United States Office of EPA 520/5-83-022
Environmental Protection Radiation Programs September 1983
Agency Washington, DC 20460
Radiation
xvEPA
Radiological Survey of
Ingalls Shipbuilding
Division, Pascagoula,
Mississippi, and Environs
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EPA 520/5-83-022
RADIOLOGICAL SURVEY
OF
INGALLS SHIPBUILDING DIVISION, PASCAGOULA, MISSISSIPPI,
AND ENVIRONS
T. W. Fowler
S. T. Windham
R. S. Callis
C. R. Phillips
Eastern Environmental Radiation Facility
P. 0. Box 3009
Montgomery, Alabama 36193
August 1982.
U. S. Environmental Protection Agency
Office of Radiation Programs
401 M Street, SW
Washington, DC 20460
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TABLE OF CONTENTS
List of Illustrations iii
Preface v
Acknowledgements vi
Introduction 1
Characteristics of Ingalls Shipbuilding Site 2
Survey and Analytical Methods ........ 8
Results and Discussion 13
Conclusions 39
References 41
Appendix 1 Sediment Sample Analysis Results 42
Appendix 2 Core Sample Analysis Results 51
Appendix 3 Sampling Locations in SORB 64
11
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LIST OF ILLUSTRATIONS
FIGURES page
1 Map of General Area 3
2 Map of Survey Locations Off site 4
3 Map of Sediment, Probe, and Water Sample Sites 5
4 Map of Core Sample Locations 6
5 Map of Shoreline Gamma Measurement Sites 7
6 East End of SORB: First Floor Paint and Concrete Samples . . 64
7 West End of SORB: First Floor Paint and Concrete Samples . . 65
8 Center of SORB: First Floor Paint and Concrete Samples ... 66
9 East End of SORB: Second Floor Paint and Concrete Samples . 67
10 Center of SORB: Second Floor Paint and Concrete Samples . . 68
11 West End of SORB: Second Floor Paint and Concrete Samples . 69
TABL ES
1 Results of Aquatic Life Sample Gamma Analyses 15
2 Results of Water Sample Analyses 16
3 Gamma Shoreline Measurements 17
4 Paint Samples with Detectable Gamma Activities 21
5 Gamma Activity in Concrete Samples 24
6 Surface Contamination Sampling Sites for Beta Analyses ... 26
7 Surface Contamination Sampling Sites for Tritium Analyses . . 27
8 Air Sampling Sites 28
9 Gamma Activity in Soil Samples 29
m
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LIST OF ILLUSTRATIONS—continued
page
10 Results of Miscellaneous Sample Analyses 33
11 Results of Asphalt Sample Gamma Analyses 34
12 External Gamma Radiation Measurements Inside SORB 35
13 Travel Routes for Power Units 37
14 Gamma Measurements in Other Shipyard Locations 38
iv
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PREFACE
The Eastern Environmental Radiation Facility (EERF) helps solve
problems defined by the Office of Radiation Programs. The Facility
provides capability for evaluating radiation sources through environmental
studies, nationwide surveillance, and laboratory analysis. The EERF also
provides special analytical support for Environmental Protection Agency
Regional Offices and other federal government agencies as requested as
well as technical assistance to the radiological health programs of state
and local health departments.
This report presents results of the survey conducted by EERF personnel
to assess environmental radioactivity remaining from operations of
nuclear-powered vessels at Ingalls Shipyard, Pascagoula, Mississippi.
Since Ingalls shipyard will no longer build or service nuclear powered
ships and has completed the decommissioning of the nuclear support
facilities, an additional purpose of the survey was to determine if there
is any remaining radioactivity from previous operations which could
contribute to significant population exposure.
Readers of our reports are encouraged to bring comments, omissions or
errors to our attention.
Charles R. Porter, Director
Eastern Environmental Radiation Facility
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ACKNOWLEDGMENTS
The authors gratefully acknowledge the U.S. Naval Sea System Command
staff and Ingalls staff that assisted us in identifying areas which were
previously used for radioactive work so tht EERF could select locations
for collecting samples and making measurements. We also thank Eddie
Fuente and Greg Dempsey of the Mississippi State Board of Health for
participating in the survey.
VI
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INTRODUCTION
Since 1963, the Eastern Environmental Radiation Facility (EERF), U.S.
Environmental Protection Agency (USEPA), in cooperation with the U.S.
Naval Sea Systems Command (NAVSEA) has conducted several surveys of ports
serving nuclear powered vessels on the Atlantic, Gulf, and Pacific coasts,
including Pearl Harbor (Ca77, Ca79). These surveys assessed whether
nuclear powered vessel operations, including berthing, repair, and
servicing, have created elevated levels of environmental radioactivity.
The surveys emphasized sampling those areas and pathways that could result
in significant exposure to the public.
Ingalls Shipbuilding Division (ISO), Pascagoula, Mississippi, was
surveyed by EERF personnel in December 1981. This was the first survey of
this facility by the EPA in its series of harbor surveys. The survey was
requested by NAVSEA in conjunction with Ingalls1 plan to decommission the
ISO, which has discontinued work on nuclear powered vessels. Two main
areas were surveyed: the harbor and the Submarine Overhaul and Refueling
Building (SORB). Representatives from the Mississippi State Board of
Health participated in the survey.
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CHARACTERISTICS OF INGALLS SHIPBUILDING SITE (Bu75)
Ingalls Shipbuilding consists of two major facilities, one on the east
and one on the west bank of the Pascagoula River where it meets the
Mississippi Sound (see Fig. 1). The east bank shipyard, which has been
used to construct, overhaul, and refuel nuclear submarines, is bordered on
the north and east by the city of Pascagoula. The west bank facilities
were not utilized in nuclear operations at Ingalls, and therefore, were
not included in this survey -
The Pascagoula River channel extends into the Mississippi Sound and
permits the area of the river between the shipbuilding facilities to be
used by commercial shipping interests for reaching the Port of Pascagoula
located north of ISO. The channel is 350 feet wide and 9.3 nautical miles
long. It is maintained at a depth of thirty-eight feet at mean low tide
by dredging. The river bottom is comprised primarily of sediment.
Most of the water is accessible to the public by boat with the
exception of certain areas which are restricted for security reasons.
There is commercial fishing in the area.
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Mississippi
Sound
Fig . 1 General Area
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Mississippi
Sound
Fig. 2 Survey Locations Offsite for Background Measurements
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Fig. 3 Sediment Sample, Water Sample and Probe Measurement
Sites
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Fig. 4 Sediment Core Sample Locations
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Ingafts
West.
. Yard
Pascagoula
River
Fig. 5 Shoreline Gamma Measurement
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SURVEY AND ANALYTICAL METHODS
Harbor Survey
The sampling locations covered a large area as shown in Figs. 2-5.
Concentrated sampling was performed in close proximity of the ISO east
bank facilities and primarily in locations where, based on shipyard
operations, radioactivity most likely could be found (Fig. 3).
Discussions with representatives of NAVSEA and local shipyard personnel
helped determine our sampling locations.
An underwater scintillation probe utilizing a 10-centimeter by
10-centimeter sodium iodide detector was used with a 1024 channel pulse
height analyzer to help locate areas of radioactivity. A 10-minute
background spectrum was taken at the mouth of Mary Walker Bayou (site B-l,
Fig. 2) for subtracting from counts taken at other sampling locations.
All probe counts were made for 10 minutes. Locations of probe
measurements are shown in Fig. 3. The underwater scintillation probe has
been useful in past surveys to select areas for dredge sampling of bottom
sediment. Sediment samples, identified in Table 2, were taken at locations
where radioactivity seemed most probable based on shipyard operations.
Extensive sampling was performed at all dry docks, berthing areas, repair
facilities, and at the radioactive liquid effluent discharge point which
had been deactivated in 1972. A standard Peterson dredge was used to
sample approximately the top 10 centimeters of sediment. The samples were
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dried at 110°C, ground to a fine powder, placed in a 400 cm "cottage
cheese container," and counted on a Ge(Li) or intrinsic germanium detector.
Sediment core samples in past surveys have been useful in defining the
vertical distribution of radioactivity. Also, radioactive materials from
past operations which were subsequently covered with sediment might be
observed in the deep core samples. These samples were taken by divers at
locations noted in Fig. 4. A 2.4-centimeter diameter by 61-centimeter
tube was used for sample collection. The tube was pushed into the bottom
as far as possible and then the ends were capped. When the core samples
arrived at the laboratory, they were frozen and cut into 5.1 centimeter
sections except for the first section which was sometimes 7.6 or 8.9
centimeters. The core sections were counted in the wet state on a Ge(Li)
or intrinsic germanium detector.
One gallon water samples were collected at the sites noted in Fig. 3
and analyzed for gamma emitters.
Aquatic life samples, consisting of oysters, assorted small fish,
shrimp, and crabs were collected where available in the area and analyzed
for gamma-emitting radionuclides. Sample preparation for counting
2
consisted of cutting and packing the material in 400 cm "cottage cheese
containers."
Direct gamma radiation exposure measurements were made at the
locations noted in Fig. 5 using a pressurized ionization chamber (PIC)
(De72). Those areas accessible to the public were of particular interest.
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Survey of Submarine Overhaul and Refueling Building (SORB)
The building survey evaluated the extent of contamination of the
Submarine Overhaul and Refueling Building (SORB). This building formerly
housed the support systems required for overhauling and refueling nuclear
powered submarines. The SORB has been surveyed and decontaminated by
Ingalls in anticipation of converting it for non-nuclear activities. The
Ingalls survey began in 1980 and employed a survey work force of about 100
people. The entire building was laid out in a grid system and surveys
were made to ensure that walls, ceilings, floors, and pavement are below
2
operational limits: < 450 pCi/100 cm for surfaces and < 30 pCi/gm
(Co-60 equivalent) for bulk material (earth, ground coverings, paint or
building materials). All contaminated equipment, piping, and ventilation
systems were removed and shipped offsite as radioactive waste. Therefore,
the EERF survey was mainly done in empty, stripped-down rooms within the
SORB which were extensively identified with grid numbers.
Gamma exposure levels were measured at appropriate locations inside
and adjacent to the SORB with scintillation survey meters (Ludlum Model
12S) and pressurized ionization chambers (Reuter-Stokes Environmental
Monitor Model RSS-111). In areas where there was a potential for alpha
contamination, an alpha survey was done with an Eberline PAC-1SA portable
alpha counter-
Air samples were collected to determine the presence of airborne gamma
and beta emitters, and a mositure sample was collected to determine if
10
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tritium was present. A high volume air sampler with an MSA dust filter
was used to collect particulate gamma emitters, and a low volume air pump
was used with a drierite column to collect moisture in the air for tritium
analysis.
Representatives of NAVSEA and shipyard personnel indicated where they
had found contamination in the SORB and also pointed out areas that had a
high potential for contamination based on past shipyard operations. Paint
and concrete samples were taken from these areas and the nuclide
composition of any contaminated areas were determined with a Ge(Li) or
intrinsic germanium detector. The sample material obtained from the walls
of the rooms was mainly of two specific types: 3.5 gm paint samples and
50 gm concrete samples. Five-hundred-gram soil samples were taken under
the SORB and at other possibly contaminated locations. Fifty gram asphalt
samples were also analyzed. Smear samples were taken to identify any
removable surface contamination. Some of the smear samples, particularly
those taken in remaining exhaust system ducts, were taken using millipore
HAWP 4700 filter paper. This filter material is clear when inserted into
10 ml of organic based liquid scintillation solution for counting. Counts
from tritium were recorded on a liquid scintillation counter to determine
tritium surface contamination.
It was recognized that gamma measurements could be influenced by
materials not associated with nuclear activities at the shipyard. One
such material identified was a sand used for sand blast cleaning of
11
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metals. The material, in local jargon, was referred to as "Black Beauty"
due to its dark color. This high natural radioactivity material was well
distributed throughout the shipyard. A radium, uranium, and thorium
analysis was done on the material to document the content of natural
radionuclides.
12
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RESULTS AND DISCUSSION
Harbor Survey
All samples were analyzed for gamma -emitting isotopes, particularly
Co-60, a radioi sotope resulting from nuclear operations that has been
measured in past surveys. In addition, air samples were analyzed for beta
acti vi ty -
Since there are commercial and sport fishing in the area, aquatic life
samples were collected in the publicly accessible waters. No
4.D ???
radioactivity (other than natural K and Th) above minimum
detectable levels was found in any of the aquatic life samples other than
a trace amount of Cs-137 (0.02 pCi/gm _+ 65%) attributed to fallout.
Results of the aquatic life sample gamma analyses are shown in Table 1.
The sediment sampling was the most extensive, since recent releases of
radioactivity will usually be detectable in the sediment. Samples were
collected at 35 locations (Fig. 3) and only a trace amount of Co-60
(0.013 pCi/gm +_ 45%) was detected at Site 31. Except for the Co-60
measured at this one sampling site, the only radionuclides detected were
those attributed to fallout and those which are naturally occurring as
shown by the analyses of the background sample (Site B-l). Reported
values for U-238 are attributed to natural radioactivity. Sediment
analyses data are reported in Appendix 1.
13
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Core samples were collected at nine locations (see Fig. 4) to
determine the vertical distribution of radioactivity in the sediment. The
only detectable radionuclides were naturally occurring and those which are
attributed to fallout. Results of core sample analyses are shown in
Appendix 2.
Water samples were collected at seven sites (see Figs. 2 and 3) and
analyzed for gamma emitters. All radionuclides detected were naturally
occurring. Results of water sample analyses are shown in Table 2.
Gamma shoreline measurements were made using a Reuter-Stokes RSS-111
PIC at the locations indicated in Fig. 5. Gamma exposure rates ranged
from 5.0 uR/hr to 9.4 uR/hr with an average of 6.5 uR/hr (see Table 3).
Some of the "Black Beauty" sand blasting material was obvious on the
ground at locations G4, G5, and G6 and contributed to the slightly
elevated gamma exposure rates at these locations. These sites not
excluded, the average was in the range of normal background for other Gulf
Coast towns, for example, Crystal River, Florida, 5.9
uR/hr, Venice, Florida, 6.6 uR/hr, Port Richey, Florida, 7.7 uR/hr, and
Inglis, Florida, 6.2 uR/hr (Le68).
14
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Table 1
Results of Aquatic Life Sample Gamma Analyses
Sample Type
Oysters (background sample)
Oysters
Assorted small fish, shrimp
Assorted small fish
Crabs
Collection1 Radi
Location
Pascagoula River-N
of U.S. 90 Bridge
Pier No. 4
Pascagoula River-N
of U.S. 90 Bridge
Pascagoula River-N
of U.S. 90 Bridge
SW of Dock No. 4
onuclide
40K
40K
40K
40K
40, ,
137CS
232Th
Specific Gamma
Activity (pCi'/gm
wet weight)
1.6 + 18%
1.8 + 11%
2.9 + 10%
2.5 + 11%
1.1 + 50%
0.02 + 65%
0.12 + 92%
^Site locations are approximate, since these are aquatic life samples
collected underwater.
15
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Table 2
Results of Water Sample Analyses
Location1 Radionuclide2 Activity (pCi/1)
Site B-l 214Pb 38 + 62%
214Bi 54^43%
Si te 4 40K 200 + 53%
Site 13 40K 180 + 80%
214Pb 42 +_ 53%
214Bi 44 + 52%
Site 18 H< 160 +_ 89%
214Pb 33 + 69%
214Bi 31 + 70%
dfi
Si te 22 HUK 240 + 48%
Si te 27 ^UK 1 70 ^ 85%
Site 32 NDA3
^Locations (sites) shown in Figs. 2 and 3.
2The only radionuclides with detectable activity in the sample are
those listed in Table 2. All are naturally occurring members of the
uranium and thorium decay series plus K-40.
3No detectable activity (NDA).
16
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Table 3
Gamma Shoreline Measurements
PIC Data
Location
Gl
G2
G3
G4
G5
G6
G7
G8
G9
G10
Gil
G12
G13
G14
G15
G16
G17
Exposure Rate (uR/hr)
5.1
7.6
5.2
8.6
9.0
9.4
6.5
7.0
8.0
5.5
5.2
7.0
6.0
5.5
5.5
5.0
5.0
^Locations (sites) shown in Fig. 5.
17
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Survey of Submarine Overhaul and Refueling Building (SORB) and
Miscellaneous Areas
Extensive samples of surface materials were taken to evaluate the
extent of the contamination of the SORB. A gamma analysis was done on
paint samples at 92 sites and concrete samples at 12 sites identified in
Appendix 3. Paint samples with detectable activity are shown in Table 4.
Residual Co-60 fixed contamination was found on painted surfaces at
several sites, but all levels were well below the NAVSEA limit of 30
pCi/gram (Co-60 equivalent) for bulk material (earth, ground covering,
paint, or building materials). The highest Co-60 level measured in paint
was 4 pCi/grn. The added exposure to personnel from this residual
contamination would be insignificant to individuals who may work in a room
containing Co-60 at this level. For example, if an individual ingested 50
grams of paint containing Co-60 at a concentration of 4 pCi/gm, the dose
equivalent commitment to the lower large intestine wall would only be
0.008 mrem. Dose equivalent commitments to other target organs would be
smaller. The highest paint sample contained 14 pCi of Co-60 (4 pCi/gm x
e\
3.5 gms). If the 14 picocuries of Co-60 were spread over a 100 cm
surface area, an individual would receive about 0.07 mrem/yr external
exposure if he spent 40 hours per week every week of the year adjacent to
this surface. For an individual to receive this exposure, surrounding
surfaces would also have to be contaminated at the 0.14 pCi/cm2 level.
Actual exposures would be much less to individuals spending only a small
fraction of their time in areas with residual Co-60 contamination.
18
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A sample of paint from room 114 contained a trace amount of Cr-51
(1.6 pCi/g + 86%). Due to the short half-life of Cr-51, it is not
credible that this activity remained from nuclear operations conducted in
the rooms. The activity reported is very near background and probably
resulted from inaccuracies in the spectrum analysis program used.
Concrete samples were taken at 12 sites (identified in Appendix 3) and
analyzed for gamma emitters. Except for a small amount of Co-60 found in
rooms 138 and 223, radionuclides detected v/ere naturally occurring at
ambient levels. Results of the concrete sample gamma analyses are shown
in Table 5.
Forty-three smear samples v/ere taken and counted with a low background
beta counter to check for removable beta surface contamination (see Table
6). Eight additional smears were taken using millipore HAWP 4700 filter
paper and counted with a liquid scintillation counter to check for
removable tritium surface contamination (see Table 7). No removable
surface contamination was detected wi th the smears. Also, a survey was
made in several of the rooms with a portable alpha survey meter, and no
alpha contamination was found during this survey.
Air samples were collected at several locations using a 4-inch MSA
dust filter. The volume of air sampled was approximately 1800 m . No
detectable gamma activity above natural background was observed on any of
the filters. The sampling sites are listed in Table 8 and are shown in
Appendix 3. No airborne moisture samples collected on drierite columns
contained detectable tritium.
19
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Soil samples were collected at several locations under the SORB and
other shipyard sites. Activity found in the soil was attributed to
fallout, naturally occuring radionuclides, and trace amounts of Co-60 (see
Table 9).
Samples v/ere collected from the SORB wall insulation and from the
abrasive (Black Beauty) used in sand blasting. Only natural radionuclides
were found in these materials (see Table 10).
Asphalt samples were taken at three locations because of positive
readings on the survey instruments. However, results indicated that the
readings were due to natural radioactivity (see Table 11).
Gamma radiation measurements were made at several locations using a
pressurized ionization chamber. Measurements from the SORB (Table 12),
power unit travel routes (Table 13), and other miscellaneous shipyard
areas (Table 14) were all in the range of normal background for that area.
20
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Table 4
Paint Samples with Detectable Gamma Activities
Location
Rm 106, grid F-8 (Site 1)
Rm 109, grid F-27 (Site 2)
Rm 111, grid F-8 (Site 3)
Rm 114, grid F-7 (under
calibrator rail) (Site 4)
Rm 115, grid F-26 (Site 5)
Rm 115, grid SW-13 (Site 6W)
^m 118, grid F-39 (Site 7)
Rm 119, grid F-13 (Site 8)
Rm 119, grid F-19 (Site 9)
Rm 131, grid F-25 (Site 10)
Rm 133, grid F-27 (Site 11)
Radionuclide
60Co
58Co
60Co
60Co
60Co
51 Cr
Co
60Co
40K
60rn
Co
60Co
60Co
fin
bUCo
137Cs
60Co
60Co
Acti vi ty
(pCi/gm dry weight)
0.97
0.06
0.43
3.1
4.0
1.6
0.63
0.55
4.5
0.37
1.30
1.30
1.40
0.30
0.42
0.23
+ 31%
+ 73%
+ 62%
+ 18%
+ 14%
+ 86%
+ 50%
+ 56%
+ 84%
+ 74%
+ 34%
+ 34%
+ 26%
+ 75%
+ 86%
+114%
Location identified on drawings in Appendix 3
21
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Table 4—Continued
Paint Samples v/ith Detectable Gamma Activities
Location
Rm
Rm
Rm
Rm
Rm
Rm
Rm
Rm
Rm
Rm
Rm
134, grid
134, grid
137, grid
138, grid
138, grid
139, grid
139, grid
139, grid
140, grid
140, grid
141, grid
F-16 (Site 12)
F-41 (Site 13)
F-18 (Site 14)
F-27 (Site 15)
F-42 (Site 16)
F-226 (Site 17)
F-239 (Site 18)
F-310 (Site 19)
WW-11 (Site 20)
F-8 (Site 21)
F-2 (Site 22)
Radionuclide
60Co
60Co
fin
60Co
60
uu «
Co
137Cs
Co
214Pb
214Bi
60Co
60Co
60Co
60Co
58
•J <->f»_
Co
fin
bUCo
60CO
214Pb
214Bi
Activity
(pCi/gm dry weight)
1.3
4.0
3.5
3.30
0.43
0.40
2.6
2.2
0.42
0.47
0.27
0.75
0.15
0.73
1.5
3.9
4.2
+ 27%
+ 21%
+ 16%
+ 22%
+ 64%
+ 91%
+ 33%
+ 45%
+ 66%
+ 56%
+1 24%
+ 60%
+ 83%
—
+ 40%
+ 39%
+ 32%
+ 34%
22
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Table 4--Continued
Paint Samples with Detectable Gamma Activities
Location Radionuclide , r-/. u*v
(pCi/gm dry weight)
Rm 143, grid F-34 (Site 23) 137Cs 0.15+49%
Rm 143, grid F-76 (Site 24) 60Co 0.96 + 49%
Rm 143, grid F-162 (Site 25) 60Co 1.2 +44%
Rm 207 east, grid F-4 (Site 26) 60Co 0.88 +_ 56%
Rm 223, grid EW-8 (Site 27) 214Pb 1.5 +55%
214Bi 1.8 + 54%
23
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Table 5
Gamma Activity in Concrete Samples
Location Radionuclide
Rm 109, grid F-5 (sump G) (Site 28)
Rm 116, grid F-26 (Site 29)
Rm 129, grid F035 (including
cervice) (Site 30)
Rm 138, grid F-2 (center) (Site 31)
Rm 138, grid F-lll (Site 32)
Rm 138, grid WW-6 (at anchors)
(Site 33)
Rm 139, grid SW-58 (cervice)
(Site 34)
Rm 142, grid F-2 (adjacent to area
decontaminated by concrete removal)
(Site 35)
Rm 215, grid F-26 (Site 36)
40K
40K
40,
40,
214Pb
214Bi
232Th
60Co
40,
214Pb
214Bi
232Th
214Pb
214Bi
232Th
40,
40K
Activity
(pCi/gm dry weight)
0.80
1.00
0.48
0.56
0.12
0.14
0.26
+ 52%
+ 86%
+ 96%
+ 68%
+ 61%
+_ 62%
+ 43%
0.04 ^102%
0.94
0.35
0.35
0.19
0.32
0.35
0.23
0.74
0.81
+ 73%
+ 37%
+ 45%
+ 85%
+_ 29%
+ 40%
+ 97%
+_ 84%
+ 77%
24
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Table 5--Continued
Gamma Activity in Concrete Samples
Ucation Radlonuclide
Rm 222, grid F-136 (around 214Pb 0.33 +_ 33%
ventilation ducting) (Site 37) 214Bi 0.38+31%
232Th 0.25 + 54%
Rm 223, grid F-9 and adjacent grids 214Pb 0.31 +_ 33%
(around ventilation penetration) 214Bi 0.31 +38%
(Site 38) 232Th 0.21 +_ 55%
Rm 223, grid F-72 (around area 60Co 0.39 +_ 74%
decontaminated by concrete removal)
(Site 39)
25
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Table 6
Surface Contamination Sampling Sites for Beta Analyses
Location
Location
Metrology Lab, granite table
Rad Services Bldg. M-18, Vent Flue,
Rm 8A, Shower Floor
Requlated exhaust vent on roof of
SORB
Air Handling Unit 4, exhaust for
SORB uncontrolled areas
SORB M-l, floor by grinder
SORB M-3, edge above door on unit 2
compartment #1
SORB M-3, top of Honeywell
Control Box
SORB M-3, top of chilled water pipe
Rm 209, F-18, EW-11, door casing
by NWS
Rm 215, airhandling unit, filter
return central (upstream)
Rm 222, filter returnsite (F43)
Rm 223, exhaust ducting
Rm 109, sink
Rm 110, sump G(F5) and duct
between C14-C8
Rm 116, filter return site
Rm 120, F-275, F-2, F-39, duct
work on floor, F-106, F-256,
and sink
Rm 122, exhaust
Rm 122A
Rm 123, exhaust upstream of HEPA
Rm 128, fume hood duct
Rm 134, F-17
Rm 138, filter return site,
F-144, Nw-63, and floor of
sump F
Rm 140, F-7, F-6 and exhaust
ducting
Rm 141, exhaust ducting
Rm 143, F-130
Note. - Locations (sites) shown in Appendix 3.
26
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Table 7
Surface Contamination Sampling Sites for Tritium Analyses
Location
Rm 109, drain plug, and F-28
Rm 110, F-5 (sump G)
Rm 134, F-17
Rm 138, F-5, F-42, F-54, and WW-92
Note. - Locations (sites) shown in Appendix 3.
27
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Table 8
Air Sampli ng Sites
Beta and Gamma Sampling Sites
Tri ti urn Sam pi i ng Si te s
Rm 109 (Sump G) (Site 40)
Rm 120, F-288 (Site 41)
Between Rm 138 and Rm 139 (Site 42)
Rm 143 (Site 43)
Rm 209 (Site 44)
loading dock at tank farm area (Site 45)
Rm 138, Sump F (Site 46)
Rm 138, Sump F (Site 47)
Rm 209 (Site 48)
Note. - Sites shown in Appendix 3.
28
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Table 9
Gamma Activity in Soil Samples
Location
Surface soil at grid F-l (under
graving dock hardline penetration)
Surface soil at grid F-8 (at
Sump "G" penetration)
Surface soil at grid F-7 (at
southwest corner of Sump "G")
Soil sample under SORB adjacent
to Sump F at grid F-127 at a
depth of = 30 cm
Radio nuclide
40,
214Pb
214Bi
232Th
40,
137CS
214Pb
214Bi
232Th
238U
40,
214Pb
214Bi
232Th
4°K
214Pb
214Bi
232Th
Gamna Activity
(pCi/gm dry weight)
0.59 + 22%
0.41 + 7%
0.40 + 7%
0.43 +_ 10%
0.34 + 26%
0.014+ 55%
0.16 +_ 12%
0.16 +_ 12%
0.20 + 14%
0.76 +_100%
0.23 +_ 41%
0.19 + 10%
0.19 + 10%
0.20 + 14%
0.20 + 41%
0.09 + 21%
0.053+_ 37%
0.17 + 16%
Twith the exception of Co-60 in four samples, all other
radionuclides with detectable activity are naturally occurring members of
the uranium and thorium decay chains, K-40, or Cs-137 from nuclear weapons
testing.
29
-------
Table 9--Continued
Gamma Activity in Soil Samples
Location
Soil sample under SORB adjacent
to Sump F at grid F-127 at a depth
of 1 to 3 cm
Surface soil at #10 Headhouse
Soil sample in shower drain of
the rad. services building
Soil sample at #1 Warehouse
storage site (west side -
inside fenced area)
Radionuclide
40K
137Cs
214Pb
232Th
40K
137Cs
214Pb
232Th
40,
60CO
214Bi
232Th
238U
40,
137Cs
214Pb
232Th
Gamma Activity
(pCi/gm dry weight)
0.43 + 23%
0.008+ 99%
0.26 +_ 9%
0.25 + 9%
0.28 + 12%
0.55 +_ 19%
0.025+_ 32%
0.23 + 8%
0.25 +_ Wo
0.10 + 23%
0.54 + 15%
0.02 + 26%
0.18 +_ 10%
0.15 + 12%
0.20 +_ 12%
0.73 + 79%
0.46 + 24%
0.38+ 5%
0.12 +_ 16%
0.13 + 15%
0.064+ 35%
30
-------
Table 9--Continued
Gamma Activity in Soil Samples
Location Radio nuclide , ^ma 5ctiv1*y.«.
_ _ (pCi/gm dry weight)
Soil sample at WAY 7 (TRG-427) 40K 3.5 +_ 15%
60Co 0.13+27%
137Cs 0.08 + 44%
214Pb 0.94 + 9%
214Bi 0.90 + 11%
232Th 0.48 + 21%
Rm 117, grid F-58 (drit and 60Co 0.13 +_ 42%
gravel from railroad bed) 60Co 0.11 +39%
40K 1.00+_45%
214Pb 0.31 +_ 26%
214Bi 0.21 + 43%
232Th 0.30 + 40%
South wing-wall (west end storm 40K 0.81 + 55%
drain) 137Cs 0.14 + 32%
214Pb 0.17 + 48%
214Bi 0.13 + 72%
232Th 0.28 + 43%
South wingwall (east end storm 7Be 0.48+49%
C 1.1 +65%
*Pb 0.35 + 33%
*Bi 0.28 + 47%
232Th 0.15 + 85%
drain) K 1.1 +65%
214
214Bi 0.28 + 47%
31
-------
Table 9—Continued
Gamma Activity in Soil Samples
Location
Radionuclide
Gamma Acti vi ty
(pCi/gm dry weight)
Composite soil from the tank
farm area
40,
60Co
137
214
Cs
Pb
214Bi
232
Th
106
Ru
0.63 +_ 18%
0.055+ 17%
0.068+ 16%
0.25 + 11%
0.21 +_ 12%
0.26 +_ 13%
1.1 +_ 72%
0.11 + 54%
32
-------
Table 10
Results of Miscellaneous Sample Analyses
Location and
Type of Sample
Rm 117, grid EW-26
(wall material -
insulation)
Black Beauty (used
in sand blasti ng)
Type of Analysis Radio nuclide
gamma all
gamma K
214Pb
2l4Bi
232Th
238^
OO£
Ra (Rn emanation Ra
into Lucas cell) 226Ra
234
U (alpha spectroscopy) U
235U
238U
234u
235u
238u
227
Th (alpha spectroscopy) Th
238Th
230Th
232Th
227Th
228Th
230Th
232Th
Ac ti vi ty
(pCi/gm)
0.00 + 0%
13.0 + 1%
4.6 + 4%
3.9 +_ 3%
1.4 +_ 13%
1.4 + 50%
5.2 + 2%(ash)
4.2 + 2%(wet)
3.4 +_ 12%(ash)
0.36 + 19%(ash)
3.9 + 12%(ash)
2.8 +_ 12%(wet)
2.9 +_ 19% (wet)
3.2 +_ 12%(wet)
0.35 + 2U(ash)
1.1 + m(ash)
3.8 + 8%(ash)
1.1 + 10%(ash)
0.28 + 20% (wet)
0.92 + ll%(wet)
3.0 + 8% (wet)
0.92 + 10%(wet)
IAH radionuclides with detectable activity reported in Table 10 are
naturally occurring.
33
-------
Table 11
Results of Asphalt Sample Gamma Analyses
Cation Radionucllde1
Warehouse #1
(west side -
outside fenced area)
40,
137Cs
214Pb
214BT
232Th
1.1 + 51%
0.038+ 99%
0.23 + 38%
0.24 + 41%
0.38 + 36%
Metrology - (east side -
outside door)
Between rad. services building
and hospital
40,
214Pb
214Bi
232Th
40,
214Pb
214Bi
232Th
238U
5.8
1.3
1.1
2.5
8.1
1.3
1.2
3.2
2.1
+ 17%
+ 11%
+_ 14%
+ 11%
+ 4%
+ 4%
+ 6%
+_ 3%
+ 71%
^All radionuclides with detectable activity reported in Table 11 are
naturally occurring except Cs-137 from weapons testing.
34
-------
Table 12
External Gamma Radiation Measurements Inside Submarine
Overhaul and Refueling Building (SORB)
Location (Room)
104
105
106
107
108
109
110
111
112
114
115
116
117
118
119
120
121
122
12 2A
123
124
125
126
127
128
129
130
Reading u R/hr (average)
5.6
6.7
6.4
6.5
5.6
5.2
5.5
7.3
6.2
5.6
4.6
4.5
4.0
5.8
6.0
5.8
6.0
5.3
4.7
6.6
6.2
5.8
4.7
5.4
5.2
6.1
7.1
35
-------
Table 12--Continued
External Gamma Radiation Measurements Inside Submarine
Overhaul and Refueling Building (SORB)
Location (Room)
131
133
134
135
136
137
138
138A
139
140
141
142
143
144
145
146
209
213
222
223
Reading u R/hr (Average)
6.5
5.1
5.9
5.1
5.3
5.2
4.8
4.5
4.6
5.4
5.6
5.3
5.7
6.6
7.1
6.1
5.5
6.9
5.0
5.6
36
-------
Table 13
Travel Routes for Power Units
Location Reading u R/hr (Average)
Warehouse 5.5
No. 8 Head house 4.0
8 Dock 4.0
Pier 7 4.4
Pier 1 5.3
Transportation Building 5.4
No. 4 Tool room 4.7
9C Substation 4.9
East End of SORB 4.5
37
-------
Table 14
Gamma Measurements in Other Shipyard Locations
Location
Re a ding u R/hr (Average)
Storage area where spent fuel
cars were worked on
Resin storage area
Graving dock
Electric shop
Metrology building
Graving dock
Roof of SORB
West end storage area
North wing wall of graving
dock
No. 10 Head House
6.0
7.0
5.0
4.0
6.5
3.5
4.0
4.0
3.5
6.0
Radiation Service Building Room
1
3
5
6
7
8
8a
9
4.0
4.0
4.0
4.5
4.5
4.5
5.5
5.5
38
-------
V. CONCLUSIONS
The radiological survey of the Ingalls Shipbuilding Division provided
the basis for the following conclusions.
1. The procedures used to control the releases of radioactive
materials into the harbor have been effective.
2. Levels of activity measured in the harbor are close to the
minimum detection limit for most equipment. Except for a trace
amount of Co-60 measured at one sediment sampling site, the only
radionuclides detected are those attributable to fallout and
those which are naturally occurring.
3. The only shoreline gamma exposure rates which are elevated above
background are attributable to sandblasting material on the
ground at these locations.
4. The levels of radioactivity found by EPA in the survey at Ingalls
Shipbuilding Division, Pascagoula, Mississippi, do not constitute
a detriment to the environment nor a significant radiation
exposure to the public or shipyard employees.
39
-------
5. The Submarine Overhaul and Refueling Building (SORB) has been
decontaminated by Ingalls prior to converting this building to
non-nuclear use. Residual levels of Co-60 contamination were found,
but all levels were well below the NAVSEA limit of 30 pCi/gm (Co-60
equivalent) for bulk material (earth, ground coverings, paint, or
building materials). The radiation dose to individuals from these
residual levels of Co-60 contamination are estimated to be extremely
small. However, in keeping with the concept of reducing radiation
doses to as low as reasonably achievable, it would be prudent to
remove from possible human contact those materials with detectable
levels which are easily removable.
Subsequent to the December 7-11, 1981 decommissioning surveys,
Ingalls Shipbuilding decontaminated painted surfaces containing
residual Cobalt 60 activity. "Sample analysis results of eighty-two
grids (rooms 115, 118, 120, 134, 136, 137, 138, 140, 141, and 209)
indicated residual Cobalt 60 below NAVSEA criteria but above minimum
detectable activity (MDA). The surface layer was removed on these
grids and subsequent sample analysis results were less than MDA of
approximately 3 x 10" uCi/gm (3 pCi/gm). Sample analysis results
of four grids in room 117 indicated residual Cobalt 60 below NAVSEA
criteria but above 1 x 10~ uCi/gm (1 pCi/gm) (concrete and
crevice). The surface layer was removed from these grids and
subsequent sample analysis results were less than 1 x 10
uCi/gm." From Deactivation of Ingalls Radiological Facilities,
Volume 1, page 68, Ingalls Shipbuilding Division, Litton Industries,
Pascagoula, Mississippi, 1982.
40
-------
REFERENCES
Bu75 Bugg S.G., 1975, Assessment of Environmental Radioactivity and
Population Exposure Resulting from Operation Associated with Nuclear
Propulsion Plant Work at Ingalls Shipbuilding Division, Pascagoula,
Mississippi.
Ca77 Call is R.S., Windham S.T., and Phillips C.R., 1977, Radiological
Survey of Puget Sound Naval Shipyard, Bremerton, Washington, and
Environs, EPA-520/5-77-001 (Washington, DC: U.S. Environmental
Protection Agency, Office of Radiation Programs).
Ca79 Callis R.S., Windham S.T., and Phillips C.R., 1979, Radiological
Survey of Portsmouth Naval Shipyard, Kittery, Maine, and Environs,
EPA-520/5-79-003 (Washington, DC: U.S. Environmental Protection
Agency, Office of Radiation Programs).
De72 Decampo J.A., Beck H.L., and Raff P.O., 1972, High Pressure Argon
lonization Chambers for Measurement of Environmental Radiation
Exposure Rates, HASL-260.
Le68 Levin S.G., Stoms R.K., Kuerze E., and Huskisson W., 1968, "Summary
of Natural Environmental Gamma Radiation Using a Calibrated Portable
Scintillation Counter", Radiological Health Data and Reports, 9, 11.
41
-------
Appendix 1
Results of Sediment Sample Analyses
Location
Site B-l1
Site 2
Site 4
Site 6
2
Radionuclide
40K
137CS
106Ru
214Pb
214Bi
232Th
40K
214Pb
214Bi
232Th
23^
4°K
137Cs
214Pb
214Bi
232Th
40,
137Cs
214Pb
214Bi
232Th
Acti vi ty
(pCi/gm dry weight)
2.5 + 8%
0.098 + 13%
0.079 + 63%
0.21 + 13%
0.19 +_ 12%
0.23 + 16%
0.85 + 10%
0.11 + 13%
0.087 + 17%
0.11 + 15%
0.76 ^ 60%
2.1 + 11%
0.07 + 20%
0.26 + 13%
0.18 +_ 16%
0.14 + 27%
0.85 + 12%
0.024 ^ 28%
0.17 + 9%
0.15 + 11%
0.13 + 18%
1 Sites locations are shown in Fig. 3.
2With the exception of Co-60 at Site 31 and Cs-137 fallout from
weapons testing, all radionuclides reported are naturally occurring
members of the uranium and thorium decay chains or K-40. No other
detectable activity was present.
42
-------
Appendix 1--Continued
Results of Sediment Sample Analyses
Location
Site 8
Site 9
Site 10
Site 11
Radionuclide
40K
137CS
214Pb
214Bi
232Th
40,
137CS
106Ru
214Pb
214Bi
232Th
4°K
137Cs
106Ru
214Pb
214Bi
232Th
40,
137Cs
214Pb
21 4n.
Bi
232Th
238U
Activity
(pCi/gm dry weight)
2.3 + 9%
0.063 + 19%
0.15 + 14%
0.16 + 14%
0.11 + 27%
2.3 + 8%
0.078 + 15%
0.075 + 70%
0.13 + 16%
0.12 + 17%
0.13 + 23%
2.0 + 8%
0.058 + 19%
0.015 + 97%
0.13 + 15%
0.13 + 15%
0.12 + 23%
2.7 + 6%
0.049 +_ 17%
0.18 + 10%
—
0.15 + 14%
0.22 + 13%
0.90 + 77%
43
-------
Appendix 1— Continued
Results of Sediment Sample Analyses
Location
Site 13
Site 14
Site 15
Site 16
Site 17
Radionuclide
40K
137CS
214Pb
214Bi
232Th
40,
137Cs
106Ru
214Pb
214Bi
232Th
40K
137Cs
214Pb
214Bi
232Th
40,
137Cs
214Pb
214B1
232Th
40K
137CS
214Pb
Activity
(pCi/gm dry weight)
2.4 + 8%
0.075 + 17%
0.14 + 18%
0.14 + 16%
0.15 +_ 21%
2.0 + 7%
0.041 + 19%
0.058 + 89%
0.14 + 16%
0.08 + 66%
0.18 +_ 14%
2.0 + 9%
0.043 + 23%
0.29 + 9%
0.27+ 9%
0.22 + 12%
1.6+ 9%
0.023 +_ 35%
0.29 + 7%
0.29+ 8%
0.29 + 14%
2.4 + 7%
0.051 + 18%
0.09 + 21%
44
-------
Appendix 1--Continued
Results of Sediment Sample Analyses
Location
Site 17
(conti nued)
Site 18
Site 19
Site 20
Site 21
Radionuclide
214Bi
232Th
23^
40,
137CS
214Pb
214Bi
232Th
40,
137CS
214Pb
214Bi
232Th
40,
137CS
106Ru
214Pb
214Bi
232Th
4°K
137CS
214Pb
Acti vi ty
(pCi/gm dry weight)
0.49 + 41%
0.17 +_ 16%
0.80 + 96%
2.4 + 8%
0.064 +_ 18%
0.29^ 8%
0.28 + 9%
0.20 + 16%
1.3+ 8%
0.018 + 35%
0.17 + 10%
0.15 + 12%
0.19 +_ 12%
2.2 +_ 13%
0.062 + 19%
0.082 +107%
0.20 + 12%
0.19 + 16%
0.16 + 29%
2.5 +_ 8%
0.074 + 17%
0.25 + 10%
45
-------
Appendix 1--Continued
Results of Sediment Sample Analyses
Location
Site 21
(conti nued)
Site 22
Site 23
Site 24
Site 25
Radionuclide
214Bi
232Th
40,
137CS
214Pb
214Bi
232Th
40
K
137Cs
214Pb
214Bi
232Th
40
K
137Cs
214Pb
214Bi
232Th
40
K
106RU
137Cs
214Pb
214Bi
232Th
Acti vi ty
(pCi/gm dry weight)
0.24 + 10%
0.18 +_ 19%
2.4 + 8%
0.06 + 19%
0.17 + 12%
0.16 + 14%
0.16 +_ 20%
2.4 + 13%
0.072 + 21%
0.17 + 14%
0.17 + 18%
0.14 + 35%
2.7 + 8%
0.07 + 21%
0.17 + 16%
0.15 + 14%
0.16 + 20%
2.1 + 9%
0.057 + 96%
0.072 + 16%
0.17 + 13%
0.16 + 14%
0.14 + 21%
46
-------
Appendix 1—Continued
Results of Sediment Sample Analyses
Location
Site 26
Site 27
Site 28
Site 29
Radionuclide
40K
137CS
214pb
214Bi
232Th
40,
137CS
214pb
214Bi
232Th
40,
137CS
106Ru
214Pb
214Bi
232Th
4°K
137Cs
106Ru
214Pb
214Bi
232Th
Activity
(pCi/gm dry weight)
2.2 + 6%
0.047 + 17%
0.22 + 9%
0.18 +_ 12%
0.19 + 13%
2.7 + 8%
0.076 + 16%
0.19 +_ 12%
0.16 + 14%
0.17 + 19%
2.3 + 7%
0.058 + 17%
0.067 + 66%
0.081 + 24%
0.042 + 50%
0.14 + 18%
2.3+; 9%
0.075 + 16%
0.076 + 85%
0.21 + 10%
0.21 + 13%
0.18 + 19%
47
-------
Appendix 1--Continued
Results of Sediment Sample Analyses
Location
Site 30
Site 31
Site 32
Site 34
Radionuclide
40,
137CS
214Pb
214Bi
232Th
23^
4°K
60Co
137Cs
214Pb
214Bi
232Th
238U
40
"\Jti
137Cs
214Pb
214Bi
232Th
40
K
137CS
214Pb
214Bi
232Th
Activity
(pCi/gm dry weight)
0.92 + 12%
0.012 + 56%
0.31 + 6%
0.31 + 7%
0.21 + 18%
1.0 + 78%
1 . 90 + 8%
0.013 + 45%
0.11 + 10%
0.12 + 17%
0.077 + 29%
0.20 + 14%
1.4 + 69%
2.0 + 15%
0.074 + 19%
0.17 + 16%
0.12 + 29%
0.16 +_ 35%
2.7 + 8%
0.078 + 14%
0.18 + 11%
0.16 +_ 14%
0.19 + 18%
48
-------
Appendix 1--Continued
Results of Sediment Sample Analyses
Location
Site 37
Site 38
Site 39
Site 40
Radionuclide
40K
137CS
106Ru
214Pb
214Bi
232Th
40
UK
137CS
106Ru
214Pb
214Bi
232Th
40,
137Cs
214Pb
214Bi
232Th
40,
137CS
214Pb
21 4n.
Bl
232Th
Activity
(pCi/gm dry weight)
2.3 + 8%
0.072 +_ 17%
0.066 + 80%
0.22 + 11%
0.21 + 11%
0.16 + 20%
2.3+ 7%
0.048 + 20%
0.05 + 91%
0.083 + 23%
0.048 + 42%
0.16 +_ 17%
1.9 + 15%
0.068 + 20%
0.16 + 16%
0.16 +_ 20%
0.18 +_ 28%
2.3 + 8%
0.072 +_ 16%
0.18 + 11%
—
0.18 +_ 13%
0.22 + 16%
49
-------
Appendix 1--Continued
Results of Sediment Sample Analyses
Locatl'on Radionuclide (pCi/gfdry "weight)
Site 41 40K 2.2 + 9%
137Cs 0.066 + 19%
214Pb 0.20 +
214Bi 0.17 +
232Th 0.15 +_ 21%
Site 42 40K 2.3 + 7%
137Cs 0.051 + 19%
214Pb 0.081 +_ 25%
214Bi 0.039 +_ 55%
232Th 0.14 + 19%
50
-------
Appendix 2
Results of Core Sample Analyses
Location
Below Sediment
Water Interface (cm)
Radionuclide2 , _., Activity
(pCi/gm wet weight)
Core #1
0-5.1
40K
232
Th
1.2 +_ 26%
1.3 + 41%
5.1 - 10.2
40K
137
232
CS
Th
3.2 + 29%
.12 + 44%
.17 + 82%
10.2 - 15.2
4°K
232
Th
2.5 + 37%
.18 + 82%
15.2 - 20.3
4°K
232
Th
2.5 + 32%
.27 + 60%
20.3 - 25.4
40
K
137
232
CS
Th
3.1 + 24%
.13 + 34%
.26 + 49%
25.4 - 30.5
4°K
137
232
Cs
Th
2.2 + 30%
0.06 + 78%
.19 + 65%
Core #2
0-5.1
40K
232
Th
2.1 + 21%
.15 + 53%
^Site locations are shown on Fig. 4.
2A11 radionuclides reported in this appendix are either naturally
occurring members of the uranium and thorium decay chains, naturally
occurring K-40, or Cs-137 fallout from nuclear weapons testing. No other
detectable activity was present.
51
-------
Appendix 2—Continued
Results of Core Sample Analyses
Location P6 Pth Below Sediment Radionuclide
Water Interface (cm)
Core #2 5.1 - 10.2 40K
(continued) Cs
232Th
10.2 - 15.2 40K
137CS
an
15.2 - 20.3 K
20.3 - 25.4 40K
137CS
232Th
25.4 - 30.5 40K
137Cs
30.5 - 35.6 40K
232Th
35.6 - 40.6 40K
232Th
40.6 - 45.7 40K
137Cs
232Th
Core #3 0-7.6 40K
137Cs
Activity
(pCi/gm wet weight)
2.8 +_ 32%
.07 + 70%
.23 + 71%
2.6 + 37%
.07 + 92%
2.2 + 35%
2.3 + 44%
.12+40%
.28 + 71%
2.7 +_ 25%
.11 + 36%
2.3 + 32%
.21 + 63%
2.2 +_ 28%
.24 + 54%
1.4 +_ 39%
.05 + 89%
.13 + 87%
2.4 + 37%
.06 +101%
52
-------
Appendix 2—Continued
Results of Core Sample Analyses
Core #3 7.6 - 12.7 40K 2.6 + 30%
919
(continued) "^Th .22 +_ 63%
12.7 - 17.8 40K 2.2 + 47%
137Cs .09 +
232Th .24 + 85%
17.8 - 22.9 4°K 2.1 + 30%
137Cs .07 + 76%
232Th .15 + 83%
22.9 - 27.9 4°K 2.4 + 33%
137Cs .08 + 70%
27.9 - 33.0 40K 2.3 + 28%
232Th .16 + 97%
33.0 - 38.1 4°K 2.7 + 35%
137Cs .10 + 54%
232Th .17 + 82%
38.1 - 43.2 4°K 2.5 + 44%
137Cs .07+99%
214Pb .37+45%
214Bi .48 + 40%
53
-------
Appendix 2—Continued
Results of Core Sample Analyses
Location fj1* Below Sediment Rad1onuclide
Water Interface (cm)
Core #3 43.2 - 48.3 40K
232
(continued) Th
48.3 - 53.3 40K
dn
53.3 - 58.4 UK
58.4 - 63.5 4°K
232Th
Core #4 0-7.6 40K
137CS
214Pb
214Bi
7.6 - 12.7 40K
12.7 - 17.8 40K
17.8 - 22.9 40K
137Cs
232Th
22.9 - 27.9 40K
137Cs
232Th
Activity
(pCi/gm wet weight)
2.4 +_ 37%
.24 + 80%
2.5 +_ 36%
2.2 +_ 46%
2.5 + 32%
.25 +_ 65%
1.8 +37%
.09 + 49%
.11 + 74%
.13 +_ 74%
2.2 +43%
3.5 + 28%
2.7 + 32%
.09 + 57%
. 1 8 +_ 84%
3.5 +_ 31%
.10 + 73%
.37 + 53%
54
-------
Appendix 2—Continued
Results of Core Sample Analyses
I oration Depth Be low Sediment
Location Water Interface (cm)
Core #4 27.9 - 33.0
(conti nued)
33.0 - 38.1
38.1 - 43.2
43.2 - 48.3
48.3 - 53.3
53.3 - 58.4
58.4 - 63.5
Core #7 0 - 5.1
Radio nuclide
40K
232Th
40,
137CS
214Pb
214Bi
232Th
40K
137CS
232Th
40,
232Th
40,
137CS
232Th
40,
232Th
40R
232Th
4°K
232Th
Acti vi ty
(pCi/gm wet weight)
4.4 + 22%
.30 + 53%
4.2 + 23%
.10 +_ 50%
.19 + 58%
.24 + 51%
.39 + 43%
3.6 + 30%
.10 + 67%
.39 +_ 49%
4.2 +_ 21%
.42 + 40%
3.4 + 20%
.08^ 71%
.30 +_ 54%
3.3 + 25%
.33 + 45%
2.8 + 32%
.30 + 53%
1.7 +40%
.50 + 33%
55
-------
Appendix 2—Continued
Results of Core Sample Analyses
De D th Be low Se di me nt • • Ac ti vi ty
Water Interface (cm) (pCi/gm wet weight)
Core #7 5.1 - 10.2 40K
(continued) Cs
214Pb
214Bi
232Th
10.2 - 15.2 40K
137Cs
40
15.2 - 20.3 K
232Th
238U
20.3 - 25.4 40K
232Th
25.4 - 30.5 40K
137
30.5 - 35.6 40K
232Th
35.6 - 40.6 40K
137Cs
214pb
214
Bi
232Th
2.0 + 40%
.10 + 51%
.14 +_ 81%
.13 + 85%
.28 + 56%
1.8 + 56%
.15 + 53%
2.2 +_ 34%
.16 +_ 82%
5.4 + 78%
3.1 + 32%
.19 + 89%
2.7 + 36%
^~~
.07 + 86%
1.8 +25%
.20 + 70%
2.2 +_ 35%
.10 + 46%
.29 + 58%
*~
.27 + 46%
.23 + 69%
56
-------
Appendix 2—Continued
Results of Core Sample Analyses
location Depth Below Sediment
Location Water Interface (cm)
Core #7 40.6 - 45.7
(conti nued)
45.7 - 50.8
Core #8 0-8.9
8.9 - 14.0
14.0 - 19.0
19.0 - 24.1
24.1 - 29.2
29.2 - 34.3
Radionuclide
40K
137Cs
40,
137Cs
232Th
137Cs
232Th
40,
137Cs
232Th
40,
137Cs
40,
232Th
40,
137Cs
40,
137Cs
Ac ti vi ty
(pCi/gm wet weight)
1.8 + 53%
.07 + 91%
1.9 + 39%
.09 + 56%
.16 + 77%
2.1 + 36%
.07 + 72%
.12 +103%
2.7 + 33%
.14 + 44%
.18 + 78%
2.2 +42%
.11 + 67%
2.0 + 38%
.26 + 64%
2.6 + 38%
.11 + 56%
1.7 + 56%
.15 + 53%
57
-------
Appendix 2--Continued
Results of Core Sample Analyses
Location fP*1 Below Sediment Radionuclide
Water Interface (cm)
Core #8 34.3 - 39.4 40K
(continued) Cs
232Th
39.4 - 44.4 40K
137Cs
232Th
44.4 - 49.5 40K
137p
232ThS
49.5 - 54.6 4°K
232Jh
54.6 - 59.7 40K
137Cs
214Pb
214Bi
232Th
59.7 - 64.8 40K
137CS
232Th
Activity
(pCi/gm wet weight)
1.6 +47%
.12 + 42%
.20+78%
2.2 + 38%
.14 +_ 40%
.20 + 79%
3.5 + 38%
.14 + 68%
.23 +_ 89%
2.7 + 33%
.19 + 80%
3.0 +_ 31%
.12+46%
.15 + 61%
.13 + 91%
.23 +_ 58%
1.8 +52%
.08 + 83%
.16 + 92%
58
-------
Appendix 2--Continued
Results of Core Sample Analyses
L°««°" Eg SffceX"? «"«<»«"*
Core #10 0 - 5.1 40K
232Th
5.1 - 10.2 4°K
137CS
232Th
An
10.2 - 15.2 H<
137CS
214Pb
214Bi
232Th
15.2 - 20.3 4°K
232Th
20.3 - 25.4 40K
137CS
214Pb
214BT
232Th
40
25.4 - 30.5 UK
137CS
Activity
(pCi/gm wet weight)
1.8 + 34%
.21 + 54%
2.4 + 21%
.10 + 33%
. 21 + 46%
2.5 + 25%
.07 + 65%
.38 + 26%
.41 + 26%
.22 + 55%
2.3 + 24%
.15 + 62%
4.8 + 43%
.20 + 50%
.56 + 34%
.59 + 42%
.61 + 69%
3.4 + 19%
.12 + 32%
59
-------
Appendix 2--Continued
Results of Core Sample Analyses
Location J* ?th Below Sediment
Water Interface (cm)
Core #10 30.5 - 35.6
(conti nued)
35.6 - 40.6
40.6 - 45.7
45.7 - 50.8
50.8 - 55.8
55.8 - 61.0
Core #11 0 - 7.6
Radionuclide
40K
137CS
214Pb
214Bi
232Th
40K
137CS
232Th
40,
232Th
137Cs
232Th
238U
40,
137«
232ThS
40,
137CS
Acti vi ty
(pCi/gm wet weight)
1.5 + 42%
.09 + 53%
. 21 + 45%
. 21 + 50%
.13 + 87%
2.3 + 41%
.17 + 38%
2.0 + 50%
.20 + 81%
2.2 + 26%
. 20 +_ 56%
2.7 + 40%
.07 + 63%
.33 +_ 63%
7.7 + 91%
2.9 + 20%
.09 + 39%
.14 + 61%
1.2 +35%
.04 + 89%
60
-------
Appendix 2--Continued
Results of Core Sample Analyses
• DG p th BG low So di mo nt • * Activity
Water Interface (cm) (pCi/gm wet weight)
Core #11 7.6-12.7 40K
107
(continued) Cs
232Th
12.7 - 17.8 40K
137Cs
17.8 - 22.9 40K
232Th
22.9 - 27.9 40K
137CS
214Pb
214Bi
232Th
27.9 - 33.0 4°K
137CS
232Th
23^
33.0 - 38.1 4°K
137Cs
232Th
38.1 - 43.2 4°K
232Th
2.1 ^39%
.09 + 56%
.15 + 93%
2.4 +_ 45%
.12 + 67%
2.6 + 35%
.22 +_ 83%
2.4 + 44%
.12 + 43%
.18^48%
.20 +_ 67%
.26 + 81%
2.5 +_ 22%
.12 + 34%
.15 +_ 66%
3.6 +_ 97%
2.4 +_ 30%
.09 + 56%
.13 + 89%
2.8 +_ 20%
.23 + 44%
61
-------
Appendix 2--Continued
Results of Core Sample Analyses
Location !*Pth Below Sediment
Water Interface (cm)
Core #11 43.2 - 48.3
(continued)
48.3 - 53.3
Core #12 0 - 7.6
7.6 - 12.7
12.7 - 17.8
17.8 - 22.9
Radio nuclide
40K
137CS
232Th
40K
137CS
40K
232Th
40,
214Pb
214Bi
232Th
238U
40,
2l4Pb
214Bi
232Th
214Pb
214Bi
232Th
Acti vi ty
(pCi/gm wet weight)
2.8 + 33%
.10 +_ 64%
.26 +_ 64%
2.7 +44%
.08 + 98%
1.2 +37%
.32 +_ 38%
2.0 + 20%
.15 + 37%
.15 + 41%
.23 +_ 35%
2.7 + 90%
2.0 + 25%
.25 + 28%
.38 + 39%
.18 + 45%
3.3 +_ 27%
.19 + 49%
.19 +_ 58%
.29 + 56%
62
-------
Appendix 2—Continued
Results of Core Sample Analyses
inratinn Depth Be low Sediment
Location Watgr Interface (cm)
Core #12 22.9 - 27.9
(continued)
27.9 - 33.0
33.0 - 38.1
38.1 - 43.2
Radionuclide
40K
214Pb
214Bi
232Th
4fl
4UK
232Th
40K
?14
*'4Pb
214Bi
232Th
238,j
40K
232Th
Activity
(pCi/gm wet weight)
3.6 + 28%
.14 + 91%
.19 + 77%
.31 + 56%
3.3 + 25%
.38 + 42%
3.9 + 16%
.19 + 38%
.19 + 40%
.34 + 32%
3.4 +_ 90%
3.4 + 15%
.28 + 33%
63
-------
Appendix 3
Sampling Locations in SORB
East End of SORB - First Floor Paint and Concrete Samples
RM 114
4
/
y
-
RM 115
5
J 6W
RM 119
8
RM 120
RM 116 ' RM 117
29
Illllll RM118
9
41
7
Fig. 6: East End of SORB First Floor
Paint and Concrete Samples
64
-------
O)
en
RM
33
31
137
14
42
32
RM 138
16
15
r i
18
20W
21 RM 140
RM 139
RM 141
22
34 W
RM 133
I
17
RM 142
35
RM 143
43
24
I 13
RM 134
45
11
RM 131
10
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Fig. 7: West End of SORB - First Floor
Paint and Concrete Samples
-------
LI
d
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RM 109
40
28
RM 106
3
RM 111
RM 110
CTl
Fig. 8: Center of SORB - First Floor
Paint and .Concrete Samples
o
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3
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rc
Fig. 9: East End of SORB - Second Floor
Paint and Concrete Samples
-------
Appendix 3--continued
Sampling Locations in SORB
Center of SORB - Second Floor Paint and Concrete Samples
RM 215
36
Fig. 10: Center of SORB - Second Floor
Paint and Concrete Samples
68
-------
i-D
r---,- -}
,
1
1
L J
27 W
ftt-
RM 223
39
38
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s= i'
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(~l 7O
D3
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0
o
-s
I'D
(Q
Q>
Fig. 11: West End of SORB - Second Floor
Paint and Concrete Samples
------- |