ML010710184
| ML010710184 | |
| Person / Time | |
|---|---|
| Site: | 07000734 (SNM-0696) |
| Issue date: | 02/15/2001 |
| From: | Asmussen K General Atomics |
| To: | Adams M, Wesley D NRC/NMSS/FCSS, State of CA |
| References | |
| -RFPFR, 696/CAL-3329 | |
| Download: ML010710184 (66) | |
Text
+
GENERAL ATOMICS February 15, 2001 696/CAL-3329 VIA EXPRESS MAIL SERVICE Ms. Mary Adams Licensing Section 1/Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Docket No.70-734; SNM-696: Request to Release Certain Portions of General Atomics' Facility to Unrestricted Use and Delete them from License: Namely, Areas 2 and 3 of Sorrento Valley West Land Area and ATTN: Mr. David Wesley (in Duplicate)
State of California Department of Health Services Radiologic Health Branch Mail Stop 178 601 North 7th Street Sacramento, CA 95814-0208
Subject:
Radioactive Materials License No. 0145-37: Request to Release Certain Portions of General Atomics' Facility to Unrestricted Use and Delete them from License: Namely, Areas 2 and 3 of Sorrento Valley West Land Area
Dear Ms. Adams and Mr. Wesley:
As you are aware, General Atomics (GA) is continuing its efforts to decontaminate, as appropriate, and obtain the release to unrestricted use of selected facilities on its site. GA has recently completed the Final Radiological Survey of portions of its Sorrento Valley West (SVW) Land Area.
These portions are referred to as "Area 2" and "Area 3" of the Sorrento Valley West land area. The total area of Areas 2 and 3 is about 43,700 ft2. The Sorrento Valley West Land Area is located on GA's Sorrento Valley Site. (See attached figure).
The SVW Land Area is comprised of three (3) areas: Area 1, Area 2 and Area 3. The Final Radiological Survey of "Area 1" was completed in advance of the rest of the SVW Land Area because of GA's urgent need to begin construction of a trench needed for an important government project. GA's request to release and delete SVW "Area 1" from GA's special nuclear and radioactive materials licenses was submitted to both the U.S. Nuclear Regulatory Commission (NRC) and the State of California DOHS Radiologic Health Branch (State) by GA letter number 696/CAL-3311, dated January 10, 2001. That letter request included a copy of the Final Radiological Survey Report for SVW "Area 1").
3550 GENERAL ATOMICS COURT, SAN DIEGO, CA 92121-1122 PO BOX 85608, SAN DIEGO, CA 92186-5608 (858) 455-3000
Mary Adams, U.S. NRC/ David Wesley, State February 15, 2001 6961CAL-3329 Page 2 In response to GA's request, Mr. Emilio Garcia from NRC's Region IV office performed a radiological survey of the Sorrento Valley West Area 1 on January 10, 2001. A copy of the Final Radiological Survey Report for "Area 1" was provided to Mr. Emilio Garcia prior to his survey.
GA has now completed extensive and comprehensive radiological measurements in "Areas 2 and 3" of the SVW Land Area. Some areas of localized radiological contamination were identified in "Area 2." All such contamination was remediated. Subsequent radiological surveys verified that residual contamination levels are below the approved release criteria. These results are summarized in the enclosed report titled, "General Atomics' Final Radiological Survey Report for Areas 2 and 3 of the Sorrento Valley West Land Area," dated February 2001. The results of these surveys demonstrate that Areas 2 and 3 of SVW meet the approved criteria for release to unrestricted use.
Accordingly, GA hereby requests that Areas 2 and 3 of its Sorrento Valley West Land Area, as described in the enclosed report, be released to unrestricted use and deleted from its NRC and State special nuclear and radioactive material licenses, respectively.
The history of use of Areas 2 and 3 involves both NRC and State licensed material.
However, the radioactive contamination found during the radiologic surveys is attributable to the preparation for shipment of concrete slabs from GA's Hot Cell Decommissioning Project.
Because the NRC was the agency with the lead regulatory oversight role for GA's Hot Cell decommissioning activities, it follows that it is appropriate for the NRC to take the lead in coordinating this release; including regulatory agency confirmatory surveys, as deemed appropriate.
If you should have any questions regarding this information, please contact Laura Q.
Gonzales at (858) 455-2758, or me at (858) 455-2823. Your assistance in responding to our request is very much appreciated.
Very truly yours, 64AZ6. 2a-1--ý Keith E. Asmussen, Ph.D., Director Licensing, Safety and Nuclear Compliance Attached Figure:
Sorrento Valley West Land Area showing the location of Areas 1, 2 and 3
Enclosure:
Report titled: "General Atomics' Final Radiological Survey Report for Areas 2 and 3 of The Sorrento Valley West Land Area," dated February 2001.
cc:
Dr. D. Blair Spitzberg, Chief, NMSS Branch 3, Region WV Mr. Wayne L. Britz, Fuel Cycle Inspector, NRC Region IV Mr. Emilio Garcia, Fuel Cycle Inspector, NRC Region IV Ms. Kathleen Henner, State of CA, Brea, CA Dr. Ron Rogus, State of CA, Sacramento, CA
Sorrento Valley West Land Area within the Sorrento Valley Sil N
SORRENTO VALLEY HILLS AREA 1 of SORRENTO VALLEY WEST -.
AREA 2 of WEST BUNKE SVA NORTH SOUTH SORRENTO VALLEY CENTRAL AREA 3 of SORRENTO VALLEY WI (Southern Portion)
ENTO VALLEY SOUTH TEST TOWER SORRENTO VALLEY EAST Scale in Feet 0
200 400
+ GENERAL ATOMICS FINAL RADIOLOGICAL SURVEY REPORT FOR AREAS 2 AND 3 OF THE SORRENTO VALLEY WEST LAND AREA Prepared by: Cornelius Stanley, Richard Stowell, Laura Gonzales, Paul Maschka, Barbara Hunter, Joseph Sullivan, Jeff Vassett, Michael Dupray and Phil Poole February 2001
Final Radiological Survey Report for the Sorrento Valley West Land - Areas 2 and 3 +CMU,*WS TABLE OF CONTENTS Pag.e Introdu ction I
Site Description..............................................................
1I Criteria For Release to Unrestricted Use...............................................
2 Facilities and Equipm ent.....................................................
2 Exposure Rate G uideline 2
Soil Release C riteria.....................................................
2 Instrum entation 3
Background M easurem ents..................
3 Background Measurements for Instruments/Detectors.............................
3 Background Soil Concentrations...............................
4 Exposure Rate Background.......
Previous Activities (History of Use).....
Decontamination Activities Final Survey Plan...................
Objectives and Responsibilities Classification of Areas Survey Summary....................
Soil Samples from Underneath the Asphalt Soil Samples Collected.........
Sample Preparation and Counting Results of Final Surveys..............
Scanning....................
Fixed Measurements...........
Removable Contamination Surveys Exposure Rate Surveys.........
. 4 S.
.4 5
S.
5 S.
5 S.
5
..°.
6 6
6
. °.
... 6 7
. 7
. 7
. 7 S.
. 8 Soil S am ples...........................................................
8 GA Internal Confirmatory Survey.................................................
8 P urpo se...........................
........... 8 Survey Description and Results of the Internal Confirmatory Survey...............
8 B eta Scans.......................................................
8 G am m a Scans....................................................
8 Soil S am ples.....................................................
9 A dditional Survey.................................................
9 C onclu sion 9
ii
Final Radiological Survey Report for the Sorrento Valley West Land - Areas 2 and 3 +Gm,,w Table 1:
Table 2:
Table 3:
Table 4:
Table 5:
Table 6:
Table CS 1:
LIST OF TABLES Page USNRC's Acceptable Surface Contamination Levels.......................
10 State of CA Acceptable Surface Contamination Levels......................
11 L ist of Instrum ents..................................................
12 Results of Final Surveys in Areas 2 & 3 17 Soil Sample Results................................................
18 Background Soil Sample Results........................................
22 Gamma Spectroscopy Results of SVW Area 2 Confirmatory Survey Soil Samples
... 23 LIST OF FIGURES (unuaLed)
Figure 1:
Figure 2:
Figure 3:
Figure 4:
Figure 5:
Figure 6:
Figure 7:
Figure 8:
Figure 9:
Figure 10:
Figure H1:
Figure 12:
Figure 13:
Figure 14:
Figure 15:
Figure 16:
Figure 17:
Figure 18:
Figure 19:
Figure 20:
Figure CS I:
Figure CS 2:
Figure CS 3:
Figure CS 4:
Appendix A:
Appendix B:
Plan View of the GA Site Sorrento Valley West (SVW) Land Area within the Sorrento Valley Site Sorrento Valley West Land Area Showing Areas 1, 2 and 3 Initial Survey of Area 2 of SVW 100% 434 cm 2 Beta Scan of Area 2 of SVW 10% 434 cm 2 Alpha Scan of Area 2 of SVW Exposure Rate Surface Scan Survey of Area 2 of SVW Exposure Rate Survey Measurements of Area 2 of SVW Alpha and Beta Fixed Measurements of Area 2 of SVW Smear Survey of Area 2 of SVW Locations of Soil Samples Collected in Area 2 of SVW 100% 434 cm 2 Beta Scan of Area 3 of SVW 10% 434 cm 2 Alpha Scan of Area 3 of SVW Alpha and Beta Fixed Measurements of Area 3 of SVW Smear Survey of Area 3 of SVW Exposure Rate Measurements of Area 3 of SVW Exposure Rate Surface Scan Survey of Area 3 of SVW 100% 434 cm 2 Beta Scan Survey of Area 3 Loading Dock 10% 434 cm 2 Alpha Scan Survey of Area 3 Loading Dock Alpha and Beta Fixed Measurements of Area 3 Loading Dock Areas 2 and 3 Confirmatory Survey Beta Scans Areas 2 and 3 Confirmatory Survey MicroR Scans Areas 2 and 3 Confirmatory Survey Soil Samples Additional Survey of a Portion of Areas 2 and 3 Survey Plan for Sorrento Valley West Land Area GA Confirmatory Survey Plan for Sorrento Valley West iii
Final Radiological Survey Report for the Sorrento Valley West Land - Areas 2 and 3 Introduction General Atomics is continuing its efforts directed at decontaminating, as appropriate, and obtaining the release to unrestricted use of selected facilities and land areas at General Atomics. GA has recently completed the Final Radiological Survey of "Areas 2 and 3" of the Sorrento Valley West (SVW) land area. The Sorrento Valley West (SVW) Land Area is located in GA's Sorrento Valley Site (Figure 1), and is comprised of three (3) areas: Area 1, Area 2 and Area 3.
This report documents the results of extensive and comprehensive radiological measurements completed in Areas 2 and 3 of the SVW Land Area; the total of which is - 43,700 ft2. The results of the surveys performed demonstrate that this area meets the approved criteria for release to unrestricted use. A summary of the results is provided in this report.
Note: The Final Radiological Survey of "Area 1" of the Sorrento Valley West (SVW) Land area was completed in advance of the rest of the SVW area due to GA's urgent need to begin construction of a trench needed for an important government project. The request to delete SVW "Area I" from GA's radioactive materials licenses was made to the NRC and the State of CA on January 10, 2001 (letter 696/CAL-3311 which included the Final Radiological Survey Report for SVW "Area I "). In response to GA's request, Mr. Emilio Garcia from NRC's Region IV office performed a radiological survey of the Sorrento Valley West Area I land area on January 10, 2001. A copy of GA's final survey ("Area I ") report was provided to Mr. Emilio Garcia prior to his surveying Area I of Sorrento Valley West land area.
Site Description A plan view of the GA Site is shown in Figure 1. The Sorrento Valley West (SVW) Land Area is located on GA's Sorrento Valley Site. The location of the Sorrento Valley West Land Area in relation to other facilities and land areas on GA's Sorrento Valley Site is shown in Figure 2. The three Sorrento Valley West Land Areas (Area 1, Area 2 and Area 3) are shown in Figure 3. Area I occupies -19,000 ft2, Areas 2 and 3 occupy - 43,700 ft-.
The only history of radioactive materials use on the SVW land area occurred in a former radioactive materials storage area located in a portion of Area 2. This fenced-in area occupies about 8,500 ft2 and was used for the storage of packaged radioactive waste and for the preparation of concrete slabs and other materials for bulk shipment. Initially, the land area was classified as an unaffected area.
However, radiological surveys determined that radioactive contamination above the release limits existed in the soil and asphalt of the previous radioactive waste storage area. Analysis of asphalt and soil demonstrated that the predominant contaminant was Cs-137, which GA believes was a result of preparation of Hot Cell concrete slabs for bulk shipment during decommissioning of its Hot Cell I
Final Radiological Survey Report for the Sorrento Valley West Land - Areas 2 and 3 +cWMaLAMwcS Facility (Building 23). The fenced-in area (and surrounding area as shown in Figure 4) was reclassified as a suspect affected area. GA remediated the area and conducted additional surveys during the Final Radiological Survey.
Criteria for Release to Unrestricted Use Facilities and Equipment U.S. NRC's criteria for releasing facilities and equipment to unrestricted use is shown in Table I. The State of California's guidelines, "DHS Criteria for Release of Facilities and Equipment to Unrestricted Use," also known as "DECON-1," is shown in Table 2.
Based on the gamma spectroscopy results of asphalt and soil which detected Cs-137 as the predominant contaminant (with trace quantities of Co-60), the approved guideline values for release to unrestricted use are provided below:
5,000 dpm/l100 cm 2 (averaged over a I m2 area) 15,000 dpm/100 cm 2 (maximum in a 100 cm 2 area if the average over I m2 is met) 1000 dpm/100 cm 2 (removable activity)
Exposure Rate Guideline The guideline value for exposure rates measured at I m above the surface, is 10 /.R/hr above background levels.
Soil Release Criteria The predominant radionuclides found in soil at GA and the soil release criteria (above background concentrations) in pCi/g for these radionuclides is provided below:
Cs-137 15 pCi/g Co-60 8 pCi/g Thorium (Th-228 + Th-232) 10 pCi/g Enriched Uranium (U-234 + U-235) 30 pCi/g Depleted Uranium 35 pCi/g If more than one radionuclide exists, the sum of the fractions of the concentrations is calculated as follows:
C <1 i= 1 L. ! A 2
Final Radiological Survey Report for the Sorrento Valley West Land - Areas 2 and 3 +
-mm,,
Where Ci
= The average concentration of radionuclides i in the soil above background levels.
Li = The release criteria for radio nuclides i.
The sum of the fractions must be less than or equal to one in order for the soil to meet the release criteria.
Instrumentation A list of instruments used during the radiological surveys is shown in Table 3. The table includes: (1) a description of the instrument, model number and its serial number, (2) a description of the detector (if applicable) and its serial number, (3) instrument ranges, (4) calibration due dates, (5) typical background readings and MDA's (minimum detectable activities), and (6) calibration efficiencies.
All of the instruments used were calibrated semiannually and after repair except for exposure rate meters which were calibrated quarterly.
Background Measurements Background Measurements for Instruments/Detectors Asphalt backgrounds were obtained outside of Building 10 on GA's main site. This land area is unaffected.
For the fixed background measurements, shown in Table 3, the mean and standard deviation for each surface surveyed with the 100 cm 2 gas flow proportional detector were calculated using equations 8 11 and 8-12 from the draft version of NUREG/CR-5849' as shown below:
Equation (8-11) x=--2.,i=l X!
ns Equation (8-12)
EA n (x-x,)2 n-I Minimum detectable activities (MDA's) for each type of surface (see Table 3), were calculated using equation (5-2) from the NUREG/CR-5849 as shown below:
for Conducting Radiological Surveys in Support of License Termination (Draft for Comment), NUREG/CR-5849, ORAU-92/C57, Oak Ridge Associated Universities, June 1992.
3
Final Radiological Survey Report for the Sorrento Valley West Land - Areas 2 and 3
+CWAWA, OS Equation (5-2) 2.71+4.65 B xt MDA -
R (dpm/100cm 2) txEx,-A Where:
100 BR =background rate (cpm) t = count time (min)
E = efficiency A = area of the detector (cm 2)
Background Soil Concentrations Typical background concentrations measured by gamma spectroscopy in soil near the GA site have been established (at the 95% confidence level) and are provided in Table 6. The soil samples were counted for 30 minutes each (same count time as the soil samples collected in Areas 2 and 3 of SVW).
Exposure Rate Background Typical exposure rate background for this site is about 15 pR/hr measured at I m from the surface.
This value can be measured south of Building 15 (an office building on the eastern portion of the GA site). Measurements taken offsite in 10 different locations over a period of a year also give an average of about 15 ptRlhr (measured at 1 m from the surface). Normal background exposure rates increase to about 22 HRJhr at I m from the surface in small rooms with concrete floors and walls and up to 28 4R/hr inside concrete lined trenches or concrete lined pits (background measurements inside a concrete pit near Building 2 confirm this).
Previous Activities (History of Use)
The only history of radioactive materials use occurred in the south fenced area, within what is referred to as "Area 2" in this report. This fenced area was used for the storage of packaged radioactive waste and preparation of concrete slabs and other contaminated solid materials for bulk shipment. Initially, the land area was classified as an unaffected area. However, radiological surveys determined that radioactive contamination above the release limits existed in the soil and asphalt of the previous radioactive waste storage area. Analysis of asphalt and soil demonstrated that the predominant contaminant was Cs-137, which apparently was a result of preparation of Hot Cell concrete slabs for bulk shipment during decommissioning of its Hot Cell Facility (Building 23). The fenced-in area (and surrounding area as shown in Figure 4) was reclassified as a suspect affected area.
4
Final Radiological Survey Report for the Sorrento Valley West Land - Areas 2 and 3 +C.4u*m.,,,,
Decontamination Activities During scanning of the area using a beta gas flow proportional detector (with a 434 cm2 detector),
elevated levels well above the alert levels were noted. These levels were verified using micro R meters and geiger counters. Contamination levels up to -936,000 dpm/100 cm 2 (well above the average allowable release level of 5,000 dpm/100 cm2 were noted. See Figure 4 for the results of the initial survey.
The contaminated asphalt and soil were removed and the area re-surveyed. This process was repeated until radiation levels met the approved release criteria. Approximately 69.5 ft3 of asphalt/soil was removed during decontamination activities. This material will be disposed of as radioactive waste.
Post decontamination surveys demonstrated that radiation levels had decreased to levels below the approved release criteria. This location was reclassified as a suspect affected area and additional surveys performed to demonstrate compliance with the release criteria.
Final Survey Plan Obiectives and Responsibilities The objectives of the final survey plan wdre (1) to demonstrate that the average surface contamination levels for each survey unit were within the approved release criteria, (2) to show that the maximum residual activity ("hot spot" area) did not exceed three times the average value in an area up to 100 cm 2, (3) that a reasonable effort was made to clean removable contamination and fixed contamination (4) that the exposure rates are less than 10 pR/hr above background measured at 1 meter above the surface, and (5) that the soil concentrations were below the approved soil release criteria.
Surveys were taken only by qualified Health Physics Technicians having a minimum of three years Health Physics experience in accordance with approved Survey Plans. Samples were counted in GA's Health Physics Laboratory which maintains an effective QA program.
A copy of the Survey Plan is provided in Appendix A.
Classification of Areas There was no history of radioactive materials use in this area other than storage of packaged radioactive waste in the south fenced area which had been posted with a "Caution, Radioactive Materials" sign. Therefore, the land area was originally classified as an unaffected area. However, radiological surveys determined that radioactive contamination above the release limits existed in an area previously used for radioactive waste storage and the preparation of contaminated soil materials for bulk shipment. Analysis of asphalt and soil demonstrated that the predominant contaminant was Cs-137.
5
Final Radiological Survey Report for the Sorrento Valley West Land - Areas 2 and 3 +4MWWA A,,,,S This location was reclassified as a suspect affected area. The contaminated asphalt and soil were removed and the area re-surveyed. This process was repeated until radiation levels met the approved release criteria. Approximately 69.5 ft3 of asphalt/soil was removed during decontamination activities. Additional surveys (as required for suspect affected areas) were performed in Area 2. In addition, a total of 61 soil samples, in a 5 m triangular grid pattern as shown in Figure 11, were collected.
Survey Summary A summary of the number of fixed measurements, smears, exposure rate measurements (gR/hr), and samples taken is provided below:
SVW Areas 2 and 3 -- Survey Summary Survey
- of Fixed
- of Smears
- of Exposure Rate
- of Soil Measurements Measurements Samples
(__R/hr)
Final Survey 286 145 392 @ contact Area 2 392 @ I meter 61 Final Survey 95 33 67 @ contact Area 3 67 @ 1 meter Total 381 178 918 61 Soil Samples from Underneath the Asphalt Soil Samples Collected A total of 61 soil samples were collected underneath the asphalt; primarily in Area 2, where decontamination activities occurred. The approximate locations are shown in Figure I 1.
Sample Preparation and Counting Each of these samples were properly logged, labeled, packaged and tracked. Samples were dried, placed into a marinelli beaker, weighed and counted by gamma spectroscopy. All samples were analyzed in GA's Health Physics Laboratory with a Canberra Low Sensitivity Gamma Spectroscopy MCA System using a high purity Germanium Detector. The system is calibrated using NIST traceable standards and performance checked daily.
Samples were counted for a minimum of 30 minutes each. A 30 minute count is sufficient to detect the radionuclides of interest (Cs-137, Co-60, U-235, U-238 and thorium daughters) at levels well below GA's approved release criteria.
6
Final Radiological Survey Report for the Sorrento Valley West Land - Areas 2 and 3 +G--,l-Anc Results of the Final Surveys Scanning Scans with the 434 cm 2 gas-flow proportional detectors (floor monitors) were conducted in order to identify elevated areas of activity. Areas with elevated readings were further investigated with either the 100 cm 2 (P3) gas-flow proportional detectors or hand held (ca and P3) instruments/detectors to determine if the levels were above the release criteria.
The results of these scans are provided in Table 4 and Figures 5 and 6 for Area 2, Figures 12 and 13 for Area 3 and Figures 18 and 19 for the loading dock located in Area 3. After remediation, scans showed radiation levels below the alert levels.
Fixed Measurements A total of 381 fixed measurements were taken during the final survey. An appropriate background was determined for each type of surface and subtracted from the survey readings. The readings were converted from cpm to dpm/100 cm2 using the appropriate count time, the efficiency of the detector and the geometry of the detector. The results are provided in Table 4 and the approximate locations (and results) are shown in Figure 9 for Area 2, Figure 14 for Area 3, and Figure 20 for the loading dock located in Area 3.
Of the 381 fixed measurements, 188 were alpha measurements and 193 were beta measurements. For the alpha measurements, fixed measurements (-6-10 seconds) were taken using a 50 cm 2 hand-held alpha detector. All results were <218 dpm/100 cm 2 after decontamination.
For the 193 beta measurements, one minute fixed measurements were taken using a beta gas proportional counter having a 100 cm2 detector. All results were <445 dpm/ 100 cm 2 after decontamination; well below the beta/gamma limit of 5,000 dpm/ 100 averaged over I r.
Removable Contamination Surveys Removable contamination measurements (smears) were performed on all asphalt an concrete surfaces.
A total of 178 smears were taken during the final survey.
Smears consisted of using a Whatman Filter Paper (4.7 cm 2 diameter) and wiping an area of - 100 cm 2. The smears were counted in GA's Health Physics Laboratory using a Canberra 2400 low level alpha/beta counting system. The maximum smear result in dpm/100 cm 2 for both alpha and beta are provided in Table 4 and the approximate locations are shown in Figure 10 for Area 2 and Figure 15 for Area 3. The maximum smear results were 18 dpm/100 cm 2 a and 22 dpm/100 cm 2 P3; well below the release criteria of 1000 dpm/100 cm 2.
7
Final Radiological Survey Report for the Sorrento Valley West Land - Areas 2 and 3 +C S
Exposure Rate Measurements The summary of exposure rate measurements is provided in Table 4. Surface scan results ranged from 15-24 IR/hr; see Figure 7 for Area 2 and Figure 17 for Area 3. Contact readings ranged from 12-25 pR/hr and fixed measurements taken 1 m readings ranged from H -24 /R/hr; see Figure 8 for Area 2 and Figure 16 for Area 3.
Soil Samples A total of 61 soil samples were collected underneath the asphalt; primarily in Area 2 where decontamination activities occurred. The approximate locations are shown in Figure 11.
The gamma spectroscopy results are provided in Table 5. The results show radioactivity levels at or near natural background levels (see Table 6); all levels were far below the approved soil release criteria.
GA Internal Confirmatory Survey Purpose GA conducted an Internal Confirmatory Survey to ensure that the results of the Final Survey are indeed below the State of California RHB and NRC approved release criteria. This survey was conducted in accordance with a written survey plan, by Health Physics Technicians not assigned to perform the Final Survey (i.e., an independent survey). A copy of the Confirmatory Survey Plan for the SVW area is provided in Appendix B.
Survey Description and Results of the Internal Confirmatory Survey Beta Scans Scans using the 434 cm 2 gas-flow proportional beta detectors were conducted on asphalt and concrete surfaces as shown in Figure CS 1. During these scans two small spots of contamination, <15 cm 2, were detected in the Suspect Affected Area at grid M,3. These two, 5,000 cpm and 8,000 cpm, spots were chipped up using a hammer and chisel and disposed of as radioactive waste. Subsequent scans of grid M,3 were 1700 to 2000 cpm. Overall scan results for all of Areas 2 & 3 range from 1200 to 2400 cpm on asphalt and 1600 to 2000 cpm on concrete. All were at or near background levels of 1900 to 2400 cpm for asphalt and 1400 to 2200 cpm for concrete.
Results: No contamination remains.
Gamma Scans Scans using pR meters (2" X 2"NaI detectors) were also conducted on all surfaces as shown in Figure CS 2. During these scans one small spot of contamination, <15 cm 2, was detected in the Suspect Affected Area at grid M,2. This 34 lpR/hr spot was chipped up using a hammer and chisel and 8
Final Radiological Survey Report for the Sorrento Valley West Land - Areas 2 and 3 +6---=M=U, disposed of as radioactive waste. Subsequent scans of the grid M,2 were 19 to 23 pR/hr. Overall scan results for all of Areas 2 and 3 range from 14 to 18 pR/hr for concrete, 15 to 25 pR/hr for soil, and 14 to 25 VR/hr for asphalt. All were at or near background levels of 13 to 18 pR/hr for concrete, 12 to 19 pR/hr for soil and 17 to 21 pR/hr for asphalt.
Results: No contamination remains.
Soil Samples Soil samples were collected inside the Suspect Affected Area of SVW Area 2 where the asphalt had been remediated and at one location where the bank had been remediated. A total of 14 surface soil samples, 0-6", were collected. The soil sample locations are shown in Figure CS 3 and the individual results are provided in Table CS 1.
Results: All 14 soil samples were below the release criteria.
Additional Survey:
Because contamination above the release criteria was found during GA's Internal Confirmatory Survey, an additional survey was performed by another technician who had limited duties during previous surveys.
Scans using both the 434 cm 2 gas-flow proportional beta detector and a microR meter (2"x2" Nal detector), were conducted in an area of -85.5 m2 just inside the eastern fence of the prior radioactive materials area. The survey results are provided in Figure CS 4. Beta scan results ranged from 1700-2300 cpm; levels at or near the background levels of 2175-2460 cpm for this instrument and that type of surface (asphalt). MicroR scan results ranged from 18-23 ptR/hr (surface) compared to typical background of 17-20 microR/hr on the surface.
Conclusion Final contamination and radiation surveys as well as soil sample results provided in this report for Areas 2 and 3 of the Sorrento Valley West Land Area, demonstrate that these areas meet the approved criteria for release to unrestricted use.
9
Table 1: USNRC'S ACCEPTABLE SURFACE CONTAMINATION LEVELS Nuclides Average'-'
Maximumb'AS Removableb.,
(dpm/100_m')
(dpm/100 cm_)
(dpm/100cm2)
U-nat, 235U, 238U, & associated decay products 5,000 u 15,000 a 1,000 U Transuranics, 226Ra, 128Ra, 230Th, 228Th, 231Pa, 100 300 20 227Ac, 1251, 1291 Th-nat, 232Th, 9°Sr, 2 3Ra, 224Ra, 232U, 1261, 133I, 1,000 3,000 200 1311 Beta/gamma emitters (nuclides with decay modes other than alpha emission or 5,000 15,000 1,000 spontaneous fission) except 90Sr and other 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 table 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, efficiency, an 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.
d The maximum contamination level applies to an area of not more than 100 cm 2.
e The amount of removable radioactive material per 100 cm 2 of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, then pertinent levels should be reduced proportionally and the entire surface should be wiped.
f The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mRad/hr at 1 cm 2 and 1.0 mRad/hr at 1 cm 2, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.
I Guidelines For Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses For byproduct, Source, or Special Nuclear Material, USNRC, July 1982, incorporated into GA's SNM 696 license.
10
Table 2: STATE OF CA ACCEPTABLE SURFACE CONTAMINATION LEVELS Nuclides' Averageb'.s Maximumh.J I
Renmvablebf I____ (dpm/lOOcm2)
(dpm/lOOcm2)
(dpm/0n0Ocm 2)
U-nat, 235U, 238U, & associated decay 5,000 15,000 1,000 products Transuranics, 226Ra, 228Ra, '1-rh, 228Th, 100 300 20 2D'Pa, 227 Ac, 121, 1291 Th-nat, 232Th, 90Sr, 223Ra, 224Ra, 232U, 1261, 1,000 3,000 200 1331, 1 I Beta/gamma emitters (nuclides with decay modes other than alpha emission or 5,000 15,000 1,000 spontaneous fission) except 9"Sr and other 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 table 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, efficiency, an 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.
d The maximum contamination level applies to an area of not more than 100 cm 2 e
The amount of removable radioactive material per 100 cm 2 of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, then pertinent levels should be reduced proportionally and the entire surface should be wiped.
f The average and maximum radiation levels associated with surface contamination resulting from beta gamma emitters should not exceed 0.2 mrad/hr at 1 cm 2 and 1.0 mrad/hr at 1 cm2, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.
Guidelines For Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses For byproduct, Source, or Special Nuclear Material, also known as "Decon-l incorporated into GA's State of CA Radioactive Materials License.
11
Table 3: List of Instruments Meter Detector Detector Calibration Efficiency Range
Background
Description S/N S/N Due Date (cpm) and MDA (minimum detectable activity)
Ludlum Rate Ludlum S/N 148926 02-26-01 21.25%
Four Linear 0-20 cpm The instrument is a gas-flow proportional counter Meter Model 07-20-01 21.25%
Ranges 0-(asphalt and with an active probe area of 434 cm'. The detector Model 2221 43-37 500,000 &
concrete) and rate meter are combined and mounted on a roll S/N 97287 434 cm 2 One Log 50-around cart. The instrument features a static-flow Alpha 500,000 system, quick connects, a portable gas bottle and a means to adjust the height of the detector from the floor for optimum performance.
Ludlum Rate Ludlum S/N 94119 06-09-01 20.13%
Four Linear (cpm)
The instrument is a gas-flow proportional counter Meter Model 07-03-01 20.42%
Ranges 0-1900-2400 with an active probe area of 434 cm2. The detector Model 2221 43-37 07-05-01 20.13%
500,000 &
(asphalt) and rate meter are combined and mounted on a roll S/N 97817 434 cm 2 07-18-01 20.03%
One Log 50-around cart. The instrument features a static-flow Beta 500,000 1400-2200 system, quick connects, a portable gas bottle and a means to adjust the height of the detector from the floor for optimum performance.
Ludlum Rate Ludlum S/N 149017 04-09-01 22.72%
Four Linear (cpm)
The instrument is a gas-flow proportional counter Meter Model 07-04-01 22.64%
Ranges 0-2175-2460 with an active probe area of 434 cm 2. The detector Model 2221 43-37 500,000 &
(asphalt) and rate meter are combined and mounted on a roll S/N 154202 434 cm2 One Log 50-around cart. The instrument features a static-flow Beta 500,000 1600-1995 system, quick connects, a portable gas bottle and a (concrete) means to adjust the height of the detector from the floor for optimum performance.
Ludlum Rate Ludlum S/N 092451 07-05-01 20.39%
Four Linear (cpm)
The instrument is a gas-flow proportional counter Meter Model 06-14-01 20.45%
Ranges 0-1900-2300 with an active probe area of 434 cm 2. The detector Model 2221 43-37 07-03-01 20.13%
500,000 &
(asphalt) and rate meter are combined and mounted on a roll S/N 86302 434 cm 2 07-18-01 20.31%
One Log 50-around cart. The instrument features a static-flow Beta 500,000 1400-2100 system, quick connects, a portable gas bottle and a (concrete) means to adjust the height of the detector from the floor for optimum performance.
12
Table 3: List of Instruments Meter Detector Detector Calibration Efficiency Range
Background
Description SIN S/N Due Date (cpm) and MDA (minimum detecable activity)
Ludlum Rate Ludlum S/N 120477 06-06-01 27.11%
Four Linear 644 +/- 26 cpm The instrument is a gas-flow proportional counter Meter Model Ranges 0-MDA = 445 with an active probe area of 100 cm 2.
Model 2221 43-68 500,000 &
dpm/100 cm2 r
S/N 148436 100 cm 2 One Log 50-(asphalt)
"Beta 500,000 554 + 28 cpm MDA = 414 dpm/100 cm2 (Concrete)
S.....
pm )
02-20-01 21.35%
Four Ranges 0-100,000 (cpm)
Concrete 80-140 Asphalt 80-100 MDA - 1,500 dpm/100 cm2 I _______________
.1.
.1.
1 I
I Ludlum S/N 092192 Model 43-65 50 cm2 Alpha 03-26-01 21.58%
Four Ranges 0-500,000 0-20 cpm MDA - 218 dpm/100 cm 2 The instrument is used pr beta/gamma surveying.
The detector has an active probe area of 15 cm2.
Alpha scintillator ZnS(Ag) with an active probe area of 50 cm2.
I I__
I I__
_ J_
_ J_
1_
13 S/N 145963 Ludlum Model 44-9 15 cm 2 Beta/Gamma Ludlum Model 3 S.N 138880 Ludlum Model 12 S/N 91103
Table 3: List of Instruments Meter Detector Detector Calibration Efficiency Range
Background
Description S/N S/N Due Date (cpm) and MDA (minimum detectable activity)
Ludlum Ratemeter S/N 155190 03-08-01 N/A Four Ranges (In kzR/hr)
Used for measuring external dose rates on the Model 3 coupled to a 0-500 /R/hr surface and at one (1) meter from the surface (i.e.,
Ratemeter Nal Model Soil initial ground floor surveys). The scintillator [2" x S/N 153590 44-10 11-13 contact 2" Nal (TI)] contained in an external probe.
Nal detector 11-13 @ lm Asphalt 19-21 contact 18-20 @ I m Concrete 15-18 @ Im Ludlum Ratemeter S/N 155109 04-04-01 N/A Four Ranges (In iR/hr)
Used for measuring external dose rates on the Model 3 coupled to a 03-20-01 0-500 gR/hr surface and at one (1) meter from the surface (i.e.,
Ratemeter Nal Model Soil initial ground floor surveys). The scintillator [2" x S/N 153551 44-10 11-13 contact 2" Nal (TI)] contained in an external probe.
Nal detector 11-13 @ Im Asphalt 17-20 contact 17-19 @ I m Concrete 15-18 @ Im 14
Table 3: List of Instruments Meter Detector Detector Calibration Efficiency Range
Background
Description SIN S/N Due Date (cpin) and MDA (minimum detectable activity)
Ludlum Ratemeter S/N 154618 04-06-01 N/A Four Ranges (In/uR/hr)
Used for measuring external dose rates on the Model 3 coupled to a 01-08-01 0-500 kR/hr surface and at one (1) meter from the surface (i.e.,
Ratemeter Nal Model Soil initial ground floor surveys). The scintillator [2" x S/N 151348 44-10 13-19 contact 2" Nal (T1)] contained in an external probe.
Nal detector 19-20 @ Im Asphalt 20-21 contact 19-20 @ I m Concrete 19-20 @ lm Ludlum Ratemeter S/N 153765 01-31-01 N/A Four Ranges (In MR/hr)
Used for measuring external dose rates on the Model 3 coupled to a 0-500,R/hr surface and at one (1) meter from the surface (i.e.,
Ratemeter NaI Model Soil initial ground floor surveys). The scintillator [2" x SiN 147819 44-10 12-17 contact 2" Nal (TI)] contained in an external probe.
NaI detector 16-18 @ lm Asphalt 18-19 contact 13-18 @C1 m Concrete 16-18 @ Im Canberra High Purity Calibrated as needed.
Varies with Varies with Gamma Spectroscopy MCA system using a high Gamma Germanium N/A Calibration checked daily Sample Sample purity Germanium detector.
Spectroscopy Detector with NIST traceable standard.
System Efficiency varies with sample.
15
16 Table 3: list of Instruments
\\Meter Detector Detector Calibration Efficiency Range
Background
Description S/N S/N Due Date (cpmn) and MDA mininimunm detectable activily)
Canberra Gas Flow N/A As needed 30%
N/A Varies with Canberra Model 2400 Low Level a/[3 gas Low Level Proportional Sample proportional counting system used to count wipes (4P/ Counter Detector for removable contamination. Results are usually I_
I_
I_
I_
I_
I Ireported as dpm/100 cm 2.
17
Table 5: Gamma Spectroscopy Results of Sorrento Valley West Area 2 Final Survey Soil Samples 0)
Radionuclide Concentration (pCi/gm) - Results + 2a - Backgrounds not Subtracted-Approximately 30 Minute Counts Sample ID Grid 137 CS 60Co 228Th 232 Th Total 238U 235u Coordinate 661.6 keV 1173 keV 238 keV peak 911 keV Thorium 63 keV peak 144 keV peak peak peak peak 228Th + 232
(
)
(186 keV peak)
SVW-1 B,2 0.11 +/- 0.07 ND 1.49 +/- 0.13 2.00 +/- 0.37 3.49 2.92 +/- 0.87 (0.24 +/- 0.12)
SVW-2 B,3 0.16 +/- 0.09 ND 1.57 + 0.12 2.02 + 0.32 3.59 2.28 +/- 1.28 (0.16 +/- 0.09)
SVW-3 B,5 0.12 + 0.08 ND 1.59 + 0.13 2.30 +/- 0.40 3.89 2.05 +/- 1.40 (0.15 +/- 0.09)
SVW-4 B,6 ND ND 1.58 +/- 0.12 2.03 +/- 0.37 3.61 1.72 +/- 1.03 (0.17 +/- 0.09)
SVW-5 B,8 ND ND 1.27 +/- 0.11 1.55 +/- 0.33 2.82 0.92 +/- 0.90 (0.14 +/- 0.08)
SVW-6 B,9 ND ND 1.32 +/- 0.10 1.48 +/- 0.34 2.80 1.39 +/- 0.97 (0.20 +/- 0.07)
SVW-7 C,8 ND ND 1.34 +/- 0.12 1.98 +/- 0.39 3.33 2.26 + 1.28 (0.14 +/- 0.08)
SVW-8 C,7 ND ND 1.51 +/- 0.12 1.79 +/- 0.36 3.29 1.06 +/- 1.16 (0.19 +/- 0.09)
SVW-9 C,5 ND ND 1.46 +/- 0.12 1.92 +/- 0.37 3.38 0.94 +/- 1.14 (0.15 +/- 0.08)
SVW-10 C,4 ND ND 1.68 +/- 0.11 1.64 +/- 0.33 3.32 1.47 +/- 0.98 (0.21 +/- 0.08)
SVW-11 C,2 ND ND 1.62 k 0.13 2.23 +/- 0.40 3.85 1.74 + 1.20 (0.30 +/- 0.13)
SVW-12 C,1 ND ND 1.68 +/- 0.12 2.37 +/- 0.39 4.04 (1.77 +/- 0.76)
(0.18 +/- 0.12)
SVW-13 E,2 ND ND 1.63 +/- 0.12 2.04 +/- 0.38 3.67 1.38 +/- 1.01 (0.18 +/- 0.09)
SVW-14 E,3 ND ND 1.64 +/- 0.11 1.79 +/- 0.31 3.42 2.08 +/- 1.26 (0.14 +/- 0.08)
SVW-15 E,5 ND ND 1.64 +/- 0.18 1.84 +/- 0.52 3.47 (2.16 +/- 1.14)
(0.21 +/- 0.11)
SVW-16 E,6 ND ND 1.40 +/- 0.12 1.62 +/- 0.29 3.02 1.83 +/- 0.95 (0.15 +/- 0.06)
SVW-17 E,8 ND ND 1.51 +/- 0.12 1.85 +/- 0.34 3.36 1.65 +/- 1.11 (0.09 +/- 0.09) 18
Table 5: Gamma Spectroscopy Results of Sorrento Valley West Area 2 Final Survey Soil Samples (1 Radionuclide Concentration (pCi/gm) - Results ý- 2o - Backgrounds not Subtracted - Approximately 30 Minute Counts Sample ID Grid 13CS 60Co 228Th 232 Th Total 238u 235U keV 1173 keV 238 keV peak 911 keV T horium 63 keV peak 144 keV peak peak peak I
peak
'2 Th + 232 Th (93 keV peak)
(186 keV peak)
SVW-18 E,9 ND ND 1.40 +/- 0.09 1.69 +/- 0.24 3.09 1.30 - 1.01 (0.11+/- 0.06)
SVW-19 F,8 ND ND 1.38 + 0.19 2.18 +/- 0.41 3.56 (2.25 +/- 0.77)
(0.19 +/- 0.10)
SVW-20 F,7 ND ND 1.70 +/- 0.11 1.85 + 0.25 3.54 0.93 +/- 0.92 (0.12 +/- 0.06)
SVW-21 F,5 ND ND 1.69 +/- 0.13 2.42 + 0.38 4.11 1.04 +/- 1.21 (0.21 +/- 0.13):
SVW-22 F,4 ND ND 1.64 +/- 0.11 1.64 +/- 0.35 3.28 1.53 +/- 0.94 (0.18 +/- 0.07)
SVW-23 F,2 ND ND 1.76 +/- 0.14 2.24 +/- 0.44 4.00 1.50 +/- 1.24 (0.26 +/- 0.10)
SVW-24 F,1 ND ND 1.50 + 0.11 1.81 +/- 0.28 3.31 2.71 +/- 1.02 (0.19 +/- 0.07)
SVW-25 H,2 ND ND 1.54 +/- 0.13 2.13 +/- 0.46 3.67 1.56 +/- 1.10 (0.17 4 0.10)
SVW-26 H,3 ND ND 1.60 +/- 0.11 1.80 +/- 0.35 3.40 2.33 +/- 1.56 (0.18 +/- 0.07)
SVW-27 H,5 ND ND 1.65 +/- 0.13 2.33 +/- 0.46 3.98 1.75 +/- 1.33 (0.21 +/- 0.10)
SVW-28 H,6 ND ND 1.73 +/- 0.11 1.88 +/- 0.32 3.60 2.03 +/- 1.44 (0.12 +/- 0.07)
SVW-29 H,8 ND ND 1.63 +/- 0.12 1.89 +/- 0.36 3.51 2.00 +/- 1.26 (0.18 +/- 0.12)
SVW-30 H,9 ND ND 1.32 +/- 0.10 1.42 +/- 0.30 2.74 0.92 +/- 0.89 0.25 +/- 0.24 SVW-31 1,8 ND ND 1.55 +/- 0.12 1.94 +/- 0.32 3.50 1.63 +/- 1.15 (0.08 +/- 0.09)
SVW-32 1,7 ND ND 1.37:+/- 0.11 1.80 +/- 0.33 3.16 1.32 +/- 0.87 (0.15 +/- 0.06)
SVW-33 1,5 ND ND 1.31 +/- 0.12 1.82 +/- 0.37 3.14 1.71 +/- 1.28 (0.18 + 0.09)
SVW-34 1,4 ND ND 1.45 +/- 0.11 1.87 +/- 0.30 3.32 (2.40 +/- 0.77)
(0.22 +/- 0.08) 19 I
Table 5: Gamma Spectroscopy Results of Sorrento Valley West Area 2 Final Survey Soil Samples (1)
Radionuclide Concentration (pCi/gm) - Results +/- 2o - Backgrounds not Subtracted - Approximately 30 Minute Counts Sample ID Grid 137CS 60CO 228Th 232 Th Total 23Su 235u Coordinate 661.6 keV 1173 keV 238 keV peak 911 keV Thorium 63 keV peak 144 keV peak peak peak peak 228Th + 232Th (93 keV peak)
(186 keV peak)
SVW-35 1,2 ND ND 1.47 :L 0.13 1.98 +/- 0.37 3.45 1.40 +/- 1.20 (0.16 +/- 0.09)
SVW-36 1,1 ND ND 1.59 +/- 0.11 1.98 +/- 0.38 3.57 1.36 +/- 0.12 (0.20 +/- 0.08)
SVW-37 K,2 ND ND 1.72 4- 0.14 1.73 +/- 0.29 3.45 1.88 +/- 0.14 (0.14 +/- 0.09)
SVW-38 K,3 ND ND 1.55 +/- 0.11 1.49 +/- 0.22 3.04 1.79 1 1.27 (0.18 +/- 0.06)
SVW-39 K,5 ND ND 1.45 +/- 0.12 1.86 +/- 0.34 3.31 1.45 + 1.15 (0.10 +/- 0.11)
SVW-40 K,6 ND ND 1.31 +/- 0.09 1.49 +/- 0.27 2.80 1.32 +/- 0.91 (0.16 +/- 0.06)
SVW-41 K,8 ND ND 1.68 +/- 0.13 2.18 +/- 0.42 3.86 1.01 +/- 1.25 (0.24 +/- 0.10)
SVW-42 K,9 ND ND 1.35 +/- 0.09 1.58 +/- 0.24 2.93 1.45 +/- 0.80 (0.10 +/- 0.06)
SVW-43 L,8 ND ND 1.48 +/- 0.12 2.15 +/- 0.38 3.63 1.13 +/- 1.27 (0.16 +/- 0.09)
SVW-44 L,7 ND ND 1.46 +/- 0.10 1.68 +/- 0.31 3.14 2.70 +/- 1.66 (0.17 1 0.07)
SVW-45 L,5 ND ND 1.48 +/- 0.63 2.22 +/- 0.39 3.70 1.09 +/- 1.08 (0.21 +/- 0.09)
SVW-46 L,4 ND ND 1.61 +/- 0.10 1.66 +/- 0.31 3.27 1.31 +/- 1.04 (0.20 +/- 0.08)
SVW-47 L.2 ND ND 1.67 +/- 0.14 2.33 +/- 0.39 4.00 2.37 +/- 1.26 (0.27 +/- 0.11)
SVW-48 L,1 ND ND 1.50 +/- 0.10 1.60 +/- 0.28 3.09 2.05 +/- 1.23 (0.23 +/- 0.07)
SVW-49 N,2 ND ND 1.63 +/- 0.13 2.08 +/- 0.43 3.70 0.94 1 1.12 0.46 +/- 0.40 (see re-count)
SVW-49 N,2 ND ND 1.56 +/- 0.06 1.94 +/- 0.19 3.50 2.44 +/- 0.71 (0.21 +/- 0.05) 2.5 hr count 20
Table 5: Gamma Spectroscopy Results of Sorrento Valley West Area 2 Final Sutvey Soil Samples Radionuclide Concentration (pCi/gm) - Results +/- 2a - Backgrounds not Subtracted - Approximately 30 Minute Counts Sample ID Grid 137CS 60Co 228Th 232 Th Total 238u 235U Coordinate
. V....
T ri m
.i 661.6 keV 1173 keV 238 keV peak 911 keV Thorium 63 keV peak 144 keV peak peak peak peak 228Th + 232Th (93 keV peak)
(186 keV peak)
SVW-50 N,3 ND ND 1.56 +/- 0.11 1.71 + 0.28 3.26 1.12 +/- 1.15 (0.21 +/- 0.07)
SVW-51 N,5 ND ND 1.57 +/- 0.13 2.05 +/- 0.43 3.61 0.94 +/- 1.13 (0.12 4 0.11)
SVW-52 N,6 ND ND 1.60 +/- 0.11 1.72 +/- 0.32 3.32 (2.69 +/- 0.85)
(0.12 + 0.07)
SVW-53 N,8 ND ND 1.48 +/- 0.12 2.08 +/- 0.39 3.56 (2.19 +/- 0.83)
(0.18. 0.10)
SVW-54 N,9 ND ND 1.52 +/- 0.10 1.54 +/- 0.26 3.06 (1.95 +/- 1.08)
(0.14 1 0.06)
SVW-55 P,2 ND ND 1.45 +/- 0.13 1.63 +/- 0.50 3.08 1.32 +/- 1.23 (0.21 +/- 0.10)
SVW-58 F,14 ND ND 0.88 +/- 0.08 0.77 +/- 0.25 1.65 0.94 +/- 0.83 (0.10 +/- 0.06)
SVW-60 Q,14 ND ND 1.05 +/- 0.10 1.58 +/- 0.23 2.63 1.95 +/- 0.95 (0.24 +/- 0.07)
SVW-61 S,15 ND ND 0.64 +/- 0.11 1.34 +/- 0.37 1.98 0.82 +/- 0.89 0.28 +/- 0.35 SVW-64 B,25 ND ND 1.58 +/- 0.11 1.61 +/- 0.27 3.19 2.04 E 1.12 (0.14 +/- 0.07)
SVW-65 A,25 ND ND 1.94 +/- 0.15 2.45 +/- 0.38 4.39 2.09 +/- 1.43 (0.26 +/- 0.12)
SVW-66 A,14 ND ND 1.71 +/- 0.10 1.57 - 0.27 3.28 1.65 +/- 0.98 (0.14. 0.06 See Figure 11 for approximate locations of soil samples. Note: Soil samples SVW-56, SVW-57, SVW-59, SVW-62 and SVW-63 are located in Area 1 of SVW. The results of these soil samples are in the Area 1 Final Radiological Survey Report.
ND - means Not Detected Cs-137 = < 0.1 pCi/g Co-60 = < 0.1 pCi/g 21 (1)
Table 6: Gamma Spectroscopy Results of Background Soil (Surface) Samples Radionuclide Concentrations (pCi/gm) - Results +/- 2 a - 30 Minute Counts Sample 1"7CS 6UCo 228Th 23, Th Total 2-SU
-*131U
- 11) 661.6 kcV peak 1173 keV peak 238 keV peak 911 keV peak Thorium 63.3 (92.7) 144 (186) keV 2'8Th + 2"'Th keV peak peak X-I ND ND 0.71+/- 0.07 0.97 +/- 0.25 1.69 1.17 +/- 0.77 (0.13 +/- 0.06)
X-2 ND ND 0.90 +/- 0.13 1.49 +/- 0.31 1.49 1.91 +/- 1.18 (0.13 +/- 0.08)
X-3 0.06 +/- 0.04 ND 1.49 +/- 0.10 1.56 +/- 0.25 3.05 1.45 +/- 0.80 (0.23 +/- 0.09)
X-4 ND ND 1.52 +/- 0.23 3.22 +/- 0.61 4.74 3.74 +/- 2.18 (0.28 +/- 0.17)
X-5 ND ND 1.92 +/- 0.17 2.41 +/- 0.53 4.33 (4.49 +/- 1.64)
(0.32 +/- 0.16)
X-6 ND ND 1.02 +/- 0.08 0.96 +/- 0.23 1.99 1.31 +/- 0.80 (0.14 +/- 0.06)
X-7 0.13 +/- 0.08 ND 1.59 +/- 0.14 2.40 +/- 0.38 3.98 2.16 +/- 1.48 (0.18 +/- 0.10)
X-8 ND ND 1.44 +/- 0.28 1.40 +/- 0.28 2.84 2.30 +/- 1.16 (0.14 +/- 0.09)
X-9 0.09 +/- 0.08 ND 0.89 +/- 0.10 1.27 +/- 0.31 2.15 1.59 +/- 1.05 (0.10 +/- 0.08)
X-10 ND ND 1.29 +/- 0.11 1.52 +/- 0.36 2.80 1.10 +/- 0.96 (0.16 +/- 0.08)
Notes:
- 1.
Soil samples were collected on 06/05/00 and 06/06/00 By Ed Rudgers off GA's site but close to GA.
- 2.
Samples were counted 7/20/00 through 7/24/00 for 30 minutes (same count as the soil samples).
- 3.
ND means:
< 0.1 pCi/g for Cs-137
< 0.1 pCi/g for Co-60 22
Table CS 1: Gamma Spectroscopy Results of SVW Area 2 Confirmatory Survey Soil Samples Radionuclide Concentration (pCi/gm) - Results +/ Backgrounds not Subtracted - Approximately 30 Minute Counts Grid
'3PCS 60CO 228Tb 232Th Total 3U25 Sample ID Figure #
Co-ord 661.6 keV peak 1173keV peak[ 238 keVpeak 911 keV peak Thorium 63.3(92.7) 144(186) 228 Th + 32 Th keY peak keY peak SVWCS 1 CS3 J,l ND ND 2.09+/-0.17 2.86 +/- 0.50 4.95 1.52+/- 1.30 (0.28+/-0.13)
SVW CS 2 CS 3 J,I ND ND 1.38 +/- 0.19 2.32 +/- 0.40 3.70 1.47 +/- 1.26 (0.21 0.08)
SVW CS 3 CS 3 J,1 ND ND 1.42 +/- 0.11 2.18 +/- 0.35 3.60 (1.60 +/- 0.79)
(0.20 0.08)
SVW CS 4 CS3 J,1 ND ND 1.76+/--0.14 1.92+/-0.35 3.68 1.67+/- 1.40 (0.15+/-0.11)
SVW CS 5 CS3 L,2 ND ND 1.60+/-0.13 2.06+/-0.34 3.66 1.99 +/- 1.45 (0.18-0.10)
SVWCS 6 CS3 L,2 0.18+/--0.14 ND 1.48+/-0.10 1.46+/-0.26 2.95 2.06+/- 1.37 (0.16+/-0.07)
SVW CS 7 CS3 M,2 ND ND 1.67+/-0.13 2.00+/-0.38 3.66 1.64+/- 1.33 (0.17+/-0.09)
SVW CS 8 CS 3 M,2 3.47 +/- 0.17 ND 1.61 +/- 0.12 1.96 +/- 0.29 3.57 2.38 +/- 1.03 (0.20 +/- 0.09)
SVW CS 9 CS 3 M,3 ND ND 1.62 +/- 0.14 0.96 +/- 0.46 3.58 (2.41 +/- 0.99)
(0.22 0.11)
SVW CS 10 CS 3 M,4 ND ND 1.42 +/- 0.10 1.49 +/- 0.32 2.91 1.97 +/- 1.05 (0.18 0.07)
SVWCS 11 CS3 M,6 ND ND 1.49+/-0.12 1.76+/-0.37 3.25 2.87 +/- 1.19 0.44+/-0.38 SVWCS 12 CS3 M,7 ND ND 1.45+/-0.09 1.40+/-0.29 2.85 0.88+/-0.96 (0.13+/-0.07)
SVWCS 13 CS3 1,8 ND ND 1.52+/-0.12 2.21 +/-0.29 3.72 (2.17+/--0.80)
(0.16+/-0.09)
SVWCS 14 CS3 D,9 ND ND 1.07+/--0.09 1.38+/-0.25 2.45 1.44+/- 1.21 (0.14+/-0.06)
ND - Not Detected -(<0.1 pCi/gm '3TCS, <0.1 pCi/gm 6"CO) 23
Figure 1: Main Site and Sorrento Valley Site Building Numbers Building 1 Building 2 Building 7 Building 9 Building 10 Building 13 Building 14 Building 15 Building 19 Building 21 Building 22 Building 23 Building 25 Building 27 Building 27-7 Building 29 Building 29-2 Building 30 Building 31 Building 31-1 Building 31-2 Building 31-3 Building 33 Building 33-1 Building 33-5 Building 34 Building 34-1 Building 34-2 Building 34-3 Building 35 Building 35-1 Building 36 Building 37 Building 39 Building 39-1 Building 41 Building 42 Building 45 Building 63 Building 64 Building 65 Building 66 Building 66 Names Administration Science Laboratories A. B. C Cafeteria Experimental Building Maintenance Building Technical Office Building Technical Office East Technical Office East Swimming Pool Building TRIGA Building TRIGA Fuel Lab Building Hot Cell Waste Yard Building Experimental Area Experimental Area Experimental Area Emergency Vehicle Storage Building LINAC Complex TRIGA Storage Building Neulron Radiography Building ECF Critical Building Storage Building Fusion Building Fusion Lab Building Fusion Building Annex 5 Fusion Doublet Ill Building Fusion Doublet Ill Capacitor Building Fusion Doublet III Lab Building Fusion Doublet Ill Slorage Building Test Tower Building Facilities (Shipping & Receiving) Building Blower Assembly Building Sorrenlo Valley Building Sorrento Valley Building Storage Building Raw Stock Facilily NDT Facility Helium Circulator Test Facility 3550 Dunhill Str 11930 Ruselle Sit.
11090 Roselle St
/
3520 Dunhill St.
I
/
3510 Dunhill St
$* /
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SITE cct tu Z.
LU IX cc UCSD LOTS FENCING PROPERTY LINE 0
250 500 750 1000 SCALE IN FEET N
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SITE OPEN SPACE
Figure 2: Sorrento Valley West N
S ENTO VALLEY NORTH
Sorrento Valley vegeta,.
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Wes__BANK BAN)
West geta NWPF 9
AspýhaO a Area 2 44 Aspthalt An 4Area 3 II
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.7 ea 2 S V "A" BRilding 37 w
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PLOT PLAN SCALE I -1o00 I
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a-b."n m;
o
Figure 4: Initial Survey of Area 2 of SVW Survey Date: 12/09/2000 - 01/08/2001
.. x-
-X -........X-
+-
Highest reading was
- 30,000cpm
- 936,000 dpm/100cmz Units are in cpm/15cm2 unless otherwise noted
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A-Denotes Suspect F7 Affected Area 4ý000 16o000
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Building 37 Area 2 of SVW
Figure 5: 100% 434cm 2 Beta Scan Survey of Area 2 of SVW Survey Date: 12/09/2000 - 01/15/2001 w
E
. X..
.XX.... X.....X
.+
A ix x
x D}
EN F is H
1700 1700 1800 2000
!1800 11700 2000 2000
<1800 F 1700 2000 2000 1600 11700 1900 2000 i
1600 1700 1900 12000 K)
J 17 "7'
1700 1700 2000 2000 K
1600 1700 K.- 180o 2000 X.
.. X---
-x-
-X nnn
= Denotes Area Scann s VWi Model 121 Model - 2221 Modal-2221 154202 97817 86302 04/09/2001 06/09//2001 07105/2001 2272%
20,13%
20.39%
p 149017 434cm*
2 175-.2460 094119 434cmi 1900-2400 M !
1600 1600 1900 1900 1600 1800 1900 2000 1700 1
9 1900 1800 1800 1800 2000 2100 2100 2100 2000 2100 2100-r 1700 1900 1800 1900 1900 1800 1800 2000 2000 2100 2100 2000 2150 2100 L
I M,...
'T21900229002290022900"1900 Sil 01o 1o1 1oo ! 19 00i19o 0 0,190 1,90 2100 2200 2200 2200 2200 1,2300 2I2di23_0 0-2300 i
_N 1900 1900 1900!
1 900 19 00 200 1900 1900 1900 1900 2200 12200 12200i2200 12200 2200 e
1800:1800!1800 1800 19 1700 180180 1800 180 o
170080 0710700 50I 14 iT6 uI SO
-1800 1190 190 1900 p
190p0 70 80] L+0,,+10 *,50 2
if 6
)00......190 2222020 0 2200 00 122 00o,2200 2200 1 i20 1200_122_1*
_=001I...
1800 190000 0
19 2TiO :190011500 1900 2000 12100 12000 2100 2300 2400 12400 2400 19o0919 00o 1900F 1900 1900 11900 19 1900 1900 19001 1900 1900 1900 1900; 1900 1500i 1500 I 15001 150011900 1900 1900 1900 1900 1900 220 1
00 2100 20 20120 210210 200 h6 230022302300 2
200 2200 2300 123002300 2300
-200 F 20 0 2200 2200 2200 22o-l 2
1*0- 20 2100 10 0
2100 2300 2300 2400 2400 2216000*
_4 2300 i
,_,___l_._
nmo 1900 11900 1900 1900 111900 11900 i1900 19 0 15 30*
50 150 1500 1500 1500oo 1500 1560 4150 Soo00 1500 100 1 0 100 1 0 90 90 :i*
130 100 10 o
1900 1900 1900 190 190 0
23001240 200 300-200 220 220 1 200 22
.170.170 100 1
viu
~230 I220 200220 200 2 015590 1550' F10 170 70100 1700 11700 170 1700 1700 170 I200I20 2100 2100 2100 2100 2---
190--10010900 19001090001900 190 190/90 19011900900 19090000 1
94a 1-L900 1900 J90!
1O 0'j 1900 F 1900T I
19L00 1900 1900 15 0 '1509 50 15O40 90 1900' 1900 1900 11900 N/A 2400 !2400 2400 2300 2200 2300 2200F2200 2200 i 2200 2200 i 22001 2200 2200--F 0 2 2 0 0 0
2200 2200 220 21 001 2200 2200 2100 2100 210012100 2100 1 S N/A--F 220 I
I N/0 1900 1900 1900 1900 1900 1900 1900 1900 1900 1900 19009 190001900 1900 1900 190-0a002'00 9oo 19 0099000119000_!0,1 0 I2 00 2
-900100 2 00 9001900 2200 2200 2200 2400 2300 2200 2300 2200 2200 1O2200 2200 2200 2200 2200 2
00 2200 2200 2200 2
12290000 19001 1900 11oO 1900 2200 N/A 092451 N/A 4 34cm.
N/A 1900-2300 N/A 3 meters Building 37 Area 2 of SVW x
x A-A-
A-A-,
.4-Comments: Results are provided in cpm Signature
.Paol aC Cnley C
DateT' jZ0/22000.-OI I S/0I.
4&d~C~vJ Q6 m
m
Figure 6: 10% 434cm2 Alpha Scan Survey of Area 2 of SVW Survey Date: 12/09/2000 - 01/16/2001 w
A S 4
N V
E
,/...
1 2..
3 4
5 6
7 9
10-, 11 12 x
x
- x.
B Ix X1 4-,
X-I 13 14 -
x 15 x
16 x
- 17. 18 19 x
x x
20 21 22
,X x
x 23 24 x -
25 *7,26: -27 x
A-
+
28 iA i~iB 2-17 9-18 2-9
- 7 *.
7
,., 1-17 ',6_ *
-2")
0 7-18 8 2 7-26 10-246-30 9-34 12-20 1030 10-27 9-16 E
5-14 7-25 9-25
~ I20-38 2J-4 5~ 17-35 j27-50 1 2146 1 9-36 24-40 25-34
!X X
X F
...... i, i... 7...1..... !.......... *................
cx
.1 X
-I 17-39121-38116-3920-3320_35116 -2515-2816-3323-*32 O 17_3818-35123-43222-40;15-4326-46!20-3419-37119-33 nn - nn = Denotes Scanned area readings in cpm.
Ss vw
___e_-222__1_
N/A N/A N/A 402/26/2009 N/A N/A N/A 148926 N/A N/A N/A 434cnF N/A N/A N/A fickgourdc (cpm) 0-20 N/A N/A N/A SCorimraens:
-A 1 - 3422-203--214
.26-7--.
1-17-28, 18 30,
19 -31J8-3213
-33114-23118-30! 19-44 19-37,118-36 20-33,14-26 17-3217-41 15, - 321JO 18-29-8
_ 3A7' 2
3 11 118-5.9-5 3,
-5
- 23!1 32... 16_-_ 28_20__-_27 2:
9-18 2-3 1-45I18-3519-5017-33122-43 13-32'15 -2719-3522 38 15-35117-34!14-1331 15-26 17-2415-31 18-33:14 2519-3921-3216-2820-27 I
~.
's------_______-----_
__'p l80 14301
) i*1 R
19 - 2718-24i14-31i15-2515-2618-4814-24i25-50:16-24115-30°13-241-30 12-241 11-21 10-20 14-23 15-23 182014-3012-231 13-2114-2 19-314-21 15-25 818-23R 23 -45133 -48122 -50 16 -45125 -45133 - 4120 -39117 -33;6379-229115
-271-2 1-2 12
- ___23 -433-42 06 42-37 19-32112-26;17-331 16-30 212 17-212 717 29-15 712-23 162-2514-27 T7-I I
l2 2-3 1
2 72'6 1
26 - 52 17 - 32 120 - 35125 - 4120 - 37 !16 - 3218 - 38124 - 45119 - 4114 - 2619 - 371 15 - 33' 15 - 29 14 - 34115 - 2718 - 29117 -k 16 - 30! 15 - 23ý 18 - V 17 - 34! 15 4-2l42-7-14 -6 20-32-z2---48¢-17-37 17-39 16-25 12-30-4:23--"51-6---f9-35 14-27, 12-33 10-21 14-32 17-371 3 meters Building 37 Building 37 Area 2 of SVW
-N-x x
X
-k
-N-
-N 4-I A-A-
-N-i I
I Date
Figure 7: Exposure Rate Surface Scan Survey of Area 2 of SVW 17-21 pE R/hr
-/,-
...... -x -.....
x A
x X
x x
X-X----X-x-X 4--
-N-Survey Date: 12/09/2000 - 01/04/2001 W
S "*i+
- *1-N E
2 3
4 5 7-8
'9 j 11 12 -13 14 15-16.
17 18 1:9
'20 21 22 23 24 25
-2 6 27 28 x
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x-x x -
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-23)2 232]122-244 2 242 222-2 24 A :18-24! 17_2217 2317_3I19X22,.20X-23,.I9 I22 1
- 23 17 22 24 22-24!22-2422-2 21 1821 21-2321-23 2 2422 242 24222-1'522-2422-2422-4 R/hr'.
p R/hi rR R/hr p R-hr hX R/hri_ R/hrAI hr' R*--
".j.
1P k/hr, R/hr!P R/lr 1p R/hr k/hr p Rfhr.u k/hr p R/hrp k/hr p k/hr k/hr p R/
hrp R/hr
, R/hrp k/hr'A S
22117-21:17-20,17-201 18-211 17-22ý17-21'17-23! 17-23 1
22-2
.24122-24;22 -24119-23 19-2319-2319 2
9-23 21-242-24! 21
-22 1 24 421-2 4
2422 g R/hrp i-R/hrp, R/hr ;p R/hr:p R/hr p k/hr p /Rhr p R/hrp kR/hr ip p
p/2r p-Rh r2p k/hr-R/hr p k/hr k/hr p k/hr-p k/hrp R/h rip k/hr p-4 1
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. R/hr,21 R/hr k/hrp k/
r/hr h
R/h
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/hr IM Rr p R/ h r i R/I h rp R/ hr' p
R/lr 1k/hr:p1B/hr 17 -232018-22 18-2,117-21T17-22217-20 1,,><.-.. 2-29124o2-2 21424 i-
ý k/ri
/ýL R/hr18-21 W i 17-20 R/17-20 hr k
R/ hr p R/hr I<
k/hr:P lp khr197-h r 2
4',ý 21 -24121 -24 21-24121-2421 -241 21 -241 21 24:21 -24:21-2 224 19 23 19 -23 1 9
- 23. 18 R
2 1:18r - 21r!l* 17-21'17-21116* -2hr1x 17-rl20'
/hrx R/h I
/hrg
/hrlpRR/hrlk/hrp k/hrp R/hr
- p k/
R/
hr pl R
/hr'pi khrj kr/
hR/hrpR/hr 19 2-2S182-217-0
-72121-212-2221-226 19 2221 9
'219-2 24 19 24!
22 242224!18 -21118-2118
-218-21:18-1 19-23 k/19-2 2-'
222
-II
-22202"!
t8 2
19-22122*
18220 19-2,219-1219
-24119 23 i
I I
I k/hrl. k/hrlpi-k/hrPI k/hr!X R.
.r..
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E~~~~[ p /rpRhrpRhrpR/rpr/rp
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/hrp k/hr' k/h k/hrp io/hr~p k/hrip R/r~pR/hr p
k/hr pRlr
-,1 20-22 - 25!92122-22921-221201-24120 -21201-12-1-274....
2...9-.
2 1
232522Th21231-3:1 4,123121822182 19-229-2 19I2411-2 9
- i Wmpk/hrpkIr'p R/hrp
/rlp kghrpk/hr~p k/hrlpk/hrjlp k/hr
~R/hr i
/r h
Rhrt-p p p
Rfhlrp /hR/hrig R/hrl~i/hr 1-R/irpR/
r pk/r~p k
rp ihr 4 Rfhr~Rr~.R/,
R/rýh
.23-251220-'4521 -'23;21 - 22,21 -242123!21-2 21 1
19 24iIiY9-2419,24-2 i-pR/hr'jp k/hrlp k/hripwkhr~p k/hr'p k/hr l k/hrlp k/rlk/r 19 -~2219 -23!21 -22i21 -2221 -24121-23i'1 218-221 pR/h k/hrip h
/hr h
k/hr hr k
t/hrRk/hr p R/hrikR/hr p-R/hrl kR/hr l
,rjp k
p Rp k/hrgp
-3 21 21_
20-23 204-123i19-23_18_-22'I18-22 4 R/hVp k
R/hr p hrhklp
'p g
hr p
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}'IS' 9 2[1-2218 - 22 221
- 2220 2
- 21121 - 23 121"31
- 22 18S-202IS8-20 4L,.R/hr!R/hr ghR/hrlhrk/hr lLpR/hr hrý p R/hrp*R /hrp
/Rhr
' 18-2*218-2220-22 20- 21ý2 -2320 -2319-23 18-20 18-20 K
P k2R/hrp k/hr k/hr k/hrl k/hrl R/hr k R/hr p R/hrl kLR/hr
!18.2018!2020 i
hrh
'p: k/h2r18-k/hr
-21120-21120-23;,20-23'19-23]18-20'18-201 F
18-20i18-20I20-21120-21 19-22_
19-22119-23;18-20 18-20
kW/h r
p k/h r h ri k/h r -p k/h r R k/h r hp r
'/h r p k/h r *p R /h r
,j R /h r Ký XT
ý-20-23,20 - 232 22-2322-2-322 -_24,
- 4 G
S H I
I I
I I
I I
I I
I I
-
K I
I
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rL IM p,
R/hrp k/hr pkR/hrP-R/hr*p/ihr! 2k/h r'p k /hr k/hr p. k/hr'h
_ 24 23-24.23-24:23-24i22-24122 -24122-24 22-241,,2 241ý -
I U
,tkR/hr R/hr R/hr /hr hp
/hr lp R khrhr R/h rI'--III.I
,~pk/hrrlp Ihrit W-k /hr ; m.<
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i khp k/r 1
T i
j
- i nnR-hr e= Denotes Area Scanned I
D 23-241 2 3 - 2 4 23-24 23-24 23-24i23-24:22-241T22
- 27 22-24i22-23120 -24i20-2420-24244-20 8-24 15-2j15-.2 20-2420 2
42........2.
k
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/ r~
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111 Rhr ~ ~p ~hrp khr RlripR~h~p /hrP khr~i khryk/hllik'hy rAb I~~L~i.R 1 5 2 0 ~rI
/h R
20 2218-2 R/hr~p k/hrip R/hrjix R/hrlp R/hf r
1i80-204 18
-23418-2824 18-24 18-24018-24 18-24 18-,240I16-124 18-24 181-6-24181-2418-24158-2315-123i16 5-2 15-23515-23822318-23 18-23 18-22!20-2420-24! 20-24l20-24',
"Ix ]p1 R/hrp k2 /hr p R/hr 12 k/hrp k*/hrt p k/hrp2 R/hr~ip k/hrp! R*.hr]
kX /hr 12 Rhrl IR/hrf IX Rhr WR7I/hr 1 f R/hrp k2/hrpi R-/hr' IX PhrF2 *hr i* R/hr 1 ~r I /hr-~ Ft/hri1 R/hrf1 /hrip k/hr p k/h rp kX/hri'J 2
2
-20 0-2 18-20 8 - 2 08-2018-2_205182
-0116_18116-115-1-16-1816-18 1618816-18 16-218316-18 16-28181-818-23l186
-2l18 1622020-*-24!20-24120-24'20-24 R
/......
p p
i i
I I.
1 I
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n nr unr p
hrji hp h rý-./hr lp t
/hrjp, 23-2 20-123-20 - 23018 - 20 18-20 18-20 18-12018-20-1820!
1-8J20116--18 181 6-18 16-188 166-18816-_1816-218 16-18 16-18 16-016-1 8-23216 oL 20 -24..20-24 20- 24120 -24 20- 24 S
0jS<
1k/hr16-18hr 1k/hr p
16/h-1_1khr19'18 -i23-16
-al16 R/hr R/hrIR/hrpR/hrkR/hrlR/hr12R/hriiRhr R/hriR/hrIgRhr R/hrlR/h r
I f
Rr/hrkR/hr/h r
k/'r.
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k/hr 0 k/hr2 k S
S1-2018-20
- [_
k/hri p k/hr ~ k/hr k/hr p
/hrp kr p k/hr r
Ir k
p.
r k/Ti--Ohtr IithrrIr 3
82-meters2o82 8-08 2
6-81-86-81-8,611-8 61!68 681 2*621!2I62 9 102 2
402202102 hkre 2
/h of rSVWS I
~
~
k/h l p R/hr hr p It/hr,
-~18-20 8 0 18-'~
8-.-20 1 8-20-18 --20; 8 -20 18 -20118 -20'16 - 18i 16-IS188,6 16-182016 U
it R /hr p R/hr it k/hr p k/r pkh/hr hrp
/hr hr p/hr hr p/hr pR h
rpk/
r pkhrl p k/hr gRhi
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Wf~-h-IM 20-2W
-2v'4s 702 f
-- 8-61816 1
3 meters Building 37 Area 2 of SVW MS=vW
-N-A-ii Model-3 Model-3 Model-3 Model-3
- [*t iq0310812001 04/104/1-001 04/06/2001 01/3112001 S
y y
y S,
155190 155109 154618 153765 44-0 44-10 44-10 44-10
"--a
- u*D
- 4.
9-2, 1-1o 20-,
,8119 Comments: n-n Demotes comel background Y
Jr 1 /04
Figure 8: Exposure Rate Survey Measurements of Area 2 of SVW Survey Date: 01/08/2001 - 01/10/2001 W
S -, +/- -- ::'I. N E
Y............ XX 1 2/1 6
7 8,
9 10
-11 h12 13 14/
15-16 17 18 19 20 21 22 23 24 25 26 2,7 28 X-Jx x
x B R/h21....
-R.
212" A]W/68 19/18.
81 8 19/17118/17ý 18/17 19/188 20/19 20/179 20/17 1
18/181 19/171201 17 8/
1
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2 0
109/18 1
7 J2W 20/18 1hr8 19119 20/19/10/7'i 19/17' 19/17 A R/h~rl, rR/h r
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KR/hr p.IxR/hr, p.!R/hrp.
R-hr /hr A 21/211 21/21 20/20! 21/201 19/191; 9/18 1 19/181 19/18, 20/19 20
' 20/18, 0/19.
91 1/9 19/18 18/171I 18/17218/18 1/9 1/8 18/1711917-t7/7118/171 19/17 20 19/181 19/19 R/iigRhrp
/ri
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RfilIRhr 18/18 1919/178/1820/18 13/1 B~~~~!
pR/rp hrpR/rpRhr.RrpK/rpK/rpK/rp
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/r, 22/221 22/211 21/21-18/19, 17/18! 18/18 18/171 18/183 17/18, 20/18, 19/1819/199
/201 i
[J8
/
/ i. R/hrh K/hr/fp. 9/18
- p.
19/191 19/181 19/18: 18/18 19/18 19/18 19/17!
19/18 18/17 18/17 1/18 18/17 19/17 lK rp.
hr p.K/r./hrhrjp.
8/17.K
/h r
- . K/hrjp.ý/hrlRAr K1--
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/hrp. K/hrp I hpr'p. R/hr p. K/h p. K/hr p. K/p Ih p.KR/hr r p. R/hr c S22/22 21/21! 120/20 1 21/21 18/19, 19/18 18/17917/181019/19!
18/17
.8/.71/.8..
"222/1p.K/hrp.1hr1p K/h p K p K8 K
r p
18/1 I19/18 20/20 9
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P r IX tw
, p rwurp vihr Ip R/hr-l 12/20 22/21 20/201
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20/19/
19/1..9'17/17 22/20 22121 20/20 20/19! 18/18 20/19 20/19, 21/21 21/21
/
16
1119/18 920/19 20/18 20/1 1/18 0
1 9/1 191920/1920/19219/1
._ R/h/I.
KR/hrp.P R/hrp KR/hrlp. R/hrixp R/hrp.
K./hrp K/hrit.
pRhr Rh /h r Rh-h, K
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<22/211 21/20 21/20, 20/191 19/19 20/20 120/19 221/21121/21 2 -1/21 22/21'2222 2222/22 2
/'-0'1 20/20
- p.Ki/hrIp.R/hrp.K/hr p.R/hr p.K/hrl p. R/hr p. K/hr p. R/hrp.
- /h K/
hr P-hrrR/hr'ip.R/hr.
20/19 19/19 20/191 21/201 19/18 20/191 21/207:22/21C 21/211 pR/hr p. R/hrpR/hr'p R/hri hrR/hr/,p./R/hr/p.
A/hr*rp.K/hr p Khr /
hr H :'i 19/18 20/191 20/191 20/19! 20/18 21/20 1 20/191 22/21 21/21Kr K*
R/hr!ix R/hrhp. K/hrhp.K/hrhp. K/hrp.K hr R/ p hr p. R/hr I'H
_h_
I hr
___]i S 1 20/20 19/191 19/201 20/19!119/20' 19/191 20/19. 21/21 2 /21,!
I I
J "Rh-IR/hr p. R/hrp. R/hrlp. KR/hrhp.,
R R/hrl KRhr'p..
19/18 20/19 21/191 20/19119/20 20/20I 21/21.!a22 R/hrR/
/hh/hr K/hrp/hrpK/hr, ip R/higR/hr p.-
- p.
K/hi p hr J
K L
M X 18/17h h
11*i R/hr g Rh 19/18 20/18 19/191 19/19 21/201 18/17' 19/20: 19/18 20/20i419 R/lh h
R/hrO.
hrt. R/hrloit R/hrt R/hrlp.
R/hrp
. K/hrR hr aRh.VR*:'
1jMhP--ir1 1 19/19 19/19 p R/hr p. R/hr x "0/19 19/19 M
R /h p.VK/hr 19/19 1 20/191 20/201 19/181 19/18! 19/191 20/20
'2
- p. R/hr~ip R/hrip. K/hrlpt R/hrip. R/hr:p KR/hp. R/hr j, 19/19 18/18 20/20 18/18 18/18 19/19' 20/20I19
- p.
R/hKr pR/hr ip K/hr p.rR/hr p R/hrIp. R/hr p. R/hr pAl I
I 1/21' 18
'hr
= Contact/One Meter (Fixed Measurements) 201 121/19i 21/191 21/20 1/9 L'i...ll2/y'""*lm
/2 121/19 20/201 22/20 21/201 21/19! 21/21! 21/20 20/19 20/20 *,2/22-Kt R/hr,p.[KR/hrIg R/hr! gR/hrý, p R/hrý; p R/hri p R/hr t R/hfi P
/hr h
r
/
N I0 D **
2/19 20/9 2/20 21/91 1/11 2/19 2119 20/191 20/9 21/20 01 8 1918 9/17I 19/17119/17 I 9
.7"
'l,7,.*1:7I115*f/15' p~L7ilT:.":
2OI7:6!151 16/14i 20/181 20/19; 20/20 21/20; 201 01 2/0 11 1
2/1 1/191'21/19ý120/91 0/191 2/2120/181 19/J8!19/19/1717ý 19/171 20/1.9 2 I 9-1 /8~~_
01j20/17121/120119/1/18/17'/16/141 16 /16 7,____M____7_______IT________0 21/9 17 18/179 1/17 1 9/ 7 16/14116/16 14/13 13/13 14/13 12/12 14/14 14/13 12/11 117/151 18/18 19/17 18/18 20/19 21/20 R/hrliv I/hr IX R/h R/hr, riXR/h*
Ii R/hr R/h' R/hr]-pR/htf"-
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-*-16/15
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____--'_-____-t__________
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T M181 17/17 17/16 17/16 17/16 1
17/16 17/16 15/13R 17/16 16/15 15/113 15/14 15/13 15/14 17/14'1 19/15, 17/12 16/15 16/13 15/14 15/141 16/131 14/141 17/1A,17/15 1I1/141 13/13115/14 1
,a R/hr /hgR
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/hr.
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-i*Ryhr* -U 3 meters Building 37 Area 2 of SVW x
x X
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"Denotes contact I Denotes one meter readings U
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Figure 9: 100cm2 Fixed 1-Minute Beta Counts and 50cm2 Fixed Alpha Survey of Area 2 of SVW 12/09/2000 - 01/16/2001 W
A S *
"-*1-
'1 N E
x
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,0-201 640 1 0-201 574 0-20 a B'CC B
a B.
a B
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495 0-20 592 0- 20 582 0-20 554 0-20 516 l4
- B a
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I o B ot.aB"B a c B
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535 0-20 529 0-20 546 0-20 474 i 0-201565L1, XJta B
5 4 6 B
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L 1, o-201 537 o0-20 584 0-20 646 0 0-20 537 0- 20 0*
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0 0-20' 442 0-20' 555 0
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I I
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L 633' 020 610 0 -20 633 026 N
63 ot3 a'0o6B B
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"20 601 20 602 0-20 602:
586 0-20 609)0 a'_Ba Bl B
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,0-2162 0-2 629 I0-201 602 1
'002-20634614 0-20 634 10-201 580 0 -20:
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4 02 38 02 59 0 2 0-8 0 20 48 o-o(X o o.
0 - 20 Denotes fixed count location.
B6_E3_9 2
B' B.
a a
8
--20a 488 00' 563 0-20 538 0-20 5690-20' 0 2~9--
=:
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B at B,
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o a B
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' 59 0 9 0 -
20642 S
_40-q20 520 2
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a B
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- p564 0-201B 0-0 69 ot
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B ' a0 B
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a Ba 3
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I 0-20 6.*2 0 - 20 63 1 9
020 6655 0 -20 15 9
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0-- 230 Jt*',*
B gB BB ia B
C-C B OC
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B54 0-01 5
O-0X B, u O C
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-'A 6//01 36 0-AN 635 0-2 01 646 '
- 0-20 566 0-20 595 0-20 581 45621 27 11%
21 58%
N/A N/A B
cc B
aX B
aX B
a B
aC B
~
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1247 092 192 NIA NIA P...
'z OO....
50c.'
N/A N/A ackground (cas
)
644 26 0-20 N/A N A Coni
- ens, 3 meters Building 37 Area 2 of SVW A
A-ni E A -h A
A-iM
ý111'
ý-ttL
ý--,
Figure 10: Smear Survey of Area 2 of SVW Survey Date: 12/09/2000 - 01/15/2001 W
S '4 + !1 N E
A-x NA x
x x
X A
I C
G fi
I, x
x
--- X-A-
nn'; = Denotes Smear Location 2
3 4.-5 6
7 8 '9 1 1'12 13 14 15 16 17 18 19 20 21 22 23 24 25.26 27 28
"...XXX'..
X x
x x
x x.x X
X x
Xx X
X.
X X XI IA I
S!
I z
2
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'6 124) 125
'126' j
,149, 148 147'
- 146, I15';i4--i4 r'14
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~~3 38 17 3
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-144
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'153,1 154'
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-;60,ý
' -16*1' 162:
- 163, svw N'A N/A N/A N/A NiA N/A N/A N/A N/A NIA NVA N/A N/A MNA N/A N/A N/A N/A
/A NMA PrC m*S NA N/A N/A N/A NA
'A
[AN/A N/A Coimmits:
Date: 1L292oJ-jjX)I R'1635 157
'158 159 160 161 66167,166)R IT
-I-
, 4
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i I.
t
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T t
l
- i S(178 179/
180 181)1 1827 --
8 3'7-l8 4 T -I8 i86T, 8-S 2-05 0&
120_
___1) 190,
91 1198205' 2
'203)97; 202" 201
- 00.
'19' 198' 19 196
'195
-194) 193 192Z 20 k,2141 3 meters Building 37Aa f
Area 2 of SVW A-A-
4-
%-_.--- r i
I i
11
- !:t(;
i-
Figure 11: Locations of Soil Samples Collected in Area 2 of SVW Survey Date: 12/19/2000 Asphalt Surface (Soil samples cored through asphalt surface)
-/-Notes (1) SVW.
are locate A-A-
A-W A
RN E
Figure 12: 100% 434cm 2 Beta Scan of Area 3 of SVW A
B C
D E
1700 1
1800 1800 2100 ý 2300 2100 21001 1700 1800 1800 1800 2
2200 2100 12100 2100ý 1600 1800 1700 ' 1800:
3 2100 2000 2000 2100i 4
1700 1700 1800 1800 2100 2000 21 H)
_2100 1700 1700 17 0 2106 2000 190o 6
1700 i 1800 180 1700 Building 2000 2100 2000 1900o 17001 1900 1900 1800 37 7 2000 2200 2100 2100 1900 1900 1900 19001 8
2100 2200 2200 12200 9 1900 1900 19 00 2100 2200 10' 1900 1900 1900 1900 2100 2300 2300 2100 1900 :1900 1900 1800 2100 2300 2300
- 2100, 1
'1900 1 900 17001 12 2100 2200 2200 2000 13! 1900 1800 1700 1700 2100 2100 200 2000 14 1800 1900 1700 1700 240 0 1800' 2000 1900 1800 18001 15 2300 24001-2300 2000
-2000 2000 180s 80 16: 2300 2400 2300 ý2200 1
o2000 2000 190 1900 17_-zoo 2300 ]r 2300 2200 3 meters Mm S VW Jnsteumt.)
Model - 2221 N/A N/A N/A S m1Number 154202 N/A N/A N/A Czirttion Due 07/04/2001 N/A N/A N/A 22 64%
N/A N/A N/A p
N/A N/A NIA S149017 N/A N/A N/A Probe uS m
434CM2 N/A N/A N/A Biolkgrounid 4(c m) 2175-2460 N/A N/A N/A Comments:
Date: 0111920l01 Sienatu..e C Stanley Sinaurý Sale
(-
Sk k
W E
01/19/2001 nnn = Denotes Area Scanned
Figure 13: 10% 434cm 2 Alpha Scan of Area 3 of SVW A
B C
D E
1 15-30 11-23 9-22 10-27---T 7
2 18-26 9-23 11-23*
9-21 3
12-22 6-29 13-22 10-18 4
17-28 8-16 9-35 1 11-22 5
13-31 4-23 12130 6
17-34 6-28 10-19 17-2#
Building 37 7
16-38 15-22 14-26 6-2ý 8
7-40 11-30 11-23 6-11 9
11-32 11-28 15-29 10 11-23 13-24 11-25' 15-1 11 10-331 7-21 16-30 14-33 121 11-251 10-18 1 15-242 16-2ý 13 17-21 17-24 116-291 9-17 14 11-20 13-25 9-Z8 13-23 15 21-32 19-23 3-23 15-26 16 15-25 20-37 15-25 16-2t 7 T
1711-_2
-2033 12-18 19 3 meters w
A E
01/19/2001 nn-nn = Denotes Area Scanned SS VW USU104MI(s)
Model -2221 N!A N/A N/A swinambq8 97287 N/A N/A N/A c4b3a1a Due 07/20/2001 NiA N/A N/A Efr$ciy 21250o N/A N/A N1A 4
A y
N/A N/A N/A Prob"Number 148926 N/A N/A N/A
- ob ze 434cmr N/A N/A N/A Background (cpm) 0-20 N/A N/A N/A Comments Signature: C Stanley Date 0109/1001
Figure 14: 100cm2 Fixed 1-Minute and 50cm2 Fixed Alpha Survey of Area 3 of SVW A
B C
D E
1;567 0-20 635 0-20LAZ B
a B
a 4
2 0-20 595 0-20 587 2 a B
CC B~
w V
E 646 01/19/2001 B
3 566 0-20 565 0-20' 4
0-20 564 0-20 575 a
B a---i-532 0-20 581 0-20 5
B B
iB a
6 0-20 548 0-20 i564 Building a'
B a
B 622 0-20 565r0-20 37 7
B8 a
Ba 0-20 631 0-20 673 a
B a
1-633 0-20 7041 0-201 B
cc
!B a
10 0-20 61 20 573 11 648 0-20 610 0-20 B
a B
a 12 0-20 600 0-20 573 13 B
a IBt a
.1 14 0-20 550 0-20ý 5491 a
B 672 0-2 5560 0-20 15 B
a B
a, 16 0-20 655 0-20 658 c
B a
B 635 0-20 688 0-20 173 meter 3 meters nnn B = Denotes 1-Minute fixed count location (in cpm).
0-20= Denotes fixed count location (in cpm).
cc SAaw:0e
,9120ia kmotWO'st(.)
Model.- 2221 Model -12 NIAN/
- Sa'*[ *u o
149436 91103
]
N/A N/A Ca1br.
De 06/06/2001 03/26/2001 N/A N/A S27.11%
21.58%
N/A N/A S
P "N/A N/A Pmbo INAbw 120477 092192 N/A N/A NO* S ac 1 00cmn 50era; N/A N/A ftaw-od.(Ov) 6446+/-26 0-20 N/A N/A Comments
Figure 15: Smear Survey of Area 3 of SVW 1
1.
A B
C D
E 18' 3-.
3 4
33, 2
-,,1 5
- 6.
7 16, 15 4 - 8 14~
-30) 9 10 1
13 29 141 2
7 1612 1 7
,3 mets24 17 10+--26 3 meteis w
E 01/18/2001 Building 37 SVw N/A N/A N/A N/A SerialNuubse NIA N/A N/A N/A CrWwA~
N/A N/A N/A N/A
.yN/A N/A N/A NA 4
N/A N/A N/A N/A pwt.0 N/A NIA N/A NIA P
ix N/A N/A N/A N/A
,auksmd N/A N/A N/A N/A Comments:
Sgtu Date 011LROfM
W Figure 16: Exposure Rate Measurements of Area 3 of SVW s +
N E
A B
C D
E 21/21 20/20 1 20/20 20/1*
pR/hr RR/hr ILR/hr~i pMI 20/20 20/20 19/19 19/11 2pR/hr gifR/hr pi*Rhr pIR/hr 21/20
- 20/20 1 20/20 20/19 3 jiR/hr 1+/-R/hr jjR/hr piR/hl 4120/20 20/20 [ 19/19 19/1I jiRfbr jiR/hr PRR~tr i
1212 20/20 14 6
7 8
9 21/21 21/21 121'21 1 I/1R IAR/hr AR/hr IxR/hr I RIh!
21/21 21/21 2 20 :20/15 llPR/hr jpi.hr ýL rgRb 1 21/20 20/20 18/18 18/1' 1 lR/hr ILR/hr 1iR/hr *tR/h 20/20 20/19 19/19 19/1 12 1+/-R/hr giR/hr 1tR/hr 1
9 R/h9 13 ý214/23 24/24 231M4 17/14 gRIhhr RR/hr AR/Ir J.LR/h 14 23/22 22/22 a21/ 1 17/1 14A1"2,.2 r,,, Rib 01/19/2001 Building 37 nn/nn
- p. R/hr 3 meters S VW lwmtmaxasa Model N/A N/A N/A 151348 N/A N/A N/A C&ulPa60oDue 04/06/2001 N/A N/A NIA EIcuyN/A N/A N/A N/A y
N/A N/A N/A Pobe Numb~t 154618 N/A N/A N/A Prob.Su.
44-10 N/A N/A NIA S"20-21 /19-20 N/A NIA NIA S~atore q-",
V-Datetn.fIILfD
= Contact/One Meter Comments: *n-n / n-n = -Denotes contact / Denotes one meter readings Readings in Mro R/hr.
DIte: 0111000M I
Figure 17: Exposure Rate Surface Scan Survey of Area 3 of SVW A
B C
D E
1 19-22 18-21 18-20 18-21 jiR/hr jilR/hr jR/hr piR/h-19-22 19-20 19-21 17-21:
2 jllR/hr: jRi/hr jll/hr jill/hr 18-21 18-20 18-21 17-201 3
jiR/hr jtR/hr jLR/hr giR/hr 19-21 18-21 18-22 17-20 4 jtR/hrl iRl/hr AitJ/hr jlh, 18-20 ' 18-20 17-20 5 jR/hr pilR/hr! ;RLhr 6
18-21 18-21 18-21 8-2 Illt/hrj tR/hr IiR/hr! jiR/hi 7 jiR/hr jiR/hr jIR/hrjpd/ht 8
19-22 18-22 '19-22 16-23 jil/hr jil/hr' jilhr4LR/hl 20-22 20-22 20--22A8M21 9 jll/hr jil/hr gill/hr1 RlR/h" 18-24 19-22 19M-22 15-22 10" gRlhr pRfhr!' jillbhriL/h 18-21 19-21 1 17-21 '14-20 il*lR/hr jiR/hr j IR/hr igR/hi 12 18-20 18-21 16-20 14-20 1ilR/hr jill/hr jil/hr jilR/hi 13:
N-23 16-26 -627 15-18 jill/hr jil/hr ARl/ r jill/hr 14 18-24 18-26 16-6 16-1?
1 -KtKhr! *'
r rll/hr S18-21 19-2,1!
ý17-25 li18-21 15' jil/hr jill/kr~jiLlhr! jill/hr 16 18-21 19-21 18-21. 18-20 jl;lR/hr lR/hr pR/hri tRl/hr 17j1-21 r
19-21 p18-1-2 17 jill/hr jillhr jill/br jll/hr Building 37 3 meters SSVw 104towst(t)
Model-3 N/A N/A N/A SruW Nulmbr 153551 N/A NIA NIA lAoba DUC 04/04/200 N/A N/A N/A Efcisy N/A N/A NIA NIA a
y N/A N/A N/A P"Nw 155109 N/A N/A NIA Ptoývs 44-10 N/A N/
NA Ienoqd 17-20 N/A N/A N/A Comments: n-n Denotes contact background. Readings in Micro-Rjhr Sigrgture:Tum-Date 0.L1L200I nn-nn
=Denotes Area Surveyed
[t R/hr w
SN E
01/19/2001
1700-2200 C
i!i* oncretei~i i!iii::?:::.
- /::
=
==
=== = ==
= =
==
=
==
= ===.*
.: a ' * ". :............
- ~ ~ ~ ~.......
- 170 : *I : ::::::....
ii~ i!!iiiii~iii~
ii:iii *i i ii..........
i i:t*
C-13 1..
.::2:.:.50
. : '21-50:...
Wood 150' Conc re'0.te I
.........L 8 0...
C-14 1:4650 B-14 Asphalt (See other figure)
A-14 for readings on ground surface N
w4E S
01/23/2001 1650-2100 0-2140 E7-1iS:::
1600-2200
= Denotes one minute Beta fixed count S VW SModel-2221 N/A N/A N/A S154202 N/A N/A N/A 77ot 07/04/2001 N/A N/A N/A E
22.64%
N/A N/A N/A O
0 N/A N/A N/A Probe Numbe 149017 N/A N/A N/A ProbeSie 434cm' N/A N/A N/A Background (cpm) 1600-1995 N/A N/A N/A Comments: Readings recorded in cpm.
A.ý-
Figure 18: 100% 434cm2 Beta Scan Survey of Area 3 Loading Dock 1720-2050 1500-2280
, i It -
Signature: I V-geltt Date : AI /?*I I2Mo-
Figure 19: 10% 434cm 2 Alpha Scan Survey of Area 3 Loading Dock
-1$
Concrete Walls
= Denotes Scanned area range in +/-tR/hr.
svw
)
Model-2221 N/A N/A N/A siiaNý 97287 N/A NIA N/A D*
jgi
- l 02/26/2001 N/A NVA N/A 21.25%
N/A N/A N/A a
N/A N/A N/A PrC Nu 148926 N/A N/A N/A 434cnf N/A N/A N/A B-kgT--d (cpný 0-20 N/A N/A N/A Conmmnts: Readings are in Micro-R/1f scan on surface.
S ulreeC *t*=4ny 1
Date: 01W.24MLI N
E 01/24/2001 9-15
Figure 20: 100cm 2 Fixed Beta 1-Minute and 50cm 2 Fixed Alpha Survey of Area 3 Loading Dock Wood Concrete Walls F 543 409 Concrete Walls 471C-13 471<
B-13 A-13 B-14 A-14 N
S 01/23/2001-01/24/2001
<20 Concrete" Walls D
= Denotes one minute Beta fixed count LO= Denotes fixed Alpha count vw SModel
-2221 Model - 12 N/A N/A S e.
.. Number 148436 91103 N/A N/A C ation D
06/06/2001 03/26/2001 N/A N/A Effi tcy 27.1 1%
2 1.58%
N/A N/A c
Y 0
a N/A N/A Probe Numbtr 120477 092192 N/A N/A Probe S iz IOcm 50cm N/A N/A BOMkgrood(cpm) 554 +_ 28 0 -20 N/A N/A Comments: Readings recorded in cpm.
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S ignature.C S tan ley L
ýý D ate. 01(I 2312001 -011 241200 1
Figure CS 1: Areas 2 and 3 Confirmatory Survey Beta Scans S2 4
5 6
7 8
2 Iý 2
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 AREA 2 vegetation ELECTRICAL PAD concrete asphalt AnCA -
BUILDING 37 (Re/eased)
Instruments Moel Ludlum 2221 Ludlurn 2221 Serial #
86302 97817 CalDue 06-14-01 06-09-01 Efficiency 20.45%
20.13 CalDue 07-03-01 07-03-01 Efficiency 20.13%
20.42%
Cal Due 07-05-01 07-05-01 Efficiency 20.39%
20.13%
Cal Due 07-18-01 07-18-01 Efficiency 20.310%
20.03%
3m Notes:
- 1. !00% scan of asphalt in Suspect Affected Area, 10% scan of flat surfaces outside Suspect Affected Area.
Probe 43-37( 434 cm2 P) 43-37) 434 cm 1
Probe #
092415 094119 Bkgd (asphalt) 1900-2300 cpm 1900-2400 cpm Bkgd (concrete) 1400-2100 cpm 1400-2200 cpm Surveys Conducted By: R. StowelloAj Dates: 01-02-01 to 01-19-01 Wl if
- 2. Scan results range from 1200 to 2400 cpm !3 for asphalt and 1600 to 2000 I3 cpm for concrete.
- 3.
Denotes location of scan.
C w
t-N asphalt AREA 9 43 u
AA AE A
E Ai AP
............. \\....
concrete 3
Figure CS 2 Areas 2 and 3 Confirmatory Survey MicroR Scans 0 1 2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 S'j N
"AI 1
1*.rEH Notes:
Surveys Conducted By: B. Hunter & R. Sto Dates: 12-20-00 to 01-22-01
- 1. !00 % of surface scanned inside the Suspect Affected Area.
10% of surface scanned outside of the Suspect Affected Area.
2..
Scan results range from 14 to 25,R/hr for asphalt, 14 to 18 pR/hr for concrete, and 15 to 25 pR/hr for soil.
- 3.
Denotes location of scan.
W(
Figure CS 3: Area 2 and 3 Confirmatory Survey Soil Samples 0
1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 19 2C 21 22 23 24 25 26 27 28 AA.
A R E A2 140 vegetation A
8 C
D E
F G
H J
L M
N 0
P 0
R S
T x
Y 2
V AA AE A'
Al At AF AJ At asphalt ELECTRICAL PAD concrete W t N asphalt AREA 2:
BUILDING 37 (Released) 3m Samples Collected by : R. Stowell Date: 01-19-01 Notes:
- 1. Soil sample results are provided in Table CS 1.
- 2.
- XX Denotes sample location
- 3. Sample ID's: SVW-SC-XX 130 lieOO2 Suspect Affected Area 0 9 asphalt
!1 7.,,09,
AREA 2
Figure CS 4: Additional Survey of a Portion of Areas 2 and 3 S2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 A.,,A 2 AREA 2 ee.tinvegetation etatio.i ELECTRICAL PAD concrete asphalt AREA 2 3m Notes:
- 1. -100%
Beta and Gamma scans were repeated in the area where contamination was found and remediated during the Confirmatory Survey.
- 2.
Denotes the area scanned.
- 3. Beta scans range from 1700 to 2300 cpm.
- 4. Gamma scans range from 18 to 23 t.R/hr.
Surveys Conducted by: P. Poole Dates: 02-09-01 & 02-12-01 0
I.
I' 1.
W asphalt AREA 2 U
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Ak A E M
At AI Al Af AF Al AJ
APPENDIX A TO THE FINAL RADIOLOGICAL SURVEY REPORT FOR AREAS 2 AND 3 OF SORRENTO VALLEY WEST LAND AREA "FINAL SURVEY PLAN FOR THE SORRENTO VALLEY WEST LAND AREA" DATED NOVEMBER 20, 2000
Date: November 20, 2000
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Prepared by: Mi hael Dupray Approved by:
IkfIjui,%,
Final Survey Plan for the Sorrento Valley West Land Area SITE DESCRIPTION AND CLASSIFICATION The "Building 37 West Land Area" is located in GA's Sorrento Valley Site as shown in Figure 1 and is classified as an Unaffected Area. There is no history of radioactive materials use in this area other than storage of packaged radioactive waste in the south fenced area marked RMA. Figure 2 shows the location of storm drains and fixed location equipment (storage areas, cooling tower, and associated piping). Figure 3 shows required soil sample locations. The total surface area is approximately 43,000 ft.2.
CRITERIA FOR RELEASE TO UNRESTRICTED USE Exposure Rate Guideline The guideline value for exposure rates measured at 1 m above the surface, is 10 pR/hr above background levels. Normal background is 15 pR/hr measured at 1 meter up from the surface.
Acceptable Surface Contamination Levels The potential contaminants of concern for this site are natural thorium and enriched uranium since these materials were used in nearby buildings.
Enriched Uranium:
The applicable guidelines for residual contamination on surfaces for enriched uranium are:
5,000 dpm/1 00 cm2 (averaged over a I m2 area) 15,000 dpm/1 00 cm2 (maximum in a 100 cm2 area if the average over 1m2 is met) 1000 dpm/100 cm 2 (removable activity)
Natural Thorium The approved guideline values for residual contamination for release to unrestricted use for natural thorium are provided below:
1,000 dpm/1 00 cm 2 (averaged over a I m 2 area) 3,000 dpm/100 cm 2 (maximum in a 100 cm2 area if the average over I m2 is met) 200 dpm/1 00 cm 2 (removable activity)
As interpreted by the NRC, the average 1000 dpm/1 00cm2 and the maximum 3000 dpm/1 00cm2 should apply to both alpha and beta measurements, independently, for surface contamination involving natural thorium.'
Alpha measurements will be performed to detect <
1000 a dpm/100 cm 2.
(')1Interpretation of Thorium Surface Decontamination Limits," U.S. Nuclear Regulatory Commission, February 9, 1992.
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Thorium emits alpha radiation to beta radiation in a 1:0.67 ratio; therefore, the corresponding average and maximum beta activity guidelines were adjusted to be 670 dpmrlOOcm 2 and 2000 dpm/1 00cm2, respectively, for beta monitoring.
Beta Guideline Values (thorium)
The modified guideline values for residual contamination for release to unrestricted use for natural thorium are provided below:
670 dpm/100 cm 2 13 (averaged over a 1 m2 area) 2000 dpm/1 00 cm2 0 (maximum in a 100 cm2 area if the average over 1 m2 is met) 200 dpm/100 cm2 13 (removable activity)
If elevated levels are detected, GA will collect soil samples to determine the contaminants. For now, assuming a 50/50 mix is reasonable, therefore, GA will demonstrate that radiation levels are:
<2800 dpm/1OOcm 2 13 (averaged over a I m2 area)
<8400 dpm/1 00cm 2 13 (maximum in a 100cm2 area if the average over 1 m 2 is met)
<600 dpm/1 00cm 2 13 (removable activity)
Soil Release Criteria The soil release criteria in pCi/g is provided below:
Thorium (Th-228 + Th-232) 10 pCifg Enriched Uranium (U-234 + U-235) 30 pCi/g (1 pCi/g U-235 and 29 pCi/g U-234)
Depleted Uranium 35 pCi/g If more than one radio nuclide exists, the sum of the fractions of the concentrations is calculated as follows:
c,=
Ci =
The average concentration of radio nuclides I in the soil above background levels.
L; =
The release criteria for radio nuclides I.
The sum of the fractions must be less than or equal to one in order for the soil to meet the release criteria.
ALERT LEVELS If the following "alert levels" are exceeded, notify HP Management so an evaluation can be performed to determine if increased survey coverage is required or to evaluate if decontamination is required.
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Beta Alert Levels
>300 cpm beta above background using the large area (434 cm2) probe
>150 cpm above background using the 100 cm 2 probe Alpha Alert Levels
>150 cpm alpha using the large area (434 cm2) probe
>75 cpm using a hand-held 50 cm 2 alpha probe (- 750 dpm/1 00cm2 )
Survey Plan For The Sorrento Valley West Land Area Tvne of Surv
, Unaffected Area Gridding Not Required (The area will be gridded, 10' X 10', to facilitate location of soil samples and radiation measurements)
Direct pR/hr Take readings at Im from surface and contact readings (at surface) every 3m Readings Scans a Using 434 cm2 10% of the concrete or asphalt-surfaces.
probe Scans 13 using 434 cm2 probe or 25% the concrete and/or asphalt-covered areas.
Using the dual probe unit Radiation One measurement every 7m (with a minimum of 30 measurements)
Measurements One every other grid block, on concrete or asphalt alternate between:
(')I. Direct alpha fixed measurement,
- . -Direct beta fixed -measurement, (c)3. A 100 cm2 smear.
Soil Samoles Collect 16 soil samoles as shown on Fiaure 2 (a) For a measurements use the 50 cm2 hand-held detector and count for 10 seconds. Record readings in cpm and mark locations on drawings.
(b)
For P measurements use 100 cm2 beta gas flow proportional counter. Count for 2 minutes.
Record readings in cpm and mark locations on drawings.
(c) For removable measurements, take a 100 cm2 wipe at each location and send to HP lab for counting NOTE:
If radiation readings are above alert levels, continue surveying area until the entire area of contamination is identified and outlined (i.e. marked with paint or chalk).
Quantify contamination levels in all elevated areas where the floor monitor readings are above the alert level using hand held instruments.
3 of 4
DOCUMENTATION Radiation Surveys Every survey conducted will be documented on a daily basis to a worksheet/drawing showing the approximate locations surveyed/sampled. The documentation must include the results of the measurements (including units), the technician's signature, date, instrument(s) used (including the model and serial number of both the rate meter and detector), calibration due date, % efficiency, background readings (if applicable) and any other pertinent information.
Soil Samples Mark exact locations of the soil samples on a map or drawing and refer to the grid locations. Each soil sample must also be properly labeled and tracked.
The label should include:
The Date; Sample ID number; (such as 37West-001, 37W-002, etc.);
Grid location; HP Tech name.
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APPENDIX B TO THE FINAL RADIOLOGICAL SURVEY REPORT FOR AREAS 2 AND 3 OF SORRENTO VALLEY WEST LAND AREA "GA INTERNAL CONFIRMATORY SURVEY PLAN FOR THE SORRENTO VALLEY WEST LAND AREA" DATED DECEMBER 19, 2000
Appendix B to Radiological Survey Report for Areas 2 and 3 the Sorrento Valley West Land Area December 19, 2000 Prepared by: Richard Stowell Approved by: Laura Gonzales GA Confirmatory Radiological Survey Plan for Sorrento Valley West This confirmatory survey covers "Building 37 West Land Area" located in GA's Sorrento Valley Site. This area consists of the land west of Building 37 to the GA boundary.
Background and Classification The area inside the fenced Radioactive Material Area and a 6 meter buffer on the west, north and east sides was reclassified as a Suspect Affected Area following previous surveys. The remainder of the Sorrento Valley West area remains an Unaffected Area. Figure 1 shows these areas.
Survey Objectives and Responsibility The purpose of performing an internal confirmatory survey is to double check that the radiological conditions in Sorrento Valley West satisfy the NRC and Stat of CA guidelines for release for unrestricted use.
Surveys will be taken only by qualified Health Physics Technicians having a minimum of three years Health Physics Technician experience not assigned to perform the Final Survey, i.e. an independent survey. The survey and final report documenting the survey will be performed by GA's Health Physics Group.
Release Criteria (per GA Decommissioning Plan)
As per "Final Survey Plan for the Sorrento Valeey West Land Area" approved: 11/21/00.
Alert Levels If the following "alert levels" are exceeded notify HP Management so an evaluation can be performed to determine if increased survey coverage is required or to evaluate if decontamination is required.
Beta Monitoring
>300 cpm above the appropriate background using the 434 cm2 probe.
>200 cpm above the appropriate background using the 100 cm2 probe.
>150 cpm above the appropriate background using the 15 cm2 probe.
1 of 3 Exposure Rate Measurements
>25 pR/hr at surface
>20 p R/hr at I m
Appendix B to Radiological Survey Report for Areas 2 and 3 the Sorrento Valley West Land Area Confirmatory Survey Plan for The Sorrento Valley West Land Area Type ofSurv Suspct Affected Area ( inide fe.cned RMA and 6 meters north ad et outsidethe
" [
g, fehc 6
ad6to
,jtfih lkt nsiO, the RMAI)
Direct pR/hr 100% surface scan of the area using 2" x 2" NaI probe.
Readings Beta Scans Using 100% of accessible flat surface areas (asphalt).
434 probe Soil Samples Collect under asphalt where contamination was found on previous survey.
Typeof SrveyUnaffected Area (ten giftin area otside Sguspe Affected)
Direct pR/hr 10% surface scan to include all depressions and low-lying areas.
Readings Beta Scans Using 10% of accessible flat surface areas (asphalt).
434 probe Soil Samples None Documentation Radiation Surveys Every survey conducted will be documented on a daily basis to a worksheet/drawing showing the approximate locations surveyed/sampled. The documentation must include the results of the measurements (including units), the technician's signature, date, instrument(s) used ( including the model and serial number of both the rate meter and detector), calibration due date, % efficiency, background readings (if applicable) and any other pertinent information.
Soil Samples Mark exact locations of the soil samples on a map or drawing and refer to the grid locations. Each soil sample must also be properly labeled and tracked.
The label should include:
Date; Sample ID, Tare Weight (gins); Net Weight (gins); HP Technician's Name.
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T LU Building 37 AA 0
'1 0
Sorrento Figure 1 Valley West Land Area Building 37
= Area to be surveyed RMA
Sorrento RMA Figure Valley \\A RMA H
Fl F
2 (est Land Area I
Building 37 Fixed equipment/equipment storage area A Storm Drain B Unknown C Storm Drain D Electrical E Storm Drain F Monitoring Well G Main storm drain access H Storm Drain RMA = Radioactive Materials Area A
0 E
5 EC
Sorrenti Soil Figure 3 Valley West Land Sample Locations 13 0
(10)
Building 37 Area 12