FINAL DRAFT REPORT ON
RADIATION SURVEY OF BUILDINGS
IN THE GSA RARITAN DEPOT,
EDISON, NEW JERSEY
PROJECT FOR
PERFORMANCE OF
REMEDIAL RESPONSE ACTIVITIES AT
UNCONTROLLED HAZARDOUS
SUBSTANCE FACILITIES-ZONE 1
NUS CORPORATION
SUPERFUND DIVISION
-------
R-58W) 1-86-03
FINAL DRAFT REPORT ON
RADIATION SURVEY OF BUILDINGS
IN THE GSA RARITAN DEPOT,
EDISON, NEW JERSEY
PREPARED UNDER
TECHNICAL DIRECTIVE DOCUMENT NO. 02-8506-08
CONTRACT NO. 68-01-6699
FOR THE
ENVIRONMENTAL SERVICES DIVISION
U.S. ENVIRONMENTAL PROTECTION AGENCY
MARCH 10, 1986
NUS CORPORATION
SUPERFUND DIVISION
SUBMITTED BY REVIEWED/APPROVED BY
CHARLOTTE RYDEN RONALD M. NAMAN
PROJECT MANAGER REGIONAL PROJECT MANAGER
-------
1.0 INTRODUCTION
From January 6 through January 8, 1986, a radiation survey was conducted at the
GSA, Raritan Depot by NUS Radiological Programs Department, under the
direction of David K. Dougherty. This report details the methods, results, and
conclusions of the survey. Sampling to identify the radionuclides present at
Building 214 was conducted by FIT II on January 9, 1986. To determine the working
levels of radiation in Buildings 205 and 214, Radiation Progeny Integrated Sampling
Units (RPISU's) were installed February 19 to February 24, 1986.
Buildings in the GSA, Raritan Depot, located in Edison, New Jersey were surveyed
to determine the presence or absence of radioactive contamination. Figure 1
provides a site location map and figure 2 provides a site map. The interiors of
Buildings 205 and 214 were surveyed in detail. During these surveys, it was
discovered that the ceilings were the source of elevated radiation levels found
inside the buildings. Based on this discovery, rooftops of other buildings in the
GSA, Raritan Depot were surveyed, and a sampling plan was developed and
implemented. Subsequently, monitoring was done to determine the concentration
of radon and radon daughters in Buldings 205 and 214.
-------
OUADRANGLE LOCATION
(QUAD) PERTH AM BOY/SO UTH AMBOY, N..I.
SITE LOCATION MAP
GSA, RARITAN DEPOT, EDISON, N.J.
SCALE: 1* - 2000'
FIGURE 1
IM US
CORPORATION
A Halliburton Company
-------
EPA PROPERTY
OPEN SEWER
INDUSTRIAL ROAD
ABANDONED
BLOQ.
FORMER
DEMOLITION
AREA
OIL TANK
LEGEND:
EPA PROPERTY
> QSA PROPERTY
-P088IDLE DISPOSAL AREA
FIGURE 2
SITE MAP
GSA, RARITAN DEPOT, EDISON, N.J.
(NOT TO SCALE )
IMUS
CXDRPORATONJ
o A Halliburton Company
-------
2.0 SURVEY METHODS
2.1 Instrumentation
A variety of portable survey meters and a Reuter-Stokes pressurized ionization
chamber (PIC) were used in the study. Pertinent information is included in the list
of equipment in Table 1.
The Ludlum-2000 portable scalers were operated with Ludlum scintillation
detectors, each with a different size sodium iodide (Nal) crystal to determine
gamma radiation count rates. A Ludlum-19 micro-R meter, with a built-in Nal
scintillator, was used to take general gamma dose rate readings. Two Ludlum-177
alarm rate meters with Ludlum pancake Geiger-Mueller probes were used to
measure beta/gamma count rates. A Ludlum-12 and an Eberline El20, each
equipped with a thin-wall Geiger-Mueller probe (with rotary beta shield) were also
used to measure beta/gamma count rates. The rotary beta shields were in the open
position while taking measurements. Comparative measurements of gamma
radiation dose rates in Microroentgens per hour (micro-R/hr) were made with a
Reuter-Stokes RS-111 pressurized ionization chamber (PIC). All instruments were
operated on battery power in the field.
2.2 Locations and Grid Systems
Detailed measurements were made at Buildings 205 and 214 using a 20' x 20' grid
system. A grid system was laid out in Buildings 205 and 214, as shown in Figures 3
and 4, respectively. There are 262 grid point locations in Building 205 and 300 grid
point locations in Building 214.
A general survey of the remaining GSA, Raritan Depot buildings' rooftops was
made after the detailed surveys of Buildings 205 and 214 were completed.
2.2.1 Building 214 Survey
In Building 214 dose rate measurements were taken at a height of 1 meter with the
Ludlum-19 at each grid point. At approximately 10% of the grid point locations,
measurements were also made at the floor level with the Ludlum-19, Ludlum-177,
-------
Table 1. Equipment List for the GSA, Raritan Depot Radiation Survey
Survey Meter Detector
(If Applicable) Type of Measurement
Ludlum(l)-2000
Ludlum-2000
Ludlum-19
Ludlum-12
Ludlum-177
Ludlum-177
Eberline E120 (2)
Reuter-Stokes (*) RS-
PIC
111
Ludlum 44-10
Ludlum 44-2
N/A
Ludlum 44-6
Ludlum 44-9
Ludlum 44-9
Eberline El20
Filled Ion
Chamber
Gamma (2" x 2"NaI (Tl)) CPM
Gamma (1" x 1" Nal (Tl)) CPM
Gamma (1" x 1" Nal (Tl)) micro-R/hr
Beta, Gamma (Geiger-Mueller) CPM
Beta, Gamma (Geiger-Mueller) CPM
Beta, Gamma (Geiger-Mueller) CPM
Beta, Gamma (Geiger-Mueller) CPM
Gamma (Ion Chamber) micro-R/hr
(1) Ludlum Measurements, Inc., 501 Oak Street, Sweetwater, Texas 79556
(2) Eberline Instrument Corp., P.O. Box 2108, Sante Fe, New Mexico 87501
(3) Reuter-Stokes, 18530 South Mile Parkway, Cleveland, Ohio 4-4128
Tl = Thallium
Micro-R = Micro Roentgens
CPM = Counts Per Minute
N/A = Not Applicable
-------
35 34 33 32 31 30 29 28 27 26 25 24 23 22 21 20 19 18 17 16 15 14 13 12 II 10 9 S 7 8 5 4 3 2 1
'
r :r. i. :n.
u
>
i
FIGURE 3
GRIP SYSTEM FOR BUILDING 205
GSA, RARITAW DEPOT, EDISON, N.J.
NUS
eXJRPCDRATOrsJ
A Halliburton Company
-------
FIGURE 4
GRID SYSTEM FOR BUILDING 214
GSA, RARITAN DEPOT, EDISON, N.J.
primus
_LJ CCDRFORATOfSI
A Halliburton Company
-------
Ludlum-12, and Ludlum-2000 (with the 44-10 detector). A vertical survey, both
along several walls and near the center of several grid points was also conducted in
Building 214. Measurements were made at the ceiling and the floor and at five
foot increments with the Ludlum-2000 (with the 44-10 detector) and the Ludlum-
177. Comparison measurements of "old" and "new" ceiling tiles were also made at
several points with the Ludlum-2000 and Ludlum-177.
2.2.2 Building 205 Survey
In Building 205 dose rate measurements were taken at a height of 1 meter with the
Ludlum-19 at each grid point. At approximately 10% of the grid point locations,
measurements were also made at the floor level with the Ludlum-19, Ludlum-177,
Ludlum-12, and Ludlum-2000 (with the 44-2 detector).
The pressurized ionization chamber (PIC) was used to take dose rate measurements
at several locations in both Buildings 205 and 214. These readings were used to
correct the Ludlum-19 dose rate measurements.
No vertical survey of Building 205 was performed since the vertical survey of
Building 214 had isolated the ceiling tiles as the source of radiation and these same
tiles were present in Building 205.
2.2.3 Rooftop Survey
At the conclusion of the detailed surveys of Buildings 205 and 214, a rooftop survey
was performed at the non-wooden framed buildings at the GSA, Raritan Depot
complex. Several rooftop measurements were made at each building, depending on
its size, with the Ludlum-2000 scalers (both the 44-2 and 44-10 detectors were
used).
-------
2.3 Sampling
Building 214 was chosen for sample collection since it is presently unoccupied and
unused. Seven samples of building materials were obtained for laboratory analysis.
Five samples were taken from the gypsum-like roofing material at locations
indicated in figure 5, the sample location map. These samples were obtained by
first removing the tar paper and stone layer above the tiles, and then chipping the
tiles. The chips were pulverized prior to shipment. A sample of the concrete floor
was collected from the dust created by drilling through the slab. An auger was
used to collect a sample of the soil beneath the concrete. Two 8-ounce glass jars
were collected per sample. Gamma spectroscopy and alpha spectroscopy for
uranium-238 and thorium-230, analyses were performed on all samples.
2A RPISU Installation
On February 19 and 20, 1986 three Radon Progency Integrated Sampling Units
(RPISU) were installed in Buildings 205 and 214. RPISU's 1167-E and 52-E were
installed in Building 205 on February 19, 1986 in grids A-3 and C-21, respectively.
Grid A-3 is located in a portion of the bulding with minimal ventilation. There are
no windows in this area of building 205 and doors are padlocked shut. Grid C-21 is
located in an area of the building that is well ventilated. There are several broken
windows on the west wall, entrance doors are commonly open and a skylight,
although closed, may allow some ventilation through the roof. The RPISU's were
removed from Building 205 on February 24, 1986.
A portable gillian pump (//12098) was installed on February 20, 1986 in Building 214
in grid L-16. The sampling area was partially ventilated. The swinging metal
entrance could not be completely closed and there are holes in the ceiling,
resulting from the sampling of the roof tiles. The sampling device was removed on
February 21, 1986.
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~ NJP6-RS
©
"1
0NJP6-M
MJP6-R7
1NJPI-R4
~ NJP0-R3
'
ANJPA-R1
LEGEND
CONCRETE FLOOR/SOIL BORtNO SAMPie
A CCtLMQ TILE SAMPLE
COLUMN
SAMPLE LOCATION MAP
BUB-PING 214
GSA, RARITAN DEPOT, EDISON. N.J.
=s y=
FIGURE 5
VMUS
I CXDRRCDRATDTsj
CXDRRORATCMNJ
A Halliburton Company
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3.0 SURVEY RESULTS
The interiors of Buildings 205 and 214 were surveyed to determine the existence or
absence of radioactive contamination. Readings in both buildings were found to be
somewhat higher than those associated with natural background radiation. During
the vertical survey of Building 214, it was discovered that the source of the
contaminant leading to the elevated readings was in the ceiling of the building.
Based upon this discovery, rooftops of buildings in the GSA, Raritan Depot
compound were surveyed for elevated readings. The results of these surveys
follow.
3.1 Survey of Buildings 205 and 214
A gamma exposure rate survey and floor survey were conducted in Buildings 205
and 214. A vertical survey was performed in Building 214. The results of these
surveys are presented in Sections 3.1.1, 3.1.2, and 3.1.3.
Building 205 is currently being used by EPA for training exercises. Through
conversation with equipment room personnel it was discovered that several
radiation sources may have been hidden throughout parts of the building for
training purposes. Five radiation sources were identified attached to support
beams in the equipment room area (southwest section of the building).
3.1.1 Gamma Exposure Rate Survey
The results of the gamma exposure rate surveys conducted in Buildings 205 and 214
are presented in Tables 2 and 3 respectively. Values presented in the tables have
been "corrected" to yield gamma exposure rates through cross calibration with a
Rueter-Stokes pressurized ion chamber.
Gamma exposure rates varied from 8.7 micro-R/hr to 20.6 micro-R/hr in Building
205 and from 16.1 micro-R/hr to 22.3 micro-R/hr in Building 214. These numbers
can be put into perspective by comparing them to the gamma exposure rate
attributable to natural background radiation which is about 8.7 micro-R/hr.
-------
Table 2. Gamma Exposure Rate Survey, Building 205
Grid
Location A*ABCDEFGH
1
17.2
18.3
18.3
19.5
18.3
17.2
18.3
17.8
17.2
2
18.3
18.3
18.9
18.9
17.2
18.3
17.8
18.9
17.2
3
18.3
18.3
19.5
20.6
18.9
19.5
18.9
18.9
16.1
4
17.2
17.8
19.5
20.0
18.3
18.9
19.5
19.5
17.8
5
17.2
17.2
18.3
20.0
18.3
19.5
19.5
18.9
17.8
6
17.2
17.2
18.3
19.5
19.5
18.9
18.3
18.3
17.8
7
16.6
16.1
18.3
18.9
20.6
19.5
18.9
17.8
N/A
8
16.1
16.1
18.3
18.3
17.2
18.3
18.3
17.2
16.6
9
16.1
16.1
18.3
18.3
18.3
18.3
18.3
17.8
17.8
10
16.6
17.2
18.3
18.3
17.8
18.3
17.8
17.8
16.1
11
17.2
17.2
18.3
18.3
18.3
18.3
18.3
18.3
14.9
12
16.6
16.6
18.3
18.9
18.3
18.3
18.3
18.3
16.1
13
17.2
17.2
18.3
18.3
18.9
17.8
17.8
17.8
16.1
14
17.2
17.8
17.8
18.3
17.8
17.8
17.8
17.8
14.9
15
17.8
17.8
17.8
18.3
17.2
18.3
18.3
17.8
15.5
16
17.2
17.2
17.8
17.8
18.3
18.3
17.8
18.3
15.5
17
17.2
17.2
17.8
17.8
18.3
18.3
18.3
17.8
15.5
18
17.2
17.8
17.8
18.3
18.3
18.3
17.8
18.3
15.5
19
14.9
14.9
18.3
18.3
17.8
18.3
17.8
18.3
15.5
20
14.9
14.9
17.8
16.6
17.2
17.2
17.8
17.8
15.5
21
16.1
16.1
16.6
16.6
16.1
16.6
16.1
17.2
16.1
22
15.5
17.2
16.6
16.1
15.5
16.1
13.8
16.6
14.9
23
16.1
16.1
16.6
14.9
14.9
16.1
13.2
16.1
14.9
24
16.1
16.1
16.1
14.9
14.4
14.9
13.8
16.1
14.9
25
15.5
15.5
16.1
13.8
14.9
14.9
13.8
16.1
14.9
26
16.1
16.1
15.5
13.8
14.9
14.4
13.2
16.1
14.9
27
16.1
15.5
14.9
14.4
14.9
14.4
13.8
16.1
14.4
28
16.1
16.1
15.5
14.9
14.4
14.9
14.4
16.1
13.8
29
14.4
14.4
15.5
14.9
13.8
14.9
14.9
15.5
13.8
30
N/A
N/A
N/A
9.8
10.4
9.8
10.4
11.5
N/A
31
N/A
N/A
N/A
8.7
9.8
9.3
9.8
11.0
N/A
32
N/A
N/A
N/A
8.7
9.3
9.3
9.3
9.3
N/A
33
N/A
N/A
N/A
9.3
9.3
9.3
9.3
9.3
N/A
34
N/A
N/A
N/A
10.4
9.3
9.3
10.4
11.0
N/A
Note:
Instrument used: Ludlum - 19; all readings in Micro-R/hr.
Readings taken at 1 meter except where * appears; readings taken at
floor level.
N/A = Not Applicable
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Table 3. Gamma Exposure Rate Survey, Building 21^
Grid
Location A* ABC DE F G H I 3 KL
1
17.8
17.8
19.5
18.9
19.5
18.3
18.3
18.9
18.9
18.3
18.9
19.5
17.2
2
18.3
18.3
20.6
18.9
19.5
19.5
18.9
18.3
19.5
18.9
20.0
20.0
18.3
3
18.3
18.3
20.6
19.5
19.5
20.0
19.5
18.3
20.0
19.5
20.0
19.5
18.3
it
19.5
19.5
20.6
19.5
20.6
20.6
19.5
17.8
20.0
19.5
19.5
19.5
18.3
5
19.5
18.9
20.6
20.0
20.6
20.0
18.9
18.3
19.5
20.0
19.5
19.5
17.8
6
17.8
17.8
19.5
20.6
20.0
20.6
18.9
18.3
19.5
20.6
19.5
19.5
17.8
7
18.9
18.9
19.5
21.2
20.0
20.6
19.5
18.3
19.5
20.6
18.9
19.5
18.3
8
18.3
18.3
19.5
20.0
19.5
20.0
N/A
18.3
18.9
20.0
18.9
20.0
17.8
9
18.9
18.9
20.6
18.9
20.6
19.5
20.0
17.8
19.5
19.5
19.5
19.5
18.3
10
19.5
19.5
20.6
19.5
21.7
20.0
20.0
17.8
19.5
20.0
19.5
19.5
18.9
11
18.9
18.3
21.2
20.6
21.2
20.0
20.6
17.8
19.5
20.0
20.0
19.5
18.9
12
18.9
19.5
20.6
20.6
21.7
20.0
21.7
18.3
20.6
20.6
20.0
19.5
18.3
13
18.9
18.9
20.6
21.2
21.2
20.6
20.6
18.3
20.6
20.6
20.0
20.6
18.3
1^
18.3
18.3
21.7
22.3
21.2
21.7
20.0
18.3
20.6
20.6
20.0
20.0
17.2
15
17.8
17.8
20.6
22.3
20.6
21.2
19.5
18.3
19.5
21.7
20.0
19.5
17.8
16
18.3
< 18.3
20.0
21.2
20.6
21.2
19.5
18.3
19.5
20.6
20.0
19.5
17.2
17
17.8
17.8
20.6
20.0
20.0
21.2
N/A
17.8
19.5
20.6
19.5
19.5
18.3
IS
17.8
18.3
19.5
19.5
20.6
19.5
19.5
18.3
19.5
20.0
20.0
19.5
18.3
19
18.3
18.3
19.5
20.0
20.6
20.6
19.5
17.8
19.5
19.5
20.0
20.6
18.3
20
17.2
17.2
18.9
20.6
20.6
20.6
19.5
17.8
20.6
20.0
20.0
20.6
18.3
21
17.8
18.3
19.5
20.6
20.6
21.2
18.9
18.3
20.0
20.6
19.5
20.6
18.3
22
18.9
18.9
19.5
19.5
20.0
20.0
18.9
17.8
19.5
20.0
19.5
19.5
17.2
23
18.3
17.8
19.5
20.0
18.9
20.0
18.9
18.3
18.3
20.0
18.3
19.5
17.2
2H
18.3
18.3
18.3
19.5
19.5
19.5
18.3
17.2
17.8
18.3
17.2
18.9
17.8
25
17.8
17.8
17.8
18.9
19.5
18.9
17.8
16.6
17.8
17.2
17.2
17.2
16.1
Note:
Instrument used: Ludlum - 19; all readings in Micro-R/hr.
Readings taken at 1 meter except where * appears; readings taken at
floor level.
N/A = Not Applicable
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3.1.2 Floor Survey
The floors of Buildings 205 and 214 were surveyed in several randomly selected
locations. The floors were surveyed using a (1) Ludlum-177 with a "pancake" probe
(L-177), (2) Ludlum-12 with open window Geiger-Mueller probe (L-12), and (3)
Ludlum-2000 scalar (L-2000) with either a Ludlum 44-2 Nal probe (in Building 205)
or a Ludlum 44-10 Nal probe (in Building 214).
The floor survey results for Buildings 205 and 214, presented in Tables 4 and 5
respectively, show elevated readings when compared to readings associated with
background radiation. Background readings were taken with each instrument
outside of each building and are presented on the first line of both tables. It should
be noted that background readings for the L-2000 with the 44-2 probe, used to
survey Building 205, and the L-2000 with the 44-10 probe, used to survey Building
214, are markedly different. This is due to the effective size of the probe.
Because the probe used to survey Building 205 has a different response than the
probe used to survey Building 214, L-2000 readings between the two buildings
should not be directly compared.
It should also be noted that the L-177 and L-12 are analog instruments which yield
instantaneous results, in counts per minute (CPM), and display a fairly wide
variability in readings in a stationary location. This is due to the variability of
radiation fields over time. Values reported for these instruments in the table
represent gross averages as determined by the field technician from observing the
varying reading of the analog display. In contrast, the L-2000 is an integrating
device that integrates counts over a one minute period displaying CPM on a digital
display.
3.1.3 Vertical Survey
A vertical survey was conducted in Building 214 to determine what variability
existed in radiation levels with height. The results of this survey are presented in
Table 6.
Measurements were taken in several locations using the L-2000 with a Nal (Ludlum
44-10 probe) detector at various orientations (i.e., pointing up, pointing down, and
lateral). Measurements were taken at 0, 5, 10, and 15 foot elevations and at the
-------
Table 4. Building 205 Floor Survey
Instrument
Grid Location L-177(CPM) L-12(CPM) L-2000(44-2 Probe)
(CPM)
BKGD
40
20
1151
A-03
60
30
4160
A-13
60
40
3730
A-18
70
30
3880
A-21
50
30
3240
B-06
70
50
4190
B-09
70
40
4190
B-15
60
40
4030
B-28
30
40
3480
C-02
60
40
4280
C-10
70
40
4230
C-20
50
30
3910
C-26
40
40
2770
D-07
60
-
4730
D-15
30
40
3780
E-16
60
40
4570
E-23
20
30
3470
F-05
80
50*
4150
F-12
60
40
4750
F-21
30
30
4180
G-25
30
40
3430
H-01
60
40*
3550
H-05
50
30
4240
H-09
HO
40
4070
H-15
40
40
3650
H-23
30
40
3300
H-29
30
30
2750
Note:
* Readings at this location were taken with an Eberline E-120 which yields comparable
results to the L-12.
BKGD = background; reading taken outside of building.
CPM = counts per minute
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Table 5. Building 14 Floor Survey
Instrument
Grid Location L-177(CPM) L-12(CPM) L-2000(44-2 Probe)
(CPM)
BKGD
40
to
7162
A-01
60
to
20180
A-08
SO
20
19800
A-18
50
20
19510
B-17
70
to
21380
B-25
60
50
19120
C-09
80
to
21380
D-04
70
to
23620
D-12*
70
50
2t9t0
D-12**
60
to
25420
D-15
70
to
24660
D-21
70
to
23390
E-06
70
60
23810
E-24
60
to
21530
F-02
70
50
21860
F-14
60
to
24750
F-19
70
30
22310
H-04
80
to
22550
H-06
60
to
23260
H-13
70
to
23300
H-18
60
30
21110
H-2 4
50
30
20480
1-01
70
20
21230
1-15
60
50
23850
1-16
70
30
21320
3-21
50
to
23040
K-08
50
to
21870
K-14*
70
50
20780
K-14**
70
20
21240
K-19
50
20
21140
L-02
60
to
20540
L-09
60
to
19970
L-25
40
20
16270
Note:
* Asphalt
** Concrete
Where no *'s are indicated, floor was made of concrete
CPM = counts per minute
BKGD = background; reading taken out side of building
-------
Table 6. Vertical Survey Building 214
Instrument & Grid BKGD A-21* C-& C-25* 0-12 E-I8*\ E-20 C-3 H-15 H-13 H-15 1-20 1-2? 1-22 3-7 L-13
Location
I. L-2000(W-]0 Probe)
Elevation-0 it
5 it
10 it
15 ft
Ceiling
II. L-177
1. Ceiling Measurements
6260-D
6130-D
6290-D
6160-D
17010-L
20S10-L
21130-D
18520-L
21520-L
22890-L
26570-E-
17060-L
18600-L
18*»20-L
20910-L
23190-L
24380-L
26320-L
IS8S0-L
214-30-L
21200-L
23780-L
19390-1
21680-1
22670-L
2^950-L
18320-L
21M0-L
216W-L
230UO-L
19090-D
21090-D
2134C-D
22350-D
2QS0Q-U
22230-U
2 2470-U
238W-D
19S9Q-L
21470-L
22200-L
23380-U
20620-D
21350-D
21QD0-D
24 320-D
19040-D
20 970-D
22J30-D
2
-------
ceiling. The first column of measurements in the table presents background
radiation readings taken at the same heights. The results presented in the table
consistently show an increase in radiation levels with height with peak readings on
the ceiling.
To investigate the nature and location of the contamination, the ceiling and ceiling
support beams were surveyed using the L-177 pancake probe at several locations.
At these locations, the ceiling, the vertical side of the ceiling support beam, and
the base of the ceiling support beam were surveyed. The results, shown in Table 6,
show peak readings on the ceiling.
The walls of Building 214 were surveyed in three locations with the L-177 at
various heights. These measurements, presented in Table 6, show increasing
readings with height.
The roof of Building 214 was constructed of "tiles" made of a gypsum-like material.
During the survey, it was found that ceiling tiles in grids C-3 and C-ll differed in
appearance from the other tiles. Upon closer inspection it was determined that
these were replacement tiles based on their "whiter" appearance and the presence
of patching tar which had dripped to the floor. Readings were taken on these
"new" tiles and on adjacent "old" tiles. The "old" tiles were found to have higher
readings as shown in Table 7.
Table 7. Ceiling Tile Comparison, Building 214 *
Grid Location
L-2000 (44-10 Probe)
L-177
Old Tile New Tile Old Tile New Tile
C-3, inside ceiling 24,760 11,730
C-ll, inside ceiling 27,590 13,410
J-20, inside ceiling 26,970 14,250
160 40
150 50
* All readings in counts per minute.
-------
3.2 Roof Survey
Results of the vertical survey in Buidling 214 showed that the source of
contamination was apparently in the ceiling of the building. Readings were taken
on the rooftop of Building 214 to determine whether or not contamination detected
on the inside ceiling could be detected from the roof. The results showed that the
contamination was detectable on the roof.
Since it was determined that ceiling contamination was detectable from the
rooftop, the roofs of buildings in the depot were measured using Ludlum 2000's with
the **4-10 and 44-2 probe. The results of the rooftop survey are presented in Table
8. Readings in Table 8 can be put in perspective by comparing them to average
background readings of 7,162 CPM and 1,151 CPM for the 44-10 and 44-2 probe,
respectively.
3.3 Sampling Results
The results of the gamma spectroscopy appear in Table 9. These analyses showed
concentrations of the three major gamma emitting radionuclides in the naturally
occurring uranium-238 (U-238) chain ranging from 25.9 to 39.6 picocuries per gram
(pCi/g). These same radionuclides, radium-226, lead-214, and bismuth-214 were
observed at about background concentrations of 1 pCi/g in the floor and soil
samples. Concentration of the naturally occurring radionuclides of the thorium-
232 chain: Iead-212, actinium-228, and thallium-208, were detected at about
background level of 1 pCi/g. Trace amounts of cobalt-60 were present in one roof
tile sample and the floor sample.
Alpha spectroscopy results are also given in Table 9. The concentrations of U-238
and thorium-230 (Th-230), measured through alpha spectroscopy, are expected to
be about the same as for the concentrations of other members of the U-238 chain
previously discussed. Little or no U-238 and Th-230 were detected in the samples.
This may be because the chemical extraction required for alpha spectroscopy was
not effective in removing these radionuclides from the building materials analyzed.
-------
TableS. Rooftop Survey
Building No.
Probe No.
CPM
Location
Observations
S-ll
14
15
16
17
18
19
22
S-23
S-25, S-26, 200
44-10
44-10
44-10
6,820 Southeast corner
18,490 Middle section, inside at 6 ft.
from ceiling
19,320 Inside, 5 ft. from ceiling
Appears to be wood construction from
outside observation
Gravel covered roof, old construction
Appears to be wood construction
Reading taken from top of stairway
Appears to be wood construction
Appears to be wood construction
Appears to be wood construction
Appears to be wood construction
Ceiling constructed with painted
tiles as in Building 214.
Appears to be wood construction
Appears to be wood construction
* No reading possible
= Not applicable
CPM = Counts Per Minute
-------
Table 8. Rooftop Survey (Continued)
Building No.
Probe No.
CPM
Location
Observations
202
*
Appears to be wood construction
203
44-10
7,260
North end of west wall
Wooden roof construction
205
44-10
7,610
Southwest corner
Reading taken on roof of what
appeared to be an additon
205
205
44-10
44-10
24,380
27,780
Inside at ceiling, Grid C-9
Inside at ceiling, Grid D-3
Roof not accessible
Tile roof construction
206, 207, 208
*
Wooden roof construction
209, 210
*
Wooden roof construction, EPA office
building
211
44-10
7,790
North end, west wall
Wooden roof construction
212
44-10
19,850
20,450
19,480
21,490
South end, west wall
North end, west wall
North end, east wall
South end, east wall
Tile ceiling construction as in
Buildings 205 and 214
214
44-10
21,570
22,820
South end, east wall
South end, east wall
Tile ceiling construction
215
44-10
23,000
22,220
22,960
South end, east wall
North end, east wall
North end, west wall
Tile ceiling construction as in
Building 205 and 214
* No reading possible
= Not applicable
CPM = Counts Per Minute
-------
Table 8. Rooftop Survey (Continued)
Building No.
Probe No.
CPM
Location
Observations
228
23 4
S-235
238
241
245
246
255
256
44-10
44-10
44-2
44-2
44-2
44-2
44-2
25,310 Inside, ceiling of 1st floor
15,380 Inside, 8 ft. above ground
3,340
1,550
North side
East side
1,210 West side
1,530 Inside, 8 ft. high
1,590 Inside, from ladder top
810 South side
870 South side
1,060 North side
1,050 North side
920 South side
900 South side
880 North side
960 North side
Two story building. Second story
appears to be wooden addition.
Possibly used as a firehouse
Tile ceiling, approximately 30 ft.
high
Wood construction
Tile roof construction as in 214
Shingled roof construction
Tile roof construction as in 214.
Ceiling too high for access
Tile roof construction as in 214.
Ceiling too high for access
Tile roof construction as in 214
Tile roof construction as in 214
* No reading possible
= Not applicable
CPM = Counts Per Minute
-------
Table 9
GSA, Raritan Depot
Edison, New Jersey
Sample Results for Buildig 214
January 9, 1986
Sample Identification
Matrix
Units
NJP6-R1
Solid
pCi/g + 2SD
NJP6-R2
Solid
pCi/g + 2SD
NJP6-R3
Solid
pCi/g t 2SD
NJP6-R4
Solid
pCi/g _t 2SD
N3P6-R5
Solid
pCi/g ~ 2SD
NJP6-R6
Solid
pCi/g ~ 2SD
NJP6-R7
Solid
pCi/g ~ 2SC
Type of Analysis:
Thorium-230
<0.05
<0.05
< 0.05
<0.05
< 0.05
< 0.05
< 0.05
Uranium-238
< 0.05
0.26 + 0.03
<0.05
0.56 ~ 0.04
0.99 ~ 0.06
0.10+0.02
< 0.05
Gamma Spectralanalysis:
Radium-226
Lead-212
Lead-214
Actinium-228
Thallium-208
Bisinuth-214
Cobalt-60
32.30 + 0.02
1.07 + 0.08
39.60 ~ 0.20
3.01 ~ 0.17
0.69 + 0.04
36.50 + 0.10
ND
30.10 + 0.20
0.64 + 0.07
34.90 + 0.20
0.42 ~ 0.04
2.18 +0.13
35.30 ~ 0.20
ND
29.40 x 0.30
1.13 ~ 0.08
35.50 7 0.20
3.21 ~ 0.16
0.75 * 0.04
33.60 * 0.80
ND
29.40 t 0.20
1.16 ~ 0.09
34.60 + 0.20
3.13 ~ 0.17
0.76 ~ 0.04
33.00 ~ 0.70
ND
25.90 + 0.20
1.19 + 0.09
29.80 + 0.20
3.34 7 0.16
0.78 * 0.05
31.00 ~ 0.70
0.21 ~ 0.03
1.44 + 0.04
0.84 + 0.03
1.15 ~ 0.04
2.08 + 0.07
0.52 + 0.02
3.25 + 0.12
0.05 + 0.01
1.33 ~ 0.03
1.14 + 0.03
1.17 + 0.03
1.87 + 0.06
0.51 + 0.02
1.21 + 0.11
ND
Note:
pCi/g = picocuries per gram
ND = none detected
SD = standard deviation
-------
3.4 RPISU Results
The results of the RPISU sampling appear below in Table 10. Working levels ranged
from 0.00712 at location C-21 in building 205 to 0.07672 at location A-3 in Building
205. The working level in Building 214 was 0.01428.
Table 10. RPISU Results, Buidlings 205 and 214
SAMPLING ID WORKING LEVEL* LOCATION
EB001 0.07672
EB002 0.00712
EB003 0.01438
Building 205, Grid A-3
Building 205, Grid C-21
Building 214, Grid L-16
The Working Level* is defined as the potential alpha energy from the
shortlived daughters of radon which will produce 1.3 x 10^ MEV (MEV =
Million Electron Volts) in one liter of air.
-------
4.0 FINDINGS
The radiation surveys of Buildings 205 and 214, along with the rooftop survey of
other GSA, Raritan Depot buildings, indicated radiation levels that were higher
than natural background radiation. From this study the natural background
radiation level in the GSA, Raritan Depot was found to be about 8.7 micro-R/hr or
about 76 milli-R/year. Oakley (1972) calculates an ionizing radiation dose
equivalent of 78.9 milli-R/year for New Jersey including a terrestrial component of
43.5 milli-R/year (excludes neutron component). Although Oakley's values
represent averages covering wide geographical areas, the measured ambient
radiation level of 76 milli-R/year for the GSA, Raritan Depot area agrees with
Oakley's observations.
Dose rates inside of Buidlings 205 and 214 ranged from 8.7 micro-R/hr to 22.3
micro-R/hr, or 76 milli-R/year to 195 milli-R/year. The field survey indicated the
source of radiation to be the gypsum-like ceiling tiles. Based on visual
observations and readings taken during the roof top survey, in addition to building
214, these gypsum tiles, with elevated levels of U-238 chain radionuclides, are
present in buildings 15, 22, 205, 212, 215, 228, 234, and 238. Based on visual
observation only, buildings 245 and 246 probably also contain these tiles, but their
roofs were not accessible for the survey team to confirm this. Based on visual
observation and readings taken during the survey, buildings S-ll, 203, 205, 211,
238, 241, 255, and 25.6 do not contain tiles with elevated levels of U-238 chain
radionuclides. Additionally, visual observation indicates these tiles are not present
in buildings 5, 14, 16, 17, 18, 19, S-23. S-25, S-26, 200, 202, 206, 207, 208, 209, 210,
and S-235,
The Laboratory analyses of samples of the building materials concur with the
results of the radiation survey. They indicate the source of the elevated radiation
levels is naturally occurring U-238 chain radionuclides in the gypsum-like roof
material. The concentrations of the U-238 radionuclides detected in the ceiling
tiles are 15 to 35 times higher than the levels found in typical surface soils of this
area. They are also 15 to 35 times lower than the concentrations expected in
uranium processing wastes. The clean up standard for uranium processing sites, as
established in title 40 of the Code of Federal Regulations, part 192, subsection B,
is 5 pCi/g.
-------
Working levels inside Building 205 ranged from 0.00712 of at grid C-21 to 0.07672
at grid A-3. The working level in building 21 ^ was 0.01428. On December 6, 1983,
the Public Health Advisory for Montclair/Glen Ridge, NJ deemed no action
necessary for homes with a working level of 0.02 or less.
-------
Reference
Oakley, D.C. National Radiation Exposure in the U.S.. ORP/SID 72-1, Office of
Radiation Programs, U.S. EPA, Washington, D.C., June 1972.
-------
year
J CORPORATION
RARITAN PLAZA III. FIELOCREST AVENUE
EDISON. NEW JERSEY OB037
am -225-61 BO
C-584-03-86-50
March 6, 1986
Ms. Diana Messina
U.S. Environmental Protection Agency
Region II
Edison, New Jersey 08817
Dear Ms. Messina:
On February 19 and 20, 1986 three Radon Progency Integrated Sampling Units
(RPISU) were installed in buildings 205 and 214 located in the Raritan Depot as
shown in Figure 1.
RPISU's 1167-E and 52-E were installed in building 205 on February 19, 1986 at the
locations shown in Figure 2. Station EB001 is located in a portion of the building
with minimal ventilation. There are no windows in this area of building 205 and
doors are padlocked shut. Station EB002 is located in an area of the building that
is well ventilated. There are several broken windows on the west wall, entrance
doors are commonly open and a skylight, although closed, may allow some
ventilation through the roof. The RPISU's were removed from building 205 on
February 24, 1986.
A portable gillian pump (//12098) was installed on February 20, 1986 in building 214
at the location shown in Figure 3. The sampling area was partially ventilated. The
swinging metal entrance could not be completely closed and a two foot square hole
was observed in the ceiling. The sampling device was removed on February 21,
The sampling results are shown in Table 1. Working levels ranged from 0.00712 at
location EB002 in building 205 to 0.07672 at location EB001 in building 205. The
working level is building 214 was 0.01428.
Very truly yours,
1986
JBT/jm
A Halliburton Company
-------
OPEN SEWER
INDUSTRIAL ROAD
ABANDONED
BLDQ.
FORMER
DEMOLITION
AREA
OIL TANK
¦POSSIBLE DISPOSAL AREA
FIGURE 1
SITE MAP
GSA, RARITAN DEPOT, EDISON, N.J.
(NOT TO SCALE )
IMUS
I CORPORATION!
o A Halliburton Company
-------
35 34 33 32 31 30 28 28 27 26 25 24 23 22 21 20 19 18 17 IS IS M 13 12 11 M 8 8 7 6 S 4 3 2 1
LEGEND:
¦ R.PJ.S.U. LOCATION
£3non VENTILATED
P3 VENTILATED
R.P.I.S.U. LOCATION MAP
BUILDING 205
GSA, RARITAN DEPOT, EDISON, N.J.
FIGURE 2
IMUS
CXDRPORATOSJ
o A Halliburton Company
-------
I
25 24 23 22 21 20 IB 16 17 16 16 14 13 12 11 10 9 6 7 6 6 4 3 2 1
LEGEND:
¦ R.PJ.S.U. LOCATION
NON VENTILATED
FIGURE 3
R.P.I.S.U. LOCATION MAP
BUILDING 214
GSA, RARITAN DEPOT, EDISON, N.J.
PRIMUS
I CXDRPORATOSJ
o A Halliburton Company
-------
TABLE 1
RPISU RESULTS
GSA, RARITAN DEPOT
EDISON, NEW JERSEY
02-8506-08
2/19/86 - 2/24/86
SAMPLE ID. WORKING LEVEL LOCATION
EB00I
EB002
EB003
0.07672
0.00712
0.01438
Building 205, Grid A-3
Building 205, Grid C-21
Building 214, Grid L-16
------- |