ML031970643
| ML031970643 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 07/10/2003 |
| From: | Asmussen K General Atomics |
| To: | Adams M, Kwok S NRC/NMSS/FCSS, State of CA, Dept of Health Services |
| References | |
| -RFPFR, CAL/696-3622 | |
| Download: ML031970643 (47) | |
Text
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GENERAL ArOMIC5 July 10, 2003 CAU696-3622 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 Former Building 25 Site and Ms. Mary Adams (in Duplicate)
Fuel Cycle Licensing Branch/Section 1 U.S. Nuclear Regulatory Commission Mail Stop T-8A33 Two White Flint North 11557 Rockville Pike Rockville, MD 20852-2738
Subject:
Docket No.70-734; SNM-696: Request to Release a Certain Portion of General Atomics' Facility to Unrestricted Use and Delete it fromn License SNM-696: Namely, the Former Building 25 Site
Dear Ms. Kwok and Ms. Adams:
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. GA has recently completed the final radiological survey of the "Former Building 25 Site".
Building 25, which had housed a radioactive liquid waste treatment facility, was completely dismantled and disposed of as low level radioactive waste. The former Building 25 site consists of the land previously occupied by Building 25 (it's footprint) and a narrow strip of land area adjacent to each of the four sides of the former building footprint.
The subject land area, which is approximately 4,720 ft 2 (-439 in2) in size, is bounded by the LINAC Land Area to the south and the LINAC North Land Area to the north, east and west.
3550 GENERAL ATOMICS COURT, SAN DIEGO. CA 92121-1122 P0 BOX 85608. SAN DIEGO, CA 92186-5608 (858) 455-3000 I
S. Kwok (State) I M. Adams (NRC)
July 10, 2003 CAU696-3622 Page 2 Enclosed is a GA report titled "General Atomics' Final Radiological Survey Report for the Former Building 25 Site." This report documents the results of GA's comprehensive radiological survey measurements and sampling and analyses related to the subject land area.
In accordance with decisions made during joint NRC, State of California and GA meetings, the State has the regulatory lead for the release of the Building 25 Site.
Accordingly, on April 10, 2003, Mr. Thomas Schell from the State of California conducted "in-process" surveys at the Building 25 site. A total of 5 soil samples were collected and split with GA. GA's results are included in this report. Mr. Tom Schell provided GA with a copy of the State's results (which are not included in the report). The GA results and the State's are consistent with each other. Both sets of results are well below the NRC-and State-approved release criteria.
Accordingly, GA hereby requests both the State of California Department of Health Services' Radiologic Health Branch (DOHS/RHB) and the Nuclear Regulatory Commission (NRC) to release the Former Building 25 Site, as described in the enclosed final survey report, to unrestricted use and delete it from GA's State of California and NRC radioactive material and special nuclear material licenses, respectively.
If you should have any questions regarding this request, orthe 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
Enclosures:
- 1) GA report titled: "General Atomics' Final Radiological Survey Report for the Former Building 27 Site," dated July 2003.
cc:
Dr. D. Blair Spitzberg, Chief, NMSS Branch 3, Region IV Mr. Wayne L. Britz, Fuel Cycle Inspector, NRC Region IV Ms. Kathleen Henner, State of CA, Brea, CA Mr. Tom Schell, State of CA, Sacramento, CA Ms. Barbara Hamrick, State of CA, Brea, CA
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CENER4L ATOMIC5 FINAL RADIOLOGICAL SURVEY REPORT FOR THE Former Building 25 Site Prepared By: William LaBonte, William Schuck and Laura Gonzales Illustrated By: William LaBonte Final Survey Technician: William Schuck July 2003
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GENERAL ATOMZCS
Table of Contents INTRODUCTION.......................................
I SITE DESCRIPTION........................................
I History of Use.........................................
1 Classification................................................
2 CRITERIA FOR RELEASE TO UNRESTRICTED USE..................................
2 As Low As Reasonably Achievable (ALARA).2 Facilities and Equipment (and Asphalt or Concrete Surfaces).2 Release Criteria for Soils.2 Exposure Rate Guideline
.3 INSTRUMENTATION & BACKGROUND MEASUREMENTS
.3 Background Measurements for Instruments/Detectors.3 Background Soil Concentrations of Concern.4 Exposure Rate Background.4 FINAL SURVEYS PERFORMED.5 Objectives and Responsibilities
.5 Survey Plans
.5 Soil Sampling.5 Survey Summary.
6 Comparisons of Site Decommissioning Plan Requirements with Final Surveys Performed. 6 RESULTS OF THE FINAL SURVEYS.
7 Scanning
.7 Fixed Measurements (a and >)
.7 Removable Activity
.7 Exposure Rate Scans.7 Fixed Exposure Rate Measurements.7 Soil Samples
.8 CONFIRMATORY SURVEY.
9 CONCLUSION.9 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:
List of Instruments for the Former Building 25 Site.........................
T-3 Table 4:
Background Soil Concentrations........................................
T4 Table 5:
Building 25 Site Wipe Survey Results...
................................ T-7 Table 6:
Gamma Spectroscopy Results of Building 25 Site Land Area Soil Samples
.... T-8 ii
List of Figures (unpaged)
Figure 1:
GA's Torrey Pines (Main) Site Figure 2:
Building 25 Site Land Area and Adjacent Land Areas Figure 3:
Building 25 Site Alpha Scan Locations and Results Figure 4:
Building 25 Site Beta Scan Locations and Results Figure 5:
Building 25 Site Fixed Alpha and Beta Locations and Results and Wipe Locations Figure 6:
Building 25 Site Exposure Rate Scan Measurement Locations and Results Figure 7:
Building 25 Site Fixed Exposure Rate Measurement Locations and Results Figure 8:
Building 25 Site Soil Sample Locations and Exposure Rate Measurements at Sample Locations Appendices Appendix A:
Final Survey Plan for Building 25 Site Land Area.
Appendix B:
Sr-90 Analysis Results iii
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CENERAL ArOMICS Final Radiological Survey Report for' the Former Building 25 Site 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 Former Building 25 Site located on GA's Main Site (Figure 1). Building 25, a radioactive liquid waste treatment facility, was completely dismantled during decommissioning activities. The "Former Building 25 Site" consists of the land previously occupied by Building 25 and the surrounding land area.
This parcel of land, which is approximately 4,720 ft (439 m2), is bounded by the LINAC Land Area to the south and LINAC North Land Area to the north, east and west (Figures 1 and 2).
GA is requesting both the Nuclear Regulatory Commission (NRC) and the State of California Department of Health Services' Radiologic Health Branch (DOHS/RHB) to release this land area to unrestricted use.
This report documents the results of GA's radiological measurements and soil sampling and analyses performed on the Former Building 25 Site. The results of these surveys and analyses demonstrate that this land area meets the NRC-and State-approved criteria for release to unrestricted use.
Site Description The Building 25 Site is open land area, a small portion of which is paved with asphalt. The land area, which is approximately 4,720 ft ( 439 in2), is located on GA's main site (Figure 1). The site overlaps the LINAC Land Area to the south and the LINAC North Land Area to the north, east and west (Figure 2).
History of Use Since the late 1980's, Building 25 housed the radioactive liquid (aqueous) waste treatment facility used to treat and filter low levels of radioactively contaminated liquid wastes collected at various nuclear facilities around GA. The aqueous liquid waste was analyzed prior to disposal into the sanitary sewer system to ensure compliance with State-and NRC-regulatory and license requirements.
The facility was shut down in the late 1990's. The sewer line previously located between Building 25 and the closest sewer manhole (#15) was excavated, removed and disposed of as low level radioactive waste during the remediation activities conducted on the main sewer system in 2002.
Page 1 of 9
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GENERAL ATOMICS Final Radiological Survey Report for ihe Former Building 25 Site The surveys and soil sample results for this portion of the sewer line were provided in the report submitted to the NRC and State for the S-13 to S-15 to S-18 Sewer Trench.'
During decommissioning activities, Building 25 was completely dismantled and packaged for disposal as low level radioactive waste at an authorized disposal facility.
Classification Characterization surveys were completed inside the building which indicated some small areas of contamination on the concrete floor surfaces and walls. It was decided to completely dismantle the building and package it for disposal as low level radioactive waste (which was completed). The soil underneath the building and the soil and asphalt surrounding the building were classified as a Suspect Affected Area.
Criteria for Release to Unrestricted Use As Low As Reasonably Achievable (ALARA)
During decommissioning efforts, GA attempts to decontaminate to levels as close to "background" and as far below the approved Release Criteria (as identified in GA's Site Decommissioning Plan) as reasonably achievable.
Facilities and Eguipment (and Asphalt or Concrete Surfaces)
The NRC release criteria for mixed fission (e.g., Cs-137) and mixed activation (e.g., Co-60) products (suspected predominant contaminants) is as follows:
5,000 dpm /100 cm', averaged over a 1 m' area 15,000 dpm /100 cm2, total, maximum in a 100 cm2 area 1,000 dprn/I00 cm, removable activity Release Criteria for Soils The predominant radionuclides found in the soil at GA and the NRC-and State-approved release criteria in pCi/g (above natural background concentrations) for these radionuclides are provided as follows:
Letter dated February 4, 2002 (696/CAL-3429) from Keith E. Asmussen "Request to Release Certain Portions of General Atomics' Facility to Unrestricted Use and Delete them from its License: Namely, Sewer Line Trench S-18 to S-15 to S-1 3" to Ms. Mary Adams (NRC) and Ms.
Sudana Kowk (State).
Page 2 of 9
+ GENERAL ArOMICS Final Radiological Survey Report for the Former Building 25 Site Enriched Uranium (U-234 + U-235) 30 pCilg Thorium (Th-228 + Th-232) 10 pCi/g Depleted Uranium 35 pCi/g Cs-137 15 pCilg Cs-134 10 pCi/g Co-60 8 pCi/g Eu-152 11 pCi/g If more than one radionuclide exists, the sum of the fractions of the concentrations is calculated as follows:
nC
'=
<1 Where: C The average concentration levels of radionuclide i in the sample (above background).
L, = 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 1 m above the surface are not to exceed 10 R/hr above natural 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 minimum detectable activity (MDA's, if applicable)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.
Background Measurements for Instruments/Detectors Asphalt near Building 13 on GA's main site was used for conducting background measurements with instruments used for the final survey because there is no history involving radioactive materials or storage of radioactive materials in Building 13 asphalt near Building ?5 could also be found outside Building 13. Background information, where appropriate, is included in Table 3.
Page 3 of 9
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GENERAL ArOMICS Final Radiological Survey Report for the Former Building 25 Site 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:
Equation (5-2) 2.71 + 4.65BRXt 2
JMA-4 (dpm/l OOem JA txExA Where:
BR =background rate (cpm) t = count time (min)
E = efficiency A = area of the detector (cm2)
The MDA for scan surveys using the 434 cm2 gas flow proportional detector (floor monitor) was calculated using equation 5-3 from the draft NUREG/CR-5849 (modified in accordance with the discussion on page 5.8 of the draft NUREG/CR-5849).
Equation (5-3):
MDA= XxBR (dpm/lOOcm2)
Ex. A 100 Where:
X = the multiple/portion of the background rate that can be discernable as an increase in instrument response by the surveyor (dependent on the type of instrument used).
BR= background rate in (cpm)
E= efficiency A = area of the detector (cm2)
Background Soil Concentrations of Concern Typical background concentrations measured by gamma spectroscopy in soil near the GA site have been established (at the 95% confidence level) and are provided in Table 4 along with 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 pR/hr measured at I 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 Page 4 of 9
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GENERAL ATOMICS Final Radiological Survey Report for the Former Building 25 Site 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 pR/hr (measured at 1 m from the surface). The range of 12-18 pR/hr is typical at the GA site for the external dose rates measured 1 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 soil sample results at the surface were well below GA's approved release criteria for unrestricted use, and, (2) that the exposure rate measurements taken in these areas, measured at 1 meter above the surface, were less than 10 pR/hr above background.
Survey Plans A Final Survey Plan (provided in Appendix A) was developed based on the previous use history of the Former Building 25 Site, the radionuclides of concern for this area, the potential for contamination, the various types of surfaces encountered and the classification of the various areas.
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. Soil samples were counted in GA's Health Physics Laboratory which maintains an effective QA program.
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 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.
Soil Sampling Soil samples were collected in a 5m x 5m triangular grid pattern in the approximate locations shown in Figure 5. Each of the soil samples taken was approximately 1 kilogram in mass. The samples were properly logged, labeled, tracked and packaged into plastic bags. All debris (i.e., grass, rocks, sticks, asphalt and foreign objects) was removed from each sample. Each soil sample was individually crushed to reduce large lumps, dried, placed into tarred marinelli beakers (filled to the top), weighed, sealed and transported to GA's Health Physics Laboratory.
Soil samples were analyzed in GA's Health Physics Laboratory with a Canberra Low Sensitivity Page 5 of 9
I+ GENERAL AOMICS Final Radiological Survey Report for the Former Building 25 Site I
Gamma Spectroscopy MCA System using a high purity germanium detector. The system is calibrated using NIST traceable standards and performance checked daily. Soil samples were counted for a minimum of 30 minutes each. A 30 minute count was sufficient to detect the radionuclides of concern at levels below GA's approved soil release criteria.
Two (2) of the soil samples were sent to an offsite contracted laboratory (Severn Trent Laboratories) for Strontium-90 analysis.
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 (e.g., number of fixed radiation measurements), exposure rate measurements (piR/lbr) and soil samples taken are provided as follows:
'Comparisons of Site Decommissioning Plan Requirementswith
..-Final Surveys Performed on the Former Building 25 Site:
Survey Gidding
- of Direct
- f Exposure Rate i/f c Sure' of Soil Saples Area*+
Required ? -
Measurements IMeasurements Scans on asphalt Taken and Fixed a,], or
-(gR/hr) or concrete Analyzed wipes on concrete orasphalt
__', _:i:
__i: _____
D-Plan*
Yes I every 4m2 or I per 4 m2 or 100% of 31 based on a 5m Suspect I every 2 m.
I every 2m.
accessible triangular grid Affected 19 measurements 1 10 measurements concrete and system.
Area based on 75 n2.
based on 439 m2 asphalt surfaces e
Final Yes Total = 19 Total - I 10 100% of Total = 31 Surveys lIOm x lOrn Fixed a = 6 plus a contact & I accessible locations (45 total)
Suspect grids Fixed = 7 meter measurement concrete and Affected Wipes = 6 at each soil sample asphalt surfaces 31 surface Areas location & 100%
5 subsurface 4
scan of the surface 9 under asphalt (at-I")
- D-Plan = GA Site Decommissioning Plan
- The total surface area to be released is approximately 4,720 ft2 (
439 in2 ). The total surface area of the paved surfaces is approximately 810 ft ( 75 in2 )
Page 6 of 9
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GENERAL ATOMICS Finai Radiological Survey Report for the Former Building 25 Site Results of the Final Surveys The final radiological survey results for the Former Building 25 Site are provided in figures and tables as noted below:
Scanning 100% of the asphalt surfaces were scanned using gas flow proportional detectors (floor monitors) having a 434 cm2 detector for both a and P radiation. The results were below the Minimum Detectable Activity (MDA) level for the instruments used. The results and scan MDA's, are presented in Figure 3 (for a) and Figure 4 (for ).
Fixed Measurements (a and )
There were six (6) fixed a and seven (7) fixed fI measurements taken. All results were below the Minimum Detectable Activity (MDA) of 184 dpm/I 00 cm2 for a and 244 dpm/1 00 cm2 for i. See Figure 5 for a and P locations and results.
Removable Activity A total of six (6) wipe measurements were taken and analyzed for a and P activity. The highest a activity was <20 dpm/100 cm2 and, the highest P activity was <20 dpm/100 cm2. These results are far below the approved release criteria. See Table 5 for results and Figure 5 for appropriate sample locations.
Exposure Rate Scans Exposure rate scans were performed on all accessible surfaces (100% coverage) using a 2"x2" NaI(Tl) detector held approximately I " from the surface. The results ranged from 13-19 pR/hr on soil surfaces and 11-21 1pR/hr on asphalt surfaces. See Figure 6 for scan results.
Fixed Exposure Rate Measurements One hundred and ten (110) fixed exposure rate measurements were taken at I m from the surface every 2 meters using a 2"x2" NaI(TI) detector (pR meter). The highest measurements were 16 pR/hr above the soil surface and 17 pR/hr above the asphalt surface, which is less than 10 pR/hr above background (the release criteria). See Figure 7 for locations and results.
In addition, exposure rate measurements were taken at contact and at I meter above each soil sample location (over soil surfaces only). The highest readings were 19 i[R/hr at contact and 17 pR/hr at 1 meter from the surface, which is less than 10 [tR/hr above background (i.e., well below the release criteria). The approximate locations and the results are provided in Figure 8. The results are also provided in Table 6.
Page 7 of 9
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GENERAL ATOMICS Final Radiological Survey Report for the Former Building 25 Site Soil Samples Soil samples were collected in a 5 m triangular grid as shown in Figure 8. Thirty-nine (39) surface soil samples (0"-6") and five (5) subsurface (6"-12") soil samples were collected from the exposed ground areas and nine(9) surface (0-6") soil samples were collected beneath the asphalt pavement.
The samples were counted by gamma spectroscopy for 30 minutes.
The gamma spectroscopy results for these samples are provided in Table 6. The results (in pCi/g) showed trace concentrations of 'Cs in a few of the soil samples; but the results were all well below the approved soil release criteria as summarized below. Naturally occurring 238U, 2"U, 228Th, and 232Th were present at levels that were not discernable from background levels. A summary of the soil sample results is as follows:
-Radionuclide Concentrations in pCilg 238 U 23
- 37Cs 228 h 212 b 232Th (60c)
High 3.62 +/- 2.69 0.35 +/- 0.09 0.67 +/- 0.10 1.99 +/- 0.35 2.19 +/- 0.41 0.14 +/- 0.17 Low ND ND ND 0.64 0.15 0.66 0.18 ND Average 1.53 0.17 0.13 1.52 1.55 0.13 (N = 4 5 )
Nominal See Table 4 for background range and background locations.
Background
Notes:
- 1.
ND means not detected.
- 2.
Average Minimum Detectable Activity (MDA):
U-238 = 1.58 pCi/g (63 keV peak)
U-235 = 0.14 pCi/g (186 keV peak)
Cs-137= 0.13 pCi/g (662 keV peak)
Co-60 = 0.13 pCi/g (1173 keV peak)
Th-228 = 0.21 pCi/g (238 keV peak)
Th-232 = 0.43 pCi/g (911 keV peak)
- 3.
The high concentrations for each isotope did not occur in the same sample.
- 4.
No sample had a sum of fractions greater than 1.0.
- 5.
The Average Activity is based on the numerical average of all (45) samples, using the Average MDA value when the isotope was not detected. The soil sample results obtained from the State are not included in this summary.
- 6.
Background is not subtracted. See Table 4 for soil background infornation.
- 7.
Soil sample locations are illustrated in Figure 8. Soil sample results are presented in Table 6 and Figure 8.
Page 8 of 9
4+ GENERAL ATOMICs Final Radiological Survey Report for the Former Building 25 Site The activation product,Co, was identified in only one (1) soil sample having a concentration of 0.14 +/- 0.17 pCilg (trace level). The remaining 44 samples were less than the average Minimum Detectable Activity concentration of 0.13 pCi/g.
In a few of the soil samples, trace concentrations of the fission product 137CS was identified. The maximum concentration detected in the soil was 0.67 +/- 0.10 pCi/g (sample S-21, Figure 8) with an average of 0.13 pCilg. All were well below the release limit of 15 pCilg.
Three (3) samples were sent to Severn-Trent Laboratories for Sr-90 analysis. Two (2) samples with the highest Cs-137 results were selected for Sr-90 analysis because Cs-137 and Sr-90 are both fission products. One sample with the highest uranium result was also selected for Sr-90 analysis. Sr-90 was detected 1 of the 3 soil samples at a level of 0.67 +/- 0.39 pCilg (the MDA is 0.5 pCi/g). This concentration is far below the approved soil release limit for Sr-90 (1800 pCi/g). The Sr-90 results are provided in Appendix B.
In April 2003, Mr. Thomas Schell, from the State of California, Department of Health Services' Radiologic Health Branch (DOHS/RHB) performed an "in-process" survey at the Building 25 Site.
A total of five locations were chosen for sampling. Enough soil was collected at each location to allow the sample to be split; one sample for the State and one sample for GA to analyze. A copy of GA's results were provided to Mr. Thomas Schell. A copy of the State's results were provided to GA. GA has concluded that both sets of results are consistent with each other. GA's results are provided in Table 6.
Confirmatory Survey A confirmatory survey was not performed in this area by GA because of it's small size and because no remediation was required. Mr. Thomas Schell from the State of California DHS/RHB performed an "In-Progress" confirmatory survey during the performance of GA's final radiological survey.
Conclusion Final contamination and radiation surveys, as well as the results of analyses of soil samples, as documented in this report, demonstrate that the Former Building 25 Site meets the approved criteria for release to unrestricted use.
Page 9 of 9
Table 1:USNRC'S CEPTABLE SURFACE CONTAMINATION LEVELS '
Nu...s My lRemioabebi
-'K.
U nat 235U, 238U, & associated decayproducts5,000 a 15,000 a 1,000 a Transuranics 226Ra 228Ra 230Th, 228Th, 23 Pa, 227Ac, 100 300 20
- 125i, 291 Th-nat, 232Th 9Sr, 223Ra, 224Ra, 232u, 126i 33 I,3I 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 100 cm 2 of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency.
When removable contamination on objects of less surface area is determined, then pertinent levels should be reduced proportionally and the entire surface should be wiped.
f The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mRad/hr at 1 cm2 and 1.0 mRad/hr at 1 cm2, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.
T-1
S T A OFICAACCEPTABEISUFACN-A T
N I
V L S Table-12: STATE OF CA ACCEPTABLE SURFACE'CONTAMINATION LEVELS Nuclides" 1 Averagebv A J laximumb,"
Remo labieb
___________i__________.__-__
. (dpint 0O0cmi)
(dpmilOOcm 2 j-l
______cm_
U-nat, 235U, 38U, & associated decay 5,000 15,000 1,000 products Transuranics, 6 Ra, 22Ra, 230Th, 228Th, 100 300 20 23'Pa 227Ac, 25i, 291 Th-nat, 232Th, 9Sr, 22Ra, 224Ra, 232u, 1261 1,000 3,000 200 133i 1311 Beta/gamma emitters (nuclides with decay modes other than alpha emission or 5,000 15,000 1,000 spontaneous fission) except 90Sr and other noted above E
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-gamma emitters should not exceed 0.2 mrad/hr at 1 cm2 and 1.0 mrad/hr at I 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
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- z c ri tr lTABE 3: LIST OFJNSTRUMENTS for the Former uiidng 25 Site
_______________j.__._.D Instrument Detector
,Rangel Calibration Due iciency grud Desciption (cpm, liR/hr)
Dae MDA (00cm 2 P & Ocm, a-detecors 6nly)
Ludlum Ludlum Model 43-37 gas Four Linear Ranges 09/26/03 20.98%
Active Probe Area = 434 cm'. The detector and rate meter Model 2221 (434cm2) proportional 0-500,000 & one Log 10-30 cpm are combined and mounted on a roll around cart. The S/N 97287 Alpha detector 50-500,000 instrument features a static-now system, quick connects, a S/N 083293 (CPM)
Scan MDA = 66 dpm/I00 cm2 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 09/26/03 31.17%
Active Probe Area = 434 cm'. The detector and rate meter Model 2221 (434cm2) proportional 0-500,000 & one Log 1800-2400 cpm are combined and mounted on a roll around cart. The S/N 84459 Beta detector 50-500,000 instrument features a static-flow system, quick connects, a S/N 086215 (CPM)
Scan MDA= 481 dpn'I00 cm' 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 08/13/03 35.82%
100 cm3 gas flow proportional counter Model 2221 100 cm' proportional 0-500,000 & one Log M4DA = 244 dphtl0cmt)
S/N 84423 Beta detector 50-500,000 A
S/N 119444 (CPM) l Ludlum Ludlum Model 44-10 Four Ranges 04/03/03 NA 19-21 tR/hr contact (Asphalt) 2 inch x 2 inch Nal (TI) scintillator. Used for measuring Model 3 Nal (TI) Scintillator 0-500 ptRlhr 12-13 pR/hr contact (Soil) external dose rates on the surface and at one meter.
S/N 153311 Ganmma Detector 11-19pR/hr@ Im (Asphalt)
S/N 155594 12-l2ptRihr e Im(Soil)
Ludlum Ludlum Model 43-64 Four Ranges 10/29/03 21.77%
1 -20cpm (All Surfaces)
Active Probe Area =50cm2 Model 12 Alpha Scintilator 0-500,000cpm MDA=184dpm/lOOcm2 Used for Alpha surveying S/N 91056 ZnS (Ag)
S/N CanberraLow Level Gas Flow N/A As needed 30%
Varies with Sample Canberra Model 2404 Low Level a/P gas flow proportional CE/O Counter Proportional Detector counting system used to count wipes for removable Model 2404 contamination. Results are usually reported as dpm/lOOcm'.
Canberra Gamma Iligh Purity N/A As needed Varies with Varies with Sample Gamma Spectroscopy MCA system using a high purity Spectroscopy System Germanium Detector Sample Germanium detector.
T-3
or-(--
1' a--
t-(
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r( E
[i 7-T-L
(-r (1-
¶7 l
ND = Energy peak not identified T-4
v- -
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t r
T-5
(77 CIT (7
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177 r.
(77 tIT7 (C-_
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(7 g -
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Table 4 (continued): General Atomics Gamma Spectroscopy Results of Background Surface Soil Samples September 24, 2002 Sample Locations:
Xi Sorrento Valley Road near sample location ST65 on the hillside -1 mile from Building 37.
X2 Sorrento Valley Road near Carmel Mountain Road junction on steep cliff.
X3 Sorrento Valley Road in Los Penasquitos Preserve -2 miles from Building 37.
X4 Sorrento Valley Court at the end of the road in the field.
X5 Roselle Street, East of sample location ST64 1/2 mile from Building 37 (collected on the hillside)
X6 Roselle Street, East of sample location ST64 -1 1/2 mile from Building 37 (collected on hillside).
X7 Lusk Boulevard, from the hillside - 1 /2 miles from Building 37 (collected on the hillside).
X8 Vista Sorrento Parkway, -
1/2 mile from Building 37 (collected on the hillside).
X9 Callahan Road, -
2 mile from Building 37 (collected on the hillside).
X10 Eastgate Mall road, -3 miles from Building 37 (collected in a field).
Xi Creek Road (North County).
X12 Canyon de Oro (North County).
X13 Palomar (North E County).
X14 Deer Springs Rd. (North County).
X15 Rice Canyon Rd. (North County).
X16 Las Pulgas Rd. (North County).
X17 Boderfield Park (South W County).
X18 Otay Mesa (South E County).
X19 Sunset Cliff (South W County).
X20 Marion Bear Park (South County).
X21 Mission Valley (South County).
X22 Santee (South E County)
X23 Ramona (East County).
X24 Via Abitura (San Diego).
X25 Black Mtn. Park (San Diego).
X26 Park Village (San Diego).
X27 Harris Plant Rd. (San Diego).
X28 Daley Center Dr. (San Diego).
X29 Harbison Canyon (East County).
X30 Apple St. (East San Diego).
T-6
-Table 5: Building 25 Site Wipe Survey Results Sample Number
-a Activityin dp100cm2 t f3Activityindpmll 00cm2
- -010
- l
<20
<20 2
<20
<20 0 -
3 a;-
<20
<20 4
<20
<20
- -: -^E: 0t^5-
- -::<: - -<20
<20
<20
<20 T-7
t' C.--_- (r R e
a 1rc t-C
[.-
Cz cc r-r--
t-Cn a-r.-
T-8
(r-r-:
.r.r.-
n-E-= u--
M7
- r.
rr Bra.
f O
7 ET7
= r L ri:
V T-9
El[-
(7 El 7
177.
a777x Ra r
(--I A=
7=
_ r l F-
- 1.
ND means not detected.
- 2.
Sample Numbers S-4 = Surface (0-6") soil samples, Sample Numbers SS-# = Sub Surface (6-12") soil samples.
- 3.
Average Minimum Detectable Activities (MDAs):
U-238 = 1.37 pCi/g (63 keV peak)
Co-60 = 0.13 pCi/g (1173 keV peak)
U-235 = 0.12 pCi/g (186 keV peak)
Th-228 = 0.17 pCi/g (238 keV peak)
Cs-137= 0.10 pCi/g (662 keV peak)
Th-232 = 0.38 pCi/g (911 keV peak)
T-10
Figure 1: Torrey Pines (Main) Site Land Areas HOT CELL LAND TORREY PINES NORTHEAST BUILDING 25 LAND AREA TORREY PINES EAST
Figure 2: Building 25 Site Land Area and Adjacent Land Areas 41, iVVA LINAC LINAC LAND NORTH LAND HOT CEL LAWO TFF UTILITY CORRIDOR The Building 25 Site Land Survey Area overlaps onto the LINAC Land and LINAC North Land Areas
Figure 3: Building 25 Site Alpha Scan Locations and Results I
2 3
S I........................................................................
................................................................................................ I...................................
0M~
6 CD 0
0) 0T CD 07 0D 0
0T 0o 0
0 0o I
C 00
?
0~~~~~~~~~~C)
.0 ow.0 C
SOa)
N CD 0D
~Sphat -0 F~~~~~~~~s~~~id 25 1,
~~~~~~~~~~~97287 221 1O~ns I 0X1Om ri Suyr I
?
209
,DI=
434 l Comments WmXilm Grid Sk l
Date:
~~~~~04/04/2003 ignat1ure:
Will Schuck Scan MDA Data Ave. Background 10-30 cpm X
3 Scan MDA, Concrete 66 dpmVIO0 cm2 All Readings in CPM Background = 10-30 CPM
Figure 4: Building 25 Site Beta Scan Locations and Results 1
2 3
10, 60 00 C Co A' N
6 0 Nq N 001 60 0I 00 C>C 0C)
I 5 "
C4 NI" N
0)
C0 0
........................................................................ I CN 0) 0D 0
0O ZN 0
N ZN 0
01 0~
0 C 0D 0(N CD 011 N~
0~
0O 0) oil 00 N
6 0 N~
'Sonalt --
- 4 I--- - ----
Allegheny 84459~~fldz2
,~~~~~~~ 00~~22 OR a J a~~
s IF - *T v
~~~~~~434 rmmmtns, IOmX1Om Grid iEX Dat ~ ~ ~
40420 Signaturem Will Schuck Scan MDA Data Ave. Background 1800-2400 cpm X
0.3 Scan MDA, Concrete 481 dpmll 00 cm 2
.All Readings in CPM
Background
1800-2400 CPM
Figure 5: Building 25 Site Fixed Alpha and Beta Locations and Results and Wipe Locations 11- VI NN A(V 5
Fixed MDA Data Ave. Background 20 cpm, Asphalt a
Fixed MDA, 184 dpmlOO cm2 Asphalt a Ave. Background P 1422 cp2m, Asphalt Fixed MDA, 244 dpmI00 cm2 Asphalt_
_____244 Building 25 L222 1 L:12 Senil nkr 84423 91056 D b e
- o08/13n2o3 10o29n203
-};Eft 35.82%
21.77%
.A
.Alpha
. XP Nuberl 119444 1
CommentS:
2mX2m Grid Survey Date 05t01t2003 Signature Will Schuck 0
Wipe Locations XX Alpha Reading in CPM IS Beta Reading in CP2M 0
<20 1098 1135 <20 1159
<20 2 0 F<2 23
<20
L Figure 6: Building 25 Site Exposure Rate Scan Measurement Locations and Results 1
2 I
_Asphalt I,
13-1 3
5
- i....................................................................................
l -
~~*~
13-16 13-16 1-15 13-16 I
+
1-I I
14-16 15-17 14-16 11-15 14-16 14-16 15-17
.13-15 16-15 13-17 13-15
.13-15 13-15 15-18 15-18 E
r I
1 co0 c) 0 Cb Cb 15-18.
I Asphalt
'1
'-CD, 0CD CD 16-18 15-17C CC LI.
1 5.1 I 1.
__1 _
tz.
C to l
C 6 c
co 1
co I o CD c
-~~~~~~~~~~~
U)
C;)
I;0_
15-17 k 15-17 15-17 :
\\
I 0C'J
- 0 co CD I M 25 Model-3 153311
- WOY23003 W~A 15-17 I.,~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
L 1
_L Fence Line I
lb All Readings in MicroRem/Hour icroJ L i Asphal ce n i
I Gamma 155594
- s_*M emtnougm t = 19-21 te= 14-15
=12-13 Comments 1OmX1Om Grid SeY DaL 03131/2003 Sintr:
Will Schuck Concrel Soil
Figure 7: Building 25 Site Fixed Exposure Rate Measurement Locations and Results 1
1 2
3 5I
.Asphalt Measurements taken at 1 meter from the surface, at 2m intervals.
All results are in MicroRem/Hour.
For clarity Background = 11-19 MicroRemlhour @ Im (Asphalt), 12-12 MicroRemlhour I m (Soil).
177 W.
(77 FlY.
(77 1777' KY (77 1177 1
(-
I7-
'f_
7-(-7
-(7 T
(__
r -
F -
-1,
11 17--
[7I Figure 8: Building 25 Site Soil Sample Locations and Exposure Rate Measurements at Sample Locations A
1 B 24 3
4 4
5 10 9 0 18 2
3 I
....... I.................
= 0-6" Surface
= 0-6"surface & 6"-12" subsurface 270 34 re = 0-6" Beneath Asphalt I
11*
200 28*
8 17.
26 0
33 35 36 12 21 29 w
PI Ii 40 3
3 E-01 ki, j:iO*
Model-3 Comments.
10mX10m Grid Survey Date:
03/26/2003 at e lill Schick 70 160 25 0
32.
13*
226 30 37 31 6
15 24 I
23 14 Location Contact 1 Meter Location Contact 1 Meter 1
15 14 21 18 16 2
14 14 22 15 15 3
15 14 23 16 14 4
15 14 24 15 13.
5 15 14 25 16 15 6
15 14 26 19 17 7
15 14 27 15 14 8
16 15 28 19 17 9
14 14 29 17 15 10 17 15 30 17 15 11 15 14 31 NA NA 12 17 15 32 17 15 13 16 14 33 NA NA 14 16 15 34 NA NA
-ID in 14 NrAA NlA I15 15Z
-14 3.11 NA NA
+
4 16O I (
15 36 NA NA Note: Exposure Rate Measurements only taken at soil sample locations on soil surfaces 17 17 16 37 NA I
NA 18 16 15 38 NA I
NA 19 16 14 39 NA I
NA 20 16 14 40 NA NA
General Atomics' Final Radiological Survey Report For The Former Building 25 Land Area Appendix A The Former Building 25 Land Area, Final Survey Plan A-1
Page 1 of3 1
February 24, 2003 Prepared By: W. T. LaBonte Approved By:
C W o A_
)
L. Q. Gonzales Final Radiological Survey Plan for the Former Building 25 Land Area i
This Final Survey Plan is for land formerly occupied by Building 25. Building 25, and it's contents, were completely dismantled and packaged as low level radioactive waste for disposal at a licensed burial facility. This parcel of land, which is approximately 4720 ft (439 m2 ), is bordered by the U
LINAC and LINAC North Land Areas which were previously released to unrestrictive use. See Figure-I for the former Building 25 Land Area location and Figure-2 for the Land Area boundaries, dimensions, grid layout, and soil sample locations.
This Final Radiological Survey Plan covers only open land areas, a small portion of which is paved with asphalt. All connections to the GA sewer system have been removed.
L History and Classification The former building 25 housed the liquid waste processing equipment used to decontaminate radioactive liquids collected at various radiological facilities at GA prior to disposal into the sewer system in accordance with State and NRC licensing requirements.
During decommissioning activities, building 25 was completely dismantled and packaged for disposal as low level radioactive waste at a licensed disposal facility. The sewer line previously connected to the GA main sewer system was excavated, removed and disposed of as low level radioactive waste Ui during the remediation activities conducted on the main sewer system in 2002. The remediation of, and final surveys conducted on, the GA main sewer system will be the subject of a future report.
L There were no known spills of radioactive material on the land that surrounded building 25, however, due to its proximity to building 25 and the history of the building's use, the entire land area is classified as a Suspect Affected Area.
Survey Objectives and Responsibility The purpose of performing a final survey is to demonstrate that the radiological conditions within the Building 25 Land Area satisfy the NRC and State of CA guidelines for release to unrestricted use. The objectives include (1) to show that the average surface contamination levels for each survey unit are within the authorized value, (2) to show that the maximum residual activity ("hot spot" area) do not exceed three times the average value in an area up to 100 cm2, (3) that a reasonable effort has been made to clean removable contamination and fixed contamination and (4) that the exposure rates in W:\\Building 25.wpd A-2
Page 2 of 3 L
occupiable locations are less than 10 VlR/hr above background measured at 1 meter above the surface.
Samples will be counted in the Health Physics laboratory (onsite). Surveys will be taken only by L
qualified Health Physics Technicians having a minimum of 3 years Health Physics Technician experience. The survey and final report documenting the survey will be performed by GA's Health Physics group.
Release Criteria (per GA Site Decommissioning Plan)
ConcreteAshalt Surface Release Criteria The NRC release criteria-for Sr-90, which is conservatively selected for beta measurements due to the potential exposure of this area to Sr-90, is:
1,000 dpm /100 cm, averaged over a 1 m area 3,000 dpm /100 cm2, total, maximum in a 100 cm2 area 200 dpm/100 cm2, removable activity The NRC release criteria for Alpha activity is:
5,000 dpm /100 cm', averaged over a 1 m2 area 15,000 dpm /100 cm2, total, maximum in a 100 cm2 area 1,000 dpm/100 cm, removable activity Exposure Rate Measurements L
The guideline value for exposure rates measured at 1 m above the surface, is 10 pR/hr above background.
L Alert Levels i !
Alpha Alert Values If the following "alert levels" are exceeded, notify HP Management so an evaluation can be performed and to evaluate if decontamination is required.
i
> 100 cpm alpha using the large area (434 cm2) probe (check area with a hand-held alpha meter).
> 60 cpm using a 50 cm2 hand-held alpha probe (- 600 dpm/100 cm2)
Beta Monitoring
>250 cpm above the appropriate background using the 434 cm 2 probe.
>100 cpm above the appropriate background using the 100 cm2 probe.
>40 cpm above background using a portable GM detector. (Note: this meter should ONLY be used in areas the 434cm2 or 100 cm2 probes will not fit).
WABuilding 25.wpd A-3
Page 3 of 3 Exposure Rate Measurements
> 25 p.R/hr at surface
? 20 pR/hr at 1 m i,
Documentation Every survey conducted must be documented on a daily basis on a drawing showing the approximate locations surveyed. Include the results (including units), the technicians signature, date, instrument(s) used (including model and serial number of both the ratemeter and the detector), calibration due date,
%-efficiency, background readings (if applicable) and any other applicable information.
i Final Radiological Surveys Planned for the Building 25 Land Area Type of Survey/Activity l
Suspect Affected Area Gridding Required?
Yes Asphalt or Concrete Surfaces (1) 100 %
(Scan w/ 434 cm 2alpha probe).
Asphalt or Concrete Surfaces (
100%
(Scan w/ 434 cm' beta probe).
Minimum number of I measurement per 4 m2, or, Measurements (2) (3)
I measurement every -2 m Alternate between (1) a wipe, (2) an alpha fixed measurement and (3) a beta fixed measurement on all asphalt or concrete surfaces.
Soil samples Take surface (0-6") soil samples in a 5m triangular grid system in each Om x lOin grid and(l) 6" to 12" sub-surface sample in each grid. See Figure 2 for details. If soil sample results are greater than 50% of the approved release limit, the number of samples in each grid will be increased.
[R/hr Readings (Scan Survey) 100% scan on all surfaces, detector held -1 " from surface l.LR/hr Readings (Fixed I every 2m Plus I at each soil sample location.
Measurements c1 Im from surface)
(I)
Clean surfaces, debris or dirt removed.
(2)
For the fixed measurements:
For a measurements; use either the hand held alpha counter (minimum of -6 second count).
Document all readings in cpm.
For P measurements; take a 2 minute count using the 100 cm2 gas flow proportional detector (beta) with the Model 2221 ratemeter.
Document all readings and mark on a drawing the locations the readings were taken.
For wipes, analyze each 100 cm2 wipe for a and P activity.
(3)
A "measurement" is either (I) a "fixed" radiation measurement representing total activity or (2) a wipe (removable activity).
WABuilding 25.wpd A-4
and~
~
t -
(----
F t>
of Age 1-4 r
- -=e i C C I t,- -
V C,
v T1--- r T
C N
vIt SureY conducted by: W SChUcK Dates: o2-i9 l
L General Atomics' Final Radiological Survey Report For The Former Building 25 Land Area Appendix B Sr-90 Analysis Summary Li I'
B-i
Building 25 Site Sr-90 Analysis Summary Because GA no longer has Radio-Chemistry Analysis capabilities, and, Sr-90 does not emit a gamma ray, three (3) soil samples were sent to the Severn Trent Laboratories for Sr-90 analysis.
Two (2) with the highest Cs-137 gamma spectroscopy analysis results and One (1) with the highest Uranium gamma spectroscopy results. The reasons for selecting these three (3) samples are; Cs-137 and Sr-90 are both fission products (Cs-137 is the only gamma emitting fission product identified in the gamma spectroscopy analysis performed by GA), and, U-235 is a fissionable isotope of Uranium.
A summary of Sr-90 analysis results for the samples sent to the Severn Trent Laboratories are as follows (see the attached analysis results provided by Severn Trent Laboratories for details):
1<. &7Sil Samle ID JK+. ~~Sr-9OConcenration GA's Gamma~ pec 25~~~Si~~~Fiii~~~~V~~
~~
iesn pfi
',D' I
- Dam oogicd1 eportor 16cationsJ) -
5 5
Res;u=<<,tsi.~-
in pci '/g'-.
b--=,1.;,,,-~,
S-17 0.67 +/- 0.39 Cs-137 0.50 +/- 0.09 Minimum Detectable Concentration (MDC) 0.57 S-21
<MDC (0.49)
Cs-137 0.67i 0.10 S-35
< MDC (0.55)
U-235 = 0.32 0.12 U-238 = 3.62 +/-2.69
==
Conclusion:==
Residual Strontium-90, when present in the soil at the Building 25 site land area, is far below the approved release criteria identified the GA Site Decommissioning Plan.
B-2
,TL ST.
LOUIS 4
GENERAL ATOMICS Client Samnle ID: B-25 S-17 Savern Trent Laboratories - Radiochemistry
- Lab Sample ID: F3E130184-001 I i Work Order:
FNLWN I !
1Matrix:
COMP Date Collected:
Date Received:
04/03/03 0800 05/13/03 0845
'otal Uncert.
Prop Analyuiu parnamter Result 9Nel (2 a+/-)
Y2C Date Date Datch I Y1d SR-90 BY arPC DOE 7500-SR MOD PCI/g 7500-SR MOD strontitu 90 0.67 J
0.39 0.57 05/21/03 06/03/03 3141396 91 L-J NOTE(S)
Data are incowplete without the came narrative.
i I MDC i deterzined by instrument performance only.
I Bold results are greater than the MDC J
Result is greater than wepl-detection limit but le than stated reporting limit.
LiOT# F3E130184 B-3
iSTL ST. LOUIS GENERAL ATOMICS Client SamDle ID: B-25 S-17 DUP Severn Trent Laboratories -
adiochemistry Lab Sample ID:
1, Work Order:
i-Matrix:
F3E130184-001X FNLWN COMP Date Collected:
Date Received:
04/03/03 0800 05/13/03 0845 Total uncert.
121~
Prop Analysis ult
¶ teh Yldl v
Parane-tr C
SR-90 Y OrPC DOE 7500-SR MOD pCi/g 7500-SR MOD Strontium 90 0.65 J
0.36 0.52 05/21/03 06/03/03 3141396 98 NOTE ()
L--
D-ta trs incomplete witbot ths cae narratie.
i I mDC in determined by instrment performance only.
II Bold results are greater than te tMC J
Result i greater than wa*le detection limit but le~s tan stated reporting limit.
I 3
LLOT# F3E130184 B-4
. STL ST.
LOUIS GENERAL ATOMICS Client Samile ID: B-25 S-21 Savern Trent Laboratories - Radiochemistry Lab Sample ID: F3El30184-002 Work Order:
FNLW4 Matrix:
COMP Date Collected:
Date Received:
04/03/03 0830 05/13/03 0845 Total uncurt.
Prep Analysis Parameter Result
- Qual (2 0+/-)
3= -
Date Date match Yld %
SR-90 BY GC DOE 7500-SR MOD pCi/g 7500-SR MOD Strontium 90 0.35 U
0.31 0.49 05/21/03 06/03/03 3141396 96 Lj NOTE (S)
Data are incomplete without the case narrative.
MDC i determined by nstrument performance only.
Bold results ae greater than the MDC 1
Result i leass than the sample detection limit.
LLOT# F3E130184 B-5
5STL ST. LOUIS GENERAL ATOMICS Client SamDle ID: B-25 S-35 Severn Trent Laboratories - Radiochemistry Lab Sample ID:
Work Order:
Matrix:
F3E130184-003 FNLW6 COMP Date Collected:
Date Received:
04/10/03 0800 05/13/03 0845 Total encert.
(2
+/-)
Result Qual prop Analysis Date Date Batch Yld %
Pnrainter YDC sR-90 BY Gyc OE 7500-SR MOD Strontium 90 0.15 pCi/g 7500-SR MoD 05/21/03 06/03/03 3141396 U
0.33 0.55 94 U
- NO:
Dae. xe incosplete ithout the case narrative l :
NDC ia dtermined by nstrunen prformance only Lt Eold results are greater than the XDC U
Reault lee t
the alo detection lt L:OT# F3E130184 B-6
- STL ST.
LOUIS MEITHOD BLANK REPORT Severn Trent Laboratories - Radiochemistry Client Lot ID:
Matrix:
F3E130184 SOLID otal Uancrt.
Lab Sple r
prop alysim Piaramter Result Quul (2 a+/-)
Mm Date Date Batch rid S SR-90 BY GFPC DOZ 7500-SR MOD pCi/g 7500-SR MOD F3Z210000-396B Strontium 90
-0.02 U
0.31 0.54 05/21/03 06/03/03 3141396 97 Lj NO=(B)
Data ar ine lts without the cm..
arrativ.
MDC is dtez=ined using instrument performance only Bold results are reater than the MDC U
Result lse than the sample detection limit.
LLOT# F3E130184 B-7
iSTL ST.
LOUIS Ls Client Lot ID:
L Matrix:
L Parameter DUPLICATE EVALUATION REPORT Severn Trent Laboratories - Radiochemistry F3E130184 Date Sampled:
04/03/03 SOLID Date Received:
05/13/03 BMILZ Rugult Total rucert.
(2e +/-)
Total EMLXCMTIK ancert.
S TId Reault (2
+jr )
QC ample D
S Yld Precision sR-90 BY GPC DOE 7500-SR MOD pCi/g 7500-SR MOD F3E30184-001 Strontium 90 0.67 J
0.39 91 0.65 J
0.36 98 4
%RPD Batch 3141396 Sample) 3141396 Duplicate)
NOTE(S) i Data are jncoplete without the came narrative.
i 'Clcultion ara performed before rounding to avoid rund-off error in calculated results J
Result in greater than sample detection limit but less than stated reporting limit.
LT# F3E130184 B-8 11
STL ST.
LOUIS L
L Client Lot ID:
Matrix:
L Laboratory Control Sample Report Severn Trent Laboratories - Radiochemistry F3E130184 SOLID oeal Lab 8aw~1 ID Uncort.
OC Control Paratar Spike Amount Result (2 a*/-)
M xld S Rc LAmito SR-90 BY GFPC DOZ 7500-SR MOD pcl/g 7500-SR MOD F3E210000-396C Strontium 90 10.4 10.5 2.2 0.5 99 101 (60 - 140)
Batch S2 3141396 Analysis Datet 06/03/03 L
L L
NOTE(31 30)0 i determined by inatruonnt performanee oly ti l
Calculations are performed before rounding to aoid rouad-off error in calculated results LOT# F3E130184 B-9 10
II J
J iI Li j
I~
~~~~~
j Li lil I
G ENEL ATOMICS
.O. BOX 85608 SAN DIEGO, CA 92186-5608 (858) 455-3000 Li