ML20134F466

Final Survey Rept for ISFSI Site for Trojan Nuclear Plant

ML20134F466
Person / Time
Site:	Trojan  File:Portland General Electric icon.png
Issue date:	10/30/1996
From:	PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20134F462	List: ML20134F459 ML20134F466
References
NUDOCS 9611050324
Download: ML20134F466 (77)

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TNP FINAL SURVEY REPORTFOR THEISFSI SITE Paae 2 EXECUTIVE

SUMMARY

This report presents the results of the final survey measurements performed within a portion of the Trojan Nuclear Plant industrial area, located north and east of the power block, referred to as the ISFSI Survey Area. Completion of the ISFSI Survey Area final survey is intended to support release of the area from the requirements of license NPF-1 and 10 CFR 50 in preparation for the area being licensed under 10 CFR 72.

The survey area was categorized into five survey units, one of which was classified as affected, the other four as unaffected. The final survey of this area was performed in accordance with the TNP Final Survey Plan for the ISFSI Site and approved survey procedures.

The final survey of open land areas included the collection of 66 exposure rate measurments and 66 surface soil samples. The final survey of surfaces and structures included 120 direct measurements for total surface activity,120 measurements for removable alpha and beta activity, and 120 measurements for exposure rates. All exposure rate measurements were less than 5 R/hr above background. All surface activity measurements were less than 25% of the release limit values for unrestricted use, and soil concentrations were equivalent to environmental background concentrations.

The boundaries of the ISFSI Survey Area have been defined by the existing industrial area security fence on the north and east, and temporary installed fencing on the south and west. In addition, administrative controls have been implemented to control personnel and material access to prevent licensed material from entering the area.

The results of the final survey data presented in this report demonstrate, with a high degree of confidence, that the criteria established for release of the defined area for unrestricted use have been satisfied.

October 30,1996

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TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 3 TABLE OF CONTENTS Section Page Executive Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Table of C ontents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 1.0 Introduction 1.1 . Purpose and Scope . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1.2 H i story . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1.3 Survey Area Description . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Figure 1-1 Trojan Industrial Area, Northeast Corner . . . . . . . . . . . 7 2.0 Decommissioning Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3.0 Final Survey Overview 3.1 General Approach . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3.2 Identity of Contaminants . . . . . . . . . . . . . . . . . . . ..... 8 3.3 Relea se Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 3.4 Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 3.5 Minimum Detectable Activity . . . . . . . . . . . . . . . ...... 11 3.6 Survey Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 3.7 Quality Assurance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 3.8 Data interpretation . . . . . . ........................ 16 Figure 3-1, ISFSI Survey Area . . . . . . . . . . . . . . . . . . . . . . . . . . 18 Table 3-1, Final Site Survey Procedures . . . . . . . . . . . . . . . . . . 19 Table 3-2, Surface Contamination Limits . . . . . . . . . . . . . . . . . . 20 Table 3-3, Final Survey Instrumentation . . . . . . . . . . . . . . . . . . . 21 Table 3-4, Typical Detection Sensitivities . . . . . . . . . . . . . . . . . . 22 Table 3-5, Survey Units Classification . . . . . . . . . . . . . . . . . . . . . 24 4.0 Final Survey Results 4.1 Background Radiation Levels . . . . . . . . . . . . . . . . . . . 25 4.2 Survey Unit: BES . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 4.3 Survey Unit: NAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 October 30,1996

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.TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 4 Section Paae 4.4 Survey Unit: WSH ...... ............. ....... 29 4.5 Survey Unit: TIA . . . . . . . . . . . ........... ..... 31 4.6 Survey Unit: RWA . . . . . . . . . . . . . . . . . . . . . . . . 32 Table 4-1, Background Values for Gamma Exposure Rates . . 34 Table 4-2, Background Total Surface Activity .. ... .... . 35 Table 4-3, Background Radionuclide Concentrations in Soil . 36 Table 4-4, Summary Results for Survey Unit BES . . . . . . . . . 37 Table 4-5, Summary Results for Survey Unit NAM . . . . . . . . 38 Table 4-6, Summary Results for Survey Unit WSH . . . . . . . . 39 Table 4-7, Summary Results for Survey Unit TIA . ... .. 40 Table 4-8, Summary Results for Survey Unit RWA . . . ... .. 41 5.0 Summary . . . . . . . . ..... . .. . .. ... . . 42 6.0 References . .. . . . .. ... . .. ........ . 43 Appendix A, Survey Unit BES Survey Data Appendix B, Survey Unit NAM Survey Data Appendix C, Survey Unit WSH Survey Data i

Appendix D, Survey Unit TIA Survey Data Appendix E, Survey Unit RWA Survey Data Appendix F, Background Radiation Survey Data October 30,1996

TNP FINAL SURVEYREPORTFOR THEISFSISITE Paoe 5

1.1 Purpose and Scope

The purpose of this report is to present the results of the final survey of the proposed independent Spent Fuel Storage Installation (ISFSI) area and the surrounding area that will have elevated gamma exposure rates when the ISFSI is fuity loaded. It is PGE's intent that this report supports the eventuil authorization by the Nuclear Regulatory Commission (NRC) to remove the seveyed area from the conditions of the 10 CFR 50 license, and satisfies, in part, condition number 5 of the Oregon Energy Facility Siting Council's Order Approving Decommissioning Plan.

Portland General Electric is planning to site an ISFSI in the northeast corner of the Trojan Nuclear Plant (TNP) industrial area. As preparation for this project, final survey measurements were collected in accordance with the TNP Final Survey Plan For The ISFSI Site, PGE-1074 (Reference 1), and approved implementing procedures. The survey operation was performed from August 5 through October 17,1996 by trained PGE employees.

The scope of this report is limited to the final survey associated with surfaces and structures and open land area located within the northeast portion of the TNP industrial area, known as the ISFSI Survey Area. The report discusses the measurement requirements, implementation of the final survey for the identified area, and the results of the measurements.

1.2 History TNP achieved initial criticality in November 1975 and began commercial operation in May 1976. The reactor output was rated at 3411 Mwt with an approximate net electrical output of 1130 Mwe. The nuclea steam supply system was a four-loop pressurized water reactor designed by Westinghouse Electric Corporation.

TNP was shutdown for the last time on November 9,1992. On January 27,1993, after cpproximately 17 years of operation, PGE notified the NRC of its decision to permanently cease power operations. This decision was predicated on both financial end reliability considerations. The NRC amended the TNP Facility Operation License (NPF-1) to a Possession Only License on May 5,1993. Limited dismantlement cctivities commenced in 1995.

October 30,1996 l

TNP FINAL SURVEY REPORTFOR THEISFSI SITE Paae 6 1.3 Survey Area Description The ISFSI Survey Area is a section of land, approximately 10,000 square meters in size, located within the northeast end of the TNP industrial area, as shown in Figure 1-1, Trojan Industrial Area. The area includes the area that will be used for the proposed ISFSI, and additional area that will have radiation levels due to ISFSI fuel storage that will interfere with the final TNP site survey pursuant to 10 CFR 50.82, and

) over which positive control of the movement of personnel and materials can be I

reasonably maintained. .

The ISFSI Survey Area has been isolated from the rest of the industrial area by a temporary chain link fence with locked gates along the west and south boundaries. The east and north boundaries are the original security protected area (now industrial area) fence. Approval and gate key must be obtained from TNP Security or Radiation Protection for access to the surveyed area. This combination of administrative and physical controls ensure that licensed radioactive material is not brought into the surveyed area.

A Low-Level Radioactive Waste Storage Building, that was located in the northeast corner of the survey area, approximately 50 feet of the Maintenance Building, and approximately 100 feet of the WSH Warehouse were dismantled and removed, including concrete slab floors, prior to commencing survey data collection. The remaining west portion of the WSH Warehouse, and the North American Fabrication Shop are the only two buildings within the survey area. Other accessible structural surfaces within the survey area include an open, concrete lined, storm water drainage ditch along the east and north boundaries, locelized areas of concrete pavement, and utility fixtures (light poles, electrical transformers, fire water stations). The balance of the survey area is open land that is gravel fill.

Except for the location of the no longer existing Low-Level Radioactive Waste Storage Building, the survey area does not have a history of licensed radioactive material

{ contamination. The Fabrication Shop had experienced naturally occurring radioactive material contamination in the past from grinding the tips of tungsten welding rods, which I

contained naturally occurring thorium. Based on this and the low probability of residual radioactive contamination, the survey area was classified as unaffected, except for the area on which the Low-Level Radioactive Waste Storage Building sat, which was cleasified as affected.

October 30,1996 l

TNP FINAL SURVEY REPORT FOR THE ISFSI SITE Pace 7 Figure 1-1 TROJAN INDUSTRIAL AREA NORTHEAST CORNER l /v $

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TNP FINAL SURVEY REPORT FOR THEISFSI SITE Pace 8 2.0 DECOMMISSIONING ACTIVITIES PGE chose the DECON alternative for decommissioning. TNP is currently in the middle of a transition period of approximately six years to allow for deca / heat dissipation, prior to transferring fuel to an ISFSt. A radiological characterization of the TNP site was performed in 1993 (Reference 2). The four steam generators and the pressurizer were removed ar.d disposed of in 1995. Dismantlement activities in 1996 have included removw of reactor coolant system piping, and pumps, and miscellaneous Auxiliary Buildog equipment. Decommissioning activities are further described in the TNP Decommissioning Plan, PGE-1061 (Reference 3).

As already described in Section 1.3, one building and portions of two other buildings were removed from within the survey area prior to initiating the final survey data collection.

3.0 FINAL SURVEY OVERVIEW 3.1 General Approach The purpose of the final survey was to demonstrate that NRC criteria for unrestricted use of the surveyed area are met. The survey was also to meet, in part, condition number 5 of the Oregon Energy Facility Siting Council's Order Approving Decommissioning Plan. This required evaluation of licensed radionuclide concentrations in soils, residual surface radioactivity levels, and radiation surface scans and exposure rates of structural surfaces and open land areas.

The final survey was performed in accordance with the TNP Final Survey Plan For The ISFSI Site, PGE-1074 (Reference 1), and approved plant procedures, which are listed in Table 3-1, Final Site Survey Procedures. The survey plan and procedures identify survey instrumentation requirements, measurement and sample collection, and data evaluation methods.

3.2 Identity of Contaminants The primary radionuclides of interest for this survey were Co-60 and Cs-137, based on the data complied in the TNP Radiological Site Characterization Report (Reference 2) and summarized in the Decommissioning Plan (Reference 3). Hard to detect radionuclides, such as Sr-90 and Pu-239/240, are considered potential contaminants at Trojan; however, such radionuclides are expected to be present with other beta / gamma emitting radionuclides that can easily be detected. This conclusion is based on a review of the radioactive waste sample data from the annual scaling factor samples, which showed that Co-60 was always present when alpha emitting transuranic radionuclides October 30,1996 '

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TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 9 were identified. Cesium 137 was present in 85% of the radwaste samples. The average proportion of Cs-137 to Sr-90 was 349, for dry active waste, based on the dirty

waste filter analyses, and 33 based on clean waste demin analyses.

All final survey locations were evaluated to identify the presence of any radionuclide which may be attributed to licensed activities at TNP, specifically the gamma emitting radionuclides Co-60 and Cs-137.

Extensive ~ o ackground surveys were conducted to confirm the conclusions drawn from the radiological site characterization survey, and to further characterize radiation backgrounds for building surfaces, concrete and asphalt pavement, and gravel filled open land.

3.3 Release Limits The results of final survey individual measurements within the survey area were compared to release limits to determine suitability for release for unrestricted use. For the unaffected area survey units, tctal and removable surface activity, or radionuclide soil concentrations were compared to 25% of the release limit values to verify area classification (unaffected versus affected). For the one affected area survey unit, radionuclide soil concentrations were compared to 75% of the release limit values.

Additionally, the 95% upper confidence level of the mean for each type of measurement

, in each survey unit was compared to the applicable release limit.

To compare survey measurements to the release limits, background radiation and radioactivity data were collected from locations outside the plant industrial area and unaffected by licensed activities. Background levels were subtracted from final survey measurements to obtain net measurements.

3.3.1 Surface Activity For total and removable surface radioactivity, release limits are given in Regulatory Guide 1.86, (Reference 4) and reproduced here in Table 3-2, Surface Contamination Limits. Individual fixed point measurements were compared to the table column labeled " Maximum," and smear samples were compared to the table column labeled " Removable." Action levels of 25% or 75% of the release limit for investigation survey were established for obtaining additional data, if required, to average over one square meter. The statistical mean and 95%

upper confidence level values for total surface activity were compared to the .

Table column labeled " Average."

October 30,1996

TNP FINAL SURVEY REPORT FOR THE ISFSI SITE Paae 10 3.3.2 Exposure Rates The acceptance criteria for exposure rates, measured at a distance of one treter from accessible surfaces in buildings and open land areas, are an average of 5 .

pR/hr above background for the survey unit, with individual measurements not to exceed 10 pR/hr above background. An action level of 5 pR/hr above background was established for obtaining additional data by investigation survey to average over 10 square meters for structures and 100 square meters for open land areas.

3.3.3 Radionuclide Concentrations in Soll Radiological analysis results of surface and subsurface samples were evaluated to demonstrate that the Total Effective Dose Equivalent (TEDE) to the average individual was below 15 mrem /yr using the default concentration values for soil residential scenario recommended in NUREG-1500 (Reference 5). For the principle gamma emitters, Co-60 and Cs-137, the release limit values are 2.97 and 10.70 picocurie per gram respectively. Action levels of 25% or 75% of a release limit were established for obtaining additional data by investigation survey.

3.4 Instrumentation Selection and use of instrumentation ensured sensitivities were sufficient to detect the primary radionuclides of concern. A list of the instruments, radiation detected, and calibration sources used is provided in Table 3-3, Final Survey Instrumentation.

3.4.1 Field Instrumentation The Eberline Model ESP-2 Smart Portable was used for total surface activity and exposure rate measurements. The ESP-2 is a data logging, microcomputer based, portable radiation survey instrument designed to operate with a variety of radiation detectors as a digital scaler or rate meter. Detecter parameters (e.g.,

high voltage, calibration constant) are stored in the ESP-2 memory. For this survey, three detectors were used with the ESP-2 instrument:

• SPA-8, a 1" by 1" Nal(TI) gamma scintillator for exposure rate measurements and scan surveys.

• 2 BP-100, a 100 cm plastic scintillator for total beta surface activity.

October 30,1996 I

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TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 11

• 2 AC-3-8, a 59 cm ZnS(Ag) scintillator for total alpha surface activity. This detector was used for background characterization surveys only.

A Reuter-Stokes Model RSS-112 PIC portable environmental radiation monitor was used for exposure rate measurements. The RSS-112 PIC asists of a microcomputer based electronics enclosure, and a high pressurized ion chamber detector filled with ultra-high purity argon.

t An NE Technology Limited Model CM11 contamination monitor was used for building surface scan surveys. The CM11 contamination monitor consists of a microcomputer based electronics enclosure, and a Type DP11 A gas flow dual detector. The gas flow proportional detector has an active area of 100 cm2, and is capable of detecting both alpha and beta contaminate simultaneously.

3.4.2 Laboratory Instrumentation Radionuclide sample analyses were performed on-site using the following counting systems:

Tennelec Model LB5100 Low Background Alpha Beta Counter, a gas-flow proportional automatic counting system, to c ount smear samples for alpha and beta activity.

I Ortec/ Canberra Gamma Spectroscopy system, equipped with liquid nitrogen cooled High Purity Germanium (HPGe) detector, to analyze soil i

samples for gamma emitting radionuclide concentrations.

3.5 Minimum Detectable Activity (MDA)

The MDA is defined as the minimum amount of activity that can be statistically detected

' above background with a 95% probability and with a maximum of 5% probability of falsely interpreting sample activity as activity due to background. The MDA is dependent on the counting times, detector efficiency, background count rate, and sample size, if applicable. The a prioriMDA for each instrument and detector combination was calculated in accordance with the survey plan (Reference 1) and documented as specified in RP 454, Site Release Survey Background Determination.

In addition to MDA, the critical level was also calculated, following the methodology contained in NCRP Report No. 58 (Reference 6). The critical level is the net activity for reaching the decision of detection or non-detection. Table 3-4 provides a summary of typical detection sensitivities for the instruments used to determine activity. The MDAs for fixed-point measurements 2

of total beta surface activity were typically less than 230 dpm/100cm , and less than 90 dpm/100cm2 for fixed-point total alpha surface October 30,1996

TNP FINAL SURVEY REPORT FOR THE ISFSI SITE Paae 12 activity measurements.

The instrument used to perform alpha beta surface activity scan surveys for surfaces and structures was operated in the rate meter mode. The detector was held within 1 cm from the surface and moved at a rate not to exceed 5 cm per second, as specified in procedure RP 452, Site Release Survey Measurements. The detection sensitivity and survey technique were capable of detecting approximately 3850 dpm/100 cm2 The r

alarm feature of the instrument was also used to alert the surveyor of counts greater than about 3 times expected background count rate.

The instrument used to perform exposure rate scan surveys for open areas was also used in the rate meter mode. The detector was held at approximately 1 to 2 inches from the surface and moved at a rate of 12 to 36 inches per second (slow walk), as specified in procedure RP 452, Site Release Survey Measurements. The alarm feature of the instrument was used to alert the surveyor of counts greater than about 2 times expected background count rate. {

To ensure consistency in detection response, each survey instrument was source checked prior to and at the end of each day of use. The net instrument response was required to be within 10% of a predetermined count rate. An instrument would not be used if it failed the check at the start of the day. The survey data would require a determination of acceptability if the instrument failed the check at the end of the day.

A priori MDA values for laboratory instruments used to analyze survey samples were determined in accordance with approved plant procedures. The Tennelec LB5100, i

used to count smear samples for gross alpha and gross beta activity, had MDA values 2

of 8 dpm per 100 cm or less. The gamma spectroscopy system, used to isotopically analyze soil samples, automatically calculates MDA values. Soil samples were counted for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, yielding MDA values for Co-60 and Cs-137 of 0.01 pCi per gram or less.

3.6 Survey Design in addition to the final survey plan (Reference 1), and approved plant procedures (see Table 3-1), the final survey was designed and implemented in accordance with the guidance provided in draft NUREG/CR-5849 (Reference 7). The areas surveyed included open land areas (grounds), and two structures within the plant industrial area, as shown in; Figure 3-1, ISFSI Survey Area. This includes the area that will be used for the proposed ISFSI, and additional areas that will have radiation levels due to ISFSI fuel storage that will interfere with the final site survey pursuant to 10 CFR 50.82.

The boundaries of the survey area are defined by the existing industrial area security fence (the original protected area fence) along the north and east, and temporary fence October 30,1996 I

TNP FINAL SURVEYREPORTFOR THEISFSISITE Pax 13 installed along the south and west prior to start of survey data collection. This area was secured to establish positive control of personnel and rnaterial access in accordance f with plant procedure TPP 20-40, Control of Areas Surveyed for Final Release.

The survey area was divided into five survey units and classified as affected or unaffected, as shown in Table 3-5. Two survey units were categorized as open land areas, and three survey units were categorized as surfaces / structures. One survey unit was classified as affected, and four survey units as unaffected.

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A wa.idown of each survey unit was performed and survey instruction sheets and maps prepared identifying measurements and measurement locations. To aid in determining measurement locations, a 10 meter by 10 meter grid system was superimposed on the survey maps for the two open land area survey units, and a 10 foot by 10 foot grid on building survey maps. Measurement locations within the affected survey unit were systematically selected as 4 points within each 10 meter grid, equidistant from the grid center and its 4 corners. Measurement locations within the unaffected survey units were randomly selected by lottery method using the survey map grid identification

1. numbers. Generally,30 measurement locations were selected. All survey locations were physically marked and labeled after data collection.

The radiological parameters measured included:

• Surface scans to identify areas of elevated radiation.

e Surface contamination measurements.

• Gamma exposure rate measurements.

• Soil samples for radioisotopic analysis.

3.6.1 Background Radiation Surveys Background levels were determined for exposure rate, alpha and beta surface activity and soil concentrations. These measurements were obtained from areas outside the plant industrial area, in accordance with procedure RP 454, Site Release Survey Background Determination. The survey instruments and methods used for background measurements were similar to that used for fixed point measurements. Background levels were determined for the following media: ,

• Concrete Surfaces e Sheet Metal Building Surfaces e Sheet Metal with Fiber Glass insulation Building Surfaces e Surface Soil / Gravel October 30,1996 l

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TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 14 For documentation purposes, the background survey was treated as a survey unit, with a survey package developed to define the type and number of background measurements, and to organize and manage the background data collected.

3.6.2 Open Land Survey The final survey of the affected survey wiit (PWA) included an exposure rate scan survey of 100% of the surface area. The intent of the exposure rate scan was to identify potentially elevated areas of activity requiring additional sampling.

No elevated areas were detected during the exposure rate scan survey. Fixed point exposure rate measurements were collected with a Reuter-Stokes RSS-112 PIC at a distance of one meter from the surface at 3G systematically selected locations. Soil samples were collected at the same 36 locations, after exposure rate measurements. Six soils samples were split with a contractor laboratory for independent verification analysis. This survey unit was physically gridded into 10 meter by 10 meter sections.

The final survey of the unaffected survey unit (TIA) included an exposure rate scan survey of greater than 10% of the accessible surface area, and 100%of the accessible surface area of the concrete lined, storm drainage d;tch. No elevated areas were detected during the exposure rate scan survey. Fixed point exposure rate measurements were collected with the RSS-112 PIC et a distance of one meter from the surface at 60 randomly selected locations (30 over gravel ground, 25 over concrete surfaces, and 5 from utility structures). Soil samples were collected at the 30 gravel ground locations, after exposure rate measurements.

Three soils samples were split with a contractor laboratory for independent verification analysis. Surface contamination measurements (total beta activity and smears) were obtained from the 25 concrete and 5 utility surfaces, after exposure rate measurements. This survey unit was not physically gridded.

3.6.3 Surveys of Structural Surfaces Each structural survey unit (BES, NAM and WSH) received a surface activity scan survey over a minimum of 10% of the surface area to identify any areas of elevated radioactivity requiring additional measurement. Scan surveys were

' performed using a NE Technology Model CM11 gas-flow proportional dual alpha / beta contamination monitor. The detector was placed approximately 1 cm from the surface being surveyed and moved at a rate of 5 cm/sec or less.

Exposure rate measurements were obtained from 30 randomly selected locations for each survey unit, using an Eberline ESP-2 meter with SPA-8 Nal detector.

October 30,1996

l TNP HNAL SURVEY REPORT FOR THE ISFSI SITE Pace 1S '

Measurements were obtained one meter from each measurement location.

Following the exposure measurements, total beta surface activity was measured using an Eberline ESP-2 meter with the BP-100 plastic detector placed on contact with the surface being surveyed. A smear for removable surface activity was collected at the location of each total surface activity measurement. Smear samples were collected over an area of 100 cm' using standard smear sample media and collection techniques. Smear samples were analyzed for gross alpha and gross beta-gamma activity using a Tennelec LB5100 gas-flow proportional counter.

3.7 Quality Assurance Conduct of this final survey was subject to the requirements of the Trojan Nuclear Quality Assurance Program (NOAP)(Reference 8). The applicable quality assurance program elements were described in the final survey plan (Reference 1) and include the training of survey personnel, selection, calibration and operation of survey instrumentation, survey documentation, sample chain of custody, independent quality checking, and records management. In addition, Trojan Nuclear Oversight provided an independent review of all survey packages to verify that documentation is complete, and that the documented results meet the release limits.

Personnel involved in survey data collection, evaluation and/or review received classroom training covering an overview of the survey plan, and survey data collection methods and procedures. In addition, the survey technicians performed practice surveys covering all the survey techniques.

Radiation detection and counting instruments, and calibration and check sources are controlled, maintained and calibrated in accordance with the existing Trojan Radiation Protection Program (Reference 9). All instruments used for this final survey were properly calibrated prior to the start of data collection. Field instruments were checked for acceptable operation with radioactive sources (source ch3cks) prior to and at the end of each day of use. Analytical laboratory instruments received the routine prescribed QC checks each day of use. All radioacitve sources used for calibration, i

source checks and QC checks are traceable to NIST.

3.7.1 Survey Documentation Survey records are contained in a survey package for each survey unit, and maintained as Quality records and Decommissioning records in accordance with Plant procedure TPP 18-4 (Reference 10). Survey package records include:

• Independent review check sheet October 30,1996

iNP FINAL SURVEY REPORT FOR THE ISFSI SITE Pace 16 o Survey package documentation checksheet

• Documentation of survey data evaluations e Survey data summary tables e Survey instruction sheets, maps and diagrams e Scan survey results I

• e Exposure rate results Gurface activity results s

• Soils analysis results

[ e Sample chain of custody records e independent quality checking documentation sheets 3.7.2 Independent Quality Checking Independent quality checking of field and laboratory measurements was i performed for quality control purposes and to verify that survey measurements were being collected and documented correctly. Quality checking was g performed by qualified plant personnel not directly responsible for or otherwise B involved in final survey data collection. Quality checking included direct observations and record reviews of survey data and sample collections, and sample analyses of approximately 10% of the survey measurements. Results of I quality checking activities are documented in the applicable survey packages.

l In addition to quality checking by plant personnel, six background and nine B

survey unit soils samples were sent to Thermo Nutech, a contracted radinchemistry laboratory, to provide independent verification of gamma l spectroscopy analysis. This contractor laboratory has an acceptable quality I assurance program audited by Trojan Nuclear Oversight. Results of this split sample analysis confirmed the results obtained from in-house gamma analysis.

The survey data collection program was also observed by regulatory personnel with split samples shared.

3.8 Data Interpretation

{ The guidance provided in Section 8 of draft NUREG/CR-5849 (Reference 7) was used to assist in data interpretation. Measurements are reported in units appropriate for comparison to the release limits by correcting for background, efficiency, detector area, l and sample size as applicable. The reporting units are as follows:

• Surface Contamination: dpm/100 cm 2

• Exposure Rate: pR/hr

• Radionuclide Concentrations: pCi/g October 30,1996

TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 17 Mean values and 95% confidence level values were calculated for each type of measurement performed within a given survey unit and compared to the action levels f and release limits as described in the survey plan (Reference 1) and plant procedure RP 453, Site Release Survey Data Evaluation.

Survey data from field instruments and sample analysis results acquired from laboratory measurements were input into a computer spreadsheet database for statistical evaluation and report preparation.

t October 30,1996

TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 18 Figure 3-1 ISFSI SURVEY AREA s

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October 30,1996

TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 19 TABLE 3-1 Final Site Survey Procedures Procedure Number Procedure Title TPP 20-40 Control of Areas Surveyed for Final Release RP 450 Site Release Survey Administrative & Quality Controls RP 451 Site Release Survey Package Preparation RP 452 Site Release Survey Measurements RP 453 Site Release Survey Data Evaluation RP 454 Site Release Survey Background Determination RP 40 Calibration Procedure - RP Equipment Calibration Records and instrument Source Check Data Sheets RP 90 RSS-112 Pressurized lon Chamber RP 92 Operation of Eberline ESP-2 " Smart Meter" RP 94 Contamination Monitor CM-11 RP 111 Portable Radiation Instrument Source Checks RP 159 Conduct of Portable / Semi-Portable RP instrument Program CL 153 Calibration Check & Efficiency Calibration of Germanium Gamma Detectors CL 161 LB5100 Planchet Counting System Calibration Procedure LI162 LB5100 Planchet Counting System Operation Lt175 Liquid Scintillation Li187 ND-9900 Count Procedure October 30,1996 i

l

TNP FINAL SURVEY REPORT FOR THE ISFSI SITE Paae 20 TABLE 3-2 Surface Contamination Limits (*)

NUCLIDE S) AVERAGE (*#3 MAXIMUM (*#) REMOVABLE (*')

U-nat, U-235, U-238 and 5,000 dpm a/100 cm 2 15,000 dpm a/100 cm 2 1,000 dpm a/100 cm'

, associated decay products Transuranics, 100 dpm/100 cm2 300 dpm/100 cm 2 20 dpm/100 cm 2 Ra-226, Ra-228, Th-230, Th-228, Pa-231, Ac-227, 1-125,1-129 Th-nat, Th-232, Sr-90, 1,000 dpm/100 cm' 3,000 dpm/100 cm 2 200 dpm/100 cm' Ra-223, .Ra-224. U-232, 1-126,1-131,1-133 Beta-gamma emitters 5,000 dpm/100 cm' 15,000 dpm/100 cm 2 1,000 dpm/100 cm' (nuclides with decay modes other than alpha emission or spontaneous fission) except Sr-90 and others noted above.

a.

Reproduced from Regulatory Guide 1.86, Table 1, June 1974. Referred to throughout this survey plan as release limits.

b. Where surface contamination by both alpha and beta-gamma-emitting nuclides exists, the limits established for alpha and beta-gamma emitting nuclides should applyindependently.

c.

As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.

d.

i Measurements of average contaminant should not be averaged over more than 1 m2 . For objects with less surface area, the average should be derived for each object.

e. The maximum contamination level applies to an area of not more than 100 cm',

f. 2 The amount of removable material per 100 cm of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency.

When removable contamination on objects with less surface area is determined, the pertinent levels should be reduced proportionately and the entire surface should be wiped.

October 30,1996

TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 21 j TABLE 3-3 Final Survev instrurnentation instrument Detector Calibration Measurement Manufacturer Model & Source Type and Model # Type Eberline Smart AC-3-8, ZnS(Ag) Pu-239 Fixed-point, total Portable, ESP-2 Scintillator alpha surface activity Eberline Smart BP-100, Plastic Tc-99 Fixed-point, total Portable, ESP-2 Scintillator beta surface activity Eberline Smart SPA-8, Nal(TI) Cs-137 Gamma exposure Portable, ESP-2 Scintillator rate and scan survey Reuter-Stokes High Pressurized Cs-137 Gamma exposure RSS-112 PIC lon Chamber rate NE Technology Type DP11 A Alpha: Pu-239 Surface scan survey Contamination Dual Gas Flow Beta: Tc-99 Monitor CM11 100 cm2 detector Tennelec Gas Flow Alpha: Am-241 Removable surface LB5100 Series 2 Proportional ' Beta: Cs-137 activity Counter Counter Ortec/ Canberra High-Purity Mixed Gamma Radionuclide analysis Multi-channel Germanium Standard of soil / gravel samples Analyzer October 30,1996 f

y TNP FINAL SURVEY REPORT FOR THE ISFSI SITE Paae 22 TABLE 3-4 Tvolcal Detection Sensitivities i

INSTRUMENT BKG") EFF<23 COUNT MDA"' CRITICAL TIME LEVELW (CPM) (CPM /DPM) (MIN) (DPM/100 CM') (DPM/100 CM')

ESP-2 with 6 0.22 2 75 31 -

I AC-3-D (a) Pu-239 ESP-2 with 500 0.49 1 220 106 BP-100 (p) Tc-99 Tennelec 1 0.22 10 7.9 3.3 LB5100 (a) Am-241 Tennelec 2.4 0.33 10 7.7 3.4 LB5100 (D) Cs-137 CM11 with 200 0.147 0.022(d) 3850(') N/A DP11 A (p) Tc-99 CM11 with 1 0.04 0.022(') 3860(') N/A DP11 A (a) Pu-239 I (1) BKG = Background count rate.

l (2) EFF = Instrument efficiency. Sources used for efficiencies are traceable to NIST. Calibration radionuclides are listed in this column.

f (3) MDA = Minimum Detectable Activity.

(4) Scan Survey MDA, assumes detector width of 6.5 cm and scan rate of 5 cm/second, which gives a count time of 0.022 minute.

(5) NCRP Report 58 defines the decision limit, L,, as the net number of counts (total minus background) for reaching a decision of no detection of signal if the actual net counts are less than L , and detection if the actual net counts are larger than L,. The NCRP 58 decision limit is essentially the same as the critical /evel, L, , defined below, except that the critical l

October 30,1996

/

TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 23 '

TABLE 3-4 (continued) level is calculated as the net activity, in dpm/100 cm2 , rather than the net number of counts. The equation for critical level determination is:

l l 1.64 +

L,=

A 100 l

Where:

L, =

minimum amount of activity that can be statistically detected above background with a 95% probability (dpm/100cm 2),

BR =

background count rate in counts per minute (cpm),

T, =

sample counting time (minutes),

=

T. background counting time (minutes),

E =

counting efficiency, (cpm /dpm), and A =

detector area or the area sampled for smear samples, (cm2),

When T, = T, :

1=  % 4 E* '

9 October 30,1996

1 TNP FINAL SURVEY REPORT FOR THE ISFSI SITE Paoe 24 TABLE 3-5 Survey Units Classification SURVEY UNIT DESCRIPTION AFFECTED UNAFFECTED BES - Exterior surfaces of two buildings xxx within survey area NAM - North America Fabrication Shop, xxx interior structural surfaces WSH - WSH Warehouse, interior xxx structural surfaces RWA - RadWaste building site area, xxx contains open land area only TIA - Open land area within the Trojan xxx Industrial Area, contains ground, concrete surfaces and utility fixtures October 30,1996 i

l

TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 25 4.0 FINAL SURVEY RESULTS A summary of the survey results is provided in this section. The tables included in this section summarize the data collected for each survey unit and the background survey.

In accordance with NUREG/CR-5849 (Reference 7), actual analysis results (positive or negative) are presented rather than reporting the MDA, unless the MDA is the value reported from sample analysis. The measurement and sample data used to generate the tables are provided in Appendices A through F. The ISFSI Survey Area was divided into five survey units. The background radiation survey was treated as an additional survey unit. The results presented in this section are arranged by survey unit.

4.1 Background Radiation Levels Background levels were determined for exposure rate, alpha and beta surface activity and soil concentrations, from areas outside the plant industrial area for concrete pavement, concrete floor, sheet metal building wall surfaces, and surface soil Background measurements were also collected from other types of construction materials that are not present within the defined survey area (e.g., asphalt pavement).

The areas and buildings selected for background measurement locations includeri the Asset Recovery Building and Yard area, the Trojan North Building and parking lot area, the Switch Yard, the Meteorological Tower Yard, and an open land area identified as the South Yard area, comprising the area north of the plant sewer treatment facility, south of the main access road, and east of the Burlington Northern railroad tracks.

The arithmetically calculated average (mean) background value is applied to the final survey measurement to obtain the net measurement value.

4.1.1 Exposure Rates Gamma exposure rates were measured with a Reuter-Stokes RS-112 PIC and/or an Eberline EPS-2 with SPA-8 detector. At several of the measurement locations, multiple individual readings were recorded to evaluate instrument precision. For these locations, the averages of the multiple readings were used to evaluate background. The results of these gamma background evaluations are provided in Table 4-1.

4.1.2 Total Surface Activity Background values for total surface activity are dependent upon the contribution from naturally occurring radionuclides in construction materials, the local area exposure rate where the survey measurement is collected, and instrument noise.

Measurements were made separately for both alpha and beta surface activity.

For this survey no corrections were made for the contribution from naturally October 30,1996

TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 26 occurring radionuclides in construction materials, or the instrument background count rate. At several of the measurement locations, multiple individual readings were recorded to evaluate instrument precision. For these locations, the averages of the multiple readings were used to evaluate background.

Background measurements obtained are listed in Table 4-2. Smear :,amples were also collected following each surface activity measurement. Smears were analyzed for gross alpha and gross beta activity. All removable contamination 2

results were less than 8 dpm/100 cm for both alpha and beta activity.

4.1.3 Radionuclide Concentrations in Soil Radionuclide concentrations were measured in 35 soil samples collected from four locations outside the plant industrial area, where the soil consisted of gravel sand fill material similar to the survey area. Each sample was counted for two hours (7200 seconds). For the mean activity determination, each sample result was rounded to the nearest hundredth of a picocurie per gram (E-02 pCi/g). If no activity was detected, the reported MDA value, rounded to the nearest E-02 pCi/g, was used. The only radionuclide identified consistently in soil, other than naturally occurring radionuclides, was Cs-137, with an average value of 0.02 pCi/g. Seven samples reported Mn-54 with activity from 0.005 to 0.008 pCilg (rounded to 0.01 pCi/g for analysis). The Mn-54 values had large variances of 35% to 67%, indicative of possibly false positive identifications; however,0.01 pCi/g was estimated for background subtraction purposes. Six samples were split with a contractor laboratory for independent verification analysis. No radionuclides above counting system MDAs (<0.1 pCi/g) were repoded by the contractor for these, six samples. The results of the background evaluations are provided in Table 4-3. Results of verification analysis are documented in the survey package.

4.2 Survey Unit: BES Survey Unit BES covers the exterior surfaces of the two buildings in the defined survey area. The buildings are identified from their previous use as the North American Fabrication Shop, and the WSH Warehouse. Only approximately 80 feet of the orginal WSH Warehouse remains standing in the survey area. Since the total exterior surface 2

area of the two buildings is less than 1500 m ,30 survey locations were randomly selected for exposure rate and surface activity measurements. The measurement locations included 2 for the Fab Shop roof (BES001 & BES002),13 for the exterior walls of the Fab Shop (BES003 - BES015), and 15 for the exterior walls of WSH (BES016 -

BES030). A summary of the survey results is provided in Table 4-4 and discussed below. It is concluded from the survey results, that survey unit BES meets the applicable release limits for unrestricted use.

{ October 30,1996

TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 27 4.2.1 Surface Scan Survey The total surface area of the lower walls (ground level up to 6 feet height) of 2

these2two buildings 2

is approximately 2185 ft (203 m2 ). A total of approximately 400 ft (37 m ) of exterior su9ce area was surface scanned with the CM11 gas I flow proportional counter. The threshold set for indicating potential elevated 2

radiation levels was 4000 dpm/100cm for beta radiation and 3000 dpm/100cm 2 for alpha radiation. The surface scans detected no areas of elevated radiation.

I The surface scan survey is documented in the survey unit survey package.

4.2.2 Exposure Rates Gamma exposure rates were measured with an Eberline ESP-2 portable meter with SPA-8 Nal detector one meter from each measurement location. A I background value of 4.4 R/hr was applied to each survey to obtain the net measurement. No individual exposure rate measurement exceeded the release criterion of 5 R/hr. The net average exposure rate for the survey unit was I 1.2 R/hr, and 1.3 R/hr for the 95% upper confidence level.

4.2.3 Surface Activity Total beta surface activity was measured with an Eberline ESP-2 portable meter with BP-100 plastic detector following each exposure rate measurement. A I 2 background value of 527 dpm/100cm was applied to each reading to obtain the net measurement. No individual2measurement exceeded the administrative action level of 3750 dpm/100cm . The net average total surface activity for the I 2 survey unit was 188 dpm/100cm , and 249 dpm/100cm2 for the 95% upper confidence level, which are below the release criterion of 5000 dpm/100cm2 ,

Smear samples were obtained following total surface activity measurements for each location. The smears were analyzed for gross alpha and gross beta I activity. No smear sample exceeded the release criterion of 20 dpm/100cm2 for alpha and 1000 dpm/100cm2 for beta.

4.3 Survey Unit: NAM l

Survey Un't NAM is comprised of the interior structural surfaces of the North American l Fabrication Shop. The building's sheet metal walls are covered with plastic faced fiberglan2 insulation. Since the total surface area of the building interior is less than 1500 m , 30 survey locations were randomly selected for exposure rate and surface l activity measurements. The measurement locations included 15 on the concrete slab s

floor ( NAM 001 - NAM 015), and 15 on the interior walls (NAM 016 - NAM 030). A

{ October 30,1996 g

l TNP FINAL SURVEY REPORT FOR THE ISFSI SITE Paae 28 summary of the survey results is provided in Table 4-5 and discussed below. It is concluded from the survey results, that survey unit NAM meets the applicable release limits for unrestricted use.

This building had previously been used by contracted craftsmen to fabricate a variety of materials for plant maintanence and modifications. It was known that one area of the shop had been used to grind thorium-tungsten welding rod tips. Naturally Occuring Radioactive Material (NORM) had been found and removed from this area in the past.

At the start of this suwey this suspected area was surveyed for NORM contamination in accordance with roubne Radiation Protection procedures and practices, and NORM contamination was found in a small area at the base of the west wall and immediately outside this wall location. The area was decontaminated of the NORM by removing the particles of weld rod filings that had accumulated at the junction of the building base plate and concrete floor, removing a small section of the base plate and wall insulation, and removing a small amount of soil material. Routine radiation surveys after this decontamination effort indicated the residual NORM had been removed.

4.3.1 Surface Scan Survey The total surface area of the floor and lower walls (ground level up to 6 feet height) of this building is approximately 3385 ft2 (314 m2 ). A total of approximately 340 ft2 (32 m 2) of interior surface area was surface scanned with the CM11 gas flow proportional counter. The threshold set for indicating potential elevated radiation levels was 4000 dpm/100cm2 for beta radiation and 2

3000 dpm/100cm for alpha radiation. A gamma scan of 100% of the floor area 2

(approximately 2160 ft ) was performed with an ESP-2 with SPA-8 detector, with 3000 cpm set as the level indicating potentially elevated radiation. The surface scans detected no areas of elevated radiation. The surface scan surveys are documented in the survey unit survey package.

4.3.2 Exposure Rates Gamma exposure rates were measured with an Eberline ESP-2 portable meter with SPA-8 Nal detector one meter from each measurement location.

Background values of 4.3 R/hr for locations NAM 001 - NAM 015, and 3.8 R/hr for locations NAM 016 - NAM 030 were applied to each survey to obtain net measurements. No individual exposure rate measurement exceeded the release criterion of 5 R/hr. The net average exposure rate for the survey unit was 3.5 R/hr, and 3.6 R/hr for the 95% upper confidence level.

At the time the exposure rate measurements were collected, the general area radiation background on the north side of the industrial area was elevated by October 30,1996 l

TNP FINAL SURVEY REPORTFOR THEISFSISITE Paae 29 approximately 1 - 2 R/hr due to the presence of reactor coolant piping in shipping containers at various locations within the power block outside of the survey area. Since all of the survey measurements were less than the release criteria, it was decided to not correct for this elevated general area background.

A resurvey at the floor measurement locations after the majority of this piping had been shipped off-site showed the average net exposure rate had decreased to approximately 1.0 R/hr.

4.3.3 Surface Activity Total beta surface activity was measured with an Eberline ESP-2 portable meter with BP-100 plastic detector following each exposure rate measurement.

Background values of 934 dpm/100cm2for locations NAM 001 - NAM 015 and 2

722 dpm/100cm for locations NAM 016 - NAM 030 were applied to each reading to obtain net measurements. No individual measurement exceeded the administrative action level of 3750 dpm/100cm2 , The net average total surface activity for the survey unit was -43 dpm/100cm2 , and -22 dpm/100cm2 for the 95% upper confidence level, which are below the release criterion of 5000 dpm/100cm2, Smear samples were obtained following total surface activity measurements for each location. The smears were analyzed for gross alpha and gross beta activity. No smear sample exceeded the release criteria of 20 dpm/100cm2 for alpha and 1000 dpm/100cm2 for beta.

4.4 Survey Unit: WSH Survey Unit WSH is comprised of the interior structural surfaces of the remaining portion of the WSH 2 Warehouse. Since the total surface area of the building interior is less than 1500 m , 30 survey locations were randomly selected for exposure rate and surface activity measurements. The measurement locations included 16 on the concrete slab floor (WSH001 - WSH016), and 14 on the interior walls (WSH017 -

WSH030). A summary of the survey results is provided in Table 4-6 and discussed below. It is concluded from the survey results, that survey unit WSH meets the applicable release limits for unrestricted use.

4.4.1 Surface Scan Survey The total surface area of the floor and lower walls (ground level up to 6 feet height) of this building is approximately 6960 ft2 (647 m2). A total of-2 approximately 700 ft (65 m 2) of interior surface area was surface scanned with the CM11 gas flow proportional counter. The threshold set for indicating October 30,1996 l

J

TNP FINAL SURVEYREPORTFOR THEISFSISITE Pace 30 potential elevated radiation levels was 4000 dpm/100cm2 for beta radiation and 2

3000 dpm/100cm for alpha radiation. A gamma scan of 100% of the floor area 2

(approximately 6000 ft ) was performed with an ESP-2 with SPA-8 detector, with 3000 cpm set as the level indicating potentially elevated radiation. The surface scans detected no areas of elevated radiation. The surface scan surveys are documented in the survey unit survey package.

4.4.2 Exposure Rates Gamma exposure rates were measured with an Eberline ESP-2 portable meter with SPA-B detector one meter from each measurement location. Background values of 4.3 R/hr for locations WSH001- WSH016, and 4.4 R/hr for locations WSH017- WSH030 were applied to each survey to obtain net measurements.

No individual exposure rate measurement exceeded the release criterion of 5 R/hr. The net average exposure rate for the survey unit was 2.6 R/hr, and 2.7 R/hr for the 95% upper confidence level.

At the time the exposure rate motourements were collected the general area radiation background was elevated by approximately 1 - 2 R/hr, ar, already discussed in Section 4.3.2. A resurvey at the floor measurement locations after the majority of this piping had been shipped off-site showed the average net exposure rate had decreased to 1.3 R/hr.

4.4.3 Surface Activity Total beta surface activity was measured with an Eberline ESP 2 portable meter with BP-100 plastic detector following each exposure rate measurement.

Background values of 934 dpm/100cm2 for locations WSH001 - WSH016 and 2

527 dpm/100cm for locations WSH017 - WSH030 were applied to each reading to obtain net measurements. No individual measurement exceeded the administrative action level of 3750 dpm/100cm 2 The net average total surface activity for the survey unit was 79 dpm/100cm2 , and 125 dpm/100cm2 for the 95%

upper confidence level, which are below the release criterion of 5000 dpm/100cm 2, Smear samples were obtained following total surface activity measurements for each location. The smears were analyzed for gross alpha and gross beta activity. No smear sample exceeded the release criteria of 20 dpm/100cm2 for alpha and 1000 dpm/100cm2 for beta.

October 30,1996 l

TNPflNAL SURVEY REPORT FOR THE ISFSI SLT_E_ Paae 31 4.5 Survey Unit: TIA Survey Unit TIA is comprised of open land area, concrete pavement and utility structures within the defined survey area. Since the survey unit contains both open land and structural surfaces, 30 survey locations were randomly selected for soil sampling (TIA037 - TIA066), and 30 locations for surface activity measurements (TIA067 - -

TIA096). Gamma exposure rates were also measured at each of the 60 locations. The area was not physically gridded. A summary of the survey results is provided in Table 4-7 and discussed below. It is concluded from the survey results, that survey unit TlA meets the applicable release limits for unrestricted use.

4.5.1 Surface Scan Survey More than 25% of the open land area, and 100% of the concrete paved surfaces in the survey unit received a gamma scan survey, performed with an ESP-2 with SPA-8 detector, with 3000 cpm set as the level indicating potentially elevated radiation. The surface scans detected no areas of elevated radiation. The surface scan surveys are documented in the survey unit survey package.

4.5.2 Exposure Rates Gamma exposure rates were measured with a Reuter-Stokes RS-112 PIC and an Eberline ESP-2 portable meter with SPA-8 detector one meter from each measurement location. Only the PIC measurements are reported in the summary table and discussed here. Background values of 6.9 R/hr for locations TIA037- TIA066, and 7.3 R/hr for locations TIA067- TIA096 were applied to each survey to obtain net measurements. No individual exposure rate measurement exceeded the release criterion of 5 R/hr. The net average exposure rate for the survey unit was 0.6 R/hr, and 0.7 R/hr for the 95% upper confidence level.

4.5.3 Surface Activity Total beta surface activity was measured with an Eberline ESP-2 portable meter with BP-100 plastic detector following each exposure rate measurement. A background value of 1057 dpm/100cm2 was applied to each reading to obtain net measurements. No individual measurement exceeded the administrative action 2

level of 3750 dpm/100cm The net average total surface activity for the survey unit was -85 dpm/100cm2 , and -36 dpm/100cm2 for the 95% upper confidence level, which are below the release criterion of 5000 dpm/100cm 2 October 30,1996

TNP FINAL SURVEYREPORTFOR THEISFSISITE Page_3_2 Smear samples were obtained following total surface activity measurements for each location. The smears were analyzed for gross alpha and gross beta activity. No smear sample exceeded the release criteria of 20 dpm/100cm2 for alpha and 1000 dpm/100cm2 for beta.

4.5.4 Radionuclide Concentrations in Soil Cesium 137 was identified in the majority of the soil samples with gross activity ranging from MDA to 0.21 pCi/g. The net average Cs-137 concentration was 0.01 pCi/g, and 0.02 pCi/g for the 95% upper confidence level. No sample exceeded the action level for Cs-137 of 2.7 pCi/g or the release criterion of 10.7 pCi/g. Two samples initially reported Co-60 at greater than MDA (0.02 and 0.01 pCi/g), but were not confirmed on recounts. The average MDA for Co-60 for all the samples was 0.01 pCi/g, which is much less than the action level of 0.75 pCi/g.

Seven samples reported gross activity of Mn-54 above MDA, but within the same range of activity as background samples. The net activity for Mn-54 was zero for each of the seven samplec. Two samples reported Nb-95 activity above MDA (0.02 and 0.01 pCi/g), which were orders of magnitude less than the action level of 15.6 pCi/g and the release limit of 62.3 pCi/g. Only Cs-137 is reported, since the unity value for Cs-137/Nb-95 is miniscule (less than 0.0001).

Three samples were split with a contractor laboratory, and the split sample analysis results reported no radionuclides above the counting system MDAs.

Contractor verification analysis results are documented in the survey unit survey package.

4.6 Survey Unit: RWA Survey Unit RWA is comprised of the open land area, measuring 30 meters by 30 meters, upon which the Low Level Radioactive Waste Storage Building had previously sat. This is the only affected area survey unit The area was physically gridded into 10 meter by 10 meter sections. Four measurement locations were systematically selected within each of the 9 sections. A summary of the survey results is provided in Table 4-8 cnd discussed below. It is concluded from the survey results, that survey unit RWA meets the applicable release limits for unrestricted use.

4.6.1 Surface Scan Survey One hundred percent of the survey unit area received a gamma scan survey, performed with an ESP-2 with SPA-8 detector, with 3000 cpm set as the level October 30,1996 i

TNP FINAL SURVEY REPORT FOR THE ISFSI SITE Pace 33 indicating potentially elevated radiation. The exposure rate scan survey detected no areas of elevated radiation. The area was also 100% surface scan surveyed with the CM11 gas flow contamination counter, with no elevated radiation detected. The scan surveys is documented in the survey unit survey package.

4.6.2 Exposure Rates Gamma exposure rates were measured with a Reuter-Stokes RS-112 PIC and an Eberline ESP-2 portable meter with SPA-8 detector one meter from each measurement location. Only the PIC measurements are reported in the summary table and discussed here. A background value of 6.9 R/hr was applied to each survey to obtain net measurements. No individual exposure rate measurement exceeded the release criterion of 5 gR/hr. The net average exposure rate for the survey unit was 0.2 R/hr, and 0.3 uR/hr for the 95% upper confidence level.

4.6.3 Radionuclide Concentrations in Soil Cesium 137 was identified in the majority of the soil samples with gross activity ranging from MDA to 0.06 pCilg. The net average Cs-137 concentration was

-0.01 pCi/g, and -0.01 pCi/g for the 95% upper confidence level. No sample exceeded the action level for Cs-137 of 8.0 pCi/g or the release criteria of 10.7 pCi/g. The average MDA for Co-60 for all the samples was 0.01 pCi/g, which is much less than the action level of 2.3 pCi/g.

Three samples reported gross activity of Mn-54 above MDA, but within the same range of activity as background samples. The net activity for Mn-54 was zero for each of the three samples. Four samples reported Nb-95 activity above MDA (0.01 pCi/g each), and one sample reported Ru-103 activity above MDA I (0.006 pCi/g), which were orders of magnitude less than the action level for l

Nb-95 of 46.7 pCi/g and for Ru-103 of 69.5 pCi/g, and the release limits of 62.3 l and 93.0 pCi/g respectively. Only Cs-137 is reported, since the unity values for Cs-137/Nb-95 and Cs-137/Ru-103 are miniscule (less than 0.0001).

Six samples were split with a contractor laboratory, and the split sample analysis results reported no radionuclides above the counting system MDAs. Contractor verification analysis results are documented in the survey unit survey package.

October 30,1996

TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 34 TABLE 4-1 Background Values for Gamma Exposure Rates (uR/hr)

Material / Number of Mean Standard Maximum Minimum instrument Locations Result Deviation Result Result Concrete 30 7.3 0.4 7.9 6.4 Pavement with Plc Concrete 30 5.0 0.4 6.12 3.9 Pavement with ESP 2 Concrete 12 7.0 0.3 7.5 6.5 Floor with PIC Concrete 12 4.3 0.3 4.8 3.8 Floor with ESP 2 Gravel Soil 35 6.9 0.3 7.5 6.3 With Plc Gravel Soil 35 5.0 0.6 7.1 4.2 With ESP 2 Sheet Metal 28 4.4 0.3 5.0 3.5 Walls with ESP 2 Sheet Metal 7 3.8 0.6 4.6 2.9 Wallsm with EPS2 (1) Interior sheet metal walls covered with plastic surfaced fiber glass insulation.

October 30,1996 l

_a

TNP FINAL SURVEYREPORTFOR THEISFSISITE Paoe 35 TABLE 4-2 Background Total Surface Activity (dpm/100cm2)

Material W Mean Result Standard Maximum Minimum Type Deviation Result Result concrete 30 Beta: 1057 247 1444 574 Pavement Alphe: 39 10 64 21 concrete 12 Beta: 934 292 Floor 1664 455 Alpha: 38 26 113 21 Sheet Metal 28 Beta: 527 92 740 399 Walls Alpha: 112 38 174 33 Sheet Metal 7 Beta: 722 471 1736 264 Walls")

Alpha: 74 25 119 54 (1) Interior sheet metal walls covered with plastic surfaced fiber glass insulation.

October 30,1996

i TNP FINAL SURVEY REPORTFOR THE ISFSI SITE Paae 36 TABLE 4-3 Background Radionuclide Concentrations in Soil (pCi/ gram)

Radionuclide Number of Mean Standard Maximum Minimum i Locations Result Deviation Result Result l Cs-137 35 0.02 0.01 0.05 0.'01 Mn 54 35 <0.01 0.001 0.01 MDA Co-60 35 <0.01 0.001 MDA MDA Ce-144 35 <0.07 0.01 MDA MDA l i

^

October 30,1996 '

l l

l

TNP FINAL SURVEY REPORT FOR THE ISFSI SITE Paae 37 TABLE 4-4 Summary Results for Survey Unit BES Radiological Units N MDA Critical Mean Std Max UCL Parameter Level Dev (95%)

Gamma uR/hr 30 N/A N/A 1.2 0.3 1.8 1.3 Exposure Rate Total Beta dpm/100cm 2 30 226 110 188 197 673 249 '

Surface Activity Removable dpm/100cm2 30 6.8 3.4 7.2 1.5 13.3

~

7.7 Beta Surface Activity Removable dpm/100cm 2 30 6.2 5.5 6.2 0.0 6.2 N/A Alpha Surface Activity October 30,1996 l

l

TNP FINAL SURVEY REPORT FOR THE ISPSI SITE Pace 38 TABLE 4-5 Summary Results for Survey Unit NAM Radiological Units N MDA Critical Mean Std Max UCL Parameter Level Dev (95%)

Gamma uR/hr 30 N/A N/A 3.5 0.4 4.3 3.6 Exposure Rate Total Beta dpm/100cm' 30 226 110 -43 68 95 -22 Surface Activity Removable Beta dpm/100cm 2 30 8.3 4.2 8.3 0.0 8.3 N/A Surface Activity Removable dpm/100cm' 30 4.1 3.4 4.1 0.0 4.1 N/A Alpha Surface Activity 9

October 30,1996 i

A"

TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 39 TABLE 4-6 Summary Results for Survey Unit WSH Radiological Units N MDA Critical Mean Std Max UCL Parameter Level Dev (95%)

Gamma uR/hr 30 N/A N/A 2.6 0.4 3.4 Exposure Rate 2.7 Total Beta dpm/100cm 2 30 226 110 79 149 543 125 Surface Activity Removable dpm/100cm2 30 5.6 2.8 7.0 3.3 23.7 8.0 Beta Surface Activity Removable dpm/100cm 2 30 6.5 5.5 6.5 0.0 6.5 N/A Alpha Surface Activity October 30,1996

TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 40 TABLE 4-7 Summary Results for Survey Unit TIA Radiological Units N MDA Critical Mean Std Max UCL Parameter Level Dev (95%)

Gamma uR/hr 60 N/A N/A 0.6 .05 1.8 0.7 Exposure Rate Total Beta dpm/100cm 2 30 226 110 -85 156 79 -36 Surface Activity Removable dpm/100cm 2 30 8.0 4.0 8.0 0.0 8.0 N/A Beta Surface Activity Removable dpm/100cm 2 30 5.4 4.6 5.4 0.0 5.4 N/A Alpha Surface Activity Cs-137 Soil pCi/g 30 N/A N/A 0.01 0.04 0.19 0.02 Activity October 30,1996 I

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l TNP FINAL SURVEYREPORTFOR THEISFSISITE Paae 41 '

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TABLE 4-8 Summary Results for Survey Unit RWA Radiological Units N Mean Std Max UCL Parameter Dev (95%)

Gamma uR/hr 36 0.2 0.5 1.2 0.3 Exposure Rate i

Cs-137 Soil pCi/g 36 -0.01 0.01 0.04 -0.01 1 Activity '

i October 30,1996

f TNP FINAL SURVEY REPORT FOR THE ISPSI SITE Paae 42 5.0

SUMMARY

This report documents the final survey results of a small area of the Trojan site that is proposed for use as an ISFSI. It also documents the background characterization surveys performed to derive radiation background subtraction values. The survey area was divided into five survey units, and the collected survey data was analyzed, summarized and reported for each survey unit separately. The data presented in this report supports the conclusion that the survey area meets the criteria for reiease of the area from the requirements of 10 CFR 50 and for unrestricted use. It is noted, however, that about one third of the surveyed area will be dedicated to a future ISFSI under 10 CFR 72. The remainder of the surveyed area will have elevated background radiation levels due to fuel storage on the future ISFSI that will make a future final site release survey pursuant to 10 CFR 50 difficult.

The final survey of open land areas included the collection of 66 exposure rate measurements and 66 surface soils samples. All exposure rate measurements wore less than 5 R/hr above background. Analysis of the soil samples for the principal gamma emitters indicated that, after correction for environmental concentrations, no activity from licensed radionuclides exceeded any action level or release limit.

The final survey of surfaces and structures included 120 direct measurements for total surface activity,120 measurements for removable alpha and beta activity, and 120 measurements for exposure rates. All exposure rate measurements were less than 5 R/hr above background. All surface contamination measurements indicated no action levels or release limits were exceeded.

The final survey for the ISFSI site area was performed in accordance with the TNP Final Survey Plan For The ISFSI Site (Reference 1), and approved plant procedures. The implementation of the final survey plan and the results of the data acquired, analyzed and presented in this report demonstrate, with a high degree of confidence, that the criteria established for release of the defined area for unrestricted use have been satisfied.

October 30,1996 l

f TNP FINAL SURVEYREPORTFOR THEISFSISITE Paoe 43

{

6.0 REFERENCES

1. Trojan Nuclear Plant Final Survey for the ISFSI Site, PGE-1074, August 13, i 1996.

h

2. Trojan Nuclear Plant Radiological Site Characterization Report, Revision 0.1, 2/8/95. l

3. Trojan Nuclear Plant Decommissioning Plan, PGE-1061.

3

4. Regulatory Guide 1.86, Termination of Operating Licenses for Nuclear Reactors, i June 1974. '

5. NUREG-1500, Working Draft Regulatory Guide on Release Criteria for Decommissioning: NRC Staff's Draft for Comment,-August 1994. i

6. NCRP Report No. 58, A Handbook of Radioactivity Measurements Procedures, Second Edition,1985. '

' 7. NUREG/CR-5849, Manual for. Conducting Radiological Surveys in Support of i License Termination, June 1992 draft.

8. Trojan Nuclear Quality Assurance Program, PGE-8010. I l

9. TPP 20-2, Radiation Protection Program.

10 TPP 18-4, Nuclear Division Quality Assurance Records Management Program.

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i October 30,1996 ' l

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' APPENDIX A l SURVEY UNIT BES SURVEY DATA The following tables present data for each measurement and sample performed in the survey unit BES. The data were manually entered into a computer spreadsheet database from survey data collection sheets and sample analysis reports for statistical evaluation and report preparation.

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Table A-1 Survey Unit BES Gamma Exposure Rate Data (Units: pR/hr)

Location Net Location Net BES001 0.7 BES016 1.7 BES002 1.3 BES017 1.4 BES003 1.3 BES018 1.6 BES004 1.1 BES019 1.0 BES005 1.4 BES020 1.8 BES006 0.9 BES021 1.3 BES007 1.4 BES022 1.1 BES008 012 BES023 1.8 BES009 1.4 BES024 0.8 BES010 1.4 BES025 0.8 BES011 1.3 BES026 1.1 BES012 1.1 BES027 1.1 BES013 1.3 BES028 0.6 BES014 1.6 BES029 0.6 BES015 1.6 BES030 0.9 Total Points 30 Mean 1.2 Std Deviation 0.3 Min Value 0.6 Max Value 1.8 95% UCL 1.3

Table A-2 Survey Unit BES Surface Contamination Data (Units: dpm/100 cm2)

Direct Removable Direct Removable Location Beta Alpha Beta Location Beta Alpha Beta

~

BES001 20 <6.2 <6.8 BES016 375 <6.2 <6.8 BES002 -39 <6.2 <6.8 BES017 313 <6.2 <6.8 BES003 -33 <6.2 <6.8 BES018 439 <6.2 <6.8 BES004 70 <6.2 <6.8 BES019 563 <6.2 <6.8 BES005 55 <6.2 <6.8 BES020 219 <6.2 <6.8 BES006 -54 <6.2 <6.8 BES021 73 <6.2 <6.8 BES007 31 <6.2 <6.8 BESO22 663 <6.2 <6.8 BES008 21 <6.2 <6. 8 BES023 673 <6.2 <6.8 BES009 40 <6.2 <6. 8 BES024 298 <6.2 10.3 BES010 84 <6.2 <6.8 BES025 277 <6.2 10.3 BES011 111 <6.2 7.3 BES026 84 <6.2 <6.8 BES012 111 <6.2 <6.8 BES027 158 <6.2 <6. 8 BES013 156 <6.2 <6.8 BES028 246 <6.2 13.3 BES014 105 <6.2 <6. 8 BES029 260 <6.2 <6.8 BES015 25 <6.2 <6.8 BES030 294 <6.2 <6.8 Total Pts 30 30 30 Mean 188 <6.2 7.2 Std Dev 197 0.0 1.5 Min Value -54 <6.2 <6.8 Max Value 673 <6.2 13.3 95% UCL 249 N/A 7.7 l

APPENDlX B SURVEY UNIT NAM SURVEY DATA The following tables present data for each measurement and sample performed in the survey unit NAM. The data were manually entered into a computer spreadsheet database from survey data collection sheets and sample analysis reports for statistical .

cvaluation and report preparation. {

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Table B-1 Survey Unit NAM

, Gamma Exposure Rate Data (Units: pR/hr) l

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i Location Net Location Net ]

NAM 001 3.1 NAM 016 2.9 NAM 002 3.1 NAM 017 3.1 I 4

NAM 003 3.2 NAM 018 3.2 l NAM 004 3.6 NAM 019 3.0  !

! NAM 005 3.4 NAM 020 2.8 l NAM 006 3.6 NAM 021 3.8 '

NAM 007 4.0 NAM 022 3.4 ,

NAM 008 3.9. NAM 023 4.3 NAM 009 3.0 NAM 024 3.8 l NAM 010 3.7 NAM 025 3.7 I NAM 011 3.3 NAM 026 3.7  !

NAM 012 4.0 NAM 027 3.9 '

i NAM 013 3.2 NAM 028 3.6  ;

l:

NAM 014 4.1 NAM 029 3.3 NAM 015 2.4 NAM 030 3.6  :

i Total Points ' 30 l Mean 3.5  ;

! Std Deviation 0.4 j I Low Value 2.4 High Value

~

4.3

! 95% UCL 3.6  ;

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Table B-2 Survey Unit NAM Surface Contamination Data (Units: dpm/100 cm2)

Direct Removable Direct Removable Location Beta Alpha Beta Location Beta Alpha Beta NAM 001 -43 <4.1 <8.3 NAM 016 -49 <4.1 <8.3 NAM 002 -90 <4.1 <8.3 NAM 017 62 <4.1 <8.3 NAM 003 -45 <4.1 <8.3 NAM 018 -152 <4.1 <8.3 NAM 004 -71 <4.1 <8.3 NAM 019 95 <4.1 <8.3 NAM 005 -83 <4.1 <8.3 NAM 020 79 <4.1 <8.3 NAM 006 -56 <4.1 <8.3 NAM 021 19 <4.1 <8.3 NAM 007 -135 <4.1 <8.3 NAM 022 -145 <4.1 <8.3 NAM 008 -131 <4.1 <8.3 NAM 023 -61 <4.1 <8.3 NAM 009 -88 <4.1 <8.3 NAM 024 46 <4.1 <8.3 NAM 010 -88 <4.1 <8.3 NAM 025 11 <4.1 <8.3 NAM 011 -91 <4.1 <8.3 NAM 026 -16 <4.1 <8.3 NAM 012 -63 <4.1 <8.3 NAM 027 59 <4.1 <8.3 NAM 013 -91 <4.1 <8.3 NAM 028 -24 <4.1 <8.3 NAM 014 -80 <4.1 <8.3 NAM 029 12 <4.1 <8.3 NAM 015 -76 <4.1 <8.3 NAM 030 15 <4.1 <8.3 Total Pts 30 30 30 Mean -43 4.1 8.3 Std Dev 68 0.0 0.0 Min Value -152 <4.1 <8.3 Max Value 95 <4.1 <8.3 95% UCL -22 N/A N/A l

APPENDIX C SURVEY UNIT WSH SURVEY DATA The following tables present data for each measurement and sample performed in the survey unit WSH. The data were manually entered into a computer spreadsheet database from survey data collection sheets and sample analysis reports for statistical evaluation and report preparation.

, Table C-1 Survey Unit WSH Gamma Exposure Rate Data (Units: pR/hr)

~

Location Net Location Net WSH001 2.6 WSH016 3.0 WSH002 2.6 WSH017 2.1 WSH003 2.4 WSH018 1.9 WSH004 2.9 WSH019 2.8 4

WSH005 3.4 WSH020 1.8 WSH006 3.2 WSH021 1.7 WSH007 2.6 WSH022 2.0 WSH008 2.6 WSH023 1.9 WSH009 2.7 WSH024 2.5 WSH010 2.8 WSH025 2.7 WSH011 2.9 WSH026 2.7 WSH012 2.9 WSH027 2.8 WSH013 2.7 WSH028 2.7 WSH014 3.1 WSH029 2.5 WSH015 3.1 WSil030 2.8 Total Points 30 Mean 2.6 Std Deviation 0.4 l Low Value 1.7 High Value 3.4  !

95% UCL 2.7 1

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Table C-2 Survey Unit WSH Surface Contamination Data (Units: dpm/100 cm2)

Direct Removable Direct Removable Location Beta Alpha Beta Location Beta Alpha Beta WSH001 116 <6.5 <5.6 WSH016 -107 <6. 5 7.3 WSH002 -178 <6. 5 6.7 WSH017 226 <6.5 6.1 WSH003 176 <6.5 <5.6 WSH018 543 <6.5 7.0 WSH004 -47 <6.5 <5.6 WSH019 232 <6.5 <5.6 WSH005 -62 <6.5 <5.6 WSH020 206 <6.5 <5.6 WSH006 -36 <6.5 6.4 WSH021 40 <6.5 <5.6 WSH007 -39 <6.5 6.7 WSH022 -51 <6.5 6.7 WSH008 76 <6.5 8.2 WSH023 -14 <6.5 <5.6 WSH009 86 <6.5 <5.6 WSH024 167 <6.5 6.7 WSH010 55 <6.5 <5.6 WSH025 37 <6.5 <5.6 WSH011 -35 <6.5 <5.6 WSH026 142 <6.5 7.9 WSH012 6 <6.5 9.4 WSH027 206 <6.5 <5.6 WSH013 -2 <6.5 6.1 WSH028 104 <6.5 6.7 WSH014 -43 <6.5 <5.6 WSH029 329 <6. 5 23.7 WSH015 -16 <6.5 8.8 WSH030 239 <6.5 <5.6 Total Pts 30 30 30 Mean 79 6.5 7.0 Std Dev 149 0.0 3.3 Min Value -178 <6.5 <5.6 Max Value 543 <6.5 23.7 95% UCL 125 N/A 8.0 l

I APPENDIX D SURVEY UNIT TIA SURVEY DATA The following tables present data for each measurement and sample performed in the survey unit TlA. The data were manually entered into a computer spreadsheet database from survey data collection sheets and sample analysis reports for statistical evaluation and report preparation.

0 P

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Table D-1 '

Survey Unit TIA Gamma Exposure Rate Data (Units: pR/hr) 4 4 Location Net Location Net Location Net

TIA037 0.8 TIA057 1.2 TIA077 0.0 TIA038 0.9 TIA058 -0.2 TIA078 0.8

TIA039 0.9 TIA059 -0.3 TIA079 0.4 TIA040 0.9 TIA060 0.7 TIA080 0.2 TIA041 1.1 TIA061 0.0 TIA081 0.4  !

TIA042 1.2 TIA062 0.8 TIA082 0.3 TIA043 1.8 TIA063 0.7 TIA083 0.3  :

TIA044 0.3 TIA064 0.5 TIA084 -0.3  ;

TIA045 0.7 TIA065 0.3 TIA085 0.3

. TIA046 0.9 TIA066 1.1 TIA086 0.4 TIA047 1.6 TIA067 1.0 T!A087 0.6 TIA048 1.0 TIA068 0.9 TIA088 -0.3 TIA049 0.5 TIA069 0.7 TIA089 0.0 TIA050 1.4 TIA070 0.7 TIA090 0.5 TIA051 1.0 TIA071 0.7 TIA091 0.4 i TIA052 1.1 TIA072 0.8 TIA092 0.5 TIA053 -0.1 TIA073 0.8 TIA093 0.7 TIA054 0.2 TIA074 0.3 TIA094 1.0 TIA055 0.5 TIA075 0.1 TIA095 1.1  :

TIA056 0.7 TIA076 0.6 TIA096 0.9 Total Points 60 Mean 0.6 Std Deviation 0.5 Low Value -0.3 l

High Value 1.8 i 95% UCL 0.7 i

Table D-2 Survey Unit TIA Soil Activity Concentration Data (Units: pCl/g)

Cs-137 Reference MDAs Cs-137 Reference MDAs ,

Location Net Co-60 Ce-144 Location Net Co-60 Ce-144 i TIA037 0.01 0.01 0.08 TIA052 -0.01 0.01 0.07 TIA038 -0.01 0.01 0.07 TIA053 0.01 0.01 0.09 j TIA039 0.02 0.01 0.08 TIA054 0.01 0.01 0.09 l TIA040 0.03 0.01 0.09 TIA055 -0.01 0.01 0.08 TIA041 0.02 0.01 0.09 TIA056 -0.01 0.01 0.07 i

TIA042 -0.01 0.01 0.08 TIA057 0.12 0.01 0.08 TIA043 -0.01 0.01 0.09 TIA058 -0.01 0.01 0.07

TIA044 0.00 0.01 0.08 TIA059 -0.01 0.01 0.08 TIA045 -0.01 0.01 0.08 TIA060 0.01 0.01 0.08 TIA046 0.04 0.01 0.09 TIA061 0.04 0.01 0.09 TIA047 -0.01 0.01 0.08 TIA062 -0.01 0.01 0.08 TIA048 -0.01 0.01 0.10 TIA063 -0.01 0.01 0.08 TIA049 0.00 0.01 0.08 TIA064 0.19 0.01 0.10 i TIA050 -0.01 0.01 0.09 TIA065 0.01 0.01 0.07 TIA051 0.02- 0.01 0.08 TIA066 0.00 0.01 0.09 Total Pts 30 Mean 0.01 Std Dev 0.04 Low Value -0.01 I High Value 0.19 95% UCL 0.02 1

Table D-3 Survey Unit TIA Surface Contamination Data (Units: dpm/100 cm2 )

Direct Removable Direct Removable Location Beta Alpha Beta Location Beta Alpha Beta TlA067 75 <5.4 <8.0 TIA082 -175 <5.4 <8.0 TIA068 43 <5.4 <8.0 TIA083 1 <5.4 <8.0 TIA069 7 <5.4 <8.0 TIA084 -80 <5.4 <8.0 TIA070 79 <5.4 <8.0 TIA085 -143 <5.4 <8.0 TIA071 -29 <5.4 <8.0 TIA086 -143 <5.4 <8.0 TIA072 51 <5.4 <8.0 TIA087 -233 <5.4 <8.0 TIA073 -76 <5.4 <8.0 TIA088 -586 <5.4 <8.0 TIA074 -102 <5.4 <8.0 TIA089 -534 <5.4 <8.0 TIA075 41 <5.4 <8.0 TIA090 -46 <5.4 <8.0 TIA076 -9 <5.4 <8.0 TIA091 -26 <5.4 <8.0 TIA077 -200 <5.4 <8.0 TIA092 -88 <5.4 <8.0 TIA078 7 <5.4 <8.0 TIA093 -131 <5.4 <8.0 TIA079 -54 <5.4 <8.0 TIA094 -58 <5.4 <8.0 TIA080 -9 <5.4 <8.0 TIA095 -216 <5.4 <8.0 TIA081 47 <5.4 <8.0 TIA096 51 <5.4 <8.0 Total Pts 30 30 30 Mean -85 <5.4 <8.0 Std Dev 156 0.0 0.0 Min Value -586 <5.4 <8.0 Max Value 79 <5.4 <8.0 95% UCL -36 N/A N/A

APPENDIX E SURVEY UNIT RWA SURVEY DATA The following tables present data for each measurement and sample performed in the survey unit RWA. The data were manually entered into a computer spreadsheet database from survey data collection sheets and sample analysis reports for statistical cvaluation and report preparation.

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1 Table E-1 l

j. Survey Unit RWA l Gamma Exposure Rate Data i j -.(Units: pR/hr) l

! I Location Net l Location Net l

] RWA 001 0.0 .l RWA 019 0.1  !

j RWA 002 -0.4 l RWA 020 -0.4 l

RWA 003 -0.6 l RWA 021 0.0  !

. RWA 004 -0.5 l RWA 022 0.8 i j RWA 005 -0.5 l RWA 023 0.6  ;

RWA 006 0.0 l RWA 024 0.3 l RWA 007 -0.6 l RWA 025 0.5 l l RWA 008 -0.3 l RWA 026 0.4 j l RWA 009 -0.2 l RWA 027 0.8 l

l RWA 010 0.5 l RWA 028 1.2 l

RWA 011 0.2 l RWA 029 0.5 j j RWA 012 0.1 l RWA 030 0.6  ;

} RWA 013 0.0 l RWA 031 0.3 l l

f RWA 014 -0.5 RWA 032 0.3

] RWA 015 -0.1 l RWA 033 0.5

RWA 016 0.7~ l RWA 034 0.8 f RWA 017 -0.3 l RWA 035 0.8 l-RWA 018 -0.4 l RWA 036 0.3  !

j l Total Points 36 ,

j~ l Mean 0.2  :

. l Std Deviation 0.5 l Low Value -0.6

! l High Value 1.2 f l 95% UCL 0.3 i c-l i

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f Table E-2 Survey Unit RWA Soil Activity Concentration Data (Units: pC!/g)

Cs-137 Reference MDAs Cs-137 Reference MDAs Location Net Co-60 Ce-144 Location Net Co-60 Ce-144 RWA 001 0.03 0.01 0.07 L RWA 019 0.00 0.01 0.07 RWA 002 -0.01 0.01 0.08 RWA 020 -0.01 0.01 0.07 RWA 003 -0.01 0.01 0.07 RWA 021 -0.01 0.01 0.06 RWA 004 -0.01 0.01 0.08 RWA 022 -0.01 0.01 0.07 RWA 005 -0.01 0.01 0.07 RWA 023 0.02 0.01 0.07 RWA 006 -0.01 0.01 0.07 RWA 024 -0.01 0.01 0.08 RWA 007 -0.01 0.01 0.06 RWA 025 0.00 0.01 0.07 RWA 008 -0.01 0.01 0.07 RWA 026 -0.01 0.01 0.07 RWA 009 -0.01 0.01 0.06 RWA 027 -0.01 0.01 0.08 RWA 010 0.04 0.01 0.08 RWA 028 -0.01 0.01 0.08 RWA 011 0.00 0.01 0.07 RWA 029 -0.01 0.01 0.06-RWA 012 -0.01 0.01 0.07 RWA 030 -0.01 0.01 0.07 RWA 013 -0.01 0.01 0.07 RWA 031 -0.01 0.01 0.07 RWA 014 -0.01 0.01 0.06 RWA 032 -0.01 0.01 0.07 RWA 015 -0.01 0.01 0.07 RWA 033 -0.01 0.01 0.07 RWA 016 -0.01 0.01 0.06 RWA 034 -0.01 0.01 0.08 RWA 017 0.01 0.01 0.07 RWA 035 -0.01 0.01 0.07 RWA 018 0.00 0.01 0.07 RWA 036 -0.01 0.01 0.07 Total Pts 36 Mean -0.01

[ Std Dev 0.01 Low Value -0.01 High Value 0.04 95% UCL -0.01

I APPENDIX F BACKGROUND RADIATION SURVEY DATA The following tables present data for each background measurement and sample performed. The data were manually entered into a computer spreadsheet database from survey data collection sheets and sample analysis reports for statistical evaluation .

and report preparation. I i

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Table F-1 Background Radiation Survey Open Land Areas - Soil / Gravel Fill Gamma Exposure Rate Data (Units: pR/hr)

Location PIC ESP 2 Location PIC ESP 2 AY001 6.9 4.6 YYO18 73 5.6 AYOO2 6.4 4.7 YYO19 7.2 5.4 AYOO3 6.3 5.1 YYO20 6.9 5.0 AYOO4 6.7 4.8 YYO21 6.8 4.7 AY005 6.8 4.5 YYO22 7.2 5.3 AY006 6.5 4.2 YYO23 7.2 5.2 AY007 6.5 4.3 YYO24 7.0 4.9 AY008 6.8 5.0 YYO25 6.7 4.6 AY009 6.9 4.8 YYO26 7.2 5.4 AYO10 7.0 4.7 YYO27 6.8 4.5 SYO11 7.2 6.8 YYO28 7.0 4.7 SYO12 6.8 5.1 YYO29 6.9 4.9 SY013 6.6 4.6 YYO30 7.2 4.9 SYO14 6.9 52 MM031 7.2 5.1 SYO15 7.5 7.1 MM032 6.7 4.8 YY016 6.8 .:. 8

. MM033 6.8 4.9 YYO17 71 5.5 MM034 7.2 5.8 MM035 6.6 5.0 Total Points 35 35 Mean 6.9 5.0 Std Deviation 0.3 0.6 Low Value 6.3 4.2 High Value 7.5 7.1

1 Table F-2 Background Radiation Survey Open Land Areas - Soil / Gravel Fill Soil Activity Concentration Data (Units: pCi/g)

Location Cs-137 Mn-54 Co-60 Ce-144 Location Cs-137 Mn-54 Co40 Ce-144 AY001 0.01 <0.01 <0.01 <0.07 YYO18 0.04 <0.01 <0.01 <0.07 l

, AYOO2 0.01 <0.01 <0.01 <0.07 YYO19 0.01 <0.01 <0.01 <0.07 l AYOO3 0.01 0.01 <0.01 <0.07 YYO20 0.02 <0.01 <0.01 <0.07 AYOO4 0.01 <0.01 <0.01 <0.07 YYO21 0.01 <0.01 <0.01 <0.07 AY005 0.01 <0.01 <0.01 <0.07 YYO22 0.03 <0.01 <0.01 <0.07 )

AY006 0.01 <0.01 <0.01 <0.07 YYO23 0.03 <0.01 <0.01 <0.07 I

AYOO7 0.01 <0.01 <0.01 <0.07 YYO24 0.01 <0.01 <0.01 <0.07 AY008 0.01 0.01 <0.01 <0.07 YYO25 0.05 <0.01 <0.01 <0.07 AYOO9 0.01 <0.01 <0.01 <0.07 YY026 0.01 0.01 <0.01 <0.07 AYO10 0.01 0.01 <0.01 <0.07 YYO27 0.03 <0.01 <0.01 <0.07 SYO11 0.02 <0.01 <0.01 <0.07 YYO28 0.03 <0.01 <0.01 <0.07 I SYO12 0.02 <0.01 <0.01 <0.07 YYO29 0.02 <0.01 <0.01 <0.07 SY013 0.02 <0.01 <0.01 <0.07 YYO30 0.02 <0.01 <0.01 <0.07

SYO14 0.05 <0.01 <0.01 <0.07 MM031 0.04 0.01 <0.01 <0.07

. SYO15 0.02 0.01 <0.01 <0.07 MM032 0.02 <0.01 <0.01 <0.07 YYO16 0.01 <0.01 <0.01 <0.07 MM033 0.03 <0.01 <0.01 <0.07 YYO17 0.02 <0.01 <0.01 <0.07 MM034 0.03 0.01 <0.01 <0.07 MM035 0.05 <0.01 <0.01 <0.07 Tot Pts 35 35 35 35 Mean 0.02 <0.01 <0.01 <0.07 Std Dev 0.01 0.001 0.001 0.01 Low 0.01 <0.01 <0.01 <0.01

]

High 0.05 0.01 <0.01 <0.01 4

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4 Table F-3

Background Radiation Survey Asset Recovery Building Interior Surfaces .

Gamma Exposure Rate Data J j (Units: pR/hr).

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Concrete Floors Insulated Sheet Metal Walls  !

Location PIC ESP 2 l Location PIC ESP 2  !

INO36 7.0 4.4 l lNO39 5.9 3.2 i

! INO38 6.8 4.2 l lN041 6.9 4.1 l j IN040 6.8 4.3 l lN042 6.4 3.6 i j lN043 6.7 4.0 l lN046 6.1 2.9 l IN044 7.1 4.3 l lN049 6.7 3.8 j

IN045 6.5 3.8 l IN053 7.1 4.3 j .IN048 7.0 4.5 l lN055 6.9 4.6 .

l lN050 7.3 4.8 l Total Points 7 7 l l'

lN052 7.5 4.6 l Mean 6.6 3.8 IN054 7.0 4.3 l Std Deviation 0.4 0.6 IN061 6.8- 4.2 l Low Value 5.9 2.9 IN064 6.9 4.4 l High Value. 7.1 4.6 ,

Total Points 12 12 l f Mean 7.0 4,3 l l Std Deviation 0.3 0.3 l Low Value 6.5 3.8 l ,

High Value 7.5 4.8 l l i

1 1

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Table F-3 (continued)

Background Radiation Survey Asset Recovery Building Interior Surfaces Gamma Exposure Rate Data (Units: pR/hr)

Shestrocked Sheet Metal Walls Location PIC ESP 2 INO37 6.8 3.9 IN047 6.9 4.2 IN051 7.0 4.4 IN057 6.6 3.9 IN060 6.7 3.5 IN062 6.4 3.9 IN063 6.7 3.9 IN065 6.8 4.3 Total Points 8 8 Mean 6.7 4.0 Std Deviation 0.2 0.3 Low Value 6.4 3.9 High Value 7.0 4.4 WIu4II 1

Table F-4 Background Radiation Survey Asset Recovery Building Interior Surfaces Surface Contamination Data (Units: dpm/100 cm2)

Concrete Floors in; mated Sheet Metal Walls Direct l Removable Direct Removable Location Alpha Beta /ipha Beta Location Alpha Beta Alpha Beta INO36 33 925 <4.1 <8.0 IN039 67 1736 <4.1 <8.0 INO38 26 1664 <4.1 <8.0 IN041 61 522 <4.1 <8.0 IN040 23 996 <4.1 <8.0 IN042 62 264 <4.1 <8.0 IN043 28 822 <4.1 <8.0 IN046 54 558 <2.9 <8.0 IN044 23 835 <4.1 <8.0 IN049 57 587 <2.9 <8.0 IN045 27 862 <4.1 <8. 0 IN053 101 738 <2.9 <8.0 IN048 30 898 <2.9 <8.0 IN055 119 650 <2.9 <8.0 IN050 23 873 <2.9 <8.0 Total Pts 7 7 7 7 IN052 56 1232 <2.9 <8.0 Mean 74 722 <4.1 <8.0 IN054 21 810 <2.9 <8.0 Std Dev 25 471 0.0 0.0 IN061 51 807 <2.9 <8.0 Lo Value 54 264 <2.9 <8.0 IN064 113 455 <2.9 <8.0 Hi Value 119 1736 <4.1 <8.0

~

Total Pts 12 12 12 12 Mean 38 934 <4.1 <8.0 Std Dev 26 292 0.0 0.0 Lo Value 21 455 <2.9 <8.0 Hi Value 113 1664 <4.1 <8.0 f

f

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Table F-4 (cont:nued)

Background Radiation Survey Asset Recovery Building Interior Surfaces Surface Contamination Data (Urats: dpm/100 cm')

Sheatrocked Sheet Metal Walls Direct Removable Location Alpha Beta Alpha Beta INO37 73 529 <4.1 <8.0 IN047 52 481 3.6 <8.0 IN051 56 538 <2.9 <8.0 IN057 108 538 <2.9

<6.')]

IN060 78 555 <2.9 <8.0 IN062 75 506 <2.9 <E '

IN063 47 828 <2.9 <870 IN065 110 587 <2.9 <8.0 Total Pts 8 8 8 8 Mean 75 570 <4.1 <8.0 Std Dev 24 109 0.0 0.0 Lo Value 47 481 <2.9 <8.0 Hi Value 110 828 <4.1 <8.0 f

I

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1 Table F-5 Background Radiation Survey Asset Recovery Building Exterior Surfaces Garrima Exposure Rate Data (Units: pR/hr)

Sheet Metal Walls Locatior. ESP 2 Location ESP 2 OSO6~ 4.3 OS082 4.4 OS068 4.8 OS083 4.7 OS069 4.4 OS084 4.5

~

OS070 4.8 OS085 4.6 OS071 4.2 OS086 4.7 OS072 4.6 OS087 4.4 OS073 4.4 OS088 4.7 OS074 4.4 OS089 4.7 OS075 4.3 OSO90 5.0 OS076 4.3 OS091 4.6 OS077 4.2 OSO92 4.7 OS078 4.1 OS093 4.3 OS079 4.4 OSO94 3.5 OS080 4.5 OSO95 4.1 Total Points 28 Mean 4.4 Std Deviation 0.3 Low Value 3.5 High Value 5.0

Table F-6 Backpround Radiation Survey Asset Recesvery Building Exterior Surfaces Surface Contamination Data (Units: dpm/100 cm2)

Sheet Metal Walls Direct Removable Direct Removable Location Alpha Beta Alphe Beta Location Alpha Beta Alpha Beta OS067 89 434 <G.2 <7.0 OS082 127 517 <6.2 <7.0 OS068 113 516 <6.2 <7.0 OS083 150 620 <6.2 <7.0 OS069 108 399 <6.2 <7.0 OS084 113 665 <6.2 <7.0 OS070 33 407 <6.2 <7.0 OS085 145 532 <6.2 <7.0 OS071 94 534 <6.2 <7.0 OS086 113 702 <6.2 <7. 0 OS072 117 518 <6.2 <7.0 OS087 127 730 <6.2 <7.0 OS073 113 465 <6.2 <7.0 OS088 159 740 <6.2 <7.0 OS074 131 509 <6.2 <7.0 OS089 174 575 <6.2 <7. 0

~

OS075 136 494 <6.2 l <7.0 OS090 70 567 <6.2 <7.0 OS076 122 427 <6.2 ' <7.0 OS091 169 567 <6.2 <7.0 OS077 33 484 <6.2 <7.0 OSO92 66 519 <6.2 <7.0 OS078 94 467 <6.2 <7.0 OS093 141 483 <6.2 <7.0 OS079 38 464 <6.2 <7.0 OS094 84 448 <6.2 7.6 OS080 127 495 <6.2 <?.0 OSO95 141 465 <6.2 <7. 0 Total Pts 28 28 28 28 Mean 112 527 <6.2 <7.6 Std Dev 38 92 0.0 0.0 Lo Value 33 399 <6.2 <7.0 Hi Value 174 740 <6.2 7.6

Table F-7 Background Radiation Survey Outside Trojan North Building - Concrete Surfaces Gamma Exposure Rate Data (Units: pR/hr)

Location PIC ESP 2 Location PIC ESP 2 TN001 6.4 4.2 TN016 7.2 5.0 TN002 6.8 4.7 TN017 7.3 5.1 TN003 7.1 5.0 TN018 7.6 5.1 TN004 7.3 5.2 TN019 7.4 4.9 TN005 7.4 5.6 TN020 7.6 5.0 TN006 7.7 5.5 TN021 7.4 4.5 TN007 7.9 5.4 TN022 7.7 4.9 TN008 7.3 5.0 TN023 7.2 5.2 TN009 7.7 5.2 TN024 7.3 3.9 TN010 7.3 4.8 TN025 7.2 4.4 TN011 7.6 5.0 TN026 6.6 4.8 TN012 7.4 5.2 TN027 6.4 5.3 TN013 7.6 5.4 TN028 7.4 4.5 TN014 7.9 6.1 TN029 7.5 5.1 TN015 7.5 4.6 TNO30 7.2 4.7 Total Points 30 30 Mean 7.3 5.0 Std Deviation 0.4 0.4 Low Value 6.4 3.9 High Value 7.9 6.1 l

i

Table F-8 Background Radiation Survey Outside Trojan North Building - Concrete Surfaces Surface Contamination Data (Units: dpm/100 cm')

Direct Removable Direct Removable Location Alpha Beta Alpha Beta Location Alpha Beta Alpha Beta TN001 39 904 <4.6 <8.0 TN016 23 1320 <4.6 <8.0 TN002 35 894 <4.6 <8.0 TN017 21 1384 <4.6 <8.0 TN003 di 986 <4.6 <8.0 TN018 26 1354 <4.6 <8.0 TN004 35 1013 <4.6 <8.0 TN019 35 1444 <4.6 <8.0 TN005 41 1036 <4.6 <8.0 TN020 52 1346 <4.6 <8.0 TN006 39 1056 <4.6 <8.0 TN021 42 951 <5.8 <8.0 TN007 31 1056 <4.6 <8.0 TN022 51 900 <5.8 <8.0 TN008 43 1013 <4.6 <8.0 TN023 56 848 <5.8 <8.0 TN009 26 1184 <4.6 <8.0 TN024 47 G3 <5.8 <8.0 TN010 47 1250 <4.6 <8.0 TN025 64 643 <5.8 <8.0 TN011 30 1262 <4.6 <8.0 TN026 48 818 <5.8 <8.0 TN012 28 1232 <4.6 <8.0 TNO27 54 687 <5.8 <8.0 TN013 30 1302 <4.6 <8.0 TN028 37 574 <5.8 <8.0 TN014 27 1350 <4.6 <8.0 TN029 42 748 <5.8 <8.0 TN015 37 1376 <4.6 <8.0 TN030 42 947 <5.8 <8.0 Total Pts 30 30 30 30 f Mean 39 1057 <5.8 <8.0 Std Dev 10 247 0.0 0.0 f Lo Value 21 574 <4.6 <8.0 Hi Value 64 1444 <5.8 <8.0

{

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I Table F-9 Background Radiation Survey Outside Trojan North Building - Asphalt Pavement Gamma Exposure Rate Data (Units: pR/hr)

Location PIC ESP 2 l Location PIC ESP 2 TNO31 6.3 3.4 l TN046 6.3 3.8 TNO32 6.1 3.6 l TN047 6.5 3.5 k TNO33 6.5 3.4 l TN048 6.2 3.5 TNO34 6.3 3.5 l TN049 6.0 3.7 TNO35 6.3 3.5 l TN050 6.0 3.8 TNO36 6.8 3.8 l TN051 - 6.0 3.6 TNO37 6.4 3.6 l TN052 6.7 3.6 TNO38 6.3 4.0 l TN053 6.3 3.8

-TNO39 6.4 3.7 l TN054 6.6 3.7 l

TN040 7.5 3.9 TN055 6.3 3.8 TN041 6.5 3.8 l TN056 6.4 3.7

. TN042 6.2 3.4 l TN057 S.8 4.0 TN043 S.2 l

3.7 l TN058 6.5 3.7 TN044 6.3 3.6 l TN059 6.6 3.9

.TN045 6.7 3.6 l TN060 6.6 4.0 l Total Points 30 30 l Mean 6.4 3.7 f l Std Deviation 0.3 0.2 l Low Value 6.0 3.4

[ l High Value 7.5 4.0

(

Table F-10 Background Radiation Survey l Outside Trojan North Building - Asphalt Pavement I Surface Contamination Data (Units: dpm/100 cm )

l Direct Removable Direct Removable Location Alpha l Beta Alpha Beta Location Alpha Beta Alpha Beta TNO31 36 938 <5.8 <8.0 TN046 44 906 <5.8 <8.0 TNO32 35 935 <5.8 <8.0 TN047 57 920 <5.8 <8.0 TNO33 37 964 < 5. 8 <8.0 TN048 47 950 <5.8 <8.0 TNO34 33 1026 <5.8 <8.0 TN049 32 952 < 5.8 <8.0 TN035 42 974 <5.8 <8.0 TN050 34 1015 < 5. 8 <8.0 i TNO36 43 956 <5.8 <8.0 TN051 37 1142 <5.8 <8.0 TNO37 33 1023 <5.8 <8.0 TN052 51 1210 <5.8 <8.0 TNO38 27 998 < 5. 8 <8.0 TN053 33 1220 <5.8 <8.0 TNO39 37 1010 <5.8 <3.0 TN054 41 1240 <5 3 <8.0 TN040 32 918 <5. 8 <8.0 TN055 42 1238 <5.8 <8.0 TN041 37 895 <5.8 <8.0 TN056 51 1314 <5.8 <8.0 TN042 37 934 <5.f <8.0 TN057' 37 1210 <5.8 <8.0 TN043 37 915 <5 3 <8.0 TN058 43 1186 <5.8 <8.0 TN044 46 924 (5.8 <8.0 TN059 33 1176 <5.8 <8.0 TN045 35 879 E5.8 <8.0 TN060 36 1244 <5.8 <8.0

== .

Total Pts 30 30 30 30 Mean 39 1040 <5.8 <8.0 Std Dev 7 135 0.0 0.0 Lo Value 27 879 <5.8 <8.0 I Hi Value 57 1314 < 5. 8 <8.0 i

l l

l 1

1 Table F-11 Background Radiation Survey Trojan North Building Exterior Surfaces Gamma Exposure Rate Data (Units: pR/hr)

Window Glass Concrete Walls Location PIC ESP 2 Location PIC ESP 2 TN061 7.5 5.4 TN062 7.8 5.8 TN063 8.0 5.7 TN068 7.4 5.6 TN067 8.2 5.7 TN071 7.7 5.4 TN069 7.4 5.2 TN074 7.5 5.7 TN070 7.5 5.7 TN076 7.6 5.1 TN072 8.0 6.0 TN083 7.4 5.4 TN073 7.4 5.3 TN085 7.4 5.6 TN075 7.4 5.6 TN086 7.3 6.0 TN077 7.2 5.4 TN088 7.1 6.2 TN078 7.4 5.3 TN090 7.3 6.2 TN079 7.8 5.4 Total Points 10 10 TN080 7.3 5.4 Mean 7.5 5.7 TN081 7.5 5.3 Std Deviation 0.2 0.4 TN082 7.2 6.0 Low Value 7.1 5.1 TN084 7.2 5.9 High Value 7.8 6.2 TN087 6.9 5.8 TN089 7.4 6.2 Total Points 17 17 Mean 7.5 5.6 Std Deviation 0.3 0.3 Low Value 6.9 5.2 High Value 8.2 6.2

Table F-11 (continued)

Background Radiation Survey Trojan North Building Exterior Surfaces Gamma Exposure Rate Data (Units: pR/hr)

Ceramic Tile Walls Location PIC ESP 2 TN064 8.6 6.2 TN065 7.8 6.1 TN066 7.9 6.1 Total Points 3 3 Mean 8.1 6.1 Std Deviation 0.4 0.1 Low Value 7.8 6.1 High Value 8.6 6.2

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Table F-12 Background Radiation Survey Trojan North Building Exterior Surfaces Surface Contamination Data (Units: dpm/100 cm')

. Window Glass l Concrete Walls Direct Removable l Direct Removable Location Alpha Beta Alpha Beta l Location Alpha Beta Alpha Beta l TN061 73 579 <5.4 <8.1 l TN062 80 915 <5.4 <8.1 TN063 69 747 <5.4 <8.1 l TN068 64 918 <5.4 <8.1 TN067 74 794 <5.4

( <8.1 l TN071 61 854 <5.4 <8.1 TN069 70 596 <5.4 <8.1 l TN074 66 945 <5.4 <8.1

~

TN070 59 753 <5.4 <8.1 l TN076 66 916 <5.4 <8.1 TN072 83 701 <5.4 <8.1 l TN083 77 768' <5.4 <8.1 TN073 90 730 <5.4 <8.1 l TN085 64 682 <5.4 <8.1 TN075 47 644 <5.4 <8.1 l TN086 60 690 <5.4 <8.1 TN077 67 735- <5.4 <8.1 l TN088 77 911 <5.4 <8.1

f. TN078 77 700 <5.4 <8.1 lTN090 68 723 <5.4 <8.1 TN079 79 687 <5.4 <8.1 l Total Pts 10 10 10 10 f TN080. 83 715 <5.4 <8.1 l Mean 68 832 <5.4 <8.1 TN081 61 571 <5.4 <8.1 l Std Dev 7 105 0.0 0.0

( TN082 49 599 <5.4 <8.1 l Lo Value 60 682 <5.4 <8.1 TN084 74 709 <5.4 <8.1 l Hi Value 80 945 <5.4 <8.1

{ TN087 75 679 <5.4 <8.1 l TN089 58 727 <5.4 <8.1 l

[ Total Pts 17 17 17 17 l Mean 70 686 <5.4 <8.1 l Std Dev 12 66 0.0 0.0 l

{

Lo Value 47 571 <5.4 <8.1 l Hi Value 90 794 <5.4 <8.1 l

{

k N

l Table F-12 (continued)

Background Radiation Survey Trojan North Building Exterior Surfaces l Surface Contamination Data (Units: dpm/100 cm2)

Ceramic Tile Walls Direct Removable l Location Alpha Beta Alpha Beta TN064 80 1226 <5.4 <8.1 l TN065 81 1216 <5.4 <8.1 TN066 92 1304 <5.4 <8.1

~

Total Pts 3 3 3 3 Mean 84 1249 <5.4 <8.1 Std Dev 7 48 0.0 0.0 l

Lo Value 80 1216 <5.4 <8.1 Hi Value 92 1304 <5.4 <8.1 l

l l

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