ML033110274
| ML033110274 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 10/31/2003 |
| From: | Asmussen K General Atomics |
| To: | Adams M, Kwok S NRC/NMSS/FCSS, State of CA, Dept of Health Services |
| References | |
| -RFPFR, 696/CAL-3665 | |
| Download: ML033110274 (100) | |
Text
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GENER2AL ATOMICS October 31, 2003 696/CAL-3665 Ms. Mary Adams, Fuel Cycle Licensing (In Duplicate) p/J)A dCb-Branch/Section 1 U.S. Nuclear Regulatory Commission 7
3 Mail Stop T-8A33 Two White Flint North 11557 Rockville PikeX at Rockville, MD 20852-2738
,9,2.
Subject:
Docket No.70-734; SNM-696: Request to Release a Certain Portion of General Atomics' Facility to Unrestricted Use and Delete it from License SNM-696: Namely, the Roof of GA's Building 2 and Ms. Sudana Kwok (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 a Certain Portion of General Atomics' Facility to Unrestricted Use and Delete it from License 0145-37:
Namely, the Roof of GA's Building 2
Dear Ms. Adams and Ms. Kwok:
As you are aware, General Atomics (GA) 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' site in San Diego. Most recently, GA completed the final radiological survey of the roof of GA's Building 2 located on GA's Main Site.
Building 2, also known as the Science Laboratories Building, consists of approximately 142 laboratories and associated offices, hallways and a service corridor (which contains utilities for the labs and offices).. GA is continuing to use very small quantities of radioactive material (licensed by the State of California) in eight of the laboratories (for bioscience research). All of the other laboratories (and associated offices and hallways) have previously been released to unrestricted use. This request is for the release of the roof of Building 2; the release of the service corridor in Building 2 will be the subject of future requests.
There are four (4) different roofs over Building 2. These are designated as Levels A, B, C and D (see enclosed report).
The total area of these 4 levels to be released to unrestricted use is approximately -126,000 ft2 (- 11,706 in2).
No radiological contamination was found on Levels A, B or D. Radioactive contamination exceeding GA's NRC-and State-approved release criteria was detected on Level C in three (3) 3550~~~~6 1
GEEA1TMC OR.SNDEO A91112 0BX868 A
IGC 28-68 (5)4530 (858) 455-3000
Ms. Mary Adams (NRC) and Ms. Sudana Kwok (State)
October 31, 2003 6961CAL-3665 Page 2 different areas designated as Areas 1, 2 and 3. The contaminant in Area 1 was identified as thorium and the contaminant in Areas 2 and 3 was identified as Cs-1 37. In another location on Level C (Area 4), Cs-1 37 concentrations were found to be below the approved release criteria, but higher than the remainder of the roof (-60% of the release limits). After remediation of these 4 areas, concentrations of thorium and Cs-137 on Level C were reduced to <10% of the NRC-and State-approved release criteria.
On November 13, 2001, Mr. Wayne Britz from NRC's Region IV office performed an in-process survey of the remediated roof in Areas 1 and 2, prior to GA resurfacing the roof. No contamination was found. The results of their survey were documented in NRC Inspection Report 70-734/01-04, a copy of which is provided in Appendix B of the enclosed Radiological Survey Report.
Enclosed is a GA report titled 'General Atomics' Final Radiological Survey Report for the Building 2 Roof'. This report documents the results of the comprehensive radiological surveys, measurements and analyses conducted by GA to demonstrate that the subject Building 2 roof meets the NRC-and State-approved criteria for release to unrestricted use.
Accordingly, GA hereby requests the NRC and the State to release the Building 2 Roof, as described in the enclosed final survey report, to unrestricted use and delete it from GA's NRC and State of California special nuclear material and radioactive material licenses, respectively. Consistent with decisions made during joint NRC, State of California and GA decommissioning coordination meetings, the NRC has the regulatory lead for the release of Building 2; including the roof.
If you should have any questions regarding this request, or the enclosed report, please don't hesitate to contact Ms. Laura Q. Gonzales at (858) 455-2758, or me at (858) 455-2823.
Very truly yours, Keith E. Asmussen, Ph.D., Director Licensing, Safety and Nuclear Compliance
Enclosure:
GA report titled: "General Atomics' Final Radiological Survey Report for the Building 2 Roof," dated October 2003.
cc:
Dr. D. Blair Spitzberg, Chief, NMSS Branch 3, Region IV Mr. Rick Mufioz, Fuel Cycle Inspector, NRC Region IV Ms. Kathleen Henner, State of CA, Brea, CA Mr. Jeff Wong, State of CA, Sacramento, CA Ms. Barbara Hamrick, State of CA, Brea, CA
GENERAL ATOMICS' FINAL RADIOLOGICAL SURVEY REPORT FOR THE BUILDING 2 ROOF Prepared By: William LaBonte, Richard Stowell and Laura Gonzales Survey Technicians: Scott Cowan, Steve Finchum, Barbara Hunter, Greg Sayer, Will Schuck, Joseph Sullivan, Dana Koelker and Richard Stowell October 2003
Table of Contents INTRODUCTION..........................................................
I SITE DESCRIPTION.........................................................
2 History of Use.........................................................
2 Classification.
2 Decontamination Efforts......................................................
3 CRITERIA FOR RELEASE TO UNRESTRICTED USE.................................
4 As Low As Reasonably Achievable (ALARA)..........
........................... 4 Facilities and Equipment (and Asphalt or Concrete Surfaces)..........................
5 Release Criteria for Soils......................................................
5 Exposure Rate Guideline......................................................
6 INSTRUMENTATION AND BACKGROUND MEASUREMENTS........................
6 Background Measurements for Instruments/Detectors...............................
6 Background Roofing Material Concentrations of Concern............................
7 Exposure Rate Background.....................................................
7 FINAL SURVEYS PERFORMED.
7 Objectives and Responsibilities.
7 Survey Plans..........................................................
7 SURVEY
SUMMARY
8 Comparisons of Site Decommissioning Plan with Final Surveys Performed.....
......... 9 Gravel/Tar Sampling.
10 RESULTS OF THE FINAL SURVEYS.
10 Exposure Rate Scans........................................................
10 Exposure Rate Fixed Measurements...............
11 Scanning (a and P).........................................................
11 Fixed Measurements (a and ).11.................................................
11 Removable Activity.........................................................
11 Gravel Samples..........................................................
12 CONFIRMATORY SURVEYS......................................................
13 CONCLUSION.
13 List of Tables Table 1:
USNRC's Acceptable Surface Contamination Levels........................
T-1 Table 2:
State of California's Acceptable Surface Contamination Levels.....
........... T-2 Table 3:
Building 2 Roof List of Instruments.....................................
T-3 Table 4A:
Background Roof Gravel Sample Results..................................
T-6 Table 4B:
Background Roof Tar Sample Results.........
........................... T-8 Table 5:
Building 2 Roof Gamma Spectroscopy results, Roof Samples.....
............ T-10 Table 6:
Building 2, Section "C" Wipe Sample Results.............................
T-21 ii
List of Fieures (unpaged)
Figure 1:
GA's Main Site and Sorrento Valley Site.
Figure 2:
Building 2 in Relation to Surrounding Area.
Figure 3:
Building 2 Roof.
Figure 4:
Building 2 Roof Level "A" Exposure Rate Fixed Measurement Locations and Results.
Figure 5:
Building 2 Roof Level "A" Exposure Rate Scan Locations and Results and Sample Locations.
Figure 6:
Building 2 Roof Level "B" Exposure Rate Fixed Measurement Locations and Results.
Figure 7:
Building 2 Roof Level "B" Exposure Rate and Ventilation Scan Locations and Results and Sample Locations.
Figure 8A: Building 2 Roof Level "C" Exposure Rate Fixed Measurement Locations and Results.
Figure 8B: Building 2 Roof Level "C" Exposure Rate Fixed Measurement Locations and Results.
Figure 9:
Building 2 Roof Level "C" Exposure Rate and Ventilation Scan Locations and Results.
Figure 10:
Building 2 Roof Level "C" Sample Locations.
Figure 11:
Building 2 Roof Level "D" Exposure Rate Fixed Measurement Locations and Results.
.Figure 12:
Building 2 Roof Level "D" Exposure Rate Scan Locations and Results and Sample Locations.
Figure 13:
Building 2 Roof Level "C" Remediation Areas 1, 2, 3 & 4 Locations.
Figure 14:
Building 2 Roof Level "C" Remediation Area 1 Sample Locations.
Figure 15:
Building 2 Roof Level "C" Remediation Area 1 Exposure Rate Fixed Measurements and Scan Locations and Results.
Figure 16: Building 2 Roof Level "C" Remediation Area 1 Alpha and Beta Scan Locations and Results.
Figure 17:
Building 2 Roof Level "C" Remediation Area I Fixed Measurement Locations and Results and Wipe Locations..
Figure 18:
Building 2 Roof Level "C" Remediation Area 2 Sample Locations.
Figure 19:
Building 2 Roof Level "C" Remediation Area 2 Exposure Rate Fixed Measurement and Scan Locations and Results.
Figure 20: Building 2 Roof Level "C" Remediation Area 2 Alpha and Beta Scan Locations and Results.
Figure 21: Building 2 Roof Level "C" Remediation Area 2 Fixed Measurement Locations and Results and Wipe Locations.
Figure 22:
Building 2 Roof Level "C" Remediation Area 3 Sample Locations.
Figure 23: Building 2 Roof Level "C" Remediation Area 3 Exposure Rate Fixed Measurement and Scan Locations and Results.
Figure 24: Building 2 Roof Level "C" Remediation Area 3 Alpha and Beta Scan Locations and Results.
Figure 25: Building 2 Roof Level "C" Remediation Area 3 Fixed Measurement Locations and Results and Wipe Locations.
Figure 26: Building 2 Roof Level "C" Remediation Area 4 Sample Locations.
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Figure 27:
Building 2 Roof Level "C" Remediation Area 4 Exposure Rate Fixed Measurement and Scan Locations and Results.
Figure 28:
Building 2 Roof Level "C" Remediation Area 4 Alpha and Beta Scan Locations and Results.
Figure 29:
Building 2 Roof Level "C" Remediation Area 4 Fixed Measurement Locations and.
Results and Wipe Locations.
Figure 30:
Building 2 Roof Level "C" Remediation Area 4 Insulation Scan Locations and Results.
Appendix A:
Appendix B:
Appendix C:
Appendices Final Survey Plans and Supplements for the Building 2 Roof NRC Inspection Report 70-734/01-04 Building 2 Roof Level "C" Remediation iv
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CENERAL ATOMICS Final Radiological Survey Report for the Building 2 Roof Introduction General Atomics (GA) 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 the Building 2 Roof located on GA's Main Site.
Building 2, also known as the Science Laboratories Building consists of 142 laboratories, offices, hallways and a service corridor which contains utilities for the labs and offices. GA uses radioactive material (licensed by the State of California) in very small quantities in only eight (8) of the laboratories (for bioscience research). All the other laboratories (and associated offices and hallways) have been released to unrestricted use. The release of the Building 2 service corridor is the subject of other release requests.
There are four (4) different roofs over Building 2. These are designated as Levels A, B, C and D.
The total area of these 4 levels to be released to unrestricted use is approximately -126,000 ft2 (-
11,706 M2 ).
No radiological contamination was found on Levels A, B or D. Radioactive contamination exceeding GA's NRC-and State-approved release criteria was detected on Level C in three (3) different areas designated as Areas 1, 2 and 3. The contaminant in Area 1 was identified as thorium and the contaminant in Areas 2 and 3 was identified as Cs-137. The roofing material was removed from these three locations (down to bare metal) and was packaged for disposal as low-level radioactive waste. Another location on Level C was also remediated where Cs-137 concentrations were found to be higher than other locations on the roof (-60% of the release limits) and the roof was found to be leaking in this area.
After remediation of these 4 areas, concentrations of thorium and Cs-1 37 on Level C were reduced to <10% of the approved release criteria.
This report documents the results of GA's radiological measurements and surveys completed on the Building 2 Roof. The results of these surveys demonstrate that the Building 2 Roof meets the NRC-and State-approved criteria for release to unrestricted use.
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CENERAL ATOMICs Final Radiological Survey Report for the Building 2 Roof Site Description Building 2 is located on GA's Main Site, as shown in Figure 1. It's location in relation to other surrounding facilities is shown in Figure 2.
There are four (4) different levels of roof over Building 2 to be released to unrestricted use.
These are designated as Levels A, B, C and D as shown in Figure 3. Level A, with an area of
-24,086 ft2 (- 2,238 m2), covers the inner upper level offices and hallway. Level B, with an area of -40,494 ft2 (- 3,762 m2), covers the upper laboratories and service corridor. Level C, with an area of -31,866 ft2 (- 2,961 m2), covers the lower laboratories. Level D, with an area of -29,551 ft2 (- 2,745 m2), covers the hallway and outer lower level offices. A diagram of the various levels of Building 2 roof to be released to unrestricted use is shown in Figure 3. This roof contains some exhaust ducts and ventilation/air conditioning equipment. The total area of these 4 levels to be released to unrestricted use is approximately -126,000 f2
(- 11,706 m2 ).
History of Use GA's Science Laboratories Building 2, also called the "L" Building ("L" for Laboratory) contains approximately 142 laboratories, offices associated with these laboratories, hallways, and a service corridor which houses the utilities for the labs and offices. This building was used during the past -45 years primarily for research and development activities, many of which involved the use of radioactive material.
All 142 laboratories within Building 2 were released to unrestricted use by both the NRC and the State of California after Final Radiological Survey Reports were submitted and confirmatory surveys by the appropriate agency were performed. Subsequently, GA amended it's State of California Radioactive Materials license to add eight (8) laboratories (labs 517, 523, 530/532, 534, 560/562/564) as locations authorized for work involving the possession and the use of radioactive material. GA's Diazyme Group uses these laboratories for work which requires the use of low level radioactive isotopes in the conduct of basic biological research.
Classification Because there was no known radiological contamination on the roof of Building 2, the entire roof was initially classified as an Unaffected Area for radiological survey purposes. Following the discovery of elevated activity levels on Level C, this Level was re-classified as a Suspect Affected Area for radiological survey purposes. A copy of the survey plans are provided in Appendix A.
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GENERAL ATOMICS Final Radiological Survey Report for the Building 2 Roof l
Decontamination Efforts During the performance of the final survey in accordance with the initial Final Survey Plan, two (2) areas with elevated radiation levels were discovered on Level C (called "Area 1 " and "Area 2").
The first area was near column A12 where radiation levels of-70 pR/hr were measured on the surface of the roof. The second area was near column C58 where radiation levels were -30
,uR/hr. Roof gravel samples taken in these areas were analyzed by gamma spectroscopy. The first location had -250 pCi/g of thorium contamination (the corresponding approved release criteria is 10 pCi/g) and the second location had -234 pCi/g of Cs-137 contamination (the corresponding approved release criteria is 15 pCi/g). Additional samples were collected in order to bound the area of contamination. These locations are shown in Figure 14 and Figure 18, respectively. The gamma spectroscopy results are provided in Table 5.
Level C of the Building 2 roof was then re-classified as a "Suspect Affected Area". More scanning, exposure rate measurements and roof sampling were performed resulting in a third area
("Area 3") of contamination found on Level C. This area was located near column B45 (see Figure 22 for approximate location). The highest result of gamma spectroscopy of gravel samples in this area was 29.81 pCi/g Cs-137 (at location 65 shown in Figure 22). Additional samples were collected in this area to bound the area of contamination. The gamma spectroscopy results are provided in Table 5.
The roofing material in all three of these areas was removed down to bare metal and disposed of as radioactive waste in an authorized low level radioactive waste burial facility. Surveys taken on the metal roof following remediation indicated that the metal roof was not contaminated. All radiation levels were at normal background levels (see Figures 15 through 29).
On November 13, 2001, the NRC performed an in-process survey of the metal roof in Areas 1 and 2, prior to GA resurfacing the roof. No contamination was found. The results of their survey were documented in NRC Inspection Report 70-734/01-04, a copy of which is provided in Appendix B. Before remediation of Area 3, the NRC was contacted and asked if an in-process survey was necessary. The NRC decided they did not have to perform another in-process survey.
Subsequently, GA removed the roofing material on Area 3 down to bare metal and disposed of the material as radioactive waste and surveyed the metal roof. No contamination was detected (see Figures 15-29).
Cs-137 contamination was also detected between columns C58 and C64 on Level C ("Area 4").
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Additional samples were taken to characterize the area. The highest concentration found was 9.41 pCi/g of Cs-137. Although this activity level was below the approved release criteria of 15 pCi/g for Cs-137, GA decided to remediate this area for the following reasons: 1) the roof in this area and the surrounding area was in need of repair, 2) for ALARA purposes and 3) removal of a small section of roof material would result in residual concentrations being reduced to approximately 10% of the Cs-137 release limits everywhere on the roof.
A remediation plan was issued which sectioned the roof to be resurfaced into three (3) areas (Areas A, B and C) based on the gamma spectroscopy results (see Figure 3 of Appendix B).
Remediation was performed in May 2003.
"Area A" contained Cs-137 concentrations as high as 9.41 pCi/g; the material was removed down to bare metal and disposed of as radioactive waste. Area B had concentrations as high as 1.5 to 2.0 pCi/g. Area C had Cs-137 concentrations <1.5 pCi/g (< 10% of the limits). The plan was to stage "Area B" and "Area C" gravel/tar material until the State of California's moratorium against disposal of anything "above background" in Class II1 landfills was lifted or until GA obtained approval for disposal in a Class I, Class II or Class HI landfill. However, GA decided to dispose of all of the roofing material from the entire area as radioactive waste to avoid having to store the material due to a potentially lengthy delay in the lifting of the moratorium. The insulation from this fourth area was found to be clean (at normal background levels) and was released to unrestricted use (disposed of at the local landfill).
Surveys of the bare metal roof were performed. No radioactive contamination above normal background was detected. Due to the fact that this area already met GA's NRC-and State-approved release criteria, the NRC was not requested to perform a confirmatory survey, though they had been informed about GA's plan to remediate this area.
All of the remediated areas are shown on Figure 13. Additional information on GA's remediation of the roof is provided in Appendix C.
Criteria for Release to Unrestricted Use As Low As Reasonably Achievable (ALARA)
During decommissioning efforts, GA always attempts to decontaminate to levels as close to "background" as feasible and as far below the approved Release Criteria as reasonably achievable.
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The U.S. NRC-and the State of California-approved criteria for releasing facilities and equipment to unrestricted use are shown in Tables 1 and 2, respectively. The applicable guidelines for enriched uranium (and beta/gamma emitters including Cs-137 and Co-60) are as follows:
For enriched Uranium and most A/ emitters:
5,000 dpm/100 cm2, averaged over a 1 m2 area 15,000 dpm/l00 cm2, maximum in a 100 cm2 area if the average over 1 m2 is met 1,000 dpm/1lO cm2, removable activity For Thorium:
1,000 dpm/100 cm2, averaged over a 1 m2 area 3,000 dpm/100 cm2, maximum in a 100 cm2 area if the average over 1 m2 is met 200 dpm/100 cm2, removable activity Release Criteria for Soils The primary radionuclides found at other nearby GA facilities, on occasion, are enriched uranium and mixed fission and activation products (mainly Cs-137 and Co-60). The approved release criteria, for the predominant radionuclides found in the soil at GA (above normal background concentrations), as identified in the NRC-and State-approved GA Site Decommissioning Plan, are as follows:
Enriched Uranium (U-234 + U-235) 30 pCi/g Thorium (Th-228 + Th-232) 10 pCi/g Depleted Uranium 35 pCi/g Cs-137 15 pCi/g Cs-134 10 pCi/g Co-60 8 pCi/g If more than one radionuclide exists, the sum of the fractions of the concentrations is calculated as follows:
- f. I Li 5
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CENERAL ATOMICS Final Radiological Survey Report for the Building 2 Roof l
C1 = The average concentration levels of radionuclide i in the sample (above background).
Li = The release criteria for radionuclide i.
The sum of the fractions must be less than or equal to one (1).
Exposure Rate Guideline Exposure rates measured at I m above the surface are not to exceed 10 IiR/hr above normal background levels.
Instrumentation and Background Measurements 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 (6) calibration efficiencies (if applicable). All of the instruments used were calibrated semiannually and after repair, except for exposure rate meters which were calibrated quarterly and after repair.
Backeround Measurements for Instruments/Detectors Building 13 on GA's main site was used for conducting background measurements with instruments used for the final survey because: (1) there is no history involving the use or storage of radioactive materials in Building 13, and (2) the various surfaces and construction materials found on the Building 2 roof could also be found within and outside of Building 13. Background information, where appropriate, is included in Table 3.
Minimum detectable activities (MDA's) for instruments used for fixed measurements, for each type of surface (see Table 3), were calculated using equation (5-2) from the NUREG/CR-5849 as shown below:
2.1 46J~7Rdm/ 0c 2)
Equation (5-2) 2.71+4.65,_
tXEx A 100 Where:
BR=background rate (cpm) t = count time (min)
E = efficiency A = area of the detector (cm2) 6
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CENERAL ATOMICs Final Radiological Survey Report for the Building 2 Roof l
Background Roofing Material Concentrations of Concern Typical background concentrations measured by gamma spectroscopy in roofing material on non-impacted building roofs at the GA site are provided in Table 4A (Roof Gravel) and Table 4B (Roof Tar) along with a description of the locations where these samples were taken.
Exposure Rate Background Typical exposure rate background for GA's site (using a Ludlum Model 19 micro R meter) is 12-18 gRIhr measured at 1 m from the surface of soil. This range of exposure rates 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 (9 offsite and 1 onsite at a non-impacted area near Building 15) over a period of 15 months also averaged - 15 jiR/hr (measured at I m from the surface). The range of 12-18 jiR/hr is typical at the GA site for the external dose rates measured at I meter from the surface.
Final Surveys Performed Objectives and Responsibilities The objectives of the final survey plans were: (1) to demonstrate that the average surface contamination levels for each survey unit were below the approved release criteria, (2) to show that the maximum residual activity did not exceed three times the approved release criteria for average surface contamination value in an area up to 100 cm2, (3) to demonstrate the results of analyses of gravel samples were well below GA's approved release criteria for unrestricted use, and, (4) that the exposure rate measurements taken in these areas, measured at I meter above the surface, were less than 10 pR/hr above background.
Survey Plans A Final Survey Plan was developed based on the previous history of use, results of periodic surveys performed on the Building 2 roof, the radionuclides of concern, the potential for contamination, the various types of surfaces encountered and the classification of the various areas. Revisions and supplements to the plan were issued following discovery of elevated levels on Level C (See Appendix A).
Surveys were taken in accordance with an approved survey plan(s) by qualified Health Physics Technicians having a minimum of three years health physics experience.
Every survey taken was documented on a daily basis to a worksheet/drawing showing the approximate locations surveyed/sampled. The documentation included the results of the 7
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GENERAL ATOMICS Final Radiological Survey Report for the Building 2 Roof l
measurements (including units), the technician's signature, date, instrument(s) used (including the model and serial number of both the ratemeter and detector), calibration due date, %
efficiency, background readings (if applicable) and any other pertinent information.
Survey Summary Comparisons of the Site Decommissioning Plan requirements with the Final Surveys performed in relation to the percentage of surface area scanned, number of measurements (i.e., number of fixed radiation measurements), exposure rate measurements (gxR/hr) and gravel/tar samples taken are provided as follows:
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GENERAL ATOMICS Final Radiological Survey Report for the Building 2 Roof
. "Comparisons of Site'Decommissioning Plan-Requirements with.
l;FinalSurveys Performed on the Buildin 2 oof Sury Areal. Gridding
- ofDirect of Exposure Sure n
-f
,Required Measurements
.: CRate Samples I <.' ? - '
Fixed a, A, or Measurements Taken and -
^
-Wipes a
l D-Plan(2 )
No Not Required.
I per 10 rn2 or 10%
Not Unaffected I every 3 m.
Applicable Area(required)
Minimum of 4
875 Final Surveys No Not required.
Total = 1016 Level A - -27% gamma(3)
Total = 20 Unaffected at I m from Level B (4) - -16% gamma (3)
Area the surface.
Level C - -10% gamma(3)
Level A -6 (performed)
Level D - -27% gamma(3)
Level B-7 4
Level D -
7 D-Plan(2 )
Yes, if Not Required I per4 m2 or 100% of Suspect Affected Not Suspect feasible (except on bare I every 2 m.
Area Applicable Affected Area metal roof where Minimum of (required) remediation was 741 4
performed).
Final Surveys No, not On remediated Total = 798 Level C - 100% of Suspect Total = 125 Suspect feasible areas of bare at I m from Affected Area; 10% other gravel Affected Area (I-beams metal roof the surface.
areas(3).
samples (performed) used as 4
markers)
Total = 122 See Figure 9 for scan locations and results.
alpha = 42 beta = 40 Bare metal scanned (100%)
wipes = 40 for a, A, & y in remediated areas.
(X) The total surface area to be released is approximately 11,707 m2. Level C (Suspect Affected Area) is
-2,961 m2.
(2)
D-Plan = GA's NRC-and State-Approved Site Decommissioning Plan.
(3)
Scanned with a 2" x 2" Nal(TI) detector held within 1" of the surface.
(4)
Level B -Also scanned selected exhaust vents and roof edges near selected vents.
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CENERAL ATOMICS Final Radiological Survey Report for the Building 2 Roof Gravel/Tar Sampling The outer layer of the Building 2 roof is gravel on a coating of tar. Gravel/tar samples were collected in approximate locations as indicated on Figures 5, 7, 10, 12, 14, 18, 22 and 26. Each of the gravel/tar samples taken was approximately I kilogram in mass. The samples were properly logged, labeled, tracked and packaged into plastic bags. The sampling locations were documented on a drawing. Each gravel sample was dried, placed into tared marinelli beakers (filled to the top), weighed, sealed and transported to GA's Health Physics Laboratory.
The gravel/tar 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. The gravel samples were counted for a minimum of 30 minutes each. A 30 minute count was sufficient to detect the radionuclides of concern at levels well below GA's approved soil release criteria.
The results of the roof samples collected were compared with the results of background samples taken on non-impacted building roofs at the GA main site. See tables 4A and 4B for roofing material gamma spectroscopy backgrounds.
Results of the Final Surveys The results for the Building 2 roof Final Surveys are provided in figures and tables as noted below:
Exposure Rate Scans Prior to remediation, radiation levels as high as 70 ipR/hr were detected on Level C (approximate area is shown in Figure 9) using a 2" x 2" NaI(TI) detector held within 1" of the surface. Another location (also shown in Figure 9) had readings of 15-30 pR/hr. After remediation the radiation decreased to normal levels (< 17 [iR/hr).
About 27% of Level A, 16% of Level B, 10% of Level C (unaffected areas) and 27% of Level D were scanned for gamma radiation. In addition, all suspect affected areas of Level C were scanned. Radiation measurements (after remediation) ranged from 6-17 pLR/hr as shown on Figures 5, 7, 9 and 12. The levels are not distinguishable from normal background levels.
In addition, the bare metal roof was scanned for gamma radiation in remediated areas. The survey results are provided in Figures 15, 19, 23 and 27. Radiation levels, which ranged from 7-11 [tR/hr were not distinguishable from normal background levels.
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GENERAL ATOMICS Final Radiological Survey Report for the Building 2 Roof l
Exposure Rate Fixed Measurements A total of 1814 fixed gamma measurements were taken using a 2" x 2" NaI(Tl) detector held at 1 meter from the surface. The results ranged from 6-14 itR/hr which is not distinguishable from normal background levels typically 13-18 WR/hr. The results and approximate locations of the fixed exposure rate measurements are provided in Figure 4 (for Level A), Figure 6, (for Level B), Figures 8A and 8B (for Level C), Figure 11 (for Level D), and Figures 15, 19, 23 and 27 in the remediated Areas 1, 2, 3 and 4, respectively.
Scanning (a and P!
Areas around randomly selected ventilation exhausts on Levels B and C, were scanned for,
activity. The results were indistinguishable from normal background levels as shown on Figures 7 and 9.
In addition, the bare metal surface in each of the four remediated areas on Level C was scanned for a and 13 activity using a 434 cm2 gas flow proportional detector. The results ranged from 0 to 40 cpm for a activity (normal background was 0 to 26 cpm). The P results ranged from 800 to 1400 cpm (normal background ranged from 900 to 1300 cpm). The approximate locations and results are provided in Figure 16 (for Area 1), Figure 20 (for Area 2), Figure 24 (for Area
- 3) and Figure 28 (for Area 4).
Fixed Measurements (a and a!
Forty-two (42) a and forty (40) P fixed measurements were taken on bare metal surfaces on Level C after remediation of the roof. No contamination was detected. The fixed a measurements and the fixed P measurements were all less than the minimum detectable activity (MDA) for the instruments used. For approximate locations and results, see Figure 17 (for Area 1), Figure 21 (for Area 2), Figure 25 (for Area 3) and Figure 29 (for Area 4).
Removable Activity Forty (40) wipe samples were taken on the bare metal roof in remediated areas of Level C following removal of the roofing material. The samples were analyzed using a Canberra low-level a/p counting system. Both alpha and beta activity levels were less than 20 dpm/100 cm2 which is far less than the approved release criteria for removable activity and not discernable from normal background activity. For approximate wipe locations, see Figure 17 (Area 1),
Figure 21 (Area 2), Figure 25 (Area 3) and Figure 29 (Area 4). The results are provided in Table 6.
11
l+
CENERAL ArOMICS Final Radiological Survey Report for the Building 2 Roof l
Gravel Samples A total of 144 gravel/tar samples were taken prior to and following remediation. Approximate locations are shown in Figure 5 (level A), Figure 7 (level B), Figure 12 (Level D) and Figures 10, 14, 18, 22 and 26 (all taken on Level C). The results are provided in Table 5.
Of these, 70 gravel/tar samples were taken of the roofing material which remained (these are the "final" samples). A summary of the gamma spectroscopy results for these 70 gravel/tar samples is provided below. The results for each sample is provided in Table 5.
Radionuclide Concentration (pCi g) 137Cs
- Co 228 232.
High 1.11 4 0.15 0.04 + 0.04 0.38 A 0.23 3.81 X 1.83 3.39 +/- 0.96 2.69 0.38 Low N)
ND ND ND 0.28 +/-0.09 ND Average
- 0.15 s0.13 50.16
- 1.57 1.60 s2.01 (N = 70)
Notes:
- 1. ND means not detected or less than the average minimum detectable activity (MDA) for the geometry and counting times used.
- 2.
Average Minimum Detectable Activities (MDA's):
U-238 = 1.37 pCi/g (63 keV peak)
U-235 = 0.12 pCi/g (186 keV peak)
Cs-I 37= 0.10 pCi/g (662 keV peak)
Co-60 = 0.13 pCi/g (1173 keV peak)
Th-228 = 0.17 pCi/g (238 keV peak)
Th-232= 0.38 pCi/g (911 keV peak)
- 3. The high concentrations for each isotope did not occur in the same sample. No sample had a sum of fractions greater than 1.0.
- 4.
Background is not subtracted from results. See Tables 4A and 4B for Background Roofing Material concentrations.
- 5.
The average MDA was used to determine the average activity when the results were ND.
- 6.
Average radioactive material concentrations were not discernable from normal background levels.
Cs-137 was detected in 34 out of 70 gravel/tar samples. The highest activity was 1.11 + 0.15 pCi/g (sample B2-Roof-30 shown on Figure 10). The average concentration was
- 0.15 pCi/g.
These values are far below the approved release criteria of 15 pCi/g.
Co-60 was detected in one (1) out of 70 gravel/tar samples. The activity was 0.04 +/- 0.04 pCi/g, (sample B2-Roof-37 shown in Figure 7), which is far below the approved release criteria of 8 pCi/g.
12
I +
CENERAL ATOMICS Final Radiological Survey Report for the Building 2 Roof l
The average concentrations of U-235, U-238, Th-228 and Th-232 are not discernible from normal background activity concentrations for these isotopes.
Confirmatory Surveys On November 13, 2001, the NRC performed an in-progress survey on two (2) areas following remediation and no activity above normal background was detected. See Appendix B for NRC Inspection Report 70-734/01-04 which addresses the in-progress survey performed by the NRC.
Conclusion Final contamination and radiation surveys, as well as the results of analyses of gravel/tar samples, as documented in this report, demonstrate that the Building 2 Roof meets the NRC-and State-approved criteria for release to unrestricted use and that residual activity levels are as low as reasonably achievable.
13
Table i: USNRC'S ACCEPTABLE SURFACECONTAMINATION LEVLS I.u'li es, IAverage j
I,I a ov-b ebl r..-I.,
-,^
i (dpniI1D~cm2)
-'(..............dpmVIO0 cm' Ii(d im I006n )
U-nat, 235U, 238U, & associated decay products 5,000 ac 15,000 a 1,000 a Transuranics, 226Ra, 228Ra, 230Th, 228Th, 231Pa, 227Ac, 100 300 20 125i, 129i1 Th-nat, 232Th,9OSr, 223Ra, 224Ra, 232U, 126i 133i, 131I 1,000 3,000 200 Beta/gamma emitters (nuclides with decay modes other than alpha emission or spontaneous fission) 5,000 15,000 1,000 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 1 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 1 00 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 cm2 and 1.0 mRad/hr at 1 cm2, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.
T-I
Tahle 2: STATE OF CA ACCEPTABLE SURFACE CONTAMINATION LEVELS '
Nuclides' Averageb 4 I
Maxlmumb`4 Removable","
(dpm/lOOcrn)
(dpm/100cm2)
(dpmIIOOcm2)
U-nat, 235U, 238U, & associated decay 5,000 15,000 1,000 products Transuranics, 2 26Ra, 2 28 Ra, 23T,
- nTh, 100 300 20 2'Pa, 2 2 7Ac, 1251, 1291 Th-nat, 232Th, 9OSr, 223Ra, 224Ra, 22u, 26i, 1,000 3,000 200 "133, "'1I Beta/gamma emitters (nuclides with decay modes other than alpha emission or 5,000 15,000 1,000 spontaneous fission) except '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 1 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'.
e The amount of removable radioactive material per 100 cm2 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-lgamma emitters should not exceed 0.2 mrad/hr at I cm2 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.
T-2
r - [
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I-I I'
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(
I V
Li-I I
I V r-_
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Table 3: List of Instruments Building 2 Roof -
.d Instrument Detect r bRangeiCalibrai on Desitiency:
(cpn,pR/hrormRhrT)
Due Date MDA (l00cin2
& 5Ocm:
Description dete ciors on ly)'
only
-Ludlum Ludlum Model 43-37 gas Four Linear Ranges Active Probe Area = 434 cm2. The detector and rate Model 2221 (434cm2) proportional 0-500,000 & one Log 12-03-01 21.29%
meter are combined and mounted on a roll around cart.
S/N 148425 Alpha detector 50-500,000 7 -26 cpm (metal)
The instrument features a static-flow system, quick S/N 086236 (cpm) 07-31-02 21.09%
connects, a portable gas bottle and a means to adjust the height of the detector from the floor for optimum performance.
Ludlum Ludlum Model 43-37 gas Four Linear Ranges Active Probe Area = 434 cm2. The detector and rate Model 2221 (434cm2) proportional 0-500,000 & one Log 11-05-03 20.98%
0-20 cpm (metal) meter are combined and mounted on a roll around cart.
SIN 97287 Alpha detector 50-500,000 The instrument features a static-flow system, quick S/N 083293 (cpm) connects, a portable gas bottle and a means to adjust the height of the detector from the floor for optimum performance.
Ludlum Ludlum Model 43-37 gas Four Linear Ranges Active Probe Area = 434 cm2. The detector and rate Model 2221 (434cm2) proportional 0-500,000 & one Log 01-10-02 23.62%
meter are combined and mounted on a roll around cart.
S/N 84459 Beta detector 50-500,000 1150-1290 cpm (metal)
The instrument features a static-flow system, quick S/N 086215 (cpm) 09-27-02 31.0%
connects, a portable gas bottle and a means to adjust the height of the detector from the floor for optimum performance.
Ludlum Ludlum Model 43-37 gas Four Linear Ranges Active Probe Area = 434 cm2. The detector and rate Model 2221 (434cm2) proportional 0-500,000 & one Log 09-26-03 30.17%
900-1300 cpm (metal) meter are combined and mounted on a roll around cart.
S/N 154202 Beta detector 50-500,000 The instrument features a static-flow system, quick SIN 149017 (cpm)connects, a portable gas bottle and a means to adjust the height of the detector from the floor for optimum performance.
Ludlum Ludlum Model 43-68 Four Linear Ranges 655 + 70 cp2m (metal)
Model 2221 100 cm' proportional 0-500,000 & one Log 100 cm2 gas flow proportional counter S/N 84423 Beta detector 50-500,000 01-08-02 24.43%
MDA =249 dpm/lOOcm2 SIN 119444 (cpm) 08-05-02 36.47%
MDA= 167 dpm/lOOcm2 l Ludlum' Ludlum Model 43-68 Four Linear Ranges Model 2221, 100 cm' proportional 0-500,000 & one Log 435 + 170 cp2m (metal) 100 cm2 gas flow proportional counter S/N 86302v '
Beta detector 50-500,000 07-24-03 31.20%
SIN 142547 (cpm)
MDA= 160 dpm/IOOcm2 Ludlum Model 19 RCA 6199 coupled to a Five Ranges I inch x I inch Nal (TI) scintillator is mounted intemally.
Micro-R Meter Nal (TI) Scintillator 0-5000,uR/hr 07-04-01 N/A 12-18 pRhr Used for measuring external dose rates on the surface and SIN 87120 at one meter T-3
r-F --
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I Table 3: List of Instruments Building 2 Roof Background '
Instrument Detector Range.i Calibration:
' Efficiency'..'
Description.
(cpm, pR/hr or mR/hr)
-'Due Date MDA (l00cmp' &'50cm'ia,,
-,,detectorsionly)
Ludlum Model 19 RCA 6199 coupled to a Five Ranges tar/gravel roof I inch x I inch Nal (TI) scintillator is mounted internally.
Micio-R Meter '
Nal (TI) Scintillator 0-5 000 pR/hr 02-10-02 NA 9-10 pR/hr contact Used for measuring external dose rates on the surface SIN 158881..
9-10 VR/hr @ I meter and at one meter.
Ludlum Ludlum Model 44-10 tar/gravel roof 2 inch x 2 inch Nal (Tl) scintillator. Used for measuring Model 3 Nal (TI) Scintillator Four Ranges 07-04-01 NA 7-9 pR/hr contact external dose rates on the surface and at one meter.
SIN 147819 Gamma Detector 0-500 pR/hr 09-28-01 8-lOupR/hr@ I meter S/N 153765 12-07-01 LLudlumLudlum Model 44-tO tar/gravel roof 2 inch x 2 inch Nal (TI) scintillator. Used for measuring Model 3 Nal (TI) Scintillator Four Ranges 02-05-02 NA 9-10 pR/hr contact external dose rates on the surface and at one meter.
S/N 153590 Gamma Detector 0-500 pR/hr 11-17-03 10-11 IlR/hr @ I meter S/N 155190 Ludlumn' Ludlum Model 44-10 tar/gravel roof 2 inch x 2 inch Nal (TI) scintillator. Used for measuring Model 3 '
Nal (tI) Scintillator Four Ranges 06-12-01 NA 8-9 pR/hr contact external dose rates on the surface and at one meter.
SIN 153311, Gamma Detector 0-500 pR/hr 12-07-01 7-9 pR/hr @ I meter SIN 155594 10-09-03 metal roof 5-8 p R/hr contact 5-8 pR /hr @ I m eter Ludlum Ludlum Model 44-10 tar/gravel roof 2 inch x 2 inch Nal (TI) scintillator. Used for measuring Model 3 Nal (Tl) Scintillator Four Ranges 07-04-01 NA 9-10 pR/hrcontact external dose rates on the surface and at one meter.
S/N 153551, Gamma Detector 0-500 pR/hr 12-07-01 9-11 pR/hr @ I meter SIN 155109 07-09-02 metal 11-17-03 8-9 pR/hrcontact 8-9 pR/hr @I meter Ludlum.
Ludlum Model 43-64
<20 cpm (all)
Active Probe Area = 50 cm2
'Model 12 '
Alpha Scintillator Four Ranges 05-11-02 22.52%
MDA= 209 dpm/l OOcm' Used for alpha surveying.
S/N 13880i ZnS (Ag) 0-500,000 cpm SIN 145696
- Ludlum, Ludlum Model 43-64
< 20 cpm (all)
Active Probe Area = 50 cm2 Model 12' Alpha Scintillator Four Ranges 06-27-02 21.77%
MDA = 216 dpm/lOOcm2 Used for alpha surveying.
S/N 138738.
ZnS (Ag) 0-500,000 cpm S/N 44834 Ludlum;
Ludlum Model 43-64
<20 cpm (all)
Active Probe Area = 50cm2 Model 12' Alpha Scintillator Four Ranges 10-23-03 21.77%
MDA = 216 dpm/l OOcm2 Used for alpha surveying.
SIN 91103, ZnS (Ag) 0-500,000 cpm S/N 092192 T-4
F-7*
F _7..
17 _-" F
(
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F -
I -
rT f7_1 I-f -
[
i_
Table 3: List of Instruments Buildinig2 Rof:;
.k un*
, N,
,.P.
K.., ' -Backround
.-a.c:g 'o.n Instrument Detector Range Calibration Effi iy Description
'cpimp R/hr or'mR r Due Date. -
0 d
dkte~tors only
, Ludlum '
Ludlum Model 44-9 Four Ranges 01-17-01 21.35%
80-100 cpm (metal)
The instrument isused forbeta/gamma surveying. The Model 3 15 cm2 0-100,000 cpm detector has an active probe area of 15 cm2.
S/N 138880 Beta/Gamma 07-18-03 24.62%
20-60 cpm (insulation)
S/N 145693 Ludlum' Ludlum Model 44-9 Four Ranges The instrument is used for beta/gamma surveying. The Model 3 15 cm2 0- 100,000 cpm 03-11-04 26.14%
60-120 cpm (tar/gravel roof) detector has an active probe area of 15 cm2.
S/N 138880 Beta/Gamma S/N 117851 Ludlum Ludlum Model 44-9 The instrument is used for beta/gamma surveying. The Model 3 15 cm2 Four Ranges 09-10-01 21.05%
20-80 cpm (metal) detector has an active probe arca of 15 cm2.
S/N 139180 Beta/Gamma 0-100,000 cpm 40-60 cpm (tar/gravel roof)
S/N 145973 Ludlum Ludlum Model 44-9 The instrument is used for beta/gamma surveying. The Model 3 15 cm2 Four Ranges 11-20-03 29.18%
20-60 cpm (insulation) detector has an active probe area of 15 cm2.
SIN 143349 Beta/Gamma 0-100,000 cpm S/N 145967 Ludlum,'
Ludlum Model 44-9 The instrument is used for beta/gamma surveying. The Model 3. '15 cm2 Four Ranges 11-20-03 27.96%
20-60 cpm (insulation) detector has an active probe area of 15 cm2.
SIN 61488 Beta/Gamma 0-100,000 cpm S/N 117851 Ludlum,
Ludlum Model 44-9 The instrument is used for beta/gamma surveying. The Model 3.
15 cm2 Four Ranges 11-20-03 27.96%
20-60 cpm (insulation) detector has an active probe area of 15 cm2.
S/N 4687,:
Beta/Gamma 0-100,000 cpm SIN 117842 Canberra Low Level.
Gas Flow Canberra Model 2404 Low Level a/l gas proportional a/p Counter Proportional Detector N/A As needed 30%
Varies with Sample counting system used to count wipes for removable Model 2404 contamination. Results are usually reported as
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _,_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ d p m ll 0 0 cm 2.
Canber',ria 6arnma l ligh Purity Varies with Gamma Spectroscopy MCA system using a high purity Spectroscopy, Germanium Detector N/A As needed Sample Varies with Sample Germanium detector.
System ICM-..
T-5
F7 F77._,
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17'-
K-_
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(-
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(
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~:Table 4A: Backgrud Roof Gravel Sample,Results(Gammafi Spectir6scp, 30 Minite Count Times (Samplesi Collectfe~d fro-m' Buidifii~-1t033-1 and 33)
~~.-.Radionuclide C'oii~en rti6n' OCplg:."- Res4lts'l 2 SD SaniplelD I
w~~o K
rn~~a Total coori22 23#u23u I
~~~~~Averge of II73 and
.:A-eraeMf BIO-Roof-IG
'661.6 keV ak' { 1332 peaks 238/893 keV peaks AMerae of 22Th + 2 92.77 kVpa 8(4)kVpa BIO-Roof-IG ND ND
~~~~0.26
+0.04 0.45 +/-0.14 0.71 0.88+ 0.27 0.06 0.03 BIO-Roof-2G ND ND 0.25 +0.06 0.51 +/- 0.21 0.76 1.03 +0.40 0.06 +0.04 BIO-Roof-3G ND 0.02 + 0.02 0.27 +0.06 0.37 + 0.24 0.64 0.81 +0.51 0.05 +0.04 BIO-Roof-4G ND ND 0.32 +0.08 0.73 +/- 0.37 1.05 ND 0.06 +0.06 BIO-Roof-5G ND ND 0.35+I0.09 0.77 +0.33 1.12 0.70 +/-0.50 0.10+0.07 B33-1-Roof-6G 1.10+4.0.10 ND 1.07+0.11 1.77++/-0.34 2.84 2.77 +/-0.56 0.17 +0.09 B33-1-Roof-7G 0.91++/-0.13 ND 3.01 +0.35 1.81 + 0.43 4.82 2.41 +0.70 0.27+4-0.12 B33-1-Roof-8G 1.09+E0.10o ND 1.05+0.10 1.74++/-0.33 2.79 2.73 +0.55 0.17 +/-0.09 B33-1-Roof-9G 0.98+0.09 ND 2.55 0.28 1.66++/-0.35 4.21 1.77 I0.43 0.27 +/-0.07.
B33-1-Roof-IOG 0.87+0.09 ND 2.89+h0.27 1.53+I0.31 4.42 2.50+-10.57
- 0. 18+0.08 B33-Roof-1G ND ND 0.50 +/-0.11 1.01+A.0.40 1.51 0.87 +0.62 0.13+0.09 B33-Roof-2G ND 0.04 4+ 0.05 0.50 + 0.10 1.05 I 0.41 1.55 0.72 4+ 0.58 0.10A: 0.08 B33-Roof-3G ND ND 0.59 +0.10 1.08 +0.33 1.67 1.09+ 0.54 0.05++/-0.06 B333-Roof-4G ND ND 0.49 I 0.08 0.77 +/- 0.25 1.26 0.82 4+ 0.40 0.1 I + 0.06 T-6
1F.
1-
[7-W-
C(-
I-T~
(
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f ---"
F-
- 1.
k
,'....: :.".sTable 4A ' Backgrorund Roof Grav'elSampleRe'sults(Gaiina'Spectro'c"py, 30 Mimite Count Times).
- Radionu lide Cobene ation (pCi g).- R-tesults 4
2 SD Sample ID
':-7f v.
r
'"Cs
'~Co.
"~Th
~
Ra Total Thriu, i rU tU 66:' ':
1.6 -'V p-ak.
Average of 1173 and veage.
(232
)..-.
' ' ' -. l,661.6 eV ep::.:13eaks 238/583 keV Pe~aiks.,'
veiage ofi','
1 2 3.:
27 e'a:,86 (144) keV ' cak s:
l
- x g
'R I 1 ke r~
-K.
R i
B33-Roof-5G ND ND 0.69 0.13 1.32 + 0.43 2.01 1.12 + 0.73 0.08: f0.08 Average - I SD 0.33 +/- 0.49
< 0.06 0.98 0.99 1.10 + 0.51 2.09 +/- 1.41 1.35 +/- 0.86 0.12 + 0.07 Averageplus 1 0.82
<0.06 1.97 1.61 3.50 2.21 0.19 Standard Deviations Average plus 2 1.30
< 0.06 2.96 2.12 4.91 3.07 0.26 S
Standard Deviations Typical Gravel Background Levels in pCi/e (at +/- 2 SD)
Cs 137 Co-60 1.35 pCi/g +/- 1.72 0.12 pCi/g +/- 0.14 2.09 pCifg +/- 2.82 0.33 pCi/g +/- 0.98
< 0.06 pCi/g ND = Not Detected Not Dctected - s 0.06 pCi/g for Cs0137 and Co-60, s 0.62 pCi/g for U.238 T-7
F.-I F -I F-,
f--
(I ---. ( --
F c:
C-1-
(-
U- * ~-
(-
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(~
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Tabie 4B.
Gamma Spectroscopy iesults of (Backgr
) Tar Saiics Clected fromBuildings 10,33-1 and 33.
~~~~~~~s -,:.:
.j- " ;,
=, i-:
... 22::8 2 5 Samp eID- :
37
.C6,,
, 2-Th 2 Ra' Tota iTmh's 2
I (Annroiiniatclv 30 Minute Cout Tm
- '. ,,,, ^,.
. Ave ge6 of 1 173 and
, verage of,,
2
).
Sample ID J '"Cs
. ~~~~133 fk
.53 23 8 T ke Jea(
228 ragf.'
Toa hoim23J8 5
___________________ I.
Avengep of17Tnhvrg o
2 2 h
.kpa
.661.6 kVpeak
- 1332 peaks 583238keVpeak Avengeof
+ 232T 92.7 keV7peak 186(144) keV peak B1O-Roof-IT 0.26 0.12 ND 0.81 +/- 0.17 1.88 +/- 0.72 2.69 5.53 +/- 1.11 0.49 +/- 0.14 BIO-Roof-2T ND ND 1.03 0.38 3.21 +/- 1.47 4.24 4.84 +/-2.31 0.37 0.31 B10-Roof-3T ND ND 1.40 0.37 3.99k 1.60 5.39 ND ND B10-Roof-4T ND ND 0.50 +/- 0.24 2.16b0.97 2.66 5.10 1.69 0.30 + 0.21 BIO-Roof-5T ND ND 1.41 +/- 0.40 5.30 +/- 1.93 6.71 ND ND B33-1-Roof-6T 0.34 +/- 0.18 ND 0.49 0.19 1.93 0.70 2.42 3.03 +/-1.63 0.30+0.18 B33-1-Roof-7T ND ND 2.71 +/- 0.66 6.32 +/- 2.66 9.03 ND ND B33-1-Roof-8T 0.36 +/- 0.20 0.23 +/- 0.13 0.76 +/- 0.37 1.73 +/- 1.31 2.49 4.75 +/- 1.66 0.30 +/- 0.26 B33-1-Roof-9T 0.29 +/- 0.24 ND 0.60 +/- 0.28 2.24 +/- 1.10 2.84 4.38 +/- 1.93 0.45 +/- 0.22 B33-1-Roof-IOT 0.30 +/- 0.21 ND 1.98 +/- 0.47 6.02 + 2.10 8.00 ND 0.51 4 0.32 B33-Roof-IT ND ND 1.68 +/- 0.35 4.64 +/- 2.01 6.32 ND 0.32 +/- 0.25 B33-Roof-2T 0.19 0.15 ND 0.63 0.20 2.28 +/- 0.90 2.91 2.73 +/- 1.18 0.20+/-0.18 B33-Roof-3T ND ND 1.68 +/- 0.43 5.38 I 2.44 7.06 ND 0.31 +/- 0.32 table 4b tar backgrounds.wpd T-8
I- ---
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I Table 4B.
GammaSpectroscopy Resultsof (Backgound) Tar Samples Collected from Buldins 10,33-1 and 33.
^
.Anrxim aelv 30 Minute C nt Tieg --
Rdionuchlde Co"n'centration ('pi/g),-,Results : 2 SD-.
Sample ID
.,Cs
- "CO 228T 228 Ra Total Thorium 2
Average of 1173 and Average of (232Th)
.p 661 keV eak 133 pea
- -' 58323 ke~~~~pc t1 /
i >v
>2g
+2s2
~92.77 keV peak 186 (144) keV.peakl 661.6ke~peak
`1332pjeAks 583/238 keV peaks Average of*"T+
3 h 661.6 keV'Oek TRI 92.77 keVf peak B33-Roof-4T 0.25 + 0.20 ND 0.70 +/- 0.28 2.67 +/- 0.91 3.37 4.26 4 1.78 0.25 +/- 0.21 B33-Roof-5T ND ND 1.69 +/- 0.38 4.85 +/- 2.04 6.54 ND 0.31 +/- 0.30 Average I a 0.13 pCi/g i 0.02 pCi/g +/- 0.06 1.20 pCi/g b 0.65 3.64 pCi/g +/- 1.65 4.84 pCi/g + 2.27 2.31 pCi/g +/- 2.34 0.27 pCi/g + 0.16 0.15 Average plus I a 0.28 pCi/g 0.08 pCi/g 1.85 pCi/g 5.29 pCi/g 7.11 pCi/g 4.65 pCi/g 0.43 pCi/g Average plus 2 a 0.43 pCi/g 0.14 pCi/g 2.50 pCi/g 6.94 pCi/g 9.38 pCi/g 6.99 pCi/g 0.59_pi/g Tyvpical Tar Backaround Levels in PCi/M (at +/- 2 SD)
Cs-137 Co-60 2.31 pCi/g + 4.68 0.27 pCi/g + 0.32 4.84 pCi/g + 4.54 0.13 pCi/g 0.30 0.02 pCi/g + 0. 12 ND = Not Detected Not Detected:
s 2.07 pCi/g for Ac-228 (338 keV).
table 4b tar backgrounds.wpd T-9
(7
(
- 7 C.
r--
Ip.-1
(_ '
(F-c_-
V i_
(- --
t __
C -
C ____
(-
C --- -
C-_
I..
- Table 5. Gamma' Spectrs opyR isituIt Biii' B
ipdin 2
-2;;Roof S-a;iiip
- -
- RadionuclidecConce -eidon s
2 ackgro s
is_
Subtated-30 Minute Cot§ (Unl Othev.ise No VICS CO.C Th-T Total
- Sample ID Fig
.¢;-661.6 ^"
'1173.<.-
238 '
T orium 63.3 (144) 186 Comments keV:ek e-keV p
22 T keV peak
- p e a k T h k V p a 1
B2-ROOF-A 1 5
ND ND 2.15 + 0.07 2.53 + 0.21 4.68 + 0.28 1.55 + 0.61 0.23 + 0.05 Below Release Criteria
( 2 h r )
2l B2-ROOF-A 2 5
ND ND 1.97 + 0.13 2.44 0.38 4.41 + 0.51 1.16 + 1.25 0.18 + 0.09 Below Release Criteria 3l B2-ROOF-A 3 5
0.03 + 0.02 ND 2.05 + 0.07 2.61 +0.19 4.66 +0.26 1.41 + 0.62 0.19 + 0.05 Below Release Criteria (2 hr) 4 B2-ROOF-A 4 5
ND ND 2.01 + 0.13 2.69 + 0.38 4.70 +0.51 1.70 + 1.15 0.20 + 0.09 Below Release Criteria 5
B2-ROOF-A 5 5
ND ND 0.38 + 0.09 0.81 + 0.25 1.19 + 0.34 ND ND Below Release Criteria 6
B2-ROOF-A 6 5
ND ND 1.99 4 0.14 2.44 + 0.45 4.43 + 0.59 2.07 + 1.41 0.16 + 0.09 Below Release Criteria 7
h2-ROOF-B 7 7
0.03 + 0.03 ND 2.07 + 0.07 2.46 + 0.18 4.54 + 0.25 1.59 0.70 0.25 + 0.07 Below Release Criteria
( 2 h r )_
8 B2-ROOF-B 8 7
ND ND 2.07 + 0.13 2.30 +0.43 4.37 + 0.56 1.88 + 0.84 0.17 + 0.09 Below Release Criteria 9
B2-ROOF-B 9 7
ND ND 2.07 + 0.14 2.28 + 0.38 4.35 + 0.52 2.31 + 1.49 0.23 + 0.11 Below Release Criteria 10 B2-ROOF-B 10 7
ND ND 2.02 + 0.06 2.46 + 0.18 4.48 + 0.24 1.51 + 0.57 (0.20 +
Below Release Criteria (2 hr) 0.04) 11 B2-ROOF-B 11 7
ND ND 2.15 + 0.14 2.52 4 0.39 4.67 I 0.53 1.80 + 1.22 0.14 + 0.10 Below Release Criteria 12 B2-ROOF-B 12 7
ND ND 2.14 + 0.13 2.38 + 0.41 4.52 + 0.54 1.22 + 1.23 0.15 + 0.09 Below Release Criteria 13 B2-ROOF-C 13 10 ND ND 2.10 + 0.13 2.56 + 0.41 4.66 + 0.54 2.22 + 1.53 0.15 + 0.09 Below Release Criteria 14 B2-ROOF-C 14 10 ND ND 0.67 + 0.11 1.68 + 0.30 2.35 + 0.41 0.99 + 0.68 0.07 + 0.07 Below Release Criteria T-10
f"'
U---
[
(7 r ~ ~ _- _
r u'
i--(--r f F-U.*-
(
(7.-
(7
(-,
V
(,
I Table 5: Gam-a Speeto:coy Re "ult" o Building Roof Saiil
..<:7 ~ ; ;-
______once (pCi/g)
Mt agrunt__
u2ac'u-Ssun Radionuclide.
ncen io s
S'
.' l am pleID6,
' Fig
- . ^ >
'1173, 9i
,s Thortual
'( ii)
.6' C mments 15 B2-ROOF-C15 10 ND ND 2.1150.13 2.55+0.41 4.66+0.53 1.94+1.32 0.16+0.11 BelowReleaseCiteria
~~~~~~~~~~~~~~~~~O Th -'Th" T'61 i6_______
- ~N>~
X2O~.4
,. 65' O.-.,,:4.9051.
~20+ 1.1 0ii___________________
17' 1132:.ROOFz C 17' IO 0.3010 ND, *,,
2.4 0uqu 0
l i
-,ov dii~ea~~
at o.
18 B2-ROOF-C 18 10 ND ND 2.12 +0.13 2.58 +0.43 4.71 + 0.56 1.07 + 1.08 0.18 +0.10 Below Release Cntenia 19 B2-ROOF-19 12 ND ND 2.11 +0.13 2.52 + 0.42 4.63+0.55 2.81 + 1.45 0.20+0.10 Below ReleaseCntena 20 B2-ROOF-D 20 12 ND ND 0.34 + 0.10 0.91 + 0.24 125 + 0.34 ND ND Below Release Crtera 21 B2-ROOF-D21 12 ND ND 2.19+0.14 2.58+0.37 4.77i0.51 2.35+0.70 0.18+0.09 Below ReleaseCntena 22 B2-ROOF-D22 12 ND ND 2.03+0.13 2.38+0.36 4.40 +0.49 1.36+ 1.19 0.21+0.10 Below ReleaseCntena 23 B2-ROOF-D 23 12 ND ND 2.05 + 0.13 2.51 5 0.41 4.55 + 0.54 2.04 + 1.46 0.14 + 0.09 Below Release Criteria 24 B2-ROOF-D 24 12 ND ND 1.99 + 0.13 2.27 I 0.36 4.26 + 0.49 0.86 + 0.93 0.22 + 0.10 Below Release Citera 25 B2-ROOF-C 257 '10; fND7~I:
iKND mv
<22.4O28.40'+~
- s 250.80+ ;>11062i 'O0.75' 0.34 dring a reiiediati6n' B2ROOF q7W'_______-
45*2 43+4i AITH P21
.J'i 1 '(;'.<^S0 86 268 1B2-ROOF C26 ;
s10 ND233 8+ 64 21ND3 25; 2+/-5 0.43 45710.5695+10
,1 90.
0.1635 veddonw Reea 2 ritedaion 19
_B2-_
ROO_ D 19 12 ND.
ND 2O. 0.13 12.65+
0.42 2.4 4+1.09 2.81 + 2.61 0.20+O.l4 BelowdReleas Citrdiao 28' 32-ROOFC 20 10 090N 6+0.70 v12.
30.93 ND ND 4 8 Releas 1 rieriat 21N B2-RO 4OF;CD21~
12 ND1~OP ND 2~.19+'0.14.
2.58490.37
- 4.
1~770.71 2.35 + 1.910 0.38 +0.09.
Belmowe dRenlAeas 1Criereiato 30' B2-ROOF-30 D2 10',
02 ND' 2.0301 2
.38 036 440 049 3
1 01 Ba Critemiatian 24 _____ROOF-D_24_
_2_NDND_1_99_
0.13 2.27 0_36_4_26_ 0_ 49_ 0.864 1.87' 20.2244 0.15 Below__
Release__Crit
__ria
_2
_4
_________r4
'~
1 24
-~
.6A 7
1
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r ri..
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- f. -_
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T---
Ta 5: Gammap r co py eu lts of
-u.ldi R:a::diox iclide Coniceir ation (pCi/g)- Results 4+ 2d Bk' 'dg t... S66.d' 30 C.
.t.
i__
-on sae-in.e s n
oe, m
p
(
Th:^...
T
'3; B
2 0a-0...2
.,,..' i Sampe.ID '
Fi i6 1173>.'
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T30rium
- 6.
"4 0441 4'
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'#'7
- eVpe6a k
V kiV jeak keV ek'9. -Th k.-.
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, peak" 2Th
'keV peak Y
L~~~~~~~~~
3 rB2-IROO.35 2
710 3
ai, 1
1 3
- a.
B2 OOF 36 0
- 23155 0.20 r,,.,
0016 2.09 O.5.
4.09`0.74 7.43 0.3787 0 52 z G32' 10i;'
3A41tt09'"4
-t'
!4
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\\
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t N
a4 40 B2-ROOF-C33 40 o
10 0.09 0.06 4ND-1.73 4:0.13 2.42 4 0.436
.4.16
+ 0.49 1.8i60 +1.2 0.420 f0.42 B~m'elo Reeae ring tc2emdriaii 341~. B2-ROOF-C 341 10 06.13 +0.08 ND 1.86+05 0.1 2.326+ 0.54 4.784 0.685: 3.91 +1.4460.14
- 21.
R d
B Ras itediatio 10' '034
.,<~~~~~~~~~
2.8184d'697~
0.424+6-R-emoveduring ~Ai=earemdato
- 3'-'%
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, N 1
` :1.38. 0.16i 2867:E035 4-.79+~E0.71 2.37+2.0k1.36 0.32 +
70.14,, Removed duing, ra r2'emedifatido
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~~~
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.,.7.
2+0.67.~ 2175+1.20
.0.1700 40 B32-ROOF-C40 10 0.09 +0.06 ND 1.73++/-0.13 2.43+0.36 4.16+0.49 1.60 + 1.24 0.20 +0.08 Below Release Criteria 41 B2-ROOF-C41 1 0 0.13+0.08 ND 1.86 +/-0.14 2.02 0.54 3.88+0.68 1.91 +/- 1.44 0.14 +/-0.11 Below Release Criteria R~n~ddu8 Ri
'Area 1rremedieaioni 4 ~~~~~~~~~~4a,(
4~-N
-'``%
4 1o1 4
I a
01
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43,,2-ROQF-~b,43 1-2.6+0i-',c:~.4O2,T.411
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.4
~~~~~~~~~~~~~~~~~~~~~~~'2.2 68 2tkemovedRe vdddmdrexngi" 1d.807+O~
0- 17 ~2.66+
4' 7-,.
nfA
- 064,
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Rern6d'diiiiArareewttn 4
- 2-ROO'Ff-aC-46. J4;02+.9
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- .5~7
,'2.71 4't0.59.
4.5'.7 2.80 +/- 1.81`
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."'65 "b47 '
s-A 4
aŽ
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_____________ ~~10'~ ~~6.00+0.27'~ '>ND
-- j90.7,;4+45 4450.62,,,.5.081+2.04' t O.-48+-0.13'
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_________I_______-6.0 ND,.
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7_
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I
[Table'5: Gamma Spectrosc py Results of Building 2Roof S pe.:.
No:.-
- te)
- j -Radionticlide Conceitriaitioh (pCilg) - Results' +/- 2c. 'Babkg-rounds h:of'~ Subfractd jOMinute A,
L.
-.,.<< > '. E ~~~~~~~o itec nttiij"'
cuns ucd'
-;......iUnes§t erwis
- ted,
- -,9'
"".3 r
i
'CS
o-
Ti'
.,-ti':
- ~h.
To tal4
5+
.7
.2%
Sample ID
'i';i 616I (1173.I
'238
'911>
I Tolrn um
- 3.
Vj)1 Comments kV
.'Fig::;.
661.6'keV "keV peak,...
keV
'13k
'Th +:.,- 2;.
.(92.7)
'. kCe eak> '
L:____ '
^peak
,T
.\\eV peak 40, ROC 511B20 0416 02.96I 110, -01.2704 Remed r
A2 ier
-iieiatiion' S
VR C siV
.1 rVI 0
Y62;-
36
- 0.
5 I
15 49t, AB2:ROOF C49 10 717+/-0.26i r NDt N-46 A +/- 0.16'.:
0.03§
-3.96'O.59t' 2:02'i
- 6; 4017 6'Oillt !R MA d
Adudhg"Aretithi i
503 AB2-ROOR-C 50F, 40'.71 0.12
~
'N-r "2.05 +/-0
'2.710.
.4.76 1 0O.64/
32.09 L182"..0.9+/-0.3v'eddu-ngAre2ridiitidW 55~ ~~~.'
C"~
x ~ '
0;2 A23<
i'
,,.,,- -'N
- r.
~~~~~~~~~~~i'i,
-Nl('
- 042;'°':sD-60 ND'~'B.".'. -_2'23 z >,-5 1 0.357,
.84'17; 2N ;6,056 4,,
i8807 61 B2-ROOF-C 61 10
'I 1
6,.9 N
.7
.5 2.7404 4.3 06 2.7 i 1.45~
0.20
']6d
.01 elwRelaertci 51 B2-ROOF-C 1
710" 0.1 0
ND 1.69 0.3 24
.5 4.1 l
.4D
(.25'
+0.60)
Re elow RlasCr6iteriat 52 B2-ROOF-C;2 2 10,
.290.14 ND
'961.540.16 12.54670.623 3.25
.4
- .849 0.85' 0.25
' O.lB-Remed dring` eas2'e itriao 65.
B2-ROOFC-3
- 10 0417+/- 0.10,. :tND 1.6720O.13 0.2 4
c2.396+/-0.45.. ~3.5940.69' 2.5001.3981 ND32O -
B ReleRemoveddurng
'Ar&2diiiediatidn' 54 112-ROOF54 4N051f0D12 kC.-"
4~(4.
4 4
'1.824.182 o.23!46'AL
~"
.'a
-M OF~._
41031:*.2 155+/-,.13
§2.22+/-0~
AS,
'3`77,*0.58%'~.82.
1
___1 I
$-h&e'ui'"fe2efeito 55-
'B2ROO1G55 10~
0.62 0.11 N.I
'il6s95.i 0.7.,
3.6O+/-~E0:4.
243+/-
0.76
.0.17k
.0.09,-.
,Removed dridA' ea2'remediati6W~
12 9
243 d
V'JAi 56~~
- B2 2
ROO~~tC56' 10'-,0A`84o'..09" tD "14+/-.1'
~.1.737+/--0.33
';)3.23+/-
0.44; 4--..1,.
3.24..
,0.2710.11 i~emove "dluring'Are~i2rcdaoh 4;7".
1 ~
~
~
~
~ ~ ~ ~
-'vv
-'4 4
br-css~~~~~~~0 3,.
I;.o1,+
N.
.50IQ724+/-04.,
.6166 2.209 0.24
-0 I0.12,.
-,,Removed durn AreA" fl-remn g
-~~~~~~~~~~~~~~~~~~~~~~
8
~
8'a Ar6i*'5diatio.
`434 6~179+/-01"
-.:;2 C'
16ib~
duQAr61 iTh~ici"dtidrf
'-6.
782--ROOF C5!, 60
- 01$
0.35 0.0`
D,
- .L 04"."42 05
- 1446.8
.2"01
-eoe uig-6
'382-'ROOF-i"C5~,
10 0.16+/-ik0.
I08',
ND 1?_~.69+/- 0.23 2.41
+/-3.5 4.1+/-074 N
(02+/-.1)Blw ees Cdei 64 B2-ROOF-2 10 0.21
+/-
008 ND 1.54 0.21 1.67+/-
.33 3.21
+/-
.54 0.39+/-0.5 (0.13+/-0.0)8Below0Relase7Criteri 65 B2-ROOF-3C6 10 0.17
+/-
0.109 ND 1.20 I
0.24 2.39
+/-- 0.45 3.59
+/-- 0.69 2.00
+/-
1.98 ND0+.1 Below Release Criteria T-13
(i-177 rC-r--
[2 V-F-
( 7
(.-
V 1 -
(--
I -
lTable 5: Gamma:Sp'ectroscopyRe'sut of Buigldi
'g2 R' '
am es :.
K "
Radiouclie Conentriion~f (6tiVg
_________A__eun L ; : :: ; adio-Results o c t
Backg 2r ound ot ubtracte 30 Minute o
s (Uness Othei Nt ed)
- 'o~~o - 2z~~i 2 3 2 h
235tl SampcID
- Fig
. 661.6-
-1173; 238 911$ -
Thorium 63.3 (144) 186 Comments 22 ke '
Vpe~
eV
',Vpeak
-;eV peak 22Th :2 (92.7)k keVpeak ea1k 2 Th keV peak 66 B2-ROOF-4 10 0.77 0.06 ND 1.56 +/- 0.30 2.11 +/- 0.36 3.67 +/- 0.66 0.79 +/- 1.03 (0.19 +/-0.08)
Below Release Criteria 67 B2-ROOF-5 10 ND ND 1.58 +/- 0.33 1.62+/-0.38 3.21 +/-0.71 ND (0.16 +/-0.09)
Below Release Critcria 68 B2-ROOF-6 10 0.15 +/- 0.06 ND 1.61 +/- 0.32 1.69 + 0.36 3.30 +/- 0.68 1.38 +/- 1.24 (0.22 +/-0.06)
Below Release Criteria 69 B2-ROOF-7 10 0.21 +/- 0.09 ND 1.49 +/- 0.21 1.95 +/- 0.41 3.44 +/- 0.62 ND (0.23 +/-0.11)
Below Release Criteria 70 B2-ROOF-8 10 0.16+0.07 ND 1.34+/-0.18 1.87 +/- 0.37 3.21 +/-0.55 ND (0.11 I0.06)
Below Release Criteria 71 B2-ROOF-9 10 ND ND 2.21 +/-0.33 2.30+/-0.44 4.51 +/-0.77 ND (0.24+/-0.11)
Below Release Criteria 72 B2-ROOF-10 10 0.09 +/- 0.04 ND 1.36 +/- 0.20 1.91 +/- 0.38 3.27+/-0.58 ND (0.21 +0.09)
Below Release Criteria 73 B2-ROOF-Il 10 ND ND 1.83 +/- 0.30 1.80 +/- 0.49 3.63 +/- 0.79 ND (0.15 +/-0.09)
Below Release Criteria 74 B2-ROOF-12 10 0.51 +/- 0.10 ND 1.64 +/- 0.22 1.78 +/- 0.36 3.42 +/- 0.58 1.74 +/- 1.40 (0.13 +/-0.06)
Below Release Criteria 75 B2-ROOF-13 10 0.15 +/- 0.07 ND 1.82 +/- 0.25 2.35 +/- 0.42 4.17 +/- 0.67 0.95 +/- 1.08 (0.14 +/- 0.09 Below Release Criteria 76 B2-ROOF-14 10 ND ND 0.32 4 0.10 ND 0.32+/-0.10 ND (0.05+/-0.09)
Below Release Criteria 77 B2-ROOF-15 10 ND ND 0.30 +/- 0.15 1.20 +/- 0.48 1.50 +/- 0.63 ND ND Below Release Criteria 78 B2-ROOF-16 10 ND ND 0.97 + 0.19 1.02 + 0.27 1.99 +/- 0.46 ND (0.06+/-0.05)
Below Release Criteria 79 B2-ROOF-17 10 ND ND 0.62 +/- 0.16 1.46 +/- 0.41 2.09 +/- 0.57 ND ND Below Release Criteria 80 B2-ROOF-18 10 ND ND 0.28 +/- 0.09 ND 0.28 +/- 0.09 ND ND Below Release Criteria 81 B2-ROOF-19 10 ND ND 0.57 +/- 0.23 1.07 +/- 0.31 1.64 +/- 0.54 ND ND Below Release Criteria 82 B2-ROOF-20 10 ND ND 0.31 +/- 0.09 ND 0.31 +/- 0.09 ND ND Below Release Criteria 83 B2-ROOF-21 10 ND ND 0.47 +/- 0.19 1.38 +/- 0.47 1.85 +/- 0.66 ND ND Below Release Criteria T-14
F -
I-r-_I7
( i r" 7 F - - ~ -~
IF---.,
I-(_ -
C.-.
1, __
( --
I ___
(.- -
F-Table 5:
G~~am m a Spectroscopy Results oof a mp es.
.q i:
i Rai cI'de C rcnrtion (OC'/g~ -Results h 2 0: Bac kgroiiiids iot'Sibtract~d_ 30M n t unts (U niless Othrwisb Noted
' C S "C
23 2.T ta 5s~
i5 s~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ThvzRo' U
Sample ID Fig 66i.6 1173 238 911 Thorium
~~~ ~ ~ ~ ~~63.3 (144) 186
,C om m ents
'-Sampl e ID,-.
- 38 6 6
.17,
- 7 ke V peak-"',
keV pe k i
. keV pe k hT
~ 4 (9 2. )k V p a L : t-;; -: -: : ' - \\ - o -
pea k 232Th keV peak 84 B2-ROOF-22 10 ND ND 0.43 + 0.10 ND 0.43 4 0.10 0.23 + 0.40 (0.04 +/-0.05)
Below Release Criteria 85 B2-ROOF-23 10 0.21 + 0.12 ND 1.63 + 0.23 1.93 4 0.40 3.56 + 0.62 ND (0.13 0.10)
Below Release Criteria 86 B2-ROOF-24 10 0.12 + 0.06 ND 1.42 + 0.23 2.17 + 0.41 3.59 + 0.65 ND (0.11 +/-0.10)
Below Release Criteria 87 3B2-ROOF-25 10 0.16 +/- 0.07 ND 1.35 + 0.22 2.16 + 0.40 3.51 + 0.62 ND (0.24 0.11)
Below Release Criteria 88 B2 -ROOF-26 10 0.19 + 0.04 ND 1.90 I 0.27 2.20 + 0.29 4.10 + 0.56 2.57 + 1.50 0.38 + 0.23 Below Release Criteria (2hr) 89 B2-ROOF-27 10 0.28 + 0.05 ND 1.76 + 0.28 2.29 + 0.27 4.05 + 0.55 1.95 + 1.23 0.15 + 0.16 Below Release Criteria (2hr)
- 90.
jB2ROOF 28
]'J 10 1.03 4 0: 14 N.
7 5.':0.3 3
- 2. 144O
+0.k w3.90 0.73
!2'07'.1'69
(
`4+?ii oir A
A.
A' e:
.Y;.
, 4 2
d ff 91k B2-R O OF-29\\ <
10 1:,31 0 18',
L N D 1
OL7-21
'2
,04 4AO 45.r
>331+066 N D
( 1 R m dA4-t 4
A>
- ,* X t s
. l t.
,A
.A.
m
.A*.
_*.~.4.'.Z 0 8 3
92
,,,sB2.ROQF030 W'1' i;'0 4
,3 21; 79+0.24 2--2 04 393+
4
' t SB2-R O OwF-31 10 ; <S1 52
.0'20 9
N D 1.79-025 2.07+
0.47 5'38
+0.72 9O; 92
--IO A
O R e 4r d d ri i g A r a 4 r e m e ~ t o
'31'
'20'L TJ O,
F.,.: 2'.07 Ad'.
A,'I-46 (0.0
'..Rem A l
94 1f,';B2-ROO F32 10 148+n018 N D
':3+021 2.08+-0.42
. :341+0.63 5iND R
ed i
er 95 B2-ROOF-33 10 1.11
+0.15 ND 1.66+40.37 2.02
+ 0.39 3.68
+ 0.76 ND (0.26
+
Below Release Crntena 0.1 1 )
96 B2-ROOF-34 10 0.17 + 0.09 ND 1.75 + 0.44 2.05 + 0.41 3.80 + 0.85 1.13 + 1.29 ND Below Release Critera T-15
r---
r--
r-- r --
. t--
I---I r 1 i-.
r
- c t
c-1 I
l T abl e Ga Spectroscopy Reiuls o uidig 2 f S iaples G'-
A.-.;-,:Radionuclide Cohcent tion not acted 30.
Con "Coi fiT
'Th
T ta l '
6 iSmple ID fl Fig 661.6 1173 238 911 Tu
- 6.
(144) 186 l
Comments V peak' 5
, key I
keY peak'" keY peak Tli+
(92.7) ke pek peak^
2Th keY peak 97 B2-ROOF-35 10 0.09 0.05 ND 1.46 + 0.20 1.87 4 0.45 3.33 +/- 0.65 ND (0.14 0.10)
Below Release Criteria 98 B2-ROOF-36 10 0.12 0.04 ND 1.54 0.19 1.84 + 0.24 3.38 +/- 0.43 0.85 + 0.58 0.14 +/- 0.14 Below Release Critena (2hr) 99 B2-ROOF-37 10 0.17 +/- 0.04 0.04 +/-
1.53 +/- 0.19 2.07 +/- 0.29 3.60 +/- 0.48 1.52 +/- 1.02 0.14 +/- 0.19 Below Release Criteria (2hr) 0.04 10 B2-ROOF-38 10 0.11 0.06 ND 1.75 0.24 2.12 + 0.44 3.87 +/- 0.68 1.43 1.36 (0.15 +/-0.10)
Below Release Criteria 0
10 B2-ROOF-39 10 0.19 +/- 0.17 ND 1.77 0.37 2.25 +/- 0.45 4.02 + 0.82 ND (0.21 +/-0.15)
Below Release Criteria I
10 B2-ROOF-40 10 0.14 +/- 0.09 ND 1.37 +/- 0.23 1.90 +/- 0.42 3.27 + 0.65 ND ND Below Release Criteria 2
10 B2-ROOF-41 10 0.31 +/- 0.10 ND 1.78 +/- 0.25 2.25 +/- 0.45 4.03 +/- 0.69 0.82 I 1.28 (0.11 +/-0.09)
Below Release Criteria 3
i-oi 2 a'F4 f;^1f'M'fli-4o'>s*r 30i
.- g 6-V;B2-Roo-43zX ts :^! 40.95'i0.96.I"
@3'~62 5
0 23 0 04& 4 ;14 0.73 iS10 6
2D
'25 0
421+/-073.
NDRein z'
06 2v.23 4W.ci o-D
)b]742-~,-O~
i O';!
?-I-;68':EO'.2f~,
8 NW-f, ~VJ.LU+/-0.10)
Rmvedrui~e 0
iO
^
1, 34 i
. tt t _,~
...... 31""n..,..
4 i
X 0 1 zr 0
t 0
D0037;3.4 20 4
t:
5 47,t
.9 9'.
V,,s 4;
't.,('>,s.-Ž. s.'
'.49'
,hP-,5t.' S O
I-',
.4.10.7."
- n 10 B2-ROOF-46 10 ND ND 1.80 0.39 2.32 I 0.51 4.12 0.90 ND (0.10 10.08)
Below Release Criteria T-16
V~-
F~
UI~'
r vU r7F-F-i V,
r-u T v'
r7
[*
r i.-
v-.
('-
Table :
Gam a Spetroscpy~esilts f Buii "I2 Roo SamiplesONtd
,Radionu'clid Concenntrioh (pC Reuls a
nd o
-30 Count (ns Otheiwis o
-t
- 7CS, 2
- - -f ;..
35U.
01,
-Th-
~~~~Total Sa'mpile D,,
Fig K ':'661.6.-
173 :.
238 911' 3.,.ThoriI m
633
.'(144) 186 Comments keVpeae vpea keVpeak~'-.
h927 keN peak'
',peak 2-Th keV peak 10 B2-ROOF-47 01 0.05 + 0.07 ND 1.79 + 0.28 2.42 + 0.44 4.22 + 0.72 0.43 + 1.27 (0.26 +/-0.14)
Below Release Criteria 9
11 B2-ROOF-48 10 ND ND 1.37 +/- 0.22 2.19 I 0.41 3.56 +/- 0.63 ND ND Bclow Release Criteria 0
11 B2-ROOF149 10 0.07 + 0.09 ND 1.75 +/- 0.24 2.34 + 0.48 4.09 +/- 0.73 ND (0.13 +/-0.08)
Below Release Criteria I
11 B2-ROOF-50 10 ND ND 1.66 +/- 0.34 2.23 +/- 0.45 3.88 + 0.79 ND (0.14 +/-0.09)
Below Release Criteria 2
11 B2-ROOF-51 10 0.04 +/- 0.06 ND 1.40 + 0.25 2.06 +/- 0.44 2.45 + 0.69 0.74 +/- 1.24 (0.18 +/-0.08)
Below Release Criteria 3
11 B2-ROOF-52 10 ND ND 1.59+/- 0.33 1.96 0.38 3.55 +/- 0.72 ND (0.14 +/-0.07)
Below Release Criteria 4
11 B2-ROOF-53 01 0.05 +/-0.03 ND 1.76 +/- 0.38 2.35 +/-0.46 4.10 +/- 0.84 ND (0.1 1 0.13)
Below Release Criteria 5
11'
">,,B2. OOf 54.-'
10 2.10.25.
N,
- 1.
£ 0.25,- 2.44 +/-0 49, a4.254 O.74 ND
- 2) ddungAa'4'e 10 14< '
ND-B2'RO'O~i5 150+/-025 2.13 +/-
43-0.7'.
ND 00 0;25 9)2.13 0.Remvdunga emediaim
~~~~E 025 2"
1 3
3.' ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~V'.d'"A
-4
~~~~~~a
7
'aa
.'4.
j'
>,t
""',. a.t'
~
a.5;'
r a,",
11
- 'B-~~
ROOF756'::"
IO,
.941+/-8'. N"'
1304-
,.603 31+/-
,2 06+/-15 (0.23+11) emoveddurng irea4'remedtir~
- 8
'a.'
!5>g ;F
?^;,, ;=tisC;
,=,,
- ,'A
?'11:i"'2 aB2:ROOF:57
'a 10
. 45J'O. 19.
N2'4O2+/-027.
2:
96 8
(
0 Ri eddunng rea remediaiom.
.9
,,wgi, iS t.a.
g,-............
t"'
T-17
r---
r--- r-r-
[-- r -- -
-7 Ra r-' -
w r ---
r-r ----
r ----
n r ---
r:-
c F
r"---
I Table'5:' Gam'ma
':Spe't'o
p',R's'i o
ding 2 Ro f Sanpl
,A Radionuc~id~
Conbenratbi (pig eut 6-Bcgrounds not! Subtr~dctd - 30 Mhifitc Colinis (Unlss OthierwisdNoted)'
joigci6Cof-dtr 6
(pi..
R§t 6
- Bc
'"7 0co'T
.. t.:,,>~h Total
- ,,'U.'
To,
-SamplelD g
66 1
11173
-238<
4K 91 Ti 63.3 Co ments U keV~~xik
' keV keV p~ak' keV peak
"'Th 4~""
(92.7) keV peak
^.
. :. : ::> :.peak 232Th keV peak 12'..
B2-ROOPF58 ci 10~
1 98+/-0.24.
-`ND`i2O.
3 6
1 50+/- 141 (02 +/-0 OJ Remove ringAa rmiatibND
'4 A
t 4~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-
- 0.,ir,;,;,
V 2
.8,...
i i
'4' 4
_k6O'4 4 t;.ro;
`
>(r I
I A
.2 4..066.
rm
-2~~~~~~~~~~~~~~~~~~~~~~~~4 (P""'
', j4-t.=i ;4A k<~
'"4
.4 4.'
12e j< i2.ROOF 6i9. "10' W1.8540':j;"
- ND 61 7+/-0.20 52.23 293 3.?t3066 0N (5+/-9 Removd'durig-rea3 remediatio
., 5.
>...; - i. 4 s e X
- g -xs-.
ip, H.;;
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ '.'..'
..4 12< ^~ - -2:RiOOFO 4
'vw i
" 0°4+/-012 "W
-iK
~.20.0
.6 9'f 8-~
l063 9
N (0-16+0.07)
Remove, u,gA3 rmedion 4'. \\-x,'~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-~~~~~~~~~~'
'44."AZ 4 3 4
'~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~'r~~~~~~~~~~~~~~'"-
.~~~~~~~~~~~~~~~~~~~~~~~~~~~.
m v
r 612" R
F
&~2.95+/-031
- VAND, 1i69+/-037Ž;
3 g
- ,
- 1.974.05 3.65+/-0 244 9' _
i..
.W Remdk'e'ddringtArea 3` reii'ition;
- 7.
^
4
. ^
, i..
- .q-12>
- B2-ROOF-662^
s 10 185+/-0i1:<720 aND 146+/-020 8:1.57+/-0.2930 92 10+/-150 (0.1l4+/-006~
Removeddunng4ea3remeiatibn
-4.~~~~~~~~~~~~~~~~~~44 8' A a
' Z.
Z
4 4
-7)-
.4
.4 12 B2-ROOF:63.
10'1060 1 6 ND 4--31+/-021 2.53- 0A6"'3.4t+/-07 N
- 2.
4 021301)
R0 edd nn remed ation
'3.
14 2'R
V6 "
- 7' i
.' '4\\;
00....
4 4'Yt-6 9
0 a2
< '^-,-
4 4
"'..8 12.1 200 72
' N3101 ii 5
.30$ 2.8049 65+/- 162 (01410m.2vdungArea3 ;
- 12. "B2R00E67:c<
10~.,' 224f-D 1.350 190- 1932 +/- 6.278 2.67 +/-0-46!
ND
-I (02 9010 Removed during Area 3rmediation' Z.
I i
k I~~~*4.4C w
- 13 82.ROOTC6S"
~~~iO'6+/-.0 a'NVt; 903 11032-36+/-5,'8+/-4 0509 oveddunng'Area-3 remedihtibh'
- 4T 4
T-18
r--
r--
r-r--
r -
r-r-
' -r-v-
r:
C-fl V-
.r
(
r
[Table': Gammapec ospy su i
g Roof 1iu~
./
it.,
-- l..K) 2 ~~~~Raifi6id'oncenratifie 4rn pgY9 euls 2aBckgrounfs not SuG 6Couins (U ess'te'rw~ise Noted) 17.~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~.
.~~~~~~~~~5.
'.Rdould r
- <- x -; r
~.7 0C
.3/41,"- 2 'mi.
232' Th-Y:.
w:
T '4' t
SamplelD Fig D-,66-6
.-, a 1173 238'W-9`.
- Thbrii.:.
63.3..
(144)186 Comments kVpeak:
ke e
peak peak i'
(92.7).
pek ;pT-keV peak 13
';.<. B2-ROOF-69~
10 1 190'I5*'
A16+034 i697A
- 034
-3683+06 1
16 014+007)
Rerovcddurin reme ro^imiicdiation,
4 C
~~~~~~~~~~~~~~~~~~~~-69~;
13:
- 0,B2-ROOF70
'101 -i0s620.
'0.14 i7055 2
°:,
i';17+043k 3<9649 N
ND)"
Re ii 0;a3' remediation:.:
t3^>.B2-ROOF.-71>'.
i10 1~ 1.82+ 04-ND (185+041 281 064 466+105 D
(0i24 +01 2)
Reiiied duning Area4rmedio n 13'
- 2>B2-ROOF; 4 t2K;
'10"- i-234.02Y" ND i700 0 59*041"" 329+
n 4
V4-'
+74~~~~~~~~~~~~~~~~-4,0~-.
.,6l E W i - W. t~~~~~~f.9
.B'} rc
'x^
- ~- i, w-
-i
,,M~
0 0 F7 3
?i 1
'~~`~,4'.0,`h P4E
.24';
,'.`2
'1/444 0
4j 4M475*.--
'-~
l~4~
4 t
13'1 D
03604"B2-OOF473 -r 1 A 01 +048 Jr 7eion 4
ri V
r 30 4,4..
i0....."....,
B"' '82-ROOF 74 10 323'032' ND 161+022 ~~~~~~~~~~1.55'
.03 3L-116+V0520444+
(2+16'"RmoveddunnAred4iemediation 2 RO OF
- sI iA 0'wv.'2 Re'
- d. d
'W "4~~~~~~~~~~~~~4 X
-r
--wr rv ou, a
4
,,rj..
,' 4e it
,e3¢....'V 50'25 374 2..4 0i6 4+/-28 0
13s
' >-B2-R0F75 s10.
'IS272+029 62-'N 175+30' O.9+4 364+7 ND D
R2.o2iin 'Aa3 reedato.+
X
- i.
i 4.4<4,r
'V.
.i:'.;tz S.,X rz-titoZ'
_. r; 5
2-. B2 ROOFr7fi,,i0-
.%14,8,3y1--.Dx 142+ 03 83 iO;
'34'" "'29064 1191 23; (008 08)
Rmv dung Area -remeiation-'
8
'~~~~~~'
" 'I'
".4
- c;J44.A~~~~~~~~~~~~~~~~'7-fiditin 13 rSi-4B2RO 77O 9
tlO 1876+41D62 N
16026 27 0
362;077 N
(
R:moeddnngrea 3e eeiai 8
-24" 414.
a '.
.2'
'65
.t
,2.a. ;..
4.A 3
m 14"' t82-R00F79 ~~~~~~510.. 063+~008 ND 75+0O27,.,
41.87+/-_~0.28:361+055 186+
18' (02+006)
Reovd dudingeArte'a4:r'reii-e'diatio"n'."
A"9 rt,;.-.4 T-19
rF r-r-- r-r-:
r-r-
r' r-r r--- 1
-?
(C r-I
,,am m
A;.'.',
":nuii'Cocn 4
u-B c T. ble
-janom
... Sam. l 1
^
Radionuicid Concentration (pOig) Results +'2o - akrddwo SubfractedŽ ;3'0 Mhiutet Counts'(Unless Otherwise Noted) t:.'
.,^..
- r.,,.
,t;':;.~'......
s
, e.peaV-
..lu.
f SamlDa
-Fig" 3
23 9
- 9.
h oriumi.
(144) 186..
Comments 3~~~~A ID
&4,l-1
- "';s,;
peakikeV ke pikek' 2l RT (92 -27) ke pea
'-4;
.1
. 4"* i iX
>X s ; <.
V t
.a.
B
/2-ROOF 81 10
.0595V 4tb1 ND 78o34
.1+o3:,3.8068 06+02(0138+0.08). -,Removed'duning Area 4retnediationn 4..',
~
~
~
~
V 14 )132-ROOF-82
-~~:10-1` 95+02 4
~D 181 3
0.5 2.1 0'.34:
-4138
- ,3 ~ ~
~
~
,.r
'~
- ~*
08*i813(2+0)--Rmvdun~e~eeita 4 ~~~~AX~~
Notes:
- 1. ND means not detected.
- 2.
Average Minimum Detectable Activities (MDAs):
U-238 = 1.37 pCi/g (63 keV peak)
U-235 = 0.12 pCi/g (186 keV peak)
Cs-137= 0.10 pCi/g (662 keV peak)
- 3.
Shaded data is for areas removed during remediation.
Co-60 = 0.13 pCi/g (1173 keV peak)
Th-228 = 0.17 pCi/g (238 keV peak)
Th-232 = 0.38 pCi/g (911 keV peak)
T-20
Table 6: Wipe Survey Results for the Building 2 Metal Roofin Remediated Areas
-Wipe No.
Gross a in Gross 3 in
'Wipe No.
-Gross a in -
Gross' p in
.:_'_'_._._'_' dpi/f 100'cm2 dpm/100 cm2 dpmi/iO0cm2 jdpm/lO cm2 Level C Remediaton Area 1 (Figure 17) 1
<20
<20 6
<20
<20 2
<20
<20 7
<20
<20 3
<20
<20 8
<20
<20 4
<20
<20 9
<20
<20 5
<20
<20 Level C Remediation Area 2 (Figure 21) 1
<20
<20 6
<20
<20 2
<20
<20 7
<20
<20 3
<20
<20 8
<20
<20 4
<20
<20 9
<20
<20 5
<20
<20 10
<20
<20 Level C Remediation Area 3 (Figure 25) 1
<20
<20 8
<20
<20 2
<20
<20 9
<20
<20 3
<20
<20 10
<20
<20 4
<20
<20 11
<20
<20 5
<20
<20 12
<20
<20 6
<20
<20 13
<20
<20 7
<20
<20 T-21
Figure 1: GA's Main Site and Sorrento Valley Site Building Numbers Names 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 t
Building 27 Building 29 Building 29-2 Building 30 Building 31 Building 31-2 Building 33 Building 33-1 L
Building 33-5 Building 34 Building 34-1 Building 34-2 Building 34-3 Building 35 Building 35-1 Building 36 Building 37 Building 341 Building 42 Building 45 L
Building 63 Building 64 Building 65 Building 66 Building 66 Administration Science Laboratories A, B, C Cafeteria Office/Lab Building Office Building/Health Physics Technical Office Building Technical Office East Technical Office East Swimming Pool Building TRIGA Building Inertial Fusion Development Building Former Hot Cell Site Former Liquid Waste Processing Building Space Power Building Office Building Landscapers Building Officellab Building (Former LINAC Complex)
Storage/Nuclear Calibration Lab Building ICF Lab Building ICF Office Building Painters Building Fusion DIII-D Building Fusion DIII-D Capacitor Building Fusion DIII-D Lab Building Fusion DIII-D Storage Building Test Tower Building Facilities (& Shipping & Receiving)
Experimental Building Sorrento Valley Building A d
Storage Building Laboratory Building (OA)
Machine Shop
/
3550 Dunhill St.
/
11030 Roselle St.
/
/
of S 11040 Roselle St.
/ /
3520 Dunhill St.
/
/
3510 Dunhill St..4
/0 /
31 N
A W4ej~ E S
SITE OPEN SPACE SITE 0) 0.W
'UJ rat 0
-I-0E LOTS UCSD
- FENCING
~ PROPERTY LINE 0
250 500 750 1000 SCALE IN FEET 10/24/03
Figure 2: Building 2 in Relationship to Surrounding Area General Atomics Torrey Pines (Main) Site Figure 2
C-,
.. W- ---
-=MO-fm.
0)
- 5 m
a) 5 C
w 0
CO, 0
0 U-tm r._
-S N
N%
(4:I I
I I
I I
I
/
-cn E
- 30 C.
/
/
z4 3¶F us ci,
/
//
/
/
/
.I.
S.
Figure 3
Figure 4: Building 2 Roof Level A Exposure Rate Fixed Measurement Locations and Results S
Y Notes:
- 1. # Denotes fixed exposure rate measurement taken at-1 meter above the surface.
- 2. All readings are In iilRhr. Results range from 7 to 11 pxR/hr.
Survey Conducted by: W. Schuck and R Stowell Date: 05-09-01 Figure 4
Figure 5: Building 2 Roof Level A Exposure Rate Scan Locations and Results and Sample Locations 5
w E 0 NN I
Column #s Roof Levels B30
- inner, Inner wall
--922 ft C55 C70 t
S A# Denotes approximate sample location (B2 Roof A #).
- 2. Roof sample results are provided In Table S.
- 3. U =`-
Denotes area, 2 meters wide, where surface was scanned using 2" X 2' Nal detectors.
- 4.
- #0 -
Denotes surface scan range in pR/hr.
- 5. Results range from 6 to 15 1jR/hr.
Instruments
-Model e
3.3 3
.Sedal g 153311 147t819
'Cal Due Date 06-12-01 07-0441
'.Effidency, NA NA
.. Probe; 2
Nal Y X2 Nal Y Probe SerU 155594 153765
.1ackgrounmd 8-9 IIRA 7-9 pRfir Surveys Conducted by: B. Hunter. W. Schuck and R. Stowell Dates: 05-02-01 to 05-09-01 Figure 5
Figure 6: Building 2 Roof Level B Exposure Rate Fixed Measurement Locations and Results E
rA25 Column #s B.
A C
-24
-275 Roof Levels D
/24 _
Drawing Not to Scale B50 C51
.Y
- 75 C9
't 7
C70 I 0
~.Wc~l A5 Drawing Not to Scale
- ~~~~~~~~~~~~~~-- - - - -Vl
-~~~1094 ft I;nstrument j~S~al~jfJ87120 NoWs:
- 1. All readings are In pR/hr
- 2. ## Denotes exposure rate fixed measurement taken at - 1 meter above the surface.
Results range from 7 to 11 jpR/hr.
Survey Conducted by: R. Stowell & W Schuck Date: 05-09-01 Figure 6
Figure 7: Building 2 Roof Level B Exposure Rate and Ventilation Scan Locations and Results and Sample Locations
- 1.
- B# Denotes approximate sample location (B2 Roof B#)
- 2. Sample results are provided In Table 4.
3 E
Denotes area, - 2 meter wide, where the surface was scanned using 2-X 2-Nal detectors.
- 4.
- _;, Denotes surface scan range In pRthr.
- 5. Results range from 8 to 14 pR/hr.
- 6.
FM Denotes area where the surface was scanned using a 15 cm2 G-M detector In the vicinity of ventillation exhausts. Results range from 40 to 80 cpm (metal), background = 20 to 80 cpm. and 40 to 120 cpm (roofing), background 60 to 120 cpm. Areas scanned along the roof edge are near discharges of vents from level C.
. Modell Ludlurn 3 Ludlum 3 Ludlum 3 Ludwum 3
'sertai t 153551 147819 139180 138880 Cal Due Date 07404-01 07.04-01 09-10.01 03-11.04 4*Efficecy.
NA NA 21.05%
26.14%
Probe',
2X Nat 7 2XT Nat 15 cm, p-15 emr
? 7 Probe Ser$
155109 153765 145973 117851
- lackground 9-10 iRft 7-9 pRhr 20-0 cpm metal 60-120 epm roof Surveys Conducted By: R. Stowell, B. Hunter, W. Schuck & D. Koelker Dates: 05.02-01 to 05-10-01 & 10-02-03 Figure 7
Figure 8A: Building 2 Roof Level C Exposure Rate Fixed Measurement Locations and Results Column Ns Roof Levels B
A20 Inner Wall A5 A2
\\
C1
.- V, Outer I c70
-- -1094fl Outer Edge Drawing Not to Scale use_
- 1. ## Denotes fixed exposure rate measurement taken at - 1 meter above the surface.
- 2. All readings are In VRIhr.
- 3. Results range from 6 to 13 pR/hr.
7,<r.~~<r.<
47t If 1,lnt ents
.i^}.t
-Model Ludlum 19 Ludlum 3 Ludlum 3 Ludlum 3 Serial 87120 153311 147819 153551 Cal Due Date 07-04-01 12-07-01 12-07-01 07-09-02 7 iProbe.*
NA 2x NalI 2x Nal 2x2 Nal
.Probe Ser.#
NA 155594 153765 155109
.Background
12-18 pR/hr 7-9 § r
8-10 pRlhr 9-11 W;Ubr Surveys Conducted by: R. Stowell, W. Schuck, B. Hunter & S.Cowan Dates: 05-9-01,12-01-01 & 04-23-02 Figure 8A
Figure 8B: Building 2 Roof Level C Exposure Rate Fixed Measurement Locations and Results Roof Levels B
B30 7 A20 Inner Wall 015
\\ A10 C70 Outer Edge Drawing Not to Scale NotesL
- 1. ## Denotes fixed exposure rate measurement taken at -1 meter above the surface.
- 2. All readings are hI pR/hr.
- 3. Results range from 6 to 14 pR/tr.
2.' ifIMnsktument. -
Model l
Ludlum 3 Serial #1 Cal Due Date 11-17-03 Probe 2x2Nal Probe #
155109 Backround 9-11 pR/hr Surveyed Conducted by: R. Stowell & W. Shuck Date: 09-10-03 Figure 8B
Figure 9: Building 2 Roof Level C Exposure Rate and Ventilation Scan Locations and Results 40.80 metal s
i 810-100 roofing 27.4 It
- .Column
- s
- A25
~~~~~~~~~~~~~~~~Colurnn#s Roof Levels 83 10-16 l 85 i-
<<1-40' 60-120rooling 9
A..
4 -:.
F Z Mo Ludhm 3 Ludhm e
Ludl 3 Luum 40-60 metal 812 k~~~~xf20a
-4
.-:::eurdg
- .-.\\**w
- :> t:
- 0 7-12
, s~kjrr~und s-to prmr 7-9 pR/hr 20 SO 60-t20 cpm Or s 1 o B4^
543
>r\\oing o
4040 metal 835 80-100 roofing ao~~~~~~~~~~~~~~~~~~~~~~~~8-10 oofiog Inner Wall ~~~~~~~~~~~~~~--24' nerWl
'Metr Luiffum 3 Lutttufl3 Ludlum 3 Ludlum 3 LudiumO 3 0-meta
________ 1
~~~~~~~~~20.100 MOofn 207 pf tfisrla 153551 1481 139180 138880 153590 80 rmediation
______..8.
0-2
~~~~~~
~~~~~~~~Probe 2Xr al 7 2rxrNat 7 1 cm 40-8O2XthNt AIO ~
Prbe Ser,
155109 153785 145973 117851 155190 N..
- ~~~~~~~~~~Efficiency NA NA 21.05%
261%NA 712 Sakrwd 9-10.Thtr 7-9 pRIY 20.80 epm metat 60-120epm mof 9-l0,pRf 8
5-3 406 e&-40-60mea 40-150 metal 4
..~~~~~~~!.
A.
AS ~~~~~~~~
40o80 etat 80100 roofing 8-11
~~~~~~~~~~40-80 roofirng 40-60 metel f~
A2 4-60 metat krtftialev 60s4 roug 5
m.-.
1 40-80 roofing 40-6 metal 17tRlr 40-B0roolat 1
r C5 0lorott remedletlo 44 ea Outer Edge
(.
20-80 r~ocfing 8.2
- ~~~-*-*~~~~*- 3 ~~~~
C63 C60
~~~~~Outer Edge 512 4)~~~~~~C3
-1 Drawing.c.:~1~'
~~~~~~~~~~~~~~Ntt cl
- 1.
-- X.XX -*
Denotes scan range In p+/-lhr.
- 2.
I:-
Denotes area where 100% of the surface was scanned using a 2" X 2' Nal detector. Results range from 5 to 17 iR/hr.
Surveys Conducted by: B.Hunter. R.Stowell, S.Cowan, S.Finchurn, W. Schuck & D. Koelker Dates: 05-02-01 to 10-02403
- 3.
Denotes area where 10 % of the surface was scanned using a 2' X 2" Nal detector. Results range from 5 to 16 1 Rhr.
- 4.
I Denotes area where the surface, in the vicinity of ventilation exhausts, was scanned using a 15 crn2 G-M detector. Results range from 40 to 80 cpm (metal), and 20-140 cpm (roofing).
- 5.
i i Denotes area of elevated pPx r readings found during initial scan survey.
Figure 9
Figure 10: Building 2 Roof Level C Sample Locations S
-4
'%- E I
I I*"'\\
- 1.
Sample results are provided in Table 5.
- 2.
0 C## Denotes locations of samples collected during the initial surveys In May. 2001
- i.
(i)
Denotes samples collected following the November 2001 remediations.
- 4. [-l Denotes areas remediated, see Figures 14.18.
22 and 26 for details.
- 5.
EM Denotes areas of new roofs, - 1.5 yrs old, that were not sampled.
Samples Collected by: B Hunter, W. Schuck & R Stowell Dates: 05-02-01 to 01-15-02 Figure 10
Figure 11: Building 2 Roof Level D Exposure Rate Fixed Measurement Locations and Results 0
W E
N
-24 ft Column #Ns
>A26 A25
'A20 Column #Ss \\
B29\\
B30 B
-40' 0
O RoofRLevelsoB Inne, Wan Wall s
9- -24*,J ~~~~~~~RofrotEdge Drawing,P Not to Scale Inner Wall Instrument 4 L Model, L udlurn N9 B41!
,-,Seral S 87120 N~lDue Date-07-04-01/
-Backgrund,:<
12-18pR/hr B
a 850 /
1 C51
,to 1o C55,<..2 1.
A5 Roof Edge Roof Edge Drawing Not to Scale
- 1265 ft Not;
- 1. ## Denotes fixed exposure rate measurement taken at - 1 meter above the surface.
Survey Conducted by: B. Hunter & R. Stowell Date: 05-08-01
- 2. All readings are In lRihr. Results range from 8 to 12 pR/hr.
Figure 1 1
Figure 12: Building 2 Roof Level D Exposure Rate Scan Locations and Results and Sample Locations
- c.
w E
N Column #s
/A20 Column #s
\\
B29 B30 B
A C
-24
_'2r g
~~~Roof Levels-2 Ra Eg Roof Edge Drawing Not to Scale Inner Wall jX.:
Inaftrnent Moderal.
Ludtn 3 Ludurm 3 kS~erial#
153551 147819 B4 Cal Due Dat.
07-04-0t 0740t-
.tEmncency2..
NA NA
'~ *prbe *.X:T2 Na y 2?X2Nal y ProbeSer#
155109 153765 1BackgroundI 9-iC Rftwr 7-9 p0r B50 hi C511 C55 d AS Roof Edge Roof Edge C70 C60 Drawing Not to Scale
- 1265 ft Notes:
- 1. *D## Denotes approximate sample location (B2 Roof *D ##).
Sample results are provided in Table 5.
- 2.
E::
Denotes area, - 2 meter wide, where the surface was scanned using 2-X 2" Nal detectors.
- 3. q-x-xx -l Denotes surface scan range In pjR/hr.
Results range from 8 to 17 pR/hr.
- 4. Sample D62 collected at the highest surface scan reading. 17 iR/hr.
Surveys Conducted by: R. Stowell & B. Hunter Dates: 05-02-01 to 05-31-01 Figure 12
IrI< r. -
(1 FI r7 7
(~ -.
f (7---
( 7 f --
IV T-(7-Figure 13: Building 2 Roof Level C Remediation Areas 1, 2, 3 & 4 Locations w
N.
E column fiq Oi Inner Wall Breezeway A Roof Levels column #s\\,
25 B
A t:~.:~
\\B3(
4- -24'
~
Drawing Not to Scale Notes:
- 1.
Denotes Areas (1, 2, 3 & 4) where the roof was remediated.
- 2. The bare metal was surveyed in the four remediation areas prior to replacing the roofing material. See Figures 14 through 30 for details.
- 3. Column #s are from the columns inside the service corridor.
B50
- - 1094 ft C63 Outer Edge Breezeway E C
CD Drawing '
Not to Scale
Y r~ iT (7 -
(_
(
77_
V7. f 1'
C V
r V --
I---
(
1'7 r
VI 1>
¶7 rT_
Figure 14: Building 2 Roof Level C Remediation Area 1 Sample Locations A-13 A-12 A-1I A-10 innPr tenil
__I..
- I C41 C0 Remediated -
Area roofing also removed here C46:'
C28.
........0.
... ~~~~~~~~~~~I
~~~~~~~~~I
. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~~~~~~~I I
I
~~~~~~.
C20 a 43
.1 -..
- 1.
.: S~~~C31 C4
~~~.
.'4.
.!t...5.0,.. gth..m~
....~~~~~~~~~~~~~~~~~~~.
..~ ~~~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~~~~~~~~~.
IIII I
ii I I I
ii II I I II I
ii I I I I I I I I IIii II
-27.4' I I I I II II II I I I I II II II I I III I I I I I I I I I
+
I I
-15.8.
=
roof edge Samples Collected by: B Hunter, W Schuck & R Stowell Dates: 05-02-01 to 05-29-01 Notes:
- 1. All samples collected prior to remediation, sample results are provided in Table 5.
- 2.
C Denotes sample number and approximate location.
c-n C5 aD
r-r-- -. --
I(-- r-- r-- It--
(- r--
r -
r-:- T-- 'I-l-
--- Or-(.
Fig ur 15 :
- 2IT, Roof L V --
r and S ca Figure 15: Building 2 Roof Level C Remediation Area I Exposure Rate Fixed Measurement and Scan A-13 Locations and Results A-12 A-11 A-10 ni III~~~~IIIUI d~
Remediated Area 100% Scan roofing also removed here 25% Scan 10 10 10
- 10 14 10 8.
n 7-1l r
0 10 10 10 10 10:
10 10
..1
- : : :.:::-I
-.1
- I 8 I
.................8 1 8-10
-o-l u
,7.. 8..
I -....... --.--
I I.:.!.......
9.4 16: K II
II I I I
'I I
II II I I II I
i
II II II
-27.4' I
'I I I
'I II II II II II I I II II II II I I II II II II
-15.8' I.....
9.
~~~.
. ~
~
^
S~~~~~~
I..10'. '. -
11, "
1 : :: ::
T
- I
-~ ~~~~........
roof edge ModelMode Ludlum 3
~.V~ria#.+/-,\\Y' 153590
,:,Ca Duei Dater 02-05.02 c
Ency.Inc,4`
NA Piob~3/42 2"X 2' Naly
'.~ ~Probe#i 155190___ __
Surveyed Conducted by: S Cowan Date: 11-11-01 Notes:
- 1. All readings are in pRlhr.
- 2. #-## Denotes surface scan Results range from 7-11 pR/hr.
- 2. ## Denotes Fixed measurement taken at - 1 meter above the surface. Results range from 8 to 14 pR/hr.
-n
-I CD Ml
) - r f--
rC r
, (_ _
(7-t-
r _
f -_
T.- I -
(-_
( ___ I I -
(r_
(Vi f7_
tF--
U?
Figure 16: Building 2 Roof Level C Remediation Area I Alpha and Beta Scan Locations and Re8ults A-13 A-12 A-11 A-10 innne ^/nil IIIII~~~~~~~~~~111I WdII 2
Remediated Area 100% Scan roofing also removed here 10% Scan 1000-130013 0-20 a 1000-1400,
0-20 a r
-~~~~~~~~~~~~
I 1
~~~
.I 10 0.1~0 I
........~ ~ ~ ~ ~ ~ ~ ~ ~~~~~~~~~~~~~~~~~~~~~~~~__________________________________________
..0..
1000 1..00 13..
4.
~~~~~~~~..'r
~
~
I
.I.
~
~
~
I
.~~~~~~~~~
I
~
~~~~I
.. ~~- -15.8' ~~~I Suvee Codce byI Dae 111
-0 Ii i
iII roof edge
_W......
Stowell
- '*'"7>'.
-7 aeInstrument
- bwr,
- A
-. *~ ~ ~ ~ rj ts*XL.
Model,,
'Ludlum 2221 Ludlum 2221 148425 84459
'lCa Due 12-03-01 01-10-02
,:K.^ Effcincy, f-*..
21.29%
23.62%
27't Prob~
e."4 434 cm2 a 434 CM2 p A, P iProbe-#
086236 086215 Backgrkbrid (
mial)'.7-26 cpm 1150-1290 cpm Notes:
- 1. All readings are in cpm, shown in ranges Alpha (#-## a ), Beta (###
3 )
Results range from 0-30 cpm Alpha and 1000-1400 cpm Beta.
2 100% of the surface scanned in the remediated area, 10% in the remaining uncovered area out to the roof edge..
-n C:
CD
I1.
F-~
f-7 F
r-r(i rT f
F
(--
F,-
v v- :
F-T
,--7 I-i~
1~T7.
C-F?-
Figure 17: Building 2 Roof Level C Remediation Area I Fixed Measurement Locations and Results A-13 and Wipe Locations A-12 A-1li A-1 I Wall
<20 a..'
.0
.482 3 442 13-Remediated Area roofing also removed here
-cN bc
<20 a
- 465 13
.i20 at CE I I I I 48813 I
I Ii I I
<2Oa If g
It I
it I I II 0
I'.
I I
j I
I I I I:A:.
II H>.:
27.4' H
II II
- 42613 I
I I
II II II II I
I I I I
I I
II I I I Ig II II I
ii I
II II I
Ii I
I II I
I I
I I
<2Oct I
I I
I, I
II II J. 'F
-15.8' Surveyed Conducted by: S. Cowan & R. Stowell Date 1111 01 roof edge
________________lnstruments; Q ~Mod~I~ Ludlum 2221 Ludium 12
.SraI#z 843138801
- c~ii 6D-bi~
010-205-11-02 Effcfi~d'>i~
24.43%
22.52%
P~~'~*
100 cm2 50 cm2 ci PrObe#,
i 119444 145696 Backgr'ound:,,
655+/- 70 cp2m 0-20 cpm MDA 249 dpm/IOO cm2 209 dpmnlO00c 2
Notes:
- 1. Q)Denotes wipe number and location. Wipe results are provided in Table 6.
- 2. 1I# a Denotes fixed alpha measurement in cpm. Maximum reading was <20 cpm,
<MDA ( 209 dpmll 00 CM 2).
- 3. ON~f 13 Denotes fixed beta measurement in cp2m. Maximum reading was 488 cp2m,
<MDA (249 dpm/100 CM 2).
C'1 C
CD
-.4
VF.
I r-fc--
17 r- --
(-.
1772 f7-FT-V. -
FT-, V7 FT (
V-I'-
VY-I r-T-r-- r--
Figure 18: Building 2 Roof Level C Remediation Area 2 Sample Locations C-58 C-57 C-56 C-55 innPr wnil 11111M W011
...,....1
....... 32 C26 C34
.- C50 0C33.
7 C49.
/ 5 ;
C47~~~~
b52 O~~~~~~~~~~~~~~~
048-c16.
27.4' I
I I
I
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ :
.....~
I I
~
~
I I1 I
I 12.1....
0 6 0 I I 1~~~.
W I I I :~~~~~~
..........~
~ ~ ~ ~~~~~~~~~~~1 I I
~ ~ ~ ~ ~ ~ ~
I g
1 7..
roof edge
-1 5.8 roofing removed Samples Collected by: B Hunter, W Schuck & R Stowell Dates: 05-02-01 to 05-31-01 Notes:
- 1. All samples collected prior to remediation, sample results are provided in Table 5.
C2a
- 2.
Denotes sample number and approximate location.
'1 C
CD Or,
V.7 r -.
I7-rY.-
I UT.
F7 F-(--
[
V _ _
[
r r_.
Iv-1- -
[
Figure 19: Building 2 Roof Level C Remediation Area 2 Exposure Rate Fixed Measurements and Scans C-58 C-57 C-56 C-55
- nneLr v^we11 i~~~~~~~~~~~111riiir wallr.
r I
7 4~~~~~~
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
- r..
l 1-1
- r.
I 1 6-8 a n q., -,
I I
a I
II.
7 -.
I:
- I.I ucv Remediated Area 100% scan A
. ^
. I f%
8-9
'I..,..
II I1.
I I
--4 nIl
-t IIII
I g
II I
II I
9 II I
IIt.L 8-9 V
. v I
.9 I.
7 I
I ~.
.7-9 7 0
' i9...
.. 9.a I I.
-274 1-0
..............\\
~~~~~~~~~..
o--
9:::::::: ::::::::::
- 4 s
9:::B:::::::: : : :::.:.:
9' I
¢:~~~~~~~~~~~~~~~~
1::::::::::::::::::::
1 1
l:.::
n:::.:
- .:..:::i 1
9 -9 1........
j
~~~~~~~~.
.89...
~~~~~~~~.
i,,..,
... 9,,..,
...., -n
- : !: ::1 7
I II..: :
'I I.
'I Ii
'3
- . ; :. ;.....-.-.-
m
4,.
---i:.:)4;
^4nstr-ument,:..r'>.^
e-..Modei..^.j 2
Ludlum3
.S.153590
_!:Cal Wuebate 02-05-02
_Eficency_____
NA
.. Pro'be'
".X 2" Nal y
-_Tnrobe__... _
155190
- t -.
- ;Bacgrou'nd 9-10 pRlhr cont 10-11 pR/hr @1m roofing removed 25% scan Notes:
roof edge 4 -__
-15.8' Surveyed Conducted by: S. Cowan Date: 11-11-01
- 1. All readings are in pR/hr.
- 2. #-## Denotes surface scan. Results range from 6-9 pR/hr.
- 2. ## Denotes Fixed measurement taken at - 1 meter above the surface. Results range from 7-9 pR/hr.
'1 O'.
C CD CD
F7-r--
C -
177..
r r:
(-
![7--,
f-(--.
r 7. -.
7r r -7 ( 7 frY-f rT(7 Figure 20: Building 2 Roof Level C Remediation Area 2 Alpha and Beta Scan Locations and Results C-58 C-57 C-56 C-55 inner wall Remediated Area 1000-1309 IB
. As
~~~~0-30a cl 1000-1309 1 0-40 d&...... : --
II1000-131 I1,000-~1300ji II
~~~ ~~~~~~.
..0O-.3.
3 60:~~~~~
bt,~
~ ~
1 vn, 366 B~~
~i 274.
'1 I;:..!
0-201 100.
I I ;
roofing removed roof edge
.4.-.-........-
-1 5.8' Instruments Model Ludlum 2221 Ludlum 2221 Serial #
148425 84459 Cal Due Date 12-03-01 01-10-02 Efficiency %
21.29 23.62 Probe 434 cm=2 434 CM2 Probe Ser.#
086236 086215 Background (metal) 7-26 cpm 1150-1290 cpm Surveyed conducted by: R Stowell Date: 11-11-01
- 1. All readings are in cpm, shown in ranges Alpha ( #-## a ), Beta ( #### #### p )
Results range from 0-40 cpm Alpha and 1000-1300 cpm Beta.
2 100% of the surface scanned in the remediated area, 10% in the remaining uncovered area out to the roof edge..
-n (B.
CD N,
C0
I r.
I777 7
1.
[U7 IF-,
r-C.-
f7,
V
? ---- r- -
(*T-(I-j.
F-~
f( -
C-:-
Figure 21: Building 2 Roof Level C Remediation Area 2 Fixed Measurement Locations and Results and Wipe Locations C-58 C-57 C-56 C-55 in.rwa
~~~~~~~~~~~~~~~~~~~~~~C5 Remediated Area
<20a
.414,B 4251,
.5.
<20 a dc '3911 4
,<21 j,......
365 I,
i,..
0C
<20 ao 4011
<20 a I.
II I.
373 1 :
(D.
. <20 a
'A I 11 II i i :
3821 pi P3 r7-
.(7-.
I r--.
< 20a-3963 394
-27.4' I..
-<20 "X.
i:
i:
ii II I
m
-7
- - -I roofina removed roof edge
-4.
-15.8'..
....... JAI..
Instruments :a xw
- Mo delt ^i,.Ludlum 2221 Ludlum 12
..2S'eralIs<7;.
84423 138801
- .'-Cal Due.Date,,.
01-08-02 05-11-02 Efficileni=y,'2-24.43%
22.52%
______________100 Cnrp 50cm 1`
'.V-Prbi t1 0c 5cm2 a
.'1'.,.
Prbbe#Kf' 119444 145696
'Bacground <>
655 +/- 70 cp2m 0-20 cpm
-MDA -..'-
249 dpm/100 cm2 209 dpm/100 cm2 Surveyed Conducted by: S. Cowan & R Stowell Date: 11-11-01 Nlotes:
- 1.
/2\\
Denotes wipe number and location. Wipe results are provided in Table 6.
- 2.
a Denotes fixed alpha measurement in cpm. Maximum reading was <20 cpm,
<MDA (209 dpm/100 cm2).
- 3. ### 1 Denotes fixed beta measurement in cp2m. Maximum reading was 426 cp2m,
<MDA (249 dpm/100 cm2).
-n co CD N)
- 1. -
C.. --
I--
F --
r -
- t..
- 1.
r..
(r -
Ir -_
Figure 22: Building 2 Roof Level C Remediation Area 3 Sample Locations B45 B44 B-43 B-42 llhI1er waill I
Remediated Area _
roofing also removed here -
~~
1581 i~~~gii6Oi u61l ~~~43j 65
.68,,,t6Sj j~~~~ujj4 4j n id,I I..
~~~~~~~~~~~~~27.4' 0
Loct.o o..mp......
GI~~~~~~~~~I Ld d6 U
- 6 p"IWithi::
1
~ ~ ~ ~ ~ ~ ~ ~ ~~~~~~'
I1
.......... ~~~~~
~'
I,~ ~ ~ ~~..
roof edge
-4........
-- -15.8' Samples Collected by: B Hunter, W Schuck & R Stowell Dates: 05-02-01 to 01-15-02
- 1. All samples collected prior to remediation, sample results are provided in Table 5.
-n CD
- 2.
a Denotes sample number (B2-Roof-##) and approximate location.
- 3.
c##
Denotes sample number (B2-Roof-C##) and approximate location of samples collected during the initial survey.
0D
17-VI7 r7 tP7 t7 L1.
V7 F,
F V
W7 V.
177 C
I 11.
Fl -
Figure 23: Building 2 Roof Level C Remediation Area 3 Exposure Rate Fixed Measurement and Scan Locations and Results B-44 B-45 B-43 B-42 Remedial Area 100 % SC roofing al remove here 10 % SC;
~~~~~~~~~inner waiill 8 ~~~~~~~~~~~~~I.
I I
ted
_________________________ :4
- 8 1 0 _____
~~~.....
- 0
-27.4'
,an I
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ISO.
.I.'.
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~I d
~~~~~~~~~~~~~~~~~~~~~~~~~~9-10 d.I.~~~~~~~~~~~~~~~~~..
an
......~~~~~~1 1 I
~~~~~~~~~~~~~~~~~~~~~~~~~~~~
...~~~~~~~~~~~~~I 9 -1 0 I,
II i~~~~~~~~~~~~~~~..
~I I
I II I~~~~~~~~~..
roof edge 4.........--
-15.8........-I
. -, -- f F., 1,.-, ;,i i.,
-- Y AZ """"
f
... :, " -
I 6 W d
k ,, JO, -" " f C.,
,C
I. -.., I,
-, 4-;-
Model-7" Ludlum 3 Serial 153551 tCal Due~ Date.
07-09-02 Surveyed Conducted by: R Stowell Date: 04-13-02
- 1. All readings are in pR/hr.
- 2. #-## Denotes surface scan Results range from 7-10 jiR/hr.
, 2.
-- P ro b e,: -, : I 2'x 2" Nal -y 1:~Probe Ser.#,
155109
- ,Background,.1, 9-10 PR/hr cont
.J9-11 pR/hr~lm
-n CB aD
- 2. #t Denotes Fixed measurement taken at - 1 meter above the surface. Results range from 7-10 pR/hr.
V77 Ir7. C-V-
r1 -i V7 tF-V T F
(-7 F7.
CV7 I`- --
F"o I 7 F- -
7-Figure 24: Building 2 Roof Level C Remediation Area 3 Alpha and Beta Scan Locations and Results B-45 B-44.
.-I.
B-43 B-42 Remedial Area.
100% Scai roofing al remove here 1 0% Sca inner wait**l
., :........:.j 1 '
S '
'.I I "'.,..
IIi ted 000-oo 10 oo t
10001i200p 1 00 9001200 0::
'::2:::::::: :-:
3
- -:.:::.: :0:20: :,:
_e ned
- O :,
2 -.
O...
20-a
~~~~~~~~~~~~~~~~~~~~~~~~~.
- ~~~~~~~~~
J:...
' : : :: : : : : : I 1: : : :: : :
1 5
':~~~~~~~~~~~~~~~
'," ':"~~~~~~.
sg '"":
4~~~~~~~~~~4 9001200 10200............................
- u..
a I
] ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~.
I:
I: I I: I I I..
I: I l
I 1
I I i*1
- : ' ~~ ~...,: '
1::
- 1
- : : : : : : 1 1: : : : : : : : : : : : : : : :
Is
- 4
.t 1:
- 1 1
, ~~~~~~~~~~~~~~~~~.
.....,,,1::::::'
0 0 0_
~
9
_ _ _ __I_
roof edge
-4.
-15.8' I
I Mde z.;
Ludlum 2221 Ludlum 2221 84459 148425
- Ca Date Dt 09-27-02.-2702 07-31-02
_________ ff 31.00%
21.09%
- 'b'i.,.t. Probe's'>-'
434 c2 p 434 cm2 a Probe# ',
086215 086236
.E3 iBackground.
'1150-1290 cpm 7-26 cpm Surveyed Conducted by: S. Cowan Date: 04-13-02 Notes:
- 1. All readings are in cpm, shown in ranges Alpha ( #-## a), Beta (
-### f ),
results range from 0-20 cpm Alpha and 900-1300 cpm Beta.
2 100% of the surface scanned in the first - 8 feet from the wall, 10% in the remaining uncovered area out to the roof edge..
'1 CD N,
r--
F-F-, I- -.-- F,-,
(.'1 t77
-- U VF-
[FT -
V T
t
-~ F-V.?
IVT-V7-17 (7---
f-T Figure 25: Building 2 Roof Level C Remediation Area 3 Fixed Measurement Locations and Results and Wipe Locations B-45 B-44.
B-43 B-42 II.
_____inner waii Remediated Area-roofing also removed here-526:
I
<2oa ot 51913:.>..'j 151713 0
.~
~ ~~~~~~~..........
I I
I~~..
.4!JV pi
<20a:
47713 77 711:
711:
77 - - - - - - -~
I
...~~~i
<20a 53013
(~~~~~~~~~~~..
.2c 49313
.(..
51 1.<20.....
49 1 j'
.2 a
......I 1
A~I
~
~
~
~
~
~
I I
27.4
<20cc 53513 E...J...
.....I 49413
<20cc
~
~
~
I
.......... ~i roof edge
-4.-----.......-
15.8'
~Modelt ~
Ludlum 2221 Ludluml12
,,. en-aI'
'7 84423 138738 27caii DueDat 08-05-02 06-27-02 Efficiency ~
36.47%
21.77%
- i~c~ j~b~'~.22~
100 cm2 I 50 cm2 a ro
~~~119444 44834
~B~ckg~und
~
655 +/-70Ocp2m 0-20 cpm
~ ~MA'~
Kf:167dpm/100cmr2 216dpmfI/10CM2 Surveyed Conducted by: S Cowan & R Stowell Date: 04-13-02 Notes:
- 1. ($2N Denotes wipe number and location. Wipe results are provided in Table 6.
- 2. fl# a Denotes fixed alpha measurement in cpm. Maximum reading was <20 cpm,
<MDA ( 216 dpm/1O 00CM2).
- 3. ### 13 Denotes fixed beta measurement in cp2m. Maximum reading was 535 cp2m,
<MDA (167 dpm/1I0OCM 2).
r-3 ci'
F7 r-c*"
r7-I v--- r r-v
[
rf-v F -
(i V7-f77 V*<
Figure 26: Building 2 Roof Level "C" Remediation Area 4 Sample Locations Remediated Area C-63 C-62 61\\, inner wall C-60 C-58 C-59
..... ~ ~ ~ ~ ~
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79 I
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- 4..... A
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lr
1
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-15.8'
-1017 roof edge Notes:
- 1. All samples were collected prior to remediation. Sample results are provided in Table 5.
- 2. (
Denotes sample number (B2-Roof-##) and approximate location.
Samples Collected by: R.Stowell & W. Schuck Date(s): 11-28-01 to 01-08-03
r-r r
-- 7 r-7 r7
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(
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Figure 27: Building 2 Roof Level C Remediation Area 4 Exposure Rate Fixed Measurement and Scan Locations and Results Remediated Area C-63 C-62 C-61 \\
innor waIl C-60 C-59 C-58 i I.....
6 v....
5 r..
- l.....
4
-~~54
- H, -
- 1.
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I: 6 V ~~-27.4' 7I 7
7I C ':
j4.
57;'~~~~~..
roof edge t-0--
-15.8'
-Wi Notes:
- 1. 100% of the accessible surface scanned in Section A and 25% in Sections B & C.
- 2.
-o-Denotes surface scan in pR/hr. Results range from 5 to 7 ItR/hr.
- 3.
Denotes fixed exposure rate measurement taken - 1 meter from the surface.
Results range from 5 to 8 pR/hr.
x',K:-
Instrument' 7>-3
,-..,Model--..,
Ludlum 3
-Serial 153311
.Cal Due Date'.
10-09-03
-..ff.Probe,.-'
2 X2 Nal
- Probe.Ser.#.'
155594
- X 5-8 IpR/hr cont.
5-8 iR/hr @ 1m Survey Conducted by: J Sullivan Date: 05-24-03
[_
r-
-- r:
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r--
r-.-
r--- r -
r r'
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Figure 28: Building 2 Roof Level C Remediation Area 4 Alpha and Beta Scan Locations and Results Remediated Area c-63 c-62 C-61
\\i.
C-60 C-59 C-58 Ii _
- 800-900,13>,.
800-900
,Bl.00990 l
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1
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ai n:l'~i~
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roof edge L*-
Notes:
- ~~~~~~~~~~~~~~~~~~Instruments-]
Notes:
~..
- 1. All readings are in cpm, shown in ranges, Alpha (X-XX a),
Beta ((XXX-XXX p). Results range from 0-20 cpm Alpha and 800-900 cpm Beta.
- 2. 100% of accessible surface scanned in Section A, 25% in sections B and C.
Model Ludlum 2221 Lundum 2221 Serial #
154202 97287 Cal Due Date 09-26-03 11-05-03 Probe 434 cm2 p 434 cm2 a Probe Serial #
149017 083293 Efficiency %
30.17 20.98 Bkgd. metal 900-1300 cpm 0-20 cpm Surveys Conducted by: R. Stowell & S. Cowan Date: 05-24-03
C---
r It r r-r-
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I Figure 29: Building 2 Roof Level C Remediation Area 4 Fixed Measurement Locations and Results and Wipe Locations Remediated Area C-63 C-62 C-61k innerwall C-60 C-58 C-59 S
<20cc 416fl.
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roof edge K
1 Survey Conducted by: R. Stowell & G. Sayer Date: 05-24-03 Notes:
Model' Ludlum 2221 Ludlum 12
.;, 4Serial
- r-86302 91103 Cal Due Date2l 07-24-03 10-23-03 te,*>rtkS> Prober; U
100 cm2 I 50 cm2 a
,Probe Serial#
142547 092192 wEfficiency,%,,-,
31.20 21.77 m Bkgd::. Metal,,. 435 + 170 cp2m
< 20 cpm
'.t,;l MDA w;.:.
160 dpm/100 cm2 216 dpm/100 cm2
- 1.
)
Denotes wipe number and location. Wipe results are provided in Table 6.
- 2.
- a Denotes fixed Alpha measurement in cpm. Maximum reading was < 20 cpm,
<MDA (216 dpm/100 cm2).
- 3.
- P Denotes fixed beta measurement in cp2m. Maximum reading was 503 cp2m,
<MDA (160 dpm/100 cm2).
r-F F----
VF v-[-
( -
V- -
F-r--
C-c---rw.- F~--.
r-v-
(
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Figure 30: Building 2 Roof Level C Remediation Area 4 Insulation Scan Locations and Results Remediated Area aterial C-61n innerwall C-60 C-63 C-62 C-59 C-58 ad.
t'1:
~
~ 1
___5 and'\\ FIH26 6
]
20-60 IA
//I C. :,l ::::::
L:l:::::::::::::::::::::::1::..:.:.:..
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- 30-60 i,
-27.4' 4'
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- ~~:*.::::!,
I roof edge I
I~~~~~~~~~~~~~~~~~~
Notes:
- 1. 100% of the insulation layer was scanned prior to removal in sections B & C.
- 2.
All readings are ranges in cpm.
>.2Model -
S
.Ludlum 3
Ludlum 3 Ludlum 3 Ludlum 3
-. >:Serial 143349 138880 61488 4687 Cal Due Date;.
11-20-03 07-18-03 11-20-03 11-20-03
>>-e;^; Probe,;
15cm2 3 15 cm2
-y 15 cm 2,B-y 15 cm 2 0-y 7Probe-Serial#
145967 145963 117851 117842
- . Efficiencyl%.os 29.18 24.62 27.96 27.96
. Background, 20-60 cpm 20-60 cpm 20-60 cpm 20-60 cpm Survey Conducted by: J. Sullivan, R. Stowell, S. Cowan, & G. Sayer Dates: 05-23-03 to 05-24-03
General Atomics' Final Radiological Survey Report For Building 2 (Science Laboratories Building) Roof Appendix A Final Survey Plan
April 12,2001 Page l of 3 Prepared By: Laura Gonzal Final Survey Plan for the Roof of Building 2
Background
Building 2, also known as the Science Laboratories Building has about 142 laboratories, offices, hallways and a service corridor which houses the utilities for the labs and offices. The building was used over the past -35 years primarily for various research and development activities involving the use of radioactive material. All but 3 of the laboratories have been released to unrestricted use by the NRC and the State of California after a Final Radiological Survey Report was submitted and confirmatory surveys by the agencies performed as needed. The roof of the building has been spot checked for radiological contamination periodically by Health Physics but never surveyed for release to unrestricted use.
Classification There is no known radiological contamination on the roof of Building 2. The roof was therefore classified as an "unaffected area". Although exhaust ducts have vented through the roof over the years the exhaust was required to be filtered through high efficiency particulate air (HEPA) filters prior to being exhausted.
Site Description There are 4 levels of roof over Building 2. Level "A" covers the inner upper offices and hallway, Level "B" (which is the highest level) covers the upper laboratories and the service corridor, Level "C" covers the lower laboratories and Level "D" covers the hallway and outer offices. -ee
- A igIJ 4/2I0 1 Safety Requirements
- 1. Two people must work together when on the roof. One must carry a radio or working cell phone.
- 2. Under no circumstances shall any work be done within 6 feet from any edge of any roof level.
CRITERIA FOR RELEASE TO UNRESTRICTED USE Exposure Rate Guideline The guideline value for exposure rates measured at 1 m above the surface, is 10 MR/hr above background levels. Normal background is 15.iR/hr measured at 1 meter up from the surface.
Gravel Surfaces The entire surface of the roof (all 4 levels) is covered with tar and gravel. There is no known contamination present. Gravel samples will be collected on each level and compared with the approved soil release criteria which applies to gravel. The predominant nuclides found at the GA site and the applicable release criteria (in pCi/g) are as follows: (The, guideline limits are above background values).
Final Survey Plan for the Roof of Building 2 Page 2 of 3
Enriched Uranium (U-234 + U-235)
Depleted Uranium 10 pCi/g 30 pCi/g 35 pCi/g.
If more than one radio nuclide exists, the sum of the fractions of the concentrations is calculated as follows:
S X = <1 C, = The average concentration of radio nuclides 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.
Survey Plan Summary
- ~:~Urve'rano The of Building
...~.*.
.:5..
Gridding Not Required Exposure Rate Scan each level in a path 2 m wide, the length of the roof. On Levels A, C and D, scan a Surface Scanning 2 m path beginning at the wall out 2 m. On level B, scan a 2 m path along the center of
(,pR/hr) the level, the entire length.
Never work 2m from any edge.
Exposure Rate Take a measurement every 3 mn (width and length). Record the Measurements measurement in /,R/hr.
(uR/hr)
Make sure not to get within 2 nifrom the edge.
Direct Using a GM counter, scan around the main exhaust on Level "B".
beta/gamma Using a GM counter, scan the surface around other exhausts on each level measurements (at least 2 on each level).
Gravel Samples Collect 6 gravel samples evenly spaced on each level of the Building 2 roof.
(There are 4 levels, therefore, collect 24 gravel samples).
Final Survey Plan for the Roof of Building 2 Page 3 of 3 ALERT LEVELS If the following "alert levels" are exceeded, notify HIP Management so an evaluation can be performed to determine if increased survey coverage is required or to evaluate if decontamination is required.
Exposure Rate Measurements
> 25 yR/hr on the surface
> 20 pR/hr at 1 m Gravel Sample Results (analyzed by gamma spectroscopy)
All results will be reviewed and anything above natural background levels will be evaluated.
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.
Gravel Samples Mark exact locations of the gravel samples on a map or drawing and refer to the grid locations. Each gravel sample must also be properly labeled and tracked.
The label should include:
The Date; Sample ID number beginning with B2-Roof A-I (for Building 2 Roof, Level A, Sample # 1)
Grid location; HP Technician's name(s)
I -
U7 Figur 1:
B u ldI-2 R
Su r
t (e
Figure 1: Building 2 Roof Survey W,
s w
EX N B
-922' 1F
May 22,2001 Prepared By: R. Stowell & B. Hunter Approved By: L. Gonzales Page 1 of 2 Follow up Survey for Final Survey Plan for the Roof of Building
Background
Two elevated areas were found during the Exposure Rate Surface Scans of Level "C" See Figure 1 for locations. Two gravel/tar samples were collected at the highest readings in each area, C-25 and C-26. Sample C-25 exceeded the release criteria for Thorium and C-26 exceeded the release criteria for Cs-137.
As a result of these samples, an arbitrary 15 ttR/hr boundary was drawn in an attempt to define these two areas.
Sampling Further sampling of the gravel/tar along these contaminated area boundaries is necessary to confirm these boundaries.
Collect 5 gravel/tar samples along the boundary in the vicinity of sample C-25.
Collect 3 gravel/tar samples along the boundary in the vicinity of sample C-26.
Transport samples to General Atomics H.P.Lab for analysis.
November 1, 2001 Prepared by: Richard Stowell 4 Approved by: Laura Gonzales &
Page 1 of 2 Final Survev Supplemental Plan for the Roof of Buildina 2
Background
Two contaminated areas were found on Level "C" during the initial surface scans. The contamination is fixed in the layer of tar/gravel beneath the loose gravel. Subsequent scanning and sampling has defined these areas for remediation, see attached Figure 1. To ensure that other contamination does not exist this supplemental plan increases the survey requirements for Level "C".
Classification Building 2 Roof, Level C has be reclassified "Suspect Affected".
Safety Requirements
- 1. Two people must work together when on the roof. One must carry a radio or working cell phone.
- 2. Under no circumstances shall any work be done within 6 feet from any edge of any roof.
Criteria for Release The release criteria stated in the Final Survey Plan of April 12, 2001 will apply for this survey.
Alert Levels The alert levels stated in the Final Survey Plan of April 12, 2001 will apply for this survey.
Survey Plan Summary
-Si a Enn i wi/i'2kzj lidvj if F
i p
t~~S :1 fiio WM:
W X40
~'
~-04 Exposure Rate Surface Scan a path 2 meters wide, the length of the roof beginning 2 meters out Scanning (WRlhr) from the wall.
Never work 2 meters from any edge.
Tar/Gravel Samples
'ollect 72 tar/gravel samples evenly spaced, one for each section of the roof (sweep away any loose gravel prior to sampling) These should be taken at the same distance from the wall as the previously contaminated samples. (See Figure 1) 040^41-v~(I-A
~q-xw A
(.Jt4
- PI
)VAI-,-
11-16-01; 4:04PM;FACILITIES
- 858 455 4375 page 2 d 2 U
1 /
1 Figure 1: Building 2 Roof Level "C" x,
I 1
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I I
I i
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= contaminated area
= surface scan area
= tar/gravel sample location vd _ -tz, 6A,* 7f,6 6Ai f
/I 7 y'
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Buildina 2 Roof Level "C" Survey Plan for Remediation / Replacement Prepared by: R. Stowell Approved by: L. Gonzales O
January 22.2002 After Roofers Remove the Material Down to Bare Metal
- 1. Suspect Affected (-first 8 feet out from wall) - 18 m2.
- a. 100 % Gamma Scan w/ 2"x 2" NaI Probe
- b. 100 % Beta Scan w/ 434 cm2 probe.
- c. 100% Alpha Scan w/ 434 cm2 probe.
- d. Fixed Measurements 12 (tot)
(4) smears (4) two min Fixed Beta (4) one min Fixed Alpha
- e. Exposure Rate Measurements 6 @ 1 meter.
- 2. Non-Suspect Affected (frornt 8 feet out to roof edge*) - 44 m2.
- a. 10 % Gamma Scan w/ 2"x 2" NaI Probe
- b. 10 % Beta Scan w/ 434 cm2 probe.
- c. 10 % Alpha Scan w/ 434 cm2 probe.
- d. Fixed Measurements 18 (tot)
(6) smears (6) two min Fixed Beta (6) one min Fixed Alpha
- e. Exposure Rate Measurements 6 @ 1 meter.
- Do not work within 6 feet of the roof edge without a safety restraint.
Fig. I Building 2 Roof Lervei: "C" breezeway N
breezeway l
A!!
g
~~~~~~~~~~~~~~~Column Vs
/
'9^
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~~~~~~B
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- 5.
so60 Remediation Area, (Suspect Affected Area)
\\,--S C
Roofing replacement area C55 breeze\\way breezeway B3 0O U4b
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General Atomics' Final Radiological Survey Report For Building 2 (Science Laboratories Building) Roof Appendix B NRC Inspection Report 70-734/01-04
12/20/2001 14:54 G A LICENSING -
HP 7
NU.YbS L001 4f.06V AEQ,,C4..
10
- f.
P 00C to UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 611 RYAN PLAZA DRIVE, SUITE 400 ARLINGTON, TEXAS 760114084 December 14, 2001 Cc,-
B. La, c on1 4-Q 2-0o I N ~ C4` 7k-
.1 3-f r
204k Susan G. Lowenstam, Vice President General Counsel and Secretary General Atomics P.O. Box 8560B San Diego, California 92166-9784
SUBJECT:
NRC INSPECTION REPORT 70-734101-04
Dear Mrs. Lowenstam:
On September25 and November 13-15, 2001 The NRC conducted an inspection at your Torrey Pines Mesa and Sorrento Valley facilities. An exit briefing was conducted onsite on November 15, 2001, and a telephonic followup exit was conducted on November 21, 2001, with the results of confirmatory measurements performed by the NRC inspector. The enclosed report presents the scope and results of that Inspection.
The inspection included a confirmatory survey of the Torrey Pines East Land Area and surveys of in-process decontamination activities at the TRIGA Mark IlIl facility and the Building 2 roof.
The inspection also included the closeout of two inspector followup items. No violations of NRC regulations were identified.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS).
ADAMS is accessible from the NRC Web site at httn :/Iwww.nrc.-ovlreading-rm/adams.html (the Public Electronic Reading Room)."
Should you have any questions concerning this inspection, please contact D. Blair Spitzberg at (817) 860-8191 or Wayne Britz at ((817) 860-8194.
Sin rely, dry Dwight D. Chamberlain, Director 5/ Division of Nuclear Materials Safety Docket No.: 70-734 License No.: SNM-696
Enclosure:
NRC Inspection Report 70-734/01-04 RECEIVED DEC 2 0 2001 LICENSING
12/20.
I'-
1.,I 20 14:54 G A LICENSING 4 HP NU.'eb-S WL' General Atomics zwlencfosure:
VDr. K. E. Asmussen, Director Licensing, Safety and Nuclear Compliance P.O. Box 85608 San Diego, California 92186-9784 California Radiation Control Program Director
12/20/2001 14:54 6 R L I UNS I 14 -9' HH NU. Im
< 5 ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket No.:
License No.:
Report No.:
Licensee:
Facility:
Location:
Dates:
Inspector:
Approved By:
70-734 SNM-696 70-734/01-04 General Atomics Torrey Pines Mesa and Sorrento Valley Facilities San Diego, California September 25 and November 13-15, 2001 Wayne L. Britz, Fuel Cycle Inspector D. Blair Spitzberg, Ph.D., Chief Fuel Cycle/Decommissioning Branch Supplemental Information
Attachment:
12/20/2001 14:54 G R LICENSING 4 HP NU. leb.5 VIJ4 EXECUTIVE
SUMMARY
General Atomics (GA)
NRC Inspection Report 70-734101-04 This routine, announced inspection focused on a confirmatory radiological survey of the Torrey Pines East land area and the decontamination program In process to support site decommissioning activities at the TRIGA Mark III facility and the Building 2 roof. The Inspection also included the closeout of two inspection followup items.
Closeout Inspection and Survey (83890)
The.decontamination-and decommissioning activities being conducted at the ToTrey Pines Mesa and Sorrento Valley facilIties were in compliance with the Site Decommissioning Plan (Section 1).
Results of confirmatory surveys performed by the NRC at the Torrey Pines East Land Area and the in-process surveys of the Building 2 roof and the TRIGA Mark IlIl land area were consistent with measurements taken by the licensee. The NRC's confirmatory measurements supported the licensee's determination that these areas and facilities met the criteria for unrestricted release (Section 1).
Followup (92702)
Inspection followup item (IFI) 70-734/0101-01 concerning deficiencies in the respiratory protection program identified during the licensee's annual review of their radiation protection program was reviewed by the NRC inspector. The inspector found the corrective actions taken for closure to be acceptable. Therefore, this item is closed (Section 2).
Inspection followup Item (IFI) 70-734/0103-01 concerning background levels in Building 30 and the anomalies at one of the background environmental air sampler's was reviewed by the NRC inspector. The Inspector found the evaluations and actions taken to be acceptable. Therefore, this item is closed (Section 2).
12/20/2001 14:54 L R LICENSINU 4 NU.'et.
Lout) Report Details Summary of Facility Status All production and research activities Involving the use of special nuclear material (SNM) had been discontinued. Decontamination and decommissioning of various site buildings and structures was underway. The waste treatment facilities and the remaining land areas are expected to be decontaminated and decommissioned by the end of 2001. The only remaining SNM facilities to be decommissioned after that time will be the TRIGA Mark IlIl reactor facilities and the nuclear materials storage areas. The facilities were being decommissioned according to the Site Decommissioning Plan dated September 1996. Extensive site characterization and radiological surveys for release of several areas from the SNM license had been completed.
Decommissioning was also proceeding for radioactive byproduct materials licensed by the State of California.
1 Closeout Inspection and Survey (83890) 1.1 Scope The licensee's preparations, final survey plan, conduct of the final survey, and analysis of data for the Torrey Pines East Land Area were reviewed to verify compliance with the methodologies in NUREG-5849, the licensee's Site Decommissioning Plan, and the requirements of 10 CFR 70.380).
NRC confirmatory surveys for surface alpha, beta and gamma, and ambient gamma radiation exposure rates of selected areas within the aforementioned area and the Building 2 roof were conducted by the NRC inspector to determine the radiological status of the facilities being considered for release. Soil samples were obtained for laboratory analysis from the Torrey Pines East Land Area and the TRIGA Mark IlIl land area.
1.2 Observations and Findincs
- a.
NRC Confirmatory Survey Instruments and Unrestricted Release Criteria Used During the confirmatory surveys, the NRC inspector used the following radiation detection instruments:
Eberline Model E-600 to measure for alpha and beta radiation with an alpha/beta dual phosphor scintillator probe; and Ludlum Model 19 sodium iodide micro-R meter to measure low level gamma exposure rates.
Model
-Serlal Calibration Due Eberline E-600 763 09/06/02 Ludlum Model 19 84259 06/28/02
12/2e/2001 I
12/2~2001 14:b4 Ii R LIULNSINUi 4 HI-The inspector performed operational checks of NRC radiation Instruments with National Institute of Standards and Technology traceable radiation check sources.
Criteria for unrestricted release, as approved in the licensee's Site Decommissioning Plan, are shown below:
Alpha-and Bela/Gamma Emitters 5,000 dpmr/100cm2 Fixed and removable natural uranium, U-235, U-238, and associated decay products and beta/gamma emitters 1,000 dprn/l1Ocm2 Removable natural uranium, U-235, U-238, and associated decay products and beta/gamma emitters General Area Gamma Exposure Rate Limit Less than 10 microRoentgen per hour (,uRlhr) above background when measured at approximately 1 meter (-3 feet) above surfaces/floors.
cobalt-60 8 pCi/g cesium-137 15 pCVg thorium (Th-232 & Th-228) 10 pCVg enriched' uranium (U-234 & U-235) 30 pCVg depleted uranium 35 pCVg
- b.
Final Radiological Survey of the Torrey Pines East Land Area The licensee's "Final Radiological Survey Report for the Torrey Pines East (TPE) Land Area," dated November 2001, was reviewed and found acceptable.
The inspector performed a confirmatory survey of selected areas of the Torrey Pines East Land Area using an alpha/beta dual phosphor scintillator probe and a sodium iodide micro-R meter. The direct (fixed and removable) beta readings ranged from 220 to 1340 dpm/100 cm2 above background. The direct (fixed and removab)e) alpha readings ranged from 0 to 55 dpm/100 cm2 above background. The gamma readings at 1 meter above the ground ranged from background to 5 uR/hr above background. The inspector obtained eleven soil samples from locations chosen at random and biased toward areas that were suspect affected from the Torrey Pines East Land Area. The samples were sent to the NRC's contract laboratory (Oak Ridge Institute for Science and Education) for analysis. The results of eleven soil samples taken by the NRC inspector ranged from background to:
12/20/2001 14:54 G A LICENSING 4 HP NU.J t:.5
[Ad L'
Isotope Hlahest Result cesium-137 1.92 pCIlg cobalt-60 0.14 pGVg thorium-228 1.82 pCVg thorium-232 1.93 pCVg uranium-235 0.22 pCVg uranium-238 3.36 pCOg The results of all surveys and soil samples were less than the criteria established in the Site Decommissioning Plan for unrestricted release and were consistent with results that had been obtained by the licensee.
L.
- c.
Survey of the Building 2 Roof The inspector performed an in-process survey during the decontamination of the Building 2 roof using a sodium iodide micro-R meter and the alpha/beta dual phosphor scinbilator probe. The direct (fixed and removable) beta readings ranged from 0 to 144 dpm/1 00 cm2 above background. The direct (fixed and removable) alpha readings ranged from 0 to 16 dpm/l 00 cm' above background. The gamma readings at ground level and 1 meter above the roof were equivalent to background. The results of the surveys were less than the criteria established In the Site Decommissioning Plan for unrestricted release and were consistent with the licensee's measurements.
- d.
Soil samples of the TRIGA Mark IlIl area The inspector performed an in-process soil survey during the decommissioning of the TRIGA Mark IlIl area. The license for the TRIGA Mark IlIl reactor, adjacent rooms, and yard areas. was previously terminated and decommissioning of this facility is being implemented in accordance with the General Atomics Site Decommissioning Plan. The TRIGA Mark I and TRIGA Mark F reactors are being decommissioned in accordance with the GeneralAtomics TRIGA Reactor Facility Decommissioning Plan. After a buried tank was removed from the TRIGA Mark IlIl area, the soil in the cavity was sampled and analyzed. The cavity was then filled to preserve the structural integrty of the adjacent TRIGA Mark IlIl facility. The results of three soil samples taken ranged from background to:
Isotope Highest Result
'a cobalt-60 0.03 pCVg cesium-1 37 0.01 pCi~g thorium-228 1.09 pCig thorium-232 1.13 pCE/g uranium-235 0.12 pCi/g uranium 238 0.95 pCig
12/20/2001 14:54 G A LICENSING 4 HP Nu.-t:3-wU The results of the soil samples were less than the criteria established in the Site Decommissioning Plan for unrestricted release and were consistent with the licensee's measurements.
1.3 Conclusion The decontamination and decommissioning activities being conducted at the Torrey Pines Mesa and Sorrento Valley facilities were in compliance with the Site Decommissioning Plan.
Results of confirmatory surveys performed by the NRC at the Torrey Pines East Land Area and the in-process surveys of the Building 2 roof and the TRIGA Mark IlIl land area were consistent with measurements taken by the licensee. The NRC's confirmatory measurements supported the licensee's determination that these areas and facilities met the criteria for unrestricted release.
2 Followup (92702)
(Closed) IFI 70-734/0101-01: Deficiencies in the resDiratory protection program identified durnn the annual review of the radiation protection program resulted in the licensee prohibiting the use of respiratory protection eauipment The licensee's closure of the action items concerning the respiratory protection equipment during the licensee's annual review of the radiation protection program was reviewed. The action items were closed out and documented in a licensee memo dated October 9, 2001. The action items included improved storage facilities, updating the respiratory protection program procedure, ensuring the respirators are inspected and cleaned after use, and clean and inspect the respirators every six months, The Inspector found the corrective actions taken for closure to be acceptable. This Item is closed.
(Closed) IFI 70-734/0103-01: Backound Levels in Building 30 and the Environmental Air Samvler: The review of the area thermoluminescent dosimeter results for Building 30 were reviewed. The licensee determined that the background subtractions for this particular building were not representative of the building's construction materials.
The licensee's review of the anomalies at one of the two background environmental air samplers was reviewed and no cause for the anomalies was determined. The use of the results from this background air sampler location was discontinued and the results of the remaining background air sampler are being used to subtract background from the other environmental air samplers.
The inspector found the evaluations and actions taken to be acceptable. This item is closed.
12/20/2001 14:54 G A LICENSING 4 HP NU. 'e.5 3 Exit Meeting Summary The inspector presented the inspection results to members of licensee management at the conclusion of the inspection period on November 15, and the soil sample analysis results by telephone on November 21, 2001. The licensee did not identify as proprietary any information provided to; or reviewed by, the inspector.
12/20/2001 14:54 B R L
UCIMLi 4 HP "U. 'ao V10 L.¢
. e LATTACHMENT SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED Licensee Keith Asmussen, Director, Licensing, Safety and Nuclear Compliance Ruben DeValasco, Nuclear Waste Processing Facility Manager Laura Gonzales, GA Radiation Safety Officer/Health Physics Manager William LaBonte, Lead Health Physicist, Hot Cell Facility Mario Monreal, Nuclear Calibration Technician INSPECTION PROCEDURES USED IP 83890 Closeout Inspection and Survey L
IP 88104 Decommissioning Inspection IP 92702 Followup ITEMS OPENED, CLOSED AND DISCUSSED Closed 70-734/0101-01 IFI Deficiencies in respiratory protection program Identified during annual review of the radiation protection program resulted in licensee prohibiting the use of respiratory protection equipment 70-73410103-01 IF Background Levels in Building 30 and the Environmental Air Sampler LIST OF ACRONYMS USED cm2 square centimeters cpm counts per minute dpm disintegrations per.minute L
D&D decontamination and decommissioning GA General Atomics GM Geiger Mueller HP health physics IFI inspection follow up item NMSS Nuclear Material Safety and Safeguards pCVg picoCuries per gram PDR Public Document Room SDP Site Decommissioning Plan SNM special nuclear material pR/hr microRoentgen per hour
General Atomics' Final Radiological Survey Report For Building 2 (Science Laboratories Building) Roof L
Appendix C May 2003 Remediation Summary with : Remediation Plans L
L
Appendix C: May 2003 Remediation Summary Scope Elevated activity was detected in gravel/tar samples collect between columns C-58 and C-63.
The highest activity concentration was 9.41 pCi/g, Cs-137. This is below the approved release criteria, however, GA, in it's determination to decontaminate areas and facilities to as low as reasonably achievable, decided to remediate this area.
Description A remediation plan for this decontamination effort was issued in February 2003. This remediation was planned to be performed under the following conditions:
- 1.
During an extended weekend when the tenants were not present, and,
- 2.
The threat of rain was minimal.
Both of theses conditions were met during the Memorial Day weekend.
The area with elevated activity levels was sectioned off into three (3) areas based on their gravel/tar sample gamma spectroscopy results. See Enclosure-i, Remediation Plan, for details.
Area A, which was approximately 160 ft2 in area, had Cs-137 concentrations as high as 9.41 pCi/g. This area was treated as a Suspect Affected Area. All roofing material down to the bare metal roof was removed and disposed of as low level radioactive waste.
Area B and C is approximately 2000 ft2 in area, combined. Area B had Cs-137 concentrations at less than 1.5 pCi/g and Area C had Cs-137 concentrations between 1.5 and 2.0 pCi/g. The gravel/tar layer in each of these Areas was removed, placed in "roll-off" containers, and stored in a secure area with the expectation that a regulatory agency may want to perform a confirmatory measurement in the future. The insulation material between the gravel/tar layer was surveyed and found to be at natural background levels. This material was disposed of as "Clean" waste.
Surveys performed on the bare metal roof were not distinguishable from natural background levels. See Figures 27, 28, 29 and 30 for details.
L L
General Atomics' Final Radiological Survey Report IL For Building 2 (Science Laboratories Building) Roof L
Appendix C L
May 2003 Remediation Summary : Remediation Plans
February 11, 2003 Prepared by: R. Sto Approved by c_4 1,, A/oA al U/3 Q.Gonzale-s Building 2 Level "C" Roof Remediations 2003 History and Classification This remediation, - 2160 ft2, on Level C is the third remediation in a continuing effort to have Building 2 Roof released for unrestricted use. This area of Level "C" roof, as shown in Figure 1, columns C58 to C63, has three distinct areas of varying concentrations of Cs-137 contamination. All of these concentrations are below the approved release criteria but above background. These three contiguous areas, A, B & C, are shown in Figure 2.
Area A, -160 ft2, has Cs-137 concentrations of up to 9.41 pCi/g (15 pCi/g. release limit).
Although it is below the limit this area will be treated as a Suspect Affected Area and the roofing material removed will be handled and disposed of as low level radioactive waste.
Areas B & C., - 2000 ft2, have lower Cs-137 concentrations of up to 2pCi/g.( B <1.5 pCi/g., C 1.5 -2.0pCi/g.). These areas will be treated as Non-Suspect Affected and the roofing materials removed and stored on site pending further survey and release.
Remdiation Activities Area A The roofing will be removed down to the bare metal. This material will be handled as radioactive material and placed in approved low level radioactive waste containers. The underlying metal surface will be surveyed as a Suspect Affected Area as shown in Table 1.
Areas B & C An attempt may be made, surface conditions and time permitting, to release the underlying insulation. The gravel / tar layers will be removed from each area, B & C, and placed in separate, marked containers or locations for each.
This is NOT radioactive material but we must retain this on site pending further survey and disposition.
A beta surface scan, 100% of the accessible surface, will be performed, if possible. If the Page 1 of 2
levels detected are at or below background this material can be released. If unable to perform the beta scan survey or levels are not at background, this material, down to the bare metal, will be removed and located with the gravel and tar removed from areas B & C. Material from areas B
& C are to be kept separate.
If during this survey the underlying material isfound to be contaminated: stop the remediation, survey personnel and equipment. take steps necessary to control this material as radioactive material and notify Health Physics Supervision.
Once the roof is down to the bare metal, the surface of both areas B & C will be surveyed as a Non-Suspect Affected Area as shown in Table 1.
Surveys Table 1: Required Surveys.
Survey Suspect Affected Area Non-Suspect Affected Area Area A, Figure 2 Areas B & C, Figure 2
- 16 m'
-190 n?
Alpha Surface Scans 100% of accessible area 10% of accessible area (w/ 434 Cm2 detector)
Beta Surface Scans 100% of accessible area 10%/o of accessible area (w/ 434 cm2 detector) uRlhr Readings (Surface 100% of accessible area 10% of accessible area Scans)
(w/ 2" x 2" Nal detector) uR/hr Readings I measurement per 4 m2,or, 1 measurement per 10 m2,or, (Fixed Measurements @
I measurement every - 2 in I measurement every - 3 in I meter)
Fixed Measurements I measurement per 4 m2,or, I measurement per 10 m2,or, I measurement every - 2 in I measurement every -3 in alternate between (I) a wipe, alternate between (1) a wipe, (2) an alpha fixed measurement and (2) an alpha fixed measurement and (3) a 2 minute beta fixed measurement (3) a 2 minute beta fixed measurement Installation of new roofing material Roofers may install new roofing material only after the surveys are complete and results are acceptable.
Page 2 of 2
Fig. 1 Building 2 Roof Level
'ICII l
I I
I I
I
.IaI I
I I
-g breezeway E
S 194W M
B breezeway Location of 2003 remediations Areas A, B & C
,, breezeway
[- --
r-r-
u
(
I --
( --
(F.
r7 7-,
n-F--
- F-Figure 2: Building 2 Roof Level "C" 2003 Remediation C63 Column #
C58 C62 C59 Breezeway C roof edge Notes:
- 1.
Area A Cs-137 concentrations of up to 9.41 pCi/g. Roofing to be handled as radioactive material. All material, down to bare metal, to radioactive waste containers.
- 2.
E Area B Cs-137 concentrations of 1.5 to 2.0 pCi/g. Segregate this material in a separate, marked location and/or containers.
- 3.
Z Area C Cs-137 concentrations of <1.5 pCi/g. Segregate this material in a separate, marked location and/or containers.
A~~~~~~~~~~~~~~~~~~~~~~~~!A t GENERAL ATOMIC P 0. BOX 85608 SAN DIEGO, CA 92186-5608 (858) 455-3000
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