ML031000195
| ML031000195 | |
| Person / Time | |
|---|---|
| Site: | University of Virginia |
| Issue date: | 04/04/2003 |
| From: | Mulder R University of Virginia |
| To: | Hughes D NRC/NRR/DRIP/RORP |
| References | |
| Download: ML031000195 (207) | |
Text
{{#Wiki_filter:UNIVERSITY OF VIRGINIA NUCLEAR REACTOR FACILITY U.S. MAIL ADDRESS STREET ADDRESS P.O. Box 400322 675 Old Reservoir Road Charlottesville, VA Charlottesville, VA 22903 22904-4322 Telephone 434-982-5440 Fax 434-982-5473 April 4, 2003 Docket 50-396 United States Nuclear Regulatory Commission Mail Stop 012-G13 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2783 Attention: Mr. Daniel E. Hughes, Project Manager Operating Reactor Improvements Program Subject Transmittal of Evaluation of Radiological Characterization Results Relative to Termination of NRC License R-123, March 2003
References:
- 1. Order Authorizing Dismantling of Facility and Disposition of Component Parts - University of Virginia CAVALIER Research Reactor
- 2. Docket 50-396
Dear Mr. Hughes,
We are pleased to transmit the "Evaluation of Radiological Characterization Results Relative to Termination of NRC License R-123," March 2003, prepared for the University of Virginia by CH2M HILL and its subcontractor, Safety and Ecology Corporation. This report serves as the basis by which we ask the United States Nuclear Regulatory Commission to grant termination of NRC Facility License No. R-123. The University has completed physical decommissioning activities for the CAVALIER reactor. Upon decommissioning of the CAVALIER, radiological surveys were performed to confirm that the requirements of NRC Regulatory Guide 1.86 had been met. The room previously occupied by the CAVALIER has been transferred to and is being presently maintained with restricted access as a part of the University of Virginia Research Reactor (UVAR) Facility under Amended Facility Operating License No. R-66. Release of the area previously occupied by CAVALIER to the UVAR Facility conforms with the Change Evaluation approved by the University Reactor Decommissioning Committee on May 16, 2002, and subsequently reviewed by NRC staff during routine inspection of the facility.
April 4, 2003 Page 2 If you have any questions regarding this transmittal, please contact me at (434) 982-5446. Robert Mulder
Enclosure:
Evaluation of Radiological Characterization Results Relative to Termination of NRC License R-123, March 2003 c: Ralph Allen, Chair Reactor Decommissioning Committee Stephen Holmes, NRC
EVALUATION OF RADIOLOGICAL CHARACTERIZATION RESULTS RELATIVE TO TERMINATION OF NRC LICENSE R 123 Prepared for the University of Virginia Reactor Facility Decommissioning Project Prepared by CH2MHILL 151 Lafayette Drive, Suite 110 Oak Ridge, TN 37830 With assistance from Safety and Ecology Corporation 2800 Solway Road Knoxville, TN 37931 March 2003 Infrnafon Copy
EVALUATION OF RADIOLOGICAL CHARACTERIZATION RESULTS RELATIVE TO TERMINATION OF NRC LICENSE R.123 Prepared for the University of Virginia Reactor Facility Decommissioning Project March 2003 Client Approvals: QO9EP SLS QESH Date 312 -7 Technical Director Date CH2MHILL 151 Lafayette Drive, Suite 110 Oak Ridge, TN 37830
EVALUATION OF RADIOLOGICAL CHARACTERIZATION RESULTS RELATIVE TO TERMINATION OF NRC LICENSE R-123 Prepared for the University of Virginia Reactor Facility Decommissioning Project March 2003 Date ByPe t (.i6^ 0- (-0 3 ES&H & QA Director Date Project Engineer a D Date Foject Manager tl Date CH2MHILL ill
Contents
- 1. Introduction............................................................................................................................ 1-1
- 2. Summary of Characterization Results ........................................... 2-1
- 3. Data Assessment and Evaluation ........................................... 3-1
- 4. Conclusion.............................................................................................................................. 4-1
- 5. Work Cited ............................................ 5-1 Tables 3-1 Summary of Direct Beta Surface Activity Measurements ........................................... 3-1 Appendix A Cavalier Facility Characterization Report Attachment 1 Instrumentation Information Attachment 2 Characterization Survey Data EVALUATION OF RADIOLOGICAL CHARACTERIZATION RESULTS RELATIVE TO TERMINATION OF NRC LICENSE R-123 ill
- 1. Introduction The University of Virginia Reactor Facility contains two reactors: the University of Virginia Reactor (UVAR) (License No. R-66 to operate at a power level of 2 MWatts) and the smaller CAVALIER (License No. R-123 to operate at a power level of 100 Watts). Both of these reactors have ceased operation and fuel has been removed and transferred off-site. The decommissioning plan for the CAVALIER (Ref. 1) was submitted to the NRC in February 1990 and was approved by the NRC in February 1992 (Ref. 2). That plan authorized the radiological contamination levels in NRC Regulatory Guide 1.86 (Ref. 3) as the decommissioning criteria.
The decommissioning plan for the UVAR (Ref. 4) was approved by the NRC in March 2002 (Ref. 5). The approval authorized the radiological screening levels from the NRC DandD Code as the decommissioning criteria for the UVAR site. The authorization also required that the CAVALIER facility would first be decommissioned to satisfy Regulatory Guide 1.86 and would then be integrated into the UVAR site. The UVAR site would be decommissioned in accordance with the approved UVAR decommissioning plan. GTS Duratek performed an initial characterization of the entire facility, including the CAVALIER and the environs, beginning in July 1999. Results of that characterization effort are presented in the characterization survey report (Ref. 6). Findings of this site characterization were that the accessible surfaces of the CAVALIER facility were below the characterization release criteria and free of hazardous material contamination concerns. However, at the time of the initial characterization, some potentially impacted locations were not accessible for survey. For this reason it was necessary to conduct further characterization of such locations, as the decommissioning effort progressed and such characterization became possible and practicable. Decontamination and disassembly of the CAVALIER facility was performed during June and July 2002. During August through November 2002, Safety and Ecology Corporation (SEC) of Knoxville, TN conducted a radiological characterization survey of the dismantled CAVALIER facility. The purpose of this characterization survey was to provide a comprehensive radiological evaluation of the dismantled facility, including identifying any radiological conditions that might prevent termination of the license. The characterization survey was designed and implemented such that, if conditions requiring decommissioning actions were not identified, the findings could be used for final status survey purposes to demonstrate that the facility satisfies radiological conditions for termination of the NRC license. Appendix A provides a description of the characterization survey design and results. In summary, in accordance with the NRC-approved Decommissioning Plan, the survey was designed to demonstrate compliance with the radiological surface contamination guidelines established by Regulatory Guide 1.86, Termination of Operating Licensesfor Nuclear Reactors. For the potential radionuclide contaminants at this facility, the applicable above-background guideline levels are: EVALUATION OF RADIOLOGICAL CHARACTERIZATION RESULTS RELATIVE TO TERMINATION OF NRC LICENSE R-123 1-1
CH2MHILL
- 5,000 beta dpm/100 cm2 average total activity.
- 15,000 beta dpm/100 cm2 maximum total activity.
- 1,000 beta dpm/100 cm 2 removable activity.
- 5 pR/h average exposure rate @1 m above the surface.
- 10 pR/h maximum exposure rate @1 m above the surface.
Also in accordance with the Decommissioning Plan, the guidance in draft NUREG/CR-5849, ManualforConducting RadiologicalSurveys in Support of License Tennination, (Ref. 7) was the basis for design, implementation, and evaluation of the survey. The findings of the characterization survey indicate that the conditions of the CAVALIER facility satisfy the applicable radiological guideline levels. Based on those findings, the characterization data have been evaluated for final status application, following the guidance of NUREG/CR-5849. This report describes the methods and results of that evaluation. EVALUATION OF RADIOLOGICAL CHARACTERIZATION RESULTS RELATIVE TO TERMINATION OF NRC UCENSE R-123 1-2
- 2. Summary of Characterization Results Gamma and beta surface scans identified small areas of elevated direct surface activity on the floor and lower wall of the Reactor Pit, on the drain in the bottom of the Reactor Pit, and on the outlet of facility piping to the storm drain. The maximum levels were approximately 1.5 to 2 times background levels. Scans did not identify additional facility locations impacted by reactor operations.
Total surface activity levels were all within the acceptable level of 5,000 dpm/100 cm 2 . The highest level measured was 2,288 dpm/100 cm 2 on insulation from the air handling unit; gamma spectrometry indicated this was due to naturally occurring radionuclides, rather than those of reactor origin. The next highest level was 1,883 dpm/100 cm 2 on the lower wall of the Reactor Pit; gamma spectrometry also identified the source of activity at this location as naturally occurring radionuclides. The highest removable activity level was 62 dpm/100 cm2 on the inside of the air handling unit. Total and removable surface activity measurements on all surfaces were typically less than the detection sensitivities of the procedures. The maximum dose equivalent rate measured in the CAVALIER facility was 10 lprem/h; this is 6.0 prem/h above the minimum dose equivalent background level of 4 prem/h (about 4.5 1 iR/h). The average in the facility was 7.7 jirem/h, which is 2.2 prem/h (about 2.6 pR/h) above the average background level of 5.5 prem/h for this portion of the building. EVALUATION OF RADIOLOGICAL CHARACTERIZATION RESULTS RELATIVE TO TERMINATION OF NRC UCENSE R-123 2-1
- 3. Data Assessment and Evaluation Classification by contamination potential as "affected" is appropriate from the standpoint of historical use but conservative, considering the maximum activity measured is less than 50% of the guideline value. No investigation or reclassification of surfaces was required.
Average and standard deviation were calculated for direct beta surface activity measurements in all areas. Upper confidence levels (UCL) were also calculated using the following equation from NUREG/CR-5849: UCL = X + tif, 9s%(S/n0f5) Values of t were obtained from Appendix B of NUREG/CR-5849. Results are summarized in Table 3-1. Table 3-1 Summary of Direct Beta Surface Activity Measurements Survey Surface Total Beta Activity Level (dpm/l00 cm 2 ) Area Maximum Average Std. Dev. n* UCL I Reactor Room Floor 956 130 242 40 194 2 Room Walls 1344 441 305 32 533 3 Reactor Pit 1883 735 476 40 862 4 Ceiling/Overhead 650 387 213 18 474 5 Laboratory Bench 635 28 204 14 125 6 Cage walls 295 125 101 16 169 7 Air Handling Unit 2288 597 721 8 1071
- n = number of data points (measurements)
No total surface beta activity measurement exceeds the maximum guideline of 15,000 dpm/100 cm2 , and the total surface activity UCL's for all areas are well below the average guideline level of 5,000 dpm/100 cm 2 . Although the number of measurements for surfaces other than the floor, walls, and Reactor Pit is less than the 30 recommended by NUREG/CR-5849 for statistical testing purposes, each measurement can be individually compared with the guideline level to evaluate the conditions, relative to meeting license termination criteria. Removable surface activity levels are well below the guideline of 1,000 dpm/100 cm 2 . Maximum and average exposure rate levels are also well below the guideline values of 10 pR/h amd 5 -PR/h, respectively. EVALUATION OF RADIOLOGICALCHARACTERIZATION RESULTS RELATIVETO TERMINATION OFNRC UCENSE R-123 3-1
- 4. Conclusion Based on these results the radiological conditions of the CAVALIER facility satisfy the Regulatory Guide 1.86, NUREG/CR-5849, and CAVALIER Decommnissioning Plan requirements for release from licensing restrictions. It is requested that License No. R-123 be terminated and the former CAVALIER facility be combined with the University of Virginia Reactor Facility under License No. R-66, for eventual evaluation of the entire facility in accordance with the UVAR Decommissioning Plan.
EVALUATION OF RADIOLOGICALCHARACTERIZATION RESULTS RELATIVETO TERMINATION OFNRC UCENSE R-123 4-1
- 5. Works Cited
- 1. Decommissioning Plan for the University of Virginia 100 W CAVALIER Reactor, and Application for the Termination of the CAVALIER Operating License, University of Virginia, February 1990.
- 2. Order Authorizing Dismantling of Facility and Disposition of Component Ports-University of Virginia Cavalier Research Reactor, letter from A. Adams (NRC) to R. Mulder (UVA),
February 3,1992
- 3. Regulatory Guide 1.86, Termination of Operating Licenses for Nuclear Reactors, NRC, June 1974.
- 4. University of Virginia Reactor Decommissioning Plan, GTS Duratek, February 2000.
- 5. University of Virginia Reactor - Amendment Re: Decommissioning Plan Approval, letter from A. Adams (NRC) to R. Mulder (UVA), March 26,2002.
- 6. Characterization Survey Report for the University of Virginia Reactor Facility, GTS Duratek, March 2000.
- 7. Manual for Conduction Radiological Surveys in Support of License Termination, draft NUREG/CR-5849, June 1992.
- 8. Evaluation of Surface Contamination - Part 1: Beta Emitters) Maximum Beta Energy Greater Than 0.15 Mev) and Alpha Emitters, IS-7503-1, First Edition 1988-08-01.
- 9. Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), NUREG-1575, June 2001.
- 10. Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions, NUREG-1507, December 1997.
EVALUATION OF RADIOLOGICALCHARACTERIZATION RESULTS RELATIVETO TERMINATION OFNRC LICENSE R-123 5-1
APPENDIX A CAVALIER FACILITY CHARACTERIZATION REPORT EVALUATION OF RADIOLOGICALCHARACTERIZATION RESULTS RELATIVETO TERMINATION OFNRC LICENSE R-123
1.Introduction The University of Virginia Reactor Facility contains two reactors: the Research Reactor UVAR (License No. R-66 to operate at a power level of 2 MWatts) and the smaller CAVALIER (License No. R-123 to operate at a power level of 100 Watts). Both of these reactors have ceased operation and fuel has been removed and transferred off-site. The decommissioning plan for the CAVALIER was approved by the NRC in February 1992; that plan authorized the radiological contamination levels in NRC Regulatory Guide 1.86 as the decommissioning criteria. The decommissioning plan for the UVAR was approved by the NRC in March 2002; that plan authorized the radiological screening-levels from the NRC DandD code as the decommissioning criteria. The general approach is to first demonstrate that the disassembled and decontaminated CAVALIER satisfies the'applicabIe radiological criteria. Following its decommissioning the CAVALIER facility will be integrated with the Reactor facility, and the combined facility will be decommissioned to satisfy the approved March 2002 decommissioning plan for the UVAR. GTS Duratek performed an initial characterization of the entire facility, including the CAVALIER and the environs, beginning in July 1999. Results of that characterization effort are presented in the March 2000 characterization survey report. Findings of this site characterization were that the accessible surfaces of the CAVALIER facility were below the characterization release criteria and free of hazardous material contamination concerns. However, at the time of the initial characterization, some potentially impacted locations were not accessible for survey. For this reason it was necessary to conduct further characterization of such locations, as the decommissioning effort progressed and such characterization became possible and practicable. Disassembly and decontamination of the CAVALIER occurred in June and July 2002, during the period of August through November 2002, a thorough characterization of the CAVALIER facility was conducted by the CH2MHILL team, contracted by the University of Virginia for the UVAR Decommissioning Project. This report describes the methods used and the results of that characterization effort. AEVALUATION OF RADIOLOGICALCHARACTERIZATION RESULTS RELATIVETO TERMINATION OFNRC LICENSE R-123 A-1
- 2. Purpose and Scope The purpose of this characterization was to identify the presence of reactor operations-related radiological contamination on surfaces or in materials associated with the CAVALIER facility.
The contamination levels determined from this characterization were compared with the NRC-approved decommissioning criteria to identify those portions of the facility, which might require remediation. The characterization findings also provide the bases for design of the final status survey and for classification of facility areas by contamination potential, in accordance with the approach of draft NUREG/CR-5849 and as specified in the NRC-approved CAVALIER decommissioning plan. Finally, the design and implementation of the characterization were such that, depending upon the characterization findings and further remediation activities required, data from the characterization survey could be used for final status survey purposes of demonstrating compliance with the established release criteria, provided the measurements were associated with areas not disturbed following the measurements. The scope of this characterization encompassed all surfaces of the CAVALIER facility, including drains, potential aerosol deposition surfaces, and ventilation in and from the facility. EVALUATION OF RADIOLOGICAL CHARACTERIZATION RESULTS RELATIVE TO TERMINATION OF NRC LICENSE R-123 A-2
- 3. Facility Description The CAVALIER is located on the northwest grounds of the University of Virginia in Charlottesville, Virginia. The UVAR and CAVALIER reactors, as well as the former Department of Nuclear Engineering (including offices for faculty, students, and staff), are housed in the Reactor Facility. The facility is sited approximately 0.6 kilometers (km) west of the city limits of Charlottesville. To the north, east, and south of the facility (no closer than 0.5 km) there are city residential districts. The only access to the facility is by way of Old Reservoir Road. The land and facilities are the property of the University of Virginia, which is responsible for facility oversight and support. Figure 1 is a plan of the Reactor Facility and environs.
The CAVALIER facility is located on the ground floor level of the reactor building (Figure 2) and consists of the CAVALIER reactor room and pit. A small room known as the fuel storage area, is accessed from the CAVALIER reactor room, but is included as part of the LVAR site for purposes of characterization and final status survey of the entire Reactor Facility. Figure 3 is a floor plan of the CAVALIER facility. The reactor room (excluding the pit) has a floor area of approximately 41 m2 . The pit measures approximately 2 m x 7 m and is covered on the east end by a metal grating; the west end of the pit, where the reactor core was located, is open. Except for the metal grating over the pit, the floor is tile over a concrete slab. Walls are approximately 3.5 m in height and are concrete block, with exception of a portion of the poured concrete west wall, a metal gate at the room entrance, and windows along the upper portion of the south wall. The ceiling is covered with acoustical tile; light fixtures, electrical conduit, drain piping from the floors above, and a supply-air unit is mounted near the ceiling. Furnishings and equipment have been removed from the room, with the exception of a laboratory bench along the west wall. This bench contains a sink, which drains to the pond via the storm sewer. There are also 2 floor drains near the center of the room; these also empty to the pond. A metal cage, extending from floor to ceiling on the north and east sides of the reactor pit, has been left in place to prevent access to the open pit for industrial safety reasons. The reactor room housed the operating controls and was used for some experimental activities and to access the reactor for maintenance and other purposes. The reactor pit is approximately 2.75 m deep with a bottom surface area of about 14 m2 . Pit surfaces are poured concrete. Near the center of the pit floor is a drain with an outfall to the outside pond. All reactor and support components have been removed, as have the reactor tank and concrete blocks that supported the tank and provided shielding. These components and materials have been disposed of as radioactive waste or surveyed and released off-site. EVALUATION OF RADIOLOGICALCHARACTERIZATION RESULTS RELATIVETO TERMINATION OF NRC LICENSE R-123 A-3
Figure 1 University of Virginia Reactor Facility and Environs
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- 4. Radiological Criteria The GTS-Duratek characterization data and facility radiological history indicate that no significant spills, releases, or incidents that would have resulted in significant contamination of the remaining facility surfaces occurred. The dominant contaminant as a result of CAVALIER operations is Cs-137; lesser quantities of Co-60 are also present No contamination by Sr-90, transuranics, or other radionuclides with more restrictive contamination criteria than that for Cs-137 and Co-60 is expected. These contaminants are the basis for the release criteria.
The NRC-approved decommissioning plan establishes the radiological release criteria for residual contamination on surfaces as those established in the NRC Regulatory Guide (RG) 1.86-Termination of OperatingLicensesfor Nuclear Reactors. The criteria for total surface contamination for Cs-137 and Co-60, as listed in that document, are 5,000 beta dpm/100 cm2 , averaged over an area of 1 m2 , and 15,000 beta dpm, maximum in any 100 cm 2 area. The limit for removable beta contamination is 1,000 alpha dpm/100 cm 2. Criteria for direct radiation levels at 1 m above the floor surface are 5 1uR/h (average) and 10 pR/h (maximum). The criteria presented above, all refer to levels in excess of normal, ambient background. Typically, there are background levels of approximately 5 to 8 gR/h direct exposure rate. Surface contamination backgrounds are negligible; however, radiological survey instrumentation will indicate a background for direct radiation, due to naturally occurring terrestrial materials and cosmic sources. Instrument backgrounds depend on the specific instrument being used and are determined at the time of the survey. EVALUATION OF RADIOLOGCALCHARACTEPIZATION RESULTS RELATIVETO TERMINATION OFNRC LICENSE R-123 A-7
- 5. Survey Approach 5.1 General The survey plan was prepared in accordance with the guidelines and recommendations, presented in draft NUREG/CR-5849, ManualforConductingRadiological Surveys in Support of License Termination. Survey activities were conducted by trained and qualified personnel, following documented procedures. Training and qualification requirements are documented in the QAPP.
5.2 Instrumentation Table 1 lists the instrumentation used for survey activities described in this report, along with nominal operating parameters and estimated detection sensitivities. Instrument response was based on use of an average surface efficiency of 0.50 (per recommendations of ISO 7503 for radionuclides with maximum beta energies > 0.400 Mev) (Ref. 8); this yields a conservatively low efficiency, considering use of a detector efficiency for Tc-99, underestimates the true detector response for the higher beta energies associated with Cs-137 and Co-60. Detection sensitivities were estimated, using the guidance in draft NUREG/CR-5849, NUREG-1575 (MARSSIM) (Ref. 9), and NUREG-1507 (Ref. 10). Instrumentation and survey techniques were chosen to achieve detection sensitivities of <25% of the criteria for structure surfaces, for both scanning and direct measurement. This assured identification of areas of elevated activity of a size and activity level that could adversely impact the average for the survey units. All instruments had current calibrations using NIST-traceable standards. Operational and background checks were performed at the beginning of each day of characterization activities and whenever there was reason to question instrument performance. Defective instruments were removed from service and data obtained with that instrument since its previous acceptable performance, were not accepted. Attachment 1 contains calibration and performance testing information for the instruments used for this characterization. EVALUATION OF RADIOLOGICALCHARACTERIZATION RESULTS RELATIVETO TERMINATION OFNRC LICENSE R-123 A-t
Table 1 Instrumentation for CAVALIER Characterization Detector Type Make Meter Application Sensitivity (dpn100 cm 2 , except as Scanning Static Count (1 minute) 43-68 Gas Ludlum 2221 Beta scan & 1200 500 Proportiona measurement 1 43-37 Floor Ludlum 2221 Beta scan 800 N/A Monitor 43-68 Gas Ludlum 2221 Alpha 200 70 Proportiona measurement 1 Tennelec Gas Tennelec N/A Alpha smear N/A 5 LB5100 proportiona measurement 1 Tennelec Gas Tennelec N/A Beta smear N/A 10 LB5100 proportiona measurement 1 44-10 NaI Ludlum 2221 Gamma scan 10 pCi/g N/A Bicron Organic Bicron same Dose-rate N/A 2 .irem/hr prem Scint. measurement 5.3 Survey Areas All CAVALIER facility surfaces were considered "affected" for the purpose of determining the rigor of survey. Surfaces were divided into contiguous areas having common history and/or contamination potential. Areas and survey patterns were sized with the objective of obtaining a minimum of 30 systematic measurements for each major structure surface, i.e., the floor, walls, and CAVALIER pit. The maximum interval between measurement points for these surfaces was 2 m; the maximum size for a survey area was 120 m2 . In addition, surfaces with smaller areas, such as the Wire Cage, laboratory bench, and air-handling unit, were grouped into survey areas by common history, material, or use, and the ceiling and overhead surfaces were surveyed as a combined area; the number of measurements from each of these latter surfaces ranged between 14 and 18. Survey areas are listed in Table 2. In addition to these survey areas, supplemental surveys were performed on drains. A total of 112 measurements were performed on the floor, walls, and pit surfaces, and 71 measurements were performed on other surfaces, including 15 measurements on drains. EVALUATION OF RADIOLOGICAL CHARACTERIZATION RESULTS RELATIVE TO TERMINATION OF NRC LICENSE R-123 A-9
Table 2 Survey Areas for Characterization of the CAVALIER Facility Survey area Description Area (m2) Measurement Interval (m) 1 Reactor Room Floor 41 1 2 Reactor Room Walls 120 2 3 Reactor Pit 64 1.5 4 Reactor Room Ceiling/Overhead Surfaces 70 1.5 5 Laboratory Bench -25 -1.5 6 Wire Cage Walls 25 1.5 -2 7 Air handling Unit .4 0.5-1 5.4 Reference Grid Systems Grids were established for the purpose of referencing locations of measurements and sampling, relative to structure and/or site features. Structure surfaces were gridded at 1-meter intervals. Grid systems were assigned alphanumeric indicators to enable survey locations to be uniquely identified. Figures provided with the attached survey data packages illustrate the structure survey areas and reference grid systems. 5.5 Structure Surveys 5.5.1 Surface Scans Surfaces were scanned to identify locations of residual surface activity, according to the following schedule: Floor area surfaces - 100% Pit surfaces - 100% Uncontaminated wall, ceiling, and other upper surfaces - 10% (in vicinity of measurements or samples) Non-structure surfaces (laboratory bench, sink, etc.) - 30% Surface scans were conducted for alpha-plus-beta and gamma radiations. Alpha-plus-beta scanning was performed using gas proportional (43-37 and 43-68) detectors; detectors were maintained within 0.5 cm of the surface. The scanning speed was no greater than 1 detector width per second. Gamma scans were performed using a 44-10 NaI detector; the detector was moved in a serpentine pattern, while advancing at a speed of approximately 0.5 m per second. The distance between the detector and surface was maintained within 5 cm. Audible signals were monitored (headphones) and locations of elevated direct radiation levels were identified, for further investigation. EVALUATION OF RADIOLOGICAL CHARACTERIZATION RESULTS REIATIVE TO TERMINATION OF NRC LICENSE R-123 A-10
5.5.2 Surface Activity Measurements Direct measurements of beta surface activity were performed at selected locations, using the 43-68 gas proportional detectors described above. Measurements were conducted by integrating the count over a 1-minute period. Because the selected scanning technique has the sensitivity of detecting residual Cs-137 and Co-60 contamination at <25% of the guideline level, direct surface activity measurements were performed at maximum intervals of 2 m. Spacing between measurement locations for the floor, walls, and Reactor Pit were based on the surface area of the survey unit and were determined to assure a minimum of 30 measurement points per survey unit. For the small surface areas and other miscellaneous surfaces, survey units were not established. Instead, measurements were performed at a frequency of approximately 1 per 1 to 4 m2 ; these measurement locations were selected from locations of highest contamination potential, on the basis of surveyor's professional judgment. 5.5.3 Removable Activity Measurements A smear was obtained at each direct measurement location. 5.5.4 Dose Rate Measurements Gamma dose rate measurements were performed at 1 meter above the floor surface, using a tissue-equivalent, organic scintillation instrument. Measurements were uniformly spaced to provide a minimum of 1 measurement per 4 m2 . 5.5.5 Drain Surveys Scans for alpha-plus-beta and gamma radiations, direct beta measurements, and smears for alpha and beta activity were performed on surfaces at the entrances and outfalls of each drain. Specially designed gas proportional pipe probes were inserted into drains and used to scan for indication of elevated direct radiation levels. Swabs were obtained from each drain opening and outfall, using a plumber's snake; these swabs were counted for gross beta activity and analyzed for identifiable radionuclides by gamma spectrometry. 5.5.6 Air Handling System Surveys The interior of the air-handling unit was accessed and 8 measurements were performed on the interior and exterior surfaces of this equipment. A sample of insulation from the unit was obtained and analyzed by gamma spectrometry to identify the radionuclides responsible for the slightly elevated direct measurement at this location. 5.5.7 Additional Measurements/Sampling A sample of material was obtained from the reactor pit wall to determine the source of a slightly elevated direct radiation level. This sample was analyzed by gamma spectrometry to identify the radionuclides responsible for the elevated reading. 5.5.8 Background Determinations Because of the variations in surface construction materials and surface-detector geometries encountered during the CAVALIER facility characterization, attempts were not made to correct individual surface activity measurements for specific material background levels. Instead, two EVALUATION OF RADIOLOGICAL CHARACTERIZATION RESULTS RELATIVE TO TERMINATION OF NRC LICENSE R-123 A-11I
measurements were performed at each location - one with the detector in its typical measurement configuration and the second with the detector face covered (shielded) with a piece of 1/2/inch thick plastic. Subtracting the shielded from the unshielded measurement yielded the net beta activity emitted from the surface, conservatively including activity originating from naturally occurring radionuclides in the construction materials. Background dose rate measurements were obtained from unaffected areas within the building. 5.5.9 Sample Analysis Smears and swabs for removable contamination were analyzed for gross alpha and gross beta activity; the sample of pit wall material was evaluated by gamma spectrometry. All analyses were conducted on site using instrumentation belonging to the University of Virginia and/or dedicated to this D&D project. 5.5.10 Data Conversions Shielded surface activity measurements were subtracted for corresponding unshielded measurements and net activity levels were converted to units of dpm/100 cm 2 . Smear counts were corrected for instrument background and net levels were converted to units of dpm/100 cm 2 . Results were compared with project release criteria. The building dose rates were compared with building background levels, relative to project criteria. EVALUATION OF RADIOLOGICAL CHARACTERIZATION RESULTS RELATIVE TO TERMINATION OF NRC LICENSE R-123 A-12
- 6. Survey Results Detailed results of the characterization survey are provided in the field data packages, included as Attachment 2 of this Report. Those results are summarized and evaluated in this Section.
6.1 Scanning Scanning identified an elevation (up to approximately 50% above levels at other facility locations) in the gamma and beta radiation levels along the north wall of the room. Beta measurements with the detector shielded and gamma surveys in the hallway on the opposite side of the wall identified the elevated direct levels as originating from the nearby room being used to store radiological sources and wastes. Scanning also identified slightly elevated gamma and beta radiation levels (again up to approximately 50% above levels at other locations on pit surfaces) near the lower southeast corner of the reactor pit; a sample of the pit wall material was obtained from this location for gamma analysis. All other facility surfaces had levels in the ranges of ambient facility levels, without identifiable locations of elevated activity. 6.2 Surface Activity Measurements Beta surface activity measurements in each survey unit are summarized in Table 3-1. Most of the measurements were less than the measurement sensitivity of the procedure. The maximum total beta activity level measured on any of the structure surfaces was 1883 dpm/100 cm 2 ; this measurement was on the lower southwest wall of the reactor pit (in the area identified by scans as slightly elevated). All surface activity measurements were less than the average release criteria of 5000 dpm/100 cm2 . Table 3-1 Summary of Surface Activity Measurements Survey Surface Total Beta Activity Level (d m/100 cm 2 ) Area Maximum Average Std. Dev./n* 1 Reactor Room Floor 956 130 242/40 2 Room Walls 1344 441 305/32 3 Reactor Pit 1883 735 476/40 4 Ceiling/Overhead 650 387 213/18 5 Laboratory Bench 635 28 204/14 6 Cage walls 295 125 101/16 7 Air Handling Unit 2288 597 721/8 n = number of data points (measurements) EVALUATION OF RADIOLOGICAL CHARACTERIZATION RESULTS RELATIVE TO TERMINATION OF NRC LICENSE R-123 A-13
6.3 Removable Activity Measurements Removable beta surface activity measurements in each survey unit are summarized in Table 4. Most of the measurements were less than the measurement sensitivity of the procedure. The maximum removable beta activity level measured on any of the surfaces was 62 dpm/100 cm 2 ; this measurement was on the inside of the air handling unit. There were no removable alpha measurements that exceeded the detection sensitivity of the procedure of 19 dpm/100 cm 2 . All removable activity measurements were well below the established criteria of 1000 dpm/100 CM 2 . Table 4 Summary of Removable Activity Measurements Survey Surface Removable Activity Levels (dpm/100 cm 2 ) Area Maximum alpha Maximum beta 1 Reactor Room Floor < 19 23 2 Room Walls < 19 < 23 3 Reactor Pit < 19 <23 4 Ceiling/Overhead < 19 23 5 Laboratory Bench < 19 < 23 6 Cage walls < 19 23 7 Air Handling Unit < 19 62 6.4 Dose Rate Measurements Dose rates measured at 1 m above the surface ranged from 7 to 10 glrem/h. For comparison, background dose rates throughout the portion of the building without a radiological use history ranged from 6 to 9 ptrem/h. 6.5 Drain Surveys Gamrnma scans of the three floor drains (one in the pit and two on the main reactor room floor) did not identify any elevated levels. Beta scans identified a slightly elevated beta level at the drain opening in the pit bottom. The direct beta measurement at the location of the maximum scan level on the pit drain was 3854 dpm/100 cm2 ; removable activity measurements at this drain opening were < 19 alpha dpm/100 cm 2 and < 23 beta dpm/100 cm2 . No elevated activity was detected by scans, direct measurements, or smears in the other floor drains or in the drain in the Laboratory Bench sink. Scans of drains with pipe-crawlers identified slightly elevated gross beta levels at the outlets from the floor and sink drains to the storm drain basin. Because of the high sensitivity of these pipe crawlers to gas flow rates, geometry conditions, shielding effects of soil and drain materials, and natural radioactive content of soil and drain material, results should only be regarded as indicating relative changes, rather than as actual quantities present. No elevated levels were identified in the piping from the pit drain. Direct measurements in these drains indicated a maximum beta activity of 400 dpm/100 cm2 . Swabs from the drains did not contain EVALUATION OF RADIOLOGICALCHARACTERIZATION RESULTS RELATPIETO TERMINATION OFNRC UCENSE R-123 A-14
detectable removable activity; gamma spectrometry identified low levels of naturally occurring radionuclides, but there were no detectable radionuclides of reactor origin present. 6.6 Air Handling Unit Scans of internal and external ventilation ductwork surfaces did not identify any elevated direct levels. Static, l-minute measurements on these surfaces identified a maximum total activity level of 2288 beta dpm/100 cm 2 on insulation inside the unit. This insulation had removable (smearable) activity of < 19 alpha dpm/100 cm 2 and 62 beta dpm/100 cm 2 . 6.7 Sample analysis Samples of pit wall material, insulation from the air-handling unit, and swabs from the facility drains were evaluated by gamma spectrometry. Results identified naturally occurring K-40. Pb-212, Pb-214, and Bi-214 - all members of the naturally occurring thorium and uranium decay series - were also identified in some samples at concentrations less than several pCi/g. These concentrations of naturally occurring radionuclides are typical of those commonly present in soil, concrete, and other construction materials. No radionuclides of reactor origin were identified. EVALUATION OF RADIOLOGICALCHARACTERIZATION RELATNETO TERMINATION OFNRC LICENSE R-123 RESULTS A-15
- 7. Conclusions Results of this characterization survey of the CAVALIER facility demonstrate that all radiological levels in the facility are within the guidelines of Regulatory Guide 1.86, and no remediation or decontamination activities are required to satisfy the conditions established as the criteria for termination of NRC License R-123. A Final Status Survey Report will be prepared, following the guidance of draft NUREG/CR-5849 and using the data developed by this characterization, to demonstrate that the criteria have been satisfied.
EVALUATION OF RADIOLOGICALCHARACTERIZATION RESULTS RELATIVETO TERMINATION OFNRC LICENSE R-123 A-16
ATITACHMENT 1 INSTRUMENTATION INFORMATION 1/44
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X100 16000 ISOM 0ee 40O0 3Do0 .6 % X1t 1600 1600 0.0 400 330o % Xi 160) 160 .00 o 40eA 42.0 5.0 % I XO.1 114.0 16.0 ! .0 4.00 3.80 .5% Z CalIbration Source . Source to Detector Intensity at 1 meter 172 mRh '-Datt 0222/02' Cometry peoDendtuecr Zero Check ok HV Check - 07tY Threshold Set n Battery Ok ok Scaler Rate :Ceotropic Check ok Checkband Respo bse+ +/ %,;'; +/-2% ReproducibIlity ok (Checked 3 times, Identical conditions +F-10%) Check Source nhla : CbeckSourceResding Quality Assurance Review By: F. " --Date r 0408102 Calibrated By .. - I " -. -. Date 0408/02 Re-Cal Due 1106/02 j 6 MWN- 0 0. O . . s__a lS0.9001 Quklttyi bm Cer"fr Page 1 of 3 4nirwam _ _ _ 2144
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Type J.L SHEPHERD CS-137 SIN 10081 Re-Cal Due 02/22103 Type EBERLINE MINI PULSER MP-2 - SIN 788.-- Re-Cal Due Type S51' . I Re-Cal Doe PROCEDURES USED DURING CALIBRATION *- Procedure Used QC ACCEPTANCEPROCEDUREI 056930. - 1, Procedure Used Procedure Used . .
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Safety and Ecology Corporation 2800 Solhay Road Page I of I KnoxrJlle, TN 37931 Calibration Certificate 5O2002 Calibration Certificate for 2221,Serfal # 1t2035, Bar Code X ,Property# SEC0000938 Dat: 05103/02 Date Last Cal. Expiras: 12119102 TechnIcian: Carl Hal Location: 90. RasonForCalbration: Other EQUIPMENT USED DURING CALIBRATION MODEL 500-2 SERIAL : 13283S CALDUE: 111tS102 MODEL, SERIALI: CALDUE, AS FOUND DATA Geotroplim: SAT AF Instrument Condtlonm SAT AL Instrument Conditlon: SAT IIGHIVOLTAGE ASFOUNDHy ASLEFTHY ENow Batteri? AFFM*chantca Zoro: 0 t-6110%tolermncat o00V: 467 494 Thrreholdrato: tDm0gnV ALMechanicalZero: 0 tODOV: 951 1000 AFTHRESHOLD 100mV AF VRaadlng 114DV t6DDV 1477 1503 ALTHRESHOLD. 10.OmV ALHVRaSding 1350V 6CALE RATE CPM AS FOUND ERROR AS LEFT SF LI orXI 100 100 000% AF o.o3% AF2D0 200 %ERROR., 0.00% 250 250 000% AF 0.00% AF 2000 2000 % ERRORk 0.00% 400 400 000% AF 0.00% AF20K1 20 K %ERROR. 0.00% xI or 10tO 1000 Q00% AF 0.00% xt0 25W 2500 AF
-00C 00% AF 200W 200 K % ERROR. 0.00.
4000 4000 0D0% AF 0.00% AL200 AF % ERROR, 0.00% xtO or 10K t0 0.00S AF 0. X100 25K 25 0.00% AF 0.00% AL 200k AF % ERROR: 0.00% (x1000) 40K 40 0.00S AF 0.00% AL 20K AF K % ERROR. 0.00% x100 or 1 K 100 0.0% AF 0 00% x1000 260K 2AF 000% AL200K AP K %ERROR: 000% xW00) 400K 400 000% AF 0.00% Is the As Found Dots Within 20% of the Set Point? SCALER: 250 C000 AF 0.00% Is the As Found Date Within 20% of the Sot Point? Audio Response: SAT LI orXI SAudio Divide: SAT xIorxloScale 2500 2500 2500 xt orx100Scat: 25 K 25 K 25 K Lapnr: SAT x100 orXtOSO Scale: 250 K 250 K 250 K Scaler/Digital: SAT 2] Are the Individual Counts Within 101%ofthe Average? E1FastI Slow Response Function Properly? Comments Married es asetwth: Modeb 4337 Sertle# PRIS13S7 Recd lor rental. 21 Does Instrumenit Met Final Acceptance Criteria? la Calibration StIcker Attached? Date Instrument is Due For Next Calibration: rarrarmac Dr Reviewed hr D.t Printed Name: Coa Hall { *' - _a~. r3j Entered In Computer Meintnonce BYr r - wor 5/44
. I Safety and Ecology Corporation 2800 Solway Road Knoxvll, TN 37831 Page I of 1 P
Calibration Certificate 4/3/02 Callbrutlon CerotfJcats for4347,SedAl# PR161368, Bar Code #,Property#SEC1166 Data: 04/3= Data Lae CaL Expires: Technician: Shane Day Locaion: 9 . Reason For Callthralon; Duo for Caobasion EQUIPMENT USED DURING3 CALIBRATION MODEL' 500-2 SERIAL t' 85781 CAL MME05117=0 M0OEL. SZRIALII; CAL DMM NISTTRALPA8RLE 80RCES USED SOURCE ISOTOPE ACTIVYTY ASSAY DATE 99T0470.0276 To-4 17900 dpm 319m 99SR470-83 Sr-gO 386 dpm 38 99TH4704271 ThIo 17900 dprn 3/1/9 ISPU470.0289 PU-235 15500 dpm 3111502 AS FOUND TA AF Inirent Conditlon SAT AL Instrument Condition: SAT efficienv from last cal. SotpobltkorisastcL: HV(Alpha): 1250 V HYVpets): 1750 V ThrehoU 4 mY Pu: % Tc: 31.03 t 1; fjAf 2nd AF Response In CPM: Ahlf Tk 18.74 % 8r 32.59 AF Response In CPU A12hs Bockground: (aIte r par Tc49: AFEfIIcianclee: - T38 Sro - -_ Th.2C Sr-S0 Th-230 I Sr-S: I _ I 1 DIn the An Found Daa Within 23% of Os efflelancy from the last caL9 Reproducibility(Sr4D): 12433 124A5 12378 Average: 12434.7 2 Are the Indidual counts wthin 10% ofthe average? Alpha Sowcu: Pu- PLATEAU DATA t So . TO." Rspon Bround - Reponas Background NV (CPU): (CPUq: NV (CPU): (CPU: (Alpha) Ach. Ach. MMtZff. (0ets) Bh. Bj d Not M 1t50 17 4 8 11.54S 1eD 2DtO m 14.72S
. 1200 2t6T 4 14 08S 17W0 _w E12 t1.8%
t12bO 2421 4 15.59% t7E0 459 t7 2D.40S 1300 2493 7 15 04% . UW 4 0D 21.70% Alhs V PuI9 mh= Atal aft H Dts>4V 12 An 1250 2421 CPU 2D61 CPM 4 1087 1775 4350 CPM 12364 CPM AL Efficiencies: AL Efflcincrla Comments Married as a set w Model Uf 2221 Serial #I1.8382 2 Does Instrunot Meet FIrnl Acceptanee CrIteria? 2 CalW.to Maw Achcd7 Ib Due For Next Cadlbrntlow: Pero dby. RevIewed by Printed Nam: Shane Day 1 Enterod In Computer Imventory Byi7 06101. 6144
Safety andEcology Corporatlon 2800 SolwayRoad Page I Of I Knoxville, TN 37931 43/2 Calibration Certificate Calibration Certificate for 2221,Ser al# 138352, Bar Code # ,Propertyl SECO000587 Date Lat Col. Expires: Technician: Shan. Day Dota: 04103/O2 ReasonForCallbration: DuetorCallbraton Locatiorn 9999. EOUIPMENT USED DURING CALiBRAEWON MODEL: 500.2 - SERIAL. 87591t CAL DUE. 0W171D2 MODEL, SERIAL P: CAL DUEL Geotroplan: SAT AFinstruunentCondition: SAT ALtintrument Condition SAT AS FOUND DATA AS FOUND HY ASLEFT El New vBtteris? AF Mechanil 1Zero: 0 IGHVOLTAGE 500V: 491 501 ThresholdratNo100.1Om0V ALlschanlcalZero. 0 W. IOfolerneSl I1OOV: 978 1000 AFTHRESHOLD: 1DmV AFHVReading t81V 1472 1504 ALTHRESHOLD: tmrnV ALHVReading: 90tV 1500V: RAEEMA;CA6 ON
- RROR ALEFT % ERROR X~iorxiID 0.0% AF l00D'0%00 DAF 200: 200 0 -AERROR.
SM t 000% 0' LI oitt 100 100 0.00% lAF 2S0 250 0.00% AF 0.00% AP 20000 2000 % ERROR: 000% 400 400 0.% AF 0.00% AF 20K: 20. K % ERROR. 000% 0 00% AF 0 00% AF 200K 200 K X ERROR. 0.00% xI or 1000 1000 x10 2500 . 2500 0.00% AF 0.00% 0 CD% AF 0 00% AL 2 AF A0 X ERROR: 0.00% 4000 40DO x10 or 10K 10 0.00% AF 0 00% 0.00% AL 2000: AF % ERROR: 000% x100 25K 25 0:.00% 0.00% AL 20K AF K X ERROR: 0.00% xOC00) 40K 40 _ x100 or 100K 100 000X AF' 0.00% 0 D0S AF Q.h AL 200K: AF K %. EROR. 0.00% xtOO 250K 260 A' 0.00%- (xlO00I 200K 400 0n% _40 _x_00) 0% AF_
- 0h_ is the Astound Date WlthIn 20X of the Set Point?
SCALER: 251 O.40% AF 0.40% 2 Is the As Found Data Within 20% of the Set Point? Audio Rapons : SAT x,1 orxt Scale: 250 250 250 Audio Divide: SAT xi orxiS Scale: 25D0 250 2500 PuhButtons: SAT x10orx100 Sclbe: 26K 25K 25K Lamp SAT x100 oraxI00 Scate: 250 K 250 K 250 K Scahirlflglttl. SAT Are the Individual Counts Wlthin 10% of the Average? 2 FgtlSlow Rsponse Function Properly? MarrLed as*a t with: Model: 43-37 Sorbil#: PR1St3'6tS Comments: Z Does Instrument Met Final Acceptance Criterta? 2 CalIbration Sticker Altachd? DateInstrunwnt is Due For Next Calbraton: _ Perd.,med by,, ___,_, Ravtwod by., DdraJF-Printed Nrae: Shune Day 0 Entered In Comput Maintenance Br 7/44
Safety and Ecology Corporation 2800 Solway Road page 1 of 1 Knoxville, TN 37931 CalibrationCertificate 4d32 Calbration Cerflcate for44-10,Serfal # PR18695B, Bar Code # ,Prqperty# SECoooo999 Dat LaSt Cal Expires: T chnFo C oaon: CrHell Date: 0V 02 Rnason For Caibration: Other I 0929 FOUlPMENT USED DURING CALIBRATION MODEL: =21 SERIALt 1S7031 CAL DUE 04D03/03 MODELI SERIAL. CALDUE NISTTRACEAELF SOURCES USED SOURCE ISOTOPE ACTIVlTY ASSAY CATE 09C52510>288 Cr-It37 S. uCt 3(1/99 AS FOUND DAT AF Inormnt Condition: SAT AL Instrument Condilton: SAT V Callbration Threshold: 10 mV Efficiency Irom Last Cal.l: % I From Last Calibratlon: Ifteieround Coun IProbe Effchenro la Center Gount - D 0C 0 137 AS FOUND: V Cs- 137 AS LEFT: AF V o Is the As Found Efficincy Within 20% of the efficiency trom the last cal.? io-roducibiltv 138908 137428 137112 Average: 137149 3AretheindividulcountswithInl1% flmeaverage? PLATEAU AND SET POINT DATA (CPM) Sourc Reponse Background HV CENTER72981 High vot B0,Z 12tO 4301 ON5 V 13722 45Xt C&-137 [2 _ 1272S4 A404 850 13082S 44t7 FT 134111 4A5I 900 13554 _ 472 925 13b918 4888 950 137178 4809 975 137385 467 1000 13733 9 Serial 3: 187031 Model: 2221 S rlal t 157031 Comments: Mar nad as se wth: Initial celiraton of new probc Dos Intrurnent Most Final Acceptance Criteria? i Calibration Sticker Attached? Dob noru~mpnt Is Due For Next Callbrsllon: v wedby e_... Da s: PerfR PrInted Name: Cat Hall _7_ _ - -- e:
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Entared In Computer Inventory by-8144
Safety and Ecology Corporation -.. 0 2800 Sowahy Road p59.1 of 1 KnoxrDile, TN 37931 CalibrationCerificate 4/32 Calbration Certficate ftor2221,Seria) #157031, Bar Code # ,Property# SECOOOO4S5 Data: 041W02 Dt LatCal.Expires: 051l62 Technician: C Hail Locatlon 99OM, Reson For Calbratlon: Other R6UIFIVIIENT VSED DURING CALlIRALMON MODEL, 500-2 SERIAL t 132895 CALDUEL W16102 MODEL SERIALt. CALDUE: AS FOUND DATA Geotroplant SAT AF Inutnent Condition: SAT AL Instrument CondItIon: SAT HIGHVOLTAGE SFOUND. ASLEF7V 0 New Batteries? AF MechnlcalZero: 0 10Stonabncal 50 V: 500 AF Thrsholdratl o100 tDrmV ALMechanicalZero: 0 1000 V, 100S AF AFTHRESHOLD: 35.JmV AF HV Reading, 740V 15COV. 1517 A? ALTHRESHOLD: t0.OmV ALHV Reading: 050V SrALF RATEC~ PM.E %1ERROR &2. E rxl 100 100 OCO% l AF 0.0l AF20D: 200 %ERROk 000% x.i 250 250 0.00% AF 0.00% AF 2000: 2000 % ERROR: 0.00% 400 305 125% A _5% l AF 20K: 20 K % ERROR: 0.00% 1io i000 1000 0.D0% A?- 0.00%A?00:15K %EOP 7.% x10 2500 2500 0.00% AF 000% AF200K 1 K ERROR 750S 400 3 125% AF 125% AL 200: AF %ERROR. 000% x1 Dor 10K 10 0.00% AF 0 00% x1W0 25K 25 000% AF 000Y AL 2000: AF % ERROR 0D0% 40K 39.5 125% AF 125% AL20K: AF K % ERROR. 0.00% ExIC0O) xtOD or 100K 100 0.00% AF 0.00% xItD0 250K 250 0.00% AF 0W0% AL 200K AF K % ERRORP 7.50% Ix100 40CK 395 125% AF 125% Is the As Found Date Within 20% otthe Set Point? SCALER 250 0.00% AF 0.00% 0 be As Found Dat WthtIn 20% of the Set PoInt? Audio Response: SAT xi or xi Scale: 250 250 250 Audio Dhde: SAT xi or x10Scale: 2500 2500 2500 Push Buttons: SAT x10rorxt0Scale: 25K 25K 25K x100 orxlO0 scale: 250 K 250 K 25D K SraerDlgtam: SAT 2 An h. Indrldual Counts Within 10% of the Average? 0 FastSlow Response FunctIon Properly? Comments: Marriedlasasatwith: Modet 44-10 Seil C: PR1St8S6 2 Does Instrument Meet Final Acceptance Criteria? 2 CalIbration Strker Attachod? Date Instrument Is Due For Next Callbration, Perored br Reviewed b r Date, Printed Name: Carl Hall - _ Entered In Computer alrenana tBt -.Data: ,/ 9144
Safety and Ecology Corporation -0 2800 Sohvay Road Knoxvlfle, 7T 37931 Page I of I Callbration Certfflcate 72M SV2 Calibration Cerificate for4348,S0rla11#PR116718, Bar Code #,Prop~rty# SECOOOOU8 Date: 002 DataLst Col. Expirexs07/0912 Technician: Cad Hal Looaon. 9999. Reason For Callbraion: Other EQUIPMENTUSEDDURINGICALIBRATION MODEL 2221 SERIALt 172051 CAL DUE 040803 MODEL: SERIALt CALDUE NISTThACA9L SOURCES USED SOURCE ISOTOPE ACTIYTY ASSAY DATE 99TC470-0276 Tc-9g 17900 dpn 3/St39 99PU470D-2 Pu-239 155sodpm r313109 95TH4700271 Th230 17900 dpm 3/13/39 S3SR470-0283 Sr-.O 38088 dpm 318/99 AatIJVUNU DATA Ar IOumIentuonlrdion SAT AL Instrument Condition: SAST EmfIienc from last cal-Setpolni fromlastcl.: HV: 1725 V Threshold: mV Pu: 21.97 % Tc 28 40% Alftr repalr. AF Response In CPIA Abft J1It 2nd AF Response In CPM: Ahtnh n Th: 22.52 % Sr 36.11% Backgrond, - 0 211 Pu-23t 4242 A-B XTLK A4BXThK-4987 S-AXTLKt c1% B-AXTLKl <1% AF Efficlencis: l~ E a Th 230 Srzi 1 1 0liTh-230 Sr4a Th-230 I Sr490 U76 I IN= II 2 b the As Found Data Within20% ofthe efficiencyfrom the laetcar.? RoproducIbIlny: Isotops: Tc-93 481B 4785 - 4991 Avorge: 45S7.3 Are the tdlMdual counts wIthbn 10% of the vege? PLATEAU DATA Source 1: Tc49 Source2 Th230 Background(CPM)* NetAtoB BtoAXtsIk: Response 1CPM): Response (CPM): Xtallc 10% HV/Vernber 01% Ach. Bch. NotEft. Ach. Brdc. NstEif. Ach. Srh. I Vornle PUI239 Tim0 Date CPU CPM CPM CPM
Background:
ALEffictencles: Comments: Manledassaetwlth: Model: 2221 8eriatR. 172051 Efficiencies lnghty different due to usihg a different source and a new geometry. Calibrated as a married set. IDoe$ Instrument Mset Finsl Acceptance CrItera? 2 CalIbration Sticker Attached? Date Instrument Is Due For Nex Calibration: _ Perfonned - Reviewed by _ Prinlad Name: CaldHall Entered In Computer inventoryBy* Date:_ __e 10/44
Safety and Ecology Corporation 2800 Solway Road - 0 KnoxvUll, TN 37031 Pae. I of I Callbrafion Certficate 4/8)02 Calibraton CerUt7catofor43-68,Serlal#PR116719,Bar Code # ,Property# SECO000650 Data: 041 2 Date Last Cal. Expire.: 0710902 Technician: Corl Hal Location: 999, ReasonForCallbratlon: Other EQUIPMENT USED DURING CALIBRATION MODEL: 2221 SERIAL 172M51 CALDUE 04108/03 MODEL, SERIAL-:L _ CAL DUE NISTTRACEASLE SOURCES USED SOURCE ISOTOPE - ACTMY ASSAY DATE 29PU470-M29 Pu-239 15500 dpm 3/13/99 99TC470.0276 Tc-09 17900 dpm 31SM9 95TH470D0271 Th-230 17900 dpm 3/13/99 99SR47042S3 Sr-go 38088 dpm 3W99 AS FOUND DATA AF InstrumenttConditlorc SAT AL bIstrument Condition: SAT Efficlency frorn lost cal Setpolntsfromlast cl: HV: 1725 V Threshold: 10 reV Afhrrepah P¢r 21.87% Tc: 28.30% AF Rasponse bI CPM; A~ lb 2nd AF Response In CPM: Abft Th 22.42 % Sr 37.30% Baclwround: 0 208 Pu-23: 4214 A4XTLK: A-SXTLK TrA9 4981 E-AX7tK ci% BAX1K- c0% AF Efficiencies: Th250 SrC40 Th-230 Sr-90 Th230 ISr90: 5383 / 13232 t _ / tj I R Isthe As Found Data Within 20% of the efficiency from the last cal.? Reproducibillty: Isotope: Tc-99 4899 4997 4934 Averoge: 4943.3 Are the Individul counts wIthin 10% of the average? PLATEAU DATA Source 1. Tc4O Sourc 2: Th-230 Beckground(CPM): NetAto B BtoAXtalk: Reponse (CPM): Response (CPUl): Xtalk l-C10 <1% HVIVemIenr Ach. Bch. NetEff. Arb Bch. NntEff. Act. Ech. NtA = = = 1% NV/Iernier Pu.239 T Th-230 CpM CPM CPM CPMU
Background:
AL Efficiencies: Comments: Marriedasanotwith: Model 2221 SerialS: t72051 Effldendes lghty dlifferent due to using a different source nds new geometry Calbretd as a marded set. Does Instrument Met Finsl Acceptance Criterts? E Calibration Sticker Attached? Date aFstrument Is Due For Next Calbration: i Z Perfoned b 2 Reviewed br &to,... Printed Name: Carl Had Enisred In Computer Inventory By Date,_______ 11/44
Safety and Ecology Corporation 2800 Sohvay Road 0 Knotll, TN 37931 Pago I of I Callbration Certificate £0112002 Cailbration Certificate for 2221,Serll 1 172051, Bar Code #,Pmpery# SECO000957 Data: 002 Date Lat Gol Expires. 05/31O03 Tee niclan: JeryDe~roodt Location: 9999. ReasonForCallbrition OCtr C ECUIPMENT USED DURING CALIBRAION MODEL- 5002 SERIALt., 171700 CAL DUE: 03103 MODEL SERIALt CAL DUEJ AS FOUND DATA Oeotropiam SAT APinsfrumettCondition: SAT AL tntumont.Condition: SAT HIGH ViTAOH AS FOUND iiY AS LFT 0 New atteries7 AF Uechwniral 2ro: 0 1 5-00tolnel SW VI 504 AF Throaholdratio t100-OmV ALMechanlalZero: 0 1000V. 10O2 AF AFTHRESHOLD: 10mV AFiVRaading 1711V 1500 V: 1500 AF ALTHRESHOLD 10nnV ALWVteading. 1ooOV 8ZALE RATE AS FOUND ERROR ASLEF ERBRO L1or xI 100 100 0.00% AF AF20: 2D4% 200 % ERROR. 0.00% 230 250 000% AP 000% AF 20004 2000 % ERROR. 0 00% 400 400 000% A 000% e AF 2CK 20 K %ERROR. 0.00% XI or 1o00 1000 000% AF C.o0% Xno 2500 2600 000% AF 000% AF 200K0 200 K % EMOR 0.CCS 4000 4000 0.00% AF 0.00% AL 200: AF % ERROR. 0.00% 110 or 10K 10 0.00% AF 0.00% Xt00 25K 25 n.o% AF ooo% AL 2000: AF % ERROR. 0.00% X0001 40K 40 0.00% AF 000% AL 20K: AF K % ERROR. 0.00% xiOO or 10OK 100 0.00% A? 0.00 1O000 250K 250 0.00% AF 0_00X AL 200K. AF K % ERROR: 000% jmiOOO) 400K 400 000% AF 000% 2IhtheAsFoundDataWlthin20%oftheSatPolnt? SCALER. 250 0.00% AF 0.00% 2 i the As Found Data Within 20% of the Set Point? Audio Reponsr SAT Y1 oarxSiea: 250 250 250 Audio Dhde. SAT xi orxi Scale: 2500 2500 2500 xiO or Xl00 Scal: Push Buttona.' SAT 25 K 25 K 25 K xt00 orx1000 Scale: 260 K 250 K 250 K SeaidDlgit.t SAT Are the indMdual Counts Within 10% ofahe Ave ?e7 2 Fast I Slow Response Function Properly? Comments Melrred easnset with., aodeL, Sril1#: Racallbrated asindiidual motar. 0 Does Inaruent Moet Finsl Accetonce Criteria? ; Calibration SIdcr Attached? Dat Insbtrument Is Due For Nex Calnbratlon: rn... .-U .. r I -_ Reviewedbr - Printed Name: Kiy Demondt Entered In Comnputar Malntianarce y-_ o10 _Dts C r ZS0fble 12/44
Safety and Ecology Corporation 2800 SoiwayRoad Page I of I KnoxvIlle, TN 37931 CalibrationCertificate .442 Calbratfon Cerificate for2221,Seria # 172051, Bar Code IV,Properfy # SECO000957 Date: 04108/02 Date Last CaL Expires: DB/3 Technician: Cad Hal LocatIon: 9999, ResonForCalUbration: Other EQUIPMENT USED DURING CALIBRATION MODEL 600-2 SERIALt 132898 CALDUE: 11/161 MODEL: SERIAL#: CAL DUE AS FOQ UND DATA Gotropiemn: SAT AF Instrurnent Condition: SAT AL instrument Condlton: SAT HIGH VOLTAGE ASBFOUNDHV ABLEFTH , Now Satter$e? AFMechanloIzero: 0 h10In% tolerance) S00V: 498 AF Threshold r*Uo:100.10mV ALMechanIcalZaro: 0 1000 V; 1009 AF AFTHRESHOLD: 10.0mV AFHVR eding: 1050V 1500 V. 1510 AF ALTHRESHOLD; 10D.mV ALHVResding: 1725V vt F RATE CPM -ASFOUND % ERF z AS LEF %.3W At20MOR% RO. 10 xtl orx _1 tD0 100 l0.00% lAF AF00 00,%ERkO0 250 250 0 00% AF 0.00% AF 2000, 2000 S ERROR: 0.00% 400 400 0.00% AF 0 00% AF 20K1 20 K % ERROR. OD0% xior 1000 1000 % hF AF200K 195 K %ERROR: 2.50% x10 2500 2500 0 00% AF 0 00% 4000 4000 0.00% AF 0.0% AL200: AF V.ERRORF 000% x10 or 10K 10 0 00% AF O.OO% X100 26K 25 000% AF 0.00% AL 2000: AF % ERROR: 0.00Y Ox1OD) 40K 40 0.00% AF 0.00% AL 20K AF K % ERROR. 0 00% 100 or 100K 100 0.D0% AF 0 D0% X1000 250K 250 0D 0% AF ODDz AL 2W0K. AF K % ERROR: 2.50% (1000) 400K 400 0 00% -F o ooY Is the As Found Dats Within 20% of the Set Point? SCALERk 250 0.0D% AF 0.00% E kstheAsFoundDataWlthin20%oftheSetPoint? Audio Response: SAT x.1 or xi Scale: 250 250 250 Audio Dlvide: SAT xi or x10 Scal: 2500 2500 2500 Push Buttons. SAT x10orx1OOScale: 25K 25K 25K Lamp: SAT x100 orx1000 Scale: 250K 250 K 250 K Scrler/Dlgltul: SAT
.0 Are the Individual Counts Within 10% of the Average? Fast I Slow Response Funcion Properly?
Comments: Marrlied asa set with: Model: 4348 SerlaiM. PRI1B719 Calibrated ass married set with (2)43-SWa? PRt16719 & PR116718 S3 Does Inairument Meet FInal Acceptance Criteris? Colbratlon StickerAttached? Date Instrument IsDue For Next CalIbratIon: Pertorm ec __ _ _ __ _ _ _ __ _ _ _ __ _ _ _ R-1sed by, Dd 6 t/_ S/ Printed Name: Carl Hall Entered In Comp Put. li~nnn. r -_
< n_+.
- Y/§ 13/44
A Safety and Ecology Corporation 2800 Solway Road Paeg Iot I Knoxvlle, 771 37931 Calibration Certificate 1ma*2002 CalibrationCertffcate for 2221,Seal # 172020, Bar Code # ,Property'#SEC0000937 Date: 101302 Date Last CaL Expire Technician: JerryDe~rood Location: O9M, Reason For Calilbntlon: Due for Calobraiorn EQUIPMENT USED DURING CALIBRATION MODEL' 500-2 SERIAL3: 171700 CAL DUE 03V003 MODEL: . BERIALW CAL DUE: AS FOUND DATA Soolrop SAT AF Instrument Condition: SAT AL.IAfrinent Condition: SAT HIGH VOLTAGE AS FOUND NV A LEFT H New Batteries? AF Mechanical Zero: 0
+1-10%tolannri1 800 V: o03 AF Thresholdratio:10010rmV ALMchanic&alZero: 0 1000V 1001 AF AFTHRE5HOLD. 10mV AFHV Rading: No0V 119V: 1495 AF ALTHRESHOLD tOrmV AL HV R"ding: 150V 100 100 000% AF 000% AF200 200 %ERROR: 0.00%
c1 orx1 250 250 0.00% AF 0.00% AF 2D00: 2000 % ERROR. 000% 409 400 0.00% AF . 0.00% A 20K: 20.5 K %ERROR. 250% xi or 1000 1000 0.00% AF 000% AF 200K 200 K %iRROR 000% xID 2500 2500 0.00% AF A?20K 20 ERO 4000 4000 0.00% AF 000S AL 200 AF ERROR. O.00% I ...- x10 or 10K 10 0 00% AF 000% xIDo 25K 25 0 00% AF 0.00% AL 2D00: AF %ERROR 0.00% (xl 40K 40 0 00% AF 00D% AL 20K AP K % ERROR. 2.50% xtD or 100K 100 0.00% AF 000% x1000 2WX 250 O*OOX AF Q00% AL 200K: AF K %ERROR, 000% (xlOOO) 400K 400 0.DW% AF 0.00% I the An Found Dat Wlthln 20X of the Set Point? SCALER1 250 - 0.00% AF 000% is the As Found Data Within 20% of the S3t Point? Audio Response: SAT xr or xi Scale: 250 250 260 Audlo Diide: SAT xi orx1OrScale: 2500 2500 PuhButMona: SAT xi oorxio0Scae: 25K 25K 2S K amp: SAT x100lorcxIoDoScale: 250 K 250 K 250 K ScaledDtlgtal: SAT 0 Aa the Indidual CountaWithin 10% ofthe Average? Fast/ Slow Response Function Properly? Comments Marrledaasetwtit. Model: Serflalt 0 Dos In nt Ueet Finl Acceptance Crtrha? CalIbratUon Sticker Attched7 Date Instrument aDue For Next Calibration: Performed br jZ Nevlewdb Oy - ' - u'u. v -. Printed Name:/ Jny DeOroodt rs-. 1n /,?./.I Entered In Computer maintenance I. u -r V I I V-14/44
ORIGINAL i T H E DO N7O1=MVE P11M PIA 4.- I N C 0 R P O ARA T E D 2810 Slier Lane, Santa Fe, NM 87505 Business: (505) 473-9538 FAX: (505) 473-5805 Certificate of Calibration (Gamma Source) Ref. PO# 49456 The Cesium 137 gamma source was compared with a calibrated NIST gamma source 92CS2503309 used in establishing NIST traceability following ANSI N42.22 participating in the NIST radioactive measurements assurance program annually. The comparison was completed using a sodium iodide detector. The activity of the source on 03/18/99 was 8.95 uCi . The overall uncertainty of the measurement and the activity of the source is + 5.0%. Serial No. 99CS2500289 Model No. S-Cs-25 Active Diameter (or area) 1 /8" Mounting Material Plastic Total Diameter (or area) 1.0" Thickness 1 /8" Cover Length
)Izlllh7g~Y
_<Z-- ;- :,-r*^ Michael A. Ortiz . . . . Calibration Manager _ oI - _ -
.Vera Padilla . . Quality Control
<0.00 1 leak test' results (uCi)
The overall uncertainty of the measurement Is three times the value found from combining quadratically the sum of the overall uncertainty reported by NIST in the radioactive measurements assurance program; the standard deviation of the mean for the NIST standard as measured in the system used for calibration; and the standard deviation of the mean for the source measurements. GCO08-95 15144
- URIGINAL LUJ 4. -F 0 : DO1Nj7,PxUMVE FROM ILE INC RadiIation Standards and Check Soiurcesk -.. I 2810 Slier Lane Santa Fe, NM 87501 (505) 473-9538 FAX: (505) 473-5805 Certificate of Calibration (Beta Source)
The Technetium 99 beta source was measured in a gas proportional counter using P-10 as counting gas. The beta emissions from the surface of the source were measured at Its plateau voltage to determine Its ZiT particle emission. rate (I.e. particles per minute). Corrections were applied for background coincidence loss and backscatter factors when applicable. Beta standard 91TC4704553 - is our NIST calibrated source used in establishing NIST Irvabeability following ANSI N42.22 participating in the NIST radioactivity measurement .aisurance program annually. RE4fz.?PX 49244 Model S-Tc-47 Active Diameter (or area) 44mm
- Mounting Material -SiR Total Diameter (or. area) 47mm- Thickness _ 0.79mm 22,300 Ippm+ 1,115 .ppm2xR 3 5,800 dpm + 1.790 dpm 4Tr 0.0161 .
uCi __Bq 02/03/98 date of measurement 98TC4700730 source serial number
- 5.0 overall uncertainty (percent) 25 backscatter(percent)
Michael A. Ortiz . . . . Calibration Manager Charles L. Gonzales . . Quality Assurance Manager
<2200 dpm leak test results (dpm/100cm')
The overall uncertainty d the'measuremont Is tree times the value tound from combining quaraticailythe sum of the woerall uncertainty reported by MST In the radioac1ive measurements assuraince program; the standard deviation of the mean for the NIST standard as measured in the system used for calibratton; and the standard devialoiof the mean forthe source measurements. AC0O6-97 16144
Soure Type.Cs137/199cs250-0285 Source Activftr. 8.96 pCi Instrument . L2221 SIN: 157031 Voltage: 950 W. Due: 4/3/03 Detectorn L44-10 SIN: PR188958 Threshold: 100 Cal. Due: 4/3/03 41z41UZ IU:uu 79,141 10,555 68586 n/a 950 6.2 ok ok AT 4125/02 10:15 78,968 10,542 68424 n/a 950 6.1 ok ok AT 4/28/02 08:10 78,558 10,307 - 68249 n/a 952 6.1 ok ok AT 8/6/02 10:00 70,183 10,750 59413 n/a 950 5.9 ok ok BL 818/02 9:00 70,941 10,674 60267 n/a 951 5.9 ok ok BL 8/9/02 7:35 1 66,463 10,659 55804 /ae 950 5.9 ok ok BL 8/12/02 8:42 70,860 11,407 59453 n/a 950 5.7 ok ok BL 8/20102 10:25 70,778 12,199 58579 n/a 950 5.8 ok ok BL 822/02 8:00 71,404 11,006 80398 n/a 950 5.8 ok ok BL 8/27/02 7:30 71,098 10,488 60610 n/a 950 5.8 ok ok BL 8/28/02 -7:30 71,029- 10,372 60657 n/a 950 5.8 ok ok BL 8/29102 07:30 70,777 10,730 60047 rva 950 5.7 ok ok BiL 9/16102 13:50 68,852 10,723 58129 n/a 948 5.7 ok ok BL 9/17/02 09:30 70,075 10,319 59756 n/a 950 5.6 ok ok MW 9/18102 8:00 69,373 10,387 58986 nla 950 5.5 ok ok MW __-_____ n/a __nla____ n/a
.____ _ n/a
- -n/a n /a --
________n/a _ __=- n/a - - -_ - _ _ _n _ _ _ _ _ /a Remarks
+20% 81,770- -20% S4,W14 17/44
SERIAL #'. 157D31 CAL DUE: 4/3/03 INSTRUMENT: L2221 SERIAL t PR186956 CAL DUE. 413103 PROBE: L44-10 SERIAL t. Cs137199cs250-0289 Setup Date 4/24102 SOURCE: . CS-1 37 ACTIMY: 8.95uCI ipCi IMINUTE SOURCE COUNT TIME: 1 MINUTE BKG COUNT TIME: THRESHOLD VALUE: 'iD0 CALIBRATED OPERATING VOLTAGE: 950 Wii;' '*s irz: , s' 1 79,232 105561 68,676 NIA 2 77,586 105481 67,038 N/A 3 79_442 103571 89,085 NIA 4 78,863 109851 67,878 NWA 68,502 6852I/ NWA
- 5) 70,013 10511 6 78,549 10973 - 67,576 NIA 7 79,623 11022 - 68,601 NIA 8 78,311 105831 67,728 NIA 9 79,541 107481 68,793 N/A 10 78,544 -10579 67,965 N/A 11 78,679 10921 - 67,758 NIA 12 76,422 10994 65,428 NIA 13 78,653 9998 68,655 N/A 14 79,414 101481 69,268 NIA 1S 79,268 10511 68,757 N/A 16 78,923 10432 68,491 NtA 17 79,103 10713 68,390 N/A 18 78,911 10642 68,269 NIA 19 78,342 104231 67,919 NIA 20 77,995 9899 68.096 NWA 21 78,586 10458 68,108 N/A Averages 78,71310,571 68,142 NIA
+ 10% 74,956 -10% 61,328
+20% 81,T70 -20% 54,514
.RFORMED BY: Alice Thompson DATE: 04124102 MEWED BY: Frank Myers DATE: 04124/02 18144
Daily Source Daily Source Range Instrument:L'-2221 # 157006 Probe: L-44-10 # 150870 85,000 li
-l- +20%
75,000
+10%
l-iDaily Sourse Counts U
-10%
55,000 l -20% 45,000 l Mean
,P,& & & ss, qsv & ss & & & & & a ,,A 44%4444(t\4 Date
Daily BKG Daily Background Range lnstrument:L-2221 # 157006 Probe: L-44-10 # 150870 14000 13500
--. +20%
13000 12500 +10% 12000 X 11500 -_-- Net Counts 11000
-10%
10500
-U--20%
9000
- Average s\ \ P' 49 b~4 O' p4 4 n4 Date
SERIAL # 172051 CAL DUE: 418/03 INSTRUMENT: 12221 SERIAL#: PR116718 CAL DUE: 4/8/03 PROBE: L43-68 Tc99 SERIAL #: tc4700730 Setup Date 4124102 SOURCE: ACTMTY: 38500 BKG COUNT TIME: 1 MINUTE - SOURCE COUNT TIME: I MINUTE CALIBRATED OPERATING VOLTAGE: 1725 THRESHOLD VALUE: 100 I _ __ __ __-251 6,610 NIA 2_ _ _ __ 25 _ 6,654 N/A 3 7,495 254 7,241 NIA 4 6,893 24E 6,647 NIA S 7,445 241 7,200 NWA 6 7,410 2381 7,172 NIA 7 7,087 249 1 6,838 N/A B 7_392 24E1 _ 7,146 N/A
, 25E 6,970 NWA 10 7,110 246 6,864 N/A 11 7,529 271 7,259 N_A 12 6,826 243 6,583 N/A 13 7,243 2551 6,988 WA 14 7,303 224 7,079 NIA 15 6,922 276 6,646 N/A 16 6,921 237 - 6,684 NJA 17 7,348 2481 7,100 NIA 18 6,684 2521 6,432 N/A 19 7,490 257 7,233 N/A W
20 6,915 232 6,683 N/A 21 7,297 250 7,047 NrA Averages 7,1571 249 6,908 N/A
+ 10% 7,59S -10% B,218
+ 20% 8,290 - 20% 5,527
'ERFORMED BY: Alice Thompson DATE: 04/24/02 IEVIEWED BY: Frank Myrra2 DATE: 04/24/02
/ VX
§1 ,I.
IW 4-- ' Source Type Tc991tc4700730 Source Actity: 0 jiCi Instrument:- L2221 SIN: 172051 Voltage: 1725 Cal. Due: 418103 Detector: L43-68 SIN: PR116718 Threshold: 100 Cal. Due: 4/8/03
- If - -
10/15/02 09:28 8,187 321 7866 0.215 1725 5.4 ok ok BL 10/16/02 8:15 8,385 395 7990 0.215 1725 5.4 ok ok BL 10/30/02 10:00 8,227 303 7924 0.215 1725 5.4 ok ok AT 10/31/02 9'05 8,187 336 7851 0.215 1725 5.4 ok ok AT 1111/02 8:35 8,425 299 8126 0.215 1725 5.4 ok ok AT 11/1102 13:30 8,488 305 8183 0.215 1725 5.4 ok . ok BL 11/4/02 14:00 7,138 333 6805 0.215 1725 5.3 ok ok BL 11/5/02 7:35 7,962 353 7609 0.215 1725 5.3 ok .ok AT 11/6/02 7:40 7,735 307 7428 0.215 1725 5.2 ok Ok BM 1117/02 7:40 7,638 348 7290 0.215 1725 5.2 ok ok BM 11/8/02 7:40 7,153 265 6885 0.215 1725 5.2 ok ok BM 11/11/02 10:15 7,080 344 6736 0215 1725 5.1 ok ok BM 11/12/02 15:30 6,967 344 6623 0.215 1725 5.1 ok ok BL 11/13/02 8:20 7,274 292 6982 0.215 1725 5.2 ok Ok JS 11/14J02 15:10 7,657 288 7369 0.215 1725 5.2 ok ok BM 11/15/02 8:00 7,069 288 6881 0.215 1725 5.2 ok ok JS 11/18/02 8:45 6,448 240 6208 0.215 1725 5.1 ok ok AT 11/19/02 9:00 6,439 293 6146 0.215 1725 5.1 ok ok JS 11120/02 8:15 6,708 270 6488 0215 1725 5.1 ok ok JS 1121/02 8:00 6,442 271 6171 0.215 1725 6.2 ok ok JS 11121/02 17:00 6,733 312 6421 0.215 1725 6.1 ok ok JS 11/25/02 9:00 6,487 274 6213 0.215 1725 6.1 ok ok BL 11126/02 8:35 7,491 273 7248 0.215 1725 6 ok ok BM 11/27/02 7:45 7,498 297 7201 0.215 1725 5 ok ok BM 12/2/02 9:50 7,549 279 7270 0.215 1725 5.9 ok ok BM 12/3/02 8:00 7,413 291 7122 0.215 1725 5.8 ok ok BM 12/4/02 7:45 7,108 274 6834 0.215 1725 5.7 ok ok BM 1215/02 8:10 7,150 292 6858 0.215 1725 5.7 ok ok BM 12/9/02 8:10 7,980 205 7775 0.215 1725 5.7 ok ok BM Remarks .i jj_ t
+20% 8,290 (A)- (B) = (D)(Dally Calculated EffigiencyI 7
-20% - S,527 xc-Fv_
22/44
I Daily Source Daily Source Range Instrument:L-2221 # 172051 Probe: L-43-68 f 116718 7,000-l-Daily Source Counts 6,500 7,500 -1 6,00 10% 5,000 Mean Date
Daily 3KG Daily Background Range Instrument:L-2221 # 172051 Probe: L-43-68# 116718 350
- +20%
300 -- I A1ig
+10%
250 0.0 i . Net Counts a. 200-
-10%
150 --. 20%
-- Average 100 im4ma I . a a . I II I I am . . I I I . I A I I I I
.§61, # A A a a &&& &
Date
t 0m L2221 SERIAL #: 172035 CAL DUE: 5/3/03 PROBE L43-68 SERIAL#: PR116719 CAL DUE. 4/8103 SOURCE: Tc-99 SERIAL #:-C4700730 Setup Date 6120/02 ACTIVITY: 35.800 ACi BKG COUNT TIME: 1MINUTE SOURCE COUNT TIME: 1 MINUTE CALIBRATED OPERATING VOLTAGE: 1725 THRESHOLD VALUE: 100 1 7,024 199 6,825 NIA 2 7,515 180 7,335 NIA 3 7,513 166 7,347 N/A 4 7,100 176 6,924 N/A 5 7,044 193 6,851 N/A 6 7,599 183 7,416 N/A 7 7,565 2051 7,360 NWA 8 7,596 189 7,407 NIA 9 7,132 180 6,952 NIA 10 7,145 185 6,980 NIA 11 7,163 163 7,000 NIA 12 7,643 172 . 7,471 NJA 13 7,401 189 7,212 N/A 14 7,570 1851 7,385 NIA 15 7,797 178 7,619 NIA 16 7,039 188 6,851 N/A 17 7,836 181 7,655 N/A 18 7,089 190 6,899 N/A 19 7,139 190 6,949 NIA 20 7,026 211 6,815 N/A 21 7,085 181 6,904 NIA Averages 17.3341 85 7,149 N/A
+ 10% 7,864 -10% 6,434
- 20% 8,579 - 20% 5,720
.PERFORMED BY: Alice Thompson , DATE: 04/24/02 REVIEWED BY: Frank Myers DATE: 04/24/02
/1 'U 25/44
WVAP DAILY FIELD SOURCE CHECK LOG - FIELD INSTRUMENT Source Typa Tc-99/98TC4700730 Source Activity: 35800 dpm Inetrument. 12221 SIN: 172035 Voltage: 1725 Cal. Due: 5/3103 Detector L43-68 SIN: PR116719 Threshold: 100 Cal. Due: 418103 Date lime Source Check Bkg. cpM Net Eff. 2PI HV Bat_ Spkr. Phys. By ____Gross CPM (A) (B) Counts ____ 116103 09:15 6,881 223 6658 0.222 1725 5.3 ok ok JS 117103 08-20 6,898 208 6690 0.222 1724 5.3 ok ok JS 118103 08:05 7,218 196 7022 0.222 1725 5.3 ok ok JS 1/9/03 08:00 6,583 235 6348 0.222 1724 5.2 ok ok JS 1/13/03 08:10 6,837 228 6619 0.222 1725 5.3 ok ok JS 1/14/03 07:45 6,775 227 6548 0.O2 1725 5.2 ok ok BM 1/15/03 08:10 6,877 218 6859 0222 1725 5.2 ok ok BM 1116103 08:20 6,674 198 6476 0.222 1725 5.2 ok ok BM 1/20/3 08:00 7,200 231 6969 0.222 1726 5.2 ok ok JS 1/21/03 08:10 6,923 219 6704 0.222 1726 5.2 ok ok JS 1/22103 08-00 7,049 216 6833 0.222 1726 5.2 ok ok JS 1123/03 08.00 6,916 234 6882 0.222 1726 5.2 ok ok JS 1127/03 08.20 6,686 226 6460 0.222 1726 5.2 ok ok JS _ _ =_ ___0.222
'_ _ _ 0.222
. _ 0.222
=_________
_ __ _ 0.222 0.222 0.222 0.222 ________s_ C ,/5 2 _ __0.222 ____ ___ ____ ___ 0.2 22 Remarks
+20% 8,579
-20% - 5720 26/44
Daily Source Daily Source Range I Instrument:L-2221 # 172035 Probe: L-43-68 # 116719 I
*I
-*+20%
*1
+10%
I
'I I:
'I
- 0. 'I
- Daily Source Counts C-II IX
'I 1'I
-10%
I I I I 11 11 i
, 4q& Ip
-l- Mean
,4Te,,e
,,\ N \ \ 't". 4I 4 , 4
\'O' '--
Ib SP 41 %p "Krl.,\ -,\ Date
Daily BKG Daily Background Range Instrument:L-2221 # 172035 Probe: L-43-68 # 116719 400 350
-- +20%
300
-+- Net Counts IL 250 200
--- 20%
150 w Average 100 g
,,\'O\ ~\4 "a- - 'j5 a \ 05 5b Date
I -. , - . .I V I , .... , -, I INStRUMENT: L2221 SERIAL #: 138352 CAL DUE: 4/3102 PROBE: L 43-37 SERIAL#: PRI61368 CAL DUE: 413102 SOURCE: TC-99 SERIAL #: C4700730 Setup Date 4124102 ACTIVITY: 35,800 uCI BKG COUNT TIME: 1MINUTE SOURCE COUNT TIME: 1 MINUTE CALIBRATED OPERATING VOLTAGE. 900 THRESHOLD VALUE: 500 500 1 6,933 1128 5,805 NIA 2 7,743 . 1155 6,588 N/A 3 7,810 1146 6,664 N/A 4 8,390 1171 7,219 NIA 5 7,892 1152 6,740 NWA 8 8,127 1145 6,982 NIA 7 8,404 1140 7,264 N/A 8 7,711 12031 6,508 NWA 9 7,203 11361 6,067 NIA 10 8,007 1172 6,835 N/A 11 8,001 1149 ... 6,852 NIA 12 8,013 1156 6,857 NIA 13 7,773 1108 6,665 N/A 14 7,590 1162 6,428 NIA 15 7,124 1144 5,980 NIA 16 8,581 1112 7,469 N/A 17 8,290 11611 7,129 NIA .' 18 7,922 11481 6,774 N/A 19 7,715 11881 6,627 NIA .I 20 8,216 1150 7,066 N/A 21 7,117 1126 5,991 N/A Averages 107,8361 1,1 6,686 N1A
+ 10% 7,355 -10% 6,018
+ 20% 8,023 - 20% 5,349 PERFORMED BY: Alice Thompson DATE: 04124/02 REVIEWED BY: Frank Myers >4 ~ w DATE: 04124/02 29/44
I II INSTRUMENT: L2221 SER1AL t 138352 CAL DUE: 4131D2 PROBE: 1. 43-37 SERIAL#: PR161388 CAL DUE: 4/3/02 SOURCE: Tc-99 SERIAL #: C4700730 Setup Date 4124/02 ACTMTY: 35.800 uCI r BKG COUNT TIME:
- IMINUTE SOURCE COUNT TIME: 1 MINUTE CALIBRATED OPERATING VOLTAGE. 900 THRESHOLD VALUE: 500 1 6,933 1128 5,805 N/A 2 7,743 11551 6,588 N/A 3 7,810 1146 8,664 N/A 4 8,390 1171 7,219 N/A 5 7,892 1152 6,740 NMA B 8,127 1145 6,982 NIA 7 8,404 11401 7,264 N/A 8 7,711 12031 6,508 N/A 9 7,203 1136 1 6,067 N/A 10 8,007 11721 6,835 NIA 11 8,001 1149 6,852 N/A 12 8,013 11561 6,857 NIA 13 7,773 11081 6,665 NIA 14 7,5690 1162 6,428 N/A 15 7,124 11441 5,980 N/A 16 8,581 11121 7,469 N/A 17 8,290 1161i 7,129 N/A 18 7,922 11481 6,774 NIA 19 7,715 11881 6,527 NIA 20 8,216 1150 7,068 NIA 21 7,117 1126 5,991 N/A Avemges 7,8361,1,686 NIA
+ 10% 7,355 -10% 6,018
+ 20% 8,023 -20% 5,349
'ERFORMED BY: Alice Thompson DATE: 04124/02
'EVIEWED BY: DATE: 04124102 0=-
30/44
UVAP DALY FIELD SOURCE CHECK LOG - FIELD INSTRUMENT Source Type T-99198TC4700730 Source Activity: 35800 DPM L2221 SIN: 138352 Voltage: 1775 Cal. Due: 413/03 Instrument: SIN: PR161368 Threshold: 40 Cal. Due: 413103 Detector. L43-37 Time Source check Bkg. cpm Net H_. Ba Spkr. Phys. By Date I___ I Gross CPM (A) (BI Counfl1 8,728 1,084 7644 N/A 1773 5.9 ok ok AT 4/2902 _9.00 8,802 1,104 7698 NUA 1774 5.9 ok ok AT 4/30/02 10:00 8,796 1,102 7694 N/A 1775 5.9 ok ok AT 5/25102 10:00 8,313 1,201 7112 NUA 1775 -5.6 ok ok BL 8/6102 13:30 7,929 1,193 6736 NVA 1775 5.6 ok ok BL 8112102 13:30 8,685 1,209 7476 N/A 1775 5.6 ok ok BL 8/13/02 8:16 8,998 1,089 7909 N/A 1775 5.6 ok ok BL 8/20/02 8:00 8,999 1,011 7988 NIA 1775 5.6 ok ok BL 11/6102 8:00 9:00 8,476 1,107 7369 N/A 1775 5.5 ok ok JS 11/19102 8,554 1101 7453 N/A 1775 5.6 ok ok JS 11/20/02 8;30 15:20 8,035 1,057 B981 NUA 1775 5.5 ok ok JS 12/11/02 7,762 1,107- 6655 N/A 1775 5.5 ok ok JS 12/12/02 8:10 8:50 7,738 1,086 6652 NIA 1774 5.5 ok ok JS 12/1302 12:00 7,525 1,123 6402 NIA 1775 5.5 ok ok BL 1/21/03 8:05 8,019 1,130 6889 N/A 1776 5.5 ok ok JS 1/22/03 NIA NIA N/A N/A NIA N/A
- ___ NUA_
_ _ _ _ _ N/A NUA__ N/A N/A __=__=N= NUA____ N/A Remarks ^-YZT A -
+20% 8,023 ( (Daily Calculated Efficiency)
(A)- (B) (D) V
-20% 5,349 Activity 31/44
I Daily Source Daily Source Range Instrument:L-2221 # 138352 Probe: 143-37 # 161368 9,500 -- 9,000 - +20% 8,5\S\00 41 dl
+10%
7,500 7,000 550 - Daily Source Counts 6,500 - -10% 8,000 q j
-.- 20Ma 5,500
~ Mean 4\'
Date
Daily BKG Daily Background Range Instrument:L-2221 #138352 Probe: L-43-37 #161368 1500 -~~v A; 1450,- OZ, ,;~
-4 H A M .
frm 1 .4 gio. vif;ele I hIa iqo I aiW F 1350-~ uil "Olf "1. fo; ~ IA
,f I.F"T I(l
, ~-t
.im q i!;rp j~il - ` Date ihinjzL I
UVAP lINIIAL SETUP I ACCEPTABLE RANGE DATA SHEETI L221 SERIAL #: 172035 CAL DUE: 513103 PROBE: L43-68 SERIAL#: PR116719 CAL DUE: 4/8103 SOURCE: Tc-99 SERIAL #: C4700730 Setup Date 6/20/02 ACTIVITY: 35.800 uCi BKG COUNT TIME: IMINUTE SOURCE COUNT TIME: 1 MINUTE CALIBRATED OPERATING VOLTAGE: 1725 THRESHOLD VALUE. 100 COUNT # SOURCE CPM BKG CPI i NET SOURCE CTS EFFICIENCY (D) 1 7,024 1991 6.825 N/A 2 7,515 180 7,335 N/A 3 7,513 166 7,347 N/A 4 7,100 176 6,924 NWA 5 7,044 193 6,851 NA 6 7,599 183 7,416 NWA 7 7,565 205 7,360 NIA 8 7,596 189 7,407 NWA 9 7,132 180 6,952 NWA 10 7,145 185 6,960 N/A 11 7,163 163 7,000 N/A 12 7,643 172 7,471 N/A 13 7,401 189 7,212 N/A 14 7,570 185 7,385 N/A 15 7,797 178 7,619 NWA 16 7,039 188 6,851 NIA 17 7,836 181 7,655 NIA 18 7,089 1901 6,899 N/A 19 7,139 1901 6,949 N/A 20 7,026 211 6,815 N/A 21 7,085 181 6,904 N/A Averages 718341 185 7,149 ,NIA
+ 10% 7,864 -10% 6,434
+ 20% 8,579 - 20% 5,720 PERFORMED BY: Alice Thompson DATE: 04/24102 REVIEWED BY: Frank Myers_ 45 2Z(,- DATE: 04/24/02
/V 34/44
UVAP DAILY FIELD SOURCE CHECK LOG - FIELD INSTRUMENT Source Type, Tc_99/98TC4700730 Source Activity: 35800 ,uCi Instrument: 12221 SIN: 172035 Voltage: 1725 Cal. Due: 5WO3 Detector: L43-68 SIN: PRI16719 Threshold: 100 Cal. Due: 4/8103 ___ 2Pi=0.222 Date Time Source Check Bkg. cpm Not Eff.213 HV Bat_ Spkr. Phys. By 6120/02 13:30 7,085 181 7570 0.222 1725 6.1 ok ok AT 6121/02 08:45 7,928 219 7707 0.222 1725 6.1 ok ok AT 6124/02 08.45 6,578 171 6407 0.222 1725 6 ok ok AT 6/25/02 08-46 7,068 240 6828 0.222 1725 5.8 ok -ok BL 711/02 12:00 7,505 237 7265 0.222 1725 5.8 ok ok AT 7/2/02 07:45 6,922 230 6692 0.222 1725 5.8 ok ok AT 7/11/02 08:30 7,304 192 7112 0.222 1725 5.7 ok ok AT 7/12/02 08:50 7,914 295 7619 0.222 1726 5.7 ok ok AT 7/15102 08.30 7,948 280 7468 0.222 1726 5.7 ok ok AT 7/16/02 09.30 7,904 262 7642 0.222 1725 5.6 ok ok BL 8/15/02 8:30 7,489 255 7234 0.222 1723 5.7 ok ok MW 8/16/02 8.00 7,839 280 7559 0.222 1724 5.6 ok ok MW 8/19/02 8.00 7,965 264 7701 0.222 1726 5.6 ok ok MW 8120/02 8:00 8,392 268 8124 0.222 1725 5.5 ok ok MW 8121102 9:20 7,524 294 7230 0.222 1726 5.5 ok ok MW 8122/02 8.00 8,531 275 8256 0.222 1726 5.4 ok ok MW 8/23/02 8:00 7,826 273 7553 0.222 1726 5.4 ok ok. MW 8126/02 08:30 8,543 273 8270 0.222 1725 5.4 ok ok MW 8127/02 08:0 7,769 248 7521 0.222 1725 5.2 ok ok MW 8/28/02 08:00 8,501 271 8230 0.222 1725 5.2 ok ok MW 8/29/02 08:30 7,725 262 7460 0.222 1725 5.2 ok ok MW 919/02 09:00 8,578 271 8307 0.222 1725 5.2 ok ok MW 9/10102 08:00 8,517 279 8238 0.222 1725 5.2 ok ok MW 9/11/02 08:00 7,622 261 7361 0.222 1725 5.2 ok ok MW 9/16102 08:00 7,815 270 7545 0.222 1725 5.2 ok ok- MW 9118/02 08:30 8,788 237 8551 0.222 1725 5.2 ok ok AT 9/19/02 08:38 8,099 223 7876 0.222 1725 5.1 ok ok BL 0.222
. .~0.222 ==
Remarks 4_
+20% 8,579 7 jc-
-20% -Y,72/-
35/44
Daily Source Daily Source Range Jnstrument:L-2221 ft172036 Probe: L-43-68 ft116719 kN g p V0811j .!, QuuuE Count J11 roi
~ ~J Inia r U M ,TI T 4
.g~1 ~ g OR.IJ S.5-0--Mean DataD Wa0 ,Fr Date
Daily BKG Daily Background Range lnstrument:L-2221 # 172035 Probe: L-43-68 # 116719 400 350 300
- Net Counts
- o. 250 200
-w-2096 150 Su Average 100 Date P'I1'1
UVAP 7 INITIAL SETUP / ACCEPTABLE RANGE DATA SHEET L2221 SERIAL #: 172035 CAL DUE: 513/03 PROBE: 143-68 SERIAL#: PR116719 CAL DUE: 418/03 SOURCE: Tc-99 SERIAL #: C4700730 Setup Date 6120102 ACTIVITY: 35.800 RCI I BKG COUNT TIME: 1MINUTE SOURCE COUNT TIME: 1 MINUTE 1725 THRESHOLD VALUE: 100 CALIBRATED OPERATING VOLTAGE: COUNT # SOURCE CPM BKG CPM NET SOURCE CT8 EFFICIENCY (D) 1 7,024 199 6,825 NIA 2 7,515 180 7,335 NIA 3 7,513 168 7,347 NIA 4 7,100 176, 6,924 NIA 5 7,044 193 6,851 N/A 6 7,599 183 7,416 NIA 7 7,565 205 7,360 N/A 8 7,596 189 7,407 N/A 9 7,132 180 6,952 NIA 10 7,145 1805 6,960 N/A 11 7,163 1631 7,000 N/A 12 7,643 1721 7,471 N/A 13 7,401 189 7,212 N/A 14 7,570 185 7,385 NIA 15 7,797 178 7,619 N/A 16 7,039 188 6,851 NIA 17 7,836 181 7,655 N/A 18 7,089 1901 6,899 N/A 19 7,139 190 6,949 N/A 20 7,026 211 6,815 NIA 21 7,085 181 6,904 N/A Averages 7,3341 185 7,149 NIA
+ 10% 7,864 -10% 6,434
+ 20% B,579 -20% 5,720 PERFORMED BY: Alice Thompson DATE: 04124102 REVIEWED BY: ;
Fran Z @ >DATE: 04/24/02 38/44
UVAP DAILY FIELD SOURCE CHECK LOG - FIELD INSTRUMENT SourceType Tc-99198TC4700730 Source Activity: 35800 dpm Instrument: L2221 SIN: 172035 Voltage: 1725 Cal. Due: 53/M03 Detector 143-68 SIN: PR116719 Threshold: 100 Cal. Due: - 418/03 2Pi=0.222 Date Time SourceChec Bkg. Cpmn Not Eff. 2P1 HV Ba- Spkr. Phys. By Gross CPM (A) *JB) Counts - - - 11/4102 14:39 6,384 266 6118 0.222 1728 5.2 ok ok JS 11/5102 7:45 6,423 259 6164 0.222 1728 5.2 ok ok BM 11/6/025 7:45 6,363 291 6072 0.222 1727 5 ok ok JS 11/7/02 7:45 6,595 261 6334 0.222 1729 6.2 ok ok JS 1118102 7:30 6,274 255 6019 0.222 1729 6 ok ok BM 11/11/02 8:15 6,151 276 5875 0.222 1726 5.9 ok ok JS 11/131025 8:00 6,359 227 6132 0.222 1729 6.7 ok ok iJS 11/14/02 13:50 6,298 181 6117 0.222 1727 57 ok ok iS 11/15/02 8:00 6,272 194 6078 0.222 1726 5.6 ok ok iS 11/18/02 8:45 6,178 166 6012 0.222 1727 5.6 ok ok JS 11/19/02 9:20 6,459 199 6260 0.222 1727 5.6 ok ok JS 11120/02 8:20 6,246 171 6075 0.222 1727 5.6 ok ok Js 11121/02 8:00 6,192 188 6004 0.222 1727 5.6 ok ok JS 11/25102 10:15 6,077 207 5870 0.222 1728 5.7 ok ok iS 11/26/02 8&20 6,480 168 6312 0.222 1727 5.6 ok ok JS 11127102 7:40 6,263 192 6071 0.222 1725 5.6 ok ok JS 12/2102 8:15 6,208 211 5997 0.222 1725 5.6 ok ok JS 12/3/02 8:00 6,191 160 6030 O.22 1726 5.5 ok ok iS 12/4/02 8:00 6,306 176 6130 0.222 1726 .5.5 ok ok iS 12/5/02 8:00 7,289 257 7032 0.222 1727 5.5 ok ok iS 1219/02 8:00 6,997 218 6779 o0222 1727 5.5 ok ok JS 12/10/02 7:55 6,708 168 6540 0.222 1727 5.4 ok ok iS 12111/02 8:00 6,564 201 6363 O0.22 1728 5.4 ok ok iS 12/12102 8:15 6,428 209 6219 o.22 1727 5.4 ok ok JS 12113/02 8:40 6,961 240 6721 0.222 1727 5.4 ok ok iS 12/16/02 8:15 7,237 256 6981 0.222 1725 5.4 ok ok .S 12/17/02 8:30 6,593 196 6397 0.222 1725 5.3 ok ok .S 12118/02 8:30 6,745 183 6562 0.222 1724 5.3 ok ok JS 12/19/02 8:10 6,544 199 6345 0.222 1725 5.3 ok ok BM Remarks TE c f
+20% 8,579 /
-20% S,720 39/44
Daily Source Daily Source Range lnstrument:L-2221 # 172035 Probe: L-43-68# 116719 1I, Z g~ In tA
'It, pm, Re o, 144n,.I w E R 46 0 a
-- +20%
vel T~"
* ~~ ~ -"~~ ~~ L
+10%
a.17.
'Hit. RC)
Mj;T l
- Daily Source Counts
* ~ ~-. IT
- L DIN
-10%
*g* Mk7I 17`, a N- A 24q INA
-*--20%
--- Mean Date
Daily 8KG Daily Background Range Instrument:L-2221 # 172035 Probe: L-43-68 # 116719 400 350 - 300 - X Net Counts D. 250 200
----20%
150
*Average 100 Date
). I,. ..
UVAP DAILY FIELD SOURCE CHECK LOG - FIELD INSTRUMENT Source TypeSCs1371199cs250-0289 Source ActLviy: 8.95uCi pCi Instrument Microrem SIN: C669J Voltage: nla Cal. Due: S108102 Detector n/a SIN: n/a Threshold: n/a Cal. Due: Iva Date rime Source Check Bkg. Net Eff. - batt. Spkr. Phys. By ______ _ ___ uRenm uRem, _ _ _ _ _ _ 7/22/02 07:55 8000 8 n/a n/a n/a ok ok ok DM 7123/02 7:23 7500 8 n/a n/a n/a ok ok ok BL 7124/02 7:35 7900 9 rda n/a n/a ok ok ok AT 7130/02 8:05 8000 8 nda r/a n/a ok ok ok BL 7/31102 8:00 8000 5 n/a n/a n/a ok ok ok DM 811/02 -7:45 7500 6 n/a n/a n/a ok ok ok AT 8/5/02 8:15 8000 5 n/a n/a n/a ok ok ok AT 816/02 8:15 7500 5 r/a n/a n/a ok ok ok AT 817/02 7:30 7500 6 n/a ri/a n/a ok ok ok BL 8/12/02 7:32 7500 5 n/a n/a n/a ok ok ok DM 8113102 7:55 7500 5 n/a n/a n/a ok ok ok DM 8114/02 11:00 7500 7 n/s n/a nla ok ok ok BL 8/15102 12:45 7500 5 n/a n/a n/a ok ok ok BL 8/16/02 14:15 7500 9 n/a n/a n/a ok ok ok MW 8/19/02 08:00 7500 9 n/a n/a n/a ok ok ok MW 8/20/02 8:00 7500 10 n/a n/a n/a ok ok ok MW 8/21102 12:00 7500 10 n/a n/a n/a ok ok ok MW
._ a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a ii/a n/a n/a n/a n/a n/a n/a n/a n/a n/a rna n/a n/a n/a nla n/a nra n/a n/a n/a n/a n/a n/a n/a Remarks +20% 9,000 ( (Dally Calculated Efficiency)
(A)- (B) (D)
-20% 6UW000 7mrvj 42/44
Daily Source Daily Source Range Instrument:lMicro rem # C669J 10,000 pzg '. -"k ~< . 9,000 1;OK 8,000 +10%
-OM-0~ 7,000 - Daily Source Counts TATI Gi ia lp 0 % L -
6,000 -10% Elx ~ ' 5,000 - ~ i
---- 20%
eMean Date I ¢: L
Daily BKG Daily Background Range Instrument:Mlcro rem # C669J 15.0 - ' 9.0 II, I I1 F 14.0 84.0 - '. fic
+1 0%
12.0 a L A i .i 17.0 i s -A flti a uRem 32.0 -
-10%
4.0 I t
-i-a-20%
xbAverage Date
ATTACHMENT 2 CHARACTERIZATION SURVEY DATA 1/133
UVAP _______ Radiological Survey Formn Location, RWPN1WP jSurvey # ye age I of I PSre Cavalier Reactor I UVAP 0171 Characterization-Comments: Surveyed By: Date: Is ument Serial 8 Col. Due Probe Area Serial 5 CaL. Due a Elf. 0tEff. a Bkq. kgt a L. §urveyof the Cavalier Roonl Floor Frank MIra .t 08P,9102 IT-elnee 840152 5/15103 Wea nra Wea na Na nWa Ws WS W nra
~08/20/02 N -north. E =east.Z =eievation Blobb Le IIM ReviewedB.
V2221 21 Date: II ml, TRern 157031 172051 C889J 4/3/0 4/8/0 10/812 44-10 n/a 43-08 128 Iva 188956 118718 nra 43m0 48103 n/a Wea nra N~a Wsa Wea Via N a1 fir Iva
~e rda Va nra nWe Iva nra
~ ~ ~ ~ F3gI Myers jrank 0 1222 138352 4/r3/03 43-37 56 161368 4/=3/0 2 r r /
Key:I Q) =Smearxinto ,oo= Direct Frisk r#ara e -beta lose rate In mRad/hr -X--X- . Boundary SOP Step Off Pad x/trcontact/i2 dose rat. Az General doeserate Smears________ GamaSa Ih e cn______Static Counts Coordinates 2 Gross CPM DPMlloacm Gross CPM un-tsper Minute DPMIIOOCM' No. a* CL 1 lgo. No.1 Unsh~ Shielded Net . Northi East Eleva ion I See 1 See Attached Sheet 1 473 374 365 166 1 3 0 2Attached 2 2 478 338 517 158 1 4 0 Reot 3 584 379 757 187 I 5 415 362 3502 185 14 3 3 0 165 402 34 0 72 1 59 3 4 0 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 17 6 317 3217 .515 154 3 a 0 _ _ _ _ _ _ _ _ _ _ 193 7 90 378 44 167 3 7 0 20 385 3452 489 161 2 6 0_ _ _ _ _ _ _ _ _ _ _ OC1013 88 3 62 223 154 3_ 8 0 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 2II 1 3 33 3 07 96 151l 4
- 2. 0 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
22-1 2 330 305 924 150 2 2 0_ _ _ _ _ _ _ _ _ _ _ 13134 3 32 350 -68 161 6 4 0 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 35 Is35 35233 302 -103 143 6 5 0 I6 36 363540 316 140 153 7 14 0 37 37 37 360 379 .70 167 7 2 0 38 38 38 371 373 -76 166 3 a 0 _ _ _ _ _ _ _ _ _ _
- 39. 3119 3938 3278 203156 7 4 0 40 40 40 3 58 3 96 -4 0 171 7 5 0 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
2c 21 2C 344 351 g26 181 7 5 *0 _ _ _ _ _ _ _ _ _ Form SEC-RP-21 2 Rev 0
WU 0171 R. L6E16# J! =SURVe Pol TS 3 _ Z=O 5 5
.in/
rfll 0t 7
., l i S I Ia I-1 (7
a
. -X 0 . (D I GRATIN&
OPEN PiT l I ffi )D i cI S I 7 I rLo O1.
- 31133
uvA Olm 9-20-02 R. LtIQ6
.# =CENW~C j~f DosE gAM-S IN MlCkREAAM/if&
s 2 _ 7 I 1 _. I 7 7
$- Is 7
7 7 V1 7 7 7 /o
.2 2 i 3- '1 S 7 FLtbRi 4/133
UVA OJ°Y loo% SO&ME *5,cVJ WINt PD L,2g -1(1570I3( J MA E4, Lq10DX Isc/s/ 3 4 CAL DOE All3/03-1 I S 7 along 5/133
?120o/.Z R, L6/66' 1000 Sj)u4C6ASCAN
> E LT 12Sq Y3.37 s 1.7T3A ITD PAo8E m A AP Itl 13/6S A AA A A A Al: CLDO -0 I
3 5S 7 R~oo,~ 6/133
I.I LB5I00-W Low BackgroundCounfinq Sysfem - SmearAnalysis Aphaeicency log fle th230ab Alph Efficdemy 25.7M 0D6: 2094 AlphWa nctknIe(DPMY): 10.00 Alph tb Beta Cro&M* 26.85% Counth Unit Id: I Beta *Acty ctlon Ieml (DPM): 50.00 Alpha Backgrouid (CIPPM: 0.445 Data fib nf: d3BJJNlT1SME1B004),UD Ccaanty bM for MDA md o: 95.00% Alphs Cmvrclii Factor 1.000 BaldtEriadWM 8/19194t9:03 Hlgh VdltaeW Stng 1350 ldkncylobgfllk to9't Crosstalk Cetkm NtApplWa Beta Effidef. 30.83% Application R&Aslorr 3 Beta IntoAlph Crosstakc 0.10% AppllcafkrimVeL Standard Bea BSafkraimd (CPM): 1.765 Batch ID: WA-171 Beta Crecmtion Factor 1.000 I~c r1 X._ J -
^-p~m AG~vtIyq Beta Aetvttv Caurt Alpha BWa CoIPon
- I --.. - A-Laneq IDP'M . +-
l1tks MDA DPM a- -L flao MDA.. tkne (mn) CPM CPM Date-Thu 31 -1.727 3.89 <MDA 19.04 7.25 6.51 <AL 22.99 1.00 -0.445 2.24 81914 1815 32 9.918 8.74 AtAL 19.04 4.01 5.63 <MDA 22.99 1.00 2.655 1.24 8/1l9/4 1816 33 -1.727 3.80 'MDA 10.04 0.76 4.60 <MbA 22.99 1.00 -OA45 0.24 6/19/94 1817 34 2.154 3.84 eMDA 19.04 4.01 5.63 <MDA 22.99 1.00 O.t5 1.24 8/19/94118 35 2.154 3.89 <MA 19.04 23.47 9.81 eAL 22.99 1.00 0.655 7.24 819/64 1&M0 36 -1.727 3.89 <MDA 19.04 -Z48 3.2 <MbA 22.90 1.00 -0.445 -0.77 811994 1821 37 -1.727 389 cMDA 19.04 4.01 5.63 <MDA 2299 1.00 -0.445 1.24 8/19M4 18:22 1I 38 2.154 3.89 MDA 19.04 7.25 e&51 'AL 2299 1.00 0.555 2.24 812JI94 1823 39 -1.727 3.89 <MDA 1904 0.76 4.G0 <MbA 22.90 1.00 -0445 0.24 8119M/4 124 40 -1.721 +/-89 MOA 19.04 401 8.83 <Mt)A 22.99 1.00 -0.445 1.24 8/19/4 18i25 41 -1.721 3.89 <MWA 19.04 0.7s 4.00 cMbA 22.90 1.00 -0.445 0.24 8/1904 i827 42 2.154 3.89 <MDA 19.04 7.25 6.51 -4L 22.90 1.00 0.655 Z24 8e194 18;8 43 -1.727 389 <MDA 19.04 0.78 4.60 <MDA 22.99 1.00 -0.445 0.24 8/1994 1829 44 Z154 389 <MDA 19.04 0.76 4.60 <MbA 2299 1.00 .555 to I)0 45 0.24 8/19/84 1830
-1.727 389 <MDA 1904 -5.73 3.27 <MDA 22.99 1.00 -0.445 -1.77 81M194 18:31 48 -1.727 3.89 qDA 1904 -2.48 3.28 <MDA 22.99 1.00 -0445 -0.77 819194 1832 47 -1.727 3.89 dUDA 19.04 0.78 460 <MDA 2299 1.00 -0.445 024 B11994 18:33 48 -1.727 3.89 <MDA 19,04 1049 7.28 CAL 22.99 1.00 -0445 324 8/1191418:35 49 -1.727 389 .cMDA 1904 .248 3Z0 <MDA 2299 1.00 -0445 -0.77 8/19M4O1M 36 50 Z154 389 <MOA 19.04 *,2.48 326 <-MDA 22.99 1.00 0 655 -0.77 8U19/94 1R37 96 2.154 3.89 <IidA 19.04 .2.48 3.28 <MDA 22.90 1.00 0.t5 -0.77 819/04 1'38 51 6036 550 AAt. 19.04 0.76 4.60 <MDA 2299 1.00 1.5S5 0.24 3/19/9418:39 52 Z154 389 cMtA 1904 078 460 <MDA 22.99 1.00 0.555' 024 811919418:41 53 -1.727 3.89 MDA 19 04 -Z48 326 <MDA 22.99 1.00 -0445 -0.77 81S/94 18:42 54 2.154 3.89 <MDA 19.04 7.25 6.51 <AL 2Z99 1.00 0.655 - Z24 8/19/0418:43 55 -1.721 3.89 <DA 19.d4 -Z48 326 -<4A 22.99 1.00 -0.445 -0.77 8/1194 1844 56 2.154 3.89 <MDA 19.04 -Z48 3.20 <MDA 22.99 1.00 0.555 -0.77 A l& 8t19/94 1545
--I LB5IOO-WLow Background Count!np System - SmearAnalysis Alpha effcency log fthZ3MOd Alpha Effldecy. 25.76%
Dt 620/94 Alpha9thty actin eve (DPM): 1000 Ald to BeaCrosstk 21M5 CountIng Unt kI I Bela bctty action "ei(DPM): 60.00 Alpt Baclind (CPM): 0.445 Data file ram C:Bl.LJUNIT1aSME1 sW34XLD Ceftnty rul for MDA and Als: 09.00% AXphab C4~eft Fadtr: l.O Batch Erded: 8/19/94 1i03 Hgh VdIVO Slngy 1350 BZ efcMien byeXtdlfcab CrmsstakConrdlok4 NotAgpled Beta EfflcWW 30.53% Akppflon Rfeblon: 3 Beta ntoAphaCrsstc 0.10% ApplMcon VeskMI Standad Beta Badkgund (CPM): 1.765 Batch ID: WA-171 Beta Carein Fador 1.000 Alpha ActIlvty Beta ActIvIty II Count Al Beta Completbon DPM o flogp IDA tIPM a fl MDAltiOmsndn) CPIM CPM Date-Tkn
- I 57 -1.727 3.89 MDA 19.04 _
U.1 fi 4.60 <MDA 22.99 1.00 -0.449 0.24 5/191941W46 58 -. 7271 3.89 MDA 19.04 .2.48 326 <MOA 22.99 1.00 -0.445 -0.17 91W4 8'48 O 59 -1.727 3.80 MDA 19.04 -2.48 328 0MDA 22.99 1.00 -0.445 -0.77 8O4 18:49 60 2.154 389 <MDA 19.04 7.25 8.51 <AL 22.99 1.00 O.555 224 W194 18'50 61 -1.727 3.80 eMDA 19.04 401 5.63 cMDA 22.99 1.00 -0.44S 124 W019/4 18'51 62 3.89 -DA '1904 -8.73 3Z7 <MbA 22.99 1.00 0.555 -1.77 8/19/94 18'52 2.154 83 Z.154 3.89 'MDA 1904 7.25 6.51 <AL 22.99 1.00 0.555 Z24 d1994 1854 64 -1.727 3 89 <MOA 19.04 0.78 480 'MDA 2299 1.00 -0.445 024 89194 18:55 o3 65 -1.727 389 <MOA 19.04 401 5 63 dMDA 22.99 1.00 -0.445 124 8/19t9418:56 68 Z154 389 NMDA 19.04 -Z48 3.26 4MDA 22.99 1.00 0.55 -0.77 81W941857 67 * -1.727 3.89 <MDA 19.04 4.01 563 <MDA 2299 1.00 '-0.445' 124 EV19/94 18.58 68 9.918 6.74. AtAL 1904 0.76 4.60 'MDA 2299 1.00 2.655 0.24 8/19/9418*59 69 2.154 389 <MDA 19.04 71.01 563 <MbA 2299 1.00 0.555 1.24 El194 19 01 70 6036 5.50 AIAL. 1904 '4.01 583 CIDA 2.99 1.00 1.565 124 8/9194 1W.02 94 -1.727 3.89 MOA 19.04 7.25 6.51 <AL 499 1.00 -0.445 Z24 8/19/04 19.t
UVAP ___ ____ ___ ___ ___ ___ ___ Radiological Survey Form LoatonSurvey # 09 Survey Type: Page I of 13 Comments,_____________ Survoyedt B3y: Date: Instrument Serial If CalDue Prob~eAreal Spirial Cal. Due ct Eff 0 Elf i Kg. II 13kg tt L~ It L Cavaier_ all Alice Thorrpson 43e 08/27/02 Ternelec 64052 /IO= to na n/ ri/a n/a Wsa fla n/a n/a n/1 ni/a
. ..... Bobby Leigh 05,127I02 IA2221 '72051 /0=3 43-88 126 11678 AIM,0 MI/ 0 215 nt VIV Wea rifa
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LB51OO.WLow Background Counting System - SmearAnalysls Alpha bg fik 2306b HfdRc AwftaEm 2q.7" O'* 517Jg4 AM bwOYWdU( MD (DPM): 1000 APhOtb Bea Cr*mtk 2.655% Cwr Un Ung id: i BOSf aWYOl SOq (DPW.: 50 W0 AV a r&md (CMPR: 0 445 data fle nil* C:\1LBXLMJj81%I1D737.gfl CaWnty WlM fo MOA Gd fi4! Od 00% bwth edw: &/4 14:31 BbW odwcy IMFhk IC090 , ,
.HblV85Wnr 1350 sbrt CD:Batch uo NO Ap beta EfflOd.y 361.4%
Apokd)M keSklr 3 BMl WaAa Cftsat 0.10%' AppbcatonVetskIn: Stmtdad Bea Badvotwid (CiM): 1.7B5 Batch ID: tp0194 Beta CaTdkm Fator: 1.000 0 .Y_ Alpha Activity II II - .I b1b Activity-. CouLn Aph Beta Ca Carrl i rn \ a JIMS MDA I I DPM a fltak MDA --- . Th"M Dab
- PjM.* fir rlnihi CPM CPM b ...
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1 2.194 3.89 -MOA' 19.04 07le 4.00 4$ '22.9 1.D 0.6B5 0.24 W2114 13rQ2 2 2154 380 <MDA 19.04 0d7 4 60 <M41t 22.9 024 &27/04 13153 3 -1.721 t.80 4WDA 18.04 1.00 -0445 0.77 0/1194 1384 4 -1.721 -1a 3.26 4M~ 22.99
.q -0.445 -1.7t 71114 1358 b -1.727 389 (MOA 19.04 IJ-I Q.51 k-AL ago9 i.00 -OA4 224 51014 1.57 a aw30 5.50 AtL 19 04 0.16 4.60 4rlDA 22.9k 1.00 1.5m 024 Wt214 13:S8 7 Z154 3.89 <MOA 1904 1.25 8.81 cAL 2Z99 1.00 0.555 2.24 &27/94 13:59 a B.038 5.50 3.89 AZAIA 1904 2D23 924 eAL 22.90 1.00 1.655 6.a4 02t194 14:00 1154 4MOA ig.64 O.tB 450 A" 220k 1.00 0.24 3.88 189 6.5S /7194 14:01 10 -1.72t <MM 19.04 die 4.60 -4&aB a2. 1.00 -0.445 0.i4 5114 14,03 11 -1.721 3.89 4MIJA 19.d4 O.As 4.00 41DA 22.90 1.w 4.445 0.24 8W21/4 14o04 12 6W6 5.50 AtA,4 19.04 4.01 5.53 cMWA 22.90 1 00 1.5' 1.24 8W1114 14:05 13 -1.721 3.89 -CMDA 19 04 13.74 7.98 -AL aZ99 1.00 -0.445 4.24 5/2.194 14.5 14 -1.727 389 'MOA 1904 0.10 4.00 4NDA 2290 1.00 -0.445 024 8/1,7t4 14:07 15 -1.727 3.89 tMOA 1904 1.25 e.1 eAt. 2299 1.00 40.445 224 e/27ls414.:9 16 -1.727 3.89 <4c13A 19.04 0.70 460 MMDA 22.99 1.00 -0445 024 /27194 14:10 17 6.036 5.50 AlAL. 19.04 -5.73 3.27 <MDA 22.99 1.00 1.555 -1.77 /27/94 14:11 18 -1.727 3.89 'MDA 19.04 -248 316 <MDA 22s 1.00 -0.445 -0.77 8=27/94 14:12 19 2154 389 kMOA 19.04 7.25 8.51 tAl 2299 1.00 0.555 224 Wtt74 14:13 20 O.03 5.50 AAL 19.04 4 01 5.63 AftA 2ZS9 1.00 1.t55 1.24 127104 14:14 95 .154 3ss -MDA 1904 401 5.63 <M1A 22.99 1.00 08t5 1.24 WI214 14:16 21 -1.727 3.89 4MIA 1904 10.49 1.28 tAL 2299 1.00 -0.445 3.24 ' 2.,4 14:17 22 -1.721 3.89 'MM 1904 0.16 4.60 <*1A 2299 1.00 -0.445 024 5W194 1t418 23 -1.721 389 .cMVA 19.04 0.76 4.50 <MA 22.99 1.00 -0.445 0.24 8/2719414:19
-1.724 389 CMDA 1¶.04 1049 t.28 -AL 22.9 1.00 -0.44- &24 8219414:20 25 M154 389 <MOA 1904 4.d1 5.63 t4LA U29 1.00 O.5S 124 A'104 14:21 2o O.03 550 AItL 1904 4 01 5.B3 <MEA 2299 1.00 1.855 124 e1W/I4 14 23
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Y." LB5100lWLowBackgmundCoun ingp Systin 0 - SmoarAnalysis Alpha defency tog flleU30ab AM *4 ayatio 25.7Q% A~dh .toh&Ef.t~y: WeM (DPMY 10.00 comuN Une kt: I a,asf* 2 4 2d.C Stat *&Y actk WM (DPM): 5000 Alphi d*nxi (dmA). 0.448 Dala flb r*r* C:V1xrj.lT\SMEt1X=.i'J BtlEfwded:,?/94 14431 qenrthiy I.o fr WA fidgs! 0.OQ% CM:ostE11K feW* NgApp Klth Vt&at S#. 1:5o Bob t BMa Eh:cWW 2.3% Appkdl ke*lbW t f Into A411a drOssti 0.10.Q AlpebmVevir tfa~da BalcF ID: uva,-0194 Bea &mJun(dO"M): 1.7M Alpha Activity ii ' .Beta, Cmctin Factr 1.00tl
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28 O.W6 &SO AAL O.1
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3.80 4WMI).A04 '6.24 0/94 J*4:
- 1 :Lts4 380. .AA ig.01 4.01 9.03 <4DA 2.a 1.00 645' U44' *5/l4 1410
- 2 -7 389 <W MDA 10t04 4.01 5.53 I.Od O.*S ,i1;4 tll9414::g8 go 48.117 11374 *
- 7. <WA
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UVAP Radiological Survey Form Location: IRWPIUWP jSurvey S Survey Type: jPage l of 10-CaalerRectr VA 016 Characte. zat-o-Comments:. Surveyed By Date: instrument Serial a Cal. Due IProbe Area Serial 4 Cal. Due aiEff. p Eff. et Bkrg. PBPL Sryof the Cavalier Pit a1r0 ersr Iinlec. 64052 5)15M0 n/a na uWa Iva WSl Iva We riga V Iv / Ws N anorth, E =east Zeelevation B~obby Leih h (, -2... 05114102. 142221 157031 4r310 44.10 Wie 186956 4r310 Iva Wsl n/a Wia Wil Iva __ _ -222I 172051 4/81W ~43-68 126 116718 41810 rile -0215 rye iWa wea n/ ___Reviewed B' Data: 142.221 1385 41313 _43-37' 585 15138 4113 Ive 0.21a iv. iv Wsa n/ gr -n jT GInCP FWMyes de=8 9J!em10 T n/a n/a ril We________Ws__ W Ke:IY QY=Smear xxx to joo=Direct Frisk CAalr sample E. =bet- dose rate in mRadfhr =XXBoundoary SOP Stee Off Pad xi/y CanlacUl2' dose rate 4f eleribal doerate Smears Gamma Scan Aipt eta= Scan- Static Counts Coordinates Gross CPM DPMoo0 W - Gross CPKI ___ Counts per Minute _______0_____ No CL CV N'o ______nsh Shieed R Ne L. North East _________n 1 See ___ I SeeAttached Sheets 1 396 266 408 145 1 1 -2 75 2 Attached ___ _2 ______ 3-88 -299 329 149 1 2 . 2.75 3 Report 3 -- 405 291 421 147 1 3 -2.75 44 4139 285 __95 145___..7 5 51 F34___ 2_3 214 _4_ 5.27 6 __6 6 464 274 701 142 2 1 .2 75 __7 __ 7 7 403 243 691 134 2 2 -2.75 8____8 8 405 301 384 149 2 3 -2.75 9 8 422 252 628 137 2 4 .2.75 1010 10 434 284 554 145 2 5 -2.75 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 12 1 II 11 348 273 277 142 2.25 1 -1 121,12' 373 296 271 148 2 25 _ 2 -1 113 3 O_____ 13 378 264 340 145 2 25 3 -l 14 .14 14 433 1297 502 148 2.25 4 -1
'15 15 16 462 1291 831 147 2 25 -5 .1 16 1s 16 412 284 472 145 2 25 I -2 1 17 398 261 508 139 2.25 2 -2 i 18 451 250 742 138 2 25 3 .2 11919 578 267 1141 141 2.25 4 -2 22020, 500 277 823 143 2.25 5 -2 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
QCCC.491 289 746 146 2 25 5 _ -2 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 212121 450 251' 698 139 *.05 5 -1 22 22 22 431 250 658 136 0 25 4 -1 223? 420 292 472 147 0 25 3 -1 24_2424_ 36 264 365 140 0 25 2 -1 252 2 7 240 480 133 0 25 1 -1 ____604__246 1322 135 0 25 5 -2 227271 544 248 1093 135 0 25 4 -2 2828Z 872 243 1584 134 0 25 3 .2 29 29 __ 29 389 247 524 135 025 2 -2 30382 300 254 472 137 025_ 1 -2 1 11 31 382 272 332 142 1 0 25 -1 32____32 2r 388 251 425 136 1 0 25 -2. 3 333 455 267 694 141 1 0.25 -2.75 34 34 __ __ 341 454 286 620 145 1 5 75 -1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 33535 482I 249 '860 136 1 5 75 -2 363136 379 268 417 140 1 575 -2.75 37 ______ 37 7-386 255 1776 137 0 25- 5 25 ___ ______ ___ 38! 685 240 1643 133 025 5 25 25 39 39___ __ _ _ _ _ _ _ _ 39i 740 283 1687 145 0 25 55 25 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 40_ ______40 770 280 1883 139'- 0 25 5 75 25 QC__ _____ QC 731 2500 17;76 136 0 25 5 75 25 Form SEC-RP-21 2 Rev 0
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LB51OO-W Low Backgmund CountUng System ..- Smear Analysis Albpa ffibncylog: bth;3ab Alpha Efficy 25.76% Date: 8/15194 Aih adlvfy action WW (DPM): 1000 A to Beta Crosataic 28.85% Ccun Ungt Id:I Beta actit acmt kd (DPM): 50.00 Alpha BaciWd (CPb: 0.445 Deabienme: C.NMl MITISMEIAD14.X Ceratety iv for NMAad fl: 95.00% Apha Corcl Factor: 1.000 Balch Ended: V15194 13:2 High Vcge Seftn: 1350 Beta Slitn log fir Icgb CsaMk Corectdo Not AppWd Bdta EMdfcn 30 83% Apatim Re&isbn 3 Betd ntoAlha Cstatc 0.10%* ApplcatiVemrlo Strard Beta Badgwwnd (CPR: 1.765 Batch ID: UVAP-0167 Beta Corecton Factor 1.000 tr . Alpha Activity Beta Activity Count Alpha Beta COnpOM 1I II. Cafla = DPM_ a . flans . MDA . DPM a flog MDA 1Om (rnin) CPM CPM Da - Thin 1 2.164 389 <MDA 19.04 4.01 5.63 4MDA 2299 1.00 0.555 1.24 8154M 12:38 2 9.918 6.74 AtAL 19.04 -2.48 326 <MDA 22.S9 1.00 7Z555 -0.77 /15/94 12.40 3 -1.72 3.89 'MDA 19.04 7.25 6.51 <AL 22.99 1.00 -0.445 2.24 8/15194 12.41 4 Z154 389 cMDA 19.04 0.70 4.60 .MDA 22.99 1.00 0.5S5 0.24 8WS94 12:42 5 2.154 389 CMDA 19.04 10.49 7.28 'AL 22.99 1.00 0.555 3.24 8115Y9412:43 6 2.154 389 <MDA 19.04 7.25 5.51 <AL 22.99 1.l Q555 2.24 8/15Y8412.44 7 2.154 389 <MOA 19.04 10.49 7.28 <AL 2Z.99 1.00 0.555 3.24 8/1S594 1245 8 8.038 5.50 AtAL 19.04 -248 328 <MDA 22.99 1.00 1.555 -0.77 8/159412t47 9 2.154 389 cWA 19.04 1049 7.28 cAL 22.99 1.00 0555 3.24 8V15/9412.48 10 -1.727 389 'UDA 19.04 4.01 5.83 chMA 22.99 1.00 -0.445 1.24 8/15M141249 11 2.154 389 <MbA 19.04 4 01 5.53 'MDA 22.90 1.00 0.555 1.24 8/1594 1250 12 -1.727 3.89 <MDA 19.04 4.01 563 -MDA 2299 1.00 -0.445 1.24 8/18194 1Z51 13 Z154 3.89 <MDA 19.04 4.01 5.e3 MDA '299 1.00 0.555 1.24 8f15s941Z-53 14 6.030 5.50 AtAl. 19.04 13.74 7.98 'Al. 22.99 1.00 1.555 4.24 V151D4 12.54 15 -1.727 3.89 <MW, 19.04 7.25 6.51 MAL 22.99 1.00 -0.445 2.24 /1519412t55 16 .1.727 3.89 <MO)A 19.04 -5.73 3.27 4VA 22.99 1.00 -0.445 -1.7 8/1594 1t255 17 2.154 389 <VMA 19 04 -248 328 4vMDA 2299 1.00 0.555 -0.77 U15194 12S57 18 2.154 389 <MDA 19.04 7.25 5.51 <AL 22.99 1.00 . 0.555 224 81151941t258 19 2.154 3.89 <MDA 19.04 10A9 728 'AL 2299 1.00 0555 3.24 US t5 13:00 20 -1.727 3.89 <MWA 19.04 7.25 6.51 MAL 2299 1.00 -0.445 2.24 8/15'9413:01 91 6.038 5.50 AtAL 19.04 1049 7.28 'AL 22.90 1.0 1.555 3.24 IV15/941302 21 6 03 550 AtAL 19.04 16.98 8.63 <AL 2299 100 1.555 5.24 8/1519413:03 22 2.154 3.89 'li)AO 19.04 1049 7.28 cAL 2299 1.00 O.S5 3.24 V15194 13:04 23 -1.727 3.89 <IMOA 19.04 4.01 5.63 <IDA 2299 1.00 -0.445 124 8/15/9413:05 24 2.154 389 <MDA 19.04 16.98 883 'AL 2299 1.00 0.55 - 5.24 8V1519413.07 25 -1.727 3.89k, <MbA 19 04 4.01 5.83 <MDA 22.99 1.00 -0.445 124 f/1519413:08 26 6.038 5.50 AtIA 19.04 0.76 480 4MDA 2299 1.00 1.65 . 024 8/1W5413:09
- . ,t LBSIOO-W Low Background Cour.ling Sysenm *- SmgarAnalysis AM elb>icy g f O230ob AlM Ellhncr 25.76%
D0a.8/1594 AlhaVM AytYdebI&(DPt): 10.00 Alphato BetWCrm*h* 2.165% Cwntlld Unk I: 1 Odaact*y mom IM (PM: SO.00 Alpha hakow (cP. 0A45 Dsa fe nab* C:LBXLUNlT1%SMEAl14.uLD Cwelmky kr for MOA MdA Ome 90.00% Ah OCgdim Fbad 1AM Batch Erknde 8h15#94 13:26 HghVdtrsSdt. 1350 Beft M ancy N Ih tc9 Croeadk Cafctsctx NotAppbed tda Effld&W. 30.83% Appkc~m Revi~s*L 3 BftalDtoAk Cmmtakc 0.10% Applcekm Veraktr Stidard Bda BaVMW (CPM): 1.785 BatchID: LJVAP-0167 WAta Cmectlan Factm 1.000 AIE-- A-"-W. AUf 'I rI - * . .- :. 1 _ . _ . : IUII VeHvlS .. . r m s- l .
^r-- J-R --
yS~ _ COjni A"pha BOt CM UMM a 195 MmA i __ DPM_ ff fb" UnAI
..-. w - ,- . ... ..
fU fl* r"-n. MOW FIHI I 2771 V1W 389 <MDA 19.04 II _ _ 1.00 e.53
'Al. 22.99 0.655 524 8/189413:10 28 6.03 5.50 AIAL 1904 18.98 8.63 CAL 22.99 1.0 1.555 524 81599413:11 29 -1.727 389 OMDA 1904 4.01 5.83 d4lA 22.99 1.00 -0.445 t124 W189413 12 30 68.0 6.50 AIAL *904 -248 328 41A 22.99 1.00 31 -1.727 1.656 -0.77 8W154 1314 3.89 cMDA 1904 -248 3.28 -MDA 22.99 1.00 -0.445 -0.77 8/15'94 13:15 32 2Z154 3.89 cMOA 19.04 -5.73 327 <MDA 22.99 1.00 0.665 -1.77 33 8/15/941318
.- 1.727 3.89 4VDA 19.04 078 4.80 'MDA 22.99 1.00- -0.445- 0.24 8/185941317 34 2.154 3.89 cNYJ 19.04 .10A8 863 MAL 22.99 1.00 0.Q55 624 W5/94 13:18 35 -1.727 3.89 4MEA 19.04 I:-10.49 728 'AL 22.99 1.00 -0.445 3.24 35 81&"94 13:19
-1.727 389 .M 19.04 -2.48
- 328 Mcl 22.99 1.00 -0.445 -0.77 811594 13:21 37 -1.727 3.89 <NMA 19.04 18.98 8.63 MAL 22L99 1.00 -0.445 5.24 8/1Y9413:22 38 2.154 3.89 ,:WA 1904 -5.73 327 4NYI 2.99 1.00 0.Q55 39 -1.77 8MW413:23
-1.727 389 <MDA 19.04 7.25 6.51 'AL 22.09 1.00 -0.445 224 40 8/15/9413:24
-1.727 3.89 4c9A 19.04 4.0$ 5.83 4A 299 1.00 -0.445 1.24 8W1594i1325 92 -1.727 3.89 4MDA 19.04 -248 328 <MDA 1.00
;ZOO -0.445 i0.77 /15413i2 4 -
G A M M A S P E C T R U M A N A L Y S I S **** ISOCS Report Generator ISOCSAN.TPL 2/26/96 Report Generated On : 10/28/02 4:12:05 PM Spectrum File Name : C:\PCNT2K\CAMFILES\marisoil\MRS00007.CNF Sample Title : Mari. Soil Sample Identification : UVA-SL-004 Sample Type : MRS Desc. 1 : Cavalier wall concrete Desc. 2 : Desc. 3 : Desc. 4 : Peak Locate Threshold 5.00 Peak Locate Range (in channels) 150 - 8192 Peak Area Range (in channels) 150 - 8192 Identification Energy Tolerance 1.500 FWHM Sample Size : 6.089E+002 G Note: For Point Source, report UNIT = none. Sample Taken On : 8/29/02 8:45:00 PM Acquisition Started : 9/10/02 3:29:27 PM Live Time : 1800.0 seconds Real Time : 1800.7 seconds Energy Calibration Used Done On : 9/5/02 Efficiency / Geometry ID : mari soil Efficiency Calibration Used Done On : 9/6/02 341133
Peak Locate Analysis Report1 10/28/2002 4:12:05 PM P E A K L O C A T E R E P O R T Detector Name: LABSOCS Sample
Title:
Mari. Soil Peak Locate Performed on: 10/28/2002 4:12:04 PM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Search Sensitivity: 5.00 Peak Centroid Centroid Energy Peak No. Channel Uncertainty (keV) Significance 1 299.31 0.2550 74.87 5.49 2 308.18 0.2274 77.12 6.38 3 952.89 0.2271 238.41 5.27 4 1178.82 0.1916 294.94 7.08 5 1405.42 0.1543 351.64 10.30 6 2434.08 0.1656 609.01 7.52 7 5838.87 0.1077 1460.89 12.35 ? = Adjacent peak noted Errors quoted at 2.000 sigma 351133
Interference Corrected Activity Report 10/28/2002 4:12:05 PM
- N U C L I D E I D E N T I F I C A T IO N R E P O R T *****
Sample
Title:
Mari. Soil Nuclide Library Used: C:\GENIE2K\CAMFILES\uva.NLB
.................... ...IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/G Uncertainty K-40 1.000 1460.81* 10.67 3.54240E+001 4.39162E+000 PB-212 0.806 74.81* 9.60 1.15789E+000 3.72800E-001 77.11* 17.50 9.13443E-001 2.28520E-001 87.20 6.30 238.63* 44 . 60 1.70747E-001 1.19800E-001 300.09 3.41 BI-214 0.409 609.31* 46.30 5.27253E-001 1.92015E-001 768.36 5.04 1120.29 15.10
- 1764.49 15.80 PB'214 0.794 - 241.98 7.49 295.21* 19.20 1.12257E+000 3.54082E-001 351.92* 37.20 1.13597E+000 2.55689E-001
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.500 FWHM Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma 36/133
Interference Corrected Activuity Report 10/28/2002 4:12:05 PM
- I N T E R F E R E N C E C O R R E C T E D R E P O R T *****
Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/G ) Uncertainty K-40 1.000 3.542403E+001 4.391624E+000 PB-212 0.806 3.928326E-001 1.020512E-001 BI-214 0.409 5.272527E-001 1.920151E-001 PB-214 0.794 1.131376E+000 2.072918E-001
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis Q = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma U N I D E N T I F I E D P E A K S
- Peak Locate Performed on: 10/28/2002 4:12:04 PM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS No. (keV) Counts per Second % Uncertainty All peaks were identified.
371133
- . r-;
"I UVAP Location: - -RW tW Radiological Survey Form Survey S UVP08 Survey Type: Pag Io 6 Comments: Surveyed By Date: Instrument Serial # Cal. Due Probe Area Serial # Cal. Due is Eff. P Eff. ot kg. PBkg iiL pL Nnorth, C- east lvto______lobby B Letg ~ 82/2 M-2221 151031 4/3103 44-10 nila 186958 4/0103 We/ Wea ri/a Wi/ ria n/a tlgA C-22inRvi2e1 Dtei72051 4/8/0 43-68 126 116715 4/813 WSa 0215 lila n/a WSa n/a gkey In 01F SMea C Fratnk MyirctFise- mW 12Pd I --- -= tp -I enra2 Keyxx tQ-mo=Drec a S Fsk iL, ='rsamle8 btads teI mRad/hr _______ =Boundary SOP ___StepOff Pad _ contact12- dose rate Ger dose rate Smears_______ Gamma scanI Alpha Beta Scan Static Counts Coordinates 5
Gross CPM DPM/lO0cm' Gross CPM 17ounsper Minute DPM/1O0CM ___ N~o. CZ QF No-. I No_____ nUshi ShielueI RF Ne L. North East Elevation I See ____1 10000-12000 355-427 1 408 285 45.4 145 15 15 3 __ 2Attached 2 ____2 _ ___ 457 353 384 162 iS5 3 3 3 Report __ _ _3 __ _ _ 3 461 358 380 163 15 .4 5 3 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 4 ___ 4 9600.11300 47'-554 A 530 382 545 168 15 a 3 5 ___ _5 5 508 360 548 163 1.5 7.5 3 6 ___ 6 _ 6 511 358 585 183 3 156 3 7 ___ 7 10500.11600 44'..512 7 453 406 254 173 I 3 3 3 ___ 5 8 a 550 404 539 173 3 45 ____3 __ 99 9 440 414 96 175 3 a __ 3 10 10 8700.11100 488-522 1o 510 342 650 159 3 7.5- 3 Ii1I I 341 339 7 158 45 15 _ __3 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 12 12 11600.13900 47'(-528 1 510 352 583 161 45 3 3 ___ 13 13 1Z 509 381 472 168 45 45 3 14 '14 10300-11600 480-512 I~. 502 384 438 169 6 15 3 ___ Is5 15 _ _ _ _ __ IC 381 403 .81 173 8 3 3 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Is is 16 407 353 199 162 6 4.5 3 17 171 17 518 417 365 176 7.5 15 3 15 16 10000-12600 400-520 IS6 481 415 244 175 75 3 3 QC QC -QC 490 421 255 178 7.5 3 3 I I T 1 I ~~t i tt- - *4 4 ____________ 4-4 4 4-I I I
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LB5100-W Low Background Countng System - SmearAnalysis Alpha eficiency log file: 230a Alpha Emiclency.r 25.7B% bbte 8W2("4 Alh actiMty action level (DPM): 10.00 Alpha to Beta Crosstalk 26.65% Contin" Unit Id: 1 Beta actity actiB Miel (DP"): 50.00 Alpha Badrod (CPNR: 0.445 Data file nane: C:5LBXLWUNIT1WSME1AM25XLD Certainly iel for MDA ad NOgs: 05,00% Alpha Cacrdlon dor 1.000 Batch Ended: 8/20194 148 Hlgh Volage Sftthzlg 1350 Beta ef*InCY log file tc99ab CrosstalkCorrectlon: Not Appled Beta Effcieticy- 30 63% Atplplon AL-hislm 3 Beta oAlphaCrostak 0.10% Applicaton Version: Staidar1 Beta Bacground (CPM): 1.765 Batch ID: WAP-0185 Beta Correction Factor. 1.000
.i Alpha Activity Bots Activity Count Alpha Beta Catpon
- *IF rlCbd
-1 I DPM. -
ffmiq MDA 1I
,I _
DPM a _I.-I MMna MDA tkne min) CPM CPM Dde - Thi 1 -1.727 389 <cMDA 19.04 725 6.51 <AL 22.99 1.00 -0.445 2.24 sn21941626 2 -1.727 389 7.25 8.51 <AL 22.99 1.00 -0.445 2.24 =2194168:26 3 -1.727 3.89 cMDA 19.04 4.01 5.63 MDA 22.99 1.00 -0.445 124 80 41829 4 -1.727 3.89 4MDA 19.04 0.76 460 <'MI 2g99 1.00 -0.445 0.24 &24 1e:30 5 6.036 5.50 At AL 19.04 23.47 9.81 <AL 22.99 1.00 1.555 724 612194&131 6 -1.727 389 cMDA 19.04 4.01 563 MWDA 22.99 1.0 -0.445 1.24 81201041e:32 7 2.154 3.89 <MDA 19.04 4.01 5.63 cMDA 22.99 1.00 0.555 124 8/2019416:34 8 6.036 550 AtAL 19.04 13.74 7.98 <AL 22.99 I.00 1.555 4.24 812019416:35 9 -1.727 3.89 .cMDA 19.04 10.49 1.28 cAL 22.99 1.00 -0A445 324 8/2/4 16:38 10 2.154 3.89 <MDA 19.04 0.t6 4.60 <MDA 22.99 1.o0 0.555 024 W1M14:37 11 -1.727 3.89 4MDA 19.04 10.49 7.28 <AL 2299 1.00 -0.445 3.24 & 1638 8 12 -1.727 3.89 <MDA 10 04 16.98 8.63 <AL 22.99 1.00 -0.445 524 829416 39 13 2.154 3.89 <MDA 19.04 0.76 4.60 MDA 22.99 1.00 0.565 024 MM 94'1eA41 14 -1.727 3.89 'MDA 19.04 -2.48 3.2e cMDA 2299 1.00 -0.445 -. 77 614 16:42 15 -1.7m7 3.89 cMDA 19.04 1049 7.28 'Al. 22.99 1.00 -0.445 324 829416:43 16 -1.727 389 <MDA 19.04 0.78 480 <MDA 22.99 1.00 -0.445 024 8B2019416.44 17 Z154 3.89 cMDA 19.04 0.76 4.60 <MDA 22.99 1.00 0.555 024 8Q019416A45 18 -1.727 389 cMDA 19.04 7.25 6.51 cAL 22.99 1.00 -0.445 2.24 8/209416:47 95 -1.727 389 cMDA 19.04 7.25 6.51 SAL 2299 1.00 -0.445 2.24 82041:48 A(; S,5
LB5100-W Low BackgroundCountikwg System - Smear Analysts Aa Alpha Efficency. 25.76% Datle 8/21/94 Alpha actity actlon Iel (DPM): 10.00 Alpha to Beat Cronsflc 26.65% Camt'ng Unit Id: I Beta activty action 1 (DPM): 50.00 Alpha Badcgkund (CPM): 0 445 Data file naw C:5IBYSUNIT1TMME1A027XLD Ceu'nty WM for MDA and fMPs: 95 00% Alpha Carection Ftor: 1.000 Batch Ended: 8/21194 6.30 Iligh Volta Seg: 1350 CrosstlCorrection: Not Applied Beaa Efficiency. 30.83% z ApplicatIon Revsion 3 Beta Into Alpha Crosstal 0.10% A4pflc3p!onVemUion: Standard Beta Background (CPM): 1.765 Batch ID UVAP-0165 RECOUNT Bdta Corection Factr: 1.000 I Ainhs Activity BeSt Activity I Count Alpha Deta Ca" I - II - AMDAI time (in) CPM CPM The MaCP I- _ -~am n- UnA 11 OMU n [M
=l UrM __- _ __ ... w14 11W, 13.799 7.79 AIAL 19.04 l1l 3.74 7.98 <AL 2z99 1.M 3.55 14.4 V0l 1-4,.
I SII I.
Lhtion: ava Reae# r RdooiaSurvyAor Caaler RectrVAP urveTe:a vaertCa mrea~ 3204 o1 SuT d Dae lnstnument Characterization ell# Cl Due Probe AraSrag Cal. Du El. pE, a8k pkg . pL Key: Serxx o~ Direc air sampe8rns
-rs l.I nf~ --
L I ro Gamma Sc l AlphaBet Sc
------ -.. tatic
,.,..-,., -A-A Ii"d WY- CDMMW1Z'dosjrsj
-1 G 3 CpM Counts nu e Milo x rmal doze rat Coordinates as 0-12000 3-34 139 2-7 1 11300 1 1
149 2 7
-100 138 137 78 5 144 00-119 3 -II 54 1 28 W6 36 1800 1-388 14 1 1200a a TO 14 14 6 Z10 Q 12800 5 QC 2 -3 fV; I
4
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- SuRVEY POINTS SHIELDOD PAGE 2 UtJSHIlL 6ED CLOSED CAGE
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U2IV odor 2 27-o6 R. A,IC/0 ARES scSNlvmD W17W L; I7&OSI Wrfli PRog6 q3.?g It PPR /14719. 4 AR SCANNAE I MEW,- -SVUAR _ CGEG CLOSED 6,q TC CE$T 3.-75 NORTH 2.75
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UVAP 60,6q A.A. LEtR6 ARC6S SCAVNTSD WIT7I Lp4a l PA6C I
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WeIldaoWin (dPM: 1.765 l!~,* .r 1. :ll BstQ ConeIjon Fedor 1.000 O * * : ,;,Adni
-'--M-WF(IP eisk$,Sta'~dhtt V~ctkfty~twm 11I r. t . *M. it =h 0 na-4 t-.
t't ' .' ' I .I . .- tk (MM) NIA PM Bet Cpm CaT T'eo 1 Data-Tkw 2 6.80 -CMIA i .O4 1.00 0.605
.1.721 7.25 8.51 2.24 W4 8:40 ML 22.99 a 154 .to bDA 1g.ft 8.81 < =2. .do -0.445 2.24 8 8:41 "MM. 19.64 l0o 4.600 ' t 1.00 O$ms 0.041 6.74 22I. 9 04 82O46:42 bAi ~4ADA i9.04 t a8 4 2z.9 1.00 2.o 32.4 0.74 - dle &704&44
. b d.Ow h4A 0P.04 4.t0 2zbg 1.00 f5 bad - YJ5
. 0,4 8a*;4$
b AtAL t i.04 Q8.1 kAL Z29o j.00 03.018 0d036 0.74 zz4 Z25 82" 6,44 d.1e 4.00 A IZG6 1.00 AtAL iVo V05 024 8W 4 8:47 p.50 2.47 0.41 4 29 1.00 1.65 004 d08 7.24 /2W94:48 10 4AL¢AAJ 19.' 10 4t.717 tag 1J~tX 1 .74 440 -MDA 22.99 l.io i.p5 0Q24 &kW* hA 11 +/-154 10.49 1.00 -. 445 4.Z4 a&h'4 os1 4444 12 41.7t7 089 40'A 1i4.4 dao 4.65 1.2541 22.99 gz29 3a24 ShW 8:52 t3 4A 19.04 lb.49 1.00 ¢.t445 324 ak" g5d 14 154 p.89 145 .8 6.5 1 44 22nb 1.i0 0 ¢5 7j15 ' Ai 22.9 9 224 W8, 54 15 0.89 -Z 5 19.64 10.49 1.00 .fM5 224 sW&f4 8:5$ Z164 3.89 728 <4I 9Z99 1.o0 18 -573 327 0.565 3-24 8kW 4 8.5b 95 2194 3.89 *1AD 19.04 4MOA 2z99 1.00 4.01 0.555 -1.17 828094 8:58 1M A 9. 4 5.63 <MM 2299 1.00 0.555 1.24 8/2094 8.59 (A
UVAP Radiological Survey Form Location: CRWP#MP Suey Type: 1Sursurvev 2 oiageIof Cavalier Reactor I P - UVAP 0307 Characterization Surve Comments: Surveyed By: Date: instrument Serial f CaL Due Probe Area Serial I Cal. Due aEff. lp Elfl a Blg p Bkg I P_ heventilatn unitnoverheadourveyol BobLe 1tOZ Temnelec 64052 511503 rna nill nta nila na n/a rta ntv a ina n/ia
= I3obbyLe 11/06/02 l 2221 172035 W/03 4-s 124 tilhi9 4M103 itea 0222 'J. rnt vita a l, a te~wod By: D t:_ _ _ _ _ _ ___ _ _ _ _ _ _ _ _
F-rank Mye 1110 0- - -- _____4___=_._= __ = _= Key: Q Smear )e to x~o- Dired Frisk &=air senle B =beta dose rate in ad/hr *-X-X- Boundary SOP=tep Off Pad xly crinnact/12'dosa rale tl* General dose rW Static Counts Dlscription Gross CPM Smearst. UPM11OOcm r_ 2 GammaScan l_Alpha Beta Scan Gross CPM Counts per Minute No Unsh Shielded DPMI0ocm2 ltLe* . I _Net _
-No.l it
- I p We ci A I1 See Il _1 _
_rva_ ntaa 1004 l_3ri4 _22088___ 159 _ __gammaspe__rrt _nsuatoninsidelowercover _ 2 Attached l 2 ta na 2 365 334 1 152 Outsielwer cover 3 Repoli l nta 3 474 357 418 157 Vent grate 4 4 la I nla 4 404 323 290 150 Ventsonide 5 _ (_1_ nt lJ 5 551 349 722 156 Inside blower 6 6 la l na 6 529 356 618 157 Inside blower 1 7 ra na 7 394 381 46 13 Inside venl t nta ra i 8 442 363 282 159 Outside venl QCl Q e nta QC rnta rnta Wa rita QC I I1 - Al l i l l41-- l-5-l 5- + - II. I I L Ii L L I l III1I- I -I - IIII b I
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*r )' I I-G AM M A S P E C T R U M A N A L Y S I S ****k GOCS Report Generator ISOCSAN.TPL 2/26/96 ecort Generated On : 11/4/02 4:22:58 PM pectrum File Name : C:\PCNT2K\CAMFILES\marisoil\MRS00157.CNF ample Title : Mari. Soil ample Identification : Insulation ample Type : MRS
-esc. 1 : Cavalier ventilation insulation esc. 2 : esc. 3 : -esc. 4 : 'eak Locate Threshold 5.00 'eak Locate Range (in channels) 150 - 8192 leak Area Range (in channels) 150 - 8192 dentification Energy Tolerance 1.500 FWEM .ample Size : 1.000E+000 Ea 'ote: ,For Point Source, report UNIT = none. ,ample Taken On : 11/4/02 4:15:21 PM \cqulsltion Started : 11/4/02 4:15:21 PM ive Time 300.0 seconds ,eal Time 300.1 seconds Energy Calibration Used Done On : 10/16/02 Efficiency / Geometry ID : mari soil Efficiency Calibration Used Done On : 9/6/02
- .. -- I-no0v Ub ue +/-4:"Up rT~~~r~r r r -sri rizerr :b 11/4/2002 4:22:58 PM
,ak Locate Analysis Report
*A****A***********
L O C ATE R EP OR T ** t*** P E AK Detector Name: LABSOCS Sample
Title:
Mari. Soil Peak Locate Performed on: 11/4/2002 4:22:57 PM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Search Sensitivity: 5.00 Peak Centroid Centroid Energy Peak No. Channel Uncertainty (keV) Significance 308.65 0. 2387 77..19 6.83 1 5.24 2 966.23 0.2377 241.74 3 1179.20 0.1957 295.03 7 . 68 4 1405.65 0.1637 351:70 9.95 2434.01 0.1672 609.03 7.79 5
= Adjacent peak noted rrors quoted at 2.000 sigma 53/133
'TJ 'r. C- ; Q. _-0 -1 f
. . l.,, nyers 1I / /2002 4:22:58 PM
-ak Analysis Report A NA L YS IS
-. R E P O RT
-*+ P EA X Detector Name: LABSOCS Sample
Title:
Mari. Soil 4:22:57 PM Performed on: 11/4/2002 Peak Analysis From Channel: 150 PeaX~c Analysis 8192 Peak A Analysis To Channel: Area Continuum Peak Energy FWnM Net Peak Ne: Counts Peak ROI ROI (keV) (keV) Area Uncert. No. start end centroid 06E+001 33. 39 S. 44E+001 1 304- 313 308 . 65 77. 19 0. 90 9. 0.71
- 7. 29E+001 22.07 2.31E+001 966.23 241.74 1. 47E+001 2 960- 973 295.03 1.07 1. 49E+002 26.99 3 1171- 1187 1179.20 2. 63E4002 34.03 1.27E+001 1405. 65 351.70 1.05 7. 69E+000 4 1397- 1413 1.24 1.7 5E+002 27 . 68 2434 . 01 609.03 5 2424- 2443
. multiplet region I = First peak in 2 =- Other peak in <a multiplet region ' = Fitted singlet .rrors quoted at 2.000-sigma 541133
Nov06 E U2 12: 4U p Frank rtyers t0-a t1an.c't3. aa .r-U u
- nterference Corrected Activity Report 11/4/2002 4:22:58 PM t*11* *** * ***** * *** * ****** * **** *** * **** * *t***** ****** ** **** ***** * ** * **** * *
- N U C L I D E I D E N T I F I C A T IO N R E P O R T *****
Samples
Title:
Mari. Soil Nuclide Library Used: C:\GENIE2K\CAMFILES\uva.NLB
.................... ...IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (pci/Ea 1 Uncertainty BI-214 0.409 609.31* 46.30 3.71812E+003 7.20891E+002 768.36 5.04 1120.29 15.10 1764.49 15.80 PB-214 0.999 241.98* 7.49 5.01084E+003 1. 67708E+003 295.21* . 19.20 4.48079E+003 9. 71648E+002 351.92* 37.20 4. 62249E+003 7.85433E+002
* = Energy line found in the spectrum.
= Energy line not used for Weighted Mean Activity Energy Tolerance : 1.500 FWHM Nuclade confidence index threshold = 0.30 1 Errors quoted at 2.000 sigma I.
551133
Nov US UE 1 M: 4Up t-ranK nyers 'TO.T. CSVO. _g-p I U
; r nterference Corrected Activity Report 11/4/2002 4:22:58 PM
**tr~~~~~~~rt*****~~~
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++***S* * * ***,***** ****** *l*********** **S *~******** *****+***
Nuclide Wt mean Wt mean Nucl de Id Activity Activity Name Confidence (pCi/Ea ) Uncertainty BI-214 0.409 3.718116E+003 7 .208913E+002 PB-214 0. 999 4.618533E+003 5.739406E+002
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis G = nuclide contains energy lines not used in Weighted Mean Activity Errors cuoted at 2.000 sigma ** ******#+
U N I D E N T I F I E D P E A K S Peak Locate Performed on: 11/4/2002 4:22:57 PM Peak Locate From ChanneL: 150 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS No. tkeV) Counts per Second % Uncertainty 1 77.19 2.7411E-001 40.61 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma 56/133
*g) UVAP Radiological Survey Form Loca__on: IRWPWP - Survey 0 Survey Type: _____i ____7 Cavalier Reactor I .... 0206
__UVAP Characterization Comnients: Surveyed Ny, Date: In trument Serial # Cal. Due Probe Area Serial # Cal. Due n Etl. p Et, n Bkg. p Bkg nL Cavalier West Wall Cabinet Alice Thompson A- 08/29t02 Tefdeec 64052 5t15t03 nts nW nta l na nta nta nra nta nta j ova Bobby Leigh 08/28M02 2221 172051 48/03 43-68 Wte 11871t 4t3 n-Ia 215 rnt nta We inta na WrotW-sE=at S~sOuth, Revieed BtlDal: 1A2221 157031 410/03 44-10 1261 186955 4r20 n/a3 na nfit pie nifa file kgiBP. .i P Frari Myer s 03129/z7 Key:l Q =SmearxxoxtoxiowDlrectFrjsk - -air samplisbtidoert I ~dh -X-X- oundarv SOPSIC fPa f ofaV 'dserl e" oert Smears_ _ _ Gamma Scan I Alpha Beta Scan __ Static Counts Coordinates Gross CPM DPW'I00cm' -Gross CPM Conts pr Minute ____________ a 1 P g a Q M CP Uns5 Shielded Net 11L. NorthI East ElevaUon I See 1 9200-10700 2e7-337 1 309 302 26 149 45 05 1 2 Attached 2 9000-10800 2'9-320 I 432 260 635 139 5.5 05 275 3Report 3 12000-14500 284-368 2 295 313 -65 152 6.5 05 _ 1 4 4 8700-9600 . 2A9.324 4 234 254 -74 137 35 05 05 5 5 11800-13400 328-372 r 304 340 -133 159 725 05 05 6 6 8800-10100 _ 250-321 _ 244 287 .159 146 4 25 075 _ 05 771 9600-11200 2e1-314 7 260 258 7 138 1 5.5 0 75 1 0.5 ___________________ 7 a 10800-12300 25t -321 8 310 244 244 134 65 0 75 0.5 9 9 7900-8600 251.257 a 257 259 .7 135 4 05 025 o 2s 10 10 8800.10500 267-293 10 293 267 96 141 45 05 0 75 _ 11 II 7800-9500 289-253 11 253 269 .59 141 5 05 05 12 12 8100-9700 322-281 12 281 322 -151 154 55 05 025 13 13 8800-9700 299-308 13 308 299 33 149 6 25 0.5 0 25 14 14 11100-13700 299.300 14 300 299 4 149 7 05 0
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S_ Page I ol I Cavalier Reactor I UVAP-0208 Characterization Comments: Suryvd Br, Date: Instrument Serial Cal. Dui Probe Are, Serial Cal. Due a Elf. p Elf. A Bkg. PBkg AL pL Alice ThornO2so 09/0302 Terneec 64052 5/1103 nIva nVa na _ nt- nta Wel na nhna_ae
- BobbY Leig 29/02 _42221 172051 403 48 26 118718 4ip i 0215 nt8 unt n nt wM221 157031 4t3103 44-10 Vr 186956 4a302 Wsa nta nta nra nta nWa Reviewed Bv. Date:_ _ _
5 1rg1 M.LiCPM vran vers K 09/03t02
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- 4*44+4*44*4*4*4* * **4*4** ********************* **+*******4*4**4**4*4* ****
ISOCS Report Generator ISOCSAN.TPL 2/26/96 Report Generated On 11/25/02 8:55:40 AM Spectrum File Name C: \PCNT2K\CAMFILES\TUNASOIL\TCS0003 l.CNF Sample Title tuna can soil - Sample Identification UVA-CD-021 Sample Type tcs Desc. 1 : Drain swab "A" Desc. 2 : Desc. 3 : Desc. 4 : Peak Locate Threshold 5.00 Peak Locate Range (in channels) 150 - 8192 Peak Area Range (in channels) 150 - 8192 Identification Energy Tolerance 1.500 FWHM Sample Size : 1.140E+001 G Note: For Point Source, report UNIT - none. Sample Taken On : 11/21/02 10:15:33 AM Acquisition Started : 11/25/02 8:25:33 AM Live Time : 1800.0 seconds Real Time : 1800.3 seconds Energy Calibration Used Done On : 10/16/02 Efficiency / Geometry ID : tuna can Efficiency Calibration Used Done On : 10/16/02
Peak Locate Analysis Report 11/25/2002 8:55:40 AM 1ase - * *P
*** E A K L 0 *******
C A T E***** R****E P 0 **** R T*** Detector Name: LABSOCS Sample
Title:
- tuna can soil
, Peak Locate Performed on:
Peak 11/25/2002 8:55:39 AM Locate From Channel: 150 Peak Locate To Channel: Peak 8192 Search Sensitivity: 5.00 Peak .Centroid Centroid Energy Peak No. Channel Uncertainty (keV) Significance 1 5839.35 0.1655 1461.1B 6.05
-? Adjacent peak noted Errors quoted at 2.000 sigma
Peak Analysis Report 11/25/2002 8:55:40 AM -- ***** P E A K A N A L Y S I S R E P R T***** Detector Name: LABSOCS Sample
Title:
tuna can soil - Peak Analysis Performed on: 11/25/2002 8:55:39 AM
- 1. Peak Analysis From Channel: 150 Peak Analysis To Channel: 5192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuun No. start end centroid (keV) (keV) Area Uncert. Counts 1 5830- 5849 5839.35 1461.18 0.72 9.65E+001 20.44 4.55E+000 M - First peak in a multiplet region n - Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma 82/133
Interference Corrected Activity'Report 11/25/2002 8:55:40 AM
- N U C L I D E I D E N T I F I C A T I O N R E P O R T *****
Sample
Title:
tuna can soil Nuclide Library Used: C:\GENIE2K\CAMFILES\uva.NLB
.................... IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (M) (pCi/G Uncertainty K-40 0.997 1460.81* 10.67 1.54821E+002 3.86771E+001
* - Energy line found in the spectrum.
6 = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.500 FWHM Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma '
Interference Corrected Activity Report 11/25/2002 8:55:40 AM
- I N T E R F E R E N C E C O R R E C T E D R E P O R T *****
Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/G Uncertainty K-40 0.997 1.548211E+002 3.867711E+001
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
- U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 11/25/2002 8:55:39 AM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS No. (keV) Counts per Second % Uncertainty All peaks were identified.
*****GA M MA S PE CT R UM A NA L YSI S **
ISOCS Report Generator ISOCSAN.TPL 2/26/96 Report Generated On : 11/25/02 10:54:13 AM Spectrum File Name : C:\PCNT2K\CAMFILES\TUNASOIL\TCS00032.CNF Sample Title : tuna can soil Sample Identification : UVA-CD-022 Sample Type : tcs Desc. 1 : Drain swab "B" Desc. 2 : Desc. 3 : Desc. 4 : Peak Locate Threshold- 5.00 Peak Locate Range (in channels) 150 - 8192 Peak Area Range (in channels) 150 - 8192 Identification Energy Tolerance 1.500 FWHM Sample Size : 1.380E+001 G Note: For Point Source, report UNIT = none. Sample Taken On : 11/21/02 10:05:07 AM Acquisition Started : 11/25/02 10:24:07 AM Live Time : 1800.0 seconds Real Time : 1800.3 seconds Energy Calibration Used Done On : 10/16/02 Efficiency / Geometry ID : tuna can Efficiency Calibration Used Done On : 10/16/02
Peak Locate Analysis Report 1 11/25/2002 10:54:13 AM I
- T********************
***P E AK L OC A TE R E PO RT ****
- DetectorsName: LABSOCS Sample
Title:
tuna can soil Peak Locate Performed on: 11/25/2002 10:54:12 AM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Search Sensitivity: 5.00 Peak Centroid Centroid Energy Peak No. Channel Uncertainty (keV) Significance 1 5837.67 0.1642 1460.76 5.88 ? = Adjacent peak noted Errors quoted at 2.000 sigma
Peak Analysis Report A11/25/2002 10:54:14 AM
****P EA K A NA L YS IS R E P OR T
- s,*********************************************************************** **
Detector Name: LABSOCS Sample
Title:
tuna can soil Peak Analysis Performed on: 11/25/2002 10:54:12 AM Peak Analysis From Channel: 150 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 5828- 5849 5837.67 1460.76 1.70 1.25E+002 23.47 6.73E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 11/25/2002 10:54:14 AM S.****************************************************** F***
- N U C L I D E I D E N T I F I C A T IO N R E P O R T *****
- *************+*** ************************************** ***
- N U C L I D E I D E N T I F I C A T IO N R E P O R T *****
Sample
Title:
tuna can soil Nuclide Library Used: C:\GENIE2K\CAMFILES\uva.NLB
.................... ...IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/G Uncertainty K-4 0 1.000 1460.81* 10.67 1.66085E+002 3.B0595E+001
* = Energy line found in the spectrum.
Q = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.500 FWHM Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma-
Interference Corrected Activity Report 11/25/2002 10:54:14 AM
- INTERFERE'NCE CORRECTED REPORT *****
Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/G Uncertainty K-40 1.000 1.660846E+002 3.805949E+001
? = nuclide is part of an undetermined solution X= nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma .
******* U N I D E N T I F I E D P E A K S ******
Peak Locate Performed on: 11/25/2002 10:54:12 AM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS No. (keV) Counts per Second % Uncertainty All peaks were identified.
I*************** **************,***************************************** **
****G A M M A S P E C T R U M A N A 1 Y S I S * * **
ISOCS Report Generator ISOCSAN.TPL 2/26/96 Report Generated On 11/25/02 1:16:27 PM Spectrum File Name C:\PCNT2K\CAMFILES\TUNASOIL\TCS00035. CNF Sample Title tuna can soil Sample Identification UVA-CD-025 Sample Type tcs Desc. 1 Drain swab "C " Desc. 2 Desc. 3 Desc. 4 Peak Locate Threshold 5.00 Peak Locate Range (in channels).: 150 - 8192 Peak Area Range (in channels) 150 - 8192 Identification Energy Tolerance 1.500 FWHM Sample Size 9.300E+000 G Note: For Point Source, report UNIT = none. Sample T'aken On 11/21/02 1:30:20 PM Acquisition Started 11/25/02 12:46:20 PM Live Time 1800.0 seconds Real Time 1800.3 seconds Energy Calibration Used Done On : 10/16/02 Efficiency / Geometry ID : tuna can Efficiency Calibration Used Done On : 10/16/02
"eak Locate Analysis Report = I . 11/25/2002 1:16:27 PM :0.,- ^ P E A K L O CA TE R E PO R T Detector Name: LABSOCS Sample
Title:
tuna can soil Peak Locate Performed on: 11/25/2002 1:16 :26 PM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Search Sensitivity: 5.00 Peak Centroid Centroid Energy Peak No. Channel Uncertainty (key) Significance
} 5839.57 0.1649 1461.24 5.86
? = Adjacent peak noted Errors quoted at 2.000 sigma
Peak Analysis Report 11/25/2002 1:16:27 PM P E A K A N A L Y S I S R E P O R T Detector Name: LABSOCS Sample
Title:
tuna can soil Peak Analysis Performed on: 11/25/2002 1:16:26 PM Peak Analysis From Channel: 150 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 5826- 5848 5839.57 1461.24 0.89 1.12E+002 21.67 2.70E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma nfl,.'
Interference Corrected Activity Report 11/25/2002 1:16:27 PM ,, N U C L I D E I D E N T I F I C A T I0 N R E P O RT Sample
Title:
tuna can soil Nuclide ILibrary Used: C:\GENIE2K\CAMFILES\uva.NLB
. .. .. .. .. .. .. .. .. .. . l+/-uzN'XIlCZ vU"LIuz Nuclide Id Energy Yield Activity Activity t Name Confidence (keV) (%) (pCi/G Uncertainty K-40 0.996 1460.81* 10.67 2.20957E+002 5.16990E+001
* - Energy line found in the spectrum.
@ = Energy line not used for. Weighted Mean Activity Energy Tolerance : 1.500 FWHM Nuclide confidence index threshold - 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 11/25/2002 1:16:27 PM ,xraye,
- I N TE RFE RE NC E C OR RE C TED R EP O RT ***
Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/G ) Uncertainty K-40 0.996 2.209567E+002 5.169895E+001
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
- U N I D E N T I F I E D P E A K S
- Peak Locate Performed on: 11/25/2002 1:16:26 PM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS No. (keV) Counts per Second % Uncertainty All peaks were identified.
***t* +******* ******
G A M M A S P E CT R U M A N A L Y S I S
*** *** ********* *****F** ********** ******** *** ******S* ***** *l**
ISOCS Report Generator ISOCSAN.TPL 2/26/96 Report Generated On : 11/25/02 11:27:12 AM Spectrum File Name : C:\PCNT2K\CAMFILES\TUNASOIL\TCS00033.CNF Sample Title : tuna can soil Sample Identification : UVA-CD-023 Sample Type : tcs Desc. 1 : Drain swab ",Z Desc. 2 : Desc. 3 : Desc. 4 : Peak Locate Thteshold 5.00 Peak Locate Range (in channels} 150 - 8192 Peak Area Range (in channels) 150 - 8192 Identification Energy Tolerance 1.500 FWHM Sample Size : 1.370E+001 G Note: For Point Source, report UNIT = none. Sample Taken On : 11/21/02 1:20:06 PM Acquisition Started : 11/25/02 10:57:06 AM Live Time : 1800.0 seconds Real Time : 1800.4 seconds Energy Calibration Used Done On : 10/16/02 Efficiency / Geometry ID : tuna can Efficiency Calibration Used Done On : 10/16/02
Peak Loc'ate Analysis Report 11/25/2002 11:27:12 AM Pac; P E A K L O C A T E R E PO R T Detector' Name: LABSOCS Sample
Title:
tuna can soil
- Peak Locate Performed on: 11/25/2002 11:27:11 AN Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Search Sensitivity: 5.00 Peak Centroid Centroid Energy Peak No. Channel Uncertainty (keV) Significance 1 5838.80 0.1654 1461.05 6.21
? Adjacent peak noted Errors quoted at 2.000 sigma
- 1 11/25/2002 11:27:12 AM Peak Analysis Report - ***P E A K A N A L Y S I S R E P 0 R T***
- V**********************************************************
Detector-Name: LABSOCS Sample
Title:
tuna can soil Peak Analysis Performed on: 11/25/2002 11:27:11 AM Peak Analysis From Channel: 150 Peak Analysis To Channel: 8192 Peak Energy FWHM Net Peak Net Area Continuum Peak ROI ROI Uncert. Counts No. start end centroid (keV) (keV) Area 1461.05 0.69 8.90E+001 19.78 5.03E+000 1 5829- 5847 5838.80 M = First peak in a multiplet region m -Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity' Report 11/25/2002 11:27:12 AM P cC I
- N U C L I DE I D E N T I F I C A T IO N R E PO R T *****
Sample
Title:
tuna can soil Nuclide Library.Used: C:\GENIE2K\CAMFILES\uva.NLB
.................... ... IDENTIFIED NUCLIDES .;
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (M) (pCi/G Uncertainty K-40 0.999 1460.81* 10.67 1.18846E+002 3.07312E+001
* = Energy line found in the spectrum.
@= Energy line not used for Weighted Mean Activity Energy Tolerance : 1.500 FWHM Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 11/25/2002 11:27:12 AM __,
- I N T E R F E R E N C E C O R R E C T E D R E PO R T *****
- ~************************ *******,********************* ************* **
Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/G Uncertainty K-40 0.999 1.188456E+002 3.073119E+001
? = nuclide is part of an undetermined solution X - nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma U N I D E N T I F I E D P E A K S Peak Locate Performed on: 11/25/2002 11:27:11 AM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS No. (keV) Counts per Second % Uncertainty All peaks were identified.
G A M M A S P E C T R U M A N A L Y S I S ISOCS Report Generator [SOCSAN.TPL 2/26/96 Report Generated On 11/25/02 12:00:04 PM Spectrum File Name C: \PCNT2K\CAMFILES\TUNASOIL\TCS00034. CNF Sample TitIe tuna can soil Sample Identification UVA-CD-024 Sample Type tcs Desc. 1 : Drain swab " E n Desc. 2 : Desc. 3 : Desc. 4 : Peak Locate Threshold 5.00 Peak Locate Range (in channels) 150 - 8192 Peak Area Range.(in channels) 150 - 8192 Identification Energy Tolerance 1.500 FWHM Sample Size : 1.680E+001 G Note: For Point Source, report UNIT = none. Sample Taken On : 11/21/02 1:20:58 AM Acquisition Started : 11/25/02 11:29:58 AM Live Time
- 1800.0 seconds Real Time : 1800.3 seconds Energy Calibration Used Done On : 10/16/02 Efficiency / Geometry ID : tuna can Efficiency Calibration Used Done On : 10/16/02
Peak Locate Analysis Report I 11/25/2002 12:00:04 PM
***** PE AK L OC A TE R EP OR T***
Detector Name: LABSOCS Sample TItle: tuna can soil Peak Locate Performed on: 11/25/2002 12:00:03 PM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Search Sensitivity: 5.00 Peak Centroid Centroid Energy Peak No. Channel Uncertainty (keV) Significance 1 5839.83 0.1679 1461.30 5.36 ?.= Adjacent peak noted Errors quoted at 2.000 sigma
. a a ;ege 3 Peatk Analysis Report 11/25/2002 12:00:04 PNM
*********************************AA*****
- ****P EA K**** A NA LY S IS R EP OR T t*
-.*** ** **** *** s,** ****
Detector Name: LABSOCS Sample
Title:
tuna can soil 12:00:03 PM Peak Analysis Performed on: 11/25/2002 150 Peak Analysis From Channel: Peak Analysis To Channel: 8192 Peak Energy FWHM Net Peak Net Area Continuum Peak ROI ROI Uncert. Counts No. start end centroid (keV) (keV) Area 1461.30 2.35 l.llE+002 21.38 1.58E+000 1 5829- 5850 5839.83 M - First peak in a multiplet region m = Other peak in a multiplet region F - Fitted singlet Errors quoted at 2.000 sigma ingii"S
J Report 11/25/2002 12:00:04 PM r:-,. Interference Corrected Activity R E P O R T ***
*** N U C L I D E I D E N T I F I C A T I O N Sample
Title:
tuna can soil Nuclide Library Used: C:\GENIE2K\CAMFILES\uva.NLB
. IDENTIFIED NUCLIDES Yield Activity Activity Nuclide Id Energy Uncertainty (keV) (%) (pCi/G Name Confidence 1460.81* 10.67 1.21369E4+002 2.82865E+001 K-40 0.995
* - Energy line found in the spectrum. Mean Activity
@ = Energy line not used for Weighted Energy Tolerance : 1.500 FWHM index threshold - 0.30 Nuclide confidence Errors quoted at 2.000 sigma
Interference Corrected Activity Report 11j25/2002 12:00:04 PM Page .^
- I N T E R F E R E N C E C O R R E C T E D R E P O R T **+**
Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/G ) Uncertainty K-40 0.995 1.213687E+002 2.828651E+001
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
,****** U N I D E N T I F I E D P E AKS **********
Peak Locate Performed on: 11/25/2002 12:00:03 PM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Energy Peak-Size in Peak CPS No. (keV) Counts per Second % Uncertainty All peaks were identified.
A****A***************************A***************************************
**** G A MM A S PE C TR UM A NA L Y SI S
- ISOCS Report Generator ISOCSAN.TPL 2/26/96 Report Generated On : 11/25/02 1:48:18 PM Spectrum File Name : C: \PCNT2K\CAMFILES\TUNASOIL\TCS00036. CNF Sample Title : tuna can soil Sample Identification : UVA-CD-026 Sample Type : tcs Desc. 1 : Drain swab " F "
Desc. 2 : Desc. 3 Desc. 4 Peak Locate Threshold 5.00 Peak Locate Range (in channels) 150 - 8192 Peak Area Range (in channels) 150 - 8192 Identification Energy Tolerance 1.500 FWHM Sample Size : 1.280E+001 G Note: For Point Source, report UNIT = none. Sample Taken On : 11/21/02 1:30:12 PM Acquisition Started : 11/25/02 1:18:12 PM Live Time : 1800.0 seconds Real Time : 1800.3 seconds Energy Calibration Used Done On : 10/16/02 Efficiency / Geometry ID : tuna can Efficiency Calibration Used Done On : 10/16/02
Peak Locate Analysis Report 11/25/2002 1:48:19 PM P E A K L O C A T E R E P O R T
*********************************~*****************************************
Detector Name: LABSOCS Sample
Title:
tuna can soil Peak Locate Performed on: 11/25/2002 1:48:17 PM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Search Sensitivity: 5.00 Peak Centroid Centroid Energy Peak No. Channel Uncertainty (keV) Significance 1 5839.37 0.1659 1461.19 5.89 . ? = Adjacent peak noted Errors quoted at 2.000 sigma
ieak Analysis Report 11/25/2002 1:48:19 PM
. i a R E P 0 R T P E A K A N A L Y S I S **** ** ***
******** ** ** *** *****t****
- Detector Namfe: LABSOCS Sample
Title:
tuna can soil Peak Analysis Performed on: 11/25/2002 1:48:18 PM Peak Analysis From Channel: 150 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 5829- 5849 5839.37 1461.19 1.60 1.04E+002 21.40 5.62E+000 M - First peak in a multiplet region m - Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 11/25/2002 1:48:19 PM Pa.o & - I ***** N U C L I D E I D E N T I F I C A T IO N R E PO R T ***** Sample T5 tle: tuna can soii Nuclide Library Used: C:\GENIE2K\CAMFILES\uva.NLB
....... .......... IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (P) (pCi/G Uncertainty K-40 0.997 1460.81* 10.67 1.49220E+002 3.64090E+001
* - Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity
- Energy Tolerance : 1.500 FWHM Nuclide confidence index threshold - 0.30 Errors quoted at 2.000 sigma 108/133
Interference Corrected Activity Report 11/25/2002 1:48:19 PM
- I N TE RF ER E NCE CO RR EC T ED R EP O RT ***
Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/G Uncertainty K-40 0.997 1.492203E+002 3.640902E+001
? = nuclide is part of an undetermined solution X -=nuclide rejected by the interference analysis
@ - nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
- UN I D E N T I F I E D P E A K S Peak Locate Performed on: 11/25/2002 1:4B:17 PM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS No. (keV) Counts per Second % Uncertainty All peaks were identified.
G A MM A S P EC T I U M A N A L Y S I S
. ISOCS Report Generator ISOCSAN.TPL 2/26/96 I Report Generated On : 11/25/02 2:54:31 PM Spectrum',File Name : C:\PCNT2K\CAMFILES\TUNASOIL\TCS00037.CNF Sample Title : tuna can soil Sample Identification : UVA-CD-027 Sample: Type : tcs Desc. 1 : Drain swab "G if Desc. 2 :
Deso. 3 : Desc. 4 :
- -: Peak Locate Threshold 5.00
*Peak Locate Range (in channels) : 150 - 8192 Peak Area Range (in channels) 150 - 8192 ! Identification Energy Tolerance : 1.500 FWHM Sample Size 5.800E+000 G Note: For Point Source, report UNIT - none.
Sample Taken On : 11/21/02 1:45:23 PM Acquisition Started : 11/25/02 2:24:23 PM Live Time : 1800.0 seconds Real Time :1800.3 seconds Energy Calibration Used Done On : 10/16/02 Efficiency / Geometry ID : tuna can Efficiency Calibration Used Done On : 10/16/02
bae 2 i 11/25/2002 2:54:31 PM Report Peak Locate Analysis R E p o T 2 42
*PE A K L C A TE 1 LABSOCS Detector Nam :
Sample
Title:
tuna can soil I1/25/2002 2:54:29 PM
..Peak Locate Performed on: 50 1.
Peak Locate From Channel: 83 92 Peak Locate To Channel: 5 .00 Peak Search Sensitivity: Energy Peak Centroid Centroid (keV) Significance Peak Uncertainty No. Channel 1461.35 5.24 5840.01 o.1731 1
?= Adjacent peak noted sigma Errors quoted at 2.000
- 11/25/2002 2:54:31 PM Peak Analysis Report A N A L Y S I S R E P O R P E A K Detector Name: LABSOCS Sample Ti~tle: tuna can soil Peak Analysis Performed on: 11/25/2002 2:54:29 PM 150 Peak Analysis From Channel: 8192 Peak Analysis To Channel:
FWXM Net Peak Net Area Continuum Peak Energy Counts Peak ROI ROI (keV) Area Uncert. No. start end centroid (keV) 1.40 9.39E+001 20.71 7;OBE+000 1 5828- 5850 5840.01 1461.35 regi6n m = First peak in a multiplet region m Other peak in a multiplet F = Fitted singlet
-Errors quoted at 2.000 sigma
Interference Corrected Activit'y Report 11/25/2002 2:54:31 PM
- **t***********************************************
N U C L I D E I D E N T I F I C A T IO N R E P O RT Sample
Title:
tuna can soil Nuclide Library Used: C:\GENIE2K\CAMFILES\uva.NLB
.................... ... IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/G ) Uncertainty K-40 0.994 1460.61* 10.67 2.96332E+002 7.62136E+001
* - Energy line found in the spectrum.
= Energy line not used for Weighted Mean Activity Energy Tolerance : 1.500 FWHM Nuclide confidence index threshold = 0.30 Errors quloted at 2.000 sigma
11/25/2002 2:54:31 PM Interference Corrected Activity Report C O R R E C T E D R E P O R T *****
- I N T E R F E R E N C E
- F** *********************************************************
- I N T E R F E R E N C E
Nuclide Wt mean Wt mean Id Activity Activity Nuclide Uncertainty Name Confidence (pCi/G 0.994 2.963321E+002 7.621358E+001 K-40 solution
? = nuclide is part of an undetermined analysis X = nuclide rejected by the interference energy lines not used in Weighted Mean Activity t - nuclide contains Errors quoted at 2.000 sigma
*** *** U N I D E N TI F IE D P E AK S **********
Peak Locate Performed on: 11/25/2002 2:54:29 PM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Energy Peak Size in Peak CPS Peak % Uncertainty No. (keV) Counts per Second All peaks were identified.
****AA***************A***********************I****************************
*****G A MMA S PE C TR UM A NA-L YS I S *
***********S****************** ********** *
- k****~******.****e**************
ISOCS Report Generator ISOCSAN.TPL 2/26/96 Report Generated On : 11/25/02 4:09:38 PM Spectrum File Name : C:\PCNT2K\CAMFILES\TUNASOIL\TCS00038.CNF Sample Title : tuna can soil Sample Identification : UVA-CD-028 Sample Type : tcs Desc. 1 : Drain swab "H" Desc. 2 : Desc. 3 : Desc. 4 : Peak Locate Threshold 5.00 Peak Locate Range (in channels) 150 - 8192 Peak Area Range (in channels) 150 - 8192 Identification Energy Tolerance 1.500 FWHM Sample Size : 1.340E+001 G Note: For Point Sourcet report UNIT = none. Sample Taken On : 11/21/02 1:45:31 PM Acquisition Started : 11/25/02 3:39:31 PM Live Time : 1800.0 seconds Real Time : 1800.4 seconds Energy Calibration Used Done On : 10/16/02 Efficiency / Geometry ID : tuna can Efficiency Calibration Used Done On : 10/16/02
Peak Locate Analysis Report
. I__ I ; zI/2002 4:09:38 PM? *ar.
P E A K L O C A T E R EPORT Detector Name: LABSOCS Sample
Title:
tuna can soil Peak Locate Performed on: 11/25/2002
-t Peak Locate From Channel: 4:09:37 PM Peak Locate To Channel: 150 Peak Search Sensitivity: 8192 5.00 Peak Centroid Centroid No. Channel Energy Peak Uncertainty (keV) Significance 1 5838.25 0.1706 1460.91 5.01
? = Adjacent peak noted Errors quoted at 2.000 sigma f I I i II II i I I I
!I I
I I II II I I II I i I I I --
11/25/2002 4:09:38 PM Paae 3 Peak Analysis Report P E A K A N A L Y S I S R E P O R T **** i
*S****************l~F************************
Detector-Name: LABSOCS Sample
Title:
tuna can soil Peak Analysis Performed on: 11/25/2002 4:09:37 PM Peak Analysis From Channel: 150 Peak Analysis To Channel: 8192 Peak Energy FWHM Net Peak Net Area Continuum Peak ROI ROI centroid (keV) (keV) Area Uncert. Counts No. start end 1 5828- 5851 5838.25 1460.91 1.54 1.02E+002 20.92 3.69E+ODO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Report 11/25/2002 4:09:39 PM Interference Corrected Activity R E P O R T ** N U C L I D E I D E N T I F I C A T I O N4 -- ~****NUCLIDEIDENT Sample
Title:
tuna can soil Nuclide Library Used: C:\GENIE2K\CAMFILES\uva.N$B
. cti.it .
IDENTIFIED NUCLIDES Yield Activity Activity Nuclide Id Energy Uncertainty Confidence (keV) l%) (pCi/G Name 10.67 1.39698E+002 3.40083E+001 K-40 1.000 1460.81*
- Energy line found in the spectrum. Mean ActivitY
@ 5 Energy line not used for Weighted Energy Tolerance : 1.500 FWHM index threshold - 0.30 Nuclide confidence Errors quoted at 2.000 sigma
Interference Corrected Activity Report 11/25f2002 4:09:39 PM
- I N T E R F E R E N C E C O R R E C T E D R E P O R T *****
- *******************************i***********************t********
- I N T E R F E R E N C E C O R R E C T E D R E P O R T *****
Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/G Uncertainty K-40 1.000 1.396978E+002 3.400834E+001
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma U N I D E N T I F I E D P E A K S Peak Locate Performed on: 11/25/2002 4:09:37 PM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS No. (keV) Counts per Second % Uncertainty All peaks were identified.
G A M M A S P E C T R U M A N A L Y S I S
- *********** *+**************,****************************~*********
ISOCS Report Generator ISOCSAN.TPL 2/26/96 Report Generated On : 11/25/02 4:43:12 PM 39
- C:\PCNT2K\CAMFILES\TUNASOIL\TCS000 .CNF Spectrum File Name Sample Title : tuna can soil Sample Identification : UVA-CD-029 Sample Type : tcs Desc. 1 : Drain swab " I Desc. 2 :
Desc. 3 : Desc. 4 : Peak Locate Threshold 5.00 Peak Locate Range (in channels) 150 - 8192 Peak Area Range (in channels) 150 - 8192 Identification Energy Tolerance 1.500 FWHM Sample Size : 1.230E+001 G Note: For Point Source, report UNIT = none. Sample Taken On : 11/21/02 1:45:06 PM Acquisition Started : 11/25/02 4:13:06 PM Live Time : 1800.0 seconds Real Time : 1800.3 seconds Energy Calibration Used Done On : 10/16/02 Efficiency / Geometry ID
- tuna can Efficiency Calibration Used Done On : 10/16/02
1 11/25/2002 4:43:12 PM raac Peak Locate Analysis Report . No peak locate results available for reporting purposes No peak analysis results available for reporting purposes
Interference Corrected Activity Report 11/25/2002 4:43:12 PM 3
- N U C L I D E I D E N T I F I C A T IO N R E P O RT Sample
Title:
tuna can soil Nuclide Library Used: C:\GENIE2K\CAMFILES\uva.NLB
.................... IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/G ) Uncertainty
- Energy line found in the spectrum.
= Energy line not used for Weighted Mean Activity Energy Tolerance : 1.500 FWHM Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
11/25/2002 4:43:12 PM -ze Interference Corrected Activity Report
- Yr************** ***********************************
- I NT ER F ERE NC E CO RR EC T ED R EP O RT ***
Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/G Uncertainty
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis e = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma No peak search results available for nuclide analysis.
S P E C T R U M A NA L Y S I S **** G A MMA
*******t*** ** ******* ***** ******** **,k*
ISOCS Report Generator :SOCSAN.TPL 2/26/96 Report Generated On 11/25/02 5:23:45 PM Spectrum File,, Name C: \PCNT2K\CAMFILES\TUNASOIL\TCSODD40. CNF Sample Title tuna can soil Sample Identification UVA-CD-030 Sample Type tcs Desc. 1 : Drain swab " J Desc. 2 : m Desc. 3 : - Desc. 4 : Peak Locate Threshold 5.00 Peak Locate Range (in channels) 150 - 8192 Peak Area Range (in channels) 150 - 8192 Identification Energy Tolerance 1.500 FWHM Sample Size : 1.400E+001 G Note: For Point Source, report UNIT - none. Sample Taken On : 11/21/02 11:30:39 AM Acquisition Started : 11/25/02 4:53:39 PM Live Time : 1800.0 seconds Real Time : 1800.3 seconds Energy Calibration Used Done On : 10/16/02 Efficiency / Geometry ID : tuna can Efficiency Calibration Used Done On : 10/16/02 124/133
Peak Locate Analysis Report 11/25/2002 5:23:45 PM P E A K L O C A T E R E PO R T Detecto; Name: LABSOCS Sample
Title:
tuna can soil Peak Locate Performed on: 11/25/2002 5:23:44 PM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Search Sensitivity: 5.00 Peak Centroid Centroid Energy Peak No. Channel Uncertainty (keV) Significance 1 5839.38 0.1679 1461.19 5.88 ?= Adjacent peak noted Errors quoted at 2.000 sigma
Peak Analysis Report e 11/25/2002 5:23:45 PM
***** PE AK A A L YS IS R EP OR T***
Detector Name: LABSOCS Sample,
Title:
tuna can soil Peak Analysis Performed on: 11/25/2002 5:23:44 PM Peak Analysis From Channel: 150 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 5831- 5849 5839.38 1461.19 1.27 l.OE+002 21.90 6-.66E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
11/25/2002 5:23:45 PM ',.,- Interference Corrected Activity Report
- N U C L I D E I D E N T I F ICA T I ON R E P 0 R T Sample title: tuna can soil Nuclide Library Used: C:\GENIE2K\CAMFILES\uva.NLB
. ........ .... ;IDENTIFIED NUCLIDES Id Energy Yield Activity Activity Nuclide Name Confidence (keV) (%) (pCi/G ) Uncertainty K-40 0.997 1460.81* 10.67 1.41614E+002 3.42013E+001
* = Energy line found in the spectrum.
e Energy line not used for Weighted Mean Activity Energy Tolerance . 1.500 FWHM Nuclide confidence index threshold = 0.30 Errors quoted at .2.000 sigma I
Interference Corrected Activity Report 11/25/2002 5:23:45 PM
- I N T E R F E R E N C E C OR R E C T E D R E PO R T *****
Nuclide Wt mean Wt mean Nuclide Id Activity Activity Nam& Confidence (pCi/G Uncertainty K-40 0.997 1.416137E+002 3.420127E+001
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S
- Peak Locate Performed on: 11/25/2002 5:23:44 PM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS No. (keV) Counts per Second % Uncertainty All peaks were identified.
******+******** * **k ********************}****************t**+***************
GA MM A S P E'C T R U M A N A L Y S I S *
- ISOCS Report Generator [SOCSAN.TPL 2/26/96 Report Generated On 11/25/02 5:55:57 PM Spectrum File Name C: \PCNT2K\CAMFILES\TUNASOIL\TCS00041. CNF Sample Title tuna cam soil Sample Identification UVA-CD-031 Sample Type tcs Desc. 1 : Drain swab " K Desc. 2 :
Desc. 3 : Desc. 4 :
- Peak Locate Threshold 5.00 Peak Locate Range (in channels) 150 - 8192 Peak Area Range (in channels) 150 - 8192 Identification Energy Tolerance 1.500 FWHM Sample Size : 1.350E+001 G Note: For Point Source, report UNIT = none.
Sample Taken On : 11/21/02 1:55:50 PM Acquisition Started : 11/25/02 5:25:50 PM Live Time : 1800.0 seconds Real Time : 1800.3 seconds Energy Calibration Used Done On : 10/16/02 Efficiency / Geometry ID : tuna can Efficiency Calibration Used Done On : 10/16/02
Peak Locate Analysis Report , 11/25/2002 5:55:57 PM P E A K L O C A T E R E P O R T ***
*************f******************************************
Detector Name: LABSOCS Sample title: tuna can soil Peak Locate Performed on: 11/25/2002 5:55:56 PM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Search Sensitivity: 5.00 Peak Centroid Centroid Energy Peak No. Channel Uncertainty (key) Significance 1 5838.56 0.17.01 1460.98 5.45 ? Adjacent peak noted Errors quoted at 2.000 sigma
Peak Analysis Report 11/25/2002 5:55:57 PM A K A N A L Y S I S P E*************************************jr**************** R E P O R T *** Detector Name: LABSOCS Sample
Title:
tuna can soil PM Peak Analysis Performed on: 11/25/2002 5:55:56 Peak Analysis From Channel: 150 Peak Analysis To Channel: 8192 Peak Energy FWHM Net Peak Net Area Continuum Peak ROI ROI Counts centroid {keV) (keV) Area Uncert. No. start end 5838.56 1460.98 1.12 1.16E+002 21.92 2.46E+O00 1 5828- 5850 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 11/25/2002 5:55:57 PM
- N U C L I D E I D E N T I F I C A T IO N R E P O R T *****
Sample title: tuna can soil Nuclide Library Used: C:\GENIE2K\CAMFILES\uva.NLB
.................... IDENTIFIED .. NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/G Uncertainty K-40 0.999 1460.81* 10.67 1.56613E+002 3.62025E+001
* - Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.500 FWHM Nuclide confidence index threshold'= 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 11/25/2002 5:55:57 PM 7
- I N T E R FE R E N C E C O R R E C T E D R E PO R T *****
Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/G Uncertainty K-40 0.999 1.566134E+002 3.620255E+001
? - nuclide is part of an undetermined solution X - nuclide rejected by the interference analysis
@ - nuclide contains energy lines not used in.Weighted Mean Activity Errors quoted at 2.000 sigma
* ********* U N I D E N T I FI E D P E A K S Peak Locate Performed on: 11/25/2002 5:55:56 PM Peak Locate From Channel: 150 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS No. (keV) Counts per Second % Uncertainty All peaks were identified.}}