ML052140104
| ML052140104 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 07/31/2005 |
| From: | GPU Nuclear Corp |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML052140104 (86) | |
Text
Final Status Survey Report For Saxton Nuclear Experimental Corporation Containment Vessel Yard Excavation - Soil and Structural Remnants Prepared by GPU Nuclear, Inc.
July 2005
Table of Contents Section No. Page Executive Summary .................................................. 2
1.0 Purpose and Scope
.................................................. 3 2.0 Survey Unit Layout (diagram) ................................................. 4 3.0 Operating History .................................................. 7 3.1 Plant Operation ........ 7......................
3.2 Remediation Status .................................................. 8 4.0 Site Release Criteria ................................................. 10 5.0 Survey Designs/DQO Process ............................................ 11 6.0 Final Status Survey Results .............................................. 11 6.1 Northwest Sector ................................................. 11 6.2 South Sector of CV (including CV External Shell) ..................... ............. 16 6.3 Northeast Sector of CV (including CV Concrete Cap) ............... ............. 21 6.4 Southwest Sector of CV ................................................. 26 6.5 Backfill Materials ........................ ; 29 7.0 Data Assessment ....................... 31 8.0 Final Survey Conclusions ....................... 37 9.0 References ........................ 38 10.0 Appendices ........................ 38 I
Executive Summary This report presents the results and conclusions of the Final Status Survey (FSS) conducted by GPU Nuclear, Inc. on the SNEC Facility Containment Vessel Concrete Cap and surrounding open land areas, below-grade concrete structural remnants, and backfill materials. FSS was started in May 2004 and completed in November 2004.
This FSS Report provides the summary of survey/sampling results taken from the areas/structures covered under this report.
This FSS was performed in accordance with the SNEC License Termination Plan (LTP).
The listed areas were divided into 10 survey units. 8 Class 1, 1 Class 2, and 1 Class 3 area. Survey data was collected from each survey unit in accordance with the collection requirements specified in the LTP.
The following types of measurements were performed:
- 1. Sodium Iodide scan measurements were performed on 10 survey units.
- 2. GFPC static measurements were performed at 114 locations.
- 3. Soil samples were obtained in 315 locations as specified by the survey designs. In addition, 14 samples were obtained in response to activity identified during scanning that exceeded assigned action level.
Results of the above measurements were less than the applicable DCGLs for each of the respective survey units. The collected FSS data demonstrate that each survey unit meets the radiological criteria for unrestricted use specified in 10 CFR 20.1402 (Reference 9.1). Based on these results, GPU Nuclear, Inc. concludes that all areas surveyed meet the NRC requirements for release to unrestricted use.
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1.0 Purpose and Scope
This report presents the results and conclusions of the final status surveys performed on the following areas:
- Northwest Sector of CV Yard - Survey Units OL1-2 and MA8-1
- South Sector of CV Yard (including CV external shell) - Survey Units OL1-3, MA8-2, CV4-2, and CV5-1
- Northeast Sector of CV Yard (including CV concrete cap) - Survey Units OL1-4 and MA8-3
- Southwest Sector of CV Yard - Survey Units OL1-5 and MA8-4
- Backfill Soils These surveys provide the information required by 10 CFR 50.82(a)(1 1) (Reference 9.2) and SNEC's License Termination Plan (LTP) (Reference 9.3) to demonstrate that these areas meet the radiological criteria for unrestricted use specified in 10 CFR 20.1402 (Reference 9.1).
The survey units listed and reported herein cover the below grade soils surrounding the CV Shell (down to approximately 794' Elevation and the external CV shell surface down to 800' Elev. and structural concrete remnants from the CV Steam Tunnel, Ventilation Pads, and the North Support Wall of the Control and Auxiliary Building. The Containment Vessel was removed at an approximate elevation of 804' Elev. External surfaces of the CV Shell below this elevation and not covered under survey units CV4-2 and CV5-1 were surveyed previously and the results were reported in the 'FSS Report of the CV Interior Above 774' Elev. And Exterior" report (Reference 9.4). The interior surface of the CV Shell below 774' Elevation was performed and reported in the 'FSS Report of the CV Interior, 774' El. & Below (Reference 9.5).
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2.0 Survey Unit Description/Lavout (diagram)
This report covers ten survey units. The following section provides a description of the physical composition, surface area, and classification of each survey unit:
OL -2: covers approximately 309 m2 of open land area (soil) from 803' El. to 811' El.
This unit is bounded on the northeastern side by a line drawn between a monitoring well to the CV Shell and on the western side by the southern edge of an old concrete transformer support structure (Misc. Concrete A). This survey unit is a Class I area.
MA8-1: covers approximately 48 m2 of concrete surface composed of two below-grade concrete structural remnants (Misc. Concrete A and B) and one excess concrete surface (spoils). These three concrete components are within the boundaries of OL1-2.
This survey unit is a Class 1 area.
OL1--3: covers approximately 395 m2 of both open land area (soil, rock) and concrete block in the vicinity. This unit is bounded on the eastern side by CV anchor bolthole #40 and on the southwest side by CV anchor bolthole #5. This survey unit is a Class 1 area.
MA8-2: covers approximately 13 m2 of exposed solid concrete structures such as old foundation remnants and pillars of the Control and Auxiliary Building, the Decommissioning Support Facility and CV Pipe Tunnel. These components lie to the south of OL1-3. This survey unit is a Class I area.
CV4-2: covers approximately 7.4 m2 of steel (external surface of the CV Vessel) from 804' El. to 802.5' El. on the south side of the CV extending approximately 77 feet. This survey unit is a Class 1 area.
CV5-1: covers approximately 16.2 m2 of steel (external surface of the CV Vessel) from 802.5' El. To 800' El. on the south side of the CV extending approximately 77 feet. This survey unit is a Class 2 area.
OLI-4: covers approximately 441 m2 of open land area (soil) from 804' El. To 811' El.
This unit is bounded on the eastern side by the remaining CV yard area at grade level and on the southern edge by a wing wall extension from the CV support structure. The line drawn from same well to the CV Shell that bounds OL1-2 bounds this unit on the western side. This survey unit is a Class 1 area.
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MAB-3: covers approximately 182 m2Of surface (CV concrete cap). The unit lies within the circumference of the CV Vessel. This survey unit is a Class 3 area.
OL1-5: covers approximately 66 m2 of open land area (soil) from 803' El to 811 ' El. This unit is bounded by the eastern end of the CV Steam/Pipe Tunnel and, in general, is located in the southwest sector of the CV Yard. This survey unit is a Class I area.
MA8-4: covers approximately 7.8 m2 of concrete surfaces. This unit covers the miscellaneous below-grade concrete structures in the vicinity of OL1-5. This survey unit is a Class 1 area.
These survey units are depicted on the following diagram:
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CV YARD - STRUCTURAL REMNANTS Well N
OL14 OL1-2
.. A..,
CV OUTLINE MA8-3 GRAPHIC SCALE (IN FEET) 25 III I. ¢4 CV4-2
\.. IS CV5-1 MA8-2 (Approximate Survey Unit Boundaries) 6
3.0 Operating History 3.1 Plant Operation The Saxton Nuclear Experimental Corporation (SNEC) facility included a pressurized water reactor (PWR), which was licensed to operate at 23.5 megawatts thermal (23.5 MWTh). The reactor, containment vessel and support buildings have all been removed.
The facility is owned by the Saxton Nuclear Experimental Corporation and is licensed by GPU Nuclear, Inc. The SNEC facility is maintained under a Title 10 Part 50 license and associated Technical Specifications. In 1972, the license was amended to permit SNEC to possess although not to operate the SNEC reactor.
The facility was built from 1960 to 1962 and operated from 1962 to 1972 primarily as a research and training reactor. After permanent cessation of operation in 1972, the facility was placed in a condition equivalent to the current SAFSTOR status. Since then, it had been maintained in a monitored condition. The fuel was removed in 1972 and shipped to a (now DOE) facility at Savannah River, SC, who is now the owner of the fuel. As a result of this, neither SNEC nor GPU Nuclear, Inc. has any further responsibility for the spent fuel from the SNEC facility. The building and structures that supported reactor operation were partially decontaminated by 1974.
In the late 1980s and through the 1990s, additional decontamination and disassembly of the containment vessel and support buildings and final equipment and large component removal was completed. Final decontamination and dismantlement of the reactor support structures and buildings was completed in 1992. Large component structures, the pressurizer, steam generator, and reactor vessel were removed in late 1998.
Containment vessel removal (to below grade) and backfill was completed in late 2003.
Currently, decontamination, disassembly and demolition of the SNEC facility buildings and equipment have been completed and the facility is in the process of Final Status Survey for unrestricted release and license termination.
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3.2 Remediation Status The Northwest Sector was contaminated as a result of SNEC Facility nuclear system leakage. Initial remediation began with the removal of the spent resin storage tanks and associated piping (1974). More recent excavation was done in the area to facilitate the installation of the Containment Vessel (CV) anchor bolts and the removal of the CV Steam Tunnel. Contaminated soil was identified during this phase and the soil was removed for disposal. Analysis of soil samples obtained after the excavation indicated activity in the region between anchor bolt number 5 and proceeding clockwise to anchor bolt number 40 (below the 803' elevation) has been reduced to an average of 0.82 pCi/g (Cs-137) with a maximum value of 4.5 pCi/g. Other activities in the vicinity include the installation of a grout curtain and digging and installing dewatering wells. Subsurface sample data collected in conjunction with these activities indicated activity up to 1.46 pCi/g (Cs-137). Remediation activities adjacent to this area are discussed in the Historical Site Assessment (Reference 9.6) and the 1994 Soil Remediation Project (Reference 9.7). Further remediation was performed in response to the identification of contaminated soil during excavation activities in adjacent areas during the same time period.
The South Sector of CV (including CV External Shell) was contaminated as a result of SNEC Facility CV Steam and Pipe Tunnel / system leakage. Excavation was done in the area to facilitate the installation of the CV anchor bolts and removal of the Steam Tunnel. Contaminated soil was identified during this phase and the soil was removed for disposal. Other activities in the vicinity include the installation of grout curtain and digging and installing dewatering wells. Earlier characterization sampling in the vicinity of the CV Steam and Pipe Tunnel sections indicated activity above the DCGLW but remediation could not be performed until the CV concrete removal activities were completed. After the removal of these structures, soil samples in the vicinity indicated that the residual contamination levels had been reduced to an average of 0.19 pCi/g (Cs-137) with a maximum value of 0.4 pCilg. Remediation activities adjacent to this area are discussed in the Historical Site Assessment (Reference 9.6) and the 1994 Soil Remediation Project (Reference 9.7). Further remediation was performed in response to 8
the identification of contaminated soil during excavation activities in adjacent areas during the same time period.
The Northeast Sector of CV (including CV Concrete Cap) was contaminated as a result of SNEC Facility CV Pipe Tunnel / system leakage. Initial remediation began with the removal of the spent resin storage tanks and associated piping (1974). More recent excavation was done in the area to facilitate the installation of the Containment Vessel (CV) anchor bolts and the removal of the CV Steam Tunnel. Contaminated soil was identified during this phase and the soil was removed for disposal. Other activities in the vicinity include the installation of grout curtain and digging and installing dewatering wells. Remediation activities adjacent to this area are discussed in the Historical Site Assessment (Reference 9.6) and the 1994 Soil Remediation Project (Reference 9.7).
Further remediation was performed in response to the identification of contaminated soil during excavation activities in adjacent areas during the same time period.
The Southwest Sector of CV was contaminated as a result of SNEC Facility CV Steam Tunnel / system leakage. Excavation was done in the area to facilitate installation of the CV anchor bolts and removal of the Steam Tunnel. Other activities in the vicinity include the installation of grout curtain and digging and installed dewatering wells. Analysis of soil samples taken after excavation of the area shows that the region has been reduced to an average of 0.26 pCi/g (Cs-1 37) with a maximum value of 0.51 pCi/g. Remediation activities adjacent to this area are discussed in the Historical Site Assessment (Reference 9.6) and the 1994 Soil Remediation Project (Reference 9.7). Further remediation was performed in response to the identification of contaminated soil during excavation activities in adjacent areas during the same time period.
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4.0 Site Release Criteria The site release criteria that is applied to the open land areas, structures, and backfill materials corresponds to the radiological dose criteria for unrestricted use per 10CFR20.1402. The dose criteria is met 'if the residual radioactivity that is distinguishable from background radiation results in a Total Effective Dose Equivalent (TEDE) to an average member of the critical group that does not exceed 25 mrem/yr, including that from groundwater sources of drinking water, and that the residual radioactivity has been reduced to levels that are as low as reasonably achievable (ALARA)". Levels of residual radioactivity that correspond to the allowable dose to meet the site or survey unit release criteria for open land were derived by analyses using a resident farmer scenario. The dose modeling for this scenario is explained in the SNEC LTP (Reference 9.3). The derived concentration guideline levels (DCGL) shown in Table 5-1 of the SNEC LTP form the basis for satisfying the site release criteria.
Levels of residual radioactivity that correspond to the allowable dose to meet the site or survey unit release criteria for the building structures were derived by analyses using the building occupancy (surface area) scenario.
The dose modeling for both scenarios is explained in the SNEC LTP, Chapter 6. The derived concentrations guideline levels (DCGLs) determined in the LTP form the basis for satisfying the site release criteria.
Residual radioactivity sample results from the appropriate media were used to calculate a surrogate Cs-137 DCGL. The adjusted surrogate DCGL was developed using the methodology described in the SNEC LTP section 5.2.3.2.3 based on nuclide specific DCGLw from Table 5-1 of the LTP.
An adjustment was made to the surrogate Cs-137 DCGL to address the de-listed radionuclides as described in the LTP section 6.2.2.3. SNEC has instituted an administrative limit of 75% of the DCGL for all measurement results. The de-listed radionuclides are conservatively accounted for in this 25% reduction since the de-listed radionuclides were only 4.7% of the dose contribution. These adjustment factors are discussed in section 6 of the SNEC LTP.
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5.0 Survey Desiqns/DQO Process The DQO Process is a series of planning steps based on the scientific method for establishing criteria for data quality and developing survey designs. Planning radiation surveys using the DQO Process improves the survey effectiveness and efficiency, and thereby, the defensibility of decisions. Survey unit designs are provided in Appendices A through E. Scan coverage measurements were set at 100% for Class 1 and 2 areas and approx. 17% for the Class 3 area. The number of static measurement points was determined using the COMPASS computer program (Reference 9.8). These points were located on survey maps for each survey unit using the VSP, Visual Sample Plan (Reference 9.9) computer code.
Survey designs use gross activity DCGLW values developed from results of samples taken in the respective areas. The samples consisted of soil and sediment media obtained in the vicinity of the CV excavation areas. The sample results were tabulated to calculate the mean of each data set. Isotopic ratios were determined from the mean and used to calculate the effective DCGLw.
Isotopic ratios were calculated using representative sample data for each survey unit covered under this report. In all cases Cs-137 is the predominate radionuclide and provides the most detectable radionuclide in the various mixes. Specific DQO's for each survey unit is listed within Section 6.1 to 6.5.
6.0 Final Status Survey Results The following sections provide the survey summary results for each survey unit as required by the respective design. Summary data was taken from the survey request summaries for each respective survey unit.
6.1 Northwest Sector The northwest sector is divided into two (2) survey units, OL1-2 and MA8-1. Table 1 presents the Data Quality Objectives (DQO) and other relevant information from the survey design package.
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Table 1 Data Quality Objectives Listing for OL1-2, MA8-1 DQO/Design Parameter OL1-2 MA8-1 Area Size (M2) 309 48 Statistical Test Sign WRS Type I Decision Error (a) 0.05 0.05 Type II Decision Error (p) 0.10 0.10 Lower Boundary of the Gray 35 pCi/g 1,100 cpm Region (LBGR) 3.5 ______1,100 ____
Estimated a (cpm) 1.06 53.6 A/a 0.75 3.0 Minimum Number of Static 39 8 Data Points (COMPASS) 9_8 19,834 dpm/100 Administrative Cs-137 DCGLW 4.3 pCi/g cm 2 DCGLW (ncpm) N/A 1,260 447dpm/1 2 00 Scan MDC 3.2 pCi/g cm Static MDC (dpm/100 cm2 ) N/A 2,231 SNEC Survey Request No. 116 117 Ludlum 2350-1 Ludlum 2350-1 Survey Instrument Model with a 44-10 with a 43-68 detector detector Instrument Total Efficiency N/A 0.054 Measurement Type Scan Scan/static 6.1.1 Scan survey Scan measurements were performed in both survey units. Nal scans were performed on OL1 -2 using a MDCSan of 3.2 pCi/g (page 3 of Appendix A). Coverage was 100% as required by the Survey Design. The action level was 200 net cpm (page 2 of Appendix A). The Administrative Cs-1 37 DCGLW was 4.3 pCi/g (page 2 of Appendix A).
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Results: All areas indicated levels below action level except for one area designated AP1 (approx. 0.3 M2 ). A static measurement of this area indicated 1945 net cpm. A sample was obtained. The sample indicated 120 pCi/g, Cs-137 and 1.0 pCi/g, Co-60.
Follow-up action: An investigational survey was performed in accordance with section 5.5.1.3 of the SNEC LTP. The scan was performed covering approximately 1 m2 of surface area surrounding AP1. All areas indicated measured activity below the action level. Additionally, a sample was obtained adjacent to the initial sample location. This sample indicated an activity of 3.6 pCi/g, Cs-137 and <0.06 pCi/g, Co-60.
==
Conclusion:==
Based on the follow-up scan and sample results, the investigation concluded that the initial sampling removed this small area of elevated activity. As indicated by the scan and sample results, the residual contamination levels in this area therefore indicate activity well below the action level.
Gas Flow Proportional Counter scans (GFPC) scans were performed on MA8-1 with an MDAsc.,of 4,407 dpm/100 cm2. Scan coverage was 100% as required by the Survey Design. The action level was 500 net cpm (page 4 of Appendix A). The gross activity administrative DCGLW was 33,325 dpm/1 00cm 2 (attachment 2-6 of Appendix A).
Results: All surfaces indicated activity below the action level.
6.1.2 Static measurements GFPC measurements were performed on MA8-1. A total of twenty measurement pairs were obtained in locations using a random start, triangular grid, systematic method as required by the Survey Design. The effective gross DCGLw for this survey unit was 1,260 ncpm (page 4 of Appendix A). Detector window was on contact with the surface.
Results: The highest activity indicated was 445 cpm (unshielded). Therefore, all results indicate activity well below the action level. Table 2 lists the results:
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Table 2 Northwest Sector GFPC Static Measurements e ID Point Unshielded Reading Survey D Fixed (cpm) 1 366 2 333 3 349 4 309 5 355 6 362 Concrete A - Ventilation Pad 7 341 8 403 Mean 352 2 St. Dev. 27 Max 403 Min 309 Median 352 1 307 2 274 3 202 4 323 5 304 Concrete B - Old Railroad 6 358 Pad Mean 295 2 St. Dev. 53 Max 358 Min 202 Median 306 1 410 2 445 3 411 4 432 5 417 Concrete Spoils 6 418 Mean 422 2 St. Dev. 147 Max 445 Min 410 Median 418 14
6.1.3 Surface Soil Samples A total of thirty-nine random start, triangular grid, systematic soil samples were obtained in survey unit OL1-2 as required by the Survey Design. The Administrative Cs-137 DCGLW was 4.3 pCi/g (page 2 of Appendix A).
Results: Thirty-five samples indicated positive Cesium-137 activity ranging from 0.06 to 1.6 pCi/g. Cobalt-60 was not identified. Typical achieved MDA for non-positive Cesium-137 was 0.08 pCi/g and Cobalt-60 was 0.07 pCi/g. Therefore, all samples indicated Cs-137 activity well below the Administrative Cs-137 DCGLW. Table 3 lists the results for each sample:
Table 3 Sample Cs-137 Result (pCilg) Sample Cs-137 Result (pCilg)
NIimhpr N__MPr 1 0.09 23 0.08 2 0.15 24 <0.09 3 1.0 25 0.06 4 0.1 26 1.0 5 0.4 27 0.16 6 0.09 28 0.2 7 0.86 29 <0.08 8 <0.08 30 0.13 9 0.1 31 0.2 10 0.07 32 0.3 11 1.4 33 1.4 12 0.1 34 1.0 13 0.1 35 0.4 14 0.08 36 0.3 15 0.09 37 0.2 16 1.0 38 0.8 17 0.1 39 1.3 18 0.6 MEAN 0.42 19 <0.05 2 SIGMA 0.9 20 0.35 MAX 1.4 21 0.08 MIN 0.06 22 0.3 15
6.2 South Sector of CV (including CV External Shell)
The south sector is divided into four (4) survey units, OL1-3, MA8-2, CV4-2 and CV5-1.
Table 4 presents the Data Quality Objectives (DQO) and other relevant information from the survey design package.
Table 4 Data Quality Objectives Listing for OLI-3, MA8-2, CV4-2, CV5-1 DQO/Design OL1--3 MA8-2 CV4-2 CV5-1 Parameter .
SNEC Design Calc. E900-04-009 E900-04-009 E900-04-009 E900-04-009 N o ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Area Size (M2) 395 13 7.4 16.2 Statistical Test WRS WRS WRS WRS Type I Decision Error 0.05 0.05 0.05 0.05 (a)
Type II Decision Error 0.10 0.10 0.10 0.10 Lower Boundary of the 3.7 pCi/g 2,375 cpm 5,600 cpm 5,600 cpm Gray Region (LBG R) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Estimated a (cpm) 0.39 50.9 93.9 93.9 A/a 1.5 2.8 3.0 3.0 Minimum Number of Static Data Points 14 8 8 8 (COMPASS)
Administrative Cs-137 2.2 19,834 19,834 19,834 DCGLw (dpm/100 cm2) pCi/g9_1_83_1983 19_834 DCGLW (ncpm) - 200 2,519 5,879 5,879 Scan MDC (dpm/100 4.1 pCi/g 2,204 784 784 Static MDC (dpm/100 N/A 1,116 400 400 cm2)/A) 1,116 400 400 SNEC Survey Request 140 140 140 140 N o ._ _ _ _ _ __ _ _ _ _ _
Ludlum 2350- Ludlum 2350- Ludlum 2350- Ludlum 2350-Survey Instrument 1 with a 44-10 1 w/43-68 and 1 wlth a 43-68 1 with a 43-68 Model detector 44-10 detector detector Instrument Total N/A 0.0624 0.014 0.14 Efficiency Measurement Type Scan Scan/static Scan/static Scan/static 16
6.2.1 Scan survey Scan measurements were performed in each of the four survey units. Nal scans were performed on OL1-3 (open land areas and the concrete block) using a MDCscan of 2.2 to 4.4 pCi/g (page 3 of Appendix B). The Cs-1 37 Scan coverage was 100% as required by the Survey Design. The action level was 300 gross cpm (page 4 of Appendix B). The Administrative Cs-1 37 DCGLW was 4.3 pCi/g. (page 3 of Appendix B).
Results: Activity exceeding the action level was identified in fourteen locations throughout OL1-3. These areas were bounded, static measurements were obtained in the highest activity areas of each area, and samples were obtained. The static measurement results ranged from 300 to 386 gross cpm. Eight samples indicated positive Cesium-137 activity, ranging from 0.17 to 2.0 pCi/g. No Cobalt-60 activity was indicated.
Follow-up Action: Bismuth-214 was identified in the isotopic analyses. The peak energy of 609 KeV is detectable within the 100 KeV width of the Cs-137 window of the Nal detector. Although the scan action level was exceeded, the sample results indicate that the residual soil contamination levels are well below the DCGLw.
Nal detector scans was also performed on MA8-2. Scan coverage was 100% as required by the Survey Design. The action level was 300 gross cpm (page 4 of Appendix B). The MDCscan was 4.1 pCi/g. The Administrative Cs-137 DCGLw was 4.3 pCi/g (page 3 of Appendix B).
Results: All areas indicated levels below the action level with one exception. An area (approx. 1 ft2) indicated 309 cpm on a one-minute static measurement. A concrete sample was obtained in this location indicating 1.0 +/- 0.1 pCi/g, Cs-137, <0.05 pCi/g, Co-60.
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Follow-up Action: Bismuth-214 was identified in the isotopic analyses. The peak energy of 609 KeV is detectable within the 100 KeV width of the Cs-1 37 window of the Nal detector. Although the scan action level was exceeded, the sample results indicate that the residual soil contamination levels are well below the DCGLW.
GFPC scans were performed on MA8-2, CV4-2, and CV5-1. Scan coverage was 100%
as required by the Survey Design. The action level was 2,500 gross cpm for the CV shell and 1,200 gross cpm for the concrete structures (page 4 of Appendix B). The gross activity administrative DCGLw was 33,325 dpm/100 cm2 (attachment 3-5 of Appendix B).
Results: All areas indicated activity below the action level.
6.2.2 Static Measurements GFPC measurements were performed on MA8-2, CV4-2, and CV5-1. A total of forty-two measurement pairs were obtained in locations using a random start, triangular grid, systematic method as required by the Survey Design. The DCGLw for the CV shell was 5,879 ncpm and the DCGLwfor the concrete wall was 2,519 ncpm. The detector window was on contact with the surface.
Results: The highest activity indicated was 482 cpm (unshielded). All results indicate activity well below the respective DCGLw. Table 5 lists the results:
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Table 5 South Sector GFPC Static Measurements y
SreID l Unshielded Reading(cpm)
Su SreID ID 1Reading(cpm)
Unshielded CV4-2 -1 304 CV5-1 -1 336 2 383 2 291 3 357 3 374 4 380 4 408 5 297 5 335 6 346 6 320 7 328 7 317 8 298 8 335 9 334 9 307 10 367 10 351 11 328 11 356 12 333 12 317 13 391 13 271 14 351 MEAN 332 15 354 2 ST. DEV. 71 16 376 MAX 408 17 268 MIN 271 18 261 MEDIAN 335 MEAN 336 MA8-2 -1 369 2 ST. DEV. 77 2 345 MAX 391 3 371 MIN 261 4 399 5 414 6 409 7 389 8 482 9 430 10 357 11 369 MEAN 394 2 ST. DEV. 78 MAX 482 MIN 345 MEDIAN 389 19
6.2.3 Surface Soil Samples A total of eighteen random start, triangular grid, systematic soil samples were obtained in survey unit OL1-3. The Administrative Cs-137 DCGLw was 4.3 pCi/g (page 3 of Appendix B).
Results: The highest activity indicated was 0.4 +/- 0.1 pCi/g, Cs-137, <0.1 pCi/g, Co-60.
Positive Cs-137 samples ranged from 0.07 to 0.4 pCi/g. Co-60 was not indicated on the samples. Typical achieved MDA for non-positive Cesium-137 was 0.07 pCi/g and Cobalt-60 was 0.09 pCi/g. All results indicate activity well below the Administrative Cs-137 DCGLW. Table 6 lists the results:
Table 6 Sample Number Cs-I37 Result (pCi/g) 1 <0.09 2 <0.1 3 0.2 4 <0.1 5 <0.1 6 0.18 7 <0.07 8 0.3 9 <0.14 10 0.18 11 <0.07 12 <0.07 13 0.07
.14 0.2 15 <0.05 16 0.4 17 0.09 18 0.3 MEAN 0.2 2 SIGMA 0.2 MAX 0.4 MIN 0.07 20
6.3 Northeast Sector of CV (including CV Concrete Cap)
The Northeast Sector is divided into two (2) survey units, OLI-4 and MA8-3. Table 7 presents the Data Quality Objectives (DQO) and other relevant information from the survey design package.
Table 7 Data Quality Objectives Listing for OLI-4 and MA8-3 DQOIDesign Parameter OL1-4 MA8-3 SNEC Design Caic. No. E900-04-013 E900-04-013 Area Size (M2) 441 182 Statistical Test WRS WRS Type I Decision Error (a) 0.05 0.05 Type II Decision Error (13) 0.10 0.10 Lower Boundary of the Gray 3.2 pCi/g 5,770 cpm Region (LBGR) 3.2 ______5,770 ____
Estimated a (cpm) 1.06 38.7 A/a 1.0 2.8 Minimum Number of Static 26 8 Data Points (COMPASS) 26 Administrative Cs-137 19,834 dpm/100 DCGLw 4. pCi/g cm 2 DCGLW (ncpm) N/A 5,879 Scan MDC (dpm/100 cm 2 ) 3.2 pCi/g 929 Static MDC (dpm/100 cm2 ) N/A 478 SNEC Survey Request No. 147 147 Ludlum 2350-1 with a Ludlum 2350-1 Survey Instrument Model 44-10 detector w/43-68 detector Instrument Total Efficiency N/A 0.14 Measurement Type Scan/static Scan/static 21
6.3.1 Scan Results Scan measurements were performed in both survey units. Nal scans were performed on OL1-4 using a MDCscan of 2.2 to 4.4 pCi/g (page 2 of Appendix C). Scan coverage was 100% as required by the Survey Design. The action level was 300 gross cpm (page 3 of Appendix C). The Administrative Cs-137 DCGLW was 4.3 pCi/g (page 2 of Appendix C).
Results: All areas indicated activity below the action level with five exceptions. The area was approx. 1 ft2 and the activity ranged from 314 to 350 cpm. Soil samples were obtained in these areas. Two samples indicated positive Cs-137 with results indicating 0.07 and 0.2 pCi/g. Co-60 was not indicated.
Follow-up Action: Bismuth-214 was identified in the isotopic analyses. The peak energy of 609 KeV is detectable within the 100 KeV width of the Cs-1 37 window of the Nal detector. Although the scan action level was exceeded, the sample results indicate that the residual soil contamination levels are well below the DCGLw.
GFPC scans were performed on MA8-3. Thirty-six 1m2 grids were required by the Survey Design using a MDCsan of 929 dpm/100 cm2 (page 2 of Appendix C). The action level was 3,000 gross cpm (page 3 of Appendix C). The gross activity administrative DCGLW was 33,325 dpm/1 00 cm 2 (attachment 4-6 of Appendix C).
Results: All required areas were scanned with some exceptions. Due to placement of grids on map, a total of 7.41 m2 of surface area fell outside the boundaries of the CV.
The scan coverage was approximately 15%. All areas indicated activity below the action level.
6.3.2 Static Measurements GFPC measurements were performed on MA8-3. Ten measurement pairs were obtained using a random start, triangular grid, systematic method as required by the 22
Survey Design. The effective gross DCGLw for this survey unit was 5,879 ncpm (page 3 of Appendix C). The detector window was on contact with the surface.
Results: The highest activity indicated was 555 cpm (unshielded). All areas indicated activity well below the DCGLW. Table 8 lists the results:
Table 8 Northeast Sector GFPC Static Measurements Static Location Number Unshielded Reading(cpm)
MA8-3-1 410 2 555 3 366 4 376 5 410 6 469 7 454 8 456 9 538 10 453 MEAN 449 2 ST. DEV. 125 MAX 555 MIN 366 MEDIAN 454 Nal measurements were performed on OL1-4. Thirty measurements were obtained as required. The DCGLw for this survey unit was approximately 200 ncpm (page 3 of Appendix C). The detector was held within 4 inches of the surface.
Results: The highest activity indicated was 293 gross cpm. Background in the area ranged from 100 to 400 cpm. All areas indicated activity well below the DCGLW. Table 9 lists the results:
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Table 9 Northeast Sector Nal Static Measurement Results Survey Results (gross Survey Results (gross ID cpm) ID cpm) 0L1-4 -1 193 19 197 2 185 20 181 3 176 21 175 4 160 22 207 5 177 23 239 6 185 24 249 7 192 25 189 8 218 26 149 9 185 27 167 10 163 28 232 11 186 29 122 12 166 30 137 13 293 MEAN 190 2 ST. 777 14 122 DEV.
15 190 MAX 293 16 214 MIN 122 17 264 MEDIAN 186 18 h 189 6.3.3 Surface Soil Samples A total of 30 random start, triangular grid, systematic soil samples were obtained in OL1-4 in the locations listed in the Survey Design. The highest activity indicated was 1.0
+/- 0.14 pCi/g, Cs-137, <0.1 pCi/g, Co-60. Positive Cs-137 samples ranged from 0.07 to 1.0 pCi/g. Co-60 was not indicated on the samples. Table 10 lists the results:
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Table 10 Sample Number Cs-137 Result (pCilg) 1 <0.1 2 0.1 3 <0.09 4 0.13 5 <0.12 6 0.07 7 <0.15 8 1.0 9 0.19 10 0.13 11 <0.14 12 <0.1 13 <0.1 14 <0.09 15 0.13 16 <0.13 17 <0.1 18 0.15 19 0.1 20 0.1 21 0.1 22 0.66 23 0.3 24 0.45 25 <0.07 26 0.13 27 <0.13 28 <0.08 29 0.12 30 0.26 MEAN 0.24 2 SIGMA 0.50 MAX 1.0 MIN 0.07 25
6.4 Southwest Sector of CV The Southwest Sector is divided into two (2) survey units, OL1-5 and MA8-4. Table 11 lists the Data Quality Objectives (DQO) and relevant other information from the survey package.
Table 11 Data Quality Objectives Listing for OLI-5 and MA8-4 DQOIDesign OLI-5 MA8-4 Parameter SNEC Design Calc. No. E900-04-024 E900-04-024 Area Size (M2 ) 66 7.8 Statistical Test Sign WRS Type I Decision Error 0.05 0.05 (a)
Type II Decision Error 0.10 0.10 (13 ) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Lower Boundary of the 3.9 pCi/g 2,300 cpm Gray Region (LBGR) 3.9 ______2,300 ____
Estimated a (cpm) 0.14 101 A/a 2.9 2.1 Minimum Number of Static Data Points 11 10 (COMPASS)
Administrative Cs-137 4.3 pCi/g 19,834 dpm/100 cm2 DCGLw _ _ _ _ _ _ _
DCGLw (ncpm) N/A 2,515 Scan MDC 3.3 pCi/g 2,204 Static MDC2 (dpm/100 N/A 1,116 dpm/100 cm2 cm ) __N___ __ __ __ ___ 16____ ________
SNEC Survey Request 185 185 N o._ _ _ _ _ _ _ _
Survey Instrument Ludlum 2350-1 with Ludlum 2350-1 with a Model a 44-10 detector 43-68 detector Instrument Total N/A 0.06 Efficiency N/A 0.06 Measurement Type Scan Scan/static 26
6.4.1 Scan Survev Scan measurements were performed in both survey units. Nal scans were performed on OL1-5 using a MDCS.an of 3.3 pCi/g (page 2 of Appendix D). Scan coverage was 100% as required by the Survey Design. The action level was 200 net cpm (page 2 of Appendix D). The Cs-137 Administrative DCGLW was 4.3 pCi/g (page 2 of Appendix D).
Results: All areas indicated activity below the action level.
GFPC scans were performed on MA8-4 using a MDCsc>n of 2,204 dpm/100 cm2 (page 4 of Appendix D). The coverage was 100% as required by the Survey Design. The action level was 1,500 net cpm (page 4 of Appendix D). The Cs-137 Administrative DCGLW was 19,88ldpm/100 cm2 (attachment 2-5 of Appendix D).
Results: All surfaces indicated activity below the action level.
6.4.2 Static Measurements GFPC measurements were performed on MA8-4. 12 measurement pairs were obtained using a random start, triangular grid, systematic method as required by the Survey Design. The effective administrative DCGLw for this survey unit was 2,515 ncpm. The detector window was on contact with the surface.
Results: The highest activity indicated was 539 cpm. Table 13 lists the results:
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Table 13 Southwest Sector GFPC Static Measurements Location Unshielded Reading (cpm)
FP# 1 341 FP# 2 275 FP# 3 369 FP# 4 312 FP# 5 257 FP# 6 270 FP# 7 291 FP#8 452 FP# 9 392 FP# 10 410 FP# 11 414 FP# 12 539 Mean 360 2 Standard Deviations 171 Max 539 Min 257 Median 355 6.4.3 Surface soil samples Twelve soil samples were obtained in OL1-5 in the locations listed in the Survey Design.
The highest activity indicated was 0.46 +/- 0.13 pCi/g, Cs-137, <0.19 pCi/g, Co-60.
Positive Cs-137 samples ranged from 0.06 to 0.46 pCi/g. Co-60 was not indicated.
Table 14 lists the results:
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Table 14 Sample Number Cs-137 Result (pCi/g) 1 0.06 2 <0.17 3 <0.12 4 0.46 5 0.26 6 <0.13 7 0.21 8 0.29 9 <0.18 10 <0.13 11 0.1 12 <0.19 MEAN 0.22 2 SIGMA 0.29 MAX 0.46 MIN 0.06 6.5 Backfill Materials The material used for backfill throughout the CV Yard excavation areas (following the completion of FSS) was comprised of various soil/debris/boulder piles from on-site excavations and additional shale rock delivered from an off-site location. FSS was performed on the original East and West Soil piles and results were reported in Reference 9.4. FSS was performed on the balance of on-site materials under Survey Requests 0121 (Appendix K), 0122 (Appendix L), 0156 (Appendix M), and 0170 (Appendix N). FSS was performed on the off-site shale rock and results indicate activity below the site release criteria. This data will be reported at a later date. The following section described the survey requirements and survey results for the balance of soil/boulders used as backfill.
The material is divided into two (2) survey units, OLl-Misc-S (Soil) and OLl-Misc-B (Boulder). Table 15 lists the Data Quality Objectives (DQO) and relevant other information from the survey package.
29
Table 15 Data Quality Objectives Listing for OL1-Misc-S and OLI -Misc-B DQOIDesign Parameter OLI-Misc-S OLI-Misc-B l SNEC Design Caic. No. E900-04-006 E900-04-006 Area Size (M2) -1800 N/A Statistical Test Sign Sign Type I Decision Error (a) 0.05 0.05 Type II Decision Error (1) 0.10 0.10 Lower Boundary of the Gray 4 pCi/g 4 pCi/g Region_(LBGR) _ _ _ _ _ _ _ _ _ _
Estimated a (cpm) 0.11 0.10 A/a 2.7 2.9 Minimum Number of Static 11 11 Data Points (COMPASS)
DCGLW 4.3 pCi/g 4.3 pCi/g DCGLw (ncpm) N/A N/A Scan MDC 3.2 pCi/g 3.2 pCi/g Static MDC (dpm/100 cm2) N/A N/A SNEC Survey Request No. 122,170 121,156 Ludium 2350-1 with Ludlum 2350-1 with a Survey Instrument Model a 2350 with 43-68 and a 44-10 a detctordetector 44-0 Instrument Total Efficiency N/A N/A Measurement Type Scan Scan 6.5.1 Scan survey Scan measurements were performed on both survey units. Nal scans were performed using a MDCsca of 3.2 pCi/g (page 2 of Appendix E). Scan coverage was 100% as required by the Survey Design. The action level was 304 cpm (boulders) and either 200 ncpm (ABCR) or 289 gross cpm for soil (page 2 of Appendix E or survey requests). The Administrative Cs-1 37 DCGLw was 4.3 pCi/g (page 2 of Appendix E).
Results: All surfaces indicated activity below the respective action level.
30
6.5.2 Soil/Rock Samples One hundred-four soil samples were obtained in OLl-Misc-S in the locations identified in the Survey Design. ). The Administrative Cs-137 DCGLw was 4.3 pCi/g (page 2 of Appendix E).
Material indicating activity above 4.3 pCi/g, Cs-137 would be removed for disposal.
Results: The highest Cs-137 activity identified at 2.4 +/- 0.02 pCi/g, <0.08 pCi/g, Co-60.
No Co-60 was indicated in the samples. The range of positive Cs-137 samples was 0.08 to 2.4 pCi/g. The typical achieved Co-60 MDA was 0.11 pCi/g.
One hundred-twelve rock samples were obtained in OL1-Misc-B in the locations identified in the Survey Design.
Results: The highest Cs-137 activity indicated was 0.36 +/- 0.08 pCi/g, <0.08 pCi/g, Co-
- 60. No Co-60 was identified in the samples. The range of positive Cs-137 samples was 0.05 to 0.36 pCi/g.
7.0 Data Assessment 7.1 Assessment Criteria The final status survey data has been reviewed to verify authenticity, appropriate documentation, and technical acceptance. The review criteria for data acceptability are:
Instruments used to collect the data were capable of detecting the radiation of interest at or below the investigation level.
Calibration of the instruments, used to collect the data was current and radioactive sources used for calibration were traceable to recognized standards or calibration organizations.
Instrument response was checked before and, where required, after instrument use each day data was collected.
31
- Survey team personnel were properly trained in the applicable survey techniques, and this training was documented.
- MDCs and the assumptions used to develop them were appropriate for the instruments and the survey methods used to collect the data.
- Survey methods used to collect the data were appropriate for the media and types of radiation being measured.
- Special measurement methods used to collect data were applied as warranted by survey conditions, and were documented in accordance with an approved site Survey Request procedure.
- Chain of custody of samples that were sent for off-site laboratory analysis, were tracked from the point of collection until the final results were obtained.
The final status survey data consists of qualified measurement results representative of current facility status collected in accordance with the applicable survey design package.
Discrepancies were reviewed and corrective actions taken (as appropriate) in accordance with site procedures.
The statistical test does not. need to be performed for this final status survey since the data clearly show that the survey units meets the site release criteria. All measurements in the survey units are less than the DCGLW.
32
7.2 Summary of Overall Results OL1-2: 100% scan indicated one alarm point. Sampling of this area removed the activity. Follow-up scans and sampling was performed to verify the residual contamination levels. All areas therefore indicated levels below the applicable DCGLW.
39 soil samples were obtained that indicated activity well below the DCGLw. Therefore the survey unit meets the release criteria of the LTP and the requirements of MARRSIM.
OL1-3: 100% scan indicated 14 locations exceeding the action level. Eight (8) of the 14 samples obtained indicated positive Cesium-137 activity (up to 2.0 pCi/g). All areas therefore indicated levels well below the DCGLw. 14 soil samples were obtained indicating activity well below the DCGLw. Therefore the survey unit meets the release criteria of the LTP and the requirements of MARRSIM.
OL1-4: 100% scan indicated five (5) locations exceeding the action level. Two of the five samples indicated positive Cs-137 (up to 0.2 pCi/g). All areas therefore indicated levels well below the DCGLW. 30 static measurements performed indicated activity well below the DCGLW. 14 soil samples were obtained indicating activity well below the DCGLW.
Therefore the survey unit meets the release criteria of the LTP and the requirements of MARRSIM.
OL1-5: 100% scan indicated levels in all areas well below the DCGLW. 12 soil samples obtained indicated activity well below the DCGLw. Therefore the survey unit meets the release criteria of the LTP and the requirements of MARRSIM.
MA8-1: 100% scan indicated levels in all areas well below the DCGLw. 22 static measurements performed indicated activity well below the DCGLw. Therefore the survey unit meets the release criteria of the LTP and the requirements of MARRSIM.
33
MA8-2: 100% scan indicated levels in all areas well below the DCGLw. 11 static measurements performed indicated activity well below the DCGLw. Therefore the survey unit meets the release criteria of the LTP and the requirements of MARRSIM.
MA8-3: The 36 grids scanned indicated levels in all areas well below the DCGLw. 10 static measurements performed indicated activity well below the DCGLw. Therefore the survey unit meets the release criteria of the LTP and the requirements of MARRSIM.
MA8-4: 100% scan indicated levels in all areas well below the DCGLw. 12 static measurements performed indicated activity well below the DCGLW. Therefore the survey unit meets the release criteria of the LTP and the requirements of MARRSIM.
OL1-Misc-S: 100% scan indicated levels in all areas well below the DCGLw. 104 soil samples obtained indicated activity well below the DCGLw. Therefore the survey unit meets the release criteria of the LTP and the requirements of MARRSIM.
OLI-Misc-B: 100% scan indicated levels in all areas well below the DCGLw. 112 soil samples obtained indicated activity well below the DCGLw. Therefore the survey unit meets the release criteria of the LTP and the requirements of MARRSIM.
7.3 Survey Variations (Design, survey request, LTP)
Section 6.3.1: Due to placement of grids on map, a total of 7.41 m2 of surface area fell outside the boundaries of the CV. The scan coverage was approximately 15%.
Section 6.5.2: Technicians failed to perform an initial surface scan (prior to the first filling) of each lift section floor as required by Survey Request 0122. This was due to an oversight of the technicians and GRCS. Impact: Since all soil scan survey results indicated activity below the action level, this pre-load scan requirement was not necessary.
34
7.4 QC Comparisons 7.4.1 Scan surveys Areas were rescanned as QC duplicates. The coverage percentages are listed in Table 16:
Table 16 Detector Initial Scan Re-scan Survey Unit Type SurfaceArea (m2) coverage (m2 Percentage OL1-2 44-10 309 20 6.5 MA8-1 43-68 48 3 6.3 OL1--3 44-10 395 23.2 5.9 CV4-2/CV5-1/MA8-2 43-68 20 2.9 14.5 MA8-2 44-10 13 1.7 13 MA8-3 43-68 31 2 6.4
_OL1-4 44-10 441 24 5.4 MA8-4 43-68 7.8 1.1 14.1 OL1--5 44-10 66 4.15 6.3 OL-Misc-S 44-10 600 90 15 OL-Misc-B 44-10 297.6 35.8 12 These percentages met the 5% requirement. All QC duplicate results have good agreement with the initial results and met the acceptance criteria of Reference 9.10.
QC rescans did not identify activity above the action levels with one exception:
Section 4.3.3: The Nal repeat scan of the northeast yard determined that four areas exceeded the action level. These areas were not identified on the initial scan survey.
Therefore this comparison does not meet the acceptance criteria. An investigation was performed in accordance with Reference 9.10 to establish an explanation for the failure.
Explanation: Although these areas indicated activity above the action level, samples obtained of these areas indicated a maximum of 0.07 pCi/g, Cs-137. This indicates activity well below the DCGLW of 3.4 pCi/g. Bismuth-214 was identified in the isotopic analyses. The peak energy of 609 KeV is detectable within the 100 KeV width of the Cs-35
137 window of the Nal detector. Although the scan action level was exceeded, the sample results indicate that the residual soil contamination levels are well below the DCGLW. Based upon the findings of the investigation, the Nal scan results covering survey unit OL1-4 are concluded to be valid.
7.4.2 Fixed-Point measurements Repeat fixed-point measurements were performed as QC duplicates. The coverage percentages are listed in Table 17:
Table 17 Survey Detector Number of Initial Number of Unit Type Fixed-point Repeat Percentage Measurements Measurements OL1--2 44-10 40 3 7.5 MA8-1 43-68 20 4 20 OL1-3 44-10 14 2 14.3 CV4-2/CV5-1/MA8-2 43-68 42 5 11.9 MA8-3 43-68 10 1 10 OL1-4 44-10 35 3 8.6 MA8-4 43-68 12 1 8.3 These percentages met the 5% requirement. All QC duplicate results have good agreement with the initial results and met the acceptance criteria of Reference 9.10.
7.4.3 Soil Samples Repeat soil sampling was performed as QC duplicates. The percentages were as follows. SR-116 (7.3%), SR-140 (5.5%), SR-147 (5.4%), SR-185 (7.7%). Note: SR-117 required no sampling. This exceeds the minimum 5% required. All QC duplicate results have good agreement with the initial results and met the acceptance criteria of Reference 9.10.
36
8.0 Final Survey Conclusions The FSS on the SNEC Facility Containment Vessel Concrete Cpp and surrounding open land areas, below-grade concrete structural remnants, and Packfill materials was performed in accordance with Revision 2 and 3 of the SNEC LTP and site implementing procedures. Final status survey data was collected to meet and/or exceed the quantity and quality specified for each survey unit as prescribed by the applicable survey design.
The survey data for each survey unit met the following conditions:
- 1. The average residual radioactivity in the areas surveyed was less than the assigned DCGLw.
2 Since all measurements were less than the DCGLw, no DCGLEMC criteria needed to be applied.
3 Remediation was performed to reduce levels of residual radioactivity to below the concentrations necessary to meet the applicable DCGLW.
These conditions satisfy the release criteria established in the SNEC LTP and the radiological criteria for unrestricted use given in 10 CFR 20.1402. Therefore, it is concluded that the open land areas, concrete structures, and the CV concrete cap as described in this report are suitable for unrestricted release.
37
9.0 References 9.1 10 CFR 20.1402 9.2 10 CFR 50.82(a)(1 1) 9.3 SNEC License Termination Plan 9.4 FSS Report, "SNEC CV Interior Above 774' Elev. and Exterior" 9.5 FSS Report, "SNEC CV Interior, 774' El. & Below' 9.6 Historical Site Assessment 9.7 1994 Soil Remediation Project Report 9.8 Compass Computer Program, Version 1.0.0, Oak Ridge Institute for Science and Education 9.9 Visual Sample Plan, Version 2.0 (or greater), Copyright 2002, Battelle Memorial Institute 9.10 SNEC procedure E900-IMP-4520.04, "Survey Methodology to Support SNEC License Termination" 10.0 Appendices Appendix A - SNEC Calculation #E900-04-005, 'CV Yard Survey Design - North West Side of CV."
Appendix B - SNEC Calculation #E900-04-009, "CV Yard Survey Design - South Side of CV."
Appendix C - SNEC Calculation #E900-04-013, "CV Yard Survey Design - North East Side of CV."
Appendix D - SNEC Calculation #E900-04-024, "CV Yard Phase 4 - Survey Design" Appendix E - SNEC Calculation E900-04-006, "CV Yard Boulder and Soil Survey Designs" Appendix F - SNEC Survey Request (SR) # 116, CV Yard - "North West Side of CV" 38
Appendices (cont.)
Appendix G - SNEC Survey Request (SR) # 117, CV Yard - "North West Side of CV -
Concrete Structures" Appendix H - SNEC Survey Request (SR) # 140, "South Side of CV - concrete, steel, soil" Appendix I - SNEC Survey Request (SR) # 147, "North East Side of CV Yard and CV Cap" Appendix J - SNEC Survey Request (SR) # 185, Phase 4- "South West CV Yard -
Soil, Concrete Structures / Open Land" Appendix K - SNEC Survey Request (SR) # 121, "CV Yard Boulder Lift Area" Appendix L - SNEC Survey Request (SR) # 122, "CV Yard Soil Lift Area" Appendix M - SNEC Survey Request (SR) # 156, TCV Yard - Remaining Boulders" Appendix N - SNEC Survey Request (SR) # 170, "New CV Yard Soil Lifts" 39
ORIGINAL SNEC CALCULATION COVER SHEET
.. -CALCULATION DESCRIPTiON5-Calculation Number Revision Number )veDajePage DEffec Number E9004-005 0 Jox I Of Subject CV Yard Survey Design - North West Side of CV Question I - Is this calculation defined as 'In QA Scope'? Refer to definition 3.5. Yes 0 No 0 Question 2- Is this calculation defined as a 'Design Caicubtion'? Refer to definitions 3.2 and 3.3. Yes 0 No 0 Question 3- Does the calculation have the potential to affect an SSC as described in the USAR? Yes 0 No 0 NOTES: If a 'Yes' answer Isobtained for Question 1, the calculation must meet the requirements of the SNEC Faclity Decommissioning Quality Assurance Plan. If a 'Yes' answer is obtained for Question 2, the Calculation Originato's immediate supervisor should not review the calculation as the Technical Reviewer. If a 'YES' answer Isobtained for Question 3, SNEC Management approval Is required to implement the calculation. Calculations that do not have the potential to affect SSC's may be implemented by the TR.
. ;-. 7DESCRIPTIONOFREVISION :?:s ;-;:: ....
-.. _ '. -* APPROVALSIGNA Technical Reviewer Additional Review Additional Review N
SNEC Management ApprovalI
SNEC CALCULATION SHEET :
Calculation Number Revision Number Page Number E90040)05 0 Page 2 of /° Subjct CV Yard Survey Design - North West Side of CV 1.0 PURPOSE 1.1 The purpose of this calculation is to develop a survey design for one (1) CV Yard soil survey unit, and three miscellaneous concrete surfaces located in the same area. This is a below grade Class I open land area that is adjacent to the remaining SNEC CV structure. It extends upward from -about the 803' El (from the cut-off portion of the SNEC CV) to grade at -811' El. This survey unit is bounded on the south western side by the southern edge of an old concrete transformer support structure (Misc. Concrete A), and on the north eastern side by a single monitoring well. These landmarks are shown in Attachments 1-1 through 1-3.
1.2 The soil survey unit lies largely in site area OLI but borders QL2 and is designated OLI-
- 2. The three concrete surfaces are collectively designated MAS-1.
1.3 The total exposed soil surface area is -309 square meters and the concrete surfaces are collectively -48 square meters.
2.0
SUMMARY
OF RESULTS The following information should be used to develop a survey request for these survey units. The effective DCGLW-values are listed below. The Us -NRC has reviewed and concurred with these derived values. See Attachment 2-1 to 2-6.
Volurnetric DCGLw (pClfg -Cs137) I Surface Gross Ac&ity DCGLw (dpvnV 00 a 5.73 (4.3 A.L.) 44,434 (33,325 A.L.)
NOTE. AL Is tee site Amnistrattve Lmiht (75% of effecive DCGLw) 2.1 Soil and Fill Materials Survey Design 2.1.1 Scanning of soil and fill materials shall be performed using a 2" D by 2' L Nat detector wha Cs-137 window setting. The window will straddle the Cs-137 662 keV full energy peak width (see Attachment 3-1).
Soil Scanning Parameters MOCscan (pCUg) - cs- 37 Scan Speed (cmhec) Maxdmum Distance from Surface 3.2 25 4' (gap between)
The instrument conversion factorlefficiency shall be not less than the value reported on Attachment 3-1 (208oxm/uRih).
Class 1 soil should be scanned using a serpentine pattern that is -0.5 meters wide.
2.1.4 The MDCscan is determined using a MicroShield model (Attachment 4-1).
Calculatipos-are shown on Attachments 5-1 and 5-2.
2.1.5 Background has been measured in the area over similar background materials, and ranges from about 100 cpm to approximately 400 cpm (see Reference 3.1). If a count rate of greater than 200 ncPm is encountered during the scanning process, the surveyor should stop and locate the boundary of the elevated area. The surveyor should then mark the elevated area with stakes or other appropriate marking
I r_, -SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-04-005 0 Page 3 of l0 Subje]
CV Yard Survey Design - North West Side of CV methods. Sample the elevated areas(s) lAW SNEC procedure E900-MP-4520.04 (Reference 3-F).
NOTE This survey design must be revised if it is shown that the true background count rate (from natural occurring materials) is greater than -550 counts per minute.
Sampling points are to be clearlymarked, identified and documented.
2.1.7 All survey personnel shall be trained to identify 200 ncnm above background based on an audible instrument response.
Other instruments of the type specified in Section 2.1.1 above may be used during the FSS P1t they must demonstrate a detection efficiency at or above the value listed in Section 2.1.2 (-208 cpmluRlh).
2.1.9 The minimum number of sampling points indicated for this survey unit by Compass (Referenc .3.3) is 39. Soilifill sampling depth should be top 6 inches (15-cm). VSP (Reference 3.4) is used to plot all sampling points on included diagrams. In cases where the diagram is odd shaped (edge effect) andlor because of the selected starting point, the number of random start systematically spaced sample points may be greater than required by the Compass computer code.
2.1.10 The starting points for physically locating sample sites in the excavation area is based on measurements from the CV outer shell. All key measurement points are marked on Attachments 6-1 through 6-5. Soil sample points are positioned using coordinates developed from the center of the CV shell (see Attachment 6-7). Once the key points are located in the survey unit, a standard triangular grid system is laid out over the sloped survey area. Distances for soil sample points are measured over the contourof the survey 4mit.
2.1.11 Some starting point locations may need to be adjusted to accommodate obstructions within the survey area. Contact the SR coordinator to report any difficulties encountered when laying out systematic grid sampling points.
2.1.12 When an obstruction is encountered (during the sampling phase) that will not allow collection of a sample, contact the cognizant SR coordinatorfor permission to delete the surveypoint.
2.2 Survey Wok for Concrete Surfaces A Gas Flow Proportional Counter (GFPC) shall be used to survey concrete surfaces in this survey area. The folowing parameters should be used to develop a survey request.
Detection Efficiency Data
£i es % Cs8437 Efficiency Loss Factor counts/dlslntegration 0.478 0.5 0.595 0.21 0.0299 The overall counting efficiency for this survey design assumes a mix ratio as shown Attachment 2-6. The instrument and source efficiency -is assumed to be as shown in the previous Table. The detection efficiency is based on the instruments response to Cs-137. All other nuclides except H-3 are less than 1% of the total mix lAW
SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-04-005 I0 Page 4 of /D Subjed CV Yard Survey Design - North West Side of CV Attachment 2-6. A rough surface efficiency factor is employed to ensure that a representative efficiency is used for-weathered concrete. From Attachment 7-1 to 7-5 the assessment of the surface area of these rough concrete surfaces indicates that some pock marks and surface gouges are up to -2.8 inches deep. From Reference 3-5 and Attachment 7-5 this gap would reduce the overall efficiency by a factor of
-0.21. The resulting efficiency is then 0.03 csdis.
All GFPC instruments having an instrument efficiency (el) less than 0.478 should not be used for this survey work.
These parameters were incorporated into the Compass computer program. The following is the Compass output for this survey design.
MDCstc MDCscan (dp D cmOO2)a (dpn/1 00 cO2 )- Action Levl AssIgned During Phase I Scanning (ncpm) 2,231 4,407 500
- As calculated by the Compess computer progrem essuming badground velue df 306-pmn.
The number of static measurement points on miscellaneous concrete surfaces were determined using the Compass computer program (see Attachment 12-1 through 12-5). The required number of static measurement points was determined to be eight (8) points for the entire .48 M 2. VSP wasused to plot these locations. VSP plotted additional points and therefore some points may be deleted as necessary.
CV Yard Concrete Spoils Area (Attachment 6-3) --6 oints, CV Yard Concrete Misc. A (Attachment 6-4) -8 DOiftS
. CV Yard Concrete Misc. B (Attachment 6-5) - -6snts, 2.6.3 This survey design requires the detector be in contact with the surface during all measurement phases except in areas where this is not physically possible (gouges, cavities, etc.). .
2.6.4 The action level during first phase scanning is 500 cpm above background. If this level is reached, the surveyor should stop and perform a count of at least 1/2 minute duration to identify the actual count rate from the elevated location.
Areas greater than the DCGLw (1260 ncpm) must be identified, documented, marked, and bounded to include an area estimate.
NOTE If remediation actions are taken as a result of this survey, this survey design must be revised or re-written entirely.
3.0 REFERENCES
3.1 SNEC Calculation No. E900-03-018, Optimize Window and Threshold Settings for the Detection of Cs-1 37 Using the Ludlum 2350-1 and a 44/10 Nal Detector", 8/7103.
< SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900.04-005 I0 Page 5 of _L Subject CV Yard Survey Design - North West Side of CV 3.2 SNEC Procedure E900-IMP-4520.04, 'Survey Methodology to Support SNEC License Termination'.
3.3 Compass Computer Program, Version 1.0.0, Oak Ridge Institute for Science and Education.
3.4 Visual Sanple Plan, Version 2.0 {or greater), Copyright 2002, Battelle Memorial Institute.
3.5 SNEC Calculation No. 6900-02-028, GFPC Instrument Efficiency Loss Study.
3.6 SNEC Calculation No; E900-03-022, RevO, UCV YardSoil - Survey Design to El 803'".
3.7 Plan SNEC Facility License Termination Plan.
3.8 SNEC Pr9pedure E900-IMP-4500.59, "Final Site Survey Planning and DQA".
3.9 Westinghouse Electric Corporation, Gilbert Associates, Inc., Drawing No. D-37798, Saxton Reactor Project, Containment Vessel Penetration Access', 7121160.
GPU Nuclear, SNEC Facility, uContainment Vessel Survey", SNECRM-019, Rev I i 1/18/02.
ISO 7503-1, Evaluation of Surface Contamination, Part 1: Beta-emitters (maximum beta energy greater than 0.15 MeV) and alpha-emitters, 1988.
SNEC Facility HIstorical Site Assessment, Rev 0, March, 2000.
3.13 SNEC Calculation No. E900-03-012, Effective DCGL Worksheet Verification.
3.14 SNEC procedure E900-IMP-4520.06, "Survey Unit lnspectionin Support of ESS Design".
3.15 NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual", August, 2000.
Microsoft Excel 97, Microsoft Corporationl-nc., SR-2, 1985-1997.
4.0 ASSUMPTIONS AND BASIC DATA 4.1 The Compass computer program is used to calculate the required number of random start systematic samples to be taken in the survey unit (Reference 3.3).
4.2 Soil samples from this area are used as the initial estimate of variability for the OL1 area.
These results are shown on Attachment 8-1 (from Reference 3.6).
4.3 Concrete variability of the area structures was performed at the start of this work and are reported in Attachment 9-1. Backgroundd.variability results are taken form the Williamsburg survey work of non-impacted background material (see Attachment 10-1). No elevation correction has been applied to the Williamsburg results.
4.4 The MARSSIM Sign Test will be applicable for the soil section of this survey design. No background subtraction will be performed under this criteria.
4.5 The MARSSIM WRS Test criteria is applicable for concrete survey work in this area.
4.6 The number of points chosen by Compass are located on the survey map for the survey
.unit by the Visual Sample Plan VSP) -computer code (Reference 3.4).
SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-04-005 l 0 Page 6 of /jo Subjed CV Yard Survey Design - North West Side of CV 4.7 VSP is used to plot random start systematically spaced sampling points. The dimensions of selected pSurvey points are provided for each survey unit referenced to an existing survey area landmark (key point measurement location).
4.8 Reference 3.6, 3.7 and 3.8 was used as guidance during the survey design development phase.
The construction/assembly drawings used to determine the original physical extent of these areas are listed as Reference 3.9 and 3.10.
4.9 Remediation -History A review of survey request data pertaining to this open land area adjacent to the CV shell was conducted in support of this survey design. Analysis of soil samples taken after remediation of the area (from SR-0019), shows that the region between anchor bolt number 5 and proceeding Clockwise to-anchor bolt number 40 (below the 803' elevation), has been reduced to an average of 0.82 pCi/g (Cs-137) with a maximum value of 4.5 pCilg. Other subsurface sample data collected in conjunction with installation of the anchor bolts, grout curtain, and various wells within this area were also reviewed. These data are compiled and summarized in SR-0029. The highest activity of this sample group was .1.46 pCi/g for Cs-137. Earlier remediation history in this area is reported in the SNEC facility Historical Site Assessment document (Reference 3-12) and the 1994 Soil Remediation Project Report.
4.10 This survey design uses Cs-137 as a surrogate to bound the average concentration for all SNEC facility related radionuclides in the survey unit. The effective DCGLw is just the permitted Cs-137 concentration (6.6 pCilg) lowered to compensate for the presence (or potential presence) of other SNEC related radionuclides. In addition, an administrative limit (75%) has been set that further lowers the permissible Cs-1 37 concentration to an effective DCGLw for this radionuclide.
4.11 The sample data base used to determine the effective radionuclide mix for the CV Yard area has been drawn from previous samples that were assayed at off-site laboratories. This list is shown as Attachment 2-1 and 2-6, and includes (23) analysis results. Review of the data shows several radionuclides have -not been positively identified at any significant concentration. These radionuclides have been removed from the data set and will not be considered further. Radionuclides removed include Am-241, C-14, Eu-152, Ni-63, Pu-238, Pu-239 and Pu-41. Additionally, the data shows Cs-137 to be the predominant radioactive contaminant founo -in this area. Sr-90 on the other hand, was positively identified in only one (1)sample. H-3 was identified as a positive contaminant in six (6) samples, and Co-60 was identified in three (3)samples.
Remediation has impacted radionuclide concentration levels in this survey unit.
Remediation efforts -have been shown to-be effective in lowering the average concentration of Cs-137 in this survey unit to less than 4.5 pCig (see Attachment 8-1). Therefore, the impact of remediation must be considered in determining the effective Cs-137 DCGLw surrogate value. Remediation of this survey unit was completed by about July of 2001.
Samples collected prior to this date have been disqualified in the final listing which was decayed to Seppember 20 th, 2003. Inall, about twenty three (23) sample results were used to determine the best representative mix for this survey unit.
The decayed sample results were input to the spreadsheet titled 'Effective DCGL Calculator for Cs-137" (Reference 3-13)-to determine the effective volumetric and surface
SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-04-005 0 Page 7 of _IO Subject CV Yard Survey Design - North West Side of CV DCGLw values for the OL1 area. The output of this spreadsheet is shown o Attachment 2-5 and 2-6.
The Nal scan MDC calculation is determined based on a 25 cmlsec scan rate, a 1.38 index of sensitivity (95% correct detection probability and 60% false positive) and a detector sensitivity of 208 cpm/uR/h for Cs-137. Additionally, the detection system incorporates a Cs-1 37 window that lowers sensitivity to.background in the survey unit. The resulting range of background values varies from about 100 cpm to -400 cpm. The resulting MDCscan is
-3.2 pCVg (see Attachment 5-I1 and 5-2). This value is based on a nominal background value of 200 cpm.
The survey unit described in this survey design was inspected after remediation efforts were shown effective. A copy of portions of the SNEC facility post-remediation inspection report (Reference 3.14), is included as Attachment 7-1 to 7-4.
No special area characteristics including any additional residual radioactivity (not previously noted during characterization) have been identified in this survey area.
4.14 The decision error-for this survey design is 0.05 for the a value and 0.1 for the P value.
4.15 Special measurements including gamma-ray spectroscopy are not included in this survey design.
No additional sampling will be performed lAW this survey design beyond that described herein.
4.17 The applicable SNEC site radionuclides and their individual DCGLw values are listed on Exhibit I of this calculation.
The surveydessign checklist is listed in Exhibit 2.
4.19 Area factors are not applicable in subsurface soil volumes (below 1 meter). Therefore, the area factor input requirement for soil in the Compass computer program is I for both a 10,000 square meter-area as well as for-a I square meter area (see Attachment 11-1).
Area factors for concrete surface areas are shown on Attachment 12-1. These values are for Co-60 which is a constituent of the mix. However, Cs-137 and Co-60 area factors are very similar and therefore there-is little Impact from using the more conservative area factor.
5.0 CALCULATIONS 5.1 All calculations are performed internal to applicable computer codes or within an Excel spreadsheet.
6.0 APPENDICES 6.1 Attachment 1-1 to 4-2, are diagrams of survey unit OLI-2 and MA8 -1.
6.2 Attachment 2-1 to 2-6 is the sample results from the OLI area. In addition to the DCGL calculation sheets.
6.3 Attachment 3-1, is a copy of the calibration data from a typical Nal radiation detector that will be usoe~ in this survey.
6.4 Attachment 4-1, is a MicroShield model of a soil volume used to determine the exposure rate from a 1 pClg Cs-137 source term.
SNEC CALCULATION SHEET Calcutation Number Revision Number Page Number E9004-0O5 0 l Page 8 of /0
-Subjes CV Yard Survey Design - North West Side of CV 6.5 Attachment 5-1 and 5-2, is the MDC ari calculation sheets.-
6.6 Attachment 6-1 to 6-5, are static point locations calculated using the VSP computer code.
6.7 Attachment 66, is the sample -point locations with coordinates from the CV shell.
6.8 Attachment 7-1 to 7-4, is the results of the inspection reports from the OL1-2 survey area.
Attachment 7-5, is the efficiency correction factor employed for a GFPC -instrument as a result of the-4nspection results.
Attachment 8-1, is the soil variability results for selected soil samples from the OLI area.
Attachment 9-1, is the concrete surface variability measurements from MA8 concrete sections.
Attachment 10-1, is the Williamsburg GFPC background measurements.
6.13 Attachment 11-Ito 1-4, is the Compass output forthe OL-2 soil survey unit (Nal).
6.14 Attachment 12-1 to 12-, is the Compass output for the MAB concrete survey unit (GFPC).
SNEC CALCULATION SHEET - ;.
Calculation Number Revision Number Page Number E90040)05 0 Page 9 of 10 Subject CV Yard Survey Design - North West Side of CV Exhibit I SNEC Facility Individual Radionuclide DCGL Values (a) 25 mremly Limit 4 mremly Goal 25 mremly Limit (All Pathways) (Drinking Water)
Radionuclide Surface Area Open Land Areas Open Land Areas (b)
(dpm/1OOcm 2 ) (Surface & Subsurface) (Surface & Subsurface)
(pCUg) (pCUg)
Am-241 2.7E+01 9.9 2.3 C-14 3.7E+06 2 5.4 Co-60 7.1E+03 3.5 67 Cs-137 2.8E+04 6.6 397 Eu-152 1.3E+04 10.1 1440 H-3 1.2E+08 132 31.1 Ni-63 1.8E+06 747 1.9E+04 Pu-238 3.OE+01 1.8 0.41 Pu-239 2.8E+01 1;6 0.37 Pu-241 8.8E+02 86 19.8 Sr-90 8.7E+03 1.2 0.61 NOTES:
(a)While drinking water DCGLs will be used by SNEC to meet the drinking water 4 mrem/y goal, only the DCGL values that constitute the 25 mrem/y regulatory limnit will be controlled under this LTP and the NRC's approving license amendment (b) Usted values are from the subsurface model. -These values are the most consevative values between the two models (i.e.,
surface & subsurface).
SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E9004"005 0 Page 10 of 10 Subject CV Yard Survey Design - North West Side of CV Exhibit 2 Survey Desion Checklist Calculation No. Location Codes E900-04-005 O11-2 & MA81 iSta REus Reviewer (Circle One) In is &LDate
_ Has a survey design calculation number been assigned and is a survey design summary (
description provided? 2L.J 2 Are drawings/diagrams adequate for the subject area (drawings should have compass headings)? (e /
3 Are boundaries properly Identified and is the survey area classification clearty Indicated? es. N/A o 4 Has the survey area(s) been properly divided into survey units IAW EXHIBIT 10 es.) N/A/ /
6 Are physical characteristics of the areallocation or system documented? es, N/A S Isa remedlation effectiveness discussion induded? Fes) N/A 7 Have characterization survey and/or sampling results been converted to units that are N/A N4 A comparable to applicable DCGL values?
a Is survey and/or sampling data that was used for determining survey unit variance Induded?
8 Is a description of the background reference areas (or materials) and their survey and/or sampling results Included along with a lustification for their selection?
) N/A N/A 10 Are applicable survey and/or sampling data that was used to determine variability Induded? es) N/A I Will the condition of the survey area have an impact on the survey design, and has the probable impact been considered inthe design?
m, ib
/A 1/41 Has any special area characteristic induding any additional residual radioactivity (not 12 previously noted during characterization) been identified along with its impact on survey Ye N/A 13 Are all necessary supporting calculations and/or site procedures referenced or Induded? ibl /A A 14 Has an effective DCGLw been Identified for the survey unit(s)? 1'7eDs N/
15 Was the appropriate DCGLuc Included In the survey design calculation? N/A/
16 . Has the statistical tests that will be used to evaluate the data been identified? es, A 17 Has an elevated measurement comparison been performed (Class 1 Area)? A 18 Has the decision error levels been identified and are the necessary justifications provided? s)N/A V S 19 Has scan Instrumentation been identified along with the assigned scanning methodology? N/AL 20 Has the scan rate been identified, and Isthe MDCscan adequate for the survey design? Nes) N/A 4 /0 Xi Are special measurements e.g.. in-situ gamma-ray spectroscopy required under this design. Yes, N/
and Is the survey methodology, and evaluation methods described?
22 Issurvey Instrumentation calibration data Included and are detection sensitivities adequate? 6 ) NIA ib/
23 Have the assigned sample and/or measurement locations been clearly identified on a diagram m to/ I or CAD drawing of the survey area(s) along with their coordinates? (Yes),N6A
_ Are Investigation levels and administrative limits adequate, and are any associated actions e N/A clearly Indicated?(e N/
25 For sample analysis, have the required MDA values been determined.?Y N/A 26 Has any special sampling methodology been identified other than provided in Reference 6.3? YesNA NOTE: a copy of this completed form or equivalent, shall be included within the survey design calculation. ki
SNEC CV YARD AREA EXCAVATION Well
. e - Grade t
Toe of Elevation Change Ii
-161 Square Meters I,I*
4l Access Road
.4 . 6- I
- qM f . -
- 5 . . I I
,..I I Concrete Spoils Area
-26 Sawaro Meters U
C,
. Concrtet
-148 Square Meters , I _
4 I
4 I . .4I-MIec. Concrete AI.I __. :; :4 4.
/
CV Yard Area Misc Concrete A
-13.4 Square Meters 8we s Top VW FiO Maw rSitsA
{
I ATTACHMENT 1- 2.
CV Yard Concrete B lI -O,.Aqmm1rp Matorc Front View Grade (-811' El)
Side View Extended Side View Under Edge Sections ATTACHMENT .1 .3S
DCGL Calculation Logic-CV Yard Soil & Boulders Survey "nit: SNEC Containment Vessel (CV) Yard Soil and Boulders II.
Description:
The purpose of this calculation is to determine a representative isotopic mix for the CV Yard Soil and associated Boulders from available sample analyses. The effective volumetric DCGLWs are then determined from the mean percent of applicable samples.-- -
Ill. Data Selection Logic Tables: The radionuclide selection logic and subsequent DCGL calculations are provided in six (6) tables. These tables were developed using Microsoft Excel. Table explanation is as follows.
Table 1: Data Listing - This table, which has been extracted from a larger database, provides a list of the most representative sample analyses. Results are from scoping, characterization, and prelpost remediation surveys. The samples consist of soil media that was taken in.support of the aforementioned surveys. As applicable, a sample number, sample location/description, radionuclide concentration, analysis date are provided for each sample. Positive nuclide concentrations are noted with yellowishaded background fields while MDA values are noted in the gray shaded fields.
Table 2: Decayed Listing - This table decays the data from Table 1. Half-life values (days) are listed above each respective nuclide column. Samples are decayed from the respective analysis date to January 15, 2004. Positive results are denoted in a yellow background field while MDA values are noted in the gray shaded fields.
Table 3: Decayed Listing of Positive Nuclides & MDAs Removed - This table provides the best overall representation of the data. Non-positive nuclide columns have been removed as well as all the MDA values. Therefore, 11 nuclides have been reduced to four (4).
Table 4: Ratio to Cs-1 37 for Positive Nuclides - This table provides the calculation methodology for determining the surrogate ratio to Cs-137 for each radionuclide. From this information the mean, sigma, and mean % of total are calculated. The mean % of total values is used to calculate fe volumetric DCGLW per MARSSIM equation 1-14. See Table 5. Note that the mean percent values were averaged using only the positive sample results in each column. In some cases only a single nuclide value (e.g. Sr-90) had a positive result This value is listed as the value in the mean result field. This results in higher "mean percent of totar values in the mix, which are conservative.
Note: From Table 4 only the "mean % of total" values are used as input to the "Effective DCGL Calculation Spreadsheet" as Illustrated in Table 5.
Table 5: Effective DCGL Calculator for Cs-1 37 (in pCi/g) - This table provides the surrogate volume)4c modified Cs-137 DCGL, calculation results from data derived from Table 4.
IV. Summary - Since the CV Yard and Boulders are volumes of soil or rock material, existing in place or in a -pile, the release limit is pimarily based on the volumetric DCGLW. Using the above data selection logic tables the calculated Cs-137 volumetric DCGLW is 5.73 pCilg. This value will be reduced by 25% as part of SNEC's requirement to apply an administrative limit as discussed in the Ucense Termination PlanLTP).
1 ~~AlTACH lV -
TABLE I ~ L#4sinI qpCiial 1, -- ,4 'Z-j- ' rC- Is.
-ig3kc-00 I 4!K.Oo I I WIDI i
ILS-I ~I-~.I51t42 3II ¶1 02)1.2 4So.02 *?112 t -1TIF-6 I )la-" !
li j. lZ_ j uI, ~~I 174, 1 W iE 10,1M +0 RW 1 6 IA 1.340.3 p2 :
Sfa.i.E;llI. 1 - 2 ~ 0 44 1000-s s-re
- Ll l , ~ titj1.,&WIklj I l .t#e 60t I 12 062
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40.01r-11OW300 2430.00~ 500.E0
_ _ _ b_ I _ I_ _ _ _ i _ _
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CV YARD SOIL BOULDERS I TABLE 3 - RElDUCED LFSTING - DECAYE0 -.UDAD REUMOVD fficxet Oi-1371 mpw
- SSECS mew LvEi Xo. Io~aDs .13 C1-0
-l a ar 1g oe ~l
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- 1. 8. 59E41 03 11785.3 2 SX5SL0}3I1 I 1074 :,5u17 E111714#23In. AY-129, - ' F1 7 5, 3 5S0w15 c .. ic. 1 27 t1ZE, fltmpl *5, 01 5 05 4 5XSLOii5 OICVY55 8c5AY.127,510 EL,hple. 53 27iE+OC W0 4C2 5 sXSL1115 5,CVY5.1 54i AY.12I AM ELSfto l2 52' 7i 78 SXSI.123 26,42 01 5 23 0 SXSL27C 2.52 10 tXSL1281
- 4. 01. 4 74 11 SXSL24 A 0.5s 13 SXSL3571 A c552 14 S.XL2 02.
5512 151 6XSL342 Li1 0 is DO7 17 SXSI_3S45 122 4 0 2t 022 22 ss44 0.50 23 SXSL4!Ag T.W*I4 L22513T4 CVYwt $01.\ 6.74E42 I0.r lI_ TABLE 4 -% OF TOTAL CALCULATION _
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&Bould
CVYARD SOIL WOULRS I TABLE 5 - RAT1O TO Ce417 I
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Table 5
[ EC AmLe7 Totl
- W*"JJLM#tDCLw I dn~ar~ ie Effectjve DCGL AAi 1I-LF for Cs.137 (In pCUI) .. 16. Jpii 1 27 p ,'
_ La! n SAMPLE NUMBER(s)*CV YARD SOIL& EJOULDER SAMPLES . I I ' a----It 1 1 m~mitz:e u 17.45% 25.0 mremy TE°E Limit I 5tt IP- 3s 4.30 lvIg Ip>CI I t7 7O An fl..&ni.nz 3djtr. Itwl I imi.
Sample Input (pCifg. uCi, % 26 mremly TEDE 4 mremly DW A - Allowed pCIfg for B - Allowed pCijg Value Checked from This Sample This Sample Isotope of Total, etc.) % of Tota Lmts (pCIg) Limits (pCi g) 26 mremly TEDE for 4 mrem?' OW Column A or B mrem/v TEDE mremty DW I Am-241 0 000% 9.9 2.3 0.00 0.00 0 00 0.00 0.00 Am-241 2 C-14 0.000% 2.0 5.4 0.00 0 00 0 00 000 0 00 C-14 3 Co.60 0.0064 0.216% 3.5 67.0 0 04 0.08 0 04 0.06 0 00 Co-60 4 Cs-137 1.0000 33.738% 6.6 397 6.73 12 83 .7 Ew- 3.79 001 Cs-137 6 Eu-152 0 000% 10.1 1440 0.00 0 00 0 00 0.00 0 00 Eu-152 6 H.3 1.9499 65.786 13i 31.1 117 25 02 11.17 037 0 25 1H-3 7 Ni.63 0000% 747 19000 0.00 0 00 0.00 0.00 0.00 Ni.63 I Pu-238 0.000% 1.8 0.41 0.00 0 00 0.00 000 000 0 Pu-238 Pu-239 0.000% 1.6 0.37 000 000 0.00 0.00 0 00 Pu-239 10 Pu-241 0 0000% 86 19.8 000 000 0.00 0 00 0 00 - Pu.241 11 Sr-90 0.0077 0.260% 1.2 0.61 0.04 q10
. 0.04 0 16 0.05 Sr-90 2.9E00 I lOO.OOOX 16.98 38.03 16.98 i 4.364 1 0.312
'I
?':: - ' '.. ~'
. -t S iL.-1: TA flij VIl To Use This Information.
pCIlg Sample Input UnIts Mwust Be In (25 mrsmry) (4 mremly) *1 C
I I PCI11g not liofTotal, 4
CO v
Effective DCGL Calculator for Cs-137 (dpm/100 cmA2) 44434 dpml1OO cmra2 33325 Idpml100 cmA2 m 2 rnmrem/y TEDE Limit SAMPLE NOsp FV YAk4 S'b-, 6 aduih UlFRPAMPL izF 2644! ldpml10O cm^2 19834 ldpm/1GO cm-2 7 57 I Sample Input Individual Lrnits Allowed dpml100 Beta dpm/100 Alpha dpm/100 Isotope Ipcitg, UCI, tetc) % of Total (dpml100 cmA2) cm12 mromly TEDE cm^2 cmrA2 1 Am-241 °_ 00_ 27 0 00 0.00 WA OM Am-241 2 C-14 0 000% 3,700,000 0 00 0 00 O00 WA C-14 3 Co-60 2SE OV 0.443% 7,100 196.87 0.69 196.87 WA Co-80 5 Eu-152 0 000% 13,000 0 00 0 00 0.00 WA Eu-152 6 H-3 s tE 1 39 500% 120,000,000 17551.45 000 Not Detectable WA H-3 7 Ni-63 0.000% 1,800,000 o.0G 0 00 Not Detectable WA NI-63 a Pu 238 _ __0% 30 0.00 0.00 WA 0.00 Pu-238 s Pu-239 _ _ _ _% O2 000 0.00 WA 0.00 Pu-239 10 Pu-241 0000% 880 0.00 0.00 Not Detectable WA Pu-241 ii Sr-90 '64E -OJ 0 542% 8,700 240.75 0.69 240 75 WA Sr-s9O 100 000% 44434 25.0 26882 0 Maximum petm:.-.ble dpmnOOPCm'l*Z I
Cog-
ORIGINAL LUDLUM MODEL 44-10 HIGH VOLTAGE PLATEAU DATA SHEET Serial Number: 196022 HIGH VOLTAGE SOURCE (10 second count) 705 17,537 706 21,507 707 24,743 708 25,998 709 27,826 710 (SET) 28,245 711 28,040 712 26,415 713 25,339 714 22,792 Detector plateau performed using Cs137 #019454 SuCi nominal value button source
___Detector Parameters for Peaking Parameter Setting Setting Threshold (10mV/1 00) 642 612 Window (On) 40 100 High Voltage 710 710 CPM/mRIHr 122,572 208,705 Background CPM 27 63 CPMlmR/lr conversion performed using Cs137 #049711 Certification Date: 04109103 FWHM values performed with CsI 37 #019454 (Threshold = 642 and Window = 40)
FWHM= 679 - 596 11.5%
662 xlO00%________________ ____
Detector peaked for Cs'3 using Ludlum peaking procedure and threshold setting of 642 and window setting of 40. As left threshold setting is 612 and window at 100 as requested by John Duskin. 2350-1 #126172 calibration due 04106105 used for peaking 44-10 detector.
Performed By: "U, 11-P=L Date: 4 l L9 10ifW Reviewed By: - ( Date: e- Go- of ATTACHMENT- .,I
MicroShield v5.05 (5.05-00121)
GPU Nuclear
'age :1 File Ref:
)OS File: SOIL.MS5 Date:
Run Date: April 19, 2004 By:
Run Time: 11:22:42 AM Checked:
)uration : 00:00:01 Case
Title:
Soil
Description:
Soil Density 1.6 glcc, B" Cylinder @ 5" from Surfice Y Geometry: 8 - Cylinder Volume - End Shields Source Dimensions Height 15.24 cm 6.0 in Radius 28.21 cm 11.1 in Dose Points X Y z
- 1 O cn 1 27.94 cm 0 cm 0.0ifI 11.0 in 0.0 in Shields Shield Name Dimension Material Density Source 2325.091 in3 Concrete 1.6 Air Gap Air 0.00122 Source Input Grouping Method: Actual Photon Energies Nuclide curies m3 uecierels w Ba/CM 3 Ba-137m 5.7670e-008 2.1338e+003 1.5136e-006 5.6003e-002 Cs-1 37 6.0962e-008 2.2556e+003 1.6000e-006 5.9200e-002 Buildup The material reference is : Source Integration Parameters Radial 40 Circumferential 40 Y Direction (axial) 40 Results Eneray Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/CM2 /sec mR/hr mR/hr No Buildup With BuilduR No Buildup With Buildup 0.0318 4.418e+01 6.794e-06 8.222e-06 5.659e-08 6.849e-08 0.0322 8.150e+01 1.306e-05 1.591e-05 1.051e-07 1.280e-07 0.0364 2.966e+01 7.236e-06 9.448e-06 4.1 1e-08 5.368e-08 0.6616 1.920e+03 6.17ge-02 1.091e-01 1.198e-04 2.115e-04 TOTALS: 2.075e+03 6.182e-02 1.091e-01 1.200e-04 2.1 18e-04 AT1TACHMENT.q-.--
Nal Scan MDC Calculaion- CV Soil.mcd Nal Scan MDC Calculation b := 200 p := 0.5 HS d := 56.42 SR:= 25 d := 138 Conv := 208.705 -4 MSoutput := 2.151 HS d
- = 2.257 ObservationInteival (veconds)
SR HSd ObservationInterval (seconds)
' b60 i @ SR bi := )0 MDCRi:=Id-jb 7 O MDCR - = 100.629 net counts per mintute MDCR; MDCR survcyor r Al MDCR MDCRS..... 6~ = 142.31 i urveo net counts per minute MDCR surveyor MDER :
Colnv MDER = 0.682. gR/h MDER MDC scan := 3 Ms output' -1 0 MDC san = 3.224 pCi/g A119r2004 4 of 5 ATrACHMENT -* -
Nal Scan MDC Calculation- CV Soil.mcd where:
h background in counts per minute hi background counts in observation imnerval Conv = Nal mnaiwfacturersrtported1 response to energy ofcontaminant (cpnlutR/h1) d = inder o/sensitivity (7fia6e 6.3 AARS.Sl1Jf 1.38 = 95% ofcorrect derection's 60%falsc positiveS H.Sd = hot spot diameter (in centinwtersj IA1IDC1 ,, Minimum Detectable Concentrarionforscanning (pCi/g)
,iIDCR, Minimun Delecable Cournt Rate (ncpm)
.iiiDCRjj,",,r= AIDCR, corrected Iky Inunwn performancefactor (ncpmn)
.IDER = Afininiu Detectabl E rposure Role (4R/h1)
V.lo,,,,, = AlicroShicil outpur exsure rawtefor I pCilg ofcontiaminant(mRfh)
Ct = obenration Intrcnal .seconds) p = human perfonnancefactor SR = .scan rate in centimreterspersecond 5of 5 ATTACHMENT. .5 .. k -
SNEC CV YARD AREA EXCAVATION
+ Well Grade Toe of Elevation Change Acces! s Road Concrete Spoils Area
-:6 Scuare Meters I/
I ATrACHMENT *_I
NN I
(0, 0)
XT CHNME T A
CV YARD CONCRETE SPOILS AREA 4
.A o 2
-. m 3
286" 9/1 LINE TO WELL 200 204' /
CV SHELL I
ATTACHMEN E .-
CV Yard Concrete Misc A 7 B Inside Back Top 61 6
eft Inside I I
-1 2
Front
_ . 1 eft Outside J 4:6,
_. . -..t .1. .
.. . I I
Inside Front
16" CV Yard Concrete Misc B De
.I
... I i I1 II1 .
.. d I Left Side -'
- N., _ S
.....-. 1 Over Hang ATTACHMENT -
POINTS AND LOCATIONS Letter Point No. Angle From (0,0) (in Degrees) Inches Along CV Curvature A 2 4.00 21 B 4 18.00 94 C 6 34.90 183 D 9 51.30 269 E 10 65.70 344 F 14 79.30 415 G 15 95.30 499 H 32 99.20 519
Exhibit 1 VZSUVEY~fTINSECTION ZSSUnCTIt InseUNITICch DESCRIPTION, '
SurveyUnit OLI-2 SurveyUnitLocation SNEC Facility Site - Excavation Soils SuvyUI
- I12SrvyUi Surrounding CV Date 4/19104 Time 1400 Inspection Team Members D.Sarge
-SECTION 2 - SURVEY UNIT INSPECTION SCOPE' Inspection Requirements (Check the appropriate Yes/No answer.) Yes No N/A
- 1. Have sufficient surveys (I.e., post remedlation, characterization, etc.) been obtained for the survey unit? X
- 2. Do the surveys (from Question 1)demonstrate that the survey unit will most likely pass the FSS? X
- 3. Isthe physical work (I.e.. remediation & housekeeping) In or around the survey unit complete? X
- 4. Have all tools, non-permanent equipment, and material not needed to perform the FSS been removed? X
- 5. Are the survey surfaces relatively free of loose debris (O.e., dIrt, concrete dust, metal filings, etc.)? X
- 6. Are the survey surfaces relatively free of liquids (i.e.. water, moisture, oil, etc.)? X
- 7. Are the survey surfaces free of all paint, which has the potential to shield radiation? X
- 8. Have the Surface Measurement Test Areas (SMTA) been established? (Refer to Exhibit 2 for instructions.) X
- 9. Have the Surface Measurement Test Areas (SMTA) data been collected? (Refer to Exhibit 2 for Instructions.) X
- 10. Are the survey surfaces easily accessible? (No scaffolding, high reach. etc. is needed to perform the FSS) X
- 11. Is lighting adequate to perform the FSS? X
- 12. Isthe area Industrially safe to perform the FSS? (Evaluate potential falf& trip hazards, confined spaces, etc.) X
- 13. Have photographs been taken showing the overall condition of the area? X
- 14. Have all unsatisfactory conditions been resolved? I X NOTE: If a 'No answer is obtained above, the Inspector should Immediately correct the problem or initiate corrective actions through the responsible site department as applicable. Document actions taken andlorjustifications inthe Comments section below. Attach additional sheets as necessary.
Comments:
Response to Question #3 - Rernediation is still underway in adjacent areas (CV Steam Pipe Tunnel, MHB excavation).
Response to Question #4 - Miscellaneous debris, equipment in area needs to be removed prior to survey.
Response to Question #10 - Survey/sampling of the sloped soils will require the aid on scaffolding or similar apparatus.
Survey Unit Inspector (print/sign) D. Sarge / jf Date 4/19/04 Survey Designer (print/sign) /3 l Date A1TACHMENT.~-'-l-
EXHIBIT3 Surface Measurement Test Area (SMTA) Data Sheet F- _ECTIO 1 -_DESCRIPTION *. .
SMTA Number MA8-1 (Concrete Pad) Survey Unit Number l MA8-1 SMTA Location CV Excavation Area - North of shell (approx. 803' el.)
Survey Unit Inspector D. Sarge I Date 4/19/04 Time 1420 SECTION 2 - CALIPER INFORMATION & PERSONNEL INVOLVED Caliper Manufacturer Mitotoyo Caliper Model Number CD-6 CS Caliper Serial Number 763893 Calibration Due Date (as applicable) N/A RadConTechnician I D.Sarge l Date 4/19/04 Time 1420 Survey Unit Inspector Approval D Date ¶LI/'
SECTION 3-MEASUREMENT RESULTS SMTA Grid Map & Measurement Results in Units of mm Comments (Insert Results in White Blocks Below) 1 7 13 19 25 31
- Concrete Pad has rough unfinished top surface.
15 12- 94 7.9 7.7
- Areas of pad are crumbling due to construction 2 8 14 20 26 32 equipment traffic.
11.4 141 9.8 8.8 7.5 8.6
- The top surface has similar topical 3 9 15 21 27 33 characteristics.
8.2 16.9 23.2 10.5 14.9 10.7 4 10 1s 22 28 34 8.8 9.6 9.3 10.8 5.1 11.8 6 1 17 23 29 35 7.8 10 13.9 5.4 9.4 11.9 6 12 1i 24 30 36 7.12 11.9 8.8 10.4 12.6 8.1 Average Measurement - 10.6 mm Additional Measurements Required iC,,4MEW r~1Al Z,
EXHIBIT 3 Surface Measurement Test Area (SMTA) Data Sheet SECTION ?i-- =
, w ., . , _ .
SMTANumber MA81 (VentilationPad) Survey Unit Number MA8-1 SMTA Location CV Excavation Area - West of shell (approx. 807' el.)
Survey Unit Inspector D. Sarge I Date 4/19/04 Time 1400 ECTIO5ECTlON 2 -CAUPERiNFORMATION s PESONNNE_ d-= u Caliper Manufacturer l Mitotoyo Caliper Model Number CD-6 CS Caliper Serial Number 763893 Calibration Due Date (as applicable) NIA RadConTechnician I D.Sarge/ l4119/04 Date 1410 SurveyUnkinspectorApproval I -D S7)C ip Date i
-_.- --j '- E - C*, -M- . A.SUR-EM1ET TtS I3 -IEMUREMENT-"T-,U SMTA Grid Map &Measurement Results in Units of mm (Insert Results in White Blocks Below) Comments 1 7 13 19 25 31
- Concrete structure has jagged top surfaces due 1.22 94 0.42 6.72 0.63 09 to previous remediation activities. Ranges of depth between 30 - 72 mm..
2 8 14 20 26 32
- Some of the structure is obstructed by soil 6.05 1.23 2.65 0.62 4.1 0.94 (slope).
3 s 21 27 33
- The exposed surfaces have similar topical 8.t 28 221 0.25 0.72 0.96 characteristics.
4 10 16 22 28 34 3.5 4.3 1.9 1.75 35 0.35 5 1i 17 23 29 36 1.3 3.72 682 0.87 022 0.45 6 12 18 24 30 36 0.32 053 0 16 0.24 051 081 Average Measurement - 2.26 mm Additional Measurements Required A1TACHMENTN--l 3
V ORIGINAL EXHIBIT 3 Surface Measurement '.est Area (SMTA) Data Sheet SECTIONC 1- DESCRIPTION.
SMTA Number MA8-1(Train Track Support) Survey Unit Number MA8-1 SMTA Location CV Excavation Area - West of shell (approx. 807' el.)
Survey Unit Inspector l D. Sarge l Date 4/19104 -Time 1410 SECTION 2- CALIPER INFORMATION & PERSONNEL INVOLVED Caliper Manufacturer Mitotoyo Caliper Model Number CD-6-CS Caliper Serial Number 763893 Calibration Due Date (as applicable) N/A Rad Con Technician [D. Sarge I gV I Date 4/19104 Time 1410 Survey Unit Inspector Approval P. ll Date
- ; - . . SECTION 3 MEASUREMENT RESULTS SMTA Grid Map & Measurement Results in Units of mm Comments (Insert Results in White Blocks Below) Comments
'. 7
- 13 . 25 31
- Concrete structure has jagged surfaces due to 97 previous chipping activities. Ranges of depth
.7 4.23 11.25 9.37 35.56 15.71 between 30 - 55 mm.
2U14 20 26 32
- SMTA taken on jagged surface and is 27.3 8.24 25.22 11.67 15.85 12.36 representative of most of the surfaces.
- 9. 15 21 27 .33
- Some of the structure is obstructed by soil 5.89 10.3 13.7 9.25 18.36 11.86 (slope).
- -.. 1 6: 22 28 - 4s34.
- The exposed surfaces have similar topical 9.36 6.6 23.09 127 7.92 13.7 characteristics.
> 5 7s . 23 f %35 3.6 13.9 34.C0 25.17 13.27 20.64
-Sxt -wv.-2~f- -. .°42^a~
7.4 6.0 19.1 20.71 33.37 28.74 Average Measurement -15.4 mm Additional Measurements Required ATTACHMEW-
W Effi- Loss,with is Cs-I 37 Efficiency Loss with Distance From Source 1.0 0
V I-U-
0.6 C:
V w 0.4 0.2 0.0 0.5 1.0 1.5 2.0 2.5 3.0 Inches from 150 cm2 Source ATTACHMENTEh
UL1-1 POST RKEIILEDATION SAMPLES OL1-1 POST REMEDLATION SAMPLES OL1-1 POST REM EDIATION SAMPLES Onsit analysis Onsitt analysis, with additlonal samples Onsita analysis. wilt even mom samples Samole Number Grid C-137 pCllb Sample NtrmberGfrd Cs-137 pCUq Sample Number Grid Cs-137 oCEo SX-SiL-1Z1 AX-128 4.5 SX-SL-1281 AX-128 45 SX-SL-1281 AX-1i28 4.5 SX-SL-1282 AX-128 0.94 SX-SL-1282 AX.128 0.94 SX-SL-1282 AX-128 0 94 SX-SL-1283 AX-128 3 SX-SL-1283 AX-128 3 SX-SL-1283 AX-12a 3 SX-SL-1284 AX-128 1.4 SX-SL-1284 AX-125 I ' SX-SL-1234 AX-128 14 SX-SL-4078 AX-128 0.9 SX.SL-4076 AX.128 09 SX-SL-4076 AX.128 09 SX-SL-4073 AX-128 0.0t7 I SX-SL.4135 APt-l O 06 SX-SL.4135 APt-I 006 SX-SL-1.28t AX-128 1.5 2 SX-SL-4136 :A . 011 SX-SL-4136 AP1?-2 10 I SX-SL-1225 AX-130 0.48 3SX-SL4137 1API-3 0.17 SX-SL*4137 API-3 0 1t SX-SL-1229 AX-130 0.15 4 SX-SL-4138 tAPI-4 0.16 SX-SL-t138 API.4 0 16 1SX-SL1230 AX-130 3.7 5 SX-SL-4133 IAP.5 10o0 SX-SL-4133 AP1.S 0.06 SX-SL-1231 AX-130 0.49 d SX-SL-4134 AP1.0 Io0 s SX.SL-4134 AP7.u 0.05 SX-SL-1232 AX-130 1.25 7SX-SL.4139 API- 008 SX-SL-4139 APt.7 0.06 SX-SL-1128 AZ-130 0.38 8 SX-SL-t440 IAP1- 005 SX-SL-4140 API-b 09o SX-SL-1127 AZ-130 0.64 9 SX SL.4141 IUP19 ace SX-SL-4141 AP-I9 a06 SX-SL-1128 AZ-130 0.22 10 SX-SL-4142 lAP-1-0 0 SX-SL-L142 API-10 09 SX-SL-1132 AZ-130 2 11 SX-SL-1143 APJllt 05 SX-SL-4 t43 API-11 0 5 SX-SL-1104 AZ-129 o0.08 12 SX-SL-4149 AP1-12 39 SX-SL 1149 APIt 12 13S SX-SL-1I05 AZ-129 0.34 13 SX-SL-1150 API13 005 SX-SL-41M0 API.13 0.00 SX-SL-110 AZ-129 0.78 14 SX.SL-4152 JAPI-14 006 SX-SL-41523 l^Pt-14 00e SX-SL-1 107 AZ-129 0.25 SX-SL-4073 AX-12B 0 07 SX45L 4,1S3 0 05 SX-SL-1108 AZ-129 028 SX.SL.12B5 AX-128 I 5 2SX SL-4154 005 SX-SL-1099 AZ-128 1.2 SX-SR-1228 AX-130 0 48 3 SX-SL-4158 I 006 SX-SL-1100 AZ-128 0.12 SX-SL-1229 AX-130 0 15 4 SX-SL-4156 0.14 SX-SL-1101 AZ-128 Q07~ SX.SL-11230 AX-i3O 37 5 SX-SL-4157 0J03 SX-SL-1102 AZ-128 0.2 SX-SL-1231 AX-130 0.49 I6 SX-SL-4160 006 SX-SL-1103 AZ-128 0.23 SX-SL-IZ32 AX-130 1 25 7 SX-SL-4.18t jC SX-SL-1075 AX-127 0.23 SX-SL-l 178 AZ-130 0.38 I8 SX-SL.4 Iz 0805 SX-SL-1078 AX-127 0.16 SX-SL-1 127 A2-130 0 04 i 5X-4L-4 I 59 B 0 08 SX-SL-1077 AX-127 0.7 SX-S-.I 128 AZ-130 022 IIS 3X-SL-4164 4-SX-SL-1078 AX-127 0.13 SX-SL-1132 AZ-130 2 I 1 sX-SL.475 -
SX-SL-1079 AX-127 0.13 SX-SL-1 IG04 AZ-129 ~08 0
SX-SL-4073 AX-12B 0 07 SX-SL-1087 AY-127 0.08 SX.SL-1105 AZ-129 0 34 SX-SL-1285 AX-128 15 SX-SL-1088 AY-t7 0.07 SX-SL-1 IIC AZ-129 0.78 SX-SL-1228 AX.130 048 SX-SL-1089 AY-127 0.05 SX-SL- 107 AZ-129 025 SX-SL-1229 AX-130 0.15 SX-SL-1090 AY-127 0 08 SX-SL-1 10a AZ-120 0 28 SX-SL-1230 AX-130 37 SX-SL-1091 AY-127 0 07 SX-SL-1099 AZ.128 1.2 SX-S*L-1231 AX-130 0 49 SX-SL-1027 AZ-127 0 35 SX.SL.1 100 AZ-128 0.12 SX-SL-1232 AX-130 1.25 SX-SL-1028 AZ-127 0.57 SX-SL.I101 AZ-128 ~07 O SX-SL-1128 AZ-130 0 56 SX-SL-1029 AZ-127 0.5 SX SL- 1102 AZ-128 02 SX-SL-1127 AZ-130 O C4 SX-SL-1030 AZ-127 045 SX-SL-1 103 AZ-12B 0.23 SX-SL I I28 AZ-130 0 22 SX-SL-1031 AZ-127 0.7 SX-SL-1075 AX-127 0 23 SX-SL-1132 AZ-13G 2 SX-SL-1233 AY-130 0.14 SX-SL-1076 AX-127 0.16 SX-SL-1104 AZ-129 F0.08 SX-SL-1234 AY-130 0.8 SX-SL 1077 AX-127 07 SX-SL-1t05 AZ-129 34 SX-SL-1235 AY-130 1.3 SX-SL-1078 AX.127 0 13 SX-SL-I1C6 AZ-.29 0 78 SX-SL-1121 AY-129 0.035 SX.SL-1079 AX-127 0.13 SX-SL-1107 AZ-129 0.25 SX-SL-1122 AY-129 4.3 SX-SL-1087 AY-127 0.08 SX-SL-t 1CB AZ-129 0 28 SX-SL-1221 AY-128 0.17 SX-SL-1088 AY-127 0 07 SX.SL-.099 AZ-128 12 SX-SL-.1 AY-128 1.1 SX-SL-1089 AY-127 0.0 SX-SL-1100 AZ-128 012 SX-SL-1223 AY-128 2.1 SX-SL-IC 90 AY-127 0.08 SX-SL-1101 AZ-128 0 07 SX-SL-1224 AY-128 2 SX-SL- 191 AY-127 0.07 SX-SL-' 102 AZ-128 02 SX-SL-1225 AY-128 1.75 SX-SL-1027 AZ-127 0 35 SX-SL-t 103 AZ-128 0 23 SX-SL-4083 AX-129 0.3 SX.SL-1020 AZ.127 0 57 SX-SL.1075 AX-:27 0.23 SX-SL-4082 AX-129 0.14 SX-SL-1029 AZ-i27 05 SX-SL-1076 AX-127 0 10 SX-SL-1030 AZ-127 045 SX-SL-1077 AX-127 07 SX-SL-1031 AZ-127 07 SX-SL-107B AX.1?7 0 13 Avg 02 STDEV 10 SX-SL-1233 AY-130 0.14 SX-SL-1079 AX-127 0.13 SX-SL-1087 AY-127 00 -:
ODenotos MADA I SX-SL-t234 AY.130 06 SX-SL-1235 AY-1Z0 13 SX-SL-1088 AY-1Z7 0 07 SX-SL-t 121 AY-1Z9 0 035 5X-SL-t089 AY-127 0.05 - .
SX-SL-1 122 AY-129 4.3 SX-SL- lO5 AY-127 0.06 SX-SL-1221 AY-12B 0 17 SX-31-I0131 AY-127 0.07 SX-SL-1222 AY-128 I I SX-SL-1027 AZ-127 0 35 SX-SL 3 AY-128 21 SX-SL-1028 AZ-127 0 57 SX-SL-1224 AY-128 2 SX-SL- 10-9 AZ-127 05 SX-SL-1223 AY-S2S 1.75 SX-SL-1030 A7-127 0 45 SX-SL-4083 AX-129 03 SX-SL-tC31 'Z-127 07 SX-SL-4082 AX-129 0.14 SX-SL-1233 AY-130 0 14 Max 4 50 SX-SL-1234 AY-13S 0.6 Avg I0 7a SX-SL-1235 AY-130 13 STDEV I105 SX-SL-I 121 AY-129 0.035 Denotes .c DADA l. SX-SL-1 122 AY-129 4.3 SX-SL-1221 AY-:28 0 17 SX-SL-1222 AY-128 11 SX-SL-1223 AY-128 21 SX-.SL- 1274 AY.t28 2 SX-SL- 1225 AY-:20 I 75 SX-SL-4A83 AX.12g 03 SX-SL-082 AX.129 0 14 Max 4 50 Avg 0 STOEV I CO ATACHMENT . 12i Denotes MDA I
j/At+64L llt WC0 . Y, O -DfS-b VERSION IS 3t122N21 MODEL 2350 SOFTWARE IS 126179 NUM3BER MODEL 2350' SERIAL COUNT MODE STATUS TIME DET COUNT DATE TIME SAMPLE LOCATION SCL 0 01 3.021000e+03 600 0 BKG CK 04/19/04 05:53 1.652170e+05 60 SCL 0
SC CK 04/19/04 06:10 01 60 SCL 0 1 04/19/04 13:16 61 v2,.840000e+02 SCL 0 2 CVEXC FP1S 13:17 01 2.390000e*02 60 SCL .0 CVEXC Ui*Pi )04/19/04 01 Y2.630000e+02 60 3 04/19/04 13:19 Vd.380000e+02 60 SCL 0 4 CVEXC FP2S 13:20 01 SCL 5 CVEXC FP2U 04/19/04 13.: 21 01 ;2.580000e+02 s0 SCL 0
CVEXC PP3S 04/19/04 01 v3.960000e+02 60 0 6
CVEXC FP3U 04/19/04 13:22 ,2.990000ei02 60 SCL 0 7 13:24 01 SCL CVEXC FP4S 04/19/04 01 /3.800000e+02 60 0 B
9 CVEXC FP4U CVEXC FPSS 04/19/04 13:27 04/19/04 13:29 01 01
? .780000e+02 3 .770000e+02 60 60 SCL SCL 0
0 10 04/19/04 13:30 60 SCL CVEXC FPsU 0 Li 04/19/04 13:32 01 7. 920000e+02 60 SCL L2 CVEXC FP6S 01 '.290000e+02 I_ 4 CVEXC FP6U 04/19/04 13:34 60 SCL a 13 04/19/04 13:35 01 72.470000e.02 60 SCt 0 14 CVEXC FP7S 01 /3.480000e+02 0 CVEXC FP7U 04/19/04 13:36 60 SCL L5 04/19/04 13:40 01 V3540000e+02 G0 SCL 0 IL6 CVEXC FPFS 01 q.670000e+02 SCL 0 I, .
04/19/04 *13:42 60 17 CVEXC FPBU 04/19/04 13:44 03 4'.460000e+02 60 SCL 0 L8 CVEXC FP9S 01 v).430000e+02 0 CVEXC FP9U 04/19/04 13:46 $. 060000e+02 60 SCL 19 CVEXCFP1OS 04/19/04 13:48. 01 AZ.330000e+02 60 SCL 0 20 CVEXCFPlOU 04/19/04 13:50 01 1.659660e405 60 SCL 0 21 04/19/04 14:14 01 22 CVEXCSC CK LOG USER ID IS KL3171 z-1.)
I ORIGIN"NAL
- S3 . S 14r- 'zo/i LTEZSE9b8 6E :bT tbQOZ/61/09 NOXX3 AII-1IV 33NS Z 9d
Williamsburg Concrete Background Measurements 37122N21 Instrumont 95348 RLM6220 Tlmo Dotoctor Counts Count Time (sec) Mode Dosignator
- -- ,SS-IO1 BHB 0 BKGNO 114/202--- B:52 1 7.25E+03 1800 SCL Inflal Background f%
1 Source Check 11412002 9.07 1 1 7 OE+05 60 SCL Source It 2 BKGNO 11412002 10:05 2 4.40E+01 1800 SCL Inital 83ckgroufld
- 14 Source Check 1/412002 10:39 2 1 5lE405 60 SCL Source in Shielded Unshielded 15 CON AIS 114/2002 13:00 1 2.78E-02 60 SCL Shielded ns 2.78E+021 16 CONA1U 11412002 13:02 1 3.88E'02 60 SCL Unshielded It 1 3 U8E-02 17 CON A2S 1/412002 13:20 1 2.39E-02 60 SCi Shielded _i 2 39E602 18 CON A2U 11412002 13 21 1 2.22E-02 60 SCL Unshielded it 2 22E602 29 CON A3S 1/4R2002 1328 1 2.39E+02 60 SCL Shlelded II 239E,02 _
20 CON A3U _ 1/4f2002 13.30 1 2.62E#02 60 SCL Unshielded iI 2.62E+02 21 CON A4S 1/412002 1336 1 2.45E*02 60 SCL Shieldea I 2.45E+02 22 CON A4U 11412002 13:38 1 2.71E-02 G0 SCL Unshielded D 23 2.71E.02 CON A5S 1t412002 13:58 t 2.OOE-02 60 SCL Shielded ll 2.00E602_
24 CON A5U 1/4n2002 14 00 1 2.82E-02 60 SCL Unshielded _ 2.82E *02 25 CON A6S 1/412002 14:03 1 1.54E402 60 SCL Shielded . 1.84E-021 26 CON A6U 1/4/2002 14 05 1 3.10E402 60 SCL Unshielded _ 3.10E+02 27 CON A7S 1/4.2DO2 14:09 1 1.98E-02 60 SCL Shielded _ I 98E-021 28 CON A7U 1/4t2002 14 10 1 3 15E+02 60 SCL Unshielded _ -3 1515E.02 29 CON A8S 11412002 14:19 1 2.34E-02 60 SCL Shielded IS 2.34E6021 30 CON A8S 11412002 14.22 1 2.31E-02 60 SCL Shielded _: 2.31E+021 31 CON A8U 1)4t2002 14 24 1 2.88E-02 60 SCL Unshiolded Is 2.88E-02 32 CON A9S 1/4/2002 1431 1 2.65E402 60 SCL Shielded _ 2 65E602 33 CON A9U 1/412002 14:33 1 2.89E602 60 SCL Unshielded _ 2.89E.02 34 CON A10S 1/412002 14 42 1 2.46E+02 60 SCL Shielded II 2 4GE-02 35 CON A1OU 1/1/2002 14:43 1 3.16E+02 60 SCL Unshielded _ 3.1GE602 36 CON A11S 1/412002 15:10 1 1.95E402 60 SCL Shielded _I 1.95E+02 37 CONAttU 1/4Q002 15:12 1 2.94E-02 60 SCL Unshielded il 2.94E602 38 CON A12S 1/412002 15.13 1 2.2t1E02 60 SCL Shielded _I 2.21E+02 39 CONA12U 1l412002 15:14 1 2.8tE402 60 SCL Unshielded _i 2.84E602 40 CON A13S 1/412002 15:23 1 1.74E#02 60 SCL Shielded 11 1.74E+02 41 CON A13U 114t2002 15:24 1 2.94E+02 60 SCL Unshiekled it 2.94E.02 42 CON A14S 11412002 15:25 1 1.95E+02 60 SCL Shielded It 1.96E+02 43 CON A14U t14/2002 15:26 t 3.33E+02 60 SCL Unshielded n1 3.33E.02 44 CON A155S 114/2002 1528 1 2.16E+02 60 SCL Shielded _1 2.16E-02 . -
45 CONA15U 1l412002 15:29 1 3.45E+02 60 SCL Unshieided _ 3.45E'02 46 CON A16S 1/412002 15:30 1 1.83E+02 60 SCL Shielded _ 1.83E-02 47 CONA16U 1/412002 15.31 1 3.135+02 60 SCL UnshIelded ni 3 13E602 48 CONA17S 1/4Q2002 15:33 1 1.82E+02 60 SCL Shielded 1 1.82E-02 49 CON A17U 114/2002 15:34 1 3 22E 02 60 SCL Unshielded II I3.22E+02 50 CON A1BS 1/412002 15:35 1 1.84E-02 60 SCL Shielded _ I 84E.02_
51 CON A18U 1/412002 15.36 1 3.24E602 60 SCL Unshiolded _ 3.24E+02 52 CON A15S 1/412002 15:37 1 1.91E+02 60 SCL Shielded II 1.911E-02 53 CON A19U 1/412002 15:39 1 3.07E402 60 SCL Unshielded _ 3 07E+02 54 CON A20S 114R2002 15:40 1 1.94E-02 60 SCL Shielded 1t.94E-02 55 CON A20U 1/412002 15:41 1 3.33E-02 60 SCL Unshielded _ 3 33E-02 56 CON A215 11412002 15:57 1 2.23E*02 60 SCL Shielded 1 2.23E'02 57 CON A21U 11412002 15:60 1 2.92E-02 60 SCL Unshlelded a 2 92E602 58 CON A22S I4RG00Z 15:59 1 1.72E-02 60 SCL Shielded B 1.72t-o02_
so CON A22U 114/2002 16:00 1 2.80E+02 60 SCL Unshielded .1. 2.80E+02 60 CON A23S 1/412002 16:01 1 1.94E-02 60 sCC. Shielded I 94E-02 61 CON A23U 1I412002 16:02 1 3.29E+02 60 SCL Unshielded 3.29E-02 62 CON A245 1/41200Z 16:04 1 1.87E+02 60 SCL Shielded I 1.87021329 63 CON A24U 1/412002 16:05 1 3.48E*02 60 SCL Unshielded 13 3.48E+02 64 CON A25S 1/412002 16 06 1 2.07E*02 60 SCL Shlelded it 2.07E+02 65 CON A25U 1/4/2002 16 07 1 3.72E602 60 SCL Unshielded pL 372E402 66 CON A26S 1/412002 16:09 1 2.09E602 60 SCL Shielded p 2.09E.02 67 CON A26U 1/4/2002 16:10 1 3.26E+02 60 SCL Unshielded ii 326E+02 68 CON A27S 1/412002 16:11 1 2.07E+02 60 SCL Shielded 2.07E6021 69 CON A27U 1/412002 16.12 1 3.30E+02 60 SCL Unshlelded fl 3.30E 02 70 CON A285 1/4/2002 16:14 1 2.30Ea02 60 2.30£-02 =
SCL Shielded I 71 CON A28U 1/412002 16:15 1 3 06E+02 60 SL Unshielded 3 06E-02 IP 72 CON A29S 1/412002 16 20 1 2.13=+02 60 SCL Shielded I 2 131-02 73 CON A29U w1/42002 16:21 1 2.58E+02 60 SCL Unshielded 2.58E.02 IŽ 74 CON A30S 11412002 16:24 1 2.33E-02 2.33E+02 60 SCL Shielded n 2.896+02 75 CON A3OU 1/412002 16:25 1 2.89 6'02 60 SCL Unshielded n 1.84E602 76 CON A31S 114/2002 16:28 1 1.54E+02 60 SCL Shtelded 11 77 CON A31U 1/4/2002 16:29 2 2.63E.02 2.63E602 60 SCL Unshielded 1t
- Souwce Check 1/4/2002 17:27 1 1.70E+05 60 SCL M~nimuM -' 1.72E+!02 .22E2 Maximum -> .8+238E0 Mean -; 2.1 1E+021.3.06E+02 Sigmo = .9+13~0 AMTCHMENNT q L
ai. -j.
Site Report Site Summary Site Name: OL1-2 AREA Planner(s): BHB Contaminant Summary NOTE: Surface soHl DCGLw units are pCIg.
Building surface DCGLw units are dpn/10 Ocm 2.
Screening Contaminant Typo DCGLW Value Used? Area {m') Area Factor Cs.137 4.30 No 10.000 1 1
COMPASS vl.0.0 411912004 rava IstI An___
- an F
ATTACHMENT l. _ .. I
'.j Surface Soil Survey Plan Survey Plan Summary OL1-2 AREA Planner(s): BHB Survey Unit Name: 803' to Grade - CV Yard Comments: Partial Survey of CV Yard Area Area (m2): 309 Classification: I Selected Test: Sign Estimated Sigma (pCig): 1.06 DCGL (pCig): 4.30 Sample Size (N): 39 LBGR (pCig): 3.5 Estimated Conc. (pCi/g): 0.8 Alpha: 0.050 Estimated Power:
0.100 EMC Sample Size (N): 39 Scanning Instrumentation: 2" by 2" Nal -C! s-1 37 W Prospective Power Curve
- I
" 0.9
_to p.
= 0.8 C
- 0.7 t 0.4 02.
- 0.3
- k. 0.3 t- 0.2 3-5 0.1
=
0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 SO Soil Concextration (pCi/g), includig backgro)al
- Power DCGL - - Esimated Power
- LBGR n 1beta COMPASS v1.0.0 4/9/2004 Page 1 ATTACHMENrLfJ / 2-
,-. Surface Soil Survey Plan Contaminant Summary -
DCGLw Modified DCGLw Scan MDC Coitnant pCVg) Contwminat Ratio 1pC19g) (pCI/9)
Cs-137 4.30 NIA WUA NIA 3.2 Survey Unit Estimate Reference Area Estimate (Moan I 1-Signw) (Mean I 1-Stgma)
Contaminant (pCUg) 0pCUg)
Cs-137 0.82t 1.08 0.28 +/- 0.39
,F2W64 Page 2 COMPASS vI.0.0 ATTACHMENT /I .
___ I__
W TI ~ l 8 * * !*! IX 1l aI..qVUt9l-U Mrn usItUementIIi tournpt1rIsF n (tMU)
I Enter in a descdiption for the scanning instrumentation used. Then enter a scan MDC for each measured ccntaminart. Click the CALCULATE button to view the integrated suivey design results. All entered and calculated scan MDC and DCGL units are in pCi/g.
Scanning Ins:rumentation Desciiption: 12' by 2" Nel - Cs-i 37 W Scan MDC 1111 C- , . .. . I. . - .
Contaminant I - I: il~l:;,,:.'ji.,-,i,)l.. --
Cs-1 3 7 3.2 NUREG-1507
- , I.
CALCULAE Statistical Design Hot Soot Design N: 39 Actual Scan M D C 3.2 Bounded Area (rn: l 7.9 Area Factor. l N/A Area Faaor: F 1 Bounded Area(m): l N/A DCGLw: l 4.30 Post-ENICN: I 39 Scan MDC Required: l N/A . i.
. 'I No addilional samples are ieqjired becaise the actual
`-gr scan MDC is less than [he DCGLw. i PF Enable Traininc
.i 1'.
I I# L/
Site Report Site Summary Site Name: CV YARD CONCRETE MISC Planner(s): BHB Contaminant Summary NOTE: Surface soil DCGLw units are pCVg.
Building surface DCGLw units are dpm/100 anm.
Screening Contaminant . .:". Type DCGLw Value Used? Area (in?) Area Factor Gross Actvty . . - Building Surface No COMPASS Vl.0.0 411A912004 ATTACHMENT 12 *L{
'-) Building SurFace Survey Plan Survey Plan Summary CV YARD CONCRETE MISC Planner(s): 8HB Survey Unit Name: CV Yard Misc.
Comments:
Area (m2): 48 Classification: I Selected Test: WRS Estimated Sigma (cpm): 53.58 DCGL (cpm): 1,260 Sample Size (N/2): 8 LBGR (cpm): 1,100 Estimated Conc. (cpm): 13.9 Alpha: 0.050 Estimated Power: 1.00 0.100 EMC Sample Size (N): 8 Prospective Power Curve 09
>.0.7
' 0.6 0.5
~0.4
- 0.1 0 200 400 600 8~0 1000 1200 1400 Net Beta (cpa)
- Power -DCG. - - Esfrnated Power a- LBG 1-beta COMIPASS v1.0.0 4/20/2004 Page 1 ATTACHMENT _ 2
%J Building Surface Survey Plan Contaminant Summary DCGLw Contaminant (dpmIOO cm)
Gross Activity 33,325 Beta Instrumentation Summary Gross Beta DCGLw (dp/t100 cm): 33,325 Total Efficiency. 0.03 Gross Beta DCGLw (cpm): 1,260 ID Type Mode '_ Arma (crn) la GFPC Beta 126 Contaminant ,,S;! Eno17. . . _. .
Fraction' Inst. Eff. !iv- Surf. Eff. Total Efl.
O Gross Activity 187.87 1.0000 0.48
' Average beta energy (keV) [N/A indicates alpha emission]
' Activity fraction Gross Survey Unit Mean (cpm): 320
- 54 (1-sigma)
Count ime (min): 1 Number of Average .Standard MDC Matertal ."r
- -: ~*-- 2t 4 *3 BKG Counts : (cpmi) DeviaWon (cprn) (d2M2O3O 1 Concrete 31 306 34.5 2,231 COMPkSS'v.0.O 4/20J2004 Page 2 ATTACHMENTH12_- -
N.1I -. It, I IMI I -xi WRS TEST Sample Size and Prospective Power Curve Design This step calculates the WRS Test sample size end prospective power curve for the selected survey unit(s). Enter values for the DQO parameters. then click the CALCULATE button. When you are sotisfied with this design, click the NEXT button.
- Enter Values _ 1 I LBGR: l100- 0.9 Alpha: 10.50 o J a- ___ I
= 0.?
Bela: 0.100 Calculations J
=' 0.7 C 0.6 I
_l ___ --: = =I 4-DCGL l 1.260 R 0.4 Sigma: l 53.58 = 03 a
Aj/a: l 2.99 = _ __- _A t..
Pr: 10.974067 = 0.1 s .. #
N/Z rT -0.1 C.40 I I!
Conc.: l13.9 0 200 400 600 800 1000 1200 1400 Powet:I 1.00 Net Beta (cpm)
- Prospective Power - DCGL -a Estimated Power i- 1..LlLP T - LBGR
- I-beta I
W,Enable Training Card Help
,, ':,.i BAGK NE)(1 A~AHET--A I 2f i L-
tt Z; -
Elevated Measurement Comparison (EMC) for Beta Follow the order of each tab belowto perform the EMC.
1)Enker Scanrn'g Irnstiwnent Efficimncie 2)Enter Scan MDC Parametess I 31 View EMC Results Scan MDC Required per Contaminant
.4 Contarminant I DCGLw- I AreaFactor I Scan MDC RequiredA l Gross Activity 33.325 2.84 94,643 Statistical Design Hot Spot Design N/2: l 8 Actual Scan MDC" l 4.407 BoundedArea(ml: I 6.0 .Area Factor. l N/A Area.Factor. l 2.84 Bounded Area (mrr: l N/A DCGLw*-: l 33.325 Post-EMC N/2: l 8 Scan MDC Required- . 94.643
- _i xI "dpmr/1 00 ac 2 No addiconal samrrpes are reqtir~d because the arlual fi scan MDC is ess than the DCGLw for eaah ctndan P EnableTrainin
.I O-E_0
-11OO ATTACHMENT-IŽ.o. *