ML20148S472
| ML20148S472 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 03/31/1988 |
| From: | Cotten P OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20148S452 | List: |
| References | |
| CON-FIN-A-9076 ORAU-88-C-44, NUDOCS 8804180460 | |
| Download: ML20148S472 (65) | |
Text
_
ORAU 88/C-44 dx Prepared by Oak Ridge Associated CONFIRMATORY SURVEY Universities Prepared for Qf U.S. Nuclear
$$*i s!!n s PHASE 11 DECOMMISSIONING Region V Office Sponsored by FORMER WASTE PROCESSING FACILITY Division of
$ee"icai Eu*c"ieer Safety MEWWWG8 d'*
d SAN DIEGO, CALIFORNIA P. R. COTTEN
{
(
Radiological Site Assessment Program Manpower Education, Research, and Training Division FINAL REPORT MARCH 1988
=,= m
}
c non
r y
I CONFIRMATORY SURVEY OF PHASE II DECOMMISSIONING FORMER WASTE PROCESSING FACILITY I
CA TECliNOLOGIES SAN DIEGO, CALIFORNIA I
Prepared by P.R. COTTEN Radiological Site Assessment Program Manpower Education, Research, and Training Division I
Oak Ridge Associated Universities Oak Ridge, TN 37831-0117 I
Project Staff J.D. Berger R.C. Rookard R.D. Condra T.J. Sowell D.A. Gibson C.F. Weaver C.L. ffurphy Prepared for Division of Industrial and Medical Nuclear Safety U.S. Nuclear Regulatory Commission Region V Office Final Report
'tarch 1988 I
This report is based on work performed under Interagency Agreement DOE I
No. 40-816-83 NRC Fin. No. A-9076 between the U.S. Nuclear Regulatory Commission and the U.S.
Department of Energy.
Oak Ridge Associated Universities performs complementary work under contract number DE-AC05-760R00033 with the U.
S.
Department of Energy.
I
I l
i TABLE OF CONTENTS
}
Lau
\\
List of Figures 11 i
List of Tables iii Introduction and Site History..
1 Site Description
?
P,oceeures 2
Results 6
Comparison of Survey Results with Guidelines 9
I Summary.
10 4
g R.f., enc.s e
Appendices Appendix A:
liajor Sampling and Analytical Equipment Appendix B:
Ifeasurement and Analytical Procedures Appendix C:
Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material Appendix D:
Decommissioning Guidelines for the GA Technologies I
Uaste Processing Facilities I
\\
I i
E I
I I
i
)
I LIST OF FIGURES Page FIGURE 1: !!ap of San Diego Area, Indicating the Location of the GA Technologies Facilities.
11 FIGURE 2:
GA Technologies Plant Layout 12 FIGURE 3:
Area of CA Technologies Plant, Included in Phase II Decommissioning.
13 FIGURE 4:
Phase II Decommissioning Areas of the Former Uaste Processing Facility.
14 FIGURE 5:
By-Products Storage Building Layout, Indicating the Raference Grid System and Locations of Contamination
?feasurements on the Floor and Lower Walls.
15 FIGURE 6:
Carage/0ffice Building Layout, Indicating the Reference and System and Locations of Contamination ?teasurements on the Floor and Lower Walls.
16 FIGURE 7:
ifeasurement Locations on Other Surfaces in the i
By-Products Storage Building.
17 FIGURE 8:
ifeasurement Locations on Other Surfaces in the Garage / Office Builing.
18 FIGURE 9:
Phase II Area, Indicating the 30 ft Grid System Used for Survey Reference 19 FIGURE 10: Locations of Surface Contamination ?!easurements and Samples from Pads and Foundations.
20 FIGURE 11: Locations of Background tieasurements and Baseline Soil Samples From the Vicinity of CA Technologies.
21 FIGURE 12:
l Area on the By-Products Storage Building Floor, Identified By Surface Scans.
22 FIGURE 13: Locations of Elevated Direct Radiation, Identified by Surface Gamma Scans.
23 I
~
I I
I 11 I
LIST OF TABLES I
TABLE 1:
Background Radiation Levels.
24 TABLE 2:
Baseline Radionuclide Concentrations in Soil 25 TABLE 3:
Summary of Surface Contamination Measurements in the By-Products Storage and Garage / Office Buildings 26 TABLE 4:
Exposure Rates Measured at 30 ft Grid Intervals 27 TABLE 5:
Exposure Rates Measured in the Incinerator Pad Area.
32 TABLE 6:
Direct Radiation Levels Measured on Concrete Pads 33 I
TABLE 7:
Exposure Rates Measured After Remediation of Areas Identified By Surface Scans.
34 TABLE 8:
Summary of Surf ace Contamination Measur sments - Concrete Pads and Foundations.
35 TABLE 9:
Radionuclide Concentrations in Surface Soil Samples from 30 ft Grid Intervals.
36 TABLE 10: Radionuclide Concentrations in Soil Samples Collected From the Incinerator Pad Area.
40 I
TABLE 11: Radionuclide Concentrations in Soil From Beneath Concrete Pads 41 TABLE 12: Radionuclide Concentrations in Surface Soil Samples Collected I
Following Remediation of Areas Identified by Surface Scans.
42 TABLE 13: Radionuclide Concentrations in Composite Soil..
43 TABLE 14: Radionuclide Concentrations in Miscellaneous Samples.
44 I
I I
iii
I CONFIRMATORY SURVEY I
l 0F PHASE II DEC0FetISSIONING FORttER WASTE PROCESSING FACILITY I
CA TECHNOLOGIES SAN DIEGO, CALIFORNIA INTRODUCTION AND SITE HISTORY In mid 1984, CA Technologies (CA) of San Diego, California, initiated decommissioning activities for the purpose of releasing portions of its facilities from Nuclear Regulatory Commission (NRC) licensing restrictions.
Potential radiological contaminants at GA have been identified as enriched uranium, thorium, and longer half-life fission and activation products.
Decommissioning of these facilities was separated into three phases.
Phase I activities, which encompassed the Solar Evaporation Pond Area, the areas immediately surrounding the former Uaste Processing Facility and the Incinerator Pad, a previous burial site for contaminated asphalt, the hillside and canyon below the waste handling facilities, and undeveloped land surrounding the waste processing facilities, were completed in late 1985.
A confirmatory survey, performed by Oak Ridge Associated Universities in December 1985, identified small isolated areas in need of additional remedial action.1 These areas have been addressed and discussed in a separate report.
Phase II consists of two major areas, the former Uaste Processing Facility and the Incinerator Pad.
Phase III consists of approximately I
87 hectares (215 acres) of primarily undeveloped land, surrounding the main GA Technologies plant site:
survey findings of these areas have also been described in a separate report.3 During July and August 1987, CA conducted decommissioning activities of the Phase II facilities.
A report of CA's findings, issued in August 1987, indicates I
that the post-decontamination radiological conditions satisfy the NRC guidelines for decommissioning."
At the request of the NRC, Region V Office, the Radiological Site Assessment Program of Oak Ridge Associated Universities (0RAU) conducted a radiological survey in September, 1987 to confirn the status of the Phase II area, relative to the NRC criteria for release for unrestricted use.
I I
I
SITE DESCRIPTION I
The GA Technologies facilities are located near the intersections of Interstate 5 and Genesee Road, approximately 20 km north of San Diego, CA (Figures 1 and 2).
Site activities include a wide variety of research and development programs.
The Phase II area, shown in Figure 3, is reached via the main access road from the plant entrance gate.
This area includes the Waste Processing Facility, consisting of the upper and lower storage yards, and the I
Incinerator Pad site (Figure 4).
Much of this area is paved with asphalt; also included are a truck scale and several concrete pads or foundations.
Some of the original paving :nd pads have been removed during the decontamination operations.
Located in the lower storage yard are two s, mall buildings the By-Products Storage Building and the Garage / Office Building. The By-Products Storage Building was utilized for sample preparation and storage before and during decommissioning activities.
The garage area of the other building was also used for short-term storage of radioactive materials.
The buildings are of simple construction; the By-Products Storage Building is constructed of corrugated metal and the i
Garage / Office Building is of wood frame.
Both buildinga have concrete floors.
PROCEDURES A survey of the Phase II Decommissioning area was performed by the Radiological Site Assessment Program of ORAU during September 9-28, 1987.
This I
survey was in accordance with a survey plan submitted to the Region V Of fice of the NRC.5 kfethods and procedures utilized in the survey are presented in this section.
Objectives The objectives of the survey were to confirm that the radiological condition of the Phase II area was as presented in the CA Technologies report and to provide information and data for evaluation of the site status, relative to NRC guidelines
)
for release for unrestricted use.
Radiological information collected included gamma exposure rates; location of elevated direct radiation levels; concentrations l
of radionuclides in surface soil; and surface contamination levels.
I I
2 l
j r
E Procedures I
Document Review The licensee's final survey report for the release of the Phase II area for unrestricted use and supporting documents were reviewed by ORAU.
Data presented in these reports were compared to the established release guidelines.
E 9uilding Survey I
Gridding An alphanumeric 6 ft (1.8 m) x 6 ft (1.8 m) reference gric was established on the floor and lower walls (up to 6 ft (1.8) in each building.
The grid baseline coordinates (A,0) were located in the southwest corner of each building.
Figures 5 and 6 show the building layouts and reference grid systems used for this survey. Measurements on the upper walls and ceilings were referenced to the floor grid designation.
I Surface Scans Alpha, beta gamma, and gamma scans were performed on floors, using an alpha / beta gas proportional floor monitor and NaI(TI) gamma scintillation detectors with audible indicating scaler /ratemeters.
Scans of surfaces not accessible to the floor monitor, i.e.,
walls, ceilings, and overhead areas such as ledges, beams, piping, fixtures, and equipment were performed using portable ZnS alpha scintillation detectors and "Pancake" GM beta gamma detectors.
Areas indicating elevated radiation levels were marked for additional decontamination I
and for further measurements.
Measurement of Surface Contamination 1.evels Approximately 20% of the grid blocks on the floor and lower walls of each building were randomly selected for surface contamination measurements.
Blocks selected for these measureuents are indicated on Figures 5 and 6.
In each grid block surveyed, direct measurements of alpha and beta-gamma contamination levels were systematically performed at the center and four equidistant points, midway I
between the center and block corners.
Smears for removable alpha and beta I
E I
contamination were performed at that location in each grid block, where the highest direct level was obtained.
Seven locations on upper walls, ceilings, fixtures, and equipment were selected for single point measurements of total and removable alpha and beta gamma contamination levels.
These locations are identified on Figures 7 and 8.
Direct measurements and/or smears were also obtained from elevated locations identified by surface scans.
I Outside Area Survey Gridding In the upper and lower storage yards the licensee's 10 ft (3.0 m) grid system was reestablished at 30 f t (9.1 m) intervals (Figure 9) and the licensee's 3 ft (0.9 m) grid was used on the Incinerator Pad.
I Surface Scans U31kover gamma surface scans were conducted at I to 2 m intervals in the upper and lower storage yard and on the Incinerator Pad, using portable NaI(Tl) gamma scintillation detectors and ratemeters.
The exposed surface of the wall; separating the upper and lower storage yards, was scanned using a "Pancake" GM detector coupled to a ratemeter.
Scans of concrete pads and some larger areas of asphalt paving were performed using the alpha /teta gas proportional floor monitor.
Locations of elevated radiation identified by the scans, were brought to I
the licensee's attention and marked for further evaluation.
Exposure Rate Measurements I.
Exposure rate measurements were made at the surface and at 1 m above surface at 30 ft (9.1 m) intervals in unpaved areas of the former Waste Processing Facility, at seven locations in the Incinerator Pad area, and at locations of elevated direct radiation, identified by the surface scans.
Portable ganma
{
scintillation detectors, calibrated onsite against a pressurized ionization I
chamber, were used for these measurements.
4 I
I Measurement of Surface Contamination Levels I
Total and removable alpha and beta-gamma contamination levels were measured at nine locations, on the concrete pads (Figure 10).
Sampling Surf ace (0-15 cm) samples were collacted f rom areas of exposed soil at 30 ft I
grid intervals throughout the area and at locations identified by sttef ace scans.
Following further cleanup by the licensee, followup soil samples were obtained.
Concrete coring was performed at the location on each concrete pad, where the highest direct measurement was obtained.
These locations are indicated on Figure 10.
Canna monitoring of the soil beneath the removed core was performed to identify the presence of elevated radiation levels and soil samples were collected from the exposed surface.
A sample of residue was also collected from a drain near the By-Products Storage Building (Figure 10).
I 9ackcround and Baseline Measurements During a previous site visit, measurements and soil samples were obtained in the vicinity of the CA Technologies plant to determine area background levels and baseline radionuclide concentrations for comparison purposes.
Locations of the background measurements and baseline samples are shown on Figure 11.
Tables 1 and 2
present the background exposure rates and baseline radionuclide concentrations, respectively.
I Sample Analyses and Interpretation of Results Samples were returned to laboratories in Oak Ridge, Tennessee, for analyses.
All soil and residue samples were analyzed by gamma spectrometry.
The major radionuclides of interests were Cs-137, Co-60, U-235, U-238, Th-228, Th-232, and Ra-226; however, spectra were reviewed for the presence of other significant l
photopeaks.
Selected individual samples and composite samples were also analyzed for Sr-90 and isotopic uraniun.
Smears for the determination of removable I
contamination were analyzed for gross alpha and beta concentrations.
I 5
'I
I Additional information concerning analytical equipment and procedures is contained in Appendices A and B.
Results of this survey were compared to the guidelines, established by the NRC, for decommissioning of the GA Technologies Uaste Processing Facility.
These guidelines are presented in Appendices C and D.
RESULTS Document Review ORAU's review of the survey report submitted by GA to the NRC, indicates that the procedures and instrumentation used were consistent with industry accepted practices.
Sampling conducted by CA was primarily from the waste processing area, where contaminated soil was stored awaiting shipment, and in several locations where the potential for contamination was the highest, based on previous facility use history.
The data developed by CA are within the NRC guidelines established for this decommissioning activity.
Building Survey Surface Scans Surface scans identified an area of residual contamination on te floor of the By-Products Storage Building.
This location is indicated on Figure 12.
According to site personnel a spill had occurred at this location during facility ope ra t icr.a.
No additional areas of elevated radiation were noted inside the buildings.
Surface Contamination Measurements Table 3 summarizes the results of surface contamination measurements in the two buildings.
The total contamination data presented in this table are direct measurements which include removable and non-removable activity.
Total contamination levels in the By-Products Storage Building were higher than in the Carage/ Office Building because the building had been used for sample preparation I
before and during decommissioning.
At the floor location in the By-Products Storage Building identified by the surface scan, the highest total alpha and 2
2 beta-gamma levels were 10,600 dpm/100 cm and 17,800 dpm/100 cm, respectively.
6 E
l
I 2
2 These levels were reduced to <27 alpha dpm/100 cm and 820 beta gamma dpe/100 cm,
after additional remedial actions by the licensee.
At other locations in this 2
building the individual alpha measurements ranged from <27 to 890 dpm/100 cm and 2
the individual beta gamma measurements ranged from (470 to 3600 dpm/100 cm,
Total alpha and beta gamma contamination levels in the Carage/Of fice Building were I
generally less than the detection sensitivity of the instruments.
Levels for 2
2 alpha and beta-gamma ranged from <27 dpm/100 cm to 130 dpm/100 cm and 2
2
<470 dpm/100 cm to 2550 dpm/100 cm, respectively.
Removable alpha and beta contamination levels were also generally less than the mea sure me nt sensitivity.
The highest level of removable alpha activity 2
detected was 27 dpm/100 cm, on the floor in By-Products Storage Building; the 2
highest beta level was 12 dpm/100 cm, on the floor in the Carage/ Office Building.
Outside Area Survey Surface Scans I
Eight areas of elevated direct gamma radiation were identified by the surface scans.
These areas are shown on Figure 13.
The icensee performed additional remedial action at these locations and follow-up scanning indicated that cleanup of these locations had been effective in removing the contaminant.
Exposure Rate Measurements Table 4 presents the results of exposure rate measurements at 30 ft (9.1 m)
I grid intervals.
Levels ranged from 11 to 16 pR/h at I m above the surface and from 11 to 21 pR/h at surface contact.
The highest levels were at grid coordinate 7300N, 9560E.
Levels in the area of the Incinerator Pad ranged f rom 15 to 20 LR/h at 1 o above the surface and from 16 to 28 pR/h at surface contact.
The highest levels were at grid coordinate 7585N, 9722E.
Results are presented in Table 5.
Exposure rates on the concrete pads ranged from 13 to 16' pR/h at I m above the surface and from 15 to 18 pR/h at contact (Table 6).
After further remediation of areas identified by surface scans, exposure I
rates were measured at each location.
The maximum exposure rate measured was 20 pR/h at 1 m and 21 pR/h at the surface. The results of these measurements are presented in Table 7 7
l
I Surf ace Contamination Measurements Table 8 summa rizes surface contamination measurements on concrete pad foundations.
Total contamination levels for alpha and beta-gamma ranged from 2
2 2
2
<27 dpe/100 cm to 1550 dpm/100 cm and from 1240 dpm/100 cm to 5390 dpm/100 cm,
respectively.
Removable contamination levels were generally less than the detection sensitivity of the instrument.
I Radionuclide Concentrations in Soil Concentrations of gamma emitting radionuclides, measured in surface soil samples from 30 ft (9.1 m) grid intervals, are presented in Table 9.
Ranges of concentrations were:
Co-60, <0.03 to 0.90 pCi/g; Cs-137, <0.02 to 9.54 pCi/g; Ra-226, 0.44 to 2.23 pCi/g; U-235, 0.05 to 1.26 pCi/g; U-238, 0.3 to 3.9 pCi/g; Th-228, 0.47 to 2.80 pCi/g; and Th-232, 0.41 to 2.70 pCi/g.
Radionuclide concentrations in samples from the Incinerator Pad area are presented in Table 10.
The highest levels of gamma emitting radionuclides measured in these I
samples were:
Co-60, 1.37 pCi/g; Cs-137, 19.28 pCi/g; Ra-226, 1.74 pCi/g; U-235, 0.66 pCi /g,;
U-238, 1.31 pCi/g; Th-228, 2.11 pCi/g, and Th-232, 2.26 pCi/g.
Radionuclide concentrations in soil samples obtained from beneath concrete pads (Table 11) were in the ranges of concentrations in baseline soil.
Table 12 presents the concentrations in samples from locations identified by surface scans, collected following further remedial action by the licensee.
Maximun concentrations in these samples were Co-60, 1.77 pci/g; Cs-137, i
15.62 pCi/g; Ra-226, 1.32 pCi/g; U-235, 0.88 pCi/g; U-238, 2.1 pCi/g; Th-228, 2.64 pCi/g; and Th-232, 2.53 pCi/g.
I Results of Sr-90 and isotopic uranium analyses performed on three composite samples, are presented in Table 13.
The highest concentration of Sr-90 was 1.46 pCi/g in composite sample B.
Isotopic uranion concentrations were 1.53 to 3.83 pCi/g of U-234; 0.05 to 0.16 pCi/g of U-235; and 1.04 to 2.19 pCi/g of U-238.
A soil sample, collected from beneath the concrete floor of the By-Products Storage, contained con entrations in the ranges of baseline soll.
Data are presented in Table 14 I
8
I
?tiscellaneous Samples Table 14 also presents the results of analyses on samples of drain residue and a piece of asphalt from the location on the Incinerator Pad, exhibiting an elevated gamma level.
The Cs-137 level in the drain residue (2.41 pCi/g) was slightly elevated above baseline concentrations.
Other radionuclide concentrations in the two samples did not differ from typical baseline levels.
I COMPARISON OF SURVEY RESULTS WITH CUIDELINES Cuidelines for decommissioning the Former Uaste Processing Facilities of GA Technologies are presented in Appendices C and D.
Surface contamination limits, based on primary contaminants of Uranium, Cs-137, and Co-60, identified on this site, are:
Alpha I
2 2
5000 dpm/100 cm, averaged over 1 m 2
2 15000 dpm/100 cm, maximum in 100 cm 2
1000 dpa/100 cm, removable
)I Beta-Camma I
2 2
5000 dpm/100 cm, averaged over 1 m 2
2 15000 dpm/100 cm, maximum in 100 cm 5
2 1000 dpm/100 cm, ramovable Surveys of the two remaining buildings and concrete pads indicate that the surfaces satisfied these guidelines, with the exception of one small area on the floor of the By-Products Storage Building.
Additional remedial action reduced this location to within the guideline levels.
Exposure rate guidelines limit the level at 1 m above the surface to 10 LR/h, above background, over an area of 30 ft (9.1 m) x 30 ft (0.1 m) or greater; the I
guideline level for smaller areas is 20 LR/h above background.
At the GA Technologies Site, the total exposure rate guidelines are 19.7 LR/h and 29.7 LR/h, i.e.,
10 pR/h and 20 uR/h, respectively, plus the average background level of I
I 9.7 UR/h (from Table 1).
One area, at the Incinerator Pad had an associated exposure rate of 20 pR/h at 1 m above the surface.
Although this is slightly above the 19.7 pR/h average for areas in excess of 30 ft x 30 ft, this radiation was limited to a small isolated area and the exposure rate was less than 20 pR/h above background.
All other measurements were well below 19.7 uR/h. The external exposure rate target guideline has theref ore been satisfied.
I Most samples collected from the site had radionuclide concentrations in the ranges of typical baseline soils from the La Jolla area.
Only two samples contained radionuclide levels in excess of the guideline.
One of these was a I
sample of soil f rom grid coordinate 7270N, 9543E; this sample, from an area of elevated direct radiation identified by surface scans, contained 15.62 pCi/g of Cs-137, as compared to the guideline level of 15 pCi/g.
The other sample containing a concentration above guideline levels was f..m the Incinerator Pad
)
area; this sample contained 19.28 pCi/g of Cs-137. At both of these locations the extent of contamination is limited to small isolated areas, based on results of surface gamma scans.
Also, the exposure route from Cs-137 in surface so'l is direct radiation; exposure rates measured at these locations were within guideline limits.
The elevated Cs-137 concentrations, when averaged across adjacent land I
areas would be well within the 15 pCi/g guideline. Radionuclide concentrations in the soil therefore satisfy the guidelines established for this decommissioning 1
project.
SU"MARY At the request of the tJRC Region V Office, on September 7-28, 1988, Oak Ridge Associated Universities performed a
confirmatory survey of Phase II Decommissioning at GA Technologies, Inc. in San Diego, California.
The survey I
included
- gamma, beta-gamma, and alpha scans; exposure rate measurements; measurements of total and removable surface contamination; and measurements of radionuclide concentrations in soil. The survey identified several small areas of residual contamination, which were promptly reeleaned by the licensee and resurveyed by ORAU.
Although there are several isolated locations of residual low-level soil contamination, the size of the involved areas and the associated levels are such that the concentrations can be averaged and the guidelines satisfied.
It is theref ore ORAU's opinion that the decontamination efforts by the licensee have been effective in meeting the radiological conditions established I
for release of this site for unrestricted use.
10
GAT 4 MA PACIFIC CO AS T H WY.
/
GA TECHNOLOGIES f'
FACIUTIES i
p GENESEE AVE.
E F6UNik RSITY
\\
I
((
LA #ALA PA C/r/C PACIFIC OCEAN BEACH l
MISSION
, BEACH e
I e\\
I SAN EGO a
M'LES d
i i l I I I I I i 0
2 4
6 8
KILCMETERS I
FIGURE 1:
Map of San Diego Area, Indicating the Location of the GA Technologies Facilities 11 I
GAT 7 5
0 1000 METERS GA TECHNOLOG ES BOUT AY
'(
n
, l}
- L'4e N s
e
([s%
$s e
kr r
s
'!)
N\\
=
i FIGURE 2:
GA Techologies Plant Layout n
y
GAT 7b N
I i
i 0
1000 METERS l
9t..
WASTE PROCESSING i
i FACilliY
)
I L
\\'
//l
, - QF"
~
- T I
200 3'
f
/ 'f
}
4
,. Q. y=
g 1
g }
300 F
CENgggg%
l 8
W I
W%
q
"\\
100 FOOT ELEVATION CONTOURS (RELATIVE TO SEA LEVEL) jl FIGURE 3:
Area of GA Technologies Plant, included in j
Phase 11 Decommissioning 13 iE i
i l
1 I
I 4
i G A T) 40 lI l
ll l
ACCESS ROAD
/
4 i
1 i
1 l
il g
FORMER SOLAR l
EVAPORATION pot 4DS
@E l
D l
7 o' @
LL t' x j
r l
l N\\
N l
N\\
/
\\
g/
ACCESS ROAD l
N
/
h i
i
@ Waste Processing fccihty and Lower Storage Yord l
I
@ G4 oge/ Office Building
@ By-Products Stc;oge Building i
@ Embonkrnent Wall Below the Upper Storoge Yord FEET l
0 100 t
j
@ Upper Storage Yord l
7
@ Moin Access Road I
O M
METERS
@ incirierotor Pod l
i I
FIGURE 4:
Phase 11 Decommissioning Areas of the Former Waste Processing Facility
.\\
l
l l
l r
GAT 13 i
l i
i l
l/
0 6
12 18 24 30 j
77 -
--/A B
/
I C
'y w
CW D
1 i
GRID BLOCKS
/'
SURVDED WN 1
o 6
l l
l FEET j
FIGURE S: By-Products Storage Building Layout, Indicating the Reference Grid System and Locations of Contemination Measurements on the Floor and Lower Walls
)
CAT 12 l
i l
/
0 6
12 18 24 30 36 l// /,
V},
lk
//)
/4 i
'/
GARAGE OFnCE j
2 //;
4
= 4
\\
. /////////
////-
-n i
i i
FEET FIGURE 6:
Garage / Office Building Layout, Indicating the Reference and System and Locations of Contamination Measurements on the Floor and Lower Wolls
W W
M M
M M
M M
M M
M M
M M
W W
W W
W l
I i
l l
GAT 130 l
l l
l I
\\
\\
I i
l i
?
i i
l 0
6 12 18 24 30 I
A g
A J
B JL l
i j
C C
i i
D 1
MEASUREMEtJT LOCATICrJS l
9 CDUf4G l
l UGHT FlxTURES g
[
l At;D EOU;PLEt4T i
wrt O
6 i
i f
FEET t
a i
i FIGURE 7: Measurement Locations on Other Surfaces in the By-Products Storage Building I
_... _ ~ _ -.. - -.
_. -. ~ -
M M
M M
M M
M M
M M
M M
M M
M M
M l
1 i
l l
l I
GA T120 h
/
I
/
l Y
/
/
O 6
12 18
?4
,/ 30 36 1
/
l i
/
j 8
/
GARAGE OFFICE 7
-. DIVIDING
/
l
)
WALL
/
C 9
i
/
l
/
e 0
/
\\
j MEASUREMEt4T LOCATIONS l
UPPER WALLS I
O AND CEILING i
1 1 LIGiT FlxTURE i
l
=N O
6 d
I J
I FEET FIGURE 8: Measurement Locations on Other Surfaces j
in the Garage / Office Building I
l I
i l
l O
8 3
A 3
2 2
2 n
n nu un 0
2 2
2 3
3 0
3 M
M M
C l
UU U
Il U
EU6 6
E UUEEUU U5 EEEEEE G
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
9200E f
l f
e
/
</
-T1 9230E
-e c
1 d
O M /
I C
9260E A#
l l 'l m
x l
/
9290E
)
in
/
g
/
(
9320E
'/'
/
\\
o
\\
f(
cm
+'
n M 7 9350E 4
/
\\
eo V
Q
'n
/
$ /
\\
O
/
d 9380E x
t rl f-T
\\
i
_-+,
l
)
Wk
/
'-,/
l O =
f/
\\
f C O
/
/'/
A
\\
k
~
/
/\\
h l
gd
[~'
k,/
NNN l
r j
c5 9500E h
9530E (t,
9560E
[
m 1
O 3
\\
-.'n L/\\
x o
2
\\
\\
/
.(sj/
(\\
l s'f
\\\\
l 959 E
/ V/
p 9620E o
y 3
---o
$m 9650E "8
Z
__ u MC
'9 l
O, m
o
- m 75 j
1 9680E o
]
g-p
____ z a2 3 m,w js Dj l
b
- o o
I W
9710E
" w' 3
1
-b
//
/
A i
_e 4
M o
>r x
h
//
/
s 9740E
$j 4
^9j l
7 3
N I
9770E 4
j
=
1 N
/
i 9800E i
l i
I f
}
u
-a u
u
-s
-4
~4 u
u u
i
-4 w
-a u
y y
-s
-2
-a u
-a se u
.-s 0 N
M l
8 8
N 8
G G
G S
2 U
N 5
3 2
9 9
9 9
9 9
9 9
9 9
9 9
9 9
9 9
9 2
9 2
2 2
2 O
9200E I
3)
/
,[/'7
/
C i
9230E
(
j m
1
/
c
\\
f
'3260E G
i
=
/
/
t m
(n r-
's290E
~
l ng w
j o, O
~/+' o r
n m
320E j
\\
a o s
EC
/*
M
/
\\
\\
9350E f
go y
/
/
\\
(.
T 9380E A'
\\
m
/
h g u 4
[T
\\
3 [ Et > G i
/<
k k
9430t womam
/
I
/
T
- 90C
/
//
~A
\\
\\
o, y y r q " p 9440E o
QO m>>z
/y
>\\
g, n
u 1
e u nc.m m 9470E
~/~/
~,/.\\
p'\\
ps'N'N'
)
i tn o r m>rn o
//-
h/
/"
\\
/'
o me7E
\\
i
//
4 g /
N 1
ao
- g F, 3
\\
(
g
- )
J oo m
9530E
/
M'
\\
3 c
9560E
~
x Q_ 3 A
4
\\If 1
' s~sj/
oo c
(
s oO O
/
'\\
'y 3m cC m
95900 O$
\\\\
\\'/,
r-m
\\$
3 a e
O m
9620E t
$x
\\'
I5 DR
\\
m Z
O 9650E o
}
o"h N
[m u
O ym j
x:
3p 968DE
-r o
3 m.
p
~
)%
j' n],
3)* N
- h 7/.
~o m m
~
e
- E 9710E
<o j
a s
- c N :&/ /e /
O a
N m
9740E O<
-g 7
O h^-
'P J
3 9770E f
}
9800E i
4
GAT 4o DEL MAR PACIFIC l
COAST HWY.
l GA TECHNOLOGIES
[3 /
FACILITIES i3 l
/6 CEt!ESEE AVE.
/
'a 4
Y 5
U" UNIVERSITY i
CITY 2
I y
4 I
PA C/R C PACIFIC OCEAN BEACH i
MISSION BEACH e
I SAN DIEGO I
(
l
\\
MILES I
0 1
2 3
4 5
1 I
I I
i l
I I i l i I i l i O
2 4
6 8
I KILOMETERS I
FIGURE 11:
Locations ( e ) of Background Measuremerits and I
Baseline Soil Samples from the Vicinity of GA Technologies 21 I
1 m m
M C.,
m m
m m
m m
e e
m m
m m
m m
l t
j CAT 13b t
j t
)
[
l i
i I
i j
0 6
12 18 24 30
^
// 'l I
d B
}
I
=
c i
i D
4 1
i i
CON TAMiN ATED l
FLOOR AREA i
i WN I
I O
6 l
l l
)
S FEET l
l FIGURE 12: Area on the By-Products Storage Building Floor, I
identified by Surface Scans t
i
It
,!I:
4
?
l
,l l'l l
i
- l o55a M
5 82
/
7
/
M j
5 82
/
/
\\
Q\\g\\
j V'
$ 82 s
v p
h N
M N
$82 7
/
j/
N-N Ua2
_zSI' $m g
M s
/
~(
x Ue.
x U 5, A%
M W
$8-.
M
\\
$8
\\
f
.\\
$ 8-j
^'
/
\\
M
/
U 8,
\\.
G
/
/
f' l/
3
(\\
U8.
YI Da 5$$ m$ y A <
M
/
/
y
\\
f Nm"'D m$ $ so=ia<-
Ua.
f
/
r
- o M
/
/
U8.
i t
/
Ua-4L
- l
/
O
\\
/
M U a, w.
>0
$a
/y f^O n 5.
y f
h 28-T
/
\\
X
/,
2 S-
~
,/
. y 2 M-v.
5 M
7 7
\\
$8, i
$8.
M
$M.
$8, E
E E
E E
E E
E c
E l
E E
E E
E E
E E
0 0
0 0
0 0
0 0
0 0
0 l
0 0
0 0
0 0
0 0
M 0
3 6
9 2
5 8
1 4
7 0
l' e 9
2 5
8 1
4 7
0 5
6 6
6 7
7 7
8 2
2 2
2 3
3 3
4 4
4 5
9 9
9 9
9 9
9 9
9 e
4~
l 9
9 9
9 9
9 9
9 M
2_
O u
8 eo
_ Agm M
h '-
7 aC~ R a -
rkO 53 n.
0 wleQ aqeO E$5 OJ-1 D
M T' r1n e]3o A o3W GJ.,[
C
(
e M
,l jI 1
1!
li.j i'lI
,-I
!i it'
!!'j:,
q I
TABLE 1 BACKGROUND RADIATION LEVELS I
GA TECHNOLOGIES SAN DIEGO, CALIFORNIA I
Gamma Exposure Rates Gamma Exposure Rates Locationa at 1 m Above the Surface at the Surface (pR/h)
(tR/h)
I 1
7 8
2 8
8 3
7 7
4 10 10 I
5 13 15 6
13 15 I
RANGE 7 TO 13 7 TO 15 AVERAGE 9.7 10.5 aRefer to Figure 11.
I I
I
~
I I
I I
2.
m W
W W
W m
M M
M M
M M
M M
M TABLE 2 BASELINE RADIONUCLIDE CONCENTRATIONS IN S0ll GA TECHNOLOGIES SAN DIEGO, calif 0RNIA 8
Location Radionuclide Concentrations (pCl/q)
Co-60 Cs-137 Ra-226 U-235 U-238 Th(228 & 232)
K-40 b
1
<0.03
<0.02 0.59 i 0.14
<0.17 1.6 1 1.2 1.34 i 0.46 14.0 11.7 2
<0.05 0.16 i 0.11 0.53 1 0.22
<3.20 1.6 1.5 1.98 i 0.86 25.0 13.3 3
<0.04
<0.04 0.79 i 0.20 0.39 i 0.24 1.1 i 0.5 2.24 1 0.62 10.4 i 1.7 4
<0.08
<0.05 1.20 1 0.29
<0.32
<1.1 3.08 i 0.79 29.0 13.4 5
<0.05
<0.05 1.23 1 0.22 0.69 i 0,55 1.3 1 0.6 3.20 i 0.80 24.3 i 2.7 3
6
<0.05
<0.05 0.65 1 0.16
<0.22 1.0 1 0.9 1.92 1 0.78 30.2 1 2.9 D
RfNGE
<0.03 to <0.08
<0.02 to <0.16 0.53 to 1.23
<0.17 to 0.69 1.1 to 1.6 1.34 to 3.20 10.4 to 30.2 MERAGE
<0.05
<0.06 0.83
<0.33 1.3 2.29 22.2 aRefer to Figure 11 bUncertainties represent the 95% confidence levels, based only on count 8ag statistics; additional laboratory uncertainties of 6 to 10% have not been propagated in these data.
i
m m
m m
m m
m e
e m
M M
M M
M M
M M
TAf5LE 3
SUMMARY
OF SURFACE CONTAMINATION KASUREMENTS IN THE BY-PRODUCTS STORAGE AND GARAGE /0FFICE DUILDINGS PHASE Il DEC0mlS$10NING GA TECINOLOGIES SAN DIEGO, CALIFORNIA Number of TOTAL CONTAMINATION (dpm/100 cm2)
REMOVABLE CONTAMINATION (dpm/100 cm )
Number of 2
8 Location Grid Blocks Alpha Range Beta-Gamma Range Alpha Range Deta Range Areas Surveyed Exceeding Criterla BY-PRODUCTS STORAGE BUILDING Floors 6
330 - 10600 820 - 17800
<3 - 27
<6 - 8 1C Lower walls 3
36 -
80
<470
<3 - 7
<6 - 9 0
Upper walls / celling g
b
/ equipment 4
90 -
300
<470
<3 - 4
<6 0
GARACE/0FFICE BUILDING Floors 11 50 -
130
<4 70 - 2550
<3-5
<6 - 12 0
Lower walls 9
<27 -
120
<470
<3
<6 - 10 0
b Upper walIs/ceIIing 3
<27
<470
<3
<6 0
aRafer to Figures 5, 6, 7, and 8.
bSingle point measurements.
2 2
CArea remed;ated, resurvey reduced alpha levels f rom 10600 to <27 dpm/100 cm and beta-gamma level from 17800 to 890 dpm/100 cm,
I TABLE 4 EXPOSURE RATES MEASURED AT 30 FT GRID INTERVALS I
PHASE II DECOMMISSIONING GA TECHNOLOGIES SAN DIEGO, CALIFORNIA I
Gamma Exposure Rates Gamma Exposure Rates I
Locationa at Im above the surface at the surface (UR/h)
(uR/h)
I 7360N, 9260E 13 15 7330N, 9260E 13 14 7300N, 9260E 14 14 7240N, 9290E 11 11 7270N, 9290E 13 13 7310N, 9290E 13 14 7330N, 9290E 13 14 7360N, 9290E
-D 7210N, 9320E 13 13 7240N, 9320E 13 13 7270N, 9320E 13 12 7300N, 9320E 7330N, 9320E 13 13 7360N, 9320E 14 13 7390N, 9320E 7420N, 9320E 7180N, 9350E 13 13 7210N, 9350E 13 13 7240N, 9350E 7270N, 9350E 11 11 I
7300N, 9350E 14 14 7330N, 9350E 13 13 7360N, 9350E I
I 27
I TABLE 4 (Continued)
EXPOSURE RATES MEASURED AT 30 FT GRID INTERVALS I
PHASE II DEC0F01ISSIONING GA TECHNOLOGIES SAN DIEGO, CALIFORNIA I
Gamma Exposure Rates Gamma Exposure Rates l
I Location at im above the surface at the surface (pR/h)
(pR/h) 7390N, 9350E 7420N, 9350E 11 11 7120N, 9380E 11 11 7150N, 9380E 13 11 7180N, 9380E 11 11 I
7210N, 9380E 13 13 7240N, 9380E 13 12 7270N, 9380E 7300N, 9390E 7330N, 9390E 7360N, 9390E 7390N, 9390E 7420N, 9380E 7090N, 9410E 11 11 I
7120N, 9410E 11 11 7150N, 9410E 11 11 7180N, 9410E 12 12 7210N, 9410E 12 13 7240N, 9410E 7270N, 9410E 7300N, 9410E 7330N, 9410E 7360N, 9410E I
I I
2e
I TABLE 4 (Continued)
EXPOSURE RATES MEASURED AT 30 FT GRID INTERVALS I
PHASE II DECOMMISSIONING GA TECHNOLOGIES SAN DIEGO, CALIFORNIA Gamma Exposure Rates Gamma Exposure Rates I
Location at im above the surface at the surface (pR/h)
( pR/h) 7390N, 9410E 7380N, 9410E 13 13 7090N, 9440E 7120N, 9440E 11 11 7150N, 9440E 7180N, 9440E 7210N, 9440E 7240N, 9440E 7270N, 9440E 7300N, 9440E 7330N, 9440E 13 14 7360N, 9440E 15 16 7390N, 9440E 11 13 7420N, 9440E I
7450N, 9440E 7120N, 9470E 13 12 7150N, 9470E 7180N, 9470E 7210N, 9470E 7140N, 9470E 16 16 7300N, 9410E 7 3.'0N, 9470E 13 13 I
7369N, 9470E I
I 29 I
I TABLE 4 (Continued)
EXPOSURE RATES MEASURED AT 30 FT GRID INTERVALS I
PHASE II DEC0tetISSIONING GA TECHNOLOGIES SAN DIEGO, CALIFORNIA Gamma Exposure Rates Gamma Exposure Rates I
Location at im above the surface at the surface (pR/h)
(uR/h)
I 7390N, 9410E 14 13 7420N, 9470E 13 12 7450N, 9470E 7480N, 9470E 7030N, 9500E 7060N, 9500E 11 11 7090N, 9500E 11 11 7120N, 9500E 13 14 7150N, 9500E 7180N, 9500E 7210N, 9500E 7240N, 9500E 16 17 7270N, 9500E 15 14 7300N, 9500E 7335N, 9500E 15 15 7360N, 9500E 7390N, 9500E 7420N, 9500E 7450N, 9500E 7480N, 9500E 1
7510N, 9500E 7030N, 9500E 7060N, 9530E 12 12 I
30
I TABLE 4 (Continued)
EXPOSURE RATES MEASURED AT 30 FT GRID INTERVALS PHASE II DEC0!!MISSIONING GA TECHNOLOGIES SAN DIEGO, CALIFORNIA Gamma Exposure Rates Gamma Exposure Rates I
Location at im above the surface at the surface (pR/h)
( pR/h) 7090N, 9530E 11 11 7120N, 9530E 13 13 I
7150N, 9530E 13 13 7180N, 9530E 7210N, 9530E 13 13 7240N, 9530E 7270N, 9530E 7300N, 9530E 7320N, 9530E 7360N, 9530E 16 17 7000N, 9560E 7030N, 9560E 7060N, 9560E 13 13 7090N, 9560E 15 16 I
7120N, 9560E 13 13 7150N, 9560E 13 13 7180N, 9560E 15 15 7210N, 9560E 14 13 7240N, 9560E 15 15 7270N, 9560E 14 14 7300N, 9560E 16 21 7330N, 9560E 7360N, 9560E I
aRefer to Figure 9.
b(---) indicates measurement not performed.
31 l
I TABLE 5 EXPOSURE RATES MEASURED IN THE INCINERATOR PAD AREA PHASE II DECOMMISSIONING GA TECHNOLOGIES SAN DIEGO, CALIFORNIA I
Gacima Exposure Rates Gacima Exposure Rates Locationa at I m above the surface at the surface (pR/h)
(DR/h)
I 7620N, 9715E 16 18 7585N, 9722E 20 28 I
7627N, 9675E 16 16 7610N, 9670E 15 16 7565N, 9690E 16 20 I
7645N, 9658E 16 18 7587N, 9710E 16 16 I
aRefer to Figure 9.
I I
I I
I I
32 il l
sieim sem i
E TABLE 6 DIRECT RADIATION LEVELS MEASURED ON CONCRETE PADS PHASE II DECOMMISSIONING CA TECHNOLOGIES SAN DIEGO, CALIFORNIA I
Camma Exposure Rates Gamma Exposure Rates Locationa Description at im above the surface at the surface (pR/h)
(LR/h) 7261N, 9551E Waste Pad 15 16 7197N, 9515E By Products Storage Bldg.
13 15 I
7354N, 9458E North Waste Pad 13 16 7625N, 9720E Incinerator Pad 16 18 I
a.,er to ris.. e.
I I
I I
I E
I I
I 33 l
l
TABLE 7 EXPOSURE RATES IIEASURED AFTER REffEDIATION OF AREAS I
IDENTIFIED BY SURFACE SCANS PHASE II DEC0FfMISSIONING GA TECHNOLOGIES SAN DIEGO, CALIFORNIA Gamma Exposure Rates Gamma Exposure Rates Locationa at 1 m above the surface at the surface (pR/h)
(pR/h) 7240N, 9490E 20 20 7260N, 9480E 18 18 I
7270N, 9480E 18 21 7370N, 9543E 15 15 I
7330N, 9430E 14 16 7260N, 9400E 13 13 7135N, 9455E 13 11 7380N, 9360E 13 14 aRefer to Figure 13.
I I
R I
I
~
I I
I 34 I
I TABLE 8
SUMMARY
OF SURFACE CONTAMINATION MEASUREMENTS - CONCRETE PADS AND F0VNDATIO4S
'I PHASE ll DECOMMISSIONING GA TECm0LOGIES SM DIEGO, CALIFORNI A I
TOTAL CONTAMINATION (dpm/100 cm2)
REMOVABLE CONTAMINATIOi (dpm/100 cm )
2 Locationa ALPHA BETA-GAMMA ALPHA BETA 7620N, 9730E 370 1240 5
<6 7610N, 9720E 36 1880
<3
<6 7260N, 9550E 310 5390
<3
<6 I
7355N, 9455E
<27 3420
<3
<6 7370N, 9480E 130 1330
<3
<6 7405N, 9415E
<27
-- b 7260N, 9547E 330 5640
<3
<6 m
7615N, 9725E 1550 1150
<3
<6 7624N, 9723E 930 1270
<3
<6 I
aRefer to Figure 10 bDesh Indicates reasurement not perf orned.
I I
I I
I I
I I
35
M M
M W
M M
M M
W W
W M
M M
M M
M M
M TABLE 9 RADIONUCLIDE CONCENTRATIONS IN SURFACE $0ll SAMPLES FROM 30 FT GRID INTERVALS PHASE 11 DECOMMISSIONtNG CA TECm0LOGIES SAN DIEGO, CAllFORNIA Sample RadlonuctIde Concentratlons (pCl/q) a No.
Location Co-60 Cs-137 Ha-226 U-235 U-238 Th-228 Th-232 114A 7360N,9260E
<0.05 0.26 1 0.07 1.14 1 0.20 0.08 1 0.10 0.8 i 0.5 1.22 i 0.22 1.24 10.33 IISA 7330N,9260E
<0.07 0.27 1 0.13 1.33 1 0.28 0.16 1 0.11 1.0 11.4 1.64 1 0.47 2.10 1 0.50 116A 7300N,9260E
<0.04 0.15 1 0.11 0.98 1 0.23 0.20 1 0.08 0.9 i 1.2 1.45 1 0.33 1.65 1 0.52 117A 7240N,9290E
<0.03 0.27 1 0.10 0.77 i 0.17 0.77 1 0.09 1.1 10.9 0.75 1 0.25 0.62 1 0.40 118A 7270N,9290E
<0.05 0.14 1 0.09 0.78 1 0.19 0.12 i 0.04 0.8 1 0.5 0.89 i 0.28 0.76 i 0.41 y
119A 7300N,9290E
<0.05
<0.04 1.12 1 0.31 0.18 i 0.10 1.4 11.1 1.22 1 0.39 1.8! 1 0.47 120A 7330N,9320E
<0.05 0.26 1 0.09 1.03 1 0.22
<0.21 2.5 1 0.5 1.28 i 0.28 0.97 1 0.35 121A 7210N,9320E
<0.05 0.45 1 0.11 0.73 1 0.21 0.17 1 0.09 1.0 1.0 0.64 10.22 0.76 i 0.32 122A 7240N,9320E
<0.13 0.45 1 0.24 1.40 1 0.46 0.06 i 0.18
<1.2 0.78 1 0.53 0.64 1 0.68 125A 7270N,9320E
<0.05 0.26 i 0.10 0.74 1 0.15 0.12 1 0.11 0.9 1 1.0 1.11 10.31 0.76 1 0.37 j
124A 7330N,9320E
<0.05 0.49 1 0.13 1.14 i 0.27 0.13 1 0.10 1.5 i 0.9 1,25 1 0.31 1.35 1 0.43 D
125A 7360N,9320E 0.03 1 0.15 0.41 i 0.13 1.16 1 0.30 0.19 1 0.11 0.6 1 1.4 1.62 1 4.07 1.57 1 0.47 126A 7180N,9350E
<0.19 0.56 1 0.11 1.22 1 0.89 0.13 1 0.08 4.9 1 0.3 0.67 1 0.28 1.06 1 0.36 127A 7210N,9350E
<0.54 0.11 1 0.11 1.30 1 0.24 0.18 i 0.11 0.3 1 1.0 1.11 1 0.28 0.70 1 0.51 128A 7270N,9350E
<0.04 0.2210.07 0.62 1 0.25 0.09 1 0.07 0.8 1 0.8 2.56 1 0.58 0.70 1 0.40 129A 7300N,9350E
<0.06 0.34 1 0.10 0.93 1 0.30 0.13 i O.11
<0.9 1.05 1 0.47 1.16 1 0.57 130A 7330N.9 M0E
<0.09 0.68 1 0.20 1.16 1 0.51 0.07 i 0.20 1.9 1 1.0 1.39 i 0.50 1.49 i 0.81
m W6 ea m
W m
W W
W m
M M
W W
W W
W TABLE 9 (Continued)
RA010NUCL10E CONCENTRATIONS IN SURFACE Soll SAMPLES FROH 30 FT GRID INTERVALS PHASE 18 DECOMMISSIONING GA TECtNOLOGIES SAN DIEGO, CALIFORNIA Sample RadlonucIlde Concentrations (pCl/q)
No.
Location Co-60 Cs-137 Ra-226 U-235 U-238 Th-228 Th-232 131A 7420N,9350E
<0.06 0.40 t 0.11 1.37 1 0.24 0.23 1 0.13
<0.8 1.47 1 0.36 1.30 10.44 132A 7120N,9380E
<0.44 0.18 1 0.08 0.93 i 0.19 0.05 1 0.06 0.6 1 0.1 0.70 1 0.19 0.52 1 0.40 133A 7150N,9380E
<0.05
<0.05 0.97 1 0.20 0.13 1 0.11 0.6 i 1.1 1.06 i 0.28 0.91 10.40 134A 7180N,9380E
<0.06 0.52 i 0.12 0.73 1 0.26 0.07 1 0.11 0.9 1 0.9 0.53 1 0.22 0.83 i 0.36 135A 7210N,9380E
<0.13 0.30 f 0.20 0.78 i 0.63 0.10 1 0.18 1.5 i 1.6 0.93 i 0.81 0.87 1 0.84 136A 7240N,9380E
<0.05 0.43 1 0.11 1.21 1 0.25 0.14 1 0.52 1.1 0.8 0.86 1 0.28 1.18 1 0.45 137A 7270N,9380E
<0.05 0.11 1 0.06 1.04 1 0.24 0.30 1 0.11 1.5 1 1.3 1.62 i 0.36 1.50 1 0.51 138A 7090N,9410E
<0.04
<0.03 0.61 t 0.22 0.14 1 0.07 0.3 1 0.8 0.56 1 0.22 0.46 i 0.32 139A 7120N.9410E
<0.06 1.30 1 0.15 0.62 1 0.20 0.10 1 0.05
<0.6' O.47 1 0.22 0.60 1 0.32 140A 7150N,9410E
<0.05 0.1810.12 0.7310.26 0.13 10.09
<0.5 0.61 10.31 0.40 1 0.51 141A 7180N,9410E
<0.06 0.31 0.08 0.74 1 0.27 0.12 1 0.10 1.6 1 2.7 0.81 1 0.36 0.88 1 0.28
}
142A 7210N,9410E 0.10 1 0.10 1.03 i 0.19 0.75 1 0.19 0.26 1 0.08 1.0 1 0.9 0.70 1 0.22 1.02 1 0.34 143A 7380N,9410E 0.21 1 0.09 3.10 1 0.24 1.16 1 0.24 0.21 1 0.12 0.4 11.2 1.39 1 0.33 1.41 1 0.55 144A 7120N,9440E
<0.05 0.46 1 0.11 0.75 i 0.26
<0.25 1.0 1 0.5 0.75 1 0.30 0.58 1 0.39 145A 7330N,9440E
<0.03 0.45 i 0.11 0.62 1 0.30 0.05 1 0.14
<0.7 0.97 1 0.31 1.15 1 2.0 l
146A 7360N,9440E
<0.07 1.57 1 0.20 1.30 1 0.29 0.14 1 0.13 1.1 1 0.6 1.50 1 0.36 1.45 1 0.48 l
W W
W W
W W
W W
W W
W W
M M
M M
M M
M TABLE 9 (Continued)
RADIONUCLIDE CONCENTRATIONS IN SURFACE Soll SAMPLES FROM 30 FT ORID INTERVALS MIASE 11 DEComl SS10NING GA TECm0LOGIES SAN DIEGO, CAllFORNIA Sample Radionuelide Concentratlons (pC1/g)
No.
Location Co-60 Cs-137 Ra-226 U-235 U-238 Th-228 Th-232 147A 7390N,9440E
<0.05 0.06 1 0.04 0.44 1 0.16 0.09 i 0.09
<0.6 0.67 1 0.25 0.73 1 0.31 148A 7120N,9470E
<0.06 0.30 1 0.11 0.85 i 0.18 0.10 1 0.08
<0.5 0.86 1 0.28 0.41 1 0.45 149A 7240N,9470E 0.90 1 0.17 9.54 1 0.41 1.41 1 0.30 0.21 1 0.14
<0.7 1.22 1 0.36 1,44 1 0.44 150A 7330N,9470E 0.09 1 0.10 0.17 1 0.09 0.69 i 0.16 0.12 1 0.10 0.9 i 1.2 1.16 1 0.30 1.11 1 0.38 151A 7390N,9470E
<0.06 0.45 1 0.12 1.02 i 0.30
<0.25
<0.7 1.94 i 0.30 1.53 1 0.60 152A 7450N,9470E
<0.05 0.52 1 0.13
- 1. 36 + 0. 35 0.15 i 0.11 1.1 11.0 1.45 1 0.33 1.72 1 0.41 153A 7060N,9500E
<0.05
<0.05 0.70 1 0.21 0.09 1 0.09 0.7 1 0.8 0.63 1 0.22 0.79 1 0.28 154A 7090N,9500E
<0.04 0.05 1 0.06 0.60 1 0.21
<0.18
<0.5 0.83 1 0.20 0.81 1 0.27 155A 7120N,9500E
<0.04 0.23 + 0.11 0.86 1 0.23 0.14 1 0.08 0.5 i 1.0 0.78 1 0.19 0.85 1 0.43 156A 7240N,9500E 0.33 1 0.18 2.60 1 0.24 1.00 1 0.28 0.19 1 0.12 1.8 1 1.3 1.85 1 0.42 1.72 1 0.60 157A 7270N,9500E 0.20 1 0.14 U.05 1 0.09 1.15 1 0.25
<0.26
<0.8 1.72 10.33 1.45 10.44 158A 7335N,9500E
<0.32 2.74 1 0.28 1.29 1 0.24 0.24 1 0.12 1.7 10.7 1.78 1 0.36 2.70 1 0.55 159A 7060N,9530E
<0.05 0.02 1 0.08 0.70 1 0.16 0.12 1 0.09
<0.7 0.84 1 0.27 0.95 1 0.31 160A 7090N,9530E
<0.07 0.39 1 0.13 1.11 1 0.30
<0.24
<0.8 1.44 1 0.81 2.01 10.46 161A 7120N,9530E
<0.04
<0.05 1.48 1 0.24 0.20 1 0.09 1.4 10.5 1.17 i 0.28 1.08 1 0.42 l
162A 7150N,9530E
<0.06 0.27 1 0.13 1.85 i 0.30 0.56 1 0.55 2.5 i 1.6 1.35 1 0.52 1.42 10.39
m a
m W
W M
M M
M W
M M
m W
W W
W M
r TABLE 9 (Continued) l i
I RADICNUCLlDE CONCENTRATIONS IN SURFACE Soll SAWLES l
)
FROM 30 FT GRID INTERVALS l
PHASE il DECOMMISSIONING l
l GA TEONOLOGIES I
SAN DIEGO, CALIFORNIA Sompte Radionuclide Concentrations (pCl/g)
No.
Location Co-60 Cs-137 Ra-226 U-235 U-238 Th-228 Th-232 163A 7360N,9530E 0.6110.17 6.64 1 0.31 1.18 1 0.25
<0.25
<0.7 1.08 1 0.40 1.13 1 0.58 l
164A 7060N,9560E
<0.04 0.06 1 0.04 1.02 1 0.23 0.11 1 0.09 0.9 1 0. *>
1.00 1 0.25 1.19 1 0.45 l
165A 7090N,9560E
<0.04
<0.06 1.31 1 0.31 0.25 1 0.13 0.9 1 1.6 1.2 0.47 1.42 1 0.49 166A 7120N,9560E
<0.05 0.0310.07 1.09 i 0.28 0.14 1 0.07 1.2 1 0.5 1.17 1 0.28 1.1310.41 167A 7150N,9560E
<0.06
<0.06 1.27 1 0.26
<0.26
<0.8 1.86 1 0.36 1.59 1 0.58 168A 7180N,9560E
<0.05 0.4710.10 1.00 1 0.26 0.39 1 0.12 2.9 1 1.6 1.63 1 0.52 1.60 1 0.52 169A 7210N,9560E 0.24 1 0.17
<0.07 1.03 1 0.26
<0.24
<0.8 1.11 1 0.42 1.00 1 0.79 170A 7240N,9560E 0.2110.17 2.?0 1 0.21 1.28 1 0.27 0.41 1 0.08 3.9 1 0.8 2.80 i 0.33 2.67 1 0.5G 171A 7270N,9560E 0.17 1 0.10 2.14 1 0.20 1.05 1 0.26 0.23 t 0.13 1.711.2 1.34 1 0.26 1,43 1 0.40 172A 7300N,9560E 0.29 t 0.12 3.05 t 0.25 1.10 f 0.28 1.26 1 0.71
<0.9 1.78 1 0.47 1.86 1 0.47 173A 7210N,9530E O.14 1 0.12
<0.05 2.23 1 0.35
<0.30 3.6 1 0.8 1.50 1 0.36 1.30 1 0.48 8Refer to Figure 9 h)ncertainties represent the 95% confidence levels based only or. counting statistics; additional laboratory uncertainties of 6 to 10% have not been propagated into these data.
l MnBM1
N O
O h
E E
E E
N O
O E
O O
O N
O TABLE 10 RADIONUCLlDE CONCENTRATIONS IN SOIL SAMPLES COLLECTED FROM THE INCINERATOR PAD AREA PHASE 11 DECOMMISSIONING CA TECHNOLOGIES SA WLES SAN DIEGO, CALIFORNIA Sample Radionuclide Concentrations (pCl/ql a
No.
Location Co-60 Cs-137 Ra-226 U-235 U-238 Th-228 Th-232 D
107A 7620N, 9715E 0.84 1 0.18 1.46 i 0.18 1.33 1 0.31 0.54 1 0.54 1.31 1 1.04 1.75 1 0.36 1.82 1 0.51 108A 7585N, 9722E 1.37 1 0.20 19.28 1 0.56 0.97 i 0.32 0.66 1 0.78
<1.05 1.45 1 0.44 1.7410.46 109A 7630N, 9680E
<0.06
<0.04 1.27 1 0.25
<0.22
<0.75 1.50 1 0.36 1.85 1 0.38 l
110A 7610N, 9670E
<0.06 0.11 1 0.08 1.12 1 0.27
<0.25 0.50 1 0.11 1.39 1 0.31 1.52 1 0.42 l
tilA 7565N, 9690E 0.82 i O.20 9.7110.40 1.17 1 0.27
<0.36
<0.70 1.22 1 0.36 1.56 1 0.43 l
3 O
If2A 7645N, 9685E 0.32 1 0.18
<0.04 1.74 1 0.30
<0.30
<0.98 2.11 1 0.44 2.26 1 0.56 113A 7587N, 9710E
<0.08 1.0510.15 0.97 1 0.21
<0.23
<0.81 1.53 1 0.36 1.39 1 0.48 I
l l
aRefer to Figure 9 Nncertaintles represent the 951 confidence levels based only on counting statistics; addditional laboratory uncertaintles of 6 to 10%
have not been propagated into these data.
l 3
1 0 64 2
5 10 3
0 0 0 2
o 1 i 1 t
h N
T 8 9 1 6
3 3 8 f
0 0 o
1 se 3 0 0 i
O t
5 2 4,
n 82 0 0 0 ia 2
t 1 1 1 r
h e
T 0 4 8 c
7 4 7 n
O u
1 0 0 yro tar E
8 o
S 3
2 57 b
D 2
P U
la A
1 0 0
)
E q
la T
/
n E
I o
O R
C i
C p
t N
(
i D
d
(
s d
n d
H T
io 5
a 3
8 7 9 N
A t
2 3
1 2
E a
s N
r U
0 0 0 E G t
ic B N I
e s
A n
t M IN N
c i
O O S R n
t R
I E O o
a N
F S I
F C
t S G I
s 1
L IM L A d
g O L e
1 1
M O C i
3 1
1 0
6 0 9 n
E S O N l
6 i
L C H,
c t
B N E C O u
2 0 0 0 n
E I
D E G n
2 u
AT T E o
1 1 1 o
S 1
A D ld R
N I
a c
O 1
G a
1 3 5 4 4 8 n
TI E N
R o
S A
3 0 0 A A S
T P ly R H O
J b
d n
N o
EC 6 5 4 e
M 1
01 s
7 a
3 0 O 0 b
E I
s ls E
1 D
t i 1 L
C 9 3 5 e
UC 2 00 v
N 0 0 0 le O
E I
e D
c.
A n a R
et d ad i
0 0 3 6 f
6 1
00 n e O
os o
0 0 0 c e C
h
% t 59 o t
en h i O
t d
E E E t e 1
8 0 nt 5 5 2 ea a
5 4 7 s g n
9 9 9
.e a o
0 r p E
i 1
p o t
N N N er a
1 4 5 e r p c
6 5 2 r
o 2 3 6 u sn L
7 7 7 g ieee Fi t b n
N lp e e e oit t a o e
t n r r m o aN 18 8 8 f
c v 3 4 e n a S
0 0 0 R uh E
0 0 0 ab
~e~
O l
l
TABLE 12 RADIONUCLIDE (DNCENTRATIONS IN SURFACE Soll SAMPLES COLLECTED FOLLOWING REMEDI ATION OF AREAS IDENTIFIED BY SURFACE SCANS PHASE 11 DECOMMISSIONING GA TECtNOLOGIES SAN D1 EGO, CALiFORN1A Sample RadIonuctIde Concentrations (pCl/g)
No.
Location Co-60 Cs-137 Ra-226 U-235 U-238 Th-228 Th-232 174A 7240N,9490E 0.53 1 0.19 2.94 1 0.25 1.24 1 0.28 0.24 1 0.12 2.1 1 1.7 1.75 1 0.33 2.00 10.45 175A 7270N,9480E 0.8510.19 9.68 1 0.39 1.32 1 0.36 0.88 1 0.64 2.1 1 1.7 2.64 1 0.~6 2.53 1 0.53 176A 7270N,9543E 1,7710.27 15.62 1 0.52 1.00 1 0.40
<0.41 1.1 1 0.8 2.06 1 0.42 1.58 1 0.47 177A 7370N,9460E 0.06 1 0.19 0.63 1 0.15 1.23 1 0.67 0.22 1 0.12 0.8 1 1.5 1.81 1 0.40 1,73 1 0.43 178A 7330N,9460E
<0.04 0.12 1 0.09 1.25 1 0.24
<0.22
<0.8 1.61 1 0.36 1.6010.42 179A 7260N,9400E
<0.04
<0.04 1.15 1 0.24
<0.24 1.1 10.6 1,44 1 0.31 1.27 1 0.39 d
180A 7135N,9455E
<0.04 0.09 1 0.09 1.24 1 0.25 0.24 1 0.11 0.9 1 1.2 1.40 1 0.35 1.48 1 0.46 181A 7380N,9360E
<0.04
<0.05 0.71 1 0.18
<0.20
<0.6 1.06 1 0.28 0.77 1 0.47 aRefer to Figure 13 buncertaintles represent the 95% confidence levels based only on counting statistics; additional laboratory uncertalnties of 6 to 10% have not been propagated into these data.
'I TABLE 13 RADIONUCLIDE CONCENTRATIONS IN COMPOSITE S0IL I
PHASE II DECOMMISSIONING GA TECHNOLOGIES SAN DIEGO, CALIFORNIA I
I Radionuclide Concentrations (pCi/g) a Sample Type Depth Sr-90 U-234 U-235 U-238 Composite A Surface 0.72 ! 0.16b 1.58 0.22 0.05 t 0.04 1.04 i 0.18 Composite B 1.46 0.25 3.83 1 0.37 0.16 0.09 2.19 1 0.28 Composite C 0.21 0.15 1.53 1 0.24 0.05 2 0.05 1.32 t 0.22 aSample identification numbers:
I Composite A:
(7060N, 9500E; 7090N, 9500E; 7120N, 9500E; 7240N, 9500E; 7270N,9500E)
Composite B:
(7240N, 9490E; 7270N, 9480E)
Composite C:
(7261N, 9551E; 7197N, 9458E; 7354N, 9458E; 7625N, 9720E) bUncertaitaties represent the 95% confidence levels, based only on counting I
statistics; additional laboratory uncertainties of 6 to 10% have not been propagated into these data.
E I
I I
I E
I E
I 43 I
E E
E E
E E
E E
E E
M N
E E
E E
O E
E TABLE 14 RAD lCNtCLIDE CONCENTRATIONS 1N MISCELLANE00S SAMPLES FHASE 11 DECOMMISSIONING GA TECHNOLOGIES SAM)LES SAN DIEGO, CALIFORNIA Descri pt ion Radionuclide Concentrations (pCl/g and Co-60 Cs-137 Ra-226 U-235 U-238 Th-228 Th-232 8
Location Soll FROM BENEATH OY-PRODUCTS STORACE BUILDING FLOOR D
(7197N, 9515E)
<0.06
<0.06 0.85 1 0.36
<0.21
<0.6
<0.23 0.85 1 0.35 DRAIN RESIDUE (717CN, 9562E) 0.14 1 0.26 2.41 1 0.31 1.07 t 0.58 0.24 1 0.74
<1.3
<0.46
!.89 1 0.84 ASPHALT (7587N, 9710E)
<0.05 0.48 1 0.09 1.49 1 0.24
<0.29 2.1 1 0.9
<0.26 1.78 1 0.58 aRefer to Figures 9 and 10 buncertainties represent the 95% confidence levels based only on Counting statistics; addditional laboratory uncertainties of 6 to 10%
have not been propagated into these data.
'I REFERENCES 1.
"Confirmatory Survey of Phase I Decommissioning Former, Waste Processing Facility, CA Technologies, San Diego, California," Oak Ridge Associated Universities, July 1986.
2.
"Follow-Up Confirmatory Survey of Phase I Decommissioning, Former Vaste Processing F'
'lity, CA Technologies, San Diego, California," Oak Ridge I
Associated Un wersities, March 1988.
3.
"Confirmatory Survey of Phase III Decommissioning, GA Technologies, San Diego, Calif ornia," Oak Ridge Associated Universities, February 1988.
4 Letter from K.
Asmussen (CA Technologies, Inc.) to R. D. Thomas (U.S.
I Nuclear Regult'
,y Commission, Region V),
Reference:
"License SNM-696, Docket 70-734", August 25, 1987.
5.
"Proposed Confirmatory Survey Plan f or Phase I (Follow-up) and Phase II o f the Former Waste Processing Facility, CA Technologies, San Diego, California," Oak Ridge Associated Universities, September 4, 1987.
I B
5 I
I I
I I
I E
I 45 I
a w,,u._.a,.-
.a s
2..,
I I
I I
I I
I g
A,ezNo1x A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT 5
5 I
I I
E I
E I
E
APPENDIX A MAJOR SAliPLING AND ANALYTICAL EQUIPl!ENT I
The display or description of a specific product is not to be construed as an endorsement of that product or its manufacturer by the authors or their employer.
A.
Direct Radiation tieasurements Eberline "RASCAL" i
Portable Ratemeter-Scaler ifodel PRS-1 (Eberline, Sante Fe, N'i)
Eberline PR!!-6 Portable Ratemeter (Eberline, Sante Fe, N?i)
Ludlum Floor !!on'. tor
?fodel 239-1 (Ludlum, Sweetwater, TX)
Eberline Alpha Scintillation Probe I
!!odel AC-3-7 (Eberline, Sante Fe, N!!)
Eberline G'I Pancake Probe i
!!odel HP-260 (Eberline, Sante Fe, N!!)
I Victorcen Beta-Canna "Parcake" Detector Model 489-110 (Victoreen, Cleveland, OH)
Victoreen NaI Scintillation Detector Model 489-55 (Victoreen, Cleveland, OH)
Reuter-Stokes Pressurized Ionization Chamber
!! ode 1 RSS-111 (Reuter-Stokes, Cleveland, OH)
B.
Laboratory Analyses Automatic low-background Alpha-Beta Counter
!!odel LB5110-2080 (Tennelec, Inc., Oak Ridge, TN)
I High-Purity Germanium Detector
!!odel GMX-23195-S, 23% ef ficiency (EC&G ORTEC. Oak Ridge, TN) f A-1 1
I I
Used in conjunction with:
Lead Shield, G-16 (Gamma Products Inc., Palos liills, IL)
High Purity Germanium Coaxial Hell Detector Model GWL-110210-PUS-S, 23% Efficiency (EC&G ORTEC, Oak Ridge, TN)
Used in conjunction with:
Lead Shield Model G-16 (Applied Physical Technology, Atlanta, GA)
High Purity Germanium Detector I
(Princeton Gamma-Tech, Princeton, NJ)
Model IGC25, 25% Efficiency Used in conjunction with:
Lead Shield-(Nuclear Data, Schaumburg, IL)
I Multichannel Analyzer ND-66/ND-680 System (Nuclear Data Inc., Schaumburg, IL)
Alpha Spectrometry System Tennelec Electronics (Tennelec, Oak Ridge, TN)
Surface Barrier Detectors (EG&G ORTEC, Oak Ridge, TN)
?fultichannel Analyzer tiodel ND-66 (Nuclear Data, Schaumburg, IL)
I ll E
I I
I A-2 I
l
j,a
_aqu.-w.,-.-..M.
e5.-u.r.._A.-.m-_
5
-m-4-ma-a
- I i
I I
!I I
- I e
APPENDIX B ttEASUREttENT AND ANALYTICAL PROCEDURES
- I I
'I i
' I I
i
!E e
.I
,'I
!I
l APPENDIX B Measuremer.t and Analytical Procedures Surface Scans Surface scans were performed by passing the probes slowly over the surface.
The distance between the probes and the surface was maintained at a minimum -
nominally about I cm.
Identification of elevated levels was based on increases in the audible signal from the recording or indicating instrument.
Alpha and beta-gamma scans of large surface areas on the floor of the facility were 2
I accomplished by use of a gas proportional floor monitor, with a 600 cm sensitive area.
The instrument was slowly moved in a systentic pattern to cover 100% of the accessible area.
Combinations of detectors and instrument for the scans I
were:
I Beta-Gamma - Pancake GM probe with PRM-6 ratemeter.
Beta-Gamma - Pancake G'i probe with PRS-1 scaler /ratemeter.
Gamma
- NaI scintillation detector (3.2 cm x 3.8 cm crystal) with I
PRM-6 ratemeter.
Alpha
- ZnS probe with PRS-1 scaler /ratemeter.
Alpha / Beta - Gas proportional ficor monitor with Ludlum Model 2220 scaler /ratemeter.
Alpha and Beta gamma Surface Contamination Measurements I
Measurements of total alpha radiation level were performed using Eberline Model P P.S-1 portable scaler /ratemeters with Model AC-3-7 alpha scintillation probes.
E.u;ureme nt s of total beta gamma radiation levels were performed using I
Eberline 'fodei PRS-1 portable scaler /ratemeters with Model HP-260 thin-window "pancake" GM probes.
Count ratec (com) were converted to disintegration rates 2
(dpm/100 cm ) by dividing the net rate by the 4w efficiency and correcting for 2
the active area of the detector.
Effective window areas were 59 cm for the Zns detectors and 15 cm for the G'i detectors.
The background count rate for ZnS alpha probes averaged approximately 2 cpm; the average background count rate was approximately 40 cpm for the GM detectors.
I I
B-1 I
r I
Renvable Contamination Measurements I
Smear measurements were performed on numbered filter paper disks, 47 mm in diameter.
Smears were placed in labeled envelopes with the location and other pertinent information recorded.
Smears were counted on a low background proportional counter at the Oak Ridge laboratory.
Exposure Rate Measurements I
tteasurements of gamma exposure rates were performed using an Eberline PRIt-6 portable ratemeter with a Victoreen Model 489-55 gamma scintillation probe containing a 3.2 cm x 3.8 cm NaI(T1) scintillation crystal.
Count rates were converted to exposure rates (pR/h) by onsite cross-calibration using a Reuter Stokes model RSS-Ill pressurized ionization chamber.
Soil, Asphalt, and Residue Sample Analysis I
Gamma Spectroscopy I
Samples were dried, mixed, and a portion sealed in 0.5-liter liarinelli beaker. The quantity placed in the beaker was chosen to reproduce the calibrated I
countir.g geometry and ranged from 600 to 800 g of soil. Net soil weights were determined and the samples counted using intrinsic germanium and Ge(Li) detectors coupled to a Nuclear Data tiodel ND-680 pulse height analyzer system. Background and Compton stripping, peak search, peak identification, and concentration calculations were performed using the computer capabilities inherent in the analyzer system. Energy peaks used for determination of radionuclides of concern were:
Co 1.173 MeV I
Cs-137 - 0.662 !!eV Ra-226 - 0.609 tieV f rom Bi-214 (secular equilibrium assumed)
U-235 - 0.144 !!eV U-238 - 0.094 tieV f rom Th-234 (secular equilibrium assumed)
Th-228 - 0.583 tieV from T1-209 (secular equilibrium assumed)
Th-232 - 0.911 !!eV f rom Ac-228 (secular equilibrium assumed)
I Spectra were also reviewed for :he presence of other radionuclides.
B-2
r I
Strontium-90 Analysis Aliquots of soil were dissolved by pyrosulfate fusion and the strontium precipitated as a sulfate.
Successive treatments with EDTA preferentially removed lead and excess calcium and returned the strontium to solution.
Ferric I
and other insoluble hydroxides was precipitated at a pH of 12 to 14.
Strontium was reprecipitated as a sulfate.
Barium was removed as a chromate using DTPA.
The final precipitate of strontium carbonate was counted 'using a low-background Tennelee alpha-beta proportional counter.
I Alpha Spectrometry for Isotopic Uranium I
Aliquots of soil were dissolved by pyrosulfate fusion and precipitated witt barium s ul f a'.e.
The barium sulfate precipitates were redissolved and uranium separated by liquid - liquid extraction.
Uranium was then precipitated with a
+
cerium fluoride carrier and counted using surface barrier detectors (ORTEC),
alpha spectrometers (Tennelec), and an ND-66 Multichannel Analyzer (Nuclear Data).
I Uncertainties and Detection Limits I
The uncertainties associated with the analytical data presented in the tables of this report, represent the 95% confidence levels for that data. These I
uncertainties were calculated based on both the gross sample count levels and the associated background count levels.
When the net sample count was less than the 95% statistical deviation of the background count, the sample concentration was reported as less than the detection capability of the meas u reme nt procedure.
Because of variations in background levels and Compton contributions from other radionuclides in samples, the detection limits differ from sample to sample and instrument to instrument.
Additional uncertainties of ! 6 to 10%, associated with sampling and laboratory procedures, have not been propagated into the data presented in this report.
I Calibration and Quality Assurance Laboratory and field survey procedures are documented in the following manuals, developed specifically for the Oak Ridge Associated Universities' B-3 I
Radiological Site Assessment Program:
"Survey Procedures !!anual," Revision 3,
!!ay 1987; "Laboratory Procedures itanual", Revision 3,
!!ay 1987 and "Quality Assurance !!anual", Revision 1, June 1987.
With the exception of the measurements conducted with portable gamma scintillation survey meters, instruments were calibrated
'i t h NBS-traceable standards.
The calibration p-ocedures for the portable gamma instruments are I
performed by comparison with an NBS calibrated pressurized ionization chamber.
Quality control procedures on all instruments included daily background and check-source measurements to confirm equipment operation within acceptable statistical fluctuations.
The ORAU laboratory participates
.1 the EPA and E?tL Quality Assurance Programs.
I I
I I
I I
I I
I
- I e-.
- g
I I
I I
APPENDIX C I
I GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE I
I I
5 I
I
~
I I
I
- I l
m.
, _. _ _, _ _. - _,.,..,, _. _,.., ~, _.. - -.
l'I I
I GUIDELINES FOR DECONTAMINAT*UN OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE I
OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE OR SPECIAL COLEAR MATERIAL I
I l
I I
I U.S. Nuclear Regulatory Commission I
Division of rael Cycle & Material Safety Washington, D.C.
20555 I
I I
July 1982 I
'I I
C-1 I
i I
The instructions in this guide, in conjunct 2 2n with Table 1, specify the radionuclides and radiation exposure rate lieits which should be used in decontamination and survey of surf aces or premises and equipment prior to abandonment or release'for unrestricted use.
The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity for which the radiological considerations pertinent to their use may be different. The release of such facilities or items from regulatory control I
is considered on case-by-case basis.
1.
The licensee shall make a reasonable effort to eliminate residual contamination.
2.
Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unless contamination levels, as I
determined by a survey and documented, are below the limits specified in Table 1 prior to the application of the covering.
A reasonable effort must be made to minimize the contamination prior to use of any covering.
3.
The radioactivity on the interior surfaces of pipes, drain lines, or I
ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contamination at these locations is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork.
Surfaces or I
premises, equipment, or scrap which are likely to be contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in excess of the limits.
4.
Upon request, the Commission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces I
contaminated with materials in excess of the limits specified.
This may include, but would not be limited to, special circumstances such as razing of buildings, transfer of premises to another organization I
continuing work with radioactive materials, or conversion of facilities to a long-term storage or standby status.
Such requests must:
a.
Provide detailed, specific information deocribing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surf ace contamination.
b.
Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with I
other considerations such as prospective use of the premises, equipment or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.
5.
Prior to release of premises for unrestricted use, the licensee shall make a
comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1.
A copy of I
I C-2 I
'I the survey report shall be filed with the Division of Fuel Cycle and Material Safety, USNRC, Washington, D.C.
- 20555, and also the Administrator of the NRC Regional Office having 4urisdiction.
The report should be filed at least 30 days prior co the planned date of abandonment. They survey report shall:
a.
Identify the premises.
I.
b.
Show that reasonable ef fort has been made to eliminate residual contamination.
c.
Describe the scope of the survey and general procedures followed.
d.
State the findings of the survey in units specified in the I
instruction.
Following review of the report, the NRC will consider visiting the I
facilities to confirm the survey.
I I
1 I
I E
I I
I l
I I
I C-3
E E
E E
E E
E E
E E
E E
E E
E E
TABLE I ACCEPTABLE SURFACE Q)NTAMINATION LEVELS Nuclides Averageb,c,f Maximumb,d,f Removableb,c,f a
2 2
2 U-nat, U-235, U-238, and 5,000 dpm a/100 cm 15,000 dpm a/100 cm 1,000 dpm a/100 cm associated decay products 2
2 2
Transuranics, Ra-226, Ra-228, 100 dpm/100 cm 300 dpm/100 cm 20 dpm/100 cm Th-230, 3 -228, Pa-231, Ac-227, 1-125, I-129 2
2 2
Th-nat, Th-232, Sr-90, Ra-223 1000 dpm/100 cm 3000 dpm/100 cm 200 dpm/100 cm Ra-224, U-232, I-126, 1-131, I-133 2
2 2
Beta gamma emitters (nuclides 5000 dpm Sy/100 cm 15,000 dpm SY/100 cm 1000 dpm Sy/100 cm with decay modes other than alpha emission or spontaneous
?
fission) except Sr-90 and others noted above.
a Where surface contamination by both alpha-and beta-gamma-emitting nuclides exists, the limits established for alpha-and beta-gamma-emitting nuclides should apply independently.
b As used in this tab 10, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, ef ficiency, and geometric factors associated with the instrumentation.
c Measurements of average contaminant should not be averaged over more than I square meter.
For objects of less surface area, the average should be derived for each such object.
more than 100 cm2, d n e maximum contamination level cpplies to an area of ngt e ne amount of removable radioactive material per 100 cm of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and ar,sessing I
the amount of radioactive material on the wipe with an appropriate lustrument of known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.
i I
f The average and maximum radiation levels associated with surf ace contamination resulting from beta gamma emitters should not exceed 0.2 mrad /h at I cm and 1.0 mrad /h at I cm, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.
I I
I I
I I
3 I
seesme1x e I
cs ;;=::itrt;;e 1=:
= m I
I I
I I
I I
~
I I
I I
F I
APPENDIX D I
Decommissioning Guidelines for the CA Technologies Uaste Processing Facilities Target criteria for unrestrict,' release of the CA Technologies' Uaste Processing Facility and surrounding areas are presented in the licensee's final report and are as follows:
External Radiation The gamma exposure rate at 1 e above the ground surface shall not exceed 10 uR/h above background for an area of greater than 30 f t (9.1 m) x 30 ft (9.1 m) and shall not exceed 20 uR/h above background for any discrete area (i.e. less than 30 ft (9.1 m) x 30 ft (9.1 m)].
Inhalation and Ingestion Concentrations of radionuclides in soil shall be such that inhalation and ingestion are not expected to result in annual dose equivalents exceeding 20 crem to the lung or 60 mrem to the bone.
I Liniting soil concentrations were derived to satisfy these external and internal target criteria.
The concentration limits are presented in the following Table.
I Radionuclide Concentration Littit Above Background (pCi/g)
I Depleted Uranium 35 Enriched Uranium 30 Thoriun (Natural) 10 Co-60 8
Cs-137 15 3
Sr-90 1.8 x 10 I
Where more than one radionuclide is present, the sum of the ratios of the individual radionuclide enneentrations to their respective concentration limits I
shall not exceed 1.
D-1
_