cm
NPTU008-C-D
Fourth 14cm
NPTU008-C-E
Bottom 1 4 cm
NPTU 024-C-A
Top 5 cm
NPTU 024-C-B
Second 5 cm
NPTU 024-C-C
Third 5 cm
NPTU 024-C-D
Fourth 12cm
NPTU 024-C-E
Doiiom 1 2 cm
NAREL ID
99.02492
99.02493
99.02494
99.02495
99.02496
99.02488
99.02489
99.02490
99.02491
99.02502
99.02503
99.02504
99.02505
99.02506
99.02497
99.02498
99.02499
99.02500
99.02501
Activity (pCi/g-dry2(J counting error)
Gross Alpha
10.85*424
8.764.00
12.54*4.36
1 1.46*4.13
8.273.88
7.7I3.65
12.424.5S
H.374.26
12.054.45
27.75*6.57
11.664.33
13.20*4.56
8.94*3.94
16.23*4.97
14.62*4.85
I4.434.77
2.28*2.36
16.33*5.02
2.60*2.45
Cross Beta
19.04*3.86
25.47*4.21
20.133.80
21.50*3.97
26.054.55
25.274.26
25.50*4.35
23.0U4.02
24.18*4.30
41.74*5.14
18.31*3.74
22.73*3.96
I9.6l3.81
23.49*3.98
24.01*4.13
21.32*4.01
10.98*3.20
24.56*4.13
1I.3?3.I2
                    46

-------
TABLE A.25 - Continued
SAMPLE ID
NPTU 024-C-DU-A
Top 5 cm
NPTU 024-C-DU-B
Second 5 cm
NPTU 024-C-DU-C
Bottom 6 cm
NPTU 025-C-A
Top 5 cm
NPTU 025-C-B
Second 5 cm
NPTU 025-C-C
Third 5 cm
NPTU 025-C-D
Bottom 8 cm
NPTU 025-C-02-A
Top 5 cm
NPTU 025-C-02-B
Second 5 cm
NPTU 025-C-02-C
Bottom 5 cm
NPTU 026-C-A
Top 5 cm
NPTU 026-C-B
Second 5 cm
NPTU 026-C-C
Bottom 6 cm
NAREL ID
99.02485
99.02486
99.02487
99.02481
99.02482
99.02483
99.02484
99.02478
99.02479
99.02480
99.02507
99.02508
99.02509
Activity (pCi/g-dry2o counting error)
Gross Alpha
15.654.95
13.804.83
10.36*4.18
12.22*4.41
25.47*6.31
16.665.06
16.73*5.09
19.68*5.51
25.516.19
17.72*5.38
13.61*4.51
9.92*3.92
5.472.96
Gross Beta
I5.6U3.63
20.1U3.98
22.96*4.04
26.46*4.26
39.97*5.08
28.564.34
29.264.46
26.35*4.37
26.33*4.34
28.17*4.46
23.52*4.09
19.89*3.74
20.43*3.78
         47

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                  TABLE A.26
      Gross Alpha and Beta Activities in Biota
SAMPLE ID
NPTU 003-BO
NPTUOIS-BMG
NPTUOI6-BMO
NPTU016-BMG-DU
NPTUOI7-BMG
NPTU 029-BMG
NAREL ID
99.02359
99.02342
99.02343
99.02361
99.02341
99.02360
Activity (pCi/g-dry  2O counting error)
Gross Alpha
0.682.0
0.980.49
0.98O.S4
0.780.5I
0.55*0.40
0.490.36
Gross Beta
0.802.3
20.81.2
20.51.2
30.3*1.6
16.91.1
18. 11.0
                  TABLE A.27
Background: Gross Alpha and Beta Activities in Biota
SAMPLE ID
NPTU 032-BMG-BK
NPTU 032-BMG-DU-BK
NAREL ID
99.02406
99.02362
Activity (pCi/g-dry  2O counting error)
Gross Alpha
0.380.26
0.350.25
Gross Beta
18.60.97
16.1 0.84
                      48

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